DOE M 470.4-6, Nuclear Material Control and Accountability
Functional areas: Safeguards, Security, and Emergency Management, Work Processes
The manual establishes a program for the control and accountability of nuclear materials within the Department of Energy.
Cancels: DOE M 474.1-1B DOE M 474.1-2A
Supersedes:
Superseded By:
DOE M 470.4-3 Chg 1, Protective Force on Mar 07, 2006
DOE M 470.4-6 Chg 1, Nuclear Material Control and Accountability on Aug 26, 2005
Version history and related documents
Superseded by
A newer version replaces this document.
- DOE M 470.4-3 Chg 1Protective Force (Mar 07, 2006)
- DOE M 470.4-6 Chg 1Nuclear Material Control and Accountability (Aug 26, 2005)
Supersedes
Earlier documents this one replaced.
Document text
Text extracted from the attached file. Refer to the original document for the authoritative version.
Section 1
AVAILABLE ONLINE AT: INITIATED BY:
http://www.directives.doe.gov Office of Security and Safety
Performance Assurance
NUCLEAR MATERIAL CONTROL
AND ACCOUNTABILITY
U.S. DEPARTMENT OF ENERGY
Office of Security and Safety Performance Assurance
Approved: 08-26-05
Review: 08-26-07
DOE M 470.4-6
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1
NUCLEAR MATERIAL CONTROL AND ACCOUNTABILITY
1. PURPOSE. To establish a program for the control and accountability of nuclear
materials within the U.S. Department of Energy (DOE), including the National Nuclear
Security Administration (NNSA).
2. OBJECTIVES.
a. To prescribe DOE requirements, including those for the NNSA, for nuclear
material control and accountability (MC&A) for DOE-owned and DOE-leased
facilities and DOE-owned nuclear materials at other facilities that are exempt
from licensing by the Nuclear Regulatory Commission (NRC).
b. Effect the policy in DOE P 470.1, Integrated Safeguards and Security
Management (ISSM) Policy, by integrating nuclear materials control and
accountability into DOE operations as determined by line management, and
according to sound risk management practices. (DOE Policy 470.1, Integrated
Safeguards and Security Management (ISSM) Policy, is the Department’s
philosophical approach to the management of the Safeguards & Security (S&S)
Program. A principal objective of the ISSM Program is to integrate S&S into
management and work practices at all levels, based on program line
management’s risk management-based decisions, so that missions may be
accomplished without security events, such as interruption, disruption or
compromise. This approach includes individual responsibility and
implementation of the safeguards and security requirements found in this
Manual.)
3. PROGRAM INTEGRATION. The Nuclear Material Control & Accountability program
must be integrated with other programs such as S&S program planning and management,
physical protection, protective force, information security, and personnel security.
Additionally, the activities and requirements in the weapons surety, foreign visits and
assignments, safety, emergency management, cyber security, intelligence, and
counterintelligence programs should also be considered in the implementation of this
Manual.
4. CANCELLATIONS. The directives listed below are canceled. Cancellation of a
directive does not, by itself, modify or otherwise affect any contractual obligation to
comply with such a directive. Cancelled directives that are incorporated by reference in a
contract remain in effect until the contract is modified to delete the reference to the
requirements in the cancelled directives. The publication of this Manual incorporates all
previous memoranda and letters that were issued by the Office of Security or its
predecessor organizations that established policy.
a. DOE M 474.1-1B, Manual for Control and Accountability of Nuclear Materials,
dated 6-13-03.
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b. DOE M 474.1-2A, Nuclear Materials Management and Safeguards System
Reporting and Data Submission, dated 8-19-03.
5. APPLICABILITY.
Section 2
a. General. Except for exclusions listed in paragraph 5.d., this Manual applies to
nuclear materials at DOE-owned and DOE-leased facilities, and DOE-owned
nuclear material at other facilities that are exempt from licensing by the NRC.
Where a responsibility or authority is assigned to an organization that is
restructured, the responsibility or authority will be reassigned to the appropriate
successor organization as explicitly determined by the appropriate Departmental
Element. (Pursuant to NRC NUREG/BR-0006, Instructions for Completing
Nuclear Material Transaction Reports (DOE/NRC Forms 741 and 740M), NRC
licensees are responsible for routinely reporting all DOE-owned, -loaned, or -
leased material in their possession to the Nuclear Materials Management and
Safeguards System [NMMSS] as prescribed in DOE Orders. Hence, the NMMSS
reporting sections of the Manual also apply indirectly to NRC licensees.)
b. Departmental Elements. Except for exclusions listed in paragraph 5.d., this
Manual applies to all Departmental Elements listed on Attachment 1. This
Manual automatically applies to Departmental Elements created after it is issued.
The Administrator of the National Nuclear Security Administration (NNSA) will
assure that NNSA employees and contractors comply with their respective
responsibilities under this Manual.
c. Contractors.
(1) The Contractor Requirements Document (CRD), Attachment 2, sets forth
requirements of this Manual that will apply to site/facility management
contracts that include the CRD.
(2) The CRD must be included in all site/facility management contracts that
involve nuclear materials and contain DOE Acquisition Regulation
(DEAR) clause 952.204-2, titled Security Requirements.
(3) Departmental elements must notify contracting officers of affected
site/facility management contracts to incorporate this directive into those
contracts.
(4) Once notified, contracting officers are responsible for incorporating this
directive into the affected contracts via the Laws, Regulations, and DOE
Directives clause of the contracts.
(5) As stated in DEAR clause 970.5204-2, Laws, Regulations, and DOE
Directives, regardless of the performer of the work, the site/facility
contractors with the CRD incorporated into their contracts are responsible
for compliance with the CRD. Affected site/facility management
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contractors are responsible for flowing down the requirements of the CRD
to subcontracts at any tier to the extent necessary to ensure compliance
with the requirements. In doing so, contractors must not unnecessarily or
imprudently flow down requirements to subcontracts. That is, contractors
shall both ensure that they and their subcontractors comply with the
requirements of this CRD and incur only costs that would be incurred by a
prudent person in the conduct of competitive business.
(6) This Manual does not automatically apply to other than site/facility
management contracts. Application of any of the requirements in this
Manual to other than site/facility management contracts will be
communicated as follows.
(a) Heads of Field Elements and Headquarters Departmental
Elements. Review procurement requests for new non-site/facility
management contracts that involve classified information or
matter, or nuclear materials and contain DEAR clause 952.204-2,
titled Security Requirements. If appropriate, ensure that the
requirements of the CRD of this Manual are included in the
contract.
Section 3
(b) Contracting Officers. Assist originators of procurement requests
who want to incorporate the requirements of the CRD of this
Manual in new non-site/facility management contracts, as
appropriate.
d. Exclusions.
(1) This Manual does not apply to DOE-owned nuclear materials at U.S.
Department of Defense facilities or foreign facilities. To avoid duplicative
or conflicting requirements, DOE facilities, projects, and programs that are
under the cognizance of the Office of Civilian Radioactive Waste
Management and are subject to NRC regulation must use the rules,
standards, and criteria specified by the NRC or NRC-State agreements in
lieu of this Manual. Pursuant to NRC NUREG/BR-0006, Instructions for
Completing Nuclear Material Transaction Reports (DOE/NRC Forms 741
and 740M), NRC licensees are responsible for routinely reporting all
DOE-owned, -loaned, or -leased material in their possession to the
Nuclear Materials Management and Safeguards System (NMMSS) as
prescribed in DOE Orders. Hence, the NMMSS reporting sections of the
Manual also apply indirectly to NRC licensees, including Department of
Defense facilities licensed by NRC.
(2) In accordance with the responsibilities and authorities assigned by
Executive Order 12344 and to ensure consistency throughout the joint
Navy and DOE organization of the Naval Nuclear Propulsion Program,
the Deputy Administrator for Naval Reactors will implement and oversee
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all requirements and practices pertaining to this Manual for activities
under the Deputy Administrator’s cognizance.
6. DEVIATIONS. Deviations from requirements in this Manual must be processed in
accordance with DOE M 470.4-1, Safeguards and Security Program Planning and
Management.
7. DEFINITIONS. Terms commonly used in the program are defined in the S&S Glossary
in DOE M 470.4-7, Safeguards and Security Program References. In addition to those in
the Glossary, the following definitions are provided for use in this Manual.
a. DOE line management refers to DOE and NNSA Federal employees who have
been granted the authority to commit resources or direct the allocation of
personnel or approve implementation plans and procedures in the accomplishment
of specific work activities.
b. Line management refers to DOE and NNSA Federal and contractor employees
who have been granted the authority to commit resources or direct the allocation
of personnel or approve implementation plans and procedures in the
accomplishment of specific work activities.
c. DOE cognizant security authority refers to DOE and NNSA Federal employees
who have been granted the authority to commit security resources or direct the
allocation of security personnel or approve security implementation plans and
procedures in the accomplishment of specific work activities.
d. Cognizant security authority refers to DOE and NNSA Federal and contractor
employees who have been granted the authority to commit security resources or
direct the allocation of security personnel or approve security implementation
plans and procedures in the accomplishment of specific work activities.
e. For the purposes of this Manual, the site/facility operator refers to the corporate or
governmental entity responsible for the day-to-day operations involving storage,
processing, or use of nuclear materials at the site/facility. For contractor-operated
facilities, this refers to the site/facility contractor. For the DOE-operated
facilities, this refers to the DOE organization operating the facility.
Section 4
f. For the purposes of this Manual, the responsible Departmental Element refers to
the Departmental Element with responsibility for safeguards and security of the
nuclear materials to which a requirement is being applied.
g. For the purposes of this Manual, nuclear materials are the materials listed in
Section A, Table I-1.
h. For the purposes of this Manual, the Office of Security refers to the DOE Office
of Security and Safety Performance Assurance.
8. IMPLEMENTATION. Requirements that cannot be implemented within 6 months of the
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effective date of this Manual or within existing resources must be documented by the
cognizant security authority and submitted to the relevant program officers; the Under
Secretary for Energy, Science and Environment or the Under Secretary for Nuclear
Security/Administrator, NNSA; and the Office of Security. The documentation must
include timelines and resources needed to fully implement this Manual. The
documentation must also include a description of the vulnerabilities and impacts created
by the delayed implementation of the requirements.
9. CONTACT. Questions concerning this Manual should be directed to the Office of
Security at (301) 903-6008.
BY ORDER OF THE SECRETATY OF ENERGY:
CLAY SELL
Deputy Secretary
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TABLE OF CONTENTS
SECTION A - NUCLEAR MATERIAL CONTROL AND ACCOUNTABILITY
CHAPTER I, PROGRAM ADMINISTRATION
1. General..............................................................................................................................I-1
2. Graded Safeguards ............................................................................................................I-7
3. MC&A Requirements for Source and Other Nuclear Materials.....................................I-10
4. Loss Detection Evaluation, Performance Testing and Performance Requirements .......I-12
5. Reporting Incidents of Security Concern........................................................................I-15
6. Assessment Programs .....................................................................................................I-15
CHAPTER I, TABLES
Table I-1. Nuclear Materials ........................................................................................................I-2
Table I-2. Additional Attractiveness Level E Criteria for SNM..................................................I-5
Table I-3. Technical Criteria for Retained Waste........................................................................I-6
Table I-4. Graded Safeguards ......................................................................................................I-9
Table I-5. Effective Quantities...................................................................................................I-10
CHAPTER II, MATERIALS ACCOUNTABILITY
1. General............................................................................................................................ II-1
2. Accounting Systems........................................................................................................ II-1
3. Physical Inventories ........................................................................................................ II-3
4. Measurement and Measurement Control ........................................................................ II-7
5. Nuclear Material Transfers ........................................................................................... II-12
Section 5
6. Material Control Indicators........................................................................................... II-16
CHAPTER II, TABLES
Table II-1. Minimum Sampling Parameters for Physical Inventories ....................................... II-3
Table II-2. Inventory Periods Based on Alternative Measures for Category I and II
Storage Locations................................................................................................... II-6
Table II-3. Minimum Sampling Parameters for Verification/Confirmation Measurements ..... II-6
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Table II-4, Shipper/Receiver Measurement Requirements...................................................... II-13
CHAPTER III. MATERIALS CONTROL
1. General........................................................................................................................... III-1
2. Access Controls ............................................................................................................. III-1
3. Material Surveillance ..................................................................................................... III-1
4. Material Containment .................................................................................................... III-3
5. Detection/Assessment .................................................................................................... III-4
SECTION B – BASIC REQUIREMENTS FOR NUCLEAR MATERIALS
MANAGEMENT AND SAFEGUARDS SYSTEM REPORTING AND DATA
SUBMISSION
1. Documentation and Reporting .............................................................................................1
2. Forms ...................................................................................................................................2
3. Reporting Identification Symbol (RIS)................................................................................2
4. Correction Data....................................................................................................................2
5. Periodic Reconciliation of Facility Data with NMMSS ......................................................2
6. Confidentiality of Data ........................................................................................................2
7. Classification of Data...........................................................................................................3
8. Contact .................................................................................................................................3
9. NMMSS Program Management and Quality Control .........................................................3
10. Specification for Software and Hardware Systems .............................................................3
CHAPTER I, INSTRUCTIONS FOR APPLYING FOR, CHANGING, OR DELETING A RIS
1. Introduction.......................................................................................................................I-1
2. Procedures and Criteria for Establishing a RIS ................................................................I-1
3. Application for a RIS ........................................................................................................I-2
4. Deactivation of a RIS........................................................................................................I-4
5. Changing RIS Information................................................................................................I-5
Section 6
CHAPTER II, GENERAL INSTRUCTIONS
1. Reporting to NMMSS..................................................................................................... II-1
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2. Data Accuracy................................................................................................................. II-1
3. NMMSS Reportable Elements and Isotopes and Reporting Units ................................. II-1
4. Material Type Codes....................................................................................................... II-2
5. Units, Standards, Conversions, and Data Definitions..................................................... II-2
6. Rounding Policy.............................................................................................................. II-2
7. Nuclear Material Blending Transactions ........................................................................ II-3
8. Owner Codes................................................................................................................... II-4
9. Limits of Error on Transfers of SNM and Tritium ......................................................... II-4
10. Normal Operational Losses (NOLs) Measured Discards and Accidental Losses .......... II-5
11. Waste and Burial Sites .................................................................................................... II-6
12. Radioactive Decay .......................................................................................................... II-7
CHAPTER II, TABLES
Table II-1, Rounding Policy ....................................................................................................... II-3
Table II-2, Blending Transaction Example................................................................................. II-4
CHAPTER III, NUCLEAR MATERIAL TRANSACTION REPORTING – GENERAL
1. Introduction.................................................................................................................... III-1
2. Transfer Reporting Timelines ........................................................................................ III-2
3. Transaction Documentation Methods ............................................................................ III-2
4. Classification and Security Requirements ..................................................................... III-3
5. Distribution of DOE/NRC F 741 ................................................................................... III-3
6. Facility Transfers of Material to a Foreign Entity ......................................................... III-4
7. Facility Receives Nuclear Material from a Foreign Entity............................................ III-5
8. Tracking of Foreign Obligated Material within the U.S................................................ III-5
9. Transfers Involving the DoD ......................................................................................... III-5
10. Transfers of Nuclear Material Between DOE Contractors and Licensees .................... III-5
11. Internal Project Transfers............................................................................................... III-5
12. Nonphysical Transfer of Nuclear Material .................................................................... III-8
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13. Other Types of Receipts and Removals......................................................................... III-9
Section 7
14. Special Requirements..................................................................................................... III-9
15. Amendments or Adjustments to Previously Issued DOE/NRC F 741 ........................ III-11
CHAPTER III, TABLES
Table III-1, Submission Dates, Physical Transfer of Material .................................................. III-2
Table III-2, Primary Distribution............................................................................................... III-4
Table III-3, Secondary Distribution........................................................................................... III-4
CHAPTER IV, NUCLEAR MATERIAL TRANSACTION REPORTING – SHIPPER
1. Shipper’s Data................................................................................................................ IV-1
CHAPTER V. NUCLEAR MATERIAL TRANSACTION REPORTING – RECEIVER
1. Receiver’s Data............................................................................................................... V-1
CHAPTER VI, NUCLEAR MATERIAL TRANSACTION REPORTING—DOE TO DoD
1. From DOE to DoD.........................................................................................................VI-1
2. Distribution of DOE/NRC F 741 ...................................................................................VI-4
3. Memorandum Inventory Accounts ................................................................................VI-6
4. From DoD to DOE.........................................................................................................VI-6
5. Prohibition of Use of Foreign Obligated Material.........................................................VI-7
CHAPTER VII, NUCLEAR MATERIAL TRANSACTION REPORTING—U.S. AND
FOREIGN NATIONS, FOREIGN REGIONAL ORGANIZATIONS, OR SUPRANATIONAL
ORGANIZATIONS
1. Introduction...................................................................................................................VII-1
2. Preparation of DOE/NRC F 741 ...................................................................................VII-1
3. Transfers to a Foreign Entity ........................................................................................VII-1
4. Transfers from a Foreign Entity....................................................................................VII-2
5. Batch Formation and Naming.......................................................................................VII-2
6. Specific Instructions for Facilities Engaged in the Import and/or Export
of Nuclear Materials ...................................................................................................VII-3
7. Distribution of DOE/NRC F 741 ..................................................................................VII-5
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CHAPTER VIII, NUCLEAR MATERIAL TRANSACTION REPORTING—FOREIGN
OBLIGATIONS TRACKING FOR DOE/NRC F 741 BLOCKS 17, 18, 19, 20, AND 21
1. Introduction................................................................................................................. VIII-1
2. Prohibition on Use of Foreign Obligated Material ..................................................... VIII-1
3. Imports ........................................................................................................................ VIII-1
4. Completion of Obligation Information ....................................................................... VIII-2
Section 8
5. Domestic Transfers, Internal Transactions, and Exports ............................................ VIII-2
CHAPTER IX, NUCLEAR MATERIAL TRANSACTION REPORTING—FACILITIES
SELECTED BY THE IAEA.
1. Introduction.................................................................................................................... IX-1
2. Batch Formation and Naming........................................................................................ IX-1
3. Detailed Instructions ...................................................................................................... IX-2
CHAPTER X, NUCLEAR MATERIAL TRANSACTION REPORTING—CONCISE NOTE
1. Introduction..................................................................................................................... X-1
2. Instructions for Completing DOE/NRC F 740M............................................................ X-1
CHAPTER XI, MATERIAL BALANCE REPORTING
1. Introduction....................................................................................................................XI-1
2. Classification and Security Requirements .....................................................................XI-1
3. Reporting Units..............................................................................................................XI-2
4. Instructions for Completing DOE/NRC F 742 ..............................................................XI-2
CHAPTER XII, MATERIAL BALANCE REPORTING – FACILITIES SELECTED BY THE
IAEA
1. Introduction...................................................................................................................XII-1
2. Preparation of DOE/NRC F742 ....................................................................................XII-1
CHAPTER XIII, INVENTORY REPORTING
1. Introduction................................................................................................................. XIII-1
2. Nuclear Material Composition Codes and Descriptions............................................. XIII-1
3. Authorized Profiles of Inventory Data........................................................................ XIII-2
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4. Nuclear Material Type Codes ..................................................................................... XIII-2
5. Reconciliation of Facility Data with NMMSS............................................................ XIII-2
6. Preparation of DOE/NRC F 742C .............................................................................. XIII-3
7. Distribution of DOE/NRC F 742C Data..................................................................... XIII-5
CHAPTER XIV, INVENTORY REPORTING FACILITIES SELECTED BY THE IAEA
1. Introduction................................................................................................................. XIV-1
2. Batch Formation and Naming..................................................................................... XIV-1
CHAPTER XV, NUCLEAR MATERIAL REPORTING – DATA ITEMS SUMMARY
TABLES
1. Introduction ................................................................................................................. XV-1
2. Data Items Explanatory Notes ..................................................................................... XV-1
3. Accountable Quantities, Materials Types, and Other Information Needed
for Reporting................................................................................................................ XV-1
Section 9
CHAPTER XV, TABLES
Table XV-1, Nuclear Material Reporting Units and Characteristics...................................... XV-2
Table XV-2, Nuclear Material Type Codes............................................................................ XV-3
Table XV-3, Owner Codes ..................................................................................................... XV-4
Table XV-4, Half Life and Daily Decay Factors.................................................................... XV-4
Table XV-5, Decay Factors for Monthly Reporting Periods.................................................. XV-4
Table XV-6, Decay Factors for Quarterly Reporting Periods ................................................ XV-5
Table XV-7, Instruction for Preparation of Transaction Data Items ...................................... XV-7
Table XV-8, Instructions When Either the DoD or Mutual Defense is Involved................... XV-8
Table XV-9, Processing Code (PC) ........................................................................................ XV-8
Table XV-10, Action Code (AC)............................................................................................ XV-9
Table XV-11, Nature of Transaction Code (TI) ..................................................................... XV-9
Table XV-12, Inventory Change Code – Receipts ............................................................... XV-10
Table XV-13, Inventory Change Code – Removals ............................................................. XV-10
Table XV-14, Material Type Codes and IAEA Element Codes – Import Export ................ XV-11
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Table XV-15, Foreign Obligation Codes.............................................................................. XV-11
Table XV-16, Material Type Codes, IAEA Element Codes, and Quantities for
Source and SNM – Obligations Tracking.................................................... XV-11
Table XV-17, Material Type Codes Used for Specific Circumstances ................................ XV-12
Table XV-18, Inventory Change Type (ICT) Codes – IAEA............................................... XV-12
Table XV-19, DOE Contractor Reporting Procedure for Normal Operational Losses/
Measured Discards and Accidental Losses................................................... XV-13
CHAPTER XVI, ACRONYMS AND ABBREVIATIONS
CHAPTER XVII, FORMS
1. DOE/NRC F 740M ....................................................................................................XVII-2
2. DOE/NRC F 741........................................................................................................XVII-3
3. DOE/NRC F 742........................................................................................................XVII-4
4. DOE/NRC F 742C .....................................................................................................XVII-6
5. DOE F DP-749...........................................................................................................XVII-7
ATTACHMENTS
Attachment 1 Departmental Elements to which DOE M 470.4-6 Applies ............Attachment 1-1
Attachment 2 Contractor Requirements Document ...............................................Attachment 2-1
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Section A
I-1
SECTION A - NUCLEAR MATERIAL CONTROL AND ACCOUNTABILITY
CHAPTER I - PROGRAM ADMINISTRATION
1. GENERAL. This Chapter provides minimum requirements for implementing a nuclear
Section 10
material control and accountability (MC&A) program at Department of Energy (DOE)
facilities and for DOE- owned materials at other facilities that are exempt from licensing
by the Nuclear Regulatory Commission (NRC). DOE line management and site/facility
operators must consider MC&A requirements, systems, technologies, and activities when
planning, designing, constructing, and operating new or renovated DOE facilities. The
site/facility operator must use techniques and equipment that maximize material loss
detection sensitivity, increase the quality of accountability measurements, minimize
material holdup, and reduce the magnitude of inventory differences and associated
control limits consistent with the consequences of the loss of the material.
a. An MC&A program must be established and maintained for all materials
identified in Table I-1, Nuclear Materials. The level of control and accountability
must be graded based on the consequence of their loss.
b. Special nuclear material (SNM) must not be received, processed, or stored at a
facility until a facility approval has been granted.
c. MC&A programs must be designed to deter and detect theft and diversion of
nuclear material by both outside and inside adversaries.
d. A performance testing program to verify MC&A procedures and practices and to
demonstrate that material controls are effective must be established.
e. MC&A programs must address both the theft and diversion of SNM and the
unauthorized control of a weapon, test device, or materials that can be used to
make an improvised nuclear device.
f. This Manual requires that various documents, actions, and activities be approved
by the DOE cognizant security authority.
(1) For each site/facility subject to the requirements of this Manual, a specific
DOE cognizant security authority must be designated as the approving
authority for these documents, actions and plans.
(2) Approval authorities may be delegated in writing to other DOE cognizant
security authorities.
(3) The same official can be designated as the approving authority for more
than one site/facility.
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Section A
I-2
Table I-1. Nuclear Materials
*Reportable quantity is the minimum amount of material subject to the requirements of this Manual. Facilities with less than a reportable
quantity of a material are exempt from the requirements of the manual for that material. Reporting unit is the mass unit that facility/site
nuclear materials accounting systems must use for recording and reporting inventories and transactions.
1Report as Pu-242 if the contained Pu-242 is 20 percent or greater of total plutonium by weight; otherwise, report as Pu-239-241.
2Report as Pu-238 if the contained Pu-238 is 10 percent or greater of total plutonium by weight; otherwise, report as Pu-239-241.
3Americium and Neptunium-237 contained in plutonium as part of the natural in-growth process are not required to be accounted for or
reported until separated from the plutonium.
4For deuterium in the form of heavy water, both the element and isotope weight fields will be used; otherwise, report isotope weight only.
5 Tritium contained in water (H2O or D2O) used as a moderator in a nuclear reactor is not an accountable material.
g. The site/facility operator must designate a management official to be responsible
for the MC&A program. This official must be organizationally independent from
responsibility for nuclear material utilization programs, including nuclear material
production, storage, processing, research, and disposition. This official must have
responsibility for and the authority to ensure the safeguards of accountable
nuclear material, along with operations personnel.
Section 11
h. A reporting identification symbol (RIS) must be established for all nuclear
materials on inventory. Requirements for establishing and maintaining a RIS are
detailed in Section B of this Manual.
i. A nuclear materials representative (NMR) must be designated for each
site/facility with a RIS. The NMR is to be responsible for nuclear materials
reporting and data submission to the Nuclear Materials Management and
Safeguards Systems (NMMSS) (see Section B of this Manual for NMMSS
reporting requirements).
Material Type
SNM,
Source, or
Other
Reportable
Quantity*
Weight Field
Used for
Element
Weight Field Used
for Isotope
Material
Type Code
Depleted Uranium (U) source kilogram total U U-235 10
Enriched Uranium SNM gram total U U-235 20
Normal Uranium source kilogram total U — 81
Uranium-233 SNM gram total U U-233 70
Plutonium-2421 (Pu) SNM gram total Pu Pu-242 40
Plutonium-239-241 SNM gram total Pu Pu-239 + Pu-241 50
Plutonium-2382 SNM tenth of a gram total Pu Pu-238 83
Americium2413 (Am) other gram total Am Am-241 44
Americium-2433 other gram total Am Am-243 45
Berkelium (Bk) other microgram — Bk-249 47
Californium-252 (Cf) other microgram — Cf-252 48
Curium (Cm) other gram total Cm Cm-246 46
Deuterium4 (D) other tenth of a
kilogram
D2O D2 86
Enriched Lithium (Li) other kilogram total Li Li-6 60
Neptunium-237 (Np)3 other gram total Np — 82
Thorium (Th) source kilogram total Th — 88
Tritium5 (H-3) other gram total H-3 — 87
Uranium in Cascades SNM gram total U U-235 89
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Section A
I-3
j. Authorities and responsibilities for MC&A functions (e.g., accounting system,
measurements, measurement control, inventories, audit, material access controls,
and surveillance) must be defined and documentation must be maintained.
k. MC&A program implementation must facilitate, to the extent practical, the cost-
effective integration of the operational mission of the program while protecting
the environment, health and safety of employees, and the public.
l. Personnel performing MC&A functions must be trained and qualified to perform
their duties and responsibilities. (See DOE M 470.4-1, Safeguards and Security
Program Planning and Management, for additional information on safeguards
and security training programs.) A site-specific training program must be
established, implemented and maintained. Personnel must be knowledgeable of
the requirements and procedures related to their functions.
m. An MC&A plan providing the safeguards authorization basis must be developed
and maintained for each facility possessing nuclear materials. The MC&A plan
must be approved by the DOE cognizant security authority.
n. The MC&A plan must specify how nuclear material inventory holdings will be
accounted for and controlled. The MC&A plan must include, at a minimum:
(1) the elements of the MC&A program that are designed to deter and detect
loss, theft, and diversion of nuclear materials and the unauthorized control
of a weapon, test device, or materials that can be used to make an
improvised nuclear device;
(2) measures to ensure that nuclear materials are in their authorized locations
and being used for their intended purposes;
(3) a description of the local implementation of this Manual, which must
document how the MC&A program meets the requirements of this
Manual;
(4) facility-specific requirements approved by the DOE cognizant security
authority including, but not limited to, agreements between Government
and contractor organizations, access control and material surveillance
testing measures, and the scope and extent of the performance testing
program; and
Section 12
(5) MC&A plan review frequency and change control mechanisms.
o. Procedures must be established by the site/facility operator for emergency
conditions and periods when MC&A systems are inoperative. These measures
must ensure that access to or removal of SNM would be detected during these
periods. The MC&A plan must address control of SNM during emergency
operations and measures to be taken before resuming operations following an
emergency.
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p. Materials previously removed from inventory, for which safeguards were
terminated in accordance with DOE MC&A directives in effect at the time of
their removal, are exempt from the requirements of this Manual unless these
materials are recovered. (Materials for which safeguards were terminated may
still need to be protected and controlled pursuant to other DOE security directives
based on radiological sabotage, information security, or property protection
concerns. See DOE M 470.4-1, Safeguards and Security Program Planning and
Management, DOE M 470.4-2, Physical Protection, and DOE M 470.4-4,
Information Security).
q. Termination of safeguards exempts nuclear materials from requirements of this
Manual and thereby removes the safeguards basis for applying physical protection
requirements for theft and diversion of nuclear material, providing termination
requirements are met as specified in items (1) and (2) and below. (After
safeguards termination, nuclear materials may still need to be protected and
controlled pursuant to other DOE security directives based on radiological
sabotage, information security, or property protection concerns. See DOE M
470.4-1, Safeguards and Security Program Planning and Management, DOE M
470.4-2 Physical Protection, and DOE M 470.4-4, Information Security).
Requirements for safeguards termination depend on the safeguards attractiveness
levels of the material. Attractiveness levels are described in Table I-4, Graded
Safeguards.
(1) Safeguards can be terminated on nuclear materials provided the following
conditions are met.
(a) If the material is SNM or protected as SNM, it must be
attractiveness level E and have a measured value. (The second
column of Table I-2, Attractiveness Level E Criteria for SNM,
contains additional and more descriptive information on lower-
grade forms of SNM that can be classified as attractiveness level E
for purposes of terminating safeguards and/or determining
appropriate levels of safeguards protection.)
(b) The material has been determined by DOE line management to be
of no programmatic value to DOE.
(c) The radiological sabotage risks associated with the materials have
been evaluated and additional measures beyond waste management
regulations put in place to ensure that protection requirements, if
applicable, will be met after safeguards termination. Only nuclear
materials that are of radiological sabotage concern need to be
evaluated against this requirement.
(d) The material is transferred to the control of a waste management
organization where the material is accounted for and protected in
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accordance with waste management regulations. The material
must not be collocated with other accountable nuclear materials.
Table I-2. Additional Attractiveness Level E Criteria for SNM
Section 13
(2) In some cases, it may be necessary to dispose of nuclear materials of
attractiveness level D or higher SNM. For DOE facilities, termination of
safeguards for such materials must be approved by the Departmental
Element after consultation with the Office of Security. For National
Nuclear Security Administration (NNSA) facilities, termination of
safeguards for such materials must be approved by the Associate
Administrator for Defense Nuclear Security, after consultation with the
Office of Security.
When disposal of a SNM quantity Category II or greater is being
considered, a security analysis for the theft or diversion of the material
must be performed. A copy of the security analysis must be provided to
the responsible approving authority (i.e., the Departmental Element or the
Description/Form
Maximum concentration*
(wt%) for MC&A and
physical protection
termination
Maximum SNM
concentration1 (wt%) for
only physical protection
equivalent to Category IV
SNM solutions and oxides: nitrate, caustic or chloride
solutions; contaminated/impure oxides, metal fines and
turnings, glove box sweepings
0.1
N/A
SNM amenable to dissolution and subsequent
separation: pyrochemical salts; chloride melt; hydroxide
cake; floor sweepings; alumina; condensates; reduction
residues; sand, slag, and crucible; magnesium oxide
crucibles spent fuel and spent fuel residues
0.1
0.2
SNM in organic matrixes or requiring mechanical
separation disassembly and subsequent multiple
recovery operations: HEPA filters, organic solutions,
oils and sludges, graphite or carbon scrap, surface
contaminated plastics, metal components, combustible
rubber
0.2
1.0
SNM bound in matrix of solid, sintered, or
agglomerated refractory materials: SNM embedded in
glass or plastic, high-fired incinerator ash, spent resins,
salt sludges, raffinates, and sulfides
0.5
2.0
SNM microencapsulated in refractory compounds or
in solid-dilution: vitrified, bituminized, cemented, or
polymer-encapsulated materials; SNM alloyed with
refractory elements (tungsten, platinum, chromium,
stainless steel); ceramic/glass salvage
1.0
5.0
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Associate Administrator for Defense Nuclear Security) before approval of
safeguards termination. Conditions (1)(b) and (c), above, also apply to
these materials).
r. Reduced safeguards can be applied to materials that both meet the criteria of
Table I-3, Technical Criteria for Retained Waste, and have been removed from
processing material balance areas (MBAs). Such materials are referred to as
retained waste. Reductions in safeguards for retained waste require the approval
of the DOE cognizant security authority. The reduced requirements for retained
waste materials are:
Table I-3. Technical Criteria for Retained Waste
Description and Form SNM Concentration Range
(Wt %)
SNM solutions and oxides >0.1<0.5
SNM amenable to dissolution and subsequent separation >0.2<1.0
SNM alloyed with aluminum, thorium, zirconium, spent fuel <1.0
SNM in organic matrixes; SNM requiring mechanical
separation/disassembly and multiple recovery operations
>1.0<5.0
SNM bound in matrix of solid, sintered, or agglomerated refractory
metals
>2.0<7.5
SNM microencapsulated in refractory compounds in solid-dilution >5.0<10.0
Section 14
(1) Physical protection of retained waste must be commensurate with the
safeguards category of the material as defined in Table I-4, Graded
Safeguards. Protection measures against other risks, such as radiological
sabotage, property protection, and information security, may still be
required based on results of vulnerability assessments.
(2) Nuclear materials accountability information must remain on the site’s
inventory records and within NMMSS.
(3) Physical inventory requirements including inventory measurement
requirements for material identified in Table I-3, Technical Criteria for
Retained Waste, can be deferred until:
(a) the material is removed from the site; or
(b) the material is reintroduced into the processing MBA.
s. Identification of a facility (building or other location where an MBA has been
established) for decommissioning, closure, or deactivation does not exempt the
facility from compliance with requirements stated in this Manual. The facility’s
MC&A program must be maintained at a level commensurate with the category
and attractiveness of the nuclear material on inventory until a termination survey
determines that no nuclear material remains at the facility. Such a determination
may be made if no material remains or the only remaining material is waste or
residual holdup that meets the definition of attractiveness level E and has been
written off the MC&A books to a waste management organization. Writing the
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material off the books means terminating safeguards on the material (see 1.q.,
above). With the approval of the DOE cognizant security authority, attractiveness
level E waste and residual holdup for a facility undergoing decommissioning may
be written be off the MC&A books to a decontamination and decommissioning
organization rather than a waste management organization.
Before a facility is decommissioned the following must be accomplished.
(1) All nuclear material holdup must be measured and credited to the
accountability books. (After holdup has been measured and properly
credited to the accountability books, it can subsequently be written off the
books pursuant to paragraph 1.q. above.) Unless demonstrated to be
otherwise, the category of SNM in process holdup must be considered to
be the highest category of the total SNM put into the process during its
lifetime.
(2) All nuclear material, except attractiveness level E residual holdup and
waste, must be transferred to another facility, and the nuclear materials
accounting inventory balance must be verified to be zero.
(3) The termination survey must be completed.
t. Site/facility operators with decommissioned facilities may still need to maintain a
RIS account with NMMSS. For such facilities, transfers of nuclear material in
waste to and from other RIS accounts will need to be reported to NMMSS using
DOE/NRC F 741/741A, Nuclear Material Transaction Report. With the approval
of the DOE cognizant security authority, attractiveness level E waste and residual
holdup for a facility undergoing decommissioning may be written off the MC&A
books to a decontamination and decommissioning organization rather than a
waste management organization.
u. DOE line management must assure that technical standards developed or adopted
by voluntary consensus standards bodies, such as the American Technical
Standards Institute and ASTM International, are considered in development of
MC&A programs under their cognizance.
Section 15
v. MC&A systems should be integrated with physical security systems to protect
against radiological and/or toxicological sabotage involving nuclear materials.
2. GRADED SAFEGUARDS. The site/facility operator must establish and follow a graded
safeguards program for nuclear materials. Under the graded safeguards concept, a
safeguards program must provide the greatest relative amount of control and
accountability for the types and quantities of SNM that can be most effectively used in a
nuclear explosive device. Table I-4, Graded Safeguards, and the following paragraphs
present basic information and requirements for determining nuclear safeguards
categories.
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a. Categories and attractiveness of nuclear material for implementation of DOE’s
graded safeguards program are shown in Table I-4, Graded Safeguards.
Changes to facility safeguards categories that affect protection strategies must be
reviewed and approved by the DOE cognizant security authority based on
materials holdings at the facility and the credibility of rollup.
b. The material category of SNM locations (e.g., MBAs, material access areas
(MAA), protected areas (PA), and facilities) must be determined to establish the
required protection levels. In many cases, the material category is determined
directly from Table I-4, Graded Safeguards. Directions for determining the
material category when multiple material types and attractiveness levels must be
considered are provided in the following paragraphs. Determination of category
involves grouping materials by type, attractiveness level, and quantity. Material
quantities are element weights for plutonium and isotope weights for uranium-235
(U-235) and uranium-233 (U-233). The following procedures are used for
determining material category.
(1) One Material Type, One Attractiveness Level. Sum the material in the
attractiveness level and determine the category from Table I-4, Graded
Safeguards.
(2) One Material Type, Multiple Attractiveness Levels (where a Category III
or greater quantity of B-level material is included).
(a) Determine the amounts of SNM for materials in each of
attractiveness levels B, C, and D.
(b) Calculate the “effective” quantity for attractiveness levels B and C
by multiplying the quantity in attractiveness levels B and C by the
appropriate factors in Table I-5, Effective Quantities.
(c) Sum the effective amounts in attractiveness levels B and C.
(d) Compare the total effective amount, as calculated in paragraph
2.b.(2)(c) above, to the amounts in attractiveness level B from
Table I-4, Graded Safeguards.
(e) Compare the amount of attractiveness level D to Table I-4, Graded
Safeguards.
(f) The material category is the highest level of material category
determined using the procedures in paragraphs 2.b.(2)(a) through
2.b.(2)(d) or in paragraph 2.b.(2)(e).
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Pu/U-233 Category
(kg)
Contained U-235/Separated Np-
237/Separated Am-241 and -243
Category (kg)
Attractiveness
Level I II III IV1 I II III IV1
All E
Materials
Category IV
WEAPONS
Assembled weapons and test
devices
A All N/A N/A N/A All N/A N/A N/A N/A
PURE PRODUCTS
Pits, major components, button
ingots, recastable metal, directly
convertible materials
B >2 >0.4<2 >0.2<0.4 <0.2 >5 >1<5 >0.4<1 <0.4 N/A
HIGH-GRADE MATERIALS
Carbides, oxides, nitrates, solutions
(>25 g/L) etc.; fuel elements and
assemblies; alloys and mixtures;
UF4 or UF6 ( > 50% enriched)
Section 16
C >6 >2<6 >0.4<2 <0.4 >20 >6<20 >2<6 <2 N/A
LOW-GRADE MATERIALS
Solutions (1 to 25 g/L), process
residues requiring extensive
reprocessing; moderately irradiated
material; Pu-238 (except waste);
UF4 or UF6 (> 20% < 50%
enriched)
D N/A >16 >3<16 <3 N/A >50 >8<50 <8 N/A
ALL OTHER MATERIALS
Highly irradiated forms, solutions
(<1 g/L), uranium containing <20%
U-235 or <10% U-2332 (any form,
any quantity)
E N/A N/A N/A Reportable
Quantities
N/A N/A N/A Reportable
Quantities
Reportable
Quantities
1The lower limit for Category IV is equal to reportable quantities in this Manual.
2The total quantity of U-233 = [Contained U-233 + Contained U-235]. The category is determined by using the Pu/U-233 side of this table.
Table I-4. Graded Safeguards
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Table I-5. Effective Quantities
(3) One Material Type, Multiple Attractiveness Levels (where less than a
Category III quantity of B-level material is included).
(a) Determine the amounts of SNM for all attractiveness levels.
(b) Compare the total amounts in each level to those in Table I-4,
Graded Safeguards.
(c) The material category level is the highest level of the material
categories determined using the procedures in paragraphs
2.b.(3)(a) and 2.b.(3)(b).
(4) Multiple Material Types.
(a) Determine the category for each material type following the above
procedures.
(b) The category is that determined for the individual material type
that requires the highest level of protection.
c. Roll-up is the accumulation of smaller quantities of SNM to a higher category,
based upon a compliance standard using Table I-4, Graded Safeguards. Unless it
has been demonstrated by a vulnerability assessment that roll-up is not credible,
SNM must be safeguarded and protected based on the total quantity of SNM for a
location (e.g., MAA, PA, building, or group of buildings.)
3. MC&A REQUIREMENTS FOR SOURCE AND OTHER NUCLEAR MATERIALS.
a. Separated neptunium-237 and separated americium (Am-241 and Am-243) must
be protected, controlled, and accounted for as if they were SNM. For the purposes
of this Manual, separated neptunium-237 and separated americium, refer to the
recovered or product material generated from chemical and processing operations
on the target/source material.
(1) Departmental protection program strategies and graded safeguards
thresholds for separated neptunium-237 and separated americium are to be
identical to those for U-235. The category for these isotopes is determined
using the U-235 side of Table I-3, Graded Safeguards.
Attractiveness Level Pu/U-233 Factor U-235 Factor
B 1 1
C 1/3 1/4
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(2) Americium and neptunium-237 contained in plutonium as part of the
natural in-growth process are not required to be controlled, accounted for,
or reported until separated from the plutonium.
b. Tritium is a nuclear material of strategic importance; therefore, a graded
safeguards programs for tritium must be implemented according to the following
categorizations.
(1) Category III. Weapons or test components containing reportable quantities
of tritium, deuterium-tritium mixtures, or metal tritides that can be easily
decomposed to tritium gas, containing greater than 50 grams of tritium
(isotope) with a tritium isotopic fraction of 20 percent or greater.
(2) Category IV. All other reportable quantities, isotopic fractions, types, and
forms of tritium.
Section 17
c. Excluding tritium, separated neptunium-237, and separated americium (Am-241
and Am-243), source and other nuclear materials listed in Table I-1, Nuclear
Materials, are exempt from the requirements of this Manual except for the
following:
(1) An MC&A program must be established and maintained for these
materials based on the strategic and monetary value of the materials.
(2) Data fields used in the materials accounting system must be consistent
with Table I-1, Nuclear Materials.
(3) Nuclear materials inventories and transactions must be documented in the
nuclear materials accounting at a level specified by the DOE cognizant
security authority. At a minimum, all RIS-level inventories and
transactions must be documented by the system.
(4) RIS level transactions and inventories must be reported to NMMSS in
accordance with Section B of this Manual. Transactions and inventories
for Berkelium are excluded from this requirement and do not need to be
reported to NMMSS.
(5) When these materials are potential substitution materials for SNM and are
collocated with SNM, the requirements of Section A, II, 3.a.(2), Physical
Inventory Frequencies, of this Manual apply.
(6) The frequency and manner of conducting physical inventories must be
approved by the DOE cognizant security authority and documented in the
site/facility MC&A plan.
(7) Other MC&A requirements are to be determined by the DOE cognizant
security authority and documented in the site/facility MC&A plan or other
MC&A program documents.
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4. LOSS DETECTION EVALUATION, PERFORMANCE TESTING, AND
PERFORMANCE REQUIREMENTS.
a. Loss Detection Evaluation. An assessment program for identifying and
evaluating facility capability to detect the loss of Category I quantities of SNM
must be developed for each Category I facility. Potential targets must include all
Category I and any other areas for which a credible scenario for unauthorized
accumulation of a Category I quantity of SNM have been identified. Vulnerability
assessments must be approved by the DOE cognizant security authority and must
be reviewed annually (at least every 12 months) and updated when there are
system changes or new information indicates a potentially significant change in
the risk of unauthorized removal of SNM. Results of the reviews, including
changes in the vulnerability assessments, must be reflected in the vulnerability
analyses reports. (See DOE M 470.4-1, Safeguards and Security Program
Planning and Management, for additional information on vulnerability
assessment programs.)
b. Performance Testing. MC&A performance testing programs must be developed
and documented to support and verify loss detection capability and system
effectiveness. (See DOE M 470.4-1, Safeguards and Security Program Planning
and Management, for additional information on performance testing programs.)
The scope and intent of performance testing must be based on the graded
safeguards concept, i.e., the testing program demonstrates greater testing for
higher category facilities than for lower category facilities.
(1) Performance tests must be designed to demonstrate that the MC&A
system is functional and to ensure that the system performs as specified or
required. In addition, the site/facility operator for the facilities must:
(a) identify those system components that provide the greatest
effectiveness against theft and diversion;
(b) design, conduct, and document tests that substantiate component
effectiveness; and
Section 18
(c) integrate the results of these component tests into S&S risk
management programs and vulnerability assessments.
(2) The performance testing program must include those elements that can
detect a threat in time to prevent it and those elements that can effectively
account for SNM to detect material loss and ensure that safeguards and
security systems are functioning properly. The performance testing
program design must also focus on testing individual detection elements.
Elements identified in a vulnerability assessment that contribute to
detection capability must be tested on a frequency that is based on the
level of risk.
(3) Performance testing must include testing to determine whether S&S
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systems have failed, including testing for loss of SNM. The accuracy of
the accounting system and its capability to provide information about the
quantity, location, and identifying characteristics of nuclear material, must
be tested.
(4) Corrective action plans for systems that have failed performance testing
must be developed and interim compensatory measures put in place.
c. MC&A Performance Requirements. Specific performance requirements for
selected MC&A system elements are established below in (1)-(7). The
performance of the selected system elements must be validated on a frequency
documented in the MC&A plan. If system elements fail to meet the performance
requirements, a corrective action plan must be developed and, where necessary,
compensatory measures must be taken.
(1) Access controls. Performance tests must be designed and conducted to
fully evaluate the effectiveness of access controls for Category I and II
quantities of SNM.
(a) At least 95 percent of the tests conducted must demonstrate
detection of unauthorized access to Category I and II quantities of
SNM.
(b) Testing of access controls must be facility-specific, and the scope
and the extent of the testing must be documented by the
site/facility operator and approved by the DOE cognizant security
authority.
(2) Material Surveillance. Performance tests must be designed and conducted
to fully evaluate the effectiveness of material surveillance activities for
Category I and II quantities of SNM.
(a) At least 95 percent of the tests conducted must demonstrate
detection of unauthorized actions related to the control of Category
I and II quantities of SNM.
(b) Material surveillance testing must be facility-specific, and the
scope and the extent of the testing must be documented by the
site/facility operator and approved by the DOE cognizant security
authority.
(3) Tamper-Indicating Devices (TIDs). The TID record system must
accurately reflect the location and identity of TIDs for at least 99 percent
of the TIDs inspected. The TID program must ensure that TIDs are
properly in place for at least 95 percent of the TIDs inspected.
(a) To comply with the TID performance requirement, TIDs must be
inspected for all items selected for physical inventory and/or
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transfer.
(b) Testing to ensure TIDs are properly in place must include checking
to see that the TID has been properly applied and the integrity of
the TID has not been violated.
(c) Performance must be verified at least annually (at least every 12
months) except for facilities whose physical inventories are
conducted less frequently than once a year. For such facilities,
performance must be verified at the same frequency as inventories
are conducted.
Section 19
(d) Testing for this requirement is not intended to require destruction
of properly applied TIDs whose integrity has not been violated.
(4) SNM and Metal Portal Monitoring. Performance testing requirements
must include those necessary to verify vulnerability assessments, detection
requirements, and applicable tests described in ASTM International
Standard Guides.
(5) Accounting Record Systems. The accounting record system must
accurately reflect item identity and location for at least 99 percent of items
selected. If more than 1 percent of the accounting records selected are
found to be in error, corrective actions must be taken for the accounting
system as a whole.
(a) Accounting record systems must be verified against all items
selected for physical inventory and/or transfer.
(b) Performance must be verified at least annually (at least every 12
months) except for facilities whose physical inventories are
conducted less frequently than once a year. For such facilities,
performance must be verified at the same frequency as inventories
are conducted.
(6) Inventory Confirmation/Verification Measurements. For Category I and II
items, acceptance/rejection criteria for verification measurements and,
where possible, for confirmatory measurements, must be based on the
standard deviation for the measurement method under operating
conditions. Control limits for such criteria must be set at no wider than
three times the standard deviation for the method. The control limits must
be reviewed and approved by the DOE cognizant security authority
(7) Inventory Difference Control Limits.
(a) For Category I and II MBAs, limits-of-error must not exceed 2
percent of the active inventory during the inventory period or a
Category II quantity of material.
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(b) For Category III and IV MBAs, limits-of-error of inventory
differences must not exceed a specified percentage of the active
inventory during the inventory period to a maximum of a specified
quantity; the specified percentage and maximum quantity must be
approved by the DOE cognizant security authority.
(c) For purposes of the performances requirements (a) and (b), the
term “active inventory” means the sum of additions to inventory,
beginning inventory, ending inventory, inventory adjustments, and
removals from inventory after all “common terms” have been
excluded (in this context, “common terms” are material values that
appear in the active inventory calculation more than once and
come from the same measurement).
5. REPORTING INCIDENTS OF SECURITY CONCERN.
a. The site/facility operator must identify MC&A loss detection elements for each
MBA and must establish a graded program for monitoring these elements and
associated data to determine the status of nuclear material inventories and to
identify security incidents. (See DOE M 470.4-1, Safeguards and Security
Program Planning and Management, for additional information on reporting
security incidents.)
b. In addition, the DOE cognizant security authority must independently evaluate the
significance of the incident. Information and actions related to loss detection,
monitoring, and assessment activities must be documented and maintained.
6. ASSESSMENT PROGRAMS.
Section 20
a. General. The site/facility operator must establish a program to periodically
review and assess the integrity and quality of its MC&A program and practices.
The assessment program must address both normal operations and emergency
conditions. The frequency and content of these assessments must be on a graded
basis approved by the DOE cognizant security authority. (See DOE M 470.4-1,
Safeguards and Security Program Planning and Management, for additional
information on safeguards and security assessment programs.) The results of all
assessments must be reported to the DOE cognizant security authority, and
assessment reports must be reviewed for classification. Deficiencies must be
identified and corrective action plans developed. The assessment must be
performed by personnel who are knowledgeable of MC&A.
Reviews must be conducted and documented before startup of new facilities or
operations and when changes occur in facilities, operations, or MC&A features
that might alter the performance of the MC&A system.
b. Assessment Program Elements. At a minimum, the assessment program must
address the following.
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(1) Identification of abnormal situations.
(2) Loss mechanisms, loss detection capabilities, and localization of inventory
differences.
(3) Selection, maintenance, calibration, and testing functions to ensure proper
equipment and system performance.
(4) MC&A system checks and balances, including separation of
responsibilities and duties, used to identify irregularities and detect
tampering with materials or MC&A system components.
(5) Change controls, including authorization requirements, to detect
unauthorized or inappropriate modification of system components,
procedures, or data. The change control system must address
requirements for review, authorization, documentation, notification, and
controls on equipment selection, procurement, and maintenance.
(6) Procedures or checks to ensure the reliability and accuracy of MC&A data
and information.
(7) Performance testing conducted by the site/facility operator. This portion
of the assessment should address the design of performance tests and the
results obtained by the testing program since the last assessment.
(8) Procedures for emergency conditions and for periods when MC&A system
components are inoperative.
(9) Material containment, material access, and material surveillance
procedures.
(10) Physical inventory program and reconciliation practices.
(11) Accounting system procedures, capabilities, and sensitivities.
(12) Identification of personnel with MC&A responsibilities who should be
included in the facility human reliability program, (See 10 Code of Federal
Regulations 712, Human Reliability Program, for additional information.)
(13) Measurement control program.
(14) TID programs.
c. Independent Assessments. In addition to the assessments described above, an
organization independent of MC&A must conduct internal audits of the facility’s
MC&A function to assess compliance with internal plans and procedures. The
frequency of these audits must be approved by the DOE cognizant security
authority.
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CHAPTER II - MATERIALS ACCOUNTABILITY
1. GENERAL. This Chapter describes requirements for nuclear materials accountability.
Section 21
Nuclear material accountability programs must ensure accountable nuclear materials are
accounted for and unauthorized acts are detected. These requirements must be applied in
a manner consistent with the graded safeguards concept. The Chapter is divided into five
functional areas: accounting systems, physical inventories, measurement and
measurement control, nuclear material transfers, and material control indicators.
2. ACCOUNTING SYSTEMS. A system for tracking nuclear material inventories,
documenting nuclear material transactions, issuing periodic reports, and assisting with the
detection of unauthorized system access, data falsification, and material gains or losses
must be established and implemented. The accounting system must provide a complete
audit trail for all nuclear material from receipt through disposition. The generally
accepted accounting principles promulgated by the Financial Accounting Standards
Board must be used in the design and operation of the nuclear material accounting
system.
The facility nuclear materials accounting system must include checks and balances and
must be structured to ensure timely detection of errors or discrepancies in records
associated with a Category I or II quantity of SNM, including, where possible, detecting
falsified data and identifying the responsible persons. Timeframes for detection of errors
and discrepancies must be approved by the DOE cognizant security authority and
documented in the MC&A plan. The system also must be capable of detecting omissions
and other data discrepancies and ensuring completeness of accounting records.
a. Accounting Systems Databases and Procedures. Procedures must be established
and maintained that describe the structure and operation of the nuclear materials
accounting system. The procedures must accurately reflect current nuclear
material accounting practices. Specific requirements for accounting procedures
must include the following.
(1) Descriptions of the inventory database (including procedures for updating
and reconciling inventory data with the results of physical inventories) and
the required data elements for each applicable material type.
(2) Identification of accounting reports and their frequency, distribution, and
timeliness, consistent with accounting requirements.
(3) Identification of organizational responsibilities for management and
operation of the accounting system.
(4) Recording, reporting, and submitting data to the NMMSS, by material
type and reporting unit, as specified in Section B of this Manual.
b. Account Structure.
(1) Facility nuclear material accounts must consist of one or more MBAs
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established to identify the location and quantity of nuclear materials in the
facility. Readily retrievable accountability data must be maintained by
MBA and reflect quantities of nuclear materials inventory, quantities of
nuclear materials received and shipped, and other adjustments to
inventory.
(2) The MBA account structure must sort data by material types, processes,
and functions; provide the capability to localize inventory differences; and
provide a system of checks and balances for verifying the accuracy of the
accountability data and records.
(3) An MBA boundary must not cross an MAA boundary. Each MBA must
consist of a single geographical area and be an integral operation.
(4) The site/facility operator must designate an MBA custodian for each MBA
to ensure that MC&A requirements are implemented in that MBA.
Section 22
(5) The MBA custodian is responsible for controlling nuclear material located
in the MBA, preparing and signing internal material transfer documents,
and conducting and reconciling MBA physical inventories.
(6) An MBA custodian must not be responsible for multiple MBAs when
transfers of nuclear material occur between those MBAs (i.e., a single
custodian must not serve as both shipper and receiver for material
transfers).
c. Records and Reports.
(1) The site/facility operator must maintain records, submit data, and issue
reports as required by this Manual and facility procedures. The reports
must accurately describe all nuclear material transactions and inventories.
Inventory adjustments must be identified by MBA and must be reported as
required in this Manual.
(2) Nuclear materials records must be updated by authorized personnel only.
The records system must provide an audit trail for all transactions
affecting the nuclear materials database.
(3) The accounting records system must be capable of being updated daily or
on demand for all nuclear materials transactions. This requirement is for
updating records based on reports or information; it does not pertain to
how quickly a facility must be able to complete measurements. The
records system must also be capable of generating electronic and/or hard
copy book inventory listings of all SNM within 3 hours. The listing must
differentiate between SNM and other nuclear material when necessary.
The accuracy of the accounting record system must be validated in
accordance with requirements of Section A, Chapter I, paragraph 4.b., of
this Manual. Specific performance requirements for accounting record
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system accuracy are contained in Chapter I, paragraph 4.c.
3. PHYSICAL INVENTORIES. The site/facility operator must implement a physical
inventory program for nuclear materials to demonstrate that materials are present in their
stated quantities and to detect the unauthorized removal of nuclear materials. Inventory
requirements for separated Np-237 and separated americium are the same as for SNM.
When facilities are precluded from performing physical inventories as required by this
Manual, material control and protection features must be enhanced to ensure inventory
integrity. Physical inventory programs must comply with the following requirements.
a. Periodic Physical Inventories. Periodic and special physical inventories must be
performed for each MBA according to the strategic importance of the material
and the consequence of its loss.
(1) Conduct of Physical Inventories. Inventories must be based on measured
values, including measurements or technically justifiable estimates of
holdup. Process monitoring techniques may be used for material that is
undergoing processing and recovery operations and is inaccessible for
measurements. Plans and procedures must be developed and documented
that define responsibilities for performing inventories and specify criteria
for conducting, verifying, and reconciling inventories. Statistical
sampling, based on graded safeguards, may be used to verify the presence
of items during inventories. Parameters for statistical sampling plans must
be defined by the site/facility operator, and approved by the DOE
cognizant security authority. Sampling plans must specify the population,
confidence level, minimum detectable defect, definition of a defect, and
action to be taken if a defect is encountered.
Section 23
Table II-1, Minimum Sampling Parameters for Physical Inventories,
provides minimum sampling parameters for safeguards categories.
Table II-1. Minimum Sampling Parameters for Physical Inventories
Category Confidence Level Minimum Detectable Defect
I 95 percent 3 percent
II 95 percent 5 percent
III & IV 95 percent 10 percent
The inventory population must be stratified according to item category as
shown in Table II-1, Minimum Sampling Parameters for Physical
Inventories. Separate samples must be derived for each inventory stratum.
(2) Physical Inventory Frequencies. Physical inventories must be performed
for Category I and II MBAs that involve activities other than processing at
a frequency determined by the DOE cognizant security authority but at
least semiannually (once every 6 months). The site/facility operator must
ensure that physical inventories are performed bimonthly (once every 2
months) in Category I and II MBAs where processing occurs.
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In processing areas where process controls provide equivalent levels of
theft and diversion detection, physical inventories may be performed upon
completion of the material campaign. In such cases, the DOE cognizant
security authority must approve a processing plan before starting the
campaign. The process plan must identify compositions and quantities of
material to be processed, projected processing timetable, process control
measures used, and procedures necessary for material controls during
process interruptions. Other factors to be considered for frequency
determination include personnel radiation exposure, the operational mode
of the facility, and credible protracted diversion scenarios.
At least annually, each facility must perform a simultaneous physical
inventory of all Category I and II MBAs for which the established
inventory frequency is annual or more frequent. MBAs with extended
inventory frequencies of greater than 1 year are excluded from this
requirement.
Physical inventories for Category III and IV SNM MBAs must be
performed at a frequency specified by the DOE cognizant security
authority, but at least every 2 years (every 24 months).
Category IV source and other nuclear material in Category I and II MBAs
must be inventoried at least every 2 years (every 24 months), except when
the source and/or other nuclear material is a credible substitution material.
When source or other nuclear materials are credible substitution materials
for SNM and are collocated with SNM, facilities must inventory
substitution materials with the same frequency as the SNM and use
inventory measurement methods that can distinguish between SNM,
source, and other nuclear material.
Except for materials required to be protected as SNM and potential
substitution materials collocated with SNM, source and other materials
outside Category I and II MBAs must be inventoried at a frequency
approved by the DOE cognizant security authority and as documented in
the MC&A plan.
In addition to the requirements listed above, inventory checks for
Category IA items not in storage must be performed weekly for physical
count verification and monthly for serial number verification. Inventory
checks for stored Category IA items must consist of a physical count
whenever the storage area is accessed and a monthly serial number
verification.
(3) Extensions to Inventory Frequency Requirements. Extensions to
inventory frequencies must be approved by the DOE cognizant security
authority in accordance with the alternative inventory control provisions in
Section 24
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Table II-2, Inventory Periods Based on Alternative Measures for Category
I and II Storage Locations. For Category I and II storage areas, Table II-2
may be used to determine the frequency of physical inventories based on
the successful implementation of alternative inventory control measures.
Inventory periods specified for each alternative measure are additive so
long as the measures function independently.
Total inventory extension is equal to the sum of inventory periods for all
alternative measures used, with a maximum allowable period of 5 years
(60 months). The longest inventory extensions are given for measures that
provide material attribute information. Items added to these storage areas
must have appropriately measured values. If inventory extensions are
granted for Category I or II storage areas other than in accordance with the
provisions of Table II-2, a deviation must be submitted. (See DOE M
470.4-1 for additional information on submission of deviations.) The DOE
cognizant security authority may extend inventory periods beyond 2 years
(24 months), with a maximum inventory period of 5 years (60 months), for
Category III and IV storage areas that have alternative inventory control
measures.
Inventory values must be determined by the site/facility operator in time to
complete inventory computation and reconciliation and to determine
inventory differences within DOE reporting requirements as specified in
this Manual and based on approved inventory frequencies.
(4) Physical Inventory Reconciliation Program. A physical inventory
reconciliation program must be implemented in which the book inventory
for each MBA is compared with, and if necessary, adjusted to the physical
inventory. The reconciliation must be completed within 15 calendar days
following receipt of all inventory information, measurement data, and
sample analyses. Any inventory differences must be identified and
reported as required.
b. Special Inventories. Procedures must be established and implemented for
conducting special inventories at the request of authorized facility personnel, the
DOE cognizant security authority, or as a result of routine disassembly of critical
assemblies, changes in custodial responsibilities, missing items, inventory
differences exceeding established control limits, and abnormal occurrences.
c. IAEA Inventories. Physical inventories performed during IAEA inspections may,
with the concurrence of the DOE cognizant security authority, serve in place of a
scheduled physical inventory.
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Table II-2. Inventory Periods Based on Alternative Measures
for Category I and II Storage Locations
d. Inventory Verification/Confirmation Measurements.
(1) A system for performing measurements as part of a physical inventory
must be established and implemented by the site/facility operator for each
MBA. Verification measurements must be made on SNM items that are
not tamper-indicating. Confirmation measurements must be made on
tamper-indicating SNM items. Such measurements may use a statistically
based sampling plan applied in a manner consistent with the graded
safeguards concept. The site/facility operator must develop sampling
plans, which the DOE cognizant security authority must approve. These
plans must be based on the defined population and must not be a subset of
the sample selected for physical inventory. Separate sampling plans must
be implemented for verification and confirmation measurements to ensure
that a sufficient number of non-tamper-indicating items are measured.
Sampling plans must specify the population, confidence level, minimum
detectable defect, definition of a defect, and action to be taken if a defect
is encountered. Minimum sampling parameters for safeguards categories
are as noted in Table II-3, Minimum Sampling Parameters for
Verification/Confirmation Measurements, below.
Section 25
Table II-3 Minimum Sampling Parameters for Verification/Confirmation
Measurements
Category Confidence Level Minimum Detectable Defect
I 95 percent 3 percent
II 95 percent 5 percent
III & IV 95 percent 10 percent
Alternative Inventory Control Measures1 Inventory Periods
Formidable barriers 1 year
Hazardous environment 1 year
Bulk containment 1 year
Vault enhancement above baseline requirements 9 months
Continuous monitoring of physical or mechanical parameters 1 year
General (area-wide) confirmatory measurements 1 year
Continuous item observation (e.g., video/image, laser surveillance) 2 years
Continuous item monitoring (e.g., monitoring of serial number,
TIDs, movement)
2 years
Mass (load cell) 2 years
Confirmatory measurements on individual items (e.g., thermal,
gamma, or neutron emission)
3 years
Quantitative measurements on individual items May qualify as a continuous
inventory2
1When multiple measures are used for storage MBAs, the inventory periods are additive as long as the alternative measures function
independently.
2If the measurements are both item- and material-specific and there is a level of confidence that the measurements are correct, the monitoring
may qualify as a continuous physical inventory. To be considered a continuous physical inventory, automated measurements must be made
on all items on a second-to-second basis.
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The inventory population must be stratified according to item category, as
shown in Table II-3, Minimum Sampling Parameters for
Verification/Confirmation Measurements. Separate samples must be
derived for each stratum.
For tamper-indicating items stored in vaults or vault-type rooms, the DOE
cognizant security authority may approve sampling plans based on
sampling parameters other than those required by Table II-3.
The DOE cognizant security authority may establish a material quantity
threshold for requiring inventory verification and confirmation
measurements. For materials not amenable to verification measurement,
confirmatory measurements of two material attributes must be substituted
for verification measurements. Materials not amenable to verification
measurement must be identified and documented in the MC&A plan.
(2) The site/facility operator must establish documented acceptance or
rejection criteria for inventory confirmation and verification
measurements based on valid technical and statistical principles. For
Category I and II items, acceptance and rejection criteria must be
consistent with performance requirements for confirmation and
verification measurements shown in Chapter I, paragraph 4.c. The
site/facility operator must prepare and implement a response plan for
evaluating and resolving all verification and confirmation measurements
that fail to meet acceptance criteria. Items that fail to meet the
confirmation or verification measurement acceptance criteria must not be
processed before the discrepancy is resolved.
4. MEASUREMENT AND MEASUREMENT CONTROL. Measurement and
measurement control programs approved by the DOE cognizant security authority must
be implemented at all facilities with nuclear material. Measurement programs used to
determine Category I or II inventories of SNM or used to determine a Category I or II
SNM throughput over a 6-month period must meet the requirements set forth in
paragraphs 4.a. through e., below. All measurement systems used for accountability
purposes must have associated measurement control programs to ensure the quality of
measurement data generated.
Section 26
Measurement programs used to determine Category III or IV inventories of SNM must
address the topics set forth in paragraphs 4.a. through e., below ,but the specific
measurement and measurement control requirements will be determined by the DOE
cognizant security authority.
Measurement systems used for accountability purposes must be precise and accurate
enough to minimize the contribution of measurement error to the limit of error of the
inventory difference. Nuclear materials not amenable to verification measurement must
be identified in the facility’s MC&A plan. Inventory values for these materials must be
based on measured values or technically justified estimates. Justification and supporting
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documentation for these inventory values must be maintained and readily retrievable for
review.
a. Organization. Measurement and measurement control programs must be
independent from operations.
b. Selection and Qualification of Measurement Methods. The site/facility operator
must select, qualify, and validate measurement methods capable of providing the
required levels of precision and accuracy. Target values for precision and
accuracy of nuclear material measurements endorsed by recognized national and
international nuclear organizations must be considered performance goals for
facility measurement systems. Alternative measurement performance goals must
be defensible and documented. Precision and accuracy requirements must be
approved by the DOE cognizant security authority and documented in the MC&A
plan. Procedures must be documented and implemented for each facility to
ensure that only qualified measurement methods are used for accountability
purposes.
c. Training and Qualification of Measurement Personnel. Individuals responsible
for performing nuclear material measurements must have sufficient knowledge to
perform the measurements in an acceptable manner.
(1) Training. A documented plan for training measurement personnel must be
established and implemented for each facility. The plan must be reviewed
annually (at least every 12 months) and updated as necessary to reflect
changes in measurement technology and must specify training
qualification and re-qualification requirements for each measurement
method.
(2) Qualification. A documented qualification program must be established
and implemented for each facility to ensure that measurement personnel
demonstrate acceptable levels of proficiency before performing
measurements and that measurement personnel are re-qualified according
to requirements in the training plan. Measurement personnel must
demonstrate proficiency in destructive analysis of nuclear material at a
minimum of once per day for each method they will use that day.
d. Measurement Systems. Nuclear material measurement systems must provide
accurate nuclear material values for inventories and transactions.
(1) Sampling. Sampling programs must be implemented to ensure that
portions of bulk material taken for measurement are representative of the
bulk material. The site/facility operator must establish and implement a
documented sampling plan for each measurement point used for
accountability purposes. The plans must be based on valid technical and
statistical principles and must take into account material type,
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measurement requirements, and any special process or operational
considerations.
Section 27
(a) The basis for the sampling plan must be documented and validated
through studies of the materials or items being sampled.
(b) The sampling plan must specify, at a minimum, the sampling
procedure, number and size of required samples, mixing time and
procedure (when applicable), provisions for retaining archive
samples, and estimates of variance associated with the sampling
method.
(c) Sampling procedures must be documented and reviewed annually
(at least every 12 months) or whenever changes are made,
including changes to the type or composition of the material being
sampled.
(2) Measurement Methods. The site/facility operator must develop, document,
and maintain measurement methods for all nuclear material on inventory.
These methods must be written to provide clear direction to the analyst or
operator and must be validated initially and revalidated whenever changes
are made.
(a) In determining inventory values and consistent with the graded
safeguards concept, measurement methods must be selected in a
manner that minimizes the contribution of measurement error to
the uncertainty of the inventory difference.
(b) Verification measurements, when used to adjust accountability
records, must have accuracy and precision comparable to or better
than the original measurement method.
(c) The method used for confirmatory measurements must be capable
of determining the presence or absence of a specific attribute of the
material consistent with valid acceptance and rejection criteria.
(d) All measurement methods must be calibrated using standard or
certified reference materials or secondary standards traceable to the
national measurement base and must be revalidated as necessary.
(e) Measurement equipment and instruments must meet precision and
accuracy requirements under in-plant conditions.
(f) Documentation of measurement data must be maintained to
provide an audit trail from source data to accounting records.
e. Measurement Control Programs. The site/facility operator must develop and
implement control programs for all measurement systems used for accountability
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purposes. Control programs must ensure the effectiveness of measurement
systems and the quality of measured values used for accountability purposes.
Control programs must also produce precision and accuracy values for use in
determining inventory difference control limits and shipper/receiver limits of
error. A measurement control program, as referred to herein, must include, at a
minimum, the following elements.
(1) Scales and Balances Program. All scales and balances used for
accountability purposes must be maintained in good working condition,
recalibrated according to an established schedule, and checked for
accuracy and linearity on each day that the scale or balance is used for
accountability purposes.
(2) Analytical Quality Control. Data from routine measurements must be
analyzed statistically to determine and ensure accuracy and precision of
the measurements.
(3) Sampling Variability. The uncertainty associated with each sampling
method, or combination of sampling and measurement methods, must be
determined and maintained on a current basis.
(4) Physical Measurement Control. The precision and accuracy of volume,
temperature, pressure, and density measurements must be determined and
ensured.
Section 28
(5) Instrument Calibration. Instruments must be calibrated using appropriate
standards, when available. At a minimum, measurement values must be
compared with more accurate measurement system values on a prescribed
basis; the frequency is defined by demonstrated instrument performance.
(6) Reference Materials (Standards). All calibration and working standards
used in a measurement control program must be traceable to the national
measurement base through the use of standard reference materials or
certified reference materials. They must have smaller uncertainties
associated with their reference values than the uncertainties of the
measurement method in which they are used. Working standards used in a
measurement control program must be representative of the type and
composition of the material being measured when the material matrix
affects the measured values.
(7) Sample Exchange Programs. Each facility’s measurement control
program must include participation in interlaboratory control programs to
provide independent verification of internal analytical quality control.
(8) Statistical Controls. For each measurement method used for
accountability purposes, control limits must be calculated and monitored,
and documented procedures must exist to correct out-of-limits conditions.
Control limits must be established at the two-Sigma level (warning limits)
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and three-Sigma level (alarm limits). Control data exceeding the two-
Sigma limits must be investigated, and when warranted, corrective action
must be taken. If a single data point exceeds the three-Sigma level, the
measurement system in question must not be used for an accountability
measurement until the measurement system has been demonstrated to be
within statistical control. For measurement methods relying substantially
on operator technique, control limits must include uncertainties for each
analyst/method combination. Statistical control limits must be monitored
to ensure they are consistent with target values as approved in the MC&A
plan.
(9) Measurement Method Qualification. The site/facility operator must have a
documented measurement method qualification program. The qualified
measurement methods must demonstrate acceptable performance before
being used for accountability purposes. For destructive analysis and
nondestructive assay of nuclear material, performance must be
demonstrated at least once per day for each method being used. For
nondestructive analysis measurement systems for which meeting this
requirement is impractical or unnecessary, the control measurement
frequency must be at least one of every five measurements unless
otherwise approved by the DOE cognizant security authority.
(10) Measurement Control Procedures. The site/facility operator must develop
and document measurement control procedures for all measurement
methods used for accountability. The site/facility operator must develop
and implement a program for each facility to ensure measurement control
procedures are followed.
(11) Statistical Programs. The site/facility operator must develop and
implement a documented program for the statistical evaluation of
measurement data to determine control limits and precision and accuracy
levels for each measurement system used for accountability. The program
must ensure the quality of measurement and measurement control data and
provide estimates of uncertainty on inventory and inventory control
statements.
Section 29
The statistical program, at a minimum, must contain the following
elements.
(a) Valid statistical techniques to determine the total random error, the
measurement biases generated for each measurement system or
sampling/measurement system, and the control limits, rejection
limits, and outlier criteria.
(b) A valid statistical technique to develop sampling plans for
inventory and measurement of nuclear material.
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(c) Analysis of measurement control data and reporting to the
responsible organization at specified times and frequencies.
(d) Documentation of all major assumptions made in each data
evaluation process.
5. NUCLEAR MATERIAL TRANSFERS. The site/facility operator must develop and
implement a program to control and account for both internal and external transfers of
nuclear materials for each facility. This program must include documented procedures
that specify requirements for authorization, documentation, tracking, verification, and
response to abnormal situations that may occur during transfer of nuclear materials. The
site/facility operator must establish and implement a graded system of measurements and
records to monitor internal and external transfers of nuclear material and to deter/detect
unauthorized removal of material during such transfers (see Section B of this Manual for
requirements for submitting DOE/NRC F 741 and DOE forms required for documenting
transfers for materials accounting purposes).
a. External Transfers.
(1) The shipper must obtain written verification and maintain documentation
that the intended receiver is authorized to accept the material before the
material is transferred.
(2) Transfers of nuclear material between facilities having a different RIS
must be documented using the electronic equivalent of DOE/NRC F 741.
Manual/paper DOE M 741’s may be used to meet this requirement with
the approval of the DOE cognizant security authority. These forms must
be prepared and distributed to the principals of the transaction and line
management, as required by Section B of this Manual.
(3) Immediately after receipt, shipments must be subjected to a transfer check.
Transfer checks must consist of confirming the shipping container or item
count, validating the TID integrity and identification, verifying the
tamper-indicating characteristics of the container, and comparing with
shipping documentation to ensure the shipment was received intact. For
external transfers, all SNM containers must be tamper-indicating.
For purposes of transfer checks, receipt occurs when the transfer vehicle is
unloaded or the transfer vehicle’s integrity is breached (TIDs removed or
broken) at the receiving facility. The site/facility operator must have
documented procedures that specify actions to be taken in the event
discrepancies are detected. Records of transfer checks are subject to audit
and must be retained at least until the next S&S survey. For accountability
purposes, material in transit at the end of a reporting period must be
included in the receiver’s reported inventory even though physical receipt
of the material has not yet occurred.
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Section 30
(4) For all unirradiated Category I and II quantities of SNM transferred
between facilities having a different RIS, the receiver must perform a
verification or accountability measurement unless both RISs are located
on the same site and are operated by the same site contractor. Both
verification measurements and accountability measurements are
quantitative measurements used by the receiver to verify that the amount
of SNM in a shipment is as stated by the shipper. Accountability
measurements differ from verification measurements only in how they are
used in receiver’s accountability system. Accountability measurements are
entered in receiver’s accountability system as the value for the shipment.
When verification measurements are used, the shipper’s values are entered
into the receiver’s accountability records.
(a) The receiver may choose to establish a new accountability value or
accept and book the shipper’s accountability value considering the
potential impact on the inventory difference. Transfer of nuclear
material produced to program specification and inherently tamper-
indicating may be verified by performing a confirmatory
measurement rather than a verification/accountability measurement
unless the DOE cognizant security authority requires
verification/accountability measurements.
Use of confirmatory measurements in lieu of
verification/accountability measurements for such items requires a
shipper/receiver agreement approved by both the shipper’s and
receiver’s DOE cognizant security authority. For Category III and
IV transfers, the DOE cognizant security authority may require that
measurements be made consistent with the strategic,
nonproliferation, and/or monetary value of the material, or as
required for environmental, safety, and operational controls.
Verification/accountability measurements must be completed prior
to processing material, unless a deviation is approved or the
criteria defined in paragraph 5.a.(4)(f) are met. When
verification/accountability measurements are required and
materials are to be processed before the verification/accountability
measurements have been made, the shipper and receiver must
reach an agreement as to how significant shipper/receiver
differences will be handled.
(b) The shipper must independently determine the measured values
before shipment unless the integrity of the item and of the existing
measured values have been ensured. The shipper’s measured
values must be documented on DOE/NRC F 741.
(c) The receiver’s confirmation and verification/accountability
measurements (when required) for Category I and II quantities of
SNM transfers must be accomplished in accordance with the
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requirements in Table II-4, Shipper/Receiver Measurement
Requirements. The receiver’s verification/ accountability
measurements for transfers involving other categories of nuclear
material, when required by the DOE cognizant security authority
[see paragraph 5.a.(4)(a)], must be performed in accordance with
the requirements in Table II-4, Shipper/Receiver Measurement
Requirements.
(d) For shipment of unirradiated SNM containing greater than 250
grams of a single SNM type and for each discrete item exceeding
250 grams, limits of error at the 95 percent confidence level must
be assigned to shipper and receiver accountability/verification
measurements for both the element and isotope values. Limits of
error need not be reflected on the DOE/NRC F 741 for external
transfers when accountability measurements cannot be performed.
For other shipments, the shipper and receiver may estimate the
limits of error. Limits of error are also required for all
measurements of external transfers of tritium that exceed 2 grams,
except as noted above.
Section 31
Table II-4. Shipper/Receiver Measurement1 Requirements
Material Category and
Attractiveness Level
Material
Confirmation
Verification/Accountability2
Measurements
IA 3 working days Shipper’s value
IB 5 working days 30 calendar days
IC, II 10 working days 30 calendar days
III 10 working days 120 calendar days or on input to process
IV 20 working days On statistical bases within 180 days or on input to process
1Confirmatory measurement by nondestructive analysis, gross weight check, and item count (if not done as part of transfer checks). Confirmatory
measurements are not required for all materials. When confirmatory measurements are required, they must be performed within the time frames of this
table.
2Quantitative determination of material quantities (within designated measurement uncertainty limits). Accountability measurement values are entered
into receiver’s accountability records. For verification measurements, the shipper’s values are entered into the receiver’s accountability records.
Verification/accountability measurements are not required for all materials. When verification/accountability measurements are required, they must be
performed within the time frames of this table.
(e) Documented acceptance/rejection criteria must be established and
used to evaluate confirmatory measurement data. A response plan
for investigation and resolution of confirmatory measurements that
fail acceptance criteria must be developed and implemented, and
all anomalies must be investigated and resolved.
(f) If delays in completing the receiver’s verification/accountability
measurement will result in a protracted delay in closure of the
transaction, a confirmatory measurement may be used to affect a
“safeguards closure” of the transaction. The transaction is
documented by an “A-S” entry on DOE/NRC F 741. A safeguards
closure may be used when the integrity of the shipment is ensured
and only verification/accountability measurement differences are
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possible between shipper and receiver. If the receiver’s
verification/accountability measurement performed after a
safeguards closure indicates a shipper/receiver difference, the
difference may be resolved by mutual agreement of the shipper and
receiver with the approval of their DOE cognizant security
authorities and an adjustment (correcting entry) to the DOE/NRC F
741, if required.
The safeguards closure may be affected only when all of the
following conditions have been met.
1 No discrepancies are found in the verification of the piece
count, identification number, integrity of the TIDs, and
gross weight of the items or containers received, and no
evidence indicating theft or diversion of the material is
found.
2 The shipper and receiver confirmation measurements must
confirm the same nuclear material attribute, must compare
results of the methods on a technically valid basis, and the
results must be within the established limits of agreement.
3 Criteria for closing transactions, based on confirmatory
measurements, are approved by both shipper’s and
receiver’s DOE cognizant security authority, and the
shipper/receiver agreement is in effect for the transaction.
(g) Limited processing is acceptable for materials not amenable to
nondestructive assay in order to perform a receipt measurement, as
approved by both shipper’s and receiver’s DOE cognizant security
authority. Limited processing can include homogenization and
dissolution.
Section 32
(5) SNM in foreign reactor fuel returns must either be measured; or the risk of
diversion of material from the fuel must be documented, and the
acceptance of the fuel without measurement must be approved by the
responsible Under Secretary or his/her designee.
b. Internal Transfers.
(1) The site/facility operator must provide a graded system of measurements
and records to reflect the flow of material between MBAs within that
facility and between it and other facilities on the same site.
(2) The facility control system must be designed to monitor transfer activities
and to deter and detect unauthorized removal of material during transfers.
It must flag abnormal situations (e.g., inappropriate transfers of quantities,
materials, or unauthorized personnel receiving or shipping materials).
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(3) Transfers must be documented on nuclear material transfer forms or
electronic equivalents that contain required information, prepared and
distributed within established time frames, and signed by authorized
custodians or their alternates.
(4) Materials must be subjected to a transfer check within 1 work day after
receipt. These checks must include verification of shipping container or
item count, TID integrity (if applied), and identification number. These
transfer checks must be compared with appropriate documentation.
Irradiated SNM requires only a transfer check.
(5) When the isotope content of SNM transferred between MBAs is 50 grams
(fissile) or more, the material must have a measured value before transfer.
Measured values are not required for enriched uranium that is below 20
percent U-235 and below10 percent U-233. Confirmation/verification
measurement requirements for internal transfers must be approved by the
DOE cognizant security authority, including when measurements are not
required.
(6) Acceptance/rejection criteria must be established and documented to
evaluate measurement data for internal material transfers. In addition,
procedures must specify notification and response requirements if nuclear
material removal or another abnormal situation is detected. (See DOE M
470.4-1, Safeguards and Security Program Planning and Management,
for additional information about reporting security incidents.)
6. MATERIAL CONTROL INDICATORS. The site/facility operator must develop and
implement a program that is capable of detecting losses through evaluation and
assessment of shipper/receiver differences, inventory differences, and other inventory
adjustments. The program must assess the material control indicators described below
and ensure detection of losses and unauthorized removal of nuclear materials.
Documented plans must specify responsibilities and procedures for evaluating material
control indicators.
a. Shipper/Receiver Difference Assessment. Written procedures must be developed
for evaluating shipper/receiver differences and for investigating and reporting
significant shipper/receiver differences.
(1) A shipper/receiver difference is defined to be significant when it meets
any of the following criteria.
(a) It involves a discrepancy in the number of items, regardless of the
quantity of nuclear material, or confirmation measurements for the
shipment fail to meet acceptance criteria covered in a
shipper/receiver agreement.
(b) It is statistically significant. The determination of whether
shipper/receiver difference is statistically significant is only
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required for those shipments for which verification/accountability
measurements are made by both the shipper and receiver. A
shipper/receiver difference is defined to be statistically significant
when the magnitude of the difference exceeds either of the
following:
1 the limit obtained by a statistical combination of the valid
limits of error for the shipper and receiver’s measured
values;
OR
2 the square root of two times a single valid limit of error
when either the shipper or receiver’s limit of error is
invalid. When both the shipper’s and receiver’s limits of
error are determined to be invalid, the limits of error must
be recalculated, and the statistical significance of the
shipper/receiver difference must be reevaluated.
(2) Shipper/receiver difference data must be subjected to trend analysis to
detect measurement bias or material loss. Analyses must be designed to
detect statistically significant cumulative shipper/receiver differences and
to trigger investigations when these differences are detected.
(3) The receiver must notify its DOE cognizant security authority and the
shipper of any shipper/receiver difference determined to be significant.
Both shipper and receiver must investigate their measurements and limits
of error. Such investigations must be completed and documented.
(4) Shipper/receiver differences involving a discrepancy in number of items
must be reported.
(5) When shipper/receiver differences are determined to be statistically
significant, but the quantities and strategic or monetary values are
insufficient to warrant an investigation and subsequent correction to
transfer documents, and when the receiver is DOE or one of its contractors
or subcontractors, the difference need not be investigated and the party
must record its own quantitative value. In the context of this paragraph,
differences of less than 50 grams of fissile material or less than 5 grams of
tritium are considered to be insufficient to require an investigation unless
there are special circumstances. Authority to invoke the stipulations of
this paragraph rests mutually with the shipper’s and receiver’s DOE
cognizant security authority.
(6) Statistically significant shipper/receiver differences may be resolved
through any of the following methods.
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(a) If both the shipper’s and receiver’s DOE cognizant security
authorities obtain assurance that the measurements and limits of
error are valid, and the investigation indicates that theft or
diversion has not occurred, the shipper and receiver must record
their own quantitative values.
OR
(b) If either the shipper or receiver and their DOE cognizant security
authority agree to accept the other’s value, the shipper or receiver
must prepare a corrected copy of the shipping document using the
other’s data.
OR
(c) If the investigation does not result in a satisfactory resolution, the
shipper/receiver difference must be resolved by the Departmental
Elements concerned through traditional DOE line management
channels.
(7) The receiving facility must not process SNM contained in a shipment
involving an unresolved significant shipper/receiver difference unless a
shipper/receiver agreement allowing this has been approved by both the
shipper’s and receiver’s DOE cognizant security authority.
b. Inventory Difference Evaluation.
Section 34
(1) A program for evaluating all SNM inventory differences, including those
involving missing items must be developed, documented and implemented
for each facility. Programs for evaluation of inventory differences for
other nuclear materials may be established at the option of DOE line
management. The site/facility operator must develop and implement
procedures for establishing control limits and requiring an investigation
when those limits are exceeded. All inventory differences that exceed
control limits must be reported. Assessments of inventory differences
must include statistical tests (e.g., tests of trends and biases) and must be
applied, as appropriate, to both total inventory difference and actual
inventory difference on both an individual and a cumulative basis for each
processing MBA. Inventory records, process logs (where available), or
other information may also be used to detect anomalies and trigger
investigations.
(2) Procedures for establishing control limits for inventory differences of
SNM must be based on variance propagation using current data. The data
should reflect operating conditions for the material balance period of the
inventory. Other methodologies may be used but they must be approved
by the DOE cognizant security authority and must be justified based on
factors such as limited data, low transfer rates, and/or material category.
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For Category IV MBAs, control limits may be based on professional
judgment with the approval of the DOE cognizant security authority.
Significant differences between historical limits and limits based on
variance propagation must be investigated for the purpose of validating,
revising, and refining the variance propagation model.
(3) Documented procedures must be established and implemented for
responding to and reporting missing items and inventory differences in
excess of control limits. (See DOE M 470.4-1 for additional information
on reporting missing items and inventory differences exceeding control
limits.)
c. Evaluation of Other Inventory Adjustments.
(1) The site/facility operator must establish a documented program for
evaluating all inventory adjustments entered in the accounting records.
The program must have written procedures, including equations for
applying radioactive decay and fission transmutation adjustments. A
program for holdup adjustments must be justified on the basis of
measurements or other factors. The program must include documented
procedures for the statistical review of inventory adjustments using
techniques such as tests of trends, biases, and correlation.
(2) Procedures must be developed and implemented to ensure that all
inventory adjustments are supported by measured values or other
technically justifiable bases. The program must include procedures for
measuring and monitoring environmental waste such as stack effluent and
liquid waste streams as required by environmental protection program
directives and regulations.
(3) Procedures must be established and implemented for reporting reviews of
inventory adjustments, including abnormal situations, to the DOE
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CHAPTER III - MATERIALS CONTROL
1. GENERAL. This Chapter describes the requirements for nuclear material control,
consisting of four functional areas: access controls, material surveillance, material
containment, and detection/assessment. The graded nuclear materials control program
must be documented in the MC&A plan.
Section 35
2. ACCESS CONTROLS. A graded program must be established to control personnel
access to: nuclear materials; nuclear materials accountability, inventory, and
measurement data; data-generating equipment; and other items/equipment the misuse of
which could compromise the safeguards system.
a. Materials Access. A documented program must be established and implemented
for each facility to ensure that only properly authorized personnel have access to
nuclear materials. This program must address procedures and mechanisms to
detect and respond to access by unauthorized personnel. To minimize the
potential for unauthorized access to nuclear material, the amount of material in
use must be limited to that necessary for operational requirements, and excess
material must be stored in repositories or kept in enclosures designed to ensure
that access will be limited to authorized individuals.
b. Data Access. Procedures must be established that ensure only authorized persons
have the ability to enter, change, or access MC&A data and information.
c. Equipment Access. Access must be controlled to data-generating and other
equipment used in material control activities. Such equipment includes
measurement equipment, data-recording devices, and TIDs.
d. Other Considerations. Access control programs must protect against unauthorized
data and equipment modification and detect unauthorized activities during
emergency or other unusual conditions.
3. MATERIAL SURVEILLANCE. A nuclear materials surveillance program must: ensure
that nuclear materials are in their authorized locations, be capable of detecting
unauthorized activities or anomalous conditions, and be capable of reporting material
status. The surveillance program must address both normal and emergency conditions
and include periodic testing.
a. Material Surveillance Mechanisms. Material surveillance methodologies must
include: automated systems (e.g., monitoring devices, sensors, or other
instrumentation); or visual surveillance/direct observation (e.g., the two-person
rule, monitoring by external personnel); or other alternative safeguards measures
that provide the necessary detection.
When the direct observation method is used, the observer must have the means to
recognize, correctly assess, and report activities that are unauthorized or
inconsistent with established safeguards and security requirements.
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b. Material Surveillance Programs. Surveillance procedures must describe the
methodologies and operational/control points on which the program is based and
provide for investigation, notification, and reporting of anomalies.
(1) Category I and II. Material surveillance programs for Category I and II
quantities of SNM must ensure that materials are in authorized locations
and that unauthorized material flows and transfers are detected. Category
I locations must be evaluated to determine the ability of the material
surveillance system to assess material losses from MAA and PA
boundaries. Category II locations must be evaluated to determine the
ability of the material surveillance system to assess material losses from
the PA boundary.
(a) Material surveillance programs for all areas containing Category I
or II quantities of SNM must include the following measures.
1 Only authorized and knowledgeable personnel who are
capable of detecting incorrect or unauthorized actions can
be assigned responsibility for surveillance of SNM.
Section 36
2 Controls must be sufficient to ensure that a lone individual
cannot gain access to a secure storage area.
3 All persons in secure storage areas must be under constant
surveillance (e.g., the two-person rule or equivalent
surveillance) at any time the storage area is not locked and
protected by an active alarm system.
4 Surveillance must ensure that unauthorized or
unaccompanied authorized personnel cannot enter the
storage/processing area undetected when the door is
unlocked or open.
5 When items are outside an alarmed storage area within an
MAA or PA, there must be a system of hardware,
procedures, and administrative controls sufficient to ensure
that unauthorized accumulation of a Category I quantity is
detected. When the two-person rule is utilized as an
administrative control, the two authorized persons assigned
responsibility for maintaining direct control of the items
must be physically located where they have an
unobstructed view of each other and the items, and can
positively detect unauthorized or incorrect procedures.
6 SNM in use or process must be under material surveillance,
under alarm protection, or, with the approval of the DOE
cognizant security authority, protected by alternative means
that can be demonstrated to provide equivalent protection.
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(2) Category III. The material surveillance program for Category III
quantities must ensure that when materials are not in locked storage, they
are attended, are in authorized locations, and are not accessed by
unauthorized persons.
(3) Category IV. The material surveillance program for Category IV
quantities must be site-specific and approved by the DOE cognizant
security authority.
4. MATERIAL CONTAINMENT. A documented program must be in place to provide
controls for nuclear materials operations relative to MAAs, PAs, MBAs, other authorized
storage repositories, and processing areas.
a. Material Access Area and Protected Area. Controls must be in place to ensure
that Category I quantities of SNM are used, processed, or stored only within a
MAA contained in a PA and that Category II quantities of SNM are used,
processed, or stored only within a PA. The containment program must do the
following:
(1) identify authorized activities and locations for nuclear materials;
(2) identify mechanisms used to detect unauthorized activities;
(3) identify material types, forms, and amounts authorized to be removed
from the MAA or PA;
(4) identify containment controls for normal and emergency conditions;
(5) require a periodic audit of the containment program to ensure compliance
and system effectiveness; and
(6) evaluate roll-up.
b. Material Balance Area. Controls must be established and implemented for each
facility to ensure that nuclear materials are used, processed, or stored within an
MBA and are controlled in accordance with the graded safeguards concept. These
controls must ensure that materials are removed only through authorized
pathways or portals and are subject to transfer and verification procedures
identified in Section A, Chapter II, paragraph 5 of this Manual. Controls for
MBAs must meet the following:
(1) be formally documented;
(2) identify geographical boundaries and functions of the MBA;
(3) identify material types, forms, and quantities permitted in each MBA;
(4) describe administrative controls for each MBA;
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Section 37
(5) define custodial responsibilities for nuclear materials contained within an
MBA;
(6) identify personnel authorized to receive or ship nuclear material;
(7) identify material flow into and out of the MBA;
(8) ensure material transfer procedures are followed; and
(9) ensure that material quantities transferred across MBA boundaries are
based on measured values consistent with Chapter II, paragraph 5.b.(5).
c. Storage Repositories. (See DOE M 470.4-2)
d. Processing Areas. Controls must be established for nuclear materials being used
or stored in processing areas. The controls for in-process areas must do the
following:
(1) describe activities and locations for storing material;
(2) identify components used to detect unauthorized activities or conditions;
(3) include procedures for moving material into or out of the processing area;
(4) describe control procedures for normal and emergency conditions and for
maintenance activities;
(5) describe response actions to be taken in abnormal situations; and
(6) provide for audit of the processing controls on a periodic basis to ensure
system effectiveness.
5. DETECTION/ASSESSMENT. Systems must be in place to detect and assess the
unauthorized removal of nuclear materials, consistent with the graded safeguards
concept. The system must be interfaced with the facility’s physical protection and other
organizational systems, as appropriate, and must be able to detect and localize removal of
SNM from its authorized location, and notify the protective force and other organizations
to respond when such events are detected.
a. Tamper Indicating Devices. A documented program, administered by the MC&A
organization, must be in place to control TIDs and ensure that TIDs are used to
detect violations of container integrity. TID programs cannot be regarded as
effective unless used in conjunction with a material surveillance program.
Verification measurements rather than confirmation measurements must be used
for Category III or greater items that are not under a material surveillance
program. Testing of TID integrity, location, application, and the TID record
system must be conducted. The TID control program must include the following
elements:
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(1) TID acquisition/procurement/destruction;
(2) types of TIDs used;
(3) unique TID identification;
(4) storage;
(5) issuance;
(6) personnel authorized to apply, remove, and dispose of TIDs;
(7) containers on which TIDs are to be applied;
(8) procedures for application TIDs;
(9) frequency and method of TIDs verification;
(10) procedures for responding to and reporting of TIDs violations;
(11) assurance that TIDs cannot be reused after violation;
(12) frequency and method of internal program audits;
(13) a DOE cognizant security authority approved listing of all containers
considered to be intrinsically tamper-indicating.
b. Portal Monitoring. The detection level of the SNM portal monitors must be based
on the types and forms of SNM used, stored, or processed in the area and the
credible number of removals associated with theft of a Category I quantity of
SNM. Controls must be established to prevent unauthorized access to portal
monitor instrumentation and cabling. A written response plan must be prepared
and implemented to provide evaluation and resolution of all alarm conditions.
(See DOE M 470.4-1, Safeguards and Security Program Planning and
Management, for additional information on reporting security incidents.)
Section 38
c. Controls. Controls must be established to ensure detection equipment remains
operational during emergency conditions. Detectors and calibration standards
must be maintained and controlled to ensure that portal monitors are capable of
meeting detection requirements. Periodic performance testing of portal monitors
must be conducted in accordance with this Manual.
d. Waste Monitors.
(1) All liquid, solid, and gaseous waste streams leaving an MAA must be
monitored to detect the theft or diversion of SNM. Facility waste-
monitoring equipment must be maintained and controlled to ensure that
the equipment is capable of detecting specified amounts of SNM as
determined by the DOE cognizant security authority. Instrumentation
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used to monitor waste and equipment removed from an MAA must be able
to detect, in combination with other detection elements, the removal of a
Category I quantity of SNM through a credible theft or diversion scenario.
(2) A response plan for evaluating and resolving situations involving any
discharge exceeding facility-specific limits must be established by the
site/facility operator for the facility, and approved by the DOE cognizant
security authority.
e. Daily Administrative Checks. Daily administrative checks must be implemented
for each Category I MBA (or multiple MBAs where roll-up to a Category I
quantity of SNM is credible). The DOE cognizant security authority must
determine and approve the scope and extent of the checks and specify the
detection objectives on the basis of recognized vulnerabilities.
f. Other Detection/Assessment Mechanisms. MC&A systems must be established
for monitoring and control to provide the capability of detecting and assessing
unauthorized SNM removals. Systems can include weight sensors, SNM/physical
presence detectors, fiber optic seals, surveillance cameras, vault monitors,
emergency egress radiation monitors, real-time inventory locator systems, etc.
The MC&A system must provide sufficient information to correctly assess the
alarms, localize the removal, and estimate the quantity and form of the diverted or
stolen material.
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1
SECTION B - BASIC REQUIREMENTS FOR NUCLEAR MATERIALS
MANAGEMENT AND SAFEGUARDS SYSTEM REPORTING AND DATA
SUBMISSION
1. DOCUMENTATION AND REPORTING.
a. All RIS-level nuclear materials transactions, material balances, and inventories
must be documented in accordance with the instructions provided in Section B of
this Manual and reported to the Nuclear Materials Management and Safeguards
System (NMMSS), the national database for nuclear materials.
b. The NMMSS will be used to accumulate and distribute information concerning
nuclear materials transactions, material balances, and inventories.
c. Submissions must be made in a timely manner to achieve reporting of accurate
and complete data as soon as possible after the events described by the data occur.
d. The national database will provide nuclear materials information relating to
safeguards, materials management and production, inventory quantities and
valuations, and other information requested or required by DOE and NRC.
e. The national database will serve as the centralized reporting facility to provide the
information required under the provisions of the United States/International
Atomic Energy Agency (IAEA) Safeguards Agreement.
f. All NMMSS data submissions that are mailed will be sent to the NMMSS
operator at—
Section 39
NAC International
NMMSS Project
P.O. Box 922088
Norcross, GA 30010
Attn: Document Control
g. The correct manuals to use when reporting nuclear material to NMMSS are as
follows.
(1) This Manual will be used to report all United States (U.S.) Government
owned (owner code G) nuclear materials (See Tables XV-1 and XV-3),
and non-Government owned (owner code J) nuclear materials located on a
DOE site.
(2) NRC NUREG-006 and NRC NUREG-007 are used to report
non-Government owned (owner code J) nuclear materials located at a
licensee facility.
(3) Facilities, projects, and programs under the cognizance of the Office of
Civilian Radioactive Waste Management subject to NRC regulation must
use the rules, standards, and criteria specified by the NRC or the NRC
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Agreement State in lieu of this Manual.
2. FORMS.
a. Data collection forms identified and described in this Manual (see Chapter XVII)
(or the electronic equivalent) will be used to document and report nuclear
materials transactions, material balances, and inventories in accordance with the
instructions provided in this Manual.
b. A computer-generated form must contain all information necessary for proper
documentation and reporting of nuclear materials transactions, material balances
and inventories. Examples of the paper forms are provided in Chapter XVII for
informational purposes and are not to be used to supply data to the NMMSS. The
required forms that must be used are available from the NMMSS operator and
online at the DOE Directives website (www.directives.doe.gov).
3. REPORTING IDENTIFICATION SYMBOL (RIS).
a. Data entered into the NMMSS is keyed to sets of RISs. The establishment,
maintenance, and deactivation of an individual RIS will be based on criteria
detailed in Chapter I of this Manual.
b. Unless a shipment is covered by one of the exclusions noted in this Manual (e.g.,
shipments to DoD), in other DOE Orders or Manuals, or other agreements,
reportable quantities of accountable nuclear material will be shipped only to
facilities with a valid RIS.
c. Following annual review of RIS information, cognizant DOE line management
will provide to the NMMSS operator a locally generated memorandum verifying
the information listed for the RISs under their purview, or noting any changes.
The memorandum may be submitted via facsimile, e-mail, or online, as
appropriate.
d. A yearly updated copy of the RIS directory is available from the NMMSS
operator.
4. CORRECTION DATA. Corrections of data previously submitted and found to be in
error must be submitted to NMMSS within 1 working day following notification of the
error.
5. PERIODIC RECONCILIATION OF FACILITY DATA WITH NMMSS. Reconciliation
of inventory data is required of facilities following September submissions. The process
to be followed is set forth in Chapter XIII, Inventory Reporting.
6. CONFIDENTIALITY OF DATA.
a. Information requested must be classified as required by DOE classification
guidance. Classified information is exempt from public disclosure under the
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Freedom of Information Act (FOIA). (See 5 U.S.C. 552.)
b. Unclassified information collected in NMMSS is subject to public disclosure.
Exemption from disclosure can be requested. (See exemption categories in DOE
G 471.3-1, Guide to Identifying Official Use Only Information, dated 4-9-03.) A
respondent may specifically request that data be withheld under the applicable
FOIA exemption; however, the final determination with regard to disclosure or
nondisclosure of information will be made by DOE.
Section 40
c. DOE regulations for handling proprietary information of a private business,
foreign government, or an international organization [10 CFR 1004.11(b)] allow a
respondent to advise DOE that data submitted on the forms should not be made
available to the public. A new written justification need not be submitted each
time data is submitted if the respondent’s views with regard to the confidentiality
of the information requested have not changed.
7. CLASSIFICATION OF DATA. Data submitted to NMMSS must be classified, marked,
transmitted, and handled commensurate with DOE M 470.4-6, Information Security,
DOE M 475.1-1A, Identifying Classified Information, and applicable DOE classification
guidance.
8. CONTACT. Comments and inquiries may be directed to the Office of Plutonium,
Uranium and Special Materials Inventory, or the NMMSS operator (www.nmmss.com) at
the following address.
NAC International
NMMSS Project
P.O. Box 922088
Norcross, GA 30010
Attn: Document Control
9. NMMSS PROGRAM MANAGEMENT AND QUALITY CONTROL. Two sources for
information regarding quality assurance of the NMMSS database and program are the
DOE Chief Information Office (CIO) and the DOE Management Control Program. (See
DOE O 413.1A, Management Control Program, dated 4-18-02.) In the CIO’s Office, the
DOE Information Architecture program helps ensure compliance with OMB Circular
A-130, Management of Federal Information Resources (2003) and the Clinger-Cohen
Act of 1996 by promoting standard architectural practices, providing a framework for
corporate systems modernization, and establishing an information architecture vision
aligned with the Department’s strategic goals.
10. SPECIFICATIONS FOR SOFTWARE AND HARDWARE SYSTEMS. Software and
hardware systems used to implement NMMSS must follow guidelines promulgated by
the DOE CIO’s office in accordance with OMB Circular A-130 and the Clinger-Cohen
Act of 1996. One of the goals of these standards is to ensure compatibility of systems
and databases and thereby decrease the costs associated with non-standard or
incompatible systems.
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I-1
CHAPTER I - INSTRUCTIONS FOR APPLYING FOR, CHANGING, OR DELETING
A REPORTING IDENTIFICATION SYMBOL
1. INTRODUCTION.
a. Each contractor and facility Reporting Identification Symbol (RIS) is associated
with a specific DOE element. A RIS must consist of a minimum of three
alphabetic characters, and in special circumstances, a maximum of four
characters. This and other information concerning instructions for RIS lettering
conventions can be obtained from the NMMSS operator.
b. DOE line management must forward requests for new RISs or revisions of RIS
information and any requests for activation, or deactivation, of a RIS
accompanied with the effective date of activation, deactivation, and/or transfer, to
the following address:
NAC International
NMMSS Project
P.O. Box 922088
Norcross, GA 30010
Attn: Document Control
2. PROCEDURES AND CRITERIA FOR ESTABLISHING A RIS.
a. To establish a RIS the following procedure applies.
(1) A request from the MC&A field representative, who may be either a DOE
Federal or contractor employee, is routed to the DOE cognizant security
authority for review and approval.
(2) A DOE Headquarters (HQ) sponsoring program office must approve
activities for which the RIS is requested.
Section 41
(3) The request is then sent from the DOE cognizant security authority,
through the appropriate HQ program office, for coordination with the
Office of Plutonium, Uranium and Special Materials Inventory to establish
the RIS required for DOE approved activities.
(4) The Office of Plutonium, Uranium and Special Materials Inventory
instructs the NMMSS operator to add the RIS.
b. Justification must exist before a new RIS can be established. The following is a
list of common reasons for requesting a new RIS. The facility must:
(1) anticipate Departmental authorization to contain an inventory of nuclear
materials within the next 12 months;
(2) be involved in international shipments or receipts of nuclear materials; or
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(3) be storing or processing material under International Atomic Energy
Agency safeguards.
c. A facility that does not meet the above criteria, but believes a RIS is necessary for
operations, can request a RIS by submitting proper justification and
documentation through the DOE Cognizant Security Authority to the Office of
Plutonium, Uranium and Special Materials Inventory by following the procedure
outlined in paragraphs 2.a.(1)-(4) above.
3. APPLICATION FOR A RIS. To establish a new RIS, the DOE cognizant security
authority must provide the following information to be listed in the NMMSS directory.
a. Facility/RIS information.
(1) Facility name.
(2) Date RIS issued.
(3) Contract number.
(4) Code of responsible financial organization.
(5) DOE field element or site office RIS.
(6) Contractor type.
(7) Operation type.
(8) FAX Numbers.
(a) Classified.
(b) Unclassified.
(9) FAX verification number.
(a) Classified.
(b) Unclassified.
(10) Secure Information Management and Exchange Network (SIMEX)
routing indicator.
(11) Additional information on facility/RIS.
b. Contact information.
(1) Nuclear materials representative (NMR).
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(a) Name.
(b) Telephone number.
(2) Alternate NMR (NOTE: More than one alternate NMR is allowed).
(a) Name.
(b) Telephone number.
(3) Nuclear materials financial representative.
(a) Name.
(b) Telephone number.
(4) Authorized contact for information changes.
(a) Name.
(b) Telephone number.
(5) Any additional contact/inquiry information.
c. Mailing information.
(1) Addresses (including facility name and unclassified address).
(2) For a classified address, use guidance from the Safeguards and Security
Information Management System (SSIMS). Contact a cognizant security
authority for the current phone number. Do not enter a classified address
with this data.
(3) Any additional financial and mailing information.
d. Shipping address and information.
e. Additional information not covered elsewhere.
f. The following logistical information is required for RIS directory appendices and
program controls. Enter “N/A” where requested data is not applicable.
(1) Effective date nuclear materials will be transferred from old
contractor/facility (enter old RIS) to new contractor/facility.
(2) Effective date the DOE office will assume responsibility for the new RIS.
(3) Frequency of the new RIS inventory reporting.
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(4) The nuclear materials inventory profile (I-17 report from NMMSS) for the
new RIS (may be the same as the old RIS; if not, provide new profiles).
Section 42
(5) Level of classification for transactions, inventory, and material balance
reports (MBRs) throughput for the new RIS and for related reporting
products from NMMSS.
(6) Mode of transmitting input data from the new RIS to NMMSS.
(7) Cost center for new RIS’s financial activity.
(8) Authorized contacts (may be different from NMR or alternate) and phone
numbers.
g. NMMSS operator staff will work with each facility to identify reports that must
be submitted for each RIS.
4. DEACTIVATION OF A RIS.
a. RIS deactivation will occur when a facility’s authorization to store/handle nuclear
materials inventory is withdrawn. Before deactivation, all open transactions must
be resolved and all inventory removed to a balance of zero.
b. The NMR of the RIS being deactivated should initiate and receive certification
from the NMMSS operator that no project numbers exist for that RIS. If there are
project numbers associated with the RIS that is to be deactivated, the project
numbers must be cancelled or changed to reflect proper status of the material.
c. An assessment by the MC&A field representative must conclude the following.
(1) All physical MC&A activities have been terminated.
(2) All material has been shipped from the facility.
(3) The balance for that RIS in NMMSS is zero (0).
(4) No investigations or audits are under way concerning any aspect of
MC&A.
d. Notification of deactivation is sent from the DOE cognizant security authority to
the Director, Office of Plutonium, Uranium and Special Materials Inventory, who
will instruct the NMMSS operator to deactivate the RIS.
e. A waste facility’s RIS must not be removed except with specific approval of the
responsible Departmental Element through the DOE cognizant security authority
and upon coordination with the Director, Office of Plutonium, Uranium and
Special Materials Inventory.
f. A parent RIS must not be deactivated when a sub-RIS is still active.
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5. CHANGING RIS INFORMATION.
a. The following procedure must be followed to change information entered on a
facility’s RIS directory page.
(1) Make a copy of both sides of the page from the RIS directory for each
affected RIS.
(2) Draw a line through the outdated/erroneous information on the copy.
(3) Immediately above the strike-out, print the new information clearly.
(4) Submit the pages marked for change to the NMR, or other authorized
person who will sign and date all directory pages on which changes have
been recorded. Unsigned changes cannot be made.
(5) Send page changes to the DOE cognizant security authority for approval
and forwarding to the NMMSS operator.
b. The NMMSS operator will provide a written copy to the Office of Plutonium,
Uranium and Special Materials Inventory for information/file purposes.
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CHAPTER II - GENERAL INSTRUCTIONS
This Chapter provides general instructions for all reports sent to NMMSS and additional
guidance where appropriate. Three types of information are submitted to NMMSS: transactions,
material balances, and inventories. Additional guidance for specific types of reporting is
provided in subsequent Chapters.
1. REPORTING TO NMMSS.
a. Facilities must report data to the NMMSS electronically. If electronic means are
unavailable, reporting using paper forms is permitted; however, it must be
coordinated through the DOE cognizant security authority. Under emergency
conditions or if a special, non-standard report is required, paper forms may be
used.
Section 43
NOTE: In this Manual, paper forms and numbers (e.g., DOE/NRC Form (F) 741)
are mentioned for instructional purposes. The fact that a paper form is available
does not relieve the facility from the requirement to report electronically.
b. When a reportable quantity of an accountable nuclear material is recovered during
deactivation, decommissioning, or decontamination, the recovered material must
be reported to NMMSS, even when the material has been previously written off
the NMMSS records. A DOE/NRC F 741 must be used.
c. Facilities are encouraged to use the NMMSS software package, Safeguards
Management of Software, to edit site data prior to submitting electronic data to
NMMSS. This software may be obtained from the NMMSS operator.
2. DATA ACCURACY. DOE line management is responsible for ensuring that the
NMMSS accurately reflects nuclear material inventory data at license-exempt facilities,
and DOE-owned nuclear material inventory data at licensed facilities.
3. NMMSS REPORTABLE ELEMENTS AND ISOTOPES, AND REPORTING UNITS.
a. The elements and isotopes that must be reported to NMMSS are shown in
Table XV-1.
b. Weights must be reported in the metric weight units specified for each nuclear
material as shown in Table XV-1.
c. Both element and isotope weights are reported if they round to a reportable
quantity. In cases where the element is a reportable quantity, but the isotope is
not a reportable quantity, the material must still be reported, but for the isotope,
enter 0 (zero). In cases where the isotope is a reportable quantity, but the element
is not a reportable quantity, the material must still be reported but for the element
enter 0 (zero). (See paragraph 6. and Table II-1, below)
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4. MATERIAL TYPE CODES. Table XV-2 provides the material type (MT) codes used by
DOE for reporting nuclear materials. Note that other entities (e.g., IAEA) may use
different codes for the same materials.
5. UNITS, STANDARDS, CONVERSIONS, AND DATA DEFINITIONS.
a. Metric units are required for reporting information to the NMMSS.
b. If weights are in pounds, the conversion factor 0.45359 kg/pound must be used.
c. A year is defined as 365.2422 days.
d. Nuclear material properties (e.g., half-lives) can be found online at
www.nndc.bnl.gov. For other material properties and equations, see CRC
Handbook of Chemistry and Physics.
e. Measurements that have been made, and records that have been kept, in volume
units must be converted to the reporting unit for the material type. Material
properties and equations in the CRC Handbook of Chemistry and Physics must be
used to convert gas or liquid volumes to the appropriate units.
f. Parts per million calculations will be recorded as—
(1) ppmv for volume basis,
(2) ppm for mass basis, and
(3) ppma for number of atoms basis.
g. The calculation for ppm of U-232 in total uranium is a mass basis.
h. NMMSS will not accept slashes (\ and/), semi-colons (;), colons (:), question
marks (?) or number sign (#). Do not use those characters when entering data.
i. For the definitions of data elements, e.g., field length and whether a numeric or
alpha character is allowed, see NMMSS Reports D-23 (for DOE) and D-24 (for
NRC), available from the NMMSS operator.
6. ROUNDING POLICY.
a. Quantities will be reported as shown in Table II-1, below with fractions of ½ or
greater rounded upwards and fractions of less than ½ of a reporting unit reported
as the number zero (0).
Section 44
b. Nuclear material transactions should be documented and reported as accurately as
possible to reflect the actual quantity of material transferred. If a transaction of
discrete items, each of which is less than a reportable quantity, sum to a reportable
quantity, the transaction should be recorded to most accurately reflect the actual
quantity involved. The shipper and receiver will decide how to ensure appropriate
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accounting documentation in NMMSS. Both the shipper and receiver must agree
on the method to use. If the shipper and receiver cannot agree, the Office of
Plutonium, Uranium, and Special Material Inventory will decide how best to
document the transaction.
c. When performing general calculations not related to discrete items in a
transaction (see paragraph 6.b. above), do the calculation first before rounding.
d. For software development purposes, sites or facilities may use more significant
digits than noted in this Manual.
Table II-1. Rounding Policy.
Quantity Action
Equal to or greater than
0.5 of the reporting unit
Report to the nearest
whole reporting unit
Less than 0.5 of the
reporting unit
Report as 0 (zero)
7. NUCLEAR MATERIAL BLENDING TRANSACTIONS.
a. Blending or crossovers of materials are reported to the NMMSS to ensure
accurate records of the facility’s material inventory. The report to the NMMSS
would show the reduction in one or more quantities and the increase in another.
(1) Inventory change code 22 (from other materials) is used to show the gain
in material.
(2) Code 71 (degradation to other materials) is used to show the reduction of
material.
b. The NMMSS has been programmed to recognize a blending or crossover
operation by the order in which the codes 22 and 71 are presented. The lines of
data on DOE/NRC F 741 must appear in sequence. That is, a line or lines with
code 22 must be followed by matching line or lines with code 71. There are two
methods of matching codes 22 and 71. One method is to pair code 22 with the
corresponding 71, a second method is to list a series of code 22s followed by
corresponding 71s (See Table II-2 below for an example).
c. When reporting a blending transaction with multiple sets of code 22/71
combinations, the position of the 22 in the data set must correspond to the
position of the 71 in the data set. For example, row number 1 must correspond to
row number 6. This case represents the blending of material from summary
MT 10 to summary MT 20. Row 2 must correspond with row 7 in the data set,
etc. For specific format requirements, refer to the guidance for electronic format
data submissions.
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Table II-2. Blending Transaction Example.
Row
Number
Type
Inventory
Code
Summary
Material Type
1 22 10
2 22 10
3 22 50
4 22 50
5 22 50
6 71 20
7 71 81
8 71 83
9 71 83
10 71 83
d. In reporting blending operations, follow the code 22 and 71 matching rules in
addition to the following.
(1) As an internal transaction, RIS entries must be identical.
(2) Use action code M.
(3) The two data lines, codes 22 and 71, must agree in terms of quantities,
plus or minus a reportable unit.
(4) Plutonium blending operations must also be reported. For such blending
operations, only the element weight (total plutonium) is compared. The
different MTs of plutonium account for the different isotopes of
plutonium. For example, the reportable isotope for MT 50 is Pu-239+241.
The reportable isotope for MT 83 is Pu-238. When blending these
plutonium MTs, there is no direct relationship between the individual
isotope weights.
Section 45
(5) For blending operations with different accountable nuclear materials, the
relative quantity (mass) of each accountable material is to be maintained.
8. OWNER CODES. The codes in Table XV-3 are used to identify ownership of nuclear
material for transactions and inventory reporting. For instructions regarding the proper
owner code to be used in a particular circumstance, contact the NMMSS operator.
9. LIMITS OF ERROR ON TRANSFERS OF SPECIAL NUCLEAR MATERIAL AND
TRITIUM.
a. DOE contractors will determine and notify DOE of limits of error on transfers of
SNM and/or tritium (except in the case of tritium in reservoirs), as required by
Section A, Chapter II, 5.a.(4)(d).
b. Such notification will be made on a DOE/NRC F 741.
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c. Limits of error will be recorded on all copies of the form.
10. NORMAL OPERATIONAL LOSSES (NOLs), MEASURED DISCARDS AND
ACCIDENTAL LOSSES.
a. The instructions in this Section are provided to supplement the reporting
procedures for NOLs, measured discards and accidental losses. Losses and
discards are reported using a DOE/NRC F 741.
b. When reporting NOLs, measured discards or accidental losses, the following
apply.
(1) License-exempt and/or licensed contractors not subject to the requirements
of the U.S./IAEA Safeguards Agreement will use one of the following.
(See Chapter IV for transaction definitions.)
(a) A-M transactions to remove loss or discard material from active
inventory for subsequent shipment to a waste management site.
(b) A-A transactions remove material from active inventory when—
1 it is shipped to a waste management site,
2 it has been discharged to the atmosphere or the ground, or
3 it has been consumed in use.
(2) License-exempt and/or licensed contractors subject to the requirements of
the U.S./IAEA Safeguards Agreement will use A-A transactions.
(3) If paragraph 10.b.(1)(a) or 10.b.(1)(b) applies, one of the letters listed
below may be appended to the facility’s 3-character RIS, as appropriate.
The 3-character identifier will be entered as the shipper’s RIS in block 1
of DOE/NRC F 741 or as the receiver’s RIS in block 2. The 3-character
identifier must be on file with the NMMSS before it is used for reporting
to the system. The following letters are for use by all reporting facilities.
(a) A—discharge to the atmosphere,
(b) G—discharge to the ground or a body of water or stream,
(c) I—discharge to run-off, and
(d) R—consumed during use.
NOTE: It is understood that recovery of material discharged to the ground
as a result of an accidental loss may not be possible.
(4) The following letters are for use only by license-exempt contractors
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subject to the requirements of the U.S./IAEA Safeguards Agreement and
licensed contractors.
(a) H—a waste holding area from which material could be recovered
and
(b) L—a lagoon, holding pond, or tank from which material could be
recovered.
(c) The use of codes H and L is optional for non-licensed contractors
not under IAEA reporting requirements.
(5) When reporting NOLs or measured discards, enter code 74 as the
inventory change code in block 26c or 27c of DOE/NRC F 741, as
appropriate.
(6) When reporting accidental losses, enter code 75 as the inventory change
code in block 26c or 27c of F 741, as appropriate.
(7) When reporting the return to active inventory of material previously
reported as a NOL, measured discard, or accidental loss, follow the
instructions below. (See Table XV-19 for additional information.)
Section 46
(a) A previously reported NOL, measured discard, or accidental loss
may be reversed through the adjustment process.
(b) An A-B transaction with no inventory change code, (transfer from
a V RIS, or waste disposition area, to a facility) may be reported to
the NMMSS as a receipt on line 30 of the MBR generated for the
receiving facility. [NOTE: This applies only if the waste
disposition area is an onsite waste holding area (H) or a
lagoon (L).]
11. WASTE AND BURIAL SITES.
a. For site closure or decommissioning, or if the receiver requires documentation,
report waste transactions as follows.
(1) Document transactions of waste material using DOE/NRC F 741.
(2) For transfers of nuclear material from a waste disposition area (i.e., a
3-character RIS with a fourth character H, G, or L appended) to a waste
management site (V RIS), the applicable composition/facility code will be
entered in block 26h of the DOE/NRC F 741 documenting the transfer.
(3) Transfers to or from a waste management site (V RIS), including transfer
from one waste management site to another, and transfers identified with
character H appended to the RIS, will be reported to the NMMSS on a
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DOE/NRC F 741.
(4) Shippers and receivers will evaluate and make changes and adjustments to
records, as necessary, based upon remeasurement.
b. A waste disposition area on the site subject to both DOE and NRC reporting
requirements will be assigned at least one 4-character RIS. The first three
characters must correspond to the DOE or the NRC RIS for the facility. It is only
required that one 3-character RIS be assigned for reporting data for the waste
disposition area. The assignment of more than one RIS to a waste disposition
area will be at the discretion of DOE line management.
12. RADIOACTIVE DECAY.
a. Radioactive decay will be reported in accordance with Chapter XV, Tables XV-4,
XV-5, and XV-6.
b. Facilities will send data on reportable quantities of radioactive decay to the
NMMSS on a DOE/NRC F 741 in accordance with instructions in Chapter III of
this Manual.
c. The shipping facility will calculate and report decay on material in transit up to
the first day of the month in which the material was shipped.
d. Using a locally generated report or memorandum, the shipper will inform the
receiver of the date on which decay for the items being shipped was last
calculated.
e. The receiving facility will calculate decay for the entire month in which the
shipment was received or in which the shipment was in transit at the report date;
however, no decay will be reported until the end of the month in which the
material is actually received.
f. For material in transit over the period from the end of one month through the
beginning of another, the receiving facility will calculate and report decay for a
2-month period, i.e., the month in which the material was shipped and the month
in which it was received.
g. Daily decay constants will be calculated using the formula below (unless
half-lives are stated in days).
Decay Constant (days-1) = Ln(2) / (T½ * 365.2422)
where—
T½ = Half Life (years)
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h. Decay calculations are made for days, months, and quarters. Month and quarter
decay factors are provided for the convenience of the user. To calculate decay,
use the following formula.
Qt = Qo * e^(-d* C)
where—
Section 47
Qt = quantity of material left at time t after undergoing decay
Qo = initial quantity of material before calculating decay
d = number of days
C = decay constant from table. Can be either days, months, or quarters.
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CHAPTER III - NUCLEAR MATERIAL TRANSACTION REPORTING—GENERAL
1. INTRODUCTION. This Chapter provides general instructions for transaction reporting.
In addition to the instructions in this Chapter, specific procedures for completing each
form and for submitting the data to NMMSS are contained in Chapters IV and V. The
in-transit accounting rule that DOE has adopted states that when nuclear material leaves
the shipper, it officially goes on the receiver’s books in NMMSS.
a. Shipper-Receiver Differences. Consult Section A of this Manual for requirements
on evaluating shipper-receiver differences.
b. Transactions within the U.S. (non-DoD). Instructions are provided in Chapters
III, IV, and V.
c. Transactions of Obligated Material. See Chapters III, IV, V, and VIII of this
Manual.
d. Transactions Involving DoD. In any instance where either a contractor of U.S.
Government facility has a transaction involving a shipment to or receipt from
DoD pursuant to 42 U.S.C. 2121(b), or 2121(c) (which address DOE and mutual
defense activities) such facility must prepare and distribute DOE/NRC F 741 in
accordance with instructions provided in Chapter VI of this Manual and any
additional guidance which may be provided by DOE line management or the
DOE cognizant security authority.
e. Transactions Involving International Accounts. See Chapter VII of this Manual
for details.
(1) Foreign nations, foreign regional organizations, supranational
organizations, or foreign facilities (hereinafter referred to collectively as
foreign entities) may receive or return U.S. Government-owned material
obtained by sale, lease, grant, donation, or loan from contractor facilities,
or from NRC or Agreement State licensees, pursuant to 42 U.S.C. 2074
and 2094 and 42 U.S.C. 2112 or 2121(c).
(2) For a transaction involving an export/import, the facility must prepare
both the shipper’s and the receiver’s data and distribute the forms.
(a) For exports, the shipper should request that the foreign receiver
sign and return the DOE/NRC F 741 to the shipping facility to
document the transfer.
(b) For imports, if the foreign shipper’s data are incomplete or
unknown, the receiver should contact the DOE cognizant security
authority for further guidance.
(3) International transfer data should be handled according to the instructions
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for data input to the International Nuclear Material Tracking System
(INMTS) contained in INMTS Data Entry Procedures. For further
guidance regarding INMTS, contact the NMMSS operator.
(4) For international transfers that are covered by more than one export/import
license, a separate DOE/NRC F 741 must be prepared for the material
covered by each individual export/import license. See Chapter VII of this
Manual for details.
(5) Tracking imported material having foreign accounting obligations requires
the use of special tracking procedures. See Chapter VIII of this Manual
for details.
2. TRANSFER REPORTING TIMELINES. Data on all transactions occurring during a
calendar month will be submitted no later than 8 working days following the end of the
month during which the transactions occurred. These extra days are justified as time
needed for monthly closure of the books for reasons of monthly adjustments. Table III-1
shows deadlines for distribution of DOE/NRC F 741.
Section 48
Table III-1. Submission Dates for Physical Transfer of Material.
Type of Physical Transfer Requiring DOE/NRC F 741
Preparation and Distribution
Reporting Timelines
Shipper distributes to NMMSS and receiver for domestic
shipment
1 workday after receiving the foreign
receiver’s data.
Domestic receiver distributes to NMMSS and Shipper on
domestic shipment
10 workdays after receipt of shipment
Shipper distributes to NMMSS shipment and foreign
receiver’s side of the form
1 workday after receipt of shipment
Domestic distribution to NMMSS reporting material received
from foreign shipper
10 workdays after receipt of shipment
Corrections to submitted data sent to NMMSS and other party 1 workday after receipt of shipment
3. TRANSACTION DOCUMENTATION METHODS. Facilities must distribute
transaction documentation electronically unless manual/paper submission is coordinated
through the DOE cognizant security authority.
a. Electronic Method.
(1) Procedures and instructions in this Manual will apply except that
signatures on transaction documents are not required. Internal controls
will ensure that data transmitted has been properly authorized.
(2) The sender and recipient of electronic data will produce hard copies as
needed by organizations on the distribution lists in Table III-2 and Table
III-3, below.
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(3) The hard copies will contain the information normally included on
DOE/NRC F 741.
(4) For activities involving NRC or Agreement State licensees, the electronic
method of handling and transmitting transfer data will follow all
requirements of 10 CFR 74, Material Control and Accounting of Special
Nuclear Material.
b. Manual Method.
(1) Facilities with a low volume of reporting activity may prepare DOE/NRC
F 741 in paper form if coordinated with the DOE cognizant security
authority.
(2) Such facilities are encouraged to convert to electronic form preparation in
coordination with the NMMSS operator.
c. Either Method.
(1) Regardless of method used, nuclear material types, elements, and isotopes
to be reported, and their respective reporting units will be as specified in
Table XV-1.
(2) For each detail line of shipper/receiver data entries on DOE/NRC F 741,
material quantities reported by assay may be summarized, but only within
detailed MT assay ranges (e.g., for enriched uranium, within 10 to
20 percent U-235 or within 80 to 92 percent U-235, as appropriate)
required for reporting inventory (See Chapter XIII, Inventory Reporting).
d. Agreement of Transaction Data. Data sent to NMMSS will agree on a
line-for-line-basis with data sent between the shipper and receiver on DOE/NRC
F 741, or electronic equivalent.
4. CLASSIFICATION AND SECURITY REQUIREMENTS. DOE/NRC F 741 will be
classified using appropriate guidance and following the procedures contained in DOE
M 475.1-1A, Identifying Classified Information, and will be marked with appropriate
classification markings and transmitted following procedures contained in DOE M 470.4-
4, Information Security.
5. DISTRIBUTION OF DOE/NRC F 741.
a. Transaction information is generally distributed electronically; however, a few
small facilities continue to use the paper DOE/NRC F 741.
b. The distribution requirements, below, are to be followed regardless of transaction
format.
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(1) If an electronic format is used, do not also distribute a paper copy unless
specifically requested by the recipient.
Section 49
(2) It is recognized that some field elements or site offices do not desire
copies of transaction information in any format but, instead, rely on
NMMSS reports to satisfy local needs.
(3) As an absolute minimum requirement for distribution of transactions
information, copies should be provided to the other party to the transaction
and to the NMMSS operator at RIS QFA. For one-party transactions, the
facility generating the transaction must also provide a copy to the
NMMSS operator at QFA.
c. Primary Distribution is illustrated in Table III-2.
Table III-2. Primary Distribution.
Type of Transaction Other Party To
Transaction
QFA Shipper’s Field
Element (If Desired)
Receiver’s Field
Element
(If Desired)
Shipment of Material Yes Yes Yes Yes
Receipt of Material Yes Yes Yes Yes
One-party Transaction Yes Yes Yes Yes
d. Secondary Distribution is illustrated in Table III-3. Secondary distribution is the
distribution of transaction data by NMMSS operator staff, RIS QFA, based on
receipt of transaction data by primary distribution.
Table III-3. Secondary Distribution.
Transactions With Specific Material
Types and Conditions
Copy Distributed to
Operations/Site Office
Depleted uranium, normal uranium, enriched uranium,
californium, enriched lithium, U-233, thorium under
loan/lease to a licensee
Oak Ridge Field CFO and or
Financial Managers
Americium-241, plutonium, plutonium-238,
plutonium-242, neptunium-237, tritium, deuterium under
loan/lease to a licensee
Savannah River Field CFO’s and or
Financial Managers
e. The transaction data selected for secondary distribution is limited to ownership
code G, reflecting U.S. Government ownership of material under the loan/lease
program or sales of material.
f. Distribution is made to the field element or site office responsible for the specific
material under loan/lease to the element’s or office’s financial representative.
6. FACILITY TRANSFERS OF MATERIAL TO A FOREIGN ENTITY. The shipper will
include with the shipment a copy of DOE/NRC F 741 containing the shipper’s data. (See
Chapters VII, VIII, and IX and refer to DOE line management or the DOE cognizant
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security authority for guidance and further instructions.)
7. FACILITY RECEIVES NUCLEAR MATERIAL FROM A FOREIGN ENTITY. See
Chapters VII, VIII, and IX and refer to DOE line management or the DOE cognizant
security authority for guidance and further instructions.
8. TRACKING OF FOREIGN OBLIGATED MATERIAL WITHIN THE U.S.
a. Each facility will submit information necessary to track materials among facilities
that use foreign obligation codes.
b. The shipper is responsible for supplying foreign obligation information for each
shipment. Refer to Chapter VIII for further information.
c. If the resolution of a shipper-receiver difference on a detail line of data results in a
reduction of the shipper’s value to an amount less than the obligated amount, the
obligated amount must also be reduced. The obligated amount may not be greater
than the amount of like material shipped.
9. TRANSFERS INVOLVING THE DoD. Except for transfers of nuclear material in naval
cores and associated items, transactions will be documented in accordance with the
instructions provided in Chapter VI.
10. TRANSFERS OF NUCLEAR MATERIAL BETWEEN DOE CONTRACTORS AND
LICENSEES.
a. Transfers to Licensees. DOE contractors who receive authorization and requests
for distribution of nuclear material to a licensee, pursuant to 42 U.S.C. 2073,
2093, and 2111, will document such transfers using DOE/NRC F 741.
Section 50
b. Transfers from Licensees. Transfer documents for nuclear material shipped to
DOE for credit or service by a licensed facility will be prepared and distributed by
the shipper in accordance with the requirements of the CFR. When such material
is received it will be documented by the receiver using DOE/NRC F 741.
11. INTERNAL PROJECT TRANSFERS. It is required that transfers of material between
DOE projects under the same RIS be reported to the NMMSS (i.e. a change in project
numbers). Reporting is accomplished by submitting DOE F DP-749 or by electronic data
submission. Instructions for internal project transfers follow the general instructions for
transaction reporting with the following special guidance.
a. Facilities transmitting data to the NMMSS by automated means need not
complete DOE F DP-749, but must follow the data format defined below.
(1) Negative Values. Enter a minus sign or a dash preceding the digits to
show a negative number.
(2) Transaction Identification Information (columns 1–18 on DOE F DP-749),
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described below, is common to both header and detail records.
(a) Shipper columns 1–4. Enter the shipper’s or originator’s RIS for
transactions involving project transfers, left justified.
(b) Receiver columns 5–8. For project transfers enter the receiver’s
RIS left justified. The shipper’s and receiver’s RISs must be the
same.
(c) Columns 9–14, Internal Transaction Number. Enter the number
which indicates a specific transfer in a transfer series. An
alphanumeric journal entry number may be used in lieu of the
transfer number.
(d) Column 15, Correction Number. When a shipper or receiver
issues a corrected document to adjust data previously reported, an
alphanumeric character is appended to the original transfer number
to identify the transaction as a correction. For correction or
adjustment entries, this is a required data field. For all other
transactions, this field is left blank.
(3) Transaction Codes (THAN CODE).
(a) Column 16, Processing Code (PC). Enter the appropriate
1-character, alphabetic code from the list below to identify the
specific type of processing action required.
1 A—initial entry of data to report a transaction.
2 C—replacement of data for a transaction. An initial entry
cannot be replaced after the close of a processing period.
3 D—deletion of a transaction. An initial entry cannot be
deleted after the close of a processing period.
(b) Column 17. Make no entry.
(c) Column 18, Action Code (ACT CODE). Code letter P is
preprinted on the form to identify in-place transfers between
projects.
(4) Header Information—Data Record Number 1.
(a) Column 19, Data Code. Code number 1 is preprinted on the
form.
(b) Columns 20–21, Number of Lines. Enter numeric digits (01-99)
to indicate the total number of detail information lines pertaining to
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a specific transaction.
(c) Columns 22–23. Make no entry.
(d) Columns 24-33, Sealed Source Serial Number. Make no entry.
(e) Columns 34–50, Contract/Identification Number. Use is
optional.
(f) Columns 51-69. Make no entry.
(g) Columns 70–77, Action Date. Enter the date the activity occurs.
In the event of a correction, the date to be entered here is the date
of the activity and not the date of the original transaction. The
numbers representing the month should be entered in the first two
columns, the day of the month in the next two columns, and the
year in the final four columns. For example, January 5, 2000,
would be recorded as:
Section 51
MO DAY YEAR
0 1 3 1 2 0 0 0
(h) Columns 78–80. Make no entry.
(5) Detail Information—Data Record Number 2.
(a) Column 19, Data Code. Code number 2 is preprinted on the
form.
(b) Columns 20–21, Line Number. Enter a sequential number
(01-99) for one transaction to identify a discrete line.
(c) Columns 22–31, from Project Number. Enter the project
number from which the material is being transferred, left justified.
(d) Columns 32–35, From Composition Code. Enter the numeric
code that identifies the chemical and/or physical form of the
material under the project number from which it is being
transferred, left justified. A complete set of composition codes is
listed in the DOE inventory profile (NMMSS Report I-17) which
consists of available nuclear material composition codes and
descriptions. When reporting unirradiated enriched uranium or
plutonium scrap material, enter the appropriate ANSI
alphanumeric code (see ANSI N15.1-1970 and N15.10-1987).
(e) Columns 36–45, To Project Number. Enter the project number
to which the material is being transferred, left justified.
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(f) Columns 46–49, To Composition Code. Enter the numeric code
that identifies the chemical and/or physical form of the material
under the project number from which it is being transferred, left
justified. Composition codes and descriptions are listed in the
DOE inventory profile (NMMSS Report I-17). When reporting
unirradiated enriched uranium or plutonium scrap material, enter
the appropriate ANSI alphanumeric code (see ANSI N15.1-1970
and N15.10-1987).
(g) Columns 50–51, Material Type. Enter the appropriate two-digit
numeric code to identify the type of nuclear material being
reported. See Table XV-1.
(h) Column 52, Owner Code. Code letter G is preprinted on the
form.
(i) Columns 53–63, Element Weight. Enter the metric weight of the
contained nuclear material.
1 Enter decimal units, when required, in columns 62 and/or
63 (segregated by broken lines).
2 To show negative numeric data, enter a minus sign in the
column preceding the first digit. In instances where
negative data are shown in whole units or tenths of a unit,
zeros must be entered in the remaining decimal places with
a minus sign in the column preceding the first digit.
(j) Columns 64–69, Weight percent Isotope. For each line, enter the
weight percent of the isotope U-235, Li-6, Pu-240, Pu-242, or
Pu-238 reported to not more than four decimal places. For U-233,
enter the parts per million of U-232 right justified to column 69.
(k) Columns 70–80, Isotope Weight. Enter the metric weight of
accountable isotopes using instructions for rounding off data in
paragraph 11.a.(5) above.
1 Enter decimal units, when required, in columns 79 and/or
80 (segregated on DOE F DP-749 by broken lines).
2 To show negative numeric data, enter a minus sign in the
column preceding the first digit. In instances where
negative data are shown in whole units or tenths of a unit,
zero(s) must be entered in the remaining decimal places(s)
with a minus sign in the column preceding the first digit.
12. NONPHYSICAL TRANSFER OF NUCLEAR MATERIAL. DOE/NRC F 741 or
electronic equivalent will be used to record a change in ownership or financial
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responsibility.
13. OTHER TYPES OF RECEIPTS AND REMOVALS.
Section 52
a. Various other types of receipts and removals including, but not limited to,
production, transfers to and from other materials, sales, decay, losses, inventory
changes, and inventory differences (see Chapter XIII), will be documented using
DOE/NRC F 741 or electronic equivalent.
b. Such other types of receipt and removal data involving reportable quantities will
be documented and reported consistent with the use of inventory change codes
specified in Tables XV-12, XV-13, and XV-19.
14. SPECIAL REQUIREMENTS.
a. Authority to transfer material. Each facility must maintain documentation of
authorities and responsibilities for MC&A functions, including the process and
authorized signatures required to transfer nuclear material.
b. Authority to receive material. The shipper must verify that the receiver is
authorized to receive the amount and type of material that is to be shipped.
c. Notifying Receiver of Nuclear Material Shipments.
(1) Each shipper will be responsible for advising and obtaining authorization
from the intended receiver of proposed shipments of nuclear material and
for providing all pertinent advance information.
(2) Specific notification requirements applicable to individual facilities are
contained in the RIS Directory (available from the NMMSS operator).
d. Reporting of Nuclear Material in Transit for Domestic Shipments.
(1) Material in transit at the end of a reporting period will be entered into the
intended receiver’s inventory.
(2) A facility making a shipment of nuclear material and/or initiating a
DOE/NRC F 741 during the last 5 calendar days of a month will, on the
day of shipment, provide the intended receiver with the following
information to facilitate the reporting of material balance, transaction, and
inventory data.
(a) Transfer series (shipper’s RIS, receiver’s RIS, and transaction
number).
(b) Material types. See Table XV-1.
(c) Total element weights and (if warranted) isotope weights,
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weight percent and/or parts per million (based on estimates, if
necessary). See Table XV-1.
(d) Project number (for owner code G material).
(e) Obligation tracking data, blocks 17 through 21.
(f) Number of items.
(g) Composition codes.
(h) Owner codes.
(i) Date of shipment.
(3) The information specified above will be transmitted to the receiver by
telephone on the agreed day of shipment, with confirmation by facsimile,
Internet, or other electronic means (e.g., SIMEX).
(4) This requirement may be satisfied by the timely distribution of DOE/NRC
F 741 data via appropriate telecommunications systems when both the
shipper and receiver possess such capabilities.
e. Delayed Receiver Measurements. In cases where the receiver can not determine
independent measured values for a shipment within 10 calendar days of receipt of
the shipment, and there is no agreement in place whereby the receiver can accept
shipper’s values, the receiver will confirm receipt of the material with either an
action code N, U, or S. (see Table XV-10 and the footnotes to Table XV-10 for
additional information).
f. Mixtures of U-233 and U-235. For the case where reportable quantities of U-233
and U-235 are mixed together, a transaction on a DOE/NRC F 741 must contain
two lines and be reported as follows.
(1) Line 1 will be reported with MT 20. The element weight will be the total
uranium weight. The isotope weight will be the isotopic weight of U-235.
Section 53
(2) Line 2 will be reported with MT 70. The element weight will be the total
uranium weight. The isotope weight will be the isotopic weight of U-233.
15. AMENDMENTS OR ADJUSTMENTS TO PREVIOUSLY ISSUED DOE/NRC F 741.
a. When one party makes an adjustment to a transaction, DOE line management will
ensure that contractors under their jurisdiction will document the adjustment on a
DOE/NRC F 741 or electronic equivalent.
b. For specific instructions regarding corrections or adjustments, see Chapters IV
and V. .
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c. Contractors must transmit the completed form to the other party to the transaction
within 1 workday after obtaining the adjustment data.
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CHAPTER IV - NUCLEAR MATERIAL TRANSACTION REPORTING—SHIPPER
The instructions that follow provide specific guidance in the preparation of the DOE/NRC F 741
or the electronic equivalent. The file formats for reporting electronically are maintained by the
NMMSS operator and can be provided upon request.
1. SHIPPER’S DATA The shipper of the material will complete the shipper’s portion of
DOE/NRC F 741 by completing the numbered blocks as follows:
a. Block 1, Shipper’s RIS. Enters the shipper’s facility RIS his/her facility,
normally a 3-character field. Under some circumstances, a 4-character RIS will
be entered (e.g. appending a letter to the end of a 3-character RIS to denote
discharge of material to air or ground). See subsequent Chapters for special
instructions for importers and exporters of nuclear materials. This block must be
completed for the following types of transactions.
(1) Transfers between facilities.
(2) Transfers between RISs within a facility.
(3) Transfers between facilities and DoD.
(4) Transfers between domestic and foreign facilities.
(5) Loan/lease, sale or donation.
(6) One-party transactions (e.g., transactions with a M action code)
(7) Corrections to the above transactions.
b. Block 2, Receiver’s RIS. Enter the receiver’s RIS, normally 3-characters when
the transaction is a transfer of material from the shipper to another facility. Care
should be taken to ensure that the receiving facility’s RIS is reported and not the
RIS for the agent handling the shipment. The shipper or originator enters its
facility’s RIS in this block for a one-party transaction (e.g., a transaction with a M
action code). This field is completed for the types of transactions listed in
paragraphs 1.a.(1) through 1.a.(7) above. See Chapter VII for special instructions
for importers and exporters of nuclear materials.
c. Block 3, Transaction Number. Enter a consecutive number for the same
shipper-receiver combination and ensures that a number is not skipped in the
series or duplicated. (NOTE: An exception to the consecutive numbering
requirement is allowed when a facility has pre-assigned or reserved numbers for
programmatic needs, but the shipment does not subsequently occur. This applies
to both physical and nonphysical transfers of material.) For one-party
transactions, it is desirable that the shipper enter the appropriate journal entry
number to identify the transaction as it occurs (e.g., 000105), the first two digits
indicating the year, the next two digits indicating the month (i.e., 01 through 12),
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Section 54
and the last two digits identifying the specific transaction in the month. (The
example above is for transaction 5 for January of 2000.) Do not prefix or suffix
the transfer series number. For one-party or in-place transactions between
projects or uranium enrichment contracts, an alphanumeric number may be used
when necessary to maintain uniqueness.
d. Block 4, Correction Number. This block is used to correct or adjust a
previously issued DOE/NRC F 741. In preparing the corrected copy, the shipper
or receiver will enter in blocks 1, 2, and 3, the same shipper RIS, receiver RIS,
and transaction number (transfer series) used in the original report, and then enter
in block 4 a consecutive correction number, beginning with 1 (numeral one). The
corrected copy will clearly identify the items being corrected. The party making
the adjustment will notify the other party to the transaction that an adjustment is
necessary and follow up by issuing a corrected DOE/NRC F 741. The correction
number is a 1-character field. An alpha correction number may be used by a
facility when the correction does not affect the other facility. The shipper and/or
receiver must enter the date the adjustment is entered in the facility records in
block 22b or 22e, as appropriate. The shipper and receiver will distribute the
corrected copy in accordance with the distribution pattern for the original
DOE/NRC F 741. This field must be completed when:
(1) A shipper or receiver issues a corrected DOE/NRC F 741 to adjust data
previously reported to the NMMSS;
(2) A correction affects another facility. A numeric character is required,
action code C for the shipper and action code D for the receiver [also see
blocks 26a and 27a for further guidance (back reference line number)];
(a) For each detail line in block 26 or 27 being corrected, two lines
must appear on the corrected copy one with the data originally
submitted and the other with the correct data. The line containing
the original data must show the number of items, element weight,
isotope weight, and limits of error as negative quantities. (For
correcting lines that were originally negative, add a positive
quantity.) The corrected line must show current quantities in these
data fields.
(b) For each detail line in block 26 or 27 being deleted, the original
line must be repeated, with the number of items, element weight,
isotope weight, and limits of error shown as negated quantities.
(For deleting lines that were originally negative, add a positive
quantity.)
(3) Either the shipper or receiver makes an adjustment. The other party to the
transaction must either accept the adjustment or acknowledge that an
adjustment has been made;
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(4) It is necessary to adjust or correct any data element in a M action code
(one-party) transaction reported in a previous period. Either a numeric or
an alphabetic character may be used;
(5) Scrap material is recovered or remeasured for a more accurate total value
for the amount of nuclear material in the original shipments. The
DOE/NRC F 741 for the original shipments should be corrected by
prorating the total amount of the correction according to the amounts of
the original shipments. When this method is determined to be
impracticable, e.g., for reprocessing campaigns, measurements on several
shipments of material recovered simultaneously may be reported as a
correction to a single document with additional details provided to the
other party.
Section 55
e. Block 5, Processing Code. Enter the appropriate 1-character, alphabetic code to
identify the specific type of processing action required.
(1) A—initial entry of data.
(2) C—replacement of data. An entire data set may be replaced at any time
prior to the close of the processing period in which the initial entry was
made with the concurrence of the other party to the transaction.
(3) D—deletion of data. Data may be deleted at any time prior to the close of
the processing period in which the initial entry was made.
f. Block 6, Action Code. Enter a code letter from the list below which describes
the shipper’s purpose in issuing the DOE/NRC F 741. The action code field is a
1-character alpha field.
(1) A—shipper’s original data (requires completion of block 22a, action date
of shipment).
(2) C—shipper’s adjustment or acknowledgment of receiver’s adjustment
(requires completion of block 22b, action date of shipper’s correction).
(3) M—one-party transaction, (e.g., an onsite gain or loss) reported on
DOE/NRC F 741 (or electronic equivalent), and requires completion of
block 22a, 20b, 22c, or 22e.
(4) R—a one-party transaction to remove the WR obligation on material.
(5) X—a shipper’s side of an obligation exchange.
g. Block 7. Enter the number of pages if the submission is classified as Secret.
NOTE: The block is reserved for paper copy submissions only.
h. Block 8, Shipper. No data required. This information is not captured in the
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NMMSS but is for documentation purposes or desired by one or more users of the
transaction information.
(1) Block 8a. Enter the name and address of the shipper.
(2) Block 8b. Enter the appropriate possession license number if the shipper
is a licensee. (Do not enter an export/import license number in this block.)
(3) Block 8c, Attention. Enter the name of a specific individual to be
contacted concerning the shipment.
(4) Block 8d, Telephone. Enter the telephone number of the individual
identified in block 8c.
i. Block 9, Receiver. No data required. This information is not captured in the
NMMSS, but is for documentation purposes or desired by one or more users of
the transaction information.
(1) Block 9a. Enter the name and address of the receiver.
(2) Block 9b, License Number. Enter the receiver’s possession license
number if the receiver is a licensee. (Do not enter an export/import license
number in this block.)
(3) Block 9c. Attention. Enter the name of the individual designated by the
receiver to be contacted concerning receipt of the shipment.
(4) Block 9d, Telephone. The shipper enters the telephone number of the
individual identified in block 9c.
j. Block 10, Number of Data Lines. Enter the total number of detail information
lines supplied in block 26 for the shipper’s transaction data. The total number of
data lines should be between 01 and 99.
k. Block 11, Nature of Transaction.
(1) This block is to be completed for DOE-owned material under lease or loan
agreements, material sold or donated by or to DOE. See Table XV-11 for
TI codes.
(2) If applicable, enter the appropriate code from the list in Table XV-11.
(3) This list is not applicable to one-party transactions.
(4) This block is not to be completed for transfers of DOE-owned contract
nuclear material within or between DOE programs, transfers of material
owned by other U.S. Government agencies, transfers of privately owned
material, or transfers to DOE under 42 U.S.C. 2121(b) or (c), as amended.
Section 56
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l. Block 12, For Account.
(1) The shipper completes block 12 if the material is either DOE-owned
leased/loaned material or DOE-owned contract material being transferred
to a licensee or foreign entity, if the shipment represents a sale or donation
of privately owned material to DOE, or if the DOE field element or site
office having programmatic responsibility for the material being
transferred is different from both the shipper’s and receiver’s DOE field
elements or site offices.
(2) Enter the address of the facility or entity having lease or loan financial
responsibility for the material in block 12a and the RIS in block 12b.
(3) For shipments by DoD, under 42 U.S.C. 2121(b) with the exception of
transfers of Navy cores and associated items, the initiator of the
DOE/NRC F 741 enters the appropriate RIS for the DOE shipping point
reported in block 12a. For transfers of Navy cores and associated items
from DoD to DOE, under 42 U.S.C. 2121(b) the RIS QZD will be entered
in block 12b.
m. Block 13, To Account.
(1) The shipper completes this block if the material is either DOE -owned
leased/loaned material or DOE-owned contract material being transferred
to a licensee or foreign entity, if the shipment represents a sale or donation
of privately owned material to DOE, or the DOE field element or site
office having programmatic responsibility for the material being
transferred is different from both the shipper’s and receiver’s DOE field
elements or site offices.
(2) Enter the address of the facility or entity having lease or loan financial
responsibility for the material in block 13a and the RIS in block 13b.
(3) For shipments to DoD, under 42 U.S.C. 2121(b) (with the exception of
transfers of Navy cores and associated items), the initiator of DOE/NRC
F 741 enters the appropriate RIS for the DoD first destination point
reported. For transfers of Navy cores and associated items from DOE to
DoD under 42 U.S.C. 2121(b) the RIS QZD will be entered in block 13b.
n. Block 14, Transfer Authority—Contract, Nuclear Material Draft or Order
Number.
(1) Enter transfer authority for DOE-owned materials as may be appropriate,
e.g., DOE contract or usage agreement number, loan/lease agreement
number, draft number, SNM order number, purchase order number, letter
of authorization, and so forth. Block 14 data is not required for domestic
shipments.
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(2) If the shipment is to a foreign country, enter the DOE foreign contract
number if applicable.
(3) The shipper will ensure that it has appropriate authorization and approval
to ship the material to the receiver before its movement.
(4) An entry is optional otherwise, and if not one of the cited cases, the
block may be used for local purposes.
o. Block 15, Export/Import Information.
(1) Make no entry when reporting the following.
(a) One-party transactions (i.e., action code M).
(b) Transfers that reflect change in ownership or financial
responsibility (i.e., all nonphysical transfers of nuclear material
other than project transfers).
(c) Transfers between two RISs at the same location.
(2) Block 15. Export or Import Transfers, License Number. For all
export/import transfers, the shipper or originator enters the following:
(a) Specific NRC export/import license number if shipping
arrangements are handled by an agent who is required to obtain a
NRC license to export/import. If more than one export/import
license is applicable to a transfer, a separate DOE/NRC F 741 must
be prepared for each license.
Section 57
(b) GEN-LIC, if the transfer is authorized under a general license.
(c) LIC-EXEMPT, if the transfer is exempt from licensing.
(d) Authorizing shipper’s export declaration (SED) number if
applicable. The SED number will correspond with the foreign
contract number in block 14.
(e) DOE line management or the DOE cognizant security authority
will assign and monitor SED numbers.
(3) For further instructions for transfers of nuclear material between the U.S.
and foreign nations, foreign regional organizations, or supranational
organizations, see Chapter VII and INMTS Data Entry Procedures which
are maintained by the Office of International Safeguards.
p. Block 16, Material Type and Description. This information is not captured in
the NMMSS but is for documentation purposes or is desired by one or more users
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of the transaction information.
q. Block 17, Obligations Accounting, Line Number. Enter sequential
line number. (See also Chapter VIII.)
r. Block 18, Obligations Accounting, Country of Obligation. Enter the
two-character country or entity designation from Table XV-15 related to the
line number entered in block 17. (See also Chapter VIII.)
s. Block 19, Obligations Accounting, Material Type. Enter the 2-character MT to
which the obligation is attached. Refer to Table XV-16. The only MTs to be
reported are 10, 20, 50, 70, 81, and 88. (See also Chapter VIII.)
t. Block 20, Obligations Accounting, Obligated Element Weight. Enter the
element weight of the amount obligated. (See also Chapter VIII.)
u. Block 21, Obligations Accounting, Obligated Isotope Weight (for Enriched
Uranium (in U-235 and or U-233) only). Enter the isotope weight of the amount
obligated to the nearest gram. (See also Chapter VIII.)
v. Block 22, Action Date. The action date for a transaction is entered in one of the
blocks below. Enter numerical date (MMDDYYYY).
(1) Block 22a, Shipment. Enter the date of the transaction (i.e., date of
physical or nonphysical transfer of material). (See Chapter VII for special
instructions for importers or exporters of nuclear materials.)
(2) Block 22b, Shipper’s Correction. When either shipper’s or receiver’s
data on a previously issued DOE/NRC F 741 is adjusted, the shipper
enters either the date of shipper’s adjustment or acknowledgment of
receiver’s adjustment.
w. Block 23, Miscellaneous Data. See instructions for shipper.
(1) Block 23a, Miscellaneous. This information is not captured in the
NMMSS but is for documentation purposes or desired by one or more
users of the transaction information.
(2) Block 23b, Concise Note Attached (DOE/NRC F 740M). This
information is captured in NMMSS. Facilities engaged in the import
and/or export of nuclear materials (see Chapter VII) and facilities selected
under the U.S./IAEA Safeguards Agreement (see Chapter IX) may prepare
a Concise Note to report additional information. The shipper places a
code letter X in the 1-character field to indicate that a Concise Note is
attached, if applicable. See Chapter VII for special instructions for
importers and exporters of nuclear materials.
(3) Block 23c. This information is captured in NMMSS. U.S. importers
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and/or exporters of nuclear material will use this field only if the other
party to the transaction is the United Kingdom. Check the appropriate box
to identify the specific type of processing action required (See
Chapter VII).
Section 58
x. Block 24, Total Gross Weight. Enter the total gross weight of the shipment in
kilograms if the transfer is between physically separated facilities. For transfers
of nuclear material to or from contractor waste management sites, completion of
this block is optional.
y. Block 25, Total Volume. The shipper must enter the total volume, in cubic
meters, if the transfer is to a DOE or NRC licensed waste management site,
otherwise no entry is required.
z. Block 26, Shipper’s Data.
(1) Block 26a, Back Reference Number.
(a) This field is used to reference previously reported data for change
purposes.
(b) The field is comprised of a change digit and a back reference
line number.
(c) This field is required for corrections with the following:
1 Action code C.
2 Action codes M and I when reporting adjustments.
(d) Both the back reference change digit and back reference
line number must be reported. For further guidance, contact the
NMMSS operator.
(e) The back reference change digit represents the change digit of the
document being corrected for a nullifying entry and the change
digit of the document now being completed for a correcting entry.
For further guidance, contact the NMMSS operator.
(f) The back reference line number represents the line number being
corrected for a nullifying entry and the line number of the
corresponding nullifying line for a correcting entry. For further
guidance, contact the NMMSS operator.
(2) Block 26b, Line Number. Enter a sequential number (e.g., 01 through 99
for each transaction) to identify a discrete line. The total number of
discrete lines must agree with the number shown in block 10. For paper
submission, if more lines of data are to be reported than can be
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accommodated on one page, prepare an additional DOE/NRC F 741.
(3) Block 26c, Type of Inventory Change1. Enter from Table XV-12 or
XV-13 the two-digit code. For a full description of each change code see
the corresponding line explanations in Chapter XI, Material Balance
Reporting. Facilities selected under the U.S./IAEA Safeguards Agreement
should see Chapter IX. For shipments to burial sites, see Chapter II.
(4) Block 26d, Identification (Batch Name). Facilities engaged in the import
and/or export of nuclear materials should see Chapter VII for additional
requirements; facilities selected under the U.S./IAEA Safeguards
Agreement should see Chapter IX for additional requirements.
(a) If this block is not used for import/export or IAEA reporting
purposes, other data may be entered.
(b) An entry is required on import or export transactions. Importers
must use the batch name used by the shipper.
(c) Batch name is limited to 16 characters with the right hand eight
characters unique to the reporting facility for the duration of the
material balance period in which reported. Uniqueness of batch
name within the RIS must be maintained. However, the receiver
must use the same batch name used by the shipper. If the receipt
of material results in a duplicate of an existing batch name, a
subsequent internal transaction must be created to change one of
the duplicate batch names.
(5) Block 26e, Number of Items. Enter the number of similar items (e.g.,
cylinders, packs, drums, bottles, tank vessels) to which the line of data
pertains.
(a) When reporting fuel pins, rods, or plates, report the number of
separate fuel pins, rods, or plates involved.
Section 59
(b) When reporting fuel assemblies, report the number of complete
assemblies represented by the line entry.
(c) For transfers of bulk material in a single container, enter the
number 1. No entry is required when reporting transactions
involving RISs assigned to facilities on the same site (i.e., paired
RISs). Leave blank if a M action code is used.
(6) Block 26f, Project Number. Project numbers are structured upon the
DOE budget and reporting classification codes, and identify the
Headquarters and field elements or site offices having programmatic
1 Also applicable to single party/onsite transactions or when one party does not have a RIS.
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responsibility for each project. Indices of current project identifications
are maintained and issued annually (NMMSS Report T-141) to
organizations engaged in DOE production and research programs. Project
numbers are required for all G owner code transactions with the following
specifications.
(a) If the material is loan/lease material, the project number is
QGD04LLEASE
(b) All export/import transactions involving DOE-owned material
require the project number R50000000G on the foreign entity’s
side of the data indicating that the material, though located outside
the U.S., will remain DOE -owned.
(7) Block 26g, Material Type. Enter one of the numeric codes from the list
of MTs in Table XV-2 to identify the nuclear material involved in the
transaction. Facilities engaged in the import and/or export of nuclear
materials should see Chapter VII for special instructions.
(8) Block 26h, Composition/Facility Code. Enter the code that identifies the
physical and/or chemical form of the nuclear material at the time the
transaction occurs. A complete set of composition codes, which consists
of available nuclear material composition codes and descriptions, may be
obtained from the NMMSS operator (referred to as Composition of
Ending Inventory—COEI codes).
(a) For reporting unirradiated uranium (MTs 10, 20, 81) or plutonium
(MTs 40, 50, 83) scrap material, use the ANSI 3-character
alphanumeric codes (ANSI N15.1-1970 and N15.10-1987).
(b) No entry is required for inventory difference or rounding bias data
(e.g., inventory change code 65 or 77 entries).
(c) Facilities selected under the U.S./IAEA Safeguards Agreement
should see Chapter IX.
(9) Block 26i, Owner Code. Enter one of the 1-character alphabetic codes
from Table XV-3 to identify the material ownership at the time the
shipment is made. If the ownership of material on inventory is changed, a
transaction must be submitted to the NMMSS reporting the change. The
change is reported by an A–M transaction (in-place transfer).
(10) Block 26j, Key Measurement Point. Required only for facilities selected
under the U.S./IAEA Safeguards Agreement; see Chapter IX, if
applicable.
(11) Block 26k, Measurement Identification. If selected under the
U.S./IAEA Safeguards Agreement (see Chapter IX), report the following
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data:
(a) Measurement basis.
(b) Other measurement point.
(c) Measurement method.
(12) Block 26l, Gross Weight. Enter the gross weight of the line entry in
rounded kilograms, i.e., weight of material plus packaging and container
weight. An approximate or estimated gross weight figure is acceptable.
(13) Block 26m, Net Weight. Enter the net weight of the line entry in the
reportable units, i.e., weight of material excluding packaging and
container weight. An approximate or estimated net weight figure is
acceptable.
Section 60
(14) Block 26n, Element Weight. For each line, enter the metric weight of the
contained nuclear material as prescribed in Table XV-1. (See Chapter II,
paragraph 6., for rounding policy.)
(15) Block 26o, Element Limit of Error. For transactions involving SNM or
tritium, measurement uncertainties are to be entered as weight quantities
in accordance with the established reporting unit for the MT.
(16) Block 26p, Weight % Isotope. For each line, enter the weight percent of
the isotopes U-235, Li-6, Pu-240, Pu-242, and Pu-238, as applicable, to
not more than four decimal places.
(a) For U-233, enter the parts per million of U-232 in whole numbers.
(b) When reporting fission and transmutation, inventory difference or
rounding bias for enriched uranium only; enter the approximate
original weight percent of U-235 of the material with which the
transaction is associated.
(c) When reporting transactions involving more than one assay range
of one or more materials, data pertaining to each assay range of a
material must be entered on a separate line.
(17) Block 26q, Isotope Weight. For each line, enter the metric weight of
accountable isotopes. See Chapter II, paragraph 6., for rounding policy.
(18) Block 26r, Isotope Limit of Error. For transactions involving SNM or
tritium, measurement uncertainties are to be entered as weight quantities
in accordance with the established reporting unit for the MT.
(19) Block 24s, Signature of Authorized Official and Date Signed. When
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submitting the data as paper copy the following apply.
(a) The shipper’s authorized representative must sign the DOE/NRC
F 741 and enter the date signed.
(b) For facilities that use computer-linked telecommunications systems
in the transfer of data, the signature requirement is waived.
(c) For both imports and exports, the requirement to sign the non-DOE
portion of a DOE/NRC F 741 only verifies that the individual
providing the information is authorized to do so. It was never, nor
is it now, intended that a signature on the non-DOE portion
indicates an assumed responsibility for proper shipment or receipt
of materials.
(d) If facilities wish, they may provide a disclaimer with the signature
on the non-DOE portion to indicate that they are only signing as
authorized transmitters of the data to the NMMSS.
aa. Block 25, Receiver’s Data. Shipper makes no entry.
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CHAPTER V - NUCLEAR MATERIAL TRANSACTION REPORTING—RECEIVER
1. RECEIVER’S DATA. The receiver will complete the receiver’s portion of the form by
making entries in the numbered blocks as follows.
a. For blocks 1 through 5, follow shipper’s data instructions.
b. Block 6, Action Code. Enter the alphabetic code from the list in Chapter XV
which describes the receiver’s purpose in issuing the DOE/NRC F 741. The
action code is a 1-character alpha field.
(1) B—identifies receiver’s data accepting shipper’s weights and requires
completion of block 22c. This action code is not to be used if the receiver
intends to make delayed measurements.
(2) D—identifies receiver’s adjustment or acknowledgment of shipper’s
adjustment and requires completion of block 22e.
(3) E—identifies receiver’s independent measurement or determination
(including rounding) and requires completion of block 22d.
Section 61
(4) J—identifies receiver’s interim reporting of project receipts of DOE
production or research materials that are in transit at the end of the month
or that have been received but not reported. A transaction with action
code J must be followed with action code B, E, or S.
(5) M—identifies one-party transactions, (e.g., an onsite gain or loss) reported
on DOE/NRC F 741 (or electronic equivalent), and requires completion of
block 22a, 22b, 22c, or 22e.
(6) N—identifies known delay for independent measurements of at least 10
days but for less than 30 days. A transaction with action code N must be
followed by an action code of B, E, or S.
(7) U—identifies known delay for independent measurements of at least 30
days. A transaction with action code U must be followed by an action
code of B, E, or S.
(8) S—identifies receiver’s data accepting shipper’s weights under safeguards
closure arrangement and requires completion of block 22c. (Use restricted
to DOE contractor sites where an approved shipper-receiver agreement is
in effect.)
(9) T—identifies contested weights.
(10) Y—identifies the receiver’s side of an obligation exchange.
c. Block 22, Action Date. The action date for a transaction is entered in one of the
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blocks below. Enter numerical date (MMDDYYYY).
(1) Block 22c, Receipt. Enter the date the material is received if the receiver
is accepting shipper’s values without making independent measurements.
(a) For safeguards closures, enter the date the safeguards closure was
performed.
(b) The receiver also should use this block to report the date of receipt
of material involved in nonphysical transfers, one-party
transactions (i.e., transactions with M action code), project number
changes and transactions in which weights are contested. See
Chapter VII for special instructions for importers or exporters of
nuclear materials.
(2) Block 22d, Receiver’s Measurement. Enter the date that independent
measurements are performed.
(3) Block 22e, Receiver’s Correction. When either the shipper’s or the
receiver’s data on a previously issued DOE/NRC F 741 is adjusted, the
receiver enters the date of the receiver’s adjustment or acknowledgment of
shipper’s adjustment.
d. Block 23, Miscellaneous Data. See Chapter IV, shipper’s instructions.
e. Block 27, Receiver’s Data.
(1) Block 27a, Back Reference Number. See Chapter IV, shipper’s
instructions. Also, this field is required for corrections with action codes
D or M, and I when an adjustment is made.
(2) Block 27b, Line Number. See Chapter IV, shipper’s instructions.
(3) Block 27c, Type of Inventory Change. See Chapter IV, shipper’s
instructions.
(4) Block 27d, Identification (Batch Name). See Chapter IV, shipper’s
instructions.
(5) Block 27e, Number of Items. See Chapter IV, shipper’s instructions.
(6) Block 27f, Project Number. See Chapter IV, shipper’s instructions.
(7) Block 27g, Material Type. See Chapter IV, shipper’s instructions.
(8) Block 27h, Composition/Facility Code. See Chapter IV, shipper’s
instructions.
(9) Block 27i, Owner Code. See Chapter IV, shipper’s instructions.
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(10) Block 27j, Key Measurement Point. See Chapter IV, shipper’s
instructions.
(11) Block 27k, Measurement Identification. See Chapter IV, shipper’s
instructions.
(12) Block 27l, Gross Weight. See Chapter IV, shipper’s instructions.
(13) Block 27m, Net Weight. See Chapter IV, shipper’s instructions.
Section 62
(14) Block 27n, Element Weight. See Chapter IV, shipper’s instructions.
(15) Block 27o, Element Limit of Error. See Chapter IV, shipper’s
instructions.
(16) Block 27p, Weight % Isotope. See Chapter IV, shipper’s instructions.
(17) Block 27q, Isotope Weight. See Chapter IV, shipper’s instructions.
(18) Block 27r, Isotope Limit of Error. See Chapter IV, shipper’s
instructions.
(19) Block 27s, Signature of Authorized Official and Date Signed. See
Chapter IV, shipper’s instructions.
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CHAPTER VI - NUCLEAR MATERIAL TRANSACTION REPORTING—
DOE TO DoD
1. FROM DOE TO DoD.
a. Weapons Transfers.
(1) SNM in weapons will not be transferred to DoD under 42 U.S.C. §2121(b)
until DOE has received direction from the President.
(2) DOE line management must not transfer nuclear material to DoD, or
authorize contractor facilities to make such transfers, until it has received
prior written authorization for specific transfers.
(3) Contractors that are the transferring organization must not ship materials
without having prior written authority from DOE line management having
jurisdiction for this purpose.
(4) DOE line management and the contractor must retain written authorization
on file for audit purposes.
(5) DoD is not required to have a license to possess nuclear material for the
purposes identified above.
b. Non-weapon Transfers.
(1) In addition to the conditions identified in paragraph 1.a., above, a
non-weapon transfer of SNM to DoD under 42 U.S.C. §2121(b) requires
the completion of DOE/NRC F 741.
(2) With the exception of SNM transfers to the Naval Reactors program,
authorization for non-weapon transfers of SNM to DoD under
42 U.S.C. §2121(b) will be obtained either from the program office
responsible for the DOE-DoD activity, or from the Defense Programs
Administrator when there is no DOE programmatic interface with DoD.
(3) Authorization for SNM transfers to the Naval Reactors program will be
obtained from the Deputy Assistant Secretary for Naval Reactors, NNSA.
c. Transfer of Material in the Possession of Licensees to DoD. NRC is expected to
advise all 42 U.S.C. §2131 license holders that whenever licensees are required to
deliver SNM to DoD, the licensee will determine from DoD whether the material
is being requested by DoD under the conditions of either 42 U.S.C. §2131 or
42 U.S.C. §2121(b), as amended.
(1) Transfers of Material to DoD as Licensees Under 42 U.S.C. §2131. When
delivery is to be made, the licensee will follow the normal procedures that
NRC has in effect for transfers between licensees.
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(2) Transfer of SNM to DoD Pursuant to 42 U.S.C. §2121(b).
(a) When delivery is to be made, the licensee will advise the DoD
installation to contact the DOE Headquarters, Office of Plutonium,
Uranium and Special Materials Inventory for the purpose of
obtaining a determination of which DOE line management is to
maintain liaison with DoD and the licensee concerning the
disposition of the material.
(b) The responsible Departmental Element, in coordination with and
through the appropriate Headquarters elements, will issue a letter
to the DoD installation, with copies to the licensee and all
appropriate DOE personnel, approving the transfer to DoD and
designating the appropriate DOE line management as liaison with
DoD and the licensee office in handling the transfer to DoD.
Section 63
(c) When the licensee is ready to deliver the product ordered by the
DoD or DoD contractor, the DOE or site office designated as
liaison for the licensee will advise the licensee to initiate a
DOE/NRC F 741 in accordance with the preparation and
distribution instructions that apply to licensees, showing a DOE
RIS as the receiving RIS for the nuclear material in block 2. The
receiving RIS for such transfers must be a DOE organization and
not a contractor organization.
(d) Further, if the receiving RIS is other than the NNSA Service
Center (RIS AAA), a copy of the shipping document will be sent
to AAA and so reflected in the “Distribution of Copies” block.
Line management designated as the liaison with DoD and the
licensee must also ensure the following.
1 Nature of transaction (TI) code D is entered in block 11 to
indicate material is being returned to DOE.
2 The licensee is shown as the shipper in block 8, and as the
entity having financial responsibility for the material in
block 12.
3 The receiving RIS assigned by the designated DOE line
management is shown as the receiver in block 9, with a
parenthetical entry giving the name and address of the DoD
organizational unit or contractor to whom physical delivery
is made.
4 DOE and the designated DOE line management are shown
as assuming financial responsibility for the material in
block 13.
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5 The letter from the responsible Departmental Element is
referenced in block 23.
(e) From the data on the DOE/NRC F 741 prepared by the licensee,
the NMR for the designated receiving RIS will prepare a
DOE/NRC F 741 from DOE to DoD using one of the following
RISs for the receiving DoD installation.
1 QZA for Air Force,
2 QZB for Army, or
3 QZD for Navy.
(f) After DoD has received the material, the NMR of the designated
receiving RIS will sign as receiver in block 27s of the licensee’s
DOE/NRC F 741 using the data furnished by DoD.
(g) The following statement will be entered in block 14 by the NMR
of the receiving RIS.
Acceptance of the material in its existing form is in the best
interest of the U.S. Government.
(h) The NNSA Service Center will be provided a copy of the
completed DOE/NRC F 741. The nuclear material transferred to
DoD pursuant to 42 U.S.C. 2121(b) will not contain any foreign
obligated material.
d. Other Nuclear Material Transfers.
(1) When nuclear material, other than SNM, is associated with weapons being
transferred to DoD, the procedures described in paragraph 1.a. above, will
be followed.
(2) When nuclear material other than SNM is not associated with weapons
and is being transferred to DoD, the procedures and authorization
necessary for making such transfers to licensees will apply. Therefore,
DoD will obtain and possess the material in the capacity of a licensee
under a licensee RIS.
e. Transfer Documents. All transfers to DoD will be documented on DOE/NRC
F 741 in accordance with the instructions in this Manual.
(1) Preparation. Preparation of DOE/NRC F 741 will vary with the nature of
the transfers, as indicated below.
(a) Transfer of Training Account Material. Complete instructions for
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such transfers are contained in Technical Manual, TP100-4,
Custody, Accountability, and Control of Nuclear Weapons and
Nuclear Material, published under the authority of the Secretaries
of the Army, Navy, and Air Force for use by the Defense Special
Weapons Agency and DOE. DOE elements that need this
information should contact the NNSA Service Center.
Section 64
(b) Transfer of War Reserve Stockpile Items Containing Nuclear
Materials. Complete instructions for such transfers are contained
in Section 3 of Technical Manual TP100-4.
(c) Other Transfers of SNM.
1 Transfers of nuclear materials contained in Navy cores and
associated items are reflected in DoD memorandum
inventory accounts maintained by the Pittsburgh Naval
Reactors Office. The distribution of DOE/NRC F 741 for
such transfers will be in accordance with the distribution
list in Chapter III, appropriately modified to provide copies
to the Pittsburgh Naval Reactors Office. See paragraph 2.
below.
2 Other SNM Transfers under 42 U.S.C. §2121(b) are
reflected in DoD memorandum inventory accounts
maintained by the NNSA Service Center. The distribution
of DOE/NRC F 741 for such transfers, excluding those
described in paragraph 1.a., above, will be in accordance
with the distribution list in Chapter III, appropriately
modified to provide copies to the NNSA Service Center as
per paragraph 2. below.
2. DISTRIBUTION OF DOE/NRC F 741.
a. Distribution of DOE/NRC F 741 for transfers of weapon-related materials is
shown in Technical Manuals TP100-1 and TP100-4.
b. Distribution of DOE/NRC F 741 for transfers of Navy cores and/or other SNM
transfers is as follows.
(1) Copies 1, 2, 3, and 5 are forwarded to the receiver.
(2) Copy 4 is sent to the shipper’s DOE cognizant security authority.
(3) Copy 6 is forwarded, as appropriate, to either of the following.
U.S. Department of Energy
Manager, NNSA Service Center
P.O. Box 5400
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Albuquerque, NM 87115
Attn: Manager, Technical Security Department (RIS AAA)
OR
U.S. Department of Energy
Manager, Pittsburgh Naval Reactors Office
P.O. Box 109
West Mifflin, PA 15122-0109
Attn: PAA Nuclear Material Representative
(4) Copy 7 is retained by the shipper.
(5) The shipper will instruct the receiver to—
(a) complete block 27 on copies 1, 2, 3, and 5;
(b) return copy 1 to the shipper;
(c) retain copy 2 for filing;
(d) mail copy 3 to the shipper’s DOE cognizant security authority; and
(e) mail copy 5 to either the NNSA Service Center or the Pittsburgh
Naval Reactors Office, as appropriate.
c. Other Transfers of Nuclear Material. All transfers of nuclear material under
42 U.S.C. §2121(b) will also be documented on DOE/NRC F 741. Distribution
will be made as follows.
(1) Copies 1, 2, 3, and 5 are forwarded to the receiver.
(2) Copy 4 is sent to the shipper’s DOE cognizant security authority.
(3) Copy 6 is forwarded to—
Manager, NNSA Service Center
National Nuclear Security Administration—USDOE
P.O. Box 5400
Albuquerque, NM 87115
Attn: Manager, Technical Security Department (RIS AAA)
(4) Copy 7 is retained by the shipper.
(5) The shipper will instruct the receiver to—
(a) complete block 27 on copies 1, 2, 3, and 5;
(b) return copy 1 to the shipper;
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(c) retain copy 2 for filing;
(d) mail copy 3 to the shipper’s DOE cognizant security authority; and
(e) mail copy 5 to the address for the NNSA Service Center shown
above.
3. MEMORANDUM INVENTORY ACCOUNTS.
a. The Pittsburgh Naval Reactors Office and the NNSA Service Center will maintain
memorandum inventory accounts for all transfers under their purview identified in
paragraphs 1. and 2. above.
b. The NNSA Service Center and the Pittsburgh Naval Reactors Office will maintain
current inventory records that will provide the following information.
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(1) All quantities shipped to DoD.
(2) All quantities returned to DOE (based on the receiver’s measured
quantities).
(3) All quantities determined to have been consumed or lost.
(4) Inventory and loss data for reports of composition of ending inventory.
c. As of September 30 each year, the NNSA Service Center and the Pittsburgh
Naval Reactors Office will forward transcripts of their memorandum accounts to
the Director, Office of Nuclear Energy, Science and Technology, DOE
Headquarters, for other than weapon-related inventories.
4. FROM DoD TO DOE.
a. Transfer of training account material will be made by DoD as described in
Technical Manual TP100-4, Section 3, for nuclear material transfers to U.S. DoD
(RIS QZE) and Section 6 for transfers of SNM and source material to the training
account (RIS QZC). The instructions prescribe the use of DoD Form 1348 to
document the transfer.
b. Transfer of war reserve stockpile items containing nuclear materials will be made
by DoD as described in Technical Manual TP100-4, Section 3, for nuclear
material transfers to U.S. DoD (RIS QZE). The instructions prescribe the use of
DoD Form 1348 to document the transfer.
c. DOE elements having need for information referred to in paragraphs 4.a. and 4.b.
should contact the NMR at RIS AAA.
d. Other than the transfers referred to above, DoD does not prescribe a form for the
shipping DoD installation to document the transfer. However, for any such
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transfers, the receiving facility must provide DoD with appropriate
acknowledgment of receipt, and ensure that DoD documentation of the transfer
contains all essential information. In addition, the receiving facility is required to
provide the NNSA Service Center or the Pittsburgh Naval Reactors Office with
copies of any documentation of the transfer; i.e., receipt acknowledgment or
DOE/NRC F 741, as appropriate. DOE line management must maintain a
receipted copy of such documents for audit purposes. The basic information
which should be included on the transfer document is as follows.
(1) Date of shipment.
(2) Name and address of the shipper.
(3) Description of the nuclear materials (including information as to the
purpose for which it was used).
(4) Type of material.
(5) If available, the quantity of material by element and isotope.
(6) Date of receipt.
(7) Receiver’s name and address.
(8) Signature of the receiving facility’s authorized representative.
e. Transfer Documents. All transfers of nuclear material from DoD will be
documented on DOE/NRC F 741.
(1) Preparation. The receiver will prepare a DOE/NRC F 741 promptly,
completing all appropriate blocks, with the exception of block 26, in
accordance with the instructions in Chapter V.
(2) Distribution.
(a) One copy to the receiver’s DOE cognizant security authority.
(b) One copy to either the NNSA Service Center or the Pittsburgh
Naval Reactors Office, as appropriate.
(c) One copy retained by the receiver.
5. PROHIBITION ON USE OF FOREIGN OBLIGATED MATERIAL. Material that has a
foreign obligation attached under an Agreement for Cooperation in the Peaceful Uses of
Nuclear Energy may not be shipped to or received by a facility with a Q RIS.
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CHAPTER VII - NUCLEAR MATERIAL TRANSACTION REPORTING—U.S. AND
FOREIGN NATIONS, FOREIGN REGIONAL ORGANIZATIONS, OR
SUPRANATIONAL ORGANIZATIONS
1. INTRODUCTION. This Chapter provides instructions for the preparation and
Section 66
distribution of DOE/NRC F 741 for transfers of nuclear material between the U.S. and
foreign nations, foreign regional elements, or supranational organizations.
2. PREPARATION OF DOE/NRC F 741.
a. License-exempt contractors who ship to or receive nuclear materials from foreign
entities will prepare DOE/NRC F 741.
b. Prior to the export/import of nuclear materials by license-exempt contractors
under their jurisdiction, DOE line management should ensure that INMTS
procedures for the transfer of nuclear materials to foreign entities are followed.
c. For further information regarding INMTS, contact the NMMSS operator. The
referenced procedures are designed to assist DOE in accounting for and
controlling the export/import of nuclear materials. If the imported or exported
nuclear material has foreign obligations, see Chapter VIII for further instructions.
Additional information on export/import requirements can be obtained from the
Office of Defense Nuclear Nonproliferation through DOE line management.
3. TRANSFERS TO A FOREIGN ENTITY.
a. The shipper will ensure that appropriate authorization and approval to transfer the
nuclear material has been obtained.
b. It is important in preparing DOE/NRC F 741 that the entry in block 2 be the
proper international nuclear facility code for the receiver’s facility. (Refer to the
NMMSS International Nuclear Facilities Codes Directory, which lists the names
and corresponding RISs of international nuclear facilities identified to possess
source and/or SNM.)
c. The receiver’s name and address, which are not necessarily the same as the name
and address of the facility, will be entered in block 9a. This data is not captured
by NMMSS.
d. Transfers of material under a mutual defense agreement will be identified by
entering QZF in block 2 of DOE/NRC F 741 for transfers to France or QZG for
transfers to the United Kingdom.
e. Owner code G (U.S. Government owned) or J (other owned), as appropriate, will
be entered in block 26i to reflect material ownership.
f. Facilities engaged in the import and/or export of nuclear materials also will follow
the special instructions in this Chapter and in Chapter VIII of this Manual. No
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entry is required in block 15 for transfers of material under a mutual defense
agreement. Transfers under 42 U.S.C. §2121(c) involving defense activities,
other than those for which responsibility has been specifically assigned by
Headquarters, must be coordinated through the Manager, NNSA Service Center.
g. In addition to any other markings, transfers of nuclear material to the United
Kingdom must be reported in block 23c.
h. Facilities engaged in the import and/or export of nuclear materials also will follow
the special instructions in this Chapter and in Chapter VIII of this Manual.
4. TRANSFERS FROM A FOREIGN ENTITY.
a. The receiver, in preparing DOE/NRC F 741, will enter in block 1 the proper RIS
for the shipper’s facility. In block 8a, enter the shipper’s name and address,
which are not necessarily the same as the name and address of the facility. This
data is not captured by NMMSS.
b. Transfers of material under a mutual defense agreement will be identified by
entering QZF in block 1 of DOE/NRC F 741 for transfers from France or QZG
for transfers from the United Kingdom.
c. Owner code G or J, as appropriate, will be entered in block 27i to reflect material
ownership.
Section 67
d. No entry is required in block 15 for transfers of material under a mutual defense
agreement. Transfers of material originally shipped under 42 U.S.C. §2121(c)
involving defense activities, other than those for which responsibility has been
specifically assigned by Headquarters, must be coordinated through the Manager,
NNSA Service Center.
e. In addition to any other markings, transfers of nuclear material from the United
Kingdom must be reported in block 23c.
f. Facilities engaged in the import and/or export of nuclear material will also follow
the special instructions in this Chapter and Chapter VIII of this Manual.
5. BATCH FORMATION AND NAMING.
a. For the import of material from a foreign nation or entity, use the shipper’s batch
identification.
b. Reporting of inventory changes on DOE/NRC F 741 under the U.S./IAEA
Safeguards Agreement is done at the batch level of detail; and under an agreement
between the U.S. Government and the IAEA, imports and exports also will be
reported at the batch level of detail.
c. Special instructions for importers and exporters are in paragraph 6. of this
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Chapter and in Chapters VIII and X of this Manual.
d. Data on a batch are contained on a single detail line of DOE/NRC F 741. All
material in a single batch must have the same value for all of the following data
elements.
(1) Type of inventory change (required under the U.S./IAEA Safeguards
Agreement only).
(a) Batch name.
(b) Number of items.
(c) Composition/facility code.
(2) Key measurement point (required under the U.S./IAEA Safeguards
Agreement only).
(3) Measurement identification code, i.e., measurement basis, other
measurement point, and measurement method (required under the
U.S./IAEA Safeguards Agreement only).
e. If the material in a single batch has multiple values for data elements, the data for
the batch must be listed on two or more detail lines, with common data elements
repeated. An example of a batch requiring more than one line would be irradiated
fuel containing both uranium and plutonium. The data for such a batch would be
listed using one line for uranium data and one line for plutonium data.
6. SPECIFIC INSTRUCTIONS FOR FACILITIES ENGAGED IN THE IMPORT
AND/OR EXPORT OF NUCLEAR MATERIALS.
a. U.S. importers and/or exporters of nuclear materials are required to use
DOE/NRC F 741 for documentation of all transactions. In addition, U.S. facilities
involved in importing or exporting are required to complete the portion of the
DOE/NRC F 741 normally completed by the other facility involved in a transfer.
(1) U.S. importers and exporters will complete both the shipper’s and the
receiver’s portion of the form.
(2) The required signing of the non-DOE portion of a DOE/NRC F 741 will
indicate only that the signing individual is authorized to provide the
information to the NMMSS and will not imply any responsibility for
proper shipment or receipt of the materials reflected on the non-DOE side
of the document.
(3) These facilities will complete the numbered blocks on DOE/NRC F 741 as
specified in the main body of Chapters II, III, IV, and V of this Manual.
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b. The following instructions are specific for importers and exporters of nuclear
materials and apply only to shipments containing 1 gram or more of SNM or 1
kilogram or more of source material.
Section 68
(1) Block 1, Shipper’s RIS. The U.S. exporting facility will enter its RIS in
block 1. The U.S. importing facility will enter the foreign shipper’s RIS
from the NMMSS International Nuclear Facilities Codes Directory.
(2) Block 2, Receiver’s RIS. The U.S. exporting facility will enter the
foreign receiver’s RIS from the NMMSS International Nuclear Facilities
Codes Directory. The U.S. importing facility will enter its RIS.
c. Block 14, Transfer Authority. For exports, the U.S. exporter will enter the
authorizing contract or foreign contract number as applicable, in accordance with
the INMTS procedures. For further information regarding INMTS, contact the
NMMSS operator. The U.S. importer will enter the authorizing contract, if
applicable.
d. Block 15, Export or Import Transfers, License Number. The U.S. facility will
enter the appropriate authorizing SED number or license in this field if applicable.
See Chapter IV for further guidance.
e. Block 23c, U.K. Reportable. U.S. exporters or importers involved in a transfer
with the United Kingdom will enter the transfer category in this block by
checking one of the following.
(1) A transfer of material pursuant to the U.S./U.K. Mutual Defense
Agreement, check NO.
(2) A transfer of material for military use but not pursuant to the U.S./U.K.
Agreement, check NO.
(3) A transfer of material for peaceful use, check YES.
f. Block 26d, Identification (Item/Batch Name).
(1) A U.S. facility that is an exporter completing the shipper’s data will create
a batch name that will be unique to that transaction within the facility. For
fuel assemblies, pins, sealed sources, and UF6 cylinders, the batch name
will be its identification number. In addition, fuel assemblies, pins, sealed
sources, and UF6 cylinders will each be separate batches.
(2) A U.S. facility that is an importer completing the shipper’s portion of the
data for the foreign facility will obtain and use the shipper’s batch name as
provided by the shipper.
(3) If data previously reported on a batch are being corrected, the same batch
name must be used on the correction document as on the original
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document. If the batch name is being corrected, the “was” line should
show the batch name originally reported and the “should be” line should
show the correct batch name.
g. Block 26g, Material Type.
(1) A U.S. facility that is an exporter completing the shipper’s data will enter
the correct U.S. MT code from Table XV-2.
(2) A U.S. facility that is an importer completing the shipper’s data for a
foreign facility will convert the IAEA element code provided by the
shipper to the U.S. MT code from Table XV-14. If the foreign facility
does not provide an IAEA element code, the U.S. facility will supply the
appropriate U.S. MT code and attach a Concise Note to this effect.
h. Block 27d, Identification (Batch Name). Whether the U.S. facility is an
importer completing the receiver’s data or an exporter completing the receiver’s
portion of the data for a foreign facility, the U.S. facility will enter the same batch
name as entered in block 26d.
i. Block 27g, Material Type.
(1) A U.S. facility that is an importer completing the receiver’s data will enter
the correct U.S. MT code from the list of material types in block 26g.
(2) A U.S. facility that is an exporter completing the receiver’s data for the
foreign facility will enter the same MT code as entered in block 26g.
Section 69
j. Blocks 17-21, Obligation Information. For imports or exports involving foreign
obligated material, the U.S. facility will complete these fields as described in
Chapter VIII. NOTE: Only EURATOM2 and U.S. non-obligated material may
be transferred under a Mutual Defense Agreement.
7. DISTRIBUTION OF DOE/NRC F 741. Distribution of DOE/NRC F 741 data will be in
accordance with the following procedures.
a. Secondary Distribution of DOE/NRC F 741. The NMMSS (QFA) will make
secondary distribution of DOE/NRC F 741 at the close of the process month for
the countries/entities with which the United States has bilateral agreements for
cooperation that require report distribution. This distribution is made for
Australia, Canada, EURATOM, and Japan through the DOE Office of
Nonproliferation Policy.
(1) For transactions involving 42 U.S.C. §2121(c), Material for EURATOM,
2EURATOM comprises the following member states: Austria, Belgium, Denmark, Finland, France, Germany,
Greece, Ireland, Italy, Luxembourg, The Netherlands, Portugal, Spain, Sweden, and the United Kingdom
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the shipper must prepare and distribute an additional copy of the receipted
DOE/NRC F 741 to the NNSA Service Center.
(2) Copy 2 of DOE/NRC F 741 will accompany the shipment if it contains 1
or more grams of SNM or 1 or more kilograms of source material.
b. For Transfers of Material to or from the United Kingdom (QZG) under the
Mutual Defense Program, the distribution instructions below will apply.
(1) If the data documenting the transfer is classified RD/FRD, 9 copies are to
be distributed as follows.
(a) Copies 1–5
1 OUTER ENVELOPE
Chief, Joint Atomic Information Exchange Group
8725 John J Kingman Road
Mail Stop 6201
Ft. Belvoir, VA 22060-6201
Attn: JAIEG
2 INNER ENVELOPE
Chief, Joint Atomic Information Exchange Group
8725 John J Kingman Road
For: (name of recipient)
Ft. Belvoir, VA 22060-6201
Attn: JAIEG
(b) Copy 6.
1 OUTER ENVELOPE
U.S. Department of Energy
P.O. Box 23865
Washington, D.C. 20026-3865
2 INNER ENVELOPE
U.S. Department of Energy
NNSA Office of Operations and Construction Management
P.O. Box 23865
Washington, D.C. 20026-3865
(c) Copy 7.
Chief, Joint Atomic Information Exchange Group
Defense Special Weapons Agency
6801 Telegraph Road
Alexandria, VA 22310-3398
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(d) Copy 8.
NNSA Service Center
P.O. Box 5400
Albuquerque, NM 87115
Attn: Manager, Technical Security Department
(e) Copy 9 . Retain for internal use.
(f) The shipper/receiver will include a letter of transmittal to the
Chief, Joint Atomic Information Exchange Group requesting that
copies 1 through 5 of DOE/NRC F 741 be forwarded [for ultimate
transmittal to Atomic Weapons Establishment (AWE)] to—
British Embassy
Washington, D.C.
Attn: Atomic Coordinating Office
(2) If the transfer represents a loan of weapons material, both the DOE/NRC
F 741 and the letter of transmittal should include a reference to a U.S. loan
authorization.
(3) If the transfer represents a sale of nuclear material to the United Kingdom,
record the transaction as Purchased by Aldermaston (PALD) or Purchased
by Aviation Ministry (PAM) sales authorization, as appropriate.
(4) The shipper/receiver also should instruct the British Defense Staff to sign
two copies of the DOE/NRC F 741 documenting the transfer, and to
forward one copy to the DOE shipper/receiver and one copy to—
Section 70
NNSA Service Center
RIS AAA
P.O. Box 5400
Albuquerque, NM 87115
Attn: Manager, Technical Security Department
(5) If the DOE/NRC F 741 documenting the transfer is unclassified, or
classified NSI, three copies (copies 6 and copies 8–9) of the form are to be
distributed according to the locations noted above. Copy 1-5 and 7 are not
required by the Joint Atomic Information Exchange Group; however,
copies 1-5 are to be distributed to the U.S. DOE locations noted above.
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CHAPTER VIII - NUCLEAR MATERIAL TRANSACTION REPORTING—FOREIGN
OBLIGATIONS TRACKING FOR DOE/NRC F 741 BLOCKS 17, 18, 19, 20, AND 21
1. INTRODUCTION.
a. Special procedures must be used to implement the reporting requirements of the
U.S. Bilateral Agreements for Peaceful Nuclear Cooperation. These agreements
for cooperation are necessary to allow the U.S. Nuclear Industry to trade with
foreign countries/entities, per Section 123 of the Atomic Energy Act of 1954.
b. The Agreements require that the U.S. track and report the foreign-obligated
nuclear materials and produced nuclear materials from these countries/entities
within the boundaries of the U.S.
c. A foreign obligation can be defined as a commitment by one government to
another to treat nuclear materials, nonnuclear materials, equipment and
components in a manner consistent with the agreement signed between the two
governments.
d. In addition to these agreements for cooperation, the U.S. has a requirement to
track and report to Russia the imports, exports, and use of the Former Soviet
Union down-blended highly-enriched uranium.
e. Facilities that are importers and/or exporters of nuclear material also should
comply with Chapters VII and IX.
2. PROHIBITION ON USE OF FOREIGN OBLIGATED MATERIAL. Material that has a
foreign obligation attached under an Agreement for Cooperation in the Peaceful Uses of
Nuclear Energy may not be shipped to or received by a facility with a Q RIS.
3. IMPORTS.
a. For U.S. facilities importing nuclear material with foreign obligations, the
relevant obligation information will be supplied by the appropriate Government
agency (DOE, Department of State, and NRC) in advance of the receipt. This
Government notification will supply the U.S. facility with the information
necessary to complete blocks 17-21, if applicable.
b. For imports, the foreign obligation information can be—
(1) country/entity from which the nuclear material was shipped, and/or
(2) country/entity attaching third-party obligations.
(3) In most cases, for imports from a country that has made the entire
shipment subject to the agreement, the total import quantity will be
obligated. If only a portion of the shipment is subject to an agreement
(third party obligation), that amount will be clearly specified on the
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documentation. These will be identified as such in the Government
notification supplied to the U.S. facility in advance of the import.
c. The Government notification will supply the following information for the
completion of blocks 17–21:
(1) the country/entity code of obligation,
(2) the material type, and
(3) the amount obligated.
d. See Table XV-15 for country/entity codes. See Table XV-16 for reportable
obligated material types and quantities.
4. COMPLETION OF OBLIGATION INFORMATION.
Section 71
a. Block 17, Line Number. The facility will enter a sequential number
(01 through 99) for each obligated country or material. If there is more than one
separate obligation or more than one obligated material type, enter the appropriate
numbers in the subsequent lines.
b. Block 18, Country of Obligation. For each obligation line, enter the code from
Table XV-15 that represents the country/entity of obligation.
c. Block 19, Material Type. For each obligation line, enter the domestic code from
Table XV-16 that represents the material obligated. The only material types to be
reported are 10, 20, 50, 70, 81, and 88.
d. Block 20, Obligated Element Weight. Enter the element weight of the amount
obligated. Refer to Table XV-16.
e. Block 21, Obligated Isotope Weight (for Enriched Uranium in U-235 and or
U-233 only). Enter the isotope weight of the amount obligated to the nearest
gram.
5. DOMESTIC TRANSFERS, INTERNAL TRANSACTIONS, AND EXPORTS.
a. For U.S. facilities shipping or exporting material with foreign obligations, or for
the reporting of onsite gains and losses, the obligations on the material must be
stated as such in blocks 17–21.
b. For domestic transfers, blocks 17–21 will be filled out as explained in
paragraph 4. above.
(1) The U.S. shipper will assign the appropriate obligations on the material, if
any, and complete the line number, country/entity of obligation, material
type and obligated weight entries, as applicable.
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(2) The U.S. receiver will complete the matching obligation information as
assigned by the shipper, if accepting shipper’s values. If receiver does not
accept shipper’s weights, the receiver’s weights will be recorded for the
foreign obligated material.
c. For internal transactions (e.g., burn-up, decay, production, measured discards,
accidental losses or gains, category changes, fission and transmutation, inventory
differences, etc.), enter the line number, country/entity of obligation, material type
and obligated weights, if applicable.
d. For exports, the U.S. shipper will complete both, the shipper’s and receiver’s
DOE/NRC F 741.
e. If the U.S. shipper is exporting foreign obligated material, the U.S. shipper will
complete blocks 17–21 for each obligated country/entity or material exported.
NOTE: If the export requires a NRC export license, the license should
specifically permit the export of that obligated material on the face of the license.
See Chapters VII and IX for additional information on imports and exports.
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CHAPTER IX - NUCLEAR MATERIAL TRANSACTION REPORTING—FACILITIES
SELECTED BY THE IAEA
1. INTRODUCTION.
a. Special procedures must be used to implement some of the reporting requirements
of the U.S./IAEA Safeguards Agreement.
b. This Chapter provides direction for use of these special procedures for facilities
that have been selected either under the terms of the U.S./IAEA Safeguards
Agreement or Protocol. Such facilities should note that all requirements and
procedures in the main body of this Manual apply, in addition to the special
requirements of this Chapter.
c. Facilities selected under the U.S./IAEA Safeguards Agreement that are importers
and/or exporters of nuclear material also should comply with Chapters VII and
VIII.
d. For further guidance, refer to Code 10 of the Subsidiary Arrangements to the
U.S./IAEA Safeguards Agreement.
2. BATCH FORMATION AND NAMING.
Section 72
a. Reporting of inventory changes on DOE/NRC F 741 under the U.S./IAEA
Safeguards Agreement is at the batch level of detail.
b. In general, the data on a batch are contained on a single detail line of DOE/NRC
F 741.
c. All material in a single batch must have the same value for all of the following
data elements:
(1) type of inventory change,
(2) batch name,
(3) number of items,
(4) composition/facility code,
(5) key measurement point, and
(6) measurement identification code (i.e., measurement basis, other
measurement point, and measurement method).
d. If the material in a single batch has multiple values for data elements, the data for
the batch must be listed on two or more detail lines, with common data elements
repeated. An example of a batch requiring more than one line would be irradiated
fuel containing both uranium and plutonium. The data for such a batch would be
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listed using one line for uranium data and one line for plutonium data.
e. If a facility selected by the IAEA receives a shipment, the receiver’s data must be
reported with a one-to-one, line-by-line correspondence to the shipper’s data
rather than at the batch level of detail.
f. If inventory change code 22 or 71 is entered in block 26c or 27c, as applicable,
the batch name in block 26d or 27d must be composed of the appropriate
character code from Table XV-18, followed by a unique sequence number (e.g.,
EN-800423). (The IAEA does not require the reporting of category changes of
enrichment for enriched uranium.) For each entry with an inventory change code
of 22, there must be a corresponding entry with an inventory change code of 71
with the same batch name.
g. Guidance for reporting de-exemption for use or quantity and exemption for
use, quantity, or termination due to nonnuclear use will be provided by the
Office of Plutonium, Uranium and Special Materials Inventory, and the Office
of International Regimes and Agreements. A description of de-exemption codes
(e.g., DU, DQ, EU, EQ, etc.) is given in Code 10 of the Subsidiary
Arrangements to the U.S./IAEA Safeguards Agreement.
3. DETAILED INSTRUCTIONS.
a. Facilities selected by the IAEA are required to use DOE/NRC F 741 for
documentation of all transactions, including transfers between the IAEA material
balance areas (MBAs) within the facility and certain other types of onsite
inventory changes. Specific instructions for these onsite inventory changes will
be provided by the Office of International Regimes and Agreements on a
case-by-case basis.
b. Facilities notified of selection by the IAEA will complete the numbered blocks on
DOE/NRC F 741 as specified in Chapters XII, XIII, and XIV of this Manual with
the following additional requirements.
(1) Block 23b, Concise Note Attached. The domestic shipper or receiver
places an X in the appropriate box to indicate whether or not a Concise
Note is attached to the DOE/NRC F 741.
(2) DOE/NRC F 740M. A Concise Note will be used by the shipper or
receiver to supply additional nuclear materials transaction data in free text
format, either at the reporting facility’s option or as required by the facility
attachment or transitional facility attachment. See Chapter X for further
information on Concise Notes.
(3) Block 26, Shipper Data.
(a) Block 26c, Type of Inventory Change. When reporting types of
transactions denoted by codes DU, DQ, EU, EQ, or TU, a special
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code will be required in this block. Special codes and procedures
will be provided by the Office of International Regimes and
Agreements on a case-by-case basis.
(b) Block 26d, Identification (Item/Batch Name).
1 The shipper will create a unique batch name. For guidance
regarding the number of characters in a batch name, contact
the NMMSS operator. For fuel assemblies, pins, sealed
sources, and UF6 cylinders, the batch name will be its
identification number. A batch name will not appear more
than once on a single DOE/NRC F 741 unless the data for a
single batch requires more than one line.
2 If inventory change code 22 or 71 is entered in block 26c or
27c or transaction code DU, DQ, EU, EQ, or TU is being
reported, see Chapter VII of this Manual for guidance in
constructing a batch name.
3 If data previously reported on a batch is being corrected,
the same batch name must be used on the correction
document as on the original document. If the batch name is
being corrected, the “was” line should show the batch name
originally reported and the “should be” line should show
the correct batch name.
(c) Block 26h, Composition/Facility Code. Special codes and
procedures will be provided by the Office of International Regimes
and Agreements on a case-by-case basis.
(d) Block 26j, Key Measurement Point. Enter the appropriate flow
key measurement point code of the facility attachment or
transitional facility attachment.
(e) Block 26k, Measurement Identification consists of measurement
basis, other measurement point, and measurement method as
shown below.
1 Measurement Basis. Enter the appropriate code from the
following list.
a N—batch data are based on measurements made at
another MBA, and this is the first time the data are
being reported for this MBA.
b L—batch data are based on measurements made at
another MBA, the data are being reported for the
MBA and this is the second, third, etc., time.
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c M—batch data are based on measurements made at
this MBA, and this is the first time the data are
being reported for this MBA.
d T—batch data are based on measurements made at
this MBA, and this is the second, third, etc., time
the data are being reported for this MBA.
2 Other Measurement Point. If a M was entered for the
measurement basis, enter the appropriate code to indicate
the key measurement point if different from the key
measurement point indicated by the code in block 26j.
3 Measurement Method. If two or more measurement
methods having different measurement uncertainties may
be employed at a particular key measurement point, enter
the appropriate code to indicate the method used for
measurement, as agreed with the IAEA.
c. Block 27, Receiver’s Data.
(1) Block 27c, Type of Inventory Change. Fill out as per instructions above
for block 26c.
(2) Block 27d, Identification (Item/Batch Name). Enter the same batch
name as the shipper entered in block 26d.
(a) If a batch name has not been assigned, see Chapter VII of this
Manual for guidance in constructing a batch name.
(b) If the material is being imported, the receiver will use the batch
name provided by the shipper.
(3) Block 27h, Composition/Facility Code. Fill out as per instructions above
for block 26h.
(4) Block 27j, Key Measurement Point. Fill out as per instructions above
for block 26j.
(5) Block 27k, Measurement Identification. Fill out as per instructions
above for block 26k.
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CHAPTER X - NUCLEAR MATERIAL TRANSACTION REPORTING—
CONCISE NOTE
1. INTRODUCTION. Facilities are to submit a Concise Note under the following
circumstances.
a. Facilities selected under the U.S./IAEA Safeguards Agreement or Protocol are
required to submit Concise Notes to accompany submission of transaction,
material balance and physical inventory data, as appropriate, for conveying
explanatory information to the IAEA.
b. Facilities engaged in the import and/or export of nuclear materials that for any
reason cannot use the same batch name as the shipper or if the shipper fails to
supply a batch name, the importer should supply his own batch names and attach
a Concise Note to that effect.
c. If the shipper fails to supply its IAEA facility code or the IAEA material type
code, a Concise Note should be prepared stating that the data was not supplied.
d. Facility attachments or transitional facility attachments for selected facilities may
specify circumstances under which Concise Notes are required to be submitted to
the IAEA accompanying other reports. Such Concise Notes are used to convey to
the Foreign State the required data items associated with reported accounting data.
2. INSTRUCTIONS FOR COMPLETING DOE/NRC FORM 740M.
a. Block 1, Name and Address. Leave blank.
b. Block 2, Attachment to. Place a check mark or a X in the appropriate box to
indicate whether this explanatory information will be attached to a DOE/NRC
F 741, 742, or 742C.
c. Block 3, RIS. Enter the RIS for your facility to which the explanatory
information in this report applies.
d. Block 4, Reporting Period. Complete this block if 2b or 2c was checked,
indicating that this concise note is attached to a DOE/NRC F 742C, Physical
Inventory Listing. Enter the beginning and ending dates of the reporting period as
shown on DOE/NRC F 742 or F 742C.
e. Block 5, Transaction Data. Complete this block only if box 2a was checked,
indicating that this F 740M is attached to a DOE/NRC F 741. All entries in this
block must be identified to those on the DOE/NRC F 741. Fill in the blocks as
follows.
(1) Block 5a. Enter shipper’s RIS.
(2) Block 5b. Enter receiver’s RIS.
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(3) Block 5c. Enter the unique transaction number.
(4) Block 5d, Correction Number. Used when DOE/NRC F 741 is a
correction to a previous report.
(5) Block 5e, Processing Code. Enter the same code as was used in the
DOE/NRC F 741.
(6) Block 5f, Action Code. If a DOE/NRC F 740M is attached enter the
same action code as in block 6 of the DOE/NRC F 741. Otherwise enter
action code M.
f. Block 6, Reporting Date. Complete this block if box 2a or 2c was checked.
Copy the date shown on DOE/NRC F 741 or 742C.
g. Block 7. The actual explanatory data and the other data necessary to link the
explanatory data to the parts of the report to which they apply. Complete this
block as follows.
(1) Block 7a, Line Number. Enter the consecutive number beginning with
one (01) for each explanatory reference.
(2) Block 7b, Entry Reference.
(a) If the explanatory information entered on this line of the
DOE/NRC F 740M applies to the entire DOE/NRC F 741, 742, or
742C, enter the words, “Whole Report.”
(b) If the explanation applies to the data on a specific batch on a
DOE/NRC F 741 or 742C, copy the batch name exactly as it
appears on DOE/NRC F 741 or 742C.
Section 75
(c) If the explanation applies to a specific material balance category on
a DOE/NRC F 742, enter the two-digit number of the material
balance category.
(d) If the explanation applies to material balance categories 11, 30, 42,
43, or 51, enter the RIS shown on the line of the DOE/NRC F 742.
(e) If the explanation applies to categories 22 or 71, enter the
2-character inventory change type (ICT) as shown on that line of
the DOE/NRC F 742.
(f) If DOE/NRC F 740M action code is M, enter “General.”
(3) Block 7c, Text of Concise Note. Enter any 43 characters, letters,
numbers, or special characters per line. Up to 99 lines of text may be used
for any one explanation.
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h. Block 8. The DOE/NRC F 740M is to be signed by an authorized representative
of the facility.
i. Block 9. Enter the title of the person signing the form.
j. Block 10. Enter the date the form was signed.
k. Computer-Readable Format. DOE/NRC F 740M may be put into
computer-readable format following additional guidance in NMMSS Reports
D-22 and D-23.
l. Distribution.
(1) The Concise Note will be submitted at the same time as the submission of
the data to which the Concise Note refers.
(2) If associated with a DOE/NRC F 741, 742, and/or 742C, copies of
DOE/NRC F 740M will be attached as applicable.
(3) Under certain circumstances, a DOE/NRC F 740M can be submitted as a
stand alone document (e.g., to comply with IAEA reporting requirements).
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CHAPTER XI - MATERIAL BALANCE REPORTING
1. INTRODUCTION.
a. This Chapter provides instructions to DOE license-exempt contractors and NRC
and Agreement State licensees that are DOE contractors for the preparation and
distribution of DOE/NRC F 742, Material Balance Report, (MBR) or its
electronic equivalent.
b. Chapter XII contains special MBR instructions for facilities that have been
selected under the terms of either the U.S./IAEA Safeguards Agreement or
Protocol. The calculations for, and preparation of, the MBR to be provided to the
IAEA will be performed by NMMSS. Before the report is dispatched to the
IAEA, NMMSS will provide a copy to the facility concerned to ensure that the
data is correct.
c. A MBR must be prepared either by the NMMSS operator or by the facility. A
facility may place a standing request with NMMSS to have a NMMSS-generated
MBR, DOE/NRC F 742, provided to the facility in lieu of submission of reports.
In such cases, the facility that receives the NMMSS-generated report must
reconcile the facility’s balances to the NMMSS. Reconciling transactions must be
submitted if NMMSS balances are to be changed.
d. MBRs must be submitted—
(1) annually, by September 30 for all facilities and additionally as directed by
the DOE cognizant security authority; or
(2) as specified in facility attachments or transitional facility attachments for
DOE facilities selected under the provisions of the U.S./IAEA Safeguards
Agreement.
e. Nuclear material in transit at the end of a reporting period will be included in the
receiver’s reported inventory as if it had reached the intended receiver within the
reporting period (in transit rule).
f. Radioactive decay will be reported on MBRs on an annual basis when the decay
has reached reportable quantities or at a more frequent reporting interval if
required by the DOE cognizant security authority.
Section 76
2. CLASSIFICATION AND SECURITY REQUIREMENTS. The submitted MBR,
whether submitted on paper or electronically, will be classified using appropriate
classification guidance and following the procedures contained in DOE M 475.1-1A,
Identifying Classified Information and will be marked with appropriate classification
markings and transmitted following procedures contained in DOE M 470.4-4,
Information Security.
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3. REPORTING UNITS.
a. Quantities will be reported by element and isotope weight in metric units. Refer
to Tables XV-2 and XV-17.
b. Enter the element weight, i.e., total weight of all isotopes contained in the element
being reported in column A.
c. Enter the isotope weight, i.e., weight of the isotopes for the element being
reported in column B.
d. Convert volume measurements that have been made or records that are kept in
volume units to the reporting unit for the material type.
e. If the degree of precision to which facility records are kept is greater than that
required for reporting purposes, the rounding procedures defined in Chapter II,
paragraph 6. will be used.
4. INSTRUCTIONS FOR COMPLETING DOE/NRC F 742. Data submitted on paper will
be reported as follows.
a. Block 1. Enter the name and address of the facility.
b. Block 2. Enter the appropriate possession license numbers if the reporting facility
is a licensed contractor.
c. Block 3, RIS. Enter the RIS under which the material being reported is or was
held. Submit a separate DOE/NRC F 742 for each RIS.
d. Block 4, Report Period. Enter inclusive dates (MM/DD/YYYY).
e. Block 5, Material Type. Enter the name of the material (See Table XV-1).
NOTE: Submit a separate report for each type.
f. Block 6a, Process Code. Leave blank.
g. Block 6b, Correction ID. Leave blank.
h. Block 7, DOE/NRC F 740M Attached. Only required for facilities selected
under the U.S./IAEA Safeguards Agreement.
i. Line 8, Beginning Inventory—U.S. Government Owned. Enter inventory of
U.S. Government owned material as of opening of business on the first day of the
report period covered by the DOE/NRC F 742. These figures will not differ from
line 80 of the DOE/NRC F 742 submitted at the close of the preceding report
period.
j. Line 9, Beginning Inventory—Not U.S. Government Owned. Enter inventory
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of non-DOE-owned material as of the opening of business on the first day of the
report period covered by the DOE/NRC F 742. These figures will not differ from
line 81 of the DOE/NRC F 742 submitted at the close of the preceding report
period.
k. Line 11, Procurement from DOE. Enter quantities of material purchased from
DOE during the report period. (Quantities entered on line 11 will not be entered
on line 30.)
l. Line 13, Procurement for the Account of DOE. Enter quantities of material
procured from domestic and foreign sources that increase the assets of DOE.
Returns of DOE-owned leased material from licensees and foreign entities will be
entered on line 30. The following are examples of procurement to be reported on
line 13.
(1) Material acquired under the terms of an international agreement for
cooperation with foreign entity.
(2) Material previously sold by DOE to a licensee or foreign entity and then
repurchased by DOE.
(3) Material procured from private owners.
m. Line 14, DoD Returns—Use A. Enter quantities of material in returns of
weapons and weapons components issued to DoD under Presidential directive.
Section 77
n. Line 15, DoD Returns—Use B. Enter quantities of material contained in returns
of training material issued to DoD under Presidential directive.
o. Line 16, DoD Returns—Other Uses. Enter quantities of material in returns of
reactor cores, fission chambers, and other material issued to DoD under
Presidential directive for use in military non-weapons programs (e.g., nuclear
research and development, propulsion, or electric power generation programs).
p. Line 21, Production. Enter quantities of material obtained through
transmutation.
(1) For production reactors, production will be reported in the period during
which transmutation takes place in the reactor.
(2) For reactors other than production reactors, production will be reported no
less often than upon discharge from the reactor. If the operation of the
reactor for the year long period October 1 through September 30, results in
nuclear production of 5 kilograms or more of enriched uranium or
plutonium, production must be reported on DOE/NRC F 742 as of
September 30, and no less often than annually.
(3) Differences between reactor calculations and dissolution measurements
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will be reported on line 21. Production of insignificant quantities of
material (quantity is less than 0.5 of the reporting unit for a specific
material type), as in a materials testing reactor, need not be reported unless
the material is to be recovered or a reporting requirement is imposed by
the DOE cognizant security authority.
q. Line 22, From Other Materials. Enter receipts from other material balances as
a result of intentional blending or crossovers. Facilities selected under the
U.S./IAEA Safeguards Agreement should see Chapter XII for additional
requirements. Examples of receipts to be reported on line 22 are given below.
(1) In a production reactor, normal uranium will become depleted uranium
during operation of the reactor. Line 22 on the depleted uranium MBR for
the facility operating the reactor will indicate receipts from the normal
uranium balance. Correspondingly, line 71 on the normal uranium MBR
for the facility will reflect removals to the depleted uranium balance.
(2) The blending of depleted and enriched uranium in the proper proportions
will result in normal uranium. Line 22 on the normal uranium MBR will
indicate receipts from the depleted and enriched uranium balances.
Correspondingly, line 71 on the depleted and enriched uranium MBRs will
reflect removals to the normal uranium balance.
r. Line 30. Receipts Reported to DOE/NRC (on DOE/NRC F 741). Enter, by
transfer series, all receipts for the report period not entered on lines 11-16, 34, 37,
38, and 39. If more space is needed than is provided on DOE/NRC F 742,
prepare a sub-schedule entitled “Receipts Reported to DOE/NRC on DOE/NRC
F 741 (not listed elsewhere).” Facilities selected under the U.S./IAEA Safeguards
Agreement should see Chapter XII for additional requirements.
s. Line 34, Receipts—Miscellaneous. Enter quantities of material received in
two-party transactions where only receiver’s data are reported. Examples include
receipts of material (not reported elsewhere) from facilities that have not been
assigned a RIS, and receipts from licensees that are not required to document or
report transactions.
t. Line 37, Procurement by Others. Enter quantities of material purchased by the
facility for its own account from in situ material, which it had been holding under
lease from the DOE, or, material that the facility is processing for a non-DOE
facility against a non-DOE purchase order.
Section 78
u. Line 38, Donated Material—from U.S. Government to Others. Enter
quantities of material donated, i.e., change in ownership without transfer of funds,
which increase the reporting facility’s non-U.S. Government-owned inventory
and decrease the assets of the U.S. Government.
v. Line 39, Donated Material—from Others to the U.S. Government. Enter
quantities of material donated, i.e., change in ownership without transfer of funds,
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which increase the assets of U.S. Government and decreases the reporting
facility’s non-U.S. Government owned inventory.
w. Line 40, Total. Enter the total of lines 8–39.
x. Line 41, Expended in Space Programs. Enter quantities of material transferred
for use in a space vehicle (e.g., for propulsion or nuclear auxiliary power system).
The reporting facility will provide the DOE cognizant security authority the
following details with respect to ultimate disposition of the material.
(1) Date vehicle was launched into space or placed into orbit, or if vehicle
misfired or failed to orbit, losses of material associated therewith (if
attempts at recovery have been made and there is some recovery, only
material not recovered will be reported on line 41).
(2) Project name.
(3) Launch site.
(4) Any other pertinent information.
y. Line 42, Sales to U.S. Government. Enter quantities of material sold during the
reporting period. (Quantities entered on line 42 will not be entered on line 51.)
z. Line 43, Sales to Others for the Account of U.S. Government. Enter quantities
of U.S. Government owned material sold to other Government agencies,
licensees, and foreign entities.
aa. Line 44, DoD—Use A. Enter quantities of material in shipments of weapons and
weapons components to DoD under Presidential directive.
bb. Line 45, DoD—Use B. Enter quantities of material in shipments of Training
Material to DoD under Presidential directive.
cc. Line 46, DoD—Other Uses. Enter quantities of material in shipments of reactor
cores, fission chambers, and other material to DoD under Presidential directive
for use in military non-weapons programs (e.g., nuclear research and
development, propulsion, or electric power generation programs).
dd. Line 47, Expended in U.S. Government Tests. Enter quantities of material
expended in U.S. tests authorized by the President.
ee. Line 48, Routine Tests. Enter quantities of source material expended in routine
testing associated with weapons-related research and development activities. The
use of line 48 for the reporting of other than source material requires prior
approval by the DOE cognizant security authority.
ff. Line 49, Shipper-Receiver Difference. Leave blank.
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gg. Line 51, Shipments Reported to DOE/NRC (on DOE/NRC F 741). Enter, by
transfer series, all shipments for the reporting period not entered on lines 42–46,
54, 58, and 59. If more space is needed than is provided on DOE/NRC F 742,
prepare a sub schedule entitled “Shipments Reported to DOE/NRC on DOE/NRC
F 741 (not listed elsewhere).” Facilities selected under the U.S./IAEA Safeguards
Agreement should see Chapter XII for additional requirements.
hh. Line 54, Shipments—Miscellaneous. Enter quantities of material shipped in
two-party transactions where only shipper’s data are reported. Examples include
shipments (not reported elsewhere) to facilities that have not been assigned a RIS,
and shipments to licensees that are not required to document or report
transactions.
Section 79
ii. Line 58, Donated Material—to U.S. Government by Others. Enter quantities
of material donated i.e., change in ownership without transfer of funds, which
decrease the reporting facility’s non-U.S. Government owned inventory and
increase the assets of the U.S. Government.
jj. Line 59, Donated Material—to Others by the U.S. Government. Enter
quantities of material donated i.e., change in ownership without transfer of funds,
which decrease the assets of the U.S. Government and increase the reporting
facility’s non-U.S. Government owned inventory.
kk. Line 65, Rounding Bias. Enter any rounding bias quantity that is technically
supportable.
ll. Line 71, Degradation to Other Materials. Enter removals to other material
balances as a result of intentional blending degradation, or crossovers. Facilities
selected under the U.S./IAEA Safeguards Agreement should see Chapter XII for
additional requirements. Examples of removals to be reported on line 71 are
given below.
(1) In a production reactor, normal uranium will become depleted uranium
during operation of the reactor. Line 71 on the normal uranium MBR for
the facility operating the reactor will indicate removals to the depleted
uranium balance. Correspondingly, line 22 on the depleted uranium MBR
for the facility will reflect receipts from the normal uranium balance.
(2) The blending of depleted and enriched uranium in the proper proportions
will result in normal uranium. Line 71 on the depleted and enriched
uranium MBRs will indicate removals to the normal uranium balance.
Correspondingly, line 22 on the normal uranium MBR will reflect receipts
from the depleted and enriched uranium balances.
mm. Line 72, Decay. Apply the appropriate decay factor as indicated in Chapter XV
and enter the calculated radioactive decay on line 72.
nn. Line 73, Fission and Transmutation. Enter quantities of material consumed as a
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result of exposure in a device.
(1) For DOE production reactors, material consumed will be reported on a
current basis, i.e., as transmutation and burn-up take place in the reactor.
(2) For reactors other than production reactors, material consumed will be
reported no less often than upon discharge from the reactor. If the
operation of the reactor for the year long period October 1 through
September 30 results in a nuclear loss of 5 kilograms or more of enriched
uranium or plutonium, the quantity of material consumed must be reported
on line 73 of DOE/NRC F 742 as of September 30 and no less often than
annually.
(3) Differences between reactor-calculated quantities of material consumed
and the quantities measured after dissolution will be reported on line 73.
oo. Line 74, NOLs/Measured Discards. Enter known quantities of material,
determined by measurement or by estimate on the basis of measurement, which
have been intentionally removed from inventory and disposed of by approved
methods. NOLs/measured discards result when known quantities of nuclear
material are separated from a process or operation as waste during processing and
are determined to be uneconomical to recover. Facilities selected under the
U.S./IAEA Safeguards Agreement should see Chapter XII for additional
requirements. Examples of quantities to be reported on line 74 of DOE/NRC
F 742 are—
(1) discards to cribs, tanks, settling ponds, or waste management sites; and
(2) discards in contaminated equipment, laundry, or shoe covers.
Section 80
pp. Line 75, Accidental Losses. Enter known quantities of material, determined by
measurement or by estimate on the basis of measurement to have been
inadvertently lost as a result of an operational accident.
qq. Line 76, Approved Write-offs. Enter known quantities of “good” materials
which, with prior approval by the DOE cognizant security authority, have been
removed from inventory records. Approved write-offs are usually restricted to
“good” material that has been used in such a manner as to lose its identity and for
which nuclear material accountability is deemed no longer necessary. If material
that was previously removed as a write-off is returned to active inventory, enter a
negative quantity on line 76 to reestablish nuclear material accountability.
rr. Line 77, Inventory Difference. Enter the algebraic difference between the
physical inventory and its corresponding book inventory after determining that all
known additions and removals have been reflected in the book inventory.
Inventory difference may be either a positive or negative quantity. A gain of
material is reflected by a negative inventory difference, and will be indicated by a
negative (minus) sign.
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ss. Lines 80, Ending Inventory—U.S. Government Owned. Enter, as appropriate,
the inventory as of the close of business of the last day of the reporting period. If
a physical inventory is to be used as the basis for ending inventory reported on
lines 80 and 81, the physical inventory must be adjusted for all additions and
removals occurring between the time of the physical inventory and the close of
the report period. The ending inventory entered on lines 80 and 81 must agree
with the respective totals for the material type submitted to the NMMSS on
DOE/NRC F 742C, Physical Inventory Listing.
tt. Line 81, Ending Inventory— Not U.S. Government Owned. Enter, as
appropriate, the inventory as of the close of business of the last day of the
reporting period.
uu. Line 82, Total. Enter total of lines 41–81. The total reported on line 82 must
agree with the total reported on line 40.
vv. Line 83, Bias Adjustment. Not applicable to contractors.
ww. Section B—Foreign Obligations. The total amount of obligated nuclear material
on hand as of the date of the report (amount on line 80 or 81 or the sum of lines
80 and 81) must be accounted for within material type, but may not exceed
physical inventory. The following entries, by column, are required.
(1) Block 1: Country of Obligation. Enter the 2-character country or entity
designation from Table XV-15.
(2) Block 2: Element Weight. Enter the element weight of the amount
obligated from Table XV-16. The only material types to be reported are
10, 20, 50, 70, 81, and 88.
(3) Block 3, Isotope Weight. For enriched uranium (in U-235 and or U-233)
only. Enter the isotope weight of the amount obligated to the nearest
gram.
(4) Block 4, Total Weight. Enter the totals for columns 2 and 3. These totals
represent the total obligated material at the facility.
xx. Section C—Certification. DOE/NRC F 742 will be signed and dated by the
reporting facility’s authorized representative.
yy. Distribution of DOE/NRC F 742 Data. Do not send a copy of DOE/NRC F 742
data to the NMMSS if arrangements have been made to receive a NMMSS
generated MBR or if reporting electronically. If DOE/NRC F 742 is prepared in
paper form, copies of each will be distributed to NMMSS and also to other
recipients, if any, in accordance with instructions provided by the DOE cognizant
security authority.
Section 81
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CHAPTER XII - MATERIAL BALANCE REPORTING—
FACILITIES SELECTED BY THE IAEA
1. INTRODUCTION. Special procedures must be used to implement some of the reporting
requirements of the U.S./IAEA Safeguards Agreement. This Chapter provides
instructions for use of these special procedures for facilities that have been selected under
the terms of either the U.S./IAEA Safeguards Agreement or Protocol. Such facilities
should note that all requirements and procedures in the main body of this Manual apply
in addition to the special requirements of this Chapter.
2. PREPARATION OF DOE/NRC F 742.
a. DOE/NRC F 742 or its electronic equivalent will be completed by filling in the
numbered blocks or lines listed in Chapter XI plus the fields that follow.
b. Block 7, DOE/NRC F 740M Attached. Place a X in the appropriate box.
Concise Notes are optional unless required by facility attachments or transitional
facility attachments. DOE/NRC F 740M, Concise Note, will be used by selected
facilities to supplement material balance data on DOE/NRC F 742. Instructions
for preparation and distribution of DOE/NRC F 740M are provided in Chapter X.
c. Line 22, From Other Materials. For each entry on this line, fill in the
appropriate 2-character ICT code (see Table XV-18) in the space provided to
indicate the source and destination material balances for the inventory change
being reported. The IAEA does not require the reporting of category changes for
enriched uranium.
d. Line 30, Receipts Reported to DOE/NRC on DOE/NRC F 741. Reporting of
receipts of material for facilities selected by the IAEA may require additional
procedures. Contact the Office of Plutonium, Uranium and Special Materials
Inventory for further information. (See also code 10 of the Subsidiary
Arrangements to the U.S./IAEA Safeguards Agreement.)
e. Line 51, Shipments Reported to DOE/NRC (on DOE/NRC F 741 Shipments of
material for facilities selected by the IAEA may require additional procedures.
Contact the Office of Plutonium, Uranium and Special Materials Inventory for
further information. (See, also code 10 of the Subsidiary Arrangements to the
U.S./IAEA Safeguards Agreement.
f. Line 71, Degradation to Other Materials. For each entry on this line, enter the
appropriate 2-character ICT code (Degradation), as shown in Table XV-18, in the
space provided to indicate the source and destination material balances for the
inventory change being reported.
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CHAPTER XIII - INVENTORY REPORTING
1. INTRODUCTION.
a. This Chapter provides instructions to license-exempt contractors and NRC and
Agreement State licensees that are contractors for the preparation and distribution
of DOE/NRC F 742C, Physical Inventory Listing.
b. Facilities transmitting data electronically to the NMMSS do not need to complete
DOE/NRC F 742C but must follow the data format defined in these instructions.
c. Data submitted will accurately reflect data entered on the related DOE/NRC
F 742C, if F 742C is prepared. If data is submitted to NMMSS electronically, do
not also submit the paper form.
d. Special instructions for facilities selected by the IAEA under the terms of the
U.S./IAEA Safeguards Agreement or Protocol are provided in Chapter XIV.
e. Inventory reports will be submitted to the NMMSS—
(1) By September 30 and additionally as directed by the DOE cognizant
security authority; or
Section 82
(2) as specified in facility attachment or transitional facility attachments for
DOE facilities selected under the provisions of the U.S./IAEA Safeguards
Agreement.
f. Reports are due to the NMMSS operator no later than the 15th calendar day of the
month following the due date of the inventory report.
g. Nuclear material in transit at the end of a reporting period will be included in the
receiver’s reported inventory as if it reached the intended receiver within the
reporting period (in transit rule).
2. NUCLEAR MATERIAL COMPOSITION CODES AND DESCRIPTIONS.
a. Nuclear material composition codes and descriptions may be found in the
inventory profile report (I-17 report from NMMSS) developed by DOE, their
contractors, and NRC. The report is to be used as a guide for reporting the
inventory composition code on DOE/NRC F 742C. A facility selected by the
IAEA will report the IAEA material description code as appropriate.
b. The inventory profile will be updated as warranted and distributed to the
appropriate users. The report is divided into an inventory data section (lines 005–
899) and a miscellaneous data section (lines 900–998). Each section is arranged
according to process, usage, chemical, and physical form. The report is designed
so that additional lines can be added as necessary to both the inventory data
section and the miscellaneous data section. Any proposed changes in the format
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are to be reported to the Office of Plutonium, Uranium and Special Materials
Inventory.
3. AUTHORIZED PROFILES OF INVENTORY DATA.
a. Based on the nuclear material composition codes and descriptions referred to
above, inventory profiles (I-17 reports from NMMSS) have been established for
individual facilities and are contained in the authorized inventory profile report.
Submission of compositions of ending inventory (COEI)3 is to be based on the
facility’s profile. Necessary additions to the profile should be made prior to
submission of inventory data to the NMMSS. The authorized inventory profile
(I-17 reports from NMMSS) must contain one of the codes, P, B, or C, for
inventory data lines 005-899 as follows:
(1) P—piece count, material having a serial or other identification number.
(2) B—bulk count, material not having a serial or other identification number.
Material in a container having an identification number should be held on
a bulk count basis, unless the material in the container has an
identification number.
(3) C—combination piece count/bulk count, material being held on both a
piece count and a bulk count basis.
(4) The authorized inventory profile by facility report (I-17 report from
NMMSS) acknowledges miscellaneous data lines 900–998 with an X in
lieu of codes P, B, or C.
(5) Entry lines will be deleted from a facility’s profile when it is determined
that no material in a category will be held on inventory for a reasonable
period of time, i.e., at least 12 months.
(6) Any proposed changes in a facility’s profile must be submitted through the
DOE cognizant security authority prior to coordination with the Office of
Plutonium, Uranium and Special Materials Inventory.
4. NUCLEAR MATERIAL TYPE CODES. Material type codes, descriptions, and
reporting units are given in Table XV-2.
5. RECONCILIATION OF FACILITY DATA WITH NMMSS.
a. Reconciliation of facility data is required annually of facilities after submission of
September 30 inventory data. The process is as follows:
Section 83
(1) The facility submits its inventory for the period just ended and is provided
with the results of processing in NMMSS.
3 For a listing of the COEI codes, contact the NMMSS Operator.
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(2) Preliminary reports are available upon request from the NMMSS for
facility use in comparing facility data to NMMSS balances.
(3) The data at the facility and comparable data in the NMMSS are compared
and adjustments are made to the facility books or to NMMSS, as
appropriate, regarding balances of material by type, ownership code, and
project number, if DOE-owned.
b. Reconciliation of facility data with NMMSS more frequently than the annual
periods required above is permissible.
6. PREPARATION OF DOE/NRC F 742C. The instructions that follow correspond to
those data fields and columns appearing on DOE/NRC F 742C. To obtain instructions
for electronic reporting, contact the NMMSS operator. Whether reporting electronically
or by DOE/NRC F 742C, the following instructions apply.
a. Block 1, Name and Address. Enter reporting facility information.
b. Block 2, DOE/NRC Form 740M Attached. Check the appropriate box.
c. Block 3, RIS. Enter the RIS of the reporting facility.
d. Block 4, Inventory Date. Enter the ending date on which the MBR is based.
e. Block 5, Process Code. Leave blank.
f. Block 6, Correction ID. Leave blank.
g. Block 7, License Numbers. Leave blank.
h. Block 8, Batch Data.
(1) Block 8a, Material Type. Enter the material type code that reflects the
material assay range unless, the material is being reported under one of the
following categories.
(a) Losses—Weapons and Nonweapons [42 U.S.C. §2121(b),
Material]. For material reported by assay range, use the
appropriate material type code from Table XV-17.
(b) Losses—42 U.S.C. §2121(c) Material. For material reported by
assay range, use the appropriate material type code from Table
XV-17.
(c) Scrap Data (Lines 971–974). If reporting scrap generated onsite,
recovered onsite, recategorized onsite, or declared to the Central
Scrap Management Office, use the appropriate material type code
from Table XV-17.
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(2) Block 8b, Comp/Fac Code. Enter the appropriate codes from the
Tables in Chapter XV.
(3) Block 8c, Element Weight. Enter element weights as per the instructions
in Chapter XI for DOE/NRC F 742.
(4) Block 8d, Isotope Weight. Enter isotope weights as per the instructions
in Chapter XI for DOE/NRC F 742.
(5) Block 8e, DOE Project Number. Make no entry unless reporting DOE
owned material.
(6) Block 8f, Scrap Program. Leave blank.
(7) Block 8g, Weight percent Isotope. Leave blank.
(8) Block 8h, Owner Code. Enter the appropriate code from Table XV-3.
(9) Block 8i, Sequence Number. Enter the line sequence numbers
consecutively. Do not repeat or skip numbers.
(10) Block 8j, Batch Name. No entry required. Can be used locally by
reporting facility.
(11) Block 8k, Number of Items. Leave blank.
(12) Block 8l, Key Measurement Point. Leave blank.
(13) Block 8m, Measurement ID (Measurement Basis, Other Measurement
Point, Measurement Method). Leave blank.
(14) Block 8n, Entry Status. Leave blank.
(15) Block 8o, MBA. Leave blank.
(16) Block 8p, Site/Item Description Code. Leave blank.
i. Block 9, Totals. Enter the total inventory reported in the above categories. This
total must agree with the sum of the quantities entered on Line 80 and 81 on the
DOE/NRC F 742.
Section 84
j. Block 10, Signature. The report, if submitted as a hard copy, will be signed by
an authorized representative of the facility.
k. Block 11, Title. Enter the title of the person submitting the report.
l. Block 12, Date. Enter the date the report was submitted.
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7. DISTRIBUTION OF DOE/NRC F 742C DATA. Provide the physical inventory listing
to NMMSS and to others as specified by the DOE cognizant security authority.
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CHAPTER XIV - INVENTORY REPORTING—
FACILITIES SELECTED BY THE IAEA
1. INTRODUCTION. Special procedures must be used to implement some of the reporting
requirements of the U.S./IAEA Safeguards Agreement. This Chapter provides
instructions for facilities that have been selected either under the terms of the U.S./IAEA
Safeguards Agreement or Protocol. Such facilities should note that all requirements and
procedures in the main body of this Manual apply, in addition to the special requirements
of this Chapter. Refer to Chapter XIII for specific data entry instructions.
2. BATCH FORMATION AND NAMING.
a. The U.S./IAEA Safeguards Agreement requires inventories to be reported at the
batch level of detail.
b. The nuclear material may be in bulk form or contained in a number of separate
items. Typical batches for inventory reporting are given in facility attachments or
transitional facility attachments.
c. In general, all of the data for one batch will be entered on one line of DOE/NRC
F 742C. Material in any one batch must have only one value for the following
elements:
(1) batch identification;
(2) number of items;
(3) inventory composition code;
(4) key measurement point; and
(5) measurement identification (i.e., measurement basis, other measurement
point, and measurement method).
d. If a batch has more than one value for any other data element, the data should be
listed on two or more lines, with all data elements completed for each line, even if
this requires that some batch data be repeated.
e. A typical case where two lines would be required for the data on one batch would
be a batch of irradiated fuel containing both uranium and plutonium. In this case,
one line would be used for the uranium data, and a second for the plutonium data.
The two lines should have identical entries for all data elements except for project
number (if applicable), material type code, element weight, weight percent
isotope, and isotope weight.
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CHAPTER XV - NUCLEAR MATERIAL REPORTING—
DATA ITEMS SUMMARY TABLES
1. INTRODUCTION. The following are explanatory comments regarding the data item
tables. This Chapter provides shorthand tables to further assist personnel in determining
the information needed for nuclear material reporting.
2. DATA ITEMS EXPLANATORY NOTES.
a. General. The RISs used and For/To accounts are as follows.
(1) ANY—any RIS except DoD RISs,
(2) CON—any contractor RISs,
(3) LIC—licensee RISs,
(4) FOR—foreign RISs,
(5) CONV—contractor V RISs,
(6) SEP for isotopic separation facility RISs, and
(7) DoD for Department of Defense RISs.
b. For additional instructions, See Table XV-7.
3. ACCOUNTABLE QUANTITIES, MATERIAL TYPES AND OTHER INFORMATION
NEEDED FOR REPORTING. Tables follow:
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Table XV-1. Nuclear Material Reporting Units and Characteristics.
Name of Material MT
Code
Reporting Weight
Unit Report to
Section 85
Nearest Whole Unit
Element
Weight
Isotope
Weight
Isotope
Weight %
Depleted Uranium 10 Whole Kg Total U U-235 U-235
Enriched Uranium 20 Whole Gm Total U U-235 U-235
Plutonium-2421 40 Whole Gm Total Pu Pu-242 Pu-242
Americium-2412 44 Whole Gm Total Am Am-241 –
Americium-2432 45 Whole Gm Total Am Am-243 –
Curium 46 Whole Gm Total Cm Cm-246 –
Californium 48 Whole Microgram – Cf-252 –
Plutonium 50 Whole Gm Total Pu Pu-239+Pu-241 Pu-240
Enriched Lithium 60 Whole Kg Total Li Li-6 Li-6
Uranium-233 70 Whole Gm Total U U-233 U-232 (ppm)
Normal Uranium 81 Whole Kg Total U – –
Neptunium-237 82 Whole Gm Total Np – –
Plutonium-2383 83 Gm to tenth Total Pu Pu-238 Pu-238
Deuterium4 86 Kg to tenth D2O D2
Tritium5 87 Gm to hundredth Total H-3 – –
Thorium 88 Whole Kg Total Th – –
Uranium in Cascades6 89 Whole Gm Total U U-235 U-235
1 Report as Pu-242 if the contained Pu-242 is 20 percent or greater of total plutonium by weight; otherwise, report as
Pu 239-241.
2 Americium and Neptunium-237 contained in plutonium as part of the natural in-growth process are not required to
be accounted for or reported until separated from the plutonium.
3 Report as Pu-238 if the contained Pu-238 is 10 percent or greater of total plutonium by weight; otherwise, report as
plutonium Pu 239-241.
4 For deuterium in the form of heavy water, both the element and isotope weight fields will be used; otherwise,
report isotope weight only.
5 Tritium contained in water (H2O or D2O) used as a moderator in a nuclear reactor is not an accountable material.
6 Uranium in cascades is treated as enriched uranium and should be reported as material type 89.
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Table XV-2. Nuclear Material Type Codes.
Type
Code
Type
Description
Reporting
Unit
Type
Code
Type
Description
Reporting
Unit
Uranium Depleted in U-235 44 Americium 241 gm
10 Total 45 Americium 243 gm
11 <0.21% U-235 kg 46 Curium gm
12 0.21 to < 0.24% U-235 kg 48 Californium microgram
13 0.24 to < 0.26% U-235 kg Plutonium
14 0.26 to < 0.28% U-235 kg 50 Total gm
15 0.28 to < 0.31% U-235 kg 51 < 4.00% Pu-240 gm
16 0.31 to < 0.50% U-235 kg 52 4.00 < 7.00% Pu-240 gm
17 0.50 to < 0.60% U-235 kg 53 7.00 < 10.00% Pu-240 gm
18 0.60 to <0.710% U-235 kg 54 10.00 < 13.00% Pu-240 gm
Uranium Enriched in U-235 55 13.00 < 16.00% Pu-240 gm
20 Total 56 16.00 < 19.00% Pu-240 gm
21 > 0.712 to < 0.90% U-235 gm 57 19.00% and above Pu-240 gm
22 0.90 to < 1.15% U-235 gm Lithium Enriched in Li-6
23 1.15 to < 1.60% U-235 gm 60 Total kg
24 1.60 to < 2.00% U-235 gm 61 >Normal (7.42%) to
< 55.00%
kg
25 2.00 to < 2.60% U-235 gm 62 55.00 to < 80.00% kg
26 2.60 to < 2.90% U-235 gm 63 80.00% and above kg
27 2.90 to < 3.10% U-235 gm Uranium Enriched in U-233
28 3.10 to < 3.40% U-235 gm 70 Total gm
29 3.40 to < 3.90% U-235 gm 71 < 5 ppm U-232 gm
30 3.90 to < 4.10% U-235 gm 72 5 to < 10 ppm U-232 gm
31 4.10 to < 5.00% U-235 gm 73 10 to < 50 ppm U-232 gm
32 5.00 to < 10.00% U-235 gm 74 50 ppm and above U-232 gm
33 10.00 to < 20.00% U-235 gm 81 Normal U
34 20.00 to < 35.00% U-235 gm Total
35 35.00 to < 45.00% U-235 gm 0.710 to < 0.712% U-
235
kg
36 45.00 to < 80.00% U-235 gm 82 Np 237 Total gm
37 80.00 to < 92.00% U-235 gm 83 Pu 238 Total gm to tenth
38 92.00 to < 94.00% U-235 gm 86 D2 Total kg to tenth
39 94.00% and above U-235 gm 87 Tritium Total gm to
Section 86
hundredth
Plutonium 242 88 Thorium Total kg
40 Total gm 89 U in Cascades Total gm
41 20% thru 60% gm 90 This series is available for local
use
42 > 60% gm
Table XV-3. Owner Codes.
Owner Code Type of Ownership of Material
G U.S. Government owned material
J All other non U.S. Government owned material
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Table XV-4. Half Life and Daily Decay Factors.
Radioactive Half-life and Decay Constants
Source: Brookhaven National Laboratory, National Nuclear Data Center, Nuclear
Wallet Cards, 6th Edition, January 2000
Element Isotope Half-Life
Standard
Deviation
Daily Decay
Constant (days-1)
Americium 241 432.2 y 0.700 y 0.00000439
Curium 242 162.8 d 0.200 d 0.00425766
Curium 244 18.10 y 0.020 y 0.00010485
Berkelium 249 330 d 4.000 d 0.00210045
Californium 252 2.645 y 0.008 y 0.00071749
Plutonium 238 87.7 y 0.300 y 0.00002164
Plutonium 241 14.290 y 0.006 y 0.00013280
Hydrogen
(Tritium)
3 12.33 y 0.060 y 0.00015392
Table XV-5. Decay Factors for Monthly Reporting Periods. *
Decay Factors for Months—Days in Month
Element
Isotope
Deduct
From
28
29
30
31
Americium 241 E&I 0.000123 0.000127 0.000132 0.000136
Curium 242 E only 0.119215 0.123472 0.127730 0.131987
Curium 244 E only 0.002936 0.003041 0.003145 0.003250
Berkelium 249 I only 0.058812 0.060913 0.063013 0.065114
Californium 252 I only 0.020090 0.020807 0.021525 0.022242
Plutonium 238 E&I 0.000606 0.000628 0.000649 0.000671
Plutonium 241 E&I 0.003719 0.003851 0.003984 0.004117
Hydrogen
(Tritium)
3 E only
0.004310 0.004464 0.004617 0.004771
*“E only” means that the calculated Decay Weight is to be deducted from the Element Weight. “I only” means that the calculated Decay Weight
is to be deducted from the Isotope Weight. “E&I” means that the calculated Decay Weight is to be deducted from the weights of both Element
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Table XV-6. Decay Factors for Quarterly Reporting Periods.
Decay Factors for Quarters—
Days in Quarter
Element Isotope Deduct
From 89 90 91 92
Americium 241 E&I 0.000391 0.000395 0.000399 0.000404
Curium 242 E only 0.378932 0.383189 0.387447 0.391705
Curium 244 E only 0.009332 0.009436 0.009541 0.009646
Berkelium 249 I only 0.186940 0.189040 0.191141 0.193241
Californium 252 I only 0.063857 0.064575 0.065292 0.066010
Plutonium 238 E&I 0.001926 0.001948 0.001969 0.001991
Plutonium 241 E&I 0.011820 0.011952 0.012085 0.012218
Hydrogen
(Tritium)
3 E only 0.013698 0.013852 0.014006 0.014160
For tables XV-7 and XV-8, the following notes apply. Within the tables, specific numbers
are shown in parentheses to highlight some of the following notes.
(1) For those transaction types where there is a difference between shipper's
and receiver's reporting requirements, an S and an R will exist in this
column to reflect the differences. Only those data items which have
different requirements will be separated into the S row and R row. All
other common data items will exist on the row between the S and R.
(2) When to licensee, shipper RIS may be ANY, receiver RIS must be LIC.
When from licensee, receiver RIS may be ANY, shipper RIS must be LIC.
(3) For and to accounts must both contain contractor RIS when owner is G,
there is no change in ownership, and shipper and/or receiver have licensee
or foreign RIS. RISs identify the DOE contractors having programmatic
responsibility for the material before and after shipment.
Section 87
(4) DoD or mutual defense side of entry is not applicable.
(5) Must contain a regular DoD RIS or a valid Q military installation RIS to
reflect points of first destination for DoD receipts or pickup points for
DoD returns.
(6) Required only when shipper has a licensee or foreign RIS; then it must be
contractor RIS.
(7) Must be licensee RIS if shipper owner code is A or B, foreign entity RIS if
shipper owner code is S.
(8) Must be licensee RIS if receiver owner code is A or B, foreign entity RIS
if receiver owner code is S.
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(9) For/to accounts cannot be equal.
(10) For/to accounts must be equal.
(11) Required only when receiver has a licensee or foreign RIS; then it must be
contractor RIS.
(12) Appropriate licensee or foreign RIS in the account if shipper's owner code
is an A, B, or S; contractor in the account if shipper's owner code is G and
shipper has a licensee or foreign RIS; the field is blank otherwise.
(13) Shipper or receiver RIS must be in the V series.
(14) Appropriate licensee or foreign RIS in the account if receiver's owner code
is an A, B, or S; contractor in the account if receiver's owner code is G and
receiver has a licensee or foreign RIS; the field is blank otherwise.
(15) QZA, QZB, and QZD are restricted to material types 20, 40, 50, 70, and
83.
(16) If the DOD's RIS is QZE the Inventory Change code will be deemed to be
either 14 or 44; if the RIS is QZC the IC code will be either 15 or 45; if
the RIS is QZA, QZB, or QZD the IC code will be either 16 or 46.
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Table XV-7. Instructions for Preparation of Transaction Data Items.
Transaction Type S/R
(1) TI Code S RIS R RIS For
Account
To
Account
Owner
Code
Required
1. DOE-owned material; transfer between contractors Blank CON CON Blank Blank G
2. Transfer of on-DOE owned Blank ANY ANY Blank Blank J
3. DOE-owned project material transfers to/from licensees
(non-lease or loan)
Blank -2 (2) (3) (3) G
S A ANY ANY (6) LIC, FOR G
4. Initiates loan/lease of DOE-owned material
R A ANY ANY (6) LIC, FOR G
5. Transfer of leased/loaned material; change in financial
responsibility
B ANY ANY (7,9) (8,9) G,J
S C ANY ANY (7,10) (7,10) G,J 6. Transfer of leased/loaned material; no change in financial
responsibility R C ANY ANY (8,10) (8,10) G,J
S D ANY ANY LIC, FOR (11) G,J
7. Leased/loaned material returned to DOE for credit
R D ANY ANY LIC, FOR (11) G,J
S E ANY ANY (12) LIC, FOR G,J
8. Sale for account of DOE
R E ANY ANY (12) LIC, FOR J
S F ANY SEP LIC, FOR Blank J
9. Enriching service procurement (feed receipt)
R F ANY SEP LIC, FOR Blank J
S F SEP ANY Blank LIC, FOR J
10. Enriching service sale (product shipment)
R F SEP ANY Blank LIC, FOR J
S G ANY ANY LIC, FOR (11) J
11. Procurement of privately owned material by DOE
R G ANY ANY LIC, FOR G,J
12. Donated material to others by DOE R (Same requirement as transaction Type 8)
13. Donated material to DOE by others S (Same requirement as transaction Type 11)
14. In-place transactions
In-place transaction should change ownership. Use data requirements of
applicable transaction type as a guide. Shipper and receiver must be same
RIS.
15. In-place project transfer Shipper and receiver must be same RIS. Use DOE Form DOE/NRC F 741.
16. Exports; shipments to foreign countries (R RISs) Transactions are prepared in the same manner as transfers to/from licensees
except reporting entity must report both sides.
Section 88
17. Imports; receipts from foreign countries (R RISs) Transactions are prepared in the same manner as transfers to/from licensees
except reporting entity must report both sides.
18. Inventory changes—removal Blank ANY ANY (12) Blank G, J
19. Inventory changes—receipt Blank ANY ANY Blank (14) G, J
20. Transfers involving waste facilities (V RISs) Blank (13) (13) Blank Blank G, J
21. Shipper or receiver adjustment
Must have an entry in correction field (block 4). Used to correct prior entries,
therefore, prepare the adjusting entry using the same guidelines as the original
entry for data records numbers 2 and 5, back out the original line entry in error
and add the correct entry. Any of the permissible owner codes for the applicable
transaction type will be accepted independently without the presence of a required
owner code.
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Table XV-8. Instructions When Either the DoD or
Mutual Defense Is Involved.
S RIS R RIS TI
Code
Action
Code
For
Account
To
Account
Owner
Code
Required
1. Transfer to DoD
(4, 16)
CON DoD
(15)
Blank A, C Blank (5) G
2. Transfer from DoD
(4, 16)
DoD CON Blank B, D, E (5) Blank G
3. Transfer from DoD
(16)
DoD DoD
(16)
Blank M Blank Blank G
4. Transfer to Mutual
Defense;
Loan/Lease
CON QZF or
QZG
A A, C Shipper Shipper G
5. Transfer to Mutual
Defense; Return of
Loaned Material
CON QZF or
QZG
Blank Blank Receiver Receiver J
6. Transfer to Mutual
Defense; Sale
CON QZF or
QZG
E Blank Blank Receiver G
7. Transfer from Mutual
Defense; Loan of
Material
QZF or
QZG
CON Blank B, D, E Shipper Shipper J
8. Transfer from
Mutual Defense;
Return of
Loaned/Leased
Material
QZF or
QZG
CON D B, D, E Receiver Receiver G
9. Transfer from Mutual
Defense; Sale to
DOE
QZF or
QZG
CON Blank B, D, E Blank Receiver J
Table XV-9. Processing Code (PC).
Processing Code (PC) Block 5
A Entry of new data set
C Replacement of data set
D Deletion of data set
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Table XV-10. Action Code (AC).
Action Code
(AC) Block 6
A Shipper's original data
B Receiver's data accepting shipper's weights without measurement
C Shipper's adjustment or acknowledgment
D Receiver's adjustment or acknowledgment
E Receiver's independent measurement or determination
J1 Receiver's interim data reporting material in transit or project receipts
M One-party transaction
N2 Known delay in receiver reporting of at least 10 days but less than 30 days
P In-place transfers between projects
R Identifies a one-party transaction to remove the WR obligation on material.
S3 Receiver's data accepting shipper's weights under a safeguards closure
T Contested weights
U4 Known delay in receiver reporting of at least 30 days
X Shipper's side of an obligation exchange
Y Receiver's side of an obligation exchange
1Action code J identifies receiver’s interim reporting of project receipt of DOE production or research materials that are in transit at the end of
the month or that have been received but not reported. A transaction with action code J must be followed with action code B, E, or S.
2A transaction with action code N must be followed with action code B, E, or S. Note: NRC defines action code N differently from DOE, and
NRC does not use action code S.
3Safeguards closure only for certain facilities. Restricted to DOE sites, owner code G, shipper and receiver can’t be the same, TI is blank, can’t
use with a V RIS, and detail lines are reported.
Section 89
4A transaction with action code U must be followed with action code B, E, or S.
Table XV-11. Nature of Transaction Indicator (TI) Code.
Nature of
Transaction
Code (TI)
Block 11
A Initiates loan/lease
B Transfers loan/lease
C Transfer of leased/loaned material with no change in loan/lease responsibility
D Return of leased/loaned material to DOE for credit
E Sale for DOE
F Pursuant to an enriching service agreement
G Sale to DOE
R Transfer from Government to private inventory other than by sale or enriching service agreement
S Transfer from private to Government inventory other than by sale or enriching service agreement
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Table XV-12. Inventory Change Code—Receipts.
Inventory
Change
Code
Blocks 26c and 27c Other Receipts
11 Procurement from DOE
13 Purchase Procurement—For Account of DOE
14 DoD Returns—Use A
15 DoD Returns—Use B
16 DoD Returns—Other Uses
21 Production
22 From Other Materials
30 Receipts reported to DOE/NRC on DOE/NRC F 741 (not listed elsewhere)
34 Receipts—Miscellaneous
37 Procurement by Others
38 Donated Material—from DOE to Others
39 Donated Material—from Others to DOE
Table XV-13. Inventory Change Code—Removals.
Inventory
Change
Code
Blocks 26c and 27c Other Removals
41 Expended in Space Programs
42 Sales to DOE
43 Sales to Others for the Account of DOE
44 DoD—Use A
45 DoD—Use B
46 DoD—Other Uses
47 Expended by DOE Tests
48 Routine Tests
51 Shipments reported to DOE/NRC on DOE/NRC F 741 (not listed
elsewhere)
54 Shipments - Miscellaneous
58 Donated Material—to DOE by Others
59 Donated Material—to Others by DOE
65 Rounding Bias (used for A-M transactions)
71 Degradation to Other Materials
72 Decay
73 Fission and Transmutation
74 Normal Operational Losses/Measured Discards
75 Accidental Losses
76 Approved Write-offs
77 Inventory Differences
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Table XV-14 Material Type Codes and IAEA Element Codes—Import Export.
Description U.S. Material Type Code IAEA Element Code
Depleted Uranium 10 D
Enriched Uranium 20 EG
Plutonium 50 P
Normal Uranium 81 N
Thorium 88 T
All Others (All Other Codes) (Blank)
Table XV-15. Foreign Obligation Codes.
Country/Entity Obligation Codes*
31 Australia
32 Canada
33 EURATOM
34 Japan
35 Peoples Republic of China
36 Czech Republic
91 Australia and EURATOM
92 Canada and EURATOM
WR Former Soviet Union Weapons
*NOTE: For any other obligation codes not included above, contact the NMMSS Operator for further instructions.
Table XV-16. Material Type Codes, IAEA Element Codes, and Quantities for
Source and SNM—Obligations Tracking.
Type Domestic Code IAEACode Reportable Obligated Quantity*
Natural Uranium MT 81 N Kilogram Uranium
Depleted Uranium MT 10 D Kilogram Uranium
Thorium MT 88 T Kilogram Thorium
Plutonium MT 50 P Gram Plutonium
High Enriched Uranium MT 20 ≥ 20% EG Gram Total Uranium for Element
Gram U-235 for Isotope
Low Enriched Uranium MT 20 < 20% EG Gram Total Uranium for Element
Gram U-235 for Isotope
Uranium-233 MT 70 EK Gram Total Uranium for Element
Gram U-233 for Isotope
*For foreign obligations tracking, only the element weight is required except for uranium enriched in U-235 or U-233.
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Table XV-17. Material Type Codes Used For Specific Circumstances.
Name of Material Material Type
Code
Uranium-Depleted in U-235 11
Uranium-Enriched in U-235 21
Plutonium 51
Lithium-Enriched in Li-6 61
Section 90
Losses—Weapons and Nonweapons
(See 42 U.S.C. §2121(b) Material)
Uranium-Enriched in U-233 71
Uranium-Depleted in U-235 11
Uranium-Enriched in U-235 21
Plutonium 51
Lithium-Enriched in Li-6 61
Losses
(See 42 U.S.C. §2121(c) Material)
Uranium-Enriched in U-233 71
Uranium-Depleted in U-235 10
> 0.711% to < 10.00% 21
10.00% and above 33
Scrap Data
Plutonium 51
Uranium-Depleted in U-235 10
Uranium-Enriched in U-235 20
Plutonium-242 40
Plutonium 50
Lithium-Enriched in Li-6 60
Total—Inventory Data
Uranium-Enriched in U-233 70
Table XV-18. Inventory Change Type (ICT) Codes—IAEA.
ICT Code From Balance To Balance
DN Depleted Uranium Normal Uranium
DE Depleted Uranium Enriched Uranium
ND Normal Uranium Depleted Uranium
NE Normal Uranium Enriched Uranium
ED Enriched Uranium Depleted Uranium
EN Enriched Uranium Normal Uranium
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DOE M 470.4-6
08-26-05
Section B
XV-13
Table XV-19. DOE Contractor Reporting Procedure for
Normal Operational Losses/Measured Discards and Accidental Losses.
Types of Transactions
Shipper Receiver
(S) (R)
Action Code
S R
Applicable to
(Type of Facility)
Description from Viewpoint
Of the Facility
Inventory
Change Code
(use code)
S R
Project Number
S R
Data
Generated
By NMMSS
Facility RIS
with H, I, L
appended
Facility RIS
with H, I, L
appended
M (one single
party entry)
1. Non-Lic DOE contr.
(non-IAEA)
2. FAC under IAEA
3. Lic contr.
Material written off to reflect
internal changes to waste
disposition areas inventory—
removed from facility's
inventory
Single entry:
65, 72, 76, 77
Single entry: not
required
None
Facility is same
as Receiver
Facility is same
as Shipper
M (one single
party entry)
1. Non-Lic DOE contr.
(non-IAEA)
NOL/MD/AL not to
atmosphere, or ground and not
coincident with transfer to
burial site—removed from
facility's inventory
Single entry:
74, 75 or 48
Single entry:
req. if G owner
code
None
Facility RIS
Facility RIS
with A, G, R
appended
(same site as
Shipper)
A N/A 1. Non-lic DOE contr.
(non-IAEA)
2. Fac under IAEA
3. Lic contr.
NOL/MD/AL1 to atmosphere,
ground, or consumed in
research—removed from
shipper's inventory
74, 75
or 48
N/A Req.
for
owner
code
G
N/A
Receiver
Facility RIS Facility RIS
with H, I, L
appended
(same site as
Shipper)
A N/A 1. Fac. under IAEA
2. Lic. contr.
3. See note 3
NOL/MD/AL1 to a retained
waste holding area—removed
from shipper's inventory
74, 75 N/A Req.
for
owner
code
G
N/A Receiver
when type fac
= 1 or 2
None when
type
fac = 3
Facility RIS VVV A B/E 1. Non-Lic. DOE contractor
(non-IAEA)
2. Facility under IAEA
3. Licensed contractor
NOL/MD/AL1 removed from
shipper's inventory coincident
with the removal to a burial
site
74, 75
or 48
not
req.
(leave
blank)
Req.
for
owner
code
G
not req.
(leave
blank)
None
FAC > VVV A B/E2 1. Non-Lic. DOE contractor
non-IAEA)
Transfer of material to burial
site where material previously
removed from shipper's
inventory by M transaction—
no effect to shipper's records
not req.
(leave
blank)
not
req.
(leave
blank)
not req.
(leave
blank)
not req.
(leave
blank)
None
Facility RIS
with
H or L
appended
VVV A B/E2 1. Fac. under IAEA
2. Lic. contr.
3. See footnote
Transfer of material from a
retained waste holding area to
the burial site
not
req.
(leave
blank)
not
req.
(leave
blank)
not req.
(leave
blank)
not req.
(leave
blank)
None
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08-26-05
Section B
XV-14
Table XV-19. (continued)
Section 91
Types of Transactions
Shipper Receiver
(S) (R)
Action Code
S R Applicable to (Type of Facility) Description from Viewpoint
Of the Facility
Inventory
Change Code
(use code)
S R
Project
Number
S R
Data Generated
By NMMSS
Facility RIS
with I or G
appended
VVV A B/E2 1. Non-Lic. DOE
contr. (non-IAEA)
2. Fac. under IAEA
3. Lic. contr.
Material previously written off as
discarded to the ground now being
recovered and transferred to a
burial site
not
req.
(leave
blank)
not req.
(leave
blank)
not
req.
(leave
blank)
not
req.
(leave
blank)
None
Facility RIS
with I or G
appended
VVV A B/E2 1. Non-Lic. DOE
contr. (non-IAEA)
2. Fac. under IAEA
3. Lic. contr.
Material previously written off as
discarded to the ground now being
recovered and transferred to a
burial site
not
req.
(leave
blank)
not req.
(leave
blank)
not
req.
(leave
blank)
not
req.
(leave
blank)
None
Facility RIS
with H, I, L
appended
Facility RIS
(same site
as,Shipper)
N/A B/E2 1. Fac. under IAEA
2. Lic. contr.
3. See footnote 3
Transfer of material from a
retained waste holding area back to
facility's inventory
N/A N/A N/A req.
if G
owner
code
Shipper when type
fac = 1 or 2
None when type fac
= 3
VVV Facility RIS A2 B/E 1. Non-Lic. DOE
contr. (non IAEA)
2. Fac. under IAEA
3. Lic. contr.
Material being retrieved from a
burial site for some specific use—
increases receiver's inventory
not
req.
(leave
blank)
not req.
(leave
blank)
not
req.
(leave
blank)
req.
if G
owner
code
None
VVV Facility RIS A2 B/E 1. Non-Lic. DOE
contr. (non IAEA)
Material previously written off as
NOL/MD/AL and transferred to a
burial site—now being returned to
the facility—NOL REVERSAL
not
req.
(leave
blank)
74, 75
or 48
not
req.
(leave
blank)
req.
if G
owner
code
None
VVV Facility RIS with
A, G, I appended
A2 B/E Burial site shipping is specifically
identified contractor's waste
disposition area
Material previously written off as
NOL/MD/AL1 and transferred to a
burial site—now being dissipated
to atmosphere or ground or
transferred to an incinerator from
burial site—not to be treated as
NOL/MD/AL1
not
req.
(leave
blank)
not req.
(leave
blank)
not
req.
(leave
blank)
not
req.
(leave
blank)
None
1NOL/MD/AL—Normal Operational Loss/Measured Discard/Accidental Loss
2For DOE burial site, applicable shipper or receiver data is not reported to NMMSS
3Reporting under this method is optional for non-licensed DOE contractors not under IAEA reporting requirements
FAC = DOE contractor facility, VVV = Burial Site
Facility fourth character indicates a discharge to: A = atmosphere, G = ground, H = on-site waste holding area, I = toxic substance control act incinerator, L = lagoon, tank or
holding pond, R = consumed in research
NOTE: All other data elements are the same as normal requirements.
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Section B
XVII-1
CHAPTER XVI - ACRONYMS AND ABBREVIATIONS
ANSI American National Standards Institute
CFR Code of Federal Regulations
COEI Composition of Ending Inventory
CRD Contractor Requirements Document
DoD Department of Defense
DOE Department of Energy
FOIA Freedom of Information Act
IAEA International Atomic Energy Agency
ICT inventory change type
ID inventory difference
INMTS International Nuclear Materials Tracking System
MBA material balance area
MBR material balance report
MC&A materials control and accountability
MT material type
NDA nondestructive assay
NMR nuclear materials representative
NMMSS Nuclear Materials Management Safeguards System
NNSA National Nuclear Security Administration
NOL normal operational loss
NRC Nuclear Regulatory Commission
PC processing code
RIS reporting identification symbol
SED shipper's export declaration
SIMEX Secure Information Management and Exchange Network
SNM special nuclear materials
TI transaction indicator
U.S.C. United States Code
Section 92
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Section B
XVII-1
CHAPTER XVII - FORMS
The following images are examples of the paper forms that can be used for data submission to
the NMMSS. However, electronic submission of data is the required method unless manual
submission is coordinated with the DOE cognizant security authority. The forms are for
illustrative and instructional purposes. Do not print out these forms and use them to submit data
to NMMSS. The correct copies of the forms to use to submit data to the NMMSS are available
for download in portable document format (PDF) from the NMMSS operator or from
http://directivesdoe.gov/forms/index.htm.
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Section B
XVII-2
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Section B
XVII-3
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Section B
XVII-4
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Section B
XVII-5
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Section B
XVII-6
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Section B
XVII-7
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Attachment 1-1
DEPARTMENTAL ELEMENTS TO WHICH
DOE M 470.4-6 APPLIES
Office of the Secretary
National Nuclear Security Administration
Office of the Chief Information Officer
Office of Civilian Radioactive Waste Management
Office of Counterintelligence
Office of Energy Efficiency and Renewable Energy
Office of Environment, Safety and Health
Office of Environmental Management
Office of Fossil Energy
Office of the Inspector General
Office of Intelligence
Office of Management, Budget and Evaluation and Chief Financial Officer
Office of Nuclear Energy, Science and Technology
Office of Policy and International Affairs
Office of Science
Office of Security and Safety Performance Assurance
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Attachment 2-1
ATTACHMENT 2
CONTRACTOR REQUIREMENTS DOCUMENT
Regardless of the performer of the work, the contractor is responsible for compliance with the
requirements of this Contractor Requirements Document (CRD). The contractor is responsible
for flowing down the requirements of this CRD to subcontracts at any tier to the extent necessary
to ensure the contractor's compliance. In doing so, the contractor will neither unnecessarily nor
imprudently flow down requirements to subcontracts.
A violation of the provisions of this directive relating to the safeguarding or security of
Restricted Data or other classified information may result in a civil penalty pursuant to
subsection a. of section 234B. of the Atomic Energy Act of 1954 (42 U.S.C. 2282b.). The
procedures for the assessment of civil penalties are set forth in Title 10, Code of Federal
Regulations, Part 824, "Procedural Rules for the Assessment of Civil Penalties for Classified
Information Security Violations," (10 CFR part 824.)
This CRD consists of Section A and B of the preceding Manual, DOE M 470.4-6, Nuclear
Material Control and Accountability, with the exception of the following paragraphs that only
apply to DOE elements.
Section A, Chapter I, paragraph 1.f.
Section A, Chapter I, paragraph 5.b.
Section B, paragraph 3.c.
Section B, Chapter I, paragraph 1.b.Section B, Chapter III, paragraph 15.a.
Section B, Chapter IV, paragraph 1.o.(2)(e)
Section B, Chapter VI, paragraph 1.c.(2)(a)-(h)
Section B, Chapter VI, paragraph 3.a.-c.
Section B, Chapter VII, paragraph, 2.b
The following paragraphs should be substituted for designated sub-sections as they only apply to
DOE contractors.
Section A, Chapter II, paragraph 5.a.(5)
Section 93
The site/facility management contractor must submit request for acceptance of SNM in
foreign reactor fuel without measurement through DOE line management to be approved
by the Under Secretary and or his/her designee.
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08-26-05
Attachment 2-2
Additionally, where DOE M 470.4-6, Nuclear Material Control and Accountability, requires the
DOE cognizant security authority or DOE line management to approve a plan, procedure, or
requirement, the contractor shall submit the plan, procedure, or requirement to the DOE
cognizant security authority or DOE line management for approval in a timely manner and shall
not operate under the plan, procedure, or requirement until it has been approved by the DOE
cognizant security authority or DOE line management, whichever approval is applicable. Where
DOE M 470.4-6, Nuclear Material Control and Accountability, requires the DOE cognizant
security authority or DOE line management to establish materials control and accountability
requirements, the contractor will follow the requirements established by the DOE cognizant
security authority or DOE line management.
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