DOE O 5820.2, Radioactive Waste Management

u.s. Department "of Energy ORDER Washington, D.C. DOE 5820.2 2-6-84 SUBJECT: RADIOACTIVE WASTE MANAGEMENT 1. PURPOSE. To establish policies and guidelines by which the Department of Energy (DOE) manages its radioactive waste, waste byproducts, and radioactively contaminated surplus facilities. 2. CANCELLATION. DOE 5820.1, MANAGEMENT OF TRANSURANIC CONTAMINATED MATERIAL, of 9-30-82. 3. SCOPE. The provisions of this Order apply to all DOE elements and, as required by law and/or contract, all DOE contractors and subcontractors performing work that involves management of radioactive waste and/or radio­ actively contaminated facilities for DOE under the Atomic Energy Act of 1954 as amended (Public Law 83-703). 4. REFERENCES. a. DOE 5440.18, IMPLEMENTATION OF THE NATIONAL ENVIRONMENTAL POLICY ACT, of 5-14-82, ,,;hich establishes the Department's policy for implementation of the Nationai Environmental Policy Act of 1969 (Public Law 91-190). b. DOE 5480.1A, ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH PROTECTION PROGRAM FOR DOE OPERATIONS, of 8-13-81, which establishes an overall framework of program requirements for safety and environmental and health protection, including criteria for radiation exposure and radioactive effluent releases for operating facilities and sites. c. DOE 5480.2, HAZARDOUS AND RADIOACTIVE MIXED WASTE MANAGEMENT, OF 12-13-82, which provides interim guidance for managing mixed waste (radioactive waste containing nonradioactive hazardous constituents). d. DOE 5484.1, ENVIRONMENTAL, SAFETY, AND HEALTH PROTECTION INFORMATION REPORTING REQUIREMENTS, of 8-13-81, which establishes requirements and practices for reporting environmental, health, and safety information for J • DOE operations. e. DOE 5484.2, UNUSUAL OCCURRENCE REPORTING SYSTEM, of 8-13-81, which establishes the Department's policy and provides instructions for a system of reporting, analyzing, and disseminating information on programmatically Significant events. DISTRIBUTION: INITIATED BY: All Departmental Elements Assistant Secretary for Federal Energy Regulatory Commission (info) Defense Programs 2 DOE 5820. 2 2-6-84 J f. DOE 5481.1A, SAFETY ANALYSIS AND REVIEW SYSTEM, of 8-13-81, which establishes uniform requirements for the preparation and review of safety analyses of DOE operations. g. DOE 5632.2, PHYSICAL PROTECTION OF SPECIAL NUCLEAR MATERIALS, of 2-16-79, which establishes minimum physical protection standards for special nuclear materials. h. DOE 5700.6A, QUALITY ASSURANCE, of 8-31-81, which sets forth principles and assigns responsibilities for establishing, implementing, and main­ taining programs of plans and actions to assure quality achievement in the Department's programs. i. DOE 1540.1, MATERIALS TRANSPORTATION AND TRAFFIC MANAGEMENT, of 5-3-82, which establishes the Department's policies for management of materials transportation activities. j. DOE 4320.1A, SITE DEVELOPMENT AND FACILITY UTILIZATION PLANNING, of 3-17-83, which establishes policies and procedures and assigns responsi­ bilities and authorities for site development and facility utilization planning. k. DOE 6410.1, MANAGEMENT OF CONSTRUCTION PROJECTS, of 5-26-83, which establishes policies and procedures for the planning and execution of construction programs and projects. 1. DOE 4300.1A, REAL ESTATE MANAGEMENT, of 7-7-83, which establishes Departmentwide policies and procedures for the acquisition, use, and disposal of real estate (real property) or interests therein.

m. DOE 1430.1, MANAGING THE DEPARTMENT OF ENERGY'S SCIENTIFIC AND TECHNICAL INFORMATION, of 2-23-83, which establishes the policy that scientific and technical information developed during work supported by DOE shall be promptly and fully reported to the Technical Information Center (MA-28), located in Oak Ridge, Tennessee, for inclusion in the Department's information data base. n. WIPP-DOE-069, "TRU Waste Acceptance Criteria for the Waste Isolation Plant," of 9-81, as updated, which specifies basic requirements for disposal of contact-handled and remote-handled transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP). Copies of this and other DOE WIPP reports can be obtained from the Albuquerque Operations Office. o. RLO/SFM-83-12, "Program Plan,.' volume I, of 10-83, as updated, which is issued by the Department of Energy's Surplus Facilities Management Program and provides procedures for managing surplus radioactively contaminated facilities. Copies may be obtained from the Director of the Surplus Facilities Management Program, Richland Operations Office. p. DOE/NE-0017-1, "Spent Fuel and Radioactive Waste Inventories, Projections, J and Characteristics," of 10-82, ~lhich with annual updates, sUDll1arizes data in the Integrated Data Base program on all domestic spent fuel and o DOE 5820.2 3 2-6-84 radioactive waste. Energy, Germantown, Copies may be obtained from the Office of Nuclear or the Technical Information Center, Oak Ridge. q. Uranium Mill Tailings Radiation Control Act of 1978 (Public Law 95-604), which establishes national policy for control of uranium mill tailings. r. Nuclear Waste Policy Act of 1982 (Public Law 97-425), which provides for the development of repositories for the disposal of high-level waste and spent nuclear fuel. s. RLO/SFM-82-7, uSurpl us Facil iti es Management Program Methodology for Establishing Decommissioning Priorities," of 6-82, which establishes methods for developing priorities for decommissioning surplus facilities. t. Title 5 CFR 1320, "Controlling Paper!;/ork Burdens on the Public," which serves as the implementing regulation for Public Law 96-511, JlPaperwork Reduction Act of 1980,11 and directs the identification and clearance of information collections levied on the public, including contractors, State and local government units, and persons who perform services for the Department on an individual basis. 5. OBJECTIVE. To establish requirements to assure that all DOE operations involving the management of radioactive ,/aste, waste byproducts, and surplus facilities pursuant to the Atomic Energy Act of 1954 as amended (Public Law 83-703) are conducted to adequately protect the public health and safety, and in accordance with radiation protection standards specified in DOE 'Orders. 6. DEFINITIONS. a. Buffer Zone. The portion of a DOE site that surrounds the storage/ disposal site and is not used for storage/disposal, but \/here publ ic access is restricted. i I • b. Byproduct Material. Waste produced by the extraction or concentration of uranium or thorium from any ore processed primarily for its source material content, including discrete surface waste resulting from uranium solution extraction processes. The term excludes fission products and other radioactive material covered in 10 CFR Part 20.3(3). c. Certified Waste. Waste that has site 'taste acceptance criteria. been confirmed to comply with disposal

d. Decontamination. The removal of radioactive contamination from facilities, soils, or equipment by washing, chenica1 action, mechanical cleaning, or other techniques. e. Deconvnissioning. Actions taken to reduce the potential health and safety impacts of surplus facilities, including activities to stabilize, reduce, or remove radioactive contamination. 4 DOE 5820. 2 2-6-84 f. Defense Waste. Radioactive waste from any activity performed in whole in part in support of DOE atomic energy defense activities. The term excludes radioactive waste under purview of the Nuclear Regulatory Commission or generated by the commercial nuclear power industry. or g. Department of Enerff Radioactive Waste. Radioactive waste generated directly by activi~es of the Department (or its predecessors) and its contractors or subcontractors or other radioactive waste for which the Department is responsible. Such waste may be referred to as DOE waste. h. Disposal. Emplacement of waste in a manner that assures isolation from the blosphere without maintenance and with no intent of retrieval and that requires deliberate action to gain access to the waste after emplacement. i. Diseosal Site. acbvities. The area dedicated to waste disposal and related j. Engineered Barrier. A manmade addition to the disposal site that is designed to retard or preclude radionuclide transport and/or to preserve the integrity of the disposal site. k. Geologic Repository. radioactive waste. An underground mined cavity used for the disposal of 1. Greater Confinement. A technique for disposal of waste that uses natural and/or engineered barriers which provide a degree of isolation greater than that of shallow land burial but possibly less than that of a geologic repository. m. High-Level Waste (HlW). The highly radioactive waste material that results from the reprocessing of spent nuclear fuel, including liquid waste produced directly in reprocessing and any solid waste derived from the liquid, that contains a combination of TRU waste and fission products in concentrations as to require permanent isolation. n. low-level Waste (LLW). Radioactive waste not classified as waste, TRO waste, spent nuclear fuel, or byproduct material this Order. high-level as defined by o. ~latural Barrier. The physical, chemical, and hydrological characteristics of the geological environment at the disposal site that, individually and collectively, act to retard or preclude transport of radioactivity. p. Naturally Occurring Radionuclides. Radionuclides and their decay products (except transuranlum radionuclides) that occur naturally in the environment. q. Radioactive Waste. Solid, liquid, or gaseous material of negligible economic value that contains radionuclides in excess of threshold quantities except for radioactive material activities. from post weapons test o DOE 5820. 2 5 2-6-84 r. Radioactive Waste Management. The planning, coordination, and control of those functions related to handling, treatment, storage, transportation, and disposal of radioactive waste, as well as associated surveillance and maintenance activities. s. Remedial Action. Activities conducted to reduce potential radiation exposure to people and potential harm to the environment from radioactive contamination. t. Shallow Land Burial. Disposal of waste in near-surface excavations that are covered with a protective overburden.

u. Spent Nuclear Fuel. Fuel that has been withdrawn from a nuclear reactor following irradiation, the constituent elements of which have not been separated by reprocessing. v. Storage. Retention of waste in a retrievable manner that requires survel11ance and institutional control. w. Storage Site. The area dedicated to waste storage and related activities. x. Surplus Facility. Any facility or site (including equipment) that has no identified programmatic use and is radioactively contaminated to levels that require controlled access. y. Threshold Quantity. With reference to DOE waste, a quantity or concen­ trat.ion of radioactivity above which the waste must be managed according to the requirements of this Order and below which the waste may be disposed of as nonradioactive waste at an approved sanitary landfill. z. Transuranium Radionuclide. Any radionuclide having an atomic number greater than 92. aa. TRU Waste. Without regard to source or form, radioactive waste that at the end of institutional control periods is contaminated with alpha­ emitting transuraniurn radionuclides with half-lives greater than 20 years and concentrations greater than 100 nCi/g. Regarding the Waste Isolation Pilot Plant, high-level waste and spent nuclear fuel as defined by this Order are specifically excluded by this defjnition. bb. Waste Byproducts. Material, other than special nuclear material, that if separated and recovered from nuclear fuel cycle waste streams can be used for safe, environmentally acceptable, and cost-effective applications. cc. Waste Container. A containment vessel for radioactive waste, including any liner or shielding material that is intended for disposal. dd. Waste Package. The radioactive waste, waste container, and absorber that are intended for storage or disposal as a unit. In the case of 6 DOE 5820.2 2-6-84 contaminated, damaged, leaking, or breached waste packages, any overpack shall be considered the waste container, and the original container shall be considered part of the waste. 7. RESPONSIBILITIES. a. for Defense Pro ra~s (DP-l) has pri~ary authority for estab ishing po icy or the management 0 radioactive \'taste and responsibility for assuring that DOE radioactive \'/aste generated by the Department's activities under DP-l cognizance, or any other radioactive waste within the purview of DP-l, is managed according to the requirements of this Order and that DP-l programmatic decisions include waste ~anage~ent considerations, as appropriate. Specific responsibilities include: (1) I~plementing safe storage and disposal of all DOE \'taste except LLW and byproduct materials disposed of by the Assistant Secretary for Nuclear Energy and radioactive waste and spent nuclear fuel stored or disposed of by the Director of Civilian Radioactive Waste Management, and for developing and i~ple~enting beneficial uses for waste byproduct ~aterials; (2) Implementing alternative technologies and processes to support disposal of DOE waste; (3) Developing the Waste Isolation Pilot Plant (WIPP), a facility near Carlsbad, New Mexico, for conducting research and development to der.lOnstrate safe disposal of radioactive \/aste from defense activities and progra~s of the United States exempted fro~ regulation by the Nuclear Regulatory COQrnission; (4) Conducting research and development for DOE waste transportation syste~s, and providing for safe, efficient, and econo~ic transport of ~aterials pursuant to DOE 1540.1;

(5) Managing surplus facilities fro~ the Depart~ent's defense prograQ activities; (6) Assuring that environ~ental, safety, health, transportation, quality assurance, unusual occurrence, construction project ~anage~ent, real estate manage~ent, and facil ity design require~ents set forth in DOE Orders are impl e~ented for DOE \laste ~anage~ent progra~s under DP-l authori ty; (7) Operating documentation systems to provide data to the Integrated Data Base progra~ (see page 2, paragraph 4p) from defense progra~ activities and providing, in cooperation with RW-l, for ~aintenance and operation of the Integrated Data Base progra~; and 7 o DOE 5820.2 2-6-84 (8) Implementing the information collection and clearance requirements contained in 5 CFR 1320 as they apply to Defense Program contractors, their employees, and other members of the public from whom informa­ tion is collected under the provisions of this Order. b. Director of Defense Waste and Eyproducts Management (DP-12) has lead responslbillty for general overview, and for preparing and interpreting policy set forth in this Order, and for Headquarters implementation of requirements under this Order for DOE radioactive waste management programs under DP-12 cognizance. Specific responsibilities include: storage/disposal operations for defense waste; management of defense surplus facilities; consultation with other Headquarters organizations, as appropriate, and field organizations when new or alternative site-specific waste management practices are proposed; arranging for independent health, safety, and quality assurance audits to assess the degree of field organization implementation of the requirements of this Order; issuing updated guidance; and reviewing documents and plans required on page 9, paragraph 7i and page 10, paragraph 8. c. Director of Civilian Radioactive ~Jaste Manaaement RW- ; responsi b e or se ec e researc an eve opmen , s1 1ng, construction, operation, and management activities assigned to the Secretary of Energy by the Nuclear Waste Policy Act of 1982 (Public law 97-425) for the interim storage and disposal of HlW and spent nuclear fuel and for long-term care of closed commercial llW sites transferred to DOE; has lead responsibility, in cooperation with the Assistant Secretries for Defense Programs and Nuclear Energy, for managing the Integrated Data Base program (see page 2, paragraph 4p); and is responsible for assuring that environ­ mental, safety, health, transportation, quality assurance, unusual occurrence, construction project management, real estate management, facility design requirements, and information collection and clearance procedures set forth in DOE Orders are implemented for RW-l activities. d. Assistant Secretary for Nuclear Energy (NE-1) is responsible for assuring that DOE radioactive waste generated by all DOE operations under NE-l cognizance are managed according to the requirements of this Order and that program decisions include waste management considerations, as necessary. Specific responsibilities include: (1) Managing DOE radioactive waste from NE-1 projects, including designated inactive uranium mill tailings sites, formerly utilized sites, surplus facilities, and the Three Mile Island and West Valley projects, until transferred to a DOE or licensed storage/disposal site; (2) Managing DOE radioactive waste generated by the Department's uranium enrichment operations and disposed at sites located at the Oak Ridge, Portsmouth, and Paducah gaseous diffusion plants;

8 DOE 5820.2 2-6-84 J (3) Managing DOE radioactive waste generated by the Departr.1ent ' s breeder reactor, space nuclear, and naval reactor progra~s until it is transferred to a DOE or licensed storage/disposal site; (4) Developing alternative technologies and processes to support storage and disposal of radioactive ~/aste or spent fuel generated by the Departr.1ent's nuclear energy progra~; (5) Managi ng surpl us faci 1 ities fro~ the DepartJ:lent I s nuclear activities and radioactive ,<,aste storage/disposal sites that are the responsibility of NE-l; (6) Developing and i~pl~enting cOr.1~ercial applications for uaste byproducts; (7) Assuring that environr.1ental, safety, health, transportation, quality assurance, unusual occurrence, construction project ~anager.1ent, real estate ~anage~ent, and facility design requirer.lents set forth in DOE Orders are i~ple~ented for nuclear energy waste prograr.1s; (8) Operating support docur.1entation syster.1s to provide data to the Integrated Data Base progra~ (see page 2, paragraph 4p) and providing, in cooperation \lith RW-l, for r.1aintenance and operation of the Integrated Data Base progra~; and (9) Ir.lpler.1enting the infomation collection and clearance requirer.1ents contained in 5 CFR 1320 as they apply to Nuclear Energy contractors, their employees, and other ~~bers of the public from uhol:1 inforna­ tion is collected under the provisions of this Order. e. Assistant Secretary for Policy, Safety, and Environment (PE-l) l$'responsible for providinq an independent overview and acivisinq the Secretary of the status of Departmental compliance with the requirements of this Order and, as they apply to radioactive waste management and decommissioning operations, other a~plicable Orders such as DOE 5480.1A, IS DOE 5480.2,_and DOE 5440.1B. f. Directors of Other Headquarters Progra~ Organizations are responsible for i~plel:1enting the requirer.1ents of this Order for all radioactive waste generated by their progra~s until it is transferred to a DOE or licensed storage/disposal site and for assuring that progra~ decisions include uaste ~anage~ent considerations as necessary, and that environl:1ental, safety, health, transportation, quality assurance, construction project manager.1ent, real estatel:1anager.1ent, and facility design requirel:1ents set forth in DOE orders are ir.lplel:1ented for their radioactive \/aste ~anagel:1ent progra~s. g. Office of General Counsel (GC-l) provides legal advice to program organizations regarding DOE wastel:1anager.1ent and decol:1r.1issioning activities involving DOE-owned and privately owned sites. Renders legal opinion on DOE authority to undertake re~edial action and other waste http:syster.1s http:prograr.1s o 9DOE 5820.2 2-6-84 management activities. Renders legal opinions and concurs in program actions to comply with the National Environmental Policy Act (see page 1 t paragraph 4a) and other legal authorities in conjunction with proposed waste management and decommissioning activities. h. i. Heads of Field Organizations are responsible for assuring that day-to-day radioactive waste management operations and surplus facility programs at their sites are conducted in compliance with the requirements of this Order. Field organizations in consultation with DP-12, PE-l, and other Headquarters organizations as appropriate, may establish threshold quantities and new or alternate waste disposal practices at their specific sites based on appropriate documented safety, health protection. and economic analyses. Specific responsibilities include:

(1) Documenting detailed radioactive waste management practices and procedures that apply to all operations at their respective sites. These documents shall include appropriate references to safety, health, environmental, economic, and other analyses. They shall also include procedures for performance of impact analyses and obtaining exemptions from their respective site-specific requirements for storage/disposal of radioactive waste that are consistent with applicable law. (2) Preparing annual updates of waste Management Plans for all operations under their cognizance according to the format in Attachment 1. These plans shall be submitted at the end of each fiscal year and distributed to DP-12, PE-l, and other appropriate Headquarters Program Offices for review and comment. (3) Fiscal responsibility for waste transportation and establishing fees, as necessary, for storage and disposal of DOE waste at their sites. (4) Maintaining environmental, safety, health and quality assurance programs for all radioactive waste management programs under their cognizance. (5) Managing surplus facilities for which they are responsible according to the requirements of this Order. (6) Reporting any unusual occurrences (including potential excessive radiation exposures) associated with DOE waste management operations at their sites per the requirements of DOE 5484.2. (7) Approval authority for certification programs, standard containers, transportation, waste acceptance criteria (see page 2, paragraph 4n), 10 DOE 5820. 2 2-6-84 and all other aspects related to TRU \laste er.lplacer.1ent at the WIPP have been delegated to the Manager of Albuquerque Operations Office. j. Deputy Ass i stant secreta~~ for Nava 1 Reactors (NE-60) a SSUr.1es the sar.le responsibility as Heads 0 Field Organizations for his prograr.1 activities. O. IMPLEMENTING PROCEDURES AND REQUIREMENTS. a. Within 6 r.1onths of the date of issuance, Heads of Field Organizations shall prepare and subr.lit an if.1pler.lentation plan containing schedules and costs for cOr.1pliance \lith the requirenents of this Order to appropriate progran organizations \'1ith a copy to PE-l and DP-12 for revie\! and coment. Thereafter, the status of compliance shall be reported in the annual \taste r.lanager.lent plans (Attachnent 1). b. Chapters I through V address specific requirer.1ents and guidance for r.lanaging radioactive Hastes. 9. CLEARANCE UNDER THE PAPERWORK REDUCTION ACT OF 1~80. This directive has been deternined to contain infornation collections cOr.1ing under the provisions of 5 CFR 1320, IIControlling Paper\tork Burdens on the Public. 1I The Office of Manager.lent and Budget (OMB) has issued a clearance to the Departr.1ent (OMB No. 1901-0261) \thich covers these infomation collections through 3-31-04. Action is unden'lay \lithin the Departr.Jent to obtain subsequent OMB clearances, as mandated by 5 CFR 1320. Further infomation about this clearance action can be obtained fror.1 the prograr.1 office. BY ORDER OF THE SECRETARY OF ENERGY: WILLIAM S. HEFFELFINGER Director of Administration o DOE 5820.2 Attachment 1 2-6-84 Page 1 WASTE MANAGEMENT PLAN 1. PURPOSE. To provide guidance on the development of a radioactive waste management plan for each site as required by page 9, paragraph 7i(2).

2. DISCUSSION. Existing conditions at the various facilities shall require different types and degrees of effort to meet the operating criteria of this Order. Accordingly, the plans need not be identical in degree of detail but must be unclassified (classified addenda are permissible). Appropriate references to supplement or SUbstantiate the information or conclusions stated in the plan should be provided. A suggested outline of a waste management plan is given in paragraph 3, below. 3. FORMAT FOR THE SITE WASTE MANAGEMENT PLANS. a. Program Administration. (1) Site (2) Office Responsible (3) Contractors (4) Lead Responsibility for Site Plans (5) Source of Funds for Waste Management (6) Status of Compliance with DOE 5820 Requirements b. Description of Waste Generating Processes. (1) Waste Process Flowcharts (2) Radiological and Chemical Characteristics of Waste c. Description of Waste Management Facilities (1) Identification and Location of Facilities (2) Description of Waste Treatment Facilities (3) Description of Waste Storage and Disposal Sites (4) Description of Surplus Facilities (5) Description of Effluent Control Systems (6) Site Administration Limits on Effluents d. Radioactive Waste Disposed of or Stored, (1) High-Level Waste from Chemical Processing Operations (2) TRU waste (a) Certified (b) Uncertified (3) Low-Level Waste (4) Waste Contaminated with Naturally Occurring Radionuc1ides (5) Other Radioactive Materials Attachment 1 DOE 5820.2 Page 2 2-6-84 e. Schedules and Major Milestones for Waste Management Activities. (1) (2) (3) (4) High-Level Waste TRU Waste Low-Level Waste Other Waste (liquids, gases) f. Quality Assurance Implementation Plans. (per DOE 5l00.6A) g. Environmental Monitoring Programs. (Radioactive and Nonradioactive) h. Radioactive Waste Documentation Systems. (1) (2) (3) (4) (5) High-Level Waste TRU Waste Low-Level Waste Waste Containing Only Naturally Occurring Radioactivity Other Waste o Q DOE 5820. 2 2-6-84 TABLE OF CONTENTS CHAPTER I - MANAGEMENT OF HIGH-LEVEL WASTE 1. Overview ••••• 2. Policy •••••• 3. Requirements ••.•.••• a. Interim Storage b. Treatment c. Disposal ••••• CHAPTER II - MANAGEMENT OF TRU WASTE 1. Overview ••••••••• 2. Pol icy •••••••••• 3. Requirements •••••••• a. Waste Classification b. Waste Certification c. Storage and Disposal d. Other RequireQents • CHAPTER III - MANAGEMENT OF LOW-LEVEL 1- Overview . . · · · · 2. Pol icy •• . · · 3. Requirements · · · · · · · a. Waste Disposal · · · . b. Waste Acceptance · · · · c. Site Selection .· · · · · · d. Site Design · · · e. Site Operations · · · · · f. Site Closure/Post Closure · · . . · . . . . . . . . . . . . ., . . . . . . . . i Page • 1-1 • • 1-1 • 1-1 1-1 1-2 1-2 • I 1-1 · . . . . . . . • II-l • II-1 · I 1-1 • II-2 • 11-2 II -3 WASTE I II-l·· · · · . . · . · II 1-1 · I II-l · III-1 · .· · . · III-l. · · · · · · . · · · III-2 · . . · · . · III-2 · · . · III-3 · · · · · · 111-4 CHAPTER IV - MANAGEMENT OF WASTES CONTAMINATED WITH NATURALLY OCCURRING RAoIONUCLIOES 1. Overview •• IV-l 2. Policy ••• · . I V-1 3. Requirements • • • • IV-1 CHAPTER V - DECONTAMINATION AND DECOMMISSIONING OF SURPLUS FACILITIES 1. Overview • V-l 2. Po1; cy •.• . • • • . • . • . . . . • • . • • • • • . • . • • . V-l ii DOE 5820. 2 2-6-84

3. Requirements · . . • . · V-l. . . . . · · · · · · · · · · a. General . . . . . · · • • . • V-l· •· · • · · b. Preproject Activities • • · • · • · . • • · • · • . V-2· c. Project Activities • V-3· •· · · · • · · · d. Transfer of Facilities . . • • . V-3· · • · · · • · · J J o o DOE 5820.2 2-6-84 I-l CHAPTER I MANAGEMENT OF HIGH-LEVEL RADIOACTIVE WASTE 1. OVERVIEW. This Chapter establishes policies and guidelines for managing the Department1s high-level waste (HLW) and any other materials which, because of their hazardous nature (health risk, longevity of hazard, and thermal activity), are determined by Heads of Field Organizations to require similar handling. 2. POLICY. All HLW generated by DOE operations shall be safely stored, treated, and disposed of in a geologic repository or at a DOE-owned site according to requirements set forth in this Order. To the extent practical, waste byproducts shall be recovered and utilized or stored. Operations other than disposal involving HLW shall comply with applicable Environmental Protection Agency (EPA) standards and, to the extent practical, with comparable Nuclear Regulatory Commission (NRC) regulations. Disposal of HLW ,.,il1 comply with applicable laws and regulations. 3. REQUIREMENTS. a. Interim Storage. CI (1) HLW shall be stored in interim engineered tank systems that, together with intertank transfer systems are designed to meet applicable engineering standards. (2) Stored HLW should be contained so as to be retrievable for removal and transfer elsewhere. The physical and chemical forms of the waste and the method of storage shall be predicated on safety, cost­ effectiveness, minimization of environmental releases and health concerns, and on maintaining options for beneficial use and disposal where practical. (3) Monitoring and leak detection systems shall be incorporated in the engineered systems to provide rapid identification of failed containment, and routine surveillance and inspection of the engineered systems shall be performed. . (4) The volume, radioactive content, and chemical and physical characteristics of HLW in storage shall be documented and updated at least annually in the Waste Management Plan (Attachment 1). This data shall be supplied as necessary to the Integrated Data Base program (see page 2, paragraph 4p). (5) For emergencies, spare capacity with adequate heat dissipation capabi 1ity for each tank farr.l shall be mai ntai ned to receive the ! I I I I I I I i f I largest volume of liquid contained in anyone tank. Adequate sparee transfer pipelines shall also be maintained. Interconnected tank 1-2 DOE 5820.2 2-6-84 farns with adequate \'iaste transfer capabilities and spare capacity may be considered requirer.Jent. as a single tank farm for purposes of this (6) All ne\-I HLW handling, transfer, and storage facilities (e.g., tanks, bins, pipelines, and capsules) shall be doubly contained. Existing singly contained syster.Js for handling, transfer, and storage of HLW shall be replaced with doubly contained systems as practical. b. Treatment. (1) Development and ir.Jp1ementation of prograr.Js to safely and econor.Jica11y separate and recover valuable waste byproducts and safely store them or r.Jake ther.J available for beneficial use shall be encouraged, as practical. (2) As soon as practical, prograr.Js shall be developed and ir.Jp1er.Jented to reduce the volur.Je and mobility of HLW in interim storage so that it \/i11 meet applicable disposal requirer.Jents.

c. Disposal. New and readily retrievable existing HLW shall be processed for disposal in a geologic repository according to tile requirements of the Nuclear Waste Policy Act of 1982 (Public Law 97-425). Other waste \li11 be stabilized in place if, after the requisite environmental docur.Jentation, the stabilization in place meets applicable EPA standards. Analytic predictions of disposal syster.l perfornance shall be prepared in accordance with applicable EPA standards and incorporated in the NEPA process (see page 1, paragraph 4a). (1) Any radioactive waste disposed prior to shall be periodically monitored insitu. imp1er.Jentation of this Order Program organizations, in consultation with DP-12 and PE-1, shall reevaluate the safety of such Haste to deterr.Ji ne the need for correcti ve measures as necessary. (2) Heads of Field Organizations shall assure that disposal of HLW from their operations provides adequate protection for the public and the environr.Jent fror.l the potential hazards of nonradioactive constituents per the requirer.Jents of DOE 5480.2, and r.Jay impose additional requirer.Jents deer.Jed necessary to achieve such protection. (3) HLW shall be placed in approved \'/aste containers that meet trans­ portation and disposal site acceptance criteria prior to shipr.Jent offsite. o Q DOE 5820.2 11-1 2-6-84 CHAPTER II MANAGEMENT OF TRU WASTE 1. OVERVIEW. This Chapter establishes policies and guidelines for managing the Depar~ent's TRU waste. 2. POLICY. TRU waste shall be certified as practical, and stored in preparation for disposal at the WIPP, or by exception at other sites as appropriate. TRU waste impractical to certify for acceptance at the WIPP shall be evaluated for alternate disposal. Operations involving TRU waste shall comply with applicable EPA standards. 3. REQUIREMENTS. a. Waste Classification. (1) Any material that is known or suspected to be contaminated with transuranium radionuc1ides shall be evaluated and determined to be recoverable scrap, TRU waste, LLW, or waste below threshold quantities as soon as practical in the generating process to avoid commingling the various material streams. (2) Materials to be managed as TRU waste are, with the exception of HLW, those that meet the requirements of the definition (see page 5, paragraph 6aa) or are determined on a case-by-case basis to have a comparable long-term health hazard by Heads of Field Organizations. (3) The concentration limit for TRU waste (100 nCi/g) shall apply to any single waste package. In determining whether the concentration limit for TRU waste is exceeded, corrections shall be made for radioactive decay during institutional control periods (in the absence of other formal guidance, assume 100 years from the date of waste package certification) and the ingrowth of transuranium daughter products. For isotopes with other decay modes or alpha half-lives less than 20 years, the radioactivity concentration at the time of maximum activity for the radionuclide of concern must correspond, by calcula­ tion, to the concentration limit for TRU waste. For example, 24lpu is a beta emitter which decays with a 14.37 year half-life to 241Am, an alpha emitter with alpha half-life of 438 years. The peak buildup of 241Am is 2.9 percent of the initial 24lpu activity in the waste. By dividing the 100 nCi/g maximum alpha activity by 0.029, a concentration limit of 3400 nCi/g (beta) is obtained for waste contaminated with only 241pu.

(4) Radioactive waste with radioactivity concentrations above threshold quantities but below the limit for TRU waste shall be considered LLW and disposed of according to the requirements of Chapter III. 11-2 DOE 5820.2 2-6-84 b. Waste Certification. (1) Each site that generates TRU waste shall prepare. docu~ent, and implement a certification program to demonstrate that the waste meets disposal site acceptance criteria. I~plementation costs for all TRU waste certification operations. except those in paragraph 3b(2) of this Chapter. shall be the responsibility of the program generating the waste. (2) TRU waste stored prior to issuance of this Order shall be certified prior to disposal. Stored waste that cannot be certified without treatment shall be treated, as practical. using safe cost-effective techniques to meet disposal site acceptance criteria or otherwise disposed of (see paragraph 3c(3) of this Chapter). Costs for certifying stored TRU ~/aste shall be the responsibility of the storage site operator and DP-12 or other appropriate progra~ organi zati ons. (3) Administrative controls shall be directed to\'Iard reducing or completely eli~inating the generation of TRU waste that cannot be certified in a practical ~anner. In unusual circumstances, s~all amounts of TRU \laste may be impractical to certify, and acceptance of this ~aterial at a storage or disposal site may be approved on a case-by-case basis by a controlled review and approval process under the direction of the responsible field organization. J c. Storage and Disposal. (1) Certified waste shall be shipped to disposal as soon as practical. Certified waste that cannot be disposed of im~ediately shall be stored in a manner that is unlikely to alter its certification determi nati on. (2) TRU waste that is classified for security reasons ~ust be treated to remove or destroy the characteristic(s) requiring classification prior to disposal at an unclassified site. (3) TRU waste that cannot be certified by practical techniques shall be stored or disposed of by greater confine~ent at the expense of the generating program. (4) TRU \taste that has been buried in shallo\l land burial sites or emplaced on soil colu~ns prior to issuance of this Order shall be periodically monitored in place to assess both radioactive and nonradioactive hazards. Program offices in consultation with DP-12 and PE-l shall reevaluate the safety of such \laste to determine the need for corrective measures, as necessary. (5) Heads of Field Organizations shall assure that disposal under this Order provides adequate protection for the public and the environ~ent fro~ potential hazards of nonradioactive constituents as required by DOE 5480.2, and ~ay i~pose additional requirements dee~ed necessary to achieve such protection. o Q DOE 5820. 2 11-3 (and 11-4) 2-6-84 (6) The Waste Isolation Pilot Plant is being developed as a facility for conducting research and development to demonstrate safe disposal of radioactive waste from defense activities and programs of the United States exempted from regulation by the Nuclear Regulatory Commission. d. Other Requirements. (1) Technical and administrative controls shall be directed toward reducing the gross volume of TRU waste generated and the amount of radioactivity in such waste. Reduction shall be based on the implementation of practical techniques, such as process optimization, materials substitution, assay of suspect waste and new technology development. Volume reduction techniques (e.g., compaction, incineration, and decontamination processes) shall be implemented wherever cost-effective and practical.

(2) TRU waste shall be placed in approved waste containers that meet transportation and disposal site acceptance criteria, as appropriate, prior to shipment offsite for storage or disposal. (3) A documentation system shall be developed and implemented that identifies TRU waste storage and disposal sites, waste quantities, ~.....,. and waste characteristics and provides data as necessary to the ~ Integrated Data Base program (see page 2, paragraph 4p). The data collected by this system shall be included in the annual Waste Management Plans (Attachment 1) and site development plans required by DOE 4320.1A. c o o DOE 5820.2 2-6-84 II 1-1 CHAPTER III MANAGEMENT OF LOW-LEVEL WASTE 1. OVERVIEW. This Chapter establishes policies and guidelines for managing the Department's lou-level waste (LLW). 2. POLICY. LLW generated by DOE operations shall be disposed of, where practical, by shallow land burial or greater confinement disposal. Site­ specific requirements for waste acceptance and disposal, site selection, site design, site operation, and site closure/post closure shall be developed and implemented by field organizations according to the guidance set forth in this Chapter. 3. REQUIREMENTS. a. Waste Disposal. (1) Consistent with approved waste acceptance criteria, solid LLW shall be disposed of at DOE shallow land burial or greater confinement disposal sites. (2) Disposal operations involving discharge of liquid LLW directly to the environment or on natural soil columns shall be replaced by other techniques such as solidification prior to disposal or in-place immobilization, unless specifically approved by Heads of Field Organizations in consultation with DP-12 and PE-l. b. Waste Acceptance. Waste form acceptance criteria that assure that the objective of this Order is met for shallou land burial and, if necessary greater confinement disposal of LLW, shall be developed for each disposal site. General guidance is provided below for use by field organizations in developing their site-speCific waste acceptance criteria. Waste acceptance criteria should address, as appropriate, the following for both shallow land burial and greater confinement disposal: (1) Allowable quantities and/or concentrations of radioactivity, including threshold quantities for radioactive waste; (2) Criticality safety requirements (Haste forr.Js and geometries); (3) Radiative or thermal energy output for waste; (4) Restrictions on the generation of ha~fu1 gases, vapors, or liquids in waste; (5) Restrictions for radioactive waste having hazardous chemical properties, such as toxic, pyrophoric, ignitable, corrosive, or explosive material, which are covered by reference in DOE 5480.2; 1II-2 DOE 5820. 2 2-6-84 (6) Mechanical stability requirements for \laste packages and any special v/aste package requi rements for greater confi nement di sposal ; (7) Restrictions for chelating and complexing agents or other substances with the potential to mobilize harmful contaminants; (8) Physical properties of \/aste, including restrictions on respirable substances and quantities of free liquids; and (9) Other items \/hich are deemed necessary by the field organizations. c. Disposal Site Selection. Siting criteria shall be developed for establishing any new disposal sites for LLW. Such criteria shall apply to areas not contiguous with existing disposal sites designated prior to approval of this Order. General guidance is provided below for use by

field organizations in developing their site-specific selection criteria. Site selection criteria should address, as appropriate, the follo\ling: (1) Size, including disposal and administrative areas, and buffer zones; (2) Hydrogeologic characteristics which permit disposal cOI;lpletely above or completely below the transition zone (the zone between the unsaturated and saturated zones) and reliable prediction and control of radionuclide migration; J (3) Potential impacts of natural hazards such as floods, erosion, tornadoes, earthquakes, and volcanos on site performance; and (4) Impacts on current and projected population distributions and local families or businesses; land use, resource development plans and nearby public facilities (i.e., parks, schools, and streets); accessibility to transportation routes, and utilities; and the location of waste generators. d. Disposal Site Desi~n. Design criteria shall be established prior to selection of new dlsposal sites. These design criteria slla11 be based on analyses of environmental and hydrogeological data, assure that the objective of this Order can be met, and be based on assessments of projected waste volumes, \'/aste characteristics, and site performance. Additional guidance is provided belo\l for use by field organizations in developing their design criteria. Design criteria should address, as appropri ate, the fo110\'; ng : (1) Measures for reducing ''lind and \later erosion and other effects of surface water runoff, efficient land use, enhancement of the natural physical characteristics of the area, long-term isolation of the "aste, and minimizing the need for active maintenance or remedial action; (2) Environmental monitoring, fire suppression, utility and security systems; disposal and buffer zone areas; administrative, J o o DOE 5820.2 II 1-3 2-6-84 decontamination and maintenance facilities; access to road and rail systems; and formal emergency plans; (3) Waste handling and treatment facility(ies) located and designed for ease of waste handling and minimizing the potential for human exposure and contamination spread; (4) A grid system for locating all disposal excavations on a site map which is referenced to U.S. Geological Surveyor National Geodetic Survey benchmarks; and (5) Disposal excavations designed and constructed consistent with site hydrology, geology, and waste characteristics, and having excavation covers which provide for effective isolation of the .'1aste. e. Disposal Site Operations. Field organizations shall develop and implement operating procedures for new and eXisting LLW disposal sites that protect the environment and the health and safety of the public and site personnel, assure the security of the site, encourage good housekeeping practices, minimize the need for long-term control, and meet the require­ ments of the closure/post-closure plan. Disposal sites shall provide data on waste quantities and characteristics to the Integrated Data Base program (see page 2, paragraph 4p) and include it in the annual Waste Management Plans (Attachment 1) and site development plans required by DOE 4320.1A. Additional guidance is provided below for use by field organizations in developing operating procedures for their sites. Operating procedures should address, as appropriate, the follO\/ing: (1) Training for operating personnel in radiological health and safety and in the use of the equipment and facilities for which they are responsible;

(2) Techniques and procedures for \/aste volume reduction to the extent they are consistent with health, safety, and environmental require­ ments and economically attractive to implement; (3) Emergency response plans that identify persons to contact, response equipment, and testing procedures for both radiological and nonradiological emergency conditions; (4) A documentation system that identifies disposal excavations \/ith reference to permanent surface markers, records the characteristics and location of bulk waste quantities or waste shipments, and maintains these records in a permanent archive compatible \/ith the Integrated Data Base program; (5) A contingency plan for handling waste shipments that fail to meet waste acceptance criteria; (6) Personnel, equipment, and facilities for first aid treatment; (7) Availability, maintenance, and decontamination of operating equipment; 111-4 DOE 5820.2 2-6-84 (8) An environ~enta1 monitoring progra~ having docu~ented procedures and access to sa~p1ing and analytical equipment; (9) Procedures to ~ini~ize interactions a~ong the contents of uaste packages that could jeopardize attain~ent of the objectiv~ of this Order; (10) Access control to the \'1aste disposal site; and (11) Unusual occurrence reporting per DOE 5484.2 and quality assurance and control per DOE 5700.6A. f. Disposal Site Closure/Post-Closure. Field organizations shall develop a site-specific co~prehensive closure plan prior to initiation of operations at new or closure of existing LLW disposal sites. The plan shall be revie\'1ed and, if necessary, a~ended prior to initiation of closure activities to assure that the objective of this Order can be ~et. LLW disposal sites closed prior to imple~entation of this Order shall be periodically ~onitored to assess both radioactive and nonradioactive hazards, and program offices, in consultation \lith DP-12 and PE-l, shall reevaluate the safety of such sites to detemine the need for corrective measures, as necessary. Guidance is provided below for use by field organizations in developing their site-specific plans. The plans should address, as appropriate, the following: (1) Stabilization of the disposal site for post-closure care including filling and capping of disposal excavations, as specified in design require~ents, and re~oval of unneeded equip~ent and facilities; (2) Residual radioactivity levels for surface soils that co~ply \lith site threshol d quanti ty requi rer.lents; (3) A security syste~ to prevent unauthorized entry or removal of equip~ent or ~aterial during closure and a passive security syster,l for the post-closure period; (4) Maintenance of e~ergency response plans, facilities, and equip~ent until closure is co~plete; (5) Permanent identification ~arkers for locating disposal excavations and monitoring \lells \'/hen closure is complete; (6) Periodic surveillance and maintenance progra~s until closure is complete and modification of those progra~s, as necessary, to measure performance and assess the need for corrective ~easures follo\ling closure; and (7) Corrective measures to be applied to eXisting disposal sites if conditions occur that could jeopardize attainment of the objective of this Order. o o DOE 5820.2 IV-l (and IV-2) 2-6-84 CHAPTER IV MANAGEMENT OF WASTES CONTAMINATED WITH NATURALLY OCCURRING RADIONUCLIDES

1. OVERVIEW. This Chapter establishes policies and guidelines for managing DOE waste that contains only naturally occurring radionuclides, including uranium or thorium isotopes or their decay products and byproduct material as defined by this Order. 2. POLICY. Storage or stabilization in place shall be considered the primary technique for managing DOE waste containing only byproduct material. DOE waste containing only uranium and/or thorium isotopes shall be managed as LLW and if enriched uranium is involved, in compliance with the requirements of DOE 5632.2. Disposal shall be according to the requirements of Chapter III of this Order if practical, or applicable EPA standards. 3. REQUIREMENTS. a. With the approval of the appropriate field organization, DOE waste contaminated with naturally occurring radionuclides, may be disposed of at existing DOE LLW disposal sites. b. With the approval of the appropriate program organization, DOE waste contaminated with naturally occurring radionuclides may be disposed of at new, specially designated disposal sites that are selected, designed, operated, and closed according to Chapter III requirements. c. With the approval of NE-l, other involved Federal agenCies, States and Indian tribes, waste contaminated \/ith naturally occurring radionuclides may be disposed of at tailings disposal sites established under the Uranium Mill Tailings Radiation Control Act of 1978 (Public Law 95-604). d. Byproduct material that is owned or controlled by the Department and cannot be disposed of at eXisting DOE disposal sites shall be disposed of according to the intent of the EPA standard 40 CFR Part 192, Subpart A, promulgated in 1-83 pursuant to the Uranium Mill Tailings Radiation Control Act of 1978. e. Data on waste location, quantities, and characteristics shall be provided to the Integrated Data Base program (see page 2, paragraph 4p). J J J o o DOE 5820. 2 2-6-84 V-l CHAPTER V DECONTAMINATION AND DECOMMISSIONING OF SURPLUS FACILITIES 1. OVERVIEW. This Chapter establishes policies and guidelines for the management, decontamination, and decommissioning of surplus facilities under DOE ownership or control. 2. POLICY. Surplus facilities for which DOE is responsible shall be Qanaged in a safe, cost-effective manner to assure that exposure to radiation and hazardous chemicals complies with DOE standards. Facilities, equipment, and valuable materials shall be recovered and reused when practical. 3. REQUIREMENTS. Progra~ organizations shall develop and document specific requirements for their decommissioning activities and shall manage their surplus facilities as follows: a. General. (1) Facilities in which radioactive or other hazardous ~aterials (DOE 5480.2) are utilized shall be designed to limit dispersion of these materials and to simplify decontamination and decommissioning or reuse. To the extent feasible, features and procedures that facilitate decontamination during operation and ultimate decontamination and decommissioning shall be identified during the planning and design phase based upon a proposed decommissioning method or conversion to other use. Such features and procedures sha11 i ncl ude: (a) Walls, ceilings, and floors having suitable washable or strippable paints or coverings; (b) Caulking (or otlJer\/ise finishing off) all cracks, crevices and joints to prevent contamination spread to inaccessible areas; (c) Modular, moveable enclosures for actual work with contaQinating materials;

(d) Modular radiation shielding, in lieu of or in addition to monolithic shielding walls; (e) Separate contamination barriers within shielded areas to prevent or reduce shielding contamination; (f) Air exhaust filters located near individual radioactive material (or other contaminant) enclosures to reduce contaminated exhaust ductwork; V-2 DOE 5820. 2 2-6-84 (g) Architectural/structural designs to ease dis~antle~ent and re~oval of contaminated equipment from the facility (e.g., removal of gloveboxes or dis~antle~ent and re~oval of air filtration equipment and ductwork); and (h) Localized liquid transfer systems to reduce buried contaminated piping, equipment for batch solidification to reduce liquid waste volu~esJ and special design/construction methods to assure integrity of joints in transfer piping (particularly buried piping). (2) Headquarters or field organizations issuing neH contracts, grants and cooperative agreements, or modifications to those in effect involving nuclear work at non-DOE o\lned or controlled facilities shall address DOE contractual responsibility, if any, for decommissioning in the contractual agree~ent. (3) Available operational records for all nuclear facilities (e.g., facil ity desi gn dra\"i ngs and modifi cati ons, characteri zational data on conta~ination levels, prior deconta~ination and deco~issioning activities, and incident reports required by DOE Orders) shall be ~aintained by the cognizant field organization for use in preparing decommissioning plans (see page V-3, paragraph 3c(1)). (4) The services of the surplus facilities progra~ i~ple~ented under DP-l \ and NE-l shall be available on a rei~bursable basis for voluntary use ~ by other progra~ organizations in conducting deco~~issioning acti vi ti es. b. Preproject Activities. (l) Field organizations, in consultation \lith appropriate Headquartel"s program organizations, shall identify surplus facilities under their jurisdiction, docu~ent the potential for reuse and recovery of materials and equipment, and develop schedules for decommissioning them. Project priorities shall be based on public health and safety impacts and assessed per the guidance of RLO/SFM-82-7 (see page 3, paragraph 4s). Contractual and legal requirements, econo~ic i~pacts of immediate vs. delayed decommissioning, future site plans, cost­ effective program ~anage~ent and other factors shall be considered in project imple~entation plans. (2) Surveillance and ~aintenance shall be provided for all surplus facilities prior to deconta~ination or deco~issioning to assure adequate contain~ent of contamination, provide physical safety and security, and reduce potential public and environmental hazards. (3) Radiological criteria for decontamination of surplus facilities shall be developed, as needed, based on accepted radiation protection standards (DOE 5480.1A) and consideration of natural background , radiation levels. ~ o Q DOE 5820. 2 V-3 2-6-84 c. Project Activities. (1) A decommissioning project plan shall be developed by the responsible field organization for each decommissioning project. The plan shall include, as appropriate, the following iteQs: (a) Physical, radiological, and chemical data to support subsequent planning efforts, including a complete characterization of the facility or references to available documents containing such data; (b) A summary of an evaluation of decommissioning alternatives for the facility and a recommendation for a preferred alternative;

{c} Information on factors which could influence the decommissioning alternative selection process such as safety concerns, potential future use, long-range site plans required by DOE 4320.1A, facility condition, health, environment and safety risks, schedules, and costs; (d) Plans for compliance with the applicable provisions of the National Environmental Policy Act {see page 1, paragraph 4a}; (e) Radiological criteria to be used for the project which meet the objectives of this Order; and (f) Projections of radioactive waste generated by decommissioning. (2) Following approval of the decommissioning plan, the decommissioning project shall be conducted according to the requirements of the plan. Significant deviations shall be approved by the responsible field organization. (3) All waste generated by the project shall be managed according to the requirements of this Order or DOE 5480.2, as appropriate. (4) Information on waste quantities and characteristics shall be provided to the Integrated Data Base program (see page 2, paragraph 4p); and (5) Following completion of the project, a final report that includes a facility description and final radiation survey shall be prepared and forwarded to the appropriate Headquarters program office. d. Transfer of Facilities. (1) Responsibility for individual surplus facilities may be transferred to other DOE program organizations, including in certain instances the NE Surplus Facilities Management Program or the DP Defense 0&0 Program, by mutual agreement of the program organizations involved. V-4 DOE 5820.2 2-6-84 The acceptance procedures of RLO/SFM-B3-l2 (see page 2, paragraph 40) shall be followed. The program organization to which the facility is transferred shall accept full responsibility for surveillance, maintenance, and decommissioning of the surplus facility according to the requirements of this Order. (2) DOE surplus facilities may be released to the public according to the requireQents of DOE 4300.1A, if the responsible prograQ organization in consultation with PE-l certifies that they meet applicable release criteria for residual radioactivity; (3) When they do not meet applicable release criteria for residual radioactivity, DOE surplus facilities may be reused for prograQ activities that mayor may not involve radioactivity provided that adequate safety controls pursuant to DOE 54BO.1A are maintained; and (4) Decommissioned facilities shall be identified by notations in the legal land records of the local government entity before they are released from DOE ownership. Permanent summary records of the site status following decommissioning shall be maintained by the responsible field and program organizations. J