DOE O 5480.1 Chg 5 Transmittal Memo, Environmental Protection, Safety, and Health Protection Program for DOE Operations

u.s. Department of I:nergy Washington, D.C. PAGE CHANGE lODE 5480.1 Chg 5 J 8-13-81 SUBJECT: ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH PROTECTION PROGRAM FOR DOE OPERATIONS 1. PURPOSE. To transmit revised chapters to the subject Order. 2. EXPLANATION OF CHANGE. The following chapters, revised by the Acting Under Secretary's Task Force, supersede previously published chapters a sin d i c ate d : a. Chapter I "Envi ronmenta 1 Protection, Safety, and Heal th Protecti on Standards." b. Chapter V, "Safety of Nuclear Facil ities", which now includes former Chapter IV, also superseded. c. Chapter VI, "Safety of Department of Energy Owned Reactors." 3. FILING INSTRUCTIONS. a. Remove Page Dated Insert Page Dated -- I-I thru 1-18 5-22-81 I-I thru 1-18 and Attachment I-I and Attachment I-I 8-13-81 IV-1 thru IV-16 12-18-80 V-I thru V-6 12 18-80 V-I thru 1-26 8-13-81 VI-1 thru VI-18 12-18-80 VI-1 thru VI-23 8-13-81 and Attachment VI-1 and Attachment VI-1 b. After filing the attached pages, this transmittal may be discarded. DISTRIBUTION: All Departmental Elements Federal Energy Regulatory Commission William S. Heffelfinger Assistant Secretary Management and Administration INITIATED BY: . Assistant Secretary, Envionmental Protection, Safety, and Emergency Preparedness i9k Highlight DOE 54BO.1A 8-13-B1 CHAPTER I ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH PROTECTION STANDARDS 1-1 1. PURPOSE. This chapter sets forth the environmental protection, safety, and health-protection standards applicable to all operations of the Department of Energy, hereafter referred to as the Department. 2. GENERAL REQUIREMENTS. a. Provisions of this chapter shall be followed during facility design, construction, operation, modification, and decommissioning. EXisting facilities need not be changed arbitrarily to comply with the specified standards except as required by law. As part of the normal facility design effort for each new facility the applicable codes, standards, and guides to be used in the design and operation are to be identified and documented. b. This chapter covers the prescribed standards to be used by the Department and its contractors. In addition, DOE and its contractors shall comply with all legally applicable Federal and State standards. Where a Depart­ ment contractor is also a Nuclear Regulatory Commission licensee, the contract relationship will not exempt the contractor from compliance with Nuclear Regulatory Commission regulations and the terms of the license. Where Department of Energy contractors are tenants on a military instal­ lation and a Host-Tenant Agreement has been executed, the standards established by the host shall be observed unless the Department prescribed standards provide for greater protection, in which case Department standards shall be observed. Facilities covered by this chapter include those owned, leased or otherwise controlled by the Department or leased by contractors for use in work, and include those of either a permanent or temporary nature (e.g., trailers, rented spaces, field sites). c. In addition to the prescribed and recommended standards set forth by this chapter, the user should also consult the other chapters of this Order. The sources for the standards and a glossary of abbreviations are contained in Attachment 1. d. If there are conflicts between prescribed standards in this chapter, or between this chapter and other chapters of this Order, the standards providing the greater protection shall govern.

e. Those DOE-owned reactor plants which are prototype reactor plants for design and development of Naval reactor plants, and which are concom­ mitantly used for training of operators for Naval nuclear propulsion plants, have certain unique requirements because of their military application. All of these plants and supporting laboratory facilities are under the cognizance of the Deputy Assistant Secretary for Naval J-2 DOE 54·S0 . 1A 8-13-81 Reactors who jointly serves as the Director of the Naval Nuclear Program. Accordingly, the Deputy Assistant Secretary for Naval Reactors is responsible for assuring that adequate standards are applied for emergency preparedness, environmental protection, nuclear safety, and health pro­ tection for Naval reactor prototype plants and supporting laboratory facil iti es owned by DOE." 3. RESPONSIBILITIES AND AUTHORITIES. a. Program Secretarial Officers shall: (1) Assure compliance with the standards of this chapter on a site­ wide basis by organizations under their jurisdiction by review and approval of the summary type implementation plans for DOE Orders submitted by field organizations. (2) Prescribe, as appropriate, additional or more stringent standards for individual facilities after appropriate consultation with field organization management and other affected Program Secretarial Offi ces. b. Heads of Field Organizations and the Assistant Secretary, Management and Administration shall: (1) Apply the prescribed standards contained herein. (2) Assure that the level of performance of health and safety are maintained consistent with the intent of these standards, for those activities under their direction. (3) Prescribe, as appropriate, additional or more stringent standards, based on the determination that such standards are essential to safety and proper performance of their function. (4) Grant exemptions as set forth in paragraph 4, where such action will best serve the interest of DOE, providing that the safety of employees, the public, and Government and private property can be maintained. (5) Identify needs to Deputy Assistant Secretary for Environmental Safety and Health (EP-30) for new standards to address environment, safety, and health concerns. c. Assistant Secretary, Environmental Protection, Safety, and Emergency Preparedness (EP-1) shall: (1) Review nationally recognized health and safety requirements, guides, codes, and standards and prescribe those applicable to DOE activities, DOE 5480 . 1 A 8-1 3-81 1-3 fonowing appropr-iate review and comment by affected Departmental elements. (2) Determi ne the need for and develop or promote the development of ne'f' or revised standards appliccble to environmental safety and heaith. (3) Act as liaison with voluntary standards bodies and other Federal agencies on ES&H standards to reflect DOE needs and requirements. (4) Develop and maintain appropriate mechanisms for maintaining the standards listing comprehensive. up-to-date, and revising the standards listing, as necessary. 4. PROCEDURE FOR GRANTING EXEMPTIONS . a. Heads of Field Organizations are authorized to grant exemptions from the prescribed standards of this chapter for specific facilities or activi­ ties, except as noted in subparagraph 4b. Specific exemptions to the prescribed standards identified in this chapter, which are dependent on specific facility designs, shall be identified in the facility design documentation and safety analysis, which will be reviewed and approved in the normal process of facility design and operation and assessed as part of the Environmental, Safety, Quality Assurance, and Health Appraisal Programs.

b. Exemptions from standards established pursuant to the Federal regulations listed herein, unless allowed by the procedure identified in subparagraph 4c, are to be submitted with suitable justification to EP-1. c. Those Department contractor operations subject to DOE 5483.1, OCCUPATIONAL SAFETY AND HEALTH PROGRAM FOR GOVERNMENT-OWNED CONTRACTOR-OPERATED FACILITIES, must follow the procedures of that Order to obtain variances from the Occupational Safety and Health Administration standards listed herein. Those Department operations directly subject to the Occupational Sa fety and Heal th Admi ni stration IS regul at; ons must fo 11 ow the procedures of 29 CFR 1960, Subpart C, or 29 CFR 1905, as appropriate, to obtain relief from standards listed herein (which are also listed in 29 CFR 1910, 1915-1918. and 1926). Requests are to be forwarded to the appropriate Department of Energy official as defined in DOE 5483.1 or DOE 3790.1- 5. EMERGENCY PREPAREDNESS. The following standards, in addition to those listed in the other chapters, shall be used as applicable. a. Prescribed Standards. To be identified. b. Recommended Standards. "Immediate Evacuation Signal for Use in Industrial Installations Where Radiation Exposure May Occur," ANSI N2.3-1979 (ANSI). I-4 6. in on to se i 1 e. a. (1) 1 11 ianee 1 on (2 ) 1nes (a) r. 1 nee ) . 2 r lutant 61). 3 r i ions (b) 1 sc 1 ( 1 ). 2 011 1 ) . 3 an 4 5 1 ). 6 sc 7 8 ). 9 into I 5 (c) 1 P ry Dr; i ter ons 2 ry ons 1 ( d) 1 ). 2 ). (e) 1 on Ac vi- I! 2 3 ... 4 5 ci 6 on ci i 171) • b. (1) on stewater ( ( 2) ) . (3) c ce, 1 i on ). 1-6 DOE 5480.1A 8-13-81 (4) Sanitary Landfill Design and Operation Publication No. SW-65ts. (EPA). (5) Interim Guide of Good Practice for Incineration at Federal Facilities, Publication No. AP-46 (USPHS). (6) Incinerator Guidelines, Publication No. 2012 (USPHS). (7) Air Pollution Engineering Manual, Publication No. AP-40 (USPHS). (8) Compilation of Air Pollutant Emission Factors (EPA). 7. FIRE PROTECTION. The following standards, in addition to those listed in the other chapters, shall be used as applicable. a. Prescribed Standards. (1) National Fire Codes (NFPA). (2) Standard for Fire Protection of AEC Electronic Computer Data Processing Systems, WASH 1245-1. (Compliance with this standard satisfies the requirements for NFPA-75). (3) Product Directories of Underwriters Laboratories together with the periodic supplements (UL). (4) Factory Mutual Approval Guide (FM). (5) TP20-11 General Fire Fighting Guidance for Nuclear Weapons (this document is confidential restricted data). (6) Standard on Fire Protection for portable structures, DOE/EV-0043, August 1979. b. Recommended Standards. (1) Handbook of Fire Protection (NFPA). (2) Loss Prevention Data Sheets (FM). 8. HEALTH PROTECTION. The following standards, in addition to those listed in the other chapters, shall be used as applicable. -7 a. on. (1) Presc s. ( a) r Di I irect r X a on, (b) on I .1-1 I). ( c) on cle on r ( e) ( es Less I). r I ant (9) reet . ( I). ( h) ( 2) ( a) ( b) ) . (e) sin 1 ear (d) 1). ( e) ib on, I b. (g) r ( h) on (n (I 1 2 1 3 14, 1 (j) { k} (l) 1 2 3 4 (l) P --~------~--~ (2) Ca) (b) on inst on (10 CFR ). on (I ) . on on In on on es on 5 on 3 P.L. In on -1 ; ons DOE 5480.1A I-9 8-13-81 (c) An Administrative Guide for Federal Occupational Health Units, HEW, Public Health Service Publication No. 1325-A (March 1966), (USPHS) .

(d) Epidemiology in Occupational Disease and Injury, 00CH-290 (AMA). (e) Medical Aspects of Radiation Accidents Handbook, Eugene Saenger, M.D., Editor (GPO). c. Industrial Hygiene. (1) Prescribed Standards. (a) Current Threshold Limit Values (ACGIH). (b) Practices for Respiratory Protection, ANSI Z88.2-1980 (ANSI). (2) Recommended Standards. (a) Hygienic Guide Series (AIHA). (b) Heating and Cooling for Man in Industry (AIHA). (c) Respirator Manual, LA-6370-M (DOE). (d) Industrial Ventilation Manual (ACGIH). (e) Industrial Noise Manual (AIHA). (f) Guide for Conservation of Hearing and Noise (AAOO). (g) NIOSH Criteria Documents (NIOSH). d. Public Health and Sanitation. (1) Prescribed Standards. (a) Food. 1 Food Service Sanitation Manual, DHEW Publication No. 78-2081 (FDA). 2 The Vending of Food and Beverages, USPHS Publication No. 546 (1965). (b) Water. 1 National Interim Primary Drinking Water Regulations, Publication No. EPA-570/9-76-003 (EPA). 1-10 DOE 5480.11-\ 8 -13-81 2 Manual for Evaluating Public Drinking Water Supplies, Publication No. 1820 (EPA). 3 Manual of Individual Water Supply Systems, Publication No. 430 9/73-003 (EPA). 4 Quality Standards for Bottled Water (21 CFR 11). o Sanitary Standard for Manufactured Ice, USPHS 1183 (1964). 6 GSA Handbooks on Performance Standards for Cleaning Public Buildings (GSA). 9. OCCUPATIONAL SAFETY. The following standards, in addition to those listed in the other chapters, sh311 be used as applicable. a. General Safety. (1) Prescribed Standards. ( a) ( b) ( c) ( d) ( e) (f) ( g) ( h) ( .) \ 1 (j) Forest Sel"vice Safety Standards (USDA). Boiler and Pressure Vessel Code; Sections I-XI (ASME). Occupational Safety and Health Standards, 29 CFR 1910. Safety and Health Regulations for Construction, 29 CFR 1926. Safety and Health Regulations for Ship Repairing. 29 erR 1915. Safety and Health Regulations for Shipbu ·'l d ing~ 29 CFR 1916. Safety and Health Regulations for Shipbreaking, 29 eFR 1917. Safety and Health P.egulations fo\" Longshoring . 29 CFR 1918. Department of Defense Explosive Safety Board Standards (Ordnance Operations). Department of Navy Standards (for Naval Reactors program applications) (NAV). (2) Recommended Standards. (a) Chemical Rocket Propellant Hazards, JANNAF Propulsion Com­ mittee, Volume I - General Safety Engineering Design Criteric., NTIS-AD 889763, May 1970. Volume II - Solid Rocket Propellant Processing, Handli~g. Storage, and Transportation, NTIS-AD I-ll 1 ume III - Li id on, N.T.I.S. les are iate). ( b) ). (c) (d) t ons ( ( e) ) . (f) Ha ) . (g) 11 !"IC. $ ( h) ). (i) ) . (j) s, i k) ;c e ) ( l w~ \ Ha ses ) . , " Ace; on 5 ( I). ( n) e; b. (1) Presc ( a) , ). (b) ons nstrue on ( ). (2 ) ( a) on ;n on ( (b) r I 2 c. (1) ( a) ( b) sod on ca, i on (2) (a) (b) i Ma 1 d. (1) ( a) (b) (c) ces in ill i ons, on, 1 1). ( 2) ( a) on ( b) e vi on on 1 ns n. e. (1) p ( a) c (b) ) . I 3 (2) { a} ons, ) U.S. (b) 1 aneous ee ie st, , U. S. ( ). (e) 1 ee e on ( d) , a re ( e) r ili es, (9) a f. (l) ( a) (b) 51 fe) ). (2 ) ( a) r , a ves, 5 ( b) i ( e) ( d) on 0 on 1-14 b. .1A b) (c) (2) ( a) (b) (c) ( d) ( e) ( g) ( h) (i) (j) ( k) (1) ( n) (1) Presc ( a) (b) Bo 11 er ic ) rsl I si ssure c s. lear } (DOE). Licenses, 10 Cri a. 10 C on on 1 eal~ r ili es. d r te ann tern, search ants, es I-I. tors, I I I. I-IV. e I 15 A NE tors,

... 1. (I I). s I 6 (c) s, (2 ) ( a) • TID- 6 ). (b) ( c) ces U ( d) i (e) i • (3 urnes) • ( g) 1 i on i 1 ; es, (10 ) . (i) ic ili Li cens; t (j) L icensi ). ( k) rsl Li censes (10 ). (1) 1 ons te a (10 1 ) . ) . 11. s in on li as e. a. (1) p Av on ons ) . (2 ) on d on r 7 b. (1) Presc s. ( a) ons, s ) . ( c) ( d) ( e) sign on ) . (2) (I ) . ( b) 11 (c) } . ( d) r ice, c ). ces ( c. (l) ons r s. et • U.S. (2 ) (3 ) ) . (4) ons Ma s, 1-18 DOE 5480.1A 8-13-81 (5) Ventilation System for Small Craft, Booklet 395, U.S. Coast Guard (DOT). d. Transportation of Radioactive Material. (1) Prescribed Standards. (a) Department of Transportation Hazardous Materials Regulations (49 CFR 100-179). (b) Packaging of Radioactive Materials for Transport (10 CFR 71). (2) Recommended Standards. (a) Cask Designers Guide ORNL-NSIC-68, 1970 (DOE). (b) Structural Analysis of Shipping Casks, ORNL-TM-1312, Volumes r through X (DOE). (c) Packaging of Uranium Hexafluoride for Transport, ANSI N14.1-1971 (ANSI). e. Railroad Safety. Prescribed Standard. Federal Railroad Administration, (49 CFR 211-240). I-I Pa 1 a 2. a on 3. IH I ieni 4. ca, Inc. 5. ene sod 6. 7. I In 1 8 8. I In 9. c i neers, Inc. 10. s nt I 11. sod on, Inc. 12. a 1 3 13. ons 14. on, Inc. 15. on ca, Inc. 1 16. 17. 18. 19. on on 21. nt I-I 22. 23. on 24. 25. ce on on on on on 7 Ie on on on its 4 I ic 7 os s IRI I 35. I 41. 42. nt I 1 G. 0« 11 P.O. st nances ssachusetts ton, D. C. tute i neers, Inc« r Drive soc; on NW « Inc. ts Division ni on ons vania 191 on on 1016 i nn c D 8 45. NI .1A soc; o 46. on s on 51 on es. Inc. 53. s I 6) on ice DOE 5".80.1A 8-13-81 CHAPTER V SAFETY OF NUCLEAR FACILITIES 1. PURPOSE. This chapter establishes safety procedures and requirements for nuclear facilities to assure: a. That nuclear facilities are sited, designed, constructed, modified, operated, maintained, and decommissioned in accordance with generally uniform standards, guides, and codes which are consistent with those applied to comparable licensed nuclear facilities. b. That radioactive and fissionable materials are produced, processed, stored, transferred, or handled in such a manner that the probability of an accident is acceptably low. - V-I c. That an environmental protection, safety, and health protection program is established in accordance with the requirements stipulated in para­ graphs 6 through 11 of this chapter. d. That environmental protection, safety, and health protection matters are comprehensively addressed and receive an objective review with all identifiable risks reduced to acceptably low levels, and that management authorization of the operation is documented. e. That consideration is given to all potential criticality hazards associ­ ated with fissionable material operations outside nuclear reactors. f. The protection of Government property and essential operations from the effects of potential accidents. 2. SCOPE. This chapter applies to Headquarters and field organizations, Department of Energy contractors, and Government-owned laboratories and non­ reactor nuclear facilities. The requirements of this chapter shall be applied to the design, construction, maintenance, operation, and decommissioning of a given facility with due consideration to the degree of risk that facility presents to employees, the public, and the environment. Accelerator and nuclear reactor facilities and their operation are not included in this chapter, but are covered by other Environmental, Safety, and Health Orders, as appropriate.

3. REFERENCES. a. DOE 5480.1, Chapter XI, "Requirements for Radiation Protection." b. Code of Federal Regulations, Title 10, Part 30, "Rules of General Appli­ cability to Licensing of Byproduct Material." c. ons, e 10, rt Li cens i d. ons, e 10, • "Licensi P on es. I! e. ons, e 10, II censes. II f. e 10. I! lear \I g. " II H.K., 1 ). • h. " c ) . 1- c j. sium. k. ve. 6.8, 6.9. 1. rt ies. m. ssil e 5. 11 11- n. II II • E.D., Bierman, o. 2. 1 • ava il e as p. q. r. s. IUT u. IS .IA v. Dimensions of Contain; II 4. a. 11 b. a cant c. e. • constant g. h. v i. j. k. 1. m. n. o. p. q. A (l) (2 ) r. U rrence. ~~~~~~~~ ve t a le .2, i ch is rm a nuclear s t or E s r ves e to is s. 5. a. (1) (2) (3) (4 ) (5 ) (6) (7) sume line r nuclear (a) (b) ons to nucl ear ce ear ili sa (as ons t V-6 (9 ) (a) (b) (10 ) (11 ) (12 ) (13) (l4 ) (15 ) (16 ) b. on ons as assessments to nuclear 5(e) ld es .1A 13- on s to re ces to assure sa is to curtail ram yes ans, rements as in se is not avai assessmen DOE 5480. 1A V-7 (l) Prov; des the Secretary w"lth ani ndependent safety overvi e iV ana assessment of the operation at DOE-owned nuclear 'facilities. (2) Esta.blishes priorities for conducting siifety appraisals of programs in conjunction with program Secretarial Officers and Operations Office Managers. (3) Assures that nuclear facilities projects are consistent with Dor nuclear safety policy. (4) Overviews and appraises both the line and independent nuclear safety activities of the cognizant Secretarial Officers and the Operations Office Managers to assure that DOE nuclear projects are accomplished in consonance with a need for protecting the safety and health of DOE and DOE contractor employees, and the public. Specific emphasis will be placed on training programs to assure that they include requirements necessary to achieve the goal of well-trained operators. (5) Conducts appraisal with teams which are augmented with experts from other DOE organizations. (6) Provides nuclear safety expertise to assist other Headqua r ters and field organizations. (7) Develops and maintains generic qualification and training standards for operators. (8) Assures that responsible EP personnel are proficient in the opera­ tions personnel training area, including diverse expertise so that important areas related to nuclear safety are covered. (9) Collects new safety requirements applicable to licensed nuclear facilities and consults with the cognizant program Secretarial Officer to make a preliminary evaluation to determine their potential applicability to DOE nuclear facilities and: (a) Evaluates field office assessments and program Secretarial Office disposition of newly proposed requirements and considers the requirements for inclusion in DOE Orders, as appropriate. (b) Maintains a summary of the consideration and disposition given by the Department to each of the newly proposed requirements for nuclear facilities. NOTE: The above process for implementing newly proposed environ­ mental protection, safety, and health requirements into DOE orders, policies, or directives does not relieve the line V-8 c. (1) (2) (3 ) d. (l) (2 ) (3) (4) (5 ) ram new envi are con ons re 1 • r nuciear sibili r i 1 i ; 1 i es of a o s; on, Sa 3 es. ons 11 not create un env; on s. (6 ) (a) (b) (7) (9) contractors (a) (b) (c) (d) e i on. sa V-9 review on.

r environ- an V -~Q DO E 5~80.1A 8-13-81 (10) Assume the e?tablishment of an unusual occurrence investigation and reporti ng system in accordance with DOE 5484.1 and DOE 5484 . 2 , (11) Assist in the review and development of environmental protection, safety, and health protection codes, standards, and guides. (12) Conduct appraisals in accordance w1th DOE 5482.lA. (13) Review ne'f:ly proposed safety requ"jrements and determine appl "ica­ bil ity to specific faeil ities and submit assessments of suci"; proposed requirements to the cognizant program Secretarial Officer. (14) Identify those fac lities on his or her site(s) which are designated to be nuclear faci ities and submit to the cognizant program Secretarial Officer for approval. S. BASIC REQUIREMENTS. The environmental protection, safety. and health protec­ tion program for nuclear facilities shall include the following: a. An independent safety analysis review process which includes a formal documented system for the identification and control of risks through preparation. independent review, and approval of safety analyses. b. Administrative and procedural controls that delineate (1) responsibilities and methods for safe operation under normal and emergency conditions, and (2) a system of configuration control that requires independent safety review and approval of all changes to components, equipment, procedures and systems required for facility safety. c. A documented training program for personnel involved in operating nuclear facilities which meets the requirements specified on page V-13, paragraph 8. d. Operational Safety Requirements setting forth, in a concise manner. the approved limitations of safe operation. The requirements shall be commensurate with the potential risks involved. e. Development and implementation of quality assurance programs that fulfill the requirements of DOE 5700.6A. f. Application of environmental protection, safety, and health protection codes, standards, and guides covering siting, design, construction, modi­ fication, operation, maintenance, deactivation. decontamination, and decommissioning. Where established standards are determined to be inadequate or not available, suitable operating standards shall be DOE 5480 ,. l~; 8-13- 81 h. i . j. k. , I • ill. de""eiOped, using contractor expertise as necessary. so that a defined and agreed upon basis for conducting and assessing operations is estab­ l"lshed and used. The Safety Analysis JI" othey design documelltation shall -icientify. on a facility specific basis, the standards applied. Notification, investigation, and reporting of occurrences and the followup system to assur"e remedial action has been implemented. (See DOE 5484.1 and 5484.2). For new nuclear facilities and for significant modifications to existing nuclear facilities. review of safEty analyses design criteria, environ­ mental assessments and environmental impact statements, and other design documents to assure adequate env1ronmental protection, safety, and health protection consideration. For new nuclear facilit~es and for significant modifications to existing nuclear facilities. reviews and inspections during construction, accept­ ance of systems and preoperational phases to assure compliance with the appropri ate envi ronmental protecti on. safety. and heal th protection standards and requirements. A formal documented system for the control and trsceabil"ity of records and documentati on specified herein.

A program of nuclear criticality safety which meets the Y'equirements of paragraphs 9 and 10 of this chapter. A contractor independent safety ,eview and appraisal system which meets the requirements of paragraph 7 of this chapter. The safe storage criteria for unirradiated fissionable material meeting the requirements of paragraph 11 of this chapter. 7. CONTRACTOR INDEPENDENT OF REVIEW AND APPRAISAL SYSTEM. The field office shall require each contractor to estab1ish and maintain an internal safety rev;e';1 system for nuclear facilities which: a. Functions primarily in an advisory capacity to the line organization, reporting to a designated position or authority at a level of management sufficiently high to take any necessary corrective action. (Safety is a 1 i ne respons ib il it),; neither revi ew nor subsequent approval rel eases 1 i ne management from its respons ibn i ty for safety of peopl e and equi pment. ) b. Is clearly defined and delineated in writing (e.g., purposes, objectives, functions, authority. responsibility, composition, quorum, meeting frequency. and reporting requirements). "1-12 c. e. f. g. h. (1) P (2) P (3 ) (4 ) (5) (6 ) on scussions reviewers on i cance. } , Li i. 8. a. (7) (8 ) (9 ) Is eve (1) (2) (3 ) (4 ) (5) r ni i (a) ear to ; es. 1 assure ons. as inc; rmance V-13 , ts or ion. at lea es. a (b) Emergency actions. (c) Radiation control practices. DOE 5480 < lb. 8-13-81 (d) Location and functions of the pertinent sofety systems. (e) Configuration control procedures. (f) Procedures for making changes or alterations in the operations. (6) Verification of training shall be made by a cognizant management or supervisory official following a finding that the candidatels proficiency is sati;factory after completion of the training program and recei pt of a sat; sfactory stateiilent of the candi date IS medi cal condition and other pertinent information. Verification of training for fissionable material handlers, operators, or supervisors may not be made by hi s or her ':mmedi atE! 5upervi sor. (7) Retraining and reexamination shall be required at least annually on all procedures for handl iYig abnoY'rna 1 1";;;c1 ear fac; 1 i ty condi ti ons and emergency situCl.tions relative t.o the employee1s assigned responsibil­ ities, and at least eve~~y 2 Years on a11 other subjects in which the fissionabla materials handle r, ope~atcr. or supervisor is expected to be proficient. (a) Verification of training shall be documented by contractor management at least every 2 years. (9) The program shall be audi tab 'j e by contractor management and by the Depa r~tmei1t. (10) In addition to the above, a program shall be established for those fissionable materials handlers, operators, and supervisor candidates who process, store, transfer, or handie significant quantities of fissionable materials, which includes the following elements: (a) Fissionable materials handlers, operators, and supervisor candidates shall possess either formal training or pertinent experience or both, commensurate with the stated degree of responsibility and complexity of the prospective position. (b) The training program shall provide for evaluating the progress of each trainee periodica1ly during training. Each evaluation shall require the demonstraiton of a satisfactory knowledge of all required subjects and procedures covered in the training program. This demonstration may include written, oral, and operational examinations as appropriate to the position,

DOE 5480 ,.lA 8- 13-81 V-iS experience, and educationa 'l level of the employee. Upon completion of the program, the final evaluation of the candi­ date's proficiency shall be made by the examining official. A file record of the employee's training, including a record of the subjects covered in oral and operating tests along with the written examinations, shall be maintained. (c) Retraining for fissionable materials handlers, operators, and supervisors following extended absence from the nuclear facility shall be required. The extent of retraining will depend upon the length of absence and the type of work and operational routine in the event of changes. For absences of 3 months or less, if retraining is deemed necessary, informal retraining and oral testing may be sufficient. For absences of 3 to 12 months, selected retraining as appears necessal~, including training in the use of, and familiarization with, any new devices or changes in the process, with appropriate demonstrations of knowledge and proficiency, is required . For absences greater than 1 year, a written reexamination shall be required and where indicated by the results of that examination. retraining shall be mandatory. (d) The program shall provide for training, retraining, exami­ nation, and reexamination in the following areas to the extent that they are pertinent to the posHicn in question (supervisor training shall require an understanding in greater depth than fissionable materials handler and operator training): 1 Standard and Emergency Operating Procedures. Normal operating procedures, abnormal and emergency actions, and administrative controls and responsibilities. 2 Radiological Safety and Control. Radiation hazards, monitoring, safety practices, control procedures, and termi no logy. 3 Safety and Emergency Systems. The kind of equipment, operating characteristics and procedures, and testing requirements of safety systems. 4 Instrumentation and Control. Types of instruments and control systems, inc1uding principles of operation and consequences of malfunctions. 5 Facility Operating Characteristics. Principal features, operating parameters, and operating limits of the facility, including the auxiliary systems. V-16 DOE 5480.1A 8-13-81 6 Principles of Nuclear Facility Operation. The processes involved and technical terminology for the chemical, physical, and metallurgical reactions. (e) In the case of initial startup of a new nuclear facility or operation precluding prior on-the-job training, practical experience at similar facilities, training on simulators, training with inert materials, or other appropriate training shall be considered. (f) The supervisor training program, in addition to the above, shall include the following material to the extent that it is pertinent: 1 Design, control, and operating limitations for the facility. including instrumentation characteristics, adjustment, operation, facility console control mechanisms. and control room manipulations. 2 Procedures for making design and operating changes, including changes in operating procedures. 3 Radiation hazards which may arise during the performance of experiments other than those in critical assemblies. 4 Nuclear and radiation theory, including details of fission process, neutron multiplication, source effects, neutron poison effects, and reactor kinetics. 5 Specific operating characteristics of the facility, such as causes and effects of temperature, pressure, and reactivity changes.

6 Procedures and limitations involved in initial equipment loading, alterations in fissionable material configuration, and determination of various internal and external effects on reactivity. 7 Procedures, equipment, and facilities available for handling and disposing of radioactive materials and effluents. (g) Any waiver from the requirements set forth in subparagraph 8a shall be obtained from the field office manager. (The name of the fissionable materials handler, operator, or supervisor and the specific subject for which the waiver is requested, DOE 5480 . 1A 8-13-81 V-17 along with the justification for the waiver shall be submitted.} Waivers may be requested only in specific areas for those fissionable materials handlers, operators, and supervisors who are exceptionally well qualified by past experience and education, and who have been continuously employed in the same type position. b. Maintenance Personnel. The training requirements for maintenance person­ nel shall be determined by the class of maintenance which the personnel are to perform, the degree of supervision required, and the required knowledge of the nuclear facility. (1) All maintenance operations shall be performed by personnel who are properly trained in their respective discipline or under direct supervision of trained personnel. (2) A written policy shall be established that describes functions, assignments, and responsibilities of the maintenance organization as it relates to nuclear safety. (3) The successful completion of the training and qualification effort shall be documented. 9. NUCLEAR CRITICALITY SAFETY ELEMENTS. The following basic elements of nuclear criticality safety shall be provided in contractors' programs involving significant quantities of fissionable materials: a. b. c. Process Anal~sis. Before beginning an operation with significant quantities 0 fissionable materials, or changing an existing operation, a preoperational audit shall be made to determine that the entire process will be subcritical under both normal and abnormal operating conditions that could reasonably be expected to occur. Distinction may be made between shielded and unshielded facilities, and the criteria may be less stringent when adequate shielding assures the protection of personnel. Identification of the Parameters on which Prevention of Accidental Nuclear Criticality will Depend. The basis for establishing subcriticality shall be noted for all significant conditions at each step in the process. This may, in the case of established facilities or operations, consist of references to existing nuclear criticality safety evaluations. Written Plans and Procedures. Operations shall be governed by written plans and procedures. These plans and procedures shall be an integral part of the initial proposal for the nuclear facility, its operations, and subsequent modifications that may affect the nuclear reactivity. The plans and procedures shall include the following, where applicable: V-IS DOE 5480. 1A (; ·-1::'-81 (1) Plans For receiv ng fissio;I3.G!e material into tile faci'iity and for inspecting t e shipment en receipt, including procedures for: (a) [)e'~ermin-ing, verifying , or' (Ioting the contents of each pa.ckage, inc luding the net weight of fissionable mater ial therein. (b) The placing of materials in the receiving area and the storage ·Pd,: ·i~ i tYe (c) Handling wet or damaged packages. Plans and p~ocedures for storing fissicnable material, including:

(a) Limitati ons on total quantity of mate,,,; ai, quant'ity of each individua~ unit, container dimension~. and spacing between !1nits. (b) Description of co~tainers In which fissionab1e ma ter ials are stored. (e) Description of the storage facility. includ-ing dimension and materia.ls used in eonstr!1stion of the enclosure ~nd shelving, cubicles , cages, and other equipment within the storage area. (d) Precautions to avoid ent)~y of I'lat.er or other material int.o a storage area where moderating and reflecting effects would be un sa fe. (e) Administrative controls over the distribution of fissionable material from storage and its return to storage, including means of verify, n9' the wei ght . i sotopi c con t ent, cherni cal composition, and degree of moderaticn. (3) Plans and procedures for pr oce ssing the fissionable mater~~l. including: (a) A descriptions using appropriate sketches or drawings. ~f equipme:1t and facil ities in which the hazard of cr1t~cal it), exists, and showing dimensio ns in sufficient detail to permit evaluation of the illfoI1Tlat-io!'! mentioned in subparagraphs (c) and (f), below. (b) A statement of the chemical and physical form of fissionable material in each step of the operation, inCluding isotooic content, the nature of any material> and the resulting con­ centrations, densities s and degrees of moderation throughout the steps of the process. DOE 548G . IA 8- 13- 81 \' --1 9 (c) A statement of the maximum quantities of fiss1cnable mater i al allowed at anyone time in each step af the process. (d) Spacing of masses of fissionable material within each process area, and separation from fissionable material in adjoining 2rea:; . (e) ( .;:: \ : l ( g) (h) Methods of collecting. handling, and transporting fissionable m~terial from each process area or individua1 operat~o;l, and evalLlation of the nuclear safety of th ,=se methods. Description of procedures which are intended to prevent critica"lity resulting from accumulation of fissionable mater-;al in scrap or waste, lathe turnings, crucible slag, pickling solutions, croppings, sumps, filters. 111stalled or proposed criticality alarm system B.nd emergency p~ocedures, including alarm l~vels, fail-safe features, response time of devic2s, and frequency of evacuation drills. Pertinent documents shall show the location of all detectors, their dista.nce to possible sources of criticality, and inter­ vening shielding. The criticality alarm system shall be installed in all locations wherein the quantities of fission­ able material may exceed 700 grams of uranium 235) 520 grams of uranium 233, 450 grams of plutonium, or 450 grams of any combination of these three nuclides. (Limits for other fission­ able materials shall be as indicated in American National Standard Institute Standard ANS 8.15, "Nuclear Critical ity Control of Soecial Actinide Elements,~ when issued.) These limits may be exceeded when j~stified by consideratio~ of the physical form and isotopic distribution of the fissionable material. This justification must be based upon a documented analysis demonstrating that, -in such cases, the alarm system is not required< Special attention shall be given to all processes in which reflectors and moderators more effective than hydrogen are present and, as appropriate, the above limits reduced so that nuclear reactivity is not increased.

A monitoring system. using gamma- or neutron-sensitive radi­ ation detectors which will initiate a clearly audible alarm, distinctive in tone, if accidental criticality occurs, is required. The detectors shall be capable of detecting a criticality condition that produces an absorbed dose in free air of 20 rads of combined neutron and gamma radiation at an unshielded distance of 2 met~rs from the fissionable material within 60 seconds. Provisions shall be made to minimize false alarms. These provisions may include concurrent response of V-20 .1A (j) d. 1 a. lear c i is ac exerc; (1) s. (a) (b) (e) (2 ) , V-2 2 DOE 5480.1A 2- 13-81 (a) Neutron Absorbers. Neutron-absorbing materials, such as cadmium and boron, may be used to make equipment and processes safe, provided availabie data confirm theh' :;uitabllity and assure their presence and reliability. Care should be exer­ cised in the use of solutions of neutron absorbers because of the controls required to assure their co~tinued effectiveness. (b) Moderation Controls. For operations in which nuclear critical­ lty stl.fety depends upon control of neutron moderation, ther~e shall be assurance that the .prescri bed extent of moderati on remains unchanged or that, if it does change, the reactivity of the system remains below acceptable subcritical limits. Such assurance shall include consideration of all credible accidents involving any moderator or combination of moderators. (c) Neutron Reflection. Neutron reflection shall be considered for all systems of fissionable material. The extent of reflection shall be based upon the actual reflectors present or those to be expected during normal operations or as a result of a credible -accident. b. Doubl~ Contingency Principle. Process designs shall incorporate suffi­ cient factors of safety to require at least two unlikely. independent. and concurrent changes in process conditions before an accidental nuclear criticality is possible. c. Geometry Control. Where practicable, reliance shall be placed on equip­ ment design in which dimensions are limited, rather than on administrative controls. Full advantage may be taken of any nuclear characteristics of the process materials. Control shall be exercised to maintain all dimensions and nuclear properties on which reliance is placed. d. Nuclear Criticality Safety Limits. Limits for nuclear criticality safety shall be established on bases derived from experiments. In the absence of directly applicable experimental measurements t the limits may be derived from calculations made by a method shown to be valid by comparison with experimental data, provided allowances are made for uncertainties in the data and in the calculations. e. Margins of Safety. Safety margins used shall meet the control parameter requirements above. Further, a cumulative margin of safety shall provide allowance for experimental and computational uncertainties. Procedure violations also shall be a consideration. f. Onsite Movement and Offsite Shipment of Fissionable Materials. (l)Onsite movement includes all activities where fissionable materials are transferred from one operation to another within a facility and DO 5480 . J.l1 from location to location cn site . Fer all such movements. t he following requirements shal l be met: 11-23 (a) For the onsite movement of fissionabl~ mate r ials that dc not present a radiation hazard, the pertinent requirements set forth in this chapter shall be met.

(b) For onsite movement of fissinable materials that presents a radi ation hazard, as well as the possibil ity of an accidenta1 chain reaction. the pertinent requirements of this chapte r and Chapter XI of this Order shall be met. (c) In addition to the physical controls specified above, adminis­ trative controls, including traffic controls, shall be exercise~ as deemed necessary by Hea.ds of Field Or ganizations to minimize accident probabilities. (d) Fire protection, security, health physics, and any other emergency personnel, when deemed appropriate by Heads of Field Organizations, shall be alerted and advised of movements and routings. (2) Safety standards for the packaging of f -; ssionable mRterials for any offsite shipment are outlined in Chapter III of this Order. Further, such shipments shall meet the nuclear criticality safety requirements set forth in this chapter and the radiological safety standards outlined in Chapter XI of this Order. 11. SAFE STORAGE CRITERIA FOR UNIRRADIATED FISSIONABLE MATERIAL . These criteria are appl icable to the storage of all fonns and significant quant'lt'f'?s af unirradiated fissionable material. (a) Where these materials are in-process as part of production, analytical and development procedures, or transpo r t operations. I I r OTE;- These criteri a are not appl icabl e: (b) Where an assembly cell is used for assembly and/or storage of weapons components made with these materials. I (e) For these materials packaged for shipment with number of packages limited in accordance with the requirements of Chapter III of this Order. (d) To radioactive waste storage or disposal facilities. I I I v a. (1) s ble materi s s "in (2 ) r (3 ) y (4 ) Li ; sa 1 in cuous aces (5 ) S; iate ices ill at ic 10c instruc ons ( a ) In ons a re nse to arms. (b) Evacua on routes. (c) res. (6 ) (7) 1 (8) "In-Process" (9) iners (10 ) 5 (11 ) rm to 11 no t ib1e mater; s (12) (13 ) (14) (I5) (1n V 6 Provisions in utonium es 1 i ed b. c. n a utonium necessary and assessment. 8- 3 to 8ssure temova. as DOE S48CJ . 1A 3-13--81 CHAPTER V I SAFETY OF DEPARTMENT Of ENERGY aWNED REACTORS 'I T -1 1" PURPOSE. The purpose of thi s chapter 1 s to estab l -i sh safety procedures and requirements for nuclear reactors to assure that: a. The safety of each Department of Energy-owned reactor is properly analyzed. evaluated, documented, and approved by the Department. b. Reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate protection for health and safety and will be in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. 2. SCOPE. This chapter applies to Headquarters and field organizations, 5nd Departmental contractors having respons-ibil ities for Department reactor projects . This chapter applies to Department-owned reactors exempt from Nuclear Regulatory Commission licensing; additional guidance applicable to Department-owned 1 icensed reactors will be provided as needed by future revision of the chapter. 3. REFERENCES. a. Code of Federal Regulations, Title 10, Part 50, "Licensing of Production and Util ization Facil ities. II b. Code of Federal Regu1ations, Title 10, Part 100, ;'Reactor Site Criteria. 1I c. DOE 5484.1, ENVIRONMENTAL PROTECTION. SAFETY AND HEALTH PROTECTION INFORMATION REPORTING REQUIREMENTS. d. DOE 5700.5A, QUALITY ASSURANCE.

e. DOE 5482.1A, ENVIRONMENTAL SAFETY AND HEALTH APPRAISAL PROGRAM. f. DOE 5500.2, EMERGENCY PLANNING, PREPAREDNESS, AND RESPONSE FOR OPERATIONS. g. ANS 3.1, American Nuclear Society Standard 3.1, IISelection, Qualification, and Training of Personnel for Nuclear Power Plants," October 1980. h. ANSI N546-1976. "Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants." VI j. 4. a. b. c. d. e. g. h. i . .2, (1 ) term reac ; vi reactor. , Licenses." c contractor on ;c;an to nt to on is I i ncl udi test r reactors, to rm s 1y c (2 ) j. k. to m. n. is o. r GOE 5'+80. 1/\ 8- 13 -,81 po ,:.af'et.y F, E:\i'[ew ., A o.el·;bero.'(;E: and IHi c )'] ex am nation of '~he safety 'impact of a proposed iictivHy or an ongo ng activ H y uring the sit1ng, designing, const ruct"ing) ;Yi~in tc.' ! ning~ modif,Y ~g~ 0:" deCOrn!1I1Ssioning Cof a (ea.ct fJr~ 'tihich could affect health a.nd safety . uocumen-cat'ion shall be considered pa.rt of 'the safety revi2~~, to provide manageme nt with adequate identifi­ ca.tion of the safety -issues and their possible imp'lications, and also to allow others not directly involved in the program or review process to independently evaluate the completeness or 3deq~acy of the review. q. Senior Reactor Operator. An individual certified by contractor management to operate or to direct the operati on of a Depa.rtmerlt-owned Cate90i~Y p, reactor~ s. Shutdmvn. That coroit'ion in I'!h ic h a re,1ctor facil ity has ceased :)peratlon and the Dep3.rtment has declared officially tha.t it does rlot -intend to operate the reactor further. Standby . That condi ti on i 11 \i/h i eh a reactor faci Ii ty ~ 5 [lei the. vperab"; e nor decl ared ~xcess. "nd documentary authori zati on ex; sts to rnai ntai n the reactor for possible future operati on. 'L Technical Specifications. A safety doculTient apptoved by the Department "yhich in a specified format defines the condit ion s, safety boun daries, and procedures under which activities ~reto be carried out at a reactor. See Code ~f Federal Regulations, ~itle 10, part 50. 35. J. Under Construction. When the authorization for construction has been issued and authorization for operation has not yet been issued. v. Unreviewed Safety Question. A. proposed change, test, or exper '!ment shall be deemed to involve an unreviewed safety question if: (1) The probabii H.Y of occurr-ence or the consequences of an ~ccident or malfunction of equipment important to safety previously evaluated in the Safet.y Analysis Report a.nd addenda will be sigrrificantiy in­ creased. (2) A possibil ity for an accident or malfunction of a different type tha.n any evaluated previously in the Safety Analysis Report and addenda will be created which could r-esult in s-ignificant safety consequences. w. UAusua1 Occ~rrence. See DOE 5484.2, UNUSUAL OCCURRENCE REPORTING SYSTEM. 5. RESPONSIBILITIES AND AUTHORITIES. a. Program Secretarial Officers, or their designees. perform the following functions for reactors under their program responsibil Hy: (1) Assume l ine management responsibility for reactol" safety. DOE 5480 . lJ\ 8-13-81 '11·5 (2) Provide for an independent review and assessment of the reactor program activities in their program organizations and the field offices ~o assure that they are accomplished in consonance with the need for protecting the safety and heal til of DO E and DOE centacto;" employees, and "t"le Dublic. (3) Assure that the construction. initial startup. and subsequent modifica.tior's of reactors "involving an unrev i ewed safety question V;ln 1 not create undue envi Y'onmenta"\, safety, or heal th ri sks by:

to.) A.ssdr"·:n'9 't.h3t an acce-ptab·!e sa'f'e~:..y review has been made and. documented by the c.ppropri ate f"; el d of"gani zati on. (b) De+:er;r.1,r"ing that such independent safety r-ev;ews indicate that an adequate degree of protection of heal th and safety ex"j sts. (4) Approve summary ·)f training plans ';Jhich define and describe the select i ve appl i cution of ANS 3.1 ;-equirements to Category A reactors (see Attachment VI-I, paragraph 3), when assured that the summary proy; des for H:e requi rements nec2ssc.ry to achi eve the goal of we11- trained pei'sonn e'l fo '( the reactod S \:overed by the summary. (5) Tr~nsmit the re;u1ts of ~he act ions ta~en under subparagraph (2), (3i, and (4), c:.oeve, to the i"c!;ponsible field organizations with any i,ecessary:)r apprJpr'iate instructions .:1S to subsequent a,ction to be taken, with a copy to EP-30. (6) Submit to higher management fer action any disagreement with recom­ mencations made d~iri;)g safety i"evieltlS that cannet be resolved, (7) Provide assistance and guidance to field organizations in the performanc~"' of safe t y teviews.3.ppraisals, and the preparation of safety analysi s repcrts. (8) Recommend ~. dd .. i '~·Icns cr ~"2'i.:is~rons :S :"23.ctO:'" 5afety ;tanda7'ds, guides, and codes to EP-30. (9 ) Perfo rlTI program revi ews c.nd assessmsnts to za~lons comply with subparagraph d, bel ow. thi s responsi b-l1i ty, maximum use shaul ci be and other reviews pe:formed by EP-30. assure that field organi­ In the execution of made of the appraisals (10) Assure the safe operati on of r~actor5 by: (a) Directing the res onsible field organiz2ticn to require modification of e uipment, procedures. or practices to ass~re s3.fe operati on. V1- b. E olA 1 en is curta il or 5U ( c) ac ons. as (11 ) a rections given un {l2l I u to assure sa (13 ) at ram uirements {l4 } (15) (16) (l) (2 ) (3) reactor (4 ) es r pram ;ves in connec are consi nt ans, in avai overview rements and ce reactor sa VI-7 (5 ) teams ich are au n til ex ons. (6) sa se to ass; ons. (7) ic on. (8) Issues ci s reactor. (9 ) e in se so (10) cer ( a) (b) on yen rements c. (1) (2 ) [;OE 5480. lie, 8- ],2 - 81 pl ants and critical facil Hies at supporting contractor 1 aboratory facilities. for Derforming appraisals in accordance with DOE 5482.1 3.S deemed ilecessary at Naval Reactor prototype p1 <:.nts and supportl!-,g contractor laboratory critical facilities and, for selection, qualifi­ cation, training, and certification of operating personnel for naval reactor prototype plants and critical facilities of supporting contractor laboratory facilities. (3) Is exempt from appraisa1s conducted by EP-l, and for reporting and analysis of occurrences. (4) Fulfills the responsibilities listed under paragraph 5d for Heads of Field Organizations. d, Heads of Field Organizations have the immediate responsibil ity fer assuring that adequate provision is made for the protect~on of health and safety in accordance with the provisions of this chapter. They: (1) Assume line management responsibility for the safety of assigned reactors. (2) Provide for an overview of reactor safety in their organization independent of line management responsibility. (3) Review and provide to the appropriate Headquarters offices, Safety Analysis Reports, addenda, and other safety documents for all new reactor construction and for modifications involving an unreviewed safety question.

(4) Assure that approved Technical Specifications exist for all reactors under their surveillance. (5) Authorize construction and initial operation of a new reactor or modifications involving an unreviewed safety question. Prior to initial operation or after modifications involving an unreviewed safety question, a preoperational inspection of the reactor shall be conducted and documented. (6) Specify in writing to the contractor those activities for which safety evaluations are to be submitted for Department of Energy review and approval. Field offices shall. as a mlnlmum. review proposed modifications involving plant protection, reactivity control systems, and engineered safety features. (7) Authorize modifications to reactor operations including the addition of critical assemblies or critical assembiy rooms to existing and approved critical facilities when these modifications could have DOE 5480.1;), 8·-13 -81 an impact on reactor safety. but do not involve unreviewed safety questions after assuring that: (a) The contractor has performed and documented a detailed evalu­ ation of each proposed modification. (b) The fie1d offices' safety reviews are appropriately performed and documented in the depth necessary to justify authorizing the modifi cation. (c) An adequate degree of protection of health and safety exists. (d) Additional requirements of the Headquarters program organization having safety review responsibility have been met. (8) Review (either during inspections, appraisals, or through reviews of documents submitted by the contractor) changes made to reactor operations, including revision of procedures, experimental program changes, and physical modifications which could have safety implica­ tions, to assure that the contractor has made appropriate reviews and that the changes made do not violate Technical Specifications or involve an unreviewed safety question. (9) Take such actions as may be appropriate including curtailment and suspension of operation of any reactor under their surveillance when, in their opinion, such operation may result in undue risk to health and safety. (10) Monitor contractor activities, as appropriate, during siting, design, construction, operation, modification, and decommissioning phases by periodic inspections of, and visits to, individual reactor facilities. (II) Assure the establishment of an appraisal program in accordance with DOE 5482.1, including periodic appraisal of the reactor operating personnel training program. Appraisals of the overall operation of each reactor facility shall be conducted; however, individual reactor facility appraisal reports may be combined. (12) Assure the establishment of an appropriate quality assurance program by the contractor in accordance with DOE 5700.6. (I3) Assure the establishment of a reactor personnel training and qualifi­ cation program by the contractor in accordance with paragraphs 6e(I) and (2). (I4) Assist in the review and development of environmental protection. safety, and health protection codes, standards, and guides. VI-IO (IS) es 1i nt of an system in acco nce (16) of (17) sta i si some p ciencies. (19 ) (20) 6. p a. b. (1) 1 new construc on reactor ili (2 ) more ve an c. 0 DOE 5480.1A 8-13 occurrence invest; on and .1 a .2. b ons ons reviews, in tions, 1 e He rters ram and nes suc ri cer. reactor and duri cant t on ul t; i in e 1 be es. can cr1te e. structures, , or com- stion are un ). E 1 d. e.

.1A ( 1 (2 ) (1) ( a ) 1 \II 11 uclear reactors ons. 2 n2 and ANS 3. requirements, contractor of each Ca c on shall be i not d 0 ce manager .. J l-\ scr~;Je sh 1 be A ans ~ .. secL!rit.y rces, rtmen';.: of (b) D ------------~----~~--------~ 1 sis. 2 (c) 1 2 3 4 acqui at , research reactors rience on a one-far-one ni or reactOt s a reactor fic train; 5.4 r se irements, icians DOE 1-13 8-1 s d i ni in tions 5. .4 5.4 traini in: a on; b rements concerni ra ation c of ten c d es r r on; e ician in no 5 (d) 1 2 c VI-14 concerns. 3 a b in c 4 5 VI-IS 1 6 a b 7 3.1, (e) (2 ) 13 (a) on. sc i ence. 2 IS (b) 1 rator l s train; to cover areas i are sc on. a b 2 , f'eactivi tenance ac (c) ( d i ( .::> \ ..... 1 2 3 ate ni ni in i le \! annually in areas (see ( ve ate VI- ( f) on. 1 a 1; in s - s isors, b • in c I written, 2 contractor ons: a on covers 1 - es. b on es c - 3 (g) ences 2 3 4 5 (h) 1 2 3 4 a b c i e ence. iate VI 9 ons retrain- s ner VI 5 1 2 3 rt (j) 1 2 3 &: I • g. in ir on es ibil i reactor sa 1 most recent sis. e(2)(h) ce ons. iza- on ve review system cons on. (l) (2) Is cl ec (3 ) (4 ) (5 ) (6) Prov; s an ; VI -21 se the reactor ram 1i ( e. g •• S1 ra on) i (e.g., ses. i. s 1 on. i rements. ) scussions between reviewers on more VI (9) h. i . j. k. (c) (d) (e) (9) (h) (1) Is at currences, on rev; lea 8-1 ) , c ons, and c s i vi ons. s; a on. rmance 1 in e 1. m. 7. (1) (2) (3 ) {4 } (5) area. VI ( VI st area 1 es n nnE :'480. 8-1J··81 , .l. • 2. sign FI DP-l -. ··14 IONS. p ry Livermore ce ce on ng Division iences Environme Research h rtment es and ect Attac VI -1 ce ry Attac VI-l Page 2 3. K N - N P - P tor II · I--' '" ar a e In r 9 e e e va IV e e J e e asma e } e s e r e W::::r :3 fI) ::') M" <: ...... I ...... ::::> r:- <: on Orqanization ReSDons i bi I i tv Contractor Status ....... I ...... 1 ear 1 RI e it le t. e e servo; r II IA UDeraD e r I I 1 R II I -1 IA UDeraD e r I II e e ca Kesearcn JANU:::i CH tK-l ,A..NL raD e r Pi1 e . 5 0 0::> I , 0::;0 10 ..... [Tl .;....J I . ..... R II CH le r II tor CH le CH le CH le 9 CH ANL le r le Plutonium tor III le r 1 e r 1 e -0):> Olrt vi I 1D le ~rt 11) Ol () U'1 C rt -< ....... I ):> 10 e e 10 e t ID e le d ID 4 e F 4 e i1 i es IS In ili es e litles 1 i tl es In r DIG tor w es on sne e e le e le e e e <: ...... I I-' u:t;> 1l.>M" REACTORS \0 rt (,!)Il.> n CXl :;y Responsible Headquarters 3 (D ri el d Program Operating Current ;:\ M" t~ame Designation Organ1zat·jon Res p 0 n sib il i ty Contractor Status <: ...... I Submarine Advanced S3G NE-40 NE-40 GE Operable """ Rea,ctor Prototype The rrna 1 Reac tc r nE,·l NE-40 NE·-40 GE Operable No. 1 Trident Rea,ctci" S8G NE--40 NE-40 GE Operable Prototype Bulk Shielding 3SR OR ER-IO ORNL Operable Reactor H"j gh Flux HFIR OR ER-IO ORNL Operable Isotope Reactor Hea,1th Phys i cs HPRR OR ER-30 ORI~L Operable Research Reactor Oak Ridge Critical OR-CEF: OR ER-IO ORNL Operable Experiments Facili:y eel"! : : \~" Oak Ridge Research ORR OR ER-IO ORNL Operable Reactor Pool Critical PCA OR ER-IO ORNL Operable Assembly Tavler Shi el di :-19 TSR- I j. OR NE-530 ORNL Operable Rea,ctor I I ro 0 10 I-' fTl W I U1 C) ..,. I-' co 0 . """ » REACTORS

Responsible Headquarters Fi ei d Program Name Designation Organization Kesponsibil ity Puert.o Rico PRNC-L··77 OR ER-30 Nuclear Center pe L-77 B Production B RL DP-l Reactor C Production Reactor r RL DP-l ",. Fast F~ux Test FFTF FFTFPO NE-530 Faci: ity Neutron Radiography NRF FFTFPO NE-530 Facility K East Production KE RL DP-l Reactor K West Production KW RL DP-l Reactor N Product i or~ :-.J RL DP-l Reactor Operating Current Contractor Status PRNC Shutdown UNI Shutdown UNI Shutdown HEDL Under Construction HEDL Operable UNI In Standby UNI In Standby UNI Operable ex:> 0 10 I-' rn w I lT1 co ..,.. I-'CP 0 . I-' );:> "0);:> OJrt <.Crt (!) OJ (") <.D :::s :3 (!) ::::I rt < ..... I I-' t urn le C p on r C K P on tor K L on r L in p on tor P s uevel PDP Pile on -1 SI{ UP-l Uu pont SI{ IJP-l Uu pont t t e le In Ie Ie Ie Ie In I-' i-' ):>