NUREG-1537, Part 2 - NRC

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CHAPTER I the operaing history of licensed ficilities cited by the applicant demonstrates consistently safe operation, use, and protection of the public. Evaluation Findings This section of the SAR should contain sufficient information to support the following types of conclusions, which will be included in the stafs safety evaluation report: * The applicant has compared the design bases and safety considerations with facilities of similar fuel type, thermal power level, and siting considerations. The history of these facilities demonstrates consistently safe operation that is acceptable to the staff. * The applicant's design does not differ in any substantive way from similar facilities that have been found acceptable to NRC, and should be expected to perform in a similar manner when constructed to that design * The applicant has used test data from similar reactor facilities in designing components. The applicant cited the actual facilities with the components. These data provide assurance that the facility can operate safely as designed. The stafs safety evaluation report should contain a summary of the similar facilities discussed by the applicant. 1.6 Summary of Operations Areas of Review Many non-power reactors do not operate frequently at the maximum licensed power level, and many operate on demand. Some operate daily at the licensed power level, and some operate continuously with periodic shutdowns for maintenance, fuel shuffling, and experiment changes. Unless there is a safety reason to limit operation of the reactor, the reviewer should assume that the reactor will operate continuously. If there is a safety reason to limit operation of the reactor, then the reactor operating time should be limited by license condition as discussed in the appropriate chapter of the SAR. Areas of review should include the proposed operating plans for a new facility to evaluate the following: possible effect on the power and heat removal capabilities discussed in Chapters 4 and 5 of the SAR NUREG-1537, PART 2 1-10 REV. O. 2/96
* assumed inventory of fission products and source of decay heat _ THE FArHM * assumed releases of radioactive effluents to the unrestricted environment The reviewer should also evaluate the operating characteristics and schedules in an application for license renewal for significant changes and for consistency with the proposed technical specifications. Acepkawce Criteria The acceptance criteria for the applicant's summary of operations include the following: * The applicant should demonstrate the consistency of proposed operations with the assumptions in later chapters of the SAR, including the effect on reactor integrity and potential radiological exposures. * The applicant should demonstrate that the proposed reactor operation was conservatively considered in the design and safety analyses.- * The proposed operations for license renewal should be consistent with the assumptions in later chapters of the SAR. Review Procedures Although NRC has not issued criteria for evaluating proposed operations, the reviewer should compare proposed operations with the cumrent operations of any similar ficilifies. The reviewer should verify that proposed operations are summarized and should compare them with similar facilities for initial licensing, or with previous operations if the application is for license renewal. For license renewal, the reviewer should solicit evaluations by NRC inspectors from the appropriate regional office. Evaluations by NRC regional inspectors and evaluations based on the annual report from the facility should provide additional verification that the applicant can operate the facility as specified mi the SAR; If there are limitation's on operation of the reactor, the reviewer should verify that they are represented as license conditions. Eialuatn FiRings This section of the SAR should contain sufficient information to support the following type of conclusion, which will be included in the staffs safety evaluation report: -. REv.O,2196 . . 1-11 I-1 1 . STANDARD REVIEW PLi.N -''STANDARDREvmwPLAN REV .V9
Page 1 and 2: NUREG-1537, Part 2 Guidelines for P
Page 3 and 4: AVAILABILlTY NOTICE Availability of
Page 5 and 6: NUREG-1537, Part 2, has been reprod
Page 7 and 8: Page 4 REACTOR DESCRIPTION ........
Page 9 and 10: - | CON1, Page 12.6 Records .......
Page 11 and 12: ABBOEVW7!NS IAEA International Atom
Page 13 and 14: INTRODUCTION Background Ts document
Page 15 and 16: NTRODUCMON accidents, since the maj
Page 17 and 18: INTRODUCnION reviewers dealing with
Page 19 and 20: IRODUCriON accident consequences. T
Page 21 and 22: 1 THE FACILITY Chapter 1 of the saf
Page 23 and 24: * safety criteria proposed by the a
Page 25 and 26: THE FACILITY SAR. The technical spe
Page 27 and 28: Evaluaton Findings NRC does not wri
Page 29: THE FACILTIY Applicants are expecte
Page 33 and 34: ThE ForAaXy agreement with the Depa
Page 35 and 36: Appendix 1.1 Introduction from NURE
Page 37 and 38: Appendix 1.2 DOE Letter to NRC Conc
Page 39 and 40: 2 SIT CHARACTERISCS This chapter pr
Page 41 and 42: SnE CHARAcrmusncs * The demographic
Page 43 and 44: SIE CHARAcXERIcs * historical seaso
Page 45 and 46: SrYI CHARAcrIsnTc other water-induc
Page 47 and 48: SrnE CHARAcYmusna * The geologic fe
Page 49 and 50: 3 DESIGN OF STRUCTURES, SYSTEMS, AN
Page 51 and 52: DESIGN OF STRUCTURES, SYSTEM, AND C
Page 53 and 54: DESIGN OF SRUCrURES Sysms. AND COMP
Page 55 and 56: Evasion Findings - DESIGN OF STRucn
Page 57 and 58: DESIGN OF STRnUtURES, SYSTEMS, AND
Page 59 and 60: CHAPTER 4 reactor core. Subsequent
Page 61 and 62: CHAPTER 4 * The discussion of the f
Page 63 and 64: CHAPTER 4 * The control rod design
Page 65 and 66: CHAPTER4 * materials * compatibilit
Page 67 and 68: CHAPrER4 when starting the reactor
Page 69 and 70: CHAPT 4 * The applicant has justifi
Page 71 and 72: CHAFtE4 characteristics of the reac
Page 73 and 74: CHAPTER4 Review Procedures The revi
Page 75 and 76: CHAPrER4 calculational models and a
Page 77 and 78: CHAPTER 4 Anticipated rearrangement
Page 79 and 80: CHAPTER 4 4.5.2 Reactor Core Physic
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CHAPTER 4 included them in the tech
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CHAPTER. 4 Evaluation Findings This
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CHAPTER 4 For a pulsing reactor, li
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CHAPTER5 This chapter gives the rev
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CHAPTER S The descriptions and disc
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CHAPTRS acceptable radiological dos
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CHAPTER 5 dissipation is accomplish
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CHAPTER 5 5.4 Primary Coolant Clean
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CHAPTERS achieved. The design ensur
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CHAPTERS Ewauation Findings This se
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CHAPTR5 Evaluation Findings This se
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CHAPTER5 analyzed. The reviewer sho
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CHAPTER 6 The accident analyses by
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CHAmR 6 6.1 Summary Description In
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CtwxR 6 Acceptance CnItenad The acc
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I CUAPTER6 Higher power non-power r
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CHAPT6 * The design that should red
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CHArr't 6 * The ECCS should not int
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7 INSTRUMENTATION ANDCONTROL SYSTEM
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INSTRumENTAIroN AND CoNIROL SYmtm s
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INSRUMENTAnON AND CONTROL SYSTEMS *
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_ INsTRumE3nArroN AND CONTROL SYSTE
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INSIIuMETrATnON MD CoNmoL SYSTEm *
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Acceptance Cnteria INSFRUMENTAMON A
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Review Procedures INTUMENTATION AND
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- -- IxStRUMwnTAToN AND CONTRoL Sys
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* . personnel and equipment protect
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-.... - . INSTRUMENTATION AND CONTR
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INSRUMENATION AD CONIMOL SYSTMS * c
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INSgtmrNTA1ION AND CoNmoL SySIEmm A
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CHAPrER 8 * The system should be de
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CHAPTER8 Acceptance Criteria ) The
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9 AUXILIARY SYSTEMS This chapter co
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AUXILIARY SYSEms * 0 CFR Part 20 an
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. AuxiLARY SYSTEMS * Methods for in
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Evaluation Findings AuxnARY SYSTEMS
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Rewew Procedures AUXILIARY SYSTEMS
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AuxLiARY SYSTEMS * The facility com
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Revew Procedures AUXLARY SYSmEm The
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AuxILIARY SYSTEM * analyses of the
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AuNARY SYSTEMS * No function or mal
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CHAPTER 10 accidents including malf
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CHAPrER 10 Areas of review should i
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CHAPTER 10 dimensions, materials, a
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CHAPt 10 integrity during all antic
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I CHAPTER 10 The applicant should l
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11 RADIATION PROTECTION-PROGRAM AND
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RADIAnON PRoTEcnoN PROGRAM AND WAST
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RADiAnoN PROTECTON PROGRAM AND WAST
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Acceptance Criteria RADIATIoN PRtow
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RADIATION PROTECION PROGRAM AND WAS
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RADIAnON PRoTECTION PROM AND WASTE
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RADAION PROTECTnON PRoORAmAND WAsTE
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RADIATION PRtowCioN PRoGRAm AND WAS
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* radiation monitors, alarms and sa
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RADIATnON PROTECrON PRORAM AND WAsT
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. RADiuTION PROTEcoN PROGRAM AND WA
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I - - RADiA11ON PRCoECnON PROCRAM A
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Revew Procedures RADIATINo PRoTEoN
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RADiiAoNPRaorcnoN PROGRAM AND WASTE
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RADLATnON PRoTCTON PROGRAM AND WAST
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CHAPTER 12 day-to-day operation of
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CHA'rER 12 12.2 Review and Audit Ac
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CHAPTER 12 staff has determined tha
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CHAPE 12 to correct and prevent rec
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CHArER 12 12.6 Records Areas of Rev
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CHAPrER 12 * requalification docume
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CHATRi 12 operator skills and knowl
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CHAPTER 12 applicant's safety analy
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Appendix 12.1 Environmental Conside
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APPENDvc 12.1 Chemical and sanitary
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APPENDix 12.1 Conclusion The staff
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CHAPTER 13 The information in this
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CHAPSER 13 * The single malfunction
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CHITER 13 (c) (For high-powered rea
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CHAPTER 13 or * protracted malfunct
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CHAPTER 13 * With natural-convectio
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CHAPTER 13 (If the MHA is not afuel
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CHAPTDl 13 Bibliography Non-Power R
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CHAPShR 13 U.S. Nuclear Regulatory
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14 TECHNCAL SPECIFICATIONS This cha
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TEcHnICAL SpEcmcAnoms * The staff h
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CHAPTER 15 * Areas of review should
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CHAnM R1S * The applicant should es
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CHAP~i~tIS Environmental Review Pro
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CHAPD 16 system; engineered safety
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CHAF1a 16 Medical therapy at non-po
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CHAPS 16 treatment. The door or ent
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CHAEW 16 * Requirements for reporti
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17 DECOMMISSIONING AN) POSSESSION-O
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- DEcOM iSNNG AND PossEssION-ONLY A
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DEcOmm oNG ANDPossEsoN-ONLYAmm .ES
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Review Procedires DEamRsoNEA PosHmo
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DEcOmmXsoNU4G AD PossEssioN-ONLY AM
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DEcoMMiSsIoNING AND PossEssioN-ONLY
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NRC Review of Decommissioning Plan
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2.2.2 Current Radiological Status o
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DEMMM=ONMPJANS 2.4 Decommissioning
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DECCMMISSIONI0PLANS The DP should s
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DEco wIssioNDJGPLA controls to comp
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- - ~DECOM SSOKMGPLANS facility. Su
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8 ENVIRONMENTAL REPORT ..DECOMOM=ON
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18 HIGH1LY ENRICHED TO LOW-ENRICHED
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NIowLy ENmI ToLow-EmIAEDURAwrum CoN
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Standard Review Plan and Acceptance
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HEU To LEU CoNvEaswoN since the las
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HEU To LEU CONVERSION should also d
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HEU TO LEU CoNVERSION this section,
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4.2.1 Fuel Elements HEU TO LEU CONV
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Evaluation Findings (Sections 4.2.1
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Acceptance Criteria _HEU TOLEU CoNv
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- HEU TO LEU CONVERSON Calculations
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HEU TO LEU CONVERSION should be dis
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HEU TO LEU CoNvERSoN *Acceptable ch
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BEU To LEU CoNvEasioN Generally, co
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Evluation Findings HEU TOLEU CONVER
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... HEU TO LEU CONVERSION * The coo
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Accepktace Criteria HEU To LEU CONV
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9.4 Fuel Element Handling and Stora
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10 EXPERIMENTAL FACILITIES AND UTIL
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11.1 Radiation Protection Program A
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*HEU TOLEU CONVERSION The areas of
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BEU TO LEU CONVERSION specification
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- - - - HEU To LEU CoNvmESioN relia
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HEUrTo LEU Cowv~ptstoN design ofthe
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BIEU To I.EU Col~vERSoN MHA, the ba
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HEU To LEU CoNvRiow acceptable assu
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Review Procedures -- HEU TOLEU CONV
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13.3.1 Loss-of-Coolant Accident Are
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HEU To LEU CONVERSION methods and a
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Evaluation Findings BEU To LEU Comv
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BEU TO LEU COPvERSION characteristi
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HEU TOLEU CONVON American National
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HEU TO LEU CONVERSION U.S. Nuclear
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NUREG-1537, Part 2 - NRC

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