NUREG-1537, Part 2 - NRC

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ABBREVIATIONS- ACRS Advisory Committee on Reactor Safeguards. AEA AtomicEnergy Act of 1954, as amended AEC Atomic Energy Commission AGN Aerojet-General Nucleonics ALARA as low as is reasonably achievable ANS American Nuclear Society ANSI American National Standards Institute ASLAB Atomic Safety and Licensig Appeal Board ATR advanced test reactor BNCT boron neutron captre therapy BSF bulk shielding ficility CAM continuous air momtor(ng) CFR Code ofFederalRegultions- CP construction permit CP-5 Chicago Pile #5 CP-1 I Chicago Pile #11 DNBR departure from nucleate boiling ratio DOE Department of Energy DOT Department of Transportation DP decommissioning plan EA environmental assessment EC effluent concentration ECCS emergency core cooling system ER environmental report ESF engineered safety feature EPRI Electric Power Research Institute EPZ emergency preparedness zone FDA Food and Drug Administtion FLIP fuel lifetime improvement program FR Federal Register FSAR final safety analysis report GA General Atomics HEU highly enriched uranii-um HVAC heating, ventilation, and air conditioning REV. 0. 2)96 .1x- - - STANDARD REVIEW PLAN REV.O,.2/96 . _ . LY - - - STAM".1) REViEWPL" I
ABBOEVW7!NS IAEA International Atomic Energy Agency I&C instrumentation and control IEEE Institute of Electrical and Electronic Engineers INEL Idaho National Engineering Laboratory LCO limiting condition for operation LEU low-enriched uranium LOCA loss-of-coolant accident LOFA loss-of-flow accident LSSS limiting safety system setting LWR light-water reactor MHA x hypothetical accident MIT Massachusetts Institute of Technology MPC maximum permissible concentration MR materials testing reactor NFPA National Fire Protection Association NRC Nuclear Regulatory Commission NRR Office of Nuclear Reactor Regulation NUMARC Nuclear Management and Resources Council ORNL Oak Ridge National Laboratory ORRR Oak Ridge Research Reactor OSHA Occupational Safety and Health Administration OWR Omega West Reactor PSAR preliminary safety analysis report PULSTAR pulsed training assembled reactor QA quality assurance RAM remote area monitor RCS reactor control system RG regulatory guide RO reactor operator RPS reactor protection system SAR safety analysis report SI Internation System of Units SL safety limit SNM special nuclear material SNAP system for nuclear auxiliary power SPERT special power excursion reactor test SRO senior reactor operator NUREG-1537.PART2 x REv 0.2/96 - -
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: - | CON1, Page 12.6 Records .......
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 and 30: THE FACILTIY Applicants are expecte
Page 31 and 32: * assumed inventory of fission prod
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
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CHAPTER 4 * The discussion of the f
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CHAPTER 4 * The control rod design
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CHAPTER4 * materials * compatibilit
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CHAPrER4 when starting the reactor
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CHAPT 4 * The applicant has justifi
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CHAFtE4 characteristics of the reac
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CHAPTER4 Review Procedures The revi
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CHAPrER4 calculational models and a
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CHAPTER 4 Anticipated rearrangement
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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
Page 213 and 214:
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
Page 239 and 240:
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
Page 249 and 250:
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
Page 257 and 258:
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
Page 273 and 274:
2.2.2 Current Radiological Status o
Page 275 and 276:
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
Page 335 and 336:
Review Procedures -- HEU TOLEU CONV
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13.3.1 Loss-of-Coolant Accident Are
Page 339 and 340:
HEU To LEU CONVERSION methods and a
Page 341 and 342:
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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