NUREG-1537, Part 2 - NRC

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TLD thermmoluiniescence dosimeter TRIGA training reactor, isotope [production), General Atomics TS technical specification USGS U.S. Geological Survey UTM Universal Transverse Mercator ADBVATIONS REV. 0, 2196 Xl STANDARD REVIEW PLAN REV.0,2/% xi STANDARDREvEw PLAN
INTRODUCTION Background Ts document gives guidance to staff reviewers in the Office of Nuclear Reactor Regulation (NRR) and reviewers under contract to the U.S. Nuclear Regulatory Commission (NRC) for performing safety reviews of applications to construct,. modify, or operate a nuclear non-power reactor. The principal purpose of this document is to ensure the quality and uniformity of reviews by presenting a definitive base from which to evaluate applications for license or license renewal. This document also makes information about regulatory matters widely available and helps interested members of the public and the non-power reactor community better understand the review process. NRC has published several documents that give guidance that is applicable to commercial power reactors. In 1972, the NRC issued Regulatory. Guide (RG) 1.70, "Siandard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWREdition)" to help commercial power plants in applying for light-water reactor (LWR) licenses. The staff revised RG 1.70 in 1972, 1975, and 1978. In 1975, NRC issued the "Standard Review Plan for the Review of Safety Analysis Reports forNuclear Power Plants (LWR Edition)" (NUTREG-75/087) to ensure the quality, completeness, and uniformity of staff reviews of power reactor safety anysis reports (SARs), and to assist the staff in performing the reviews., In 1981, the staff completely revised the earlier Standard Review Plan (NUREG- 75/087) and published the revision as NUREG-0800. In,1987, the staff revised NUREG-0800. The staff issued RG 1.70 and NUREG-0800 for LWR nuclear power plants, w;hich are much larger and more complex than non-power reactor facilities. Recognizing that non-power reactor licensees need not be required to comply with the SAR guidelines for power reactors, NRC issued a format and content guide (NUREG- 1537, Part 1) for non-power reactor license applicants and is issuing this.. companion document for the'NRC staff to use in reviewing and evaluating SARs submitted for non-power reactors. Reactors designed and Bperaeed for research, development, education, and medical " therapy are called non-power reactors (defined in the Code of Federal Reglatio~n, Title 10, Section'50.2 (10 CFR 50.2)). ,This.class of reactors, comprises research reactors (defined in 10 CFR 170.3)j and testing facilities (also 'referred to as test reactor in some regulations), which are defined in 10 CFR 50.2 and 10 CFR 100.3. The format and content guide contains additional information on the classification of non-power reactors.' 5REV. 0,9 xI ST).NDumAw REVI PLAN
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: ABBOEVW7!NS IAEA International Atom
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
Page 61 and 62: 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
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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
Page 241 and 242:
14 TECHNCAL SPECIFICATIONS This cha
Page 243 and 244:
TEcHnICAL SpEcmcAnoms * The staff h
Page 245 and 246:
CHAPTER 15 * Areas of review should
Page 247 and 248:
CHAnM R1S * The applicant should es
Page 249 and 250:
CHAP~i~tIS Environmental Review Pro
Page 251 and 252:
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
Page 263 and 264:
DEcOmm oNG ANDPossEsoN-ONLYAmm .ES
Page 265 and 266:
Review Procedires DEamRsoNEA PosHmo
Page 267 and 268:
DEcOmmXsoNU4G AD PossEssioN-ONLY AM
Page 269 and 270:
DEcoMMiSsIoNING AND PossEssioN-ONLY
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NRC Review of Decommissioning Plan
Page 273 and 274:
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
Page 295 and 296:
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
Page 311 and 312:
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
Page 331 and 332:
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
Page 345 and 346:
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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