NUREG-1537, Part 2 - NRC

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CONDUCr OF OPER.AIONS covers the unique aspects of these reactors The emergency plan reviewer should provide an evaluation for inclusion in the staff's safety evaluation report. 12.8 Security Planning Security planning is a specialized area of review. The technical reviewer should forward security planning information and proposed security plans to the Safeguards Branch in NRR for review. Security planning information is considered either proprietary or safeguards information and must receive special handling. The technical reviewer should ensure that this information is handled properly. The reviewer should contact the Information Security Branch in the Division of Security regarding any questions on the proper handling of security information. The security plan reviewer should provide an evaluation for inclusion in the staffs safety evaluation report and a license condition for inclusion in the facility license. 12.9 Quality Assurance Quality assurance is a specialized area of review. The technical reviewer should forward proposed quality assurance information to the Quality Assurance and Maintenance Branch in NRR for review. The technical reviewer should remind the quality assurance reviewer that this information is for a non-power reactor and that Regulatory Guide 2.5 (appears as Appendix 12.3 in the format and content guide) and ANSIIANS-15.8 should be consulted. The quality assurance reviewer should provide an evaluation for inclusion in the staff's safety evaluation report.-' 12.10 Operator Training and Requalification Areas ofReview The applicant should submit a reactor operator requalification plan within 3 months after the facility operating license is issued. Each reactor operator or senior reactor operator is required to successlly complete a requalification program developed by the licenseeth'at has been approved by the Commission. Areas of review should include the following: ,- requalification schedule' * lectures, reviews, and examinations * on-the-job training emergency procedures * 'inactive operators * evaluation and retraining of operators REV. 0. 2)96 12-lU STANDARD REVIEW PLAN REV.0, 2/96- . 12-1 1 STANDARD REviEw PLAN
CHAPrER 12 * requalification documentation and records * requalification document review and audit Additional information on the areas of review is given in this section of the format and content guide. Acceptance Criteria The acceptance criteria for the information on reactor operator requalification plans include the following: * The duration of the program should not exceed 24 months. The next requalification period should start immediately after the completion of the preceding period. * Preplanned lectures should be given on a regular and continuing basis as required by 10 CAR 55.59(c)(2). The lecture topics should follow those given in 10 CFR 55.59(c)(2), at a nminimun. * On-the-job training should occur during the requalification period so that each operator (1) is involved in facility manipulations [see 10 CFR 55.59(c)(3)(i)], (2) understands the operation of apparatus and mechanisms associated with control manipulations and knows operating procedures [see 10 CFR 55.59(cX3)(i)], (3) is cognizant of changes in facility design, procedures, and license [see 10 CFR 55.59(c)(3)(iii)], and (4) reviews the contents of all abnormal and emergency procedures on a regular basis [see 10 CFR 55.59(c)(3)(iv)]. * The requalification program should include provisions for evaluating of operators [see 10 CFR 55.59(cX4)] that include written examinations, observation and evaluation of operator performance, and simulation of emergency or abnormal conditions. * Written examinations should be used to determine operators' knowledge of subjects covered in the requalification lectures' and abnormal and emergency procedures; They should be used to determine areas where retraining is needed. The written examination should contain a sample of the items specified in 10 CFR 55.41 and 55 43 as appropriate to the facility and the operators. * The operating test should require the operator to demonstrate an understanding of and the ability to perform the actions necessary for a sample of the items specified in 10 CFR 55.45(aX2-13) as appropriate to NURBG-1537,PuT2 12-12 REV 0,2196 NUREG- 1537, PART 2 12-12 REV 0, 2/96
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NUREG-1537, Part 2 Guidelines for P
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AVAILABILlTY NOTICE Availability of
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NUREG-1537, Part 2, has been reprod
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Page 4 REACTOR DESCRIPTION ........
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- | CON1, Page 12.6 Records .......
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ABBOEVW7!NS IAEA International Atom
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INTRODUCTION Background Ts document
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NTRODUCMON accidents, since the maj
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INTRODUCnION reviewers dealing with
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IRODUCriON accident consequences. T
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1 THE FACILITY Chapter 1 of the saf
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* safety criteria proposed by the a
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THE FACILITY SAR. The technical spe
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Evaluaton Findings NRC does not wri
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THE FACILTIY Applicants are expecte
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* assumed inventory of fission prod
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ThE ForAaXy agreement with the Depa
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Appendix 1.1 Introduction from NURE
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Appendix 1.2 DOE Letter to NRC Conc
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2 SIT CHARACTERISCS This chapter pr
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SnE CHARAcrmusncs * The demographic
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SIE CHARAcXERIcs * historical seaso
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SrYI CHARAcrIsnTc other water-induc
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SrnE CHARAcYmusna * The geologic fe
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3 DESIGN OF STRUCTURES, SYSTEMS, AN
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DESIGN OF STRUCTURES, SYSTEM, AND C
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DESIGN OF SRUCrURES Sysms. AND COMP
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Evasion Findings - DESIGN OF STRucn
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DESIGN OF STRnUtURES, SYSTEMS, AND
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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
Page 161 and 162: AuNARY SYSTEMS * No function or mal
Page 163 and 164: CHAPTER 10 accidents including malf
Page 165 and 166: CHAPrER 10 Areas of review should i
Page 167 and 168: CHAPTER 10 dimensions, materials, a
Page 169 and 170: CHAPt 10 integrity during all antic
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Page 173 and 174: 11 RADIATION PROTECTION-PROGRAM AND
Page 175 and 176: RADIAnON PRoTEcnoN PROGRAM AND WAST
Page 177 and 178: RADiAnoN PROTECTON PROGRAM AND WAST
Page 179 and 180: Acceptance Criteria RADIATIoN PRtow
Page 181 and 182: RADIATION PROTECION PROGRAM AND WAS
Page 183 and 184: RADIAnON PRoTECTION PROM AND WASTE
Page 185 and 186: RADAION PROTECTnON PRoORAmAND WAsTE
Page 187 and 188: RADIATION PRtowCioN PRoGRAm AND WAS
Page 189 and 190: * radiation monitors, alarms and sa
Page 191 and 192: RADIATnON PROTECrON PRORAM AND WAsT
Page 193 and 194: . RADiuTION PROTEcoN PROGRAM AND WA
Page 195 and 196: I - - RADiA11ON PRCoECnON PROCRAM A
Page 197 and 198: Revew Procedures RADIATINo PRoTEoN
Page 199 and 200: RADiiAoNPRaorcnoN PROGRAM AND WASTE
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Page 203 and 204: CHAPTER 12 day-to-day operation of
Page 205 and 206: CHA'rER 12 12.2 Review and Audit Ac
Page 207 and 208: CHAPTER 12 staff has determined tha
Page 209 and 210: CHAPE 12 to correct and prevent rec
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Page 215 and 216: CHATRi 12 operator skills and knowl
Page 217 and 218: CHAPTER 12 applicant's safety analy
Page 219 and 220: Appendix 12.1 Environmental Conside
Page 221 and 222: APPENDvc 12.1 Chemical and sanitary
Page 223 and 224: APPENDix 12.1 Conclusion The staff
Page 225 and 226: CHAPTER 13 The information in this
Page 227 and 228: CHAPSER 13 * The single malfunction
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Page 237 and 238: CHAPTDl 13 Bibliography Non-Power R
Page 239 and 240: CHAPShR 13 U.S. Nuclear Regulatory
Page 241 and 242: 14 TECHNCAL SPECIFICATIONS This cha
Page 243 and 244: TEcHnICAL SpEcmcAnoms * The staff h
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Page 249 and 250: CHAP~i~tIS Environmental Review Pro
Page 251 and 252: CHAPD 16 system; engineered safety
Page 253 and 254: CHAF1a 16 Medical therapy at non-po
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Page 257 and 258: CHAEW 16 * Requirements for reporti
Page 259 and 260: 17 DECOMMISSIONING AN) POSSESSION-O
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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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