NUREG-1537, Part 2 - NRC

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CHAPT 7 7.5 Engineered Safety Features Actuation Systems Non-power reactors can generally be designed and operated so they pose an acceptably small or insignificant radiological risk to the public. If the SAR analyses show that no unacceptable radiation doses would result from any postulated accident, even without consequence mitigation, such a facility need not include ESFs. The reviewer should, therefore, study Chapter 6, 'Engineered Safety Features," and Chapter 13 of the SAR to determine if there is a requirement for ESFs and their related ESF actuation system. The guidance in this section applies to any non-power reactor for which an ESF is required. Areas of Review The reviewer should evaluate the information in Chapter 6 describing the ESFs, the scenarios of the postulated accidents in Chapter 13 which involve the use of an ESF, and the detector channels that sense the need for mitigation of possible consequences. The information to be reviewed in this section should also include the design criteria of each ESF actation system, and the design bases and functional requirements for the ESF actuation systems. Additional information for review should include details of the design and operating characteristics of the actuation systems such as the following:. * logic and schematic diagrams * description of instruments, computer hardware and software, electromechanical components, detector channels, trip devices and set points * discussion of the bases of technical specifications, including surveillance tests and intervals that are designed to ensure operability Acceptance Criteria Acceptance criteria for ESF actuation systems should include the following considerations: * The engineering design of ESF actuation systems and the components procured for them should be of high quality to ensure reliable operation. This quality is essential because these systems are designed to mitigate the consequences of postulated accidents. * The ESF actuation system should be designed not to fail or operate in a mode that would prevent the RPS from performing its designed function, or prevent safe reactor shutdown. NUREG-1537, PART 2 7-14 RE 0, 2/96
- -- IxStRUMwnTAToN AND CONTRoL SysTEM * .The ESF actuation system should be designed to assume a safe state on loss of electrical power. * 'The range and sensitivity ofESF actuation system sensors should be sufficient to ensure timely and accurate signals to the actuation devices. * The equipment should be designed to operate reliably in the ambient environment until the accident has been brought to a stable condition. * The equipment should be designed to be readily tested and calibrated to ensure operability. * Technical specifications including surveillance tests and intervals should ensure availability and operability of the ESF actuation system. * ESF actuation systems should be designed to be operable whenever an accident could happen for which the SAR shows consequencie itigation is necessary. * Hardware nd software for computerized systems'should meet the guidelines of IEEE 74.3.2-1993 and RG 1.152, Revision 1, and software should meet the guidelines of ANSI/ANS 10.4-1987 that'apply to nonpower reactor systems. ANSI/ANS 15.15-1978 and draft ANSI/ANS 15.20 are general guides for the design, implementation, 'and evaluation of I&C systems for non-power reactors and should be used where applicable. * -Consult NRC Generic Letter 95-02 for I&C systems that are being upgraded to systems based on digital technology.- Review Procedres The reviewer should compare the design criteria and bases of the ESF actuations system with the designs of the ESFs and the accident scenarios and possible consequences. The reviewer should also compare the design and functional descriptions of the ESF actuation system with the acceptance criteria'and with applicable criteria and functions discussed in Chapters 6 and '13. The reviewer should obtain the assistance of experts in the I&C Branch to review computer Systems. Evaluation Findings This section of the SAR should'contain'sufficient information to support the following types of conclusions, which will be included in the staffs safety evaluation report: ..REV. 0, 2/96 7-15 STANDARDREVIEWPLAN
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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
Page 79 and 80: CHAPTER 4 4.5.2 Reactor Core Physic
Page 81 and 82: CHAPTER 4 included them in the tech
Page 83 and 84: CHAPTER. 4 Evaluation Findings This
Page 85 and 86: CHAPTER 4 For a pulsing reactor, li
Page 87 and 88: CHAPTER5 This chapter gives the rev
Page 89 and 90: CHAPTER S The descriptions and disc
Page 91 and 92: CHAPTRS acceptable radiological dos
Page 93 and 94: CHAPTER 5 dissipation is accomplish
Page 95 and 96: CHAPTER 5 5.4 Primary Coolant Clean
Page 97 and 98: CHAPTERS achieved. The design ensur
Page 99 and 100: CHAPTERS Ewauation Findings This se
Page 101 and 102: CHAPTR5 Evaluation Findings This se
Page 103 and 104: CHAPTER5 analyzed. The reviewer sho
Page 105 and 106: CHAPTER 6 The accident analyses by
Page 107 and 108: CHAmR 6 6.1 Summary Description In
Page 109 and 110: CtwxR 6 Acceptance CnItenad The acc
Page 111 and 112: I CUAPTER6 Higher power non-power r
Page 113 and 114: CHAPT6 * The design that should red
Page 115 and 116: CHArr't 6 * The ECCS should not int
Page 117 and 118: 7 INSTRUMENTATION ANDCONTROL SYSTEM
Page 119 and 120: INSTRumENTAIroN AND CoNIROL SYmtm s
Page 121 and 122: INSRUMENTAnON AND CONTROL SYSTEMS *
Page 123 and 124: _ INsTRumE3nArroN AND CONTROL SYSTE
Page 125 and 126: INSIIuMETrATnON MD CoNmoL SYSTEm *
Page 127 and 128: Acceptance Cnteria INSFRUMENTAMON A
Page 129: Review Procedures INTUMENTATION AND
Page 133 and 134: * . personnel and equipment protect
Page 135 and 136: -.... - . INSTRUMENTATION AND CONTR
Page 137 and 138: INSRUMENATION AD CONIMOL SYSTMS * c
Page 139 and 140: INSgtmrNTA1ION AND CoNmoL SySIEmm A
Page 141 and 142: CHAPrER 8 * The system should be de
Page 143 and 144: CHAPTER8 Acceptance Criteria ) The
Page 145 and 146: 9 AUXILIARY SYSTEMS This chapter co
Page 147 and 148: AUXILIARY SYSEms * 0 CFR Part 20 an
Page 149 and 150: . AuxiLARY SYSTEMS * Methods for in
Page 151 and 152: Evaluation Findings AuxnARY SYSTEMS
Page 153 and 154: Rewew Procedures AUXILIARY SYSTEMS
Page 155 and 156: AuxLiARY SYSTEMS * The facility com
Page 157 and 158: Revew Procedures AUXLARY SYSmEm The
Page 159 and 160: 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
Page 171 and 172: I CHAPTER 10 The applicant should l
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
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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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