NUREG-1537, Part 2 - NRC

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APPENDIX 18.1 Review Procedures The reviewer should compare any changed environmental interactions between the converted LEU facility and the existing HE faciity. The reviewer should evaluate the discussions in the licensee's submittal about any changed interactions vith characteristics of the site, either in kind or in magnitude, that results from the fuel conversion. The conversion of the reactor should not change the conclusions about the suitability of the site for operation of the reactor with the LEU fuel. Changes in the impact on site characteristics due to conversion may be compensated for by changes in facility design which should be listed and referenced to applicable sections of the SARI Evauafion Findngs This section of the SAR should contain sufficient information to support one of the following types of conclusions, which will be included in the staffs safety evaluation report: * The site characteristics and associated environmental hazards will not be significantly changed by the reactor conversion, so there will be' no decrease in the suitability of the present site for continued operation of the reactor. The conclusions of site suitability reached in the SAR and the safety evaluation report for the HEU operating license remain valid for the > LEU-fueled reactor, as proposed. * The impact on the site characteristics and associated environmental hazards due to conversion have been identified. Faclity-structures, systems, and components have been analyzed in subsequent sections of the safety analysis to demonstrate acceptable design to compensate for changes in site inpact. 3 DESIGN OF STRUCTURES, SYSTEMS, AND COMPONENTS Areas of Review This section of the SAR should contain information on the design bases of faicility structures, systems, and components, and a discussion of any modifications in the design bases for the BEU to LEU conversion; This section should reference all significant standards and guides applicable to the conversion, including rules and regulations, siaff reports (NUREGs), regulatory guides, and the American National Standards Institute/American Nuclear Society (ANSI/ANS) standards used to design all proposed modifications to the reactor facility. This section NtJREG-1537,PART2 4 REV. 0. 296 NUREG- 1537, PART 2 4 REV. O. 2/96
HEU To LEU CONVERSION should also describe how the facility is designed to accommodate potential wind, water, and seismic damage. The information should note the subsequent sections in the SAR in which the modifications to design bases are used.- It should consider the safety-related consequences of all of the natural and manmade external forces and events noted in Section 2 of the SAR, and how the structures, systems, and components limit the potential consequences of operation to the environment and the surrounding population. The emphasis should be to compare the design requirements from the proposed LEU-fueled reactor with the HEU-fueled reactor. The reviewer should evaluate any design changes from conversion-related changes in structures, systems, components, and reactor operating characteristics. It is not expected that BEU to LEU conversions should raise the need for design bases changes to structures, systems, and components. If no changes are made to the design bases for structures, systems, and components, the SAR should so state and the reviewer should verify that there is no change. Acceptance Criteria Acceptance criteria should be based on the following considerations: * The design bases for the faiity structures, systems, and components have been compared and are the same for the HEU and LEU facilities. * Changes in design bases for the LEU-fueled reactor facility structures, systems and components from those of the lIEU facility were noted. The associated sections in which these changes in the design bases are used in the SAR is specified. Reiew Procedures The reviewer should evaluate design bases changes to structures, systems, and components required by conversion from HEU fuel. The reviewer should ensure that changes are compared between the HEU and LEU facilities, and should verify that reference is made to the associated safety analyses in subsequent sections. Evaluation Findings This section of the SAR should contain sufficient information to support one of the following types of conclusions, which will be included in the staffs safety evaluation report: REv 0.2/96 S SmNIMw REVIEW PLAN REV 0, 2/96- as STANDARD REVEM %PLAN
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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
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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
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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
Page 255 and 256: CHAPS 16 treatment. The door or ent
Page 257 and 258: CHAEW 16 * Requirements for reporti
Page 259 and 260: 17 DECOMMISSIONING AN) POSSESSION-O
Page 261 and 262: - DEcOM iSNNG AND PossEssION-ONLY A
Page 263 and 264: DEcOmm oNG ANDPossEsoN-ONLYAmm .ES
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Page 269 and 270: DEcoMMiSsIoNING AND PossEssioN-ONLY
Page 271 and 272: 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
Page 277 and 278: DECCMMISSIONI0PLANS The DP should s
Page 279 and 280: DEco wIssioNDJGPLA controls to comp
Page 281 and 282: - - ~DECOM SSOKMGPLANS facility. Su
Page 283 and 284: 8 ENVIRONMENTAL REPORT ..DECOMOM=ON
Page 285 and 286: 18 HIGH1LY ENRICHED TO LOW-ENRICHED
Page 287 and 288: NIowLy ENmI ToLow-EmIAEDURAwrum CoN
Page 289 and 290: Standard Review Plan and Acceptance
Page 291: HEU To LEU CoNvEaswoN since the las
Page 295 and 296: HEU TO LEU CoNVERSION this section,
Page 297 and 298: 4.2.1 Fuel Elements HEU TO LEU CONV
Page 299 and 300: Evaluation Findings (Sections 4.2.1
Page 301 and 302: Acceptance Criteria _HEU TOLEU CoNv
Page 303 and 304: - HEU TO LEU CONVERSON Calculations
Page 305 and 306: HEU TO LEU CONVERSION should be dis
Page 307 and 308: HEU TO LEU CoNvERSoN *Acceptable ch
Page 309 and 310: BEU To LEU CoNvEasioN Generally, co
Page 311 and 312: Evluation Findings HEU TOLEU CONVER
Page 313 and 314: ... HEU TO LEU CONVERSION * The coo
Page 315 and 316: Accepktace Criteria HEU To LEU CONV
Page 317 and 318: 9.4 Fuel Element Handling and Stora
Page 319 and 320: 10 EXPERIMENTAL FACILITIES AND UTIL
Page 321 and 322: 11.1 Radiation Protection Program A
Page 323 and 324: *HEU TOLEU CONVERSION The areas of
Page 325 and 326: BEU TO LEU CONVERSION specification
Page 327 and 328: - - - - HEU To LEU CoNvmESioN relia
Page 329 and 330: HEUrTo LEU Cowv~ptstoN design ofthe
Page 331 and 332: BIEU To I.EU Col~vERSoN MHA, the ba
Page 333 and 334: HEU To LEU CoNvRiow acceptable assu
Page 335 and 336: Review Procedures -- HEU TOLEU CONV
Page 337 and 338: 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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