NUREG-1537, Part 2 - NRC

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APPENDix 18.1 1.4 Summary of Operating License, Technical Specifications, and Procedural Changes The reviewer should verify that any changes, as a result of the fuel conversion, proposed to the facility operating license, the technical specifications, or operating procedures are briefly listed with a reference to the SAR sections in which they are discussed in more detail. Such specific changes may include (1) the uranium-235 possession limits for LEU fuel in the license, (2) license provisions to possess both HEU and LEU fuel at the same time if need be, and (3) technical specifications changes, including such LEU fuel design parameters as dimensions, materials, enrichments, number of plates and elements, heat fluxes and power densities, coolant flow rates, and reactivity coefficients. 1.5 Comparison With Similar Facilities Already Converted The reviewer should ensure that the licensee has compared its proposed LEU reactor with similar non-power reactor facilities that have already undergone a conversion from HEU to LEU fuel, if there are any such similar reactors. The licensee should have identified (1) the similarities and differences between the ficilities in design, construction, testing, and onperaion; (2) any problems that wee r identified and resolved at the other facilities; and (3) plans to address such problems at their facility. 2 SMIE CHARACTERISTICS Areas of Review This section of the SAR should describe the environmental factors that could affect the suitability of the site for the location and operation of the non-power reactor. The areas of review should include the geography, demography, meteorology, geology, seismology, hydrology, and nearby transportation, industrial, and military facilities, and their interaction with the reactor. These interactions are of two general types: (1) the effects that the reactor could have on the environment and the population surrounding the reactor site (2) the effects that environmental factors could have on the reactor facility that affect its safe operation or shutdown Generally, there should be no change to these topics with a conversion from HEU to LEU fuel. However, it is possible that new information has become available
HEU To LEU CoNvEaswoN since the last SAR revision. For example, it is possible that demography, and nearby transportation, industrial, and military facilities around the reactor facility have changed since the last SAR revision. If these changes are significant to the safety analysis of the reactor or if the licensee wants the SAR to be Current, these new fictors should be justified by the licensee and submitted to NRC as an update to the HEU SAR before the LEU SAR is submitted. Changes to the site characteristics due to the passage of time or due to the discoveiy of new information unrelated to the conversion cannot be approved by NRC using the conversion order. The reviewer should ensure that the conversion application does not result in the NRC approving changes to site characteristics by enforcement order. Most non-power reactors release small quantities of radioactive argon-41 to the unrestricted area during normal operations. Any changes in this and other radioactive effluents resulting from the proposed conversion should be considered in this section and analyzed in Section 11.- Comparisons, between the existing HEU-fiueled reactor and the proposed LEU-fueled reactor, of potential doses to the public considering current population distributions should be made in Section 11 of this safety analysis, as well as comparisons with regulatory requirements to account for any changes since the most recent revision of the SAR. Information should be provided on any environmental effects at the site that have the potential for causing damage, or other significant effects due to the conversion to the proposed LEU-fueled reactor. If changed, the information should include analyses of the impacts on reactor safety and response to such site-dependent factors as hydrology, geography, demography, geology, meteorology, seismology, and manmade accidental events. The analysis of these changes may be listed in this section and referenced to other sections of the SAR where the design or operating criteria of the specific systems, structures, or components are analyzed to address such changes. Unless the informiation indicates significant changes in environmental impacts, a separate environmental report need not be provided. Acceptance Criteria The site characteristics should be specified to be considered in the facility design changes as documented in subsequent sections ofthe'SAR. Additional general guidance may be found in ANSI/ANS 15.7. Since changes in site characteristics should have already been considered for the HEU reactor, there should not be any significant difference between HEU and LBU site characteristics. REV. 0, 2/96 3 STANDMW REVIEW PLAN REV. 0.2n96 3 STANDARD REVIEW 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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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
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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
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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
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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: Standard Review Plan and Acceptance
Page 293 and 294: HEU To LEU CONVERSION should also d
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
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Page 335 and 336: Review Procedures -- HEU TOLEU CONV
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Page 339 and 340: 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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