NUREG-1537, Part 2 - NRC

More documents

Recommendations

Info

APPENDX 1 8.1 14 TECHNICAL SPECIFICATIONS Areas of Review 10 CFR 50.36 requires that the non-power reactor operating licenses contain technical specifications for the specific facility as an appendix to the license. ANSI/ANS 15.1-1990 is a specific standard developed with <strong>NRC</strong> support to guide the format and content for non-power reactor technical specifications. Chapter 14 of the format and content guide contains additional guidance on technical specifications. The areas of review for HEU to LEU conversion are the technical specifications and their bases that address parameters related to the fuel, its safety limits, and core reactor physics parameters dependent on fuel characteristics. If the replacement LEU fuel were fabricated exactly like the HEU fuel and from the same materials, the only differences in reactor parameters would result from the uranium-235 enrichments. The technical specifications should describe fuel parameters that are essential to the safety analyses for the licensed HEU-fueled reactor. The technical specifications should be reviewed for consistency with the proposed LEU-fueled reactor. Acceptkmce Criteria Acceptance criteria should be based on the following considerations: Revised technical specifications should state the minimum changes required by differences in characteristics of the HEU and LEU fuels. For example, the revised technical specifications should accurately specify the uranium enrichment, the chemical and material form of the uranium in the fuel, and cladding materials and dimensions. The revised technical specifications also should include the safety limits, limiting safety system settings, reactor physics parameters, and other safety-related parameters for the proposed LEU-fueled reactor. The bases for any changed technical Specifications should be traced to the LEU conversion safety analysis discussions and analysis from which they are derived. The format and content ofthe LEU technical specifications should not be different from those of the HEUfueled reactor, except as required by the fuel conversion. The format should follow ANSIVANS 15.1-1990. Revew Proceidres The reviewer should compare the proposed technical specifications for the LEUfueled reactor with those for the existing HEU. The reviewer should compare the proposed changes in technical specifications with the bases and with the reactor analyses in the SAR that employ or derive them The reviewer should compare the proposed changes in specifications with other tabulations of fuel and core NLJR.EG-1 537. PART 2 54 REV. 0. 2i96 <strong>NUREG</strong>-15S37. PART2 54 REV.0, 2/96
BEU TO LEU COPvERSION characteristics. The reviewer should compare the format of the proposed technical specifications with Chapter 14 of the format and content guide, the content with 10 CFR 50.36, and the specifications with the technical specifications for similar non-power reactors that have been converted from the use of HEU fuel. Evaluation Findings This section of the SAR should contain sufficient information on technical specifications to support the following types of conclusions, which will be included in the staffs safety evaluation report: * The proposed changes in technical specifications are the minimum required by the conversion from BEU to LEU. * The proposed technical specifications for the LEU-fueled reactor are consistent with the dynamic and safety analyses that have been reviewed and accepted. They provide assurance that the risks to the health and safety of the public from the LEU-fueled reactor will not be significantly greater than from the existing HEU fueled reactor and are acceptable. 15 OTBER LICENSE CONSIDERATIONS This section includes some considerations and issues that might not be completely covered in other chipters. The examples given below are typical topics that should be considered, but additional topics may be necessary on a case-by-case basis. The reviewer should verify that the information submitted is consistent with the guidance in Chapter 15 of the fornat and content guide, as supplemented below. 15.1 Prior Utilization of Reactor Components Two issues worthy of additional comment follow: * Safety limits and resistance to failure of the fuel may be based on assumptions concerning the softening temperatures, burnup, cladding thickness, and strength of materials. The licensee should provide assurance that these parameters have not been changed significantly by prior use or storage and that the alloy or composition specifications of ihe rmateiials are consistent with the assumptions in the analyses. * Thermal-hydraulic analyses require knowledge of material composition, thickness, and heat conductivity. For pulsing reactors, heat capacity and temperature coefficients of reactivity also are essential parameters. The licensee should provide assurance that prior use or storage has not changed REv. 0. 2/96 55 STAXARD REViE 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 and 12:
ABBOEVW7!NS IAEA International Atom
Page 13 and 14:
INTRODUCTION Background Ts document
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
Page 63 and 64:
CHAPTER 4 * The control rod design
Page 65 and 66:
CHAPTER4 * materials * compatibilit
Page 67 and 68:
CHAPrER4 when starting the reactor
Page 69 and 70:
CHAPT 4 * The applicant has justifi
Page 71 and 72:
CHAFtE4 characteristics of the reac
Page 73 and 74:
CHAPTER4 Review Procedures The revi
Page 75 and 76:
CHAPrER4 calculational models and a
Page 77 and 78:
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 and 130:
Review Procedures INTUMENTATION AND
Page 131 and 132:
- -- IxStRUMwnTAToN AND CONTRoL Sys
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
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
Page 201 and 202:
RADLATnON PRoTCTON PROGRAM AND WAST
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
Page 211 and 212:
CHArER 12 12.6 Records Areas of Rev
Page 213 and 214:
CHAPrER 12 * requalification docume
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
Page 229 and 230:
CHITER 13 (c) (For high-powered rea
Page 231 and 232:
CHAPTER 13 or * protracted malfunct
Page 233 and 234:
CHAPTER 13 * With natural-convectio
Page 235 and 236:
CHAPTER 13 (If the MHA is not afuel
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
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
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
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
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 and 292: HEU To LEU CoNvEaswoN since the las
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
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: Evaluation Findings BEU To LEU Comv
Page 345 and 346: HEU TOLEU CONVON American National
Page 347 and 348: HEU TO LEU CONVERSION U.S. Nuclear
show all

NUREG-1537, Part 2 - NRC

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?