ML13289A273
| ML13289A273 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/04/2013 |
| From: | James Shea Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13289A273 (16) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 October 4, 2013 10 CFR 50.4 10 CFR 50.71 (e)(4)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Browns Ferry Nuclear Plant - Updated Final Safety Analysis Report, Amendment 25 Pursuant to the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 50.71, "Maintenance of Records, Making of Reports," paragraph (e)(4), the Tennessee Valley Authority (TVA) is submitting Amendment 25 of the Updated Final Safety Analysis Report (UFSAR) for the Browns Ferry Nuclear Plant (BFN).
Amendment 25 of the BFN UFSAR is a 24-month update that reflects editorial corrections, changes, and analyses pursuant to 10 CFR 50.59, "Changes Tests, and Experiments," to the facility, which were in effect through July 1, 2013. All UFSAR pages issued as a result of this update are clearly delineated with a "BFN-25" in the page header and a revision bar is shown in the right margin next to the specific change.
The summaries of evaluations of these changes made under the provisions of 10 CFR 50.59, will be provided to the NRC in separate correspondence by November 30, 2013.
The Enclosure to this letter contains one (1) Compact Disk - Recordable (CD-R) of the BFN UFSAR, Amendment 25. TVA has also included a listing of the UFSAR files and their size in the enclosure. Please note that some files do not have embedded fonts; however, these files are from a;scanned source and are thus. consistent with Section 2.23 of the "Guidance for Electronic Submissions to the NRC, Revision 6.1." Chris Bennett of the BFN Site Licensing staff verified this with Kenny D. Nguyen of the NRC staff on September 11, 2013.
TVA has determined that some of the information contained on the CD-R is considered to be sensitive unclassified non-safeguards information. As such, the enclosed CD-R is labeled "Tennessee Valley Authority, Browns Ferry Nuclear Plant, Updated Final Safety Analysis Report, Amendment 25, Non-Public Version." This CD-R submittal of the entire BFN UFSAR supersedes all previously submitted hard copies and CD-R copies of the document.
Printed on reCycled paper
U.S. Nuclear Regulatory Commission Page 2 October 4, 2013 Pursuant to the requirements of 10 CFR 54.37, "Additional Records and Recordkeeping Requirements," paragraph (b), TVA has revised Appendix 0 of the BFN UFSAR to include newly identified systems, structures, and components that would have been subject to an aging management review or evaluation of time-limited aging analyses. Specifically, the Discharge Control Structure is a newly identified structure that meets the scope of 10 CFR 54.4(a)(2) and Gate Structure Number 2 is a newly identified structure that meets the scope of 10 CFR 54.4(a)(1).
The summary information provided in Appendix 0 for the newly identified systems, structures, and components is consistent with the requirements of 10 CFR 54.21(d). Using guidance provided by an NRC license renewal Frequently Asked Question, the technical details of the newly identified systems, structures and components are addressed in separate correspondence to be submitted concurrently with this UFSAR submittal.
This letter certifies that the information provided in the enclosed Amendment 25 accurately reflects the information and analyses from the changes made since the issuance of the previous amendment.
There are no new regulatory commitments contained in this letter. If you have any questions, please contact Tom Hess at (423) 751-3487.
Res *tfully, JW Shea
'Atce resident, Nuclear Licensing
Enclosures:
CD-ROM Containing Browns Ferry Nuclear Plant Updated Final Safety Analyses Report, Amendment 25, Non-Public Version and a Listing of the UFSAR Files, Including File Size
U.S. Nuclear Regulatory Commission Page 3 October 4, 2013 cc (w/Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1, 2, and 3 Updated Final Safety Analysis Report (UFSAR)
Amendment 25 This enclosure provides the following:
- One CD-ROM Copy of Amendment 25 of the Browns Ferry Nuclear Plant UFSAR, Non-Public Version
- Listing of the Browns Ferry Nuclear Plant UFSAR, Amendment 25 files, including file size
BROWNS FERRY NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR), AMENDMENT 25 CHAPTERS 1 THROUGH 14 AND APPENDICES A THROUGH 0 LIST OF FILES ON DISK (ALL LISTED FILES - NON-PUBLIC VERSION)
FILE NAME FILE SIZE (KB) 01 BFN FSAR Amendment 25 EPL.pdf 83 001 BFN FSAR Table of Contents.pdf 47 CHAPTER 1 - INTRODUCTION AND
SUMMARY
002 1.1 Project Identification.pdf 42 003 1.2 Definitions.pdf 60 004 1.2 Figure - Definitions.pdf 462 005 1.3 Methods of Technical Presentation.pdf 41
-006 1.3 Table - Methods of Technical Presentation. pdf 71
-007 1.3 Figure - Methods of Technical Presentation. pdf 94 008 1.4 Class of BWR Systems Criteria Requirements for Safety Evaluation.pdf 38 009 1.4 Table - Class of BWR Systems Criteria. Requirements for Safety Evaluation.pdf 58 010 1.5 Principal Design Criteria.pdf 55 011 1.6 Plant Description.pdf 77 012 1.6 Figure - Plant Description.pdf 5043 013 1.7 Comparison of Principal Design Characteristics.pdf 37 014 1.7 Table - Comparison of Principal Design Characteristics.pdf 67 015 1.8 Summary of Radiation Effects.pdf 36 016 1.9 Plant Management.pdf 31 017 1.10 Quality Assurance Program.pdf 33 018 1.11 Identification Resolution of Construction Permit Concern - Summary.pdf 38 019 1.11 Table - Identification Resolution of Construction Permit Concern - Summary.pdf 52 020 1.12 General Conclusions.pdf 37 021 1 -Table of Contents.pdf 40 CHAPTER 2 - SITE 022 2.1 Summary Description.pdf 34
-0232.2 Site Description.pdf 41 024 2.2 Table - Site Description.pdf 85
-025 2.2 Figure - Site Description.pdf 782 1
FILE NAME FILE SIZE (KB) 026 2.3 Meteorology.pdf 64 027 2.3 Table - Meteorology.pdf 122 028 2.3 Figure - Meteorology.pdf 1695 029 2.4 Hydrology, Water Quality, and Aquatic Biology.pdf 58 030 2.4 Table - Hydrology, Water Quality, and Aquatic Biology.pdf 43 031 2.4 Figure - Hydrology, Water Quality, and Aquatic Biology.pdf 782 032 2.4A Probable Maximum Flood.pdf 69 033 2.4A Table - Probable Maximum Flood.pdf 449 034 2.4A Table 1 - Maximum Possible Flood.pdf 440 035 2.4A Figure - Maximum Possible Flood.pdf 5417 036 2.5 Geology and Seismology.pdf 71 037 2.5 Table - Geology and Seismology.pdf 49 038 2.5 Figure - Geology and Seismology.pdf 2093 039 2.6 Environmental Radiological Monitoring .Program.pdf 38 040 2 Table of Contents.pdf 58 CHAPTER 3 - REACTOR 041 3.1 Summary Description.pdf 38 042 3.2 Fuel Mechanical Design.pdf 56 043 3.2 Table - Fuel Mechanical Design.pdf 27 044 3.2 Figure - Fuel Mechanical Design.pdf 387 045 3.3 Reactor Vessel Internals Mechanical Design.pdf 74 046 3.3 Table - Reactor Vessel Internals Mechanical Design.pdf 38 047 3.3 Figure - Reactor Vessel Internals.pdf 1020 048 3.4 Reactivity Control Mechanical Design.pdf 102 049 3.4 Figure - Reactivity Control Mechanical Design.pdf 2332 050 3.5 Control Rod Drive Housing Supports.pdf 46 051 3.5 Figure - Control Rod Drive.pdf 420 052 3.6 Nuclear Design.pdf 59 053 3.6 table - Nuclear Design.pdf 41 054 3.6 Figure - Nuclear Design.pdf 390 055 3.7 Thermal and Hydraulic Design.pdf 144 056 3.7 Figure - Thermal and Hydraulic Design.pdf 624 2
FILE NAME FILE SIZE (KB) 057 3.8 Standby Liquid Control.pdf 60 058 3.8 Figure - Standby Liquid Control.pdf 859 059 3 Table of Contents.pdf 43 CHAPTER 4 - REACTOR COOLANT SYSTEM 060 4.1 Summary Description.pdf 39 061 4.2 Reactor Vessel and Appurtenances Mechanical Design.pdf 75 062 4.2 Table - Reactor Pressure Vessel Materials.pdf 45 063 4.2 Figure - Reactor Vessel and Appurtenances Mechanical Design.pdf 1165 064 4.3 Reactor Recirculation System.pdf 56 065 4.3 Table - Reactor Recirculation System.pdf 46 066 4.3 Figure - Reactor Recirculation System.pdf 958 067 4.4 Nuclear Steam Pressure Relief System.pdf 61 068 4.4 Table - Nuclear Steam Pressure Relief System.pdf 38 069 4.4 Figure - Nuclear Steam Pressure Relief System.pdf 1230 070 4.5 Main Steam Line Flow Restrictor.pdf 40 071 4.5 Figure - Main Steam Line Flow Restrictor.pdf 287 072 4.6 Main Steam Isolation Valves.pdf 57 073 4.6 Figure - Main Steam Isolation Valves.pdf 419 074 4.7 Reactor Core Isolation Cooling.pdf 48 075 4.7 Table - Reactor Core Isolation Cooling.pdf 41 076 4.7 Figure - Reactor Core Isolation Cooling.pdf 1395 077 4.8 Residual Heat Removal .pdf 59 078 4.8 Table - Residual Heat Removal.pdf 44 079 4.8 Figure - Residual Heat Removal.pdf 421 080 4.9 Reactor Water Cleanup.pdf 41 081 4.9 Table - Reactor Water Cleanup .pdf 42 082 4.9 Figure - Reactor Water Cleanup .pdf 1970 083 4.10 Nuclear System Leakage Rate Limits .pdf 55 084 4.10 Figure - Nuclear System Leakage Rate.pdf 444 085 4.11 Main Steam Lines, Feedwater Piping and Drains.pdf 40 086 4.11 Figure - Main Steam Lines, Feedwater Piping and Drains.pdf 67 087 4.12 Inservice Inspection and Testing.pdf 38 3
FILE NAME FILE SIZE (KB) 088 4 - Table of Contents 46 CHAPTER 5 - CONTAINMENT 089 5.1 Summary Description.pdf 34 090 5.2 Primary Containment.pdf 155 091 5.2 Table - Primary Containment.pdf 90 092 5.2 Figure - Primary Containment.pdf 4346 093 5.3 Secondary Containment.pdf 93 094 5.3 Figure - Secondary Containment.pdf 1387 095 5 -Table of Contents.pdf 41 CHAPTER 6 - EMERGENCY CORE COOLING SYSTEM 096 6.1 Safety Objective.pdf 33 097 6.2 Safety Design Basis.pdf 36 098 6.3 Emergency Core Cooling.pdf 38 099 6.3 Table - Emergency Core Cooling.pdf 43 100 6.3 Figure - Emergency Core Cooling.pdf 389 101 6.4 Description.pdf 57 102 6.4 Table - Description.pdf 24 103 6.4 Figure - Description.pdf 1613 104 6.5 Safety Evaluation.pdf 83 105 6.5 Table - Safety Evaluation.pdf 68 106 6.5 Figure - Safety Evaluation.pdf 712 107 6.6 Inspection and Testing.pdf 41 108 6 Table of Contents.pdf 39 CHAPTER 7 - CONTROL AND INSTRUMENTATION 109 7.1 Summary Description.pdf 45 110 7.1 Figure - Summary Description.pdf 420 111 7.2 Reactor Protection System.pdf 78 112 7.2 Table - Reactor Protection System.pdf 42 113 7.2 Figure - Reactor Protection System.pdf 2278 114 7.3 Primary Containment Isolation.pdf 87 115 7.3 Table - Primary Containment Isolation.pdf 44 116 7.3 Figure - Primary Containment Isolation.pdf 1009 4
FILE NAME FILE SIZE (KB)
-117 7.4 Emergency Core Cooling Control.pdf 97
-118 7.4 Table - Emergency Core Cooling Control.pdf 46 119 7.4 Figure - Emergency Core Cooling Control.pdf 3646 120 7.5 Neutron Monitoring System.pdf 84 121 7.5 Table - Neutron Monitoring System.pdf 38 122 7.5 Figure - Neutron Monitoring System.pdf 1788 123 7.6 Refueling Interlocks.pdf 44
-124 7.6 Table - Refueling Interlocks.pdf 37
-125 7.6 Figure - Refueling Interlocks.pdf 420
-126 7.7 Reactor Manual Control System.pdf 58
-127 7.7 Table - Reactor Manual Control System.pdf 42 128 7.7 Figure - Reactor Manual Control System.pdf 506 129 7.7AB Rod Sequence Control.pdf 32 130 7.8 Reactor Vessel Instrumentation.pdf 48 131 7.8 Table - Reactor Vessel Instrumentation.pdf 45 132 7.8 Figure - Reactor Vessel Instrumentation.pdf 1873 133 7.9 Recirculation Flow Control.pdf 57 134 7.9 Figure - Recirculation Flow Control.pdf 31 135 7.10 Feedwater Control System.pdf 54 136 7.10 Figure - Feedwater Control System.pdf 763 137 7.11 Pressure Regulator and Turbine.pdf 46 138 7.11 Figure- Pressure Regulator and Turbine.pdf 436 139 7.12 Process Radiation Monitoring.pdf 55 140 7.12 Table - Process Radiation Monitoring.pdf 36 141 7.12 Figure - Process Radiation Monitoring.pdf 2423 142 7.13 Area Radiation Monitoring.pdf 41 143 7.13 Table - Area Radiation Monitoring.pdf 50 144 7.13 Figure - Area Radiation Monitoring.pdf 389 145 7.14 Drywell Leak Detection Radiation.pdf 37 146 7.15 Health Physics Laboratory.pdf 35 147 7.16 Process Computer System.pdf 53 148 7.16 Table - Process Computer System.pdf 25 5
FILE NAME FILE SIZE (KB) 149 7.16 Figure - Process Computer System.pdf 388 150 7.17 Deleted.pdf 28 151 7.17 Table - Deleted.pdf 24 152 7.17 Figure - Deleted.pdf 391 153 7.18 Backup Control System.pdf 44 154 7.19 Anticipated Transient Without Scram.pdf 45 155 7.20 Instrument Setpoint Methodology.pdf 44 156 7.20 Table - Instrument Setpoint Methodology.pdf 50 157 7 Table of Contents.pdf 53 CHAPTER 8 - ELECTRICAL POWER SYSTEMS 158 8.1 Summary Description.pdf 41 159 8.2 Generators.pdf 36 160 8.3 Transmission System.pdf 43 161 8.3 Figure - Transmission System.pdf 1629 162 8.4 Normal Auxiliary Power.pdf 79 163 8.4 Table - Normal Auxiliary Power.pdf 77 164 8.4 Figure - Normal Auxiliary Power.pdf 1659 165 8.5 Standby AC Power Supply.pdf 73 166 8.5 Table - Standby AC Power Supply.pdf 112 167 8.5 Figure - Standby AC Power Supply.pdf 31982 168 8.6 250-V DC Power Supply.pdf 49 169 8.6 Table - 250-V DC Power Supply.pdf 37 170 8.6 Figure - 250-V DC Power Supply.pdf 1296 171 8.7 120-V AC Power Supply.pdf 42 172 8.7 Figure - 120-V AC Power Supply.pdf 724 173 8.8 Auxiliary DC Power Supply.pdf 48 174 8.8 Table - Auxiliary DC Power Supply.pdf 37 175 8.8 Figure - Auxiliary DC Power Supply.pdf 391 176 8.9 Safety Systems Independence Criteria.pdf 57 177 8.9 Table - Safety Systems Independence Criteria.pdf 25 178 8.9 Figure - Safety Systems Independence Criteria.pdf 389 179 8.10 Station Blackout.pdf 39 6
FILE NAME FILE SIZE (KB) 180 8 Table of Contents.pdf 46 CHAPTER 9 - RADIOACTIVE WASTE CONTROL SYSTEMS 181 9.1 Summary Description.pdf 34 182 9.2 Liquid Radwaste System.pdf 52 183 9.2 Table - Liquid Radwaste System.pdf 49 184 9.2 Figure - Liquid Radwaste System.pdf 2945 185 9.3 Solid Radwaste System.pdf 45 186 9.3 Figure - Solid Radwaste System.pdf 391 187 9.4 Gaseous Radwaste System.pdf 25 188 9.5 Gaseous Radwaste System - Modified.pdf 61 189 9.5 Table - Gaseous Radwaste System - Modified.pdf 70 190 9.5 Figure - Gaseous Radwaste System - Modified.pdf 1175 191 9 Table of Contents.pdf 38 CHAPTER 10- AUXILIARY SYSTEMS 192 10.1 Summary Description.pdf 34 193 10.2 New Fuel Storage.pdf 40 194 10.2 Figure - New Fuel Storage.pdf 437 195 10.3 Spent Fuel Storage.pdf 56 196 10.3 Figure - Spent Fuel Storage.pdf 638 197 10.4 Tools and Servicing Equipment.pdf 54 198 10.4 Table - Tools and Servicing Equipment.pdf 36 199 10.4 Figure - Tools and Servicing Equipment.pdf 439 200 10.5 Fuel Pool Cooling and Cleanup.pdf 52 201 10.5 Table - Fuel Pool Cooling and Cleanup.pdf 41 202 10.5 Figure - Fuel Pool Cooling and Cleanup.pdf 1664 203 10.6 Reactor Building Closed Cooling.pdf 41 204 10.6 Table - Reactor Building Closed Cooling.pdf 69 205 10.6 Figure - Reactor Building Closed Cooling.pdf 534 206 10.7 Raw Cooling Water.pdf 39 207 10.7 Figure - Raw Cooling Water.pdf 2296 208 10.8 Raw Service Water.pdf 37 209 10.9 RHR Service Water.pdf 46 7
FILE NAME FILE SIZE (KB) 210 10.9 Figure - RHR Service Water.pdf 1206 211 10.10 Emergency Equipment Cooling Water.pdf 43 212 10.10 Figure - Emergency Equipment Cooling Water.pdf 917 213 10.11 Fire Protection System.pdf 34 214 10.11 Figure- Fire Protection System.pdf 391 215 10.12 Heating Ventilating and Air Conditioning.pdf 60 216 10.12 Figure - Heating Ventilating and Air Conditioning.pdf 1956 217 10.13 Demnineralized Water System.pdf 42 218 10.13 Figure - Demnineralized Water System.pdf 390 219 10.14 Control and Service Air.pdf 45 220 10.14 Figure - Control and Service Air.pdf 1284 221 10.15 Potable Water and Sanitary.pdf 32 222 10.16 Equipment and Floor Drainage.pdf 45 223 10.17 Process Sampling Systems.pdf 41 224 10.17 Table - Process Sampling Systems.pdf 42 225 10.17 Figure - Process Sampling Systems.pdf 995 226 10.18 Plant Communications System.pdf 47 227 10.18 Figure - Plant Communications System.pdf 726 228 10.19 Lighting System.pdf 36 229 10.20 Auxiliary Boiler System.pdf 43 230 10.21 Postaccident Sampling.pdf 43
-231 10.21 Table - Postaccident Sampling.pdf 39
-232 10.21 Figure - Postaccident Sampling.pdf 634 233 10.22 Auxiliary Decay Heat Removal.pdf 37 234 10.23 Hydrogen Water Chemistry.pdf 44 235 10 Table of Contents.pdf 47 CHAPTER 11 - POWER CONVERSION SYSTEMS 236 11.1 Summary Description.pdf 30 237 11.1 Figure - Summary Description.pdf 639 238 11.2 Turbine Generator.pdf 48 239 11.3 Main Condenser.pdf 44 240 11.4 Main Condenser Gas Removal.pdf 37 8
FILE NAME FILE SIZE (KB) 241 11.5 Turbine Bypass.pdf 36 242 11.6 Condenser Circulating Water.pdf 48 243 11.6 Figure - Condenser Circulating Water.pdf 1678 244 11.7 Condensate Filter Demineralizer.pdf 41 245 11.7 Figure - Condensate Filter Demineralizer.pdf 394 246 11.8 Condensate and Reactor Feedwater.pdf 43 247 11.8 Figure - Condensate and Reactor Feedwater.pdf 592 248 11.9 Condensate Storage.pdf 44 249 11.9 Table - Condensate Storage.pdf 37 250 11.9 Figure - Condensate Storage.pdf 741 251 11 Table of Contents.pdf 41 CHAPTER 12 -STRUCTURES AND SHIELDING 252 12.1 Summary Description.pdf 34 253 12.2 Principal Structures and Foundations.pdf 201 254 12.2 Table - Principal Structures and Foundations.pdf 142 255 12.2 Figure - Principal Structures and Foundations.pdf 5751 256 12.3 Shielding and Radiation.pdf 49 257 12.3 Table - Shielding and Radiation.pdf 32 258 12 Table of Contents.pdf 44 CHAPTER 13 - CONDUCT OF OPERATIONS 259 13.1 Organizational Structure for Conduct.pdf 37 260 13.2 Organization and Responsibility.pdf 43 261 13.2 Figure - Organization and Responsibility.pdf 393 262 13.3 Training Programs.pdf 35 263 13.4 Preoperational Test Program.pdf 120 264 13.4 Figure - Preoperational Test Program.pdf 426 265 13.5 Startup and Power Test Program.pdf 144 266 13.5 Table - Startup and Power Test Program.pdf 68 267 13.5 Figure - Startup and Power Test Program.pdf 607 268 13.6 Normal Operations.pdf 44 269 13.6 Figure - Normal Operations.pdf 390 9
FILE NAME FILE SIZE (KB) 270 13.7 Records.pdf 23 271 13.8 Operational Review and Audits.pdf 38 272 13.9 Refueling Operations.pdf 34 273 13.10 Refueling Test Program.pdf 57 274 13 Table of Contents.pdf 39 CHAPTER 14 - PLANT SAFETY SYSTEMS 275 14.1 Plant Safety Analysis.pdf 36 276 14.2 Unacceptable Safety Results for Abnormal Operational Transients.pdf 32 277 14.3 Unacceptable Safety Results for Accidents.pdf 393 278 14.4 Approach to Safety Analysis.pdf 56 279 14.4 Table - Approach to Safety Analysis.pdf 397 280 14.4 Figure - Approach to Safety Analysis.pdf 532 281 14.5 Analyses of Abnormal Operational Transients.pdf 158 282 14.5 Table - Analyses of Abnormal Operational Transients.pdf 406 283 14.5 Figure - Analyses of Abnormal Operational Transients.pdf 1972 284 14.6 Analysis of Design Basis Accidents.pdf 128 285 14.6 Table - Analysis of Design Basis Accidents.pdf 65 286 14.6 Figure - Analysis of Design Basis Accidents.pdf 781 287 14.7 Conclusions.pdf 393 288 14.8 Analytical Methods.pdf 462 289 14.8 Table - Analytical Methods.pdf 403 290 14.8 Figure - Analytical Methods.pdf 433 291 14.9 Dose Sensitivity Evaluation.pdf 400 292 14.9 Table - Dose Sensitivity Evaluation.pdf 401 293 14.10 Analyses of Abnormal Operational.pdf 428 294 14.10 Figure - Analyses of Abnormal Operational.pdf 1118 295 14.11 Analysis of Design Basis Accidents.pdf 483 296 14.11 Table - Analysis of Design Basis Accidents.pdf 404 297 14.11 Figure - Analysis of Design Basis Accidents.pdf 709 298 14 Table of Contents.pdf 47 10
FILE NAME FILE SIZE (KB)
APPENDIX A - CONFORMANCE OF AEC PROPOSED GENERAL DESIGN CRITERIA 299 Appendix A Conformance to AEC Propose.pdf 128 300 Appendix A Table - Conformance to AEC Propose.pdf 52 301 Appendix A - Table of Contents.pdf 35 APPENDIX B - TECHNICAL SPECIFICATIONS 302 Appendix B - Technical Specifications.pdf 32 APPENDIX C - STRUCTURAL QUALIFICATION OF SUBSYSTEMS AND COMPONENTS 303 Appendix C - Structural Qualification.pdf 133 304 Table - Appendix C - Structural Qualification.pdf 236 305 Appendix C - Table of Contents.pdf 42 APPENDIX D - QUALITY ASSURANCE PLAN 306 Appendix D Quality Assurance Plan.pdf 39 307 Figure - Appendix D - Quality Assurance Plan.pdf 390 308 Appendix D - Table of Contents.pdf 32 APPENDIX E - SITE GASEOUS RELEASE RATE LIMIT CALCULATION 309 Appendix E - Site Gaseous Release Rate.pdf 36 310 Appendix E - Table of Contents.pdf 27 APPENDIX F - UNIT SHARING AND INTERACTIONS 311 Appendix F - Unit Sharing and lnteractions.pdf 85 312 Appendix F - Table of Contents.pdf 41 APPENDIX G - PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS 313 Appendix G - Plant Nuclear Safety Operational.pdf 314 Table - Appendix G - Plant Nuclear Safety Operational.pdf 38 315 Figure - Appendix G - Plant Nuclear Safety Operational.pdf 1764 316 Appendix G Matrices Plant Nuclear Safety Operational.pdf 46 317 Appendix G - Table of Contents.pdf 41 318 Appendix G STATEA.pdf 684 319 Appendix G STATEB.pdf 689 320 Appendix G STATEC.pdf 693 321 Appendix G STATED.pdf 693 322 Appendix G STATEE.pdf 692 323 Appendix G STATEF.pdf 693 11
FILE NAME FILE SIZE (KB)
APPENDIX H - CORE THERMAL DESIGN 324 Appendix H - Core Thermal Design.pdf 25 APPENDIX I - IDENTIFICATION-RESOLUTION OF CONSTRUCTION PERMIT CONCERNS 325 Appendix I - Identification Resolution of Constr.pdf 139 326 Appendix I - Table of Contents.pdf 40 APPENDIX J - REACTOR PRESSURE VESSEL DESIGN
SUMMARY
REPORT - UNIT 1 327 Appendix J - Reactor Pressure Vessel Design.pdf 39 328 Appendix J - Table of Contents.pdf 31 APPENDIX K - REACTOR PRESSURE VESSEL DESIGN
SUMMARY
REPORT - UNIT 2 329 Appendix K - Reactor Pressure Vessel Design.pdf 39 330 Appendix K - Table of Contents.pdf 33 APPENDIX L - REACTOR PRESSURE VESSEL DESIGN
SUMMARY
REPORT - UNIT 3 331 Appendix L - Reactor Pressure Vessel Design.pdf 39 332 Appendix L - Table of Contents.pdf 31 APPENDIX M - REPORT PIPE FAILURES OUTSIDE CONTAINMENT 333 Appendix M - Report on Pipe Failures Outside.pdf 114 334 Table - Appendix M - Report on Pipe Failures.pdf 25 335 Figure - Appendix M - Report on Pipe Failures.pdf 729 336 Appendix M - Table of Contents.pdf 39 APPENDIX N - RELOAD LICENSING REPORT 337 Appendix N - BFN Unit 1 Cycle 10 Reload Safety Analysis.pdf 801 338 Appendix N - BFN Unit 2 Cycle 18 Reload Safety Analyses.pdf 720 339 Appendix N - BFN Unit 3 Cycle 16 Reload Safety Analyses.pdf 714 340 Appendix N - Table of Contents.pdf 30 APPENDIX 0 - AGING MANAGEMENT PROGRAM 341 Appendix 0 - Introduction.pdf 110 342 Appendix 0 - Table of Contents.pdf 50 12