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Browns Ferry, Units 1, 2, and 3 - Updated Final Safety Analysis Report, Amendment 26
	ML15295A025
Person / Time
Site:	Browns Ferry
Issue date:	10/05/2015
From:	Bono S M; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML15295A025 (16)
	v • d • e

Security-Related Information Withhold Under 10 CFR 2.390.This letter is decontrolled when separated from the enclosure.

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 3 5609-2000 October 5, 201510 CER 50.410 CFR 50.71 (e)(4)ATTN: Document Control DeskU.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Browns Ferry Nuclear Plant -Updated Final Safety Analysis Report,Amendment 26Pursuant 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 26 of the Updated Final Safety Analysis Report(UFSAR) for the Browns Ferry Nuclear Plant (BEN).Amendment 26 of the BEN UFSAR is a 24-month update that reflects editorial corrections,

changes, and analyses pursuant to 10 CFR 50.59, "Changes Tests, and Experiments,"

to thefacility, which were in effect through July 1, 2015. All UFSAR pages issued as a result of thisupdate are clearly delineated with a "BFN-26" in the page header and a revision bar is shown inthe 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, 2015.The Enclosure to this letter contains one (1) Compact Disk -Recordable (CD-R) of the BENUFSAR, Amendment

26. TVA has also included a listing of the UFSAR files and their size inthe enclosure.

Please note that some files do not have embedded fonts; however, these filesare from a scanned source and are thus consistent with Section 2.23 of the "Guidance forElectronic Submissions to the NRC, Revision 6.1."TVA has determined that some of the informration contained on the CD-R is considered to besensitive unclassified non-safeguards information.

As such, the enclosed CD-R is labeled"Tennessee Valley Authority, Browns Ferry Nuclear Plant, Updated Final Safety Report, Amendment 26, Non-Public Version."

This CD'R submittal of the entire BEN UFSAR {, LLsupersedes all previously submitted hard copies and CD-R copies of the document.

Security-Related Information Withhold Under 10 CFR 2.390.This letter is decontrolled when separated from the enclosure.

U.S. Nuclear Regulatory Commission Page 2October 5, 2015Pursuant to the requirements of 10 CFR 54.37, "Additional Records and Recordkeeping Requirements,"

paragraph (b), TVA has determined that there are no newly identified systems,structures, and components that would have been subject to an aging management review orevaluation of time-limited aging analyses.

I certify that I am duly authorized by TVA, and that, to the best of my knowledge and belief, theinformation contained herein accurately presents changes made since the previous submittal, necessary to reflect information and analyses submitted to the Commission or preparedpursuant to Commission requirements.

There are no new regulatory commitments contained in this letter. If you have any questions, please contact Jamie L. Paul, Nuclear Site Licensing

Manager, at (256) 729-2636.

Enclosures:

CD-ROM Containing Browns Ferry Nuclear Plant Updated Final Safety AnalysesReport, Amendment 26, Non-Public Version and a Listing of the UFSAR Files,Including File Sizecc (w/ Enclosure):

NRC Regional Administrator

-Region IINRC Senior Resident Inspector

-Browns Ferry Nuclear Plant Security-Related Information Withhold Under 10 CFR 2.390.This letter is decontrolled when separated from the enclosure.

U.S. Nuclear Regulatory Commission Page 3October 5, 2015JLP:MWOEnclosure bcc (wi Enclosure):

NRC Project Manager -Browns Ferry Nuclear Plantbcc (w/o Enclosure):

M. A. BalduzziG. A. Boerschig S. M. BonoK. H. BronsonC. R. ChurchD. M. CzufinS. M. DouglasJ. P. GrimesE. K. Henderson D. L. HughesS. W. Hunnewell G. W. MaudlinJ. L. PaulE. D. SchrullJ. W. SheaP. B. Summers, Jr.S. A. VanceB. A. WetzelG. R. WilliamsP. R. WilsonCNL-1 5-199 Security-Related Information Withhold Under 10 CFR 2.390.This letter is decontrolled when separated from the enclosure.

Enclosure Tennessee Valley Authority Browns Ferry Nuclear PlantUnits 1, 2, and 3Updated Final Safety Analysis Report (UFSAR)Amendment 26This enclosure provides the following:

One CD-ROM Copy of Amendment 26 of the Browns Ferry Nuclear Plant UFSAR,Non-Public Version* Listing of the Browns Ferry Nuclear Plant UFSAR, Amendment 26 files, including file size BROWNS FERRY NUCLEAR PLANTUPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR),

AMENDMENT 26CHAPTERS 1 THROUGH 14 AND APPENDICES A THROUGH 0LIST OF FILES ON DISK(ALL LISTED FILES -NON-PUBLIC VERSION)FILE NAME FILESIZE(KB)01 BEN FSAR Amendment 26 EPL001 BEN FSAR Table of ContentsCHAPTER 1 -INTRODUCTION AND SUMMARY002 1.1 Project Identification 54003 1.2 Definitions 66004 1.2 Figure -Definitions 78005 1.3 Methods of Technical Presentation 41006 1.3 Table -Methods of Technical Presentation 85007 1.3 Figure -Methods of Technical Presentation 80008 1.4 Class of BWR Systems Criteria Requirements for Safety Evaluation 37009 1.4 Table -Class of BWR Systems Criteria.

Requirements for Safety Evaluation 76010 1.5 Principal Design Criteria 60011 1.6 Plant Description 89012 1.6 Figure -Plant Description 1136013 1.7 Comparison of Principal Design Characteristics 35014 1.7 Table -Comparison of Principal Design Characteristics 84015 1.8 Summary of Radiation Effects 34016 1.9 Plant Management 29017 1.10 Quality Assurance Program 31018 1.11 Identification Resolution of Construction Permit Concern -Summary 37019 1.11 Table -Identification Resolution of Construction Permit Concern -Summary 59020 1.12 General Conclusions 35021 1-Table of Contents 56CHAPTER 2 -SITE022 2.1 Summary Description 34023 2.2 Site Description 13024 2.2 Table -Site Description 85025 2.2 Figure -Site Description 362I FILE NAME FILESIZE(KB)026 2.3 Meteorology 64027 2.3 Table -Meteorology 122028 2,3 Figure -Meteorology 1695029 2.4 Hydrology, Water Quality, and Aquatic Biology 58030 2.4 Table -Hydrology, Water Quality, and Aquatic Biology 43031 2.4 Figure -Hydrology, Water Quality, and Aquatic Biology 782032 2.4A Maximum Possible Flood 69033 2.4A Table -Maximum Possible Flood 449034 2-4A-Table 1 Maximum Possible Flood 390035 2.4A Figure -Maximum Possible Flood 5417036 2.5 Geology and Seismology 77037 2.5 Table -Geology and Seismology 49038 2.5 Figure -Geology and Seismology 2093039 2.6 Environmental Radiological Monitoring Program 38040 2 Table of Contents 58CHAPTER 3 -REACTOR041 3,1 Summary Description 38042 3,2 Fuel Mechanical Design 56043 3,2 Table -Fuel Mechanical Design 27044 3.2 Figure -Fuel Mechanical Design 387045 3.3 Reactor Vessel Internals Mechanical Design 74046 3,3 Table -Reactor Vessel Internals Mechanical Design 38047 3.3 Figure -Reactor Vessel Internals 1020048 3.4 Reactivity Control Mechanical Design 102049 3.4 Figure -Reactivity Control Mechanical Design 1879050 3,5 Control Rod Drive Housing Supports 46051 3,5 Figure -Control Rod Drive 420052 3,6 Nuclear Design 59053 3.6 table -Nuclear Design 41054 3,6 Figure -Nuclear Design 390055 3.7 Thermal and Hydraulic Design 144056 3.7 Figure -Thermal and Hydraulic Design 6242 FILE NAME FILESIZE(KB)057 3.8 Standby Liquid Control 36058 3.8 Figure -Standby Liquid Control 472059 3 Table of Contents 43CHAPTER 4 -REACTOR COOLANT SYSTEM060 4.1 Summary Description 39061 4.2 Reactor Vessel and Appurtenances Mechanical Design 76062 4.2 Table -Reactor Pressure Vessel Materials 44063 4.2 Figure -Reactor Vessel and Appurtenances Mechanical Design 1165064 .3 Ractr Reircuatin Sytem57065 .3 able- Racto Reircuatin Sytem46066 .3 igue -Reator ecicultio Sytem1269 067 4.4 Nuclear Steam Pressure Relief System 38068 4.4 Table -Nuclear Steam Pressure Relief System 38069 4.4 Figure -Nuclear Steam Pressure Relief System 1230070 4.5 Main Steam Line Flow Restrictor 40071 4.5 Figure -Main Steam Line Flow Restrictor 287072 4.6 Main Steam Isolation Valves 58073 4.6 Figure -Main Steam Isolation Valves 419074 4.7 Reactor Core Isolation Cooling 48075 4.7 Table -Reactor Core Isolation Cooling 41076 .7 igur -eacor Cve soltionCooing1956 077 .8 esiual eatRemval63 078 .8 abl -esidal eatRemval44 079 .8 igue -esiualHeatRemval421 080 4.9 Reactor Water Cleanup 1081 4.9 Table -Reactor Water Cleanup 4082 4.9 Figure -Reactor Water Cleanup 20083 4.10 Nuclear System Leakage Rate Limits 5084 4.10 Figure -Nuclear System Leakage Rate44085 4.11 Main Steam Lines, Feedwater Piping and Drains 39086 4.11 Figure -Main Steam Lines, Feedwater Piping and Drains 67087 4.12 Inservice Inspection and Testing 383 FILE NAME FILESIZE(KB)088 4- Tabie of Contents 46CHAPTER 5 -CONTAINMENT 089 5.1 Summary Description 34-090 5.2 Primary Containment 496091 5.2 Table -Primary Containment 58092 5.2 Figure -Primary Containment 4784-093 5.3 Secondary Containment 93094 5.3 Figure -Secondary Containment 1454095 5 -Table of Contents 41CHAPTER 6 -EMERGENCY CORE COOLING SYSTEM-096 6.1 Safety Objective 33-097 6.2 Safety Design Basis 36098 6.3 Emergency Core Cooling 38-099 6.3 Table -Emergency Core Cooling 43100 6.3 Figure -Emergency Core Cooling 389101 6.4 Description 39102 6.4 Table -Description 24103 6.4 Figure -Description 1890'104 6.5 Safety Evaluation 62105 6.5 Table -Safety Evaluation 186.5 Figure -Safety Evaluation 712107 6.6 Inspection and Testing 41"108 6 Table of Contents 39CHAPTER 7 -CONTROL AND INSTRUMENTATION 109 7.1 Summary Description 45-110 7.1 Figure -Summary Description 4201117.2 Reactor Protection System 78112 7.2 Table -Reactor Protection System 42113 7.2 Figure -Reactor Protection System 2278114 7.3 Primary Containment Isolation 75115 7.3 Table -Primary Containment Isolation 40-116 7.3 Figure -Primary Containment Isolation 8684 FILE NAME FILESIZE(KB)117 7.4 Emergency Core Cooling Control 87118 7.4 Table -Emergency Core Cooling Control 46119 7.4 Figure -Emergency Core Cooling Control 4788120 7.5 Neutron Monitoring System 84121 7.5 Table -Neutron Monitoring System 38122 7.5 Figure- Neutron Monitoring System 1788123 7.6 Refueling Interlocks 4124 7.6 Table -Refueling Interlocks 37125 7.6 Figure -Refueling Interlocks 450126 7.7 Reactor Manual Control System 58127 7.7 Table -Reactor Manual Control System 42128 7.7 Figure -Reactor Manual Control System 506129 7.7A_B Rod Sequence Control 32130 7.8 Reactor Vessel Instrumentation 48131 7.8 Table -Reactor Vessel Instrumentation 45132 7.8 Figure -Reactor Vessel Instrumentation 1873133 7.9 Recirculation Flow Control 57134 7.9 Figure -Recirculation Flow Control 31135 7.10 Feedwater Control System 54136 7.10 Figure -Feedwater Control System 763137 7.11 Pressure Regulator and Turbine 46138 7.11 Figure -Pressure Regulator and Turbine 436139 7.12 Process Radiation Monitoring 55140 7.12 Table -Process Radiation Monitoring 36141 7.12 Figure -Process Radiation Monitoring 2423142 7.13 Area Radiation Monitoring 41143 7.13 Table -Area Radiation Monitoring 50144 7.13 Figure -Area Radiation Monitoring 389145 7.14 Drywell Leak Detection Radiation 37146 7.15 Health Physics Laboratory 35147 7.16 Process Computer System 53148 7.16 Table -Process Computer System 255 FILE NAME FILESIZE(KB)149 7.16 Figure -Process Computer System 388150 7.17 Deleted 28151 7.17 Table -Deleted 24152 7.17 Figure -Deleted 391153 7.18 Backup Control System 4154 7.19 Anticipated Transient Without Scram 45155 7.20 Instrument Setpoint Methodology 44156 7.20 Table -Instrument Setpoint Methodology 50157 7 Table of Contents 53CHAPTER 8 -ELECTRICAL POWER SYSTEMS158 8.1 Summary Description 41159 8.2 Generators 36160 8.3 Transmission System 16161 8.3 Figure -Transmission System 4193162 8.4 Normal Auxiliary Power 79163 8.4 Table -Normal Auxiliary Power 5164 8.4 Figure -Normal Auxiliary Power 1385165 8.5 Standby AC Power Supply 47166 8.5 Table -Standby AC Power Supply 112167 8.5 Figure -Standby AC Power Supply 19510168 8.6 250-V DC Power Supply 49169 8.6 Table -250-V DC Power Supply 37170 8.6 Figure -250-V DC Power Supply 1296171 8.7 120-V AC Power Supply 42172 8.7 Figure-I 120-V AC Power Supply 978173 8.8 Auxiliary DC Power Supply 48174 8.8 Table -Auxiliary DC Power Supply 37175 8.8 Figure -Auxiliary DC Power Supply 391176 8.9 Safety Systems Independence Criteria 57177 8.9 Table -Safety Systems Independence Criteria 25178 8.9 Figure -Safety Systems Independence Criteria 389179 8.10 Station Blackout 396 FILE NAME FILESIZE(KB)180 8 Table of Contents 20CHAPTER 9 -RADIOACTIVE WASTE CONTROL SYSTEMS181 9.1 Summary Description 3182 9.2 Liquid Radwaste System 26183 9.2 Table -Liquid Radwaste System 49184 9.2 Figure -Liquid Radwaste System 3475185 9.3 Solid Radwaste System 45187 .4 Gseos Rawase Sytem25190 9.5 Figure -Gaseous Radwaste System -Modified 1432191 9 Table of Contents 38CHAPTER 10 -AUXILIARY SYSTEMS192 10.1 Summary Description 34193 10.2 New Fuel Storage 40194 0.2Figue

-NewFuelStoage437

-19510.3Spen Fue Stoage66198 10.4 Table -Tools and Servicing Equipment 36199 10.4 Figure -Tools and Servicing Equipment 439200 10.5 Fuel Pool Cooling and Cleanup 52201 10.5 Table -Fuel Pool Cooling and Cleanup 41202 10.5 Figure -Fuel Pool Cooling and Cleanup 2086203 10.6 Reactor Building Closed Cooling 41204 10.6 Table -Reactor Building Closed Cooling 80205 10.6 Figure -Reactor Building Closed Cooling 711206 10.7 Raw Cooling Water 39207 10.7 Figure -Raw Cooling Water 2671208 10.8 Raw Service Water 37209 10.9 RHR Service Water 197 FILE NAME FILESIZE210 10.9 Figure -RHR Service Water 1313211 10.10 Emergency Equipment Cooiing Water 44212 10.10 Figure -Emergency Equipment Cooling Water 1665213 10.11 Fire Protection System 24214 10.11 Figure- Fire Protection System 391215 10.12 Heating Ventilating and Air Conditioning 60216 10.12 Figure -Heating Ventilating and Air Conditioning 2122217 10.13 Demineralized Water System 42218 10.13 Figure -Demineralized Water System 390219 10.14 Control and Service Air 46220 10.14 Figure -Control and Service Air 1249221 10.15 Potable Water and Sanitary 32222 10.16 Equipment and Floor Drainage 45223 10.17 Process Sampling Systems 41224 10.17 Table -Process Sampling Systems 42225 10.17 Figure -Process Sampling Systems 1204226 10.18 Plant Communications System 49227 10.18 Figure -Plant Communications System 726228 10.19 Lighting System 36229 10.20 Auxiliary Boiler System 4230 10.21 Postaccident Sampling 43231 10.21 Table -Postaccident Sampling 39232 10.21 Figure -Postaccident Sampling 634233 10.22 Auxiliary Decay Heat Removal 37234 10.23 Hydrogen Water Chemistry 44235 10 Table of Contents 47CHAPTER 11 -POWER CONVERSION SYSTEMS236 11.1 Summary Description 30237 11.1 Figure -Summary Description 910238 11.2 Turbine Generator 48239 11.3 Main Condenser 44240 11.4 Main Condenser Gas Removal 378 FILE NAME FILESIZE241 11.5 Turbine Bypass 36242 11.6 Condenser Circulating Water 21242a 11.6 Table -Condenser Circulating Water 21243 11.6 Figure -Condenser Circulating Water 1512244 11.7 Condensate Filter Demineralizer 41245 11.7 Figure -Condensate Filter Demineralizer 394246 11.8 Condensate and Reactor Feedwater 43250 1.9 igue -ondesat Stoage1140 251 11 Table of Contents 15CHAPTER 12 -STRUCTURES AND SHIELDING 252 12.1 Summary Description 34253 12.2 Principal Structures and Foundations 227254 12.2 Table -Principal Structures and Foundations 145255 12.2 Figure -Principal Structures and Foundations 9257256 12.3 Shielding and Radiation 49257 12.3 Table -Shielding and Radiation 32258 12 Table of Contents 44262 13.3 Training Programs 35263 13.4 Preoperational Test Program 115264 13.4 Figure -Preoperational Test Program 426265 13.5 Startup and Power Test Program 144266 13.5 Table -Startup and Power Test Program 68267 13.5 Figure -Startup and Power Test Program 607268 13.6 Normal Operations 44269 13.6 Figure -Normal Operations 3909 FILE NAME FILESIZE(KB)270 13.7 Records 23271 13.8 Operational Review and Audits 38272 13.9 Refueling Operations 3273 13.10 Refueling Test Program 57___274 13 Table of Contents 39CHAPTER 14 -PLANT SAFETY SYSTEMS275 14.1 Plant Safety Analysis 36276 14.2 Unacceptable Safety Results for Abnormal Operational Transients 322 7 9 4 .4 T a b l -p p r o c h o S a e ty A n a l s i s3 9 7280 14.4 Figure -Approach to Safety Analysis 532281 14.5 Analyses of Abnormal Operational Transients 162282 14.5 Table -Analyses of Abnormal Operational Transients 21283 14.5 Figure -Analyses of Abnormal Operational Transients 1972284 14.6 Analysis of Design Basis Accidents 106285 4.6Tabe -nalsisof Dsig Bais Acidnts65 286 4.6Figue

-Analsisof esig Bais Acidnts781 2 8 7 1 .7 C n cl u i o n s3 9 3288 4.8 naltica Metods462 289 14.8 Table -Analytical Methods 403290 14.8 Figure -Analytical Methods 433291 14.9 Dose Sensitivity Evaluation 400292 14.9 Table -Dose Sensitivity Evaluation 401293 14.10 Analyses of Abnormal Operational 428294 4.1 Fiure Anlyss ofAbnrma Opeatinal1118 295 4.1 Anaysi of esin Bais ccidnts483*

296 4.1 Tabe -Analsisof esig Bais Acidnts404 297 14.11 Figure -Analysis of Design Basis Accidents 709298 14 Table of Contents 2510 FILE NAME FILESIZE(KB)APPENDIX A -CONFORMANCE OF AEC PROPOSED GENERAL DESIGN CRITERIA-299 Appendix A Conformance to AEC Propose 128-300 Appendix A Table -Conformance to AEC Propose 52-303 Appendix C -Structural Qualification 134304 Table -Appendix C -Structural Qualification 236-305 Appendix C -Table of Contents 232-APPENDIX D -QUALITY ASSURANCE PLAN-309 iur Appendix E Sit GaeusRaitAssrne R late 360-3108 Appendix E -Table of Contents 327-APPENDIX F -UNIT SHARING AND INTERACTIONS

-311 Appendix F -Unit Sharing and Interactions71-312 Appendix F -Table of Contents41-316 Appendix G Marc Plant Nuclear Safety Operational 461"317 Appendix G -Table of Contents41-318 Appendix G STATE A 684-319 Appendix G STATE B 689"320 Appendix G STATE C 693-321 Appendix G STATE D 693-322 Appendix G STATE E 692'323 Appendix G STATE F 69311 FILE NAME FILESIZE(KB)APPENDIX H -CORE THERMAL DESIGN324 Appendix H -Core Thermal Design 25APPENDIX I -IDENTIFICATION-RESOLUTION OF CONSTRUCTION PERMIT CONCERNS327 Appendix J -Reactor Pressure Vessel Design 39328 Appendix J -Table of Contents 3APPENDIX K -REACTOR PRESSURE VESSEL DESIGN SUMMARY REPORT -UNIT 2329 Appendix K -Reactor Pressure Vessel Design 3330 Appendix K -Table of Contents 3APPENDIX L -REACTOR PRESSURE VESSEL DESIGN SUMMARY REPORT -UNIT 3331 Appendix L -Reactor Pressure Vessel Design 39-332 Appendix L -Table of Contents 31APPENDIX M -REPORT PIPE FAILURES OUTSIDE CONTAINMENT 333 Appendix M -Report on Pipe Failures Outside 113334 Table -Appendix M -Report on Pipe Failures 25335 Figure -Appendix M -Report on Pipe Failures 7293"36 Appendix M -Table of Contents 39APPENDIX N -RELOAD LICENSE REPORT337 Appendix N -Unit 1 Cycle 11 Reload Safety Analysis (July, 2014) 1293338 Appendix N -Unit 2 Cycle 18 Reload Safety Analysis (July, 2014) 162443"39 Appendix N -Unit 3 Cycle 17 Reload Analysis

-Revision 2 (July, 2014) 726340 Appendix N -Table of Contents 7APPENDIX 0 -AGING MANAGEMENT PROGRAM3"41 Appendix 0 -Introduction 100342 Appendix 0 -Table of Contents 13812 Security-Related Information Withhold Under 10 CFR 2.390.This letter is decontrolled when separated from the enclosure.