ML21286A240

Amendment 29 to Updated Final Safety Analysis Report, Appendix I, Identification Resolution of Construction Permit Concerns, Table of Contents

ML21286A240
Person / Time
Site:	Browns Ferry
Issue date:	10/04/2021
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
Shared Package
ML21286A574	List: ML21277A142 ML21286A195 ML21286A196 ML21286A197 ML21286A198 ML21286A199 ML21286A200 ML21286A201 ML21286A204 ML21286A205 ML21286A206 ML21286A210 ML21286A211 ML21286A212 ML21286A213 ML21286A216 ML21286A217 ML21286A218 ML21286A219 ML21286A220 ML21286A221 ML21286A222 ML21286A223 ML21286A224 ML21286A225 ML21286A226 ML21286A227 ML21286A229 ML21286A230 ML21286A231 ML21286A232 ML21286A233 ML21286A234 ML21286A235 ML21286A236 ML21286A237 ML21286A238 ML21286A239 ML21286A240 ML21286A241 ML21286A242 ML21286A243 ML21286A244 ML21286A245 ML21286A246 ML21286A247 ML21286A248 ML21286A249 ML21286A250 ML21286A252 ... further results
References
Download: ML21286A240 (2)

Text

BFN-26 APPENDIX I IDENTIFICATION-RESOLUTION OF CONSTRUCTION PERMIT CONCERNS TABLE OF CONTENTS I.1 Summary Description .............................................................................................................I.0-1 I.2 Areas Specified In The Browns Ferry AEC-ACRS Construction Permit Reports ....................I.0-2 I.2.1 Introduction ................................................................................................................I.0-2 I.2.2 Effects of Fuel Failure on CSCS Performance ...........................................................I.0-2 I.2.3 Effects of Fuel Bundle Flow Blockage ........................................................................I.0-4 I.2.4 Verification of Fuel Damage Limit Criterion ................................................................I.0-5 I.2.5 Quality Assurance and Inspection of the Reactor Primary System ............................I.0-6 I.2.6 Effects of Cladding Temperatures and Materials on CSCS Performance ..................I.0-9 I.2.7 Control Rod Block Monitor Design .............................................................................I.0-10 I.2.8 Station Startup Program .............................................................................................I.0-11 I.2.9 Main Steamline Isolation Valve Testing Under Simulated Accident Conditions .........I.0-12 I.2.10 Performance Testing of the Station Standby Diesel Generator System .....................I.0-13 I.2.11 Formulation of an Inservice Inspection Program ........................................................I.0-13 I.2.12 Diversification of the CSCS Initiation Signals .............................................................I.0-14 I.2.13 Control Systems for Emergency Power......................................................................I.0-14 I.2.14 Misorientation of Fuel Assemblies ..............................................................................I.0-15 I.2.15 Concern of Dr. Stephen H. Hanauer-Emergency Power and Core Standby Cooling Systems ..........................................................................................I.0-16 I.2.16 Fuel Clad Disintegration Limitations ...........................................................................I.0-17 I.2.17 General Concern with Regard to Reactors of High Power Density and All Large Water-Cooled Power Reactor .....................................................................I.0-18 I.2.18 Summary ....................................................................................................................I.0-19 I.3 Areas Specified in the AEC-Staff Construction Permit - Safety Evaluation Reports ...............I.0-19 I.3.1 General ......................................................................................................................I.0-19 I.3.2 Unit 1 and 2 AEC-STAFF-Construction Permit Concerns ..........................................I.0-19 I.3.3 Unit 3 AEC-Staff-Construction Permit Concerns ........................................................I.0-26 I.3.4 Summary ....................................................................................................................I.0-32 I.4 Areas Specified in Other Related AEC-ACRS Construction Permit And Operating License Reports......................................................................................................................I.0-33 I.4.1 General ......................................................................................................................I.0-33 I.4.2 Ring Header Leakage Design ....................................................................................I.0-34 I.4.3 CSCS Thermal Effects on the Reactor Vessel and Internals .....................................I.0-34 I.4.4 Effects of Blowdown Forces on Reactor Primary System Components .....................I.0-35 I.4.5 Separation of Control and Protection System Functions ............................................I.0-36 I.4.6 Instrumentation for Prompt Detection of Gross Fuel Failure ......................................I.0-36 I.4.7 Design of Piping Systems to Withstand Earthquake Forces ......................................I.0-37 I.4.8 LPCIS-Logic Control System Design..........................................................................I.0-37 I.4.9 Reevaluation of Main Steamline Break Accident ........................................................I.0-38 I.4.10 Depressurization Performance of HPCIS ...................................................................I.0-39 I.0-i

BFN-26 APPENDIX I IDENTIFICATION-RESOLUTION OF CONSTRUCTION PERMIT CONCERNS TABLE OF CONTENTS I.4.11 AEC General Design Criterion No. 35-Design Intent and Conformance ....................I.0-39 I.4.12 Automatic Pressure Relief System-Initiation Interlock ................................................I.0-39 I.4.13 Scram Reliability Study ..............................................................................................I.0-40 I.4.14 Design Basis of Engineered Safety Features .............................................................I.0-41 I.4.15 Hydrogen Generation Study .......................................................................................I.0-42 I.4.16 Primary Containment Inerting .....................................................................................I.0-43 I.4.17 Seismic Design and Analysis Models .........................................................................I.0-44 I.4.18 Automatic Pressure Relief System-Single Component Failure Capability-Manual Operation .......................................................................................................I.0-46 I.4.19 Matters of Current Regulatory Staff-Applicant Discussion..........................................I.0-46 I.4.20 Flow Reference Scram ...............................................................................................I.0-47 I.4.21 Future Items of Considerations for Incorporation .......................................................I.0-48 I.4.22 Diesel Generator Synchronization Considerations .....................................................I.0-48 I.4.23 Development of Instrumentation-Primary Containment Leakage Detection System -Increased Sensitivity Studies .......................................................................I.0-49 I.4.24 Development of Instrumentation-Vibration and Loose Parts Detection Studies .........I.0-49 I.4.25 CSCS Leakage Detection, Protection, and Isolation Capability .................................I.0-50 I.4.26 Main Steamlines-Standards for Fabrication, QC, and Inspection ...............................I.0-52 I.4.27 Summary ....................................................................................................................I.0-53 I.5 Areas Specified in Other Related AEC-Staff Construction Permit or Operating License Safety Evaluation Reports .........................................................................................I.0-53 I.5.1 General ......................................................................................................................I.0-53 I.5.2 Tornado and Missile Protection-GE-BWR-Spent Fuel Storage Pool ..........................I.0-53 I.5.3 BWR System Stability Analysis ..................................................................................I.0-54 I.5.4 Summary ....................................................................................................................I.0-54 I.6 Summary Conclusions ............................................................................................................I.0-54 1.7 References .............................................................................................................................I.0-55 I.0-ii