ML21286A240
| 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:
|
| References | |
| Download: ML21286A240 (2) | |
Text
BFN-26 I.0-i 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
BFN-26 I.0-ii 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