ML18024A390

From kanterella
Jump to navigation Jump to search
Updated Final Safety Analysis Report (Ufsar), Amendment 27, Appendix I - Table of Contents
ML18024A390
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/05/2017
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML18018A778 List: ... further results
References
Download: ML18024A390 (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