ML21286A218
| ML21286A218 | |
| 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: ML21286A218 (5) | |
Text
BFN-26 APPENDIX G PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS TABLE OF CONTENTS G.1 Analytical Objective ................................................................................................................ G.0-1 G.2 Basis for Selecting Operational Requirements ....................................................................... G.0-1 G.2.1 Unacceptable Safety Results ................................................................................... G.0-1 G.2.2 Nuclear Safety Operational Criteria .......................................................................... G.0-4 G.2.3 Origin of the Unacceptable Safety Results and Criteria ........................................... G.0-5 G.3 Basis for Selection of Surveillance Test Frequencies for Nuclear Safety Systems and Engineered Safeguards ......................................................................... G.0-5 G.3.1 Normal Surveillance Test Frequencies ..................................................................... G.0-5 G.3.2 Allowable Repair Times ............................................................................................ G.0-5 G.3.3 Repair Time Rule ..................................................................................................... G.0-6 G.4 Method of Analysis ................................................................................................................. G.0-6 G.5 Analysis and Results .............................................................................................................. G.0-7 G.5.1 Identification of BWR Operating States .................................................................... G.0-7 G.5.2 Identification of Types of Operation and Events Applicable in Each BWR Operating State ...................................................................................... G.0-8 G.5.3 Identification of Safety Actions and Systems Essential to Satisfying the Nuclear Safety Operational Criteria .................................................................... G.0-13 G.5.4 Remainder of the Nuclear Safety Operational Analysis ............................................ G.0-45 G.6 Conclusion ............................................................................................................................. G.0-45 G.0-i
BFN-26 APPENDIX G PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS LIST OF TABLES Table Title G.0-1 Interpretation of Symbols Used in Example Matrix on Figure G.0.2 G.0-ii
BFN-26 APPENDIX G PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS LIST OF FIGURES AND MATRICES (Sheet 1)
Figure Title G.0-1 Block Diagram of Method Used to Derive Operational Nuclear Safety Requirements and Technical Specifications G.0-2 Example of Matrix 3 Information G.0-3 Safety System Auxiliaries, Example of Convention Used on Block Diagrams G.0-4 RCICS Auxiliaries G.0-5 RHRS - Shutdown Cooling Mode Auxiliaries G.0-6 RHRS - LPCI Mode Auxiliaries G.0-7 RHRS - Torus Cooling Mode Auxiliaries G.0-8 HPCIS Auxiliaries G.0-9 Automatic Depressurization System Auxiliaries G.0-10 Core Spray System Auxiliaries G.0-11 Standby Liquid Control System Auxiliaries G.0-12 Standby Coolant System Auxiliaries G.0-13 Primary Containment and Reactor Vessel Isolation Control System Auxiliaries G.0-14 Standby AC Power System Auxiliaries G.0-15 Primary Containment Auxiliaries G.0-16 Standby Gas Treatment System Auxiliaries G.0-17 Incident Detection Circuitry Auxiliaries G.0-18 RHRS - Drywell Cooling Mode Auxiliaries G.0-19 Control Building Heating, Ventilating, and Air Conditioning System G.0-20 Equipment Area Cooling System Auxiliaries G.0-21 Emergency Equipment Cooling Water System Auxiliaries G.0-22 RHR Service Water System Auxiliaries G.0-23 Protection Sequence Diagram Example G.0-24 Sequence for Refueling Restrictions G.0-25 Sequence for Rod Worth Control G.0-26 Protection Sequence for Generator Trip G.0-iii
BFN-26 APPENDIX G PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS LIST OF FIGURES AND MATRICES (Cont'd)
(Sheet 2)
Figure Title G.0-27 Protection Sequences for Turbine Trip G.0-28a, b Protection Sequences for Isolation of All Main Steam Lines G.0-29 Protection Sequence for Isolation of One Main Steam Line G.0-30a, b Protection Sequences for Loss of Condenser Vacuum G.0-31 Protection Sequence for Loss of Feedwater Heating G.0-32 Protection Sequence for Rod Withdrawal Error G.0.33 Protection Sequences for Pressure Regulator Failure G.0-34 Protection Sequences for Inadvertent Opening of a Relief or Safety Valve G.0-35a, b Protection Sequences for Loss of Feedwater Flow G.0-36 Protection Sequences for Total Loss of Offsite AC Power a, b, c, d, e G.0-37 Protection Sequence for Recirculation Flow Control Failure - Maximum Demand G.0-38 Protection Sequences for Startup of Idle Recirculation Pump G.0-39 Protection Sequences for Loss of Shutdown Cooling G.0-40 Protection Sequences for Feedwater Controller Failure - Maximum Demand G.0-41a, b, c Protection Sequences for Control Rod Drop Accident G.0-42a, b Protection Sequences for Pipe Breaks Inside the Primary Containment G.0-43 Protection Sequence for Fuel Handling Accident G.0-44a, b, c Protection Sequences for Pipe Breaks Outside Primary Containment G.0-45 Protection Sequences for Loss of Habitability of the Control Room G.0-46 Protection Sequences for Shutdown Without Control Rods G.0-iv
BFN-26 APPENDIX G PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS LIST OF FIGURES AND MATRICES (Cont'd)
(Sheet 3)
Matrix Number 1 BWR Operating States 2 Types of Operation and Events Applicable in Each BWR Operating State Sheet 1 Sheet 2 3A Operational Nuclear Safety Analysis for Operating State A 3B Operational Nuclear Safety Analysis for Operating State B 3C Operational Nuclear Safety Analysis for Operating State C 3D Operational Nuclear Safety Analysis for Operating State D 3E Operational Nuclear Safety Analysis for Operating State E 3F Operational Nuclear Safety Analysis for Operating State F G.0-v