ML23110A196

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9 to Updated Final Safety Analysis Report, Appendix G, Table of Contents
ML23110A196
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 04/10/2023
From:
Constellation Energy Generation
To:
Office of Nuclear Reactor Regulation
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ML23110A266 List: ... further results
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Download: ML23110A196 (1)
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Text

PBAPS UFSAR

APPENDIX G -PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS TABLE OF CONTENTS

The material presented in Appendix G is historical and describes information relevant to the original Technical Specifications.

Information may be used for understanding accidents,transients, and special events. For accurate information regarding the details of committed equipment for mitigation of these accidents, The Improved Technical Specifications (ITS), Chapter 14 of the UFSAR, or reload licensing documents may be used.

G.1 ANALYTICAL OBJECTIVE G.2 INTRODUCTION G.2.1 Nuclear Safety Operational Criteria G.2.2 Unacceptable Safety Results G.3 METHOD OF ANALYSIS G.3.1 Boiling Water Reactor Operating States G.3.2 Selection of Events for Analysis G.3.2.1 Planned Operations G.3.2.2 Abnormal Operational Transients and Accidents G.3.2.3 Special Events G.3.3 Rules for Event Analysis G.3.4 Steps in an Operational Analysis G.4 DISPLAY OF OPERATIONAL ANALYSIS RESULTS G.4.1 Protection Sequence and Safety System Auxiliary Diagrams G.4.2 Operational Matrices (Matrices A Through D)

G.5 OPERATIONAL ANALYSES FOR PEACH BOTTOM ATOMIC POWER STATION G.5.1 Special Consideration of Particular Systems for Sequence Diagram Format G.5.1.1 Primary Containment and Reactor Vessel Isolation and Control System (System 72)

G.5.1.2 Residual Heat Removal System -Low-Pressure Coolant Injection Mode (System 63) and Core Spray (System 64)

G.5.1.3 Mode Switch Positions G.5.2 Planned Operations G.5.3 Abnormal Operational Transients G.5.4 Accidents G.5.5 Safety System Auxiliaries G.5.6 Special Events G.5.7 Other Events G.6 REMAINDER OF NUCLEAR SAFETY OPERATIONAL ANALYSIS

APPENDIX G G-i REV. 25, APRIL 2015 PBAPS UFSAR

APPENDIX G -PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS

LIST OF TABLES

TABLE TITLE

G.3.1 Boiling Water Reactor Operating States

G.3.2 Events Applicable in Each Boiling Water Reactor Operating State

G.5.1 Sequence of Events for a Combined LOOP, Loss of One DG, Loss of All Class II Systems, and a T-G Trip on Both Units

APPENDIX G G-ii REV. 25, APRIL 2015 PBAPS UFSAR

APPENDIX G -PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS

LIST OF FIGURES

The material presented in Appendix G is historical and describes information relevant to the original Technical Specifications.

Information may be used for understanding accidents, transients, and special events. For accurate information regarding the details of committed equipment for mitigation of these accidents, The Improved Technical Specifications (ITS), Chapter 14 of the UFSAR, or reload licensing documents may be used.

FIGURE TITLE G.4.1 Format Used for Protection Sequence Diagrams G.4.2 Format Used for Safety System Auxiliary Diagrams G.4.3 Example of Matrix Information G.5.1 Safety Action Sequences for Planned Operations in State A G.5.2 Safety Action Sequences for Planned Operations in State B

G.5.3 Safety Action Sequences for Planned Operations in State C

G.5.4 Safety Action Sequences for Planned Operations in State D G.5.5 Protection Sequences for Electrical Load Rejection (Turbine Trip With Bypass)

G.5.6 Protection Sequences for Turbine Trip Without Bypass G.5.7 Protection Sequences for Isolation of All Main Steam Lines G.5.8 Protection Sequence for Isolation of One Main Steam Line

G.5.9 Protection Sequence for Feedwater Controller Failure

-Maximum Demand G.5.10 Protection Sequence for Loss of Feedwater Heating G.5.11 Protection Sequence for Control Rod Withdrawal Error G.5.12 Protection Sequences for Pressure Regulator Failure G.5.13 Protection Sequences for Inadvertent Opening of a Relief or Safety Valve

APPENDIX G G-iii REV. 25, APRIL 2015 PBAPS UFSAR

LIST OF FIGURES (cont'd)

FIGURE TITLE

G.5.14 Protection Sequences for Loss of Feedwater Flow

G.5.15 Protection Sequences for Loss of Auxiliary Power

G.5.16 Protection Sequences for Loss of Shutdown Cooling

G.5.17 Protection Sequence for Recirculation Flow Control Failure -Increasing Flow

G.5.18 Protection Sequences for Startup of Idle Recirculation Pump

G.5.19 Protection Sequences for Control Rod Drop Accident

G.5.20 Protection Sequences for Pipe Breaks Inside Primary Containment

G.5.21 Protection Sequences for Fuel Handling Accident

G.5.22 Protection Sequences for Pipe Breaks Outside Primary Containment

G.5.23a Safety System Auxiliaries

G.5.23b Safety System Auxiliaries

G.5.24 Protection Sequences for Shutdown from Outside the Control Room

G.5.25 Protection Sequence for Shutdown Without Control Rods

G.5.26 Protection Sequence for Loss of Normal Heat Sink

G.5.27 Emergency Shutdown -Reactor Temperature and Pressure and Torus Temperature

G.5.28 Emergency Shutdown -Drywell Temperature

G.5.29 Emergency Shutdown -Shutdown Cooling Mode Unavailable Suppression Pool Temperature

G.5.30 Emergency Shutdown -Shutdown Cooling Mode Unavailable Drywell Temperature

APPENDIX G G-iv REV. 25, APRIL 2015 PBAPS UFSAR

MATRICES

The material presented in Appendix G is historical and describes information relevant to the original Technical Specifications.

Information may be used for understanding accidents, transients, and special events. For accurate information regarding the details of committed equipment for mitigation of these accidents, The Improved Technical Specifications (ITS), Chapter 14 of the UFSAR, or reload licensing documents may be used.

MATRIX TITLE

A Operational Matrix for Operating State A

B Operational Matrix for Operating State B

C Operational Matrix for Operating State C

D Operational Matrix for Operating State D

APPENDIX G G-v REV. 25, APRIL 2015

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