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Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23110A2402023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Table of Contents ML23173A0132023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 12, Structures and Shielding, Sections 1 Thru 4 - Redacted ML23110A2462023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, PEA Chapter 00, Cover Page and General Table of Contents ML23110A2472023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix E, Table of Contents ML23110A2372023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary, Table of Contents ML23110A2422023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Control and Instrumentation, Table of Contents ML23110A2592023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix N, Peach Bottom Site Meteorology ML23110A2392023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix D, Table of Contents ML23110A2532023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations, Sections 1 Thru 8 ML23110A2202023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Exhibit IV, Vessel Fabrication and Assembly ML23173A0552023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix E, Station Atmospheric Release Limit Calculations - Redacted ML23110A2232023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix G, Plant Nuclear Safety Operational Analysis ML23173A0402023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Control and Instrumentation - Redacted ML23173A0382023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix M Containment Report - Redacted ML23172A2812023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix C, Figures - Redacted ML23173A0582023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 10, Figures - Redacted ML23110A2312023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 11, Table of Contents ML23110A2602023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 3, Figures ML23173A0162023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 5, Figures - Redacted Rev1 ML23173A0172023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Sections 10 Thru 23 - Redacted ML23172A2802023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 9, Figures - Redacted ML23110A2652023-04-10010 April 2023 Submittal of Revision 29 to Updated Final Safety Analysis Report and Rev. 24 to Fire Protection Program ML23173A0452023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 9, Table of Contents - Redacted ML23172A2752023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix a, Table of Contents - Redacted ML23173A0332023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 2, Site - Redacted ML23172A2622023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Figures - Redacted ML23173A0482023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 12, Table of Contents - Redacted ML23110A2562023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML23110A2322023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix P, Environmental Technical Specifications ML23173A0232023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 12, Figures - Redacted ML23110A2242023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Exhibit Vi.B Unit 3, Deleted ML23110A2612023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix O, Table of Contents ML23173A0592023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix J, Identification-Resolution of AEC-ACRS and Staff Concerns - Redacted ML23173A0492023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix a, Figures - Redacted ML23110A2512023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, PEA Chapter 6, Figures ML23173A0572023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix C, Structural Design Criteria - Redacted ML23173A0562023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 10, Auxiliary Systems, Sections 1 Thru 24 - Redacted ML23173A0292023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 8, Figures - Redacted ML23173A0432023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 8, Electrical Power Systems - Redacted ML23172A2842023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix C, Table of Contents - Redacted ML23173A0372023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix a, Pressure Integrity of Piping and Equipment Pressure Parts - Redacted ML23110A2482023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Exhibit III, Summary Stress Report ML23110A2452023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix H, Table of Contents ML23110A2502023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 8, Table of Contents ML23110A2292023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 10, Table of Contents ML23110A2572023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 5, Containment ML23110A2212023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 1, Figures ML23110A2282023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix F, Interaction of Units 2 and 3 ML23110A2412023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix Q, Figure ML23110A2622023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 13, Table of Contents 2023-04-10
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PBAPS UFSAR SECTION 6.0 - CORE STANDBY COOLING SYSTEMS TABLE OF CONTENTS SECTION TITLE 6.1 SAFETY OBJECTIVE 6.2 SAFETY DESIGN BASIS 6.3
SUMMARY
DESCRIPTION
6.4 DESCRIPTION
6.4.1 High-Pressure Coolant Injection System 6.4.2 Automatic Depressurization System 6.4.3 Core Spray System 6.4.4 Low-Pressure Coolant Injection 6.4.5 Core Standby Cooling System NPSH 6.4.6 Gas Management Program 6.5 SAFETY EVALUATION 6.5.1 Summary 6.5.2 Analysis Models 6.5.3 Individual System Adequacy 6.5.3.1 High-Pressure Coolant Injection System 6.5.3.2 Automatic Depressurization System 6.5.3.3 Core Spray System 6.5.3.4 Low-Pressure Coolant Injection System 6.5.4 Integrated Operation of Core Standby Cooling Systems 6.6 INSPECTION AND TESTING 6.7 CONFORMANCE OF PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 EMERGENCY CORE COOLING SYSTEMS TO AEC/NRC INTERIM ACCEPTANCE CRITERIA FOR LIGHT WATER REACTORS 6.7.1 Introduction 6.7.2 Request for Additional Information 6.7.3 Additional Information Response 6.7.4 Summary 6.7.5 Effect of Revised Core Design on Emergency Core Cooling System's Analysis CHAPTER 06 6-i REV. 26, APRIL 2017
PBAPS UFSAR SECTION 6.0 - CORE STANDBY COOLING SYSTEMS LIST OF TABLES TABLE TITLE 6.3.1 Core Standby Cooling Systems Equipment Design Data Summary 6.7.1 Peak Clad Temperatures CHAPTER 06 6-ii REV. 26, APRIL 2017
PBAPS UFSAR SECTION 6.0 - CORE STANDBY COOLING SYSTEMS LIST OF FIGURES FIGURE TITLE 6.3.1 CSCS's Performance Capability Chart 6.4.1 Deleted 6.4.2 Deleted 6.5.1 Peak Cladding Temperature versus Time, Design Basis Accident Break.
6.5.2 Water Level in Hot and Average Channel vs Time, Design Basis Accident Break.
6.5.3 Reactor Pressure versus Time, Design Basis Accident Break.
6.5.4 Peak Cladding Temperature versus Time, 80% Design Basis Accident Break.
6.5.5 Water Level in Hot and Average Channel vs Time, 80%
Design Basis Accident Break.
6.5.6 Reactor Pressure versus Time, 80% Design Basis Accident Break.
6.5.7 Peak Cladding Temperature versus Time, 60% Design Basis Accident Break.
6.5.8 Water Level in Hot and Average Channel vs Time, 60%
Design Basis Accident Break.
6.5.9 Deleted.
6.5.10 Deleted.
6.5.11 Deleted.
6.5.12 Deleted.
6.7.1 Peak Clad Temperature Versus Break Area, Two Core Spray Systems, AEC/NRC Assumptions CHAPTER 06 6-iii REV. 26, APRIL 2017
PBAPS UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE 6.7.2 Cladding Temperature Versus Time, Two Core Spray Systems Plus ADS, AEC/NRC Assumptions, .02-Sq Ft Break 6.7.3 Cladding Temperature Versus Time, Two Core Spray Systems Plus ADS, AEC/NRC Assumptions, .05-Sq Ft Break 6.7.4 Design Basis Accident, Two Core Spray Systems, AEC/NRC Assumptions 6.7.5 Core Flow Following Design Basis Accident Versus Time 6.7.6 Heat Transfer Coefficient Versus Time, Two Core Spray Systems Plus ADS, AEC/NRC Assumptions, .02-Sq Ft Break 6.7.7 Heat Transfer Coefficient Versus Time, Two Core Spray Systems Plus ADS, AEC/NRC Assumptions, .05-Sq Ft Break 6.7.8 Heat Transfer Coefficient Versus Time, Two Core Spray Systems, AEC/NRC Assumptions, Design Basis Accident 6.7.9 Reactor Pressure Vessel Water Level Versus Time, Two Core Spray Systems Plus ADS, AEC/NRC Assumptions, .02-Sq Ft Break 6.7.1 Reactor Pressure Vessel Water Level Versus Time, Two Core Spray Systems Plus ADS, AEC/NRC Assumptions, .05-Sq Ft Break 6.7.11 Reactor Pressure Vessel Water Level Versus Time, Two Core Spray Systems, AEC/NRC Assumptions, Design Basis Accident 6.7.12 Minimum Critical Heat Flux Ratio Versus Time Following a Design Basis Accident 6.7.13 Peak Clad Temperature Versus Time, 1,000 MWd/T Exposure, Two Core Spray Systems, AEC/NRC Assumptions, .05-Sq Ft Break CHAPTER 06 6-iv REV. 26, APRIL 2017
PBAPS UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE 6.7.14 Peak Clad Temperature Versus Time, 10,000 MWd/T Exposure, Two Core Spray Systems, AEC/NRC Assumptions, .05-Sq Ft Break 6.7.15 Peak Clad Temperature Versus Time, 25,000 MWd/T Exposure, Two Core Spray Systems, AEC/NRC Assumptions, .05-Sq Ft Break 6.7.16 Peak Clad Temperature Versus Time, 1,000 MWd/T Exposure, Two Core Spray Systems, AEC/NRC Assumptions, Design Basis Accident 6.7.17 Peak Clad Temperature Versus Time, 10,000 MWd/T Exposure, Two Core Spray Systems, AEC/NRC Assumptions, Design Basis Accident 6.7.18 Peak Clad Temperature Versus Time, 25,000 MWd/T Exposure, Two Core Spray Systems, AEC/NRC Assumptions, Design Basis Accident 6.7.18a Peaking Factor Study, Effect of Exposure on Maximum Cladding Temperature for Peach Bottom Units 2 and 3 6.7.19 Power Generation Following a Design Basis LOCA 6.7.20 Quality Versus Time for the Design Basis Accident CHAPTER 06 6-v REV. 26, APRIL 2017