ML23110A198
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PBAPS UFSAR SECTION 4.0 - REACTOR COOLANT SYSTEM TABLE OF CONTENTS SECTION TITLE 4.1
SUMMARY
DESCRIPTION 4.2 REACTOR VESSEL AND APPURTENANCES MECHANICAL DESIGN 4.2.1 Power Generation Objective 4.2.2 Power Generation Design Basis 4.2.3 Safety Design Basis 4.2.4 Description 4.2.4.1 Reactor Vessel 4.2.4.2 Shroud Support 4.2.4.3 Reactor Vessel Support Assembly 4.2.4.4 Vessel Stabilizers 4.2.4.5 Refueling Bellows 4.2.4.6 Control Rod Drive Housings 4.2.4.7 Control Rod Drive Housing Support 4.2.4.8 In-Core Neutron Flux Monitor Housings 4.2.4.9 Reactor Vessel Insulation 4.2.5 Safety Evaluation 4.2.5.1 Brittle Fracture Considerations 4.2.5.1.1 Compliance with 10CFR50 Appendix G, July 1983 4.2.5.1.2 Method of Initial RTNDT Evaluation 4.2.5.1.3 Calculated Values of Initial RTNDT 4.2.5.1.4 Irradiation Effects on Core Beltline 4.2.5.1.5 Operating Pressure - Temperature Limits Curves 4.2.5.1.6 Temperature Limit for Boltup and Pressurization 4.2.5.1.7 Temperature Limits for Hydrostatic or Leakage Tests 4.2.5.1.8 Temperature Limits for Non-Nuclear Heatup/Cooldown 4.2.5.1.9 Temperature Limits for Core Critical Operation 4.2.5.1.10 Operating Transients versus Pressure-Temperature Limits 4.2.6 Inspection and Testing 4.3 REACTOR RECIRCULATION SYSTEM 4.3.1 Power Generation Objective 4.3.2 Power Generation Design Basis 4.3.3 Safety Design Basis 4.3.4 Description 4.3.5 Safety Evaluation 4.3.6 Inspection and Testing 4.4 NUCLEAR SYSTEM PRESSURE RELIEF SYSTEM 4.4.1 Safety Objective 4.4.2 Safety Design Basis 4.4.3 Power Generation Objective CHAPTER 04 4-i REV. 25, APRIL 2015
PBAPS UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE 4.4.4 Power Generation Design Basis 4.4.5 Description 4.4.6 Safety Evaluation 4.4.7 Power Generation Evaluation 4.4.8 Inspection and Testing 4.5 MAIN STEAM LINE FLOW RESTRICTORS 4.5.1 Safety Objective 4.5.2 Safety Design Basis 4.5.3 Description 4.5.4 Safety Evaluation 4.5.5 Inspection and Testing 4.6 MAIN STEAM LINE ISOLATION VALVES 4.6.1 Safety Objective 4.6.2 Safety Design Basis 4.6.3 Description 4.6.4 Safety Evaluation 4.6.5 Inspection, Testing, and Operation with MSIV Closed 4.7 REACTOR CORE ISOLATION COOLING SYSTEM 4.7.1 Safety Objective 4.7.2 Safety Design Basis 4.7.3 Description 4.7.4 Safety Evaluation 4.7.5 Inspection and Testing 4.8 RESIDUAL HEAT REMOVAL SYSTEM 4.8.1 Safety Objective 4.8.2 Safety Design Basis 4.8.3 Power Generation Objective 4.8.4 Power Generation Design Basis 4.8.5 Summary Description 4.8.6 Description 4.8.6.1 Shutdown Cooling 4.8.6.2 Containment Cooling 4.8.6.3 Low-Pressure Coolant Injection 4.8.7 Safety Evaluation 4.8.8 Inspection and Testing 4.9 REACTOR WATER CLEANUP SYSTEM 4.9.1 Power Generation Objective CHAPTER 04 4-ii REV. 25, APRIL 2015
PBAPS UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE 4.9.2 Power Generation Design Basis 4.9.3 Description 4.9.4 Inspection and Testing 4.10 NUCLEAR SYSTEM LEAKAGE DETECTION AND LEAKAGE RATE LIMITS 4.10.1 Safety Objective 4.10.2 Safety Design Basis 4.10.3 Description 4.10.3.1 Identified Leakage Rate 4.10.3.2 Unidentified Abnormal Leakage Rate and Detection within the Primary Containment 4.10.3.3 Total Leakage Rate within the Primary Containment 4.10.3.4 Detection of Abnormal Leakage Outside the Primary Containment 4.10.4 Safety Evaluation 4.10.5 Inspection and Testing 4.11 MAIN STEAM LINES, FEEDWATER PIPING, AND DRAINS 4.11.1 Power Generation Objective 4.11.2 Power Generation Design Basis 4.11.3 Safety Design Basis 4.11.4 Description 4.11.5 Safety Evaluation 4.11.6 Inspection and Testing CHAPTER 04 4-iii REV. 25, APRIL 2015
PBAPS UFSAR SECTION 4.0 - REACTOR COOLANT SYSTEM LIST OF TABLES TABLE TITLE 4.2.1 Reactor Pressure Vessel Materials 4.2.2 Reactor Vessel Data 4.2.3 Reactor Vessel Attachments 4.2.4 Reactor Fatigue Monitoring Locations (60-Year Life) 4.2.5 Equivalent Tranverse RTNDT Valves for Reactor Vessel Materials for Unit 2 4.2.6 Equivalent Tranverse RTNDT Valves for Reactor Vessel Materials for Unit 3 4.2.7 Beltline Evaluation for Unit 2 4.2.8 Beltline Evaluation for Unit 3 4.3.1 Reactor Recirculation System Design Characteristics 4.4.1 Nuclear System Safety and Relief Valves 4.7.1 Reactor Core Isolation Cooling System Turbine Pump Design Data 4.8.1 Residual Heat Removal System Equipment Design Data 4.9.1 Reactor Water Cleanup System Equipment Data CHAPTER 04 4-iv REV. 25, APRIL 2015
PBAPS UFSAR SECTION 4.0 - REACTOR COOLANT SYSTEM LIST OF FIGURES FIGURE TITLE 4.2.1 Reactor Vessel Schematic 4.2.2 Reactor Vessel Nozzles and Penetrations 4.2.3 DELETED 4.2.4 DELETED 4.2.5 DELETED 4.3.1 Recirculation System Elevation, Isometric 4.3.2A Deleted 4.3.2B Deleted 4.3.3 Jet Pump Operating Principle 4.3.4 Recirculation System Core Flooding Capability 4.4.1 Nuclear System Relief Valve - Closed Position 4.4.2 Nuclear System Relief Valve - Open Position 4.4.3 DELETED 4.5.1 Main Steam Line Flow Restrictor Location 4.6.1 Main Steam Isolation Valve 4.7.1A Deleted 4.7.1B Deleted 4.7.2A Deleted 4.7.2B Deleted 4.7.2C Deleted 4.7.2D Deleted CHAPTER 04 4-v REV. 25, APRIL 2015
PBAPS UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE 4.7.2E Deleted 4.7.2F Deleted 4.8.1 Deleted 4.8.2 Deleted 4.9.1 Deleted 4.9.2 Deleted 4.9.3 Deleted 4.9.4A Deleted 4.9.4B Deleted 4.10.1 Drywell Leak Detection System Diagram 4.10.2 Drywell Sumps Diagram CHAPTER 04 4-vi REV. 25, APRIL 2015