ML21133A074
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LGS UFSAR CHAPTER 6 - ENGINEERED SAFETY FEATURES TABLE OF CONTENTS
6.0 INTRODUCTION
6.1 ENGINEERED SAFETY FEATURE MATERIALS 6.1.1 Metallic Materials 6.1.1.1 Materials Selection and Fabrication 6.1.1.1.1 NSSS Supplied Components 6.1.1.1.2 Non-NSSS Supplied Components 6.1.1.1.3 Controls for Austenitic Stainless Steel 6.1.1.2 Composition, Compatibility, and Stability of Containment and Core Spray Coolants 6.1.2 Organic Materials 6.1.2.1 NSSS Supplied Components 6.1.2.2 Non-NSSS Supplied Components 6.1.2.3 Insoluble Debris 6.1.3 Postaccident Chemistry 6.2 CONTAINMENT SYSTEMS 6.2.1 Containment Functional Design 6.2.1.1 Pressure-Suppression Containment 6.2.1.1.1 Design Bases 6.2.1.1.2 Design Features 6.2.1.1.3 Design Evaluation 6.2.1.1.4 Negative Pressure Design Evaluation 6.2.1.1.5 Steam Bypass of the Suppression Pool 6.2.1.1.6 Suppression Pool Dynamic Loads 6.2.1.1.7 Asymmetric Loading Conditions 6.2.1.1.8 Containment Environment Control 6.2.1.1.9 Postaccident Monitoring 6.2.1.2 Containment Subcompartments 6.2.1.3 Mass and Energy Release Analyses for Postulated LOCAs 6.2.1.3.1 Mass and Energy Release Data 6.2.1.3.2 Energy Sources 6.2.1.3.3 Reactor Blowdown Model Description 6.2.1.3.4 Effects of Metal-Water Reaction 6.2.1.3.5 Thermal-Hydraulic Data for Reactor Analysis 6.2.1.4 Pressurized Water Reactor - Not Applicable 6.2.1.5 Pressurized Water Reactor - Not Applicable 6.2.1.6 Testing and Inspection 6.2.1.7 Instrumentation Requirements 6.2.1.8 Containment System Response at Rerate Power CHAPTER 06 6-i REV. 20, SEPTEMBER 2020
LGS UFSAR TABLE OF CONTENTS (Cont'd) 6.2.2 Containment Heat Removal System 6.2.2.1 Design Bases 6.2.2.2 System Design 6.2.2.3 Design Evaluation 6.2.2.4 Tests and Inspections 6.2.2.5 Instrumentation Requirements 6.2.3 Secondary Containment Functional Design 6.2.3.1 Design Bases 6.2.3.2 System Design 6.2.3.2.1 Secondary Containment Design 6.2.3.2.2 Secondary Containment Isolation System 6.2.3.2.3 Containment Bypass Leakage 6.2.3.3 Design Evaluation 6.2.3.4 Tests and Inspections 6.2.3.5 Instrumentation Requirements 6.2.4 Containment Isolation System 6.2.4.1 Design Bases 6.2.4.2 System Design 6.2.4.3 Design Evaluation 6.2.4.3.1 Evaluation Against General Design Criteria 6.2.4.3.2 Failure Mode and Effects Analyses 6.2.4.4 Tests and Inspections 6.2.5 Combustible Gas Control in Containment 6.2.5.1 Design Bases 6.2.5.2 System Description 6.2.5.2.1 Containment Hydrogen Recombiner Subsystem 6.2.5.2.2 Combustible Gas Analyzer Subsystem 6.2.5.2.3 Containment Atmosphere Mixing 6.2.5.2.4 Post-LOCA Purging 6.2.5.2.5 Venting of Combustible Gases from the Reactor Vessel 6.2.5.3 Hydrogen and Oxygen Generation Analysis 6.2.5.4 Safety Evaluation 6.2.5.5 Tests and Inspections 6.2.5.6 Instrumentation Applications 6.2.5.6.1 Containment Hydrogen Recombiner Subsystem 6.2.5.6.2 Combustible Gas Analyzer Subsystem 6.2.6 Primary Reactor Containment Leakage Rate Testing 6.2.6.1 Primary Reactor Containment Integrated Leakage Rate Tests 6.2.6.2 Primary Containment Penetration Leakage Rate Tests 6.2.6.3 Primary Containment Isolation Valve Leakage Rate Tests 6.2.6.4 Scheduling and Reporting of Periodic Tests 6.2.6.5 Special Testing Requirements 6.2.6.5.1 Drywell Steam Bypass Test 6.2.6.5.2 Risk Informed Alternative Treatment Due to 10 CFR 50.69 6.2.7 Postaccident System Isolation 6.2.7.1 System Isolation Provisions CHAPTER 06 6-ii REV. 20, SEPTEMBER 2020
LGS UFSAR TABLE OF CONTENTS (Cont'd) 6.2.7.2 Potentially Contaminated Systems 6.2.8 Leakage Reduction Program 6.2.8.1 Systems to be Leak Tested 6.2.8.2 Systems Excluded from the Program 6.2.8.3 Leak Testing Method 6.2.9 References 6.3 EMERGENCY CORE COOLING SYSTEMS 6.3.1 Design Bases and Summary Description 6.3.1.1 Design Bases 6.3.1.1.1 Performance and Functional Requirements 6.3.1.1.2 Reliability Requirements 6.3.1.1.3 ECCS Requirements for Protection from Physical Damage 6.3.1.1.4 ECCS Environmental Design Basis 6.3.1.2 Summary Descriptions of ECCS 6.3.1.2.1 High Pressure Coolant Injection System 6.3.1.2.2 Core Spray System 6.3.1.2.3 Low Pressure Coolant Injection Subsystem 6.3.1.2.4 Automatic Depressurization System 6.3.1.2.5 Management of Gas Accumulation in Fluid Systems 6.3.2 System Design 6.3.2.1 Piping and Instrumentation and Process Diagrams 6.3.2.2 Equipment and Component Descriptions 6.3.2.2.1 High Pressure Coolant Injection System 6.3.2.2.2 Automatic Depressurization System 6.3.2.2.3 Core Spray System 6.3.2.2.4 Low Pressure Coolant Injection Subsystem 6.3.2.2.5 ECCS NPSH Margin and Vortex Formation 6.3.2.2.6 Safeguard Piping Fill System 6.3.2.3 Applicable Codes and Classification 6.3.2.4 Materials Specifications and Compatibility 6.3.2.5 System Reliability 6.3.2.6 Protection Provisions 6.3.2.7 Provisions for Performance Testing 6.3.2.8 Manual Actions 6.3.2.9 Correct Positioning of Manual Valves 6.3.3 ECCS Performance Evaluation 6.3.3.1 ECCS Bases for Technical Specifications 6.3.3.2 Acceptance Criteria for ECCS Performance 6.3.3.3 Single Failure Considerations 6.3.3.4 System Performance During the Accident 6.3.3.5 Use of Dual-Function Components for ECCS 6.3.3.6 Limits on ECCS System Parameters 6.3.3.7 ECCS Analyses for LOCA 6.3.3.7.1 LOCA Analysis Procedures and Input Variables 6.3.3.7.2 Accident Description CHAPTER 06 6-iii REV. 20, SEPTEMBER 2020
LGS UFSAR TABLE OF CONTENTS (Cont'd) 6.3.3.7.3 Break Spectrum Calculations 6.3.3.7.4 Large Recirculation Line Break Calculations 6.3.3.8 LOCA Analysis Conclusions 6.3.4 Tests and Inspections 6.3.4.1 ECCS Performance Tests 6.3.4.2 Reliability Tests and Inspections 6.3.4.2.1 HPCI Testing 6.3.4.2.2 ADS Testing 6.3.4.2.3 CS Testing 6.3.4.2.4 LPCI Testing 6.3.5 Instrumentation Requirements 6.3.6 References 6.4 HABITABILITY SYSTEMS 6.4.1 Design Bases 6.4.2 System Design 6.4.2.1 Definition of Control Room Envelope 6.4.2.2 Ventilation System Design 6.4.2.3 Leak-Tightness 6.4.2.4 Interaction with Other Zones and Pressure- Containing Equipment 6.4.2.5 Shielding Design 6.4.3 System Operational Procedures 6.4.3.1 Normal Operation 6.4.3.2 Postaccident Operation 6.4.3.2.1 Chlorine Isolation Mode 6.4.3.2.2 Radiation Isolation Mode 6.4.3.2.3 Toxic Chemical Isolation Mode 6.4.4 Design Evaluations 6.4.4.1 Radiological Protection 6.4.4.2 Toxic Gas Protection 6.4.4.2.1 Chlorine 6.4.4.2.2 Offsite Toxic Chemical System 6.4.4.2.3 Respiratory Protection 6.4.5 Testing and Inspection 6.4.6 Instrumentation Requirement 6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.5.1 Engineered Safety Feature Filter Systems 6.5.1.1 Standby Gas Treatment System 6.5.1.1.1 Design Bases CHAPTER 06 6-iv REV. 20, SEPTEMBER 2020
LGS UFSAR TABLE OF CONTENTS (Cont'd) 6.5.1.1.2 System Description 6.5.1.1.3 Design Evaluation 6.5.1.1.4 Tests and Inspections 6.5.1.1.5 Instrumentation 6.5.1.1.6 Materials 6.5.1.2 Control Room Emergency Fresh Air Filter Units 6.5.1.2.1 Design Bases 6.5.1.2.2 System Description 6.5.1.2.3 Design Evaluation 6.5.1.2.4 Tests and Inspections 6.5.1.2.5 Instrumentation 6.5.1.2.6 Materials 6.5.1.3 Reactor Enclosure Recirculation System Filter Units 6.5.1.3.1 Design Bases 6.5.1.3.2 System Description 6.5.1.3.3 Design Evaluation 6.5.1.3.4 Tests and Inspections 6.5.1.3.5 Instrumentation 6.5.1.3.6 Materials 6.5.2 Containment Spray System 6.5.3 Fission Product Control Systems 6.5.3.1 Primary Containment 6.5.3.2 Secondary Containment 6.5.4 Ice Condenser as a Fission Product Cleanup System 6.5.5 References 6.6 PRESERVICE/INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS 6.6.1 Components Subject to Examination 6.6.2 Accessibility 6.6.3 Examination Techniques and Procedures 6.6.4 Inspection Intervals 6.6.5 Examination Categories and Requirements 6.6.6 Evaluation of Examination Results 6.6.7 System Pressure Tests 6.6.8 Augmented Inservice Inspection to Protect Against Postulated Piping Failures 6.6.9 References CHAPTER 06 6-v REV. 20, SEPTEMBER 2020
LGS UFSAR TABLE OF CONTENTS (Cont'd) 6.7 MSIV LEAKAGE ALTERNATE DRAIN PATHWAY 6.7.1 Design Bases 6.7.1.1 Safety Criteria 6.7.1.2 Regulatory Acceptance Criteria 6.7.1.3 Deleted 6.7.2 System Description 6.7.2.1 Deleted 6.7.2.2 Deleted 6.7.2.3 Deleted 6.7.2.4 Deleted 6.7.3 System Evaluation 6.7.3.1 Delete 6.7.3.2 Delete 6.7.3.3 Delete 6.7.3.4 Delete 6.7.3.5 Delete 6.7.3.6 Delete 6.7.3.7 Delete 6.7.3.8 Delete 6.7.4 Instrumentation Requirements 6.7.5 Inspection and Testing 6.7.6 References Appendix 6A Subcompartment Differential Pressure Considerations CHAPTER 06 6-vi REV. 20, SEPTEMBER 2020
LGS UFSAR TABLE OF CONTENTS (Cont'd)
CHAPTER 6 - ENGINEERED SAFETY FEATURES LIST OF TABLES TABLE TITLE 6.1-1 Engineered Safety Features Discussed in Other Chapters of the UFSAR 6.1-2 NSSS Supplied Engineered Safety Features Component Materials 6.1-3 Principal Pressure-Retaining Materials for ESF Components 6.1-4 Organic Materials Within the Primary Containment 6.1-5 Coatings Used Inside the Primary Containment 6.1-6 Estimated Weight of Unqualified Paint on NSSS Containment Equipment 6.2-1 Containment Design Parameters 6.2-2 Engineered Safety Feature Systems Information for Containment Response Analyses 6.2-3 Accident Assumptions and Initial Conditions for Containment Response Analyses 6.2-4 Initial Conditions for Containment Response Analyses (Original design conditions) 6.2-4A Initial Conditions for Containment Response Analyses at Rerate Power Conditions 6.2-5 Summary of Short-Term Containment Responses to Recirculation Line and Main Steam Line Breaks (Original design conditions) 6.2-5A Containment LOCA Response at Rerate Power Conditions 6.2-6 Summary of Long-Term Containment Responses to Recirculation Line and Main Steam Line Breaks 6.2-7 Energy Balance for Recirculation Line Break Accident 6.2-8 Accident Chronology for Recirculation Line Break Accident 6.2-9 Initial and Boundary Conditions for Drywell Spray Actuation Analysis 6.2-10 Reactor Blowdown Data for Recirculation Line Break 6.2-11 Reactor Blowdown Data for Main Steam Line Break 6.2-12 Core Decay Heat Following LOCA for Containment Analyses 6.2-13 Secondary Containment Access Openings CHAPTER 06 6-vii REV. 20, SEPTEMBER 2020
LGS UFSAR LIST OF TABLES (cont'd)
TABLE TITLE 6.2-14 Secondary Containment Design Data 6.2-15 Evaluation of Potential Secondary Containment Bypass Leakage Paths 6.2-16 Accident Chronology for Main Steam Line Break Accident 6.2-17 Containment Penetration Data 6.2-18 Assumptions Used in Evaluating the Production of Combustible Gases Following a LOCA 6.2-19 Parameters Used in Evaluating the Production of Hydrogen Following a LOCA 6.2-20 Containment Hydrogen Recombiner Subsystem Failure Modes and Effects Analysis 6.2-21 Combustible Gas Analyzer Subsystem Failure Modes and Effects Analysis 6.2-22 Type A Test Data 6.2-23 Data Acquisition System for Primary Containment Integrated Leakage Rate Test 6.2-24 System Venting and Draining Exceptions for Primary Containment Integrated Leakage Rate Test 6.2-25 Containment Penetrations Compliance with 10CFR50, Appendix J 6.2-26 Remotely Actuated Valves Required for Postaccident System Isolation 6.2-27 Essential/Nonessential Systems 6.2-28 Reactor Enclosure and Refueling Area Secondary Containment Ventilation System Automatic Isolation Valves (Separate Zone System Alignment) 6.2-29 Reactor Enclosure and Refueling Area Secondary Containment Ventilation System Automatic Isolation Valves (Combined Zone Alignment) 6.3-1 Significant Input Variables Used in the SAFER/GESTR Analysis 6.3-1A Significant Input Variables Used in the Reference 6.3-1 Methodology.
6.3-2 Operational Sequence of ECCS for Design Basis LOCA 6.3-2A Operational Sequence of ECCS for Design Basis LOCA Based on Original Plant Conditions and Reference 6.3-1 Methodology 6.3-3 Single Failure Evaluation 6.3-4 Deleted 6.3-5 Summary of Results of LOCA Analysis with SAFER/GESTR-LOCA Using Table 6.2-1 Inputs CHAPTER 06 6-viii REV. 20, SEPTEMBER 2020
LGS UFSAR LIST OF TABLES (cont'd)
TABLE TITLE 6.3-6 Deleted 6.3-7 Deleted 6.4-1 Control Room Emergency HVAC System Failure Analysis 6.4-2 Control Room Potential Leak Paths 6.5-1 Engineering Safety Feature Filter Systems Design Parameters 6.5-2 Compliance with Regulatory Guide 1.52 of Light-Water-Cooled Nuclear Power Plants (Rev 2) 6.5-3 Standby Gas Treatment System Failure Modes and Effects Analysis 6.5-4 Materials Used in the Standby Gas Treatment Filter System 6.5-5 Materials Used in the Control Room Emergency Fresh Air Filter System 6.5-6 Reactor Enclosure Recirculation System Failure Modes and Effects Analysis (Typical for Zone I or Zone II) 6.5-7 Materials Used in the Reactor Enclosure Recirculation Filter System 6.5-8 Instrumentation for ESF Atmosphere Cleanup Systems 6.7-1 Deleted CHAPTER 06 6-ix REV. 20, SEPTEMBER 2020
LGS UFSAR CHAPTER 6 - ENGINEERED SAFETY FEATURES LIST OF FIGURES FIGURE TITLE 6.2-1 Downcomer Design Details 6.2-2 Effective Blowdown Area for Recirculation Line Break 6.2-3 Short-Term Containment Pressure Response Following Recirculation Line Break 6.2-3A Short-Term Containment Pressure Response Following Recirculation Line Break at Rerate Power Conditions 6.2-4 Short-Term Containment Temperature Response Following Recirculation Line Break 6.2-4A Short-Term Containment Temperature Response Following Recirculation Line Break at Power Rerate Conditions 6.2-5 Short-Term Differential Pressure Across Diaphragm Slab Following Recirculation Line Break 6.2-6 Short-Term Downcomer Flow Following Recirculation Line Break 6.2-7 Long-Term Containment Pressure Response Following Recirculation Line or Main Steam Line Break 6.2-7A Long-Term Containment Pressure LOCA Response - Case C at 3528 MWt 6.2-8 Long-Term Drywell Temperature Response Following Recirculation Line or Main Steam Line Break 6.2-8A Long-Term Containment Temperature Response - Case C at 3528 MWt 6.2-9 Long-Term Suppression Pool Temperature Response Following Recirculation Line or Main Steam Line Break 6.2-9A Long-Term Suppression Pool Temperature Response - Case C at 3528 MWt 6.2-10 RHR Heat Removal Rate Following Recirculation Line or Main Steam Line Break 6.2-11 Effective Blowdown Area for Main Steam Line Break 6.2-12 Short-Term Containment Pressure Response Following Main Steam Line Break CHAPTER 06 6-x REV. 20, SEPTEMBER 2020
LGS UFSAR LIST OF FIGURES FIGURE TITLE 6.2-13 Short-Term Containment Temperature Response Following Main Steam Line Break 6.2-14 Short-Term Containment Pressure Response Following Intermediate Size Break (0.1 ft2 Liquid Break) 6.2-15 Short-Term Containment Temperature Response Following Intermediate Size Break (0.1 ft2 Liquid Break) 6.2-16 Schematic of Analytical Model for RHR Containment Cooling System 6.2-17 Model for Analysis of Inadvertent Drywell Spray Actuation 6.2-18 Thermal Heat Removal Efficiency of Drywell Spray 6.2-19 Drywell Pressure Response to Spray Actuation 6.2-20 Drywell Temperature Response to Spray Actuation 6.2-21 Maximum Allowable Steam Bypass Leakage Flow Area 6.2-22 Reactor Vessel Liquid Blowdown Flow Rate Following Recirculation Line Break 6.2-23 Reactor Vessel Steam Blowdown Flow Rate Following Recirculation Line Break 6.2-24 Reactor Vessel Blowdown Flow Rate Following Main Steam Line Break 6.2-25 Reactor Vessel Temperature Response Following Recirculation Line Break 6.2-26 Sensible Energy in Reactor Vessel and Internal Structure Metals Following Recirculation Line Break 6.2-27 Secondary Containment Boundary Outline, Plan at el 177' 6.2-28 Secondary Containment Boundary Outline, Plan at el 201' 6.2-29 Secondary Containment Boundary Outline, Plan at el 217' 6.2-30 Secondary Containment Boundary Outline, Plan at el 253' 6.2-31 Secondary Containment Boundary Outline, Plan at el 283' 6.2-32 Secondary Containment Boundary Outline, Plan at el 313' 6.2-33 Secondary Containment Boundary Outline, Plan at el 352' 6.2-34 Secondary Containment Boundary Outline, North-South Section View (Unit 1) 6.2-35 Secondary Containment Boundary Outline, East-West Section View 6.2-36 Containment Penetration Details CHAPTER 06 6-xi REV. 20, SEPTEMBER 2020
LGS UFSAR LIST OF FIGURES FIGURE TITLE 6.2-37 Deleted 6.2-38 Containment Hydrogen Recombiner Skid, Cutaway View 6.2-39 Rate of Energy Absorption by LOCA Water as a Function of Time After LOCA 6.2-40 Integrated Energy Absorption by LOCA Water as a Function of Time After LOCA 6.2-41 Integrated Hydrogen Production as a Function of Time After LOCA 6.2-42 Short-Term Containment Hydrogen Concentration After LOCA 6.2-43 Long-Term Containment Hydrogen Concentration After LOCA 6.2-44 Short-Term Containment Oxygen Concentration After LOCA 6.2-45 Long-Term Containment Oxygen Concentration After LOCA 6.2-46 Long-Term Suppression Chamber Oxygen Concentration After LOCA 6.2-47 Deleted 6.2-48 Containment Personnel Lock Penetrations 6.2-49 Containment Personnel Lock Door Seals 6.2-50 Containment Personnel Lock Inner Door Tie-downs 6.2-51 Suppression Pool Suction Strainers 6.2-52 Reactor Enclosure Drawdown 6.2-53 Event Tree for TIP System Line Isolation 6.3-1 Deleted 6.3-2 Deleted 6.3-3 Deleted 6.3-4 Deleted 6.3-5 Deleted 6.3-6 Deleted 6.3-7 Deleted CHAPTER 06 6-xii REV. 20, SEPTEMBER 2020
LGS UFSAR LIST OF FIGURES FIGURE TITLE 6.3-8 Deleted 6.3-9 Deleted 6.3-10 Deleted 6.3-11 Normal Power vs Time After Break (Original 6.3-1 Method) 6.3-11A Normalized Power vs Time After Break (SAFER/GESTR Methodology) 6.3-12 thru Deleted 6.3-74 6.4-1 Control Room Arrangement 6.4-2 Plant Layout with Respect to Control Room Intake 6.7-1 Deleted 6.7-2 Deleted 6.7-3 Deleted 6.7-4 Deleted 6.7-5 Deleted CHAPTER 06 6-xiii REV. 20, SEPTEMBER 2020