ML22278A232
| ML22278A232 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/19/2022 |
| From: | Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML22278A223 | List:
|
| References | |
| Download: ML22278A232 (9) | |
Text
LGS UFSAR CHAPTER 5 - REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS TABLE OF CONTENTS 5.1
SUMMARY
DESCRIPTION 5.1.1 Schematic Flow Diagram 5.1.2 Piping and Instrumentation Diagrams 5.1.3 Arrangement Drawings 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 5.2.1 Compliance with Codes and Code Cases 5.2.1.1 Compliance with 10CFR50.55a 5.2.1.2 Applicable Code Cases 5.2.2 Overpressure Protection 5.2.2.1 Design Basis 5.2.2.1.1 Safety Design Bases 5.2.2.1.2 Power Generation Design Bases 5.2.2.1.3 Discussion 5.2.2.1.4 Main Steam Safety/Relief Valve Capacity 5.2.2.2 Design Evaluation 5.2.2.2.1 Method of Analysis 5.2.2.2.2 System Design 5.2.2.2.3 Evaluation of Results 5.2.2.3 Piping & Instrument Diagrams 5.2.2.4 Equipment and Component Description 5.2.2.4.1 Description 5.2.2.4.2 Design Parameters 5.2.2.5 Mounting of Main Steam Relief Valves 5.2.2.6 Applicable Codes and Classification 5.2.2.7 Material Specification 5.2.2.8 Process Instrumentation 5.2.2.9 System Reliability 5.2.2.10 Inspection and Testing 5.2.3 Reactor Coolant Pressure Boundary Materials 5.2.3.1 Material Specifications 5.2.3.2 Compatibility With Reactor Coolant 5.2.3.2.1 PWR Chemistry of Reactor Coolant 5.2.3.2.2 BWR Chemistry of Reactor Coolant 5.2.3.2.3 Compatibility of Construction Materials with Reactor Coolant 5.2.3.2.4 Compatibility of Construction Materials with External Insulation and Reactor Coolant 5.2.3.3 Fabrication and Processing of Ferritic Materials 5.2.3.3.1 Fracture Toughness of Ferritic Materials CHAPTER 05 5-i REV. 21, SEPTEMBER 2022
LGS UFSAR TABLE OF CONTENTS (cont'd) 5.2.3.3.2 Control of Welding 5.2.3.3.3 Nondestructive Examination of Ferritic Tubular Products - Regulatory Guide 1.66 (October 1973) 5.2.3.3.4 Moisture Control for Low Hydrogen, Covered Arc Welding Electrodes 5.2.3.4 Fabrication and Processing of Austenitic Stainless Steels 5.2.3.4.1 Avoidance of Stress-Corrosion Cracking 5.2.3.4.2 Control of Welding 5.2.3.4.3 Nondestructive Examination of Tubular Products - Regulatory Guide 1.66 5.2.4 Preservice/Inservice Inspection, Examination and Testing of the Reactor Coolant Pressure Boundary 5.2.4.1 System Boundary 5.2.4.2 Accessibility 5.2.4.3 Examination Techniques and Procedures 5.2.4.4 Inspection Intervals 5.2.4.5 Examination Categories and Requirements 5.2.4.6 Evaluation of Examination Results 5.2.4.7 System Leakage and Hydrostatic Pressure Tests 5.2.4.8 Augmented Inservice Inspection 5.2.5 Reactor Coolant Pressure Boundary Leak Detection System 5.2.5.1 Design Bases 5.2.5.2 Description 5.2.5.2.1 Detection of Abnormal Leakage Within the Primary Containment 5.2.5.2.2 Detection of Abnormal Leakage Outside the Primary Containment 5.2.5.3 Indication in Control Room 5.2.5.4 Limits for Reactor Coolant Leakage Inside the Containment 5.2.5.5 Sensitivity and Response Time 5.2.5.6 Crack Length and Through-Wall Flow 5.2.5.7 Margins of Safety 5.2.5.8 Criteria to Evaluate the Adequacy and Margin of the Leak Detection System 5.2.5.9 Differentiation Between Identified and Unidentified Leakage 5.2.5.10 Sensitivity and Operability Tests 5.2.5.11 Testing and Calibration 5.2.6 References 5.3 REACTOR VESSEL 5.3.1 Reactor Vessel Materials 5.3.1.1 Materials Specifications 5.3.1.2 Special Processes Used for Manufacturing and Fabrication 5.3.1.3 Special Methods for Nondestructive Examination 5.3.1.4 Special Controls for Ferritic and Austenitic Stainless Steels 5.3.1.4.1 Compliance with Regulatory Guide 5.3.1.5 Fracture Toughness 5.3.1.5.1 Assessment of 10CFR50, Appendix G CHAPTER 05 5-ii REV. 21, SEPTEMBER 2022
LGS UFSAR TABLE OF CONTENTS (cont'd) 5.3.1.5.2 Method of Compliance 5.3.1.5.3 Methods of Obtaining Operating Limits Based on Fracture Toughness 5.3.1.6 Material Surveillance 5.3.1.6.1 Compliance with "Reactor Vessel Material Surveillance Program Requirements" 5.3.1.6.2 Neutron Flux and Fluence Calculations 5.3.1.6.3 Predicted Irradiation Effects on Vessel Beltline Materials 5.3.1.6.4 Positioning of Surveillance Capsules and Method of Attachment 5.3.1.6.5 Time and Number of Dosimetry Measurements 5.3.1.7 Vessel Beltline Plates and Welds 5.3.1.7.1 Test Data 5.3.1.7.2 Effects of Irradiation 5.3.1.7.3 Upper-Shelf Toughness Testing 5.3.1.8 Nonbeltline Region and Ferritic Piping and Valves 5.3.1.9 Assessment of Appendix G, 1983 Revision 5.3.1.10 RPV Surveillance Program 5.3.1.10.1 LGS Unit 1 Surveillance Program 5.3.1.10.2 LGS Unit 2 Surveillance Program 5.3.1.11 Reactor Vessel Fasteners 5.3.2 Pressure - Temperature Limits 5.3.2.1 Limit Curves 5.3.2.1.1 Temperature Limits for Bolt-up 5.3.2.1.2 Temperature Limit for Preoperational Tests and Inservice Inspection 5.3.2.1.3 Operating Limits During Heatup, Cooldown, and Core Operation 5.3.2.1.4 Reactor Vessel Annealing 5.3.2.2 Operating Procedures 5.3.3 Reactor Vessel Integrity 5.3.3.1 Design 5.3.3.1.1 Description 5.3.3.1.2 Safety Design Basis 5.3.3.1.3 Power Generation Design Basis 5.3.3.1.4 Reactor Vessel Design Data 5.3.3.2 Materials of Construction 5.3.3.3 Fabrication Methods 5.3.3.4 Inspection Requirements 5.3.3.5 Shipment and Installation 5.3.3.6 Operating Conditions 5.3.3.7 Inservice Surveillance 5.3.4 References 5.4 COMPONENT AND SUBSYSTEM DESIGN 5.4.1 Reactor Recirculation Pumps 5.4.1.1 Safety Design Bases 5.4.1.2 Power Generation Design Bases 5.4.1.3 Description CHAPTER 05 5-iii REV. 21, SEPTEMBER 2022
LGS UFSAR TABLE OF CONTENTS (cont'd) 5.4.1.4 Safety Evaluation 5.4.1.5 Inspection and Testing 5.4.2 Steam Generators (PWR) 5.4.3 Reactor Coolant Piping 5.4.4 Main Steam Line Flow Restrictors 5.4.4.1 Safety Design Bases 5.4.4.2 Description 5.4.4.3 Safety Evaluation 5.4.4.4 Inspection and Testing 5.4.5 Main Steam Line Isolation System 5.4.5.1 Safety Design Bases 5.4.5.2 Description 5.4.5.3 Safety Evaluation 5.4.5.4 Inspection and Testing 5.4.6 Reactor Core Isolation Cooling (RCIC) System 5.4.6.1 Design Bases 5.4.6.1.1 Residual Heat and Isolation 5.4.6.1.2 Reliability, Operability, and Manual Operation 5.4.6.1.3 Loss of Offsite Power 5.4.6.1.4 Physical Damage 5.4.6.1.5 Environment 5.4.6.2 System Design 5.4.6.2.1 General 5.4.6.2.2 Equipment and Component Description 5.4.6.2.3 System Reliability Considerations 5.4.6.2.4 System Operation 5.4.6.3 Performance Evaluation 5.4.6.4 Preoperational Testing 5.4.6.5 Safety Interfaces 5.4.7 Residual Heat Removal System 5.4.7.1 Design Bases 5.4.7.1.1 Functional Design Basis 5.4.7.1.2 Design Basis for Isolation of RHR System from Reactor Coolant System 5.4.7.1.3 Design Basis for Pressure Relief Capacity 5.4.7.1.4 Design Basis with Respect to GDC 5 5.4.7.1.5 Design Basis for Reliability and Operability 5.4.7.1.6 Design Basis for Protection from Physical Damage 5.4.7.2 System Design 5.4.7.2.1 System Diagrams 5.4.7.2.2 Equipment and Component Description 5.4.7.2.3 Controls and Instrumentation 5.4.7.2.4 Applicable Codes and Classifications 5.4.7.2.5 Reliability Considerations CHAPTER 05 5-iv REV. 21, SEPTEMBER 2022
LGS UFSAR TABLE OF CONTENTS (cont'd) 5.4.7.2.6 Manual Action 5.4.7.3 Performance Evaluation 5.4.7.3.1 Shutdown with All Components Available 5.4.7.3.2 Shutdown with Most Limiting Failure 5.4.7.4 Preoperational Testing 5.4.7.5 Conformance to Regulatory Guide 1.139 5.4.8 Reactor Water Cleanup System 5.4.8.1 Design Basis 5.4.8.1.1 Safety Design Basis 5.4.8.1.2 Power Generation Design Basis 5.4.8.2 System Description 5.4.8.3 System Evaluation 5.4.9 Main Steam Line and Feedwater Piping 5.4.10 Pressurizer 5.4.11 Pressurizer Relief Discharge System 5.4.12 Valves 5.4.12.1 Safety Design Bases 5.4.12.2 Description 5.4.12.3 Safety Evaluation 5.4.12.4 Inspection and Testing 5.4.13 Safety and Relief Valves 5.4.13.1 Safety Design Bases 5.4.13.2 Description 5.4.13.3 Safety Evaluation 5.4.13.4 Inspection and Testing 5.4.14 Component Supports 5.4.14.1 Design Bases 5.4.14.2 Description 5.4.14.3 Safety Evaluation 5.4.14.4 Inspection and Testing 5.4.15 References CHAPTER 05 5-v REV. 21, SEPTEMBER 2022
LGS UFSAR CHAPTER 5 - REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS LIST OF TABLES TABLE TITLE 5.2-1 Applicable Code Cases for Reactor Coolant Pressure Boundary Components 5.2-2 Nuclear System Safety/Relief Valve Setpoints 5.2-3 Reactor Coolant Pressure Boundary Materials 5.2-4 Expected BWR Water Chemistry for Normal Operation 5.2-5 Systems That May Initiate During Overpressure Event 5.2-6 Water Sample Locations 5.2-7 Leak Detection Methods Used and System Alarms and Interlocks Provided 5.2-8 Sequence of Events (REDY, ODYN, and TRACG) 5.2-9 RCPB Operating Thermal Cycles 5.2-10 Main Steam Sweepolet Material Data from Other BWRs 5.2-11 MSIV Bonnet Cover Material 5.2-12 MSIV Body Data 5.2-13 MSIV Body Data From Other BWRs 5.3-1 Appendix G Matrix for LGS 5.3-2 Appendix H Matrix for LGS 5.3-3 LGS Beltline Plate Toughness Data 5.3-4 Beltline Weld Toughness Data 5.3-5 LGS Beltline Plate Welds and Forgings EOL RTNDT Based on 57 EFPY 5.3-6 LGS Typical Beltline Plate (Surveillance Plate) 5.3-7 SA533 Grade B, Class 1 Plate Toughness Data Base Including Upper-Shelf CHAPTER 05 5-vi REV. 21, SEPTEMBER 2022
LGS UFSAR LIST OF TABLES (cont'd)
TABLE TITLE 5.3-8 Upper-Shelf Toughness for Beltline Welds 5.3-9 Weld Procedure Specification for Vessel Material Representative of LGS Beltline Welds (Unit 1) 5.3-10 Typical Surveillance Program Weld Procedure for LGS and Other BWRs 5.3-11 Estimated RTNDT for Components in LGS Vessel Nonbeltline Region 5.3-12 Surveillance Capsule 5.4-1 Reactor Recirculation System Design Characteristics 5.4-2 Reactor Water Cleanup System Equipment Design Data 5.4-3 RHR System Relief Valve Data CHAPTER 05 5-vii REV. 21, SEPTEMBER 2022
LGS UFSAR CHAPTER 5 - REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS LIST OF FIGURES FIGURE TITLE 5.1-1 Rated Operating Conditions of the Boiling Water Reactor - Historical 5.1-2 Coolant Volumes of the Boiling Water Reactor 5.1-3 Deleted 5.1-4 Deleted 5.1-5 Pipe Routing of Reactor Coolant System and Associated Systems 5.1-6 Reactor Recirculation System 5.1-7 Main Steam Piping Layout Inside Primary Containment 5.2-1 Intentionally Left Blank 5.2-2 Overpressure Transient Response to MSIV Closure with Flux Scram (ODYN) 5.2-3 Control Rod Position and Scram Reactivity versus Time Characteristic 5.2-4 Intentionally Left Blank 5.2-5 Intentionally Left Blank 5.2-6 Safety/Relief Valve Schematic Elevation 5.2-7 MSRV and Steam Line Schematic 5.2-8 Two-Stage, Pilot Actuated, Safety/Relief Valve (Vertical Discharge) 5.2-9 Typical BWR Flow Diagram 5.2-10 Conductance Vs pH as a Function of Chloride Concentration of Aqueous Solution at 25oC 5.2-11 Deleted 5.2-12 Calculated Leak Rate as a Function of Crack Length and Applied Hoop Stress 5.2-13 Axial Through-Wall Crack Length Data Correlation 5.3-1 Reactor Vessel Cutaway Diagram 5.3-2 Nominal Reactor Vessel Water Level Trip and Alarm Elevation Settings CHAPTER 05 5-viii REV. 21, SEPTEMBER 2022
LGS UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE 5.3-3 Surveillance Capsule 5.3-4 Minimum Temperatures Required versus Reactor Pressure (Unit 1) 5.3-5 Minimum Temperatures Required versus Reactor Pressure (Unit 2) 5.3-6 Intentionally Left Blank 5.3-7 Beltline Plate and Weld Seam Locations 5.3-8 General Welding Techniques 5.4-1 Recirculation System Elevation and Isometric 5.4-2 Deleted 5.4-3 Recirculation Pump Head, NPSH, and Efficiency Curves 5.4-4 Operating Principle of Jet Pump 5.4-5 Core Flooding Capability of Recirculation System 5.4-6 Main Steam Line Flow Restrictor 5.4-7 Main Steam Isolation Valve 5.4-8 Deleted 5.4-9 Deleted 5.4-10 Deleted 5.4-11 Vessel Coolant Temperature versus Time (Two Heat Exchangers Available) 5.4-12 Vessel Coolant Temperature versus Time (One Heat Exchanger Available) 5.4-13 Deleted 5.4-14 Deleted 5.4-15 RHR Pump Characteristic Curves 5.4-16 Deleted 5.4-17 Deleted 5.4-18 Deleted CHAPTER 05 5-ix REV. 21, SEPTEMBER 2022