ML19150A464
Text
GINNA/UFSAR 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 1 5.1
SUMMARY
DESCRIPTION 2 5.1.1 GENERAL 2 5.1.2 PERFORMANCE OBJECTIVES 2 5.1.3 DESIGN CRITERIA 2 5.1.3.1 Quality Standards 3 5.1.3.2 Performance Standards 3 5.1.3.3 Records Requirements 4 5.1.3.4 Missile Protection 4 5.1.3.5 Reactor Coolant Pressure Boundary 4 5.1.3.6 Monitoring Reactor Coolant Leakage 5 5.1.3.7 Reactor Coolant Pressure Boundary Capability 6 5.1.3.8 Reactor Coolant Pressure Boundary Rapid Propagation Failure Prevention 6 5.1.3.9 Reactor Coolant Pressure Boundary Surveillance 7 5.1.3.10 Adequacy of Reactor Coolant System Design Relative to 1972 10 CFR 50, 8 Appendix A, Criteria 5.1.4 DESIGN CHARACTERISTICS 8 5.1.4.1 Design Pressure 8 5.1.4.2 Design Temperature 9 5.1.5 CYCLIC LOADS 9 5.1.6 SERVICE LIFE 9 5.1.7 RELIANCE ON INTERCONNECTED SYSTEMS 10 5.1.8 SYSTEM INCIDENT POTENTIAL 10 Table 5.1-1 REACTOR COOLANT SYSTEM PRESSURE SETTINGS 12 Table 5.1-2 REACTOR COOLANT PIPING DESIGN DATA 13 Table 5.1-3 REACTOR COOLANT SYSTEM DESIGN PRESSURE DROP 14 Table 5.1-4 THERMAL AND LOADING CYCLES 15 5.2 INTEGRITY OF THE REACTOR COOLANT PRESSURE BOUNDARY 16 5.2.1 COMPLIANCE WITH CODES 16 5.2.1.1 System Integrity 16 5.2.1.2 Codes and Classifications 17 5.2.1.2.1 Code Requirements 17 5.2.1.2.2 Quality Control 17 5.2.1.2.3 Field Erection Procedures 18 5.2.1.3 Seismic Loads 18 Page 1 of 8 Revision 28 5/2019
GINNA/UFSAR 5.2.2 OVERPRESSURIZATION PROTECTION 19 5.2.2.1 Normal Operation 19 5.2.2.2 Low Temperature Overpressure Protection (LTOP) System 19 5.2.2.2.1 Design Bases 20 5.2.2.2.2 System Description 20 5.2.2.2.3 System Evaluation 21 5.2.2.2.3.1 General 21 5.2.2.2.3.2 Mass Addition Case 22 5.2.2.2.3.3 Heat Addition at 60F 22 5.2.2.2.3.4 Heat Addition at 320F 23 5.2.2.2.3.5 Administrative Controls 23 5.2.2.2.4 Tests and Inspections 24 5.2.3 REACTOR COOLANT PRESSURE BOUNDARY MATERIALS 24 5.2.3.1 Material Specifications 24 5.2.3.1.1 Nondestructive Examination of Materials and Components Prior to Operation 24 5.2.3.1.1.1 Quality Assurance Program 24 5.2.3.1.1.2 Welding and Heat Treatment 25 5.2.3.1.2 Quality Assurance for Electroslag Welds 26 5.2.3.1.2.1 Piping Elbows 26 5.2.3.1.2.2 Reactor Coolant Pump Casings 26 5.2.3.1.2.3 Reactor Coolant Pump Field Erection and Welding 28 5.2.3.2 Compatibility With Reactor Coolant 28 5.2.4 INSERVICE INSPECTION AND TESTING OF THE REACTOR COOLANT SYS- 29 TEM PRESSURE BOUNDARY 5.2.4.1 Inservice Inspection Program 29 5.2.4.2 Inspection Areas and Components 29 5.2.4.2.1 Accessible Components and Areas 29 5.2.4.2.2 Accessible Areas During Refueling 31 5.2.4.3 Accessibility 31 5.2.4.4 Examination Methods 32 5.2.4.5 Evaluation of Examination Results 33 5.2.4.6 Repair Requirements 33 5.2.4.7 Pressure Testing 33 5.2.4.8 Exemptions 33 Page 2 of 8 Revision 28 5/2019
GINNA/UFSAR 5.2.5 DETECTION OF LEAKAGE THROUGH REACTOR COOLANT PRESSURE 34 BOUNDARY 5.2.5.1 Leakage Detection Methods 34 5.2.5.2 Leakage Limitations 35 5.2.5.3 Locating Leaks 36 5.2.5.4 Leakage Detection System Descriptions 36 5.2.5.4.1 Containment Air Particulate and Radiogas Monitor 36 5.2.5.4.1.1 Air Particulate Monitor 36 5.2.5.4.1.2 Sensitivity Assumptions 36 5.2.5.4.1.3 Leakage Detection Threshold 38 5.2.5.4.1.4 Radiogas Monitor 39 5.2.5.4.2 Humidity Detector 39 5.2.5.4.3 Condensate Measuring System 39 5.2.5.4.4 Liquid Inventory in Process Systems and Containment Sumps 40 5.2.5.5 Leakage Detection System Evaluation 40 Table 5.2-1 REACTOR COOLANT SYSTEM CODE REQUIREMENTS 43 Table 5.2-2 MATERIALS OF CONSTRUCTION OF THE REACTOR COOLANT SYSTEM 44 COMPONENTS Table 5.2-3 REACTOR COOLANT SYSTEM QUALITY ASSURANCE PROGRAM 45 Table 5.2-4 Table DELETED 48 Table 5.2-5 REACTOR COOLANT PRESSURE BOUNDARY TO CONTAINMENT LEAK- 49 AGE DETECTION SYSTEMS Table 5.2-6 REACTOR COOLANT PRESSURE BOUNDARY INTERSYSTEM LEAKAGE 50 DETECTION SYSTEMS Table 5.2-7 SEQUENCE OF EVENTS - MASS ADDITION CASE 51 Table 5.2-8 HEAT ADDITION AT 60F - SEQUENCE OF EVENTS 52 Table 5.2-9 HEAT ADDITION AT 320F - SEQUENCE OF EVENTS 53 5.3 REACTOR VESSEL 54 5.3.1 REACTOR VESSEL MATERIALS 54 5.3.1.1 Reactor Vessel Description 54 5.3.1.2 Material Specifications 55 5.3.1.3 Testing and Surveillance 56 5.3.2 PRESSURE-TEMPERATURE LIMITS 56 Page 3 of 8 Revision 28 5/2019
GINNA/UFSAR 5.3.2.1 Thermal and Pressure Loadings 56 5.3.2.2 Pressure-Temperature Limits 57 5.3.2.3 Pressure-Temperature Limit Calculation 58 5.3.2.4 Irradiation Effect on Pressure-Temperature Limit 58 5.3.2.5 Heatup and Cooldown Rates 59 5.3.3 REACTOR VESSEL INTEGRITY 59 5.3.3.1 Safety Factors 59 5.3.3.2 Material Surveillance Program 61 5.3.3.3 Surveillance Program Analysis 62 5.3.3.3.1 Results Summary 63 5.3.3.3.2 Charpy V-Notch Impact Test Results 65 5.3.3.3.3 Tension Test Results 66 5.3.3.3.4 Radiation Analysis and Neutron Dosimetry 66 5.3.3.4 Analysis of Effects of Loss of Coolant and Safety Injection on the Reactor Vessel 66 5.3.3.4.1 Reactor Vessel 66 5.3.3.4.2 Safety Injection Nozzles 68 5.3.3.4.3 Fuel Assembly Grid Springs 68 5.3.3.4.4 Core Barrel and Thermal Shield 68 5.3.3.4.5 Subsequent Analyses of Reactor Vessel 68 5.3.3.5 Pressurized Thermal Shock 69 Table 5.3-1 REACTOR VESSEL SPECIFICATIONS 74 Table 5.3-2 REACTOR VESSEL DESIGN DATA 75 Table 5.3-3 REACTOR VESSEL MATERIALS 76 Table 5.3-4 IDENTIFICATION OF BELTLINE MATERIALS 77 Table 5.3-5 BELTLINE MATERIAL CHEMICAL COMPOSITION (WEIGHT PERCENT) 78 Table 5.3-6a MECHANICAL PROPERTIES OF BELTLINE MATERIALS - FORGINGS 79 Table 5.3-6b MECHANICAL PROPERTIES OF BELTLINE MATERIALS 80 Table 5.3-7
SUMMARY
OF PRIMARY-PLUS-SECONDARY STRESS INTENSITY FOR 81 COMPONENTS OF THE REACTOR VESSEL Table 5.3-8
SUMMARY
OF CUMULATIVE FATIGUE USAGE FACTORS FOR COMPO- 83 NENTS OF THE REACTOR VESSEL Table 5.3-9
SUMMARY
OF SURVEILLANCE CAPSULE RESULTS 84 Table 5.3-10 COMPARISON OF SURVEILLANCE MATERIAL 30 FT-LB TRANSITION 85 TEMPERATURE SHIFTS AND UPPER SHELF ENERGY DECREASES WITH REGULATORY GUIDE 1.99, REVISION 2, PREDICTIONS Page 4 of 8 Revision 28 5/2019
GINNA/UFSAR 5.4 COMPONENT AND SUBSYSTEM DESIGN 87 5.4.1 REACTOR COOLANT PUMPS 87 5.4.1.1 General Description 87 5.4.1.1.1 Centrifugal Pump 87 5.4.1.1.2 Controlled Leakage Shaft Seal 87 5.4.1.1.3 Pump Motor 88 5.4.1.1.4 Vibration Measurement 89 5.4.1.1.5 Lube Oil Leakage Collection System 89 5.4.1.2 Pump Flywheel Integrity 89 5.4.1.2.1 Pump Overspeed 89 5.4.1.2.2 Pump Flywheel Design and Fabrication 90 5.4.1.2.3 Flywheel Design Evaluation 90 5.4.1.2.4 Pump Seismic Design 91 5.4.1.2.5 Inservice Inspection Program 91 5.4.1.2.6 Conclusion 91 5.4.2 STEAM GENERATORS 91 5.4.2.1 Replacement Steam Generator Materials 92 5.4.2.2 Steam Generator Inservice Inspection 92 5.4.2.3 Replacement Steam Generator Design Evaluation 92 5.4.2.4 High Cycle Fatigue Failure of Original Steam Generator Tubes 93 5.4.3 REACTOR COOLANT PIPING 93 5.4.3.1 General 93 5.4.3.1.1 General Description 93 5.4.3.1.2 Pressure Isolation of Low-Pressure Systems 94 5.4.3.2 Reactor Coolant System Vents 94 5.4.3.2.1 General 94 5.4.3.2.2 Reactor Head Vent System Description 95 5.4.4 MAIN STEAM LINE ISOLATION SYSTEM 96 5.4.5 RESIDUAL HEAT REMOVAL (RHR) SYSTEM 97 5.4.5.1 Design Bases 97 5.4.5.2 System Design 98 5.4.5.2.1 Codes and Classifications 99 5.4.5.2.2 Components 99 Page 5 of 8 Revision 28 5/2019
GINNA/UFSAR 5.4.5.2.2.1 Heat Exchangers 99 5.4.5.2.2.2 Pumps 99 5.4.5.2.2.3 Valves 99 5.4.5.2.2.4 Piping 100 5.4.5.3 Performance Evaluation 100 5.4.5.3.1 Isolation Requirement 100 5.4.5.3.1.1 Isolation Valve Description 100 5.4.5.3.1.2 Deviations From Branch Technical Position RSB 5-1 101 5.4.5.3.2 Residual Heat Removal Overpressure Protection 102 5.4.5.3.2.1 Design Basis 102 5.4.5.3.2.2 Analysis 102 5.4.5.3.2.3 Effect of Stuck Open Relief Valve 103 5.4.5.3.3 Residual Heat Removal Pump Protection 104 5.4.5.3.4 Single-Failure Considerations 105 5.4.5.3.5 Leakage Provisions 106 5.4.5.3.6 Boron Concentration 107 5.4.5.4 Residual Heat Removal at Reduced Coolant Inventory 107 5.4.5.4.1 Generic Letter 88-17 Requirements 107 5.4.5.4.2 Containment Closure 108 5.4.5.4.3 Instrumentation for Reduced Inventory Operation 109 5.4.5.4.4 Available Equipment to Mitigate Loss of Residual Heat Removal Cooling 110 5.4.5.4.5 Reduced Inventory Procedures 110 5.4.5.4.6 Analyses 111 5.4.5.5 Tests and Inspections 112 5.4.6 MAIN STEAM AND FEEDWATER PIPING 112 5.4.7 PRESSURIZER 113 5.4.7.1 System Description 113 5.4.7.2 Seismic Evaluation 114 5.4.8 PRESSURIZER RELIEF DISCHARGE SYSTEM 115 5.4.8.1 System Description 115 5.4.8.2 System Analysis 116 5.4.9 VALVES 116 5.4.9.1 Original Valve Design 116 5.4.9.2 Valve Wall Thickness 117 5.4.9.3 Motor-Operated Valve Program 117 Page 6 of 8 Revision 28 5/2019
GINNA/UFSAR 5.4.10 SAFETY AND PRESSURIZER POWER OPERATED RELIEF VALVES (PORVs) 119 5.4.10.1 System Description 119 5.4.10.2 Performance Testing and Evaluation 120 5.4.11 COMPONENT SUPPORTS 121 5.4.11.1 Design Criteria 121 5.4.11.1.1 General 121 5.4.11.1.2 Asymmetric Loss-of-Coolant Accident Loading 121 5.4.11.1.3 Lamellar Tearing 122 5.4.11.2 Support Structures 122 5.4.11.2.1 Reactor Vessel Supports 122 5.4.11.2.2 Steam Generator Supports 123 5.4.11.2.3 Reactor Coolant Pump Supports 123 5.4.11.2.4 Pressurizer Supports 123 5.4.11.2.5 Reactor Coolant Piping Supports 123 5.4.11.2.6 Inspection and Testing 123 Table 5.4-1 REACTOR COOLANT PUMP DESIGN DATA 129 Table 5.4-2 REPLACEMENT STEAM GENERATOR DESIGN DATA 130 Table 5.4-3 REACTOR COOLANT PUMP COMPOSITE HOT PERFORMANCE CURVE 131 DATA Table 5.4-4 REACTOR COOLANT PUMPS COLD PERFORMANCE CURVE DATA FOR 133 INDIVIDUAL IMPELLERS Table 5.4-5 REACTOR VESSEL HEAD VENT EQUIPMENT PARAMETERS 134 Table 5.4-6 RESIDUAL HEAT REMOVAL SYSTEM COMPONENT DESIGN DATA 136 Table 5.4-7 PRESSURIZER DESIGN DATA 138 Table 5.4-8 PRESSURIZER RELIEF TANK DESIGN DATA 139 Table 5.4-9 VALVE AND PIPING INFORMATION 140 Page 7 of 8 Revision 28 5/2019
GINNA/UFSAR FIGURES Figure 5.2-1 Figure DELETED Figure 5.2-2 Figure DELETED Figure 5.2-3 Reactor Coolant Leak Detection Sensitivity Figure 5.3-1 Reactor Vessel Schematic Figure 5.3-2 Identification and Location of Beltline Region Material Figure 5.3-3 Arrangement of Surveillance Capsules in the Reactor Vessel Figure 5.4-1 Reactor Coolant Pump Figure 5.4-2 Reactor Coolant Pump Estimated Performance Characteristics Figure 5.4-2a Reactor Coolant Pump Composite Curve, Calculated Hot Performance, Total Head and Hydraulic Efficiency Versus Flow Figure 5.4-2b Reactor Coolant Pump Composite Curve, Calculated Hot Performance, Brake Horse- power Versus Flow Figure 5.4-2c Reactor Coolant Pump Composite Curve, Calculated Cold Performance, Total Head and Hydraulic Efficiency Versus Flow Figure 5.4-2d Reactor Coolant Pump Composite Curve, Calculated Cold Performance, Brake Horsepower Versus Flow Figure 5.4-3 Reactor Coolant Pressure Shaft Seal Arrangement Figure 5.4-4 Reactor Coolant Pump Flywheel Figure 5.4-5 Reactor Coolant Pump Flywheel Primary Stress at Operating Speed Figure 5.4-6 Replacement Steam Generator Figure 5.4-7 Figure DELETED Figure 5.4-8 Pressurizer Figure 5.4-9 Pressurizer Relief Tank Page 8 of 8 Revision 28 5/2019