ML20339A028
| ML20339A028 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/20/2020 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20339A309 | List:
|
| References | |
| Download: ML20339A028 (14) | |
Text
GINNA/UFSAR 6 ENGINEERED SAFETY FEATURES 1 6.1 ENGINEERED SAFETY FEATURES INTRODUCTION AND MATERIALS 2 6.
1.1 INTRODUCTION
2 6.1.2 ENGINEERED SAFETY FEATURES MATERIALS 2 6.1.2.1 Postaccident Environmental Conditions 2 6.1.2.1.1 General 2 6.1.2.1.2 Design-Basis Accident Temperature-Pressure Cycle 3 6.1.2.1.3 Design-Basis Accident Radiation Environment 4 6.1.2.1.4 Design Chemical Composition of the Emergency Core Cooling Solution 4 6.1.2.1.5 Trace Composition of Emergency Core Cooling Solution 5 6.1.2.2 Materials of Construction in the Containment 5 6.1.2.3 Corrosion of Metals of Construction in Design-Basis Emergency Core Cooling 6 Solution 6.1.2.3.1 Corrosion Resistance 6 6.1.2.3.2 Caustic Stress Cracking Resistance 7 6.1.2.4 Corrosion of Metals of Construction by Trace Contaminants in Emergency Core 7 Cooling Solution 6.1.2.4.1 Low Temperature of Emergency Core Cooling Solution 8 6.1.2.4.2 Low Chloride Concentration of Emergency Core Cooling Solution 8 6.1.2.4.3 Alkaline Nature of the Emergency Core Cooling Solution 9 6.1.2.4.4 Summary 9 6.1.2.5 Corrosion of Aluminum Alloys 9 6.1.2.6 Compatibility of Protective Coatings With the Postaccident Environment 10 6.1.2.7 Evaluation of the Compatibility of Concrete-Emergency Core Cooling Solution in 10 the Postaccident Environment 6.1.2.8 Miscellaneous Materials of Construction 12 6.1.2.8.1 Sealants 12 6.1.2.8.2 Containment Recirculation Fan Cooler (CRFC) Materials 12 6.1.2.8.3 Polyvinyl Chloride Protective Coating 13 6.1.2.8.4 Vinylcel Insulation 14 6.1.2.9 Organic Materials Evaluation 15 Table 6.1-1 REVIEW OF SOURCES OF VARIOUS ELEMENTS IN CONTAINMENT 18 AND THEIR EFFECTS ON MATERIALS OF CONSTRUCTION Table 6.1-2 MATERIALS OF CONSTRUCTION IN GINNA STATION CONTAINMENT 21 Table 6.1-3 INVENTORIES OF ALUMINUM INSIDE CONTAINMENT BUILDING 22 Table 6.1-4 CORROSION OF MATERIALS IN SODIUM BORATE SOLUTION 23 Page 1 of 14 Revision 29 11/2020
GINNA/UFSAR Table 6.1-5 GINNA Post-LOCA CONTAINMENT TEMPERATURES 24 Table 6.1-6 CONCRETE SPECIMEN TEST DATA 25 Table 6.1-7 EVALUATION OF SEALANT MATERIALS FOR USE IN THE CONTAINMENT 26 6.2 CONTAINMENT SYSTEMS 27 6.2.1 CONTAINMENT SYSTEM STRUCTURE 27 6.2.1.1 Design Basis 27 6.2.1.1.1 Principal Design Criteria 28 6.2.1.1.1.1 General 28 6.2.1.1.1.2 Quality Standards 28 6.2.1.1.1.3 Performance Standards 28 6.2.1.1.1.4 Fire Protection 29 6.2.1.1.1.5 Records Requirement 29 6.2.1.1.1.6 Reactor Containment 30 6.2.1.1.1.7 Reactor Containment Design Basis 31 6.2.1.1.1.8 Nil Ductility Transition Requirement for Containment Material 31 6.2.1.1.2 Supplementary Accident Criteria 31 6.2.1.1.3 Energy and Material Release 32 6.2.1.2 Containment Integrity Evaluation 32 6.2.1.2.1 Systematic Evaluation Program (SEP) Evaluation 32 6.2.1.2.1.1 Introduction 32 6.2.1.2.1.2 NRC Analyses 33 6.2.1.2.1.3 Summary 33 6.2.1.2.2 Mass and Energy Release Safety Analysis 33 6.2.1.2.2.1 Loss-of-Coolant (LOCA) Mass and Energy Releases 33 6.2.1.2.2.2 Input Parameters and Assumptions 35 6.2.1.2.2.3 Description of Analyses 39 6.2.1.2.2.4 Mass and Energy Release Data 42 6.2.1.2.2.5 Long-Term Mass and Energy Releases 45 6.2.1.2.2.6 Long-Term LOCA Containment Response 46 6.2.1.2.2.7 Description of the LOCA GOTHIC Containment Model 50 6.2.1.2.2.8 Results 54 6.2.1.2.3 Secondary System Pipe Break Analysis 56 6.2.1.2.3.1 Event Analysis 56 6.2.1.2.3.2 Protective Features 56 6.2.1.2.3.3 Single Failures Assumed 57 6.2.1.2.3.4 Operator Actions Assumed 57 6.2.1.2.3.5 Chronological Description of Event 57 6.2.1.2.3.6 Impact on Fission Product Barriers 58 6.2.1.2.3.7 Reactor Core and Plant System Evaluation 58 Page 2 of 14 Revision 29 11/2020
GINNA/UFSAR 6.2.1.2.3.8 Input Parameters and Initial Conditions 59 6.2.1.2.3.9 Methodology 59 6.2.1.2.3.10 Acceptance Criteria 59 6.2.1.2.3.11 Results 59 6.2.1.2.3.12 Radiological Consequences 59 6.2.1.2.3.13 Conclusion 60 6.2.1.3 Evaluation of Containment Internal Structures 60 6.2.1.3.1 Introduction 60 6.2.1.3.2 Reactor Coolant Loop Compartment Pressure 60 6.2.1.3.3 Thermal Gradients 61 6.2.1.3.4 Reactor Vessel and Steam Generator Annulus Pressure 61 6.2.1.3.5 Seismic Evaluation 62 6.2.1.3.6 Technical Evaluation for Extended Power Uprate (EPU) Conditions 62 6.2.1.3.6.1 Introduction 62 6.2.1.3.6.2 Input Parameters and Assumptions 62 6.2.1.3.6.3 Acceptance Criteria 63 6.2.1.3.6.4 Description of Analysis 64 6.2.1.3.6.5 Short-Term LOCA M&E Releases Results 64 6.2.1.4 Minimum Operating Conditions 65 6.2.1.5 Instrumentation Requirements 65 6.2.1.5.1 Pressure 65 6.2.1.5.2 Sump Level 65 6.2.1.5.3 Radiation 66 6.2.1.5.4 Containment Temperature and Dewpoint 66 6.2.2 CONTAINMENT HEAT REMOVAL SYSTEMS 66 6.2.2.1 Containment Recirculation Fan Cooler (CRFC) System 67 6.2.2.1.1 Design Bases 67 6.2.2.1.1.1 Capacity 67 6.2.2.1.1.2 Design Objectives 68 6.2.2.1.1.3 Special Features 69 6.2.2.1.2 System Design 69 6.2.2.1.2.1 System Description 69 6.2.2.1.2.2 Design Analysis 70 6.2.2.1.2.3 Redundancy Provisions 71 6.2.2.1.2.4 Actuation Provisions 72 6.2.2.1.2.5 Environmental Protection 72 6.2.2.1.3 Design Evaluation 73 6.2.2.1.4 Tests and Inspections 74 6.2.2.1.5 Instrumentation 74 6.2.2.2 Containment Spray System 75 Page 3 of 14 Revision 29 11/2020
GINNA/UFSAR 6.2.2.2.1 Design Bases 75 6.2.2.2.1.1 Design Criteria 75 6.2.2.2.1.2 Performance Objectives 76 6.2.2.2.1.3 Service Life 77 6.2.2.2.1.4 Codes and Classifications 77 6.2.2.2.2 System Design 77 6.2.2.2.2.1 Operational Requirements 77 6.2.2.2.2.2 Refueling Water Storage Tank (RWST) 78 6.2.2.2.2.3 Containment Spray Pumps 78 6.2.2.2.2.4 Liquid Jet Eductor 78 6.2.2.2.2.5 Spray Ring Headers 78 6.2.2.2.2.6 Spray Nozzles 79 6.2.2.2.2.7 Environmental Qualification 79 6.2.2.2.2.8 System Tests 79 6.2.2.2.3 Design Evaluation 79 6.2.2.2.3.1 Design Basis 79 6.2.2.2.3.2 Heat Transfer Calculations 80 6.2.2.2.3.3 Reliance on Interconnected Systems 82 6.2.2.2.3.4 Reliability Considerations 82 6.2.2.2.3.5 Containment Spray Pump Net Positive Suction Head Requirements 82 6.2.2.2.3.6 Equipment Protection 82 6.2.2.2.4 Minimum Operating Conditions 83 6.2.2.2.5 Tests and Inspections 83 6.2.2.2.6 Instrumentation 83 6.2.2.2.6.1 Interlock and Control Features 83 6.2.2.2.6.2 Control Room and Local Indication 83 6.2.3 SECONDARY CONTAINMENT 84 6.2.4 CONTAINMENT ISOLATION SYSTEM 84 6.2.4.1 Design Criteria 84 6.2.4.2 Design Basis 85 6.2.4.2.1 Functional Requirements 85 6.2.4.2.2 Seismic Design 86 6.2.4.3 System Design 86 6.2.4.3.1 Isolation Valve Parameters Tabulation 87 6.2.4.3.2 Isolation Valve Operability 87 6.2.4.4 Design Evaluation 88 6.2.4.4.1 Current Safety Criteria 88 6.2.4.4.2 Class 1 Penetrations (Outgoing Lines, Reactor Coolant System) 89 6.2.4.4.2.1 Applicable Lines 89 6.2.4.4.2.2 Class 1 Penetration Evaluation 89 Page 4 of 14 Revision 29 11/2020
GINNA/UFSAR 6.2.4.4.3 Class 2 (Outgoing Lines) 90 6.2.4.4.3.1 Applicable Lines 90 6.2.4.4.3.2 Class 2 Evaluation 90 6.2.4.4.4 Class 3 (Incoming Lines) 91 6.2.4.4.4.1 Class 3A Penetrations 92 6.2.4.4.4.2 Class 3B Penetrations 92 6.2.4.4.5 Class 4 Penetrations (Closed System, Missile Protected) 93 6.2.4.4.5.1 Applicable Lines 93 6.2.4.4.5.2 Class 4 Evaluation 94 6.2.4.4.6 Class 5 Penetrations (Special Service) 95 6.2.4.4.6.1 Applicable Lines 95 6.2.4.4.6.2 Class 5 Evaluation 95 6.2.4.4.7 Special Cases 96 6.2.4.4.8 Instrumentation and Controls Evaluation 96 6.2.4.4.9 Containment Purging During Normal Plant Operation 97 6.2.5 COMBUSTIBLE GAS CONTROL IN THE CONTAINMENT 97 6.2.5.1 Introduction 98 6.2.5.2 Hydrogen Recombiner System 99 6.2.5.2.1 Description 99 6.2.5.2.2 Containment Venting 100 6.2.5.3 Design Evaluation 100 6.2.5.3.1 Hydrogen Production and Accumulation 100 6.2.5.3.1.1 Zirconium-Water Reaction 101 6.2.5.3.1.2 Radiolytic Hydrogen Generation 101 6.2.5.3.1.3 Corrosion of Materials 102 6.2.5.3.1.4 Initial Inventory in the RCS and Pressurizer 103 6.2.5.3.2 Effect of Recombiners 103 6.2.6 CONTAINMENT LEAKAGE TESTING 104 6.2.6.1 Containment Design Leakage 104 6.2.6.2 Tests and Inspections 104 6.2.6.2.1 Design Criteria 104 6.2.6.2.2 Initial Containment Leakage Rate Testing 104 6.2.6.2.3 Periodic Containment Leakage Rate Testing (Type A Tests) 105 6.2.6.2.4 Provisions for Testing of Type B Penetrations 105 6.2.6.2.5 Provisions for Testing of Isolation Valves (Type C) 106 6.2.6.3 Leakage Test Compliance with 10 CFR 50, Appendix J 106 Table 6.2-1 SYSTEM PARAMETERS INITIAL CONDITIONS 112 Table 6.2-2 SAFETY INJECTION FLOW - MINIMUM SAFEGUARDS 113 Table 6.2-3 SAFETY INJECTION FLOW - MAXIMUM SAFEGUARDS 114 Page 5 of 14 Revision 29 11/2020
GINNA/UFSAR Table 6.2-4 LOCA M&E RELEASE ANALYSIS - CORE DECAY HEAT FRACTION 115 Table 6.2-5 DOUBLE-ENDED HOT LEG BREAK BLOWDOWN M&E RELEASE 117 Table 6.2-6 DOUBLE-ENDED HOT LEG BREAK - MASS BALANCE 121 Table 6.2-7 DOUBLE-ENDED HOT LEG BREAK - ENERGY BALANCE 122 Table 6.2-8 DOUBLE-ENDED PUMP SUCTION BREAK MIN SI BLOWDOWN M&E 125 RELEASE Table 6.2-9 DOUBLE-ENDED PUMP SUCTION BREAK MIN SI 127 Reflood M&E Release Table 6.2-10 DOUBLE-ENDED PUMP SUCTION BREAK 133 Min SI Principle Parameters During Reflood Table 6.2-11 DOUBLE-ENDED PUMP SUCTION BREAK 135 Post Reflood M&E Release-Minimum Safeguards Table 6.2-12 DOUBLE-ENDED PUMP SUCTION BREAK MASS BALANCE - MIN SI 142 Table 6.2-13 DOUBLE-ENDED PUMP SUCTION BREAK ENERGY BALANCE - 143 MINIMUM SAFEGUARDS Table 6.2-14 Table DELETED 144 Table 6.2-15 Table DELETED 145 Table 6.2-16 CONTAINMENT RESPONSE ANALYSIS PARAMETERS 146 Table 6.2-17 CONTAINMENT RECIRCULATION FAN COOLER HEAT REMOVAL 147 CAPABIL- ITY AS A FUNCTION OF CONTAINMENT STEAM SATURATION TEMPERA- TURE Table 6.2-18 LOCA CONTAINMENT RESPONSE ANALYSIS RECIRCULATION 148 SYSTEM ALIGNMENT PARAMETERS Table 6.2-19 CONTAINMENT STRUCTURAL HEAT SINK INPUT 149 Table 6.2-20 MATERIAL PROPERTIES FOR CONTAINMENT STRUCTURAL HEAT SINKS 152 Table 6.2-21 DOUBLE-ENDED HOT LEG BREAK SEQUENCE OF EVENTS 153 Table 6.2-22 DOUBLE-ENDED PUMP SUCTION BREAK SEQUENCE OF EVENTS 154 (Minimum Safeguards)
Table 6.2-23 LOCA CONTAINMENT RESPONSE RESULTS 156 Table 6.2-24 INITIAL CONDITIONS AND MAJOR ASSUMPTIONS FOR THE STEAMLINE 157 BREAK MASS AND ENERGY RELEASE MODEL (LIMITING CONTAINMENT PRESSURE CASE)
Table 6.2-25 MAJOR CONTAINMENT ANALYSIS ASSUMPTIONS 158 Table 6.2-26 SEQUENCE OF EVENTS 159 STEAMLINE BREAK, VITAL BUS FAILURE Table 6.2-27 CONTAINMENT SPRAY PUMP DESIGN PARAMETERS 160 Table 6.2-28 SINGLE FAILURE ANALYSIS - CONTAINMENT SPRAY SYSTEM 161 Table 6.2-29 CONTAINMENT PIPING PENETRATIONS AND ISOLATION BOUNDARIES 162 Table 6.2-30 CONTAINMENT PIPING PENETRATIONS AND ISOLATION BOUNDARIES 179
- NOTES FOR TABLE 6.2-29 Table 6.2-31 CONTAINMENT PIPING PENETRATIONS AND ISOLATIONBOUNDARIES - 182 LEGEND FOR Table 6.2-29 Table 6.2-32 EFFECT OF LOSS OF AIR OR POWER SUPPLY TO AIR-OPERATED VALVES 183 Page 6 of 14 Revision 29 11/2020
GINNA/UFSAR Table 6.2-33 ESSENTIAL AND NONESSENTIAL SYSTEM CONTAINMENT PENETRATIONS 185 Table 6.2-34 PARAMETERS AND ASSUMPTIONS USED TO DETERMINE HYDROGEN GENERATION (HISTORICAL) 189 Table 6.2-35 FISSION PRODUCT DECAY ENERGY IN SUMP SOLUTION (HISTORICAL) 190 Table 6.2-36 FISSION PRODUCT DECAY ENERGY IN THE CORE (HISTORICAL) 191 6.3 EMERGENCY CORE COOLING SYSTEM (ECCS) 192 6.3.1 DESIGN CRITERIA 192 6.3.1.1 Emergency Core Cooling System (ECCS) Capability 192 6.3.1.2 Inspection of Emergency Core Cooling System (ECCS) 193 6.3.1.3 Testing of Emergency Core Cooling System (ECCS) and Components 193 6.3.1.4 Testing of Operational Sequence of Emergency Core Cooling System (ECCS) 193 6.3.1.5 Service Life 194 6.3.1.6 Codes and Classifications 194 6.3.2 SYSTEM DESIGN AND OPERATION 194 6.3.2.1 System Description 194 6.3.2.1.1 General 194 6.3.2.1.2 Injection Phase 197 6.3.2.1.3 Recirculation Phase 198 6.3.2.2 Component Description 198 6.3.2.2.1 Accumulators 198 6.3.2.2.2 Safety Injection Pumps 199 6.3.2.2.2.1 Operation 199 6.3.2.2.2.2 Pump Design and Fabrication 200 6.3.2.2.3 Refueling Water Storage Tank (RWST) 200 6.3.2.2.4 Heat Exchangers 201 6.3.2.2.5 Boric Acid Storage Tanks 201 6.3.2.2.6 Containment Sump B 202 6.3.2.2.7 Valves 202 6.3.2.2.7.1 General 202 6.3.2.2.7.2 Motor-Operated Valves 203 6.3.2.2.7.3 Manual Valves 204 6.3.2.2.7.4 Accumulator Check Valves 204 6.3.2.2.7.5 Leakage Limitations 205 6.3.2.2.8 Piping 206 6.3.2.2.8.1 General 206 6.3.2.2.8.2 Design Criteria 206 6.3.2.2.8.3 Design Review 206 6.3.2.2.8.4 Materials 207 6.3.2.2.8.5 Welding and Fabrication 207 Page 7 of 14 Revision 29 11/2020
GINNA/UFSAR 6.3.2.2.8.6 Packaging 208 6.3.2.2.9 Motors 208 6.3.2.3 System Operation 208 6.3.2.3.1 Separation 208 6.3.2.3.2 System Actuation 208 6.3.2.3.3 Injection Phase 209 6.3.2.3.4 Recirculation Phase 209 6.3.2.3.5 Steam Line Break Protection 210 6.3.2.3.6 Safety Injection System Leakage Outside Containment 211 6.3.3 DESIGN EVALUATION 211 6.3.3.1 Range of Core Protection 211 6.3.3.1.1 Safety Injection Requirements Versus Break Size 211 6.3.3.1.2 Makeup System Capacity 212 6.3.3.1.3 System Evaluation 212 6.3.3.2 System Response 213 6.3.3.3 Safety Injection System Switchover From Injection to Recirculation 213 6.3.3.4 Boron Precipitation During Long-Term Cooling 215 6.3.3.5 Single Failure Analysis 215 6.3.3.6 Passive Systems 216 6.3.3.7 Emergency Flow to the Core 216 6.3.3.8 Recirculation Loop Leakage 217 6.3.3.9 Safety Injection Pump Net Positive Suction Head Requirements 217 6.3.3.10 Seismic Analysis 219 6.3.3.11 MODE 4 (Hot Standby) LOCA Evaluation 219 6.3.3.12 Alternate RCS Injection (BDB) 220 6.3.4 MINIMUM OPERATING CONDITIONS 221 6.3.5 TESTS AND INSPECTIONS 221 6.3.5.1 Inspection 221 6.3.5.2 System Testing 221 6.3.5.3 Components Testing 222 6.3.5.4 Operational Sequence Testing 223 6.3.5.5 Gas Intrusion Management Program 224 6.3.6 INSTRUMENTATION 224 6.3.6.1 Containment Sump Level 224 6.3.6.2 Refueling Water Storage Tank (RWST) Level 225 6.3.6.3 Accumulator Pressure and Level 225 6.3.6.4 Boric Acid Storage Tank Level 225 6.3.6.5 Residual Heat Exchanger Flow and Temperature 225 6.3.6.6 Safety Injection Line Flow 225 Page 8 of 14 Revision 29 11/2020
GINNA/UFSAR 6.3.6.7 Safety Injection Pumps Discharge Pressure 225 6.3.6.8 Pump Energization 226 6.3.6.9 Valve Position 226 Table 6.3-1 QUALITY STANDARDS OF SAFETY INJECTION SYSTEM COMPONENTS 229 Table 6.3-2 ACCUMULATOR DESIGN PARAMETERS 233 Table 6.3-3 SAFETY INJECTION SYSTEM PUMPS DESIGN PARAMETERS 234 Table 6.3-4 REFUELING WATER STORAGE TANK (RWST) DESIGN PARAMETERS 235 Table 6.3-5 RESIDUAL HEAT REMOVAL HEAT EXCHANGERS DESIGN PARAMETERS 236 Table 6.3-6 RECIRCULATION LOOP LEAKAGE INFORMATION USED IN 237 ORIGINAL ANALYSIS Table 6.3-7 INSTRUMENTATION READOUTS ON THE CONTROL BOARD FOR 238 OPERATOR MONITORING DURING RECIRCULATION Table 6.3-8 SAFETY INJECTION VALVE OPERATION AND INTERLOCKS 240 Table 6.3-9 SINGLE FAILURE ANALYSIS - SAFETY INJECTION SYSTEM 242 6.4 HABITABILITY SYSTEMS 244 6.4.1 DESIGN CRITERION 244 6.4.2 SYSTEM DESIGN 245 6.4.2.1 Definition of Control Room Envelope (CRE) 245 6.4.2.2 Ventilation System Design 245 6.4.2.2.1 Normal HVAC System - NORMAL and PURGE Modes of Operation 245 6.4.2.2.2 CREATS System - EMERGENCY Mode of Operation 245 6.4.2.3 Leak Tightness 246 6.4.2.4 Interaction with Other Zones and Pressure-containing Equipment. 246 6.4.2.4.1 Interaction with the Turbine Building 247 6.4.2.4.2 Interaction with the Relay Room 247 6.4.2.5 Shielding Design 247 6.4.2.6 System Operational Procedures 247 6.4.3 DESIGN EVALUATIONS 248 6.4.3.1 Radiological Analysis 248 6.4.3.2 Protection from Toxins 249 6.4.3.2.1 Chlorine 250 6.4.3.2.2 Ammonia 250 6.4.3.2.3 Halon 250 6.4.3.2.4 Refrigerant 250 6.4.3.2.5 Sodium Hypochlorite 250 6.4.3.2.6 Carbon Dioxide 251 6.4.3.3 Protection from Smoke and Fire 251 Page 9 of 14 Revision 29 11/2020
GINNA/UFSAR 6.4.3.3.1 Internal Sources of Smoke and Fire 251 6.4.3.3.2 External Sources of Smoke and Fire 251 6.4.3.4 Protection from Temperature Extremes 252 6.4.4 TESTS AND INSPECTIONS 252 6.4.5 INSTRUMENTATION REQUIREMENT 253 Table 6.4-1 Control Room Habitability Radiological Evaluation - Assumptions and Results 256 Table 6.4-2 CORE ACTIVITIES 259 6.5 FISSION PRODUCT REMOVAL SYSTEMS 260 6.5.1 ENGINEERED SAFETY FEATURE FILTER SYSTEMS 260 6.5.1.1 Introduction 260 6.5.1.2 Containment Air Filtration System 260 6.5.1.2.1 Design Basis 260 6.5.1.2.2 System Design 261 6.5.1.2.2.1 General Description 261 6.5.1.2.2.2 Charcoal Filters 261 6.5.1.2.2.3 HEPA Filters 262 6.5.1.2.2.4 Protection From Sodium Hydroxide Attack 262 6.5.1.2.2.5 Fire Protection 263 6.5.1.2.3 Design Evaluation 264 6.5.1.2.3.1 Decay Heat Generation in the Charcoal Filters 264 6.5.1.2.3.2 Decay Heat Dissipation With Normal Air Flow 264 6.5.1.2.3.3 Decay Heat Dissipation With Loss of Air Flow 264 6.5.1.2.4 Tests and Inspections 265 6.5.1.2.4.1 HEPA Filter Tests 265 6.5.1.2.4.2 Charcoal Filter Tests 266 6.5.1.2.4.3 System Tests 266 6.5.1.2.5 Instrumentation Requirements 266 6.5.1.3 Generic Letter 96-06 Requirements 267 6.5.1.4 Generic Letter 99-02 Requirements 268 6.5.2 CONTAINMENT SPRAY AND NaOH SYSTEMS 268 6.5.2.1 System Design and Operation 268 6.5.2.1.1 Spray Additive Tank 268 6.5.2.1.2 Effect of Sodium Hydroxide and Boric Acid Mixing 269 6.5.2.1.3 Iodine Retention 271 6.5.2.2 Iodine Effectiveness Evaluation of the Containment Spray and NaOH Systems 272 Page 10 of 14 Revision 29 11/2020
GINNA/UFSAR 6.5.2.2.1 Purpose of Chemical Modification 272 6.5.2.2.1.1 Thermal Capacity 272 6.5.2.2.1.2 Absorption of Iodine in Refueling Water Spray 272 6.5.2.2.1.3 Iodine Absorption with Sodium Hydroxide Addition 273 6.5.2.2.1.4 Spray Absorption Process for Iodine Removal 274 6.5.2.2.2 Technical Basis for Iodine Removal Factor 274 6.5.2.2.2.1 Analytical Model and Assumptions 274 6.5.2.2.2.2 Removal of Elemental Iodine 277 6.5.2.2.2.3 Removal of Other Airborne Forms of Iodine 278 6.5.2.2.2.4 Experimental Verification 278 Table 6.5-1 DATA FOR CHARCOAL FILTER EVALUATION 282 6.6 INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS 283 6.
6.1 INTRODUCTION
283 6.6.2 INSERVICE INSPECTION PROGRAM
SUMMARY
283 6.6.2.1 Scope 283 6.6.2.2 Inspection Intervals 283 6.6.2.3 Extent and Frequency 283 6.6.2.4 Examination Methods 284 6.6.2.5 Evaluation of Examination Results 284 6.6.2.6 System Pressure Testing 284 6.6.2.7 Records and Reports 284 6.6.2.8 Exemptions 284 FIGURES Figure 6.1-1 Design-Basis Accident, Containment Temperature Profile Figure 6.1-2 Design-Basis Accident, Containment Pressure Profile Figure 6.1-3 Postaccident Core Materials Design Conditions Figure 6.1-4 Containment Atmosphere Total Gamma Dose Figure 6.1-5 Containment Atmosphere Total Beta Dose Figure 6.1-6 pH of Unadjusted Boric Acid Solutions Figure 6.1-7 Titration Curve for Boric Acid With Sodium Hydroxide Figure 6.1-8 Temperature-Concentration Relation For Caustic Corrosion of Austenitic Stainless Steel Figure 6.1-9 Aluminum Corrosion Rates in LOCA Environment Figure 6.1-10 Post LOCA Containment Hydrogen Production Rate Figure 6.1-11 Boron Loss From Boron-Concrete Reaction Following a Design-Basis Accident Figure 6.1-12 Post LOCA Containment Hydrogen Production Figure 6.2-1 Containment Atmosphere Pressure, Double-Ended Hot Leg Break Figure 6.2-2 Containment Atmosphere Temperature, Double-Ended Hot Leg Break Figure 6.2-3 Containment Sump Temperature, Double-Ended Hot Leg Break Page 11 of 14 Revision 29 11/2020
GINNA/UFSAR Figure 6.2-4 Containment Atmosphere Pressure, Double-Ended Pump Suction Break -
Minimum Safeguards Figure 6.2-5 Containment Atmosphere Temperature, Double-Ended Pump Suction Break -
Mini mum Safeguards Figure 6.2-6 Containment Sump Temperature, Double-Ended Pump Suction Break -
Minimum Safeguards Figure 6.2-7 1.1-Ft2 Break Case 25B With 102% Power and Diesel Failure Assumed, Containment Pressure Versus Time Figure 6.2-8 1.4-Ft2 Break Case 13A With 102% Power and Vital Bus Failure Assumed, Containment Steam Temperature Versus Time Figure 6.2-9 1.1-Ft2 Break Case 25B With 102% Power and Diesel Failure Assumed, Containment Steam Temperature Versus Time Figure 6.2-10 Reactor Containment Fan Cooler, Accident Versus Normal Air Flow Figure 6.2-11 Figure DELETED Figure 6.2-12 Figure Deleted Figure 6.2-13 Steam Generator Inspection and Maintenance Cabling Access Penetration 2 Figure 6.2-13a Fuel Transfer Tube Penetration 29 Figure 6.2-14 Reactor Coolant System Charging Line Penetration 100 Figure 6.2-15 Safety Injection System Penetrations 101, 110b, and 113 Figure 6.2-16 Alternate Charging Line Penetration 102 Figure 6.2-17 Construction Fire Service Water Penetration 103 Figure 6.2-18 Containment Spray Header A Penetration 105 Figure 6.2-19 Reactor Coolant Pump A Seal Water Line Penetration 106 Figure 6.2-20 Sump A Discharge Penetration 107 Figure 6.2-21 Reactor Coolant Pump Seal Water Return and Excess Letdown Penetration 108 Figure 6.2-22 Containment Spray Header B Penetration 109 Figure 6.2-23 Reactor Coolant Pump B Seal Water Line Penetration 110a Figure 6.2-24 Residual Heat Removal to Loop B Cold Leg Penetration 111 Figure 6.2-25 Letdown Line from Reactor Coolant System Penetration 112 Figure 6.2-26 Standby Auxiliary Feedwater to Steam Generators A and B Penetrations 119 and 123b Figure 6.2-27 Nitrogen to Accumulators Penetration 120a Figure 6.2-28 Pressurizer Relief Tank Gas Analyzer Penetration 120b Figure 6.2-29 Pressurizer Relief Tank Makeup Water Penetration 121a Figure 6.2-30 Pressurizer Relief Tank N2 Penetration 121b Figure 6.2-31 Containment Pressure Transmitters PT-945 and PT-946 Penetration 121c Figure 6.2-32 Reactor Coolant Drain Tank to Gas Analyzer Penetration 123a Figure 6.2-33 Component Cooling Water to and from Excess Letdown Heat Exchanger Penetrations 124a and 124c Figure 6.2-34 Containment Postaccident Air Sample (C Fan) Penetrations 124b and 124d Figure 6.2-35 Component Cooling Water from Reactor Coolant Pump 1B Penetration 125 Figure 6.2-36 Component Cooling Water from Reactor Coolant Pump 1A Penetration 126 Page 12 of 14 Revision 29 11/2020
GINNA/UFSAR Figure 6.2-37 Component Cooling Water to Reactor Coolant Pump 1A Penetration 127 Figure 6.2-38 Component Cooling Water to Reactor Coolant Pump B Penetration 128 Figure 6.2-39 Reactor Coolant Drain Tank Gas Header Penetration 129 Figure 6.2-40 Component Cooling Water from and to Reactor Support Coolers Penetrations 130 and 131 Figure 6.2-41 Mini-Purge Exhaust Penetration 132 Figure 6.2-42 Residual Heat Removal from Loop A Hot Leg Penetration 140 Figure 6.2-43 Sump B to Reactor Coolant Drain Tank Pump A Penetration 141 Figure 6.2-44 Sump B to Reactor Coolant Drain Tank Pump B Penetration 142 Figure 6.2-45 Reactor Coolant Drain Tank Discharge Penetration 143 Figure 6.2-46 Reactor Compartment Cooling Unit A Supply and Return Penetrations 201a and 209b Figure 6.2-47 Reactor Compartment Cooling Unit B Supply and Return Penetrations 201b and 209a Figure 6.2-48 Hydrogen Recombiner B (Main and Pilot) Penetrations 202a and 202b Figure 6.2-49 Containment Pressure Transmitters PT-947 and PT-948 Penetration 203a Figure 6.2-50 Figure DELETED Figure 6.2-51 Purge Supply Penetration 204 Figure 6.2-52 Reactor Coolant System Loop B Hot Leg Sample Penetration 205 Figure 6.2-53 Pressurizer Liquid Sample Penetration 206a Figure 6.2-54 Steam Generator A Sample Penetration 206b Figure 6.2-55 Pressurizer Steam Sample Penetration 207a Figure 6.2-56 Steam Generator B Sample Penetration 207b Figure 6.2-57 Hydrogen Recombiner A and B Oxygen Makeup Penetration 210 Figure 6.2-58 Purge Exhaust Penetration 300 Figure 6.2-59 Figure Deleted Figure 6.2-60 Hydrogen Recombiner A (Main and Pilot) Penetrations 304a and 304b Figure 6.2-61 Containment Postaccident Air Sample Penetrations 305a, 305c, and 305d Figure 6.2-62 Containment Air Sample (Return) Penetration 305b Figure 6.2-63 Containment Air Sample Outlet Penetration 305e Figure 6.2-64 Fire Service Water Penetration 307 Figure 6.2-65 Service Water for Containment Fan Coolers, Penetrations 308, 311, 312, 315, 316, 319, 320, and 323 Figure 6.2-66 Mini-Purge Supply Penetration 309 Figure 6.2-67 Instrument Air Penetration 310a Figure 6.2-68 Service Air Penetration 310b Figure 6.2-69 Leakage Test Depressurization Penetration 313 Figure 6.2-70 Leakage Test Supply Penetration 317 Figure 6.2-71 Steam Generator A Blowdown Penetration 321 Figure 6.2-72 Steam Generator B Blowdown Penetration 322 Page 13 of 14 Revision 29 11/2020
GINNA/UFSAR Figure 6.2-73 Demineralized Water Penetration 324 Figure 6.2-74 Containment H2 Monitors Penetrations 332a, 332b, and 332d Figure 6.2-75 Containment Pressure Transmitters PT-944, PT-949, and PT-950 Penetration 332c Figure 6.2-76 Main Steam from Steam Generator A Penetration 401 Figure 6.2-77 Main Steam from Steam Generator B Penetration 402 Figure 6.2-78 Main and Auxiliary Feedwater to Steam Generators A and B Penetrations 403 and 404 Figure 6.2-79 Figure DELETED Sheet 1 -
Figure 6.2-79 Figure DELETED Sheet 2 -
Figure 6.2-80 Containment Hydrogen Production With and Without Recombiner Figure 6.3-1 Sheet Figure DELETED 1-Figure 6.3-1 Sheet Figure DELETED 2-Figure 6.3-2 Safety Injection Pump Performance Characteristics Figure 6.3-3 Residual Heat Removal Pump Reactor Injection Capability Figure 6.3-4 Range of Core Protection Provided by Various Components of the Safety Injection System Figure 6.5-1 Carbon Cell Banking Arrangement Figure 6.5-2 Filters - Containment Unit Figure 6.5-3 Iodine Partition Coefficient and pH in the Containment Versus Time Figure 6.5-4 Pressure Dependence of the Ratio vG/t Page 14 of 14 Revision 29 11/2020