ML19150A431
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GINNA/UFSAR 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE 1 PLANT
1.1 INTRODUCTION
2 REFERENCES FOR SECTION 1.1 4 1.2 GENERAL PLANT DESCRIPTION 5 1.2.1 SITE AND ENVIRONMENT 5 1.2.2
SUMMARY
PLANT DESCRIPTION 5 1.2.3 STRUCTURES 6 1.2.3.1 General 6 1.2.3.2 Containment 6 1.2.3.3 Auxiliary Building 7 1.2.3.4 Intermediate Building (See Drawings 33013-2101, 33013-2102, 9 33013-2105, 33013-2106, 33013-2107, 33013-2113, 33013-2114, 33013-2115, and 33013-2121) 1.2.3.5 Turbine Building 10 1.2.3.6 Control Building 11 1.2.3.7 All-Volatile-Treatment Building 12 1.2.3.8 Standby Auxiliary Feedwater Pump Building 12 1.2.3.9 Screen House 12 1.2.3.10 Service Building 12 1.2.3.11 Diesel Generator Building 13 1.2.3.12 Old Steam Generator Storage Facility 13 1.2.3.13 Canister Preparation Building 13 1.2.3.14 ISFSI Transfer Path and Storage Pad 14 1.2.3.15 Administration Building 14 1.2.4 NUCLEAR STEAM SUPPLY SYSTEM 14 1.2.5 REACTOR AND PLANT CONTROL 15 1.2.6 WASTE DISPOSAL SYSTEM 15 1.2.7 FUEL HANDLING SYSTEM 15 1.2.8 TURBINE AND AUXILIARIES 16 1.2.9 ELECTRICAL SYSTEM 16 1.2.10 ENGINEERED SAFETY FEATURES PROTECTION SYSTEMS 16 1.2.11 DESIGN HIGHLIGHTS 17 1.2.11.1 Power Level 17 Page 1 of 9 Revision 28 5/2019
GINNA/UFSAR 1.2.11.2 Reactor Coolant Loops 17 1.2.11.3 Peak Specific Power 17 1.2.11.4 Fuel Clad 17 1.2.11.5 Fuel Assembly Design 18 1.2.11.6 Engineered Safety Features 18 1.2.11.7 Emergency Power 18 1.2.12 STATION WATER USE 18 1.2.13 FACILITY SAFETY CONCLUSIONS 19 1.3 COMPARISON TABLES 20 1.3.1 COMPARISONS WITH SIMILAR FACILITY DESIGNS 20 1.3.2 COMPARISON OF FINAL AND PRELIMINARY SAFETY 20 ANALYSIS REPORT INFORMATION (Historical) 1.3.2.1 Partial Length Rod Cluster Control Assemblies 20 1.3.2.2 Burnable Shim Rods 20 1.3.2.3 Safety Injection System Trip Signal 20 1.3.2.4 Containment Spray System Signal 20 1.3.2.5 Safety Injection System Accumulators 21 1.3.2.6 Spray Additive 21 1.3.2.7 Rod Stop and Reactor Trip on Startup 21 1.3.2.8 Miniature Neutron Flux Detectors 21 1.3.2.9 Core Thermocouples 21 1.3.2.10 Initial Leak Rate Test Method 21 1.3.2.11 Auxiliary Building Ventilation Filters 21 1.3.2.12 Control Center Buses 21 1.3.2.13 Condenser Circulating Water Flow 21 1.3.2.14 Ramp Loading Range 21 1.3.2.15 Condensate Storage Tanks Capacity 22 1.3.2.16 Fuel Transfer System Drive 22 1.3.2.17 Steam Line Flow Nozzles 22 1.3.3 Comparison of Uprate Parameters 22 Table 1.3-1 COMPARISON OF DESIGN PARAMETERS WITH POINT 23 BEACH Page 2 of 9 Revision 28 5/2019
GINNA/UFSAR Table 1.3-2 COMPARISON OF DESIGN PARAMETERS WITH SAN 33 ONOFRE AND CONNECTICUT YANKEE Table 1.3-3 COMPARISON OF GINNA AND KEWAUNEE UPRATE NSSS 35 DESIGN PARAMETERS 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 36 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 38 1.
5.1 INTRODUCTION
38 1.5.2 DEVELOPMENT OF THE FINAL CORE DESIGN AND FINAL 38 THERMAL-HYDRAULIC AND PHYSICS PARAMETERS 1.5.3 CORE STABILITY 39 1.5.3.1 Core Power Distribution 39 1.5.3.2 Out-of-Core Ion Chambers 39 1.5.3.3 In-Core Control Equipment 40 1.5.3.4 Startup Test Program 40 1.5.4 DEVELOPMENT OF LONG ION CHAMBERS 41 1.5.5 CONTROL ROD EJECTION AND DROPPED CONTROL ROD 42 ACCIDENT ANALYSES 1.5.6 CHARCOAL FILTERS 43 1.5.7 REACTOR COOLANT PUMP CONTROLLED LEAKAGE 43 SEALS 1.5.8 SAFETY INJECTION SYSTEM 44 1.5.8.l Development of Safety Injection System Design 44 1.5.8.2 Development of Core Cooling Analysis 44 1.5.9 DEVELOPMENT OF DESIGN, INSPECTION, AND ACCEP- 45 TANCE CRITERIA FOR PRESTRESSED REINFORCED-CON-CRETE PRESSURE VESSELS 1.5.9.1 Rock Anchors 45 1.5.9.1.1 Design Criteria and Assumptions 45 1.5.9.1.2 Test Verification and Results 45 1.5.9.2 Rock Anchor Grout 45 1.5.9.3 Tendon Inspection and Acceptance Criteria 46 1.5.9.4 Wall Tendons 46 1.5.9.4.1 Corrosion Protection 46 1.5.9.4.2 Inspection and Acceptance 47 Page 3 of 9 Revision 28 5/2019
GINNA/UFSAR 1.5.10 DEVELOPMENT OF CONTAINMENT HYDROGEN RECOM- 47 BINER REFERENCES FOR SECTION 1.5 48 1.6 MATERIAL INCORPORATED BY REFERENCE 49 1.7 DRAWINGS AND OTHER DETAILED INFORMATION 59 1.7.1 ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAW- 59 INGS 1.7.2 PIPING AND INSTRUMENTATION DIAGRAMS (P&ID) 59 1.7.3 OTHER DETAILED INFORMATION 59 Table 1.7-1 ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAW- 60 INGS Table 1.7-2 PIPING AND INSTRUMENTATION DIAGRAMS (P&ID) 61 1.8 CONFORMANCE TO NRC REGULATORY GUIDES 68 1.8.1 CONFORMANCE TO AEC SAFETY GUIDES 68 1.8.1.1 Safety Guide 1 -Net Positive Suction Head for Emergency Core 68 Cooling and Containment Heat Removal System Pumps 1.8.1.2 Safety Guide 2 -Thermal Shock to Reactor Pressure Vessels 68 1.8.1.3 Safety Guide 3 -Assumptions Used for Evaluating the Potential 69 Radiological Consequences of a Loss-of-Coolant Accident for Boil-ing Water Reactors 1.8.1.4 Safety Guide 4 -Assumptions Used for Evaluating the Potential 69 Radiological Consequences of a Loss-of-Coolant Accident for Pres-surized Water Reactors 1.8.1.5 Safety Guide 5 - Assumptions Used for Evaluating the Potential 69 Radiological Consequences of a Steam Line Break Accident for Boil-ing Water Reactors 1.8.1.6 Safety Guide 6 -Independence Between Redundant Standby (Onsite) 69 Power Sources and Between Their Distribution Systems 1.8.1.7 Safety Guide 7 -Control of Combustible Gas Concentrations in Con- 70 tainment Following a Loss-of-Coolant Accident 1.8.1.8 Safety Guide 8 -Personnel Selection and Training 70 1.8.1.9 Safety Guide 9 -Selection of Diesel-Generator Set Capacity for 70 Standby Power Supplies 1.8.1.10 Safety Guide 10 -Mechanical (Cadweld) Splices in Reinforcing Bars 71 of Concrete Containments 1.8.1.11 Safety Guide 11 -Instrument Lines Penetrating Primary Reactor Con- 72 tainment 1.8.1.12 Safety Guide 12 -Instrumentation for Earthquakes 72 Page 4 of 9 Revision 28 5/2019
GINNA/UFSAR 1.8.1.13 Safety Guide 13 -Fuel Storage Facility Design Basis 72 1.8.1.14 Safety Guide 14 -Reactor Coolant Pump Flywheel Integrity 73 1.8.1.15 Safety Guide 15 -Testing of Reinforcing Bars for Concrete Structures 74 1.8.1.16 Safety Guide 16 -Reporting of Operating Information 75 1.8.1.17 Safety Guide 17 -Protection Against Industrial Sabotage 75 1.8.1.18 Safety Guide 18 - Structural Acceptance Test for Concrete Primary 76 Reactor Containments 1.8.1.18.1 Structural Integrity Test 76 1.8.1.18.2 Instrumentation 76 1.8.1.18.3 Displacement Measurements 77 1.8.1.18.4 Strain Measurements 78 1.8.1.18.5 Test Results 78 1.8.1.19 Safety Guide 19 -Nondestructive Examination of Primary Contain- 79 ment Liners 1.8.1.19.1 Test Provisions 79 1.8.1.19.2 Examination of Welds 79 1.8.1.19.3 Pressure Tests 80 1.8.1.19.4 Quality Control Provisions 80 1.8.1.20 Safety Guide 20 -Vibration Measurements on Reactor Internals 81 1.8.1.21 Safety Guide 21 -Measuring and Reporting Effluents From Nuclear 81 Power Plants 1.8.1.22 Safety Guide 22 -Periodic Testing of Protection System Actuation 82 Functions 1.8.1.23 Safety Guide 23 -Onsite Meteorological Programs 82 1.8.1.24 Safety Guide 24 -Assumptions Used for Evaluating the Potential 83 Radiological Consequences of a Pressurized Water Reactor Radioac-tive Gas Storage Tank Failure 1.8.1.25 Safety Guide 25 - Assumptions Used for Evaluating the Potential 83 Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors 1.8.1.26 Safety Guide 26 -Quality Group Classification and Standards 83 1.8.1.27 Safety Guide 27 -Ultimate Heat Sink 83 1.8.1.28 Safety Guide 28 -Quality Assurance Program Requirements 84 1.8.1.29 Safety Guide 29 -Seismic Design Classification 84 1.8.2 CONFORMANCE TO DIVISION I REGULATORY GUIDES 85 Page 5 of 9 Revision 28 5/2019
GINNA/UFSAR 1.8.2.1 Regulatory Guide 1.4 -Assumptions Used for Evaluating the Poten- 85 tial Radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors 1.8.2.2 Regulatory Guide 1.10 -Mechanical (Cadweld) Splices in Reinforc- 85 ing Bars of Category I Concrete Structures 1.8.2.3 Regulatory Guide 1.15 -Testing of Reinforcing Bars for Category I 85 Concrete Structures 1.8.2.4 Regulatory Guide 1.16 -Reporting of Operating Information 85 1.8.2.5 Regulatory Guide 1.17 -Protection of Nuclear Plants Against Indus- 85 trial Sabotage 1.8.2.6 Regulatory Guide 1.18 -Structural Acceptance Test for Concrete Pri- 85 mary Reactor Containments 1.8.2.7 Regulatory Guide 1.19 -Nondestructive Examination of Primary 85 Containment Liner Welds 1.8.2.8 Regulatory Guide 1.26, Revision 3 - Quality Group Classifications & 86 Standards for Water, Steam, and Radioactive -Waste Containing Components of Nuclear Power Plants 1.8.2.9 Regulatory Guide 1.29, Revision 3 -Seismic Design Classification 86 1.8.2.10 Regulatory Guide 1.30 - Quality Assurance Requirements for the 86 Installation, Inspection, and Testing of Instrumentation and Electrical Equipment 1.8.2.11 Regulatory Guide 1.31 -Control of Stainless Steel Welding 87 1.8.2.12 Regulatory Guide 1.32 -Use of IEEE Standard 308-1971, Criteria for 88 Class IEE Electric Systems for Nuclear Power Generating Stations 1.8.2.13 Regulatory Guide 1.33 -Quality Assurance Program Requirements 89 (Operation) 1.8.2.14 Regulatory Guide 1.34 -Control of Electroslag Weld Properties 89 1.8.2.15 Regulatory Guide 1.35 -Inservice Surveillance of Ungrouted Ten- 89 dons in Prestressed Concrete Containment Structures 1.8.2.16 Regulatory Guide 1.36, Revision 0 -Nonmetallic Thermal Insulation 90 for Austenitic Stainless Steel 1.8.2.17 Regulatory Guide 1.37, Revision 0 -Quality Assurance for Cleaning 90 of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants 1.8.2.18 Regulatory Guide 1.38, Revision 2 - Quality Assurance Require- 91 ments for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants 1.8.2.19 Regulatory Guide 1.39 -Housekeeping Requirements for Water- 92 Cooled Nuclear Power Plants Page 6 of 9 Revision 28 5/2019
GINNA/UFSAR 1.8.2.20 Regulatory Guide 1.40 -Qualification Tests of Continuous-Duty 92 Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants 1.8.2.21 Regulatory Guide 1.41 - Preoperational Testing of Redundant Onsite 92 Electric Power Systems to Verify Proper Load Group Assignments 1.8.2.22 Regulatory Guide 1.42 -Interim Licensing Policy on As Low As 93 Practicable for Gaseous Radioiodine Releases from Light-Water-Cooled Nuclear Power Reactors 1.8.2.23 Regulatory Guide 1.43 -Control of Stainless Steel Weld Cladding of 93 Low-Alloy Steel Components 1.8.2.24 Regulatory Guide 1.44 - Control of the Use of Sensitized Stainless 94 Steel 1.8.2.25 Regulatory Guide 1.45 -Reactor Coolant Pressure Boundary Leakage 95 Detection System 1.8.2.26 Regulatory Guide 1.46 -Protection Against Pipe Whip Inside Con- 96 tainment 1.8.2.27 Regulatory Guide 1.47 -Bypassed and Inoperable Status Indication 96 for Nuclear Power Plant Safety Systems 1.8.2.28 Regulatory Guide 1.48 -Design Limits and Loading Combinations 96 for Seismic Category I Fluid System Components 1.8.2.29 Regulatory Guide 1.49 -Power Levels of Water-Cooled Nuclear 97 Power Plants 1.8.2.30 Regulatory Guide 1.50 -Control of Preheat Temperature for Welding 97 of Low-Alloy Steel 1.8.2.31 Regulatory Guide 1.51 -Inservice Inspection of ASME Code Class 2 98 and 3 Nuclear Power Plant Components 1.8.2.32 Regulatory Guide 1.52 - Design, Testing, and Maintenance Criteria 98 for Atmospheric Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants 1.8.2.33 Regulatory Guide 1.53 -Application of the Single-Failure Criterion 99 To Nuclear Power Plant Protection Systems 1.8.2.34 Regulatory Guide 1.54, Revision 0 -Quality Assurance Requirements 99 for Protective Coatings Applied to Water-Cooled Nuclear Power Plants 1.8.2.35 Regulatory Guide 1.55 -Concrete Placement in Seismic Category I 100 Structures 1.8.2.36 Regulatory Guide 1.57 -Design Limits and Loading Combinations 100 for Metal Primary Reactor Containment System Components 1.8.2.37 Regulatory Guide 1.59 -Design-Basis Floods for Nuclear Power 100 Plants Page 7 of 9 Revision 28 5/2019
GINNA/UFSAR 1.8.2.38 Regulatory Guide 1.94, Revision 1 - Quality Assurance Installation, 101 Inspections, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants 1.8.2.39 Regulatory Guide 1.143, Revision 1 - Design Guidance for Radioac- 101 tive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants 1.8.3 CONFORMANCE TO IEEE CRITERIA 101 1.8.3.1 Criteria for Protection Systems for Nuclear Power Generating Sta- 101 tions (IEEE 279-1971) 1.8.3.2 Class 1E Electric Systems for Nuclear Power Generating Stations 101 (IEEE 308-1971) 1.8.3.2.1 Principal Design Criteria 101 1.8.3.2.2 Alternating Current Power Systems 102 1.8.3.2.2.1 General 102 1.8.3.2.2.2 Distribution Systems 103 1.8.3.2.2.3 Preferred Power Supply 103 1.8.3.2.2.4 Standby Power Supply 103 1.8.3.2.3 Direct Current Power Systems 104 1.8.3.2.3.1 General 104 1.8.3.2.3.2 Distribution System 104 1.8.3.2.3.3 Battery Supply 104 1.8.3.2.3.4 Battery Charger Supply 104 1.8.3.2.3.5 Protective Devices 105 1.8.3.2.3.6 Performance Discharge Test Provisions 105 1.8.3.2.4 Vital Instrumentation and Control Power Systems 105 1.8.3.2.5 Surveillance Requirements 105 1.8.3.3 Electrical Penetration Assemblies in Containment Structures for 106 Nuclear Fueled Power Generating Stations (IEEE 317 - April 1971) 1.8.3.4 Qualifying Class I Electric Equipment for Nuclear Power Generating 106 Stations (IEEE 323-April 1971) 1.8.3.5 Type Tests of Continuous Duty Class I Motors Installed Inside the 107 Containment of Nuclear Power Generating Stations (IEEE 334-1971) 1.8.3.6 Installation, Inspection, and Testing Requirements for Instrumenta- 107 tion and Electric Equipment During the Construction of Nuclear Power Generating Stations (IEEE 336-1971) 1.8.3.7 Trial Use Criteria for the Periodic Testing of Nuclear Power Generat- 108 ing Station Protection Systems (IEEE 338-1971)
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GINNA/UFSAR 1.8.3.8 Seismic Qualification of Class I Electrical Equipment for Nuclear 108 Power Generating Stations (IEEE 344-1971)
REFERENCES FOR SECTION 1.8 109 FIGURES Figure 1.2-1 Ginna Station Plot Plan Page 9 of 9 Revision 28 5/2019