ML20323A318
| ML20323A318 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/29/2020 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20323A313 | List: |
| References | |
| WBL-20-047 | |
| Download: ML20323A318 (17) | |
Text
WBN TABLE OF CONTENTS i
1.0 INTRODUCTION
AND GENERAL PLANT DESCRIPTION
1.1 INTRODUCTION
1.1.1 Introduction 1.1-1 1.1.2 Licensing Basis Documents 1.1-2 1.1.3 NRC commitments 1.1-3 1.2 GENERAL PLANT DESCRIPTION 1.2-1 1.2.1 Site Characteristics 1.2-1 1.2.2 Facility Description 1.2-2 1.2.3 General Arrangement of Major Structures and Equipment 1.2-14 1.3 COMPARISON TABLES 1.3-1 1.3.1 Comparisons with Similar Facility Designs (Historical Information) 1.3-1 1.3.2 Comparison of Final and Preliminary Designs (Historical Information) 1.3-1 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS (Historical Information) 1.4-1 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.5-1 1.5.1 17 x 17 Fuel Assembly 1.5-1 1.5.2 Heat Transfer Tests (17 x 17) 1.5-2 1.6 MATERIAL INCORPORATED BY REFERENCE 1.6-1 1.7 ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAWINGS 1.7-1 1.8 TECHNICAL QUALIFICATION OF APPLICANT 1.8-1 1.9 NUCLEAR PERFORMANCE PLAN (Historical Information) 1.9-1 1.9.1 Corrective Action Plans (CAPs) (Historical Information) 1.9-1 1.9.2 Special Programs (SPs) (Historical Information) 1.9-6 2.0 SITE CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPHY 2.1-1 2.1.1 Site Location and Description 2.1-1 2.1.2 Exclusion Area Authority and Control 2.1-2 2.1.3 Population Distribution 2.1-3 2.2 NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES 2.2-1 2.2.1 Location and Route 2.2-1 2.2.2 Descriptions 2.2-1 2.2.3 Evaluations of Potential Accidents 2.2-2
WBN TABLE OF CONTENTS ii 2.3 METEOROLOGY 2.3-1 2.3.1 Regional Climate 2.3-1 2.3.2 Local Meteorology 2.3-5 2.3.3 Onsite Meteorological Measurements Program 2.3-9 2.3.4 Short-Term (Accident) Diffusion Estimates 2.3-13 2.3.5 Long-Term (Routine) Diffusion Estimates 2.3-17 2.4 HYDROLOGIC ENGINEERING 2.4-1 2.4.1 Hydrological Description 2.4-1 2.4.2 Floods 2.4-5 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers 2.4-10 2.4.4 Potential Dam Failures, Seismically Induced 2.4-26 2.4.5 Probable Maximum Surge and Seiche Flooding 2.4-38 2.4.6 Probable Maximum Tsunami Flooding 2.4-38 2.4.7 Ice Effects 2.4-38 2.4.8 Cooling Water Canals and Reservoirs 2.4-39 2.4.9 Channel Diversions 2.4-39 2.4.10 Flooding Protection Requirements 2.4-40 2.4.11 Low Water Considerations 2.4-40 2.4.12 Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents 2.4-42 2.4.13 Groundwater 2.4-45 2.4.14 Flooding Protection Requirements 2.4-48 APPENDIX 2.4A SOCH MODEL 2.4A-1 2.5 GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING
SUMMARY
OF FOUNDATION CONDITIONS - Historical Information 2.5-1 2.5.1 Basic Geology and Seismic Information 2.5-2 2.5.2 Vibratory Ground Motion 2.5-34 2.5.3 Surface Faulting 2.5-46 2.5.4 Stability of Subsurface Materials 2.5-57 2.5.5 Stability of Slopes 2.5-121 2.5.6 Embankments 2.5-130 3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 3.1-1 3.1.1 Introduction 3.1-1 3.1.2 WBNP Conformance with GDCs 3.1-1 3.2 CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS 3.2-1 3.2.1 Seismic Classifications 3.2-1 3.2.2 System Quality Group Classification 3.2-2 3.2.3 Code Cases and Code Editions and Addenda 3.2-4
WBN-1 TABLE OF CONTENTS iii 3.3 WIND AND TORNADO LOADING 3.3-1 3.3.1 Wind Loadings 3.3-1 3.3.2 Tornado Loadings 3.3-1 3.4 WATER LEVEL (FLOOD) DESIGN 3.4-1 3.4.1 Flood Protection 3.4-1 3.4.2 Analysis Procedure 3.4-1 3.5 MISSILE PROTECTION 3.5-1 3.5.1 Missile Selection and Description 3.5-2 3.5.2 Systems To Be Protected 3.5-17 3.5.3 Barrier Design Procedures 3.5-18 APPENDIX 3.5A ESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES 3.5A-1 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING 3.6-1 APPENDIX 3.6A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIPING) 3.6A-l 3.6A.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment 3.6A-7 3.6A.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping 3.6A-10 3.7 SEISMIC DESIGN 3.7-1 3.7.1 Seismic Input 3.7-2 3.7.2 Seismic System Analysis 3.7-4 3.7.3 Seismic Subsystem Analysis 3.7-30 3.7.4 Seismic Instrumentation Program 3.7-61
WBN TABLE OF CONTENTS iv 3.8 DESIGN OF CATEGORY I STRUCTURES 3.8-1 3.8.1 Concrete Shield Building 3.8-1 3.8.2 Steel Containment System 3.8.2-1 3.8.3 Concrete Interior Structure 3.8.3-1 3.8.4 Other Category I Structures 3.8.4-1 3.8.5 Foundations and Concrete Supports 3.8.5-1 3.8.6 Category I(L) Cranes 3.8.6-1 APPENDIX 3.8A SHELL TEMPERATURE TRANSIENTS 3.8A-1 3.8B BUCKLING STRESS CRITERIA 3.8B-1 3.8C DOCUMENTATION OF CB&I COMPUTER PROGRAMS 3.8C-1 3.8D COMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS (historical) 3.8D-1 3.8E CODES, LOAD DEFINITIONS, AND LOAD COMBINATIONS 3.8E-1 FOR THE MODIFICATION AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF NEW FEATURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIATED AFTER JULY 1979 3.9 MECHANICAL SYSTEMS AND COMPONENTS 3.9-1 3.9.1 General Topics for Analysis of Seismic Category I ASME Code and Non-Code Items 3.9-1 3.9.2 Dynamic Testing and Analysis 3.9-4 3.9.3 ASME Code Class 1, 2 and 3 Components, Component Supports and Core Support Structures 3.9-22 3.9.4 Control Rod System 3.9-48 3.9.5 Reactor Pressure Vessel Internals 3.9-49 3.9.6 Inservice Testing of Pumps and Valves 3.9-49 3.10 SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIPMENT 3.10-1 3.10.1 Seismic Qualification Criteria 3.10-1 3.10.2 Methods and Procedures for Qualifying Electrical Equipment and Instrumentation 3.10-6 3.10.3 Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumentation and Cables 3.10-7 3.10.4 Operating License Review 3.10-10 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT 3.11-1 3.11.1 Equipment Identification and Environmental Conditions 3.11-1 3.11.2 Environmental Conditions 3.11-2 3.11.3 Electrical Equipment Within the Scope of 10 CFR 50.49 3.11-4 3.11.4 Qualification Tests and Analyses 3.11-4 3.11.5 Qualification Test Results 3.11-4 3.11.6 Loss of Heating, Ventilation, and Air Conditioning (HVAC) 3.11-5 3.11.7 Estimated Chemical and Radiation Environment 3.11-5 3.12 CONTROL OF HEAVY LOADS 3.12-1 3.12.1 Introduction/Licensing Background 3.12-1 3.12.2 Safety Basis 3.12-1
WBN TABLE OF CONTENTS v
3.12.3 Scope of Heavy Load Handling System 3.12-1 3.12.4 Control of Heavy Loads Program 3.12-2 3.12.5 Safety Evaluation 3.12-6 4.0 REACTOR 4.1
SUMMARY
DESCRIPTION 4.1-1 4.2 MECHANICAL DESIGN 4.2-1 4.2.1 Fuel 4.2-2 4.2.2 Reactor Vessel Internals 4.2-21 4.2.3 Reactivity Control System 4.2-27 4.2.4 Tritium Producing Burnable Assembly Rod - Tritium 4.2-56 Production Core 4.3 NUCLEAR DESIGN 4.3-1 4.3.1 Design Bases 4.3-1 4.3.2 Description 4.3-7 4.3.3 Analytical Methods 4.3-42 4.4 THERMAL AND HYDRAULIC DESIGN 4.4-1 4.4.1 Design Bases 4.4-1 4.4.2 Description 4.4-4 4.4.3 Evaluation 4.4-23 4.4.4 Testing and Verification 4.4-34 4.4.5 Instrumentation Application 4.4-35 5.0 REACTOR COOLANT SYSTEM 5.1
SUMMARY
DESCRIPTION 5.1-1 5.1.1 Schematic Flow Diagram 5.1-6 5.1.2 Piping and Instrumentation Diagrams 5.1-6 5.1.3 Elevation Drawing 5.1-6 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 5.2-1 5.2.1 Design of Reactor Coolant Pressure Boundary Components 5.2-2 5.2.2 Overpressurization Protection 5.2-34 5.2.3 General Material Considerations 5.2-41 5.2.4 Fracture Toughness 5.2-44 5.2.5 Austenitic Stainless Steel 5.2-47 5.2.6 Pump Flywheels 5.2-54 5.2.7 RCPB Leakage Detection Systems 5.2-56 5.2.8 Inservice Inspection of ASME Code Class 1 Components 5.2-67 5.3 THERMAL HYDRAULIC SYSTEM DESIGN 5.3-1 5.3.1 Analytical Methods and Data 5.3-1 5.3.2 Operating Restrictions on Pumps 5.3-1 5.3.3 Power-Flow Operating Map (BWR) 5.3-1 5.3.4 Temperature-Power Operating Map 5.3-1 5.3.5 Load Following Characteristics 5.3-1
WBN TABLE OF CONTENTS vi 5.3.6 Transient Effects 5.3-1 5.3.7 Thermal and Hydraulic Characteristics Summary Table 5.3-1 5.4 REACTOR VESSEL AND APPURTENANCES 5.4-1 5.4.1 Design Bases 5.4-1 5.4.2 Description 5.4-2 5.4.3 Evaluation 5.4-4 5.4.4 Tests and Inspections 5.4-13 5.5 COMPONENT AND SUBSYSTEM DESIGN 5.5-1 5.5.1 Reactor Coolant Pumps 5.5-1 5.5.2 Steam Generators 5.5-8 5.5.3 Reactor Coolant Piping 5.5-21 5.5.4 Steam Outlet Flow Restrictor (Steam Generator) 5.5-26 5.5.5 Main Steam Line Isolation System 5.5-27 5.5.6 Reactor Vessel Head Vent System 5.5-27 5.5.7 Residual Heat Removal System 5.5-30 5.5.8 Reactor Coolant Cleanup System 5.5-38 5.5.9 Main Steam Line and Feedwater Piping 5.5-38 5.5.10 Pressurizer 5.5-38 5.5.11 Pressurizer Relief Tank 5.5-43 5.5.12 Valves 5.5-45 5.5.13 Safety and Relief Valves 5.5-46 5.5.14 Component Supports 5.5-48 5.6 INSTRUMENTATION APPLICATION 5.6-1 6.0 ENGINEERED SAFETY FEATURES 6.1 ENGINEERED SAFETY FEATURE MATERIALS 6.1-1 6.1.1 Metallic Materials 6.1-1 6.1.2 Organic Materials 6.1-3 6.1.3 Post-Accident Chemistry 6.1-5 6.1.4 Degree of Compliance with Regulatory Guide 1.54 for Paints and Coatings Inside Containment 6.1-6 6.2 CONTAINMENT SYSTEMS 6.2.1-1 6.2.1 Unit 1 Containment Functional Design UNIT 1 6.2.1-1 6.2.1 Unit 2 Containment Functional Design UNIT 2 6.2.1-1 6.2.2 Containment Heat Removal Systems 6.2.2-1 6.2.3 Secondary Containment Functional Design 6.2.3-1 6.2.4 Containment Isolation Systems 6.2.4-1 6.2.5 Unit 1 Combustible Gas Control in Containment UNIT 1 6.2.5-1 6.2.5A Hydrogen Mitigation System 6.2.5-5 6.2.6 Unit 1 Containment Leakage Testing UNIT 1 6.2.6-1 6.2.6 Unit 2 Containment Leakage Testing UNIT 2 6.2.6-1 6.3 Unit 1 EMERGENCY CORE COOLING SYSTEM UNIT 1 6.3-1 6.3.1 Design Bases 6.3-1
WBN TABLE OF CONTENTS vii 6.3.2
System Design
6.3-2 6.3.3 Performance Evaluation 6.3-26 6.3.4 Tests and Inspections 6.3-30 6.3.5 Instrumentation Application 6.3-32 6.3 Unit 2 EMERGENCY CORE COOLING SYSTEM UNIT 2 6.3-1 6.3.1 Design Bases 6.3-1 6.3.2
System Design
6.3-2 6.3.3 Performance Evaluation 6.3-21 6.3.4 Tests and Inspections 6.3-26 6.3.5 Instrumentation Application 6.3-27 6.4 HABITABILITY SYSTEMS 6.4-1 6.4.1 Design Bases 6.4-1 6.4.2
System Design
6.4-1 6.4.3 System Operational Procedures 6.4-5 6.4.4 Design Evaluations 6.4-7 6.4.5 Testing and Inspection 6.4-9 6.4.6 Instrumentation Requirements 6.4-9 6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.5-1 6.5.1 Engineered Safety Feature (ESF) Filter Systems 6.5-1 6.5.2 Containment Spray System for Fission Product Cleanup 6.5-8 6.5.3 Fission Product Control Systems 6.5-9 6.5.4 Ice Condenser as a Fission Product Cleanup System 6.5-11 6.6 INSERVICE INSPECTION OF ASME CODE CLASS 2 AND 3 COMPONENTS 6.6-1 6.6.1 Components Subject to Examination and/or Test 6.6-1 6.6.2 Accessibility 6.6-1 6.6.3 Examination Techniques and Procedures 6.6-1 6.6.4 Inspection Intervals 6.6-1 6.6.5 Examination Categories and Requirements 6.6-1 6.6.6 Evaluation of Examination Results 6.6-2 6.6.7 System Pressure Tests 6.6-2 6.6.8 Protection against Postulated Piping Failures 6.6-2 6.7 ICE CONDENSER SYSTEM 6.7-1 6.7.1 Floor Structure and Cooling System 6.7-1 6.7.2 Wall Panels 6.7-7 6.7.3 Lattice Frames and Support Columns 6.7-9 6.7.4 Ice Baskets 6.7-13 6.7.5 Crane and Rail Assembly 6.7-20 6.7.6 Refrigeration System 6.7-21 6.7.7 Air Handling Units 6.7-29 6.7.8 Lower Inlet Doors 6.7-31 6.7.9 Lower Support Structure 6.7-38 6.7.10 Top Deck and Doors 6.7-49 6.7.11 Intermediate Deck and Doors 6.7-54 6.7.12 Air Distribution Ducts 6.7-58 6.7.13 Equipment Access Door 6.7-59
WBN TABLE OF CONTENTS viii 6.7.14 Ice Technology, Ice Performance, and Ice Chemistry 6.7-60 6.7.15 Ice Condenser Instrumentation 6.7-66 6.7.16 Ice Condenser Structural Design 6.7-69 6.7.17 Seismic Analysis 6.7-71 6.7.18 Materials 6.7-75 6.7.19 Tests and Inspections 6.7-79 6.8 AIR RETURN FANS 6.8-1 6.8.1 Design Bases 6.8-1 6.8.2
System Description
6.8-1 6.8.3 Safety Evaluation 6.8-2 6.8.4 Inspection and Testing 6.8-4 6.8.5 Instrumentation Requirements 6.8-4 6.9 MOTOR-OPERATED VALVE (MOV) PROGRAMS 6.9-1 7.0 INSTRUMENTATION AND CONTROLS
7.1 INTRODUCTION
7.1-1 7.1.1 Identification of Safety-Related Systems 7.1-4 7.1.2 Identification of Safety Criteria 7.1-6 7.2 REACTOR TRIP SYSTEM 7.2-1 7.2.1 Description 7.2-1 7.2.2 Analyses 7.2-19 7.2.3 Tests and Inspections 7.2-38 7.3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM 7.3-1 7.3.1 Description 7.3-1 7.3.2 Analysis 7.3-9 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.4-1 7.4.1 Description 7.4-1 7.4.2 Auxiliary Control Room (ACR) 7.4-5 7.4.3 Analysis 7.4-6 7.5 INSTRUMENTATION SYSTEMS IMPORTANT TO SAFETY 7.5-1 7.5.1 Post Accident Monitoring (PAM) 7.5-1 7.5.2 Plant Computer System 7.5-9 7.6 ALL OTHER SYSTEMS REQUIRED FOR SAFETY 7.6-1 7.6.1 120V ac and 125V dc Vital Plant Control Power System 7.6-1 7.6.2 Residual Heat Removal Isolation Valves 7.6-1 7.6.3 Refueling Interlocks 7.6-2 7.6.4 Deleted 7.6-2 7.6.5 Accumulator Motor-Operated Valves 7.6-2 7.6.6 Spurious Actuation Protection for Motor Operated Valves 7.6-3 7.6.7 Loose Parts Monitoring System (LPMS) Description 7.6-4 7.6.8 Interlocks for RCS Pressure Control During Low Temperature Operation 7.6-8
WBN-1 TABLE OF CONTENTS ix 7.6.9 Switchover from Injection to Recirculation Mode Following a LOCA 7.6-10 7.7 CONTROL SYSTEMS 7.7-1 7.7.1 Description 7.7-1 7.7.2 Analysis 7.7-26 APPENDIX 7A Instrumentation Identifications and Symbols 7A-1 8.0 ELECTRIC POWER
8.1 INTRODUCTION
8.1-1 8.1.1 Utility Grid and Interconnections 8.1-1 8.1.2 Plant Electrical Power System 8.1-1 8.1.3 Safety-Related Loads 8.1-3 8.1.4 Design Bases 8.1-3 8.1.5 Design Criteria and Standards 8.1-4 8.2 OFFSITE (PREFERRED) POWER SYSTEM 8.2-1 8.2.1 Description 8.2-1 8.2.2 Analysis 8.2-20 8.3 ONSITE (STANDBY) POWER SYSTEM 8.3-1 8.3.1 AC Power System 8.3-1 8.3.2 DC Power System 8.3-53 8.3.3 Fire Protection for Cable Systems 8.3-68 APPENDIX 8A Analysis of Submerged Electrical Equipment (During Post LOCA)
Powered from Auxiliary Power System 8A-1 8B Analysis of Submerged Electrical Equipment (During Post LOCA)
Powered from Instrumentation and Control Power System 8B-1 8C Probability/Reliability Analysis of Protection Device Schemes 8C-1 for Associated and Non-class 1E Cables 9.0 AUXILIARY SYSTEM 9.1 FUEL STORAGE AND HANDLING 9.1-1 9.1.1 New Fuel Storage 9.1-1 9.1.2 Spent Fuel Storage 9.1-2 9.1.3 Spent Fuel Pool Cooling and Cleanup System (SFPCCS) 9.1-5 9.1.4 Fuel Handling System 9.1-14 9.1.5 Tritium Producing Burnable Absorber Rods (TPBARs) 9.1-29 Consolidation Activity (Unit 1 Only) 9.1.6 Independent Spent Fuel Storage Installation (ISFSI) 9.1-31
WBN-3 TABLE OF CONTENTS x
9.2 WATER SYSTEMS 9.2-1 9.2.1 Essential Raw Cooling Water (ERCW) 9.2-1 9.2.2 Component Cooling System (CCS) 9.2-11 9.2.3 Demineralized Water Makeup System 9.2-24 9.2.4 Potable and Sanitary Water Systems 9.2-26 9.2.5 Ultimate Heat Sink 9.2-31 9.2.6 Condensate Storage Facilities 9.2-34 9.2.7 Refueling Water Storage Tank 9.2-37 9.2.8 Raw Cooling Water System 9.2-40 9.3 PROCESS AUXILIARIES 9.3-1 9.3.1 Compressed Air System 9.3-1 9.3.2 Process Sampling System 9.3-6 9.3.3 Equipment and Floor Drainage System 9.3-13 9.3.4 Chemical and Volume Control System 9.3-17 9.3.5 Failed Fuel Detection System 9.3-44 9.3.6 Auxiliary Charging System 9.3-45 9.3.7 Boron Recycle System 9.3-48 9.3.8 Heat Tracing 9.3-48 9.4 AIR CONDITIONING, HEATING, COOLING, AND VENTILATION SYSTEMS 9.4-1 9.4.1 Control Room Area Ventilation System 9.4-1 9.4.2 Fuel Handling Area Ventilation System 9.4-9 9.4.3 Auxiliary and Radwaste Area Ventilation System 9.4-13 9.4.4 Turbine Building Area Ventilation System 9.4-25 9.4.5 Engineered Safety Feature Ventilation System 9.4-28 9.4.6 Reactor Building Purge Ventilating System (RBPVS) 9.4-39 9.4.7 Containment Air Cooling System 9.4-46 9.4.8 Condensate Demineralizer Waste Evaporator Building Environmental Control System (Historical Information) 9.4-50 9.4.9 Post Accident Sampling Facility Environmental Control System 9.4-51 UNIT 1 ONLY 9.5 OTHER AUXILIARY SYSTEMS 9.5-1 9.5.1 Fire Protection System 9.5-1 9.5.2 Plant Communications System 9.5-1 9.5.3 Lighting Systems 9.5-8 9.5.4 Diesel Generator Fuel Oil Storage and Transfer System 9.5-11 9.5.5 Diesel Generator Cooling Water System 9.5-16 9.5.6 Diesel Generator Starting System 9.5-18 9.5.7 Diesel Engine Lubrication System 9.5-20 9.5.8 Diesel Generator Combustion Air Intake and Exhaust System 9.5-23 10.0 MAIN STEAM AND POWER CONVERSION SYSTEMS 10.1
SUMMARY
DESCRIPTION 10.1-1 10.2 TURBINE GENERATOR 10.2-1 10.2.1 Design Bases 10.2-1 10.2.2 Description 10.2-1 10.2.3 Turbine Rotor and Disc Integrity - Historical Information 10.2-4
WBN TABLE OF CONTENTS xi 10.2.4 Evaluation 10.2-21 10.3 MAIN STEAM SUPPLY SYSTEM 10.3-1 10.3.1 Design Bases 10.3-1 10.3.2
=
System Description===
10.3-1 10.3.3 Design Evaluation 10.3-2 10.3.4 Inspection and Testing Requirements 10.3-4 10.3.5 Water Chemistry 10.3-4 10.3.6 Steam Feedwater System Materials 10.3-7 10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-1 10.4.1 Main Condenser 10.4-1 10.4.2 Main Condenser Evacuation System 10.4-5 10.4.3 Turbine Gland Sealing System 10.4-7 10.4.4 Turbine Bypass System 10.4-8 10.4.5 Condenser Circulating Water System 10.4-10 10.4.6 Condensate Polishing Demineralizer System 10.4-15 10.4.7 Condensate and Feedwater Systems 10.4-19 10.4.8 Steam Generator Blowdown System 10.4-30 10.4.9 Auxiliary Feedwater System 10.4-33 11.0 RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE TERMS 11.1-1 11.1.1 Historical Design Model for Radioactivities in Systems and Components 11.1-1 11.1.2 Realistic Model for Radioactivities in Systems and Components 11.1-3 11.1.3 Plant Leakage 11.1-3 11.1.4 Additional Sources 11.1-4 11.2 LIQUID WASTE SYSTEMS 11.2-1 11.2.1 Design Objectives 11.2-1 11.2.2 System Descriptions 11.2-1 11.2.3
System Design
11.2-5 11.2.4 Operating Procedure 11.2-10 11.2.5 Performance Tests 11.2-16 11.2.6 Estimated Releases 11.2-17 11.2.7 Release Points 11.2-20 11.2.8 Dilution Factors 11.2-20 11.2.9 Estimated Doses from Radionuclides in Liquid Effluents 11.2-20 11.3 GASEOUS WASTE SYSTEMS 11.3-1 11.3.1 Design Bases 11.3-1 11.3.2
=
System Description===
11.3-1 11.3.3
System Design
11.3-3 11.3.4 Operating Procedure 11.3-5 11.3.5 Performance Tests 11.3-7 11.3.6 Deleted 11.3-7 11.3.7 Radioactive Releases 11.3-7 11.3.8 Release Points 11.3-9 11.3.9 Atmospheric Dilution 11.3-10 11.3.10 Estimated Doses from Radionuclides in Gaseous Effluents 11.3-11
WBN TABLE OF CONTENTS xii 11.4 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEM 11.4-1 11.4.1 Design Objectives 11.4-1 11.4.2 Continuous Monitors 11.4-2 11.4.3 Sampling 11.4-8 11.4.4 Calibration and Maintenance 11.4-8 11.5 SOLID WASTE MANAGEMENT SYSTEM 11.5-1 11.5.1 Design Objectives 11.5-1 11.5.2 System Inputs 11.5-1 11.5.3
=
System Description===
11.5-1 11.5.4 Equipment Operation 11.5-4 11.5.5 Storage Facilities 11.5-4 11.5.6 Shipment 11.5-5 11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM 11.6-1 11.6.1 Expected Background 11.6-2 11.6.2 Critical Pathways to Man 11.6-3 11.6.3 Sampling Media, Locations and Frequency 11.6-4 11.6.4 Analytical Sensitivity 11.6-5 11.6.5 Data Analysis and Presentation 11.6-5 11.6.6 Program Statistical Sensitivity 11.6-5 APPENDIX 11A TRITIUM CONTROL 11A-1 11A.1 System Sources 11A-1 11A.2 The Fission Source 11A-1 11A.3 Control Rod Source 11A-1 11A.4 Boric Acid Source 11A-2 11A.5 Burnable Shim Rod Source 11A-2 11A.6 Tritium Releases 11A-2 11A.7 Design Bases 11A-2 11A.8 Design Evaluation 11A-3 11A.9 Tritium Lead Test Assembly 11A-3 11A.10 Tritum Producing Burnable Adsorber Rod (TPBAR) (Unit 1 Only) 11A-4 12.0 RADIATION PROTECTION 12.1 ASSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS REASONABLY ACHIEVABLE (ALARA) 12.1-1 12.1.1 Policy Considerations 12.1-1 12.1.2 Design Considerations 12.1-1 12.1.3 ALARA Operational Considerations 12.1-2 12.2 RADIATION SOURCES 12.2-1 12.2.1 Contained Sources 12.2-1 12.2.2 Airborne Radioactive Material Sources 12.2-10
WBN TABLE OF CONTENTS xiii 12.3 RADIATION PROTECTION DESIGN FEATURES 12.3-1 12.3.1 Facility Design Features 12.3-1 12.3.2 Shielding 12.3-5 12.3.3 Ventilation 12.3-17 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation 12.3-19 12.4 DOSE ASSESSMENT 12.4-1 12.5 RADIATION PROTECTION PROGRAM 12.5-1 12.5.1 Organization 12.5-1 12.5.2 Equipment, Instrumentation, and Facilities 12.5-2 12.5.3 Procedures 12.5-4 APPENDIX 12A RADIATION PROTECTION FEATURES FOR THE TRITIUM PRODUCTION PROGRAM UNIT 1 ONLY 12A-1 13.0 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE OF APPLICANT 13.1-1 13.1.1 Corporate Organization 13.1-1 13.1.2 Nuclear Power 13.1-2 13.1.3 Qualification Requirements for Nuclear Facility Personnel 13.1-2 13.2 TRAINING PROGRAMS 13.2-1 13.2.1 Accredited Training Programs 13.2-1 13.2.2 General Employee and Fitness for Duty Training Program 13.2-1 13.2.3 Other Training Programs 13.2-1 13.3 EMERGENCY PLANNING 13.3-1 13.4 REVIEW AND AUDIT 13.4-1 13.4.1 Onsite Review 13.4-1 13.4.2 Independent Review and Audit 13.4-1 13.5 SITE INSTRUCTIONS 13.5-1 13.5.1 System of Site Instructions 13.5-1 13.5.2 Administrative Procedures 13.5-1 13.5.3 Operating Instructions and Procedures 13.5-2 13.5.4 Maintenance Instructions 13.5-3 13.5.5 Surveillance Instructions 13.5-4 13.5.6 Technical Instructions 13.5-4 13.5.7 Radiation Control Instructions 13.5-4 13.5.8 Special Test Instructions 13.5-4 13.5.9 Radiological Emergency Plan (REP) Implementing Procedures 13.5-4
WBN TABLE OF CONTENTS xiv 13.5.10 Vendor or Contractor Instructions 13.5-4 13.5.11 Radwaste Handling & Shipping 13.5-5 13.5-12 Modifications and additions Instructions 13.5-5 13.5-13 Plant Security Instructions/Standard Programs and Process 13.5-5 13.5-14 Periodic Instructions 13.5-5 13.5-15 Safety and Health Manual 13.5-5 13.5-16 Section Instructions, Manuals or Equivalent 13.5-5 13.5-17 Power Escalation Tests 13.5-6 13.5-18 Fire Protection Instructions 13.5-6 13.6 PLANT RECORDS 13.6-1 13.6.1 Plant History 13.6-1 13.6.2 Operating Records 13.6-1 13.6.3 Event Records 13.6-2 13.7 NUCLEAR SECURITY 13.7-1 13.7.1 Physical Security and Contingency Plan 13.7-1 13.7.2 Personnel and Program Evaluation 13.7-1 13.7.3 Physical Security of TPBARs 13.7-1 14.0 INITIAL TEST PROGRAM 14.1 SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY ANALYSIS REPORTS 14.1-1 14.2 TEST PROGRAM 14.2-1 14.2.1 Summary Of Test Program and Objectives 14.2-1 14.2.2 Organization and Staffing 14.2-3 14.2.3 Test Procedures and Instructions 14.2-9 14.2.4 Conduct of the Test Program 14.2-12 14.2.5 Review, Evaluation, and Approval of Test Results 14.2-14 14.2.6 Test Records 14.2-15 14.2.7 Conformance of Test Programs With Regulatory Guides 14.2-15 14.2.8 Utilization of Reactor Operating and Testing Experience in Development of Test Program 14.2-28 14.2.9 Trial Use Of Plant Operating and Emergency Procedures 14.2-28 14.2.10 Initial Fuel Loading, Postloading Tests, Initial Criticality, Low Power Tests and Power Ascension 14.2-29 14.2.11 Test Program Schedule 14.2-33 14.2.12 Individual Test Descriptions 14.2-33 APPENDIX 14A UNIT 1 TEST PROGRAM 14A.1-1 14A.0 Initial Test Program - Historical Information 14A.1-1 14A.2 Test Program - Historical Information 14A.2-1
WBN TABLE OF CONTENTS xv 15.0 ACCIDENT ANALYSES 15.1 CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS 15.1-1 15.1.1 Optimization of Control Systems 15.1-3 15.1.2 Initial Power Conditions Assumed in Accident Analyses 15.1-3 15.1.3 Trip Points and Time Delays To Trip Assumed in Accident Analyses 15.1-5 15.1.4 Instrumentation Drift and Calorimetric Errors -
Power Range Neutron Flux 15.1-6 15.1.5 Rod Cluster Control Assembly Insertion Characteristic 15.1-6 15.1.6 Reactivity Coefficients 15.1-7 15.1.7 Fission Product Inventories 15.1-9 15.1.8 Residual Decay Heat 15.1-10 15.1.9 Computer Codes Utilized 15.1-12 15.2 CONDITION II - FAULTS OF MODERATE FREQUENCY 15.2-1 15.2.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Subcritical Condition 15.2-2 15.2.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power 15.2-6 15.2.3 Rod Cluster Control Assembly Misalignment 15.2-10 15.2.4 Uncontrolled Boron Dilution 15.2-14 15.2.5 Partial Loss of Forced Reactor Coolant Flow 15.2-22 15.2.6 Startup of an Inactive Reactor Coolant Loop at an Incorrect Temperature 15.2-24 15.2.7 Loss of External Electrical Load and/or Turbine Trip 15.2-25 15.2.8 Loss of Normal Feedwater 15.2-29 15.2.9 Coincident Loss of Onsite and External (Offsite) AC Power to the Station - Loss of Offsite Power to the Station Auxiliaries 15.2-33 15.2.10 Excessive Heat Removal Due to Feedwater System Malfunctions 15.2-33 15.2.11 Excessive Load Increase Incident 15.2-36 15.2.12 Accidental Depressurization of the Reactor Coolant System 15.2-38 15.2.13 Accidental Depressurization of the Main Steam System 15.2-40 15.2.14 Inadvertent Operation of Emergency Core Cooling System 15.2-42 15.2.15 Chemical and Volume Control System Malfunction During Power Operation (Unit 2 Only) 15.2-47 15.3 CONDITION III - INFREQUENT FAULTS 15.3-1 15.3.1 Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in Large Pipes Which Actuate the Emergency Core Cooling System 15.3-1 15.3.2 Minor Secondary System Pipe Breaks 15.3-7 15.3.3 Inadvertent Loading of a Fuel Assembly into an Improper Position 15.3-7 15.3.4 Complete Loss of Forced Reactor Coolant Flow 15.3-10 15.3.5 Waste Gas Decay Tank Rupture 15.3-12 15.3.6 Single Rod Cluster Control Assembly Withdrawal at Full Power 15.3-12
WBN TABLE OF CONTENTS xvi 15.4 CONDITION IV - LIMITING FAULTS 15.4-1 15.4.1 Major Reactor Coolant System Pipe Ruptures (Loss of Coolant Accident) 15.4-1 15.4.2 Major Secondary System Pipe Rupture 15.4-31 15.4.3 Steam Generator Tube Rupture 15.4-43 15.4.4 Single Reactor Coolant Pump Locked Rotor 15.4-52 15.4.5 Fuel Handling Accident 15.4-55 15.4.6 Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection) 15.4-56 15.5 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS 15.5-1 15.5.1 Environmental Consequences of a Postulated Loss of AC Power to the Plant Auxiliaries 15.5-1 15.5.2 Environmental Consequences of a Postulated Waste Gas Decay Tank Rupture 15.5-2 15.5.3 Environmental Consequences of a Postulated Loss of Coolant Accident 15.5-3 15.5.4 Environmental Consequences of a Postulated Main Steam Line Break 15.5-22 15.5.5 Environmental Consequences of a Postulated Steam Generator Tube Rupture 15.5-24 15.5.6 Environmental Consequences of a Postulated Fuel Handling Accident (FHA) 15.5-26 15.5.7 Environmental Consequences of a Postulated Rod Ejection Accident 15.5-29 15.5.8 Tritium Production Accident Releases 15.5-30 APPENDIX 15A DOSE MODELS USED TO EVALUATE THE ENVIRONMENTAL 15A-1 CONSEQUENCES OF ACCIDENTS APPENDIX 15B OPERATION WITH A TRITIUM PRODUCTION CORE (UNIT 1 ONLY) 15B-1 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16-1 16.2 TECHNICAL SPECIFICATIONS 16-1 16.3 RELOCATED SPECIFICATIONS 16-2 16.3.1 Discussion 16-2 16.3.2 Document Control 16-2 16.3.3 Changes to the Relocated Specifications 16-2
WBN TABLE OF CONTENTS xvii 17.0 QUALITY ASSURANCE 17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION 17.1-1 17.1.1 TVA Organization 17.1-1 17.1.2 Quality Assurance Program 17.1-1 17.2 QUALITY ASSURANCE FOR STATION OPERATION 17.2-1 17.2.1 Identification of Safety Related Features 17.2-1