ML20323A317
| ML20323A317 | |
| 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: ML20323A317 (15) | |
Text
PAGE 1 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
ABBREVIATIONS BOP SYSTEM ENGINEERING - BALANCE OF PLANT CHEM CHEMISTRY CIVIL DESIGN ENGINEERING - CIVIL ENGINEERING PGM/PGMS PROGRAM/COMPONENT PROGRAM ENGINEERING EIC SYSTEM ENGINEERING - ELECTRICAL INSTRUMENTATION & CONTROL ELEC DESIGN ENGINEERING - ELECTRICAL ENGINEERING EP EMERGENCY PREPAREDNESS ENV ENVIRONMENTAL FOPS FIRE OPERATIONS FP DESIGN ENGINEERING - FIRE PROTECTION FUELS CORPORATE FUELS HR HUMAN RESOURCES LIC LICENSING MAINT MAINTENANCE - INSTRUMENT/ELECTRICAL MATL DESIGN ENGINEERING - MATERIAL ENGINEERING MECH DESIGN ENGINEERING - MECHANICAL/NUCLEAR ENGINEERING MS MANAGEMENT SERVICES NS NUCLEAR SECURITY NSA NUCLEAR SAFETY ANALYSIS NSSS SYSTEM ENGINEERING - NUCLEAR STEAM SUPPLY SYSTEM OPS OPERATIONS PGM PROGRAM/COMPONENT ENGINEERING PROGRAM QA QUALITY ASSURANCE RADPRO RADIATION PROTECTION RDS RIVER SYSTEMS OPERATIONS (DAM SAFETY)
RSO RIVER SYSTEMS OPS (AIR/LAND/WATER)
RXE REACTOR ENGINEERING TRG NUCLEAR TRAINING TPS TRANSMISSION & POWER SUPPLY
PAGE 2 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT
1.0 INTRODUCTION
AND GENERAL PLANT DESCRIPTION
1.1 INTRODUCTION
LIC 1.1.2 Licensing Basis Document LIC 1.1.3 NRC Commitments LIC 1.2 GENERAL PLANT DESCRIPTION CIVIL RXE 1.2.1.1 Location CIVIL 1.2.1.2 Demography CIVIL 1.2.1.3 Meteorology CIVIL RSO 1.2.1.4 Hydrology CIVIL 1.2.1.5 Geology CIVIL RDS 1.2.1.6 Seismology CIVIL RDS 1.2.2 Facility Description 1.2.2.2 Nuclear Steam Supply System MECH 1.2.2.3 Control and Instrumentation ELEC 1.2.2.4 Fuel Handling System MECH 1.2.2.5 Waste Processing System MECH 1.2.2.6 Steam and Power Conversion System MECH 1.2.2.7 Plant Electrical system ELEC 1.2.2.8 Cooling Water MECH 1.2.2.9 Component Cooling system MECH 1.2.2.10 Chemical and Volume Control System MECH 1.2.2.11 Sampling and Water Quality System MECH 1.2.2.12 Ventilation MECH 1.2.2.13 Fire Protection System FP 1.2.2.14 Compressed Air System MECH 1.2.2.15 Engineered Safety Features MECH 1.2.2.16 Shared Facilities and Equipment MECH 1.2.3 General Arrangement of Major Structures and MECH Equipment 1.3 COMPARISON TABLES - HISTORICAL NE 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS NE HISTORICAL 1.5 REQUIREMENTS FOR FURTHER TECHNICAL MECH RXE/FUELS INFORMATION 1.6 MATERIAL INCORPORATED BY REFERENCE MECH 1.7 ELECTRICAL, I&C CONTROL DRAWINGS ELEC EIC 1.8 TECHNICAL QUALIFICATION OF APPLICANT ELEC 1.9 NUCLEAR PERFORMANCE PLAN - HISTORICAL LIC NE
PAGE 3 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 2.0 SITE CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPHY 2.1.1 Site Location and Description CIVIL CHEM/RADPRO 2.1.1.2 Site Area Map RADPRO 2.1.1.3 Boundaries For Establishing Effluent Limits RADPRO 2.1.2 Exclusion Area Authority and Control RADPRO NS 2.1.3 Population Distribution EP CIVIL 2.1.3.4 Low Population Zone EP CIVIL/LIC 2.1.3.5 Population Center EP CIVIL/LIC 2.1.3.6 Population Density EP CIVIL/LIC 2.2 NEARBY INDUSTRIAL TRANSPORTATION, AND MILITARY FACILITIES 2.2.1 Location and Route CIVIL 2.2.2 Descriptions CIVIL 2.2.3 Evaluations of Potential Accidents CIVIL 2.3 METEOROLOGY 2.3.1 Regional Climate ENV RSO 2.3.2 Local Meteorology ENV RSO 2.3.3 Onsite Meteorological Measurements Program ENV BOP/RSO 2.3.4 Short-Term (Accident) Diffusion Estimates ENV RSO 2.3.5 Long-Term (Routine) Diffusion Estimates ENV RSO 2.4 HYDROLOGIC ENGINEERING CIVIL 2.4.1 Hydrologic Description CIVIL 2.4.2 Floods CIVIL 2.4.3 Probable Maximum Flood on Streams & Rivers CIVIL 2.4.4 Potential Dam Failures, Seismically Induced CIVIL 2.4.5 Probable Maximum Surge and Seiche Flooding CIVIL 2.4.6 Probable Maximum Tsunami Flooding CIVIL 2.4.7 Ice Effects CIVIL 2.4.8 Cooling Water Canals and Reservoirs CIVIL 2.4.9 Channel Diversions CIVIL 2.4.10 Flooding Protection Requirements CIVIL 2.4.11 Low Water Considerations CIVIL 2.4.12 Dispersion, Dilution, and Travel Times of Accidental CIVIL CHEM Releases of Liquid Effluents 2.4.13 Groundwater CIVIL 2.4.14 Flooding Protection Requirements CIVIL 2.5 GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL CIVIL ENGINEERING
SUMMARY
OF FOUNDATION CONDITIONS - HISTORICAL 3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS 3.1 CONFORMANCE WITH NRC GENERAL DESIGN CIVIL CRITERIA 3.2 CLASSIFICATION OF STRUCTURES, SYSTEMS CIVIL AND COMPONENTS
PAGE 4 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 3.3 WIND AND TORNADO LOADING CIVIL RSO 3.4 WATER LEVEL (FLOOD) DESIGN CIVIL 3.5 MISSILE PROTECTION CIVIL 3.5A ESTIMATES OF VELOCITIES OF JET CIVIL PROPELLED MISSILES 3.6 PROTECTION AGAINST DYNAMIC EFFECTS CIVIL ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING 3.6A PROTECTION AGAINST DYNAMIC EFFECTS CIVIL ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIPING) 3.6B PROTECTION AGAINST DYNAMIC EFFECTS CIVIL ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING 3.7 SEISMIC DESIGN 3.7.1 Seismic Input CIVIL RDS 3.7.2 Seismic System Analysis CIVIL RDS 3.7.3 Seismic Subsystem Analysis CIVIL RDS 3.7.4 Seismic Instrumentation Program CIVIL MAINT/EIC/RDS 3.8 DESIGN OF CATEGORY I STRUCTURES 3.8.1 Concrete Shield Building CIVIL 3.8.2 Steel Containment System CIVIL 3.8.3 Concrete Interior Structure CIVIL 3.8.4 Other Category I Structures CIVIL 3.8.5 Foundations and Concrete Supports CIVIL 3.8.6 Category I(L) Cranes CIVIL BOP 3.8A SHELL TEMPERATURE TRANSIENTS CIVIL RDS 3.8B BUCKLING STRESS CRITERIA CIVIL RDS 3.8C DOCUMENTATION OF CB&I COMPUTER PROGRAMS CIVIL RDS 3.8D COMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS CIVIL RDS 3.8E CODES, LOAD DEFINITIONS, AND LOAD CIVIL RDS COMBINATIONS FOR THE MODIFICATION &
EVALUATION OF EXISTING STRUCTURES &
FOR THE DESIGN OF NEW FEATURES ADDED To EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIATED AFTER JULY 1979
PAGE 5 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 3.9 MECHANICAL SYSTEMS AND COMPONENTS 3.9.1 General Topics for Analysis of Seismic CIVIL Category I ASME Code & Non-Code Items 3.9.2 Dynamic Testing and Analysis CIVIL 3.9.3 ASME Code Class 1, 2, and 3 Components, CIVIL MECH Component Supports and Core Support Structures 3.9.4 Control Rod System CIVIL NSSS/RXE 3.9.5 Reactor Pressure Vessel Internals CIVIL NSSS/RXE 3.9.6 Inservice Testing of Pumps and Valves PGM MECH 3.10 SEISMIC DESIGN OF CATEGORY 1 INSTRUMENTATION AND ELECTRICAL EQUIPMENT 3.10.1 Seismic Qualification Criteria CIVIL 3.10.2 Methods and Procedures for Qualifying CIVIL Electrical Equipment Instrumentation 3.10.3 Methods of Qualifying TVA-Designed CIVIL Supports for Electrical Equipment Instrumentation and Cables 3.10.4 Operating License Review CIVIL 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT 3.11.1 Equipment Identification & Environmental Conditions MECH BOP 3.11.2 Environmental Conditions MECH EIC 3.11.3 Electrical Equipment within the Scope of 10 CFR 50.49 ELEC EIC 3.11.4 Qualification Tests and Analyses ELEC EIC 3.11.5 Qualification Test Results ELEC EIC 3.11.6 Loss of Heating, Ventilation, and Air Conditioning (HVAC) MECH EIC 3.11.7 Estimated Chemical & Radiation MECH EIC Environment 3.12 CONTROL OF HEAVY LOADS CIVIL CIVIL 3.12.1 Introduction/Licensing Background CIVIL CIVIL 3.12-2 Safety Basis CIVIL CIVIL 3.12.3 Scope of Heavy Load Handling System CIVIL CIVIL 3.12.4 Control of Heavy Loads Program CIVIL CIVIL 3.12.5 Safety Evaluation CIVIL CIVIL 4.0 REACTORS 4.1
SUMMARY
DESCRIPTION FUELS MECH/RXE 4.2 MECHANICAL DESIGN MECH RXE/NSSS/FUELS 4.2.1 Fuel FUELS MECH/RXE/NSSS 4.2.2 Reactor Vessel Internals MECH RXE/NSSS/FUELS 4.2.3 Reactivity Control System MECH FUELS/RXE/NSSS 4.2.4 Tritium Producing Burnable Assembly Rods - MECH Tritium Production Core 4.3 NUCLEAR DESIGN FUELS MECH/RXE 4.4 THERMAL AND HYDRAULIC DESIGN NSA MECH
PAGE 6 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 5.0 REACTOR COOLANT SYSTEM 5.1
SUMMARY
DESCRIPTION MECH NSSS 5.2 INTEGRITY OF RCS PRESSURE BOUNDARY 5.2.1 Design of Reactor Coolant Pressure MECH SE-NSS Boundary Components 5.2.2 Overpressurization Protection MECH NSSS/OPS 5.2.3 General Material Considerations MECH NSSS 5.2.4 Fracture Toughness MECH NSSS 5.2.5 Austenitic Stainless Steel MECH NSSS 5.2.6 Pump Flywheels MECH NSSS 5.2.7 RCPB Leakage Detection System MECH OPS/MECH/CHEM 5.2.8 Inservice Inspection of ASME Code Class 1 Components PGM MECH 5.3 THERMAL HYDRAULIC SYSTEM DESIGN 5.3.1 Analytical Methods and Data NSA MECH 5.3.2 Operating Restrictions on Pumps NSA MECH 5.3.4 Temperature-Power Operating Map NSA MECH 5.3.5 Load Following Characteristics NSA MECH 5.3.6 Transient Effects NSA MECH 5.3.7 Thermal & Hydraulic Characteristics Summary Table NSA MECH 5.4 REACTOR VESSEL AND APPURTENANCES MECH NSSS 5.5 COMPONENT AND SUBSYSTEM DESIGN MECH NSSS/OPS 5.5.1 Reactor Coolant Pumps MECH NSSS/OPS 5.5.2 Replacement Steam Generators MECH NSSS/OPS/CHEM 5.5.3 Reactor Coolant Piping MECH NSSS/OPS 5.5.4 Steam Outlet Flow Restrictor (Steam Generator) MECH NSSS/OPS 5.5.5 Main Steam Line Isolation System MECH BOP/OPS 5.5.6 Reactor Vessel Head Vent System MECH NSSS/OPS 5.5.7 Residual Heat Removal System MECH NSSS/OPS 5.5.8 Reactor Coolant Cleanup System MECH NSSS/OPS/CHEM 5.5.10 Pressurizer MECH NSSS/OPS 5.5.11 Pressurizer Relief Tank MECH NSSS/OPS 5.5.12 Valves MECH NSSS/OPS 5.5.13 Safety and Relief Valves MECH NSSS/OPS 5.5.14 Component Supports MECH NSSS/OPS 5.6 INSTRUMENTATION APPLICATION ELEC MAINT/EIC 6.0 ENGINEERED SAFETY FEATURES 6.1 ENGINEERED SAFETY FEATURE MATERIALS 6.1.1 Metallic Material MATL 6.1.2 Organic Material MATL NSSS 6.1.3 Post-Accident Chemistry MECH CHEM 6.1.4 Degree of Compliance with RG 1.54 for MATL Paints & Coatings Inside Containment
PAGE 8 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 6.2 CONTAINMENT SYSTEMS 6.2.1 Containment Functional Design MECH NSSS 6.2.2 Containment Heat Removal Systems MECH NSSS/OPS 6.2.3 Secondary Containment Functional Design MECH NSSS 6.2.4 Containment Isolation Systems MECH NSSS 6.2.5 Combustible Gas Control in Containment MECH NSSS 6.2.5A Hydrogen Mitigation System MECH NSSS 6.2.6 Containment Leakage Testing PGM MECH 6.3 EMERGENCY CORE COOLING SYSTEM 6.3.1 Design Bases NSA MECH/NSSS/OPS 6.3.2 System Design NSA MECH/NSSS/OPS 6.3.3 Performance Evaluation NSA MECH/NSSS/OPS 6.3.4 Tests and Inspections MECH NSSS/OPS/EIC/NSA 6.3.5 Instrumentation Application EIC MECH/MAINT/NSA 6.4 HABITIBILITY SYSTEM 6.4.1 Design Bases NSA MECH/BOP 6.4.2 System Design NSA MECH/BOP 6.4.3 System Operational Procedures NSA MECH/OPS 6.4.4 Design Evaluations NSA MECH/BOP 6.4.5 Testing and Inspection MECH BOP/NSA 6.4.6 Instrumentation Requirements EIC MECH/MET/NSA 6.5 FISSION PRODUCT REMOVAL & CONTROL SYSTEMS NSA MECH/CHEM/OPS/NSSS 6.5.1 Engineered Safety Feature (ESF) Filter Systems NSA MECH/CHEM/OPS/NSSS 6.5.2 Containment Spray System for Fission Product Cleanup NSA MECH/CHEM/OPS/NSSS 6.5.3 Fission Product Control Systems NSA MECH/CHEM/OPS/NSSS 6.5.4 Ice Condenser as a Fission Product Cleanup System NSA MECH/CHEM/OPS/NSSS 6.6 INSERVICE INSPECTION OF ASME CODE PGM MATL CLASS 2 AND 3 COMPONENTS 6.7 ICE CONDENSER SYSTEM 6.7.1 Floor Structure and Cooling System MECH NSSS/NSA 6.7.2 Wall Panels MECH NSSS/NSA 6.7.3 Lattice Frames and Support Columns MECH NSSS/NSA 6.7.4 Ice Baskets MECH NSSS/NSA 6.7.5 Crane and Rail Assembly MECH NSSS/NSA 6.7.6 Refrigeration System MECH NSSS/NSA 6.7.7 Air Handling Units MECH NSSS/NSA 6.7.8 Lower Inlet Doors MECH NSSS/NSA 6.7.9 Lower Support Structure MECH NSSS/NSA 6.7.10 Top Deck and Doors MECH NSSS/NSA 6.7.11 Intermediate Deck and Doors MECH NSSS/NSA 6.7.12 Air Distribution Ducts MECH NSSS/NSA 6.7.13 Equipment Access Door CIVIL NSSS/NSA 6.7.14 Ice Technology, Ice Performance, & Ice Chemistry MEC NSSS/CHEM/NSA 6.7.15 Ice Condenser Instrumentation ELEC EIC/MAINT/NSA 6.7.16 Ice Condenser Structural Design CIVIL NSSS/NSA 6.7.17 Seismic Analysis NSA CIVIL/NSSS 6.7.18 Materials MATL NSSS/NSA 6.7.19 Tests and Inspections MECH NSSS
PAGE 8 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 6.8 AIR RETURN FANS 6.8.1 Design Bases NSA MECH/BOP 6.8.2 System Description NSA MECH/BOP 6.8.3 Safety Evaluation NSA MECH/BOP 6.8.4 Inspection and Testing NSA MECH/BOP 6.8.5 Instrumentation Requirements ELEC EIC/MET/BOP/NSA 6.9 MOTOR-OPERATED VALVE (MOV) PROGRAMS PROG MECH/NSA 7.0 INSTRUMENTATION AND CONTROLS
7.1 INTRODUCTION
ELEC MAINT/EIC 7.1.1 Identification of Safety-Related Systems ELEC MAINT/EIC 7.1.2 Identification of Safety Criteria ELEC MAINT/EIC 7.2 REACTOR TRIP SYSTEM ELEC MAINT/EIC/OPS 7.3 ENGINEERED SAFETY FEATURES ACTUATION ELEC EIC/MAINT/OPS SYSTEM (ESFAS) 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN ELEC EIC/MAINT/OPS 7.5 INSTRUMENTATION SYSTEMS IMPORTANT ELEC EIC/MAINT TO SAFETY 7.5.1 Post Accident Monitoring Instrumentation (PAM) ELEC EIC/MAINT 7.5.2 Plant Computer System ELEC EIC/MAINT 7.6 ALL OTHER SYSTEMS REQUIRED FOR SAFETY 7.6.1 120V AC and 125DC Vital Plant Control ELEC EIC/MAINT Power System 7.6.2 Residual Heat Removal Isolation Valves ELEC EIC/MAINT/OPS 7.6.3 Refueling Interlocks ELEC EIC/MAINT 7.6.5 Accumulator Motor-Operated Valves ELEC EIC/MAINT 7.6.6 Spurious Actuation Protection for MOVs ELEC EIC/MAINT 7.6.7 Loose Parts Monitoring System (LPMS) ELEC MAINT/EIC 7.6.8 Interlocks for RCS Pressure Control During Low ELEC EIC/MAINT Temperature Operation 7.6.9 Switchover from Injection to Recirculation Mode ELEC EIC/MAINT Following a LOCA 7.7 CONTROL SYSTEMS ELEC MAINT/EIC APP 7.A INSTRUMENTATION IDENTIFICATIONS AND SYMBOLS ELEC MAINT/EIC
PAGE 9 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 8.0 ELECTRIC POWER
8.1 INTRODUCTION
ELEC EIC/MAINT 8.2 OFFSITE (PREFERRED) POWER SYSTEM ELEC EIC/OPS/MAINT 8.3 ONSITE (STANDBY) POWER SYSTEM ELEC EIC/OPS/MAINT 8.3.1 A.C. Power System ELEC EIC/OPS/MAINT 8.3.2 D.C. Power System ELEC EIC/OPS/MAINT APP 8A DELETED by UFSAR Amendment 1 APP 8B DELETED by UFSAR Amendment 1 APP 8C DELETED by Initial UFSAR APP 8D IEEE STD 387-1984 FOR DIESEL-GENERATING ELEC EIC/MAINT UNITS APPLIED AS STANDBY POWER SUPPLIES FOR NUCLEAR POWER GENERATING STATIONS APP 8E PROBABILITY/RELIABILITY ANALYSIS OF ELEC PROTECTION DEVICE SCHEMES FOR ASSOCIATED AND NON-CLASS 1E CABLES 9.0 AUXILIARY SYSTEM 9.1 FUEL STORAGE AND HANDLING 9.1.1 New Fuel Storage MECH RXE/OPS/FUELS 9.1.2 Spent Fuel Storage MECH RXE/OPS/FUELS 9.1.3 Spent Fuel Pool Cooling and Cleanup System MECH RXE/PGM/FUELS (SFPCCS) OPS/CHEM 9.1.4 Fuel Handling System MECH RXE/BOP/
OPS/FUELS 9.1.5 Tritium Producting Burnable Absorber Rods (TPBARs) MECH RXE/BOP/
Consolidation Activity OPS/FUELS 9.2 WATER SYSTEMS 9.2.1 Essential Raw Cooling Water (ERCW) MECH CHEM/NSSS 9.2.2 Component Cooling System MECH CHEM/NSSS 9.2.3 Demineralized Water Makeup System MECH CHEM/BOP 9.2.4 Potable and Sanitary Water Systems MECH CHEM/BOP 9.2.5 Ultimate Heat Sink MECH BOP 9.2.6 Condensate Storage Facilities MECH BOP 9.2.7 Refueling Water Storage Tank NSA CHEM/NSSS 9.2.8 Raw Cooling Water System MECH CHEM/NSSS 9.3 PROCESS AUXILIARIES 9.3.1 Compressed Air System MECH BOP/CHEM 9.3.2 Process Sampling System MECH NSSS/CHEM 9.3.3 Equipment and Floor Drainage System MECH NSSS/CHEM 9.3.4 Chemical and Volume Control System MECH NSSS/CHEM 9.3.5 Failed Fuel Detection System MECH BOP/CHEM 9.3.6 Auxiliary Charging System MECH NSSS/CHEM 9.3.7 Boron Recycle System MECH BOP/CHEM 9.3.8 Heat Tracing MECH BOP/CHEM
PAGE 10 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 9.4 AIR CONDITIONING, HEATING, COOLING, AND VENTILATION SYSTEMS 9.4.1 Control Room Area Ventilation System MECH BOP 9.4.2 Fuel Handling Area Ventilation System MECH BOP 9.4.3 Auxiliary Building & Radwaste Area Ventilation MECH BOP 9.4.4 Turbine Building Area Ventilation MECH BOP 9.4.5 Engineered Safety Feature Ventilation MECH BOP 9.4.6 Reactor Building Purge Ventilating System MECH BOP 9.4.7 Containment Air Cooling System MECH BOP 9.4.8 Condensate Demineralizer Waste Evaporator MECH BOP Building Environmental Control System (Historical) 9.4.9 Post Accident Sampling Facility (PASF) MECH BOP/CHEM Environmental Control System 9.5 OTHER AUXILIARY SYSTEMS 9.5.1 Fire Protection System PGM FOPS (Fire Protection Report) PGM FOPS/BOP (Table 14.10.1 impact) OPS/FP/BOP 9.5.2 Plant Communications System ELEC EIC/NS 9.5.3 Lighting Systems ELEC EIC 9.5.4 Diesel Generator Fuel Oil Storage and Transfer System MECH BOP/EIC 9.5.5 Diesel Generator Cooling Water System MECH BOP/EIC 9.5.6 Diesel Generator Starting System MECH BOP/EIC 9.5.7 Diesel Engine Lubrication System MECH BOP/EIC 9.5.8 Diesel Generator Combustion Air MECH BOP/EIC Intake and Exhaust System 10.0 MAIN STEAM AND POWER CONVERSION SYSTEMS 10.1
SUMMARY
DESCRIPTION MECH 10.2 TURBINE GENERATOR 10.2.1 Design Bases MECH BOP/OPS 10.2.2 Description MECH BOP/OPS 10.2.3 Turbine Rotor and Disc Integrity HISTORICAL MECH BOP/OPS 10.2.4 Evaluation MECH BOP/OPS 10.3 MAIN STEAM SUPPLY SYSTEM 10.3.1 Design Bases NSA MECH/BOP 10.3.2 System Description NSA MECH/BOP 10.3.3 Design Evaluation NSA MECH/BOP 10.3.4 Inspection and Testing Requirements NSA MECH/BOP 10.3.5 Water Chemistry NSA MECH/BOP/CHEM 10.3.6 Steam Feedwater System Materials NSA MECH/BOP 10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION 10.4.1 Main Condenser MECH CHEM/BOP 10.4.2 Main Condenser Evacuation System MECH BOP 10.4.3 Turbine Gland Sealing System MECH BOP/OPS 10.4.4 Turbine Bypass System MECH BOP/OPS 10.4.5 Condenser Circulating Water System MECH CHEM/BOP 10.4.6 Condensate Polishing Demineralizer System MECH CHEM/BOP 10.4.7 Condensate and Feedwater Systems MECH CHEM/BOP 10.4.8 Steam Generator Blowdown System MECH CHEM/BOP 10.4.9 Auxiliary Feedwater System NSA MECH
PAGE 11 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 11.0 RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE TERMS 11.1.1 Historical Design Model for Radioactivities MECH CHEM in Systems and Components 11.1.2 Realistic Model for Radioactivities MECH CHEM in Systems and Components 11.1.3 Plant Leakage MECH CHEM 11.1.4 Additional Sources MECH CHEM 11.2 LIQUID WASTE SYSTEMS 11.2.1 Design Objectives MECH CHEM/PGM/OPS 11.2.2 System Descriptions MECH CHEM/PGM/OPS 11.2.3 System Design MECH CHEM/PGM/OPS 11.2.4 Operating Procedure MECH CHEM/PGM/OPS 11.2.5 Performance Tests MECH CHEM/PGM/OPS 11.2.6 Estimated Releases MECH CHEM/PGM/OPS 11.2.7 Release Points MECH CHEM/PGM/OPS 11.2.8 Dilution Factors CHEM RADPRO/OPS/
ENV/PGM 11.2.9 Estimated Doses from Radionuclides CHEM PGM/RADPRO in Liquid Effluents 11.3 GASEOUS WASTE SYSTEMS 11.3.1 Design Bases MECH CHEM/PGM/OPS 11.3.2 System Description MECH CHEM/PGM/OPS 11.3.3 System Design MECH CHEM/PGM/OPS 11.3.4 Operating Procedure MECH CHEM/PGM/OPS 11.3.5 Performance Tests MECH CHEM/PGM/OPS 11.3.7 Radioactive Releases MECH CHEM/PGM/OPS 11.3.8 Release Points MECH CHEM/PGM/OPS 11.3.9 Atmospheric Dilution CHEM MECH/PGM 11.3.10 Estimated Doses from Radionuclides CHEM RADPRO/
in Gaseous Effluents MECH/PGM 11.4 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEM 11.4.1 Design Objectives MECH CHEM/EIC 11.4.2 Continuous Monitors MECH CHEM/EIC 11.4.3 Sampling MECH CHEM/EIC 11.4.4 Calibration and Maintenance MECH CHEM/MAINT 11.5 SOLID WASTE MANAGEMENT SYSTEM 11.5.1 Design Objectives ENV MECH 11.5.2 System Inputs ENV MECH 11.5.3 System Description ENV MECH 11.5.4 Equipment Operation ENV MECH 11.5.5 Storage Facilities ENV MECH 11.5.6 Shipment ENV MECH 11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM 11.6.1 Expected Background RADPRO CHEM 11.6.2 Critical Pathways to Man RADPRO CHEM
PAGE 12 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 11.6.3 Sampling Media, Locations, and Frequency RADPRO CHEM 11.6.4 Analytical Sensitivity RADPRO CHEM 11.6.5 Data Analysis and Presentation RADPRO CHEM 11.6.6 Program Statistical Sensitivity RADPRO CHEM APP 11A TRITIUM CONTROL APP 11A.1 System Sources MECH CHEM/RXE RADPRO/OPS APP 11A.2 Tritium Releases MECH CHEM/RXE RADPRO/OPS APP 11A.3 Design Bases MECH CHEM/RXE RADPRO/OPS APP 11A.4 Design Evaluation MECH CHEM/RXE RADPRO/OPS APP 11A.5 Tritium Producing Burnable Absorber Rods (TPBARs) MECH RXE APP 11A.6 Tritium Production Core Impact on Station Operation MECH RXE 12.0 RADIATION PROTECTION 12.1 ASSURING THAT OCCUPATIONAL RADIATION MECH RADPRO EXPOSURES ARE AS LOW AS REASONABLY ACHIEVALBE (ALARA) 12.1.1 Policy Considerations MECH RADPRO 12.1.2 Design Considerations MECH RADPRO 12.1.3 ALARA Operational Considerations MECH RADPRO 12.2 RADIATION SOURCES 12.2.1 Contained Sources MECH RADPRO/CHEM 12.2.2 Airborne Radioactive Material Sources MECH RADPRO/CHEM 12.3 RADIATION PROTECTION DESIGN FEATURES 12.3.1 Facility Design Features MECH RADPRO 12.3.2 Shielding MECH RADPRO 12.3.3 Ventilation MECH RADPRO/BOP 12.3.4 Area Radiation and Airborne Radioactivity MECH RADPRO/
Monitoring Instrumentation EIC/CHEM 12.4 DOSE ASSESSMENT RADPRO CHEM 12.5 RADIOLOGICAL CONTROL (RADCON) PROGRAM RADCON APP 12A RADIATION PROTECTION FEATURES FOR THE RADCON TRITIUM PRODUCTION PROGRAM 13.0 CONDUCT OF OPERATIONS 13.1 ORGANIZATION STRUCTURE OF APPLICANT 13.1.1 Corporate Organization HR QA/LIC 13.1.2 Nuclear Power HR QA/LIC 13.1.3 Qualification Requirements for Nuclear Facility HR QA/TRG/OPS Personnel RADPRO/CHEM
PAGE 13 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 13.2 TRAINING PROGRAMS TRG OPS/MAINT 13.2.1 Accredited Training Programs TRG 13.2.2 General Employee and Fitness for Duty Training Programs TRG 13.2.3 Other Training Programs TRG 13.3 EMERGENCY PLANNING EP QA/RADPRO 13.4 REVIEW AND AUDIT QA LIC 13.5 SITE PROCEDURES MS OPS 13.6 PLANT RECORDS MS QA/OPS/
RADPRO 13.7 NUCLEAR SECURITY NS QA 14.0 INITIAL TEST PROGRAM- HISTORICAL 15.0 ACCIDENT ANALYSES 15.1 CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS 15.1.1 Optimization of Control Systems NSA MECH 15.1.2 Initial Power Conditions Assumed in Accident Analyses NSA MECH 15.1.3 Trip Points and Time Delays to Trip NSA OPS/MECH/EIC Assumed in Accident Analyses 15.1.4 Instrumentation Drift and Calorimetric ELEC OPS/NSA/EIC Errors - Power Range Neutron Flux 15.1.5 Rod Cluster Control Assembly Insertion Characteristic NSA OPS/MECH 15.1.6 Reactivity Coefficients NSA OPS/MECH 15.1.7 Fission Product Inventories NSA OPS/MECH 15.1.8 Residual Decay Heat NSA OPS/MECH 15.1.9 Computer Codes Utilized NSA OPS/MECH 15.2 CONDITION II - FAULTS OF MODERATE FREQUENCY 15.2.1 Uncontrolled Rod Cluster Control Assembly Bank NSA OPS/MECH Withdrawal from Subcritical Condition 15.2.2 Uncontrolled Rod Cluster Control Assembly Bank NSA OPS/MECH Withdrawal at Power 15.2.3 Rod Cluster Control Assembly Misalignment NSA OPS/MECH 15.2.4 Uncontrolled Boron Dilution NSA OPS/MECH 15.2.5 Partial Loss of Forced Reactor Coolant Flow NSA OPS/MECH 15.2.6 Startup of an Inactive Reactor Coolant Loop at an NSA OPS/MECH Incorrect Temperature 15.2.7 Loss of External Electrical Load and/or Turbine Trip NSA OPS/MECH 15.2.8 Loss of Normal Feedwater NSA OPS/MECH 15.2.9 Coincident Loss of Onsite and External (Offsite) NSA OPS/MECH AC Power to the Station - Loss of Offsite Power to the Station Auxiliaries
PAGE 14 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 15.2.10 Excessive Heat Removal Due to NSA OPS/MECH Feedwater System Malfunctions 15.2.11 Excessive Load Increase Incident NSA OPS/MECH 15.2.12 Accidental Depressurization of the NSA OPS/MECH Reactor Coolant System 15.2.13 Accidental Depressurization of the NSA OPS/MECH Main Steam System 15.2.14 Inadvertent Operation of Emergency NSA OPS/MECH Core Cooling System 15.3 CONDITION III - INFREQUENT FAULTS 15.3.1 Loss of Reactor Coolant from Small NSA OPS/MECH Ruptured Pipes or from Cracks in Large Pipes Which Actuate the Emergency Core Cooling System 15.3.2 Minor Secondary System Pipe Breaks NSA OPS/MECH 15.3.3 Inadvertent Loading of a Fuel Assembly into an NSA OPS/MECH Improper Position 15.3.4 Complete Loss of Forced Reactor Coolant Flow NSA OPS/MECH 15.3.5 Waste Gas Decay Tank Rupture NSA OPS/MECH 15.3.6 Single Rod Cluster Control Assembly Withdrawal NSA OPS/MECH at Full Power 15.4 CONDITION IV - LIMITING FAULTS 15.4.1 Major RCS Pipe Ruptures (LOCA) 15.4.2 Major Secondary System Pipe Rupture NSA OPS/MECH 15.4.3 Steam Generator Tube Rupture NSA OPS/MECH 15.4.4 Single Reactor Coolant Pump Locked Rotor NSA OPS/MECH 15.4.5 Fuel Handling Accident NSA OPS/MECH 15.4.6 Rupture of a Control Rod Drive Mechanism NSA OPS/MECH Housing (RCCA Ejection) 15.5 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS 15.5.1 Environmental Consequences of a Postulated NSA CHEM/EIC/
Loss of AC Power to the Plant Auxiliaries RADPRO/MECH 15.5.2 Environmental Consequences of a Postulated NSA CHEM/MECH/
Waste Gas Decay Tank Rupture RADPRO 15.5.3 Environmental Consequences of a NSA CHEM/NSSS/
Postulated Loss of Coolant Accident RADPRO 15.5.4 Environmental Consequences of a Postulated NSA CHEM/MECH/
Steam Line Break RADPRO 15.5.5 Environmental Consequences of a Postulated NSA CHEM/MECH/
Steam Generator Tube Rupture RADPRO 15.5.6 Environmental Consequences of a Postulated NSA CHEM/NSSS/
Fuel Handling Accident RADPRO 15.5.7 Environmental Consequences of a Postulated NSA CHEM/NSSS Rod Ejection Accident 15.5.8 Tritium Production - Accident Releases NSA MECH 15A DOSE MODELS USED TO EVALUATE THE NSA MECH ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS
PAGE 15 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR)
SAR CHAPTER TITLE LEAD SUPPORT 15B OPERATION WITH A TRITIUM PRODUCTION CORE NSA RXE 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.2 FINAL TECHNICAL SPECIFICATIONS LIC 16.3 RELOCATED SPECIFICATIONS 16.3.1 Discussion LIC 16.3.2 Document Control LIC 16.3.3 Changes to the Relocated Specifications LIC 17.0 QUALITY ASSURANCE 17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION 17.1.1 TVA Organization QA TPS 17.1.2 Quality Assurance Program QA APP 17.1A WESTINGHOUSE NUCLEAR ENERGY SYSTEM QA NSSS DIVISIONS QUALITY ASSURANCE PLAN 17.2 QUALITY ASSURANCE FOR STATION OPERATION 17.2.1 Identification of Safety Related Features QA MECH/MAINT/OPS