ML092460770
| ML092460770 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/27/2009 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML092460770 (19) | |
Text
Table of Contents 1-xxxvii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 003_TVA_WB_FSAR_Section_1.pdf 004_TVA_WB_FSAR_Section_2_A.pdf 005_TVA_WB_FSAR_Section_2_B.pdf 005_TVA_WB_FSAR_Section_2_B.pdf 005_TVA_WB_FSAR_Section_2_B.pdf 013_TVA_WB_FSAR_Section_4.pdf 014_TVA_WB_FSAR_Section_5.pdf 017_TVA_WB_FSAR_Section_7.pdf 018_TVA_WB_FSAR_Section_8 024_TVA_WB_FSAR_Section_13.pdf 026_TVA_WB_FSAR_Section_15.pdf 027_TVA_WB_FSAR_Section_16.pdf 028_TVA_WB_FSAR_Section_17.0.pdf
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
1.1-1 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 1.2-13 1.3 COMPARISON TABLES 1.3-1 1.3.1 Comparisons With Similar Facility Designs 1.3-1 1.3.2 Comparison Of Final And Preliminary Designs 1.3-1 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 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 1.9-1 1.9.1 Corrective Action Plans 1.9-1 1.9.2 Special Programs (SPs) 1.9-5 1.
9.3 REFERENCES
1.9-7 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 2.1-2 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 Evaluation of Potential Accidents 2.2-2 2.3 METEOROLOGY 2.3-1 2.3.1 Regional Climate 2.3-1 2.3.2 Local Meteorology 2.3-5
1-xxxviii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 2.3-16 2.4 HYDROLOGIC ENGINEERING 2.4-1 2.4.1 Hydrological Description 2.4-1 2.4.2 Floods 2.4-6 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers 2.4-12 2.4.4 Potential Dam Failures, Seismically Induced 2.4-28 2.4.5 Probable Maximum Surge and Seiche Flooding 2.4-40 2.4.6 Probable Maximum Tsunami Flooding 2.4-40 2.4.7 Ice Effects 2.4-40 2.4.8 Cooling Water Canals and Reservoirs 2.4-41 2.4.9 Channel Diversions 2.4-42 2.4.10 Flooding Protection Requirements 2.4-42 2.4.11 Low Water Considerations 2.4-42 2.4.12 Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents 2.4-45 2.4.13 Groundwater 2.4-48 2.4.14 Flooding Protection Requirements 2.4-51 2.5 GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING
SUMMARY
OF FOUNDATION CONDITIONS 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 2.5-45 2.5.4 Stability of Subsurface Materials 2.5-56 2.5.5 Stability of Slopes 2.5-118 2.5.6 Embankments 2.5-127 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 3.2-1 3.2.3 Code Cases and Code Editions and Addenda 3.2-3 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
Table of Contents 1-xxxix WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 3.5-28 3.5.3 Barrier Design Procedures 3.5-29 3.5.A ESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES 3.5-1 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING 3.6-1 3.6A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIPING) 3.6A-1 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 Postu-lated Rupture of Piping 3.6A-10 3.6B PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING 3.6A-24 3.6B.1 Break Locations And Dynamic Effects Associated With Postulated Primary Loop Pipe Rupture 3.6A-24 3.6B.2 Analytical Methods to Define Forcing Function and Response Models 3.6A-25 3.6B.3 Dynamic Analysis of the Reactor Coolant Loop Piping Equipment Supports and Pipe Whip Restraints 3.6A-27 3.7 SEISMIC DESIGN 3.7-1 3.7.1 Seismic Input 3.7-2 3.7.2 Seismic System Analysis 3.7-3 3.7.3 Seismic Subsystem Analysis 3.7-31 3.7.4 Seismic Instrumentation Program 3.7-61 3.8 DESIGN OF CATEGORY I STRUCTURES 3.8-1 3.8.1 Concrete Shield Building 3.8-1 3.8.2 Testing and Inservice Surveillance Requirements 3.8-13 3.8.2 Steel Containment System 3.8-1 3.8.2.1 Description of the Containment and Penetrations 3.8-1 3.8.2.2 Applicable Codes, Standards and Specifications 3.8-3 3.8.2.3 Loads and Loading Combinations 3.8-7 3.8.2.4 Design and Analysis Procedures 3.8-11 3.8.2.5 Structural Acceptance Criteria 3.8-18 3.8.2.6 Materials, Quality Control, and Special Construction Techniques 3.8-18
1-xl Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.2.7 Testing and Inservice Inspection Requirements 3.8-25 3.8.3 Concrete Interior Structure 3.8-1 3.8.3.1 Description of the Interior Structure 3.8-1 3.8.3.13 Applicable Codes, Standards and Specifications 3.8-7 3.8.3.14 Loads and Loading Combinations 3.8-13 3.8.3.15 Design and Analysis Procedures 3.8-16 3.8.3.29 Structural Acceptance Criteria 3.8-31 3.8.3.42 Materials, Quality Control and Special Construction Techniques 3.8-34 3.8.3.47 Testing and Inservice Surveillance Requirements 3.8-38 3.8.3.48 Environmental Effects 3.8-38 3.8.3.49 Interface Control 3.8-39 3.8.4 Other Category I Structures 3.8-1 3.8.4.1 Description of the Structures 3.8-1 3.8.4.10 Applicable Codes, Standards, and Specifications 3.8-17 3.8.4.13 Loads and Loading Combinations 3.8-21 3.8.4.16 Design and Analysis Procedures 3.8-23 3.8.4.25 Structural Acceptance Criteria 3.8-35 3.8.4.32 Materials, Quality Control, and Special Construction Techniques General 3.8-37 3.8.4.36 Testing and Inservice Surveillance Requirements 3.8-38 3.8.5 Foundations and Concrete Supports 3.8-1 3.8.5.1 Description of Foundations and Supports 3.8-1 3.8.5.2 Applicable Codes, Standards, and Specifications 3.8-3 3.8.5.3 Loads and Loading Combinations 3.8-3 3.8.5.4 Design and Analysis Procedure 3.8-4 3.8.5.5 Structural Acceptance Criteria 3.8-5 3.8.5.6 Materials, Quality Control, and Special Construction Techniques 3.8-6 3.8.6 Category I(L) Cranes 3.8-1 3.8.6.1 Polar Cranes 3.8-1 3.8.6.2 Auxiliary Building Crane 3.8-4 3.8A SHELL TEMPERATURE TRANSIENTS 3.8-1 3.8B BUCKLING STRESS CRITERIA 3.8-1 3.8B.1 INTRODUCTION 3.8-1 3.8B.2 SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS 3.8-1 3.8B.3 SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND VERTICAL STIFFENERS 3.8-5 3.8B.4 SPHERICAL SHELLS 3.8-7 3.8B.3 FACTOR OF SAFETY 3.8-8 3.8C DOCUMENTATION OF CB&I COMPUTER PROGRAMS 3.8-1
Table of Contents 1-xli WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8C.1 INTRODUCTION 3.8-1 3.8C.2 PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN VALUE TECHNIQUE 3.8-1 3.8C.3 PROGRAM 1044-SEISMIC ANALYSIS of VESSEL APPENDAGES 3.8-1 3.8C.4 PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS DIGITIZED AT EQUAL INTERVALS 3.8-3 3.8C.5 PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS 3.8-3 3.8C.6 PROGRAM E1623-POST PROCESSOR PROGRAM FOR PROGRAM E1374 3.8-4 3.8C.7 PROGRAM E1374-SHELL DYNAMIC ANALYSIS 3.8-5 3.8C.8 PROGRAM E1622-LOAD GENERATION PREPROCESSOR FOR PROGRAM E1374 3.8-6 3.8C.9 PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION 3.8-7 3.8C.10 PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS 3.8-7 3.8C.11 PROGRAM 119-CHECK of FLANGE DESIGN 3.8-7 3.8C.12 PROGRAM 772-NOZZLE REINFORCEMENT CHECK 3.8-7 3.8C.13 PROGRAM 1027-WRC 107 STRESS INTENSITIES AT LOADED ATTACH-MENTS FOR SPHERES OR CYLINDERS WITH ROUND OR SQUARE ATTACHMENT3.8-8 3.8C.14 PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES 3.8-8 3.8D COMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS 3.8-1 3.8E CODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFICATION AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF NEW FEA-TURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIAT-ED AFTER JULY 1979 3.8-1 3.8E.1 Application Codes and Standards 3.8-1 3.8E.2 Load Definitions 3.8-1 3.8E.3 Load Combinations - Concrete 3.8-3 3.8E.4 Load Combinations - Structural Steel 3.8-5 3.9 MECHANICAL SYSTEMS AND COMPONENTS 3.9-1 3.9.1 General Topic 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 3.9-20 3.9.4 Control Rod System 3.9-46 3.9.5 Reactor Pressure Vessel Internals 3.9-47 3.9.6 Inservice Testing of Pumps and Valves 3.9-47 3.10 SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIP-MENT 3.10-1 3.10.1 Seismic Qualification Criteria 3.10-1
1-xlii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.10.2 Methods And Procedures For Qualifying Electrical Equipment And Instrumentation 3.10-4 3.10.3 Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumen-tation and Cables 3.10-4 3.10.4 Operating License Review 3.10-7 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, Ventilating, and Air-Conditioning (HVAC) 3.11-4 3.11.7 Estimated Chemical and Radiation Environment 3.11-4 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 4.2-22 4.2.3 Reactivity Control System 4.2-29 4.3 NUCLEAR DESIGN 4.3-1 4.3.1 DESIGN BASES 4.3-1 4.3.2 Description 4.3-6 4.3.3 Analytical Methods 4.3-33 4.4 THERMAL AND HYDRAULIC DESIGN 4.4-1 4.4.1 Design Bases 4.4-1 4.4.2 Description 4.4-3 4.4.3 EVALUATION 4.4-21 4.4.4 Testing and Verification 4.4-31 4.4.5 Instrumentation Application 4.4-32 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
Table of Contents 1-xliii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.2.1 Design of Reactor Coolant Pressure Boundary Components 5.2-2 5.2.2 Overpressurization Protection 5.2-35 5.2.3 General Material Considerations 5.2-40 5.2.4 Fracture Toughness 5.2-43 5.2.5 Austenitic Stainless Steel 5.2-46 5.2.6 Pump Flywheels 5.2-53 5.2.7 RCPB Leakage Detection Systems 5.2-55 5.2.8 Inservice Inspection of ASME Code Class 1 Components 5.2-65 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 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 5.4-12 5.5 COMPONENT AND SUBSYSTEM DESIGN 5.5-1 5.5.1 Reactor Coolant Pumps 5.5-1 5.5.2 Steam Generators 5.5-7 5.5.3 Reactor Coolant Piping 5.5-15 5.5.4 Steam Outlet Flow Restrictor (Steam Generator) 5.5-20 5.5.5 Main Steam Line Isolation System 5.5-20 5.5.6 Reactor Vessel Head Vent System 5.5-21 5.5.7 Residual Heat Removal System 5.5-23 5.5.8 Reactor Coolant Cleanup System 5.5-31 5.5.9 Main Steam Line and Feedwater Piping 5.5-31 5.5.10 Pressurizer 5.5-32 5.5.11 Pressurizer Relief Tank 5.5-37 5.5.12 Valves 5.5-38 5.5.13 Safety and Relief Valves 5.5-40 5.5.14 Component Supports 5.5-41 5.6 INSTRUMENTATION APPLICATION 5.6-1 6.0 ENGINEERED SAFETY FEATURES 6.1 ENGINEERED SAFETY FEATURE MATERIALS 6.1-1
1-xliv Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.1.1 Metallic Materials 6.1-1 6.1.2 Organic Materials 6.1-3 6.1.3 Post-Accident Chemistry 6.1-4 6.1.4 Degree of Compliance with Regulatory Guide 1.54 for Paints and Coatings Inside Containment 6.1-5 6.2 CONTAINMENT SYSTEMS 6.2-1 6.2.1 Containment Functional Design 6.2-1 6.2.2 CONTAINMENT HEAT REMOVAL SYSTEMS 6.2-1 6.2.3 Secondary Containment Functional Design 6.2-1 6.2.3.1 Design Bases 6.2-1 6.2.3.2
System Design
6.2-2 6.2.3.3 Design Evaluation 6.2-12 6.2.3.4 Test and Inspections 6.2-21 6.2.3.5 Instrumentation Requirements 6.2-23 6.2.4 Containment Isolation Systems 6.2-1 6.2.4.1 Design Bases 6.2-1 6.2.4.2
System Design
6.2-4 6.2.4.3 Design Evaluation 6.2-12 6.2.4.4 Tests and Inspections 6.2-16 6.2.5 Combustible Gas Control in Containment 6.2-1 6.2.5.1 Design Bases 6.2-1 6.2.5.2
System Design
6.2-2 6.2.5.3 Design Evaluation 6.2-5 6.2.5.4 Testing and Inspections 6.2-5 6.2.5.5 Instrumentation Application 6.2-5 6.2.5.6 Materials 6.2-6 6.2.5.7 Hydrogen Mitigation System 6.2-6 6.2.6 Containment Leakage Testing 6.2-1 6.2.6.1 Containment Integrated Leak Rate Test 6.2-1 6.2.6.2 Containment Penetration Leakage Rate Test 6.2-2 6.2.6.3 Scheduling and Reporting of Periodic Tests 6.2-6 6.2.6.4 Special Testing Requirements 6.2-6 6.3 EMERGENCY CORE COOLING SYSTEM 6.3-1 6.3.1 Design Bases 6.3-1 6.3.2
System Design
6.3-2 6.3.3 Performance Evaluation 6.3-25 6.3.4 Tests and Inspections 6.3-31 6.3.5 Instrumentation Application 6.3-33
Table of Contents 1-xlv WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 6.5-8 6.5.4 Ice Condenser as a Fission Product Cleanup System 6.5-10 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 6.6-1 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 6.7-8 6.7.3 Lattice Frames and Support Columns 6.7-9 6.7.4 Ice Baskets 6.7-14 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 6.7-37 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 6.7-57 6.7.13 Equipment Access Door 6.7-58 6.7.14 Ice Technology, Ice Performance, and Ice Chemistry 6.7-59 6.7.15 Ice Condenser Instrumentation 6.7-65 6.7.16 Ice Condenser Structural Design 6.7-68 6.7.17 Seismic Analysis 6.7-70 6.7.18 Materials 6.7-74 6.7.19 Tests and Inspections 6.7-78
1-xlvi Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 6.8-3 6.8.5 Instrumentation Requirements 6.8-3 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 7.1-5 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 7.2-36 7.3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM 7.3-1 7.3.1 Description 7.3-1 7.3.2 Analysis 7.3-8 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.4-1 7.4.1 Description 7.4-1 7.4.2 Analysis 7.4-6 7.5 INSTRUMENTATION SYSTEMS IMPORTANT TO SAFETY 7.5-1 7.5.1 Post Accident Monitoring Instrumentation (PAM) 7.5-1 7.5.2 Emergency Response Facilities Data System (ERFDS) 7.5-8 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 by Amendment 63.
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 Part Monitoring System (LPMS) System Description 7.6-4 7.6.8 Interlocks for RCS Pressure Control During Low Temperature Operation 7.6-6 7.6.9 Switchover From Injection to Recirculation 7.6-8 7.7 CONTROL SYSTEMS 7.7-1 7.7.1 Description 7.7-1 7.7.2 Analysis 7.7-20 7.7.3 Deleted by Amendment 81 7.7-26
Table of Contents 1-xlvii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7A INSTRUMENTATION IDENTIFICATIONS AND SYMBOLS 7A.1 IDENTIFICATION SYSTEM 7A.1-1 7A.1.1 FUNCTIONAL IDENTIFICATION 7A.1-1 7A.1.2 SYSTEM IDENTIFICATION 7A.1-3 7A.1.3 LOOP IDENTIFICATION 7A.1-3 7A.2 SYMBOLS 7A.1-3 7A.2.1 INSTRUMENT SYMBOL 7A.1-4 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 8.1-2 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 8.2-19 8.3 ONSITE (STANDBY) POWER SYSTEM 8.3-1 8.3.1 AC Power System 8.3-1 8.3.2 DC Power System 8.3-55 8.3.3 Fire Protection for Cable Systems 8.3-70 8A Analysis of Submerged Electrical Equipment (During Post LOCA) Powered from Auxiliary Power System 8-1 8B Analysis of Submerged Electrical Equipment (During Post LOCA) Powered from In-strumentation and Control Power System 8-3 8C Deleted by Amendment 75 8-5 8D IEEE STD 387-1984 FOR DIESEL-GENERATING UNITS APPLIED AS STANDBY POWER 8-6 8E Probability/Reliability Analysis of Protection Device Schemes for Associated and Non-Class 1E Cables 8-8 9.0 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 9.1-1
1-xlviii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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) 9.1-4 9.1.4 FUEL HANDLING SYSTEM 9.1-12 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) 9.2-10 9.2.3 Demineralized Water Makeup System 9.2-23 9.2.4 Potable and Sanitary Water Systems 9.2-25 9.2.5 Ultimate Heat Sink 9.2-30 9.2.6 Condensate Storage Facilities 9.2-33 9.2.7 Refueling Water Storage Tank 9.2-35 9.2.8 Raw Cooling Water System 9.2-39 9.3 PROCESS AUXILIARIES 9.3-1 9.3.1 Compressed Air System 9.3-1 9.3.2 Process Sampling System 9.3-5 9.3.3 Equipment and Floor Drainage System 9.3-12 9.3.4 Chemical and Volume Control System 9.3-16 9.3.5 Failed Fuel Detection System 9.3-39 9.3.6 Auxiliary Charging System 9.3-40 9.3.7 Boron Recycle System 9.3-42 9.3.8 Heat Tracing 9.3-51 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 9.4-8 9.4.3 Auxiliary and Radwaste Area Ventilation System 9.4-12 9.4.4 Turbine Building Area Ventilation System 9.4-23 9.4.5 Engineered Safety Feature Ventilation Systems 9.4-27 9.4.6 Reactor Building Purge Ventilating System 9.4-40 9.4.7 Containment Air Cooling System 9.4-45 9.4.8 Condensate Demineralizer Waste Evaporator Building Environmental Control Sys-tem 9.4-49 9.4.9 Postaccident Sampling Facility Environmental Control System 9.4-49 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 9.5-7 9.5.4 Diesel Generator Fuel Oil Storage and Transfer System 9.5-10 9.5.5 Diesel Generator Cooling Water System 9.5-15 9.5.6 Diesel Generator Starting System 9.5-16 9.5.7 Diesel Engine Lubrication System 9.5-18
Table of Contents 1-xlix WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.5.8 Diesel Generator Combustion Air Intake and Exhaust System 9.5-21 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 10.2-5 10.2.4 Evaluation 10.2-13 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 10.3-3 10.3.5 Water Chemistry 10.3-3 10.3.6 Steam and Feedwater System Materials 10.3-5 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 10.4-28 10.4.9 Auxiliary Feedwater System 10.4-32 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 11.1-2 11.1.3 Plant Leakage 11.1-3 11.1.4 Additional Sources 11.1-3 11.2 LIQUID WASTE SYSTEMS 11.2-1 11.2.1 DESIGN OBJECTIVES 11.2-1 11.2.2 SYSTEMS DESCRIPTIONS 11.2-1 11.2.3 SYSTEM DESIGN 11.2-5 11.2.4 Operating Procedure 11.2-11 11.2.5 PERFORMANCE TESTS 11.2-18
1-l Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 11.2.6 ESTIMATED RELEASES 11.2-18 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 11.2-21 11.3 GASEOUS WASTE SYSTEMS 11.3-1 11.3.1 Design Bases 11.3-1 11.3.2 SYSTEM DESCRIPTIONS 11.3-1 11.3.3 SYSTEM DESIGN 11.3-3 11.3.4 Operating Procedure 11.3-4 11.3.5 Performance Tests 11.3-6 11.3.6 Deleted by Amendment 77 11.3-6 11.3.7 Radioactive Releases 11.3-6 11.3.8 Release Points 11.3-7 11.3.9 Atmospheric Dilution 11.3-8 11.3.10 Estimated Doses from Radionuclides in Gaseous Effluents 11.3-9 11.4 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYS-TEM 11.4-1 11.4.1 Design Objectives 11.4-1 11.4.2 Continuous Monitors 11.4-2 11.4.3 SAMPLING 11.4-9 11.4.4 CALIBRATION AND MAINTENANCE 11.4-9 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 Systems 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 11.6-2 11.6.3 Sampling Media, Locations, and Frequency 11.6-4 11.6.4 Analytical Sensitivity 11.6-4 11.6.5 Data Analysis and Presentation 11.6-4 11.6.6 Program Statistical Sensitivity 11.6-4 11A TRITIUM CONTROL 11A.1 SYSTEM SOURCES 11A.1-1 11A.1.1 The Fission Source 11A.1-1
Table of Contents 1-li WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 11A.1.2 Control Rod Source 11A.1-1 11A.1.3 Boric Acid Source 11A.1-1 11A.1.4 Burnable Shim Rod Source 11A.1-2 11A.2 Tritium Releases 11A.1-2 11A.3 Design Bases 11A.1-2 11A.4 Design Evaluation 11A.1-2 11A.5 Tritium Lead Test Assembly (This section to be provided at a later date) 11A.1-3 11A.6 Tritium Producing Burnable Absorber Rod (TPBAR) Source (Unit 1 Only) 11A.1-3 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 12.1-1 12.2 RADIATION SOURCES 12.2-3 12.2.1 Contained Sources 12.2-3 12.2.2 Airborne Radioactive Material Sources 12.2-11 12.3 RADIATION PROTECTION DESIGN FEATURES 12.3-1 12.3.1 Facility Design Features 12.3-1 12.3.2 Shielding 12.3-3 12.3.3 Ventilation 12.3-15 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation 12.3-17 12.4 DOSE ASSESSMENT 12.4-1 12.5 RADIOLOGICAL CONTROL (RADCON) 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 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 13.1-1 13.1.3 Qualification Requirements for Nuclear Facility Personnel 13.1-2
1-lii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 Programs 13.2-1 13.2.3 Other Training Programs 13.2-2 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 PROCEDURES 13.5-1 13.5.1 SYSTEM OF SITE PROCEDURES 13.5-1 13.5.2 Operating and Maintenance Procedures 13.5-2 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 13.6-1 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 REPORT 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 14.2-9 14.2.4 Conduct of Test Program 14.2-12 14.2.5 Review, Evaluation, and Approval of Test Results 14.2-14 14.2.6 Test Records 14.2-14 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 Pro-gram 14.2-29 14.2.9 Trial Use of Plant Operating and Emergency Procedures 14.2-30 14.2.10 Initial Fuel Loading, Postloading Tests, Initial Criticality, Low Power Tests and Pow-er Ascension 14.2-30 14.2.11 Test Program Schedule 14.2-34 14.2.12 Individual Test Descriptions 14.2-35
Table of Contents 1-liii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 15.0 ACCIDENT ANALYSES 15.1 CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS 15.1-1 15.1.1 Optimization of Control Systems 15.1-2 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 15.1-4 15.1.4 Instrumentation Drift And Calorimetric Errors - Power Range Neutron Flux 15.1-5 15.1.5 Rod Cluster Control Assembly Insertion Characteristic 15.1-5 15.1.6 Reactivity Coefficients 15.1-6 15.1.7 Fission Product Inventories 15.1-7 15.1.8 Residual Decay Heat 15.1-9 15.1.9 Computer Codes Utilized 15.1-11 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 WITH-DRAWAL AT POWER 15.2-5 15.2.3 ROD CLUSTER CONTROL ASSEMBLY MISALIGNMENT 15.2-9 15.2.4 UNCONTROLLED BORON DILUTION 15.2-13 15.2.5 PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW 15.2-17 15.2.6 Startup of an Inactive Reactor Coolant Loop 15.2-19 15.2.7 LOSS OF EXTERNAL ELECTRICAL LOAD AND/OR TURBINE TRIP 15.2-21 15.2.8 LOSS OF NORMAL FEEDWATER 15.2-24 15.2.9 COINCIDENT LOSS OF ONSITE AND EXTERNAL (OFFSITE) AC POWER TO THE STATION - LOSS OF OFFSITE POWER TO THE STATION AUXILIARIES 15.2-28 15.2.10 EXCESSIVE HEAT REMOVAL DUE TO FEEDWATER SYSTEM MALFUNC-TIONS 15.2-28 15.2.11 Excessive Load Increase Incident 15.2-31 15.2.12 ACCIDENTAL DEPRESSURIZATION OF THE REACTOR COOLANT SYS-TEM 15.2-33 15.2.13 ACCIDENTAL DEPRESSURIZATION OF THE MAIN STEAM SYSTEM 15.2-34 15.2.14 Inadvertent Operation of Emergency Core Cooling System 15.2-38 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 15.3-5 15.3.3 Inadvertent Loading of a Fuel Assembly Into an Improper Position 15.3-5 15.3.4 Complete Loss of Forced Reactor Coolant Flow 15.3-7 15.3.5 Waste Gas Decay Tank Rupture 15.3-9 15.3.6 Single Rod Cluster Control Assembly Withdrawal at Full Power 15.3-10
1-liv Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 15.4-12 15.4.3 Steam Generator Tube Rupture 15.4-23 15.4.4 Single Reactor Coolant Pump Locked Rotor 15.4-32 15.4.5 Fuel Handling Accident 15.4-35 15.4.6 Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection) 15.4-35 15.5 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS 15.5-1 15.5.1 Environmental Consequences of a Postulated Loss of AC Power to the Plant Auxil-iaries 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 15.5-2 15.5.4 Environmental Consequences of a Postulated Steam Line Break 15.5-19 15.5.5 Environmental Consequences of a Postulated Steam Generator Tube Rupture 15.5-20 15.5.6 Environmental Consequences of a Postulated Fuel Handling Accident 15.5-21 15.5.7 Environmental Consequences of a Postulated Rod Ejection Accident 15.5-23 15A DOSE MODELS USED TO EVALUATE THE ENVIRONMENTAL CONSEQUENC-ES OF ACCIDENTS 15A.1 INTRODUCTION 15A-1 15A.2 ASSUMPTIONS 15A-1 15A.3 GAMMA DOSE AND BETA DOSE 15A-1 15A.4 THYROID INHALATION DOSE 15A-2 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.1-1 16.2 PROPOSED FINAL TECHNICAL SPECIFICATIONS 16.2-1 16.3 RELOCATED SPECIFICATIONS 16.1-1 16.3.1 Discussion 16.1-1 16.3.2 Document Control 16.1-1 16.3.3 Changes to the Relocated Specifications 16.1-1 17.0 QUALITY ASSURANCE 17-1 17.1 Quality Assurance During Design and Construction 17-1
Table of Contents 1-lv WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 17.2 QUALITY ASSURANCE FOR STATION OPERATION 17.2-1 17.2.1 Identification of Safety-Related Features 17.2-1