ML091400518

Final Safety Analysis Report (Fsar), Amendment 93, Table of Contents

ML091400518
Person / Time
Site:	Watts Bar
Issue date:	04/30/2009
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
References
Download: ML091400518 (50)

Text

Table of Contents 1-i WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 003_TVA_WB_FSAR_Section_1.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 1.2.1.1 Location 1.2-1 1.2.1.2 Demography 1.2-1 1.2.1.3 Meteorology 1.2-1 1.2.1.4 Hydrology 1.2-1 1.2.1.5 Geology 1.2-1 1.2.1.6 Seismology 1.2-2 1.2.2 Facility Description 1.2-2 1.2.2.1 Design Criteria 1.2-2 1.2.2.2 Nuclear Steam Supply System (NSSS) 1.2-2 1.2.2.3 Control and Instrumentation 1.2-4 1.2.2.4 Fuel Handling System 1.2-5 1.2.2.5 Waste Processing System 1.2-5 1.2.2.6 Steam and Power Conversion System 1.2-5 1.2.2.7 Plant Electrical System 1.2-6 1.2.2.8 Cooling Water 1.2-7 1.2.2.9 Component Cooling System 1.2-7 1.2.2.10 Chemical and Volume Control System 1.2-7 1.2.2.11 Sampling and Water Quality System 1.2-8 1.2.2.12 Ventilation 1.2-9 1.2.2.13 Fire Protection System 1.2-9 1.2.2.14 Compressed Air Systems 1.2-9 1.2.2.15 Engineered Safety Features 1.2-9 1.2.2.16 Shared Facilities and Equipment 1.2-10 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 1.5.1.1 Rod Cluster Control Spider Tests 1.5-1 1.5.1.2 Grid Tests 1.5-1 1.5.1.3 Fuel Assembly Structural Tests 1.5-1 1.5.1.4 Guide Tube Tests 1.5-2

1-ii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 1.5.1.5 Prototype Assembly Tests 1.5-2 1.5.2 Heat Transfer Tests (17 x 17) 1.5-2 1.5.2.1 17 x 17 LOCA Heat Transfer Tests 1.5-2 1.5.2.2 Departure from Nucleate Boiling (DNB) 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 1.9.1.1 Cable Issues 1.9-1 1.9.1.2 Cable Tray and Cable Tray Supports 1.9-1 1.9.1.3 Design Baseline and Verification Program (DBVP) 1.9-2 1.9.1.4 Electrical Conduit and Conduit Support 1.9-2 1.9.1.5 Electrical Issues 1.9-2 1.9.1.6 Equipment Seismic Qualification 1.9-2 1.9.1.7 Fire Protection 1.9-3 1.9.1.8 Hanger and Analysis Update Program (HAAUP) 1.9-3 1.9.1.9 Heat Code Traceability 1.9-3 1.9.1.10 Heating, Ventilation, and Air Conditioning (HVAC) Duct Supports 1.9-3 1.9.1.11 Instrument Lines 1.9-3 1.9.1.12 Prestart Test Program 1.9-3 1.9.1.13 QA Records 1.9-4 1.9.1.14 Q-LIST 1.9-4 1.9.1.15 Replacement Items Program (RIP-CAP) 1.9-4 1.9.1.16 Seismic Analysis 1.9-4 1.9.1.17 Vendor Information 1.9-4 1.9.1.18 Welding 1.9-5 1.9.2 Special Programs (SPs) 1.9-5 1.9.2.1 Concrete Quality Program 1.9-5 1.9.2.2 Containment Cooling 1.9-5 1.9.2.3 Detailed Control room Design Review 1.9-5 1.9.2.4 Environmental Qualification Program 1.9-6 1.9.2.5 Master Fuse List 1.9-6 1.9.2.6 Mechanical Equipment Qualification 1.9-6 1.9.2.7 Microbiologically Induced Corrosion (MIC) 1.9-6 1.9.2.8 Moderate Energy Line Break Flooding (MELB) 1.9-6 1.9.2.9 Radiation Monitoring System 1.9-6 1.9.2.10 Soil Liquefaction 1.9-7 1.9.2.11 Use-As-Is CAQs 1.9-7 1.

9.3 REFERENCES

1.9-7 004_TVA_WB_FSAR_Section_2_A.pdf 005_TVA_WB_FSAR_Section_2_B.pdf 005_TVA_WB_FSAR_Section_2_B.pdf

Table of Contents 1-iii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.0 SITE CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPHY 2.1-1 2.1.1 Site Location and Description 2.1-1 2.1.1.1 Specification of Location 2.1-1 2.1.1.2 Site Area Map 2.1-1 2.1.1.3 Boundaries for Establishing Effluent Limits 2.1-2 2.1.2 Exclusion Area Authority And Control 2.1-2 2.1.2.1 Authority 2.1-2 2.1.2.2 Control of Activities Unrelated to Plant Operation 2.1-2 2.1.2.3 Arrangements for Traffic Control 2.1-2 2.1.2.4 Abandonment or Relocation of Roads 2.1-2 2.1.3 Population Distribution 2.1-2 2.1.3.1 Population Within 10 Miles 2.1-3 2.1.3.2 Population Between 10 and 50 Miles 2.1-3 2.1.3.3 Transient Population 2.1-4 2.1.3.4 Low Population Zone 2.1-4 2.1.3.5 Population Center 2.1-5 2.1.3.6 Population Density 2.1-5 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 2.2.2.1 Description of Facilities 2.2-1 2.2.2.2 Description of Products and Materials 2.2-1 2.2.2.3 Pipelines 2.2-1 2.2.2.4 Waterways 2.2-1 2.2.2.5 Airports 2.2-2 2.2.2.6 Projections of Industrial Growth 2.2-2 2.2.3 Evaluation of Potential Accidents 2.2-2 2.2.

3.1 REFERENCES

2.2-3 2.3 METEOROLOGY 2.3-1 2.3.1 Regional Climate 2.3-1 2.3.1.1 Data Sources 2.3-1 2.3.1.2 General Climate 2.3-1 2.3.1.3 Severe Weather 2.3-2 2.3.2 Local Meteorology 2.3-5 2.3.2.1 Data Sources 2.3-5 2.3.2.2 Normal and Extreme Values of Meteorological Parameters 2.3-6 2.3.2.3 Potential Influence of the Plant and Its Facilities on Local Meteorology 2.3-8 2.3.2.4 Local Meteorological Conditions for Design and Operating Bases 2.3-9

1-iv Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.3.3 Onsite Meteorological Measurements Program 2.3-9 2.3.3.1 Preoperational Program 2.3-9 2.3.3.2 Operational Meteorological Program 2.3-12 2.3.3.3 Onsite Data Summaries of Parameters for Dispersion Meteorology 2.3-13 2.3.4 Short-Term (Accident) Diffusion Estimates 2.3-14 2.3.4.1 Objective 2.3-14 2.3.4.2 Calculation Results 2.3-17 2.3.5 Long-Term (Routine) Diffusion Estimates 2.3-18 005_TVA_WB_FSAR_Section_2_B.pdf 2.4 HYDROLOGIC ENGINEERING 2.4-1 2.4.1 Hydrological Description 2.4-1 2.4.1.1 Sites and Facilities 2.4-1 2.4.1.2 Hydrosphere 2.4-2 2.4.2 Floods 2.4-6 2.4.2.1 Flood History 2.4-6 2.4.2.2 Flood Design Considerations 2.4-7 2.4.2.3 Effects of Local Intense Precipitation 2.4-9 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers 2.4-12 2.4.3.1 Probable Maximum Precipitation (PMP) 2.4-13 2.4.3.2 Precipitation Losses 2.4-14 2.4.3.3 Runoff and Stream Course Model 2.4-14 2.4.3.4 Probable Maximum Flood Flow 2.4-18 2.4.3.5 Water Level Determinations 2.4-25 2.4.3.6 Coincident Wind Wave Activity 2.4-26 2.4.4 Potential Dam Failures, Seismically Induced 2.4-28 2.4.4.1 Dam Failure Permutations 2.4-28 2.4.4.2 Unsteady Flow Analysis of Potential Dam Failures 2.4-40 2.4.4.3 Water Level at Plantsite 2.4-40 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 2.4-41 2.4.8 Cooling Water Canals and Reservoirs 2.4-42 2.4.9 Channel Diversions 2.4-42 2.4.10 Flooding Protection Requirements 2.4-42 2.4.11 Low Water Considerations 2.4-44 2.4.11.1 Low Flow in Rivers and Streams 2.4-44 2.4.11.2 Low Water Resulting From Surges, Seiches, or Tsunami 2.4-44 2.4.11.3 Historical Low Water 2.4-44 2.4.11.4 Future Control 2.4-45 2.4.11.5 Plant Requirements 2.4-45 2.4.12 Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents 2.4-46 2.4.12.1 Radioactive Liquid Wastes 2.4-46 2.4.12.2 Accidental Slug Releases to Surface Water 2.4-46

Table of Contents 1-v WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.4.12.3 Effects on Ground Water 2.4-48 2.4.13 Groundwater 2.4-49 2.4.13.1 Description and On-Site Use 2.4-49 2.4.13.2 Sources 2.4-50 2.4.13.3 Accident Effects 2.4-51 2.4.13.4 Monitoring and Safeguard Requirements 2.4-52 2.4.13.5 Design Basis for Subsurface Hydrostatic Loading 2.4-52 2.4.14 Flooding Protection Requirements 2.4-52 2.4.14.1 Introduction 2.4-53 2.4.14.2 Plant Operation During Floods Above Grade 2.4-54 2.4.14.3 Warning Scheme 2.4-56 2.4.14.4 Preparation for Flood Mode 2.4-56 2.4.14.5 Equipment 2.4-58 2.4.14.6 Supplies 2.4-59 2.4.14.7 Plant Recovery 2.4-59 2.4.14.8 Warning Plan 2.4-59 2.4.14.9 Basis For Flood Protection Plan In Rainfall Floods 2.4-60 2.4.14.10 Basis for Flood Protection Plan in Seismic-Caused Dam Failures 2.4-66 2.4.14.11 Special Condition Allowance 2.4-68 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 2.5.1.1 Regional Geology 2.5-3 2.5.1.2 Site Geology 2.5-27 2.5.2 Vibratory Ground Motion 2.5-34 2.5.2.1 Seismicity 2.5-34 2.5.2.2 Geologic Structures and Tectonic Activity 2.5-42 2.5.2.3 Correlation of Earthquake Activity With Geologic Structures to Tectonic Prov-inces 2.5-42 2.5.2.4 Maximum Earthquake Potential 2.5-43 2.5.2.5 Seismic Wave Transmission Characteristics of the Site 2.5-45 2.5.2.6 Safe Shutdown Earthquake 2.5-45 2.5.2.7 Operating Basis Earthquake 2.5-45 2.5.3 Surface Faulting 2.5-45 2.5.3.1 Geologic Conditions of the Site 2.5-45 2.5.3.2 Evidence of Fault Offset 2.5-45 2.5.3.3 Earthquakes Associated With Capable Faults 2.5-54 2.5.3.4 Investigations of Capable Faults 2.5-54 2.5.3.5 Correlation of Epicenters With Capable Faults 2.5-56 2.5.3.6 Description of Capable Faults 2.5-56 2.5.3.7 Zone Requiring Detailed Faulting Investigation 2.5-56 2.5.3.8 Results of Faulting Investigations 2.5-56 2.5.4 Stability of Subsurface Materials 2.5-57

1-vi Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.5.4.1 Geologic Features 2.5-57 2.5.4.2 Properties of Subsurface Materials 2.5-57 2.5.4.3 Exploration 2.5-90 2.5.4.4 Geophysical Surveys 2.5-90 2.5.4.5 Excavations and Backfill 2.5-93 2.5.4.6 Groundwater Conditions 2.5-101 2.5.4.7 Response of Soil and Rock to Dynamic Loading 2.5-103 2.5.4.8 Liquefaction Potential 2.5-103 2.5.4.9 Earthquake Design Basis 2.5-114 2.5.4.10 Static Analysis 2.5-114 2.5.4.11 Safety-Related Criteria for Foundations 2.5-115 2.5.4.12 Techniques to Improve Subsurface Conditions 2.5-116 2.5.4.13 Construction Notes 2.5-118 2.5.5 Stability of Slopes 2.5-119 2.5.5.1 Slope Characteristics 2.5-119 2.5.5.2 Design Criteria and Analysis 2.5-120 2.5.5.3 Logs of Borings 2.5-128 2.5.5.4 Compaction Specifications 2.5-128 2.5.6 Embankments 2.5-12 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 3.1.2.1 Overall Requirements 3.1-1 3.1.2.2 Protection By Multiple Fission Product Barriers 3.1-5 3.1.2.3 Protection and Reactivity Control Systems 3.1-12 3.1.2.4 Fluid Systems 3.1-17 3.1.2.5 Reactor Containment 3.1-30 3.1.2.6 Fuel and Radioactivity Control 3.1-35 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 3.2.2.1 Class A 3.2-2 3.2.2.2 Class B 3.2-2 3.2.2.3 Class C 3.2-2 3.2.2.4 Class D 3.2-2 3.2.2.5 Relationship of Applicable Codes to Safety Classification for Mechanical Com-ponents 3.2-3 3.2.2.6 Nonnuclear Safety Class (NNS) 3.2-3 3.2.2.7 Heating, Ventilation and Air Conditioning (HVAC) Safety Classification3.2-3 3.2.3 Code Cases and Code Editions and Addenda 3.2-3

Table of Contents 1-vii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.2.3.1 TVA Design and Fabrication 3.2-3 3.2.3.2 Purchased Materials and Components 3.2-4 3.3 Wind and Tornado Loading 3.3-1 3.3.1 Wind Loadings 3.3-1 3.3.1.1 Design Wind Velocity 3.3-1 3.3.1.2 Determination of Applied Force 3.3-1 3.3.2 Tornado Loadings 3.3-1 3.3.2.1 Applicable Design Parameters 3.3-1 3.3.2.2 Determination of Forces on Structures 3.3-2 3.3.2.3 Ability of Category I Structures to Perform Despite Failure of Structures Not Designed for Tornado Loads 3.3-3 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 3.5.1.1 Internally Generated Missiles (Outside Containment) 3.5-2 3.5.1.2 Internally Generated Missiles (Inside Containment) 3.5-5 3.5.1.3 Turbine Missiles 3.5-9 3.5.1.4 Missiles Generated By Natural Phenomena 3.5-27 3.5.1.5 Missiles Generated by Events Near the Site.

3.5-28 3.5.1.6 Aircraft Hazards 3.5-28 3.5.2 Systems To Be Protected 3.5-29 3.5.3 Barrier Design Procedures 3.5-29 3.5.3.1 Additional Diesel Generator Building (And Other Category I Structures Added After July 1979) 3.5-32 3.5A ESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES 3.5A-1 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POS-TULATED RUPTURE OF PIPING 3.6-1 3.6A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POS-TULATED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIP-ING) 3.6A-1 3.6A.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment 3.6A-7 3.6A.1.1 Design Bases 3.6A-7 3.6A.1.2 Description of Piping System Arrangement 3.6A-10 3.6A.1.3 Safety Evaluation 3.6A-10 3.6A.2 Determination of Break Locations and Dynamic Effects Associated with the Postu-lated Rupture of Piping 3.6A-10

1-viii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.6A.2.1 Criteria Used to Define Break and Crack Location and Configuration 3.6A-10 3.6A.2.2 Analytical Methods to Define Forcing Functions and Response Models 3.6A-16 3.6A.2.3 Dynamic Analysis Methods to Verify Integrity and Operability 3.6A-19 3.6A.2.4 Guard Pipe Assembly Design Criteria 3.6A-22 3.6A.2.5 Summary of Dynamic Analysis Results 3.6A-23 3.6B PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POS-TULATED RUPTURE OF PIPING 3.6A-24 3.6B.1 Break Locations And Dynamic Effects Associated With Postulated Primary Loop Pipe Rupture 3.6A-24 3.6A.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 3.7.1.1 Ground Response Spectra 3.7-2 3.7.1.2 Design Time Histories 3.7-2 3.7.1.3 Critical Damping Values 3.7-3 3.7.1.4 Supporting Media for Seismic Category I Structures 3.7-3 3.7.2 Seismic System Analysis 3.7-3 3.7.2.1 Seismic Analysis Methods 3.7-4 3.7.2.2 Natural Frequencies and Response Loads for NSSS 3.7-22 3.7.2.3 Procedures Used for Modeling 3.7-22 3.7.2.4 Soil/Structure Interaction 3.7-23 3.7.2.5 Development of Floor Response Spectra 3.7-24 3.7.2.6 Three Components of Earthquake Motion 3.7-25 3.7.2.7 Combination of Modal Responses 3.7-26 3.7.2.8 Interaction of Non-Category I Structures With Seismic Category I Structures 3.7-28 3.7.2.9 Effects of Parameter Variations on Floor Response Spectra 3.7-29 3.7.2.10 Use of Constant Vertical Load Factors 3.7-29 3.7.2.11 Methods Used to Account for Torsional Effects 3.7-29 3.7.2.12 Comparison of Responses - Set A versus Set B 3.7-30 3.7.2.13 Methods for Seismic Analysis of Dams 3.7-30 3.7.2.14 Determination of Category I Structure Overturning Moments 3.7-30 3.7.2.15 Analysis Procedure for Damping 3.7-31 3.7.3 Seismic Subsystem Analysis 3.7-31 3.7.3.1 Seismic Analysis Methods for Other Than NSSS 3.7-31 3.7.3.2 Determination of Number of Earthquake Cycles 3.7-32 3.7.3.3 Procedure Used for Modeling 3.7-32 3.7.3.4 Basis for Selection of Frequencies 3.7-34 3.7.3.5 Use of Equivalent Static Load Method of Analysis 3.7-35

Table of Contents 1-ix WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.7.3.6 Three Components of Earthquake Motion 3.7-35 3.7.3.7 Combination of Modal Responses 3.7-36 3.7.3.8 Analytical Procedures for Piping Other Than NSSS 3.7-37 3.7.3.9 Multiple Supported Equipment and Components with Distinct Inputs 3.7-43 3.7.3.10 Use of Constant Vertical Load Factors 3.7-44 3.7.3.11 Torsional Effects of Eccentric Masses 3.7-45 3.7.3.12 Buried Seismic Category I Piping Systems 3.7-45 3.7.3.13 Interaction of Other Piping with Seismic Category I Piping 3.7-51 3.7.3.14 Seismic Analyses for Fuel Elements, Control Rod Assemblies, Control Rod Drives, and Reactor Internals 3.7-51 3.7.3.15 Analysis Procedure for Damping 3.7-53 3.7.3.16 Seismic Analysis and Qualification of Category I Equipment Other Than NSSS 3.7-53 3.7.3.17 Seismic Analysis and Design of HVAC Duct and Duct Support Systems 3.7-56 3.7.4 Seismic Instrumentation Program 3.7-60 3.7.4.1 Comparison with Regulatory Guide 1.12 3.7-60 3.7.4.2 Location and Description of Instrumentation 3.7-60 3.7.4.3 Control Room Operator Notification 3.7-64 3.7.4.4 Comparison of Measured and Predicted Responses 3.7-64 3.8 DESIGN OF CATEGORY I STRUCTURES 3.8.1 Concrete Shield Building 3.8.1-1 3.8.1.1 Description of the Shield Building 3.8.1-1 3.8.1.1.1 Equipment Hatch Doors and Sleeves 3.8.1-2 3.8.1.2 Applicable Codes, Standards, and Specifications 3.8.1-3 3.8.1.3 Loads and Loading Combinations 3.8.1-5 3.8.1.4 Design and Analysis Procedures 3.8.1-8 3.8.1.5 Structural Acceptance Criteria 3.8.1-10 3.8.1.6 Materials, Quality Control and Special Construction Techniques 3.8.1-11 3.8.1.6.1 Materials 3.8.1-11 3.8.1.6.2 Quality Control 3.8.1-12 3.8.1.6.3 Construction Techniques 3.8.1-13 3.8.1.7 Testing and Inservice Surveillance Requirements 3.8.1-13 3.8.2 Steel Containment System 3.8.2-1 3.8.2.1 Description of the Containment and Penetrations 3.8.2-1 3.8.2.1.1 Description of the Containment 3.8.2-1 3.8.2.1.2 Description of Penetrations 3.8.2-1 3.8.2.2 Applicable Codes, Standards and Specifications 3.8.2-3 3.8.2.2.1 Codes 3.8.2-3 3.8.2.2.2 Design Specification Summary 3.8.2-4 3.8.2.2.3 NRC Regulatory Guides 3.8.2-6

1-x Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.2.3 Loads and Loading Combinations 3.8.2-7 3.8.2.3.1 Design Loads 3.8.2-7 3.8.2.3.2 Loading Conditions 3.8.2-9 3.8.2.4 Design and Analysis Procedures 3.8.2-11 3.8.2.4.1 Introduction 3.8.2-11 3.8.2.4.2 Static Stress Analysis 3.8.2-12 3.8.2.4.3 Dynamic Seismic Analysis 3.8.2-12 3.8.2.4.4 Non-Axisymmetric Pressure Loading Analysis 3.8.2-13 3.8.2.4.5 Thermal Analysis 3.8.2-14 3.8.2.4.6 Penetrations Analysis 3.8.2-14 3.8.2.4.7 Interaction of Containment and Attached Equipment 3.8.2-17 3.8.2.4.8 Anchorage 3.8.2-17 3.8.2.5 Structural Acceptance Criteria 3.8.2-18 3.8.2.5.1 Margin of Safety 3.8.2-18 3.8.2.6 Materials, Quality Control, and Special Construction Techniques 3.8.2-19 3.8.2.6.1 Materials - General 3.8.2-19 3.8.2.6.2 Corrosion Protection 3.8.2-22 3.8.2.6.3 Protective Coatings 3.8.2-24 3.8.2.6.4 Tolerances 3.8.2-25 3.8.2.6.5 Vessel Material Inspection and Test 3.8.2-25 3.8.2.6.6 Impact Testing 3.8.2-25 3.8.2.6.7 Post-Weld Heat Treatment 3.8.2-26 3.8.2.6.8 Welding 3.8.2-26 3.8.2.7 Testing and Inservice Inspection Requirements 3.8.2-26 3.8.2.7.1 Bottom Liner Plates Test 3.8.2-26 3.8.2.7.2 Vertical Wall and Dome Tests 3.8.2-26 3.8.2.7.3 Soap Bubble Tests 3.8.2-26 3.8.2.7.4 Overpressure Tests 3.8.2-26 3.8.2.7.5 Leakage Rate Test 3.8.2-27 3.8.2.7.6 Operational Testing 3.8.2-27 3.8.2.7.7 Leak Testing Airlocks 3.8.2-27 3.8.2.7.8 Penetration Tests 3.8.2-28 3.8.2.7.9 Inservice Inspection Requirements 3.8.2-28 3.8.3 Concrete Interior Structure 3.8.3-1 3.8.3.1 Description of the Interior Structure 3.8.3-1 3.8.3.1.1 General 3.8.3-1 3.8.3.1.2 Containment Floor Structural Fill Slab 3.8.3-1 3.8.3.1.3 Reactor Cavity Wall 3.8.3-2 3.8.3.1.4 Compartment Above Reactor 3.8.3-2 3.8.3.1.5 Refueling Canal Walls and Floor (Divider Barrier) 3.8.3-3 3.8.3.1.6 Crane Wall 3.8.3-3 3.8.3.1.7 Steam Generator Compartments (Divider Barrier) 3.8.3-5 3.8.3.1.8 Pressurizer Compartment (Divider Barrier) 3.8.3-5

Table of Contents 1-xi WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.3.1.9 Divider Deck at Elevation 756.63 (Divider Barrier) 3.8.3-5 3.8.3.1.10 Ice Condenser Support Floor - Elevation 744.5 (Divider Barrier) 3.8.3-5 3.8.3.1.11 Penetrations Through the Divider Barrier Canal Gate 3.8.3-6 3.8.3.2 Applicable Codes, Standards and Specifications 3.8.3-7 3.8.3.3 Loads and Loading Combinations 3.8.3-13 3.8.3.4 Design and Analysis Procedures 3.8.3-16 3.8.3.4.1 General 3.8.3-16 3.8.3.4.2 Structural Fill Slab on Containment Floor 3.8.3-16 3.8.3.4.3 Reactor Cavity Wall 3.8.3-16 3.8.3.4.4 Compartment Above Reactor 3.8.3-18 3.8.3.4.5 Seals Between Upper and Lower Compartments 3.8.3-18 3.8.3.4.6 Refueling Canal Walls and Floor (Divider Barrier) 3.8.3-19 3.8.3.4.7 Crane Wall 3.8.3-20 3.8.3.4.8 Steam Generator Compartments (Divider Barrier) 3.8.3-23 3.8.3.4.9 Pressurizer Compartment (Divider Barrier) 3.8.3-25 3.8.3.4.10 Operating Deck at Elevation 756.63 (Divider Barrier) 3.8.3-26 3.8.3.4.11 Ice Condenser Support Floor Elevation 744.5 (Divider Barrier) 3.8.3-27 3.8.3.4.12 Ice Condenser 3.8.3-28 3.8.3.4.13 Penetrations Through the Divider Barrier 3.8.3-29 3.8.3.5 Structural Acceptance Criteria 3.8.3-31 3.8.3.5.1 General 3.8.3-31 3.8.3.5.2 Structural Fill Slab on Containment Floor 3.8.3-31 3.8.3.5.3 Reactor Cavity Wall and Compartment Above Reactor 3.8.3-32 3.8.3.5.4 Refueling Canal Walls and Floor 3.8.3-32 3.8.3.5.5 Crane Wall 3.8.3-32 3.8.3.5.6 Steam Generator and Pressurizer Compartment 3.8.3-32 3.8.3.5.7 Operating Deck at Elevation 756.63 3.8.3-33 3.8.3.5.8 Ice Condenser Support Floor Elevation 744.5 3.8.3-33 3.8.3.5.9 Penetrations Through the Divider Barrier 3.8.3-33 3.8.3.5.10 Personnel Access Doors in Crane Wall 3.8.3-33 3.8.3.5.11 Seals Between Upper and Lower Compartments 3.8.3-34 3.8.3.5.12 Ice Condenser 3.8.3-35 3.8.3.6 Materials, Quality Control and Special Construction Techniques 3.8.3-36 3.8.3.6.1 Materials 3.8.3-36 3.8.3.6.2 Quality Control 3.8.3-37 3.8.3.6.3 Construction Technique 3.8.3-38 3.8.3.6.4 Ice Condenser 3.8.3-38 3.8.3.7 Testing and Inservice Surveillance Requirements 3.8.3-41 3.8.3.8 Environmental Effects 3.8.3-41 3.8.3.9 Interface Control 3.8.3-42 3.8.4 Other Category I Structures 3.8.4-1 3.8.4.1 Description of the Structures 3.8.4-1 3.8.4.1.1 Auxiliary-Control Building 3.8.4-1

1-xii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.4.1.2 Diesel Generator Building 3.8.4-13 3.8.4.1.3 Category I Water Tanks and Pipe Tunnels 3.8.4-14 3.8.4.1.4 Class 1E Electrical System Manholes and Duct Runs 3.8.4-15 3.8.4.1.5 North Steam Valve Room 3.8.4-16 3.8.4.1.6 Intake Pumping Station and Retaining Walls 3.8.4-17 3.8.4.1.7 Miscellaneous Essential Raw Cooling Water (ERCW) Structures 3.8.4-18 3.8.4.1.8 Additional Diesel Generator Building 3.8.4-19 3.8.4.2 Applicable Codes, Standards, and Specifications 3.8.4-20 3.8.4.2.1 List of Documents 3.8.4-20 3.8.4.2.2 Basis for Use of the 1963 Edition of ACI 318 3.8.4-22 3.8.4.3 Loads and Loading Combinations 3.8.4-25 3.8.4.3.1 Description of Loads 3.8.4-25 3.8.4.3.2 Load Combinations and Allowable Stresses 3.8.4-26 3.8.4.4 Design and Analysis Procedures 3.8.4-27 3.8.4.4.1 Auxiliary-Control Building 3.8.4-27 3.8.4.4.2 Diesel Generator Building 3.8.4-35 3.8.4.4.3 Category I Water Tanks and Pipe Tunnels 3.8.4-36 3.8.4.4.4 Class 1E Electrical System Manholes 3.8.4-37 3.8.4.4.5 North Steam Valve Room 3.8.4-37 3.8.4.4.6 Intake Pumping Station and Retaining Walls Pumping Station 3.8.4-37 3.8.4.4.7 Miscellaneous ERCW Structures 3.8.4-38 3.8.4.4.8 Additional Diesel Generator Building 3.8.4-39 3.8.4.5 Structural Acceptance Criteria 3.8.4-41 3.8.4.5.1 Concrete 3.8.4-41 3.8.4.5.2 Structural and Miscellaneous Steel 3.8.4-41 3.8.4.5.3 Miscellaneous Components of the Auxiliary Building 3.8.4-42 3.8.4.5.4 Intake Pumping Station Traveling Water Screens 3.8.4-43 3.8.4.5.5 Diesel Generator Building Doors and Bulkheads 3.8.4-43 3.8.4.5.6 Additional Diesel Generator Building Missile Barriers 3.8.4-43 3.8.4.6 Materials, Quality Control, and Special Construction Techniques General 3.8.4-43 3.8.4.6.1 Materials 3.8.4-44 3.8.4.6.2 Quality Control 3.8.4-44 3.8.4.6.3 Special Construction Techniques 3.8.4-45 3.8.4.7 Testing and Inservice Surveillance Requirements 3.8.4-45 3.8.4.7.1 Concrete and Structural Steel Portions of Structures 3.8.4-45 3.8.4.7.2 Miscellaneous Components of Auxiliary-Control Building 3.8.4-45 3.8.4.7.3 Deleted by Amendment 79 3.8.4-46 3.8.4.7.4 Miscellaneous Components of the Intake Pumping Station 3.8.4-46 3.8.5 Foundations and Concrete Supports 3.8.5-1 3.8.5.1 Description of Foundations and Supports 3.8.5-1 3.8.5.1.1 Primary Containment 3.8.5-1 3.8.5.1.2 Foundations of Other Category I Structures 3.8.5-1 3.8.5.2 Applicable Codes, Standards, and Specifications 3.8.5-4

Table of Contents 1-xiii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.5.3 Loads and Loading Combinations 3.8.5-4 3.8.5.4 Design and Analysis Procedure 3.8.5-4 3.8.5.4.1 Primary Containment Foundation 3.8.5-4 3.8.5.4.2 Auxiliary-Control Building 3.8.5-4 3.8.5.4.3 Intake Pumping Station 3.8.5-5 3.8.5.4.4 Soil-Supported Structures 3.8.5-5 3.8.5.4.5 Pile Supported Structures 3.8.5-5 3.8.5.5 Structural Acceptance Criteria 3.8.5-5 3.8.5.5.1 Primary Containment Foundation 3.8.5-5 3.8.5.5.2 Foundations of Other Category I Structures Auxiliary-Control Building3.8.5-6 3.8.5.6 Materials, Quality Control, and Special Construction Techniques 3.8.5-7 3.8.5.6.1 Materials 3.8.5-7 3.8.5.6.2 Quality Control 3.8.5-8 3.8.5.6.3 Special Construction Techniques 3.8.5-8 3.8.6 Category I(L) Cranes 3.8.6-1 3.8.6.1 Polar Cranes 3.8.6-1 3.8.6.1.1 Description 3.8.6-1 3.8.6.1.2 Applicable Codes, Standards, and Specifications 3.8.6-1 3.8.6.1.3 Loads, Loading Combinations, and Allowable Stresses 3.8.6-2 3.8.6.1.4 Design and Analysis Procedure 3.8.6-2 3.8.6.1.5 Structural Acceptance Criteria 3.8.6-2 3.8.6.1.6 Materials, Quality Controls, and Special Construction Techniques 3.8.6-3 3.8.6.1.7 Testing and Inservice Surveillance Requirements 3.8.6-3 3.8.6.1.8 Safety Features 3.8.6-3 3.8.6.2 Auxiliary Building Crane 3.8.6-4 3.8.6.2.1 Description 3.8.6-4 3.8.6.2.2 Applicable Codes, Standards, and Specifications 3.8.6-5 3.8.6.2.3 Loads, Loading Combinations, and Allowable Stresses 3.8.6-5 3.8.6.2.4 Design and Analysis Procedure 3.8.6-5 3.8.6.2.5 Structural Acceptance Criteria 3.8.6-6 3.8.6.2.6 Materials, Quality Controls, and Special Construction Techniques 3.8.6-6 3.8.6.2.7 Testing and Inservice Surveillance Requirements 3.8.6-7 3.8.6.2.8 Safety Features 3.8.6-7 3.8A SHELL TEMPERATURE TRANSIENTS 3.8A-1 3.8B BUCKLING STRESS CRITERIA 3.8B-1 3.8B.1 INTRODUCTION 3.8B-1 3.8B.2 SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS 3.8B-1 3.8B.2.1 Circular Cylindrical Shells Under Axial Compression 3.8B-1 3.8B.2.2 Circular Cylindrical Shells in Circumferential Compression 3.8B-2 3.8B.2.3 Circular Cylindrical Shells Under Torsion 3.8B-2 3.8B.2.4 where a is the effective length and b is the circumference of the cylinder. The

1-xiv Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page coefficient K's is given in Figure 3.8B-10.Circular Cylindrical Shells Under Bending 3.8B-3 3.8B.2.5 Circular Cylindrical Shell Under Combined Loads 3.8B-3 3.8B.3 SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND VERTICAL STIFFENERS 3.8B-5 3.8B.4 SPHERICAL SHELLS 3.8B-7 3.8B.4.1 The critical buckling stress in the spherical dome, except for external pressure, was determined by the following equation:

3.8B-7 3.8B.4.2 Spherical Shell Under Combined Loads 3.8B-7 3.8B.5 FACTOR OF SAFETY 3.8B-8 3.8C DOCUMENTATION OF CB&I COMPUTER PROGRAMS 3.8C-1 3.8C.1 INTRODUCTION 3.8C-1 3.8C.2 PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN VALUE TECHNIQUE 3.8C-1 3.8C.3 PROGRAM 1044-SEISMIC ANALYSIS of VESSEL APPENDAGES 3.8C-1 3.8C.4 PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS DIGITIZED AT EQUAL INTERVALS 3.8C-3 3.8C.5 PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS 3.8C-3 3.8C.6 PROGRAM E1623-POST PROCESSOR PROGRAM FOR PROGRAM E1374 3.8C-4 3.8C.7 PROGRAM E1374-SHELL DYNAMIC ANALYSIS 3.8C-5 3.8C.7.1 Introduction 3.8C-5 3.8C.8 PROGRAM E1622-LOAD GENERATION PREPROCESSOR FOR PROGRAM E1374 3.8C-6 3.8C.9 PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION 3.8C-7 3.8C.10 PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS 3.8C-7 3.8C.11 PROGRAM 119-CHECK of FLANGE DESIGN 3.8C-7 3.8C.12 PROGRAM 772-NOZZLE REINFORCEMENT CHECK 3.8C-7 3.8C.13 PROGRAM 1027-WRC 107 STRESS INTENSITIES AT LOADED ATTACH-MENTS FOR SPHERES OR CYLINDERS WITH ROUND OR SQUARE AT-TACHMENT 3.8C-8 3.8C.14 PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES 3.8C-8 3.8D COMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS 3.8D-1 3.8E CODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFI-CATION 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 3.8E-1 3.8E.1 Application Codes and Standards 3.8E-1 3.8E.2 Load Definitions 3.8E-1 3.8E.3 Load Combinations - Concrete 3.8E-3 3.8E.4 Load Combinations - Structural Steel 3.8E-5

Table of Contents 1-xv WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 3.9.1.1 Design Transients 3.9-1 3.9.1.2 Computer Programs Used in Analysis and Design 3.9-1 3.9.1.3 Experimental Stress Analysis 3.9-3 3.9.1.4 Consideration for the Evaluation of the Faulted Condition 3.9-3 3.9.2 Dynamic Testing and Analysis 3.9-4 3.9.2.1 Preoperational Vibration and Dynamic Effects Testing on Piping 3.9-4 3.9.2.2 Seismic Qualification Testing of Safety-Related Mechanical Equipment 3.9-6 3.9.2.3 Dynamic Response Analysis of Reactor Internals Under Operational Flow Transients and Steady-State Conditions 3.9-8 3.9.2.4 Preoperational Flow-Induced Vibration Testing of Reactor Internals 3.9-10 3.9.2.5 Dynamic System Analysis of the Reactor Internals Under Faulted Conditions 3.9-12 3.9.2.6 Correlations of Reactor Internals Vibration Tests With the Analytical Results 3.9-19 3.9.3 ASME Code Class 1, 2 and 3 Components, Component Supports and Core Support Structures 3.9-20 3.9.3.1 Loading Combinations, Design Transients, and Stress Limits 3.9-20 3.9.3.2 Pumps and Valve Operability Assurance 3.9-27 3.9.3.3 Design and Installation Details for Mounting of Pressure Relief Devices3.9-39 3.9.3.4 Component Supports 3.9-42 3.9.4 Control Rod System 3.9-46 3.9.4.1 Descriptive Information of CRDS 3.9-46 3.9.4.2 Applicable CRDS Design Specifications 3.9-47 3.9.4.3 Design Loadings, Stress Limits, and Allowable Deformations 3.9-47 3.9.4.4 CRDS Performance Assurance Program 3.9-47 3.9.5 Reactor Pressure Vessel Internals 3.9-47 3.9.5.1 Design Arrangements 3.9-47 3.9.5.2 Design Loading Conditions 3.9-47 3.9.5.3 Design Loading Categories 3.9-47 3.9.5.4 Design Basis 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 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 3.10-4 3.10.3 Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumen-tation and Cables 3.10-4 3.10.3.1 Electrical Equipment and Instrumentation Assemblies 3.10-5

1-xvi Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.10.3.2 Cable Trays and Supports 3.10-6 3.10.3.3 Conduit and Supports 3.10-7 3.10.3.4 Conduit Banks 3.10-8 3.10.4 Operating License Review 3.10-8 3.10.4.1 TVA Supplied Instrumentation and Electrical Equipment 3.10-8 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIP-MENT 3.11-1 3.11.1 Equipment Identification and Environmental Conditions 3.11-1 3.11.1.1 Identification of Safety Systems and Justification 3.11-1 3.11.1.2 Identification of Equipment in Harsh Environments 3.11-1 3.11.2 Environmental Conditions 3.11-2 3.11.2.1 Harsh Environment 3.11-2 3.11.2.2 Mild Environment 3.11-3 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 3.11.7.1 Chemical Spray 3.11-4 3.11.7.2 Radiation 3.11-5 013_TVA_WB_FSAR_Section_4.pdf 4.0 REACTOR 4.1

SUMMARY

DESCRIPTION 4.1-1 4.2 MECHANICAL DESIGN 4.2-1 4.2.1 Fuel 4.2-2 4.2.1.1 Design Bases 4.2-2 4.2.1.2 Design Description 4.2-5 4.2.1.3 Design Evaluation 4.2-9 4.2.1.4 Tests and Inspections 4.2-18 4.2.2 Reactor Vessel Internals 4.2-22 4.2.2.1 Design Bases 4.2-22 4.2.2.2 Description and Drawings 4.2-23 4.2.2.3 Design Loading Conditions 4.2-26 4.2.2.4 Design Loading Categories 4.2-27 4.2.2.5 Design Criteria Basis 4.2-28 4.2.3 Reactivity Control System 4.2-29 4.2.3.1 Design Bases 4.2-29 4.2.3.2 Design Description 4.2-32 4.2.3.3 Design Evaluation 4.2-42 4.2.3.4 Tests, Verification, and Inspections 4.2-52 4.2.3.5 Instrumentation Applications 4.2-55

Table of Contents 1-xvii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 4.3 NUCLEAR DESIGN 4.3-1 4.3.1 DESIGN BASES 4.3-1 4.3.1.1 Fuel Burnup 4.3-2 4.3.1.2 Negative Reactivity Feedbacks (Reactivity Coefficient) 4.3-2 4.3.1.3 Control of Power Distribution 4.3-3 4.3.1.4 Maximum Controlled Reactivity Insertion Rate 4.3-4 4.3.1.5 Shutdown Margins With Vessel Head in Place 4.3-4 4.3.1.6 Shutdown Margin for Refueling 4.3-5 4.3.1.7 Stability 4.3-5 4.3.1.8 Anticipated Transients Without Trip 4.3-6 4.3.2 Description 4.3-6 4.3.2.1 Nuclear Design Description 4.3-6 4.3.2.2 Power Distributions 4.3-8 4.3.2.3 Reactivity Coefficients 4.3-19 4.3.2.4 Control Requirements 4.3-23 4.3.2.5 Control 4.3-25 4.3.2.6 Control Rod Patterns and Reactivity Worth 4.3-27 4.3.2.7 Criticality of Fuel Assemblies 4.3-28 4.3.2.8 Stability 4.3-33 4.3.2.9 Vessel Irradiation 4.3-38 4.3.3 Analytical Methods 4.3-38 4.3.3.1 Fuel Temperature (Doppler) Calculations 4.3-39 4.3.3.2 Macroscopic Group Constants 4.3-40 4.3.3.3 Spatial Few-Group Diffusion Calculations 4.3-41 4.4 THERMAL AND HYDRAULIC DESIGN 4.4-1 4.4.1 Design Bases 4.4-1 4.4.1.1 Departure from Nucleate Boiling Design Basis 4.4-1 4.4.1.2 Fuel Temperature Design Basis 4.4-2 4.4.1.3 Core Flow Design Basis 4.4-2 4.4.1.4 Hydrodynamic Stability Design Bases 4.4-3 4.4.1.5 Other Considerations 4.4-3 4.4.2 Description 4.4-3 4.4.2.1 Summary Comparison 4.4-3 4.4.2.2 Fuel and Cladding Temperatures 4.4-4 4.4.2.3 Critical Heat Flux Ratio or Departure from Nucleate Boiling Ratio and Mixing Technology4.4-6 4.4.2.4 Flux Tilt Considerations 4.4-13 4.4.2.5 Void Fraction Distribution 4.4-14 4.4.2.6 Core Coolant Flow Distribution 4.4-14 4.4.2.7 Core Pressure Drops and Hydraulic Loads 4.4-14 4.4.2.8 Correlation and Physical Data 4.4-15 4.4.2.9 Thermal Effects of Operational Transients 4.4-17

1-xviii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 4.4.2.10 Uncertainties in Estimates 4.4-18 4.4.2.11 Plant Configuration Data 4.4-20 4.4.3 EVALUATION 4.4-20 4.4.3.1 Core Hydraulics 4.4-20 4.4.3.2 Influence of Power Distribution 4.4-22 4.4.3.3 Core Thermal Response 4.4-24 4.4.3.4 Analytical Techniques 4.4-24 4.4.3.5 Hydrodynamic and Flow Power Coupled Instability 4.4-26 4.4.3.6 Temperature Transient Effects Analysis 4.4-28 4.4.3.7 Potentially Damaging Temperature Effects During Transients 4.4-29 4.4.3.8 Energy Release During Fuel Element Burnout 4.4-29 4.4.3.9 Deleted 4.4-30 4.4.3.10 Fuel Rod Behavior-Effects from Coolant Flow Blockage 4.4-30 4.4.4 Testing and Verification 4.4-31 4.4.4.1 Tests Prior to Initial Criticality 4.4-31 4.4.4.2 Initial Power and Plant Operation 4.4-31 4.4.4.3 Component and Fuel Inspections 4.4-32 4.4.5 Instrumentation Application 4.4-32 4.4.5.1 Incore Instrumentation 4.4-32 4.4.5.2 Overtemperature and Overpower T Instrumentation 4.4-32 4.4.5.3 Instrumentation to Limit Maximum Power Output 4.4-33 014_TVA_WB_FSAR_Section_5.pdf 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 5.2.1.1 Performance Objectives 5.2-2 5.2.1.2 Design Parameters 5.2-3 5.2.1.3 Compliance with 10 CFR Part 50, Section 50.55a 5.2-4 5.2.1.4 Applicable Code Cases 5.2-4 5.2.1.5 Design Transients 5.2-5 5.2.1.6 Identification of Active Pumps and Valves 5.2-14 5.2.1.7 Design of Active Pumps and Valves 5.2-14 5.2.1.8 Inadvertent Operation of Valves 5.2-14 5.2.1.9 Stress and Pressure Limits 5.2-15 5.2.1.10 Stress Analysis for Structural Adequacy 5.2-15 5.2.1.11 Analysis Methods For Faulted Conditions 5.2-34 5.2.1.12 Protection Against Environmental Factors 5.2-34 5.2.1.13 Compliance With Code Requirements 5.2-34

Table of Contents 1-xix WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.2.1.14 Stress Analysis For Faulted Conditions Loadings 5.2-34 5.2.1.15 Stress Levels in Category I Systems 5.2-34 5.2.1.16 Analytical Methods for Stresses in Pumps and Valves 5.2-34 5.2.1.17 Analytical Methods for Evaluation of Pump Speed and Bearing Integrity 5.2-35 5.2.1.18 Operation of Active Valves Under Transient Loadings 5.2-35 5.2.2 Overpressurization Protection 5.2-35 5.2.2.1 Location of Pressure Relief Devices 5.2-35 5.2.2.2 Mounting of Pressure Relief Devices 5.2-35 5.2.2.3 Report on Overpressure Protection 5.2-35 5.2.2.4 RCS Pressure Control During Low Temperature Operation 5.2-37 5.2.3 General Material Considerations 5.2-40 5.2.3.1 Material Specifications 5.2-40 5.2.3.2 Compatibility With Reactor Coolant 5.2-41 5.2.3.3 Compatibility With External Insulation and Environmental Atmosphere 5.2-42 5.2.3.4 Chemistry of Reactor Coolant 5.2-42 5.2.4 Fracture Toughness 5.2-43 5.2.4.1 Compliance With Code Requirements 5.2-43 5.2.4.2 Acceptable Fracture Energy Levels 5.2-43 5.2.4.3 Operating Limitations During Startup and Shutdown 5.2-43 5.2.5 Austenitic Stainless Steel 5.2-46 5.2.5.1 Cleaning and Contamination Protection Procedures 5.2-46 5.2.5.2 Solution Heat Treatment Requirements 5.2-47 5.2.5.3 Material Inspection Program 5.2-48 5.2.5.4 Unstablilized Austenitic Stainless Steels 5.2-48 5.2.5.5 Prevention of Intergranular Attack of Unstabilized Austenitic Stainless Steels 5.2-48 5.2.5.6 Retesting Unstabilized Austenitic Stainless Steel Exposed to Sensitization Temperatures5.2-51 5.2.5.7 Control of Delta Ferrite in Austenitic Stainless Steel Welding 5.2-51 5.2.6 Pump Flywheels 5.2-53 5.2.6.1 Design Basis 5.2-53 5.2.6.2 Fabrication and Inspection 5.2-53 5.2.6.3 Acceptance Criteria and Compliance with Regulatory Guide 1.14 5.2-54 5.2.7 RCPB Leakage Detection Systems 5.2-55 5.2.7.1 Collection of Identified Leakage 5.2-55 5.2.7.2 Unidentified Leakage to Containment 5.2-56 5.2.7.3 Methods of Detection 5.2-56 5.2.7.4 Intersystem Leakage Detection 5.2-58 5.2.7.5 Unidentified Leakage System Sensitivity and Response Time 5.2-62 5.2.7.6 Seismic Capability 5.2-64 5.2.7.7 Indicators and Alarms 5.2-64 5.2.7.8 Testing 5.2-65 5.2.8 Inservice Inspection of ASME Code Class 1 Components 5.2-65

1-xx Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.2.8.1 Components Subject to Examination and/or Test 5.2-65 5.2.8.2 Accessibility 5.2-65 5.2.8.3 Examination Techniques and Procedures 5.2-67 5.2.8.4 Inspection Intervals 5.2-67 5.2.8.5 Examination Categories and Requirements 5.2-67 5.2.8.6 Evaluation of Examination Results 5.2-67 5.2.8.7 System Pressure Tests 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 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 5.4.1.1 Codes and Specifications 5.4-1 5.4.1.2 Design Transients 5.4-1 5.4.1.3 Protection Against Non-Ductile Failure 5.4-2 5.4.1.4 Inspection 5.4-2 5.4.2 Description 5.4-2 5.4.2.1 Fabrication Processes 5.4-3 5.4.2.2 Protection of Closure Studs 5.4-4 5.4.3 Evaluation 5.4-4 5.4.3.1 Steady State Stresses 5.4-4 5.4.3.2 Fatigue Analysis Based on Transient Stresses 5.4-4 5.4.3.3 Thermal Stresses Due to Gamma Heating 5.4-4 5.4.3.4 Thermal Stresses Due to Loss of Coolant Accident 5.4-4 5.4.3.5 Heatup and Cooldown 5.4-4 5.4.3.6 Irradiation Surveillance Programs 5.4-4 5.4.3.7 Capability for Annealing the Reactor Vessel 5.4-12 5.4.4 Tests and Inspections 5.4-12 5.4.4.1 Ultrasonic Examinations 5.4-13 5.4.4.2 Penetrant Examinations 5.4-13 5.4.4.3 Magnetic Particle Examination 5.4-13 5.4.4.4 Inservice Inspection 5.4-14 5.5 COMPONENT AND SUBSYSTEM DESIGN 5.5-1 5.5.1 Reactor Coolant Pumps 5.5-1 5.5.1.1 Design Bases 5.5-1 5.5.1.2 Design Description 5.5-1

Table of Contents 1-xxi WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.5.1.3 Design Evaluation 5.5-3 5.5.1.4 Tests and Inspections 5.5-7 5.5.2 Steam Generators 5.5-7 5.5.2.1 Design Basis 5.5-7 5.5.2.2 Design Description 5.5-8 5.5.2.3 Design Evaluation 5.5-9 5.5.2.4 Tests and Inspections 5.5-14 5.5.3 Reactor Coolant Piping 5.5-15 5.5.3.1 Design Bases 5.5-15 5.5.3.2 Design Description 5.5-16 5.5.3.3 Design Evaluation 5.5-18 5.5.3.4 Tests and Inspections 5.5-19 5.5.4 Steam Outlet Flow Restrictor (Steam Generator) 5.5-20 5.5.4.1 Design Basis 5.5-20 5.5.4.2 Description 5.5-20 5.5.4.3 Evaluation 5.5-20 5.5.4.4 Tests and Inspections 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 5.5.6.1 Design Basis 5.5-21 5.5.6.2

System Description

5.5-21 5.5.6.3 Design Evaluation 5.5-22 5.5.7 Residual Heat Removal System 5.5-23 5.5.7.1 Design Bases 5.5-24 5.5.7.2

System Description

5.5-24 5.5.7.3 Design Evaluation 5.5-28 5.5.7.4 Tests and Inspections 5.5-31 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 5.5.10.1 Design Bases 5.5-32 5.5.10.2 Design Description 5.5-33 5.5.10.3 Design Evaluation 5.5-34 5.5.10.4 Tests and Inspections 5.5-36 5.5.11 Pressurizer Relief Tank 5.5-37 5.5.11.1 Design Bases 5.5-37 5.5.11.2 Design Description 5.5-37 5.5.11.3 Design Evaluation 5.5-38 5.5.12 Valves 5.5-38 5.5.12.1 Design Bases 5.5-38 5.5.12.2 Design Description 5.5-39 5.5.12.3 Design Evaluation 5.5-39 5.5.12.4 Tests and Inspections 5.5-39 5.5.13 Safety and Relief Valves 5.5-40

1-xxii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.5.13.1 Design Bases 5.5-40 5.5.13.2 Design Description 5.5-40 5.5.13.3 Design Evaluation 5.5-40 5.5.13.4 Tests and Inspections 5.5-41 5.5.14 Component Supports 5.5-41 5.5.14.1 Design Bases 5.5-41 5.5.14.2 Description 5.5-41 5.5.14.3 Evaluation 5.5-43 5.5.14.4 Tests and Inspections 5.5-43 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 6.1.1.1 Materials Selection and Fabrication 6.1-1 6.1.1.2 Composition, Compatibility, and Stability of Containment and Core Spray Coolants 6.1-2 6.1.2 Organic Materials 6.1-3 6.1.2.1 Electrical Insulation 6.1-3 6.1.2.2 Surface Coatings 6.1-3 6.1.2.3 Ice Condenser Equipment 6.1-4 6.1.2.4 Identification Tags 6.1-4 6.1.2.5 Valves and Instruments within Containment 6.1-4 6.1.2.6 Heating and Ventilating Door Seals 6.1-4 6.1.3 Post-Accident Chemistry 6.1-4 6.1.3.1 Boric Acid, H3BO3 6.1-5 6.1.3.2 Lithium Hydroxide 6.1-5 6.1.3.3 Sodium Tetraborate 6.1-5 6.1.3.4 Final Post-Accident Chemistry 6.1-5 6.1.4 Degree of Compliance with Regulatory Guide 1.54 for Paints and Coatings Inside Containment 6.1-5 6.2 CONTAINMENT SYSTEMS 6.2.1 Containment Functional Design 6.2.1-1 6.2.1.1 Design Bases 6.2.1-1 6.2.1.1.1 Primary Containment Design Bases 6.2.1-1 6.2.1.2 Primary Containment System Design 6.2.1-3 6.2.1.3 Design Evaluation 6.2.1-3 6.2.1.3.1 Primary Containment Evaluation 6.2.1-3 6.2.1.3.2 General Description of Containment Pressure Analysis 6.2.1-4 6.2.1.3.3 Long-Term Containment Pressure Analysis 6.2.1-4

Table of Contents 1-xxiii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.2.1.3.4 Short-Term Blowdown Analysis 6.2.1-8 6.2.1.3.5 Effect of Steam Bypass 6.2.1-17 6.2.1.3.6 Mass and Energy Release Data 6.2.1-20 6.2.1.3.7 Accident Chronology 6.2.1-24 6.2.1.3.8 Energy Balance Tables 6.2.1-24 6.2.1.3.9 Containment Pressure Differentials 6.2.1-24 6.2.1.3.10 Steam Line Break Inside Containment 6.2.1-27 6.2.1.3.11 Maximum Reverse Pressure Differentials 6.2.1-33 6.2.2 CONTAINMENT HEAT REMOVAL SYSTEMS 6.2.2-1 6.2.2.1 Design Bases 6.2.2-1 6.2.2.2

System Design

6.2.2-3 6.2.2.3 Design Evaluation 6.2.2-5 6.2.2.4 Testing and Inspections 6.2.2-7 6.2.2.5 Instrumentation Requirements 6.2.2-8 6.2.2.6 Materials 6.2.2-8 6.2.3 Secondary Containment Functional Design 6.2.3-1 6.2.3.1 Design Bases 6.2.3-1 6.2.3.1.1 Secondary Containment Enclosures 6.2.3-1 6.2.3.1.2 Emergency Gas Treatment System (EGTS) 6.2.3-1 6.2.3.1.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-2 6.2.3.2

System Design

6.2.3-2 6.2.3.2.1 Secondary Containment Enclosures 6.2.3-2 6.2.3.2.2 Emergency Gas Treatment System (EGTS) 6.2.3-7 6.2.3.2.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-10 6.2.3.3 Design Evaluation 6.2.3-12 6.2.3.3.1 Secondary Containment Enclosures 6.2.3-12 6.2.3.3.2 Emergency Gas Treatment System (EGTS) 6.2.3-15 6.2.3.3.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-19 6.2.3.4 Test and Inspections 6.2.3-21 6.2.3.4.1 Emergency Gas Treatment System (EGTS) 6.2.3-21 6.2.3.4.2 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-22 6.2.3.5 Instrumentation Requirements 6.2.3-23 6.2.3.5.1 Emergency Gas Treatment System (EGTS) 6.2.3-23 6.2.3.5.2 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-23 6.2.4 Containment Isolation Systems 6.2.4-1 6.2.4.1 Design Bases 6.2.4-1 6.2.4.2

System Design

6.2.4-4 6.2.4.2.1 Design Requirements 6.2.4-5 6.2.4.2.2 Containment Isolation Operation 6.2.4-5 6.2.4.2.3 Penetration Design 6.2.4-6 6.2.4.3 Design Evaluation 6.2.4-12

1-xxiv Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.2.4.3.1 Possible Leakage Paths 6.2.4-14 6.2.4.4 Tests and Inspections 6.2.4-16 6.2.5 Combustible Gas Control in Containment 6.2.5-1 6.2.5.1 Design Bases 6.2.5-1 6.2.5.2

System Design

6.2.5-2 6.2.5.3 Design Evaluation 6.2.5-5 6.2.5.4 Testing and Inspections 6.2.5-5 6.2.5.5 Instrumentation Application 6.2.5-5 6.2.5.6 Materials 6.2.5-6 6.2.5A Hydrogen Mitigation System 6.2.5-6 6.2.5A.1 Design Basis 6.2.5-6 6.2.5A.2

System Description

6.2.5-6 6.2.5A.3 Operation 6.2.5-7 6.2.5A.4 Safety Evaluation 6.2.5-7 6.2.5A.5 Testing 6.2.5-7 6.2.6 Containment Leakage Testing 6.2.6-1 6.2.6.1 Containment Integrated Leak Rate Test 6.2.6-1 6.2.6.2 Containment Penetration Leakage Rate Test 6.2.6-2 6.2.6.3 Scheduling and Reporting of Periodic Tests 6.2.6-6 6.2.6.4 Special Testing Requirements 6.2.6-6 6.3 EMERGENCY CORE COOLING SYSTEM 6.3-1 6.3.1 Design Bases 6.3-1 6.3.1.1 Range of Coolant Ruptures and Leaks 6.3-1 6.3.1.2 Fission Product Decay Heat 6.3-2 6.3.1.3 Reactivity Required for Cold Shutdown 6.3-2 6.3.1.4 Capability To Meet Functional Requirements 6.3-2 6.3.2

System Design

6.3-2 6.3.2.1 Schematic Piping and Instrumentation Diagrams 6.3-2 6.3.2.2 Equipment and Component Design 6.3-2 6.3.2.3 Applicable Codes and Classifications 6.3-17 6.3.2.4 Materials Specifications and Compatibility 6.3-17 6.3.2.5 Design Pressures and Temperatures 6.3-17 6.3.2.6 Coolant Quantity 6.3-18 6.3.2.7 Pump Characteristics 6.3-18 6.3.2.8 Heat Exchanger Characteristics 6.3-18 6.3.2.9 ECCS Flow Diagrams 6.3-18 6.3.2.10 Relief Valves 6.3-18 6.3.2.11 System Reliability 6.3-18 6.3.2.12 Protection Provisions 6.3-23 6.3.2.13 Provisions for Performance Testing 6.3-23 6.3.2.14 Net Positive Suction Head 6.3-24

Table of Contents 1-xxv WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.3.2.15 Control of Motor-Operated Isolation Valves 6.3-24 6.3.2.16 Motor-Operated Valves and Controls 6.3-25 6.3.2.17 Manual Actions 6.3-25 6.3.2.18 Process Instrumentation 6.3-25 6.3.2.19 Materials 6.3-25 6.3.3 Performance Evaluation 6.3-25 6.3.3.1 Evaluation Model 6.3-25 6.3.3.2 ECCS Performance 6.3-26 6.3.3.3 Alternate Analysis Methods 6.3-26 6.3.3.4 Fuel Rod Perforations 6.3-27 6.3.3.5 Evaluation Model 6.3-27 6.3.3.6 Fuel Clad Effects 6.3-27 6.3.3.7 ECCS Performance 6.3-27 6.3.3.8 Peak Factors 6.3-27 6.3.3.9 Fuel Rod Perforations 6.3-27 6.3.3.10 Conformance with Interim Acceptance Criteria 6.3-27 6.3.3.11 Effects of ECCS Operation on the Core 6.3-28 6.3.3.12 Use of Dual Function Components 6.3-28 6.3.3.13 Lag Times 6.3-30 6.3.3.14 Thermal Shock Considerations 6.3-30 6.3.3.15 Limits on System Parameters 6.3-30 6.3.3.16 Use of RHR Spray 6.3-30 6.3.4 Tests and Inspections 6.3-31 6.3.4.1 Preoperational Tests 6.3-31 6.3.4.2 Component Testing 6.3-32 6.3.4.3 Periodic System Testing 6.3-32 6.3.5 Instrumentation Application 6.3-33 6.3.5.1 Temperature Indication 6.3-33 6.3.5.2 Pressure Indication 6.3-33 6.3.5.3 Flow Indication 6.3-34 6.3.5.4 Level Indication 6.3-34 6.3.5.5 Valve Position Indication 6.3-35 6.4 HABITABILITY SYSTEMS 6.4-1 6.4.1 Design Bases 6.4-1 6.4.2

System Design

6.4-1 6.4.2.1 Definition of MCRHS Area 6.4-1 6.4.2.2 Ventilation System Design 6.4-2 6.4.2.3 Leak Tightness 6.4-2 6.4.2.4 Interaction with Other Zones and Pressure-Containing Equipment 6.4-3 6.4.2.5 Shielding Design 6.4-4 6.4.2.6 Control Room Emergency Provisions 6.4-4 6.4.2.7 MCRHS Fire Protection 6.4-4 6.4.3 System Operational Procedures 6.4-5

1-xxvi Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.4.4 Design Evaluations 6.4-7 6.4.4.1 Radiological Protection 6.4-7 6.4.4.2 Toxic Gas Protection 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 6.5.1.1 Design Bases 6.5-1 6.5.1.2

System Design

6.5-2 6.5.1.3 Design Evaluation 6.5-5 6.5.1.4 Tests and Inspections 6.5-5 6.5.1.5 Instrumentation Requirements 6.5-6 6.5.1.6 Materials 6.5-7 6.5.2 Containment Spray System for Fission Product Cleanup 6.5-8 6.5.2.1 Design Bases 6.5-8 6.5.2.2

System Design

6.5-8 6.5.2.3 Design Evaluation 6.5-8 6.5.2.4 Tests and Inspections 6.5-8 6.5.2.5 Instrumentation Requirements 6.5-8 6.5.2.6 Materials 6.5-8 6.5.3 Fission Product Control Systems 6.5-8 6.5.3.1 Primary Containment 6.5-8 6.5.3.2 Secondary Containments 6.5-10 6.5.4 Ice Condenser as a Fission Product Cleanup System 6.5-10 6.5.4.1 Ice Condenser Design Basis (Fission Product Cleanup Function) 6.5-11 6.5.4.2 Ice Condenser System Design 6.5-11 6.5.4.3 Ice Condenser System Design Evaluation (Fission Product Cleanup Function) 6.5-11 6.5.4.4 Condenser System Tests and Inspections 6.5-13 6.5.4.5 Ice Condenser Materials 6.5-13 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

Table of Contents 1-xxvii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.7.1 Floor Structure and Cooling System 6.7-1 6.7.1.1 Design Bases 6.7-1 6.7.1.2 Design Evaluation 6.7-5 6.7.2 Wall Panels 6.7-8 6.7.2.1 Design Basis 6.7-8 6.7.2.2

System Design

6.7-8 6.7.2.3 Design Evaluation 6.7-9 6.7.3 Lattice Frames and Support Columns 6.7-9 6.7.3.1 Design Basis 6.7-9 6.7.3.2

System Design

6.7-12 6.7.3.3 Design Evaluation 6.7-13 6.7.4 Ice Baskets 6.7-14 6.7.4.1 Design Basis 6.7-14 6.7.4.2

System Design

6.7-15 6.7.4.3 Design Evaluation 6.7-18 6.7.5 Crane and Rail Assembly 6.7-20 6.7.5.1 Design Basis 6.7-20 6.7.5.2

System Design

6.7-20 6.7.5.3 Design Evaluation 6.7-21 6.7.6 Refrigeration System 6.7-21 6.7.6.1 Design Basis 6.7-21 6.7.6.2

System Design

6.7-22 6.7.6.3 Design Evaluation 6.7-25 6.7.7 Air Handling Units 6.7-29 6.7.7.1 Design Basis 6.7-29 6.7.7.2

System Design

6.7-30 6.7.7.3 Design Evaluation 6.7-31 6.7.8 Lower Inlet Doors 6.7-31 6.7.8.1 Design Basis 6.7-31 6.7.8.2

System Design

6.7-34 6.7.8.3 Design Evaluation 6.7-36 6.7.9 Lower Support Structure 6.7-37 6.7.9.1 Design Basis 6.7-37 6.7.9.2

System Design

6.7-39 6.7.9.3 Design Evaluation 6.7-40 6.7.10 Top Deck and Doors 6.7-49 6.7.10.1 Design Basis 6.7-49 6.7.10.2

System Design

6.7-51 6.7.11 Intermediate Deck and Doors 6.7-54 6.7.11.1 Design Basis 6.7-54 6.7.11.2

System Design

6.7-55 6.7.11.3 Design Evaluation 6.7-56 6.7.12 Air Distribution Ducts 6.7-57 6.7.12.1 Design Basis 6.7-57

1-xxviii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.7.12.2

System Design

6.7-58 6.7.12.3 Design Evaluation 6.7-58 6.7.13 Equipment Access Door 6.7-58 6.7.13.1 Design Basis 6.7-58 6.7.13.2

System Design

6.7-59 6.7.13.3 Design Evaluation 6.7-59 6.7.14 Ice Technology, Ice Performance, and Ice Chemistry 6.7-59 6.7.14.1 Design Basis 6.7-59 6.7.14.2

System Design

6.7-59 6.7.14.3 Design Evaluation 6.7-60 6.7.15 Ice Condenser Instrumentation 6.7-65 6.7.15.1 Design Basis 6.7-65 6.7.15.2 Design Description 6.7-66 6.7.15.3 Design Evaluation 6.7-67 6.7.16 Ice Condenser Structural Design 6.7-68 6.7.16.1 Applicable Codes, Standards, and Specifications 6.7-68 6.7.16.2 Loads and Loading Combinations 6.7-68 6.7.16.3 Design and Analytical Procedures 6.7-68 6.7.16.4 Structural Acceptance Criteria 6.7-69 6.7.17 Seismic Analysis 6.7-70 6.7.17.1 Seismic Analysis Methods 6.7-70 6.7.17.2 Seismic Load Development 6.7-73 6.7.17.3 Vertical Seismic Response 6.7-74 6.7.18 Materials 6.7-74 6.7.18.1 Design Criteria 6.7-74 6.7.18.2 Environmental Effects 6.7-75 6.7.18.3 Compliance with 10 CFR 50, Appendix B 6.7-76 6.7.18.4 Materials Specifications 6.7-77 6.7.19 Tests and Inspections 6.7-78 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 6.8-3 017_TVA_WB_FSAR_Section_7.pdf 7.0 INSTRUMENTATION AND CONTROLS

7.1 INTRODUCTION

7.1-1 7.1.1 Identification of Safety-Related Systems 7.1-4 7.1.1.1 Safety-Related Systems 7.1-4 7.1.1.2 Safety-Related Display Instrumentation 7.1-5 7.1.1.3 Instrumentation and Control System Designers 7.1-5

Table of Contents 1-xxix WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.1.1.4 Plant Comparison 7.1-5 7.1.2 Identification of Safety Criteria 7.1-5 7.1.2.1 Design Bases 7.1-8 7.1.2.2 Independence of Redundant Safety-Related Systems 7.1-12 7.1.2.3 Physical Identification of Safety-Related Equipment 7.1-15 7.1.2.4 Process Signal Isolation Relays 7.1-17 7.2 REACTOR TRIP SYSTEM 7.2-1 7.2.1 Description 7.2-1 7.2.1.1

System Description

7.2-1 7.2.1.2 Design Bases Information 7.2-17 7.2.1.3 Final Systems Drawings 7.2-19 7.2.2 Analyses 7.2-19 7.2.2.1 Evaluation of Design Limits 7.2-20 7.2.2.2 Evaluation of Compliance to Applicable Codes and Standards 7.2-23 7.2.2.3 Specific Control and Protection Interactions 7.2-33 7.2.2.4 Additional Postulated Accidents 7.2-36 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 7.3.1.1

System Description

7.3-1 7.3.1.2 Design Bases Information 7.3-6 7.3.1.3 Final System Drawings 7.3-8 7.3.2 Analysis 7.3-8 7.3.2.1 System Reliability/Availability and Failure Mode and Effect Analyses 7.3-8 7.3.2.2 Compliance With Standards and Design Criteria 7.3-9 7.3.2.3 Further Considerations 7.3-16 7.3.2.4 Summary 7.3-17 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.4-1 7.4.1 Description 7.4-1 7.4.1.1 Monitoring Indicators 7.4-1 7.4.1.2 Controls 7.4-2 7.4.1.3 Equipment and Systems Available for Cold Shutdown 7.4-6 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 7.5.1.1

System Description

7.5-1 7.5.1.2 Variable Types 7.5-1 7.5.1.3 Variable Categories 7.5-2 7.5.1.4 Design Bases 7.5-3 7.5.1.5 General Requirements 7.5-6

1-xxx Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.5.1.6 Analysis 7.5-7 7.5.1.7 Tests and Inspections 7.5-7 7.5.2 Emergency Response Facilities Data System (ERFDS) 7.5-8 7.5.2.1 Safety Parameter Display System 7.5-8 7.5.2.2 Bypassed and Inoperable Status Indication System (BISI) 7.5-10 7.5.2.3 Technical Support Center and Nuclear Data Links 7.5-13 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 7.6.2.1 Description 7.6-1 7.6.2.2 Analysis 7.6-2 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 7.6.8.1 Analysis of Interlock 7.6-7 7.6.9 Switchover From Injection to Recirculation 7.6-8 7.6.9.1 Description of Instrumentation Used for Switchover 7.6-8 7.6.9.2 Initiation Circuit 7.6-9 7.6.9.3 Logic 7.6-9 7.6.9.4 Bypass 7.6-9 7.6.9.5 Interlocks 7.6-9 7.6.9.6 Sequence 7.6-10 7.6.9.7 Redundancy 7.6-10 7.6.9.8 Diversity 7.6-10 7.6.9.9 Actuated Devices 7.6-10 7.7 CONTROL SYSTEMS 7.7-1 7.7.1 Description 7.7-1 7.7.1.1 Control Rod Drive Reactor Control System 7.7-1 7.7.1.3 Plant Control Signals for Monitoring and Indicating 7.7-8 7.7.1.4 Plant Control System Interlocks 7.7-12 7.7.1.5 Pressurizer Pressure Control 7.7-13 7.7.1.6 Pressurizer Water Level Control 7.7-13 7.7.1.7 Steam Generator Water Level Control 7.7-14 7.7.1.8 Steam Dump Control 7.7-14 7.7.1.9 Incore Instrumentation 7.7-16 7.7.1.10 Control Board 7.7-18 7.7.1.11 Boron Concentration Measurement System 7.7-18 7.7.1.12 Anticipated Transient Without Scram Mitigation System Actuation 7.7-19 7.7.2 Analysis 7.7-20

Table of Contents 1-xxxi WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.7.2.1 Separation of Protection and Control System 7.7-21 7.7.2.2 Response Considerations of Reactivity 7.7-21 7.7.2.3 Step Load Changes Without Steam Dump 7.7-24 7.7.2.4 Loading and Unloading 7.7-24 7.7.2.5 Load Rejection Furnished By Steam Dump System 7.7-25 7.7.2.6 Turbine-Generator Trip With Reactor Trip 7.7-25 7.7.3 Deleted by Amendment 81 7.7-26 7A INSTRUMENTATION IDENTIFICATIONS AND SYMBOLS 7A.1 IDENTIFICATION SYSTEM 7A.1-1 7A.1.1 FUNCTIONAL IDENTIFICATION 7A.1-1 7A.1.1.1 Principal Function 7A.1-1 7A.1.1.2 Measured Variable 7A.1-2 7A.1.1.3 Readout or Passive Functions 7A.1-2 7A.1.1.4 Modifying Letters 7A.1-2 7A.1.1.5 Tagging Symbols 7A.1-2 7A.1.1.6 Special Identifying Letters 7A.1-2 7A.1.1.7 Pilot Lights 7A.1-2 7A.1.2 SYSTEM IDENTIFICATION 7A.1-3 7A.1.2.1 Identification Numbers 7A.1-3 7A.1.3 LOOP IDENTIFICATION 7A.1-3 7A.1.3.1 Instruments Common to Multiple Control Loops 7A.1-3 7A.1.3.2 Multiple Instruments with a Common Function 7A.1-3 7A.2 SYMBOLS 7A.1-3 7A.2.1 INSTRUMENT SYMBOL 7A.1-4 018_TVA_WB_FSAR_Section_8 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 8.1.5.1 Design Criteria 8.1-5 8.1.5.2 Other Standards and Guides 8.1-5 8.1.5.3 Compliance to Regulatory Guides and IEEE Standards 8.1-8 8.2 OFFSITE (PREFERRED) POWER SYSTEM 8.2-1 8.2.1 Description 8.2-1 8.2.1.1 Preferred Power Supply 8.2-1 8.2.1.2 Transmission Lines, Switchyard, and Transformers 8.2-3

1-xxxii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 8.2.1.3 Arrangement of the Start Boards, Unit Boards, Common Boards, and Reactor Coolant Pump (RCP) Boards 8.2-4 8.2.1.4 Arrangement of Electrical Control Area (Nuclear Plant) 8.2-5 8.2.1.5 Switchyard Control and Relaying 8.2-6 8.2.1.6 6.9-kV Start Boards Control and Relaying 8.2-8 8.2.1.7 6.9-kV Unit and RCP Board Control and Relaying 8.2-10 8.2.1.8 Conformance with Standards 8.2-11 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 8.3.1.1 Description 8.3-1 8.3.1.2 Analysis 8.3-28 8.3.1.3 Physical Identification of Safety-Related Equipment in AC Power Systems 8.3-38 8.3.1.4 Independence of Redundant ac Power Systems 8.3-38 8.3.2 DC Power System 8.3-55 8.3.2.1 Description 8.3-55 8.3.2.2 Analysis of Vital 125V DC Control Power Supply System 8.3-63 8.3.2.3 Physical Identification of Safety-Related Equipment in dc Power Systems 8.3-68 8.3.2.4 Independence of Redundant DC Power Systems 8.3-68 8.3.2.5 Sharing of Batteries Between Units 8.3-68 8.3.3 Fire Protection for Cable Systems 8.3-70

Table of Contents 1-xxxiii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 Deleted by Amendment 75 8C-1 8D IEEE STD 387-1984 FOR DIESEL-GENERATING UNITS APPLIED AS STAND-BY POWER 8D-1 8E Probability/Reliability Analysis of Protection Device Schemes for Associated and Non-Class 1E Cables 8E-1 9.0 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 9.1-1 9.1.1 New Fuel Storage 9.1-1 9.1.1.1 Design Bases 9.1-1 9.1.1.2 Facilities Description 9.1-1 9.1.1.3 Safety Evaluation 9.1-1 9.1.2 SPENT FUEL STORAGE 9.1-2 9.1.2.1 Design Bases 9.1-2 9.1.2.2 Facilities Description 9.1-2 9.1.2.3 Safety Evaluation 9.1-3 9.1.2.4 Materials 9.1-4 9.1.3 Spent Fuel Pool Cooling and Cleanup System (SFPCCS) 9.1-4 9.1.3.1 Design Bases 9.1-4 9.1.3.2

System Description

9.1-5 9.1.3.3 Safety Evaluation 9.1-8 9.1.3.4 Tests and Inspections 9.1-11 9.1.3.5 Instrument Application 9.1-11 9.1.4 FUEL HANDLING SYSTEM 9.1-12 9.1.4.1 Design Bases 9.1-12 9.1.4.2

System Description

9.1-13 9.1.4.3 Design Evaluation 9.1-20 9.1.4.4 Tests and Inspections 9.1-26 9.2 WATER SYSTEMS 9.2-1 9.2.1 Essential Raw Cooling Water (ERCW) 9.2-1 9.2.1.1 Design Bases 9.2-1 9.2.1.2

System Description

9.2-1 9.2.1.3 Safety Evaluation 9.2-4

1-xxxiv Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.2.1.4 Tests and Inspections 9.2-7 9.2.1.5 Instrument Applications 9.2-7 9.2.1.6 Corrosion, Organic Fouling, and Environmental Qualification 9.2-9 9.2.1.7 Design Codes 9.2-11 9.2.2 Component Cooling System (CCS) 9.2-11 9.2.2.1 Design Bases 9.2-11 9.2.2.2

System Description

9.2-13 9.2.2.3 Components 9.2-16 9.2.2.4 Safety Evaluation 9.2-19 9.2.2.5 Leakage Provisions 9.2-19 9.2.2.6 Incidental Control 9.2-20 9.2.2.7 Instrument Applications 9.2-20 9.2.2.8 Malfunction Analysis 9.2-22 9.2.2.9 Tests and Inspections 9.2-23 9.2.2.10 Codes and Classification 9.2-23 9.2.3 Demineralized Water Makeup System 9.2-23 9.2.3.1 Design Bases 9.2-23 9.2.3.2

System Description

9.2-24 9.2.3.3 Safety Evaluation 9.2-25 9.2.3.4 Test and Inspection 9.2-25 9.2.3.5 Instrumentation Applications 9.2-25 9.2.4 Potable and Sanitary Water Systems 9.2-26 9.2.4.1 Potable Water System 9.2-26 9.2.4.2 Sanitary Water System 9.2-27 9.2.5 Ultimate Heat Sink 9.2-30 9.2.5.1 General Description 9.2-30 9.2.5.2 Design Bases 9.2-31 9.2.5.3 Safety Evaluation 9.2-32 9.2.5.4 Instrumentation Application 9.2-33 9.2.6 Condensate Storage Facilities 9.2-33 9.2.6.1 Design Bases 9.2-34 9.2.6.2

System Description

9.2-34 9.2.6.3 Safety Evaluation 9.2-35 9.2.6.4 Test and Inspections 9.2-35 9.2.6.5 Instrument Applications 9.2-36 9.2.7 Refueling Water Storage Tank 9.2-36 9.2.7.1 ECCS Pumps Net Positive Suction Head (NPSH) 9.2-37 9.2.8 Raw Cooling Water System 9.2-39 9.2.8.1 Design Bases 9.2-39 9.2.8.2

System Description

9.2-40 9.2.8.3 Safety Evaluation 9.2-42 9.2.8.4 Tests and Inspection 9.2-42 9.3 PROCESS AUXILIARIES 9.3-1

Table of Contents 1-xxxv WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.3.1 Compressed Air System 9.3-1 9.3.1.1 Design Basis 9.3-1 9.3.1.2

System Description

9.3-1 9.3.1.3 Safety Evaluation 9.3-2 9.3.1.4 Tests and Inspections 9.3-5 9.3.1.5 Instrumentation Applications 9.3-5 9.3.2 Process Sampling System 9.3-5 9.3.2.1 Design Basis 9.3-5 9.3.2.2

System Description

9.3-5 9.3.2.3 Safety Evaluation 9.3-8 9.3.2.4 Tests and Inspections 9.3-8 9.3.2.5 Instrumentation Applications 9.3-8 9.3.2.6 Postaccident Sampling Subsystem 9.3-8 9.3.3 Equipment and Floor Drainage System 9.3-12 9.3.3.1 Design Bases 9.3-12 9.3.3.2

System Design

9.3-12 9.3.3.3 Drains - Reactor Building 9.3-15 9.3.3.4 Design Evaluation 9.3-15 9.3.3.5 Tests and Inspections 9.3-15 9.3.3.6 Instrumentation Application 9.3-15 9.3.3.7 Drain List 9.3-15 9.3.4 Chemical and Volume Control System 9.3-16 9.3.4.1 Design Bases 9.3-16 9.3.4.2

System Description

9.3-18 9.3.4.3 Safety Evaluation 9.3-36 9.3.4.4 Tests and Inspections 9.3-38 9.3.4.5 Instrumentation Application 9.3-39 9.3.5 Failed Fuel Detection System 9.3-39 9.3.5.1 Design Bases 9.3-39 9.3.5.2

System Description

9.3-40 9.3.5.3 Safety Evaluation 9.3-40 9.3.5.4 Tests and Inspections 9.3-40 9.3.5.5 Instrument Applications 9.3-40 9.3.6 Auxiliary Charging System 9.3-40 9.3.6.1 Design Bases 9.3-40 9.3.6.2 System Design Description 9.3-41 9.3.6.3 Design Evaluation 9.3-42 9.3.6.4 Tests and Inspection 9.3-42 9.3.6.5 Instrument Application 9.3-42 9.3.7 Boron Recycle System 9.3-42 9.3.7.1 Design Bases 9.3-43 9.3.7.2

System Description

9.3-44 9.3.7.3 Safety Evaluation 9.3-50 9.3.7.4 Tests and Inspections 9.3-50

1-xxxvi Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.3.7.5 Instrumentation Application 9.3-50 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 9.4.1.1 Design Bases 9.4-1 9.4.1.2

System Description

9.4-3 9.4.1.3 Safety Evaluation 9.4-7 9.4.1.4 Tests and Inspection 9.4-8 9.4.2 Fuel Handling Area Ventilation System 9.4-8 9.4.2.1 Design Bases 9.4-8 9.4.2.2

System Description

9.4-10 9.4.2.3 Safety Evaluation 9.4-10 9.4.2.4 Inspection and Testing 9.4-11 9.4.3 Auxiliary and Radwaste Area Ventilation System 9.4-12 9.4.3.1 Design Bases 9.4-12 9.4.3.2

System Description

9.4-13 9.4.3.3 Safety Evaluation 9.4-19 9.4.3.4 Inspection and Testing Requirements 9.4-23 9.4.4 Turbine Building Area Ventilation System 9.4-23 9.4.4.1 Design Bases 9.4-23 9.4.4.2

System Description

9.4-24 9.4.4.3 Safety Evaluation 9.4-26 9.4.4.4 Inspection and Testing Requirements 9.4-26 9.4.5 Engineered Safety Feature Ventilation Systems 9.4-26 9.4.5.1 ERCW Intake Pumping Station 9.4-26 9.4.5.2 Diesel Generator Buildings 9.4-29 9.4.5.3 Auxiliary Building Safety Features Equipment Coolers 9.4-36 9.4.6 Reactor Building Purge Ventilating System 9.4-39 9.4.6.1 Design Bases 9.4-39 9.4.6.2

System Description

9.4-41 9.4.6.3 Safety Evaluation 9.4-43 9.4.6.4 Inspection and Testing Requirements 9.4-44 9.4.7 Containment Air Cooling System 9.4-45 9.4.7.1 Design Bases 9.4-45 9.4.7.2

System Description

9.4-46 9.4.7.3 Safety Evaluation 9.4-48 9.4.7.4 Test and Inspection Requirements 9.4-48 9.4.8 Condensate Demineralizer Waste Evaporator Building Environmental Control Sys-tem (Not required for Unit 1 operation) 9.4-49 9.4.8.1 Design Basis 9.4-49 9.4.8.2

System Description

9.4-49 9.4.8.3 Safety Evaluation 9.4-50

Table of Contents 1-xxxvii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.4.8.4 Inspection and Testing Requirements 9.4-50 9.4.9 Postaccident Sampling Facility Environmental Control System 9.4-50 9.4.9.1 Design Basis 9.4-50 9.4.9.2

System Description

9.4-50 9.4.9.3 Safety Evaluation 9.4-51 9.4.9.4 Inspection and Testing Requirements 9.4-51 9.5 OTHER AUXILIARY SYSTEMS 9.5-1 9.5.1 Fire Protection System 9.5-1 9.5.1.1 Deleted by Amendment 87 9.5-1 9.5.1.2 Deleted by Amendment 87 9.5-1 9.5.1.3 Deleted by Amendment 87 9.5-1 9.5.1.4 Deleted by Amendment 87 9.5-1 9.5.1.5 Deleted by Amendment 87 9.5-1 9.5.2 Plant Communications System 9.5-1 9.5.2.1 Design Bases 9.5-1 9.5.2.2 General Description Intraplant Communications 9.5-1 9.5.2.3 General Description Interplant System 9.5-4 9.5.2.4 Evaluation 9.5-5 9.5.2.5 Inspection and Tests 9.5-8 9.5.3 Lighting Systems 9.5-9 9.5.3.1 Design Bases 9.5-9 9.5.3.2 Description of the Plant Lighting System 9.5-10 9.5.3.3 Diesel Generator Building Lighting System 9.5-11 9.5.3.4 Safety Related Functions of the Lighting Systems 9.5-12 9.5.3.5 Inspection and Testing Requirements 9.5-13 9.5.4 Diesel Generator Fuel Oil Storage and Transfer System 9.5-13 9.5.4.1 Design Basis 9.5-13 9.5.4.2

System Description

9.5-14 9.5.4.3 Safety Evaluation 9.5-16 9.5.4.4 Tests and Inspections 9.5-17 9.5.5 Diesel Generator Cooling Water System 9.5-18 9.5.5.1 Design Bases 9.5-18 9.5.5.2

System Description

9.5-18 9.5.5.3 Safety Evaluation 9.5-19 9.5.5.4 Tests and Inspections 9.5-19 9.5.6 Diesel Generator Starting System 9.5-19 9.5.6.1 Design Bases 9.5-19 9.5.6.2

System Description

9.5-20 9.5.6.3 Safety Evaluation 9.5-21 9.5.6.4 Tests and Inspections 9.5-21 9.5.7 Diesel Engine Lubrication System 9.5-21 9.5.7.1 Design Bases 9.5-21 9.5.7.2

System Description

9.5-23

1-xxxviii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.5.7.3 Safety Evaluation 9.5-25 9.5.7.4 Test and Inspections 9.5-25 9.5.8 Diesel Generator Combustion Air Intake and Exhaust System 9.5-25 9.5.8.1 Design Bases 9.5-25 9.5.8.2 System Descriptions 9.5-25 9.5.8.3 Safety Evaluation 9.5-26 9.5.8.4 Tests and Inspection 9.5-27 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 10.2.3.1 Materials Selection 10.2-5 10.2.3.2 Fracture Toughness 10.2-7 10.2.3.3 High Temperature Properties 10.2-9 10.2.3.4 Turbine Disc Design 10.2-9 10.2.3.5 Preservice Inspection 10.2-9 10.2.3.6 Inservice Inspection 10.2-11 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 10.3.2.1

System Design

10.3-1 10.3.2.2 Material Compatibility, Codes, and Standards 10.3-2 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 10.3.5.1 Purpose 10.3-3 10.3.5.2 Feedwater Chemistry Specifications 10.3-4 10.3.5.3 Operating Modes 10.3-4 10.3.5.4 Effect of Water Chemistry on the Radioactive Iodine Partition Coefficient 10.3-5 10.3.6 Steam and Feedwater System Materials 10.3-5 10.3.6.1 Fracture Toughness 10.3-5 10.3.6.2 Materials Selection and Fabrication 10.3-5 10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-1 10.4.1 Main Condenser 10.4-1 10.4.1.1 Design Bases 10.4-1

Table of Contents 1-xxxix WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 10.4.1.2

System Description

10.4-1 10.4.1.3 Safety Evaluation 10.4-4 10.4.1.4 Inspection and Testing 10.4-5 10.4.1.5 Instrumentation 10.4-5 10.4.2 Main Condenser Evacuation System 10.4-5 10.4.2.1 Design Bases 10.4-5 10.4.2.2

System Description

10.4-5 10.4.2.3 Safety Evaluation 10.4-6 10.4.2.4 Inspection and Testing 10.4-6 10.4.2.5 Instrumentation 10.4-6 10.4.3 Turbine Gland Sealing System 10.4-7 10.4.3.1 Design Bases 10.4-7 10.4.3.2

System Description

10.4-7 10.4.3.3 Safety Evaluation 10.4-7 10.4.3.4 Inspection and Testing 10.4-8 10.4.3.5 Instrumentation 10.4-8 10.4.4 Turbine Bypass System 10.4-8 10.4.4.1 Design Bases 10.4-8 10.4.4.2

System Description

10.4-8 10.4.4.3 Safety Evaluation 10.4-9 10.4.4.4 Inspection and Testing 10.4-10 10.4.5 Condenser Circulating Water System 10.4-10 10.4.5.1 Design Basis 10.4-11 10.4.5.2

System Description

10.4-11 10.4.5.3 Safety Evaluation 10.4-13 10.4.5.4 Inspection and Testing 10.4-14 10.4.5.5 Instrumentation Application 10.4-14 10.4.6 Condensate Polishing Demineralizer System 10.4-15 10.4.6.1 Design Bases - Power Conversion 10.4-15 10.4.6.2

System Description

10.4-15 10.4.6.3 Safety Evaluation 10.4-17 10.4.6.4 Inspection and Testing 10.4-18 10.4.6.5 Instrumentation 10.4-18 10.4.7 Condensate and Feedwater Systems 10.4-19 10.4.7.1 Design Bases 10.4-19 10.4.7.2

System Description

10.4-19 10.4.7.3 Safety Evaluation 10.4-26 10.4.7.4 Inspection and Testing 10.4-28 10.4.7.5 Instrumentation 10.4-28 10.4.8 Steam Generator Blowdown System 10.4-28 10.4.8.1 Design Bases 10.4-28 10.4.8.2 System Description and Operation 10.4-30 10.4.8.3 Safety Evaluation 10.4-30 10.4.8.4 Inspections and Testing 10.4-31

1-xl Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 10.4.9 Auxiliary Feedwater System 10.4-32 10.4.9.1 Design Bases 10.4-32 10.4.9.2

System Description

10.4-32 10.4.9.3 Safety Evaluation 10.4-34 10.4.9.4 Inspection and Testing Requirements 10.4-37 10.4.9.5 Instrumentation Requirements 10.4-37 10.4.10 Heater Drains and Vents 10.4-38 10.4.10.1 Design Bases 10.4-38 10.4.10.2

System Description

10.4-38 10.4.10.3 Safety Evaluation 10.4-43 10.4.10.4 Inspection and Testing 10.4-44 10.4.10.5 Instrumentation 10.4-44 10.4.11 Steam Generator Wet Layup System 10.4-44 10.4.11.1 Design Bases 10.4-44 10.4.11.2

System Description

10.4-44 10.4.11.3 Safety Evaluation 10.4-45 10.4.11.4 Inspection and Testing 10.4-45 10.4.11.5 Instrumentation 10.4-45 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 11.1.1.1 Reactor Coolant Historical Design Activity 11.1-1 11.1.1.2 Volume Control Tank Historical Design Activity 11.1-2 11.1.1.3 Pressurizer Historical Design Activity 11.1-2 11.1.1.4 Gaseous Waste Processing System Historical Design Activities 11.1-2 11.1.1.5 Secondary Coolant Historical Design Activities 11.1-2 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 11.2.3.1 Component Design 11.2-5 11.2.3.2 Instrumentation Design 11.2-11 11.2.4 Operating Procedure 11.2-11 11.2.5 PERFORMANCE TESTS 11.2-18 11.2.6 ESTIMATED RELEASES 11.2-18 11.2.6.1 NRC Requirements 11.2-18 11.2.6.2 Westinghouse PWR Release Experience 11.2-19 11.2.6.3 Expected Liquid Waste Processing System Releases 11.2-19

Table of Contents 1-xli WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 11.2.6.4 Turbine Building (TB) Drains 11.2-19 11.2.6.5 Estimated Total Liquid Releases 11.2-20 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 11.2.9.1 Assumptions and Calculational Methods 11.2-21 11.2.9.2 Summary of Dose from Radionuclides in Liquid Effluents 11.2-23 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 11.3.3.1 Component Design 11.3-3 11.3.3.2 Instrumentation 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 11.3.7.1 NRC Requirements 11.3-6 11.3.7.2 Westinghouse PWR Experience Releases 11.3-6 11.3.7.3 Expected Gaseous Waste Processing System Releases 11.3-6 11.3.7.4 Releases from Ventilation Systems 11.3-7 11.3.7.5 Estimated Total Releases 11.3-7 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 11.3.10.1 Assumptions and Calculational Methods 11.3-9 11.3.10.2 Summary of Annual Population Doses 11.3-11 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 11.4.2.1 Liquid Monitors 11.4-2 11.4.2.2 Gaseous Monitors 11.4-4 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 11.5.3.1 Wet Active Waste Handling 11.5-1

1-xlii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 11.5.3.2 Dry Active Waste Handling 11.5-3 11.5.3.3 Miscellaneous Waste Handling 11.5-4 11.5.4 Equipment Operation 11.5-4 11.5.4.1 Deleted 11.5-4 11.5.4.2 Mobile Solidification System (MSS) 11.5-4 11.5.5 Storage Facilities 11.5-4 11.5.5.1 Inplant Storage Area 11.5-4 11.5.5.2 Outside Radwaste Storage 11.5-5 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 11.6.2.1 Doses from Gaseous Effluents 11.6-3 11.6.2.2 Internal Doses from Liquid Effluents 11.6-3 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 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

Table of Contents 1-xliii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 12.2.1.1 Primary System Sources 12.2-3 12.2.1.2 Auxiliary Systems Sources 12.2-4 12.2.1.3 Sources During Refueling 12.2-10 12.2.1.4 Maximum Hypothetical Accident (MHA) Sources 12.2-10 12.2.1.5 Condensate Demineralizer Waste Evaporator 12.2-11 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 12.3.2.1 Design Objectives 12.3-3 12.3.2.2 Design Description 12.3-3 12.3.3 Ventilation 12.3-15 12.3.3.1 Airflow Control 12.3-15 12.3.3.2 Typical System 12.3-15 12.3.3.3 Additional Radiation Controls 12.3-16 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation 12.3-17 12.3.4.1 Area Radiation Monitoring Instrumentation 12.3-17 12.3.4.2 Airborne Particulate Radioactivity Monitoring 12.3-19 12.3.4.3 Deleted by Amendment 84.

12.3-23 12.3.4.4 Special Radiation Monitors 12.3-23 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 12.5-4 024_TVA_WB_FSAR_Section_13.pdf 13.0 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE OF APPLICANT 13.1-1 13.1.1 Corporate Organization 13.1-1 13.1.1.1 Design Responsibilities 13.1-1 13.1.2 Nuclear Power 13.1-1 13.1.2.1 Offsite Organizations 13.1-1 13.1.2.2 Onsite Organization 13.1-2 13.1.3 Qualification Requirements for Nuclear Facility Personnel 13.1-2

1-xliv 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 13.5.1.1 Conformance with Regulatory Guide 1.33 13.5-1 13.5.1.2 Preparation of Procedures 13.5-1 13.5.1.3 Administrative Procedures 13.5-2 13.5.2 Operating and Maintenance Procedures 13.5-2 13.5.2.1 Operating Procedures 13.5-2 13.5.2.2 Other Procedures 13.5-3 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 14.2.2.1 Startup and Test Organization 14.2-3 14.2.2.2 Plant Operating Organization 14.2-5 14.2.2.3 Nuclear Assurance 14.2-6 14.2.2.4 Major Participating Organizations 14.2-6 14.2.2.5 Joint Test Group 14.2-7

Table of Contents 1-xlv WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 14.2.2.6 Test Review Group 14.2-8 14.2.2.7 Personnel Qualifications 14.2-9 14.2.3 Test Procedures 14.2-9 14.2.3.1 General 14.2-9 14.2.3.2 Development of Procedures 14.2-10 14.2.3.3 Review and Approval of Test Procedures 14.2-10 14.2.3.4 Format of Test Procedures 14.2-10 14.2.3.5 Test Procedure Revisions/Changes 14.2-11 14.2.4 Conduct of Test Program 14.2-12 14.2.4.1 Administrative Procedures 14.2-12 14.2.4.2 Component Testing 14.2-12 14.2.4.3 Preoperational and Acceptance Testing 14.2-13 14.2.4.4 Power Ascension Testing 14.2-13 14.2.4.5 Test Prerequisites 14.2-13 14.2.4.6 Phase Evaluation 14.2-13 14.2.4.7 Design Modifications 14.2-14 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 14.2.10.1 Fuel Loading 14.2-30 14.2.10.2 Postloading Tests 14.2-33 14.2.10.3 Initial Criticality 14.2-33 14.2.10.4 Low Power Tests 14.2-33 14.2.10.5 Power Ascension 14.2-34 14.2.11 Test Program Schedule 14.2-34 14.2.12 Individual Test Descriptions 14.2-35 14.2.12.1 Preoperational Tests 14.2-35 14.2.12.2 Power Ascension Tests 14.2-36 026_TVA_WB_FSAR_Section_15.pdf 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 15.1.2.1 Power Rating 15.1-3 15.1.2.2 Initial Conditions 15.1-3 15.1.2.3 Power Distribution 15.1-4 15.1.3 Trip Points And Time Delays To Trip Assumed In Accident Analyses 15.1-4

1-xlvi Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 15.1.7.1 Radioactivity in the Core 15.1-7 15.1.7.2 Radioactivity in the Fuel Pellet Clad Gap 15.1-8 15.1.8 Residual Decay Heat 15.1-9 15.1.8.1 Fission Product Decay Energy 15.1-9 15.1.8.2 Decay of U-238 Capture Products 15.1-10 15.1.8.3 Residual Fissions 15.1-11 15.1.8.4 Distribution of Decay Heat Following Loss of Coolant Accident 15.1-11 15.1.9 Computer Codes Utilized 15.1-11 15.1.9.1 FACTRAN 15.1-11 15.1.9.2 Deleted by Amendment 72.

15.1-12 15.1.9.3 MARVEL 15.1-12 15.1.9.4 LOFTRAN 15.1-13 15.1.9.5 LEOPARD 15.1-14 15.1.9.6 TURTLE 15.1-14 15.1.9.7 TWINKLE 15.1-14 15.1.9.8 Deleted by Amendment 80.

15.1-15 15.1.9.9 THINC 15.1-15 15.1.9.10 LOFTTR 15.1-15 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 15.2.1.1 Identification of Causes and Accident Description 15.2-2 15.2.1.2 Analysis of Effects and Consequences 15.2-3 15.2.1.3 Conclusions 15.2-5 15.2.2 UNCONTROLLED ROD CLUSTER CONTROL ASSEMBLY BANK WITH-DRAWAL AT POWER 15.2-5 15.2.2.1 Identification of Causes and Accident Description 15.2-5 15.2.2.2 Analysis of Effects and Consequences 15.2-7 15.2.2.3 Conclusions 15.2-9 15.2.3 ROD CLUSTER CONTROL ASSEMBLY MISALIGNMENT 15.2-9 15.2.3.1 Identification of Causes and Accident Description 15.2-9 15.2.3.2 Analysis of Effects and Consequences 15.2-11 15.2.3.3 Conclusions 15.2-13 15.2.4 UNCONTROLLED BORON DILUTION 15.2-13 15.2.4.1 Identification of Causes and Accident Description 15.2-13 15.2.4.2 Analysis of Effects and Consequences 15.2-14 15.2.4.3 Conclusions 15.2-16 15.2.5 PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW 15.2-17 15.2.5.1 Identification of Causes and Accident Description 15.2-17

Table of Contents 1-xlvii WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 15.2.5.2 Analysis of Effects and Consequences 15.2-18 15.2.5.3 Conclusions 15.2-19 15.2.6 Startup of an Inactive Reactor Coolant Loop 15.2-19 15.2.6.1 Identification of Causes and Accident Description 15.2-19 15.2.6.2 Analysis of Effects and Consequences 15.2-19 15.2.6.3 Conclusions 15.2-21 15.2.7 LOSS OF EXTERNAL ELECTRICAL LOAD AND/OR TURBINE TRIP 15.2-21 15.2.7.1 Identification of Causes and Accident Description 15.2-21 15.2.7.2 Analysis of Effects and Consequences 15.2-22 15.2.7.3 Conclusions 15.2-24 15.2.8 LOSS OF NORMAL FEEDWATER 15.2-24 15.2.8.1 Identification of Causes and Accident Description 15.2-24 15.2.8.2 Analysis of Effects and Consequences 15.2-25 15.2.8.3 Conclusions 15.2-28 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 15.2.10.1 Analysis of Effects and Consequences 15.2-28 15.2.10.2 Conclusions 15.2-31 15.2.11 Excessive Load Increase Incident 15.2-31 15.2.11.1 Identification of Causes and Accident Description 15.2-31 15.2.11.2 Analysis of Effects and Consequences 15.2-32 15.2.11.3 Conclusions 15.2-33 15.2.12 ACCIDENTAL DEPRESSURIZATION OF THE REACTOR COOLANT SYS-TEM 15.2-33 15.2.12.1 Identification of Causes and Accident Description 15.2-33 15.2.12.2 Analysis of Effects and Consequences 15.2-33 15.2.12.3 Conclusions 15.2-34 15.2.13 ACCIDENTAL DEPRESSURIZATION OF THE MAIN STEAM SYSTEM 15.2-34 15.2.13.1 Identification of Causes and Accident Description 15.2-34 15.2.13.2 Analysis of Effects and Consequences 15.2-36 15.2.13.3 Conclusions 15.2-38 15.2.14 Inadvertent Operation of Emergency Core Cooling System 15.2-38 15.2.14.1 Identification of Causes and Accident Description 15.2-38 15.2.14.2 Analysis of Effects and Consequences 15.2-39 15.2.14.3 Conclusions 15.2-42 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 15.3.1.1 Identification of Causes and Accident Description 15.3-1

1-xlviii Table of Contents WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 15.3.1.2 Analysis of Effects and Consequences 15.3-2 15.3.1.3 Reactor Coolant System Pipe Break Results 15.3-3 15.3.1.4 Conclusions - Thermal Analysis 15.3-4 15.3.2 Minor Secondary System Pipe Breaks 15.3-5 15.3.2.1 Identification of Causes and Accident Description 15.3-5 15.3.2.2 Analysis of Effects and Consequences 15.3-5 15.3.2.3 Conclusions 15.3-5 15.3.3 Inadvertent Loading of a Fuel Assembly Into an Improper Position 15.3-5 15.3.3.1 Identification of Causes and Accident Description 15.3-5 15.3.3.2 Analysis of Effects and Consequences 15.3-6 15.3.3.3 Conclusions 15.3-7 15.3.4 Complete Loss of Forced Reactor Coolant Flow 15.3-7 15.3.4.1 Identification of Causes and Accident Description 15.3-7 15.3.4.2 Analysis of Effects and Consequences 15.3-8 15.3.4.3 Conclusions 15.3-9 15.3.5 Waste Gas Decay Tank Rupture 15.3-9 15.3.5.1 Identification of Causes and Accident Description 15.3-9 15.3.5.2 Analysis of Effects and Consequences 15.3-10 15.3.6 Single Rod Cluster Control Assembly Withdrawal at Full Power 15.3-10 15.3.6.1 Identification of Causes and Accident Description 15.3-10 15.3.6.2 Analysis of Effects and Consequences 15.3-11 15.3.6.3 Conclusions 15.3-11 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 15.4.1.1 Thermal Analysis 15.4-3 15.4.1.2 Hydrogen Production and Accumulation 15.4-6 15.4.2 Major Secondary System Pipe Rupture 15.4-12 15.4.2.1 Major Rupture of a Main Steam Line 15.4-12 15.4.2.2 Major Rupture of a Main Feedwater Pipe 15.4-19 15.4.3 Steam Generator Tube Rupture 15.4-23 15.4.3.1 Identification of Causes and Accident Description 15.4-23 15.4.3.2 Analysis of Effects and Consequences 15.4-26 15.4.3.3 Conclusions 15.4-32 15.4.4 Single Reactor Coolant Pump Locked Rotor 15.4-32 15.4.4.1 Identification of Causes and Accident Description 15.4-32 15.4.4.2 Analysis of Effects and Consequences 15.4-32 15.4.4.3 Conclusions 15.4-35 15.4.5 Fuel Handling Accident 15.4-35 15.4.5.1 Identification of Causes and Accident Description 15.4-35 15.4.5.2 Analysis of Effects and Consequences 15.4-35 15.4.6 Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection) 15.4-35 15.4.6.1 Identification of Causes and Accident Description 15.4-35

Table of Contents 1-xlix WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 15.4.6.2 Analysis of Effects and Consequences 15.4-39 15.4.6.3 Conclusions 15.4-43 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 15.5-18 15.5.5 Environmental Consequences of a Postulated Steam Generator Tube Rupture 15.5-19 15.5.6 Environmental Consequences of a Postulated Fuel Handling Accident 15.5-20 15.5.7 Environmental Consequences of a Postulated Rod Ejection Accident 15.5-22 027_TVA_WB_FSAR_Section_16.pdf 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 16.3-1 16.3.1 Discussion 16.3-1 16.3.2 Document Control 16.3-1 16.3.3 Changes to the Relocated Specifications 16.3-1 028_TVA_WB_FSAR_Section_17.0.pdf 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 17.1A WESTINGHOUSE NUCLEAR ENERGY SYSTEM DIVISIONS QUALITY ASSUR-ANCE PLAN 17.1-2 17.2 QUALITY ASSURANCE FOR STATION OPERATION 17.2-1 17.2.1 Identification of Safety-Related Features 17.2-1

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