Latest revision as of 06:39, 14 November 2019

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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)
	v • d • e

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 Table of Contents 1-i

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

1.9-7 005_TVA_WB_FSAR_Section_2_B.pdf 004_TVA_WB_FSAR_Section_2_A.pdf 1-ii Table of Contents

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 Table of Contents 1-iii

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 1-iv Table of Contents

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 Table of Contents 1-v

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 Classification 3.2-3 3.2.3 Code Cases and Code Editions and Addenda 3.2-3 1-vi Table of Contents

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 Table of Contents 1-vii

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 1-viii Table of Contents

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 Table of Contents 1-ix

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 1-x Table of Contents

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 Table of Contents 1-xi

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 1-xii Table of Contents

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 Table of Contents 1-xiii

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 1-xiv Table of Contents

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 Table of Contents 1-xv

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 1-xvi Table of Contents

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 Table of Contents 1-xvii

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 1-xviii Table of Contents

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 Table of Contents 1-xix

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 1-xx Table of Contents

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 Table of Contents 1-xxi

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 1-xxii Table of Contents

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 Table of Contents 1-xxiii

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 1-xxiv Table of Contents

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 Table of Contents 1-xxv

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 1-xxvi Table of Contents

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 Table of Contents 1-xxvii

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 1-xxviii Table of Contents

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 Table of Contents 1-xxix

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 1-xxx Table of Contents

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 Table of Contents 1-xxxi

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 1-xxxii Table of Contents

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 Table of Contents 1-xxxiii

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 1-xxxiv Table of Contents

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 Table of Contents 1-xxxv

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 1-xxxvi Table of Contents

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 Table of Contents 1-xxxvii

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 1-xxxviii Table of Contents

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 Table of Contents 1-xxxix

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 1-xl Table of Contents

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 Table of Contents 1-xli

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 1-xlii Table of Contents

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 Table of Contents 1-xliii

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 1-xliv Table of Contents

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 Table of Contents 1-xlv

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 1-xlvi Table of Contents

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 Table of Contents 1-xlvii

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 1-xlviii Table of Contents

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 Table of Contents 1-xlix

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 | number = ML091400518
 | issue date = 04/30/2009
-| title = Watts Bar, Unit 2 - Final Safety Analysis Report (Fsar), Amendment 93, Table of Contents
+| title = Final Safety Analysis Report (Fsar), Amendment 93, Table of Contents
 | author name =
 | author affiliation = Tennessee Valley Authority
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 =Text=
-{{#Wiki_filter:Table of Contents 1-iWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page003_TVA_WB_FSAR_Section_1.pdf
+{{#Wiki_filter:WATTS BAR                                                                               WBNP-76 TABLE OF CONTENTS Section                                                            Title                 Page 003_TVA_WB_FSAR_Section_1.pdf
-==1.0INTRODUCTION==
+==1.0                                INTRODUCTION==
 AND GENERAL DESCRIPTION OF PLANT
-==1.1INTRODUCTION==
+==1.1                           INTRODUCTION==
-.1-1 1.2GENERAL PLANT DESCRIPTION1.2-11.2.1Site Characteristics1.2-11.2.1.1Location1.2-11.2.1.2Demography1.2-1 1.2.1.3Meteorology1.2-11.2.1.4Hydrology1.2-11.2.1.5Geology1.2-1 1.2.1.6Seismology1.2-21.2.2Facility Description1.2-21.2.2.1Design Criteria1.2-2 1.2.2.2Nuclear Steam Supply System (NSSS)1.2-21.2.2.3Control and Instrumentation1.2-41.2.2.4Fuel Handling System1.2-5 1.2.2.5Waste Processing System1.2-51.2.2.6Steam and Power Conversion System1.2-51.2.2.7Plant Electrical System1.2-6 1.2.2.8Cooling Water1.2-71.2.2.9Component Cooling System1.2-71.2.2.10Chemical and Volume Control System1.2-7 1.2.2.11Sampling and Water Quality System1.2-81.2.2.12Ventilation1.2-91.2.2.13Fire Protection System1.2-9 1.2.2.14Compressed Air Systems1.2-91.2.2.15Engineered Safety Features1.2-91.2.2.16Shared Facilities and Equipment1.2-10 1.2.3General Arrangement of Major Structures and Equipment1.2-131.3COMPARISON TABLES1.3-11.3.1Comparisons With Similar Facility Designs1.3-11.3.2Comparison Of Final And Preliminary Designs1.3-11.4IDENTIFICATION OF AGENTS AND CONTRACTORS1.4-11.5REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION1.5-11.5.117 x 17 Fuel Assembly1.5-11.5.1.1Rod Cluster Control Spider Tests1.5-1 1.5.1.2Grid Tests1.5-11.5.1.3Fuel Assembly Structural Tests1.5-11.5.1.4Guide Tube Tests1.5-2 1-iiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page1.5.1.5Prototype Assembly Tests1.5-21.5.2Heat Transfer Tests (17 x 17)1.5-21.5.2.117 x 17 LOCA Heat Transfer Tests1.5-21.5.2.2Departure from Nucleate Boiling (DNB)1.5-21.6MATERIAL INCORPORATED BY REFERENCE1.6-1 1.7ELECTRICAL, INSTRUMENTATIO N, AND CONTROL DRAWINGS1.7-11.8TECHNICAL QUALIFICATION OF APPLICANT1.8-11.9NUCLEAR PERFORMANCE PLAN1.9-11.9.1Corrective Action Plans1.9-11.9.1.1Cable Issues1.9-11.9.1.2Cable Tray and Cable Tray Supports1.9-1 1.9.1.3Design Baseline and Verification Program (DBVP)1.9-21.9.1.4Electrical Conduit and Conduit Support1.9-21.9.1.5Electrical Issues1.9-2 1.9.1.6Equipment Seismic Qualification1.9-21.9.1.7Fire Protection1.9-31.9.1.8Hanger and Analysis Update Program (HAAUP)1.9-31.9.1.9Heat Code Traceability1.9-31.9.1.10Heating, Ventilation, and Air Conditioning (HVAC) Duct Supports1.9-31.9.1.11Instrument Lines1.9-3 1.9.1.12Prestart Test Program1.9-31.9.1.13QA Records1.9-41.9.1.14Q-LIST1.9-4 1.9.1.15Replacement Items Program (RIP-CAP)1.9-41.9.1.16Seismic Analysis1.9-41.9.1.17Vendor Information1.9-4 1.9.1.18Welding1.9-51.9.2Special Programs (SPs)1.9-51.9.2.1Concrete Quality Program1.9-5 1.9.2.2Containment Cooling1.9-51.9.2.3Detailed Control room Design Review1.9-51.9.2.4Environmental Qualification Program1.9-6 1.9.2.5Master Fuse List1.9-61.9.2.6Mechanical Equipment Qualification1.9-61.9.2.7Microbiologically Induced Corrosion (MIC)1.9-61.9.2.8Moderate Energy Line Break Flooding (MELB)1.9-61.9.2.9Radiation Monitoring System1.9-6 1.9.2.10Soil Liquefaction1.9-71.9.2.11Use-As-Is CAQs1.9-71.
+.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 Table of Contents                                                                            1-i
-==9.3REFERENCES==
+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.
-.9-7004_TVA_WB_FSAR_Section_2_A.pdf005_TVA_WB_FSAR_Section_2_B.pdf 005_TVA_WB_FSAR_Section_2_B.pdf Table of Contents1-iiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.0SITE CHARACTERISTICS2.1GEOGRAPHY AND DEMOGRAPHY2.1-12.1.1Site Location and Description2.1-12.1.1.1Specification of Location2.1-1 2.1.1.2Site Area Map2.1-12.1.1.3Boundaries for Establishing Effluent Limits2.1-22.1.2Exclusion Area Authority And Control2.1-22.1.2.1Authority2.1-22.1.2.2Control of Activities Unrelated to Plant Operation2.1-22.1.2.3Arrangements for Traffic Control2.1-22.1.2.4Abandonment or Relocation of Roads2.1-22.1.3Population Distribution2.1-22.1.3.1Population Within 10 Miles2.1-3 2.1.3.2Population Between 10 and 50 Miles2.1-32.1.3.3Transient Population2.1-42.1.3.4Low Population Zone2.1-4 2.1.3.5Population Center2.1-52.1.3.6Population Density2.1-52.2NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES2.2-12.2.1Location and Route2.2-1 2.2.2Descriptions2.2-12.2.2.1Description of Facilities2.2-12.2.2.2Description of Products and Materials2.2-1 2.2.2.3Pipelines2.2-12.2.2.4Waterways2.2-12.2.2.5Airports2.2-2 2.2.2.6Projections of Industrial Growth2.2-22.2.3Evaluation of Potential Accidents2.2-22.2.
-==3.1REFERENCES==
+==9.3                             REFERENCES==
-.2-32.3METEOROLOGY2.3-12.3.1Regional Climate2.3-1 2.3.1.1Data Sources2.3-12.3.1.2General Climate2.3-12.3.1.3Severe Weather2.3-22.3.2Local Meteorology2.3-52.3.2.1Data Sources2.3-5 2.3.2.2Normal and Extreme Values of Meteorological Parameters2.3-62.3.2.3Potential Influence of the Plant and Its Facilities on Local Meteorology2.3-82.3.2.4Local Meteorological Conditions for Design and Operating Bases2.3-9 1-ivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.3.3Onsite Meteorological Measurements Program2.3-92.3.3.1Preoperational Program2.3-92.3.3.2Operational Meteorological Program2.3-122.3.3.3Onsite Data Summaries of Parameters for Dispersion Meteorology2.3-132.3.4Short-Term (Accident) Diffusion Estimates2.3-142.3.4.1Objective2.3-14 2.3.4.2Calculation Results2.3-172.3.5Long-Term (Routine) Diffusion Estimates2.3-18005_TVA_WB_FSAR_Section_2_B.pdf2.4HYDROLOGIC ENGINEERING2.4-12.4.1Hydrological Description2.4-12.4.1.1Sites and Facilities2.4-1 2.4.1.2Hydrosphere2.4-22.4.2Floods2.4-62.4.2.1Flood History2.4-6 2.4.2.2Flood Design Considerations2.4-72.4.2.3Effects of Local Intense Precipitation2.4-92.4.3Probable Maximum Flood (PMF) on Streams and Rivers2.4-122.4.3.1Probable Maximum Precipitation (PMP)2.4-132.4.3.2Precipitation Losses2.4-142.4.3.3Runoff and Stream Course Model2.4-14 2.4.3.4Probable Maximum Flood Flow2.4-182.4.3.5Water Level Determinations2.4-252.4.3.6Coincident Wind Wave Activity2.4-26 2.4.4Potential Dam Failures, Seismically Induced2.4-282.4.4.1Dam Failure Permutations2.4-282.4.4.2Unsteady Flow Analysis of Potential Dam Failures2.4-402.4.4.3Water Level at Plantsite2.4-402.4.5Probable Maximum Surge and Seiche Flooding2.4-402.4.6Probable Maximum Tsunami Flooding2.4-402.4.7Ice Effects2.4-412.4.8Cooling Water Canals and Reservoirs2.4-422.4.9Channel Diversions2.4-42 2.4.10Flooding Protection Requirements2.4-422.4.11Low Water Considerations2.4-442.4.11.1 Low Flow in Rivers and Streams2.4-442.4.11.2Low Water Resulting From Surges, Seiches, or Tsunami2.4-442.4.11.3Historical Low Water2.4-442.4.11.4Future Control2.4-452.4.11.5Plant Requirements2.4-452.4.12Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents 2.4-462.4.12.1Radioactive Liquid Wastes2.4-462.4.12.2Accidental Slug Releases to Surface Water 2.4-46 Table of Contents 1-vWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.4.12.3Effects on Ground Water2.4-482.4.13Groundwater2.4-492.4.13.1Description and On-Site Use2.4-492.4.13.2 Sources2.4-502.4.13.3Accident Effects2.4-512.4.13.4Monitoring and Safeguard Requirements2.4-522.4.13.5Design Basis for Subsurface Hydrostatic Loading2.4-522.4.14 Flooding Protection Requirements2.4-522.4.14.1Introduction2.4-53 2.4.14.2Plant Operation During Floods Above Grade2.4-542.4.14.3Warning Scheme2.4-562.4.14.4Preparation for Flood Mode2.4-56 2.4.14.5Equipment2.4-582.4.14.6Supplies2.4-592.4.14.7Plant Recovery2.4-59 2.4.14.8Warning Plan2.4-592.4.14.9Basis For Flood Protection Plan In Rainfall Floods2.4-602.4.14.10Basis for Flood Protection Plan in Seismic-Caused Dam Failures2.4-662.4.14.11Special Condition Allowance2.4-682.5GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING
+.9-7 005_TVA_WB_FSAR_Section_2_B.pdf 004_TVA_WB_FSAR_Section_2_A.pdf 1-ii                                                                                               Table of Contents
+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==
+.2-3 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 Table of Contents                                                                                 1-iii
+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 1-iv                                                                                                   Table of Contents
+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
+OF FOUNDATION CONDITIONS                                                                      2.5-1 2.5.1           Basic Geology and Seismic Information                                         2.
 ==SUMMARY==
-DESCRIPTION4.1-14.2MECHANICAL DESIGN4.2-14.2.1Fuel4.2-24.2.1.1Design Bases4.2-24.2.1.2Design Description4.2-5 4.2.1.3Design Evaluation4.2-94.2.1.4Tests and Inspections4.2-184.2.2Reactor Vessel Internals4.2-22 4.2.2.1Design Bases4.2-224.2.2.2Description and Drawings4.2-234.2.2.3Design Loading Conditions4.2-26 4.2.2.4Design Loading Categories4.2-274.2.2.5Design Criteria Basis4.2-284.2.3Reactivity Control System4.2-294.2.3.1Design Bases4.2-294.2.3.2Design Description4.2-32 4.2.3.3 Design Evaluation4.2-424.2.3.4Tests, Verification, and Inspections4.2-524.2.3.5Instrumentation Applications4.2-55 Table of Contents1-xviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page4.3NUCLEAR DESIGN4.3-14.3.1DESIGN BASES4.3-14.3.1.1Fuel Burnup4.3-24.3.1.2Negative Reactivity Feedback s (Reactivity Coefficient)4.3-24.3.1.3Control of Power Distribution4.3-34.3.1.4Maximum Controlled Reactivity Insertion Rate4.3-44.3.1.5Shutdown Margins With Vessel Head in Place4.3-44.3.1.6Shutdown Margin for Refueling4.3-5 4.3.1.7Stability4.3-54.3.1.8Anticipated Transients Without Trip4.3-64.3.2Description4.3-6 4.3.2.1Nuclear Design Description4.3-64.3.2.2Power Distributions4.3-84.3.2.3Reactivity Coefficients4.3-19 4.3.2.4Control Requirements4.3-234.3.2.5Control4.3-254.3.2.6Control Rod Patterns and Reactivity Worth4.3-274.3.2.7Criticality of Fuel Assemblies4.3-284.3.2.8Stability4.3-334.3.2.9Vessel Irradiation4.3-38 4.3.3Analytical Methods4.3-384.3.3.1Fuel Temperature (Doppler) Calculations4.3-394.3.3.2Macroscopic Group Constants4.3-404.3.3.3Spatial Few-Group Diffusion Calculations4.3-414.4THERMAL AND HYDRAULIC DESIGN4.4-14.4.1Design Bases4.4-14.4.1.1Departure from Nucleate Boiling Design Basis4.4-14.4.1.2Fuel Temperature Design Basis4.4-2 4.4.1.3Core Flow Design Basis4.4-24.4.1.4Hydrodynamic Stability Design Bases4.4-34.4.1.5Other Considerations4.4-3 4.4.2Description4.4-34.4.2.1Summary Comparison4.4-34.4.2.2Fuel and Cladding Temperatures4.4-4 4.4.2.3Critical Heat Flux Ratio or Departure from Nucleate Boiling Ratio and Mixing Technology4.4-64.4.2.4Flux Tilt Considerations4.4-134.4.2.5Void Fraction Distribution4.4-144.4.2.6Core Coolant Flow Distribution4.4-14 4.4.2.7Core Pressure Drops and Hydraulic Loads4.4-144.4.2.8Correlation and Physical Data4.4-154.4.2.9Thermal Effects of Operational Transients4.4-17 1-xviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page4.4.2.10Uncertainties in Estimates4.4-184.4.2.11Plant Configuration Data4.4-204.4.3EVALUATION4.4-204.4.3.1Core Hydraulics4.4-204.4.3.2Influence of Power Distribution4.4-224.4.3.3Core Thermal Response4.4-24 4.4.3.4Analytical Techniques4.4-244.4.3.5Hydrodynamic and Flow Power Coupled Instability4.4-264.4.3.6Temperature Transient Effects Analysis4.4-284.4.3.7Potentially Damaging Temperature Effects During Transients4.4-294.4.3.8Energy Release During Fuel Element Burnout4.4-294.4.3.9Deleted4.4-30 4.4.3.10 Fuel Rod Behavior-Effects from Coolant Flow Blockage4.4-304.4.4Testing and Verification4.4-314.4.4.1Tests Prior to Initial Criticality4.4-31 4.4.4.2Initial Power and Plant Operation4.4-314.4.4.3Component and Fuel Inspections4.4-324.4.5Instrumentation Application4.4-32 4.4.5.1Incore Instrumentation4.4-324.4.5.2Overtemperature and Overpower T Instrumentation4.4-324.4.5.3Instrumentation to Limit Maximum Power Output4.4-33014_TVA_WB_FSAR_Section_5.pdf5.0REACTOR COOLANT SYSTEM5.1
+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 1-xvi                                                                                        Table of Contents
+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 Table of Contents                                                                             1-xvii
+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==
-DESCRIPTION5.1-15.1.1Schematic Flow Diagram5.1-65.1.2Piping and Instrumentation Diagrams5.1-6 5.1.3Elevation Drawing5.1-65.2INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY5.2-15.2.1Design of Reactor Coolant Pressure Boundary Components5.2-25.2.1.1Performance Objectives5.2-25.2.1.2Design Parameters5.2-3 5.2.1.3Compliance with 10 CFR Part 50, Section 50.55a5.2-45.2.1.4Applicable Code Cases5.2-45.2.1.5Design Transients5.2-5 5.2.1.6Identification of Active Pumps and Valves5.2-145.2.1.7Design of Active Pumps and Valves5.2-145.2.1.8Inadvertent Operation of Valves5.2-145.2.1.9Stress and Pressure Limits5.2-155.2.1.10Stress Analysis for Structural Adequacy5.2-15 5.2.1.11Analysis Methods For Faulted Conditions5.2-345.2.1.12Protection Against Environmental Factors5.2-345.2.1.13Compliance With Code Requirements5.2-34 Table of Contents1-xixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.2.1.14Stress Analysis For Faulted Conditions Loadings5.2-345.2.1.15Stress Levels in Category I Systems5.2-345.2.1.16Analytical Methods for Stresses in Pumps and Valves5.2-345.2.1.17Analytical Methods for Evaluation of Pump Speed and Bearing Integrity5.2-355.2.1.18Operation of Active Valves Under Transient Loadings5.2-355.2.2Overpressurization Protection5.2-355.2.2.1Location of Pressure Relief Devices5.2-355.2.2.2Mounting of Pressure Relief Devices5.2-355.2.2.3Report on Overpressure Protection5.2-355.2.2.4RCS Pressure Control During Low Temperature Operation5.2-375.2.3General Material Considerations5.2-40 5.2.3.1Material Specifications5.2-405.2.3.2Compatibility With Reactor Coolant5.2-415.2.3.3Compatibility With External Insulation and Environmental Atmosphere5.2-425.2.3.4Chemistry of Reactor Coolant5.2-425.2.4Fracture Toughness5.2-435.2.4.1Compliance With Code Requirements5.2-43 5.2.4.2Acceptable Fracture Energy Levels5.2-435.2.4.3Operating Limitations During Startup and Shutdown5.2-435.2.5Austenitic Stainless Steel5.2-46 5.2.5.1Cleaning and Contamination Protection Procedures5.2-465.2.5.2Solution Heat Treatment Requirements5.2-475.2.5.3Material Inspection Program5.2-48 5.2.5.4Unstablilized Austenitic Stainless Steels5.2-485.2.5.5Prevention of Intergranular Attack of Unstabilized Austenit ic Stainless Steels 5.2-485.2.5.6Retesting Unstabilized Au stenitic Stainless Steel Exposed to Sensitization Temperatures5.2-515.2.5.7Control of Delta Ferrite in Austenitic Stainless Steel Welding5.2-515.2.6Pump Flywheels5.2-535.2.6.1Design Basis5.2-535.2.6.2Fabrication and Inspection5.2-53 5.2.6.3Acceptance Criteria and Compliance with Regulatory Guide 1.145.2-545.2.7RCPB Leakage Detection Systems5.2-555.2.7.1Collection of Identified Leakage5.2-55 5.2.7.2Unidentified Leakage to Containment5.2-565.2.7.3Methods of Detection5.2-565.2.7.4Intersystem Leakage Detection5.2-585.2.7.5Unidentified Leakage System Sensitivity and Response Time5.2-625.2.7.6Seismic Capability5.2-64 5.2.7.7Indicators and Alarms5.2-645.2.7.8Testing5.2-655.2.8Inservice Inspection of ASME Code Class 1 Components5.2-65 1-xxTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.2.8.1Components Subject to Examination and/or Test5.2-655.2.8.2Accessibility5.2-655.2.8.3Examination Techniques and Procedures5.2-675.2.8.4Inspection Intervals5.2-675.2.8.5Examination Categories and Requirements5.2-675.2.8.6Evaluation of Examination Results5.2-675.2.8.7System Pressure Tests5.2-675.3THERMAL HYDRAULIC SYSTEM DESIGN5.3-15.3.1Analytical Methods and Data5.3-15.3.2Operating Restrictions On Pumps5.3-15.3.3Power-Flow Operating Map (BWR)5.3-1 5.3.4Temperature-Power Operating Map5.3-15.3.5Load Following Characteristics5.3-15.3.6Transient Effects5.3-1 5.3.7Thermal and Hydraulic Characteristics Summary Table5.3-15.4REACTOR VESSEL AND APPURTENANCES5.4-15.4.1Design Bases5.4-15.4.1.1Codes and Specifications5.4-15.4.1.2Design Transients5.4-1 5.4.1.3Protection Against Non-Ductile Failure5.4-25.4.1.4Inspection5.4-25.4.2Description5.4-2 5.4.2.1Fabrication Processes5.4-35.4.2.2Protection of Closure Studs5.4-45.4.3Evaluation5.4-4 5.4.3.1Steady State Stresses5.4-45.4.3.2Fatigue Analysis Based on Transient Stresses5.4-45.4.3.3Thermal Stresses Due to Gamma Heating5.4-4 5.4.3.4Thermal Stresses Due to Loss of Coolant Accident5.4-45.4.3.5Heatup and Cooldown5.4-45.4.3.6Irradiation Surveillance Programs5.4-4 5.4.3.7Capability for Annealing the Reactor Vessel5.4-125.4.4Tests and Inspections5.4-125.4.4.1Ultrasonic Examinations5.4-13 5.4.4.2Penetrant Examinations5.4-135.4.4.3Magnetic Particle Examination5.4-135.4.4.4Inservice Inspection5.4-145.5COMPONENT AND SUBSYSTEM DESIGN5.5-15.5.1Reactor Coolant Pumps5.5-15.5.1.1Design Bases5.5-15.5.1.2Design Description5.5-1 Table of Contents1-xxiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.5.1.3Design Evaluation5.5-35.5.1.4Tests and Inspections5.5-75.5.2Steam Generators5.5-75.5.2.1Design Basis5.5-75.5.2.2Design Description5.5-85.5.2.3Design Evaluation5.5-9 5.5.2.4Tests and Inspections5.5-145.5.3Reactor Coolant Piping5.5-155.5.3.1Design Bases5.5-15 5.5.3.2Design Description5.5-165.5.3.3Design Evaluation5.5-185.5.3.4Tests and Inspections5.5-19 5.5.4Steam Outlet Flow Restrictor (Steam Generator)5.5-205.5.4.1Design Basis5.5-205.5.4.2Description5.5-20 5.5.4.3Evaluation5.5-205.5.4.4Tests and Inspections5.5-205.5.5Main Steam Line Isolation System5.5-20 5.5.6Reactor Vessel Head Vent System5.5-215.5.6.1Design Basis5.5-215.5.6.2System Description5.5-21 5.5.6.3Design Evaluation5.5-225.5.7Residual Heat Removal System5.5-235.5.7.1Design Bases5.5-24 5.5.7.2System Description5.5-245.5.7.3Design Evaluation5.5-285.5.7.4Tests and Inspections5.5-31 5.5.8Reactor Coolant Cleanup System5.5-315.5.9Main Steam Line and Feedwater Piping5.5-315.5.10Pressurizer5.5-32 5.5.10.1Design Bases5.5-325.5.10.2Design Description5.5-335.5.10.3Design Evaluation5.5-34 5.5.10.4Tests and Inspections5.5-365.5.11Pressurizer Relief Tank5.5-375.5.11.1Design Bases5.5-37 5.5.11.2Design Description5.5-375.5.11.3Design Evaluation5.5-385.5.12Valves5.5-385.5.12.1Design Bases5.5-385.5.12.2Design Description5.5-39 5.5.12.3Design Evaluation5.5-395.5.12.4Tests and Inspections5.5-395.5.13Safety and Relief Valves5.5-40 1-xxiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.5.13.1Design Bases5.5-405.5.13.2Design Description5.5-405.5.13.3Design Evaluation5.5-405.5.13.4Tests and Inspections5.5-415.5.14Component Supports5.5-415.5.14.1Design Bases5.5-41 5.5.14.2Description5.5-415.5.14.3Evaluation5.5-435.5.14.4Tests and Inspections5.5-435.6INSTRUMENTATION APPLICATION5.6-16.0ENGINEERED SAFETY FEATURES6.1ENGINEERED SAFETY FEATURE MATERIALS6.1-16.1.1Metallic Materials6.1-16.1.1.1Materials Selection and Fabrication6.1-16.1.1.2Composition, Compatibility, and Stabi lity of Containment and Core Spray Coolants 6.1-26.1.2Organic Materials6.1-36.1.2.1Electrical Insulation6.1-3 6.1.2.2Surface Coatings6.1-36.1.2.3Ice Condenser Equipment6.1-46.1.2.4Identification Tags6.1-4 6.1.2.5Valves and Instruments within Containment6.1-46.1.2.6Heating and Ventilating Door Seals6.1-46.1.3Post-Accident Chemistry6.1-4 6.1.3.1Boric Acid, H3BO36.1-56.1.3.2Lithium Hydroxide6.1-56.1.3.3Sodium Tetraborate6.1-5 6.1.3.4Final Post-Accident Chemistry6.1-56.1.4Degree of Compliance with Regulatory Gu ide 1.54 for Paints and Coatings Inside Containment6.1-56.2CONTAINMENT SYSTEMS6.2.1Containment Functional Design6.2.1-16.2.1.1Design Bases6.2.1-16.2.1.1.1Primary Containment Design Bases6.2.1-16.2.1.2Primary Containment System Design6.2.1-36.2.1.3Design Evaluation6.2.1-3 6.2.1.3.1Primary Containment Evaluation6.2.1-36.2.1.3.2General Description of Containment Pressure Analysis6.2.1-46.2.1.3.3Long-Term Containment Pressure Analysis6.2.1-4 Table of Contents1-xxiiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.2.1.3.4Short-Term Blowdown Analysis6.2.1-86.2.1.3.5Effect of Steam Bypass6.2.1-176.2.1.3.6Mass and Energy Release Data6.2.1-206.2.1.3.7Accident Chronology6.2.1-246.2.1.3.8Energy Balance Tables6.2.1-246.2.1.3.9Containment Pressure Differentials6.2.1-246.2.1.3.10Steam Line Break Inside Containment6.2.1-276.2.1.3.11Maximum Reverse Pressure Differentials6.2.1-336.2.2CONTAINMENT HEAT REMOVAL SYSTEMS6.2.2-16.2.2.1Design Bases6.2.2-16.2.2.2System Design6.2.2-3 6.2.2.3Design Evaluation6.2.2-56.2.2.4Testing and Inspections6.2.2-76.2.2.5Instrumentation Requirements6.2.2-8 6.2.2.6Materials6.2.2-86.2.3Secondary Containment Functional Design6.2.3-16.2.3.1Design Bases6.2.3-16.2.3.1.1Secondary Containment Enclosures6.2.3-16.2.3.1.2Emergency Gas Treatment System (EGTS)6.2.3-16.2.3.1.3Auxiliary Building Gas Treatment System (ABGTS)6.2.3-26.2.3.2System Design6.2.3-26.2.3.2.1Secondary Containment Enclosures6.2.3-2 6.2.3.2.2Emergency Gas Treatment System (EGTS)6.2.3-76.2.3.2.3Auxiliary Building Gas Treatment System (ABGTS)6.2.3-106.2.3.3Design Evaluation6.2.3-12 6.2.3.3.1Secondary Containment Enclosures6.2.3-126.2.3.3.2Emergency Gas Treatment System (EGTS)6.2.3-156.2.3.3.3Auxiliary Building Gas Treatment System (ABGTS)6.2.3-196.2.3.4Test and Inspections6.2.3-216.2.3.4.1Emergency Gas Treatment System (EGTS)6.2.3-216.2.3.4.2Auxiliary Building Gas Treatment System (ABGTS)6.2.3-226.2.3.5Instrumentation Requirements6.2.3-236.2.3.5.1Emergency Gas Treatment System (EGTS)6.2.3-236.2.3.5.2Auxiliary Building Gas Treatment System (ABGTS)6.2.3-236.2.4Containment Isolation Systems6.2.4-16.2.4.1Design Bases6.2.4-16.2.4.2System Design6.2.4-46.2.4.2.1Design Requirements6.2.4-5 6.2.4.2.2Containment Isolation Operation6.2.4-56.2.4.2.3Penetration Design6.2.4-66.2.4.3Design Evaluation6.2.4-12 1-xxivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.2.4.3.1Possible Leakage Paths6.2.4-146.2.4.4Tests and Inspections6.2.4-166.2.5Combustible Gas Control in Containment6.2.5-16.2.5.1Design Bases6.2.5-16.2.5.2System Design6.2.5-2 6.2.5.3Design Evaluation6.2.5-56.2.5.4Testing and Inspections6.2.5-56.2.5.5Instrumentation Application6.2.5-5 6.2.5.6Materials6.2.5-66.2.5AHydrogen Mitigation System6.2.5-66.2.5A.1Design Basis6.2.5-6 6.2.5A.2System Description6.2.5-66.2.5A.3Operation6.2.5-76.2.5A.4Safety Evaluation6.2.5-7 6.2.5A.5Testing6.2.5-76.2.6Containment Leakage Testing6.2.6-16.2.6.1Containment Integrated Leak Rate Test6.2.6-16.2.6.2Containment Penetration Leakage Rate Test6.2.6-26.2.6.3Scheduling and Reporting of Periodic Tests6.2.6-6 6.2.6.4Special Testing Requirements6.2.6-66.3EMERGENCY CORE COOLING SYSTEM6.3-16.3.1Design Bases6.3-16.3.1.1Range of Coolant Ruptures and Leaks6.3-16.3.1.2Fission Product Decay Heat6.3-2 6.3.1.3Reactivity Required for Cold Shutdown6.3-26.3.1.4Capability To Meet Functional Requirements6.3-26.3.2System Design6.3-2 6.3.2.1Schematic Piping and Instrumentation Diagrams6.3-26.3.2.2Equipment and Component Design6.3-26.3.2.3Applicable Codes and Classifications6.3-176.3.2.4Materials Specifications and Compatibility6.3-176.3.2.5Design Pressures and Temperatures6.3-176.3.2.6Coolant Quantity6.3-18 6.3.2.7Pump Characteristics6.3-186.3.2.8Heat Exchanger Characteristics6.3-186.3.2.9ECCS Flow Diagrams6.3-186.3.2.10Relief Valves6.3-186.3.2.11System Reliability6.3-18 6.3.2.12Protection Provisions6.3-236.3.2.13Provisions for Performance Testing6.3-236.3.2.14Net Positive Suction Head6.3-24 Table of Contents1-xxvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.3.2.15Control of Motor-Operated Isolation Valves6.3-246.3.2.16Motor-Operated Valves and Controls6.3-256.3.2.17Manual Actions6.3-256.3.2.18Process Instrumentation6.3-256.3.2.19Materials6.3-256.3.3Performance Evaluation6.3-25 6.3.3.1Evaluation Model6.3-256.3.3.2ECCS Performance6.3-266.3.3.3Alternate Analysis Methods6.3-26 6.3.3.4Fuel Rod Perforations6.3-276.3.3.5Evaluation Model6.3-276.3.3.6Fuel Clad Effects6.3-27 6.3.3.7ECCS Performance6.3-276.3.3.8Peak Factors6.3-276.3.3.9Fuel Rod Perforations6.3-27 6.3.3.10Conformance with Interim Acceptance Criteria6.3-276.3.3.11Effects of ECCS Operation on the Core6.3-286.3.3.12Use of Dual Function Components6.3-28 6.3.3.13Lag Times6.3-306.3.3.14Thermal Shock Considerations6.3-306.3.3.15Limits on System Parameters6.3-30 6.3.3.16Use of RHR Spray6.3-306.3.4Tests and Inspections6.3-316.3.4.1Preoperational Tests6.3-31 6.3.4.2Component Testing6.3-326.3.4.3Periodic System Testing6.3-326.3.5Instrumentation Application6.3-33 6.3.5.1Temperature Indication6.3-336.3.5.2Pressure Indication6.3-336.3.5.3Flow Indication6.3-34 6.3.5.4Level Indication6.3-346.3.5.5Valve Position Indication6.3-356.4HABITABILITY SYSTEMS6.4-16.4.1 Design Bases6.4-16.4.2System Design6.4-1 6.4.2.1Definition of MCRHS Area6.4-16.4.2.2Ventilation System Design6.4-26.4.2.3Leak Tightness6.4-26.4.2.4Interaction with Other Zones and Pressure-Containing Equipment6.4-36.4.2.5Shielding Design6.4-4 6.4.2.6Control Room Emergency Provisions6.4-46.4.2.7MCRHS Fire Protection6.4-46.4.3System Operational Procedures6.4-5 1-xxviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.4.4Design Evaluations6.4-76.4.4.1Radiological Protection6.4-76.4.4.2Toxic Gas Protection6.4-76.4.5Testing and Inspection6.4-96.4.6Instrumentation Requirements6.4-96.5FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS6.5-16.5.1Engineered Safety Feature (ESF) Filter Systems6.5-16.5.1.1Design Bases6.5-1 6.5.1.2System Design6.5-26.5.1.3Design Evaluation6.5-56.5.1.4Tests and Inspections6.5-5 6.5.1.5Instrumentation Requirements6.5-66.5.1.6Materials6.5-76.5.2Containment Spray System for Fission Product Cleanup6.5-8 6.5.2.1Design Bases6.5-86.5.2.2System Design6.5-86.5.2.3Design Evaluation6.5-8 6.5.2.4Tests and Inspections6.5-86.5.2.5Instrumentation Requirements6.5-86.5.2.6Materials6.5-8 6.5.3Fission Product Control Systems6.5-86.5.3.1Primary Containment6.5-86.5.3.2Secondary Containments6.5-10 6.5.4Ice Condenser as a Fission Product Cleanup System6.5-106.5.4.1Ice Condenser Design Basis (Fission Product Cleanup Function)6.5-116.5.4.2Ice Condenser System Design6.5-11 6.5.4.3Ice Condenser System Design Evalua tion (Fission Product Cleanup Function) 6.5-116.5.4.4Condenser System Tests and Inspections6.5-13 6.5.4.5Ice Condenser Materials6.5-136.6INSERVICE INSPECTION OF ASME CODE CLASS 2 AND 3 COMPONENTS 6.6-16.6.1Components Subject to Examination and/or Test6.6-16.6.2Accessibility6.6-1 6.6.3Examination Techniques and Procedures6.6-16.6.4Inspection Intervals6.6-16.6.5Examination Categories and Requirements6.6-16.6.6Evaluation of Examination Results6.6-16.6.7System Pressure Tests6.6-2 6.6.8Protection against Postulated Piping Failures6.6-26.7ICE CONDENSER SYSTEM6.7-1 Table of Contents1-xxviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.7.1Floor Structure and Cooling System6.7-16.7.1.1Design Bases6.7-16.7.1.2Design Evaluation6.7-56.7.2Wall Panels6.7-86.7.2.1Design Basis6.7-86.7.2.2System Design6.7-8 6.7.2.3Design Evaluation6.7-96.7.3Lattice Frames and Support Columns6.7-96.7.3.1Design Basis6.7-9 6.7.3.2System Design6.7-126.7.3.3Design Evaluation6.7-136.7.4Ice Baskets6.7-14 6.7.4.1Design Basis6.7-146.7.4.2System Design6.7-156.7.4.3Design Evaluation6.7-18 6.7.5Crane and Rail Assembly6.7-206.7.5.1Design Basis6.7-206.7.5.2System Design6.7-20 6.7.5.3Design Evaluation6.7-216.7.6Refrigeration System6.7-216.7.6.1Design Basis6.7-21 6.7.6.2System Design6.7-226.7.6.3Design Evaluation6.7-256.7.7Air Handling Units6.7-29 6.7.7.1Design Basis6.7-296.7.7.2System Design6.7-306.7.7.3Design Evaluation6.7-31 6.7.8Lower Inlet Doors6.7-316.7.8.1Design Basis6.7-316.7.8.2System Design6.7-34 6.7.8.3Design Evaluation6.7-366.7.9Lower Support Structure6.7-376.7.9.1Design Basis6.7-37 6.7.9.2System Design6.7-396.7.9.3Design Evaluation6.7-406.7.10Top Deck and Doors6.7-49 6.7.10.1Design Basis6.7-496.7.10.2System Design6.7-516.7.11Intermediate Deck and Doors6.7-546.7.11.1Design Basis6.7-546.7.11.2System Design6.7-55 6.7.11.3Design Evaluation6.7-566.7.12Air Distribution Ducts6.7-576.7.12.1Design Basis6.7-57 1-xxviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.7.12.2System Design6.7-586.7.12.3Design Evaluation6.7-586.7.13Equipment Access Door6.7-586.7.13.1Design Basis6.7-586.7.13.2System Design6.7-596.7.13.3Design Evaluation6.7-59 6.7.14Ice Technology, Ice Performance, and Ice Chemistry6.7-596.7.14.1Design Basis6.7-596.7.14.2System Design6.7-59 6.7.14.3Design Evaluation6.7-606.7.15Ice Condenser Instrumentation6.7-656.7.15.1Design Basis6.7-65 6.7.15.2Design Description6.7-666.7.15.3Design Evaluation6.7-676.7.16Ice Condenser Structural Design6.7-68 6.7.16.1Applicable Codes, Standards, and Specifications6.7-686.7.16.2Loads and Loading Combinations6.7-686.7.16.3Design and Analytical Procedures6.7-68 6.7.16.4Structural Acceptance Criteria6.7-696.7.17Seismic Analysis6.7-706.7.17.1Seismic Analysis Methods6.7-70 6.7.17.2Seismic Load Development6.7-736.7.17.3Vertical Seismic Response6.7-746.7.18Materials6.7-74 6.7.18.1Design Criteria6.7-746.7.18.2Environmental Effects6.7-756.7.18.3Compliance with 10 CFR 50, Appendix B6.7-76 6.7.18.4Materials Specifications6.7-776.7.19Tests and Inspections6.7-786.8AIR RETURN FANS6.8-16.8.1Design Bases6.8-16.8.2System Description6.8-1 6.8.3Safety Evaluation6.8-26.8.4Inspection and Testing6.8-36.8.5Instrumentation Requirements6.8-3017_TVA_WB_FSAR_Section_7.pdf7.0INSTRUMENTATION AND CONTROLS
+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 1-xviii                                                                                            Table of Contents
+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 Table of Contents                                                                                 1-xix
+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 1-xx                                                              Table of Contents
+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 Table of Contents                                                  1-xxi
+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 1-xxii                                                                         Table of Contents
+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 Table of Contents                                                         1-xxiii
+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 1-xxiv                                                         Table of Contents
+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 Table of Contents                                                                       1-xxv
+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 1-xxvi                                                                          Table of Contents
+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 Table of Contents                                         1-xxvii
+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
-==7.1INTRODUCTION==
+==7.1                           INTRODUCTION==
-.1-17.1.1Identification of Safety-Related Systems7.1-47.1.1.1  Safety-Related Systems7.1-47.1.1.2 Safety-Related Display Instrumentation7.1-57.1.1.3 Instrumentation and Control System Designers7.1-5 Table of Contents1-xxixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.1.1.4 Plant Comparison7.1-57.1.2Identification of Safety Criteria7.1-57.1.2.1Design Bases7.1-87.1.2.2Independence of Redundant Safety-Related Systems7.1-127.1.2.3Physical Identification of Safety-Related Equipment7.1-157.1.2.4Process Signal Isolation Relays7.1-177.2 REACTOR TRIP SYSTEM7.2-17.2.1Description7.2-1 7.2.1.1System Description7.2-17.2.1.2Design Bases Information7.2-177.2.1.3Final Systems Drawings7.2-19 7.2.2Analyses7.2-197.2.2.1Evaluation of Design Limits7.2-207.2.2.2Evaluation of Compliance to Applicable Codes and Standards7.2-237.2.2.3Specific Control and Protection Interactions7.2-337.2.2.4Additional Postulated Accidents7.2-367.2.3Tests and Inspections7.2-367.3ENGINEERED SAFETY FEATURES ACTUATION SYSTEM7.3-17.3.1Description7.3-1 7.3.1.1System Description7.3-17.3.1.2Design Bases Information7.3-67.3.1.3Final System Drawings7.3-8 7.3.2Analysis7.3-87.3.2.1System Reliability/Availability and Failure Mode and Effect Analyses7.3-87.3.2.2Compliance With Standards and Design Criteria7.3-9 7.3.2.3 Further Considerations7.3-167.3.2.4Summary7.3-177.4SYSTEMS REQUIRED FOR SAFE SHUTDOWN7.4-17.4.1Description7.4-17.4.1.1Monitoring Indicators7.4-1 7.4.1.2Controls7.4-27.4.1.3Equipment and Systems Available for Cold Shutdown7.4-67.4.2Analysis7.4-67.5INSTRUMENTATION SYSTEMS IMPORTANT TO SAFETY7.5-17.5.1Post Accident Monitoring Instrumentation (PAM)7.5-17.5.1.1System Description7.5-17.5.1.2Variable Types7.5-1 7.5.1.3Variable Categories7.5-27.5.1.4Design Bases7.5-37.5.1.5General Requirements7.5-6 1-xxxTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.5.1.6Analysis7.5-77.5.1.7Tests and Inspections7.5-77.5.2Emergency Response Facilities Data System (ERFDS)7.5-87.5.2.1Safety Parameter Display System7.5-87.5.2.2Bypassed and Inoperable Status Indication System (BISI)7.5-107.5.2.3Technical Support Center and Nuclear Data Links7.5-137.6ALL OTHER SYSTEMS REQUIRED FOR SAFETY7.6-17.6.1120V ac and 125V dc Vital Plant Control Power System7.6-1 7.6.2Residual Heat Removal Isolation Valves7.6-17.6.2.1Description7.6-17.6.2.2Analysis7.6-2 7.6.3Refueling Interlocks7.6-27.6.4Deleted by Amendment 63.7.6-27.6.5Accumulator Motor-Operated Valves7.6-2 7.6.6Spurious Actuation Protection for Motor Operated Valves7.6-37.6.7Loose Part Monitoring System (LPMS) System Description7.6-47.6.8Interlocks for RCS Pressure Control During Low Temperature Operation7.6-67.6.8.1Analysis of Interlock7.6-77.6.9Switchover From Injection to Recirculation7.6-87.6.9.1Description of Instrumentation Used for Switchover7.6-8 7.6.9.2Initiation Circuit7.6-97.6.9.3Logic7.6-97.6.9.4Bypass7.6-9 7.6.9.5Interlocks7.6-97.6.9.6Sequence7.6-107.6.9.7Redundancy7.6-10 7.6.9.8Diversity7.6-107.6.9.9Actuated Devices7.6-107.7CONTROL SYSTEMS7.7-17.7.1Description7.7-17.7.1.1Control Rod Drive Reactor Control System7.7-1 7.7.1.3Plant Control Signals for Monitoring and Indicating7.7-87.7.1.4Plant Control System Interlocks7.7-127.7.1.5Pressurizer Pressure Control7.7-137.7.1.6Pressurizer Water Level Control7.7-137.7.1.7Steam Generator Water Level Control7.7-147.7.1.8Steam Dump Control7.7-147.7.1.9Incore Instrumentation7.7-167.7.1.10Control Board7.7-18 7.7.1.11Boron Concentration Measurement System7.7-187.7.1.12Anticipated Transient Without Scram Mitigation System Actuation7.7-197.7.2Analysis7.7-20 Table of Contents1-xxxiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.7.2.1Separation of Protection and Control System7.7-217.7.2.2Response Considerations of Reactivity7.7-217.7.2.3Step Load Changes Without Steam Dump7.7-247.7.2.4Loading and Unloading7.7-247.7.2.5Load Rejection Furnished By Steam Dump System7.7-257.7.2.6Turbine-Generator Trip With Reactor Trip7.7-25 7.7.3Deleted by Amendment 817.7-267AINSTRUMENTATION IDENTIFICATIONS AND SYMBOLS7A.1IDENTIFICATION SYSTEM7A.1-17A.1.1FUNCTIONAL IDENTIFICATION7A.1-1 7A.1.1.1  Principal Function7A.1-17A.1.1.2  Measured Variable7A.1-27A.1.1.3  Readout or Passive Functions7A.1-2 7A.1.1.4  Modifying Letters7A.1-27A.1.1.5  Tagging Symbols7A.1-27A.1.1.6  Special Identifying Letters7A.1-2 7A.1.1.7  Pilot Lights7A.1-27A.1.2  SYSTEM IDENTIFICATION7A.1-37A.1.2.1  Identification Numbers7A.1-37A.1.3  LOOP IDENTIFICATION7A.1-37A.1.3.1  Instruments Common to Multiple Control Loops7A.1-37A.1.3.2  Multiple Instruments with a Common Function7A.1-37A.2SYMBOLS7A.1-37A.2.1INSTRUMENT SYMBOL7A.1-4018_TVA_WB_FSAR_Section_88.0ELECTRIC POWER
+.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 1-xxviii                                                                                Table of Contents
-==8.1INTRODUCTION==
+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 Table of Contents                                                                            1-xxix
-.1-18.1.1Utility Grid and Interconnections8.1-18.1.2Plant Electrical Power System8.1-1 8.1.3Safety-Related Loads8.1-28.1.4Design Bases8.1-38.1.5Design Criteria and Standards8.1-4 8.1.5.1Design Criteria8.1-58.1.5.2Other Standards and Guides8.1-58.1.5.3Compliance to Regulatory Guides and IEEE Standards8.1-88.2OFFSITE (PREFERRED) POWER SYSTEM8.2-18.2.1Description8.2-18.2.1.1Preferred Power Supply8.2-18.2.1.2Transmission Lines, Switchyard, and Transformers8.2-3 1-xxxiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page8.2.1.3Arrangement of the Start Boards, Un it Boards, Common Boards, and Reactor Coolant Pump (RCP) Boards8.2-48.2.1.4Arrangement of Electrical C ontrol Area (Nuclear Plant)8.2-58.2.1.5Switchyard Control and Relaying8.2-68.2.1.66.9-kV Start Boards Control and Relaying8.2-88.2.1.76.9-kV Unit and RCP Board Control and Relaying8.2-10 8.2.1.8Conformance with Standards8.2-118.2.2 Analysis8.2-198.3ONSITE (STANDBY) POWER SYSTEM8.3-18.3.1AC Power System8.3-18.3.1.1Description8.3-1 8.3.1.2Analysis8.3-288.3.1.3Physical Identification of Safety-Rel ated Equipment in AC Power Systems 8.3-388.3.1.4Independence of Redundant ac Power Systems8.3-388.3.2DC Power System8.3-558.3.2.1Description8.3-55 8.3.2.2Analysis of Vital 125V DC Control Power Supply System8.3-638.3.2.3Physical Identification of Safety-Related Equipment in dc Power Systems8.3-688.3.2.4Independence of Redundant DC Power Systems8.3-688.3.2.5Sharing of Batteries Between Units8.3-688.3.3Fire Protection for Cable Systems8.3-70 Table of Contents1-xxxiiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page8AAnalysis of Submerged Electrical Equipment (During Post LOCA) Powered from Auxiliary Power System8A-18BAnalysis of Submerged Electrical Equipment (During Post LOCA) Powered from Instrumentation and Control Power System8B-18CDeleted by Amendment 758C-18DIEEE STD 387-1984 FOR DIESEL-GENERATING UNITS APPLIED AS STAND-BY POWER8D-18EProbability/Reliability Analysis of Protection Device Schemes for Associated and Non-Class 1E Cables8E-19.0AUXILIARY SYSTEMS9.1FUEL STORAGE AND HANDLING9.1-19.1.1New Fuel Storage9.1-19.1.1.1Design Bases9.1-19.1.1.2Facilities Description9.1-1 9.1.1.3Safety Evaluation9.1-19.1.2SPENT FUEL STORAGE9.1-29.1.2.1Design Bases9.1-2 9.1.2.2Facilities Description9.1-29.1.2.3Safety Evaluation9.1-39.1.2.4Materials9.1-4 9.1.3Spent Fuel Pool Cooling and Cleanup System (SFPCCS)9.1-49.1.3.1Design Bases9.1-49.1.3.2System Description9.1-5 9.1.3.3Safety Evaluation9.1-89.1.3.4Tests and Inspections9.1-119.1.3.5Instrument Application9.1-11 9.1.4FUEL HANDLING SYSTEM9.1-129.1.4.1Design Bases9.1-129.1.4.2System Description9.1-13 9.1.4.3Design Evaluation9.1-209.1.4.4Tests and Inspections9.1-269.2WATER SYSTEMS9.2-19.2.1Essential Raw Cooling Water (ERCW)9.2-1 9.2.1.1Design Bases9.2-19.2.1.2System Description9.2-19.2.1.3Safety Evaluation9.2-4 1-xxxivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.2.1.4Tests and Inspections9.2-79.2.1.5Instrument Applications9.2-79.2.1.6Corrosion, Organic Fouling, and Environmental Qualification9.2-99.2.1.7Design Codes9.2-119.2.2Component Cooling System (CCS)9.2-119.2.2.1Design Bases9.2-11 9.2.2.2System Description9.2-139.2.2.3Components9.2-169.2.2.4 Safety Evaluation9.2-19 9.2.2.5Leakage Provisions9.2-199.2.2.6Incidental Control9.2-209.2.2.7Instrument Applications9.2-20 9.2.2.8Malfunction Analysis9.2-229.2.2.9Tests and Inspections9.2-239.2.2.10Codes and Classification9.2-239.2.3Demineralized Water Makeup System9.2-239.2.3.1Design Bases9.2-239.2.3.2System Description9.2-24 9.2.3.3Safety Evaluation9.2-259.2.3.4Test and Inspection9.2-259.2.3.5Instrumentation Applications9.2-25 9.2.4Potable and Sanitary Water Systems9.2-269.2.4.1Potable Water System9.2-269.2.4.2Sanitary Water System9.2-27 9.2.5Ultimate Heat Sink9.2-309.2.5.1General Description9.2-309.2.5.2Design Bases9.2-31 9.2.5.3Safety Evaluation9.2-329.2.5.4Instrumentation Application9.2-339.2.6Condensate Storage Facilities9.2-33 9.2.6.1Design Bases9.2-349.2.6.2System Description9.2-349.2.6.3Safety Evaluation9.2-35 9.2.6.4Test and Inspections9.2-359.2.6.5Instrument Applications9.2-369.2.7Refueling Water Storage Tank9.2-36 9.2.7.1ECCS Pumps Net Positive Suction Head (NPSH)9.2-379.2.8Raw Cooling Water System9.2-399.2.8.1Design Bases9.2-399.2.8.2System Description9.2-409.2.8.3Safety Evaluation9.2-42 9.2.8.4Tests and Inspection9.2-429.3PROCESS AUXILIARIES9.3-1 Table of Contents1-xxxvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.3.1Compressed Air System9.3-19.3.1.1Design Basis9.3-19.3.1.2System Description9.3-19.3.1.3Safety Evaluation9.3-29.3.1.4Tests and Inspections9.3-59.3.1.5Instrumentation Applications9.3-5 9.3.2Process Sampling System9.3-59.3.2.1Design Basis9.3-59.3.2.2System Description9.3-5 9.3.2.3Safety Evaluation9.3-89.3.2.4Tests and Inspections9.3-89.3.2.5Instrumentation Applications9.3-8 9.3.2.6Postaccident Sampling Subsystem9.3-89.3.3Equipment and Floor Drainage System9.3-129.3.3.1Design Bases9.3-12 9.3.3.2System Design9.3-129.3.3.3Drains - Reactor Building9.3-159.3.3.4Design Evaluation9.3-15 9.3.3.5Tests and Inspections9.3-159.3.3.6Instrumentation Application9.3-159.3.3.7Drain List9.3-15 9.3.4Chemical and Volume Control System9.3-169.3.4.1Design Bases9.3-169.3.4.2System Description9.3-18 9.3.4.3Safety Evaluation9.3-369.3.4.4Tests and Inspections9.3-389.3.4.5Instrumentation Application9.3-39 9.3.5Failed Fuel Detection System9.3-399.3.5.1Design Bases9.3-399.3.5.2System Description9.3-40 9.3.5.3Safety Evaluation9.3-409.3.5.4Tests and Inspections9.3-409.3.5.5Instrument Applications9.3-40 9.3.6Auxiliary Charging System9.3-409.3.6.1Design Bases9.3-409.3.6.2System Design Description9.3-41 9.3.6.3Design Evaluation9.3-429.3.6.4Tests and Inspection9.3-429.3.6.5Instrument Application9.3-429.3.7Boron Recycle System9.3-429.3.7.1Design Bases9.3-43 9.3.7.2System Description9.3-449.3.7.3Safety Evaluation9.3-509.3.7.4Tests and Inspections9.3-50 1-xxxviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.3.7.5Instrumentation Application9.3-509.3.8Heat Tracing9.3-519.4AIR CONDITIONING, HEATING, COOLING, AND VENTILATION SYSTEMS 9.4-19.4.1Control Room Area Ventilation System9.4-19.4.1.1Design Bases9.4-19.4.1.2System Description9.4-39.4.1.3Safety Evaluation9.4-7 9.4.1.4Tests and Inspection9.4-89.4.2Fuel Handling Area Ventilation System9.4-89.4.2.1Design Bases9.4-8 9.4.2.2System Description9.4-109.4.2.3Safety Evaluation9.4-109.4.2.4 Inspection and Testing9.4-11 9.4.3Auxiliary and Radwaste Area Ventilation System9.4-129.4.3.1Design Bases9.4-129.4.3.2System Description9.4-13 9.4.3.3Safety Evaluation9.4-199.4.3.4Inspection and Testing Requirements9.4-239.4.4Turbine Building Area Ventilation System9.4-23 9.4.4.1Design Bases9.4-239.4.4.2System Description9.4-249.4.4.3Safety Evaluation9.4-26 9.4.4.4Inspection and Testing Requirements9.4-269.4.5 Engineered Safety Feature Ventilation Systems9.4-269.4.5.1ERCW Intake Pumping Station9.4-26 9.4.5.2Diesel Generator Buildings9.4-299.4.5.3Auxiliary Building Safety Features Equipment Coolers9.4-369.4.6Reactor Building Purge Ventilating System9.4-39 9.4.6.1Design Bases9.4-399.4.6.2System Description9.4-419.4.6.3Safety Evaluation9.4-43 9.4.6.4Inspection and Testing Requirements9.4-449.4.7Containment Air Cooling System9.4-459.4.7.1Design Bases9.4-45 9.4.7.2System Description9.4-469.4.7.3Safety Evaluation9.4-489.4.7.4Test and Inspection Requirements9.4-489.4.8Condensate Demineralizer Wa ste Evaporator Building Environmental Control Sys-tem  (Not required for Unit 1 operation)9.4-499.4.8.1Design Basis9.4-499.4.8.2System Description9.4-499.4.8.3Safety Evaluation9.4-50 Table of Contents1-xxxviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.4.8.4Inspection and Testing Requirements9.4-509.4.9Postaccident Sampling Facility Environmental Control System9.4-509.4.9.1Design Basis9.4-509.4.9.2System Description9.4-509.4.9.3Safety Evaluation9.4-519.4.9.4Inspection and Testing Requirements9.4-519.5OTHER AUXILIARY SYSTEMS9.5-19.5.1Fire Protection System9.5-1 9.5.1.1Deleted by Amendment 879.5-19.5.1.2Deleted by Amendment 879.5-19.5.1.3Deleted by Amendment 879.5-1 9.5.1.4Deleted by Amendment 879.5-19.5.1.5Deleted by Amendment 879.5-19.5.2Plant Communications System9.5-1 9.5.2.1Design Bases9.5-19.5.2.2General Description Intraplant Communications9.5-19.5.2.3General Description Interplant System9.5-4 9.5.2.4 Evaluation9.5-59.5.2.5Inspection and Tests9.5-89.5.3Lighting Systems9.5-9 9.5.3.1Design Bases9.5-99.5.3.2Description of the Plant Lighting System9.5-109.5.3.3Diesel Generator Building Lighting System9.5-11 9.5.3.4Safety Related Functions of the Lighting Systems9.5-129.5.3.5Inspection and Testing Requirements9.5-139.5.4Diesel Generator Fuel Oil Storage and Transfer System9.5-139.5.4.1Design Basis9.5-139.5.4.2System Description9.5-149.5.4.3Safety Evaluation9.5-16 9.5.4.4Tests and Inspections9.5-179.5.5Diesel Generator Cooling Water System9.5-189.5.5.1Design Bases9.5-18 9.5.5.2System Description9.5-189.5.5.3Safety Evaluation9.5-199.5.5.4Tests and Inspections9.5-19 9.5.6Diesel Generator Starting System9.5-199.5.6.1Design Bases9.5-199.5.6.2System Description9.5-209.5.6.3Safety Evaluation9.5-219.5.6.4Tests and Inspections9.5-21 9.5.7Diesel Engine Lubrication System9.5-219.5.7.1Design Bases9.5-219.5.7.2System Description9.5-23 1-xxxviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.5.7.3Safety Evaluation9.5-259.5.7.4Test and Inspections9.5-259.5.8Diesel Generator Combustion Air Intake and Exhaust System9.5-259.5.8.1Design Bases9.5-259.5.8.2System Descriptions9.5-259.5.8.3Safety Evaluation9.5-26 9.5.8.4Tests and Inspection9.5-2710.0MAIN STEAM AND POWER CONVERSION SYSTEMS10.1
+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 1-xxx                                                                          Table of Contents
+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==
+.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 Table of Contents                                                                          1-xxxi
+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 1-xxxii                                                                         Table of Contents
+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 Table of Contents                                                                 1-xxxiii
+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 1-xxxiv                                                                     Table of Contents
+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 Table of Contents                                         1-xxxv
+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 1-xxxvi                                                                     Table of Contents
+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 Table of Contents                                                            1-xxxvii
+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==
-DESCRIPTION10.1-110.2TURBINE-GENERATOR10.2-110.2.1Design Bases10.2-110.2.2Description10.2-1 10.2.3Turbine Rotor and Disc Integrity10.2-510.2.3.1 Materials Selection10.2-510.2.3.2Fracture Toughness10.2-7 10.2.3.3 High Temperature Properties10.2-910.2.3.4 Turbine Disc Design10.2-910.2.3.5 Preservice Inspection10.2-9 10.2.3.6 Inservice Inspection10.2-1110.2.4Evaluation10.2-1310.3MAIN STEAM SUPPLY SYSTEM10.3-110.3.1Design Bases10.3-110.3.2System Description10.3-1 10.3.2.1System Design10.3-110.3.2.2Material Compatibility, Codes, and Standards10.3-210.3.3Design Evaluation10.3-2 10.3.4Inspection and Testing Requirements10.3-310.3.5Water Chemistry10.3-310.3.5.1Purpose10.3-3 10.3.5.2Feedwater Chemistry Specifications10.3-410.3.5.3Operating Modes10.3-410.3.5.4Effect of Water Chemistry on the Radi oactive Iodine Partition Coefficient 10.3-510.3.6Steam and Feedwater System Materials10.3-510.3.6.1Fracture Toughness10.3-510.3.6.2Materials Selection and Fabrication10.3-510.4OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-110.4.1Main Condenser10.4-110.4.1.1Design Bases10.4-1 Table of Contents1-xxxixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page10.4.1.2System Description10.4-110.4.1.3Safety Evaluation10.4-410.4.1.4Inspection and Testing10.4-510.4.1.5Instrumentation10.4-510.4.2Main Condenser Evacuation System10.4-510.4.2.1Design Bases10.4-5 10.4.2.2System Description10.4-510.4.2.3Safety Evaluation10.4-610.4.2.4Inspection and Testing10.4-6 10.4.2.5Instrumentation10.4-610.4.3Turbine Gland Sealing System10.4-710.4.3.1Design Bases10.4-7 10.4.3.2System Description10.4-710.4.3.3Safety Evaluation10.4-710.4.3.4Inspection and Testing10.4-8 10.4.3.5Instrumentation10.4-810.4.4Turbine Bypass System10.4-810.4.4.1Design Bases10.4-8 10.4.4.2System Description10.4-810.4.4.3Safety Evaluation10.4-910.4.4.4Inspection and Testing10.4-10 10.4.5Condenser Circulating Water System10.4-1010.4.5.1Design Basis10.4-1110.4.5.2System Description10.4-11 10.4.5.3Safety Evaluation10.4-1310.4.5.4Inspection and Testing10.4-1410.4.5.5Instrumentation Application10.4-14 10.4.6Condensate Polishing Demineralizer System10.4-1510.4.6.1Design Bases - Power Conversion10.4-1510.4.6.2System Description10.4-15 10.4.6.3Safety Evaluation10.4-1710.4.6.4Inspection and Testing10.4-1810.4.6.5Instrumentation10.4-18 10.4.7Condensate and Feedwater Systems10.4-1910.4.7.1Design Bases10.4-1910.4.7.2System Description10.4-19 10.4.7.3Safety Evaluation10.4-2610.4.7.4Inspection and Testing10.4-2810.4.7.5Instrumentation10.4-2810.4.8Steam Generator Blowdown System10.4-2810.4.8.1Design Bases10.4-28 10.4.8.2System Description and Operation10.4-3010.4.8.3Safety Evaluation10.4-3010.4.8.4Inspections and Testing10.4-31 1-xlTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page10.4.9Auxiliary Feedwater System10.4-3210.4.9.1Design Bases10.4-3210.4.9.2System Description10.4-3210.4.9.3Safety Evaluation10.4-3410.4.9.4Inspection and Testing Requirements10.4-3710.4.9.5Instrumentation Requirements10.4-37 10.4.10Heater Drains and Vents10.4-3810.4.10.1Design Bases10.4-3810.4.10.2System Description10.4-38 10.4.10.3Safety Evaluation10.4-4310.4.10.4Inspection and Testing10.4-4410.4.10.5Instrumentation10.4-44 10.4.11Steam Generator Wet Layup System10.4-4410.4.11.1Design Bases10.4-4410.4.11.2System Description10.4-44 10.4.11.3Safety Evaluation10.4-4510.4.11.4Inspection and Testing10.4-4510.4.11.5Instrumentation10.4-4511.0RADIOACTIVE WASTE MANAGEMENT11.1SOURCE TERMS11.1-111.1.1Historical Design Model for Radioact ivities in Systems and Components11.1-111.1.1.1Reactor Coolant Historical Design Activity11.1-111.1.1.2Volume Control Tank Historical Design Activity11.1-211.1.1.3Pressurizer Historical Design Activity11.1-211.1.1.4Gaseous Waste Processing System Historical Design Activities11.1-211.1.1.5Secondary Coolant Historical Design Activities11.1-211.1.2Realistic Model for Radioactivities in Systems and Components11.1-211.1.3Plant Leakage11.1-3 11.1.4Additional Sources11.1-311.2LIQUID WASTE SYSTEMS11.2-111.2.1DESIGN OBJECTIVES11.2-111.2.2SYSTEMS DESCRIPTIONS11.2-111.2.3SYSTEM DESIGN11.2-5 11.2.3.1Component Design11.2-511.2.3.2Instrumentation Design11.2-1111.2.4Operating Procedure11.2-1111.2.5PERFORMANCE TESTS11.2-1811.2.6ESTIMATED RELEASES11.2-18 11.2.6.1NRC Requirements11.2-1811.2.6.2 Westinghouse PWR Release Experience11.2-1911.2.6.3Expected Liquid Waste Processing System Releases11.2-19 Table of Contents1-xliWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page11.2.6.4Turbine Building (TB) Drains11.2-1911.2.6.5Estimated Total Liquid Releases11.2-2011.2.7RELEASE POINTS11.2-2011.2.8DILUTION FACTORS11.2-2011.2.9ESTIMATED DOSES FROM RADIONUCLIDES IN LIQUID EFFLUENTS11.2-2111.2.9.1Assumptions and Calculational Methods11.2-2111.2.9.2Summary of Dose from Radionuclides in Liquid Effluents11.2-2311.3GASEOUS WASTE SYSTEMS11.3-111.3.1Design Bases11.3-111.3.2SYSTEM DESCRIPTIONS11.3-1 11.3.3SYSTEM DESIGN11.3-311.3.3.1Component Design11.3-311.3.3.2Instrumentation Design11.3-3 11.3.4Operating Procedure11.3-411.3.5Performance Tests11.3-611.3.6Deleted by Amendment 7711.3-6 11.3.7Radioactive Releases11.3-611.3.7.1NRC Requirements11.3-611.3.7.2Westinghouse PWR Experience Releases11.3-6 11.3.7.3Expected Gaseous Waste Processing System Releases11.3-611.3.7.4Releases from Ventilation Systems11.3-711.3.7.5Estimated Total Releases11.3-7 11.3.8Release Points11.3-711.3.9Atmospheric Dilution11.3-811.3.10Estimated Doses from Radionuclides in Gaseous Effluents11.3-911.3.10.1Assumptions and Calculational Methods11.3-911.3.10.2Summary of Annual Population Doses11.3-1111.4PROCESS AND EFFLUEN T RADIOLOGICAL MONITO RING AND SAMPLING SYSTEM11.4-111.4.1Design Objectives11.4-1 11.4.2Continuous Monitors11.4-211.4.2.1Liquid Monitors11.4-211.4.2.2Gaseous Monitors11.4-4 11.4.3SAMPLING11.4-911.4.4CALIBRATION AND MAINTENANCE11.4-911.5SOLID WASTE MANAGEMENT SYSTEM11.5-111.5.1Design Objectives11.5-1 11.5.2System Inputs11.5-111.5.3Systems Description11.5-111.5.3.1Wet Active Waste Handling11.5-1 1-xliiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page11.5.3.2Dry Active Waste Handling11.5-311.5.3.3Miscellaneous Waste Handling11.5-411.5.4Equipment Operation11.5-411.5.4.1Deleted11.5-411.5.4.2Mobile Solidification System (MSS)11.5-411.5.5Storage Facilities11.5-4 11.5.5.1Inplant Storage Area11.5-411.5.5.2Outside Radwaste Storage11.5-511.5.6Shipment11.5-511.6Offsite Radiological Monitoring Program11.6-111.6.1Expected Background11.6-2 11.6.2Critical Pathways to Man11.6-211.6.2.1Doses from Gaseous Effluents11.6-311.6.2.2Internal Doses from Liquid Effluents11.6-3 11.6.3Sampling Media, Locations, and Frequency11.6-411.6.4Analytical Sensitivity11.6-411.6.5Data Analysis and Presentation11.6-4 11.6.6Program Statistical Sensitivity11.6-411ATRITIUM CONTROL 11A.1SYSTEM SOURCES11A.1-111A.1.1The Fission Source11A.1-1 11A.1.2Control Rod Source11A.1-111A.1.3Boric Acid Source11A.1-111A.1.4Burnable Shim Rod Source11A.1-211A.2Tritium Releases11A.1-211A.3 Design Bases11A.1-211A.4Design Evaluation11A.1-2 11A.5Tritium Lead Test Assembly (This section to be provided at a later date)11A.1-311A.6Tritium Producing Burnable Absorber Rod (TPBAR) Source (Unit 1 Only)11A.1-312.0RADIATION PROTECTION 12.1Assuring that Occupational Radiation Exposures Are as Low as Reasonably Achievable (ALARA)12.1-1 Table of Contents 1-xliiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page12.1.1Policy Considerations12.1-112.1.2Design Considerations12.1-112.1.3ALARA Operational Considerations12.1-112.2RADIATION SOURCES12.2-312.2.1Contained Sources12.2-3 12.2.1.1Primary System Sources12.2-312.2.1.2Auxiliary Systems Sources12.2-412.2.1.3Sources During Refueling12.2-10 12.2.1.4Maximum Hypothetical Accident (MHA) Sources12.2-1012.2.1.5Condensate Demineralizer Waste Evaporator12.2-1112.2.2Airborne Radioactive Material Sources12.2-1112.3RADIATION PROTECTION DESIGN FEATURES12.3-112.3.1Facility Design Features12.3-1 12.3.2Shielding12.3-312.3.2.1Design Objectives12.3-312.3.2.2 Design Description12.3-3 12.3.3Ventilation12.3-1512.3.3.1Airflow Control12.3-1512.3.3.2Typical System12.3-15 12.3.3.3Additional Radiation Controls12.3-1612.3.4Area Radiation and Airborne Radioactivity Monitoring Instrumentation12.3-1712.3.4.1Area Radiation Monitoring Instrumentation12.3-1712.3.4.2Airborne Particulate Radioactivity Monitoring12.3-1912.3.4.3Deleted by Amendment 84.12.3-2312.3.4.4Special Radiation Monitors12.3-2312.4DOSE ASSESSMENT12.4-112.5RADIOLOGICAL CONTROL (RADCON) PROGRAM12.5-112.5.1Organization12.5-112.5.2Equipment, Instrumentation, and Facilities12.5-212.5.3Procedures12.5-4 024_TVA_WB_FSAR_Section_13.pdf13.0CONDUCT OF OPERATIONS13.1ORGANIZATIONAL STRUCTURE OF APPLICANT13.1-113.1.1Corporate Organization13.1-113.1.1.1Design Responsibilities13.1-113.1.2Nuclear Power13.1-1 13.1.2.1Offsite Organizations13.1-113.1.2.2Onsite Organization13.1-213.1.3Qualification Requirements for Nuclear Facility Personnel13.1-2 1-xlivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page13.2TRAINING PROGRAMS13.2-113.2.1Accredited Training Programs13.2-113.2.2General Employee and Fitness for Duty Training Programs13.2-113.2.3Other Training Programs13.2-213.3Emergency Planning13.3-113.4REVIEW AND AUDIT13.4-113.4.1Onsite Review13.4-113.4.2Independent Review and Audit13.4-113.5SITE PROCEDURES13.5-113.5.1SYSTEM OF SITE PROCEDURES13.5-113.5.1.1Conformance with Regulatory Guide 1.3313.5-1 13.5.1.2Preparation of Procedures13.5-113.5.1.3Administrative Procedures13.5-213.5.2Operating and Maintenance Procedures13.5-2 13.5.2.1Operating Procedures13.5-213.5.2.2Other Procedures13.5-313.6PLANT RECORDS13.6-113.6.1Plant History13.6-113.6.2Operating Records13.6-1 13.6.3Event Records13.6-113.7NUCLEAR SECURITY13.7-113.7.1Physical Security and Contingency Plan13.7-113.7.2Personnel and Program Evaluation13.7-113.7.3Physical Security of TPBARs13.7-114.0INITIAL TEST PROGRAM14.1SPECIFIC INFORMATION TO BE IN CLUDED IN PRELIMINARY SAFETY ANALYSIS REPORT14.1-114.2TEST PROGRAM14.2-114.2.1Summary of Test Program and Objectives14.2-114.2.2Organization and Staffing14.2-314.2.2.1Startup and Test Organization14.2-314.2.2.2Plant Operating Organization14.2-5 14.2.2.3Nuclear Assurance14.2-614.2.2.4Major Participating Organizations14.2-614.2.2.5Joint Test Group14.2-7 Table of Contents1-xlvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page14.2.2.6Test Review Group14.2-814.2.2.7Personnel Qualifications14.2-914.2.3Test Procedures14.2-914.2.3.1General14.2-914.2.3.2Development of Procedures14.2-1014.2.3.3Review and Approval of Test Procedures14.2-1014.2.3.4Format of Test Procedures14.2-1014.2.3.5Test Procedure Revisions/Changes14.2-1114.2.4Conduct of Test Program14.2-12 14.2.4.1Administrative Procedures14.2-1214.2.4.2Component Testing14.2-1214.2.4.3Preoperational and Acceptance Testing14.2-1314.2.4.4Power Ascension Testing14.2-1314.2.4.5Test Prerequisites14.2-1314.2.4.6Phase Evaluation14.2-13 14.2.4.7Design Modifications14.2-1414.2.5Review, Evaluation, and Approval of Test Results14.2-1414.2.6Test Records14.2-14 14.2.7Conformance of Test Programs with Regulatory Guides14.2-1514.2.8Utilization of Reactor Oper ating and Testing Experience in Development of Test Pro-gram14.2-2914.2.9Trial Use of Plant Operating and Emergency Procedures14.2-3014.2.10Initial Fuel Loading, Postloading Tests, Initial Criticality, Low Power Tests and Pow-er Ascension14.2-3014.2.10.1Fuel Loading14.2-3014.2.10.2Postloading Tests14.2-3314.2.10.3Initial Criticality14.2-33 14.2.10.4Low Power Tests14.2-3314.2.10.5Power Ascension14.2-3414.2.11Test Program Schedule14.2-34 14.2.12Individual Test Descriptions14.2-3514.2.12.1Preoperational Tests14.2-3514.2.12.2Power Ascension Tests14.2-36026_TVA_WB_FSAR_Section_15.pdf15.0ACCIDENT ANALYSES15.1CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS 15.1-115.1.1Optimization of Control Systems15.1-215.1.2Initial Power Conditions Assumed In Accident Analyses15.1-315.1.2.1Power Rating15.1-3 15.1.2.2Initial Conditions15.1-315.1.2.3Power Distribution15.1-415.1.3Trip Points And Time Delays To Trip Assumed In Accident Analyses15.1-4 1-xlviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.1.4Instrumentation Drift And Calorimetric Errors - Power Range Neutron Flux15.1-515.1.5Rod Cluster Control Assembly Insertion Characteristic15.1-515.1.6Reactivity Coefficients15.1-615.1.7Fission Product Inventories15.1-715.1.7.1Radioactivity in the Core15.1-715.1.7.2Radioactivity in the Fuel Pellet Clad Gap15.1-815.1.8Residual Decay Heat15.1-915.1.8.1Fission Product Decay Energy15.1-915.1.8.2Decay of U-238 Capture Products15.1-10 15.1.8.3Residual Fissions15.1-1115.1.8.4Distribution of Decay Heat Following Loss of Coolant Accident15.1-1115.1.9Computer Codes Utilized15.1-11 15.1.9.1FACTRAN15.1-1115.1.9.2Deleted by Amendment 72.15.1-1215.1.9.3 MARVEL15.1-12 15.1.9.4LOFTRAN15.1-1315.1.9.5LEOPARD15.1-1415.1.9.6TURTLE15.1-14 15.1.9.7TWINKLE15.1-1415.1.9.8Deleted by Amendment 80.15.1-1515.1.9.9THINC15.1-15 15.1.9.10LOFTTR15.1-1515.2CONDITION II - FAULTS OF MODERATE FREQUENCY15.2-115.2.1Uncontrolled Rod Cluster Control Asse mbly Bank Withdrawal from a Subcritical Condition15.2-215.2.1.1Identification of Causes and Accident Description15.2-2 15.2.1.2Analysis of Effects and Consequences15.2-315.2.1.3Conclusions15.2-515.2.2UNCONTROLLED ROD CLUSTER C ONTROL ASSEMBLY BANK WITH-DRAWAL AT POWER15.2-515.2.2.1Identification of Causes and Accident Description15.2-515.2.2.2Analysis of Effects and Consequences15.2-7 15.2.2.3Conclusions15.2-915.2.3ROD CLUSTER CONTROL ASSEMBLY MISALIGNMENT15.2-915.2.3.1Identification of Causes and Accident Description15.2-9 15.2.3.2Analysis of Effects and Consequences15.2-1115.2.3.3Conclusions15.2-1315.2.4UNCONTROLLED BORON DILUTION15.2-1315.2.4.1Identification of Causes and Accident Description15.2-1315.2.4.2Analysis of Effects and Consequences15.2-14 15.2.4.3Conclusions15.2-1615.2.5PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW15.2-1715.2.5.1Identification of Causes and Accident Description15.2-17 Table of Contents1-xlviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.2.5.2Analysis of Effects and Consequences15.2-1815.2.5.3Conclusions15.2-1915.2.6Startup of an Inactive Reactor Coolant Loop15.2-1915.2.6.1Identification of Causes and Accident Description15.2-1915.2.6.2Analysis of Effects and Consequences15.2-1915.2.6.3Conclusions15.2-21 15.2.7LOSS OF EXTERNAL ELECTRICAL LOAD AND/OR TURBINE TRIP15.2-2115.2.7.1Identification of Causes and Accident Description15.2-2115.2.7.2Analysis of Effects and Consequences15.2-22 15.2.7.3Conclusions15.2-2415.2.8LOSS OF NORMAL FEEDWATER15.2-2415.2.8.1Identification of Causes and Accident Description15.2-24 15.2.8.2Analysis of Effects and Consequences15.2-2515.2.8.3Conclusions15.2-2815.2.9COINCIDENT LOSS OF ONSITE AND EXTERNAL (OFFSITE) AC POWER TO THE STATION - LOSS OF OFFSITE POWER TO THE STATION AUXILIARIES 15.2-2815.2.10EXCESSIVE HEAT REMOVAL DUE TO FEEDWATER SY STEM MALFUNC-TIONS15.2-2815.2.10.1Analysis of Effects and Consequences15.2-2815.2.10.2Conclusions15.2-31 15.2.11Excessive Load Increase Incident15.2-3115.2.11.1Identification of Causes and Accident Description15.2-3115.2.11.2Analysis of Effects and Consequences15.2-3215.2.11.3Conclusions15.2-3315.2.12ACCIDENTAL DEPRESSURIZATION OF THE REACTOR COOLANT SYS-TEM15.2-3315.2.12.1Identification of Causes and Accident Description15.2-3315.2.12.2Analysis of Effects and Consequences15.2-3315.2.12.3Conclusions15.2-34 15.2.13ACCIDENTAL DEPRESSURIZATION OF THE MAIN STEAM SYSTEM15.2-3415.2.13.1Identification of Causes and Accident Description15.2-3415.2.13.2Analysis of Effects and Consequences15.2-3615.2.13.3Conclusions15.2-3815.2.14Inadvertent Operation of Emergency Core Cooling System15.2-3815.2.14.1Identification of Causes and Accident Description15.2-3815.2.14.2Analysis of Effects and Consequences15.2-3915.2.14.3Conclusions15.2-4215.3CONDITION III - INFREQUENT FAULTS15.3-115.3.1Loss of Reactor Coolant From Small Ruptured Pipes or From Cracks in Large Pipes Which Actuate the Emergency Core Cooling System15.3-115.3.1.1Identification of Causes and Accident Description15.3-1 1-xlviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.3.1.2Analysis of Effects and Consequences15.3-215.3.1.3Reactor Coolant System Pipe Break Results15.3-315.3.1.4Conclusions - Thermal Analysis15.3-415.3.2Minor Secondary System Pipe Breaks15.3-515.3.2.1Identification of Causes and Accident Description15.3-515.3.2.2Analysis of Effects and Consequences15.3-5 15.3.2.3Conclusions15.3-515.3.3Inadvertent Loading of a Fuel Assembly Into an Improper Position15.3-515.3.3.1Identification of Causes and Accident Description15.3-5 15.3.3.2Analysis of Effects and Consequences15.3-615.3.3.3Conclusions15.3-715.3.4Complete Loss of Forced Reactor Coolant Flow15.3-7 15.3.4.1Identification of Causes and Accident Description15.3-715.3.4.2Analysis of Effects and Consequences15.3-815.3.4.3Conclusions15.3-9 15.3.5Waste Gas Decay Tank Rupture15.3-915.3.5.1Identification of Causes and Accident Description15.3-915.3.5.2Analysis of Effects and Consequences15.3-10 15.3.6Single Rod Cluster Control Assembly Withdrawal at Full Power15.3-1015.3.6.1Identification of Causes and Accident Description15.3-1015.3.6.2Analysis of Effects and Consequences15.3-11 15.3.6.3Conclusions15.3-1115.4CONDITION IV - LIMITING FAULTS15.4-115.4.1Major Reactor Coolant System Pipe Ru ptures (Loss of Coolant Accident)15.4-115.4.1.1Thermal Analysis15.4-315.4.1.2Hydrogen Production and Accumulation15.4-615.4.2Major Secondary System Pipe Rupture15.4-1215.4.2.1Major Rupture of a Main Steam Line15.4-1215.4.2.2Major Rupture of a Main Feedwater Pipe15.4-1915.4.3Steam Generator Tube Rupture15.4-2315.4.3.1Identification of Causes and Accident Description15.4-2315.4.3.2Analysis of Effects and Consequences15.4-26 15.4.3.3Conclusions15.4-3215.4.4Single Reactor Coolant Pump Locked Rotor15.4-3215.4.4.1Identification of Causes and Accident Description15.4-32 15.4.4.2Analysis of Effects and Consequences15.4-3215.4.4.3Conclusions15.4-3515.4.5Fuel Handling Accident15.4-3515.4.5.1Identification of Causes and Accident Description15.4-3515.4.5.2Analysis of Effects and Consequences15.4-35 15.4.6Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection)15.4-3515.4.6.1Identification of Causes and Accident Description15.4-35 Table of Contents1-xlixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.4.6.2Analysis of Effects and Consequences15.4-3915.4.6.3Conclusions15.4-4315.5ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS15.5-115.5.1Environmental Consequences of a Postulated Loss of AC Power to the Plant Auxil-iaries15.5-115.5.2Environmental Consequences of a Postulated Waste Gas Decay Tank Rupture15.5-215.5.3Environmental Consequences of a Postulated Loss of Coolant Accident15.5-215.5.4Environmental Consequences of a Postulated Steam Line Break15.5-1815.5.5Environmental Consequences of a Postulated Steam Generator Tube Rupture15.5-1915.5.6Environmental Consequences of a Po stulated Fuel Handling Accident15.5-2015.5.7Environmental Consequences of a Postulated Rod Ejection Accident15.5-22027_TVA_WB_FSAR_Section_16.pdf16.0TECHNICAL SPECIFICATIONS16.1PROPOSED TECHNICAL SPECIFICATIONS (NOT USED)16.1-116.2PROPOSED FINAL TECHNICAL SPECIFICATIONS16.2-116.3RELOCATED SPECIFICATIONS16.3-116.3.1Discussion16.3-116.3.2Document Control16.3-1 16.3.3Changes to the Relocated Specifications16.3-1028_TVA_WB_FSAR_Section_17.0.pdf17.0QUALITY ASSURANCE17.1Quality Assurance During Design and Construction17.1-117.1.1TVA Organization17.1-1 17.1.2Quality Assurance Program17.1-117.1AWESTINGHOUSE NUCLEAR ENERGY SYSTEM DIVISIONS QUALITY ASSUR-ANCE PLAN17.1-217.2QUALITY ASSURANCE FOR STATION OPERATION17.2-117.2.1Identification of Safety-Related Features17.2-1 1-lTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle PageTHIS PAGE INTENTIONALLY BLANK}}
+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 1-xxxviii                                                                        Table of Contents
+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 Table of Contents                                           1-xxxix
+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 1-xl                                                                         Table of Contents
+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 Table of Contents                                                               1-xli
+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 1-xlii                                                             Table of Contents
+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 Table of Contents                                                                                         1-xliii
+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 1-xliv                                                            Table of Contents
+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 Table of Contents                                                                                                 1-xlv
+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 1-xlvi                                                                        Table of Contents
+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 Table of Contents                                                                          1-xlvii
+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 1-xlviii                                                                   Table of Contents
+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 Table of Contents                                                                                            1-xlix
+WATTS BAR                                      WBNP-76 TABLE OF CONTENTS Section           Title                           Page THIS PAGE INTENTIONALLY BLANK 1-l                                     Table of Contents}}

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