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| number = ML093570483 | | number = ML093570483 | ||
| issue date = 12/14/2009 | | issue date = 12/14/2009 | ||
| title = | | title = Final Safety Analysis Report, Amendment 96, Table of Contents - Section 1 - Introduction and General Description of Plant | ||
| author name = | | author name = | ||
| author affiliation = Tennessee Valley Authority | | author affiliation = Tennessee Valley Authority | ||
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{{#Wiki_filter: | {{#Wiki_filter:WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 028_TVA_WB_FSAR_Section_17.0.pdf 027_TVA_WB_FSAR_Section_16.pdf 026_TVA_WB_FSAR_Section_15.pdf 024_TVA_WB_FSAR_Section_13.pdf 018_TVA_WB_FSAR_Section_8 017_TVA_WB_FSAR_Section_7.pdf 014_TVA_WB_FSAR_Section_5.pdf 013_TVA_WB_FSAR_Section_4.pdf 005_TVA_WB_FSAR_Section_2_B.pdf 004_TVA_WB_FSAR_Section_2_A.pdf 003_TVA_WB_FSAR_Section_1.pdf | ||
==1.0 INTRODUCTION== | |||
AND GENERAL DESCRIPTION OF PLANT | |||
==1.1 INTRODUCTION== | |||
1.1-1 1.2 GENERAL PLANT DESCRIPTION 1.2-1 1.2.1 Site Characteristics 1.2-1 1.2.1.1 Location 1.2-1 1.2.1.2 Demography 1.2-1 1.2.1.3 Meteorology 1.2-1 1.2.1.4 Hydrology 1.2-1 1.2.1.5 Geology 1.2-1 1.2.1.6 Seismology 1.2-2 1.2.2 Facility Description 1.2-2 1.2.2.1 Design Criteria 1.2-2 1.2.2.2 Nuclear Steam Supply System (NSSS) 1.2-2 1.2.2.3 Control and Instrumentation 1.2-4 1.2.2.4 Fuel Handling System 1.2-5 1.2.2.5 Waste Processing System 1.2-5 1.2.2.6 Steam and Power Conversion System 1.2-5 1.2.2.7 Plant Electrical System 1.2-6 1.2.2.8 Cooling Water 1.2-7 1.2.2.9 Component Cooling System 1.2-7 1.2.2.10 Chemical and Volume Control System 1.2-7 1.2.2.11 Sampling and Water Quality System 1.2-8 1.2.2.12 Ventilation 1.2-9 1.2.2.13 Fire Protection System 1.2-9 1.2.2.14 Compressed Air Systems 1.2-9 1.2.2.15 Engineered Safety Features 1.2-9 1.2.2.16 Shared Facilities and Equipment 1.2-10 1.2.3 General Arrangement of Major Structures and Equipment 1.2-13 1.3 COMPARISON TABLES 1.3-1 1.3.1 Comparisons With Similar Facility Designs 1.3-1 1.3.2 Comparison Of Final And Preliminary Designs 1.3-1 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 1.4-1 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.5-1 1.5.1 17 x 17 Fuel Assembly 1.5-1 1.5.1.1 Rod Cluster Control Spider Tests 1.5-1 1.5.1.2 Grid Tests 1.5-1 1.5.1.3 Fuel Assembly Structural Tests 1.5-1 1.5.1.4 Guide Tube Tests 1.5-2 1.5.1.5 Prototype Assembly Tests 1.5-2 Table of Contents 1-xxxvii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 1.9-2 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 1.9-3 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 1.9-4 1.9.1.12 Prestart Test Program 1.9-4 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 1.9-5 1.9.1.17 Vendor Information 1.9-5 1.9.1.18 Welding 1.9-5 1.9.2 Special Programs (SPs) 1.9-5 1.9.2.1 Concrete Quality Program 1.9-6 1.9.2.2 Containment Cooling 1.9-6 1.9.2.3 Detailed Control room Design Review 1.9-6 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) 1.9-7 1.9.2.8 Moderate Energy Line Break Flooding (MELB) 1.9-7 1.9.2.9 Radiation Monitoring System 1.9-7 1.9.2.10 Soil Liquefaction 1.9-7 1.9.2.11 Use-As-Is CAQs 1.9-7 1. | |||
== | ==9.3 REFERENCES== | ||
AND | 1.9-7 2.0 SITE CHARACTERISTICS 1-xxxviii Table of Contents | ||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 2.1-4 2.1.3.6 Population Density 2.1-4 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. | |||
==1 | ==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 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 Table of Contents 1-xxxix | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.3.3.3 Onsite Data Summaries of Parameters for Dispersion Meteorology 2.3-12 2.3.4 Short-Term (Accident) Diffusion Estimates 2.3-13 2.3.4.1 Objective 2.3-13 2.3.4.2 Calculation Results 2.3-15 2.3.5 Long-Term (Routine) Diffusion Estimates 2.3-16 2.4 HYDROLOGIC ENGINEERING 2.4-1 2.4.1 Hydrological Description 2.4-1 2.4.1.1 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 2.4-39 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 2.4-40 2.4.8 Cooling Water Canals and Reservoirs 2.4-41 2.4.9 Channel Diversions 2.4-42 2.4.10 Flooding Protection Requirements 2.4-42 2.4.11 Low Water Considerations 2.4-42 2.4.11.1 Low Flow in Rivers and Streams 2.4-42 2.4.11.2 Low Water Resulting From Surges, Seiches, or Tsunami 2.4-43 2.4.11.3 Historical Low Water 2.4-43 2.4.11.4 Future Control 2.4-43 2.4.11.5 Plant Requirements 2.4-44 2.4.12 Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents 2.4-45 2.4.12.1 Radioactive Liquid Wastes 2.4-45 2.4.12.2 Accidental Slug Releases to Surface Water 2.4-45 2.4.12.2.1 Calculations 2.4-46 2.4.12.3 Effects on Ground Water 2.4-47 2.4.13 Groundwater 2.4-48 1-xl Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.4.13.1 Description and On-Site Use 2.4-48 2.4.13.2 Sources 2.4-48 2.4.13.3 Accident Effects 2.4-50 2.4.13.4 Monitoring and Safeguard Requirements 2.4-50 2.4.13.5 Design Basis for Subsurface Hydrostatic Loading 2.4-51 2.4.14 Flooding Protection Requirements 2.4-51 2.4.14.1 Introduction 2.4-51 2.4.14.1.1 Design Basis Flood 2.4-51 2.4.14.1.2 Combinations of Events 2.4-52 2.4.14.1.3 Post Flood Period 2.4-52 2.4.14.1.4 Localized Floods 2.4-52 2.4.14.2 Plant Operation During Floods Above Grade 2.4-52 2.4.14.2.1 Flooding of Structures 2.4-52 2.4.14.2.2 Fuel Cooling 2.4-53 2.4.14.2.3 Cooling of Plant Loads 2.4-54 2.4.14.3 Warning Scheme 2.4-55 2.4.14.4 Preparation for Flood Mode 2.4-55 2.4.14.4.1 Reactor Initially Operating at Power 2.4-55 2.4.14.4.2 Reactor Initially Refueling 2.4-55 2.4.14.4.3 Plant Preparation Time 2.4-56 2.4.14.5 Equipment 2.4-56 2.4.14.5.1 Equipment Qualification 2.4-56 2.4.14.5.2 Temporary Modification and Setup 2.4-56 2.4.14.5.3 Electric Power 2.4-56 2.4.14.5.4 Instrument, Control, Communication and Ventilation Systems 2.4-57 2.4.14.6 Supplies 2.4-57 2.4.14.7 Plant Recovery 2.4-57 2.4.14.8 Warning Plan 2.4-58 2.4.14.8.1 Rainfall Floods 2.4-58 2.4.14.8.2 Seismically-Induced Dam Failure Floods 2.4-58 2.4.14.9 Basis For Flood Protection Plan In Rainfall Floods 2.4-59 2.4.14.9.1 Overview 2.4-59 2.4.14.9.2 TVA Forecast System 2.4-59 2.4.14.9.3 Basic Analysis 2.4-61 2.4.14.9.4 Hydrologic Basis for Warning System 2.4-61 2.4.14.9.5 Hydrologic Basis for Target States 2.4-62 2.4.14.9.6 Communications Reliability 2.4-63 2.4.14.10 Basis for Flood Protection Plan in Seismic-Caused Dam Failures 2.4-64 2.4.14.11 Special Condition Allowance 2.4-65 2.5 GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING | |||
==SUMMARY== | ==SUMMARY== | ||
OF FOUNDATION | 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 Table of Contents 1-xli | ||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.5.1.1.1 Regional Physiography 2.5-3 2.5.1.1.2 Regional Tectonics and Geology 2.5-7 2.5.1.1.3 Regional Geologic Setting 2.5-9 2.5.1.1.4 Regional Geologic History 2.5-10 2.5.1.1.5 Regional Lithologic, Stratigraphic, and Structural Geology 2.5-20 2.5.1.1.6 Regional Tectonics 2.5-22 2.5.1.1.7 Groundwater 2.5-26 2.5.1.2 Site Geology 2.5-26 2.5.1.2.1 Site Physiography 2.5-26 2.5.1.2.2 Site Lithologic, Stratigraphic, and Structural Geologic Conditions 2.5-27 2.5.1.2.3 Site Structural Geology 2.5-29 2.5.1.2.4 Surface Geology 2.5-30 2.5.1.2.5 Site Geologic History 2.5-31 2.5.1.2.6 Plot Plan 2.5-31 2.5.1.2.7 Bedrock Foundation Characteristics 2.5-31 2.5.1.2.8 Excavation and Backfill 2.5-31 2.5.1.2.9 Evaluation of Geologic Conditions 2.5-32 2.5.1.2.10 Groundwater 2.5-33 2.5.1.2.11 Geophysical Surveys 2.5-33 2.5.1.2.12 Soil and Rock Properties 2.5-34 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 2.5-41 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 2.5-42 2.5.2.5 Seismic Wave Transmission Characteristics of the Site 2.5-44 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 2.5-56 2.5.4.1 Geologic Features 2.5-56 2.5.4.2 Properties of Subsurface Materials 2.5-57 2.5.4.2.1 In Situ Soils 2.5-57 General Description 57 Investigations 57 1-xlii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page Test Results and Selection of Design Properties 61 2.5.4.2.2 Rock 2.5-74 Engineering Description of Bedrock 74 Test Program 75 Description of Testing Techniques 75 Test Results for Menard Pressuremeter 77 Comparison of Results from Menard Pressuremeter and Birdwell 3D Sonic Logger 78 Settlement Analysis 78 Behavior of Watts Bar Lock 83 Excavation Experience in the Rutledge Shale at Watts Bar Lock 85 Evaluation of Settlement 86 2.5.4.3 Exploration 2.5-89 2.5.4.4 Geophysical Surveys 2.5-90 2.5.4.4.1 Rock Characteristics 2.5-90 2.5.4.4.2 Soil Characteristics 2.5-90 Equipment 90 Velocity Measurement Procedures 90 Data Analysis and Results 91 Data Analysis and Results - Evaluation Seismic Criteria and New 93 2.5.4.5 Excavations and Backfill 2.5-93 2.5.4.5.1 Earthfill 2.5-93 Investigation 93 Test Results 94 Field Work 97 Construction Control 98 2.5.4.5.2 Granular Fill 2.5-98 General 98 Section 1032 Material 98 Section 1075 Material 100 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 2.5-113 2.5.4.10 Static Analysis 2.5-113 2.5.4.10.1 Settlement 2.5-113 2.5.4.10.2 Bearing Capacity 2.5-114 2.5.4.11 Safety-Related Criteria for Foundations 2.5-115 2.5.4.11.1 General 2.5-115 2.5.4.11.2 Rock Strength 2.5-115 2.5.4.11.3 Soil Strength 2.5-115 2.5.4.12 Techniques to Improve Subsurface Conditions 2.5-115 2.5.4.13 Construction Notes 2.5-118 2.5.5 Stability of Slopes 2.5-118 2.5.5.1 Slope Characteristics 2.5-118 Table of Contents 1-xliii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.5.5.1.1 Essential Raw Cooling Water Intake Channel Slopes 2.5-118 2.5.5.1.2 Underground Barrier for Protection Against Potential Soil Liquefaction 2.5-118 2.5.5.2 Design Criteria and Analysis 2.5-120 2.5.5.2.1 Design Criteria and Analyses for the Essential Raw Coolant Water 2.5-120 2.5.5.2.2 Additional Analyses Due to Unexpected Soil Conditions Encountered During Excavation of the Intake Channel 2.5-123 2.5.5.2.3 Design Criteria and Analysis for the Underground Barrier for the ERCW Pipeline and 1E Conduit Alignment 2.5-125 2.5.5.3 Logs of Borings 2.5-127 2.5.5.4 Compaction Specifications 2.5-127 2.5.6 Embankments 2.5-127 3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 3.1-1 3.1.1 Introduction 3.1-1 3.1.2 WBNP Conformance with GDCs 3.1-1 3.1.2.1 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 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 1-xliv Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 3.5.1.1.1 Shield Building 3.5-2 3.5.1.1.2 North and South Steam Valve Rooms 3.5-2 3.5.1.1.3 Auxiliary Building 3.5-3 3.5.1.1.4 Control Building 3.5-4 3.5.1.1.5 ERCW Structures 3.5-4 3.5.1.1.6 ERCW Pipe Tunnels and RWST Foundations 3.5-4 3.5.1.1.7 Diesel Generator Building 3.5-4 3.5.1.2 Internally Generated Missiles (Inside Containment) 3.5-5 3.5.1.2.1 Missile Selection 3.5-5 3.5.1.2.2 Missile Description 3.5-7 3.5.1.2.3 Electrical Cables 3.5-8 3.5.1.2.4 Upper Compartment 3.5-8 3.5.1.2.5 Ice Condenser Compartment 3.5-8 3.5.1.2.6 Lower Compartment 3.5-8 3.5.1.3 Turbine Missiles 3.5-9 3.5.1.3.1 Introduction 3.5-9 3.5.1.3.2 Potential Missile Sources and Missile Characteristics 3.5-10 3.5.1.3.3 Primary Safety-Related Equipment Installations and Structures 3.5-15 3.5.1.3.4 Turbine Missile Protection Criterion 3.5-15 3.5.1.3.5 Turbine Missile Hazard Evaluation 3.5-16 3.5.1.3.6 Turbine Missile Selection 3.5-22 3.5.1.4 Missiles Generated By Natural Phenomena 3.5-23 3.5.1.5 Missiles Generated by Events Near the Site. 3.5-23 3.5.1.6 Aircraft Hazards 3.5-24 3.5.2 Systems To Be Protected 3.5-24 3.5.3 Barrier Design Procedures 3.5-25 3.5.3.1 Additional Diesel Generator Building (And Other Category I Structures Added After July 1979) 3.5-28 3.5.A ESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES 3.5-1 Table of Contents 1-xlv | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING 3.6-1 3.6A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIPING) 3.6-1 3.6A.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment 3.6-8 3.6A.1.1 Design Bases 3.6-8 3.6A.1.1.1 List of Potential Targets 3.6-8 3.6A.1.1.2 Interaction Criteria 3.6-8 3.6A.1.1.3 Acceptability Criteria 3.6-9 3.6A.1.1.4 Protective Measures 3.6-10 3.6A.1.2 Description of Piping System Arrangement 3.6-10 3.6A.1.3 Safety Evaluation 3.6-10 3.6A.2 Determination of Break Locations and Dynamic Effects Associated with the Postu-lated Rupture of Piping 3.6-11 3.6A.2.1 Criteria Used to Define Break and Crack Location and Configuration 3.6-11 3.6A.2.1.1 Pipe Failure Type, Size, and Orientation 3.6-11 3.6A.2.1.2 Break Location 3.6-12 3.6A.2.1.3 Failure Consequences 3.6-15 3.6A.2.1.4 Flooding 3.6-16 3.6A.2.1.5 Leak-Before-Break Application 3.6-17 3.6A.2.2 Analytical Methods to Define Forcing Functions and Response Models 3.6-17 3.6A.2.2.1 Assumptions 3.6-17 3.6A.2.2.2 Blowdown Thrust Loads 3.6-17 3.6A.2.2.3 Jet Impingement Loads 3.6-19 3.6A.2.3 Dynamic Analysis Methods to Verify Integrity and Operability 3.6-21 3.6A.2.3.1 General Criteria for Pipe Whip Evaluation 3.6-21 3.6A.2.3.2 Main Reactor Coolant Loop Piping System 3.6-21 3.6A.2.3.3 Other Piping Systems 3.6-21 3.6A.2.3.4 Simplified Pipe Whip Analysis 3.6-22 3.6A.2.3.5 Pipe Whip Restraint Design 3.6-23 3.6A.2.3.6 Energy Absorbing Materials 3.6-24 3.6A.2.4 Guard Pipe Assembly Design Criteria 3.6-24 3.6A.2.5 Summary of Dynamic Analysis Results 3.6-25 3.6A.2.5.1 Stress Summary and Isometrics - Inside Containment 3.6-25 3.6A.2.5.2 Summary of Protection Requirements and Isometrics-Outside Contain-ment 3.6-26 3.6B PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING 3.6-26 3.6B.1 Break Locations And Dynamic Effects Associated With Postulated Primary Loop Pipe Rupture 3.6-26 3.6B.2 Analytical Methods to Define Forcing Function and Response Models 3.6-27 3.6B.3 Dynamic Analysis of the Reactor Coolant Loop Piping Equipment Supports and Pipe Whip Restraints 3.6-29 1-xlvi Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 3.7.1.1.1 Original Site Ground Response Spectra (Set A and Set C) 3.7-2 3.7.1.1.2 Site Specific Ground Response Spectra (Set B) 3.7-2 3.7.1.2 Design Time Histories 3.7-2 3.7.1.2.1 Time Histories for Original Site Ground Response Spectra (Set A and Set C) 3.7-2 3.7.1.2.2 Time Histories for Site Specific Ground Response Spectra (Set B) 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 3.7.2.1.1 Category I Rock-Supported Structures - Original Analyses (Set A) 3.7-4 3.7.2.1.2 Category I Rock - Supported Structures - Evaluation and New Design or Modification Analyses (Set B and Set B+C) 3.7-9 3.7.2.1.3 Category I Soil-Supported Structures - Original Analysis (Set A) 3.7-13 3.7.2.1.4 Category I Soil-Supported Structures - Evaluation and New Design/Mod-ification Analysis (Set B and Set B+C) 3.7-18 3.7.2.1.5 Category I Pile-Supported Structures - Original Analysis (Set A) 3.7-19 3.7.2.1.6 Category I Pile-Supported Structures - Evaluation and New Design/Mod-ification Analyses (Set B and Set B+C) 3.7-21 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 3.7.2.3.1 Other Than NSSS 3.7-22 3.7.2.3.2 For NSSS Analysis 3.7-22 3.7.2.4 Soil/Structure Interaction 3.7-23 3.7.2.4.1 Original Analysis (Set A) 3.7-23 3.7.2.4.2 Evaluation and New Design or Modification Analyses3.7-23 3.7.2.5 Development of Floor Response Spectra 3.7-24 3.7.2.5.1 Original Analysis 3.7-24 3.7.2.5.2 Evaluation and New Design or Modification Analysis 3.7-24 3.7.2.6 Three Components of Earthquake Motion 3.7-25 3.7.2.6.1 Original Analysis (Set A) 3.7-25 3.7.2.6.2 Evaluation and New Design/Modification Analyses (Set B and Set C) 3.7-25 3.7.2.7 Combination of Modal Responses 3.7-26 3.7.2.7.1 Other Than NSSS 3.7-26 Original Analysis (Set A) 26 Evaluation and New Design or Modification Analyses 26 3.7.2.7.2 NSSS System 3.7-27 3.7.2.8 Interaction of Non-Category I Structures With Seismic Category I Structures 3.7-29 Table of Contents 1-xlvii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 3.7.2.10.1 Other Than NSSS 3.7-29 Original Analysis (Set A) 29 Evaluation and New Design or Modification Analyses 30 3.7.2.10.2 For NSSS 3.7-30 3.7.2.11 Methods Used to Account for Torsional Effects 3.7-30 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 3.7-31 3.7.2.14 Determination of Category I Structure Overturning Moments 3.7-31 3.7.2.14.1 Original Analysis 3.7-31 3.7.2.14.2 Evaluation and New Design or Modification Analysis 3.7-31 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 3.7.3.2.1 Category I Systems and Components Other Than NSSS 3.7-32 3.7.3.2.2 NSSS System 3.7-33 3.7.3.3 Procedure Used for Modeling 3.7-33 3.7.3.3.1 Other Than NSSS 3.7-33 Modeling of Piping Systems for Detailed Rigorous Analysis 33 Modeling of Equipment 33 Modeling of HVAC, Conduit, and Cable Tray Subsystems 33 3.7.3.3.2 Modeling of NSSS Subsystems 3.7-34 3.7.3.4 Basis for Selection of Frequencies 3.7-34 3.7.3.4.1 Other Than NSSS 3.7-34 3.7.3.4.2 NSSS Basis for Selection of Forcing Frequencies 3.7-34 3.7.3.5 Use of Equivalent Static Load Method of Analysis 3.7-35 3.7.3.5.1 Other Than NSSS 3.7-35 3.7.3.5.2 Use of Equivalent Static Load Method of Analysis for NSSS 3.7-36 3.7.3.6 Three Components of Earthquake Motion 3.7-36 3.7.3.6.1 Piping Subsystems 3.7-36 3.7.3.6.2 HVAC Ducting, Conduit, and Cable Tray Subsystems 3.7-36 3.7.3.6.3 Other Than NSSS Equipment and Components 3.7-36 3.7.3.7 Combination of Modal Responses 3.7-37 3.7.3.7.1 Other Than NSSS 3.7-37 3.7.3.7.2 Combination of Modal Responses of NSSS 3.7-37 3.7.3.8 Analytical Procedures for Piping Other Than NSSS 3.7-37 3.7.3.8.1 General 3.7-37 3.7.3.8.2 Detailed Seismic Analysis (Rigorous) for Piping Systems 3.7-41 3.7.3.8.3 Alternate (Simplified) Analysis for Piping Systems 3.7-43 3.7.3.8.4 Seismic Analysis of Piping Systems That Span Two or More Seismic Sup-port Zones Such as Buildings, Portions of Buildings, or Primary Compo-nents 3.7-44 1-xlviii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.7.3.9 Multiple Supported Equipment and Components with Distinct Inputs 3.7-44 3.7.3.9.1 Other Than NSSS 3.7-44 3.7.3.9.2 Multiple Supported NSSS Equipment and Components with Distinct In-puts 3.7-44 3.7.3.10 Use of Constant Vertical Load Factors 3.7-45 3.7.3.10.1 Use of Constant Load Factors for Equipment Other Than NSSS 3.7-45 3.7.3.10.2 Use of Constant Vertical Load Factors for NSSS 3.7-45 3.7.3.11 Torsional Effects of Eccentric Masses 3.7-45 3.7.3.11.1 Piping Other Than NSSS 3.7-45 3.7.3.11.2 Torsional Effects of Eccentric Masses of NSSS 3.7-46 3.7.3.12 Buried Seismic Category I Piping Systems 3.7-46 3.7.3.13 Interaction of Other Piping with Seismic Category I Piping 3.7-52 3.7.3.14 Seismic Analyses for Fuel Elements, Control Rod Assemblies, Control Rod Drives, and Reactor Internals 3.7-52 3.7.3.15 Analysis Procedure for Damping 3.7-54 3.7.3.16 Seismic Analysis and Qualification of Category I Equipment Other Than NSSS 3.7-54 3.7.3.16.1 Dynamic Analysis Method For Equipment and Components 3.7-55 3.7.3.16.2 Simplified Dynamic Analysis Method For Equipment and Components 3.7-55 3.7.3.16.3 Equivalent Static Load Method 3.7-56 3.7.3.16.4 Testing Method 3.7-56 3.7.3.16.5 Equipment and Component Mounting Considerations 3.7-56 3.7.3.17 Seismic Analysis and Design of HVAC Duct and Duct Support Systems 3.7-57 3.7.3.17.1 Description of HVAC Duct and Duct Support Subsystems 3.7-57 3.7.3.17.2 Applicable Codes, Standards, and Specifications 3.7-57 3.7.3.17.3 Loads and Load Combinations 3.7-58 3.7.3.17.4 Analysis and Design Procedures 3.7-59 3.7.3.17.5 Structural Acceptance Criteria 3.7-59 3.7.3.17.6 Materials and Quality Control 3.7-60 3.7.3.18 Seismic Qualification of Main Control Room Suspended Ceiling and Air Deliv-ery Components 3.7-61 3.7.4 Seismic Instrumentation Program 3.7-61 3.7.4.1 Comparison with Regulatory Guide 1.12 3.7-61 3.7.4.2 Location and Description of Instrumentation 3.7-61 3.7.4.3 Control Room Operator Notification 3.7-64 3.7.4.4 Controlled Shutdown Logic 3.7-64 3.7.4.5 Comparison of Measured and Predicted Responses 3.7-65 3.7.4.5.1 Retrieval of Data 3.7-65 3.7.4.5.2 Evaluation of Recorded Earthquake 3.7-66 3.8 DESIGN OF CATEGORY I STRUCTURES 3.8-1 3.8.1 Concrete Shield Building 3.8-1 Table of Contents 1-xlix | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.1.1 Description of the Shield Building 3.8-1 3.8.1.1.1 Equipment Hatch Doors and Sleeves 3.8-2 3.8.1.2 Applicable Codes, Standards, and Specifications 3.8-3 3.8.1.3 Loads and Loading Combinations 3.8-5 3.8.1.4 Design and Analysis Procedures 3.8-7 3.8.1.5 Structural Acceptance Criteria 3.8-10 3.8.1.6 Materials, Quality Control and Special Construction Techniques 3.8-11 3.8.1.6.1 Materials 3.8-11 3.8.1.6.2 Quality Control 3.8-12 3.8.1.6.3 Construction Techniques 3.8-13 3.8.2 Testing and Inservice Surveillance Requirements 3.8-13 3.8.2 Steel Containment System 3.8-1 3.8.2.1 Description of the Containment and Penetrations 3.8-1 3.8.2.1.1 Description of the Containment 3.8-1 3.8.2.1.2 Description of Penetrations 3.8-1 3.8.2.2 Applicable Codes, Standards and Specifications 3.8-3 3.8.2.2.1 Codes 3.8-3 3.8.2.2.2 Design Specification Summary 3.8-4 3.8.2.2.3 NRC Regulatory Guides 3.8-6 3.8.2.3 Loads and Loading Combinations 3.8-7 3.8.2.3.1 Design Loads 3.8-7 3.8.2.3.2 Loading Conditions 3.8-9 3.8.2.4 Design and Analysis Procedures 3.8-11 3.8.2.4.1 Introduction 3.8-11 3.8.2.4.2 Static Stress Analysis 3.8-12 3.8.2.4.3 Dynamic Seismic Analysis 3.8-12 3.8.2.4.4 Non-Axisymmetric Pressure Loading Analysis 3.8-13 3.8.2.4.5 Thermal Analysis 3.8-14 3.8.2.4.6 Penetrations Analysis 3.8-14 3.8.2.4.7 Interaction of Containment and Attached Equipment 3.8-16 3.8.2.4.8 Anchorage 3.8-17 3.8.2.5 Structural Acceptance Criteria 3.8-18 3.8.2.5.1 Margin of Safety 3.8-18 3.8.2.6 Materials, Quality Control, and Special Construction Techniques 3.8-18 3.8.2.6.1 Materials - General 3.8-18 3.8.2.6.2 Corrosion Protection 3.8-21 3.8.2.6.3 Protective Coatings 3.8-23 3.8.2.6.4 Tolerances 3.8-24 3.8.2.6.5 Vessel Material Inspection and Test 3.8-24 3.8.2.6.6 Impact Testing 3.8-25 3.8.2.6.7 Post-Weld Heat Treatment 3.8-25 3.8.2.6.8 Welding 3.8-25 3.8.2.7 Testing and Inservice Inspection Requirements 3.8-25 1-l Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.2.7.1 Bottom Liner Plates Test 3.8-25 3.8.2.7.2 Vertical Wall and Dome Tests 3.8-25 3.8.2.7.3 Soap Bubble Tests 3.8-25 3.8.2.7.4 Overpressure Tests 3.8-26 3.8.2.7.5 Leakage Rate Test 3.8-26 3.8.2.7.6 Operational Testing 3.8-26 3.8.2.7.7 Leak Testing Airlocks 3.8-26 3.8.2.7.8 Penetration Tests 3.8-27 3.8.2.7.9 Inservice Inspection Requirements 3.8-27 3.8.3 Concrete Interior Structure 3.8-1 3.8.3.1 Description of the Interior Structure 3.8-1 3.8.3.2 General 3.8-1 3.8.3.3 Containment Floor Structural Fill Slab 3.8-1 3.8.3.4 Reactor Cavity Wall 3.8-2 3.8.3.5 Compartment Above Reactor 3.8-2 3.8.3.6 Refueling Canal Walls and Floor (Divider Barrier) 3.8-3 3.8.3.7 Crane Wall 3.8-3 3.8.3.8 Steam Generator Compartments (Divider Barrier) 3.8-5 3.8.3.9 Pressurizer Compartment (Divider Barrier) 3.8-5 3.8.3.10 Divider Deck at Elevation 756.63 (Divider Barrier) 3.8-5 3.8.3.11 Ice Condenser Support Floor - Elevation 744.5 (Divider Barrier) 3.8-5 3.8.3.12 Penetrations Through the Divider Barrier Canal Gate 3.8-6 3.8.3.13 Applicable Codes, Standards and Specifications 3.8-7 3.8.3.14 Loads and Loading Combinations 3.8-13 3.8.3.15 Design and Analysis Procedures 3.8-16 3.8.3.16 General 3.8-16 3.8.3.17 Structural Fill Slab on Containment Floor 3.8-16 3.8.3.18 Reactor Cavity Wall 3.8-16 3.8.3.19 Compartment Above Reactor 3.8-18 3.8.3.20 Seals Between Upper and Lower Compartments 3.8-18 3.8.3.21 Refueling Canal Walls and Floor (Divider Barrier) 3.8-19 3.8.3.22 Crane Wall 3.8-20 3.8.3.23 Steam Generator Compartments (Divider Barrier) 3.8-23 3.8.3.24 Pressurizer Compartment (Divider Barrier) 3.8-25 3.8.3.25 Operating Deck at Elevation 756.63 (Divider Barrier) 3.8-26 3.8.3.26 Ice Condenser Support Floor Elevation 744.5 (Divider Barrier) 3.8-27 3.8.3.27 Ice Condenser 3.8-28 3.8.3.28 Penetrations Through the Divider Barrier 3.8-29 3.8.3.29 Structural Acceptance Criteria 3.8-31 3.8.3.30 General 3.8-31 3.8.3.31 Structural Fill Slab on Containment Floor 3.8-31 3.8.3.32 Reactor Cavity Wall and Compartment Above Reactor 3.8-31 3.8.3.33 Refueling Canal Walls and Floor 3.8-32 Table of Contents 1-li | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.3.34 Crane Wall 3.8-32 3.8.3.35 Steam Generator and Pressurizer Compartment 3.8-32 3.8.3.36 Operating Deck at Elevation 756.63 3.8-32 3.8.3.37 Ice Condenser Support Floor Elevation 744.5 3.8-32 3.8.3.38 Penetrations Through the Divider Barrier 3.8-32 3.8.3.39 Personnel Access Doors in Crane Wall 3.8-33 3.8.3.40 Seals Between Upper and Lower Compartments 3.8-33 3.8.3.41 Ice Condenser 3.8-33 3.8.3.42 Materials, Quality Control and Special Construction Techniques 3.8-34 3.8.3.43 Materials 3.8-34 3.8.3.44 Quality Control 3.8-35 3.8.3.45 Construction Technique 3.8-36 3.8.3.46 Ice Condenser 3.8-36 3.8.3.47 Testing and Inservice Surveillance Requirements 3.8-38 3.8.3.48 Environmental Effects 3.8-38 3.8.3.49 Interface Control 3.8-39 3.8.4 Other Category I Structures 3.8-1 3.8.4.1 Description of the Structures 3.8-1 3.8.4.2 Auxiliary-Control Building 3.8-1 3.8.4.3 Diesel Generator Building 3.8-10 3.8.4.4 Category I Water Tanks and Pipe Tunnels 3.8-12 3.8.4.5 Class 1E Electrical System Manholes and Duct Runs 3.8-13 3.8.4.6 North Steam Valve Room 3.8-13 3.8.4.7 Intake Pumping Station and Retaining Walls 3.8-14 3.8.4.8 Miscellaneous Essential Raw Cooling Water (ERCW) Structures 3.8-15 3.8.4.9 Additional Diesel Generator Building 3.8-16 3.8.4.10 Applicable Codes, Standards, and Specifications 3.8-17 3.8.4.11 List of Documents 3.8-17 3.8.4.12 Basis for Use of the 1963 Edition of ACI 318 3.8-19 3.8.4.13 Loads and Loading Combinations 3.8-21 3.8.4.14 Description of Loads 3.8-21 3.8.4.15 Load Combinations and Allowable Stresses 3.8-22 3.8.4.16 Design and Analysis Procedures 3.8-23 3.8.4.17 Auxiliary-Control Building 3.8-23 3.8.4.18 Diesel Generator Building 3.8-30 3.8.4.19 Category I Water Tanks and Pipe Tunnels 3.8-31 3.8.4.20 Class 1E Electrical System Manholes 3.8-31 3.8.4.21 North Steam Valve Room 3.8-31 3.8.4.22 Intake Pumping Station and Retaining Walls Pumping Station 3.8-32 3.8.4.23 Miscellaneous ERCW Structures 3.8-32 3.8.4.24 Additional Diesel Generator Building 3.8-33 3.8.4.25 Structural Acceptance Criteria 3.8-35 3.8.4.26 Concrete 3.8-35 1-lii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.4.27 Structural and Miscellaneous Steel 3.8-35 3.8.4.28 Miscellaneous Components of the Auxiliary Building 3.8-36 3.8.4.29 Intake Pumping Station Traveling Water Screens 3.8-37 3.8.4.30 Diesel Generator Building Doors and Bulkheads 3.8-37 3.8.4.31 Additional Diesel Generator Building Missile Barriers 3.8-37 3.8.4.32 Materials, Quality Control, and Special Construction Techniques General 3.8-37 3.8.4.33 Materials 3.8-37 3.8.4.34 Quality Control 3.8-38 3.8.4.35 Special Construction Techniques 3.8-38 3.8.4.36 Testing and Inservice Surveillance Requirements 3.8-38 3.8.4.37 Concrete and Structural Steel Portions of Structures 3.8-38 3.8.4.38 Miscellaneous Components of Auxiliary-Control Building 3.8-39 3.8.4.39 Deleted by Amendment 79 3.8-40 3.8.4.40 Miscellaneous Components of the Intake Pumping Station 3.8-40 3.8.5 Foundations and Concrete Supports 3.8-1 3.8.5.1 Description of Foundations and Supports 3.8-1 3.8.5.1.1 Primary Containment 3.8-1 3.8.5.1.2 Foundations of Other Category I Structures 3.8-1 3.8.5.2 Applicable Codes, Standards, and Specifications 3.8-3 3.8.5.3 Loads and Loading Combinations 3.8-3 3.8.5.4 Design and Analysis Procedure 3.8-4 3.8.5.4.1 Primary Containment Foundation 3.8-4 3.8.5.4.2 Auxiliary-Control Building 3.8-4 3.8.5.4.3 Intake Pumping Station 3.8-4 3.8.5.4.4 Soil-Supported Structures 3.8-4 3.8.5.4.5 Pile Supported Structures 3.8-5 3.8.5.5 Structural Acceptance Criteria 3.8-5 3.8.5.5.1 Primary Containment Foundation 3.8-5 3.8.5.5.2 Foundations of Other Category I Structures Auxiliary-Control Building 3.8-5 3.8.5.6 Materials, Quality Control, and Special Construction Techniques 3.8-6 3.8.5.6.1 Materials 3.8-6 3.8.5.6.2 Quality Control 3.8-7 3.8.5.6.3 Special Construction Techniques 3.8-7 3.8.6 Category I(L) Cranes 3.8-1 3.8.6.1 Polar Cranes 3.8-1 3.8.6.1.1 Description 3.8-1 3.8.6.1.2 Applicable Codes, Standards, and Specifications 3.8-1 3.8.6.1.3 Loads, Loading Combinations, and Allowable Stresses 3.8-2 3.8.6.1.4 Design and Analysis Procedure 3.8-2 3.8.6.1.5 Structural Acceptance Criteria 3.8-2 3.8.6.1.6 Materials, Quality Controls, and Special Construction Techniques 3.8-3 3.8.6.1.7 Testing and Inservice Surveillance Requirements 3.8-3 Table of Contents 1-liii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.6.1.8 Safety Features 3.8-3 3.8.6.2 Auxiliary Building Crane 3.8-4 3.8.6.2.1 Description 3.8-4 3.8.6.2.2 Applicable Codes, Standards, and Specifications 3.8-5 3.8.6.2.3 Loads, Loading Combinations, and Allowable Stresses 3.8-5 3.8.6.2.4 Design and Analysis Procedure 3.8-5 3.8.6.2.5 Structural Acceptance Criteria 3.8-6 3.8.6.2.6 Materials, Quality Controls, and Special Construction Techniques 3.8-6 3.8.6.2.7 Testing and Inservice Surveillance Requirements 3.8-7 3.8.6.2.8 Safety Features 3.8-7 3.8A SHELL TEMPERATURE TRANSIENTS 3.8-1 3.8B BUCKLING STRESS CRITERIA 3.8-1 3.8B.1 INTRODUCTION 3.8-1 3.8B.2 SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS 3.8-1 3.8B.2.1 Circular Cylindrical Shells Under Axial Compression 3.8-1 3.8B.2.2 Circular Cylindrical Shells in Circumferential Compression 3.8-2 3.8B.2.3 Circular Cylindrical Shells Under Torsion 3.8-2 3.8B.2.4 where a is the effective length and b is the circumference of the cylinder. The coefficient K's is given in Figure 3.8B-10.Circular Cylindrical Shells Under Bending 3.8-3 3.8B.2.5 Circular Cylindrical Shell Under Combined Loads 3.8-3 3.8B.3 SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND VERTICAL STIFFENERS 3.8-5 3.8B.4 SPHERICAL SHELLS 3.8-7 3.8B.2.1 The critical buckling stress in the spherical dome, except for external pressure, was determined by the following equation: 3.8-7 3.8B.2.2 Spherical Shell Under Combined Loads 3.8-7 3.8B.3 FACTOR OF SAFETY 3.8-8 3.8C DOCUMENTATION OF CB&I COMPUTER PROGRAMS 3.8-1 3.8C.1 INTRODUCTION 3.8-1 3.8C.2 PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN VALUE TECHNIQUE 3.8-1 3.8C.3 PROGRAM 1044-SEISMIC ANALYSIS of VESSEL APPENDAGES 3.8-1 3.8C.4 PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS DIGITIZED AT EQUAL INTERVALS 3.8-3 3.8C.5 PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS 3.8-3 3.8C.6 PROGRAM E1623-POST PROCESSOR PROGRAM FOR PROGRAM E1374 3.8-4 3.8C.7 PROGRAM E1374-SHELL DYNAMIC ANALYSIS 3.8-5 3.8C.7.1 Introduction 3.8-5 3.8C.8 PROGRAM E1622-LOAD GENERATION PREPROCESSOR FOR PROGRAM E1374 3.8-6 1-liv Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8C.9 PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION 3.8-7 3.8C.10 PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS 3.8-7 3.8C.11 PROGRAM 119-CHECK of FLANGE DESIGN 3.8-7 3.8C.12 PROGRAM 772-NOZZLE REINFORCEMENT CHECK 3.8-7 3.8C.13 PROGRAM 1027-WRC 107 STRESS INTENSITIES AT LOADED ATTACH-MENTS FOR SPHERES OR CYLINDERS WITH ROUND OR SQUARE ATTACHMENT 3.8-8 3.8C.14 PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES 3.8-8 3.8D COMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS 3.8-1 3.8E CODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFICATION AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF NEW FEA-TURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIAT-ED AFTER JULY 1979 3.8-1 3.8E.1 Application Codes and Standards 3.8-1 3.8E.2 Load Definitions 3.8-1 3.8E.3 Load Combinations - Concrete 3.8-3 3.8E.4 Load Combinations - Structural Steel 3.8-5 3.9 MECHANICAL SYSTEMS AND COMPONENTS 3.9-1 3.9.1 General Topic for Analysis of Seismic Category I ASME Code and Non-Code Items 3.9-1 3.9.1.1 Design Transients 3.9-1 3.9.1.2 Computer Programs Used in Analysis and Design 3.9-1 3.9.1.2.1 Other Than NSSS Systems, Components, Equipment, and Supports 3.9-1 3.9.1.2.2 Programs Used for Category I Components of NSSS 3.9-3 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 3.9.1.4.1 Subsystems and Components Analyzed by Westinghouse 3.9-3 3.9.1.4.2 Subsystems and Components Analyzed by TVA 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 3.9.2.5.1 Evaluation of Reactor Internals for Limited Displacement RPV Inlet and Outlet Nozzle Break 3.9-17 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 Table of Contents 1-lv | |||
Section | WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.9.3.1 Loading Combinations, Design Transients, and Stress Limits 3.9-20 3.9.3.1.1 Subsystems and Components Supplied by Westinghouse 3.9-20 Plant Conditions and Design Loading Combinations For ASME Code Class 2 and 3 Components Supplied by Westinghouse 21 Design Loading Combinations by Westinghouse 21 Design Stress Limits By Westinghouse 22 3.9.3.1.2 Subsystems and Components Analyzed or Specified by TVA 3.9-22 3.9.3.2 Pumps and Valve Operability Assurance 3.9-27 3.9.3.2.1 Active* ASME Class 1, 2, & 3 Pumps and Valves 3.9-27 3.9.3.2.2 Operability Assurance 3.9-28 Westinghouse Scope of Supply 28 TVA Scope of Supply 33 3.9.3.2.3 Criteria For Assuring Functional Adequacy of Active Seismic Category I Fluid System Components (Pumps and Valves) and Associated Essential Auxiliary Equipment 3.9-34 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 3.9.3.4.1 Subsystem and Component Supports Analyzed or Specified by Westing-house 3.9-42 3.9.3.4.2 Subsystem and Component Supports Analyzed or Specified by TVA 3.9-43 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 3.9-46 3.9.4.3 Design Loadings, Stress Limits, and Allowable Deformations 3.9-46 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 EQUIP-MENT 3.10-1 3.10.1 Seismic Qualification Criteria 3.10-1 3.10.2 Methods And Procedures For Qualifying Electrical Equipment And Instrumentation 3.10-6 3.10.3 Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumen-tation and Cables 3.10-6 3.10.3.1 Electrical Equipment and Instrumentation Assemblies 3.10-7 3.10.3.2 Cable Trays and Supports 3.10-7 3.10.3.2.1 Cable Trays 3.10-7 3.10.3.2.2 Supports 3.10-7 1-lvi Table of Contents | ||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.10.3.3 Conduit and Supports 3.10-8 3.10.3.3.1 Conduit 3.10-8 3.10.3.3.2 Supports 3.10-8 3.10.3.4 Conduit Banks 3.10-9 3.10.4 Operating License Review 3.10-9 3.10.4.1 TVA Supplied Instrumentation and Electrical Equipment 3.10-9 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT 3.11-1 3.11.1 Equipment Identification and Environmental Conditions 3.11-1 3.11.1.1 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 3.11.7.2.1 Inside Containment 3.11-5 3.11.7.2.2 Radiation - Auxiliary Building Spaces 3.11-6 4.0 REACTOR 4.1 | |||
==SUMMARY== | ==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 4.2.1.1.1 Fuel Rods 4.2-2 4.2.1.1.2 Fuel Assembly Structure 4.2-3 4.2.1.2 Design Description 4.2-5 4.2.1.2.1 Fuel Rods4.2-6 4.2.1.2.2 Fuel Assembly Structure 4.2-6 4.2.1.3 Design Evaluation 4.2-10 4.2.1.3.1 Fuel Rods 4.2-10 4.2.1.3.2 Fuel Assembly Structure 4.2-17 4.2.1.3.3 Operational Experience 4.2-18 4.2.1.3.4 Test Rod and Test Assembly Experience 4.2-18 4.2.1.3.5 Evaluation of the Reactor Core for a Limiting LOCA Load - Accumulator Line Break 4.2-18 4.2.1.4 Tests and Inspections 4.2-19 Table of Contents 1-lvii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 4.2.1.4.1 Quality Assurance Program 4.2-19 4.2.1.4.2 Quality Control 4.2-19 4.2.1.4.3 Tests and Inspections by Others 4.2-22 4.2.1.4.4 Onsite Inspection 4.2-22 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 4.2-27 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 4.2.3.1.1 Design Stresses 4.2-29 4.2.3.1.2 Material Compatibility 4.2-29 4.2.3.1.3 Reactivity Control Components 4.2-29 4.2.3.1.4 Control Rod Drive Mechanisms 4.2-31 4.2.3.2 Design Description 4.2-32 4.2.3.2.1 Reactivity Control Components 4.2-33 4.2.3.2.2 Control Rod Drive Mechanism (CRDM) 4.2-37 4.2.3.3 Design Evaluation 4.2-42 4.2.3.3.1 Reactivity Control Components 4.2-42 4.2.3.3.2 Control Rod Drive Mechanism 4.2-48 4.2.3.4 Tests, Verification, and Inspections 4.2-51 4.2.3.4.1 Reactivity Control Components 4.2-51 4.2.3.4.2 Control Rod Drive Mechanisms 4.2-52 4.2.3.5 Instrumentation Applications 4.2-53 4.2.4 Tritium Producing Burnable Absorber Rod - Tritium Production Core 4.2-54 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 4.3-3 4.3.1.5 Shutdown Margins With Vessel Head in Place 4.3-4 4.3.1.6 Shutdown Margin for Refueling 4.3-4 4.3.1.7 Stability 4.3-5 4.3.1.8 Anticipated Transients Without Trip 4.3-5 4.3.2 Description 4.3-5 4.3.2.1 Nuclear Design Description 4.3-5 4.3.2.2 Power Distributions 4.3-7 4.3.2.2.1 Definitions 4.3-7 4.3.2.2.2 Radial Power Distributions 4.3-9 4.3.2.2.3 Assembly Power Distributions 4.3-9 1-lviii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 4.3.2.2.4 Axial Power Distribution 4.3-9 4.3.2.2.5 Limiting Power Distributions 4.3-10 4.3.2.2.6 Experimental Verification of Power Distribution Analysis 4.3-14 4.3.2.2.7 Testing 4.3-15 4.3.2.2.8 Monitoring Instrumentation 4.3-16 4.3.2.3 Reactivity Coefficients 4.3-16 4.3.2.3.1 Fuel Temperature (Doppler) Coefficient 4.3-16 4.3.2.3.2 Moderator Coefficients 4.3-17 4.3.2.3.3 Power Coefficient 4.3-18 4.3.2.3.4 Comparison of Calculated and Experimental Reactivity Coefficients 4.3-18 4.3.2.3.5 Reactivity Coefficients Used in Transient Analysis 4.3-19 4.3.2.4 Control Requirements 4.3-19 4.3.2.4.1 Doppler 4.3-20 4.3.2.4.2 Variable Average Moderator Temperature 4.3-20 4.3.2.4.3 Redistribution 4.3-20 4.3.2.4.4 Void Content 4.3-20 4.3.2.4.5 Rod Insertion Allowance 4.3-20 4.3.2.4.6 Burnup 4.3-20 4.3.2.4.7 Xenon and Samarium Concentrations 4.3-21 4.3.2.4.8 pH Effects 4.3-21 4.3.2.4.9 Experimental Confirmation 4.3-21 4.3.2.5 Control 4.3-21 4.3.2.5.1 Chemical Shim 4.3-21 4.3.2.5.2 Rod Cluster Control Assemblies 4.3-21 4.3.2.5.3 Burnable Absorbers 4.3-22 4.3.2.5.4 Peak Xenon Startup 4.3-22 4.3.2.5.5 Load Follow Control and Xenon Control 4.3-22 4.3.2.5.6 Burnup 4.3-23 4.3.2.6 Control Rod Patterns and Reactivity Worth 4.3-23 4.3.2.7 Criticality of Fuel Assemblies 4.3-24 4.3.2.8 Stability 4.3-28 4.3.2.8.1 Introduction 4.3-28 4.3.2.8.2 Stability Index 4.3-28 4.3.2.8.3 Prediction of the Core Stability 4.3-29 4.3.2.8.4 Stability Measurements 4.3-29 4.3.2.8.5 Comparison of Calculations with Measurements 4.3-31 4.3.2.8.6 Stability Control and Protection 4.3-31 4.3.2.9 Vessel Irradiation 4.3-32 4.3.3 Analytical Methods 4.3-33 4.3.3.1 Fuel Temperature (Doppler) Calculations 4.3-33 4.3.3.2 Macroscopic Group Constants 4.3-34 4.3.3.3 Spatial Few-Group Diffusion Calculations 4.3-35 Table of Contents 1-lix | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 4.4-3 4.4.1.4 Hydrodynamic Stability Design Bases 4.4-3 4.4.1.5 Other Considerations 4.4-3 4.4.2 Description 4.4-4 4.4.2.1 Summary Comparison 4.4-4 4.4.2.2 Fuel and Cladding Temperatures 4.4-4 4.4.2.2.1 UO2 Thermal Conductivity 4.4-4 4.4.2.2.2 Radial Power Distribution in UO2 Fuel Rods 4.4-5 4.4.2.2.3 Gap Conductance 4.4-6 4.4.2.2.4 Surface Heat Transfer Coefficients 4.4-6 4.4.2.2.5 Fuel Clad Temperatures 4.4-6 4.4.2.2.6 Treatment of Peaking Factors 4.4-6 4.4.2.3 Critical Heat Flux Ratio or Departure from Nucleate Boiling Ratio and Mixing Technology 4.4-7 4.4.2.3.1 Departure from Nucleate Boiling Technology 4.4-7 4.4.2.3.2 Definition of Departure from Nucleate Boiling Ratio 4.4-8 4.4.2.3.3 Mixing Technology 4.4-10 4.4.2.3.4 Hot Channel Factors 4.4-11 4.4.2.3.5 Effects of Rod Bow on DNBR 4.4-13 4.4.2.4 Flux Tilt Considerations 4.4-13 4.4.2.5 Void Fraction Distribution 4.4-14 4.4.2.6 Deleted 4.4-14 4.4.2.7 Core Pressure Drops and Hydraulic Loads 4.4-14 4.4.2.7.1 Core Pressure Drops 4.4-14 4.4.2.7.2 Hydraulic Loads 4.4-15 4.4.2.8 Correlation and Physical Data 4.4-15 4.4.2.8.1 Surface Heat Transfer Coefficients 4.4-15 4.4.2.8.2 Total Core and Vessel Pressure Drop 4.4-16 4.4.2.8.3 Void Fraction Correlation 4.4-17 4.4.2.9 Thermal Effects of Operational Transients 4.4-17 4.4.2.10 Uncertainties in Estimates 4.4-18 4.4.2.10.1 Uncertainties in Fuel and Clad Temperatures 4.4-18 4.4.2.10.2 Uncertainties in Pressure Drops 4.4-18 4.4.2.10.3 Uncertainties Due to Inlet Flow Maldistribution 4.4-19 4.4.2.10.4 Uncertainties in DNB Correlation 4.4-19 4.4.2.10.5 Uncertainties in DNBR Calculations 4.4-19 4.4.2.10.6 Uncertainties in Flow Rates 4.4-19 4.4.2.10.7 Uncertainties in Hydraulic Loads 4.4-19 4.4.2.10.8 Uncertainties in Mixing Coefficient 4.4-20 4.4.2.11 Plant Configuration Data 4.4-20 1-lx Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 4.4.3 EVALUATION 4.4-20 4.4.3.1 Core Hydraulics 4.4-20 4.4.3.1.1 Flow Paths Considered in Core Pressure Drop and Thermal Design 4.4-20 4.4.3.1.2 Inlet Flow Distributions 4.4-21 4.4.3.1.3 Empirical Friction Factor Correlations 4.4-22 4.4.3.2 Influence of Power Distribution 4.4-22 4.4.3.2.1 Nuclear Enthalpy Rise Hot Channel Factor, FNH 4.4-22 4.4.3.2.2 Axial Heat Flux Distributions 4.4-23 4.4.3.3 Core Thermal Response 4.4-24 4.4.3.4 Analytical Techniques 4.4-24 4.4.3.4.1 Core Analysis 4.4-24 4.4.3.4.2 Fuel Temperatures 4.4-26 4.4.3.4.3 Hydrodynamic Instability 4.4-26 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 4.4-31 4.4.5 Instrumentation Application 4.4-31 4.4.5.1 Incore Instrumentation 4.4-31 4.4.5.2 Overtemperature and Overpower T Instrumentation 4.4-32 4.4.5.3 Instrumentation to Limit Maximum Power Output 4.4-32 5.0 REACTOR COOLANT SYSTEM 5.1 | |||
==SUMMARY== | ==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 Table of Contents 1-lxi | |||
Loading Conditions 27 Reactor Vessel and Internals Modeling | WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 5.2.1.10.1 Loading Conditions 5.2-15 5.2.1.10.2 Analysis of the Reactor Coolant Loop and Supports 5.2-15 5.2.1.10.3 Reactor Coolant Loop Models and Methods 5.2-17 5.2.1.10.4 Primary Component Supports Models and Methods 5.2-22 5.2.1.10.5 Analysis of Primary Components 5.2-24 5.2.1.10.6 Reactor Vessel Support L0CA Loads 5.2-26 Introduction 26 Interface Information 27 Loading Conditions 27 Reactor Vessel and Internals Modeling 28 Analytical Methods 30 Results of the Analysis 30 5.2.1.10.7 Stress Criteria for Class 1 Components and Component Supports 5.2-32 5.2.1.10.8 Computer Program Descriptions 5.2-33 5.2.1.10.9 LOCA Evaluation of the Control Rod Drive Mechanisms 5.2-34 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 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 5.2-34 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 5.2.2.4.1 System Operation 5.2-37 5.2.2.4.2 Pressure Transient Analyses 5.2-37 Evaluation of Low Temperature Overpressure Transients 37 Operating Basis Earthquake Evaluation 38 5.2.2.4.3 Administrative Procedures 5.2-38 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 1-lxii Table of Contents | ||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 Temperatures 5.2-51 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 5.2.7.3.1 Containment Air Particulate Monitors and Containment Radioactive 5.2-56 5.2.7.3.2 Reactor Building Floor and Equipment Drain (RBF&ED) Sump and the 5.2-57 5.2.7.3.3 Humidity Monitors 5.2-58 5.2.7.3.4 Temperature Monitors 5.2-58 5.2.7.4 Intersystem Leakage Detection 5.2-58 5.2.7.4.1 ECCS Intersystem Leakage 5.2-58 5.2.7.4.2 Condenser Vacuum Pump Air Exhaust Monitors 5.2-60 5.2.7.4.3 Component Cooling System Liquid Effluent Monitors 5.2-61 5.2.7.4.4 Steam Generator Blowdown Liquid Effluent Monitor 5.2-62 5.2.7.5 Unidentified Leakage System Sensitivity and Response Time 5.2-62 5.2.7.5.1 Containment Air Particulate Monitors and Containment Radioactive Gas Monitors 5.2-62 5.2.7.5.2 Reactor Building Floor and Equipment Drain (RBF&ED) Pocket Sump 5.2-63 5.2.7.5.3 Humidity Monitors 5.2-63 5.2.7.5.4 Temperature Monitors 5.2-64 5.2.7.6 Seismic Capability 5.2-64 5.2.7.7 Indicators and Alarms 5.2-64 5.2.7.7.1 Radiation Monitors 5.2-64 5.2.7.7.2 RBF&ED Pocket Sump Level Monitors 5.2-64 5.2.7.7.3 Humidity Monitors 5.2-64 Table of Contents 1-lxiii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.2.7.7.4 Temperature Monitors 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 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 5.4.3.6.1 Measurement of Integrated Fast Neutron (E>l.0MeV) Flux at the Irradia-tion Samples 5.4-6 Determination of Sensor Reaction Rates 7 Corrections to Reaction Rate Data 8 Least Squares Adjustment Procedure 9 5.4.3.6.2 Calculation of Integrated Fast Neutron (E > 1.0 MeV) Flux at the Irradia-tion Samples 5.4-10 Reference Forward Calculation 11 1-lxiv Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page Cycle Specific Adjoint Calculations 11 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 5.5.1.3 Design Evaluation 5.5-3 5.5.1.3.1 Pump Performance 5.5-3 5.5.1.3.2 Coastdown Capability 5.5-4 5.5.1.3.3 Flywheel Integrity 5.5-4 5.5.1.3.4 Bearing Integrity 5.5-4 5.5.1.3.5 Locked Rotor 5.5-4 5.5.1.3.6 Critical Speed 5.5-5 5.5.1.3.7 Missile Generation 5.5-5 5.5.1.3.8 Pump Cavitation 5.5-5 5.5.1.3.9 Pump Overspeed Considerations 5.5-5 5.5.1.3.10 Anti-Reverse Rotation Device 5.5-6 5.5.1.3.11 Shaft Seal Leakage 5.5-6 5.5.1.3.12 Seal Discharge Piping 5.5-6 5.5.1.3.13 Spool Piece 5.5-7 5.5.1.3.14 Motor Air Coolers 5.5-7 5.5.1.3.15 Discharge Nozzle Weir 5.5-7 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 5.5.2.3.1 Forced Convection 5.5-9 5.5.2.3.2 Natural Circulation Flow 5.5-9 5.5.2.3.3 Tube and Tubesheet Stress Analyses 5.5-10 5.5.2.3.4 Corrosion 5.5-10 5.5.2.3.5 Compatibility of Steam Generator Tubing with Primary and 5.5-10 5.5.2.3.6 Flow Induced Vibration 5.5-12 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 Table of Contents 1-lxv | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.5.3.3.1 Material Corrosion/Erosion Evaluation 5.5-18 5.5.3.3.2 Sensitized Stainless Steel 5.5-19 5.5.3.3.3 Contaminant Control 5.5-19 5.5.3.4 Tests and Inspections 5.5-19 5.5.4 Steam Outlet Flow Restrictor (Steam Generator) 5.5-19 5.5.4.1 Design Basis 5.5-19 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 5.5.6.2.1 Component Description 5.5-22 5.5.6.2.2 System Operation 5.5-22 5.5.6.3 Design Evaluation 5.5-22 5.5.6.3.1 System Availability and Reliability 5.5-22 5.5.6.3.2 Leakage Provisions 5.5-23 5.5.6.3.3 Pipe Rupture Provisions 5.5-23 5.5.6.3.4 Radiological Considerations 5.5-23 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 5.5.7.2.1 Component Description 5.5-25 5.5.7.2.2 System Operation 5.5-27 5.5.7.3 Design Evaluation 5.5-28 5.5.7.3.1 System Availability and Reliability 5.5-28 5.5.7.3.2 Leakage Provisions and Activity Release 5.5-29 5.5.7.3.3 Overpressurization Protection 5.5-29 5.5.7.3.4 Prevention of Exposure of the Residual Heat Removal System to Normal Reactor Coolant System Operating Pressure 5.5-30 5.5.7.3.5 Shared Function 5.5-30 5.5.7.3.6 Radiological Consideration 5.5-31 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 5.5.10.1.1 Pressurizer Surge Line 5.5-32 5.5.10.1.2 Pressurizer Volume 5.5-32 5.5.10.2 Design Description 5.5-33 5.5.10.2.1 Pressurizer Surge Line 5.5-33 5.5.10.2.2 Pressurizer Vessel 5.5-33 5.5.10.3 Design Evaluation 5.5-34 1-lxvi Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.5.10.3.1 System Pressure 5.5-34 5.5.10.3.2 Pressurizer Performance 5.5-34 5.5.10.3.3 Pressure Setpoints 5.5-35 5.5.10.3.4 Pressurizer Spray 5.5-35 5.5.10.3.5 Pressurizer Design Analysis 5.5-35 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 5.5.11.2.1 Pressurizer Relief Tank Pressure 5.5-38 5.5.11.2.2 Pressurizer Relief Tank Level 5.5-38 5.5.11.2.3 Pressurizer Relief Tank Water Temperature 5.5-38 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 5.5-40 5.5.13 Safety and Relief Valves 5.5-40 5.5.13.1 Design Bases 5.5-40 5.5.13.2 Design Description 5.5-40 5.5.13.3 Design Evaluation 5.5-41 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 5.5-42 5.5.14.3 Evaluation 5.5-43 5.5.14.4 Tests and Inspections 5.5-44 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 Table of Contents 1-lxvii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 6.2.1 Containment Functional Design 6.2-1 6.2.1.1 Design Bases 6.2-1 6.2.1.1.1 Primary Containment Design Bases 6.2-1 6.2.1.2 Primary Containment System Design 6.2-3 6.2.1.3 Design Evaluation 6.2-3 6.2.1.3.1 Primary Containment Evaluation 6.2-3 6.2.1.3.2 General Description of Containment Pressure Analysis 6.2-4 6.2.1.3.3 Long-Term Containment Pressure Analysis 6.2-4 6.2.1.3.4 Short-Term Blowdown Analysis 6.2-8 6.2.1.3.5 Effect of Steam Bypass 6.2-17 6.2.1.3.6 Mass and Energy Release Data 6.2-20 6.2.1.3.7 Accident Chronology 6.2-24 6.2.1.3.8 Energy Balance Tables 6.2-24 6.2.1.3.9 Containment Pressure Differentials 6.2-25 6.2.1.3.10 Steam Line Break Inside Containment 6.2-27 6.2.1.3.11 Maximum Reverse Pressure Differentials 6.2-33 6.2.2 CONTAINMENT HEAT REMOVAL SYSTEMS 6.2-1 6.2.2.1 Design Bases 6.2-1 6.2.2.2 System Design 6.2-3 6.2.2.3 Design Evaluation 6.2-5 6.2.2.4 Testing and Inspections 6.2-7 6.2.2.5 Instrumentation Requirements 6.2-8 6.2.2.6 Materials 6.2-8 6.2.3 Secondary Containment Functional Design 6.2-1 6.2.3.1 Design Bases 6.2-1 6.2.3.1.1 Secondary Containment Enclosures 6.2-1 6.2.3.1.2 Emergency Gas Treatment System (EGTS) 6.2-1 6.2.3.1.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2-2 6.2.3.2 System Design 6.2-2 6.2.3.2.1 Secondary Containment Enclosures 6.2-2 6.2.3.2.2 Emergency Gas Treatment System (EGTS) 6.2-7 6.2.3.2.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2-10 6.2.3.3 Design Evaluation 6.2-12 1-lxviii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.2.3.3.1 Secondary Containment Enclosures 6.2-12 6.2.3.3.2 Emergency Gas Treatment System (EGTS) 6.2-15 6.2.3.3.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2-19 6.2.3.4 Test and Inspections 6.2-21 6.2.3.4.1 Emergency Gas Treatment System (EGTS) 6.2-21 6.2.3.4.2 Auxiliary Building Gas Treatment System (ABGTS) 6.2-22 6.2.3.5 Instrumentation Requirements 6.2-23 6.2.3.5.1 Emergency Gas Treatment System (EGTS) 6.2-23 6.2.3.5.2 Auxiliary Building Gas Treatment System (ABGTS) 6.2-23 6.2.4 Containment Isolation Systems 6.2-1 6.2.4.1 Design Bases 6.2-1 6.2.4.2 System Design 6.2-4 6.2.4.2.1 Design Requirements 6.2-5 6.2.4.2.2 Containment Isolation Operation 6.2-5 6.2.4.2.3 Penetration Design 6.2-6 6.2.4.3 Design Evaluation 6.2-12 6.2.4.3.1 Possible Leakage Paths 6.2-14 6.2.4.4 Tests and Inspections 6.2-16 6.2.5 Combustible Gas Control in Containment 6.2-1 6.2.5.1 The containment combustible gas control system is designed to control the concen-tration of hydrogen that may be released into the containment following a beyond-design-basis ac-cident to ensure that containment structural integrity is maintained. The combustible gas control system of the containment air return system, the hydrogen analyzer system (HAS) and the hydro-gen mitigation system (HMS) which conform to 10CFR50.44 requirements.Design Bases 6.2-1 6.2.5.2 System Design 6.2-2 6.2.5.3 Design Evaluation 6.2-4 6.2.5.4 Testing and Inspections 6.2-5 6.2.5.5 Instrumentation Application 6.2-5 6.2.6 Containment Leakage Testing 6.2-1 6.2.6.1 Containment Integrated Leak Rate Test 6.2-1 6.2.6.2 Containment Penetration Leakage Rate Test 6.2-2 6.2.6.3 Scheduling and Reporting of Periodic Tests 6.2-6 6.2.6.4 Special Testing Requirements 6.2-6 6.3 EMERGENCY CORE COOLING SYSTEM 6.3-1 6.3.1 Design Bases 6.3-1 6.3.1.1 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 Table of Contents 1-lxix | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.3.2.2 Equipment and Component Design 6.3-2 6.3.2.3 Applicable Codes and Classifications 6.3-15 6.3.2.4 Materials Specifications and Compatibility 6.3-15 6.3.2.5 Design Pressures and Temperatures 6.3-16 6.3.2.6 Coolant Quantity 6.3-16 6.3.2.7 Pump Characteristics 6.3-16 6.3.2.8 Heat Exchanger Characteristics 6.3-16 6.3.2.9 ECCS Flow Diagrams 6.3-17 6.3.2.10 Relief Valves 6.3-17 6.3.2.11 System Reliability 6.3-17 6.3.2.11.1 Definitions 6.3-17 6.3.2.11.2 Active and Passive Failure Criteria 6.3-18 6.3.2.11.3 Subsequent Leakage from Components in Safeguards Systems 6.3-19 6.3.2.12 Protection Provisions 6.3-21 6.3.2.13 Provisions for Performance Testing 6.3-22 6.3.2.14 Net Positive Suction Head 6.3-22 6.3.2.15 Control of Motor-Operated Isolation Valves 6.3-22 6.3.2.16 Motor-Operated Valves and Controls 6.3-23 6.3.2.17 Manual Actions 6.3-23 6.3.2.18 Process Instrumentation 6.3-23 6.3.2.19 Materials 6.3-23 6.3.3 Performance Evaluation 6.3-23 6.3.3.1 Evaluation Model 6.3-23 6.3.3.2 ECCS Performance 6.3-24 6.3.3.3 Alternate Analysis Methods 6.3-24 6.3.3.4 Fuel Rod Perforations 6.3-25 6.3.3.5 Effects of ECCS Operation on the Core 6.3-25 6.3.3.6 Use of Dual Function Components 6.3-25 6.3.3.7 Lag Times 6.3-27 6.3.3.8 Thermal Shock Considerations 6.3-27 6.3.3.9 Limits on System Parameters 6.3-27 6.3.3.10 Use of RHR Spray 6.3-27 6.3.4 Tests and Inspections 6.3-28 6.3.4.1 Preoperational Tests (Historical Information - Not Updated) 6.3-28 6.3.4.2 Component Testing 6.3-29 6.3.4.3 Periodic System Testing 6.3-29 6.3.5 Instrumentation Application 6.3-30 6.3.5.1 Temperature Indication 6.3-30 6.3.5.2 Pressure Indication 6.3-30 6.3.5.3 Flow Indication 6.3-30 6.3.5.4 Level Indication 6.3-31 6.3.5.5 Valve Position Indication 6.3-32 1-lxx Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.4 HABITABILITY SYSTEMS 6.4-1 6.4.1 Design Bases 6.4-1 6.4.2 System Design 6.4-1 6.4.2.1 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 6.4.2.4.1 Other Ventilation Zones 6.4-3 6.4.2.4.2 Pressure-Containing Equipment 6.4-4 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 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 6.5.1.1.1 Emergency Gas Treatment System Air Cleanup Units 6.5-1 6.5.1.1.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-1 6.5.1.1.3 Reactor Building Purge Air System Air Cleanup Units 6.5-1 6.5.1.1.4 Main Control Room Emergency Air Cleanup Units 6.5-2 6.5.1.2 System Design 6.5-2 6.5.1.2.1 Emergency Gas Treatment System Air Cleanup Units 6.5-2 6.5.1.2.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-3 6.5.1.2.3 Reactor Building Purge System Air Cleanup Units 6.5-4 6.5.1.2.4 Main Control Room Emergency Air Cleanup Units 6.5-4 6.5.1.3 Design Evaluation 6.5-5 6.5.1.3.1 Emergency Gas Treatment System Air Cleanup Units 6.5-5 6.5.1.3.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-5 6.5.1.3.3 Reactor Building Purge System Air Cleanup Units 6.5-5 6.5.1.3.4 Main Control Room Emergency Air Cleanup Units 6.5-5 6.5.1.4 Tests and Inspections 6.5-5 6.5.1.4.1 Emergency Gas Treatment System Air Cleanup Units 6.5-5 6.5.1.4.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-6 6.5.1.4.3 Reactor Building Purge System Air Cleanup Units 6.5-6 6.5.1.4.4 Main Control Room Emergency Air Cleanup Units 6.5-6 6.5.1.5 Instrumentation Requirements 6.5-6 6.5.1.5.1 Emergency Gas Treatment System Air Cleanup Units 6.5-6 6.5.1.5.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-6 Table of Contents 1-lxxi | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.5.1.5.3 Reactor Building Purge System Air Cleanup Units 6.5-7 6.5.1.5.4 Main Control Room Emergency Air Cleanup Units 6.5-7 6.5.1.6 Materials 6.5-7 6.5.1.6.1 Emergency Gas Treatment System Air Cleanup Units 6.5-7 6.5.1.6.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-7 6.5.1.6.3 Reactor Building Purge System Air Cleanup Units 6.5-7 6.5.1.6.4 Main Control Room Emergency Air Cleanup Units 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 6.5.4.2.1 Component Description 6.5-11 6.5.4.2.2 System Operation 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 6.5.4.4.1 Ice Condenser System Instrumentation 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 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 1-lxxii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 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 Table of Contents 1-lxxiii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 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 7.1.1.1.1 Reactor Trip System 7.1-4 7.1.1.1.2 Engineered Safety Features Actuation System 7.1-4 7.1.1.1.3 Vital Instrumentation and Control Power Supply System 7.1-4 7.1.1.1.4 Auxiliary Control Air System 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 7.1.1.4 Plant Comparison 7.1-5 1-lxxiv Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.1.2 Identification of Safety Criteria 7.1-5 7.1.2.1 Design Bases 7.1-8 7.1.2.1.1 Reactor Trip System 7.1-8 7.1.2.1.2 Engineered Safety Features Actuation System (ESFAS) 7.1-9 7.1.2.1.3 Vital Control Power Supply System 7.1-10 7.1.2.1.4 Standby Power 7.1-10 7.1.2.1.5 Interlocks 7.1-10 7.1.2.1.6 Bypasses 7.1-10 7.1.2.1.7 Equipment Protection 7.1-10 7.1.2.1.8 Diversity 7.1-11 7.1.2.1.9 Trip Setpoints 7.1-11 7.1.2.2 Independence of Redundant Safety-Related Systems 7.1-11 7.1.2.2.1 General 7.1-12 7.1.2.2.2 Specific Systems 7.1-12 7.1.2.2.3 Fire Protection 7.1-14 7.1.2.3 Physical Identification of Safety-Related Equipment 7.1-14 7.1.2.4 Process Signal Isolation Relays 7.1-16 7.2 REACTOR TRIP SYSTEM 7.2-1 7.2.1 Description 7.2-1 7.2.1.1 System Description 7.2-1 7.2.1.1.1 Functional Performance Requirements 7.2-2 7.2.1.1.2 Reactor Trips 7.2-2 7.2.1.1.3 Reactor Trip System Interlocks 7.2-10 7.2.1.1.4 Reactor Coolant Temperature Sensor Arrangement and Calculational Methodology 7.2-12 7.2.1.1.5 Pressurizer Water Level Reference Leg Arrangement 7.2-15 7.2.1.1.6 Process Protection System 7.2-15 7.2.1.1.7 Solid State Logic Protection System 7.2-15 7.2.1.1.8 Isolation Devices 7.2-16 7.2.1.1.9 Energy Supply and Environmental Variations 7.2-16 7.2.1.1.10 Setpoints 7.2-16 7.2.1.1.11 Seismic Design 7.2-16 7.2.1.2 Design Bases Information 7.2-16 7.2.1.2.1 Generating Station Conditions 7.2-16 7.2.1.2.2 Generating Station Variables 7.2-17 7.2.1.2.3 Spatially Dependent Variables 7.2-17 7.2.1.2.4 Limits, Margins and Levels 7.2-17 7.2.1.2.5 Abnormal Events 7.2-18 7.2.1.2.6 Minimum Performance Requirements 7.2-18 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 7.2.2.1.1 Trip Setpoint Discussion 7.2-20 Table of Contents 1-lxxv | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.2.2.1.2 Reactor Coolant Flow Measurement 7.2-22 7.2.2.2 Evaluation of Compliance to Applicable Codes and Standards 7.2-22 7.2.2.3 Specific Control and Protection Interactions 7.2-32 7.2.2.3.1 Neutron Flux 7.2-32 7.2.2.3.2 Reactor Coolant Temperature 7.2-32 7.2.2.3.3 Pressurizer Pressure 7.2-33 7.2.2.3.4 Pressurizer Water Level 7.2-34 7.2.2.3.5 Steam Generator Water Level 7.2-34 7.2.2.4 Additional Postulated Accidents 7.2-35 7.2.3 Tests and Inspections 7.2-35 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 7.3.1.1.1 Function Initiation 7.3-2 7.3.1.1.2 Process Protection Circuitry 7.3-3 7.3.1.1.3 Logic Circuitry 7.3-4 7.3.1.1.4 Final Actuation Circuitry 7.3-4 7.3.1.1.5 Support Systems 7.3-5 7.3.1.2 Design Bases Information 7.3-6 7.3.1.2.1 Generating Station Conditions 7.3-6 7.3.1.2.2 Generating Station Variables 7.3-6 7.3.1.2.3 Spatially Dependent Variables 7.3-6 7.3.1.2.4 Limits, Margin and Levels 7.3-6 7.3.1.2.5 Abnormal Events 7.3-7 7.3.1.2.6 Minimum Performance Requirements 7.3-7 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 7.3-8 7.3.2.2.1 Single Failure Criterion 7.3-9 7.3.2.2.2 Equipment Qualification 7.3-9 7.3.2.2.3 Channel Independence 7.3-9 7.3.2.2.4 Control and Protection System Interaction 7.3-9 7.3.2.2.5 Capability for Sensor Checks and Equipment Test and Calibration 7.3-9 7.3.2.2.6 Manual Initiation, Reset and Blocks of Protective Actions7.3-15 7.3.2.3 Further Considerations 7.3-15 7.3.2.4 Summary 7.3-16 7.3.2.4.1 Loss-of-Coolant Protection 7.3-16 7.3.2.4.2 Steam Line Break Protection 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 1-lxxvi Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.4.1.2 Controls 7.4-2 7.4.1.2.1 General Considerations 7.4-2 7.4.1.2.2 Pumps and Fans 7.4-3 7.4.1.2.3 Diesel Generators 7.4-4 7.4.1.2.4 Valves and Heaters 7.4-4 7.4.1.3 Equipment and Systems Available for Cold Shutdown 7.4-5 7.4.2 Analysis 7.4-5 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 7.5.1.4.1 Definitions 7.5-3 7.5.1.4.2 Selection Criteria 7.5-3 7.5.1.4.3 Design Criteria For Category 1 Variables 7.5-4 7.5.1.4.4 Design Criteria For Category 2 Variables 7.5-5 7.5.1.4.5 Design Criteria For Category 3 Variables 7.5-5 7.5.1.5 General Requirements 7.5-6 7.5.1.5.1 Display Requirements 7.5-6 7.5.1.5.2 Identification 7.5-6 7.5.1.6 Analysis 7.5-7 7.5.1.7 Tests and Inspections 7.5-7 7.5.1.7.1 Programs 7.5-7 7.5.1.7.2 Removal of Channels from Service 7.5-8 7.5.1.7.3 Administrative Control 7.5-8 7.5.2 Plant Computer System 7.5-8 7.5.2.1 Safety Parameter Display System 7.5-8 7.5.2.1.1 System Description 7.5-8 7.5.2.1.2 Design Bases 7.5-9 7.5.2.2 Bypassed and Inoperable Status Indication System (BISI) 7.5-11 7.5.2.3 Technical Support Center and Nuclear Data Links 7.5-13 7.5.2.3.1 Technical Support Center 7.5-13 7.5.2.3.2 Communication 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 Table of Contents 1-lxxvii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 7.6-8 7.6.8.1 Analysis of Interlock 7.6-9 7.6.9 Switchover From Injection to Recirculation Mode Following a LOCA 7.6-10 7.7 CONTROL SYSTEMS 7.7-1 7.7.1 Description 7.7-1 7.7.1.1 Control Rod Drive Reactor Control System 7.7-1 7.7.1.1.1 Reactor Control Input Signals 7.7-1 7.7.1.1.2 Rod Speed Control Program 7.7-3 7.7.1.2 Rod Control System 7.7-3 7.7.1.2.1 Rod Control System Function 7.7-3 7.7.1.2.2 Rod Control System Failures 7.7-5 7.7.1.3 Plant Control Signals for Monitoring and Indicating 7.7-9 7.7.1.3.1 Monitoring Functions Provided by the Nuclear Instrumentation System 7.7-9 7.7.1.3.2 Main Control Room Rod Position Indication 7.7-10 7.7.1.3.3 Control Bank Rod Insertion Monitoring 7.7-12 7.7.1.3.4 Rod Deviation Alarm 7.7-14 7.7.1.3.5 Rods At Bottom 7.7-14 7.7.1.3.6 Bypassed and Inoperable Status Indication System (BISI) 7.7-14 7.7.1.4 Plant Control System Interlocks 7.7-14 7.7.1.4.1 Rod Stops 7.7-14 7.7.1.4.2 Automatic Turbine Load Runback 7.7-15 7.7.1.5 Pressurizer Pressure Control 7.7-15 7.7.1.6 Pressurizer Water Level Control 7.7-16 7.7.1.7 Steam Generator Water Level Control 7.7-16 7.7.1.8 Steam Dump Control 7.7-17 7.7.1.8.1 Load Rejection Steam Dump Controller 7.7-17 7.7.1.8.2 Plant Trip Steam Dump Controller 7.7-18 7.7.1.8.3 Steam Header Pressure Controller 7.7-18 7.7.1.9 Incore Instrumentation System 7.7-18 7.7.1.9.1 Thermocouples 7.7-18 7.7.1.9.2 Incore Instrumentation System 7.7-19 7.7.1.9.3 Incore Instrumentation System Neutron Signal Processing 7.7-19 7.7.1.10 Control Board 7.7-19 7.7.1.11 Deleted 7.7-20 7.7.1.12 Anticipated Transient Without Scram Mitigation System Actuation 7.7-20 7.7.2 Analysis 7.7-21 7.7.2.1 Separation of Protection and Control System 7.7-22 7.7.2.2 Response Considerations of Reactivity 7.7-22 7.7.2.3 Step Load Changes Without Steam Dump 7.7-24 7.7.2.4 Loading and Unloading 7.7-25 1-lxxviii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.7.2.5 Load Rejection Furnished By Steam Dump System 7.7-25 7.7.2.6 Turbine-Generator Trip With Reactor Trip 7.7-26 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.1.2.1.1 Instruments Common to Multiple Process Systems 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 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 8.1-2 8.1.5 Design Criteria and Standards 8.1-4 8.1.5.1 Design Criteria 8.1-4 8.1.5.2 Other Standards and Guides 8.1-4 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 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 Table of Contents 1-lxxix | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 8.3-26 8.3.1.2.1 Standby AC Power Systems 8.3-26 8.3.1.2.2 Analysis of Vital 120V AC Control Power Systems AC Distribution Boards and Inverters 8.3-29 8.3.1.2.3 Safety-Related Equipment in a LOCA Environment 8.3-32 8.3.1.3 Physical Identification of Safety-Related Equipment in AC Power Systems 8.3-36 8.3.1.4 Independence of Redundant ac Power Systems 8.3-37 8.3.1.4.1 Cable Derating and Raceway Fill 8.3-38 8.3.1.4.2 Cable Routing and Separation Criteria 8.3-38 8.3.1.4.3 Sharing of Cable Trays and Routing of Non-Safety Related Cables8.3-46 8.3.1.4.4 Fire Detection and Protection in Areas Where Cables are Installed 8.3-50 8.3.1.4.5 Cable and Cable Tray Markings 8.3-51 8.3.1.4.6 Spacing of Power and Control Wiring and Components Comprising the Class 1E Electrical Systems in Control Boards, Panels, and Relay Racks 8.3-52 8.3.1.4.7 Fire Barriers and Separation Between Redundant Trays 8.3-53 8.3.2 DC Power System 8.3-53 8.3.2.1 Description 8.3-53 8.3.2.1.1 Vital 125V dc Control Power System 8.3-53 8.3.2.1.2 Non-Safety-Related DC Power Systems 8.3-60 8.3.2.2 Analysis of Vital 125V DC Control Power Supply System 8.3-61 8.3.2.3 Physical Identification of Safety-Related Equipment in dc Power Systems 8.3-66 8.3.2.4 Independence of Redundant DC Power Systems 8.3-66 8.3.3 Fire Protection for Cable Systems 8.3-67 8A Analysis of Submerged Electrical Equipment (During Post LOCA) Powered from Auxiliary Power System 8-1 8B Analysis of Submerged Electrical Equipment (During Post LOCA) Powered from In-strumentation and Control Power System 8-3 8C Deleted by Amendment 75 8-5 8D IEEE STD 387-1984 FOR DIESEL-GENERATING UNITS APPLIED AS STANDBY POWER 8-6 1-lxxx Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 8E Probability/Reliability Analysis of Protection Device Schemes for Associated and Non-Class 1E Cables 8-8 9.0 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 9.1-1 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 9.1.3.1.1 Spent Fuel Pool Cooling 9.1-4 9.1.3.1.2 Spent Fuel Pool Dewatering Protection 9.1-5 9.1.3.1.3 Water Purification 9.1-5 9.1.3.1.4 Flood Mode Cooling 9.1-5 9.1.3.2 System Description 9.1-5 9.1.3.2.1 Component Description 9.1-7 9.1.3.3 Safety Evaluation 9.1-8 9.1.3.3.1 Availability and Reliability 9.1-8 9.1.3.3.2 Spent Fuel Pool Dewatering 9.1-9 9.1.3.3.3 Pool and Fuel Temperatures 9.1-9 9.1.3.3.4 Water Quality 9.1-11 9.1.3.3.5 Leakage Detection for the Spent Fuel Pool 9.1-11 9.1.3.4 Tests and Inspections 9.1-11 9.1.3.5 Instrument Application 9.1-11 9.1.3.5.1 Temperature 9.1-11 9.1.3.5.2 Pressure 9.1-12 9.1.3.5.3 Flow 9.1-12 9.1.3.5.4 Level 9.1-12 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 9.1.4.2.1 Refueling Procedure 9.1-14 9.1.4.2.2 Component Description 9.1-17 9.1.4.3 Design Evaluation 9.1-20 9.1.4.3.1 Safe Handling 9.1-20 9.1.4.3.2 Seismic Considerations 9.1-25 9.1.4.3.3 Containment Pressure Boundary Integrity 9.1-26 Table of Contents 1-lxxxi | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.1.4.3.4 Radiation Shielding 9.1-26 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 9.2.1.4 Tests and Inspections 9.2-7 9.2.1.5 Instrument Applications 9.2-7 9.2.1.5.1 General Description 9.2-7 9.2.1.5.2 Pressure Instrumentation 9.2-7 9.2.1.5.3 Flow Instrumentation 9.2-8 9.2.1.5.4 Temperature Instrumentation 9.2-8 9.2.1.5.5 Deleted by Amendment 87 9.2-8 9.2.1.5.6 Control Valves 9.2-8 9.2.1.6 Corrosion, Organic Fouling, and Environmental Qualification 9.2-9 9.2.1.7 Design Codes 9.2-10 9.2.2 Component Cooling System (CCS) 9.2-10 9.2.2.1 Design Bases 9.2-10 9.2.2.2 System Description 9.2-12 9.2.2.3 Components 9.2-15 9.2.2.3.1 Component Cooling Heat Exchangers 9.2-15 9.2.2.3.2 Component Cooling Pumps 9.2-15 9.2.2.3.3 Thermal Barrier Booster Pumps 9.2-16 9.2.2.3.4 Component Cooling Surge Tanks 9.2-16 9.2.2.3.5 Seal Leakage Return Unit 9.2-16 9.2.2.3.6 Valves 9.2-16 9.2.2.3.7 Piping 9.2-17 9.2.2.4 Safety Evaluation 9.2-18 9.2.2.5 Leakage Provisions 9.2-18 9.2.2.6 Incidental Control 9.2-19 9.2.2.7 Instrument Applications 9.2-19 9.2.2.7.1 General Description 9.2-19 9.2.2.7.2 Flow Instrumentation 9.2-20 9.2.2.7.3 Level Instrumentation 9.2-20 9.2.2.7.4 Pressure Instrumentation 9.2-20 9.2.2.7.5 Temperature Instrumentation 9.2-20 9.2.2.7.6 Valves 9.2-21 9.2.2.7.7 Conclusion 9.2-21 9.2.2.8 Malfunction Analysis 9.2-21 9.2.2.9 Tests and Inspections - Historical Information 9.2-21 9.2.2.10 Codes and Classification 9.2-22 9.2.3 Demineralized Water Makeup System 9.2-22 1-lxxxii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.2.3.1 Design Bases 9.2-22 9.2.3.2 System Description 9.2-22 9.2.3.3 Safety Evaluation 9.2-23 9.2.3.4 Test and Inspection 9.2-23 9.2.3.5 Instrumentation Applications 9.2-23 9.2.4 Potable and Sanitary Water Systems 9.2-24 9.2.4.1 Potable Water System 9.2-24 9.2.4.1.1 System Description 9.2-24 9.2.4.1.2 Safety Evaluation 9.2-24 9.2.4.1.3 Tests and Inspections 9.2-25 9.2.4.1.4 Instrumentation Applications 9.2-25 9.2.4.2 Sanitary Water System 9.2-25 9.2.4.2.1 Design Bases 9.2-25 9.2.4.2.2 System Description 9.2-25 9.2.4.2.3 Safety Evaluation 9.2-26 9.2.4.2.4 Tests And Inspections 9.2-27 9.2.4.2.5 Instrumentation Applications 9.2-28 9.2.5 Ultimate Heat Sink 9.2-28 9.2.5.1 General Description 9.2-28 9.2.5.2 Design Bases 9.2-29 9.2.5.3 Safety Evaluation 9.2-29 9.2.5.4 Instrumentation Application 9.2-31 9.2.6 Condensate Storage Facilities 9.2-31 9.2.6.1 Design Bases 9.2-31 9.2.6.2 System Description 9.2-32 9.2.6.3 Safety Evaluation 9.2-32 9.2.6.4 Test and Inspections 9.2-33 9.2.6.5 Instrument Applications 9.2-33 9.2.7 Refueling Water Storage Tank 9.2-34 9.2.7.1 ECCS Pumps Net Positive Suction Head (NPSH) 9.2-35 9.2.8 Raw Cooling Water System 9.2-37 9.2.8.1 Design Bases 9.2-37 9.2.8.2 System Description 9.2-38 9.2.8.3 Safety Evaluation 9.2-40 9.2.8.4 Tests and Inspection 9.2-41 9.3 PROCESS AUXILIARIES 9.3-1 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 Table of Contents 1-lxxxiii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 9.3.2.6.1 System Description 9.3-9 9.3.2.6.2 Postaccident Sampling Facility 9.3-9 9.3.2.6.3 Sampling Equipment 9.3-9 Liquid Sampling Panel 10 Chemical Analysis Panel 10 Containment Air Sampling Panel (CASP) 10 HRSS Control Panels 11 9.3.2.6.4 Sample Points 9.3-11 9.3.2.6.5 Postaccident Counting Facilities 9.3-11 9.3.2.6.6 Piping, Tubing, and Valves 9.3-11 9.3.2.6.7 Safety Evaluation 9.3-12 9.3.2.6.8 Tests and Inspections 9.3-12 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 9.3.3.2.1 Drains from Lowest Floor Level in the Auxiliary Building 9.3-13 9.3.3.2.2 Residual Heat Removal Pump (RHR) and Containment Spray Pump (CSP) Compartments 9.3-13 9.3.3.2.3 CVCS Holdup Tank Compartment and Tritiated Drain Collector Tank Room 9.3-14 9.3.3.2.4 Volume Control Tanks 9.3-14 9.3.3.2.5 Boric Acid Tanks 9.3-14 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 9.3.4.1.1 Reactivity Control 9.3-16 9.3.4.1.2 Regulation of Reactor Coolant Inventory 9.3-17 9.3.4.1.3 Reactor Coolant Purification 9.3-17 9.3.4.1.4 Chemical Additions for Corrosion Control 9.3-17 9.3.4.1.5 Seal Water Injection 9.3-17 9.3.4.1.6 Hydrostatic Testing of the Reactor Coolant System 9.3-17 9.3.4.1.7 Emergency Core Cooling 9.3-18 9.3.4.2 System Description 9.3-18 9.3.4.2.1 Charging, Letdown, and Seal Water System 9.3-18 1-lxxxiv Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.3.4.2.2 Chemical Control, Purification and Makeup System 9.3-20 9.3.4.2.3 Chemical Shim and Reactor Coolant Makeup 9.3-21 9.3.4.2.4 Component Description 9.3-24 9.3.4.2.5 System Operation 9.3-32 9.3.4.3 Safety Evaluation 9.3-36 9.3.4.3.1 Reactivity Control 9.3-36 9.3.4.3.2 Reactor Coolant Purification 9.3-37 9.3.4.3.3 Seal Water Injection 9.3-37 9.3.4.3.4 Hydrostatic Testing of the Reactor Coolant System 9.3-38 9.3.4.3.5 Leakage Provisions 9.3-38 9.3.4.3.6 Ability to Meet the Safeguards Function 9.3-38 9.3.4.4 Tests and Inspections 9.3-38 9.3.4.5 Instrumentation Application 9.3-38 9.3.5 Failed Fuel Detection System 9.3-39 9.3.6 Auxiliary Charging System 9.3-39 9.3.6.1 Design Bases 9.3-39 9.3.6.2 System Design Description 9.3-40 9.3.6.3 Design Evaluation 9.3-41 9.3.6.4 Tests and Inspection 9.3-41 9.3.6.5 Instrument Application 9.3-41 9.3.7 Boron Recycle System 9.3-41 9.3.8 Heat Tracing 9.3-41 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 9.4.3.2.1 Building Air Supply and Exhaust Systems (General Ventilation) 9.4-13 9.4.3.2.2 Building Cooling System (Chilled Water) 9.4-14 9.4.3.2.3 Safety Feature Equipment Coolers 9.4-15 9.4.3.2.4 Shutdown Board Room Air-Conditioning System 9.4-15 9.4.3.2.5 Auxiliary Board Rooms Air-Conditioning Systems 9.4-16 9.4.3.2.6 Shutdown Transformer Room Ventilating Systems 9.4-17 9.4.3.2.7 Miscellaneous Ventilation and Air Conditioning Systems 9.4-18 Table of Contents 1-lxxxv | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.4.3.3 Safety Evaluation 9.4-19 9.4.3.3.1 General Ventilation System 9.4-19 9.4.3.3.2 Building Cooling System 9.4-20 9.4.3.3.3 Safety Feature Equipment Coolers 9.4-20 9.4.3.3.4 Shutdown Board Room Air-Conditioning System 9.4-20 9.4.3.3.5 Auxiliary Board Rooms Air-Conditioning System 9.4-21 9.4.3.3.6 Shutdown Transformer Room Ventilating System 9.4-22 9.4.3.3.7 Miscellaneous Ventilation and Air-Conditioning System 9.4-23 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 9.4.4.2.1 Elevation 755.0 Ventilation 9.4-24 9.4.4.2.2 Elevation 729.0 and Elevation 708.0 Ventilation 9.4-24 9.4.4.2.3 El. 685.5 Ventilation 9.4-24 9.4.4.2.4 Cold Weather Building Pressurization 9.4-25 9.4.4.2.5 Miscellaneous Ventilating Systems 9.4-25 9.4.4.2.6 Coolers 9.4-25 Space Coolers 25 Pump Coolers 26 9.4.4.2.7 Building Heating System 9.4-26 9.4.4.3 Safety Evaluation 9.4-26 9.4.4.4 Inspection and Testing Requirements 9.4-27 9.4.5 Engineered Safety Feature Ventilation Systems 9.4-27 9.4.5.1 ERCW Intake Pumping Station 9.4-27 9.4.5.1.1 Design Bases 9.4-27 9.4.5.1.2 System Description 9.4-28 9.4.5.1.3 Safety Evaluation 9.4-28 9.4.5.1.4 Inspection and Testing Requirements 9.4-29 9.4.5.2 Diesel Generator Buildings 9.4-29 9.4.5.2.1 Diesel Generator Building 9.4-29 Design Bases 29 System Description 31 Safety Evaluation 32 Tests and Inspections 33 9.4.5.2.2 Additional Diesel Generator Building (Not required Unit 1 operation) 9.4-33 Design Bases 33 System Description 34 Safety Evaluation 35 Tests and Inspections 36 9.4.5.3 Auxiliary Building Safety Features Equipment Coolers 9.4-36 9.4.5.3.1 Design Bases 9.4-36 9.4.5.3.2 System Description 9.4-38 1-lxxxvi Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.4.5.3.3 Safety Evaluation 9.4-38 9.4.5.3.4 Inspection and Testing Requirements 9.4-40 9.4.6 Reactor Building Purge Ventilating System 9.4-40 9.4.6.1 Design Bases 9.4-40 9.4.6.2 System Description 9.4-42 9.4.6.3 Safety Evaluation 9.4-44 9.4.6.4 Inspection and Testing Requirements 9.4-45 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 9.4.7.2.1 Lower Compartment Air Cooling System 9.4-46 9.4.7.2.2 Control Rod Drive Mechanisms Air Cooling System 9.4-47 9.4.7.2.3 Upper Compartment Air Cooling System 9.4-47 9.4.7.2.4 Reactor Building Instrument Room Air Cooling System 9.4-48 9.4.7.2.5 Controls and Instrumentation 9.4-48 9.4.7.3 Safety Evaluation 9.4-48 9.4.7.4 Test and Inspection Requirements 9.4-49 9.4.8 Condensate Demineralizer Waste Evaporator Building Environmental Control Sys-tem 9.4-49 9.4.9 Postaccident Sampling Facility (PASF) Environmental Control System 9.4-49 9.5 OTHER AUXILIARY SYSTEMS 9.5-1 9.5.1 Fire Protection System 9.5-1 9.5.1.1 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 9.5-7 9.5.3 Lighting Systems 9.5-8 9.5.3.1 Design Bases 9.5-8 9.5.3.2 Description of the Plant Lighting System 9.5-8 9.5.3.3 Diesel Generator Building Lighting System 9.5-9 9.5.3.4 Safety Related Functions of the Lighting Systems 9.5-10 9.5.3.5 Inspection and Testing Requirements 9.5-10 9.5.4 Diesel Generator Fuel Oil Storage and Transfer System 9.5-10 9.5.4.1 Design Basis 9.5-10 9.5.4.2 System Description 9.5-11 9.5.4.3 Safety Evaluation 9.5-14 Table of Contents 1-lxxxvii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.5.4.4 Tests and Inspections 9.5-15 9.5.5 Diesel Generator Cooling Water System 9.5-15 9.5.5.1 Design Bases 9.5-15 9.5.5.2 System Description 9.5-15 9.5.5.3 Safety Evaluation 9.5-16 9.5.5.4 Tests and Inspections 9.5-16 9.5.6 Diesel Generator Starting System 9.5-17 9.5.6.1 Design Bases 9.5-17 9.5.6.2 System Description 9.5-17 9.5.6.3 Safety Evaluation 9.5-18 9.5.6.4 Tests and Inspections 9.5-18 9.5.7 Diesel Engine Lubrication System 9.5-18 9.5.7.1 Design Bases 9.5-18 9.5.7.2 System Description 9.5-19 9.5.7.3 Safety Evaluation 9.5-20 9.5.7.4 Test and Inspections 9.5-21 9.5.8 Diesel Generator Combustion Air Intake and Exhaust System 9.5-21 9.5.8.1 Design Bases 9.5-21 9.5.8.2 System Descriptions 9.5-21 9.5.8.3 Safety Evaluation 9.5-22 9.5.8.4 Tests and Inspection 9.5-22 10.0 MAIN STEAM AND POWER CONVERSION SYSTEMS 10.1 | |||
==SUMMARY== | ==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 10.2-8 10.2.3.3 High Temperature Properties 10.2-9 10.2.3.4 Turbine Disc Design 10.2-10 10.2.3.5 Preservice Inspection 10.2-10 10.2.3.5.1 Low Pressure Turbine Rotor 10.2-10 10.2.3.5.2 High Pressure Turbine Rotor 10.2-11 10.2.3.5.3 Preoperational and Initial Startup Testing 10.2-11 10.2.3.6 Inservice Inspection 10.2-11 10.2.3.6.1 Turbine Rotors 10.2-11 10.2.3.6.2 Turbine Overspeed Protection 10.2-12 10.2.3.6.3 Other Turbine Protection Features 10.2-13 10.2.4 Evaluation 10.2-13 1-lxxxviii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 10.3-4 10.3.5.1 Purpose 10.3-4 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 10.3-6 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 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 10.4-9 10.4.4.3 Safety Evaluation 10.4-9 10.4.4.4 Inspection and Testing 10.4-10 10.4.4.5 Instrumentation 10.4-11 10.4.5 Condenser Circulating Water System 10.4-11 10.4.5.1 Design Basis 10.4-11 Table of Contents 1-lxxxix | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 10.4.5.2 System Description 10.4-12 10.4.5.3 Safety Evaluation 10.4-14 10.4.5.4 Inspection and Testing 10.4-15 10.4.5.5 Instrumentation Application 10.4-15 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 10.4-16 10.4.6.3 Safety Evaluation 10.4-18 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 10.4-20 10.4.7.3 Safety Evaluation 10.4-27 10.4.7.4 Inspection and Testing 10.4-28 10.4.7.5 Instrumentation 10.4-29 10.4.8 Steam Generator Blowdown System 10.4-29 10.4.8.1 Design Bases 10.4-29 10.4.8.2 System Description and Operation 10.4-30 10.4.8.3 Safety Evaluation 10.4-31 10.4.8.4 Inspections and Testing 10.4-32 10.4.9 Auxiliary Feedwater System 10.4-32 10.4.9.1 Design Bases 10.4-32 10.4.9.2 System Description 10.4-33 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 10.4-38 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 1-xc Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 11.2.3 SYSTEM DESIGN 11.2-4 11.2.3.1 Component Design 11.2-4 11.2.3.2 Instrumentation Design 11.2-9 11.2.4 Operating Procedure 11.2-10 11.2.5 PERFORMANCE TESTS 11.2-16 11.2.6 ESTIMATED RELEASES 11.2-17 11.2.6.1 NRC Requirements 11.2-17 11.2.6.2 Westinghouse PWR Release Experience 11.2-17 11.2.6.3 Expected Liquid Waste Processing System Releases 11.2-17 11.2.6.4 Turbine Building (TB) Drains 11.2-17 11.2.6.4.1 Purpose 11.2-17 11.2.6.4.2 Description 11.2-17 Condensate Polishing Demineralizer System Drains 18 Other Turbine Building Drainage 18 Oil and Oily Water Drainage 18 11.2.6.5 Estimated Total Liquid Releases 11.2-18 11.2.7 RELEASE POINTS 11.2-18 11.2.8 DILUTION FACTORS 11.2-19 11.2.9 ESTIMATED DOSES FROM RADIONUCLIDES IN LIQUID EFFLUENTS 11.2-19 11.2.9.1 Assumptions and Calculational Methods 11.2-19 11.2.9.2 Summary of Dose from Radionuclides in Liquid Effluents 11.2-21 11.3 GASEOUS WASTE SYSTEMS 11.3-1 11.3.1 Design Bases 11.3-1 11.3.2 SYSTEM DESCRIPTIONS 11.3-1 11.3.3 SYSTEM DESIGN 11.3-3 11.3.3.1 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 11.3-7 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 11.3-9 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 11.3-12 Table of Contents 1-xci | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 11.4 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYS-TEM 11.4-1 11.4.1 Design Objectives 11.4-1 11.4.2 Continuous Monitors 11.4-2 11.4.2.1 Liquid Monitors 11.4-2 11.4.2.1.1 Waste Disposal System Liquid Effluent Monitor 11.4-2 11.4.2.1.2 Essential Raw Cooling Water Effluent Monitors 11.4-2 11.4.2.1.3 Component Cooling System Liquid Effluent Monitors 11.4-3 11.4.2.1.4 Steam Generator Blowdown Effluent Monitor 11.4-3 11.4.2.1.5 Condensate Demineralizer Regenerant Effluent Monitor 11.4-3 11.4.2.1.6 Turbine Building Sump Effluent Monitor 11.4-3 11.4.2.2 Gaseous Monitors 11.4-4 11.4.2.2.1 Waste Gas Holdup System Effluent Monitor 11.4-4 11.4.2.2.2 Condenser Vacuum Air Exhaust Monitors 11.4-4 11.4.2.2.3 Spent Fuel Pool Accident Radiation Monitors 11.4-5 11.4.2.2.4 Ventilation Monitors and Containment Atmosphere Monitors 11.4-5 11.4.2.2.5 Main Control Room Air Intake Monitors 11.4-7 11.4.2.2.6 Containment Purge Air Exhaust Monitors 11.4-8 11.4.2.2.7 Main Steamline Radiation Monitors 11.4-8 11.4.3 SAMPLING 11.4-8 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 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 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 11.5-4 11.5.6 Shipment 11.5-5 11.6 Offsite Radiological Monitoring Program 11.6-1 11.6.1 Expected Background 11.6-2 11.6.2 Critical Pathways to Man 11.6-2 11.6.2.1 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 1-xcii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 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 12.2.1.1.1 Sources Shielded by Primary Shield Concrete 12.2-3 12.2.1.1.2 Sources Shielded by Secondary Shield Concrete 12.2-4 12.2.1.2 Auxiliary Systems Sources 12.2-4 12.2.1.2.1 Chemical and Volume Control System - Mixed-Bed Demineralizers 12.2-4 12.2.1.2.2 Chemical and Volume Control System - Cation Bed Demineralizer 12.2-4 12.2.1.2.3 Chemical and Volume Control System - Volume Control Tanks 12.2-5 12.2.1.2.4 Chemical and Volume Control System - Reactor Coolant Filter 12.2-5 12.2.1.2.5 Chemical and Volume Control System - Seal Water Return Filter 12.2-5 12.2.1.2.6 Chemical and Volume Control System - Seal Water Injection Filters 12.2-6 12.2.1.2.7 Chemical and Volume Control System - Holdup Tanks 12.2-6 12.2.1.2.8 Chemical and Volume Control System - Evaporator Feed Mixed-Bed Ion Table of Contents 1-xciii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page Exchangers 12.2-6 12.2.1.2.9 Chemical and Volume Control System - Evaporator Feed Cation Bed Ion Exchanger 12.2-7 12.2.1.2.10 Chemical and Volume Control System - Ion Exchange Filters 12.2-7 12.2.1.2.11 Gas Stripper and Boric Acid Evaporator Package 12.2-7 12.2.1.2.12 Spent Fuel Pool Cooling System Demineralizer and Filters 12.2-8 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 12.3.4.1.1 Objectives and Design Basis 12.3-17 12.3.4.1.2 Operation Characteristics 12.3-17 Area Monitor Detector 17 Main Control Room Ratemeter (0-M-12, 1-,2-M-30) 18 Local Indicator-Alarm Panel 18 Multipoint Recorders (Main Control Room 0-M-12, 1-,2-M-31) 18 Monitor Sensitivity and Range 18 12.3.4.1.3 Area Monitor Calibration and Maintenance 12.3-18 12.3.4.2 Airborne Particulate Radioactivity Monitoring 12.3-19 12.3.4.2.1 Design Basis 12.3-19 12.3.4.2.2 Airborne Monitoring Channels 12.3-20 12.3.4.2.3 Operational Characteristics 12.3-20 12.3.4.2.4 Component Descriptions 12.3-21 12.3.4.2.5 Sensitivity, Range and Set Point 12.3-22 12.3.4.2.6 Calibration and Maintenance 12.3-22 12.3.4.3 Deleted by Amendment 84. 12.3-23 12.3.4.4 Special Radiation Monitors 12.3-23 12.3.4.4.1 Portal Monitors 12.3-23 12.3.4.4.2 Personnel Contamination Monitors 12.3-23 12.3.4.4.3 Deleted by Amendment 84. 12.3-23 12.4 DOSE ASSESSMENT 12.4-1 1-xciv Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 12.5 RADIATION PROTECTION PROGRAM 12.5-1 12.5.1 Organization 12.5-1 12.5.2 Equipment, Instrumentation, and Facilities 12.5-2 12.5.3 Procedures 12.5-4 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 13.1-2 13.1.2.1 Offsite Organizations 13.1-2 13.1.2.2 Onsite Organization 13.1-2 13.1.3 Qualification Requirements for Nuclear Facility Personnel 13.1-2 13.2 TRAINING PROGRAMS 13.2-1 13.2.1 Accredited Training Programs 13.2-1 13.2.2 General Employee and Fitness for Duty Training 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 13.5.2.1.1 General Operating Instructions 13.5-2 13.5.2.1.2 System Operating Instructions 13.5-2 13.5.2.1.3 Abnormal Operating Instructions 13.5-3 13.5.2.1.4 Emergency Instructions 13.5-3 13.5.2.1.5 Alarm Response Instructions 13.5-3 13.5.2.1.6 Fuel Handling Instructions 13.5-3 13.5.2.2 Other Procedures 13.5-3 13.5.2.2.1 Maintenance Instructions and Modification Procedures 13.5-3 13.5.2.2.2 Instrument Maintenance Instructions 13.5-3 13.5.2.2.3 Surveillance Instructions and Technical Requirement Instructions 13.5-4 13.5.2.2.4 Technical Instructions 13.5-4 Table of Contents 1-xcv | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 13.5.2.2.5 Miscellaneous Procedures 13.5-4 13.5.2.2.6 Power Escalation Tests 13.5-4 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 14.2.2.1.1 Startup Manager 14.2-3 14.2.2.1.2 Section deleted by Amendment 84 14.2-4 14.2.2.1.3 System Test Engineers 14.2-4 14.2.2.2 Plant Operating Organization 14.2-5 14.2.2.2.1 Technical Support Manager 14.2-5 14.2.2.2.2 Power Ascension Test Engineers 14.2-5 14.2.2.2.3 Operations 14.2-6 14.2.2.2.4 Maintenance 14.2-6 14.2.2.3 Nuclear Assurance 14.2-6 14.2.2.4 Major Participating Organizations 14.2-6 14.2.2.4.1 Nuclear Engineering 14.2-6 14.2.2.4.2 Construction 14.2-7 14.2.2.4.3 Westinghouse Electric Corporation 14.2-7 14.2.2.5 Joint Test Group 14.2-7 14.2.2.5.1 JTG Membership 14.2-8 14.2.2.6 Test Review Group 14.2-8 14.2.2.6.1 TRG Membership 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 1-xcvi Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 14.2-34 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 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 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 Table of Contents 1-xcvii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 15.2.4.2.1 Method of Analysis 15.2-14 15.2.4.2.2 Dilution During Refueling 15.2-14 15.2.4.2.3 Dilution During Startup 15.2-15 15.2.4.2.4 Dilution at Power 15.2-15 15.2.4.3 Conclusions 15.2-16 15.2.4.3.1 For Dilution During Refueling 15.2-16 15.2.4.3.2 For Dilution During Startup 15.2-16 15.2.4.3.3 For Dilution Following Reactor Shutdown 15.2-16 15.2.4.3.4 For Dilution During Full Power Operation 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-xcviii 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 15.2.10.0.1 Identification of Causes and Accident Description 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-xcix | |||
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 15.4.1.1.1 Westinghouse Performance Criteria for Emergency Core Cooling System 15.4-3 15.4.1.1.2 Method of Thermal Analysis 15.4-3 15.4.1.1.3 Containment Analysis 15.4-3 15.4.1.1.4 Results of Large Break Spectrum 15.4-4 15.4.1.1.5 Effect of Containment Purging 15.4-5 15.4.1.1.6 Conclusions - Thermal Analysis 15.4-6 15.4.1.2 Hydrogen Production and Accumulation 15.4-6 15.4.1.2.1 Method of Analysis 15.4-6 15.4.1.2.2 Typical Assumptions 15.4-7 15.4.1.2.3 Core Solution Radiolysis 15.4-9 15.4.1.2.4 Sump Solution Radiolysis 15.4-11 15.4.1.2.5 Results 15.4-12 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 15.4.2.1.1 Identification of Causes and Accident Description 15.4-12 15.4.2.1.2 Analysis of Effects and Consequences 15.4-14 15.4.2.1.3 Conclusions 15.4-19 1-c Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 15.4.2.2 Major Rupture of a Main Feedwater Pipe 15.4-19 15.4.2.2.1 Identification of Causes and Accident Description 15.4-19 15.4.2.2.2 Analysis of Effects and Consequences 15.4-20 15.4.2.2.3 Conclusions 15.4-22 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 15.4.6.1.1 Design Precautions and Protection 15.4-35 15.4.6.1.2 Limiting Criteria 15.4-38 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 15.5-19 15.5.5 Environmental Consequences of a Postulated Steam Generator Tube Rupture 15.5-20 15.5.6 Environmental Consequences of a Postulated Fuel Handling Accident 15.5-21 15.5.7 Environmental Consequences of a Postulated Rod Ejection Accident 15.5-23 15A DOSE MODELS USED TO EVALUATE THE ENVIRONMENTAL CONSEQUENC-ES OF ACCIDENTS 15A.1 INTRODUCTION 15A-1 15A.2 ASSUMPTIONS 15A-1 15A.3 GAMMA DOSE AND BETA DOSE 15A-1 15A.4 THYROID INHALATION DOSE 15A-2 Table of Contents 1-ci | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.1-1 16.2 PROPOSED FINAL TECHNICAL SPECIFICATIONS 16.2-1 16.3 RELOCATED SPECIFICATIONS 16.1-1 16.3.1 Discussion 16.1-1 16.3.2 Document Control 16.1-1 16.3.3 Changes to the Relocated Specifications 16.1-1 17.0 QUALITY ASSURANCE 17-1 17.1 Quality Assurance During Design and Construction 17-1 17.1.1 TVA Organization 17-1 17.1.2 Quality Assurance Program 17-1 17.1A WESTINGHOUSE NUCLEAR ENERGY SYSTEM DIVISIONS QUALITY ASSURANCE PLAN 17-2 17.2 QUALITY ASSURANCE FOR STATION OPERATION 17.2-1 17.2.1 Identification of Safety-Related Features 17.2-1 1-cii Table of Contents | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page Table of Contents 1-ciii | |||
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 1-civ Table of Contents}} | |||
Latest revision as of 23:21, 13 November 2019
| ML093570483 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/14/2009 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML093570483 (68) | |
Text
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 028_TVA_WB_FSAR_Section_17.0.pdf 027_TVA_WB_FSAR_Section_16.pdf 026_TVA_WB_FSAR_Section_15.pdf 024_TVA_WB_FSAR_Section_13.pdf 018_TVA_WB_FSAR_Section_8 017_TVA_WB_FSAR_Section_7.pdf 014_TVA_WB_FSAR_Section_5.pdf 013_TVA_WB_FSAR_Section_4.pdf 005_TVA_WB_FSAR_Section_2_B.pdf 004_TVA_WB_FSAR_Section_2_A.pdf 003_TVA_WB_FSAR_Section_1.pdf
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
1.1-1 1.2 GENERAL PLANT DESCRIPTION 1.2-1 1.2.1 Site Characteristics 1.2-1 1.2.1.1 Location 1.2-1 1.2.1.2 Demography 1.2-1 1.2.1.3 Meteorology 1.2-1 1.2.1.4 Hydrology 1.2-1 1.2.1.5 Geology 1.2-1 1.2.1.6 Seismology 1.2-2 1.2.2 Facility Description 1.2-2 1.2.2.1 Design Criteria 1.2-2 1.2.2.2 Nuclear Steam Supply System (NSSS) 1.2-2 1.2.2.3 Control and Instrumentation 1.2-4 1.2.2.4 Fuel Handling System 1.2-5 1.2.2.5 Waste Processing System 1.2-5 1.2.2.6 Steam and Power Conversion System 1.2-5 1.2.2.7 Plant Electrical System 1.2-6 1.2.2.8 Cooling Water 1.2-7 1.2.2.9 Component Cooling System 1.2-7 1.2.2.10 Chemical and Volume Control System 1.2-7 1.2.2.11 Sampling and Water Quality System 1.2-8 1.2.2.12 Ventilation 1.2-9 1.2.2.13 Fire Protection System 1.2-9 1.2.2.14 Compressed Air Systems 1.2-9 1.2.2.15 Engineered Safety Features 1.2-9 1.2.2.16 Shared Facilities and Equipment 1.2-10 1.2.3 General Arrangement of Major Structures and Equipment 1.2-13 1.3 COMPARISON TABLES 1.3-1 1.3.1 Comparisons With Similar Facility Designs 1.3-1 1.3.2 Comparison Of Final And Preliminary Designs 1.3-1 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 1.4-1 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.5-1 1.5.1 17 x 17 Fuel Assembly 1.5-1 1.5.1.1 Rod Cluster Control Spider Tests 1.5-1 1.5.1.2 Grid Tests 1.5-1 1.5.1.3 Fuel Assembly Structural Tests 1.5-1 1.5.1.4 Guide Tube Tests 1.5-2 1.5.1.5 Prototype Assembly Tests 1.5-2 Table of Contents 1-xxxvii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 1.9-2 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 1.9-3 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 1.9-4 1.9.1.12 Prestart Test Program 1.9-4 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 1.9-5 1.9.1.17 Vendor Information 1.9-5 1.9.1.18 Welding 1.9-5 1.9.2 Special Programs (SPs) 1.9-5 1.9.2.1 Concrete Quality Program 1.9-6 1.9.2.2 Containment Cooling 1.9-6 1.9.2.3 Detailed Control room Design Review 1.9-6 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) 1.9-7 1.9.2.8 Moderate Energy Line Break Flooding (MELB) 1.9-7 1.9.2.9 Radiation Monitoring System 1.9-7 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 2.0 SITE CHARACTERISTICS 1-xxxviii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 2.1-4 2.1.3.6 Population Density 2.1-4 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 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 Table of Contents 1-xxxix
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.3.3.3 Onsite Data Summaries of Parameters for Dispersion Meteorology 2.3-12 2.3.4 Short-Term (Accident) Diffusion Estimates 2.3-13 2.3.4.1 Objective 2.3-13 2.3.4.2 Calculation Results 2.3-15 2.3.5 Long-Term (Routine) Diffusion Estimates 2.3-16 2.4 HYDROLOGIC ENGINEERING 2.4-1 2.4.1 Hydrological Description 2.4-1 2.4.1.1 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 2.4-39 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 2.4-40 2.4.8 Cooling Water Canals and Reservoirs 2.4-41 2.4.9 Channel Diversions 2.4-42 2.4.10 Flooding Protection Requirements 2.4-42 2.4.11 Low Water Considerations 2.4-42 2.4.11.1 Low Flow in Rivers and Streams 2.4-42 2.4.11.2 Low Water Resulting From Surges, Seiches, or Tsunami 2.4-43 2.4.11.3 Historical Low Water 2.4-43 2.4.11.4 Future Control 2.4-43 2.4.11.5 Plant Requirements 2.4-44 2.4.12 Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents 2.4-45 2.4.12.1 Radioactive Liquid Wastes 2.4-45 2.4.12.2 Accidental Slug Releases to Surface Water 2.4-45 2.4.12.2.1 Calculations 2.4-46 2.4.12.3 Effects on Ground Water 2.4-47 2.4.13 Groundwater 2.4-48 1-xl Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.4.13.1 Description and On-Site Use 2.4-48 2.4.13.2 Sources 2.4-48 2.4.13.3 Accident Effects 2.4-50 2.4.13.4 Monitoring and Safeguard Requirements 2.4-50 2.4.13.5 Design Basis for Subsurface Hydrostatic Loading 2.4-51 2.4.14 Flooding Protection Requirements 2.4-51 2.4.14.1 Introduction 2.4-51 2.4.14.1.1 Design Basis Flood 2.4-51 2.4.14.1.2 Combinations of Events 2.4-52 2.4.14.1.3 Post Flood Period 2.4-52 2.4.14.1.4 Localized Floods 2.4-52 2.4.14.2 Plant Operation During Floods Above Grade 2.4-52 2.4.14.2.1 Flooding of Structures 2.4-52 2.4.14.2.2 Fuel Cooling 2.4-53 2.4.14.2.3 Cooling of Plant Loads 2.4-54 2.4.14.3 Warning Scheme 2.4-55 2.4.14.4 Preparation for Flood Mode 2.4-55 2.4.14.4.1 Reactor Initially Operating at Power 2.4-55 2.4.14.4.2 Reactor Initially Refueling 2.4-55 2.4.14.4.3 Plant Preparation Time 2.4-56 2.4.14.5 Equipment 2.4-56 2.4.14.5.1 Equipment Qualification 2.4-56 2.4.14.5.2 Temporary Modification and Setup 2.4-56 2.4.14.5.3 Electric Power 2.4-56 2.4.14.5.4 Instrument, Control, Communication and Ventilation Systems 2.4-57 2.4.14.6 Supplies 2.4-57 2.4.14.7 Plant Recovery 2.4-57 2.4.14.8 Warning Plan 2.4-58 2.4.14.8.1 Rainfall Floods 2.4-58 2.4.14.8.2 Seismically-Induced Dam Failure Floods 2.4-58 2.4.14.9 Basis For Flood Protection Plan In Rainfall Floods 2.4-59 2.4.14.9.1 Overview 2.4-59 2.4.14.9.2 TVA Forecast System 2.4-59 2.4.14.9.3 Basic Analysis 2.4-61 2.4.14.9.4 Hydrologic Basis for Warning System 2.4-61 2.4.14.9.5 Hydrologic Basis for Target States 2.4-62 2.4.14.9.6 Communications Reliability 2.4-63 2.4.14.10 Basis for Flood Protection Plan in Seismic-Caused Dam Failures 2.4-64 2.4.14.11 Special Condition Allowance 2.4-65 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 Table of Contents 1-xli
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.5.1.1.1 Regional Physiography 2.5-3 2.5.1.1.2 Regional Tectonics and Geology 2.5-7 2.5.1.1.3 Regional Geologic Setting 2.5-9 2.5.1.1.4 Regional Geologic History 2.5-10 2.5.1.1.5 Regional Lithologic, Stratigraphic, and Structural Geology 2.5-20 2.5.1.1.6 Regional Tectonics 2.5-22 2.5.1.1.7 Groundwater 2.5-26 2.5.1.2 Site Geology 2.5-26 2.5.1.2.1 Site Physiography 2.5-26 2.5.1.2.2 Site Lithologic, Stratigraphic, and Structural Geologic Conditions 2.5-27 2.5.1.2.3 Site Structural Geology 2.5-29 2.5.1.2.4 Surface Geology 2.5-30 2.5.1.2.5 Site Geologic History 2.5-31 2.5.1.2.6 Plot Plan 2.5-31 2.5.1.2.7 Bedrock Foundation Characteristics 2.5-31 2.5.1.2.8 Excavation and Backfill 2.5-31 2.5.1.2.9 Evaluation of Geologic Conditions 2.5-32 2.5.1.2.10 Groundwater 2.5-33 2.5.1.2.11 Geophysical Surveys 2.5-33 2.5.1.2.12 Soil and Rock Properties 2.5-34 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 2.5-41 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 2.5-42 2.5.2.5 Seismic Wave Transmission Characteristics of the Site 2.5-44 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 2.5-56 2.5.4.1 Geologic Features 2.5-56 2.5.4.2 Properties of Subsurface Materials 2.5-57 2.5.4.2.1 In Situ Soils 2.5-57 General Description 57 Investigations 57 1-xlii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page Test Results and Selection of Design Properties 61 2.5.4.2.2 Rock 2.5-74 Engineering Description of Bedrock 74 Test Program 75 Description of Testing Techniques 75 Test Results for Menard Pressuremeter 77 Comparison of Results from Menard Pressuremeter and Birdwell 3D Sonic Logger 78 Settlement Analysis 78 Behavior of Watts Bar Lock 83 Excavation Experience in the Rutledge Shale at Watts Bar Lock 85 Evaluation of Settlement 86 2.5.4.3 Exploration 2.5-89 2.5.4.4 Geophysical Surveys 2.5-90 2.5.4.4.1 Rock Characteristics 2.5-90 2.5.4.4.2 Soil Characteristics 2.5-90 Equipment 90 Velocity Measurement Procedures 90 Data Analysis and Results 91 Data Analysis and Results - Evaluation Seismic Criteria and New 93 2.5.4.5 Excavations and Backfill 2.5-93 2.5.4.5.1 Earthfill 2.5-93 Investigation 93 Test Results 94 Field Work 97 Construction Control 98 2.5.4.5.2 Granular Fill 2.5-98 General 98 Section 1032 Material 98 Section 1075 Material 100 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 2.5-113 2.5.4.10 Static Analysis 2.5-113 2.5.4.10.1 Settlement 2.5-113 2.5.4.10.2 Bearing Capacity 2.5-114 2.5.4.11 Safety-Related Criteria for Foundations 2.5-115 2.5.4.11.1 General 2.5-115 2.5.4.11.2 Rock Strength 2.5-115 2.5.4.11.3 Soil Strength 2.5-115 2.5.4.12 Techniques to Improve Subsurface Conditions 2.5-115 2.5.4.13 Construction Notes 2.5-118 2.5.5 Stability of Slopes 2.5-118 2.5.5.1 Slope Characteristics 2.5-118 Table of Contents 1-xliii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 2.5.5.1.1 Essential Raw Cooling Water Intake Channel Slopes 2.5-118 2.5.5.1.2 Underground Barrier for Protection Against Potential Soil Liquefaction 2.5-118 2.5.5.2 Design Criteria and Analysis 2.5-120 2.5.5.2.1 Design Criteria and Analyses for the Essential Raw Coolant Water 2.5-120 2.5.5.2.2 Additional Analyses Due to Unexpected Soil Conditions Encountered During Excavation of the Intake Channel 2.5-123 2.5.5.2.3 Design Criteria and Analysis for the Underground Barrier for the ERCW Pipeline and 1E Conduit Alignment 2.5-125 2.5.5.3 Logs of Borings 2.5-127 2.5.5.4 Compaction Specifications 2.5-127 2.5.6 Embankments 2.5-127 3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 3.1-1 3.1.1 Introduction 3.1-1 3.1.2 WBNP Conformance with GDCs 3.1-1 3.1.2.1 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 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 1-xliv Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 3.5.1.1.1 Shield Building 3.5-2 3.5.1.1.2 North and South Steam Valve Rooms 3.5-2 3.5.1.1.3 Auxiliary Building 3.5-3 3.5.1.1.4 Control Building 3.5-4 3.5.1.1.5 ERCW Structures 3.5-4 3.5.1.1.6 ERCW Pipe Tunnels and RWST Foundations 3.5-4 3.5.1.1.7 Diesel Generator Building 3.5-4 3.5.1.2 Internally Generated Missiles (Inside Containment) 3.5-5 3.5.1.2.1 Missile Selection 3.5-5 3.5.1.2.2 Missile Description 3.5-7 3.5.1.2.3 Electrical Cables 3.5-8 3.5.1.2.4 Upper Compartment 3.5-8 3.5.1.2.5 Ice Condenser Compartment 3.5-8 3.5.1.2.6 Lower Compartment 3.5-8 3.5.1.3 Turbine Missiles 3.5-9 3.5.1.3.1 Introduction 3.5-9 3.5.1.3.2 Potential Missile Sources and Missile Characteristics 3.5-10 3.5.1.3.3 Primary Safety-Related Equipment Installations and Structures 3.5-15 3.5.1.3.4 Turbine Missile Protection Criterion 3.5-15 3.5.1.3.5 Turbine Missile Hazard Evaluation 3.5-16 3.5.1.3.6 Turbine Missile Selection 3.5-22 3.5.1.4 Missiles Generated By Natural Phenomena 3.5-23 3.5.1.5 Missiles Generated by Events Near the Site. 3.5-23 3.5.1.6 Aircraft Hazards 3.5-24 3.5.2 Systems To Be Protected 3.5-24 3.5.3 Barrier Design Procedures 3.5-25 3.5.3.1 Additional Diesel Generator Building (And Other Category I Structures Added After July 1979) 3.5-28 3.5.A ESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES 3.5-1 Table of Contents 1-xlv
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING 3.6-1 3.6A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIPING) 3.6-1 3.6A.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment 3.6-8 3.6A.1.1 Design Bases 3.6-8 3.6A.1.1.1 List of Potential Targets 3.6-8 3.6A.1.1.2 Interaction Criteria 3.6-8 3.6A.1.1.3 Acceptability Criteria 3.6-9 3.6A.1.1.4 Protective Measures 3.6-10 3.6A.1.2 Description of Piping System Arrangement 3.6-10 3.6A.1.3 Safety Evaluation 3.6-10 3.6A.2 Determination of Break Locations and Dynamic Effects Associated with the Postu-lated Rupture of Piping 3.6-11 3.6A.2.1 Criteria Used to Define Break and Crack Location and Configuration 3.6-11 3.6A.2.1.1 Pipe Failure Type, Size, and Orientation 3.6-11 3.6A.2.1.2 Break Location 3.6-12 3.6A.2.1.3 Failure Consequences 3.6-15 3.6A.2.1.4 Flooding 3.6-16 3.6A.2.1.5 Leak-Before-Break Application 3.6-17 3.6A.2.2 Analytical Methods to Define Forcing Functions and Response Models 3.6-17 3.6A.2.2.1 Assumptions 3.6-17 3.6A.2.2.2 Blowdown Thrust Loads 3.6-17 3.6A.2.2.3 Jet Impingement Loads 3.6-19 3.6A.2.3 Dynamic Analysis Methods to Verify Integrity and Operability 3.6-21 3.6A.2.3.1 General Criteria for Pipe Whip Evaluation 3.6-21 3.6A.2.3.2 Main Reactor Coolant Loop Piping System 3.6-21 3.6A.2.3.3 Other Piping Systems 3.6-21 3.6A.2.3.4 Simplified Pipe Whip Analysis 3.6-22 3.6A.2.3.5 Pipe Whip Restraint Design 3.6-23 3.6A.2.3.6 Energy Absorbing Materials 3.6-24 3.6A.2.4 Guard Pipe Assembly Design Criteria 3.6-24 3.6A.2.5 Summary of Dynamic Analysis Results 3.6-25 3.6A.2.5.1 Stress Summary and Isometrics - Inside Containment 3.6-25 3.6A.2.5.2 Summary of Protection Requirements and Isometrics-Outside Contain-ment 3.6-26 3.6B PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULAT-ED RUPTURE OF PIPING 3.6-26 3.6B.1 Break Locations And Dynamic Effects Associated With Postulated Primary Loop Pipe Rupture 3.6-26 3.6B.2 Analytical Methods to Define Forcing Function and Response Models 3.6-27 3.6B.3 Dynamic Analysis of the Reactor Coolant Loop Piping Equipment Supports and Pipe Whip Restraints 3.6-29 1-xlvi Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 3.7.1.1.1 Original Site Ground Response Spectra (Set A and Set C) 3.7-2 3.7.1.1.2 Site Specific Ground Response Spectra (Set B) 3.7-2 3.7.1.2 Design Time Histories 3.7-2 3.7.1.2.1 Time Histories for Original Site Ground Response Spectra (Set A and Set C) 3.7-2 3.7.1.2.2 Time Histories for Site Specific Ground Response Spectra (Set B) 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 3.7.2.1.1 Category I Rock-Supported Structures - Original Analyses (Set A) 3.7-4 3.7.2.1.2 Category I Rock - Supported Structures - Evaluation and New Design or Modification Analyses (Set B and Set B+C) 3.7-9 3.7.2.1.3 Category I Soil-Supported Structures - Original Analysis (Set A) 3.7-13 3.7.2.1.4 Category I Soil-Supported Structures - Evaluation and New Design/Mod-ification Analysis (Set B and Set B+C) 3.7-18 3.7.2.1.5 Category I Pile-Supported Structures - Original Analysis (Set A) 3.7-19 3.7.2.1.6 Category I Pile-Supported Structures - Evaluation and New Design/Mod-ification Analyses (Set B and Set B+C) 3.7-21 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 3.7.2.3.1 Other Than NSSS 3.7-22 3.7.2.3.2 For NSSS Analysis 3.7-22 3.7.2.4 Soil/Structure Interaction 3.7-23 3.7.2.4.1 Original Analysis (Set A) 3.7-23 3.7.2.4.2 Evaluation and New Design or Modification Analyses3.7-23 3.7.2.5 Development of Floor Response Spectra 3.7-24 3.7.2.5.1 Original Analysis 3.7-24 3.7.2.5.2 Evaluation and New Design or Modification Analysis 3.7-24 3.7.2.6 Three Components of Earthquake Motion 3.7-25 3.7.2.6.1 Original Analysis (Set A) 3.7-25 3.7.2.6.2 Evaluation and New Design/Modification Analyses (Set B and Set C) 3.7-25 3.7.2.7 Combination of Modal Responses 3.7-26 3.7.2.7.1 Other Than NSSS 3.7-26 Original Analysis (Set A) 26 Evaluation and New Design or Modification Analyses 26 3.7.2.7.2 NSSS System 3.7-27 3.7.2.8 Interaction of Non-Category I Structures With Seismic Category I Structures 3.7-29 Table of Contents 1-xlvii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 3.7.2.10.1 Other Than NSSS 3.7-29 Original Analysis (Set A) 29 Evaluation and New Design or Modification Analyses 30 3.7.2.10.2 For NSSS 3.7-30 3.7.2.11 Methods Used to Account for Torsional Effects 3.7-30 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 3.7-31 3.7.2.14 Determination of Category I Structure Overturning Moments 3.7-31 3.7.2.14.1 Original Analysis 3.7-31 3.7.2.14.2 Evaluation and New Design or Modification Analysis 3.7-31 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 3.7.3.2.1 Category I Systems and Components Other Than NSSS 3.7-32 3.7.3.2.2 NSSS System 3.7-33 3.7.3.3 Procedure Used for Modeling 3.7-33 3.7.3.3.1 Other Than NSSS 3.7-33 Modeling of Piping Systems for Detailed Rigorous Analysis 33 Modeling of Equipment 33 Modeling of HVAC, Conduit, and Cable Tray Subsystems 33 3.7.3.3.2 Modeling of NSSS Subsystems 3.7-34 3.7.3.4 Basis for Selection of Frequencies 3.7-34 3.7.3.4.1 Other Than NSSS 3.7-34 3.7.3.4.2 NSSS Basis for Selection of Forcing Frequencies 3.7-34 3.7.3.5 Use of Equivalent Static Load Method of Analysis 3.7-35 3.7.3.5.1 Other Than NSSS 3.7-35 3.7.3.5.2 Use of Equivalent Static Load Method of Analysis for NSSS 3.7-36 3.7.3.6 Three Components of Earthquake Motion 3.7-36 3.7.3.6.1 Piping Subsystems 3.7-36 3.7.3.6.2 HVAC Ducting, Conduit, and Cable Tray Subsystems 3.7-36 3.7.3.6.3 Other Than NSSS Equipment and Components 3.7-36 3.7.3.7 Combination of Modal Responses 3.7-37 3.7.3.7.1 Other Than NSSS 3.7-37 3.7.3.7.2 Combination of Modal Responses of NSSS 3.7-37 3.7.3.8 Analytical Procedures for Piping Other Than NSSS 3.7-37 3.7.3.8.1 General 3.7-37 3.7.3.8.2 Detailed Seismic Analysis (Rigorous) for Piping Systems 3.7-41 3.7.3.8.3 Alternate (Simplified) Analysis for Piping Systems 3.7-43 3.7.3.8.4 Seismic Analysis of Piping Systems That Span Two or More Seismic Sup-port Zones Such as Buildings, Portions of Buildings, or Primary Compo-nents 3.7-44 1-xlviii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.7.3.9 Multiple Supported Equipment and Components with Distinct Inputs 3.7-44 3.7.3.9.1 Other Than NSSS 3.7-44 3.7.3.9.2 Multiple Supported NSSS Equipment and Components with Distinct In-puts 3.7-44 3.7.3.10 Use of Constant Vertical Load Factors 3.7-45 3.7.3.10.1 Use of Constant Load Factors for Equipment Other Than NSSS 3.7-45 3.7.3.10.2 Use of Constant Vertical Load Factors for NSSS 3.7-45 3.7.3.11 Torsional Effects of Eccentric Masses 3.7-45 3.7.3.11.1 Piping Other Than NSSS 3.7-45 3.7.3.11.2 Torsional Effects of Eccentric Masses of NSSS 3.7-46 3.7.3.12 Buried Seismic Category I Piping Systems 3.7-46 3.7.3.13 Interaction of Other Piping with Seismic Category I Piping 3.7-52 3.7.3.14 Seismic Analyses for Fuel Elements, Control Rod Assemblies, Control Rod Drives, and Reactor Internals 3.7-52 3.7.3.15 Analysis Procedure for Damping 3.7-54 3.7.3.16 Seismic Analysis and Qualification of Category I Equipment Other Than NSSS 3.7-54 3.7.3.16.1 Dynamic Analysis Method For Equipment and Components 3.7-55 3.7.3.16.2 Simplified Dynamic Analysis Method For Equipment and Components 3.7-55 3.7.3.16.3 Equivalent Static Load Method 3.7-56 3.7.3.16.4 Testing Method 3.7-56 3.7.3.16.5 Equipment and Component Mounting Considerations 3.7-56 3.7.3.17 Seismic Analysis and Design of HVAC Duct and Duct Support Systems 3.7-57 3.7.3.17.1 Description of HVAC Duct and Duct Support Subsystems 3.7-57 3.7.3.17.2 Applicable Codes, Standards, and Specifications 3.7-57 3.7.3.17.3 Loads and Load Combinations 3.7-58 3.7.3.17.4 Analysis and Design Procedures 3.7-59 3.7.3.17.5 Structural Acceptance Criteria 3.7-59 3.7.3.17.6 Materials and Quality Control 3.7-60 3.7.3.18 Seismic Qualification of Main Control Room Suspended Ceiling and Air Deliv-ery Components 3.7-61 3.7.4 Seismic Instrumentation Program 3.7-61 3.7.4.1 Comparison with Regulatory Guide 1.12 3.7-61 3.7.4.2 Location and Description of Instrumentation 3.7-61 3.7.4.3 Control Room Operator Notification 3.7-64 3.7.4.4 Controlled Shutdown Logic 3.7-64 3.7.4.5 Comparison of Measured and Predicted Responses 3.7-65 3.7.4.5.1 Retrieval of Data 3.7-65 3.7.4.5.2 Evaluation of Recorded Earthquake 3.7-66 3.8 DESIGN OF CATEGORY I STRUCTURES 3.8-1 3.8.1 Concrete Shield Building 3.8-1 Table of Contents 1-xlix
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.1.1 Description of the Shield Building 3.8-1 3.8.1.1.1 Equipment Hatch Doors and Sleeves 3.8-2 3.8.1.2 Applicable Codes, Standards, and Specifications 3.8-3 3.8.1.3 Loads and Loading Combinations 3.8-5 3.8.1.4 Design and Analysis Procedures 3.8-7 3.8.1.5 Structural Acceptance Criteria 3.8-10 3.8.1.6 Materials, Quality Control and Special Construction Techniques 3.8-11 3.8.1.6.1 Materials 3.8-11 3.8.1.6.2 Quality Control 3.8-12 3.8.1.6.3 Construction Techniques 3.8-13 3.8.2 Testing and Inservice Surveillance Requirements 3.8-13 3.8.2 Steel Containment System 3.8-1 3.8.2.1 Description of the Containment and Penetrations 3.8-1 3.8.2.1.1 Description of the Containment 3.8-1 3.8.2.1.2 Description of Penetrations 3.8-1 3.8.2.2 Applicable Codes, Standards and Specifications 3.8-3 3.8.2.2.1 Codes 3.8-3 3.8.2.2.2 Design Specification Summary 3.8-4 3.8.2.2.3 NRC Regulatory Guides 3.8-6 3.8.2.3 Loads and Loading Combinations 3.8-7 3.8.2.3.1 Design Loads 3.8-7 3.8.2.3.2 Loading Conditions 3.8-9 3.8.2.4 Design and Analysis Procedures 3.8-11 3.8.2.4.1 Introduction 3.8-11 3.8.2.4.2 Static Stress Analysis 3.8-12 3.8.2.4.3 Dynamic Seismic Analysis 3.8-12 3.8.2.4.4 Non-Axisymmetric Pressure Loading Analysis 3.8-13 3.8.2.4.5 Thermal Analysis 3.8-14 3.8.2.4.6 Penetrations Analysis 3.8-14 3.8.2.4.7 Interaction of Containment and Attached Equipment 3.8-16 3.8.2.4.8 Anchorage 3.8-17 3.8.2.5 Structural Acceptance Criteria 3.8-18 3.8.2.5.1 Margin of Safety 3.8-18 3.8.2.6 Materials, Quality Control, and Special Construction Techniques 3.8-18 3.8.2.6.1 Materials - General 3.8-18 3.8.2.6.2 Corrosion Protection 3.8-21 3.8.2.6.3 Protective Coatings 3.8-23 3.8.2.6.4 Tolerances 3.8-24 3.8.2.6.5 Vessel Material Inspection and Test 3.8-24 3.8.2.6.6 Impact Testing 3.8-25 3.8.2.6.7 Post-Weld Heat Treatment 3.8-25 3.8.2.6.8 Welding 3.8-25 3.8.2.7 Testing and Inservice Inspection Requirements 3.8-25 1-l Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.2.7.1 Bottom Liner Plates Test 3.8-25 3.8.2.7.2 Vertical Wall and Dome Tests 3.8-25 3.8.2.7.3 Soap Bubble Tests 3.8-25 3.8.2.7.4 Overpressure Tests 3.8-26 3.8.2.7.5 Leakage Rate Test 3.8-26 3.8.2.7.6 Operational Testing 3.8-26 3.8.2.7.7 Leak Testing Airlocks 3.8-26 3.8.2.7.8 Penetration Tests 3.8-27 3.8.2.7.9 Inservice Inspection Requirements 3.8-27 3.8.3 Concrete Interior Structure 3.8-1 3.8.3.1 Description of the Interior Structure 3.8-1 3.8.3.2 General 3.8-1 3.8.3.3 Containment Floor Structural Fill Slab 3.8-1 3.8.3.4 Reactor Cavity Wall 3.8-2 3.8.3.5 Compartment Above Reactor 3.8-2 3.8.3.6 Refueling Canal Walls and Floor (Divider Barrier) 3.8-3 3.8.3.7 Crane Wall 3.8-3 3.8.3.8 Steam Generator Compartments (Divider Barrier) 3.8-5 3.8.3.9 Pressurizer Compartment (Divider Barrier) 3.8-5 3.8.3.10 Divider Deck at Elevation 756.63 (Divider Barrier) 3.8-5 3.8.3.11 Ice Condenser Support Floor - Elevation 744.5 (Divider Barrier) 3.8-5 3.8.3.12 Penetrations Through the Divider Barrier Canal Gate 3.8-6 3.8.3.13 Applicable Codes, Standards and Specifications 3.8-7 3.8.3.14 Loads and Loading Combinations 3.8-13 3.8.3.15 Design and Analysis Procedures 3.8-16 3.8.3.16 General 3.8-16 3.8.3.17 Structural Fill Slab on Containment Floor 3.8-16 3.8.3.18 Reactor Cavity Wall 3.8-16 3.8.3.19 Compartment Above Reactor 3.8-18 3.8.3.20 Seals Between Upper and Lower Compartments 3.8-18 3.8.3.21 Refueling Canal Walls and Floor (Divider Barrier) 3.8-19 3.8.3.22 Crane Wall 3.8-20 3.8.3.23 Steam Generator Compartments (Divider Barrier) 3.8-23 3.8.3.24 Pressurizer Compartment (Divider Barrier) 3.8-25 3.8.3.25 Operating Deck at Elevation 756.63 (Divider Barrier) 3.8-26 3.8.3.26 Ice Condenser Support Floor Elevation 744.5 (Divider Barrier) 3.8-27 3.8.3.27 Ice Condenser 3.8-28 3.8.3.28 Penetrations Through the Divider Barrier 3.8-29 3.8.3.29 Structural Acceptance Criteria 3.8-31 3.8.3.30 General 3.8-31 3.8.3.31 Structural Fill Slab on Containment Floor 3.8-31 3.8.3.32 Reactor Cavity Wall and Compartment Above Reactor 3.8-31 3.8.3.33 Refueling Canal Walls and Floor 3.8-32 Table of Contents 1-li
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.3.34 Crane Wall 3.8-32 3.8.3.35 Steam Generator and Pressurizer Compartment 3.8-32 3.8.3.36 Operating Deck at Elevation 756.63 3.8-32 3.8.3.37 Ice Condenser Support Floor Elevation 744.5 3.8-32 3.8.3.38 Penetrations Through the Divider Barrier 3.8-32 3.8.3.39 Personnel Access Doors in Crane Wall 3.8-33 3.8.3.40 Seals Between Upper and Lower Compartments 3.8-33 3.8.3.41 Ice Condenser 3.8-33 3.8.3.42 Materials, Quality Control and Special Construction Techniques 3.8-34 3.8.3.43 Materials 3.8-34 3.8.3.44 Quality Control 3.8-35 3.8.3.45 Construction Technique 3.8-36 3.8.3.46 Ice Condenser 3.8-36 3.8.3.47 Testing and Inservice Surveillance Requirements 3.8-38 3.8.3.48 Environmental Effects 3.8-38 3.8.3.49 Interface Control 3.8-39 3.8.4 Other Category I Structures 3.8-1 3.8.4.1 Description of the Structures 3.8-1 3.8.4.2 Auxiliary-Control Building 3.8-1 3.8.4.3 Diesel Generator Building 3.8-10 3.8.4.4 Category I Water Tanks and Pipe Tunnels 3.8-12 3.8.4.5 Class 1E Electrical System Manholes and Duct Runs 3.8-13 3.8.4.6 North Steam Valve Room 3.8-13 3.8.4.7 Intake Pumping Station and Retaining Walls 3.8-14 3.8.4.8 Miscellaneous Essential Raw Cooling Water (ERCW) Structures 3.8-15 3.8.4.9 Additional Diesel Generator Building 3.8-16 3.8.4.10 Applicable Codes, Standards, and Specifications 3.8-17 3.8.4.11 List of Documents 3.8-17 3.8.4.12 Basis for Use of the 1963 Edition of ACI 318 3.8-19 3.8.4.13 Loads and Loading Combinations 3.8-21 3.8.4.14 Description of Loads 3.8-21 3.8.4.15 Load Combinations and Allowable Stresses 3.8-22 3.8.4.16 Design and Analysis Procedures 3.8-23 3.8.4.17 Auxiliary-Control Building 3.8-23 3.8.4.18 Diesel Generator Building 3.8-30 3.8.4.19 Category I Water Tanks and Pipe Tunnels 3.8-31 3.8.4.20 Class 1E Electrical System Manholes 3.8-31 3.8.4.21 North Steam Valve Room 3.8-31 3.8.4.22 Intake Pumping Station and Retaining Walls Pumping Station 3.8-32 3.8.4.23 Miscellaneous ERCW Structures 3.8-32 3.8.4.24 Additional Diesel Generator Building 3.8-33 3.8.4.25 Structural Acceptance Criteria 3.8-35 3.8.4.26 Concrete 3.8-35 1-lii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.4.27 Structural and Miscellaneous Steel 3.8-35 3.8.4.28 Miscellaneous Components of the Auxiliary Building 3.8-36 3.8.4.29 Intake Pumping Station Traveling Water Screens 3.8-37 3.8.4.30 Diesel Generator Building Doors and Bulkheads 3.8-37 3.8.4.31 Additional Diesel Generator Building Missile Barriers 3.8-37 3.8.4.32 Materials, Quality Control, and Special Construction Techniques General 3.8-37 3.8.4.33 Materials 3.8-37 3.8.4.34 Quality Control 3.8-38 3.8.4.35 Special Construction Techniques 3.8-38 3.8.4.36 Testing and Inservice Surveillance Requirements 3.8-38 3.8.4.37 Concrete and Structural Steel Portions of Structures 3.8-38 3.8.4.38 Miscellaneous Components of Auxiliary-Control Building 3.8-39 3.8.4.39 Deleted by Amendment 79 3.8-40 3.8.4.40 Miscellaneous Components of the Intake Pumping Station 3.8-40 3.8.5 Foundations and Concrete Supports 3.8-1 3.8.5.1 Description of Foundations and Supports 3.8-1 3.8.5.1.1 Primary Containment 3.8-1 3.8.5.1.2 Foundations of Other Category I Structures 3.8-1 3.8.5.2 Applicable Codes, Standards, and Specifications 3.8-3 3.8.5.3 Loads and Loading Combinations 3.8-3 3.8.5.4 Design and Analysis Procedure 3.8-4 3.8.5.4.1 Primary Containment Foundation 3.8-4 3.8.5.4.2 Auxiliary-Control Building 3.8-4 3.8.5.4.3 Intake Pumping Station 3.8-4 3.8.5.4.4 Soil-Supported Structures 3.8-4 3.8.5.4.5 Pile Supported Structures 3.8-5 3.8.5.5 Structural Acceptance Criteria 3.8-5 3.8.5.5.1 Primary Containment Foundation 3.8-5 3.8.5.5.2 Foundations of Other Category I Structures Auxiliary-Control Building 3.8-5 3.8.5.6 Materials, Quality Control, and Special Construction Techniques 3.8-6 3.8.5.6.1 Materials 3.8-6 3.8.5.6.2 Quality Control 3.8-7 3.8.5.6.3 Special Construction Techniques 3.8-7 3.8.6 Category I(L) Cranes 3.8-1 3.8.6.1 Polar Cranes 3.8-1 3.8.6.1.1 Description 3.8-1 3.8.6.1.2 Applicable Codes, Standards, and Specifications 3.8-1 3.8.6.1.3 Loads, Loading Combinations, and Allowable Stresses 3.8-2 3.8.6.1.4 Design and Analysis Procedure 3.8-2 3.8.6.1.5 Structural Acceptance Criteria 3.8-2 3.8.6.1.6 Materials, Quality Controls, and Special Construction Techniques 3.8-3 3.8.6.1.7 Testing and Inservice Surveillance Requirements 3.8-3 Table of Contents 1-liii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8.6.1.8 Safety Features 3.8-3 3.8.6.2 Auxiliary Building Crane 3.8-4 3.8.6.2.1 Description 3.8-4 3.8.6.2.2 Applicable Codes, Standards, and Specifications 3.8-5 3.8.6.2.3 Loads, Loading Combinations, and Allowable Stresses 3.8-5 3.8.6.2.4 Design and Analysis Procedure 3.8-5 3.8.6.2.5 Structural Acceptance Criteria 3.8-6 3.8.6.2.6 Materials, Quality Controls, and Special Construction Techniques 3.8-6 3.8.6.2.7 Testing and Inservice Surveillance Requirements 3.8-7 3.8.6.2.8 Safety Features 3.8-7 3.8A SHELL TEMPERATURE TRANSIENTS 3.8-1 3.8B BUCKLING STRESS CRITERIA 3.8-1 3.8B.1 INTRODUCTION 3.8-1 3.8B.2 SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS 3.8-1 3.8B.2.1 Circular Cylindrical Shells Under Axial Compression 3.8-1 3.8B.2.2 Circular Cylindrical Shells in Circumferential Compression 3.8-2 3.8B.2.3 Circular Cylindrical Shells Under Torsion 3.8-2 3.8B.2.4 where a is the effective length and b is the circumference of the cylinder. The coefficient K's is given in Figure 3.8B-10.Circular Cylindrical Shells Under Bending 3.8-3 3.8B.2.5 Circular Cylindrical Shell Under Combined Loads 3.8-3 3.8B.3 SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND VERTICAL STIFFENERS 3.8-5 3.8B.4 SPHERICAL SHELLS 3.8-7 3.8B.2.1 The critical buckling stress in the spherical dome, except for external pressure, was determined by the following equation: 3.8-7 3.8B.2.2 Spherical Shell Under Combined Loads 3.8-7 3.8B.3 FACTOR OF SAFETY 3.8-8 3.8C DOCUMENTATION OF CB&I COMPUTER PROGRAMS 3.8-1 3.8C.1 INTRODUCTION 3.8-1 3.8C.2 PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN VALUE TECHNIQUE 3.8-1 3.8C.3 PROGRAM 1044-SEISMIC ANALYSIS of VESSEL APPENDAGES 3.8-1 3.8C.4 PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS DIGITIZED AT EQUAL INTERVALS 3.8-3 3.8C.5 PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS 3.8-3 3.8C.6 PROGRAM E1623-POST PROCESSOR PROGRAM FOR PROGRAM E1374 3.8-4 3.8C.7 PROGRAM E1374-SHELL DYNAMIC ANALYSIS 3.8-5 3.8C.7.1 Introduction 3.8-5 3.8C.8 PROGRAM E1622-LOAD GENERATION PREPROCESSOR FOR PROGRAM E1374 3.8-6 1-liv Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.8C.9 PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION 3.8-7 3.8C.10 PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS 3.8-7 3.8C.11 PROGRAM 119-CHECK of FLANGE DESIGN 3.8-7 3.8C.12 PROGRAM 772-NOZZLE REINFORCEMENT CHECK 3.8-7 3.8C.13 PROGRAM 1027-WRC 107 STRESS INTENSITIES AT LOADED ATTACH-MENTS FOR SPHERES OR CYLINDERS WITH ROUND OR SQUARE ATTACHMENT 3.8-8 3.8C.14 PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES 3.8-8 3.8D COMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS 3.8-1 3.8E CODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFICATION AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF NEW FEA-TURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIAT-ED AFTER JULY 1979 3.8-1 3.8E.1 Application Codes and Standards 3.8-1 3.8E.2 Load Definitions 3.8-1 3.8E.3 Load Combinations - Concrete 3.8-3 3.8E.4 Load Combinations - Structural Steel 3.8-5 3.9 MECHANICAL SYSTEMS AND COMPONENTS 3.9-1 3.9.1 General Topic for Analysis of Seismic Category I ASME Code and Non-Code Items 3.9-1 3.9.1.1 Design Transients 3.9-1 3.9.1.2 Computer Programs Used in Analysis and Design 3.9-1 3.9.1.2.1 Other Than NSSS Systems, Components, Equipment, and Supports 3.9-1 3.9.1.2.2 Programs Used for Category I Components of NSSS 3.9-3 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 3.9.1.4.1 Subsystems and Components Analyzed by Westinghouse 3.9-3 3.9.1.4.2 Subsystems and Components Analyzed by TVA 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 3.9.2.5.1 Evaluation of Reactor Internals for Limited Displacement RPV Inlet and Outlet Nozzle Break 3.9-17 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 Table of Contents 1-lv
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.9.3.1 Loading Combinations, Design Transients, and Stress Limits 3.9-20 3.9.3.1.1 Subsystems and Components Supplied by Westinghouse 3.9-20 Plant Conditions and Design Loading Combinations For ASME Code Class 2 and 3 Components Supplied by Westinghouse 21 Design Loading Combinations by Westinghouse 21 Design Stress Limits By Westinghouse 22 3.9.3.1.2 Subsystems and Components Analyzed or Specified by TVA 3.9-22 3.9.3.2 Pumps and Valve Operability Assurance 3.9-27 3.9.3.2.1 Active* ASME Class 1, 2, & 3 Pumps and Valves 3.9-27 3.9.3.2.2 Operability Assurance 3.9-28 Westinghouse Scope of Supply 28 TVA Scope of Supply 33 3.9.3.2.3 Criteria For Assuring Functional Adequacy of Active Seismic Category I Fluid System Components (Pumps and Valves) and Associated Essential Auxiliary Equipment 3.9-34 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 3.9.3.4.1 Subsystem and Component Supports Analyzed or Specified by Westing-house 3.9-42 3.9.3.4.2 Subsystem and Component Supports Analyzed or Specified by TVA 3.9-43 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 3.9-46 3.9.4.3 Design Loadings, Stress Limits, and Allowable Deformations 3.9-46 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 EQUIP-MENT 3.10-1 3.10.1 Seismic Qualification Criteria 3.10-1 3.10.2 Methods And Procedures For Qualifying Electrical Equipment And Instrumentation 3.10-6 3.10.3 Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumen-tation and Cables 3.10-6 3.10.3.1 Electrical Equipment and Instrumentation Assemblies 3.10-7 3.10.3.2 Cable Trays and Supports 3.10-7 3.10.3.2.1 Cable Trays 3.10-7 3.10.3.2.2 Supports 3.10-7 1-lvi Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 3.10.3.3 Conduit and Supports 3.10-8 3.10.3.3.1 Conduit 3.10-8 3.10.3.3.2 Supports 3.10-8 3.10.3.4 Conduit Banks 3.10-9 3.10.4 Operating License Review 3.10-9 3.10.4.1 TVA Supplied Instrumentation and Electrical Equipment 3.10-9 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT 3.11-1 3.11.1 Equipment Identification and Environmental Conditions 3.11-1 3.11.1.1 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 3.11.7.2.1 Inside Containment 3.11-5 3.11.7.2.2 Radiation - Auxiliary Building Spaces 3.11-6 4.0 REACTOR 4.1
SUMMARY
DESCRIPTION 4.1-1 4.2 MECHANICAL DESIGN 4.2-1 4.2.1 Fuel 4.2-2 4.2.1.1 Design Bases 4.2-2 4.2.1.1.1 Fuel Rods 4.2-2 4.2.1.1.2 Fuel Assembly Structure 4.2-3 4.2.1.2 Design Description 4.2-5 4.2.1.2.1 Fuel Rods4.2-6 4.2.1.2.2 Fuel Assembly Structure 4.2-6 4.2.1.3 Design Evaluation 4.2-10 4.2.1.3.1 Fuel Rods 4.2-10 4.2.1.3.2 Fuel Assembly Structure 4.2-17 4.2.1.3.3 Operational Experience 4.2-18 4.2.1.3.4 Test Rod and Test Assembly Experience 4.2-18 4.2.1.3.5 Evaluation of the Reactor Core for a Limiting LOCA Load - Accumulator Line Break 4.2-18 4.2.1.4 Tests and Inspections 4.2-19 Table of Contents 1-lvii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 4.2.1.4.1 Quality Assurance Program 4.2-19 4.2.1.4.2 Quality Control 4.2-19 4.2.1.4.3 Tests and Inspections by Others 4.2-22 4.2.1.4.4 Onsite Inspection 4.2-22 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 4.2-27 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 4.2.3.1.1 Design Stresses 4.2-29 4.2.3.1.2 Material Compatibility 4.2-29 4.2.3.1.3 Reactivity Control Components 4.2-29 4.2.3.1.4 Control Rod Drive Mechanisms 4.2-31 4.2.3.2 Design Description 4.2-32 4.2.3.2.1 Reactivity Control Components 4.2-33 4.2.3.2.2 Control Rod Drive Mechanism (CRDM) 4.2-37 4.2.3.3 Design Evaluation 4.2-42 4.2.3.3.1 Reactivity Control Components 4.2-42 4.2.3.3.2 Control Rod Drive Mechanism 4.2-48 4.2.3.4 Tests, Verification, and Inspections 4.2-51 4.2.3.4.1 Reactivity Control Components 4.2-51 4.2.3.4.2 Control Rod Drive Mechanisms 4.2-52 4.2.3.5 Instrumentation Applications 4.2-53 4.2.4 Tritium Producing Burnable Absorber Rod - Tritium Production Core 4.2-54 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 4.3-3 4.3.1.5 Shutdown Margins With Vessel Head in Place 4.3-4 4.3.1.6 Shutdown Margin for Refueling 4.3-4 4.3.1.7 Stability 4.3-5 4.3.1.8 Anticipated Transients Without Trip 4.3-5 4.3.2 Description 4.3-5 4.3.2.1 Nuclear Design Description 4.3-5 4.3.2.2 Power Distributions 4.3-7 4.3.2.2.1 Definitions 4.3-7 4.3.2.2.2 Radial Power Distributions 4.3-9 4.3.2.2.3 Assembly Power Distributions 4.3-9 1-lviii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 4.3.2.2.4 Axial Power Distribution 4.3-9 4.3.2.2.5 Limiting Power Distributions 4.3-10 4.3.2.2.6 Experimental Verification of Power Distribution Analysis 4.3-14 4.3.2.2.7 Testing 4.3-15 4.3.2.2.8 Monitoring Instrumentation 4.3-16 4.3.2.3 Reactivity Coefficients 4.3-16 4.3.2.3.1 Fuel Temperature (Doppler) Coefficient 4.3-16 4.3.2.3.2 Moderator Coefficients 4.3-17 4.3.2.3.3 Power Coefficient 4.3-18 4.3.2.3.4 Comparison of Calculated and Experimental Reactivity Coefficients 4.3-18 4.3.2.3.5 Reactivity Coefficients Used in Transient Analysis 4.3-19 4.3.2.4 Control Requirements 4.3-19 4.3.2.4.1 Doppler 4.3-20 4.3.2.4.2 Variable Average Moderator Temperature 4.3-20 4.3.2.4.3 Redistribution 4.3-20 4.3.2.4.4 Void Content 4.3-20 4.3.2.4.5 Rod Insertion Allowance 4.3-20 4.3.2.4.6 Burnup 4.3-20 4.3.2.4.7 Xenon and Samarium Concentrations 4.3-21 4.3.2.4.8 pH Effects 4.3-21 4.3.2.4.9 Experimental Confirmation 4.3-21 4.3.2.5 Control 4.3-21 4.3.2.5.1 Chemical Shim 4.3-21 4.3.2.5.2 Rod Cluster Control Assemblies 4.3-21 4.3.2.5.3 Burnable Absorbers 4.3-22 4.3.2.5.4 Peak Xenon Startup 4.3-22 4.3.2.5.5 Load Follow Control and Xenon Control 4.3-22 4.3.2.5.6 Burnup 4.3-23 4.3.2.6 Control Rod Patterns and Reactivity Worth 4.3-23 4.3.2.7 Criticality of Fuel Assemblies 4.3-24 4.3.2.8 Stability 4.3-28 4.3.2.8.1 Introduction 4.3-28 4.3.2.8.2 Stability Index 4.3-28 4.3.2.8.3 Prediction of the Core Stability 4.3-29 4.3.2.8.4 Stability Measurements 4.3-29 4.3.2.8.5 Comparison of Calculations with Measurements 4.3-31 4.3.2.8.6 Stability Control and Protection 4.3-31 4.3.2.9 Vessel Irradiation 4.3-32 4.3.3 Analytical Methods 4.3-33 4.3.3.1 Fuel Temperature (Doppler) Calculations 4.3-33 4.3.3.2 Macroscopic Group Constants 4.3-34 4.3.3.3 Spatial Few-Group Diffusion Calculations 4.3-35 Table of Contents 1-lix
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 4.4-3 4.4.1.4 Hydrodynamic Stability Design Bases 4.4-3 4.4.1.5 Other Considerations 4.4-3 4.4.2 Description 4.4-4 4.4.2.1 Summary Comparison 4.4-4 4.4.2.2 Fuel and Cladding Temperatures 4.4-4 4.4.2.2.1 UO2 Thermal Conductivity 4.4-4 4.4.2.2.2 Radial Power Distribution in UO2 Fuel Rods 4.4-5 4.4.2.2.3 Gap Conductance 4.4-6 4.4.2.2.4 Surface Heat Transfer Coefficients 4.4-6 4.4.2.2.5 Fuel Clad Temperatures 4.4-6 4.4.2.2.6 Treatment of Peaking Factors 4.4-6 4.4.2.3 Critical Heat Flux Ratio or Departure from Nucleate Boiling Ratio and Mixing Technology 4.4-7 4.4.2.3.1 Departure from Nucleate Boiling Technology 4.4-7 4.4.2.3.2 Definition of Departure from Nucleate Boiling Ratio 4.4-8 4.4.2.3.3 Mixing Technology 4.4-10 4.4.2.3.4 Hot Channel Factors 4.4-11 4.4.2.3.5 Effects of Rod Bow on DNBR 4.4-13 4.4.2.4 Flux Tilt Considerations 4.4-13 4.4.2.5 Void Fraction Distribution 4.4-14 4.4.2.6 Deleted 4.4-14 4.4.2.7 Core Pressure Drops and Hydraulic Loads 4.4-14 4.4.2.7.1 Core Pressure Drops 4.4-14 4.4.2.7.2 Hydraulic Loads 4.4-15 4.4.2.8 Correlation and Physical Data 4.4-15 4.4.2.8.1 Surface Heat Transfer Coefficients 4.4-15 4.4.2.8.2 Total Core and Vessel Pressure Drop 4.4-16 4.4.2.8.3 Void Fraction Correlation 4.4-17 4.4.2.9 Thermal Effects of Operational Transients 4.4-17 4.4.2.10 Uncertainties in Estimates 4.4-18 4.4.2.10.1 Uncertainties in Fuel and Clad Temperatures 4.4-18 4.4.2.10.2 Uncertainties in Pressure Drops 4.4-18 4.4.2.10.3 Uncertainties Due to Inlet Flow Maldistribution 4.4-19 4.4.2.10.4 Uncertainties in DNB Correlation 4.4-19 4.4.2.10.5 Uncertainties in DNBR Calculations 4.4-19 4.4.2.10.6 Uncertainties in Flow Rates 4.4-19 4.4.2.10.7 Uncertainties in Hydraulic Loads 4.4-19 4.4.2.10.8 Uncertainties in Mixing Coefficient 4.4-20 4.4.2.11 Plant Configuration Data 4.4-20 1-lx Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 4.4.3 EVALUATION 4.4-20 4.4.3.1 Core Hydraulics 4.4-20 4.4.3.1.1 Flow Paths Considered in Core Pressure Drop and Thermal Design 4.4-20 4.4.3.1.2 Inlet Flow Distributions 4.4-21 4.4.3.1.3 Empirical Friction Factor Correlations 4.4-22 4.4.3.2 Influence of Power Distribution 4.4-22 4.4.3.2.1 Nuclear Enthalpy Rise Hot Channel Factor, FNH 4.4-22 4.4.3.2.2 Axial Heat Flux Distributions 4.4-23 4.4.3.3 Core Thermal Response 4.4-24 4.4.3.4 Analytical Techniques 4.4-24 4.4.3.4.1 Core Analysis 4.4-24 4.4.3.4.2 Fuel Temperatures 4.4-26 4.4.3.4.3 Hydrodynamic Instability 4.4-26 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 4.4-31 4.4.5 Instrumentation Application 4.4-31 4.4.5.1 Incore Instrumentation 4.4-31 4.4.5.2 Overtemperature and Overpower T Instrumentation 4.4-32 4.4.5.3 Instrumentation to Limit Maximum Power Output 4.4-32 5.0 REACTOR COOLANT SYSTEM 5.1
SUMMARY
DESCRIPTION 5.1-1 5.1.1 Schematic Flow Diagram 5.1-6 5.1.2 Piping and Instrumentation Diagrams 5.1-6 5.1.3 Elevation Drawing 5.1-6 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 5.2-1 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 Table of Contents 1-lxi
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 5.2.1.10.1 Loading Conditions 5.2-15 5.2.1.10.2 Analysis of the Reactor Coolant Loop and Supports 5.2-15 5.2.1.10.3 Reactor Coolant Loop Models and Methods 5.2-17 5.2.1.10.4 Primary Component Supports Models and Methods 5.2-22 5.2.1.10.5 Analysis of Primary Components 5.2-24 5.2.1.10.6 Reactor Vessel Support L0CA Loads 5.2-26 Introduction 26 Interface Information 27 Loading Conditions 27 Reactor Vessel and Internals Modeling 28 Analytical Methods 30 Results of the Analysis 30 5.2.1.10.7 Stress Criteria for Class 1 Components and Component Supports 5.2-32 5.2.1.10.8 Computer Program Descriptions 5.2-33 5.2.1.10.9 LOCA Evaluation of the Control Rod Drive Mechanisms 5.2-34 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 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 5.2-34 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 5.2.2.4.1 System Operation 5.2-37 5.2.2.4.2 Pressure Transient Analyses 5.2-37 Evaluation of Low Temperature Overpressure Transients 37 Operating Basis Earthquake Evaluation 38 5.2.2.4.3 Administrative Procedures 5.2-38 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 1-lxii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 Temperatures 5.2-51 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 5.2.7.3.1 Containment Air Particulate Monitors and Containment Radioactive 5.2-56 5.2.7.3.2 Reactor Building Floor and Equipment Drain (RBF&ED) Sump and the 5.2-57 5.2.7.3.3 Humidity Monitors 5.2-58 5.2.7.3.4 Temperature Monitors 5.2-58 5.2.7.4 Intersystem Leakage Detection 5.2-58 5.2.7.4.1 ECCS Intersystem Leakage 5.2-58 5.2.7.4.2 Condenser Vacuum Pump Air Exhaust Monitors 5.2-60 5.2.7.4.3 Component Cooling System Liquid Effluent Monitors 5.2-61 5.2.7.4.4 Steam Generator Blowdown Liquid Effluent Monitor 5.2-62 5.2.7.5 Unidentified Leakage System Sensitivity and Response Time 5.2-62 5.2.7.5.1 Containment Air Particulate Monitors and Containment Radioactive Gas Monitors 5.2-62 5.2.7.5.2 Reactor Building Floor and Equipment Drain (RBF&ED) Pocket Sump 5.2-63 5.2.7.5.3 Humidity Monitors 5.2-63 5.2.7.5.4 Temperature Monitors 5.2-64 5.2.7.6 Seismic Capability 5.2-64 5.2.7.7 Indicators and Alarms 5.2-64 5.2.7.7.1 Radiation Monitors 5.2-64 5.2.7.7.2 RBF&ED Pocket Sump Level Monitors 5.2-64 5.2.7.7.3 Humidity Monitors 5.2-64 Table of Contents 1-lxiii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.2.7.7.4 Temperature Monitors 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 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 5.4.3.6.1 Measurement of Integrated Fast Neutron (E>l.0MeV) Flux at the Irradia-tion Samples 5.4-6 Determination of Sensor Reaction Rates 7 Corrections to Reaction Rate Data 8 Least Squares Adjustment Procedure 9 5.4.3.6.2 Calculation of Integrated Fast Neutron (E > 1.0 MeV) Flux at the Irradia-tion Samples 5.4-10 Reference Forward Calculation 11 1-lxiv Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page Cycle Specific Adjoint Calculations 11 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 5.5.1.3 Design Evaluation 5.5-3 5.5.1.3.1 Pump Performance 5.5-3 5.5.1.3.2 Coastdown Capability 5.5-4 5.5.1.3.3 Flywheel Integrity 5.5-4 5.5.1.3.4 Bearing Integrity 5.5-4 5.5.1.3.5 Locked Rotor 5.5-4 5.5.1.3.6 Critical Speed 5.5-5 5.5.1.3.7 Missile Generation 5.5-5 5.5.1.3.8 Pump Cavitation 5.5-5 5.5.1.3.9 Pump Overspeed Considerations 5.5-5 5.5.1.3.10 Anti-Reverse Rotation Device 5.5-6 5.5.1.3.11 Shaft Seal Leakage 5.5-6 5.5.1.3.12 Seal Discharge Piping 5.5-6 5.5.1.3.13 Spool Piece 5.5-7 5.5.1.3.14 Motor Air Coolers 5.5-7 5.5.1.3.15 Discharge Nozzle Weir 5.5-7 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 5.5.2.3.1 Forced Convection 5.5-9 5.5.2.3.2 Natural Circulation Flow 5.5-9 5.5.2.3.3 Tube and Tubesheet Stress Analyses 5.5-10 5.5.2.3.4 Corrosion 5.5-10 5.5.2.3.5 Compatibility of Steam Generator Tubing with Primary and 5.5-10 5.5.2.3.6 Flow Induced Vibration 5.5-12 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 Table of Contents 1-lxv
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.5.3.3.1 Material Corrosion/Erosion Evaluation 5.5-18 5.5.3.3.2 Sensitized Stainless Steel 5.5-19 5.5.3.3.3 Contaminant Control 5.5-19 5.5.3.4 Tests and Inspections 5.5-19 5.5.4 Steam Outlet Flow Restrictor (Steam Generator) 5.5-19 5.5.4.1 Design Basis 5.5-19 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 5.5.6.2.1 Component Description 5.5-22 5.5.6.2.2 System Operation 5.5-22 5.5.6.3 Design Evaluation 5.5-22 5.5.6.3.1 System Availability and Reliability 5.5-22 5.5.6.3.2 Leakage Provisions 5.5-23 5.5.6.3.3 Pipe Rupture Provisions 5.5-23 5.5.6.3.4 Radiological Considerations 5.5-23 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 5.5.7.2.1 Component Description 5.5-25 5.5.7.2.2 System Operation 5.5-27 5.5.7.3 Design Evaluation 5.5-28 5.5.7.3.1 System Availability and Reliability 5.5-28 5.5.7.3.2 Leakage Provisions and Activity Release 5.5-29 5.5.7.3.3 Overpressurization Protection 5.5-29 5.5.7.3.4 Prevention of Exposure of the Residual Heat Removal System to Normal Reactor Coolant System Operating Pressure 5.5-30 5.5.7.3.5 Shared Function 5.5-30 5.5.7.3.6 Radiological Consideration 5.5-31 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 5.5.10.1.1 Pressurizer Surge Line 5.5-32 5.5.10.1.2 Pressurizer Volume 5.5-32 5.5.10.2 Design Description 5.5-33 5.5.10.2.1 Pressurizer Surge Line 5.5-33 5.5.10.2.2 Pressurizer Vessel 5.5-33 5.5.10.3 Design Evaluation 5.5-34 1-lxvi Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 5.5.10.3.1 System Pressure 5.5-34 5.5.10.3.2 Pressurizer Performance 5.5-34 5.5.10.3.3 Pressure Setpoints 5.5-35 5.5.10.3.4 Pressurizer Spray 5.5-35 5.5.10.3.5 Pressurizer Design Analysis 5.5-35 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 5.5.11.2.1 Pressurizer Relief Tank Pressure 5.5-38 5.5.11.2.2 Pressurizer Relief Tank Level 5.5-38 5.5.11.2.3 Pressurizer Relief Tank Water Temperature 5.5-38 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 5.5-40 5.5.13 Safety and Relief Valves 5.5-40 5.5.13.1 Design Bases 5.5-40 5.5.13.2 Design Description 5.5-40 5.5.13.3 Design Evaluation 5.5-41 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 5.5-42 5.5.14.3 Evaluation 5.5-43 5.5.14.4 Tests and Inspections 5.5-44 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 Table of Contents 1-lxvii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 6.2.1 Containment Functional Design 6.2-1 6.2.1.1 Design Bases 6.2-1 6.2.1.1.1 Primary Containment Design Bases 6.2-1 6.2.1.2 Primary Containment System Design 6.2-3 6.2.1.3 Design Evaluation 6.2-3 6.2.1.3.1 Primary Containment Evaluation 6.2-3 6.2.1.3.2 General Description of Containment Pressure Analysis 6.2-4 6.2.1.3.3 Long-Term Containment Pressure Analysis 6.2-4 6.2.1.3.4 Short-Term Blowdown Analysis 6.2-8 6.2.1.3.5 Effect of Steam Bypass 6.2-17 6.2.1.3.6 Mass and Energy Release Data 6.2-20 6.2.1.3.7 Accident Chronology 6.2-24 6.2.1.3.8 Energy Balance Tables 6.2-24 6.2.1.3.9 Containment Pressure Differentials 6.2-25 6.2.1.3.10 Steam Line Break Inside Containment 6.2-27 6.2.1.3.11 Maximum Reverse Pressure Differentials 6.2-33 6.2.2 CONTAINMENT HEAT REMOVAL SYSTEMS 6.2-1 6.2.2.1 Design Bases 6.2-1 6.2.2.2 System Design 6.2-3 6.2.2.3 Design Evaluation 6.2-5 6.2.2.4 Testing and Inspections 6.2-7 6.2.2.5 Instrumentation Requirements 6.2-8 6.2.2.6 Materials 6.2-8 6.2.3 Secondary Containment Functional Design 6.2-1 6.2.3.1 Design Bases 6.2-1 6.2.3.1.1 Secondary Containment Enclosures 6.2-1 6.2.3.1.2 Emergency Gas Treatment System (EGTS) 6.2-1 6.2.3.1.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2-2 6.2.3.2 System Design 6.2-2 6.2.3.2.1 Secondary Containment Enclosures 6.2-2 6.2.3.2.2 Emergency Gas Treatment System (EGTS) 6.2-7 6.2.3.2.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2-10 6.2.3.3 Design Evaluation 6.2-12 1-lxviii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.2.3.3.1 Secondary Containment Enclosures 6.2-12 6.2.3.3.2 Emergency Gas Treatment System (EGTS) 6.2-15 6.2.3.3.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2-19 6.2.3.4 Test and Inspections 6.2-21 6.2.3.4.1 Emergency Gas Treatment System (EGTS) 6.2-21 6.2.3.4.2 Auxiliary Building Gas Treatment System (ABGTS) 6.2-22 6.2.3.5 Instrumentation Requirements 6.2-23 6.2.3.5.1 Emergency Gas Treatment System (EGTS) 6.2-23 6.2.3.5.2 Auxiliary Building Gas Treatment System (ABGTS) 6.2-23 6.2.4 Containment Isolation Systems 6.2-1 6.2.4.1 Design Bases 6.2-1 6.2.4.2 System Design 6.2-4 6.2.4.2.1 Design Requirements 6.2-5 6.2.4.2.2 Containment Isolation Operation 6.2-5 6.2.4.2.3 Penetration Design 6.2-6 6.2.4.3 Design Evaluation 6.2-12 6.2.4.3.1 Possible Leakage Paths 6.2-14 6.2.4.4 Tests and Inspections 6.2-16 6.2.5 Combustible Gas Control in Containment 6.2-1 6.2.5.1 The containment combustible gas control system is designed to control the concen-tration of hydrogen that may be released into the containment following a beyond-design-basis ac-cident to ensure that containment structural integrity is maintained. The combustible gas control system of the containment air return system, the hydrogen analyzer system (HAS) and the hydro-gen mitigation system (HMS) which conform to 10CFR50.44 requirements.Design Bases 6.2-1 6.2.5.2 System Design 6.2-2 6.2.5.3 Design Evaluation 6.2-4 6.2.5.4 Testing and Inspections 6.2-5 6.2.5.5 Instrumentation Application 6.2-5 6.2.6 Containment Leakage Testing 6.2-1 6.2.6.1 Containment Integrated Leak Rate Test 6.2-1 6.2.6.2 Containment Penetration Leakage Rate Test 6.2-2 6.2.6.3 Scheduling and Reporting of Periodic Tests 6.2-6 6.2.6.4 Special Testing Requirements 6.2-6 6.3 EMERGENCY CORE COOLING SYSTEM 6.3-1 6.3.1 Design Bases 6.3-1 6.3.1.1 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 Table of Contents 1-lxix
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.3.2.2 Equipment and Component Design 6.3-2 6.3.2.3 Applicable Codes and Classifications 6.3-15 6.3.2.4 Materials Specifications and Compatibility 6.3-15 6.3.2.5 Design Pressures and Temperatures 6.3-16 6.3.2.6 Coolant Quantity 6.3-16 6.3.2.7 Pump Characteristics 6.3-16 6.3.2.8 Heat Exchanger Characteristics 6.3-16 6.3.2.9 ECCS Flow Diagrams 6.3-17 6.3.2.10 Relief Valves 6.3-17 6.3.2.11 System Reliability 6.3-17 6.3.2.11.1 Definitions 6.3-17 6.3.2.11.2 Active and Passive Failure Criteria 6.3-18 6.3.2.11.3 Subsequent Leakage from Components in Safeguards Systems 6.3-19 6.3.2.12 Protection Provisions 6.3-21 6.3.2.13 Provisions for Performance Testing 6.3-22 6.3.2.14 Net Positive Suction Head 6.3-22 6.3.2.15 Control of Motor-Operated Isolation Valves 6.3-22 6.3.2.16 Motor-Operated Valves and Controls 6.3-23 6.3.2.17 Manual Actions 6.3-23 6.3.2.18 Process Instrumentation 6.3-23 6.3.2.19 Materials 6.3-23 6.3.3 Performance Evaluation 6.3-23 6.3.3.1 Evaluation Model 6.3-23 6.3.3.2 ECCS Performance 6.3-24 6.3.3.3 Alternate Analysis Methods 6.3-24 6.3.3.4 Fuel Rod Perforations 6.3-25 6.3.3.5 Effects of ECCS Operation on the Core 6.3-25 6.3.3.6 Use of Dual Function Components 6.3-25 6.3.3.7 Lag Times 6.3-27 6.3.3.8 Thermal Shock Considerations 6.3-27 6.3.3.9 Limits on System Parameters 6.3-27 6.3.3.10 Use of RHR Spray 6.3-27 6.3.4 Tests and Inspections 6.3-28 6.3.4.1 Preoperational Tests (Historical Information - Not Updated) 6.3-28 6.3.4.2 Component Testing 6.3-29 6.3.4.3 Periodic System Testing 6.3-29 6.3.5 Instrumentation Application 6.3-30 6.3.5.1 Temperature Indication 6.3-30 6.3.5.2 Pressure Indication 6.3-30 6.3.5.3 Flow Indication 6.3-30 6.3.5.4 Level Indication 6.3-31 6.3.5.5 Valve Position Indication 6.3-32 1-lxx Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.4 HABITABILITY SYSTEMS 6.4-1 6.4.1 Design Bases 6.4-1 6.4.2 System Design 6.4-1 6.4.2.1 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 6.4.2.4.1 Other Ventilation Zones 6.4-3 6.4.2.4.2 Pressure-Containing Equipment 6.4-4 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 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 6.5.1.1.1 Emergency Gas Treatment System Air Cleanup Units 6.5-1 6.5.1.1.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-1 6.5.1.1.3 Reactor Building Purge Air System Air Cleanup Units 6.5-1 6.5.1.1.4 Main Control Room Emergency Air Cleanup Units 6.5-2 6.5.1.2 System Design 6.5-2 6.5.1.2.1 Emergency Gas Treatment System Air Cleanup Units 6.5-2 6.5.1.2.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-3 6.5.1.2.3 Reactor Building Purge System Air Cleanup Units 6.5-4 6.5.1.2.4 Main Control Room Emergency Air Cleanup Units 6.5-4 6.5.1.3 Design Evaluation 6.5-5 6.5.1.3.1 Emergency Gas Treatment System Air Cleanup Units 6.5-5 6.5.1.3.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-5 6.5.1.3.3 Reactor Building Purge System Air Cleanup Units 6.5-5 6.5.1.3.4 Main Control Room Emergency Air Cleanup Units 6.5-5 6.5.1.4 Tests and Inspections 6.5-5 6.5.1.4.1 Emergency Gas Treatment System Air Cleanup Units 6.5-5 6.5.1.4.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-6 6.5.1.4.3 Reactor Building Purge System Air Cleanup Units 6.5-6 6.5.1.4.4 Main Control Room Emergency Air Cleanup Units 6.5-6 6.5.1.5 Instrumentation Requirements 6.5-6 6.5.1.5.1 Emergency Gas Treatment System Air Cleanup Units 6.5-6 6.5.1.5.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-6 Table of Contents 1-lxxi
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 6.5.1.5.3 Reactor Building Purge System Air Cleanup Units 6.5-7 6.5.1.5.4 Main Control Room Emergency Air Cleanup Units 6.5-7 6.5.1.6 Materials 6.5-7 6.5.1.6.1 Emergency Gas Treatment System Air Cleanup Units 6.5-7 6.5.1.6.2 Auxiliary Building Gas Treatment System Air Cleanup Units 6.5-7 6.5.1.6.3 Reactor Building Purge System Air Cleanup Units 6.5-7 6.5.1.6.4 Main Control Room Emergency Air Cleanup Units 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 6.5.4.2.1 Component Description 6.5-11 6.5.4.2.2 System Operation 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 6.5.4.4.1 Ice Condenser System Instrumentation 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 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 1-lxxii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 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 Table of Contents 1-lxxiii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 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 7.1.1.1.1 Reactor Trip System 7.1-4 7.1.1.1.2 Engineered Safety Features Actuation System 7.1-4 7.1.1.1.3 Vital Instrumentation and Control Power Supply System 7.1-4 7.1.1.1.4 Auxiliary Control Air System 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 7.1.1.4 Plant Comparison 7.1-5 1-lxxiv Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.1.2 Identification of Safety Criteria 7.1-5 7.1.2.1 Design Bases 7.1-8 7.1.2.1.1 Reactor Trip System 7.1-8 7.1.2.1.2 Engineered Safety Features Actuation System (ESFAS) 7.1-9 7.1.2.1.3 Vital Control Power Supply System 7.1-10 7.1.2.1.4 Standby Power 7.1-10 7.1.2.1.5 Interlocks 7.1-10 7.1.2.1.6 Bypasses 7.1-10 7.1.2.1.7 Equipment Protection 7.1-10 7.1.2.1.8 Diversity 7.1-11 7.1.2.1.9 Trip Setpoints 7.1-11 7.1.2.2 Independence of Redundant Safety-Related Systems 7.1-11 7.1.2.2.1 General 7.1-12 7.1.2.2.2 Specific Systems 7.1-12 7.1.2.2.3 Fire Protection 7.1-14 7.1.2.3 Physical Identification of Safety-Related Equipment 7.1-14 7.1.2.4 Process Signal Isolation Relays 7.1-16 7.2 REACTOR TRIP SYSTEM 7.2-1 7.2.1 Description 7.2-1 7.2.1.1 System Description 7.2-1 7.2.1.1.1 Functional Performance Requirements 7.2-2 7.2.1.1.2 Reactor Trips 7.2-2 7.2.1.1.3 Reactor Trip System Interlocks 7.2-10 7.2.1.1.4 Reactor Coolant Temperature Sensor Arrangement and Calculational Methodology 7.2-12 7.2.1.1.5 Pressurizer Water Level Reference Leg Arrangement 7.2-15 7.2.1.1.6 Process Protection System 7.2-15 7.2.1.1.7 Solid State Logic Protection System 7.2-15 7.2.1.1.8 Isolation Devices 7.2-16 7.2.1.1.9 Energy Supply and Environmental Variations 7.2-16 7.2.1.1.10 Setpoints 7.2-16 7.2.1.1.11 Seismic Design 7.2-16 7.2.1.2 Design Bases Information 7.2-16 7.2.1.2.1 Generating Station Conditions 7.2-16 7.2.1.2.2 Generating Station Variables 7.2-17 7.2.1.2.3 Spatially Dependent Variables 7.2-17 7.2.1.2.4 Limits, Margins and Levels 7.2-17 7.2.1.2.5 Abnormal Events 7.2-18 7.2.1.2.6 Minimum Performance Requirements 7.2-18 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 7.2.2.1.1 Trip Setpoint Discussion 7.2-20 Table of Contents 1-lxxv
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.2.2.1.2 Reactor Coolant Flow Measurement 7.2-22 7.2.2.2 Evaluation of Compliance to Applicable Codes and Standards 7.2-22 7.2.2.3 Specific Control and Protection Interactions 7.2-32 7.2.2.3.1 Neutron Flux 7.2-32 7.2.2.3.2 Reactor Coolant Temperature 7.2-32 7.2.2.3.3 Pressurizer Pressure 7.2-33 7.2.2.3.4 Pressurizer Water Level 7.2-34 7.2.2.3.5 Steam Generator Water Level 7.2-34 7.2.2.4 Additional Postulated Accidents 7.2-35 7.2.3 Tests and Inspections 7.2-35 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 7.3.1.1.1 Function Initiation 7.3-2 7.3.1.1.2 Process Protection Circuitry 7.3-3 7.3.1.1.3 Logic Circuitry 7.3-4 7.3.1.1.4 Final Actuation Circuitry 7.3-4 7.3.1.1.5 Support Systems 7.3-5 7.3.1.2 Design Bases Information 7.3-6 7.3.1.2.1 Generating Station Conditions 7.3-6 7.3.1.2.2 Generating Station Variables 7.3-6 7.3.1.2.3 Spatially Dependent Variables 7.3-6 7.3.1.2.4 Limits, Margin and Levels 7.3-6 7.3.1.2.5 Abnormal Events 7.3-7 7.3.1.2.6 Minimum Performance Requirements 7.3-7 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 7.3-8 7.3.2.2.1 Single Failure Criterion 7.3-9 7.3.2.2.2 Equipment Qualification 7.3-9 7.3.2.2.3 Channel Independence 7.3-9 7.3.2.2.4 Control and Protection System Interaction 7.3-9 7.3.2.2.5 Capability for Sensor Checks and Equipment Test and Calibration 7.3-9 7.3.2.2.6 Manual Initiation, Reset and Blocks of Protective Actions7.3-15 7.3.2.3 Further Considerations 7.3-15 7.3.2.4 Summary 7.3-16 7.3.2.4.1 Loss-of-Coolant Protection 7.3-16 7.3.2.4.2 Steam Line Break Protection 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 1-lxxvi Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.4.1.2 Controls 7.4-2 7.4.1.2.1 General Considerations 7.4-2 7.4.1.2.2 Pumps and Fans 7.4-3 7.4.1.2.3 Diesel Generators 7.4-4 7.4.1.2.4 Valves and Heaters 7.4-4 7.4.1.3 Equipment and Systems Available for Cold Shutdown 7.4-5 7.4.2 Analysis 7.4-5 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 7.5.1.4.1 Definitions 7.5-3 7.5.1.4.2 Selection Criteria 7.5-3 7.5.1.4.3 Design Criteria For Category 1 Variables 7.5-4 7.5.1.4.4 Design Criteria For Category 2 Variables 7.5-5 7.5.1.4.5 Design Criteria For Category 3 Variables 7.5-5 7.5.1.5 General Requirements 7.5-6 7.5.1.5.1 Display Requirements 7.5-6 7.5.1.5.2 Identification 7.5-6 7.5.1.6 Analysis 7.5-7 7.5.1.7 Tests and Inspections 7.5-7 7.5.1.7.1 Programs 7.5-7 7.5.1.7.2 Removal of Channels from Service 7.5-8 7.5.1.7.3 Administrative Control 7.5-8 7.5.2 Plant Computer System 7.5-8 7.5.2.1 Safety Parameter Display System 7.5-8 7.5.2.1.1 System Description 7.5-8 7.5.2.1.2 Design Bases 7.5-9 7.5.2.2 Bypassed and Inoperable Status Indication System (BISI) 7.5-11 7.5.2.3 Technical Support Center and Nuclear Data Links 7.5-13 7.5.2.3.1 Technical Support Center 7.5-13 7.5.2.3.2 Communication 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 Table of Contents 1-lxxvii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 7.6-8 7.6.8.1 Analysis of Interlock 7.6-9 7.6.9 Switchover From Injection to Recirculation Mode Following a LOCA 7.6-10 7.7 CONTROL SYSTEMS 7.7-1 7.7.1 Description 7.7-1 7.7.1.1 Control Rod Drive Reactor Control System 7.7-1 7.7.1.1.1 Reactor Control Input Signals 7.7-1 7.7.1.1.2 Rod Speed Control Program 7.7-3 7.7.1.2 Rod Control System 7.7-3 7.7.1.2.1 Rod Control System Function 7.7-3 7.7.1.2.2 Rod Control System Failures 7.7-5 7.7.1.3 Plant Control Signals for Monitoring and Indicating 7.7-9 7.7.1.3.1 Monitoring Functions Provided by the Nuclear Instrumentation System 7.7-9 7.7.1.3.2 Main Control Room Rod Position Indication 7.7-10 7.7.1.3.3 Control Bank Rod Insertion Monitoring 7.7-12 7.7.1.3.4 Rod Deviation Alarm 7.7-14 7.7.1.3.5 Rods At Bottom 7.7-14 7.7.1.3.6 Bypassed and Inoperable Status Indication System (BISI) 7.7-14 7.7.1.4 Plant Control System Interlocks 7.7-14 7.7.1.4.1 Rod Stops 7.7-14 7.7.1.4.2 Automatic Turbine Load Runback 7.7-15 7.7.1.5 Pressurizer Pressure Control 7.7-15 7.7.1.6 Pressurizer Water Level Control 7.7-16 7.7.1.7 Steam Generator Water Level Control 7.7-16 7.7.1.8 Steam Dump Control 7.7-17 7.7.1.8.1 Load Rejection Steam Dump Controller 7.7-17 7.7.1.8.2 Plant Trip Steam Dump Controller 7.7-18 7.7.1.8.3 Steam Header Pressure Controller 7.7-18 7.7.1.9 Incore Instrumentation System 7.7-18 7.7.1.9.1 Thermocouples 7.7-18 7.7.1.9.2 Incore Instrumentation System 7.7-19 7.7.1.9.3 Incore Instrumentation System Neutron Signal Processing 7.7-19 7.7.1.10 Control Board 7.7-19 7.7.1.11 Deleted 7.7-20 7.7.1.12 Anticipated Transient Without Scram Mitigation System Actuation 7.7-20 7.7.2 Analysis 7.7-21 7.7.2.1 Separation of Protection and Control System 7.7-22 7.7.2.2 Response Considerations of Reactivity 7.7-22 7.7.2.3 Step Load Changes Without Steam Dump 7.7-24 7.7.2.4 Loading and Unloading 7.7-25 1-lxxviii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 7.7.2.5 Load Rejection Furnished By Steam Dump System 7.7-25 7.7.2.6 Turbine-Generator Trip With Reactor Trip 7.7-26 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.1.2.1.1 Instruments Common to Multiple Process Systems 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 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 8.1-2 8.1.5 Design Criteria and Standards 8.1-4 8.1.5.1 Design Criteria 8.1-4 8.1.5.2 Other Standards and Guides 8.1-4 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 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 Table of Contents 1-lxxix
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 8.3-26 8.3.1.2.1 Standby AC Power Systems 8.3-26 8.3.1.2.2 Analysis of Vital 120V AC Control Power Systems AC Distribution Boards and Inverters 8.3-29 8.3.1.2.3 Safety-Related Equipment in a LOCA Environment 8.3-32 8.3.1.3 Physical Identification of Safety-Related Equipment in AC Power Systems 8.3-36 8.3.1.4 Independence of Redundant ac Power Systems 8.3-37 8.3.1.4.1 Cable Derating and Raceway Fill 8.3-38 8.3.1.4.2 Cable Routing and Separation Criteria 8.3-38 8.3.1.4.3 Sharing of Cable Trays and Routing of Non-Safety Related Cables8.3-46 8.3.1.4.4 Fire Detection and Protection in Areas Where Cables are Installed 8.3-50 8.3.1.4.5 Cable and Cable Tray Markings 8.3-51 8.3.1.4.6 Spacing of Power and Control Wiring and Components Comprising the Class 1E Electrical Systems in Control Boards, Panels, and Relay Racks 8.3-52 8.3.1.4.7 Fire Barriers and Separation Between Redundant Trays 8.3-53 8.3.2 DC Power System 8.3-53 8.3.2.1 Description 8.3-53 8.3.2.1.1 Vital 125V dc Control Power System 8.3-53 8.3.2.1.2 Non-Safety-Related DC Power Systems 8.3-60 8.3.2.2 Analysis of Vital 125V DC Control Power Supply System 8.3-61 8.3.2.3 Physical Identification of Safety-Related Equipment in dc Power Systems 8.3-66 8.3.2.4 Independence of Redundant DC Power Systems 8.3-66 8.3.3 Fire Protection for Cable Systems 8.3-67 8A Analysis of Submerged Electrical Equipment (During Post LOCA) Powered from Auxiliary Power System 8-1 8B Analysis of Submerged Electrical Equipment (During Post LOCA) Powered from In-strumentation and Control Power System 8-3 8C Deleted by Amendment 75 8-5 8D IEEE STD 387-1984 FOR DIESEL-GENERATING UNITS APPLIED AS STANDBY POWER 8-6 1-lxxx Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 8E Probability/Reliability Analysis of Protection Device Schemes for Associated and Non-Class 1E Cables 8-8 9.0 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 9.1-1 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 9.1.3.1.1 Spent Fuel Pool Cooling 9.1-4 9.1.3.1.2 Spent Fuel Pool Dewatering Protection 9.1-5 9.1.3.1.3 Water Purification 9.1-5 9.1.3.1.4 Flood Mode Cooling 9.1-5 9.1.3.2 System Description 9.1-5 9.1.3.2.1 Component Description 9.1-7 9.1.3.3 Safety Evaluation 9.1-8 9.1.3.3.1 Availability and Reliability 9.1-8 9.1.3.3.2 Spent Fuel Pool Dewatering 9.1-9 9.1.3.3.3 Pool and Fuel Temperatures 9.1-9 9.1.3.3.4 Water Quality 9.1-11 9.1.3.3.5 Leakage Detection for the Spent Fuel Pool 9.1-11 9.1.3.4 Tests and Inspections 9.1-11 9.1.3.5 Instrument Application 9.1-11 9.1.3.5.1 Temperature 9.1-11 9.1.3.5.2 Pressure 9.1-12 9.1.3.5.3 Flow 9.1-12 9.1.3.5.4 Level 9.1-12 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 9.1.4.2.1 Refueling Procedure 9.1-14 9.1.4.2.2 Component Description 9.1-17 9.1.4.3 Design Evaluation 9.1-20 9.1.4.3.1 Safe Handling 9.1-20 9.1.4.3.2 Seismic Considerations 9.1-25 9.1.4.3.3 Containment Pressure Boundary Integrity 9.1-26 Table of Contents 1-lxxxi
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.1.4.3.4 Radiation Shielding 9.1-26 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 9.2.1.4 Tests and Inspections 9.2-7 9.2.1.5 Instrument Applications 9.2-7 9.2.1.5.1 General Description 9.2-7 9.2.1.5.2 Pressure Instrumentation 9.2-7 9.2.1.5.3 Flow Instrumentation 9.2-8 9.2.1.5.4 Temperature Instrumentation 9.2-8 9.2.1.5.5 Deleted by Amendment 87 9.2-8 9.2.1.5.6 Control Valves 9.2-8 9.2.1.6 Corrosion, Organic Fouling, and Environmental Qualification 9.2-9 9.2.1.7 Design Codes 9.2-10 9.2.2 Component Cooling System (CCS) 9.2-10 9.2.2.1 Design Bases 9.2-10 9.2.2.2 System Description 9.2-12 9.2.2.3 Components 9.2-15 9.2.2.3.1 Component Cooling Heat Exchangers 9.2-15 9.2.2.3.2 Component Cooling Pumps 9.2-15 9.2.2.3.3 Thermal Barrier Booster Pumps 9.2-16 9.2.2.3.4 Component Cooling Surge Tanks 9.2-16 9.2.2.3.5 Seal Leakage Return Unit 9.2-16 9.2.2.3.6 Valves 9.2-16 9.2.2.3.7 Piping 9.2-17 9.2.2.4 Safety Evaluation 9.2-18 9.2.2.5 Leakage Provisions 9.2-18 9.2.2.6 Incidental Control 9.2-19 9.2.2.7 Instrument Applications 9.2-19 9.2.2.7.1 General Description 9.2-19 9.2.2.7.2 Flow Instrumentation 9.2-20 9.2.2.7.3 Level Instrumentation 9.2-20 9.2.2.7.4 Pressure Instrumentation 9.2-20 9.2.2.7.5 Temperature Instrumentation 9.2-20 9.2.2.7.6 Valves 9.2-21 9.2.2.7.7 Conclusion 9.2-21 9.2.2.8 Malfunction Analysis 9.2-21 9.2.2.9 Tests and Inspections - Historical Information 9.2-21 9.2.2.10 Codes and Classification 9.2-22 9.2.3 Demineralized Water Makeup System 9.2-22 1-lxxxii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.2.3.1 Design Bases 9.2-22 9.2.3.2 System Description 9.2-22 9.2.3.3 Safety Evaluation 9.2-23 9.2.3.4 Test and Inspection 9.2-23 9.2.3.5 Instrumentation Applications 9.2-23 9.2.4 Potable and Sanitary Water Systems 9.2-24 9.2.4.1 Potable Water System 9.2-24 9.2.4.1.1 System Description 9.2-24 9.2.4.1.2 Safety Evaluation 9.2-24 9.2.4.1.3 Tests and Inspections 9.2-25 9.2.4.1.4 Instrumentation Applications 9.2-25 9.2.4.2 Sanitary Water System 9.2-25 9.2.4.2.1 Design Bases 9.2-25 9.2.4.2.2 System Description 9.2-25 9.2.4.2.3 Safety Evaluation 9.2-26 9.2.4.2.4 Tests And Inspections 9.2-27 9.2.4.2.5 Instrumentation Applications 9.2-28 9.2.5 Ultimate Heat Sink 9.2-28 9.2.5.1 General Description 9.2-28 9.2.5.2 Design Bases 9.2-29 9.2.5.3 Safety Evaluation 9.2-29 9.2.5.4 Instrumentation Application 9.2-31 9.2.6 Condensate Storage Facilities 9.2-31 9.2.6.1 Design Bases 9.2-31 9.2.6.2 System Description 9.2-32 9.2.6.3 Safety Evaluation 9.2-32 9.2.6.4 Test and Inspections 9.2-33 9.2.6.5 Instrument Applications 9.2-33 9.2.7 Refueling Water Storage Tank 9.2-34 9.2.7.1 ECCS Pumps Net Positive Suction Head (NPSH) 9.2-35 9.2.8 Raw Cooling Water System 9.2-37 9.2.8.1 Design Bases 9.2-37 9.2.8.2 System Description 9.2-38 9.2.8.3 Safety Evaluation 9.2-40 9.2.8.4 Tests and Inspection 9.2-41 9.3 PROCESS AUXILIARIES 9.3-1 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 Table of Contents 1-lxxxiii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 9.3.2.6.1 System Description 9.3-9 9.3.2.6.2 Postaccident Sampling Facility 9.3-9 9.3.2.6.3 Sampling Equipment 9.3-9 Liquid Sampling Panel 10 Chemical Analysis Panel 10 Containment Air Sampling Panel (CASP) 10 HRSS Control Panels 11 9.3.2.6.4 Sample Points 9.3-11 9.3.2.6.5 Postaccident Counting Facilities 9.3-11 9.3.2.6.6 Piping, Tubing, and Valves 9.3-11 9.3.2.6.7 Safety Evaluation 9.3-12 9.3.2.6.8 Tests and Inspections 9.3-12 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 9.3.3.2.1 Drains from Lowest Floor Level in the Auxiliary Building 9.3-13 9.3.3.2.2 Residual Heat Removal Pump (RHR) and Containment Spray Pump (CSP) Compartments 9.3-13 9.3.3.2.3 CVCS Holdup Tank Compartment and Tritiated Drain Collector Tank Room 9.3-14 9.3.3.2.4 Volume Control Tanks 9.3-14 9.3.3.2.5 Boric Acid Tanks 9.3-14 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 9.3.4.1.1 Reactivity Control 9.3-16 9.3.4.1.2 Regulation of Reactor Coolant Inventory 9.3-17 9.3.4.1.3 Reactor Coolant Purification 9.3-17 9.3.4.1.4 Chemical Additions for Corrosion Control 9.3-17 9.3.4.1.5 Seal Water Injection 9.3-17 9.3.4.1.6 Hydrostatic Testing of the Reactor Coolant System 9.3-17 9.3.4.1.7 Emergency Core Cooling 9.3-18 9.3.4.2 System Description 9.3-18 9.3.4.2.1 Charging, Letdown, and Seal Water System 9.3-18 1-lxxxiv Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.3.4.2.2 Chemical Control, Purification and Makeup System 9.3-20 9.3.4.2.3 Chemical Shim and Reactor Coolant Makeup 9.3-21 9.3.4.2.4 Component Description 9.3-24 9.3.4.2.5 System Operation 9.3-32 9.3.4.3 Safety Evaluation 9.3-36 9.3.4.3.1 Reactivity Control 9.3-36 9.3.4.3.2 Reactor Coolant Purification 9.3-37 9.3.4.3.3 Seal Water Injection 9.3-37 9.3.4.3.4 Hydrostatic Testing of the Reactor Coolant System 9.3-38 9.3.4.3.5 Leakage Provisions 9.3-38 9.3.4.3.6 Ability to Meet the Safeguards Function 9.3-38 9.3.4.4 Tests and Inspections 9.3-38 9.3.4.5 Instrumentation Application 9.3-38 9.3.5 Failed Fuel Detection System 9.3-39 9.3.6 Auxiliary Charging System 9.3-39 9.3.6.1 Design Bases 9.3-39 9.3.6.2 System Design Description 9.3-40 9.3.6.3 Design Evaluation 9.3-41 9.3.6.4 Tests and Inspection 9.3-41 9.3.6.5 Instrument Application 9.3-41 9.3.7 Boron Recycle System 9.3-41 9.3.8 Heat Tracing 9.3-41 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 9.4.3.2.1 Building Air Supply and Exhaust Systems (General Ventilation) 9.4-13 9.4.3.2.2 Building Cooling System (Chilled Water) 9.4-14 9.4.3.2.3 Safety Feature Equipment Coolers 9.4-15 9.4.3.2.4 Shutdown Board Room Air-Conditioning System 9.4-15 9.4.3.2.5 Auxiliary Board Rooms Air-Conditioning Systems 9.4-16 9.4.3.2.6 Shutdown Transformer Room Ventilating Systems 9.4-17 9.4.3.2.7 Miscellaneous Ventilation and Air Conditioning Systems 9.4-18 Table of Contents 1-lxxxv
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.4.3.3 Safety Evaluation 9.4-19 9.4.3.3.1 General Ventilation System 9.4-19 9.4.3.3.2 Building Cooling System 9.4-20 9.4.3.3.3 Safety Feature Equipment Coolers 9.4-20 9.4.3.3.4 Shutdown Board Room Air-Conditioning System 9.4-20 9.4.3.3.5 Auxiliary Board Rooms Air-Conditioning System 9.4-21 9.4.3.3.6 Shutdown Transformer Room Ventilating System 9.4-22 9.4.3.3.7 Miscellaneous Ventilation and Air-Conditioning System 9.4-23 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 9.4.4.2.1 Elevation 755.0 Ventilation 9.4-24 9.4.4.2.2 Elevation 729.0 and Elevation 708.0 Ventilation 9.4-24 9.4.4.2.3 El. 685.5 Ventilation 9.4-24 9.4.4.2.4 Cold Weather Building Pressurization 9.4-25 9.4.4.2.5 Miscellaneous Ventilating Systems 9.4-25 9.4.4.2.6 Coolers 9.4-25 Space Coolers 25 Pump Coolers 26 9.4.4.2.7 Building Heating System 9.4-26 9.4.4.3 Safety Evaluation 9.4-26 9.4.4.4 Inspection and Testing Requirements 9.4-27 9.4.5 Engineered Safety Feature Ventilation Systems 9.4-27 9.4.5.1 ERCW Intake Pumping Station 9.4-27 9.4.5.1.1 Design Bases 9.4-27 9.4.5.1.2 System Description 9.4-28 9.4.5.1.3 Safety Evaluation 9.4-28 9.4.5.1.4 Inspection and Testing Requirements 9.4-29 9.4.5.2 Diesel Generator Buildings 9.4-29 9.4.5.2.1 Diesel Generator Building 9.4-29 Design Bases 29 System Description 31 Safety Evaluation 32 Tests and Inspections 33 9.4.5.2.2 Additional Diesel Generator Building (Not required Unit 1 operation) 9.4-33 Design Bases 33 System Description 34 Safety Evaluation 35 Tests and Inspections 36 9.4.5.3 Auxiliary Building Safety Features Equipment Coolers 9.4-36 9.4.5.3.1 Design Bases 9.4-36 9.4.5.3.2 System Description 9.4-38 1-lxxxvi Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.4.5.3.3 Safety Evaluation 9.4-38 9.4.5.3.4 Inspection and Testing Requirements 9.4-40 9.4.6 Reactor Building Purge Ventilating System 9.4-40 9.4.6.1 Design Bases 9.4-40 9.4.6.2 System Description 9.4-42 9.4.6.3 Safety Evaluation 9.4-44 9.4.6.4 Inspection and Testing Requirements 9.4-45 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 9.4.7.2.1 Lower Compartment Air Cooling System 9.4-46 9.4.7.2.2 Control Rod Drive Mechanisms Air Cooling System 9.4-47 9.4.7.2.3 Upper Compartment Air Cooling System 9.4-47 9.4.7.2.4 Reactor Building Instrument Room Air Cooling System 9.4-48 9.4.7.2.5 Controls and Instrumentation 9.4-48 9.4.7.3 Safety Evaluation 9.4-48 9.4.7.4 Test and Inspection Requirements 9.4-49 9.4.8 Condensate Demineralizer Waste Evaporator Building Environmental Control Sys-tem 9.4-49 9.4.9 Postaccident Sampling Facility (PASF) Environmental Control System 9.4-49 9.5 OTHER AUXILIARY SYSTEMS 9.5-1 9.5.1 Fire Protection System 9.5-1 9.5.1.1 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 9.5-7 9.5.3 Lighting Systems 9.5-8 9.5.3.1 Design Bases 9.5-8 9.5.3.2 Description of the Plant Lighting System 9.5-8 9.5.3.3 Diesel Generator Building Lighting System 9.5-9 9.5.3.4 Safety Related Functions of the Lighting Systems 9.5-10 9.5.3.5 Inspection and Testing Requirements 9.5-10 9.5.4 Diesel Generator Fuel Oil Storage and Transfer System 9.5-10 9.5.4.1 Design Basis 9.5-10 9.5.4.2 System Description 9.5-11 9.5.4.3 Safety Evaluation 9.5-14 Table of Contents 1-lxxxvii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 9.5.4.4 Tests and Inspections 9.5-15 9.5.5 Diesel Generator Cooling Water System 9.5-15 9.5.5.1 Design Bases 9.5-15 9.5.5.2 System Description 9.5-15 9.5.5.3 Safety Evaluation 9.5-16 9.5.5.4 Tests and Inspections 9.5-16 9.5.6 Diesel Generator Starting System 9.5-17 9.5.6.1 Design Bases 9.5-17 9.5.6.2 System Description 9.5-17 9.5.6.3 Safety Evaluation 9.5-18 9.5.6.4 Tests and Inspections 9.5-18 9.5.7 Diesel Engine Lubrication System 9.5-18 9.5.7.1 Design Bases 9.5-18 9.5.7.2 System Description 9.5-19 9.5.7.3 Safety Evaluation 9.5-20 9.5.7.4 Test and Inspections 9.5-21 9.5.8 Diesel Generator Combustion Air Intake and Exhaust System 9.5-21 9.5.8.1 Design Bases 9.5-21 9.5.8.2 System Descriptions 9.5-21 9.5.8.3 Safety Evaluation 9.5-22 9.5.8.4 Tests and Inspection 9.5-22 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 10.2-8 10.2.3.3 High Temperature Properties 10.2-9 10.2.3.4 Turbine Disc Design 10.2-10 10.2.3.5 Preservice Inspection 10.2-10 10.2.3.5.1 Low Pressure Turbine Rotor 10.2-10 10.2.3.5.2 High Pressure Turbine Rotor 10.2-11 10.2.3.5.3 Preoperational and Initial Startup Testing 10.2-11 10.2.3.6 Inservice Inspection 10.2-11 10.2.3.6.1 Turbine Rotors 10.2-11 10.2.3.6.2 Turbine Overspeed Protection 10.2-12 10.2.3.6.3 Other Turbine Protection Features 10.2-13 10.2.4 Evaluation 10.2-13 1-lxxxviii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 10.3-4 10.3.5.1 Purpose 10.3-4 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 10.3-6 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 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 10.4-9 10.4.4.3 Safety Evaluation 10.4-9 10.4.4.4 Inspection and Testing 10.4-10 10.4.4.5 Instrumentation 10.4-11 10.4.5 Condenser Circulating Water System 10.4-11 10.4.5.1 Design Basis 10.4-11 Table of Contents 1-lxxxix
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 10.4.5.2 System Description 10.4-12 10.4.5.3 Safety Evaluation 10.4-14 10.4.5.4 Inspection and Testing 10.4-15 10.4.5.5 Instrumentation Application 10.4-15 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 10.4-16 10.4.6.3 Safety Evaluation 10.4-18 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 10.4-20 10.4.7.3 Safety Evaluation 10.4-27 10.4.7.4 Inspection and Testing 10.4-28 10.4.7.5 Instrumentation 10.4-29 10.4.8 Steam Generator Blowdown System 10.4-29 10.4.8.1 Design Bases 10.4-29 10.4.8.2 System Description and Operation 10.4-30 10.4.8.3 Safety Evaluation 10.4-31 10.4.8.4 Inspections and Testing 10.4-32 10.4.9 Auxiliary Feedwater System 10.4-32 10.4.9.1 Design Bases 10.4-32 10.4.9.2 System Description 10.4-33 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 10.4-38 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 1-xc Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 11.2.3 SYSTEM DESIGN 11.2-4 11.2.3.1 Component Design 11.2-4 11.2.3.2 Instrumentation Design 11.2-9 11.2.4 Operating Procedure 11.2-10 11.2.5 PERFORMANCE TESTS 11.2-16 11.2.6 ESTIMATED RELEASES 11.2-17 11.2.6.1 NRC Requirements 11.2-17 11.2.6.2 Westinghouse PWR Release Experience 11.2-17 11.2.6.3 Expected Liquid Waste Processing System Releases 11.2-17 11.2.6.4 Turbine Building (TB) Drains 11.2-17 11.2.6.4.1 Purpose 11.2-17 11.2.6.4.2 Description 11.2-17 Condensate Polishing Demineralizer System Drains 18 Other Turbine Building Drainage 18 Oil and Oily Water Drainage 18 11.2.6.5 Estimated Total Liquid Releases 11.2-18 11.2.7 RELEASE POINTS 11.2-18 11.2.8 DILUTION FACTORS 11.2-19 11.2.9 ESTIMATED DOSES FROM RADIONUCLIDES IN LIQUID EFFLUENTS 11.2-19 11.2.9.1 Assumptions and Calculational Methods 11.2-19 11.2.9.2 Summary of Dose from Radionuclides in Liquid Effluents 11.2-21 11.3 GASEOUS WASTE SYSTEMS 11.3-1 11.3.1 Design Bases 11.3-1 11.3.2 SYSTEM DESCRIPTIONS 11.3-1 11.3.3 SYSTEM DESIGN 11.3-3 11.3.3.1 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 11.3-7 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 11.3-9 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 11.3-12 Table of Contents 1-xci
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 11.4 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYS-TEM 11.4-1 11.4.1 Design Objectives 11.4-1 11.4.2 Continuous Monitors 11.4-2 11.4.2.1 Liquid Monitors 11.4-2 11.4.2.1.1 Waste Disposal System Liquid Effluent Monitor 11.4-2 11.4.2.1.2 Essential Raw Cooling Water Effluent Monitors 11.4-2 11.4.2.1.3 Component Cooling System Liquid Effluent Monitors 11.4-3 11.4.2.1.4 Steam Generator Blowdown Effluent Monitor 11.4-3 11.4.2.1.5 Condensate Demineralizer Regenerant Effluent Monitor 11.4-3 11.4.2.1.6 Turbine Building Sump Effluent Monitor 11.4-3 11.4.2.2 Gaseous Monitors 11.4-4 11.4.2.2.1 Waste Gas Holdup System Effluent Monitor 11.4-4 11.4.2.2.2 Condenser Vacuum Air Exhaust Monitors 11.4-4 11.4.2.2.3 Spent Fuel Pool Accident Radiation Monitors 11.4-5 11.4.2.2.4 Ventilation Monitors and Containment Atmosphere Monitors 11.4-5 11.4.2.2.5 Main Control Room Air Intake Monitors 11.4-7 11.4.2.2.6 Containment Purge Air Exhaust Monitors 11.4-8 11.4.2.2.7 Main Steamline Radiation Monitors 11.4-8 11.4.3 SAMPLING 11.4-8 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 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 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 11.5-4 11.5.6 Shipment 11.5-5 11.6 Offsite Radiological Monitoring Program 11.6-1 11.6.1 Expected Background 11.6-2 11.6.2 Critical Pathways to Man 11.6-2 11.6.2.1 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 1-xcii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 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 12.2.1.1.1 Sources Shielded by Primary Shield Concrete 12.2-3 12.2.1.1.2 Sources Shielded by Secondary Shield Concrete 12.2-4 12.2.1.2 Auxiliary Systems Sources 12.2-4 12.2.1.2.1 Chemical and Volume Control System - Mixed-Bed Demineralizers 12.2-4 12.2.1.2.2 Chemical and Volume Control System - Cation Bed Demineralizer 12.2-4 12.2.1.2.3 Chemical and Volume Control System - Volume Control Tanks 12.2-5 12.2.1.2.4 Chemical and Volume Control System - Reactor Coolant Filter 12.2-5 12.2.1.2.5 Chemical and Volume Control System - Seal Water Return Filter 12.2-5 12.2.1.2.6 Chemical and Volume Control System - Seal Water Injection Filters 12.2-6 12.2.1.2.7 Chemical and Volume Control System - Holdup Tanks 12.2-6 12.2.1.2.8 Chemical and Volume Control System - Evaporator Feed Mixed-Bed Ion Table of Contents 1-xciii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page Exchangers 12.2-6 12.2.1.2.9 Chemical and Volume Control System - Evaporator Feed Cation Bed Ion Exchanger 12.2-7 12.2.1.2.10 Chemical and Volume Control System - Ion Exchange Filters 12.2-7 12.2.1.2.11 Gas Stripper and Boric Acid Evaporator Package 12.2-7 12.2.1.2.12 Spent Fuel Pool Cooling System Demineralizer and Filters 12.2-8 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 12.3.4.1.1 Objectives and Design Basis 12.3-17 12.3.4.1.2 Operation Characteristics 12.3-17 Area Monitor Detector 17 Main Control Room Ratemeter (0-M-12, 1-,2-M-30) 18 Local Indicator-Alarm Panel 18 Multipoint Recorders (Main Control Room 0-M-12, 1-,2-M-31) 18 Monitor Sensitivity and Range 18 12.3.4.1.3 Area Monitor Calibration and Maintenance 12.3-18 12.3.4.2 Airborne Particulate Radioactivity Monitoring 12.3-19 12.3.4.2.1 Design Basis 12.3-19 12.3.4.2.2 Airborne Monitoring Channels 12.3-20 12.3.4.2.3 Operational Characteristics 12.3-20 12.3.4.2.4 Component Descriptions 12.3-21 12.3.4.2.5 Sensitivity, Range and Set Point 12.3-22 12.3.4.2.6 Calibration and Maintenance 12.3-22 12.3.4.3 Deleted by Amendment 84. 12.3-23 12.3.4.4 Special Radiation Monitors 12.3-23 12.3.4.4.1 Portal Monitors 12.3-23 12.3.4.4.2 Personnel Contamination Monitors 12.3-23 12.3.4.4.3 Deleted by Amendment 84. 12.3-23 12.4 DOSE ASSESSMENT 12.4-1 1-xciv Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 12.5 RADIATION PROTECTION PROGRAM 12.5-1 12.5.1 Organization 12.5-1 12.5.2 Equipment, Instrumentation, and Facilities 12.5-2 12.5.3 Procedures 12.5-4 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 13.1-2 13.1.2.1 Offsite Organizations 13.1-2 13.1.2.2 Onsite Organization 13.1-2 13.1.3 Qualification Requirements for Nuclear Facility Personnel 13.1-2 13.2 TRAINING PROGRAMS 13.2-1 13.2.1 Accredited Training Programs 13.2-1 13.2.2 General Employee and Fitness for Duty Training 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 13.5.2.1.1 General Operating Instructions 13.5-2 13.5.2.1.2 System Operating Instructions 13.5-2 13.5.2.1.3 Abnormal Operating Instructions 13.5-3 13.5.2.1.4 Emergency Instructions 13.5-3 13.5.2.1.5 Alarm Response Instructions 13.5-3 13.5.2.1.6 Fuel Handling Instructions 13.5-3 13.5.2.2 Other Procedures 13.5-3 13.5.2.2.1 Maintenance Instructions and Modification Procedures 13.5-3 13.5.2.2.2 Instrument Maintenance Instructions 13.5-3 13.5.2.2.3 Surveillance Instructions and Technical Requirement Instructions 13.5-4 13.5.2.2.4 Technical Instructions 13.5-4 Table of Contents 1-xcv
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 13.5.2.2.5 Miscellaneous Procedures 13.5-4 13.5.2.2.6 Power Escalation Tests 13.5-4 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 14.2.2.1.1 Startup Manager 14.2-3 14.2.2.1.2 Section deleted by Amendment 84 14.2-4 14.2.2.1.3 System Test Engineers 14.2-4 14.2.2.2 Plant Operating Organization 14.2-5 14.2.2.2.1 Technical Support Manager 14.2-5 14.2.2.2.2 Power Ascension Test Engineers 14.2-5 14.2.2.2.3 Operations 14.2-6 14.2.2.2.4 Maintenance 14.2-6 14.2.2.3 Nuclear Assurance 14.2-6 14.2.2.4 Major Participating Organizations 14.2-6 14.2.2.4.1 Nuclear Engineering 14.2-6 14.2.2.4.2 Construction 14.2-7 14.2.2.4.3 Westinghouse Electric Corporation 14.2-7 14.2.2.5 Joint Test Group 14.2-7 14.2.2.5.1 JTG Membership 14.2-8 14.2.2.6 Test Review Group 14.2-8 14.2.2.6.1 TRG Membership 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 1-xcvi Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 14.2-34 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 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 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 Table of Contents 1-xcvii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 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 15.2.4.2.1 Method of Analysis 15.2-14 15.2.4.2.2 Dilution During Refueling 15.2-14 15.2.4.2.3 Dilution During Startup 15.2-15 15.2.4.2.4 Dilution at Power 15.2-15 15.2.4.3 Conclusions 15.2-16 15.2.4.3.1 For Dilution During Refueling 15.2-16 15.2.4.3.2 For Dilution During Startup 15.2-16 15.2.4.3.3 For Dilution Following Reactor Shutdown 15.2-16 15.2.4.3.4 For Dilution During Full Power Operation 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-xcviii 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 15.2.10.0.1 Identification of Causes and Accident Description 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-xcix
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 15.4.1.1.1 Westinghouse Performance Criteria for Emergency Core Cooling System 15.4-3 15.4.1.1.2 Method of Thermal Analysis 15.4-3 15.4.1.1.3 Containment Analysis 15.4-3 15.4.1.1.4 Results of Large Break Spectrum 15.4-4 15.4.1.1.5 Effect of Containment Purging 15.4-5 15.4.1.1.6 Conclusions - Thermal Analysis 15.4-6 15.4.1.2 Hydrogen Production and Accumulation 15.4-6 15.4.1.2.1 Method of Analysis 15.4-6 15.4.1.2.2 Typical Assumptions 15.4-7 15.4.1.2.3 Core Solution Radiolysis 15.4-9 15.4.1.2.4 Sump Solution Radiolysis 15.4-11 15.4.1.2.5 Results 15.4-12 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 15.4.2.1.1 Identification of Causes and Accident Description 15.4-12 15.4.2.1.2 Analysis of Effects and Consequences 15.4-14 15.4.2.1.3 Conclusions 15.4-19 1-c Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 15.4.2.2 Major Rupture of a Main Feedwater Pipe 15.4-19 15.4.2.2.1 Identification of Causes and Accident Description 15.4-19 15.4.2.2.2 Analysis of Effects and Consequences 15.4-20 15.4.2.2.3 Conclusions 15.4-22 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 15.4.6.1.1 Design Precautions and Protection 15.4-35 15.4.6.1.2 Limiting Criteria 15.4-38 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 15.5-19 15.5.5 Environmental Consequences of a Postulated Steam Generator Tube Rupture 15.5-20 15.5.6 Environmental Consequences of a Postulated Fuel Handling Accident 15.5-21 15.5.7 Environmental Consequences of a Postulated Rod Ejection Accident 15.5-23 15A DOSE MODELS USED TO EVALUATE THE ENVIRONMENTAL CONSEQUENC-ES OF ACCIDENTS 15A.1 INTRODUCTION 15A-1 15A.2 ASSUMPTIONS 15A-1 15A.3 GAMMA DOSE AND BETA DOSE 15A-1 15A.4 THYROID INHALATION DOSE 15A-2 Table of Contents 1-ci
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.1-1 16.2 PROPOSED FINAL TECHNICAL SPECIFICATIONS 16.2-1 16.3 RELOCATED SPECIFICATIONS 16.1-1 16.3.1 Discussion 16.1-1 16.3.2 Document Control 16.1-1 16.3.3 Changes to the Relocated Specifications 16.1-1 17.0 QUALITY ASSURANCE 17-1 17.1 Quality Assurance During Design and Construction 17-1 17.1.1 TVA Organization 17-1 17.1.2 Quality Assurance Program 17-1 17.1A WESTINGHOUSE NUCLEAR ENERGY SYSTEM DIVISIONS QUALITY ASSURANCE PLAN 17-2 17.2 QUALITY ASSURANCE FOR STATION OPERATION 17.2-1 17.2.1 Identification of Safety-Related Features 17.2-1 1-cii Table of Contents
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