ML090340701
| ML090340701 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/18/2008 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML090340701 (50) | |
Text
tion Title Page R_Section_1.pdf INTRODUCTION AND GENERAL DESCRIPTION OF PLANT INTRODUCTION 1.1-1 GENERAL PLANT DESCRIPTION 1.2-1 1 Site Characteristics 1.2-1 1.1 Location 1.2-1 1.2 Demography 1.2-1 1.3 Meteorology 1.2-1 1.4 Hydrology 1.2-1 1.5 Geology 1.2-1 1.6 Seismology 1.2-2 2 Facility Description 1.2-2 2.1 Design Criteria 1.2-2 2.2 Nuclear Steam Supply System (NSSS) 1.2-2 2.3 Control and Instrumentation 1.2-4 2.4 Fuel Handling System 1.2-5 2.5 Waste Processing System 1.2-5 2.6 Steam and Power Conversion System 1.2-5 2.7 Plant Electrical System 1.2-6 2.8 Cooling Water 1.2-7 2.9 Component Cooling System 1.2-7 2.10 Chemical and Volume Control System 1.2-7 2.11 Sampling and Water Quality System 1.2-8 2.12 Ventilation 1.2-9 2.13 Fire Protection System 1.2-9 2.14 Compressed Air Systems 1.2-9 2.15 Engineered Safety Features 1.2-9 2.16 Shared Facilities and Equipment 1.2-10 3 General Arrangement of Major Structures and Equipment 1.2-13 COMPARISON TABLES 1.3-1 1 Comparisons With Similar Facility Designs 1.3-1 2 Comparison Of Final And Preliminary Designs 1.3-1 IDENTIFICATION OF AGENTS AND CONTRACTORS 1.4-1 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.5-1 1 17 x 17 Fuel Assembly 1.5-1 1.1 Rod Cluster Control Spider Tests 1.5-1 1.2 Grid Tests 1.5-1 1.3 Fuel Assembly Structural Tests 1.5-1 1.4 Guide Tube Tests 1.5-2 e of Contents 1-i
tion Title Page 1.5 Prototype Assembly Tests 1.5-2 2 Heat Transfer Tests (17 x 17) 1.5-2 2.1 17 x 17 LOCA Heat Transfer Tests 1.5-2 2.2 Departure from Nucleate Boiling (DNB) 1.5-2 MATERIAL INCORPORATED BY REFERENCE 1.6-1 ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAWINGS 1.7-1 TECHNICAL QUALIFICATION OF APPLICANT 1.8-1 NUCLEAR PERFORMANCE PLAN 1.9-1 1 Corrective Action Plans 1.9-1 1.1 Cable Issues 1.9-1 1.2 Cable Tray and Cable Tray Supports 1.9-1 1.3 Design Baseline and Verification Program (DBVP) 1.9-2 1.4 Electrical Conduit and Conduit Support 1.9-2 1.5 Electrical Issues 1.9-2 1.6 Equipment Seismic Qualification 1.9-2 1.7 Fire Protection 1.9-3 1.8 Hanger and Analysis Update Program (HAAUP) 1.9-3 1.9 Heat Code Traceability 1.9-3 1.10 Heating, Ventilation, and Air Conditioning (HVAC) Duct Supports 1.9-3 1.11 Instrument Lines 1.9-3 1.12 Prestart Test Program 1.9-3 1.13 QA Records 1.9-4 1.14 Q-LIST 1.9-4 1.15 Replacement Items Program (RIP-CAP) 1.9-4 1.16 Seismic Analysis 1.9-4 1.17 Vendor Information 1.9-4 1.18 Welding 1.9-5 2 Special Programs (SPs) 1.9-5 2.1 Concrete Quality Program 1.9-5 2.2 Containment Cooling 1.9-5 2.3 Detailed Control room Design Review 1.9-5 2.4 Environmental Qualification Program 1.9-6 2.5 Master Fuse List 1.9-6 2.6 Mechanical Equipment Qualification 1.9-6 2.7 Microbiologically Induced Corrosion (MIC) 1.9-6 2.8 Moderate Energy Line Break Flooding (MELB) 1.9-6 2.9 Radiation Monitoring System 1.9-6 2.10 Soil Liquefaction 1.9-7 2.11 Use-As-Is CAQs 1.9-7 3 REFERENCES 1.9-7 R_Section_2_B.pdf R_Section_2_A.pdf Table of Contents
tion Title Page SITE CHARACTERISTICS GEOGRAPHY AND DEMOGRAPHY 2.1-1 1 Site Location and Description 2.1-1 1.1 Specification of Location 2.1-1 1.2 Site Area Map 2.1-1 1.3 Boundaries for Establishing Effluent Limits 2.1-2 2 Exclusion Area Authority And Control 2.1-2 2.1 Authority 2.1-2 2.2 Control of Activities Unrelated to Plant Operation 2.1-2 2.3 Arrangements for Traffic Control 2.1-2 2.4 Abandonment or Relocation of Roads 2.1-2 3 Population Distribution 2.1-2 3.1 Population Within 10 Miles 2.1-3 3.2 Population Between 10 and 50 Miles 2.1-3 3.3 Transient Population 2.1-4 3.4 Low Population Zone 2.1-4 3.5 Population Center 2.1-5 3.6 Population Density 2.1-5 NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES 2.2-1 Location and Route 2.2-1 2 Descriptions 2.2-1 2.1 Description of Facilities 2.2-1 2.2 Description of Products and Materials 2.2-1 2.3 Pipelines 2.2-1 2.4 Waterways 2.2-1 2.5 Airports 2.2-2 2.6 Projections of Industrial Growth 2.2-2 3 Evaluation of Potential Accidents 2.2-2
3.1 REFERENCES
2.2-3 METEOROLOGY 2.3-1 1 Regional Climate 2.3-1 1.1 Data Sources 2.3-1 1.2 General Climate 2.3-1 1.3 Severe Weather 2.3-2 2 Local Meteorology 2.3-5 2.1 Data Sources 2.3-5 2.2 Normal and Extreme Values of Meteorological Parameters 2.3-6 2.3 Potential Influence of the Plant and Its Facilities on Local Meteorology 2.3-8 2.4 Local Meteorological Conditions for Design and Operating Bases 2.3-9 e of Contents 1-iii
tion Title Page 3 Onsite Meteorological Measurements Program 2.3-9 3.1 Preoperational Program 2.3-9 3.2 Operational Meteorological Program 2.3-12 3.3 Onsite Data Summaries of Parameters for Dispersion Meteorology 2.3-13 4 Short-Term (Accident) Diffusion Estimates 2.3-14 4.1 Objective 2.3-14 4.2 Calculation Results 2.3-17 5 Long-Term (Routine) Diffusion Estimates 2.3-18 R_Section_2_B.pdf HYDROLOGIC ENGINEERING 2.4-1 1 Hydrological Description 2.4-1 1.1 Sites and Facilities 2.4-1 1.2 Hydrosphere 2.4-2 2 Floods 2.4-6 2.1 Flood History 2.4-6 2.2 Flood Design Considerations 2.4-7 2.3 Effects of Local Intense Precipitation 2.4-9 3 Probable Maximum Flood (PMF) on Streams and Rivers 2.4-12 3.1 Probable Maximum Precipitation (PMP) 2.4-13 3.2 Precipitation Losses 2.4-14 3.3 Runoff and Stream Course Model 2.4-14 3.4 Probable Maximum Flood Flow 2.4-18 3.5 Water Level Determinations 2.4-25 3.6 Coincident Wind Wave Activity 2.4-26 4 Potential Dam Failures, Seismically Induced 2.4-28 4.1 Dam Failure Permutations 2.4-28 4.2 Unsteady Flow Analysis of Potential Dam Failures 2.4-40 4.3 Water Level at Plantsite 2.4-40 5 Probable Maximum Surge and Seiche Flooding 2.4-40 6 Probable Maximum Tsunami Flooding 2.4-40 7 Ice Effects 2.4-41 8 Cooling Water Canals and Reservoirs 2.4-42 9 Channel Diversions 2.4-42 10 Flooding Protection Requirements 2.4-42 11 Low Water Considerations 2.4-44 11.1 Low Flow in Rivers and Streams 2.4-44 11.2 Low Water Resulting From Surges, Seiches, or Tsunami 2.4-44 11.3 Historical Low Water 2.4-44 11.4 Future Control 2.4-45 11.5 Plant Requirements 2.4-45 12 Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents 46 12.1 Radioactive Liquid Wastes 2.4-46 12.2 Accidental Slug Releases to Surface Water 2.4-46 Table of Contents
tion Title Page 12.3 Effects on Ground Water 2.4-48 13 Groundwater 2.4-49 13.1 Description and On-Site Use 2.4-49 13.2 Sources 2.4-50 13.3 Accident Effects 2.4-51 13.4 Monitoring and Safeguard Requirements 2.4-52 13.5 Design Basis for Subsurface Hydrostatic Loading 2.4-52 14 Flooding Protection Requirements 2.4-52 14.1 Introduction 2.4-53 14.2 Plant Operation During Floods Above Grade 2.4-54 14.3 Warning Scheme 2.4-56 14.4 Preparation for Flood Mode 2.4-56 14.5 Equipment 2.4-58 14.6 Supplies 2.4-59 14.7 Plant Recovery 2.4-59 14.8 Warning Plan 2.4-59 14.9 Basis For Flood Protection Plan In Rainfall Floods 2.4-60 14.10 Basis for Flood Protection Plan in Seismic-Caused Dam Failures 2.4-66 14.11 Special Condition Allowance 2.4-68 GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING
SUMMARY
FOUNDATION CONDITIONS 2.5-1 1 Basic Geology and Seismic Information 2.5-2 1.1 Regional Geology 2.5-3 1.2 Site Geology 2.5-27 2 Vibratory Ground Motion 2.5-34 2.1 Seismicity 2.5-34 2.2 Geologic Structures and Tectonic Activity 2.5-42 2.3 Correlation of Earthquake Activity With Geologic Structures to Tectonic Prov-s 2.5-42 2.4 Maximum Earthquake Potential 2.5-43 2.5 Seismic Wave Transmission Characteristics of the Site 2.5-45 2.6 Safe Shutdown Earthquake 2.5-45 2.7 Operating Basis Earthquake 2.5-45 3 Surface Faulting 2.5-45 3.1 Geologic Conditions of the Site 2.5-45 3.2 Evidence of Fault Offset 2.5-45 3.3 Earthquakes Associated With Capable Faults 2.5-54 3.4 Investigations of Capable Faults 2.5-54 3.5 Correlation of Epicenters With Capable Faults 2.5-56 3.6 Description of Capable Faults 2.5-56 3.7 Zone Requiring Detailed Faulting Investigation 2.5-56 3.8 Results of Faulting Investigations 2.5-56 4 Stability of Subsurface Materials 2.5-57 e of Contents 1-v
tion Title Page 4.1 Geologic Features 2.5-57 4.2 Properties of Subsurface Materials 2.5-57 4.3 Exploration 2.5-90 4.4 Geophysical Surveys 2.5-90 4.5 Excavations and Backfill 2.5-93 4.6 Groundwater Conditions 2.5-101 4.7 Response of Soil and Rock to Dynamic Loading 2.5-103 4.8 Liquefaction Potential 2.5-103 4.9 Earthquake Design Basis 2.5-114 4.10 Static Analysis 2.5-114 4.11 Safety-Related Criteria for Foundations 2.5-115 4.12 Techniques to Improve Subsurface Conditions 2.5-116 4.13 Construction Notes 2.5-118 5 Stability of Slopes 2.5-119 5.1 Slope Characteristics 2.5-119 5.2 Design Criteria and Analysis 2.5-120 5.3 Logs of Borings 2.5-128 5.4 Compaction Specifications 2.5-128 6 Embankments 2.5-12 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 3.1-1 1 Introduction 3.1-1 2 WBNP Conformance with GDCs 3.1-1 2.1 Overall Requirements 3.1-1 2.2 Protection By Multiple Fission Product Barriers 3.1-5 2.3 Protection and Reactivity Control Systems 3.1-12 2.4 Fluid Systems 3.1-17 2.5 Reactor Containment 3.1-30 2.6 Fuel and Radioactivity Control 3.1-35 CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS 3.2-1 1 Seismic Classifications 3.2-1 2 System Quality Group Classification 3.2-1 2.1 Class A 3.2-2 2.2 Class B 3.2-2 2.3 Class C 3.2-2 2.4 Class D 3.2-2 2.5 Relationship of Applicable Codes to Safety Classification for Mechanical Com-ponents 3.2-3 2.6 Nonnuclear Safety Class (NNS) 3.2-3 2.7 Heating, Ventilation and Air Conditioning (HVAC) Safety Classification 3.2-3 3 Code Cases and Code Editions and Addenda 3.2-3 Table of Contents
tion Title Page 3.1 TVA Design and Fabrication 3.2-3 3.2 Purchased Materials and Components 3.2-4 Wind and Tornado Loading 3.3-1 1 Wind Loadings 3.3-1 1.1 Design Wind Velocity 3.3-1 1.2 Determination of Applied Force 3.3-1 2 Tornado Loadings 3.3-1 2.1 Applicable Design Parameters 3.3-1 2.2 Determination of Forces on Structures 3.3-2 2.3 Ability of Category I Structures to Perform Despite Failure of Structures Not Designed for Tornado Loads 3.3-3 WATER LEVEL (FLOOD) DESIGN 3.4-1 1 Flood Protection 3.4-1 2 Analysis Procedure 3.4-1 MISSILE PROTECTION 3.5-1 1 Missile Selection and Description 3.5-2 1.1 Internally Generated Missiles (Outside Containment) 3.5-2 1.2 Internally Generated Missiles (Inside Containment) 3.5-5 1.3 Turbine Missiles 3.5-9 1.4 Missiles Generated By Natural Phenomena 3.5-27 1.5 Missiles Generated by Events Near the Site. 3.5-28 1.6 Aircraft Hazards 3.5-28 2 Systems To Be Protected 3.5-29 3 Barrier Design Procedures 3.5-29 3.1 Additional Diesel Generator Building (And Other Category I Structures Added After July 1979) 3.5-32 A ESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES 3.5A-1 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POS-LATED RUPTURE OF PIPING 3.6-1 A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POS-LATED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIP-
) 3.6A-1 A.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment 3.6A-7 A.1.1 Design Bases 3.6A-7 A.1.2 Description of Piping System Arrangement 3.6A-10 A.1.3 Safety Evaluation 3.6A-10 A.2 Determination of Break Locations and Dynamic Effects Associated with the Postu-lated Rupture of Piping 3.6A-10 e of Contents 1-vii
tion Title Page A.2.1 Criteria Used to Define Break and Crack Location and Configuration 3.6A-10 A.2.2 Analytical Methods to Define Forcing Functions and Response Models 3.6A-16 A.2.3 Dynamic Analysis Methods to Verify Integrity and Operability 3.6A-19 A.2.4 Guard Pipe Assembly Design Criteria 3.6A-22 A.2.5 Summary of Dynamic Analysis Results 3.6A-23 B PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POS-LATED RUPTURE OF PIPING 3.6A-24 B.1 Break Locations And Dynamic Effects Associated With Postulated Primary Loop Pipe Rupture 3.6A-24 A.2 Analytical Methods to Define Forcing Function and Response Models 3.6A-25 B.3 Dynamic Analysis of the Reactor Coolant Loop Piping Equipment Supports and Pipe Whip Restraints 3.6A-27 SEISMIC DESIGN 3.7-1 1 Seismic Input 3.7-2 1.1 Ground Response Spectra 3.7-2 1.2 Design Time Histories 3.7-2 1.3 Critical Damping Values 3.7-3 1.4 Supporting Media for Seismic Category I Structures 3.7-3 2 Seismic System Analysis 3.7-3 2.1 Seismic Analysis Methods 3.7-4 2.2 Natural Frequencies and Response Loads for NSSS 3.7-22 2.3 Procedures Used for Modeling 3.7-22 2.4 Soil/Structure Interaction 3.7-23 2.5 Development of Floor Response Spectra 3.7-24 2.6 Three Components of Earthquake Motion 3.7-25 2.7 Combination of Modal Responses 3.7-26 2.8 Interaction of Non-Category I Structures With Seismic Category I Structures 3.7-28 2.9 Effects of Parameter Variations on Floor Response Spectra 3.7-29 2.10 Use of Constant Vertical Load Factors 3.7-29 2.11 Methods Used to Account for Torsional Effects 3.7-29 2.12 Comparison of Responses - Set A versus Set B 3.7-30 2.13 Methods for Seismic Analysis of Dams 3.7-30 2.14 Determination of Category I Structure Overturning Moments 3.7-30 2.15 Analysis Procedure for Damping 3.7-31 3 Seismic Subsystem Analysis 3.7-31 3.1 Seismic Analysis Methods for Other Than NSSS 3.7-31 3.2 Determination of Number of Earthquake Cycles 3.7-32 3.3 Procedure Used for Modeling 3.7-32 3.4 Basis for Selection of Frequencies 3.7-34 3.5 Use of Equivalent Static Load Method of Analysis 3.7-35 Table of Contents
tion Title Page 3.6 Three Components of Earthquake Motion 3.7-35 3.7 Combination of Modal Responses 3.7-36 3.8 Analytical Procedures for Piping Other Than NSSS 3.7-37 3.9 Multiple Supported Equipment and Components with Distinct Inputs 3.7-43 3.10 Use of Constant Vertical Load Factors 3.7-44 3.11 Torsional Effects of Eccentric Masses 3.7-45 3.12 Buried Seismic Category I Piping Systems 3.7-45 3.13 Interaction of Other Piping with Seismic Category I Piping 3.7-51 3.14 Seismic Analyses for Fuel Elements, Control Rod Assemblies, Control Rod Drives, and Reactor Internals 3.7-51 3.15 Analysis Procedure for Damping 3.7-53 3.16 Seismic Analysis and Qualification of Category I Equipment Other Than NSSS 3.7-53 3.17 Seismic Analysis and Design of HVAC Duct and Duct Support Systems 3.7-56 4 Seismic Instrumentation Program 3.7-60 4.1 Comparison with Regulatory Guide 1.12 3.7-60 4.2 Location and Description of Instrumentation 3.7-60 4.3 Control Room Operator Notification 3.7-64 4.4 Comparison of Measured and Predicted Responses 3.7-64 DESIGN OF CATEGORY I STRUCTURES
.1 Concrete Shield Building 3.8.1-1 1.1 Description of the Shield Building 3.8.1-1 1.1.1 Equipment Hatch Doors and Sleeves 3.8.1-2 1.2 Applicable Codes, Standards, and Specifications 3.8.1-3 1.3 Loads and Loading Combinations 3.8.1-5 1.4 Design and Analysis Procedures 3.8.1-8 1.5 Structural Acceptance Criteria 3.8.1-10 1.6 Materials, Quality Control and Special Construction Techniques 3.8.1-11 1.6.1 Materials 3.8.1-11 1.6.2 Quality Control 3.8.1-12 1.6.3 Construction Techniques 3.8.1-13 1.7 Testing and Inservice Surveillance Requirements 3.8.1-13
.2 Steel Containment System 3.8.2-1 2.1 Description of the Containment and Penetrations 3.8.2-1 2.1.1 Description of the Containment 3.8.2-1 2.1.2 Description of Penetrations 3.8.2-1 2.2 Applicable Codes, Standards and Specifications 3.8.2-3 2.2.1 Codes 3.8.2-3 2.2.2 Design Specification Summary 3.8.2-4 2.2.3 NRC Regulatory Guides 3.8.2-6 e of Contents 1-ix
tion Title Page 2.3 Loads and Loading Combinations 3.8.2-7 2.3.1 Design Loads 3.8.2-7 2.3.2 Loading Conditions 3.8.2-9 2.4 Design and Analysis Procedures 3.8.2-11 2.4.1 Introduction 3.8.2-11 2.4.2 Static Stress Analysis 3.8.2-12 2.4.3 Dynamic Seismic Analysis 3.8.2-12 2.4.4 Non-Axisymmetric Pressure Loading Analysis 3.8.2-13 2.4.5 Thermal Analysis 3.8.2-14 2.4.6 Penetrations Analysis 3.8.2-14 2.4.7 Interaction of Containment and Attached Equipment 3.8.2-17 2.4.8 Anchorage 3.8.2-17 2.5 Structural Acceptance Criteria 3.8.2-18 2.5.1 Margin of Safety 3.8.2-18 2.6 Materials, Quality Control, and Special Construction Techniques 3.8.2-19 2.6.1 Materials - General 3.8.2-19 2.6.2 Corrosion Protection 3.8.2-22 2.6.3 Protective Coatings 3.8.2-24 2.6.4 Tolerances 3.8.2-25 2.6.5 Vessel Material Inspection and Test 3.8.2-25 2.6.6 Impact Testing 3.8.2-25 2.6.7 Post-Weld Heat Treatment 3.8.2-26 2.6.8 Welding 3.8.2-26 2.7 Testing and Inservice Inspection Requirements 3.8.2-26 2.7.1 Bottom Liner Plates Test 3.8.2-26 2.7.2 Vertical Wall and Dome Tests 3.8.2-26 2.7.3 Soap Bubble Tests 3.8.2-26 2.7.4 Overpressure Tests 3.8.2-26 2.7.5 Leakage Rate Test 3.8.2-27 2.7.6 Operational Testing 3.8.2-27 2.7.7 Leak Testing Airlocks 3.8.2-27 2.7.8 Penetration Tests 3.8.2-28 2.7.9 Inservice Inspection Requirements 3.8.2-28
.3 Concrete Interior Structure 3.8.3-1 3.1 Description of the Interior Structure 3.8.3-1 3.1.1 General 3.8.3-1 3.1.2 Containment Floor Structural Fill Slab 3.8.3-1 3.1.3 Reactor Cavity Wall 3.8.3-2 3.1.4 Compartment Above Reactor 3.8.3-2 3.1.5 Refueling Canal Walls and Floor (Divider Barrier) 3.8.3-3 3.1.6 Crane Wall 3.8.3-3 3.1.7 Steam Generator Compartments (Divider Barrier) 3.8.3-5 3.1.8 Pressurizer Compartment (Divider Barrier) 3.8.3-5 Table of Contents
tion Title Page 3.1.9 Divider Deck at Elevation 756.63 (Divider Barrier) 3.8.3-5 3.1.10 Ice Condenser Support Floor - Elevation 744.5 (Divider Barrier) 3.8.3-5 3.1.11 Penetrations Through the Divider Barrier Canal Gate 3.8.3-6 3.2 Applicable Codes, Standards and Specifications 3.8.3-7 3.3 Loads and Loading Combinations 3.8.3-13 3.4 Design and Analysis Procedures 3.8.3-16 3.4.1 General 3.8.3-16 3.4.2 Structural Fill Slab on Containment Floor 3.8.3-16 3.4.3 Reactor Cavity Wall 3.8.3-16 3.4.4 Compartment Above Reactor 3.8.3-18 3.4.5 Seals Between Upper and Lower Compartments 3.8.3-18 3.4.6 Refueling Canal Walls and Floor (Divider Barrier) 3.8.3-19 3.4.7 Crane Wall 3.8.3-20 3.4.8 Steam Generator Compartments (Divider Barrier) 3.8.3-23 3.4.9 Pressurizer Compartment (Divider Barrier) 3.8.3-25 3.4.10 Operating Deck at Elevation 756.63 (Divider Barrier) 3.8.3-26 3.4.11 Ice Condenser Support Floor Elevation 744.5 (Divider Barrier) 3.8.3-27 3.4.12 Ice Condenser 3.8.3-28 3.4.13 Penetrations Through the Divider Barrier 3.8.3-29 3.5 Structural Acceptance Criteria 3.8.3-31 3.5.1 General 3.8.3-31 3.5.2 Structural Fill Slab on Containment Floor 3.8.3-31 3.5.3 Reactor Cavity Wall and Compartment Above Reactor 3.8.3-32 3.5.4 Refueling Canal Walls and Floor 3.8.3-32 3.5.5 Crane Wall 3.8.3-32 3.5.6 Steam Generator and Pressurizer Compartment 3.8.3-32 3.5.7 Operating Deck at Elevation 756.63 3.8.3-33 3.5.8 Ice Condenser Support Floor Elevation 744.5 3.8.3-33 3.5.9 Penetrations Through the Divider Barrier 3.8.3-33 3.5.10 Personnel Access Doors in Crane Wall 3.8.3-33 3.5.11 Seals Between Upper and Lower Compartments 3.8.3-34 3.5.12 Ice Condenser 3.8.3-35 3.6 Materials, Quality Control and Special Construction Techniques 3.8.3-36 3.6.1 Materials 3.8.3-36 3.6.2 Quality Control 3.8.3-37 3.6.3 Construction Technique 3.8.3-38 3.6.4 Ice Condenser 3.8.3-38 3.7 Testing and Inservice Surveillance Requirements 3.8.3-41 3.8 Environmental Effects 3.8.3-41 3.9 Interface Control 3.8.3-42
.4 Other Category I Structures 3.8.4-1 4.1 Description of the Structures 3.8.4-1 4.1.1 Auxiliary-Control Building 3.8.4-1 e of Contents 1-xi
tion Title Page 4.1.2 Diesel Generator Building 3.8.4-13 4.1.3 Category I Water Tanks and Pipe Tunnels 3.8.4-14 4.1.4 Class 1E Electrical System Manholes and Duct Runs 3.8.4-15 4.1.5 North Steam Valve Room 3.8.4-16 4.1.6 Intake Pumping Station and Retaining Walls 3.8.4-17 4.1.7 Miscellaneous Essential Raw Cooling Water (ERCW) Structures 3.8.4-18 4.1.8 Additional Diesel Generator Building 3.8.4-19 4.2 Applicable Codes, Standards, and Specifications 3.8.4-20 4.2.1 List of Documents 3.8.4-20 4.2.2 Basis for Use of the 1963 Edition of ACI 318 3.8.4-22 4.3 Loads and Loading Combinations 3.8.4-25 4.3.1 Description of Loads 3.8.4-25 4.3.2 Load Combinations and Allowable Stresses 3.8.4-26 4.4 Design and Analysis Procedures 3.8.4-27 4.4.1 Auxiliary-Control Building 3.8.4-27 4.4.2 Diesel Generator Building 3.8.4-35 4.4.3 Category I Water Tanks and Pipe Tunnels 3.8.4-36 4.4.4 Class 1E Electrical System Manholes 3.8.4-37 4.4.5 North Steam Valve Room 3.8.4-37 4.4.6 Intake Pumping Station and Retaining Walls Pumping Station 3.8.4-37 4.4.7 Miscellaneous ERCW Structures 3.8.4-38 4.4.8 Additional Diesel Generator Building 3.8.4-39 4.5 Structural Acceptance Criteria 3.8.4-41 4.5.1 Concrete 3.8.4-41 4.5.2 Structural and Miscellaneous Steel 3.8.4-41 4.5.3 Miscellaneous Components of the Auxiliary Building 3.8.4-42 4.5.4 Intake Pumping Station Traveling Water Screens 3.8.4-43 4.5.5 Diesel Generator Building Doors and Bulkheads 3.8.4-43 4.5.6 Additional Diesel Generator Building Missile Barriers 3.8.4-43 4.6 Materials, Quality Control, and Special Construction Techniques General 3.8.4-43 4.6.1 Materials 3.8.4-44 4.6.2 Quality Control 3.8.4-44 4.6.3 Special Construction Techniques 3.8.4-45 4.7 Testing and Inservice Surveillance Requirements 3.8.4-45 4.7.1 Concrete and Structural Steel Portions of Structures 3.8.4-45 4.7.2 Miscellaneous Components of Auxiliary-Control Building 3.8.4-45 4.7.3 Deleted by Amendment 79 3.8.4-46 4.7.4 Miscellaneous Components of the Intake Pumping Station 3.8.4-46
.5 Foundations and Concrete Supports 3.8.5-1 5.1 Description of Foundations and Supports 3.8.5-1 5.1.1 Primary Containment 3.8.5-1 5.1.2 Foundations of Other Category I Structures 3.8.5-1 5.2 Applicable Codes, Standards, and Specifications 3.8.5-4 Table of Contents
tion Title Page 5.3 Loads and Loading Combinations 3.8.5-4 5.4 Design and Analysis Procedure 3.8.5-4 5.4.1 Primary Containment Foundation 3.8.5-4 5.4.2 Auxiliary-Control Building 3.8.5-4 5.4.3 Intake Pumping Station 3.8.5-5 5.4.4 Soil-Supported Structures 3.8.5-5 5.4.5 Pile Supported Structures 3.8.5-5 5.5 Structural Acceptance Criteria 3.8.5-5 5.5.1 Primary Containment Foundation 3.8.5-5 5.5.2 Foundations of Other Category I Structures Auxiliary-Control Building3.8.5-6 5.6 Materials, Quality Control, and Special Construction Techniques 3.8.5-7 5.6.1 Materials 3.8.5-7 5.6.2 Quality Control 3.8.5-8 5.6.3 Special Construction Techniques 3.8.5-8
.6 Category I(L) Cranes 3.8.6-1 6.1 Polar Cranes 3.8.6-1 6.1.1 Description 3.8.6-1 6.1.2 Applicable Codes, Standards, and Specifications 3.8.6-1 6.1.3 Loads, Loading Combinations, and Allowable Stresses 3.8.6-2 6.1.4 Design and Analysis Procedure 3.8.6-2 6.1.5 Structural Acceptance Criteria 3.8.6-2 6.1.6 Materials, Quality Controls, and Special Construction Techniques 3.8.6-3 6.1.7 Testing and Inservice Surveillance Requirements 3.8.6-3 6.1.8 Safety Features 3.8.6-3 6.2 Auxiliary Building Crane 3.8.6-4 6.2.1 Description 3.8.6-4 6.2.2 Applicable Codes, Standards, and Specifications 3.8.6-5 6.2.3 Loads, Loading Combinations, and Allowable Stresses 3.8.6-5 6.2.4 Design and Analysis Procedure 3.8.6-5 6.2.5 Structural Acceptance Criteria 3.8.6-6 6.2.6 Materials, Quality Controls, and Special Construction Techniques 3.8.6-6 6.2.7 Testing and Inservice Surveillance Requirements 3.8.6-7 6.2.8 Safety Features 3.8.6-7 A SHELL TEMPERATURE TRANSIENTS 3.8A-1 B BUCKLING STRESS CRITERIA 3.8B-1 B.1 INTRODUCTION 3.8B-1 B.2 SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS 3.8B-1 B.2.1 Circular Cylindrical Shells Under Axial Compression 3.8B-1 B.2.2 Circular Cylindrical Shells in Circumferential Compression 3.8B-2 B.2.3 Circular Cylindrical Shells Under Torsion 3.8B-2 B.2.4 where a is the effective length and b is the circumference of the cylinder. The e of Contents 1-xiii
tion Title Page coefficient K's is given in Figure 3.8B-10.Circular Cylindrical Shells Under Bending 3.8B-3 B.2.5 Circular Cylindrical Shell Under Combined Loads 3.8B-3 B.3 SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND VERTICAL STIFFENERS 3.8B-5 B.4 SPHERICAL SHELLS 3.8B-7 B.4.1 The critical buckling stress in the spherical dome, except for external pressure, was determined by the following equation: 3.8B-7 B.4.2 Spherical Shell Under Combined Loads 3.8B-7 B.5 FACTOR OF SAFETY 3.8B-8 C DOCUMENTATION OF CB&I COMPUTER PROGRAMS 3.8C-1 C.1 INTRODUCTION 3.8C-1 C.2 PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN VALUE TECHNIQUE 3.8C-1 C.3 PROGRAM 1044-SEISMIC ANALYSIS of VESSEL APPENDAGES 3.8C-1 C.4 PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS DIGITIZED AT EQUAL INTERVALS 3.8C-3 C.5 PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS 3.8C-3 C.6 PROGRAM E1623-POST PROCESSOR PROGRAM FOR PROGRAM E1374 3.8C-4 C.7 PROGRAM E1374-SHELL DYNAMIC ANALYSIS 3.8C-5 C.7.1 Introduction 3.8C-5 C.8 PROGRAM E1622-LOAD GENERATION PREPROCESSOR FOR PROGRAM E1374 3.8C-6 C.9 PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION 3.8C-7 C.10 PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS 3.8C-7 C.11 PROGRAM 119-CHECK of FLANGE DESIGN 3.8C-7 C.12 PROGRAM 772-NOZZLE REINFORCEMENT CHECK 3.8C-7 C.13 PROGRAM 1027-WRC 107 STRESS INTENSITIES AT LOADED ATTACH-MENTS FOR SPHERES OR CYLINDERS WITH ROUND OR SQUARE AT-TACHMENT 3.8C-8 C.14 PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES 3.8C-8 D COMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS 3.8D-1 E CODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFI-TION AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF W FEATURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF RUCTURES INITIATED AFTER JULY 1979 3.8E-1 E.1 Application Codes and Standards 3.8E-1 E.2 Load Definitions 3.8E-1 E.3 Load Combinations - Concrete 3.8E-3 E.4 Load Combinations - Structural Steel 3.8E-5 Table of Contents
tion Title Page MECHANICAL SYSTEMS AND COMPONENTS 3.9-1 1 General Topic for Analysis of Seismic Category I ASME Code and Non-Code Items 3.9-1 1.1 Design Transients 3.9-1 1.2 Computer Programs Used in Analysis and Design 3.9-1 1.3 Experimental Stress Analysis 3.9-3 1.4 Consideration for the Evaluation of the Faulted Condition 3.9-3 2 Dynamic Testing and Analysis 3.9-4 2.1 Preoperational Vibration and Dynamic Effects Testing on Piping 3.9-4 2.2 Seismic Qualification Testing of Safety-Related Mechanical Equipment 3.9-6 2.3 Dynamic Response Analysis of Reactor Internals Under Operational Flow Transients and Steady-State Conditions 3.9-8 2.4 Preoperational Flow-Induced Vibration Testing of Reactor Internals 3.9-10 2.5 Dynamic System Analysis of the Reactor Internals Under Faulted Conditions 3.9-12 2.6 Correlations of Reactor Internals Vibration Tests With the Analytical Results 3.9-19 3 ASME Code Class 1, 2 and 3 Components, Component Supports and Core Support Structures 3.9-20 3.1 Loading Combinations, Design Transients, and Stress Limits 3.9-20 3.2 Pumps and Valve Operability Assurance 3.9-27 3.3 Design and Installation Details for Mounting of Pressure Relief Devices3.9-39 3.4 Component Supports 3.9-42 4 Control Rod System 3.9-46 4.1 Descriptive Information of CRDS 3.9-46 4.2 Applicable CRDS Design Specifications 3.9-47 4.3 Design Loadings, Stress Limits, and Allowable Deformations 3.9-47 4.4 CRDS Performance Assurance Program 3.9-47 5 Reactor Pressure Vessel Internals 3.9-47 5.1 Design Arrangements 3.9-47 5.2 Design Loading Conditions 3.9-47 5.3 Design Loading Categories 3.9-47 5.4 Design Basis 3.9-47 6 Inservice Testing of Pumps and Valves 3.9-47 0 SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL UIPMENT 3.10-1 0.1 Seismic Qualification Criteria 3.10-1
.2 Methods And Procedures For Qualifying Electrical Equipment And Instrumentation 3.10-4
.3 Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumen-tation and Cables 3.10-4
.3.1 Electrical Equipment and Instrumentation Assemblies 3.10-5 e of Contents 1-xv
tion Title Page
.3.2 Cable Trays and Supports 3.10-6
.3.3 Conduit and Supports 3.10-7
.3.4 Conduit Banks 3.10-8
.4 Operating License Review 3.10-8
.4.1 TVA Supplied Instrumentation and Electrical Equipment 3.10-8 1 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIP-NT 3.11-1
.1 Equipment Identification and Environmental Conditions 3.11-1
.1.1 Identification of Safety Systems and Justification 3.11-1
.1.2 Identification of Equipment in Harsh Environments 3.11-1
.2 Environmental Conditions 3.11-2
.2.1 Harsh Environment 3.11-2
.2.2 Mild Environment 3.11-3
.3 Electrical Equipment Within the Scope of 10 CFR 50.49 3.11-4
.4 Qualification Tests and Analyses 3.11-4
.5 Qualification Test Results 3.11-4
.6 Loss of Heating, Ventilating, and Air-Conditioning (HVAC) 3.11-4
.7 Estimated Chemical and Radiation Environment 3.11-4
.7.1 Chemical Spray 3.11-4
.7.2 Radiation 3.11-5 R_Section_4.pdf REACTOR
SUMMARY
DESCRIPTION 4.1-1 MECHANICAL DESIGN 4.2-1 1 Fuel 4.2-2 1.1 Design Bases 4.2-2 1.2 Design Description 4.2-5 1.3 Design Evaluation 4.2-9 1.4 Tests and Inspections 4.2-18 2 Reactor Vessel Internals 4.2-22 2.1 Design Bases 4.2-22 2.2 Description and Drawings 4.2-23 2.3 Design Loading Conditions 4.2-26 2.4 Design Loading Categories 4.2-27 2.5 Design Criteria Basis 4.2-28 3 Reactivity Control System 4.2-29 3.1 Design Bases 4.2-29 3.2 Design Description 4.2-32 3.3 Design Evaluation 4.2-42 3.4 Tests, Verification, and Inspections 4.2-52 3.5 Instrumentation Applications 4.2-55 Table of Contents
tion Title Page NUCLEAR DESIGN 4.3-1 1 DESIGN BASES 4.3-1 1.1 Fuel Burnup 4.3-2 1.2 Negative Reactivity Feedbacks (Reactivity Coefficient) 4.3-2 1.3 Control of Power Distribution 4.3-3 1.4 Maximum Controlled Reactivity Insertion Rate 4.3-4 1.5 Shutdown Margins With Vessel Head in Place 4.3-4 1.6 Shutdown Margin for Refueling 4.3-5 1.7 Stability 4.3-5 1.8 Anticipated Transients Without Trip 4.3-6 2 Description 4.3-6 2.1 Nuclear Design Description 4.3-6 2.2 Power Distributions 4.3-8 2.3 Reactivity Coefficients 4.3-19 2.4 Control Requirements 4.3-23 2.5 Control 4.3-25 2.6 Control Rod Patterns and Reactivity Worth 4.3-27 2.7 Criticality of Fuel Assemblies 4.3-28 2.8 Stability 4.3-33 2.9 Vessel Irradiation 4.3-38 3 Analytical Methods 4.3-38 3.1 Fuel Temperature (Doppler) Calculations 4.3-39 3.2 Macroscopic Group Constants 4.3-40 3.3 Spatial Few-Group Diffusion Calculations 4.3-41 THERMAL AND HYDRAULIC DESIGN 4.4-1 1 Design Bases 4.4-1 1.1 Departure from Nucleate Boiling Design Basis 4.4-1 1.2 Fuel Temperature Design Basis 4.4-2 1.3 Core Flow Design Basis 4.4-2 1.4 Hydrodynamic Stability Design Bases 4.4-3 1.5 Other Considerations 4.4-3 2 Description 4.4-3 2.1 Summary Comparison 4.4-3 2.2 Fuel and Cladding Temperatures 4.4-4 2.3 Critical Heat Flux Ratio or Departure from Nucleate Boiling Ratio and Mixing Technology4.4-6 2.4 Flux Tilt Considerations 4.4-13 2.5 Void Fraction Distribution 4.4-14 2.6 Core Coolant Flow Distribution 4.4-14 2.7 Core Pressure Drops and Hydraulic Loads 4.4-14 2.8 Correlation and Physical Data 4.4-15 2.9 Thermal Effects of Operational Transients 4.4-17 e of Contents 1-xvii
tion Title Page 2.10 Uncertainties in Estimates 4.4-18 2.11 Plant Configuration Data 4.4-20 3 EVALUATION 4.4-20 3.1 Core Hydraulics 4.4-20 3.2 Influence of Power Distribution 4.4-22 3.3 Core Thermal Response 4.4-24 3.4 Analytical Techniques 4.4-24 3.5 Hydrodynamic and Flow Power Coupled Instability 4.4-26 3.6 Temperature Transient Effects Analysis 4.4-28 3.7 Potentially Damaging Temperature Effects During Transients 4.4-29 3.8 Energy Release During Fuel Element Burnout 4.4-29 3.9 Deleted 4.4-30 3.10 Fuel Rod Behavior-Effects from Coolant Flow Blockage 4.4-30 4 Testing and Verification 4.4-31 4.1 Tests Prior to Initial Criticality 4.4-31 4.2 Initial Power and Plant Operation 4.4-31 4.3 Component and Fuel Inspections 4.4-32 5 Instrumentation Application 4.4-32 5.1 Incore Instrumentation 4.4-32 5.2 Overtemperature and Overpower T Instrumentation 4.4-32 5.3 Instrumentation to Limit Maximum Power Output 4.4-33 R_Section_5.pdf REACTOR COOLANT SYSTEM
SUMMARY
DESCRIPTION 5.1-1 1 Schematic Flow Diagram 5.1-6 2 Piping and Instrumentation Diagrams 5.1-6 3 Elevation Drawing 5.1-6 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 5.2-1 1 Design of Reactor Coolant Pressure Boundary Components 5.2-2 1.1 Performance Objectives 5.2-2 1.2 Design Parameters 5.2-3 1.3 Compliance with 10 CFR Part 50, Section 50.55a 5.2-4 1.4 Applicable Code Cases 5.2-4 1.5 Design Transients 5.2-5 1.6 Identification of Active Pumps and Valves 5.2-14 1.7 Design of Active Pumps and Valves 5.2-14 1.8 Inadvertent Operation of Valves 5.2-14 1.9 Stress and Pressure Limits 5.2-15 1.10 Stress Analysis for Structural Adequacy 5.2-15 1.11 Analysis Methods For Faulted Conditions 5.2-34 1.12 Protection Against Environmental Factors 5.2-34 1.13 Compliance With Code Requirements 5.2-34 ii Table of Contents
tion Title Page 1.14 Stress Analysis For Faulted Conditions Loadings 5.2-34 1.15 Stress Levels in Category I Systems 5.2-34 1.16 Analytical Methods for Stresses in Pumps and Valves 5.2-34 1.17 Analytical Methods for Evaluation of Pump Speed and Bearing Integrity 5.2-35 1.18 Operation of Active Valves Under Transient Loadings 5.2-35 2 Overpressurization Protection 5.2-35 2.1 Location of Pressure Relief Devices 5.2-35 2.2 Mounting of Pressure Relief Devices 5.2-35 2.3 Report on Overpressure Protection 5.2-35 2.4 RCS Pressure Control During Low Temperature Operation 5.2-37 3 General Material Considerations 5.2-40 3.1 Material Specifications 5.2-40 3.2 Compatibility With Reactor Coolant 5.2-41 3.3 Compatibility With External Insulation and Environmental Atmosphere 5.2-42 3.4 Chemistry of Reactor Coolant 5.2-42 4 Fracture Toughness 5.2-43 4.1 Compliance With Code Requirements 5.2-43 4.2 Acceptable Fracture Energy Levels 5.2-43 4.3 Operating Limitations During Startup and Shutdown 5.2-43 5 Austenitic Stainless Steel 5.2-46 5.1 Cleaning and Contamination Protection Procedures 5.2-46 5.2 Solution Heat Treatment Requirements 5.2-47 5.3 Material Inspection Program 5.2-48 5.4 Unstablilized Austenitic Stainless Steels 5.2-48 5.5 Prevention of Intergranular Attack of Unstabilized Austenitic Stainless Steels 5.2-48 5.6 Retesting Unstabilized Austenitic Stainless Steel Exposed to Sensitization Temperatures5.2-51 5.7 Control of Delta Ferrite in Austenitic Stainless Steel Welding 5.2-51 6 Pump Flywheels 5.2-53 6.1 Design Basis 5.2-53 6.2 Fabrication and Inspection 5.2-53 6.3 Acceptance Criteria and Compliance with Regulatory Guide 1.14 5.2-54 7 RCPB Leakage Detection Systems 5.2-55 7.1 Collection of Identified Leakage 5.2-55 7.2 Unidentified Leakage to Containment 5.2-56 7.3 Methods of Detection 5.2-56 7.4 Intersystem Leakage Detection 5.2-58 7.5 Unidentified Leakage System Sensitivity and Response Time 5.2-62 7.6 Seismic Capability 5.2-64 7.7 Indicators and Alarms 5.2-64 7.8 Testing 5.2-65 8 Inservice Inspection of ASME Code Class 1 Components 5.2-65 e of Contents 1-xix
tion Title Page 8.1 Components Subject to Examination and/or Test 5.2-65 8.2 Accessibility 5.2-65 8.3 Examination Techniques and Procedures 5.2-67 8.4 Inspection Intervals 5.2-67 8.5 Examination Categories and Requirements 5.2-67 8.6 Evaluation of Examination Results 5.2-67 8.7 System Pressure Tests 5.2-67 THERMAL HYDRAULIC SYSTEM DESIGN 5.3-1 1 Analytical Methods and Data 5.3-1 2 Operating Restrictions On Pumps 5.3-1 3 Power-Flow Operating Map (BWR) 5.3-1 4 Temperature-Power Operating Map 5.3-1 5 Load Following Characteristics 5.3-1 6 Transient Effects 5.3-1 7 Thermal and Hydraulic Characteristics Summary Table 5.3-1 REACTOR VESSEL AND APPURTENANCES 5.4-1 1 Design Bases 5.4-1 1.1 Codes and Specifications 5.4-1 1.2 Design Transients 5.4-1 1.3 Protection Against Non-Ductile Failure 5.4-2 1.4 Inspection 5.4-2 2 Description 5.4-2 2.1 Fabrication Processes 5.4-3 2.2 Protection of Closure Studs 5.4-4 3 Evaluation 5.4-4 3.1 Steady State Stresses 5.4-4 3.2 Fatigue Analysis Based on Transient Stresses 5.4-4 3.3 Thermal Stresses Due to Gamma Heating 5.4-4 3.4 Thermal Stresses Due to Loss of Coolant Accident 5.4-4 3.5 Heatup and Cooldown 5.4-4 3.6 Irradiation Surveillance Programs 5.4-4 3.7 Capability for Annealing the Reactor Vessel 5.4-12 4 Tests and Inspections 5.4-12 4.1 Ultrasonic Examinations 5.4-13 4.2 Penetrant Examinations 5.4-13 4.3 Magnetic Particle Examination 5.4-13 4.4 Inservice Inspection 5.4-14 COMPONENT AND SUBSYSTEM DESIGN 5.5-1 1 Reactor Coolant Pumps 5.5-1 1.1 Design Bases 5.5-1 1.2 Design Description 5.5-1 Table of Contents
tion Title Page 1.3 Design Evaluation 5.5-3 1.4 Tests and Inspections 5.5-7 2 Steam Generators 5.5-7 2.1 Design Basis 5.5-7 2.2 Design Description 5.5-8 2.3 Design Evaluation 5.5-9 2.4 Tests and Inspections 5.5-14 3 Reactor Coolant Piping 5.5-15 3.1 Design Bases 5.5-15 3.2 Design Description 5.5-16 3.3 Design Evaluation 5.5-18 3.4 Tests and Inspections 5.5-19 4 Steam Outlet Flow Restrictor (Steam Generator) 5.5-20 4.1 Design Basis 5.5-20 4.2 Description 5.5-20 4.3 Evaluation 5.5-20 4.4 Tests and Inspections 5.5-20 5 Main Steam Line Isolation System 5.5-20 6 Reactor Vessel Head Vent System 5.5-21 6.1 Design Basis 5.5-21 6.2 System Description 5.5-21 6.3 Design Evaluation 5.5-22 7 Residual Heat Removal System 5.5-23 7.1 Design Bases 5.5-24 7.2 System Description 5.5-24 7.3 Design Evaluation 5.5-28 7.4 Tests and Inspections 5.5-31 8 Reactor Coolant Cleanup System 5.5-31 9 Main Steam Line and Feedwater Piping 5.5-31 10 Pressurizer 5.5-32 10.1 Design Bases 5.5-32 10.2 Design Description 5.5-33 10.3 Design Evaluation 5.5-34 10.4 Tests and Inspections 5.5-36 11 Pressurizer Relief Tank 5.5-37 11.1 Design Bases 5.5-37 11.2 Design Description 5.5-37 11.3 Design Evaluation 5.5-38 12 Valves 5.5-38 12.1 Design Bases 5.5-38 12.2 Design Description 5.5-39 12.3 Design Evaluation 5.5-39 12.4 Tests and Inspections 5.5-39 13 Safety and Relief Valves 5.5-40 e of Contents 1-xxi
tion Title Page 13.1 Design Bases 5.5-40 13.2 Design Description 5.5-40 13.3 Design Evaluation 5.5-40 13.4 Tests and Inspections 5.5-41 14 Component Supports 5.5-41 14.1 Design Bases 5.5-41 14.2 Description 5.5-41 14.3 Evaluation 5.5-43 14.4 Tests and Inspections 5.5-43 INSTRUMENTATION APPLICATION 5.6-1 ENGINEERED SAFETY FEATURES ENGINEERED SAFETY FEATURE MATERIALS 6.1-1 1 Metallic Materials 6.1-1 1.1 Materials Selection and Fabrication 6.1-1 1.2 Composition, Compatibility, and Stability of Containment and Core Spray lants 6.1-2 2 Organic Materials 6.1-3 2.1 Electrical Insulation 6.1-3 2.2 Surface Coatings 6.1-3 2.3 Ice Condenser Equipment 6.1-4 2.4 Identification Tags 6.1-4 2.5 Valves and Instruments within Containment 6.1-4 2.6 Heating and Ventilating Door Seals 6.1-4 3 Post-Accident Chemistry 6.1-4 3.1 Boric Acid, H3BO3 6.1-5 3.2 Lithium Hydroxide 6.1-5 3.3 Sodium Tetraborate 6.1-5 3.4 Final Post-Accident Chemistry 6.1-5 4 Degree of Compliance with Regulatory Guide 1.54 for Paints and Coatings Inside tainment 6.1-5 CONTAINMENT SYSTEMS
.1 Containment Functional Design 6.2.1-1 1.1 Design Bases 6.2.1-1 1.1.1 Primary Containment Design Bases 6.2.1-1 1.2 Primary Containment System Design 6.2.1-3 1.3 Design Evaluation 6.2.1-3 1.3.1 Primary Containment Evaluation 6.2.1-3 1.3.2 General Description of Containment Pressure Analysis 6.2.1-4 1.3.3 Long-Term Containment Pressure Analysis 6.2.1-4 i Table of Contents
tion Title Page 1.3.4 Short-Term Blowdown Analysis 6.2.1-8 1.3.5 Effect of Steam Bypass 6.2.1-17 1.3.6 Mass and Energy Release Data 6.2.1-20 1.3.7 Accident Chronology 6.2.1-24 1.3.8 Energy Balance Tables 6.2.1-24 1.3.9 Containment Pressure Differentials 6.2.1-24 1.3.10 Steam Line Break Inside Containment 6.2.1-27 1.3.11 Maximum Reverse Pressure Differentials 6.2.1-33
.2 CONTAINMENT HEAT REMOVAL SYSTEMS 6.2.2-1 2.1 Design Bases 6.2.2-1 2.2 System Design 6.2.2-3 2.3 Design Evaluation 6.2.2-5 2.4 Testing and Inspections 6.2.2-7 2.5 Instrumentation Requirements 6.2.2-8 2.6 Materials 6.2.2-8
.3 Secondary Containment Functional Design 6.2.3-1 3.1 Design Bases 6.2.3-1 3.1.1 Secondary Containment Enclosures 6.2.3-1 3.1.2 Emergency Gas Treatment System (EGTS) 6.2.3-1 3.1.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-2 3.2 System Design 6.2.3-2 3.2.1 Secondary Containment Enclosures 6.2.3-2 3.2.2 Emergency Gas Treatment System (EGTS) 6.2.3-7 3.2.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-10 3.3 Design Evaluation 6.2.3-12 3.3.1 Secondary Containment Enclosures 6.2.3-12 3.3.2 Emergency Gas Treatment System (EGTS) 6.2.3-15 3.3.3 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-19 3.4 Test and Inspections 6.2.3-21 3.4.1 Emergency Gas Treatment System (EGTS) 6.2.3-21 3.4.2 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-22 3.5 Instrumentation Requirements 6.2.3-23 3.5.1 Emergency Gas Treatment System (EGTS) 6.2.3-23 3.5.2 Auxiliary Building Gas Treatment System (ABGTS) 6.2.3-23
.4 Containment Isolation Systems 6.2.4-1 4.1 Design Bases 6.2.4-1 4.2 System Design 6.2.4-4 4.2.1 Design Requirements 6.2.4-5 4.2.2 Containment Isolation Operation 6.2.4-5 4.2.3 Penetration Design 6.2.4-6 4.3 Design Evaluation 6.2.4-12 e of Contents 1-xxiii
tion Title Page 4.3.1 Possible Leakage Paths 6.2.4-14 4.4 Tests and Inspections 6.2.4-16
.5 Combustible Gas Control in Containment 6.2.5-1 5.1 Design Bases 6.2.5-1 5.2 System Design 6.2.5-2 5.3 Design Evaluation 6.2.5-5 5.4 Testing and Inspections 6.2.5-5 5.5 Instrumentation Application 6.2.5-5 5.6 Materials 6.2.5-6 5A Hydrogen Mitigation System 6.2.5-6 5A.1 Design Basis 6.2.5-6 5A.2 System Description 6.2.5-6 5A.3 Operation 6.2.5-7 5A.4 Safety Evaluation 6.2.5-7 5A.5 Testing 6.2.5-7
.6 Containment Leakage Testing 6.2.6-1 6.1 Containment Integrated Leak Rate Test 6.2.6-1 6.2 Containment Penetration Leakage Rate Test 6.2.6-2 6.3 Scheduling and Reporting of Periodic Tests 6.2.6-6 6.4 Special Testing Requirements 6.2.6-6 EMERGENCY CORE COOLING SYSTEM 6.3-1 1 Design Bases 6.3-1 1.1 Range of Coolant Ruptures and Leaks 6.3-1 1.2 Fission Product Decay Heat 6.3-2 1.3 Reactivity Required for Cold Shutdown 6.3-2 1.4 Capability To Meet Functional Requirements 6.3-2 2 System Design 6.3-2 2.1 Schematic Piping and Instrumentation Diagrams 6.3-2 2.2 Equipment and Component Design 6.3-2 2.3 Applicable Codes and Classifications 6.3-17 2.4 Materials Specifications and Compatibility 6.3-17 2.5 Design Pressures and Temperatures 6.3-17 2.6 Coolant Quantity 6.3-18 2.7 Pump Characteristics 6.3-18 2.8 Heat Exchanger Characteristics 6.3-18 2.9 ECCS Flow Diagrams 6.3-18 2.10 Relief Valves 6.3-18 2.11 System Reliability 6.3-18 2.12 Protection Provisions 6.3-23 2.13 Provisions for Performance Testing 6.3-23 2.14 Net Positive Suction Head 6.3-24 v Table of Contents
tion Title Page 2.15 Control of Motor-Operated Isolation Valves 6.3-24 2.16 Motor-Operated Valves and Controls 6.3-25 2.17 Manual Actions 6.3-25 2.18 Process Instrumentation 6.3-25 2.19 Materials 6.3-25 3 Performance Evaluation 6.3-25 3.1 Evaluation Model 6.3-25 3.2 ECCS Performance 6.3-26 3.3 Alternate Analysis Methods 6.3-26 3.4 Fuel Rod Perforations 6.3-27 3.5 Evaluation Model 6.3-27 3.6 Fuel Clad Effects 6.3-27 3.7 ECCS Performance 6.3-27 3.8 Peak Factors 6.3-27 3.9 Fuel Rod Perforations 6.3-27 3.10 Conformance with Interim Acceptance Criteria 6.3-27 3.11 Effects of ECCS Operation on the Core 6.3-28 3.12 Use of Dual Function Components 6.3-28 3.13 Lag Times 6.3-30 3.14 Thermal Shock Considerations 6.3-30 3.15 Limits on System Parameters 6.3-30 3.16 Use of RHR Spray 6.3-30 4 Tests and Inspections 6.3-31 4.1 Preoperational Tests 6.3-31 4.2 Component Testing 6.3-32 4.3 Periodic System Testing 6.3-32 5 Instrumentation Application 6.3-33 5.1 Temperature Indication 6.3-33 5.2 Pressure Indication 6.3-33 5.3 Flow Indication 6.3-34 5.4 Level Indication 6.3-34 5.5 Valve Position Indication 6.3-35 HABITABILITY SYSTEMS 6.4-1 1 Design Bases 6.4-1 2 System Design 6.4-1 2.1 Definition of MCRHS Area 6.4-1 2.2 Ventilation System Design 6.4-2 2.3 Leak Tightness 6.4-2 2.4 Interaction with Other Zones and Pressure-Containing Equipment 6.4-3 2.5 Shielding Design 6.4-4 2.6 Control Room Emergency Provisions 6.4-4 2.7 MCRHS Fire Protection 6.4-4 3 System Operational Procedures 6.4-5 e of Contents 1-xxv
tion Title Page 4 Design Evaluations 6.4-7 4.1 Radiological Protection 6.4-7 4.2 Toxic Gas Protection 6.4-7 5 Testing and Inspection 6.4-9 6 Instrumentation Requirements 6.4-9 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.5-1 1 Engineered Safety Feature (ESF) Filter Systems 6.5-1 1.1 Design Bases 6.5-1 1.2 System Design 6.5-2 1.3 Design Evaluation 6.5-5 1.4 Tests and Inspections 6.5-5 1.5 Instrumentation Requirements 6.5-6 1.6 Materials 6.5-7 2 Containment Spray System for Fission Product Cleanup 6.5-8 2.1 Design Bases 6.5-8 2.2 System Design 6.5-8 2.3 Design Evaluation 6.5-8 2.4 Tests and Inspections 6.5-8 2.5 Instrumentation Requirements 6.5-8 2.6 Materials 6.5-8 3 Fission Product Control Systems 6.5-8 3.1 Primary Containment 6.5-8 3.2 Secondary Containments 6.5-10 4 Ice Condenser as a Fission Product Cleanup System 6.5-10 4.1 Ice Condenser Design Basis (Fission Product Cleanup Function) 6.5-11 4.2 Ice Condenser System Design 6.5-11 4.3 Ice Condenser System Design Evaluation (Fission Product Cleanup Function) 6.5-11 4.4 Condenser System Tests and Inspections 6.5-13 4.5 Ice Condenser Materials 6.5-13 INSERVICE INSPECTION OF ASME CODE CLASS 2 AND 3 COMPONENTS
-1 1 Components Subject to Examination and/or Test 6.6-1 2 Accessibility 6.6-1 3 Examination Techniques and Procedures 6.6-1 4 Inspection Intervals 6.6-1 5 Examination Categories and Requirements 6.6-1 6 Evaluation of Examination Results 6.6-1 7 System Pressure Tests 6.6-2 8 Protection against Postulated Piping Failures 6.6-2 ICE CONDENSER SYSTEM 6.7-1 vi Table of Contents
tion Title Page 1 Floor Structure and Cooling System 6.7-1 1.1 Design Bases 6.7-1 1.2 Design Evaluation 6.7-5 2 Wall Panels 6.7-8 2.1 Design Basis 6.7-8 2.2 System Design 6.7-8 2.3 Design Evaluation 6.7-9 3 Lattice Frames and Support Columns 6.7-9 3.1 Design Basis 6.7-9 3.2 System Design 6.7-12 3.3 Design Evaluation 6.7-13 4 Ice Baskets 6.7-14 4.1 Design Basis 6.7-14 4.2 System Design 6.7-15 4.3 Design Evaluation 6.7-18 5 Crane and Rail Assembly 6.7-20 5.1 Design Basis 6.7-20 5.2 System Design 6.7-20 5.3 Design Evaluation 6.7-21 6 Refrigeration System 6.7-21 6.1 Design Basis 6.7-21 6.2 System Design 6.7-22 6.3 Design Evaluation 6.7-25 7 Air Handling Units 6.7-29 7.1 Design Basis 6.7-29 7.2 System Design 6.7-30 7.3 Design Evaluation 6.7-31 8 Lower Inlet Doors 6.7-31 8.1 Design Basis 6.7-31 8.2 System Design 6.7-34 8.3 Design Evaluation 6.7-36 9 Lower Support Structure 6.7-37 9.1 Design Basis 6.7-37 9.2 System Design 6.7-39 9.3 Design Evaluation 6.7-40 10 Top Deck and Doors 6.7-49 10.1 Design Basis 6.7-49 10.2 System Design 6.7-51 11 Intermediate Deck and Doors 6.7-54 11.1 Design Basis 6.7-54 11.2 System Design 6.7-55 11.3 Design Evaluation 6.7-56 12 Air Distribution Ducts 6.7-57 12.1 Design Basis 6.7-57 e of Contents 1-xxvii
tion Title Page 12.2 System Design 6.7-58 12.3 Design Evaluation 6.7-58 13 Equipment Access Door 6.7-58 13.1 Design Basis 6.7-58 13.2 System Design 6.7-59 13.3 Design Evaluation 6.7-59 14 Ice Technology, Ice Performance, and Ice Chemistry 6.7-59 14.1 Design Basis 6.7-59 14.2 System Design 6.7-59 14.3 Design Evaluation 6.7-60 15 Ice Condenser Instrumentation 6.7-65 15.1 Design Basis 6.7-65 15.2 Design Description 6.7-66 15.3 Design Evaluation 6.7-67 16 Ice Condenser Structural Design 6.7-68 16.1 Applicable Codes, Standards, and Specifications 6.7-68 16.2 Loads and Loading Combinations 6.7-68 16.3 Design and Analytical Procedures 6.7-68 16.4 Structural Acceptance Criteria 6.7-69 17 Seismic Analysis 6.7-70 17.1 Seismic Analysis Methods 6.7-70 17.2 Seismic Load Development 6.7-73 17.3 Vertical Seismic Response 6.7-74 18 Materials 6.7-74 18.1 Design Criteria 6.7-74 18.2 Environmental Effects 6.7-75 18.3 Compliance with 10 CFR 50, Appendix B 6.7-76 18.4 Materials Specifications 6.7-77 19 Tests and Inspections 6.7-78 AIR RETURN FANS 6.8-1 1 Design Bases 6.8-1 2 System Description 6.8-1 3 Safety Evaluation 6.8-2 4 Inspection and Testing 6.8-3 5 Instrumentation Requirements 6.8-3 R_Section_7.pdf INSTRUMENTATION AND CONTROLS INTRODUCTION 7.1-1 1 Identification of Safety-Related Systems 7.1-4 1.1 Safety-Related Systems 7.1-4 1.2 Safety-Related Display Instrumentation 7.1-5 1.3 Instrumentation and Control System Designers 7.1-5 viii Table of Contents
tion Title Page 1.4 Plant Comparison 7.1-5 2 Identification of Safety Criteria 7.1-5 2.1 Design Bases 7.1-8 2.2 Independence of Redundant Safety-Related Systems 7.1-12 2.3 Physical Identification of Safety-Related Equipment 7.1-15 2.4 Process Signal Isolation Relays 7.1-17 REACTOR TRIP SYSTEM 7.2-1 1 Description 7.2-1 1.1 System Description 7.2-1 1.2 Design Bases Information 7.2-17 1.3 Final Systems Drawings 7.2-19 2 Analyses 7.2-19 2.1 Evaluation of Design Limits 7.2-20 2.2 Evaluation of Compliance to Applicable Codes and Standards 7.2-23 2.3 Specific Control and Protection Interactions 7.2-33 2.4 Additional Postulated Accidents 7.2-36 3 Tests and Inspections 7.2-36 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM 7.3-1 1 Description 7.3-1 1.1 System Description 7.3-1 1.2 Design Bases Information 7.3-6 1.3 Final System Drawings 7.3-8 2 Analysis 7.3-8 2.1 System Reliability/Availability and Failure Mode and Effect Analyses 7.3-8 2.2 Compliance With Standards and Design Criteria 7.3-9 2.3 Further Considerations 7.3-16 2.4 Summary 7.3-17 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.4-1 1 Description 7.4-1 1.1 Monitoring Indicators 7.4-1 1.2 Controls 7.4-2 1.3 Equipment and Systems Available for Cold Shutdown 7.4-6 2 Analysis 7.4-6 INSTRUMENTATION SYSTEMS IMPORTANT TO SAFETY 7.5-1 1 Post Accident Monitoring Instrumentation (PAM) 7.5-1 1.1 System Description 7.5-1 1.2 Variable Types 7.5-1 1.3 Variable Categories 7.5-2 1.4 Design Bases 7.5-3 1.5 General Requirements 7.5-6 e of Contents 1-xxix
tion Title Page 1.6 Analysis 7.5-7 1.7 Tests and Inspections 7.5-7 2 Emergency Response Facilities Data System (ERFDS) 7.5-8 2.1 Safety Parameter Display System 7.5-8 2.2 Bypassed and Inoperable Status Indication System (BISI) 7.5-10 2.3 Technical Support Center and Nuclear Data Links 7.5-13 ALL OTHER SYSTEMS REQUIRED FOR SAFETY 7.6-1 1 120V ac and 125V dc Vital Plant Control Power System 7.6-1 2 Residual Heat Removal Isolation Valves 7.6-1 2.1 Description 7.6-1 2.2 Analysis 7.6-2 3 Refueling Interlocks 7.6-2 4 Deleted by Amendment 63. 7.6-2 5 Accumulator Motor-Operated Valves 7.6-2 6 Spurious Actuation Protection for Motor Operated Valves 7.6-3 7 Loose Part Monitoring System (LPMS) System Description 7.6-4 8 Interlocks for RCS Pressure Control During Low Temperature Operation 7.6-6 8.1 Analysis of Interlock 7.6-7 9 Switchover From Injection to Recirculation 7.6-8 9.1 Description of Instrumentation Used for Switchover 7.6-8 9.2 Initiation Circuit 7.6-9 9.3 Logic 7.6-9 9.4 Bypass 7.6-9 9.5 Interlocks 7.6-9 9.6 Sequence 7.6-10 9.7 Redundancy 7.6-10 9.8 Diversity 7.6-10 9.9 Actuated Devices 7.6-10 CONTROL SYSTEMS 7.7-1 1 Description 7.7-1 1.1 Control Rod Drive Reactor Control System 7.7-1 1.3 Plant Control Signals for Monitoring and Indicating 7.7-8 1.4 Plant Control System Interlocks 7.7-12 1.5 Pressurizer Pressure Control 7.7-13 1.6 Pressurizer Water Level Control 7.7-13 1.7 Steam Generator Water Level Control 7.7-14 1.8 Steam Dump Control 7.7-14 1.9 Incore Instrumentation 7.7-16 1.10 Control Board 7.7-18 1.11 Boron Concentration Measurement System 7.7-18 1.12 Anticipated Transient Without Scram Mitigation System Actuation 7.7-19 2 Analysis 7.7-20 x Table of Contents
tion Title Page 2.1 Separation of Protection and Control System 7.7-21 2.2 Response Considerations of Reactivity 7.7-21 2.3 Step Load Changes Without Steam Dump 7.7-24 2.4 Loading and Unloading 7.7-24 2.5 Load Rejection Furnished By Steam Dump System 7.7-25 2.6 Turbine-Generator Trip With Reactor Trip 7.7-25 3 Deleted by Amendment 81 7.7-26 INSTRUMENTATION IDENTIFICATIONS AND SYMBOLS 1 IDENTIFICATION SYSTEM 7A.1-1 1.1 FUNCTIONAL IDENTIFICATION 7A.1-1 1.1.1 Principal Function 7A.1-1 1.1.2 Measured Variable 7A.1-2 1.1.3 Readout or Passive Functions 7A.1-2 1.1.4 Modifying Letters 7A.1-2 1.1.5 Tagging Symbols 7A.1-2 1.1.6 Special Identifying Letters 7A.1-2 1.1.7 Pilot Lights 7A.1-2 1.2 SYSTEM IDENTIFICATION 7A.1-3 1.2.1 Identification Numbers 7A.1-3 1.3 LOOP IDENTIFICATION 7A.1-3 1.3.1 Instruments Common to Multiple Control Loops 7A.1-3 1.3.2 Multiple Instruments with a Common Function 7A.1-3 2 SYMBOLS 7A.1-3 2.1 INSTRUMENT SYMBOL 7A.1-4 R_Section_8 ELECTRIC POWER INTRODUCTION 8.1-1 1 Utility Grid and Interconnections 8.1-1 2 Plant Electrical Power System 8.1-1 3 Safety-Related Loads 8.1-2 4 Design Bases 8.1-3 5 Design Criteria and Standards 8.1-4 5.1 Design Criteria 8.1-5 5.2 Other Standards and Guides 8.1-5 5.3 Compliance to Regulatory Guides and IEEE Standards 8.1-8 OFFSITE (PREFERRED) POWER SYSTEM 8.2-1 1 Description 8.2-1 1.1 Preferred Power Supply 8.2-1 1.2 Transmission Lines, Switchyard, and Transformers 8.2-3 e of Contents 1-xxxi
tion Title Page 1.3 Arrangement of the Start Boards, Unit Boards, Common Boards, and Reactor Coolant Pump (RCP) Boards 8.2-4 1.4 Arrangement of Electrical Control Area (Nuclear Plant) 8.2-5 1.5 Switchyard Control and Relaying 8.2-6 1.6 6.9-kV Start Boards Control and Relaying 8.2-8 1.7 6.9-kV Unit and RCP Board Control and Relaying 8.2-10 1.8 Conformance with Standards 8.2-11 2 Analysis 8.2-19 ONSITE (STANDBY) POWER SYSTEM 8.3-1 1 AC Power System 8.3-1 1.1 Description 8.3-1 1.2 Analysis 8.3-28 1.3 Physical Identification of Safety-Related Equipment in AC Power Systems 8.3-38 1.4 Independence of Redundant ac Power Systems 8.3-38 2 DC Power System 8.3-55 2.1 Description 8.3-55 2.2 Analysis of Vital 125V DC Control Power Supply System 8.3-63 2.3 Physical Identification of Safety-Related Equipment in dc Power Systems 8.3-68 2.4 Independence of Redundant DC Power Systems 8.3-68 2.5 Sharing of Batteries Between Units 8.3-68 3 Fire Protection for Cable Systems 8.3-70 xii Table of Contents
tion Title Page Analysis of Submerged Electrical Equipment (During Post LOCA) Powered m Auxiliary Power System 8A-1 Analysis of Submerged Electrical Equipment (During Post LOCA) Powered m Instrumentation and Control Power System 8B-1 Deleted by Amendment 75 8C-1 IEEE STD 387-1984 FOR DIESEL-GENERATING UNITS APPLIED AS STAND-POWER 8D-1 Probability/Reliability Analysis of Protection Device Schemes for Associated Non-Class 1E Cables 8E-1 AUXILIARY SYSTEMS FUEL STORAGE AND HANDLING 9.1-1 1 New Fuel Storage 9.1-1 1.1 Design Bases 9.1-1 1.2 Facilities Description 9.1-1 1.3 Safety Evaluation 9.1-1 2 SPENT FUEL STORAGE 9.1-2 2.1 Design Bases 9.1-2 2.2 Facilities Description 9.1-2 2.3 Safety Evaluation 9.1-3 2.4 Materials 9.1-4 3 Spent Fuel Pool Cooling and Cleanup System (SFPCCS) 9.1-4 3.1 Design Bases 9.1-4 3.2 System Description 9.1-5 3.3 Safety Evaluation 9.1-8 3.4 Tests and Inspections 9.1-11 3.5 Instrument Application 9.1-11 4 FUEL HANDLING SYSTEM 9.1-12 4.1 Design Bases 9.1-12 4.2 System Description 9.1-13 4.3 Design Evaluation 9.1-20 4.4 Tests and Inspections 9.1-26 WATER SYSTEMS 9.2-1 1 Essential Raw Cooling Water (ERCW) 9.2-1 1.1 Design Bases 9.2-1 1.2 System Description 9.2-1 1.3 Safety Evaluation 9.2-4 e of Contents 1-xxxiii
tion Title Page 1.4 Tests and Inspections 9.2-7 1.5 Instrument Applications 9.2-7 1.6 Corrosion, Organic Fouling, and Environmental Qualification 9.2-9 1.7 Design Codes 9.2-11 2 Component Cooling System (CCS) 9.2-11 2.1 Design Bases 9.2-11 2.2 System Description 9.2-13 2.3 Components 9.2-16 2.4 Safety Evaluation 9.2-19 2.5 Leakage Provisions 9.2-19 2.6 Incidental Control 9.2-20 2.7 Instrument Applications 9.2-20 2.8 Malfunction Analysis 9.2-22 2.9 Tests and Inspections 9.2-23 2.10 Codes and Classification 9.2-23 3 Demineralized Water Makeup System 9.2-23 3.1 Design Bases 9.2-23 3.2 System Description 9.2-24 3.3 Safety Evaluation 9.2-25 3.4 Test and Inspection 9.2-25 3.5 Instrumentation Applications 9.2-25 4 Potable and Sanitary Water Systems 9.2-26 4.1 Potable Water System 9.2-26 4.2 Sanitary Water System 9.2-27 5 Ultimate Heat Sink 9.2-30 5.1 General Description 9.2-30 5.2 Design Bases 9.2-31 5.3 Safety Evaluation 9.2-32 5.4 Instrumentation Application 9.2-33 6 Condensate Storage Facilities 9.2-33 6.1 Design Bases 9.2-34 6.2 System Description 9.2-34 6.3 Safety Evaluation 9.2-35 6.4 Test and Inspections 9.2-35 6.5 Instrument Applications 9.2-36 7 Refueling Water Storage Tank 9.2-36 7.1 ECCS Pumps Net Positive Suction Head (NPSH) 9.2-37 8 Raw Cooling Water System 9.2-39 8.1 Design Bases 9.2-39 8.2 System Description 9.2-40 8.3 Safety Evaluation 9.2-42 8.4 Tests and Inspection 9.2-42 PROCESS AUXILIARIES 9.3-1 xiv Table of Contents
tion Title Page 1 Compressed Air System 9.3-1 1.1 Design Basis 9.3-1 1.2 System Description 9.3-1 1.3 Safety Evaluation 9.3-2 1.4 Tests and Inspections 9.3-5 1.5 Instrumentation Applications 9.3-5 2 Process Sampling System 9.3-5 2.1 Design Basis 9.3-5 2.2 System Description 9.3-5 2.3 Safety Evaluation 9.3-8 2.4 Tests and Inspections 9.3-8 2.5 Instrumentation Applications 9.3-8 2.6 Postaccident Sampling Subsystem 9.3-8 3 Equipment and Floor Drainage System 9.3-12 3.1 Design Bases 9.3-12 3.2 System Design 9.3-12 3.3 Drains - Reactor Building 9.3-15 3.4 Design Evaluation 9.3-15 3.5 Tests and Inspections 9.3-15 3.6 Instrumentation Application 9.3-15 3.7 Drain List 9.3-15 4 Chemical and Volume Control System 9.3-16 4.1 Design Bases 9.3-16 4.2 System Description 9.3-18 4.3 Safety Evaluation 9.3-36 4.4 Tests and Inspections 9.3-38 4.5 Instrumentation Application 9.3-39 5 Failed Fuel Detection System 9.3-39 5.1 Design Bases 9.3-39 5.2 System Description 9.3-40 5.3 Safety Evaluation 9.3-40 5.4 Tests and Inspections 9.3-40 5.5 Instrument Applications 9.3-40 6 Auxiliary Charging System 9.3-40 6.1 Design Bases 9.3-40 6.2 System Design Description 9.3-41 6.3 Design Evaluation 9.3-42 6.4 Tests and Inspection 9.3-42 6.5 Instrument Application 9.3-42 7 Boron Recycle System 9.3-42 7.1 Design Bases 9.3-43 7.2 System Description 9.3-44 7.3 Safety Evaluation 9.3-50 7.4 Tests and Inspections 9.3-50 e of Contents 1-xxxv
tion Title Page 7.5 Instrumentation Application 9.3-50 8 Heat Tracing 9.3-51 AIR CONDITIONING, HEATING, COOLING, AND VENTILATION SYSTEMS
-1 1 Control Room Area Ventilation System 9.4-1 1.1 Design Bases 9.4-1 1.2 System Description 9.4-3 1.3 Safety Evaluation 9.4-7 1.4 Tests and Inspection 9.4-8 2 Fuel Handling Area Ventilation System 9.4-8 2.1 Design Bases 9.4-8 2.2 System Description 9.4-10 2.3 Safety Evaluation 9.4-10 2.4 Inspection and Testing 9.4-11 3 Auxiliary and Radwaste Area Ventilation System 9.4-12 3.1 Design Bases 9.4-12 3.2 System Description 9.4-13 3.3 Safety Evaluation 9.4-19 3.4 Inspection and Testing Requirements 9.4-23 4 Turbine Building Area Ventilation System 9.4-23 4.1 Design Bases 9.4-23 4.2 System Description 9.4-24 4.3 Safety Evaluation 9.4-26 4.4 Inspection and Testing Requirements 9.4-26 5 Engineered Safety Feature Ventilation Systems 9.4-26 5.1 ERCW Intake Pumping Station 9.4-26 5.2 Diesel Generator Buildings 9.4-29 5.3 Auxiliary Building Safety Features Equipment Coolers 9.4-36 6 Reactor Building Purge Ventilating System 9.4-39 6.1 Design Bases 9.4-39 6.2 System Description 9.4-41 6.3 Safety Evaluation 9.4-43 6.4 Inspection and Testing Requirements 9.4-44 7 Containment Air Cooling System 9.4-45 7.1 Design Bases 9.4-45 7.2 System Description 9.4-46 7.3 Safety Evaluation 9.4-48 7.4 Test and Inspection Requirements 9.4-48 8 Condensate Demineralizer Waste Evaporator Building Environmental Control Sys-tem (Not required for Unit 1 operation) 9.4-49 8.1 Design Basis 9.4-49 8.2 System Description 9.4-49 8.3 Safety Evaluation 9.4-50 xvi Table of Contents
tion Title Page 8.4 Inspection and Testing Requirements 9.4-50 9 Postaccident Sampling Facility Environmental Control System 9.4-50 9.1 Design Basis 9.4-50 9.2 System Description 9.4-50 9.3 Safety Evaluation 9.4-51 9.4 Inspection and Testing Requirements 9.4-51 OTHER AUXILIARY SYSTEMS 9.5-1 1 Fire Protection System 9.5-1 1.1 Deleted by Amendment 87 9.5-1 1.2 Deleted by Amendment 87 9.5-1 1.3 Deleted by Amendment 87 9.5-1 1.4 Deleted by Amendment 87 9.5-1 1.5 Deleted by Amendment 87 9.5-1 2 Plant Communications System 9.5-1 2.1 Design Bases 9.5-1 2.2 General Description Intraplant Communications 9.5-1 2.3 General Description Interplant System 9.5-4 2.4 Evaluation 9.5-5 2.5 Inspection and Tests 9.5-8 3 Lighting Systems 9.5-9 3.1 Design Bases 9.5-9 3.2 Description of the Plant Lighting System 9.5-10 3.3 Diesel Generator Building Lighting System 9.5-11 3.4 Safety Related Functions of the Lighting Systems 9.5-12 3.5 Inspection and Testing Requirements 9.5-13 4 Diesel Generator Fuel Oil Storage and Transfer System 9.5-13 4.1 Design Basis 9.5-13 4.2 System Description 9.5-14 4.3 Safety Evaluation 9.5-16 4.4 Tests and Inspections 9.5-17 5 Diesel Generator Cooling Water System 9.5-18 5.1 Design Bases 9.5-18 5.2 System Description 9.5-18 5.3 Safety Evaluation 9.5-19 5.4 Tests and Inspections 9.5-19 6 Diesel Generator Starting System 9.5-19 6.1 Design Bases 9.5-19 6.2 System Description 9.5-20 6.3 Safety Evaluation 9.5-21 6.4 Tests and Inspections 9.5-21 7 Diesel Engine Lubrication System 9.5-21 7.1 Design Bases 9.5-21 7.2 System Description 9.5-23 e of Contents 1-xxxvii
tion Title Page 7.3 Safety Evaluation 9.5-25 7.4 Test and Inspections 9.5-25 8 Diesel Generator Combustion Air Intake and Exhaust System 9.5-25 8.1 Design Bases 9.5-25 8.2 System Descriptions 9.5-25 8.3 Safety Evaluation 9.5-26 8.4 Tests and Inspection 9.5-27 0 MAIN STEAM AND POWER CONVERSION SYSTEMS 1
SUMMARY
DESCRIPTION 10.1-1 2 TURBINE-GENERATOR 10.2-1
.1 Design Bases 10.2-1
.2 Description 10.2-1
.3 Turbine Rotor and Disc Integrity 10.2-5
.3.1 Materials Selection 10.2-5
.3.2 Fracture Toughness 10.2-7
.3.3 High Temperature Properties 10.2-9
.3.4 Turbine Disc Design 10.2-9
.3.5 Preservice Inspection 10.2-9
.3.6 Inservice Inspection 10.2-11
.4 Evaluation 10.2-13 3 MAIN STEAM SUPPLY SYSTEM 10.3-1
.1 Design Bases 10.3-1
.2 System Description 10.3-1
.2.1 System Design 10.3-1
.2.2 Material Compatibility, Codes, and Standards 10.3-2
.3 Design Evaluation 10.3-2
.4 Inspection and Testing Requirements 10.3-3
.5 Water Chemistry 10.3-3
.5.1 Purpose 10.3-3
.5.2 Feedwater Chemistry Specifications 10.3-4
.5.3 Operating Modes 10.3-4
.5.4 Effect of Water Chemistry on the Radioactive Iodine Partition Coefficient 10.3-5
.6 Steam and Feedwater System Materials 10.3-5
.6.1 Fracture Toughness 10.3-5
.6.2 Materials Selection and Fabrication 10.3-5 4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-1
.1 Main Condenser 10.4-1
.1.1 Design Bases 10.4-1 xviii Table of Contents
tion Title Page
.1.2 System Description 10.4-1
.1.3 Safety Evaluation 10.4-4
.1.4 Inspection and Testing 10.4-5
.1.5 Instrumentation 10.4-5
.2 Main Condenser Evacuation System 10.4-5
.2.1 Design Bases 10.4-5
.2.2 System Description 10.4-5
.2.3 Safety Evaluation 10.4-6
.2.4 Inspection and Testing 10.4-6
.2.5 Instrumentation 10.4-6
.3 Turbine Gland Sealing System 10.4-7
.3.1 Design Bases 10.4-7
.3.2 System Description 10.4-7
.3.3 Safety Evaluation 10.4-7
.3.4 Inspection and Testing 10.4-8
.3.5 Instrumentation 10.4-8
.4 Turbine Bypass System 10.4-8
.4.1 Design Bases 10.4-8
.4.2 System Description 10.4-8
.4.3 Safety Evaluation 10.4-9
.4.4 Inspection and Testing 10.4-10
.5 Condenser Circulating Water System 10.4-10
.5.1 Design Basis 10.4-11
.5.2 System Description 10.4-11
.5.3 Safety Evaluation 10.4-13
.5.4 Inspection and Testing 10.4-14
.5.5 Instrumentation Application 10.4-14
.6 Condensate Polishing Demineralizer System 10.4-15
.6.1 Design Bases - Power Conversion 10.4-15
.6.2 System Description 10.4-15
.6.3 Safety Evaluation 10.4-17
.6.4 Inspection and Testing 10.4-18
.6.5 Instrumentation 10.4-18
.7 Condensate and Feedwater Systems 10.4-19
.7.1 Design Bases 10.4-19
.7.2 System Description 10.4-19
.7.3 Safety Evaluation 10.4-26
.7.4 Inspection and Testing 10.4-28
.7.5 Instrumentation 10.4-28
.8 Steam Generator Blowdown System 10.4-28
.8.1 Design Bases 10.4-28 4.8.2 System Description and Operation 10.4-30
.8.3 Safety Evaluation 10.4-30
.8.4 Inspections and Testing 10.4-31 e of Contents 1-xxxix
tion Title Page
.9 Auxiliary Feedwater System 10.4-32
.9.1 Design Bases 10.4-32
.9.2 System Description 10.4-32
.9.3 Safety Evaluation 10.4-34
.9.4 Inspection and Testing Requirements 10.4-37
.9.5 Instrumentation Requirements 10.4-37
.10 Heater Drains and Vents 10.4-38
.10.1 Design Bases 10.4-38
.10.2 System Description 10.4-38
.10.3 Safety Evaluation 10.4-43
.10.4 Inspection and Testing 10.4-44
.10.5 Instrumentation 10.4-44 4.11 Steam Generator Wet Layup System 10.4-44
.11.1 Design Bases 10.4-44
.11.2 System Description 10.4-44
.11.3 Safety Evaluation 10.4-45
.11.4 Inspection and Testing 10.4-45
.11.5 Instrumentation 10.4-45 0 RADIOACTIVE WASTE MANAGEMENT 1 SOURCE TERMS 11.1-1
.1 Historical Design Model for Radioactivities in Systems and Components 11.1-1
.1.1 Reactor Coolant Historical Design Activity 11.1-1
.1.2 Volume Control Tank Historical Design Activity 11.1-2
.1.3 Pressurizer Historical Design Activity 11.1-2
.1.4 Gaseous Waste Processing System Historical Design Activities 11.1-2
.1.5 Secondary Coolant Historical Design Activities 11.1-2
.2 Realistic Model for Radioactivities in Systems and Components 11.1-2
.3 Plant Leakage 11.1-3
.4 Additional Sources 11.1-3 2 LIQUID WASTE SYSTEMS 11.2-1
.1 DESIGN OBJECTIVES 11.2-1
.2 SYSTEMS DESCRIPTIONS 11.2-1
.3 SYSTEM DESIGN 11.2-5
.3.1 Component Design 11.2-5
.3.2 Instrumentation Design 11.2-11
.4 Operating Procedure 11.2-11
.5 PERFORMANCE TESTS 11.2-18
.6 ESTIMATED RELEASES 11.2-18
.6.1 NRC Requirements 11.2-18
.6.2 Westinghouse PWR Release Experience 11.2-19
.6.3 Expected Liquid Waste Processing System Releases 11.2-19 Table of Contents
tion Title Page
.6.4 Turbine Building (TB) Drains 11.2-19
.6.5 Estimated Total Liquid Releases 11.2-20
.7 RELEASE POINTS 11.2-20
.8 DILUTION FACTORS 11.2-20
.9 ESTIMATED DOSES FROM RADIONUCLIDES IN LIQUID EFFLUENTS 11.2-21
.9.1 Assumptions and Calculational Methods 11.2-21
.9.2 Summary of Dose from Radionuclides in Liquid Effluents 11.2-23 3 GASEOUS WASTE SYSTEMS 11.3-1
.1 Design Bases 11.3-1
.2 SYSTEM DESCRIPTIONS 11.3-1
.3 SYSTEM DESIGN 11.3-3
.3.1 Component Design 11.3-3
.3.2 Instrumentation Design 11.3-3
.4 Operating Procedure 11.3-4
.5 Performance Tests 11.3-6
.6 Deleted by Amendment 77 11.3-6
.7 Radioactive Releases 11.3-6
.7.1 NRC Requirements 11.3-6
.7.2 Westinghouse PWR Experience Releases 11.3-6
.7.3 Expected Gaseous Waste Processing System Releases 11.3-6
.7.4 Releases from Ventilation Systems 11.3-7
.7.5 Estimated Total Releases 11.3-7
.8 Release Points 11.3-7
.9 Atmospheric Dilution 11.3-8
.10 Estimated Doses from Radionuclides in Gaseous Effluents 11.3-9
.10.1 Assumptions and Calculational Methods 11.3-9
.10.2 Summary of Annual Population Doses 11.3-11 4 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING STEM 11.4-1
.1 Design Objectives 11.4-1
.2 Continuous Monitors 11.4-2
.2.1 Liquid Monitors 11.4-2
.2.2 Gaseous Monitors 11.4-4
.3 SAMPLING 11.4-9
.4 CALIBRATION AND MAINTENANCE 11.4-9 5 SOLID WASTE MANAGEMENT SYSTEM 11.5-1
.1 Design Objectives 11.5-1
.2 System Inputs 11.5-1
.3 Systems Description 11.5-1
.3.1 Wet Active Waste Handling 11.5-1 e of Contents 1-xli
tion Title Page
.3.2 Dry Active Waste Handling 11.5-3
.3.3 Miscellaneous Waste Handling 11.5-4
.4 Equipment Operation 11.5-4
.4.1 Deleted 11.5-4
.4.2 Mobile Solidification System (MSS) 11.5-4
.5 Storage Facilities 11.5-4
.5.1 Inplant Storage Area 11.5-4
.5.2 Outside Radwaste Storage 11.5-5
.6 Shipment 11.5-5 6 Offsite Radiological Monitoring Program 11.6-1
.1 Expected Background 11.6-2
.2 Critical Pathways to Man 11.6-2
.2.1 Doses from Gaseous Effluents 11.6-3
.2.2 Internal Doses from Liquid Effluents 11.6-3
.3 Sampling Media, Locations, and Frequency 11.6-4
.4 Analytical Sensitivity 11.6-4
.5 Data Analysis and Presentation 11.6-4
.6 Program Statistical Sensitivity 11.6-4 TRITIUM CONTROL
.1 SYSTEM SOURCES 11A.1-1
.1.1 The Fission Source 11A.1-1
.1.2 Control Rod Source 11A.1-1
.1.3 Boric Acid Source 11A.1-1
.1.4 Burnable Shim Rod Source 11A.1-2
.2 Tritium Releases 11A.1-2
.3 Design Bases 11A.1-2
.4 Design Evaluation 11A.1-2
.5 Tritium Lead Test Assembly (This section to be provided at a later date) 11A.1-3
.6 Tritium Producing Burnable Absorber Rod (TPBAR) Source (Unit 1 Only) 11A.1-3 0 RADIATION PROTECTION 1 Assuring that Occupational Radiation Exposures Are as Low as Reasonably hievable (ALARA)12.1-1 Table of Contents
tion Title Page
.1 Policy Considerations 12.1-1
.2 Design Considerations 12.1-1
.3 ALARA Operational Considerations 12.1-1 2 RADIATION SOURCES 12.2-3
.1 Contained Sources 12.2-3
.1.1 Primary System Sources 12.2-3
.1.2 Auxiliary Systems Sources 12.2-4
.1.3 Sources During Refueling 12.2-10
.1.4 Maximum Hypothetical Accident (MHA) Sources 12.2-10
.1.5 Condensate Demineralizer Waste Evaporator 12.2-11
.2 Airborne Radioactive Material Sources 12.2-11 3 RADIATION PROTECTION DESIGN FEATURES 12.3-1
.1 Facility Design Features 12.3-1
.2 Shielding 12.3-3
.2.1 Design Objectives 12.3-3
.2.2 Design Description 12.3-3
.3 Ventilation 12.3-15
.3.1 Airflow Control 12.3-15
.3.2 Typical System 12.3-15
.3.3 Additional Radiation Controls 12.3-16
.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation 12.3-17 3.4.1 Area Radiation Monitoring Instrumentation 12.3-17
.4.2 Airborne Particulate Radioactivity Monitoring 12.3-19
.4.3 Deleted by Amendment 84. 12.3-23
.4.4 Special Radiation Monitors 12.3-23 4 DOSE ASSESSMENT 12.4-1 5 RADIOLOGICAL CONTROL (RADCON) PROGRAM 12.5-1
.1 Organization 12.5-1
.2 Equipment, Instrumentation, and Facilities 12.5-2
.3 Procedures 12.5-4 R_Section_13.pdf 0 CONDUCT OF OPERATIONS 1 ORGANIZATIONAL STRUCTURE OF APPLICANT 13.1-1
.1 Corporate Organization 13.1-1
.1.1 Design Responsibilities 13.1-1
.2 Nuclear Power 13.1-1
.2.1 Offsite Organizations 13.1-1
.2.2 Onsite Organization 13.1-2
.3 Qualification Requirements for Nuclear Facility Personnel 13.1-2 e of Contents 1-xliii
tion Title Page 2 TRAINING PROGRAMS 13.2-1
.1 Accredited Training Programs 13.2-1 2.2 General Employee and Fitness for Duty Training Programs 13.2-1
.3 Other Training Programs 13.2-2 3 Emergency Planning 13.3-1 4 REVIEW AND AUDIT 13.4-1
.1 Onsite Review 13.4-1
.2 Independent Review and Audit 13.4-1 5 SITE PROCEDURES 13.5-1
.1 SYSTEM OF SITE PROCEDURES 13.5-1
.1.1 Conformance with Regulatory Guide 1.33 13.5-1
.1.2 Preparation of Procedures 13.5-1
.1.3 Administrative Procedures 13.5-2
.2 Operating and Maintenance Procedures 13.5-2
.2.1 Operating Procedures 13.5-2
.2.2 Other Procedures 13.5-3 6 PLANT RECORDS 13.6-1
.1 Plant History 13.6-1
.2 Operating Records 13.6-1
.3 Event Records 13.6-1 7 NUCLEAR SECURITY 13.7-1
.1 Physical Security and Contingency Plan 13.7-1
.2 Personnel and Program Evaluation 13.7-1
.3 Physical Security of TPBARs 13.7-1 0 INITIAL TEST PROGRAM 1 SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY ALYSIS REPORT 14.1-1 2 TEST PROGRAM 14.2-1
.1 Summary of Test Program and Objectives 14.2-1
.2 Organization and Staffing 14.2-3
.2.1 Startup and Test Organization 14.2-3
.2.2 Plant Operating Organization 14.2-5
.2.3 Nuclear Assurance 14.2-6
.2.4 Major Participating Organizations 14.2-6
.2.5 Joint Test Group 14.2-7 v Table of Contents
tion Title Page
.2.6 Test Review Group 14.2-8
.2.7 Personnel Qualifications 14.2-9
.3 Test Procedures 14.2-9
.3.1 General 14.2-9
.3.2 Development of Procedures 14.2-10
.3.3 Review and Approval of Test Procedures 14.2-10
.3.4 Format of Test Procedures 14.2-10
.3.5 Test Procedure Revisions/Changes 14.2-11
.4 Conduct of Test Program 14.2-12
.4.1 Administrative Procedures 14.2-12
.4.2 Component Testing 14.2-12
.4.3 Preoperational and Acceptance Testing 14.2-13
.4.4 Power Ascension Testing 14.2-13
.4.5 Test Prerequisites 14.2-13
.4.6 Phase Evaluation 14.2-13
.4.7 Design Modifications 14.2-14
.5 Review, Evaluation, and Approval of Test Results 14.2-14
.6 Test Records 14.2-14
.7 Conformance of Test Programs with Regulatory Guides 14.2-15
.8 Utilization of Reactor Operating and Testing Experience in Development of Test Pro-gram 14.2-29
.9 Trial Use of Plant Operating and Emergency Procedures 14.2-30
.10 Initial Fuel Loading, Postloading Tests, Initial Criticality, Low Power Tests and Pow-er Ascension 14.2-30
.10.1 Fuel Loading 14.2-30
.10.2 Postloading Tests 14.2-33
.10.3 Initial Criticality 14.2-33
.10.4 Low Power Tests 14.2-33
.10.5 Power Ascension 14.2-34
.11 Test Program Schedule 14.2-34
.12 Individual Test Descriptions 14.2-35
.12.1 Preoperational Tests 14.2-35
.12.2 Power Ascension Tests 14.2-36 R_Section_15.pdf 0 ACCIDENT ANALYSES 1 CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS 1-1
.1 Optimization of Control Systems 15.1-2
.2 Initial Power Conditions Assumed In Accident Analyses 15.1-3
.2.1 Power Rating 15.1-3
.2.2 Initial Conditions 15.1-3
.2.3 Power Distribution 15.1-4
.3 Trip Points And Time Delays To Trip Assumed In Accident Analyses 15.1-4 e of Contents 1-xlv
tion Title Page
.4 Instrumentation Drift And Calorimetric Errors - Power Range Neutron Flux 15.1-5
.5 Rod Cluster Control Assembly Insertion Characteristic 15.1-5
.6 Reactivity Coefficients 15.1-6
.7 Fission Product Inventories 15.1-7
.7.1 Radioactivity in the Core 15.1-7
.7.2 Radioactivity in the Fuel Pellet Clad Gap 15.1-8 1.8 Residual Decay Heat 15.1-9
.8.1 Fission Product Decay Energy 15.1-9
.8.2 Decay of U-238 Capture Products 15.1-10
.8.3 Residual Fissions 15.1-11
.8.4 Distribution of Decay Heat Following Loss of Coolant Accident 15.1-11
.9 Computer Codes Utilized 15.1-11
.9.1 FACTRAN 15.1-11
.9.2 Deleted by Amendment 72. 15.1-12
.9.3 MARVEL 15.1-12
.9.4 LOFTRAN 15.1-13
.9.5 LEOPARD 15.1-14
.9.6 TURTLE 15.1-14
.9.7 TWINKLE 15.1-14
.9.8 Deleted by Amendment 80. 15.1-15
.9.9 THINC 15.1-15
.9.10 LOFTTR 15.1-15 2 CONDITION II - FAULTS OF MODERATE FREQUENCY 15.2-1
.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Subcritical Condition 15.2-2
.1.1 Identification of Causes and Accident Description 15.2-2
.1.2 Analysis of Effects and Consequences 15.2-3
.1.3 Conclusions 15.2-5
.2 UNCONTROLLED ROD CLUSTER CONTROL ASSEMBLY BANK WITH-DRAWAL AT POWER 15.2-5
.2.1 Identification of Causes and Accident Description 15.2-5
.2.2 Analysis of Effects and Consequences 15.2-7
.2.3 Conclusions 15.2-9
.3 ROD CLUSTER CONTROL ASSEMBLY MISALIGNMENT 15.2-9
.3.1 Identification of Causes and Accident Description 15.2-9
.3.2 Analysis of Effects and Consequences 15.2-11
.3.3 Conclusions 15.2-13
.4 UNCONTROLLED BORON DILUTION 15.2-13
.4.1 Identification of Causes and Accident Description 15.2-13
.4.2 Analysis of Effects and Consequences 15.2-14
.4.3 Conclusions 15.2-16
.5 PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW 15.2-17
.5.1 Identification of Causes and Accident Description 15.2-17 i Table of Contents
tion Title Page
.5.2 Analysis of Effects and Consequences 15.2-18
.5.3 Conclusions 15.2-19
.6 Startup of an Inactive Reactor Coolant Loop 15.2-19
.6.1 Identification of Causes and Accident Description 15.2-19
.6.2 Analysis of Effects and Consequences 15.2-19
.6.3 Conclusions 15.2-21
.7 LOSS OF EXTERNAL ELECTRICAL LOAD AND/OR TURBINE TRIP 15.2-21
.7.1 Identification of Causes and Accident Description 15.2-21
.7.2 Analysis of Effects and Consequences 15.2-22
.7.3 Conclusions 15.2-24
.8 LOSS OF NORMAL FEEDWATER 15.2-24
.8.1 Identification of Causes and Accident Description 15.2-24
.8.2 Analysis of Effects and Consequences 15.2-25
.8.3 Conclusions 15.2-28
.9 COINCIDENT LOSS OF ONSITE AND EXTERNAL (OFFSITE) AC POWER TO THE STATION - LOSS OF OFFSITE POWER TO THE STATION AUXILIARIES 15.2-28
.10 EXCESSIVE HEAT REMOVAL DUE TO FEEDWATER SYSTEM MALFUNC-TIONS 15.2-28
.10.1 Analysis of Effects and Consequences 15.2-28
.10.2 Conclusions 15.2-31
.11 Excessive Load Increase Incident 15.2-31
.11.1 Identification of Causes and Accident Description 15.2-31
.11.2 Analysis of Effects and Consequences 15.2-32
.11.3 Conclusions 15.2-33
.12 ACCIDENTAL DEPRESSURIZATION OF THE REACTOR COOLANT SYS-TEM 15.2-33
.12.1 Identification of Causes and Accident Description 15.2-33
.12.2 Analysis of Effects and Consequences 15.2-33
.12.3 Conclusions 15.2-34
.13 ACCIDENTAL DEPRESSURIZATION OF THE MAIN STEAM SYSTEM 15.2-34
.13.1 Identification of Causes and Accident Description 15.2-34
.13.2 Analysis of Effects and Consequences 15.2-36
.13.3 Conclusions 15.2-38
.14 Inadvertent Operation of Emergency Core Cooling System 15.2-38
.14.1 Identification of Causes and Accident Description 15.2-38
.14.2 Analysis of Effects and Consequences 15.2-39
.14.3 Conclusions 15.2-42 3 CONDITION III - INFREQUENT FAULTS 15.3-1
.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
.1.1 Identification of Causes and Accident Description 15.3-1 e of Contents 1-xlvii
tion Title Page
.1.2 Analysis of Effects and Consequences 15.3-2
.1.3 Reactor Coolant System Pipe Break Results 15.3-3
.1.4 Conclusions - Thermal Analysis 15.3-4
.2 Minor Secondary System Pipe Breaks 15.3-5
.2.1 Identification of Causes and Accident Description 15.3-5
.2.2 Analysis of Effects and Consequences 15.3-5
.2.3 Conclusions 15.3-5
.3 Inadvertent Loading of a Fuel Assembly Into an Improper Position 15.3-5
.3.1 Identification of Causes and Accident Description 15.3-5
.3.2 Analysis of Effects and Consequences 15.3-6
.3.3 Conclusions 15.3-7
.4 Complete Loss of Forced Reactor Coolant Flow 15.3-7
.4.1 Identification of Causes and Accident Description 15.3-7
.4.2 Analysis of Effects and Consequences 15.3-8
.4.3 Conclusions 15.3-9
.5 Waste Gas Decay Tank Rupture 15.3-9
.5.1 Identification of Causes and Accident Description 15.3-9
.5.2 Analysis of Effects and Consequences 15.3-10
.6 Single Rod Cluster Control Assembly Withdrawal at Full Power 15.3-10
.6.1 Identification of Causes and Accident Description 15.3-10
.6.2 Analysis of Effects and Consequences 15.3-11
.6.3 Conclusions 15.3-11 4 CONDITION IV - LIMITING FAULTS 15.4-1
.1 Major Reactor Coolant System Pipe Ruptures (Loss of Coolant Accident) 15.4-1
.1.1 Thermal Analysis 15.4-3
.1.2 Hydrogen Production and Accumulation 15.4-6
.2 Major Secondary System Pipe Rupture 15.4-12 4.2.1 Major Rupture of a Main Steam Line 15.4-12 4.2.2 Major Rupture of a Main Feedwater Pipe 15.4-19
.3 Steam Generator Tube Rupture 15.4-23
.3.1 Identification of Causes and Accident Description 15.4-23
.3.2 Analysis of Effects and Consequences 15.4-26
.3.3 Conclusions 15.4-32
.4 Single Reactor Coolant Pump Locked Rotor 15.4-32
.4.1 Identification of Causes and Accident Description 15.4-32
.4.2 Analysis of Effects and Consequences 15.4-32
.4.3 Conclusions 15.4-35
.5 Fuel Handling Accident 15.4-35
.5.1 Identification of Causes and Accident Description 15.4-35
.5.2 Analysis of Effects and Consequences 15.4-35 4.6 Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection) 15.4-35
.6.1 Identification of Causes and Accident Description 15.4-35 iii Table of Contents
tion Title Page
.6.2 Analysis of Effects and Consequences 15.4-39
.6.3 Conclusions 15.4-43 5 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS 15.5-1
.1 Environmental Consequences of a Postulated Loss of AC Power to the Plant Auxil-iaries 15.5-1
.2 Environmental Consequences of a Postulated Waste Gas Decay Tank Rupture 15.5-2
.3 Environmental Consequences of a Postulated Loss of Coolant Accident 15.5-2
.4 Environmental Consequences of a Postulated Steam Line Break 15.5-18
.5 Environmental Consequences of a Postulated Steam Generator Tube Rupture 15.5-19
.6 Environmental Consequences of a Postulated Fuel Handling Accident 15.5-20
.7 Environmental Consequences of a Postulated Rod Ejection Accident 15.5-22 R_Section_16.pdf 0 TECHNICAL SPECIFICATIONS 1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.1-1 2 PROPOSED FINAL TECHNICAL SPECIFICATIONS 16.2-1 3 RELOCATED SPECIFICATIONS 16.3-1
.1 Discussion 16.3-1
.2 Document Control 16.3-1
.3 Changes to the Relocated Specifications 16.3-1 R_Section_17.0.pdf 0 QUALITY ASSURANCE 1 Quality Assurance During Design and Construction 17.1-1
.1 TVA Organization 17.1-1
.2 Quality Assurance Program 17.1-1 1A WESTINGHOUSE NUCLEAR ENERGY SYSTEM DIVISIONS QUALITY ASSUR-CE PLAN 17.1-2 2 QUALITY ASSURANCE FOR STATION OPERATION 17.2-1
.1 Identification of Safety-Related Features 17.2-1 e of Contents 1-xlix
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