ML091400518

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

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

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Table of Contents 1-iWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page003_TVA_WB_FSAR_Section_1.pdf

1.0INTRODUCTION

AND GENERAL DESCRIPTION OF PLANT

1.1INTRODUCTION

1.1-1 1.2GENERAL PLANT DESCRIPTION1.2-11.2.1Site Characteristics1.2-11.2.1.1Location1.2-11.2.1.2Demography1.2-1 1.2.1.3Meteorology1.2-11.2.1.4Hydrology1.2-11.2.1.5Geology1.2-1 1.2.1.6Seismology1.2-21.2.2Facility Description1.2-21.2.2.1Design Criteria1.2-2 1.2.2.2Nuclear Steam Supply System (NSSS)1.2-21.2.2.3Control and Instrumentation1.2-41.2.2.4Fuel Handling System1.2-5 1.2.2.5Waste Processing System1.2-51.2.2.6Steam and Power Conversion System1.2-51.2.2.7Plant Electrical System1.2-6 1.2.2.8Cooling Water1.2-71.2.2.9Component Cooling System1.2-71.2.2.10Chemical and Volume Control System1.2-7 1.2.2.11Sampling and Water Quality System1.2-81.2.2.12Ventilation1.2-91.2.2.13Fire Protection System1.2-9 1.2.2.14Compressed Air Systems1.2-91.2.2.15Engineered Safety Features1.2-91.2.2.16Shared Facilities and Equipment1.2-10 1.2.3General Arrangement of Major Structures and Equipment1.2-131.3COMPARISON TABLES1.3-11.3.1Comparisons With Similar Facility Designs1.3-11.3.2Comparison Of Final And Preliminary Designs1.3-11.4IDENTIFICATION OF AGENTS AND CONTRACTORS1.4-11.5REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION1.5-11.5.117 x 17 Fuel Assembly1.5-11.5.1.1Rod Cluster Control Spider Tests1.5-1 1.5.1.2Grid Tests1.5-11.5.1.3Fuel Assembly Structural Tests1.5-11.5.1.4Guide Tube Tests1.5-2 1-iiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page1.5.1.5Prototype Assembly Tests1.5-21.5.2Heat Transfer Tests (17 x 17)1.5-21.5.2.117 x 17 LOCA Heat Transfer Tests1.5-21.5.2.2Departure from Nucleate Boiling (DNB)1.5-21.6MATERIAL INCORPORATED BY REFERENCE1.6-1 1.7ELECTRICAL, INSTRUMENTATIO N, AND CONTROL DRAWINGS1.7-11.8TECHNICAL QUALIFICATION OF APPLICANT1.8-11.9NUCLEAR PERFORMANCE PLAN1.9-11.9.1Corrective Action Plans1.9-11.9.1.1Cable Issues1.9-11.9.1.2Cable Tray and Cable Tray Supports1.9-1 1.9.1.3Design Baseline and Verification Program (DBVP)1.9-21.9.1.4Electrical Conduit and Conduit Support1.9-21.9.1.5Electrical Issues1.9-2 1.9.1.6Equipment Seismic Qualification1.9-21.9.1.7Fire Protection1.9-31.9.1.8Hanger and Analysis Update Program (HAAUP)1.9-31.9.1.9Heat Code Traceability1.9-31.9.1.10Heating, Ventilation, and Air Conditioning (HVAC) Duct Supports1.9-31.9.1.11Instrument Lines1.9-3 1.9.1.12Prestart Test Program1.9-31.9.1.13QA Records1.9-41.9.1.14Q-LIST1.9-4 1.9.1.15Replacement Items Program (RIP-CAP)1.9-41.9.1.16Seismic Analysis1.9-41.9.1.17Vendor Information1.9-4 1.9.1.18Welding1.9-51.9.2Special Programs (SPs)1.9-51.9.2.1Concrete Quality Program1.9-5 1.9.2.2Containment Cooling1.9-51.9.2.3Detailed Control room Design Review1.9-51.9.2.4Environmental Qualification Program1.9-6 1.9.2.5Master Fuse List1.9-61.9.2.6Mechanical Equipment Qualification1.9-61.9.2.7Microbiologically Induced Corrosion (MIC)1.9-61.9.2.8Moderate Energy Line Break Flooding (MELB)1.9-61.9.2.9Radiation Monitoring System1.9-6 1.9.2.10Soil Liquefaction1.9-71.9.2.11Use-As-Is CAQs1.9-71.

9.3REFERENCES

1.9-7004_TVA_WB_FSAR_Section_2_A.pdf005_TVA_WB_FSAR_Section_2_B.pdf 005_TVA_WB_FSAR_Section_2_B.pdf Table of Contents1-iiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.0SITE CHARACTERISTICS2.1GEOGRAPHY AND DEMOGRAPHY2.1-12.1.1Site Location and Description2.1-12.1.1.1Specification of Location2.1-1 2.1.1.2Site Area Map2.1-12.1.1.3Boundaries for Establishing Effluent Limits2.1-22.1.2Exclusion Area Authority And Control2.1-22.1.2.1Authority2.1-22.1.2.2Control of Activities Unrelated to Plant Operation2.1-22.1.2.3Arrangements for Traffic Control2.1-22.1.2.4Abandonment or Relocation of Roads2.1-22.1.3Population Distribution2.1-22.1.3.1Population Within 10 Miles2.1-3 2.1.3.2Population Between 10 and 50 Miles2.1-32.1.3.3Transient Population2.1-42.1.3.4Low Population Zone2.1-4 2.1.3.5Population Center2.1-52.1.3.6Population Density2.1-52.2NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES2.2-12.2.1Location and Route2.2-1 2.2.2Descriptions2.2-12.2.2.1Description of Facilities2.2-12.2.2.2Description of Products and Materials2.2-1 2.2.2.3Pipelines2.2-12.2.2.4Waterways2.2-12.2.2.5Airports2.2-2 2.2.2.6Projections of Industrial Growth2.2-22.2.3Evaluation of Potential Accidents2.2-22.2.

3.1REFERENCES

2.2-32.3METEOROLOGY2.3-12.3.1Regional Climate2.3-1 2.3.1.1Data Sources2.3-12.3.1.2General Climate2.3-12.3.1.3Severe Weather2.3-22.3.2Local Meteorology2.3-52.3.2.1Data Sources2.3-5 2.3.2.2Normal and Extreme Values of Meteorological Parameters2.3-62.3.2.3Potential Influence of the Plant and Its Facilities on Local Meteorology2.3-82.3.2.4Local Meteorological Conditions for Design and Operating Bases2.3-9 1-ivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.3.3Onsite Meteorological Measurements Program2.3-92.3.3.1Preoperational Program2.3-92.3.3.2Operational Meteorological Program2.3-122.3.3.3Onsite Data Summaries of Parameters for Dispersion Meteorology2.3-132.3.4Short-Term (Accident) Diffusion Estimates2.3-142.3.4.1Objective2.3-14 2.3.4.2Calculation Results2.3-172.3.5Long-Term (Routine) Diffusion Estimates2.3-18005_TVA_WB_FSAR_Section_2_B.pdf2.4HYDROLOGIC ENGINEERING2.4-12.4.1Hydrological Description2.4-12.4.1.1Sites and Facilities2.4-1 2.4.1.2Hydrosphere2.4-22.4.2Floods2.4-62.4.2.1Flood History2.4-6 2.4.2.2Flood Design Considerations2.4-72.4.2.3Effects of Local Intense Precipitation2.4-92.4.3Probable Maximum Flood (PMF) on Streams and Rivers2.4-122.4.3.1Probable Maximum Precipitation (PMP)2.4-132.4.3.2Precipitation Losses2.4-142.4.3.3Runoff and Stream Course Model2.4-14 2.4.3.4Probable Maximum Flood Flow2.4-182.4.3.5Water Level Determinations2.4-252.4.3.6Coincident Wind Wave Activity2.4-26 2.4.4Potential Dam Failures, Seismically Induced2.4-282.4.4.1Dam Failure Permutations2.4-282.4.4.2Unsteady Flow Analysis of Potential Dam Failures2.4-402.4.4.3Water Level at Plantsite2.4-402.4.5Probable Maximum Surge and Seiche Flooding2.4-402.4.6Probable Maximum Tsunami Flooding2.4-402.4.7Ice Effects2.4-412.4.8Cooling Water Canals and Reservoirs2.4-422.4.9Channel Diversions2.4-42 2.4.10Flooding Protection Requirements2.4-422.4.11Low Water Considerations2.4-442.4.11.1 Low Flow in Rivers and Streams2.4-442.4.11.2Low Water Resulting From Surges, Seiches, or Tsunami2.4-442.4.11.3Historical Low Water2.4-442.4.11.4Future Control2.4-452.4.11.5Plant Requirements2.4-452.4.12Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents 2.4-462.4.12.1Radioactive Liquid Wastes2.4-462.4.12.2Accidental Slug Releases to Surface Water 2.4-46 Table of Contents 1-vWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.4.12.3Effects on Ground Water2.4-482.4.13Groundwater2.4-492.4.13.1Description and On-Site Use2.4-492.4.13.2 Sources2.4-502.4.13.3Accident Effects2.4-512.4.13.4Monitoring and Safeguard Requirements2.4-522.4.13.5Design Basis for Subsurface Hydrostatic Loading2.4-522.4.14 Flooding Protection Requirements2.4-522.4.14.1Introduction2.4-53 2.4.14.2Plant Operation During Floods Above Grade2.4-542.4.14.3Warning Scheme2.4-562.4.14.4Preparation for Flood Mode2.4-56 2.4.14.5Equipment2.4-582.4.14.6Supplies2.4-592.4.14.7Plant Recovery2.4-59 2.4.14.8Warning Plan2.4-592.4.14.9Basis For Flood Protection Plan In Rainfall Floods2.4-602.4.14.10Basis for Flood Protection Plan in Seismic-Caused Dam Failures2.4-662.4.14.11Special Condition Allowance2.4-682.5GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING

SUMMARY

OF FOUNDATION CONDITIONS2.5-12.5.1Basic Geology and Seismic Information2.5-22.5.1.1Regional Geology2.5-3 2.5.1.2Site Geology2.5-272.5.2Vibratory Ground Motion2.5-342.5.2.1Seismicity2.5-34 2.5.2.2Geologic Structures and Tectonic Activity2.5-422.5.2.3Correlation of Earthquake Activity With Geologic Structures to Tectonic Prov-inces 2.5-422.5.2.4Maximum Earthquake Potential2.5-432.5.2.5Seismic Wave Transmission Characteristics of the Site2.5-452.5.2.6Safe Shutdown Earthquake2.5-45 2.5.2.7Operating Basis Earthquake2.5-452.5.3Surface Faulting2.5-452.5.3.1Geologic Conditions of the Site2.5-45 2.5.3.2Evidence of Fault Offset2.5-452.5.3.3Earthquakes Associated With Capable Faults2.5-542.5.3.4Investigations of Capable Faults2.5-542.5.3.5Correlation of Epicenters With Capable Faults2.5-562.5.3.6Description of Capable Faults2.5-56 2.5.3.7Zone Requiring Detailed Faulting Investigation2.5-562.5.3.8Results of Faulting Investigations2.5-562.5.4Stability of Subsurface Materials2.5-57 1-viTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page2.5.4.1Geologic Features2.5-572.5.4.2Properties of Subsurface Materials2.5-572.5.4.3Exploration2.5-902.5.4.4Geophysical Surveys2.5-902.5.4.5Excavations and Backfill2.5-932.5.4.6Groundwater Conditions2.5-101 2.5.4.7Response of Soil and Rock to Dynamic Loading2.5-1032.5.4.8Liquefaction Potential2.5-1032.5.4.9Earthquake Design Basis2.5-114 2.5.4.10Static Analysis2.5-1142.5.4.11Safety-Related Criteria for Foundations2.5-1152.5.4.12Techniques to Improve Subsurface Conditions2.5-1162.5.4.13Construction Notes2.5-1182.5.5Stability of Slopes2.5-1192.5.5.1Slope Characteristics2.5-119 2.5.5.2Design Criteria and Analysis2.5-1202.5.5.3Logs of Borings2.5-1282.5.5.4Compaction Specifications2.5-128 2.5.6Embankments2.5-123.0DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS3.1CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA3.1-13.1.1Introduction3.1-1 3.1.2WBNP Conformance with GDCs3.1-13.1.2.1Overall Requirements3.1-13.1.2.2Protection By Multiple Fission Product Barriers3.1-5 3.1.2.3Protection and Reactivity Control Systems3.1-123.1.2.4Fluid Systems3.1-173.1.2.5Reactor Containment3.1-30 3.1.2.6Fuel and Radioactivity Control3.1-353.2CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS3.2-1 3.2.1 Seismic Classifications 3.2-13.2.2System Quality Group Classification3.2-13.2.2.1Class A3.2-2 3.2.2.2Class B3.2-23.2.2.3Class C3.2-23.2.2.4Class D3.2-23.2.2.5Relationship of Applicable Codes to Safety Classification for Mechanical Com-ponents3.2-33.2.2.6Nonnuclear Safety Class (NNS)3.2-33.2.2.7Heating, Ventilation and Air Conditioning (HVAC) Safety Classification3.2-33.2.3Code Cases and Code Editions and Addenda3.2-3 Table of Contents1-viiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.2.3.1TVA Design and Fabrication3.2-33.2.3.2Purchased Materials and Components3.2-43.3Wind and Tornado Loading3.3-13.3.1Wind Loadings3.3-13.3.1.1Design Wind Velocity3.3-1 3.3.1.2Determination of Applied Force3.3-13.3.2Tornado Loadings3.3-13.3.2.1Applicable Design Parameters3.3-1 3.3.2.2Determination of Forces on Structures3.3-23.3.2.3Ability of Category I Structures to Pe rform Despite Failure of Structures Not Designed for Tornado Loads3.3-33.4WATER LEVEL (FLOOD) DESIGN3.4-13.4.1Flood Protection3.4-1 3.4.2Analysis Procedure3.4-13.5MISSILE PROTECTION3.5-13.5.1Missile Selection and Description3.5-23.5.1.1Internally Generated Missiles (Outside Containment)3.5-23.5.1.2Internally Generated Missiles (Inside Containment)3.5-53.5.1.3Turbine Missiles3.5-93.5.1.4Missiles Generated By Natural Phenomena3.5-273.5.1.5Missiles Generated by Events Near the Site.3.5-283.5.1.6Aircraft Hazards3.5-283.5.2Systems To Be Protected3.5-293.5.3Barrier Design Procedures3.5-29 3.5.3.1Additional Diesel Generator Building (And Other Category I Structures Added After July 1979)3.5-323.5AESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES3.5A-13.6PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POS-TULATED RUPTURE OF PIPING3.6-13.6APROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POS-TULATED RUPTURE OF PIPI NG (EXCLUDING REACTO R COOLANT SYSTEM PIP-ING)3.6A-13.6A.1Postulated Piping Failures in Fluid Systems Inside and Outside Containment3.6A-73.6A.1.1Design Bases3.6A-73.6A.1.2Description of Piping System Arrangement3.6A-103.6A.1.3Safety Evaluation3.6A-103.6A.2Determination of Break Lo cations and Dynamic Effects Associated with the Postu-lated Rupture of Piping3.6A-10 1-viiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.6A.2.1Criteria Used to Define Break and Crack Location and Configuration3.6A-103.6A.2.2Analytical Methods to Define Forcing Functions and Response Models3.6A-163.6A.2.3Dynamic Analysis Methods to Verify Integrity and Operability3.6A-193.6A.2.4Guard Pipe Assembly Design Criteria3.6A-223.6A.2.5Summary of Dynamic Analysis Results3.6A-233.6BPROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POS-TULATED RUPTURE OF PIPING3.6A-24 3.6B.1Break Locations And Dynamic Effects Associated With Postulated Primary Loop Pipe Rupture3.6A-243.6A.2Analytical Methods to Define Forcing Function and Response Models3.6A-253.6B.3Dynamic Analysis of the Reactor Cool ant Loop Piping Equipment Supports and Pipe Whip Restraints3.6A-273.7SEISMIC DESIGN3.7-13.7.1Seismic Input3.7-23.7.1.1Ground Response Spectra3.7-2 3.7.1.2Design Time Histories3.7-23.7.1.3Critical Damping Values3.7-33.7.1.4Supporting Media for Seismic Category I Structures3.7-3 3.7.2Seismic System Analysis3.7-33.7.2.1Seismic Analysis Methods3.7-43.7.2.2Natural Frequencies and Response Loads for NSSS3.7-22 3.7.2.3Procedures Used for Modeling3.7-223.7.2.4Soil/Structure Interaction3.7-233.7.2.5Development of Floor Response Spectra3.7-24 3.7.2.6Three Components of Earthquake Motion3.7-253.7.2.7Combination of Modal Responses3.7-263.7.2.8Interaction of Non-Cate gory I Structures With Seismic Category I Structures 3.7-283.7.2.9Effects of Parameter Variations on Floor Response Spectra3.7-293.7.2.10Use of Constant Vertical Load Factors3.7-29 3.7.2.11Methods Used to Account for Torsional Effects3.7-293.7.2.12Comparison of Responses - Set A versus Set B3.7-303.7.2.13Methods for Seismic Analysis of Dams3.7-30 3.7.2.14Determination of Category I Structure Overturning Moments3.7-303.7.2.15Analysis Procedure for Damping3.7-313.7.3Seismic Subsystem Analysis3.7-313.7.3.1Seismic Analysis Methods for Other Than NSSS3.7-313.7.3.2Determination of Number of Earthquake Cycles3.7-32 3.7.3.3Procedure Used for Modeling3.7-323.7.3.4Basis for Selection of Frequencies3.7-343.7.3.5Use of Equivalent Static Load Method of Analysis3.7-35 Table of Contents1-ixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.7.3.6Three Components of Earthquake Motion3.7-353.7.3.7Combination of Modal Responses3.7-363.7.3.8Analytical Procedures for Piping Other Than NSSS3.7-373.7.3.9Multiple Supported Equipment and Components with Distinct Inputs3.7-433.7.3.10Use of Constant Vertical Load Factors3.7-443.7.3.11Torsional Effects of Eccentric Masses3.7-453.7.3.12Buried Seismic Category I Piping Systems3.7-453.7.3.13Interaction of Other Piping with Seismic Category I Piping3.7-513.7.3.14Seismic Analyses for Fuel Elements , Control Rod Assemblies, Control Rod Drives, and Reactor Internals3.7-513.7.3.15Analysis Procedure for Damping3.7-533.7.3.16Seismic Analysis and Qualification of Category I Equipment Other Than NSSS 3.7-533.7.3.17Seismic Analysis and Design of HVAC Duct and Duct Support Systems3.7-563.7.4Seismic Instrumentation Program3.7-603.7.4.1Comparison with Regulatory Guide 1.123.7-603.7.4.2Location and Description of Instrumentation3.7-603.7.4.3Control Room Operator Notification3.7-643.7.4.4Comparison of Measured and Predicted Responses3.7-643.8DESIGN OF CATEGORY I STRUCTURES3.8.1Concrete Shield Building3.8.1-13.8.1.1Description of the Shield Building3.8.1-13.8.1.1.1Equipment Hatch Doors and Sleeves3.8.1-23.8.1.2Applicable Codes, Standards, and Specifications3.8.1-33.8.1.3Loads and Loading Combinations3.8.1-53.8.1.4Design and Analysis Procedures3.8.1-83.8.1.5Structural Acceptance Criteria3.8.1-103.8.1.6Materials, Quality Control and Special Construction Techniques3.8.1-113.8.1.6.1Materials3.8.1-113.8.1.6.2Quality Control3.8.1-12 3.8.1.6.3Construction Techniques3.8.1-133.8.1.7Testing and Inservice Surveillance Requirements3.8.1-133.8.2Steel Containment System3.8.2-13.8.2.1Description of the Containment and Penetrations3.8.2-13.8.2.1.1Description of the Containment3.8.2-13.8.2.1.2Description of Penetrations3.8.2-13.8.2.2Applicable Codes, Standards and Specifications3.8.2-33.8.2.2.1Codes3.8.2-33.8.2.2.2Design Specification Summary3.8.2-43.8.2.2.3NRC Regulatory Guides3.8.2-6 1-xTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.2.3Loads and Loading Combinations3.8.2-73.8.2.3.1Design Loads3.8.2-73.8.2.3.2Loading Conditions3.8.2-93.8.2.4 Design and Analysis Procedures3.8.2-113.8.2.4.1Introduction3.8.2-113.8.2.4.2Static Stress Analysis3.8.2-123.8.2.4.3Dynamic Seismic Analysis3.8.2-123.8.2.4.4Non-Axisymmetric Pressure Loading Analysis3.8.2-133.8.2.4.5Thermal Analysis3.8.2-14 3.8.2.4.6Penetrations Analysis3.8.2-143.8.2.4.7Interaction of Containment and Attached Equipment3.8.2-173.8.2.4.8Anchorage3.8.2-17 3.8.2.5Structural Acceptance Criteria3.8.2-183.8.2.5.1Margin of Safety3.8.2-183.8.2.6Materials, Quality Control, and Special Construction Techniques3.8.2-193.8.2.6.1Materials - General3.8.2-193.8.2.6.2Corrosion Protection3.8.2-223.8.2.6.3Protective Coatings3.8.2-24 3.8.2.6.4Tolerances3.8.2-253.8.2.6.5Vessel Material Inspection and Test3.8.2-253.8.2.6.6Impact Testing3.8.2-25 3.8.2.6.7Post-Weld Heat Treatment3.8.2-263.8.2.6.8Welding3.8.2-263.8.2.7Testing and Inservice Inspection Requirements3.8.2-263.8.2.7.1Bottom Liner Plates Test3.8.2-263.8.2.7.2Vertical Wall and Dome Tests3.8.2-263.8.2.7.3Soap Bubble Tests3.8.2-26 3.8.2.7.4Overpressure Tests3.8.2-263.8.2.7.5Leakage Rate Test3.8.2-273.8.2.7.6Operational Testing3.8.2-273.8.2.7.7Leak Testing Airlocks3.8.2-273.8.2.7.8Penetration Tests3.8.2-283.8.2.7.9Inservice Inspection Requirements3.8.2-283.8.3Concrete Interior Structure3.8.3-13.8.3.1Description of the Interior Structure3.8.3-1 3.8.3.1.1General3.8.3-13.8.3.1.2Containment Floor Structural Fill Slab3.8.3-13.8.3.1.3Reactor Cavity Wall3.8.3-23.8.3.1.4Compartment Above Reactor3.8.3-23.8.3.1.5Refueling Canal Walls and Floor (Divider Barrier)3.8.3-33.8.3.1.6Crane Wall3.8.3-33.8.3.1.7Steam Generator Compartments (Divider Barrier)3.8.3-53.8.3.1.8Pressurizer Compartment (Divider Barrier)3.8.3-5 Table of Contents1-xiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.3.1.9Divider Deck at Elevation 756.63 (Divider Barrier)3.8.3-53.8.3.1.10Ice Condenser Support Floor - Elevation 744.5 (Divider Barrier)3.8.3-53.8.3.1.11Penetrations Through the Divider Barrier Canal Gate3.8.3-63.8.3.2Applicable Codes, Standards and Specifications3.8.3-73.8.3.3Loads and Loading Combinations3.8.3-133.8.3.4Design and Analysis Procedures3.8.3-16 3.8.3.4.1General3.8.3-163.8.3.4.2Structural Fill Slab on Containment Floor3.8.3-163.8.3.4.3Reactor Cavity Wall3.8.3-16 3.8.3.4.4Compartment Above Reactor3.8.3-183.8.3.4.5Seals Between Upper and Lower Compartments3.8.3-183.8.3.4.6Refueling Canal Walls and Floor (Divider Barrier)3.8.3-193.8.3.4.7Crane Wall3.8.3-203.8.3.4.8Steam Generator Compartments (Divider Barrier)3.8.3-233.8.3.4.9Pressurizer Compartment (Divider Barrier)3.8.3-253.8.3.4.10Operating Deck at Elevation 756.63 (Divider Barrier)3.8.3-263.8.3.4.11Ice Condenser Support Floor El evation 744.5 (Divider Barrier)3.8.3-273.8.3.4.12Ice Condenser3.8.3-28 3.8.3.4.13Penetrations Through the Divider Barrier3.8.3-293.8.3.5Structural Acceptance Criteria3.8.3-313.8.3.5.1General3.8.3-31 3.8.3.5.2Structural Fill Slab on Containment Floor3.8.3-313.8.3.5.3Reactor Cavity Wall and Compartment Above Reactor3.8.3-323.8.3.5.4Refueling Canal Walls and Floor3.8.3-323.8.3.5.5Crane Wall3.8.3-323.8.3.5.6Steam Generator and Pressurizer Compartment3.8.3-323.8.3.5.7Operating Deck at Elevation 756.633.8.3-333.8.3.5.8Ice Condenser Support Floor Elevation 744.53.8.3-333.8.3.5.9Penetrations Through the Divider Barrier3.8.3-333.8.3.5.10Personnel Access Doors in Crane Wall3.8.3-333.8.3.5.11Seals Between Upper and Lower Compartments3.8.3-343.8.3.5.12Ice Condenser3.8.3-353.8.3.6Materials, Quality Control and Special Construction Techniques3.8.3-363.8.3.6.1Materials3.8.3-363.8.3.6.2Quality Control3.8.3-373.8.3.6.3Construction Technique3.8.3-38 3.8.3.6.4Ice Condenser3.8.3-383.8.3.7Testing and Inservice Surveillance Requirements3.8.3-413.8.3.8Environmental Effects3.8.3-413.8.3.9Interface Control 3.8.3-423.8.4Other Category I Structures3.8.4-13.8.4.1Description of the Structures3.8.4-13.8.4.1.1Auxiliary-Control Building3.8.4-1 1-xiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.4.1.2Diesel Generator Building3.8.4-133.8.4.1.3Category I Water Tanks and Pipe Tunnels3.8.4-143.8.4.1.4Class 1E Electrical System Manholes and Duct Runs3.8.4-153.8.4.1.5North Steam Valve Room3.8.4-163.8.4.1.6Intake Pumping Station and Retaining Walls3.8.4-173.8.4.1.7Miscellaneous Essential Raw Cooling Water (ERCW) Structures3.8.4-183.8.4.1.8Additional Diesel Generator Building3.8.4-193.8.4.2Applicable Codes, Standards, and Specifications3.8.4-203.8.4.2.1List of Documents3.8.4-20 3.8.4.2.2Basis for Use of the 1963 Edition of ACI 3183.8.4-223.8.4.3Loads and Loading Combinations3.8.4-253.8.4.3.1Description of Loads3.8.4-25 3.8.4.3.2Load Combinations and Allowable Stresses3.8.4-263.8.4.4Design and Analysis Procedures3.8.4-273.8.4.4.1Auxiliary-Control Building3.8.4-27 3.8.4.4.2Diesel Generator Building3.8.4-353.8.4.4.3Category I Water Tanks and Pipe Tunnels3.8.4-363.8.4.4.4Class 1E Electrical System Manholes3.8.4-373.8.4.4.5North Steam Valve Room3.8.4-373.8.4.4.6Intake Pumping Station and Reta ining Walls Pumping Station3.8.4-373.8.4.4.7Miscellaneous ERCW Structures3.8.4-383.8.4.4.8Additional Diesel Generator Building3.8.4-393.8.4.5Structural Acceptance Criteria3.8.4-413.8.4.5.1Concrete3.8.4-41 3.8.4.5.2Structural and Miscellaneous Steel3.8.4-413.8.4.5.3Miscellaneous Components of the Auxiliary Building3.8.4-423.8.4.5.4Intake Pumping Station Traveling Water Screens3.8.4-433.8.4.5.5Diesel Generator Building Doors and Bulkheads3.8.4-433.8.4.5.6Additional Diesel Generator Building Missile Barriers3.8.4-433.8.4.6Materials, Quality Control, and Special Construction Techniques General3.8.4-433.8.4.6.1Materials3.8.4-443.8.4.6.2Quality Control3.8.4-443.8.4.6.3Special Construction Techniques3.8.4-453.8.4.7Testing and Inservice Surveillance Requirements3.8.4-453.8.4.7.1Concrete and Struct ural Steel Portions of Structures3.8.4-453.8.4.7.2Miscellaneous Components of Auxiliary-Control Building3.8.4-453.8.4.7.3Deleted by Amendment 793.8.4-463.8.4.7.4Miscellaneous Components of the Intake Pumping Station3.8.4-463.8.5Foundations and Concrete Supports3.8.5-13.8.5.1Description of Foundations and Supports3.8.5-1 3.8.5.1.1Primary Containment3.8.5-13.8.5.1.2Foundations of Other Category I Structures3.8.5-13.8.5.2Applicable Codes, Standards, and Specifications3.8.5-4 Table of Contents1-xiiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.8.5.3Loads and Loading Combinations3.8.5-43.8.5.4Design and Analysis Procedure3.8.5-43.8.5.4.1Primary Containment Foundation3.8.5-43.8.5.4.2Auxiliary-Control Building3.8.5-43.8.5.4.3Intake Pumping Station3.8.5-53.8.5.4.4Soil-Supported Structures3.8.5-5 3.8.5.4.5Pile Supported Structures3.8.5-53.8.5.5Structural Acceptance Criteria3.8.5-53.8.5.5.1Primary Containment Foundation3.8.5-5 3.8.5.5.2Foundations of Other Category I Structures Auxiliary-Control Building3.8.5-63.8.5.6Materials, Quality Control, and Special Construction Techniques3.8.5-73.8.5.6.1Materials3.8.5-7 3.8.5.6.2Quality Control3.8.5-83.8.5.6.3Special Construction Techniques3.8.5-83.8.6Category I(L) Cranes3.8.6-13.8.6.1Polar Cranes3.8.6-13.8.6.1.1Description3.8.6-1 3.8.6.1.2Applicable Codes, Standards, and Specifications3.8.6-13.8.6.1.3Loads, Loading Combinations, and Allowable Stresses3.8.6-23.8.6.1.4Design and Analysis Procedure3.8.6-2 3.8.6.1.5Structural Acceptance Criteria3.8.6-23.8.6.1.6Materials, Quality Controls, and Special Construction Techniques3.8.6-33.8.6.1.7Testing and Inservice Surveillance Requirements3.8.6-33.8.6.1.8Safety Features3.8.6-33.8.6.2Auxiliary Building Crane3.8.6-43.8.6.2.1Description3.8.6-4 3.8.6.2.2Applicable Codes, Standards, and Specifications3.8.6-53.8.6.2.3Loads, Loading Combinations, and Allowable Stresses3.8.6-53.8.6.2.4Design and Analysis Procedure3.8.6-5 3.8.6.2.5Structural Acceptance Criteria3.8.6-63.8.6.2.6Materials, Quality Controls, and Special Construction Techniques3.8.6-63.8.6.2.7Testing and Inservice Surveillance Requirements3.8.6-73.8.6.2.8Safety Features3.8.6-73.8ASHELL TEMPERATURE TRANSIENTS3.8A-13.8BBUCKLING STRESS CRITERIA3.8B-13.8B.1INTRODUCTION3.8B-13.8B.2SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS3.8B-13.8B.2.1Circular Cylindrical Shells Under Axial Compression3.8B-13.8B.2.2Circular Cylindrical Shells in Circumferential Compression3.8B-23.8B.2.3Circular Cylindrical Shells Under Torsion3.8B-23.8B.2.4where a is the effective length and b is the circumference of the cylinder. The 1-xivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page coefficient K's is given in Figure 3.8B

-10.Circular Cylindric al Shells Under Bending3.8B-33.8B.2.5Circular Cylindrical Shell Under Combined Loads3.8B-33.8B.3SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND VERTICAL STIFFENERS3.8B-53.8B.4SPHERICAL SHELLS3.8B-7 3.8B.4.1The critical buckling stress in the spherical dome, except for external pressure, was determined by the following equation:3.8B-73.8B.4.2Spherical Shell Under Combined Loads3.8B-7 3.8B.5FACTOR OF SAFETY3.8B-83.8CDOCUMENTATION OF CB&I COMPUTER PROGRAMS3.8C-13.8C.1INTRODUCTION3.8C-13.8C.2PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN VALUE TECHNIQUE3.8C-13.8C.3PROGRAM 1044-SEISMIC ANALYS IS of VESSEL APPENDAGES3.8C-13.8C.4PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS DIGITIZED AT EQUAL INTERVALS3.8C-33.8C.5PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS3.8C-33.8C.6PROGRAM E1623-POST PROCESSO R PROGRAM FOR PROGRAM E1374 3.8C-43.8C.7PROGRAM E1374-SHELL DYNAMIC ANALYSIS3.8C-53.8C.7.1Introduction3.8C-53.8C.8PROGRAM E1622-LOAD GENERATI ON PREPROCESSOR FOR PROGRAM E13743.8C-63.8C.9PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION3.8C-73.8C.10PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS3.8C-73.8C.11PROGRAM 119-CHECK of FLANGE DESIGN3.8C-73.8C.12PROGRAM 772-NOZZLE REINFORCEMENT CHECK3.8C-73.8C.13PROGRAM 1027-WRC 107 STRESS INTEN SITIES AT L OADED ATTACH-MENTS FOR SPHERES OR CYLINDERS WITH ROUND OR SQUARE AT-TACHMENT3.8C-83.8C.14PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES3.8C-83.8DCOMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS3.8D-13.8ECODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFI-CATION AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF NEW FEATURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIATED AFTER JULY 19793.8E-13.8E.1Application Codes and Standards3.8E-13.8E.2Load Definitions3.8E-13.8E.3Load Combinations - Concrete3.8E-33.8E.4Load Combinations - Structural Steel3.8E-5 Table of Contents1-xvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.9MECHANICAL SYSTEMS AND COMPONENTS3.9-13.9.1General Topic for Analysis of Seismic Category I ASME Code and Non-Code Items 3.9-13.9.1.1Design Transients3.9-13.9.1.2Computer Programs Used in Analysis and Design3.9-13.9.1.3Experimental Stress Analysis3.9-33.9.1.4Consideration for the Evaluation of the Faulted Condition3.9-33.9.2Dynamic Testing and Analysis3.9-4 3.9.2.1Preoperational Vibration and Dynamic Effects Testing on Piping3.9-43.9.2.2Seismic Qualification Testing of Safety-Related Mechanical Equipment3.9-63.9.2.3Dynamic Response Analysis of Reactor Internals Under Operational Flow Transients and Steady-State Conditions3.9-83.9.2.4Preoperational Flow-Induced Vibration Testing of Reactor Internals3.9-103.9.2.5Dynamic System Analysis of the R eactor Internals Under Faulted Conditions 3.9-123.9.2.6Correlations of Reactor Internals Vibration Tests Wi th the Analytical Results 3.9-193.9.3ASME Code Class 1, 2 and 3 Component s, Component Supports and Core Support Structures3.9-203.9.3.1Loading Combinations, Design Transients, and Stress Limits3.9-20 3.9.3.2Pumps and Valve Operability Assurance3.9-273.9.3.3Design and Installation Details for Mounting of Pressure Relief Devices3.9-393.9.3.4Component Supports3.9-42 3.9.4Control Rod System3.9-463.9.4.1Descriptive Information of CRDS3.9-463.9.4.2Applicable CRDS Design Specifications3.9-473.9.4.3Design Loadings, Stress Limits, and Allowable Deformations3.9-473.9.4.4CRDS Performance Assurance Program3.9-473.9.5Reactor Pressure Vessel Internals3.9-473.9.5.1Design Arrangements3.9-473.9.5.2Design Loading Conditions3.9-473.9.5.3Design Loading Categories3.9-47 3.9.5.4Design Basis3.9-473.9.6Inservice Testing of Pumps and Valves3.9-473.10SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIPMENT3.10-13.10.1Seismic Qualification Criteria3.10-13.10.2Methods And Procedures For Qualifying Electrical Equipment And Instrumentation 3.10-43.10.3Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumen-tation and Cables3.10-43.10.3.1Electrical Equipment and Instrumentation Assemblies3.10-5 1-xviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page3.10.3.2Cable Trays and Supports3.10-63.10.3.3Conduit and Supports3.10-73.10.3.4Conduit Banks3.10-83.10.4Operating License Review3.10-83.10.4.1TVA Supplied Instrumentation and Electrical Equipment3.10-83.11ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIP-MENT3.11-13.11.1 Equipment Identification and Environmental Conditions3.11-13.11.1.1Identification of Safety Systems and Justification3.11-13.11.1.2Identification of Equipment in Harsh Environments3.11-13.11.2Environmental Conditions3.11-2 3.11.2.1Harsh Environment3.11-23.11.2.2Mild Environment3.11-33.11.3Electrical Equipment Within the Scope of 10 CFR 50.493.11-43.11.4Qualification Tests and Analyses3.11-43.11.5Qualification Test Results3.11-43.11.6Loss of Heating, Ventilating, and Air-Conditioning (HVAC)3.11-43.11.7Estimated Chemical and Radiation Environment3.11-43.11.7.1Chemical Spray3.11-43.11.7.2Radiation3.11-5013_TVA_WB_FSAR_Section_4.pdf4.0REACTOR4.1

SUMMARY

DESCRIPTION4.1-14.2MECHANICAL DESIGN4.2-14.2.1Fuel4.2-24.2.1.1Design Bases4.2-24.2.1.2Design Description4.2-5 4.2.1.3Design Evaluation4.2-94.2.1.4Tests and Inspections4.2-184.2.2Reactor Vessel Internals4.2-22 4.2.2.1Design Bases4.2-224.2.2.2Description and Drawings4.2-234.2.2.3Design Loading Conditions4.2-26 4.2.2.4Design Loading Categories4.2-274.2.2.5Design Criteria Basis4.2-284.2.3Reactivity Control System4.2-294.2.3.1Design Bases4.2-294.2.3.2Design Description4.2-32 4.2.3.3 Design Evaluation4.2-424.2.3.4Tests, Verification, and Inspections4.2-524.2.3.5Instrumentation Applications4.2-55 Table of Contents1-xviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page4.3NUCLEAR DESIGN4.3-14.3.1DESIGN BASES4.3-14.3.1.1Fuel Burnup4.3-24.3.1.2Negative Reactivity Feedback s (Reactivity Coefficient)4.3-24.3.1.3Control of Power Distribution4.3-34.3.1.4Maximum Controlled Reactivity Insertion Rate4.3-44.3.1.5Shutdown Margins With Vessel Head in Place4.3-44.3.1.6Shutdown Margin for Refueling4.3-5 4.3.1.7Stability4.3-54.3.1.8Anticipated Transients Without Trip4.3-64.3.2Description4.3-6 4.3.2.1Nuclear Design Description4.3-64.3.2.2Power Distributions4.3-84.3.2.3Reactivity Coefficients4.3-19 4.3.2.4Control Requirements4.3-234.3.2.5Control4.3-254.3.2.6Control Rod Patterns and Reactivity Worth4.3-274.3.2.7Criticality of Fuel Assemblies4.3-284.3.2.8Stability4.3-334.3.2.9Vessel Irradiation4.3-38 4.3.3Analytical Methods4.3-384.3.3.1Fuel Temperature (Doppler) Calculations4.3-394.3.3.2Macroscopic Group Constants4.3-404.3.3.3Spatial Few-Group Diffusion Calculations4.3-414.4THERMAL AND HYDRAULIC DESIGN4.4-14.4.1Design Bases4.4-14.4.1.1Departure from Nucleate Boiling Design Basis4.4-14.4.1.2Fuel Temperature Design Basis4.4-2 4.4.1.3Core Flow Design Basis4.4-24.4.1.4Hydrodynamic Stability Design Bases4.4-34.4.1.5Other Considerations4.4-3 4.4.2Description4.4-34.4.2.1Summary Comparison4.4-34.4.2.2Fuel and Cladding Temperatures4.4-4 4.4.2.3Critical Heat Flux Ratio or Departure from Nucleate Boiling Ratio and Mixing Technology4.4-64.4.2.4Flux Tilt Considerations4.4-134.4.2.5Void Fraction Distribution4.4-144.4.2.6Core Coolant Flow Distribution4.4-14 4.4.2.7Core Pressure Drops and Hydraulic Loads4.4-144.4.2.8Correlation and Physical Data4.4-154.4.2.9Thermal Effects of Operational Transients4.4-17 1-xviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page4.4.2.10Uncertainties in Estimates4.4-184.4.2.11Plant Configuration Data4.4-204.4.3EVALUATION4.4-204.4.3.1Core Hydraulics4.4-204.4.3.2Influence of Power Distribution4.4-224.4.3.3Core Thermal Response4.4-24 4.4.3.4Analytical Techniques4.4-244.4.3.5Hydrodynamic and Flow Power Coupled Instability4.4-264.4.3.6Temperature Transient Effects Analysis4.4-284.4.3.7Potentially Damaging Temperature Effects During Transients4.4-294.4.3.8Energy Release During Fuel Element Burnout4.4-294.4.3.9Deleted4.4-30 4.4.3.10 Fuel Rod Behavior-Effects from Coolant Flow Blockage4.4-304.4.4Testing and Verification4.4-314.4.4.1Tests Prior to Initial Criticality4.4-31 4.4.4.2Initial Power and Plant Operation4.4-314.4.4.3Component and Fuel Inspections4.4-324.4.5Instrumentation Application4.4-32 4.4.5.1Incore Instrumentation4.4-324.4.5.2Overtemperature and Overpower T Instrumentation4.4-324.4.5.3Instrumentation to Limit Maximum Power Output4.4-33014_TVA_WB_FSAR_Section_5.pdf5.0REACTOR COOLANT SYSTEM5.1

SUMMARY

DESCRIPTION5.1-15.1.1Schematic Flow Diagram5.1-65.1.2Piping and Instrumentation Diagrams5.1-6 5.1.3Elevation Drawing5.1-65.2INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY5.2-15.2.1Design of Reactor Coolant Pressure Boundary Components5.2-25.2.1.1Performance Objectives5.2-25.2.1.2Design Parameters5.2-3 5.2.1.3Compliance with 10 CFR Part 50, Section 50.55a5.2-45.2.1.4Applicable Code Cases5.2-45.2.1.5Design Transients5.2-5 5.2.1.6Identification of Active Pumps and Valves5.2-145.2.1.7Design of Active Pumps and Valves5.2-145.2.1.8Inadvertent Operation of Valves5.2-145.2.1.9Stress and Pressure Limits5.2-155.2.1.10Stress Analysis for Structural Adequacy5.2-15 5.2.1.11Analysis Methods For Faulted Conditions5.2-345.2.1.12Protection Against Environmental Factors5.2-345.2.1.13Compliance With Code Requirements5.2-34 Table of Contents1-xixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.2.1.14Stress Analysis For Faulted Conditions Loadings5.2-345.2.1.15Stress Levels in Category I Systems5.2-345.2.1.16Analytical Methods for Stresses in Pumps and Valves5.2-345.2.1.17Analytical Methods for Evaluation of Pump Speed and Bearing Integrity5.2-355.2.1.18Operation of Active Valves Under Transient Loadings5.2-355.2.2Overpressurization Protection5.2-355.2.2.1Location of Pressure Relief Devices5.2-355.2.2.2Mounting of Pressure Relief Devices5.2-355.2.2.3Report on Overpressure Protection5.2-355.2.2.4RCS Pressure Control During Low Temperature Operation5.2-375.2.3General Material Considerations5.2-40 5.2.3.1Material Specifications5.2-405.2.3.2Compatibility With Reactor Coolant5.2-415.2.3.3Compatibility With External Insulation and Environmental Atmosphere5.2-425.2.3.4Chemistry of Reactor Coolant5.2-425.2.4Fracture Toughness5.2-435.2.4.1Compliance With Code Requirements5.2-43 5.2.4.2Acceptable Fracture Energy Levels5.2-435.2.4.3Operating Limitations During Startup and Shutdown5.2-435.2.5Austenitic Stainless Steel5.2-46 5.2.5.1Cleaning and Contamination Protection Procedures5.2-465.2.5.2Solution Heat Treatment Requirements5.2-475.2.5.3Material Inspection Program5.2-48 5.2.5.4Unstablilized Austenitic Stainless Steels5.2-485.2.5.5Prevention of Intergranular Attack of Unstabilized Austenit ic Stainless Steels 5.2-485.2.5.6Retesting Unstabilized Au stenitic Stainless Steel Exposed to Sensitization Temperatures5.2-515.2.5.7Control of Delta Ferrite in Austenitic Stainless Steel Welding5.2-515.2.6Pump Flywheels5.2-535.2.6.1Design Basis5.2-535.2.6.2Fabrication and Inspection5.2-53 5.2.6.3Acceptance Criteria and Compliance with Regulatory Guide 1.145.2-545.2.7RCPB Leakage Detection Systems5.2-555.2.7.1Collection of Identified Leakage5.2-55 5.2.7.2Unidentified Leakage to Containment5.2-565.2.7.3Methods of Detection5.2-565.2.7.4Intersystem Leakage Detection5.2-585.2.7.5Unidentified Leakage System Sensitivity and Response Time5.2-625.2.7.6Seismic Capability5.2-64 5.2.7.7Indicators and Alarms5.2-645.2.7.8Testing5.2-655.2.8Inservice Inspection of ASME Code Class 1 Components5.2-65 1-xxTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.2.8.1Components Subject to Examination and/or Test5.2-655.2.8.2Accessibility5.2-655.2.8.3Examination Techniques and Procedures5.2-675.2.8.4Inspection Intervals5.2-675.2.8.5Examination Categories and Requirements5.2-675.2.8.6Evaluation of Examination Results5.2-675.2.8.7System Pressure Tests5.2-675.3THERMAL HYDRAULIC SYSTEM DESIGN5.3-15.3.1Analytical Methods and Data5.3-15.3.2Operating Restrictions On Pumps5.3-15.3.3Power-Flow Operating Map (BWR)5.3-1 5.3.4Temperature-Power Operating Map5.3-15.3.5Load Following Characteristics5.3-15.3.6Transient Effects5.3-1 5.3.7Thermal and Hydraulic Characteristics Summary Table5.3-15.4REACTOR VESSEL AND APPURTENANCES5.4-15.4.1Design Bases5.4-15.4.1.1Codes and Specifications5.4-15.4.1.2Design Transients5.4-1 5.4.1.3Protection Against Non-Ductile Failure5.4-25.4.1.4Inspection5.4-25.4.2Description5.4-2 5.4.2.1Fabrication Processes5.4-35.4.2.2Protection of Closure Studs5.4-45.4.3Evaluation5.4-4 5.4.3.1Steady State Stresses5.4-45.4.3.2Fatigue Analysis Based on Transient Stresses5.4-45.4.3.3Thermal Stresses Due to Gamma Heating5.4-4 5.4.3.4Thermal Stresses Due to Loss of Coolant Accident5.4-45.4.3.5Heatup and Cooldown5.4-45.4.3.6Irradiation Surveillance Programs5.4-4 5.4.3.7Capability for Annealing the Reactor Vessel5.4-125.4.4Tests and Inspections5.4-125.4.4.1Ultrasonic Examinations5.4-13 5.4.4.2Penetrant Examinations5.4-135.4.4.3Magnetic Particle Examination5.4-135.4.4.4Inservice Inspection5.4-145.5COMPONENT AND SUBSYSTEM DESIGN5.5-15.5.1Reactor Coolant Pumps5.5-15.5.1.1Design Bases5.5-15.5.1.2Design Description5.5-1 Table of Contents1-xxiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.5.1.3Design Evaluation5.5-35.5.1.4Tests and Inspections5.5-75.5.2Steam Generators5.5-75.5.2.1Design Basis5.5-75.5.2.2Design Description5.5-85.5.2.3Design Evaluation5.5-9 5.5.2.4Tests and Inspections5.5-145.5.3Reactor Coolant Piping5.5-155.5.3.1Design Bases5.5-15 5.5.3.2Design Description5.5-165.5.3.3Design Evaluation5.5-185.5.3.4Tests and Inspections5.5-19 5.5.4Steam Outlet Flow Restrictor (Steam Generator)5.5-205.5.4.1Design Basis5.5-205.5.4.2Description5.5-20 5.5.4.3Evaluation5.5-205.5.4.4Tests and Inspections5.5-205.5.5Main Steam Line Isolation System5.5-20 5.5.6Reactor Vessel Head Vent System5.5-215.5.6.1Design Basis5.5-215.5.6.2System Description5.5-21 5.5.6.3Design Evaluation5.5-225.5.7Residual Heat Removal System5.5-235.5.7.1Design Bases5.5-24 5.5.7.2System Description5.5-245.5.7.3Design Evaluation5.5-285.5.7.4Tests and Inspections5.5-31 5.5.8Reactor Coolant Cleanup System5.5-315.5.9Main Steam Line and Feedwater Piping5.5-315.5.10Pressurizer5.5-32 5.5.10.1Design Bases5.5-325.5.10.2Design Description5.5-335.5.10.3Design Evaluation5.5-34 5.5.10.4Tests and Inspections5.5-365.5.11Pressurizer Relief Tank5.5-375.5.11.1Design Bases5.5-37 5.5.11.2Design Description5.5-375.5.11.3Design Evaluation5.5-385.5.12Valves5.5-385.5.12.1Design Bases5.5-385.5.12.2Design Description5.5-39 5.5.12.3Design Evaluation5.5-395.5.12.4Tests and Inspections5.5-395.5.13Safety and Relief Valves5.5-40 1-xxiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page5.5.13.1Design Bases5.5-405.5.13.2Design Description5.5-405.5.13.3Design Evaluation5.5-405.5.13.4Tests and Inspections5.5-415.5.14Component Supports5.5-415.5.14.1Design Bases5.5-41 5.5.14.2Description5.5-415.5.14.3Evaluation5.5-435.5.14.4Tests and Inspections5.5-435.6INSTRUMENTATION APPLICATION5.6-16.0ENGINEERED SAFETY FEATURES6.1ENGINEERED SAFETY FEATURE MATERIALS6.1-16.1.1Metallic Materials6.1-16.1.1.1Materials Selection and Fabrication6.1-16.1.1.2Composition, Compatibility, and Stabi lity of Containment and Core Spray Coolants 6.1-26.1.2Organic Materials6.1-36.1.2.1Electrical Insulation6.1-3 6.1.2.2Surface Coatings6.1-36.1.2.3Ice Condenser Equipment6.1-46.1.2.4Identification Tags6.1-4 6.1.2.5Valves and Instruments within Containment6.1-46.1.2.6Heating and Ventilating Door Seals6.1-46.1.3Post-Accident Chemistry6.1-4 6.1.3.1Boric Acid, H3BO36.1-56.1.3.2Lithium Hydroxide6.1-56.1.3.3Sodium Tetraborate6.1-5 6.1.3.4Final Post-Accident Chemistry6.1-56.1.4Degree of Compliance with Regulatory Gu ide 1.54 for Paints and Coatings Inside Containment6.1-56.2CONTAINMENT SYSTEMS6.2.1Containment Functional Design6.2.1-16.2.1.1Design Bases6.2.1-16.2.1.1.1Primary Containment Design Bases6.2.1-16.2.1.2Primary Containment System Design6.2.1-36.2.1.3Design Evaluation6.2.1-3 6.2.1.3.1Primary Containment Evaluation6.2.1-36.2.1.3.2General Description of Containment Pressure Analysis6.2.1-46.2.1.3.3Long-Term Containment Pressure Analysis6.2.1-4 Table of Contents1-xxiiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.2.1.3.4Short-Term Blowdown Analysis6.2.1-86.2.1.3.5Effect of Steam Bypass6.2.1-176.2.1.3.6Mass and Energy Release Data6.2.1-206.2.1.3.7Accident Chronology6.2.1-246.2.1.3.8Energy Balance Tables6.2.1-246.2.1.3.9Containment Pressure Differentials6.2.1-246.2.1.3.10Steam Line Break Inside Containment6.2.1-276.2.1.3.11Maximum Reverse Pressure Differentials6.2.1-336.2.2CONTAINMENT HEAT REMOVAL SYSTEMS6.2.2-16.2.2.1Design Bases6.2.2-16.2.2.2System Design6.2.2-3 6.2.2.3Design Evaluation6.2.2-56.2.2.4Testing and Inspections6.2.2-76.2.2.5Instrumentation Requirements6.2.2-8 6.2.2.6Materials6.2.2-86.2.3Secondary Containment Functional Design6.2.3-16.2.3.1Design Bases6.2.3-16.2.3.1.1Secondary Containment Enclosures6.2.3-16.2.3.1.2Emergency Gas Treatment System (EGTS)6.2.3-16.2.3.1.3Auxiliary Building Gas Treatment System (ABGTS)6.2.3-26.2.3.2System Design6.2.3-26.2.3.2.1Secondary Containment Enclosures6.2.3-2 6.2.3.2.2Emergency Gas Treatment System (EGTS)6.2.3-76.2.3.2.3Auxiliary Building Gas Treatment System (ABGTS)6.2.3-106.2.3.3Design Evaluation6.2.3-12 6.2.3.3.1Secondary Containment Enclosures6.2.3-126.2.3.3.2Emergency Gas Treatment System (EGTS)6.2.3-156.2.3.3.3Auxiliary Building Gas Treatment System (ABGTS)6.2.3-196.2.3.4Test and Inspections6.2.3-216.2.3.4.1Emergency Gas Treatment System (EGTS)6.2.3-216.2.3.4.2Auxiliary Building Gas Treatment System (ABGTS)6.2.3-226.2.3.5Instrumentation Requirements6.2.3-236.2.3.5.1Emergency Gas Treatment System (EGTS)6.2.3-236.2.3.5.2Auxiliary Building Gas Treatment System (ABGTS)6.2.3-236.2.4Containment Isolation Systems6.2.4-16.2.4.1Design Bases6.2.4-16.2.4.2System Design6.2.4-46.2.4.2.1Design Requirements6.2.4-5 6.2.4.2.2Containment Isolation Operation6.2.4-56.2.4.2.3Penetration Design6.2.4-66.2.4.3Design Evaluation6.2.4-12 1-xxivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.2.4.3.1Possible Leakage Paths6.2.4-146.2.4.4Tests and Inspections6.2.4-166.2.5Combustible Gas Control in Containment6.2.5-16.2.5.1Design Bases6.2.5-16.2.5.2System Design6.2.5-2 6.2.5.3Design Evaluation6.2.5-56.2.5.4Testing and Inspections6.2.5-56.2.5.5Instrumentation Application6.2.5-5 6.2.5.6Materials6.2.5-66.2.5AHydrogen Mitigation System6.2.5-66.2.5A.1Design Basis6.2.5-6 6.2.5A.2System Description6.2.5-66.2.5A.3Operation6.2.5-76.2.5A.4Safety Evaluation6.2.5-7 6.2.5A.5Testing6.2.5-76.2.6Containment Leakage Testing6.2.6-16.2.6.1Containment Integrated Leak Rate Test6.2.6-16.2.6.2Containment Penetration Leakage Rate Test6.2.6-26.2.6.3Scheduling and Reporting of Periodic Tests6.2.6-6 6.2.6.4Special Testing Requirements6.2.6-66.3EMERGENCY CORE COOLING SYSTEM6.3-16.3.1Design Bases6.3-16.3.1.1Range of Coolant Ruptures and Leaks6.3-16.3.1.2Fission Product Decay Heat6.3-2 6.3.1.3Reactivity Required for Cold Shutdown6.3-26.3.1.4Capability To Meet Functional Requirements6.3-26.3.2System Design6.3-2 6.3.2.1Schematic Piping and Instrumentation Diagrams6.3-26.3.2.2Equipment and Component Design6.3-26.3.2.3Applicable Codes and Classifications6.3-176.3.2.4Materials Specifications and Compatibility6.3-176.3.2.5Design Pressures and Temperatures6.3-176.3.2.6Coolant Quantity6.3-18 6.3.2.7Pump Characteristics6.3-186.3.2.8Heat Exchanger Characteristics6.3-186.3.2.9ECCS Flow Diagrams6.3-186.3.2.10Relief Valves6.3-186.3.2.11System Reliability6.3-18 6.3.2.12Protection Provisions6.3-236.3.2.13Provisions for Performance Testing6.3-236.3.2.14Net Positive Suction Head6.3-24 Table of Contents1-xxvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.3.2.15Control of Motor-Operated Isolation Valves6.3-246.3.2.16Motor-Operated Valves and Controls6.3-256.3.2.17Manual Actions6.3-256.3.2.18Process Instrumentation6.3-256.3.2.19Materials6.3-256.3.3Performance Evaluation6.3-25 6.3.3.1Evaluation Model6.3-256.3.3.2ECCS Performance6.3-266.3.3.3Alternate Analysis Methods6.3-26 6.3.3.4Fuel Rod Perforations6.3-276.3.3.5Evaluation Model6.3-276.3.3.6Fuel Clad Effects6.3-27 6.3.3.7ECCS Performance6.3-276.3.3.8Peak Factors6.3-276.3.3.9Fuel Rod Perforations6.3-27 6.3.3.10Conformance with Interim Acceptance Criteria6.3-276.3.3.11Effects of ECCS Operation on the Core6.3-286.3.3.12Use of Dual Function Components6.3-28 6.3.3.13Lag Times6.3-306.3.3.14Thermal Shock Considerations6.3-306.3.3.15Limits on System Parameters6.3-30 6.3.3.16Use of RHR Spray6.3-306.3.4Tests and Inspections6.3-316.3.4.1Preoperational Tests6.3-31 6.3.4.2Component Testing6.3-326.3.4.3Periodic System Testing6.3-326.3.5Instrumentation Application6.3-33 6.3.5.1Temperature Indication6.3-336.3.5.2Pressure Indication6.3-336.3.5.3Flow Indication6.3-34 6.3.5.4Level Indication6.3-346.3.5.5Valve Position Indication6.3-356.4HABITABILITY SYSTEMS6.4-16.4.1 Design Bases6.4-16.4.2System Design6.4-1 6.4.2.1Definition of MCRHS Area6.4-16.4.2.2Ventilation System Design6.4-26.4.2.3Leak Tightness6.4-26.4.2.4Interaction with Other Zones and Pressure-Containing Equipment6.4-36.4.2.5Shielding Design6.4-4 6.4.2.6Control Room Emergency Provisions6.4-46.4.2.7MCRHS Fire Protection6.4-46.4.3System Operational Procedures6.4-5 1-xxviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.4.4Design Evaluations6.4-76.4.4.1Radiological Protection6.4-76.4.4.2Toxic Gas Protection6.4-76.4.5Testing and Inspection6.4-96.4.6Instrumentation Requirements6.4-96.5FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS6.5-16.5.1Engineered Safety Feature (ESF) Filter Systems6.5-16.5.1.1Design Bases6.5-1 6.5.1.2System Design6.5-26.5.1.3Design Evaluation6.5-56.5.1.4Tests and Inspections6.5-5 6.5.1.5Instrumentation Requirements6.5-66.5.1.6Materials6.5-76.5.2Containment Spray System for Fission Product Cleanup6.5-8 6.5.2.1Design Bases6.5-86.5.2.2System Design6.5-86.5.2.3Design Evaluation6.5-8 6.5.2.4Tests and Inspections6.5-86.5.2.5Instrumentation Requirements6.5-86.5.2.6Materials6.5-8 6.5.3Fission Product Control Systems6.5-86.5.3.1Primary Containment6.5-86.5.3.2Secondary Containments6.5-10 6.5.4Ice Condenser as a Fission Product Cleanup System6.5-106.5.4.1Ice Condenser Design Basis (Fission Product Cleanup Function)6.5-116.5.4.2Ice Condenser System Design6.5-11 6.5.4.3Ice Condenser System Design Evalua tion (Fission Product Cleanup Function) 6.5-116.5.4.4Condenser System Tests and Inspections6.5-13 6.5.4.5Ice Condenser Materials6.5-136.6INSERVICE INSPECTION OF ASME CODE CLASS 2 AND 3 COMPONENTS 6.6-16.6.1Components Subject to Examination and/or Test6.6-16.6.2Accessibility6.6-1 6.6.3Examination Techniques and Procedures6.6-16.6.4Inspection Intervals6.6-16.6.5Examination Categories and Requirements6.6-16.6.6Evaluation of Examination Results6.6-16.6.7System Pressure Tests6.6-2 6.6.8Protection against Postulated Piping Failures6.6-26.7ICE CONDENSER SYSTEM6.7-1 Table of Contents1-xxviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.7.1Floor Structure and Cooling System6.7-16.7.1.1Design Bases6.7-16.7.1.2Design Evaluation6.7-56.7.2Wall Panels6.7-86.7.2.1Design Basis6.7-86.7.2.2System Design6.7-8 6.7.2.3Design Evaluation6.7-96.7.3Lattice Frames and Support Columns6.7-96.7.3.1Design Basis6.7-9 6.7.3.2System Design6.7-126.7.3.3Design Evaluation6.7-136.7.4Ice Baskets6.7-14 6.7.4.1Design Basis6.7-146.7.4.2System Design6.7-156.7.4.3Design Evaluation6.7-18 6.7.5Crane and Rail Assembly6.7-206.7.5.1Design Basis6.7-206.7.5.2System Design6.7-20 6.7.5.3Design Evaluation6.7-216.7.6Refrigeration System6.7-216.7.6.1Design Basis6.7-21 6.7.6.2System Design6.7-226.7.6.3Design Evaluation6.7-256.7.7Air Handling Units6.7-29 6.7.7.1Design Basis6.7-296.7.7.2System Design6.7-306.7.7.3Design Evaluation6.7-31 6.7.8Lower Inlet Doors6.7-316.7.8.1Design Basis6.7-316.7.8.2System Design6.7-34 6.7.8.3Design Evaluation6.7-366.7.9Lower Support Structure6.7-376.7.9.1Design Basis6.7-37 6.7.9.2System Design6.7-396.7.9.3Design Evaluation6.7-406.7.10Top Deck and Doors6.7-49 6.7.10.1Design Basis6.7-496.7.10.2System Design6.7-516.7.11Intermediate Deck and Doors6.7-546.7.11.1Design Basis6.7-546.7.11.2System Design6.7-55 6.7.11.3Design Evaluation6.7-566.7.12Air Distribution Ducts6.7-576.7.12.1Design Basis6.7-57 1-xxviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page6.7.12.2System Design6.7-586.7.12.3Design Evaluation6.7-586.7.13Equipment Access Door6.7-586.7.13.1Design Basis6.7-586.7.13.2System Design6.7-596.7.13.3Design Evaluation6.7-59 6.7.14Ice Technology, Ice Performance, and Ice Chemistry6.7-596.7.14.1Design Basis6.7-596.7.14.2System Design6.7-59 6.7.14.3Design Evaluation6.7-606.7.15Ice Condenser Instrumentation6.7-656.7.15.1Design Basis6.7-65 6.7.15.2Design Description6.7-666.7.15.3Design Evaluation6.7-676.7.16Ice Condenser Structural Design6.7-68 6.7.16.1Applicable Codes, Standards, and Specifications6.7-686.7.16.2Loads and Loading Combinations6.7-686.7.16.3Design and Analytical Procedures6.7-68 6.7.16.4Structural Acceptance Criteria6.7-696.7.17Seismic Analysis6.7-706.7.17.1Seismic Analysis Methods6.7-70 6.7.17.2Seismic Load Development6.7-736.7.17.3Vertical Seismic Response6.7-746.7.18Materials6.7-74 6.7.18.1Design Criteria6.7-746.7.18.2Environmental Effects6.7-756.7.18.3Compliance with 10 CFR 50, Appendix B6.7-76 6.7.18.4Materials Specifications6.7-776.7.19Tests and Inspections6.7-786.8AIR RETURN FANS6.8-16.8.1Design Bases6.8-16.8.2System Description6.8-1 6.8.3Safety Evaluation6.8-26.8.4Inspection and Testing6.8-36.8.5Instrumentation Requirements6.8-3017_TVA_WB_FSAR_Section_7.pdf7.0INSTRUMENTATION AND CONTROLS

7.1INTRODUCTION

7.1-17.1.1Identification of Safety-Related Systems7.1-47.1.1.1 Safety-Related Systems7.1-47.1.1.2 Safety-Related Display Instrumentation7.1-57.1.1.3 Instrumentation and Control System Designers7.1-5 Table of Contents1-xxixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.1.1.4 Plant Comparison7.1-57.1.2Identification of Safety Criteria7.1-57.1.2.1Design Bases7.1-87.1.2.2Independence of Redundant Safety-Related Systems7.1-127.1.2.3Physical Identification of Safety-Related Equipment7.1-157.1.2.4Process Signal Isolation Relays7.1-177.2 REACTOR TRIP SYSTEM7.2-17.2.1Description7.2-1 7.2.1.1System Description7.2-17.2.1.2Design Bases Information7.2-177.2.1.3Final Systems Drawings7.2-19 7.2.2Analyses7.2-197.2.2.1Evaluation of Design Limits7.2-207.2.2.2Evaluation of Compliance to Applicable Codes and Standards7.2-237.2.2.3Specific Control and Protection Interactions7.2-337.2.2.4Additional Postulated Accidents7.2-367.2.3Tests and Inspections7.2-367.3ENGINEERED SAFETY FEATURES ACTUATION SYSTEM7.3-17.3.1Description7.3-1 7.3.1.1System Description7.3-17.3.1.2Design Bases Information7.3-67.3.1.3Final System Drawings7.3-8 7.3.2Analysis7.3-87.3.2.1System Reliability/Availability and Failure Mode and Effect Analyses7.3-87.3.2.2Compliance With Standards and Design Criteria7.3-9 7.3.2.3 Further Considerations7.3-167.3.2.4Summary7.3-177.4SYSTEMS REQUIRED FOR SAFE SHUTDOWN7.4-17.4.1Description7.4-17.4.1.1Monitoring Indicators7.4-1 7.4.1.2Controls7.4-27.4.1.3Equipment and Systems Available for Cold Shutdown7.4-67.4.2Analysis7.4-67.5INSTRUMENTATION SYSTEMS IMPORTANT TO SAFETY7.5-17.5.1Post Accident Monitoring Instrumentation (PAM)7.5-17.5.1.1System Description7.5-17.5.1.2Variable Types7.5-1 7.5.1.3Variable Categories7.5-27.5.1.4Design Bases7.5-37.5.1.5General Requirements7.5-6 1-xxxTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.5.1.6Analysis7.5-77.5.1.7Tests and Inspections7.5-77.5.2Emergency Response Facilities Data System (ERFDS)7.5-87.5.2.1Safety Parameter Display System7.5-87.5.2.2Bypassed and Inoperable Status Indication System (BISI)7.5-107.5.2.3Technical Support Center and Nuclear Data Links7.5-137.6ALL OTHER SYSTEMS REQUIRED FOR SAFETY7.6-17.6.1120V ac and 125V dc Vital Plant Control Power System7.6-1 7.6.2Residual Heat Removal Isolation Valves7.6-17.6.2.1Description7.6-17.6.2.2Analysis7.6-2 7.6.3Refueling Interlocks7.6-27.6.4Deleted by Amendment 63.7.6-27.6.5Accumulator Motor-Operated Valves7.6-2 7.6.6Spurious Actuation Protection for Motor Operated Valves7.6-37.6.7Loose Part Monitoring System (LPMS) System Description7.6-47.6.8Interlocks for RCS Pressure Control During Low Temperature Operation7.6-67.6.8.1Analysis of Interlock7.6-77.6.9Switchover From Injection to Recirculation7.6-87.6.9.1Description of Instrumentation Used for Switchover7.6-8 7.6.9.2Initiation Circuit7.6-97.6.9.3Logic7.6-97.6.9.4Bypass7.6-9 7.6.9.5Interlocks7.6-97.6.9.6Sequence7.6-107.6.9.7Redundancy7.6-10 7.6.9.8Diversity7.6-107.6.9.9Actuated Devices7.6-107.7CONTROL SYSTEMS7.7-17.7.1Description7.7-17.7.1.1Control Rod Drive Reactor Control System7.7-1 7.7.1.3Plant Control Signals for Monitoring and Indicating7.7-87.7.1.4Plant Control System Interlocks7.7-127.7.1.5Pressurizer Pressure Control7.7-137.7.1.6Pressurizer Water Level Control7.7-137.7.1.7Steam Generator Water Level Control7.7-147.7.1.8Steam Dump Control7.7-147.7.1.9Incore Instrumentation7.7-167.7.1.10Control Board7.7-18 7.7.1.11Boron Concentration Measurement System7.7-187.7.1.12Anticipated Transient Without Scram Mitigation System Actuation7.7-197.7.2Analysis7.7-20 Table of Contents1-xxxiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page7.7.2.1Separation of Protection and Control System7.7-217.7.2.2Response Considerations of Reactivity7.7-217.7.2.3Step Load Changes Without Steam Dump7.7-247.7.2.4Loading and Unloading7.7-247.7.2.5Load Rejection Furnished By Steam Dump System7.7-257.7.2.6Turbine-Generator Trip With Reactor Trip7.7-25 7.7.3Deleted by Amendment 817.7-267AINSTRUMENTATION IDENTIFICATIONS AND SYMBOLS7A.1IDENTIFICATION SYSTEM7A.1-17A.1.1FUNCTIONAL IDENTIFICATION7A.1-1 7A.1.1.1 Principal Function7A.1-17A.1.1.2 Measured Variable7A.1-27A.1.1.3 Readout or Passive Functions7A.1-2 7A.1.1.4 Modifying Letters7A.1-27A.1.1.5 Tagging Symbols7A.1-27A.1.1.6 Special Identifying Letters7A.1-2 7A.1.1.7 Pilot Lights7A.1-27A.1.2 SYSTEM IDENTIFICATION7A.1-37A.1.2.1 Identification Numbers7A.1-37A.1.3 LOOP IDENTIFICATION7A.1-37A.1.3.1 Instruments Common to Multiple Control Loops7A.1-37A.1.3.2 Multiple Instruments with a Common Function7A.1-37A.2SYMBOLS7A.1-37A.2.1INSTRUMENT SYMBOL7A.1-4018_TVA_WB_FSAR_Section_88.0ELECTRIC POWER

8.1INTRODUCTION

8.1-18.1.1Utility Grid and Interconnections8.1-18.1.2Plant Electrical Power System8.1-1 8.1.3Safety-Related Loads8.1-28.1.4Design Bases8.1-38.1.5Design Criteria and Standards8.1-4 8.1.5.1Design Criteria8.1-58.1.5.2Other Standards and Guides8.1-58.1.5.3Compliance to Regulatory Guides and IEEE Standards8.1-88.2OFFSITE (PREFERRED) POWER SYSTEM8.2-18.2.1Description8.2-18.2.1.1Preferred Power Supply8.2-18.2.1.2Transmission Lines, Switchyard, and Transformers8.2-3 1-xxxiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page8.2.1.3Arrangement of the Start Boards, Un it Boards, Common Boards, and Reactor Coolant Pump (RCP) Boards8.2-48.2.1.4Arrangement of Electrical C ontrol Area (Nuclear Plant)8.2-58.2.1.5Switchyard Control and Relaying8.2-68.2.1.66.9-kV Start Boards Control and Relaying8.2-88.2.1.76.9-kV Unit and RCP Board Control and Relaying8.2-10 8.2.1.8Conformance with Standards8.2-118.2.2 Analysis8.2-198.3ONSITE (STANDBY) POWER SYSTEM8.3-18.3.1AC Power System8.3-18.3.1.1Description8.3-1 8.3.1.2Analysis8.3-288.3.1.3Physical Identification of Safety-Rel ated Equipment in AC Power Systems 8.3-388.3.1.4Independence of Redundant ac Power Systems8.3-388.3.2DC Power System8.3-558.3.2.1Description8.3-55 8.3.2.2Analysis of Vital 125V DC Control Power Supply System8.3-638.3.2.3Physical Identification of Safety-Related Equipment in dc Power Systems8.3-688.3.2.4Independence of Redundant DC Power Systems8.3-688.3.2.5Sharing of Batteries Between Units8.3-688.3.3Fire Protection for Cable Systems8.3-70 Table of Contents1-xxxiiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page8AAnalysis of Submerged Electrical Equipment (During Post LOCA) Powered from Auxiliary Power System8A-18BAnalysis of Submerged Electrical Equipment (During Post LOCA) Powered from Instrumentation and Control Power System8B-18CDeleted by Amendment 758C-18DIEEE STD 387-1984 FOR DIESEL-GENERATING UNITS APPLIED AS STAND-BY POWER8D-18EProbability/Reliability Analysis of Protection Device Schemes for Associated and Non-Class 1E Cables8E-19.0AUXILIARY SYSTEMS9.1FUEL STORAGE AND HANDLING9.1-19.1.1New Fuel Storage9.1-19.1.1.1Design Bases9.1-19.1.1.2Facilities Description9.1-1 9.1.1.3Safety Evaluation9.1-19.1.2SPENT FUEL STORAGE9.1-29.1.2.1Design Bases9.1-2 9.1.2.2Facilities Description9.1-29.1.2.3Safety Evaluation9.1-39.1.2.4Materials9.1-4 9.1.3Spent Fuel Pool Cooling and Cleanup System (SFPCCS)9.1-49.1.3.1Design Bases9.1-49.1.3.2System Description9.1-5 9.1.3.3Safety Evaluation9.1-89.1.3.4Tests and Inspections9.1-119.1.3.5Instrument Application9.1-11 9.1.4FUEL HANDLING SYSTEM9.1-129.1.4.1Design Bases9.1-129.1.4.2System Description9.1-13 9.1.4.3Design Evaluation9.1-209.1.4.4Tests and Inspections9.1-269.2WATER SYSTEMS9.2-19.2.1Essential Raw Cooling Water (ERCW)9.2-1 9.2.1.1Design Bases9.2-19.2.1.2System Description9.2-19.2.1.3Safety Evaluation9.2-4 1-xxxivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.2.1.4Tests and Inspections9.2-79.2.1.5Instrument Applications9.2-79.2.1.6Corrosion, Organic Fouling, and Environmental Qualification9.2-99.2.1.7Design Codes9.2-119.2.2Component Cooling System (CCS)9.2-119.2.2.1Design Bases9.2-11 9.2.2.2System Description9.2-139.2.2.3Components9.2-169.2.2.4 Safety Evaluation9.2-19 9.2.2.5Leakage Provisions9.2-199.2.2.6Incidental Control9.2-209.2.2.7Instrument Applications9.2-20 9.2.2.8Malfunction Analysis9.2-229.2.2.9Tests and Inspections9.2-239.2.2.10Codes and Classification9.2-239.2.3Demineralized Water Makeup System9.2-239.2.3.1Design Bases9.2-239.2.3.2System Description9.2-24 9.2.3.3Safety Evaluation9.2-259.2.3.4Test and Inspection9.2-259.2.3.5Instrumentation Applications9.2-25 9.2.4Potable and Sanitary Water Systems9.2-269.2.4.1Potable Water System9.2-269.2.4.2Sanitary Water System9.2-27 9.2.5Ultimate Heat Sink9.2-309.2.5.1General Description9.2-309.2.5.2Design Bases9.2-31 9.2.5.3Safety Evaluation9.2-329.2.5.4Instrumentation Application9.2-339.2.6Condensate Storage Facilities9.2-33 9.2.6.1Design Bases9.2-349.2.6.2System Description9.2-349.2.6.3Safety Evaluation9.2-35 9.2.6.4Test and Inspections9.2-359.2.6.5Instrument Applications9.2-369.2.7Refueling Water Storage Tank9.2-36 9.2.7.1ECCS Pumps Net Positive Suction Head (NPSH)9.2-379.2.8Raw Cooling Water System9.2-399.2.8.1Design Bases9.2-399.2.8.2System Description9.2-409.2.8.3Safety Evaluation9.2-42 9.2.8.4Tests and Inspection9.2-429.3PROCESS AUXILIARIES9.3-1 Table of Contents1-xxxvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.3.1Compressed Air System9.3-19.3.1.1Design Basis9.3-19.3.1.2System Description9.3-19.3.1.3Safety Evaluation9.3-29.3.1.4Tests and Inspections9.3-59.3.1.5Instrumentation Applications9.3-5 9.3.2Process Sampling System9.3-59.3.2.1Design Basis9.3-59.3.2.2System Description9.3-5 9.3.2.3Safety Evaluation9.3-89.3.2.4Tests and Inspections9.3-89.3.2.5Instrumentation Applications9.3-8 9.3.2.6Postaccident Sampling Subsystem9.3-89.3.3Equipment and Floor Drainage System9.3-129.3.3.1Design Bases9.3-12 9.3.3.2System Design9.3-129.3.3.3Drains - Reactor Building9.3-159.3.3.4Design Evaluation9.3-15 9.3.3.5Tests and Inspections9.3-159.3.3.6Instrumentation Application9.3-159.3.3.7Drain List9.3-15 9.3.4Chemical and Volume Control System9.3-169.3.4.1Design Bases9.3-169.3.4.2System Description9.3-18 9.3.4.3Safety Evaluation9.3-369.3.4.4Tests and Inspections9.3-389.3.4.5Instrumentation Application9.3-39 9.3.5Failed Fuel Detection System9.3-399.3.5.1Design Bases9.3-399.3.5.2System Description9.3-40 9.3.5.3Safety Evaluation9.3-409.3.5.4Tests and Inspections9.3-409.3.5.5Instrument Applications9.3-40 9.3.6Auxiliary Charging System9.3-409.3.6.1Design Bases9.3-409.3.6.2System Design Description9.3-41 9.3.6.3Design Evaluation9.3-429.3.6.4Tests and Inspection9.3-429.3.6.5Instrument Application9.3-429.3.7Boron Recycle System9.3-429.3.7.1Design Bases9.3-43 9.3.7.2System Description9.3-449.3.7.3Safety Evaluation9.3-509.3.7.4Tests and Inspections9.3-50 1-xxxviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.3.7.5Instrumentation Application9.3-509.3.8Heat Tracing9.3-519.4AIR CONDITIONING, HEATING, COOLING, AND VENTILATION SYSTEMS 9.4-19.4.1Control Room Area Ventilation System9.4-19.4.1.1Design Bases9.4-19.4.1.2System Description9.4-39.4.1.3Safety Evaluation9.4-7 9.4.1.4Tests and Inspection9.4-89.4.2Fuel Handling Area Ventilation System9.4-89.4.2.1Design Bases9.4-8 9.4.2.2System Description9.4-109.4.2.3Safety Evaluation9.4-109.4.2.4 Inspection and Testing9.4-11 9.4.3Auxiliary and Radwaste Area Ventilation System9.4-129.4.3.1Design Bases9.4-129.4.3.2System Description9.4-13 9.4.3.3Safety Evaluation9.4-199.4.3.4Inspection and Testing Requirements9.4-239.4.4Turbine Building Area Ventilation System9.4-23 9.4.4.1Design Bases9.4-239.4.4.2System Description9.4-249.4.4.3Safety Evaluation9.4-26 9.4.4.4Inspection and Testing Requirements9.4-269.4.5 Engineered Safety Feature Ventilation Systems9.4-269.4.5.1ERCW Intake Pumping Station9.4-26 9.4.5.2Diesel Generator Buildings9.4-299.4.5.3Auxiliary Building Safety Features Equipment Coolers9.4-369.4.6Reactor Building Purge Ventilating System9.4-39 9.4.6.1Design Bases9.4-399.4.6.2System Description9.4-419.4.6.3Safety Evaluation9.4-43 9.4.6.4Inspection and Testing Requirements9.4-449.4.7Containment Air Cooling System9.4-459.4.7.1Design Bases9.4-45 9.4.7.2System Description9.4-469.4.7.3Safety Evaluation9.4-489.4.7.4Test and Inspection Requirements9.4-489.4.8Condensate Demineralizer Wa ste Evaporator Building Environmental Control Sys-tem (Not required for Unit 1 operation)9.4-499.4.8.1Design Basis9.4-499.4.8.2System Description9.4-499.4.8.3Safety Evaluation9.4-50 Table of Contents1-xxxviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.4.8.4Inspection and Testing Requirements9.4-509.4.9Postaccident Sampling Facility Environmental Control System9.4-509.4.9.1Design Basis9.4-509.4.9.2System Description9.4-509.4.9.3Safety Evaluation9.4-519.4.9.4Inspection and Testing Requirements9.4-519.5OTHER AUXILIARY SYSTEMS9.5-19.5.1Fire Protection System9.5-1 9.5.1.1Deleted by Amendment 879.5-19.5.1.2Deleted by Amendment 879.5-19.5.1.3Deleted by Amendment 879.5-1 9.5.1.4Deleted by Amendment 879.5-19.5.1.5Deleted by Amendment 879.5-19.5.2Plant Communications System9.5-1 9.5.2.1Design Bases9.5-19.5.2.2General Description Intraplant Communications9.5-19.5.2.3General Description Interplant System9.5-4 9.5.2.4 Evaluation9.5-59.5.2.5Inspection and Tests9.5-89.5.3Lighting Systems9.5-9 9.5.3.1Design Bases9.5-99.5.3.2Description of the Plant Lighting System9.5-109.5.3.3Diesel Generator Building Lighting System9.5-11 9.5.3.4Safety Related Functions of the Lighting Systems9.5-129.5.3.5Inspection and Testing Requirements9.5-139.5.4Diesel Generator Fuel Oil Storage and Transfer System9.5-139.5.4.1Design Basis9.5-139.5.4.2System Description9.5-149.5.4.3Safety Evaluation9.5-16 9.5.4.4Tests and Inspections9.5-179.5.5Diesel Generator Cooling Water System9.5-189.5.5.1Design Bases9.5-18 9.5.5.2System Description9.5-189.5.5.3Safety Evaluation9.5-199.5.5.4Tests and Inspections9.5-19 9.5.6Diesel Generator Starting System9.5-199.5.6.1Design Bases9.5-199.5.6.2System Description9.5-209.5.6.3Safety Evaluation9.5-219.5.6.4Tests and Inspections9.5-21 9.5.7Diesel Engine Lubrication System9.5-219.5.7.1Design Bases9.5-219.5.7.2System Description9.5-23 1-xxxviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page9.5.7.3Safety Evaluation9.5-259.5.7.4Test and Inspections9.5-259.5.8Diesel Generator Combustion Air Intake and Exhaust System9.5-259.5.8.1Design Bases9.5-259.5.8.2System Descriptions9.5-259.5.8.3Safety Evaluation9.5-26 9.5.8.4Tests and Inspection9.5-2710.0MAIN STEAM AND POWER CONVERSION SYSTEMS10.1

SUMMARY

DESCRIPTION10.1-110.2TURBINE-GENERATOR10.2-110.2.1Design Bases10.2-110.2.2Description10.2-1 10.2.3Turbine Rotor and Disc Integrity10.2-510.2.3.1 Materials Selection10.2-510.2.3.2Fracture Toughness10.2-7 10.2.3.3 High Temperature Properties10.2-910.2.3.4 Turbine Disc Design10.2-910.2.3.5 Preservice Inspection10.2-9 10.2.3.6 Inservice Inspection10.2-1110.2.4Evaluation10.2-1310.3MAIN STEAM SUPPLY SYSTEM10.3-110.3.1Design Bases10.3-110.3.2System Description10.3-1 10.3.2.1System Design10.3-110.3.2.2Material Compatibility, Codes, and Standards10.3-210.3.3Design Evaluation10.3-2 10.3.4Inspection and Testing Requirements10.3-310.3.5Water Chemistry10.3-310.3.5.1Purpose10.3-3 10.3.5.2Feedwater Chemistry Specifications10.3-410.3.5.3Operating Modes10.3-410.3.5.4Effect of Water Chemistry on the Radi oactive Iodine Partition Coefficient 10.3-510.3.6Steam and Feedwater System Materials10.3-510.3.6.1Fracture Toughness10.3-510.3.6.2Materials Selection and Fabrication10.3-510.4OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-110.4.1Main Condenser10.4-110.4.1.1Design Bases10.4-1 Table of Contents1-xxxixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page10.4.1.2System Description10.4-110.4.1.3Safety Evaluation10.4-410.4.1.4Inspection and Testing10.4-510.4.1.5Instrumentation10.4-510.4.2Main Condenser Evacuation System10.4-510.4.2.1Design Bases10.4-5 10.4.2.2System Description10.4-510.4.2.3Safety Evaluation10.4-610.4.2.4Inspection and Testing10.4-6 10.4.2.5Instrumentation10.4-610.4.3Turbine Gland Sealing System10.4-710.4.3.1Design Bases10.4-7 10.4.3.2System Description10.4-710.4.3.3Safety Evaluation10.4-710.4.3.4Inspection and Testing10.4-8 10.4.3.5Instrumentation10.4-810.4.4Turbine Bypass System10.4-810.4.4.1Design Bases10.4-8 10.4.4.2System Description10.4-810.4.4.3Safety Evaluation10.4-910.4.4.4Inspection and Testing10.4-10 10.4.5Condenser Circulating Water System10.4-1010.4.5.1Design Basis10.4-1110.4.5.2System Description10.4-11 10.4.5.3Safety Evaluation10.4-1310.4.5.4Inspection and Testing10.4-1410.4.5.5Instrumentation Application10.4-14 10.4.6Condensate Polishing Demineralizer System10.4-1510.4.6.1Design Bases - Power Conversion10.4-1510.4.6.2System Description10.4-15 10.4.6.3Safety Evaluation10.4-1710.4.6.4Inspection and Testing10.4-1810.4.6.5Instrumentation10.4-18 10.4.7Condensate and Feedwater Systems10.4-1910.4.7.1Design Bases10.4-1910.4.7.2System Description10.4-19 10.4.7.3Safety Evaluation10.4-2610.4.7.4Inspection and Testing10.4-2810.4.7.5Instrumentation10.4-2810.4.8Steam Generator Blowdown System10.4-2810.4.8.1Design Bases10.4-28 10.4.8.2System Description and Operation10.4-3010.4.8.3Safety Evaluation10.4-3010.4.8.4Inspections and Testing10.4-31 1-xlTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page10.4.9Auxiliary Feedwater System10.4-3210.4.9.1Design Bases10.4-3210.4.9.2System Description10.4-3210.4.9.3Safety Evaluation10.4-3410.4.9.4Inspection and Testing Requirements10.4-3710.4.9.5Instrumentation Requirements10.4-37 10.4.10Heater Drains and Vents10.4-3810.4.10.1Design Bases10.4-3810.4.10.2System Description10.4-38 10.4.10.3Safety Evaluation10.4-4310.4.10.4Inspection and Testing10.4-4410.4.10.5Instrumentation10.4-44 10.4.11Steam Generator Wet Layup System10.4-4410.4.11.1Design Bases10.4-4410.4.11.2System Description10.4-44 10.4.11.3Safety Evaluation10.4-4510.4.11.4Inspection and Testing10.4-4510.4.11.5Instrumentation10.4-4511.0RADIOACTIVE WASTE MANAGEMENT11.1SOURCE TERMS11.1-111.1.1Historical Design Model for Radioact ivities in Systems and Components11.1-111.1.1.1Reactor Coolant Historical Design Activity11.1-111.1.1.2Volume Control Tank Historical Design Activity11.1-211.1.1.3Pressurizer Historical Design Activity11.1-211.1.1.4Gaseous Waste Processing System Historical Design Activities11.1-211.1.1.5Secondary Coolant Historical Design Activities11.1-211.1.2Realistic Model for Radioactivities in Systems and Components11.1-211.1.3Plant Leakage11.1-3 11.1.4Additional Sources11.1-311.2LIQUID WASTE SYSTEMS11.2-111.2.1DESIGN OBJECTIVES11.2-111.2.2SYSTEMS DESCRIPTIONS11.2-111.2.3SYSTEM DESIGN11.2-5 11.2.3.1Component Design11.2-511.2.3.2Instrumentation Design11.2-1111.2.4Operating Procedure11.2-1111.2.5PERFORMANCE TESTS11.2-1811.2.6ESTIMATED RELEASES11.2-18 11.2.6.1NRC Requirements11.2-1811.2.6.2 Westinghouse PWR Release Experience11.2-1911.2.6.3Expected Liquid Waste Processing System Releases11.2-19 Table of Contents1-xliWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page11.2.6.4Turbine Building (TB) Drains11.2-1911.2.6.5Estimated Total Liquid Releases11.2-2011.2.7RELEASE POINTS11.2-2011.2.8DILUTION FACTORS11.2-2011.2.9ESTIMATED DOSES FROM RADIONUCLIDES IN LIQUID EFFLUENTS11.2-2111.2.9.1Assumptions and Calculational Methods11.2-2111.2.9.2Summary of Dose from Radionuclides in Liquid Effluents11.2-2311.3GASEOUS WASTE SYSTEMS11.3-111.3.1Design Bases11.3-111.3.2SYSTEM DESCRIPTIONS11.3-1 11.3.3SYSTEM DESIGN11.3-311.3.3.1Component Design11.3-311.3.3.2Instrumentation Design11.3-3 11.3.4Operating Procedure11.3-411.3.5Performance Tests11.3-611.3.6Deleted by Amendment 7711.3-6 11.3.7Radioactive Releases11.3-611.3.7.1NRC Requirements11.3-611.3.7.2Westinghouse PWR Experience Releases11.3-6 11.3.7.3Expected Gaseous Waste Processing System Releases11.3-611.3.7.4Releases from Ventilation Systems11.3-711.3.7.5Estimated Total Releases11.3-7 11.3.8Release Points11.3-711.3.9Atmospheric Dilution11.3-811.3.10Estimated Doses from Radionuclides in Gaseous Effluents11.3-911.3.10.1Assumptions and Calculational Methods11.3-911.3.10.2Summary of Annual Population Doses11.3-1111.4PROCESS AND EFFLUEN T RADIOLOGICAL MONITO RING AND SAMPLING SYSTEM11.4-111.4.1Design Objectives11.4-1 11.4.2Continuous Monitors11.4-211.4.2.1Liquid Monitors11.4-211.4.2.2Gaseous Monitors11.4-4 11.4.3SAMPLING11.4-911.4.4CALIBRATION AND MAINTENANCE11.4-911.5SOLID WASTE MANAGEMENT SYSTEM11.5-111.5.1Design Objectives11.5-1 11.5.2System Inputs11.5-111.5.3Systems Description11.5-111.5.3.1Wet Active Waste Handling11.5-1 1-xliiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page11.5.3.2Dry Active Waste Handling11.5-311.5.3.3Miscellaneous Waste Handling11.5-411.5.4Equipment Operation11.5-411.5.4.1Deleted11.5-411.5.4.2Mobile Solidification System (MSS)11.5-411.5.5Storage Facilities11.5-4 11.5.5.1Inplant Storage Area11.5-411.5.5.2Outside Radwaste Storage11.5-511.5.6Shipment11.5-511.6Offsite Radiological Monitoring Program11.6-111.6.1Expected Background11.6-2 11.6.2Critical Pathways to Man11.6-211.6.2.1Doses from Gaseous Effluents11.6-311.6.2.2Internal Doses from Liquid Effluents11.6-3 11.6.3Sampling Media, Locations, and Frequency11.6-411.6.4Analytical Sensitivity11.6-411.6.5Data Analysis and Presentation11.6-4 11.6.6Program Statistical Sensitivity11.6-411ATRITIUM CONTROL 11A.1SYSTEM SOURCES11A.1-111A.1.1The Fission Source11A.1-1 11A.1.2Control Rod Source11A.1-111A.1.3Boric Acid Source11A.1-111A.1.4Burnable Shim Rod Source11A.1-211A.2Tritium Releases11A.1-211A.3 Design Bases11A.1-211A.4Design Evaluation11A.1-2 11A.5Tritium Lead Test Assembly (This section to be provided at a later date)11A.1-311A.6Tritium Producing Burnable Absorber Rod (TPBAR) Source (Unit 1 Only)11A.1-312.0RADIATION PROTECTION 12.1Assuring that Occupational Radiation Exposures Are as Low as Reasonably Achievable (ALARA)12.1-1 Table of Contents 1-xliiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page12.1.1Policy Considerations12.1-112.1.2Design Considerations12.1-112.1.3ALARA Operational Considerations12.1-112.2RADIATION SOURCES12.2-312.2.1Contained Sources12.2-3 12.2.1.1Primary System Sources12.2-312.2.1.2Auxiliary Systems Sources12.2-412.2.1.3Sources During Refueling12.2-10 12.2.1.4Maximum Hypothetical Accident (MHA) Sources12.2-1012.2.1.5Condensate Demineralizer Waste Evaporator12.2-1112.2.2Airborne Radioactive Material Sources12.2-1112.3RADIATION PROTECTION DESIGN FEATURES12.3-112.3.1Facility Design Features12.3-1 12.3.2Shielding12.3-312.3.2.1Design Objectives12.3-312.3.2.2 Design Description12.3-3 12.3.3Ventilation12.3-1512.3.3.1Airflow Control12.3-1512.3.3.2Typical System12.3-15 12.3.3.3Additional Radiation Controls12.3-1612.3.4Area Radiation and Airborne Radioactivity Monitoring Instrumentation12.3-1712.3.4.1Area Radiation Monitoring Instrumentation12.3-1712.3.4.2Airborne Particulate Radioactivity Monitoring12.3-1912.3.4.3Deleted by Amendment 84.12.3-2312.3.4.4Special Radiation Monitors12.3-2312.4DOSE ASSESSMENT12.4-112.5RADIOLOGICAL CONTROL (RADCON) PROGRAM12.5-112.5.1Organization12.5-112.5.2Equipment, Instrumentation, and Facilities12.5-212.5.3Procedures12.5-4 024_TVA_WB_FSAR_Section_13.pdf13.0CONDUCT OF OPERATIONS13.1ORGANIZATIONAL STRUCTURE OF APPLICANT13.1-113.1.1Corporate Organization13.1-113.1.1.1Design Responsibilities13.1-113.1.2Nuclear Power13.1-1 13.1.2.1Offsite Organizations13.1-113.1.2.2Onsite Organization13.1-213.1.3Qualification Requirements for Nuclear Facility Personnel13.1-2 1-xlivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page13.2TRAINING PROGRAMS13.2-113.2.1Accredited Training Programs13.2-113.2.2General Employee and Fitness for Duty Training Programs13.2-113.2.3Other Training Programs13.2-213.3Emergency Planning13.3-113.4REVIEW AND AUDIT13.4-113.4.1Onsite Review13.4-113.4.2Independent Review and Audit13.4-113.5SITE PROCEDURES13.5-113.5.1SYSTEM OF SITE PROCEDURES13.5-113.5.1.1Conformance with Regulatory Guide 1.3313.5-1 13.5.1.2Preparation of Procedures13.5-113.5.1.3Administrative Procedures13.5-213.5.2Operating and Maintenance Procedures13.5-2 13.5.2.1Operating Procedures13.5-213.5.2.2Other Procedures13.5-313.6PLANT RECORDS13.6-113.6.1Plant History13.6-113.6.2Operating Records13.6-1 13.6.3Event Records13.6-113.7NUCLEAR SECURITY13.7-113.7.1Physical Security and Contingency Plan13.7-113.7.2Personnel and Program Evaluation13.7-113.7.3Physical Security of TPBARs13.7-114.0INITIAL TEST PROGRAM14.1SPECIFIC INFORMATION TO BE IN CLUDED IN PRELIMINARY SAFETY ANALYSIS REPORT14.1-114.2TEST PROGRAM14.2-114.2.1Summary of Test Program and Objectives14.2-114.2.2Organization and Staffing14.2-314.2.2.1Startup and Test Organization14.2-314.2.2.2Plant Operating Organization14.2-5 14.2.2.3Nuclear Assurance14.2-614.2.2.4Major Participating Organizations14.2-614.2.2.5Joint Test Group14.2-7 Table of Contents1-xlvWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page14.2.2.6Test Review Group14.2-814.2.2.7Personnel Qualifications14.2-914.2.3Test Procedures14.2-914.2.3.1General14.2-914.2.3.2Development of Procedures14.2-1014.2.3.3Review and Approval of Test Procedures14.2-1014.2.3.4Format of Test Procedures14.2-1014.2.3.5Test Procedure Revisions/Changes14.2-1114.2.4Conduct of Test Program14.2-12 14.2.4.1Administrative Procedures14.2-1214.2.4.2Component Testing14.2-1214.2.4.3Preoperational and Acceptance Testing14.2-1314.2.4.4Power Ascension Testing14.2-1314.2.4.5Test Prerequisites14.2-1314.2.4.6Phase Evaluation14.2-13 14.2.4.7Design Modifications14.2-1414.2.5Review, Evaluation, and Approval of Test Results14.2-1414.2.6Test Records14.2-14 14.2.7Conformance of Test Programs with Regulatory Guides14.2-1514.2.8Utilization of Reactor Oper ating and Testing Experience in Development of Test Pro-gram14.2-2914.2.9Trial Use of Plant Operating and Emergency Procedures14.2-3014.2.10Initial Fuel Loading, Postloading Tests, Initial Criticality, Low Power Tests and Pow-er Ascension14.2-3014.2.10.1Fuel Loading14.2-3014.2.10.2Postloading Tests14.2-3314.2.10.3Initial Criticality14.2-33 14.2.10.4Low Power Tests14.2-3314.2.10.5Power Ascension14.2-3414.2.11Test Program Schedule14.2-34 14.2.12Individual Test Descriptions14.2-3514.2.12.1Preoperational Tests14.2-3514.2.12.2Power Ascension Tests14.2-36026_TVA_WB_FSAR_Section_15.pdf15.0ACCIDENT ANALYSES15.1CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS 15.1-115.1.1Optimization of Control Systems15.1-215.1.2Initial Power Conditions Assumed In Accident Analyses15.1-315.1.2.1Power Rating15.1-3 15.1.2.2Initial Conditions15.1-315.1.2.3Power Distribution15.1-415.1.3Trip Points And Time Delays To Trip Assumed In Accident Analyses15.1-4 1-xlviTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.1.4Instrumentation Drift And Calorimetric Errors - Power Range Neutron Flux15.1-515.1.5Rod Cluster Control Assembly Insertion Characteristic15.1-515.1.6Reactivity Coefficients15.1-615.1.7Fission Product Inventories15.1-715.1.7.1Radioactivity in the Core15.1-715.1.7.2Radioactivity in the Fuel Pellet Clad Gap15.1-815.1.8Residual Decay Heat15.1-915.1.8.1Fission Product Decay Energy15.1-915.1.8.2Decay of U-238 Capture Products15.1-10 15.1.8.3Residual Fissions15.1-1115.1.8.4Distribution of Decay Heat Following Loss of Coolant Accident15.1-1115.1.9Computer Codes Utilized15.1-11 15.1.9.1FACTRAN15.1-1115.1.9.2Deleted by Amendment 72.15.1-1215.1.9.3 MARVEL15.1-12 15.1.9.4LOFTRAN15.1-1315.1.9.5LEOPARD15.1-1415.1.9.6TURTLE15.1-14 15.1.9.7TWINKLE15.1-1415.1.9.8Deleted by Amendment 80.15.1-1515.1.9.9THINC15.1-15 15.1.9.10LOFTTR15.1-1515.2CONDITION II - FAULTS OF MODERATE FREQUENCY15.2-115.2.1Uncontrolled Rod Cluster Control Asse mbly Bank Withdrawal from a Subcritical Condition15.2-215.2.1.1Identification of Causes and Accident Description15.2-2 15.2.1.2Analysis of Effects and Consequences15.2-315.2.1.3Conclusions15.2-515.2.2UNCONTROLLED ROD CLUSTER C ONTROL ASSEMBLY BANK WITH-DRAWAL AT POWER15.2-515.2.2.1Identification of Causes and Accident Description15.2-515.2.2.2Analysis of Effects and Consequences15.2-7 15.2.2.3Conclusions15.2-915.2.3ROD CLUSTER CONTROL ASSEMBLY MISALIGNMENT15.2-915.2.3.1Identification of Causes and Accident Description15.2-9 15.2.3.2Analysis of Effects and Consequences15.2-1115.2.3.3Conclusions15.2-1315.2.4UNCONTROLLED BORON DILUTION15.2-1315.2.4.1Identification of Causes and Accident Description15.2-1315.2.4.2Analysis of Effects and Consequences15.2-14 15.2.4.3Conclusions15.2-1615.2.5PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW15.2-1715.2.5.1Identification of Causes and Accident Description15.2-17 Table of Contents1-xlviiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.2.5.2Analysis of Effects and Consequences15.2-1815.2.5.3Conclusions15.2-1915.2.6Startup of an Inactive Reactor Coolant Loop15.2-1915.2.6.1Identification of Causes and Accident Description15.2-1915.2.6.2Analysis of Effects and Consequences15.2-1915.2.6.3Conclusions15.2-21 15.2.7LOSS OF EXTERNAL ELECTRICAL LOAD AND/OR TURBINE TRIP15.2-2115.2.7.1Identification of Causes and Accident Description15.2-2115.2.7.2Analysis of Effects and Consequences15.2-22 15.2.7.3Conclusions15.2-2415.2.8LOSS OF NORMAL FEEDWATER15.2-2415.2.8.1Identification of Causes and Accident Description15.2-24 15.2.8.2Analysis of Effects and Consequences15.2-2515.2.8.3Conclusions15.2-2815.2.9COINCIDENT LOSS OF ONSITE AND EXTERNAL (OFFSITE) AC POWER TO THE STATION - LOSS OF OFFSITE POWER TO THE STATION AUXILIARIES 15.2-2815.2.10EXCESSIVE HEAT REMOVAL DUE TO FEEDWATER SY STEM MALFUNC-TIONS15.2-2815.2.10.1Analysis of Effects and Consequences15.2-2815.2.10.2Conclusions15.2-31 15.2.11Excessive Load Increase Incident15.2-3115.2.11.1Identification of Causes and Accident Description15.2-3115.2.11.2Analysis of Effects and Consequences15.2-3215.2.11.3Conclusions15.2-3315.2.12ACCIDENTAL DEPRESSURIZATION OF THE REACTOR COOLANT SYS-TEM15.2-3315.2.12.1Identification of Causes and Accident Description15.2-3315.2.12.2Analysis of Effects and Consequences15.2-3315.2.12.3Conclusions15.2-34 15.2.13ACCIDENTAL DEPRESSURIZATION OF THE MAIN STEAM SYSTEM15.2-3415.2.13.1Identification of Causes and Accident Description15.2-3415.2.13.2Analysis of Effects and Consequences15.2-3615.2.13.3Conclusions15.2-3815.2.14Inadvertent Operation of Emergency Core Cooling System15.2-3815.2.14.1Identification of Causes and Accident Description15.2-3815.2.14.2Analysis of Effects and Consequences15.2-3915.2.14.3Conclusions15.2-4215.3CONDITION III - INFREQUENT FAULTS15.3-115.3.1Loss of Reactor Coolant From Small Ruptured Pipes or From Cracks in Large Pipes Which Actuate the Emergency Core Cooling System15.3-115.3.1.1Identification of Causes and Accident Description15.3-1 1-xlviiiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.3.1.2Analysis of Effects and Consequences15.3-215.3.1.3Reactor Coolant System Pipe Break Results15.3-315.3.1.4Conclusions - Thermal Analysis15.3-415.3.2Minor Secondary System Pipe Breaks15.3-515.3.2.1Identification of Causes and Accident Description15.3-515.3.2.2Analysis of Effects and Consequences15.3-5 15.3.2.3Conclusions15.3-515.3.3Inadvertent Loading of a Fuel Assembly Into an Improper Position15.3-515.3.3.1Identification of Causes and Accident Description15.3-5 15.3.3.2Analysis of Effects and Consequences15.3-615.3.3.3Conclusions15.3-715.3.4Complete Loss of Forced Reactor Coolant Flow15.3-7 15.3.4.1Identification of Causes and Accident Description15.3-715.3.4.2Analysis of Effects and Consequences15.3-815.3.4.3Conclusions15.3-9 15.3.5Waste Gas Decay Tank Rupture15.3-915.3.5.1Identification of Causes and Accident Description15.3-915.3.5.2Analysis of Effects and Consequences15.3-10 15.3.6Single Rod Cluster Control Assembly Withdrawal at Full Power15.3-1015.3.6.1Identification of Causes and Accident Description15.3-1015.3.6.2Analysis of Effects and Consequences15.3-11 15.3.6.3Conclusions15.3-1115.4CONDITION IV - LIMITING FAULTS15.4-115.4.1Major Reactor Coolant System Pipe Ru ptures (Loss of Coolant Accident)15.4-115.4.1.1Thermal Analysis15.4-315.4.1.2Hydrogen Production and Accumulation15.4-615.4.2Major Secondary System Pipe Rupture15.4-1215.4.2.1Major Rupture of a Main Steam Line15.4-1215.4.2.2Major Rupture of a Main Feedwater Pipe15.4-1915.4.3Steam Generator Tube Rupture15.4-2315.4.3.1Identification of Causes and Accident Description15.4-2315.4.3.2Analysis of Effects and Consequences15.4-26 15.4.3.3Conclusions15.4-3215.4.4Single Reactor Coolant Pump Locked Rotor15.4-3215.4.4.1Identification of Causes and Accident Description15.4-32 15.4.4.2Analysis of Effects and Consequences15.4-3215.4.4.3Conclusions15.4-3515.4.5Fuel Handling Accident15.4-3515.4.5.1Identification of Causes and Accident Description15.4-3515.4.5.2Analysis of Effects and Consequences15.4-35 15.4.6Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection)15.4-3515.4.6.1Identification of Causes and Accident Description15.4-35 Table of Contents1-xlixWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page15.4.6.2Analysis of Effects and Consequences15.4-3915.4.6.3Conclusions15.4-4315.5ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS15.5-115.5.1Environmental Consequences of a Postulated Loss of AC Power to the Plant Auxil-iaries15.5-115.5.2Environmental Consequences of a Postulated Waste Gas Decay Tank Rupture15.5-215.5.3Environmental Consequences of a Postulated Loss of Coolant Accident15.5-215.5.4Environmental Consequences of a Postulated Steam Line Break15.5-1815.5.5Environmental Consequences of a Postulated Steam Generator Tube Rupture15.5-1915.5.6Environmental Consequences of a Po stulated Fuel Handling Accident15.5-2015.5.7Environmental Consequences of a Postulated Rod Ejection Accident15.5-22027_TVA_WB_FSAR_Section_16.pdf16.0TECHNICAL SPECIFICATIONS16.1PROPOSED TECHNICAL SPECIFICATIONS (NOT USED)16.1-116.2PROPOSED FINAL TECHNICAL SPECIFICATIONS16.2-116.3RELOCATED SPECIFICATIONS16.3-116.3.1Discussion16.3-116.3.2Document Control16.3-1 16.3.3Changes to the Relocated Specifications16.3-1028_TVA_WB_FSAR_Section_17.0.pdf17.0QUALITY ASSURANCE17.1Quality Assurance During Design and Construction17.1-117.1.1TVA Organization17.1-1 17.1.2Quality Assurance Program17.1-117.1AWESTINGHOUSE NUCLEAR ENERGY SYSTEM DIVISIONS QUALITY ASSUR-ANCE PLAN17.1-217.2QUALITY ASSURANCE FOR STATION OPERATION17.2-117.2.1Identification of Safety-Related Features17.2-1 1-lTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle PageTHIS PAGE INTENTIONALLY BLANK