ML081010116

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Review Topics for Safety Evaluation, Attachment 1
ML081010116
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 05/08/2008
From: Raghavan L
NRC/NRR/ADRO/DORL/WBSPB
To: Bhatnagar A
Tennessee Valley Authority
Williams, Joe, NRR/DNRL/NRBA, 415-1470
Shared Package
ML080860033 List:
References
TAC MD6311
Download: ML081010116 (79)
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SubsectionTitle Table 1. Table of ContentsProposed Safety Evaluation Review TopicsWatts Bar Nuclear Plant Unit 21.0.0Introduction and General Discussion1.1.0Introduction1.1.1Metrication1.1.2Proprietary Information1.1.4Additional Information1.2.0General Design Description1.3.0Comparison With Similar Facility Designs1.3.1Comparison With the Sequoyah Nuclear Plant1.3.2Comparison With Other Facilities1.4.0Identification of Agents and Contractors1.5.0Summary of Principal Review Matters1.6.0Modifications to the Watts Bar Facility During the Course of NRC Review1.7.0Summary of Outstanding Issues1.8.0Confirmatory Issues1.9.0License Conditions1.10.0Unresolved Safety Issues2.0.0Site Envelope2.1.0Geography and Demography2.1.1Site Location and Description2.1.2Exclusion Area Authority and Control2.1.3Population Distribution2.1.4Conclusions2.2.0Nearby Industrial, Transportation, and Military Facilities2.2.1Transportation Routes2.2.2Nearby Facilities2.2.3Conclusions2.3.0Meteorology2.3.1Regional Climatology2.3.2Local MeteorologyX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 1 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 22.3.3Onsite Meteorological Measurements Program2.3.4Short-Term (Accident) Atmospheric Diffusion Estimates2.3.5Long-Term (Routine) Diffusion Estimates2.4.0Hydrologic Engineering2.4.1Introduction2.4.2Hydrologic Description2.4.3Flood Potential2.4.4Local Intense Precipitation in Plant Area2.4.5Roof Drainage2.4.6Ultimate Heat Sink2.4.7Groundwater2.4.8Design Basis for Subsurface Hydrostatic Loading2.4.9Transport of Liquid Releases2.4.10Flooding Protection Requirements and Technical Specifications2.5.0Geological, Seismological, and Geotechnical Engineering2.5.1Geology2.5.2Seismology2.5.3Surface Faulting2.5.4Stability of Subsurface Materials and Foundations2.5.5Stability of Slopes2.5.6Embankments and Dams2.6.0References3.0.0Design of Structures, Components, Equipment, and Systems3.1.0Introduction3.1.1Conformance With General Design Criteria3.1.2Conformance With Industry Codes and Standards3.2.0Classification of Structures, Systems, and Components3.2.1 Seismic Qualification3.2.2System Quality Group Classification3.3.0Wind and Tornado Loadings3.3.1Wind LoadingX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 2 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 23.3.2Tornado Loading3.4.0Flood Level (Flood) Design3.4.1Flood Protection3.5.0Missile Protection3.5.1Missile Selection and Description3.5.2Structures, Systems, and Components To Be Protected From Externally Generated Missiles3.5.3Barrier Design Procedures3.6.0Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping3.6.1Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment3.6.2Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping3.6.3Leak-Before-Break Evaluation Procedures3.7.0Seismic Design3.7.1Seismic Input3.7.2Seismic Analysis3.7.3Seismic Subsystem Analysis3.7.4Seismic Instrumentation3.8.0Design of Seismic Category I Structures3.8.1Steel Containment3.8.2Concrete and Structural Steel Internal Structures3.8.3Other Seismic Category I Structures3.8.4Foundations3.9.0Mechanical Systems and Components3.9.1Special Topics for Mechanical Components3.9.2Dynamic Testing and Analysis of Systems, Components, and Equipment3.9.3ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures3.9.4Control Rod Drive Systems3.9.5Reactor Pressure Vessel InternalsX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 3 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 23.9.6Inservice Testing of Pumps and Valves3.10.0Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment3.11.0Environmental Qualification of Mechanical and Electrical Equipment3.13.0Threaded Fasteners - ASME Code Class 1, 2, and 3 [SRP TOC]4.0.0Reactor4.1.0Introduction4.2.0Fuel System Design4.2.1Description4.2.2Thermal Performance4.2.3Mechanical Performance4.2.4Surveillance4.2.5Fuel Design Conclusions4.3.0Nuclear Design4.3.1Design Basis4.3.2Design Description4.3.3Analytical Methods4.3.4Summary of Evaluation Findings4.4.0Thermal-Hydraulic Design4.4.1Perfomance in Safety Criteria4.4.2Design Bases4.4.3Thermal-Hydraulic Design Methodology4.4.4Operating Abnormalities4.4.5Loose Parts Monitoring System4.4.6Thermal-Hydraulic Comparison4.4.7N-1 Loop Operation4.4.8Instrumentation for Inadequate Core Cooling Detection (II.F.2)4.4.9Summary and Conclusion4.5.0Reactor Materials4.5.1Control Rod Drive Structural Materials4.5.2Reactor Internals and Core Support MaterialsX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 4 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 24.6.0Functional Design of Reactivity Control Systems5.0.0Reactor Coolant System and Connected Systems5.1.0Summary Description5.2.0Integrity of Reactor Coolant Pressure Boundary5.2.1Compliance With Codes and Code Cases5.2.2Overpressure Protection5.2.3Reactor Coolant Pressure Boundary Materials5.2.4RCS Pressure Boundary Inservice Inspection and Testing5.2.5Reactor Coolant Pressure Boundary Leakage Detection5.3.0Reactor Vessel5.3.1Reactor Vessel Materials5.3.2Pressure-Temperature Limits5.3.3Reactor Vessel Integrity5.4.0Component and Subsystem Design5.4.1Reactor Coolant Pumps5.4.2Steam Generators5.4.3Residual Heat Removal System5.4.4Pressurizer Relief Tank5.4.5Reactor Coolant System Vents (II.B.1)6.0.0Engineered Safety Features6.1.0Engineered Safety Features Materials6.1.1Metallic Materials6.1.2Organic Materials6.1.3Postaccident Emergency Cooling Water Chemistry6.2.0Containment Systems6.2.1Containment Functional Design6.2.2Containment Heat Removal Systems6.2.3Secondary Containment Functional Design6.2.4Containment Isolation System6.2.5Combustible Gas Control Systems6.2.6Containment Leakage TestingX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 5 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 26.2.7Fracture Prevention of Containment Pressure Boundary6.3.0Emergency Core Cooling System6.3.1System Design6.3.2Evaluation6.3.3Testing6.3.4Performance Evaluation6.3.5Conclusions6.4.0Control Room Habitability6.5.0Engineered Safety Feature (ESF) Filter Systems6.5.1ESF Atmosphere Cleanup Systems6.5.2Fission Product Cleanup System6.5.3Fission Product Control System6.5.4Ice Condenser as a Fission Product Control System6.6.0Inservice Inspection of Class 2 and 3 Components7.0.0Instrumentation and Controls7.1.0Introduction7.1.1General7.1.2Comparison with Other Plants7.1.3Design Criteria7.2.0Reactor Trip System7.2.1System Description7.2.2Manual Trip Switches7.2.3Testing of Reactor Trip Breaker Shunt Coils7.2.4Anticipatory Trips7.2.5Steam Generator Water Level Trip7.2.6Conclusions7.3.0Engineered Safety Features System7.3.1System Description7.3.2Containment Sump Level Measurement7.3.3Auxiliary Feedwater Initiation and Control7.3.4Failure Modes and Effects AnalysisX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 6 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 27.3.5IE Bulletin 80-067.3.6Conclusions7.4.0Systems Required for Safe Shutdown7.4.1System Description7.4.2Safe Shutdown from Auxiliary Control Room7.4.3Conclusions7.5.0Safety-Related Display Instrumentation7.5.1System Description7.5.2Post-Accident Monitoring System7.5.3IE Bulletin 79-277.5.4Conclusions7.6.0All Other Systems Required for Safety7.6.1System Description7.6.2Residual Heat Removal System Bypass Valves7.6.3Upper Head Injection Manual Control7.6.4Protection Against Spurious Actuation of Motor-Operated Valves7.6.5Overpressure Protection During Low Temperature Operation7.6.6Valve Power Lockout7.6.7Cold Leg Accumulator Valve Interlocks and Position Indication7.6.8Automatic Switchover From Injection to Recirculation Mode7.6.9Conclusions7.7.0Control Systems Not Required for Safety7.7.1System Description7.7.2Safety System Status Monitoring System7.7.3Volume Control Tank Level Control System7.7.4Pressurizer and Steam Generator Overfill7.7.5IE Information Notice 79-227.7.6Multiple Control System Failures7.7.7Conclusions7.7.8Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC)X.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 7 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 27.8.0NUREG-0737 Items7.8.1Relief and Safety Valve Position Indication (II.D.3)7.8.2Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2)7.8.3Proportional Integral Derivative Control Modification (II.K.3.9)7.8.4Proposed Anticipatory Trip Modification (II.K.3.10)7.8.5Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12)7.9.0Data Communication Systems [SRP TOC]8.0.0Electric Power Systems8.1.0General8.2.0Offsite Power System8.2.1Compliance With GDC 58.2.2Compliance With GDC 178.2.3Compliance With GDC 188.2.4Evaluation Findings8.3.0Onsite Power Systems8.3.1Onsite AC Power System Compliance With GDC 178.3.2Onsite DC System Compliance With GDC 178.3.3Evaluation Findings8.4.0Station Blackout9.0.0Auxiliary Systems9.1.0Fuel Storage Facility9.1.1New Fuel Storage9.1.2Spent Fuel Storage9.1.3Spent Fuel Pool Cooling and Cleanup System9.1.4Fuel Handling System9.2.0Water Systems9.2.1Essential Raw Cooling Water and Raw Cooling Water Systems9.2.2Component Cooling System (Reactor Auxiliaries Cooling Water System)9.2.3Demineralized Water Makeup System9.2.4Potable and Sanitary Water Systems9.2.5Ultimate Heat SinkX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 8 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 29.2.6Condensate Storage Facilities9.3.0 Process Auxiliaries9.3.1Compressed Air System9.3.2Process Sampling System9.3.3Equipment and Floor Drainage System9.3.4Chemical and Volume Control System9.4.0Heating, Ventilation, and Air Conditioning Systems9.4.1Control Room Area Ventilation System9.4.2Fuel Handling Area Ventilation System9.4.3Auxiliary and Radwates Area Ventilation System9.4.4Turbine Building Area Ventilation System9.4.5Engineered Safety Features Ventilation System9.5.0Other Auxiliary Systems9.5.1Fire Protection9.5.2Communication Systems9.5.3Lighting System9.5.4Emergency Diesel Engine Fuel Oil Storage and Transfer System9.5.5Emergency Diesel Engine Cooling Water System9.5.6Emergency Diesel Engine Starting Systems9.5.7Emergency Diesel Engine Lubricating Oil System9.5.8Emergency Diesel Engine Combustion Air Intake and Exhaust System10.0.0Steam and Power Conversion System10.1.0Summary Description10.2.0Turbine Generator10.2.1Turbine Generator Design10.2.2Turbine Disc Integrity10.3.0Main Steam Supply System10.3.1Main Steam Supply System (up to and including the Main Steam Isolation Valves)10.3.2Main Steam Supply System10.3.3Steam and Feedwater System MaterialsX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 9 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 210.3.4Secondary Water Chemistry10.4.0Other Features10.4.1Main Condenser10.4.2Main Condenser Evacuation System10.4.3Turbine Gland Sealing System10.4.4Turbine Bypass System10.4.5Condenser Circulating Water System10.4.6Condensate Cleanup System10.4.7Condensate and Feedwater Systems10.4.8Steam Generator Blowdown System10.4.9Auxiliary Feedwater System11.0.0Radioactive Waste Management11.1.0Summary Description11.2.0Liquid Waste Management11.3.0Gaseous Waste Management11.4.0Solid Waste Management System11.5.0Process and Effluent Radiological Monitoring and Sampling Systems11.6.0Evaluation Findings11.7.0NUREG-0737 Items11.7.1Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))11.7.2Primary Coolant Outside Containment (III.D.1.1)12.0.0Radiation Protection12.1.0General12.2.0Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable12.3.0Radiation Sources12.4.0Radiation Protection Design Features12.5.0Dose Assessment12.6.0Health Physics Program12.7.0NUREG-0737 ItemsX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 10 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 212.7.1Plant Shielding (II.B.2)12.7.2High Range Incontainment Monitor (II.F.1(3))12.7.3Inplant Radioiodine Monitor (III.D.3.3)13.0.0Conduct of Operations13.1.0Organizational Structure of the Applicant13.1.1Management and Technical Organization13.1.2Corporate Organization and Technical Support13.1.3Plant Staff Organization13.2.0Training13.2.1Licensed Operator Training Program13.2.2Training for Nonlicensed Personnel13.3.0Emergency Preparedness Evaluation13.3.1Introduction13.3.2Evaluation of the Emergency Plan13.3.3Conclusions13.4.0Review and Audit13.5.0Plant Procedures13.5.1Administrative Procedures13.5.2Operating and Maintenance Procedures13.5.3NUREG-0737 Items13.6.0Physical Security Plan14.0.0Initial Test Program15.0.0Accident Analysis15.1.0General Discussion15.2.0Normal Operation and Anticipated Transients15.2.1Loss of Cooling Transients15.2.2Increased Cooling Transients15.2.3Change in Coolant Inventory Transients15.2.4Reactivity and Power Distribution Anomalies15.2.5Conclusions15.3.0Limiting AccidentsX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 11 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 215.3.1Loss-of-Coolant Accident15.3.2Steamline Break15.3.3Feedwater System Pipe Break15.3.4Reactor Coolant Pump Rotor Seizure15.3.5Reactor Coolant Pump Shaft Break15.3.6Anticipated Transients Without Scram15.3.7Conclusions15.4.0Radiological Consequences of Accidents15.4.1Loss-of-Coolant Accident15.4.2Main Steamline Break Outside of Containment15.4.3Steam Generator Tube Rupture15.4.4Control Rod Ejection Accident15.4.5Fuel-Handling Accident15.4.6Failure of Small Line Carrying Coolant Outside Containment15.4.7Postulated Radioactive Releases as a Result of Liquid Tank Failures15.5.0NUREG-0737 Items15.5.1Thermal Mechanical Report (II.K.2.13)15.5.2Voiding in the Reactor Coolant System During Transients (II.K.2.17)15.5.3Installation and Testing of Automatic Power-Operated Relief Valve Isolation System (II.K.3.1)Report on Overall Safety Effect of Power-Operated Relief Valve Isolation System (II.K.3.2)15.5.4Automatic Trip of Reactor Coolant Pumps (II.K.3.5)15.5.5Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31)15.6.0Relative Risk of Low Power Operation16.0.0Technical Specifications17.0.0Quality Assurance17.1.0General17.2.0Organization17.3.0Quality Assurance Program17.4.0ConclusionsX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 12 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 217.6.0Maintenance Rule18.0.0Control Room Design Review18.1.0General18.2.0Conclusions19.0.0Report of the Advisory Committee on Reactor Safeguards20.0.0Common Defense and Security21.0.0Financial Qualifications22.0.0Financial Protection and Indemnity Requirements22.1.0General22.2.0Preoperational Storage of Nuclear Fuel22.3.0Operating Licenses23.0.0Nuclear Performance Plan23.1.0Introduction23.2.0Corrective Actions23.2.1Cable Issues23.2.2Cable Tray and Tray Supports23.2.3Design Baseline and Verification Program23.2.4Electrical Conduit and Conduit Support23.2.5Electrical Issues23.2.6Equipment Seismic Qualification23.2.7Fire Protection23.2.8Hanger and Analysis Update Program23.2.9Heat Code Traceability 23.2.10Heating, Ventilation, and Air-Conditioning Duct and Duct Supports 23.2.11Instrument Lines 23.2.12Prestart Test Program 23.2.13QA Records 23.2.14Q-List 23.2.15Replacement Items Program (Piece Parts) 23.2.16Seismic Analysis 23.2.17Vendor Information ProgramX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 13 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 23.2.18Welding23.3.0Special Programs23.3.1Concrete Quality Program23.3.2Containment Cooling23.3.3Detailed Control Room Design Review23.3.4Environmental Qualification Program23.3.5Master Fuse List23.3.6Mechanical Equipment Qualification23.3.7Microbiologically Induced Corrosion (MIC)23.3.8Moderate Energy Line Break Flooding23.3.9Radiation Monitoring System 23.3.10Soil Liquefaction 23.3.11Use-as-is CAQs23.4.0Implementation, Verification, and Closure of Corrective Actions23.4.1Corrective Action Program Plans and Special Programs23.4.2Quality Verification Process23.5.0Management and Organization23.5.1Introduction23.5.2Organizational and Management Improvements23.5.3Conclusions23.6.0Operational Readiness23.7.0Employee Concerns23.8.0Allegations24.0.0Generic Issues25.0.0NUREG-0737 TMI Action Items26.0.0Other Regulatory Topics26.1.0License Conditions26.2.0Orders27.0.0ConclusionsAppendix A - Chronology of Radiological Review of Watts Bar Nuclear Plant Units 1 and 2, Operating License ReviewX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 14 of 15 SubsectionTitleTable 1, continued. Table of ContentsProposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2Appendix B - BibliographyAppendix C - Nuclear Regulatory Commission Unresolved Safety IssuesAppendix D - Evaluation of the Applicant's Control Room DesignAppendix E - Principal ContributorsAppendix F - AbbreviationsX.Y.Z = chapter.section.subsection.Chapter designations shown in bold.Page 15 of 15 SubsectionTitleTable 2. Status of NUREG-0847 Review TopicsWatts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*2.1.1Site Location and DescriptionYes2.1.2Exclusion Area Authority and ControlYes2.1.3Population Distribution No2.1.4Conclusions No2.2.1Transportation Routes No2.2.2Nearby Facilities No2.2.3Conclusions No2.3.1Regional ClimatologyYes2.3.2Local MeteorologyYes2.3.3Onsite Meteorological Measurements ProgramYes2.3.4Short-Term (Accident) Atmospheric Diffusion EstimatesYes2.3.5Long-Term (Routine) Diffusion EstimatesYes2.4.1IntroductionYes2.4.2Hydrologic DescriptionYes2.4.3Flood PotentialYes2.4.4Local Intense Precipitation in Plant AreaYes2.4.5Roof DrainageYes2.4.6Ultimate Heat SinkYes2.4.7GroundwaterYes2.4.8Design Basis for Subsurface Hydrostatic LoadingYes2.4.9Transport of Liquid Releases No2.4.10Flooding Protection Requirements and Technical SpecificationsYes2.5.0Geological, Seismological, and Geotechnical EngineeringYes2.5.1GeologyYes2.5.2Seismology No2.5.3Surface FaultingYesUnresolved items are shown in bold italics.Page 1 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*2.5.4Stability of Subsurface Materials and Foundations No2.5.5Stability of Slopes No2.5.6Embankments and DamsYes3.1.1Conformance With General Design CriteriaYes3.1.2Conformance With Industry Codes and StandardsYes3.2.1 Seismic QualificationYes3.2.2System Quality Group Classification No3.3.1Wind LoadingYes3.3.2Tornado LoadingYes3.4.1Flood ProtectionYes3.5.1Missile Selection and DescriptionYes3.5.2Structures, Systems, and Components To Be Protected From Externally Generated MissilesYes3.5.3Barrier Design ProceduresYes3.6.1Plant Design for Protection Against Postulated Piping Failures in Fluid No3.6.2Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of PipingYes3.6.3Leak-Before-Break Evaluation ProceduresYes3.7.1Seismic Input No3.7.2Seismic Analysis No3.7.3Seismic Subsystem Analysis No3.7.4Seismic InstrumentationYes3.8.1Steel ContainmentYes3.8.2Concrete and Structural Steel Internal Structures No3.8.3Other Seismic Category I Structures No3.8.4FoundationsYes3.9.1Special Topics for Mechanical Components No3.9.2Dynamic Testing and Analysis of Systems, Components, and EquipmentYesUnresolved items are shown in bold italics.Page 2 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*3.9.3ASME Code Class 1, 2, and 3 Components, Component Structures, and No3.9.4Control Rod Drive SystemsYes3.9.5Reactor Pressure Vessel InternalsYes3.9.6Inservice Testing of Pumps and Valves No3.10.0Seismic and Dynamic Qualification of Seismic Category I Mechanical No3.11.0Environmental Qualification of Mechanical and Electrical Equipment No4.2.1Description No4.2.2Thermal Performance No4.2.3Mechanical Performance No4.2.4SurveillanceYes4.2.5Fuel Design Conclusions No4.3.1Design Basis No4.3.2Design Description No4.3.3Analytical Methods No4.3.4Summary of Evaluation Findings No4.4.1Perfomance in Safety CriteriaYes4.4.2Design Bases No4.4.3Thermal-Hydraulic Design Methodology No4.4.4Operating Abnormalities No4.4.5Loose Parts Monitoring System No4.4.6Thermal-Hydraulic ComparisonYes4.4.7N-1 Loop Operation No4.4.8Instrumentation for Inadequate Core Cooling Detection (II.F.2)

No4.4.9Summary and Conclusion No4.5.1Control Rod Drive Structural MaterialsYes4.5.2Reactor Internals and Core Support MaterialsYesUnresolved items are shown in bold italics.Page 3 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*4.6.0Functional Design of Reactivity Control SystemsYes5.2.1Compliance With Codes and Code CasesYes5.2.2Overpressure ProtectionYes5.2.3Reactor Coolant Pressure Boundary MaterialsYes5.2.4RCS Pressure Boundary Inservice Inspection and Testing No5.2.5Reactor Coolant Pressure Boundary Leakage DetectionYes5.3.1Reactor Vessel MaterialsYes5.3.2Pressure-Temperature Limits No5.3.3Reactor Vessel Integrity No5.4.1Reactor Coolant PumpsYes5.4.2Steam GeneratorsYes5.4.3Residual Heat Removal System No5.4.4Pressurizer Relief TankYes5.4.5Reactor Coolant System Vents (II.B.1)Yes6.1.1Metallic MaterialsYes6.1.2Organic MaterialsYes6.1.3Postaccident Emergency Cooling Water ChemistryYes6.2.1Containment Functional DesignYes6.2.2Containment Heat Removal SystemsYes6.2.3Secondary Containment Functional DesignYes6.2.4Containment Isolation SystemYes6.2.5Combustible Gas Control Systems No6.2.6Containment Leakage TestingYes6.2.7Fracture Prevention of Containment Pressure BoundaryYes6.3.0Emergency Core Cooling SystemYes6.3.1System Design No6.3.2Evaluation No6.3.3Testing NoUnresolved items are shown in bold italics.Page 4 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*6.3.4Performance EvaluationYes6.3.5Conclusions No6.4.0Control Room HabitabilityYes6.5.1ESF Atmosphere Cleanup SystemsYes6.5.2Fission Product Cleanup SystemYes6.5.3Fission Product Control SystemYes6.5.4Ice Condenser as a Fission Product Control SystemYes6.6.0Inservice Inspection of Class 2 and 3 Components No7.1.1General No7.1.2Comparison with Other PlantsYes7.1.3Design Criteria No7.2.0Reactor Trip SystemYes7.2.1System Description No7.2.2Manual Trip SwitchesYes7.2.3Testing of Reactor Trip Breaker Shunt CoilsYes7.2.4Anticipatory TripsYes7.2.5Steam Generator Water Level Trip No7.2.6Conclusions No7.3.0Engineered Safety Features System No7.3.1System DescriptionYes7.3.2Containment Sump Level MeasurementYes7.3.3Auxiliary Feedwater Initiation and ControlYes7.3.4Failure Modes and Effects AnalysisYes7.3.5IE Bulletin 80-06Yes7.3.6Conclusions No7.4.1System DescriptionYes7.4.2Safe Shutdown from Auxiliary Control Room No7.4.3ConclusionsYesUnresolved items are shown in bold italics.Page 5 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*7.5.1System DescriptionYes7.5.2Post-Accident Monitoring System No7.5.3IE Bulletin 79-27Yes7.5.4Conclusions No7.6.1System DescriptionYes7.6.2Residual Heat Removal System Bypass ValvesYes7.6.3Upper Head Injection Manual ControlYes7.6.4Protection Against Spurious Actuation of Motor-Operated ValvesYes7.6.5Overpressure Protection During Low Temperature OperationYes7.6.6Valve Power LockoutYes7.6.7Cold Leg Accumulator Valve Interlocks and Position IndicationYes7.6.8Automatic Switchover From Injection to Recirculation ModeYes7.6.9ConclusionsYes7.7.1System DescriptionYes7.7.2Safety System Status Monitoring System No7.7.3Volume Control Tank Level Control SystemYes7.7.4Pressurizer and Steam Generator OverfillYes7.7.5IE Information Notice 79-22Yes7.7.6Multiple Control System FailuresYes7.7.7ConclusionsYes7.7.8Anticipated Transient Without Scram Mitigation System Actuation No7.8.0NUREG-0737 ItemsYes7.8.1Relief and Safety Valve Position Indication (II.D.3)

No7.8.2Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2)Yes7.8.3Proportional Integral Derivative Control Modification (II.K.3.9)Yes7.8.4Proposed Anticipatory Trip Modification (II.K.3.10)Yes7.8.5Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12)YesUnresolved items are shown in bold italics.Page 6 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*8.1.0GeneralYes8.2.1Compliance With GDC 5Yes8.2.2Compliance With GDC 17 No8.2.3Compliance With GDC 18Yes8.2.4Evaluation FindingsYes8.3.0Onsite Power SystemsYes8.3.1Onsite AC Power System Compliance With GDC 17 No8.3.2Onsite DC System Compliance With GDC 17 No8.3.3Evaluation Findings No9.0.0Auxiliary SystemsYes9.1.1New Fuel StorageYes9.1.2Spent Fuel StorageYes9.1.3Spent Fuel Pool Cooling and Cleanup SystemYes9.1.4Fuel Handling System No9.2.1Essential Raw Cooling Water and Raw Cooling Water Systems No9.2.2Component Cooling System (Reactor Auxiliaries Cooling Water System)

No9.2.3Demineralized Water Makeup SystemYes9.2.4Potable and Sanitary Water SystemsYes9.2.5Ultimate Heat SinkYes9.2.6Condensate Storage FacilitiesYes9.3.1Compressed Air SystemYes9.3.2Process Sampling System No9.3.3Equipment and Floor Drainage SystemYes9.3.4Chemical and Volume Control SystemYes9.4.1Control Room Area Ventilation SystemYes9.4.2Fuel Handling Area Ventilation SystemYes9.4.3Auxiliary and Radwates Area Ventilation SystemYes9.4.4Turbine Building Area Ventilation SystemYesUnresolved items are shown in bold italics.Page 7 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*9.4.5Engineered Safety Features Ventilation System No9.5.1Fire ProtectionYes9.5.2Communication Systems No9.5.3Lighting SystemYes9.5.4Emergency Diesel Engine Fuel Oil Storage and Transfer SystemYes9.5.5Emergency Diesel Engine Cooling Water System No9.5.6Emergency Diesel Engine Starting Systems No9.5.7Emergency Diesel Engine Lubricating Oil System No9.5.8Emergency Diesel Engine Combustion Air Intake and Exhaust System No10.1.0Summary DescriptionYes10.2.1Turbine Generator DesignYes10.2.2Turbine Disc IntegrityYes10.3.0Main Steam Supply SystemYes10.3.1Main Steam Supply System (up to and including the Main Steam Isolation Valves)Yes10.3.2Main Steam Supply SystemYes10.3.3Steam and Feedwater System MaterialsYes10.3.4Secondary Water Chemistry No10.4.1Main CondenserYes10.4.2Main Condenser Evacuation SystemYes10.4.3Turbine Gland Sealing SystemYes10.4.4Turbine Bypass SystemYes10.4.5Condenser Circulating Water SystemYes10.4.6Condensate Cleanup SystemYes10.4.7Condensate and Feedwater SystemsYes10.4.8Steam Generator Blowdown SystemYes10.4.9Auxiliary Feedwater SystemYes11.1.0Summary Description NoUnresolved items are shown in bold italics.Page 8 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*11.2.0Liquid Waste ManagementYes11.3.0Gaseous Waste ManagementYes11.4.0Solid Waste Management System No11.5.0Process and Effluent Radiological Monitoring and Sampling Systems No11.6.0Evaluation Findings No11.7.0NUREG-0737 Items No11.7.1Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors No11.7.2Primary Coolant Outside Containment (III.D.1.1)

No12.1.0General No12.2.0Ensuring that Occupational Radiation Doses Are As Low As Reasonably No12.3.0Radiation Sources No12.4.0Radiation Protection Design Features No12.5.0Dose Assessment No12.6.0Health Physics Program No12.7.1Plant Shielding (II.B.2)

No12.7.2High Range Incontainment Monitor (II.F.1(3))

No12.7.3Inplant Radioiodine Monitor (III.D.3.3)

No13.1.1Management and Technical OrganizationYes13.1.2Corporate Organization and Technical SupportYes13.1.3Plant Staff Organization No13.2.1Licensed Operator Training ProgramYes13.2.2Training for Nonlicensed PersonnelYes13.3.1Introduction No13.3.2Evaluation of the Emergency Plan No13.3.3Conclusions No13.4.0Review and Audit NoUnresolved items are shown in bold italics.Page 9 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*13.5.1Administrative ProceduresYes13.5.2Operating and Maintenance ProceduresYes13.5.3NUREG-0737 ItemsYes13.6.0Physical Security Plan No14.0.0Initial Test ProgramYes15.1.0General DiscussionYes15.2.0Normal Operation and Anticipated Transients No15.2.1Loss of Cooling TransientsYes15.2.2Increased Cooling TransientsYes15.2.3Change in Coolant Inventory Transients No15.2.4Reactivity and Power Distribution Anomalies No15.2.5ConclusionsYes15.3.0Limiting AccidentsYes15.3.1Loss-of-Coolant Accident No15.3.2Steamline Break No15.3.3Feedwater System Pipe Break No15.3.4Reactor Coolant Pump Rotor Seizure No15.3.5Reactor Coolant Pump Shaft Break No15.3.6Anticipated Transients Without Scram No15.3.7ConclusionsYes15.4.0Radiological Consequences of AccidentsYes15.4.1Loss-of-Coolant Accident No15.4.2Main Steamline Break Outside of Containment No15.4.3Steam Generator Tube Rupture No15.4.4Control Rod Ejection Accident No15.4.5Fuel-Handling Accident No15.4.6Failure of Small Line Carrying Coolant Outside Containment No15.4.7Postulated Radioactive Releases as a Result of Liquid Tank Failures NoUnresolved items are shown in bold italics.Page 10 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitleTable 2, continued. Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*15.5.1Thermal Mechanical Report (II.K.2.13)

No15.5.2Voiding in the Reactor Coolant System During Transients (II.K.2.17)Yes15.5.3Installation and Testing of Automatic Power-Operated Relief Valve Isolation System (II.K.3.1)Report on Overall Safety Effect of Power-Operated Relief Valve Isolation No15.5.4Automatic Trip of Reactor Coolant Pumps (II.K.3.5)

No15.5.5Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations No15.6.0Relative Risk of Low Power OperationYes16.0.0Technical Specifications No17.1.0GeneralYes17.2.0OrganizationYes17.3.0Quality Assurance ProgramYes17.4.0ConclusionsYes18.1.0General No18.2.0Conclusions No20.0.0Common Defense and SecurityYes21.0.0Financial QualificationsYes22.1.0GeneralYes22.2.0Preoperational Storage of Nuclear FuelYes22.3.0Operating LicensesYesUnresolved items are shown in bold italics.Page 11 of 11*Resolved means that a topic was previously reviewed and approved in NUREG-0847 or its supplements.

SubsectionTitle Table 3. Review Topics Resolved in NUREG-0847Watts Bar Nuclear Plant Unit 22.1.1Site Location and Description2.1.2Exclusion Area Authority and Control2.3.1Regional Climatology2.3.2Local Meteorology2.3.3Onsite Meteorological Measurements Program2.3.4Short-Term (Accident) Atmospheric Diffusion Estimates2.3.5Long-Term (Routine) Diffusion Estimates2.4.1Introduction2.4.2Hydrologic Description2.4.3Flood Potential2.4.4Local Intense Precipitation in Plant Area2.4.5Roof Drainage2.4.6Ultimate Heat Sink2.4.7Groundwater2.4.8Design Basis for Subsurface Hydrostatic Loading2.4.10Flooding Protection Requirements and Technical Specifications2.5.0Geological, Seismological, and Geotechnical Engineering2.5.1Geology2.5.3Surface Faulting2.5.6Embankments and Dams3.1.1Conformance With General Design Criteria3.1.2Conformance With Industry Codes and Standards3.2.1 Seismic Qualification3.3.1Wind Loading3.3.2Tornado Loading3.4.1Flood Protection Page 1 of 7 SubsectionTitleTable 3, continued. Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 23.5.1Missile Selection and Description3.5.2Structures, Systems, and Components To Be Protected From Externally Generated Missiles3.5.3Barrier Design Procedures3.6.2Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping3.6.3Leak-Before-Break Evaluation Procedures3.7.4Seismic Instrumentation3.8.1Steel Containment3.8.4Foundations3.9.2Dynamic Testing and Analysis of Systems, Components, and Equipment3.9.4Control Rod Drive Systems3.9.5Reactor Pressure Vessel Internals4.2.4Surveillance4.4.1Perfomance in Safety Criteria4.4.6Thermal-Hydraulic Comparison4.5.1Control Rod Drive Structural Materials4.5.2Reactor Internals and Core Support Materials4.6.0Functional Design of Reactivity Control Systems5.2.1Compliance With Codes and Code Cases5.2.2Overpressure Protection5.2.3Reactor Coolant Pressure Boundary Materials5.2.5Reactor Coolant Pressure Boundary Leakage Detection5.3.1Reactor Vessel Materials5.4.1Reactor Coolant Pumps5.4.2Steam Generators5.4.4Pressurizer Relief Tank5.4.5Reactor Coolant System Vents (II.B.1)

Page 2 of 7 SubsectionTitleTable 3, continued. Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 26.1.1Metallic Materials6.1.2Organic Materials6.1.3Postaccident Emergency Cooling Water Chemistry6.2.1Containment Functional Design6.2.2Containment Heat Removal Systems6.2.3Secondary Containment Functional Design6.2.4Containment Isolation System6.2.6Containment Leakage Testing6.2.7Fracture Prevention of Containment Pressure Boundary6.3.0Emergency Core Cooling System6.3.4Performance Evaluation6.4.0Control Room Habitability6.5.1ESF Atmosphere Cleanup Systems6.5.2Fission Product Cleanup System6.5.3Fission Product Control System6.5.4Ice Condenser as a Fission Product Control System7.1.2Comparison with Other Plants7.2.0Reactor Trip System7.2.2Manual Trip Switches7.2.3Testing of Reactor Trip Breaker Shunt Coils7.2.4Anticipatory Trips7.3.1System Description7.3.2Containment Sump Level Measurement7.3.3Auxiliary Feedwater Initiation and Control7.3.4Failure Modes and Effects Analysis7.3.5IE Bulletin 80-067.4.1System Description Page 3 of 7 SubsectionTitleTable 3, continued. Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 27.4.3Conclusions7.5.1System Description7.5.3IE Bulletin 79-277.6.1System Description7.6.2Residual Heat Removal System Bypass Valves7.6.3Upper Head Injection Manual Control7.6.4Protection Against Spurious Actuation of Motor-Operated Valves7.6.5Overpressure Protection During Low Temperature Operation7.6.6Valve Power Lockout7.6.7Cold Leg Accumulator Valve Interlocks and Position Indication7.6.8Automatic Switchover From Injection to Recirculation Mode7.6.9Conclusions7.7.1System Description7.7.3Volume Control Tank Level Control System7.7.4Pressurizer and Steam Generator Overfill7.7.5IE Information Notice 79-227.7.6Multiple Control System Failures7.7.7Conclusions7.8.0NUREG-0737 Items7.8.2Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2)7.8.3Proportional Integral Derivative Control Modification (II.K.3.9)7.8.4Proposed Anticipatory Trip Modification (II.K.3.10)7.8.5Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12)8.1.0General8.2.1Compliance With GDC 58.2.3Compliance With GDC 188.2.4Evaluation Findings Page 4 of 7 SubsectionTitleTable 3, continued. Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 28.3.0Onsite Power Systems9.0.0Auxiliary Systems9.1.1New Fuel Storage9.1.2Spent Fuel Storage9.1.3Spent Fuel Pool Cooling and Cleanup System9.2.3Demineralized Water Makeup System9.2.4Potable and Sanitary Water Systems9.2.5Ultimate Heat Sink9.2.6Condensate Storage Facilities9.3.1Compressed Air System9.3.3Equipment and Floor Drainage System9.3.4Chemical and Volume Control System9.4.1Control Room Area Ventilation System9.4.2Fuel Handling Area Ventilation System9.4.3Auxiliary and Radwates Area Ventilation System9.4.4Turbine Building Area Ventilation System9.5.1Fire Protection9.5.3Lighting System9.5.4Emergency Diesel Engine Fuel Oil Storage and Transfer System10.1.0Summary Description10.2.1Turbine Generator Design10.2.2Turbine Disc Integrity10.3.0Main Steam Supply System10.3.1Main Steam Supply System (up to and including the Main Steam Isolation Valves)10.3.2Main Steam Supply System10.3.3Steam and Feedwater System Materials Page 5 of 7 SubsectionTitleTable 3, continued. Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 210.4.1Main Condenser10.4.2Main Condenser Evacuation System10.4.3Turbine Gland Sealing System10.4.4Turbine Bypass System10.4.5Condenser Circulating Water System10.4.6Condensate Cleanup System10.4.7Condensate and Feedwater Systems10.4.8Steam Generator Blowdown System10.4.9Auxiliary Feedwater System11.2.0Liquid Waste Management11.3.0Gaseous Waste Management13.1.1Management and Technical Organization13.1.2Corporate Organization and Technical Support13.2.1Licensed Operator Training Program13.2.2Training for Nonlicensed Personnel13.5.1Administrative Procedures13.5.2Operating and Maintenance Procedures13.5.3NUREG-0737 Items14.0.0Initial Test Program15.1.0General Discussion15.2.1Loss of Cooling Transients15.2.2Increased Cooling Transients15.2.5Conclusions15.3.0Limiting Accidents15.3.7Conclusions15.4.0Radiological Consequences of Accidents15.5.2Voiding in the Reactor Coolant System During Transients (II.K.2.17)

Page 6 of 7 SubsectionTitleTable 3, continued. Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 215.6.0Relative Risk of Low Power Operation17.1.0General17.2.0Organization17.3.0Quality Assurance Program17.4.0Conclusions20.0.0Common Defense and Security21.0.0Financial Qualifications22.1.0General22.2.0Preoperational Storage of Nuclear Fuel22.3.0Operating Licenses Page 7 of 7 SubsectionTitle Table 4. Review Topics Unresolved in NUREG-0847Watts Bar Nuclear Plant Unit 22.1.3Population Distribution2.1.4Conclusions2.2.1Transportation Routes2.2.2Nearby Facilities2.2.3Conclusions2.4.9Transport of Liquid Releases2.5.2Seismology2.5.4Stability of Subsurface Materials and Foundations2.5.5Stability of Slopes3.2.2System Quality Group Classification3.6.1Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment3.7.1Seismic Input3.7.2Seismic Analysis3.7.3Seismic Subsystem Analysis3.8.2Concrete and Structural Steel Internal Structures3.8.3Other Seismic Category I Structures3.9.1Special Topics for Mechanical Components3.9.3ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures3.9.6Inservice Testing of Pumps and Valves3.10.0Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment3.11.0Environmental Qualification of Mechanical and Electrical Equipment4.2.1Description4.2.2Thermal Performance4.2.3Mechanical Performance Page 1 of 5 SubsectionTitleTable 4, continued. Review Topics Unresolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 24.2.5Fuel Design Conclusions4.3.1Design Basis4.3.2Design Description4.3.3Analytical Methods4.3.4Summary of Evaluation Findings4.4.2Design Bases4.4.3Thermal-Hydraulic Design Methodology4.4.4Operating Abnormalities4.4.5Loose Parts Monitoring System4.4.7N-1 Loop Operation4.4.8Instrumentation for Inadequate Core Cooling Detection (II.F.2)4.4.9Summary and Conclusion5.2.4RCS Pressure Boundary Inservice Inspection and Testing5.3.2Pressure-Temperature Limits5.3.3Reactor Vessel Integrity5.4.3Residual Heat Removal System6.2.5Combustible Gas Control Systems6.3.1System Design6.3.2Evaluation6.3.3Testing6.3.5Conclusions6.6.0Inservice Inspection of Class 2 and 3 Components7.1.1General7.1.3Design Criteria7.2.1System Description7.2.5Steam Generator Water Level Trip7.2.6Conclusions7.3.0Engineered Safety Features System Page 2 of 5 SubsectionTitleTable 4, continued. Review Topics Unresolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 27.3.6Conclusions7.4.2Safe Shutdown from Auxiliary Control Room7.5.2Post-Accident Monitoring System7.5.4Conclusions7.7.2Safety System Status Monitoring System7.7.8Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC)7.8.1Relief and Safety Valve Position Indication (II.D.3)8.2.2Compliance With GDC 178.3.1Onsite AC Power System Compliance With GDC 178.3.2Onsite DC System Compliance With GDC 178.3.3Evaluation Findings9.1.4Fuel Handling System9.2.1Essential Raw Cooling Water and Raw Cooling Water Systems9.2.2Component Cooling System (Reactor Auxiliaries Cooling Water System)9.3.2Process Sampling System9.4.5Engineered Safety Features Ventilation System9.5.2Communication Systems9.5.5Emergency Diesel Engine Cooling Water System9.5.6Emergency Diesel Engine Starting Systems9.5.7Emergency Diesel Engine Lubricating Oil System9.5.8Emergency Diesel Engine Combustion Air Intake and Exhaust System10.3.4Secondary Water Chemistry11.1.0Summary Description11.4.0Solid Waste Management System11.5.0Process and Effluent Radiological Monitoring and Sampling Systems11.6.0Evaluation Findings11.7.0NUREG-0737 Items Page 3 of 5 SubsectionTitleTable 4, continued. Review Topics Unresolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 211.7.1Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))11.7.2Primary Coolant Outside Containment (III.D.1.1)12.1.0General12.2.0Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable12.3.0Radiation Sources12.4.0Radiation Protection Design Features12.5.0Dose Assessment12.6.0Health Physics Program12.7.1Plant Shielding (II.B.2)12.7.2High Range Incontainment Monitor (II.F.1(3))12.7.3Inplant Radioiodine Monitor (III.D.3.3)13.1.3Plant Staff Organization13.3.1Introduction13.3.2Evaluation of the Emergency Plan13.3.3Conclusions13.4.0Review and Audit13.6.0Physical Security Plan15.2.0Normal Operation and Anticipated Transients15.2.3Change in Coolant Inventory Transients15.2.4Reactivity and Power Distribution Anomalies15.3.1Loss-of-Coolant Accident15.3.2Steamline Break15.3.3Feedwater System Pipe Break15.3.4Reactor Coolant Pump Rotor Seizure15.3.5Reactor Coolant Pump Shaft Break15.3.6Anticipated Transients Without Scram Page 4 of 5 SubsectionTitleTable 4, continued. Review Topics Unresolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 215.4.1Loss-of-Coolant Accident15.4.2Main Steamline Break Outside of Containment15.4.3Steam Generator Tube Rupture15.4.4Control Rod Ejection Accident15.4.5Fuel-Handling Accident15.4.6Failure of Small Line Carrying Coolant Outside Containment15.4.7Postulated Radioactive Releases as a Result of Liquid Tank Failures15.5.1Thermal Mechanical Report (II.K.2.13)15.5.3Installation and Testing of Automatic Power-Operated Relief Valve Isolation System (II.K.3.1)Report on Overall Safety Effect of Power-Operated Relief Valve Isolation System (II.K.3.2)15.5.4Automatic Trip of Reactor Coolant Pumps (II.K.3.5)15.5.5Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31)16.0.0Technical Specifications18.1.0General18.2.0Conclusions Page 5 of 5 SubsectionTitle Table 5. NUREG-0847 Review Topics Where NRC Conclusions Do Not Match TVA (NRC = Open, TVA = Closed)2.5.2Seismology2.5.4Stability of Subsurface Materials and Foundations2.5.5Stability of Slopes3.2.2System Quality Group Classification3.6.1Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment3.7.1Seismic Input3.7.2Seismic Analysis3.8.2Concrete and Structural Steel Internal Structures3.8.3Other Seismic Category I Structures3.9.1Special Topics for Mechanical Components3.9.3ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures3.9.6Inservice Testing of Pumps and Valves3.10.0Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment4.2.1Description4.2.3Mechanical Performance4.3.1Design Basis4.3.2Design Description4.3.3Analytical Methods4.3.4Summary of Evaluation Findings4.4.2Design Bases4.4.4Operating Abnormalities4.4.7N-1 Loop Operation5.4.3Residual Heat Removal System6.3.1System Design Page 1 of 4 SubsectionTitleTable 5, continued. NUREG-0847 Review Topics Where NRC Conclusions Do Not Match TVA(NRC = Open, TVA = Closed)6.3.2Evaluation6.3.3Testing6.3.5Conclusions7.1.1General7.2.1System Description7.2.5Steam Generator Water Level Trip7.3.0Engineered Safety Features System7.4.2Safe Shutdown from Auxiliary Control Room7.5.2Post-Accident Monitoring System7.7.2Safety System Status Monitoring System7.7.8Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC)7.8.1Relief and Safety Valve Position Indication (II.D.3)8.2.2Compliance With GDC 178.3.1Onsite AC Power System Compliance With GDC 178.3.2Onsite DC System Compliance With GDC 178.3.3Evaluation Findings9.1.4Fuel Handling System9.2.2Component Cooling System (Reactor Auxiliaries Cooling Water System)9.3.2Process Sampling System9.4.5Engineered Safety Features Ventilation System9.5.2Communication Systems9.5.5Emergency Diesel Engine Cooling Water System9.5.6Emergency Diesel Engine Starting Systems9.5.7Emergency Diesel Engine Lubricating Oil System9.5.8Emergency Diesel Engine Combustion Air Intake and Exhaust System11.1.0Summary Description Page 2 of 4 SubsectionTitleTable 5, continued. NUREG-0847 Review Topics Where NRC Conclusions Do Not Match TVA(NRC = Open, TVA = Closed)11.6.0Evaluation Findings11.7.0NUREG-0737 Items11.7.1Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))12.1.0General12.2.0Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable12.3.0Radiation Sources12.4.0Radiation Protection Design Features12.5.0Dose Assessment12.6.0Health Physics Program 12.7.1Plant Shielding (II.B.2)12.7.2High Range Incontainment Monitor (II.F.1(3))12.7.3Inplant Radioiodine Monitor (III.D.3.3)13.1.3Plant Staff Organization13.3.1Introduction13.3.2Evaluation of the Emergency Plan13.3.3Conclusions13.6.0Physical Security Plan15.2.0Normal Operation and Anticipated Transients15.2.3Change in Coolant Inventory Transients15.2.4Reactivity and Power Distribution Anomalies15.3.1Loss-of-Coolant Accident15.3.2Steamline Break15.3.3Feedwater System Pipe Break15.3.4Reactor Coolant Pump Rotor Seizure15.3.5Reactor Coolant Pump Shaft Break15.3.6Anticipated Transients Without Scram Page 3 of 4 SubsectionTitleTable 5, continued. NUREG-0847 Review Topics Where NRC Conclusions Do Not Match TVA(NRC = Open, TVA = Closed)15.4.1Loss-of-Coolant Accident15.4.2Main Steamline Break Outside of Containment15.4.3Steam Generator Tube Rupture15.4.4Control Rod Ejection Accident15.4.5Fuel-Handling Accident15.4.6Failure of Small Line Carrying Coolant Outside Containment15.4.7Postulated Radioactive Releases as a Result of Liquid Tank Failures15.5.1Thermal Mechanical Report (II.K.2.13)15.5.3Installation and Testing of Automatic Power-Operated Relief Valve Isolation System (II.K.3.1)

Report on Overall Safety Effect of Power-Operated Relief Valve Isolation System (II.K.3.2)15.5.4Automatic Trip of Reactor Coolant Pumps (II.K.3.5)15.5.5Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31)

Page 4 of 4 SubsectionTitle Table 6. Open NUREG-0847 Review Topics Requiring Additional Information to Resolve2.5.2Seismology2.5.4Stability of Subsurface Materials and Foundations2.5.5Stability of Slopes3.2.2System Quality Group Classification3.6.1Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment3.7.1Seismic Input3.7.2Seismic Analysis3.8.2Concrete and Structural Steel Internal Structures3.8.3Other Seismic Category I Structures3.9.1Special Topics for Mechanical Components3.9.3ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures3.10.0Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment4.2.1Description4.2.3Mechanical Performance4.3.1Design Basis4.3.2Design Description4.3.3Analytical Methods4.3.4Summary of Evaluation Findings4.4.2Design Bases4.4.4Operating Abnormalities5.4.3Residual Heat Removal System6.3.1System Design6.3.2Evaluation6.3.3Testing Page 1 of 4 SubsectionTitleTable 6, continued. Open NUREG-0847 Review Topics Requiring Additional Information to Resolve6.3.5Conclusions7.1.1General7.2.1System Description7.2.5Steam Generator Water Level Trip7.3.0Engineered Safety Features System7.4.2Safe Shutdown from Auxiliary Control Room7.5.2Post-Accident Monitoring System7.7.2Safety System Status Monitoring System7.8.1Relief and Safety Valve Position Indication (II.D.3)8.2.2Compliance With GDC 178.3.1Onsite AC Power System Compliance With GDC 178.3.2Onsite DC System Compliance With GDC 178.3.3Evaluation Findings9.1.4Fuel Handling System9.2.2Component Cooling System (Reactor Auxiliaries Cooling Water System)9.3.2Process Sampling System9.4.5Engineered Safety Features Ventilation System9.5.2Communication Systems9.5.5Emergency Diesel Engine Cooling Water System9.5.6Emergency Diesel Engine Starting Systems9.5.7Emergency Diesel Engine Lubricating Oil System9.5.8Emergency Diesel Engine Combustion Air Intake and Exhaust System11.1.0Summary Description11.6.0Evaluation Findings11.7.0NUREG-0737 Items11.7.1Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))12.1.0General Page 2 of 4 SubsectionTitleTable 6, continued. Open NUREG-0847 Review Topics Requiring Additional Information to Resolve12.2.0Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable12.3.0Radiation Sources12.4.0Radiation Protection Design Features12.5.0Dose Assessment12.6.0Health Physics Program12.7.1Plant Shielding (II.B.2)12.7.2High Range Incontainment Monitor (II.F.1(3))12.7.3Inplant Radioiodine Monitor (III.D.3.3)13.1.3Plant Staff Organization13.3.1Introduction13.3.2Evaluation of the Emergency Plan13.3.3Conclusions13.6.0Physical Security Plan15.2.0Normal Operation and Anticipated Transients15.2.3Change in Coolant Inventory Transients15.2.4Reactivity and Power Distribution Anomalies15.3.1Loss-of-Coolant Accident15.3.2Steamline Break15.3.3Feedwater System Pipe Break15.3.4Reactor Coolant Pump Rotor Seizure15.3.5Reactor Coolant Pump Shaft Break15.3.6Anticipated Transients Without Scram15.4.1Loss-of-Coolant Accident15.4.2Main Steamline Break Outside of Containment15.4.3Steam Generator Tube Rupture15.4.4Control Rod Ejection Accident15.4.5Fuel-Handling Accident Page 3 of 4 SubsectionTitleTable 6, continued. Open NUREG-0847 Review Topics Requiring Additional Information to Resolve15.4.6Failure of Small Line Carrying Coolant Outside Containment15.4.7Postulated Radioactive Releases as a Result of Liquid Tank Failures15.5.1Thermal Mechanical Report (II.K.2.13)15.5.3Installation and Testing of Automatic Power-Operated Relief Valve Isolation System (II.K.3.1)Report on Overall Safety Effect of Power-Operated Relief Valve Isolation System (II.K.3.2)15.5.4Automatic Trip of Reactor Coolant Pumps (II.K.3.5)15.5.5Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31)

Page 4 of 4 Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2SubsectionTitle 2.1.1Site Location and DescriptionNUREG-0847 Supplement 0 2.1.2Exclusion Area Authority and ControlNUREG-0847 Supplement 0 2.1.3Population DistributionNUREG-0847 Supplement 0 2.1.4ConclusionsNUREG-0847 Supplement 0 2.2.1Transportation RoutesNUREG-0847 Supplement 0 2.2.2Nearby FacilitiesNUREG-0847 Supplement 0 2.2.3ConclusionsNUREG-0847 Supplement 0 2.3.1Regional ClimatologyNUREG-0847 Supplement 0 2.3.2Local MeteorologyNUREG-0847 Supplement 0 2.3.3Onsite Meteorological Measurements ProgramNUREG-0847 Supplement 0 2.3.4Short-Term (Accident) Atmospheric Diffusion EstimatesNUREG-0847 Supplement 0 2.3.5Long-Term (Routine) Diffusion EstimatesNUREG-0847 Supplement 0 2.4.1IntroductionNUREG-0847 Supplement 0 2.4.2Hydrologic DescriptionNUREG-0847 Supplement 0Page 1 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 2.4.3Flood PotentialNUREG-0847 Supplement 0 2.4.4Local Intense Precipitation in Plant AreaNUREG-0847 Supplement 0 2.4.5Roof DrainageNUREG-0847 Supplement 0 2.4.6Ultimate Heat SinkNUREG-0847 Supplement 0 2.4.7GroundwaterNUREG-0847 Supplement 0NUREG-0847 Supplement 3 2.4.8Design Basis for Subsurface Hydrostatic LoadingNUREG-0847 Supplement 0NUREG-0847 Supplement 3 2.4.9Transport of Liquid ReleasesNUREG-0847 Supplement 02.4.10Flooding Protection Requirements and Technical SpecificationsNUREG-0847 Supplement 0 2.5.0Geological, Seismological, and Geotechnical EngineeringNUREG-0847 Supplement 0 2.5.1GeologyNUREG-0847 Supplement 0 2.5.2SeismologyNUREG-0847 Supplement 0 2.5.3Surface FaultingNUREG-0847 Supplement 0Page 2 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 2.5.4Stability of Subsurface Materials and FoundationsNUREG-0847 Supplement 0NUREG-0847 Supplement 3 NUREG-0847 Supplement 9NUREG-0847 Supplement 11 2.5.5Stability of SlopesNUREG-0847 Supplement 0 2.5.6Embankments and DamsNUREG-0847 Supplement 0 3.1.1Conformance With General Design CriteriaNUREG-0847 Supplement 0 3.1.2Conformance With Industry Codes and StandardsNUREG-0847 Supplement 0 3.2.1 Seismic QualificationNUREG-0847 Supplement 0NUREG-0847 Supplement 3 NUREG-0847 Supplement 5NUREG-0847 Supplement 6NUREG-0847 Supplement 8 3.2.2System Quality Group ClassificationNUREG-0847 Supplement 0NUREG-0847 Supplement 3NUREG-0847 Supplement 6NUREG-0847 Supplement 7 NUREG-0847 Supplement 9 3.3.1Wind LoadingNUREG-0847 Supplement 0 3.3.2Tornado LoadingNUREG-0847 Supplement 0 3.4.1Flood ProtectionNUREG-0847 Supplement 0Page 3 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 3.5.1Missile Selection and DescriptionNUREG-0847 Supplement 0NUREG-0847 Supplement 9 NUREG-0847 Supplement 14 3.5.2Structures, Systems, and Components To Be Protected From Externally Generated MissilesNUREG-0847 Supplement 0NUREG-0847 Supplement 2 3.5.3Barrier Design ProceduresNUREG-0847 Supplement 0 3.6.1Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside ContainmentNUREG-0847 Supplement 0NUREG-0847 Supplement 14 3.6.2Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of PipingNUREG-0847 Supplement 0NUREG-0847 Supplement 14 3.6.3Leak-Before-Break Evaluation ProceduresNUREG-0847 Supplement 5 3.7.1Seismic InputNUREG-0847 Supplement 0NUREG-0847 Supplement 6NUREG-0847 Supplement 9NUREG-0847 Supplement 16 3.7.2Seismic AnalysisNUREG-0847 Supplement 0NUREG-0847 Supplement 6NUREG-0847 Supplement 8NUREG-0847 Supplement 11 NUREG-0847 Supplement 16Page 4 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 3.7.3Seismic Subsystem AnalysisNUREG-0847 Supplement 0NUREG-0847 Supplement 6 NUREG-0847 Supplement 7NUREG-0847 Supplement 8NUREG-0847 Supplement 9NUREG-0847 Supplement 12 3.7.4Seismic InstrumentationNUREG-0847 Supplement 0 3.8.1Steel ContainmentNUREG-0847 Supplement 0NUREG-0847 Supplement 3 3.8.2Concrete and Structural Steel Internal StructuresNUREG-0847 Supplement 0NUREG-0847 Supplement 7 3.8.3Other Seismic Category I StructuresNUREG-0847 Supplement 0NUREG-0847 Supplement 14NUREG-0847 Supplement 16 3.8.4FoundationsNUREG-0847 Supplement 0 3.9.1Special Topics for Mechanical ComponentsNUREG-0847 Supplement 0NUREG-0847 Supplement 6 NUREG-0847 Supplement 13 3.9.2Dynamic Testing and Analysis of Systems, Components, and EquipmentNUREG-0847 Supplement 0NUREG-0847 Supplement 14Page 5 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 3.9.3ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support StructuresNUREG-0847 Supplement 0NUREG-0847 Supplement 3NUREG-0847 Supplement 4NUREG-0847 Supplement 6NUREG-0847 Supplement 7NUREG-0847 Supplement 8 NUREG-0847 Supplement 15 3.9.4Control Rod Drive SystemsNUREG-0847 Supplement 0 3.9.5Reactor Pressure Vessel InternalsNUREG-0847 Supplement 0 3.9.6Inservice Testing of Pumps and ValvesNUREG-0847 Supplement 0NUREG-0847 Supplement 5NUREG-0847 Supplement 12NUREG-0847 Supplement 14 NUREG-0847 Supplement 203.10.0Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical EquipmentNUREG-0847 Supplement 0NUREG-0847 Supplement 1 NUREG-0847 Supplement 3NUREG-0847 Supplement 4NUREG-0847 Supplement 5 NUREG-0847 Supplement 6NUREG-0847 Supplement 8NUREG-0847 Supplement 93.11.0Environmental Qualification of Mechanical and Electrical EquipmentNUREG-0847 Supplement 0NUREG-0847 Supplement 15Page 6 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 4.2.1DescriptionNUREG-0847 Supplement 0NUREG-0847 Supplement 13 4.2.2Thermal PerformanceNUREG-0847 Supplement 0NUREG-0847 Supplement 2 4.2.3Mechanical PerformanceNUREG-0847 Supplement 0NUREG-0847 Supplement 2NUREG-0847 Supplement 10 NUREG-0847 Supplement 13 4.2.4SurveillanceNUREG-0847 Supplement 0NUREG-0847 Supplement 2 4.2.5Fuel Design ConclusionsNUREG-0847 Supplement 0 4.3.1Design BasisNUREG-0847 Supplement 0NUREG-0847 Supplement 13 4.3.2Design DescriptionNUREG-0847 Supplement 0NUREG-0847 Supplement 13NUREG-0847 Supplement 15 4.3.3Analytical MethodsNUREG-0847 Supplement 0NUREG-0847 Supplement 13 4.3.4Summary of Evaluation FindingsNUREG-0847 Supplement 0NUREG-0847 Supplement 13 4.4.1Perfomance in Safety CriteriaNUREG-0847 Supplement 0Page 7 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 4.4.2Design BasesNUREG-0847 Supplement 0NUREG-0847 Supplement 12 4.4.3Thermal-Hydraulic Design MethodologyNUREG-0847 Supplement 0NUREG-0847 Supplement 8NUREG-0847 Supplement 12NUREG-0847 Supplement 13 NUREG-0847 Supplement 16 4.4.4Operating AbnormalitiesNUREG-0847 Supplement 0NUREG-0847 Supplement 13 4.4.5Loose Parts Monitoring SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 3 NUREG-0847 Supplement 5NUREG-0847 Supplement 16 4.4.6Thermal-Hydraulic ComparisonNUREG-0847 Supplement 0 4.4.7N-1 Loop OperationNUREG-0847 Supplement 0 4.4.8Instrumentation for Inadequate Core Cooling Detection (II.F.2)NUREG-0847 Supplement 0NUREG-0847 Supplement 10 4.4.9Summary and ConclusionNUREG-0847 Supplement 0 4.5.1Control Rod Drive Structural MaterialsNUREG-0847 Supplement 0 4.5.2Reactor Internals and Core Support MaterialsNUREG-0847 Supplement 0Page 8 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 4.6.0Functional Design of Reactivity Control SystemsNUREG-0847 Supplement 0 5.2.1Compliance With Codes and Code CasesNUREG-0847 Supplement 0 5.2.2Overpressure ProtectionNUREG-0847 Supplement 0NUREG-0847 Supplement 2 5.2.3Reactor Coolant Pressure Boundary MaterialsNUREG-0847 Supplement 0 5.2.4RCS Pressure Boundary Inservice Inspection and TestingNUREG-0847 Supplement 0NUREG-0847 Supplement 12 5.2.5Reactor Coolant Pressure Boundary Leakage DetectionNUREG-0847 Supplement 0 5.3.1Reactor Vessel MaterialsNUREG-0847 Supplement 0 5.3.2Pressure-Temperature LimitsNUREG-0847 Supplement 0 5.3.3Reactor Vessel IntegrityNUREG-0847 Supplement 0 5.4.1Reactor Coolant PumpsNUREG-0847 Supplement 0 5.4.2Steam GeneratorsNUREG-0847 Supplement 0NUREG-0847 Supplement 4 5.4.3Residual Heat Removal SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 2NUREG-0847 Supplement 10Page 9 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 5.4.4Pressurizer Relief TankNUREG-0847 Supplement 0 5.4.5Reactor Coolant System Vents (II.B.1)NUREG-0847 Supplement 0 6.1.1Metallic MaterialsNUREG-0847 Supplement 0 6.1.2Organic MaterialsNUREG-0847 Supplement 0 6.1.3Postaccident Emergency Cooling Water ChemistryNUREG-0847 Supplement 0 6.2.1Containment Functional DesignNUREG-0847 Supplement 0NUREG-0847 Supplement 3 6.2.2Containment Heat Removal SystemsNUREG-0847 Supplement 0 6.2.3Secondary Containment Functional DesignNUREG-0847 Supplement 0 6.2.4Containment Isolation SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 3 NUREG-0847 Supplement 5NUREG-0847 Supplement 12 6.2.5Combustible Gas Control SystemsNUREG-0847 Supplement 0NUREG-0847 Supplement 4 NUREG-0847 Supplement 8 6.2.6Containment Leakage TestingNUREG-0847 Supplement 0 6.2.7Fracture Prevention of Containment Pressure BoundaryNUREG-0847 Supplement 0NUREG-0847 Supplement 4Page 10 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 6.3.0Emergency Core Cooling SystemNUREG-0847 Supplement 0 6.3.1System DesignNUREG-0847 Supplement 0NUREG-0847 Supplement 7 NUREG-0847 Supplement 11 6.3.2EvaluationNUREG-0847 Supplement 0NUREG-0847 Supplement 5 6.3.3TestingNUREG-0847 Supplement 0NUREG-0847 Supplement 2 NUREG-0847 Supplement 9 6.3.4Performance EvaluationNUREG-0847 Supplement 0 6.3.5ConclusionsNUREG-0847 Supplement 0 6.4.0Control Room HabitabilityNUREG-0847 Supplement 0 6.5.1ESF Atmosphere Cleanup SystemsNUREG-0847 Supplement 0 6.5.2Fission Product Cleanup SystemNUREG-0847 Supplement 0 6.5.3Fission Product Control SystemNUREG-0847 Supplement 0 6.5.4Ice Condenser as a Fission Product Control SystemNUREG-0847 Supplement 0 6.6.0Inservice Inspection of Class 2 and 3 ComponentsNUREG-0847 Supplement 0NUREG-0847 Supplement 10Page 11 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 7.1.1GeneralNUREG-0847 Supplement 0NUREG-0847 Supplement 13 NUREG-0847 Supplement 16 7.1.2Comparison with Other PlantsNUREG-0847 Supplement 0 7.1.3Design CriteriaNUREG-0847 Supplement 0NUREG-0847 Supplement 3NUREG-0847 Supplement 15 7.2.0Reactor Trip SystemNUREG-0847 Supplement 0 7.2.1System DescriptionNUREG-0847 Supplement 0NUREG-0847 Supplement 13NUREG-0847 Supplement 15 7.2.2Manual Trip SwitchesNUREG-0847 Supplement 0 7.2.3Testing of Reactor Trip Breaker Shunt CoilsNUREG-0847 Supplement 0 7.2.4Anticipatory TripsNUREG-0847 Supplement 0 7.2.5Steam Generator Water Level TripNUREG-0847 Supplement 0NUREG-0847 Supplement 2NUREG-0847 Supplement 14 7.2.6ConclusionsNUREG-0847 Supplement 0 7.3.0Engineered Safety Features SystemNUREG-0847 Supplement 0Page 12 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 7.3.1System DescriptionNUREG-0847 Supplement 0 7.3.2Containment Sump Level MeasurementNUREG-0847 Supplement 0NUREG-0847 Supplement 2 7.3.3Auxiliary Feedwater Initiation and ControlNUREG-0847 Supplement 0 7.3.4Failure Modes and Effects AnalysisNUREG-0847 Supplement 0 7.3.5IE Bulletin 80-06NUREG-0847 Supplement 0NUREG-0847 Supplement 3 7.3.6ConclusionsNUREG-0847 Supplement 0NUREG-0847 Supplement 13 7.4.1System DescriptionNUREG-0847 Supplement 0 7.4.2Safe Shutdown from Auxiliary Control RoomNUREG-0847 Supplement 0NUREG-0847 Supplement 7 7.4.3ConclusionsNUREG-0847 Supplement 0 7.5.1System DescriptionNUREG-0847 Supplement 0 7.5.2Post-Accident Monitoring SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 9 NUREG-0847 Supplement 14NUREG-0847 Supplement 15 7.5.3IE Bulletin 79-27NUREG-0847 Supplement 0Page 13 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 7.5.4ConclusionsNUREG-0847 Supplement 0 7.6.1System DescriptionNUREG-0847 Supplement 0 7.6.2Residual Heat Removal System Bypass ValvesNUREG-0847 Supplement 0 7.6.3Upper Head Injection Manual ControlNUREG-0847 Supplement 0 7.6.4Protection Against Spurious Actuation of Motor-Operated ValvesNUREG-0847 Supplement 0 7.6.5Overpressure Protection During Low Temperature OperationNUREG-0847 Supplement 0NUREG-0847 Supplement 4 7.6.6Valve Power LockoutNUREG-0847 Supplement 0 7.6.7Cold Leg Accumulator Valve Interlocks and Position IndicationNUREG-0847 Supplement 0 7.6.8Automatic Switchover From Injection to Recirculation ModeNUREG-0847 Supplement 0 7.6.9ConclusionsNUREG-0847 Supplement 0 7.7.1System DescriptionNUREG-0847 Supplement 0 7.7.2Safety System Status Monitoring SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 7NUREG-0847 Supplement 13 7.7.3Volume Control Tank Level Control SystemNUREG-0847 Supplement 0Page 14 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 7.7.4Pressurizer and Steam Generator OverfillNUREG-0847 Supplement 0 7.7.5IE Information Notice 79-22NUREG-0847 Supplement 0 7.7.6Multiple Control System FailuresNUREG-0847 Supplement 0 7.7.7ConclusionsNUREG-0847 Supplement 0 7.7.8Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC)NUREG-0847 Supplement 9NUREG-0847 Supplement 14 7.8.0NUREG-0737 ItemsNUREG-0847 Supplement 0 7.8.1Relief and Safety Valve Position Indication (II.D.3)NUREG-0847 Supplement 0NUREG-0847 Supplement 5 NUREG-0847 Supplement 14 7.8.2Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2)NUREG-0847 Supplement 0 7.8.3Proportional Integral Derivative Control Modification (II.K.3.9)NUREG-0847 Supplement 0 7.8.4Proposed Anticipatory Trip Modification (II.K.3.10)NUREG-0847 Supplement 0NUREG-0847 Supplement 4 7.8.5Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12)NUREG-0847 Supplement 0 8.1.0GeneralNUREG-0847 Supplement 0 8.2.1Compliance With GDC 5NUREG-0847 Supplement 0Page 15 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 8.2.2Compliance With GDC 17NUREG-0847 Supplement 0NUREG-0847 Supplement 2 NUREG-0847 Supplement 13 8.2.3Compliance With GDC 18NUREG-0847 Supplement 0 8.2.4Evaluation FindingsNUREG-0847 Supplement 0 8.3.0Onsite Power SystemsNUREG-0847 Supplement 0 8.3.1Onsite AC Power System Compliance With GDC 17NUREG-0847 Supplement 0NUREG-0847 Supplement 2NUREG-0847 Supplement 7 NUREG-0847 Supplement 13 8.3.2Onsite DC System Compliance With GDC 17NUREG-0847 Supplement 0NUREG-0847 Supplement 2NUREG-0847 Supplement 13 8.3.3Evaluation FindingsNUREG-0847 Supplement 0NUREG-0847 Supplement 2NUREG-0847 Supplement 3NUREG-0847 Supplement 7 NUREG-0847 Supplement 13 9.0.0Auxiliary SystemsNUREG-0847 Supplement 0 9.1.1New Fuel StorageNUREG-0847 Supplement 0 9.1.2Spent Fuel StorageNUREG-0847 Supplement 0Page 16 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 9.1.3Spent Fuel Pool Cooling and Cleanup SystemNUREG-0847 Supplement 0 9.1.4Fuel Handling SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 13 9.2.1Essential Raw Cooling Water and Raw Cooling Water SystemsNUREG-0847 Supplement 0NUREG-0847 Supplement 18 9.2.2Component Cooling System (Reactor Auxiliaries Cooling Water System)NUREG-0847 Supplement 0NUREG-0847 Supplement 5 9.2.3Demineralized Water Makeup SystemNUREG-0847 Supplement 0 9.2.4Potable and Sanitary Water SystemsNUREG-0847 Supplement 0 9.2.5Ultimate Heat SinkNUREG-0847 Supplement 0 9.2.6Condensate Storage FacilitiesNUREG-0847 Supplement 0 9.3.1Compressed Air SystemNUREG-0847 Supplement 0 9.3.2Process Sampling SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 3NUREG-0847 Supplement 14 9.3.3Equipment and Floor Drainage SystemNUREG-0847 Supplement 0 9.3.4Chemical and Volume Control SystemNUREG-0847 Supplement 0Page 17 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 9.4.1Control Room Area Ventilation SystemNUREG-0847 Supplement 0 9.4.2Fuel Handling Area Ventilation SystemNUREG-0847 Supplement 0 9.4.3Auxiliary and Radwates Area Ventilation SystemNUREG-0847 Supplement 0 9.4.4Turbine Building Area Ventilation SystemNUREG-0847 Supplement 0 9.4.5Engineered Safety Features Ventilation SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 9 NUREG-0847 Supplement 10NUREG-0847 Supplement 11NUREG-0847 Supplement 16 9.5.1Fire ProtectionNUREG-0847 Supplement 0NUREG-0847 Supplement 18NUREG-0847 Supplement 19 9.5.2Communication SystemsNUREG-0847 Supplement 0NUREG-0847 Supplement 5 9.5.3Lighting SystemNUREG-0847 Supplement 0 9.5.4Emergency Diesel Engine Fuel Oil Storage and Transfer SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 5 9.5.5Emergency Diesel Engine Cooling Water SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 5Page 18 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 2 9.5.6Emergency Diesel Engine Starting SystemsNUREG-0847 Supplement 0NUREG-0847 Supplement 5 9.5.7Emergency Diesel Engine Lubricating Oil SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 5 9.5.8Emergency Diesel Engine Combustion Air Intake and Exhaust SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 510.1.0Summary DescriptionNUREG-0847 Supplement 010.2.1Turbine Generator DesignNUREG-0847 Supplement 010.2.2Turbine Disc IntegrityNUREG-0847 Supplement 010.3.0Main Steam Supply SystemNUREG-0847 Supplement 010.3.1Main Steam Supply System (up to and including the Main Steam Isolation Valves)NUREG-0847 Supplement 010.3.2Main Steam Supply SystemNUREG-0847 Supplement 010.3.3Steam and Feedwater System MaterialsNUREG-0847 Supplement 010.3.4Secondary Water ChemistryNUREG-0847 Supplement 0NUREG-0847 Supplement 510.4.1Main CondenserNUREG-0847 Supplement 010.4.2Main Condenser Evacuation SystemNUREG-0847 Supplement 0Page 19 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 210.4.3Turbine Gland Sealing SystemNUREG-0847 Supplement 010.4.4Turbine Bypass SystemNUREG-0847 Supplement 010.4.5Condenser Circulating Water SystemNUREG-0847 Supplement 010.4.6Condensate Cleanup SystemNUREG-0847 Supplement 010.4.7Condensate and Feedwater SystemsNUREG-0847 Supplement 010.4.8Steam Generator Blowdown SystemNUREG-0847 Supplement 010.4.9Auxiliary Feedwater SystemNUREG-0847 Supplement 011.1.0Summary DescriptionNUREG-0847 Supplement 0NUREG-0847 Supplement 1611.2.0Liquid Waste ManagementNUREG-0847 Supplement 0NUREG-0847 Supplement 4 NUREG-0847 Supplement 1611.3.0Gaseous Waste ManagementNUREG-0847 Supplement 0NUREG-0847 Supplement 8NUREG-0847 Supplement 1611.4.0Solid Waste Management SystemNUREG-0847 Supplement 0NUREG-0847 Supplement 16Page 20 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 211.5.0Process and Effluent Radiological Monitoring and Sampling SystemsNUREG-0847 Supplement 0NUREG-0847 Supplement 16 NUREG-0847 Supplement 2011.6.0Evaluation FindingsNUREG-0847 Supplement 1611.7.0NUREG-0737 ItemsNUREG-0847 Supplement 0NUREG-0847 Supplement 5NUREG-0847 Supplement 611.7.1Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))NUREG-0847 Supplement 5NUREG-0847 Supplement 1511.7.2Primary Coolant Outside Containment (III.D.1.1)NUREG-0847 Supplement 5NUREG-0847 Supplement 10 NUREG-0847 Supplement 1612.1.0GeneralNUREG-0847 Supplement 0NUREG-0847 Supplement 1412.2.0Ensuring that Occupational Radiation Doses Are As Low As Reasonably AchievableNUREG-0847 Supplement 0NUREG-0847 Supplement 1412.3.0Radiation SourcesNUREG-0847 Supplement 0NUREG-0847 Supplement 1412.4.0Radiation Protection Design FeaturesNUREG-0847 Supplement 0NUREG-0847 Supplement 10NUREG-0847 Supplement 14NUREG-0847 Supplement 18Page 21 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 212.5.0Dose AssessmentNUREG-0847 Supplement 0NUREG-0847 Supplement 1412.6.0Health Physics ProgramNUREG-0847 Supplement 0NUREG-0847 Supplement 10NUREG-0847 Supplement 1412.7.1Plant Shielding (II.B.2)NUREG-0847 Supplement 0NUREG-0847 Supplement 14 NUREG-0847 Supplement 1612.7.2High Range Incontainment Monitor (II.F.1(3))NUREG-0847 Supplement 512.7.3Inplant Radioiodine Monitor (III.D.3.3)NUREG-0847 Supplement 0NUREG-0847 Supplement 1613.1.1Management and Technical OrganizationNUREG-0847 Supplement 013.1.2Corporate Organization and Technical SupportNUREG-0847 Supplement 0NUREG-0847 Supplement 813.1.3Plant Staff OrganizationNUREG-0847 Supplement 0NUREG-0847 Supplement 813.2.1Licensed Operator Training ProgramNUREG-0847 Supplement 013.2.2Training for Nonlicensed PersonnelNUREG-0847 Supplement 0Page 22 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 213.3.1IntroductionNUREG-0847 Supplement 0NUREG-0847 Supplement 13 NUREG-0847 Supplement 2013.3.2Evaluation of the Emergency PlanNUREG-0847 Supplement 0NUREG-0847 Supplement 13NUREG-0847 Supplement 2013.3.3ConclusionsNUREG-0847 Supplement 0NUREG-0847 Supplement 13NUREG-0847 Supplement 2013.4.0Review and AuditNUREG-0847 Supplement 0NUREG-0847 Supplement 813.5.1Administrative ProceduresNUREG-0847 Supplement 0NUREG-0847 Supplement 9NUREG-0847 Supplement 1013.5.2Operating and Maintenance ProceduresNUREG-0847 Supplement 0NUREG-0847 Supplement 9 NUREG-0847 Supplement 1013.5.3NUREG-0737 ItemsNUREG-0847 Supplement 0NUREG-0847 Supplement 313.6.0Physical Security PlanNUREG-0847 Supplement 0NUREG-0847 Supplement 10 NUREG-0847 Supplement 15Page 23 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 214.0.0Initial Test ProgramNUREG-0847 Supplement 0NUREG-0847 Supplement 3 NUREG-0847 Supplement 5NUREG-0847 Supplement 7NUREG-0847 Supplement 9NUREG-0847 Supplement 10NUREG-0847 Supplement 12 NUREG-0847 Supplement 14NUREG-0847 Supplement 16NUREG-0847 Supplement 18 NUREG-0847 Supplement 1915.1.0General DiscussionNUREG-0847 Supplement 015.2.0Normal Operation and Anticipated TransientsNUREG-0847 Supplement 015.2.1Loss of Cooling TransientsNUREG-0847 Supplement 0NUREG-0847 Supplement 13NUREG-0847 Supplement 1415.2.2Increased Cooling TransientsNUREG-0847 Supplement 015.2.3Change in Coolant Inventory TransientsNUREG-0847 Supplement 0NUREG-0847 Supplement 1815.2.4Reactivity and Power Distribution AnomaliesNUREG-0847 Supplement 0NUREG-0847 Supplement 4NUREG-0847 Supplement 7NUREG-0847 Supplement 13 NUREG-0847 Supplement 14Page 24 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 215.2.5ConclusionsNUREG-0847 Supplement 0NUREG-0847 Supplement 415.3.0Limiting AccidentsNUREG-0847 Supplement 015.3.1Loss-of-Coolant AccidentNUREG-0847 Supplement 0NUREG-0847 Supplement 12NUREG-0847 Supplement 1515.3.2Steamline BreakNUREG-0847 Supplement 0NUREG-0847 Supplement 1415.3.3Feedwater System Pipe BreakNUREG-0847 Supplement 0NUREG-0847 Supplement 1415.3.4Reactor Coolant Pump Rotor SeizureNUREG-0847 Supplement 0NUREG-0847 Supplement 1415.3.5Reactor Coolant Pump Shaft BreakNUREG-0847 Supplement 0NUREG-0847 Supplement 1415.3.6Anticipated Transients Without ScramNUREG-0847 Supplement 0NUREG-0847 Supplement 3NUREG-0847 Supplement 5NUREG-0847 Supplement 6 NUREG-0847 Supplement 10NUREG-0847 Supplement 11NUREG-0847 Supplement 1215.3.7ConclusionsNUREG-0847 Supplement 0Page 25 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 215.4.0Radiological Consequences of AccidentsNUREG-0847 Supplement 015.4.1Loss-of-Coolant AccidentNUREG-0847 Supplement 0NUREG-0847 Supplement 5 NUREG-0847 Supplement 9NUREG-0847 Supplement 15NUREG-0847 Supplement 1815.4.2Main Steamline Break Outside of ContainmentNUREG-0847 Supplement 0NUREG-0847 Supplement 1815.4.3Steam Generator Tube RuptureNUREG-0847 Supplement 0NUREG-0847 Supplement 3NUREG-0847 Supplement 5 NUREG-0847 Supplement 12NUREG-0847 Supplement 14NUREG-0847 Supplement 1515.4.4Control Rod Ejection AccidentNUREG-0847 Supplement 0NUREG-0847 Supplement 1515.4.5Fuel-Handling AccidentNUREG-0847 Supplement 0NUREG-0847 Supplement 4NUREG-0847 Supplement 1515.4.6Failure of Small Line Carrying Coolant Outside ContainmentNUREG-0847 Supplement 0NUREG-0847 Supplement 1515.4.7Postulated Radioactive Releases as a Result of Liquid Tank FailuresNUREG-0847 Supplement 0NUREG-0847 Supplement 15Page 26 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 215.5.1Thermal Mechanical Report (II.K.2.13)NUREG-0847 Supplement 0NUREG-0847 Supplement 415.5.2Voiding in the Reactor Coolant System During Transients (II.K.2.17)NUREG-0847 Supplement 0NUREG-0847 Supplement 415.5.3Installation and Testing of Automatic Power-Operated Relief Valve Isolation System (II.K.3.1)Report on Overall Safety Effect of Power-Operated Relief Valve Isolation System (II.K.3.2)NUREG-0847 Supplement 0NUREG-0847 Supplement 515.5.4Automatic Trip of Reactor Coolant Pumps (II.K.3.5)NUREG-0847 Supplement 0NUREG-0847 Supplement 4 NUREG-0847 Supplement 5NUREG-0847 Supplement 1615.5.5Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31)NUREG-0847 Supplement 0NUREG-0847 Supplement 4 NUREG-0847 Supplement 5NUREG-0847 Supplement 1615.6.0Relative Risk of Low Power OperationNUREG-0847 Supplement 016.0.0Technical SpecificationsNUREG-0847 Supplement 017.1.0GeneralNUREG-0847 Supplement 0NUREG-0847 Supplement 517.2.0OrganizationNUREG-0847 Supplement 0NUREG-0847 Supplement 5 NUREG-0847 Supplement 13Page 27 of 28 SubsectionTitle Table 7.NUREG-0847 and Supplemental Safety Evaluations Topic InventoryWatts Bar Nuclear Plant Unit 217.3.0Quality Assurance ProgramNUREG-0847 Supplement 0NUREG-0847 Supplement 2 NUREG-0847 Supplement 5NUREG-0847 Supplement 10NUREG-0847 Supplement 13NUREG-0847 Supplement 1517.4.0ConclusionsNUREG-0847 Supplement 0NUREG-0847 Supplement 2NUREG-0847 Supplement 5NUREG-0847 Supplement 1318.1.0GeneralNUREG-0847 Supplement 0NUREG-0847 Supplement 1618.2.0ConclusionsNUREG-0847 Supplement 0NUREG-0847 Supplement 1620.0.0Common Defense and SecurityNUREG-0847 Supplement 021.0.0Financial QualificationsNUREG-0847 Supplement 022.1.0GeneralNUREG-0847 Supplement 022.2.0Preoperational Storage of Nuclear FuelNUREG-0847 Supplement 022.3.0Operating LicensesNUREG-0847 Supplement 0Page 28 of 28 SubsectionTitle Table 8. NUREG-0847 Supplements Not Addressed By TVA3.2.1Seismic QualificationDoes not address SSER 6 and 83.2.2System Quality Group ClassificationDoes not address SSER 3, 6, 7, and 93.5.1Missile Selection and DescriptionDoes not address SSER 9 and 143.6.2Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of PipingDoes not address SSER 143.7.1Seismic InputDoes not address SSER 9, and 163.7.2Seismic AnalysisDoes not address SSER 163.8.1Steel ContainmentNot addressed in SSER 93.9.2Dynamic Testing and Analysis of Systems, Components, and EquipmentDoes not address SSER 143.9.3ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support StructuresDoes not address SSER 153.9.6Inservice Testing of Pumps and ValvesDoes not address SSER 204.2.1DescriptionDoes not address SSER 134.2.3Mechanical PerformanceDoes not address SSER 10 and 134.3.2Design DescriptionDoes not address SSER 13 and 154.3.3Analytical MethodsDoes not address SSER 134.3.4Summary of Evaluation FindingsDoes not address SSER 13 Page 1 of 5 SubsectionTitleTable 8, continued. NUREG-0847 Supplements Not Addressed By TVA4.4.2Design BasesDoes not address SSER 124.4.3Thermal-Hydraulic Design MethodologyDoes not address SSER 8, 12, 13, and 165.2.5Reactor Coolant Pressure Boundary Leakage DetectionDoes not address SSER 9, 11, and 125.4.3Residual Heat Removal SystemDoes not address SSER 106.2.4Containment Isolation SystemDoes not address SSER 126.2.5Combustible Gas Control SystemsDoes not address SSER 4 and 86.3.1System DesignDoes not address SSER 116.3.2EvaluationDoes not address SSER 57.1.1GeneralDoes not address SSER 13 and 167.2.1System DescriptionDoes not address SSER 13 and 157.3.6ConclusionsDoes not address SSER 137.4.2Safe Shutdown from Auxiliary Control RoomDoes not address SSER 77.7.2Safety System Status Monitoring SystemDoes not address SSER 137.7.8Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC)Does not address SSER 147.8.1Relief and Safety Valve Position Indication (II.D.3)Does not address SSER 5 and 148.3.1Onsite AC Power System Compliance With GDC 17Does not address SSER 13 Page 2 of 5 SubsectionTitleTable 8, continued. NUREG-0847 Supplements Not Addressed By TVA9.1.2Spent Fuel StorageDoes not address SSER 5, 15, and 169.2.4Potable and Sanitary Water SystemsDoes not address SSER 99.2.6Condensate Storage FacilitiesDoes not address SSER 129.3.2Process Sampling SystemDoes not address SSER 169.5.4Emergency Diesel Engine Fuel Oil Storage and Transfer SystemDoes not address SSER 9, 10, 11, and 129.5.5Emergency Diesel Engine Cooling Water SystemDoes not address SSER 119.5.6Emergency Diesel Engine Starting SystemsDoes not address SSER 109.5.7Emergency Diesel Engine Lubricating Oil SystemDoes not address SSER 109.5.8Emergency Diesel Engine Combustion Air Intake and Exhaust SystemDoes not address SSER 1010.2.0Turbine GeneratorDoes not address SSER 510.2.1Turbine Generator DesignDoes not address SSER 1210.3.1Main Steam Supply System (up to and including the Main Steam Isolation Valves)Does not address SSER 12 and 1910.4.1Main CondenserDoes not address SSER 910.4.4Turbine Bypass SystemDoes not address SSER 510.4.7Condensate and Feedwater SystemsDoes not address SSER 1410.4.9Auxiliary Feedwater SystemDoes not address SSER 14 Page 3 of 5 SubsectionTitleTable 8, continued. NUREG-0847 Supplements Not Addressed By TVA11.7.0NUREG-0737 ItemsDoes not address SSER 5 or 613.5.2Operating and Maintenance ProceduresDoes not address SSER 1014.0.0Initial Test ProgramDoes not address SSER 16, 18, and 1915.2.1Loss of Cooling TransientsDoes not address SSER 13 and 1415.2.3Change in Coolant Inventory TransientsDoes not address SSER 1815.2.4Reactivity and Power Distribution AnomaliesDoes not address SSER 7, 13, and 1415.3.1Loss-of-Coolant AccidentDoes not address SSER 12 and 1515.3.2Steamline BreakDoes not address SSER 1415.3.3Feedwater System Pipe BreakDoes not address SSER 1415.3.4Reactor Coolant Pump Rotor SeizureDoes not address SSER 1415.3.5Reactor Coolant Pump Shaft BreakDoes not address SSER 1415.3.6Anticipated Transients Without ScramDoes not address SSER 6, 10, 11, 1215.4.1Loss-of-Coolant AccidentDoes not address SSER 5, 9, 15, and 1815.4.2Main Steamline Break Outside of ContainmentDoes not address SSER 1815.4.3Steam Generator Tube RuptureDoes not address SSER 1515.4.4Control Rod Ejection AccidentDoes not address SSER 15 Page 4 of 5 SubsectionTitleTable 8, continued. NUREG-0847 Supplements Not Addressed By TVA15.4.5Fuel-Handling AccidentDoes not address SSER 4 and 1515.4.6Failure of Small Line Carrying Coolant Outside ContainmentDoes not address SSER 1515.4.7Postulated Radioactive Releases as a Result of Liquid Tank FailuresDoes not address SSER 1517.1.0GeneralDoes not address SSER 517.3.0Quality Assurance ProgramDoes not address SSER 2, 5, 10, 13, and 1517.4.0ConclusionsDoes not address SSER 2, 5, and 13 Page 5 of 5

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