Text

Review Topics for Safety Evaluation, Attachment 1
	ML081010116
Person / Time
Site:	Watts Bar
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: ML080860026; ML080860040; ML081010116;
References
	TAC MD6311
	Download: ML081010116 (79)
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Subsection Title Table 1.

Table of Contents Proposed Safety Evaluation Review Topics Watts Bar Nuclear Plant Unit 2 1.0.0 Introduction and General Discussion 1.1.0 Introduction 1.1.1 Metrication 1.1.2 Proprietary Information 1.1.4 Additional Information 1.2.0 General Design Description 1.3.0 Comparison With Similar Facility Designs 1.3.1 Comparison With the Sequoyah Nuclear Plant 1.3.2 Comparison With Other Facilities 1.4.0 Identification of Agents and Contractors 1.5.0 Summary of Principal Review Matters 1.6.0 Modifications to the Watts Bar Facility During the Course of NRC Review 1.7.0 Summary of Outstanding Issues 1.8.0 Confirmatory Issues 1.9.0 License Conditions 1.10.0 Unresolved Safety Issues 2.0.0 Site Envelope 2.1.0 Geography and Demography 2.1.1 Site Location and Description 2.1.2 Exclusion Area Authority and Control 2.1.3 Population Distribution 2.1.4 Conclusions 2.2.0 Nearby Industrial, Transportation, and Military Facilities 2.2.1 Transportation Routes 2.2.2 Nearby Facilities 2.2.3 Conclusions 2.3.0 Meteorology 2.3.1 Regional Climatology 2.3.2 Local Meteorology X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 1 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 2.3.3 Onsite Meteorological Measurements Program 2.3.4 Short-Term (Accident) Atmospheric Diffusion Estimates 2.3.5 Long-Term (Routine) Diffusion Estimates 2.4.0 Hydrologic Engineering 2.4.1 Introduction 2.4.2 Hydrologic Description 2.4.3 Flood Potential 2.4.4 Local Intense Precipitation in Plant Area 2.4.5 Roof Drainage 2.4.6 Ultimate Heat Sink 2.4.7 Groundwater 2.4.8 Design Basis for Subsurface Hydrostatic Loading 2.4.9 Transport of Liquid Releases 2.4.10 Flooding Protection Requirements and Technical Specifications 2.5.0 Geological, Seismological, and Geotechnical Engineering 2.5.1 Geology 2.5.2 Seismology 2.5.3 Surface Faulting 2.5.4 Stability of Subsurface Materials and Foundations 2.5.5 Stability of Slopes 2.5.6 Embankments and Dams 2.6.0 References 3.0.0 Design of Structures, Components, Equipment, and Systems 3.1.0 Introduction 3.1.1 Conformance With General Design Criteria 3.1.2 Conformance With Industry Codes and Standards 3.2.0 Classification of Structures, Systems, and Components 3.2.1 Seismic Qualification 3.2.2 System Quality Group Classification 3.3.0 Wind and Tornado Loadings 3.3.1 Wind Loading X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 2 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 3.3.2 Tornado Loading 3.4.0 Flood Level (Flood) Design 3.4.1 Flood Protection 3.5.0 Missile Protection 3.5.1 Missile Selection and Description 3.5.2 Structures, Systems, and Components To Be Protected From Externally Generated Missiles 3.5.3 Barrier Design Procedures 3.6.0 Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping 3.6.3 Leak-Before-Break Evaluation Procedures 3.7.0 Seismic Design 3.7.1 Seismic Input 3.7.2 Seismic Analysis 3.7.3 Seismic Subsystem Analysis 3.7.4 Seismic Instrumentation 3.8.0 Design of Seismic Category I Structures 3.8.1 Steel Containment 3.8.2 Concrete and Structural Steel Internal Structures 3.8.3 Other Seismic Category I Structures 3.8.4 Foundations 3.9.0 Mechanical Systems and Components 3.9.1 Special Topics for Mechanical Components 3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures 3.9.4 Control Rod Drive Systems 3.9.5 Reactor Pressure Vessel Internals X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 3 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 3.9.6 Inservice Testing of Pumps and Valves 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment 3.11.0 Environmental Qualification of Mechanical and Electrical Equipment 3.13.0 Threaded Fasteners - ASME Code Class 1, 2, and 3 [SRP TOC]

4.0.0 Reactor 4.1.0 Introduction 4.2.0 Fuel System Design 4.2.1 Description 4.2.2 Thermal Performance 4.2.3 Mechanical Performance 4.2.4 Surveillance 4.2.5 Fuel Design Conclusions 4.3.0 Nuclear Design 4.3.1 Design Basis 4.3.2 Design Description 4.3.3 Analytical Methods 4.3.4 Summary of Evaluation Findings 4.4.0 Thermal-Hydraulic Design 4.4.1 Perfomance in Safety Criteria 4.4.2 Design Bases 4.4.3 Thermal-Hydraulic Design Methodology 4.4.4 Operating Abnormalities 4.4.5 Loose Parts Monitoring System 4.4.6 Thermal-Hydraulic Comparison 4.4.7 N-1 Loop Operation 4.4.8 Instrumentation for Inadequate Core Cooling Detection (II.F.2) 4.4.9 Summary and Conclusion 4.5.0 Reactor Materials 4.5.1 Control Rod Drive Structural Materials 4.5.2 Reactor Internals and Core Support Materials X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 4 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 4.6.0 Functional Design of Reactivity Control Systems 5.0.0 Reactor Coolant System and Connected Systems 5.1.0 Summary Description 5.2.0 Integrity of Reactor Coolant Pressure Boundary 5.2.1 Compliance With Codes and Code Cases 5.2.2 Overpressure Protection 5.2.3 Reactor Coolant Pressure Boundary Materials 5.2.4 RCS Pressure Boundary Inservice Inspection and Testing 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection 5.3.0 Reactor Vessel 5.3.1 Reactor Vessel Materials 5.3.2 Pressure-Temperature Limits 5.3.3 Reactor Vessel Integrity 5.4.0 Component and Subsystem Design 5.4.1 Reactor Coolant Pumps 5.4.2 Steam Generators 5.4.3 Residual Heat Removal System 5.4.4 Pressurizer Relief Tank 5.4.5 Reactor Coolant System Vents (II.B.1) 6.0.0 Engineered Safety Features 6.1.0 Engineered Safety Features Materials 6.1.1 Metallic Materials 6.1.2 Organic Materials 6.1.3 Postaccident Emergency Cooling Water Chemistry 6.2.0 Containment Systems 6.2.1 Containment Functional Design 6.2.2 Containment Heat Removal Systems 6.2.3 Secondary Containment Functional Design 6.2.4 Containment Isolation System 6.2.5 Combustible Gas Control Systems 6.2.6 Containment Leakage Testing X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 5 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 6.2.7 Fracture Prevention of Containment Pressure Boundary 6.3.0 Emergency Core Cooling System 6.3.1

System Design

6.3.2 Evaluation 6.3.3 Testing 6.3.4 Performance Evaluation 6.3.5 Conclusions 6.4.0 Control Room Habitability 6.5.0 Engineered Safety Feature (ESF) Filter Systems 6.5.1 ESF Atmosphere Cleanup Systems 6.5.2 Fission Product Cleanup System 6.5.3 Fission Product Control System 6.5.4 Ice Condenser as a Fission Product Control System 6.6.0 Inservice Inspection of Class 2 and 3 Components 7.0.0 Instrumentation and Controls 7.1.0 Introduction 7.1.1 General 7.1.2 Comparison with Other Plants 7.1.3 Design Criteria 7.2.0 Reactor Trip System 7.2.1

System Description

7.2.2 Manual Trip Switches 7.2.3 Testing of Reactor Trip Breaker Shunt Coils 7.2.4 Anticipatory Trips 7.2.5 Steam Generator Water Level Trip 7.2.6 Conclusions 7.3.0 Engineered Safety Features System 7.3.1

System Description

7.3.2 Containment Sump Level Measurement 7.3.3 Auxiliary Feedwater Initiation and Control 7.3.4 Failure Modes and Effects Analysis X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 6 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 7.3.5 IE Bulletin 80-06 7.3.6 Conclusions 7.4.0 Systems Required for Safe Shutdown 7.4.1

System Description

7.4.2 Safe Shutdown from Auxiliary Control Room 7.4.3 Conclusions 7.5.0 Safety-Related Display Instrumentation 7.5.1

System Description

7.5.2 Post-Accident Monitoring System 7.5.3 IE Bulletin 79-27 7.5.4 Conclusions 7.6.0 All Other Systems Required for Safety 7.6.1

System Description

7.6.2 Residual Heat Removal System Bypass Valves 7.6.3 Upper Head Injection Manual Control 7.6.4 Protection Against Spurious Actuation of Motor-Operated Valves 7.6.5 Overpressure Protection During Low Temperature Operation 7.6.6 Valve Power Lockout 7.6.7 Cold Leg Accumulator Valve Interlocks and Position Indication 7.6.8 Automatic Switchover From Injection to Recirculation Mode 7.6.9 Conclusions 7.7.0 Control Systems Not Required for Safety 7.7.1

System Description

7.7.2 Safety System Status Monitoring System 7.7.3 Volume Control Tank Level Control System 7.7.4 Pressurizer and Steam Generator Overfill 7.7.5 IE Information Notice 79-22 7.7.6 Multiple Control System Failures 7.7.7 Conclusions 7.7.8 Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC)

X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 7 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 7.8.0 NUREG-0737 Items 7.8.1 Relief and Safety Valve Position Indication (II.D.3) 7.8.2 Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2) 7.8.3 Proportional Integral Derivative Control Modification (II.K.3.9) 7.8.4 Proposed Anticipatory Trip Modification (II.K.3.10) 7.8.5 Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12) 7.9.0 Data Communication Systems [SRP TOC]

8.0.0 Electric Power Systems 8.1.0 General 8.2.0 Offsite Power System 8.2.1 Compliance With GDC 5 8.2.2 Compliance With GDC 17 8.2.3 Compliance With GDC 18 8.2.4 Evaluation Findings 8.3.0 Onsite Power Systems 8.3.1 Onsite AC Power System Compliance With GDC 17 8.3.2 Onsite DC System Compliance With GDC 17 8.3.3 Evaluation Findings 8.4.0 Station Blackout 9.0.0 Auxiliary Systems 9.1.0 Fuel Storage Facility 9.1.1 New Fuel Storage 9.1.2 Spent Fuel Storage 9.1.3 Spent Fuel Pool Cooling and Cleanup System 9.1.4 Fuel Handling System 9.2.0 Water Systems 9.2.1 Essential Raw Cooling Water and Raw Cooling Water Systems 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System) 9.2.3 Demineralized Water Makeup System 9.2.4 Potable and Sanitary Water Systems 9.2.5 Ultimate Heat Sink X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 8 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 9.2.6 Condensate Storage Facilities 9.3.0 Process Auxiliaries 9.3.1 Compressed Air System 9.3.2 Process Sampling System 9.3.3 Equipment and Floor Drainage System 9.3.4 Chemical and Volume Control System 9.4.0 Heating, Ventilation, and Air Conditioning Systems 9.4.1 Control Room Area Ventilation System 9.4.2 Fuel Handling Area Ventilation System 9.4.3 Auxiliary and Radwates Area Ventilation System 9.4.4 Turbine Building Area Ventilation System 9.4.5 Engineered Safety Features Ventilation System 9.5.0 Other Auxiliary Systems 9.5.1 Fire Protection 9.5.2 Communication Systems 9.5.3 Lighting System 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System 9.5.5 Emergency Diesel Engine Cooling Water System 9.5.6 Emergency Diesel Engine Starting Systems 9.5.7 Emergency Diesel Engine Lubricating Oil System 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System 10.0.0 Steam and Power Conversion System 10.1.0 Summary Description 10.2.0 Turbine Generator 10.2.1 Turbine Generator Design 10.2.2 Turbine Disc Integrity 10.3.0 Main Steam Supply System 10.3.1 Main Steam Supply System (up to and including the Main Steam Isolation Valves) 10.3.2 Main Steam Supply System 10.3.3 Steam and Feedwater System Materials X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 9 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 10.3.4 Secondary Water Chemistry 10.4.0 Other Features 10.4.1 Main Condenser 10.4.2 Main Condenser Evacuation System 10.4.3 Turbine Gland Sealing System 10.4.4 Turbine Bypass System 10.4.5 Condenser Circulating Water System 10.4.6 Condensate Cleanup System 10.4.7 Condensate and Feedwater Systems 10.4.8 Steam Generator Blowdown System 10.4.9 Auxiliary Feedwater System 11.0.0 Radioactive Waste Management 11.1.0 Summary Description 11.2.0 Liquid Waste Management 11.3.0 Gaseous Waste Management 11.4.0 Solid Waste Management System 11.5.0 Process and Effluent Radiological Monitoring and Sampling Systems 11.6.0 Evaluation Findings 11.7.0 NUREG-0737 Items 11.7.1 Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))

11.7.2 Primary Coolant Outside Containment (III.D.1.1) 12.0.0 Radiation Protection 12.1.0 General 12.2.0 Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable 12.3.0 Radiation Sources 12.4.0 Radiation Protection Design Features 12.5.0 Dose Assessment 12.6.0 Health Physics Program 12.7.0 NUREG-0737 Items X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 10 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 12.7.1 Plant Shielding (II.B.2) 12.7.2 High Range Incontainment Monitor (II.F.1(3))

12.7.3 Inplant Radioiodine Monitor (III.D.3.3) 13.0.0 Conduct of Operations 13.1.0 Organizational Structure of the Applicant 13.1.1 Management and Technical Organization 13.1.2 Corporate Organization and Technical Support 13.1.3 Plant Staff Organization 13.2.0 Training 13.2.1 Licensed Operator Training Program 13.2.2 Training for Nonlicensed Personnel 13.3.0 Emergency Preparedness Evaluation 13.3.1 Introduction 13.3.2 Evaluation of the Emergency Plan 13.3.3 Conclusions 13.4.0 Review and Audit 13.5.0 Plant Procedures 13.5.1 Administrative Procedures 13.5.2 Operating and Maintenance Procedures 13.5.3 NUREG-0737 Items 13.6.0 Physical Security Plan 14.0.0 Initial Test Program 15.0.0 Accident Analysis 15.1.0 General Discussion 15.2.0 Normal Operation and Anticipated Transients 15.2.1 Loss of Cooling Transients 15.2.2 Increased Cooling Transients 15.2.3 Change in Coolant Inventory Transients 15.2.4 Reactivity and Power Distribution Anomalies 15.2.5 Conclusions 15.3.0 Limiting Accidents X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 11 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 15.3.1 Loss-of-Coolant Accident 15.3.2 Steamline Break 15.3.3 Feedwater System Pipe Break 15.3.4 Reactor Coolant Pump Rotor Seizure 15.3.5 Reactor Coolant Pump Shaft Break 15.3.6 Anticipated Transients Without Scram 15.3.7 Conclusions 15.4.0 Radiological Consequences of Accidents 15.4.1 Loss-of-Coolant Accident 15.4.2 Main Steamline Break Outside of Containment 15.4.3 Steam Generator Tube Rupture 15.4.4 Control Rod Ejection Accident 15.4.5 Fuel-Handling Accident 15.4.6 Failure of Small Line Carrying Coolant Outside Containment 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures 15.5.0 NUREG-0737 Items 15.5.1 Thermal Mechanical Report (II.K.2.13) 15.5.2 Voiding in the Reactor Coolant System During Transients (II.K.2.17) 15.5.3 Installation 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) 15.5.4 Automatic Trip of Reactor Coolant Pumps (II.K.3.5) 15.5.5 Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31) 15.6.0 Relative Risk of Low Power Operation 16.0.0 Technical Specifications 17.0.0 Quality Assurance 17.1.0 General 17.2.0 Organization 17.3.0 Quality Assurance Program 17.4.0 Conclusions X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 12 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 17.6.0 Maintenance Rule 18.0.0 Control Room Design Review 18.1.0 General 18.2.0 Conclusions 19.0.0 Report of the Advisory Committee on Reactor Safeguards 20.0.0 Common Defense and Security 21.0.0 Financial Qualifications 22.0.0 Financial Protection and Indemnity Requirements 22.1.0 General 22.2.0 Preoperational Storage of Nuclear Fuel 22.3.0 Operating Licenses 23.0.0 Nuclear Performance Plan 23.1.0 Introduction 23.2.0 Corrective Actions 23.2.1 Cable Issues 23.2.2 Cable Tray and Tray Supports 23.2.3 Design Baseline and Verification Program 23.2.4 Electrical Conduit and Conduit Support 23.2.5 Electrical Issues 23.2.6 Equipment Seismic Qualification 23.2.7 Fire Protection 23.2.8 Hanger and Analysis Update Program 23.2.9 Heat Code Traceability 23.2.10 Heating, Ventilation, and Air-Conditioning Duct and Duct Supports 23.2.11 Instrument Lines 23.2.12 Prestart Test Program 23.2.13 QA Records 23.2.14 Q-List 23.2.15 Replacement Items Program (Piece Parts) 23.2.16 Seismic Analysis 23.2.17 Vendor Information Program X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 13 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 23.2.18 Welding 23.3.0 Special Programs 23.3.1 Concrete Quality Program 23.3.2 Containment Cooling 23.3.3 Detailed Control Room Design Review 23.3.4 Environmental Qualification Program 23.3.5 Master Fuse List 23.3.6 Mechanical Equipment Qualification 23.3.7 Microbiologically Induced Corrosion (MIC) 23.3.8 Moderate Energy Line Break Flooding 23.3.9 Radiation Monitoring System 23.3.10 Soil Liquefaction 23.3.11 Use-as-is CAQs 23.4.0 Implementation, Verification, and Closure of Corrective Actions 23.4.1 Corrective Action Program Plans and Special Programs 23.4.2 Quality Verification Process 23.5.0 Management and Organization 23.5.1 Introduction 23.5.2 Organizational and Management Improvements 23.5.3 Conclusions 23.6.0 Operational Readiness 23.7.0 Employee Concerns 23.8.0 Allegations 24.0.0 Generic Issues 25.0.0 NUREG-0737 TMI Action Items 26.0.0 Other Regulatory Topics 26.1.0 License Conditions 26.2.0 Orders 27.0.0 Conclusions Appendix A - Chronology of Radiological Review of Watts Bar Nuclear Plant Units 1 and 2, Operating License Review X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 14 of 15

Subsection Title Table 1, continued.

Table of Contents Proposed Safety Evaluation Review Topics - Watts Bar Nuclear Plant Unit 2 Appendix B - Bibliography Appendix C - Nuclear Regulatory Commission Unresolved Safety Issues Appendix D - Evaluation of the Applicant's Control Room Design Appendix E - Principal Contributors Appendix F - Abbreviations X.Y.Z = chapter.section.subsection.

Chapter designations shown in bold.

Page 15 of 15

Subsection Title Table 2.

Status of NUREG-0847 Review Topics Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

2.1.1 Site Location and Description Yes 2.1.2 Exclusion Area Authority and Control Yes 2.1.3 Population Distribution No 2.1.4 Conclusions No 2.2.1 Transportation Routes No 2.2.2 Nearby Facilities No 2.2.3 Conclusions No 2.3.1 Regional Climatology Yes 2.3.2 Local Meteorology Yes 2.3.3 Onsite Meteorological Measurements Program Yes 2.3.4 Short-Term (Accident) Atmospheric Diffusion Estimates Yes 2.3.5 Long-Term (Routine) Diffusion Estimates Yes 2.4.1 Introduction Yes 2.4.2 Hydrologic Description Yes 2.4.3 Flood Potential Yes 2.4.4 Local Intense Precipitation in Plant Area Yes 2.4.5 Roof Drainage Yes 2.4.6 Ultimate Heat Sink Yes 2.4.7 Groundwater Yes 2.4.8 Design Basis for Subsurface Hydrostatic Loading Yes 2.4.9 Transport of Liquid Releases No 2.4.10 Flooding Protection Requirements and Technical Specifications Yes 2.5.0 Geological, Seismological, and Geotechnical Engineering Yes 2.5.1 Geology Yes 2.5.2 Seismology No 2.5.3 Surface Faulting Yes Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

2.5.4 Stability of Subsurface Materials and Foundations No 2.5.5 Stability of Slopes No 2.5.6 Embankments and Dams Yes 3.1.1 Conformance With General Design Criteria Yes 3.1.2 Conformance With Industry Codes and Standards Yes 3.2.1 Seismic Qualification Yes 3.2.2 System Quality Group Classification No 3.3.1 Wind Loading Yes 3.3.2 Tornado Loading Yes 3.4.1 Flood Protection Yes 3.5.1 Missile Selection and Description Yes 3.5.2 Structures, Systems, and Components To Be Protected From Externally Generated Missiles Yes 3.5.3 Barrier Design Procedures Yes 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid No 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping Yes 3.6.3 Leak-Before-Break Evaluation Procedures Yes 3.7.1 Seismic Input No 3.7.2 Seismic Analysis No 3.7.3 Seismic Subsystem Analysis No 3.7.4 Seismic Instrumentation Yes 3.8.1 Steel Containment Yes 3.8.2 Concrete and Structural Steel Internal Structures No 3.8.3 Other Seismic Category I Structures No 3.8.4 Foundations Yes 3.9.1 Special Topics for Mechanical Components No 3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment Yes Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and No 3.9.4 Control Rod Drive Systems Yes 3.9.5 Reactor Pressure Vessel Internals Yes 3.9.6 Inservice Testing of Pumps and Valves No 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical No 3.11.0 Environmental Qualification of Mechanical and Electrical Equipment No 4.2.1 Description No 4.2.2 Thermal Performance No 4.2.3 Mechanical Performance No 4.2.4 Surveillance Yes 4.2.5 Fuel Design Conclusions No 4.3.1 Design Basis No 4.3.2 Design Description No 4.3.3 Analytical Methods No 4.3.4 Summary of Evaluation Findings No 4.4.1 Perfomance in Safety Criteria Yes 4.4.2 Design Bases No 4.4.3 Thermal-Hydraulic Design Methodology No 4.4.4 Operating Abnormalities No 4.4.5 Loose Parts Monitoring System No 4.4.6 Thermal-Hydraulic Comparison Yes 4.4.7 N-1 Loop Operation No 4.4.8 Instrumentation for Inadequate Core Cooling Detection (II.F.2)

No 4.4.9 Summary and Conclusion No 4.5.1 Control Rod Drive Structural Materials Yes 4.5.2 Reactor Internals and Core Support Materials Yes Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

4.6.0 Functional Design of Reactivity Control Systems Yes 5.2.1 Compliance With Codes and Code Cases Yes 5.2.2 Overpressure Protection Yes 5.2.3 Reactor Coolant Pressure Boundary Materials Yes 5.2.4 RCS Pressure Boundary Inservice Inspection and Testing No 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection Yes 5.3.1 Reactor Vessel Materials Yes 5.3.2 Pressure-Temperature Limits No 5.3.3 Reactor Vessel Integrity No 5.4.1 Reactor Coolant Pumps Yes 5.4.2 Steam Generators Yes 5.4.3 Residual Heat Removal System No 5.4.4 Pressurizer Relief Tank Yes 5.4.5 Reactor Coolant System Vents (II.B.1)

Yes 6.1.1 Metallic Materials Yes 6.1.2 Organic Materials Yes 6.1.3 Postaccident Emergency Cooling Water Chemistry Yes 6.2.1 Containment Functional Design Yes 6.2.2 Containment Heat Removal Systems Yes 6.2.3 Secondary Containment Functional Design Yes 6.2.4 Containment Isolation System Yes 6.2.5 Combustible Gas Control Systems No 6.2.6 Containment Leakage Testing Yes 6.2.7 Fracture Prevention of Containment Pressure Boundary Yes 6.3.0 Emergency Core Cooling System Yes 6.3.1

System Design

No 6.3.2 Evaluation No 6.3.3 Testing No Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

6.3.4 Performance Evaluation Yes 6.3.5 Conclusions No 6.4.0 Control Room Habitability Yes 6.5.1 ESF Atmosphere Cleanup Systems Yes 6.5.2 Fission Product Cleanup System Yes 6.5.3 Fission Product Control System Yes 6.5.4 Ice Condenser as a Fission Product Control System Yes 6.6.0 Inservice Inspection of Class 2 and 3 Components No 7.1.1 General No 7.1.2 Comparison with Other Plants Yes 7.1.3 Design Criteria No 7.2.0 Reactor Trip System Yes 7.2.1

System Description

No 7.2.2 Manual Trip Switches Yes 7.2.3 Testing of Reactor Trip Breaker Shunt Coils Yes 7.2.4 Anticipatory Trips Yes 7.2.5 Steam Generator Water Level Trip No 7.2.6 Conclusions No 7.3.0 Engineered Safety Features System No 7.3.1

System Description

Yes 7.3.2 Containment Sump Level Measurement Yes 7.3.3 Auxiliary Feedwater Initiation and Control Yes 7.3.4 Failure Modes and Effects Analysis Yes 7.3.5 IE Bulletin 80-06 Yes 7.3.6 Conclusions No 7.4.1

System Description

Yes 7.4.2 Safe Shutdown from Auxiliary Control Room No 7.4.3 Conclusions Yes Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

7.5.1

System Description

Yes 7.5.2 Post-Accident Monitoring System No 7.5.3 IE Bulletin 79-27 Yes 7.5.4 Conclusions No 7.6.1

System Description

Yes 7.6.2 Residual Heat Removal System Bypass Valves Yes 7.6.3 Upper Head Injection Manual Control Yes 7.6.4 Protection Against Spurious Actuation of Motor-Operated Valves Yes 7.6.5 Overpressure Protection During Low Temperature Operation Yes 7.6.6 Valve Power Lockout Yes 7.6.7 Cold Leg Accumulator Valve Interlocks and Position Indication Yes 7.6.8 Automatic Switchover From Injection to Recirculation Mode Yes 7.6.9 Conclusions Yes 7.7.1

System Description

Yes 7.7.2 Safety System Status Monitoring System No 7.7.3 Volume Control Tank Level Control System Yes 7.7.4 Pressurizer and Steam Generator Overfill Yes 7.7.5 IE Information Notice 79-22 Yes 7.7.6 Multiple Control System Failures Yes 7.7.7 Conclusions Yes 7.7.8 Anticipated Transient Without Scram Mitigation System Actuation No 7.8.0 NUREG-0737 Items Yes 7.8.1 Relief and Safety Valve Position Indication (II.D.3)

No 7.8.2 Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2)

Yes 7.8.3 Proportional Integral Derivative Control Modification (II.K.3.9)

Yes 7.8.4 Proposed Anticipatory Trip Modification (II.K.3.10)

Yes 7.8.5 Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12)

Yes Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

8.1.0 General Yes 8.2.1 Compliance With GDC 5 Yes 8.2.2 Compliance With GDC 17 No 8.2.3 Compliance With GDC 18 Yes 8.2.4 Evaluation Findings Yes 8.3.0 Onsite Power Systems Yes 8.3.1 Onsite AC Power System Compliance With GDC 17 No 8.3.2 Onsite DC System Compliance With GDC 17 No 8.3.3 Evaluation Findings No 9.0.0 Auxiliary Systems Yes 9.1.1 New Fuel Storage Yes 9.1.2 Spent Fuel Storage Yes 9.1.3 Spent Fuel Pool Cooling and Cleanup System Yes 9.1.4 Fuel Handling System No 9.2.1 Essential Raw Cooling Water and Raw Cooling Water Systems No 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System)

No 9.2.3 Demineralized Water Makeup System Yes 9.2.4 Potable and Sanitary Water Systems Yes 9.2.5 Ultimate Heat Sink Yes 9.2.6 Condensate Storage Facilities Yes 9.3.1 Compressed Air System Yes 9.3.2 Process Sampling System No 9.3.3 Equipment and Floor Drainage System Yes 9.3.4 Chemical and Volume Control System Yes 9.4.1 Control Room Area Ventilation System Yes 9.4.2 Fuel Handling Area Ventilation System Yes 9.4.3 Auxiliary and Radwates Area Ventilation System Yes 9.4.4 Turbine Building Area Ventilation System Yes Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

9.4.5 Engineered Safety Features Ventilation System No 9.5.1 Fire Protection Yes 9.5.2 Communication Systems No 9.5.3 Lighting System Yes 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System Yes 9.5.5 Emergency Diesel Engine Cooling Water System No 9.5.6 Emergency Diesel Engine Starting Systems No 9.5.7 Emergency Diesel Engine Lubricating Oil System No 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System No 10.1.0 Summary Description Yes 10.2.1 Turbine Generator Design Yes 10.2.2 Turbine Disc Integrity Yes 10.3.0 Main Steam Supply System Yes 10.3.1 Main Steam Supply System (up to and including the Main Steam Isolation Valves)

Yes 10.3.2 Main Steam Supply System Yes 10.3.3 Steam and Feedwater System Materials Yes 10.3.4 Secondary Water Chemistry No 10.4.1 Main Condenser Yes 10.4.2 Main Condenser Evacuation System Yes 10.4.3 Turbine Gland Sealing System Yes 10.4.4 Turbine Bypass System Yes 10.4.5 Condenser Circulating Water System Yes 10.4.6 Condensate Cleanup System Yes 10.4.7 Condensate and Feedwater Systems Yes 10.4.8 Steam Generator Blowdown System Yes 10.4.9 Auxiliary Feedwater System Yes 11.1.0 Summary Description No Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

11.2.0 Liquid Waste Management Yes 11.3.0 Gaseous Waste Management Yes 11.4.0 Solid Waste Management System No 11.5.0 Process and Effluent Radiological Monitoring and Sampling Systems No 11.6.0 Evaluation Findings No 11.7.0 NUREG-0737 Items No 11.7.1 Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors No 11.7.2 Primary Coolant Outside Containment (III.D.1.1)

No 12.1.0 General No 12.2.0 Ensuring that Occupational Radiation Doses Are As Low As Reasonably No 12.3.0 Radiation Sources No 12.4.0 Radiation Protection Design Features No 12.5.0 Dose Assessment No 12.6.0 Health Physics Program No 12.7.1 Plant Shielding (II.B.2)

No 12.7.2 High Range Incontainment Monitor (II.F.1(3))

No 12.7.3 Inplant Radioiodine Monitor (III.D.3.3)

No 13.1.1 Management and Technical Organization Yes 13.1.2 Corporate Organization and Technical Support Yes 13.1.3 Plant Staff Organization No 13.2.1 Licensed Operator Training Program Yes 13.2.2 Training for Nonlicensed Personnel Yes 13.3.1 Introduction No 13.3.2 Evaluation of the Emergency Plan No 13.3.3 Conclusions No 13.4.0 Review and Audit No Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

13.5.1 Administrative Procedures Yes 13.5.2 Operating and Maintenance Procedures Yes 13.5.3 NUREG-0737 Items Yes 13.6.0 Physical Security Plan No 14.0.0 Initial Test Program Yes 15.1.0 General Discussion Yes 15.2.0 Normal Operation and Anticipated Transients No 15.2.1 Loss of Cooling Transients Yes 15.2.2 Increased Cooling Transients Yes 15.2.3 Change in Coolant Inventory Transients No 15.2.4 Reactivity and Power Distribution Anomalies No 15.2.5 Conclusions Yes 15.3.0 Limiting Accidents Yes 15.3.1 Loss-of-Coolant Accident No 15.3.2 Steamline Break No 15.3.3 Feedwater System Pipe Break No 15.3.4 Reactor Coolant Pump Rotor Seizure No 15.3.5 Reactor Coolant Pump Shaft Break No 15.3.6 Anticipated Transients Without Scram No 15.3.7 Conclusions Yes 15.4.0 Radiological Consequences of Accidents Yes 15.4.1 Loss-of-Coolant Accident No 15.4.2 Main Steamline Break Outside of Containment No 15.4.3 Steam Generator Tube Rupture No 15.4.4 Control Rod Ejection Accident No 15.4.5 Fuel-Handling Accident No 15.4.6 Failure of Small Line Carrying Coolant Outside Containment No 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures No Unresolved 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.

Subsection Title Table 2, continued.

Status of NUREG-0847 Review Topics - Watts Bar Nuclear Plant Unit 2 Resolved in NUREG-0847?*

15.5.1 Thermal Mechanical Report (II.K.2.13)

No 15.5.2 Voiding in the Reactor Coolant System During Transients (II.K.2.17)

Yes 15.5.3 Installation 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 No 15.5.4 Automatic Trip of Reactor Coolant Pumps (II.K.3.5)

No 15.5.5 Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations No 15.6.0 Relative Risk of Low Power Operation Yes 16.0.0 Technical Specifications No 17.1.0 General Yes 17.2.0 Organization Yes 17.3.0 Quality Assurance Program Yes 17.4.0 Conclusions Yes 18.1.0 General No 18.2.0 Conclusions No 20.0.0 Common Defense and Security Yes 21.0.0 Financial Qualifications Yes 22.1.0 General Yes 22.2.0 Preoperational Storage of Nuclear Fuel Yes 22.3.0 Operating Licenses Yes Unresolved 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.

Subsection Title Table 3.

Review Topics Resolved in NUREG-0847 Watts Bar Nuclear Plant Unit 2 2.1.1 Site Location and Description 2.1.2 Exclusion Area Authority and Control 2.3.1 Regional Climatology 2.3.2 Local Meteorology 2.3.3 Onsite Meteorological Measurements Program 2.3.4 Short-Term (Accident) Atmospheric Diffusion Estimates 2.3.5 Long-Term (Routine) Diffusion Estimates 2.4.1 Introduction 2.4.2 Hydrologic Description 2.4.3 Flood Potential 2.4.4 Local Intense Precipitation in Plant Area 2.4.5 Roof Drainage 2.4.6 Ultimate Heat Sink 2.4.7 Groundwater 2.4.8 Design Basis for Subsurface Hydrostatic Loading 2.4.10 Flooding Protection Requirements and Technical Specifications 2.5.0 Geological, Seismological, and Geotechnical Engineering 2.5.1 Geology 2.5.3 Surface Faulting 2.5.6 Embankments and Dams 3.1.1 Conformance With General Design Criteria 3.1.2 Conformance With Industry Codes and Standards 3.2.1 Seismic Qualification 3.3.1 Wind Loading 3.3.2 Tornado Loading 3.4.1 Flood Protection Page 1 of 7

Subsection Title Table 3, continued.

Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 3.5.1 Missile Selection and Description 3.5.2 Structures, Systems, and Components To Be Protected From Externally Generated Missiles 3.5.3 Barrier Design Procedures 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping 3.6.3 Leak-Before-Break Evaluation Procedures 3.7.4 Seismic Instrumentation 3.8.1 Steel Containment 3.8.4 Foundations 3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment 3.9.4 Control Rod Drive Systems 3.9.5 Reactor Pressure Vessel Internals 4.2.4 Surveillance 4.4.1 Perfomance in Safety Criteria 4.4.6 Thermal-Hydraulic Comparison 4.5.1 Control Rod Drive Structural Materials 4.5.2 Reactor Internals and Core Support Materials 4.6.0 Functional Design of Reactivity Control Systems 5.2.1 Compliance With Codes and Code Cases 5.2.2 Overpressure Protection 5.2.3 Reactor Coolant Pressure Boundary Materials 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection 5.3.1 Reactor Vessel Materials 5.4.1 Reactor Coolant Pumps 5.4.2 Steam Generators 5.4.4 Pressurizer Relief Tank 5.4.5 Reactor Coolant System Vents (II.B.1)

Page 2 of 7

Subsection Title Table 3, continued.

Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 6.1.1 Metallic Materials 6.1.2 Organic Materials 6.1.3 Postaccident Emergency Cooling Water Chemistry 6.2.1 Containment Functional Design 6.2.2 Containment Heat Removal Systems 6.2.3 Secondary Containment Functional Design 6.2.4 Containment Isolation System 6.2.6 Containment Leakage Testing 6.2.7 Fracture Prevention of Containment Pressure Boundary 6.3.0 Emergency Core Cooling System 6.3.4 Performance Evaluation 6.4.0 Control Room Habitability 6.5.1 ESF Atmosphere Cleanup Systems 6.5.2 Fission Product Cleanup System 6.5.3 Fission Product Control System 6.5.4 Ice Condenser as a Fission Product Control System 7.1.2 Comparison with Other Plants 7.2.0 Reactor Trip System 7.2.2 Manual Trip Switches 7.2.3 Testing of Reactor Trip Breaker Shunt Coils 7.2.4 Anticipatory Trips 7.3.1

System Description

7.3.2 Containment Sump Level Measurement 7.3.3 Auxiliary Feedwater Initiation and Control 7.3.4 Failure Modes and Effects Analysis 7.3.5 IE Bulletin 80-06 7.4.1

System Description

Page 3 of 7

Subsection Title Table 3, continued.

Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 7.4.3 Conclusions 7.5.1

System Description

7.5.3 IE Bulletin 79-27 7.6.1

System Description

7.6.2 Residual Heat Removal System Bypass Valves 7.6.3 Upper Head Injection Manual Control 7.6.4 Protection Against Spurious Actuation of Motor-Operated Valves 7.6.5 Overpressure Protection During Low Temperature Operation 7.6.6 Valve Power Lockout 7.6.7 Cold Leg Accumulator Valve Interlocks and Position Indication 7.6.8 Automatic Switchover From Injection to Recirculation Mode 7.6.9 Conclusions 7.7.1

System Description

7.7.3 Volume Control Tank Level Control System 7.7.4 Pressurizer and Steam Generator Overfill 7.7.5 IE Information Notice 79-22 7.7.6 Multiple Control System Failures 7.7.7 Conclusions 7.8.0 NUREG-0737 Items 7.8.2 Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2) 7.8.3 Proportional Integral Derivative Control Modification (II.K.3.9) 7.8.4 Proposed Anticipatory Trip Modification (II.K.3.10) 7.8.5 Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12) 8.1.0 General 8.2.1 Compliance With GDC 5 8.2.3 Compliance With GDC 18 8.2.4 Evaluation Findings Page 4 of 7

Subsection Title Table 3, continued.

Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 8.3.0 Onsite Power Systems 9.0.0 Auxiliary Systems 9.1.1 New Fuel Storage 9.1.2 Spent Fuel Storage 9.1.3 Spent Fuel Pool Cooling and Cleanup System 9.2.3 Demineralized Water Makeup System 9.2.4 Potable and Sanitary Water Systems 9.2.5 Ultimate Heat Sink 9.2.6 Condensate Storage Facilities 9.3.1 Compressed Air System 9.3.3 Equipment and Floor Drainage System 9.3.4 Chemical and Volume Control System 9.4.1 Control Room Area Ventilation System 9.4.2 Fuel Handling Area Ventilation System 9.4.3 Auxiliary and Radwates Area Ventilation System 9.4.4 Turbine Building Area Ventilation System 9.5.1 Fire Protection 9.5.3 Lighting System 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System 10.1.0 Summary Description 10.2.1 Turbine Generator Design 10.2.2 Turbine Disc Integrity 10.3.0 Main Steam Supply System 10.3.1 Main Steam Supply System (up to and including the Main Steam Isolation Valves) 10.3.2 Main Steam Supply System 10.3.3 Steam and Feedwater System Materials Page 5 of 7

Subsection Title Table 3, continued.

Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 10.4.1 Main Condenser 10.4.2 Main Condenser Evacuation System 10.4.3 Turbine Gland Sealing System 10.4.4 Turbine Bypass System 10.4.5 Condenser Circulating Water System 10.4.6 Condensate Cleanup System 10.4.7 Condensate and Feedwater Systems 10.4.8 Steam Generator Blowdown System 10.4.9 Auxiliary Feedwater System 11.2.0 Liquid Waste Management 11.3.0 Gaseous Waste Management 13.1.1 Management and Technical Organization 13.1.2 Corporate Organization and Technical Support 13.2.1 Licensed Operator Training Program 13.2.2 Training for Nonlicensed Personnel 13.5.1 Administrative Procedures 13.5.2 Operating and Maintenance Procedures 13.5.3 NUREG-0737 Items 14.0.0 Initial Test Program 15.1.0 General Discussion 15.2.1 Loss of Cooling Transients 15.2.2 Increased Cooling Transients 15.2.5 Conclusions 15.3.0 Limiting Accidents 15.3.7 Conclusions 15.4.0 Radiological Consequences of Accidents 15.5.2 Voiding in the Reactor Coolant System During Transients (II.K.2.17)

Page 6 of 7

Subsection Title Table 3, continued.

Review Topics Resolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 15.6.0 Relative Risk of Low Power Operation 17.1.0 General 17.2.0 Organization 17.3.0 Quality Assurance Program 17.4.0 Conclusions 20.0.0 Common Defense and Security 21.0.0 Financial Qualifications 22.1.0 General 22.2.0 Preoperational Storage of Nuclear Fuel 22.3.0 Operating Licenses Page 7 of 7

Subsection Title Table 4.

Review Topics Unresolved in NUREG-0847 Watts Bar Nuclear Plant Unit 2 2.1.3 Population Distribution 2.1.4 Conclusions 2.2.1 Transportation Routes 2.2.2 Nearby Facilities 2.2.3 Conclusions 2.4.9 Transport of Liquid Releases 2.5.2 Seismology 2.5.4 Stability of Subsurface Materials and Foundations 2.5.5 Stability of Slopes 3.2.2 System Quality Group Classification 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment 3.7.1 Seismic Input 3.7.2 Seismic Analysis 3.7.3 Seismic Subsystem Analysis 3.8.2 Concrete and Structural Steel Internal Structures 3.8.3 Other Seismic Category I Structures 3.9.1 Special Topics for Mechanical Components 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures 3.9.6 Inservice Testing of Pumps and Valves 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment 3.11.0 Environmental Qualification of Mechanical and Electrical Equipment 4.2.1 Description 4.2.2 Thermal Performance 4.2.3 Mechanical Performance Page 1 of 5

Subsection Title Table 4, continued.

Review Topics Unresolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 4.2.5 Fuel Design Conclusions 4.3.1 Design Basis 4.3.2 Design Description 4.3.3 Analytical Methods 4.3.4 Summary of Evaluation Findings 4.4.2 Design Bases 4.4.3 Thermal-Hydraulic Design Methodology 4.4.4 Operating Abnormalities 4.4.5 Loose Parts Monitoring System 4.4.7 N-1 Loop Operation 4.4.8 Instrumentation for Inadequate Core Cooling Detection (II.F.2) 4.4.9 Summary and Conclusion 5.2.4 RCS Pressure Boundary Inservice Inspection and Testing 5.3.2 Pressure-Temperature Limits 5.3.3 Reactor Vessel Integrity 5.4.3 Residual Heat Removal System 6.2.5 Combustible Gas Control Systems 6.3.1

System Design

6.3.2 Evaluation 6.3.3 Testing 6.3.5 Conclusions 6.6.0 Inservice Inspection of Class 2 and 3 Components 7.1.1 General 7.1.3 Design Criteria 7.2.1

System Description

7.2.5 Steam Generator Water Level Trip 7.2.6 Conclusions 7.3.0 Engineered Safety Features System Page 2 of 5

Subsection Title Table 4, continued.

Review Topics Unresolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 7.3.6 Conclusions 7.4.2 Safe Shutdown from Auxiliary Control Room 7.5.2 Post-Accident Monitoring System 7.5.4 Conclusions 7.7.2 Safety System Status Monitoring System 7.7.8 Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC) 7.8.1 Relief and Safety Valve Position Indication (II.D.3) 8.2.2 Compliance With GDC 17 8.3.1 Onsite AC Power System Compliance With GDC 17 8.3.2 Onsite DC System Compliance With GDC 17 8.3.3 Evaluation Findings 9.1.4 Fuel Handling System 9.2.1 Essential Raw Cooling Water and Raw Cooling Water Systems 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System) 9.3.2 Process Sampling System 9.4.5 Engineered Safety Features Ventilation System 9.5.2 Communication Systems 9.5.5 Emergency Diesel Engine Cooling Water System 9.5.6 Emergency Diesel Engine Starting Systems 9.5.7 Emergency Diesel Engine Lubricating Oil System 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System 10.3.4 Secondary Water Chemistry 11.1.0 Summary Description 11.4.0 Solid Waste Management System 11.5.0 Process and Effluent Radiological Monitoring and Sampling Systems 11.6.0 Evaluation Findings 11.7.0 NUREG-0737 Items Page 3 of 5

Subsection Title Table 4, continued.

Review Topics Unresolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 11.7.1 Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))

11.7.2 Primary Coolant Outside Containment (III.D.1.1) 12.1.0 General 12.2.0 Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable 12.3.0 Radiation Sources 12.4.0 Radiation Protection Design Features 12.5.0 Dose Assessment 12.6.0 Health Physics Program 12.7.1 Plant Shielding (II.B.2) 12.7.2 High Range Incontainment Monitor (II.F.1(3))

12.7.3 Inplant Radioiodine Monitor (III.D.3.3) 13.1.3 Plant Staff Organization 13.3.1 Introduction 13.3.2 Evaluation of the Emergency Plan 13.3.3 Conclusions 13.4.0 Review and Audit 13.6.0 Physical Security Plan 15.2.0 Normal Operation and Anticipated Transients 15.2.3 Change in Coolant Inventory Transients 15.2.4 Reactivity and Power Distribution Anomalies 15.3.1 Loss-of-Coolant Accident 15.3.2 Steamline Break 15.3.3 Feedwater System Pipe Break 15.3.4 Reactor Coolant Pump Rotor Seizure 15.3.5 Reactor Coolant Pump Shaft Break 15.3.6 Anticipated Transients Without Scram Page 4 of 5

Subsection Title Table 4, continued.

Review Topics Unresolved in NUREG-0847 - Watts Bar Nuclear Plant Unit 2 15.4.1 Loss-of-Coolant Accident 15.4.2 Main Steamline Break Outside of Containment 15.4.3 Steam Generator Tube Rupture 15.4.4 Control Rod Ejection Accident 15.4.5 Fuel-Handling Accident 15.4.6 Failure of Small Line Carrying Coolant Outside Containment 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures 15.5.1 Thermal Mechanical Report (II.K.2.13) 15.5.3 Installation 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) 15.5.4 Automatic Trip of Reactor Coolant Pumps (II.K.3.5) 15.5.5 Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31) 16.0.0 Technical Specifications 18.1.0 General 18.2.0 Conclusions Page 5 of 5

Subsection Title Table 5.

NUREG-0847 Review Topics Where NRC Conclusions Do Not Match TVA (NRC = Open, TVA = Closed) 2.5.2 Seismology 2.5.4 Stability of Subsurface Materials and Foundations 2.5.5 Stability of Slopes 3.2.2 System Quality Group Classification 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment 3.7.1 Seismic Input 3.7.2 Seismic Analysis 3.8.2 Concrete and Structural Steel Internal Structures 3.8.3 Other Seismic Category I Structures 3.9.1 Special Topics for Mechanical Components 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures 3.9.6 Inservice Testing of Pumps and Valves 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment 4.2.1 Description 4.2.3 Mechanical Performance 4.3.1 Design Basis 4.3.2 Design Description 4.3.3 Analytical Methods 4.3.4 Summary of Evaluation Findings 4.4.2 Design Bases 4.4.4 Operating Abnormalities 4.4.7 N-1 Loop Operation 5.4.3 Residual Heat Removal System 6.3.1

System Design

Page 1 of 4

Subsection Title Table 5, continued.

NUREG-0847 Review Topics Where NRC Conclusions Do Not Match TVA (NRC = Open, TVA = Closed) 6.3.2 Evaluation 6.3.3 Testing 6.3.5 Conclusions 7.1.1 General 7.2.1

System Description

7.2.5 Steam Generator Water Level Trip 7.3.0 Engineered Safety Features System 7.4.2 Safe Shutdown from Auxiliary Control Room 7.5.2 Post-Accident Monitoring System 7.7.2 Safety System Status Monitoring System 7.7.8 Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC) 7.8.1 Relief and Safety Valve Position Indication (II.D.3) 8.2.2 Compliance With GDC 17 8.3.1 Onsite AC Power System Compliance With GDC 17 8.3.2 Onsite DC System Compliance With GDC 17 8.3.3 Evaluation Findings 9.1.4 Fuel Handling System 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System) 9.3.2 Process Sampling System 9.4.5 Engineered Safety Features Ventilation System 9.5.2 Communication Systems 9.5.5 Emergency Diesel Engine Cooling Water System 9.5.6 Emergency Diesel Engine Starting Systems 9.5.7 Emergency Diesel Engine Lubricating Oil System 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System 11.1.0 Summary Description Page 2 of 4

Subsection Title Table 5, continued.

NUREG-0847 Review Topics Where NRC Conclusions Do Not Match TVA (NRC = Open, TVA = Closed) 11.6.0 Evaluation Findings 11.7.0 NUREG-0737 Items 11.7.1 Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))

12.1.0 General 12.2.0 Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable 12.3.0 Radiation Sources 12.4.0 Radiation Protection Design Features 12.5.0 Dose Assessment 12.6.0 Health Physics Program 12.7.1 Plant Shielding (II.B.2) 12.7.2 High Range Incontainment Monitor (II.F.1(3))

12.7.3 Inplant Radioiodine Monitor (III.D.3.3) 13.1.3 Plant Staff Organization 13.3.1 Introduction 13.3.2 Evaluation of the Emergency Plan 13.3.3 Conclusions 13.6.0 Physical Security Plan 15.2.0 Normal Operation and Anticipated Transients 15.2.3 Change in Coolant Inventory Transients 15.2.4 Reactivity and Power Distribution Anomalies 15.3.1 Loss-of-Coolant Accident 15.3.2 Steamline Break 15.3.3 Feedwater System Pipe Break 15.3.4 Reactor Coolant Pump Rotor Seizure 15.3.5 Reactor Coolant Pump Shaft Break 15.3.6 Anticipated Transients Without Scram Page 3 of 4

Subsection Title Table 5, continued.

NUREG-0847 Review Topics Where NRC Conclusions Do Not Match TVA (NRC = Open, TVA = Closed) 15.4.1 Loss-of-Coolant Accident 15.4.2 Main Steamline Break Outside of Containment 15.4.3 Steam Generator Tube Rupture 15.4.4 Control Rod Ejection Accident 15.4.5 Fuel-Handling Accident 15.4.6 Failure of Small Line Carrying Coolant Outside Containment 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures 15.5.1 Thermal Mechanical Report (II.K.2.13) 15.5.3 Installation 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) 15.5.4 Automatic Trip of Reactor Coolant Pumps (II.K.3.5) 15.5.5 Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31)

Page 4 of 4

Subsection Title Table 6.

Open NUREG-0847 Review Topics Requiring Additional Information to Resolve 2.5.2 Seismology 2.5.4 Stability of Subsurface Materials and Foundations 2.5.5 Stability of Slopes 3.2.2 System Quality Group Classification 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment 3.7.1 Seismic Input 3.7.2 Seismic Analysis 3.8.2 Concrete and Structural Steel Internal Structures 3.8.3 Other Seismic Category I Structures 3.9.1 Special Topics for Mechanical Components 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment 4.2.1 Description 4.2.3 Mechanical Performance 4.3.1 Design Basis 4.3.2 Design Description 4.3.3 Analytical Methods 4.3.4 Summary of Evaluation Findings 4.4.2 Design Bases 4.4.4 Operating Abnormalities 5.4.3 Residual Heat Removal System 6.3.1

System Design

6.3.2 Evaluation 6.3.3 Testing Page 1 of 4

Subsection Title Table 6, continued.

Open NUREG-0847 Review Topics Requiring Additional Information to Resolve 6.3.5 Conclusions 7.1.1 General 7.2.1

System Description

7.2.5 Steam Generator Water Level Trip 7.3.0 Engineered Safety Features System 7.4.2 Safe Shutdown from Auxiliary Control Room 7.5.2 Post-Accident Monitoring System 7.7.2 Safety System Status Monitoring System 7.8.1 Relief and Safety Valve Position Indication (II.D.3) 8.2.2 Compliance With GDC 17 8.3.1 Onsite AC Power System Compliance With GDC 17 8.3.2 Onsite DC System Compliance With GDC 17 8.3.3 Evaluation Findings 9.1.4 Fuel Handling System 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System) 9.3.2 Process Sampling System 9.4.5 Engineered Safety Features Ventilation System 9.5.2 Communication Systems 9.5.5 Emergency Diesel Engine Cooling Water System 9.5.6 Emergency Diesel Engine Starting Systems 9.5.7 Emergency Diesel Engine Lubricating Oil System 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System 11.1.0 Summary Description 11.6.0 Evaluation Findings 11.7.0 NUREG-0737 Items 11.7.1 Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))

12.1.0 General Page 2 of 4

Subsection Title Table 6, continued.

Open NUREG-0847 Review Topics Requiring Additional Information to Resolve 12.2.0 Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable 12.3.0 Radiation Sources 12.4.0 Radiation Protection Design Features 12.5.0 Dose Assessment 12.6.0 Health Physics Program 12.7.1 Plant Shielding (II.B.2) 12.7.2 High Range Incontainment Monitor (II.F.1(3))

12.7.3 Inplant Radioiodine Monitor (III.D.3.3) 13.1.3 Plant Staff Organization 13.3.1 Introduction 13.3.2 Evaluation of the Emergency Plan 13.3.3 Conclusions 13.6.0 Physical Security Plan 15.2.0 Normal Operation and Anticipated Transients 15.2.3 Change in Coolant Inventory Transients 15.2.4 Reactivity and Power Distribution Anomalies 15.3.1 Loss-of-Coolant Accident 15.3.2 Steamline Break 15.3.3 Feedwater System Pipe Break 15.3.4 Reactor Coolant Pump Rotor Seizure 15.3.5 Reactor Coolant Pump Shaft Break 15.3.6 Anticipated Transients Without Scram 15.4.1 Loss-of-Coolant Accident 15.4.2 Main Steamline Break Outside of Containment 15.4.3 Steam Generator Tube Rupture 15.4.4 Control Rod Ejection Accident 15.4.5 Fuel-Handling Accident Page 3 of 4

Subsection Title Table 6, continued.

Open NUREG-0847 Review Topics Requiring Additional Information to Resolve 15.4.6 Failure of Small Line Carrying Coolant Outside Containment 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures 15.5.1 Thermal Mechanical Report (II.K.2.13) 15.5.3 Installation 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) 15.5.4 Automatic Trip of Reactor Coolant Pumps (II.K.3.5) 15.5.5 Small-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 Inventory Watts Bar Nuclear Plant Unit 2 Subsection Title 2.1.1 Site Location and Description NUREG-0847 Supplement 0 2.1.2 Exclusion Area Authority and Control NUREG-0847 Supplement 0 2.1.3 Population Distribution NUREG-0847 Supplement 0 2.1.4 Conclusions NUREG-0847 Supplement 0 2.2.1 Transportation Routes NUREG-0847 Supplement 0 2.2.2 Nearby Facilities NUREG-0847 Supplement 0 2.2.3 Conclusions NUREG-0847 Supplement 0 2.3.1 Regional Climatology NUREG-0847 Supplement 0 2.3.2 Local Meteorology NUREG-0847 Supplement 0 2.3.3 Onsite Meteorological Measurements Program NUREG-0847 Supplement 0 2.3.4 Short-Term (Accident) Atmospheric Diffusion Estimates NUREG-0847 Supplement 0 2.3.5 Long-Term (Routine) Diffusion Estimates NUREG-0847 Supplement 0 2.4.1 Introduction NUREG-0847 Supplement 0 2.4.2 Hydrologic Description NUREG-0847 Supplement 0 Page 1 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 2.4.3 Flood Potential NUREG-0847 Supplement 0 2.4.4 Local Intense Precipitation in Plant Area NUREG-0847 Supplement 0 2.4.5 Roof Drainage NUREG-0847 Supplement 0 2.4.6 Ultimate Heat Sink NUREG-0847 Supplement 0 2.4.7 Groundwater NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 2.4.8 Design Basis for Subsurface Hydrostatic Loading NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 2.4.9 Transport of Liquid Releases NUREG-0847 Supplement 0 2.4.10 Flooding Protection Requirements and Technical Specifications NUREG-0847 Supplement 0 2.5.0 Geological, Seismological, and Geotechnical Engineering NUREG-0847 Supplement 0 2.5.1 Geology NUREG-0847 Supplement 0 2.5.2 Seismology NUREG-0847 Supplement 0 2.5.3 Surface Faulting NUREG-0847 Supplement 0 Page 2 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 2.5.4 Stability of Subsurface Materials and Foundations NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 9 NUREG-0847 Supplement 11 2.5.5 Stability of Slopes NUREG-0847 Supplement 0 2.5.6 Embankments and Dams NUREG-0847 Supplement 0 3.1.1 Conformance With General Design Criteria NUREG-0847 Supplement 0 3.1.2 Conformance With Industry Codes and Standards NUREG-0847 Supplement 0 3.2.1 Seismic Qualification NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 5 NUREG-0847 Supplement 6 NUREG-0847 Supplement 8 3.2.2 System Quality Group Classification NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 6 NUREG-0847 Supplement 7 NUREG-0847 Supplement 9 3.3.1 Wind Loading NUREG-0847 Supplement 0 3.3.2 Tornado Loading NUREG-0847 Supplement 0 3.4.1 Flood Protection NUREG-0847 Supplement 0 Page 3 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 3.5.1 Missile Selection and Description NUREG-0847 Supplement 0 NUREG-0847 Supplement 9 NUREG-0847 Supplement 14 3.5.2 Structures, Systems, and Components To Be Protected From Externally Generated Missiles NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 3.5.3 Barrier Design Procedures NUREG-0847 Supplement 0 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 3.6.3 Leak-Before-Break Evaluation Procedures NUREG-0847 Supplement 5 3.7.1 Seismic Input NUREG-0847 Supplement 0 NUREG-0847 Supplement 6 NUREG-0847 Supplement 9 NUREG-0847 Supplement 16 3.7.2 Seismic Analysis NUREG-0847 Supplement 0 NUREG-0847 Supplement 6 NUREG-0847 Supplement 8 NUREG-0847 Supplement 11 NUREG-0847 Supplement 16 Page 4 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 3.7.3 Seismic Subsystem Analysis NUREG-0847 Supplement 0 NUREG-0847 Supplement 6 NUREG-0847 Supplement 7 NUREG-0847 Supplement 8 NUREG-0847 Supplement 9 NUREG-0847 Supplement 12 3.7.4 Seismic Instrumentation NUREG-0847 Supplement 0 3.8.1 Steel Containment NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 3.8.2 Concrete and Structural Steel Internal Structures NUREG-0847 Supplement 0 NUREG-0847 Supplement 7 3.8.3 Other Seismic Category I Structures NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 NUREG-0847 Supplement 16 3.8.4 Foundations NUREG-0847 Supplement 0 3.9.1 Special Topics for Mechanical Components NUREG-0847 Supplement 0 NUREG-0847 Supplement 6 NUREG-0847 Supplement 13 3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 Page 5 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 4 NUREG-0847 Supplement 6 NUREG-0847 Supplement 7 NUREG-0847 Supplement 8 NUREG-0847 Supplement 15 3.9.4 Control Rod Drive Systems NUREG-0847 Supplement 0 3.9.5 Reactor Pressure Vessel Internals NUREG-0847 Supplement 0 3.9.6 Inservice Testing of Pumps and Valves NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 NUREG-0847 Supplement 12 NUREG-0847 Supplement 14 NUREG-0847 Supplement 20 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment NUREG-0847 Supplement 0 NUREG-0847 Supplement 1 NUREG-0847 Supplement 3 NUREG-0847 Supplement 4 NUREG-0847 Supplement 5 NUREG-0847 Supplement 6 NUREG-0847 Supplement 8 NUREG-0847 Supplement 9 3.11.0 Environmental Qualification of Mechanical and Electrical Equipment NUREG-0847 Supplement 0 NUREG-0847 Supplement 15 Page 6 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 4.2.1 Description NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 4.2.2 Thermal Performance NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 4.2.3 Mechanical Performance NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 10 NUREG-0847 Supplement 13 4.2.4 Surveillance NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 4.2.5 Fuel Design Conclusions NUREG-0847 Supplement 0 4.3.1 Design Basis NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 4.3.2 Design Description NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 NUREG-0847 Supplement 15 4.3.3 Analytical Methods NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 4.3.4 Summary of Evaluation Findings NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 4.4.1 Perfomance in Safety Criteria NUREG-0847 Supplement 0 Page 7 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 4.4.2 Design Bases NUREG-0847 Supplement 0 NUREG-0847 Supplement 12 4.4.3 Thermal-Hydraulic Design Methodology NUREG-0847 Supplement 0 NUREG-0847 Supplement 8 NUREG-0847 Supplement 12 NUREG-0847 Supplement 13 NUREG-0847 Supplement 16 4.4.4 Operating Abnormalities NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 4.4.5 Loose Parts Monitoring System NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 5 NUREG-0847 Supplement 16 4.4.6 Thermal-Hydraulic Comparison NUREG-0847 Supplement 0 4.4.7 N-1 Loop Operation NUREG-0847 Supplement 0 4.4.8 Instrumentation for Inadequate Core Cooling Detection (II.F.2)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 10 4.4.9 Summary and Conclusion NUREG-0847 Supplement 0 4.5.1 Control Rod Drive Structural Materials NUREG-0847 Supplement 0 4.5.2 Reactor Internals and Core Support Materials NUREG-0847 Supplement 0 Page 8 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 4.6.0 Functional Design of Reactivity Control Systems NUREG-0847 Supplement 0 5.2.1 Compliance With Codes and Code Cases NUREG-0847 Supplement 0 5.2.2 Overpressure Protection NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 5.2.3 Reactor Coolant Pressure Boundary Materials NUREG-0847 Supplement 0 5.2.4 RCS Pressure Boundary Inservice Inspection and Testing NUREG-0847 Supplement 0 NUREG-0847 Supplement 12 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection NUREG-0847 Supplement 0 5.3.1 Reactor Vessel Materials NUREG-0847 Supplement 0 5.3.2 Pressure-Temperature Limits NUREG-0847 Supplement 0 5.3.3 Reactor Vessel Integrity NUREG-0847 Supplement 0 5.4.1 Reactor Coolant Pumps NUREG-0847 Supplement 0 5.4.2 Steam Generators NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 5.4.3 Residual Heat Removal System NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 10 Page 9 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 5.4.4 Pressurizer Relief Tank NUREG-0847 Supplement 0 5.4.5 Reactor Coolant System Vents (II.B.1)

NUREG-0847 Supplement 0 6.1.1 Metallic Materials NUREG-0847 Supplement 0 6.1.2 Organic Materials NUREG-0847 Supplement 0 6.1.3 Postaccident Emergency Cooling Water Chemistry NUREG-0847 Supplement 0 6.2.1 Containment Functional Design NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 6.2.2 Containment Heat Removal Systems NUREG-0847 Supplement 0 6.2.3 Secondary Containment Functional Design NUREG-0847 Supplement 0 6.2.4 Containment Isolation System NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 5 NUREG-0847 Supplement 12 6.2.5 Combustible Gas Control Systems NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 NUREG-0847 Supplement 8 6.2.6 Containment Leakage Testing NUREG-0847 Supplement 0 6.2.7 Fracture Prevention of Containment Pressure Boundary NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 Page 10 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 6.3.0 Emergency Core Cooling System NUREG-0847 Supplement 0 6.3.1

System Design

NUREG-0847 Supplement 0 NUREG-0847 Supplement 7 NUREG-0847 Supplement 11 6.3.2 Evaluation NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 6.3.3 Testing NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 9 6.3.4 Performance Evaluation NUREG-0847 Supplement 0 6.3.5 Conclusions NUREG-0847 Supplement 0 6.4.0 Control Room Habitability NUREG-0847 Supplement 0 6.5.1 ESF Atmosphere Cleanup Systems NUREG-0847 Supplement 0 6.5.2 Fission Product Cleanup System NUREG-0847 Supplement 0 6.5.3 Fission Product Control System NUREG-0847 Supplement 0 6.5.4 Ice Condenser as a Fission Product Control System NUREG-0847 Supplement 0 6.6.0 Inservice Inspection of Class 2 and 3 Components NUREG-0847 Supplement 0 NUREG-0847 Supplement 10 Page 11 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 7.1.1 General NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 NUREG-0847 Supplement 16 7.1.2 Comparison with Other Plants NUREG-0847 Supplement 0 7.1.3 Design Criteria NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 15 7.2.0 Reactor Trip System NUREG-0847 Supplement 0 7.2.1

System Description

NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 NUREG-0847 Supplement 15 7.2.2 Manual Trip Switches NUREG-0847 Supplement 0 7.2.3 Testing of Reactor Trip Breaker Shunt Coils NUREG-0847 Supplement 0 7.2.4 Anticipatory Trips NUREG-0847 Supplement 0 7.2.5 Steam Generator Water Level Trip NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 14 7.2.6 Conclusions NUREG-0847 Supplement 0 7.3.0 Engineered Safety Features System NUREG-0847 Supplement 0 Page 12 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 7.3.1

System Description

NUREG-0847 Supplement 0 7.3.2 Containment Sump Level Measurement NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 7.3.3 Auxiliary Feedwater Initiation and Control NUREG-0847 Supplement 0 7.3.4 Failure Modes and Effects Analysis NUREG-0847 Supplement 0 7.3.5 IE Bulletin 80-06 NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 7.3.6 Conclusions NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 7.4.1

System Description

NUREG-0847 Supplement 0 7.4.2 Safe Shutdown from Auxiliary Control Room NUREG-0847 Supplement 0 NUREG-0847 Supplement 7 7.4.3 Conclusions NUREG-0847 Supplement 0 7.5.1

System Description

NUREG-0847 Supplement 0 7.5.2 Post-Accident Monitoring System NUREG-0847 Supplement 0 NUREG-0847 Supplement 9 NUREG-0847 Supplement 14 NUREG-0847 Supplement 15 7.5.3 IE Bulletin 79-27 NUREG-0847 Supplement 0 Page 13 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 7.5.4 Conclusions NUREG-0847 Supplement 0 7.6.1

System Description

NUREG-0847 Supplement 0 7.6.2 Residual Heat Removal System Bypass Valves NUREG-0847 Supplement 0 7.6.3 Upper Head Injection Manual Control NUREG-0847 Supplement 0 7.6.4 Protection Against Spurious Actuation of Motor-Operated Valves NUREG-0847 Supplement 0 7.6.5 Overpressure Protection During Low Temperature Operation NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 7.6.6 Valve Power Lockout NUREG-0847 Supplement 0 7.6.7 Cold Leg Accumulator Valve Interlocks and Position Indication NUREG-0847 Supplement 0 7.6.8 Automatic Switchover From Injection to Recirculation Mode NUREG-0847 Supplement 0 7.6.9 Conclusions NUREG-0847 Supplement 0 7.7.1

System Description

NUREG-0847 Supplement 0 7.7.2 Safety System Status Monitoring System NUREG-0847 Supplement 0 NUREG-0847 Supplement 7 NUREG-0847 Supplement 13 7.7.3 Volume Control Tank Level Control System NUREG-0847 Supplement 0 Page 14 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 7.7.4 Pressurizer and Steam Generator Overfill NUREG-0847 Supplement 0 7.7.5 IE Information Notice 79-22 NUREG-0847 Supplement 0 7.7.6 Multiple Control System Failures NUREG-0847 Supplement 0 7.7.7 Conclusions NUREG-0847 Supplement 0 7.7.8 Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC)

NUREG-0847 Supplement 9 NUREG-0847 Supplement 14 7.8.0 NUREG-0737 Items NUREG-0847 Supplement 0 7.8.1 Relief and Safety Valve Position Indication (II.D.3)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 NUREG-0847 Supplement 14 7.8.2 Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2)

NUREG-0847 Supplement 0 7.8.3 Proportional Integral Derivative Control Modification (II.K.3.9)

NUREG-0847 Supplement 0 7.8.4 Proposed Anticipatory Trip Modification (II.K.3.10)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 7.8.5 Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12)

NUREG-0847 Supplement 0 8.1.0 General NUREG-0847 Supplement 0 8.2.1 Compliance With GDC 5 NUREG-0847 Supplement 0 Page 15 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 8.2.2 Compliance With GDC 17 NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 13 8.2.3 Compliance With GDC 18 NUREG-0847 Supplement 0 8.2.4 Evaluation Findings NUREG-0847 Supplement 0 8.3.0 Onsite Power Systems NUREG-0847 Supplement 0 8.3.1 Onsite AC Power System Compliance With GDC 17 NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 7 NUREG-0847 Supplement 13 8.3.2 Onsite DC System Compliance With GDC 17 NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 13 8.3.3 Evaluation Findings NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 3 NUREG-0847 Supplement 7 NUREG-0847 Supplement 13 9.0.0 Auxiliary Systems NUREG-0847 Supplement 0 9.1.1 New Fuel Storage NUREG-0847 Supplement 0 9.1.2 Spent Fuel Storage NUREG-0847 Supplement 0 Page 16 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 9.1.3 Spent Fuel Pool Cooling and Cleanup System NUREG-0847 Supplement 0 9.1.4 Fuel Handling System NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 9.2.1 Essential Raw Cooling Water and Raw Cooling Water Systems NUREG-0847 Supplement 0 NUREG-0847 Supplement 18 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 9.2.3 Demineralized Water Makeup System NUREG-0847 Supplement 0 9.2.4 Potable and Sanitary Water Systems NUREG-0847 Supplement 0 9.2.5 Ultimate Heat Sink NUREG-0847 Supplement 0 9.2.6 Condensate Storage Facilities NUREG-0847 Supplement 0 9.3.1 Compressed Air System NUREG-0847 Supplement 0 9.3.2 Process Sampling System NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 14 9.3.3 Equipment and Floor Drainage System NUREG-0847 Supplement 0 9.3.4 Chemical and Volume Control System NUREG-0847 Supplement 0 Page 17 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 9.4.1 Control Room Area Ventilation System NUREG-0847 Supplement 0 9.4.2 Fuel Handling Area Ventilation System NUREG-0847 Supplement 0 9.4.3 Auxiliary and Radwates Area Ventilation System NUREG-0847 Supplement 0 9.4.4 Turbine Building Area Ventilation System NUREG-0847 Supplement 0 9.4.5 Engineered Safety Features Ventilation System NUREG-0847 Supplement 0 NUREG-0847 Supplement 9 NUREG-0847 Supplement 10 NUREG-0847 Supplement 11 NUREG-0847 Supplement 16 9.5.1 Fire Protection NUREG-0847 Supplement 0 NUREG-0847 Supplement 18 NUREG-0847 Supplement 19 9.5.2 Communication Systems NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 9.5.3 Lighting System NUREG-0847 Supplement 0 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 9.5.5 Emergency Diesel Engine Cooling Water System NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 Page 18 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 9.5.6 Emergency Diesel Engine Starting Systems NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 9.5.7 Emergency Diesel Engine Lubricating Oil System NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 10.1.0 Summary Description NUREG-0847 Supplement 0 10.2.1 Turbine Generator Design NUREG-0847 Supplement 0 10.2.2 Turbine Disc Integrity NUREG-0847 Supplement 0 10.3.0 Main Steam Supply System NUREG-0847 Supplement 0 10.3.1 Main Steam Supply System (up to and including the Main Steam Isolation Valves)

NUREG-0847 Supplement 0 10.3.2 Main Steam Supply System NUREG-0847 Supplement 0 10.3.3 Steam and Feedwater System Materials NUREG-0847 Supplement 0 10.3.4 Secondary Water Chemistry NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 10.4.1 Main Condenser NUREG-0847 Supplement 0 10.4.2 Main Condenser Evacuation System NUREG-0847 Supplement 0 Page 19 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 10.4.3 Turbine Gland Sealing System NUREG-0847 Supplement 0 10.4.4 Turbine Bypass System NUREG-0847 Supplement 0 10.4.5 Condenser Circulating Water System NUREG-0847 Supplement 0 10.4.6 Condensate Cleanup System NUREG-0847 Supplement 0 10.4.7 Condensate and Feedwater Systems NUREG-0847 Supplement 0 10.4.8 Steam Generator Blowdown System NUREG-0847 Supplement 0 10.4.9 Auxiliary Feedwater System NUREG-0847 Supplement 0 11.1.0 Summary Description NUREG-0847 Supplement 0 NUREG-0847 Supplement 16 11.2.0 Liquid Waste Management NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 NUREG-0847 Supplement 16 11.3.0 Gaseous Waste Management NUREG-0847 Supplement 0 NUREG-0847 Supplement 8 NUREG-0847 Supplement 16 11.4.0 Solid Waste Management System NUREG-0847 Supplement 0 NUREG-0847 Supplement 16 Page 20 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 11.5.0 Process and Effluent Radiological Monitoring and Sampling Systems NUREG-0847 Supplement 0 NUREG-0847 Supplement 16 NUREG-0847 Supplement 20 11.6.0 Evaluation Findings NUREG-0847 Supplement 16 11.7.0 NUREG-0737 Items NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 NUREG-0847 Supplement 6 11.7.1 Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))

NUREG-0847 Supplement 5 NUREG-0847 Supplement 15 11.7.2 Primary Coolant Outside Containment (III.D.1.1)

NUREG-0847 Supplement 5 NUREG-0847 Supplement 10 NUREG-0847 Supplement 16 12.1.0 General NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 12.2.0 Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 12.3.0 Radiation Sources NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 12.4.0 Radiation Protection Design Features NUREG-0847 Supplement 0 NUREG-0847 Supplement 10 NUREG-0847 Supplement 14 NUREG-0847 Supplement 18 Page 21 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 12.5.0 Dose Assessment NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 12.6.0 Health Physics Program NUREG-0847 Supplement 0 NUREG-0847 Supplement 10 NUREG-0847 Supplement 14 12.7.1 Plant Shielding (II.B.2)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 NUREG-0847 Supplement 16 12.7.2 High Range Incontainment Monitor (II.F.1(3))

NUREG-0847 Supplement 5 12.7.3 Inplant Radioiodine Monitor (III.D.3.3)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 16 13.1.1 Management and Technical Organization NUREG-0847 Supplement 0 13.1.2 Corporate Organization and Technical Support NUREG-0847 Supplement 0 NUREG-0847 Supplement 8 13.1.3 Plant Staff Organization NUREG-0847 Supplement 0 NUREG-0847 Supplement 8 13.2.1 Licensed Operator Training Program NUREG-0847 Supplement 0 13.2.2 Training for Nonlicensed Personnel NUREG-0847 Supplement 0 Page 22 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 13.3.1 Introduction NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 NUREG-0847 Supplement 20 13.3.2 Evaluation of the Emergency Plan NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 NUREG-0847 Supplement 20 13.3.3 Conclusions NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 NUREG-0847 Supplement 20 13.4.0 Review and Audit NUREG-0847 Supplement 0 NUREG-0847 Supplement 8 13.5.1 Administrative Procedures NUREG-0847 Supplement 0 NUREG-0847 Supplement 9 NUREG-0847 Supplement 10 13.5.2 Operating and Maintenance Procedures NUREG-0847 Supplement 0 NUREG-0847 Supplement 9 NUREG-0847 Supplement 10 13.5.3 NUREG-0737 Items NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 13.6.0 Physical Security Plan NUREG-0847 Supplement 0 NUREG-0847 Supplement 10 NUREG-0847 Supplement 15 Page 23 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 14.0.0 Initial Test Program NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 5 NUREG-0847 Supplement 7 NUREG-0847 Supplement 9 NUREG-0847 Supplement 10 NUREG-0847 Supplement 12 NUREG-0847 Supplement 14 NUREG-0847 Supplement 16 NUREG-0847 Supplement 18 NUREG-0847 Supplement 19 15.1.0 General Discussion NUREG-0847 Supplement 0 15.2.0 Normal Operation and Anticipated Transients NUREG-0847 Supplement 0 15.2.1 Loss of Cooling Transients NUREG-0847 Supplement 0 NUREG-0847 Supplement 13 NUREG-0847 Supplement 14 15.2.2 Increased Cooling Transients NUREG-0847 Supplement 0 15.2.3 Change in Coolant Inventory Transients NUREG-0847 Supplement 0 NUREG-0847 Supplement 18 15.2.4 Reactivity and Power Distribution Anomalies NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 NUREG-0847 Supplement 7 NUREG-0847 Supplement 13 NUREG-0847 Supplement 14 Page 24 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 15.2.5 Conclusions NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 15.3.0 Limiting Accidents NUREG-0847 Supplement 0 15.3.1 Loss-of-Coolant Accident NUREG-0847 Supplement 0 NUREG-0847 Supplement 12 NUREG-0847 Supplement 15 15.3.2 Steamline Break NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 15.3.3 Feedwater System Pipe Break NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 15.3.4 Reactor Coolant Pump Rotor Seizure NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 15.3.5 Reactor Coolant Pump Shaft Break NUREG-0847 Supplement 0 NUREG-0847 Supplement 14 15.3.6 Anticipated Transients Without Scram NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 5 NUREG-0847 Supplement 6 NUREG-0847 Supplement 10 NUREG-0847 Supplement 11 NUREG-0847 Supplement 12 15.3.7 Conclusions NUREG-0847 Supplement 0 Page 25 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 15.4.0 Radiological Consequences of Accidents NUREG-0847 Supplement 0 15.4.1 Loss-of-Coolant Accident NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 NUREG-0847 Supplement 9 NUREG-0847 Supplement 15 NUREG-0847 Supplement 18 15.4.2 Main Steamline Break Outside of Containment NUREG-0847 Supplement 0 NUREG-0847 Supplement 18 15.4.3 Steam Generator Tube Rupture NUREG-0847 Supplement 0 NUREG-0847 Supplement 3 NUREG-0847 Supplement 5 NUREG-0847 Supplement 12 NUREG-0847 Supplement 14 NUREG-0847 Supplement 15 15.4.4 Control Rod Ejection Accident NUREG-0847 Supplement 0 NUREG-0847 Supplement 15 15.4.5 Fuel-Handling Accident NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 NUREG-0847 Supplement 15 15.4.6 Failure of Small Line Carrying Coolant Outside Containment NUREG-0847 Supplement 0 NUREG-0847 Supplement 15 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures NUREG-0847 Supplement 0 NUREG-0847 Supplement 15 Page 26 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 15.5.1 Thermal Mechanical Report (II.K.2.13)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 15.5.2 Voiding in the Reactor Coolant System During Transients (II.K.2.17)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 15.5.3 Installation 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 0 NUREG-0847 Supplement 5 15.5.4 Automatic Trip of Reactor Coolant Pumps (II.K.3.5)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 NUREG-0847 Supplement 5 NUREG-0847 Supplement 16 15.5.5 Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31)

NUREG-0847 Supplement 0 NUREG-0847 Supplement 4 NUREG-0847 Supplement 5 NUREG-0847 Supplement 16 15.6.0 Relative Risk of Low Power Operation NUREG-0847 Supplement 0 16.0.0 Technical Specifications NUREG-0847 Supplement 0 17.1.0 General NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 17.2.0 Organization NUREG-0847 Supplement 0 NUREG-0847 Supplement 5 NUREG-0847 Supplement 13 Page 27 of 28

Subsection Title Table 7.

NUREG-0847 and Supplemental Safety Evaluations Topic Inventory Watts Bar Nuclear Plant Unit 2 17.3.0 Quality Assurance Program NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 5 NUREG-0847 Supplement 10 NUREG-0847 Supplement 13 NUREG-0847 Supplement 15 17.4.0 Conclusions NUREG-0847 Supplement 0 NUREG-0847 Supplement 2 NUREG-0847 Supplement 5 NUREG-0847 Supplement 13 18.1.0 General NUREG-0847 Supplement 0 NUREG-0847 Supplement 16 18.2.0 Conclusions NUREG-0847 Supplement 0 NUREG-0847 Supplement 16 20.0.0 Common Defense and Security NUREG-0847 Supplement 0 21.0.0 Financial Qualifications NUREG-0847 Supplement 0 22.1.0 General NUREG-0847 Supplement 0 22.2.0 Preoperational Storage of Nuclear Fuel NUREG-0847 Supplement 0 22.3.0 Operating Licenses NUREG-0847 Supplement 0 Page 28 of 28

Subsection Title Table 8.

NUREG-0847 Supplements Not Addressed By TVA 3.2.1 Seismic Qualification Does not address SSER 6 and 8 3.2.2 System Quality Group Classification Does not address SSER 3, 6, 7, and 9 3.5.1 Missile Selection and Description Does not address SSER 9 and 14 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping Does not address SSER 14 3.7.1 Seismic Input Does not address SSER 9, and 16 3.7.2 Seismic Analysis Does not address SSER 16 3.8.1 Steel Containment Not addressed in SSER 9 3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment Does not address SSER 14 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures Does not address SSER 15 3.9.6 Inservice Testing of Pumps and Valves Does not address SSER 20 4.2.1 Description Does not address SSER 13 4.2.3 Mechanical Performance Does not address SSER 10 and 13 4.3.2 Design Description Does not address SSER 13 and 15 4.3.3 Analytical Methods Does not address SSER 13 4.3.4 Summary of Evaluation Findings Does not address SSER 13 Page 1 of 5

Subsection Title Table 8, continued.

NUREG-0847 Supplements Not Addressed By TVA 4.4.2 Design Bases Does not address SSER 12 4.4.3 Thermal-Hydraulic Design Methodology Does not address SSER 8, 12, 13, and 16 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection Does not address SSER 9, 11, and 12 5.4.3 Residual Heat Removal System Does not address SSER 10 6.2.4 Containment Isolation System Does not address SSER 12 6.2.5 Combustible Gas Control Systems Does not address SSER 4 and 8 6.3.1

System Design

Does not address SSER 11 6.3.2 Evaluation Does not address SSER 5 7.1.1 General Does not address SSER 13 and 16 7.2.1

System Description

Does not address SSER 13 and 15 7.3.6 Conclusions Does not address SSER 13 7.4.2 Safe Shutdown from Auxiliary Control Room Does not address SSER 7 7.7.2 Safety System Status Monitoring System Does not address SSER 13 7.7.8 Anticipated Transient Without Scram Mitigation System Actuation Circuitry (AMSAC)

Does not address SSER 14 7.8.1 Relief and Safety Valve Position Indication (II.D.3)

Does not address SSER 5 and 14 8.3.1 Onsite AC Power System Compliance With GDC 17 Does not address SSER 13 Page 2 of 5

Subsection Title Table 8, continued.

NUREG-0847 Supplements Not Addressed By TVA 9.1.2 Spent Fuel Storage Does not address SSER 5, 15, and 16 9.2.4 Potable and Sanitary Water Systems Does not address SSER 9 9.2.6 Condensate Storage Facilities Does not address SSER 12 9.3.2 Process Sampling System Does not address SSER 16 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System Does not address SSER 9, 10, 11, and 12 9.5.5 Emergency Diesel Engine Cooling Water System Does not address SSER 11 9.5.6 Emergency Diesel Engine Starting Systems Does not address SSER 10 9.5.7 Emergency Diesel Engine Lubricating Oil System Does not address SSER 10 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System Does not address SSER 10 10.2.0 Turbine Generator Does not address SSER 5 10.2.1 Turbine Generator Design Does not address SSER 12 10.3.1 Main Steam Supply System (up to and including the Main Steam Isolation Valves)

Does not address SSER 12 and 19 10.4.1 Main Condenser Does not address SSER 9 10.4.4 Turbine Bypass System Does not address SSER 5 10.4.7 Condensate and Feedwater Systems Does not address SSER 14 10.4.9 Auxiliary Feedwater System Does not address SSER 14 Page 3 of 5

Subsection Title Table 8, continued.

NUREG-0847 Supplements Not Addressed By TVA 11.7.0 NUREG-0737 Items Does not address SSER 5 or 6 13.5.2 Operating and Maintenance Procedures Does not address SSER 10 14.0.0 Initial Test Program Does not address SSER 16, 18, and 19 15.2.1 Loss of Cooling Transients Does not address SSER 13 and 14 15.2.3 Change in Coolant Inventory Transients Does not address SSER 18 15.2.4 Reactivity and Power Distribution Anomalies Does not address SSER 7, 13, and 14 15.3.1 Loss-of-Coolant Accident Does not address SSER 12 and 15 15.3.2 Steamline Break Does not address SSER 14 15.3.3 Feedwater System Pipe Break Does not address SSER 14 15.3.4 Reactor Coolant Pump Rotor Seizure Does not address SSER 14 15.3.5 Reactor Coolant Pump Shaft Break Does not address SSER 14 15.3.6 Anticipated Transients Without Scram Does not address SSER 6, 10, 11, 12 15.4.1 Loss-of-Coolant Accident Does not address SSER 5, 9, 15, and 18 15.4.2 Main Steamline Break Outside of Containment Does not address SSER 18 15.4.3 Steam Generator Tube Rupture Does not address SSER 15 15.4.4 Control Rod Ejection Accident Does not address SSER 15 Page 4 of 5

Subsection Title Table 8, continued.

NUREG-0847 Supplements Not Addressed By TVA 15.4.5 Fuel-Handling Accident Does not address SSER 4 and 15 15.4.6 Failure of Small Line Carrying Coolant Outside Containment Does not address SSER 15 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures Does not address SSER 15 17.1.0 General Does not address SSER 5 17.3.0 Quality Assurance Program Does not address SSER 2, 5, 10, 13, and 15 17.4.0 Conclusions Does not address SSER 2, 5, and 13 Page 5 of 5

v t e Letter Sequence Approval
TAC:MD6311, Clarify Application of Setpoint Methodology for LSSS Functions, Control Room Habitability, Steam Generator Tube Integrity (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, ... further results\|Request]] Acceptance... Supplement, Supplement Administration Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting Questions 4 March 2011 7 May 2008 12 October 2010 Answers 9 November 2010 11 February 2011 25 February 2011 Results Approval Other: CNL-14-154, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 12, CNL-15-137, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 13 (TAC No. MD6311) and Status of Generic Communications for Unit 2 - Revision 13, ML080860026, ML080860040, ML081700293, ML082410088, ML083460177, ML090480486, ML101200204, ML101260469, ML101600477, ML101680561, ML102170077, ML103010299, ML11213A130, ML11362A056, ML12234A688, ML13023A315, ML13213A194
MONTHYEAR2010-11-01 [Table View]

ML081010116

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