ML081930344
| ML081930344 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/28/2008 |
| From: | Milano P NRC/NRR/ADRO/DORL/WBSPB |
| To: | Office of Nuclear Reactor Regulation |
| Milano P, NRR/DORL , 415-1457 | |
| Shared Package | |
| ML081930063 | List: |
| References | |
| SECY-09-0012 | |
| Download: ML081930344 (15) | |
Text
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title AADB 2.1.1 Site Location and Description AADB 2.1.2 Exclusion Area Authority and Control AADB 2.1.3 Population Distribution AADB 2.2.1 Transportation Routes AADB 2.2.2 Nearby Facilities AADB 2.2.3 Conclusions AADB 2.3.1 Regional Climatology AADB 2.3.2 Local Meteorology AADB 2.3.3 Onsite Meteorological Measurements Program AADB 2.3.4 Short-Term (Accident) Atmospheric Diffusion Estimates AADB 2.3.5 Long-Term (Routine) Diffusion Estimates AADB 6.4.0 Control Room Habitability AADB 6.5.1 ESF Atmosphere Cleanup Systems AADB 11.1.0 Summary Description AADB 11.7.1 Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))
AADB 11.7.2 Primary Coolant Outside Containment (III.D.1.1)
AADB 15.4.0 Radiological Consequences of Accidents AADB 15.4.1 Loss-of-Coolant Accident AADB 15.4.2 Main Steamline Break Outside of Containment AADB 15.4.3 Steam Generator Tube Rupture AADB 15.4.4 Control Rod Ejection Accident AADB 15.4.5 Fuel-Handling Accident AADB 15.4.6 Failure of Small Line Carrying Coolant Outside Containment AFPB 9.5.1 Fire Protection AFPB 23.2.7 Fire Protection APOB 17.6.0 Maintenance Rule CPNB 3.6.3 Leak-Before-Break Evaluation Procedures CPNB 4.5.1 Control Rod Drive Structural Materials CPNB 5.2.3 Reactor Coolant Pressure Boundary Materials Branch has lead responsibility for Items in bold. Page B-1 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title CPNB 5.2.4 RCS Pressure Boundary Inservice Inspection and Testing CPNB 6.6.0 Inservice Inspection of Class 2 and 3 Components CPNB 10.3.3 Steam and Feedwater System Materials CPNB 23.2.9 Heat Code Traceability CPNB 23.2.18 Welding CPTB 3.9.6 Inservice Testing of Pumps and Valves CSGB 3.13.0 Threaded Fasteners - ASME Code Class 1, 2, and 3 [SRP TOC]
CSGB 5.4.2 Steam Generators CSGB 6.1.3 Postaccident Emergency Cooling Water Chemistry CSGB 6.4.0 Control Room Habitability CSGB 6.5.2 Fission Product Cleanup System CSGB 9.1.1 New Fuel Storage CSGB 9.1.2 Spent Fuel Storage CSGB 9.1.3 Spent Fuel Pool Cooling and Cleanup System CSGB 9.2.3 Demineralized Water Makeup System CSGB 9.3.2 Process Sampling System CSGB 9.3.4 Chemical and Volume Control System CSGB 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System CSGB 10.3.4 Secondary Water Chemistry CSGB 10.4.6 Condensate Cleanup System CSGB 10.4.8 Steam Generator Blowdown System CSGB 23.3.7 Microbiologically Induced Corrosion (MIC)
CVIB 4.5.2 Reactor Internals and Core Support Materials CVIB 5.2.3 Reactor Coolant Pressure Boundary Materials CVIB 5.2.4 RCS Pressure Boundary Inservice Inspection and Testing CVIB 5.3.1 Reactor Vessel Materials CVIB 5.3.2 Pressure-Temperature Limits CVIB 5.3.3 Reactor Vessel Integrity CVIB 5.4.1 Reactor Coolant Pumps Branch has lead responsibility for Items in bold. Page B-2 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title CVIB 6.1.1 Metallic Materials CVIB 6.1.2 Organic Materials CVIB 6.2.7 Fracture Prevention of Containment Pressure Boundary CVIB 10.2.2 Turbine Disc Integrity DE-AT 23.7.0 Employee Concerns DE-AT 23.8.0 Allegations DORL 1.0.0 Introduction and General Discussion DORL 1.1.0 Introduction DORL 1.1.1 Metrication DORL 1.1.2 Proprietary Information DORL 1.1.4 Additional Information DORL 1.2.0 General Design Description DORL 1.3.0 Comparison With Similar Facility Designs DORL 1.3.1 Comparison With the Sequoyah Nuclear Plant DORL 1.3.2 Comparison With Other Facilities DORL 1.4.0 Identification of Agents and Contractors DORL 1.5.0 Summary of Principal Review Matters DORL 1.6.0 Modifications to the Watts Bar Facility During the Course of NRC Review DORL 1.7.0 Summary of Outstanding Issues DORL 1.8.0 Confirmatory Issues DORL 1.9.0 License Conditions DORL 1.10.0 Unresolved Safety Issues DORL 2.0.0 Site Envelope DORL 2.1.0 Geography and Demography DORL 19.0.0 Report of the Advisory Committee on Reactor Safeguards DORL 23.0.0 Nuclear Performance Plan DORL 23.4.1 Corrective Action Program Plans and Special Programs EEEB 2.5.6 Embankments and Dams EEEB 3.1.1 Conformance With General Design Criteria Branch has lead responsibility for Items in bold. Page B-3 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title EEEB 3.1.2 Conformance With Industry Codes and Standards EEEB 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment EEEB 3.11.0 Environmental Qualification of Mechanical and Electrical Equipment EEEB 8.1.0 General EEEB 8.2.1 Compliance With GDC 5 EEEB 8.2.2 Compliance With GDC 17 EEEB 8.2.3 Compliance With GDC 18 EEEB 8.2.4 Evaluation Findings EEEB 8.3.1 Onsite AC Power System Compliance With GDC 17 EEEB 8.3.2 Onsite DC System Compliance With GDC 17 EEEB 8.3.3 Evaluation Findings EEEB 8.4.0 Station Blackout EEEB 9.5.3 Lighting System EEEB 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System EEEB 9.5.5 Emergency Diesel Engine Cooling Water System EEEB 9.5.6 Emergency Diesel Engine Starting Systems EEEB 9.5.7 Emergency Diesel Engine Lubricating Oil System EEEB 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System EEEB 23.2.1 Cable Issues EEEB 23.2.5 Electrical Issues EEEB 23.2.6 Equipment Seismic Qualification EEEB 23.3.4 Environmental Qualification Program EEEB 23.3.5 Master Fuse List EICB 3.1.1 Conformance With General Design Criteria EICB 3.1.2 Conformance With Industry Codes and Standards EICB 3.11.0 Environmental Qualification of Mechanical and Electrical Equipment EICB 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection EICB 7.1.1 General EICB 7.1.2 Comparison with Other Plants Branch has lead responsibility for Items in bold. Page B-4 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title EICB 7.1.3 Design Criteria EICB 7.2.1 System Description EICB 7.2.2 Manual Trip Switches EICB 7.2.3 Testing of Reactor Trip Breaker Shunt Coils EICB 7.2.4 Anticipatory Trips EICB 7.2.5 Steam Generator Water Level Trip EICB 7.2.6 Conclusions EICB 7.3.1 System Description EICB 7.3.2 Containment Sump Level Measurement EICB 7.3.3 Auxiliary Feedwater Initiation and Control EICB 7.3.4 Failure Modes and Effects Analysis EICB 7.3.5 IE Bulletin 80-06 EICB 7.3.6 Conclusions EICB 7.4.1 System Description EICB 7.4.2 Safe Shutdown from Auxiliary Control Room EICB 7.4.3 Conclusions EICB 7.5.1 System Description EICB 7.5.2 Post-Accident Monitoring System EICB 7.5.3 IE Bulletin 79-27 EICB 7.5.4 Conclusions EICB 7.6.1 System Description EICB 7.6.2 Residual Heat Removal System Bypass Valves EICB 7.6.3 Upper Head Injection Manual Control EICB 7.6.4 Protection Against Spurious Actuation of Motor-Operated Valves EICB 7.6.5 Overpressure Protection During Low Temperature Operation EICB 7.6.6 Valve Power Lockout EICB 7.6.7 Cold Leg Accumulator Valve Interlocks and Position Indication EICB 7.6.8 Automatic Switchover From Injection to Recirculation Mode EICB 7.6.9 Conclusions Branch has lead responsibility for Items in bold. Page B-5 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title EICB 7.7.1 System Description EICB 7.7.2 Safety System Status Monitoring System EICB 7.7.3 Volume Control Tank Level Control System EICB 7.7.4 Pressurizer and Steam Generator Overfill EICB 7.7.5 IE Information Notice 79-22 EICB 7.7.6 Multiple Control System Failures EICB 7.7.7 Conclusions EICB 7.8.1 Relief and Safety Valve Position Indication (II.D.3)
EICB 7.8.2 Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2)
EICB 7.8.3 Proportional Integral Derivative Control Modification (II.K.3.9)
EICB 7.8.4 Proposed Anticipatory Trip Modification (II.K.3.10)
EICB 7.8.5 Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12)
EICB 7.9.0 Data Communication Systems [SRP TOC]
EICB 9.2.1 Essential Raw Cooling Water and Raw Cooling Water Systems EICB 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System)
EICB 9.2.5 Ultimate Heat Sink EICB 9.3.1 Compressed Air System EICB 9.3.2 Process Sampling System EICB 9.3.4 Chemical and Volume Control System EICB 9.4.1 Control Room Area Ventilation System EICB 9.4.5 Engineered Safety Features Ventilation System EICB 9.5.2 Communication Systems EICB 10.3.0 Main Steam Supply System EICB 10.4.2 Main Condenser Evacuation System EICB 10.4.4 Turbine Bypass System EICB 10.4.5 Condenser Circulating Water System EICB 10.4.7 Condensate and Feedwater Systems EICB 10.4.8 Steam Generator Blowdown System EICB 10.4.9 Auxiliary Feedwater System Branch has lead responsibility for Items in bold. Page B-6 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title EICB 11.5.0 Process and Effluent Radiological Monitoring and Sampling Systems EICB 23.2.11 Instrument Lines EMCB 2.4.1 Introduction EMCB 2.4.2 Hydrologic Description EMCB 2.4.3 Flood Potential EMCB 2.4.4 Local Intense Precipitation in Plant Area EMCB 2.4.5 Roof Drainage EMCB 2.4.6 Ultimate Heat Sink EMCB 2.4.7 Groundwater EMCB 2.4.8 Design Basis for Subsurface Hydrostatic Loading EMCB 2.4.9 Transport of Liquid Releases EMCB 2.4.10 Flooding Protection Requirements and Technical Specifications EMCB 2.5.1 Geology EMCB 2.5.2 Seismology EMCB 2.5.3 Surface Faulting EMCB 2.5.4 Stability of Subsurface Materials and Foundations EMCB 2.5.5 Stability of Slopes EMCB 2.5.6 Embankments and Dams EMCB 3.0.0 Design of Structures, Components, Equipment, and Systems EMCB 3.1.1 Conformance With General Design Criteria EMCB 3.1.2 Conformance With Industry Codes and Standards EMCB 3.2.1 Seismic Qualification EMCB 3.2.2 System Quality Group Classification EMCB 3.3.1 Wind Loading EMCB 3.3.2 Tornado Loading EMCB 3.4.1 Flood Protection EMCB 3.5.1 Missile Selection and Description EMCB 3.5.3 Barrier Design Procedures EMCB 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Branch has lead responsibility for Items in bold. Page B-7 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title EMCB 3.7.1 Seismic Input EMCB 3.7.2 Seismic Analysis EMCB 3.7.3 Seismic Subsystem Analysis EMCB 3.7.4 Seismic Instrumentation EMCB 3.8.1 Steel Containment EMCB 3.8.2 Concrete and Structural Steel Internal Structures EMCB 3.8.3 Other Seismic Category I Structures EMCB 3.8.4 Foundations EMCB 3.9.1 Special Topics for Mechanical Components EMCB 3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment EMCB 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures EMCB 3.9.4 Control Rod Drive Systems EMCB 3.9.5 Reactor Pressure Vessel Internals EMCB 3.10.0 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment EMCB 3.11.0 Environmental Qualification of Mechanical and Electrical Equipment EMCB 5.2.1 Compliance With Codes and Code Cases EMCB 11.3.0 Gaseous Waste Management EMCB 23.2.2 Cable Tray and Tray Supports EMCB 23.2.4 Electrical Conduit and Conduit Support EMCB 23.2.6 Equipment Seismic Qualification EMCB 23.2.8 Hanger and Analysis Update Program EMCB 23.2.9 Heat Code Traceability EMCB 23.2.10 Heating, Ventilation, and Air-Conditioning Duct and Duct Supports EMCB 23.2.11 Instrument Lines EMCB 23.2.16 Seismic Analysis EMCB 23.3.1 Concrete Quality Program EMCB 23.3.6 Mechanical Equipment Qualification EMCB 23.3.10 Soil Liquefaction EQVB 3.1.1 Conformance With General Design Criteria Branch has lead responsibility for Items in bold. Page B-8 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title EQVB 3.1.2 Conformance With Industry Codes and Standards EQVB 13.4.0 Review and Audit EQVB 14.0.0 Initial Test Program EQVB 17.1.0 General EQVB 17.2.0 Organization EQVB 17.3.0 Quality Assurance Program EQVB 17.4.0 Conclusions EQVB 23.2.3 Design Baseline and Verification Program EQVB 23.2.13 QA Records EQVB 23.2.14 Q-List EQVB 23.2.15 Replacement Items Program (Piece Parts)
EQVB 23.2.17 Vendor Information Program EQVB 23.3.11 Use-as-is CAQs EQVB 23.4.2 Quality Verification Process IOLB 9.5.1 Fire Protection IOLB 13.1.1 Management and Technical Organization IOLB 13.1.2 Corporate Organization and Technical Support IOLB 13.1.3 Plant Staff Organization IOLB 13.2.1 Licensed Operator Training Program IOLB 13.2.2 Training for Nonlicensed Personnel IOLB 13.5.1 Administrative Procedures IOLB 13.5.2 Operating and Maintenance Procedures IOLB 13.5.3 NUREG-0737 Items IOLB 14.0.0 Initial Test Program IOLB 18.0.0 Control Room Design Review IOLB 18.1.0 General IOLB 18.2.0 Conclusions IOLB 23.2.12 Prestart Test Program IOLB 23.3.3 Detailed Control Room Design Review Branch has lead responsibility for Items in bold. Page B-9 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title IOLB 23.5.1 Introduction IOLB 23.5.2 Organizational and Management Improvements IOLB 23.5.3 Conclusions IOLB 23.6.0 Operational Readiness IRIB 6.5.3 Fission Product Control System IRIB 9.3.2 Process Sampling System IRIB 11.1.0 Summary Description IRIB 11.2.0 Liquid Waste Management IRIB 11.3.0 Gaseous Waste Management IRIB 11.4.0 Solid Waste Management System IRIB 11.5.0 Process and Effluent Radiological Monitoring and Sampling Systems IRIB 12.1.0 General IRIB 12.2.0 Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable IRIB 12.3.0 Radiation Sources IRIB 12.4.0 Radiation Protection Design Features IRIB 12.5.0 Dose Assessment IRIB 12.6.0 Health Physics Program IRIB 12.7.1 Plant Shielding (II.B.2)
IRIB 12.7.2 High Range Incontainment Monitor (II.F.1(3))
IRIB 12.7.3 Inplant Radioiodine Monitor (III.D.3.3)
IRIB 23.3.9 Radiation Monitoring System ITSB 16.0.0 Technical Specifications NSIR 13.3.1 Introduction NSIR 13.3.2 Evaluation of the Emergency Plan NSIR 13.3.3 Conclusions NSIR 13.6.0 Physical Security Plan NSIR 20.0.0 Common Defense and Security PFPB 20.0.0 Common Defense and Security PFPB 21.0.0 Financial Qualifications Branch has lead responsibility for Items in bold. Page B-10 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title PFPB 22.0.0 Financial Protection and Indemnity Requirements PFPB 22.1.0 General PFPB 22.2.0 Preoperational Storage of Nuclear Fuel PFPB 22.3.0 Operating Licenses SBPB 3.4.1 Flood Protection SBPB 3.5.1 Missile Selection and Description SBPB 3.5.2 Structures, Systems, and Components To Be Protected From Externally Generated Missiles SBPB 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment SBPB 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection SBPB 9.1.1 New Fuel Storage SBPB 9.1.2 Spent Fuel Storage SBPB 9.1.3 Spent Fuel Pool Cooling and Cleanup System SBPB 9.1.4 Fuel Handling System SBPB 9.2.1 Essential Raw Cooling Water and Raw Cooling Water Systems SBPB 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System)
SBPB 9.2.4 Potable and Sanitary Water Systems SBPB 9.2.5 Ultimate Heat Sink SBPB 9.2.6 Condensate Storage Facilities SBPB 9.3.1 Compressed Air System SBPB 9.3.2 Process Sampling System SBPB 9.3.3 Equipment and Floor Drainage System SBPB 9.3.4 Chemical and Volume Control System SBPB 9.5.4 Emergency Diesel Engine Fuel Oil Storage and Transfer System SBPB 9.5.5 Emergency Diesel Engine Cooling Water System SBPB 9.5.6 Emergency Diesel Engine Starting Systems SBPB 9.5.7 Emergency Diesel Engine Lubricating Oil System SBPB 9.5.8 Emergency Diesel Engine Combustion Air Intake and Exhaust System SBPB 10.1.0 Summary Description SBPB 10.2.0 Turbine Generator Branch has lead responsibility for Items in bold. Page B-11 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title SBPB 10.2.1 Turbine Generator Design SBPB 10.2.2 Turbine Disc Integrity SBPB 10.3.0 Main Steam Supply System SBPB 10.3.1 Main Steam Supply System (up to and including the Main Steam Isolation Valves)
SBPB 10.3.2 Main Steam Supply System SBPB 10.4.1 Main Condenser SBPB 10.4.2 Main Condenser Evacuation System SBPB 10.4.3 Turbine Gland Sealing System SBPB 10.4.4 Turbine Bypass System SBPB 10.4.5 Condenser Circulating Water System SBPB 10.4.7 Condensate and Feedwater Systems SBPB 10.4.9 Auxiliary Feedwater System SBPB 11.2.0 Liquid Waste Management SBPB 11.3.0 Gaseous Waste Management SBPB 11.4.0 Solid Waste Management System SBPB 11.5.0 Process and Effluent Radiological Monitoring and Sampling Systems SBPB 23.3.8 Moderate Energy Line Break Flooding SCVB 6.2.1 Containment Functional Design SCVB 6.2.2 Containment Heat Removal Systems SCVB 6.2.3 Secondary Containment Functional Design SCVB 6.2.4 Containment Isolation System SCVB 6.2.5 Combustible Gas Control Systems SCVB 6.2.6 Containment Leakage Testing SCVB 6.4.0 Control Room Habitability SCVB 6.5.1 ESF Atmosphere Cleanup Systems SCVB 6.5.2 Fission Product Cleanup System SCVB 6.5.3 Fission Product Control System SCVB 6.5.4 Ice Condenser as a Fission Product Control System SCVB 9.4.1 Control Room Area Ventilation System Branch has lead responsibility for Items in bold. Page B-12 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title SCVB 9.4.2 Fuel Handling Area Ventilation System SCVB 9.4.3 Auxiliary and Radwates Area Ventilation System SCVB 9.4.4 Turbine Building Area Ventilation System SCVB 9.4.5 Engineered Safety Features Ventilation System SCVB 11.3.0 Gaseous Waste Management SCVB 23.3.2 Containment Cooling SNPB 4.2.1 Description SNPB 4.2.2 Thermal Performance SNPB 4.2.3 Mechanical Performance SNPB 4.2.4 Surveillance SNPB 4.2.5 Fuel Design Conclusions SNPB 4.3.1 Design Basis SNPB 4.3.2 Design Description SNPB 4.3.3 Analytical Methods SNPB 4.3.4 Summary of Evaluation Findings SNPB 4.4.2 Design Bases SNPB 4.6.0 Functional Design of Reactivity Control Systems SNPB 5.2.1 Compliance With Codes and Code Cases SNPB 15.3.3 Feedwater System Pipe Break SNPB 15.3.4 Reactor Coolant Pump Rotor Seizure SNPB 15.3.5 Reactor Coolant Pump Shaft Break SNPB 15.4.0 Radiological Consequences of Accidents SNPB 15.4.1 Loss-of-Coolant Accident SNPB 15.4.2 Main Steamline Break Outside of Containment SRXB 3.0.0 Design of Structures, Components, Equipment, and Systems SRXB 3.1.1 Conformance With General Design Criteria SRXB 3.1.2 Conformance With Industry Codes and Standards SRXB 4.4.1 Perfomance in Safety Criteria SRXB 4.4.2 Design Bases Branch has lead responsibility for Items in bold. Page B-13 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title SRXB 4.4.3 Thermal-Hydraulic Design Methodology SRXB 4.4.4 Operating Abnormalities SRXB 4.4.5 Loose Parts Monitoring System SRXB 4.4.6 Thermal-Hydraulic Comparison SRXB 4.4.7 N-1 Loop Operation SRXB 4.4.8 Instrumentation for Inadequate Core Cooling Detection (II.F.2)
SRXB 4.4.9 Summary and Conclusion SRXB 5.2.2 Overpressure Protection SRXB 5.2.4 RCS Pressure Boundary Inservice Inspection and Testing SRXB 5.4.3 Residual Heat Removal System SRXB 5.4.4 Pressurizer Relief Tank SRXB 5.4.5 Reactor Coolant System Vents (II.B.1)
SRXB 6.3.1 System Design SRXB 6.3.2 Evaluation SRXB 6.3.3 Testing SRXB 6.3.4 Performance Evaluation SRXB 6.3.5 Conclusions SRXB 9.3.2 Process Sampling System SRXB 15.1.0 General Discussion SRXB 15.2.0 Normal Operation and Anticipated Transients SRXB 15.2.1 Loss of Cooling Transients SRXB 15.2.2 Increased Cooling Transients SRXB 15.2.3 Change in Coolant Inventory Transients SRXB 15.2.4 Reactivity and Power Distribution Anomalies SRXB 15.2.5 Conclusions SRXB 15.3.0 Limiting Accidents SRXB 15.3.1 Loss-of-Coolant Accident SRXB 15.3.2 Steamline Break SRXB 15.3.6 Anticipated Transients Without Scram Branch has lead responsibility for Items in bold. Page B-14 of 15
Appendix B Watts Bar Nuclear Plant Unit 2 Safety Evaluation Review Responsibilities Branch SER Title SRXB 15.3.7 Conclusions SRXB 15.4.0 Radiological Consequences of Accidents SRXB 15.4.1 Loss-of-Coolant Accident SRXB 15.4.3 Steam Generator Tube Rupture SRXB 15.4.4 Control Rod Ejection Accident SRXB 15.4.5 Fuel-Handling Accident SRXB 15.4.6 Failure of Small Line Carrying Coolant Outside Containment SRXB 15.4.7 Postulated Radioactive Releases as a Result of Liquid Tank Failures SRXB 15.5.1 Thermal Mechanical Report (II.K.2.13)
SRXB 15.5.2 Voiding in the Reactor Coolant System During Transients (II.K.2.17)
SRXB 15.5.3 Installation and Testing of Automatic Power-Operated Relief Valve Isolation System (II.K.3.1), Report on SRXB 15.5.4 Automatic Trip of Reactor Coolant Pumps (II.K.3.5)
SRXB 15.5.5 Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31)
SRXB 15.6.0 Relative Risk of Low Power Operation Branch has lead responsibility for Items in bold. Page B-15 of 15