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 BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch2.1.1Site Location and DescriptionAADB2.1.2Exclusion Area Authority and ControlAADB2.1.3Population DistributionAADB2.2.1Transportation RoutesAADB2.2.2Nearby FacilitiesAADB2.2.3ConclusionsAADB2.3.1Regional ClimatologyAADB2.3.2Local MeteorologyAADB2.3.3Onsite Meteorological Measurements ProgramAADB2.3.4Short-Term (Accident) Atmospheric Diffusion EstimatesAADB2.3.5Long-Term (Routine) Diffusion EstimatesAADB6.4.0Control Room HabitabilityAADB6.5.1ESF Atmosphere Cleanup SystemsAADB11.1.0Summary DescriptionAADB11.7.1Wide Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1(1) and II.F.1(2))AADB11.7.2Primary Coolant Outside Containment (III.D.1.1)AADB15.4.0Radiological Consequences of AccidentsAADB15.4.1Loss-of-Coolant AccidentAADB15.4.2Main Steamline Break Outside of ContainmentAADB15.4.3Steam Generator Tube RuptureAADB15.4.4Control Rod Ejection AccidentAADB15.4.5Fuel-Handling AccidentAADB15.4.6Failure of Small Line Carrying Coolant Outside ContainmentAADB9.5.1Fire Protection AFPB23.2.7Fire Protection AFPB17.6.0Maintenance RuleAPOB3.6.3Leak-Before-Break Evaluation ProceduresCPNB4.5.1Control Rod Drive Structural MaterialsCPNB5.2.3Reactor Coolant Pressure Boundary MaterialsCPNBBranch has lead responsibility for Items in bold.Page B-1 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch5.2.4RCS Pressure Boundary Inservice Inspection and TestingCPNB6.6.0Inservice Inspection of Class 2 and 3 ComponentsCPNB10.3.3Steam and Feedwater System MaterialsCPNB23.2.9Heat Code TraceabilityCPNB23.2.18WeldingCPNB3.9.6Inservice Testing of Pumps and Valves CPTB3.13.0Threaded Fasteners - ASME Code Class 1, 2, and 3 [SRP TOC]CSGB5.4.2Steam GeneratorsCSGB6.1.3Postaccident Emergency Cooling Water ChemistryCSGB6.4.0Control Room HabitabilityCSGB6.5.2Fission Product Cleanup SystemCSGB9.1.1New Fuel StorageCSGB9.1.2Spent Fuel StorageCSGB9.1.3Spent Fuel Pool Cooling and Cleanup SystemCSGB9.2.3Demineralized Water Makeup SystemCSGB9.3.2Process Sampling SystemCSGB9.3.4Chemical and Volume Control SystemCSGB9.5.4Emergency Diesel Engine Fuel Oil Storage and Transfer SystemCSGB10.3.4Secondary Water ChemistryCSGB10.4.6Condensate Cleanup SystemCSGB10.4.8Steam Generator Blowdown SystemCSGB23.3.7Microbiologically Induced Corrosion (MIC)CSGB4.5.2Reactor Internals and Core Support Materials CVIB5.2.3Reactor Coolant Pressure Boundary Materials CVIB5.2.4RCS Pressure Boundary Inservice Inspection and Testing CVIB5.3.1Reactor Vessel Materials CVIB5.3.2Pressure-Temperature Limits CVIB5.3.3Reactor Vessel Integrity CVIB5.4.1Reactor Coolant Pumps CVIBBranch has lead responsibility for Items in bold.Page B-2 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch6.1.1Metallic Materials CVIB6.1.2Organic Materials CVIB6.2.7Fracture Prevention of Containment Pressure Boundary CVIB10.2.2Turbine Disc Integrity CVIB23.7.0Employee ConcernsDE-AT23.8.0AllegationsDE-AT1.0.0Introduction and General DiscussionDORL1.1.0IntroductionDORL1.1.1MetricationDORL1.1.2Proprietary InformationDORL1.1.4Additional InformationDORL1.2.0General Design DescriptionDORL1.3.0Comparison With Similar Facility DesignsDORL1.3.1Comparison With the Sequoyah Nuclear PlantDORL1.3.2Comparison With Other FacilitiesDORL1.4.0Identification of Agents and ContractorsDORL1.5.0Summary of Principal Review MattersDORL1.6.0Modifications to the Watts Bar Facility During the Course of NRC ReviewDORL1.7.0Summary of Outstanding IssuesDORL1.8.0Confirmatory IssuesDORL1.9.0License ConditionsDORL1.10.0Unresolved Safety IssuesDORL2.0.0Site EnvelopeDORL2.1.0Geography and DemographyDORL19.0.0Report of the Advisory Committee on Reactor SafeguardsDORL23.0.0Nuclear Performance PlanDORL23.4.1Corrective Action Program Plans and Special ProgramsDORL2.5.6Embankments and DamsEEEB3.1.1Conformance With General Design CriteriaEEEBBranch has lead responsibility for Items in bold.Page B-3 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch3.1.2Conformance With Industry Codes and StandardsEEEB3.10.0Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical EquipmentEEEB3.11.0Environmental Qualification of Mechanical and Electrical EquipmentEEEB8.1.0GeneralEEEB8.2.1Compliance With GDC 5EEEB8.2.2Compliance With GDC 17EEEB8.2.3Compliance With GDC 18EEEB8.2.4Evaluation FindingsEEEB8.3.1Onsite AC Power System Compliance With GDC 17EEEB8.3.2Onsite DC System Compliance With GDC 17EEEB8.3.3Evaluation FindingsEEEB8.4.0Station BlackoutEEEB9.5.3Lighting SystemEEEB9.5.4Emergency Diesel Engine Fuel Oil Storage and Transfer SystemEEEB9.5.5Emergency Diesel Engine Cooling Water SystemEEEB9.5.6Emergency Diesel Engine Starting SystemsEEEB9.5.7Emergency Diesel Engine Lubricating Oil SystemEEEB9.5.8Emergency Diesel Engine Combustion Air Intake and Exhaust SystemEEEB23.2.1Cable IssuesEEEB23.2.5Electrical IssuesEEEB23.2.6Equipment Seismic QualificationEEEB23.3.4Environmental Qualification ProgramEEEB23.3.5Master Fuse ListEEEB3.1.1Conformance With General Design Criteria EICB3.1.2Conformance With Industry Codes and Standards EICB3.11.0Environmental Qualification of Mechanical and Electrical Equipment EICB5.2.5Reactor Coolant Pressure Boundary Leakage Detection EICB7.1.1General EICB7.1.2Comparison with Other Plants EICBBranch has lead responsibility for Items in bold.Page B-4 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch7.1.3Design Criteria EICB7.2.1System Description EICB7.2.2Manual Trip Switches EICB7.2.3Testing of Reactor Trip Breaker Shunt Coils EICB7.2.4Anticipatory Trips EICB7.2.5Steam Generator Water Level Trip EICB7.2.6Conclusions EICB7.3.1System Description EICB7.3.2Containment Sump Level Measurement EICB7.3.3Auxiliary Feedwater Initiation and Control EICB7.3.4Failure Modes and Effects Analysis EICB7.3.5IE Bulletin 80-06 EICB7.3.6Conclusions EICB7.4.1System Description EICB7.4.2Safe Shutdown from Auxiliary Control Room EICB7.4.3Conclusions EICB7.5.1System Description EICB7.5.2Post-Accident Monitoring System EICB7.5.3IE Bulletin 79-27 EICB7.5.4Conclusions EICB7.6.1System Description EICB7.6.2Residual Heat Removal System Bypass Valves EICB7.6.3Upper Head Injection Manual Control EICB7.6.4Protection Against Spurious Actuation of Motor-Operated Valves EICB7.6.5Overpressure Protection During Low Temperature Operation EICB7.6.6Valve Power Lockout EICB7.6.7Cold Leg Accumulator Valve Interlocks and Position Indication EICB7.6.8Automatic Switchover From Injection to Recirculation Mode EICB7.6.9Conclusions EICBBranch has lead responsibility for Items in bold.Page B-5 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch7.7.1System Description EICB7.7.2Safety System Status Monitoring System EICB7.7.3Volume Control Tank Level Control System EICB7.7.4Pressurizer and Steam Generator Overfill EICB7.7.5IE Information Notice 79-22 EICB7.7.6Multiple Control System Failures EICB7.7.7Conclusions EICB7.8.1Relief and Safety Valve Position Indication (II.D.3)
EICB7.8.2Auxiliary Feedwater System Initiation and Flow Indication (II.E.1.2)
EICB7.8.3Proportional Integral Derivative Control Modification (II.K.3.9)
EICB7.8.4Proposed Anticipatory Trip Modification (II.K.3.10)
EICB7.8.5Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip (II.K.3.12)
EICB7.9.0Data Communication Systems [SRP TOC]
EICB9.2.1Essential Raw Cooling Water and Raw Cooling Water Systems EICB9.2.2Component Cooling System (Reactor Auxiliaries Cooling Water System)
EICB9.2.5Ultimate Heat Sink EICB9.3.1Compressed Air System EICB9.3.2Process Sampling System EICB9.3.4Chemical and Volume Control System EICB9.4.1Control Room Area Ventilation System EICB9.4.5Engineered Safety Features Ventilation System EICB9.5.2Communication Systems EICB10.3.0Main Steam Supply System EICB10.4.2Main Condenser Evacuation System EICB10.4.4Turbine Bypass System EICB10.4.5Condenser Circulating Water System EICB10.4.7Condensate and Feedwater Systems EICB10.4.8Steam Generator Blowdown System EICB10.4.9Auxiliary Feedwater System EICBBranch has lead responsibility for Items in bold.Page B-6 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch11.5.0Process and Effluent Radiological Monitoring and Sampling Systems EICB23.2.11Instrument Lines EICB2.4.1IntroductionEMCB2.4.2Hydrologic DescriptionEMCB2.4.3Flood PotentialEMCB2.4.4Local Intense Precipitation in Plant AreaEMCB2.4.5Roof DrainageEMCB2.4.6Ultimate Heat SinkEMCB2.4.7GroundwaterEMCB2.4.8Design Basis for Subsurface Hydrostatic LoadingEMCB2.4.9Transport of Liquid ReleasesEMCB2.4.10Flooding Protection Requirements and Technical SpecificationsEMCB2.5.1GeologyEMCB2.5.2SeismologyEMCB2.5.3Surface FaultingEMCB2.5.4Stability of Subsurface Materials and FoundationsEMCB2.5.5Stability of SlopesEMCB2.5.6Embankments and DamsEMCB3.0.0Design of Structures, Components, Equipment, and SystemsEMCB3.1.1Conformance With General Design CriteriaEMCB3.1.2Conformance With Industry Codes and StandardsEMCB3.2.1Seismic QualificationEMCB3.2.2System Quality Group ClassificationEMCB3.3.1Wind LoadingEMCB3.3.2Tornado LoadingEMCB3.4.1Flood ProtectionEMCB3.5.1Missile Selection and DescriptionEMCB3.5.3Barrier Design ProceduresEMCB3.6.2Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of EMCBBranch has lead responsibility for Items in bold.Page B-7 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch3.7.1Seismic InputEMCB3.7.2Seismic AnalysisEMCB3.7.3Seismic Subsystem AnalysisEMCB3.7.4Seismic InstrumentationEMCB3.8.1Steel ContainmentEMCB3.8.2Concrete and Structural Steel Internal StructuresEMCB3.8.3Other Seismic Category I StructuresEMCB3.8.4FoundationsEMCB3.9.1Special Topics for Mechanical ComponentsEMCB3.9.2Dynamic Testing and Analysis of Systems, Components, and EquipmentEMCB3.9.3ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support StructuresEMCB3.9.4Control Rod Drive SystemsEMCB3.9.5Reactor Pressure Vessel InternalsEMCB3.10.0Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical EquipmentEMCB3.11.0Environmental Qualification of Mechanical and Electrical EquipmentEMCB5.2.1Compliance With Codes and Code CasesEMCB11.3.0Gaseous Waste ManagementEMCB23.2.2Cable Tray and Tray SupportsEMCB23.2.4Electrical Conduit and Conduit SupportEMCB23.2.6Equipment Seismic QualificationEMCB23.2.8Hanger and Analysis Update ProgramEMCB23.2.9Heat Code TraceabilityEMCB23.2.10Heating, Ventilation, and Air-Conditioning Duct and Duct SupportsEMCB23.2.11Instrument LinesEMCB23.2.16Seismic AnalysisEMCB23.3.1Concrete Quality ProgramEMCB23.3.6Mechanical Equipment QualificationEMCB23.3.10Soil LiquefactionEMCB3.1.1Conformance With General Design CriteriaEQVBBranch has lead responsibility for Items in bold.Page B-8 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch3.1.2Conformance With Industry Codes and StandardsEQVB13.4.0Review and AuditEQVB14.0.0Initial Test ProgramEQVB17.1.0GeneralEQVB17.2.0OrganizationEQVB17.3.0Quality Assurance ProgramEQVB17.4.0ConclusionsEQVB23.2.3Design Baseline and Verification ProgramEQVB23.2.13QA RecordsEQVB23.2.14Q-ListEQVB23.2.15Replacement Items Program (Piece Parts)EQVB23.2.17Vendor Information ProgramEQVB23.3.11Use-as-is CAQsEQVB23.4.2Quality Verification ProcessEQVB9.5.1Fire Protection IOLB13.1.1Management and Technical Organization IOLB13.1.2Corporate Organization and Technical Support IOLB13.1.3Plant Staff Organization IOLB13.2.1Licensed Operator Training Program IOLB13.2.2Training for Nonlicensed Personnel IOLB13.5.1Administrative Procedures IOLB13.5.2Operating and Maintenance Procedures IOLB13.5.3NUREG-0737 Items IOLB14.0.0Initial Test Program IOLB18.0.0Control Room Design Review IOLB18.1.0General IOLB18.2.0Conclusions IOLB23.2.12Prestart Test Program IOLB23.3.3Detailed Control Room Design Review IOLBBranch has lead responsibility for Items in bold.Page B-9 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch23.5.1Introduction IOLB23.5.2Organizational and Management Improvements IOLB23.5.3Conclusions IOLB23.6.0Operational Readiness IOLB6.5.3Fission Product Control System IRIB9.3.2Process Sampling System IRIB11.1.0Summary Description IRIB11.2.0Liquid Waste Management IRIB11.3.0Gaseous Waste Management IRIB11.4.0Solid Waste Management System IRIB11.5.0Process and Effluent Radiological Monitoring and Sampling Systems IRIB12.1.0General IRIB12.2.0Ensuring that Occupational Radiation Doses Are As Low As Reasonably Achievable IRIB12.3.0Radiation Sources IRIB12.4.0Radiation Protection Design Features IRIB12.5.0Dose Assessment IRIB12.6.0Health Physics Program IRIB12.7.1Plant Shielding (II.B.2)
IRIB12.7.2High Range Incontainment Monitor (II.F.1(3))
IRIB12.7.3Inplant Radioiodine Monitor (III.D.3.3)
IRIB23.3.9Radiation Monitoring System IRIB16.0.0Technical Specifications ITSB13.3.1Introduction NSIR13.3.2Evaluation of the Emergency Plan NSIR13.3.3Conclusions NSIR13.6.0Physical Security Plan NSIR20.0.0Common Defense and Security NSIR20.0.0Common Defense and SecurityPFPB21.0.0Financial QualificationsPFPBBranch has lead responsibility for Items in bold.Page B-10 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch22.0.0Financial Protection and Indemnity RequirementsPFPB22.1.0GeneralPFPB22.2.0Preoperational Storage of Nuclear FuelPFPB22.3.0Operating LicensesPFPB3.4.1Flood ProtectionSBPB3.5.1Missile Selection and DescriptionSBPB3.5.2Structures, Systems, and Components To Be Protected From Externally Generated MissilesSBPB3.6.1Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside ContainmentSBPB5.2.5Reactor Coolant Pressure Boundary Leakage DetectionSBPB9.1.1New Fuel StorageSBPB9.1.2Spent Fuel StorageSBPB9.1.3Spent Fuel Pool Cooling and Cleanup SystemSBPB9.1.4Fuel Handling SystemSBPB9.2.1Essential Raw Cooling Water and Raw Cooling Water SystemsSBPB9.2.2Component Cooling System (Reactor Auxiliaries Cooling Water System)SBPB9.2.4Potable and Sanitary Water SystemsSBPB9.2.5Ultimate Heat SinkSBPB9.2.6Condensate Storage FacilitiesSBPB9.3.1Compressed Air SystemSBPB9.3.2Process Sampling SystemSBPB9.3.3Equipment and Floor Drainage SystemSBPB9.3.4Chemical and Volume Control SystemSBPB9.5.4Emergency Diesel Engine Fuel Oil Storage and Transfer SystemSBPB9.5.5Emergency Diesel Engine Cooling Water SystemSBPB9.5.6Emergency Diesel Engine Starting SystemsSBPB9.5.7Emergency Diesel Engine Lubricating Oil SystemSBPB9.5.8Emergency Diesel Engine Combustion Air Intake and Exhaust SystemSBPB10.1.0Summary DescriptionSBPB10.2.0Turbine GeneratorSBPBBranch has lead responsibility for Items in bold.Page B-11 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch10.2.1Turbine Generator DesignSBPB10.2.2Turbine Disc IntegritySBPB10.3.0Main Steam Supply SystemSBPB10.3.1Main Steam Supply System (up to and including the Main Steam Isolation Valves)SBPB10.3.2Main Steam Supply SystemSBPB10.4.1Main CondenserSBPB10.4.2Main Condenser Evacuation SystemSBPB10.4.3Turbine Gland Sealing SystemSBPB10.4.4Turbine Bypass SystemSBPB10.4.5Condenser Circulating Water SystemSBPB10.4.7Condensate and Feedwater SystemsSBPB10.4.9Auxiliary Feedwater SystemSBPB11.2.0Liquid Waste ManagementSBPB11.3.0Gaseous Waste ManagementSBPB11.4.0Solid Waste Management SystemSBPB11.5.0Process and Effluent Radiological Monitoring and Sampling SystemsSBPB23.3.8Moderate Energy Line Break FloodingSBPB6.2.1Containment Functional DesignSCVB6.2.2Containment Heat Removal SystemsSCVB6.2.3Secondary Containment Functional DesignSCVB6.2.4Containment Isolation SystemSCVB6.2.5Combustible Gas Control SystemsSCVB6.2.6Containment Leakage TestingSCVB6.4.0Control Room HabitabilitySCVB6.5.1ESF Atmosphere Cleanup SystemsSCVB6.5.2Fission Product Cleanup SystemSCVB6.5.3Fission Product Control SystemSCVB6.5.4Ice Condenser as a Fission Product Control SystemSCVB9.4.1Control Room Area Ventilation SystemSCVBBranch has lead responsibility for Items in bold.Page B-12 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch9.4.2Fuel Handling Area Ventilation SystemSCVB9.4.3Auxiliary and Radwates Area Ventilation SystemSCVB9.4.4Turbine Building Area Ventilation SystemSCVB9.4.5Engineered Safety Features Ventilation SystemSCVB11.3.0Gaseous Waste ManagementSCVB23.3.2Containment CoolingSCVB4.2.1DescriptionSNPB4.2.2Thermal PerformanceSNPB4.2.3Mechanical PerformanceSNPB4.2.4SurveillanceSNPB4.2.5Fuel Design ConclusionsSNPB4.3.1Design BasisSNPB4.3.2Design DescriptionSNPB4.3.3Analytical MethodsSNPB4.3.4Summary of Evaluation FindingsSNPB4.4.2Design BasesSNPB4.6.0Functional Design of Reactivity Control SystemsSNPB5.2.1Compliance With Codes and Code CasesSNPB15.3.3Feedwater System Pipe BreakSNPB15.3.4Reactor Coolant Pump Rotor SeizureSNPB15.3.5Reactor Coolant Pump Shaft BreakSNPB15.4.0Radiological Consequences of AccidentsSNPB15.4.1Loss-of-Coolant AccidentSNPB15.4.2Main Steamline Break Outside of ContainmentSNPB3.0.0Design of Structures, Components, Equipment, and SystemsSRXB3.1.1Conformance With General Design CriteriaSRXB3.1.2Conformance With Industry Codes and StandardsSRXB4.4.1Perfomance in Safety CriteriaSRXB4.4.2Design BasesSRXBBranch has lead responsibility for Items in bold.Page B-13 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch4.4.3Thermal-Hydraulic Design MethodologySRXB4.4.4Operating AbnormalitiesSRXB4.4.5Loose Parts Monitoring SystemSRXB4.4.6Thermal-Hydraulic ComparisonSRXB4.4.7N-1 Loop OperationSRXB4.4.8Instrumentation for Inadequate Core Cooling Detection (II.F.2)SRXB4.4.9Summary and ConclusionSRXB5.2.2Overpressure ProtectionSRXB5.2.4RCS Pressure Boundary Inservice Inspection and TestingSRXB5.4.3Residual Heat Removal SystemSRXB5.4.4Pressurizer Relief TankSRXB5.4.5Reactor Coolant System Vents (II.B.1)SRXB6.3.1System DesignSRXB6.3.2EvaluationSRXB6.3.3TestingSRXB6.3.4Performance EvaluationSRXB6.3.5ConclusionsSRXB9.3.2Process Sampling SystemSRXB15.1.0General DiscussionSRXB15.2.0Normal Operation and Anticipated TransientsSRXB15.2.1Loss of Cooling TransientsSRXB15.2.2Increased Cooling TransientsSRXB15.2.3Change in Coolant Inventory TransientsSRXB15.2.4Reactivity and Power Distribution AnomaliesSRXB15.2.5ConclusionsSRXB15.3.0Limiting AccidentsSRXB15.3.1Loss-of-Coolant AccidentSRXB15.3.2Steamline BreakSRXB15.3.6Anticipated Transients Without ScramSRXBBranch has lead responsibility for Items in bold.Page B-14 of 15 Appendix BWatts Bar Nuclear Plant Unit 2Safety Evaluation Review ResponsibilitiesSERTitleBranch15.3.7ConclusionsSRXB15.4.0Radiological Consequences of AccidentsSRXB15.4.1Loss-of-Coolant AccidentSRXB15.4.3Steam Generator Tube RuptureSRXB15.4.4Control Rod Ejection AccidentSRXB15.4.5Fuel-Handling AccidentSRXB15.4.6Failure of Small Line Carrying Coolant Outside ContainmentSRXB15.4.7Postulated Radioactive Releases as a Result of Liquid Tank FailuresSRXB15.5.1Thermal Mechanical Report (II.K.2.13)SRXB15.5.2Voiding in the Reactor Coolant System During Transients (II.K.2.17)SRXB15.5.3Installation and Testing of Automatic Power-Operated Relief Valve Isolation System (II.K.3.1), Report on SRXB15.5.4Automatic Trip of Reactor Coolant Pumps (II.K.3.5)SRXB15.5.5Small-Break LOCA Methods (II.K.3.30) and Plant-Specific Calculations (II.K.3.31)SRXB15.6.0Relative Risk of Low Power OperationSRXBBranch has lead responsibility for Items in bold.Page B-15 of 15