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 SiteQuarterSignificanceCornerstoneCross cutting aspectViolation ofTitleSystem
05000461/FIN-2018050-02Clinton2018Q2GreenMitigating SystemsH.1210 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure to Promptly Identifya Condition Adverse to Quality
05000315/FIN-2018002-04Cook2018Q2GreenMitigating Systems
Public Radiation Safety
10 CFR 20.1501Licensee-Identified Violation
05000458/FIN-2018002-01River Bend2018Q2Severity level IVNo Cornerstone10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure to Correct Inadequate Technical Specification Pressure Temperature Curves
05000348/FIN-2018002-01Farley2018Q2GreenMitigating SystemsH.1Technical Specification - ProceduresHigh vibrations on the 1B Charging pump
05000458/FIN-2018001-01River Bend2018Q1GreenOccupational Radiation SafetyTechnical SpecificationFailure to Implement Procedure for Storage of Material in the Pools
05000327/FIN-2018001-01Sequoyah2018Q1GreenMitigating SystemsTechnical SpecificationEssential Raw Cooling Water Pumps Inoperable due to Frozen Motor Bearing Cooling Lines
05000313/FIN-2018001-03Arkansas Nuclear2018Q1GreenOccupational Radiation Safety10 CFR 20Licensee-Identified Violation
05000424/FIN-2018410-03Vogtle2018Q1GreenPhysical Protection10 CFR 73Security
05000416/FIN-2018001-03Grand Gulf2018Q1GreenMitigating SystemsTechnical SpecificationInadequate Procedural Guidance Which Resulted in Control Room Air Conditioning InoperabilityService water
05000354/FIN-2018001-02Hope Creek2018Q1Mitigating SystemsConcern Regarding As-Found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable Limit
05000269/FIN-2018013-01Oconee2018Q1TBDInitiating Events10 CFR 50 Appendix B Criterion III, Design ControlFailure to Translate Design and Licensing Basis Requirements and Verify Adequate DesignService water
05000395/FIN-2018010-02Summer2018Q1GreenBarrier Integrity10 CFR 50 Appendix B Criterion III, Design ControlFailure to Verify the Seismic Qualification of Valcor Solenoid Operated Valve XVX06050A
05000317/FIN-2018001-01Calvert Cliffs2018Q1GreenOccupational Radiation Safety10 CFR 20
10 CFR 20.1501
10 CFR 20.1601
Failure to Conduct Adequate Radiation Surveys and Evaluate Potential Radiological Hazards
05000266/FIN-2018001-04Point Beach2018Q1Severity level Enforcement DiscretionMitigating SystemsTechnical Specification - ProceduresEnforcement Action: EA18030: Unanalyzed Condition for Tornado Generated MissilesMain Steam Isolation Valve
Auxiliary Feedwater
Main Steam Safety Valve
05000266/FIN-2018001-03Point Beach2018Q1GreenInitiating Events10 CFR 50.59, Changes, Tests and ExperimentsInadequate Basis for Deletion of TRM 3.4.3 Primary System Integrity Requirements
05000324/FIN-2018001-01Brunswick2018Q1GreenBarrier IntegrityTechnical Specification - ProceduresInadequate Instruction to Perform Inspections on Emergency Ventilation DampersHVAC
Control Room Emergency Ventilation
05000265/FIN-2018001-02Quad Cities2018Q1GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Failure to Establish Design Standard for Unit 2 Residual Heat Removal Service Water PumpsResidual Heat Removal Service Water
05000321/FIN-2018001-02Hatch2018Q1GreenMitigating SystemsTechnical SpecificationLicensee-Identified Violation
05000400/FIN-2018410-01Harris2018Q1GreenPhysical Protection10 CFR 73Security
05000461/FIN-2018001-01Clinton2018Q1GreenMitigating Systems10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsFailure to Follow Procedure Results in Unplanned Reactor Core Isolation Cooling UnavailabilityReactor Core Isolation Cooling
05000499/FIN-2018001-02South Texas2018Q1GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure to Promptly Identify and Correct a Condition Adverse to Quality Associated with Reactor Containment Fan Coolers
05000255/FIN-2018010-01Palisades2018Q1GreenInitiating Events
Mitigating Systems
10 CFR 50.55aLicensee-Identified Violation
05000416/FIN-2017011-01Grand Gulf2018Q1GreenMitigating SystemsPendingFailure to Categorize Condition Reports for Significant Conditions Adverse to Quality as Required by Procedures
05000445/FIN-2018001-04Comanche Peak2018Q1GreenInitiating EventsTechnical SpecificationInadequate Maintenance Procedure for Feedwater ValvesFeedwater
05000321/FIN-2018001-01Hatch2018Q1GreenPr Safety10 CFR 71Failure to comply with Type B shipping container Certificate of Compliance (CoC) requirements.
05000458/FIN-2018001-02River Bend2018Q1GreenInitiating EventsInstallation of an Incorrectly Specified Relay Causes Plant Transient and Reactor ScramFeedwater
05000390/FIN-2018010-01Watts Bar2018Q1Mitigating SystemsPendingPotential Failure to Request NRC Approval to Increase the OPT and OTT Response TimesReactor Coolant System
Feedwater
Reactor Protection System
05000498/FIN-2018001-03South Texas2018Q1Severity level IVMitigating SystemsLicense Condition - Fire ProtectionLicensee-Identified Violation
05000335/FIN-2018411-01Saint Lucie2018Q1Severity level Enforcement DiscretionPhysical Protection10 CFR 73Security
05000395/FIN-2018001-01Summer2018Q1GreenInitiating Events10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance At Nuclear Power Plants
10 CFR 50.65(a)(4)
Failure to Perform an Adequate Risk Assessment With Consequent Reactor Trip
05000255/FIN-2018001-02Palisades2018Q1Severity level Enforcement DiscretionMitigating SystemsTechnical SpecificationLicensee Implementation of Enforcement Guidance Memorandum 15002, Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance
05000269/FIN-2018013-02Oconee2018Q1TBDNo Cornerstone10 CFR 50.59, Changes, Tests and ExperimentsFailure to Submit for License Review andObtain a License Amendment for a Modification
05000395/FIN-2018010-04Summer2018Q1Mitigating SystemsUnjustified Qualified Life for ASCO Valves
05000272/FIN-2018001-01Salem2018Q1GreenMitigating SystemsImplementing Procedures for Beyond Design Basis FLEX Mitigating Strategies Not Followed
05000254/FIN-2018001-04Quad Cities2018Q1Severity level Enforcement DiscretionMitigating SystemsTechnical SpecificationEnforcement Action: EA18021: EDG Non-conformance for Tornado Missiles (EGM 15002)Emergency Diesel Generator
05000296/FIN-2018001-04Browns Ferry2018Q1GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing PlantsInadequate Configuration Control of High Pressure Coolant Injection (HPCI)ValveDesign IssuesHigh Pressure Coolant Injection
05000413/FIN-2018001-01Catawba2018Q1GreenMitigating Systems10 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to Ensure that Conditions Adverse toQuality Managed Outside of the Corrective Action Program are Corrected
05000254/FIN-2018001-03Quad Cities2018Q1GreenInitiating EventsTechnical SpecificationHalf Scram Due to Low Voltage on 24/48 Vdc SystemReactor Protection System
05000334/FIN-2018001-02Beaver Valley2018Q1GreenPublic Radiation Safety
Pr Safety
Technical SpecificationLicensee-Identified Violation
05000354/FIN-2018410-01Hope Creek2018Q1GreenPhysical Protection10 CFR 73Security
05000461/FIN-2018001-02Clinton2018Q1GreenInitiating EventsFailure to Identify a Single Point Vulnerability Results in Manual Reactor ScramFeedwater
05000364/FIN-2018001-02Farley2018Q1Severity level Enforcement DiscretionMitigating SystemsTechnical SpecificationEnforcement Action (EA)-18-025:Unit 2 Main Steam Safety Valve (MSSV) Lift Pressure Outside of Technical Specification LimitsSteam Generator
Main Steam Safety Valve
05000387/FIN-2018010-01Susquehanna2018Q1GreenBarrier Integrity10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power PlantsLicensee-Identified ViolationPrimary containment
05000528/FIN-2018012-01Palo Verde2018Q1GreenMitigating SystemsFailure to provide adequate guidance to personnel to assure degraded or deficient emergency lighting required for post-fire safe shutdown was corrected in a timely manner
05000416/FIN-2017011-05Grand Gulf2018Q1GreenBarrier Integrity10 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to Correct Control Room Boundary Door Resulted in Loss of Safety FunctionStandby Gas Treatment System
05000259/FIN-2018001-01Browns Ferry2018Q1GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing PlantsInadequate Post-Maintenance Testing of 4kV Breaker Stationary Switches
05000255/FIN-2018001-03Palisades2018Q1GreenMitigating SystemsTechnical SpecificationLicensee-Identified ViolationSteam Generator
05000219/FIN-2018001-01Oyster Creek2018Q1Severity level IVNo Cornerstone10 CFR 50.73
10 CFR 50.73(a)(1), Submit an LER
Technical Specification
Untimely Licensee Event Report for Reportable Conditions Associated with the No. 2 Emergency Diesel GeneratorEmergency Diesel Generator
05000390/FIN-2018010-02Watts Bar2018Q1Mitigating SystemsPendingPotential Failure to Perform a 50.59 Evaluation for Auxiliary Building and Containment Isolation
05000298/FIN-2018010-01Cooper2018Q1GreenEmergency PreparednessFailure to Maintain Satellite Phones in Locations That Provide Reasonable Assurance They Will Remain Available Following All Beyond Design Basis External Events
05000331/FIN-2018411-01Duane Arnold2018Q1GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000353/FIN-2018001-01Limerick2018Q1GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
Technical Specification
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure of Emergency Diesel Generator Lube Oil Pipe Nipple FittingEmergency Diesel Generator
05000259/FIN-2018001-02Browns Ferry2018Q1GreenOccupational Radiation SafetyTechnical SpecificationUnauthorized Entry into a High Radiation Area(HRAResidual Heat Removal
05000397/FIN-2018401-02Columbia2018Q1Severity level IVPhysical Protection10 CFR 73Security
05000395/FIN-2018010-06Summer2018Q1Mitigating SystemsPotential Unjustified Activation Energy for Barton Transmitters
05000298/FIN-2018001-01Cooper2018Q1GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Licensee-Identified ViolationEmergency Diesel Generator
05000416/FIN-2018001-05Grand Gulf2018Q1GreenMitigating Systems10 CFR 50.72(b)(3)(v), Loss of Safety FunctionLicensee-Identified ViolationHigh Pressure Core Spray
05000454/FIN-2018010-03Byron2018Q1GreenBarrier Integrity10 CFR 50 Appendix B Criterion III, Design ControlFailure to Verify the Adequacy of the Air Pressure Regulator SetpointValue for Containment Isolation Valves 1(2)RF026
05000289/FIN-2018001-01Three Mile Island2018Q1Severity level Enforcement DiscretionMitigating Systems10 CFR 50 Appendix B Criterion III, Design ControlEnforcement Action (EA)-EA-18-029: Multiple Examples of Nonconforming to Design for Tornado Missile ProtectionSteam Generator
05000440/FIN-2018001-01Perry2018Q1Severity level IVNo Cornerstone10 CFR 50.73Failure to Notify the NRC within 60 Days of a Condition Prohibited by Technical Specifications
05000445/FIN-2018001-05Comanche Peak2018Q1GreenInitiating Events10 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to Correct a Significant Condition Adverse to QualityFeedwater
Auxiliary Feedwater
05000373/FIN-2018001-02LaSalle2018Q1GreenMitigating SystemsTechnical SpecificationFailure to Update Throttle Valve Position in Accordance with Station Procedures
05000364/FIN-2018001-03Farley2018Q1Severity level Enforcement DiscretionMitigating SystemsTechnical SpecificationEnforcement Action (EA)-18-026:Unit 2 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance BandReactor Coolant System
05000272/FIN-2018410-01Salem2018Q1GreenPhysical Protection10 CFR 73Security
05000369/FIN-2018010-01McGuire2018Q1GreenMitigating SystemsFailure to Update Offsite Circuit Operability Limit for Single Busline AlignmentAuxiliary Feedwater
05000289/FIN-2018001-02Three Mile Island2018Q1Severity level Enforcement DiscretionMitigating SystemsTechnical SpecificationEnforcement Action (EA)-18-038: Primary Containment Declared Inoperable Due to Both Airlock Doors Open SimultaneouslyPrimary containment
05000369/FIN-2018010-02McGuire2018Q1GreenMitigating Systems10 CFR 50.71(e)Failure to Update the FSAR With Pertinent Design InformationShutdown Cooling
Residual Heat Removal
05000331/FIN-2018010-01Duane Arnold2018Q1GreenInitiating EventsFailure to have Adequate Pre-Fire Plans
05000250/FIN-2018001-01Turkey Point2018Q1GreenBarrier Integrity10 CFR 50.55aFailure to conduct post maintenance testing in accordance with ASME OM code
05000327/FIN-2018001-03Sequoyah2018Q1GreenMitigating SystemsTechnical SpecificationLicensee-Identified ViolationSecondary containment
Auxiliary Building Gas Treatment System
05000266/FIN-2018001-01Point Beach2018Q1GreenMitigating SystemsFailure to Evaluate and Characterize Fire Protection Pipe Wall DegradationService water
05000390/FIN-2018010-03Watts Bar2018Q1Mitigating SystemsPendingPotential Failure to Maintain Design Requirements of RTDs
05000249/FIN-2018012-01Dresden2018Q1GreenMitigating Systems10 CFR 50 Appendix B Criterion III, Design ControlFailure to Ensure that Thermal Overload Relays are Sized Properly for Throttling Motor Operated Valves
05000335/FIN-2018450-01Saint Lucie2018Q1GreenPhysical Protection10 CFR 73Security
05000400/FIN-2018001-01Harris2018Q1Mitigating SystemsAdequacy of Fire Brigade Response During Fire Dril
05000250/FIN-2018001-02Turkey Point2018Q1GreenOccupational Radiation SafetyTechnical SpecificationFailure of radiation workers to notify Radiation Protection upon a spill of radioactively contaminated water
05000334/FIN-2018403-01Beaver Valley2018Q1GreenPhysical Protection10 CFR 73Security
05000368/FIN-2018001-02Arkansas Nuclear2018Q1GreenMitigating SystemsTechnical Specification - ProceduresFailure to Preplan and Perform Service Water Pre-Screen MaintenanceService water
05000387/FIN-2018001-01Susquehanna2018Q1GreenMitigating SystemsTechnical SpecificationLicensee-Identified ViolationCore Spray
05000266/FIN-2018001-05Point Beach2018Q1GreenMitigating SystemsTechnical SpecificationLicensee-Identified ViolationAuxiliary Feedwater
05000454/FIN-2018010-04Byron2018Q1Mitigating SystemsPendingUse of 10 CFR 50.54(x) for Unit AFW Cross-TieFeedwater
Auxiliary Feedwater
05000354/FIN-2018001-01Hope Creek2018Q1GreenMitigating SystemsImplementing Procedures for Beyond Design Basis FLEX Mitigating Strategies Not Followed
05000282/FIN-2018001-02Prairie Island2018Q1Mitigating SystemsQuestions Regarding the Corrective Action and Aging Management Programs Following the Discovery of 122 DDCLP FOST Vent Piping Degradation
05000327/FIN-2018001-02Sequoyah2018Q1GreenMitigating SystemsTechnical SpecificationImproper Calibration of Reactor Trip Instrumentation Results in a Condition Prohibited by Technical Specifications
05000259/FIN-2018001-03Browns Ferry2018Q1GreenOccupational Radiation SafetyTechnical SpecificationFailure to Implement Controls for Locked High Radiation Area (LHRA) Access
05000387/FIN-2018410-02Susquehanna2018Q1GreenPhysical ProtectionSecurity
05000416/FIN-2018001-02Grand Gulf2018Q1GreenBarrier IntegrityTechnical SpecificationFailure to Follow Procedure when Returning Containment Airlock to Operable Status
05000219/FIN-2018001-02Oyster Creek2018Q1Severity level Enforcement DiscretionMitigating SystemsTechnical Specification - ProceduresEnforcement Action (EA)-18-007: No. 2 Emergency Diesel Generator Ring Lug FailureEmergency Diesel Generator
Reactor Pressure Vessel
05000244/FIN-2018011-01Ginna2018Q1GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XI, Test Control
Potential Preconditioning of Turbine Driven Auxiliary Feedwater Surveillance TestingAuxiliary Feedwater
05000331/FIN-2018010-02Duane Arnold2018Q1GreenMitigating Systems10 CFR 50.48Failure to Include Operator Action in the Plant Operating Procedure
05000390/FIN-2018001-01Watts Bar2018Q1GreenMitigating SystemsTechnical SpecificationMisapplication of Technical Specification Limiting Condition for Operation 3.0.6HVAC
05000289/FIN-2018001-03Three Mile Island2018Q1GreenMitigating Systems10 CFR 50.63, Loss of All Alternating Current PowerLicensee-Identified Violation
05000266/FIN-2018001-02Point Beach2018Q1GreenBarrier Integrity10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Failure to Evaluate Material Acceptability for a Safety-Related Doorstop
05000315/FIN-2018001-01Cook2018Q1GreenMitigating SystemsTechnical Specification - ProceduresFailure of Unit 1 Turbine Driven Auxiliary Feedwater Pump to Reach Rated SpeedAuxiliary Feedwater
05000254/FIN-2018001-01Quad Cities2018Q1Severity level IVNo Cornerstone10 CFR 55.49, Integrity of Examinations and TestsRepeat Use of Written Exams During Licensed Operator Requalification Examinations
05000263/FIN-2018001-02Monticello2018Q1GreenMitigating Systems10 CFR 50.59, Changes, Tests and Experiments
10 CFR 50.90, Application for Amendment of License, Construction Permit, Or Early Site Permit
Technical Specification
Licensee-Identified ViolationReactor Protection System
Main Steam Isolation Valve
05000334/FIN-2018403-03Beaver Valley2018Q1GreenMitigating Systems10 CFR 73Security
05000397/FIN-2018001-01Columbia2018Q1GreenBarrier IntegrityTechnical Specification - ProceduresFailure to Follow Procedure Leads to Loss of Secondary ContainmentSecondary containment
05000443/FIN-2018001-01Seabrook2018Q1GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Licensee-Identified Violation
05000272/FIN-2018007-02Salem2018Q1GreenMitigating Systems10 CFR 50 Appendix R, Appendix R to Part 50-Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979
License Condition - Fire Protection
Section III.G
Section III.L
Licensee-Identified ViolationReactor Coolant System
05000445/FIN-2018001-03Comanche Peak2018Q1GreenMitigating SystemsTechnical SpecificationFailure to Provide an Adequate ProcedureSteam Generator
05000237/FIN-2018001-01Dresden2018Q1Severity level Enforcement DiscretionMitigating SystemsEnforcement Action: EA18016: Unanalyzed Condition for Tornado MissilesEmergency Diesel Generator
05000390/FIN-2017004-02Watts Bar2017Q4GreenBarrier IntegrityH.510 CFR 50.59, Changes, Tests and Experiments
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and Drawings
Inadequate Procedure for Temporary Configuration Changes
05000315/FIN-2017004-04Cook2017Q4GreenInitiating Events
Mitigating Systems
H.1410 CFR 50 Appendix B Criterion III, Design ControlFailure to Verify the Adequacy of the Design for a Temporary Modification
05000382/FIN-2017403-02Waterford2017Q4GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000482/FIN-2017008-01Wolf Creek2017Q4GreenInitiating Events
Mitigating Systems
License ConditionInadequateEvaluation of Spurious Valve Operation
05000354/FIN-2017004-01Hope Creek2017Q4GreenInitiating Events
Mitigating Systems
H.2Scaffold Installed with Insufficient Separation from Safety Related Equipment
05000382/FIN-2017008-03Waterford2017Q4Severity level IVNo Cornerstone10 CFR 50.55aTwo Examples of Failure to Submit and Receive Prior Authorization of Alternatives to ASME OM Code Leak Testing Requirements
05000261/FIN-2017007-02Robinson2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power PlantsFailure to Perform Required O-ring Replacement to Maintain Qualification
05000413/FIN-2017004-03Catawba2017Q4GreenInitiating Events
Mitigating Systems
H.8Technical Specification - ProceduresFailure to Follow Administrative Procedures
05000461/FIN-2017004-03Clinton2017Q4GreenInitiating Events
Mitigating Systems
H.810 CFR 50 Appendix B Criterion II, Quality Assurance ProgramFailure to Identify the Extent of Condition for an Inadequate 10 CFR 50.59 Evaluation
05000390/FIN-2017004-04Watts Bar2017Q4GreenMitigating SystemsTechnical SpecificationLicensee-Identified Violation
05000289/FIN-2017004-01Three Mile Island2017Q4GreenInitiating EventsP.2Failure to correct degraded control rod connections
05000395/FIN-2017004-01Summer2017Q4GreenInitiating Events
Mitigating Systems
H.1
H.1(e)
Failure to Accomplish Station Procedures for Severe Weather
05000266/FIN-2017004-01Point Beach2017Q4GreenInitiating EventsH.3License Condition - Fire ProtectionFailure to Implement Required Provisions of NFPA 805
05000348/FIN-2017009-02Farley2017Q4GreenMitigating SystemsH.810 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to Complete Corrective Action to Preclude Repetition of a Significant Conditions Adverse to Quality
05000461/FIN-2017012-02Clinton2017Q4GreenInitiating EventsH.13Failure to Properly Classify Non-Safety Related Auxiliary Transformers as Operationally Critical Components
05000498/FIN-2017407-02South Texas2017Q4GreenPhysical Protection10 CFR 73Security
05000454/FIN-2017010-04Byron2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Untimely Corrective Action for Secondary Missiles
05000395/FIN-2017007-01Summer2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Failure to Verify the Adequacy of Design for the EFW system when Supplied by SWSteam Generator
Feedwater
Service water
05000280/FIN-2017004-02Surry2017Q4GreenInitiating Events
Mitigating Systems
P.210 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure to Identify a Non-Functional Flood Control Barrier
05000251/FIN-2017004-01Turkey Point2017Q4GreenBarrier IntegrityH.810 CFR 50.55aFailure to Perform an Adequate ASME BPVC Section XI Repair/Replacement Plan for a Code Class 1 and 2 ReplacementReactor Coolant System
05000255/FIN-2017007-02Palisades2017Q4GreenBarrier IntegrityContainment Spray Pipe Support Strap DeficienciesReactor Coolant System
05000456/FIN-2017008-05Braidwood2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Inaccurate Analysis of Record
05000410/FIN-2017004-03Nine Mile Point2017Q4GreenInitiating Events
Mitigating Systems
H.510 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
Technical Specification
10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and Drawings
Inadequate Operability Determination forImpairedInternal Flood Barrier
05000413/FIN-2017004-01Catawba2017Q4GreenPublic Radiation Safety
Pr Safety
H.3Technical Specification - ProceduresInadequate Testing of Fuel Pool Ventilation Radiation Monitors
05000315/FIN-2017004-05Cook2017Q4GreenMitigating Systems10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsLicensee-Identified Violation
05000327/FIN-2017008-01Sequoyah2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power PlantsUnjustified Qualified Life for Target Rock Power-Operated Relief ValvesReactor Coolant System
05000220/FIN-2017004-01Nine Mile Point2017Q4GreenInitiating Events
Mitigating Systems
H.1310 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance At Nuclear Power Plants
Technical Specification
10 CFR 50.65(a)(2)
Main Control Room Annunciators 10 CFR 50.65(a)(2) Demonstration Not Met
05000341/FIN-2017004-02Fermi2017Q4Mitigating SystemsDivision 2 Residual Heat Removal Service Water System Outlet Flow Control Valve Lower Bonnet (Backseat) Bushing FailureService water
Residual Heat Removal Service Water
05000382/FIN-2017403-01Waterford2017Q4GreenPhysical ProtectionP.610 CFR 73Security
05000482/FIN-2017008-02Wolf Creek2017Q4GreenInitiating Events
Mitigating Systems
H.9License ConditionFailure to Provide Adequate Emergency Lighting
05000321/FIN-2017502-01Hatch2017Q4GreenMitigating Systems10 CFR 50.54
10 CFR 50.54(q)
Licensee-Identified Violation
05000298/FIN-2017012-02Cooper2017Q4GreenInitiating EventsH.3Technical Specification - ProceduresInadequate Testing Activities for Emergency Transformer Bus
05000261/FIN-2017007-03Robinson2017Q4GreenMitigating Systems10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power PlantsFailure to Determine Most Severe Containment Spray pH
05000424/FIN-2017004-03Vogtle2017Q4GreenMitigating Systems10 CFR 50.55aLicensee-Identified Violation
05000461/FIN-2017004-04Clinton2017Q4Severity level IVMiscellaneous10 CFR 72Failure to Perform an Evaluation in Accordance with 10 CFR 72.48 for Changes Made to the Time-to-Boil Calculation
05000333/FIN-2017004-03FitzPatrick2017Q4GreenMitigating Systems10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance At Nuclear Power Plants
10 CFR 50.65(a)(4)
Licensee-Identified Violation
05000269/FIN-2017004-01Oconee2017Q4GreenInitiating Events
Mitigating Systems
H.5Technical Specification - ProceduresFailure to Identify Sensitive Equipment During Modification Results in Loss of Safety Function
05000333/FIN-2017004-01FitzPatrick2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Inadequate Design Control for Battery Sizing Calculation
05000247/FIN-2017007-03Indian Point2017Q4GreenMitigating SystemsTechnical Specification - ProceduresLicensee-Identified Violation
05000461/FIN-2017012-03Clinton2017Q4Mitigating SystemsEvaluation of RCE 04082490, Reactor Scram from Trip of 1AP07EJ)Main Condenser
05000327/FIN-2017407-01Sequoyah2017Q4Greater Than GreenPhysical Protection10 CFR 73Security
05000395/FIN-2017007-03Summer2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 21
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure to Identify a CAQ for Power Shield Catalog #609903-T501N
05000282/FIN-2017004-02Prairie Island2017Q4GreenEmergency Preparedness10 CFR 50.47, Emergency Plans
10 CFR 50 Appendix E, Appendix E to Part 50-Emergency Planning and Preparedness for Production and Utilization Facilities
10 CFR 50.54
Technical Specification
10 CFR 50.47(b)(4)
10 CFR 50.54(q)
Licensee-Identified Violation
05000440/FIN-2017008-02Perry2017Q4GreenInitiating Events
Mitigating Systems
H.1210 CFR 50 Appendix B Criterion III, Design ControlInadequate Evaluation of Emergency Closed Cooling System Pipe Support
05000296/FIN-2017004-02Browns Ferry2017Q4GreenInitiating Events
Mitigating Systems
H.1310 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsFailure to Perform an IDO without delay for 3A EDG after Observing Indications of a Degraded ConditionEmergency Diesel Generator
05000255/FIN-2017007-03Palisades2017Q4Mitigating SystemsContainment Dome Truss Analysis
05000443/FIN-2017004-03Seabrook2017Q4GreenInitiating EventsH.5Inadequate Procedure Implementation Results in a Manual Reactor TripSteam Generator
Feedwater
05000395/FIN-2017004-04Summer2017Q4GreenMitigating SystemsTechnical SpecificationLicensee-Identified ViolationFeedwater
05000327/FIN-2017008-04Sequoyah2017Q4No CornerstonePendingPotential Inadequate Determination of Failure Modes for Qualified Life for Foxboro/Weed Instrument
05000272/FIN-2017004-01Salem2017Q4GreenBarrier IntegrityP.110 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Non-conformance with the Containment Thermal Insulation System was not Identified and Corrected
05000341/FIN-2017004-03Fermi2017Q4GreenOccupational Radiation SafetyH.1410 CFR 20.1703Failure to Perform Fit Testing on Self-Contained Breathing Apparatus Respirators
05000338/FIN-2017403-01North Anna2017Q4GreenPhysical ProtectionH.110 CFR 73Security
05000416/FIN-2017014-02Grand Gulf2017Q4Mitigating Systems10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsFailure to Perform Operator RoundsService water
05000440/FIN-2017410-01Perry2017Q4GreenPhysical Protection10 CFR 73Security
05000352/FIN-2017007-01Limerick2017Q4GreenBarrier IntegrityH.610 CFR 50 Appendix B Criterion III, Design ControlFailure to Document Technical Basis for Service Temperature Changes for Limitorque Motor Operated Valve Limit SwitchesHigh Pressure Coolant Injection
Primary containment
05000261/FIN-2017007-04Robinson2017Q4Initiating EventsPendingCrouse-Hinds Qualification and Life Extension
05000263/FIN-2017004-02Monticello2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix R, Appendix R to Part 50-Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979
Section III.G
Licensee-Identified Violation
05000255/FIN-2017004-01Palisades2017Q4GreenBarrier IntegrityH.210 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
Technical Specification
10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and Drawings
Improperly Connected M&TE Leads to Unexpected AFU Fan TripControl Room Emergency Ventilation
05000454/FIN-2017010-05Byron2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Inaccurate Analysis of Record
05000346/FIN-2017004-03Davis Besse2017Q4TBDInitiating Events
Mitigating Systems
H.11Technical Specification
10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and Drawings
Failure to Prescribe Appropriate Work Instructions for an Activity Affecting QualityFeedwater
Auxiliary Feedwater
05000331/FIN-2017004-02Duane Arnold2017Q4Severity level IVMiscellaneous10 CFR 72Failure to Evaluate Site Fire and Explosion Hazards in Accordance with 10 CFR 72.212(b) (6)
05000282/FIN-2017004-01Prairie Island2017Q4GreenOccupational Radiation SafetyTechnical SpecificationLicensee-Identified Violation
05000373/FIN-2017004-02LaSalle2017Q4GreenMitigating SystemsH.510 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsFailure to Establish Brazing Repair Procedures with Appropriate Acceptance Criteria
05000247/FIN-2017007-02Indian Point2017Q4GreenInitiating Events
Mitigating Systems
H.110 CFR 50.54(hh)Failure to Maintain B.5.b Mitigating Strategies
05000335/FIN-2017004-01Saint Lucie2017Q4GreenInitiating Events
Mitigating Systems
H.110 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
Technical Specification
10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and Drawings
Inadequate Reactor System Trip Process for Inoperable Channel Results in Operation in a Condition Prohibited by Technical SpecificationsReactor Protection System
05000315/FIN-2017004-02Cook2017Q4Mitigating SystemsUnit 1 Letdown System Safety Valve Lift During Preparations for CooldownSecondary containment
05000498/FIN-2017407-01South Texas2017Q4GreenPhysical Protection10 CFR 73Security
05000321/FIN-2017004-02Hatch2017Q4GreenBarrier Integrity10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsLack of Requirement for Engineering Evaluation of Scaffolding Near Safety-related Piping
05000440/FIN-2017008-03Perry2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B Criterion III, Design ControlFailure to Verify the Capability to Manually Backwash the Emergency Service WaterStrainer during Loss of Offsite PowerService water
05000425/FIN-2017004-01Vogtle2017Q4GreenInitiating Events
Mitigating Systems
Technical Specification - ProceduresFailure to Implement and Establish Appropriate Work Instructions for PMT of Namco Limit Switch on 2HV-8920
05000382/FIN-2017008-01Waterford2017Q4GreenMitigating SystemsTechnical SpecificationThree examples of Failure to Establish and Maintain Preventive Maintenance Procedures for Safety-Related Electrical Equipment
05000416/FIN-2017007-03Grand Gulf2017Q4GreenInitiating Events
Mitigating Systems
H.5Technical Specification - ProceduresFailure to Establish a Preventive Maintenance Procedure for Safety -Related Equipment
05000282/FIN-2017004-03Prairie Island2017Q4GreenBarrier IntegrityTechnical SpecificationLicensee-Identified Violation
05000461/FIN-2017004-01Clinton2017Q4GreenInitiating EventsH.510 CFR 50.65(a)(4)Reactor Down Power due to Reactor Recirculation Pump Motor Lower Bearing Oil LeakReactor Recirculation Pump
05000410/FIN-2017004-04Nine Mile Point2017Q4GreenInitiating EventsIneffective Correction Action Results in Failure of Instrument Air SystemFeedwater
Reactor Recirculation Pump
05000327/FIN-2017008-05Sequoyah2017Q4No CornerstonePendingPotential Inadequate Justification for Eliminating Preventative Maintenance for ASCO Valves
05000346/FIN-2017004-01Davis Besse2017Q4GreenPublic Radiation Safety
Pr Safety
H.510 CFR 20.1301
10 CFR 50 Appendix I
Technical Specification - Procedures
Failure to Maintain Procedures Associated with Ventilation Air Monitoring Assessment Program
05000353/FIN-2017004-01Limerick2017Q4GreenInitiating Events
Mitigating Systems
H.510 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and Drawings
Unplanned HPCI Inoperability Due to Isolating All Suction Sources During Post-Maintenance Te s t i n gHigh Pressure Coolant Injection
05000454/FIN-2017403-01Byron2017Q4GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000416/FIN-2017014-03Grand Gulf2017Q4Mitigating Systems10 CFR 50.9, Completeness and Accuracy of Information
10 CFR 50 Appendix B Criterion XVII, Control of Purchased Material, Equipment, and Services
Falsification of Operator Rounds Records
05000263/FIN-2017409-01Monticello2017Q4GreenPhysical Protection10 CFR 73Security
05000454/FIN-2017010-02Byron2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Inadequate Blow Out Panel Design Control
05000261/FIN-2017007-05Robinson2017Q4Initiating EventsPendingQuestions Regarding EQDP-0401 Method Used to Determine Activation Energy and Responsibility for Verification
05000287/FIN-2017004-02Oconee2017Q4GreenInitiating EventsH.5Technical Specification - ProceduresFailure to Properly Risk Screen Work Within Two Feet of a Single Point Vulnerability ComponentFeedwater
05000237/FIN-2017004-01Dresden2017Q4GreenBarrier Integrity
Mitigating Systems
H.9Technical Specification - ProceduresFailure to Follow Procedure,Results in Non-Functional Fire Door
05000348/FIN-2017004-03Farley2017Q4GreenInitiating Events
Mitigating Systems
H.12Technical SpecificationFailure to Follow Procedure Resulted in Inoperable TDAFW pumpAuxiliary Feedwater
05000456/FIN-2017008-01Braidwood2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B Criterion III, Design ControlFailure to Prevent Secondary Missiles Following a Postulated HELB
05000391/FIN-2017004-03Watts Bar2017Q4GreenBarrier IntegrityH.510 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure to Promptly Identify a Condition Adverse to Quality for a Boric Acid Leak on 2-SMV-68-548
05000317/FIN-2017004-01Calvert Cliffs2017Q4GreenInitiating Events
Mitigating Systems
P.6License Condition - Fire ProtectionInadequate Assessment of Fire Brigade Performance During an Announced Fire Drill
05000373/FIN-2017004-03LaSalle2017Q4GreenBarrier Integrity10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Primary Containment Structure, Suppression Pool Columns, Downcomer Vent and Downcomer Vent Bracing Did Not Meet Seismic Category I RequirementsReactor Coolant System
Primary containment
05000334/FIN-2017007-01Beaver Valley2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Non -Conservative Differential Pressure Value Used in Low Head Safety Injection Motor -Operated Valve Design AnalysisReactor Coolant System
05000461/FIN-2017011-01Clinton2017Q4WhiteInitiating Events
Mitigating Systems
P.2Technical Specification
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure to Correct an Identified Degraded Condition on the Division 3 Shutdown Service Water PumpService water
Emergency Diesel Generator
High Pressure Core Spray
05000315/FIN-2017004-03Cook2017Q4GreenInitiating Events
Mitigating Systems
H.110 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to Promptly Correct The CAQ by Not Testing the CCW Leak Isolation Valves
05000528/FIN-2017404-01Palo Verde2017Q4GreenPhysical ProtectionH.310 CFR 73Security
05000373/FIN-2017004-01LaSalle2017Q4No CornerstoneComplete versus Truncated Shifts on Proficiency Watches
05000324/FIN-2017004-02Brunswick2017Q4GreenNo CornerstoneLicensee-Identified Violation
05000374/FIN-2017010-01LaSalle2017Q4GreenInitiating Events
Mitigating Systems
Initiating Events, Mitigating Systems
H.8License Condition - Fire ProtectionFailure To Ensure Fire Door Was Engaged And Pinned
05000424/FIN-2017004-02Vogtle2017Q4GreenInitiating Events
Mitigating Systems
H.1Technical Specification - ProceduresFailure to Maintain NEMA Type 4 Qualification for the Nuclear Service Cooling Water PumpsService water
05000382/FIN-2017008-02Waterford2017Q4GreenMitigating SystemsH.11Technical SpecificationFailure to Meet RG 1.9 Emergency Diesel Testing Requirements during Surveillance Test Results in Missed SurveillanceEmergency Diesel Generator
05000416/FIN-2017007-04Grand Gulf2017Q4Severity level IVMitigating Systems10 CFR 50.71(e)Failure to Update the Final Safety Analys is Report
05000321/FIN-2017004-03Hatch2017Q4GreenMitigating SystemsTechnical SpecificationA violation of Technical Specification (TS) 3.4.3 was identified because two of eleven safety relief valves were found to be outside the tolerance allowed by TS Surveillance Requirement (SR) 3.4.3.1 for the opening set-point pressure.
05000461/FIN-2017004-02Clinton2017Q4GreenInitiating EventsH.510 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance At Nuclear Power Plants
10 CFR 50.65(a)(4)
Failure to Assess and Manage Risk Associated with the Performance of Control Rod Time Testing
05000282/FIN-2017004-04Prairie Island2017Q4GreenInitiating EventsH.110 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and Drawings
Licensee-Identified ViolationShutdown Cooling
05000327/FIN-2017008-06Sequoyah2017Q4No CornerstonePotential Unjustified Qualified Life for ASCO Solenoid Operated Valves
05000390/FIN-2017004-01Watts Bar2017Q4Mitigating SystemsMisapplication of Technical Specification Limiting Condition for Operation 3.0.6
05000280/FIN-2017004-01Surry2017Q4GreenInitiating EventsTechnical Specification - ProceduresInadequate Instructions for Corrective Maintenance on Unit 1 C RC Hot Leg Sample ValveReactor Coolant System
05000313/FIN-2017015-01Arkansas Nuclear2017Q4GreenPhysical Protection10 CFR 73Security
05000461/FIN-2017012-01Clinton2017Q4GreenInitiating EventsH.510 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure to Perform a Corrective Action to Prevent Recurrence
05000498/FIN-2017407-03South Texas2017Q4GreenPhysical Protection10 CFR 73Security
05000454/FIN-2017010-03Byron2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to Properly Correct Errors in Design Analysis for Main Steam Line Break in Main Steam Tunnel
05000261/FIN-2017007-07Robinson2017Q4No CornerstonePendingJustification of Activation Energy of ASCO Solenoid Coil Assemblies
05000395/FIN-2017004-02Summer2017Q4GreenInitiating Events
Mitigating Systems
P.310 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Failure to Implement Corrective Actions to Restore Compliance for Previous NRC-identified Green NCV 05000395/2005007-01Feedwater
Service water
05000255/FIN-2017007-01Palisades2017Q4GreenInitiating Events
Mitigating Systems
Failure to Periodically Test the Emergency Diesel Generators Capacity to Start and Accelerate Design Basis Sequenced LoadsEmergency Diesel Generator
05000456/FIN-2017008-04Braidwood2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B Criterion XVI, Corrective ActionUntimely Corrective Action for Secondary Missiles
05000395/FIN-2017004-03Summer2017Q4GreenInitiating Events
Mitigating Systems
P.2Technical SpecificationFailure of an Emergency Feedwater Auto Start Actuation SignalFeedwater
05000324/FIN-2017004-01Brunswick2017Q4GreenInitiating Events
Mitigating Systems
H.8Loss of Emergency 4160V Bus Due to Failure to Implement ProcedureEmergency Diesel Generator
05000373/FIN-2017004-04LaSalle2017Q4GreenInitiating EventsTechnical Specification - ProceduresFailure of Offsite Power Backfeed Procedure to be Appropriate to the Circumstances Caused Unit 1 Scram
05000220/FIN-2017004-05Nine Mile Point2017Q4GreenInitiating Events
Mitigating Systems
10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance At Nuclear Power Plants
10 CFR 50.65(a)(4)
Licensee-Identified ViolationFeedwater
05000413/FIN-2017004-02Catawba2017Q4GreenMitigating Systems10 CFR 50.59, Changes, Tests and ExperimentsFailure to Perform a 10 CFR 50.59 Evaluation for a Change to Engineering Safety Features Actuation Periodic Test.
05000293/FIN-2017403-03Pilgrim2017Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000282/FIN-2017003-04Prairie Island2017Q3GreenMitigating SystemsTechnical SpecificationLicensee-Identified ViolationAuxiliary Feedwater
05000400/FIN-2017003-01Harris2017Q3Severity level IVEmergency Preparedness10 CFR 50.9, Completeness and Accuracy of InformationIncomplete and Inaccurate Emergency Action Level Submittals
05000529/FIN-2017003-03Palo Verde2017Q3GreenInitiating EventsH.12Technical SpecificationFailure to Follow Conduct of Operations ProcedureReactor Coolant System
05000272/FIN-2017007-02Salem2017Q3GreenMitigating SystemsTechnical SpecificationInadequate PM for the EDG Room Ventilation SystemEmergency Diesel Generator
05000387/FIN-2017003-01Susquehanna2017Q3GreenInitiating EventsH.12Failure to Prepare Work Packages with Necessary Detail Results in Automatic Reactor Scram
05000416/FIN-2017012-02Grand Gulf2017Q3GreenPublic Radiation Safety
Pr Safety
P.3Failure to Operate the Gaseous Radwaste System Within Design Specifications
05000461/FIN-2017003-05Clinton2017Q3GreenBarrier IntegrityH.9Technical SpecificationFailure to Establish Secondary Containment Prior to Entering MODE 2Secondary containment
Reactor Water Cleanup
05000278/FIN-2017003-01Peach Bottom2017Q3GreenInitiating Events
Mitigating Systems
Technical Specification - ProceduresInstructions Not Followed for Replacement of HPSW Ventilation Switch BlockService water
05000341/FIN-2017003-02Fermi2017Q3GreenInitiating Events
Mitigating Systems
H.1Technical SpecificationTechnical Specification Allowed Outage Time Exceeded for Electrical Power Distribution Systems Due to Auxiliary Equipment Out of ServiceResidual Heat Removal
05000454/FIN-2017405-01Byron2017Q3GreenPhysical ProtectionH.110 CFR 73Security
05000458/FIN-2017404-01River Bend2017Q3Physical Protection10 CFR 73Licensee-Identified Violation
05000249/FIN-2017003-01Dresden2017Q3Severity level Enforcement DiscretionMitigating SystemsGranted Notice of Enforcement Discretion 173001: LCO 3.1.7 Required Action B.1 per TS 3.1.7, Standby Liquid Control SystemStandby Liquid Control
05000250/FIN-2017003-02Turkey Point2017Q3GreenInitiating EventsH.12Inadequate Operator Fundamentals during Diesel Driven Fire Pump Surveillance Testing
05000313/FIN-2017003-01Arkansas Nuclear2017Q3GreenInitiating Events
Mitigating Systems
H.14Technical SpecificationFailure to Maintain Service Water Train SeparationService water
05000352/FIN-2017003-02Limerick2017Q3GreenInitiating Events
Mitigating Systems
License Condition - Fire ProtectionLicensee-Identified ViolationShutdown Cooling
Spray Pond
05000373/FIN-2017008-01LaSalle2017Q3GreenInitiating Events
Mitigating Systems
H.610 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power PlantsFailure to Correctly Evaluate/Justify Post-Accident Operability Qualification for the Reliance Motor 1(2)VY03C RHR Pumps RoomCooling Fan
05000250/FIN-2017007-01Turkey Point2017Q3GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Inadequate Verification of Electrical Protective Device Selective Coordination
05000280/FIN-2017007-01Surry2017Q3GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Failure to Evaluate Design Maximum Ambient Temperature Effect on Main Steam Valve HouseFeedwater
05000397/FIN-2017003-02Columbia2017Q3Severity level IVMitigating Systems10 CFR 50.72(b)(3)(iv)(A), System ActuationFailure to Report Unplanned Valid Reactor Protection System ActuationReactor Protection System
05000482/FIN-2017003-04Wolf Creek2017Q3GreenInitiating Events
Mitigating Systems
H.1Technical Specification - ProceduresFailure to Verify Equipment or Systems are Capable of Performing Their Intended Design Function Following MaintenanceReactor Coolant System
Emergency Diesel Generator
05000293/FIN-2017007-01Pilgrim2017Q3GreenMitigating Systems10 CFR 50 Appendix B Criterion III, Design ControlFailure to Incorporate the Correct Design Limit for the Condensate Storage Tank Water Temperature
05000266/FIN-2017002-02Point Beach2017Q3GreenMitigating Systems
Initiating Events, Mitigating Systems
10 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to Identify Non-Conforming Conditionsafter Receipt of Anchor Darling Double Disc Gate Valve Related Part 21 Report
05000346/FIN-2017003-05Davis Besse2017Q3Severity level IVOther10 CFR 72Ultrasonic Testing Records to Support Fuel Selection Were Not Being Maintained
05000461/FIN-2017003-01Clinton2017Q3GreenBarrier IntegrityH.6Technical SpecificationMSIV TS Leakage Limits Exceeded Due to Condition Based Maintenance ApproachMain Steam Isolation Valve
05000255/FIN-2017003-04Palisades2017Q3GreenOccupational Radiation SafetyTechnical SpecificationLicensee-Identified Violation
05000336/FIN-2017003-01Millstone2017Q3GreenBarrier IntegrityH.12Technical Specification - Procedures
Pending
Inadequate Procedure Results in Inadvertent Lowering of Spent Fuel Pool Level
05000424/FIN-2017003-01Vogtle2017Q3GreenInitiating Events
Mitigating Systems
H.11Technical Specification - ProceduresFailure to Implement and Establish Appropriate Work Instructions Affecting Safety-Related Chiller
05000440/FIN-2017003-01Perry2017Q3GreenPublic Radiation Safety
Pr Safety
Technical SpecificationLicensee-Identified Violation