Finding

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A finding is a basic result from an NRC Inspection Report. A synonymous term is "violation" but the subtle difference between the two is that violations are for a specific regulation and a finding describes other types of deviations. The term finding may be used to describe all issues counted by the inspection report greater than minor.

Significance:

NCV violation
green white yellow red
Traditional Enforcement Violation
SLI SLII SLIII SLIV

Category:Finding

finding list

by Region

since: 1 April 2019

Region 1 0 [Region 1 Findings] [RSS]
Region 2 0 [Region 2 Findings] [RSS]
Region 3 0 [Region 3 Findings] [RSS]
Region 4 0 [Region 4 Findings] [RSS]

by site

3 year

Site#LicCompanyFinding listsRSSCCA matrix
Aerotest 0 0 [Aerotest findings] [RSS] (CCA Matrix)
Armed Forces Radiobiology Research Institute 0 0 Department of Defense [Armed Forces Radiobiology Research Institute findings] [RSS] (CCA Matrix)
Calvert Cliffs 3 0 Exelon [Calvert Cliffs findings] [RSS] (CCA Matrix)
Chattanooga 0 0 Tennessee Valley Authority [Chattanooga findings] [RSS] (CCA Matrix)
Davis Besse 15 1 Cleveland Electric [Davis Besse findings] [RSS] (CCA Matrix)
Dresden 10 1 Exelon [Dresden findings] [RSS] (CCA Matrix)
Entergy Headquarters 0 0 Entergy [Entergy Headquarters findings] [RSS] (CCA Matrix)
FitzPatrick 8 2 Exelon [FitzPatrick findings] [RSS] (CCA Matrix)
Fort Calhoun 0 0 Omaha Public Power District [Fort Calhoun findings] [RSS] (CCA Matrix)
Idaho State University 0 0 [Idaho State University findings] [RSS] (CCA Matrix)
Kennett Square 0 0 Exelon [Kennett Square findings] [RSS] (CCA Matrix)
La Crosse 0 0 Dairyland Power Cooperative [La Crosse findings] [RSS] (CCA Matrix)
LaSalle 29 3 Exelon [LaSalle findings] [RSS] (CCA Matrix)
MIT Nuclear Research Reactor 0 0 [MIT Nuclear Research Reactor findings] [RSS] (CCA Matrix)
McGuire 14 1 Duke Energy [McGuire findings] [RSS] (CCA Matrix)
Monticello 9 7 Xcel Energy [Monticello findings] [RSS] (CCA Matrix)
NRC Region 1 0 0 NRC [NRC Region 1 findings] [RSS] (CCA Matrix)
NRC Region 4 0 0 NRC [NRC Region 4 findings] [RSS] (CCA Matrix)
North Carolina State University 0 0 [North Carolina State University findings] [RSS] (CCA Matrix)
Ohio State University 0 0 [Ohio State University findings] [RSS] (CCA Matrix)
Pennsylvania State University 0 0 Pennsylvania State University [Pennsylvania State University findings] [RSS] (CCA Matrix)
Portsmouth Gaseous Diffusion Plant 0 0 [Portsmouth Gaseous Diffusion Plant findings] [RSS] (CCA Matrix)
Purdue University 0 0 [Purdue University findings] [RSS] (CCA Matrix)
Rancho Seco 0 0 Sacramento Municipal Utility District [Rancho Seco findings] [RSS] (CCA Matrix)
Reed College 0 0 Reed Research Reactor [Reed College findings] [RSS] (CCA Matrix)
Seabrook 10 1 NextEra Energy [Seabrook findings] [RSS] (CCA Matrix)
Shoreham 0 0 Long Island Lighting Company [Shoreham findings] [RSS] (CCA Matrix)
Texas A&M University 0 0 [Texas A&M University findings] [RSS] (CCA Matrix)
Turkey Point 30 0 NextEra Energy [Turkey Point findings] [RSS] (CCA Matrix)
University of Illinois 0 0 [University of Illinois findings] [RSS] (CCA Matrix)
University of Missouri-Columbia 0 0 [University of Missouri-Columbia findings] [RSS] (CCA Matrix)
University of Missouri-Rolla 0 0 [University of Missouri-Rolla findings] [RSS] (CCA Matrix)
University of Texas at Austin 0 0 [University of Texas at Austin findings] [RSS] (CCA Matrix)
University of Wisconsin 0 0 [University of Wisconsin findings] [RSS] (CCA Matrix)
Vallecitos 0 0 GEH Hitachi [Vallecitos findings] [RSS] (CCA Matrix)
Zion 0 0 Exelon [Zion findings] [RSS] (CCA Matrix)

Traditional Enforcement by site

1 year

Site#CompanyFinding lists
Aerotest 0 [Aerotest findings]
Armed Forces Radiobiology Research Institute 0 Department of Defense [Armed Forces Radiobiology Research Institute findings]
Calvert Cliffs 0 Exelon [Calvert Cliffs findings]
Chattanooga 0 Tennessee Valley Authority [Chattanooga findings]
Davis Besse 0 Cleveland Electric [Davis Besse findings]
Dresden 0 Exelon [Dresden findings]
Entergy Headquarters 0 Entergy [Entergy Headquarters findings]
FitzPatrick 0 Exelon [FitzPatrick findings]
Fort Calhoun 0 Omaha Public Power District [Fort Calhoun findings]
Idaho State University 0 [Idaho State University findings]
Kennett Square 0 Exelon [Kennett Square findings]
La Crosse 0 Dairyland Power Cooperative [La Crosse findings]
LaSalle 0 Exelon [LaSalle findings]
MIT Nuclear Research Reactor 0 [MIT Nuclear Research Reactor findings]
McGuire 0 Duke Energy [McGuire findings]
Monticello 0 Xcel Energy [Monticello findings]
NRC Region 1 0 NRC [NRC Region 1 findings]
NRC Region 4 0 NRC [NRC Region 4 findings]
North Carolina State University 0 [North Carolina State University findings]
Ohio State University 0 [Ohio State University findings]
Pennsylvania State University 0 Pennsylvania State University [Pennsylvania State University findings]
Portsmouth Gaseous Diffusion Plant 0 [Portsmouth Gaseous Diffusion Plant findings]
Purdue University 0 [Purdue University findings]
Rancho Seco 0 Sacramento Municipal Utility District [Rancho Seco findings]
Reed College 0 Reed Research Reactor [Reed College findings]
Seabrook 0 NextEra Energy [Seabrook findings]
Shoreham 0 Long Island Lighting Company [Shoreham findings]
Texas A&M University 0 [Texas A&M University findings]
Turkey Point 0 NextEra Energy [Turkey Point findings]
University of Illinois 0 [University of Illinois findings]
University of Missouri-Columbia 0 [University of Missouri-Columbia findings]
University of Missouri-Rolla 0 [University of Missouri-Rolla findings]
University of Texas at Austin 0 [University of Texas at Austin findings]
University of Wisconsin 0 [University of Wisconsin findings]
Vallecitos 0 GEH Hitachi [Vallecitos findings]
Zion 0 Exelon [Zion findings]

By reactor type

since: 1 April 2019

Type#listfeed
B&W-L-LP (1) 0 [B&W-L-LP events] [RSS]
B&W-R-LP (1) 0 [B&W-R-LP events] [RSS]
CANDU (4) 0 [CANDU events] [RSS]
CANDU-6 (1) 0 [CANDU-6 events] [RSS]
CE (2) 0 [CE events] [RSS]
GE-1 (1) 0 [GE-1 events] [RSS]
GE-2 (0) 0 [GE-2 events] [RSS]
GE-3 (2) 0 [GE-3 events] [RSS]
GE-4 (1) 0 [GE-4 events] [RSS]
GE-5 (2) 0 [GE-5 events] [RSS]
GE-6 (0) 0 [GE-6 events] [RSS]
Pool (2) 0 [Pool events] [RSS]
TRIGA (5) 0 [TRIGA events] [RSS]
W-AP1000 (0) 0 [W-AP1000 events] [RSS]
Westinghouse PWR 2-Loop (0) 0 [Westinghouse PWR 2-Loop events] [RSS]
Westinghouse PWR 3-Loop (1) 0 [Westinghouse PWR 3-Loop events] [RSS]
Westinghouse PWR 4-Loop (3) 0 [Westinghouse PWR 4-Loop events] [RSS]

List

 SiteQuarterSignificanceCornerstoneCross cutting aspectViolation ofTitleSystem
05000336/FIN-2018011-01Millstone2018Q3Mitigating SystemsPendingReviews of Incoming Industry Operation Experience Not Completed
05000251/FIN-2018003-02Turkey Point2018Q3GreenMitigating Systems10 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
Inoperable Auxiliary Feedwater Steam Supply Flow PathSteam Generator
Auxiliary Feedwater
05000266/FIN-2018003-01Point Beach2018Q3Severity level IVNo Cornerstone10 CFR 72Failure to Perform Evaluations to Ensure that the Fabrication of Dry Cask Storage Systems Meets the Requirements of the Loading Certificate of Compliance
05000334/FIN-2018411-02Beaver Valley2018Q3GreenPhysical Protection10 CFR 73Security
05000373/FIN-2018003-03LaSalle2018Q3GreenMitigating Systems10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance At Nuclear Power Plants
10 CFR 50.65(a)(1)
Failure to Establish Goals to Monitor Steam Tunnel Check Dampers
05000445/FIN-2018010-02Comanche Peak2018Q3GreenMitigating Systems10 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
Failure to Provide Procedural Guidance for the Failure of a Component Cooling Water Surge Tank Makeup Valve
05000269/FIN-2018003-01Oconee2018Q3Severity level IVEmergency Preparedness10 CFR 50.54
10 CFR 50.54(q)
Failure to Maintain the Effectiveness of the Emergency Plan
05000289/FIN-2018410-01Three Mile Island2018Q3GreenPhysical Protection10 CFR 73Security
05000483/FIN-2018003-02Callaway2018Q3GreenMitigating SystemsTechnical Specification - ProceduresLicensee-Identified ViolationAuxiliary Feedwater
05000424/FIN-2018003-01Vogtle2018Q3GreenEmergency Preparedness10 CFR 50.47, Emergency Plans
10 CFR 50.54
10 CFR 50.47(b)(4)
10 CFR 50.54(q)
Licensee-Identified ViolationReactor Coolant System
05000390/FIN-2018003-07Watts Bar2018Q3GreenMitigating SystemsTechnical SpecificationLicensee-Identified Violation
05000413/FIN-2018010-01Catawba2018Q3GreenMitigating 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
Inadequate Engineering Analyses to Support Design Basis Requirements
05000313/FIN-2018003-01Arkansas Nuclear2018Q3GreenMitigating 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 Translate the Design Requirements into Instructions for Refueling Emergency Diesel GeneratorsEmergency Diesel Generator
05000336/FIN-2018403-01Millstone2018Q3GreenPhysical ProtectionP.510 CFR 73Security
05000373/FIN-2018003-02LaSalle2018Q3GreenMitigating Systems10 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
Failure to Establish an Appropriate Inservice Testing Procedure
05000313/FIN-2018003-04Arkansas Nuclear2018Q3GreenMitigating SystemsP.3Technical Specification - ProceduresFailure to Verify Safety-Related 4160 V Breaker Operability Following Maintenance ActivitiesService water
05000456/FIN-2018003-01Braidwood2018Q3GreenMitigating SystemsH.710 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 Detail in Maintenance Procedure for Emergency Diesel Generator 2-Year Inspection Contributed to 1A Emergency Diesel GeneratorFuel Rack BindingEmergency Diesel Generator
05000369/FIN-2018012-01McGuire2018Q3GreenMitigating SystemsH.610 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 Translate Seismic Mounting Requirements for 125 VDC Vital Batteries into Installation and Replacement Procedure
05000348/FIN-2018003-02Farley2018Q3GreenNo Cornerstone10 CFR 50.48
License Condition - Fire Protection
Licensee-Identified Violation
05000373/FIN-2018412-01LaSalle2018Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000298/FIN-2018003-03Cooper2018Q3GreenInitiating EventsH.5Failure to Provide Adequate Lubrication for Drywell Fan Coil Units
05000263/FIN-2018003-01Monticello2018Q3GreenInitiating Events
Mitigating Systems
10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power PlantsLicensee-Identified Violation
05000482/FIN-2018010-03Wolf Creek2018Q3GreenMitigating SystemsP.410 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 Reoccurring Problems with Time Critical/Sensitive Action Activities
05000354/FIN-2018003-02Hope Creek2018Q3GreenInitiating EventsH.3Inadequate Procedures for Restoration of the A Reactor Feed Pump Turbine Following MaintenanceFeedwater
05000263/FIN-2018012-01Monticello2018Q3GreenBarrier Integrity10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XI, Test Control
Inboard Main Steam Isolation Valve Closure Time Test Acceptance Criteria Did Not Account for the Design Basis Accident Containment Back Pressure and Pneumatic Supply Operating PressureMain Steam Isolation Valve
05000324/FIN-2018411-01Brunswick2018Q3GreenPhysical Protection10 CFR 73.54, Protection of Digital Computer and Communication Systems and NetworksSecurity
05000282/FIN-2018003-03Prairie Island2018Q3GreenMitigating SystemsP.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 Promptly Identify Degradation of the 122 DDCLP FOST Vent Piping
05000296/FIN-2018003-01Browns Ferry2018Q3Severity level IVNo CornerstoneTechnical SpecificationMain Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
05000528/FIN-2018008-03Palo Verde2018Q3Severity level IVMitigating Systems10 CFR 50.73
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Technical Specification
Licensee-Identified Violation
05000275/FIN-2018404-03Diablo Canyon2018Q3Severity level IVPhysical Protection10 CFR 73Licensee-Identified Violation
05000341/FIN-2018003-02Fermi2018Q3GreenBarrier IntegrityH.710 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion VIII, Identification and Control of Materials, Parts, and Components
Failure to Ensure Electrolytic Capacitors Installed in the Plant Did Not Have Expired Shelf LivesReactor Water Cleanup
05000416/FIN-2018003-01Grand Gulf2018Q3GreenMitigating SystemsH.9Failure to Develop Adequate Work InstructionsFeedwater
05000373/FIN-2018003-06LaSalle2018Q3Mitigating SystemsPendingPotential Failure to Inspect Containment Post-Tensioned Tendons per Code Requirements and to Follow Corrective Action Program ProcessPrimary containment
05000390/FIN-2018003-01Watts Bar2018Q3GreenInitiating EventsH.12Technical Specification - ProceduresConfiguration Control Error Results in Actual Auxiliary Building Internal Flooding Event
05000482/FIN-2018201-01Wolf Creek2018Q3GreenPhysical Protection10 CFR 73Security
05000352/FIN-2018003-02Limerick2018Q3GreenBarrier IntegrityH.1310 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 Adverse Environmental Conditions Impacting Low Pressure Coolant Injection Outboard Primary Containment Isolation ValvePrimary containment
05000266/FIN-2018003-04Point Beach2018Q3GreenNo Cornerstone10 CFR 72Licensee-Identified Violation
05000316/FIN-2018003-01Cook2018Q3GreenInitiating EventsH.5Misaligned Heater Level Column Valves Leads to Manual Reactor TripFeedwater
Main Turbine
05000348/FIN-2018011-01Farley2018Q3GreenMitigating SystemsH.8License Condition - Fire ProtectionFailure to ensure fire barrier penetrations (including fire dampers) in fire zones protecting safety-related areas shall be functional in accordance with NFPA 805 Section 3.11.3, Fire Barrier Penetrations
05000282/FIN-2018003-02Prairie Island2018Q3GreenMitigating SystemsTechnical SpecificationFailure to Maintain a Preventative Maintenance Strategy for 12 and 22 Cooling Water Pump Diesel Engines
05000483/FIN-2018003-01Callaway2018Q3Mitigating SystemsFailure to perform 10 CFR 50.59 evaluation for compensatory measures associated with stagnant, inactive loopSteam Generator
05000255/FIN-2018411-02Palisades2018Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000247/FIN-2018003-03Indian Point2018Q3GreenBarrier IntegrityH.1310 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
Containment Fan Cooler 24 Through-Wall Service Water Leak Caused by Inadequate Application of Epoxy Coating Resulting in Corrosion and a Safety System Functional Failure of ContainmentService water
05000461/FIN-2018003-01Clinton2018Q3GreenMitigating SystemsH.3Failure to Revise an Operability Evaluation When No Longer Meeting a Compensatory Measure
05000317/FIN-2018410-01Calvert Cliffs2018Q3GreenPhysical ProtectionH.1210 CFR 73Security
05000313/FIN-2018003-02Arkansas Nuclear2018Q3GreenInitiating EventsH.2Technical Specification - ProceduresFailure to Implement Welding Standard Guidance and Examination Procedures
05000249/FIN-2018003-01Dresden2018Q3GreenMitigating SystemsH.7Technical Specification
Technical Specification - Procedures
Failure to Follow Maintenance Procedures for Assembling Unit 3 HPCI Room Cooler Fan
05000373/FIN-2018003-08LaSalle2018Q3GreenInitiating EventsH.4Technical Specification
Technical Specification - Procedures
Failure to Implement Engineering Change Results in Reactor Coolant Boundary Leakage
05000482/FIN-2018010-01Wolf Creek2018Q3GreenMitigating Systems10 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
Failure to Follow Procedures
05000458/FIN-2018003-01River Bend2018Q3Mitigating 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
05000354/FIN-2018403-01Hope Creek2018Q3GreenPhysical ProtectionH.310 CFR 73Security
05000410/FIN-2018003-02Nine Mile Point2018Q3Severity level MinorNo Cornerstone10 CFR 50.9, Completeness and Accuracy of Information
Technical Specification
Minor ViolationFeedwater
05000280/FIN-2018003-01Surry2018Q3GreenMitigating SystemsH.310 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 Control a Modification on the Containment Spray System
05000354/FIN-2018003-05Hope Creek2018Q3Severity level MinorNo CornerstoneTechnical SpecificationMinor ViolationFeedwater
Primary containment
05000336/FIN-2018003-01Millstone2018Q3GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion VII, Control of Purchased Material, Equipment, and Services
Failure to Assure that Safety-Related Service Water Piping Conformed to the Procurement DocumentsService water
05000296/FIN-2018012-01Browns Ferry2018Q3GreenMitigating SystemsTechnical SpecificationFailure to correct an inoperable 250V Shutdown Board Battery Charger
05000395/FIN-2018003-02Summer2018Q3Severity level MinorNo 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
Minor Violation
05000313/FIN-2018003-03Arkansas Nuclear2018Q3Severity level IVNo Cornerstone10 CFR 50.9, Completeness and Accuracy of InformationFailure to Provide Complete and Accurate Information in a License Amendment Request to Change Emergency Action Level Requirements
05000289/FIN-2018003-01Three Mile Island2018Q3GreenMitigating 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
1A Emergency Diesel Generator Lube Oil Leak Inadequate Corrective ActionsEmergency Diesel Generator
05000482/FIN-2018010-04Wolf Creek2018Q3GreenMitigating SystemsH.1310 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 Identify 125 VDC Equalizing Voltage Exceeded Design Requirements
05000445/FIN-2018003-02Comanche Peak2018Q3GreenMitigating Systems10 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
Failure to Establish Adequate Procedural Guidance for Processing Technical Changes Performed by A Vendor on Installed Plant EquipmentMain Steam Isolation Valve
05000263/FIN-2018012-02Monticello2018Q3GreenMitigating SystemsP.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 Implement Adequate Freeze Protection Monitoring for Condensate Storage Tank Instrumentation Piping in Response to Industry Operating Experience
05000255/FIN-2018411-01Palisades2018Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000287/FIN-2018003-03Oconee2018Q3Severity level IVMitigating SystemsTechnical SpecificationMain Steam Relief Valve As-Found Lift Pressure Prohibited by Technical Specifications
05000348/FIN-2018003-01Farley2018Q3Severity level IVNo CornerstoneTechnical SpecificationUnit 1 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance Band
05000313/FIN-2018405-01Arkansas Nuclear2018Q3GreenPhysical ProtectionP.210 CFR 73Security
05000391/FIN-2018003-02Watts Bar2018Q3GreenOccupational Radiation SafetyH.4Technical SpecificationUnauthorized Entry Into a High Radiation Area
05000250/FIN-2018003-01Turkey Point2018Q3No CornerstoneVital Inverter Alternate AC Supply Cables Were Not Included in the Nuclear Safety Capability Assessment
05000390/FIN-2018003-06Watts Bar2018Q3Severity level IVMitigating SystemsTechnical SpecificationLicensee-Identified Violation
05000266/FIN-2018010-01Point Beach2018Q3GreenNo Cornerstone10 CFR 50 Appendix B Criterion XII, Control of Measuring and Test EquipmentLicensee-Identified Violation
05000255/FIN-2018003-01Palisades2018Q3GreenMitigating SystemsH.1210 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
Wire Not Landed on Safety Injection Initiation Relay Circuit
05000482/FIN-2018201-02Wolf Creek2018Q3GreenPhysical Protection10 CFR 73Security
05000289/FIN-2018003-02Three Mile Island2018Q3Severity level MinorNo 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
Minor Violation
05000373/FIN-2018003-04LaSalle2018Q3GreenMitigating SystemsH.1310 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance At Nuclear Power Plants
10 CFR 50.65(a)(4)
Failure to Manage the Increase in Risk During a Battery Charger Capacity Tes
05000373/FIN-2018003-01LaSalle2018Q3GreenMitigating SystemsH.1210 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
Failure to Establish Heat Exchanger Inspection Procedures Appropriate for the Circumstances
05000313/FIN-2018011-01Arkansas Nuclear2018Q3GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing PlantsFailure to Properly Size the Unit 1 Emergency Diesel Generator Room Ventilation SvstemsEmergency Diesel Generator
05000237/FIN-2018003-02Dresden2018Q3Severity level IVNo Cornerstone10 CFR 50.59, Changes, Tests and ExperimentsLicensee-Identified Violation
05000414/FIN-2018003-01Catawba2018Q3GreenMitigating SystemsH.8Technical SpecificationFailure to Follow Maintenance Procedure Results in Damage to the 2A EDG During Testing
05000282/FIN-2018411-02Prairie Island2018Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000277/FIN-2018003-03Peach Bottom2018Q3WhiteMitigating SystemsTechnical SpecificationReactor Core Isolation Cooling System Pressure Switch Failure Results in Condition Prohibited by TS - EA-18-108Reactor Core Isolation Cooling
05000397/FIN-2018003-01Columbia2018Q3GreenOccupational Radiation SafetyH.12Technical Specification - ProceduresFailure to Follow Radiologically Controlled Area Procedures
05000293/FIN-2018003-01Pilgrim2018Q3GreenBarrier IntegrityH.9Technical SpecificationFailure to Identify an Adverse Condition Associated with Elevated Standby Gas Treatment System Accumulator LeakageStandby Gas Treatment System
05000315/FIN-2018010-01Cook2018Q3Mitigating SystemsRecord Retention Requirements of the Boron Injection Tank and its Associated Support Structure
05000334/FIN-2018411-01Beaver Valley2018Q3GreenPhysical ProtectionH.610 CFR 73Security
05000482/FIN-2018003-02Wolf Creek2018Q3Severity level IVNo Cornerstone10 CFR 50.73
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Failure to Submit a Licensee Event Report for a Condition Prohibited by Technical SpecificationsControl Room Emergency Ventilation
05000331/FIN-2018003-01Duane Arnold2018Q3GreenMitigating 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 ViolationMain Steam Isolation Valve
05000254/FIN-2018010-02Quad Cities2018Q3Severity level MinorNo Cornerstone10 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
Minor Violation
05000354/FIN-2018403-02Hope Creek2018Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000456/FIN-2018003-02Braidwood2018Q3Severity level MinorNo Cornerstone10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Minor Violation
05000400/FIN-2018003-01Harris2018Q3GreenMitigating SystemsP.5Failure to Implement Adequate Periodic Exercising of Turbine Trip Solenoid Operated ValvesMain Turbine
05000373/FIN-2018003-05LaSalle2018Q3GreenMitigating 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 Translate Fuel Oil Relief Valve Setting into Design Drawing of Record.
05000528/FIN-2018008-04Palo Verde2018Q3Severity level MinorNo 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
Minor Violation
05000247/FIN-2018003-01Indian Point2018Q3GreenBarrier IntegrityH.310 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 Procedural Guidance for Spent Fuel Movement and Storage Requirements
05000263/FIN-2018012-03Monticello2018Q3GreenInitiating 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
Licensee-Identified Violation
05000269/FIN-2018003-02Oconee2018Q3Severity level IVMitigating Systems10 CFR 50.73
10 CFR 50.73(a)(2)(iv)(A), System Actuation
Failure to Make a 60 Day Notification of an Actuation of an Emergency AC Power Source
05000354/FIN-2018003-04Hope Creek2018Q3Severity level Enforcement DiscretionMitigating Systems10 CFR 50.73
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Technical Specification
Enforcement Action (EA)-18-044: EGM on Dispositioning BWR Licensee Noncompliance With TS Containment Requirements During Operations With A Potential For Draining The Reactor Vessel (EGM-11-003)Secondary containment
Reactor Pressure Vessel
05000440/FIN-2018003-01Perry2018Q3Mitigating SystemsPendingApplication of ASME Code Case N5133 for the Emergency Service Water Piping DegradationsService water
05000482/FIN-2018010-05Wolf Creek2018Q3GreenMitigating 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
Licensee-Identified ViolationResidual Heat Removal
05000311/FIN-2018003-02Salem2018Q3GreenMitigating SystemsP.3PendingFailure to Follow Generic Letter 89-13 Program Procedure
05000254/FIN-2018003-01Quad Cities2018Q3GreenMitigating 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 Maintain the Design Basis for Residual Heat Removal Torus Suction ValveResidual Heat Removal
05000282/FIN-2018411-01Prairie Island2018Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000397/FIN-2018003-03Columbia2018Q3GreenEmergency PreparednessH.510 CFR 26
10 CFR 26.205, Work Hours
Failure to Adequately Control Work Hours for Covered Personnel
05000395/FIN-2018003-01Summer2018Q3GreenMitigating Systems10 CFR 50.48
License Condition
Licensee-Identified Violation
05000313/FIN-2018405-02Arkansas Nuclear2018Q3GreenPhysical ProtectionP.210 CFR 73Licensee-Identified Violation
05000298/FIN-2018003-02Cooper2018Q3GreenMitigating SystemsH.5Technical Specification - ProceduresFailure to Perform Process Applicability DeterminationResidual Heat Removal Service Water
05000282/FIN-2018003-01Prairie Island2018Q3GreenMitigating SystemsH.3Failure to Repair a D2 EDG Jacket Water Leak per the Leak Management Process
05000313/FIN-2018003-06Arkansas Nuclear2018Q3GreenInitiating EventsP.3Technical SpecificationReactor Power Transient Caused by the Turbine Bypass Valve Failing OpenMain Condenser
05000254/FIN-2018010-01Quad Cities2018Q3Severity level MinorNo 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
Minor ViolationCore Spray
05000298/FIN-2018003-01Cooper2018Q3Severity level IVNo Cornerstone10 CFR 50.9, Completeness and Accuracy of InformationFailure to Provide Complete and Accurate Information in a License Amendment Request
05000482/FIN-2018201-03Wolf Creek2018Q3GreenPhysical Protection10 CFR 73Security
05000266/FIN-2018003-02Point Beach2018Q3GreenInitiating Events
Mitigating Systems
10 CFR 50.48
License Condition - Fire Protection
Licensee-Identified Violation
05000247/FIN-2018003-04Indian Point2018Q3GreenInitiating EventsH.13Technical Specification
Technical Specification - Procedures
Inadequate Procedure for Turbine Startup Caused a Reactor TripSteam Generator
Main Turbine
05000458/FIN-2018301-01River Bend2018Q3GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsInadequate Procedure for Shutdown Operations Protection PlanShutdown Cooling
05000454/FIN-2018003-01Byron2018Q3Severity level MinorNo Cornerstone10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XII, Control of Measuring and Test Equipment
Minor Violation
05000313/FIN-2018011-02Arkansas Nuclear2018Q3GreenMitigating SystemsH.610 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 of Both Arkansas Nuclear One Units to Establish Adequate Corrective Actions Resulting in Excessive Instances of Damaged and Broken Internals of the Emergency Feedwater Pum o Turbine Steam Admission Check Valves.Feedwater
05000331/FIN-2018003-02Duane Arnold2018Q3Severity level MinorNo CornerstoneTechnical SpecificationMinor ViolationSecondary containment
05000446/FIN-2018011-01Comanche Peak2018Q3Severity level IIINo Cornerstone10 CFR 50.9, Completeness and Accuracy of Information
Pending
Failure to Maintain a Quality Record Complete and Accurate in All Material RespectsReactor Coolant System
05000461/FIN-2018412-01Clinton2018Q3GreenPhysical ProtectionH.210 CFR 73
Pending
Security
05000341/FIN-2018003-03Fermi2018Q3GreenMitigating SystemsH.1110 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 to Identify a Condition Adverse to Quality on Division 2 Residual Heat Removal Service Water Outlet Flow Control ValveResidual Heat Removal Service Water
05000352/FIN-2018003-01Limerick2018Q3GreenMitigating SystemsH.810 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 Fuel Oil Storage Tank Maintenance
05000413/FIN-2018010-02Catawba2018Q3GreenMitigating 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
Operability of the VZ and RN Systems were not AssuredService water
05000482/FIN-2018003-01Wolf Creek2018Q3GreenMitigating SystemsH.14Failure to Correct Degraded Performance of a Safety-Related Tornado Damper
05000334/FIN-2018011-01Beaver Valley2018Q3GreenMitigating SystemsTechnical Specification - ProceduresDuties of the Shift Technical Advisor for Control Room Evacuation during a Fire Event.
05000327/FIN-2018411-01Sequoyah2018Q3GreenPhysical ProtectionH.1210 CFR 73Security
05000354/FIN-2018003-03Hope Creek2018Q3GreenBarrier IntegrityH.6Technical Specificationinadequate Procedures for Fuel Conditioning Results in Multiple Fuel Leaks
05000443/FIN-2018003-01Seabrook2018Q3Severity level IVNo CornerstoneTechnical SpecificationPressurizer Safety Valve Outside of Technical Specification Limits
05000528/FIN-2018008-01Palo Verde2018Q3GreenMitigating SystemsH.1210 CFR 50 Appendix B Criterion XVI, Corrective ActionInadequate Corrective Actions For Missing Control Room Hand-Switch Operator Knob
05000275/FIN-2018404-01Diablo Canyon2018Q3GreenPhysical ProtectionH.1310 CFR 73Security
05000247/FIN-2018003-02Indian Point2018Q3GreenBarrier 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
Containment Fan Coolers 21 and 24 Motor Cooler Elbow Through-Wall Leaks Due to Excessive Service Water Flow Rates and Safety System Functional Failures of ContainmentService water
05000445/FIN-2018003-01Comanche Peak2018Q3GreenMitigating Systems10 CFR 50.63, Loss of All Alternating Current PowerFailure to Maintain the Ability to Withstand a Station Blackout
05000390/FIN-2018003-05Watts Bar2018Q3GreenMitigating SystemsLicense Condition - Fire ProtectionLicensee-Identified Violation
05000528/FIN-2018008-05Palo Verde2018Q3Severity level MinorNo Cornerstone10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion VI, Document Control
Minor Violation
05000277/FIN-2018003-01Peach Bottom2018Q3GreenMitigating SystemsP.210 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
HPCI System Exhaust Pressure Switches Exceeded Documented Qualified Life
05000373/FIN-2018201-01LaSalle2018Q3GreenPhysical Protection10 CFR 73Security
05000461/FIN-2018003-02Clinton2018Q3Severity level MinorNo Cornerstone10 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
Minor Violation
05000306/FIN-2018003-04Prairie Island2018Q3GreenMitigating SystemsH.1410 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 21 125 VDC Battery Lid Conditions Adverse to Quality
05000530/FIN-2018003-01Palo Verde2018Q3GreenInitiating EventsPendingFailure to Maintain Command and Control During a Feedwater Control Valve MalfunctionFeedwater
05000387/FIN-2018011-01Susquehanna2018Q3GreenBarrier IntegrityP.510 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XI, Test Control
Failure to conduct proper testing of 125 VDC molded case circuit breakers to confirm their design adequacy long-term
05000416/FIN-2018003-02Grand Gulf2018Q3Severity level MinorNo Cornerstone10 CFR 50.9, Completeness and Accuracy of InformationMinor Violation
05000254/FIN-2018003-02Quad Cities2018Q3Severity level IVNo Cornerstone10 CFR 72Failure to Follow Procedures for Forced Helium Dehydration of a Multipurpose Canister
05000456/FIN-2018411-01Braidwood2018Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000266/FIN-2018003-03Point Beach2018Q3GreenInitiating Events
Mitigating Systems
10 CFR 50.48
License Condition - Fire Protection
Licensee-Identified Violation
05000445/FIN-2018010-01Comanche Peak2018Q3GreenMitigating 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
Failure to Establish Test Program to Verify Residual Heat Removal Suction Valve CapabilityResidual Heat Removal
05000389/FIN-2018003-01Saint Lucie2018Q3GreenInitiating EventsH.510 CFR 50.48Failure to meet the Transient Combustible Requirements Specified by NFPA 805
05000277/FIN-2018410-01Peach Bottom2018Q3GreenPhysical ProtectionH.810 CFR 73Security
05000275/FIN-2018003-02Diablo Canyon2018Q3GreenMitigating SystemsH.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
4 kV Vital Switchgear Room Ventilation Degraded or Non-Conforming Condition and Associated Compensatory Measure Not Corrected in a Timely Manner
05000366/FIN-2018003-01Hatch2018Q3GreenMitigating SystemsH.1Technical Specification - ProceduresInoperability of 2A EDG Due to Inadequate Acceptance Criteria for Determining Cleaning Requirements of Emergency Diesel Generator Day TanksEmergency Diesel Generator
05000374/FIN-2018003-07LaSalle2018Q3Mitigating SystemsPotential Failure to Promptly Correct the Unit 2 Primary Containment Wall Cavity Leakage Condition and to Follow Corrective Action Program ProcessPrimary containment
05000352/FIN-2018010-01Limerick2018Q3Severity level MinorNo CornerstoneTechnical SpecificationMinor Violation
05000275/FIN-2018003-01Diablo Canyon2018Q3GreenMitigating SystemsP.210 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
Multiple Examples of Scaffolding in Place Greater Than 90 Days Without Required Evaluation
05000482/FIN-2018201-04Wolf Creek2018Q3GreenPhysical Protection10 CFR 73Security
05000315/FIN-2018003-02Cook2018Q3No CornerstoneSite Specific Shielding and Barriers for HI-TRAC Transfer Cask Require NRC Approval Prior to Use
05000391/FIN-2018003-04Watts Bar2018Q3GreenInitiating EventsH.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
Inadequate Sensitive Equipment Control Results in Unit 2 Reactor Trip on April 12, 2018Reactor Coolant System
05000458/FIN-2018301-02River Bend2018Q3GreenInitiating Events
Mitigating Systems
P.2
S.8(a)
10 CFR 55.49, Integrity of Examinations and TestsExam Security Compromise While Administering Simulator JPM
05000410/FIN-2018003-01Nine Mile Point2018Q3GreenMitigating SystemsH.1License ConditionFailure to Ensure that Thermal Power is Less Than or Equal to the Licensed Power Limit
05000313/FIN-2018011-03Arkansas Nuclear2018Q3No CornerstoneFailure to Evaluate the Effects and the Suitability of Components in Containment from a Main Steam Line Break.Steam Generator
05000259/FIN-2018003-02Browns Ferry2018Q3GreenNo Cornerstone10 CFR 50.48Licensee-Identified Violation
05000446/FIN-2018011-02Comanche Peak2018Q3GreenInitiating EventsH.12Technical Specification - ProceduresFailure to Follow a Quality Procedure Associated with the Reactor Makeup and Chemical Control SystemReactor Coolant System
05000333/FIN-2018412-01FitzPatrick2018Q3GreenPhysical Protection10 CFR 73Security
05000390/FIN-2018003-03Watts Bar2018Q3GreenPr SafetyH.12Technical SpecificationFailure to Collect Compensatory Samples for an Out-of-Service Effluent MonitorSteam Generator
05000369/FIN-2018003-01McGuire2018Q3Severity level IVEmergency Preparedness10 CFR 50.54
10 CFR 50.54(q)
Failure to Adequately Document the Basis for a Change to the Emergency Plan
05000482/FIN-2018010-02Wolf Creek2018Q3GreenMitigating Systems10 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
Failure to Establish an Adequate Procedure for Operator Time Critical Actions Validation
05000338/FIN-2018003-01North Anna2018Q3GreenMitigating SystemsTechnical SpecificationLicensee-Identified Violation
05000440/FIN-2018010-01Perry2018Q3GreenMitigating Systems10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power PlantsFailure to Correctly Establish Maintenance/Replacement Frequencyfor the WeedTemperature Transmitters In Zone FB-7
05000369/FIN-2018411-01McGuire2018Q3GreenPhysical ProtectionH.1210 CFR 73Security
05000272/FIN-2018003-03Salem2018Q3GreenMitigating Systems10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsLicensee-Identified Violation
05000327/FIN-2018003-01Sequoyah2018Q3GreenMitigating 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
Licensee-Identified Violation
05000528/FIN-2018008-02Palo Verde2018Q3GreenMitigating Systems10 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 Violation
05000275/FIN-2018404-02Diablo Canyon2018Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000277/FIN-2018003-02Peach Bottom2018Q3WhiteMitigating SystemsH.1110 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XVI, Corrective Action
Inadequate Corrective Actions Result in the Failure of the E-3 EDG
05000311/FIN-2018003-01Salem2018Q3GreenMitigating SystemsH.7Technical Specification - ProceduresInadequate Chiller Maintenance Procedures
05000313/FIN-2018003-05Arkansas Nuclear2018Q3GreenInitiating EventsH.4Technical Specification - ProceduresFailure to Maintain Main Feedwater Pump B Discharge Pressure in Band Caused a Reactor TripSteam Generator
Feedwater
05000341/FIN-2018003-01Fermi2018Q3GreenMitigating SystemsP.3Technical SpecificationFailure to Apply Torque Values Described in Maintenance Procedure for Flexible Couplings on Emergency Diesel Generator 12Emergency Diesel Generator
05000416/FIN-2018201-01Grand Gulf2018Q3GreenPhysical Protection10 CFR 73Security
05000397/FIN-2018003-02Columbia2018Q3GreenOccupational Radiation SafetyH.4Technical SpecificationFailure to Control Workers in a High Radiation Area (>1.0 rem per hour)
05000397/FIN-2018003-04Columbia2018Q3GreenOccupational Radiation Safety10 CFR 20
10 CFR 20.1902
Licensee-Identified Violation
05000334/FIN-2018003-01Beaver Valley2018Q3GreenMitigating SystemsH.11Technical Specification - ProceduresInadequate Verification of Full Low Head Safety Injection Suction Piping
05000458/FIN-2018012-02River Bend2018Q2GreenBarrier Integrity10 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 and Correct a Broken Feedwater Chemistry ProbeFeedwater
05000266/FIN-2018002-02Point Beach2018Q2GreenMitigating SystemsTechnical SpecificationUnanalyzed Condition for Tornado Generated MissilesMain Steam Isolation Valve
Auxiliary Feedwater
Main Steam Safety Valve
05000336/FIN-2018010-04Millstone2018Q2GreenMitigating SystemsP.310 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XIV, Inspection, Test, and Operating Status
Flood Seals Not Installed in Unit 2 A EDG and Auxiliary Building PenetrationsEmergency Diesel Generator
05000424/FIN-2018002-02Vogtle2018Q2GreenMitigating SystemsH.610 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
High Vibrations on Unit 2 NSCW Pump No. 3 Result in Pump Inoperability
05000259/FIN-2018412-01Browns Ferry2018Q2GreenPhysical ProtectionH.1210 CFR 73Security
05000321/FIN-2018002-01Hatch2018Q2Initiating Events
Mitigating Systems
10 CFR 50.48
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
Enforcement Action (EA)-18-100: Unanalyzed Conditions for a Postulated Fire Discovered During NFPA 805 TransitionPrimary containment
Remote shutdown
05000414/FIN-2018002-01Catawba2018Q2GreenInitiating EventsP.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 and Correct CAQ Associated with Failure of the 2B Seal Water Injection Filter O-ring
05000298/FIN-2018011-01Cooper2018Q2GreenMitigating Systems10 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to Correct Extent of Condition of Surge Suppression Varistor FailuresHigh Pressure Coolant Injection
Reactor Protection System
05000348/FIN-2018002-08Farley2018Q2GreenMitigating SystemsTechnical SpecificationLicensee-Identified ViolationSteam Generator
Auxiliary Feedwater
05000400/FIN-2018002-05Harris2018Q2GreenInitiating EventsH.8Technical SpecificationFailure to Follow Secondary Water Chemistry Plan for Elevated Levels of Secondary Water ImpuritiesSteam Generator
05000219/FIN-2018410-02Oyster Creek2018Q2GreenPhysical ProtectionH.1210 CFR 73Security
05000482/FIN-2018007-01Wolf Creek2018Q2GreenMitigating SystemsP.2Technical Specification - ProceduresFailure to Provide Adequate Work Instructions for Preventive Maintenance on Safety-Related Equipment
05000282/FIN-2018002-01Prairie Island2018Q2Mitigating SystemsResults of ISFSICask Array Dose Calculation Not Incorporated into FSAR
05000400/FIN-2018002-07Harris2018Q2Severity level MinorNo CornerstoneTechnical SpecificationMinor ViolationSteam Generator
Feedwater
Auxiliary Feedwater
05000387/FIN-2018002-04Susquehanna2018Q2Severity level Enforcement DiscretionNo CornerstoneTechnical SpecificationEGM on Dispositioning BWR Licensee Noncompliance With TS Containment Requirements During Operations With A Potential For Draining The Reactor Vessel (EGM-11-03)Secondary containment
Reactor Pressure Vessel
Core Spray
Reactor Water Cleanup
Intermediate Range Monitor
05000293/FIN-2018002-01Pilgrim2018Q2GreenInitiating EventsP.310 CFR 26
10 CFR 26.205, Work Hours
Failure to Properly Implement the Fatigue Management Program Work Hour Controls for Covered Workers
05000461/FIN-2018002-01Clinton2018Q2GreenMitigating SystemsH.6Failure to Perform an Operability Determination for Suspected Leakage Past Shutdown Service Water Isolation ValvesService water
05000272/FIN-2018403-02Salem2018Q2GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000458/FIN-2018012-04River Bend2018Q2Severity level IVNo Cornerstone10 CFR 50.73Failure to Submit a Licensee Event Report for a Manual Scram
05000331/FIN-2018002-02Duane Arnold2018Q2Severity level MinorNo Cornerstone10 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
Minor ViolationSecondary containment
05000390/FIN-2018002-02Watts Bar2018Q2Severity level IVNo CornerstoneTechnical SpecificationLicensee-Identified ViolationAuxiliary Building Gas Treatment System
05000346/FIN-2018002-01Davis Besse2018Q2GreenInitiating EventsH.12Technical SpecificationFailure to Follow the Makeup and Purification Procedure
05000255/FIN-2018011-03Palisades2018Q2GreenMitigating Systems10 CFR 50.48
License Condition - Fire Protection
Licensee-Identified Violation
05000458/FIN-2018406-03River Bend2018Q2GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000348/FIN-2018002-02Farley2018Q2GreenMitigating SystemsP.3Technical Specification - ProceduresFailure to develop adequate PM for diesel generator relays
05000324/FIN-2018011-02Brunswick2018Q2GreenMitigating Systems10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power PlantsFailure to Evaluate Effects of MOV Space Heaters on Qualified Life
05000333/FIN-2018002-01FitzPatrick2018Q2GreenNo Cornerstone10 CFR 71
10 CFR 71.5, Transportation of Licensed Material
49 CFR
Licensee-Identified Violation
05000461/FIN-2018050-01Clinton2018Q2TBDMitigating SystemsH.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
Failure to Follow Multiple ProcedureEmergency Diesel Generator
05000259/FIN-2018010-01Browns Ferry2018Q2GreenMitigating Systems10 CFR 50.48
License Condition
Licensee-Identified Violation
05000483/FIN-2018002-02Callaway2018Q2GreenBarrier IntegrityH.4Technical SpecificationFailure to Establish Maintenance Procedures for Doors that Provide Safety-Related Functions
05000443/FIN-2018411-01Seabrook2018Q2GreenPhysical ProtectionH.810 CFR 73Security
05000263/FIN-2018002-01Monticello2018Q2GreenEmergency Preparedness
Mitigating Systems
10 CFR 50.72
10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness
10 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
10 CFR 50.54(q)
10 CFR 50.47(b)(8)
Licensee-Identified Violation
05000397/FIN-2018002-01Columbia2018Q2GreenMitigating SystemsH.12Technical Specification - ProceduresFailure to Maintain Configuration Control in the Diesel Generator 2 Diesel Cooling Water System
05000259/FIN-2018002-04Browns Ferry2018Q2GreenNo Cornerstone10 CFR 50.48Licensee Identified Non-Cited ViolationEmergency Equipment Cooling Water
05000400/FIN-2018002-01Harris2018Q2GreenMitigating SystemsP.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
Failure to Promptly Identify and Correct a Condition Adverse to Quality For a Through-Wall Leak in the ESW Screen Wash Piping
05000275/FIN-2018008-06Diablo Canyon2018Q2Severity level MinorNo CornerstoneMinor ViolationSteam Generator
05000261/FIN-2018410-01Robinson2018Q2GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000456/FIN-2018002-03Braidwood2018Q2GreenInitiating EventsH.4Technical SpecificationInadequate Test Activity Coordination Results in Unintended Valve Actuation and Reactor Coolant System Pressure DropReactor Coolant System
05000416/FIN-2018002-05Grand Gulf2018Q2GreenOccupational Radiation SafetyH.12Technical SpecificationFailure to Follow Procedure Requirements Resulting in Unplanned Dose
05000315/FIN-2018002-05Cook2018Q2Severity level MinorNo CornerstoneMinor ViolationFeedwater
Service water
Auxiliary Feedwater
05000373/FIN-2018002-03LaSalle2018Q2GreenInitiating EventsTechnical SpecificationLicensee-Identified ViolationReactor Coolant System
05000373/FIN-2018002-02LaSalle2018Q2GreenMitigating SystemsFailure to Follow Procedure and Perform Database Revision Review Requirements
05000348/FIN-2018014-02Farley2018Q2Severity level IVNo Cornerstone10 CFR 50.9, Completeness and Accuracy of InformationFailure to Provide Complete and Accurate Information Related to System Operator Rounds
05000458/FIN-2018012-06River Bend2018Q2GreenMitigating SystemsTechnical SpecificationFailure to Provide Adequate Procedures for Post-Scram RecoveryFeedwater
Reactor Pressure Vessel
05000454/FIN-2018002-02Byron2018Q2GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsLicensee-Identified Violation
05000341/FIN-2018002-02Fermi2018Q2GreenMitigating SystemsP.210 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsInadequate Preventative Maintenance in Residual Heat Removal Service Water System Outlet Flow Control Valves Results in Lower Bonnet (Backseat) Bushing FailureResidual Heat Removal Service Water
05000373/FIN-2018010-01LaSalle2018Q2GreenInitiating EventsH.1210 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 Translate Reactor Building Superstructure Design Basis
05000423/FIN-2018010-05Millstone2018Q2GreenMitigating 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
Inadequate Test Control of ECCS Valve Interlocks
05000259/FIN-2018002-01Browns Ferry2018Q2GreenMitigating SystemsP.310 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
HPCI System Over Pressurization due to Failure to Maintain ProcedureHigh Pressure Coolant Injection
05000255/FIN-2018415-01Palisades2018Q2GreenPhysical Protection10 CFR 73Security
05000272/FIN-2018002-01Salem2018Q2GreenMitigating SystemsP.2Inadequate Design Change for Service Water PumpsService water
05000413/FIN-2018002-02Catawba2018Q2GreenMitigating SystemsP.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 Promptly Identify and Correct a Condition Adverse to Quality
05000298/FIN-2018011-02Cooper2018Q2GreenMitigating SystemsH.610 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 Ensure Adequate Design Control Measures are in Place Associated with RHR Service Water Booster Pump Room CoolingService water
Residual Heat Removal
05000275/FIN-2018008-04Diablo Canyon2018Q2GreenMitigating 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
05000400/FIN-2018002-06Harris2018Q2GreenEmergency PreparednessH.510 CFR 50.47, Emergency Plans
10 CFR 50.54
10 CFR 50.47(b)(4)
10 CFR 50.54(q)
Failure to Implement Viable Compensatory Actions with Seismic Monitoring System Out of Service for Planned Preventive Maintenance
05000275/FIN-2018008-02Diablo Canyon2018Q2GreenMitigating Systems10 CFR 21
10 CFR 50 Appendix B Criterion XV
10 CFR 50 Appendix B Criterion VII, Control of Purchased Material, Equipment, and Services
Failure to Identify Diesel Generator Air Inlet Boot Seal Critical Characteristics
05000369/FIN-2018410-02McGuire2018Q2GreenPhysical Protection10 CFR 73Security
05000331/FIN-2018002-01Duane Arnold2018Q2GreenMitigating SystemsH.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
Inappropriate Procedural Guidance Resulted in Loss of Scram Function and Failure to Enter Technical Specification Limiting Condition for OperationReactor Protection System
Main Steam Isolation Valve
Main Turbine
05000254/FIN-2018002-01Quad Cities2018Q2GreenMitigating Systems10 CFR 50 Appendix B Criterion V, Instructions, Procedures, and DrawingsFailure to Have a Procedure Appropriate to Circumstances for Degraded Voltage Relays
05000373/FIN-2018002-04LaSalle2018Q2Severity level MinorMitigating Systems10 CFR 50.9, Completeness and Accuracy of InformationMinor Violation - Follow-up of Events and Notices of Enforcement Discretion
05000293/FIN-2018002-02Pilgrim2018Q2GreenBarrier IntegrityH.9PendingLoss of Secondary Containment Integrity due to Simultaneously Opened Airlock DoorsSecondary containment
05000461/FIN-2018002-02Clinton2018Q2GreenMitigating 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
Failure to Establish Adequate Leak Rate Test Procedures for Shutdown Service Water Isolation Valve TestingService water
05000416/FIN-2018002-01Grand Gulf2018Q2GreenMitigating SystemsP.210 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to Institute Effective Corrective Action to Preclude RepetitionSecondary containment
05000454/FIN-2018002-03Byron2018Q2Severity level MinorNo Cornerstone10 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
Minor ViolationService water
05000269/FIN-2018002-02Oconee2018Q2Severity level IVNo Cornerstone10 CFR 37Failure to Coordinate a No-later-than Arrival Time for the Shipment of a Category 2 Quantity of Radioactive Material
05000346/FIN-2018002-02Davis Besse2018Q2GreenMitigating SystemsH.14Technical SpecificationFailure to Apply Technical Specification for Safety Features Actuation SystemInstrumentation
05000289/FIN-2018012-01Three Mile Island2018Q2GreenInitiating EventsP.2Failure to Establish Appropriate Corrective ActionsAssociated with a Degraded Non-Safety Related Piping System.
05000219/FIN-2018410-01Oyster Creek2018Q2GreenPhysical ProtectionH.1110 CFR 73Security
05000348/FIN-2018002-05Farley2018Q2GreenMitigating SystemsH.1Technical Specification - ProceduresFailure of a Main Steam Isolation Valve on the C Steam LineMain Steam Isolation Valve
05000324/FIN-2018011-03Brunswick2018Q2Mitigating SystemsPotential Unjustified Activation Energy for Rosemont Transmitters
05000313/FIN-2018002-01Arkansas Nuclear2018Q2GreenBarrier IntegrityH.12Technical Specification - ProceduresFailure to Implement Procedural Guidance to Close Spent Fuel Pool Cooler Outlet Crosstie Valve
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
05000277/FIN-2018010-02Peach Bottom2018Q2GreenMitigating SystemsLicense Condition
10 CFR 50.54(hh)
Failure to Develop and Maintain Mitigating StrategyAutomatic Depressurization System
... further results