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)
Arkansas Nuclear 24 5 Entergy [Arkansas Nuclear findings] [RSS] (CCA Matrix)
Armed Forces Radiobiology Research Institute 0 0 Department of Defense [Armed Forces Radiobiology Research Institute findings] [RSS] (CCA Matrix)
Beaver Valley 13 2 FirstEnergy [Beaver Valley findings] [RSS] (CCA Matrix)
Braidwood 14 1 Exelon [Braidwood findings] [RSS] (CCA Matrix)
Browns Ferry 23 8 Tennessee Valley Authority [Browns Ferry findings] [RSS] (CCA Matrix)
Brunswick 14 5 Duke Energy [Brunswick findings] [RSS] (CCA Matrix)
Byron 19 4 Exelon [Byron findings] [RSS] (CCA Matrix)
Callaway 17 6 Ameren [Callaway findings] [RSS] (CCA Matrix)
Calvert Cliffs 3 0 Exelon [Calvert Cliffs findings] [RSS] (CCA Matrix)
Catawba 13 0 Duke Energy [Catawba findings] [RSS] (CCA Matrix)
Chattanooga 0 0 Tennessee Valley Authority [Chattanooga findings] [RSS] (CCA Matrix)
Clinton 40 0 Exelon [Clinton findings] [RSS] (CCA Matrix)
Columbia 27 4 Energy Northwest [Columbia findings] [RSS] (CCA Matrix)
Comanche Peak 26 3 Luminant [Comanche Peak findings] [RSS] (CCA Matrix)
Consolidated Interim Storage Facility 0 0 Consolidated Interim Storage Facility [Consolidated Interim Storage Facility findings] [RSS] (CCA Matrix)
Cook 21 9 American Electric Power [Cook findings] [RSS] (CCA Matrix)
Cooper 31 1 Entergy [Cooper findings] [RSS] (CCA Matrix)
Crystal River 0 0 Duke Energy [Crystal River findings] [RSS] (CCA Matrix)
Davis Besse 15 1 Cleveland Electric [Davis Besse findings] [RSS] (CCA Matrix)
Diablo Canyon 16 4 Pacific Gas & Electric [Diablo Canyon findings] [RSS] (CCA Matrix)
Dresden 10 1 Exelon [Dresden findings] [RSS] (CCA Matrix)
Duane Arnold 13 2 NextEra Energy [Duane Arnold findings] [RSS] (CCA Matrix)
Entergy Headquarters 0 0 Entergy [Entergy Headquarters findings] [RSS] (CCA Matrix)
Farley 25 7 Southern Nuclear [Farley findings] [RSS] (CCA Matrix)
Fermi 24 3 DTE Energy [Fermi 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)
Fort Saint Vrain 0 0 Xcel Energy [Fort Saint Vrain findings] [RSS] (CCA Matrix)
Ginna 5 1 Exelon [Ginna findings] [RSS] (CCA Matrix)
Grand Gulf 42 10 Entergy [Grand Gulf findings] [RSS] (CCA Matrix)
Haddam Neck 0 0 Connecticut Yankee Atomic Power Co [Haddam Neck findings] [RSS] (CCA Matrix)
Hallam 0 0 [Hallam findings] [RSS] (CCA Matrix)
Harris 14 2 Duke Energy [Harris findings] [RSS] (CCA Matrix)
Hatch 11 6 Southern Nuclear [Hatch findings] [RSS] (CCA Matrix)
Hope Creek 15 3 PSEG [Hope Creek findings] [RSS] (CCA Matrix)
Humboldt Bay 0 0 Pacific Gas and Electric [Humboldt Bay findings] [RSS] (CCA Matrix)
Idaho State University 0 0 [Idaho State University findings] [RSS] (CCA Matrix)
Indian Point 16 1 Entergy [Indian Point findings] [RSS] (CCA Matrix)
Kennett Square 0 0 Exelon [Kennett Square findings] [RSS] (CCA Matrix)
Kewaunee 0 0 Dominion [Kewaunee findings] [RSS] (CCA Matrix)
Knolls Atomic Power Laboratory 0 0 Bechtel [Knolls Atomic Power Laboratory 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)
Lee 0 0 Duke Energy [Lee findings] [RSS] (CCA Matrix)
Limerick 13 3 Exelon [Limerick findings] [RSS] (CCA Matrix)
MIT Nuclear Research Reactor 0 0 [MIT Nuclear Research Reactor findings] [RSS] (CCA Matrix)
Maine Yankee 0 0 Maine Yankee Atomic Power Company [Maine Yankee findings] [RSS] (CCA Matrix)
McGuire 14 1 Duke Energy [McGuire findings] [RSS] (CCA Matrix)
Millstone 21 1 Dominion [Millstone findings] [RSS] (CCA Matrix)
Monticello 9 6 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)
Nine Mile Point 13 2 Exelon [Nine Mile Point findings] [RSS] (CCA Matrix)
North Anna 8 2 Dominion [North Anna findings] [RSS] (CCA Matrix)
North Carolina State University 0 0 [North Carolina State University findings] [RSS] (CCA Matrix)
Oconee 11 2 Duke Energy [Oconee findings] [RSS] (CCA Matrix)
Ohio State University 0 0 [Ohio State University findings] [RSS] (CCA Matrix)
Oyster Creek 8 2 Exelon [Oyster Creek findings] [RSS] (CCA Matrix)
Palisades 16 7 Entergy [Palisades findings] [RSS] (CCA Matrix)
Palo Verde 17 3 Arizona Public Service [Palo Verde findings] [RSS] (CCA Matrix)
Peach Bottom 17 2 Exelon [Peach Bottom findings] [RSS] (CCA Matrix)
Pennsylvania State University 0 0 Pennsylvania State University [Pennsylvania State University findings] [RSS] (CCA Matrix)
Perry 14 3 FirstEnergy [Perry findings] [RSS] (CCA Matrix)
Pilgrim 33 8 Entergy [Pilgrim findings] [RSS] (CCA Matrix)
Point Beach 14 6 NextEra Energy [Point Beach findings] [RSS] (CCA Matrix)
Portsmouth Gaseous Diffusion Plant 0 0 [Portsmouth Gaseous Diffusion Plant findings] [RSS] (CCA Matrix)
Prairie Island 16 11 Xcel Energy [Prairie Island findings] [RSS] (CCA Matrix)
Purdue University 0 0 [Purdue University findings] [RSS] (CCA Matrix)
Quad Cities 14 0 Exelon [Quad Cities 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)
River Bend 26 3 Entergy [River Bend findings] [RSS] (CCA Matrix)
Robinson 9 2 Duke Energy [Robinson findings] [RSS] (CCA Matrix)
SHINE Medical Technologies 0 0 [SHINE Medical Technologies findings] [RSS] (CCA Matrix)
Saint Lucie 9 1 NextEra Energy [Saint Lucie findings] [RSS] (CCA Matrix)
Salem 19 7 PSEG [Salem findings] [RSS] (CCA Matrix)
San Onofre 0 0 Southern California Edison [San Onofre findings] [RSS] (CCA Matrix)
Saxton 0 0 GPU Nuclear [Saxton findings] [RSS] (CCA Matrix)
Seabrook 10 1 NextEra Energy [Seabrook findings] [RSS] (CCA Matrix)
Sequoyah 11 6 Tennessee Valley Authority [Sequoyah findings] [RSS] (CCA Matrix)
Shoreham 0 0 Long Island Lighting Company [Shoreham findings] [RSS] (CCA Matrix)
Summer 22 5 South Carolina Electric & Gas Company [Summer findings] [RSS] (CCA Matrix)
Surry 9 1 Dominion [Surry findings] [RSS] (CCA Matrix)
Susquehanna 15 2 Talen Energy [Susquehanna findings] [RSS] (CCA Matrix)
Texas A&M University 0 0 [Texas A&M University findings] [RSS] (CCA Matrix)
Three Mile Island 9 5 Exelon [Three Mile Island findings] [RSS] (CCA Matrix)
Trojan 0 0 PGE [Trojan findings] [RSS] (CCA Matrix)
Turkey Point 30 0 NextEra Energy [Turkey Point findings] [RSS] (CCA Matrix)
Tuxedo 0 0 Union Carbide Company [Tuxedo findings] [RSS] (CCA Matrix)
University of Buffalo 0 0 [University of Buffalo 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)
Vanowen 0 0 Vanowen [Vanowen findings] [RSS] (CCA Matrix)
Vermont Yankee 0 0 Entergy [Vermont Yankee findings] [RSS] (CCA Matrix)
Vogtle 19 4 Southern Nuclear [Vogtle findings] [RSS] (CCA Matrix)
Waterford 15 3 Entergy [Waterford findings] [RSS] (CCA Matrix)
Watts Bar 26 9 Tennessee Valley Authority [Watts Bar findings] [RSS] (CCA Matrix)
Wolf Creek 29 1 Wolf Creek Nuclear Operating Corporation [Wolf Creek 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]
Arkansas Nuclear 0 Entergy [Arkansas Nuclear findings]
Armed Forces Radiobiology Research Institute 0 Department of Defense [Armed Forces Radiobiology Research Institute findings]
Beaver Valley 0 FirstEnergy [Beaver Valley findings]
Braidwood 0 Exelon [Braidwood findings]
Browns Ferry 0 Tennessee Valley Authority [Browns Ferry findings]
Brunswick 0 Duke Energy [Brunswick findings]
Byron 0 Exelon [Byron findings]
Callaway 0 Ameren [Callaway findings]
Calvert Cliffs 0 Exelon [Calvert Cliffs findings]
Catawba 0 Duke Energy [Catawba findings]
Chattanooga 0 Tennessee Valley Authority [Chattanooga findings]
Clinton 0 Exelon [Clinton findings]
Columbia 0 Energy Northwest [Columbia findings]
Comanche Peak 0 Luminant [Comanche Peak findings]
Consolidated Interim Storage Facility 0 Consolidated Interim Storage Facility [Consolidated Interim Storage Facility findings]
Cook 0 American Electric Power [Cook findings]
Cooper 0 Entergy [Cooper findings]
Crystal River 0 Duke Energy [Crystal River findings]
Davis Besse 0 Cleveland Electric [Davis Besse findings]
Diablo Canyon 0 Pacific Gas & Electric [Diablo Canyon findings]
Dresden 0 Exelon [Dresden findings]
Duane Arnold 0 NextEra Energy [Duane Arnold findings]
Entergy Headquarters 0 Entergy [Entergy Headquarters findings]
Farley 0 Southern Nuclear [Farley findings]
Fermi 0 DTE Energy [Fermi findings]
FitzPatrick 0 Exelon [FitzPatrick findings]
Fort Calhoun 0 Omaha Public Power District [Fort Calhoun findings]
Fort Saint Vrain 0 Xcel Energy [Fort Saint Vrain findings]
Ginna 0 Exelon [Ginna findings]
Grand Gulf 0 Entergy [Grand Gulf findings]
Haddam Neck 0 Connecticut Yankee Atomic Power Co [Haddam Neck findings]
Hallam 0 [Hallam findings]
Harris 0 Duke Energy [Harris findings]
Hatch 0 Southern Nuclear [Hatch findings]
Hope Creek 0 PSEG [Hope Creek findings]
Humboldt Bay 0 Pacific Gas and Electric [Humboldt Bay findings]
Idaho State University 0 [Idaho State University findings]
Indian Point 0 Entergy [Indian Point findings]
Kennett Square 0 Exelon [Kennett Square findings]
Kewaunee 0 Dominion [Kewaunee findings]
Knolls Atomic Power Laboratory 0 Bechtel [Knolls Atomic Power Laboratory findings]
La Crosse 0 Dairyland Power Cooperative [La Crosse findings]
LaSalle 0 Exelon [LaSalle findings]
Lee 0 Duke Energy [Lee findings]
Limerick 0 Exelon [Limerick findings]
MIT Nuclear Research Reactor 0 [MIT Nuclear Research Reactor findings]
Maine Yankee 0 Maine Yankee Atomic Power Company [Maine Yankee findings]
McGuire 0 Duke Energy [McGuire findings]
Millstone 0 Dominion [Millstone 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]
Nine Mile Point 0 Exelon [Nine Mile Point findings]
North Anna 0 Dominion [North Anna findings]
North Carolina State University 0 [North Carolina State University findings]
Oconee 0 Duke Energy [Oconee findings]
Ohio State University 0 [Ohio State University findings]
Oyster Creek 0 Exelon [Oyster Creek findings]
Palisades 0 Entergy [Palisades findings]
Palo Verde 0 Arizona Public Service [Palo Verde findings]
Peach Bottom 0 Exelon [Peach Bottom findings]
Pennsylvania State University 0 Pennsylvania State University [Pennsylvania State University findings]
Perry 0 FirstEnergy [Perry findings]
Pilgrim 0 Entergy [Pilgrim findings]
Point Beach 0 NextEra Energy [Point Beach findings]
Portsmouth Gaseous Diffusion Plant 0 [Portsmouth Gaseous Diffusion Plant findings]
Prairie Island 0 Xcel Energy [Prairie Island findings]
Purdue University 0 [Purdue University findings]
Quad Cities 0 Exelon [Quad Cities findings]
Rancho Seco 0 Sacramento Municipal Utility District [Rancho Seco findings]
Reed College 0 Reed Research Reactor [Reed College findings]
River Bend 0 Entergy [River Bend findings]
Robinson 0 Duke Energy [Robinson findings]
SHINE Medical Technologies 0 [SHINE Medical Technologies findings]
Saint Lucie 0 NextEra Energy [Saint Lucie findings]
Salem 0 PSEG [Salem findings]
San Onofre 0 Southern California Edison [San Onofre findings]
Saxton 0 GPU Nuclear [Saxton findings]
Seabrook 0 NextEra Energy [Seabrook findings]
Sequoyah 0 Tennessee Valley Authority [Sequoyah findings]
Shoreham 0 Long Island Lighting Company [Shoreham findings]
Summer 0 South Carolina Electric & Gas Company [Summer findings]
Surry 0 Dominion [Surry findings]
Susquehanna 0 Talen Energy [Susquehanna findings]
Texas A&M University 0 [Texas A&M University findings]
Three Mile Island 0 Exelon [Three Mile Island findings]
Trojan 0 PGE [Trojan findings]
Turkey Point 0 NextEra Energy [Turkey Point findings]
Tuxedo 0 Union Carbide Company [Tuxedo findings]
University of Buffalo 0 [University of Buffalo 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]
Vanowen 0 Vanowen [Vanowen findings]
Vermont Yankee 0 Entergy [Vermont Yankee findings]
Vogtle 0 Southern Nuclear [Vogtle findings]
Waterford 0 Entergy [Waterford findings]
Watts Bar 0 Tennessee Valley Authority [Watts Bar findings]
Wolf Creek 0 Wolf Creek Nuclear Operating Corporation [Wolf Creek findings]
Zion 0 Exelon [Zion findings]

By reactor type

since: 1 April 2019

Type#listfeed
B&W-L-LP (5) 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 (10) 0 [CE events] [RSS]
GE-1 (1) 0 [GE-1 events] [RSS]
GE-2 (2) 0 [GE-2 events] [RSS]
GE-3 (5) 0 [GE-3 events] [RSS]
GE-4 (12) 0 [GE-4 events] [RSS]
GE-5 (4) 0 [GE-5 events] [RSS]
GE-6 (4) 0 [GE-6 events] [RSS]
Pool (2) 0 [Pool events] [RSS]
TRIGA (5) 0 [TRIGA events] [RSS]
W-AP1000 (1) 0 [W-AP1000 events] [RSS]
Westinghouse PWR 2-Loop (4) 0 [Westinghouse PWR 2-Loop events] [RSS]
Westinghouse PWR 3-Loop (9) 0 [Westinghouse PWR 3-Loop events] [RSS]
Westinghouse PWR 4-Loop (18) 0 [Westinghouse PWR 4-Loop events] [RSS]

List

 SiteQuarterSignificanceCornerstoneCross cutting aspectViolation ofTitleSystem
05000390/FIN-2018003-06Watts Bar2018Q3Severity level IVMitigating SystemsTechnical SpecificationLicensee-Identified Violation
05000440/FIN-2018003-01Perry2018Q3Mitigating SystemsPendingApplication of ASME Code Case N5133 for the Emergency Service Water Piping DegradationsService water
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
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
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
05000395/FIN-2018003-01Summer2018Q3GreenMitigating Systems10 CFR 50.48
License Condition
Licensee-Identified Violation
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
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
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
05000282/FIN-2018003-01Prairie Island2018Q3GreenMitigating SystemsH.3Failure to Repair a D2 EDG Jacket Water Leak per the Leak Management Process
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
05000458/FIN-2018301-01River Bend2018Q3GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B Criterion VInadequate 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
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
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.
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
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
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
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
05000443/FIN-2018003-01Seabrook2018Q3Severity level IVNo CornerstoneTechnical SpecificationPressurizer Safety Valve Outside of Technical Specification Limits
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
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
05000397/FIN-2018003-03Columbia2018Q3GreenEmergency PreparednessH.510 CFR 26
10 CFR 26.205, Work Hours
Failure to Adequately Control Work Hours for Covered Personnel
05000445/FIN-2018003-01Comanche Peak2018Q3GreenMitigating Systems10 CFR 50.63, Loss of All Alternating Current PowerFailure to Maintain the Ability to Withstand a Station Blackout
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
05000313/FIN-2018003-06Arkansas Nuclear2018Q3GreenInitiating EventsP.3Technical SpecificationReactor Power Transient Caused by the Turbine Bypass Valve Failing OpenMain Condenser
05000530/FIN-2018003-01Palo Verde2018Q3GreenInitiating EventsPendingFailure to Maintain Command and Control During a Feedwater Control Valve MalfunctionFeedwater
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
Minor 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
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
Failure to Establish Test Program to Verify Residual Heat Removal Suction Valve CapabilityResidual Heat Removal
05000247/FIN-2018003-04Indian Point2018Q3GreenInitiating EventsH.13Technical Specification
Technical Specification - Procedures
Inadequate Procedure for Turbine Startup Caused a Reactor TripSteam Generator
Main Turbine
05000389/FIN-2018003-01Saint Lucie2018Q3GreenInitiating EventsH.510 CFR 50.48Failure to meet the Transient Combustible Requirements Specified by NFPA 805
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
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
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
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
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
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
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
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
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
05000410/FIN-2018003-01Nine Mile Point2018Q3GreenMitigating SystemsH.1License ConditionFailure to Ensure that Thermal Power is Less Than or Equal to the Licensed Power Limit
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-2018003-05Watts Bar2018Q3GreenMitigating SystemsLicense Condition - Fire ProtectionLicensee-Identified Violation
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
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
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 VLicensee-Identified 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
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
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
Failure to Establish an Adequate Procedure for Operator Time Critical Actions Validation
05000338/FIN-2018003-01North Anna2018Q3GreenMitigating SystemsTechnical SpecificationLicensee-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
05000266/FIN-2018003-03Point Beach2018Q3GreenInitiating Events
Mitigating Systems
10 CFR 50.48
License Condition - Fire Protection
Licensee-Identified Violation
05000311/FIN-2018003-01Salem2018Q3GreenMitigating SystemsH.7Technical Specification - ProceduresInadequate Chiller Maintenance Procedures
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
05000397/FIN-2018003-02Columbia2018Q3GreenOccupational Radiation SafetyH.4Technical SpecificationFailure to Control Workers in a High Radiation Area (>1.0 rem per hour)
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
05000334/FIN-2018003-01Beaver Valley2018Q3GreenMitigating SystemsH.11Technical Specification - ProceduresInadequate Verification of Full Low Head Safety Injection Suction Piping
05000416/FIN-2018201-01Grand Gulf2018Q3GreenPhysical Protection10 CFR 73Security
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
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
Failure to Provide Procedural Guidance for the Failure of a Component Cooling Water Surge Tank Makeup Valve
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
Inadequate Sensitive Equipment Control Results in Unit 2 Reactor Trip on April 12, 2018Reactor Coolant System
05000269/FIN-2018003-01Oconee2018Q3Severity level IVEmergency Preparedness10 CFR 50.54
10 CFR 50.54(q)
Failure to Maintain the Effectiveness of the Emergency Plan
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
Inoperable Auxiliary Feedwater Steam Supply Flow PathSteam Generator
Auxiliary Feedwater
05000289/FIN-2018410-01Three Mile Island2018Q3GreenPhysical Protection10 CFR 73Security
05000483/FIN-2018003-02Callaway2018Q3GreenMitigating SystemsTechnical Specification - ProceduresLicensee-Identified ViolationAuxiliary Feedwater
05000390/FIN-2018003-03Watts Bar2018Q3GreenPr SafetyH.12Technical SpecificationFailure to Collect Compensatory Samples for an Out-of-Service Effluent MonitorSteam Generator
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
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
Failure to Establish an Appropriate Inservice Testing Procedure
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
Licensee-Identified Violation
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
Inadequate Detail in Maintenance Procedure for Emergency Diesel Generator 2-Year Inspection Contributed to 1A Emergency Diesel GeneratorFuel Rack BindingEmergency Diesel Generator
05000373/FIN-2018412-01LaSalle2018Q3GreenPhysical Protection10 CFR 73Licensee-Identified Violation
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
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
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
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
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
05000397/FIN-2018003-04Columbia2018Q3GreenOccupational Radiation Safety10 CFR 20
10 CFR 20.1902
Licensee-Identified Violation
05000296/FIN-2018003-01Browns Ferry2018Q3Severity level IVNo CornerstoneTechnical SpecificationMain Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
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
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
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
05000416/FIN-2018003-01Grand Gulf2018Q3GreenMitigating SystemsH.9Failure to Develop Adequate Work InstructionsFeedwater
05000390/FIN-2018003-01Watts Bar2018Q3GreenInitiating EventsH.12Technical Specification - ProceduresConfiguration Control Error Results in Actual Auxiliary Building Internal Flooding Event
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
05000390/FIN-2018003-07Watts Bar2018Q3GreenMitigating SystemsTechnical SpecificationLicensee-Identified Violation
05000316/FIN-2018003-01Cook2018Q3GreenInitiating EventsH.5Misaligned Heater Level Column Valves Leads to Manual Reactor TripFeedwater
Main Turbine
05000482/FIN-2018201-01Wolf Creek2018Q3GreenPhysical Protection10 CFR 73Security
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
05000313/FIN-2018003-04Arkansas Nuclear2018Q3GreenMitigating SystemsP.3Technical Specification - ProceduresFailure to Verify Safety-Related 4160 V Breaker Operability Following Maintenance ActivitiesService water
05000461/FIN-2018003-01Clinton2018Q3GreenMitigating SystemsH.3Failure to Revise an Operability Evaluation When No Longer Meeting a Compensatory Measure
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
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
05000298/FIN-2018003-03Cooper2018Q3GreenInitiating EventsH.5Failure to Provide Adequate Lubrication for Drywell Fan Coil Units
05000249/FIN-2018003-01Dresden2018Q3GreenMitigating SystemsH.7Technical Specification
Technical Specification - Procedures
Failure to Follow Maintenance Procedures for Assembling Unit 3 HPCI Room Cooler Fan
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
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
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
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
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
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
05000373/FIN-2018003-06LaSalle2018Q3Mitigating SystemsPendingPotential Failure to Inspect Containment Post-Tensioned Tendons per Code Requirements and to Follow Corrective Action Program ProcessPrimary containment
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
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
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
05000266/FIN-2018003-04Point Beach2018Q3GreenNo Cornerstone10 CFR 72Licensee-Identified Violation
05000348/FIN-2018003-01Farley2018Q3Severity level IVNo CornerstoneTechnical SpecificationUnit 1 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance Band
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
Failure to Establish Adequate Procedural Guidance for Processing Technical Changes Performed by A Vendor on Installed Plant EquipmentMain Steam Isolation Valve
05000313/FIN-2018405-01Arkansas Nuclear2018Q3GreenPhysical ProtectionP.210 CFR 73Security
05000391/FIN-2018003-02Watts Bar2018Q3GreenOccupational Radiation SafetyH.4Technical SpecificationUnauthorized Entry Into a High Radiation Area
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
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
05000250/FIN-2018003-01Turkey Point2018Q3No CornerstoneVital Inverter Alternate AC Supply Cables Were Not Included in the Nuclear Safety Capability Assessment
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
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-2018003-08LaSalle2018Q3GreenInitiating EventsH.4Technical Specification
Technical Specification - Procedures
Failure to Implement Engineering Change Results in Reactor Coolant Boundary Leakage
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
Failure to Establish Heat Exchanger Inspection Procedures Appropriate for the Circumstances
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
05000354/FIN-2018003-05Hope Creek2018Q3Severity level MinorNo CornerstoneTechnical SpecificationMinor ViolationFeedwater
Primary containment
05000397/FIN-2018003-01Columbia2018Q3GreenOccupational Radiation SafetyH.12Technical Specification - ProceduresFailure to Follow Radiologically Controlled Area Procedures
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
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
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
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
Minor Violation
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
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
05000287/FIN-2018003-03Oconee2018Q3Severity level IVMitigating SystemsTechnical SpecificationMain Steam Relief Valve As-Found Lift Pressure Prohibited by Technical Specifications
05000400/FIN-2018003-01Harris2018Q3GreenMitigating SystemsP.5Failure to Implement Adequate Periodic Exercising of Turbine Trip Solenoid Operated ValvesMain Turbine
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
Inadequate Procedural Guidance for Spent Fuel Movement and Storage Requirements
05000461/FIN-2018002-03Clinton2018Q2Severity level MinorNo CornerstoneTechnical SpecificationMinor Violation
05000296/FIN-2018002-02Browns Ferry2018Q2Severity level IVNo CornerstoneTechnical SpecificationInoperable Residual Heat Removal (RHR) Pump Results in Condition Prohibited by Technical SpecificationsResidual Heat Removal
05000293/FIN-2018002-05Pilgrim2018Q2GreenNo Cornerstone10 CFR 50.72(b)(3)(v), Loss of Safety FunctionLicensee-Identified ViolationSecondary containment
05000346/FIN-2018002-03Davis Besse2018Q2GreenMitigating SystemsH.810 CFR 50 Appendix A, Appendix a to Part 50-General Design Criteria for Nuclear Power Plants
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V
Failure to Perform a Procedure Affecting Quality
05000293/FIN-2018410-01Pilgrim2018Q2GreenPhysical ProtectionP.310 CFR 73Security
05000455/FIN-2018002-01Byron2018Q2GreenMitigating SystemsH.1210 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V
Technical Specification
Overspeed Trip of 2B Auxiliary Feedwater Pump During SurveillanceAuxiliary Feedwater
05000416/FIN-2018002-02Grand Gulf2018Q2GreenMitigating SystemsH.510 CFR 50.55Failure to Follow ASME Requirements for Maintaining Inservice Inspection (ISI) Cycles and Perform ASME Required Inservice Inspections within the Scheduled ISI CycleHigh Pressure Core Spray
05000458/FIN-2018002-02River Bend2018Q2Severity level Enforcement DiscretionMitigating Systems10 CFR 50 Appendix A, Appendix a to Part 50-General Design Criteria for Nuclear Power Plants
Technical Specification
10 CFR 50 Appendix A GDC 2
10 CFR 50 Appendix A GDC 4
Enforcement Action (EA)-18-053: Enforcement Discretion for Tornado-Generated Missile Protection NoncompliancesReactor Coolant System
Service water
Emergency Diesel Generator
Residual Heat Removal
05000461/FIN-2018050-03Clinton2018Q2GreenMitigating SystemsH.610 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V
Equipment Operator Rounds Points Inadequate Acceptance Criteria
05000390/FIN-2018050-01Watts Bar2018Q2GreenInitiating Events
Mitigating Systems
10 CFR 50 Appendix B Criterion III, Design ControlLicensee-Identified Violation
05000483/FIN-2018002-04Callaway2018Q2GreenEmergency PreparednessH.1410 CFR 50.54
10 CFR 50.54(q)
Failure of an Analysis of the Impact of Changes to Emergency Action Levels to Demonstrate the Changes Did Not Reduce the Effectiveness of the Emergency Plan
05000336/FIN-2018010-03Millstone2018Q2GreenMitigating SystemsP.510 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V
Failure to Correct Part 21 Power Supply Defects
05000445/FIN-2018002-02Comanche Peak2018Q2GreenMitigating SystemsH.710 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XI
Unacceptable Preconditioning of Main Steam Isolation ValvesMain Steam Isolation Valve
05000331/FIN-2018011-01Duane Arnold2018Q2GreenMitigating 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 Environmental Qualification Requirements into Maintenance Procedures/Instructions
05000400/FIN-2018002-03Harris2018Q2Severity level IVEmergency Preparedness10 CFR 50.54
10 CFR 50.54(q)
Failure to Adequately Document Changes to the Emergency Plan
05000333/FIN-2018411-02FitzPatrick2018Q2Severity level IVPhysical Protection10 CFR 73Security
05000369/FIN-2018002-01McGuire2018Q2Severity level IVMitigating SystemsTechnical SpecificationLicensee-Identified Violation
05000416/FIN-2018002-07Grand Gulf2018Q2GreenInitiating EventsH.12Technical SpecificationLoss of Shutdown CoolingShutdown Cooling
Reactor Pressure Vessel
Residual Heat Removal
05000315/FIN-2018002-06Cook2018Q2Severity level MinorNo CornerstoneTechnical SpecificationMinor ViolationAuxiliary Feedwater
05000348/FIN-2018002-03Farley2018Q2GreenOccupational Radiation SafetyH.110 CFR 20
10 CFR 20.1501
Failure to Calibrate Portable Radiation Survey Instruments
05000275/FIN-2018010-01Diablo Canyon2018Q2GreenMitigating Systems10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power PlantsFailure to install conduit to environmentally qualified solenoid valves in a manner to prevent moisture intrusion and accumulation within the solenoid enclosure
05000482/FIN-2018002-02Wolf Creek2018Q2GreenMitigating SystemsH.3Failure to Maintain Adequate Pressurization of the Control Room EnvelopeControl Room Emergency Ventilation
05000482/FIN-2018007-02Wolf Creek2018Q2Severity level MinorMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XV, Nonconforming Materials, Parts, or Components
Minor Violation
05000440/FIN-2018410-01Perry2018Q2GreenPhysical ProtectionH.310 CFR 73Security
05000528/FIN-2018002-01Palo Verde2018Q2GreenMitigating SystemsH.1Technical SpecificationFailure to Re-baseline Valve Stroke Times as Required by ASME OM Code
05000315/FIN-2018002-02Cook2018Q2GreenInitiating Events
Mitigating Systems
Pr Safety
License ConditionLicensee-Identified Violation
05000315/FIN-2018002-04Cook2018Q2GreenMitigating Systems
Public Radiation Safety
10 CFR 20.1501Licensee-Identified Violation
05000341/FIN-2018002-04Fermi2018Q2TBDMitigating 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
05000316/FIN-2018002-01Cook2018Q2GreenInitiating EventsH.11Technical Specification - ProceduresSteam Dump Closure Caused by Human ErrorSteam Generator
05000458/FIN-2018406-01River Bend2018Q2GreenPhysical Protection10 CFR 73Security
05000220/FIN-2018002-02Nine Mile Point2018Q2GreenMitigating SystemsH.110 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V
Inadequate Procedure Causes Water Hammer Condition Resulting in Isolation and Inoperability of the 12 Train of the Emergency Condenser System
05000458/FIN-2018012-03River Bend2018Q2GreenInitiating EventsP.310 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V
Failure to Establish Procedural Guidance for Determining Core Flow During Unanticipated Single Loop Operations
05000286/FIN-2018002-01Indian Point2018Q2Severity level IVNo CornerstoneTechnical SpecificationReactor Pressure Boundary Leakage Due to Weld Failure in Reactor Vessel Head Penetration #3Reactor Coolant System
Reactor Pressure Vessel
05000281/FIN-2018002-01Surry2018Q2GreenInitiating EventsP.3Technical Specification - ProceduresFailure to Follow Preventative Maintenance Procedure Results in Additional Failures of Emergency Bus Undervoltage and Degraded Voltage Relays
05000298/FIN-2018011-04Cooper2018Q2GreenMitigating 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
Incorrect Classification of Potential Safety-Related ComponentsService water
Emergency Diesel Generator
05000390/FIN-2018012-01Watts Bar2018Q2No CornerstonePotential Failure to Implement Reviews of Adverse Employment Actions in Accordance with Confirmatory Order, EA-09-009 and EA-09-203
05000352/FIN-2018002-02Limerick2018Q2No CornerstoneTechnical SpecificationUnit 1 Core Spray Pump Failed to Start Resulting in Condition Prohibited by Technical SpecificationsCore Spray
05000275/FIN-2018008-01Diablo Canyon2018Q2Mitigating SystemsEmergency Diesel Generator Mission Time for Operability EvaluationsEmergency Diesel Generator
05000298/FIN-2018002-01Cooper2018Q2GreenMitigating SystemsH.3Technical SpecificationFailure to Maintain Alarm Procedure for Service Water Booster Pump Ventilation Manual ActionsService water
05000423/FIN-2018010-02Millstone2018Q2GreenMitigating SystemsP.110 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion III, Design Control
Over-Duty Breakers on Safety-Related Bus 34C on Unit 3
05000277/FIN-2018002-01Peach Bottom2018Q2GreenMitigating 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 Identify and Promptly Correct a Condition Adverse to Quality Concerning Battery Charger 2B-003-1
05000219/FIN-2018410-04Oyster Creek2018Q2GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000250/FIN-2018002-01Turkey Point2018Q2No CornerstoneUnit 3 Emergency Diesel Generator (EDG) Operability during Fuel Oil Transfer to Unit 4 Fuel Oil Storage TanksEmergency Diesel Generator
05000382/FIN-2018002-01Waterford2018Q2GreenMitigating SystemsH.1210 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V
Failure to Ensure Appropriate Chemistry Controls on the Component Cooling Water Heat Exchangers
05000461/FIN-2018002-04Clinton2018Q2Severity level MinorNo Cornerstone10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion II
Minor Violation
05000387/FIN-2018002-03Susquehanna2018Q2GreenMitigating SystemsP.3Technical SpecificationInadequate Justification for Deferral of Corrective Actions for certain Degraded Safety-Related Components
05000348/FIN-2018002-06Farley2018Q2GreenMitigating Systems10 CFR 50 Appendix B Criterion XILicensee-Identified Violation
05000346/FIN-2018002-04Davis Besse2018Q2GreenMitigating SystemsH.13Misapplication of the Operability Determination Process
05000282/FIN-2018011-01Prairie Island2018Q2GreenMitigating 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 Justify Load Combinations Used in Main Steam Piping Stress Analysis
05000336/FIN-2018410-01Millstone2018Q2GreenPhysical ProtectionH.110 CFR 73Security
05000457/FIN-2018002-01Braidwood2018Q2GreenMitigating SystemsH.910 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V
Inadequate Detail in Maintenance Work Instructions Resulted in Failed Gearbox Oil Cooler Head Gasket and Inoperable 2B Auxiliary Feedwater PumpAuxiliary Feedwater
05000416/FIN-2018002-03Grand Gulf2018Q2GreenMitigating Systems10 CFR 50 Appendix B Criterion III, Design ControlFailure to Adequately Test NUS Temperature SwitchReactor Core Isolation Cooling
05000324/FIN-2018002-02Brunswick2018Q2Severity level Enforcement DiscretionMitigating SystemsTechnical SpecificationEnforcement Action 18-080: Implementation of EGM 11-003, Revision 3, Enforcement Guidance Memorandum on Dispositioning Boiling Water Reactor Licensee Noncompliance with Technical Specification Containment Requirements during Operations with a Potential for Draining the Reactor Vessel (OPDRV)Secondary containment
05000244/FIN-2018403-01Ginna2018Q2GreenPhysical ProtectionH.1410 CFR 73Security
05000424/FIN-2018002-01Vogtle2018Q2GreenMitigating SystemsH.9Technical Specification - ProceduresFailure to Adequately Load Emergency Deisel Generator (EDG) During 24-Hour Endurance Test
05000458/FIN-2018012-07River Bend2018Q2Severity level IVNo Cornerstone10 CFR 50.59, Changes, Tests and ExperimentsFailure to Perform 10 CFR 50.59 Evaluation for Main Feedwater System Sparger Nozzle DamageFeedwater
05000445/FIN-2018002-03Comanche Peak2018Q2GreenMitigating Systems10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion XI
Failure to Incorporate Design Information Into System Test ProceduresMain Steam Isolation Valve
05000339/FIN-2018011-01North Anna2018Q2GreenMitigating SystemsTechnical SpecificationFailure to ensure compliance with the Technical Specification (TS) 5.4.1.a requirement relevant to procedures for plant fires
05000400/FIN-2018002-04Harris2018Q2GreenInitiating EventsH.12Technical Specification - ProceduresFailure to Implement Adequate Steam Generator Blowdown Demineralizer Control ProceduresSteam Generator
Feedwater
05000443/FIN-2018411-02Seabrook2018Q2GreenPhysical ProtectionH.310 CFR 73Security
05000387/FIN-2018002-01Susquehanna2018Q2GreenMitigating SystemsH.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
Control Structure Chiller Inoperability Due to Identified Refrigerant Leaks Not Corrected
05000416/FIN-2018002-08Grand Gulf2018Q2GreenBarrier IntegrityH.510 CFR 50 Appendix B Criterion XIPerformance of Surveillance Testing Following Maintenance on Containment Airlock
05000293/FIN-2018002-06Pilgrim2018Q2Severity level MinorNo Cornerstone10 CFR 50.73
10 CFR 50.9, Completeness and Accuracy of Information
Minor Violation
05000259/FIN-2018002-03Browns Ferry2018Q2TBDMitigating Systems10 CFR 50.48Failure to analyze for a Water Hammer event due to Spurious Operation of Residual Heat Removal Service Water (RHRSW) Valves during a Fire EventResidual Heat Removal Service Water
05000277/FIN-2018010-01Peach Bottom2018Q2GreenMitigating SystemsP.2PendingFailure to Identify Time-Critical ActionHigh Pressure Coolant Injection
05000482/FIN-2018002-03Wolf Creek2018Q2GreenInitiating EventsH.2Failure to Adequately Implement Instrumentation and Controls Surveillance Procedures
05000255/FIN-2018011-01Palisades2018Q2GreenMitigating SystemsTechnical SpecificationFailure to Maintain Adequate Fire Protection System Functional Test Procedure
05000454/FIN-2018410-01Byron2018Q2GreenPhysical Protection10 CFR 73Licensee-Identified Violation
05000530/FIN-2018002-03Palo Verde2018Q2GreenMitigating SystemsH.1310 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix B Criterion V
Failure to Assess the Operability of a Degraded or Nonconforming Structure, System, or ComponentSpray Pond
05000528/FIN-2018002-02Palo Verde2018Q2GreenOccupational Radiation SafetyH.410 CFR 20
10 CFR 20.1703
Failure to Implement and Maintain Procedures Regarding Breathing Air Quality
05000348/FIN-2018002-04Farley2018Q2GreenMitigating SystemsH.1010 CFR 50 Appendix B Criterion XVI, Corrective ActionFailure to implement timely corrective actions for charging pump discharge check valves
05000341/FIN-2018002-01Fermi2018Q2GreenInitiating EventsH.14Failure to Document a Condition Assessment Resolution Document for Reactor Recirculation Motor-Generator Set A Brush Gear Sparking
05000458/FIN-2018406-02River Bend2018Q2GreenPhysical Protection10 CFR 73Security
... further results