Licensee Event Report

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If a criteria is reached according to NUREG-1022 then a Licensee to the NRC must submit a Licensee Event Report to explain what happened.

Reporting Criteria

Writing LERs

Explain exactly what happened during the entire event or condition, including how systems,components, and operating personnel performed. Do not cover specific hardware problems in excessive detail. Describe unique characteristics of a plant as well as other characteristics that influenced the event (favorably or unfavorably).

  • Avoid using plant-unique terms and abbreviations, or, as a minimum, clearly define them.
    • The audience for LERs is large and does not necessarily know the details of each plant.
  • Include the root causes, the plant status before the event, and the sequence of occurrences.
  • Describe the event from the perspective of the Operator (i.e., what the operator saw, did, perceived, understood, or misunderstood).
  • If several systems actuate during an event, describe all aspects of the complete event, including all actuations sequentially, and those aspects that by themselves would not be reportable.
    • For example, if a single component failure (generally not reportable) occurs following a reactor scram (reportable), describe the component failure in the narrative of the LER for the reactor scram.
  • It is necessary to discuss the performance and status of equipment.
  • Paraphrase pertinent sections of the latest submitted Safety analysis report (SAR) rather than referencing them because not all organizations or individuals have access to SARs.
  • Extensive cross-referencing would be time consuming considering the large number of LERs and reviewers that read each LER.
  • Ensure that each component's safety-significant effect on the event or condition is clearly and completely described.
  • Do not use statements such as "this event is not significant with respect to the health and safety of the public" without explaining the basis for the conclusion.

Specific information that should be included, as appropriate, is described in paragraphs 50.73(b).

Submissions of LERs

Section 50.73(d) of the NUREG-1022 states that submmissions must be done with Form NRC 366 as described by section 50.4. Submissions are to be done within 60 days of the event. If that happens to be a weekend or a holiday then it must be the next working day. If a Licensee knows that a report will be late or needs an additional day or so to complete the report, the situation should be discussed with the appropriate NRC regional office. See Section 2.5 for further discussion of discovery date.


LER Forwarding Letter and Cancellations

The cover letter forwarding an LER to the NRC should be signed by a responsible official. There is no prescribed format for the letter. The date the letter is issued and the report date should be the same. Licensees are encouraged to include the NRC resident inspector and the Institute of Nuclear Power Operations (INPO) in their distribution. Multiple LERs can be forwarded by one forwarding letter. Cancellations of LERs submitted should be made by letter. The letter should state that the LER is being canceled (i.e., formally withdrawn). The bases for the cancellation should be explained so that the staff can understand and review the reasons supporting the determination. The notice of cancellation will be filed and stored with the LER and acknowledgement made in various automated data systems. The LER will be removed from the LER data base.


Voluntary LERs

Indicate information-type LERS (i.e., Voluntary LERs) by checking the "Other" block in Item 11 of the LER form and type "Voluntary Report" in the space immediately below the block. Also give a sequential LER number to the voluntary report as noted in Section 5.2.4(5). Because not all requirements of 50.73(b), "Contents," may pertain to some voluntary reports, licensees should develop the content of such reports to best present the information associated with the situation being reported. See Section 2.7 for additional discussion of Voluntary LERs.

How To Find LERs

See also

LER list

by site

1 year

Site#CompanyEvent lists
Almaraz 0 Iberdrola [Almaraz events] [RSS]
Arkansas Nuclear 0 Entergy [Arkansas Nuclear events] [RSS]
Asco 0 Endesa [Asco events] [RSS]
Beaver Valley 0 Vistra [Beaver Valley events] [RSS]
Belleville 0 Électricité de France [Belleville events] [RSS]
Big Rock Point 0 Consumers Energy [Big Rock Point events] [RSS]
Blayais 0 Électricité de France [Blayais events] [RSS]
Braidwood 0 Constellation [Braidwood events] [RSS]
Browns Ferry 0 Tennessee Valley Authority [Browns Ferry events] [RSS]
Brunswick 0 Duke Energy [Brunswick events] [RSS]
Byron 0 Constellation [Byron events] [RSS]
Callaway 0 Ameren [Callaway events] [RSS]
Calvert Cliffs 0 Constellation [Calvert Cliffs events] [RSS]
Catawba 0 Duke Energy [Catawba events] [RSS]
Chernobyl 0 [Chernobyl events] [RSS]
Clinch River 0 [Clinch River events] [RSS]
Clinton 0 Constellation [Clinton events] [RSS]
Cofrentes 0 Iberdrola [Cofrentes events] [RSS]
Columbia 0 Energy Northwest [Columbia events] [RSS]
Comanche Peak 0 Luminant [Comanche Peak events] [RSS]
Cook 0 American Electric Power [Cook events] [RSS]
Cooper 0 Entergy [Cooper events] [RSS]
Crane 0 Constellation [Crane events] [RSS]
Crystal River 0 Duke Energy [Crystal River events] [RSS]
Dampierre 0 Électricité de France [Dampierre events] [RSS]
Davis Besse 0 Cleveland Electric [Davis Besse events] [RSS]
Diablo Canyon 0 Pacific Gas & Electric [Diablo Canyon events] [RSS]
Dresden 0 Constellation [Dresden events] [RSS]
Duane Arnold 0 NextEra Energy [Duane Arnold events] [RSS]
Dungeness 0 EDF Energy [Dungeness events] [RSS]
Elk River 0 [Elk River events] [RSS]
Farley 0 Southern Nuclear [Farley events] [RSS]
Fermi 0 DTE Energy [Fermi events] [RSS]
FitzPatrick 0 Constellation [FitzPatrick events] [RSS]
Flamanville 0 Électricité de France [Flamanville events] [RSS]
Fort Calhoun 0 Omaha Public Power District [Fort Calhoun events] [RSS]
Fort Saint Vrain 0 Xcel Energy [Fort Saint Vrain events] [RSS]
Fukushima Dai-Ichi 0 TEPCO [Fukushima Dai-Ichi events] [RSS]
Ginna 0 Constellation [Ginna events] [RSS]
Grand Gulf 0 Entergy [Grand Gulf events] [RSS]
Haddam Neck 0 Connecticut Yankee Atomic Power Co [Haddam Neck events] [RSS]
Hallam 0 [Hallam events] [RSS]
Harris 0 Duke Energy [Harris events] [RSS]
Hartlepool 0 EDF Energy [Hartlepool events] [RSS]
Hatch 0 Southern Nuclear [Hatch events] [RSS]
Heysham 0 EDF Energy [Heysham events] [RSS]
Hinkley Point 0 EDF Energy [Hinkley Point events] [RSS]
Hope Creek 0 PSEG [Hope Creek events] [RSS]
Humboldt Bay 0 Pacific Gas and Electric [Humboldt Bay events] [RSS]
Hunterston 0 EDF Energy [Hunterston events] [RSS]
Indian Point 0 Entergy [Indian Point events] [RSS]
Jose Cabrera 0 Enresa [Jose Cabrera events] [RSS]
Kemmerer 0 TerraPower [Kemmerer events] [RSS]
Kewaunee 0 Dominion [Kewaunee events] [RSS]
Khmelnytskyi 0 Energoatom [Khmelnytskyi events] [RSS]
La Crosse 0 Dairyland Power Cooperative [La Crosse events] [RSS]
LaSalle 0 Constellation [LaSalle events] [RSS]
Lee 0 Duke Energy [Lee events] [RSS]
Limerick 0 Constellation [Limerick events] [RSS]
Maine Yankee 0 Maine Yankee [Maine Yankee events] [RSS]
McGuire 0 Duke Energy [McGuire events] [RSS]
Millstone 0 Dominion [Millstone events] [RSS]
Monticello 0 Xcel Energy [Monticello events] [RSS]
Nine Mile Point 0 Constellation [Nine Mile Point events] [RSS]
Nogent 0 Électricité de France [Nogent events] [RSS]
North Anna 0 Dominion [North Anna events] [RSS]
Oconee 0 Duke Energy [Oconee events] [RSS]
Olkiluoto 0 Teollisuuden Voima [Olkiluoto events] [RSS]
Oyster Creek 0 Holtec [Oyster Creek events] [RSS]
Palisades 0 Entergy [Palisades events] [RSS]
Palo Verde 0 Arizona Public Service [Palo Verde events] [RSS]
Parr 0 [Parr events] [RSS]
Peach Bottom 0 Constellation [Peach Bottom events] [RSS]
Perry 0 FirstEnergy [Perry events] [RSS]
Pilgrim 0 Holtec [Pilgrim events] [RSS]
Point Beach 0 NextEra Energy [Point Beach events] [RSS]
Prairie Island 0 Xcel Energy [Prairie Island events] [RSS]
Quad Cities 0 Constellation [Quad Cities events] [RSS]
Rancho Seco 0 Sacramento Municipal Utility District [Rancho Seco events] [RSS]
River Bend 0 Entergy [River Bend events] [RSS]
Rivne 0 Energoatom [Rivne events] [RSS]
Robinson 0 Duke Energy [Robinson events] [RSS]
Saint Lucie 0 NextEra Energy [Saint Lucie events] [RSS]
Salem 0 PSEG [Salem events] [RSS]
San Onofre 0 Southern California Edison [San Onofre events] [RSS]
Santa Maria De Garona 0 Nuclenor [Santa Maria De Garona events] [RSS]
Saxton 0 GPU Nuclear [Saxton events] [RSS]
Seabrook 0 NextEra Energy [Seabrook events] [RSS]
Sequoyah 0 Tennessee Valley Authority [Sequoyah events] [RSS]
Shippingport 0 [Shippingport events] [RSS]
Shoreham 0 Long Island Lighting Company [Shoreham events] [RSS]
Sizewell 0 EDF Energy [Sizewell events] [RSS]
South Texas 0 STP Nuclear Operating Company [South Texas events] [RSS]
South Ukraine 0 Energoatom [South Ukraine events] [RSS]
Summer 0 South Carolina Electric & Gas Company [Summer events] [RSS]
Sundesert 0 San Diego Gas & Electric Compnay [Sundesert events] [RSS]
Surry 0 Dominion [Surry events] [RSS]
Susquehanna 0 Talen Energy [Susquehanna events] [RSS]
Taishan 0 China Guangdong Nuclear Power Group [Taishan events] [RSS]
Trillo 0 Iberdrola [Trillo events] [RSS]
Trojan 0 Portland General Electric [Trojan events] [RSS]
Turkey Point 0 NextEra Energy [Turkey Point events] [RSS]
Vandellos 0 Endesa [Vandellos events] [RSS]
Vermont Yankee 0 NorthStar Vermont Yankee [Vermont Yankee events] [RSS]
Victoria 0 Exelon [Victoria events] [RSS]
Vogtle 0 Southern Nuclear [Vogtle events] [RSS]
Waterford 0 Entergy [Waterford events] [RSS]
Watts Bar 0 Tennessee Valley Authority [Watts Bar events] [RSS]
Wolf Creek 0 Wolf Creek Nuclear Operating Corporation [Wolf Creek events] [RSS]
Yankee Rowe 0 [Yankee Rowe events] [RSS]
Zaporizhzhia 0 Enerhodar [Zaporizhzhia events] [RSS]
Zion 0 ZionSolutions [Zion events] [RSS]
 SiteStart dateReporting criterionSystemTopic
05000263/LER-2024-002-01, Low Pressure Coolant Injection Inoperable Due to Motor Valve FailureMonticello30 May 202510 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Core Spray
Residual Heat Removal
Emergency Core Cooling System
Low Pressure Coolant Injection
Probabilistic Risk Assessment
Large early release frequency
05000296/LER-2025-001-01, Automatic Reactor Scram Following Main Generator TripBrowns Ferry29 May 202510 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Emergency Diesel Generator
Primary Containment Isolation System
05000382/LER-2025-002, Auxiliary Pressurizer Spray Train Inoperable Resulting in a Condition Prohibited by Technical SpecificationsWaterford29 May 202510 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B)
Reactor Coolant SystemPast operability
05000339/LER-2025-001, Reactor Trip Breakers Opened Due to High Vibes on 2-RC-P-1BNorth Anna28 May 202510 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Control Rod
05000364/LER-2025-002, Two Pressurizer Safety Valves Lift Pressure Outside of Technical Specifications Limits Due to Setpoint DriftFarley23 May 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
Emergency Core Cooling System
Time of Discovery
05000382/LER-2025-001, Inoperability of Startup Transformer a Results in a Condition Prohibited by Technical SpecificationsWaterford23 May 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel GeneratorSafe Shutdown
Foreign Material Exclusion
Offsite Circuit
Skill of the craft
05000251/LER-2025-001-01, Degraded ConditionTurkey Point23 May 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
Reactor Coolant SystemBoric Acid
05000366/LER-2025-002, A Emergency Diesel Generator Inoperable Due to Inadvertent Overspeed TripHatch23 May 202510 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Service water
Emergency Diesel Generator
Overspeed trip
Overspeed
05000528/LER-2025-001, Unit 1 Loss of High Pressure Safety Injection Safety FunctionPalo Verde22 May 2025
05000440/LER-2025-001, Automatic Actuation of Division 3 Diesel Generator Resulting from Startup Transformer TestingPerry21 May 202510 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(iv)(B)(8)
Service water
Emergency Diesel Generator
High Pressure Core Spray
Residual Heat Removal
Emergency Core Cooling System
Decay Heat Removal
Fuel cladding
05000263/LER-2025-001, Automatic Reactor Scram on Low Water LevelMonticello16 May 2025
05000315/LER-2025-001, Two Main Steam Safety Valves Failed Setpoint TestingCook15 May 2025Main Steam Safety Valve
05000416/LER-2025-002, Automatic Emergency Diesel Generator Actuation Caused by Grid TransientGrand Gulf13 May 2025Emergency Diesel Generator
05000499/LER-2024-002-01, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety FunctionSouth Texas12 May 202510 CFR 50.73(a)(2)(v), Loss of Safety FunctionHVAC
Control Room Envelope
05000254/LER-2025-003, Main Steam Isolation Valves Local Leak Rate Test Exceed Technical Specification LimitsQuad Cities9 May 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsMain Steam Isolation Valve
Primary containment
Main Steam Line
Main Steam
05000251/LER-2025-002, Emergency Diesel Generator ActuationTurkey Point9 May 202510 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel GeneratorSafe Shutdown
Loss of Offsite Power
05000353/LER-2025-001, HPCI Valve Isolated During a Surveillance Test Due to a Degraded Test ConnectorLimerick2 May 202510 CFR 50.73(a)(2)(v), Loss of Safety FunctionHigh Pressure Coolant Injection
Primary containment
Core Spray
Residual Heat Removal
Automatic Depressurization System
Emergency Core Cooling System
Test box
05000324/LER-2025-001, Automatic Actuation of Containment Isolation Valves During TestingBrunswick1 May 202510 CFR 50.73(a)(2)(iv)(A), System ActuationMain Steam Isolation Valve
Primary Containment Isolation System
Primary containment
Main Condenser
05000296/LER-2024-004-01, Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore PipingBrowns Ferry24 April 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant SystemPressure Boundary Leakage
Unidentified leakage
05000352/LER-2025-001, Bypass Leakage on the B Train of Standby Gas Treatment System HEPA Filters Exceeded Technical Specification ValueLimerick21 April 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsStandby Gas Treatment System
05000269/LER-2025-001, Inoperability of Keowee Hydroelectric Unit Due to Legacy Deficiencies in Generator Exceiter Speed Switch Calibration Procedure Resulting in a Condition Prohibited by Technical SpecificationsOconee21 April 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
Service water
Probabilistic Risk Assessment
05000366/LER-2025-001, Primary Containment Inoperable Due to Exceeding Technical Specification Allowable Leakage LimitsHatch17 April 202510 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
Primary containmentLocal Leak Rate Testing
Large early release frequency
05000416/LER-2025-001, Manual Scram Due to Degraded Condenser VacuumGrand Gulf16 April 202510 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Emergency Diesel Generator
Control Rod
05000327/LER-2024-001-01, Reactor Trip Due to a Turbine TripSequoyah9 April 202510 CFR 50.73(a)(2)(iv), System ActuationReactor Protection System
Auxiliary Feedwater
05000327/LER-2024-002-01, Treactor Trip Due to a Turbine TripSequoyah9 April 202510 CFR 50.73(a)(2)(iv), System ActuationReactor Protection System
Auxiliary Feedwater
05000296/LER-2025-001, Automatic Reactor Scram Following Main Generator TripBrowns Ferry9 April 202510 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Emergency Diesel Generator
Primary Containment Isolation System
05000335/LER-2025-001-01, Safety Injection Tank Above Technical Specifications LimitSaint Lucie8 April 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000498/LER-2025-001, Two Inoperable Emergency Core Cooling System Trains Resulting in Potential Loss of Safety FunctionSouth Texas7 April 202510 CFR 50.73(a)(2)(v), Loss of Safety FunctionHVAC
Emergency Core Cooling System
Control Room Envelope
05000395/LER-2025-001, (Vcsns), Manual Reactor Trip Due to Unisolable EHC LeakSummer7 April 202510 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Main Turbine
Emergency Feedwater System
Through-Wall Leak
05000412/LER-2025-001, Automatic Reactor Trip and Automatic Actuation of the Auxiliary Feedwater System Due to Loose Feedback Linkage on Feedwater Regulating ValveBeaver Valley1 April 202510 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(iv)(B)(6)
10 CFR 50.73(a)(2)(iv)(B)(1)
Steam Generator
Feedwater
Reactor Protection System
Auxiliary Feedwater
Main Steam
Large early release frequency
05000413/LER-2025-001, Plant Shutdown Required by Technical Specifications Due to Unidentified Reactor Coolant System LeakageCatawba31 March 202510 CFR 50.73(a)(1), Submit an LER
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
Reactor Coolant SystemAging Management
License Renewal
Pressure Boundary Leakage
Unidentified leakage
Operational leakage
05000254/LER-2025-002, Control Room Emergency Ventilation Air Conditioning System Inoperable Due to Logic IssueQuad Cities27 March 202510 CFR 50.73(a)(2)(v), Loss of Safety FunctionHVAC
Control Room Emergency Ventilation
Control Room Envelope
05000316/LER-2024-004-01, AB Emergency Diesel Generator Inoperable for Longer than Allowed by Technical SpecificationsCook27 March 202510 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Service water
Emergency Diesel Generator
Mission time
Probabilistic Risk Assessment
Large early release frequency
05000335/LER-2025-001, Safety Injection Tank Above Technical Specification LimitsSaint Lucie26 March 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000328/LER-2024-001-01, Reactor Trip Due to an Electrical Trouble Turbine Trip, Update LetterSequoyah26 March 202510 CFR 50.73(a)(2)(iv), System ActuationReactor Protection System
Auxiliary Feedwater
05000336/LER-2024-002-01, For Millstone, Unit 2, Two Main Steam Safety Valves Failed to Lift within the Acceptance Criteria Resulting in a Condition Prohibited by Technical SpecificationsMillstone20 March 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSteam Generator
Main Steam Safety Valve
Decay Heat Removal
Control Rod
Main Steam
Loss of Offsite Power
05000390/LER-2025-002, Automatic Reactor Trip Due to Main Turbine TripWatts Bar18 March 2025Feedwater
Reactor Protection System
Auxiliary Feedwater
05000338/LER-2024-003-01, Loss of Offsite Power Train a Relay Failure During Surveillance TestingNorth Anna18 March 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsAuxiliary FeedwaterLoss of Offsite Power
05000328/LER-2025-001, Reactor Trip Breakers Opened Due to Group 2 of Control Rod Bank D Failing to WithdrawSequoyah11 March 202510 CFR 50.73(b)(3)(iv)(A)Reactor Protection System
Control Rod
05000254/LER-2025-001, Technical Specification 3.6.4.2 Action Not Performed Due to Tagout Boundary Placement ErrorQuad Cities7 March 2025Secondary containment
Primary containment
Reactor Building Ventilation
05000250/LER-2024-003-01, Condition Prohibited by Technical SpecificationsTurkey Point6 March 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000390/LER-2025-001, Loss of the Control Room Emerency Air Temperature Control System Due to Chiller Oil MigrationWatts Bar3 March 202510 CFR 50.73(a)(2)(v), Loss of Safety FunctionControl Room Emergency Air Temperature Control System
05000440/LER-2024-004, Division 3 Diesel Generator Inoperable Due to Low Output Voltage Resulting in Loss of Safety FunctionPerry24 February 202510 CFR 50.73(a)(2)(v), Loss of Safety FunctionReactor Core Isolation Cooling
High Pressure Core Spray
Probabilistic Risk Assessment
Fuel cladding
05000298/LER-2024-003-01, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical SpecificationsCooper20 February 202510 CFR 50.73(a)(2)(v), Loss of Safety FunctionHigh Pressure Coolant Injection
Core Spray
Emergency Core Cooling System
Main Condenser
Low Pressure Coolant Injection
High Energy Line Break
Flow Accelerated Corrosion
Through-Wall Leak
05000446/LER-2024-002-01, Turbine Driven Auxiliary Feedwater Pump Unavailable Following Transition from Mode 4 to Mode 3Comanche Peak13 February 202510 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Steam Generator
Reactor Coolant System
Feedwater
Auxiliary Feedwater
Residual Heat Removal
Loss of Offsite Power
05000338/LER-2024-002-01, Ih EDG Failure to Achieve Rated Speed / Frequency During Surveillance TestingNorth Anna12 February 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel Generator
Auxiliary Feedwater
Loss of Offsite Power
05000313/LER-2024-002, ANO Unit 1 Inoperable Containment Isolation BoundaryArkansas Nuclear6 February 202510 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Unanalyzed Condition
Time of Discovery
Probabilistic Risk Assessment
Large early release frequency
05000364/LER-2025-001, Joseph Farley, Unit 2, Containment Isolation Valve Inoperable for Longer than Allowed by Technical SpecificationsFarley5 February 202510 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
05000250/LER-2024-004, Unplanned Reactor ScramTurkey Point31 January 2025Reactor Protection System
Auxiliary Feedwater
05000395/LER-2024-002-01, (Vcsns), Unit 1, Loss of Control Room Emergency Filtration SystemSummer28 January 2025Control Room Emergency Filtration System
... further results