Licensee Event Report: Difference between revisions

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<th>[[:Category:Site|Site]]</th><th>#</th><th>[[:Category:Company|Company]]</th><th>Event lists</th>
<th>[[:Category:Site|Site]]</th><th>#</th><th>[[:Category:Company|Company]]</th><th>Event lists</th>
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|?Reporting criterion
|?Reporting criterion
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|?System
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Latest revision as of 19:59, 15 March 2020

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]
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]
Three Mile Island 0 Constellation [Three Mile Island 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
05000265/LER-2024-002-01, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent FailureQuad Cities30 October 202410 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Main Turbine
Control Rod
Safe Shutdown
Feedwater Heater
05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel GeneratorsBrowns Ferry29 October 202410 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Emergency Diesel Generator
Primary Containment Isolation System
Safe Shutdown
05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical FailureBrowns Ferry28 October 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSecondary containment
Standby Gas Treatment System
Safe Shutdown
Time of Discovery
Past operability
Probabilistic Risk Assessment
Temporary Modification
05000186/LER-2024-003, University of Missouri Research Reactor, Specification Deviation from Technical Specification 3.2.g.21University of Missouri-Columbia25 October 2024Reactor Protection System
05000400/LER-2024-001-01, Automatic Reactor Trip Due to Main Generator Lock-OutHarris23 October 202410 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Reactor Protection System
Emergency Diesel Generator
05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel AssembliesPrairie Island22 October 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsPast operability
05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety FunctionSouth Texas22 October 202410 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
05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance TestingWolf Creek22 October 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSteam Generator
Reactor Coolant System
Feedwater
Auxiliary Feedwater
Time of Discovery
05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge ValveWolf Creek21 October 202410 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
Steam Generator
Reactor Coolant System
Feedwater
Service water
Auxiliary Feedwater
Enforcement Discretion
Overspeed trip
Overspeed
05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety FunctionSouth Texas17 October 202410 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)
HVAC
Control Room Envelope
Boric Acid
Large early release frequency
05000327/LER-2024-001, Reactor Trip Due to a Turbine TripSequoyah17 October 202410 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(iv), System Actuation
Feedwater
Reactor Protection System
Auxiliary Feedwater
Safe Shutdown
05000395/LER-2024-002, Loss of Control Room Emergency Filtration SystemSummer15 October 2024Control Room Emergency Filtration System
05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment BoundaryMillstone14 October 202410 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Secondary containment
Primary containment
Main Steam
Foreign Material Exclusion
Integrated leak rate test
05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to ActuateLaSalle9 October 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsTime of Discovery
Offsite Circuit
05000445/LER-2024-002-01, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System FunctionsComanche Peak3 October 202410 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Emergency Diesel Generator
Remote shutdown
Control Rod
Safe Shutdown
Time of Discovery
Post Accident Monitoring
Past operability
Temporary Modification
05000483/LER-2024-002, Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications LimitingCallaway1 October 2024Emergency Diesel Generator
05000446/LER-2024-001-01, Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System ModificationsComanche Peak30 September 2024Steam Generator
Feedwater
Reactor Protection System
Auxiliary Feedwater
Main Turbine
Overspeed
05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical SpecificationsMillstone26 September 202410 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(viii)(A)
Reactor Coolant System
Feedwater
Residual Heat Removal
Emergency Core Cooling System
Decay Heat Removal
Stroke time
Time Critical Operator Action
Measurement Uncertainty Recapture
05000335/LER-2024-001, Unplanned Reactor ScramSaint Lucie25 September 2024Feedwater
Main Steam Isolation Valve
Auxiliary Feedwater
05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine TripSequoyah25 September 202410 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(iv), System Actuation
Feedwater
Reactor Protection System
Auxiliary Feedwater
Safe Shutdown
05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative RateNorth Anna24 September 202410 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Auxiliary Feedwater
Control Rod
Negative Flux Rate Trip
05000461/LER-2023-002-01, Reactor Core Isolation Cooling Inoperable Prior to Mode ChangeClinton24 September 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Core Isolation Cooling
High Pressure Core Spray
05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater PumpsSouth Texas19 September 202410 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)
10 CFR 50.73(a)(2)(iv)(B)(8)
Steam Generator
Reactor Coolant System
Reactor Protection System
Emergency Diesel Generator
Auxiliary Feedwater
Main Transformer
Shutdown Margin
Large early release frequency
Offsite Circuit
05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System GroundDavis Besse19 September 202410 CFR 50.73(a)(1), Submit an LER
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Emergency Diesel Generator
Auxiliary Feedwater
Time of Discovery
Offsite Circuit
05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel AssembliesPrairie Island16 September 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsPast operability
05000318/LER-2024-002, Automatic Reactor Trip Due to Main Turbine Loss of LoadCalvert Cliffs16 September 202410 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Main Turbine
05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear ReactorSusquehanna16 September 202410 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Mission time
Probabilistic Risk Assessment
05000316/LER-2024-002-01, Manual Reactor Trip Following Rapid Downpower for Steam LeakCook12 September 202410 CFR 50.73(a)(2)(iv)(A), System ActuationSteam Generator
Reactor Protection System
Auxiliary Feedwater
Main Turbine
Decay Heat Removal
Control Rod
Probabilistic Risk Assessment
Downpower
05000317/LER-2024-003, A Diesel Generator Inoperable Due to Potential Transformer FailureCalvert Cliffs6 September 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
Emergency Diesel GeneratorOperability Determination
05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay ActuationWatts Bar5 September 2024Feedwater
Reactor Protection System
Auxiliary Feedwater
Main Transformer
Safe Shutdown
Temporary Modification
05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) SupplementHope Creek5 September 202410 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
Primary containment
05000454/LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System InoperableByron5 September 2024Reactor Coolant System
05000277/LER-2024-003, Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser VacuumPeach Bottom5 September 202410 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Reactor Protection System
Primary Containment Isolation System
Primary containment
Main Turbine
Reactor Pressure Vessel
Emergency Core Cooling System
Main Condenser
05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control ValveVogtle5 September 202410 CFR 50.73(a)(2)(iv)(A), System ActuationSteam Generator
Feedwater
Reactor Protection System
Residual Heat Removal
Emergency Core Cooling System
05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment IsolationFitzPatrick4 September 202410 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)
Reactor Protection System
Primary Containment Isolation System
Primary containment
Reactor Building Ventilation
Reactor Water Cleanup
Standby Gas Treatment System
Main Steam Line
05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel GeneratorsSouth Texas29 August 202410 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv)(B)(1)
10 CFR 50.73(a)(2)(iv)(B)(8)
Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Emergency Diesel Generator
Auxiliary Feedwater
Main Transformer
HVAC
Residual Heat Removal
Emergency Core Cooling System
Control Room Envelope
Control Rod
Main Steam
Containment Spray
Shutdown Margin
Mission time
05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve FailureMonticello27 August 202410 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
Core Spray
Residual Heat Removal
Emergency Core Cooling System
Low Pressure Coolant Injection
05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined OperableGrand Gulf26 August 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsFeedwater
Primary containment
Control Rod
Past operability
05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser VacuumSusquehanna26 August 202410 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
High Pressure Coolant Injection
Reactor Protection System
Emergency Diesel Generator
Main Steam Isolation Valve
Reactor Core Isolation Cooling
Reactor Pressure Vessel
Residual Heat Removal
Spray Pond
Emergency Core Cooling System
Safety Relief Valve
Main Condenser
05000373/LER-2024-004-01, Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary TransformerLaSalle22 August 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel GeneratorTime of Discovery
Offsite Circuit
05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified LeakageCook22 August 2024Steam Generator
Reactor Coolant System
Auxiliary Feedwater
Packing leak
Probabilistic Risk Assessment
Operational leakage
05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed GasketFitzPatrick21 August 202410 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
Emergency Diesel GeneratorMission time
Temporary Leak Repair
05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat WearSusquehanna21 August 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsMain Steam Isolation Valve
Main Steam Line
Main Steam
Local Leak Rate Testing
05000530/LER-2024-001-01, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification ViolationPalo Verde21 August 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
Shutdown Cooling
05000339/LER-2024-001-01, Loss of Generator Field for 2J Eog During 2-PT-82.28North Anna20 August 202410 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel Generator
05000318/LER-2024-001-01, Manual Reactor Trip Due to 22 Steam Generator Feed Pump TripCalvert Cliffs20 August 202410 CFR 50.73(a)(2)(iv)(A), System ActuationSteam Generator
Feedwater
Reactor Protection System
Auxiliary Feedwater
Main Condenser
05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning StrikeWaterford15 August 2024Steam Generator
Reactor Coolant System
Reactor Protection System
Emergency Core Cooling System
Emergency Feedwater System
Safe Shutdown
05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown RodVogtle9 August 202410 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection SystemSafe Shutdown
Shutdown Margin
05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction SignalVogtle6 August 202410 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Main Condenser
Control Rod
05000389/LER-2024-003, Unplanned Reactor ScramSaint Lucie5 August 202410 CFR 50.73(a)(2)(iv)(A), System ActuationLoss of condenser vacuum
... further results