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 SiteStart dateTitleDescription
05000454/LER-2024-002, Reactor Vessel Closure Head Penetration 31 DegradedByron7 November 2024Reactor Vessel Closure Head Penetration 31 Degraded
05000269/LER-2022-001-01, Ultrasonic Examination Indication Identifies Degraded Reactor Coolant System Pressure BoundaryOconee7 November 2024Ultrasonic Examination Indication Identifies Degraded Reactor Coolant System Pressure Boundary
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 2024Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
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 2024Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps
05000454/LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System InoperableByron5 September 2024Both Trains of Control Room Ventilation Temperature Control System Inoperable
05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel GeneratorsSouth Texas29 August 2024Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators
05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified LeakageCook22 August 2024Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage
05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning StrikeWaterford15 August 2024Automatic Reactor Trip Due to Lightning Strike
05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction SignalVogtle6 August 2024Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal
05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater ActuationOconee2 August 2024Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation
05000440/LER-2024-003, Technical Specification Required Shutdown Due to Increase in RCS Unidentified LeakagePerry15 July 2024Technical Specification Required Shutdown Due to Increase in RCS Unidentified Leakage
05000456/LER-2024-001, Trip on Low Steam Generator Level Ddue to Failure to Verify Isolation Valves Were OpenBraidwood3 July 2024Trip on Low Steam Generator Level Ddue to Failure to Verify Isolation Valves Were Open
05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel GeneratorsSouth Texas2 July 2024Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators
05000313/LER-2024-001, Source Range Nuclear Instrument Failure Resulting in Condition Prohibited by Technical SpecificationsArkansas Nuclear1 July 2024Source Range Nuclear Instrument Failure Resulting in Condition Prohibited by Technical Specifications
05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution PanelFarley19 June 2024Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel
05000373/LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary TransformerLaSalle19 June 2024Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer
05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint DriftFarley17 June 2024Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift
05000416/LER-2024-002, Automatic Actuation of Reactor Protection SystemGrand Gulf28 May 2024Automatic Actuation of Reactor Protection System
05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical SpecificationsMillstone20 May 2024Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
05000373/LER-2024-002, Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker TripLaSalle17 May 2024Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip
05000382/LER-2024-002, Automatic Reactor Trip Due to Transformer FailureWaterford16 May 2024Automatic Reactor Trip Due to Transformer Failure
05000272/LER-2024-001, Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat ExchangerSalem9 May 2024Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger
05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LOWatts Bar6 May 2024Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO
05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical SpecificationsMillstone2 May 2024Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong ComponentMonticello25 April 2024Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component
05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution PanelFarley15 April 2024For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel
05000483/LER-2024-001, Reactor Trip Due to Turbine TripCallaway4 April 2024Reactor Trip Due to Turbine Trip
05000364/LER-2024-001, Manual Reactor Trip Due to Rising Steam Generator LevelsFarley11 January 2024Manual Reactor Trip Due to Rising Steam Generator Levels
05000423/LER-2023-004, For Millstone Power Station, Unit 3 Regarding Reactor Coolant System Pressure Isolation Valves Operational Leakage Exceeded the Acceptance Criteria Resulting in a Condition Prohibited by Technical SpecificationsMillstone19 December 2023For Millstone Power Station, Unit 3 Regarding Reactor Coolant System Pressure Isolation Valves Operational Leakage Exceeded the Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications
05000528/LER-2023-002, Reactor Coolant System Degraded Pressure BoundaryPalo Verde8 December 2023Reactor Coolant System Degraded Pressure Boundary
05000423/LER-2023-003, RCS Temperature Detector Exceeded Time Response Acceptance Criteria Resulting in a Condition Prohibited by Technical SpecificationsMillstone8 December 2023RCS Temperature Detector Exceeded Time Response Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications
05000364/LER-2023-003, Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications LimitsFarley7 December 2023Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits
05000458/LER-2023-003-01, Drywell Atmosphere Radiation Monitor Particulate and Gaseous Channels Inoperable Due to Out of Tolerance Conversion FactorsRiver Bend15 November 2023Drywell Atmosphere Radiation Monitor Particulate and Gaseous Channels Inoperable Due to Out of Tolerance Conversion Factors
05000454/LER-2023-001-01, A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J and 0PR32JByron12 October 2023A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J and 0PR32J
05000364/LER-2023-001, Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications LimitsFarley28 September 2023Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits
05000260/LER-2023-001-01, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue FailureBrowns Ferry18 September 2023Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue Failure
05000458/LER-2023-003, Drywell Atmosphere Radiation Monitor Particulate and Gaseous Channels Inoperable Due to Out of Tolerance Conversion FactorsRiver Bend14 September 2023Drywell Atmosphere Radiation Monitor Particulate and Gaseous Channels Inoperable Due to Out of Tolerance Conversion Factors
05000455/LER-2022-001-01, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion CrackingByron31 August 2023Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking
05000336/LER-2023-002, Failed Check Valve Resulted in an Unanalyzed ConditionMillstone31 August 2023Failed Check Valve Resulted in an Unanalyzed Condition
05000261/LER-2023-002, Plant Trip During Reactor Protection System TestingRobinson17 August 2023Plant Trip During Reactor Protection System Testing
05000296/LER-2022-003-01, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue FailureBrowns Ferry31 July 2023Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure
05000412/LER-2023-002, Automatic Actuation of Auxiliary Feedwater SystemBeaver Valley12 July 2023Automatic Actuation of Auxiliary Feedwater System
05000298/LER-2022-002-01, Manual Core Spray Injection to Restore Skimmer Surge Tank LevelCooper29 June 2023Manual Core Spray Injection to Restore Skimmer Surge Tank Level
05000412/LER-2023-001, Indications Identified During Reactor Vessel Head InspectionBeaver Valley16 June 2023Indications Identified During Reactor Vessel Head Inspection
05000250/LER-2023-001, RCS Pressure Boundary DegradedTurkey Point14 June 2023RCS Pressure Boundary Degraded
05000313/LER-2023-002, Reactor Protection System Underpower Relay Test Failure Resulting in Condition Prohibited by Technical SpecificationsArkansas Nuclear9 June 2023Reactor Protection System Underpower Relay Test Failure Resulting in Condition Prohibited by Technical Specifications
05000454/LER-2023-001, A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J and 0PR032JByron15 May 2023A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J and 0PR032J
05000382/LER-2023-002, Plant Shutdown Required by Technical Specifications for Unidentified Reactor Coolant System Leakage in ContainmentWaterford9 May 2023Plant Shutdown Required by Technical Specifications for Unidentified Reactor Coolant System Leakage in Containment
05000260/LER-2023-001, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain LineBrowns Ferry19 April 2023Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line
05000333/LER-2023-001, Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam SystemFitzPatrick19 April 2023Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System
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