WEEKMONTHYEAR05000265/LER-2024-002-01, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-10-300Start date: 30 October 2024 Site: Quad Cities Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-290Start date: 29 October 2024 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000400/LER-2024-001-01, Automatic Reactor Trip Due to Main Generator Lock-Out2024-10-230Start date: 23 October 2024 Site: Harris Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-170Start date: 17 October 2024 Site: Sequoyah Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-250Start date: 25 September 2024 Site: Sequoyah Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation 05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative Rate2024-09-240Start date: 24 September 2024 Site: North Anna Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-190Start date: 19 September 2024 Site: South Texas Reporting criterion: 10 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) 05000318/LER-2024-002, Automatic Reactor Trip Due to Main Turbine Loss of Load2024-09-160Start date: 16 September 2024 Site: Calvert Cliffs Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000316/LER-2024-002-01, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-120Start date: 12 September 2024 Site: Cook Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000277/LER-2024-003, Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum2024-09-050Start date: 5 September 2024 Site: Peach Bottom Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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 Valve2024-09-050Start date: 5 September 2024 Site: Vogtle Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-040Start date: 4 September 2024 Site: FitzPatrick Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2) 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-290Start date: 29 August 2024 Site: South Texas Reporting criterion: 10 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) 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-260Start date: 26 August 2024 Site: Susquehanna Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000318/LER-2024-001-01, Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip2024-08-200Start date: 20 August 2024 Site: Calvert Cliffs Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-090Start date: 9 August 2024 Site: Vogtle Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-060Start date: 6 August 2024 Site: Vogtle Reporting criterion: 10 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) 05000389/LER-2024-003, Unplanned Reactor Scram2024-08-050Start date: 5 August 2024 Site: Saint Lucie Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation2024-08-020Start date: 2 August 2024 Site: Oconee Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-300Start date: 30 July 2024 Site: Surry Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate2024-07-250Start date: 25 July 2024 Site: North Anna Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000265/LER-2024-002, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-07-220Start date: 22 July 2024 Site: Quad Cities Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000400/LER-2024-001, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-220Start date: 22 July 2024 Site: Harris Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000382/LER-2024-003, Automatic EFAS Actuation During Surveillance Test2024-07-100Start date: 10 July 2024 Site: Waterford Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000456/LER-2024-001, Trip on Low Steam Generator Level Ddue to Failure to Verify Isolation Valves Were Open2024-07-030Start date: 3 July 2024 Site: Braidwood Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv)(B)(6) 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-020Start date: 2 July 2024 Site: South Texas Reporting criterion: 10 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) 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator2024-06-250Start date: 25 June 2024 Site: Palo Verde Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(v), Loss of Safety Function 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-240Start date: 24 June 2024 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2) 05000373/LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer2024-06-190Start date: 19 June 2024 Site: LaSalle Reporting criterion: 10 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), Loss of Safety Function, 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)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(viii)(B) 05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-190Start date: 19 June 2024 Site: Farley Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-110Start date: 11 June 2024 Site: Beaver Valley Reporting criterion: 10 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) 05000352/LER-2024-002, Invalid Actuation Due to a Trip of 1B Reactor Protection System Circuit Breaker2024-06-100Start date: 10 June 2024 Site: Limerick Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000458/LER-2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String2024-06-040Start date: 4 June 2024 Site: River Bend Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000416/LER-2024-002, Automatic Actuation of Reactor Protection System2024-05-280Start date: 28 May 2024 Site: Grand Gulf Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater2024-05-230Start date: 23 May 2024 Site: Palo Verde Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(v), Loss of Safety Function 05000373/LER-2024-002, Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip2024-05-170Start date: 17 May 2024 Site: LaSalle Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000382/LER-2024-002, Automatic Reactor Trip Due to Transformer Failure2024-05-160Start date: 16 May 2024 Site: Waterford Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000265/LER-2024-001, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing2024-05-100Start date: 10 May 2024 Site: Quad Cities Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000321/LER-2024-002, Manual Reactor Trip Due to Loss of Feedwater2024-05-090Start date: 9 May 2024 Site: Hatch Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000317/LER-2024-002, Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus2024-04-290Start date: 29 April 2024 Site: Calvert Cliffs Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-290Start date: 29 April 2024 Site: Prairie Island Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-250Start date: 25 April 2024 Site: Monticello Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 05000318/LER-2024-001, Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip2024-04-240Start date: 24 April 2024 Site: Calvert Cliffs Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000296/LER-2024-002, Breaker Trip Automatically Started an Emergency Diesel Generator2024-04-240Start date: 24 April 2024 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-150Start date: 15 April 2024 Site: Farley Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000318/LER-2023-004-01, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-04-120Start date: 12 April 2024 Site: Calvert Cliffs Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000325/LER-2024-002, Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization2024-04-100Start date: 10 April 2024 Site: Brunswick Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-270Start date: 27 March 2024 Site: Watts Bar Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000277/LER-2024-001, Automatic Reactor Scram Due to an Invalid Generator Lockout2024-03-210Start date: 21 March 2024 Site: Peach Bottom Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-210Start date: 21 March 2024 Site: Prairie Island Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000354/LER-2023-003-01, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-190Start date: 19 March 2024 Site: Hope Creek Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000391/LER-2023-003-01, Automatic Reactor Trip Due to Loss of Main Feedwater Regulating Valve Control2024-02-290Start date: 29 February 2024 Site: Watts Bar Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground2024-02-130Start date: 13 February 2024 Site: Grand Gulf Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(viii)(B) 05000354/LER-2023-003, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-02-120Start date: 12 February 2024 Site: Hope Creek Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000458/LER-2023-006, Automatic Reactor Scram Due to a Turbine Trip Following a Disconnect Failure at Switchyard2024-02-080Start date: 8 February 2024 Site: River Bend Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000528/LER-2023-003, Control Room Essential Filtration Actuation Signal (CREFAS) Actuation with Essential Spray Pond Pump Start2024-02-010Start date: 1 February 2024 Site: Palo Verde Reporting criterion: 10 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)(9) 05000499/LER-2023-002, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus2024-01-300Start date: 30 January 2024 Site: South Texas Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv)(B)(8) 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-300Start date: 30 January 2024 Site: Nine Mile Point Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000528/LER-2023-001-02, Reactor Trip Following a Main Turbine Trip2024-01-260Start date: 26 January 2024 Site: Palo Verde Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000458/LER-2023-005, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String2024-01-160Start date: 16 January 2024 Site: River Bend Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000364/LER-2024-001, Manual Reactor Trip Due to Rising Steam Generator Levels2024-01-110Start date: 11 January 2024 Site: Farley Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-01-090Start date: 9 January 2024 Site: Susquehanna Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000366/LER-2023-003, Manual Reactor Trip Due to Loss of Feedwater2023-12-190Start date: 19 December 2023 Site: Hatch Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2) 05000369/LER-1923-001, Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error2023-12-130Start date: 13 December 2023 Site: McGuire Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000250/LER-2023-004, Unplanned Automatic Scram During RPS Testing2023-12-130Start date: 13 December 2023 Site: Turkey Point Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000282/LER-2023-001, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2023-12-040Start date: 4 December 2023 Site: Prairie Island Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000265/LER-2023-001-01, Turbine Trip and Automatic Reactor Scram Due to High Moisture Separator Level2023-11-300Start date: 30 November 2023 Site: Quad Cities Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000275/LER-2023-001, Unit 1 Manual Reactor Trip at Low Power2023-11-270Start date: 27 November 2023 Site: Diablo Canyon Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000250/LER-2023-003, Grid Disturbance in Switchyard Causes Automatic Reactor Trip2023-11-200Start date: 20 November 2023 Site: Turkey Point Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000263/LER-2023-002, Reactor Scram and Containment Isolation Due to Valve Responses During Main Turbine Control Valve Testing2023-11-130Start date: 13 November 2023 Site: Monticello Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000529/LER-2023-001-01, Unit 2 Automatic Reactor Trip on Low Steam Generator Water Level Due to Degraded Feedwater Flow2023-11-090Start date: 9 November 2023 Site: Palo Verde Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000244/LER-2023-002, Overtemperature Delta Temperature Reactor Protection System and Auxiliary Feedwater System Actuations on Due to 100% Load Rejection Caused by Turbine Overspeed Circuit Card Failure2023-11-080Start date: 8 November 2023 Site: Ginna Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000424/LER-2023-002, Manual Reactor Trip Due to Failure of a Heater Drain Pump and Standby Condensate Pump2023-10-110Start date: 11 October 2023 Site: Vogtle Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000391/LER-2023-003, Automatic Reactor Trip Due to Loss of Main Feedwater Regulating Valve Control2023-10-030Start date: 3 October 2023 Site: Watts Bar Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05200025/LER-2023-006, Regarding Automatic Reactor Protection System Actuation During Startup Testing Due to Auto Reactive Power Regulator Being Active While in Island Mode Operation2023-09-190Start date: 19 September 2023 Site: Vogtle Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000528/LER-2023-001-01, Reactor Trip Following a Main Turbine Trip2023-09-130Start date: 13 September 2023 Site: Palo Verde Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05200025/LER-2023-005, Automatic Reactor Protection System Actuation During Startup Testing Due to Inadequate Turbine Trip Logic2023-09-060Start date: 6 September 2023 Site: Vogtle Reporting criterion: 10 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)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii) 05000391/LER-2023-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2023-08-240Start date: 24 August 2023 Site: Watts Bar Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000261/LER-2023-002, Plant Trip During Reactor Protection System Testing2023-08-170Start date: 17 August 2023 Site: Robinson Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000445/LER-2023-001, Automatic Reactor Trip Due to Lo-Lo Steam Generator Level2023-08-150Start date: 15 August 2023 Site: Comanche Peak Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(v), Loss of Safety Function 05000333/LER-2023-002-01, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2023-08-140Start date: 14 August 2023 Site: FitzPatrick Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2) 05000529/LER-2023-001, Regarding Unit 2 Automatic Reactor Trip on Low Steam Generator Water Level Due to Degraded Feedwater Flow2023-08-010Start date: 1 August 2023 Site: Palo Verde Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000423/LER-2023-001, Automatic Reactor Trip Due to Main Generator Output Breaker Ground Fault2023-07-270Start date: 27 July 2023 Site: Millstone Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000306/LER-2023-001, Gt/Xfmr Lockout Due to Failure of Lightning Arrester Caused Unit 2 Reactor Trip2023-07-180Start date: 18 July 2023 Site: Prairie Island Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000259/LER-2023-002, Full Reactor Scram Due to an Oscillation Power Range Monitor (OPRM) Confirmation Density Algorithm (CDA) Trip2023-07-170Start date: 17 July 2023 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000412/LER-2023-002, Automatic Actuation of Auxiliary Feedwater System2023-07-120Start date: 12 July 2023 Site: Beaver Valley Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000443/LER-2023-003, Reactor Protection System Manual Actuation Due to Failed Silicon Controlled Rectifiers2023-06-300Start date: 30 June 2023 Site: Seabrook Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(iv)(B)(1) 05000374/LER-2022-003-02, Manual Scram Due to Lsophase Bus Duct Fire Followed by 2A RPS Normal Power Supply Trip2023-06-160Start date: 16 June 2023 Site: LaSalle Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000325/LER-2023-001, Loss of Redundant Power Supply Operation Causes Turbine Trip and Subsequent Reactor Scram2023-06-150Start date: 15 June 2023 Site: Brunswick Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000333/LER-2023-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2023-06-130Start date: 13 June 2023 Site: FitzPatrick Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2) 05000443/LER-2023-001, Automatic Actuation of B Emergency Diesel Generator Emergency Power Sequencer2023-06-120Start date: 12 June 2023 Site: Seabrook Reporting criterion: 10 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) 05200025/LER-2023-003, Automatic Reactor Protection System Actuation During Startup Testing Due to Incorrect Turbine Control Valve Setting2023-06-080Start date: 8 June 2023 Site: Vogtle Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2) 05000528/LER-2023-001, Reactor Trip Following a Main Turbine Trip2023-06-070Start date: 7 June 2023 Site: Palo Verde Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000370/LER-2023-001, Manual Actuation of the Unit 2 Motor Driven Auxiliary Feedwater Pumps2023-05-310Start date: 31 May 2023 Site: Mcguire Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000395/LER-2023-001, Manual Reactor Trip Due to Loss of Main Feedwater Pump2023-05-300Start date: 30 May 2023 Site: Summer Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000366/LER-2023-002, Manual Scram Due to Trip of Both Reactor Recirculation Pumps2023-05-260Start date: 26 May 2023 Site: Hatch Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000374/LER-2021-002-02, Supplement to Reactor Protection System Half Scram Due to Motor Generator Set Output Breaker Trip2023-05-250Start date: 25 May 2023 Site: LaSalle Reporting criterion: 10 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)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(viii)(A) 05000387/LER-2023-001, Inadvertent Contact Between Relay Cover and Relay Trip Contacts Resulted in Automatic Actuation of the ‘B’ Emergency Diesel Generator2023-05-220Start date: 22 May 2023 Site: Susquehanna Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2) 05000298/LER-2022-004-01, 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open2023-05-110Start date: 11 May 2023 Site: Cooper Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation 05000333/LER-2023-001, Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System2023-04-190Start date: 19 April 2023 Site: FitzPatrick Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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