WEEKMONTHYEAR05000327/LER-2024-002-01, Treactor Trip Due to a Turbine Trip2025-04-090Start date: 9 April 2025 Site: Sequoyah Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 05000327/LER-2024-001-01, Reactor Trip Due to a Turbine Trip2025-04-090Start date: 9 April 2025 Site: Sequoyah Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 05000328/LER-2024-001-01, Reactor Trip Due to an Electrical Trouble Turbine Trip, Update Letter2025-03-260Start date: 26 March 2025 Site: Sequoyah Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 05000327/LER-2024-002, Reactor Trip Due to a Turbine Trip2024-11-200Start date: 20 November 2024 Site: Sequoyah Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 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), 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), System Actuation 05000382/LER-2024-001, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-150Start date: 15 May 2024 Site: Waterford Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 05000443/LER-2023-002, Automatic Actuation of Emergency Service Water During Testing Due to a Defective Relay2023-06-300Start date: 30 June 2023 Site: Seabrook Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation 05000348/LER-2022-001, Outdated Relay Settings Resulted in an Automatic Reactor Trip After a Floor Tile Was Dropped in High Voltage Switch House2022-09-300Start date: 30 September 2022 Site: Farley Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation 05000327/LER-2021-001, Sequoya Nuclear Plant, Unit 1, Reactor Trip on High Neutron Flux Rate Due to Dropped Control Rods2021-07-210Start date: 21 July 2021 Site: Sequoyah 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)(iv), System Actuation, 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) 05000400/LER-2020-002, Re Manual Reactor Trip Due to Control Rod Drop During Surveillance Testing2020-10-120Start date: 12 October 2020 Site: Harris Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 05000346/LER-2020-002, Manual Reactor Trip on Trip of Reactor Coolant Pumps Due to Loss of 13.8 Kv Bus Potential Transformer Fuse2020-05-260Start date: 26 May 2020 Site: Davis Besse 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)(iv), System Actuation, 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)(iii), 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) 05000483/LER-2019-001-01, Unplanned Loss of Switchyard Bus B Results in System Actuation2019-11-070Start date: 7 November 2019 Site: Callaway 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)(iv), System Actuation, 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)(ii)(A), Seriously Degraded, 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)(5) 05000346/LER-2019-001, Emergency Ventilation System Train Inoperable Due to Non-specific Test Description of Damper Operation2019-10-070Start date: 7 October 2019 Site: Davis Besse Reporting criterion: 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)(iv), System Actuation, 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)(ix), 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)(viii)(A) 05000327/LER-2019-001, Reactor Trip on Low-Low Steam Generator Level Due to the Loss of a Main Feedwater Pump2019-06-110Start date: 11 June 2019 Site: Sequoyah Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation 05000413/LER-2019-002, Condition Prohibited by Technical Specifications Due to Auxiliary Feedwater Sump Pump Conditions2019-06-100Start date: 10 June 2019 Site: Catawba Reporting criterion: 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)(iv), System Actuation, 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)(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), 10 CFR 50.73(a)(2)(viii)(A) 05000416/LER-2018-008, Unplanned System Actuation (Diesel Generator) Caused by Inadvertently Opening the Wrong Fuse Drawer2018-07-060Start date: 6 July 2018 Site: Grand Gulf 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)(iv), System Actuation, 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)(iii), 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) 05000458/LER-2017-0082017-08-180Start date: 18 August 2017 Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 05000461/LER-1917-007, Re Manual Reactor Scram Due to Loss of Feedwater Heating2017-08-090Start date: 9 August 2017 Site: Clinton 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)(iv), System Actuation, 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) 05000483/LER-2015-002, Regarding Manual Auxiliary Feedwater System Actuation2016-09-070Start date: 7 September 2016 Site: Callaway 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)(iv), System Actuation, 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)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(viii)(A) 05000389/LER-2015-002, Regarding 2A Emergency Diesel Generator Actuation Logic2015-11-160Start date: 16 November 2015 Site: Saint Lucie 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)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(iv), System Actuation, 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) 05000237/LER-2015-005, Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2015-10-300Start date: 30 October 2015 Site: Dresden Reporting criterion: 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)(iv), System Actuation, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(ix), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(viii)(A) 05000335/LER-2015-001, Regarding Reactor Trip While Performing Reactor Protection System Logic Matrix Test2015-10-070Start date: 7 October 2015 Site: Saint Lucie 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)(iv), System Actuation, 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) 05000311/LER-2015-002, Regarding Reactor Trip Due to Loss of 4 Kv Non-Vital Group Bus2015-10-020Start date: 2 October 2015 Site: Salem Reporting criterion: 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)(iv), System Actuation, 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) 05000286/LER-2015-005, Regarding Automatic Reactor Trip Due to a Turbine-Generator Trip Caused by the Trip of 345kV Main Generator Output Breaker 3 Due to a Failure of South Ring Bus 345kV Breaker 52015-08-140Start date: 14 August 2015 Site: Indian Point Reporting criterion: 10 CFR 50.73(a)(1), Submit an LER, 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), System Actuation 05000482/LER-2015-003, Regarding Manual Reactor Trip Due to High Steam Generator Level Transient at Low Power2015-07-010Start date: 1 July 2015 Site: Wolf Creek 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)(iv), System Actuation, 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) 05000454/LER-2015-002, Re Reactor Trip Resulting from a Phase to Phase Fault on the 1E Main Power Transformer2015-05-010Start date: 1 May 2015 Site: Byron 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)(iv), System Actuation, 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), 10 CFR 50.73(a)(2)(viii)(B) 05000458/LER-2015-002, Operations Prohibited by Technical Specifications Due to Deficient Local Leak Rate Test Procedures Containing Erroneous Valve Alignments2015-02-180Start date: 18 February 2015 Site: River Bend Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 05000458/LER-2014-002, Regarding Reactor Scram Due to Average Power Range Monitor High-flux Signal Following a Malfunction of the Main Turbine Electro Hydraulic System2014-12-160Start date: 16 December 2014 Site: River Bend 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)(iv), System Actuation, 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) 05000425/LER-2014-003, Regarding Unit 2 Manual Reactor Trip Due to Out of Sequence Control Rod Movement2014-12-100Start date: 10 December 2014 Site: Vogtle 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)(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)(iv), System Actuation, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(viii)(A) 05000331/LER-2014-005, Regarding Automatic Start of Standby Diesel Generators Due to Grid Disturbance2014-08-290Start date: 29 August 2014 Site: Duane Arnold 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)(iv), System Actuation, 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) 05000410/LER-2014-004, Regarding Actuation of the Alternate Rod Insertion System and Subsequent Reactor Scram2014-05-070Start date: 7 May 2014 Site: Nine Mile Point 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)(iv), System Actuation, 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) 05000387/LER-2014-004, Regarding Loss of Secondary Containment Pressure Due to Fan Trip2014-05-050Start date: 5 May 2014 Site: Susquehanna Reporting criterion: 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)(iv), System Actuation, 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)(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), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000389/LER-2013-004, Regarding Manual Trip Following Spurious Closure of Main Feedwater Isolation Valve (Mfiv) and Lowering of Steam Generator Levels2014-01-130Start date: 13 January 2014 Site: Saint Lucie 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)(iv), System Actuation, 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) 05000334/LER-2013-001, Regarding Manual Start of a Motor Driven Auxiliary Feedwater Pump2013-11-270Start date: 27 November 2013 Site: Beaver Valley 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)(iv), System Actuation, 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) 05000416/LER-2013-003, Regarding Reactor Protection System and Reactor Core Isolation Cooling Actuation Due to a High Reactor Pressure Transient2013-09-260Start date: 26 September 2013 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)(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)(iv), System Actuation, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2) 05000275/LER-2013-003, Regarding Actuation of Six Emergency Diesel Generators Due to Loss of Offsite Power2013-08-220Start date: 22 August 2013 Site: Diablo Canyon 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)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(iv), System Actuation, 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)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(i)(8), 10 CFR 50.73(a)(2)(v)(8) 05000313/LER-2013-001, Regarding Collapse of a Main Generator Stator Temporary Lift Assembly Results in a Fatality, Multiple Injuries, a Plant Scram, a Notification of Unusual Event, and Dual Unit Structural Damage2013-05-240Start date: 24 May 2013 Site: Arkansas Nuclear 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)(iv), System Actuation, 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), 10 CFR 50.73(b)(5) 05000390/LER-2011-004-01, Reactor Turbine Trip Due to Loss of Main Generator Excitation2013-04-120Start date: 12 April 2013 Site: Watts Bar Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 05000443/LER-2012-004, Regarding Manual Actuation of the Service Water Cooling Tower2012-12-260Start date: 26 December 2012 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)(iv), System Actuation, 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) 05000389/LER-2012-003, Regarding Inadvertent Trip of 2B3 4.16kv Switchgear2012-12-060Start date: 6 December 2012 Site: Saint Lucie 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)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(iv), System Actuation, 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)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000424/LER-2012-004, Regarding Unplanned Auxiliary Feedwater Actuation2012-11-290Start date: 29 November 2012 Site: Vogtle 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)(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)(iv), System Actuation, 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)(B) 05000482/LER-2012-001, For Wolf Creek Regarding Failure of 345 Kv Switchyard Breaker Due to Internal Fault Resulting in Reactor Trip and Coincident Loss of Offsite Power2012-03-120Start date: 12 March 2012 Site: Wolf Creek 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)(iv), System Actuation, 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) 05000370/LER-2011-002, For McGuire, Unit 2, Regarding Unit 2 Reactor Manually Tripped When Control Rod Did Not Respond as Expected During Control Rod Movement Testing2011-10-260Start date: 26 October 2011 Site: Mcguire Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation 05000482/LER-2011-007, Manual Reactor Trip Due to Failed Controller Cards in the B Feedwater Pump Turbine Control System2011-08-240Start date: 24 August 2011 Site: Wolf Creek 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)(iv), System Actuation, 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) 05000390/LER-2011-004, Regarding Reactor/Turbine Trip Due to Loss of Main Generator Excitation2011-07-280Start date: 28 July 2011 Site: Watts Bar 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)(iv), System Actuation, 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) 05000482/LER-2011-006, For Wolf Creek Generating Station, Regarding Auxiliary Feedwater Actuation Due to Operators Inability to Control Steam Generator Level in Mode 42011-07-250Start date: 25 July 2011 Site: Wolf Creek 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)(iv), System Actuation, 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) 05000424/LER-2011-001, Regarding Reactor Trip Due to I a Reactor Trip Breaker Opening2011-06-170Start date: 17 June 2011 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)(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)(iv), System Actuation, 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), 10 CFR 50.73(a)(2)(v)(0) 05000387/LER-2011-002, Regarding Manual Scram Due to Unisolable Extraction Steam System Leak2011-03-280Start date: 28 March 2011 Site: Susquehanna 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)(iv), System Actuation, 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) 05000263/LER-2011-002, Regarding ESF Actuation Due to Failed Power Supply2011-02-170Start date: 17 February 2011 Site: Monticello 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)(iv), System Actuation, 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000390/LER-2010-003, Manual Reactor Trip Due to High Main Bank Transformer Temperature2011-01-130Start date: 13 January 2011 Site: Watts Bar Reporting criterion: 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)(iv), System Actuation, 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)(ix), 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) 05000482/LER-2010-012, Regarding Reactor Trip Due to Operators Inability to Control Steam Generator Level Oscillations at Low Power2010-12-160Start date: 16 December 2010 Site: Wolf Creek 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)(iv), System Actuation, 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) 05000390/LER-2010-002, Regarding Valid Auxiliary Feedwater Actuation During Power Reduction for Planned Maintenance2010-10-140Start date: 14 October 2010 Site: Watts Bar 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)(iv), System Actuation, 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) 05000390/LER-2010-001, Regarding Reactor/Turbine Trip2010-07-200Start date: 20 July 2010 Site: Watts Bar 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)(iv), System Actuation, 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) 05000331/LER-2010-003, Regarding Unplanned Manual Reactor Scram Due to Increasing Turbine Vibrations2010-06-250Start date: 25 June 2010 Site: Duane Arnold 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)(iv), System Actuation, 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) 05000455/LER-2010-001, Reactor Protection and Auxiliary Feedwater System Actuation Signals from Low Steam Generator Level Due to Inadequate Surveillance Testing2010-06-180Start date: 18 June 2010 Site: Byron 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)(iv), System Actuation, 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) 05000482/LER-2010-006, Regarding Manual Reactor Trip Due to Trip of Main Feedwater Pump2010-05-050Start date: 5 May 2010 Site: Wolf Creek 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)(iv), System Actuation, 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) 05000482/LER-2010-005, Regarding Reactor Trip Due to Low Steam Generator Level from Trip of Main Feedwater Pump2010-05-030Start date: 3 May 2010 Site: Wolf Creek 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)(iv), System Actuation, 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) 05000251/LER-2010-001, Regarding Two Shutdown Bank Rods Were Dropped from Fully Withdrawn Position2010-01-250Start date: 25 January 2010 Site: Turkey Point 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)(iv), System Actuation, 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) 05000338/LER-2009-003, Regarding Inoperable Reserve Station Service Transformer Due to Improper Load Tap Changer Setting2010-01-140Start date: 14 January 2010 Site: North Anna Reporting criterion: 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)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(iv), System Actuation, 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) 05000389/LER-2009-004, Unplanned Manual Reactor Trip During Reactor Startup2009-11-190Start date: 19 November 2009 Site: Saint Lucie 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)(iv), System Actuation, 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) 05000316/LER-2009-001, For Donald C. Cook, Unit 2, Regarding Manual Reactor Trip Due to RCP Seal Degradation2009-09-110Start date: 11 September 2009 Site: Cook 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)(iv), System Actuation, 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) 05000287/LER-2009-002, For Oconee Nuclear Station Unit 3, Regarding Trip Due to Generator Phase Differential Lockout2009-07-200Start date: 20 July 2009 Site: Oconee 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)(iv), System Actuation, 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) 05000482/LER-2009-001, For Wolf Creek, Regarding Reactor Protection System Actuation and Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed2009-06-240Start date: 24 June 2009 Site: Wolf Creek 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)(iv), System Actuation, 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) 05000282/LER-2009-002, Regarding Unplanned Safety Related Actuation of 121 Cooling Water Pump2009-05-180Start date: 18 May 2009 Site: Prairie Island Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation, 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)(viii)(B) 05000293/LER-2008-007, Momentary Loss of All 345kv Off-Site Power to the Startup Transformer from Switchyard Breaker Fault2009-02-120Start date: 12 February 2009 Site: Pilgrim 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)(iv), System Actuation, 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)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000287/LER-2008-001, Trip Due to Control Rod Drive System Processor Failure2009-01-070Start date: 7 January 2009 Site: Oconee 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)(iv), System Actuation, 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) 05000263/LER-2008-005, Regarding Reactor Scram Due to Loss of Normal Offsite Power2008-11-070Start date: 7 November 2008 Site: Monticello Reporting criterion: 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)(iv), System Actuation, 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)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(viii)(B) 05000369/LER-2008-002, Reactor Trip Due to the 1B Reactor Coolant Pump Motor Trip Which Was Caused by a Failed Surge Capacitor2008-08-210Start date: 21 August 2008 Site: McGuire Reporting criterion: 10 CFR 50.73(a)(2)(iv), System Actuation 05000270/LER-2008-001, Regarding Unit 2 Reactor Trip Due to Indication of Loss of Vacuum During Calibration of a Condenser Pressure Transmitter2008-05-290Start date: 29 May 2008 Site: Oconee 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)(iv), System Actuation, 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) 05000247/LER-2008-001, Regarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Loss of Feedwater Flow as a Result of Feedwater Pump Speed Control Malfunction2008-05-220Start date: 22 May 2008 Site: Indian Point Reporting criterion: 10 CFR 50.73(a)(1), Submit an LER, 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), System Actuation 05000482/LER-2008-003, Re Manual Reactor Trip Due to Loss of Steam Generator Level2008-05-130Start date: 13 May 2008 Site: Wolf Creek 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)(iv), System Actuation, 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) 05000395/LER-2008-001, Regarding Manual Reactor Trip Due to Low Steam Generator Level Caused by Feedwater Flow Control Valve Malfunction2008-03-200Start date: 20 March 2008 Site: Summer 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)(iv), System Actuation, 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) 05000327/LER-2008-001, For Sequoyah, Unit 1, Regarding Manual Reactor Trip Resulting from a Failure to Follow Procedures2008-03-040Start date: 4 March 2008 Site: Sequoyah 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)(iv), System Actuation, 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) 05000458/LER-2007-005, Unplanned Reactor Scram During Surveillance Testing Due to Damaged Terminal Board2007-11-140Start date: 14 November 2007 Site: River Bend 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)(iv), System Actuation, 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) 05000263/LER-2007-002, Regarding Supplement 1 of LER 2007-02, Unexpected De-energizing of Bus 16 During Refuel Outage 232007-09-270Start date: 27 September 2007 Site: Monticello Reporting criterion: 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)(iv), System Actuation, 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)(viii)(B) 05000293/LER-2007-005, Re Reactor Scram Resulting from Low Vacuum Turbine Trip2007-09-100Start date: 10 September 2007 Site: Pilgrim 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)(iv), System Actuation, 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) 05000416/LER-2007-002, Regarding Reactor Scram Due to Turbine Trip Caused by Loss of Condenser Vacuum2007-07-160Start date: 16 July 2007 Site: Grand Gulf 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)(iv), System Actuation, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 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)(B), 10 CFR 50.73(b)(5) 05000423/LER-2007-002, Regarding Loss of Offsite Power Caused by Transmission System Operator While Defueled2007-06-110Start date: 11 June 2007 Site: Millstone Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation 05000328/LER-2007-002, Re Manual Reactor Trip Following Partial Loss of Main Feedwater Flow2007-05-140Start date: 14 May 2007 Site: Sequoyah 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)(iv), System Actuation, 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) 05000353/LER-2007-002, Regarding Automatic Actuation of Main Condenser Low Vacuum Isolation Logic During Refueling Outage2007-05-110Start date: 11 May 2007 Site: Limerick 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)(iv), System Actuation, 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) 05000328/LER-2007-001, Plan Re Reactor Trip Following Closure of Main Feedwater Valve Due to Control Air Line Failure2007-03-200Start date: 20 March 2007 Site: Sequoyah 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)(iv), System Actuation, 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) 05000263/LER-2007-001, Regarding Reactor Scram Due to Turbine Control Valve Housing Support Failure2007-03-120Start date: 12 March 2007 Site: Monticello 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)(iv), System Actuation, 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) 05000289/LER-2006-003, Re Automatic Reactor Trip Due to a Design Application Deficiency within the Reactor Coolant Pump Power Monitors Initiated by an Off-Site Grid Disturbance2007-02-120Start date: 12 February 2007 Site: Crane 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)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(iv), System Actuation, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(iii), 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition, 10 CFR 50.73(a)(2)(viii), 10 CFR 50.73(b)(2) 05000323/LER-2006-004, Regarding Automatic Reactor Trip Due to Circulating Water Pump Surge Capacitor Failure2007-02-120Start date: 12 February 2007 Site: Diablo Canyon Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation 05000247/LER-2006-006, Re Automatic Actuation of Both Motor Driven Auxiliary Feedwater Pumps After Local Reset of the 21 Main Feedwater Pump During Corrective Maintenance and Troubleshooting of Turbine Governor Valve2007-01-290Start date: 29 January 2007 Site: Indian Point 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), System Actuation 05000395/LER-2006-004, Re Turbine Trip Due to High Steam Generator Level P-142007-01-190Start date: 19 January 2007 Site: Summer 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)(iv), System Actuation, 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) 05000458/LER-2006-007, Regarding Automatic Reactor Scram Due to Inadvertent Isolation of Main Feedwater Headers2006-12-180Start date: 18 December 2006 Site: River Bend 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)(iv), System Actuation, 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) 05000247/LER-2006-004, Regarding Automatic Actuation of Both Motor Driven Auxiliary Feedwater Pumps Due to Trip of 21 Main Feedwater Pump Caused by High Vibrations2006-10-230Start date: 23 October 2006 Site: Indian Point Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(iv), System Actuation 05000390/LER-2006-005, Regarding Automatic Reactor Trip Due to Generator Trip2006-09-260Start date: 26 September 2006 Site: Watts Bar 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)(iv), System Actuation, 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) 05000389/LER-2006-004, Re Unplanned Manual Reactor/Turbine Trip Due to DEH Leak2006-08-140Start date: 14 August 2006 Site: Saint Lucie 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)(iv), System Actuation, 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)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000458/LER-2006-005, Unit 1 Re Automatic Start of Standby Service Water During Realignment of Reactor Plant Cooling Water2006-06-290Start date: 29 June 2006 Site: River Bend 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)(iv), System Actuation, 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) 05000458/LER-2006-004, Regarding Automatic Reactor Scram Following Recirculation Pump Downshift Due to Failed Optical Isolator Card2006-06-140Start date: 14 June 2006 Site: River Bend 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)(iv), System Actuation, 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) 05000255/LER-2006-003, Re Completion of Plant Shutdown Required by Technical Specifications2006-05-260Start date: 26 May 2006 Site: Palisades Reporting criterion: 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)(iv), System Actuation, 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 05000328/LER-2006-001, Re Reactor Trip Resulting from Actuation of the Main Generator Neutral Overvoltage Relay2006-05-220Start date: 22 May 2006 Site: Sequoyah 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)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(iv), System Actuation, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2) 05000293/LER-2006-001, 0, Pilgrim Re Manual Scram Due to High Offgas Recombiner Temperature Resulting from Inadequate Preventive Recombiner Preheater Pressure Control Valve Controller2006-05-110Start date: 11 May 2006 Site: Pilgrim 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)(iv), System Actuation, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(x), 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) 05000362/LER-2006-001, Regarding Emergency Subgroup Relay Test Causes Inadvertent Fill of Steam Generator2006-04-120Start date: 12 April 2006 Site: San Onofre 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)(iv), System Actuation, 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) 05000423/LER-2005-005, Automatic Reactor Trip of Millstone Unit 3 Due to Low-Low Steam Generator Level2006-01-180Start date: 18 January 2006 Site: Millstone 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)(iv), System Actuation, 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) 05000335/LER-2005-003, IA Emergency Diesel Generator Actuation2005-07-180Start date: 18 July 2005 Site: Saint Lucie 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)(iv), System Actuation, 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), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000289/LER-2005-002, Regarding Safe Shutdown Analysis for Control Building Fire Area 1 Was Discovered to Have Flaws in the Fire Mitigation Strategy Due to Insufficient Technical Rigor2005-06-230Start date: 23 June 2005 Site: Crane Reporting criterion: 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(iv), System Actuation, 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(iii), 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition, 10 CFR 50.73(a)(2)(viii), 10 CFR 50.73(a)(2), 10 CFR 50.73(b)(2)(ii)
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