| Site | Report date | Reporting criterion | System |
---|
05000266/LER-2017-003 | Point Beach | 13 December 2017 | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System |
05000346/LER-2017-002 | Davis Besse | 27 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | Feedwater Auxiliary Feedwater Main Steam Safety Valve Main Steam Isolation Valve Steam Generator Service water |
05000412/LER-2017-001 | Beaver Valley | 2 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | Service water |
05000373/LER-2017-006 | LaSalle Lasalle | 17 July 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Core Spray Residual Heat Removal Reactor Core Isolation Cooling |
05000293/LER-2017-007 | Pilgrim | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000483/LER-2017-003 | Callaway | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii) | Primary containment |
05000285/LER-2017-001 | Fort Calhoun | 11 May 2017 | | Reactor Coolant System |
05000423/LER-2017-001 | Millstone | 20 March 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Secondary containment |
05000220/LER-2017-001 | Nine Mile Point | 8 February 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Main Turbine High Pressure Coolant Injection Reactor Pressure Vessel Feedwater |
05000341/LER-2017-003 | Fermi | 21 July 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 | Residual Heat Removal Service Water Residual Heat Removal Reactor Pressure Vessel Emergency Diesel Generator Service water |
05000313/LER-2017-001 | Arkansas Nuclear Arkansas Nuclear One – Unit 1 | 26 June 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator Reactor Protection System Feedwater Reactor Coolant System Main Turbine Steam Generator |
05000440/LER-2017-003 | Perry | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Primary containment Shield Building |
05000254/LER-2017-004 | Quad Cities | 5 January 2018 | | High Pressure Coolant Injection Feedwater Core Spray |
05000293/LER-2017-001 | Pilgrim | 17 July 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Standby Gas Treatment System HVAC Reactor Pressure Vessel Core Standby Cooling System |
05000390/LER-2017-011 | Watts Bar | 23 October 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000390/LER-2017-007 | Watts Bar | 3 November 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Control Room Emergency Ventilation Reactor Coolant System Shield Building Emergency Gas Treatment System |
05000391/LER-2017-002 | Watts Bar | 12 May 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Protection System Auxiliary Feedwater Feedwater Steam Generator |
05000324/LER-2017-001 | Brunswick | 18 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment |
05000395/LER-2017-005 | Summer | 22 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Steam Generator |
05000263/LER-2017-002 | Monticello | 13 June 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Main Steam Isolation Valve Primary containment |
05000390/LER-2017-008 | Watts Bar | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Primary containment Shield Building Emergency Gas Treatment System |
05000416/LER-2017-005 | Grand Gulf | 7 September 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
05000374/LER-2017-002 | LaSalle Lasalle | 31 March 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Emergency Diesel Generator High Pressure Core Spray Reactor Core Isolation Cooling Core Standby Cooling System |
05000498/LER-2017-001 | South Texas | 11 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000254/LER-2017-002 | Quad Cities | 26 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Main Steam Isolation Valve Primary containment |
05000390/LER-2017-004 | Watts Bar | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Auxiliary Feedwater Steam Generator |
05000461/LER-2017-008 | Clinton | 11 August 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Core Spray Reactor Core Isolation Cooling Emergency Diesel Generator Service water |
05000219/LER-2017-005 | Oyster Creek | 3 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator |
05000263/LER-2017-001 | Monticello | 13 June 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Reactor Protection System Primary containment Primary Containment Isolation System |
05000387/LER-2017-005 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Protection System Secondary containment Reactor Building Ventilation Standby Gas Treatment System Main Turbine High Pressure Coolant Injection Reactor Core Isolation Cooling Reactor Pressure Vessel Feedwater Reactor Coolant System |
05000293/LER-2017-004 | Pilgrim | 2 June 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Standby Gas Treatment System Secondary containment Primary containment Reactor Building Ventilation |
05000461/LER-2017-003 | Clinton | 3 July 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment Residual Heat Removal Shutdown Cooling Intermediate Range Monitor Feedwater Reactor Pressure Vessel Reactor Water Cleanup |
05000293/LER-2017-010 | Pilgrim | 3 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Core Spray Residual Heat Removal Reactor Coolant System |
05000388/LER-2017-001 | | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment |
05000440/LER-2017-005 | Perry | 4 October 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Secondary containment |
05000293/LER-2017-003 | Pilgrim | 13 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Primary containment Core Spray |
05000391/LER-2017-003 | Watts Bar | 22 May 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Turbine Driven Main Feed Pump Auxiliary Feedwater Main Turbine Feedwater |
05000373/LER-2017-004 | LaSalle Lasalle | 17 April 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Secondary containment Primary containment |
05000260/LER-2017-003 | Browns Ferry | 30 May 2017 | | Intermediate Range Monitor Reactor Protection System Reactor Core Isolation Cooling Primary Containment Isolation System |
05000461/LER-2017-009 | Clinton Power Station, Unit 1 . Clinton | 4 January 2018 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Standby Gas Treatment System Service water |
05000286/LER-2017-001 | Indian Point Unit 3 Indian Point | 13 July 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | Residual Heat Removal Reactor Coolant System |
05000354/LER-2017-001 | Hope Creek | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment |
05000334/LER-2017-001 | Beaver Valley | 18 April 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(ix)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Main Steam Safety Valve |
05000397/LER-2017-004 | Columbia | 17 October 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Reactor Pressure Vessel Main Turbine Main Steam Isolation Valve |
05000388/LER-2017-004 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment |
05000249/LER-2017-001 | Dresden | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | Standby Liquid Control Reactor Pressure Vessel |
05000346/LER-2017-001 | Davis Besse | 18 September 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator |
05000280/LER-2017-001 | Surry | 11 October 2017 | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System |
05000390/LER-2017-001 | Watts Bar | 9 January 2017 | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | |
05000458/LER-2017-005 | River Bend | 5 June 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
05000374/LER-2017-003 | LaSalle Lasalle | 9 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(iv)(A), System Actuation | High Pressure Core Spray Reactor Core Isolation Cooling Reactor Pressure Vessel Main Steam Isolation Valve Reactor Protection System |
05000286/LER-2017-003 | Indian Point Unit 3 Indian Point | 29 August 2017 | 10 CFR 50.73(a)(2)(V)(B) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | Feedwater Auxiliary Feedwater Steam Generator Service water |
05000390/LER-2017-009 | Watts Bar | | 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Residual Heat Removal Emergency Diesel Generator |
05000311/LER-2017-001 | Salem | | | Emergency Diesel Generator |
05000366/LER-2017-001 | Hatch | 3 April 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment Reactor Pressure Vessel |
05000387/LER-2017-002 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment |
05000397/LER-2017-005 | Columbia | 9 November 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Secondary containment Reactor Core Isolation Cooling |
05000261/LER-2017-002 | Robinson | 14 December 2017 | | |
05000293/LER-2017-013 | Pilgrim | 25 January 2018 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Standby Gas Treatment System Secondary containment Primary containment |
05000397/LER-2017-001 | Columbia | | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Core Spray Service water |
05000364/LER-2017-002 | Farley | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Main Steam Safety Valve Reactor Coolant System Steam Generator |
05000440/LER-2017-004 | Perry | 4 October 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Core Spray |
05000395/LER-2017-002 | Summer | 31 January 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Steam Generator |
05000389/LER-2017-004 | Saint Lucie | 18 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Auxiliary Feedwater Reactor Protection System Steam Generator |
05000364/LER-2017-003 | Farley | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Coolant System |
05000461/LER-2017-005 | Clinton | 28 September 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Protection System |
05000298/LER-2017-002 | Cooper | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Main Steam Isolation Valve |
05000313/LER-2017-002 | Arkansas Nuclear One – Unit 1 Arkansas Nuclear | 13 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator |
05000373/LER-2017-003 | LaSalle Lasalle | 14 April 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Reactor Protection System Main Transformer |
05000289/LER-2017-001 | Three Mile Island Three Mile Island Unit 1 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Coolant System |
05000482/LER-2017-002 | Wolf Creek | 31 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator |
05000298/LER-2017-004 | Cooper | | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Primary containment |
05000364/LER-2017-005 | Joseph M Farley Nuclear Plant, Unit 2 Farley | 11 January 2018 | 10 CFR 50.73(a)(2)() 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) | |
05000390/LER-2017-005 | Watts Bar | 10 July 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Emergency Diesel Generator Reactor Coolant System |
05000461/LER-2017-001 | Clinton | 21 April 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Standby Gas Treatment System Service water |
05000219/LER-2017-001 | Oyster Creek | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Protection System Main Turbine |
05000266/LER-2017-001 | Point Beach | 16 November 2017 | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | |
05000341/LER-2017-001 | Fermi | 6 March 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | Reactor Protection System Main Steam Isolation Valve Reactor Coolant System |
05000334/LER-2017-002 | Beaver Valley | 13 September 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | Emergency Diesel Generator |
05000331/LER-2017-001 | Duane Arnold | 27 March 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Primary containment |
05000483/LER-2017-002 | Callaway | 13 October 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(ix)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Auxiliary Feedwater Main Steam Safety Valve Emergency Diesel Generator Steam Generator Service water |
05000388/LER-2017-010 | Susquehanna | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Core Spray Residual Heat Removal |
05000255/LER-2017-002 | Palisades | 17 July 2017 | | Reactor Protection System |
05000416/LER-2017-001 | Grand Gulf | 28 March 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Core Spray Reactor Core Isolation Cooling Residual Heat Removal Core Spray |
05000390/LER-2017-010 | Watts Bar | 16 October 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Auxiliary Feedwater |
05000458/LER-2017-001 | River Bend | 3 April 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Primary containment Reactor Pressure Vessel High Pressure Core Spray |
05000220/LER-2017-003 | Nine Mile Point | 2 November 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Protection System High Pressure Coolant Injection Feedwater Reactor Pressure Vessel Main Steam Isolation Valve Core Spray |
05000293/LER-2017-008 | Pilgrim | 2 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | Primary containment |
05000440/LER-2017-001 | Perry | 1 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment Reactor Pressure Vessel Reactor Water Cleanup |
05000390/LER-2017-003 | Watts Bar | 3 March 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000219/LER-2017-002 | Oyster Creek | 31 August 2017 | | Steam Jet Air Ejector |
05000368/LER-2017-001 | Arkansas Nuclear One – Unit 2 Arkansas Nuclear | 30 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator |
05000325/LER-2017-003 | Brunswick | 2 August 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Control Room Emergency Ventilation |
05000461/LER-2017-002 | Clinton | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator Residual Heat Removal |
05000266/LER-2017-002 | Point Beach | 13 December 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Auxiliary Feedwater Feedwater Reactor Coolant System Steam Generator |
05000366/LER-2017-003 | Hatch | 13 April 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Primary containment |
05000306/LER-2017-003 | Prairie Island | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Main Steam Isolation Valve Service water |
05000446/LER-2017-002 | Comanche Peak Nuclear Power Plant Unit 2 | 27 October 2017 | | Auxiliary Feedwater Reactor Protection System Steam Generator |
05000219/LER-2017-004 | Oyster Creek | 16 February 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Protection System Main Turbine |
05000263/LER-2017-005 | Monticello | 20 September 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator Service water |
05000390/LER-2017-012 | Watts Bar | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator Residual Heat Removal Reactor Coolant System |
05000259/LER-2017-001 | Browns Ferry | 21 February 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000373/LER-2017-001 | LaSalle Lasalle | 8 February 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Core Isolation Cooling High Pressure Core Spray |
05000458/LER-2017-002 | River Bend | 18 April 2017 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | HVAC Emergency Diesel Generator |
05000373/LER-2017-007 | LaSalle Lasalle | 18 August 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Core Spray Reactor Pressure Vessel Residual Heat Removal Reactor Building Ventilation |
05000364/LER-2017-001 | Farley | 21 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator Service water |
05000366/LER-2017-004 | Edwin I Hatch Nuclear Plant Unit 2 | 24 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Pressure Vessel Main Steam Isolation Valve Reactor Protection System |
05000440/LER-2017-007 | Perry | | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Core Spray Reactor Core Isolation Cooling Core Spray |
05000247/LER-2017-001 | Indian Point | 22 August 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Main Turbine Emergency Diesel Generator Auxiliary Feedwater Reactor Protection System Reactor Coolant System Steam Generator |
05000395/LER-2017-001 | Vc Summer.- Unit 1 Summer | 24 July 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Feedwater Steam Generator |
05000443/LER-2017-001 | Seabrook | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Reactor Protection System Steam Generator |
05000289/LER-2017-003 | Three Mile Island Unit 1 Three Mile Island | | 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)(v)(C), Loss of Safety Function - Release of Radioactive Material | Primary containment |
05000263/LER-2017-004 | Monticello | 16 August 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Coolant Injection Reactor Core Isolation Cooling |
05000483/LER-2017-001 | Callaway Docket Number | 15 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Service water |
05000388/LER-2017-003 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment |
05000416/LER-2017-002 | Grand Gulf | 3 October 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Standby Gas Treatment System |
05000261/LER-2017-001 | Robinson | 2 June 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Auxiliary Feedwater Feedwater Steam Generator |
05000389/LER-2017-003 | Saint Lucie | 18 December 2017 | | Auxiliary Feedwater Steam Generator |
05000458/LER-2017-007 | River Bend Station — Unit 1 05000-458 River Bend | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Main Turbine Feedwater Primary containment Reactor Protection System Reactor Water Cleanup |
05000306/LER-2017-002 | Prairie Island | 11 December 2017 | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System |
05000390/LER-2017-015 | Watts Bar | 8 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000341/LER-2017-004 | Fermi | 9 October 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | Residual Heat Removal Emergency Diesel Generator Service water |
05000388/LER-2017-005 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment HVAC |
05000461/LER-2017-010 | Clinton | 5 February 2018 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Secondary containment Standby Gas Treatment System Reactor Protection System Main Steam Isolation Valve Reactor Water Cleanup |
05000289/LER-2017-002 | Three Mile Island Unit 1 Three Mile Island | 6 February 2017 | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System |
05000374/LER-2017-001 | LaSalle Lasalle | 24 March 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Protection System Feedwater Main Turbine Main Steam Isolation Valve |
05000388/LER-2017-008 | Susquehanna | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Primary containment |
05000446/LER-2017-001 | Comanche Peak | 22 January 2018 | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Auxiliary Feedwater Feedwater Steam Generator |
05000255/LER-2017-001 | Palisades | 24 May 2017 | | Emergency Diesel Generator Auxiliary Feedwater Service water |
05000260/LER-2017-004 | Browns Ferry | 7 July 2017 | | |
05000389/LER-2017-001 | Saint Lucie | 27 April 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator |
05000293/LER-2017-012 | Pilgrim | 13 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator |
05000387/LER-2017-004 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment HVAC |
05000425/LER-2017-001 | Vogtle | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator |
05000286/LER-2017-004 | Indian Point | 20 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Auxiliary Feedwater Feedwater Reactor Protection System Emergency Diesel Generator Reactor Coolant System Steam Generator Permanent Magnet Generator |
05000260/LER-2017-001 | Browns Ferry | 14 April 2017 | | High Pressure Coolant Injection Reactor Core Isolation Cooling |
05000440/LER-2017-002 | Perry | | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | Main Turbine Reactor Protection System |
05000321/LER-2017-003 | Docket Number | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Primary containment |
05000382/LER-2017-002 | Waterford Steam Electric Station, Unit 3 Waterford | 18 September 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | Main Turbine Emergency Diesel Generator Feedwater Reactor Protection System Reactor Coolant System Auxiliary Feedwater Main Transformer Steam Generator |
05000458/LER-2017-004 | River Bend | 22 May 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | High Pressure Core Spray Primary containment |
05000263/LER-2017-003 | Monticello | 14 June 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Main Steam Isolation Valve Primary containment |
05000395/LER-2017-003 | Vc Summer - Unit 1 Summer | 12 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Reactor Coolant System Main Transformer |
05000397/LER-2017-002 | Columbia | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment Residual Heat Removal Shutdown Cooling Reactor Pressure Vessel |
05000333/LER-2017-001 | FitzPatrick | 13 March 2017 | 10 CFR 50.73(a)(2)(ii) | Reactor Coolant System Residual Heat Removal Shutdown Cooling Primary containment |
05000244/LER-2017-001 | Ginna | 15 June 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Main Steam Safety Valve |
05000461/LER-2017-004 | Clinton | 22 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Main Steam Isolation Valve Primary containment Feedwater |
05000335/LER-2017-002 | Saint Lucie | 28 September 2017 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Reactor Coolant System Shutdown Cooling |
05000321/LER-2017-002 | Hatch | 7 April 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Coolant Injection Reactor Pressure Vessel Residual Heat Removal Core Spray Reactor Core Isolation Cooling |
05000388/LER-2017-006 | | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | HVAC Secondary containment |
05000397/LER-2017-007 | Columbia | 30 November 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Secondary containment Emergency Diesel Generator |
05000390/LER-2017-016 | Watts Bar Nuclear Plant. Unit 1 | 20 February 2018 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Auxiliary Feedwater Emergency Diesel Generator |
05000296/LER-2017-002 | Browns Ferry | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator |
05000325/LER-2017-004 | Brunswick Steam Electric Plant (Bsep) Unit1 | 15 November 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator Primary Containment Isolation System Reactor Building Ventilation Secondary containment Standby Gas Treatment System Service water |
05000259/LER-2017-002 | | 1 May 2017 | | |
05000390/LER-2017-013 | Watts Bar | 24 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment Shield Building |
05000482/LER-2017-003 | Wolf Creek | 2 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Main Steam Safety Valve Main Turbine Main Steam Isolation Valve Steam Generator |
05000395/LER-2017-006 | Vc Summer - Unit 1 Summer | 15 December 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000298/LER-2017-001 | Cooper | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | Residual Heat Removal Low Pressure Cooling Injection Shutdown Cooling Reactor Pressure Vessel Service water |
05000458/LER-2017-003 | River Bend | 9 May 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Main Turbine Main Steam Isolation Valve Reactor Protection System |
05000388/LER-2017-009 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment |
05000324/LER-2017-003 | Brunswick | 3 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Coolant System |
05000528/LER-2017-001 | Palo Verde Palo Verde Nuclear Generating Station Unit 1 | 14 June 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Auxiliary Feedwater |
05000278/LER-2017-001 | Peach Bottom | 21 December 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System Residual Heat Removal |
05000370/LER-2017-001 | McGuire | 26 June 2017 | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System |
05000397/LER-2017-006 | Columbia | 9 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000293/LER-2017-006 | Pilgrim | 13 June 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Intermediate Range Monitor |
05000260/LER-2017-002 | Browns Ferry | | | Primary containment Reactor Core Isolation Cooling |
05000390/LER-2017-006 | Watts Bar | 31 July 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000220/LER-2017-002 | Nine Mile Point | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Main Turbine |
05000416/LER-2017-004 | Grand Gulf | 13 July 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Feedwater High Pressure Core Spray |
05000254/LER-2017-003 | Quad Cities | 17 November 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Control Room Emergency Ventilation HVAC |
05000341/LER-2017-002 | Fermi | 16 March 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i) | High Pressure Coolant Injection Reactor Core Isolation Cooling Feedwater Primary containment |
05000391/LER-2017-006 | Watts Bar | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Auxiliary Feedwater Reactor Protection System |
05000416/LER-2017-007 | Grand Gulf | 5 February 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator Secondary containment Reactor Core Isolation Cooling Main Transformer |
05000263/LER-2017-006 | Monticello | 12 January 2018 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | Reactor Protection System Main Steam Isolation Valve Reactor Coolant System |
05000335/LER-2017-001 | Saint Lucie | 2 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System |
05000293/LER-2017-011 | A Ler Number Pilgrim | 15 August 2017 | | Secondary containment Primary containment Standby Gas Treatment System |
05000461/LER-2017-006 | Clinton | 1 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment Reactor Water Cleanup |
05000251/LER-2017-001 | Turkey Point | 7 November 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Reactor Protection System Steam Generator |
05000391/LER-2017-005 | Watts Bar Nuclear Plant. Unit 2 Watts Bar | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Coolant System Emergency Diesel Generator |
05000390/LER-2017-002 | Watts Bar | 22 February 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
05000416/LER-2017-006 | Grand Gulf | 12 October 2017 | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | Residual Heat Removal |
05000387/LER-2017-007 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment |
05000364/LER-2017-004 | Joseph M. Farley Nuclear Plant. Unit 2 Farley | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Auxiliary Feedwater Reactor Coolant System Main Steam Isolation Valve Steam Generator |
05000382/LER-2017-001 | Waterford | 4 May 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Shutdown Cooling Reactor Coolant System Steam Generator |
05000373/LER-2017-005 | LaSalle Lasalle | 18 April 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Reactor Protection System Reactor Pressure Vessel Main Steam Isolation Valve |
05000390/LER-2017-014 | Watts Bar | 20 December 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Control Room Emergency Ventilation |
05000424/LER-2017-002 | Vogtle | 29 June 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator Residual Heat Removal |
05000321/LER-2017-004 | Hatch | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator |
05000293/LER-2017-002 | Pilgrim | 25 May 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Coolant Injection Reactor Core Isolation Cooling Core Spray Primary containment |
05000387/LER-2017-006 | Susquehanna | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Secondary containment |
05000335/LER-2017-003 | Saint Lucie | 13 November 2017 | | Reactor Protection System |
05000334/LER-2017-003 | Beaver Valley | 4 January 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Auxiliary Feedwater Feedwater Reactor Protection System Steam Generator |
05000458/LER-2017-006 | River Bend | 13 July 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Core Spray |
05000247/LER-2017-003 | Indian Point Unit 2 Indian Point | 23 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Protection System |
05000391/LER-2017-004 | Watts Bar | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Protection System Auxiliary Feedwater Steam Generator |
05000458/LER-2017-008 | | 12 October 2017 | 10 CFR 50.73(a)(2)(iv), System Actuation | Feedwater Reactor Protection System |
05000318/LER-2017-001 | Calvert Cliffs | 19 April 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Coolant System |
05000277/LER-2017-001 | Peach Bottom | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator |
05000454/LER-2017-001 | Byron | | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System Reactor Pressure Vessel |
05000269/LER-2017-001 | Oconee Nuclear Station Unit 1 | 9 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Service water |
05000323/LER-2017-001 | Diablo Canyon | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Reactor Coolant System Feedwater Steam Generator |
05000325/LER-2017-002 | Brunswick | 12 June 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Main Turbine Emergency Diesel Generator |
05000395/LER-2017-004 | Summer | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator |
05000368/LER-2017-002 | Arkansas Nuclear One – Unit 2 Arkansas Nuclear | 26 June 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator |
05000341/LER-2017-005 | Fermi | | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Emergency Equipment Cooling Water High Pressure Coolant Injection Emergency Diesel Generator Residual Heat Removal Reactor Core Isolation Cooling Feedwater Service water |
05000352/LER-2017-001 | Limerick | | | HVAC |
05000287/LER-2017-001 | Oconee Nuclear Station Unit 3 Oconee | 20 September 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Protection System |
05000324/LER-2017-002 | Brunswick | 9 June 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Primary containment Emergency Diesel Generator Residual Heat Removal |
05000458/LER-2017-009 | Docket Number River Bend | 13 November 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Primary containment Standby Gas Treatment System |
05000397/LER-2017-003 | Columbia | 24 August 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Secondary containment HVAC |
05000286/LER-2017-002 | Docket Number Indian Point | 9 August 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | Reactor Coolant System Feedwater Residual Heat Removal |
05000316/LER-2017-001 | Cook | 19 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Residual Heat Removal |
05000348/LER-2017-001 | Farley | 29 September 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Coolant System |
05000250/LER-2017-001 | Turkey Point | 16 May 2017 | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Emergency Diesel Generator Reactor Protection System Steam Generator |
05000498/LER-2017-002 | South Texas | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Control Room Emergency Ventilation HVAC |
05000254/LER-2017-001 | Quad Cities | 22 March 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Primary containment Standby Gas Treatment System Emergency Diesel Generator |
05000440/LER-2017-006 | Perry | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Core Spray |
05000425/LER-2017-002 | Vogtle | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator |
05000391/LER-2017-001 | Watts Bar | 3 May 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
05000293/LER-2017-005 | Pilgrim | 7 June 2017 | 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)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | High Pressure Coolant Injection Primary containment Main Steam Isolation Valve Secondary containment |
05000388/LER-2017-002 | Susquehanna Steam Electric Station Unit 2 1 Of 4 Susquehanna | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment Residual Heat Removal Reactor Pressure Vessel Shutdown Cooling Reactor Water Cleanup |
05000388/LER-2017-007 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment |
05000446/LER-2017-003 | Comanche Peak Nuclear Power Plant, Unit 2 Comanche Peak | 22 January 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Feedwater Auxiliary Feedwater Reactor Protection System Main Turbine Steam Generator |
05000327/LER-2017-001 | Sequoyah | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Shield Building |
05000306/LER-2017-001 | Prairie Island | 29 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(b) 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii) | |
05000410/LER-2017-001 | Nine Mile Point | 4 October 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Protection System Main Turbine |
05000325/LER-2017-001 | Brunswick | 22 March 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Emergency Diesel Generator |
05000293/LER-2017-009 | Pilgrim | 15 November 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | Primary containment Shutdown Cooling Residual Heat Removal Primary Containment Isolation System |
05000387/LER-2017-003 | Susquehanna Steam Electric Station Unit 2 05000-387 Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment HVAC |
05000298/LER-2017-005 | Cooper | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | Primary containment Primary Containment Isolation System |
05000461/LER-2017-007 | Clinton | 9 November 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Feedwater Main Turbine Reactor Protection System |
05000296/LER-2017-001 | Browns Ferry | 31 October 2017 | | Residual Heat Removal Reactor Core Isolation Cooling High Pressure Coolant Injection Core Spray Core Standby Cooling System |
05000374/LER-2017-004 | LaSalle Lasalle | 14 July 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Pressure Vessel |
05000387/LER-2017-001 | Susquehanna | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment |
05000410/LER-2017-002 | Nine Mile Point | 29 November 2017 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Reactor Building Ventilation Standby Gas Treatment System |
05000247/LER-2017-002 | Indian Point | 22 August 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Auxiliary Feedwater Feedwater Steam Generator |
05000272/LER-2017-001 | Salem | 8 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Coolant System Steam Generator |
05000327/LER-2017-002 | Sequoyah | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator |
05000219/LER-2017-003 | Oyster Creek | 31 August 2017 | | Reactor Pressure Vessel Feedwater |
05000389/LER-2017-002 | Saint Lucie | 14 July 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator |
05000482/LER-2017-001 | Wolf Creek | 17 May 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Service water |
05000289/LER-2017-004 | Three Mile Island Three Mile Island Unit 1 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator |
05000265/LER-2017-001 | Quad Cities | 14 July 2017 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Coolant Injection Feedwater Core Spray Primary containment |
05000366/LER-2017-002 | Hatch | 13 April 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Emergency Diesel Generator Secondary containment Standby Gas Treatment System Shutdown Cooling |
05000298/LER-2017-003 | Cooper | | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
05000313/LER-2016-003 | Arkansas Nuclear | 19 October 2016 | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Feedwater |
05000391/LER-2016-003 | Watts Bar | 2 September 2016 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Auxiliary Feedwater Feedwater Steam Generator |
05000285/LER-2016-001 | Fort Calhoun | 8 April 2016 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Reactor Coolant System |
05000416/LER-2016-006 | Grand Gulf | 27 March 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Main Steam Isolation Valve Residual Heat Removal Shutdown Cooling Reactor Protection System |