| Site | Start date | Reporting criterion | System | Topic |
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05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer | Calvert Cliffs | 16 January 2024 | | Reactor Protection System | |
05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip | Calvert Cliffs | 8 January 2024 | | Steam Generator Feedwater Auxiliary Feedwater | |
05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer | Calvert Cliffs | 8 January 2024 | | Reactor Protection System | |
05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications | Callaway | 29 November 2023 | | | |
05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case | Braidwood | 17 November 2023 | | Auxiliary Feedwater | |
05000483/LER-2022-002, Forward LER 2022-002-00 for Callaway Plant, Unit 1, Containment Spray and Cooling Systems, and a Condition Which Could Have Prevented Fulfillment of the Safety Function of the Containment Spray System (Letter Only) | Callaway | 18 August 2022 | | Containment Spray | |
05000250/LER-2021-004, Cancelation of LER 2021-004, Through-Wall Leakage from Core Exit Thermocouple Tubing | Turkey Point | 28 March 2022 | | | Through-Wall Leakage |
05000318/LER-2022-001, Forwards LER 2022-001-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to High Reactor Coolant System Pressure | Calvert Cliffs | 3 March 2022 | | Reactor Coolant System | |
05000318/LER-2021-003, Forward LER 2021-003-00 for Calvert Cliffs Nuclear Power Plant, Unit No. 2, Auxiliary Feedwater Pump Inoperable Due to Improper Reset of Trip Throttle Valve. Cover Letter Only | Calvert Cliffs | 23 September 2021 | | Auxiliary Feedwater | |
05000327/LER-2021-002, Letter Forwarding LER 2021-002-00 & LER 2021-001-00 for Sequoyah Nuclear Plant, Units 1 & 2 | Sequoyah | 22 September 2021 | | | |
05000327/LER-2021-001, & LER 2021-001-00 for Sequoyah Nuclear Plant, Units 1 & 2, Ice Bed Inoperable Due to Exceeding Surveillance Requirement Frequency | Sequoyah | 22 September 2021 | | | Safe Shutdown |
05000456/LER-2021-001, Forward LER 2021-001-00 for Braidwood Station, Unit 1, Train a and B Source Range Neutron Flux Trip Functions Bypassed During Plant Startup | Braidwood | 21 June 2021 | | | |
05000483/LER-2020-005, Forward LER 2020-005-00 for Callaway Plant, Unit 1, Inoperable Isolation Valve Between Safety-Related Essential Service Water and Nonsafety-Related Service Water | Callaway | 17 November 2020 | | Service water | |
05000281/LER-2020-001, Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication | Surry | 6 November 2020 | | Reactor Coolant System | |
05000483/LER-2020-002, Submittal of LER 2020-002-00 for Callaway, Unit 1, Reactor Trip and AFW Actuation Following Spurious MFRV Closure | Callaway | 3 June 2020 | | Feedwater Auxiliary Feedwater | |
05000482/LER-2020-001, Transmittal of LER 2020-001-00 for Wolf Creek, Plant Shutdown Due to Inoperable Containment Purge Isolation Valves | Wolf Creek | 1 April 2020 | | | |
05000461/LER-2020-001, Submittal of LER 2020-001-00 for Clinton Power Station, Unit 1, Reportable Contraband Event | Clinton | 23 March 2020 | | | Contraband |
05000366/LER-2020-001 | Hatch | 2 March 2020 | | Primary containment | Large early release frequency |
05000423/LER-2019-001 | Millstone | 13 February 2020 | | Steam Generator Emergency Diesel Generator Auxiliary Feedwater Decay Heat Removal | |
05000280/LER-2019-002 | Surry | 4 February 2020 | | Service water Auxiliary Feedwater Main Steam | Safe Shutdown Unanalyzed Condition Tornado Missile Enforcement Discretion Tornado Generated Missile Tornado Missile Protection |
05000461/LER-2017-010 | Clinton | 9 December 2017 5 February 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Reactor Protection System Main Steam Isolation Valve Reactor Water Cleanup Standby Gas Treatment System Emergency Core Cooling System Control Rod | Unanalyzed Condition |
05000289/LER-2017-004 | Three Mile Island Three Mile Island Unit 1 | 5 February 2018 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator | Safe Shutdown Unanalyzed Condition Enforcement Discretion Tornado Generated Missile Tornado Missile Protection |
05000388/LER-2017-010 | Susquehanna | 2 February 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Core Spray Residual Heat Removal Low Pressure Coolant Injection | |
05000391/LER-2017-005 | Watts Bar Watts Bar Nuclear Plant. Unit 2 | 25 January 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Coolant System Emergency Diesel Generator Emergency Core Cooling System | Safe Shutdown |
05000293/LER-2017-013 | Pilgrim | 26 November 2017 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 | Secondary containment Primary containment Standby Gas Treatment System | Mission time Recently irradiated fuel |
05000390/LER-2017-013 | Watts Bar | 6 September 2017 24 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment Auxiliary Building Gas Treatment System Shield Building | Safe Shutdown Safe Shutdown Earthquake Past operability Probabilistic Risk Assessment |
05000446/LER-2017-003 | Comanche Peak Comanche Peak Nuclear Power Plant, Unit 2 | 25 November 2017 22 January 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Steam Generator Feedwater Reactor Protection System Auxiliary Feedwater Main Turbine | |
05000498/LER-2017-002 | South Texas | 22 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | HVAC Control Room Emergency Ventilation | Large early release frequency |
05000263/LER-2017-006 | Monticello | 14 November 2017 12 January 2018 | 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)(v), Loss of Safety Function | Reactor Coolant System Reactor Protection System Main Steam Isolation Valve Main Steam Line Main Steam | Safe Shutdown Half scram Fuel cladding |
05000306/LER-2017-003 | Prairie Island | 11 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)(i)(B), Prohibited by Technical Specifications | Service water Main Steam Isolation Valve Main Steam Line Containment Spray | |
05000364/LER-2017-005 | Farley Joseph M Farley Nuclear Plant, Unit 2 | 3 January 2017 11 January 2018 | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)() | | |
05000272/LER-2017-001 | Salem | 9 November 2017 8 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Steam Generator Reactor Coolant System | Safe Shutdown |
05000390/LER-2017-015 | Watts Bar | 9 November 2017 8 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | Safe Shutdown |
05000254/LER-2017-004 | Quad Cities | 7 November 2017 5 January 2018 | | Feedwater High Pressure Coolant Injection Core Spray Low Pressure Coolant Injection | |
05000461/LER-2017-009 | Clinton Clinton Power Station, Unit 1 . | 5 November 2017 4 January 2018 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Service water Standby Gas Treatment System | |
05000334/LER-2017-003 | Beaver Valley | 7 November 2017 4 January 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Steam Generator Feedwater Reactor Protection System Auxiliary Feedwater Control Rod | |
05000219/LER-2017-005 | Oyster Creek | 9 October 2017 3 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator | Safe Shutdown Mission time |
05000296/LER-2017-002 | Browns Ferry | 29 December 2017 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator | Safe Shutdown Unanalyzed Condition Time of Discovery Large early release frequency |
05000249/LER-2017-001 | Dresden | 27 December 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)(i)(B), Prohibited by Technical Specifications | Reactor Pressure Vessel Standby Liquid Control Control Rod | Time of Discovery Enforcement Discretion Through Wall Leak |
05000364/LER-2017-004 | Farley Joseph M. Farley Nuclear Plant. Unit 2 | 22 December 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Steam Generator Reactor Coolant System Main Steam Isolation Valve Auxiliary Feedwater Main Steam Line | |
05000395/LER-2017-005 | Summer | 7 January 2017 22 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Steam Generator Feedwater Decay Heat Removal Main Condenser Control Rod | Large early release frequency |
05000364/LER-2017-003 | Farley | 20 December 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Coolant System | Time of Discovery |
05000278/LER-2017-001 | Peach Bottom | 23 October 2017 20 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 | Time of Discovery Pressure Boundary Leakage |
05000390/LER-2017-016 | Watts Bar Nuclear Plant. Unit 1 | 20 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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 | Emergency Diesel Generator Auxiliary Feedwater | Safe Shutdown Offsite Circuit |
05000390/LER-2017-014 | Watts Bar | 30 October 2017 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 | Safe Shutdown Probabilistic Risk Assessment |
05000286/LER-2017-004 | Indian Point | 3 November 2017 20 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Permanent Magnet Generator Main Condenser Control Rod Main Steam | Temporary Modification |
05000364/LER-2017-002 | Farley | 19 December 2017 | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Steam Generator Reactor Coolant System Main Steam Safety Valve Main Condenser Main Steam | |
05000395/LER-2017-006 | Summer Vc Summer - Unit 1 | 31 October 2017 15 December 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | Grab sample |
05000261/LER-2017-002 | Robinson | 24 October 2017 14 December 2017 | | | Time of Discovery Contraband Scaffolding |
05000266/LER-2017-003 | Point Beach | 30 October 2017 13 December 2017 | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System | Safe Shutdown Boric Acid |