WEEKMONTHYEAR05000454/LER-2024-002, Reactor Vessel Closure Head Penetration 31 Degraded2024-11-070Start date: 7 November 2024 Site: Byron Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-050Start date: 5 September 2024 Site: Hope Creek Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000389/LER-2024-002-01, Safety Injection Tank Vent Through Wall Leakage2024-07-110Start date: 11 July 2024 Site: Saint Lucie Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2) 05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-020Start date: 2 July 2024 Site: Hope Creek Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-020Start date: 2 July 2024 Site: Beaver Valley Reporting criterion: 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)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000341/LER-2024-001, Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-222024-05-150Start date: 15 May 2024 Site: Fermi Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000325/LER-2024-001, Primary Containment Penetration Local Leak Rate Testing Failure2024-04-100Start date: 10 April 2024 Site: Brunswick Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000321/LER-2024-001, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2024-04-090Start date: 9 April 2024 Site: Hatch Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000389/LER-2024-002, Safety Injection Tank Vent Through Wall Leakage2024-02-290Start date: 29 February 2024 Site: Saint Lucie Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000389/LER-2024-001, Safety Injection Tank Vent Through Wall Leakage2024-02-130Start date: 13 February 2024 Site: Saint Lucie Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000382/LER-2023-003, Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing2023-12-300Start date: 30 December 2023 Site: Waterford Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000260/LER-2023-001-01, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue Failure2023-09-180Start date: 18 September 2023 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000455/LER-2022-001-01, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking2023-08-310Start date: 31 August 2023 Site: Byron Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000220/LER-2023-001-01, Supplement to NMP1 Indication on the N2E Dissimilar Metal Weld Exceeding ASME Acceptance Criteria2023-08-110Start date: 11 August 2023 Site: Nine Mile Point Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000296/LER-2022-003-01, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure2023-07-310Start date: 31 July 2023 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000412/LER-2023-001, Indications Identified During Reactor Vessel Head Inspection2023-06-160Start date: 16 June 2023 Site: Beaver Valley Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000443/LER-2023-001, Automatic Actuation of B Emergency Diesel Generator Emergency Power Sequencer2023-06-120Start date: 12 June 2023 Site: Seabrook Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000388/LER-2023-001, Secondary Containment Bypass Leakage Limit Exceeded Due Inadequate Procedure Guidance Resulting in Failure of the Inboard Containment Isolation Valve to Close and Pressurize2023-05-250Start date: 25 May 2023 Site: Susquehanna Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000374/LER-2021-002-02, Supplement to Reactor Protection System Half Scram Due to Motor Generator Set Output Breaker Trip2023-05-250Start date: 25 May 2023 Site: LaSalle Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(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), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000260/LER-2023-001, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line2023-04-190Start date: 19 April 2023 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000366/LER-2023-001, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2023-04-050Start date: 5 April 2023 Site: Hatch Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000374/LER-1922-003-01, Manual Scram Due to Lsophase Bus Duct Fire Followed by 2A RPS Normal Power Supply Trip2023-02-090Start date: 9 February 2023 Site: LaSalle 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)(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), 10 CFR 50.73(a)(2)(1) 05000296/LER-2022-003, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line2023-01-310Start date: 31 January 2023 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000269/LER-1922-002, Reactor Coolant Oconee Nuclear Station, Unit 1, System Pressure Boundary Leak on Reactor Coolant Pump Lower Bearing Thermowell2023-01-120Start date: 12 January 2023 Site: Oconee Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000382/LER-2022-001-01, On Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors2023-01-030Start date: 3 January 2023 Site: Waterford Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(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) 05000323/LER-2022-001, Reactor Coolant System Pressure Boundary Degradation2022-12-210Start date: 21 December 2022 Site: Diablo Canyon Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000269/LER-2022-001, Ultrasonic Examination Indications Identifies Degraded Reactor Coolant System Pressure Boundary2022-12-210Start date: 21 December 2022 Site: Oconee Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000483/LER-2022-003, Submittal of Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2022-12-210Start date: 21 December 2022 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)(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) 05000414/LER-2022-002, Indications Identified During Reactor Vessel Head Penetration Embedded Flaw Repair Surface Examination2022-12-060Start date: 6 December 2022 Site: Catawba Reporting criterion: 10 CFR 50.73(a)(1), Submit an LER, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000456/LER-2022-001, Liquid Penetrant Indications in Control Rod Drive Mechanism Nozzle Seal Weld Repair Due to Subsurface Weld Defects Opening Up from Thermal and Pressure Stresses During Operation2022-11-300Start date: 30 November 2022 Site: Braidwood Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 05000382/LER-2022-006, Non-Compliance with Technical Specifications Due to Incorrect Conversion Factors in Plant Stack and Fuel Handling Building Radiation Monitors2022-11-070Start date: 7 November 2022 Site: Waterford Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(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) 05000335/LER-2022-002, Condition Prohibited by Technical Specifications2022-10-280Start date: 28 October 2022 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)(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) 05000416/LER-2022-001, For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 232022-08-290Start date: 29 August 2022 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)(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)(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-2022-002, Automatic Actuation of Emergency Feedwater System Due to Malfunctioning Startup Feedwater Control Valve2022-07-010Start date: 1 July 2022 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)(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) 05000397/LER-2021-002-01, Integrated Leak Rate Test2022-06-090Start date: 9 June 2022 Site: Columbia Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000259/LER-2022-001-01, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line2022-05-310Start date: 31 May 2022 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000270/LER-2022-003, Manual Reactor Trip Due to Main Feedwater Control Valve Positioner Malfunction2022-04-210Start date: 21 April 2022 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)(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) 05000270/LER-2022-002, Regarding Automatic Actuation of Emergency Feedwater System Due to Main Feedwater Pump Malfunction2022-04-140Start date: 14 April 2022 Site: Oconee Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(viii)(A) 05000270/LER-2022-001, Regarding Automatic Reactor Trip Due to Loss of Power to Reactor Coolant Pumps2022-04-060Start date: 6 April 2022 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)(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-2022-001, Response Actions Resulted in Brief Inoperability of Both Onsite and Offsite Emergency AC Power Paths2022-03-280Start date: 28 March 2022 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)(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) 05000250/LER-2021-004, Cancelation of LER 2021-004, Through-Wall Leakage from Core Exit Thermocouple Tubing2022-03-280Start date: 28 March 2022 Site: Turkey Point Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000259/LER-2022-001, From Browns Ferry Nuclear Plant, Unit 1 Regarding Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line2022-03-160Start date: 16 March 2022 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000389/LER-2022-001, Reactor Shutdown Required by Technical Specifications Due to a Misaligned Control Element Assembly2022-03-040Start date: 4 March 2022 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)(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) 05000270/LER-2021-005, Automatic Reactor Trip Due to Spurious Trip Signal Concurrent with System Testing2022-02-080Start date: 8 February 2022 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)(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) 05000270/LER-2021-003, Conditions Prohibited by Technical Specifications Due to Ssf and Psw Inoperability2022-02-070Start date: 7 February 2022 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)(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) 05000270/LER-2021-004, More than One Axial Power Shaping Rod Not Aligned within Technical Specification Limits2022-02-070Start date: 7 February 2022 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)(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) 05000335/LER-2021-001, Manual Reactor Trip Due to Insufficient Feed Flow to Steam Generators2022-02-040Start date: 4 February 2022 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)(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) 05000270/LER-2021-002, Actuation of the Keowee Hydroelectric Station Due to Loss of AC Power to the Unit 2 Main Feeder Buses2022-01-260Start date: 26 January 2022 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)(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) 05000412/LER-2021-003, Indications Identified During Reactor Vessel Head Inspection2021-12-170Start date: 17 December 2021 Site: Beaver Valley Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000368/LER-2021-002, Material Defect in Primary Coolant System That Cannot Be Found Acceptable Under American Society of Mechanical Engineers Section XI2021-12-010Start date: 1 December 2021 Site: Arkansas Nuclear Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000397/LER-2021-002, Integrated Leak Rate Test2021-11-290Start date: 29 November 2021 Site: Columbia Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000389/LER-2021-002, Foreign Material Exclusion Device Found in Containment Spray System2021-11-100Start date: 10 November 2021 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)(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) 05000266/LER-2021-001, Main Feedwater Pump Trip Results in Manual Reactor Trip2021-09-280Start date: 28 September 2021 Site: Point Beach Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000416/LER-2020-002-02, Reactor Scram Due to Main Turbine Trip2021-08-190Start date: 19 August 2021 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)(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-2020-005-02, Primarv Water Svstem Flow Lowered Causinc Turbine Trio and Subseauent Reactor Scram2021-08-190Start date: 19 August 2021 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)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(viii)(A) 05000414/LER-2021-003, Re Containment Penetration Failure Resulting in Integrated Leak Rate Test Failure2021-07-260Start date: 26 July 2021 Site: Catawba Reporting criterion: 10 CFR 50.73(a)(1), Submit an LER, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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) 05000318/LER-2021-001, Calvert Cliff Nuclear Power Plant Unit No. 2, Pressure Heater Sleeve Weld Pressure Boundary Leakage Caused by Primary Water Stress Corrosion Cracking2021-04-210Start date: 21 April 2021 Site: Calvert Cliffs 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)(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), 10 CFR 50.73(a)(2)(1) 05000483/LER-2021-001, Manual Actuation of Essential Service Water System2021-04-080Start date: 8 April 2021 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)(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), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000389/LER-2021-001, Automatic Reactor Trip Due to a Breaker Failure on the 2B2 480V Motor Control Center2021-03-100Start date: 10 March 2021 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)(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) 05000317/LER-2020-001, Regarding Undervoltage Condition on 4.16kV Electrical Bus 11 Resulted in Actuation of Emergency Diesel Generator 1 a2021-01-270Start date: 27 January 2021 Site: Calvert Cliffs 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)(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) 05000391/LER-2020-004, Steam Generators Degraded Due to Axial Outside Diameter Stress Corrosion Cracking2021-01-070Start date: 7 January 2021 Site: Watts Bar Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000277/LER-2020-002, Degraded Condition Due to RPV Instrument Nozzle Leakage2020-12-220Start date: 22 December 2020 Site: Peach Bottom Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000266/LER-2020-001, Re Reactor Coolant System Pressure Boundary Leak on Steam Generator Bowl Drain Line Results in Operation Prohibited by Technical Specifications2020-11-250Start date: 25 November 2020 Site: Point Beach 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)(ii)(A), Seriously Degraded, 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), 10 CFR 50.73(a)(2)(viii)(B), 10 CFR 50.73(a)(2)(1) 05000255/LER-2020-002, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations2020-11-050Start date: 5 November 2020 Site: Palisades Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 05000413/LER-2020-002, Re Unacceptable Indication Identified During Reactor Pressure Vessel Head Nozzle Penetration Inspection2020-07-300Start date: 30 July 2020 Site: Catawba 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)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000443/LER-2020-001, Manual Reactor Trips Due to Control Rod Bank Unexpectedly Inserting2020-07-270Start date: 27 July 2020 Site: Seabrook Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000391/LER-2020-001, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open2020-07-150Start date: 15 July 2020 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)(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-2020-002, Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 1B-B Shutdown Board2020-07-140Start date: 14 July 2020 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)(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) 05000413/LER-2020-002-01, Unacceptable Indication Identified During Reactor Pressure Vessel Head Nozzle Penetration Inspection2020-07-130Start date: 13 July 2020 Site: Catawba 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)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000296/LER-2020-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2020-07-070Start date: 7 July 2020 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000272/LER-2020-002, Unit 2 RHR Availability for Emergency Core Cooling in Mode 42020-07-060Start date: 6 July 2020 Site: Salem Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000482/LER-2020-001-01, Plant Shutdown Due to Inoperable Containment Purge Isolation Valves2020-07-060Start date: 6 July 2020 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)(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) 05000220/LER-2020-001, Control Room Air Treatment System Inoperable2020-07-020Start date: 2 July 2020 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)(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-2020-001, Automatic Reactor Scram Due to Main Turbine Trip2020-07-010Start date: 1 July 2020 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)(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) 05000400/LER-2020-001-01, Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance2020-06-290Start date: 29 June 2020 Site: Harris Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000316/LER-2020-002, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Leakage2020-06-250Start date: 25 June 2020 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)(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) 05000250/LER-2020-001, Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units2020-06-240Start date: 24 June 2020 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)(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-2020-002, 3, Automatic Reactor Trip Due to Main Generator Ground Fault2020-05-280Start date: 28 May 2020 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)(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)(B) 05000265/LER-2020-002, Electromatic Relief Valve 3D Did Not Actuate Due to Out of Specification Plunger2020-05-280Start date: 28 May 2020 Site: Quad Cities Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A) 05000272/LER-2020-001, Station, Unit 1, Manual Reactor Trip and Auxiliary Feed Water System Actuation2020-05-260Start date: 26 May 2020 Site: Salem Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000498/LER-2020-001, Automatic Actuation of Emergency Diesel Generators Due to Lockout of Switchyard Electrical Bus2020-05-220Start date: 22 May 2020 Site: South Texas Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000400/LER-2020-001, Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance2020-05-210Start date: 21 May 2020 Site: Harris Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000325/LER-2020-001, Manual Reactor Scram During Startup Due to All Bypass Valves Fully Opening2020-05-200Start date: 20 May 2020 Site: Brunswick Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000265/LER-2020-001, Loss of Both Divisions of Residual Heat Removal Low Pressure Coolant Injection Due to Swing Bus Failure to Transfer2020-05-190Start date: 19 May 2020 Site: Quad Cities 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)(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) 05000325/LER-2020-002, Technical Specification Required Shutdown Due to Unidentified Leakage2020-05-180Start date: 18 May 2020 Site: Brunswick Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000382/LER-2020-001, (Waterford 3), Violation of Technical Specification 3.3.3.7.3.a (Broad Range Gas Detection) Due to Operators and Maintenance Technicians Not Performing Procedure Step as Intended2020-05-070Start date: 7 May 2020 Site: Waterford Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000296/LER-2020-001, Automatic Actuation of Emergency Diesel Generators Due to an Offsite Lightning Strike2020-05-040Start date: 4 May 2020 Site: Browns Ferry Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000327/LER-2019-003-01, 1 for Sequoyah Nuclear Plant, Unit 1, Automatic Reactor Trio Due to Negative Rate Trip as a Result of a Dropped Control Rod2020-04-250Start date: 25 April 2020 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)(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)(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) 05000530/LER-2020-001, Condition Prohibited by Technical Specifications Due to Inoperable Spray Pond Pump2020-04-240Start date: 24 April 2020 Site: Palo Verde Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000389/LER-2020-001, Turbine Loss of Load Trip Found Outside Technical Specification Allowable Range Due to Unspecified Legacy M&TE or Calibration Deficiencies2020-04-220Start date: 22 April 2020 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)(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) 05000341/LER-2020-001, Secondary Containment Inoperable Due to Both Airlock Doors Open2020-04-220Start date: 22 April 2020 Site: Fermi Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000483/LER-2020-001, Emergency Exhaust Train Inoperable Due to Fan Belt Degradation and Failure2020-04-170Start date: 17 April 2020 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)(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), 10 CFR 50.73(a)(2)(viii)(B) 05000390/LER-2020-001, Manual Reactor Trip Due to Lowering Steam Generator Level Caused by a Hand Station Failure2020-04-170Start date: 17 April 2020 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)(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) 05000440/LER-2020-001, Combustible Gas Mixing Compressor Was Declared Inoperable Due to Degraded Thermal Overloads Resulting in Technical Specification Violation2020-04-090Start date: 9 April 2020 Site: Perry 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)(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), 10 CFR 50.73(a)(2)(viii)(B) 05000382/LER-2019-005-01, Automatic Reactor Scram Due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback Due to Failed Diode Modules with the Main Exciter2020-04-080Start date: 8 April 2020 Site: Waterford Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000366/LER-2020-001, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2020-03-020Start date: 2 March 2020 Site: Hatch Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(1) 05000446/LER-2020-001, Manual Reactor Trip Due to Trip of Both Main Feedwater Pumps2020-02-270Start date: 27 February 2020 Site: Comanche Peak 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)(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)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000341/LER-2019-006, Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Damper Malfunction2020-02-140Start date: 14 February 2020 Site: Fermi Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B) 05000423/LER-2019-001, Regarding Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time2020-02-130Start date: 13 February 2020 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)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.73(a)(2)(v), Loss of Safety Function, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications, 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded, 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System, 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(viii)(B)
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