ML21196A485
From kanterella
ML21196A485 | |
Person / Time | |
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Site: | Peach Bottom |
Issue date: | 07/16/2021 |
From: | Herr M Exelon Generation Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
CCN: 21-68 LER 2-2021-002-00 | |
Download: ML21196A485 (4) | |
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Category:Letter
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IR 05000277/20244022024-03-12012 March 2024 Cybersecurity Inspection Report 05000277/2024402 and 05000278/2024402 (Cover Letter Only) ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners ML24060A1192024-02-29029 February 2024 Notification of Conduct of a Fire Protection Team Inspection 2024-09-06 Category:Licensee Event Report (LER) MONTHYEAR05000277/LER-2024-003, Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum2024-09-0505 September 2024
[Table view]Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum 05000277/LER-2024-002, Uncoordinated DC Circuits Cause Unanalyzed Condition2024-04-0808 April 2024 Uncoordinated DC Circuits Cause Unanalyzed Condition 05000277/LER-2024-001, Automatic Reactor Scram Due to an Invalid Generator Lockout2024-03-21021 March 2024 Automatic Reactor Scram Due to an Invalid Generator Lockout 05000278/LER-2023-002, Main Steam Isolation Valves Stroke Times Exceed Technical Specification Limit2023-12-14014 December 2023 Main Steam Isolation Valves Stroke Times Exceed Technical Specification Limit 05000278/LER-2023-001, Standby Liquid Control Pump Inoperable for Greater than LCO Window Due to Gas Intrusion2023-11-0707 November 2023 Standby Liquid Control Pump Inoperable for Greater than LCO Window Due to Gas Intrusion 05000277/LER-2022-002, Automatic Depressurization System Safety Relief Valve Actuator Diaphragm Degraded2022-12-15015 December 2022 Automatic Depressurization System Safety Relief Valve Actuator Diaphragm Degraded 05000277/LER-2022-001, Automatic Reactor Scram Due to Loss of Power to Both RPS Buses2022-07-15015 July 2022 Automatic Reactor Scram Due to Loss of Power to Both RPS Buses 05000277/LER-2021-003, Manual Reactor Scram Due to Degrading Condenser Vacuum2022-01-12012 January 2022 Manual Reactor Scram Due to Degrading Condenser Vacuum ML21196A4852021-07-16016 July 2021 LER 2-2021-002-00 for Peach Bottom Atomic Power Station, Unit 2, Safety Relief Valve Inoperability Due to Nitrogen Leakage from Braided Hose Wear 05000278/LER-2017-0012017-12-20020 December 2017 Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line, LER 17-001-00 for Peach Bottom Atomic Power Station (PBAPS), Unit 3 Regarding Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line 05000277/LER-2017-0012017-03-0808 March 2017 Emergency Diesel Generator Exhaust Stacks Nonconforming Design for Tornado Missile Protection, LER 17-001-00 for Peach Bottom Atomic Power Station (PBAPS), Unit 2 Regarding Emergency Diesel Generator Exhaust Stacks Nonconforming Design for Tornado Missile Protection 05000278/LER-2016-0012016-11-22022 November 2016 Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function, LER 16-001-00 for Peach Bottom, Unit 3, Regarding Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function 05000277/LER-2016-0012016-11-11011 November 2016 Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications, LER 16-001-00 for Peach Bottom, Unit 2, Regarding Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications 05000278/LER-2015-0012016-02-26026 February 2016 Loss of High Pressure Coolant Injection System Function as a Result of Failed Flow Controller Signal Converter, LER 15-001-00 for Peach Bottom, Unit 3, Regarding Loss of High Pressure Coolant Injection System Function as a Result of Failed Flow Controller Signal Converter ML13058A0432013-02-22022 February 2013 Submittal of Independent Spent Fuel Storage Installation (ISFSI) Cask Event Report ML1007702362010-03-12012 March 2010 60-Day Security Event Report 2-10-S01 ML0927401622009-09-30030 September 2009 LER 09-S01-00 for Peach Bottom, Units 2 & 3 Regarding Unescorted Access Granted to Contract Worker Who Did Not Provide Complete Work History Information ML1015505682009-07-10010 July 2009 Event Notification for Peach Bottom on Elevated Tritium Levels Found in On-Site Well ML0434503772004-12-10010 December 2004 LER-04-S01-00 for Peach Bottom Atomic Power Station (PBAPS) Unit 2 and Unit 3, 60 Day Security Event Report 2-04-S01 ML19095A7391976-12-0505 December 1976 Reporting Abnormal Occurrence No. 50-278-74-33 at Peach Bottom Atomic Power Station for Failure of Main Steam Line High Flow Switch dPIS-3-2-116C to Trip During Surveillance Test 2024-09-05 |
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