ENS Event | |
|---|---|
16:11 Feb 22, 2025 | |
| Title | Primary Containment Degraded |
| Event Description | The following information was provided by the licensee via phone and email:
At 1111 EST on 02/22/2025, while in mode 5 at 0 percent power, it was determined during local leak rate testing (LLRT) that the Unit 2 primary containment leakage rate exceeded the allowable limit (La) as defined in 10 CFR 50, Appendix J, `Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors' due to both primary containment isolation valves in a penetration failing LLRT requirements. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The valves that failed the LLRT are located in the torus purge line. The licensee's corrective action is to remove and repair the valves. |
| Where | |
|---|---|
Hatch  Georgia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-2.93 h-0.122 days <br />-0.0174 weeks <br />-0.00401 months <br />) | |
| Opened: | John Campbell 13:15 Feb 22, 2025 |
| NRC Officer: | Karen Cotton-Gross |
| Last Updated: | Feb 22, 2025 |
| 57567 - NRC Website
Loading map... | |
WEEKMONTHYEARENS 575672025-02-22T16:11:00022 February 2025 16:11:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 569592024-02-11T15:11:00011 February 2024 15:11:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 563422023-02-07T22:38:0007 February 2023 22:38:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 544632020-01-04T16:09:0004 January 2020 16:09:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 525672017-02-20T04:23:00020 February 2017 04:23:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Penetration Exceeded Allowable Leakage ENS 517422016-02-16T11:31:00016 February 2016 11:31:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Weld Overlay Flaw Did Not Meet Acceptance Criteria ENS 487952013-02-28T16:55:00028 February 2013 16:55:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Closed Cooling Water Isolation Valve Fails Local Leak Rate Test ENS 487722013-02-20T10:28:00020 February 2013 10:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Containment Penetration Fails Local Leak-Rate Testing ENS 440382008-03-06T09:00:0006 March 2008 09:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pin Hole Leak Discovered in 1 Inch Instrument Line During Rpv Pressure Test ENS 440052008-02-23T21:00:00023 February 2008 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unacceptable Flaw in Rpv Cap-To-Pipe Weld ENS 432242007-03-09T05:30:0009 March 2007 05:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Main Steam Line Flow Instrument Line Pressure Boundary Leakage ENS 423722006-02-23T23:50:00023 February 2006 23:50:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Shroud Tie Rods 2025-02-22T16:11:00 | |