ENS Event | |
|---|---|
16:09 Jan 4, 2020 | |
| Title | Primary Containment Degraded |
| Event Description | At 1109 [EST] on 01/04/2020, it was determined that the primary containment leakage rate did not meet value La, defined in 10 CFR 50, Appendix J, 'Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors'. An additional, tested valve has been closed to maintain leakage below maximum allowable leakage, La. 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. |
| Where | |
|---|---|
Hatch  Georgia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-1.15 h-0.0479 days <br />-0.00685 weeks <br />-0.00158 months <br />) | |
| Opened: | Brandon Shuman 15:00 Jan 4, 2020 |
| NRC Officer: | Jeff Herrera |
| Last Updated: | Jan 4, 2020 |
| 54463 - NRC Website
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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 | |