ENS Event | |
|---|---|
13:37 Feb 17, 2024 | |
| Title | Primary Containment Degraded |
| Event Description | The following information was provided by the licensee via email and phone call:
At 0837 EST, on 02/17/2024, during a refueling outage at 0 percent power while performing local leak rate testing (LLRT) on the reactor core isolation cooling (RCIC) isolation valves, which is part of the containment boundary, it was determined that the Unit 1 primary containment leakage rate did not meet 10 CFR 50 Appendix J requirements specified in Technical Specification 5.5.12. 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 | |
|---|---|
Brunswick  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.5 h0.0208 days <br />0.00298 weeks <br />6.849e-4 months <br />) | |
| Opened: | Christopher Denton 14:07 Feb 17, 2024 |
| NRC Officer: | Thomas Herrity |
| Last Updated: | Feb 17, 2024 |
| 56974 - NRC Website
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WEEKMONTHYEARENS 569742024-02-17T13:37:00017 February 2024 13:37:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 441022008-03-27T20:45:00027 March 2008 20:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unacceptable Flaw Found in Rpv Cap to Pipe Weld 2024-02-17T13:37:00 | |