ENS Event | |
|---|---|
23:03 Mar 3, 2025 | |
| Title | Degraded Condition |
| Event Description | The following information was provided by the licensee via phone and email:
At 1803 EST on 03/03/25, it was determined that the reactor coolant system pressure boundary does not meet American Society of Mechanical Engineers (ASME) section XI, Table IWB-341 0-1, 'Acceptable Standards' due to a through wall leak where the thimble tube connects to penetration number 6. The cause of this event is currently being investigated. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Turkey Point  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-0.52 h-0.0217 days <br />-0.0031 weeks <br />-7.12296e-4 months <br />) | |
| Opened: | Arturo Alvarez 22:32 Mar 3, 2025 |
| NRC Officer: | Ernest West |
| Last Updated: | Mar 3, 2025 |
| 57583 - NRC Website
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WEEKMONTHYEARENS 575832025-03-03T23:03:0003 March 2025 23:03:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition ENS 564742023-04-15T15:12:00015 April 2023 15:12:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded RCS Pressure Boundary Degraded ENS 555742021-11-12T21:05:00012 November 2021 21:05:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 499332014-03-20T02:02:00020 March 2014 02:02:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Leak Discovered Around Pressurizer Heater Bank ENS 463622010-10-26T02:00:00026 October 2010 02:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Liner Corrosion Degradation ENS 443992008-08-07T16:30:0007 August 2008 16:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Principal Safety Barrier ENS 436412007-09-14T03:04:00014 September 2007 03:04:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Reactor Pressure Boundary Leakage ENS 436272007-09-08T16:28:0008 September 2007 16:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Boundary Leakage 2025-03-03T23:03:00 | |