ENS Event | |
|---|---|
07:30 Oct 10, 2025 | |
| Title | Degraded Control Rod Drive Mechanism Penetration |
| Event Description | The following information was provided by the licensee via phone and email:
At 0230 CDT, on October 10, 2025, it was determined that the control rod drive mechanism (CRDM) penetration '69' was degraded because liquid penetrant testing performed on the embedded flaw repair weld identified an unacceptable indication in accordance with American Society of Mechanical Engineers (ASME) Section Ill acceptance standards and NRC approved licensee relief request for a previously performed embedded flaw repair. Therefore, 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 | |
|---|---|
Braidwood  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+1.92 h0.08 days <br />0.0114 weeks <br />0.00263 months <br />) | |
| Opened: | Sam Keller 09:25 Oct 10, 2025 |
| NRC Officer: | Ian Howard |
| Last Updated: | Oct 10, 2025 |
| 57978 - NRC Website
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WEEKMONTHYEARENS 579782025-10-10T07:30:00010 October 2025 07:30:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Control Rod Drive Mechanism Penetration ENS 561532022-10-07T06:19:0007 October 2022 06:19:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Control Rod Drive Mechanism (CRDM) Penetration Degraded ENS 536522018-10-08T05:00:0008 October 2018 05:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Leakage ENS 533542018-04-20T22:30:00020 April 2018 22:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Reactor Vessel Head ENS 522752016-10-02T21:00:0002 October 2016 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Liquid Penetration Examination Results in Indications on Reactor Vessel Head Penetration ENS 509532015-04-03T21:31:0003 April 2015 21:31:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Liquid Penetration Examination Results in Indication on Reactor Vessel Head Penetration ENS 493532013-09-18T10:10:00018 September 2013 10:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Boroscopic Inspection of Reactor Vessel Head Determined Evidence of Boundary Leakage ENS 493432013-09-14T07:00:00014 September 2013 07:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Liquid Penetration Examination Results in Indication on Reactor Vessel Head Penetration ENS 479342012-04-23T06:00:00023 April 2012 06:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Ultrasonic Examination Results in an Indication on the Reactor Pressure Vessel Head Penetration 2025-10-10T07:30:00 | |