ENS 54680
From kanterella
ENS Event | |
|---|---|
05:30 Apr 24, 2020 | |
| Title | Reactor Coolant System (Rcs) Pressure Boundary Degraded |
| Event Description | At 0130 [EDT] on April 24, 2020, during the Beaver Valley Power Station, Unit 2 refueling outage, while performing examinations of the 66 reactor vessel head penetrations, it was determined that one penetration could not be dispositioned as acceptable per ASME Code Section XI. Penetration 37 will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-4 to find potential flaws/indications before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. 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 | |
|---|---|
Beaver Valley  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+1.5 h0.0625 days <br />0.00893 weeks <br />0.00205 months <br />) | |
| Opened: | Justin E. Crocker 07:00 Apr 24, 2020 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Apr 24, 2020 |
| 54680 - NRC Website | |
WEEKMONTHYEARENS 564852023-04-22T23:42:00022 April 2023 23:42:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 555402021-10-22T05:04:00022 October 2021 05:04:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 546802020-04-24T05:30:00024 April 2020 05:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (Rcs) Pressure Boundary Degraded ENS 543372019-10-17T23:51:00017 October 2019 23:51:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 537112018-11-01T04:00:0001 November 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Discovery of Indications That Did Not Meet Acceptance Criteria on One Reactor Vessel Head Penetration ENS 514532015-10-05T12:15:0005 October 2015 12:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Two Reactor Vessel Head Penetrations Could Not Be Dispositioned as Acceptable ENS 500792014-05-01T20:10:0001 May 2014 20:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Reactor Vessel Head Control Rod Drive Penetration ENS 494132013-10-05T03:24:0005 October 2013 03:24:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unexpected Containment Liner Penetration Found ENS 483872012-10-06T20:35:0006 October 2012 20:35:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded One of Sixty Six Reactor Vessel Penetrations Did Not Meet Acceptance Criteria ENS 467442011-04-10T07:45:00010 April 2011 07:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Manual Reactor Trip While Performing a Technical Specification Required Shutdown ENS 454632009-10-23T21:00:00023 October 2009 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Small Circumferential Indications Found on Two Reactor Vessel Head Penetrations ENS 450222009-04-26T14:00:00026 April 2009 14:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Ndt Reveals Circumferential Indications on Rcs Hot Leg Drain Piping ENS 450152009-04-23T14:15:00023 April 2009 14:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Damaged Area in Containment Liner 2023-04-22T23:42:00 | |
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