ENS 57115
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ENS Event | |
|---|---|
12:00 May 9, 2024 | |
| Title | Containment Bypass Condition Due to Degraded River Water Piping |
| Event Description | The following information was provided by the licensee via phone and email:
At 0800 EDT on May 9, 2024, it was identified during leak rate testing that through-wall flaws existed on reactor plant river water piping inside the containment building. This determination resulted in a containment bypass condition such that a gaseous release could have occurred at a location not analyzed for a release in the loss of coolant accident dose consequence analysis. This condition is not bounded by existing design and licensing documents. Evaluation of the condition of the piping is ongoing to support repair prior to startup. With the plant currently in cold shutdown, the containment, as specified in Technical Specification 3.6.1, is not required to be operable. There was no impact on the health and safety of the public or plant personnel. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A), 10 CFR 50.72(b)(3)(ii)(B), and 10 CFR 50.72(b)(3)(v)(C). 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 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| Time - Person (Reporting Time:+-0.2 h-0.00833 days <br />-0.00119 weeks <br />-2.7396e-4 months <br />) | |
| Opened: | Shawn Snook 11:48 May 9, 2024 |
| NRC Officer: | Sam Colvard |
| Last Updated: | May 9, 2024 |
| 57115 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
Beaver Valley with 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
WEEKMONTHYEARENS 571152024-05-09T12:00:0009 May 2024 12:00:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Containment Bypass Condition Due to Degraded River Water Piping ENS 565692023-06-11T05:30:00011 June 2023 05:30:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition ENS 564852023-04-22T23:42:00022 April 2023 23:42:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 563502023-02-12T13:00:00012 February 2023 13:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Control Room Emergency Ventilation System Inoperable 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 543662019-11-02T19:15:0002 November 2019 19:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Refueling Water Storage Tank Declared Inoperable Due to Low Level 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 535482018-08-12T04:00:00012 August 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown En Revision Imported Date 8/17/2018 ENS 534192018-05-22T04:00:00022 May 2018 04:00:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown En Revision Imported Date 6/22/2018 ENS 525712017-02-23T15:40:00023 February 2017 15:40:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Tornado Missile Vulnerabilities ENS 521322016-07-29T01:20:00029 July 2016 01:20:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Fire Event That Could Adversely Impact Safe Shutdown Equipment 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 500752014-04-30T15:40:00030 April 2014 15:40:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event Could Adversely Impact Safe Shutdown Equipment 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 474032011-11-02T18:30:0002 November 2011 18:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Caused by Non-Conforming Fire Barriers 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 464212010-11-16T05:01:00016 November 2010 05:01:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Control Room Envelope Inoperable Due to Excessive Emergency Core Cooling System Relief Valve Leakage During Eccs Pump Surveillance Testing ENS 462082010-08-26T20:49:00026 August 2010 20:49:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Both Trains of High Head Safety Injection Pumps Declared Inoperable 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 ENS 428692006-10-01T12:35:0001 October 2006 12:35:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Temporary Scaffolding for Upcoming Outage Renders 'A' and 'B' Msiv Inoperable ENS 400492003-08-06T20:30:0006 August 2003 20:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition 2024-05-09T12:00:00 | |
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