ENS 54257
ENS Event | |
|---|---|
02:15 Sep 6, 2019 | |
| Title | En Revision Imported Date 11/8/2019 |
| Event Description | EN Revision Text: CONTAINMENT PENETRATION DISCOVERED NOT ISOLATED
At 2115 CDT on 9/5/2019, an inside containment test connection and inoperable outside containment isolation valve were discovered to be open for a containment air sample penetration. This resulted in the containment penetration not being isolated. The inside containment test connection was closed at 2322 CDT on 9/5/2019. This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and (D) and 10 CFR 50.72(b)(3)(ii)(B). There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
This event was originally reported on September 6, 2019 under 10 CFR 50.72(b)(3)(v)(C) and (D) and 10 CFR 50.72(b)(3)(ii)(B). Upon completion of the investigation of the event, it was determined that the event had insignificant safety consequences because the containment breach was disconnected from the Reactor Coolant System by a series of closed valves for the duration of the event. Additionally, the lines to the inside containment connection and the outside inoperable containment isolation valve that was found to be open as well as the main line connecting and passing through the penetration were one-inch diameter lines. Analysis determined that containment breaches that are less than a three-inch diameter do not lead to a large radiation release. The event did not place the plant in an unanalyzed condition that significantly degrades plant safety. Therefore, 10 CFR 50.72(b)(3)(ii)(B) did not apply to this event and this notification is to retract reporting under that criterion. The licensee notified the NRC Resident Inspector. Notified R4DO (Drake). |
| Where | |
|---|---|
South Texas  Texas (NRC Region 4) | |
| Reporting | |
| 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 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+0.53 h0.0221 days <br />0.00315 weeks <br />7.25994e-4 months <br />) | |
| Opened: | Michael Chandler 02:47 Sep 6, 2019 |
| NRC Officer: | Caty Nolan |
| Last Updated: | Nov 7, 2019 |
| 54257 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
South Texas with 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)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
WEEKMONTHYEARENS 572792024-08-21T01:10:00021 August 2024 01:10:00
[Table view]10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Control Room Filtration Systems Inoperable ENS 571462024-05-26T12:20:00026 May 2024 12:20:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Two of Three Essential Chilled Water Trains Declared Inoperable ENS 570192024-03-10T08:53:00010 March 2024 08:53:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Essential Chilled Water Trains Declared Inoperable ENS 569442024-01-24T01:02:00024 January 2024 01:02:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Accident Mitigation - Relief Valves Inoperable ENS 568612023-11-16T21:41:00016 November 2023 21:41:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Essential Chiller Trains Inoperable ENS 568482023-11-10T20:13:00010 November 2023 20:13:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Essential Chiller Trains Inoperable ENS 542572019-09-06T02:15:0006 September 2019 02:15:00 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, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material En Revision Imported Date 11/8/2019 ENS 541902019-07-30T20:21:00030 July 2019 20:21:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident En Revision Imported Date 8/22/2019 ENS 494902013-10-31T22:12:00031 October 2013 22:12:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Fire Event Could Result in a Hot Short That Could Adversely Impact Safe Shutdown Equipment ENS 482772012-08-22T17:36:00022 August 2012 17:36:00 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 Missing Flood Seal ENS 474912011-11-20T11:46:00020 November 2011 11:46:00 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 Turbine Trip Protection Disabled While in Mode 3 ENS 461462010-08-03T20:06:0003 August 2010 20:06:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Potential Safety System Functional Failure of the Accident Mitigating Function ENS 456312008-07-08T03:47:0008 July 2008 03:47:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Loss of Fire Suppression Capability ENS 406122004-03-27T04:30:00027 March 2004 04:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Regarding Hhsi Flush Line Isolation Valve Leakage - ENS 403802003-12-09T21:38:0009 December 2003 21:38:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unable to Achieve Cold Shutdown Using Natural Circulation at a Cooldown Rate of 50 Degrees Per Hour 2024-08-21T01:10:00 | |