ENS 51274
ENS Event | |
|---|---|
17:58 Jul 28, 2015 | |
| Title | Discovered One Inch Diameter Hole Between Reactor Building and Auxiliary Building |
| Event Description | At 1358 [EDT] on July 28, 2015, a 1 inch diameter hole was discovered in the secondary containment wall, between the Reactor Building and the Auxiliary Building, causing the Secondary Containment to become inoperable under Technical Specification 3.6.5.1. Reactor Building pressure was maintained at a negative pressure as required by Technical Specification 3.6.5.1 with the Reactor Building ventilation system in service before and after discovery of the hole. In addition, the Filtration, Recirculation and Ventilation system remained fully operable and remained in standby. The hole was sealed at 1600 and technical specification 3.6.5.1 was exited. Plant operation was not impacted by the event and was operating at 100% power. No personnel injuries resulted from this event.
The hole was discovered by plant personnel that were walking past the wall. Due to the discovery of the hole, the plant is performing an extent of condition inspection. The licensee notified the NRC Resident Inspector and the Lower Alloways Creek Dispatch.
This event is being retracted. Hope Creek Generating Station Unit 1, is retracting the 8-hour non-emergency notification (EN 51274) made on July 28, 2015, at 1855 EDT. The notification on July 28, 2015, reported that secondary containment was declared inoperable when a 1 inch hole was discovered in the secondary containment wall, between the Reactor Building and the Auxiliary Building. Secondary containment was declared inoperable based on the initial interpretation of the definition of secondary containment. The hole did not impact the ability to maintain the Tech Spec required negative pressure. Subsequent evaluation determined that secondary containment was always operable. Based on the engineering evaluation, the condition reported in EN 51274 did not result in an inoperability of the secondary containment. Therefore, there is no reportable condition and this event report is being retracted. The NRC Resident Inspector has been briefed on the evaluation results and informed of this retraction. The licensee also notified the Lower Alloways Creek Dispatch. Notified R1DO (Powell). |
| Where | |
|---|---|
Hope Creek  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| Time - Person (Reporting Time:+0.95 h0.0396 days <br />0.00565 weeks <br />0.0013 months <br />) | |
| Opened: | Mariaz Davis 18:55 Jul 28, 2015 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Aug 12, 2015 |
| 51274 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 512742015-07-28T17:58:00028 July 2015 17:58:00
[Table view]10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Discovered One Inch Diameter Hole Between Reactor Building and Auxiliary Building ENS 496652013-12-19T20:11:00019 December 2013 20:11:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Loss of Reactor Building Ventilation ENS 450482009-05-08T12:17:0008 May 2009 12:17:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Primary Containment Isolation Valves Discovered Open ENS 409962004-08-29T23:28:00029 August 2004 23:28:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Alarm Indication of Inoperable Reactor Water Cleanup Supply Isolation Valve 2015-07-28T17:58:00 | |