ENS 49307: Difference between revisions
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| event date = 08/25/2013 18:18 PDT | | event date = 08/25/2013 18:18 PDT | ||
| last update date = 08/26/2013 | | last update date = 08/26/2013 | ||
| title = Loss | | title = Loss of Secondary Containment Differential Pressure | ||
| event text = Reactor Building (Secondary Containment) pressure increased to above the Technical Specification Surveillance requirement of 0,25 inches vacuum water gauge. This event is reportable as an event that could have prevented fulfillment of a safety function needed to control the release of radiation and mitigate the consequences of an accident. The Reactor Building differential pressure controller was placed in manual operation and Secondary Containment pressure was restored to normal (greater than 0.25 inches vacuum water gauge) returning Secondary Containment to operable status. Secondary Containment pressure was outside the allowable Technical Specification requirement for 4 minutes. | | event text = Reactor Building (Secondary Containment) pressure increased to above the Technical Specification Surveillance requirement of 0,25 inches vacuum water gauge. This event is reportable as an event that could have prevented fulfillment of a safety function needed to control the release of radiation and mitigate the consequences of an accident. The Reactor Building differential pressure controller was placed in manual operation and Secondary Containment pressure was restored to normal (greater than 0.25 inches vacuum water gauge) returning Secondary Containment to operable status. Secondary Containment pressure was outside the allowable Technical Specification requirement for 4 minutes. | ||
There were no radiological releases associated with the event. | There were no radiological releases associated with the event. | ||
Latest revision as of 22:00, 1 March 2018
| Where | |
|---|---|
Columbia Generating Station  Washington (NRC Region 4) | |
| Reporting | |
| 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:+-0.22 h-0.00917 days <br />-0.00131 weeks <br />-3.01356e-4 months <br />) | |
| Opened: | Greg Knudson 01:05 Aug 26, 2013 |
| NRC Officer: | Vince Klco |
| Last Updated: | Aug 26, 2013 |
| 49307 - NRC Website
| |
Columbia 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)(v)(C), Loss of Safety Function - Release of Radioactive Material | |