ENS 49709
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ENS Event | |
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01:43 Jan 10, 2014 | |
Title | Loss of Secondary Containment Differential Pressure |
Event Description | Reactor Building (Secondary Containment) pressure increased to above the Technical Specification Surveillance requirement of 0.25 inches vacuum water gauge briefly (two minutes or less) on two occasions. This 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. Reactor Building pressure has been restored to normal (greater than 0.25 inches vacuum water gauge) returning Secondary Containment to operable status. The cause of the event is under investigation.
There were no radiological releases associated with the event. No safety system actuations or isolations occurred. The licensee notified the NRC Resident Inspector. |
Where | |
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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:+0.52 h0.0217 days <br />0.0031 weeks <br />7.12296e-4 months <br />) | |
Opened: | Jason Lovegren 02:14 Jan 10, 2014 |
NRC Officer: | Dan Livermore |
Last Updated: | Jan 10, 2014 |
49709 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
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