ENS 49694
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ENS Event | |
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08:45 Jan 6, 2014 | |
Title | Secondary Containment Differential Pressure Exceeded Technical Specification |
Event Description | At 0245 CST secondary containment differential pressure exceeded the Technical Specifications limit due to a personnel error manipulating an incorrect component. This caused entry into LCO 3.6.4.1 for secondary containment inoperability. An event or condition that could have prevented fulfillment of a safety function requires an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report per 10CFR50.72(b)(3)(v)(C) for Control of Rad Release and 10CFR50.72(b)(3)(v)(D) for Accident Mitigation. The error was corrected and secondary containment pressure was restored to greater than or equal to 0.25 inch vacuum water gauge and secondary containment was declared operable at 0302 CST. The NRC Resident has been informed of this condition. |
Where | |
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Cooper ![]() Nebraska (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 | |
LER: | 05000298/LER-2014-001 |
Time - Person (Reporting Time:+1.77 h0.0738 days <br />0.0105 weeks <br />0.00242 months <br />) | |
Opened: | Brian Hasselbring 10:31 Jan 6, 2014 |
NRC Officer: | Charles Teal |
Last Updated: | Jan 6, 2014 |
49694 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
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