ENS 49647
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ENS Event | |
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19:32 Dec 17, 2013 | |
Title | Loss of Containment Isolation Capability Due to Surveillance Procedure Error |
Event Description | During performance of 06-IC-1E31-Q-1016-02 RCIC Steam Supply Pressure Low, the RCIC Containment Isolation Valve 1E51F063, RCIC STM SPLY DRWL INBD ISOL, closed. The procedure for this surveillance (which had recently been revised) should have directed the opening of the breakers for isolation valves 1E51F063 and 1E51F076, RCIC STM LINE WARMUP VLV, which are the division two inboard containment isolation valves for the RCIC system. The procedure incorrectly directed the breakers to be opened for the 1E51F064, RCIC STM SPLY DRWL OTBD ISOL, and 1E51F076. The 1E51F076 is a division two valve and the 1E51F064 is a division one valve. Both the 1E51F076 and 1E51F064 were open at the time their breakers were opened, which resulted in the loss of isolation capability for this containment penetration.
The NRC Resident Inspector has been notified. |
Where | |
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Grand Gulf ![]() Mississippi (NRC Region 4) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
Time - Person (Reporting Time:+2.68 h0.112 days <br />0.016 weeks <br />0.00367 months <br />) | |
Opened: | Roger Butler 22:13 Dec 17, 2013 |
NRC Officer: | Daniel Mills |
Last Updated: | Dec 17, 2013 |
49647 - 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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