ENS 51601
ENS Event | |
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08:07 Dec 13, 2015 | |
Title | Essential Services Chilled Water System Inoperable |
Event Description | This is a non-emergency eight hour notification for a condition that could have prevented fulfillment of a safety function in a system needed to remove decay heat and to mitigate the consequences of an accident.
At approximately 0307 EST on December 13, 2015, the 'A' and 'B' trains of the essential services chilled water (ESCW) system were inoperable for a time period of 23 minutes. The 'B' train of the ESCW system was being tested at the time that the 'A' train of the ESCW system became inoperable. The 'B' train of the ESCW system was returned to operable status at approximately 0330 EST and remains operable. The ESCW system provides cooling support functions to remove decay heat and mitigate the consequences of an accident. There were no safety system actuations during this time period and the plant is stable. This condition does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified. The 'A' ESCW pump tripped on low lube oil pressure.
Upon further review of the condition, it was determined that the 'A' train of the ESCW system was capable of performing its safety function throughout the time period previously reported, and the 'A' train of the ESCW system was operable. Therefore, there was no loss of safety function. Event notification 51601 is retracted. The NRC Resident Inspector has been informed of this notification retraction. Notified the R2DO (Guthrie). |
Where | |
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Harris North Carolina (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
Time - Person (Reporting Time:+2.57 h0.107 days <br />0.0153 weeks <br />0.00352 months <br />) | |
Opened: | Kate Colias 10:41 Dec 13, 2015 |
NRC Officer: | Daniel Mills |
Last Updated: | Dec 14, 2015 |
51601 - NRC Website
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Unit 1 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |