ENS 52113
ENS Event | |
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17:45 Jul 20, 2016 | |
Title | |
Event Description | On 07/20/2016 at 1245 CDT, the Browns Ferry Nuclear Plant Unit 1 High Pressure Coolant Injection (HPCI) Steam Line Inboard Isolation Valve was declared inoperable.
HPCI was declared inoperable at 0300 CDT on 7/18/2016 when it was taken out of service for planned maintenance. A 14 day LCO [Limiting Conditions for Operation] was entered and will expire at 0300 CDT on 8/1/2016. HPCI was being returned to service after the planned maintenance period. The inboard isolation valve and the bypass around the outboard isolation valve were open to warm and pressurize the HPCI steam line. HPCI steam line pressure stabilized at approximately 50 psig. The outboard isolation valve was slowly opened to determine if the inboard isolation valve was actually open. There was no change in steam line pressure or indications of flow at the valves. Based on this information, the HPCI Steam Line Inboard Isolation Valve was declared inoperable for its Primary Containment Isolation function. The appropriate Technical Specification Limiting Conditions for Operation (LCOs) were entered and the HPCI steam line was isolated. This constitutes an unplanned HPCI system inoperability and requires an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ENS notification in accordance with 10 CFR 50.72(b)(3)(v)(D), due to the failure of a single train system affecting accident mitigation and a 60 day written report in accordance with 10 CFR 50.73(a)(2)(v)(D). The Senior NRC Resident Inspector has been notified. |
Where | |
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Browns Ferry Alabama (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
LER: | 05000259/LER-2016-002 |
Time - Person (Reporting Time:+2.8 h0.117 days <br />0.0167 weeks <br />0.00384 months <br />) | |
Opened: | David Renn 20:33 Jul 20, 2016 |
NRC Officer: | Mark Abramovitz |
Last Updated: | Jul 20, 2016 |
52113 - 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 %) |