ENS 50812
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ENS Event | |
|---|---|
14:20 Feb 11, 2015 | |
| Title | High Pressure Coolant Injection System Suction Path Isolation |
| Event Description | While performing 3-SR-3.5.1.2(HPCI) High Pressure Coolant Injection System Monthly Valve Position Verification, Operators closed the supply breaker for 3-FCV-2-166, CST #3 EMERGENCY HEADER ISOLATION VALVE, in order to verify the valve is in its required OPEN position. When the breaker was closed, the position indication 3-ZI-2-166 indicated OPEN and it was observed that the valve was traveling closed. The operator at the breaker reported that the breaker contactor energized when the breaker was closed. Control Room Operators re-opened 3-FCV-2-166 using the hand switch in the control room and when the valve indicated full open, directed the operator in the field to open the breaker for 3-FCV-2-166. Valve 3-FCV-2-166 isolates both the HPCI and [Reactor Core Isolation Cooling] RCIC suction path from the Condensate storage tank, both HPCI and RCIC were declared inoperable.
The duration of the loss of suction path the HPCI and RCIC was 4 minutes. Applicable Technical Specification required actions were entered for the concurrent HPCI and RCIC inoperability and exited when the suction path was restored. This incident is reportable as an 8-hour ENS notification under 10 CFR 50.72 (b)(3)(v) as 'any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.' It also requires a 60 day written report in accordance with 10 CFR 50.73(a)(2)(vii) The NRC Resident Inspector has been notified |
| Where | |
|---|---|
| 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 | |
| Time - Person (Reporting Time:+1.93 h0.0804 days <br />0.0115 weeks <br />0.00264 months <br />) | |
| Opened: | Gregory L. Smith 16:16 Feb 11, 2015 |
| NRC Officer: | Jeff Herrera |
| Last Updated: | Feb 11, 2015 |
| 50812 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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