ENS 49382
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ENS Event | |
|---|---|
20:30 Sep 24, 2013 | |
| Title | High Pressure Coolant Injection System Declared Inoperable Due to an Unqualified Electrical Splice |
| Event Description | On 9/24/13 at 1530 CDT, the Browns Ferry Nuclear Plant Unit 2 High Pressure Coolant Injection (HPCI) System was declared inoperable due to inoperability of the minimum flow valve (2-MVOP-073-0030). Engineering identified during review of EQ [Environment Qualification] WO [Work Order] # 113598388 that the motor leads for 2-MVOP-073-0030 were taped instead of terminated with a Raychem splice. The valve actuator is an EQ component and requires termination of the motor leads to the incoming power cable by Raychem splice or a Marathon 300 terminal block. Engineering evaluation was requested and operability of 2-MVOP-073-0030 could not be supported due to the tape being unanalyzed for harsh environmental conditions. The HPCI Minimum Flow valve has a required OPEN safety function to prevent overheating the HPCI pump and a CLOSED safety function to provide containment isolation. Technical Specification 3.5.1, Emergency Core Cooling System-Operating, Condition C was entered for HPCI system inoperability. In addition, the actions of Technical Specification 3.6.1.3, Primary Containment Isolation Valves, were entered due to the inoperability of the primary containment isolation function of the HPCI Minimum Flow valve.
This incident is reportable as an 8-hour ENS notification under 10 CFR 50.72 (b)(3)(v)(D) 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. SR number associated with this report: 784462 The licensee is in a 14-day LCO action statement to return HPCI to operable under TS 3.5.1. The LCO for TS 3.6.1.3 was satisfied. |
| 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:+2.85 h0.119 days <br />0.017 weeks <br />0.0039 months <br />) | |
| Opened: | Mark Moebes 23:21 Sep 24, 2013 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Sep 24, 2013 |
| 49382 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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