ENS 48071
ENS Event | |
|---|---|
14:00 Jul 5, 2012 | |
| Title | Valve Improperly Aligned for Accident Mitigation |
| Event Description | On 7/5/12 at 0307 hrs (EDT), Salem Unit 2 declared 21 Auxiliary Feedwater Pump out of service due to the failure of the 23AF21, Auxiliary Feedwater Flow Control valve to the 23 Steam Generator. 23AF21 had failed to a full open position during performance of the in-service test. Salem Unit 2 entered Technical Specification 3.7.1.2 a, Action Statement a, which requires restoring the pump to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, otherwise be in at least Hot Standby within the next 6 hrs and in Hot Shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
At 1000 hrs on 7/5/12, the air supply to the 23AF21 was found isolated. Troubleshooting and repair of the 23AF21 was completed and, following in service testing, the valve was declared operable at 1349 hrs. Review of the valve's operability concluded that the failure of the 23AF21 valve to close represented a condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident. The Salem UFSAR assumes that during a Category IV Main Steam break accident, a faulted Steam Generator would be identified and Auxiliary Feedwater would be isolated to the affected Steam Generator within 10 minutes. Since the valve was failed open and could not be operated from the control room, the plant would have to manually isolate 23AF21 or trip the 21 Auxiliary Feedwater Pump to ensure feedwater isolation to the affected, faulted Steam Generator. The time to perform manual isolation or tripping of the Auxiliary Feedwater Pump may have required more time than that analyzed by the plant UFSAR. This is being reported under 10CFR50.72(b)(3)(v), the nuclear plant being in a condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident. There were no other safety related systems affected by this event and there were no injuries associated with this event. Maintenance was last performed on this system on May 17, 2012. The licensee will notify the NRC Resident Inspector and Lower Alloways Creek Township. |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+3.75 h0.156 days <br />0.0223 weeks <br />0.00514 months <br />) | |
| Opened: | Jason Morgan 17:45 Jul 5, 2012 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Jul 5, 2012 |
| 48071 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |