ENS 51104
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ENS Event | |
|---|---|
09:58 May 30, 2015 | |
| Title | Rhr Pump Trip in Cold Shutdown Mode |
| Event Description | At 0458 CDT on 05/30/2015, with Cooper Nuclear Station Unit 1 in Mode 4 [cold shutdown], an inadvertent trip of Residual Heat Removal (RHR) Pump B was experienced which resulted in a loss of shutdown cooling. The cause of the trip is currently not known and is under investigation. Shutdown cooling was restored with B RHR Pump at 0520 on 05/30/2015, and there have been no other issues with the system. During the loss of shutdown cooling, forced circulation of the core was not lost due to the Reactor Recirculation System remaining in service. Based on indication from the in-service Reactor Recirculation System A loop, reactor coolant temperature experienced a 7 (seven) degree Fahrenheit increase during the event. Reactor coolant temperature did not exceed 212 degrees Fahrenheit during the event.
This condition is reportable under 10CFR50.72(b)(3)(v) - 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: B) remove residual heat. The NRC Senior Resident inspector has been notified of this event.
After further evaluation of the reported transient, it was determined that the Reactor Recirculation System A Loop increased from 186 degrees F to 204 degrees F for a heatup of 18 degrees during the loss of Shutdown Cooling. The Vessel Drain temperature increased from 190 degrees F to 210 degrees F for a heatup of 20 degrees during the same time frame. The licensee will notify the NRC Resident Inspector. Notified R4DO (Whitten) |
| Where | |
|---|---|
Cooper  Nebraska (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat | |
| Time - Person (Reporting Time:+2 h0.0833 days <br />0.0119 weeks <br />0.00274 months <br />) | |
| Opened: | Steve Wheeler 11:58 May 30, 2015 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Jun 3, 2015 |
| 51104 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
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