ENS 51104: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by Mark Hawes)
 
(Created page by program invented by StriderTol)
 
Line 16: Line 16:
| event date = 05/30/2015 04:58 CDT
| event date = 05/30/2015 04:58 CDT
| last update date = 06/03/2015
| last update date = 06/03/2015
| title = Rhr Pump Trip In Cold Shutdown Mode
| title = Rhr Pump Trip in Cold Shutdown Mode
| event text = 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.
| event text = 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.
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.

Latest revision as of 20:47, 1 March 2018

ENS 51104 +/-
Where
Cooper Entergy icon.png
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
Loading map...