Lets see if this works
Here is what was reported to the NRC
Power Reactor Event Number: 46847
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RICKY GIVENS
HQ OPS Officer: JOHN KNOKE Notification Date: 05/13/2011
Notification Time: 01:53 [ET]
Event Date: 05/12/2011
Event Time: 18:25 [CDT]
Last Update Date: 05/13/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
EUGENE GUTHRIE (R2DO)
Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Cold Shutdown 0 Cold Shutdown
Event Text
LOSS OF SHUTDOWN COOLING
"At 1825 CDT on 05/12/2011, with Browns Ferry Nuclear Plant Unit 3 in Mode 4, Browns Ferry Nuclear Plant PCIS [Primary Containment Isolation System] relay maintenance activities for a Group 1 PCIS relay inadvertently interrupted the neutral for a Group 2 PCIS relay and a Group 2 PCIS isolation occurred resulting in a loss of Shutdown Cooling. Relays were reset and Shutdown Cooling was restored at 1905 CDT. Moderator temperature prior to the event was 112.5 degrees F and the highest moderator temperature recorded during the loss of Shutdown Cooling was 122 degrees F.
"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 is also reportable as a 60 day written report IAW 10CFR 50.73(a)(2)(v).
"The NRC Resident Inspector has been notified of this event.
"This event was entered into the licensee's Corrective Action Program as SR# 368205".
When I read this my first thought was oh-no not after a degraded cornerstone finding classified as RED. I think there will be lots of outage work available at the ferry soon.
Honestly I hope it works out for the folks there but does not sound promising to me
sf
