Skip to main content

Event Notification Report for February 24, 2016

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
02/23/2016 - 02/24/2016

EVENT NUMBERS
51754

Power Reactor
Event Number: 51754
Facility: RIVER BEND
Region: 4     State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JACK McCOY
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/24/2016
Notification Time: 18:16 [ET]
Event Date: 02/24/2016
Event Time: 11:00 [CST]
Last Update Date: 02/24/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
JACK WHITTEN (R4DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown
Event Text
ELECTRICAL BREAKER ISSUE IDENTIFIED DURING AN ENGINEERING REVIEW

"At 1100 CST on February 24, 2016, with the plant in cold shutdown (Mode 4), the shift manager was notified of a condition that could potentially prevent the automatic closure of the circuit breakers powering the emergency ventilation fans in the both the Division 1 and 2 emergency diesel generator rooms. These fans are not in Technical Specifications, however, they provide a support function to the emergency diesel generators, requiring that both diesel generators to be declared inoperable. This inoperability constitutes a condition that could potentially prevent fulfillment of the safety function of onsite AC power sources, and is being reported pursuant to 10 CFR 50.72(b)(3)(v).

"Four additional breakers are affected by the same condition. These breakers supply power to Division 1 and 2 containment unit coolers and the Division 1 and 2 auxiliary building 141 ft. elevation general area unit coolers. The auxiliary building unit coolers are not in Technical Specifications, however, they provide a support function to the electrical distribution system. The Technical Specification required action is to declare both trains of the residual heat removal system (shutdown cooling mode) inoperable. This inoperability constitutes a condition that could potentially prevent the fulfillment of the decay heat removal safety function, and is being reported pursuant to 10 CFR 50.72(b)(3)(v).

"Division 2 residual heat removal is operating in shutdown cooling, satisfactorily maintaining reactor coolant temperature. The affected breakers can be manually operated to start/stop their associated equipment, if necessary for operation."

This condition was identified during an Engineering review. The licensee has compensatory measures in place. Long term corrective actions are under review.

The licensee informed the NRC Resident Inspector.