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Event Notification Report for November 21, 2018

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
11/20/2018 - 11/21/2018

EVENT NUMBERS
5375053749

!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 53750
Facility: BROWNS FERRY
Region: 2     State: AL
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: ANGEL YARBROUGH
HQ OPS Officer: DAN LIVERMORE
Notification Date: 11/22/2018
Notification Time: 03:56 [ET]
Event Date: 11/21/2018
Event Time: 21:25 [CST]
Last Update Date: 12/28/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
STEVE ROSE (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 13 Power Operation 13 Power Operation
Event Text
HPCI UNEXPECTEDLY TRANSFERRED TO ALTERNATE SUCTION SOURCE DURING TESTING

"At 2125 [CST] on 11/21/2018, it was discovered that U1 High Pressure Coolant Injection System (HPCI) was inoperable; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v), as an 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 mitigate the consequences of an accident.

"During performance of a routine surveillance, HPCI automatically transferred from its normal suction source to the alternate suction source. The control room operator then manually tripped the HPCI turbine. HPCI was already inoperable in accordance with Technical Specifications (TS) Limiting Condition for Operability (LCO) 3.5.1, ECCS Operating, Condition C during performance of the surveillance. However, this condition was not expected nor induced by the testing.

"There was no impact to the safety of the public or plant personnel. The NRC Resident Inspector has been notified.

"CR 1469109 documents this condition in the Corrective Action Program."

* * * RETRACTION ON 12/28/18 AT 1300 EST FROM MARK MOEBES TO JEFFREY WHITED * * *

"ENS Event Number 53750, made on November 22, 2018, is being retracted.

"NRC notification 53750 was made to ensure that the Eight-Hour Non-Emergency reporting requirements of 10 CFR 50.72(b)(3)(v)(D) were met when the licensee discovered an 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 mitigate the consequences of an accident.

"During performance of a routine surveillance, the High Pressure Coolant Injection (HPCI) System automatically transferred from its normal suction source to the alternate suction source. As a result, Unit 1 HPCI was declared inoperable.

"On December 20, 2018, a Past Operability Evaluation was completed which determined that the HPCI System remained operable. The evaluation determined that the HPCI System could have performed its specified safety function of vessel injection throughout the time that the suction path was aligned to the torus. Therefore, this event is not reportable under 10 CFR 50.72(b)(3)(v)(D).

"TVA's evaluation of this event is documented in the Corrective Action Program in Condition Report 1469109.

"The licensee has notified the NRC Resident Inspector."

Notified R2DO (Desai).


Power Reactor
Event Number: 53749
Facility: PALISADES
Region: 3     State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: JAMES BYRD
HQ OPS Officer: OSSY FONT
Notification Date: 11/21/2018
Notification Time: 17:27 [ET]
Event Date: 11/21/2018
Event Time: 00:00 [EST]
Last Update Date: 11/21/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JAMNES CAMERON (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
Event Text
DEGRADED CONDITION IDENTIFIED DURING SURFACE INSPECTION OF REACTOR HEAD NOZZLE PENETRATION

"On November 21, 2018, during an extent of condition review, after completion of ultrasonic testing, further interrogation of reactor vessel closure head (RVCH) penetration 36 was performed using eddy current testing. The testing detected three repairable indications. No indication of boric acid leakage was identified at this location during the bare metal visual inspection. Extent of condition review is complete on all RVCH penetrations.

"The plant was in cold shutdown at 0 percent power and in Mode 6 for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage.

"This condition has no impact to the health and safety of the public.

"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) for degradation of a principal safety barrier.

"The licensee notified the NRC Senior Resident Inspector."