Event Notification Report for September 21, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/20/2019 - 09/21/2019
EVENT NUMBERS
54287
54287
Power Reactor
Event Number: 54287
Facility: FARLEY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BLAKE MITCHELL
HQ OPS Officer: JEFF HERRERA
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BLAKE MITCHELL
HQ OPS Officer: JEFF HERRERA
Notification Date: 09/21/2019
Notification Time: 10:28 [ET]
Event Date: 09/21/2019
Event Time: 08:00 [CDT]
Last Update Date: 09/21/2019
Notification Time: 10:28 [ET]
Event Date: 09/21/2019
Event Time: 08:00 [CDT]
Last Update Date: 09/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BRIAN BONSER (R2DO)
BRIAN BONSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL TRIP DUE TO REACTOR COOLANT PUMP VIBRATION ALARM
"At 0800 [CDT], with Unit 2 in Mode 1 at 100 percent [power], the reactor was manually tripped due to elevated vibration indication on the 2C reactor coolant pump exceeding annunciator response procedure trip criteria. The trip was not complex, with all systems responding normally post trip. Auxiliary Feedwater (AFW) auto actuated as expected following the manual reactor trip.
"Operations responded and stabilized the plant. Decay heat is being removed via the use of AFW and subsequent steaming of the steam generators to the main condenser.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b(2)(iv)(B). In addition, this event report is being reported as an eight-hour non-emergency notification per 10 CFR50.72(B)(3)(iv)(A) for a specified system actuation.
"There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector has been notified."
Farley reported that there was no increase in containment unidentified leakage or fluctuations with RCP seal flow during this event.
"At 0800 [CDT], with Unit 2 in Mode 1 at 100 percent [power], the reactor was manually tripped due to elevated vibration indication on the 2C reactor coolant pump exceeding annunciator response procedure trip criteria. The trip was not complex, with all systems responding normally post trip. Auxiliary Feedwater (AFW) auto actuated as expected following the manual reactor trip.
"Operations responded and stabilized the plant. Decay heat is being removed via the use of AFW and subsequent steaming of the steam generators to the main condenser.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b(2)(iv)(B). In addition, this event report is being reported as an eight-hour non-emergency notification per 10 CFR50.72(B)(3)(iv)(A) for a specified system actuation.
"There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector has been notified."
Farley reported that there was no increase in containment unidentified leakage or fluctuations with RCP seal flow during this event.