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Event Notification Report for February 01, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/31/2023 - 02/01/2023
EVENT NUMBERS
56329
Power Reactor
Event Number: 56329
Facility: Farley
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Ryan Harlos
HQ OPS Officer: Brian P. Smith
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Ryan Harlos
HQ OPS Officer: Brian P. Smith
Notification Date: 02/01/2023
Notification Time: 13:40 [ET]
Event Date: 02/01/2023
Event Time: 09:56 [CST]
Last Update Date: 02/02/2023
Notification Time: 13:40 [ET]
Event Date: 02/01/2023
Event Time: 09:56 [CST]
Last Update Date: 02/02/2023
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):
Miller, Mark (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 2/3/2023
EN Revision Text: AUTOMATIC REACTOR TRIP DUE AND AUTOMATIC ACTUATION OF AUXILIARY FEEDWATER SYSTEM
The following information was provided by the licensee via email:
"At 0956 CST with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex with all safety related systems responding normally post-trip. During the trip, the non safety related '1A' 4160V bus lost power resulting in the loss of one Reactor Coolant Pump (RCP-1A). Operations responded and stabilized the plant. The '1A' 4160V bus was re-energized at 1031 CST. Decay heat is being removed by steam dumps to the main condenser. Farley Unit 2 is not affected.
"An automatic actuation of [Auxiliary Feedwater] AFW also occurred, which is an expected response from the reactor trip.
"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) and an eight-hour report per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
EN Revision Text: AUTOMATIC REACTOR TRIP DUE AND AUTOMATIC ACTUATION OF AUXILIARY FEEDWATER SYSTEM
The following information was provided by the licensee via email:
"At 0956 CST with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex with all safety related systems responding normally post-trip. During the trip, the non safety related '1A' 4160V bus lost power resulting in the loss of one Reactor Coolant Pump (RCP-1A). Operations responded and stabilized the plant. The '1A' 4160V bus was re-energized at 1031 CST. Decay heat is being removed by steam dumps to the main condenser. Farley Unit 2 is not affected.
"An automatic actuation of [Auxiliary Feedwater] AFW also occurred, which is an expected response from the reactor trip.
"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) and an eight-hour report per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."