Event Notification Report for August 23, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/22/2024 - 08/23/2024
Power Reactor
Event Number: 57284
Facility: Wolf Creek
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Alex Meyer
HQ OPS Officer: Sam Colvard
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Alex Meyer
HQ OPS Officer: Sam Colvard
Notification Date: 08/23/2024
Notification Time: 09:02 [ET]
Event Date: 08/23/2024
Event Time: 08:00 [CDT]
Last Update Date: 08/23/2024
Notification Time: 09:02 [ET]
Event Date: 08/23/2024
Event Time: 08:00 [CDT]
Last Update Date: 08/23/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By TS
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By TS
Person (Organization):
Vossmar, Patricia (R4DO)
Vossmar, Patricia (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 98 | Power Operation | 98 | Power Operation |
SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS
The following information was provided by the licensee via phone and email:
"At 0500 CDT on 8/23/24, Wolf Creek entered technical specification limiting condition for operation (LCO) 3.7.5 required action D.1 which requires shutdown to mode 3 within 6 hours. The turbine driven auxiliary feedwater pump discharge valve to the 'B' steam generator was not successfully restored to operable prior to expiration of the 72 hour completion time. At 0800 CDT, the shutdown to mode 3 was initiated, which is being reported in accordance with 10CFR50.72(b)(2)(i)."
The NRC Resident Inspector has been notified.
The following information was provided by the licensee via phone and email:
"At 0500 CDT on 8/23/24, Wolf Creek entered technical specification limiting condition for operation (LCO) 3.7.5 required action D.1 which requires shutdown to mode 3 within 6 hours. The turbine driven auxiliary feedwater pump discharge valve to the 'B' steam generator was not successfully restored to operable prior to expiration of the 72 hour completion time. At 0800 CDT, the shutdown to mode 3 was initiated, which is being reported in accordance with 10CFR50.72(b)(2)(i)."
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 57285
Facility: Sequoyah
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Timothy Wood
HQ OPS Officer: Josue Ramirez
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Timothy Wood
HQ OPS Officer: Josue Ramirez
Notification Date: 08/23/2024
Notification Time: 13:44 [ET]
Event Date: 08/23/2024
Event Time: 12:19 [EDT]
Last Update Date: 08/23/2024
Notification Time: 13:44 [ET]
Event Date: 08/23/2024
Event Time: 12:19 [EDT]
Last Update Date: 08/23/2024
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):
Masters, Anthony (R2DO)
Masters, Anthony (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via email:
"At 1219 EDT, 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 systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed by the auxiliary feedwater (AFW) and steam dump systems. Unit 2 is currently in a refueling outage (U2R26) and was not affected.
"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, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system. The AFW system started automatically and is operating as designed.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"At 1219 EDT, 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 systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed by the auxiliary feedwater (AFW) and steam dump systems. Unit 2 is currently in a refueling outage (U2R26) and was not affected.
"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, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system. The AFW system started automatically and is operating as designed.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."