Event Notification Report for May 05, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/04/2024 - 05/05/2024
EVENT NUMBERS
57107
57107
Power Reactor
Event Number: 57107
Facility: Braidwood
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Azeam Anjum
HQ OPS Officer: Tenisha Meadows
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Azeam Anjum
HQ OPS Officer: Tenisha Meadows
Notification Date: 05/05/2024
Notification Time: 08:11 [ET]
Event Date: 05/05/2024
Event Time: 03:38 [CDT]
Last Update Date: 07/05/2024
Notification Time: 08:11 [ET]
Event Date: 05/05/2024
Event Time: 03:38 [CDT]
Last Update Date: 07/05/2024
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):
Betancourt-Roldan, Diana (R3DO)
Betancourt-Roldan, Diana (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 6 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 7/8/2024
EN Revision Text: AUTOMATIC REACTOR TRIP DUE TO LOWERING STEAM GENERATOR WATER LEVEL
The following information was provided by the licensee via email and phone:
"At 0338 CDT, with the unit 1 in mode 1 at 6 percent power, the reactor automatically tripped due to lowering steam generator water level. The trip was uncomplicated with all systems responding normally post-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, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for an actuation of the auxiliary feedwater system.
"Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to the reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
* * * UPDATE ON 07/05/2024 AT 0450 EDT FROM MATTHEW WHITE TO TENISHA MEADOWS * * *
The following information was provided by the licensee via email and phone:
"At 0338 CDT, with the unit 1 in mode 2 at 3 percent power, the reactor automatically tripped due to lowering steam generator water level. The trip was uncomplicated with all systems responding normally post-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 10CFR50.72(b)(3)(iv)(A) for an actuation of the auxiliary feedwater system, eight-hour notification.
"Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is being removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
Notified R3DO (Hartman)
EN Revision Text: AUTOMATIC REACTOR TRIP DUE TO LOWERING STEAM GENERATOR WATER LEVEL
The following information was provided by the licensee via email and phone:
"At 0338 CDT, with the unit 1 in mode 1 at 6 percent power, the reactor automatically tripped due to lowering steam generator water level. The trip was uncomplicated with all systems responding normally post-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, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for an actuation of the auxiliary feedwater system.
"Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to the reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
* * * UPDATE ON 07/05/2024 AT 0450 EDT FROM MATTHEW WHITE TO TENISHA MEADOWS * * *
The following information was provided by the licensee via email and phone:
"At 0338 CDT, with the unit 1 in mode 2 at 3 percent power, the reactor automatically tripped due to lowering steam generator water level. The trip was uncomplicated with all systems responding normally post-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 10CFR50.72(b)(3)(iv)(A) for an actuation of the auxiliary feedwater system, eight-hour notification.
"Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is being removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
Notified R3DO (Hartman)