Event Notification Report for November 02, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/01/2025 - 11/02/2025
EVENT NUMBERS
58018
58018
Power Reactor
Event Number: 58018
Facility: LaSalle
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: Eric Pratt
HQ OPS Officer: Robert A. Thompson
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: Eric Pratt
HQ OPS Officer: Robert A. Thompson
Notification Date: 11/02/2025
Notification Time: 18:37 [ET]
Event Date: 11/02/2025
Event Time: 13:46 [CST]
Last Update Date: 11/02/2025
Notification Time: 18:37 [ET]
Event Date: 11/02/2025
Event Time: 13:46 [CST]
Last Update Date: 11/02/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Ziolkowski, Michael (R3DO)
Ziolkowski, Michael (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM
The following information was provided by the licensee via phone and email:
"At 1346 CST with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped on turbine control valve fast closure due to a generator lockout. The trip was not complex 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).
"Operations responded using emergency operating procedures and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. 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."
The following information was provided by the licensee via phone and email:
"At 1346 CST with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped on turbine control valve fast closure due to a generator lockout. The trip was not complex 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).
"Operations responded using emergency operating procedures and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. 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."