Dear Beaver Valley Trackers,
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/05/2025 - 02/06/2025
EVENT NUMBERS
Power Reactor
Event Number: 57535
Facility: Beaver Valley
Region: 1
Region: 1
State: PA
Unit: [2] [] []
Unit: [2] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Jim Schwer
HQ OPS Officer: Bill NytkoNotification Date: 02/05/2025
Notification Time: 12:55 [ET]
Event Date: 02/05/2025
Event Time: 10:02 [EST]
Last Update Date: 02/05/2025
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
Person (Organization):
Young, Matt (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
Event Text
AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via phone and email:
"At 1002 EST, on February 5, 2025, with Unit 2 in mode 1 at 100 percent power, the reactor automatically tripped due to lowering 'B' steam generator level. All control rods fully inserted into the core and the auxiliary feedwater system automatically started as designed in response to the full power reactor trip. The trip was not complex, with all systems responding normally post-trip. There was no equipment inoperable prior to the event that contributed to the reactor trip or adversely impacted plant response.
"Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the condenser steam dump valves. Unit 1 is not affected and remains at 100 percent power and stable. 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). Additionally, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted 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."
The following information was provided by the licensee via phone and email:
"At 1002 EST, on February 5, 2025, with Unit 2 in mode 1 at 100 percent power, the reactor automatically tripped due to lowering 'B' steam generator level. All control rods fully inserted into the core and the auxiliary feedwater system automatically started as designed in response to the full power reactor trip. The trip was not complex, with all systems responding normally post-trip. There was no equipment inoperable prior to the event that contributed to the reactor trip or adversely impacted plant response.
"Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the condenser steam dump valves. Unit 1 is not affected and remains at 100 percent power and stable. 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). Additionally, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted 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."
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