Event Notification Report for October 22, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/21/2025 - 10/22/2025
Power Reactor
Event Number: 57994
Facility: Wolf Creek
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Michael J. Payne
HQ OPS Officer: Josue Ramirez
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Michael J. Payne
HQ OPS Officer: Josue Ramirez
Notification Date: 10/21/2025
Notification Time: 14:37 [ET]
Event Date: 10/21/2025
Event Time: 06:10 [CDT]
Last Update Date: 10/21/2025
Notification Time: 14:37 [ET]
Event Date: 10/21/2025
Event Time: 06:10 [CDT]
Last Update Date: 10/21/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
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 | N | 0 | 0 |
BOTH TRAINS OF CONTROL ROOM EMERGENCY VENTILATION SYSTEM INOPERABLE
The following is a summary of information provided by the licensee via phone and email:
On October 21, 2025, at 0610 CDT, while reloading fuel to the reactor vessel, an electrical perturbation initiated a control room ventilation isolation signal (CRVIS). The control room air conditioning system (CRACS) 'A' train A/C unit did not start upon the CRVIS due to a blown fuse. The 'B' CRACS A/C unit was out of service for planned maintenance at the time. At 1020 CDT, the 'A' train CRACS A/C unit was returned to service. Both trains of the control room emergency ventilation system (CREVS) were inoperable for 10 minutes. Due to both trains of CRACS and CREVS being inoperable, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v).
This condition caused entry into technical specification (TS) limiting condition for operation (LCO) 3.7.10 condition `E' and 3.7.11 condition `D'. Upon discovery of the condition, fuel movement and core alterations were suspended in accordance with the TS LCO required actions.
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector was notified.
The following is a summary of information provided by the licensee via phone and email:
On October 21, 2025, at 0610 CDT, while reloading fuel to the reactor vessel, an electrical perturbation initiated a control room ventilation isolation signal (CRVIS). The control room air conditioning system (CRACS) 'A' train A/C unit did not start upon the CRVIS due to a blown fuse. The 'B' CRACS A/C unit was out of service for planned maintenance at the time. At 1020 CDT, the 'A' train CRACS A/C unit was returned to service. Both trains of the control room emergency ventilation system (CREVS) were inoperable for 10 minutes. Due to both trains of CRACS and CREVS being inoperable, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v).
This condition caused entry into technical specification (TS) limiting condition for operation (LCO) 3.7.10 condition `E' and 3.7.11 condition `D'. Upon discovery of the condition, fuel movement and core alterations were suspended in accordance with the TS LCO required actions.
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector was notified.
Power Reactor
Event Number: 57996
Facility: Palisades
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: Scott Moore
HQ OPS Officer: Josue Ramirez
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: Scott Moore
HQ OPS Officer: Josue Ramirez
Notification Date: 10/21/2025
Notification Time: 16:52 [ET]
Event Date: 10/21/2025
Event Time: 16:32 [EDT]
Last Update Date: 10/21/2025
Notification Time: 16:52 [ET]
Event Date: 10/21/2025
Event Time: 16:32 [EDT]
Last Update Date: 10/21/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(xii) - Offsite Medical
10 CFR Section:
50.72(b)(3)(xii) - Offsite Medical
Person (Organization):
Edwards, Rhex (R3DO)
Grant, Jeffery (IRMOC)
Phil McKenna (NRR EO)
Edwards, Rhex (R3DO)
Grant, Jeffery (IRMOC)
Phil McKenna (NRR EO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | 0 |
TRANSPORT OF CONTAMINATED PERSON OFFSITE
The following information was provided by the licensee via phone and email:
"On 10/21/2025 at 0930 EDT an individual fell into the reactor cavity. The reactor cavity is full of water. They ingested some amount of cavity water. The individual was decontaminated by radiation protection personnel but had 300 counts per minute detected in their hair. At 1632 EDT they were sent off site to seek medical attention.
"This is an eight-hour notification, non-emergency, for the transportation of a contaminated person offsite. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xii).
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via phone and email:
"On 10/21/2025 at 0930 EDT an individual fell into the reactor cavity. The reactor cavity is full of water. They ingested some amount of cavity water. The individual was decontaminated by radiation protection personnel but had 300 counts per minute detected in their hair. At 1632 EDT they were sent off site to seek medical attention.
"This is an eight-hour notification, non-emergency, for the transportation of a contaminated person offsite. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xii).
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 57997
Facility: North Anna
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Nick Wilson
HQ OPS Officer: Josue Ramirez
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Nick Wilson
HQ OPS Officer: Josue Ramirez
Notification Date: 10/21/2025
Notification Time: 23:10 [ET]
Event Date: 10/21/2025
Event Time: 21:08 [EDT]
Last Update Date: 10/21/2025
Notification Time: 23:10 [ET]
Event Date: 10/21/2025
Event Time: 21:08 [EDT]
Last Update Date: 10/21/2025
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Mckown, Louis J (R2DO)
Mckown, Louis J (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 74 | 0 |
AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via email and phone:
"On October 21, 2025, at 2108 EDT, Unit 1 automatically tripped from 74 percent power due to a negative rate trip. The unit has been stabilized in mode 3 at normal operating temperature and pressure. The reactor trip was uncomplicated, and all control rods fully inserted into the core. This reactor protection system actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). The auxiliary feedwater pumps actuated as designed because of the reactor trip and is reportable per 10 CFR 50.72(b)(3)(iv)(A) for a valid engineered safety feature (ESF) actuation. Decay heat is being removed via the steam generator power-operated relief valves and Unit 1 is in a normal shutdown electrical lineup. Unit 2 was not affected by this event."
The NRC Resident Inspector has been notified.
The following information was provided by the licensee via email and phone:
"On October 21, 2025, at 2108 EDT, Unit 1 automatically tripped from 74 percent power due to a negative rate trip. The unit has been stabilized in mode 3 at normal operating temperature and pressure. The reactor trip was uncomplicated, and all control rods fully inserted into the core. This reactor protection system actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). The auxiliary feedwater pumps actuated as designed because of the reactor trip and is reportable per 10 CFR 50.72(b)(3)(iv)(A) for a valid engineered safety feature (ESF) actuation. Decay heat is being removed via the steam generator power-operated relief valves and Unit 1 is in a normal shutdown electrical lineup. Unit 2 was not affected by this event."
The NRC Resident Inspector has been notified.