Event Notification Report for October 26, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/25/2025 - 10/26/2025
Power Reactor
Event Number: 58010
Facility: Surry
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Scott Satterfield
HQ OPS Officer: Ian Howard
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Scott Satterfield
HQ OPS Officer: Ian Howard
Notification Date: 10/28/2025
Notification Time: 10:53 [ET]
Event Date: 10/27/2025
Event Time: 14:51 [EDT]
Last Update Date: 10/28/2025
Notification Time: 10:53 [ET]
Event Date: 10/27/2025
Event Time: 14:51 [EDT]
Last Update Date: 10/28/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
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 | N | N | 0 | Defueled | 0 | Defueled |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION FOR PERSONNEL INJURY
The following information was provided by the licensee via phone and email:
"At 0920 EDT on 10/28/25, the supervisor of nuclear site safety contacted the area director of OSHA [Occupational Safety and Health Administration] to notify them of a work-related injury which resulted in the employee being admitted to a hospital.
"The individual was not contaminated and was transported offsite to Chippenham Hospital in Richmond, VA.
"This was a 24-hour notification in accordance with 29 CFR 1904.8."
The NRC Resident Inspector has been notified.
The following information was provided by the licensee via phone and email:
"At 0920 EDT on 10/28/25, the supervisor of nuclear site safety contacted the area director of OSHA [Occupational Safety and Health Administration] to notify them of a work-related injury which resulted in the employee being admitted to a hospital.
"The individual was not contaminated and was transported offsite to Chippenham Hospital in Richmond, VA.
"This was a 24-hour notification in accordance with 29 CFR 1904.8."
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 58008
Facility: Dresden
Region: 3 State: IL
Unit: [2] [] []
RX Type: [2] GE-3,[3] GE-3
NRC Notified By: Shawn Kenady
HQ OPS Officer: Ian Howard
Region: 3 State: IL
Unit: [2] [] []
RX Type: [2] GE-3,[3] GE-3
NRC Notified By: Shawn Kenady
HQ OPS Officer: Ian Howard
Notification Date: 10/27/2025
Notification Time: 08:50 [ET]
Event Date: 10/27/2025
Event Time: 01:17 [CDT]
Last Update Date: 10/27/2025
Notification Time: 08:50 [ET]
Event Date: 10/27/2025
Event Time: 01:17 [CDT]
Last Update Date: 10/27/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Edwards, Rhex (R3DO)
Ziolkowski, Michael (R3DO)
Edwards, Rhex (R3DO)
Ziolkowski, Michael (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Shutdown | 0 | Cold Shutdown |
VALID REACTOR PROTECTION SYSTEM ACTUATION WHILE SHUTDOWN
The following information was provided by the licensee via phone and email:
"At 0117 CDT on 10/27/2025, with Unit 2 in mode 3 at 0 percent power, an actuation of the RPS system occurred during restoration of the scram instrument volume high level bypass switch to normal. The cause of the RPS system actuation was a valid high level in the scram instrument volume. All control rods had been previously inserted and the RPS system automatically initiated a scram signal as designed when the scram instrument volume high level signal was received.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the RPS 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 0117 CDT on 10/27/2025, with Unit 2 in mode 3 at 0 percent power, an actuation of the RPS system occurred during restoration of the scram instrument volume high level bypass switch to normal. The cause of the RPS system actuation was a valid high level in the scram instrument volume. All control rods had been previously inserted and the RPS system automatically initiated a scram signal as designed when the scram instrument volume high level signal was received.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the RPS system.
"There was no impact on the health and safety of the public or plant personnel."
The NRC Resident Inspector has been notified.
Agreement State
Event Number: 58009
Rep Org: Louisiana Dept of Env. Quality
Licensee: Acuren Inspection, Inc.
Region: 4
City: Kenner State: LA
County:
License #: LA-7072-L02
Agreement: Y
Docket:
NRC Notified By: Jim Pate
HQ OPS Officer: Robert A. Thompson
Licensee: Acuren Inspection, Inc.
Region: 4
City: Kenner State: LA
County:
License #: LA-7072-L02
Agreement: Y
Docket:
NRC Notified By: Jim Pate
HQ OPS Officer: Robert A. Thompson
Notification Date: 10/27/2025
Notification Time: 14:51 [ET]
Event Date: 10/27/2025
Event Time: 00:00 [CDT]
Last Update Date: 10/27/2025
Notification Time: 14:51 [ET]
Event Date: 10/27/2025
Event Time: 00:00 [CDT]
Last Update Date: 10/27/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Vossmar, Patricia (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Vossmar, Patricia (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - WORKER POTENTIALLY EXCEEDED OCCUPATIONAL DOSE LIMIT
The following information was provided by the Louisiana Department of Environmental Quality (the Department) via email:
"On October 27, 2025, Acuren Inspection, Inc. notified the Department that an industrial radiography trainee dosimetry badge had been reported as an overexposure of 8 rem from Landauer. While talking with the radiation safety officer (RSO), the Department was informed that the radiographer trainee had only worked as a trainee in Louisiana for approximately seven weeks before being transferred to Orange, Texas. The RSO indicated that the trainee worked with at least three different crews at different job sites around their Kenner satellite office over the time period of mid-May to early July 2025."
Louisiana report ID number: LA20230011
The following information was provided by the Louisiana Department of Environmental Quality (the Department) via email:
"On October 27, 2025, Acuren Inspection, Inc. notified the Department that an industrial radiography trainee dosimetry badge had been reported as an overexposure of 8 rem from Landauer. While talking with the radiation safety officer (RSO), the Department was informed that the radiographer trainee had only worked as a trainee in Louisiana for approximately seven weeks before being transferred to Orange, Texas. The RSO indicated that the trainee worked with at least three different crews at different job sites around their Kenner satellite office over the time period of mid-May to early July 2025."
Louisiana report ID number: LA20230011
Power Reactor
Event Number: 58007
Facility: Waterford
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Jean-Luc Guilbeaux
HQ OPS Officer: Ian Howard
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Jean-Luc Guilbeaux
HQ OPS Officer: Ian Howard
Notification Date: 10/26/2025
Notification Time: 09:29 [ET]
Event Date: 10/26/2025
Event Time: 00:40 [CDT]
Last Update Date: 10/26/2025
Notification Time: 09:29 [ET]
Event Date: 10/26/2025
Event Time: 00:40 [CDT]
Last Update Date: 10/26/2025
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 |
|---|---|---|---|---|---|---|
| 3 | N | Y | 94 | Power Operation | 94 | Power Operation |
CONTROL ROOM ENVELOPE INOPERABLE
The following information was provided by the licensee via phone and email:
"On October 26, 2025, at 0040 CDT, the Waterford 3 Steam Electric Unit 3 operating crew declared the control room envelope inoperable in accordance with technical specification (TS) 3.7.6.1 due to the discovery of a hairline crack in the station air supply header in the passageway outside the control room.
"Operations entered TS 3.7.6.1 action b. TS 3.7.6.1 action b was complied with by closing manual valves SA-502 and SA-514, thus isolating the section of piping that developed the crack. The station air leak was isolated at time 0120. There was no impact on the health and safety of the plant or plant personnel.
"This event is reportable pursuant to 10 CFR 50.72(b)(3)(v)(D), event or condition that could have prevented fulfillment of a safety function of structures or systems that are needed to `(D) mitigate the consequences of an accident,' due to the control room envelope being inoperable."
The licensee notified the NRC Resident Inspector.
The following information was provided by the licensee via phone and email:
"On October 26, 2025, at 0040 CDT, the Waterford 3 Steam Electric Unit 3 operating crew declared the control room envelope inoperable in accordance with technical specification (TS) 3.7.6.1 due to the discovery of a hairline crack in the station air supply header in the passageway outside the control room.
"Operations entered TS 3.7.6.1 action b. TS 3.7.6.1 action b was complied with by closing manual valves SA-502 and SA-514, thus isolating the section of piping that developed the crack. The station air leak was isolated at time 0120. There was no impact on the health and safety of the plant or plant personnel.
"This event is reportable pursuant to 10 CFR 50.72(b)(3)(v)(D), event or condition that could have prevented fulfillment of a safety function of structures or systems that are needed to `(D) mitigate the consequences of an accident,' due to the control room envelope being inoperable."
The licensee notified the NRC Resident Inspector.