Event Notification Report for July 13, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/12/2025 - 07/13/2025
Agreement State
Event Number: 57811
Rep Org: RI Dept of Radiological Health
Licensee: Electric Boat
Region: 1
City: North Kingstown State: RI
County:
License #: RI 3D-005-01
Agreement: Y
Docket:
NRC Notified By: Catherine Perham
HQ OPS Officer: Kerby Scales
Licensee: Electric Boat
Region: 1
City: North Kingstown State: RI
County:
License #: RI 3D-005-01
Agreement: Y
Docket:
NRC Notified By: Catherine Perham
HQ OPS Officer: Kerby Scales
Notification Date: 07/14/2025
Notification Time: 14:22 [ET]
Event Date: 07/14/2025
Event Time: 00:06 [EDT]
Last Update Date: 07/15/2025
Notification Time: 14:22 [ET]
Event Date: 07/14/2025
Event Time: 00:06 [EDT]
Last Update Date: 07/15/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Eve, Elise (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Eve, Elise (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - STUCK SOURCE
The following information was provided by the Rhode Island Department of Radiological Health via email:
"At 0006 EDT, on July 14th, 2025, an Electric Boat employee was attempting to retract an Ir-192 source of 19.5 Ci. The employee was only able to retract the source halfway back to the exposure device when the source would not move any further. The employee then cranked the source back out into the collimator to provide shielding. The employee then contacted their supervisor to report the emergency notification and follow the emergency procedures as required. The boundaries were verified to be less than 0.5 mR/hr at all boundaries. There were no un-monitored personnel in the area. Additional personnel were provided to maintain control of the area. The radiation safety officer (RSO) was contacted at 0013 and notified of the hung source. The RSO arrived on site at approximately 0043 to assess the incident and determine a corrective action on how to move forward. The RSO and the radiographer returned the radioactive source to the exposure device at approximately 0300. The highest dose received by any individual of the recovery team was 1 mrem. The source in the exposure device was secured and returned to storage."
Rhode Island Event Report ID Number: Rhode Island-25-01
The following information was provided by the Rhode Island Department of Radiological Health via email:
"At 0006 EDT, on July 14th, 2025, an Electric Boat employee was attempting to retract an Ir-192 source of 19.5 Ci. The employee was only able to retract the source halfway back to the exposure device when the source would not move any further. The employee then cranked the source back out into the collimator to provide shielding. The employee then contacted their supervisor to report the emergency notification and follow the emergency procedures as required. The boundaries were verified to be less than 0.5 mR/hr at all boundaries. There were no un-monitored personnel in the area. Additional personnel were provided to maintain control of the area. The radiation safety officer (RSO) was contacted at 0013 and notified of the hung source. The RSO arrived on site at approximately 0043 to assess the incident and determine a corrective action on how to move forward. The RSO and the radiographer returned the radioactive source to the exposure device at approximately 0300. The highest dose received by any individual of the recovery team was 1 mrem. The source in the exposure device was secured and returned to storage."
Rhode Island Event Report ID Number: Rhode Island-25-01
Power Reactor
Event Number: 57810
Facility: Watts Bar
Region: 2 State: TN
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Ryan Nessell
HQ OPS Officer: Josue Ramirez
Region: 2 State: TN
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Ryan Nessell
HQ OPS Officer: Josue Ramirez
Notification Date: 07/13/2025
Notification Time: 17:10 [ET]
Event Date: 07/13/2025
Event Time: 14:18 [EDT]
Last Update Date: 07/13/2025
Notification Time: 17:10 [ET]
Event Date: 07/13/2025
Event Time: 14:18 [EDT]
Last Update Date: 07/13/2025
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):
Davis, Bradley (R2DO)
Davis, Bradley (R2DO)
| 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 |
AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via phone and email:
"At 1418 EDT on 7/13/2025, with Unit 2 in mode 1 at 100 percent power, the reactor automatically tripped due to a main turbine trip. The trip was not complicated with all systems responding normally post trip.
"Operators responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the steam dump system and the auxiliary feedwater (AFW) system. Unit 1 is not affected.
"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). The expected actuation of the AFW system (an engineered safety feature) is being reported as an eight-hour report under 10 CFR 50.72 (b)(3)(iv)(A).
"There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The cause of the main turbine trip was due to the loss of both main feed pumps due to a loss of secondary power. The cause of the loss of secondary power is still being investigated.
The following information was provided by the licensee via phone and email:
"At 1418 EDT on 7/13/2025, with Unit 2 in mode 1 at 100 percent power, the reactor automatically tripped due to a main turbine trip. The trip was not complicated with all systems responding normally post trip.
"Operators responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the steam dump system and the auxiliary feedwater (AFW) system. Unit 1 is not affected.
"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). The expected actuation of the AFW system (an engineered safety feature) is being reported as an eight-hour report under 10 CFR 50.72 (b)(3)(iv)(A).
"There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The cause of the main turbine trip was due to the loss of both main feed pumps due to a loss of secondary power. The cause of the loss of secondary power is still being investigated.