Event Notification Report for May 12, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/11/2025 - 05/12/2025
Agreement State
Event Number: 57707
Rep Org: Illinois Emergency Mgmt. Agency
Licensee: Northwestern Memorial Hospital
Region: 3
City: Chicago State: IL
County:
License #: IL-01037-02
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Jordan Wingate
Licensee: Northwestern Memorial Hospital
Region: 3
City: Chicago State: IL
County:
License #: IL-01037-02
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Jordan Wingate
Notification Date: 05/13/2025
Notification Time: 12:12 [ET]
Event Date: 05/12/2025
Event Time: 00:00 [CDT]
Last Update Date: 05/13/2025
Notification Time: 12:12 [ET]
Event Date: 05/12/2025
Event Time: 00:00 [CDT]
Last Update Date: 05/13/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Sanchez Santiago, Elba (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Sanchez Santiago, Elba (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE- MEDICAL EVENT
The following information was provided by the Illinois Emergency Management Agency (Agency) via phone and email:
"The Agency was contacted the morning of May 13, 2025, by the radiation safety officer (RSO) for Northwestern Memorial Hospital to advise of a medical event involving the administration of Y-90 TheraSpheres that occurred the previous day. Reportedly, the patient received approximately 37.5 percent of the intended dose to their liver. The RSO was unsure at the time of notification if the patient and prescribing physician had been notified. At the time of notification, it was believed that there is no adverse effect to the patient.
"The licensee met the reporting requirement under 32 Illinois Administrative Code 335.1080. Agency inspectors are coordinating a site visit and additional information will be provided as it becomes available."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
The following information was provided by the Illinois Emergency Management Agency (Agency) via phone and email:
"The Agency was contacted the morning of May 13, 2025, by the radiation safety officer (RSO) for Northwestern Memorial Hospital to advise of a medical event involving the administration of Y-90 TheraSpheres that occurred the previous day. Reportedly, the patient received approximately 37.5 percent of the intended dose to their liver. The RSO was unsure at the time of notification if the patient and prescribing physician had been notified. At the time of notification, it was believed that there is no adverse effect to the patient.
"The licensee met the reporting requirement under 32 Illinois Administrative Code 335.1080. Agency inspectors are coordinating a site visit and additional information will be provided as it becomes available."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
Power Reactor
Event Number: 57705
Facility: Browns Ferry
Region: 2 State: AL
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: Mark R. Moebes
HQ OPS Officer: Josue Ramirez
Region: 2 State: AL
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: Mark R. Moebes
HQ OPS Officer: Josue Ramirez
Notification Date: 05/12/2025
Notification Time: 18:31 [ET]
Event Date: 05/12/2025
Event Time: 13:53 [CDT]
Last Update Date: 05/12/2025
Notification Time: 18:31 [ET]
Event Date: 05/12/2025
Event Time: 13:53 [CDT]
Last Update Date: 05/12/2025
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):
Desai, Binoy (R2DO)
Desai, Binoy (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 Shutdown |
AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via phone and email:
"At 1353 CDT on May 12, 2025, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip caused by a loss of the electrohydraulic control (EHC) system. The trip was not complex, with all systems responding normally post-trip with the exception of the turbine bypass valves due to the loss of EHC.
"Operations responded and stabilized the plant. At 1407 with Unit 2 in Mode 3, there was a second automatic reactor trip due to a low reactor water level transient caused by manually opening and closing a main steam relief valve. Reactor water level is being maintained via feed water pump. Decay heat is being removed by discharging steam [via main steam line drains] to the main condenser. Units 1 and 3 are not affected.
"Due to the reactor protection system (RPS) 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, due to the actuation of RPS and groups 2, 3, 6, and 8 of the primary containment isolation system, this event is being reported as an eight-hour, non-emergency notification per 50.72(b)(3)(iv)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector was notified."
The following information was provided by the licensee via phone and email:
"At 1353 CDT on May 12, 2025, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip caused by a loss of the electrohydraulic control (EHC) system. The trip was not complex, with all systems responding normally post-trip with the exception of the turbine bypass valves due to the loss of EHC.
"Operations responded and stabilized the plant. At 1407 with Unit 2 in Mode 3, there was a second automatic reactor trip due to a low reactor water level transient caused by manually opening and closing a main steam relief valve. Reactor water level is being maintained via feed water pump. Decay heat is being removed by discharging steam [via main steam line drains] to the main condenser. Units 1 and 3 are not affected.
"Due to the reactor protection system (RPS) 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, due to the actuation of RPS and groups 2, 3, 6, and 8 of the primary containment isolation system, this event is being reported as an eight-hour, non-emergency notification per 50.72(b)(3)(iv)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector was notified."