Event Notification Report for November 02, 2026
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/01/2026 - 11/02/2026
Agreement State
Event Number: 58505
Rep Org: Alabama Dept of Public Health
Licensee: Auburn University
Region: 1
City: Auburn State: AL
County:
License #: 248
Agreement: Y
Docket:
NRC Notified By: Sean Williams
HQ OPS Officer: Philip Alier
Licensee: Auburn University
Region: 1
City: Auburn State: AL
County:
License #: 248
Agreement: Y
Docket:
NRC Notified By: Sean Williams
HQ OPS Officer: Philip Alier
Notification Date: 10/23/2026
Notification Time: 13:36 [ET]
Event Date: 10/21/2026
Event Time: 00:00 [CDT]
Last Update Date: 10/23/2026
Notification Time: 13:36 [ET]
Event Date: 10/21/2026
Event Time: 00:00 [CDT]
Last Update Date: 10/23/2026
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
NMSS_EVENTS_NOTIFICATION (EMAIL)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - FAILED LEAK TEST
The following information was provided by the Radioactive Material Compliance Branch of the Alabama Department of Public Health via email:
"On October 21, 2026, the licensee reported that one of their electron capture detector (ECD) sources failed a leak test in preparation for disposal. The ECD source is an Eckert and Ziegler Ni-63 source with a 10 mCi activity and an assay date of January 1, 2026. The source model number is GL1318, and the serial number is SS2197. The device it was removed from is a Shimadzu GC-2104 with a serial number of C11485014099SA. After it was determined that the sealed source was leaking, the Shimadzu GC-2014 and the area were wiped, and no removable contamination was detected. The Ni-63 sealed source was placed in Auburn University's radiological waste area and is awaiting pickup by a commercial waste vendor."
Alabama incident number: 26-018
The following information was provided by the Radioactive Material Compliance Branch of the Alabama Department of Public Health via email:
"On October 21, 2026, the licensee reported that one of their electron capture detector (ECD) sources failed a leak test in preparation for disposal. The ECD source is an Eckert and Ziegler Ni-63 source with a 10 mCi activity and an assay date of January 1, 2026. The source model number is GL1318, and the serial number is SS2197. The device it was removed from is a Shimadzu GC-2104 with a serial number of C11485014099SA. After it was determined that the sealed source was leaking, the Shimadzu GC-2014 and the area were wiped, and no removable contamination was detected. The Ni-63 sealed source was placed in Auburn University's radiological waste area and is awaiting pickup by a commercial waste vendor."
Alabama incident number: 26-018
Power Reactor
Event Number: 58510
Facility: Palisades
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: Kyle Steffic
HQ OPS Officer: Christopher Prescott
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: Kyle Steffic
HQ OPS Officer: Christopher Prescott
Notification Date: 10/30/2026
Notification Time: 11:38 [ET]
Event Date: 09/06/2026
Event Time: 02:54 [EDT]
Last Update Date: 10/30/2026
Notification Time: 11:38 [ET]
Event Date: 09/06/2026
Event Time: 02:54 [EDT]
Last Update Date: 10/30/2026
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
Person (Organization):
Nguyen, April (R3 BC)
R3 Reactor Events (Email)
Nguyen, April (R3 BC)
R3 Reactor Events (Email)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
INVALID SPECIFIED SYSTEM ACTUATION
The following information was provided by the licensee via phone and email:
"At 0254 EDT, on September 6, 2026, operations received a containment isolation signal from the 'right' train fuel handling area radiation monitor (RIA-2317). At 0256 EDT, operations entered AOP-31, Spurious Containment Isolation, and performed the required abnormal operating procedure actions. All 'right' train valves actuated as designed.
"Radiation protection performed surveys of the general area of the 649' [elevation] of containment around the refuel monitors, and dose rates were normal. It was found that RIA-2317 had spiked high and isolated containment as designed. The monitor reading continued to rise and did not stabilize at the expected dose rates.
"RIA-2317 was determined to be inoperable and actions were taken to restore the system."
The NRC Resident Inspector was notified.
The following information was provided by the licensee via phone and email:
"At 0254 EDT, on September 6, 2026, operations received a containment isolation signal from the 'right' train fuel handling area radiation monitor (RIA-2317). At 0256 EDT, operations entered AOP-31, Spurious Containment Isolation, and performed the required abnormal operating procedure actions. All 'right' train valves actuated as designed.
"Radiation protection performed surveys of the general area of the 649' [elevation] of containment around the refuel monitors, and dose rates were normal. It was found that RIA-2317 had spiked high and isolated containment as designed. The monitor reading continued to rise and did not stabilize at the expected dose rates.
"RIA-2317 was determined to be inoperable and actions were taken to restore the system."
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 58514
Facility: Cooper
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Aric Harris
HQ OPS Officer: Robert A. Thompson
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Aric Harris
HQ OPS Officer: Robert A. Thompson
Notification Date: 11/01/2026
Notification Time: 09:20 [ET]
Event Date: 11/01/2026
Event Time: 04:54 [CST]
Last Update Date: 11/01/2026
Notification Time: 09:20 [ET]
Event Date: 11/01/2026
Event Time: 04:54 [CST]
Last Update Date: 11/01/2026
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Dodson, Doug (R4 BC)
R4_Reactor_Events (EMAIL)
Dodson, Doug (R4 BC)
R4_Reactor_Events (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 9 | Startup | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM
The following information was provided by the licensee via phone and email:
"On November 1, 2026, at 0454 CST, with the unit in Mode 2, [startup], at 9 percent power [starting up following a refueling outage], the reactor was manually tripped due to elevated vibrations on the only feedwater pump in service. The trip was not complex, with all systems responding normally post-trip.
"Operations stabilized the plant [in Mode 3, hot shutdown]. Reactor water lever is being maintained with the control rod drive system.
"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).
"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:
"On November 1, 2026, at 0454 CST, with the unit in Mode 2, [startup], at 9 percent power [starting up following a refueling outage], the reactor was manually tripped due to elevated vibrations on the only feedwater pump in service. The trip was not complex, with all systems responding normally post-trip.
"Operations stabilized the plant [in Mode 3, hot shutdown]. Reactor water lever is being maintained with the control rod drive system.
"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).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."