Event Notification Report for April 24, 2026
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Event Text
Event Text
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/23/2026 - 04/24/2026
Power Reactor
Event Number: 58256
Facility: Cook
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Richard Harris
HQ OPS Officer: Robert A. Thompson
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Richard Harris
HQ OPS Officer: Robert A. Thompson
Notification Date: 04/23/2026
Notification Time: 12:30 [ET]
Event Date: 04/23/2026
Event Time: 08:50 [EDT]
Last Update Date: 04/23/2026
Notification Time: 12:30 [ET]
Event Date: 04/23/2026
Event Time: 08:50 [EDT]
Last Update Date: 04/23/2026
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Ruiz, Robert (R3DO)
FFD Group, (EMAIL)
Ruiz, Robert (R3DO)
FFD Group, (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY
The following information was provided by the licensee via phone and email:
"On April 23, 2026, at 0850 EDT, a non-licensed supervisor had a confirmed positive test result for alcohol during a random fitness for duty (FFD) test. The employee's access to the plant has been denied.
"This notification is being made under 10 CFR 26.719 (b)(2)(ii), significant FFD policy violations or programmatic failures, as a twenty-four-hour report.
"The licensee has notified the NRC Resident Inspector."
The following information was provided by the licensee via phone and email:
"On April 23, 2026, at 0850 EDT, a non-licensed supervisor had a confirmed positive test result for alcohol during a random fitness for duty (FFD) test. The employee's access to the plant has been denied.
"This notification is being made under 10 CFR 26.719 (b)(2)(ii), significant FFD policy violations or programmatic failures, as a twenty-four-hour report.
"The licensee has notified the NRC Resident Inspector."
Power Reactor
Event Number: 58257
Facility: Hatch
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Russell Lewis
HQ OPS Officer: Robert A. Thompson
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Russell Lewis
HQ OPS Officer: Robert A. Thompson
Notification Date: 04/23/2026
Notification Time: 17:34 [ET]
Event Date: 04/23/2026
Event Time: 14:08 [EDT]
Last Update Date: 04/23/2026
Notification Time: 17:34 [ET]
Event Date: 04/23/2026
Event Time: 14:08 [EDT]
Last Update Date: 04/23/2026
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):
Williams, Robert (R2DO)
Williams, Robert (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM
The following information was provided by the licensee via phone and email:
"On April 23, 2026, at 1408 EDT, with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped on high reactor pressure. The cause of the high reactor pressure is currently under investigation. The trip was not complex, with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Reactor water level is being maintained by the feedwater system. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 2 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).
"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 rise in reactor pressure was a result of slow closure of the main turbine control valves over approximately one minute due to an unknown cause.
The following information was provided by the licensee via phone and email:
"On April 23, 2026, at 1408 EDT, with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped on high reactor pressure. The cause of the high reactor pressure is currently under investigation. The trip was not complex, with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Reactor water level is being maintained by the feedwater system. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 2 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).
"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 rise in reactor pressure was a result of slow closure of the main turbine control valves over approximately one minute due to an unknown cause.
Page Last Reviewed/Updated April 24, 2026, 04:47 am EDT