Event Notification Report for May 25, 2020
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/24/2020 - 05/25/2020
Power Reactor
Event Number: 54727
Facility: Surry
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Alan Bialowas
HQ OPS Officer: Jeffrey Whited
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Alan Bialowas
HQ OPS Officer: Jeffrey Whited
Notification Date: 05/26/2020
Notification Time: 15:55 [ET]
Event Date: 05/25/2020
Event Time: 19:38 [EDT]
Last Update Date: 05/26/2020
Notification Time: 15:55 [ET]
Event Date: 05/25/2020
Event Time: 19:38 [EDT]
Last Update Date: 05/26/2020
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
MARK MILLER (R2DO)
FFD GROUP (EMAIL)
MARK MILLER (R2DO)
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 | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
FITNESS FOR DUTY (FFD) POSITIVE TEST
A contract foreman had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector.
A contract foreman had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 54725
Facility: Grand Gulf
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Leroy Purdy
HQ OPS Officer: Bethany Cecere
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Leroy Purdy
HQ OPS Officer: Bethany Cecere
Notification Date: 05/25/2020
Notification Time: 08:44 [ET]
Event Date: 05/25/2020
Event Time: 04:33 [CDT]
Last Update Date: 05/25/2020
Notification Time: 08:44 [ET]
Event Date: 05/25/2020
Event Time: 04:33 [CDT]
Last Update Date: 05/25/2020
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):
RYAN ALEXANDER (R4DO)
RYAN ALEXANDER (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 66 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO MAIN TURBINE TRIP
"An [automatic] reactor SCRAM occurred at 0433 CDT, on 05/25/2020, from 66 percent core thermal power. The cause of the SCRAM was due to a Main Turbine Trip. The cause of the Turbine Trip is under investigation.
"All systems responded as designed. No loss of offsite power or [Emergency Safety Feature] (ESF) power occurred. No [Emergency Core Cooling System] (ECCS) or Emergency Diesel Generator initiations occurred. Main Steam Isolation valves remained open and no radioactive release occurred due to this event. The plant is stable in mode 3. This event is being reported under 10 CFR 50.72(b)(2)(iv)(B), as any event or condition that results in actuation of the Reactor Protection System (RPS), when the reactor is critical.
"The NRC Resident Inspector has been notified."
Decay heat removal is through the Feedwater and Condensate System.
"An [automatic] reactor SCRAM occurred at 0433 CDT, on 05/25/2020, from 66 percent core thermal power. The cause of the SCRAM was due to a Main Turbine Trip. The cause of the Turbine Trip is under investigation.
"All systems responded as designed. No loss of offsite power or [Emergency Safety Feature] (ESF) power occurred. No [Emergency Core Cooling System] (ECCS) or Emergency Diesel Generator initiations occurred. Main Steam Isolation valves remained open and no radioactive release occurred due to this event. The plant is stable in mode 3. This event is being reported under 10 CFR 50.72(b)(2)(iv)(B), as any event or condition that results in actuation of the Reactor Protection System (RPS), when the reactor is critical.
"The NRC Resident Inspector has been notified."
Decay heat removal is through the Feedwater and Condensate System.