Event Notification Report for September 07, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/06/2019 - 09/07/2019
Power Reactor
Event Number: 54262
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: REESE KILIAN
HQ OPS Officer: ANDREW WAUGH
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: REESE KILIAN
HQ OPS Officer: ANDREW WAUGH
Notification Date: 09/07/2019
Notification Time: 12:01 [ET]
Event Date: 09/07/2019
Event Time: 08:24 [EDT]
Last Update Date: 09/07/2019
Notification Time: 12:01 [ET]
Event Date: 09/07/2019
Event Time: 08:24 [EDT]
Last Update Date: 09/07/2019
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):
SCOTT SHAEFFER (R2DO)
SCOTT SHAEFFER (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 Standby |
AUTOMATIC REACTOR TRIP
"On September 09, 2019 at 0824 EDT, with St. Lucie Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped on Low Reactor Coolant System Flow due to a trip of the 1A1 reactor coolant pump. The trip was uncomplicated with all systems responding normally post-trip. Operators responded and stabilized the plant in Mode 3. The cause of the loss of the 1A1 reactor coolant pump is currently under investigation.
"St. Lucie Unit 2 was unaffected and remains in Mode 1 at 100 percent power.
"This report is submitted in accordance with 10 CFR 50.72(b)(2)(iv)(B) for the reactor trip."
Decay heat removal is being accomplished by main feed water and the main condenser using the turbine steam bypass valves.
The licensee notified the NRC Resident Inspector.
"On September 09, 2019 at 0824 EDT, with St. Lucie Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped on Low Reactor Coolant System Flow due to a trip of the 1A1 reactor coolant pump. The trip was uncomplicated with all systems responding normally post-trip. Operators responded and stabilized the plant in Mode 3. The cause of the loss of the 1A1 reactor coolant pump is currently under investigation.
"St. Lucie Unit 2 was unaffected and remains in Mode 1 at 100 percent power.
"This report is submitted in accordance with 10 CFR 50.72(b)(2)(iv)(B) for the reactor trip."
Decay heat removal is being accomplished by main feed water and the main condenser using the turbine steam bypass valves.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 54263
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: TIM THOMPSON
HQ OPS Officer: ANDREW WAUGH
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: TIM THOMPSON
HQ OPS Officer: ANDREW WAUGH
Notification Date: 09/07/2019
Notification Time: 15:53 [ET]
Event Date: 09/07/2019
Event Time: 13:09 [EDT]
Last Update Date: 09/07/2019
Notification Time: 15:53 [ET]
Event Date: 09/07/2019
Event Time: 13:09 [EDT]
Last Update Date: 09/07/2019
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):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 95 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP
"At 1309 EDT on September 7, 2019, with the unit in Mode 1 at approximately 95 percent power, the reactor automatically tripped during main turbine valve testing. The trip was not complex with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed by the turbine bypass valves discharging steam to the main condenser.
"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 cause of the reactor protection system actuation is under evaluation.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
"At 1309 EDT on September 7, 2019, with the unit in Mode 1 at approximately 95 percent power, the reactor automatically tripped during main turbine valve testing. The trip was not complex with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed by the turbine bypass valves discharging steam to the main condenser.
"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 cause of the reactor protection system actuation is under evaluation.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."