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Event Notification Report for July 28, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/27/2024 - 07/28/2024
EVENT NUMBERS
57249
Power Reactor
Event Number: 57249
Facility: Saint Lucie
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Dave Young
HQ OPS Officer: Ian Howard
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Dave Young
HQ OPS Officer: Ian Howard
Notification Date: 07/28/2024
Notification Time: 21:58 [ET]
Event Date: 07/28/2024
Event Time: 18:37 [EDT]
Last Update Date: 07/28/2024
Notification Time: 21:58 [ET]
Event Date: 07/28/2024
Event Time: 18:37 [EDT]
Last Update Date: 07/28/2024
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):
Coovert, Nicole (R2DO)
Coovert, Nicole (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
The following information was provided by the licensee via phone and email:
"At 1837 EDT on 7/28/24, with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped due to inadvertent closure of a main steam isolation valve. During the trip, auxiliary feedwater actuated. All other systems responded normally post-trip. Operations stabilized the plant in mode 3. Decay heat is being removed by atmospheric dump valves and auxiliary feedwater. Unit 2 is not affected.
"This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
The NRC resident inspector has been notified.
The following information was provided by the licensee via phone and email:
"At 1837 EDT on 7/28/24, with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped due to inadvertent closure of a main steam isolation valve. During the trip, auxiliary feedwater actuated. All other systems responded normally post-trip. Operations stabilized the plant in mode 3. Decay heat is being removed by atmospheric dump valves and auxiliary feedwater. Unit 2 is not affected.
"This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
The NRC resident inspector has been notified.