Event Notification Report for March 03, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/02/2025 - 03/03/2025
Power Reactor
Event Number: 57582
Facility: Limerick
Region: 1 State: PA
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: David Holcomb
HQ OPS Officer: Ernest West
Region: 1 State: PA
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: David Holcomb
HQ OPS Officer: Ernest West
Notification Date: 03/03/2025
Notification Time: 18:09 [ET]
Event Date: 03/03/2025
Event Time: 10:44 [EST]
Last Update Date: 03/03/2025
Notification Time: 18:09 [ET]
Event Date: 03/03/2025
Event Time: 10:44 [EST]
Last Update Date: 03/03/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Ford, Monica (R1DO)
Ford, Monica (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
HPCI DECLARED INOPERABLE
The following information was provided by the licensee via phone and email:
"At 1044 EST, Unit 2 high pressure coolant injection (HPCI) system was declared inoperable per technical specification 3.5.1.C.1 during planned surveillance testing due to test equipment failure and subsequent inadvertent isolation of the outboard HPCI turbine exhaust line vacuum breaker primary containment isolation valve. The test equipment was removed, and the vacuum breaker isolation valve was re-opened. HPCI was restored to operable status at 1351.
"Due to inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72.(b)(3)(v)(D).
"There was no impact to 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:
"At 1044 EST, Unit 2 high pressure coolant injection (HPCI) system was declared inoperable per technical specification 3.5.1.C.1 during planned surveillance testing due to test equipment failure and subsequent inadvertent isolation of the outboard HPCI turbine exhaust line vacuum breaker primary containment isolation valve. The test equipment was removed, and the vacuum breaker isolation valve was re-opened. HPCI was restored to operable status at 1351.
"Due to inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72.(b)(3)(v)(D).
"There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 57583
Facility: Turkey Point
Region: 2 State: FL
Unit: [4] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: Arturo Alvarez
HQ OPS Officer: Ernest West
Region: 2 State: FL
Unit: [4] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: Arturo Alvarez
HQ OPS Officer: Ernest West
Notification Date: 03/03/2025
Notification Time: 22:32 [ET]
Event Date: 03/03/2025
Event Time: 18:03 [EST]
Last Update Date: 03/03/2025
Notification Time: 22:32 [ET]
Event Date: 03/03/2025
Event Time: 18:03 [EST]
Last Update Date: 03/03/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
Person (Organization):
Penmetsa, Ravi (R2DO)
Penmetsa, Ravi (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 4 | N | N | 0 | Cold Shutdown | 0 | Refueling |
DEGRADED CONDITION
The following information was provided by the licensee via phone and email:
"At 1803 EST on 03/03/25, it was determined that the reactor coolant system pressure boundary does not meet American Society of Mechanical Engineers (ASME) section XI, Table IWB-341 0-1, 'Acceptable Standards' due to a through wall leak where the thimble tube connects to penetration number 6. The cause of this event is currently being investigated. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A).
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via phone and email:
"At 1803 EST on 03/03/25, it was determined that the reactor coolant system pressure boundary does not meet American Society of Mechanical Engineers (ASME) section XI, Table IWB-341 0-1, 'Acceptable Standards' due to a through wall leak where the thimble tube connects to penetration number 6. The cause of this event is currently being investigated. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A).
"The NRC Resident Inspector has been notified."