Event Notification Report for August 20, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/19/2023 - 08/20/2023
EVENT NUMBERS
56685
56685
Power Reactor
Event Number: 56685
Facility: Fermi
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: Richard Beck
HQ OPS Officer: Dan Livermore
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: Richard Beck
HQ OPS Officer: Dan Livermore
Notification Date: 08/20/2023
Notification Time: 18:30 [ET]
Event Date: 08/20/2023
Event Time: 16:00 [EDT]
Last Update Date: 08/20/2023
Notification Time: 18:30 [ET]
Event Date: 08/20/2023
Event Time: 16:00 [EDT]
Last Update Date: 08/20/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By Ts 50.72(b)(2)(xi) - Offsite Notification 50.72(b)(3)(ii)(A) - Degraded Condition
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By Ts 50.72(b)(2)(xi) - Offsite Notification 50.72(b)(3)(ii)(A) - Degraded Condition
Person (Organization):
Betancourt-Roldan, Diana (R3DO)
Betancourt-Roldan, Diana (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
The following information was provided by the licensee via email:
"On 8/20/2023 at 1600 EDT, during plant walkdowns in the drywell while in mode 3 to identify a cause of increasing unidentified leakage rate, reactor coolant system pressure boundary leakage (approximately 2 gpm) was identified on the reactor recirculation sample line between the reactor recirculation sample line inboard isolation valve (B3100F019) and where the sample line taps off the B reactor recirculation jet pump riser. This requires entry into technical specification 3.4.4 condition C, identification of pressure boundary leakage with a required action to be in mode 3 in 12 hours and mode 4 in 36 hours. At 1630 EDT, a technical specification required shutdown to mode 4, cold shutdown, was initiated.
"A press release by DTE is anticipated. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i), a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(xi), and an eight-hour, non-emergency notification 10 CFR 50.72(b)(3)(ii)(A) for the degraded condition of the pressure boundary.
"Investigation into the cause of the reactor coolant system pressure boundary leakage is still ongoing.
"There was no impact on 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 email:
"On 8/20/2023 at 1600 EDT, during plant walkdowns in the drywell while in mode 3 to identify a cause of increasing unidentified leakage rate, reactor coolant system pressure boundary leakage (approximately 2 gpm) was identified on the reactor recirculation sample line between the reactor recirculation sample line inboard isolation valve (B3100F019) and where the sample line taps off the B reactor recirculation jet pump riser. This requires entry into technical specification 3.4.4 condition C, identification of pressure boundary leakage with a required action to be in mode 3 in 12 hours and mode 4 in 36 hours. At 1630 EDT, a technical specification required shutdown to mode 4, cold shutdown, was initiated.
"A press release by DTE is anticipated. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i), a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(xi), and an eight-hour, non-emergency notification 10 CFR 50.72(b)(3)(ii)(A) for the degraded condition of the pressure boundary.
"Investigation into the cause of the reactor coolant system pressure boundary leakage is still ongoing.
"There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector has been notified."