Event Notification Report for October 03, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/02/2023 - 10/03/2023
EVENT NUMBERS
56774
56774
Power Reactor
Event Number: 56774
Facility: North Anna
Region: 2 State: VA
Unit: [2] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Bob Page
HQ OPS Officer: Karen Cotton-Gross
Region: 2 State: VA
Unit: [2] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Bob Page
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 10/03/2023
Notification Time: 12:55 [ET]
Event Date: 10/03/2023
Event Time: 11:54 [EDT]
Last Update Date: 10/04/2023
Notification Time: 12:55 [ET]
Event Date: 10/03/2023
Event Time: 11:54 [EDT]
Last Update Date: 10/04/2023
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):
Miller, Mark (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
DEGRADED CONDITION
The following information was provided by the licensee via email:
"At 1154 EDT on 10/03/23, investigation into a boric acid indication was determined to be through a leak on a weld-o-let upstream of a pressurizer level transmitter isolation valve. Unit 2 is currently in MODE 6 with reactor coolant system (RCS) operational leakage limits not applicable. The leak is not quantifiable as it only consists of a small amount of dry boric acid at the location. The failure constitutes welding or material defects in the primary coolant system that are unacceptable under ASME Section XI.
"Therefore, this is a degraded condition reportable under 10 CFR 50.72(b)(3)(ii)(A). This condition does not affect the health and safety of the public or station employees."
The Resident Inspector was notified.
The following information was provided by the licensee via email:
"At 1154 EDT on 10/03/23, investigation into a boric acid indication was determined to be through a leak on a weld-o-let upstream of a pressurizer level transmitter isolation valve. Unit 2 is currently in MODE 6 with reactor coolant system (RCS) operational leakage limits not applicable. The leak is not quantifiable as it only consists of a small amount of dry boric acid at the location. The failure constitutes welding or material defects in the primary coolant system that are unacceptable under ASME Section XI.
"Therefore, this is a degraded condition reportable under 10 CFR 50.72(b)(3)(ii)(A). This condition does not affect the health and safety of the public or station employees."
The Resident Inspector was notified.