Event Notification Report for March 18, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/17/2023 - 03/18/2023
EVENT NUMBERS
56421
56421
Power Reactor
Event Number: 56421
Facility: Nine Mile Point
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: Chris Grapes
HQ OPS Officer: Ernest West
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: Chris Grapes
HQ OPS Officer: Ernest West
Notification Date: 03/18/2023
Notification Time: 19:07 [ET]
Event Date: 03/18/2023
Event Time: 14:10 [EDT]
Last Update Date: 03/18/2023
Notification Time: 19:07 [ET]
Event Date: 03/18/2023
Event Time: 14:10 [EDT]
Last Update Date: 03/18/2023
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):
Bickett, Brice (R1DO)
Bickett, Brice (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 0 | Refueling | 0 | Refueling |
DEFECT IN REACTOR PENETRATION WELD
The following information was provided by the licensee via email:
"On 3/18/2023 at 1410 EDT, with Nine Mile Point Nuclear Station Unit 1 in a planned refueling outage, the main control room was notified of the results of an automated examination of a dissimilar metal weld on reactor penetration N2E. The results indicate a defect present which cannot be found acceptable under ASME Section XI, IWB-3600.
"This 8-hour non-emergency report is being made based upon requirements of 10CFR50.72(b)(3)(ii)(A) which states, `The licensee shall notify the NRC ... of the occurrence of ... any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.'
"The NRC Senior Resident was informed. A repair plan is being developed."
The following information was provided by the licensee via email:
"On 3/18/2023 at 1410 EDT, with Nine Mile Point Nuclear Station Unit 1 in a planned refueling outage, the main control room was notified of the results of an automated examination of a dissimilar metal weld on reactor penetration N2E. The results indicate a defect present which cannot be found acceptable under ASME Section XI, IWB-3600.
"This 8-hour non-emergency report is being made based upon requirements of 10CFR50.72(b)(3)(ii)(A) which states, `The licensee shall notify the NRC ... of the occurrence of ... any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.'
"The NRC Senior Resident was informed. A repair plan is being developed."