Event Notification Report for September 27, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/26/2014 - 09/27/2014
EVENT NUMBERS
50497
Power Reactor
Event Number: 50497
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: REGGIE PICKENS
HQ OPS Officer: DONG HWA PARK
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: REGGIE PICKENS
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/27/2014
Notification Time: 20:09 [ET]
Event Date: 09/27/2014
Event Time: 16:16 [EDT]
Last Update Date: 09/27/2014
Notification Time: 20:09 [ET]
Event Date: 09/27/2014
Event Time: 16:16 [EDT]
Last Update Date: 09/27/2014
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):
MALCOLM WIDMANN (R2DO)
MALCOLM WIDMANN (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Defueled | 0 | Defueled |
REACTOR COOLANT SYSTEM SAFETY INJECTION LINE ULTRASONIC TEST INDICATION
"On Friday, September 26, 2014, while performing planned inspections of Reactor Coolant System piping welds, one flaw indication was identified on each of two 1.5 inch Safety Injection Line connections to the Reactor Coolant System piping. On Saturday, September 27, 2014, after confirmatory inspections and evaluation, both of the flaw indications were determined to not meet the acceptance criteria specified in ASME Code Section XI. As such, these indications are reportable under 10 CFR 50.72(b)(3)(ii) as a Degraded Condition. A repair plan is being developed. There is no impact on current Unit 1 refueling operations while defueled and in No Mode. This condition and repair have no impact to the health and safety of the public or employees.
"The NRC Resident Inspector was notified."
"On Friday, September 26, 2014, while performing planned inspections of Reactor Coolant System piping welds, one flaw indication was identified on each of two 1.5 inch Safety Injection Line connections to the Reactor Coolant System piping. On Saturday, September 27, 2014, after confirmatory inspections and evaluation, both of the flaw indications were determined to not meet the acceptance criteria specified in ASME Code Section XI. As such, these indications are reportable under 10 CFR 50.72(b)(3)(ii) as a Degraded Condition. A repair plan is being developed. There is no impact on current Unit 1 refueling operations while defueled and in No Mode. This condition and repair have no impact to the health and safety of the public or employees.
"The NRC Resident Inspector was notified."