Event Notification Report for October 02, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/01/2016 - 10/02/2016
EVENT NUMBERS
52275
Power Reactor
Event Number: 52275
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RON BRUCK
HQ OPS Officer: DONG HWA PARK
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RON BRUCK
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/03/2016
Notification Time: 00:02 [ET]
Event Date: 10/02/2016
Event Time: 16:00 [CDT]
Last Update Date: 10/03/2016
Notification Time: 00:02 [ET]
Event Date: 10/02/2016
Event Time: 16:00 [CDT]
Last Update Date: 10/03/2016
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):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
LIQUID PENETRATION EXAMINATION RESULTS IN INDICATIONS ON REACTOR VESSEL HEAD PENETRATION
"On October 2, 2016 during the Braidwood Station Unit Refueling outage (A1R19), an in-service Liquid Penetration examination was performed on the previously repaired control rod drive mechanism (CRDM) penetration 69. During the examination on the weld build up for CRDM penetration 69, two indications were discovered. A 7/32 inch rounded indication was discovered located at 359 degrees on the reactor head portion of the weld buildup, and it is 4 inches from the transition of the head to penetration. A 1/4 inch rounded indication was also discovered located at 200 degrees at the transition of the head to penetration. 0 degrees is located at the outermost portion of the penetration on the flange side. The transition is the point where the vertical portion of the penetration meets the horizontal area of the reactor head.
"Rounded indications that exceed 3/16 inch are rejectable per ASME Code Case N-729-1.
"This is reportable pursuant to 10CFR50.72(b)(3)(ii)(A), 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded' since the as found indication did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair.
"The NRC Resident Inspector has been informed."
"On October 2, 2016 during the Braidwood Station Unit Refueling outage (A1R19), an in-service Liquid Penetration examination was performed on the previously repaired control rod drive mechanism (CRDM) penetration 69. During the examination on the weld build up for CRDM penetration 69, two indications were discovered. A 7/32 inch rounded indication was discovered located at 359 degrees on the reactor head portion of the weld buildup, and it is 4 inches from the transition of the head to penetration. A 1/4 inch rounded indication was also discovered located at 200 degrees at the transition of the head to penetration. 0 degrees is located at the outermost portion of the penetration on the flange side. The transition is the point where the vertical portion of the penetration meets the horizontal area of the reactor head.
"Rounded indications that exceed 3/16 inch are rejectable per ASME Code Case N-729-1.
"This is reportable pursuant to 10CFR50.72(b)(3)(ii)(A), 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded' since the as found indication did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair.
"The NRC Resident Inspector has been informed."