Event Notification Report for March 03, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/02/2017 - 03/03/2017
EVENT NUMBERS
52591
Power Reactor
Event Number: 52591
Facility: BYRON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN LEWIN
HQ OPS Officer: JEFF HERRERA
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN LEWIN
HQ OPS Officer: JEFF HERRERA
Notification Date: 03/03/2017
Notification Time: 20:52 [ET]
Event Date: 03/03/2017
Event Time: 17:05 [CST]
Last Update Date: 03/03/2017
Notification Time: 20:52 [ET]
Event Date: 03/03/2017
Event Time: 17:05 [CST]
Last Update Date: 03/03/2017
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):
HIRONORI PETERSON (R3DO)
HIRONORI PETERSON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
PREVIOUS OVERLAY REPAIR DID NOT MEET ACCEPTANCE CRITERIA
"On 3/3/2017 at 1705 [CST], during the Byron Station Unit 1 refueling outage, it was determined that the results of a planned Liquid Penetrant (PT) examination performed on a previous overlay repair of the reactor vessel head did not meet applicable acceptance criteria. The penetration overlay weld indication will be addressed prior to returning the vessel head to service. The examination was being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1 to ensure the structural integrity of the reactor vessel head pressure boundary. Ultrasonic examinations have been performed and no ultrasonic indications were identified.
"This event is being reported under 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.'
"The licensee has notified the NRC Resident Inspector."
"On 3/3/2017 at 1705 [CST], during the Byron Station Unit 1 refueling outage, it was determined that the results of a planned Liquid Penetrant (PT) examination performed on a previous overlay repair of the reactor vessel head did not meet applicable acceptance criteria. The penetration overlay weld indication will be addressed prior to returning the vessel head to service. The examination was being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1 to ensure the structural integrity of the reactor vessel head pressure boundary. Ultrasonic examinations have been performed and no ultrasonic indications were identified.
"This event is being reported under 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.'
"The licensee has notified the NRC Resident Inspector."