Event Notification Report for March 05, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/04/2017 - 03/05/2017
EVENT NUMBERS
52592
Power Reactor
Event Number: 52592
Facility: BYRON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMIE GETCHIUS
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMIE GETCHIUS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/05/2017
Notification Time: 16:05 [ET]
Event Date: 03/05/2017
Event Time: 08:00 [CST]
Last Update Date: 03/06/2017
Notification Time: 16:05 [ET]
Event Date: 03/05/2017
Event Time: 08:00 [CST]
Last Update Date: 03/06/2017
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 | Defueled | 0 | Defueled |
PLANNED ULTRASONIC TEST ON PREVIOUSLY REPAIRED REACTOR VESSEL PENETRATION DID NOT MEET ACCEPTANCE CRITERIA
"On 3/5/2017 at 0800 [CST], during the Byron Station Unit 1 refueling outage, it was determined that the results of a planned Ultrasonic (UT) examination performed on a previous repaired penetration of the reactor vessel head did not meet applicable acceptance criteria. These indications are not in the reactor coolant pressure boundary; however they are very near the previously repaired J-groove weld. The 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.
"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.
"Exelon Generation Company, LLC is also notifying the NRC Division of Component Integrity or its successor, by use of this ENS Report, of changes in indication(s) or findings of new indications(s) in the penetration nozzle or J-groove weld beneath a seal weld repair, or new linear indications in the seal weld repair, prior to commencing repair activities."
See also EN #52591
* * * UPDATE PROVIDED BY CHARLES BERGER TO JEFF ROTTON AT 1750 EST ON 03/06/2017 * * *
"Byron Event Notification 52952, made on March 05, 2017, reported two indications on one reactor head penetration.
"On March 06, 2017, ultrasonic examination identified two additional indications on the same penetration nozzle, (P-76). Additionally, two indications were identified on a second penetration nozzle (P-74), and one indication was identified on a third penetration nozzle (P-77). The indications on these three penetrations are all of the same type and none are within the reactor vessel head pressure boundary.
"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 NRC Resident Inspector has been notified.
"Exelon Generation Company, LLC is also notifying the NRC Division of Component Integrity or its successor, by use of this ENS Report, of changes in indication(s) or findings of new indications(s) in the penetration nozzle or J-groove weld beneath a seal weld repair, or new linear indications in the seal weld repair, prior to commencing repair activities."
Notified R3DO (Jeffers)
"On 3/5/2017 at 0800 [CST], during the Byron Station Unit 1 refueling outage, it was determined that the results of a planned Ultrasonic (UT) examination performed on a previous repaired penetration of the reactor vessel head did not meet applicable acceptance criteria. These indications are not in the reactor coolant pressure boundary; however they are very near the previously repaired J-groove weld. The 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.
"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.
"Exelon Generation Company, LLC is also notifying the NRC Division of Component Integrity or its successor, by use of this ENS Report, of changes in indication(s) or findings of new indications(s) in the penetration nozzle or J-groove weld beneath a seal weld repair, or new linear indications in the seal weld repair, prior to commencing repair activities."
See also EN #52591
* * * UPDATE PROVIDED BY CHARLES BERGER TO JEFF ROTTON AT 1750 EST ON 03/06/2017 * * *
"Byron Event Notification 52952, made on March 05, 2017, reported two indications on one reactor head penetration.
"On March 06, 2017, ultrasonic examination identified two additional indications on the same penetration nozzle, (P-76). Additionally, two indications were identified on a second penetration nozzle (P-74), and one indication was identified on a third penetration nozzle (P-77). The indications on these three penetrations are all of the same type and none are within the reactor vessel head pressure boundary.
"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 NRC Resident Inspector has been notified.
"Exelon Generation Company, LLC is also notifying the NRC Division of Component Integrity or its successor, by use of this ENS Report, of changes in indication(s) or findings of new indications(s) in the penetration nozzle or J-groove weld beneath a seal weld repair, or new linear indications in the seal weld repair, prior to commencing repair activities."
Notified R3DO (Jeffers)