Event Notification Report for November 11, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/10/2018 - 11/11/2018
EVENT NUMBERS
53734
Power Reactor
Event Number: 53734
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: MIKE BAILEY
HQ OPS Officer: DONG HWA PARK
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: MIKE BAILEY
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/11/2018
Notification Time: 21:59 [ET]
Event Date: 11/11/2018
Event Time: 00:00 [EST]
Last Update Date: 11/11/2018
Notification Time: 21:59 [ET]
Event Date: 11/11/2018
Event Time: 00:00 [EST]
Last Update Date: 11/11/2018
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):
JOHN HANNA (R3DO)
JOHN HANNA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
DEGRADED CONDITION DUE TO INDICATION DURING ULTRASONIC INSPECTION OF REACTOR HEAD NOZZLE PENETRATION
"On November 11, 2018, during ultrasonic data analysis from reactor vessel closure head in-service inspections, signals that display characteristics consistent with primary water stress corrosion cracking in head penetration 33 were identified. No indications of boric acid leakage and no surface indications were detected at this location during bare metal visual inspection.
"The plant was in cold shutdown at 0% power and in Mode 6 for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage.
"This condition has no impact to the health and safety of the public.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) for degradation of a principal safety barrier.
"The licensee notified the NRC Senior Resident Inspector. "
"On November 11, 2018, during ultrasonic data analysis from reactor vessel closure head in-service inspections, signals that display characteristics consistent with primary water stress corrosion cracking in head penetration 33 were identified. No indications of boric acid leakage and no surface indications were detected at this location during bare metal visual inspection.
"The plant was in cold shutdown at 0% power and in Mode 6 for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage.
"This condition has no impact to the health and safety of the public.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) for degradation of a principal safety barrier.
"The licensee notified the NRC Senior Resident Inspector. "