Event Notification Report for January 14, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/13/2017 - 01/14/2017
EVENT NUMBERS
52490
Power Reactor
Event Number: 52490
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: HENDRIK VERWEY
HQ OPS Officer: JOHN SHOEMAKER
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: HENDRIK VERWEY
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/14/2017
Notification Time: 13:09 [ET]
Event Date: 01/14/2017
Event Time: 06:13 [EST]
Last Update Date: 01/14/2017
Notification Time: 13:09 [ET]
Event Date: 01/14/2017
Event Time: 06:13 [EST]
Last Update Date: 01/14/2017
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):
ANTHONY DIMITRIADIS (R1DO)
ANTHONY DIMITRIADIS (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Startup | 0 | Hot Shutdown |
DEGRADED CONDITION DUE TO THROUGH-WALL LEAK
"At 0613 EST on 1/14/2017, with the unit in Mode 2 at 0 percent power at the start of Refueling Outage 22, Drywell inspection identified a through-wall leak on the 3/4-inch vent line off the bonnet of valve 02MOV-43A, Reactor Water Recirc Pump A Suction Isolation Valve, in the Reactor Coolant System (RCS) loop inside the Primary Containment. This condition constitutes a defect in the primary coolant system.
"This event notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) as a 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.
"At 0613 EST on 1/14/2017, with the unit in Mode 2 at 0 percent power at the start of Refueling Outage 22, Drywell inspection identified a through-wall leak on the 3/4-inch vent line off the bonnet of valve 02MOV-43A, Reactor Water Recirc Pump A Suction Isolation Valve, in the Reactor Coolant System (RCS) loop inside the Primary Containment. This condition constitutes a defect in the primary coolant system.
"This event notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) as a 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.