Event Notification Report for April 10, 2020
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/09/2020 - 04/10/2020
Power Reactor
Event Number: 54661
Facility: OCONEE
Region: 2 State: SC
Unit: [] [] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: SAM MORTON
HQ OPS Officer: CATY NOLAN
Region: 2 State: SC
Unit: [] [] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: SAM MORTON
HQ OPS Officer: CATY NOLAN
Notification Date: 04/11/2020
Notification Time: 01:03 [ET]
Event Date: 04/10/2020
Event Time: 21:25 [EDT]
Last Update Date: 04/11/2020
Notification Time: 01:03 [ET]
Event Date: 04/10/2020
Event Time: 21:25 [EDT]
Last Update Date: 04/11/2020
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MARK MILLER (R2DO)
MARK MILLER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | M/R | Y | 32 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP
"At 2125 EDT on April 10, 2020, with Unit 3 in Mode 1 at approximately 32 percent power, the reactor was manually tripped due to a tube leak in the 3F1 feedwater heater. The trip occurred during a planned shutdown for a refueling outage.
"The trip was not complicated, with all systems responding normally post-trip. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Units 1 and 2 were not affected.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
"At 2125 EDT on April 10, 2020, with Unit 3 in Mode 1 at approximately 32 percent power, the reactor was manually tripped due to a tube leak in the 3F1 feedwater heater. The trip occurred during a planned shutdown for a refueling outage.
"The trip was not complicated, with all systems responding normally post-trip. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Units 1 and 2 were not affected.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 54657
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROBERT GRAHAM III
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROBERT GRAHAM III
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/10/2020
Notification Time: 10:58 [ET]
Event Date: 04/10/2020
Event Time: 03:00 [EDT]
Last Update Date: 04/10/2020
Notification Time: 10:58 [ET]
Event Date: 04/10/2020
Event Time: 03:00 [EDT]
Last Update Date: 04/10/2020
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JON LILLIENDAHL (R1DO)
JON LILLIENDAHL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE CORE INJECTION SYSTEM DECLARED INOPERABLE
"On April 10, 2020, at 0300 [EDT], an oil leak from 23PCV-12, HPCI [High Pressure Core Injection] Trip System Pressure Control Valve (PCV), resulted in the system being declared inoperable. This condition is being reported as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident per 10 CFR 50.72(b)(3)(v)(D)."
The licensee notified the NRC Resident Inspector.
"On April 10, 2020, at 0300 [EDT], an oil leak from 23PCV-12, HPCI [High Pressure Core Injection] Trip System Pressure Control Valve (PCV), resulted in the system being declared inoperable. This condition is being reported as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident per 10 CFR 50.72(b)(3)(v)(D)."
The licensee notified the NRC Resident Inspector.