Event Notification Report for August 28, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/27/2022 - 08/28/2022
Power Reactor
Event Number: 56075
Facility: Harris
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: Michael Merletto
HQ OPS Officer: Ernest West
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: Michael Merletto
HQ OPS Officer: Ernest West
Notification Date: 08/28/2022
Notification Time: 07:08 [ET]
Event Date: 08/28/2022
Event Time: 03:29 [EDT]
Last Update Date: 08/28/2022
Notification Time: 07:08 [ET]
Event Date: 08/28/2022
Event Time: 03:29 [EDT]
Last Update Date: 08/28/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Miller, Mark (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP AND AUXILIARY FEEDWATER SYSTEM ACTUATION
The following information was provided by the licensee via email:
"[On 8/28/2022] at 0329 Eastern Daylight Time (EDT), with Unit 1 in Mode 1 at 100% power, the reactor was manually tripped due to a 'B' train main feedwater pump trip. The trip was not complex with all systems responding normally post-trip. The auxiliary feedwater (AFW) system started automatically as expected. Operations responded and stabilized the plant. Steam generator levels are being maintained by AFW through the AFW flow control valves. Decay heat is being removed by using the steam generator power-operated relief valves. The reason for the 'B' train main feedwater pump trip is under investigation.
"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). This event is also being reported per 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of the auxiliary feedwater system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The cause of the 'B' train main feedwater pump trip is suspected to be the result of an electrical transient due to the alarms that the operators received. In addition, the 'A' train main feedwater pump also tripped subsequent to the reactor trip and that cause is still under investigation.
The following information was provided by the licensee via email:
"[On 8/28/2022] at 0329 Eastern Daylight Time (EDT), with Unit 1 in Mode 1 at 100% power, the reactor was manually tripped due to a 'B' train main feedwater pump trip. The trip was not complex with all systems responding normally post-trip. The auxiliary feedwater (AFW) system started automatically as expected. Operations responded and stabilized the plant. Steam generator levels are being maintained by AFW through the AFW flow control valves. Decay heat is being removed by using the steam generator power-operated relief valves. The reason for the 'B' train main feedwater pump trip is under investigation.
"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). This event is also being reported per 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of the auxiliary feedwater system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The cause of the 'B' train main feedwater pump trip is suspected to be the result of an electrical transient due to the alarms that the operators received. In addition, the 'A' train main feedwater pump also tripped subsequent to the reactor trip and that cause is still under investigation.
Power Reactor
Event Number: 56076
Facility: Cook
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: John Whitten
HQ OPS Officer: Bethany Cecere
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: John Whitten
HQ OPS Officer: Bethany Cecere
Notification Date: 08/28/2022
Notification Time: 15:41 [ET]
Event Date: 08/28/2022
Event Time: 13:48 [EDT]
Last Update Date: 08/28/2022
Notification Time: 15:41 [ET]
Event Date: 08/28/2022
Event Time: 13:48 [EDT]
Last Update Date: 08/28/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Pelke, Patricia (R3DO)
Pelke, Patricia (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO REACTOR COOLANT PUMP TRIP
The following information was provided by the licensee via fax or email:
"On August 28, 2022 at 1348 EDT, DC Cook Unit 1 reactor automatically tripped due to a trip of the #13 Reactor Coolant Pump.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The DC Cook Resident NRC Inspector has been notified.
"Unit 1 is being supplied by offsite power. All control rods fully inserted. All Auxiliary Feedwater Pumps started properly. Decay heat is being removed via the Steam Dump System. Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip. DC Cook Unit 1 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event.
"Unit 2 remains stable at 100% power / Mode 1."
The following information was provided by the licensee via fax or email:
"On August 28, 2022 at 1348 EDT, DC Cook Unit 1 reactor automatically tripped due to a trip of the #13 Reactor Coolant Pump.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The DC Cook Resident NRC Inspector has been notified.
"Unit 1 is being supplied by offsite power. All control rods fully inserted. All Auxiliary Feedwater Pumps started properly. Decay heat is being removed via the Steam Dump System. Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip. DC Cook Unit 1 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event.
"Unit 2 remains stable at 100% power / Mode 1."