Event Notification Report for October 30, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/29/2022 - 10/30/2022
Power Reactor
Event Number: 56189
Facility: Harris
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: Brenden Young
HQ OPS Officer: Bill Gott
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: Brenden Young
HQ OPS Officer: Bill Gott
Notification Date: 10/30/2022
Notification Time: 09:43 [ET]
Event Date: 10/30/2022
Event Time: 06:53 [EDT]
Last Update Date: 10/30/2022
Notification Time: 09:43 [ET]
Event Date: 10/30/2022
Event Time: 06:53 [EDT]
Last Update Date: 10/30/2022
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 | A/R | Y | 16 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP AND AUXILIARY FEEDWATER SYSTEM ACTUATION
The following information was provided by the licensee via email:
"At 0653 Eastern Daylight Time (EDT), with Unit 1 in Mode 1, at 16 percent power, an automatic reactor trip occurred due to an under-voltage condition on the 'A' reactor coolant pump (RCP) and the 'C' RCP. Power was lost from the 'A' auxiliary bus while performing an operating procedure to transfer power from the 'A' start-up transformer to the 'A' unit auxiliary transformer.
"Operations responded and stabilized the plant. Decay heat is being removed by the main steam system to the atmosphere using the steam generator power-operated relief valves. 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 information was provided by the licensee via email:
"At 0653 Eastern Daylight Time (EDT), with Unit 1 in Mode 1, at 16 percent power, an automatic reactor trip occurred due to an under-voltage condition on the 'A' reactor coolant pump (RCP) and the 'C' RCP. Power was lost from the 'A' auxiliary bus while performing an operating procedure to transfer power from the 'A' start-up transformer to the 'A' unit auxiliary transformer.
"Operations responded and stabilized the plant. Decay heat is being removed by the main steam system to the atmosphere using the steam generator power-operated relief valves. 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."
Power Reactor
Event Number: 56190
Facility: Harris
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: Lonnie Hickerson
HQ OPS Officer: Adam Koziol
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: Lonnie Hickerson
HQ OPS Officer: Adam Koziol
Notification Date: 10/31/2022
Notification Time: 00:40 [ET]
Event Date: 10/30/2022
Event Time: 20:57 [EDT]
Last Update Date: 10/31/2022
Notification Time: 00:40 [ET]
Event Date: 10/30/2022
Event Time: 20:57 [EDT]
Last Update Date: 10/31/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
10 CFR Section:
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 | N | N | 0 | Hot Standby | 0 | Hot Standby |
SPECIFIED SYSTEM ACTUATION - AUXILIARY FEEDWATER SYSTEM ACTUATION
The following information was provided by the licensee via email:
"At 2057 Eastern Daylight Time (EDT), with Unit 1 in Mode 3 at 0 percent power, an actuation of the Auxiliary Feedwater (AFW) System occurred during an attempt to start the 'B' Main Feed Pump. The reason for the AFW system auto-start was due to the 'A' electrical bus being under clearance and the 'B' Main Feed Pump not starting, resulting in a valid actuation signal for loss of both Main Feedwater pumps. The 'A' and 'B' motor-driven AFW (MDAFW) pumps were running prior to the attempted start of the B Main Feedwater pump and continued to run. The MDAFW Flow Control Valves (FCVs) went full open automatically as designed when the MDAFW actuation signal was received.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW 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 information was provided by the licensee via email:
"At 2057 Eastern Daylight Time (EDT), with Unit 1 in Mode 3 at 0 percent power, an actuation of the Auxiliary Feedwater (AFW) System occurred during an attempt to start the 'B' Main Feed Pump. The reason for the AFW system auto-start was due to the 'A' electrical bus being under clearance and the 'B' Main Feed Pump not starting, resulting in a valid actuation signal for loss of both Main Feedwater pumps. The 'A' and 'B' motor-driven AFW (MDAFW) pumps were running prior to the attempted start of the B Main Feedwater pump and continued to run. The MDAFW Flow Control Valves (FCVs) went full open automatically as designed when the MDAFW actuation signal was received.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW System.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."