Event Notification Report for February 19, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/18/2024 - 02/19/2024
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 56978
Facility: Summer
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: Jason Pawlak
HQ OPS Officer: Ernest West
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: Jason Pawlak
HQ OPS Officer: Ernest West
Notification Date: 02/19/2024
Notification Time: 06:32 [ET]
Event Date: 02/19/2024
Event Time: 02:36 [EST]
Last Update Date: 06/06/2024
Notification Time: 06:32 [ET]
Event Date: 02/19/2024
Event Time: 02:36 [EST]
Last Update Date: 06/06/2024
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 | Y | 100 | Power Operation | 100 | Power Operation |
EN Revision Imported Date: 6/6/2024
EN Revision Text: AUTOMATIC START OF 'B' EMERGENCY DIESEL GENERATOR
The following information was provided by the licensee via phone and email:
"On February 19, 2024, at 0236 EST, with VC Summer Unit 1 in Mode 1 at 100 percent power, an actuation of the `B' emergency diesel generator (EDG) occurred. The reason for the `B' EDG auto-start was the trip of 1 `DB' normal incoming breaker. The `B' EDG automatically started as designed when the undervoltage signal was received. The `B' emergency feedwater pump started due to the undervoltage signal and ran for approximately 1 minute and was secured by operations per procedure. Other plant equipment and systems also responded as expected. 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 `B' EDG and a valid actuation of the `B' emergency feedwater pump. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"The `A' Emergency Diesel Generator was tagged out for maintenance earlier in the shift, but maintenance has not started. The plan is to restore the `A' emergency diesel generator to an operable status and investigate the cause of the 1 `DB' normal incoming breaker trip."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
This event resulted in the plant entering a 12 hour limiting condition for operation (LCO) in accordance with technical specification (TS) 3.8.1.1.C. due to having one operable EDG and a loss of offsite power.
*** RETRACTION ON 06/06/2024 AT 1356 EDT FROM JUSTIN BOUKNIGHT TO NATALIE STARFISH ***
"VC Summer is retracting event notification (EN) 56978 regarding the unexpected actuations of the 'B' emergency diesel generator and 'B' emergency feedwater pump on 02/19/2024. Both were previously reported as valid actuations under 10 CFR 50.72(b)(3)(iv)(A). Subsequent evaluation has determined that the actuations were the result of an invalid signal caused by equipment failure on the 1 DB bus undervoltage control circuit.
"The event, its cause, and corrective actions were reported in VC Summer licensee event report 2024-001-00 (ML24108A143) on 04/17/2024, pursuant to the requirements of 10 CFR 50.73(a)(2)(iv)(A). There was no impact on the health and safety of the public or plant personnel as a result of the actuations.
"The NRC Senior Resident Inspector has been notified."
Notified R2DO (Franke)
EN Revision Text: AUTOMATIC START OF 'B' EMERGENCY DIESEL GENERATOR
The following information was provided by the licensee via phone and email:
"On February 19, 2024, at 0236 EST, with VC Summer Unit 1 in Mode 1 at 100 percent power, an actuation of the `B' emergency diesel generator (EDG) occurred. The reason for the `B' EDG auto-start was the trip of 1 `DB' normal incoming breaker. The `B' EDG automatically started as designed when the undervoltage signal was received. The `B' emergency feedwater pump started due to the undervoltage signal and ran for approximately 1 minute and was secured by operations per procedure. Other plant equipment and systems also responded as expected. 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 `B' EDG and a valid actuation of the `B' emergency feedwater pump. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"The `A' Emergency Diesel Generator was tagged out for maintenance earlier in the shift, but maintenance has not started. The plan is to restore the `A' emergency diesel generator to an operable status and investigate the cause of the 1 `DB' normal incoming breaker trip."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
This event resulted in the plant entering a 12 hour limiting condition for operation (LCO) in accordance with technical specification (TS) 3.8.1.1.C. due to having one operable EDG and a loss of offsite power.
*** RETRACTION ON 06/06/2024 AT 1356 EDT FROM JUSTIN BOUKNIGHT TO NATALIE STARFISH ***
"VC Summer is retracting event notification (EN) 56978 regarding the unexpected actuations of the 'B' emergency diesel generator and 'B' emergency feedwater pump on 02/19/2024. Both were previously reported as valid actuations under 10 CFR 50.72(b)(3)(iv)(A). Subsequent evaluation has determined that the actuations were the result of an invalid signal caused by equipment failure on the 1 DB bus undervoltage control circuit.
"The event, its cause, and corrective actions were reported in VC Summer licensee event report 2024-001-00 (ML24108A143) on 04/17/2024, pursuant to the requirements of 10 CFR 50.73(a)(2)(iv)(A). There was no impact on the health and safety of the public or plant personnel as a result of the actuations.
"The NRC Senior Resident Inspector has been notified."
Notified R2DO (Franke)
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 56980
Facility: Peach Bottom
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: Troy Ralston
HQ OPS Officer: Thomas Herrity
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: Troy Ralston
HQ OPS Officer: Thomas Herrity
Notification Date: 02/19/2024
Notification Time: 18:44 [ET]
Event Date: 02/19/2024
Event Time: 10:45 [EST]
Last Update Date: 03/15/2024
Notification Time: 18:44 [ET]
Event Date: 02/19/2024
Event Time: 10:45 [EST]
Last Update Date: 03/15/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
Person (Organization):
Bickett, Carey (R1DO)
Bickett, Carey (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
EN Revision Imported Date: 3/18/2024
EN Revision Text: LOSS OF REACTOR BUILDING VENTILATION
The following information was provided by the licensee via email:
"At 1045 EST, on 2/19/2024, during a maintenance activity, a loss of all reactor building ventilation occurred on Unit 2. With no flow past the ventilation radiation monitors, the radiation monitors were inoperable to support their ability to perform primary and secondary containment isolation functions or start the standby gas treatment system. Reactor building ventilation was restored within 15 minutes. Due to this inoperability, the radiation monitor system was in a condition that could have prevented fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector will be notified."
* * * RETRACTION ON 3/15/24 AT 1315 EDT FROM BILL LINNELL TO ADAM KOZIOL * * *
"Upon further investigation, it was verified that the reactor building and the refueling floor radiation monitors are not needed to control the release of radiation for events described in chapter 14 of the updated Final Safety Analysis Report. For the analyzed loss of coolant accident (LOCA), the primary and secondary signals for this purpose were available and unaffected by this event. The radiation monitors provide a tertiary redundant method that is not credited within the station analysis. For all other analyzed accidents, the signal provided by the radiation monitors is not needed, as the secondary containment isolation function and start of the standby gas treatment system are not credited. Additionally, the fuel handling accident was not credible during the time of the event because no activities were in progress on the refueling floor. Therefore, the threshold for reporting the issue as an event or condition that could have prevented the fulfillment of a safety function was not met.
"The NRC Resident Inspector has been notified."
Notified R1DO (Jackson)
EN Revision Text: LOSS OF REACTOR BUILDING VENTILATION
The following information was provided by the licensee via email:
"At 1045 EST, on 2/19/2024, during a maintenance activity, a loss of all reactor building ventilation occurred on Unit 2. With no flow past the ventilation radiation monitors, the radiation monitors were inoperable to support their ability to perform primary and secondary containment isolation functions or start the standby gas treatment system. Reactor building ventilation was restored within 15 minutes. Due to this inoperability, the radiation monitor system was in a condition that could have prevented fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector will be notified."
* * * RETRACTION ON 3/15/24 AT 1315 EDT FROM BILL LINNELL TO ADAM KOZIOL * * *
"Upon further investigation, it was verified that the reactor building and the refueling floor radiation monitors are not needed to control the release of radiation for events described in chapter 14 of the updated Final Safety Analysis Report. For the analyzed loss of coolant accident (LOCA), the primary and secondary signals for this purpose were available and unaffected by this event. The radiation monitors provide a tertiary redundant method that is not credited within the station analysis. For all other analyzed accidents, the signal provided by the radiation monitors is not needed, as the secondary containment isolation function and start of the standby gas treatment system are not credited. Additionally, the fuel handling accident was not credible during the time of the event because no activities were in progress on the refueling floor. Therefore, the threshold for reporting the issue as an event or condition that could have prevented the fulfillment of a safety function was not met.
"The NRC Resident Inspector has been notified."
Notified R1DO (Jackson)