Event Notification Report for February 16, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/15/2023 - 02/16/2023
Power Reactor
Event Number: 56366
Facility: McGuire
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Terra Sanders
HQ OPS Officer: Eric Simpson
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Terra Sanders
HQ OPS Officer: Eric Simpson
Notification Date: 02/16/2023
Notification Time: 11:33 [ET]
Event Date: 02/16/2023
Event Time: 09:15 [EST]
Last Update Date: 02/16/2023
Notification Time: 11:33 [ET]
Event Date: 02/16/2023
Event Time: 09:15 [EST]
Last Update Date: 02/16/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Miller, Mark (R2DO)
Felts, Russell (NRR EO)
Crouch, Howard (IR MOC)
Miller, Mark (R2DO)
Felts, Russell (NRR EO)
Crouch, Howard (IR MOC)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFF-SITE NOTIFICATION OF AN ON-SITE FATALITY
The following information was provided by the licensee via email:
"On February 16, 2023 at 0859 EST, a contract worker at McGuire was transported off-site for treatment at an off-site medical facility. Upon arrival at the off-site medical facility, medical personnel declared the individual deceased at 0915 EST.
"The fatality was not work-related and the individual was inside the Radiologically Controlled Area. An on-site survey confirmed that neither the individual nor the individual's clothing were contaminated. A notification will be made to the Occupational Safety and Health Administration.
"This is a four-hour notification, non-emergency for an on-site fatality and notification of other government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"On February 16, 2023 at 0859 EST, a contract worker at McGuire was transported off-site for treatment at an off-site medical facility. Upon arrival at the off-site medical facility, medical personnel declared the individual deceased at 0915 EST.
"The fatality was not work-related and the individual was inside the Radiologically Controlled Area. An on-site survey confirmed that neither the individual nor the individual's clothing were contaminated. A notification will be made to the Occupational Safety and Health Administration.
"This is a four-hour notification, non-emergency for an on-site fatality and notification of other government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 56367
Facility: Vogtle 3/4
Region: 2 State: GA
Unit: [4] [] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: Will Garrett
HQ OPS Officer: Adam Koziol
Region: 2 State: GA
Unit: [4] [] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: Will Garrett
HQ OPS Officer: Adam Koziol
Notification Date: 02/16/2023
Notification Time: 15:52 [ET]
Event Date: 02/16/2023
Event Time: 07:43 [EST]
Last Update Date: 02/16/2023
Notification Time: 15:52 [ET]
Event Date: 02/16/2023
Event Time: 07:43 [EST]
Last Update Date: 02/16/2023
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Miller, Mark (R2DO)
FFD Group, (EMAIL)
Miller, Mark (R2DO)
FFD Group, (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 4 | N | N | 0 | Under Construction | 0 | Under Construction |
FAILED FITNESS FOR DUTY TEST
The following information was provided by the licensee via email:
At 0743 EST on February 16, 2023, it was determined that a contract supervisor failed a random fitness-for-duty (FFD) test. The individual's authorization for site access has been terminated.
The NRC Resident Inspector has been notified.
The following information was provided by the licensee via email:
At 0743 EST on February 16, 2023, it was determined that a contract supervisor failed a random fitness-for-duty (FFD) test. The individual's authorization for site access has been terminated.
The NRC Resident Inspector has been notified.
Agreement State
Event Number: 56370
Rep Org: PA Bureau of Radiation Protection
Licensee: Veolia ES Alaron, LLC
Region: 1
City: Wampum State: PA
County:
License #: PA-0678
Agreement: Y
Docket:
NRC Notified By: Joshua Myers
HQ OPS Officer: Adam Koziol
Licensee: Veolia ES Alaron, LLC
Region: 1
City: Wampum State: PA
County:
License #: PA-0678
Agreement: Y
Docket:
NRC Notified By: Joshua Myers
HQ OPS Officer: Adam Koziol
Notification Date: 02/17/2023
Notification Time: 12:59 [ET]
Event Date: 02/16/2023
Event Time: 00:00 [EST]
Last Update Date: 02/17/2023
Notification Time: 12:59 [ET]
Event Date: 02/16/2023
Event Time: 00:00 [EST]
Last Update Date: 02/17/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Dentel, Glenn (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Dentel, Glenn (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - UNPLANNED CONTAMINATION EVENT
The following information was provided by the Pennsylvania Department of Environmental Protection (Department / DEP) via email:
"On February 16, 2023, the licensee informed the Department of a contamination event involving Cobalt 60. It is reportable as per 10 CFR 30.50(b)(1).
"On February 16, 2023, the licensee received an exclusive use shipment of boxes of equipment from Dresden Nuclear Station. Upon surveying the conveyance after unloading, the licensee found a small area of contamination approximately 2" x 2" in surface area on the bed of the trailer outside of where the boxes were positioned. The licensee isolated the trailer at its facility, decontaminated the area of contamination, resurveyed the trailer, and released it. The licensee informed their client, Dresden Nuclear Station, of the issue. The DEP is currently in contact with the licensee and will update this event as soon as more information is provided.
"The Department will perform a reactive inspection. More information will be provided as received."
Pennsylvania Event Number: PA230007
The following information was provided by the Pennsylvania Department of Environmental Protection (Department / DEP) via email:
"On February 16, 2023, the licensee informed the Department of a contamination event involving Cobalt 60. It is reportable as per 10 CFR 30.50(b)(1).
"On February 16, 2023, the licensee received an exclusive use shipment of boxes of equipment from Dresden Nuclear Station. Upon surveying the conveyance after unloading, the licensee found a small area of contamination approximately 2" x 2" in surface area on the bed of the trailer outside of where the boxes were positioned. The licensee isolated the trailer at its facility, decontaminated the area of contamination, resurveyed the trailer, and released it. The licensee informed their client, Dresden Nuclear Station, of the issue. The DEP is currently in contact with the licensee and will update this event as soon as more information is provided.
"The Department will perform a reactive inspection. More information will be provided as received."
Pennsylvania Event Number: PA230007
Power Reactor
Event Number: 56464
Facility: Limerick
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Tim Gallacher
HQ OPS Officer: Sam Colvard
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Tim Gallacher
HQ OPS Officer: Sam Colvard
Notification Date: 04/11/2023
Notification Time: 11:05 [ET]
Event Date: 02/16/2023
Event Time: 08:05 [EDT]
Last Update Date: 04/11/2023
Notification Time: 11:05 [ET]
Event Date: 02/16/2023
Event Time: 08:05 [EDT]
Last Update Date: 04/11/2023
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation Other Unspec Reqmnt
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation Other Unspec Reqmnt
Person (Organization):
Lilliendahl, Jon (R1DO)
Lilliendahl, Jon (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 |
60 DAY NOTIFICATION FOR AN INVALID ACTUATION OF THE EMERGENCY SERVICE WATER SYSTEM
The following information was provided by the licensee via email:
"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid specific system actuation of the Emergency Service Water (ESW) System.
"On 2/16/2023, while performing a calibration planned maintenance (PM) for a jacket water pressure indicator during a D13 diesel generator system outage window, the 'C' ESW pump unexpectedly auto-started. Subsequent investigation identified that the affected jacket water pressure indicator shares a common sensing line with a jacket water pressure switch that provides a back-up to the engine speed switch for the engine running signal. At the time the jacket water pressure indicator calibration PM was being performed, the power circuits for D13 diesel generator instrumentation were energized. Pressurization of the energized jacket water pressure switch during the pressure indicator calibration activity resulted in initiation of a false engine running signal to the `C' ESW pump start logic.
"This event is considered an invalid system actuation because the 'C' ESW pump started in response to a false signal that the D13 EDG was running when the D13 EDG did not start. The actuation was not initiated in response to actual plant conditions or parameters and was not a manual initiation. The ESW system functioned as expected in response to the actuation. The affected ESW pump was shut down in accordance with plant procedures. There was no impact on the health and safety of the public or plant personnel."
The licensee notified the NRC Resident Inspector.
The following information was provided by the licensee via email:
"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid specific system actuation of the Emergency Service Water (ESW) System.
"On 2/16/2023, while performing a calibration planned maintenance (PM) for a jacket water pressure indicator during a D13 diesel generator system outage window, the 'C' ESW pump unexpectedly auto-started. Subsequent investigation identified that the affected jacket water pressure indicator shares a common sensing line with a jacket water pressure switch that provides a back-up to the engine speed switch for the engine running signal. At the time the jacket water pressure indicator calibration PM was being performed, the power circuits for D13 diesel generator instrumentation were energized. Pressurization of the energized jacket water pressure switch during the pressure indicator calibration activity resulted in initiation of a false engine running signal to the `C' ESW pump start logic.
"This event is considered an invalid system actuation because the 'C' ESW pump started in response to a false signal that the D13 EDG was running when the D13 EDG did not start. The actuation was not initiated in response to actual plant conditions or parameters and was not a manual initiation. The ESW system functioned as expected in response to the actuation. The affected ESW pump was shut down in accordance with plant procedures. There was no impact on the health and safety of the public or plant personnel."
The licensee notified the NRC Resident Inspector.