Event Notification Report for May 03, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/02/2024 - 05/03/2024
Power Reactor
Event Number: 57103
Facility: Hope Creek
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Daniel White
HQ OPS Officer: Sam Colvard
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Daniel White
HQ OPS Officer: Sam Colvard
Notification Date: 05/03/2024
Notification Time: 11:56 [ET]
Event Date: 05/03/2024
Event Time: 04:11 [EDT]
Last Update Date: 05/03/2024
Notification Time: 11:56 [ET]
Event Date: 05/03/2024
Event Time: 04:11 [EDT]
Last Update Date: 05/03/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
Person (Organization):
Eve, Elise (R1DO)
Eve, Elise (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
PRIMARY CONTAINMENT DEGRADED
The following information was provided by the licensee via email:
"At 0411 EDT on 5/03/2024, it was determined that primary containment did not meet TS (Technical Specification) 4.6.1.2 [surveillance] requirement due to a primary containment leak rate test exceeding `La' [allowable leakage rate].
"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"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 final observed leak rate is still being calculated as the test is still within the stabilization period. Testing is allowed within the stabilization period for an unspecified amount of time. Short term corrective actions are to identify and repair any leak paths. No mode changes are required due to this event.
The following information was provided by the licensee via email:
"At 0411 EDT on 5/03/2024, it was determined that primary containment did not meet TS (Technical Specification) 4.6.1.2 [surveillance] requirement due to a primary containment leak rate test exceeding `La' [allowable leakage rate].
"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"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 final observed leak rate is still being calculated as the test is still within the stabilization period. Testing is allowed within the stabilization period for an unspecified amount of time. Short term corrective actions are to identify and repair any leak paths. No mode changes are required due to this event.
Power Reactor
Event Number: 57104
Facility: Oconee
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: Wesley Boyd
HQ OPS Officer: Ian Howard
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: Wesley Boyd
HQ OPS Officer: Ian Howard
Notification Date: 05/03/2024
Notification Time: 16:18 [ET]
Event Date: 05/03/2024
Event Time: 07:50 [EDT]
Last Update Date: 05/03/2024
Notification Time: 16:18 [ET]
Event Date: 05/03/2024
Event Time: 07:50 [EDT]
Last Update Date: 05/03/2024
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 |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 96 | Power Operation | 96 | Power Operation |
CONTROLLED SUBSTANCE FOUND IN PROTECTED AREA
The following information was provided by the licensee via email and phone call:
"At approximately 0750 EDT on 05/03/24, an employee discovered an unopened can of an alcoholic beverage inside a refrigerator located in a common break area inside the protected area. The container label indicates the beverage is 5.3 percent alcohol by volume. The employee immediately reported the discovery to their supervisor and site security. Security took possession of the container and is continuing the investigation.
"The Resident Inspector has been notified."
The following information was provided by the licensee via email and phone call:
"At approximately 0750 EDT on 05/03/24, an employee discovered an unopened can of an alcoholic beverage inside a refrigerator located in a common break area inside the protected area. The container label indicates the beverage is 5.3 percent alcohol by volume. The employee immediately reported the discovery to their supervisor and site security. Security took possession of the container and is continuing the investigation.
"The Resident Inspector has been notified."