Event Notification Report for May 06, 2024

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.

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."

OFFSITE NOTIFICATION

The following information was provided by the licensee via phone and email:

"At 1630 EDT on 5/3/2024, the supervisor of nuclear site safety contacted the Area Director of OSHA to notify them of a worker's foot injury requiring removal of a toe to the first joint.

"This was a 24 hr notification in accordance with 29 CFR 1904.39.

"The NRC Residents have been notified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

The individual was not contaminated or working in a radiological area at the time of injury.

AUTOMATIC REACTOR TRIP DUE TO LOWERING STEAM GENERATOR WATER LEVEL

The following information was provided by the licensee via email and phone:

"At 0338 CDT, with the unit 1 in mode 1 at 6 percent power, the reactor automatically tripped due to lowering steam generator water level. The trip was uncomplicated with all systems responding normally post-trip. 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) and an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for an actuation of the auxiliary feedwater system.

"Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to the reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected.

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."