Event Notification Report for May 23, 2024

AUTOMATIC SCRAM DUE TO TURBINE TRIP SIGNAL

The following information was provided by the licensee via email:

"At 2223 CDT on May 23, 2024, with Quad Cities Unit 2 at 38 percent power, the reactor automatically tripped due to a turbine trip signal resulting in main stop valve closure, creating a valid reactor protection system signal. Reactor vessel level reached the low-level set-point following the scram, resulting in valid Group II and Group III containment actuation signals. The trip was not complex with all systems responding as expected 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 the Group II and Group III isolation.

"Operations responded using their emergency operating procedures and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves.

"Unit 1 remains at 100 percent power.

"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:

Unit 2 was at a reduced power for maintenance.

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN

The following information was provided by the licensee via email:

"At 0400 EDT on May 23, 2024, a technical specification required shutdown was initiated at Perry. Technical specification action 3.4.5 condition B [unidentified reactor coolant system leakage exceeds 5 gallons per minute] was entered on May 23, 2024 at 0000 with a required action to reduce leakage to within limits within 4 hours, due by 0400 on May 23, 2024. This required action was not completed within the completion time, therefore, a technical specification required shutdown was initiated, and this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i).

"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 reactor coolant leakage was stable at approximately 6 gallons per minute.

FITNESS FOR DUTY PROGRAMMATIC FAILURE

The following information was provided by the licensee via email:

"During a security inspection, it was determined that some past events at Entergy sites that were not reported may have met the reporting criterion of 10 CFR 26.719(b)(4). As a result, the following events at Arkansas Nuclear One, Units 1 and 2 are now being conservatively reported: On February 2, 2023, a condition report was written to document that an individual who should have been placed in a follow-up fitness for duty (FFD) program was not tested according to this program. On September 6, 2023, a subsequent condition report was written to document that a different individual who should have been placed in a follow-up FFD program was not tested according to this program. The resident inspector has been notified."

FITNESS FOR DUTY PROGRAMMATIC FAILURE

The following information was provided by the licensee via email:

"During a security inspection, it was determined that some past events at Entergy sites that were not reported may have met the reporting criterion of 10 CFR 26.719(b)(4). As a result, the following event at Grand Gulf, Unit 1 is now being conservatively reported: On May 11, 2023, a condition report was written to document that an individual who should have been placed in a follow-up fitness for duty program was not tested according to this program. The resident inspector has been notified."

FITNESS FOR DUTY PROGRAMMATIC FAILURE

The following information was provided by the licensee via email:

"During a security inspection, it was determined that some past events at Entergy sites that were not reported may have met the reporting criterion of 10 CFR 26.719(b)(4). As a result, the following events at River Bend Station, Unit 1 are now being conservatively reported: On March 21, 2023, a condition report was written to document that an individual who should have been placed in a follow-up fitness for duty (FFD) program was not tested according to this program. On May 11, 2023, a subsequent condition report was written to document that a different individual who should have been placed in a follow-up FFD program was not tested according to this program. The resident inspector has been notified."

FITNESS FOR DUTY PROGRAMMATIC FAILURE

The following information was provided by the licensee via email:

"During a security inspection, it was determined that some past events at Entergy sites that were not reported may have met the reporting criterion of 10 CFR 26.719(b)(4). As a result, the following event at Waterford Steam Electric Station, Unit 3 is now being conservatively reported: On May 15, 2023, a condition report was written to document that an individual who should have been placed in a follow-up fitness for duty program was not tested according to this program. The individual was no longer badged at Waterford 3 but is currently badged at another Entergy site. The resident inspector has been notified."