Event Notification Report for June 18, 2024

EN Revision Imported Date: 8/16/2024

EN Revision Text: INOPERABILITY OF DIVISION 3 DIESEL GENERATOR SUPPORTING HIGH PRESSURE CORE SPRAY

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

"At 1640 EDT on 06/18/2024, the division 3 diesel generator was declared inoperable. This condition could prevent the 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)(D). All other emergency core cooling systems were operable during this time.

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

"The division 3 diesel generator was declared inoperable due to potential water intrusion into the electrical generator. Inspection of the generator is in progress."


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

This event resulted in Perry Unit 1 entering a 72 hour limiting condition for operation (LCO) in accordance with Technical Specification 3.8.1. condition 'B'.

* * * RETRACTION ON 8/15/2024 AT 0943 EDT FROM TONY MCGOWAN TO ERNEST WEST * * *

"Investigation and assessment of the division 3 diesel generator exciter and generator as-found condition revealed that no water intrusion occurred and, therefore, would not have impacted the diesel generator's ability to start, run, and produce the required electrical power to perform its required safety function. Therefore, EN 57181 is being retracted.

"The NRC resident inspector has been notified of the Event Notification retraction."

Notified R3DO (Feliz-Adorno)

EN Revision Imported Date: 6/25/2024

EN Revision Text: MANUAL REACTOR TRIP

The following information was provided by the licensee by email:

"On 06/18/2024 at 0317 EDT with Unit 2 at 18 percent power, the reactor was manually tripped due to elevated secondary chemistry levels (sodium and chlorides).

"The trip was uncomplicated with all systems responding normally post trip. Operations stabilized the plant in Mode 3. Decay heat is being removed by auxiliary feedwater and atmospheric dump valves.

"St. Lucie Unit 1 was unaffected and remains at 100 percent power.

"This event is being reported pursuant 10CFR 50.72(b)(2)(iv)(B).

"The NRC Resident Inspector has been notified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
All rods fully inserted. An investigation is underway to determine the root cause of the elevated chemistry levels.

* * * RETRACTION ON 6/24/2024 AT 1315 FROM BOB MURRELL TO ADAM KOZIOL * * *

The following retraction was provided by the licensee via email:

"The purpose of this notification is to retract a previous report made on 06/18/2024 at 0652 (EDT) (EN# 57177). Notification of the event to the NRC was initially made because of inserting a manual reactor trip due to elevated secondary chemistry levels (sodium and chlorides).

"After the initial report, Florida Power and Light has concluded that the event did not meet the reporting requirements on 10 CFR 50.72(b)(2)(iv)(B) since it was part of a normal plant shutdown.

"Therefore, this event is not considered an unplanned scram and is not reportable to the NRC as a Licensee Event Report per 10 CFR 50.73.

"The NRC Senior Resident Inspector has been notified."

AGREEMENT STATE REPORT- STUCK SHUTTER

The following information was provided by the Nevada Division of Radiation Health via email and phone:

"On June 18, 2024, Nevada Goldmines - Elko, discovered a failed shutter while conducting required 6-month shutter checks on a Berthold LB 7440 fixed gauge in the open position. In place radiation surveys were conducted to verify safety until a contractor would be available to remove the gauge and move it to storage. All readings were normal. The licensee coordinated with Radiation Technology Inc., (RTI) to remove the gauge and move it to the authorized storage area pending decision to repair or dispose of the gauge.

"RTI conducted onsite leak checks and results were less than 0.005 microcuries. A second set of leak check samples were taken to be returned to RTI lab for verification. A radiation survey following deinstallation confirmed them to be background.

"The gauge was removed from service, plates placed over the open window to provide shielding, and the device with plates covering the window was placed in storage. Surveys of the storage area show increase in radiation consistent with adding a new gauge to the job box, with the highest radiation level being 79 microR/hour at 12 inches."

Gauge Information:
Model: Berthold LB 7440
Serial number: 3015
Activity: Cs-137 (150 Ci)

Nevada Item Number: NV240004