Event Notification Report for April 15, 2024

EN Revision Imported Date: 4/15/2024

EN Revision Text: PART 21 - LEAKING CYLINDER LINER IN EMERGENCY DIESEL GENERATOR

The following is a summary of the information provided by Engine Systems Inc. (ESI) via facsimile:

An EMD (Brand Name: Electro-Motive Diesel) cylinder liner developed a jacket water leak following installation on an emergency diesel generator set at the James A. Fitzpatrick Nuclear Power Plant. The leak occurred at a brazed joint and was detected after post-installation engine testing. Had the leak gone undetected, jacket water may have accumulated in the combustion chamber, airbox, and/or lubricating oil which could have eventually led to failure of the emergency diesel generator set.

ESI was the supplier of the EMD cylinder liner (part number: 9318833, serial number: 20D6294). The EMD cylinder was a component of a Blade Power Pack Assembly, part number: 40124898, serial number: 20L0603

Corrective Actions:
ESI will revise the dedication package to include additional verifications to prevent reoccurrence. The revision will be implemented within 30 days. Fitzpatrick returned the power assembly to ESI for replacement and no further action is required from Fitzpatrick.

Affected Plants:
Fitzpatrick. No other sites known to be affected.

The name and address of the individuals reporting this information is:

John Kriesel
Engineering Manager
Engine Systems, Inc.;
175 Freight Rd.
Rocky Mount, NC 27804

Dan Roberts
Quality Manager
Engine Systems, Inc.;
175 Freight Rd.
Rocky Mount, NC 27804

EN Revision Imported Date: 4/15/2024

EN Revision Text: AUTOMATIC REACTOR TRIP

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

"At 0035 EDT on April 13, 2024, with Unit 1 at 97 percent power, the reactor automatically tripped due to 1 of 3 reactor coolant pump (RCP) low flow reactor trip [signal] associated with a loss of the 'A' and 'B' 4160 volt normal buses. Auxiliary feedwater and the 1-1 emergency diesel generator (EDG) automatically started on valid actuation signals. The 1-1 EDG sequenced on to supply all required loads per plant design. All control rods fully inserted and the trip was not complex with all systems responding normally post-trip. Operators have responded and stabilized the unit in Mode 3 [Hot Standby]. Decay heat is being removed by discharging steam to the main condenser via the condenser steam dump system with steam generators being supplied by the main feedwater system.

"Unit 2 is not affected by the event.

"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).

"Due to the valid actuations of auxiliary feedwater and the 1-1 EDG, this event is reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A).

"There was no impact to the health and safety of the public or plant personnel. The NRC senior resident inspector has been notified."


The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Power for the A-E Bus is on the 1-1 EDG. The D-F Bus is on offsite power. One electrical train of offsite power is down.