Event Notification Report for May 08, 2025

AGREEMENT STATE REPORT - RADIATION EXPOSURE

The following information was provided by the Texas Department of State Health Services (the Department) via email:

"On May 1, 2025, a crew made up of a radiographer trainee and a trainer were working on a job site near Orla, Texas. They were using a 58 Ci Ir-192 source [probably with] a Source Production and Equipment Company (SPEC) 150 device. The radiation safety officer (RSO) stated they had completed a shot and the trainer went to look at the digital picture of the weld. The trainee went to the pipe to setup the next shot. The trainee removed the source collimator and set it down. The trainee began to remove the imaging device when the trainer walked up, and the trainer's alarming rate meter went off. The two radiographers left the area, went back to the crank out handle, and found the source was still cranked out and in the collimator. The radiographers retracted the source to the fully shielded position. The trainee's self-reading dosimeter was off scale. The radiographers contacted the RSO and informed them of the event.

"The local RSO had the radiographers reenact the event. It was determined that the trainee was near the exposed source for about three minutes. The trainee reported the collimator was strapped to a stand. The trainee did not touch the collimator when he was moving the source. The majority of the dose would have been to the trainee's knee because of the way the trainee carried the stand with the source. They believe the trainee would have been at least 18 inches from the source during the event. They also believe the trainee was exposed to the source for three minutes. The calculated dose to the knee ranges between 500 millirem and 7.8 rem, depending on what direction the collimator port was facing.

"The trainee's alarming rate meter was tested after the event and functioned properly. The trainee's dosimeter is being sent in for processing, but the results will probably not be received until May 5, 2025.

"[The Department] requested pictures of the hands of the individual involved in the event to be taken and submitted daily for the next week. The RSO agreed to submit a written report on Monday May 5, 2025."

Texas incident report number: 10195
Texas NMED number: TX250026

EN Revision Imported Date: 5/12/2025

EN Revision Text: SPECIFIED SYSTEM ACTUATION - AUTOMATIC START OF EMERGENCY DIESEL GENERATOR

The following is a summary of information that was provided by the licensee via phone and fax:

At 2108 EDT, on May 6, 2025, with Unit 3 in mode 5 at zero percent power, the plant received main steam line isolation, containment isolation phase 'A', and a safety injection signal which caused the emergency diesel generator to automatically start. The initiation signals were cause by inadvertent clearing of the pressurizer pressure low interlock during maintenance. There was no impact to decay heat removal, no injection into the core, and no loading of the emergency diesel generator. Operations staff responded and returned the plant to normal mode 5 operations.

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

DEGRADED CONDITION

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

"On May 6, 2025, with Callaway Plant in mode 3 ascending from refueling outage 27, plant personnel identified a dry white residue resembling boric acid at the interface between the reactor vessel and bottom-mounted instrument nozzle No.48. At 2220 CDT, the shift manager determined that a reactor coolant pressure boundary leak had been identified. The determination was based on the residue appearing to be in the annulus of the nozzle where it penetrates the bottom head and the residue did not previously exist during earlier inspections of the area during refueling outage 27.

"Detailed examination of the apparent leak has not yet been performed due to radiological conditions, but the condition is being treated as a reactor coolant pressure leak. As such, the condition is being reported pursuant to 10 CFR 50.72 (b)(3)(ii)(A) as an eight-hour, non-emergency notification.

"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 apparent leak placed the plant in LCO 3.4.13.B. The plant is evaluating the leak repair corrective actions and preparing for cooldown.