Event Notification Report for November 04, 2025

AGREEMENT STATE REPORT - WORKER POTENTIALLY EXCEEDED OCCUPATIONAL DOSE LIMIT

The following information was provided by the Louisiana Department of Environmental Quality (the Department) via email:

"On October 27, 2025, Acuren Inspection, Inc. notified the Department that an industrial radiography trainee dosimetry badge had been reported as an overexposure of 8 rem from Landauer. While talking with the radiation safety officer (RSO), the Department was informed that the radiographer trainee had only worked as a trainee in Louisiana for approximately seven weeks before being transferred to Orange, Texas. The RSO indicated that the trainee worked with at least three different crews at different job sites around their Kenner satellite office over the time period of mid-May to early July 2025."

Louisiana report ID number: LA20230011

AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE

The following is a summary of information provided by the Arkansas Department of Health (the Department) via email:

During a routine inspection on October 21, 2025, the Department was made aware that on two separate occasions, the production manager had performed repairs on the production line of F-18 fluorodeoxyglucose (FDG) without wearing dosimetry.

On Tuesday, October 28, 2025, inspectors from the Department were following up on the concerns and confirmed that on one occasion, the production manager was not wearing dosimetry during the replacement of tubing on a cracked line inside a production hot cell. This repair was conducted along a 25.4 cm (10 inches) tubing line with one end being 10 cm (3.9 inches) from the source vial of F-18. The activity of the source was 118.4 GBq (3.2 Ci) as per the radiation safety officer (RSO). Re-enactment of the procedure was produced with the production manager to reconstruct similar parameters. The RSO initially was not made aware of the individual not wearing dosimetry. Dose estimation is currently being conducted by the RSO and by the Department. The licensee will also have an independent contractor perform a dose calculation for the event that was conducted without dosimetry.

While dose estimations are being calculated, the Department believes it has enough information to determine that this event threatens to cause an extremity exposure greater than or equal to 250 rads, and thus, are reporting immediately to the NRC in accordance with SA-300. This investigation is ongoing and updates will be provided.

Arkansas Event Number: ARK-2025-014

AUTOMATIC REACTOR SCRAM

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

"At 1346 CST with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped on turbine control valve fast closure due to a generator lockout. The trip was not complex 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).

"Operations responded using 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 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."

EMERGENCY DIESEL GENERATOR (EDG) ACTUATION

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

"On November 3, 2025, at 1215 EST, the 'A' reserve station service transformer (RSST) pilot wire lockout actuated while restoring the 'A' RSST to service. This resulted in the electrical isolation of the 'A' RSST and the Unit 1 'J' emergency bus. The #3 EDG automatically started and loaded onto the Unit 1 'J' emergency bus, as designed. Operations entered the appropriate abnormal procedures and ensured stable conditions. All safety systems functioned as designed and all electrical parameters remained stable.

"No radiological consequences resulted from this event. This event is being reported pursuant to 10CFR50.72(b)(3)(iv)(A) due to actuation of the #3 EDG.

"The NRC Resident Inspector was notified."

AGREEMENT STATE REPORT - STOLEN GAUGE

The following information was provided by the California Department of Public Health, Radiologic Health Branch (the Department) via email:

"On October 29, 2025, a radiation safety officer (RSO) for Tetra Tech BAS, Inc. contacted the Department about a moisture density gauge that was stolen from a temporary storage unit. The gauge was a CPN Model MC-3, S/N M39068922 (10 mCi nominal of Cs-137 and 50 mCi nominal of Am:Be-241). The gauge was stored in a Conex box located at a construction site in San Juan Capistrano, California.

"The construction site is secured with fencing and a locked gate. The gauge was last used by Tetra Tech on October 28, 2025. The gauge case was locked with two padlocks, secured with a chain and two pad locks inside the locked Conex box. When the operator arrived at the site the following morning, the gate was open with the lock cut. The operator then discovered the lock on the Conex box was cut and the door open. An inspection of the inside of the Conex box found that the gauge box and miscellaneous equipment were taken from the Conex box. The operator then contacted the RSO and filed a report with the Orange County Sheriff's Department. The licensee is still investigating the incident. The Department will continue to investigate the incident."

CA incident number: 5010-102925

THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

AGREEMENT STATE REPORT - STUCK SOURCE

The following information was provided by the Utah Division of Radiation Control via email:

"An industrial radiography source failed to return to the shielded position. While setting up for a shot, the radiographers repositioned the drive cable to improve their view. The cable was inadvertently placed on a hot pipe, melting approximately 5 feet of the 35-foot drive cable near the connection point. As a result, the source could not be retracted into the shielded position. The radiographer notified the radiation safety officer. A source retrieval team was dispatched to the site. The team removed the drive handle and manually pulled the source back into the camera, securing it in the fully shielded position. One licensee personnel, trained in source retrieval, received the most dose during the incident at 28 mR during the retrieval operation according to his Mirion Instandose dosimeter and corroborated by his worn personal electronic dosimeter."

Device: 880 Delta
Activity: 49.4 Ci of Ir-192

Utah Report Number: UT250003