Event Notification Report for July 17, 2025

EN Revision Imported Date: 7/17/2025

EN Revision Text: AGREEMENT STATE - LOST STATIC ELIMINATOR

The following is a summary of information provided by the Colorado Department of Public Health and Environment (the Department) via email:

The Department reported that on August 7, 2024, the licensee notified them of a lost NRD model P-2021 static eliminator containing 0.7 mCi of polonium 210. The licensee continues to search for the device.

Colorado event ID: CO240020


* * * UPDATE ON 07/16/2025 AT 1816 EDT FROM KATHRYN KIRK TO JOSUE RAMIREZ * * *

The following update was submitted by the Colorado Department of Public Health and Environment (the Department) via email:

"The Department was notified today of a static elimination device (serial number: A2MU000) previously reported as missing in August of 2024, was found on 05/21/2025. The device was leak tested and will be sent back to the manufacturer. NMED Number: CO240020"

Notified R4DO (Drake), NMSS Events Notifications (email), ILTAB (email).

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

EN Revision Imported Date: 7/17/2025

EN Revision Text: AGREEMENT STATE REPORT - STUCK OPEN GAUGE

The following information was provided by the South Carolina Department of Environmental Services (the Department) via phone and email:

"The licensee informed the Department via telephone on June 5, 2025, that a fixed gauging device was disabled or failed to function as designed. The licensee reported that a sealed source was stuck (exposed) in a dip tube assembly that was attached to a process vessel. The licensee reported that a representative from a licensed service provider was on-site and was able to remove the sealed source from the dip tube assembly and place the sealed source into a transport shield.

"The sealed source is a 9 millicurie cobalt-60 Berthold Technologies USA, LLC Model P2608-100.

"The licensee did not report any overexposures or ongoing health/safety concerns.

"This event is still under investigation by the Department."

* * * UPDATE ON 7/1/2025 AT 1357 EDT FROM JACOB PRICE TO TENISHA MEADOWS * * *

The following information was provided by the South Carolina Department of Environmental Services via email:

"The on-call duty officer was dispatched to the facility to investigate the event on June 6, 2025. All observations and information from the interviews were consistent with the details obtained from the initial report."

South Carolina Event Report ID Number: SC250006

Notified R1DO (Carfang) and NMSS Events Notification (email)

MEDICAL EVENT

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

A planned treatment administering three Y-90 microsphere doses resulted in underdoses of greater than 20 percent for all three doses. The start of the treatment was delayed as the treatment room was not available at the scheduled time. Doses were dispensed assuming a treatment time of 0930 CDT, but actual treatments were delayed until 1118, 1156, and 1244 CDT, respectively. The licensee is also investigating a potential complication in establishing intravenous access to the treatment site (liver).

Actual doses planned and administered were as follows:

First treatment at 1118 CDT: planned 18.9 mCi, actual 14.1 mCi
Second treatment at 1156 CDT: planned 13.8 mCi, actual 10.1 mCi
Third treatment at 1244 CDT: planned 17.2 mCi, actual 12.0 mCi

Initial review by the authorized user has concluded the treatments administered were adequate and no further treatment is planned.

The attending physician and patient are being notified.

An NRC Region III inspector was on-site and has been notified.

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

AGREEMENT STATE REPORT - STUCK OPEN GAUGE SHUTTER

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

"On July 10, 2025, the Department was notified by the licensee that the shutter on a Vega model SH-F1 gauge containing a 1,000 millicurie (original activity) Cs-137 source had failed in the open position during testing. Open is the normal operating position. The licensee reported there is no risk of additional radiation exposure to members of the general public or radiation workers due to this shutter failure. Additional information will be provided as it is received in accordance with SA-300."

Texas incident number: 10209

AUTOMATIC REACTOR TRIP

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

"At 0959 CDT on 7/16/2025, with Unit 1 in mode 1 at 100 percent power, the reactor tripped coincident with operation of a bus 11 knife switch during performance of [surveillance procedure] SP 1857, 4KV bus 11/12 undervoltage and underfrequency relay test. The trip was not complicated with all systems responding normally post trip.

"Operators responded and stabilized the plant. Decay heat is being removed by discharging steam using the steam dump system and the main feedwater system. Unit 2 is not affected.

"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). The expected actuation of the auxiliary feed water system (an engineered safety feature) is being reported as an eight-hour report under 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."