Event Notification Report for January 23, 2026

AGREEMENT STATE REPORT - DAMAGED GAUGE

The following information was provided by the New York State Department of Health (NYSDOH) Bureau of Environmental Radiation Protection via email:

"On January 6, 2026, NYSDOH Bureau of Environmental Radiation Protection received a phone notification to report the inability to [affix] the shielding cap as designed on an NDC 103X gauging device containing approximately 150 millicuries of americium-241. According to the licensee, the screws to secure the shielding cover when not in use had broken off due to routine capping and uncapping of the manual shutter. A survey was performed which indicated that the source and source shell were not compromised. The radiation safety officer fabricated a temporary lead cap to cover the source, performed a shielding survey to confirm that dose rates did not exceed background levels, closed off the area to unauthorized personnel, and contacted the manufacturer for repair. NYSDOH required that the device be taken out of service until repaired by the manufacturer.

"In assessing this event, no individual exposures are believed to have occurred, and the source itself does not appear to be compromised. The licensee was able to determine that the cause of [the broken screws] was from the continued use of the manual shutter and natural wear and tear of the device.

"On January 13, 2026, a qualified and licensed third-party entity was able to repair the broken screws on the shielding cap and confirm that such repairs and conditions for the gauge were in accordance with the manufacturer's specifications and the sealed source and device registry. The gauge was recommissioned for use on January 14, 2026.

"In accordance with 10 CFR 31.5(c)(5), the licensee will be submitting a written report within thirty (30) days of notification. Additional information will be provided to NMED once available.

"NYSDOH is monitoring this incident under incident 1552."

AGREEMENT STATE REPORT - DAMAGED GAUGE

The following is a summary of information provided by the California Radiation Control Program via email:

On January 14, 2026, at approximately 1430 PST, the radiation safety officer (RSO) for the licensee contacted the California Radiologic Health Branch (RHB) Brea office concerning a Troxler moisture/density gauge that had been run over by construction equipment. The incident occurred at a temporary job site in Oceanside, CA, at approximately 1430 PST on January 13, 2026.

While the user was performing a soil density test with the source rod in the soil, the gauge was run over by a soil grader. The area around the gauge was cleared, the user raised the source rod into the shielded position and contacted the RSO. The gauge was surveyed by the RSO to confirm that the source rod was still attached and raised into the lead shielding. Due to the extent of damage to the gauge index rod, the locking mechanism on the source rod was not functional. The gauge was secured as much as possible then placed into the gauge transport package and returned to the licensee's office. The RSO will collect a leak test swab and send it to Troxler for analysis. Once the gauge is shown not to be leaking, it will be transported to Troxler for damage assessment and disposition.

A copy of the licensee's incident report will be forwarded to the RHB Brea office and will be included in this investigation.

Model: Troxler 3440
Source: 0.333 GBq Cs-137 and 1.6 GBq Am-241/Be
S/N: 15053

CA 5010 number: 011426

AGREEMENT STATE REPORT - DOSE TO AN EMBRYO

The following is a summary of information provided by the Iowa Department of Health and Human Services (the Department) via phone and email:

On January 7, 2026, a 150.4 mCi I-131 treatment was administered to a female who had tested negative on a serum pregnancy test two days before, on January 5, 2026. On January 9, 2026, a follow-up serum pregnancy test came back negative. The patient took a pregnancy test (urine) at home that day which came back positive. A second follow-up serum pregnancy test was administered on January 12, 2026, and returned a positive result.

The physician notified the licensee radiation safety officer on January 13, 2026, and the Department was notified on January 14, 2026.

Investigation into the event still ongoing. The hospital is working to calculate/determine what the dose to the embryo was. The Department will perform a reactive inspection/meeting on January 20, 2026.

Iowa event report ID number: IA260001

LOST RADIOACTIVE MATERIAL

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

At approximately 0900 EST, on January 16, 2026, it was discovered that a medical treatment, Lutathera, containing lutetium-177 with an activity of 202.2 millicuries (mCi), became missing during preparations to treat a patient. Upon investigation, the radioactive dose had been delivered on January 15, 2026, at 1029, and was checked in at 1045. At the time of check in, the dose rate at one meter was 0.05 millirem per hour. The radiation safety officer (RSO) hypothesized that the radioactive material had not been removed from its shipping container prior to being discarded. Based on surveillance video, the source left the medical facility at approximately 1620, on January 15, 2026, in regular trash. The facility's portal detectors did not detect the discarded radioactive material prior to the material leaving the facility. At the time the material became uncontrolled, the RSO estimates the source activity was 218.7 mCi. The RSO suspects the source left the facility in its original shipping container, shielded in its original shipping vial. The waste management company (WMC) was contacted. The source was suspected to have already passed through the WMC's transfer station. Currently, the RSO is waiting to receive information from the WMC regarding the lost radioactive material. The RSO stated that this event is being reported in accordance with 10 CFR 20.2201 paragraph (a)(1)(i) due to lost licensed material in an aggregate quantity equal to or greater than 1,000 times the quantity specified in 10 CFR 20, Appendix C. A follow up report will be made in 30 days.

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

PART 21 - DEFECTIVE LIMITORQUE ACTUATOR ASSEMBLIES

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

"On January 20, 2026, TVA Sequoyah Nuclear Plant completed a Part 21 evaluation concerning two Flowserve Limitorque actuator/motor assemblies. The assembly model numbers are 'SMB-2' and 'SB-1'. The evaluation of the 'SMB-2' assembly was for the motor pinion gear found installed backwards. The evaluation of the 'SB-1' assembly was for insufficient grease applied to the limit switch gearbox. The evaluation determined that a defect existed for these basic components. The conditions were corrected prior to installation in the containment spray system.

"The NRC Resident has been notified.

"A written notification will be provided within 30 days."

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

The only plant known to be affected at the time of the report is Sequoyah Unit 1.

RADIOGRAPHY SOURCE FAILED TO RETRACT

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

The source (70.9 Ci Ir-192) for a Delta 880 radiography camera, model number A424-9, could not be retracted normally. The licensee's radiation safety officer was called to the site and was able to retract the source. The camera failure is being investigated by the licensee to determine the cause of the failure. After the licensee's investigation, the camera will be sent to the manufacturer.

The maximum personal dose while retracting the source was 197 mrem.