Event Notification Report for September 08, 2025

AGREEMENT STATE REPORT - LEAKING SOURCE

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

"NYSDOH BERP received a phone call from the U.S. Nuclear Regulatory Commission (U.S. NRC) on August 29, 2025, at approximately 1045 EDT to report a call they received from Gentech Scientific, LLC, a NYSDOH radioactive material licensee, to report a leaking electron capture device (ECD) source. NYSDOH contacted Gentech Scientific, LLC on August 29, 2025, at approximately 1100 to follow up on this event. The representative from Gentech Scientific confirmed that a leak test was performed and analyzed by the National Leak Test Center (NYSDOH radioactive material license number C2323) the day prior (August 28, 2025) on entrance port, housing, and exit ports of an Agilent 58-90 ECD (serial number K3818) containing 15 millicuries of Ni-63 (foil source).

"Only the entrance port sample returned a result considered leaking in accordance with 10 CFR 31.5(c)(5) at 6789 pCi. The housing and exit port samples did not exceed this threshold.

"Following Gentech Scientific, LLC's awareness of this event, the affected device/source was carefully placed into isolation/quarantine in laboratory storage area, posted with signage, and licensee staff were informed on this event and instructed to keep away from this device. This leaking source did not result in the contamination of equipment, personnel, or surfaces.

"Gentech Scientific, LLC has notified Agilent of this leaking source and will be seeking options to return this device to Agilent or otherwise dispose of the source via transfer to a licensed waste broker. Leak test copies have been provided to NYSDOH.

"NYSDOH BERP is actively monitoring this event under Incident No. 1542. Additional information will be provided to NMED once available."

AGREEMENT STATE REPORT - MEDICAL EVENT

The following information was provided by the New Mexico Environment Department Radiation Control Bureau via email:

"One of our licensees Kaseman Presbyterian Hospital reported a medical event of a patient being administered 5 mCi of Ga-68 dotatate rather than Ga-68 PSMA [prostate-specific membrane antigen] on 8/28/2025, in Albuquerque New Mexico, license number MI-114-4. Written report is expected in 15 days. Further details will be provided as they become available."

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 - STOLEN DENSITY GAUGE

The following information was provided by the licensee via email:

"On the morning of 8/31/2025, an employee of Terracon Consultants discovered that a portable nuclear gauge (Troxler model 3440) was stolen from their vehicle overnight. The gauge was stored in the bed of a pickup truck that had a canopy cover. The gauge was also chained to the bed of the truck. The vehicle was parked inside of a parking garage with camera surveillance. Unfortunately, the cameras were [decoys] and were not operating.

"An individual gained access to the gauge by breaking through a canopy window and using a bolt cutter to cut the chain securing the Troxler gauge. The density gauge was the only nuclear material stolen. A toolbox was also taken which contained various non-nuclear equipment.

"The employee contacted Seattle Police, who at 1401 [PDT], had not arrived on scene to generate a report. The licensee will ensure that a report is generated and work with local law enforcement to recover the gauge. A full report will follow within 30 days."

Device Information:
Manufacturer: Troxler
Model: CDCW556
Serial Number: 14086

Source Information:
Manufacturer: AEA Technology/QSA
Model: CDCW556 (Cs-137) and AMNV.997 (Am-241:Be)
Isotopes and Activity: 9 mCi of Cs-137, 44 mCi of Am-241:Be, 0.066 mCi of Cf-252

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

UNANALYZED CONDITION

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

"On September 4, 2025, at 1110 EDT, it was determined that the units are in an unanalyzed condition. A review of DC control circuit protection schemes identified circuits which are uncoordinated due to inadequate fuse sizing. This results in a concern that postulated fire damage in one area could cause a short circuit without adequate protection, leading to the unavailability of equipment credited for 10 CFR 50 Appendix R safe shutdown. This condition is not bounded by existing design and licensing documents; however, it poses no impact to the health and safety of the public or plant personnel. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B).

"Compensatory actions for affected fire areas have been implemented.

"The NRC Senior Resident Inspector has been notified."

SECONDARY CONTAINMENT HATCH LEFT UNSECURED

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

"On September 4, 2025, at 0855 CDT, Grand Gulf Nuclear Station operators discovered the enclosure building roof hatch was unsecured and open approximately 1 inch. This resulted in inoperability of secondary containment.
Following discovery, the hatch was immediately closed and latched. Secondary containment operability was restored at 0940 CDT.

"This event is being reported under 10 CFR 50.72(b)(3)(v)(D) as an event or condition that could have prevented fulfillment of a safety function.

"The NRC Resident Inspector has been notified."

HIGH PRESSURE COOLANT INJECTION INOPERABLE

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

"At 0130 CDT on September 5, 2025, it was discovered that the single train high pressure coolant injection (HPCI) system was inoperable. Due to this inoperability, the system was in a condition that could have prevented the fulfilment of a safety function. Therefore, this condition is being reported as an 8-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D).

"Unit 1 reactor core isolation cooling was operable during this time period. There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified. The Illinois Emergency Management Agency has been notified."

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

The inoperability was caused by a malfunctioning turbine steam admission valve during a surveillance. Unit 1 is in a 14-day limiting condition for operations.

DEGRADED CONDITION

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

"At 0909 EDT on September 5, 2025, with the unit shut down for a scheduled refueling outage it was determined the reactor coolant system barrier had a through wall flaw with leakage. The leakage is minor in nature and unquantifiable. The leakage is coming from a welded connection upstream of a 1-inch vent valve on the chemical and volume control system letdown line. The leak was isolated in accordance with plant technical specifications.

"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."