Event Notification Report for February 11, 2025

AGREEMENT STATE REPORT - LOST THEN FOUND SOURCE

The following information was provided by the New Jersey Radiation Protection And Release Prevention Program (NJDEP) via email:

"On 1/23/2025, the Bureau of Environmental Radiation was notified that a load of municipal solid waste was rejected at a landfill in Dunmore, PA for triggering radiation alarms. The waste was originally hauled by JP Mascaro in Mt. Olive, NJ. A maximum exposure rate on contact with the truck of 4.7 mrem/hr was observed. A Department of Transportation special permit was issued to permit the load to return to JP Mascaro.

"On 1/31/2025, NJDEP was notified via email by JP Mascaro that the load had been sorted, and a package containing a shipment of 1.54 Ci of I-131 was identified. This was a shipment from a radiopharmacy in Quebec, Canada bound for Nuclear Diagnostic Products (NDP). According to tracking information provided by the common carrier, the package arrived successfully at the facility in Budd Lake, NJ, and was marked as out for delivery before it went missing.

"On 2/3/2025, NJDEP contacted NDP to alert them of the missing package. NDP agreed that one of their private couriers would retrieve the package from JP Mascaro."



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 - LOST AND RECOVERED GAUGE

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

"The Department received notification that an Instrotek 3500 Xplorer nuclear moisture/density gauge fell off the back of a truck in front of Lake Havasu High School. The technician returned to retrieve the gauge approximately 30-45 minutes later. The gauge contains 10 millicuries of Cs-137 and 40 millicuries of Am-241. The Department has requested additional information and continues to investigate the event.

"Additional information will be provided as it is received in accordance with SA-300."

Arizona Incident Number: 25-003

AGREEMENT STATE REPORT - UNQUALIFIED PERSONNEL

The following information was provided by the Arizona Department of Health Services (the Department) via phone and email:

"Seven (7) patients were injected with Tc-99m by a non-certified nuclear medicine technologist who knew he was not qualified to be injecting patients. The Department has requested additional information and continues to investigate the event."

Arizona Incident Number: 25-002

AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE

The following is a summary of information provided by the State of Florida, Bureau of Radiation Control (the BRC) via email:

On 2/4/2025, at 1334 EST, the BRC received notification of a damaged Troxler gauge. At around 1230, an employee accidently backed over the gauge. The gauge was not in use at the time of the incident. The backup radiation safety officer states the sources are contained and secured, only the housing was damaged. Prior to notifying the BRC, the licensee returned the gauge to its storage location.

Moisture Density Gauge Information
Manufacturer: Troxler
Model Number: 3430
Serial Number: 37867
Cs-137 Activity: 8 mCi
Am-241 Activity: 40 mCi

Florida Incident Number: FL25-012

NOTIFICATION OF UNUSUAL EVENT DUE TO SMOKE IN UNIT 3 TURBINE BUILDING

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

"On 2/8/2025, at 2248 CST, Browns Ferry Unit 3 experienced a main generator fault causing Unit 3 to experience an automatic reactor scram. Smoke was observed in multiple areas that required greater than 15 minutes to verify that no fire occurred. Browns Ferry declared a Notification of Unusual Event (NOUE), Emergency Action Level HU4, [at 2310] and completed the applicable notifications. The fault causing the main generator trip is still under investigation.

"A loss of power to the 3EA and 3EB 4KV shutdown boards resulted in a valid actuation of the 3A and 3B emergency diesel generators (EDGs) which successfully re-energized the boards as designed. During the scram response, there was a valid actuation of the primary containment isolation system (PCIS) groups 2, 3, 6, and 8. Upon receipt of these signals, all components actuated as required. Local offsite fire assistance was requested based on the initial indications but was not required. Operators responded and stabilized the plant. Units 1 and 2 were not affected.

"This event requires a 4 hour non-emergency report per 10 CFR 50.72(b)(2)(iv)(B), any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.

"This event requires a 4 hour non-emergency report per 10 CFR 50.72(b)(2)(xi), any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.

"This event requires an 8-hour non-emergency report per 10 CFR 50.72(b)(3)(iv)(A), any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B): 1) reactor protection system (RPS) including: reactor scram or reactor trip. 2) general containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs). 8) emergency AC electrical power systems, including: EDGs.

"All safety systems operated as expected. At no time was public health and safety at risk. The NRC Resident Inspector has been notified"

Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC, CWMD Watch Desk (email), DHS NRCC THD Desk (email), and DHS Nuclear SSA (email).

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

Browns Ferry Unit 3 intentions are to proceed to mode 4. Offsite power has been restored, and both the 3A and 3B EDGs have been secured. The NOUE was terminated on 2/9/2025, at 0110 CST.

MANUAL REACTOR TRIP DUE TO ELECTROHYDRAULIC CONTROL SYSTEM LEAK
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The following information was provided by the licensee via phone and email:

"At 1216 EST, on 2/10/2025 with Unit 1 in mode 1 at 66.5 percent power, the reactor was manually tripped due to an electro-hydraulic control power system leak. The trip was not complex with all systems responding normally post-trip.

"Operations responded and stabilized the plant. Decay heat is being removed by the emergency feedwater system.

"Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR50.72(b)(2)(iv)(B) and an eight-hour, non-emergency notification per 10CFR 50.72(b)(3)(iv)(A) resulting from a valid actuation of the reactor protection and emergency feedwater systems.

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."