Event Notification Report for February 16, 2024

AGREEMENT STATE - STUCK OPEN SHUTTER

The following was received from the Texas Department of State Health Services (the Department) via email:

"On February 8, 2024, the Department was notified by the licensee that, while testing the shutter of a Vega SH-F2B nuclear gauge containing a 200 millicurie (original activity) cesium-137 source, the shutter failed to close. Open is the normal position of the shutter. The license stated there is no risk of exposure to members of the general public or their workers. The licensee may have the repair parts for the shutter already in hand. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident Number: 10087
Texas NMED Number: TX240004

AGREEMENT STATE REPORT - STUCK OPEN SHUTTER

The following was received from the Colorado Department of Public Health and Environment via email:

"While conducting a six-month inspection of an Ohmart/Vega model SH-F2-45 fixed gauge, the shutter would not close. The fixed gauge contains a 375 mCi Cs-137 sealed source and is stuck in the open position. The licensee is following their emergency procedures, and the gauge is in a location that is not accessible by members of the public. The licensee has contacted the manufacturer to repair the gauge."

Colorado Event Report ID No: CO 240002

AGREEMENT STATE REPORT - LOST SOURCE

The following information was received from the Georgia Radioactive Material Program via email:

"On or about 9/21/23, a Filtec model FT-50C, containing 100 mCi of Am-241, was mistakenly placed into a scrap dumpster on-site by an employee of Shasta Beverages, Inc. The gauge was taken off-site in the scrap dumpster by a scrap collection company. The scrap company is unsure of which of two locations the dumpster was taken, a recycling facility or a scrap yard. This report serves as initial notification and will be followed up with additional information."

Georgia Incident Number: 78

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

OFFSITE NOTIFICATION
The following information was provided by the licensee email:

"At 1227 CST on February 14, 2024, OSHA was notified per 29 CFR 1904.39(a)(2) that an individual was transported to an offsite medical facility for treatment that required the individual to be admitted to the hospital. The individual was not working in a radiologically control area when the injury occurred.

"This event is being reported pursuant to 10 CFR 50.72(b)(2)(xi).

"The NRC Regional Inspector has been notified of this event."

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

The injured individual was working in an office environment prior to needing medical treatment.

AUTOMATIC TURBINE TRIP/REACTOR TRIP

The following information was provided by the licensee via email:

"At 0247 CST on 2/15/2024, Callaway Plant was in mode 1 at approximately 100 percent power when a turbine trip and reactor trip occurred. All safety systems responded as expected with the exception of an indication issue on the feedwater isolation valves, which were confirmed closed. A valid feedwater isolation signal and auxiliary feedwater actuation signal were also received as a result of the reactor trip. The plant is being maintained stable in mode 3.

"All control rods fully inserted from the reactor trip signal and decay heat is being removed via the auxiliary feedwater system and steam dumps.

"The NRC Resident Inspector was notified."