Event Notification Report for December 27, 2022

AGREEMENT STATE REPORT - UNABLE TO RETRACT SOURCE

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

"On December 16, 2022, the Department received calls from a licensee reporting an equipment failure with a moisture density gauge. The licensee has been unable to retract the rod with cesium-137 back to the fully shielded position and the source is sticking out about 4 inches. This is for a Humboldt 5001 gauge with 40 millicuries (mCi) of americium [-241] and 10 mCi of cesium-137. The rod is presently in the ground to maintain shielding and will be transported back to the storage site with the rod in a bucket of sand. The licensee plans to transport the gauge the same way to a repair facility tomorrow morning. The dose to personnel has not been above normal working conditions but there may be some dose during transportation. The licensee was reminded to minimize dose as much as possible. Further information will be provided per SA-300."

Texas Incident Number: 9974

AGREEMENT STATE REPORT - MISSING SOURCE

The following is a summary information was provided by the North Carolina Division of Radiation Protection via email:

On 12/13/2022, the licensee discovered that a source from a shipment of sources received on 9/1/2022, was missing from their inventory. The licensee conducted surveys of the area and did not detect the source. None of the shipping containers or bags were damaged, indicating that the source was not lost during shipping and was either not included in the original shipment from the shipper or was lost after the licensee received the shipment. The original shipper of the source was contacted and informed of the missing source; they are performing checks to verify if the source was indeed shipped to the licensee.

Source: Am-241/Be
Activity: 40 mCi
Manufacturer: Eckert & Ziegler
Model: K Model, Batch
S/N: K364-22

NC Event Number: NC220016

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

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN

The following information was provided by the licensee via email:

"At 1513 EST on 12/23/22, a Technical Specification required shutdown was initiated at the Davis-Besse Nuclear Power Station Unit 1. Technical Specification [TS] Action Limiting Condition of Operation [LCO] 3.7.9 for Ultimate Heat Sink water level minimum requirements was not met and condition 'A' was entered on 12/23/22 at 1412 EST with a required action to `Be in Mode 3' with a completion time of 6 hours and `Be Mode 5' with a completion time of 36 hours. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.

"At 1640 on 12/23/22, the NRC granted enforcement discretion for the shutdown requirements of TS LCO 3.7.9 and the shutdown was terminated with the unit remaining in Mode 1."

AUTOMATIC REACTOR TRIP

The following information was provided by the licensee via email:

"At 0222 [EST] on 12/24/22, with Unit 2 at 100 percent power during steady state operation, the reactor automatically tripped and a safety injection actuated due to steam generator differential pressure. The trip and safety injection were not complex, with all systems responding normally post-trip. An actuation of the auxiliary feedwater system occurred following the reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. The turbine bypass steam dumps and auxiliary feedwater system are removing decay heat. Salem Unit 1 was not affected.

"Due to the actuation of the reactor protection system while critical, this event is being reported as a four hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the auxiliary feedwater system.

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

"The NRC Resident Inspector has been notified."