Event Notification Report for June 29, 2023

AGREEMENT STATE REPORT - RADIOACTIVE MATERIAL RECOVERED AT A SCRAPYARD

The following information was received from the Illinois Emergency Management Agency (Agency) via email:

"Agency staff responded to a radiation monitor trip at a scrap metal recycling facility (SIMS Metal Management in Chicago) on 6/20/23 and identified an activated component from a high energy therapy device. The component is estimated to contain less than 1 microcurie of Co-60 and had an exposure rate of 100 microrem/hour on contact. The device originated from Varian Medical Systems and was decommissioned and transported by Legacy Transportation Services. Legacy is an Illinois radioactive materials licensee (IL-02445-01) that receives decommissioned Varian (and other low/high energy) devices and sorts the equipment for recoverable materials versus scrap. Radioactive components are to be identified and returned to Varian. This piece reportedly circumvented their radiation screening process. The licensee was contacted by the Agency and their staff promptly recovered the piece today (6/21/23). An assessment of contamination was performed and none identified. This incident did not result in members of the public receiving exposures in excess of (Illinois) Part 340 limits. Pending appropriate enforcement action and the licensee's written report; this matter is considered closed. Root cause and the adequacy of corrective action will be assessed in the licensee's response."

Illinois Item Number: IL230016

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 - STUCK SOURCE

The following information was provided by the South Carolina Department of Health and Environmental Control [the Department] via email:

"The South Carolina Department of Health and Environmental Control was notified via telephone at 1515 EDT on 06/22/23, that during the commissioning of a new device [at their Gaston S.C. facility] the strip source of the fixed gauging device was stuck between the source housing and dip-tube. The licensee is reporting that the fixed gauge is a Berthold Technologies USA, LLC., LB 300 IRL Type III Series gauging device, housing a Cs-137 Berthold Technologies USA, LLC., sealed source Model BT-MPLM. The licensee is reporting that no immediate health and safety concerns have been identified. The licensee is reporting that a consultant has been contacted to perform the repair. A department inspector will be dispatched to the facility to conduct an on-site investigation. This event is still under investigation by the Department."

EN Revision Imported Date: 6/29/2023

EN Revision Text: OFFSITE NOTIFICATION

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

"At 0831 [EDT] on June 27, 2023, Sequoyah Nuclear Plant reported an oil discharge into the plant intake located on the Tennessee River to the [Department of Transportation] National Response Center (report number 1371356). The source of oil was from a broken hydraulic hose from equipment in use on the intake. This oil spill is minor and did not exceed any NRC regulations or reporting criteria. This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi).

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."

EN Revision Imported Date: 6/29/2023

EN Revision Text: AUTOMATIC REACTOR TRIP

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

"At 1626 EDT, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a main turbine trip. The [reactor] trip was not complex with all systems responding normally post-trip.

"Operations responded and stabilized the plant. Decay heat is being removed using the auxiliary feedwater and steam dump systems. Unit 1 is not affected.

"Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). The expected actuation of the auxiliary feedwater system (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A).

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.

"All control rods are fully inserted. The cause of the turbine trip is being investigated."

AGREEMENT STATE REPORT - SOURCE RECOVERY MALFUNCTION

The following is a summary of the information provided by the Washington State Office of Radiation Protection via email:

On 6/22/23 at 1419 PDT, the licensee identified that a 56.4 Ci Ir-192 radiography source could not be retracted into the exposure device (QSA Model 880D) due to a crank malfunction. The radiographer immediately contacted the Radiation Safety Officer who provided source recovery/retrieval actions along with crank mechanism fixes. The radiographer secured the source in the exposure device at 1422 PDT. The problem with the retrieval was identified as a loose securing nut that caused the crank to spin freely and the drive cable to come out of the crank conduit.

During the incident, the radiographer's survey meter read 20 mr/hr at the crank location. A radiographer assistant expanded the boundaries and ensured the general public was not affected. The radiographer's total direct dosimeter reading after 6 normal radiography exposures and the source recovery actions were complete was 3 mRem. The incident took place at a temporary job site in Anacortes, WA. There were no overexposures or spread of contamination.

WA Incident Number: WA-23-010

TECHNICAL SPECIFICATIONS DEVIATION - DEGRADED FUEL PIN

The following information was provided by the Texas A&M University (TAMN) via phone and email:

"At approximately 1315 CDT on Wednesday, June 28, 2023, during routine fuel inspections required under Technical Specification (TS) 4.1.5 ['Reactor Fuel Elements'], a fuel pin (serial number 11394) did not pass the test criteria. The pin was bloated enough to not fit in the bend test rig. This meets the definition of a `Reportable Occurrence' under the definitions in TS 1.3. In accordance with the requirements of TS 6.6.2 and 6.7.2, TAMN notified the NRC Headquarters Operations Officer within one working day.

"Visual inspection of the pin did not indicate any obvious degradation that would be exceptional for a pin with sixteen years of burnup history, other than a slight bloat in the middle of the pin.

"There have been no indications of cladding failure on routine primary coolant analyses.

"As required by TS 4.1.5.2, TAMN is initiating an inspection of the entire core fuel inventory once TAMN finishes the regularly scheduled fuel inspections for the year. TAMN informed the NRC Project Manager."

FITNESS-FOR-DUTY REPORT

The following information was provided by the licensee via email:

"A non-licensed supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.

"The NRC Resident Inspector has been notified."