Event Notification Report for March 15, 2021

NON-AGREEMENT STATE REPORT - EXTERNALLY CONTAMINATED PACKAGE

The following was received from the Veterans Health Administration (VHA) via E-mail:

"Per 10 CFR 20.1906(d), VHA National Health Physics Program is reporting receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits. The package was received Friday, March 5, 2021, at 1032 CST at the Robert J. Dole VA Medical Center in Wichita, Kansas. This facility operates as a satellite location of the VA St. Louis Health Care System which holds permit number 24-00144-05 under the VHA master materials license.

"The package was checked-in and surveyed upon receipt around 1032 CST. Three wipe tests performed on the external surface of the package indicated a removable contamination level that exceeded the regulatory limit of 240 dpm/cm2 for beta-gamma emitters (reported as 13,000 - 45,000 dpm/300 cm2 not corrected for wipe efficiency).

"The package contained two unit doses of F-18. Analysis of the wipe test confirmed a 511 keV peak associated with positron emission tomography (PET) material. Two wipe tests of the interior of the delivery package resulted in levels below background. The patient dosages inside the package were not impacted and were able to be used.

"The dosage was shipped from Cardinal Health out of 410 S. Emporia St., Wichita, Kansas, which was also the delivery carrier. The facility Nuclear Medicine Technologist (NMT) immediately notified the delivery carrier by phone about the contaminated package at 1040 CST. The radiopharmacy notified the facility at 1100 CST that the driver and transport vehicle had been surveyed with no contamination noted.

"This package is the last delivery of the day. Because of the short half-life of F-18, the package will remain on the delivery rack for decay and will be returned to the Radiopharmacy on Monday. The NMT will perform extensive end of the day wipe tests in the hot lab to ensure contamination has not spread.

"VHA National Health Physics Program, who manages the master materials license, was notified of the incident around 1130 CST."

NON-AGREEMENT STATE - DAMAGED SOIL DENSITY GAUGE

The following is a summary from an e-mail received by the licensee:

On March 4, 2021 at 1435 [CST], a tracked earthmover ran over a Humboldt 5001EZ soil density gauge at the main dam of the Sweetwater Mine Tailings Storage Facility. After the accident occurred, the licensee secured the area and had the equipment operator stop and stay outside a fifteen foot diameter area until it was confirmed no contamination was present. The contractor contacted the Facility safety officer and the technician immediately contacted the manufacturer and took steps to assure there was no risk of contamination. The top of the source rod, handle, and index rod were broken off but it was confirmed the remainder of the source rod was intact. The source rod was raised to the safe position with the bottom port shutter shield closed and in-place. Since the source rod locking mechanism was broken, measures were taken to secure the Cesium containing source rod in the safe position. The Americium source cylinder was examined and confirmed to be without damage. The device was placed in its locked travel case. The manufacturer confirmed with these conditions there should be no risk of contamination.

The licensee notified via telephone the NRC Operations Center at 1516 [CST] to provide a verbal report. The licensee also followed up with the NRC Region 3 point of contact. A survey and leak test was performed which confirmed the sources to be shielded and with no loose contamination. The readings obtained were noted to be in compliance with the manufacturer's specifications. The gauge is out of service in locked storage pending shipment to the manufacturer.

FITNESS-FOR-DUTY REPORT

The licensee made the following telephone notification in accordance with 10 CFR 26.719(2)(b), to report a significant fitness-for-duty event under 10 CFR 26.75(e)(1).

"A contract employee supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. The NRC Resident Inspector has been notified."

FITNESS FOR DUTY REPORT

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

The NRC Resident Inspectors have been notified.

REACTOR RECIRCULATION PUMP TRIP

"On March 12, 2021, at 2102 (EST), Reactor Recirculation Pump (RRP) 13 tripped. The cause for the trip is under investigation.

"Following the RRP trip, the Average Power Ranger Monitors (APRMs) flow bias trips are inoperable due to reverse flow through RRP 13. The APRMs were restored to operable on March 12, 2021, at 2110 [EST] when the RRP 13 Discharge Blocking Valve was closed.

"This 8-hour non-emergency report is being made based upon requirements of 10 CFR 50.72(b)(3)(v)(A) which states: 'Licensee shall notify the NRC of any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (A) Shut down the reactor and maintain it in a safe shutdown condition.'

"The licensee has notified the NRC Resident Inspector."

MANUAL TRIP DUE TO LOSS BUS VOLTAGE

"On March 14, 2021, at 1315 CDT, Arkansas Nuclear One, Unit 1(ANO-1) was manually tripped due to degraded voltage and momentary loss of the A-2, non-vital 4160 V Bus in accordance with Abnormal Operating Procedure. All control rods fully inserted. Degraded voltage of the A-2 non-vital 4160 V Bus resulted in de-energizing the A-4 vital 4160 V Bus. Emergency Diesel Generator No. 2, K-4B, started automatically and is currently powering the A-4 vital 4160 V Bus. All other Vital and Non-Vital Buses transferred power automatically to the Startup Transformer No. 1. Offsite power remains energized and available for ANO-1. All other systems responded as designed. The loss of the A-2 Non-Vital Bus is still under investigation.

"ANO-1 is currently stable in MODE 3 (Hot Standby), maintaining pressure and temperature with Main Feedwater pumps and steaming to the Condenser.

"There are no indications of a radiological release on either unit as a result of this event.

"This report satisfies the reporting criteria of both 10 CFR 50.72(b)(2)(iv)(B) for the Reactor Protection System actuation and 10 CFR 50.72(b)(3)(iv)(A) for the actuation of the Emergency Diesel Generator.

"The Licensee has notified the NRC Senior Resident Inspector."