Event Notification Report for August 04, 2022

MEDICAL EVENT - PATIENT UNDERDOSE

The following report was received via email from the VA National Health Physics Program (NHPP):

"Tibor Rubin VA Medical Center, Long Beach, California, which holds Permit Number 04-00689-07 under the VA master materials license, reported the discovery of a medical event to NHPP at approximately 1450 CDT, July 27, 2022.

"A radium-223 dichloride (Xofigo(R)) therapy administration was performed at approximately 1115 PDT on July 27, 2022. The prescribed dosage was 211 microcuries, to be administered intravenously. Due to leakage at the IV 3-way stopcock, approximately only 160 microcuries was administered, resulting in about 75 percent of the prescribed dosage being delivered. This meets the reporting criteria of 10 CFR 35.3045 (a)(1)(i) and (a)(1)(i)(B).

"The patient and the referring physician have been notified. No harm is expected to the patient.

"NHPP will follow up with a written report in accordance with NRC requirements in 10 CFR 35.3045.

"NHPP notified our NRC Region III Project Manager, Bryan Parker."

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

AGREEMENT STATE REPORT - SOURCES FOUND IN UNLOCKED CONTAINER

The following information was provided by the Florida Bureau of Radiation Control (BRC) via email:

"Indian River County [Radiological Emergency Preparedness] (REP) [employee] called this afternoon regarding a small cardboard box, about half the size of a shoebox, with several sources inside being stored in a small, unlocked metal storage shed on property of the Emergency Operations Center. Inside the small cardboard box are six small cylindrical containers three of which are labeled `Unrefined uranium minerals emit alpha, beta, and gamma radiation', one 'No Salt' container, and the other three are smaller metal containers not labeled. Also in the box are several typical plastic check sources inside plastic bags and one wooden gamma standard check source. REP reported an 'on contact' reading with the box a dose rate of around 280 microR/hr and with a gloved hand, removed all the items inside the box and reported a contamination reading of just over 400 cpm. REP has requested a response from the BRC to handle. The Central Inspection Office has been notified and will respond."

Florida Incident Number: FL22-086

EN Revision Imported Date: 8/3/2022

EN Revision Text: PART 21 REPORT - FAILURE TO MEET RELIABLE/CONSISTENT OPERATION OF COOLING FAN ON POWER SUPPLY 16-AAT907B

The following is a synopsis of information received via fax:

DRS Consolidated Controls Inc. (currently Leonardo DRS Naval Power Systems, henceforth referred to as NPS) provided eleven, 48 VDC power supplies, Part Number 16-AA T907B to Wolf Creek Generating Station in 2018. It was discovered in 2019 by Wolf Creek that there was anomalous fan performance occurring within this power supply after several months of operation. These issues were in the form of the following: fan noise and fan failure to operate.

The power supplies were replaced by Wolf Creek upon discovery. NPS and the power supply manufacturer were notified of the issue to begin investigation on root cause and remedial actions.

Wolf Creek Generating Station is the only power plant affected by this deviation.

Kevin Andino, Senior Director of Quality, Leonardo DRS Naval Power Systems, 21 South Street, Danbury, CT 06810, Tel: +1-203-798-3000.

AUTOMATIC REACTOR TRIP DUE TO LOSS OF POWER TO START-UP TRANSFORMER

The following information was provided by the licensee via email:

"At 1258 CDT on August 3, 2022, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped due to the supply breakers of the 1B startup transformer opening. The fast dead bus transfer for the reactor coolant pumps did not occur during the event. Currently the plant is in Mode 3 on natural circulation.

"Operations responded and stabilized the plant. Decay heat is being removed by steaming with atmospheric relief valves. Unit 2 is not affected.

"An automatic actuation of the 1B diesel occurred because of the power loss to the 1G 4160V bus. Additionally, the actuation of motor driven and turbine driven auxiliary feedwater pumps (AFW) also occurred. AFW auto-start is an expected response from this reactor trip.

"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). This event is also being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the 1B diesel and the auxiliary feedwater system.

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