Event Notification Report for October 29, 2021

EN Revision Imported Date: 10/29/2021

EN Revision Text: AGREEMENT STATE REPORT - STUCK SHUTTER

The following was received from Pennsylvania, Bureau of Radiation Protection (the Department) via email:

"On October 20, 2021, the licensee informed the Department of a failure of a shutter. It is reportable per 10 CFR 31.5(b)(5).

"On March 26, 2019, the licensee identified a defective linear actuator assembly on one of its Beta Control Mk 1.0 (serial number 559 / KP983) devices. The device contains 267 mCi (9.9 GBq) of Kr-85. The defect prevented the source from returning fully to its home shielded position. After initial discovery, a service provider manually moved the device to fully align with the shutter assembly. At a later date, it was discovered the unit had drifted out of alignment again. At this time a service provider installed a plate directly on the device effectively sealing the unit, regardless of alignment with shutter assembly. No exposures resulted from this event.

"The Department will perform a reactive inspection. A service provider has already corrected the problem."

Event Report ID No: PA210016

EN Revision Imported Date: 10/29/2021

EN Revision Text: AGREEMENT STATE REPORT - STUCK/BROKEN SHUTTER

The following was received from Pennsylvania, Bureau of Radiation Protection (the Department) via email:

"On October 5, 2020, the licensee identified a failed return spring on one of its NDC 103 (serial number 3020641) devices. The device contains 148 mCi (5.55 GBq) of Am-241. The written report received from the service provider on Oct 5, 2020 stated that the secondary shutter device for the device in question failed to close. The primary shutter assembly remained operational at all times. The secondary shutter assembly defect was addressed and corrected by the service provider at the earliest possible time (next scheduled machine downtime event). No overexposures resulted from this event.

"The Department will perform a reactive inspection. A service provider has already corrected the problem."

Event Report ID No: PA210017

EN Revision Imported Date: 10/29/2021

EN Revision Text: AGREEMENT STATE REPORT - UNDERDOSE

The following report was received from the Illinois Emergency Management Agency [the Agency] via email:

"The Agency was contacted on the afternoon of 10/21/21 by the University of Chicago to advise of a reportable medical event that occurred the day before. A human research subject was reportedly administered 79.8 mCi of a prescribed 100 mCi dose of I-131 under the therapeutic portion of a study protocol. There is no root cause available at this time, although the licensee suspects an inadequate volume of saline flush. Inspectors will evaluate any other contributing factors including equipment, personnel involved and unique procedures for this study protocol. At this time, the licensee is not expecting any adverse impact to the patient and they are following up with the study sponsor to determine if additional treatment is required. The referring physician has been notified and the licensee is aware of the requirement to notify the patient. This matter is reportable under 32 Ill. Adm. Code 335.1080(a) for a dose differing from the prescribed dose by 20 percent or more. The administration was started at 1420 CDT on 10/20/21 and the matter reported to the Agency at 1219 CDT on 10/21/21. The reporting criteria has been met. In accordance with Agency policy, inspectors will perform a reactionary inspection within 10 days of the incident."

Illinois Report Number: IL210032

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.

EN Revision Imported Date: 10/29/2021

EN Revision Text: AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following information was received from the state of Illinois via email:

"The Illinois Emergency Management Agency operations center was contacted at 1904 CDT on 10/22/21 by the Radiation Safety Officer (RSO) for Flood Testing Laboratories (RML IL-01651-01) to advise that at approximately 1500 CDT that afternoon, a Troxler 3430 moisture density gauge [(40 milliCurie Am-241/Be and 8 milliCurie Cs-137 source)] was struck by a bulldozer on a construction site. The operator was uninjured and reportedly promptly notified the RSO. The area was secured and the RSO responded to the scene to package and secure the damaged gauge. The source rod was not extended when struck (glancing blow with blade) and both the source rod and the americium source housing were undamaged. The gauge was able to be repackaged in the transport container and is currently in safe storage in the licensee's facility in Chicago. The licensee does not own a radiation survey meter. Leak tests have been collected and the manufacturer contacted for expedited processing. Agency inspectors will investigate further next week to determine the adequacy of emergency procedures, results of leak tests, and the proximity/awareness of the operator during the incident.

"This matter is reportable under 32 Ill. Adm. Code 340.1220(c)(2) and was reported to the NRC Operations Center the same day under NMED event number IL210033."

EN Revision Imported Date: 10/29/2021

EN Revision Text: AUTOMATIC ACTUATION OF THE 1B EDG LOAD SEQUENCER ON BUS UNDERVOLTAGE CONDITION

"At 1429 EDT on October 27, 2021 with Unit 1 in Mode 6 at 0 percent power, the 1B Emergency Diesel Generator (EDG) Load Sequencer was actuated by a valid undervoltage condition on the 1B 4160V Essential Bus that occurred during 1B Sequencer calibration activities. Valid signals were sent to both the 1B EDG and Unit 1 Auxiliary Feedwater (CA) systems. Neither system automatically started as they were both removed from service for maintenance activities at the time.

"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the 1B EDG and Unit 1 CA systems.

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

OFFSITE NOTIFICATION DUE TO TWO MONITORING WELLS EXCEEDING NEI GPI TRITIUM THRESHOLD VALUES

"At 1340 EDT on October 28, 2021, Watts Bar Nuclear Plant (WBN) Units 1 and 2 initiated voluntary communication to the State of Tennessee and local officials as part of the Nuclear Energy Institute (NEI) Groundwater Protection Initiative (GPI), after receiving analysis results for two on-site monitoring wells that indicated tritium activity above the GPI voluntary communication threshold. The suspected source, a permitted release line, has been isolated, and additional corrective actions are in progress. This condition 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."

PART 21 REPORT - FAILURE OF A BASLER ELECTRIC TRANSFORMER IN A YORK TEMPERATURE CONTROL MODULE

The following is a synopsis of information received via facsimile:

On June 18, 2021, STP Nuclear Operating Company returned a York TCM-1A temperature control module with the reported issue that the module would not respond in auto or manual vane control and that internal relays 1R and 2R would not pick up. The subject temperature control module was previously returned by STP Nuclear Operating Company to United Controls International (UCI) for refurbishment and modification, after which it was returned by UCI to STP Nuclear Operating Company on March 13, 2017.

Troubleshooting performed by UCI identified that the secondary of the Basler Electric BE13410001 transformer that is used to isolate and step down the input voltage from 115V AC to 22V AC had an open circuit. When the subject transformer was bypassed, the module operated as designed. UCI is unable to determine the cause of the transformer failure. Post refurbishment/modification testing performed by UCI included verifying functionality of the unit before and after performance of a 48 hr. burn-in period.

The only facility that is listed as being affected is STP Nuclear Operating Company.

If you have any questions or wish to discuss this matter or this report, please contact: Wesley Hickle, Engineering Manager, whickle@unitedcontrols.com, 470-610-0870.