Event Notification Report for May 22, 2023

AGREEMENT STATE REPORT - STUCK SHUTTER

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

"The licensee [Bethune Nonwovens, Inc., d/b/a Suominen Nonwovens] notified the Department in writing on April 21, 2023, that a generally licensed fixed gauging device had a failed shutter which had been repaired by the manufacturer on April 3, 2023. The licensee discovered that the event occurred on March 31, 2023, and reported that upon discovery of the stuck shutter, that the manufacturer arrived on site on the same day and placed the device out of service until repaired. The event involved a Mahlo fixed gauging device (model number: 11-200933, serial number 11-011985-AH-5783), which housed an Isotope Product Laboratories, krypton-85 sealed source (model number KAC.D3, serial number: AH-5783), with an activity of 9.62 GBq (260 mCi). The licensee reported that the cause of this equipment failure was attributed to corrosion around the shutter assembly.

"On May 2, 2023, a Department inspector was dispatched to the facility to conduct an on-site investigation. All dose measurements were consistent with the Sealed Source Device Registry certificate for the device. Based on the resulting dose rate surveys conducted by the Department and the manufacturer, interviews with licensee representatives, and the removal of the device from service at the time that the failure was discovered, it does not appear that any radiation exposure to workers, or any other individual members of the public has occurred.

"This event is considered closed."

Internal ID number: SC230009

CONCURRENT REPORT - FIRE DOOR MALFUNCTION

The following information was provided by the licensee via email:

"At approximately 0940 EDT on May 18th, the New Hanover County Deputy Fire Marshal was notified that the fire door of the dry conversion process (DCP) elevator shaft malfunctioned and was in the open position. The DCP elevator is located on the south wall of the DCP which is a credited fire barrier. A fire watch was initiated and maintained until the elevator door was closed at approximately 1030 EDT. The elevator was restored to full operation at approximately 1330 EDT on May 18th. Because the New Hanover County Deputy Fire Marshall was notified, a concurrent notification to the NRC Operations Center is being made per 10 CFR 70, Appendix A(c)."

The NRC region will be notified.

AUTOMATIC ACTUATION OF AUXILIARY FEEDWATER SYSTEM (AFW)

The following information was provided by the licensee via email:

"At 0852 [EDT] on May 19, 2023, with Unit 2 in Mode 3 at zero percent power, an actuation of the auxiliary feedwater system (AFW) occurred. The reason for the AFW auto-start was a failed start attempt of the 'B' main feedwater pump. The 'A' and 'B' motor driven auxiliary feedwater (MDAFW) pumps automatically started as designed when the 'Loss of Both Main Feedwater Pumps' signal was received.

"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 AFW system.

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

AUTOMATIC REACTOR SCRAM

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

"On 5/20/2023 at 0315 CDT, Browns Ferry Unit 1 was at 80 percent reactor power performing, 'Turbine control valve fast closure turbine trip and RPT [recirculation pump trip] initiate logic testing'. During performance of this test, Unit 1 received a full reactor scram. An investigation is in progress to determine the cause of the scram. All systems responded as expected, and Unit 1 is stable at zero percent power in mode 3.

"All control rods fully inserted into the core. Main steam isolation valves remained open with main turbine bypass valves controlling pressure. Reactor feedwater pumps remained in service to control reactor water level. Primary containment isolation signals groups 2, 3, 6, and 8 were received with expected system actuations.

"This event is reportable per 10 CFR 50.72(b)(2)(iv)(B), 'Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation'.

"The event is also reportable within 8 hours per 10 CFR 50.72(b)(3)(iv)(A), 'Specified System Actuation'.

"The NRC Resident has been notified."