Event Notification Report for October 17, 2022

EN Revision Imported Date: 10/14/2022

EN Revision Text: DEGRADATION OF SAFETY ITEMS

The following information was provided by the licensee via e-mail:

"NFS [Nuclear Fuel Services, Inc.] evaluated a degraded Item Relied On For Safety (IROFS) in accordance with the documented Integrated Safety Analysis. During this review, the event was determined to be NON-REPORTABLE as additional controls were available and performance criteria maintained. However, during the detailed review of past performance, when the IROFS that was available in this scenario failed, the redundant IROFS would have been degraded.

"There were no actual radiological or other nuclear safety consequences to the public, workers, or the environment.

"The Senior Resident Inspector and Region II staff were notified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

The plant was shutdown pending repair or implementation of compensating measures.

AGREEMENT STATE REPORT - DAMAGE TO PORTABLE DENSITY GAUGE

The following information was provided by the Virginia Department of Health via email:

"On October 7, 2022 at 1500 EDT, the Virginia Radioactive Materials Program (VRMP) received a report from a licensee's Radiation Safety Officer (RSO) via telephone that a portable nuclear moisture/density gauge was damaged by a dump truck at a jobsite located near the intersection of I-66 and I-28 in Chantilly, VA. The incident occurred on October 7, at about 1130 EDT. The report indicated that a Troxler density gauge (Model 3440, Serial # 77069, containing 8.0 millicuries of Cesium-137 and 40.0 millicuries of Am-241) was being used at the road construction site when a dump truck drove into and hit the gauge. During the incident, the gauge housing (the plastic cover and electronic system) was damaged, but the source appeared to remain intact within the housing. The site was cordoned off with a 15 foot radius. The licensee's survey of the gauge yielded readings of background at 15 feet and 0.5 mR/hr at about 3 feet from the gauge. The gauge was taken to the licensee's storage facility located at the project site. The RSO mentioned that wipe samples taken for leakage will be sent for analysis. The VRMP is working with the licensee to obtain additional information. This report will be updated once the licensee's investigation is complete, and the information is received. According to the RSO, no public exposure occurred."

Virginia Event Report ID No.: VA220003

AGREEMENT STATE REPORT - DAMAGED GAUGE

The following is a summary of information received from the South Carolina Department of Health and Environmental Control [the Department] via email:

At 1420 EDT on October 10, 2022, the Department received a call from Summit Engineering (the licensee) to report that at approximately 1230 EDT, a double pin road roller used for paving hit a Troxler 3440 gauge (SN #34989), cracking its plastic outer covering. The licensee's radiation safety officer arrived onsite and arranged to have the gauge transported back to the licensee's office. The Department traveled to the licensee's office to survey the damaged gauge. The Department found the gauge's source in the shielded position and surveys read no higher than 8 mR/hr on the surface of the gauge and no higher than 0.06 mR/hr at a foot away. The licensee stated that the gauge would be sent back to the manufacture for repair.

OFFSITE NOTIFICATION

The following information was provided by the licensee via email:

"At approximately 1311 (EDT) on October 12th, 2022, the New Hanover County Deputy Fire Marshall was notified per State code requirements that the fire suppression system encompassing the Fuel Manufacturing Operation (FMO) was impaired. During a flow test, the backup diesel fire pump experienced an overheating condition. As a result, the diesel fire pump was placed in the manual 'Off' position. The electric fire pump remained fully operational and available to perform its safety function. The diesel pump was repaired and returned to operation at approximately 1000 (EDT) on Thursday, October 13th. The New Hanover County Deputy Fire Marshall was notified of restoration at 1020 (EDT). 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 licensee will notify the State and NRC Region II.

ALERT DECLARED DUE TO A FIRE IN LABORATORY BUILDING UNDER RENOVATION

On 10/13/2022 at 1725 CDT, the licensee declared an Alert due to a fire in a laboratory building under renovation. The licensee contacted local Fire and Emergency Medical Service who responded and extinguished the fire. There was no offsite release of radiological material.

The licensee notified local authorities and the Illinois Emergency Management Agency of the event.

* * * UPDATE ON 10/13/22 AT 1851 CDT FROM SEAN PATTERSON TO KERBY SCALES * * *

At 1851 CDT, the licensee terminated the Alert and reported the fire was out.

Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, CISA Central Watch Officer, EPA EOC, R2DO (Miller), IRMOC (Whited), Director DFM (Helton).

HIGH PRESSURE COOLANT INJECTION INOPERABLE

The following information was provided by the licensee via email:

"Unit 1 High Pressure Coolant Injection (HPCI) was declared inoperable due to an inadvertent division 2 isolation signal and subsequent valve closure.

"This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident."

The NRC Resident will be notified.

REACTOR VESSEL HEAD PENETRATION REPAIR DEGRADED
The following information was provided by the licensee via email:

"On 10/15/2022 at 1159 [EDT], during the Catawba Nuclear Station Unit 2 refueling outage, it was determined that the results of a planned surface examination Liquid Penetrant test (PT) performed on a previous overlay repair on nozzle number 74 of the reactor vessel closure head (RVCH) did not meet applicable acceptance standards. The examination was being performed to meet the requirements of Relief Request RA-21-0144, 'Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant'. The penetration required repairs for the discovered indications. The repairs have been completed in accordance with the ASME Code of Record prior to returning the vessel head to service. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).

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

"The original indication that led to the overlay repair was discovered in April 2021, during ultrasonic testing and reported to the NRC and assigned EN55201."