Event Notification Report for December 21, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/20/2024 - 12/21/2024
Fuel Cycle Facility
Event Number: 57472
Facility: Westinghouse Electric Corporation
RX Type: Uranium Fuel Fabrication
Comments:
Leu Conversion (Uf6 To Uo2)
Commercial Lwr Fuel
Region: 2
City: Hopkins State: SC
County: Richland
License #: SNM-1107
Docket: 07001151
NRC Notified By: Stephen Subosits
HQ OPS Officer: Adam Koziol
Notification Date: 12/13/2024
Notification Time: 10:23 [ET]
Event Date: 12/12/2024
Event Time: 10:30 [EST]
Last Update Date: 12/17/2024
Emergency Class: Non Emergency
10 CFR Section:
PART 70 APP A (b)(2) - Loss Or Degraded Safety Items
Person (Organization):
Franke, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
EN Revision Imported Date: 12/21/2024
EN Revision Text: DEGRADATION OF SAFETY ITEM
The following information was provided by the licensee via phone and email:
"At approximately 1030 EST, on 12/12/2024, Nuclear Criticality Safety (NCS) staff were notified that the polyvinyl chloride (PVC) piping of a passive overflow item relied on for safety (IROFS, SGD-147) for Uranium Recovery and Recycle Services (URRS) vessel V-756A was in a deformed condition. V-756A and V-756B are interconnected URRS dissolver product hold tanks. The V-756B redundant passive IROFS overflow (SGD-130) is constructed of steel. NCS staff reviewed the condition of the PVC overflow piping and determined the overflow was deformed into a position that would restrict flow to the point that it could not provide its intended safety function. The safety function of the IROFS is to prevent backflow of uranium bearing material into water and nitric acid systems by providing an overflow path below the height of the water and nitric acid inputs into V-756A/B. The SGD-130 passive overflow was available to perform its intended safety function. The issue was entered as a red-book item in the corrective action program (CAP) as IR-2024-13041.
"Per criticality safety evaluation, CSE-4A, and supporting calculation note, CN-SB-11-031, with the passive overflow IROFS SGD-147 in a failed condition, the overall likelihood index (OLI) for the fault tree scenario increased from -6 to -3 which does not meet the OLI of -4 necessary to meet 10 CFR 70.61 performance requirements. The result is reportable per 10 CFR Part 70 Appendix A(b)(2), 'Loss or degradation of items relied on for safety that results in failure to meet the performance requirements of 10 CFR 70.61.'
"Operations for the dirty dissolver process are down pending further investigation and development of compensatory actions. A causal analysis will be performed and corrective actions to prevent recurrence will be documented in the CAP.
"Further investigation determined that on 12/12/2024, during third shift URRS, while dirty dissolver operations were down, a centrifuge malfunction occurred that necessitated spill clean up of the centrifuge platform area in the ground floor level below the platform. Based on interviews of URRS personnel, it was determined that to clean up the two spill locations, two separate steam-driven eductors with suction wands were utilized to transfer spill solutions to V-756A in roughly the same timeframe. The apparent cause of the PVC overflow piping deformation is excessive steam vapor influx into V-756A from the simultaneous spill cleanup activities.
"A review of the site maintenance database identified one completed maintenance work order for the replacement of V-756A overflow piping for PVC pipe deformation. Additional review of previous maintenance activities for the V-756A will be performed to determine if there were other instances of deformation of the overflow piping for V-756A. This occurrence in September 2024 was not brought to the attention of management or engineering staff to ensure comprehensive follow-up and corrective actions. The occurrence was not captured as red-book CAP item for a degraded or failed IROFS."
"Number and types of controls necessary under normal operating conditions: For scenario 4.3 of CSE-4-A supporting Calculation Note, CN-SB-11-031, two passive overflow IROFS controls (SGD-130 and SGD-147) are necessary under normal operating conditions to prevent a backflow condition into the nitric acid supply.
"Number and types of controls which functioned properly under upset conditions: Passive overflow IROFS (SGD-130) on V-756B is constructed of metal and will not deform when exposed to steam. Criticality safety staff reviewed the SGD-130 overflow for V-756 A/B and determined it could perform its safety function.
"Number and types of controls necessary to restore a safe situation: The PVC overflow IROFS SGD-147 for vessel V-756A was replaced on 12/12/2024. An extent of condition review for process vessels with PVC/plastic pipe passive overflows with potential exposure to excess heat has been initiated.
"Safety significance of events: Passive overflow IROFS SGD-130 remained available and a review of tank level data logging confirmed there was no overflow of V-756 A/B and there was no backflow condition into the deionized water and nitric acid systems.
"Safety equipment status: The passive overflow IROFS control SGD-147 for V-756A/B was replaced on 12/12/2024. The IROFS controls necessary to meet 10 CFR 70.61 performance requirements are in place.
"Status of corrective actions: Operations for the dirty dissolver are down pending further investigation and development of compensatory actions. A causal analysis will be performed and corrective actions to prevent recurrence will be documented in the corrective action program."
Agreement State
Event Number: 57473
Rep Org: SC Dept of Health & Env Control
Licensee: Isomedix Operations Inc.
Region: 1
City: Spartanburg State: SC
County:
License #: 267
Agreement: Y
Docket:
NRC Notified By: Adam Gause
HQ OPS Officer: Ian Howard
Notification Date: 12/13/2024
Notification Time: 16:10 [ET]
Event Date: 08/13/2024
Event Time: 00:00 [EST]
Last Update Date: 12/13/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Jackson, Don (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - IRRADIATOR EVENT
The following information was provided by the South Carolina Department of Environmental Services (the Department) via phone and email:
During a routine inspection conducted by the Department on December 3, 2024, inspection and maintenance records indicated that a float switch for a panoramic pool irradiator had failed on August 13, 2024. Between December 3, 2024, and December 13, 2024, the licensee evaluated the event for reporting applicability. On December 13, 2024, the licensee reported the event to the Department. The licensee is reporting that the float switch on a Nordion (model JS8900) continuous panoramic pool irradiator (serial number IR97) failed on August 13, 2024, during routine maintenance and inspection checks. The float switch was replaced on August 13, 2024. Specifically, the float did not operate the full length to the hard stop. The licensee is reporting no current health and safety concerns. This event is under investigation by the Department.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The float switch alarms radiation workers of low water levels which would result in higher radiation levels.