ML25024A226
| ML25024A226 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 01/28/2025 |
| From: | Eric Michel NRC/RGN-II/DFRSS/FOB2 |
| To: | Stutts R Westinghouse, Columbia Fuel Fabrication Facility |
| References | |
| IR 2024004 | |
| Download: ML25024A226 (21) | |
Text
Roy Stutts, Site Director Columbia Fuel Fabrication Facility Westinghouse Electric Company 5801 Bluff Road Hopkins, SC 29061
SUBJECT:
COLUMBIA FUEL FABRICATION FACILITY - INTEGRATED INSPECTION REPORT 07001151/2024004
Dear Roy Stutts:
This letter refers to the U.S. Nuclear Regulatory Commission (NRC) inspection activities conducted from October 1, 2024, to December 31, 2024. On October 10, 2024, and November 21, 2024, the NRC inspectors discussed the results of these inspections with you and other members of your staff. The results of the inspections are documented in the enclosed report.
No violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Eric C. Michel, Chief Fuels Oversight Branch 2 Division of Fuels, Radiological Safety, and Security Docket No. 07001151 License No. SNM-1107
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV January 28, 2025 Signed by Michel, Eric on 01/28/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DFRSS RII/DFRSS RII/DFRSS NAME T. Vukovinsky J. Raudabaugh E. Michel DATE 01/27/25 01/28/25 01/28/25
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07001151 License Number:
SNM-1107 Report Number:
07001151/2024004 Enterprise Identifier:
I-2024-004-0049 Licensee:
Westinghouse Electric Company Facility:
Columbia Fuel Fabrication Facility Location:
Hopkins, SC Inspection Dates:
October 07 - 10, 2024, and November 18 - 21, 2024 Inspectors:
L. Cooke, Fuel Facilities Inspector J. Grice, Fuel Facilities Inspector N. Peterka, Sr. Fuel Facility Project Inspector J. Raudabaugh, Fuel Facilities Inspector Approved By:
Eric C. Michel, Chief Fuels Oversight Branch 2 Division of Fuels, Radiological Safety, and Security
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Columbia Fuel Fabrication Facility, in accordance with the fuel cycle facility inspection program. This is the NRCs program for overseeing the safe operation of licensed fuel cycle facilities. Refer to https://www.nrc.gov/materials/fuel-cycle-fac.html for more information.
List of Violations No violations of more than minor significance were identified.
Additional Tracking Items Type Issue Number Title Report Section Status WER 07001151/2024-004-00 EN 57152 Contaminated injured worker 88030 Closed
3 PLANT STATUS The Westinghouse facility converts uranium hexafluoride (UF6) into uranium dioxide using a wet conversion process and fabricated fuel assemblies for use in commercial nuclear power reactors. During the inspection period, normal production activities were ongoing.
INSPECTION SCOPES Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Inspections were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2600, Fuel Cycle Facility Operational Safety and Safeguards Inspection Program. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
SAFETY OPERATIONS 88020 - Operational Safety The inspectors evaluated selected aspects of the licensees Operational Safety program to verify compliance with selected portions of 10 CFR 70, including 70.24, 70.61, 70.62, and Chapter 11, Management Measures, of the facilitys license application, and applicable licensee procedures.
Identification of Safety Controls and Related Programs (IP Section 02.01)
The inspectors selected specific process areas for inspection based on the safety basis information of the facility, the risk/safety significance of the process areas, the description of plant changes submitted to the NRC, and past plant performance documentation. For the process areas of interest, the inspectors selected a sample of accident sequences in nuclear criticality safety and chemical safety based on the information provided in the integrated safety analysis (ISA) summary. The inspectors conducted a general plant tour of each major plant operating area. The process areas and accident sequences selected for review are listed below:
Scrap Uranium Processing System o
CSE-11-A-1, Non-Favorable Geometry at Staging Table o
CSE-11-A-2, Non-Favorable Geometry in Dissolver Hood o
CSE-11-B-2, Wrong Filter Press configuration o
CSE-11-B-6, Fissile Liquid Pumped into DI Water Supply Ammonia Diuranate (ADU) Rod Area o
CSE-10-A-1, Non-Favorable Geometry in Rod Loading Station o
CSE-10-A-5, Mass accumulation in rework station hood o
CSE-10-A-6, Non-Favorable Geometry and moderation in the dump hood o
CSE-10-B-2, Non-Favorable Geometry of fuel rods on the soft handling system
4 Review of Safety Controls and Related Programs (IP Section 02.02)
The inspectors reviewed information related to administrative, engineered, and passive safety controls or items relied on for safety (IROFS) for the accident sequences selected above, including the identification of the licensees assumptions and bounding cases as they apply to each of the selected accident sequences, safety controls, or IROFS. This review was performed to verify that the controls or IROFS were available and reliable to perform their intended safety functions and that the design-basis assumptions were reflected in the actual conditions in the field. The specific safety controls selected for review are listed below:
ADUSCRP-111, Staging Table has credited design attributes, Passive Engineering Control ADUSCRP-115, Scrap cage hood & dissolver have the credited design attributes, Passive Engineering Control ADUSCRA-115, Maintain Analyze Filter Press Geometry, Administrative Control ADUSCRA-116, Maintain Analyze Filter Press Geometry, Administrative Control ADUBFP-103, Prevent Flow of SNM into DI Water Tank, Active Engineered Control ADUROD-127, Prevent rods from forming a slab greater than 4.25 inches, Passive Engineering Control ADUROD-129, Operators do not stack rods greater than 4.25 inches, Administrative Control ADUROD-147, Operator remove pellet chips during enrichment changeover, Administrative Control Implementation of Safety Controls (IP Section 02.03)
For the selected safety controls listed above, the inspectors reviewed management measures to verify proper implementation in accordance with 10 CFR 70 and applicable sections of the license application. This review was performed to verify that selected safety controls or IROFS were present, available, and reliable to perform their safety function and that the design-basis assumptions were reflected in the actual conditions in the field. The inspectors conducted the following activities to verify the implementation of selected safety controls:
interviewed and performed walkdowns of the Scrap Uranium Processing System in Conversion and ADU Rod areas to verify implementation of IROFS listed in Section 2 reviewed operational and maintenance procedures for implementation of IROFS listed above (documents listed in the Documents Reviewed List) interviewed operators, criticality and process engineers, and managers for the ADU Fuel Rod and Scrap Uranium Recovery System areas regarding safety hazards, IROFS awareness, job specific training, and willingness to raise safety issues to management and/or other available avenues
5 reviewed nuclear criticality safety (NCS) postings and general housekeeping in the ADU Fuel Rod and Scrap Uranium Processing System areas for IROFS listed in Section 02.02 reviewed accident sequences, criticality safety evaluations as applicable, and engineering evaluations for the accident sequences listed in Section 02.01 reviewed drawings for selected IROFS to verify consistency of the drawings with the actual plant configuration reviewed a sample of standard operating procedures for IROFS listed in Section 02.02 Safety Control Support Programs (IP Section 02.04)
The inspectors assessed additional management measures that support the availability and reliability of the selected safety controls to verify these were implemented in accordance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors conducted the following:
reviewed preventive maintenance, functional test instructions, and work order (WO)/dispatch packages for the IROFS listed above (specific documents listed in the Documents Reviewed Section) reviewed training qualification records for operators in ADU Rods and Conversion / Scrap Uranium Processing System areas reviewed current revision of ISA for accident sequences in Section 02.01 and IROFS in Section 02.02 reviewed Environmental Health & Safety (EHS) Audit-24-12, ISA Compliance Audit, dated August 08, 2024 reviewed EHS Audit-24-8, Regulatory Component Audit for Configuration Management, Audits and Records Management reviewed organizational charts for program organizational changes and compliance with Section of 2.3.7 of the license application attended plan of the day and daily production meetings in the Conversion areas observed safety-related activities related to operator clean out of ADU Fuel Rod glove box RADIOLOGICAL CONTROLS 86740 - Inspection of Transportation Activities The inspectors evaluated select aspects of the licensees Transportation Activities program to determine whether the licensee has established and is maintaining an effective, management-controlled program; to ensure radiological and nuclear safety in the receipt, packaging, delivery to a carrier and, as applicable, the private carriage of licensed radioactive materials; and to determine whether transportation activities are in compliance with the applicable Nuclear Regulatory Commission 10 CFR Parts 20 and 71 regulations and Department of Transportation (DOT) (49 CFR Parts 171-178) transport regulations.
6 Preparation of Packages for Shipment (IP Section 02.01)
The inspectors examined the licensees procedures and shipment records and observed actual package preparations and operations to verify compliance with the regulations above.
Specifically, the inspectors reviewed, verified, and observed the following:
Radioactive Material Vehicle Disposition Checklist for CAO-2024-0244 Outbound Fuel CF-75B-020, Traveller Shipping Packaging Recertification Fuel Assembly Shipping Package Inspection Checklist for TS445 loading of fuel assemblies into travellers for shipment Delivery of Completed Packages to Carriers (IP Section 02.02)
The inspectors examined the licensees procedures and shipment records and observed actual transport activities to determine that the licensee met package delivery requirements. Specifically, the inspectors reviewed or observed the following:
records indicating completion of hazardous materials (HAZMAT) trainings by transportation department personnel, including, OSHA Hazard Communication Training (TRN-047), DOT Hazardous Materials Awareness Training (TRN-080), DOT Hazardous Materials Employee Training (TRN-089),
and Columbia Plant Hazardous Materials Transportation (CA-192)
Radioactive Material Vehicle Disposition Checklist for CAO-2024-0244 Outbound Fuel Waste Manifest WS-55938-0-322 Receipt of Packages (IP Section 02.03)
The inspectors examined the licensees procedures and records of incoming shipments to verify compliance with 10 CFR 20.1906 and applicable license requirements. Specifically, the inspectors reviewed the following:
TVA Shipping Ticket for returning travellers WBN-24-347 records of low enriched shipments from Nuclear Fuel Services (NFS) observed receipt of travellers Records and Reports (IP Section 02.04)
The inspectors examined the licensees procedures and shipment records for recordkeeping and reports to verify compliance with the regulations above. Specifically, the inspectors reviewed the following:
special inspections for traveller TS391 IR 2024-3013, Missed LR230 Tote During Offload Certificates of Disposal for radioactive waste shipments 0857-01-0247, CPWU2986325-269, and ISEU100028-314 Bills of Lading for radioactive waste shipments 0857-01-0247, CPWU2986325-260, ISEU100028-314, WS-55938-0-332, and ISEU100014-307
7 General License Requirements (IP Section 02.05)
The inspectors reviewed the licensee package certifications utilized for shipment of radioactive material packages to verify compliance with 10 CFR 71, Subpart C. Specifically, the inspectors reviewed:
Certificate of Compliance for TS391 Certificate of Compliance for T550 Certificate of Compliance for Traveller PWR Fuel Shipping Package USA/9297/AF-96 Rev. 15 Management Controls (IP Section 02.06)
The inspectors reviewed the system of management controls for transportation activities to verify compliance with licensee instructions and procedures. Specifically, the inspectors reviewed:
LCPT 23-06, LR-230 Packaging Touch Up Indoctrination and Training Program (IP Section 02.07)
The inspectors conducted interviews, reviewed training and indoctrination documentation, and observed activities for workers involved in transport activities to verify compliance with Chapter 3 of the licensee application. Specifically, the inspectors:
reviewed training requirements and records for container services personnel, final assembly packing personnel, radioactive waste personnel, and transportation department personnel reviewed sample training documents for low-level radioactive waste shipments interviewed the area manager lead manufacturing engineer for final assembly regarding tracking of personnel training and qualification interviewed training staff regarding how training and qualifications are tracked Quality Assurance Program (IP Section 02.08)
The inspectors reviewed the quality assurance documents to verify compliance with the licensees quality assurance (QA) program. Specifically, the inspectors reviewed:
LCPT 2107, Assessment of Packaging Support Activities Audit Program (IP Section 02.09)
The inspectors reviewed the latest audits to verify compliance with 10 CFR 71.137. Specifically, the inspectors reviewed:
reviewed the 2022 and 2023 audits related to packaging and transport of nuclear fuel assemblies
8 Procurement and Selection of Packagings (IP Section 02.10)
The inspectors examined the licensees packaging, and revised procedures and records to verify compliance with the Federal regulations above. Specifically, for packaging that is used by the licensee to transport or to deliver licensed material to a carrier for transport, the inspectors reviewed the following:
TAF-502-1, Document Rework Performed on Traveller by Newington Preparation of Packages for Shipment (IP Section 02.11)
The inspectors examined the licensees package markings, documentation, and records to verify compliance with applicable parts of the Federal regulations above. Specifically, the inspectors reviewed:
Radioactive Material Vehicle Dispatch Checklist for outbound fuel assembly, CA-2024-0244 on 10/02/2024 reviewed process for notification of radioactive waste shipments to Energy Solution and Waste Control Specialists reviewed document packages that include the bill of lading, DOE/NRC form 741, shipping manifests, and notification to the state, for shipments of low-level radioactive waste Periodic Maintenance of Packagings (IP Section 02.12)
The inspectors examined the licensees procedures and records to verify compliance with applicable parts of the Federal regulations above. Specifically, the inspectors reviewed the following:
Traveller Lifetime Record for TS391 Traveller Refurbishment Checklist for TS391 Records, Reports, and Notifications (IP Section 02.13)
The inspectors reviewed the licensees records and procedures for recordkeeping and reports to verify that a system is in place to verify compliance with the Federal regulations above. Specifically, the inspectors reviewed the following:
reviewed two 10 CFR 71.95 reports related to an uninstalled leak test port bolt in an LR-230 package and a disengaged 2-inch ball lock pin in a UX-30 package shipment records, including Forms 540, 541, 741, and Bills of Lading, for radioactive waste shipments WS-55938-0-332, ISEU100014-307, ISEU100028-314, CPWU2986325-269, and 0857-01-0247 88030 - Radiation Protection
9 The inspectors evaluated selected aspects of the licensees radiation protection (RP) program to verify compliance with selected portions of 10 CFR 19, 20, 61, 70, and Chapter 5, Radiation Protection, of the facilitys license application, and applicable licensee procedures.
Radiation Protection Program Review (IP Sections 02.01, 02.02, 02.03, 02.23)
The inspectors interviewed licensee staff and reviewed licensee procedures and other documentation related to the implementation of the RP and radioactive waste programs and As Low As Reasonably Achievable (ALARA) program to verify compliance with 10 CFR 20.1101(a), 20.1101(b), 20.1101(c), 20.2102, 70.72 and Chapters 3 and 5 of the license application. Specifically, the inspectors:
Radiation Protection/Waste Program Implementation and Procedures (IP Section 02.01 & 02.03) reviewed RA-203, "General HP Rules and Recommendations," revision 34 performed walk through of radiological waste area with an Engineering Technician to include dry and wet waste weighing, surveying, marking and sealing reviewed form CAF-208-1-00021, Columbia Organizational Change Control Review for the day shift Health Physics (HP) Team Manager reviewed form CAF-208-1-00044 for back shift HP Team Manager interviewed and observed a chief nuclear operator operating Assay 2 combustible trash and drums and ash residue surveys reviewed the Wet Combustible Drum Temperature Log (CF-83-904) which records wet waste drum temperature Radiation Program Review and ALARA (IP Section 02.02 & 02.23)
LTR-EHS-24-09, Annual Radiation Protection Program Review LTR-EHS-24-36, CY 2024 1st Quarter ALARA Report LTR-EHS-24-54, CY 2024 2nd Quarter ALARA Report LTR-EHS-24-35, ALARA Committee Meeting Minutes LTR-EHS-24-45, 2024 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents RAF-106-1-00124, ISA Compliance Audit Report RAF-106-1-00123, Supplier Audit of Landauer RAF-106-1-00122, Audit Report for SNM-1107 Radiological Safety and Respiratory Protection Program RAF-106-1-00084, Formal Compliance Audit Report of Areas of ISAs RAF-106-1-00114, Audit Report for the SNM-1107 Environmental Protection Program RAF-106-1-00096, EHS Audit of URRS Lagoon Sampling and Analysis for NPDES Training (IP Section 02.04)
The inspectors interviewed licensee staff and reviewed RP related training records to verify compliance with 10 CFR 19.12, 70.61(f)(2) and Chapters 3 and 5 of the license application. Specifically, the inspectors:
10 reviewed radiation worker training materials and completion records for various staff reviewed training records for six employees interviewed licensee staff regarding HP technician qualification process reviewed qualification checklist for 4 HP technicians reviewed HP Technician Radiation Protection Training Checklist (RAF-125-14 rev 9)
Safety-Significant Events (IP Section 02.05)
The inspectors reviewed the licensees review of safety-significant events, RP and radioactive waste related corrective action program (CAP) entries to verify compliance with 10 CFR 20.2201, 20.2202, 20.2202(a), 20.2202(b), 20.2203, 40.60, 70.50, 70.52, 70.74, Part 70 Appendix A, as applicable and Chapters 3 and 5 of the license application. Specifically, the inspectors:
reviewed and discussed the following RP related corrective action entries o
IR-2024-9237 o
IR-2024-8084 o
IR-2024-9012 o
IR-2024-9013 o
IR-2024-2772 o
IR-2024-3443 reviewed ROP-07-001, "Health Physics Response to Emergency Events,"
Rev. 14 Radiation Exposure Controls (IP Sections 02.06, 02.18)
The inspectors reviewed licensee's measures such as radiological work permits to control the concentration of radioactive material in air or limiting intake to keep doses ALARA to verify compliance with 10 CFR 20.1101(b), 20.1701, 20.1702, and Chapters 5 of the license application. Specifically, the inspectors:
reviewed RWP 2024-03, 05/30/2019 reviewed RWP 2024-04, 06/13/2024 observed daily fixed air sample changeout for URRS area observed flow meters on fixed air monitors to verify units were within calibration observed ventilation velocity checks for Line 4 ventilation hoods reviewed surveillance coverage records of ventilation checks interviewed RP management regarding plant areas with the highest exposure potential to workers and ALARA efforts taken in those areas.
Instrument Calibration and Surveys (IP Sections 02.07, 02.08, 02.14, 02.15)
The inspectors reviewed licensees procedures and documentation for RP instrument calibration, radiation surveys, contamination control measures; use of radiation detecting instruments and equipment and interviewed licensee staff to verify compliance with 10 CFR 20.1501 and 70.24, 20.1902, 20.2103 and Chapter 5 of the license application. Specifically, the inspectors performed the following activities:
11 Instrument and Equipment/Calibration (IP Sections 02.07 & 02.08) reviewed ROP 059 Calibration of the Sirius-4AB and Argos 5 AB Contamination Monitors and did a walk down of the Argos 5 AB reviewed Hand and Foot Operability Check Log per ROP-01-032-2 discussed Layered Process Audits of the log with HP Team Manager interviewed HP Team Manager about calibration about Sirius-4AB and ARGOS 5AB hand and foot monitors interviewed HP Team Manager about calibration of frisking instruments reviewed ROF-01-062-1 Daily Step Off Pad Change Room Frisking Instrument Check sheet walkdown of Step Off Pad areas to verify friskers and hand and foot monitors are calibrated in accordance with site procedure reviewed calibration logs for rad waste assay detection equipment Radiation Surveys & Contamination Control (IP Sections 02.14 & 02.15) observed radiation survey of the four step off pads reviewed ROP-05-014, "Performing Contamination Surveys of the Westinghouse Facility," Rev. 35 interviewed HP technician during walkdown of step off pads contamination survey interviewed HP Team Manager about contamination surveys Postings and Labeling (IP Sections 02.09, 02.10, 02.16)
The inspectors observed the posting and labeling of radiation areas, radioactive material storage areas, radioactive containers, and control of licensed sealed sources to verify compliance with 10 CFR 20.1902 and 20.1904, 20.1905, 20.1903 and Chapter 5 of the license application. Specifically, the inspectors performed the following activities:
Posting/ Container Labeling (IP Sections 02.09 & 02.10) reviewed postings for radiation areas, contamination areas, airborne radioactive material areas:
reviewed radiological postings procedure RA-213, Revision 9 observed the exemption to the labeling requirement for packages and containers that contain radioactive material to verify compliance with Sections 5.2.36 and 12.2.2 of the license application. Specifically, the inspectors observed a sign bearing the legend, "EVERY CONTAINER OR VESSEL IN THIS AREA MAY CONTAIN RADIACTIVE MATERIAL" was posted at each entrance to areas for buildings where radioactive materials are used or stored Sealed Sources (IP Section 02.16) walked down sealed source storage area to verify secure storage and proper labeling of sealed sources interviewed rad engineer regarding sealed source storage and reviewed leak testing records for 2023 and 2024 Posting of Notices (IP Section 02.11)
12 The inspectors observed NRC Form 3 and Posting of Notices to verify compliance with 10 CFR 19.11 and 10 CFR 21.
Access Control (IP Section 02.12)
The inspectors reviewed the licensees access control measures for radiation areas to verify compliance 10 CFR 20.1502(a)(4), 20.1601, 20.1602, and Chapter 5 of the license application. Specifically, the inspectors conducted the following activities:
interviewed licensee staff to verify that there are no high radiation or very high radiation areas on site performed walk downs of change rooms and step off pads at access points between the contaminated and uncontaminated sides Licensed Material Control (IP Section 02.13)
The inspectors observed the licensees measures to secure stored material and control and maintain constant surveillance of licensed material not in storage to verify compliance with 10 CFR 20.1801, 20.1802. Specifically, the inspectors:
observed storage of SNM in vaults and verified they were locked interviewed licensee staff regarding control and storage of licensed material Dose Assessment Program (IP Sections 02.17, 02.22)
The inspectors interviewed licensee staff and reviewed records and calculations related to the licenses assessment and assignment of doses to workers to verify compliance with 10 CFR 20.1201, 20.1204, 20.1207, 20.1208, 20.1502(b), 20.2104, 20.2106 and Chapter 5 of the license application. Specifically, the inspectors:
interviewed licensee staff regarding personnel dose tracking system observed dose tracking software and reviewed selected dose records for 2023 and 2024 reviewed Prospective Analysis - Monitoring Requirements for 2024 interviewed licensee staff regarding internal dose assessment methodology conducted interviews and reviewed electronic records of licensee time-in-area tracking system reviewed daily calibration records for in-vivo lung counter reviewed NRC Form 5 for four employees Dosimetry Program (IP Sections 02.19, 02.20, 02.21)
The inspectors interviewed licensee staff and reviewed the implementation and documentation of the internal and external dosimetry programs including bioassay and use of dosimetry in the field to verify compliance with 10 CFR 20.1501(d), 20.1502(a),
20.1502(b), 10 CFR 20.2103(b)(3), and Chapter 5 of the license application. Specifically, the inspectors performed the following:
13 Bioassay Program & Whole Body Counting (IP Section 02.19 & 02.20) reviewed licensee procedures relevant to the bioassay program, as listed in the Documents Reviewed Section of this report interviewed licensee staff regarding implementation of the bioassay program reviewed electronic records of in vitro program performed walkdown of in-vivo lung counter reviewed electronic records of annual in-vivo lung scans for four employees reviewed QC records for in-vivo lung counter reviewed daily calibration records for lung counter Dosimetry (IP Section 02.21) interviewed licensee staff regarding personnel dosimetry program implementation observed dosimeters being worn by licensee staff during walkdowns reviewed NVLAP accreditation certificate for the dosimeter processors used by the licensee reviewed RA-206, "Personnel Dosimetry Program" Rev. 17 reviewed a declared pregnancy package and observed dose record to verify no regulatory limits were exceeded INSPECTION RESULTS WER (Closed)
EN 57152 Contaminated injured worker WER 07001151/2024-004-00 88030
==
Description:==
On May 30, 2024, a Westinghouse employee was performing a flush on the Conversion Line 3 Decanter following completion of an acid wash. During this process the employee inadvertently stepped on a catch pan containing a small quantity of nitric acid which splashed onto the employees right leg. The employee instinctively reacted by grabbing their coveralls and pulling them up to visually inspect their leg which resulted in chemical exposure to their left hand. Appropriate treatment for exposure to nitric acid was provided by on site medical response staff. As a precautionary measure, the employee was transported to an offsite medical facility. Per procedure, the employees leg and hand were wrapped in plastic, and the employee was transported to an offsite medical facility accompanied by plant health physics personnel for evaluation. The licensee reported this event to the NRC as EN 57152 on May 30, 2024; and submitted their 30-day follow-up report dated June 28, 2024 (ADAMS Accession Number ML24180A249), in accordance with 10 CFR 70.50. This event was also entered into the licensees corrective action program.
The inspectors reviewed licensee records to verify that the potential spread of contamination was minimized by wrapping contaminated areas in plastic prior to transport by ambulance and that a licensee HP technician accompanied the worker in the ambulance in accordance with licensee procedures. Smear samples taken at the site, ambulance, and hospital confirmed that smearable contamination was below the licensees free release limits and there was no spread of contamination.
The Written Event Report 07001151/2024-004-00 was reviewed and no violations of NRC requirements were identified. This item is considered closed.
EXIT MEETINGS AND DEBRIEFS
14 The inspectors verified no proprietary information was retained or documented in this report.
On October 10, 2024, the inspectors presented the Transportation and Radiation Protection inspection results to Roy Stutts and other members of the licensee staff.
On November 21, 2024, the inspectors presented the Operational Safety inspection results to Roy Stutts and other members of the licensee staff.
15 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Corrective Action Documents IR 2024-3103 Missed LR230 Tote During Offload 03/21/2024 Low-Level Radioactive Waste Flowchart 2022-2055 Straight Bill of Lading - Original - Not Negotiable for shipment 0857-01-0247 07/18/2023 2022-2214 Straight Bill of Lading - Original - Not Negotiable for shipment CPWU2986325-269 11/15/2022 2024-2088 Straight Bill of Lading - Original - Not Negotiable for WS-55938-0-322 03/05/2024 2024-2194 Straight Bill of Lading - Original - Not Negotiable for shipment ISEU100028-314 06/25/2024 DHEC 802 South Carolina Department of Health and Environmental Control - Radioactive Waste Shipment Prior Notification and Manifest form for shipment ISEU100028-314 06/04/2024 DHEC 802 South Carolina Department of Health and Environmental Control - Radioactive Waste Shipment Prior Notification and Manifest Form for shipment WS-55938-0-322 02/22/2024 DHEC 802 South Carolina Department of Health and Environmental Control - Radioactive Waste Shipment Prior Notification and Manifest Form for shipment ISEU100014-307 DHEC 802 South Carolina Department of Health and Environmental Control - Radioactive Waste Shipment Prior Notification and Manifest form for shipment 0857-01-0247 07/12/2023 Form 540 -
Uniform Low-Level Radioactive Waste Manifest Shipping Paper 0857-01-0247 CPWU-2986325-269 ISEU100028-314 WS-55938-0-322 ISEU100014-307 86740 Miscellaneous Form 541 -
Uniform Low-Level Radioactive Waste Manifest ISEU100014-307, WC-55938-0-332, ISEU100028-314, CPWU2986325-269, 0857-01-0247
16 Inspection Procedure Type Designation Description or Title Revision or Date Container and Waste Description LR-2024-1605 NFS Data Sheet for LEUN Shipment 09/25/2024 LTR-LCPT-22-24 10 CFR 71.95 report addressing an uninstalled leak test port bolt found in a heeled Liqui-Rad transport unit package at the customer site.
01/06/2023 LTR-LCPT-24-10 10 CFR 71.95 report regarding a disengaged 2-inch ball lock pin in a heeled UX-30 package 04/15/2024 NRC Form 741 XTI to YLM 669 LEUN Nuclear Material Transaction Report 09/26/2024 Order 4709960 Bill of Lading for LR-230 Shipment 09/25/2024 Shipping LLRW Shipping Low-Level Radioactive Waste training documents TAF-502-1 Document Rework Performed on Traveller by Newington 05/24/2022 WBN-24-347 TVA Shipping Ticket 10/08/2024 CF-75B-018 Traveller Refurbishment Verification Checklist for TS391 Rev. 10 CF-75B-019 Traveller Lifetime Record for TS391 Rev. 1 Operability Evaluations CF-75B-020 Traveller Shipping Package Recertification for TS403 09/07/2023 CF-75B-020 Traveller Shipping Packaging Recertification Rev. 0 CF-75B-117 Fuel Assembly Shipping Packaging Inspection Checklist for TS445 10/09/2024 CF-85-002 Radioactive Material Vehicle Dispatch Checklist Rev. 18 TR-100 Shipment of Radioactive Materials General Guidance for Regulatory Compliance Rev. 18 TR-101 Receipt of Radioactive Materials Rev. 8 Procedures TR-225 Refurbish Traveller Shipping Package Rev. 27 2024-0245 Radioactive Shipment Smear Results 10/04/0224 Radiation Surveys ROF-02-008-3 Surveys of Outgoing Shipments of Radioactive Materials for CAO 2024-0245 10/04/24 LCPT 2107 Assessment of Packaging Support Activities 11/22/2021 LCPT 2306 LR-230 Packaging Touch Up 07/27/2023 Self-Assessments LCPT-21-07 Nuclear Fuel Transport Assessment of Fuel Packing Area Activities 11/22/2021
17 Inspection Procedure Type Designation Description or Title Revision or Date WEC-2022-54 Audit Entry Design, Fabrication, Testing and Maintenance of Radioactive Material Transportation Packagings 12/09/2022 WEC-2023-19 Audit Entry Activities related to packaging for which Westinghouse is the 10 CFR 71 certificate holder and which is used in the transport of nuclear fuel assemblies 01/19/2023 Shipping Records WS-55938-0-322 Waste Manifest to US Ecology 05/01/2024 Corrective Action Documents IR 2023-7862, 2023-7881, 2024-5872, 2024-11078, 2024-12227 Operational Safety Related Corrective Action Documents Various CSE-10-A Criticality Safety Evaluation for the ADU Rod Area Rev. 8 CSE-10-B Criticality Safety Evaluation for Product Assurance Rod Inspection Rev. 10 CSE-10-C Criticality Safety Evaluation for the Zirc Fines Vacuum Rev. 3 CSE-11-A Criticality Safety Evaluation for Uranium Scrap Cage Dissolver Rev. 9 CSE-11-B Criticality Safety Evaluation for Uranium Scrap Cage Precipitation Rev. 9 ISA-10 ADU Fuel Rod Area Rev. 19 ISA-11 Scrap Uranium Processing System Rev. 18 PSEDoc-0005652 Filter Press Hood (VH-1058) Passive Engineered Drain Holes Rev. 0 Engineering Evaluations PSEDoc-0007462 Fuel rod soft handling system accumulation check Rev. 0 CA-002 Columbia Plant Electronic Training and Procedure System (ETAPS)
Rev. 70 CA-007 Corrective and Preventive Action Rev. 54 CA-220 Safety Basis Qualification Training Rev. 16 MCP-108000 Preventive Maintenance Rev. 24 MCP-750353 General Operating Procedure - Fuel Rod Area Rev. 57 MOP-735306 Rod and Channel Handling for the Fuel Rod Storage Area Rev. 53 MOP-735505 Criticality Control Rev. 11 MOP-750287 Fuel Tube and Rod Handling Rev. 51 88020 Procedures MOP-750929 Use and Servicing of Ruwac (Zirc) Vacuum Rev. 4
18 Inspection Procedure Type Designation Description or Title Revision or Date MOP-758878 Rod Area Cleanout for Contract/Enrichment Change Rev. 46 MOP-961210 Scrap Fuel Rods and Recover Pellets Rev. 47 QCI-928110 General Fuel Rod and Tube Handling Requirements and Guidelines Rev. 30 RA-108 Safety Significant Controls Rev. 41 TA-500 Columbia Manufacturing Plant Configuration Control Rev. 43 EHS AUDIT 12 ISA Compliance Audit 08/08/2024 Self-Assessments EHS AUDIT-24-8 Regulatory Component Audit for Configuration Management, Audits and Records Management 08/02/2024 Dispatch
- 255253 SI-Safety, Scrap Cage Filter Press Plate Inspection - 52 Week OM 06/03/2024 Dispatch
- 268232 SI-Safety, DI Water RPZ Assembly Verification - 52 Week PM 08/05/2024 Work Orders Dispatch
- 286217 SI-Safety, Scrap Cage Filter Press Hood Visual Inspection -
13 Week OM 11/07/2024 IR-2024-0912 Int EHS Audit 24-10 08/27/2024 IR-2024-2772 RB UF6 Gas Release in UF6 Bay at Conversion Line 2 03/15/2024 IR-2024-3443 RB UF6 Release 03/29/2024 IR-2024-9013 Int EHS Audit SFIs 08/27/2024 Corrective Action Documents IR-2024-9237 Ext EHS Audit - Dosimetry Services 09/03/2024 LTR-EHS-24-09 Annual Radiation Protection Program Review 01/29/2024 LTR-EHS-24-35 Annual ALARA committee Meeting Minutes 06/05/2024 LTR-EHS-24-36 CY 2024 1st Quarter ALARA Report 06/18/2024 LTR-EHS-24-45 2024 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents 08/12/2024 Miscellaneous LTR-EHS-24-54 CY 2024 2nd Quarter ALARA Report 09/23/2024 COP-831012 Operation of Assay 2 Rev. 26 RA-203 General HP Rules and Recommendations Rev. 34 RA-204 Bioassay Program Rev. 16 RA-206 Personnel Dosimetry Program Rev. 17 RA-217 Personnel Monitoring Requirements Rev. 18 88030 Procedures RA-225 Control of Radiation Dose and Chemical Exposure to the Rev. 2
19 Inspection Procedure Type Designation Description or Title Revision or Date Embryo/Fetus RAF-125-14 HP Technician Radiation Protection Training Checklist Rev. 9 RAF-125-21 Environment, Health and Safety Health Physics Operations Manager Training Checklist Rev. 3 RAF-125-27 Environment, Health and Safety Health Physics Operations Team Manager Training Checklist Rev. 1 RAF-125-6 EH&S Radiation Protection Engineer/Analyst Training Checklist Rev. 6 ROP-01-032 Source Checks for Radiation Survey/Monitoring Instruments 12/7/23 ROP-01-059 Calibration of the Sirius-4AB and Argos 5 AB Contamination Monitors 10/29/2020 ROP-03-002 Personnel Exposure System - Guide 08/09/23 ROP-03-002 Personnel Exposure System - Guide Rev. 08 ROP-04-007 Performing In-vivo counts Rev. 16 ROP-05-062 Radiation Survey of Ventilation Equipment Rev. 24 ROP-05-46 Inventory and Leak Testing of Sealed Sources Rev. 14 RA-120-24 Decontamination of Potentially Contaminated Injured Personnel Rev. 1 Radiation Surveys ROP-05-065 Personnel Contamination Event Response and Over Checks Rev. 15