ML24110A050

Westinghouse Columbia Fuel Fabrication Facility - Integrated Inspection Report 07001151/2024001

ML24110A050
Person / Time
Site:	Westinghouse
Issue date:	04/22/2024
From:	Michel C NRC/RGN-II/DFFI
To:	Pope A Westinghouse
References
IR 2024001
Download: ML24110A050 (9)

Text

Annette Pope Site Director, Columbia Fuel Fabrication Facility Westinghouse Electric Company 5801 Bluff Road Hopkins, SC 29061

SUBJECT:

WESTINGHOUSE COLUMBIA FUEL FABRICATION FACILITY - INTEGRATED INSPECTION REPORT 07001151/2024001

Dear Annette Pope:

This letter refers to the U.S. Nuclear Regulatory Commission (NRC) inspection activities conducted from January 1, 2024, to March 31, 2024, for the Westinghouse Columbia Fuel Fabrication Facility. On February 8, 2024, the NRC inspectors discussed the results of this inspection with you. The results of this inspection 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 Projects Branch 2 Division of Fuel Facility Inspection Docket No. 07001151 License No. SNM-1107

Enclosure:

As stated cc w/ encl: Distribution via LISTSERVApril 22, 2024 Signed by Michel, Eric on 04/22/24

ML24110A050

SUNSI Review x Non-Sensitive x Publicly Available x Sensitive Non-Publicly Available

OFFICE RII/DFFI RII/DFFI RII/DFFI NAME T. Vukovinsky J. Raudabaugh E. Michel DATE 4/22/2024 4/22/2024 4/22/2024

U.S. NUCLEAR REGULATORY COMMISSION Inspection Report

Docket Number: 07001151

License Number: SNM-1107

Report Number: 07001151/2024001

Licensee: Westinghouse Electric Company

Facility: Westinghouse Columbia Fuel Fabrication Facility

Location: Hopkins, SC

Inspection Dates: February 5, 2024, to February 8, 2024

Inspectors: N. Peterka, Sr. Fuel Facility Project Inspector

Approved By: Eric C. Michel, Chief Projects Branch 2 Division of Fuel Facility Inspection

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Westinghouse 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

None.

2 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

88015 - Nuclear Criticality Safety

The inspectors evaluated selected aspects of the licensees Nuclear Criticality Safety program to verify compliance with selected portions of 10 CFR 70, including 70.24, 70.61, 70.62, Chapter 6, Nuclear Criticality Safety (NSC) Program, of the facilitys license application, and applicable licensee procedures.

Criticality Analysis (IP Section 02.01)

The inspectors interviewed licensee staff and reviewed nuclear criticality safety evaluations (CSEs), and associated assumptions and calculations, to verify compliance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors interviewed licensee staff and reviewed the following CSEs:

• CSE-2-A, "Criticality Safety Evaluation for Uranyl Nitrate Bulk Storage," Rev.

12, including review of what-if analysis, normal, credible abnormal, and non-credible accident sequences.

• CSE-3-G, "Criticality Safety Evaluation for the Uranium Hexafluoride (UF6)

Cylinder Vaporization and Condensate System," Rev. 11, including the review of selected accident sequences involving a release of UF6 from the vaporizer to the UF6 Bay Trench and potential backflow scenarios due to misdirected UF6 flow. The inspectors conducted walkdowns to verify that the inputs/outputs to and from cylinder vaporization, and selected controls on those inputs/outputs, were consistent with the CSE.

Criticality Implementation (IP Section 02.02)

The inspectors selected engineered and administrative controls from the licensees integrated safety analysis (ISA) summary to verify proper implementation through a review of process and system descriptions, plant walkdowns, and staff interviews to verify

3 compliance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors interviewed licensee staff and reviewed the following controls, and their management measures, associated with the CSEs listed above and other selected areas:

• ADUVAP-141, a passive engineered control to ensure geometry control in the vaporization trench via concrete blocks, and associated inspection records

• ADUVAP-904, an active engineered control to control moderator in the UF6 vaporizers in the event of a UF6 leak by shutting of steam supply via a conductivity probe, and associated inspection records

• ADUVAP-933, a passive engineered control to prevent UF6 backflow to a cold UF6 cylinder via a three-way valve, and associated inspection records

• UN-115/116, an active engineered control to limit the concentration of uranyl nitrate entering the bulk storage tanks via dual gamma monitors and block valves, and associated inspection records

Criticality Operational Oversight (IP Section 02.03)

The inspectors assessed the NCS staffs oversight of plant operators, procedures, and operations of systems involving special nuclear material to verify compliance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors performed the following activities:

• interviewed NCS engineering staff concerning criticality hazards and control methods, including monitoring and control of concentration in the Uranyl Nitrate Bulk Storage Tanks

• reviewed the documentation of selected NCS weekly facility walkthrough assessments (FWAs) performed by the licensee over the last three months

• interviewed vaporization and solvent extraction operators on implementation of administrative controls through the applicable operating procedures for their areas

• reviewed NCS safety training 2024

Criticality Programmatic Oversight (IP Section 02.04)

The inspectors reviewed NCS program procedures, audits, and NCS staff qualifications to verify compliance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors interviewed licensee NCS staff and reviewed the following documents:

• discussed qualification and training status of the NCS staff with NCS management

• interviewed NCS staff concerning the NCS review of changes, including changes to operating procedures that may affect NCS, and changes to the facility

• the most recent revision to licensee procedure RA-313, Criticality Safety Evaluations

4 Criticality Incident Response and Corrective Action (IP Section 02.05)

The inspectors reviewed the licensees criticality accident alarm system (CAAS) and corrective action program (CAP) to verify compliance with 10 CFR 70 and applicable sections of the license application, including section 6.1.8. Specifically, the inspectors observed activities, reviewed documents, and interviewed licensee staff concerning the following:

• reviewed selected issues entered in the CAP pertaining to IROFS and audit findings

• reviewed criticality safety evacuation drill records for 2023

INSPECTION RESULTS

No issues were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On February 8, 2024, the inspectors presented the integrated inspection results to Annette Pope and other members of the licensee staff.

5 DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or Procedure Date 88015 Corrective Action Criticality Safety IR-2023-6574, 2023-8093, 2024-777, 2024-808 Various Documents Corrective Action Program Entries Engineering CN-CRI-07-43 UF6 Cylinder Vaporizer and Condensate System Upsets Rev. 0 Evaluations CN-CRI-08-28 UF6 Bay Trenches Rev. 1 CSE-2-A Criticality Safety Evaluation for Uranyl Nitrate Bulk StorageRev. 12 CSE-3-G Criticality Safety Evaluation for the UF6 Cylinder Rev. 11 Vaporization and Condensate System CSE-4-L Criticality Safety Evaluation for Processing Drum H118 Rev. 0 Procedures CF-83-103 Uranyl Nitrate Tanks Checklist Rev. 13 CN-CRI-20-003 NCS Manual Rev. 8 CN-SB-18 Baseline Integrated Safety Analysis (ISA) and ISA Summary Rev. 5 Handbook COP-810098 UF6 Cylinder Installation and Removal Rev. 59 COP-810099 UF6 Vaporizer Rev. 39 COP-815417 Functional Verification of Safety Significant Controls Rev. 24 Conversion Area COP-836015 Normal Operation of UN Storage Tanks Rev. 39 COP-836038 Verification of Safety Significant Controls Rev. 12 NCS-017 Categorizing Potential Criticality Scenarios and Criticality Rev. 4 Safety Significant Controls RA-313 Criticality Safety Evaluations Rev. 17 Self-Assessments RA-316-1 Nuclear Criticality Safety Checklist for NCS Facility 11/27/2023 Walkthrough Assessments, SOLX Operator RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility 12/18/2023 Walkthrough Assessments, Conversion - Chief Operations and Various Containers RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility 12/18/2023 Walkthrough Assessments, Conversion Operations RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility 12/13/2023 Walkthrough Assessments, URRS Bay Operator Work Orders Dispatch 177729 52 Weeks OM81022 SI-Safety, East/West UF6 Bay Trench 04/27/2023

6 Inspection Type Designation Description or Title Revision or Procedure Date Sump Volume Verification Dispatch 182195 52 Weeks OM85017 SI-Safety Interlocks, Dissolvers 05/24/2023 Dispatch 211750 52 Weeks OM81026 SI-Safety, 3-way valve verification 10/19/2023 Dispatch 217371 52 Weeks OM81202 SI-Safety Items, ADU Line 2 IROFS 11/16/2023

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