ML24179A066

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Enclosure 2 - Open Session Meeting Summary - Public
ML24179A066
Person / Time
Site: Westinghouse
Issue date: 08/13/2024
From:
NRC/NMSS/DFM/FFLB
To:
NRC/NMSS/DFM/FFLB
Shared Package
ML24179A062 List:
References
Download: ML24179A066 (1)


Text

MEETING

SUMMARY

(OPEN SESSION)

Subject:

SUMMARY

OF MAY 16, 2024, PARTIALLY CLOSED PRE-APPLICATION PUBLIC MEETING WITH WESTINGHOUSE COLUMBIA FUEL FABRICATION FACILITY

Date: May 16, 2024

Following introductions by the U.S. Nuclear Regulatory Commission (NRC), and Westinghouse, staff present in-person at the meeting, and a state official online listed in Enclosure 1, Shana Helton of the NRC provided opening remarks. Shana Helton stressed the importance of pre-application meetings. Nader Mamish of Westinghouse in his introductory remarks indicated that Westinghouse anticipates requesting future pre-application meetings to discuss specific subject areas with the NRC staff.

Westinghouse then presented its slides (Agencywide Documents Access and Management System Accession No. ML24134A276). Westinghouse indicated that the objective of this project, referred to as the low-enriched uranium plus (LEU+) project, was to expand their Columbia Fuel Fabrication Facility (CFFF) for the purpose of generating higher enriched uranium (up to 8 weight percent uranium-235) for light water reactors used for generating power. Westinghouse then provided an overview of the LEU+ project. According to Westinghouse, the LEU+ project will not impact the existing CFFF that fabricates fuel enriched up to 5 weight percent uranium-235. The expansion and processes for manufacturing 8 weight percent fuel will require prior NRC approval of a license amendment request for Westinghouses special nuclear material (SNM) license SNM-1107 per the regulations in Title 10 of the Code of Federal Regulations Section 70.72

Westinghouse stated that the LEU+ project will involve conversion of uranium hexafluoride to uranium dioxide, pelleting, manufacturing of burnable absorber rods, uranium recovery, and mechanical processes in the CFFF expansion. They indicated that in contrast to the existing fuel fabrication processes for manufacturing 5 weight percent U-235 fuel, the new LEU+ process will be largely automated.

During the slide presentation, Westinghouse responded to the NRCs questions. The NRC staff asked about Westinghouses experience with the proposed dry uranium hexafluoride (UF6) conversion process since fuel is currently fabricated at the CFFF using the wet UF6 conversion process. They stated that they are leveraging their dry conversion experience at their fuel fabrication facility located in Springfield, United Kingdom. Additionally, the NRC staff asked for clarification regarding single entry access points to control the introduction of 8 weight percent material in the 5 weight percent building and encouraged Westinghouse to consider any impact the addition will have on the accident analysis of the existing fuel fabrication activities at the CFFF.

PRINCIPAL CONTRIBUTORS Diana Woodyatt, NMSS/DFM/FFLB Yawar Faraz, NMSS/DFM/FFLB

Enclosure 2