ML20175A206
| ML20175A206 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 06/23/2020 |
| From: | Murray S Global Nuclear Fuel |
| To: | Jacob Zimmerman Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| M200089 | |
| Download: ML20175A206 (1) | |
Text
GNi=
Global Nuclear Fuel M200089 June 23, 2020 Jake Zimmerman, Chief Fuel Facility Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards US Nuclear Regulatory Commission ATTN: Document Control Desk Global Nuclear Fuel Scott P. Murray Manager, Facility Licensing 3901 Castle Hayne Road P.O. Box 780 Wilmington, NC 28402 USA T (910) 819-5950 scott.murray@ge.com
Subject:
Request to Withdraw 8 % License "mendment Request and Approve Criticality Safety Methods
References:
(1).
(2)
(3)
(4)
(5)
(6)
(7)
(8)
Dear Mr. Zimmerman:
N~C License SNM-1097, Docket 70-1113 GNF-A License Amendment Request, 10/31/19 GNF-A/NRC Telecom, 11/26/19 Letter, S. Murray to J. Munson (NRC), "NRC Request for Documents, 11/27/19 Letter, J.I. Zimmerman to S. P. Murray, "GNF-A Acceptance Review and Request for Supplemental Information", 2/6/20 Letter, S. Murray to J. Zimmerman, "GNF-A Response to NRC Request for Supplemental Information", 2/27 /20 Letter, J.I. Zimmerman to S. P. Murray, "GNF-A Acceptance Review and R~quest for Supplemental Information", 5/6/20 GNF-A/NRC Telecom, 6/17/20 On October 31, 2019, the Global Nuclear Fuel - Americas, L.L.C. (GNF-A) facility in Wilmington, North Carolina, requested an amendment for NRC license SNM-1097 in order to increase the facility enrichment limit from 5 wt.% to 8 wt.% (Reference_2).
Upo~ further review and additional discussions with NRC, GNF-A has decided to withdraw the amendment request at this time and resubmit it at a laterdate.
As we discussed on November 26, 2019 (Reference 3) and June 17, 2020 (Reference 8), in order to proceed with internal safety bases evaluations, GNF-A hereby requests NRC approval of the current 1 GNF-A nuclear criticality safety analytic methods and validation techniques described in SNM-1097, Chapter 5, Nuclear Criticality Safety, integrated safety analysis hazards and risk assessment methodologies described in SNM-1097, Chapter 3, Integrated Safety Analysis and supplemental reports provided on November 27, 2019 (Reference 4) for use up to 8 wt. %.
Please contact me if you have any questions or would like to discuss this matter further.
Si~ly, au~~.e.!f)~
Facility Licensing
~
cc: M. Bartlett, NRC NMSS DFM L. Pitts, NRC RII DFFI SPM 20-025 r.