ML20247K799
| ML20247K799 | |
| Person / Time | |
|---|---|
| Site: | 05000083 |
| Issue date: | 03/27/1989 |
| From: | Vernetson W FLORIDA, UNIV. OF, GAINESVILLE, FL |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20247K803 | List: |
| References | |
| NUDOCS 8904050323 | |
| Download: ML20247K799 (2) | |
Text
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o NUCLEAR ENGINEERING SCIENCES DEPARTMENT N0 clear Reactor Facility Unimrsity of F!orida NUCLEAR REACTOR BUILDING Colnevale.Flot6da 32411 Phone (904) 3921429.Teles $4330 March 27,1989 Director Office of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, D.C. 20555 Re: University of Florida Training Reactor (UFTR)
Facility License: R-56; Docket No. 50-83
Dear Sir:
Enclosed is an updated proposal intended to meet the requirements of 10 CFR 50.64(c)(2).
Except for scheduling, this proposal is essentially unchanged from that i
originally submitted with a cover letter dated March 26,1987 and later revised as to its schedule pursuant to a request from the NRC Project Manager Theodore Michaels dated t
April 17,1989. This revised schedule was submitted with a cover letter dated May 14,1987.
It is also essentially unchanged from the updated proposal submitted with a letter dated March 22,1988 except for the schedule.
The written proposal outlines how the R-56 licensee intends to meet the requirements of 10 CFR 50.64 Paragraph (b)(2) to include certification that funding for conversion has now been received through the Department of Energy for the first phase of the project and a tentative schedule for conversion based upon availability of replacement fuel acceptable to the Commission and upon consideration of the availability of additional funding, shipping casks, implementation of arrangements for the available financial support and allowing for commitments of reactor usage. The schedule has slipped significantly due to delays in work to qualify the SPERT fuel and due to delays in safety analysis as we awaited code implementation and availability of graduate students for the work. The delays in work with the SPERT fuel were most significant as the fuel had to be moved, under the SNM-1050 license, and then various license changes approved prior to initiation of the qualification work which has been lengthy and subject to several equipment (x-ray machine) failures. Work is expected to progress more rapidly now as SPERT fuel qualification efforts are nearly complete and the code methodology for safety analyses is being implemented and tested.
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Letter to Director, NRC March 27,1989 If further information is needed, please advise. Thank you for your consideration.
Sincerely, 1
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> J' William G. Vernetson Director of Nuclear Facilities WGV/Imc P.M. Whaley 7ng A/&.7du4I 3/.27/<Pf Reactor Safety Review Subcommittee Nhtitry Putilic V
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