ML20206N783
| ML20206N783 | |
| Person / Time | |
|---|---|
| Site: | 07109270 |
| Issue date: | 05/07/1999 |
| From: | Thompson T NAC INTERNATIONAL INC. (FORMERLY NUCLEAR ASSURANCE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-L22452, NUDOCS 9905180065 | |
| Download: ML20206N783 (2) | |
Text
~D-9230 s.
ANAC Atlanta corporate Headquarters INTERNATIONAL Ilo'rc%d@5a"iL92 770-447-1144 Fax 770-447-1797 www.nacintLcom May 07,1999 U. S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, Maryland 20852-2738 Attn: Document Control Desk
Subject:
Plan for Submittal of a Revision of the UMS* Universal Transport Cask
References:
1.
Safety Analysis Report for the UMS* Universal Transpon Cask *, Docket No.
71-9270, TAC No. L22452, April 30,1997, NAC International.
2.
Supplemental Information Submittal in Support of the UMS* SAR and TSAR, December 24,1997, NAC International 3.
Revised Pages - UMS* SAR and TSAR Supplemental Information, April 23,-
1998, NAC International In accordance with the recent telecon discussions between the NRC and NAC International (NAC),
the following information is provided relative to NAC's plan for submittal of a revision of the UMS*
Universal Transpon Cask
- SAR (References 1, 2, & 3).
1 NAC completed a successful series of three, confirmatory 30-foot drop tests of a quarter-scale model g
of the UMS* Universal Transport Cask
- package in mid-April 1999 at Oak Ridge National Laboratory. In conjunction with these drop tests, a series of static compression tests will be performed on a UMS* quarter-scale model impact limiter in mid-May 1999. The results of the UMS* quarter-scale model. tests will be incorporated into a revision of the UMS* Universal Transpon Cask
- SAR that will be submitted to the NRC by June 18,1999.
In addition to the UMS* quaner-scale model test results, some nonstandard fuel-related and nonfuel-related components specific to the Maine Yankee Decommissioning Project will be included as additional authorized contents in the UMS* SAR revision. Those nonstandard components include:
Greater Than Class C (GTCC) waste, neutron sources, consolidated fuel assemblies, fuel assemblies with some replacement rods (stainless steel dummy rods or low-enriched fuel rods), fuel assemblies with the burnable poison rods replaced with hollow ziracalloy rods, fuel assemblies with Control Element Assemblies (CEAs) inserted, fuel assemblies with an in-core instrument thimble assembly insened in the center guide tube, fuel assemblies with variable radial enrichment and axial blankets, fuel assemblies with missing fuel rods, and fuel assemblies that do not fall within the design cool-time and burn-up/ enrichment curves (up to 50 GWD/MTU). All of these proposed additional contents _will be shown to be bounded by the UMS* design parameters.
9905180065 990507 F
C-POR p
ED990307. doc ATL ANTA J W A S HIN G T O N Ntw YORK Z URICH LONDON TOKvo M oscow S AN }DSE AIKEN
I a
U.S. Nuclear Regulatory Commission May 07,1999 Page 2 If you have any comments, questions, or require additional information, please contact me or Mr.
Steve Whitsett at (770) 447-1144.
Sincerely, 19%
Thomas C. Tho pson Director, Licensing & Competitive Assessment Engineering & Design Services 1
ED990307. doc -
k-