ML20053E453
| ML20053E453 | |
| Person / Time | |
|---|---|
| Site: | 07105608 |
| Issue date: | 05/27/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Ross D ENERGY, DEPT. OF |
| References | |
| NUDOCS 8206080171 | |
| Download: ML20053E453 (3) | |
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hbd (f191e d6 3% d MAY 2 71982 FCTC:WHL 71-5608 U.S. Department of Energy ATTN: Dr. Donald M. Ross MS-E-201 Washington, DC 20545 Gentlemen:
This refere to the DOE letter dated February 14,1978, requesting our roview of the Model No. BR 63-0101 package.
In connection with our review of this package, we need the information identified in the enclosure to this letter.
Please advise us within thirty (30) days from the date of this letter when this infonnation will be provided.
Sincerely.
Originni Signed by CIIARLES E. MACDONALD Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS
Enclosure:
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U.S. Department of Energy Model No. BR 63-0101 Package (71-5608)
Encl to ltr dtd: MAY 2 71982 Drawings The drawings provided in the SARP are of poor quality and are difficult to read. Provide better quality copies of drawings BR 63-0101-1-5, BR 63-0101-2-4, BR 63-0101-7-5, BR 62-0102-0-4, and BR 62-0103-0-4.
The drawings should be in sufficient detail to show all safety related components with regard to dimensions, materials, and welds. Also, show details of closure bolts, the gasket, and the general arrangement of fuel basket on the drawing.
Structural 1.
The capacity of the lifting yoke and the base pad should be based i
on the weld strength. Show that the 3/8" fillet welds have sufficient strength to sustain the lifting force.
2.
Since the cask lifting yoke acts as a pivot for the tie-down cables, show that the lifting yokes have adequate welds to withstand the vertical component of the tie-down cable forces.
3.
Show the derivations of the drop energy vs. corner lead deformation curve. (Figure 7 of SARP, November 1977).
4.
Provide an analysis to show the ability of the welds between the cask outer shell and the cask base plate to withstand the inpact force when the cask is dropped on its bottom corner.
5.
Provide an analysis to show the ability of the closure bolts to hold the contents in the cask cavity when the cask is dropped on its top corner.
i 6.
Lead settlement and the bulging effects of the cask shells when the cask is dropped on its bottom should be considered.
Containment 1.
Establish a containment criteria based on consideration of the package contents, and normal and accident conditions of transport.
Regulatory Guide 7.4 may be used.
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, 2.
Show that the package satisfies the established containment criteria following normal and accident conditions tests of 10 CFR Part 71.
3.
Establish a test program to ensure adequate containment for each package to be used to transport radioactive materials. Show that the sensitivities and testing schedules are adequate for safe use of the packages. Regulatory Guide 7.4 may be used for periodic testing. For assembly verification it is recomended that a test of sufficient sensit fity to limit the maximum release to a type A quantity in 10 day 3 is useg/g/
, however, a leak test sensitivity greater than lx10 9tm-cm ec, would not be required. The minimum a 10~givity of lx10-sensi atm-cm sec (air at 1 atm and 25'F leaking to atm ambient) as specified in ANSI N14.5 should be met.
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