ML19263B298
| ML19263B298 | |
| Person / Time | |
|---|---|
| Site: | 07105753 |
| Issue date: | 01/08/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Mott W ENERGY, DEPT. OF |
| References | |
| FCTR:WHL, NUDOCS 7901170280 | |
| Download: ML19263B298 (2) | |
Text
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UNITED STATES o,,
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NUCLEAR REGULATORY COMMisslON h
j W ASHINGTON, D. C. 20555
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JAN 0 81979 FCTR:WHL 71-5753 U.S. Department of Energy
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ATTN: Dr. William E. Mott Washington, D.C.
20545 Gentlemen:
This refers to your let'.er dated July 13, 1978, requesting our review of the Model No. ORNL Loop Transport Cask package.
In connection with our review of this package we need the information identified in the enclosure to this letter.
Please advise us when this information will be provided.
Sincerely,
[
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Materials Safety
Enclosure:
As stated cc: DOE, Oak Ridge Operations Office ATTN: Mr. William H. Travis P.O. Box E Oak Ridge, TN 37830 79011799s0
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ORNL LOOP TRANSPORT CASK DOCKET NO. 71-5753 STRUCTURAL Show that the outer mild steel shell components of the package are adequately designed against nonductile failure under the hypothetical accident 30-foot free drop test and the puncture test at low service
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temperature environments.
THERMAL The thermal model does not consider damage that may be experienced following the free drop and puncture tests. Show that the package will provide adequate shielding following all the tests in 10 CFR Part 71.
CONTAINMENT The containment evaluation provided does not demonstrate that the packaging provides adequata containment. Each of the proposed containment vessels should be defined, specified and shown to satisfy an acceptance criteria established to provide safe containment under the normal conditions of transport and accident damage conditions of 10 CFR Part 71. Tests should be developed to demonstrate the adequacy of the containment vessels fol-lowing the tests of 10 CFR Part 71, and to be performed periodically and before each use. These tests should be provided for our review and in-clusion in any NRC approval for this package.
CRITICALITY Protide an analysis which demonstrates the subcriticality of the single package, considering the actual lead reflector built into the package and the contents as optinelly moderated.