ML20003G649
| ML20003G649 | |
| Person / Time | |
|---|---|
| Site: | 07109013 |
| Issue date: | 04/22/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Jarrett R AGRICULTURE, DEPT. OF |
| References | |
| NUDOCS 8104300368 | |
| Download: ML20003G649 (2) | |
Text
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NUCLEAR REGULATORY COMMISSION s
wassmorow, o. c. 2 cess APR 2 21981 FCTC: RHO
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71-9013 R
'I IS8I U. S. Department of Agriculture Dg%
ATTN: Mr. Robert D. Jarrett
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Radiological Safety Staff Af Beltsville, MD 20705
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6 Gentlemen:
This refers to you.* spplication dated February 5,1981 requesting approval of the Model Nos. 520 and 521 packagings.
In connection with our review, 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 infomation will be provided. The additional infonnation requested by this letter should be submitted in t% fom of revised pages to the safety analysis. If you have any questions regarding this matter, we would be pleased to meet with you and your staff.
Sincerely, 5
N I
charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS
Enclosure:
As stated I
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Model Nos. 520 and 521 Docket No. 71-9013 1.
Provide legible drawings which show materials of construction, dimensions, welds, and closures significant to safety.
These values and materials should correspond to those described in the safety analysis report and the packaging as fabr!caced.
2.
Shear strtsses should be included in the tie-down stress calculations.
3.
Puncture analysis should be revised to take into account the minimum elongation of 21-25% for ASTM A516, Grade 60 material. The formula used in the analysis has a requirement of greater than 40% ultimate elongation for the equation to be valid.
4.
During a flat 30-foot drop impact on the cask end, the lead is subject to high flow stress due to impact. Demonstrate that the outer carbon steel shell will stay intact under such a high internal pressure during impact.
5.
Provide reference or derivation for the equation used for the contact area calculation in the corner drop. Revise subsequent calculations and determine the effect on the packaging.
6.
Demenstrate that the effectiveness of the thermal' shield is not sionificantly reduced after the 30-foot drop and puncture tests.
Show that no significant quantity of lead will melt during the hypothetical accident sequence.
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