ML19309G940

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Forwards Request for Addl Info Re 791017 Request for Renewal of Certificate of Compliance 6639 for Model MH-1A Shipping Package.Response Requested within 30 Days from Date of Ltr
ML19309G940
Person / Time
Site: 07106639
Issue date: 04/04/1980
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Ridihalgh J
EGGERS, RIDIHALGH PARTNERS, INC.
References
NUDOCS 8005080032
Download: ML19309G940 (2)


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UNITED STATES g

g NUCLEAR REGULATORY COMMISSION L

'E WASHINGTON, D. C. 20665

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AP'A o 41980 FCTC: RHO 71-6639 Ridihalgh, Eggers !. Associates ATTN: Mr. John L. Ridthalgh 2112 Iuka Avenue Columbus. 0.9 43201 Gentlemen:

This refers to your consolidated application dated October 17, 1979 requesting renewal of Certificate of Compliance No. 6639 for the Model No. MH-1A shipping package..

In connection with our review, we need the infonnation Identified in 1

the enclosure to this letter.

Please advise us within thirty (30) days from the date of this letter tihen this information will be provided. The additional infonnation requested by.this letter should be submitted in the form of revised pages to the cons 611 dated Safety Analysis Report in order to preserve the continuity of your application.

If,you have any questions regarding this matter, we will be pleased to meet with you and your staff.

Sincerely, Charles E.. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS i

Enclosure:

Request for Additional Information cc w/ enc 1: Dr. Donald M. Ross U.S. Department of Energy Mail Stop E-201 l

l Washington, D.C.

20545 l

t

Enc 1 to ltr dtd: APR 0 4 1980 MODEL NO. MH-1A PACKAGING DOCKET NO. 71-6639 I.

General A.

Drawings 1.

A set of legible consolidated drawings should be provided showing 'only significant safety features (e.g., dimensions.

materials of construction, welds, closures, seals, valves).

2.

Sketches of content structural components, including their adjacent ones, should be inserted in the places where these corroonents are analyzed.

B.

Design Criteria.

1.

Design criteria for content structural components, including fastners (bolts and weldments), should be given; any deviation -

of these criteria from NRC Reg. Guide 7.6 for the components' and ASME Code Class 1 component rules for fastners should be justified. The same also applies to thecother. critical cask components.

i 2.

Stress components should be combined properly in satisfying the design criteria. Note that the combined stress and force expressions used in SAR (e.g., Eqs 119. and 125) should be justified.

3.

Justify that a quasi-static analysis of impact stresses is.

appropriate for evaluating the integrity of_ the Mi-1A package design.

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II. 30-Foot Free Drop (1.7.1)

A.

Stress Analysis See comments in Item 18 above.

i B.

Side / Oblique Drop 1.

The secondary (splash-down) impact effects as functions of impact orientation angle should be. considered.

2.

For the side and top end oblique drop impact cases, justify that the case considered is most critical with respect to the impact limiter / weld / lid bolt stresses. The lid bolt material should be specified and shown in the drawings.

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