ML19209A952
| ML19209A952 | |
| Person / Time | |
|---|---|
| Site: | 07106346 |
| Issue date: | 09/06/1979 |
| From: | Mowry W GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19209A953 | List: |
| References | |
| SHP-1097, NUDOCS 7910050663 | |
| Download: ML19209A952 (4) | |
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CEMERAL AToute COMPANY 1
Po. Box 81608 In rep 7 SAN olEGo. CALIFCANIA 92138 September 6, 1979 Refer To: SHP-1097 guysm Mr. Charles MacDonald, Chief Transportation Branch Divi::; ion of Fuel Cycle and Material Safety U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Certificate of Compliance #6346; Docket #71-6346 Revision to Application Supporting Infor=ation.
References:
(a) GAC letter SHP-959 dated 8/15/78 (b) GAC letter SEP-1034 dated 2/27/79 (c) GAC letter SHP-1046 dated 4/6/79
Dear Mr. MacDonald:
General Atomic Company has made application for revision of the subject lic-ensed shipping package closure.
Subsequently additional submittals have been made in response to requests for additional infor=ation and or certain changes in technical content. This submittal when added to our previous submittals provides a complete and referenceable addendum to the package description, de-sign and supporting safety annlysis.
The submittal wentains:
1.
Instructions for accomplishing revision C to Addendum I.
2.
The new pages for insertion in the Addendum.
3.
Suggested new wording for the Certificate of Compliance.
Please note that new or revised text, in 2 or 3 above, has been marked with a ruled right-hand margin.
Attachment I gives detailed instructions for inserting Revision C into the CADR-55 Addendum I.
Attachment II contains the new pages and drawings which upon insertion into Addendum I as revised by A & B become Addendum I, Revi-sion C.
The information supplied in the attachment 17_ pages (Revision C) relate pri-marily to leak t'esting procedures, additional statements about the maintenance program and new drawings submitted to improve the clarity of the alternate closure system component interrelationship. Also supplied is a modified de-sign criteria su.=2arv table.
i s
1105 079 7910050(Q
s Charles MacDonald SHP-1097 Attachment III contains a suggestion for revised wording for the Certificate of Compliance. We believe incorporation of the new wording better describes the package features and the referenced matters supporting the Certificate.
We look forward to your early considerstion of this infor=ation with that previously provided and your issuance of the revised certificate allowing use of the alternate lid closure system.
Very truly yours, Y
William R. Motry Licensing Administrator Nuclear Materials Control Divisica WRM:hes Attachment I - Instructions for Revision C to CADR-55 Addendum I.
II - New pages for Revision C.
III - Suggestions for Revised COC wording.
1105 080
i i
e ATTACIDfENT 1 GADR-55 ADDENDLH I - Revision C Instructions This provides the instructions necessary to incorporate Revision "C" changes into the CADR-55 Addendum I, previously revised by Revision "A" and Revision "B".
The change details are given below. All added pages and drawings are labeled Pavision C.
1.
Addendum I Cover Sheet.
Remove: Revision B cover sheet Add: Revision C cover sheet 2.
Table of Contents Remove: Page 1 Add: Page 1 3.
Introduction Remove: Page 1-1 Add: Page 1-1 4.
Section I Remove: Pages I-4, I-5, I-8.
Add: Pages I-4, I-5, I-Sa, I-8, I-9, I-10, I-11, I-12.
5.
Section II Remove: Page II-2 and org. 90SK5592 Add: Page II-2 and dvgs. (3) GADR-55-2-1, 55-2-2 and 55-2-3.
6.
Section V Remove: Pages 5-2a through 5-2h Add: Pages 5-2a through 5-2d I105 081
s ATTACEMENT III Suggestion for Certificate revised wording Section 5(a)(2) Description.
The cask is cylindrical, 208" long and 28" in diameter for most of its length except for the top flange which is 11-3/8" thick and 31" in diameter.
The cask utilizes stainless steel encased depleted uranium as primary shield-ing. The cask's inner container, for fueled contents, has a cavity of 16-5/8" in, dia. x 187-5/8 in. long. The fuel contents are hexagonal crocs section elenents and are loaded into the cask's inner container, six in one column. The cask may utilize either of two closure configurations. One closure system utilizes an outer cover consisting of 3-3/4" stainless steel together with depleted uranium, 2-1/4" thick, and an inner lid of 2-1/4" thick stainless steel. The alternate closure system utilizes 4.75" thick alloy steel as the outer cover and an inner lid consisting of 1.3" stain-less steel and 4.14 inches of depleted uranium. The alternate closure sys-tem requires the use cf an impact limiter at the top during transport. The cask's total weight, including content, is approximately 46,000 pounds. The impact limiter weighs approximately 1060 pounds.
5(a)(3) Drawings The packaging is constructed in accordance with National Lead Co.
Drawings Nos. 40065D, Rev.1; 70085F, Rev. 5; 70086F, Rev. 7; 70094F, Rev. 5; 40155D, Rev.1; 70105F, Rev. 5; 70104F, Rev. 5; and 70296F, Rev. 2.
The packaging with its alternate closure system utilizes the above drawings except that closures and i= pact limiter are constructed as shown on GAC Drawings GADR 55-2-1, GADR 55-2-2 and GADR 55-2-3.
Section References Add to previous references the fellowing:
Sept. 6, 1979 1105 082
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