ML19254D880
| ML19254D880 | |
| Person / Time | |
|---|---|
| Site: | 07106581 |
| Issue date: | 10/18/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Nechodom W SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| References | |
| NUDOCS 7910300284 | |
| Download: ML19254D880 (2) | |
Text
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UNITED STATES f d M. - [)X',,o E%
NUCLEAR REGULATORY COMMISSION J
i WASHINGTON, D. C. 20555
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GCT 131373 FCTC:RH0 71-6581 Exxon Nuclear Comp'any, Inc.
ATTN:
Mr. W. S. Nechodom 2955 George Washington Way Richland, WA 99352 Gentlemen:
This refers to your application dated June 15, 1979, as amended, requesting renewal and an amendment to the approval to deliver the Models Nos. 51032-1 and 51032-la packagings to a carrier for transport.
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 information will be provided. The additional information requested by this letter should be submitted in the form of revised pages to the consol-ilated 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, Y ks Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety
Enclosure:
As stated 1238 047 7910800 2 O
EXXON Nuclear Company, Inc.
Models Nos. 51032-1 and 51032-la Packagings 0CT 181979 Encl to ltr dtd:
Structural 1.
Provide a listing of the licensing drawings for each of the two models of the packagings.
Indicate the Drawing No., Sheet No., and Revision No.
for each drawing.
2.
Provide a copy of each licensing drawing.
Each drawing should indicate the Drawing No., Sheet No., Revision No., and the Model No. of the
- packaging.
T' e present drayings are not legible, do not indicate all safety features, contain extraneous material, and are unorganized (number of drawings should be reduced to a minimum).
3.
Identify the changes made to any of design features shown on the revised drawings from the currently approved design and show that the' modified design meets the requirements of 10 CFR Part 71.
Criticality 1.
Provide specific details of each experimental array used to support the calculational methods in the criticality safety analyses.
Delineate all simplifying assumptions made and adjustments made to obtain the reported results.
2.
Provide appropriate copies (3) of References 4 and 6.
1238 043