ML20128D551
| ML20128D551 | |
| Person / Time | |
|---|---|
| Site: | 07001359, 07001703 |
| Issue date: | 06/19/1974 |
| From: | Rouse L US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Preskitt C INTELCOM INDUSTRIES, INC. |
| Shared Package | |
| ML20128D517 | List: |
| References | |
| NUDOCS 8507050139 | |
| Download: ML20128D551 (2) | |
Text
'
. h, V[7 s p,h UNI.'ID STATES ATOMIC ENE.1GY COMMISSION j.**
W ASHINC TON. D.C.
20545 g
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JU.N 19 W4 L:FFR:JCD 70-1359 SNM-1405, Amendment No.1 l
Intelcom Industries Incorporated i
ATTN: Dr. C. A. Preskitt, Vice President Intelcom Rad Tech P. O. Box 80817 San Diego, California 92138 I
Gentlemen:
Pursuant to Title 10. Code of Federal Regulations, Part 70, Special Nuclear liaterial License No. SNM-1405 is hereby amended to authorize the construc-tion and use of a suberitical assembly in accordance with the statements, representations and conditions specified in the licensee's application dated January 24, 1974, except that as a condition of this license amend-ment k,7f of the assembly shall not exceed 0.950.
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All other conditions of this license shall remain the same.
The purpose of issuing this amendment is to enable you to construct the assembly and obtain experimental data to determine the accuracy of your calculations in designing the subassembly. Of particulsr interest to us s.
are the effects of additional shielding or reflectors, measured radiation levels, function of fail-safe features, the effect of accident conditions, verification of optimum moderation conditions, structural integrity of components, expansion and temperature coefficients and thermal power.
In addition to the experimental data an extrapolation of the data to k,ff =
0.990 should be provided.
In addition to the above data some other information is needed before we i,
can further consider operation at k,7f = 0.990 as follows:
1.
Describe the mechanism for automatically moving the Cf source.
Describe also the shielding.
f 2.
Is the shutter door fail-safe? Describe.
3.
What is to prevent the further withdrawal of a control rod af ter k or by you? gff = 0.990 is attained by one of your customers e
f!l 8507050139 050314 PDR ADOCK 07001703 C
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~ 2 It is anticipated that there may be further questions after the receipt of the above information. Accordingly, it is suggested that you try to have g
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all data to us by July 15, 1974.
FOR THE ATOMIC ENERGY CO MISSION o
ft.A L. C. Rouse, Chief Fuel Fabrication and Reprocessing i
Branch 1
Directorate of Licensing
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