ML20137P611
| ML20137P611 | |
| Person / Time | |
|---|---|
| Site: | 07000738 |
| Issue date: | 01/28/1985 |
| From: | Chabot G MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20137P572 | List: |
| References | |
| 03360, 3360, NUDOCS 8509190731 | |
| Download: ML20137P611 (4) | |
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(617) 452 5000 January 28, 1985 U.S. Nuclear Regulatory Commission Nuclear Materials Section B Division of Engineering and Technical Programs Region I 631 Park Avenue King of Prussia, PA 19406
Subject:
Addendum to request of January 17, 1985 for renewal of Special Nuclear Material License No. SNM-714 Gentlemen:
Shortly following submission of our recent application for renewal of Special Nuclear Material License No. SNM-714, we were requested by the physics staff, involved in making delayed neutron measurements, to include a request for possession and use of uranium-233. Since our renewal request had already been submitted, the request for U-233 is made here as an addendum to that submission.
This request is for 0.6 grams of U-233 metal in thin foil form to be used in a manner almost exactly as described in our past. amendment request of July 27, 1984, in which we described the use of Pu-239 in a fission chamber. The U-233 would be used to line the fission chamber as described for the Pu-239; the only difference would be that some U-233 would also be attached in the horizontal plane defining the base of the hemispherical section as shown in the enclosed figure. The total amount of U-233 would be somewhat less than 0.6 grams. The installation of the U-233 in the chamber would be carried out by the Radioisotopes Division at Oak Ridge National Laboratory. The foils will be covered with an evaporated layer of gold, 50 to 100 micrograms cm-2 in thickness, as was the Pu-239.
The experimental conditions would be as desribed for the Pu-239, and expected fission product activities are very similar to what were projected for the Pu-239. Control and surveillance would be as described for the Pu-239. The expected U-232 contamination of the U-233 metal is about 1 ppm (by weight) and is thus not anticipated to make for 8509190731 850909 5
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U.S.* Nuclear Regulatory Commission Page 2 January 28, 1985 any significant health physics concerns from the point of view of external radiation levels associated with the foil mounted in the detector.
We regret the timin8 of this request with respect to our recent tenewal request. If you require any additional information, please contact us.
Very truly yours, 17.<y 7 cgff-George E. Chabot Radiation Safety Officer GEC: dam Enclosure (s)
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'.'BE' WEEN: William O. Miller, Chief License Fee Management Branch Office of Administration John E. Glenn Chief Nuclear Materials Section B Division of Engineering and Technical Programs LICENSE FEE TRANSMITTAL A.
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Amendment Renewal License Signed Afte 0 % fV Date REGION I FORM 213
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