ML19283B710
| ML19283B710 | |
| Person / Time | |
|---|---|
| Site: | 05000072, University of Utah |
| Issue date: | 02/02/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | UTAH, UNIV. OF, SALT LAKE CITY, UT |
| References | |
| NUDOCS 7903060646 | |
| Download: ML19283B710 (2) | |
Text
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Ub'1TED STATES j
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- Ut; h Dcckets Nos.: 50-72 and 50-407 The University of Utah College of Engineering ATTN: Dean of Engineering 2000 Merrill Engineering Building Salt Lake City, Utah 84112 Gentlemen:
Our letter of June 14, 1978, discussed review of your physical security plan (PSP) in connection with your license renewal application. The purpose of this letter is to provide additional information on this item. (1) As discussed with you and pursuant to 10 CFR 50.54, we plan to include your PSP in the license conditions by reference. Because of the sensitive nature of the security plan, the actual PSP will not be attached to the license and will be withheld from public disclosure in accordance with 10 CFR 2.790(d). The following is an example of such a license condition: "The license shall maintain in effect and fully implement all provisions of the NRC Staff-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan consists of documents withheld from public disclosure pursuant to 10 CFR 2.790, collectively titled, " University of California at Berkeley Security Plan," as follows: Original, submitted with letter dated May 31, 1973 Revision 1, submitted with letter dated November 26, 1973 Revision 2, submitted with letter dated January 14, 1974 Revision 3, submitted with letter dated March 11, 1974" This, of course, is only an example and does not reflect your actual PSP, 790306Olo[4 l
The University of Utah (2) The second time relates to the Department of Energy and State Department program to implement the Nonproliferation Act of March 10, 1978, by reducing the enrichment of fuels in nonpower reactors. Concomitant to this, the proposed Regulation 573.47 is designed to implement the US/IAEA Agree-ment when approved by the Senate. Both of these actions are keyed to the enrichment of fuel and other SNM. Therefore, your license, which authorizes certain maximum possession limits of SNM (U235, Pu, U233), should be changed to reflect not only the total amount of SNM, but the percent enrichment of each; the amount of SNM exempt and how exempt (i.e.,10 CFR 73.6(b)); and the amount of SNM nonexempt. This will form the basis for establishing the level of pmtection of your PSP. For your information, in September 1975, a letter was sent to all licenseas authorized to possess SNM in excess of 10 CFR 73.1(b) quantities requesting that they review their requirements and provide justification for the " lowest acceptable quantity" necessary to sustain current operations and those projected for the ensuing twelve months. There are still a number of licensees that are authorized to possess quantities in excess of 73.l(b) quantities. In view of the foregoing, you are requested to review your SNM requirements and provide: (1) The maximum amounts of SNM and types; (2) The enrichment of each item in 1; (3) The amounts of each SNM exempt and how exempt; and (4) The amounts of each SNM nonexempt you propose to be included in your licenses. Please do not hesitate to contact Mr. Steve Ramos (301492-7435) regarding this matter. Sincerely, I d Robert W. Reid, Chief Operating Reactors Branch #4 Di. vision of Operating Reactors}}