ML19345F669
| ML19345F669 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 02/10/1981 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345F668 | List: |
| References | |
| R-028-A-027, R-28-A-27, NUDOCS 8102190003 | |
| Download: ML19345F669 (4) | |
Text
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o, UNITED STATES 8 j j*3.. q., j NUCLEAR REGULATORY COMMISSION
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g W ASHINGTON. D. C. 20555 THE UNIVERSITY OF MICHIGAN DCCXET NO. 50-2 AMENDMENT TO FACILITY OPERATING LICENSE Amenument No. 27 License No. R-28 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The apolication for amendment by the University of Michigan (the licensee) dated April 2,1980 and June 26, 1980 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set fortn in 10 CFR Chapter I; 3.
The facility will operate in conformity with the applications, the provisions of the Act, and the rules and reculations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendmeat can be conducted witnout endangering the health and safety of t e public, and (ii) that such activities will be conducted in cet oliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
Tne issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and F.
Publication of notice of this amendnent is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
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2.
Accordingly, the license is amended by changes to the Technica#
Specifications as indicated in the attachment to this license amendment, l
l Ind paragraphs 2 3.(2) and 2.C.(2) of Facility Operating License No.
l K-28 are hereby amended to read as follows:
1 1
8102190003
! 2.B.(2) Pursuant to the Act and 10 CFR Part 70, "Srecial Nuclear Material," to receive, possess and use uv to a maximum of 25 kilograms of contained uranium 235 at various enrich-ments in connection with operation of the reactor. Without exceeding the foregoing maximum possession limits, the specific categories of maximum limits are as follows:
Maximum U-235
%E nrichment Exemot Status
- 8.9 kg.
<20 Exempt as in 10 CFR 73.6(a) 16.11 kg.
>20 Exempt as in 10 CFR 73.6(b) and 73.67(b)(1)(f) 4.94 kg.
>20 Not Exempt
- Material is exemot provided that it meets the requirements for exemption pursuant to the cited provisions of 10 CFR 73.
and 2.C.(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, are hereby incorp-i crated in the license. The licensee shall operate the l
facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ll !f dh,2,,,bj.7
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James R. Miller Chief Standardization and Special Projects 3 ranch Division of Licensing l
Attachment:
Changes to the Technical Soecifications Date of Issuance:
Februa ry 10, 1981 l
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ATTACHMENT TO LICENSE AMENCMENT NO. 27 FACILITY OPERATING LICENSE NO. R-28 i
DOCKET NO. 50-2 1
Revise Acpendin A Technical Specifications as follows:
Remove Dages Insert Pages 37 37 Changes on the revised page are identified by marginal lines.
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5.2 REACTOR FUEL The fuel assemblies shall be of the MTR type, consisting of plates containing uranium-aluminum alloy, uranium aluminide (UAk),), or uranium oxide (U 0a) fuel (uranium enriched in the isotope U-235 clad with 3
aluminum. ~ Partially loaded fuei assemblies in which some of the plates do not contain uranium may be used.
f 5.2.1 High Enrichment Uranium (MEU) Fuel High enrichment (93%) fuel assemblies may consist of plates containing uranium-aluminum alloy, UAi, or U 0. The x
33 authorized fuel assembly designs are:
Maximum Plate Loading Maximum Assembly Loading Number of clates (grams of Uranium 235)
(grams o' Uranium 235) 18 7.78 + 2%
140 + 2%
l 9
7.78 7 2%
70 7 2%
10 16.90[2%
169 [ 2%
l 5.2.2 Low Enrichment Uranium (LEU) Fuel Low enrichment (19.5%) fuel assemblies shall consist of plates containing UAl. The authorized fuel assembly designs are:
x Maximum Plate Loading Maximum Assembly Loading Number of Plates (grams of Uranium 235)
(grams of Uranium 235) 18 9.28 + 2%
167 + 2%
9 9.28[2%
84 + 2%
5.2.3 Reactor Power Level and Scram Setcoint for Authorized Core Loadings The 9-plate fuel usembly nall be used in all loadings for the control rod fuci assembli93. The reactor power level and scram setpoints for authorizec : ore loading shall be:
Limiting Safety Fuel Leadino Power Level System Setting Normal 18 plate core 2 MW 2.4 MW Fringe" 18 or 10-plate with center of 18-plate core 2 MW 2.4 MW Intermixed (nonfringe*)
18 and 10 fuel plate core 1 MW l.2 MW
' Fringe fuel assemDlies are those in east, west and south locations L5, L6, L7, L8, L9, L10, L20, L30, L40, L50, L60, L70, L75, L76, L77, L,'8, L79 and L80.
Amendment flo. 27
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