ML20138L557
| ML20138L557 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 04/02/1980 |
| From: | Kerr W MICHIGAN, UNIV. OF, ANN ARBOR, MI |
| To: | Conner M Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20138L505 | List:
|
| References | |
| FOIA-85-587 NUDOCS 8512190300 | |
| Download: ML20138L557 (2) | |
Text
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THE UNIVERSITY OF MICHIGAN
?j MicMioAn uswon AL-PHOENIX PROJECT 4
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April 2, 1980
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Docket No. 50-2 License No. R-28 1
U. S. Nuclear Regulatory Coselission
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Atta:
Mr. Monte Conner Operating neactors Branch No. 4 4
Division of operating meactors Washington, D. C.
20555
Dear Mr. Conner:
- j The University of Michigan requests the following amendment to the Ford Nuclear o
Asactor (FNR) License No. R-28.
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j 1.
Change section 5.2, Technical Specifications, Appendix A to License No. R-28, i
to read:
5.2 REACTOR FUEL The* fuel
- assemblies shall be of the MTR type, consisting of 7
plates containing uranium-aluminum alloy, uranium aluminide (UAL ), or uranium oxide (U 0 ) fuel (uranium enriched in the a
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isotope U-235), clad with aluminum. Partially loaded fuel assemblies in which some of the plates do not contain uranium-may be used.
5.2.1 Nish Enrichment Uranium (MEU) Fuel i.;
High enrichment (934) fuel assemblies may consist of 1
plates containing uranium-aluminum alloy, UAL,, or U 0.
3g The authorised fuel assembly designs are:
Maximumi Plate Imading Maximum Assembly Imading q
Number of Plates (erans of Uranium 235)
(erans of Uranium 235) o 18 7.78 2 2%
140 1 2%
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7.78
- 24 70 1 2%
l 10 16.90
- 24 169 1 2%
I 5.2.2 Iow Enrichment Uranium (LEU) Fuel 1i Iow enrichment (19.5%) fuel assemblies sh'all consist j
of plates containing UAL. Theauthorized fuel assembly g
'.t designs are:
Maximum Plate Imading Maximus Assembly 14ading Number of Plates (erans of Uranium 235)
(crass of Uranium 235)
)
18 9.28 1 24 167
- 2s 9
9.28 2 24 84 1 2%
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Reactor Power Level and Scram Setpoints for Authorized core Loadings
,j The 9-plate fuel assembly shall be used in all l
loadings for the control rod fual assemblies, i
The reactor power level and scraan setpoints for
'j authorized core loadings shall be Fuel Imading Limiting safety
}q Power Level system settine Normal 18 plate core 2 MW 9[
2.4 MW Fringe
- 18 or 10-plate
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with center of 18-plate core 2 MW 2.4 MW Q
Intermixed (nonfrinie*)
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18 and 10 fuel plat.e core 1 MW 1.2 MW
- Fringe fuel assemblies are those in east, west and
'i'I south locations L5, L6, L7, L8, L9, L10, L20, L30, L40, I
L50, L60, L70,'L75, L76, L77, L78, L79 and L80.
o
'1 L saf ty analysis for the utilization of low enrichment uranium (LEU)
,j enclosed.
fuel is (56.5 wt t UAL, 42.0 we t U)The I2U fuel necessitates higher weight percents of uraniu i;,j fuel.
The present UAL than are presently used for the FNR high enrichment x
x compound weight percent is 19.1.
However, test plates in the Materials Test Reactor (MTR), Engineering Test Reactor (ETR), High Flux Isoto
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Aeactor (HFIR),
and the FR2 Reactor in Kalsruhe, Germany with higher weight per-e densities than the FNR limit with no excess swelling or blister failu fuel elements with aluminide loadings comparable to those proposed are routinely Opera'tional 1
used in the Advanced Test Reactor (ATR) to higher fission densities than the FNR limit of 1.5 x 1021 fissions /cc.
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The LEU fuel elements will be physically identical, except for plate core construction j
to present uranium-aluminum alloy elements which comprise 60% of thepresent FNR cor l
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have been used since 1957.
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i The safety analysis indicates that fast and thermaliflux distributions within the core
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and in the reflector region are slightly changed by the use of LEU fuel'.
in the margins of safety are expected.
No reductions
'i ii Sincerely, f
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William Kerr J
Director
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Michigan Memorial-Phoenix Project s
R' Subscribed to and sworn to before me 4
this cM day of 19 M.
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COMM M. ITE8 w Puws. mshtem cetr. Mkh..
W Cassusteengen EJourea en Oct. 21. 311
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