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 .
MicMioAn uswon AL-PHOENIX PROJECT
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Docket No. 50-2
. License No. R-28 1
U. S. Nuclear Regulatory Coselission
? 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.
)
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
'$ (UALa ), or uranium oxide (U3g0 ) fuel (uranium enriched in the
'] 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 U3g0 .
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%
'e 9 7.78
- 24 70 1 2%
l 10 16.90
- 24 169 1 2%
I 5.2.2 Iow Enrichment Uranium (LEU) Fuel 1
i Iow enrichment (19.5%) fuel assemblies sh'all consist j of plates containing UALg. Theauthorized fuel assembly
'.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 9.28 2 24 84 1 2%
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f.i 5.2.3 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 ,
.; Limiting safety
- Fuel Imading
}q Power Level system settine Normal 18 plate core 2 MW
- 2.4 MW 9[ +
Fringe
- 18 or 10-plate a'
i.i . with center of 18-plate
. core '
2 MW 2.4 MW Q Intermixed (nonfrinie*)
7}, 18 and 10 fuel plat.e core 1 MW
- 1.2 MW
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- Fringe fuel assemblies are those in east, west and
'I south locations L5, L6, L7, L8, L9, L10, L20, L30, L40, I
o .
L50, L60, L70,'L75, L76, L77, L78, L79 and L80.
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,j L saf ty analysis for the utilization of low enrichment uranium (LEU) fuel is enclosed.
i; (56.5 wt t UAL x , 42.0 we t U)The I2U fuel necessitates higher weight percents of uranium
,j fuel. The present UALx compound than are presently used for the FNR high enrichment weight percent is 19.1. However, test plates in
,;} the Materials Aeactor (HFIR), Test Reactor (MTR), Engineering Test Reactor (ETR), High Flux e Isoto and the FR2 Reactor in Kalsruhe, Germany with higher weight per-densities than the FNR limit with no excess swelling Opera'tional or blister failu -
1 fuel elements with aluminide loadings comparable to those proposed are routinely
! used in the Advanced Test Reactor (ATR) to higher fission densities than the FNR 1 limit of 1.5 x 1021 fissions /cc. . ,'
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j The LEU fuel elements will be physically identical, except for plate core construction ,
l
+i. to present uranium-aluminum alloy elements which comprise 60% of thepresent FNR have been used since 1957. e an. cor 1
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- } The safety analysis indicates that fast and thermaliflux distributions within the core
% and in the reflector region are slightly changed by the use of LEU fuel'.
in the margins of safety are expected.
No reductions
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ii Sincerely, f
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%- William Kerr J Director
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s Michigan Memorial-Phoenix Project R' '
4 Subscribed to and sworn to before me
'"* **"*** this cM day of
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COMM M. ITE8
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W Cassusteengen EJourea en Oct. 21. 311
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