ML20138L557

Application to Amend License R-28,authorizing Conversion from High to Low Enriched U Fuel

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: IA-85-587, Submits Detailed Definition of design-basis Event, as Applicable to Facility.Licensee Should Use Definition to Show That Proposed Low Enriched U Loading Will Not Result in Significant Release of Radioactivity ML20138L502 ML20138L512 ML20138L518 ML20138L524 ML20138L549 ML20138L553 ML20138L557 ML20138L562 ML20138L567 ML20138L573 ML20138L579 ML20138L589 ML20138L592
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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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)

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18 9.28 1 24 167

• 2s 9

9.28 2 24 84 1 2%

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AFTERGO85-587 PDR a

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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.

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'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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