ML19347C250

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Safety Evaluation Supporting Amend 7 to License R-53
ML19347C250
Person / Time
Site: 05000112
Issue date: 10/02/1980
From: John Miller
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19347C234 List:
References
NUDOCS 8010170110
Download: ML19347C250 (2)


Text

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os; w SAFETY EVAL.UATION BY THE OFFICE OF NUCLEAR REACTOR REGULATICN SUPPCRTING AMENCMENT NO.7 TO FACILITY

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OPERATING LICENSE NO. R-f27 00CKET NO. 50-112 Backcround:

The research reacter at ne University of Oklancma (UG) is an AGN ZilP wnicn operates at a steady-state power level of 15 watts and utili:es (nominal) 19% enricned polyethylene fuel elements.

Tne University of West Virginia (UWV), which also has an AGN-211P researcn reac:ce, recently decided to decommission their researcn reac:cr.

It has operated at an average of 75 watts for approximately 12 years.

As the fuel elements in the two cores are identical, exces: possioly for small burnup differences, UO has made arrangements with UWV : transfer and utilize the fuel elements in the U0 reacter.

UC will not increase the number of fuel elements in the core.

They will utilice the "best" twelve (12) of tne Octal of twenty four (24) fuel elements they will have available.

UO has designed special storage facilities for storing the excess fuel.

As this type of fuel is no longer manufactured, UC will consicer the excess fuel obtained from UWV as replacements fcr spent fuel.

n sum.ary, the extra fuel obtained from UWV will be used by UO as insurance for longevity cf tne AGN facility.

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Accepting the fuel frcm UWV will increase One U-45'inventcry from 306 grams to 1700 grams of 18% enricnec 'uel.

The UWV fuel elements measure accroximately 4 mr/hr garcr.e at contac:.

Safety Evaluation:

The recuest oy U0 to cbtain the availa:la AGR 211F fuel elements from UWV will create no changes to the existin; cere, Oc cperation of the f acility.

Mcreover, the request for additional 'uel inven: cry maintains U0 in a "Lcw" Physical Security level. Acccedingly U0 is required to only maintain ucca:e and implement their Physical Securi:y Plan in accordance with sections 73.c7, anc 73.40 of 10 CFR; they neec nc: sucmit the plan :c NRC.

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e UO is preparing a fuel storage facility and a fuel transportatien plan to accept the UWV fuel elements. At present the UWV fuel elements measure approximately 4 mr/hr grams at contact.

This low level should produce no transportation problems.

In essence, the acquisition of the available AGN fuel elements from UWV will not change any of the operating aspects of the U0 facility.~ The only change to the entire reacter "com lex" will be the requirement of a secured stcrage area for the extra fuel being kept in inventory.

All safety and environmental issues were satisfacterfly considered in prior amendments. There are no additional safety issues to be considered with this amencment.

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Conclusion:==

We have concluded, based on the censiderations stated above, that:

(1) there is reasonable assurance that the hea!:h and safety of the cublic will not be endangered by an increase in the U0 fuel inventcry and storage facilities, and (2) such activities, will ce conductec in compliance with the Corsnission's regulations and the issuance of this amendment will not be inimical to the healtn anc safety of the puolic.

Environmental Imcact Accraisal Based on the feregoing analysis, we have concluded tnat there will ce no significant environmental imcact attricated to this propcsed license increase. Having made this conclusicn, we have furtner concluced that nc environmental imoact statement for the proscsed action need be p.repared and that a negative declaration to tnis effect is appropriate.

In addition, only the license itself requires the necessary amencments to reflect the increase in fuel inventcry. No amandments are recuired to the Technical Specifications.

Dated at Bethesda, Maryland this 2nd day of,0ctober 1980.

FCR EE NUCLEAR REGULATORY C M ISSION s

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James R. Miller, Chief j

Standarditation & Special 4

Projects Branch Division of Licensing

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