ML20024G496

Provides Supplementary Info Re First Monticello Reload

ML20024G496
Person / Time
Site:	Monticello
Issue date:	04/13/1973
From:	Mayer L NORTHERN STATES POWER CO.
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9102120564
Download: ML20024G496 (3)

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atoQ NORTHERN STATES POWER C O M P A P4 Y M ON N E A POLI t. MIN N E S OTA 98400 April 13, 1973 " kf o,

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'k Mr. J F O' Leary, Director .; Apgic)973 ;E Directorate of Licensing - .. w -

United States Atomic Energy Commission V -

,.h' Washington, D C 20545 - 'd,

Dear Mr. O' Leary:

IN[

MONTICELLO NUCLFAR GENERATING PIANT Docket No. 50-263 License No. DPR-22 Supplementary Information Regarding the First Monticello Reload On February 20, 1973 we submitted a document entitled "First Reload License Submittal." Calculations performed in support of that document were based on a target exposure of 6800 MWD /STU. The plant capacity factor exceeded the estimate, resulting in an exposure of approximately 7100 MWD /STU at the date scheduled for the outage. We, therefore, intend to rv lify our previously re-ported plans somewhat to reficct the achieved cycle 1.,sposure.

The reference core discussed in the initial submittal consisted of 28 R-1 type reload fuel assemblies with 456 initial core fuel assemblies having a preoutage average exposure of 6800 MWD /STU and 64 temporary control curtains. Allowable deviations of thece parameters were also discussed to establish a window for the outabe. Because exposure exceeded this window, a revised core loading plan has been selected which is compatible with existing exposure conditions. Our present plan is to load a cycle 2 core consisting of 20 R-1 type reload fuel assemblies with 464 initial core assemblies and 44 temporary control curtains. The shutdown margin for this core with the rod of highest worth fully withdrawn is calculated to be 0.015 delta k which is well in excess of the 0.01 delta k design requirement stated in the FSAR. The attached figure shows the planned cycle 2 core.

The safety analysis presented earlier has been reviewed, found to be unaffected by this change in core loafing and found not to involve an unreviewed safety ques-tion. The Monticello Operations Committee and Safety Audit Committer. have reviewed the revised loading plan.

Yours very truly, e,

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DOCKITED L 0 Mayer, P.E.

Director of Nucicar Support Services g

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USAEC, APR161973 >

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