ML20090L792

Responds to NRC Re Future Refueling Plans. Preliminary Indications Are That Reload Will Involve One Minor TS Change Re 8D219 Fuel Type

ML20090L792
Person / Time
Site:	Monticello
Issue date:	07/24/1975
From:	Mayer L NORTHERN STATES POWER CO.
To:	Goller K Office of Nuclear Reactor Regulation
References
NUDOCS 9102120663
Download: ML20090L792 (3)

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NORTHERN $TATES POWER COMPANY ' *ey u NNaapo L Me N N e sotA se4ot July 24, 10'

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Mr. K. R. Coller -I g Assistant Director for / 2,  ! g Operating Reactors D Division of Reactor Licensing ,l' ,/[y ,,,,37 h 7

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MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. OPR-22 Information Regardinn Next Fefueling i This letter is written in response to your June 23, 1975, letter regarding future refueling plans. The Monticello reactor is presently scheduled to be shut down on September 12, 1975, for an estimated duration of 35 days.

The target start-up date is therefore October 17, 1975. During this fourth refueling outage, we plan to replace all 268 nf the remaining initial core fuel assemblies (7x7) in the reactor with the standard BWR 8D219 fuel type (8x8). This fuel is described in detail in the General Electric Licensing Topical Report entitled, " General Electric Boiling Water Reactor Generic Reload Application for 8x8 Fuel", NEDO-20360, Supplement 2 to Revision 1, May 30, 1975. The mechanical and nucicar design of the 8D219 fuel type is essentially identical to that of fuel currently in use with the exception that it is of a slightly lower enrichment.

t Preliminary indications are that the reload will involve one minor technical I

specification change, but no significant hazards consideration. Since this is the first time the 8D219 fuel type is being used at Monticello, the technical specifications do not presently contain a fuel type dependent limit curve for the maximum average planer linear heat generation rate (MAPLilGR) as a function of exposure. This MAPLHGR curve was included, with curves for other fuel types, in the most current ECCS analysis submitted to Mr. D. L. Ziemann on July 9,1975. The ECCS model treat's the 8D219 fuel type the same as the other fuel types being used. We intend to submit the technical specification changes associated with the ECCS analysis in a l license amendment request on July 29, 1975.

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NO) HERN OTATED POWER Cs APANY Mr. K. R. Go11er July 24, 1975 The safety evaulation of the remaining aspects of the reload fuci design and core configuration has been in progress by our fuel supplier since January and is expected to be completed in early August. To date, nothing has been identified which appears to involve a significant hazards consideration. The final determination of this fact will be made by the plant Operations Committee promptly after receipt and review of the safety evaluation. Assuming the Operations Committee concurs, the safety evaluation of all aspects of the fuel reload, with the exception of the MAPLCHR limits which will be reviewed with the ECCS license amendment, will be completed and reported in accordance with 10 CFR Part 50.59 (b).

With the exception of the new ECCS analyses discussed abov(, the only other important licensing consideration associated with the reload is implementation of the CETAB concept. Since you have indicated for some time that you prefer the use of CETAB over the Hench-Levy correlation, we have proceeded with a GETAB evaluation for the forthcoming reload. One outstanding requirement for this conversion is that action be taken on our License Amendment Request, dated March 12, 1975, which requests implementation of CETAB, prior to

) resumption of operation following refueling. The GETAB analysis for Cycle 5 is being done in the same manner as that submitted in Cycle 4 with one exception. Unlike other BWR GETAB calculations, the Monticello Cycle 4 analysis was done assuming an axial peaking factor of 1.57 at node 16.

Appendix V of General Electric Topical Report NEDO-10958, " General Electric BWR Thermal Analysis Basis (CETAB): Data, Correlation and Design Application" states that an axial peaking factor of 1.4 at the core mid-plane is a more realistic and justifiable set of conditions. We understand that you have reviewed this on a generic basis and find the latter acceptable. The 1.4 axial peaking factor at the core mid-plane will therefore be used in the Monticello Cycle 5 analysis. We are not aware of any other significant licensing considerations associated with our refueling at this time.

Yours very truly, L. O. Mayer Manager of Nuclear Support Services cc: Mr. J. G. Keppler Mr. G. Charnoff Minnesota Pollution Control Agency Attention: Mr. J. W. Ferman

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i N rthern States Power cc DATE OF DOC DATE REC'D LTR TWX RPT OTHER FROM:

i Minneapolis, Minn i L 0 Mayer 7-2h-75 7-28-75 xx CC OTHER SENT NitC PDR XXX

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Mr. Coller SENT LOCAL POR m I none signed.  ;

UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

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DESCRIPTION: ENCLOSURES:

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