ML20090M534

Forwards Supplemental Info to Facility Second Reload Submittal

ML20090M534
Person / Time
Site:	Monticello
Issue date:	04/01/1974
From:	Mayer L NORTHERN STATES POWER CO.
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9105060220
Download: ML20090M534 (4)

Text

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. pegulotory N D3 e NORTHERN sTATEa POWKR C O M l' A N Y MIN N E A POM S. MlNNE SOTA D S erf t April 1, 1974 'k.y j m 4(-i)' 4 \

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M {t9 Mr. J F O' Leary Directorate of Licensing g4 4 Office of Regulation 7 b g ,,, ,7 N4 A U S Atomic EneTEy Corantesion * 'Ne /'

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Dear Mr. O'Lu ry:

MONTICL) 0 NUCLEAR GENERATING PIANT Docket No.40-263 License No. DPR-22 Supplemental Information to the Monticello Second Reload Submittal On November 19, 1973 we transmitted a report entitled "Monticello Nuclear Gentrating Plant Second Reload Sutnnittal". Figure 2-i was inadvertently omitted. Please incorporate the attached replacement pages in the report (s) sent to you on November 19, 1973 to correct this omission.

Retnove Cid Pages y sert New Pages 1-1/1-2 1-1/2-1 2-1/3-1 2-2/3-1 Yours very tnity,

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L 0 Mayer, PE d AEN 4 1974 C-(

Director of Nuclear Support Services ,g, Q N

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cc: J G Keppler G Charnoff Minnesota Pollution Control Agency Attn. E A Prytina attachment 9105060220 740401 PDR ADOCK 05000263 P PDR

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1. IlfrRODUCTION This docunient provides the technical basis of the license submittal for the second reload of Northern States Power /Monticello Unit 1. Presented herein is a description of the new fuct and the results of the evaluation of the refueled core for the February,1974 outage.

The fuel at the site available for loading at the outage will be 116 P.eload-2 fuel bundles, which are 8x8 bundles with an average enrichment of 2.62 vt% of U-235. There will also be available for reinsert 7 initial core bundles discharged at the end of Cycle 1 with on average exposure of about 7400 ffdd/t.

The objective of this outage is to remove the 44 temporary control cur-tains which remained in the core during Cycle 2 and to load the core so as to assure the availability of the plant at high power for approximately an annual cycle.

Sections 3, 4, 5 and 6 of this document, dealing with the subjects of reload fuel mechanical design and reloaded core thermal-hydraulic and nuclear charac-teristics, and saf ety analysis, present descriptions of design criteria, taethods and results f rom design ca* ulations and safety evaluations and represents com-plete information for the review of fuel assecbly and core design.

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Figure 2-1. Reference Core Loading Monticello Cycle 3

! 2-2 Revised 4/1/74

l AEC DI 15UT10N FOR PART SO DOCKET MA1 3 CONTROL NO: 2SEs (TDIPORARY FORM)

FILE:

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DATE OF DOC DATE REC'D LTR MDiO RPT OTHER FROM:

Northern States Pcwer Co.

Minneapolis, Minnesota X L. O. Mayer 4-1-74 4-4-74 CC OTHER SENT AEC PDR yyy TO: ORIG SENT LOCAL PDR vyy J. F. O' Leary 40 INPUT NO C15 REC'D DOCKET NO:

CLASS ~ UNCLASS PROP INTO XXXX 40 50-263 ENCLOSURES:

DESCRII' TION :

Ltr trans the following... Fig 2-1 to report "Monticello Nuclear Gen-erating Plant Second Reload Submittal" inadvertently omitted rrom original sub-ACKNOWLEDGED mittal DO NOT REMOVE PLANT NAME: MONTICELLO (40 cys enct re c ' ri ) __

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