ML20012B366

Forwards Rev 1 to Cycle 12 Reload Rept,Changing Assumed RCS Flow & Correcting Typo

ML20012B366
Person / Time
Site:	Oconee
Issue date:	02/21/1990
From:	Tucker H DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9003140274
Download: ML20012B366 (5)

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.  ; DUKE PowEn GOMPANY ' .l P.O. BOX 33189 OMARIDTTE.M.O.98242t 1

MALH.TUCHER: ..; TeLernows m _,

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', February 121, 1990- q

U. S. Nuclear Regul'atory Commission s

Document Control Desk

[' Washington, DC -~20555 a

Subject:

Oconee Nuclear-Station ,

Docket Nos. 50-269, -270, -287' '

J'

-Unit 3 Cycle 12 Reload Report. 4 Gentlemen:

1 By. letter' dated' September'25, 1989 I submitted the Oconee Ucit 3 Cycle 12-Reload Report in support'of proposed revisions to Technical Specifications. Via amendments 180/180/177, the NRC approved the  ;

revisions. Please. find. attached,for-your information Revision 1 to the

-Oconee 3; Cycle.12s Reload Report. , Revision 1 changes the assumed RCS flow l C ' and corrects a typographical error.' These changes do not impact Technical l Specifications.

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• Very truly yoitrs,- -

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<H.iB.-Tucker PJN102/td-Attachment a cc: Mr. S. D. Ebneter Regional Administrator U. S. Nuclear Regulatory. ,

Commission'- Region II 101 Marietta St. NW -

LSuite'200 Atlanta, GA : 30323.

Mr'..P. H. Skinner NRC. Resident Inspector- ,

Oconee Nuclearf Station- i

1. Mr. L.'A. Wiens, Project Manager ,

Office of Nuclear Reactor Regulation-

'U. S. Nuclear Regulatory Commission ,

Washington,-DC 20555

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p.  : System- pressurep psia : 2200 2200 Reactor. coolant L flow,--% design flow' 109.5 _ Rev.!1 h.f

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.107 . 5 l n- ', (Core - bypass- flow i '8,-. %itotel-flow' ' 7. 9 ,

.8.6 h

lVessel in1'et/ outlet coolant temp at '556.2/601.8 '554.7/603.4

[ 100% power, 'F ;

h s Ref; design radial-local power.

.1.71- 1.71 cpeaking f actor:

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b;L , ,..Ref ' design' axial flux ' shape - 1.5 cosine- 1. 5 ' cosine --

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, Min DNBR with densification penalty. >1.30/>1.18. >1.30/>1.18-

$ ~ iloti channel factors: Enthalpy rise 1.011/1.011- 1.01/1.'0111: ,

Heat flux ~ - 1~. 014 /1. 014 - 1.01/1.0144

... cFlow area 0.90/0.97 '0.98/0.97.

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.w 2 (a)i ; . .. .. . . .. Generic analyses-ibased on.>8.'0%? core bypass flow for cycle 11, n 74 29.0% core bypass flow for Cycle 12. 1

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