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 MALH.TUCHER:

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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 J

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

-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 C

' and corrects a typographical error.' These changes do not impact Technical l

Specifications.

m,

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Very truly yoitrs,- -

lk-

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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 Mr. L.'A. Wiens, Project Manager Office of Nuclear Reactor Regulation-

'U. S. Nuclear Regulatory Commission Washington,-DC 20555

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Thermal Hydraulic Desion Conditions" g,

(. i:W gp Cvele 11 Ovele-12 e

@m-Design; power" level,lMWt.

2568-2568'-

p.

System-pressurep psia :

2200 2200 h.f "

Reactor. coolant flow,--% design flow' 109.5

.107. 5 l

_ Rev.!1 L

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(Core - bypass-flow '8,-. %itotel-flow'

' 7. 9

.8.6 n-i h

lVessel in1'et/ outlet coolant temp at

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'554.7/603.4

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100% power, 'F ;

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Ref; design radial-local power.

.1.71-1.71 cpeaking f actor:

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,..Ref ' design' axial flux ' shape -

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1. 5 ' cosine --

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Active fuel' length, in.,

141.8

-141.8 Y'.

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> Avg heat. flux ats100%Jpower, fl0* Btu /hr-f t.

176N' 174-8

[

CHF '.lcorrelatilon

~ BAW-2/BWC BAW-2 /BWC- -

e p',

, 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.

O,l'

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Generic analyses-ibased on.>8.'0%? core bypass flow for cycle 11, n 74 29.0% core bypass flow for Cycle 12.

1

' (b)1.. ; Heat flux. based onf a conservative minimum densified length of '

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1

- THERMAL POWER LEVEL,%

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120 -

( 17.0,107.0)

(17.0,107.0)

M1=0.944 ADCEPTABLE 4 F UMP OPERAT M2= 0.944 100 -

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( 35.0,90,0)

(35.0,90.0)

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(17.0,79.9)

ACQEPTABLE 3 & 4 PUMP OPERAlpN

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60 (35.0,62.9)

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