ML20044H339

Rev 1 to MCEI-0400-46, McGuire Unit 1,Cycle 9 Colr.

ML20044H339
Person / Time
Site:	McGuire
Issue date:	05/28/1993
From:	Clark R DUKE POWER CO.
To:
Shared Package
ML20044H338	List: ML20044H337 ML20044H339
References
MCEI-0400-46, MCEI-0400-46-R01, MCEI-400-46, MCEI-400-46-R1, NUDOCS 9306080201
Download: ML20044H339 (7)

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DOCUMENT CONTROL NO. MCEl-0400-46 REVISION NO. O')I PAGE NO. 1 OF 153 TITLE MCGUIRE UNIT 1 CYCLE 9 CORE OPERATING LIMITS REPORT SIGNOFF DATE PREPARED BY ] ,Wau cM, /f8 y v -

CHECKED BY cm,( l 16czk- W Je, jff) '

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1 9306080201 930529 l PDR ADOCK 05000369 I PDR

MCEl-040046 2 0f 153 )

Revision 1 McGuire Nuclear Station COLR McGuire Unit 1 Cycle 9 Core Operating Limits Report May 1993 Revision 1 Duke Power Company NOTE ,

The contents of this document have been reviewed to verify that no material herein  !

either directly or indirectly changes or affects the results and conclusions presented in the 10CFR50.59 M1C9 Reload Safety Evaluation (calculation file: MCC-1552.08-

. 00-0184). j i

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MCEI-0400-46 1

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- Revision 1 McGuire 1 Cycle 9 Core Operating Limits Report REVISION LOG ,

Revision Effective Date Effective Paces OriginalIssue May 24,1993 Pages 4-8,10,12,13. &

15-153 Revision 1 May 27,1993 Pages 1-3,3A,9,11, & 14 l

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, MCEl-040046 3A of 153 Revision 1 McGuire 1 Cycle 9 Core Operating Limits Report INSERTION SilEET FOR REVISION 1 Remove pages Insert Rev. I pages Pages 1-3,9,11, & 14 Pages 1-3,3A,9, i1, & 14

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Revision i McGuire 1 Cycle 9 Core Operating Limits Report 1

1 A.F.D. LIMIT CURVE 120-(-20.100) ,_

(+10.100) iuu Ur. acceptable Operation Unacceptable Operation 80 Percent gp Acceptable Operation Rated 60-Thermal (-36.50) (+21,50)

Power 40-( 20--

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-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 Axialllux Difference (% Delta I)

Figure 3 Percent of Rated Thermal Power Versus Axial Flux Difference Limits NOTE: Compliance with Technical Specification 3.2.2 may require more restrictive AFD limits. Refer to OP/1/A/6100/22 Unit 1 Data Book for details.  ;

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Revision 1 McGuire 1 Cycle 9 Core Opernting Limits Report -

I 2.5.5 [F (X,Y,Z)]RPS = F (X,Y,Z) x 'M C(X,Y,Z)/(UMT x MT x TILT))

where [F (X,Y,Z)]RPS = cycle dependent maximum allowable design peaking factor which ensures that the centerline fuel melt limit will be preserved for operation within the LCO limits. [F (X,Y,Z)]RPS ncludesi allowances for calculational and measurement uncertainties.

F (X,Y,Z) = the design power distributions for Q F . F (X,Y,Z)is provided in Table 1 for nomial operating conditions and in Table 2 for power escalation during startup operations.

M C(X,Y,Z) = the margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. MC(X,Y,Z) calculations parallel the Mg(X,Y,Z) calculations described in DPC-NE-201 IPA, except that the LOCA limit is replaced with the CFM limit. MC (X,Y,Z)is provided in i Table 3 for normal operating conditions and in Table 4 for power escalation during startup operations.

UMT = Measurement Uncertainty (UMT = 1.05).

MT = Engineering Hot Channel Factor (MT = 1.03).

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)

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NOTE: [F (X,Y,Z)]RPS is the parameter identified as FMAX(X,Y,Z) in DPC-NE-20llPA.

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2.5.6 KSLOPE = 0.0725 where KSLOPE = Adjustment to the K 1value from OTAT required to compensate for each 1% that [F (X,Y,Z)]RPS exceeds its limit.

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14 of lS3 Revision 1 McGuire 1 Cycle 9 Core Operating Limits Report 2.6 Nuclear EnthnInv Rise Hot Channel Factor. F3 n(X.Y.Z)(Soecification 3/4.2.3)

[FAH(X,Y)]LCO = M ARP (X,Y) x [1.0 + (1/RRH) x (1.0 - P)]

2.6.1 McGuire 1 Cycle 9 Operating Limit Maximum Allowable Radial Peaks, (M ARP(X,Y)), are provided in Table 7.

The following parameters are required for core monitoring per the Surveillance Requirements of Specification 3/4.2.3:

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[F3g(X,Y)]SURV = p g(x,y)X MAH(X,Y)/(UMR x TILT),

as identified in DPC-NE-2011PA.

where UMR = Uncertainty value for measured radial peaks,(UMR = 1.04).

TILT = Factor to account for a peaking increase due to the allowed quadrant tilt ratio of 1.02. (TILT = 1.035).

D D 2.6.2 FAH(X,Y) = the design power distribution for FAH.FAH(X,Y)is provided in Table 5 for normal operating conditions and in Table 6 for power escalation during startup operations..

2.6.3 MAH(X,Y) = the margin remaining in core location X,Y to the DNB limit from the transient power distribution. MAH(X,Y) is provided in Table 5 for normal operating conditions and in Table 6 for power escalation during startup operations..

2.6.4 RRH = 3.34 when 0.0 < P ,<; 1.0, where RRH = Thermal Power reduction required to compensate for each 1% that ~

FAH(X,Y) exceeds its limit.

Thermal Power P=

Rated Thermal Power 2.6.5 TRH = 0.04 where TRH = Reduction in OTAT K 1setpoint required to compensate for each 1% that j' FAn(X,Y) exceeds its limit, i

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