ML20044H339
| ML20044H339 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 05/28/1993 |
| From: | Clark R DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20044H338 | List: |
| 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
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MCEl-040046 2 0f 153
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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).
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MCEI-0400-46 1
' 3 of 153 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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MCEl-(M00-46 9 of 153 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 80 Unacceptable Operation 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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MCEl-0400-46 i
11 of 153 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 (X,Y,Z)/(UMT x MT x TILT))
C 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 ncludes allowances for i
calculational and measurement uncertainties.
F (X,Y,Z) = the design power distributions for F. F (X,Y,Z)is provided in Table Q
1 for nomial operating conditions and in Table 2 for power escalation during startup operations.
M (X,Y,Z) = the margin remaining to the CFM limit in core location X,Y,Z from the C
transient power distribution. M (X,Y,Z) calculations parallel the C
Mg(X,Y,Z) calculations described in DPC-NE-201 IPA, except that the LOCA limit is replaced with the CFM limit. M (X,Y,Z)is provided in i
C 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)
L 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 value from OTAT required to compensate for 1
each 1% that [F (X,Y,Z)]RPS exceeds its limit.
4 o-MCEI-G400-46'
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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. F n(X.Y.Z)(Soecification 3/4.2.3) 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).
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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
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FAH(X,Y) exceeds its limit.
Thermal Power P=
Rated Thermal Power 2.6.5 TRH = 0.04 where TRH = Reduction in OTAT K setpoint required to compensate for each 1% that 1
j' F n(X,Y) exceeds its limit, A
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