ML081430227

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Transmittal of Core Operating Limits Report
ML081430227
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 05/14/2008
From: Jensen J
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:8565
Download: ML081430227 (18)
v • d • e


Text

Indiana Michigan Power Company INDIANA Nuclear Generation Group One Cook Place MICHIGAN Bridgman, Ml 49106 POWER aep.com May 14, 2008 AEP:NRC:8565 10 CFR 50.4 Docket No.: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 CORE OPERATING LIMITS REPORT Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 1, is.

submitting the Core Operating Limits Report (COLR) for Unit 1 Cycle 22 in accordance with Technical Specification 5.6.5.

Revision 0 of the Unit 1 Cycle 22 COLR is provided as an attachment to this letter.

There are no new or revised commitments in this submittal. Should you have any questions, please contact Mr. James M. Petro, Jr., Regulatory Affairs Manager, at (269) 466-2491.

Sincerely, Joseph N. Jensen Site Support Services Vice President JRW/rdw Attachment c: J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne J.7T. King - MPSC MDEQ - WHMD/RPS NRC Resident Inspector P. S. Tam - NRC Washington DC

ATTACHMENT TO AEP:NRC:8565 Donald C. Cook Nuclear Plant Unit 1 Cycle 22 Core Operating Limits Report Revision 0

D. C. COOK UNIT I CYCLE 22 Revision 0 D. C. COOK 1JT'~dT 1 CYCLE 22 Revision 0 Donald C. Cook Nuclear Plant Unit 1 Cycle. 22 Core Operating Limits Report Page 1 of 16

D. C. COOK UNIT I CYCLE 22 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit 1 Cycle 22 design has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

a. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985
b. WCAP-8385, Power Distribution Control and Load Following Procedures - Topical Report, September 1974
c. WCAP-10216-P-A, Rev. IA, Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification, February 1994
d. WCAP-10266-P-A, Rev. 2, The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code, March 1987
e. WCAP- 12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995
f. WCAP-8745-P-A, Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions, September 1986
g. WCAP-13749-P-A, Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement, March 1997 The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core Safety Limits 3.1.1 SHUTDOWN MARGIN (SDM) 3.1.3 Moderator Temperature Coefficient (MTC) 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNA1) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reactor Trip System (RTS) Instrumentation 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3.9.1 Boron Concentration Page 2 of 16

D. C. COOK UNIT 1 CYCLE 22 Revision 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specifications 5.6.5.

2.1 SAFETY LIMITS 2.1.1 Reactor Core Safety Limits (Specification 2.1.1)

In Modes 1 and 2, the combination of thermal power, pressurizer pressure, and the highest loop average temperature (Tavg) shall not exceed the limits as shown in Figure 6 for 4 loop operation.

2.2 REACTIVITY CONTROL 2.2.1 SHUTDOWN MARGIN (SDM) (Specification 3.1.1)

Shutdown margin shall be greater than or equal to 1.3% Ak/k for Tavg > 200'F Shutdown margin shall be greater than or equal to 1.0% Ak/k for Tavg < 200OF 2.2.2 Moderator Temperature Coefficient (MTC) (Specification 3.1.3)

a. The Moderator Temperature Coefficient (MTC) limits are:

The BOL/ARO-MTC shall be less positive or equal to the value given in Figure 1.

The EOL/ARO/RTP-MTC shall be less negative or equal to -4.54E-4 Ak/k/0 F.

This limit is based on a Tavg program with HFP vessel Tvg of 554.0 to 558.0 'F.

Where: ARO stands for All Rods Out BOL stands for Beginning of Cycle Life EOL stands for End of Cycle Life RTP stands for Rated Thermal Power HFP stands for Hot Full Thermal Power Page 3 of 16

D. C. COOK UNIT I CYCLE 22 Revision 0

b. The MTC Surveillance limit is:

The 300 ppm/ARO/RTP-MTC should be less negative or equal to

-3.84E-4 Ak/°kIF at a HFP vessel Tavg of 554.0 to 558.0 OF.

c. The Revised Predicted near-EOL 300 ppm MTC shall be calculated using Figure 7 and the following algorithm:

Revised Predicted MTC = Predicted MTC + AFD Correction + Predicted Correction*

  • Predicted Correction is -0.30E-4 Ak/k/°F.

If the Revised Predicted MTC is less negative than the SR 3.1.3.2 limit (COLR 2.2.2.b) and all of the benchmark data contained in the surveillance procedure are met, then a MTC measurement in accordance with SR 3.1.3.2 is not required.

d. The MTC Surveillance limit is:

The 60 ppm/ARO/RTP-MTC should be less negative or equal to -4.41E-4 Ak/k/°F at a HFP vessel Tavg of 554.0 to 558.0 OF 2.2.3 Shutdown Bank Insertion Limits (Specification 3.1.5)

The shutdown rods shall be withdrawn to at least 228 steps.

2.2.4 Control Bank Insertion Limits (Specifications 3.1.6)

a. The control rod banks shall be limited in physical insertion as shown in Figure 2.
b. Successive Control Banks shall overlap by 100 steps. The sequence for Control Bank withdrawal shall be Control Bank A, Control Bank B, Control Bank C and Control Bank D.

2.3 POWER DISTRIBUTION LIMITS 2.3.1 AXIAL FLUX DIFFERENCE (AFD) (Specification 3.2.3)

a. The Allowable Operation Limits are provided in Figure 3.
b. The AFD target band is +/-5% for a cycle average accumulated burnup

>0.0 MWD/MTU.

Page 4 of 16

D. C. COOK UNIT 1 CYCLE 22 Revision 0 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

CFQ F(Z)-<--

  • K(Z) for P>0.5 P

FQC(Z) < 2

  • CFQ
  • K(Z) for P _<0.5 CF Fj (Z)*_
  • K(Z) for P >0.5 P

Fw (Z)*-< 2

  • CFQ *K(Z) for P*<_ 0.5 THERMAL POWER RATED THERMAL POWER
a. CFQ=2.15
b. K(Z) is provided in Figure 4.
c. eQ(Z) is the measured hot channel factor including a 3% manufacturing tolerance uncertainty and a 5% measurement uncertainty.
d. W(Z) is provided in Table 1 for +/-5% AFD target band.
e. Fw (Z) = Fr(Z) x W(Z) x Fp
f. For Cycle 22, Fp = 1.02 for all bumups associated with Note 2a of SR 3.2.1.2, except as shown in the table below. When no penalty is required, Fp = 1.00.

Cycle Fp Bumup Penalty (MWD/MTU) Multiplier 2058 1.020 2205 1.021 2351 1.022 2498 1.023 2645 1.023 2792 1.022 2938 1.020 The burnup range only covers where Fp exceeds 1.02. Linear interpolation is adequate for intermediate cycle burmups.

Page 5 of 16

D. C. COOK UNIT I CYCLE 22 Revision 0 2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (Fen) (Specification 3.2.2)

FH* CFA* (1 + PFAH *(l-P))

THERMAL POWER RATED THERMAL POWER

a. CFaH= 1.49
b. PFAH = 0.3 2.4 INSTRUMENTATION 2.4.1 Reactor Trip System (RTS) Instrumentation (Specification 3.3.1)

The Overtemperature AT and Overpower AT setpoints are as shown in Figure 5.

2.5 REACTOR COOLANT SYSTEM 2.5.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (Specification 3.4.1)

a. Pressurizer Pressure shall be >_2018 psig +
b. Reactor Coolant System TAVG shall be < 580.5 0 F +
c. Reactor Coolant System Total Flow Rate shall be >_341,100 gpm Page 6 of 16

D. C. COOK UNIT 1 CYCLE 22 Revision 0 2.6 REFUELING OPERATIONS 2.6.1 Boron Concentration (Specification 3.9.1)

The boron concentration of all filled portions of the Reactor Coolant System, the refueling canal and the refueling cavity shall be greater than or equal to 2400 ppm++.

+ These are Safety Analysis values. With readability allowance, the corresponding values are 578.2°F for TaVg, and 2050 psig for Pressurizer Pressure.

-+ This concentration bounds the condition of KIf < 0.95 which includes a 1% Ak/k conservative allowance for uncertainties. The boron concentration of 2400 ppm includes a 50 ppm conservative allowance for uncertainties.

Page 7 of 16

D. C. COOK UNIT I CYCLE 22 Revision 0 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0

[UNACCEPTABLE OPERATION 0.5 U-

-I, 0

0.0 ACCEPTABLE OPERATION]

C)

H-

-0.5

-1.0 0 10 20 30 40 50 60 70 80 90 100 Percent Rated Thermal Power Page 8 of 16

D. C. COOK UNIT I CYCLE 22 Revision 0 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (FOUR-LOOP OPERATION) 250 225 200 175 CL CU 150 z 125 0

0/

0~ 100 0

0 75 0ý 50 25 0

100 POWER (% of Rated Thermal Power)

Page 9 of 16

D. C. COOK UNIT I CYCLE 22 Revision 0 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 90 x 80 N

70 x %.0 U- 60 0

0- 50 40 E

E 30 r- 20 0

10 0

FLUX DIFFERENCE (DELTA-I)

Page 10 of 16

D. C. COOK UNIT I CYCLE 22 Revision 0 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 (0.0,1.0) (6.0,1.0) 1.0 (12.0, 0.925) 0.8 (9

z w

Lu 0.6 N

0 "z

0.4 0.2 4 4 4 .1-0 I I I 0 2 4 6 8 10 12 CORE HEIGHT (FT)

Page 11 of 16

D. C. COOK UNIT 1 CYCLE 22 Revision 0 FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint F1 +r"cs 1 (-' 3(-'-f A)

Overtemperature AT < AT. [KI - K2 (T-T) + K3 (P-Pr) - f+ (AD]

L+ -rzsj Where: AT = Measured RCS AT, 'F ATo = Indicated AT at RATED THERMAL POWER, 'F T = Average temperature, 'F Tf = Nominal Tavg at RATED THERMAL POWER ( *574.0 -F)

P = Pressurizer pressure, psig P = Nominal RCS operating pressure (2085 psig) 1+ =tS The function generated by the lead-lag controller for Tayg dynamic compensation

'r1, "2 = Time constants utilized in the lead-lag controller for Tavg 1 >22 secs. r2 -<4 secs.

S Laplace transform operator, see-1 K < .1.35*

K2 > 0.0230/0 F K3 Ž> 0.001 10/psi f1 (A) = -0.33 {37% + (qt - qb)} when qt - qb < -37% RTP 0% of RTP when -37% RTP < qt - qb < 3% RTP

+2.34 {(qt - qb) - 3%} when qt - qb >3% RTP where q, and qb are percent RATED THERMAL POWER in the upper and lower halves of the core respectively, and qt + qb is total THERMAL POWER in percent RATED THERMAL POWER_

  • This is a Safety Analysis value. Refer to Technical Requirements Manual for nominal value of this coefficient used in programming the trip setpoint.

Page 12 of 16

D. C. COOK UNIT 1 CYCLE 22 Revision 0 D. C. COOK UNIT 1 CYCLE 22 Revision 0 FIGURE 5 (Page 2 of 2)

Overpower AT Trip Setpoint Overpower AT _ AT. [K4 - K5 (AI)]

[T /s T- K 6 (T- T")- f2 Where: AT = Measured RCS AT, 'F AT, = Indicated AT at RATED THERMAL POWER, 'F T = Average temperature, 'F

= Nominal Tavg at RATED THERMAL POWER (*_<562.1 cF)

K4 < 1.172*

K5 > 0.0177/F for increasing average temperature ; Ks = 0 for decreasing average temperature K6 > 0.0015/F for T greater than T"' ; I4 = 0 for T less than or equal to T"

-r3 S

- The function generated by the rate lag controller for T.* dynamic 1+-r3 s compensation "13 = Time constant utilized in the rate lag controller for Tavg "C3> 10 seCs.

S = Laplace transform operator, sec-1 f 2(A1 = 0.0

  • This is a Safety Analysis value. Refer to Technical Requirements Manual for nominal value of this coefficient used in programming the trip setpoint.

Page 13 of 16

D. C. COOK UNIT I CYCLE 22 Revision 0 D. C. COOK LJT~IT 1 CYCLE 22 Revision 0 FIGURE 6 Reactor Core Safety Limits 660 650 UNACC PTABLE ACE2400 psiaBLE QPFRATION 640 * ~~~2250 ,sia.* -. *

-630 *"" 2100 psia ýý

> 620 *i2000 psia/*

  • 610 ir 600 590 ACCEP TABLE OPER, TION 580 570 0 0.2 0.4 0.6 0.8 1 1.2 Power (fraction of rated thermal power)

DESCRIPTION OF SAFETY LIMITS PRESSURE Power Tavg Power Tavg Power Tavg (PSIA) (frac) ('-F) (Mrac) (frac) (IF) 1840 0.02 620.86 1.136 586.17 1.2 577.94 2000 0.02 632.79 1.094 600.31 1.2 586.52 2100 0.02 639.85 1.068 608.72 1.2 591.77 2250 0.02 649.96 1.031 620.83 1.2 599.40 2400 0.02 659.52 0.996 632.42 1.2 606.63 UNIT I Reactor Core Safety Limits Page 14 of 16

D. C. COOK UNIT 1 CYCLE 22 Revision 0 FIGURE 7 Unit 1 Cycle 22 Predicted HFP ARO 300 PPM MTC Versus Burnup

-1.98E-04

-2. OOE-04 v-2.02E-04 CL 03 S2.04E-04

-2.10E-040 14000 15000 16000 17000 18000 Cycle Bumup (MWDIMTU)

.Burnup (MWDIMTU) MTC (AklkI0 F) 14000 -1.9860E-4 15000 -2.0161E-4 16000 -2.0401 E-4 17000 -2.0702E-4 18000 -2.0971E-4 Page 15 of 16

D. C. COOK UNIT 1 CYCLE 22. Revision 0 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 22 w(z) FUNCTION Node Height Burnup (MWD/MTU)

PT (Ft.) 150 1000 2000 4000 6000 8000 10000 12000 14000 16000 18000 19430 1 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2 0.2 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.60000 3 0.4 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.6 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.8 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 7 1.2 1.0986 1.0958 1.0937 1.0942 1.0988 1.1049 1.1105 1.1157 1.1209 1.1267 1.1325 1.1364 8 1.4 1.0987 1.0962 1.0943 1.0948 1.0992 1.1049 1.1101 1.1149 1.1198 1.1252 1.1305 1.1341 9 1.6 1.0987 1.0964 1.0947 1.0952 1.0993 1.1046 1.1094 1.1138 1.1182 1.1231 1.1279 .1.1313 10 1.8 1.0984 1.0964 1.0949 1.0955 1.0991 1.1039 1.1082 1.1121 1.1161 1.1204 1.1247 1.1276 11 2.0 1.0979 1.0962 .1.0949 1.0955 .1.0987 1.1028 1.1066 1.1100 1.1134 1.1170 1.1207 1.1233 12 2.2 .1.0972 1.0958 1.0948 1.0954 1.0980 1.1014 1.1045 1.1074 1.1102 1.1132 1.1163 1.1184 13 2.4 1.0962 1.0953 1.0946 1.0950 1.0971 1.0997 1.1021 1.1043 1.1065 1.1089 1.1112 1.1129 14 2.6 1.0950 1.0945 1.0941 1.0945 1.0959 1.0977 1.0993 1.1008 1.1024 1.1040 1.1057 1.1068 15 2.8 1.0936 1.0935 1.0934 1.0937 1.0944 1.0953 1.0961 1.0970 1.0979 1.0989 1.0998 1.1005 16 3.0 1.0919 1.0922 1.0925 1.0927 1.0927 1.0927 1.0928 1.0930 1.0933 1.0936 1.0939 1.0941 17 3.2 1.0902 1.0908 1.0912, 1.0913 1.0908 1.0900 1.0895 1.0891 1.0887 1.0884 1.0880 1.0877 18 3.4 1.0892 1.0897 1.0901 1.0898 1.0888 1.0876 1.0866 1.0859 1.0853 1.0847 1.0840 1.0835 19 3.6 1.0887 1.0896 1.0903 1.0898 1.0879 1.0860 1.0851 1.0850 1.0855 1.0864 1.0868 1.0869 20 3.8 1.0882 1.0895 1.0904 1.0897 1.0872 1.0848 1.0841 1.0848 1.0867 1.0893 1.0910 1.0919 21 4.0 1.0878 1.0892 1.0902 1.0893 1.0863 1.0838 1.0834 1.0852 1.0884 1.0927 1.0958 1.0975 22 4.2 1.0871 1.0887 1.0898 1.0889 1.0859 '1.0834 1.0835 1.0860 1.0903 1.0959 1.1000 1.1024 23 4.4 1.0863 1.0880 1.0892 1.0886 1.0859 1.0838 1.0845 1.0876 1.0926 1.0990 1.1038 1.1067 24 4.6 1.0854 1.0871 1.0884 1.0880 1.0857 1.0840 1.0852 1.0889 1.0945 1.1017 1.1073 1.1106 25 4.8 1.0843 1.0860 1.0874 1.0872 1.0852 1.0840 1.0857 1.0900 1.0962 1.1041 1.1102 1.1140 26 5.0, 1.0831 1.0847 1.0860 1.0860 1.0845 1.0838 1.0860 1.0908 1.0975 1.1059 1.1126 1.1167 27 5.2 1.0820 1.0833 1.0844 1.0845 1.0834 1.0834 1.0861 1.0913 1.0984 1.1072 1.1144 1.1188 28 5.4 1.0807 1.0817 1.0826 1.0827 1.0821 1.0827 1.0859 .1.0914 1.0989 1.1080 1.1154 1.1201 29 5.6 1.0791 1.0799 1.0806 1.0808 1.0806 1.0816 1.0852 1.0910 1.0987 1.1080 1.1158 1.1207 30 5.8 1.0772 1.0778 1.0784 1.0788 1.0793 1.0809 1.0848 1.0908 1.0984 1. 1075 1.1152 1.1201 31 6.0 '1.0752 1.0755 1.0760 1.0770 1.0783 1.0808 1.0850 1.0908 1.0979 1.1064 1.1136 1.1183 32 6.2 1.0735 1.0734 1.0736 1.0748 1.0771 1.0805 1.0850 1.0905 1.0970 1.1045 1.1112 1.1156 33 6.4 1.0721 1.0712 1.0707 1.0720 1.0753 1.0797 1.0845 1.0897 1.0954 1.1018 1.1078 1.1119 34 6.6 1.0704 1.0685 1.0673 1.0685 1.0728 1.0783 1.0834 1.0881 1.0929 1.0981 1.1032 1.1068 35 6.8 1.0683 1.0662 1.0647 1.0659 1.0705 1.0762 1.0813 1.0859 1.0903 1.0950 1.0999 1.1032 36 7.0 1.0666 1.0647 1.0635 1.0645 1.0686 1.0739 1.0788 1.0836 1.0884 1.0936 1.0988 1.1024 37 7.2 1.0645 1.0631 1.0623 1.0638 1.0681 1.0735 .1.0785 1.0833 1.0882 1.0935 1.0987 1.1023 38 7.4 . 1.0622 1.0610 1.0605 1.0636 1.0701 1.0770 1.0826 1.0868 1.0903 1.0935 1.0974 1.1003 39 7.6 1.0654 1.0635 1.0625 1.0656 1.0727 1.0803 1.0857 1.0891 1.0912 1.0927 1.0953 1.0974 40 7.8 1.0709 1.0687 1.0674 1.0698 1.0761 1.0829 1.0874 1.0898 1.0909 1.0912 1.0927 1.0941 41 8.0 1.0754 1.0738 1.0728 1.0748 1.0799 1.0852 1.0883 1.0896 1.0895 1.0887 1.0889 1.0894 42 8.2 1.0800 1.0786 1.0778 1.0793 1.0832 1.0870 1.0889 1.0891 1.0881 1.0863 1.0855 1.0853 43 8.4 1.0843. 1.0833 1.0827 1.0835 1.0860 1.0884 1.0895 1.0893 1.0884 1.0868 1.0860 1.0857 44 8.6 1.0883 1.0877 1.0873 .1.0874 1.0883 1.0892 1.0894 1.0891 1.0883 1.0873 1.0866 1.0862 45 8.8 1.0920 1.0919 1.0916 1.0911 1.0905 1.0901 1.0898 1.0898 1.0899 1.0902 1.0904 1.0904 46 9.0 1.0954 1.0957 1.0957 1.0945 1.0926 1.0910 1.0906 1.0913 1.0929 1.0951 1.0966 1.0974 47 9.2 1.0985 1.0991 1.0994 1.0975 1.0941 1.0913 1.0906 1.0920 1.0949 1.0989 1.1017 1.1032 48 9.4 1.1011 1.1022 1.1027 1.1002 1.0952 1.0911 1.0902 1.0922 1.0964 1.1024 1.1065 1.1087 49 . 9.6 1.1035 1.1050 1.1058 1.1030 1.0973 1.0925 1.0914 1.0939 1.0988 1.1058 1.1106 1.1132 50 9.8 1.1057 1.1076 1.1087 1.1062 1.1006 1.0957 1.0947 1.0971 1.1021 1.1090 1.1138 1.1164 51 10.0 1.1079 1.1101 1.1116 1.1096 1.1.041 1.0992 1.0982 1.1005 1.1053 1.1121 1.1166 1.1191 52 10.2 1.1093 1.1118 1.1137 1.1122 1.1070 1.1023 1.1013 1.1036 1.1083 1.1147 1.1191 1.1215 53 10.4 1.1098 1.1125 1.1145 1.1136 1.1091 1.1050 1.1042 1.1065 1.1109 1.1169 1.1210 1.1233 54 10.6 1.1150 1.1193 1.1225 1.1210 1.1139 1.1071 1.1054 1.1083 1.1144 1.1227 1.1283 1.1314 55 10.8 1.1139 1.1178 1.1208 1.1201 1.1144 1.1088 1.1074 1.1097 i.1145 1.1211 1.1255 1.1279 56 11.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.2 ,1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.4 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.6 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.8 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 61 12.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Top and bottom 10% of core excluded.

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