ML063260270

Submittal of Cook, Unit 1 - Core Operating Limits Report

ML063260270
Person / Time
Site:	Cook
Issue date:	11/13/2006
From:	Peifer M Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:6565-01
Download: ML063260270 (18)

Text

Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place pYIER Bridgman, MI 49106 AEPcom A unit of American Electric Power November 13, 2006 AEP:NRC:6565-01 10 CFR 50.4 Docket No.: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-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 21 in accordance with Technical Specification 5.6.5. .

Revision 0 of the Unit'l Cycle 21 COLR is provided as an attachment to this letter.

There are no new commitments in this submittal. Should you have any questions, please contact Ms. Susan D. Simpson, Regulatory Affairs Manager, at (269) 466-2428.

KAS/jen Attachment c: J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne J. T. King - MPSC MDEQ - WHMD/RPMWS NRC Resident Inspector P. S. Tam - NRC Washington DC 4co~(

ATTACHMENT TO AEP:NRC:6565-O1 Donald C. Cook Nuclear Plant Unit / Cycle 21 Core Operating Limits Report Revision 0

A,

/

D. C. COOK UNIT 1 CYCLE 21 Revision 0

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Donald C. Cook Nuclear Plant Unit I Cycle 21 Core Operating Limits Report Revision 0 Page 1 of 16

D. C. COOK UNIT I CYCLE 21 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit I Cycle 21 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 (FNr) 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 21 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 (T.vg) 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 T.ag program with HFP vessel T.vg 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

A C. COOK UNIT 1 CYCLE 21 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/k/OF 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/IF.

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

A C. COOK UNIT I CYCLE 21 Revision 0 D. C. COOK UNIT 1 CYCLE 21 Revision 0 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

FQ (Z) CFQ

• K(Z) for P> 0.5 P

FQc(Z)*_ 2

• CFO

• K(Z) for P5 0.5 CFo FQ" (Z) <_---- = K(Z) for P> 0.5 P

Fow (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. IQ(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) = F c(Z) x W(Z) x F,

f. For Cycle 21, 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 Bumup Penalty (MWD/MTU) Multiplier 590 1.020 736 1.022 883 1.023 1030 1.023 1176 1.021 1323 1.020 The bumup range only covers where Fp exceeds 1.02. Linear interpolation is adequate for intermediate cycle bumups.

Page 5 of 16

D. C. COOK UNIT I CYCLE 21 Revision 0 D. C. COOK UNIT 1 CYCLE 21 Revision 0 2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (FNAH ) (Specification 3.2.2) leAH< CFAH * (I + PFAI *(1-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 21 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 Keff < 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

A C. COOK UNIT 1 CYCLE 21 Revision 0 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 UNACCEPTABLE OPERATION 0.5 LL 0

a) 1.

0.0

[ACCEPTABLE OPERATI N]

0 H-

-0.5

-1.0 L. - I- I- I- J.- J. - I I- I- -

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 21 Revision 0 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (FOUR-LOOP OPERATION) 250 225 200 175 CL 150 z 125 0

Ci2 0

100 0~

0~

CD 75 50 25 0

0 10 20 30 40 50 60 70 80 90 100 POWER (% of Rated Thermal Power)

Page 9 of 16

D. C. COOK UNIT 1 CYCLE 21 Revision 0 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 90 0

x 80 N

70 xa 60 0H 50 E 40 0~

E 30 20 0

10 0

FLUX DIFFERENCE (DELTA-I)

Page 10 of 16

A C. COOK UNIT 1 CYCLE 21 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 Lu zU N

0.6 0

n-0 z

0.4 0.2 0 d I 0 2 4 6 8 10 12 CORE HEIGHT (FT)

Page 11 of 16

D. C. COOK UNIT 1 CYCLE 21 Revision 0 FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT AT. [KI - V(2 1_+ 1 1 + T2SJ 1L 1 (T-T') + K3 (P-P') - f, (AI)]

Where: AT = Measured RCS AT, 'F AT = Indicated AT at RATED THERMAL POWER, 'F 0

T = Average temperature, 'F T' = Nominal Tavg at RATED THERMAL POWER ( *574.0 'F)

P = Pressurizer pressure, psig P = Nominal RCS operating pressure (2085 psig) 1 + Trs 1 + T2s 1 2 The function generated by the lead-lag controller for Tavg dynamic compensation 1 T2 = Time constants utilized in the lead-lag controller for Tavg tI* 22 secs. r2 < 4 secs.

S = Laplace transform operator, sec-1 K1 < 1.35

• K2 > 0.0230/ 0 F K3 > 0.00110/psig f1 (Al) = -0.33 {37% + (q, - qb)} when q, - qb < -37% RTP 0% of RTP when -37% RTP < q, - qb < 3% RTP

+2.3 4 {(q, - qb)-- 3 %} when q, - qb > 3% RTP where q%and qb are percent RATED THERMAL POWER in the upper and lower halves of the core respectively, and q, + 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 I CYCLE 21 Revision 0 D. C. COOK UNIT 1 CYCLE 21 Revision 0 FIGURE 5 (Page 2 of 2)

Overpower AT Trip Setpoint Overpower AT

• ATo [K4 - K5 E 'r3 s 1 i+ 3 i-6(

K(-T)f

")-f 2 A)

A Where: AT = Measured RCS AT, 'F ATo = Indicated AT at RATED THERMAL POWER, OF T = Average temperature, OF T" = Nominal Tavg at RATED THERMAL POWER ( _< 562.1 -F)

K4 < 1.172

• K5 _ 0.0177/°F for increasing average temperature ; K5 = 0 for decreasing average temperature K6 > 0.00 15/°F for T greater than T" ; K6 = 0 for T less than or equal to T"

-r3 s The function generated by the rate lag controller for Tavg dynamic compensation T3 Time constant utilized in the rate lag controller for Tavg T3> 10 secs.

S Laplace transform operator, sec"1 f2(Al) 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

A C. COOK UNIT 1 CYCLE 21 Revision 0 D. C. COOK UNIT 1 CYCLE 21 Revision 0 FIGURE 6 Reactor Core Safety Limits 660 650 640 LL 630

> 620 610 U,

W 600 590 580 570 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) (frac) (IF) (frac) 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 1 Reactor Core Safety Limits Page 14 of 16

D. C. COOK UNIT 1 CYCLE 21 Revision 0 FIGURE 7 Unit 1 Cycle 21 Predicted HFP ARO 300 PPM MTC Versus Burnup

-2.01 E-04

-2.03E-04

• -2.05E-04 1!

0 -2.07E-04 U

0

. -2.09E-04 0

02.

E I-S-2.11 E-04 0

-2.1 3E-04

-2.15E-04 1-13000 14000 15000 16000 17000 Cycle Burnup (MWDIMTU)

Burnup (MWDIMTU) MTC (Ak/k/-F) 13000 -2.0185E-4 14000 -2.0487E-4 15000 -2.0764E-4 16000 -2.1035E-4 17000 -2.1293E-4 Page 15 of 16

D. C. COOK UNIT 1 CYCLE 21 Revision 0 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 21 W(Z) FUNCTION Node Height Burnup (MWD/MTU)

No, (feet) 150 1000 2000 4000 5000 6000 8000 10000 12000 14000 16000 18614 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 1.0000 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 1,0989 1.1004 1.1019 1.1035 1.1039 1.1043 1.1057 1.1088 1.1134 1.1192 1.1257 1.1323 8 1.4 1.0990 1.0991 1.0995 1.1008 1.1017 1.1028 1.1056 1.1092 1.1136 1.1187 1.1244 1.1305 9 1.6 1.0989 1.0977 1.0969 1.0979 1.0993 1.1011 1.1052 1.1093 1.1134 1.1177 1.1225 1.1282 10 1.8 1.0985 1.0972 1.0964 1.0973 1.0986 1.1004 1.1044 1.1082 1.1119 1.1158 1.1200 1.1251 11 2.0 1.0979 1.0969 1.0962 1.0970 1.0982 1.0998 1.1032 1.1066 1.1098 1.1132 1.1169 1.1214 12 2.2 1.0971 1.0962 1.0957 1.0965 1.0975 1.0988 1.1017 1.1045 1.1073. 1.1101 1.1133 1.1171 13 2.4 1.0960 1.0954 1.0951 1.0957 1.0965 1.0975 1.0998 1.1021 1.1043 1.1066 1.1092 1.1122 14 2.6 1.0947 1.0944 1.0942 1.0947 1.0953 1.0960 1.0976 1.0992 1.1009 1.1026 1.1046 1.1069 15 2.8 1.0932 1.0931 1.0931 1.0934 1.0937 1.0941 1.0950 1.0960 1.0971 1.0982 1.0995 1.1010 16 3.0 1.0913 1.0915 1.0917 1.0920 1.0921 1.0922 1.0923 1.0927 1.0931 1.0937 1.0942 1.0949 17 .3.2 1.0895 1.0899 1.0902 1.0903 1.0902 1.0900 1.0896 1.0894 1.0893 1.0893 1.0892 1.0890 18 3.4 1.0884 1.0886 1.0888 1.0886 1.0883 1.0879 1.0870 1.0864 1.0860 1.0857 1.0854 1.0849 19 3.6 1.0876 1.0882 1.0886 1.0881 1.0875 1.0867 1.0851 1.0844 1.0842 1.0845 1.0850 1,0850 20 3.8 1.0867 1.0877 1.0884 1.0877 1.0868 1.0856 1.0837 1.0831 1.0837 1.0851 1.0869 1.0880 21 4.0 1.0860 1.0871 1.0878 1.0870 1.0859 1.0846 1.0825 1.0824 1.0839 1.0867 1.0902 1.0927 22 4.2 1.0854 1.0864 1.0871 1.0862 1.0851 1.0838 1.0821 1.0824 1.0847 1.0883 1.0929 1.0564 23 4.4 1.0846 1.0855 1.0861 1.0854 1.0844 1.0835 1.0822 1.0831 1,0859 1.0902 1.0954 1.0997 24 4,6 1.0835 1,0845 1.0852 1.0847 1.0839 1.0831 1.0823 1.0836 1.0870 1.0918 1.0976 1.1026 25 4.8 1.0826 1.0835 1.0841 1.0838 1.0832 1.0825 1.0821 1.0839 1.0877 1.0930 1.0994 1.1050 26 5.0 1.0817 1.0823 1.0828 1.0825 1.0821 1.0817 1.0818 1.0840 1.0882 1.0940 1.1008 1.1070 27 5.2 1.0807 1.0810 1.0813 1.0810 1.0807 1.0806 1.0812 1.0839 1.0884 1.0945 1.1017 1.1084 28 5.4 1.0795 1.0795 1.0794 1.0792 1.0791 1.0792 1.0803 1.0834 1.0883 1.0946 1.1021 1.1092 29 5.6 1.0780 1.0776 1.0773 1.0770 1,0771 1,0774 1.0791 1.0826 1.0877 1.0942 1.1019 1.1094 30 5.8 1.0763 1.0757 1.0753 1.0751 1.0753 1.0759 1.0780 1.0818 1.0870 1.0934 1.1011 1.1086 31 6.0 1.0745 1.0737 1.0731 1.0733 1.0739 1.0749 1.0778 1.0817 1.0867 1.0926 1.0995 1.1066 32 6.2 1.0729 1.0715 1.0705 1.0710 1.0723 1.0740 1.0780 1.0822 1.0867 1.0917 1.0973 1.1036 33 6.4 1.0712 1.0691 1.0676 1.0683 1.0701 1.0724 1.0775 1.0820 1.0860 1.0900 1.0943 1.0998 34 6.6 1.0691 1.0667 1.0649 1.0660 1.0681 1.0708 1.0766 1.0811 1.0846 1.0877 1.0909 1.0956 35 6.8 1.0672 1.0650 1.0634 1.0646 1.0667 1.0693 1.0749 1.0793 1.0828 1.0859 1.0891 1.0938 36 7.0 1.0655 1.0637 1.0626 1.0642 1.0663 1.0689 1.0744 1.0788 1.0823 1.0853 1.0885 1.0931 37 7.2 1.0635 1.0620 1.0613 1.0637 1.0663 1.0694 1.0755 1.0800 1.0832 1.0856 1.0878 1.0918 38 7.4 1.0624 1.0612 1.0607 1.0643 1.0676 1.0712 1.0782 1.0828 1.0853 1.0864 1.0869 1.0898 39 7.6 1.0659 1.0648 1.0644 1.0678 1.0708 1.0742 1.0805 1.0843 1.0859 1.0861 1.0855 1.0871 40 7.8 1.0712 1.0701 1.0695 1.0721 1.0745 1.0773 1.0823 1,0849 1.0855 1.0847 1.0831 1.0834 41 8.0 1.0757 1.0745 1.0738 1.0756 1.0775 1.0797 1.0836 1.0854 1.0855 1.0842 1.0824 1.0820 42 8.2 1.0802 10790 1.0781 1.0790 1.0802 1.0817 1.0845 1.0859 1.0860 1.0854 1.0845 1.0845 43 8.4 1.0845 1.0832 1.0821 1.0819 1.0825 1.0833 1.0848 1.0857 1.0860 1.0860 1.0860 1.0863 44 8.6 1.0885 1.0871 1.0859 1.0846 1.0844 1.0844 1.0846 1.0850 1.0853 1.0859 1.0867 1.0874 45 8.8 1.0922 1.0908 1.0894 1.0872 1.0864 1.0858 1.0852 1.0854 1.0862 1.0877 1.0898 1.0913 46 9.0 1.0956 1.0943 1.0928 1.0902 1.0892 1.0883 1.0873 1.0876 1.0891 1.0916 1.0949 1.0974 47 9.2 1.0987 1.0976 1.0963 1.0935 1.0921 1.0909 1.0894 1.0898 1.0918 1.0952 1.0996 1.1030 48 9.4 1.1014 1.1005 1.0994 1.0963 1.0947 1.0932 1.0914 1.0918 1.0943 1.0985 1.1040 1.1082 49 9.6 1.1036 1.1030 1.1021 1.0990 1.0971 1.0954 1,0932 1.0937 1.0967 1.1016 1.1080 1.1129 50 9.8 1.1057 1.1052 1.1042 1.1010 1.0990 1.0972 1.0948 1.0954 1.0988 1.1043 1.1114 1.1168 51 10.0 1.1078 1.1072 1.1063 1.1028 1.1007 1.0988 1.0963 1.0971 1.1007 1.1068 1.1145 1.1205 52 10.2 1.1092 1.1084 1.1073 1.1038 1.1018 1.0999 1.0976 1.0986 1.1025 1.1087 1.1166 1.1228 53 10.4 1.1098 1.1090 .1.1079 1.1046 1.1027 1.1010 1.0989 1.1000 1.1037 1.1098 1.1175 1.1235 54 10.6 1.1135 1,1153 1.1163 1.1127 1.1093 1.1056 1.1002 1.1007 1.1061 1.1152 1.1267 1.1353 55 10.8 1.1130 1.1146 1.1155 1.1128 1.1098 1.1066 1.1017 1.1017 1.1059 1.1132 1.1226 1.1295 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.

Page 16 of 16