AEP-NRC-2009-76, Revised Core Operating Limits Report

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Revised Core Operating Limits Report
ML093100291
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 10/29/2009
From: Weber L
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2009-76
Download: ML093100291 (18)
v • d • e


Text

Indiana Michigan Power Company IDIDANAi Nuclear Generation Group IMICIGAN One Cook Place MICHIGAM Bridgman, Ml 49106 FKI ER aep.com October 29, 2009 AEP-NRC-2009-76 10 CFR 50.4 Docket No.: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 REVISED CORE, OPERATING LIMITS REPORT Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 1, is submitting a revised Core Operating Limits Report (COLR) for Unit 1 Cycle 22 in accordance with Technical Specification 5.6.5. The Unit 1 Cycle 22 COLR has been revised to reflect a new large break loss-of-coolant accident analysis approved by the Nuclear Regulatory Commission as License Amendment 306, (ADAMS Accession Number. ML082670351), incorporate Westinghouse recommended changes regarding calculation of the heat flux hot channel factor (FQ(Z)) at less than full power, and adopt a minor format change for consistency with the Unit 2 COLR.

Revision 1 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, Lawrence J. Weber Site Vice President JRW/rdw Attachment c: T. A. Beltz, NRC Washington DC J. T. King, MPSC S. M. Krawec, Ft. Wayne AEP, w/o attachment MDEQ - WHMD/RPS NRC Resident Inspector M. A. Satorius, NRC Region III

ATTACHMENT TO AEP-NRC-2009-76 Donald C. Cook Nuclear Plant Unit 1 Cycle 22 Core Operating Limits Report Revision 1

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

D. C. COOK UNIT I CYCLE 22 Revision I 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. Plant-specific adaptation of WCAP-16009-P-A, Revision 1, Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), as approved by NRC Safety Evaluation dated October 17, 2008.
e. WCAP-126 10-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 (FNMI) 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 I CYCLE 22 Revision 1 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 Tvg > 200OF 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/°F.

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

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 1 CYCLE 22 Revision I

b. The MTC Surveillance limit is:

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

-3.84E-4 Ak/k/°F 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/JF 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 I D. C. COOK UNIT 1 CYCLE 22 Revision 1 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

FJ(Z)<-- P

  • K(Z) for P> 0.5 F*c (Z) <2
  • CFQ
  • K(Z) for P<0.5 F (Z)< CFQ, *K(Z) for P > 0.5 P

Ffw (Z)<* 2

  • CFQ
  • K(Z) for P<0.5 THERMAL POWER Where: P=

RATED THERMAL POWER

a. CFQ = 2.15
b. K(Z) is provided in Figure 4.
c. FIQ(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 I for +/-5% AFD target band.
e. FwQ(Z) - F4e(Z) x W(Z) x Fp The W(z) values are generated assuming that they will be used for a full power surveillance. When a part power surveillance is performed, the W(z) values should be multiplied by the factor lI/P, when P is > 0.5. When P is < 0.5, the W(z) values should be multiplied by the factor 11(0.5), or 2.0. This is consistent with the adjustment in the FQ(z) limit at part power conditions.

Page 5 of 16

D. C. COOK UNIT 1 CYCLE 22 Revision 1

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 Burnup 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 bumups.

2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (FN A) (Specification 3.2.2)

FNeA < CFAl * (1 + PFAH *(I-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 +

Page 6 of 16

A C. COOK UNIT I CYCLE 22 Revision 1

b. Reactor Coolant System TAVG shall be _<580.5 0F +
c. Reactor Coolant System Total Flow Rate shall be > 366,400 gpm 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

D. C. COOK UNIT 1 CYCLE 22 Revision 1 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 - Y - Y- - - q. - - - r -

I _ I _ I II_

[UNACCEPTABLE OPERAT16N 0.5 LL (U.

0 0.0 O ACCEPTABLE OPERATION x

-0.5

-1.0 - - - - - - - - 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 22 Revision 1 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250 225 200 E

175 cu 150

-0 0L z 125 0

0 0

100 03 0_

0 W 75 50 25 0

POWER (% of Rated Thermal Power)

Page 9 of 16

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

N 70 60 0 50 RLEY 40 E 30 20 0

10 0

FLUX DIFFERENCE (DELTA-I)

Page 10 of 16

D. C. COOK UNIT I CYCLE 22 Revision 1 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 0.6

-Jl N

o 0z 0.4 I I I I I 0.2 0 I 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 1 FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT < AT [K1 - K2 [1 + TS 1 (T-T') + K3 (P-P') - fl (A0]

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

T = Average temperature, OF T = Nominal T.vg at RATED THERMAL POWER ( *574.0 OF)

P = Pressurizer pressure, psig P = Nominal RCS operating pressure (2085 psig) 1+1-,s

___ = The function generated by the lead-lag controller for Tvg dynamic 1+ T2S compensation 1l, x2 = Time constants utilized in the lead-lag controller for T.vg

¶ 1>22 secs. x2 _<4 secs.

S = Laplace transform operator, sec-K, < 1.35*

K2 > 0.0230/0 F K(3 > 0.00110/psi fl (Al) = -0.33 {37% + (q, - 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 qt 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 22 Revision 1 FIGURE 5 (Page 2 of 2)

Overpower AT- Trip Setpoint Overpower AT <ATo [K 4 - Ks5 11 r3 S] T - K 6 (T - T") - f2 (AI)]

Where: AT Measured RCS AT, OF AT. = Indicated AT at RATED THERMAL POWER, °F T = Average temperature, OF T" = Nominal Ta,9 at RATED THERMAL POWER (*_<562.1 OF)

K4 < 1.172*

K5 0.0177/1F for increasing average temperature ; K5 = 0 for decreasing average temperature K6 > 0.00 15/°F for T greater than T" ; K 6 = 0 for T less than or equal to T" r3S =

_ _ The function generated by the rate lag controller for Tavg dynamic 1 + -3S compensation T3 = Time constant utilized in the rate lag controller for Tavg 3> 10 secs.

S = Laplace transform operator, sec1 f2(AI) = 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 1 CYCLE 22 Revision 1 D. C. COOK UNIT 1 CYCLE 22 Revision 1 FIGURE 6 Reactor Core Safety Limits 660 650 UNACCE PTABLE 2400 psia--V QPFR NTION 640 22501psia,-700

- 630 2100 Psia:>'-ý

> 620 2000 psia"V M

610 1840 psia-,V I 600 590 ACCEPTABLE OPER, MON 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 I Reactor Core Safety Limits Page 14 of 16

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

-1.98E-04

-2.OOE-04 2

  • -2.02E-04

.2 U

0 o -2.04E-04 E

I- -2.06E-04 0

-2.08E-04

-2.1OE-04 I 14000 15000 16000 17000 18000.

Cycle Burnup (MWD/MTU)

Burnup (MWD/MTU) MTC (AkJIkF) 14000 -1.9860E-4 15000 -2.0161E-4 16000 -2.0401 E-4 17000 -2.0702E-4 18000 -2.0971 E-4 Page 15 of 16

D. C. COOK UNIT 1 CYCLE 22 Revision 1 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 22 W(Z) FUNCTION Node Height Burnup (MWDIMTU)

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 1.0000 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 1.0986 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 1.1041 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 1.1145 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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