AEP-NRC-2013-44, Cycle 25, Core Operating Limits Report

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Cycle 25, Core Operating Limits Report
ML13134A476
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 05/13/2013
From: Gebbie J
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2013-44
Download: ML13134A476 (17)
v • d • e


Text

INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant AoWERi One Cook Place Bridgman, MI 49106 A unit of American Electric Power Indiana Mic higa nPower.com May 13, 2013 AEP-NRC-2013-44 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 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 25 in accordance with Technical Specification 5.6.5. Revision 0 of the Unit 1 Cycle 25 COLR is provided as an enclosure to this letter.

There are no new or revised commitments in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.

Sincerely, Joel P. Gebbie Site Vice President DMB/kmh

Enclosure:

Donald C. Cook Nuclear Plant Unit 1 Cycle 25 Core Operating Limits Report, Revision 0 c: C. A. Casto, NRC Region III J. T. King, MPSC S. M. Krawec, AEP Ft. Wayne, w/o enclosures MDEQ - RMD/RPS NRC Resident Inspector T. J. Wengert, NRC Washington, DC A b C)(

ENCLOSURE TO AEP-NRC-2013-44 Donald C. Cook Nuclear Plant Unit 1 Cycle 25 Core Operating Limits Report Revision 0

D. C. COOK UNIT 1 CYCLE 25 Revision 0 D. C. COOK UNIT 1 CYCLE 25 Revision 0 Donald C. Cook Nuclear Plant Unit I Cycle 25 Core Operating Limits Report Page 1 of 15

D. C. COOK UNIT I CYCLE 25 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report(COLR) for Donald C. Cook Nuclear Plant Unit 1 Cycle 25 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
h. WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, Optimized ZIRLOTM, July 2006 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 (FNAH) 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 15

D. C. COOK UNIT 1 CYCLE 25 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 Specification 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 (Taig) 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> 200OF Shutdown margin shall be greater than or equal to 1.0% Ak/k for Tavg -*200°F 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 Tayg program with HFP vessel Tavg 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 15

D. C. COOK UNIT 1 CYCLE 25 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/lF at a HFP vessel Tav9 of 554.0 to 558.0 'F.

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/0 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/0 F at a HFP vessel Tavg of 554.0 to 558.0 'F 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 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0 D. C. COOK UNIT 1 CYCLE 25 Revision 0 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

CF0 F~((z):__-

  • K(Z) for P>0.5 P

Fo (Z)< 2

  • CFQ
  • K(Z) for P<0.5 CF FAV (Z)5 Q for P>0.5 P

F*f (Z) <_2

  • CFo
  • 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. F1 (Z) = Fc(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 I/P, when P is > 0.5. When P is _<0.5, the W(z) values should be multiplied by the factor 1/(0.5), or 2.0. This is consistent with the adjustment in the FQ(z) limit at part power conditions.
f. For Cycle 25, Fp = 1.02 for all burnups associated with Note 2a of SR 3.2.1.2.

When no penalty is required, Fp = 1.00.

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

FNt

  • CFAH * (1 + PFH *(I-P))

Where: P - RATED THERMAL POWER THERMAL POWER Page 5 of 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0

a. CFAl= 1.545
b. PFH = 0.3
c. FNM is the measured Enthalpy Rise Hot Channel Factor including a 4% measurement uncertainty.

2.4 INSTRUMENTATION 2.4.1 Reactor Trip System (RTS) Instrumentation (Specification 3.3.1)

The Overtelnperature 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 TAVO shall be < 580.5 0 F +
c. Reactor Coolant System Total Flow Rate shall be > 362,900 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 0 F for Tavg, and 2050 psig for Pressurizer Pressure.

++ This concentration bounds the condition of KIff 5 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 6 of 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0

-UNACCEPTABLE OPERATION 0.5 0

U..

0.0 Cb)

[ACCEPTABLE OPERATION]

x H

-0.5

-1.0 - . - . - a- a- a- a- - - a- a-0 10 20 30 40 50 60 70 80 90 100 Percent Rated Thermal Power Page 7 of 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0 D. C. COOK UNIT 1 CYCLE 25 Revision 0 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250 -

225 U52.9%,_228) 100 Step Overl ap 200 B-AN-KC / 1 175 CL 150 Cl) z 125 0

U) 0 100 0~

0~

0 75 50 25 0

30 40 50 60 70 POWER (% of Rated Thermal Power)

Page 8 of 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 90 x 80 N

70 60 a-50 I-40 E

30 20 0I-0 10 0 0-1 50 FLUX DIFFERENCE (DELTA-I)

Page 9 of 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 (0.0, 1.0) (0.0_

1.0)_ ___________

(12.0, 1.0) 1.0

, I

. .-.-."L. . . . . . . . . . .....

0.8 z

0~

LU S....... .................

00.6 N I- ________

0 z 0 .4 0.2 ......

0.0 4 -~ 4 0 2 4 6 8 10 12 CORE HEIGHT (FT)

Page 10 of 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0 FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT < AT° [KI - K(2 [1+/-,1 (T-T') + K3 (P-P') - fl (AII)

L11+ VzS Where, AT = Measured RCS AT, 'F AT = Indicated AT at RATED THERMAL POWER, °F 0

T = Average temperature, 'F T' Nominal Ta,,g at RATED THERMAL POWER (

  • 574.0 °F)

P = Pressurizer pressure, psig P' Nominal RCS operating pressure (2085 psig) 1++_r-,s_ -ns The function generated by the lead-lag controller for Tavg dynamic 1+T2S compensation "c,

1 2 Time constants utilized in the lead-lag controller for Tavg "ci> 22 sees. "¢2 < 4 sees.

S = Laplace transform operator, sec-K1 < 1.35

  • K2 00.0230/ 0 F K3 >_ 0.00110/psi f, (Al) = -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 qt 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 11 of 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0 FIGURE 5 (Page 2 of 2)

Overpower AT Trip Setpoint Overpower AT* ATo [K4 - K5 [ -rS T-K6 (T - T") - f2 (AI)]

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

K4 < 1.172

  • K5 > 0.0177/'F for increasing average temperature ; Ks 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"

- The function generated by the rate lag controller for Tavg dynamic compensation x = Time constant utilized in the rate lag controller for Ta.g 'T3>_ 10 secs.

S = Laplace transform operator, sec 1 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 12 of 15

D. C. COOK UNIT I CYCLE 25 Revision 0 D. C. COOK UNIT 1 CYCLE 25 Revision 0 FIGURE 6 Reactor Core Safety Limits 660 650 UNACCI PTABLE 640 * ,* ~2250 psial-W * *,

i- 630

> 620 * ~ ~~2000 psia"-V - -

610 1840 psia--V C) fl:: 600 600 590 ACCEP M.TON TABLE IOPER, 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) (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 1 Reactor Core Safety Limits Page 13 of 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0 FIGURE 7 Unit 1 Cycle 25 Predicted HFP ARO 300 PPM MTC Versus Burnup

-2.02E-04 ___ F F F F F + +

-2.04E-04 ____ ____ F F + +

N

  • -2.06E-04 + F-~F F F f -F -

' -2.08E-04 0

0

-2.10E-04 C.

E i-0 -2.12E-04 0

0

-2.16E-04

-2.18E-04

-2.18E-04 4 F F F + + -F

?nP-04lA F - F1 14,000 15,000 16,000 17,000 18,000 Cycle Bumup (MWDIMTU)

Burnup (MWDIMTU) MTC (pcm/°F) MTC (Ak/ki/F) 14000 -20.316 -2.0316E-04 15000 -20.621 -2.0621 E-04 16000 -20.955 -2.0955E-04 17000 -21.252 -2.1252E-04 18000 -21.554 -2.1554E-04 Page 14 of 15

D. C. COOK UNIT 1 CYCLE 25 Revision 0 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 25 W(Z) FUNCTION Node Height Burnup (MWD/NMTU)

Point (M) 150 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 12000 14000 16000 18000 18703 19233 1 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 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 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 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 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 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 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 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 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 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 1.00 1.0000 1.0000 1.0000 1.0000 1.0000 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 1.20 1.1003 1.0978 1.0959 1.0952 1.0958 1.0972 1.0993 1.1019 J.1048 1.1079 1.1108 1.1163 1.1216 1.1273 1.1329 1.1347 1.1362 8 1.40 1.1003 1.0981 1.0964 1.0958 1.0964 1.0978 1.0998 1.1022 1.1049 1.1077 1.1104 1.1155 1.1204 1.1257 1.1308 1.1326 1.1339 9 1.60 1.1000 1.0982 1.0967 1.0963 1.0969 1.0981 1.1000 1.1022 1.1046 1.1072 1.1097 1.1143 1.1187 1.1236 1.1282 1.1298 1.1311 10 1.80 1.0996 1.0980 1.0968 1.0966 1.0971 1.0983 1.0999 1.1019 1.1040 1.1063 1.1085 1.1126 . 1.1165 1.1208 1.1249 1.1264 1.1274 11 2.00 1.0989 1.0977 1.0968 1.0966 1.0971 1.0982 1.0996 1.1012 1.1031 1.1050 1.1068 1.1103 1.1138 1.1174 1.1210 1.1222 1.1231 12 2.20 1.0979 1.0971 1.0965 1.0965 1.0970 1.0978 1,0990 1.1003 1.1018 1.1033 1,1048 1.1077 1.1105 1.1136 1.1165 1.1175 1,1183 13 2.40 1.0968 1.0963 1.0961 1.0961 1.0966 1.0972 1.0981 1.0991 1.1002 1.1013 1.1024 1.1046 1.1068 1.1092 1.1114 1.1122 1.1128 14 2.60 1.0954 1.0954 1.0954 1.0956 1.0959 1.0964 1.0970 1.0976 1.0982 1.0990 1.0997 1.1012 1.1027 1.1044 1.1059 1.1065 1.1069 15 2.80 1.0939 1.0942 1.0945 1.0948 1.0950 1.0953 1.0955 1.0957 1.0960 1.0962 1.0965 1.0973 1.0981 1.0991 1.1000 1.1003 1.1005 16 3.00 1.0920 1.0927 1.0934 1.0939 1.0940 1.0941 1.0940 1.0938 1.0936 1.0934 1.0932 1.0932 1.0933 1.0935 1.0936 1.0937 1.0937 17 3.20 1.0902 1.0912 1.0920 1.0925 1.0926 1.0924 1.0921 1.0916 1.0910 1.0904 1.0899 1.0891 1.0885 1.0879 1.0873 1.0871 1.0869 18 3.40 1.0889 1.0899 1.0907 1.0911 1.0910 1.0906 1.0899 1.0891 1.0883 1.0874 1.0867 1.0856 1.0849 1.0842 1.0834 1.0831 1.0829 19 3.60 1.0883 1.0897 1.0909 1.0913 1.0909 1.0901 1.0889 1.0876 1.0863 1.0851 1.0843 1.0840 1.0848 1.0863 1.0870 1.0872 1.0874 20 3.80 1.0877 1.0895 1.0910 1.0915 1.0910 1.0900 1.0885 1.0868 1.0853 1.0840 1.0832 1.0837 1.0862 1.0897 1.0919 1.0926 1.0932 21 4.00 1.0870 1.0891 1.0909 1.0915 1.0911 1.0900 1.0885 1.0868 1.0852 1.0839 1.0833 1.0847 1.0884 1.0935 1.0969 1.0981 1.0990 22 4.20 1.0861 1.0885 1.0906 1.0914 1.0911 1.0900 1.0885 1.0869 1.0854 1.0843 1.0839 1.0860 1.0907 1.0970 1.1014 1.1029 1.1041 23 4.40 1.0852 1.0878 1.0900 1.0909 1.0907 1.0898 1.0884 1.0869 1.0856 1.0847 1.0846 1.0873 1.0930 1.1003 1.1055 1.1074 1.1088 24 4.60 1.0842 1.0868 1.0891 1.0902 1.0904 1.0898 1.0888 1.0878 1.0868 1.0863 1.0966 1.0897 1.0957 1.1032 1.1087 1.1107 1.1121 25 4.80 1.0832 1.0857 1.0880 1.0893 1.0897 1.0895 1.0890 1.0884 1.0880 1.0879 1.0885 1.0921 1.0982 1.1056 1.1113 1.1133 1.1149 26 5.00 1.0821 1.0844 1.0867 1.0880 1.0887 1.0889 1.0889 1.0887 1.0887 1.0891 1.0900 1.0940 1.1002 1.1076 1.1134 1.1155 1.1170 27 5.20 1.0812 1.0832 1.0851 1.0865 1.0873 1.0879 1.0803 1.0887 1.0892 1.0900 1.0913 1.0956 1.1018 1.1090 1.1149 1.1170 1.1185 28 5.40 1.0805 1.0818 1.0833 1.0844 1.0854 1.0863 1.0872 1.0881 1.0892 1.0905 1.0922 1.0969 1.1029 1.1098 1.1157 1.1177 1.1193 29 5.60 1.0797 1.0803 1.0811 1.0821 1.0831 1.0843 1.0856 1.0871 1.0887 1.0906 1.0927 1.0976 1.1034 1.1100 1.1157 1.1177 1.1193 30 5.80 1.0786 1.0784 1.0786 1.0793 1.0804 1.0819 1.0836 1.0857 1.0879 1.0902 1.0926 1.0978 1.1033 1.1094 1.1150 1.1169 1.1184 31 6.00 1.0772 1.0765 1.0761 1.0766 1.0777 1.0795 1.0816 1.0840 1.0867 1.0894 1.0921 1.0973 1.1025 1.1081 1.1134 1.1153 1.1167 32 6.20 1.0755 1.0744 1.0737 1.0741 1.0753 1.0772 1.0795 1.0822 1.0851 1.0881 1.0909 1.0961 1.1010 1.1060 1.1110 1.1128 1.1141 33 6.40 1.0735 1.0720 1.0710 1.0712 1.0724 1.0744 1.0770 1.0799 1.0831 1.0862 1.0892 1.0942 1.0986 1.1031 1.1077 1.1094 1.1106 34 6.60 1.0710 1.0692 1.0679 1.0679 1.0692 1.0713 1.0740 1.0771 1.0805 1.0837 1.0868 1.0916 1.0955 1.0993 1.1034 1.1049 1.1060 35 6.80 1.0685 1.0662 1.0645 1.0643 1.0654 1.0675 1.0703 1.0735 1.0770 1.0803 1.0834 1.0881 1.0917 1.0951 1.0990 1.1003 1.1014 36 7.00 1.0663 1.0640 1.0621 1.0618 1.0628 1.0647 1.0673 1.0704 1.0737 1.0770 1.0801 1.0850 1.0891 1.0932 1.0976 1.0992 1.1003 37 7.20 1.0637 1.0620 1.0609 1.0611 1.0623 1.0643 1.0668 1.0698 1.0730 1.0761 1.0791 1.0842 1.0886 1.0931 1.0978 1.0994 1.1007 38 7.40 1.0608 1.0596 1.0590 1.0598 1.0617 1.0644 1.0676 1.0712 1.0749 1.0785 1.0816 1.0864 1.0898 1.0926 1.0963 1.0976 1.0986 39 7.60 1.0640 1.0614 1.0595 1.0596 1.0613 1.0642 1.0679 1.0721 1.0763 1.0803 1.0838 1.0881 1.0903 1.0915 1.0941 1.0950 1.0957 40 7.80 1.0694 1.0662 1.0637 1.0633 1.0646 1.0671 1.0705 1.0744 1.0784 1.0821 1.0852 1.0887 1.0898 1.0899 1.0915 1.0921 1.0925 41 8.00 1.0736 1.0713 1.0695 1.0692 1.0703 1.0724 1.0751 1.0782 1.0812 1.0840 1.0862 1.0883 1.0882 1.0872 1.0875 1.0876 1.0877 42 8.20 1.0780 1.0761 1.0746 1.0744 1.0752 1.0767 1.0787 1.0810 1.0832 1.0852 1.0867 1.0877 1.0867 1.0848 1.0842 1.0840 1.0838 43 8.40 1.0821 1.0808 1.0797 1.0794 1.0798 1.0807 1.0819 1.0832 1.0846 1.0858 1.0867 1.0874 1.0869 1.0860 1.0857 1.0856 1.0855 44 8.60 1.0860 1.0852 1.0846 1.0842 1.0841 1.0043 1.0846 1.0849 1.0853 1.0857 1.0861 1.0864 1.0866 1.0867 1.0869 1.0869 1.0870 45 8.80 1.0896 1.0894 1.0892 1.0888 1.0884 1.0878 1.0873 1.0868 1.0864 1.0861 1.0861 1.0866 1.0878 1.0896 1.0908 1.0912 1.0915 46 9.00 1.0928 1.0933 1.0935 1.0932 1.0925 1.0914 1.0902 1.0890 1.0879 1.0872 1.0869 1.0880 1.0909 1.0949 1.0976 1.0985 1.0992 47 9.20 1.0958 1.0968 1.0976 1.0975 1.0968 1.0956 1.0941 1.0926 1.0913 1.0903 1.0899 1.0912 1.0948 1.0997 1.1029 1.1041 1.1049 48 9.40 1.0983 1.1000 1.1013 1.1017 1.1012 1.1002 1.0988 1.0973 1.0959 1.0949 1.0944 1.0957 1.0993 1.1040 1.1072 1.1084 1.1092 49 9.60 1.1008 1.1029 1.1047 1.1054 1.1052 1.1043 1.1031 1.1017 1.1003 1.0993 1.0988 1.1001 1.1036 1.1082 1.1114 1.1125 1.1133 50 9.80 1.1030 1.1055 1.1077 1.1087 1.1088 1.1081 1.1069 1.1056 1.1043 1.1033 1.1028 1.1041 1.1075 1.1119 1.1150 1.1160 1.1168 51 10.00 1.1053 1.1082 1.1109 1.1122 1.1125 1.1119 1.1108 1.1094 1.1081 1.1071 1.1066 1.1078 1.1111 1.1154 1.1183 1.1193 1.1201 52 10.20 1.1067 1.1102 1.1135 1.1152 1.1157 1.1153 1.1143 1.1130 1.1116 1.1105 1.1099 1.1109 1.1140 1.1179 1.1206 1.1215 1.1222 53 10.40 1.1077 1.1114 1.1147 1.1166 1.1174 1.1172 1.1165 1.1154 1.1143 1.1133 1.1128 1.1136 1.1160 1.1191 1.1212 1.1219 1.1225 54 10.60 1.1166 1.1207 1.1244 1.1261 1.1261 1.1249 1.1229 1.1205 1.1181 1.1162 1.1151 1.1164 1.1208 1.1267 1.1306 1.1320 1.1330 55 10.80 1.1141 1.1184 1.1223 1.1244 1.1250 1.1244 1.1231 1.1213 1.1195 1.1179 1.1169 1.1176 1.1203 1.1239 1.1262 1.1271 1.1277 56 11.00 1.0000 1.0000 1.0000 1.0000 1.0000 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 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 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 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 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 11.60 1.0000 1.0000 1.0000 1.0000 1.0000 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 11.80 1.0000 1.0000 1.0000 1.0000 1.0000 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 12.00 1.0000 1.0000 1.0000 1.0000 1.0000 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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