AEP-NRC-2012-88, Core Operating Limits Report

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Core Operating Limits Report
ML12296A136
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/10/2012
From: Gebbie J
Indiana Michigan Power Co, American Electric Power
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2012-88
Download: ML12296A136 (34)
v • d • e


Text

INDIANA MICHIGAN POWER A unit of American Electric Power October 10, 2012 Indiana Michigan Power One Cook Place Bridgman, MI 49106 IndianaMichiganPower.com AEP-NRC-2012-88 10 CFR 50.4 Docket No.:

50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 CORE OPERATING LIMITS REPORT Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Units 1 and 2, is submitting Revision 2 to the Core Operating Limits Report (COLR) for Unit 1 Cycle 24 and Revision 1 to the COLR for Unit 2 Cycle 20 in accordance with Technical Specification 5.6.5. Revision 2 of Unit 1 Cycle 24 COLR is provided as Enclosure 1 to this letter. Enclosure 2 provides Revision 1 of the Unit 2 Cycle 20 COLR.

The revisions to the Unit 1 and Unit 2 COLRs updated the Nuclear Enthalpy Rise Hot Channel Factor full power limits in Section 2.3.3(a) from 1.485 to 1.545 and 1.548 to 1.61 for Units 1 and 2, respectively. The revisions were made to include a factor of 1.04 for measurement uncertainty.

Section 2.3.3(c) was added to clarify the inclusion of this uncertainty.

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, Djýt V.

Joel P. Gebbie Site Vice President DMB/kmh

Enclosures:

1.

2.

Donald C. Cook Nuclear Plant Unit 1 Cycle 24 Core Operating Limits Report, Revision 2 Donald C. Cook Nuclear Plant Unit 2 Cycle 20 Core Operating Limits Report, Revision 1 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 Project Manager

ENCLOSURE 1 TO AEP-NRC-2012-88 Donald C. Cook Nuclear Plant Unit 1 Cycle 24 Core Operating Limits Report Revision 2

D. C. COOK UNIT 1 CYCLE 24 Revision 2 D. C. COOK UNIT 1 CYCLE 24 Revision 2 Donald C. Cook Nuclear Plant Unit 1 Cycle 24 Core Operating Limits Report Revision 2 Page 1 of 15

D. C. COOK UNIT 1 CYCLE 24 Revision 2 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit 1 Cycle 24 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 (FNA) 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 I CYCLE 24 Revision 2 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 (Tag) 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 Tag > 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/°F.

This limit is based on a Tag 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 HIFP stands for Hot Full Thermal Power Page 3 of 15

. D. C. COOK UNIT 1 CYCLE 24 Revision 2

b.

The MTC Surveillance limit is:

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

-3.84E-4 Ak/k/0F at a HFP vessel Tavg 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/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 '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.

Pfige 4 of 15

D. C. COOK UNIT 1 CYCLE 24 Revision 2 D. C. COOK UNIT 1 CYCLE 24 Revision 2 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

CFQ Q* (Z) _!

---=

  • K(Z)

P Foc (Z) < 2

  • CFo
  • K(Z)

F I" (Z) <- CFQ

  • K(Z)

Q P

Fo'" (Z) <! 2

  • CFo
  • K (Z) for P > 0.5

,for P

  • 0.5 for P>0.5 for P_<0.5 THERMAL POWER Where:

P = RATED THERMAL POWER

a.

CFQ = 2.15

b.

K(Z) is provided in Figure 4.

c.

FQ(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.

FY '(Z) = F C(Z) x W(Z) x F, The W(z) values are generated assuming that they will be used for a full power surveillance. When a part power surveillance is perfornmed, the W(z) values should be multiplied by the factor 1/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 24, 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 (FNAH ) (Specification 3.2.2)

FNH < CFAH * (1 + PFAH *(l-P))

THERMAL POWER RATED THERMAL POWER Page 5 of 15

D. C. COOK UNIT 1 CYCLE 24 Revision 2

a.

CFA= 1.545

b.

PFA= 0.3

c.

F NA 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 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 Ž 2018 psig +

b. Reactor Coolant System TAVG shall be _< 580.5°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°F for Tavg, and 2050 psig for Pressurizer Pressure.

++ This concentration bounds the condition of IKf < 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

A C. COOK UNIT I CYCLE 24 Revision 2 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 0.5 I -

S -

S -

S -

S -

LL U-0 C',

7T) x F-0.0

-0.5

[UNACCEPTABLE OPERATION

[ACCEPTABLEOPERATION]

-1.0 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 24 Revision 2 D. C. COOK UNIT 1 CYCLE 24 Revision 2 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250 225 1(52.9%, 228) 100 Step Overlap 200

--FBANK C ch CL 0

I) 01=.

EL 0

or

(.D CD 00 175 150 125 100 75 50 25 0

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

Page 8 of 15

D. C. COOK UNIT 1 CYCLE 24 Revision 2 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 x

N

_-N 0

a-E m

90 80 70 60 50 40 30 20 10 0

FLUX DIFFERENCE (DELTA-I)

Page 9 of 15

D. C. COOK UNIT 1 CYCLE 24 Revision 2 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 1.0 (Dz Lu 0

z 0.8 0.6 0.4 (0.0,1.0)

(6.0,1.0)

(12.0,0.925) 0.2 0

0 2

4 6

8 10 12 CORE HEIGHT (FT)

Page 10 of 15

D. C. COOK UNIT 1 CYCLE 24 Revision 2 FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT < AT° [KI - K2 [1+/-*

/

(T-T') + K3 (P-P') - f, (AI)]

Where:

AT

=

Measured RCS AT, OF AT

=

Indicated AT at RATED THERMAL POWER, OF 0

T

=

Average temperature, OF T'

=

Nominal Tavg at RATED THERMAL POWER (

  • 574.0 OF)

P

=

Pressurizer pressure, psig P

=

Nominal RCS operating pressure (2085 psig) 1+ r,s The function generated by the lead-lag controller for Tavg dynamic 1+ T 2S compensation 19, 2 Time constants utilized in the lead-lag controller for Taig lr> 22 secs.

T;2 < 4 secs.

S Laplace transform operator, sec 1 K,

1.35

  • K2 0.0230/0F1 K3 0.00110/psi f, (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 q, and qb are percent RATED TFIERMAL 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 11 of 15

D. C. COOK UNIT 1 CYCLE 24 Revision 2 FIGURE 5 (Page 2 of 2)

Overpower AT Trip Setpoint Overpower AT* ATo [K4 - K5 T 3S T-K 6 (T - T") - f2 (AD]

Where:

AT Measured RCS AT, OF ATo

=

Indicated AT at RATED THERMAL POWER, °F T

Average temperature, OF T"

=

Nominal Ta,,g at RATED THERMAL POWER ( *562.1 OF)

K4 1.172

  • K5 0.0177/0 F for increasing average temperature ; K = 0 for decreasing average temperature K6 0.001 5/°F for T greater than T" ; K6= 0 for T less than or equal to T" rS The function generated by the rate lag controller for Tavg dynamic compensation 3

=

Time constant utilized in the rate lag controller for Tav.g

'r> 10 secs.

S

=

Laplace transform operator, sec" f2(A)

=

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 1 CYCLE 24 Revision 2 D. C. COOK UNIT 1 CYCLE 24 Revision 2 FIGURE 6 Reactor Core Safety Limits 660 650 640 630

>620 I-610 U

600 600 590 580 570 0

0.2 0.4 0.6 0.8 Power (fraction of rated thermal power)

DESCRIPTION OF SAFETY LIMITS 1.2 PRESSURE (PSIA) 1840 2000 2100 2250 2400 UNIT 1 Power (frac) 0.02 0.02 0.02 0.02 0.02 Tavg

(' F) 620.86 632.79 639.85 649.96 659.52 Power (frac) 1.136 1.094 1.068 1.031 0.996 Tavg (I F) 586.17 600.31 608.72 620.83 632.42 Power (frac) 1.2 1.2 1.2 1.2 1.2 Tavg (4 F) 577.94 586.52 591.77 599.40 606.63 Reactor Core Safety Limits Page 13 of 15

D. C. COOK UNIT 1 CYCLE 24 Revision 2 D. C. COOK UNIT 1 CYCLE 24 Revision 2 FIGURE 7 Unit 1 Cycle 24 Predicted HFP ARO 300 PPM MTC Versus Burnup

.ZOSE.4M

-108E-04

-21E -2.20E-04 14000 15000 18000 17000 Cycle Bumup (MWDIMTU) 18000 Burnup (MWD/MTU)

MTC (pomInF)

MTC (Ak/kI°F) 14000

-20.660

-2.0660E-04 15000

-20.985

-2.0985E-04 16000

-21.289

-2.1289E-04 17000

-21.587

-2.1587E-04 18000

-21.887

-2.1887E-04 Page 14 of 15

D. C. COOK UNIT 1 CYCLE 24 Revision 2 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 24 W(Z) FUNCTION Node Point 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 Height (n)j 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 1.80 2.00 2.20 2.40 2.60 2.80 3.00 3.20 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.4O 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11.40 11.60 11.80 12.00 150 1000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0D00 1.00M4 1.0970 1.0986 1.0973 1.0986 1.0975 1.0983 1.0974 1.0979 1.0972 1.0972 1.0967 1.0983 1.0960 1.0952 1.0950 1.093M 1.0939 1.0922 1.0925 1.0900 1.0909 1.0894 1.0897 1.0892 1.0897 1.0889 1.0895 1.0884 1.0891 1.0879 1.0885 1.0871 1.0878 1.0861 1.0868 1.0850 1.0856 1.0838 1.0842 1.0823 1.0826 1.0808 1.0810 1.0792 1.0791 1.0773 1.0770 1.0752 1,0748 1.0730 1.0724 1.0709 1.0699 1.0691 1.0676 1.0669 1.0654 1.0849 1.0637 1.0630 1.0620 1.0604 1.0599 1.0632 1.0626 1.0683 1.0679 1.0732 1.0729 1.0779 1.0778 1.0824 1.0825 1.0867 1.087M 1.0907 1.0912 1.0944 1.0052 1.0978 1.0987 1.1008 1.1019 1.1035 1.1048 1.1061 1.1075 1.1087 1.1103 1.1105 1.1122 1.1119 1.1138 1.1212 1,1231 1.1189 1.1208 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2000 3000 4000 5000 6000 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 1.0000 1.0000 1.0000 1.0000 1.0900 1.0000 1.60W0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0960 1.0961 1.0971 1.0988 1.1010 1.0965 1.0966 1.0976 1.0992 1.1013 1.0968 1.0970 1.0979 1.0994 1.1014 1.0969 1.0971 1.0980 1.0994

. 1.1011 1.0968 1.0970 1.0978 1.0990 1.1006 1.0964 1.0967 1.0974 1.0984 1.0997 1.0959 1.0961 1.0967 1.0976 1.0986 1.0951 1.0953 1.0958 1.0964 1.0972 1.0940 1.0943 1.0946 1.0950 1.0954 1.0928 1.0930 1.0932 1.0934 1.0935 1.0912 1.0914 1.0915 1.0914 1.0913 1.0899 1.0899 1.0898 1.0895 1.0891 1.0900 1.0899 1.0894 1.0887 1.0878 1.0899 1.0898 1.0892 1.0883 1.0873 1.0895 1.0894 1.0888 1.0879 1.0868 1.0890 1.0889 1.0883 1.0875 1.0865 1.0883 1.0883 1.0878 1.0871 1.0862 1.0874 1.0875 1.0873 1.0869 1.0865 1.0862 1.0865 1.0866 1.0866 1.0866 1.0847 1.0852 1.0855 1.0859 1.0864 1.0831 1.0836 1.0843 1.0851 1.0860 1.0813 1.0820 1.0829 1.0840 1.0884 1.0793 1.0800 1.0811 1.0826 1.0843 1.0772 1.0780 1.0793 1.0811 1.0832 1.0750 1.0759 1.0774 1.0794 1.0817 1.0724 1.0732 1.0749 1.0771 1.0797 1.0695 1.0702 1.0718 1.0741 1.0770 1.0668 1.0672 1.0687 1.0711 1.0741 1.0645 1.0649 1.0664 1.0687 1.0715 1.0631 1.0635 1.0648 1.0688 1.0692 1.0616 1.0621 1.0634 1.0653 1.0678 1.0599 1.0610 1.0630 1.0657 1.0689 1.0626 1.0637 1.0658 1.0686 1.0719 1.0679 1.0690 1.0708 1.0732 1.0760 1.0731 1.0740 1.0756 1.0777 1.0800 1.0781 1.0789 1.0802 1.0819 1.0837 1.0829 1.0836 1.0846 1.0857 1.0870 1.0874 1.0880 1.0885 1.0891 1.0897 1.0917 1.0920 1.0921 1.0921 1.0919 1.0957 1.0957 1.0953 1.0945 1.0936 1.0994 1.0992 1.0983 1.0970 1.0954 1.1026 1.1025 1.1017 1.1004 1.0988 1.10*8 1.1059 1.1053 1.1041 1.1027 1.1087 1.1090 1.1085 1.1076 1.1063 1.1116 1.1121 1.1117 1.1109 1.1097 1.1137 1.1143 1.1142 1.1135 1.1126 1.1155 1.1163 1.1163 1.1159 1.1151 1.1247 1.1250 1.1243 1.1228 1.1209 1.1224 1.1229 1.1227 1.1218 1.1206 1.0000 1.0000 1.0000 1.0000 1.0600 1.0000 1.0000 1.0090 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0060 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Bumup (MWV)MTU) 7000 8000 9000 10000 12000 14000 16000 18000 18980 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 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.000 1.0000 1.0000 1.0000 1.0000 1.0000 1000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0D00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0009 1.0000 1.0900 1.0000 1.0000 1.0000 1.0000 1.0000 1.1038 1.1064 1.1093 1.1122 1_1175 1.1226 1.1280 1.1333 1.1359 1.1037 1.1064 1.1091 1.1118 1.1167 1.1214 1.1264 1.1314 1.1338 1.1036 1.1060 1.1085 1.1110 1.1155 1.1198 1.1243 1.1288 1.1310 1.1032 1.1053 1.1076 1.1097 1.1137 1.1176 1.1216 1.1255 1.1275 1.1023 1.1042 1.1062 1.1080 1.1115 1.1148 1.1182 1.1216 1.1233 1.1012 1.1028 1.1044 1.1060 1.1088 1.1115 1.1143 1.1171 1.1184 1.0998 1.1010 1.1023 1.1035 1.1057 1.1078 1.1099 1.1120 1.1130 1.0980 1.0989 1.0998 1.1006 1.1022 1.1036 1.1050 1.1084 1.1071 1.0959 1.0964 1.0969 1.0974 1.0982 1.0989 1.0996 1.1004 1.1008 1.093M 1.0938 1.0939 1.0939 1.0941 1.0941 1.0942 1.0942 1.0943 1.0911 1.0909 1.0907 1.0904 1.0899 1.0893 1.0887 1.0881 1.0878 1.0886 1.0881 1.0876 1.0871 1.0862 1.0855 1.0847 1.0840 1.0836 1.0869 1.0861 1.0853 1.0848 1.0846 1.0852 1.0863 1.0869 1.0872 1.0862 1.0852 1.0845 1.0841 1.0847 1.0867 1.0896 1.0916 1.0925 1.0858 1.0848 1.0842 1.0841 1.0856 1.0889 1.0936 1.0969 1.0984 1.0856 1.0849 1.0845 1.0847 1.0870 1.0914 1.0972 1.1016 1.1037 1.0854 1.0849 1.0847 1.0852 1.0882 1.0936 1.1006 1,1060 1.1066 1.0861 1.0859 1.0862 1.0870 1.0906 1.0964 1.1037 1.1095 1.1123 1.0867 1.0871 1.0878 1.0890 1.0931 1.0990 1.1064 1.1125 1.1153 1.0870 1.0879 1.0891 1.0906 1.0952 1.1013 1.1087 1.1148 1.1178 1.0871 1.0885 1.0901 1.0920 1.0969 1.1031 1.1103 1.1166 1.1196 1.0870 1.0887 1.0907 1.0930 1.0982 1.1043 1.1113 1.1176 1.1206 1.0863 1.0886 1.0910 1.0935 1.0990 1.1050 1.1117 1.1178 1.1208 1.0855 1.0881 1.0908 1.0935 1.0991 1.1050 1.1113 1.1173 1.1202 1.0844 1.0872 1.0901 1.0930 1.0986 1.1042 1.1102 1.1159 1.1187 1.0826 1.0857 1.0888 1.0919 1.0975 1.1028 1.1082 1.1136 1.1163 1.0802 1.0838 1.0869 1.0901 1.0957 1.1006 1.1054 1.1104 1.1129 1.0774 1.0809 1.0844 1.0877 1.0931 1.0976 1.1019 1.1066 1.1089 1.0747 1.0781 1.0814 1.0844 1.0893 1.0930 1.0965 1.1005 1.1024 1.0720 1-0750 1.0780 1.0807 1.0855 1.0897 1.0939 1.0982 1.1004 1.0705 1.0734 1.0783 1.0792 1.0844 1.0893 1.0943 1.0994 1.1018 1.0723 1.0758 1.0792 1.0824 1.0873 1.0912 1.0945 1.0985 1.1005 1.0753 1.0789 1.0822 1.0851 1.0894 1.0921 1.0940 1.0969 1.0983 1.0790 1.0820 1.0847 1.0871 1.0904 1.0921 1.0930 1.0948 1.0957 1.0824 1.0848 1.0870 1.0888 1.0909 1.0915 1.0912 1.0919 1.0923 1.0855 1.0873 1.0888 1.0900 1.0909 1.0904 1.0889 1.0884 1.0882 1.0882 1.0893 1.0902 1.0907 1.0905 1.0890 1.0866 1.0851 1.0844 1.0902 1.0906 1.0909 1.0909 1.0902 1.0886 1.0884 1.0848 1.0840 1.0917 1.0915 1.0912 1.0909 1.0905 1.0901 1.0896 1.0892 1.0890 1.0926 1.0917 1.0909 1.0905 1.0908 1.0924 1.0947 1.0962 1.0969 1.0938 1.0923 1.0911 1.0905 1.0915 1.0947 1.0993 1.1024 1.1038 1.0972 1.0957 1.0945 1.0940 1.0962 1.0986 1.1036 1.1070 1.1086 1.1012 1.0998 1.0988 1.0983 1.0995 1.1029 1.1076 1.1109 1.1125 1.1049 1.1037 1.1027 1.1023 1.1035 1.1067 1.1113 1.1144 1.1159 1.1084 1.1073 1.1064 1.1060 1.1072 1.1103 1.1147 1.1178 1.1192 1.1114 1.1104 1.1096 1.1093 1.1104 1.1133 1.1173 1.1202 1.1215 1.1141 1.1132 1.1125 1.1121 1.1133 1-1156 1.1188 1.1211 1.1222 1.1188 1.1168 1.1152 1.1144 1.1156 1.1194 1.1250 1.1288 1.1305 1.1192 1.1178 1.1168 1.1162 1.1170 1.1196 1.1233 1.1258 1.1270 1.0090 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1J0000 1.0000 1.0000 1.00W 1.0000 1.0000 1.0000 1.0000 1.000 0

1.0 000 1.0000 1.0000 1.0000 1.0600 1.0900 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0.00 1.0000 1.000 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.

Page 15 of 15

ENCLOSURE 2 TO AEP-NRC-2012-88 Donald C. Cook Nuclear Plant Unit 2 Cycle 20 Core Operating Limits Report Revision 1

D. C. COOK UNIT 2 CYCLE 20 Revision 1 D. C. COOK UNIT 2 CYCLE 20 Revision 1 Donald C. Cook Nuclear Plant Unit 2 Cycle 20 Core Operating Limits Report Revision 1 Page 1 of 16

D. C. COOK UNIT 2 CYCLE 20 Revision 1 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 20 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 Nuclear Regulatory Commission (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. 1A, Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification, February 1994

d.

Plant-specific adaptation (approved by Amendment 297, dated March 31, 2011) of WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," Revision 0 (Westinghouse Proprietary), approved by letter from H. N. Berkow, NRC, to J. A. Gresham, Westinghouse Electric Company, dated November 5, 2004

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 SLs [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 (FNA) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reactor Trip System (RTS) Instrumentation 3.4.1 RCS [Reactor Coolant System] Pressure, Temperature', and Flow Departure from Nucleate Boiling (DNB) Limits 3.9.1 Boron Concentration Page 2 of 16

D. C. COOK UNIT 2 CYCLE 20 Revision 1 2.0 OPERATING LIMITS The cycle-specific parameter limits 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 SLs (Specification 2.1.1)

In Modes 1 and 2, the combination of thermal power, pressurizer pressure, and the highest loop average temperature (Tag) 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 < 200OF 2.2.2 Moderator Temperature Coefficient (MTC) (Specification 3.1.3)

a.

The 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. 10E-4 Ak/k/0 F.

This limit is based on a Taig program with HFP vessel Tav.g of 571.0 to 576.0 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 2 CYCLE 20 Revision 1

b.

The MTC Surveillance limit is:

The 300 ppm/ARO/RTP-MTC should be less negative or equal to -3.20E-4 Ak/k/F at a HFP vessel Taig of 571.0 to 576.0 '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 Surveillance Requirement (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 -3.90E-4 Ak/k/0 F at a HEP vessel Tavg of 571.0 to 576.0 '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

Ž0.0 MWD/MTU [Megawatt Days/Metric Ton Uranium].

Page 4 of 16

D. C. COOK UNIT 2 CYCLE 20 Revision I D. C. COOK UNIT 2 CYCLE 20 Revision 1 2,3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

CFo F*: (Z) < -

  • K(Z)

P Foc (Z)*< 2

  • CF9
  • K(Z)

CFo F0v (Z): <

~-

  • K(Z)

P Fo'(Z)*< 2

  • K(Z)

,for P > 0.5 for P* 0.5 for P > 0.5 for P_<0.5 THERMAL POWER RATED THERMAL POWER

a. CFQ

=2.335

b.

K(Z) is provided in Figure 4

c.

F*(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. FwQ (Z) = Fc (Z) x w(z) x 1p The W(z) values are generated assuming that they will be used for a fill power surveillance.

When a part power surveillance is performed, the W(z) values should be multiplied by the factor 1/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.

Page 5 of 16

D. C. COOK UNIT 2 CYCLE 20 Revision 1

f.

For Cycle 20, Fp = 1.02 for all burnups 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 Burnup Fp, Penalty Multiplier (MWD/MTU) 0 1.020 150 1.035 317 1.039 484 1.045 651 1.047 818 1.048 985 1.048 1152 1.047 1319 1.045 1486 1.043 1653 1.040 1821 1.039 1988 1.038 2155 1.036 2322 1.033 2489 1.030 2656 1.026 2823 1.022 3000 1.020 The burnup range only covers where adequate for intermediate cycle burnups.

Fp exceeds 1.02.

Linear interpolation is 2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (Specification 3.2.2)

FN A< CFAH * (1 + PFmH *(l-P))

THERMAL POWER Where:

Pr RATED THERMAL POWER

a.

CFH=1.61

b. PFH= 0.3
c.

F NA is the measured Enthalpy Rise Hot Channel Factor including a 4% measurement uncertainty.

Page 6 of 16

D. C. COOK UNIT 2 CYCLE 20 Revision I 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 > 2172.4 psig +
b.

RCS Tavg shall be*< 580.1 'F +

c.

RCS 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 RCS, 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 577.8°F for Ta,,g, and 2200 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 2 CYCLE 20 Revision I FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 0.5 U -

U -

U -

U -

U-C)

-a x

1%-1

[ UNACCEPTABLE OPERATION

[ACCEPTABLE OPERATION]

___I____I___

I___

___\\ ______

0.0

-0.5

-1.0 I -

I -

I -

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 2 CYCLE 20 Revision 1 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250 225 200

~0 F-U) 0 00-1 0

0W 175 150 125 100 75 50 25 0

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

Page 9 of 16

A C. COOK UNIT 2 CYCLE 20 Revision 1 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 0x NSN LL UH 0

a.

E 0

90 80 70 60 60 40 30 20 10 0

FLUX DIFFERENCE (DELTA-I)

Page 10 of 16

A C. COOK UNIT 2 CYCLE 20 Revision 1 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 1.0 0.8

(.9 z

w w 0.6 N

0z 0.4 0.2 0.0 (0.0, 1.0)

(8.425, 1.0) 12.0, 0.925) 4

+

4 4

4 4

0 2

4 6

CORE HEIGHT (FT) 8 10 12 Page 11 of 16

D. C. COOK UNIT 2 CYCLE 20 Revision 1 D. C. COOK UNIT 2 CYCLE 20 Revision 1 FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT <AT° KI - K2 Li+ TS]

(T-T') + K3(P-P) 4f (Al)

Where:

AT

= Measured RCS AT, OF ATo

=

Indicated AT at RATED THERMAL POWER, OF T

=

Average temperature, OF V

=

Nominal Tavg at RATED THERMAL POWER, (< 576.07F)

P

=

Pressurizer Pressure, psig Pe

=

Nominal RCS operating pressure (2235 psig)

I[+rSI =

The function generated by the lead-lag controller for Tavg dynamic compensation 1, "2

=

Time constants utilized in the lead-lag controller for Ta,,g

'T1 I 28 secs. x 2 < 4 secs.

S

=

Laplace transform operator, sec1 K,

1.19

  • K2 0.01331/0 F K3 0.00058/psig f, (Al)

-3.5 {33% + (qt - qb)}

when qt - qb <-33% RTP 0% of RTP when -33% RTP < qt - qb < 6% RTP

+1.0 {(q, - qb) - 6%}

when qt - qb > 6% 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 2 CYCLE 20 Revision I D. C. COOK UNIT 2 CYCLE 20 Revision 1 FIGURE 5 (Page 2 of 2)

Overpower AT Trip Setpoint r'

T.*

TK6 (T-T"')-f2(AD]

I + rSJI Overpower AT < ATo [1K4 - K5 Where:

AT ATo T

=

Measured RCS AT, °F

=

Indicated AT at RATED THERMAL POWER, °F

=

Average temperature, OF T"

=

Nominal Tavg at RATED THERMAL POWER, (< 576.0 OF)

K4 1.16*

K5 0.02/°F for increasing average temperature; K5 = 0 for decreasing average temperature K6 0.00 197/°F for T greater than T" ; K6=0 for T less than or equal to T" T's I1+ r3 S The function generated by the rate lag controller for Tav;g dynamic compensation

=

Time constant utilized in the rate lag controller for Ta,,g; 'r 3 Ž 10 secs.

S

=

Laplace transform operator, sec-1 f2 (A) =

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 2 CYCLE 20 Revision 1 FIGURE 6 Reactor Core Safety Limits L

620 610 FL (j) 600 0,

0 0.2 0.4 0.6 0.8 Power (fraction of rated thermal power)

DESCRIPTION OF SAFETY LIMITS 1.2 PRESSURE (psia) 1775 2000 2100 2250 2400 UNIT 2 Power (frac) 0.00 0.00 0.00 0.00 0.00 Tavg

(' F) 615.4 631.8 639.1 649.2 659.0 Power (frac) 0.98 0.86 0.82 0.72 0.62 Tavg

(* F) 583.8 605.8 614.0 628.6 642.0 Power (frac) 1.02 0.96 0.96 0.98 1.1 Tavg

(' F) 580.9 597.5 601.6 605.2 599.0 Power (frac) 1.2 1.2 1.2 1.2 1.2 Tavg

(' F) 558.1 568.5 573.1 580.4 588.1 Reactor Core Safety Limits Page 14 of 16

D. C. COOK UNIT 2 CYCLE 20 Revision 1 FIGURE 7 Unit 2 Cycle 20 Predicted HFP ARO 300 PPM MTC Versus Burnup

-Y-Y-Y-Y-Y-Y-Y-I 0

a-

-2.40E-04

-2.42E-04

-2.44E-04

-2.46E-04

-2.48E-04

-2.50E-04

-2.52E-04

-2.54E-04

-2.56E-04

-2.58E-04

-2.60E-04 17, 000 N -,ýS 18,000 19,000 20,000 Cycle Burnup (MWD/MTU) 21,000 Burnup (MWDIMTU)

MTC (pcm/IF)

MTC (Ak/k/°F) 17,000

-24.411

-2.4411E-04 18,000

-24.798

-2.4798E-04 19,000

-25.178

-2.5178E-04 20,000

-25.537

-2.5537E-04 21,000

-25.908

-2.5908E-04 Page 15 of 16

D. C. COOK UNIT 2 CYCLE 20 Revision 1 TABLE 1 D. C. Cook Unit 2 Cycle 20 W(Z) Function

____~~~~~~ ___I___B___L__

urnup Poinl (MI) 150 1 1000 1 2000 I 3000 1 40001 5000 I 6000 1

1.0000 [1.0000 r1.0000 1.0000 Ji 1, 1.000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 I 1.0000 1.0000 1.0000 1.0000 1.0000 3

IT T

IT

-T-8T 9T 76-0.40 1 1.0000 I 1.0000

1. 0000 1.0000 1.0000 1 1.0000 1.0000 1.0000 I 1.0000 1.0000 i 1.0000 1.0000 I 1.0000 I 1.0000 1.0000 1.0000 1.0000 1.0000 1.00 1 1.0000 1 1.0000 1.0000 1 1.0000 1.0000 1.0000 I 1.0000 1.1113 1 1.1100 I 1.1200 1 1.1262 1.1337 1.1408 1 1.1467 1 1.1476 1.60 1 1.1122 I 1.1100 1 1.1078 1 1.1062 1 1.1052 1.1048 I 1.1051 I 1.1072 1.1107 1.1148 1

1.1142 1

1,1124 1.1164 1 1.1202 1 1.1242 1.1283 1.1323 1 1.1329 2.20 1 1.1056 1.1035 1.1015 1 1.1001 1 1.0993 1.0992 1 1.0998 I 1.1026 I 1.1062 1.1097 1.1129 1 1.1150 1 1.1193 1.1226 1 1.1259 1 1.1264 13 2.40 1.1027 1

1.0961 1 1.0962 1.0964 1 1.0967 1 1.0974 1 1.0983 1 1.0991 1.0999 i 1.1007 1 1.1016 1.1024 1 1.1032 1 1.1033 16 3.00 I1.0924 I 1.0930 1 1.0937 1.0942 1 1.0947 1.0950 I 1.0951 I 1.0951 1 1,09050 1.0949 1

1.0658 I 1.0858 1.0856 1 1.0850 1 1.0850 is 3.60 I.O08 1 1.0870 1 1.0091 1 1.0907 1 1.0916 1.0918 I 1.0912 I 1.0686 i 1.08600 1.0850 I 1.0856 1.0875 1 1.0905 1.0929 1 1.0943 1 1.0945 20 360 1.0653 1.0874 234.40 1.082 1[093 26 5.00 1.0907 1.0902 1.0910 1.0914 1.0911 1.0901 1.0869 1 1.08M 1.0859 i 1.0901 1 1.0969 1 1.1060 1.1142 1 1.1201 1 1.1209 1.0003 1.0910 1.0912 1.0910 1 1.0901 I 1.0876 I 1.0864 1 1.0884 I 1.0934 1 1.1010 1 1.1110 1.1201 11.1268 1 1.1278 1.0883 [1.0912 1 1.0970 1 1.1052 1 1.1157 [1.1254 J 1.1328 J 1.1338

-1.0901 1.0939 11.1003 11.1090 1.1A198 L1.1299 1 1.1379 1 1.1390 1.0897 1 1.0894 1.0892 1 1.0890 1 1.0890 1 1.0895 1 1.0916 1.0962 1 1.1032 1 1.1122 1 1.1232 1.1336 1 1.1420 1.1432 27 5.20 1.011 108 S

1.0011 I1.0894 1.0866 1 1.0853 1.0846 11.0084 1.0853 I 1.0887 i 1.0940 1.1007 i 1.1087 1 1.1180 1 1.1288 1.1392 1 1.1483 1.1496 30 5.80 1.0785 1.0773 1 1.0774 I 1.0787 I 1.0842 1.0017 1.0995 1 1.1076 1 1.1162 1 1.1255 1.1349 1 1.1435 1 1.1447 33 6.40 10854 I 1.0815 1 1.0780 1.0755 1.0742 1 1.0743 I 1.0758 I 1.0818 1.1055 1 1.1126 1.1200 1 1.1273 1 1,1284 38 7.00 1.0759 1.0710 1 1,0682 1 1.0655 1.0641 1 1.0642 I 1.0656 I 1.0717 I 1.0796 1.0869 I 1.0937 1.1003 1 1.1071 1.1141 1 1,1210 1 1.1220 37 7.20 1.0743 1.0693 1 1.0651 1.0629 1 1.0629 1.0653 1 1.0748 I 1.0859 1.0945 1 1.1003 1 1.1044 1 1.1074 1.1112 1 1.1162 1 1.1170 40 7.80 1.0842 1 1.0786 1.0733 1 1.0695 1 1.0676 1 1.0677 1.0775 1.0852 1.0939 1.1000 I 1.1035 1 1.1052 1 1.1055 1.1067 1 1.1093 1 1.1096 43 8.40 1.0910 1 1.0868 1 1.0829 1 1.0802 1 1.0788 1.0790 1.0809 1.0823 1.0841 1.0853 1.0869 1.0924 1.0981 I.1014 1.1023 1 1.1015 1 1.0992 1.0077 1.0976 1.0976 46 1 9.00 1 1.0947 i 1.0923 1 1.0002 1 1.0887 1 1.0881 1.0884 I 1.0897 I 1.0941 I 1,0988 1 1.1014 I 1.1022 1 1.1015 1 1.0996 1.0984 1.0983 1.0983 47I1 9.20 11.0957 1 1.0942 1.0927 11.09171 48 1_ 9.40 1 1.0963 1 1.0955 J1.0948 1.09" 1

49 1 9.60 1.1004 1 1.0992 1.0980 i 1.0972 1 1.0968 1.0968 I 1.0974 I 1.0995 i 1.1021 1 1.1044 I 1.1065 1 1.1085 1 1.1105 1 1.1125 1.1146 1.1140 50 j 9.80 1

1.1061 1 1.1032 1 1.1016 1 1.1013 I 1.1025 I 1.1079 I 1.1141 1.1184 I 1.1208 1.1218 1 1.1219 1.1227 1.1244 1.1246 53 1 10.40 1 1.1181 i 1.1132 1.1084 1 1.1050 1 1.1029 1 1.1025 I 1.1039 i 1.1101 1.1172 1.1195 5

1.1216 1.1262 1 1.1284 1 1.1290 1 1.1264 1.1286 1 1.1300 1 1.1302 56 11.00 1.000 I 1.0000 1.0000 1.0o00 1.0000 1.0000 I 1.0000 I 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1 1.0000 1.0000 I 1.0000 1.0000 i 1.0000 1 1.0000 1 1.0000 1 1.0000 1.0000 1.0000 60 11.80 1 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 I 1.0000 1

61 12.001 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1:I Top and bottom 10% of core excluded.

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