AEP-NRC-5691-04, Core Operating Limits Report

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Core Operating Limits Report
ML053050431
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/24/2005
From: Jensen J
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-5691-04
Download: ML053050431 (68)
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Text

Z -Indiana Michigan Power Company Nuclear Generation Group INDIANAOne Cool Place MICHIGAN Bridgman, MI 49106 POWER aep.com October 24,2005 AEP:NRC:5691-04 10 CFR 50.4 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 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 two revisions to the Core Operating Limits Report (COLR) for Unit 1 Cycle 20 and Unit 2 Cycle 15 in accordance with Technical Specification 5.6.5.d. Revision 1 of the Unit 1 and Unit 2 COLR implemented Improved Technical Specifications and a license amendment allowing conditional exemption from the near-end of life Moderator Temperature Coefficient measurement.

Soon after issuance of Revision 1 of the COLRs for each unit, some administrative quality control issues with the documents were identified. Revision 2 of the Unit I and Unit 2 COLR has been issued to correct these issues.

Revisions 1 and 2 of the Unit 1 Cycle 20 COLR are provided as Attachments 1 and 2, respectively.

Revisions 1 and 2 of the Unit 2 Cycle 15 COLR are provided as Attachments 3 and 4, respectively.

There are no new commitments in this letter. Should you have any questions, please contact Mr. John A. Zwolinski, Director of Safety Assurance, at (269) 466-2428.

Sincerely,

)Jensen ice President Attachments KAS/rdw

U. S. Nuclear Regulatory Commission AEP:NRC:5691-04 Page 2 c: J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne, w/o attachments J. T. King - MPSC, w/o attachments MDEQ - WHMD/RPMWS, w/o attachments NRC Resident Inspector D. W. Spaulding - NRC Washington DC

ATTACHMENT 1 TO AEP:NRC:5691-04 DONALD C. COOK NUCLEAR PLANT (CNP) UNIT 1 CYCLE 20 CORE OPERATING LIMITS REPORT REVISION 1

D. C. COOK UNIT I CYCLE 20 Revision I Revision I D. C. COOK UNIT I CYCLE 20 Donald C. Cook Nuclear Plant Unit 1 Cycle 20 Core Operating Limits Report Revision 1

D. C. COOK UNIT I CYCLE, 20 Revision I 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit I Cycle 20 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 ControlIFQ Surveillance Technical Specification, February 1994
d. WCAP-10266-P-A, Rev.2, The 1981 Version of Westinghouse Evaluation Mode Using BASH Code, March 1987
e. WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, July 1991
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 Safety Limits 3.1.1 Shutdown Margin (SDM) 3.1.3 Moderator Temperature Coefficient (MTC) 3.1.5 Shutdown Bank Insertion Limit 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 1 of 14

D. C. COOK UNIT 1 CYCLE 20 Revision 1 D. C. COOK UNIT 1 CYCLE 20 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 Safety Limits (Specification 2.1.1)

In Modes I and 2, the combination of thermal power, pressurizer pressure, and the highest operating loop coolant 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 (Specification 3.1.1)

Shutdown margin shall be greater than or equal to 1.3% Ak/k for T8 ,, > 200OF Shutdown margin shall be greater than or equal to 1.0% Ak/k for Tavg < 2000 F 2.2.2 Moderator Temperature Coefficient (Specification 3.1.3)

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

The BOUARO-MTC shall be less positive than the value given in Figure 1.

The EOJJARO/RTP-MTC shall be less negative than -4.54E-4 AIk-PF.

This limit is based on a Tayg program with HFP T.,g of 554.0 - 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

b. The MTC Surveillance limit is:

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

-3.84E-4 Ak/k-F at a vessel average temperature of 554.0 - 558.0 'F.

Page 2 of 14

D. C. COOK UNIT 1 CYCLE, 20 Revision I D. C. COOK UNIT 1 CYCLE 20 Revision 1

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 Akfk/ 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 ppmi/ARO/RTP-MTC should be less negative or equal to -4.41E-4 Ak/k/0 F at a HFP vessel T.vg of 554 - 558 0 F 2.2.3 Shutdown Rod Insertion Limit (Specification 3.1.5)

The shutdown rods shall be withdrawn to 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 during base load operations is +3%, -3% (not applicable for this cycle).
c. The AFD target band is +5%, -5% for a cycle average accumulated burnup 20.0 MWD/MTU.

Page 3 of 14

D. C. COOK UNIT 1 CYCLE 20 Revision I 2.3.2 Heat Flux Hot Channel Factor -FQ(Z) (Specification 3.2.1)

CF FQC (Z)*< p *K(Z) for P > 0.5 FQC (Z) < 2

  • CFQ
  • K(Z) for P < 0.5 CF FQv(Z)5 CQ *K(Z) forP>0.5 P

FQw (Z)<2*CFQ,*K(Z) for P<0.5 THERMAL POWER Where: P RATED THERMAL POWER

a. CFQ = 2.15 for Westinghouse Fuel.
b. K(Z) is provided in Figure 4 for Westinghouse Fuel.

C. F'CQ(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. For Cycle 20, when applicable, Fp = 1.02 for all burnups.
f. FwQ(Z) = FQc(Z) X W(Z) X Fp 2.3.3 Nuclear Enthalpy Hot Channel Factor - FNul, (Specification 3.2.2)

FN",m

  • CFu! * (1 + PFmI *(1.P))

Whe P THERMAL POWER ere: P RATED THERMAL POWER

a. CFwI = 1.49 for Westinghouse Fuel.
b. PFuI = 0.3 Page 4 of 14

D. C. COOK UNIT 1 CYCLE,20 Revision I D. C. COOK UNIT 1 CYCLE 20 Revision 1 2.4 INSTRUMENTATION 2.4.1 Reactor Trip System 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. Reactor Coolant System TAVG shall be < 581.4 0 F +
b. Pressurizer Pressure shall be 2 2018 psig +
c. Reactor Coolant System Total Flow Rate shall be 2341,100 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 ppmr+.

+These are Safety Analysis values. With readability allowance, the corresponding values are 579.1 0 F for T.,g , and 2050 psig for Pressurizer Pressure.

+ This concentration bounds the condition of K,, < 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 5 of 14

D. C. COOK UNIT 1 CYCLE 20 Revision 1 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) 1.0 0.5 U-p

-'5 0.0 0

I-"

-0.5

-1.0 0 10 20 30 40 50 60 70 80 90 100 Percent Rated Thermal Power Page 6 of 14

D. C. COOK UNIT 1 CYCLE 20 Revision I FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (FOUR LOOP OPERATION) 250

[(52.9%,2. 8) 10Step Over 200 BAK C (10%

189) 175 CD (u

B 150 Z 125 (0%, 128) 0 0- 100 0

25 -

0 30 40 50 60 70 POWER (% of Rated Thermal Power)

Page 7 of 14

lp X C D. C. COOK UNIT I CYCLE 20 Revision 1 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 90 x 80 N

70 oe 60 0 50 40 E

30 E

'4-20 0

10 0

FLUX DIFFERENCE (DELTA-I)

(

Page 8 of 14

D. C. COOK UNIT I CYCLE 20 Revision I D. C. COOK UNIT I CYCLE 20 Revision I FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT (FOR WESTINGHOUSE FUEL) 1.2 (0.0, 1.0) _ _ _ _ _ _ _ _ __ (6.0, 1.0) _ _ _ _ _ _ _ _ _ _

1.0

( 12.0 , 0.925) 0.8 (D

z 0

w 0.6 N

-J Cl:

0 z

0.4 4- 4 + 4- 4 0.2 4. 4 + 4- 4 0 I &

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

Page 9 of 14

D. C. COOK UNIT I CYCLE 20. Revision 1 4.* 71 FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Overtemperature AT Trip Setpoint Overtemperature AT S AT [K - K2 +C (-T') +K3 (P-P') - f (A)]

Where: AT = Indicated AT at RATED THERMAL POWER 'F T = Average temperature, 'F T = Nominal T.,, at RATED THERMAL POWER ( *574.0 0 F)

P = Pressurizer pressure, psig P = Indicated RCS nominal operating pressure (2085 psig)

+ TiS The function generated by the lead-lag controller for T.,, dynamic 1+ TS2 compensation x, T2= Time constants utilized in the lead-lag controller for T.,,

a,>22 1 secs. 2 < 4 secs.

S = Laplace transform operator, sec '

K, < 1.35

  • K2 > 0.0230 K3 > 0.00110 and f1 (Al) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(i) for qt - qb between -37 percent and +3 percent, f, (AT)=0 (where q, and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER).

(ii) For each percent that the magnitude of (q, - qb) exceeds -37 percent, the AT trip setpoint shall be automatically reduced by 0.33 percent of its value at RATED THERMAL POWER (iii) For each percent that the magnitude of (q, - qb) exceeds +3 percent, the AT trip setpoint shall be automatically reduced by 2.34 percent of its value at 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 10 of 14

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

Overpower AT Setpoint Overpower AT < AT. [14 - K5 T+r I Tr

] T- K.(T - T )-C2 (Al)]

Where: AT. Indicated AT at RATED THERMAL POWER, OF T Average temperature, IF T" Nominal T.,, at RATED THERMAL POWER (< 562.1 0 F)

K4 1.172

  • K5 0.0177/ 0 F for increasing average temperature ; K5 = 0 for decreasing average temperature K6 0.0015/0 F forT> T"; K6 = 0 forT < T"

+r3S

= The function generated by the rate lag controller for T.,, dynamic 1 + T3S compensation I3 = Time constant utilized in the rate lag controller for T.vg 3> 10 secs.

S = Laplace transform operator f2 (A) = 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 11 of 14

D. C. COOK UNIT I CYCLE 20 Revision I FIGURE 6 Reactor Core Safety Limits 660 650 640

- 630

> 620 s

610 C)

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) (I F) (frac) (I F) (frac) VF) 1840 0.02 620.86 1.136 586.17 1.2 577.94 2000 0.02 632.79 1.094 600.31 12 586.52 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 12 of 14

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

-1.98E-04 L -2.00E-04

'r

-2.02E-04 I I ==== ==

C-

' -2.04E-04

  • -2.06E-04 0

t< X31 2.08E-04 0

  • -2.1 OE-04 Ad -2.12E-04 0o

-2.14E-04 2000 121 13000 14000 15000 16000 Cycle Burnup (MWDIMTU)

Burnup (MWDIMTU) MTC (Mdk/kF) 12000 -2.0020E-4 13320 -2.0458E-4 14320 -2.0770E-4 15320 -2.1064E-4 16000 -2.1256E-4 Page 13 of 14

D. C. COOK UNIT 1 CYCLE 20 Revision 1 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 20 W(Z) FUNCTION Node hreight Burnup (MW1D/M TU)

NO. (feet) I,)( 1000 200 4000 6000 8000 10000 12000 14000 16000O 17970 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 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 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 4 0.6 1.0000 1.0000 1.0000 1.0000 1.0000 1.006)0 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 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 7 1.2 1.0985 1.0993 1.1003 1.1026 1.1052 1.1081 1.1114 1.1151 1.1191 1.1231 1.1268 8 1.4 1.0987 1.0994 1.1004 1.1025 1.1050 1.1078 1.1109 1.1143 1.1181 1.1219 1.1254 9 1.6 1.0986 1.0993 1.1002 1.1022 1.1045 1.1071 1.1100 1.1132 1.1167 1.1202 1.1235 10 1.8 1.0983 1.0989 1.0997 1.1016 1.1037 1.1000 1.1087 1.1116 1.1147 1.1179 1.1209 11 2.0 1.0977 1.0983 1.0990 1.1006 1.1025 1.1046 1.1069 1.1094 1.1122 1.1151 1.1177 12 2.2 1.0969 1.0974 1.0980 1.0994 1.1010 1.1027 1.1047 1.1009 1.1093 1.1117 1.1139 13 2.4 1.0959 1.0963 1.0968 1.0978 1.0991 1.1000 1.1022 1.1040 1.1000 1.1080 1.1099 14 2.6 1.0947 1.0949 1.0952 1.0960 1.0969 1.0980 1.0993 1.1008 1.1025 1.1042 1.1057 15 2.8 1.0932 1.0933 1.0934 1.0938 1.0944 1.0951 1.0961 1.0973 1.0980 1.1000 1.1011 16 3.0 1.0916 1.0915 1.0915 1.0915 1.0917 1.0921. 1.0926 1.0934 1.0943 1.0952 1.0960 17 3.2 1.0901 1.0899 1.0897 1.0894 1.0892 1.0892 1.0893 1.0895 1.0899 1.0903 1.0906 18 3.4 1.0888 1.0885 1.0882 1.0876 1.0871 1.0868 1.0865 1.0864 1.0864 1.0805 1.0864 19 3.6 1.0880 1.0875 1.0870 1.0862 1.0856 1.0852 1.0849 1.0849 1.0851 1.0853 1.085 I 20 3.8 ~1.0875 1.0867 1.0860 1.0848 1.0a40 1.0837 1.0839 1.0845 1.0855 1.0866 1.0874 21 4.0 1.0869 1.0859 1.0849 1.0835 1.0828 1.0828 1.0836 1.0851 1.0874 1.0899 1.09 17 22 .4.2 1.0862 1.0851 1.0841 1.0828 1.0824 1.0828 1.0842 1.0864 1.0896 1.0930 1.0955 23 4.4 1.0854 1.0844 1.0835 1.0825 1.0824 1.0832 1.0851 1.0850 1.0918 1.0958 1.0989 24 1.6 1.0845 -1.0836 1.0828 1.0820 1.0822 1.0835 .1.0858 1.0893 1.0937 1.0984 1.1021 25 4.8 1.083 1.0825 1.0818 1.0813 1.0819 1.0836 1.0864 1.0903 1.0953 1.1006 1.1048 26 5.0 1.0823 1.0816 1.0810 1.0807 1.0815 1.0835 .1.0867 1.0911 1.0966 1.1025 1.1071

27. 5.2 1.0818 1.0810 1.0804 1.0800 1.0809 1.0830 1.0866 1.0914 1.0974 1.1038 1.1090 28 5.4 1.0813 1.0804 1.0797 1.0792 1.0801 1.0824 .1.0862 1.0913 1.0978 1.1047 1.1102 29 5.6 1.0805 1.0798 1.0793 1.0791 1.0803 1.0827 1.0865 1.0916 1.0981 1.1049 1.1103 30 5.8 1.0795 1.0791 1.0789 1.0793 1.0807 1.0833 1.0871 1.0920 1.0980 1.1043 1.1095 31 6.0 1.0782 1.0781 1.0782 1.0791 1.0809 1.0836 1.0873 1.0919 1.0974 1.1031 1.1079 32 6.2 1.0766 1.0768 -10772 1.0786 1.0807 1.0835 1.0870 1.0912 1.0961 1.1012 1.1056 33 6.4 1.0746 1.0751 1.0759 1.0777 1.0800 1.0828 1.0861 1.0899 1.0941 1.0986 1.1025 34 6.6 1.0722 1.0730 1.0740 1.0763 1.0788 1.0815 1.0846 1.0879 1.0915 1.0951 1.0985 35 6.8 1.0696 1.0700 1.0718 1.0743 1.0768 1.0795 1.0823 1.0852 1.0883 1.0913 1.0942 36 7.0 1.0671 1.0682 1.0695 1.0721 1.0747 1.0775 1.0803 1.0831 1.0861 1.0890 1.0919 37 7.2 1.0646 1.0660 1.0678 1.0711 1.0743 1.0775 1.0805 1.0833 1.0861 1.0889 1.0917 38 7.4 1.0630 1.0655 1.0682 1.0731 1.0773 1.0809 1.0837 1.0859 1.0874 1.0887 1.0900 39 7.6 1.0654 1.0681 1.0711 1.0763 1.0806 1.0840 1.0863 1.0876 1.0879 1.0880 1.0890 40 7.8 1.0702 1.0727 1.0755 1.0801 1.0838 1.0864 1.0879 1.0883 1.0877 1.0868 1.0869 41 8.0 1.0750 1.0773 1.0798 1.0838 1.0868 1.0886 1.0891 1.0885 1.0867 1.0846 1.0837 42 8.2 1.0796 1.0816 1.0837 1.0871 1.0892 1.0902 1.0899 1.0884 1.0858 1.0828 1.0809 43 8.4 1.0840 1.0855 1.0871 1.0895 1.0909 1.0914 1.0909 1.0895 1.0870 1.0844 1.0826 44 8.6 1.0881 1.0891 1.0900 1.0914 1.0921 1.0921 1.0914 1.0900 1.0879 1.0856 1.0840 45 8.8 1.0921 1.0923 1.0926 1.0928 1.0928 1.0924 1.0917 1.0907 1.0894 1.0879 1.0868 46 9.0 1.0957 1.0952 1.0947 1.0939 1.0932 1.0927 1.0924 1.0923 1.0924 1.0926 1.0925 47 9.2 1.0990 1.0978 1.0966 1.0946 1.0934 1.0929 1.0933 1.0943 1.0961 1.0981 1.0994 48 9.4 1.2020 1.1000 1.0980 1.0950 1.0932 1.0928 1.0037 1.0959 1.0994 1.1033 1.1059 49 9.6 1.1045 1.1021 1.0997 1.0961 1.0942 1.0938 1.0952 1.0983 1.1029 1.1081 1.1116 50 9.8 1.1069 1.1043 1.1017 1.0978 1.0958 1.0956 1.0973 1.1009 1.1064 1.1124 1.1165 51 10.0 1.1093 1.1065 1.1036 1.0994 1.0972 1.0971 1.0991 1.1033 1.1094 1.1162 1.1209 52 10.2 1.1112 1.1083 1.1054 1.1012 1.0990 1.0991 1.1013 1.1057 1.1122 1.1194 1.1244 53 10.4 1.1125 1.1099 1.1072 1.1034 1.1016 1.1018 1.1042 1.1086 1.1150 1.1219 1.1269 54 10.6 1.1136 1.1111 1.1087 1.1053 1.1037 1.1041 1.1065 1.1108 1.1170 1.1238 1.1286 55 10.8 1.1150 1.1126 1.1103 1.1070 1.1056 1.1060 1.1083 1.1125 1.1185 1.1251 1.1298 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 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 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 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 60 11.8 1.0000 1.0000 1.0000 1.0000 2.0000 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 Top and bottom 10% of core excluded.

Page 14 of 14

ATTACHMENT 2 TO AEP:NRC:5691-04 DONALD C. COOK NUCLEAR PLANT (CNP) UNIT I CYCLE 20 CORE OPERATING LIMITS REPORT REVISION 2

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

D. C. COOK UNIT 1 CYCLE 20 Revision 2 D. C. COOK UNIT I CYCLE 20 Revision 2 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit I Cycle 20 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
b. WCAP-8385, Power Distribution Control and Load Following Procedures - Topical Report
c. WCAP-10216-P-A, Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification
d. WCAP-10266-P-A, The 1981 Version of Westinghouse Evaluation Mode Using BASH Code
e. WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report
f. WCAP-8745-P-A, Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions
g. WCAP-1 3749-P-A, Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement The Technical Specifications affected by this report are listed below:

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

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNA1,)

3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reactor Trip System (RTS) Instrumentation 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3.9.1 Boron Concentration Page 1 of 14

D. C. COOK UNIT 1 CYCLE 20 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 I and 2, the combination of thermal power, pressurizer pressure, and the highest loop average temperature (Tavg) shall not exceed the limits as shown in Figure 6 for 4 loop operation.

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

Shutdown margin shall be greater than or equal to 1.3% Ak/k for Tavg > 200'F Shutdown margin shall be greater than or equal to 1.0% Ak/k for Ta.g

  • 200'F 2.2.2 Moderator Temperature Coefficient (MTC) (Specification 3.1.3)
a. The Moderator Temperature Coefficient (MTC) limits are:

The BOLIARO-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.,., program with HFP vessel Tag 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 2 of 14

D. C. COOK UNIT I CYCLE 20 Revision 2 D. C. COOK UNIT I CYCLE 20 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/Ik/ 0 F at a HFP vessel T.,g 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/WkIF.

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/AROIRTP-MTC should be less negative or equal to -4.41E-4 Ak/k/0 F at a HFP vessel Titg 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 20.0 MWD/MTU.

Page 3 of 14

D. C. COOK UNIT I CYCLE 20 Revision 2 D. C. COOK UNIT 1 CYCLE 20 Revision 2 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

CF F~c(Z)< C' Q P

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

_CF~

FQ') (Z) < P

  • K(Z) for P > 0.5 FQ (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. FCQ(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. FQ (Z) = F C(Z) X W(Z) X Fp
f. For Cycle 20, when FcQ(Z)/K(Z) is increasing, Fp = 1.02 for all burnups. When no penalty is required, Fp = 1.00.

2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (FNair, ) (Specification 3.2.2)

FNMI < CFmI * (I + PFmi *(I-P))

Where: P THERMAL POWER RATED THERMAL POWER

a. CFmI= 1.49
b. PFw=0.3 Page 4 of 14

D. C. COOK UNIT I CYCLE 20 Revision 2 D. C. COOK UNIT I CYCLE 20 Revision 2 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 2 2018 psig +
b. Reactor Coolant System TAVG shall be < 581.4 0 F +
c. Reactor Coolant System Total Flow Rate shall be 2341,100 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 579.1IF for Tavg, and 2050 psig for Pressurizer Pressure.

++ This concentration bounds the condition of Kfr < 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 5 of 14

D. C. COOK UNIT I CYCLE 20 Revision 2 D. C. COOK UNIT I CYCLE 20 Revision 2 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0

[NACCEPTABLE OPERATION 0.5 I II I I I \ _

0-LL 0) a)

0.0 I I II I I I

[ACCEPTABLE OPERATION]I I'l q

Irl x

-0.5 0 20I 1 4 5 I 60

-1.0 0 10 20 30 40 50 60 70 80 90 100 Percent Rated Thermal Power Page 6 of 14

D. C. COOK UNIT I CYCLE 20 Revision 2 D. C. COOK UNIT I CYCLE 20 Revision 2 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (FOUR-LOOP OPERATION) 250 225 200 175 150 ax 3.

1=

cn zC') 125 0

0 CO 0 100 0

0 0o 0

75 50 25 0

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

Page 7 of 14

D. C. COOK UNIT I CYCLE 20 Revision 2 D. C. COOK UNIT 1 CYCLE 20 Revision 2 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 90 5-pl T"

x 80 N _

xd N 70 x Bg a-IL 60 U.

50 a.

3 a-kF-j

._0 40 E

30 20

'4-0 10 0

SO FLUX DIFFERENCE (DELTA-I)

Page 8 of 14

D. C. COOK UNIT I CYCLE 20 Revision 2 D. C. COOK UNIT I CYCLE 20 Revision 2 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 (0.0 ,1.0) l (6.0, 1.0) l 1.0 (1.0 0.25 0.8 (D

z w

a.

0 w 0.6 N

-i 0

z 0.4 0.2 0

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

Page 9 of 14

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

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT < ATO 1KI - K2 E 1+

11 + r25]

] (T-T') + K3 (P-P') - ff (AI)]

Where: AT =MMeasured RCS AT, OF AT0 = Indicated AT at RATED THERMAL POWER 0 F T = Average temperature, 0 F Tr = Nominal Tasg at RATED THERMAL POWER ( *574.0 'F)

P = Pressurizer pressure, psig

= Nominal RCS operating pressure (2085 psig)

P~rs

= The function generated by the lead-lag controller for Ta,, dynamic compensation T1+ T2 = Time constants utilized in the lead-lag controller for T,,2 Tr> 22 secs. r2 < 4 secs.

S = Laplace transform operator, sec' K, < 1.35

  • K2 > 0.0230/0 F K3 0.001 10/psig f, (A!) 0.33 (37 + (qt - qb)) when q, - qb < -37% RTP 0% of RTP when -37% RTP < q( - qb < 3% RTP

-2.34 {(qt - qb)- 3 ) when qt-qb>3%RTP where q, and qb are percent RATED THERMAL POWER in the upper and lower halves of the core respectively, and 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 10 of 14

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

Overpower AT Trip Setpoint Overpower AT

  • AT. [K, - Ks [ ~j T - K6 (T - T") - f2 (A])J Where: AT = Measured RCS AT, OF AT. Indicated AT at RATED THERMAL POWER, IF T = Average temperature, IF T' = Nominal T.vg at RATED THERMAL POWER (< 562.1 0F)

K4 < - 1.172

  • Ks > 0.0177/1F for increasing average temperature ; Ks = 0 for decreasing average temperature K6 > 0.0015/ 0F 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 T.,, dynamic 1+ rS compensation T3 = Time constant utilized in the rate lag controller for T,,, ¶3 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 11 of 14

D. C. COOK UNIT 1 CYCLE 20 Revision 2 FIGURE 6 Reactor Core Safety Limits 660 650 2400 _sia UNACC PTABLE 640 1840 psia-

- 630 0)

>620 2000-PI--V IL610 34 jpsia- X 0

W 600 590 -_~ACETABLE ___-

== OD~QER TIQN======O 580 570 0 0.2 0.4 0.6 0.8 1 1.2 Power (fraction of rated thermal power)

DESCRIPTION OF SAFETY LIMITS PRESSURE Power Tavg Power Tavg Power Tavg (PSIA) (frac) (' F) (frac) (IF) (frac) (IF) 1840 0.02 620.86 1.136 586.17 1.2 577.94 2000 0.02 632.79 1.094 600.31 1.2 586.52 2100 0.02 639.85 1.068 608.72 1.2 591.77 2250 0.02 649.96 1.031 620.83 1.2 599.40 2400 0.02 659.52 0.996 632.42 1.2 606.63 UNIT I Reactor Core Safety Limits Page 12 of 14

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

-1.98E-04 u- -2.OOE-04 C6

, 2.02E-04 -= \

-2.04E-04 o-2.06E-04 C.,

i~ -2.108E-04 .- _ _ _ _ _ _ _ _ _

-2.12E-04 -_ _ _ _ _ __ _ _

0

-2.14E-04 12000 13000 14000 15000 16000 Cycle Burnup (MWDIMTU)

Burnup (MWD/MTU) MTC (AklkPF) 12000 -2.0020E-4 13320 -2.0458E-4 14320 -2.0770E-4 15320 -2.1064E-4 16000 -2.1256E-4 Page 13 of 14

D. C. COOK UNIT I CYCLE 20 Revision 2 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 20 W(Z) FUNCTION Node Height Burnup (MWVD/MTU)

No. (feet) 150 1000 2000 4000 6000 8000 10000 12000 14000 16000 17.00 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 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 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 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 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 6 1.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 7 1.2 1.0985 1.0993 1.1003 1.1026 1.1052 1.1081 1.1114 1.1151 1.1191 1.1231 1.1268 8 1.4 1.0987 1.09931 1.10041 1.1025 1.1050 1.1078 1.1109 1.1143 1.1181 1.1219 1.1254 9 1.6 1.0986 1.0993 1.1002 1.1022 1.1045 1.1071 1.1100 1.1132 1.1167 1.1202 1.1235 10 1.8 1.0983 1.0989 1.0997 1.1016 1.1037 1. 10GO 1.1087 1.1116 1.1147 1.1179 1.1209 11 2.0 1.0977 1.0983 1.0990 1.1006 1.1025 1.1046 1.1069 1.109.1 1.1122 1.1151 1.1177 12 2.2 1.0969 1.0974 1.0980 1.0994 1.1010 1.1027 1.1047 1.1069 1.1093 1.1117 1.1139 13 2.4 1.0959 1.0963 1.09G8 1.0978 1.0991 1. 1006 1.1022 1.1040 1.1060 1.1080 1.1099 14 2.6 1.0947 1.0949 1.0952 1.0960 1.0969 1.0980 1.0993 1.1008 1.1025 1.1042 1.1057 15 2.8 1.0932 1.0933 1.0934 1.0938 1.09.14 1.0951 1.0961 1.0973 1.0986 1.1000 1.1011 IG 3.0 1.0916 1.0915 1.0915 1.09 15 1.0917 1.0921 1.0926 1.0934 1.0943 1.0952 1.09GO 17 3.2 1.0901 1.0899 1.0897 1.0894 1.0892 1.0892 1.0893 1.0895 1.0899 1.0903 1.0906 18 3.4 1.0888 1.0885 1.0882 1.0876 1.0871 1.08G8 1.0865 1.0864 1.0864 1.0865 1.08G4 19 3.6 1.0880 1.0875 1.0870 1.0862 1.0856 1.0852 1.0849 1.0849 1.0851 1.0853 1.0853 20 3.8 1.0875 1.0867 1.0860 1.0848 1.0840 1.0837 1.0839 1.0845 1.0855 1.0866 1.0874 21 4.0 1.0869 1.0859 1.0849 1.0835 1.0828 1.0828 1.0836 1.0851 1.0874 1.0899 1.0917 22 4.2 1.0862 1.0851 1.0841 1.0828 1.0824 1.0828 1.0842 1.08G4 1.089G 1.0930 1.0955 23 4.4 1.08541 1.0844 1.0835 1.0825 1.0824 1.0832 1.0851 1.0880 1.0918 1.0958 1.0989 24 4.6 1.0845 1.0836 1.0828 1.0820 1.0822 1.0835 1.0858 1.0893 1.0937 1.0984 1.1021 25 4.8 1.0833 1.0825 1.0818 1.08 13 1.0819 1.0836 1.0864 1.0903 1.0953 1. 1006 1.1048 26 5.0 1.0823 1.0816 1.0810 1.0807 1.0815 1.0835 1.0867 1.0911 1.09GG 1.1025 1.1071 27 5.2 1.0818 1.0810 1.0801 1.0800 1.0809 1.0830 1.0866 1.0914 1.0974 1.1038 1.1090 28 5.4 1.0813 1.0804 1.0797 1.0792 1.0801 1.0824 1.0862 1.0913 1.0978 1.1047 1.1102 29 5.6 1.0805 1.0798 1.0793 1.0791 1.0803 1.0827 1.0865 1.0916 1.0981 1.1049 1.1103 SO 5.8 1.0795 1.0791 1.0789 1.0793 1.0807 1.0833 1.0871 1.0920 1.0980 1.1043 1.1095 31 6.0 1.0782 1.0781 1.0782 1.0791 1.0809 1.0836 1.0873 1.0919 1.0974 1.1031 1.1079 32 6.2 1.0766 1.0768 1.0772 1.0786 1.0807 1.0835 1.0870 1.0912 1.09G1 1.1012 1.105G 33 6.4 1.074G 1.0751 1.0759 1.0777 1.0800 1.0828 1.0861 1.0899 1.0941 1.0986 1.1025 34 6.6 1.0722 1.0730 1.0740 1.0763 1.0788 1.0815 1.0846 1.0879 1.0915 1.0951 1.0985 35 6.8 1.0696 1.070G 1.0718 1.0743 1.0768 1.0795 1.0823 1.0852 1.0883 1.0913 1.0942 36 7.0 1.0671 l.OG82 1.0695 1.0721 1.0747 1.0775 1.0803 1.0831 1.0861 1.0890 1.0919 37 7.2 1.0G46 1.0660 1.0678 1.0711 1.0743 1.0775 1.0805 1.0833 1.0861 1.0889 1.0917 38 7.4 1.0630 1.0655 1.OG82 1.0731 1.0773 1.0809 1.0837 1.0859 1.0874 1.0887 1.0906 39 7.6 1.OG54 1.0681 1.0711 1.0763 1.0806 1.0840 1.0863 1.0876 1.0879 1.0880 1.0890 40 7.8 1.0702 1.0727 1.0755 1.0801 1.0838 1.086.1 1.0879 1.0883 1.0877 1.08G8 1.0869 41 8.0 1.0750 1.0773 1.0798 1.0838 1.08G8 1.0886 1.0891 1.0885 1.0867 1.0816 1.0837 42 8.2 1.0796 1.0816 1.0837 1.0871 1.0892 1.0902 1.0899 1.0884 1.0858 1.0828 1.0809 43 8.4 1.0840 1.0855 1.0871 1.0895 1.0909 1.0914 1.0909 1.0895 1.0870 1.084-4 1.0826 44 8.6 1.0881 1.0891 1.0900 1.09 14 1.0921 1.0921 1.0914 1.0900 1.0879 1.0856 1.0840 45 8.8 1.0921 1.0923 1.0926 1.0928 1.0928 1.0924 1.0917 1.0907 1.0894 1.0879 1.0868 4G 9.0 1.0957 1.0952 1.0947 1.0939 1.0932 1.0927 1.0924 1.0923 1.0924 1.0926 1.0925 47 9.2 1.0990 1.0978 1.0966 1.0946 1.0931 1.0929 1.0933 1.0943 1.0961 1.0981 1.099.1 48 9.4 1.1020 1.1000 1.0980 1.0950 1.0932 1.0928 1.0937 1.0959 1.0991 1.1033 1.1059 49 9.G 1.1045 1.1021 1.0997 1.096 1 1.0942 1.0938 1.0952 1.0983 1.1029 1.1081 1.1116 50 9.8 1.1069 1.10413 1.1017 1.0978 1.0958 1.0956 1.0973 1.1009 1.1064 1.1124 1.1165 51 10.0 1.1093 1.1065 1.1036 1.0994 1.0972 1.0971 1.0991 1.1033 1.1094 1.1162 1.1209 52 10.2 1.1112 1.1083 1.1054 1.10 12 1.0990 1.0991 1.1013 1.1057 1.1122 1.11921 1.124.1 53 10.4 1.1125 1.1099 1.1072 1.1034 1.1016 1.1018 1.10412 1.1086 1.1150 1.1219 1.1269 54 10.6 1.1136 1.1111 1.1087 1.1053 1.1037 1.1041 1.10G5 1.1108 1.1170 1.1238 1.1286 55 10.8 1.1150 1.112G 1.1103 1.1070 1.1056 1. 10GO 1.1083 1.1125 1.1185 1.1251 1.1298 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 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 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 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 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 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 Top and bottom 10% of core excluded.

Page 14 of 14

ATTACHMENT 3 TO AEP:NRC:5691-04 DONALD C. COOK NUCLEAR PLANT (CNP) UNIT 2 CYCLE 15 CORE OPERATING LIMITS REPORT REVISION 1

D. C. COOK UNIT 2 CYCLE 15 Revision I Donald C. Cook Nuclear Plant Unit 2 Cycle 15 Core Operating Limits Report Revision I

D. C. COOK UNIT 2 CYCLE 15 Revision I D. C. COOK UNIT 2 CYCLE 15 Revision 1 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 15 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 Westinghouse Evaluation Mode Using BASH Code, March 1987
e. WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, July 1991
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 Safety Limits 3.1.1 Shutdown Margin (SDM) 3.1.3 Moderator Temperature Coefficient (MTC) 3.1.5 Shutdown Bank Insertion Limit 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 (FNm,)

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 1 of 16

D. C. COOK UNIT 2 CYCLE 15 Revision 1 D. C. COOK UNIT 2 CYCLE 15 Revision I 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 Safety Limits (Specification 2.1.1)

In Modes 1 and 2, the combination of thermal power, pressurizer pressure, and the highest operating loop coolant 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 (Specification 3.1.1)

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

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

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

The EOL/ARO/RTP-MTC shall be less negative than or equal to -4.1OE-4 Ak/kI/F.

This limit is based on a Tag program with HFP vessel Ta.g of 571 to 576 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 2 of 16

D. C. COOK UNIT 2 CYCLE, 15 Revision I

b. The MTC Surveillance limit is:

The 300 ppm/AROIRTP-MTC should be less negative or equal to -3.20E-4 Ak/kl/ 0 F at a HEFP vessel Tav. of 571 to 576 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*

  • 0 Predicted Correction is -0.30E-4 Ak/kI1F.

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 ppmIARO/RTP-MTC should be less negative or equal to -3.90E-4 Ak/k/0 F at a HFP vessel Targ of 571 to 576 0 F 2.2.3 Shutdown Rod Insertion Limit (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.

Page 3 of 16

D. C. COOK UNIT 2 CYCLE 15 Revision 1

b. The AFD target band is +5% for a cycle average accumulated burnup 20.0 MWD/MTU 2.3.2 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3.2.1)

FQC (Z) < Q

  • K(Z) for P > 0.5 FQC(Z)<2*CFQ*K(Z) forP*0.5 F}V'(Z) CFQ K(Z) for P >0.5 FQV(Z) < 2
  • CFQ *K(Z) for P < 0.5 Whe P THERMAL POWER Where: RATED THERMAL POWER
a. CFQ = 2.335
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 Tables 1 for AFD target band of +5%.
e. FQV (Z) = FcQ (Z) x W(Z) x Fp
f. For Cycle 15, when applicable, Fp = 1.02 all burnups.

Page 4 of 16

D. C. COOK UNIT 2 CYCLE 15 Revision 1 D. C. COOK UNIT 2 CYCLE 15 Revision 1 2.3.3 Nuclear Enthalpy Rise Hot Channel Factor - FN I (Specification 3.2.2)

FAH < CFuI * (1 + PFaH *(1UP))

THERMAL POWER Where: P RATED THERMAL POWER

a. CFA= 1.58
b. PF=H 0.3 2.4 INSTRUMENTATION 2.4.1 Reactor Trip System 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. Reactor Coolant System Tavg shall be < 580.1 F+
b. Pressurizer Pressure shall be 2 2172 psig +
c. Reactor Coolant System Total Flow Rate shall be 2366,400 gpm

+ These are Safety Analysis values. With readability allowance, the corresponding values are 577.80 F for Tang , and 2200 psig for Pressurizer Pressure.

Page 5 of 16

D. C. COOK UNIT 2 CYCLE 15 Revision 1 D. C. COOK UNIT 2 CYCLE 15 Revision 1 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 ppmr.

+ This concentration bounds the condition of Ken < 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 16

D. C. COOK UNIT 2 CYCLE 15 Revision I D. C. COOK UNIT 2 CYCLE 15 Revision I FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 0.5 LL CU I.

i, 0.0 Cb 0

Ir-

-0.5

-1.0 0 10 20 30 40 50 60 70 80 90 100 Percent Rated Thermal Power Page 7 of 16

D. C. COOK UNIT 2 CYCLE 15 Revision I D. C. COOK UNIT 2 CYCLE 15 Revision I FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (FOUR-LOOP OPERATION) 250 225 200 175 I

U, 150 a) 0 0:

z ci CL 125 a:

(.

cn 100 0

0 75 50 25 0

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

Page 8 of 16

D. C. COOK UNIT 2 CYCLE 15 Revision I iI FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 90 CD 0

x 80 V-N 70 Xc5LL LL 60 0 50 40 E

30 HE 20 4-0 10 0

FLUX DIFFERENCE (DELTA-I)

Page 9 of 16

D. C. COOK UNIT 2 CYCLE 15 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 -

z 7-w 5.

0 wi 0.6 -

N 0

z 0.4 0.2-0.0 0 2 4 6 8 10 12 CORE HEIGHT (FT)

Page 10 of 16

D. C. COOK UNIT 2 CYCLE 15 Revision 1 D. C. COOK UNIT 2 CYCLE 15 Revision I FIGURE 5 (Page 1 of 3)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT

  • AT [K1 - K2 [1+

0 1 1 L + r2SJ 1 (T-T') + K3 (P-P') -f1 (AI)J Where: AT. = Indicated AT at RATED THERMAL POWER, IF T = Average temperature, IF T/ = Nominal T,,ag at RATED THERMAL POWER, < 576.00 F P = Pressurizer Pressure, psig P' = 2235 psig (indicated RCS nominal operating pressure)

= The function generated by the lead-lag controller for T.,, dynamic I + T2S compensation C -r2 = Time constants utilized in the lead-lag controller for T.,,; r > 28 secs, 2< 4 secs.

S Laplace transform operator, sect Page 11 of 16

D. C. COOK UNIT 2 CYCLE 15 Revision 1 D. C. COOK UNIT 2 CYCLE 15 Revision I FIGURE 5 (Page 2 of 3) 4 Loops in Operation K, < 1.19*

K2 > 0.0133 I/OF K3 > 0.00058/psig and f1 (AI) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chamnbers; with gains to be selected based on measured instrument response during plant startup tests such that:

(i) For qt - qb between -33 percent and +6 percent, f1(AI)=0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and q, + qb is total THERMAL POWER in percent of RATED THERMAL POWER).

(ii) For each percent that the magnitude of (q, - qb) exceeds -33 percent, the AT trip setpoint shall be automatically reduced by 3.5 percent of its value at RATED THERMAL POWER.

(iii) For each percent that the magnitude of (qt - qb) exceeds +6 percent, the AT trip setpoint shall be automatically reduced by 1.0 percent of its value at 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 15 Revision I D. C. COOK UNIT 2 CYCLE 15 Revision I FIGURE 5 (Page 3 of 3)

Overpower AT Setpoint Overpower AT < AT. IK4 - Ks i+ s,S1 T- K16 - TT"] -f2 (Al)]

Where: AT 0 = Indicated AT at rated power T Average temperature, 'F Tie = Nominal T.,, at RATED THERMAL POWER, < 576.0 'F K4 < 1.16*

K5 > 0.02/0 F for increasing average temperature and 0 for decreasing average temperature K6 > 0.00197/ 0 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 T.,g dynamic 1 + -r~s compensation T3

= Time constant utilized in the rate lag controller for T.,vg; 73 > IOsecs.

S = Laplace transform operator, sec' 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

D. C. COOK UNIT 2 CYCLE 15 Revision I D. C. COOK UNIT 2 CYCLE 15 Revision I FIGURE 6 Reactor Core Safety Limits 660 650 -_ = _ = ~UNACCE PTAEBLE===

_2400 F SIA NTO 640

~2250 F ii \ _ =

630 620 t-. = = 20001 =F U.

610 U) 600 590

=_ ~~~ACCEP ABLE..= \

580

__~~PF __ __ _

570 560 550 0 0.2 0.4 0.6 0.8 I 1.2 Power (fraction of rated thermal power)

DESCRIPTION OF SAFETY LIMITS PRESSURE Power Tavg Power Tavg Power Tavg Power Tavg (psia) (frac) (' F) (frac) ( F) (frac) (' F) (frac) (' F) 1775 0.00 615.4 0.98 583.8 1.02 580.9 1.2 558.1 2000 0.00 631.8 0.86 605.8 0.96 597.5 1.2 568.5 2100 0.00 639.1 0.82 614.0 0.96 601.6 1.2 573.1 2250 0.00 649.2 0.72 628.6 0.98 605.2 1.2 580.4 2400 0.00 659.0 0.62 642.0 1.1 599.0 1.2 588.1 UNIT 2 Reactor Core Safety Limits Page 14 of 16

D. C. COOK UNIT 2 CYCLE, 15 Revision I D. C. COOK UNIT 2 CYCLE 15 Revision 1 FIGURE 7 Unit 2 Cycle 15 Predicted HFP ARO 300 PPM MTC Versus Burnup

-2.28E-04 - _ l = _ =

U- -2.30E-04 -\ \

-2.34E-04

-2.36E-04 E -2.38E-04 co

' -2.40E-04 -

c ~-2.48E-04 2.44E _ _ _ _ _ _ _ _ _

0.-2.48E-04 14000 15000 16000 17000 18000 19000 Cycle Burnup (MWD/MTU)

Burnup (MWDIMTU) MTC (AkWkPF) 14000 -2.2855E-4 15916 -2.3615E-4 16916 -2.3984E-4 17916 -2.4325E-4 19000 l -2.4679E-4 Page 15 of 16

D. C. COOK UNIT 2 CYCLE 15 Revision 1 TABLE 1 D. C. Cook Unit 2, Cycle 15 W(Z) Function Node Height Bumup (NIWD/MTU)

PT (Ft.) 150 1000 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 20650 0.0000 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 0.2000 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 0.4000 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 0.6000 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 0.8000 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 1.0000 1.0000 1.2000 1.1012 1.1007 1.1005 1.1015 1.1046 1.1097 1.1159 1.1221 1.1281 1.1342 1.1405 1.1466 1.1486 1.4000 1.1013 1.1009 1.1008 1.1018 1.1047 1.1095 1.1153 1.1210 1.1266 1.1322 1.1379 1.1435 1.1454 1.6000 1.1012 1.1008 1.1008 1.1018 1.1045 1.1090 1.1143 1.1195 1.1246 1.1297 1.1348 1.1400 1.1417 1.8000 1.100S 1.1005 1.1005 1.1014 1.1039 1.1080 1.1128 1.1175 1.1220 1.1265 1.1311 1.1356 1.1371 2.0000 1.1001 1.0999 1.0999 1.1008 1.1030 1.1066 1.1108 1.1149 1.1188 1.1226 1.1265 1.1304 1.1317 2.2000 1.0991 1.0990 1.0990 1.0998 1.1017 1.1048 1.1084 1.1118 1.1151 1.1182 1.1213 1.1246 1.1256 2.4000 1.0978 1.0977 1.0978 1.0985 1.1001 1.1027 1.1056 1.1083 1.1108 1.1132 1.1155 1.1180 1.1188 2.6000 1.0963 1.0962 1.0963 1.0969 1.0982 1.1002 1.1024 1.1043 1.1060 1.1076 1.1091 1.1107 1.1113 2.8000 1.0945 1.0945 1.0946 1.0950 1.0959 1.0972 1.0987 1.0999 1.1008 1.1016 1.1023 1.1031 1.1034 3.0000 1.0923 1.0924 1.0924 1.0928 1.0934 1.0942 1.0950 1.0955 1.0956 1.0955 1.0952 1.0953 1.0953 3.2000 1.0901 1.0902 1.0903 1.0905 1.0908 1.0911 1.0913 1.0911 1.0905 1.0897 1.0886 1.0880 1.0878 3.4000 1.0886 1.0887 1.0888 1.0888 1.0886 1.0881 1.0876 1.0872 1.0868 1.0865 1.0862 1.0858 1.0857 3.6000 '1.0880 1.0880 1.08S0 1.0879 1.0873 1.0863 1.0856 1.0861 1.0876 1.0900 1.0928 1.0946 1.0952 3.8000 1.0873 1.0870 1.0863 1.0863 1.0857 1.0851 1.0852 1.0869 1.0902 1.0949 1.1003 1.1041 1.1054 4.0000 1.0864 1.0859 1.0854 1.0848 1.0845 1.0845 1.0856 1.0886 1.0933 1.0996 1.1069 1.1122 1.1139 4.2000 1.0853 1.0848 1.0844 1.0840 1.0844 1.0854 1.0877 1.0918 1.0976 1.1049 1.1132 1.1196 1.1216 4.4000 1.0843 1.0838 1.0836 1.0838 1.0849 1.0870 1.0903 1.0954 1.1020 1.1100 1.1189 1.1261 1.1284 4.6000 1.0839 1.0834 1.0831 1.0835 1.0851 1.0882 1.0927 1.0987 1.1060 1.1147 1.1241 1.1319 1.1345 4.8000 1.0839 1.0832 1.0827 1.0830 1.0852 1.0893 1.0949 1.1017 1.1097 1.1188 1.1286 1.1370 1.1397 5.0000 1.0837 1.0828 1.0821 1.0825 1.0851 1.0901 1.0967 1.1044 1.1128 1.1222 1.1323 1.1412 1.1440 5.2000 1.0833 1.0822 1.0813 1.0816 1.0846 .1.0905 1.0982 1.1065 1.1154 1.1250 1.1351 1.1443 1.1473 5.4000 1.0827 1.0813 1.0803 1.0805 1.0839 1.0907 1.0992 1.1081 1.1173 1.1269 1.1370 1.1464 1.1495 5.6000 1.0817 1.0803 1.0793 1.0796 1.0833 1.0906 1.0997 1.1090 1.1183 1.1279 1.1378 1.1474 1.1505 5.8000 1.0805 1.0790 1.0780 1.0783 1.0823 1.0900 1.0996 1.1092 1.1185 1.1279 1.1376 1.1471 1.1502 6.0000 1.0791 1.0776 1.0765 1.0768 1.0809 1.0890 1.0990 1.1086 1.1178 1.1269 1.1363 1.1456 1.1487 6.2000 1.0777 1.0760 1.0743 1.0749 1.0791. .1.0874 1.0976 1.1072 1.1162 1.1249 1.1338 1.1429 1.1458 6.4000 1.0758 1.0740 1.0727 1.0728 1.0770 1.0853 1.0955 1.1049 1.1136 1.1218 1.1302 1.1388 1.1416 6.6000 1.0734 1.0720 1.0709 1.0713 1.0753 1.0832 1.0927 1.1016 1.1097 1.1176 1.1255 1.1336 1.1363 6.8000 1.0704 1.0691 1.0682 1.0686 1.0724 1.0798 1.0886 1.0968 1.1043 1.1115 1.1187 1.1262 1.1287 7.0000 1.0677 1.0672 1.0671 1.0685 1.0723 1.0787 1.0861 1.0933 1.1002 1.1070 1.1138 1.1208 1.1230 7.2000 1.0678 1.0686 1.0698 1.0727 1.0763 1.0808 1.0860 1.0919 1.0983 1.1053 1.1127 1.1194 1.1216 7.4000 1.0715 1.0721 1.0731 1.0757 1.0793 1.0840 1.0892 1.0945 1.0999 1.1054 1.1111 1.1166 1.1184 7.6000 1.0749 1.0753 1.0761 1.0784 1.0819 1.0866 1.0918 1.0966 1.1012 1.1056 1.1100 1.1146 1.1161 7.8000 1.0777 1.0780 1.0787 1.0808 1.0841 1.0888 1.0937 1.0981 1.1019 1.1053 1.1085 1.1122 1.1134 8.0000 1.0803 1.0804 1.0809 1.0827 1.0858 1.0904 1.0953 1.0992 1.1021 1.1043 1.1061 1.1088 1.1097 8.2000 1.0824 1.0824 1.0826 1.0841 1.0871 1.0916 1.0963 1.0997 1.1017 1.1027 1.1032 1.1049 1.1055 8.4000 1.0841 1.0839 1.0839 1.0850 1.0877 1.0922 1.0968 1.0996 1.1007 1.1005 1.0997 1.1004 1.1007 8.6000 1.0852 1.0848 1.0847 1.0854 1.0879 1.0923 1.0967 1.0989 1.0990 1.0973 1.0949 1.0944 1.0943 8.8000 1.0861 1.0855 1.0852 1.0855 1.0877 1.0918 1.0959 1.0981 1.0986 1.0977 1.0960 1.0961 1.0961 9.0000 1.0866 1.0861 1.0858 1.0862 1.0882 1.0919 1.0959 1.0987 1.1004 1.1011 1.1015 1.1029 1.1033 9.2000 1.0878 1.0878 1.0881 1.0893 1.0916 1.0951 1.0987 1.1015 1.1034 1.1047 1.1056 1.1074 1.1079 9.4000 1.0911 1.0915 1.0920 1.0936 1.0963 1.1000 1.1037 1.1064 1.1081 1.1090 1.1096 1.1110 1.1115 9.6000 1.0954 1.0957 1.0963 1.0980 1.1008 1.1046 1.1083 1.1110 1.1126 1.1134 1.1137 1.1151 1.1155 9.8000 1.0996 1.0999 1.1005 1.1022 1.1049 1.1087 1.1125 1.1151 1.1166 1.1172 1.1173 1.1185 1.1189 10.0000 1.1035 1.1038 1.1044 1.1061 1.1088 1.1126 1.1163 1.1189 1.1202 1.1207 1.1207 1.1218 1.1221 10.2000 1.1071 1.1075 1.1081 1.1097 1.1124 1.1160 1.1196 1.1221 1.1236 1.1242 1.1244 1.1256 1.1260 10.4000 1.1104 1.1108 1.1113 1.1130 1.1155 1.1189 1.1223 1.1248 1.1263 1.1270 1.1274 1.1287 1.1291 10.6000 1.1132 1.1134 1.1139 1.1154 1.1179 1.1215 1.1250 1.1275 1.1289 1.1295 1.1297 1.1309 1.1313 10.8000 1.1154 1.1156 1.1160 1.1175 1.1200 1.1235 1.1271 1.1295 1.1309 1.1314 1.1315 1.1326 1.1329 11.0000 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 11.2000 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 11.4000 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 11.6000 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 11.8000 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 12.0000 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 Page 16 of 16

ATTACHMENT 4 TO AEP:NRC:5691-04 DONALD C. COOK NUCLEAR PLANT (CNP) UNIT 2 CYCLE 15 CORE OPERATING LIMITS REPORT REVISION 2

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

D. C. COOK UNIT 2 CYCLE 15 Revision 2 D. C. COOK UNIT 2 CYCLE 15 Revision 2 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 15 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
b. WCAP-8385, Power Distribution Control and Load Following Procedures - Topical Report
c. WCAP-10216-P-A, Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification
d. WCAP-10266-P-A, The 1981 Version of Westinghouse Evaluation Mode Using BASH Code
e. WCAP-126 10-P-A, VANTAGE+ Fuel Assembly Reference Core Report
f. WCAP-8745-P-A, Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions
g. WCAP-13749-P-A, Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement 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 (FNAII) 3.2.3 AXIAL FLUX DIFFERENCE (AED) 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 1 of 14

D. C. COOK UNIT 2 CYCLE 15 Revision 2 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 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,) 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% AkMI 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 -4.1 OE-4 Ak/k/ 0 F.

This limit is based on a Tayg program with HFP vessel Tavg of 571.0 to 576.0 '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 2 of 14

D. C. COOK UNIT 2 CYCLE 15 Revision 2 D. C. COOK UNIT 2 CYCLE 15 Revision 2

b. The MTC Surveillance limit is:

The 300 ppm/ARO/RTP-MTC should be less negative or equal to -3.20E-4 Ak/k/OF at a HFP vessel Tavg 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 AkIk;I/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 -3.90E-4 Ak/k/0 F at a HFP 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

>0.0 MWD/MTU.

Page 3 of 14

D. C. COOK UNIT 2 CYCLE 15 Revision 2 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

Q( ) F ( ) for P> 0.5 FQ (Z) < 2

  • K(Z) for P < 0.5 Fc~(Z) CFQ K(Z) for P > 0.5 P

FQ"'(Z)<2*CFQ *K(Z) for P<0.5 THERMAL POWER Where: ' =RATED THERMAL POWER

a. CFQ =2.335
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 I for +5% AFD target band.
e. FZQv (Z) = FcQ (Z) x W(Z) x Fp
f. For Cycle 15, when FCQ(Z)/K(Z) is increasing, Fp = 1.02 for all burnups. When no penalty is required, Fp = 1.00.

2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (FNAIll ) (Specification 3.2.2)

FNl,< CFul * (I + PFA&I *(l.P))

THERMAL POWER Where: P RATED THERMAL POWER

a. CFmI 1.58
b. PFmi= 0.3 Page 4 of 14

D. C. COOK UNIT 2 CYCLE 15 Revision 2 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 2 2172 psig +
b. Reactor Coolant System Tavg shall be
  • 580.1 F +
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 ppmn+.

+ These are Safety Analysis values. With readability allowance, the corresponding values are 577.8 0F for Tavg , and 2200 psig for Pressurizer Pressure.

+ This concentration bounds the condition of Kff < 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 5 of 14

D. C. COOK UNIT 2 CYCLE 15 Revision 2 D. C. COOK UNIT 2 CYCLE 15 Revision 2 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0

[UNACCEPTABLE OPERATIO 0.5 0-~

Cu U) 4-a 0.0 ACCEP ABLE OPERATION]

CD 0

Fr-

-0.5

-1.0 0 10 20 30 40 50 60 70 80 90 100 Percent Rated Thermal Power Page 6 of 14

D. C. COOK UNIT 2 CYCLE 15 Revision 2 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (FOUR-LOOP OPERATION) 250 225 200 C

175 (U

V

C 150 on 0) a)

z 125 0

co 0

D-100 CD 0

0 75 Ek-50 25 0

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

Page 7 of 14

D. C. COOK UNIT 2 CYCLE 15 Revision 2 D. C. COOK UNIT 2 CYCLE 15 Revision 2 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 90 Ira x 80 N

70 LL LL 60 0

0S 50 40 kr-.- 30 0_

20 10 0

FLUX DIFFERENCE (DELTA-I)

Page 8ofl4

D. C. COOK UNIT 2 CYCLE 15 Revision 2 D. C. COOK UNIT 2 CYCLE 15 Revision 2 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 (0.0, 1.0) (6.0,1.0) l 1.0 (12.0 , 0.925) 0.8 (9

z w

0 w 0.6 N

0 z

0.4 0.2 0

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

Page 9 of 14

D. C. COOK UNIT 2 CYCIE 15 Revision 2 D. C. COOK UNIT 2 CYCLE 15 Revision 2 FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT

  • AT 1K, - K2 0

I+

+f Li1+T2~S 1(T-V) + K3 (P-P') (Al)]

Where: AT = Measured RCS AT, 0 F AT, = Indicated AT at RATED THERMAL POWER, 0 F T = Average temperature, IF T' = Nominal Tavg at RATED THERMAL POWER, (< 576.00 F)

P = Pressurizer Pressure, psig

= Nominal RCS operating pressure (2235 psig) 1 + TiS

= The function generated by the lead-lag controller for Ta.g dynamic 1+ T2S compensation IC T2 Time constants utilized in the lead-lag controller for Tg TI > 28 secs. T2 < 4 secs.

S = Laplace transform operator, sec' K, < 1.19*

K2 > 0.01331/ 0F K3 > 0.00058/psig f, (AI) = 3.5 {33 + (qt - qb)} when q, - qb <-33% RTP 0% of RTP when -33% RTP < q, - qb < 6% RTP

-1.0 {(qt - 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 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 10 of 14

D. C. COOK UNIT 2 CYCLE 15 Revision 2 FIGURE 5 (Page 2 of 2)

Overpower AT Trip Setpoint Overpower AT

  • AT0 1K4 - K5 [I + T - K6 (T - T") -f2 (AI)]

Where: AT = Measured RCS AT, OF AT, = Indicated AT at RATED THERMAL POWER, 0 F T = Average temperature, OF T" = Nominal T., at RATED THERMAL POWER, (< 576.0 0F)

K4 < 1.16

  • Ks > 0.02/ 0F for increasing average temperature; Ks = 0 for decreasing average temperature K6 > 0.00 I97/ 0 F for T greater than T"; K6=0 for T less than or equal to T" l The function generated by the rate lag controller for T,,

8 dynamic compensation T3 Time constant utilized in the rate lag controller for Tg; r3 > 10 secs.

S = Laplace transform operator, sec-'

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 II ofl4

D. C. COOK UNIT 2 CYCLE 15 Revision 2 D. C. COOK UNIT 2 CYCLE 15 Revision 2 FIGURE 6 Reactor Core Safety Limits 660 650 _ ~UNoACEP TIAOBLE

~24001P__ ==

640

- - 2250 F\E _ __

630

<_P MA\ \

620 (L, === ~20001F =

Cu 610 W

600 C.) _== 1775 PSIA--=*O' 590

= = = ~~ACCEPTAELE = =-

O1PFRP TION_

580 570 560 550 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 Power Tavg (psia) (frac) ('F) (frac) ( F) (frac) (0 F) (frac) ('F) 1775 0.00 615.4 0.98 583.8 1.02 580.9 1.2 558.1 2000 0.00 631.8 0.86 605.8 0.96 597.5 1.2 568.5 2100 0.00 639.1 0.82 614.0 0.96 601.6 1.2 573.1 2250 0.00 649.2 0.72 628.6 0.98 605.2 1.2 580.4 2400 0.00 659.0 0.62 642.0 1.1 599.0 1.2 588.1 UNIT 2 Reactor Core Safety Limits Page 12 of 14

D. C. COOK UNIT 2 CYCLE 15 Revision 2 D. C. COOK UNIT 2 CYCLE 15 Revision 2 FIGURE 7 Unit 2 Cycle 15 Predicted HFP ARO 300 PPM MTC Versus Burnup

-2.28E-04 D o _ l - - - - -

X -2.30E-04 k -2.32E l \ \

E -2.34E-04

-' -2.38E-04I

-2.36E-04 a) -2.46E-04 -__ __ __ __

-2.48E-04

-2.42E 04 lrb 1-01

&.-2.48E-04 14000 15000 16000 17000 18000 19000 Cycle Burnup (MWD/MTU)

Burnup (MWDIMTU) MTC (AknkTF) 14000 -2.2855E-4 15916 -2.361 5E-4 16916 -2.3984E-4 17916 -2.4325E-4 19000 -2.4679E-4 Page 13 of 14

- Y D. C. COOK UNIT 2 CYCLE 15 Revision 2 TABLE 1 D. C. Cook Unit 2 Cycle 15 W(Z) Function Node Height Bumup (NIWD/MTU)

PT (Ft.) 150 1000 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 20650 I 0.0000 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 0.2000 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 0.4000 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 0.6000 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 5 0.8000 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 1.0000 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 1.2000 1.1012 1.1007 1.1005 1.1015 1.1046 1.1097 1.1159 1.1221 1.1281 1.1342 1.1405 1.1466 1.1486 8 1.4000 1.1013 1.1009 1.1008 1.1018 1.1047 1.1095 1.1153 1.1210 1.1266 1.1322 1.1379 1.1435 1.1454 9 1.6000 1.1012 1.1008 1.1008 1.1018 1.1045 1.1090 1.1143 1.1195 1.1246 1.1297 1.1348 1.1400 1.1417 10 1.8000 1.1008 1.1005 1.1005 1.1014 1.1039 1.1080 1.1128 1.1175 1.1220 1.1265 1.1311 1.1356 1.1371 31 2.0000 3.1003 1.0999 1.0999 1.1008 1.1030 1.1066 1.1108 1.1149 1.1188 1.1226 1.1265 1.1304 1.1317 12 2.2000 1.0991 1.0990 1.0990 1.0998 1.1017 1.1048 1.1084 1.1118 1.1151 1.1182 1.1213 1.1246 1.1256 13 2.4000 1.0978 1.0977 1.0978 1.0985 1.1001 1.1027 1.1056 1.1083 1.1108 1.1132 1.1155 1.1180 1.1188 14 2.6000 1.0963 1.0962 1.0963 1.0969 1.0982 1.1002 1.1024 1.1043 1.1060 1.1076 1.1091 1.1107 1.1113 15 2.8000 1.0945 1.0945 1.0946 1.0950 1.0959 1.0972 1.0987 1.0999 1.1008 1.1016 1.1023 1.1031 1.1034 16 3.0000 1.0923 1.0924 1.0924 1.0928 1.0934 1.0942 1.0950 1.0955 1.0956 1.0955 1.0952 1.0953 1.0953 17 3.2000 1.0901 1.0902 1.0903 1.0905 1.0908 1.0911 1.0913 1.0911 1.0905 1.0897 1.0886 1.0880 1.0878 18 3.4000 1.0886 1.0887 1.0888 1.0888 1.0886 1.0881 1.0876 1.0872 1.0868 1.0865 1.0862 1.0858 1.0857 19 3.6000 1.0880 1.0880 1.0880 1.0879 1.0873 1.0863 1.0856 1.0861 1.0876 1.0900 1.0928 1.0946 1.0952 20 3.8000 1.0873 1.0870 1.0868 1.0863 1.0857 1.0851 1.0852 1.0869 3.0902 1.0949 1.1003 1.1041 1.1054 21 4.0000 1.0864 1.0859 1.0854 1.0848 1.0845 1.0845 1.0856 1.0886 1.0933 1.0996 1.1069 1.1122 1.1139 22 4.2000 1.0853 1.0848 1.0844 1.0840 1.0844 1.0854 1.0877 1.0918 1.0976 1.1049 1.1132 1.1196 1.1216 23 4.4000 1.0843 1.0838 1.0836 1.0838 1.0849 1.0870 1.0903 1.0954 1.1020 1.1100 1.1189 1.1261 1.1284 24 4.6000 1.0839 1.0834 1.0831 1.0835 1.0851 1.0882 1.0927 1.0987 1.1060 1.1147 1.1241 1.1319 1.1345 25 4.8000 1.0839 1.0832 1.0827 1.0830 1.0852 1.0893 1.0949 1.1017 1.1097 1.1188 1.1286 1.1370 1.1397 26 5.0000 1.0837 1.0828 1.0821 1.0825 1.0851 1.0901 1.0967 1.1044 1.1128 1.1222 1.1323 1.1412 1.1440 27 5.2000 1.0833 1.0822 1.0813 1.0816 1.0846 1.0905 1.0982 1.1065 1.1154 1.1250 1.1351 1.1443 1.1473 28 5.4000 1.0827 1.0813 1.0803 1.0805 1.0839 1.0907 1.0992 1.1081 1.1173 1.1269 1.1370 1.1464 1.1495 29 5.6000 1.0817 1.0803 1.0793 1.0796 1.0833 1.0906 1.0997 1.1090 1.1183 1.1279 1.1378 1.1474 1.1505 30 5.8000 1.0805 1.0790 1.0780 1.0783 1.0823 1.0900 1.0996 1.1092 1.1185 1.1279 1.1376 1.1471 1.1502 31 6.0000 1.0791 1.0776 1.0765 1.0768 1.0809 1.0890 1.0990 1.1086 1.1178 1.1269 1.1363 1.1456 1.1487 32 6.2000 1.0777 1.0760 1.0748 1.0749 1.0791 1.0874 1.0976 1.1072 1.1162 1.1249 1.1338 1.1429 1.1458 33 6.4000 1.0758 1.0740 1.0727 1.0728 1.0770 1.0853 1.0955 1.1049 1.1136 1.1218 1.1302 1.1388 1.1416 34 6.6000 1.0734 1.0720 1.0709 1.0713 1.0753 1.0832 1.0927 1.1016 1.1097 1.1176 1.1255 1.1336 1.1363 35 6.8000 1.0704 1.0691 1.0682 1.0686 1.0724 1.0798 1.0886 1.0968 1.1043 1.1115 1.1187 1.1262 1.1287 36 7.0000 1.0677 1.0672 1.0671 1.0685 1.0723 1.0787 1.0861 1.0933 1.1002 1.1070 1.1138 1.1208 1.1230 37 7.2000 1.0678 1.0686 1.0698 1.0727 1.0763 1.0808 1.0860 1.0919 1.0983 1.1053 1.1127 1.1194 1.1216 38 7.4000 1.0715 1.0721 1.0731 1.0757 1.0793 1.0840 1.0892 1.0945 1.0999 1.1054 1.1131 1.1166 1.1184 39 7.6000 1.0749 1.0753 1.0761 1.0784 1.0819 1.0866 1.0918 1.0966 1.1012 1.1056 1.1100 1.1146 1.1161 40 7.8000 1.0777 1.0780 1.0787 1.0808 1.0841 1.0888 1.0937 1.0981 1.1019 1.1053 1.1085 1.1122 1.1134 41 8.0000 1.0803 1.0804 1.0809 1.0827 1.0858 1.0904 1.0953 1.0992 1.1021 1.1043 1.1061 1.1088 1.1097 42 8.2000 1.0824 1.0824 1.0826 1.0841 1.0871 1.0916 1.0963 1.0997 1.1017 1.1027 1.1032 1.1049 1.1055 43 8.4000 1.0841 1.0839 1.0839 1.0850 1.0877 1.0922 1.0968 1.0996 1.1007 1.1005 1.0997 1.1004 1.1007 44 8.6000 1.0852 1.0848 1.0847 1.0854 1.0879 1.0923 1.0967 1.0989 1.0990 1.0973 1.0949 1.0944 1.0943 45 8.8000 1.0861 1.0855 1.0852 1.0855 1.0877 1.0918 1.0959 1.0981 1.0986 1.0977 1.0960 1.0961 1.0961 46 9.0000 1.0866 1.0861 1.0858 1.0862 1.0882 1.0919 1.0959 1.0987 1.1004 1.1011 1.1015 1.1029 1.1033 47 9.2000 1.0878 1.0878 1.0881 1.0893 1.0916 1.0951 1.0987 3.1015 1.1034 1.1047 1.1056 1.1074 1.1079 48 9.4000 1.0911 1.0915 1.0920 1.0936 1.0963 1.1000 1.1037 1.1064 1.1081 1.1090 1.1096 1.1110 1.1115 49 9.6000 1.0954 1.0957 1.0963 1.0980 1.1008 1.1046 1.1083 1.1110 1.1126 1.1134 1.1137 1.1151 1.1155 50 9.8000 1.0996 1.0999 1.1005 1.1022 1.1049 1.1087 1.1125 1.1151 1.1166 1.1172 1.1173 1.1185 1.1189 51 10.0000 1.1035 1.1038 1.1044 1.1061 1.1088 1.1126 1.1163 1.1189 1.1202 1.1207 1.1207 1.1218 1.1221 52 10.2000 1.1071 1.1075 1.1081 1.1097 1.1124 1.1160 1.1196 1.1221 1.1236 1.1242 1.1244 1.1256 1.1260 53 10.4000 1.1104 1.1108 1.1113 1.1130 1.1155 1.1189 1.1223 1.1248 1.1263 1.1270 1.1274 1.1287 1.1291 54 10.6000 1.1132 1.1134 1.1139 1.1154 1.1179 1.1215 1.1250 1.1275 1.1289 1.1295 1.1297 1.1309 1.1313 55 10.8000 1.1154 1.1156 1.1160 1.1175 1.1200 1.1235 1.1271 1.1295 1.1309 1.1314 1.1315 1.1326 1.1329 56 11.0000 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 11.2000 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 11.4000 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 11.6000 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 60 11.8000 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 12.0000 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.

Page 14 of 14

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