AEP-NRC-2023-29, Core Operating Limits Report

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Core Operating Limits Report
ML23170A017
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 06/19/2023
From: Scarpello M
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
AEP-NRC-2023-29
Download: ML23170A017 (1)
v • d • e


Text

LANA IGAN WER An AEP Company B O U N D L E S S E N E R G Y Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 indianamichiganpower.com June 19, 2023 AEP-NRC-2023-29 10 CFR 50.4 Docket No.:

50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 CORE OPERATING LIMITS REPORT Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 2, is submitting the Core Operating Limits Report (COLR) for Unit 2 Cycle 27 in accordance with Technical Specification 5.6.5. Revision 1 of the Unit 2 Cycle 27 COLR is provided as an enclosure to this letter.

There are no new or revised commitments in this letter. Should you have any questions, please contact me at (269) 466-2649.

i7.

Michael K. Scarpello Regulatory Affairs Director JMT/sjh

Enclosure:

Donald C. Cook Nuclear Plant Unit 2 Cycle 27 Core Operating Limits Report, Revision 1 c:

EGLE -- RMD/RPS J. B. Giessner-NRC Region Ill NRC Resident Inspector N. Quilco -- MPSC R. M. Sistevaris -AEP Ft. Wayne, w/o enclosures S. P. Wall -- NRC Washington, DC A. J. Williamson - AEP Ft. Wayne, w/o enclosures

ENCLOSURE TO AEP-NRC-2023-29 Donald C. Cook Nuclear Plant Unit 2 Cycle 27 Core Operating Limits Report Revision 1

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 Donald C. Cook Nuclear Plant Unit 2 Cycle 27 Core Operating Limits Report Page 1 of 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 27 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-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995 f.

WCAP-8745-P-A, Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions, September 1986 g.

WCAP-13749-P-A, Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement, March 1997 h.

WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, Optimized ZIRLOTM, July 2006 The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core 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 (FN,111) 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 19

DONALD C. COOK UNIT 2 CYCLE 27 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 (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% Adak for Tavg > 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 (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/°F.

This limit is based on a Tavg 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 3 of 19

DONALD C. COOK UNIT 2 CYCLE 27 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 Tan 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/°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/°F at a HFP vessel Tan 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

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

Page 4 of 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision I 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

CF0 Pl; (Z) _.=

  • K(Z)

P F.Q. (Z) _. 2

  • CF0
  • K(Z)

CF0 fow (Z) =

  • K(Z)

P Pov (Z) 2

  • CF0
  • K(Z) for P > 0.5 for P 0.5 for P > 0.5 for P 0.5 Where:

P = 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. F(Z) = 4 (z) x W(Z) x Fp The W(z) values are generated assuming that they will be used for a full power surveillance.

When a part power surveillance is performed, the W(z) values should be multiplied by the factor 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 27, 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, Fe = 1.00.

Page 5 of 19 THERMAL POWER

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 Cycle Burnup (MWD/MTU)

FP Penalty Multiplier 0

1.080 150 1.080 359 1.083 568 1.083 777 1.080 986 1.075 1195 1.067 1404 1.058 1613 1.049 1822 1.041 2031 1.034 2240 1.029 2449 1.026 2658 1.023 2867 1.022 3076 1.020 The burnup range only covers where Fp exceeds 1.02. Linear interpolation is adequate for intermediate cycle burnups.

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

Where:

P = RATED THERMAL POWER a.

CFAH= 1.61 b.

PFAH= 0.3

c. FNAH 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.

F.

CFAH* (1 + PFAH*(1-P))

THERMAL POWER Page 6 of 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 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 Tan 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 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 577.8°F for Tavg, 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 19

1.0 0.5 0.0 MTC (x 10-4 delta-k/k/°F)

-0.5

-1.0 DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS UNACCEPTABLE OPERATION

\\

ACCEPTABLE OPERATION 0

10 20 30 40 50 60 70 80 90 100 Percent Rated Thermal Power Page 8 of 19

250 225 200 ROD GROUP POSITION (Steps Withdrawn) 175 150 125 100 75 50 25 o

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (52.9%, 228) 100 Step Overlap BANK C (100%, 189)

_ (0%, 128) 1 BANK D (0%, 0) 0 10 20 30 40 50 60 70 80 90 10 POWER (% of Rated Thermal Power)

Page 9 of 19 0

(-11,90)

(+11,90)

UNACCEPTABLE OPERATION UNACCEPTABLE OPORATION 1

ACCEPTABLE OPERATION

(-31,50)

(+31,50) 50

-40

-30

-20

-10 0

10 20 30 40 5

f rE;\\

0 e-X 80 50 40 30 20 10 100 90

% of Minimum RTP OR DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP)

FLUX DIFFERENCE (DELTA-I)

Page 10 of 19

(0.0, 1.0)

(8.425, 1.0)

( 12.0, 0.954) 1' 0

2 4

6 8

10 12 CORE HEIGHT (FT) 0.8 DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 1.0 0.4 0.2 0.0 Page 11 of 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision I FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint 1 + riS Overtemperature AT 5 AT. [K1 - K2

[ + 2 (T-Ti) + K3 (1)-13)

(AM 1

rS Where:

AT

= Measured RCS AT, °F AT.

=

Indicated AT at RATED THERMAL POWER, °F T

=

Average temperature, °F Nominal Tan at RATED THERMAL POWER, (< 576.0°F)

P

=

Pressurizer Pressure, psig Nominal RCS operating pressure (2235 psig )

[1-FTS1 The function generated by the lead-lag controller for Tan dynamic compensation 1+2-2S Time constants utilized in the lead-lag controller for Tan 28 secs. T2 < 4 secs.

Laplace transform operator, sec-1 1.19

  • K2

> 0.01331/°F K3

> 0.00058/psig fi (AI)

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

0% of RTP

+1.0 {(qt - qb) 6%}

when qt - qb S.. -33% RTP when -33% RTP < qt - qb < 6% RTP when qt - qb > 6% RTP where qt and qb are percent RATED THERMAL POWER in the upper and lower halves of the core respectively, and qt

+ qb is total THERMAL POWER in percent RATED THERMAL POWER.

  • This is a Safety Analysis value. Refer to Technical Requirements Manual for nominal value of this coefficient used in programming the trip setpoint.

Page 12 of 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 FIGURE 5 (Page 2 of 2)

Overpower AT Trip Setpoint r3S 1

,,..-,,,,,,, _ f (al T K6 ( 1 1 1

'2 Overpower AT 5 AT. [K4 - K5

[

1

+ r,s, Where:

AT

=

Measured RCS AT, °F AT.

=

Indicated AT at RATED THERMAL POWER, °F T

=

Average temperature, °F T"

=

Nominal Tan at RATED THERMAL POWER, (< 576.0 °F)

K4 1. 1 6

  • K5 0.02/°F for increasing average temperature; K5 = 0 for decreasing average temperature K6 0.00197/°F for T greater than T" ; K6=0 for T less than or equal to T" r3S

=

The function generated by the rate lag controller for Tan dynamic compensation 1 + r3S T3

=

Time constant utilized in the rate lag controller for Tan; T3 > 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 13 of 19

RCS T-avg (°F) 660 650 640 630 620 610 600 590 580 570 560 550 2000 PSIA 2400 PSIA UNACCIEPTABLE OPERATION 2250 P 5IA 2100 P SIA 1775 PSIA ACCEP ABLE oPirrION DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 FIGURE 6 Reactor Core Safety Limits o

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)

(' 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 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 FIGURE 7 Unit 2 Cycle 27 Predicted HFP ARO 300 PPM MTC Versus Burnup

-2.46E-04

-2.48E-04

-2 50E-04 ir:

k -252E-04 a

E -2_54E-04

.2 E

O-256E-04 o

0 e a -2.58E-04 e

E -2.60E-04

  • i-Am -2.62E-04 a;
  • cs o -2.64E-04 2

-2.66E-04 17,000 18,000 19,000 20,000 21,000 Cycle Burnup (MWD/MTU)

Burnup (MWD/MTU)

MTC (pcm/°F)

MTC (AkIld°F) 17000

-24.845

-2.4845E-04 18000

-25.212

-2.5212E-04 19000

-25.567

-2.5567E-04 20000

-25.963

-2.5963E-04 21000

-26.333

-2.6333E-04 Page 15 of 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 Table 1 D. C. Cook Unit 2 Cycle 27 W(Z) Function Node Height Burnup (MWD/MTU)

(ft) 150 1000 2000 4000 6000 8000 9000 1

0.0 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 3

0.4 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 5

0.8 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 7

1.2 1.1133 1.1123 1.1113 1.1102 1.1099 1.1106 1.1114 8

1.4 1.1123 1.1105 1.1088 1.1068 1.1069 1.1089 1.1105 9

1.6 1.1110 1.1085 1.1061 1.1033 1.1038 1.1070 1.1092 10 1.8 1.1093 1.1066 1.1040 1.1011 1.1017 1.1054 1.1078 11 2.0 1.1073 1.1049 1.1026 1.1002 1.1009 1.1043 1.1065 12 2.2 1.1049 1.1031 1.1015 1.0997 1.1004 1.1031 1.1049 13 2.4 1.1022 1.1011 1.1000 1.0989 1.0995 1.1016 1.1029 14 2.6 1.0993 1.0987 1.0982 1.0978 1.0984 1.0998 1.1006 15 2.8 1.0961 1.0961 1.0962 1.0964 1.0969 1.0976 1.0980 16 3.0 1.0926 1.0932 1.0939 1.0948 1.0952 1.0951 1.0950 17 3.2 1.0890 1.0902 1.0914 1.0930 1.0932 1.0924 1.0918 18 3.4 1.0861 1.0878 1.0894 1.0914 1.0914 1.0898 1.0888 19 3.6 1.0846 1.0867 1.0887 1.0911 1.0907 1.0882 1.0868 20 3.8 1.0847 1.0868 1.0889 1.0912 1.0903 1.0871 1.0855 21 4.0 1.0855 1.0873 1.0890 1.0908 1.0897 1.0866 1.0850 22 4.2 1.0861 1.0876 1.0889 1.0904 1.0894 1.0867 1.0855 23 4.4 1.0867 1.0878 1.0889 1.0901 1.0893 1.0873 1.0865 24 4.6 1.0871 1.0878 1.0885 1.0895 1.0892 1.0883 1.0881 25 4.8 1.0873 1.0876 1.0879 1.0886 1.0888 1.0891 1.0896 26 5.0 1.0873 1.0871 1.0871 1.0875 1.0882 1.0896 1.0907 27 5.2 1.0871 1.0864 1.0860 1.0861 1.0873 1.0898 1.0916 28 5.4 1.0866 1.0855 1.0847 1.0844 1.0861 1.0897 1.0921 29 5.6 1.0862 1.0846 1.0833 1.0825 1.0846 1.0892 1.0921 30 5.8 1.0856 1.0835 1.0816 1.0804 1.0827 1.0882 1.0916 Top and bottom 10% of core excluded.

Page 16 of 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 Table 1 (Continued)

D. C. Cook Unit 2 Cycle 27 W(Z) Function Node Height Burnup (MWD/MTU)

(ft) 150 1000 2000 4000 6000 8000 9000 31 6.0 1.0845 1.0819 1.0797 1.0779 1.0805 1.0868 1.0907 32 6.2 1.0831 1.0800 1.0774 1.0752 1.0779 1.0849 1.0891 33 6.4 1.0812 1.0778 1.0747 1.0721 1.0750 1.0825 1.0870 34 6.6 1.0788 1.0752 1.0720 1.0692 1.0721 1.0797 1.0843 35 6.8 1.0759 1.0722 1.0689 1.0660 1.0689 1.0765 1.0811 36 7.0 1.0725 1.0690 1.0659 1.0630 1.0656 1.0728 1.0771 37 7.2 1.0714 1.0675 1.0639 1.0604 1.0629 1.0702 1.0747 38 7.4 1.0754 1.0699 1.0647 1.0594 1.0622 1.0716 1.0773 39 7.6 1.0792 1.0736 1.0685 1.0632 1.0660 1.0753 1.0809 40 7.8 1.0823 1.0774 1.0729 1.0682 1.0708 1.0792 1.0842 41 8.0 1.0854 1.0809 1.0767 1.0724 1.0749 1.0826 1.0872 42 8.2 1.0880 1.0841 1.0804 1.0767 1.0789 1.0858 1.0898 43 8.4 1.0904 1.0870 1.0839 1.0807 1.0826 1.0886 1.0921 44 8.6 1.0924 1.0897 1.0871 1.0844 1.0861 1.0910 1.0939 45 8.8 1.0941 1.0920 1.0900 1.0881 1.0894 1.0932 1.0954 46 9.0 1.0957 1.0943 1.0931 1.0918 1.0927 1.0953 1.0967 47 9.2 1.0974 1.0967 1.0961 1.0954 1.0957 1.0968 1.0974 48 9.4 1.0986 1.0987 1.0987 1.0987 1.0984 1.0981 1.0980 49 9.6 1.1002 1.1005 1.1008 1.1012 1.1013 1.1012 1.1013 50 9.8 1.1037 1.1035 1.1034 1.1035 1.1040 1.1049 1.1054 51 10.0 1.1082 1.1074 1.1066 1.1059 1.1064 1.1079 1.1089 52 10.2 1.1120 1.1105 1.1090 1.1074 1.1080 1.1105 1.1119 53 10.4 1.1156 1.1132 1.1110 1.1085 1.1092 1.1126 1.1145 54 10.6 1.1185 1.1177 1.1169 1.1160 1.1162 1.1173 1.1180 55 10.8 1.1210 1.1186 1.1162 1.1136 1.1141 1.1171 1.1190 56 11.0 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 58 11.4 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 60 11.8 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 Top and bottom 10% of core excluded.

Page 17 of 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 Table 1 (Continued)

D. C. Cook Unit 2 Cycle 27 W(Z) Function Node Height Burnup (MWD/MTU)

(ft) 10000 12000 14000 16000 18000 20000 22000 22871 1

0.0 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 3

0.4 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 5

0.8 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 7

1.2 1.1126 1.1164 1.1216 1.1282 1.1362 1.1456 1.1523 1.1551 8

1.4 1.1123 1.1166 1.1218 1.1278 1.1347 1.1427 1.1488 1.1515 9

1.6 1.1116 1.1164 1.1214 1.1268 1.1326 1.1391 1.1446 1.1470 10 1.8 1.1104 1.1152 1.1199 1.1245 1.1293 1.1346 1.1395 1.1416 11 2.0 1.1087 1.1130 1.1170 1.1210 1.1250 1.1294 1.1335 1.1353 12 2.2 1.1067 1.1101 1.1134 1.1166 1.1199 1.1235 1.1269 1.1283 13 2.4 1.1042 1.1068 1.1093 1.1117 1.1142 1.1169 1.1195 1.1206 14 2.6 1.1015 1.1032 1.1048 1.1064 1.1080 1.1097 1.1114 1.1121 15 2.8 1.0984 1.0992 1.1000 1.1008 1.1016 1.1025 1.1033 1.1037 16 3.0 1.0949 1.0947 1.0946 1.0945 1.0944 1.0942 1.0941 1.0940 17 3.2 1.0912 1.0903 1.0897 1.0893 1.0890 1.0887 1.0882 1.0880 18 3.4 1.0879 1.0868 1.0864 1.0865 1.0871 1.0880 1.0880 1.0880 19 3.6 1.0857 1.0848 1.0855 1.0876 1.0907 1.0948 1.0966 1.0974 20 3.8 1.0842 1.0838 1.0857 1.0895 1.0950 1.1020 1.1055 1.1071 21 4.0 1.0840 1.0842 1.0871 1.0923 1.0994 1.1084 1.1133 1.1154 22 4.2 1.0848 1.0859 1.0898 1.0960 1.1043 1.1145 1.1205 1.1231 23 4.4 1.0863 1.0882 1.0928 1.0998 1.1090 1.1202 1.1270 1.1299 24 4.6 1.0885 1.0913 1.0967 1.1042 1.1137 1.1252 1.1325 1.1357 25 4.8 1.0906 1.0944 1.1004 1.1082 1.1179 1.1294 1.1372 1.1406 26 5.0 1.0923 1.0970 1.1035 1.1117 1.1215 1.1329 1.1410 1.1446 27 5.2 1.0937 1.0993 1.1062 1.1146 1.1243 1.1355 1.1438 1.1475 28 5.4 1.0948 1.1010 1.1084 1.1168 1.1263 1.1371 1.1456 1.1493 29 5.6 1.0953 1.1022 1.1099 1.1182 1.1274 1.1377 1.1462 1.1498 30 5.8 1.0953 1.1028 1.1106 1.1187 1.1275 1.1371 1.1455 1.1492 Top and bottom 10% of core excluded.

Page 18 of 19

DONALD C. COOK UNIT 2 CYCLE 27 Revision 1 Table 1 (Continued)

D. C. Cook Unit 2 Cycle 27 W(Z) Function Node Height Burnup (MWD/MTU)

(ft) 10000 12000 14000 16000 18000 20000 22000 22871 31 6.0 1.0947 1.1026 1.1104 1.1183 1.1266 1.1355 1.1436 1.1472 32 6.2 1.0935 1.1017 1.1094 1.1170 1.1246 1.1327 1.1405 1.1440 33 6.4 1.0916 1.1000 1.1075 1.1147 1.1216 1.1289 1.1363 1.1396 34 6.6 1.0890 1.0973 1.1045 1.1112 1.1176 1.1241 1.1311 1.1341 35 6.8 1.0856 1.0936 1.1004 1.1064 1.1119 1.1173 1.1237 1.1264 36 7.0 1.0814 1.0890 1.0955 1.1014 1.1069 1.1124 1.1186 1.1213 37 7.2 1.0791 1.0870 1.0937 1.0997 1.1054 1.1110 1.1174 1.1202 38 7.4 1.0827 1.0916 1.0982 1.1032 1.1071 1.1103 1.1158 1.1182 39 7.6 1.0862 1.0947 1.1007 1.1049 1.1079 1.1101 1.1149 1.1170 40 7.8 1.0890 1.0966 1.1018 1.1054 1.1079 1.1095 1.1136 1.1154 41 8.0 1.0916 1.0983 1.1028 1.1057 1.1074 1.1082 1.1115 1.1130 42 8.2 1.0936 1.0994 1.1031 1.1052 1.1062 1.1064 1.1089 1.1100 43 8.4 1.0953 1.1001 1.1029 1.1043 1.1046 1.1040 1.1058 1.1065 44 8.6 1.0965 1.1002 1.1022 1.1028 1.1024 1.1011 1.1021 1.1025 45 8.8 1.0973 1.0999 1.1010 1.1009 1.1000 1.0982 1.0984 1.0984 46 9.0 1.0980 1.0997 1.1005 1.1004 1.0998 1.0986 1.0988 1.0988 47 9.2 1.0981 1.0993 1.1003 1.1013 1.1022 1.1031 1.1041 1.1045 48 9.4 1.0981 1.0987 1.0999 1.1016 1.1038 1.1065 1.1082 1.1089 49 9.6 1.1014 1.1022 1.1036 1.1055 1.1078 1.1106 1.1125 1.1133 50 9.8 1.1061 1.1074 1.1089 1.1106 1.1124 1.1145 1.1162 1.1169 51 10.0 1.1098 1.1116 1.1132 1.1147 1.1162 1.1178 1.1194 1.1201 52 10.2 1.1134 1.1157 1.1173 1.1186 1.1195 1.1203 1.1216 1.1222 53 10.4 1.1164 1.1192 1.1208 1.1217 1.1219 1.1217 1.1228 1.1233 54 10.6 1.1188 1.1205 1.1222 1.1241 1.1261 1.1283 1.1303 1.1311 55 10.8 1.1207 1.1233 1.1249 1.1257 1.1259 1.1258 1.1268 1.1273 56 11.0 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 58 11.4 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 60 11.8 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 Top and bottom 10% of core excluded.

Page 19 of 19

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