AEP-NRC-2024-69, Core Operating Limits Report

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Core Operating Limits Report
ML24254A283
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 09/09/2024
From: Scarpello M
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
AEP-NRC-2024-69
Download: ML24254A283 (1)
v • d • e


Text

Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place POWER " Bridgman, Ml 49106 indianamichiganpower.com An AEP Company

BOUNDLESS ENERGY-

September 9, 2024 AEP-NRC-2024-69 10 CFR 50.4

Docket Nos.: 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 28 in accordance with Technical Specification 5.6.5. Revision O of the Unit 2 Cycle 28 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.

Sincerely, tlL

Michael K. Scarpello Regulatory Affairs Director

OAF/sjh

Enclosures : Donald C. Cook Nuclear Plant Unit 2 Cycle 28 Core Operating Limits Report

c: EGLE - RMD/RPS J. B. Giessner - NRC Region Ill NRC Resident Inspector N. Quilico - MPSC R. M. Sistevaris -AEP Ft. Wayne S. P. Wall, NRC Washington D.C.

A. J. Williamson - AEP Ft. Wayne Enclosure to AEP-NRC-2024-69

Donald C. Cook Nuclear Plant Unit 2 Cycle 28 Core Operating Limits Report DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

Donald C. Cook Nuclear Plant Unit 2 Cycle 28 Core Operating Limits Report

Page l of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

1.0 CORE OPERATING LIMITS REPORT

This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 28 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 197 4
c. WCAP-10216-P-A, Rev. IA, 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 O (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 I). T and Thermal Overtemperature I). T Trip Functions, September l 986
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 ZIRLO', July 2006

The Technical Specifications affected by this report are listed below:

2.1.l Reactor Core SLs [Safety Limits]

3.1.1 SHUTDOWN MARGIN (SOM)

3. 1.3 Moderator Temperature Coefficient (MTC) 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2. l Heat Flux Hot Channel Factor (F Q(Z))

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN,m) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reactor Trip System (RTS) Instrumentation 3.4. l 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 28 Revision 0

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. l Reactor Core SLs (Specification 2.1. l)

In Modes l and 2, the combination of thermal power, pressurizer pressure, and the highest loop average temperature (T avg) shall not exceed the limits as shown in Figure 6 for 4 loop operation.

2.2 REACTIVITY CONTROL

2.2.1 SHUTDOWN MARGIN (SOM) (Specification 3.1.1)

Shutdown margin shall be greater than or equal to 1.3% ~k/k for T.vg > 200°F Shutdown margin shall be greater than or equal to 1.0% ~k/k for T.vg ~ 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 I.

The EOL/ARO/RTP-MTC shall be less negative or equal to -4.I0E-4,1k/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 R TP stands for Rated Thermal Power HFP stands for Hot Full Thermal Power

Page 3 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

b. The MTC Surveillance limit is:

The 300 ppm/ARO/RTP-MTC should be less negative or equal to -3.20E-4 Lik/k/°F 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 Lik/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 Lik/k/°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 l 00 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 bumup
2:0.0 MWD/MTU [Megawatt Days/Metric Ton Uranium].

Page 4 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

2.3.2 Heat Flux Hot Channel Factor (Fo(Z)) (Specification 3.2. 1)

FJ' (Z) ~ _Q

  • CF K(Z) for P>0.5 p

FJ/ (Z) ~ 2

  • CFQ
  • K(Z) for P ~ 0.5

Ff (Z) ~ _S!__

  • CF K(Z) for P > 0.5 p

F t (Z) ~ 2

  • CFIJ
  • K(Z) for P ~ 0.5

Where: THERMAL POWER p = RA TED THERMAL POWER

a. CFo = 2.335
b. K(Z) is provided in Figure 4
c. F8(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 l for +/-5% AFD target band.

e. F~ (Z) = F8 (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 Fo(z) limit at part power conditions.

f. For Cycle 28, FP= 1.02 for all bumups associated with Note 2a of SR 3.2.1.2, except as shown in the table below. When no penalty is required, FP = 1.00.

Page 5 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

Cycle Fp Penalty Burnup (MWD/MTU) Multiplier 0 1.0867 150 1.0867 359 1.0839 568 1.0798 777 1.0744 986 1.0676 1195 1.0594 1404 1.0498 1613 1.0397 1822 1.0300 2031 1.0215 2240 1.0200 20846 1.0200 21055 1.0236 22698 1.0236

The bumup range only covers where Fp exceeds 1.02. Linear interpolation is adequate for intermediate cycle bumups.

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

FN &~CF&* (1 + PF m*(l-P))

THERMAL POWER Where: p = RA TED THERMAL POWER

a. CF&= 1.61
b. PF Lill= 0.3
c. FN & 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 LiT and Overpower LiT setpoints are as shown in Figure 5.

Page 6 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

2.5 REACTOR COOLANT SYSTEM

2.5. l RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (Specification 3.4. l)

a. Pressurizer Pressure shall be 2 2172.4 psig +
b. RCS Tavg shall bes 580. l °F +
c. RCS Total Flow Rate shall be 2 366,400 gpm

2.6 REFUELING OPERATIONS

2.6.1 Boron Concentration (Specification 3.9. l)

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 T avg, and 2200 psig for Pressurizer Pressure.

++ This concentration bounds the condition of Keff :'.S 0.95, which includes a 1 % ~k/k conservative allowance for uncertainties. The boron concentration of 2400 ppm includes a 50 ppm conservative allowance for uncertainties.

Page 7 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS

1.0

I UNACCEPTABLE OPERATION I

0.5

LL

-0 "'

~

~ I '

+-' co Q) 0.0 '--

"'O I ACCEPT ABLE OPERATION I

"'l" "

0 T"""

(.)

r- -0.5

~

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

Page 8 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER

250

225 I (52.9%, 228) 100 Step Overlap I

/

200 I BANKC 1 ~

I 1-'

(100%, 189)

/ V I /

'2 175,

!: / /

e:!

"C

.c

- /

~ 150

(/)

a.

Q)

~ - /' /

z 125 H (0%, 128) I /

0 I V i'.=

u5 I BANKY 0

0.. 100 0..

0 0:::

(9 /'

0 75 0

0:::

50 / /

/ V

25 V

/I (o3/4,o) / I

0 0 10 20 30 40 50 60 70 80 90 100

POWER (% of Rated Thermal Power)

Page 9 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP)

100 I c-11,90) I I c+11,9o) I

('Q\\ 90 0 UNACCEPTABLE '1 / UNACCEPTABLE l

- LJ OPERATION OPERATION \\ I

>< 80 N -N J I \\..

~ - 70

)( ~u.° I \\ ACCEPTABLE I LL 60 I OPERATION I I \\

(.)

0::: I 0 50.. J..

Q. I c-31,50) I I (+31.50)

I-

~ 40 E

J 30
  • -E C
E 20

-0

~

0 10

O -50 -40 -30 -20 -10 0 10 20 30 40 60

FLUX DIFFERENCE (DEL TA-I)

)

Page 10 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT

1.2

1.0 (0.0, 1.0) (8.425, 1.0)

(12.0, 0.954)

0.8

0 w

N

i

<{

~ 0.6 0

z

0.4

0.2

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

Page l l of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

FIGURE 5 (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint

Overtemperature AT :s;; AT [K 1 - ~ [ l+r,S] -- (T-T') + KJ (P-P')-f1 (AI)]

0 1 +,2S

Where : AT Measured RCS AT, 0 f ATo Indicated AT at RATED THERMAL POWER, 0 f T Average temperature, 0 f T' p Nominal T avg at RA TED THERMAL POWER, (S 576.0°f)

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

The function generated by the lead-lag controller for Tavg dynamic compensation

Time constants utilized in the lead-lag controller for Tavg

't1 2'.: 28 secs. 't2 S 4 secs.

s Laplace transform operator, sec-1

S l.19*

2'.: 0.0133 l/ 0 f 2'.: 0.00058/psig

= -3.5 {33% + (qt - qb)} when qt - qb S -33% RTP 0%ofRTP when -33% RTP < qt - qb S 6% RTP

+l.0 {(qt-qb)-6%} when qt - qb > 6% RTP

where qt and qb are percent RA TED 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 28 Revision 0

FIGURE 5 (Page 2 of 2)

Overpower AT Trip Setpoint

[ -- T - K (T - T") -f r,S ] (AI)]

1 + r,S 6 2

Where: AT Measured RCS AT, °F

ATo Indicated AT at RATED THERMAL POWER, 0 f

T Average temperature, 0 f

T" Nominal Tavg at RA TED THERMAL POWER,(~ 576.0 °f}

~ ~ 1.16

  • Ks ~ 0.02/0 f for increasing average temperature; Ks = 0 for decreasing average temperature

~ ~ 0.00 l 97 / 0 f for T greater than T" ; ~=0 for T less than or equal to T"

r,S = The function generated by the rate lag controller for T avg dynamic compensation I+ r,S

Time constant utilized in the rate lag controller for Tavg; t 3 ~ IO secs.

s Laplace transform operator, sec*'

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 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

FIGURE 6 Reactor Core Safety Limits 660 r---

650 ---- r---

r---_ --- i---.. UNACCt TABLE OPED TION

r--.. 2400 F !,IA_..........,

640 ----"-

r--- --- r--..

2250P $IA__,,. ---- "'

630 - ~r--.._ ---- -- ~" ----- r--.... "'

~OP $IA_.,. ---- "

LL 620.~

-0 -----

~ 2000 F ~ --- --- ""

-C, r---..._ -.........._ ------- ", ---...... ~

> 610 -- ---- r--.. ""

ca I "'............

I- --.............._... ~ '"'

600........___ " """

0 1775 F,IA_____..

"' ' '"\\." I'\\.

a:: 590 ----- ---- ~:--..... \\. 'Ir\\."\\. " ~ "'

'\\ \\."

ACCEP ABLE --........... I'\\ '\\

580 nDS:D Tlnl\\J "\\. "\\. \\

'\\ "\\.' "\\.

570 "\\. 'I

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) (* 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

UNIT2 Reactor Core Safety Limits Page 14 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

FIGURE 7

Unit 2 Cycle 28 Predicted HFP ARO 300 PPM MTC Versus Burnup

Burnuo (MWD/MTU) MTC (ocm/°F) MTC (Ak/k/°F) 17000 -24.331 -2.4331 E-04 18000 -24.687 -2.4687E-04 19000 -25.069 -2.5069E-04 20000 -25.438 -2.5438E-04 21000 -25.813 -2.5813E-04

Page 15 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

Table 1 Donald C. Cook Unit 2 Cycle 28 W(Z) Function

Node Height Burnup (MWD/MTU)

  1. (ft) 150 1000 2000 4000 6000 8000 9000 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 1.1151 1.1141 1.1131 1.1118 1.1111 1.1111 1.1116 8 1.4 1.1139 1.1121 1.1104 1.1083 1.1080 1.1094 1.1107 9 1.6 1.1124 1.1100 1.1076 1.1049 1.1050 1.1076 1.1096 10 1.8 1.1105 1.1074 1.1045 1.1011 1.1016 1.1055 1.1080 11 2.0 1.1083 1.1053 1.1024 1.0992 1.1000 1.1040 1.1066 12 2.2 1.1057 1.1034 1.1013 1.0990 1.0998 1.1031 1.1052 13 2.4 1.1027 1.1012 1.0997 1.0982 1.0990 1.1017 1.1034 14 2.6 1.0995 1.0986 1.0978 1.0972 1.0980 1.1000 1.1012 15 2.8 1.0961 1.0959 1.0958 1.0959 1.0967 1.0980 1.0987 16 3.0 1.0923 1.0928 1.0934 1.0944 1.0952 1.0957 1.0959 17 3.2 1.0885 1.0897 1.0910 1.0928 1.0935 1.0931 1.0927 18 3.4 1.0855 1.0873 1.0892 1.0915 1.0917 1.0903 1.0893 19 3.6 1.0847 1.0869 1.0890 1.0915 1.0912 1.0887 1.0873 20 3.8 1.0853 1.0874 1.0894 1.0917 1.0909 1.0877 1.0861 21 4.0 1.0864 1.0881 1.0899 1.0916 1.0905 1.0873 1.0858 22 4.2 1.0873 1.0887 1.0900 1.0914 1.0904 1.0878 1.0867 23 4.4 1.0887 1.0895 1.0904 1.0913 1.0905 1.0888 1.0882 24 4.6 1.0898 1.0901 1.0904 1.0909 1.0905 1.0898 1.0898 25 4.8 1.0907 1.0904 1.0902 1.0901 1.0901 1.0905 1.0912 26 5.0 1.0913 1.0905 1.0898 1.0892 1.0895 1.0910 1.0923 27 5.2 1.0917 1.0903 1.0890 1.0879 1.0886 1.0912 1.0931 28 5.4 1.0917 1.0898 1.0880 1.0863 1.0874 1.0910 1.0935 29 5.6 1.0914 1.0889 1.0867 1.0845 1.0859 1.0904 1.0935 30 5.8 1.0907 1.0877 1.0850 1.0824 1.0841 1.0894 1.0930

Top and bottom I 0% of core excluded.

Page 16 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

Table 1 (Continued)

Donald C. Cook Unit 2 Cycle 28

W(Z) Function

Node Height Burnup (MWD/MTU)

  1. (ft) 150 1000 2000 4000 6000 8000 9000 31 6.0 1.0896 1.0861 1.0830 1.0799 1.0818 1.0880 1.0919 32 6.2 1.0880 1.0842 1.0807 1.0772 1.0793 1.0860 1.0903 33 6.4 1.0859 1.0817 1.0779 1.0741 1.0763 1.0835 1.0880 34 6.6 1.0832 1.0788 1.0747 1.0705 1.0728 1.0804 1.0851 35 6.8 1.0799 1.0754 1.0713 1.0670 1.0693 1.0770 1.0818 36 7.0 1.0765 1.0722 1.0683 1.0641 1.0661 1.0730 1.0773 37 7.2 1.0755 1.0707 1.0662 1.0613 1.0629 1.0699 1.0743 38 7.4 1.0791 1.0725 1.0663 1.0594 1.0616 1.0712 1.0770 39 7.6 1.0824 1.0758 1.0696 1.0628 1.0651 1.0748 1.0807 40 7.8 1.0850 1.0792 1.0736 1.0676 1.0698 1.0787 1.0840 41 8.0 1.0875 1.0821 1.0770 1.0715 1.0737 1.0821 1.0870 42 8.2 1.0896 1.0848 1.0803 1.0755 1.0776 1.0852 1. 0897 43 8.4 1.0913 1.0872 1.0832 1.0791 1.0811 1.0880 1.0919 44 8.6 1.0927 1.0892 1.0859 1.0825 1.0843 1.0903 1.0937 45 8.8 1.0935 1.0908 1.0882 1.0857 1.0874 1.0924 1.0952 46 9. 0 1.0942 1.0924 1.0906 1.0890 1.0903 1.0940 1.0960 47 9.2 1.0952 1.0941 1.0931 1.0922 1.0930 1.0953 1.0967 48 9.4 1.0967 1.0960 1.0954 1.0949 1.0957 1.0975 1.0986 49 9.6 1.1010 1.0997 1.0986 1.0975 1.0984 1.1010 1.1025 50 9.8 1.1060 1.1038 1.1017 1.0996 1. 1007 1.1044 1.1065 51 10.0 1.1103 1.1073 1.1046 1.1016 1.1028 1.1073 1.1100 52 10.2 1.1144 1.1104 1.1067 1.1026 1.1040 1.1097 1.1130 53 10.4 1.1180 1.1132 1.1086 1.1034 1.1049 1.1117 1.1156 54 10.6 1. 1211 1.1177 1.1145 1.1108 1. 1117 1.1163 1.1191 55 10.8 1.1237 1.1187 1.1139 1.1083 1.1096 I.I 162 1.1202 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 28 Revision 0

Table 1 (Continued)

Donald C. Cook Unit 2 Cycle 28 W(Z) Function

Node Height Burnup (MWD/MTU)

  1. (ft) 10000 12000 14000 16000 18000 20000 21964 22698 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 1.1125 1.1158 1.1208 1.1274 1.1355 1.1446 1.1509 1.1533 8 1.4 1.1123 1.1162 1.1211 1.1270 1.1340 1.1417 1.1475 1.1497 9 1.6 1.1117 1.1161 1.1208 1.1260 1.1318 1.1381 1.1434 1.1453 IO 1.8 1.1106 1.1155 1.1200 1.1244 1.1289 1.1337 1.1382 1.1399 II 2.0 1.1091 1.1137 1.1177 1.1213 1.1248 1.1285 1.1323 1.1337 12 2.2 1.1073 1.1110 1.1142 1.1171 1.1199 1.1227 1.1258 1.1269 13 2.4 1.1050 1.1079 1.1103 1.1125 1.1145 1.1165 1.1188 1.1196 14 2.6 1.1024 1.1044 1.1060 1.1074 1.1085 1.1097 1.1112 1.1117 15 2.8 1.0994 1.1005 1.1013 1.1019 1.1024 1.1028 1.1034 1.1037 16 3.0 1.0960 1.0962 1.0961 1.0959 1.0954 1.0949 1.0947 1.0946 17 3.2 1.0922 1.0914 1.0907 1.0900 1.0892 1.0882 1.0874 1.0871 18 3.4 1.0884 1.0872 1.0867 1.0867 1.0871 1.0875 1.0873 1.0873 19 3.6 1.0862 1.0853 1.0860 1.0880 1.0911 1.0947 1.0964 1.0970 20 3.8 1.0849 1.0845 1.0865 1.0904 1.0960 1.1024 1.1058 1.1071 21 4.0 1.0848 1.0851 1.0882 1.0935 1.1007 1.1091 1.1139 1.1157 22 4.2 1.0861 1.0873 1.0913 1.0976 1.1060 1.1157 1.1215 1.1237 23 4.4 1.0881 1.0903 1.0951 1.1021 1.1112 1.1216 1.1282 1.1307 24 4.6 1.0903 1.0934 1.0990 1.1066 1.1161 1.1269 1.1341 1.1368 25 4.8 1.0923 1.0964 1.1026 1.1106 1.1205 1.1315 1.1392 1.1420 26 5.0 1.0940 1.0990 1.1057 1.1141 1.1241 1.1352 1.1433 1.1463 27 5.2 1.0954 1.1012 1.1084 1.1170 1.1270 1.1380 1.1464 1.1495 28 5.4 1.0963 1.1029 1.1105 1.1192 1.1291 1.1399 1.1484 1.1516 29 5.6 1.0968 1.1040 1.1119 1.1205 1.1302 1.1406 1.1492 1.1524 30 5.8 1.0967 1.1044 1.1125 1.1210 1.1303 1.1402 1.1488 1.1520

Top and bottom I 0% of core excluded.

Page 18 of 19 DONALD C. COOK UNIT 2 CYCLE 28 Revision 0

Table 1 (Continued)

Donald C. Cook Unit 2 Cycle 28

W(Z) Function

Node Height Burnup (MWD/MTU)

  1. (ft) 10000 12000 14000 16000 18000 20000 21964 22698 31 6.0 1.0960 1.1041 1.1122 1.1205 1.1293 1.1387 1.1471 1.1502 32 6.2 1.0947 1.1031 I.Ill] I.I 190 1.1273 1.1360 1.1441 1.1471 33 6.4 1.0927 1.1012 1.1090 1.1166 1.1242 1.1322 1.1399 1.1428 34 6.6 1.0899 1.0985 1.1061 1.1132 1.1201 1.1273 1.1347 1.1374 35 6.8 1.0865 1.0949 1.1020 1.1084 1.1145 1.1208 1.1275 1.1300 36 7.0 1.0817 1.0895 1.0963 1.1026 1.1087 1.1151 1.1216 1.1241 37 7.2 1.0787 1.0866 1.0935 1.0998 1.1059 1.1123 1.1189 1.1213 38 7.4 1.0827 1.0918 1.0985 1.1035 1.1074 1.1111 1.1167 1.1188 39 7.6 1.0863 1.0951 1.1011 1.1052 1.1080 1.1105 1.1152 1.1170 40 7.8 1.0891 1.0969 1.1022 1.1055 1.1076 1.1093 1.1133 1.1148 41 8.0 1.0917 1.0988 1.1032 1.1057 1.1068 1.1075 1.1106 1.1118 42 8.2 1.0939 1.1000 1.1035 1.1051 1.1054 1.1051 1.1074 1.1082 43 8.4 1.0956 1.1007 1.1033 1.1041 1.1034 1.1022 1.1035 1.1040 44 8.6 1.0968 1.1009 1.1026 1.1024 1.1008 1.0986 1.0990 1.0991 45 8.8 1.0977 1.1009 1.1021 1.1017 1.1000 1.0978 1.0978 1.0978 46 9.0 1.0979 1.1004 1.1015 1.1015 1.1006 1.0993 1.0996 1.0997 47 9.2 1.0979 1.1000 1.1015 1.1026 1.1034 1.1041 1.1054 1.1058 48 9.4 1.0997 1.1016 1.1033 1.1049 1.1065 1.1081 1.1097 1.1103 49 9.6 1.1039 1.1064 1.1083 1.1098 1.1111 1.1124 1.1140 1.1146 50 9.8 1.1086 1.1117 1.1137 1.1150 1.1157 1.1162 1.1177 1.1183 51 10.0 1.1125 1.1162 1.1183 1.1194 1.1196 1.1195 1.1208 1.1214 52 10.2 I.I 161 1.1205 1.1227 1.1233 1.1228 1.1217 1.1228 1.1233 53 10.4 1.1193 1.1242 1.1263 1.1264 1.1250 1.1229 1.1236 1.1238 54 10.6 1.1218 1.1257 1.1282 1.1296 1.1302 1.1306 1.1324 1.1330 55 10.8 1.1238 1.1286 1.1308 1.1310 1.1297 1.1277 1.1285 1.1288 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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