AEP-NRC-2024-23, Core Operating Limits Report

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Core Operating Limits Report
ML24144A103
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 05/23/2024
From: Scarpello M
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
AEP-NRC-2024-23
Download: ML24144A103 (1)
v • d • e


Text

INDIANA MICHIGAN POWIR" An ARP Company BOUNDLESS ENERGY-May 23, 2024 Docket Nos.: 50-315 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 Core Operating Limits Report Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 indianamichiganpower.com AEP-NRC-2024-23 10 CFR 50.4 Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 1, is submitting the Core Operating Limits Report (COLR) for Unit 1 Cycle 32 in accordance with Technical Specification 5.6.5. Revision O of the Unit 1 Cycle 32 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,

~Mrvt-Michael K. Scarpello Regulatory Affairs Director OAF/sjh

Enclosure:

Donald C. Cook Nuclear Plant Unit 1 Cycle 32 Core Operating Limits Report, Revision 0.

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. Way

Enclosure to AEP-NRC-2024-23 Donald C. Cook Nuclear Plant Unit 1 Cycle 32 Core Operating Limits Report, Revision 0

D. C. COOK UNIT 1 CYCLE 32 Revision 0 Donald C. Cook Nuclear Plant Unit 1 Cycle 32 Core Operating Limits Report Revision 0 Page 1 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit I Cycle 32 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.

lA, Relaxation of Constant Axial Offset Control/Fo Surveillance Technical Specification, February 1994

d.

Plant-specific adaptation ofWCAP-16009-P-A, Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), as approved by NRC Safety Evaluation dated October 17, 2008

e.

WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995

f.

WCAP-8745-P-A, Design Bases for the Thermal Overpower.1T and Thermal Overtemperature.1 T 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 ZIRLO',

July 2006.

The Technical Specifications affected by this report are listed below:

2.1. l Reactor Core 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 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN.1H) 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. I Boron Concentration Page 2 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 2.0 OPERA TING 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. I SAFETY LIMITS 2.1.1 Reactor Core Safety Limits (Specification 2.1. l)

In Modes I and 2, the combination of thermal power, pressurizer pressure, and the highest loop average temperature (T ng) 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% Lik/k for Tavg > 200°F Shutdown margin shall be greater than or equal to I.0% Lik/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 BOLi 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 -4.54E-4 ~k/k/°F.

This limit is based on a Tng program with HFP vessel Tavg of 569.0 to 573.0 °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

D. C. COOK UNIT 1 CYCLE 32 Revision 0

b.

The MTC Surveillance limit is:

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

- 3.84E-4 ak/k/°F at a HFP vessel Tng of569.0 to 573.0 °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 SR 3. l.3.2 limit (COLR 2.2.2.b) and all of the benchmark data contained in the surveillance procedure are met, then a MTC measurement in accordance with SR 3.1.3.2 is not required.

d.

The MTC Surveillance limit is:

The 60 ppm/ARO/RTP-MTC should be less negative or equal to

-4.41E-4 ak/k/°F at a HFP vessel Ta,*g of569.0 to 573.0 °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. l AXIAL FLUX DIFFERENCE (AFD) (Specification 3.2.3)

a.

The Allowable Operation Limits are provided in Figure 3.

b.

The AFD target band is +/-5% for a cycle average accumulated burnup

0.0 MWD/MTU.

Page 4 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2. l)

Where:

a.
b.

C.

CF FJ (Z) ~ _

Q

  • K(Z) p CF Ft' (Z) ~ _Q
  • K(Z) p for P > 0.5 for P~ 0.5 for P > 0.5 for P~0.5 THERMAL POWER p = RA TED THERMAL POWER K(Z) is provided in Figure 4.

FQc(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.

FQw (Z) = FQc (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 perfonned, 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 32, 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

D. C. COOK UNIT 1 CYCLE 32 Revision 0 Cycle Burnup Penalty Factor

<MWD/MTUl Fo(z) 1435 l.020 1618 1.023 1802 1.028 1985 1.032 2169 1.035 2352 l.036 2536 1.035 2719 l.033 2903 l.031 3086 1.030 3270 1.028 3453 l.026 3637 1.022 3820 l.020 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.1H) (Specification 3.2.2)

THERMAL POWER Where: p = RA TED THERMAL POWER

a.

CF.1H = 1.53

b.

PF.1H = 0.3

c.

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

2.4 INSTRUMENTATION 2.4. l Reactor Trip System (RTS) Instrumentation (Specification 3.3. l)

The Overtemperature AT and Overpower AT setpoints are as shown in Figure 5.

Page 6 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 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':: 2168 psig +
b. Reactor Coolant System T AVG shall be~ 580.5°F +
c.

Reactor Coolant System Total Flow Rate shall be 2':: 362,900 gpm 2.6 REFUELING OPERA TIO NS 2.6.1 Boron Concentration (Specification 3.9. I)

The boron concentration of all filled portions of the Reactor Coolant System, the refueling canal and the refueling cavity shall be greater than or equal to 2400 ppm++.

These are Safety Analysis values. With readability allowance, the corresponding values are 578.2°F for T u *g, and 2200 psig for Pressurizer Pressure.

This concentration bounds the condition of Kerr ::: 0.95 which includes a I% Llk/k conservative allowance for uncertainties. The boron concentration of 2400 ppm includes a 50 ppm conservative allowance for uncertainties.

Page 7 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 FIGURE 1 MOD ERA TOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 I UNACCEPTABLE OPERATION 0.5 LL 0

~

~

I m

+J Q) 0.0

"'O I ACCEPTABLE OPERATION I

~

0 T'""

X -

(.)

I-

-0.5

~

-1.0 0

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

D. C. COOK UNIT 1 CYCLE 32 Revision 0 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250 225 200 c

175 Ill...

"O

~ -

~ 150 1/l a.

Q) -

~

z 125 0

j::

ci5 0

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

aANv

I (100%, 189)1

/

/

V

/

/

/

/

1 (0%, 128)

I

/

I V

I BANK DI/

a..

100 a..

0 a::

(!)

0 75 0

a::

/

vr

/

50 25

/

V

/

/

V 0 /I (0%, o) I 0

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

Page 9 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RA TED THERMAL POWER (RTP) 100 1 (-11.90) 1 I (+11,90) I

/0\\

90 0

'I""

80 N -

I

\\

UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION I

\\

~ N 70

>< ~u.° LL 60

(.)

~

50 0

.4 l

I

\\

ACCEPTABLE OPERATION I

\\

.j l

ll.

I-I (-31,50) I I (+31,50) 1

~

40 E

~

E 30 C *-

E 20 0

~

0 10 O -50

-40

-30

-20

-10 0

10 20 30 40 50 FLUX DIFFERENCE (DEL T A-1)

Page 10 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 FIGURE4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 1.0 0.8

(!) z S2

<(

UJ Cl..

@ 0.6

~

_J

<(

~

0::

0 z 0.4 0.2 0.0 (0.0, 1.0) 0 (12.0, 1.0) 2 4

6 8

10 CORE HEIGHT (FT)

Page 11 of 19 12

D. C. COOK UNIT 1 CYCLE 32 Revision 0 Where:

IJ..T IJ..T 0

T T'

p P'

l+r,s 1 + T,S

'tt, 't2 s

K1 K2 Kl f1 (IJ..I)

FIGURE 5 (Page 1 of2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature IJ.. T Trip Setpoint

=

Measured RCS !J..T, 0 f

=

Indicated IJ..T at RA TED THERMAL POWER, 0 f

=

Average temperature, 0f

=

Nominal Tavi: at RATED THERMAL POWER ( ~ 575.4 °f)

=

Pressurizer pressure, psig

=

Nominal RCS operating pressure (2235 psig)

=

The function generated by the lead-lag controller for T a,*g dynamic compensation

=

Time constants utilized in the lead-lag controller for T avg

't12'. 22 secs.

't2 ~ 4 secs.

=

Laplace transfonn operator, sec*1 1.35 *

~

0.0230/°F 0.00110/psi

=

-0.33 {37% + (Qt - Qh)} when q, - Qb ~ -37% RTP 0%ofRTP when -37% RTP < q, - Qb ~ 3% RTP

+2.34 {(Qt - Qb) - 3%}

when q, - Qb > 3% RTP where Q1 and Qb are percent RA TED 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 12 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 Overpower AT~ ATo [K.- Ks Where:

AT ATo T

T" K.

Ks r.S I+ r,S s

=

=

=

=

~

2:

~

FIGURES (Page 2 of2)

Overpower AT Trip Setpoint Measured RCS AT, °F Indicated AT at RA TED THERMAL POWER, 0P Average temperature, 0P Nominal Tavg at RATED THERMAL POWER ( :s; 575.4 °F) 1.172

  • 0.0177/°F for increasing average temperature ; Ks = 0 for decreasing average temperature 0.00 I 5/°F for T greater than T" ; ~ = 0 for T less than or equal to T" The function generated by the rate lag controller for Tavg dynamic compensation Time constant utilized in the rate lag controller for Ta,,:

't3~ 10 secs.

Laplace transform operator, sec-1

  • 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

D. C. COOK UNIT 1 CYCLE 32 Revision 0 670 660 650

~ -

,_640

~

0 -630 OJ)

~ 620

~

00. 610 u

~ 600 590 580 570 0

Pressure

-Will 1840 2000 2100 2250 2400 UNITl FIGURE6 Reactor Core Safety Limits UNA< CEPTA llLE OP RATI0 '-1 2400 p1l1--('"

r--..L..

~

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

2260p11..-r r----1

-~,

~

.......... ~lit-

-r---........1

~-

I ---..........

.....___ 20oop11r "t"

~....___

"!!I,,.._

1840 psta,..-

~r---....,1

"""'N

--...,__J,.

~

ACCEPTABLE OPERATION

~

0.2 0.4 0.6 0.8 1

1.2 Power (Fraction of rated thermal power)

DESCRIPTION OF SAFETY LIMITS Power Tavg Power Tavg Power Tavg Power Tavg (frac)

{°F)

(frac)

{°F)

(frac)

(OF)

(frac)

C°F) 0.0 621.48 0.02 620.86 1.136 586.17 1.2 577.94 0.0 633.39 0.02 632.79 1.094 600.31 1.2 586.52 0.0 640.44 0.02 639.85 1.068 608.72 1.2 591.77 0.0 650.54 0.02 649.96 1.031 620.83 1.2 599.4 0.0 660.08 0.02 659.52 0.996 632.42 1.2 606.63 Reactor Core Safety Limits Page 14 of 19

D. C. COOK UNIT 1 CYCLE 32 FIGURE 7 Unit 1 Cycle 32 Predicted HFP ARO 300 PPM MTC Versus Burnup Burnup (MWD/MTU)

MTC (pcm/°F)

MTC (Ak/k/°F) 14,000

-23.248

-2.3248E-04 15,000

-23.663

-2.3663£-04 16,000

-24.048

-2.4048E-04 17,000

-24.417

-2.4417£-04 18,000

-24.814

-2.4814E-04 Page 15 of 19 Revision 0

D. C. COOK UNIT 1 CYCLE 32 Revision 0 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 32 W(Z) FUNCTION Node Height Burnup (MWD/MTU)

(ft) 150 1000 2000 4000 6000 8000 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2

0.2 1.0000 1.0000 1.0000 l.0000 l.0000 l.0000 3

0.4 1.0000 1.0000 1.0000 1.0000 1.0000 l.0000 4

0.6 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5

0.8 l.0000 l.0000 l.0000 l.0000 l.0000 l.0000 6

1.0 1.0000 l.0000 l.0000 l.0000 l.0000 1.0000 7

1.2 1.1074 l.1036 l.1001 1.0974 l.1001 l.1056 8

1.4 l.1068 l.1033 l.1002 1.0978 l.1004 l.l 056 9

1.6 l.1059 l.l 029 l.1001 1.0981 1.1005 l.l 053 10 1.8 l.1047 l.1021 l.0997 1.0981 l.1004 l.1047 11 2.0 l.1032 l.1010 l.0991 1.0979 1.0999 l.1037 12 2.2 1.1013 l.0997 l.0982 1.0974 1.0992 l.1023 13 2.4 1.0993 l.0981 1.0971 1.0967 1.0982 l.1006 14 2.6 1.0969 l.0963 l.0958 1.0957 l.0969 1.0986 15 2.8 1.0943 1.0942 1.0942 1.0945 1.0953 1.0963 16 3.0 l.0914 l.0919 l.0923 l.0930 1.0935 1.0937 17 3.2 1.0885 1.0894 l.0904 1.0914 1.0915 1.0910 18 3.4 1.0862 1.0876 1.0889 1.0901 1.0897 1.0884 19 3.6 1.0850 1.0868 1.0884 1.0898 1.0888 1.0869 20 3.8 1.0845 l.0863 1.0880 1.0892 1.0879 l.0855 21 4.0 l.0843 l.0860 1.0875 1.0886 1.0872 1.0850 22 4.2 1.0844 1.0858 1.0871 1.0881 1.0870 1.0852 23 4.4 l.0846 1.0858 1.0869 l.0876 1.0865 1.0850 24 4.6 l.0847 1.0856 l.0864 1.0868 l.0858 1.0847 25 4.8 l.0846 1.0851 1.0856 1.0857 1.0849 1.0842 26 5.0 1.0844 1.0845 1.0847 1.0845 1.0838 1.0835 27 5.2 1.0838 1.0836 1.0835 1.0830 1.0823 1.0825 28 5.4 1.0831 1.0825 1.0820 1.0812 1.0807 l.0813 29 5.6 l.0821 1.0811 1.0802 1.0793 1.0795 1.0811 30 5.8 1.0807 1.0793 1.0781 1.0772 1.0783 l.0810 Top and bottom 10% of core excluded.

Page 16 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 TABLE 1 (continued)

DONALD C. COOK UNIT 1 CYCLE 32 W(Z) FUNCTION Node Height Burnup (MWD/MTU)

(ft) 150 1000 2000 4000 6000 8000 31 6.0 l.0791 1.0773 1.0757 1.0747 1.0766 l.0804 32 6.2 l.0774 1.0750 1.0730 1.0719 1.0745 1.0794 33 6.4 l.0753 1.0725 l.0700 1.0688 1.0720 l.0779 34 6.6 l.0730 1.0697 l.0669 1.0655 1.0693 1.0759 35 6.8 1.0715 1.0682 1.0652 1.0636 1.0674 l.0740 36 7.0 1.0706 1.0673 1.0644 1.0626 1.0660 1.0720 37 7.2 1.0702 1.0666 l.0635 1.0615 1.0650 1.0715 38 7.4 l.0722 1.0679 l.0641 1.0618 1.0662 1.0741 39 7.6 l.0758 1.0716 1.0679 1.0658 1.0702 1.0779 40 7.8 1.0796 1.0760 1.0728 1.0710 1.0749 1.0817 41 8.0 1.0831 1.0799 l.0770 l.0754 1.0790 1.0851 42 8.2 1.0863 1.0836 1.0811 1.0798 1.0829 1.0881 43 8.4 l.0892 1.0870 1.0849 1.0839 1.0865 l.0908 44 8.6 1.0918 1.0900 1.0885 1.0877 1.0897 1.0931 45 8.8 1.0940 1.0927 1.0916 1.0911 1.0926 1.0950 46 9.0 1.0958 1.0952 l.0946 1.0944 1.0954 l.0967 47 9.2 1.0972 l.0974 1.0976 1.0979 1.0981 1.0981 48 9.4 1.0981 1.0992 1.1002 1.1009 1.1001 1.0987 49 9.6 1.0991 1.1009 1.1025 1.1035 1.1017 1.0989 50 9.8 1.0999 1.1022 1.1044 1.1057 1.1032 1.0994 51 10.0 1.1002 I. I 032 1.1061 1.1080 1.1054 1.1012 52 10.2 1.0999 1.1035 1.1069 l.1097 1.1077 1.1039 53 10.4 1.1007 1.1043 1.1077 1.1108 1.1093 1.1060 54 10.6 1.1065 1.1109 I.I 151 1.1183 1.1152 1.1097 55 10.8 1.1043 1.1088 1.1131 1.1168 1.1147 1.1103 56 11.0 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 58 l l.4 1.0000 1.0000 l.0000 1.0000 1.0000 1.0000 59 l l.6 1.0000 1.0000 l.0000 1.0000 1.0000 l.0000 60 11.8 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 61 12.0 l.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Top and bottom 10% of core excluded.

Page 17 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 TABLE 1 (continued)

DONALD C. COOK UNIT 1 CYCLE 32 W(Z) FUNCTION Node Height (ft) 10000 12000 14000 16000 18000 19398 0.0 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 3

0.4 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 5

0.8 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 7

1.2 1.1119 1.1172 1.1218 1.1265 1.1315 1.1349 8

1.4 1.1114 1.1164 1.1207 l.1250 1.1297 1.1329 9

1.6 l.1107 1.1152 1.1191 1.1231 1.1273 l.1302 10 1.8 1.1094 1.1135 1.1169 l.1204 1.1241 1.1267 11 2.0 1.1078 1.1112 1.1142 1.1172 l.1203 1.1225 12 2.2 1.1057 1.1086 1.1110 1.1135 l.1160 1.1178 13 2.4 I. I 033 l.1055 1.1074 1.1093 l.1112 1.1126 14 2.6 l.l 005 1.1020 I.I 033 1.1046 1.1059 1.1069 15 2.8 1.0973 1.0981 1.0988 1.0995 1.1002 1.1007 16 3.0 1.0939 1.0940 1.0940 1.0939 1.0939 1.0939 17 3.2 I.0903 1.0897 1.0891 1.0884 1.0877 1.0872 18 3.4 1.0869 1.0859 1.0853 1.0847 1.0840 1.0835 19 3.6 1.0851 1.0844 1.0847 l.0855 1.0860 1.0861 20 3.8 1.0836 1.0834 1.0845 1.0865 1.0880 1.0888 21 4.0 1.0833 1.0835 1.085 I 1.0877 1.0898 1.0910 22 4.2 1.0841 1.0848 1.0870 1.0902 1.0929 1.0945 23 4.4 1.0845 1.0861 1.0893 1.0939 1.0979 1.1002 24 4.6 1.0848 1.0872 1.0914 1.0971 1.1023 l.1054 25 4.8 1.0849 1.0880 1.0931 1.1000 1.1062 1.1099 26 5.0 1.0848 1.0886 1.0946 1.1024 1.1095 1.1139 27 5.2 1.0843 1.0888 1.0956 1.1042 l.1123 1.1172 28 5.4 1.0837 1.0888 1.0962 1.1056 1.1144 I.I 197 29 5.6 1.0844 1.0899 1.0974 l.1066 l.1153 l.1207 30 5.8 1.0853 1.0911 1.0984 1.1071 1.1154 1.1207 Top and bottom 10% of core excluded.

Page 18 of 19

D. C. COOK UNIT 1 CYCLE 32 Revision 0 TABLE 1 (continued)

DONALD C. COOK UNIT 1 CYCLE 32 W(Z) FUNCTION Node Height (ft) 10000 12000 14000 16000 18000 19398 31 6.0 1.0856 1.0917 1.0987 1.1068 l.1147 l.1198 32 6.2 1.0854 1.0916 1.0983 1.1057 l.1131 l.1179 33 6.4 l.0846 l.0910 1.0972 1.1038 1.1106 1.1151 34 6.6 l.0832 1.0896 1.0954 1.1012 1.1073 1.1116 35 6.8 1.0810 1.0869 1.0919 l.0968 l.1021 l.1058 36 7.0 1.0787 1.0845 1.0896 1.0947 l.1002 l.1039 37 7.2 1.0786 l.0847 l.0902 1.0958 l.1017 1.1057 38 7.4 1.0823 1.0886 l.0936 l.0981 1.1032 1.1069 39 7.6 1.0858 1.0917 1.0960 1.0998 l.1042 l.1074 40 7.8 1.0887 1.0938 1.0975 l.1008 l.1045 1.1073 41 8.0 1.0913 1.0957 1.0987 1.1012 1.1042 1.1065 42 8.2 1.0934 1.0970 1.0993 1.1012 l.1034 1.1052 43 8.4 1.0950 1.0978 1.0995 1.1006 l.1020 l.1033 44 8.6 1.0962 1.0982 1.0991 1.0995 1.1002 1.1009 45 8.8 1.0972 1.0982 1.0984 1.0980 l.0979 1.0981 46 9.0 1.0977 1.0978 1.0972 1.0960 1.0951 1.0946 47 9.2 1.0978 1.0972 1.0962 1.0950 1.0938 1.0932 48 9.4 1.0974 1.0971 1.0974 l.0982 1.0987 1.0989 49 9.6 1.0968 1.0967 1.0985 l.1013 l.1037 1.1049 50 9.8 1.0967 1.0969 1.0996 l.1040 l.1076 l.1095 51 10.0 1.0982 1.0985 l.1017 l.1068 l.1109 l.l 132 52 10.2 l.1011 1.1016 1.1047 1.1095 l.1135 1.1156 53 10.4 1.1035 1.1041 1.1071 1.1118 1.1156 1.1177 54 10.6 1.1054 1.1050 1.1080 1.1131 1.1171 I.I 192 55 10.8 l.1068 l.1068 l.1098 l.1145 l.1183 l.1203 56 11.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.2 1.0000 l.0000 1.0000 1.0000 l.0000 l.0000 58 11.4 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 60 11.8 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 Top and bottom 10% of core excluded.

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