AEP-NRC-2020-70, Core Operating Limits Report

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Core Operating Limits Report
ML20304A197
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 10/27/2020
From: Scarpello M
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2020-70
Download: ML20304A197 (22)
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Text

m INDIANJl Indiana Michigan Power MICHIGAN Cook Nuclear Plant One Cook Place POWER* Bndgman, Ml 49106 A umt ofAmerican EJectnc Power lnd1anaMich1ga nPower com October 27, 2020 AEP-NRC-2020-70 10 CFR 50.4 Docket No.: 50-315 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 CORE OPERATING LIMIT,S REPORT 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 30 in accordance with Technical Specification 5.6.5. Revision 0. of the Unit 1 Cycle 30 COLF~ 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.

/4t~ru Michael K. Scarpello Regulatory Affairs Director DLW/mll

Enclosure:

Donald C. Cook Nuclear Plant Unit 1 Cycle 30 Core Operating Limits Report, Revision 0

U. S. Nuclear Regulatory Commission AEP-NRC-2020-70 Page2 c: R. J. Ancona - MPSC EGLE - RMD/RPS J.B. Giessner- NRC Region Ill D. L. Hille - AEP Ft. Wayne, w/o enclosures NRC Resident Inspector R. M. Sistevaris - AEP Ft. Wayne, w/o enclosures S. P. Wall - NRC Washington, D.C.

A. J. Williamson - AEP Ft. Wayne, w/o enclosures

ENCLOSURE TO AEP-NRC-2020-70 Donald C. Cook Nuclear Plant Unit 1 Cycle 30 Core Operating Limits Report Revision 0

D. C. COOK UNIT 1 CYCLE 30 Revision 0 Donald C. Cook Nuclear Plant Unit 1 Cycle 30 Core Operating Limits Report Revision 0 Page 1 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit 1 Cycle 30 design has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The analytical methods used to detenrune 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. 1A, Relaxation of Constant Axial Offset ControVFQ Surveillance Techrucal Specification, February 1994
d. Plant-specific adaptation of WCAP-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 LiT and Thermal Overtemperature LiT 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:

2.1.1 Reactor Core Safety Limits 3.1.1 SHUIDOWN 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 (FNm) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reactor Trip System (RTS) Instrumentation 3.4. l RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3.9.1 Boron Concentration Page 2 of 19

D. C. COOK UNIT 1 CYCLE 30 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.

2.1 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 (Tavg) shall not exceed the limits as shown in Figure 6 for 4 loop operation.

2.2 REACTMTY 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 1.00/o Afc/k for Tavs :-: :; 200°F 2.2.2 Moderator Temperature Coefficient (MTC) (Specification 3.1.3)

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

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

The EOUARO/RTP-MTC shall be less negative or equal to--4.54E-4 Lik/k/°F.

This ltmit is based on a Tavg 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 RTP stands for Rated Thermal Power HFP stands for Hot Full Thermal Power Page 3 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0

b. The MTC Surveillance limit is:

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

-3.84E-4 Aklkl°F at a HFP vessel Tavg of 569.0 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 Aklkl°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

-4.41E-4 Ak/k/°F at a HFP vessel Tavg of 569.0 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 2.3.1 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 4 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0 2.3.2 Heat Flux Hot Channel Factor (Fo(Z)) (Specification 3.2.1)

CF FJ(Z) ~-Q *K(Z) for P > 0.5 p

FJ (Z) :S 2

  • CFQ
  • K(Z) for P~0.5 CF Ff (Z) ~ _ Q
  • K(Z) for P> 0.5 p

for P ~ 0.5 THERMAL POWER Where: p = RA TED THERMAL POWER

a. CFQ = 2.09
b. K(Z) is provided in Figure 4.

C. 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 I for +/-5% AFD target band.
e. FQ w (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 performed, the W(z) values should be multiplied by the factor 1/P, when P is> 0.5. When Pis :S 0.5, the W(z) values should be multiplied by the factor 1/(0.5), or 2.0. This 1s consistent with the adjustment in the Fo(z) limit at part power conditions.
f. For Cycle 30, FP = 1.02 for all burnups associated with Note 2a of SR 3.2.1.2, except as shown in the table below. When no penalty is required, FP = 1.00.

Page 5 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0 Cycle Penalty Factor Burnup FQ(z)

(MWD/MTU) 2717 1.020 2900 1.021 3083 1.023 3267 1.024 3450 1.025 3633 1.026 3817 1.026 4000 1.025 4183 1.022 4367 1.020 4733 1.020 4917 1.021 5100 1.020 The bumup 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.IB) (Specification 3.2.2)

J<NAH ~ CFm * (1 + PFm *(1-P))

THERMAL POWER Where: p = RA TED THERMAL POWER

b. PF6tt= 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 LiT and Overpower LiT setpoints are as shown in Figure 5.

Page 6 of 19

D. C. COOK UNIT 1 CYCLE 30 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:::: 2168 psig +
b. Reactor Coolant System TAvG shall be~ 580.5°F +
c. Reactor Coolant System Total Flow Rate shall be:::: 362,900 gpm 2.6 REFUELING OPERATIONS 2.6.1 Boron Concentration (Specification 3.9.1)

The boron concentration of all filled portions of the Reactor Coolant System, the refuelmg 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°P for Tavg , and 2200 psig for Pressurizer Pressure.

++ This concentration bounds the condition ofKeff:'.:: 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

D. C. COOK UNIT 1 CYCLE 30 Revision 0 FIGURE 1 MOD ERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 I UNACCEPTABLE OPERATION I 0.5 LL 0

?2 "' "' ~

?2 I co Q,)

"'C 0

0.0 I ACCEPTABLE OPERATION I

~

X 0

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 30 Revision 0 FIGURE2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250 225 - I I

/

(52.9%, 228) 100 Step Overlap 200 I I

BANKC 1 ~

I/

I (100%, 189)1 V

- 175 / /

~ / V

~

"O

e s: 150 / /

(/)

0.

(/)

z 125

/'

l_j (0%, 128) I /

/

I 0

i=

ci5 IBANK DI/

/

0 Q.

/~

100 /

Q.

0 er:

(9 Cl 75 0

er:

50 /

V V

25

/

/

Vi

/ (0%,0) I a

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

Page 9 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0 FIGURE3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RA TED THERMAL POWER (RTP) 100 1 (-11,90) I 1 (+11.00) 1

("o'\ 90 0

>< 80 -

UNACCEPTABLE OPERATION I \ UNACCEPTABLE OPERATION ~

N

~ --

N 70 .4 I \ l u.

>< ~u.o 60 I ACCEPTABLE OPERATION \

(.)

~

0 50 ..4 I \.L

a. 1 (-31,50) 1 1 (+31,50)

I-

~ 40 E

s E 30
  • -~C: 20 Ip,,

0

~

0 10 0 -50 -40 -30 -20 -10 0 10 20 30 40 50 FLUX DIFFERENCE (DEL TA-I)

Page 10 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0 FIGURE4 K(Z)- NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 (0.0, 1.0) (12.0, 1.0) 1.0 0.8

(.!)

z

~

lll 0...

@ 0.6

~

i 0

z 0.4 --------------------------------------------------------

0.2 0.0 ----......-----.......-----,------..------,-------f 0 2 4 6 8 10 12 CORE HEIGHT (FT)

Page 11 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0 FIGURES (Page 1 of2)

Reactor Trlp System Instrumentation Trlp Setpofnts Overtemperature ~T Trip Setpoint Overtemperature ~T ~ ~T0 [1( 1 - ~

l+r,s]

-- (f-T') + K3 (P-P')- f1 (Af)l

[ 1 + T2S Where: ~T = Measured RCS ~T, 0 P

~T0 Indicated ~Tat RA TED THERMAL POWER, 0 P T = Average temperature, 0 P T' Nominal Tavg at RATED THERMAL POWER ( :s; 575.4 °F) p Pressurizer pressure, psig P' Nominal RCS operating pressure (2235 psig) l+r,s The function generated by the lead-lag controller for Tavg dynamic 1 + riS compensation

  • 1, *2 Time constants utilized in the lead-lag controller for T""K
  • ~

1 22 secs. -r2 :-S:4 secs .

s Laplace transform operator, sec- 1 K1 < 1.35

  • Kz ~ 0.0230/°F KJ ~ 0.00110/psi f1 (~I) = -0.33 {37% + (Qt - Qb)} when Qt - Qb :'S -37% RTP 03/4ofRTP when -37% RTP < Qt - Qh :'S 3% RTP

+2.34 {(Qt-Qb)-3%} when Qt - Qh > 3% RTP where Qr and Qh 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 RA TED 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 30 Revision 0 FIGURES (Page 2 of2)

Overpower AT Trip Setpoint Overpower AT~ ATo [1(4-Ks [

-r,S ] T - Ki; (f - T) - t; (Af)l 1+ TJS Where: AT = Measured RCS AT, °F ATo Indicated AT at RA TED THERMAL POWER, 0 P T Average temperature, 0 P T" = Nominal T11'1! at RA TED THERMAL POWER (::; 575.4 °F)

~ :s 1.172.

Ks  :::: 0.0177/ 0 P for increasing average temperature ; Ks = 0 for decreasing average temperature

0.0015/ 0 P for T greater than T" ; Ki;= 0 for T less than or equal to T" The function generated by the rate lag controller for T.vg dynamic compensation Time constant utilized in the rate lag controller for Tavg .;:: 10 secs.

s Laplace transform operator, sec- 1 f/Af) = 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

D. C. COOK UNIT 1 CYCLE 30 Revision 0 FIGURE6 Reactor Core Safety Limits 670 660

---:-......_ DNAC CEPTA BLE 650

---,___ ---- - OP~Tl{J"J

r--- ....._

i.---*

2400 ps,a-

,-_640

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

.....___ 2
MO P1IY]

---.i....

r---~

--t---J --

t--_

i---

-,___ 1---..

-630 '

bJ)

i.. ...._

~'ai I~-- I

 ;.....____ ---- i--.... I

-- ~ "

I i:d 620

--r----.... --;-.__ ~

2000p11r

~ ---.. ..........

lo...

-r-----.._

rJJ. 610 u hiwo ps,..,- -r---,1 r--,,..._ ___ '"""

- - ~"'

---. r---.._

~ 600 ACCEI ,fABLE t--..._

I\._',,

590 OPER \TlON I ---.. jo,.,_'

580 570 I

i

' ~

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 11W.!tl ffrac) (OF) (frac) (OF) lfI:.rua rn !fr.!!ru. .eEl 1840 0.0 621.48 0.02 620.86 1.136 586.17 1.2 577.94 2000 0.0 638.39 0.02 632.79 1.094 600.31 1.2 586.52 2100 0.0 640.44 0.02 639.85 1.068 608.72 1.2 591.77 2250 0.0 650.54 0.02 649.96 1.031 620.88 1.2 599.4 2400 0.0 660.08 0.02 659.52 0.996 632.42 1.2 606.68 UNIT 1 Reactor Core Safety Limits Page 14 of 19

D. C. COOK UNIT l CYCLE 30 Revision O FIGURE7 Unit 1 Cycle 30 Predicted HFP ARO 300 PPM MTC Versus Burnap

-2 39-04

-2 41E-04 I\

( -2 43E-04

\

.s C

u

E

-2.4!5E-04

\

8 e

a

-2 47E-04 I\

\

a.

E

{!.

s a \.

~ *2 491:-04 "8

a

\ ~

-2 51E-04

\

-2 63-04

\

\

-2 SSE-04 15,000 16.000 17,000 18,000 19,000 Cycle Burnup [MWDIM11J)

Bumup (MWD/MTU) MTC(pcml°F) MTC (Ak/k/°F) 15,000 -23.898 -2.3898E-04 16,000 -24.328 -2.4328E-04 17,000 -24.683 -2.4683E-04 18,000 -25.025 -2.5025E-04 19,000 -25.417 -2.5417E-04 Page 15 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0 TABLE t DONALD C. COOK UNIT 1 CYCLE 30 W(Z) FUNCTION Bumup (MWD/MTU)

Node Height

  1. (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 1.0000 1.0000 1.0000 3 0.4 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.6 1.1159 1.1137 1.1113 1.1077 1.1054 1.1046 5 0.8 1.1165 1.1134 1.1104 1.1060 1.1043 1.1047 6 1.0 1.1159 1.1123 1.1086 1.1039 I. I 027 1.1043 7 1.2 1.1148 1.1107 1.1067 1.1016 1.1010 1.1035 8 1.4 1.1134 1.1090 1.1046 1.0994 1.0993 1.1026 9 1.6 1.1117 1.1077 1.1038 1.0991 1.0992 1.1024 10 1.8 1.1095 1.1062 1.1029 1.0990 1.0991 1.1020 11 2.0 1.1070 1.1043 1.1016 1.0985 1.0988 1.1013 12 2.2 1.1042 1.1022 1.1002 1.0979 1.0982 1.1003 13 2.4 1.1011 1.0998 1.0985 1.0970 1.0974 1.0990 14 2.6 1.0977 1.0971 1.0965 1.0959 1.0963 1.0974 15 2.8 1.0941 1.0942 1.0943 1.0946 1.0950 1.0955 16 3.0 1.0902 1.0911 1.0919 1.0930 1.0934 1.0933 17 3.2 1.0867 1.0882 1.0896 1.0914 1.0917 1.0910 18 3.4 1.0852 1.0868 1.0883 1.0902 1.0902 1.0889 19 3.6 1.0865 1.0876 1.0887 1.0897 1.0889 1.0872 20 3.8 1.0879 1.0885 1.0890 1.0892 1.0878 1.0857 21 4.0 1.0889 1.0890 1.0890 1.0884 1.0866 1.0844 22 4.2 1.0899 1.0895 1.0889 1.0875 1.0855 1.0836 23 4.4 1.0907 1.0897 1.0886 1.0865 1.0846 1.0832 24 4.6 1.0913 1.0897 1.0880 1.0853 1.0836 1.0827 25 4.8 1.0917 1.0894 1.0872 1.0839 1.0823 1.0821 26 5.0 1.0917 1.0890 1.0862 1.0824 1.0810 1.0814 27 5.2 1.0915 1.0883 1.0851 1.0808 1.0796 1.0805 28 5.4 1.0910 1.0874 1.0837 1.0790 1.0779 1.0793 29 5.6 1.0901 1.0862 1.0822 1.0771 1.0761 1.0780 30 5.8 1.0889 1.0847 1.0805 1.0751 1.0743 1.0764 Top and bottom 53/4 of core excluded.

Page 16 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0 TABLE 1 (continued)

DONALD C. COOK UNIT 1 CYCLE 30 W(Z) FUNCTION Burnup (MWD/MTU)

Node Height

  1. (ft) 150 1000 2000 4000 6000 8000 31 6.0 1.0873 1.0829 1.0786 1.0730 1.0721 1.0744 32 6.2 1.0852 1.0807 1.0762 1.0706 1.0697 1.0721 33 6.4 1.0827 1.0781 1.0737 1.0679 1.0670 1.0695 34 6.6 1.0803 1.0756 1.0710 1.0652 1.0645 1.0672 35 6.8 1.0775 1.0728 1.0683 1.0628 1.0628 1.0665 36 7.0 1.0761 1.0713 1.0667 1.0616 1.0625 1.0674 37 7.2 1.0766 1.0714 1.0663 1.0609 1.0626 1.0689 38 7.4 1.0796 1.0730 1.0667 1.0600 1.0624 1.0703 39 7.6 1.0823 1.0758 1.0696 1.0630 1.0653 1.0731 40 7.8 1.0845 1.0790 1.0737 1.0681 1.0701 1.0768 41 8.0 1.0864 1.0818 1.0775 1.0729 1.0748 1.0806 42 8.2 1.0878 1.0843 1.0810 1.0777 1.0795 1.0845 43 8.4 1.0889 1.0865 1.0842 1.0822 1.0840 1.0881 44 8.6 1.0904 1.0889 1.0875 1.0865 1.0881 1.0912 45 8.8 1.0918 1.0912 1.0907 1.0905 1.0919 1.0940 46 9.0 1.0927 1.0930 1.0934 1.0943 1.0954 1.0965 47 9.2 1.0933 1.0945 1.0958 1.0977 1.0986 1.0987 48 9.4 1.0935 1.0957 1.0979 1.1008 1.1015 I. I 006 49 9.6 1.0936 1.0967 1.0998 I. I 037 1.1041 I. 1022 50 9.8 1.0949 1.0986 1.1022 1.1065 1.1064 1.1035 51 10.0 1.0978 1.1016 1.1053 1.1094 1.1083 1.1041 52 10.2 1.1012 1.1048 1.1083 1.1116 1.1095 1.1044 53 10.4 1.1042 1.1071 1.1099 1.1126 1.1109 1.1068 54 10.6 1.1067 1.1114 1.1159 1.1207 1.1190 1.1135 55 10.8 1.1088 1.1124 1.1158 1.1 I 89 1.1163 1.1106 56 11.0 1.1103 1.1143 1.1180 1.1218 1.1199 1.1147 57 11.2 1.1115 l. 1165 1.1213 1.1260 1.1231 1.1160 58 11.4 1.1115 1.1167 1.1215 1.1259 1.1222 1.1139 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 53/4 of core excluded.

Page 17 of 19

D. C. COOK UNIT 1 CYCLE 30 Revision 0 TABLE l (continued)

DONALD C. COOK UNIT 1 CYCLE 30 W(Z) FUNCTION Bumup (MWD/MTU)

Node Height

  1. (ft) 10000 12000 14000 16000 18000 20000 21044 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 1.1055 1.1086 1.1135 1.1201 1.1286 1.1353 1.1384 5 0.8 1.1069 1.1104 1.1153 1.1216 1.1293 1.1357 1.1388 6 1.0 1.1074 1.1114 1.1162 1.1220 1.1290 1.1350 1.1379 7 1.2 1.1075 1.1119 1.1166 1.1218 1.1280 1.1336 1.1363 8 1.4 1.1073 1.1119 1.1164 1.1211 1.1264 1.1315 1.1340 9 1.6 1.1068 1.1111 1.1152 1.1194 1.1243 1.1289 1.1312 10 1.8 1.1059 1.1097 1.1133 1.1171 1.1214 1.1255 1.1275 11 2.0 1.1046 1.1079 1.1110 1.1143 1.1180 1.1215 1.1232 12 2.2 1.1030 1.1057 1.1082 1.1109 1.1140 1.1168 1.1183 13 2.4 1.1010 1.1030 1.1050 1.1071 1.1094 1.1117 1.1128 14 2.6 1.0987 1.1000 1.1014 1.1029 1.1045 1.1061 1.1068 15 2.8 1.0960 1.0967 1.0974 1.0983 1.0992 1.1001 1.1005 16 3.0 1.0931 1.0930 1.0931 1.0933 1.0935 1.0936 1.0936 17 3.2 1.0900 1.0893 1.0887 1.0883 1.0878 1.0873 1.0870 18 3.4 1.0874 1.0862 1.0855 1.0849 1.0843 1.0835 1.0831 19 3.6 1.0855 1.0845 1.0843 1.0846 1.0852 1.0853 1.0853 20 3.8 1.0840 1.0833 1.0836 1.0848 1.0865 1.0875 1.0879 21 4.0 1.0828 1.0825 1.0834 1.0852 1.0879 1.0896 1.0903 22 4.2 1.0824 1.0824 1.0837 1.0860 1.0892 1.0915 1.0924 23 4.4 1.0825 1.0830 1.0846 1.0871 1.0904 1.0929 1.0940 24 4.6 1.0828 1.0837 1.0855 1.0880 1.0914 1.0940 1.0952 25 4.8 1.0828 1.0842 1.0862 1.0888 1.0921 1.0949 1.0961 26 5.0 1.0827 1.0845 1.0866 1.0892 1.0925 1.0953 1.0966 27 5.2 1.0824 1.0845 1.0867 1.0893 1.0925 1.0953 1.0967 28 5.4 1.0818 1.0842 1.0866 1.0891 1.0921 1.0949 1.0963 29 5.6 1.0809 1.0837 1.0862 1.0889 1.0921 1.0951 1.0966 30 5.8 1.0797 1.0829 1.0861 1.0894 1.0934 1.0970 1.0989 Top and bottom 53/4 of core a eluded.

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D. C. COOK UNIT 1 CYCLE 30 Revision 0 TABLE 1 (continued)

DONALD C. COOK UNIT 1 CYCLE 30 W(Z) FUNCTION Burnup (MWD/MTU)

Node Height

  1. (ft) 10000 12000 14000 16000 18000 20000 21044 31 6.0 1.0782 1.0820 1.0859 1.0902 1.0953 1.1000 1.1022 32 6.2 1.0761 1.0804 1.0850 1.0901 1.0962 1.1017 1.1044 33 6.4 1.0737 1.0784 1.0836 1.0895 1.0965 1.1028 1.1058 34 6.6 1.0718 1.0769 1.0824 1.0887 1.0962 1.1028 1.1061 35 6.8 1.0718 1.0772 1.0827 1.0886 1.0954 1.1017 1.1048 36 7.0 1.0736 1.0791 1.0839 1.0887 1.0939 1.0991 1.1017 37 7.2 1.0762 1.0819 1.0862 1.0897 1.0932 1.0973 1.0995 38 7.4 1.0792 1.0857 1.0901 1.0931 1.0957 1.0994 1.1015 39 7.6 1.0818 1.0881 1.0923 1.0951 1.0975 1.1010 1.1031 40 7.8 1.0843 1.0898 1.0935 1.0962 1.0985 1.1018 1.1036 41 8.0 1.0871 1.0919 1.0950 1.0973 1.0992 1.1019 1.1035 42 8.2 1.0900 1.0939 1.0964 1.0981 1.0993 1.1014 1.1026 43 8.4 1.0924 1.0954 1.0972 1.0983 1.0990 1.1004 1.1012 44 8.6 1.0944 1.0965 1.0976 1.0981 1.0982 1.0989 1.0993 45 8.8 1.0960 1.0972 1.0976 1.0975 1.0970 1.0970 1.0971 46 9.0 1.0973 1.0975 1.0973 1.0966 1.0956 1.0950 1.0947 47 9.2 1.0983 1.0977 1.0967 1.0954 1.0938 1.0924 1.0918 48 9.4 1.0991 1.0976 1.0961 1.0945 1.0925 1.0907 1.0898 49 9.6 1.0997 1.0978 1.0966 1.0955 1.0944 1.0931 1.0924 50 9.8 1.1002 1.0982 1.0975 1.0975 1.0979 1.0976 1.0973 51 10.0 1.0998 1.0977 1.0974 1.0984 1.1003 1.1009 1.1011 52 10.2 1.0995 1.0972 1.0974 1.0994 1.1026 1.1041 1.1045 53 10.4 1.1028 1.1009 1.1010 1.1025 I. I 049 1.1060 1.1063 54 10.6 1.1078 1.1047 1. 1039 1.1048 1.1066 1.1069 1.1068 55 10.8 1.1051 1.1025 1.1024 1.1043 1. 1074 1.1088 1.1091 56 11.0 1.1094 1.1065 1.1058 1.1066 1.1084 1.1087 1.1087 57 11.2 1.1089 1.1052 1.1044 1.1057 1.1084 1.1091 1.1092 58 11.4 1.1059 1.1018 1.1014 1.1035 1.1074 1.1089 1.1092 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 5% of core Hcluded.

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