AEP-NRC-2017-58, Core Operating Limits Report

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Core Operating Limits Report
ML17326A385
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 11/20/2017
From: Scarpello M
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2017-58
Download: ML17326A385 (21)
v • d • e


Text

m INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWEil. One Cook Place Bridgman, Ml 49106 A unit ofAmerican Electric Power lndianaMichiganPower.com November20,2017 AEP-NRC-2017-58 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 LIMITS 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 28 in accordance with Technical Specification 5.6.5. Revision O of the Unit 1 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.

  • t~?Lru Michael K. Scarpello Regulatory Affairs Manager DMB/mll

Enclosure:

Donald C. Cook Nuclear Plant Unit 1 Cycle 28 Core Operating Limits Report, Revision 0 c: R. J. Ancona - MPSC MDEQ - RMD/RPS NRG Resident Inspector C. D. Pederson, NRG Region Ill J. K. Rankin, NRG Washington, D.C.

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

ENCLOSURE TO AEP-NRC-2017-58 Donald C. Cook Nuclear Plant Unit 1 Cycle 28 Core Operating Limits Report Revision 0

D. C. COOK UNIT 1 CYCLE 28 Revision 0 Donald C. Cook Nuclear Plant Unit 1 Cycle 28 Core Operating Limits Report Page 1 of 19

D. C. COOK UNIT 1 CYCLE 28 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit 1 Cycle 28 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/FQ Surveillance Technical 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 ,1.T 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:

2.1.1 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 (FNm) 3.2.3 AXIAL FLUX DJFFERENCE (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 2 of 19

D. C. COOK UNIT 1 CYCLE 28 Revision 0 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 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 REACTNITY 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 1.0% 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 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--4.54E-4 Ak/k/°F.

This limit 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 28 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 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 Ak/k/°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 LTh1ITS 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 1s +/-5% for a cycle average accumulated burnup
?:0.0 MWD/MTU.

Page 4 of 19 I

D. C. COOK UNIT 1 CYCLE 28 Revision 0 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

CF Ff (Z)-:;, _ Q

  • K(Z) for P > 0.5

- p FJ(Z)-:;, 2

  • CFQ
  • K(Z) for p-::;, 0.5 CF F{ (Z)-:;, __g__
  • K(Z) for P > 0.5 p

F! (Z)-:;, 2

  • CFQ
  • K(Z) for p-::;, 0.5 THERMAL POWER Where: p = RATED THERMAL POWER
a. CFQ=2.09
b. K(Z) is provided in Figure 4.

C. ~(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.

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 Pis> 0.5. When Pis~ 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 28, FP = 1.02 for all bumups associated with Note 2a of SR 3.2.1.2.

When no penalty is required, FP = 1.00.

Page 5 of 19

D. C. COOK UNIT 1 CYCLE 28 Revision 0 2.3 .3 Nuclear Enthalpy Rise Hot Channel Factor (FNMI) (Specification 3 .2.2)

THERMAL POWER Where: p = RATED THERMAL POWER

a. CFMI= 1.53
c. FNMI 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.

Page 6 of 19

D. C. COOK UNIT 1 CYCLE 28 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 OPERATIO NS 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 578.2°F for Tavg , 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

D. C. COOK UNIT 1 CYCLE 28 Revision 0 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 I UNACCEPTABLE OPERATION I 0.5

_....._ ~

LL 0

~

~

I co Q) l:J

"-I'"I 0

~

0.0 I ACCEPTABLE OPERATION I

(.)

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 28 Revision 0 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250 225 - I V

(52.9%, 228) 100 Step Overlap I 200 1 BANK C 1 ,/

I I/

I (100%. 189)

V

~

175 / /

/

C

l: /

V CIJ

/

L.

"O

.c

~ 150 2

~

z en 0.

125 ~

/'

(0%, 128) I /

/

V I

0 i=

U) 0 I BANK DI/

0... /

0... 100

J 0

a:

CJ 0 75 V'

V 0

a:

50 /

V 25

/

/

/I

/ (0%, o) I 0

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 28 Revision 0 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 I (-11.90) I 1(+11,90)1

,ci\ 90 0

~

>< 80 '--

UNACCEPTABLE OPERATION I \ UNACCEPTABLE OPERATION ~

N

~ --

N 70 .4 I \ \

u.

>< 3:u:a 60 I ACCEPTABLE OPERATION \

u

~

0 50 .'

I \ ..

a..

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

~ 40 E

s E 30 C:
2E 20 t+-

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 28 Revision 0 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 - - - - - - - . - - - - - - , - - - - - , - - - - - , - - - - - - - - , - - - - -

1.0 ....-.-----1---....----...----;,-,o=---------t (0.0, 1.0) (12.0, 1.0)

I (9

z 0.8

---1-- 1---1------1---

S2 1  ! , I

<(

w i i 0...

Ow O.6 N

J

<(

I 1

' I ,

~

0::: l l 0

z 0.4 . . . . . . . . . . . . . . . !. . . . . . . . . . . . . . . ,. . . . . . . . . . . . . . ..t...............................,.......-**************-*****: ***-***-******************

! fi 1: II  !

§ 02 -----!-i-,--!---1------** I I I

0.0 - i - - - - - - - - ; - - - - - ; - - - - - + - - - - - i - - - - - - - - - - i - - - - - i I 0 2 4 6 8 10 12 CORE HEIGHT (Fl)

Page 11 of 19

D. C. COOK UNIT 1 CYCLE 28 Revision 0 FIGURES (Page 1 of 2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint OvertemperatureAT::;;AT0 [K1 -K2 [l+ris] (T-T')+K3 (P-P')-f1 (M)]

  • 1 + T2S Where: AT = Measured RCS AT, 0 P AT0 = Indicated AT at RATED THERMAL POWER, 0 P T = Average temperature, 0 P T' = Nominal Tavg at RATED THERMAL POWER(::;; 575.4 °P) p = Pressurizer pressure, psig P' = Nominal RCS operating pressure (2235 psig) l+T1S The function generated by the lead-lag controller for Tavg dynamic l+T2S compensation

\ , 't2 = Time constants utilized in the lead-lag controller for Tavg

\~ 22 secs. 't ::; 4 secs.

2 s = Laplace transform operator, sec-1 K1 < 1.35

  • K2 > 0.02301°P KJ > 0.00110/psi f1 (M) = -0.33 {37% + (qt - qb)} when qt - qh :S-37% RTP 0%ofRTP when -37% RTP < qt - qb::; 3% RTP

+2.34 {(qt - qb)-3%} when qt - qh > 3% RTP where q1 and qh 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

D. C. COOK UNIT 1 CYCLE 28 Revision 0 FIGURES (Page 2 of 2)

Overpower AT Trip Setpoint Overpower AT ;5; AT0 [~ - Ks [ r S 3

l+r3S J T- ~ (T- T") - f (M)]

2 Where: AT Measured RCS AT, °F ATo Indicated AT at RATED THERMAL POWER, P 0 T = Average temperature, 0 P T" = Nominal Tavg at RATED THERMAL POWER ( ~ 575.4 °P)

~ < 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" ; ~ = 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 Tavg 't :::

3 10 secs.

s 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 28 Revision 0 FIGURE 6 Reactor Core Safety Limits 670 I

~

l

  • "-r-660 ..........._ ---

UNAdCEPf.A

--,...__ ---...1'"--

OP.p:tAllu ~

650 2400 psia.f"' --......J._

-.,640 ~ '

2250 psi '

---i..__ ~ i r---.... I

~Q

-630

............... ~

I

-- i

............... 1 I ---...."'"

--- d--::

~ ............_1 I

~~psi!*

~ ~

= 620 ---

-- ......___ ~ ._ ......___ ---... -

1----...

"~

2000 psi.....-

~ I

--.....,___ 1

---+-  !"""--

00. 610 u

~

1840 psla-1 I

-r---..l_

.......... ....__ I

! r-,..._!

-- ,IN r--,.....__

J\..

600

~i---... ---------------~

ACCEkABLE/-----**

590 OPERATION  !

580 570

<>:<;;,c-A 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 fufilru ffrac) (OF) ffrac) (OF) (frac) {°F) ffrac) {°F) 1840 0.0 621.48 0.02 620.86 1.136 586.17 1.2 577.94 2000 0.0 ' 633.39 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 1.031 620.83 1.2 599.4 2400 0.0 660.08 0.02 659.52 0.996 632.42 1.2 606.63 UNITl Reactor Core Safety Limits Page 14 of 19

D. C. COOK UNIT 1 CYCLE 28 Revision 0 FIGURE 7 Unit 1 Cycle 28 Predicted HFP ARO 300 PPM MTC Versus Burnup

-2.20E-04 u:-

-2.22E-04

-2.24E-04

" I\ \

\

~

-2.26E-04

~

c., \

0

~ -2.2SE-04 i\

u 0

., \

I'\

I-

~ -2.30E-04 a.

E \

~

I-0 E

-0

. -2.32E-04

\

I\

0

E:

-2.34E-04

\

-2.36E-04 I\

\

-2.38E-04

-2.40E-04 11,000 12,000 13,000 14,000 15,000 Cycle Bumup {MWDIMlU)

Burnup (MWD/MTU) MTC(pcm/°F) MTC (Ak/k/°F) 11,000 -22.067 -2.2067E-04 12,000 -22.484 -2.2484E-04 13,000 -22.902 -2.2902E-04 14,000 -23.282 -2.3282E-04 15,000 -23.683 -2.3683E-04 Page 15 of 19

D. C. COOK UNIT 1 CYCLE 28 Revision 0 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 28 W(Z) FUNCTION Bumup (MWD/MTU)

Node Height

  1. (ft) 150 1000 2000 4000 6000 8000 1 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 1.1004 1.0985 1.0971 1.0981 1.1026 1.1090 8 1.4 1.1005 1.0987 1.0975 1.0985 1.1028 1.1088 9 1.6 1.1003 1.0988 1.0977 1.0988 1.1027 1.1083 10 1.8 1.0999 1.0986 1.0977 1.0987 1.1024 . 1.1073 11 2.0 1.0992 1.0982 1.0974 1.0984 1.1016 1.1060 12 2.2 1.0984 1.0975 1.0970 1.0979 1.1006 1.1042 13 2.4 1.0973 1.0967 1.0963 1.0971 1.0993 1.1021 14 2.6 1.0960 1.0956 1.0955 1.0961 1.0977 1.0997 15 2.8 1.0945 1.0944 1.0944 1.0948 1.0958 1.0969 16 3.0 1.0926 1.0928 1.0929 1.0933 1.0936 1.0939 17 3.2 1.0907 1.0911 1.0914 1.0915 1.0912 1.0906 18 3.4 1.0895 1.0900 1.0903 1.0900 1.0888 1.0873 19 3.6 1.0891 1.0898 1.0902 1.0896 1.0876 1.0856 20 3.8 1.0887 1.0895 1.0900 1.0893 1.0871 1.0851 21 4.0 1.0882 1.0890 1.0896 1.0891 1.0875 1.0861 22 4.2 1.0875 1.0884 1.0891 1.0893 1.0885 1.0881 23 4.4 1.0868 1.0876 1.0884 1.0891 1.0893 1.0900 24 4.6 1.0859 1.0866 1.0873 1.0886 1.0898 1.0916 25 4.8 1.0848 1.0854 1.0862 1.0879 1.0901 1.0931 26 5.0 1.0836 1.0841 1.0849 1.0871 1.0902 1.0942 27 5.2 1.0825 1.0827 1.0834 1.0860 1.0899 1.0950 28 5.4 1.0811 1.0811 1.0815 1.0844 1.0893 1.0953 29 5.6 1.0795 1.0792 1.0795 1.0827 1.0883 1.0952 30 5.8 1.0775 1.0771 1.0775 1.0810 1.0871 1.0947 Top and bottom 10% of core excluded.

Page 16 of 19

D. C. COOK UNIT 1 CYCLE 28 Revision 0 TABLE 1 (continued)

DONALD C. COOK UNIT 1 CYCLE 28 W(Z) FUNCTION Bumup (MWD/MTU)

Node Height

  1. (ft) 150 1000 2000 4000 6000 8000 31 6.0 1.0754 1.0750 1.0753 1.0790 1.0856 1.0937 32 6.2 1.0738 1.0728 1.0726 1.0761 1.0832 1.0919 33 6.4 1.0725 1.0707 1.0697 1.0726 1.0800 1.0893 34 6.6 1.0708 1.0689 1.0677 1.0704 1.0776 1.0867 35 6.8 1.0688 1.0670 1.0660 1.0686 1.0751 1.0834 36 7.0 1.0669 1.0654 1.0646 1.0669 1.0728 1.0803 37 7.2 1.0652 1.0640 1.0633 1.0659 1.0718 1.0793 38 7.4 1.0646 1.0634 1.0629 1.0661 1.0731 1.0816 39 7.6 1.0683 1.0670 1.0665 1.0696 1.0763 1.0844 40 7.8 1.0734 1.0721 1.0715 1.0740 1.0798 1.0869 41 8.0 1.0777 1.0764 1.0756 1.0776 1.0827 1.0890 42 8.2 1.0819 1.0805 1.0796 1.0810 1.0853 1.0906 43 8.4 1.0858 1.0844 1.0833 1.0841 1.0874 1.0917 44 8.6 1.0894 1.0879 1.0866 1.0868 1.0892 1.0924 45 8.8 1.0927 1.0910 1.0896 1.0890 1.0905 1.0927 46 9.0 1.0956 1.0939 1.0923 1.0912 1.0917 1.0930 47 9.2 1.0981 1.0966 1.0952 1.0937 1.0933 1.0939 48 9.4 1.1001 1.0988 1.0977 1.0967 1.0970 1.0981 49 9.6 1.1020 1.1008 1.0997 1.0992 1.1003 1.1021 50 9.8 1.1036 1.1024 1.1014 1.1013 1.1031 1.1055 51 10.0 1.1052 1.1036 1.1023 1.1025 1.1050 1.1085 52 10.2 1.1059 1.1042 1.1030 1.1037 1.1070 1.1112 53 10.4 1.1061 1.1061 1.1063 1.1083 1.1115 1.1149 54 10.6 1.1136 1.1127 1.1120 1.1125 1.1145 1.1172 55 10.8 1.1120 1.1107 1.1099 1.1108 1.1142 1.1182 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 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.

Page 17 of 19

D. C. COOK UNIT 1 CYCLE 28 Revision 0 TABLE 1 (continued)

DONALD C. COOK UNIT 1 CYCLE 28 W(Z) FUNCTION Bumup (MWD/MTU)

Node Height

  1. (ft) 10000 12000 14000 16000 16995 1 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 2 0.2 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.4 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.6 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.8 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.0 1.0000 1.0000 1.0000 1.0000 1.0000 7 1.2 1.1160 1.1227 1.1298 1.1369 1.1403 8 1.4 1.1153 1.1215 1.1280 1.1345 1.1376 9 1.6 1.1142 1.1198 1.1256 1.1314 1.1343 10 1.8 1.1126 1.1175 1.1226 1.1277 1.1302 11 2.0 1.1105 1.1147 1.1189 1.1232 1.1253 12 2.2 1.1080 1.1114 1.1147 1.1181 1.1198 13 2.4 1.1050 1.1076 1.1100 1.1125 1.1138 14 2.6 1.1016 1.1033 1.1048 1.1064 1.1072 15 2.8 1.0979 1.0988 1.0995 1.1003 1.1007 16 3.0 1.0940 1.0939 1.0937 1.0936 1.0935 17 3.2 1.0898 1.0890 1.0881 1.0872 1.0868 18 3.4 1.0861 1.0853 1.0849 1.0844 1.0841 19 3.6 1.0845 1.0852 1.0872 1.0888 1.0895 20 3.8 1.0846 1.0868 1.0909 1.0945 1.0962 21 4.0 1.0864 1.0898 1.0954 1.1004 1.1027 22 4.2 1.0894 1.0935 1.0997 1.1053 1.1079 23 4.4 1.0923 1.0971 1.1037 1.1099 1.1128 24 4.6 1.0949 1.1003 1.1074 1.1141 1.1172 25 4.8 1.0973 1.1032 1.110_6 1.1176 1.1210 26 5.0 1.0993 1.1057 1.1133 1.1206 1.1241 27 5.2 1.1009 1.1077 1.1154 1.1229 1.1265 28 5.4 1.1020 1.1091 1.1168 1.1244 1.1281 29 5.6 1.1026 1.1099 1.1174 1.1250 1.1288 30 5.8 1.1025 1.1099 1.1173 1.1248 1.1285 Top and bottom 10% of core excluded.

Page 18 of 19

D. C. COOK UNIT 1 CYCLE 28 Revision 0 TABLE 1 (continued)

DONALD C. COOK UNIT 1 CYCLE 28 W(Z) FUNCTION Bumup (MWD/MTU)

Node Height

  1. (ft) 10000 12000 14000 16000 16995 31 6.0 1.1018 1.1092 1.1164 1.1237 1.1273 32 6.2 1.1004 1.1077 1.1145 1.1216 1.1251 33 6.4 1.0983 1.1055 1.1118 1.1185 1.1218 34 6.6 1.0954 1.1023 1.1082 1.1145 1.1177 35 6.8 1.0914 1.0976 1.1029 1.1086 1.1115 36 7.0 1.0876 1.0935 1.0989 1.1045 1.1074 37 7.2 1.0867 1.0929 1.0987 1.1047 1.1077 38 7.4 1.0895 1.0954 1.1003 1.1055 1.1082 39 7.6 1.0918 1.0971 1.1012 1.1057 1.1080 40 7.8 1.0934 1.0980 1.1014 1.1052 1.1071 41 8.0 1.0946 1.0984 1.1010 1.1040 1.1056 42 8.2 1.0953 1.0982 1.1001 1.1023 1.1034 43 8.4 1.0954 1.0975 1.0986 1.1001 1.1009 44 8.6 1.0951 1.0964 1.0969 1.0976 1.0980 45 8.8 1.0944 1.0948 1.0943 1.0941 1.0941 46 9.0 1.0942 1.0945 1.0945 1.0946 1.0946 47 9.2 1.0951 1.0968 1.0993 1.1015 1.1026 48 9.4 1.0996 1.1014 1.1037 1.1059 1.1069 49 9.6 1.1041 1.1059 1.1077 1.1095 1.1104 50 9.8 1.1080 1.1098 1.1113 1.1129 1.1137 51 10.0 1.1116 1.1134 1.1145 1.1159 1.1166 52 10.2 1.1148 1.1165 1.1171 1.1180 1.1185 53 10.4 1.1175 1.1186 1.1186 1.1189 1.1192 54 10.6 1.1197 1.1215 1.1230 1.1247 1.1255 55 10.8 1.1214 1.1226 1.1226 1.1230 1.1233 56 11.0 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.2 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.4 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.6 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.8 1.0000 1.0000 1.0000 1.0000 1.0000 61 12.0 1.0000 1.0000 1.0000 1.0000 1.0000 Top and bottom 10% of core excluded.

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