AEP-NRC-2016-94, Core Operating Limits Report

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Core Operating Limits Report
ML16347A661
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 12/08/2016
From: Scarpello M
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2016-94
Download: ML16347A661 (21)
v • d • e


Text

m IN DIANA MICHIGAN POWER A unit of American Electric Power December 8, 2016 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 Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 lndianaMichiganPower.com AEP-NRC-2016-94 10 CFR 50.4 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 23 in accordance with Technical Specification 5.6.5. Revision 0 of the Unit 2 Cycle 23 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.

~~

Michael K. Scarpello Regulatory Affairs Manager DMB/rdw

Enclosure:

Donald C. Cook Nuclear Plant Unit 2 Cycle 23 Core Operating Limits Report, Revision 0 c:

R. J. Ancona, MPSC A. W. Dietrich, NRC, Washington, D.C.

  • MDEQ - RMD/RPS NRC Resident Inspector C. D. Pederson, NRC, Region Ill A. J. Williamson, AEP Ft. Wayne, w/o enclosures ol D

f N~r<--

ENCLOSURE TO AEP-NRC-2016-94 Donald C. Cook Nuclear Plant Unit 2 Cycle 23 Core Operating Limits Report Revision O

D. C. COOK UNIT 2 CYCLE 23 Donald C. Cook Nuclear Plant Unit 2 Cycle 23 Core Operating Limits Report Revision 0 Page I of 19 Revision 0

D. C. COOK UNIT 2 CYCLE 23 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 23 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.

IA, Relaxation of Constant Axial Offset Contrdl/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 ~T and Thermal Overtemperature ~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 SLs [Safety Limits]

3.1.1 SHUTDOWN MARGIN (SDM) 3.1.3 Moderator Temperature Coefficient (MTC) 3.1.5 Shutdown Bank fusertion Limits 3.1.6 Control Bank fusertion Limits 3.2.1 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) fustrumentation 3.4.1 RCS [Reactor Coolant System] Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3.9.1 Boron Concentration Page 2of19

D. C. COOK UNIT 2 CYCLE 23 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 2.1.1 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 (TavJ 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% Afdk 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.lOE-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 3of19

D. C. COOK UNIT 2 CYCLE 23 Revision 0

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 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 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 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 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 bumup

~0.0 MWD/MTU [Megawatt Days/Metric Ton Uranium].

Page 4of19

D. C. COOK UNIT 2 CYCLE 23 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)

CF F~ (Z) s __

Q

  • K(Z) p Fi (Z) s 2
  • CFQ
  • K(Z)

CF F; (Z) s _Q

  • K(Z) p for P > 0.5 for P s 0.5 for P > 0.5 for Ps0.5 THERMAL POWER Where:

p = RATED THERMAL POWER

a. CFQ

= 2.335

b. K(Z) is provided in Figure 4 Revision 0
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.
e.

F°3' (Z) = F6 (Z) x W(Z) x Fr 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.

Page 5of19

D. C. COOK UNIT 2 CYCLE 23 Revision 0

f.

For Cycle 23, 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, F p = 1.00.

Cycle Burnap Fp (MWD/MTU)

Penalty Multiplier 484 1.0200 651 1.0309 818 1.0442 985 1.0546 1152 1.0547 1319 1.0520 1486 1.0479 1652 1.0432 1819 1.0389 1986 1.0351 2153 1.0319 2320 1.0290 2487 1.0257 2654 1.0228 2821 1.0202 2988 1.0200 6494 1.0200 6661 1.0207 6828 1.0218 6995 1.0250 7161 1.0263 7328 1.0247 7495 1.0228 7662 1.0212 7829 1.0200 The bumup range only covers where Fp exceeds 1.02. Linear interpolation is adequate for intermediate cycle bumups.

Page 6of19

D. C. COOK UNIT 2 CYCLE 23 Revision 0 2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (FN MI) (Specification 3.2.2)

FNMI~ CFMI * (1 + PFMI *(1-P))

THERMAL POWER Where:

p = RATED THERMAL POWER

a.

CFMI=l.61

b. PFMI= 0.3
c.

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

2.4 INSTRUMENTATION 2.4.1 Reactor Trip System (RTS) fustrumentation (Specification 3.3.1)

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

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 Tavg 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 T avg, and 2200 psig for Pressurizer Pressure.

++This concentration bounds the condition of Keir:=:: 0.95 which includes a 1 % dk/k conservative allowance for uncertainties. The boron concentration of 2400 ppm includes a 50 ppm conservative allowance for uncertainties.

Page 7of19

D. C. COOK UNIT 2 CYCLE 23 Revision 0 FIGUREl MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 I UNACCEPTABLE OPERATION I 0.5 LL 0

I'\\ '

~

~

I ro

-+-'

Q) 0.0

"'O I ACCEPTABLE OPERATION I

'¢'

I 0

~

(.)

I-

-0.5

~

-1.0 0

10 20 30 40 50 60 70 80 90 100 Percent Rated Thermal Power Page 8of19

D. C. COOK UNIT 2 CYCLE 23 Revision 0 FIGURE2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250

/

I (52.9%, 228) 100 Step Overlap I I BANKC 1

~

I If 225 200 c

175 ro L..

-0

~ 150 Cf) 0..

Q)

+-'

~

z 125 0

E CJ) 0 v

I c100%, 189) I

/

/

/

v

~

/

/

/ /

H co%. 128)

I I

/

I BANK DI/

Cl.

100 Cl.

J 0

0::

(9 0

75 0

0::

./

/~

/

50

/

/ v

/

v 25 0 /I co%,o) I 0

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

Page 9of19

D. C. COOK UNIT 2 CYCLE 23 Revision 0 FIGURE3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 I c-1 *1.90) I 1 (+1 *1.90) I (0\\

90 0

'or-80 N -

I UNACCEPTABLE

\\ I UNACCEPTABLE L OPERATION OPERATION I

\\

~ N 70

>< 5o u.:

j I

\\

I ACCEPTABLE I OPERATION I

I

\\

~

LL.

60

(..)

~

50 0

I (-3'1,50) I I (+3*1.so) a..

I-

~

40 E

I E 30 c: *-2 20 0

~

0 10 0 -50

-40

-30

-20

-10 0

10 20 30 40 50 FLUX DIFFERENCE (DELTA-I)

Page 10of19

D. C. COOK UNIT 2 CYCLE 23 Revision 0 FIGURE4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT (9

z sz 1.2 1.0 L5 0.8 Cl..

0 w N

i

<(

~ 0.6 0 z 0.4 0.2 0.0 (0.0, 1.0) 0 2

(8.425, 1.0)

(12.0, 0.954) 4 6

8 10 12 CORE HEIGHT (FT)

Page 11 of 19

D. C. COOK UNIT 2 CYCLE 23 FIGURES (Page 1 of2)

Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint

[

I +r1S]

Overtemperature AT~ AT [K1 - K2 (T-T) + K3 (P-.P') -f1 (M)]

0 I+ r2S Where:

AT ATo T

r' p

p' Measured RCS AT, 0 P Indicated AT at RATED THERMAL POWER, 0P Average temperature, 0P Nominal Tavg at RATED THERMAL POWER, (S: 576.0°P)

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

Revision 0

[ l+riS]

l+r2S The function generated by the lead-lag controller for Tavg dynamic compensation

't1, t 2 Time constants utilized in the lead-lag controller for Tavg t 1 2: 28 secs. t 2 :::; 4 secs.

S Laplace transform operator, sec-1 K1 1.19

  • K2

> 0.01331/

0P K3 0.00058/psig

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

0%ofRTP

+1.0 {(qt-qb)-6%}

when qt - qb::::; -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 12of19

D. C. COOK UNIT 2 CYCLE 23 Revision 0 Where:

AT ATo T

T" Ki Ks K<;

s FIGURES (Page 2 of2)

Overpower AT Trip Setpoint

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

1+ r,S 6

2 Measured RCS AT, °F Indicated AT at RATED TIIERMAL POWER, °F Average temperature, °F Nominal Tavg at RATED THERMAL POWER, (:S 576.0 °F) 1.16

  • 0.021°F for increasing average temperature; Ks= 0 for decreasing average temperature 0.00197 /°F for T greater than T ; K<;=O 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; 't3 2'.: 10 secs.

Laplace transform operator, sec-1 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 13of19

D. C. COOK UNIT 2 CYCLE 23 LL 0 -

C>

co I I-en u

a:::

660 -----

650 -----

640 ---- ----

630 --

~...___

620 610 600 590 580 570 560 FIGURE6 Reactor Core Safety Limits

--r--__

UNACCt OPER 2400 F SIA_............ ---- ~

i--.._

2250 p >IA

~-

I"

--..... ~OP SIA_.,.-...___

~-

--I---_

2000 F r--.......

1775 p SIA_.... -............._

-......._ r--_

"'TABLE

~TION

~"' ""

'\\

r--_

~..........._

ACCEP ABLE

,... ~

r--.."-

r--..""" '

""\\ \\. "\\

', '\\ '\\

~'\\

'\\

I\\. '\\

550 0

0.2 0.4 0.6 0.8 1

Power (fraction of rated thermal power)

DESCRIPTION OF SAFETY LIMITS PRESSURE Power Tavg Power Tavg Power Tavg Power (psia)

(frac)

(' F)

(frac)

(' F)

(frac)

(' F)

(frac) 1775 0.00 615.4 0.98 583.8 1.02 580.9 1.2 2000 0.00 631.8 0.86 605.8 0.96 597.5 1.2 2100 0.00 639.1 0.82 614.0 0.96 601.6 1.2 2250 0.00 649.2 0.72 628.6 0.98 605.2 1.2 2400 0.00 659.0 0.62 642.0 1.1 599.0 1.2 UNIT2 Reactor Core Safety Limits Page 14of19 Revision 0

~

~~

"' '\\

I'\\. '\\

I\\. I\\.

I\\.'

I\\. '

I\\.

1.2 Tavg

(' F) 558.1 568.5 573.1 580.4 588.1

D. C. COOK UNIT 2 CYCLE 23 Revision 0 FIGURE7 Unit 2 Cycle 23 Predicted HFP ARO 300 PPM MTC Versus Burnup LL"

~

-2.36E-04

-2.38E-04

-2.40E-04

~ -2.42E-04 c

Q)

  • c:;

~ -2.44E-04 0

(.)

..... ~

Q) -2.46E-04 c..

E Q)

I-...

.S -2.48E-04

~

Q)

"C 0

!iE

-2.SOE-04

-2.52E-04

-2.54E-04

\\

-2.56E-04 13,000

\\

\\ '\\

'I

"' 'I\\.

'I'\\

14,000 15,000 16,000 17,000 Cycle Burnup (MWD/MTU)

Burnup (MWD/MTU)

MTC (pcml°F)

MTC (Ak/k/°F) 13000

-23.799

-2.3799E-04 14000

-24.212

-2.4212E-04 15000

-24.639

-2.4639E-04 16000

-25.034

-2.5034E-04 17000

-25.415

-2.5415E-04 Page 15of19

D. C. COOK UNIT 2 CYCLE 23 Revision 0 Table 1 D. C. Cook Unit 2 Cycle 23 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 1.1230 1.1178 1.1128 1.1072 1.1083 1.1139 1.1175 8

1.4 1.1214 1.1167 1.1122 1.1072 1.1084 1.1136 1.1168 9

1.6 1.1194 1.1153 1.1114 1.1071 1.1082 1.1129 1.1158 10 1.8 1.1169 1.1134 1.1101 1.1066 1.1077 1.1118 1.1143 11 2.0 1.1139 1.1112 1.1085 1.1058 1.1068 1.1102 1.1123 12 2.2 1.1106 1.1086 1.1067 1.1047 1.1055 1.1082 1.1099 13 2.4 1.1070 1.1057 1.1045 1.1033 1.1040 1.1058 1.1070 14 2.6 1.1031 1.1025 1.1020 1.1016 1.1020 1.1031 1.1038 15 2.8 1.0989 1.0991 1.0993 1.0996 1.0998 1.0999 1.1000 16 3.0 1.0944 1.0953 1.0963 1.0974 1.0973 1.0966 1.0962 17 3.2 1.0898 1.0914 1.0929 1.0947 1.0945 1.0930 1.0922 18 3.4 1.0867 1.0885 1.0903 1.0922 1.0914 1.0893 1.0881 19 3.6 1.0871 1.0887 1.0903 1.0917 1.0904 1.0877 1.0865 20 3.8 1.0886 1.0897 1.0908 1.0916 1.0902 1.0880 1.0871 21 4.0 1.0906 1.0910 1.0914 1.0915 1.0906 1.0895 1.0893 22 4.2 1.0924 1.0920 1.0917 1.0911 1.0907 1.0908 1.0912 23 4.4 1.0941 1.0929 1.0918 1.0906 1.0907 1.0919 1.0929 24 4.6 1.0955 1.0936 1.0918 1.0899 1.0905 1.0929 1.0945 25 4.8 1.0967 1.0941 1.0917 1.0892 1.0903 1.0936 1.0958 26 5.0 1.0975 1.0945 1.0917 1.0888 1.0902 1.0943 1.0968 27 5.2 1.0981 1.0947 1.0915 1.0883 1.0900 1.0947 1.0976 28 5.4 1.0983 1.0946 1.0911 1.0876 1.0896 1.0948 1.0979 29 5.6 1.0981 1.0942 1.0904 1.0867 1.0886 1.0942 1.0976 30 5.8 1.0975 1.0933 1.0894 1.0854 1.0872 1.0930 1.0967 Top and bottom 10% of core. excluded.

Page 16of19

D. C. COOK UNIT 2 CYCLE 23 Node 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 Height (ft) 6.0 6.2 6.4 6.6 6.8 7.0 7.2 7.4 7.6 7.8 8.0 8.2 8.4 8.6 8.8 9.0 9.2 9.4 9.6 9.8 10.0 10.2 10.4 10.6 10.8 11.0 11.2 11.4 11.6 11.8 12.0 150 1.0964 1.0948 1.0927 1.0900 1.0867 1.0829 1.0813 1.0848 1.0877 1.0899 1.0918 1.0933 1.0951 1.0966 1.0977 1.0983 1.0983 1.0977 1.0994 1.1037 1.1085 1.1128 1.1167 1.1200 1.1227 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Top and bottom 10% of core excluded.

Table 1 (Continued)

D. C. Cook Unit 2 Cycle 23 W(Z) Function Burnup (MWD/MTU) 1000 2000 4000 6000 1.0922 1.0908 1.0888 1.0860 1.0826 1.0788 1.0764 1.0774 1.0806 1.0840 1.0870 1.0898 1.0926 1.0951 1.0973 1.0989 1.1000 1.1005 1.1022 1.1055 1.1090 1.1120 1.1156 1.1193 1.1206 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0882 1.0842 1.0859 1.0870 1.0851 1.0824 1.0790 1.0753 1.0721 1.0707 1.0741 1.0787 1.0827 1.0866 1.0903 1.0939 1.0969 1.0996 1.1017 1.1032 1.1048 1.1073 1.1095 1.1112 1.1145 1.1186 1.1184 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Page 17of19 1.0830 1.0813 1.0793 1.0765 1.0736 1.0699 1.0658 1.0690 1.0746 1.0797 1.0847 1.0893 1.0935 1.0974 1.1007 1.1036 1.1058 1.1075 1.1091 1.1099 1.1103 1.1132 1.1177 1.1159 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0844 1.0829 1.0823 1.0815 1.0802 1.0777 1.0742 1.0765 1.0813 1.0858 1.0900 1.0937 1.0969 1.0996 1.1017 1.1029 1.1039 1.1059 1.1082 1.1094 1.1102 1.1130 1.1172 1.1159 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 8000 1.0917 1.0898 1.0883 1.0897 1.0911 1.0917 1.0913 1.0899 1.0908 1.0936 1.0966 1.0990 1.1007 1.1019 1.1025 1.1024 1.1010 1.0998 1.1023 1.1061 1.1086 1.1109 1.1139 1.1173 1.1177 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Revision 0 9000 1.0954 1.0935 1.0920 1.0942 1.0966 1.0979 1.0985 1.0981 1.0983 1.1000 1.1022 1.1035 1.1042 1.1042 1.1037 1.1025 1.1001 1.0980 1.1007 1.1052 1.1085 1.1116 1.1148 1.1177 1.1190 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

D. C. COOK UNIT 2 CYCLE 23 Revision 0 Table 1 (Continued)

D. C. Cook Unit 2 Cycle 23 W(Z) Function Node Height Burnup (MWD/MTU)

(ft) 10000 12000 14000 16000 18000 20119 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 1.1211 1.1278 1.1343 1.1414 1.1485 1.1557 8

1.4 1.1202 1.1264 1.1324 1.1389 1.1454 1.1521 9

1.6 1.1188 1.1244 1.1298 1.1357 1.1416 1.1476 10 1.8 1.1169 1.1218 1.1266 1.1318 1.1370 1.1423 11 2.0 1.1145 1.1187 1.1228 1.1272 1.1316 1.1361 12 2.2 1.1116 1.1150 1.1183 1.1219 1.1256 1.1293 13 2.4 1.1083 1.1108 1.1133 1.1162 1.1189 1.1218 14 2.6 1.1045 1.1060 1.1078 1.1097 1.1116 1.1135 15 2.8 1.1002 1.1008 1.1017 1.1029 1.1039 1.1049 16 3.0 1.0958 1.0954 1.0953 1.0953 1.0952 1.0950 17 3.2 1.0914 1.0902 1.0894 1.0888 1.0880 1.0871 18 3.4 1.0872 1.0862 1.0863 1.0869 1.0871 1.0871 19 3.6 1.0857 1.0857 1.0875 1.0905 1.0928 1.0947 20 3.8 1.0867 1.0876 1.0904 1.0948 1.0983 1.1014 21 4.0 1.0894 1.0910 1.0942 1.0988 1.1026 1.1061 22 4.2 1.0918 1.0942 1.0979 1.1026 1.1068 1.1107 23 4.4 1.0941 1.0972 1.1012 1.1060 1.1105 1.1148 24 4.6 1.0962 1.1000 1.1042 1.1090 1.1137 1.1183 25 4.8 1.0980 1.1023 1.1067 1.1115 1.1163 1.1211 26 5.0 1.0994 1.1041 1.1087 1.1135 1.1184 1.1235 27 5.2 1.1004 1.1054 1.1099 1.1146 1.1194 1.1245 28 5.4 1.1010 1.1062 1.1108 1.1153 1.1201 1.1252 29 5.6 1.1010 1.1073 1.1133 1.1197 1.1261 1.1328 30 5.8 1.1005 1.1079 1.1155 1.1239 1.1321 1.1405 Top and bottom 10% of core excluded.

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D. C. COOK UNIT 2 CYCLE 23 Revision 0 Table 1 (Continued)

D. C. Cook Unit 2 Cycle 23 W(Z) Function Node Height Burnup (MWD/MTU)

(ft) 10000 12000 14000 16000 18000 20119 31 6.0 1.0994 1.1076 1.1165 1.1266 1.1364 1.1462 32 6.2 1.0975 1.1064 1.1166 1.1284 1.1396 1.1508 33 6.4 1.0962 1.1056 1.1165 1.1293 1.1414 1.1533 34 6.6 1.0990 1.1086 1.1187 1.1299 1.1409 1.1520 35 6.8 1.1020 1.1118 1.1207 1.1296 1.1389 1.1487 36 7.0 1.1038 1.1135 1.1212 1.1281 1.1358 1.1443 37 7.2 1.1050 1.1147 1.1211 1.1256 1.1316 1.1386 38 7.4 1.1054 1.1151 1.1200 1.1221 1.1262 1.1317 39 7.6 1.1048 1.1130 1.1163 1.1167 1.1192 1.1231 40 7.8 1.1055 1.1121 1.1143 1.1138 1.1152 1.1177 41 8.0 1.1069 1.1122 1.1135 1.1123 1.1127 1.1143 42 8.2 1.1072 1.1111 1.1115 1.1095 1.1090 1.1094 43 8.4 1.1069 1.1096 1.1091 1.1066 1.1054 1.1049 44 8.6 1.1060 1.1074 1.1063 1.1035 1.1017 1.1006 45 8.8 1.1045 1.1043 1.1022 1.0986 1.0959 1.0936 46 9.0 1.1024 1.1015 1.0997 1.0973 1.0952 1.0933 47 9.2 1.0994 1.0992 1.1003 1.1021 1.1034 1.1045 48 9.4 1.0968 1.0972 1.1005 1.1059 1.1100 1.1135 49 9.6 1.0997 1.1004 1.1041 1.1099 1.1144 1.1183 50 9.8 1.1048 1.1061 1.1095 1.1145 1.1186 1.1222 51 10.0 1.1088 1.1108 1.1143 1.1191 1.1232 1.1270 52 10.2 1.1126 1.1152 1.1188 1.1234 1.1275 1.1314 53 10.4 1.1158 1.1186 1.1223 1.1269 1.1310 1.1351 54 10.6 1.1184 1.1209 1.1246 1.1295 1.1338 1.1379 55 10.8 1.1205 1.1237 1.1274 1.1318 1.1359 1.1400 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.

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