AEP-NRC-2018-41, Core Operating Limits Report

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Core Operating Limits Report
ML18141A427
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 05/17/2018
From: Scarpello M
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2018-41
Download: ML18141A427 (21)
v • d • e


Text

m INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWER One Cook Place Bridgman, Ml 49106 A unit ofAmerican Electric Power lndianaMichiganPower.com May 17, 2018 AEP-NRC-2018-41 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 24 in accordance with Technical Specification 5.6.5. Revision O of the Unit 2 Cycle 24 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. Scarpell9 Regulatory Affairs Director MOS/mil

Enclosure:

Donald C. Cook Nuclear Plant Unit 2 Cycle 24 Core Operating Limits Report, Revision O c: R. J. Ancona - MPSC A W. Dietrich - Washington, DC.

MDEQ - RMD/RPS NRC Resident Inspector K. S. West- NRC, Region Ill A J. Williamson - AEP Ft. Wayne, w/o enclosures

\.

ENCLOSURE to AEP-NRC-2018-41 Donald C. Cook Nuclear Plant Unit 2 Cycle 24 Core Operating Limits Report Revision 0

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0

. Donald C. Cook Nuclear Plant.

.Unit 2 Cycle 24 Core Operating Limits Report Revision 0

  • Page 1 of 19

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 24 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~ Pov.:er 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 (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 Lff and Thermal Overtemperature -6.T Trip Functions, September 1986
g. WCAP-13749-P-A, Safety"Eva.Iua.tiori Supporting the Conditional Exeinptiori 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 SLs [Safety Limits]

3.1.1 SHUTDOWN MARGIN (SDM) 3 .1.3 . Moderator Temperature Coefficient (MTC)

3. l_.5 . Shutdowµ Bar:ik Insertiop Lirp.its 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) Iristrunientation 3.4.1 RCS [Reactor Coolant System] Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3 .9 .1 Bo~on Conce1.tration Page 2 of 19

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 2.0 OPERATING LIMITS The cyck-specific parameter _limit~ listed in_ Section l_.O ar~ presented in the f<_Jllo""'.ing subse~tion~.

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)

I;n M(?des _l an~ 2, the C(?mbii?-atiOJ?. of thermal pqwer,. pressuriz~r pn;ssure, an1 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 % Af<lk for Tavg > 200°F Shutdown margin shall be greater than or equal to 1.0% Lik/k for Ta~g :s; 200°F 2.2.2 Moderator Temperature Coefficient (MTC) (Specification 3 .1.3)

a. The MTC limits are:

The BOLiARO-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 aTavg 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 3 of 19

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0

b. The. MTC Surveillance limit .

is:

T~e 300 ppm/ARO/RTP-M!C should be less negatiye or equal to -3.20E-4 A~°F at a I:IFP vessel Tavg of 571.0 to 576.0 °F

c. _The Revised P~edicted n~ar-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 -OJOE-4 Ak/k/°F.

. If the Revised Predicted MIC is less negative than the Surveillance. Requirement (SR) .

3.1.3.2 limit (COLR 2.22.b) and all of the benclunark data contained in the surveillance procedure are met, then a MIC measurement in accordance with SR 3 .1.3 .2 is not required:

d. The MIC-Surveillance limit is:

The 60 ppm/ARO/RTP-MTC should be less negative or equal to -3.JOE-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 shut<:lown rod_s shall be withdrawn to at least 2_i_s 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 bumup

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

Page 4 of19

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 2J.2 _Heat Flux Hot Channel Factor (FQ(~)) (Specification 3.2.1)

Ff(Z)~ CFQ . *K(Z).

- p for P >0.5 Ff (Z) ~ 2

  • CFQ
  • K(Z) for P ~ 0.5 CF Fg' (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 = 2.335
b. K(Z) is provided in Figure 4
c. Yc!(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. Fij (Z) = F6 (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 Pis> 0.5. When Pis :S 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 5 of 19

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0

f. For Cycle 24, Fr~ 1.02 for all _bumups as*sociated with Note 2a of SR 3.2.1.2, except as .

shown in. -the table below.

When no penalty is. required, Fr=- 1.00.-

Cycle Burnup Fr (MWD/MTU) Penalty Multiplier 0 1.046 150 1.046 317 1.047 484

  • 1.048 65~ 1.048 818 1.048 985 1.046 1152 1.044 1319 1.042 1487 1.038 1654 1.035 1821 1.033 1988 1.030 2155 1.026 2322 1.022 2489 1.020 The bumup range covers where Fp exceeds 1.02. Linear interpolation is adequate for intermediate cycle bumups.

2.3 .3 Nuclear Enthalpy Rise Hot Channel Factor (FNm) (Specification 3.2.2)

~MI::; CFMI * (1 + PFMI *(1-P))

. . .THERMALPOWER .

Where: p = RATED THERMAL POWER

a. CFMI= 1.61
b. PFMI==0.3_
c. ~MI is the measured Enthalpy Rise Hot Channel Factor including a 4% measurement
  • uncertainty.

Page 6 of 19

  • DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 2.4 INSTRUMENTATION

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

2.5 REACTOR COOLANT SYSTEM

  • Pressure; Temperature, and Flow Departure* from Nucleate Boiling (DNB) Limits*

_(Specific8:tion ;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 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 con;entration of 2400 ppin includes a 50 ppni conservat1ve allowance for uncertainties.

- Page 7 of 19

  • * - * * - - 4 -
  • DONALD C. COOK UNIT 2 CYCLE 24 Revision 0

. FIGUREi

- MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 I ':)_NACQ~PTf'.BLE _QPE~TIO_N I 0.5

,,-=-,...

LL 0

~~

~

~

ro

+-'

"O a>

I 0.0 I ACCEPTABLE OPERATION I

"~

-.;I"

.1 ..

0

~

X t)

I-= -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 24 Revision 0 FIGURE_2 ROD *BANK INSERTION LIMITS VERSUS THERMAL POWER 250 225 I (52.9%, 228) 100 Step.Overlap - I V

200  : BANK c: _,...i I (100%, 189) I

/

.--.. 175 /

V

/

C

$ /

"O

.c

~

~

150 / /

~

Cl) 0..

Q) z .125

/'

H_ (0.°!o, ~ ?8)_ I /

V

.1. ..

0 i=

u5 I BANKO\/

V 0

Cl. /

Cl. 100 0

0:::

C) 0 0

75

/'

0:::

50

./ V ..

V 25 V

/

/

/ I co%. 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 24 Revision 0 FIGURE.3 AXIAL FLUX DIFFERENCE LIMIT§ A§ A* FUNCTION OF RATED THERMAL POWER (RTP}

  • 100 I c-1 "1,90) 1 I(+*1*1,90) I

[Q\ 90 0

'r' J UNACCEPTABLE OPERATION I/ \ I UNACCEPTABlE OPERATION L

>< 80 N

~ ~ 70 ~

I \ ~

so X

0 u..

u:

60 I ACCEPTABLE OPERATION \

0

~

0 50 J I/

I \ ~

a,.

I-=>

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

~ 40 E

s E 30

~

C 20

~

0 0~

10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 FLUX DIFFERENCE (DELTAal)

Page 10 of 19

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 FIGURE-4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 - ..

(0.0, 1.0) (8.425, 1.0) 1.0 (9 (12.0, 0.954) z S2 i1J 0.8 0...

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 11 of 19

DONALD C. COOKUNIT 2 CYCLE 24 Revision 0 FIGURES

- (Page 1 of-2)

Reactor Trip System Instrumentation Trip §etpoints Overtemperature AT Trip Setpoint .

1 + r1SJ Overtemperature .AT :5: .AT0 [K1 - K 2

[ l+r2S (T-T) + K 3 (P-P') -f1 (AI)]

\Vhere: AT = Measured RCS .AT, 0 P

.ATO = Indicated Lff at RATED THERMAL POWER,* 0 P T = Average temperature, 0 P T = Nominal Tavg at RATED THERMAL POWER, (S 576.0°P)

P = Pressurizer Pressure, psig P' = Nominal RCS operating pressure (2235 psig)

[ 1l ++ riS r2S J= The function generated by the lead-lag controller for Tav2

~

dynamic compensation 1: ; 1:

1 2

= Time constants utilized in the lead-lag controller for Tavg

,:1 ~ 28 secs. ,:2S 4 secs.

S = Laplace transf01m operator, sec- 1 K1 < 1.19

  • K2 > 0.01331/ P 0 K3 > 0.00058/psig f1 (AI) . = .-3.5 {33% + (cit - qb)} when*qt - <ih ~ -33% RTP .

0%ofRTP when -33% RTP < qt - qb S 6% RTP

+1.0 {(qt-qb)-6%} . when qt.:. qb > 6% RTP .

where q 1 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 of19

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 FIGURES (Page 2.of 2)

Overpower AT Trip Setpoint Where: AT = Measured RCS AT, 0 P ATo = Indicated AT at RATED THERMAL POWER, 0 P T = .A.verageteD1perature, 0 P T" = Nominal Tavg at RATED THERMAL POWER,(:::; 576.0 °F)

Ki < 1.16

  • Ks > 0.02/0 P for increasing average temperature; Ks = 0 for decreasing average temperature

~ > 0.00197/0 P for T greater than T" ; Kt;=O for T less than or equal to T" The function generated by the rate lag controller for Tavg dynaDJ.ic COD1pensation Time constant utilized in the rate lag controller for Tavg; 1: ~ 10 secs.

3 s Laplace transform operator, sec-1 f2 (Af) ~ 0.0

  • This is a Safety .A.nalysis 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 24 Revision 0

-*FIGURE_6

  • .Reactor-Core Safety Limits 660 r---:...._

650

---- --- -- UNACCt TABLE OPER TION 2400 F plA/"'

~

640

--- r--.... r--. ~

-- ~"'

2250 P 151A__.,,..

1""-

630 ~

r--._

-- r---

L 0

b 620

~~p SIA:--:"""

2000 F ~ ......

"~

0)

> ~

ffl 610 I r--.. ~

II=- ....._

"""'"\ '"

fl)

()

600 1775 P SIA.........

-......_ i\. "\."' '\.

a:= --........ r---..... 'I\.'\. '\

590

---....... '"'~*,

.'\.'\ "\. "

ACCEP ABLE 580 noco1 ITlnN --......"- '\ I'\. '\

'\.

570

'\

~- '

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 *ravg Power *ravg* 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' *o.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 UNIT 2 Reactor Core Safety Umits Page 14 of19

DONALD C. COOK UNIT 2. CYCLE 24 Revision 0 FIGURE 7

-2.34E-04

-2.36E-04 \

\

-2.38E-04 \

-~ -

.\i::
  • \

~ \

-2.40E-04 a;

'<3 le \

a -2.42E-04 \ --

~

isa;

- \

~

='

-2.44E-04 \

!~

~

, \

  • 0 * * > H ** .*

-~

~ -2.46E-04

\

-2.48E-04 \

\

-2.50E-04 \

\

-2.52E-04 15,000 16,000 17,000 18,000 19,000 Cyde Bunm1> tlv'IV\ID:MTU)

Burnuo <MWD/MTln MTC (ocm/°F) MTC (Ak/k/°F) 15000 -23.514 -2.3514E-04

  • 16000 -23.917 -2.3917E-04 17000 -24.325. -2.4325E-04

- 18000. ,-24.699 - -2.4699E-04..

1900_0 -2~.098 -2.5098E-04 Page 15 of 19 .

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 Table 1

-D. C. Cook Unit 2 Cycle 24 _

  • W(Z) Function Node Height Burnup (MWD/MTU)
  1. (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 *l.0000 1.0000 * *l.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 1.1113 1.1140 1.1167 1.1201 1.1197 1.1168 1.1154 8 1.4 1.1105 1.1124 1.1143 1.1168 1.1168 1.1151 1.1144 9 1.6 1.1094 1.1105 1.1117 1.1133 1.1137 1.1131 1.1131 10 1.8 1.1080 1.1084 1.1089 1.1098 1.1104 1.1109 1.1114 11 2.0 1.1062 1.1060 1.1058 1.1061 1.1069 1.1083 1.1092 12 2.2 1.1041 1.1034 1.1029 1.1026 1.1036 1.1056 1.1069 13 2.4 1.1017 1.1010 1.1005 1.1003 1.1013 1.1032 1.1044 14 2.6 1.0989 1.0989 1.0989 1.0993 1.1001 1.1012 1.1019 15 2.8 1.0959 1.0965 1.0971 1.0981 1.0987 1.0990 1.0991 16 3.0 1.0925 1.0937 1.0949 1.0965 1.0969 1.0963 1.0959 17 3.2 1.0893 1.0910 1.0927 1.0947 1.0948 1.0933 1.0923 18 3.4 1.0872 1.0891 1.0908 1.0929 1.0925 1.0902 1.0889 19 3.6 1.0860 1.0879 1.0897 1.0918 1.0911 1.0884 1.0869 20 3.8 1.0851 1.0872 1.0891 1.0914 1.0907 1.0879 1.0863 21 4.0 1.0852 1.0871 1.0890 1.0911 1.0906 1.0881 1.0867 22 4.2 1.0861 1.0875 1.0889 1.0906 1.0907 1.0894 . 1.0887

. 23. . 4.4 . 1.0865 1.0875. .1.0885 1.0901. .1.0907 1.0908. 1.0907 24 4.6 . 1.0869 1.0874 1.0880 1.0892 1.0905 1.0919 1.0926 25 4.8. "1.0871 1.0871 . "l.0872 1.0881. "l.0900 1.0927 . 1.0942 26 5.0 1.0872 1.0867 1.0863 1.0867 1.0892 1.0933 1.0954 27 5.2 1.0871 1.0860 1.0851 1.0851 1.0881 1.0935 1.0962 28 5.4 1.0867 1.0850 1.0837 1.0832 1.0867 1.0932* 1.0966 29* 5.6 1.0860 1.0838 1.0819 1.0810 1.0849 1.0925 1.0965 30 5.8 1.0850 1.0823 1.0800 1.0786 1.0828 1.0912

  • 1.0957 Top and bottom ].0% of core excluded.

Page 16 of 19

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 Table 1 (Continued)

D. C. Cook Unit 2 Cycle 24 W(Z) Function

  • Node Height Burnup (MWD/MTU)
  1. (ft) 150 1000 2000 4000 6000 8000 9000 31 6.0 1.0839 1.0806 1.0778 1.0758 1.0801 1.0893 1.0943 32 6.2 1.0824 1.0788 1.0755 1.0731 1.0774 1.0869 1.0922 33 6.4 1.0805 1.0769 1.0736 1.0711 1.0753 1.0846 1.0898 34 6.6 1.0782 1.0747 . 1.0715 1.0690 1.0729 1.0818 1.0868
  • 35 6.8* 1.0750
  • 1-.0717
  • l.0688 1.0664
  • 1.0698
  • 1.0778 L0825 36 7.0 1.0723 1.0690 1.0659 1.0636 1.0670 1.0752 1.0799 37 7.2 1.0724 1.0685 1.0649 1.0619 1.0655 1.0744 1.0796 38 7.4 1.0758 1.0710 1.0666 1.0625 1.0661 1.0759 1.0816 39 7.6 1.0788 1.0740 1.0697 1.0655 1.0689 1.0782 1.0836 40 7.8 1.0813 1.0769 1.0728 1.0689 1.0720 1.0804 1.0853 41 8.0 1.0835 1.0794 1.0756 1.0718 1.0744 1.0821 1.0865 42 8.2 1.0853 . 1.0815 1.0780 1.0744 1.0766 1.0834 1.0872 43 8.4 1.0867 1.0833 1.0801 1.0768 1.0785 1.0841 1.0874 44 8.6 1.0878 1.0848 1.0820 1.0789 1.0799 1.0842 1.0868 45 8.8 1.0880 1.0854 1.0830 1.0803 1.0814 1.0855 1.0880 46 9.0 1.0892 1.0864 1.0839 1.0814 1.0833 1.0886 1.0916 47 9.2 1.0928 1.0895 1.0864 1.0835 1.0859 1.0925 1.0962 48 9.4 1.0978 1.0942 1.0908 1.0875 1.0900 1.0969 1.1008 49 9.6 1.1026 1.0987 1.0951 1.0915 1.0939 1.1010 1.1049 50 9.8 1.1071 1.1030 1.0991 1.0951 1.0975 1.1047 1.1087 51 10.0 1.1114 1.1071 1.1030 1.0986 1.1008 1.1080 1.1121 52 10:2 1.1154 1.1108 1.1065 1.1018 1.1038 1.1109 1.1150
53. 10.4 1.1189. .1.1142 1.1097 1,1047 1.10!54 l.1_134 1.1174 54 10.6 1.1219 1.1170 1.1123 1.1070 1.1085 1.1152 1.1190 55 10.8 1.1243 1.1192 1.1143. 1.1088 1.1103 . 1.1172 "l.1212 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 a~d bottom 10% of c~re ex~Iuded.*
  • Page 17 of 19 -

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 Table 1 (Continued)

D. C .. Cook Unit 2 Cycle i4 W(Z) Function*

Node Height Burnup (MWD/MTU)

  1. (ft) 10000 12000 14000 16000 18000 20000 21470 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 * *l.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 1.1147 1.1162 1.1212 1.1289 1.1391 1.1472 1.1520 8 1.4 1.1142 1.1163 1.1210 1.1280 1.1369 1.1442 1.1486 9 1.6 1.1134 1.1159 1.1203 1.1265 1.1342 1.1406 1.1446 10 1.8 1.1121 1.1149 1.1190 1.1242 1.1306 1.1361 1.1396 11 2.0 1.1104 1.1133 1.1169 1.1212 1.1263 1.1308 1.1338 12 2.2 1.1082 1.1111 1.1142 1.1176 1.1213 1.1248 1.1273 13 2.4 1.1056 1.1080 1.1104 1.1129 1.1155 1.1181 1.1200 14 2.6 1.1026 1.1041 1.1056 1.1073 1.1091 1.1108 1.1120 15 2.8 1.0992 1.0997 1.1004 1.1013 1.1023 1.1031 1.1037 16 3.0 1.0954 1.0948 1.0945 1.0944 1.0944 1.0942 1.0940 17 3.2 1.0913 1.0899 1.0890 1.0883 1.0879 1.0872 1.0865 18 3.4 1.0877 1.0861 1.0855 1.0856 1.0862 1.0862 1.0860 19 3.6 1.0857 1.0844 1.0846 1.0859 1.0881 1.0895 1.0901 20 3.8 1.0851 1.0841 1.0850 1.0872 1.0905 1.0927 1.0938 21 4.0 1.0857 1.0851 1.0863 1.0889 1.0925 1.0952 1.0965 22 4.2 1.0882 1.0883 1.0896 1.0918 1.0948 1.0971 1.0985

.23 .4.4. l.0~08 1.0916 1.0929 1.0947 1.0970 1.0988 1.1000 24 4.6 1.0933 1.0947 1.0960 1.0974 L0988 1.1001 1.1011 25 4.8 1.0955 1.0975 . 1.0989 1.0997 . 1.1002 1.1011" 1.1019 26 5.0 1.0973 1.0999 1.1013 1.1017 1.1013 1.1016 1.1022 27 5.2 1.0987 1.1020 1.1033 1.1032 1.1019 1.1017 1.1021 28 5.4 1.0996 1.1034 1.1048 1.1042 1.1020 1.1013 1.1015 29 5.6 1.1000 1.1044 1.1058 1.1050 1.1022 1.1013 1.1014 30 5.8 1.0997 1.1050 1.1071 1.1068 1.1046 1.1042 1.1049 Top and bottom 10% of core excluded.

  • Page 18 of 19

DONALD C. COOK UNIT 2 CYCLE 24 Revision 0 Table 1 (Continued)

D_. C. ~ook_Unit_2 C~cle_2_4 W(Z) Fmictiori

  • Node Height . -. Bumup (MWD/MTU)-
  1. (ft) 10000 12000 141000 16000 18000 20000 21470 31 6.0 1.0988 1.105-1 1.1082 1.1090 1.1080 1.1089 1.1103 32 6.2 1.0971 1.1041 1.1081 1.1099 1.1100 1.1119 1.1141 33 6.4 1.0947 1.1021 1.1069 1.1097 1.1113 1.1142 1.1171 34 6.6 'l.0916 1.0993. 1.1047 1.1087 . 1.1116 1.1157 . 1.1193 35 6.8 .-
  • l.0871 1.0948
  • l.1010 1.-1062* *l.1110 1.1165*
  • 1.1208 36 7.0 1.0846 1.0926 1.0991 1.1047 1.1099 1.1158 1.1204 37 7.2 1.0846 1.0928 1.0992 1.1043 1.1087 1.1140 1.1184 38 7.4 1.0869 1.0953 1.1010 1.1050 1.1078 1.1120 1.1156 39 7.6 1.0887 1.0964 1.1015 1.1046 1.1065 1.1099 1.1130 40 7.8 1.0899 1.0967 1.1010 1.1034 1.1047 1.1073 1.1099 41 8.0 1.0906 1.0965 1.1000 1.1016 1.1020 1.1038 1.1057 42 8.2 1.0908 1.0957 1.0984 1.0993 1.0990 1.1000 1.1014 43 8.4 1.0904 1.0946 1.0968 1.0975 1.0972 1.0980 1.0991 44 8.6 1.0892 1.0929 1.0953 1.0967 1.0977 1.0993 1.1008 45 8.8 1.0903 1.0938 1.0961 1.0976 -1.0986 1.1003 1.1017 46 9.0 . 1.0943 1,0981 1.1000 1.1005 1.1000 1.1.0Q~ 1.1014 47 9.2 1.0994 1.1036 1.1049 1.1043 1.1021 1.1015 1.1017 48 9.4 1.1041 1.1080 1.1088 1.1072 1.1038 1.1022 1.1019 49 9.6 1.1083 1.1122 1.1129 1.1110 1.1071 1.1052 1.1047 50 9.8 1.1122 1.1163 1.1170 1.1151 1.1113 1.1095 1.1091 51 10.0 1.1156 1.1197 1.1205 1.1189 1.1153 1.1136 1.1133 52 10.2 1.1185 1.1226 1.1235 1.122_0 1.1186 1.1170 1.1168 53 10.4 1.1209 1.1250 1.1260 1.1245 1.1213 1.1199 1.1197 54 10.6 1.1224 1.1265 1.1275 1.1263 1.1233 1.1220 1.1220
  • 55 10.8 1.1248 *1.1289 1.1298 -1.1283 1.1250. 1.1235 1.1233 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 b*ottom 10% of core excluded.

Page 19 of19

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