AEP-NRC-2019-58, Core Operating Limits Report, Revision 0
| ML19326A166 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/20/2019 |
| From: | Scarpello M Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP-NRC-2019-58 | |
| Download: ML19326A166 (21) | |
Text
m INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POtNE1f* One Cook Place Bndgman, Ml 49106 A umt ofAmerican El9Ctnc Power lnd1anaM1ch1ganPower com November 20, 2019 AEP-NRC-2019-58 10 CFR 50.4 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 Company, the licensee for Donald C. Cook Nuclear Plant Unit 2, is submitting the Core Operating Limits Report (COLR) for Unit 2 Cycle 25 in accordance with Technical Specification 5.6.5. Revision O of the Unit 2 Cycle 25 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, Michael K. Scarpello Regulatory Affairs Director DLW, JMT/kmh
Enclosure:
Donald C. Cook Nuclear Plant Unit 2 Cycle 25 Core Operating Limits Report, Revision 0 c: R. J. Ancona - MPSC EGLE - RMD/RPS R. F. Kuntz - NRC Washington, DC NRC Resident Inspector D. J. Roberts, NRC Region Ill A. J. Williamson - AEP Ft. Wayne, w/o enclosures
ENCLOSURE TO AEP-NRC-2019-58 Donald C. Cook Nuclear Plant Unit 2 Cycle 25 Core Operating Limits Report Revision 0
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 Donald C. Cook Nuclear Plant Unit 2 Cycle 25 Core Operating Limits Report Revision 0 Page 1 of19
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 25 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The analytical methods used to determine the core opera~g 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, Po'Yer Distribution C0ntrol and Load Following Procedures - Topical Report, September 1974
- c. WCAP-10216-P-A, Rev. IA, 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 O (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 dT and Thermal Overtemperature d T Trip Functions, September 19~6
- 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 SLs [Safety Limits]
3 .1. i 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 (FN,m) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reactor Trip System (RTS) Instrumentation 3.4.1 RCS [Reactor Coolant Sy~em] Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3 .9 .1 Boron Concentration Page 2 of 19
(
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 2.0 OPERATING LIMITS The cycle-specific parameter limits listed in Secti~n 1.0 are presented in the following subsectio{!S. 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, ~e combination of thermal power, pressurizer presSllly, and the highest loop average temperature (f.vs) shall not exceed the limits as shown in Figure 6 for 4 loop operation.
,-~
2.2 REACTIVTIY CONTROL 2.2.1 SHUTDOWN MARGIN (SDM) (Specification 3.1.1)
Shutdown margin shall be greater than or equal to 1.3% ~ for Tavg > 200°F Shutdo,wn margin shall be greater than or equal to 1.0% Mc/k for Tavg s 200°F 2.2.2 Moderator Temperature Coefficient (MTC) (Specification 3.1.3)
- a. The MTC limits are:
The BOUARO-MTC shall be less positive or equal to the value given in Figure 1.
The EOUAROIRTP-MTC shall be less negative or equal to -4.lOE-4 Aklkl°F.
This limit is based on a T.TK program with HFP vessel T.VK 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 25 Revision 0
- b. The MTC Surveillance limit is:
The 300 ppm/ARO/RTP-MTC should be less negative or equal to -3.20E-4 L\k/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 L\k/k/°F.
If the Revised Predicted MTC is less negative tl).an 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 burnup ~0.0 MWD/MTU
[Megawatt Days/Metric Ton Uranium].
Page 4 of 19
DONALD C. COOK UNIT 2 CYCLE 25 Revision O*
2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)
CF Fg (Z) ~ _ Q
- K(Z) for P > 0.5 p
Fg (Z) s 2
- CFQ
- K(Z) for P s0.5 CF pw (Z) s _ Q
- K(Z) for P > 0.5 Q p F; (Z) s 2
- CFQ
- K(Z) for P ~ 0.5 THERMALPOWER Where: p = RATED THERMAL*POWER
- a. CFQ = 2.335
- 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.
- e. F3' (Z) = Ft (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 perforrped, 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 25 Revision 0
- f. For Cycle 25, 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.
Fp Cycle Burnup Penalty Multiplier (MWD/MTU) 150 1.022 317 1.033 484 1.040 652 1.038 819 1.038 986 1.037 1153 1.035 1321 1.034 1488 1.034 1655 1.034 1822 1.035 1989 1.037 2157 1.040 2324 1.042 2491 1.044 2658 1.045 -
2826 1.045 2993 1.045 3160 1.043 3327 1.039 3495 1.033 3662 1.027 3829 1.021 3996 1.020 The burnup 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 (FNm) (Specification 3.2.2)
~MI:.:; CFm * (1 + PFm *(1-P))
J
- Page 6 of19
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 THERMAL POWER Where: p = RATED THERMAL POWER
- a. CFAH= 1.61
- b. PFAH = 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 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 Tav&,
and 2200 psig for Pressurizer PresslJ!e.
++ This concentration bounds the condition of~.::: 0.95 which includes a 1% Afc/k conservative allowance for uncertainties. The boron concentration of 2400 ppm includes a 50 ppm conservative allowan~ for uncertainties.
Page 7 of 19
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 FIGUREl MODERATOR TEIVIPERATURE COEFFICIENT (MTC) LIMITS 1.0 '
I I UNACCEPTABLE OPERATION I 0.5
-LL 0
~ "'
~
r I '
co
+-'
Q) 0.0
'U I ACCEPTABLE OPERATION I
-.:r- )
0
~
0
- 1- -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 25 Revision 0 FIGURE2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250 I - -
I 225 I
V I (52.9%, 228) 100 Step Overlap 200 : BANKC:/..-
I c100%,, 189)1 V
~
175
/ '
/
/
~ /
"C
~ 150 / /
/' 7 I
[
.....Q)
~
z . 125 Fl (0%, 128) I /
V I
0 E
Cl) 0 I BANK DI/
0.
- 0. 100 , ./
V
- )
0 0:::
(9 0 i 75 V
0 0:::
50 /
V 25 V
/ '
/
0 VI (0%, 0) I 0 10 20 30 40 50 60 70 80 90 100 POWER (% of Rated Thermal Pawer)
Page 9 of 19
, DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 FIGURE3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER(RTP) 100
- I <-11.00> 1- 1 c+11,oo> 1 90
/0\ Q
~
>< 80 -
UNACCEPTABLE OPERATION I \ I UNACCEPTABLE OPERATION 70 .,j I \.
LL 60 I II ACCEPTABLE OPERATION, \
(.)
0::
0 60 .J I \. , L
- a. '
f-'
I c-31,so> 1 ' 1 (+31,50)
~ 40 E
30
--E C -
- E 20 0
?f;.
,10 I
0
-60 -40 -30 -20 -10 0 10 20 30 40 60 FLUX DIFFERENCE (DELTA-I}
Page 10 of19
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 FIGURE4
~(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 (0.0, 1.0) (8.425, 1*.o) 1.0 (9 ( 12.0, 0.954) z*
sz ii] 0.8 a..
0 w
N
- i
<(
~ 0.6 0
z 0.4 0.2 0.0 -
0 2 4 6 8 ' 10 12 CORE HEIGHT (Fn Page 11 of 19
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 FIGURES (Page 1 of 2)
Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint 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, (:'.S 576.0°F)
P Pressuriz.er Pressure, psig P' = Nominal RCS operating pressure (2235 psig) 1 18
+' ]
[ 1+ i'2S The function generated by the lead-lag controller for T&YK dynamic compensation
't , 't 1 1
= Time constants utiliz.ed in the lead-lag controller for Tavg
. 't 1 ~ 28 secs. 't1 :'.S 4 secs.
S = Laplace transform operator, sec-1 K1 < 1.19
- KJ > 0.01331/'P K3 > 0.00058/psig f1 (Al) = -3.5 {33% + (qt - qb)} when qt - qb :'.S -33% RTP 0%ofRTP when -33% RTP < qt - qb :'.S 6% RTP
+1.0 {(qt-qb)-6%} when qt - qb > 6% RTP where q1 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 12 of 19
)
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 FIGURES (Page 2 of 2)
Overpower AT Trip Setpoint Overpower AT~ ATo [K4 - K 5 Where: AT Measured RCS AT, 0 P ATo Indicated AT at RATED THERMAL POWER, 0 P T = Average temperature, 0 P T" = Nominal Ta~ at RATED THERMAL POWER, (:S 576.0 °F) fu < 1.16
- Ks > 0.02/°P for increasing average temperature; Ks = 0 for decreasing *average temperature K6 > 0.00197/0P for T greater than T ; K6=0 for T less than or equal to T
The function generated by the rate lag controller for Tavg dynamic com~on Time constant utilized in the rate lag controller for Tavg; t 3 ~ 10 secs.
Laplace transform operator, sec-1 f2 (Al) = 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
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 FIGURE6 Reactor Core Safety Limits 660 r---
650
--- r--_
r--- -- ---
640 r--_
--- 2400 F SIA~ ----
....__ --- ~
UNA..,.,._ ,ABLE OPFR . .TION
-- ---- r---_ "' 1""- -
2250-
~
630
I"-."'"' ""-
~
-- - --...... ~ p ~ IA.--9"" ...___
L L 620 :;;:-_ -
r--._
~ """
0 2000"
--...... r--,....._
C>
~"
--- ---- r---.__ '
--- ' ~"" '
r--..."'
610
.1- -........... - -- ~ ""- \.""
"' 600 1776 fl ~~
...____ " ""\ \. '\
"'~"~"""'
0 ,_ ~
0:: ............. "-.. 'I\.'\. "'
590 ~~ lJ A~CEP" ABLE --......... "
'\."'
580 I'\. "
'\.
~ '\. ~
570 'I
~
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 Tavg Power Tavg Power Tavg (
(psla) (frac~ (' F) (frac} (' F) (frac) (' F) (frac) (' F) 1775 0.00 615.4 0.98 683.8 1.02 680.9 1.2 558.1 2000 1 0.00 631.8 0.86 605.8 0.96 697.5 1.2 668.6
\
2100 0.00 639.1 0.82 '614.0 0.96 601.6 1.2 573.1 2260 0.00 649.2 0.72 628.6 0.98 605.2 1.2 580A 2400 0.00 659.0 0.62 642.0 1.1 599.0 1.2 588.1 UNIT2 Reactor ~ore. Safety Limits Page 1.4 of 19
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 FIGURE7 Unit 2 Cycle 25 Predicted HFP ARO 300 PPM MTC Versus Burnup I
-2.44E-04
- -2 46E-04
\
\
-2 48E-04
\
\
i
- - -2 50E-04 \
u C
a,
\
i
~ -2.52E-04
\
~a, \
C.
E
~ -2.54E-04
\\
.ef!
a, "C
0
- Ii: -2 56E-04 \
-2 58E-04
'\
'\
-2 60E-04
-2.62E-04 17,000 18,000 19,000 21,000 Cycle Burnup (!'t1Wf)/MTU)
Burnup (MWD/MTU) MTC (pcm/°F) MTC (Ak/kl°F) 17000 -24.495 -2.4495E-04 18000 -24.884 -2.4884E-04 19000 -25277 -2.5277E-04 20000 -25.656 -2.5656E-04 21000 -26.038 -2.6038E-04 Page 15 of 19
)
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 Table 1 D. C. Cook Unit 2 Cycle 25 W(Z) Function Node Height Bumup (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 o'.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.QQQQ I 1.0000 1.0000 5 0.8 1.0000 1.0000 1.0000 1.0000
- 1.0000 1.0000 1.0000 6 LO 1.0000 1.0000 . 1.0000 1.0000 1.0000 1.0000 1.0000 7 1.2 1.1176 1.1176 1.1078 1.1016 1.1010 1.1052 1.1082 8 1.4 1.1161 1,.1109 - 1.1060 1.0998 1.0996 1.1044 1.1077 9 1.6 1.1142 1.1097 1.1054 1.1001 1)000 1.1044 1.1074 10 1.8 1.1119 1.1081 1.1044 1.0999 1.1000 1.1040 1.1067 11 2.0 1.1092 1.1061 1.1031 1.0996 1.0998 1.1033 1.1057 12 2.2 1.1062 1.1039 1.1016 1.0989 1.0994 1.1023 1.1042 13 2.4 1.1029 1.1013 1.0998 1.0981 1.0986 1.1009 1.1024 14 2.6 1.0993 1.0985 1.0977 1.0971 1.0977 1.0993 1.1003 15 *2.8 1.0954 1.0954 1.0955 1.0958 1.0965 1,0973 1.0978
- 16 3.0 1.0911 1.0920 1.0930 1.0944 1.0950 1.0950 1.0949 17 3.2 1.0870 1.0887 1.0903 1.0926 1.0932 1.0925 1.0919 18 3.4 1.0844 1.0864 1.0885 1.0912. 1.0916 1.0902 1.0893 19 3.6 1.0849 1.0869 1.0889 1.0914 , - 1.0912 1.0890 1.0877 20 3.8 1.0865 1.0883 1.0899 1.0916 1.0908 1.0879 1.0864 21 4.0 1.0887 1.0899 1.0909 1.0917 1.0903 1.0873 1.0858 22 4.2 1.0907 1.0912 1.0916 1.0915 1.0898 ', 1.0869 1.0856 23 4.4 1.0925 1.0924 1.0922 1.0913 I 1.0894 1.0869 1.0859 24 4.6 1 1.0941 1.0935 f.0927 1.0911 , 1.0890 1.0869 1.0861 25 4.8 1.0954 1.0943 1.0930 '1.0906 1.0884 1.0866 1.0860 J
26 5.0 1.0965 1.0947 1.0928 1.0898 1.0877 1.0865 1.0863 27 5.2 1.0971 \ 1.0947 1.0922 1.0886 1.0869 1.0870 1.0875 28 5.4 1.0974 1.0944 1.0913 1.0871 1.0858 1.0870 1.0881 29 5.6 1.0973 1.0937 . 1.0901 1.0853 1.0844 1.0866 1.0883 30 5.8 1.0967 1.0926 1.0885 1.0832 1.0826 1.0859 1.0881 Top and bottom lOo/. of core excluded.
Page 16 of 19
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 Table 1 (Confi:nued)
D. C. Cook Unit 2 Cycle 25 W~Function
/
Node
- Height Burnup (MWD/MTU)
- (ft) 150 1000 2000 4000 6000 8000 9000 31 6.0 1.0956 1.0910 1.0865 1.0808 1.0805 1.0847 1.0874 32 6.2 1.0940 1.0890 1.0841 1.0780 1.0780 1.0829 1.0860 33 6.4 1.0919 1.0865 1.0813 1.0749 1.0751 1.0806 1.0841 34 6.6 1.0891 1.0835 1.0780 1.0714 1.0717 1.0777 1.0816 35 6.8 1.0856 1.0798 1.0742 1.0674 1.0678 1.0742 1.0783 36 7.0 1.0818 1.0762 1.0708/
1.0643 1.0647 - 1.0708 1.0748 37 7.2 1.0804 1.0746 1.0689 1.0621 1.0625 1.0688 1.0730 38 7.4 1.0840 1.0765 1.0692 1.0605 1.0613 1.0698 1.0753 39 7.6 1.0872 1.0798 l'.0726 1.0642 1.0651 1.0735 1.0789 40 7.8 1.0897 1.0832 1-.0768 1.0693 1.0702 1.0778 1.0826
-41 8.0 1.0921 1.0861 1.0804 1.0736 1.0744 1.0814 1.0857 42 8.2 1.0940 1.0888 1.0838 1.0779 1.0787 1.0848 1.0886 43 8.4 1.0955; 1.0912 1.0870 1.0820 1.0827 1.0879 1.0911 44 8.6 1.0967 1.0932 1.0898 1.0858 1.0864 1.0906 1.0931 .
45 8.8 1.0974 1.0948 1.0922 1.0892 1.0897 1.0929 1.0949 46 9.0 1.0978
- 1.0961 1.0945 1.0926 1.0930 1.0952 1.,0964 47 9.2 1,.0975 1.0971 1.0967 1.0963 1.0965 1.0971 1.0975 48 9.4 1.0974 1.0982 1.0989 1.0998 1.0996 1.0987 1.0982 49 9.6 1.1012 1.1019 1.1025 1.1031 1.1026 1.1013 1.1007 50 9.8 1.1066 1.1065 1.1064 1.1060 1.1054 1.1046 1.1042 51 10.0 1.1110 1.1104 1.1098 1.1087 .1.1080 1.1077 1.1076 52 10.2 1.1153 1.1139 1.1126 1.1106 1.1099 1.11,02 1.1105 53 10.4 1.1191 1.1170 1.1150 1.1121 1.1113 1.1122 1.1130 54 10.6 1.1223 1,1217 1.1210 1:1197 1.1183 -1.1169
- 1.1163 55 10.8 . 1.1250 1.1229 1.1207 1.1176 1.1164 1.1167 1.1171 56 lLO 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 1.0Q_OO toooo 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 109/e of core exclnded.
Page 17 of 19 ,
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0
(
Table 1 (Continued)
D. C. Cook Unit 2 Cycle 25
- W(Z) Function Node Height Bumup (MWD/MTU)
\, # (ft) 10000 12000 14000 16000 18000 20000 22000 22829 1 0.0 1.0000 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 1.0000 3 0.4 1.0000 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 1.0000 5 0.8 1.0000 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 1.0000 7 1.2 1.1114 1.1175 , 1.1235 1.1295 1.1360 1.1432 i.1496 l.1523 8 1.4 1.1111 1.1174 1.1232 1.1287 1.1344 1.1405 1.1464 1.1488 9 1.6 1.1105 1.1163 1.1214 1.1264 1.1316 1.1371 L1424 1.1446 10 1.8 1.1095 1.1146 1.1192 1.1236 1.1280 1.1328 1.1375 1.1394 11 2.0 1.1080 1.1124 / 1.1163 l_.1200 1.1237 1.1278 1.1317 1.1333
- 12 2.2 1.1062 1.1097 1.1129 1.1159 1.1189 1.1221 1.1253 1.1266 13 2.4 1.1039 1.1066 1.1091 1.1113 1.1135 '1.1159 1.1183 1.1193 14 2.6 1.1013 1.1031 1.1047 1.1062 1.1077 1.1092 1.1108 1.1115 15 2.8 1.0982 1.0991 1.1000 1.1008 1.1015 1.1023 1.1031 1.1035 16 3.0
- 1.0948 1.0946 1.0946 1.0946 1.0946 1.0946 1.0946 1.0945 17 3.2 1.0912 1.0902 , 1.0895 1.0890 1.0885 1.0880 1.0874 1.0871 18 3.4 1.0883 1.0870 1.0863 1.0860 1.0859 1.0860 1.0855 1.0853 19 3.6 1.0865 1.0852 1.0849 1.0855 1.0868 1.0885 1.0889 1.0891 20 3.8 1.0851 1.0838 1.0841 1.0855 1.0880 1.0912 1.0924 1.0930 21 4.0 1.0845 1.0835 1.0842 1.0863 1.0895 1.0937 1.0956 1.0963 22 4.2 1.0846 1.0840 1.0851 1.0877 1.0915 1.0965 1.0988 1.0998 23 4.4 1.0852 1.0851 1.0866 1.0894 1.0935 1.0~87 1.1014 1.1025 24 4.6 1.0856 1.0859 1.0877 1.0908 i.0951 1.1005 1.1035 1.1048 25, 4.8 1.0857 -i.0864 1.0884 1.0918 1.0963 1.1019 1.1052 1.1065 26 5.0 1.0864 1.0876 1.0898 . 1.0931 1.0975 1.1028 1.1060 1.1074 27 5.2 1.0882 1.0900 1.0924 1.0953 1.0988 1.1031 1.1060 1.1073 28 5.4 1.0893 1.0918 1.0942 1.0967 1.0995 1.1028 1.1055 1.1066 29 5.6 1.0901 1.0930 1.0954 1.0976 1.0997 1.1019 1.1043 1.1053 30 5.8 1.0903 '1.0937 1.0960 1.0976 1.0988 1.0999 1.1018 1.1026 Top and bottom 10% of core cxclnded.
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Page 18 of19
DONALD C. COOK UNIT 2 CYCLE 25 Revision 0 Table 1 (Continued)
D. C. Cook Unit 2 Cycle 25 W(Z) Function Node Height Burnup (MWD/MTU)
- (ft) 10000 uooo 14000 16000 18000 20000 22000 22829 31 6.0 1.0900 1.0939 1.0965 ~l.0980 1.0988 1.0994 1.1013 1.1021
\
32 6.2 1.0891 1.0937 1.0968 1.0987 1.0999 1.1008 1.1031 1.1041 33 6.4 1.0876 1.0930 1.0969 1.0997 1.1019 1.1038 1.1071 1.1085 34 6.6 1.0854 1.0916 1.0963 1.1000 1.1031 1.1061 1.1102 1.1119 35 6.8 1.0825 1.0894 1.0948 1.0993 1.1034 1.1075 1.1125 1.1146 36 7.0 1.0789 1.0860 1.0921 1.0975 1.1027 1.1082 1.1140 1.1165 37 7.2 1.0773 1.0848 1.0912 1.0970 1.1027 1.1086 1.1149 1.1175 38 7.4 1.0806 1.0894 1.0959 1.1011 1.1053 1.1094 1.1152 1.1176 39 7.6 1.0842 1.0926 1.0986 1.1030 1.1065 1.1096 1.1147 1.1168 40 7.8 1.0872 1.0946 1.0999 1.1037 1.1065 1.1090, 1.1134 1.1152 41 8.0 1.0899 1.0965 1.1010 1.1041 1.1062 1.1079 1.1115 1.1130 42 8.2 1.0922 1.0978 1.1015 1.1039 1.1053 1.1063 1.1091 1.1102 43 8.4 1.0941 1.0987 1.1015 1.1031 1.1038 1.1041 1.1061 1.1069 44 8.6 1.0955 1.0990 1.1010 1.1018 1.1018 1.1014 1.1026 1.1030 45 8.8 1.0967 1.0991 1.1002 1.1004 1.0998 1.0987 1.0991 1.0993 46 9.0 1.0976 1.0991 1.0998 1.0998 1.0992 1.0983 1.0985 1.0985 47 9.2 1.0979 1.0986 1.0991 1.0996 1.1000 1.1005 1.1010 1.1012 48 9.4 1.0978 1.0976 1.0980 1.0989 1.1003 1.1020 1.1028 1.1032 49 9.6 1.1001 1.0998 1.1004 1.1016 1.1034 1.1057 1.1068 1.1072 so 9.8 1.1040 1.1041 1.1048 1.1060 1.1077 1.1098 1.1109 1.1114 51 10.0 1.1077 1.1081 1.1089 -1.1100 1.1114 1.1131 1.1142 1.1147 52 10.2 f.1109 1.1118 1.1127 1.1136 1.1148 1.1161 1.1171 1.1176 53 10.4 1.1137 1.1150 1.1160 1.1168 1.1176 1.1186 1.1195 1.1199 54 10.6 1.1159 1.1156 1.1160 1.1170 1.1185 1.1204 1.1213 1.1217 55 10.8 1.1176 1.1185 1.1193 1.1200 1.1208 1.1219 1.1227 1.1231 56 11.0 1.0000 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 1.0000 58 11.4 1.0000 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 1.0000 60 11.8 1.0000 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 1.0000 Top and bottom 10°,- of core excluded Page 19 of 19