AEP-NRC-2025-33, Core Operating Limits Report
| ML25237A234 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/25/2025 |
| From: | Scarpello M Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co) |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| AEP-NRC-2025-33 | |
| Download: ML25237A234 (1) | |
Text
INOIANA MICHIGAN POWER-An /UP Company BOUNDLESS ENERGY-August25,2025 Docket Nos.: 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 Cook Nuclear Plant One Cook Place Bridgman. Ml 49106 indianamichiganpower.com AEP-NRC-2025-33 10 CFR 50.4 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 33 in accordance with Technical Specification 5.6.5. The Unit 1 Cycle 33 COLR. Revision 0, is provided as an enofosure 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.
~~1!-
Michael K. Scarpello Regulatory Affairs Director OAF/sjh
Enclosure:
Donald C. Cook Nuclear Plant Unit 1 Cycle 33 Core Operating Limits Report, Revision 0.
c:
EGLE - RMD/RPS J. B. Giessner - NRC Region Ill NRC Resident Inspector N. Quilico-MPSC R. M. Sistevaris - AEP Ft. Wayne S. P. Wall, NRC Washington D.C.
A. J. Williamson - AEP Ft. Wayne
Enclosure to AEP-NRC-2025-33 Donald C. Cook Nuclear Plant Unit 1 Cycle 33 Core Operating Limits Report, Revision 0
Page 1 of 19 Donald C. Cook Nuclear Plant Unit 1 Cycle 33 D. C. COOK UNIT 1 CYCLE 33 Revision 0 Core Operating Limits Report Revision 0
Page 2 of 19 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit 1 Cycle 33 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. 1A, 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, 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 ZIRLOTM, 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 (FN H) 3.2.3 AXIAL FLUX DIFFERENCE (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 D. C. COOK UNIT 1 CYCLE 33 Revision 0 Design Bases for the Thermal Overpower /!!. T and Thermal Overtemperature /!!. T Trip Functions, A
Page 3 of 19 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 REACTIVITY CONTROL 2.2.1 SHUTDOWN MARGIN (SDM) (Specification 3.1.1)
Shutdown margin shall be greater than or equal to 1.3% k/k for Tavg > 200°F Shutdown margin shall be greater than or equal to 1.0% k/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 k/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 D. C. COOK UNIT 1 CYCLE 33 Revision 0
Page 4 of 19 b.
The MTC Surveillance limit is:
The 300 ppm/ARO/RTP-MTC should be less negative or equal to
-3.84E-4 k/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 k/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 k/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 MWD/MTU.
D. C. COOK UNIT 1 CYCLE 33 Revision 0 0"0<
V V
V
Page 5 of 19 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)
Where: P =
THERMAL POWER RATED 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 1 for +/-5% AFD target band.
e.
FQW (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 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.
f.
For Cycle 33, 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.
5.0
)
(
)
(
P for Z
K P
CF Z
F Q
C Q
5.0
)
(
2
)
(
P for Z
K CF Z
F Q
C Q
5.0
)
(
)
(
P for Z
K P
CF Z
F Q
W Q
5.0
)
(
2
)
(
P for Z
K CF Z
F Q
W Q
D. C. COOK UNIT 1 CYCLE 33 Revision 0
Page 6 of 19 Burnup (MWD/MTU)
Penalty Factor FQ(z)
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 (FN H ) (Specification 3.2.2)
FN H CF H * (1 + PF H *(1-P))
Where: P =
THERMAL POWER RATED THERMAL POWER a.
CF H = 1.53 b.
PF H = 0.3
- c. FN 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 T and Overpower T setpoints are as shown in Figure 5.
D. C. COOK UNIT 1 CYCLE 33 Revision 0 334 1.0200 517 1.0245 701 1.0284 885 1.0311 1069 1.0326 1252 1.0328 1436 1.0317 1620 1.0295 1804 1.0262 1987 1.0230 2171 1.0219 2355 1.0202 2539 1.0200
Page 7 of 19 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 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 k/k conservative allowance for uncertainties. The boron concentration of 2400 ppm includes a 50 ppm conservative allowance for uncertainties.
D. C. COOK UNIT 1 CYCLE 33 Revision 0 0
0
- 0.95 which includes a 1 % L'.\\
Page 8 of 19 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 0.5 0.0
-0.5
-1.0 0
10 20 30 40 50 60 Percent Rated Thermal Power 70 80 90 100 UNACCEPTABLE OPERATION ACCEPTABLE OPERATION D. C. COOK UNIT 1 CYCLE 33 Revision 0 MTC (x 10-4 delta-k/k/°F)
~
/
/ /
/
Page 9 of 19 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 0
20 40 0
ROD GROUP POSITION (Steps Withdrawn)
POWER (% of Rated Thermal Power) 60 80 100 25 75 50 100 125 175 150 200 225 250 BANK C BANK D (0%, 0)
(0%, 128)
(52.9%, 228) 100 Step Overlap (100%, 189) 10 30 50 70 90 D. C. COOK UNIT 1 CYCLE 33 Revision 0 I
/
I I
I I
~
I 1,
V I
I
/
/
V
/
/
/'
/ /
R I
I
/
I I/
/
/~
/ V
/ V
/
V 1/1 I
Page 10 of 19 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP)
FLUX DIFFERENCE (DELTA-I)
ACCEPTABLE OPERATION UNACCEPTABLE OPERATION UNACCEPTABLE OPERATION
(-11,90)
(+11,90)
(+31,50)
(-31,50)
-50
-40
-30
-20
-10 0
10 20 30 40 50 100 90 80 70 60 50 40 30 20 10 0
D. C. COOK UNIT 1 CYCLE 33 Revision 0
% of Minimum(ffTP OR CF ax K(Z) X 10~
l F~ (Z)
~
I
""' "'~
~
~"' -
~
~
V - -
v~
~
I
Page 11 of 19 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT (0.0, 1.0)
(12.0, 1.0) 0.0 0.2 0.4 0.6 0.8 1.0 1.2 0
2 4
6 8
10 12 CORE HEIGHT (FT)
NORMALIZED FQ D. C. COOK UNIT 1 CYCLE 33 Revision 0 NORMALIZED PEAKING
Page 12 of 19 FIGURE 5 (Page 1 of 2)
Reactor Trip System Instrumentation Trip Setpoints Overtemperature T Trip Setpoint Overtemperature T To [K1 - K2 s
s 2
1 1
1 (T-3 (P-
- f1 ( I)]
Where:
T
=
Measured RCS T, F To
=
Indicated T at RATED THERMAL POWER, F T
=
Average temperature, F
=
Nominal Tavg at RATED THERMAL POWER ( 575.4 F)
P
=
Pressurizer pressure, psig
=
Nominal RCS operating pressure (2235 psig) s s
2 1
1 1
=
The function generated by the lead-lag controller for Tavg dynamic compensation 1,
2 =
Time constants utilized in the lead-lag controller for Tavg 1 22 secs. 2 4 secs.
S
=
Laplace transform operator, sec-1 K1 1.35
- K2 0.0230/ F K3 0.00110/psi f1 ( I) =
-0.33 {37% + (qt - qb)} when qt - qb
-37% RTP 0% of RTP when -37% RTP < qt - qb
+2.34 {(qt - qb) - 3%} when qt - qb > 3% 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.
D. C. COOK UNIT 1 CYCLE 33 Revision 0 A ~A T'
P'
't
't
[ :; ]
A 0
A 0
A T')+K P')
A 0
0
~
0
- '.S3%RTP
Page 13 of 19 FIGURE 5 (Page 2 of 2)
Overpower T Trip Setpoint Overpower T To [K4 - K5 S
S 3
3 1
T - K6 (T - T) - f2 ( I)]
Where:
T
=
Measured RCS T, F To
=
Indicated T at RATED THERMAL POWER, F T
=
Average temperature, F T
=
Nominal Tavg at RATED THERMAL POWER ( 575.4 F)
K4 1.172
- K5 0.0177/ F for increasing average temperature ; K5 = 0 for decreasing average temperature K6 0.0015/ F for T greater than T ; K6 = 0 for T less than or equal to T
S S
3 3
1
=
The function generated by the rate lag controller for Tavg dynamic compensation 3
=
Time constant utilized in the rate lag controller for Tavg 3 10 secs.
S
=
Laplace transform operator, sec-1 f2( I) =
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.
D. C. COOK UNIT 1 CYCLE 33 Revision 0
<1 0
5 0
0 o
V V
V 0
0 V
[~]
V 1
.i+
,2, V
V V5 V
Page 14 of 19 FIGURE 6 Reactor Core Safety Limits DESCRIPTION OF SAFETY LIMITS Pressure (psia)
Power (frac)
Tavg
(°F)
Power (frac)
Tavg
(°F)
Power (frac)
Tavg
(°F)
Power (frac)
Tavg
(°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 UNIT 1 Reactor Core Safety Limits Revision 0 D. C. COOK UNIT 1 CYCLE 33 670 660 650
,_640
~
=
-630 0J) >
~ 620
~
rJJ. 610 u
~ 600 590 580 570 UNAQCEPfA 3LE OPfRATIO~
2400 psia/,.,..,,,,.
~r---.,_
~
---I""---.......
1........___
2250 psia---~
r--...L
--r--.......
--I""---.......
~sia-
---I""---.......
~ '
1---... _,
--.......___ 2000 psia/
~ ---.....
1840 psia/
-r-----.,1 r--...
, 1,'
--i--......
.1, '
ACCEP1TABLE OPERATION
--.. ~ ' ' "
0 0.2 0.4 0.6 0.8 1
1.2 Power (Fraction of rated thermal power) 0 0
0 0
Page 15 of 19 FIGURE 7 Unit 1 Cycle 33 Predicted HFP ARO 300 PPM MTC Versus Burnup Burnup (MWD/MTU)
MTC (pcm/oF)
/k/°F) 14,000
-23.482
-2.3482E-04 15,000
-23.892
-2.3892E-04 16,000
-24.311
-2.4311E-04 17,000
-24.667
-2.4667E-04 18,000
-25.051
-2.5051E-04 D. C. COOK UNIT 1 CYCLE 33 Revision 0 MTC(Ak
Page 16 of 19 TABLE 1 DONALD C. COOK UNIT 1 CYCLE 33 W(Z) FUNCTION Node Height (ft)
Burnup (MWD/MTU) 150 1000 2000 4000 6000 8000 Top and bottom 10% of core excluded.
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 1.1070 1.1035 1.1003 1.0979 1.1005 1.1058 8
1.4 1.1064 1.1033 1.1004 1.0983 1.1008 1.1058 9
1.6 1.1056 1.1028 1.1003 1.0986 1.1009 1.1055 10 1.8 1.1044 1.1020 1.0999 1.0985 1.1007 1.1048 11 2.0 1.1029 1.1010 1.0993 1.0983 1.1002 1.1038 12 2.2 1.1011 1.0997 1.0984 1.0978 1.0995 1.1024 13 2.4 1.0991 1.0981 1.0973 1.0970 1.0984 1.1007 14 2.6 1.0968 1.0963 1.0960 1.0960 1.0971 1.0987 15 2.8 1.0943 1.0943 1.0944 1.0948 1.0955 1.0963 16 3.0 1.0914 1.0920 1.0925 1.0933 1.0936 1.0938 17 3.2 1.0886 1.0895 1.0905 1.0916 1.0916 1.0911 18 3.4 1.0862 1.0875 1.0888 1.0901 1.0898 1.0886 19 3.6 1.0850 1.0867 1.0882 1.0896 1.0887 1.0868 20 3.8 1.0845 1.0862 1.0878 1.0889 1.0877 1.0854 21 4.0 1.0844 1.0858 1.0872 1.0881 1.0868 1.0848 22 4.2 1.0845 1.0855 1.0865 1.0871 1.0862 1.0847 23 4.4 1.0846 1.0852 1.0857 1.0860 1.0853 1.0845 24 4.6 1.0846 1.0847 1.0847 1.0846 1.0843 1.0841 25 4.8 1.0844 1.0840 1.0836 1.0831 1.0830 1.0835 26 5.0 1.0842 1.0833 1.0825 1.0817 1.0817 1.0826 27 5.2 1.0838 1.0826 1.0814 1.0802 1.0803 1.0816 28 5.4 1.0832 1.0816 1.0800 1.0784 1.0787 1.0804 29 5.6 1.0823 1.0803 1.0784 1.0764 1.0767 1.0788 30 5.8 1.0810 1.0787 1.0764 1.0742 1.0747 1.0774 D. C. COOK UNIT 1 CYCLE 33 Revision 0
Page 17 of 19 TABLE 1 (continued)
DONALD C. COOK UNIT 1 CYCLE 33 W(Z) FUNCTION Node Height (ft)
Burnup (MWD/MTU) 150 1000 2000 4000 6000 8000 D. C. COOK UNIT 1 CYCLE 33 Revision 0 Top and bottom 10% of core excluded.
12.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 31 6.0 1.0795 1.0767 1.0741 1.0718 1.0731 1.0767 32 6.2 1.0776 1.0744 1.0715 1.0693 1.0715 1.0764 33 6.4 1.0752 1.0719 1.0689 1.0669 1.0698 1.0756 34 6.6 1.0728 1.0696 1.0667 1.0651 1.0685 1.0748 35 6.8 1.0711 1.0680 1.0653 1.0639 1.0674 1.0736 36 7.0 1.0701 1.0670 1.0641 1.0626 1.0661 1.0723 37 7.2 1.0700 1.0664 1.0632 1.0614 1.0652 1.0720 38 7.4 1.0718 1.0676 1.0639 1.0618 1.0660 1.0735 39 7.6 1.0751 1.0712 1.0678 1.0658 1.0700 1.0772 40 7.8 1.0788 1.0755 1.0726 1.0711 1.0748 1.0812 41 8.0 1.0823 1.0794 1.0769 1.0755 1.0789 1.0846 42 8.2 1.0855 1.0831 1.0810 1.0800 1.0829 1.0877 43 8.4 1.0884 1.0865 1.0849 1.0841 1.0865 1.0904 44 8.6 1.0910 1.0896 1.0884 1.0879 1.0898 1.0928 45 8.8 1.0932 1.0924 1.0916 1.0915 1.0928 1.0949 46 9.0 1.0951 1.0949 1.0947 1.0949 1.0957 1.0967 47 9.2 1.0966 1.0972 1.0978 1.0985 1.0986 1.0982 48 9.4 1.0976 1.0991 1.1005 1.1016 1.1008 1.0990 49 9.6 1.0986 1.1008 1.1029 1.1044 1.1027 1.0997 50 9.8 1.0994 1.1023 1.1050 1.1068 1.1042 1.1001 51 10.0 1.0999 1.1035 1.1068 1.1091 1.1061 1.1011 52 10.2 1.0998 1.1039 1.1078 1.1110 1.1086 1.1041 53 10.4 1.1006 1.1048 1.1088 1.1123 1.1104 1.1063 54 10.6 1.1064 1.1114 1.1160 1.1195 1.1162 1.1100 55 10.8 1.1041 1.1091 1.1138 1.1179 1.1156 1.1107 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
Page 18 of 19 TABLE 1 (continued)
DONALD C. COOK UNIT 1 CYCLE 33 W(Z) FUNCTION Node Height (ft) 10000 12000 14000 16000 18000 19711 Top and bottom 10% of core excluded.
Revision 0 D. C. COOK UNIT 1 CYCLE 33 10 1.8 1.1093 1.1132 1.1166 1.1201 1.1238 1.1269 11 2.0 1.1077 1.1110 1.1140 1.1169 1.1201 1.1227 12 2.2 1.1056 1.1084 1.1108 1.1132 1.1158 1.1179 13 2.4 1.1032 1.1053 1.1072 1.1090 1.1109 1.1126 14 2.6 1.1004 1.1018 1.1031 1.1044 1.1057 1.1068 15 2.8 1.0972 1.0980 1.0987 1.0994 1.1001 1.1007 16 3.0 1.0938 1.0938 1.0939 1.0940 1.0940 1.0940 17 3.2 1.0904 1.0897 1.0891 1.0885 1.0878 1.0872 18 3.4 1.0873 1.0863 1.0856 1.0848 1.0840 1.0833 19 3.6 1.0851 1.0845 1.0847 1.0855 1.0861 1.0863 20 3.8 1.0837 1.0835 1.0846 1.0866 1.0884 1.0894 21 4.0 1.0834 1.0836 1.0852 1.0878 1.0901 1.0916 22 4.2 1.0838 1.0845 1.0864 1.0892 1.0918 1.0935 23 4.4 1.0843 1.0853 1.0874 1.0903 1.0931 1.0950 24 4.6 1.0846 1.0859 1.0881 1.0910 1.0938 1.0957 25 4.8 1.0847 1.0868 1.0897 1.0934 1.0970 1.0996 26 5.0 1.0845 1.0875 1.0916 1.0965 1.1015 1.1051 27 5.2 1.0842 1.0880 1.0929 1.0990 1.1051 1.1096 28 5.4 1.0835 1.0880 1.0939 1.1010 1.1081 1.1134 29 5.6 1.0825 1.0877 1.0943 1.1024 1.1105 1.1165 30 5.8 1.0818 1.0875 1.0947 1.1033 1.1120 1.1184 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 1.1117 1.1168 1.1214 1.1261 1.1310 1.1352 8
1.4 1.1113 1.1161 1.1203 1.1246 1.1292 1.1331 9
1.6 1.1105 1.1149 1.1188 1.1227 1.1269 1.1304
Page 19 of 19 TABLE 1 (continued)
DONALD C. COOK UNIT 1 CYCLE 33 W(Z) FUNCTION Node Height (ft) 10000 12000 14000 16000 18000 19711 Top and bottom 10% of core excluded.
Revision 0 D. C. COOK UNIT 1 CYCLE 33 31 6.0 1.0820 1.0882 1.0954 1.1039 1.1124 1.1190 32 6.2 1.0826 1.0891 1.0961 1.1039 1.1119 1.1182 33 6.4 1.0826 1.0893 1.0959 1.1031 1.1106 1.1166 34 6.6 1.0820 1.0886 1.0949 1.1014 1.1083 1.1139 35 6.8 1.0806 1.0869 1.0927 1.0987 1.1050 1.1102 36 7.0 1.0792 1.0851 1.0904 1.0956 1.1012 1.1059 37 7.2 1.0792 1.0850 1.0898 1.0944 1.0993 1.1037 38 7.4 1.0814 1.0875 1.0923 1.0966 1.1014 1.1057 39 7.6 1.0847 1.0904 1.0947 1.0985 1.1027 1.1065 40 7.8 1.0878 1.0927 1.0964 1.0995 1.1030 1.1063 41 8.0 1.0904 1.0946 1.0976 1.1001 1.1030 1.1057 42 8.2 1.0926 1.0960 1.0983 1.1002 1.1023 1.1044 43 8.4 1.0943 1.0969 1.0986 1.0997 1.1011 1.1025 44 8.6 1.0957 1.0975 1.0983 1.0988 1.0994 1.1001 45 8.8 1.0967 1.0977 1.0978 1.0975 1.0974 1.0975 46 9.0 1.0974 1.0974 1.0968 1.0957 1.0948 1.0942 47 9.2 1.0976 1.0968 1.0959 1.0948 1.0937 1.0928 48 9.4 1.0974 1.0969 1.0972 1.0980 1.0986 1.0989 49 9.6 1.0973 1.0971 1.0986 1.1013 1.1037 1.1051 50 9.8 1.0971 1.0971 1.0996 1.1039 1.1078 1.1101 51 10.0 1.0975 1.0976 1.1010 1.1066 1.1116 1.1146 52 10.2 1.1007 1.1009 1.1043 1.1096 1.1144 1.1173 53 10.4 1.1033 1.1037 1.1070 1.1121 1.1168 1.1197 54 10.6 1.1052 1.1048 1.1080 1.1136 1.1186 1.1214 55 10.8 1.1068 1.1068 1.1100 1.1153 1.1199 1.1227 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