ML061580586
| ML061580586 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/30/2006 |
| From: | Jensen J Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:6565 | |
| Download: ML061580586 (34) | |
Text
A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 AEP.com AEP:NRC:6565 10 CFR 50.4 May 30, 2006 Docket Nos.:
50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 and Unit 2 CORE OPERATING LIMITS REPORTS Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 1 and Unit 2, is submitting Revision 3 to the Core Operating Limits Report (COLR) for Unit 1 Cycle 20 and Revision 0 to the COLR for Unit 2 Cycle 16 in accordance with Technical Specification 5.6.5.
Revision 3 to the COLR for Unit 1 Cycle 20 is being made to correct the Overtemperature Delta T equation, add revision numbers and dates to the analytical methodology, and to provide consistent wording with the Unit 2 Cycle 16 COLR.
Revision 3 of the Unit I Cycle 20 COLR is provided as Attachment 1. Revision 0 of the Unit 2 Cycle 16 COLR is provided as Attachment 2.
There are no new commitments in this submittal. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Supervisor, at (269) 466-2649.
Sincerk ly, Site Vice President JEN/rdw Attachments c:
J. L Caldwell - NRC Region III KY D. Curry - AEP Ft. Wayne J. T. King - MPSC MDEQ - WHMDIRPMWS NRC Resident Inspector P. S. Tam - NRC Washington DC AMI
ATTACHMENT 1 TO AEP:NRC:6565 Unit 1 Cycle 20 Core Operating Limits Report Revision 3
D. C. COOK UNIT I CYCLE 20 Revision 3 D.C IOKUI CYL 20111 Reiio Donald C. Cook Nuclear Plant Unit I Cycle 20 Core Operating Limits Report Revision 3 Page I of 15
'D. C. COOK UNIT 1 CYCLE 20 Revision 3 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Donald C. Cook Nuclear Plant Unit 1 Cycle 20 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.ControI/FQ Surveillance Technical Specification, February 1994
- d.
WCAP-10266-P-A, Rev. 2, The-1981.Version of the Westinghouse ECCS Evaluation Model Using the BASH Code, March 1987
- e.
WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995
- f.
WCAP-8745-P-A, Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT 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 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 (FeN) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reactor Trip System (RTS) Instrunmentation 3.4.1 RCS Pressure, Temperature, and Flow Departure.from Nucleate Boiling (DNB) Limits 3.9.1 Boron Concentration Page 2 of 15
D. C. COOK UNIT 1 CYCLE 20 Revision 3 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 I and 2, the combination of thermal power, pressurizer pressure, and the highest loop average temperature (T,.,) 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% A*k for T, > 200"F Shutdown margin shall be greater than or equal to 1.0% Ak/ for T. < 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 EOIJARO/RTP-MTC shall be less negative or equal to -4.54E-4 Ak/kiF.
This limit is based on a T.,, program with I-FP vessel T.,, of 554.0 to 558.0 IF.
Where:
ARO stands for All Rods Out BOL stands for Beginning of Cycle Life EOL siands for End of Cycle Life RTP stands for Rated Thermal Power HFP stands for Hot Full Thermal Power Page 3 of 15
Dý C. COOK UNIT 1 CYCLE 20 Revision 3
- b.
The MTC Surveillance limit is:
The 300 ppn/ARO/RTP-MTC should be less negative or equal to
-3.84E-4 Ak/k/F at a HFP vessel Tv, of 554.0 to'558.0 OF.
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/kI0F.
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 nbt 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 Tag of 554.0 to 558.0 OF 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 MWDIMTU.
Page 4 of 15
D. C. COOK UNIT 1 CYCLE 20 Revision 3 D..COKUII CYL I0 ReIlol 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)
F* (Z)
_ cF-K(Z)
.P F* (Z)5 2.CFQ,K(Z)
F*" (Z):5
- K(Z)
P F~w (Z)*r.2 *CFg *K(Z) for P> 0.5 for P <0.5
.for P > 0.5 for P _0.5 W THERMAL POWER Where:
P = RATED THERMAL.POWER
- a.
CFQ=2.15
- b.
K(Z) is provided in Figure 4.
- c.
FCQ(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.
Fw(Z) =Fj(Z) x W(Z) x F,
- f.
For Cycle 20, Fp = 1.02 for all burnups associated with Note 2:a of SR 3.2.1.2.1 When no penalty is required, Fr - 1.00.
2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (Fem) (Specification 3.2.2) eA:9 CFAII * (I + PFAH *(l-P))
Where: P -THERMAL POWER RATED THERMAL POWER
- a.
CFAH 1.49
- b.
PFm= 0.3 Page 5 of 15
D. C. COOK UNIT I CYCLE 20 Revision 3 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 > 2018 psig +
- b. Reactor Coolant System TAvo shall be < 581.4*F +
- c.
Reactor Coolant System Total Flow Rate shall be > 341,100 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 579.1°F for T5,, and 2050 psig for Pressurizer Pressure.
This concentration bounds the condition of Kerr < 0.95 which includes a 1% Ak/k conservative allowance for uncertainties. The boron concentration of 2400 ppm includes a 50 ppm conservative allowance for uncertainties.
Page 6 of 15
D. C. COOK UNIT I CYCLE 20'i,
Revision 3 D..CO U
IT 1I CYCLEn 0Reiio FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS
.1.0 0.5 LL 0ýr x
0I-0.0
-0.5
[UNACCEPTABLE OPERATION ACCEPTABLE OPERATIONJ
-1.0 0
10 20 30 40 50 60 70 80 90 100
- Percent Rated Thermal Power Page 7 of 15
D. C. COOK UNIT 1 CYCLE 20 Revision 3 FIGURE 2 ROD BANK INSERTION LMITS VERSUS THERMAL POWER (FOUJR LOOP OPERATIlON) 250 2[(52.9%,
228) 100 Step Overlap 200 (100%. 189) 175 0
- a.
lO
- C/
7 Z
15
'0,18 SBANK D
0 C3 75 POWER (% of Rated Thermal Power)
Page. 8 of 15.
.D. C. COOK UNIT 1 CYCLE 20 Revision 3 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP)
I-SE x
SN Ix 0
a.
'I-0 100 90 80 70 60 50 40 30 20 10 0
FLUX DIFFERENCE (DELTA-I).
Page 9 of 15
D. C. COOK UNIT 1 CYCLE 20 Revision 3 FIGURE 4 K(Z) - NORMATIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 1.0 (D
z a.
a 0
,J 0<
z, 0.8 0.6 (0.0,1.0)
(6.0,1.0) 12.0,0.925) 0.4 0.2 0
0 2
4 6
8 10 12 CORE HEIGHT (FT)
Page 10 of 15
D. C. COOK UNIT 1 CYCLE 20 Revision 3 FIGURE 5 (Page I of 2)
Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT5 ~AT. [K, - Kz L,is
+ -W (I-T') + K3 (P-P') - f1 (AI)I
- l+rs]
Where:
AT
-Measured RCS AT, OF AT
=
Indicated AT at RATED THERMAL POWER OF 0
T
=
Average temperature, *F T'
=
Nominal T, at RATED THERMAL POWER (5 <574.0 'F)
P
=
Pressurizer pressure, psig P'
Nominal RCS operating pressure (2085 psig) 1 +,ris The function generated by the lead-lag controller for T., dynamic 1 + as compensation 191 z2 Time constants utilized in the lead-lag controller for T.
",r> 22 secs.
v2 :5 4 secs.
S Laplace transform operator, sec" K,
1.35*
K2 0.0230/-F K3 0.00110/psig.
f, (AI) =
-0.33 {37% + (qt -.qb)) when q, - qb5 -- 37% RTP 0% ofRTP when -37% RTP < qt -qb 5 3% RTP
- +2.34 {(qt - qb) - 3%} *when qt -qb > 3% RTP where q, 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 11 of 15
D. C. COOK UNIT I CYCLE 20 Revision 3 D.C. COOK UNIT 1 CYCLE 20 Revision 3
- FIGURE 5 (Page 2 of 2)
Overpower AT Trip Setpoint
" L+rSJ ]
Overpower AT < AT.
Where:
AT
=
Measured RCS AT, OF AT, Indicated AT at RATED THERMAL POWER, OF T
Average temperature, *F
=T Nominal T.,z at RATED THERMAL POWER.( <562.1 *F)
K4
'1.172
- Ka 0.0177/*F for increasing average temperature; K5 = 0 for decreasing average temperature Ks 0.0015/°F for T greater than Tr"; K o
=0 for T less than or equal to r' I+?sS The. function generated by the rate lag controller for T,1 dynamic compensation
,c
=
Time constant utilized in the rate lag controller for T.,
> 10secs.
S
=
Laplace transform operator, sec".
f2(AT) 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.
IP Page 12 of 15
D. C. COOK UNIT 1 CYCLE 20 Revision 3 FIGURE 6 Reactor-Core Safety Limits 660 650
- o)*
.ot 660 UNACCE PTABLE 640
> 620 20--
610"
, 600 690 ACCE
'ABLE OPER MTON 580 570
.0 0.2 0.4 0.6 0.8 1
1.;
Power (fraction of rated thermal power)
DESCRIPTION OF SAFETY LIMITS PRESSURE Power Tavg Power Tavg Power Tavg (PSIA)
(frac)
Vf.. F)
(rac (9 F)
(frac)
(OF) 1840 0.02 620.86 1.136 686.17 1.2 577.94 2000 0.02 632.79 1.094
'600.31 1.2 586.52 2100 0.02 639.85 1.068 608.72 1.2 591.77 2250 0.02 649.96 1.031 620.83 1.2 599A0 2400 0.02 659.52 0.996 632A2 1.2 606.63 UNIT i Reactor Core Safety Limits Z
Page 13 of 15
D. C. COOK UNIT 1 CYCLE 20 Revision 3 FIGURE 7 Unit 1 Cycle 20 Predicted HFP ARO 800 PPM MTC Versus Burnup
- -1.98E-04
. -2.OOE
~-2.O2E-04 5 -2.04E-04 0-2.06E-04
-2.08E-04 a*."
-2.1 OE-04
-2.12E-04 0
-2.14E-04 12000 13000 14000
."15000 16000 Cycle Burnup (MWVDIMTU)
Bumup (MWDIMTU)
MTC (hk/kPF) 12000
-2.0020E-4 13320
-2.0458E-4 14320
-2.0770E-4 15320
-2.1064E-4 16000
.-2.1256E-4 Page 14 of 15
D. C. COOK UNIT 1 CYCLE 20 Revision 3 TABLE 1 DONAIb C. COOK UNIT 1 &CLE 20 W(Z) FUNCTION Node Height No.
(f*e 150 1000 Zo 1
0.0 1.0000 1.0000 1.0000 2
0.2 t.o000 1.0L00 1.0000 a
0.4 1.0600 L0000 1.0000 4
0.6 1.0000 1.0000 1.0000 8
0.8 1.0000 1.0000 1.0000 6
1.0 1.0000 1.0000 1.0000 7
1.2 1.0985 1.0993 1.1003 8
1.4 1.0987 1.0994 1.1004 9
1.6 1.0988 1.0993 1.1002 10 1.8 1.0983 1.0989 1.0997 11 2.0 1.0977 1.0983 1.0990 12 2.2 1.0969 1.0974 1.0980 13 2.4 L0959 L0963 1.0968 14 2.6
- 1.0947 1.0949 1.0952 15 2.8 1.0932 1.0933 L0934 16 8.0 1.0916 L0915 L0915 17 3.2 1.0901 L0899 L0897 18 8.4 1.088L 1.0885 1.0882 19 8.6 1.0880 1.0876 1.0870 20 8.8 1.0875 L0867 1.0860 21 4.0 1.0869 L0859 1.0849 22 4.2 -
1.0862 1.0851 1.0841
.23 4.4 1.0854 1.0844 1.0835 24 4.6 1.0845 1.0836 1.0828 25 4.8 1.0833 L0825 1.0818 26 5.0 1.0823 1.0816 1.0810 27 5.2 1.0818 1.0810 1.0804 28 5.4 1.0813 1.0804 1.0797 29 5.6 1.0805 L0798 1.0793 80 5.8 1.0795 L0791 1.0789 31 6.0 1.0782 1.0781 1.0782 32 6.2 1.0766 L0768 1.0772 83 6.4 1.0746 1.0751 1.0759 84 6.6 1.0722 L0730 1.0740 85
&8 1.0696 1.0706 1.0718 86 7.0 1.0671 1.0682 1.0695 87 7.2 1.0646 L0660 1.0678 88 7.4 1.0630 L0655 1.0682 89 7.6 1.0654 L0681 1.0711 40 7.8 1.0702 1.0727 L0755 41 8.0 1.0750 1.0778 "1.0798 42 8.2 1.0796 1.0816 1.0837 43 8.4 1.0840 1.0855
.1.0871 44 6.6 1.0881 L0891
.1.0900 45 8.8 1.0921 L0923 1.0926.
46 9.0 L0957 1.0952 1.0947 47 9.2 1.0990 L0978 1.0966 48 9.4 L1020 1.1000 L.980 49 9.6 1.1045 L1021 1.0997 50 9.8 1.1069 L1043 1.1017 51 10.0 1.1093
.1065 1.1036 52 10.2 1.1112 1.1083 1.1054 53 10.4 1.1125 1.1099 1.1072 4
10.6 1.1186 1.1111 1.1087 55 10.8 1.1150 1.1126 1.1103 56 11.0 1.0000 1.0000 1.000 87 11.2 1.0000 1.0000 1.0000 58 11.4 LO0000 1000 1.0000 59 11.6 L0000 1.0000 1.0000 60 11.8 1.0000 L0000 L.000 61 12.0 1.0000 1.0000 1.0000 Top and bottom 10% of core excluded.
AM00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1026 1.1025
- 1. 1022 1.1016 1.1006 1.0994 1.O978 L0960 1.0938 1.0915 1.0894 1.0876 1.0862 1.0848 1.0835 1.0828 1.0825 1.0820 1.0813 1.0807 1.0800 1.0792 1.0791 1.0793 1.0791.
1.0786 1.0777 1.0763 1.0743 1.0721 1.0711 1.0731 1.0763 1.0801 1.08.8 1.o771 1.0895 1.0914 1.0928 1.0939 1.0946 1.0950 1.0961 1.0978 1.0994 1.1012 1.1034 1.1053 1.1070 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Burnup (MWD/MTU)
M o
Mo 1oo 1.0000
'.000 1.000 1.0000 1.0000 1.00O0 1.0800 1.0000 1.0000 1.000 1.000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1082 1.1081 1.1050 1.1078 1.1045 1.1071 1.1037 1.1060 1.1025 1.1046 1.1010 1.1027 1.0991 1.1006 1.0969 1.0980 1.0944 1.0951 1.0917 1.0892 1.0871 1.0856 1.0840 1.0828 1.0824 1.0824 1.0822 1.0819 1.0815 1.0809 1.0801 1.0803 1.0807 1.0809 1.0807 1.0800 L0788 L0768 1.0747 1.0743 1.0773 1.0806 1.0838 1.0868 L.0892 1.0909 1.0921 1.0928 L0932 1.0934 1.0932 1.0942 1.0958 1.0972 1.0990 1.1016 1.1037 1056 1.OOM L0800 1.0000 1.0000 L0000 1.0000 1.0921" 1.0892 L.0868 1.0852 1.0837 1.0828 1.0828 1.0859 1.0835 1.0836 1.0835 1.0830 1.0824 1.0827 1.0833 1.0886 1.0885 1.0828 1.0815 1.0795 1.0775 1.0775 1.0809 1.0840 1.0864 1.0886 1.0902 1.0914 1.0921 1.0924 1.0927 1.0929 1.0928 1.0938 1.0956 1.0971 1.0991.
1.1018 1.1041 1.1060 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1114 1.1151 1.1109 1.1143 1.1100 1.1182 1.1087 1.1116 1.1069 1.1094 1.1047 1.1069 1.1022 1.1040 1.0993 1.1008 1.0961 1.0973 1.0926 1.0984 1.0893 1.0895 L0865 1.0864 1.0849 1.0849 1.0839 1.0845 1.0836 1.0851 1.0842 1.0864 1.0851 1.0880 1.0858 1.0893 1.0864 1.0903 1.0867 1.0911 1.0866 1.0914 1.0802 1.0918 1.0885 1.0916 1.0871 1.0920 1.0878 1.0919 1.0870 1.0912 1.0861 1.0899 1.0846 1.0879 1.0823 1.0852 1.0803 1.0831 L.085 L0838 1.0837 1.0859 1.0863 1.0876 1.0879 1.0883 1.0891 1.0885 1.0899 1.0884 1.090 1.0895 1.0914 1.0900 1.0917 1.0907 1.0924 1.0928 1.0983 1.0943 1.0937 1.0959 1.0952 1.0983 1.0973 1.1009 1.0991 1.03 1.1013 1.1057 1.1042 1.I086 1.1065 1.1108 1.1083 1.1125 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 L0000 1.0000 1.0000 1.0000 1.O000 1.00O0 140DO HM 19 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000.
1.0000 1.0000 1.0000 1.0000 L9000 1.0000 1.0000 1.0000 1.1191 1.1231 1.1268 1.1181 1.1219 1.1254 1.1167 1.1202 1.1235 1.1147 1.1179 1.1209 1.1122 1.1151 1.1177 1.1093 1.1117 1.1189 1.1060 1.1080 1.1099 1.1025 L 1042 1.1057 L0986 1.1000 1.1011 1.0943 1.0952 1.0960 1.0899 1.0903 1.0906 1.0864 1.0865 1.0864 1.0851 1.0853
. 1.0853 1.0855
,' 1.0866 1.0874 1.0874 1.0899 1.0917 1.0896 1.0930 1.0955 1.0918 1.0958 1.0989 1.0937 1.0984 L1021 L0953 1.1006 L1048 1.0966 L1025 1.1071 1.0974 L1038 1.1090 1.0978 L1047 1102 1.0981 1.1049 1.1108 1.0980 1.1043 1.1095 1.0974 1.1031 1.1079 1.0961 1.1012 1.1056 1.0941 1.0986 1.1025 L0915 1.0951 1.0985 1.0883 1.0918 1.0942 1.0861 1.0890 1.0919 1.0861 1.0889 1.0917 1.0874 1.0887 1.0906 1.0879 1.0880 1.0890 1.0877 1.0868 L.0869 1.0807 1.0846 1.0837 1.0858 L0828 L0809 1.0870 L0844 1.0826 1.0879 1.0856 1.0840 1.0894 1.0879 L0868 1.0924 1.0926 1.0925 1.0961 LO981 L0994 1.0994 L1033 1.1059 1.1029 1.1081 1.1116 1.1064 1.1124 1.1165 1.1094
.1.1162 1.1209 1.1122 1.1194 1.1244 1.1150 1.1219 1.1269 1.1170 L1238 L1286 1.1185 1.1251 1.1298 1.0000 1.0000 1.0000 1.0000 L0000 1.0000 1.0000 L00L00 0000 1.0000 1.000 L0000 1.0000 1.0000 L0000 1.0000 1.0000 L.00 Page 15 of 15
ATTACHMENT 2 TO AEP:NRC:6565 Unit 2 Cycle 16 Core Operating Limits Report Revision 0
D. C. COOK UNIT 2!CYCLE 16.
Revision 0 Donald C. Cook Nuclear Plant Unit 2 Cycle 16 Core Operating Limits Report Revision 0 Page 1 of 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 D. C. COOK UNIT 2 CYCLE 16 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report(COLR) for the Donald C. Cook Nuclear Plant Unit 2 Cycle 16 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.
IA, Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification, February 1994
- d.
WCAP-10266-P-A, Rev. 2, The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code, March 1987
- e.
WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995
- f.
WCAP-8745-P-A, Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT 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 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 (FNmj) 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 Page 2 of 16
D. C. COOK UNIT 2 CYCLE 16 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 Safety Limits (Specification 2.1.1)
In Modes 1 and 2, the combination of thermal power, pressurizer pressure, and the highest loop average temperature (T8.,) shall not exceed the limits a's 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 orequal to 1.3% Ak/k for T,,.> 200°F Shutdown margin shall be greater than or equal to 1.0% Ak/k for T, < 200OF
.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. IOE-4 Ak/k/OF.
This limit is based on a T.,, program with HFP vessel T., of 571.0 to 576.0 OF 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 16
D. C. COOK UNIT 2 CYCLE 16 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/OF at a HFP vessel T,,, 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/kPF.
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 -3.90E-4 Ak/k/OF at a HFP vessel T.,, 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 MWDIMTU.
Page 4 of 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 2.3.2 Heat Flux Hot Channel Factor (Fq(Z)) (Specification 3.2.1) cFQ
- K(Z) for P >'0.5 F*" (Z)*-CF
- K(Z) for P>O0.5 P
Fw(Z)<2*CFQ
- K(Z) for P< 0.5 P
F~w(Z):52 CFQ *K(Z) for P:50.5 THERMAL POWER Where:
P = RATED THERMAL POWER
- a..CFO
=2.335
- b. K(Z) is provided in Figure 4.
- c. eQ(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 I for +5% AFD target band.
- e. F'(Z)--
(Z))x W(Z)x F,
- f. For Cycle 16, FP = 1.02 for all burnups associated with Note 2.a of SR 3.2.1.2, except as shown in the table below. When no penalty is required, Fr = 1.00.
Cycle Fp Burnup Penalty (MWD/MTU)
Multiplier 0
1.020 150 1.020 317 1.024 484 1.054 651 1.063 818 1.060 985 1.056 1152 1.052 1319 1.048 Page 5 of 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 1486.
1.043 1653 1.038 1820 1.033 1987 1.028 2154 1.024 2322 1.020 The bumup range only covers where Fp exceeds 1.02. Linear adequate for intermediate cycle burnups.
Nuclear Enthalpy Rise Hot Channel Factoi (Fsaa) (Specification 3.2.2)
FAHq< CFmn* (1 + PFm *(l-P))
Where:
P_=
TT MALPOWER RATED THERMAL POWER interpolation is 2.3.3
- a. CFfi= 1.58
- b. PFA= 0.3 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 16
D. C. COOK VNIT 2 CYCLt 16 Revisi0ja 0 -
2.5 REACTOR COOLANT SYSTEM 2.5.1 RCS Prssurd,' Termperature, and Flow Departure from Nucleate Boiling (DNB)
Limits (Specification 3.4.1)
- a. Pressurizer Pressure shall be;> 2172.4 psig +
- b. Reactor Coolant System T'7, shall be ý- 580.1 OF +
- c. Reactor Coolant System Total Flow Rate shall be Ž366,400 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.,,, and 2200 psig for Pressurizer Pressure.
+.This' concentration bounds the condition -of Kfr < 0.95 which includes a 1% Ak/k conservative allowance. for uncertainties. The boron concentration of 2400.ppm -includes a 50.ppm conservative allowance for uncertainties.
Page 7 of 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 D.C. COOKUNI[2 CCLE16 Rvison FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT. (MTC) LIMITS 1.0 0.5 1-'
0 0T-0.0
-0.5
-I
-c~TL Op.TO-I
[NACCEPTABLE OPERATION ACCEPTABLE OPERATION]
-1.0 0
10 20 30 40 50 60 70 80 90 100 Percent Rated Thermal Power Page 8 of 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 D.CICOKUNT CCL i1 ReIisiim n
FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (FOUR-LOOP OPERATION) 250 225
[(52.9%, 228) 100 Step Overlap 200 B-KC 10 (00100
%,1
-. 175 0
0:
1 0
-000 30 40
'50 60 70 POWER (% of Rated Thermal Power)
Page 9 of 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 D.
C.
COOK UN~~~IT YLE1 evsol FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 "j
1
(-11,90)
(U11,90)
UNACCEPTABLE UNACCEPTABLE
_0 OPERATION OPERATION 70
-0_
X 39ll.
L4 ACCEPTABLE 60
/
OPERATION o
5o
- 0.
(-1,50)(+31,50) 1--
J40 E
E 30 20 0
0 10
-50
-40
-30
-20 A10 0
- 10 20 30 40 FLUX DIFFERENCE (DELTA-I)
Page 10 of 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 D.C. COOK UNIT 2 CYCLE 16 Revision 0 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 1.0
(.9 Zz ILu N
0z 0.8 0.6 0.4 (0.0,1.0)
(6.0,1.0)
(12.0, 0.925) 0.2.
0 0
2 4
6 8
10 12 CORE HEIGHT (FT)
Page II of 16
D. C. COOK UNIT ICYCLE 16 Revision 0 FIGURE s (Page I of 2)
Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Ovei-temperature AT:AT [K1-K2
[1+..
s 1(T-;+
K3(P-P")-fdAI)J L1+rzsJ Where:
AT
= Measured RCS AT, OF AT.
=
Indicated AT at RATED THERMAL POWER, -F T
=. Average temperature, *F Nominal T.,; at RATED THERMAL POWER, (_5 576.0°F)
P
=
Pressurizer Pressure, psig P
=
Nominal RCS operating pressure (2235 psig) 1+rls 1
The function generated, by the lead-lag controller for T., dynamic compensation c1, r2.
Time constants utilized in the lead-lag controller for T.,
VI >728secs. '92<4secs.".
S Laplace trýnsform operator, sec" KK 1.19" K2 0.01331/ 0F K.3 0.00058/psig f1(Al)
= -3.5 {33%+(qt-qb)}
whenq,-qb_<-33%RTP
.0%.ofRTP when -33% RTP < qt"- qbh -6% RTP
+l.0 {(qt - qb) - 6%}
when q, -qb > 6% RTP where q* and qb aie percent RATED THERMAL POWER in the upper and lower halves of the core respectively, and q, + 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 16
D.- C. COOK UNIT 2 CYCLE 16 Revision O'.
FIGURE 5 (Page 2 of 2)
Overpower AT Trip Setpoint Overpower AT SAT. K4,- K5 [
T - K, ( O-T" -f1 (A)j L1 + TsJ Where:
AT
=
Measured RCS AT, OF AT.
=
Indicated AT at RATED THERMAL POWER, *F T
=
Average temperature, OF T""
Nominal T. at RATED THERMAL POWER, (< 576.0 *F)
K4 1.16" Ks 0.02/*F for increasing average temperature; K&= 0 for decreasing average temperature K6 0.00197PF for T greater than rT; Ke= for T less than or equal toT" The function generated by the rate lag controller for T,, dynamic 1 +?rS compensation
=
Time constant utilized in the rate lag controller for T.3
- > 10 secs.
S f
Laplace.transform operator, sec" f2 (AI) =
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 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 D.C OKU IT 2I CYLE16Reisin FIGURE 6 Reactor Core Safety Limits LL. 620 610 I.--
Fi.c~
CO.600 0
0.8 0"
0.2 0.4
.0.6 I
1.2 PRESSURE (psia) 1775 2000 2100 2250 Power (fraction of rated thermal power)
DESCRIPTION OF SAFETY LIMITS Power Tavg Power Tavg Power.
Tavg Power Tavg (frac)
F)
(frac)
(F)
(frac)
(OF)
(frac)
(a F) 0.00 615.4 0.98 583.8 1.02 580.9 1.2 558.1 0.00 631.8 0.86 605.8 0.96 597.5 1.2 568.5 0.00 639.14 0.82 614.0 0.96 601.6 1.2 673.1 0.00 649.2 0.72 628.6 0.98 605.2 1.2 5680.4 2400 0.00 65910 0.62 642.0 1.1 599.0 1.2 588.1 UNIT 2 Reactor Core Safety Limits Page 14 of 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 FIGURE 7 Unit.2 Cycle 16 Predicted 1[FP ARO 300 PPM MTC Versus Burnup I.
0 I.2 U
I 2
S I-
-2.54E-041 16000 17000 18000 19000 Cycle Bumu p (MWDIMTU) 20000 Bumup (MWDIMTU)
MTC (AMF) 16000
-2.4118E-4 17000
-2.4444E-4 18000
-2.4777E-4 "19000
-2.5075E-4 20000
-2.5360E-4
. Page 15 of 16
D. C. COOK UNIT 2 CYCLE 16 Revision 0 TABLE 1
. Cook Unit 2 Cycle i6 W(Z) Function Node Height Bumup (MWD/MTU)
PT (Ft.)
150 1000 2000 4000 5000 6000 8000 10000 12000 14000 16000 11000 20000 20910 3
0.00 1.0000 1.0000 1.0000
.o0oo 1.0000 I.OOo 1.0000 I.00OO 1.00O0 1.0000 1.0000 1.0000 L.0O0O 1.0000 2
0.20 1.0000 1.0000 1.0000 1..0000 1.000 1.0000 1.0000 i.0000 1.0000 1.0000 3.0000 i.0000 1.0000 1.0000 3
0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4
0.60 1.1207 1.1151 1.1095 1.1024 1.1011 1.1016 1.1061 1.1130 1.1200 1.1271 1.1348 1.1433 1.1509 1.3543 5
0.10 1.1208
!.1141 1.1075 1.0994 1.0982 1.0991 1.1053 "
.1140 1.1219 1.1289 1.1358 1.1433 1.1506 1.1539 6
3.00 1.1199 1.1133 1.1069 1.0990.
1.0979 1.0990 1.1056
.1344 1.1222 1.1290 1.1355-1.1424 1.1494 1.1526 7
1.20 1.1188 1.1126 1.1067 1.0995 1.0986 1.0997 1.1060 1.1144 1.1213 1.1282 1.1343.
1.1407 1.1472 1.1502 8
3.40 1.1171 1.1116 1.1062 1.0993 1.0991 1:1002 1.1061 1.1140 1.1209 1.1268 1.1323
.1.1381
.1.1442 1.1469 9
1.60 1.1151 1.1102 1.1055 1.0999 1.0993 1.1004 1.1060 1.1132 1.1195 1.1249 1.1298 1.1350 1.1404 1.1429 10 1.80
.1.1126 1.1084 1.1044 1.0997 1.0993 1.1003 1.1054 1.1120 1.1176 1.1223 1.1267 1:13 2 1.1360 1.1381 11 2.00 1.1097 1.1062 1.1029 1.0992
- 1.0989 1.1000 1.1045 1.1102 1.1151 1.1192 1.1229 1.1267 1.1308 1.1327 12 2.20 1.1064 1.1037 1.1012 1.0984 1.0984 1.0993 1.1033 1.1081 1.1122 1.1156 I.I!86 3.1216 1.1250 1.1265 13 2.40 1.1028 1.1009 1.0991 1.0973 1.0975" 1.0983 1.1016 1.1055 L.I08N 1.1114 1.1137
.1.1159 1.1115 1.1196 14 2.60 1.0985 1.0977 1.096 1.90 1.0963 1.0971 1.0997 1.1026 1.1049 1.1067 1.1082 1.1095 1.1113
-1.3121 15 2.80 1.0945 1.0943 1.0941 1.0944 1.0948 1.0955 1.0973 1.0992 1.1006 1.1016 1.1022 1.1027 1.1036 1.1040 16 3.00 1.0901 31.0906 1.0912 1:0924 1.0930 1.0936 1.0947 1.0956 1.0960 1.0961 1.0958 1.0953 1.0952 1.0951 17 3.20 1.0162 1.0173 1.0835 1.0903 1.0910 1.0915 1.0919 1.0919 1.0915 1.0908 1.0897 1.0833 1.0874 1.0870 I8 3.40 1.0841 1.0854 1.0968 1.0S87 1.0893 1.0895 1.0892 1.0886 1.0879 1.0874 1.0168 1.0861 1.0854 1.0852 19.
3.60 1.0852 1.0862 1.0872 1.0884 1.0886 1.0883 1.0873 1.0864 1.0867 1.0879 1.0900 1.0925 1.0941 1.0948 20 3.10 1.0877 1.0880 1.0133 1.0883 1.0830 1.0874 1.0858 1.0851 1.0864
. 1.0894
.1.0941 1.0998 1.1035 1.1052 21 4.00 1.0907 1.0900 1.0893 1.0879 1.0872 1.0864 1.0851 1.0852 1.0876 1.0920 1.0984 1.1062 1.1114 1.1138 22 4.20 1.0934 1.0916 3.0898 1.0871 1.0862 1.0856 1.0854 1.0369 1.0905 1.0961 1.1035 3.3324 3.3117 1.1216 23 4.40 1.0959 1.0930 1.0901 1.0861 1.0851 1.0849 1.0861 1.0893 1.0942 1.1006 1.1016 1.1180 1.1252 1.1284 24 4.60 1.0982 1.0941 1.0901 1.0849 1.0839 1.0839 1.0865 1.0915 1.0976 1.1041 1.1133 1.1230 1.1309 1.1345 25 4.10 1.1001 1.0952 1.0904 1.0842 1.0831 1.0834 1.0871 1.0934 1.1005 1.1083 1.1173 1.1274 1.1359 1.1398 26 5.00 1.1017 1.0961 1.0907 1.0839 1.0827 1.0832 1.0878.
1.0950 1.1029 1.1112 1.1205 1.1310 1.1400 1.1441 27 5.20 1.1029 1.0961 1.0908 1.0834 1.0822 1.0829 1.0812 1.0963 1.1048 3.1135 1.1231 1.1337 1.1431 1.1473 28 5.40 1.1036 1.0970 1.0906 1.0827 1.0815 1.0823 1.0813 1.0971 1.1061 1.1151
!.1248 1.1355 1.1451 1.1495 29 5.60 1.1038 1.0963 1.0901 1.0117 1.0305 1.0814 1.0830 1.0975 1.1069 1.3360 1.1257 1.1363 1.1460' 1.1504 30 5.80 1.1035 1.0962 1.0891 1.0804 1.0791 1.0802 1.0873 1.0973 1.1069 1.1161 1.1256 1.1360 1.1456 1.1500 31 6.00 1.1026 1.0950 1.0877 1.0787 1.0775 1.0787 1.0861 1.0965 1.1063 1.3154 1.1246 1.1346 1.1441 1.1484 32 6.20 1.1011 1.0933 1.0851 1.0766 1.0754 1.0767 1.0844 1.0951 1.1048 1.3137 1.1225 1.1320 1.1412 1.1454" 33 6.40 1.0989 1.0910 1.0834 1.0741 1.0729 1.0742 1.0822 1.0929 1.1025 1.1111 1.1194 1.1283 1.1371 1.14r" 34 6.60 1.0961 1.0184 1.0809 1.0711 1.0706.
1.0719 1.0797 1.0901 1.0993 1.1074 1.1152 1.1234 1.1317 1.1355 35 6.80 1.0921 1.0847 1.0776 1.0689 1.0677 1.0689 1.0761 1.0859 1.0946 1.1022 1.1094 1.1171 1.1249 1.1285 36 7.00 1.0883 1.0121 1.0756 1.0676 1.0665 1.0677.
1.0745
.1.0836 1.0918 1.1 1.0060 1.1134 1.1208 1.1242 37 7.20 1.083 1.0823 1.0760 1.0684 1.0673 1.0684 1.0749 1.0837 1.0916 1.0987 1.1056 1.1130 1.1203 1.1237 38 7.40 1.0915 1.0852 1.0790 1.0714 1.0704 1.0715 1.0780 1.0866 1.0939 1.1000 1.1057 1.1115 1.1178 1.1206
- 39.
7.60 1.0938 1.0875 1.0815 1.0741 1.0731 1.0743 1.0807 1.0890 1.0958 1.1011 1.1057 1.1103 1.1157 1.1181 40 7.80 1.0954 1.0894 1.0835 1.0763 1.0754 1.0765 1.0828 1.0908 1.0970 1.1016 1.1052 1.1087 3.1132 1.1153
.41 1.00 1.0967 3.0908 1.0851 1.0782 1.0774 1.0785 1.0846 1.0921 1.0977 1.1014 1.1039 1.1062 1.1097
.1.1113 42 8.20 1.0974 1.0918 1.0863 1.0797 1.0789 1.0799 3.0851 1.0929 3.0978 1.1006 1.1021 1.1032 1.1058 I1069 43 8.40 1.0976 1.0922 1.0870 1,0806 1.0799 1.0809 1.0866 1.0932 1.0975 1.0995 3.1000 1.0999 1.1015 1.1023 44 1.60 1.0973 1.0923 1.0870 1.0809 1.0802 1.0813 1.0870 1.0933 1.0969 1.0977-1.0968 1.0949 1.0952 1.0954 45 8.80 1.0964 1.0917 1.0871 1.0815 1.0809 1.0818 1.0869 1.0928 1.0963.
1.0975 1.0973 1.0964 1.0973 1.0977 46 9.00 1.0957 1.0917 1.0878 1.0832 1.0827 1.0837 1.0882 1.0937 1.0976 1.0999 1.1012 1.1022 1.1043 1.1053 47 9.20
.1.0964 1.0927 i.0892 1.0854 1.0855 1.0871 1.0930 1.0996 1.1038 1.1058 1.1062 1.1060 1.1076 1.1083 48 9.40 1.1020 1.0974 1.0931 1.0883 1.0183 1.0900 1.0969 1.1045 1.1091 1.3109 1.1109 1.1098 1.1112 1.1118 49 9.60 1.1075 1.1025 1.0976 1.0922 1.0921 1.0939 1.1011 1.1090 1.1138 1.1155 1.1151 1.1137 1.1149 1.1154 50 9.80 1.1125 1.1072 1.1021 1.0963 1.0961 1.0979 1.1053 1.1133 1.1181 1.1197 1.1190 t.I!73 1.3183 1.1188 51 10.00 1.1173 1.!116 1.1062 1.1000 1.0997 1.1014 1.1089 1.1172 1.1220 1.1235 1.1221 1.1209 1.1218 1.1222
-52 10.20 1.12 1.1157 1.1100 1.1034 1.1030 1.1047 1.1123 1.1206 1.1255 1.1271 1.1264 1.3246 1.1255 1.1260 53 10.40 1.16 1.1194 1.1135 1.1065 1.1060 1.1076 1.1152 1.1235 1.1284 1.1300 1.1293 1.1275 3.1285 1.1289 54 10.60 1.1218 1.1225 t.1163 3.1090 1.1084 1.1100 1.1174 1.1258 1.1306 1.1322 1.1315 1.1297 131306 1.1311 55 10.20 1.1316 1.1251 1.1187 1.1111 1.1103 1.1118 1.1192 1.1275 1.1323 1.1338 1.1331 1.1313 1.1322 1.1326 56 33.00 1.1337 1.1270 1.1205 1.1126 1.3118 1.1132 1.1205 1.1287 1.1333 1.1349 1.1341 1.1322 1.1331 1.1335 57 11.20 1.1352 1.1283 1.1217 1.1136 1.1126 1.1140 1.1212 1.1295 1.1341 1.1354 1.1344 1.1323 1.1330 1.1334 52 11.40 1.1359
. 1.1289 1.1221 1.3338 1.1128 1.1141 1.1213 1.1295 1.1341 1.1352 1.1340 1.1316 1.1322 1.1324 59 11.60 1.0000 1.0000 1.0000 10
.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3.0000 1.0000 1.0000 1.0000-60 13.80 3.000.0 1.0000
!.000 1.0000 3.000 1.0000 1.0000 1.0M 00D I.
1.00.
1.0000 1.0000 1.0000 1.0000 1.0000 61 12.00 1.0000 1.000 L.N0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3.0000 Top and bottom 5% of core excluded.
Page f6 of 16