ML11215A147: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(5 intermediate revisions by the same user not shown)
Line 1: Line 1:
{{Adams
#REDIRECT [[AEP-NRC-2011-49, Revised Core Operating Limits Report]]
| number = ML11215A147
| issue date = 07/21/2011
| title = Donald C. Cook, Unit 2 - Revised Core Operating Limits Report
| author name = Gebbie J P
| author affiliation = Indiana Michigan Power Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000316
| license number =
| contact person =
| case reference number = AEP-NRC-2011-49
| document type = Fuel Cycle Reload Report, Letter
| page count = 18
}}
 
=Text=
{{#Wiki_filter:Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place IERBridgman, MI 49106 PCMEROAEP~corn A unit of American Electric Power July 21, 2011 AEP-NRC-2011-49 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 REVISED CORE OPERATING LIMITS REPORT Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 2, is submitting a revised Core Operating Limits Report (COLR) for Unit 2 Cycle 19 in accordance with Technical Specification 5.6.5. The Unit 2 Cycle 19 COLR has been revised to reflect a new large-break-loss-of-coolant accident analysis approved by the Nuclear Regulatory Commission as License Amendment 297, (ADAMS Accession No. ML1 10730783).
Revision 1 of the Unit 2 Cycle 19 COLR is provided as an enclosure to this letter.There are no new or revised commitments in this submittal.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.Sincerely, Joel P. Gebbie Site Vice President JRW/jen
 
==Enclosure:==
 
Donald C. Cook Nuclear Plant Unit 2 Cycle 19 Core Operating Limits Report, Revision 1 c: J.T. King, MPSC S. M. Krawec, AEP Ft. Wayne, w/o enclosure MDEQ -WHMD/RPS NRC Resident Inspector M. A. Satorius, NRC Region III P. S. Tam, NRC Washington DC ENCLOSURE TO AEP-NRC-2011-49 Donald C. Cook Nuclear Plant Unit 2 Cycle 19 Core Operating Limits Report Revision 1 D. C. COOK UNIT 2 CYCLE 19 Revision 1 D. C. COOK UNIT 2 CYCLE 19 Revision 1 Donald C. Cook Nuclear Plant Unit 2 Cycle 19 Core Operating Limits Report (COLR)Revision 1 Page 1 of 16 D. C. COOK UNIT 2 CYCLE 19 Revision I 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 19 has been prepared in accordance with the requirements of Technical Specification 5.6.5.The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the Nuclear Regulatory Commission (NRC) in: a. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985 b. WCAP-8385, Power Distribution Control and Load Following Procedures
-Topical Report, September 1974 c. WCAP-10216-P-A, Rev. IA, Relaxation of Constant Axial Offset 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 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 SLs [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 (FNMI)3.2.3 AXIAL FLUX DIFFERENCE (AFD)3.3.1 Reactor Trip System (RTS) Instrumentation 3.4.1 RCS [Reactor Coolant System] 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 19 Revision 1 2.0 OPERATING LIMITS The cycle-specific parameter limits listed in Section 1.0 are presented in the following subsections.
These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6-5.2.1 SAFETY LIMITS 2.1.1 Reactor Core SLs (Specification 2.1.1)In Modes I 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 1.8% Ak/k for Tavg > 200'F Shutdown margin shall be greater than or equal to 1.0% Ak/k for Tavg < 200'F 2.2.2 Moderator Temperature Coefficient (MTC) (Specification 3.1.3)a. The MTC limits are: The BOL/ARO-MTC shall be less positive or equal to the value given in Figure 1.The EOL/ARO/RTP-MTC shall be less negative or equal to -4.1 OE-4 Ak/kF.This limit is based on a Ta.g program with HFP vessel Tavg 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 19 Revision I b. The MTC Surveillance limit is: The 300 ppm/ARO/RTP-MTC should be less negative or equal to -3.20E-4 Awk/&deg;F at a HFP vessel Tavg of 571:0 to 576.0 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 A/k/kF.If the. Revised Predicted MTC is less negative than the Surveillance Requirement 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/&deg;F at a HFP vessel Tavg of 571.0 to 576.0 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 burnup0.0 MWD/MTU [Megawatt Days/Metric Ton Uranium].Page 4 of 16 D. C. COOK UNIT 2 CYCLE 19 Revision 1 D. C. COOK UNIT 2 CYCLE 19 Revision 1 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2.1)CF~O Foc (z)! <---=
* K(z)FJ (Z)< 2
* CFO
* K(Z)Fow" (Z) < C-
* K(Z)-P Fow (Z)! 2
* CF
* K(Z)for P > 0.5 for P_< 0.5 for P > 0.5 for P _ 0.5 THERMAL POWER RATED THERMAL POWER a. CFQ = 2.335 b. K(Z) is provided in Figures 4.c. FQ(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. FQ (Z) = FQ (Z) x W(Z) x F, The W(z) values are generated assuming that they will be used for a full power surveillance.
When a part power surveillance is performed, the W(z) values should be multiplied by the factor 1/P, when P is > 0.5. When P is < 0.5, the W(z) values should be multiplied by the factor 1/(0.5), or 2.0. This is consistent with the adjustment in the FQ(z) limit at part power conditions.
Page 5 of 16 A C. COOK UNIT 2 CYCLE 19 Revision I f. For Cycle 19, 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.Cycle Fp Bumup Penalty (MWD/MTU)
Multiplier 0 1.020 150 1.032 317 1.040 484 1.039 651 1.037 818 1.035 985 1.032 1153 1.030 1320 1.028 1487 1.026 1654 1.026 1821 1.027 1988 1.029 2155 1.032 2322 1.034 2489 1.036 2656 1.038 2824 1.039 2991 1.039 3158 1.037 3325 1.035 3492 1.031 3659 1.028 3826 1.023 4000 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 (FNAH) (Specification 3.2.2)F N A<-I CFA * (1 + PFAH *(l-P))THERMAL POWER RATED THERMAL POWER a. CFr= 1.58 b. PFAn= 0.3 Page 6 of 16 D. C. COOK UNIT 2 CYCLE 19 Revision 1 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 T.vg 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 RCS, 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 577.87F for Tavg, and 2200 psig for Pressurizer Pressure.+ This concentration bounds the condition of Keff < 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 19 Revision I FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 0.5 0 x 0.0-0.5 UNACCEPTABLE OPERATION ACCEPTABLE OPERATION 0 10 20 30 40 50 60 70 80 90- 100 Percent Rated Thermal Power-1.0 Page 8 of 16 D. C. COOK UNIT 2 CYCLE 19 Revision I FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 250 225 200 0~U)0 T-0 0~W 175 150 125 100 75 50 25 0 0 10 20 30 40 50 60 70 80 90 100 POWER (% of Rated Thermal Power)Page 9 of 16 D. C. COOK IJNIT 2 CYCLE 19 Revision I FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP)x N X3LL0 0 E 0 100 90 80 70 60 50 40 30 20 10 0 FLUX DIFFERENCE (DELTA-I)Page 10 of 16 D. C. COOK UNIT 2 CYCLE 19 Revision 1 FIGURE 4 K(Z) -NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 1.0 (D z a-N!5-1J 0 z 0.8 0.6 0.4 (0.0,1.0)
(6.0, 1.0)(12.0, 0.925)0.2 0 h d 0 2 4 6 8 10 12 CORE HEIGHT (FT)Page 11 of 16 D. C. COOK UNIT 2 CYCLE 19 Revision 1 FIGURE 5 (Page 1 of 2)Reactor Trip System Instrumentation Trip Setpoints Overtemperature AT Trip Setpoint Overtemperature AT  AT, [KI -K2 L + c2S (T-V) + K3 (P-P) 4 1 l1 + -.S]Where: AT = Measured RCS AT, OF AT, = Indicated AT at RATED THERMAL POWER, OF T = Average temperature, OF TV = Nominal Tavg at RATED THERMAL POWER, (5 576.0 0 F)P = Pressurizer Pressure, psig P' = Nominal RCS operating pressure (2235 psig)L + S = The function generated by the lead-lag controller for T.,9 dynamic compensation r 1, "r2 = Time constants utilized in the lead-lag controller for Tavg T 1 > 28 secs. r2 < 4 secs.S = Laplace transform operator, sec-1 K, <_ 1.19 *K2 > 0.01331/&deg;F K3 > 0.00058/psig fl (Al) = -3.5 {33% + (q, -qb)} when qt -qb <-33% RTP 0% of RTP when -33% RTP < qt -qb 5 6% RTP+1.0 {(qt -qb) -6%} when q, -qb > 6% RTP where q, and qb are 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 19 Revision 1 D. C. COOK UNIT 2 CYCLE 19 Revision 1 FIGURE 5 (Page 2 of 2)Overpower AT Trip Setpoint Overpower AT < ATo [K 4-K 5 TS I 1 + 'T -K 6 (T -T") -f 2 (A)]Where: AT = Measured RCS AT, 'F AT 0 T= Indicated AT at RATED THERMAL POWER, 'F= Average temperature, 'F T" = Nominal T,9 at RATED THERMAL POWER, (< 576.0 &deg;F)K4 _ 1.16*K 5  > 0.02/'F for increasing average temperature; Ks = 0 for decreasing average temperature K 6  > 0.00 197/'F for T greater than T" ; K6=0 for T less than or equal to T" 7 3 S The function generated by the rate lag controller for Tavg dynamic compensation T-lr3S ,r3 = Time constant utilized in the rate lag controller for Tavg; T 3 >- 10 secs.S= Laplace transform operator, seca f 2 (AD = 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 19 Revision I FIGURE 6 Reactor Core Safety Limits 660 650 640 630 LL 620> 610 Cj, 600 U 590 580 570 560 550 0 0.2 0.4 0.6 0.8 1 1.2 PRESSURE (psia)1775 2000 2100 2250 2400 UNIT 2 Power (fraction of rated thermal power)DESCRIPTION OF SAFETY LIMITS Power Tavg Power Tavg Power Tavg Power Tavg (frac) (' F) (frac) (6 F) (frac) (* F) (frac) (4 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 0.00 639.1 0.82 614.0 0.96 601.6 1.2 573.1 0.00 649.2 0.72 628.6 0.98 605.2 1.2 580.4 0.00 659.0 0.62 642.0 1.1 599.0 1.2 588.1 Reactor Core Safety Limits Page 14 of 16 D. C. COOK UNIT 2 CYCLE 19 Revision 1 FIGURE 7 Unit 2 Cycle 19-Predicted HFP ARO 300 PPM MTC Versus Burnup-2.34E-04-2.36E-04-2.38E-04-24.-2.40E-04 0-2.44E-04 E I.-a -2.46E-04 0-2.48E-04-2.50E-04-2.52E-04
-15000 16000 17000 18000 Cycle Burnup (MWd/MTU)19000 Bumup MTC MTC (MWd/MTU) (pcm/&deg;F) (Ak/kIF)15,000 -23.526 -2.3526E-04 16,000 -23.935 -2.3935E-04 17,000 -24.331 -2.4331E-04 18,000 -24.726 -2.4726E-04 19,000 -25.108 -2.5108E-04 Page 15 of 16 D. C. COOK UNIT 2 CYCLE 19 Revision 1 TABLE 1 Donald C. Cook Unit 2 Cycle 19 W(Z) Function Node Point 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 Height (ft)0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 1.80 2.00 2.20 2.40 2.60 2.80 3.00 3.20 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11.40 11.60 11.80 12.00 150 1000 2000 3000 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 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1187 1.1172 1.1156 1.1144 1.1173 1.1150 1.1129 1.1113 1.1154 1 1126 1 1100 1.1080 1.1131 1.1101 1.1072 1.1051 1.1103 1.1078 1.1054 1.1036 1.1071 1.1054 1.1039 1.1027 1.1036 1.1027 1.1019 1.1013 1.0998 1.0997 1.0996 1.0997 1.0956 1.0963 1.0971 1.0977 1.0913 1.0928 1.0944 1.0956 1.0874 1.0895 1.0916 1.0932 1.0850 1.0872 1.0894 1.0910 1 0854 1.0873 1.0891 1.0905 1.0870 1.0884 1.0898 1.0908 1.0894 1.0902 1.0909 1.0913 1.0918 1.0918 1.0918 1.0917 1.0940 1.0932 1.0924 1.0917 1.0960 1.0943 1.0927 1.0914 1.0977 1.0951 1.0927 1.0909 1.0991 1.0957 1.0924 1.0900 1.1000 1.0959 1.0919 1.0890 1.1006 1.0957 1.0910 1.0876 1.1007 1.0950 1.0897 1.0858 1.1002 1.0942 1.0885 1.0844 1.0992 1.0931 1.0872 1.0830 1.0976 1.0914 1.0854 1.0811 1.0954 1.0892 1.0832 1.0789 1.0926 1.0864 1.0805 1.0762 1.0889 1.0829 1.0772 1.0731 1.0853 1.0794 1.0737 1.0696 1.0843 1.0779 1.0717 1.0672 1.0871 1.0799 1.0729 1.0678 1.0895 1.0824 1.0757 1.0708 1.0911 1.0847 1.0786 1.0741 1.0925 1.0866 1.0810 1.0769 1.0934 1.0881 1.0831 1.0794 1.0938 1.0892 1.0848 1.0816 1.0938 1.0898 1.0560 1.0832 1.0928 1.0897 1.0867 1.0846 1.0929 1.0903 1.0879 1.0861 1.0962 1.0932 1.0904 1.0884 1.1015 1.0982 1.0951 1.0929 1.1066 1.1030 1.0997 .1.0974 1.1112 1.1075 1.1039 1.1014 1.1156 1.1117 1.1079 1.1053 1.1196 1.1155 1.1116 1.1088 1.1231 1.1189 1.1148 1.1120 1.1258 1.1215 1.1175 1.1146 1.1283 1.1239 1.1198 1.1168 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 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Bumup (MWD/MTU)4000 5000 6000 8000 10000 12000 14000 16000 18000 20000 20790 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 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 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 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 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1135 1.1129 1.1126 1.1130 1.1151 1.1191 1 1249 1.1324 1.1411 1.1476 1.1502 1.1102 1.1097 1.1097 1.1114 1.1146 1.1190 1.1245 1.1312 1.1387 1.1447 1.1471 1.1068 1 1063 1.1067 1.1095 1.1138 1.1185 1 1236 1.1293 1.1357 1.1412 1.1433 1.1039 1.1035 1.1042 1.1076 1.1124 1.1171 1.1217 1.1266 1.1318 1.1367 1.1386 1.1026 1.1024 1.1031 1.1063 1.1106 1.1148 1.1187 1.1229 1.1273 1.1314 1.1331 1.1021 1.1021 1.1026 1.1051 1.1083 1.1116 1.1149 1.1183 1.1221 1.1255 1.1268 1.1011 1.1012 1.1017 1.1034 1.1057 1.1081 1.1106 1.1133 1.1162 1.1188 1.1199 1.0998 1.1001 1.1004 1.1014 1.1026 1.1041 1.1058 1.1076 1.1097 1.1115 1.1122 1.0983 1.0986 1.0989 1.0990 1.0991 1.0996 1.1005 1.1015 1.1027 1.1036 1.1040 1.0965 1.0970 1.0971 1.0964 1.0955 1.0950 1.0949 1.0951 1.0953 1.0953 1.0952 1.0943 1.0949 1.0949 1.0937 1.0920 1.0907 1.0899 1.0892 1.0886 1.0877 1.0874 1.0922 1.0927 1.0926 1.0910 1.0890 1.0877 1.0870 1.0867 1.0864 1.0858 1.0855 1.0914 1.0916 1.0910 1.0888 1.0867 1.0864 1.0877 1.0903 1.0935 1.0952 1.0959 1.0912 1.0910 1.0902 1.0874 1.0854 1.0862 1.0895 1.0948 1.1014 1.1053 1 1069 1.0913 1.0909 1.0898 1.0872 1.0857 1.0875 1.0922 1.0995 1.1082 1.1138 1.1160 1.0914 1.0908 1.0899 1.0880 1.0876 1.0905 1.0964 1.1048 1.1148 1.1216 1.1243 1.0911 1.0905 1.0899 1.0892 1.0904 1.0944 1.1012 1.1102 1.1209 1.1285 1.1315 1.0905 1.0899 1.0896 1.0902 1.0929 1.0981 1.1056 1.1152 1.1263 1.1347 1.1380 1.0896 1.0890 1.0891 1.0910 1.0952 1.1014 1.1095 1.1196 1.1311 1.1401 1.1436 1.0885 1.0879 1.0883 1.0915 1.0971 1.1043 1.1130 1.1234 1.1350 1.1445 1.1482 1.0872 1.0866 1.0873 1.0917 1.0987 1.1068 1.1159 1.1264 1.1380 1.1478 1.1517 1.0855 1.0849 1.0860 1.0916 1.0998 1.1087 1.1181 1.1286 1.1401 1.1501 1.1541 1.0835 1.0829 1.0842 1.0910 1.1004 1.1100 1.1196 1.1298 1.1410 1.1512 1.1552 1.0819 1.0814 1.0829 1.0903 1.1004 1.1103 1.1199 1.1300 1.1408 1.1509 1.1549 1.0805 1.0800 1.0816 1.0894 1.0997 1.1097 1.1192 1.1290 1.1394 1.1494 1.1533 1.0786 1.0782 1.0799 1.0878 1.0984 1.1083 1.1176 1.1269 1.1369 1.1465 1.1503 1.0764 1.0759 1 0777 1.0858 1.0963 1.1061 1.1150 1.1238 1.1332 1.1424 1.1460 1.0737 1.0733 1.0750 1.0831 1.0935 1.1030 1.1114 1.1197 1.1284 1.1371 1.1406 1.0708 1.0704 1.0721 1.0798 1.0898 1.0987 1.1066 1.1141 1.1219 .1.1300 1.1331 1.0672
* 1.0668 1.0684 1.0759 1.0856 1.0941 1.1016 1.1086 1.1161 1.1237 1.1267 1.0646 1.0640 1.0657 1.0736 1.0836 1.0922 1.0993 1.1059 1.1127 1.1200 1.1228 1.0649 1.0643 1.0663 1.0755 1.0867 1.0953 1.1015 1.1062 1.1108 1.1168 1.1191 1.0680 1.0675 1.0695 1.0785 1.0892 1.0972 1.1024 1.1061 1.1094 1.1145 1.1165 1.0715 1.0711 1.0730 1.0812 1.0910 1.0980 1.1025 1.1054 1.1079 1.1121 1.1138 1.0746 1.0742 1.0759 1.0835 1.0924 1.0986 1.1022 1.1042 1.1057 1.1090 1.1104 1.0773 1.0770 1.0786 1.0854 1.0933 1.0985 1.1013 1.1025 1.1031 1.1056 1.1066 1.0797 1.0795 1.0809 1.0869 1.0938 -1.0981 1.1001 1.1005 1.1003 1.1019 1.1026 1.0816 1.0815 1.0828 1.0882 1.0941 1.0974 1.0983 1.0975 1.0960 1.0965 1.0967 1.0834 1.0833 1.0844 1.0888 1.0935 1.0963 1.0974 1.0971 1.0964 1.0971 1.0974 1.0852 1.0851 1.0861 1.0899 1.0942 1.0972 1.0991 1.1002 1.1010 1.1027 1.1033 1.0874 1.0876 1.0890 1.0940 1.0995 1.1031 1.1049 1.1054 1.1054 1.1068 1.1074 1.0918 1.0920 1.0934 1.0988 1.1047 1.1083 1.1099 11101 1.1096 1.1109 1.1114 1.0962 1.0962 1.0977 1.1034 1.1094 1.1132 1.1147 1.1146 1.1139 1.1151 1.1155 1.1001 1.1002 1.1017 1.1076 1.1140 1.1178 1.1191 1.1188 1.1177 1.1186 1.1190 1.1039 1.1039 1.1055 1.1117 1.1183 1.1221 1.1233 1.1227 1.1213 1.1221 1.1224 1.1073 1.1074 1.1090 1.1154 1.1221 1.1260 1.1273 1.1266 1.1251 1.1258 1.1261 1.1105 1.1105 1.1122 1.1186 1.1255 1.1294 1.1306 1.1297 1.1280 1.1287 1.1289 1.1130 1.1130 1.1147 1.1212 1.1282 1.1322 1.1334 1.1326 1.1309 1.1316 1.1319 1.1152 1.1151 1.1168 1.1234 1.1304 1.1343 1.1353 1.1343 1.1323 1.1328 1.1330 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 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 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 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 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Top and bottom 10% of core excluded.Page 16 of 16}}

Latest revision as of 11:33, 30 April 2019

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML11215A147&oldid=1558514"