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{{#Wiki_filter: | {{#Wiki_filter:Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place Bridgman, MI 49106 POWER AEPcom A unit of American Electric Power November 12, 2007 AEP:NRC:7565 10 CFR 50.4 Docket No.: 50-316' U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 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 17 in accordance with Technical Specification 5.6.5. | ||
Should you have any questions, please contact Ms. Susan D. Simpson, Regulatory Affairs Manager, at (269) 466-2428.Vice President | Revision 0 of the Unit 2 Cycle 17 COLR is provided as an attachment to this letter. | ||
-Site Support Services KAS/jen Attachment c: J. L. Caldwell -NRC Region III K. D. Curry -AEP Ft. Wayne J. T. King- MPSC MDEQ -WHMD/RPMWS NRC Resident Inspector P. S. Tam -NRC Washington DC oll 104A ATTACHMENT TO AEP:NRC:7565 Donald C. Cook Nuclear Plant Unit 2 Cycle 17 Core Operating Limits Report Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UI'41T 2 CYCLE 17 Revision 0 Donald C. Cook Nuclear Plant Unit 2 Cycle 17 Core Operating Limits Report Revision 0 Page 1 of 16 D. C. COOK UNIT 2 CYCLE 17 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 17 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 | There are no new commitments in this submittal. Should you have any questions, please contact Ms. Susan D. Simpson, Regulatory Affairs Manager, at (269) 466-2428. | ||
-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 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 (Fo(Z))3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( | Vice President - Site Support Services KAS/jen Attachment c: J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne J. T. King- MPSC MDEQ - WHMD/RPMWS NRC Resident Inspector P. S. Tam - NRC Washington DC oll 104A | ||
'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 (Tavg) shall not exceed the limits as shown in Figure 6 for 4 loop operation. | ATTACHMENT TO AEP:NRC:7565 Donald C. Cook Nuclear Plant Unit 2 Cycle 17 Core Operating Limits Report Revision 0 | ||
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% 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 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 -4.10E4 Ak/k/0 F.This limit is based on a Tayg program with HFP vessel T.vg 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 16 D. C. COOK UNIT 2 CYCLE 17 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 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 | D. C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UI'41T 2 CYCLE 17 Revision 0 Donald C. Cook Nuclear Plant Unit 2 Cycle 17 Core Operating Limits Report Revision 0 Page 1 of 16 | ||
+ Predicted Correction* | |||
* Predicted Correction is -0.30E-4 Akfk/°F.If the Revised Predicted MTC is less negative than the SR 3.1.3.2 limit (COLR | D. C. COOK UNIT 2 CYCLE 17 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 17 has been prepared in accordance with the requirements of Technical Specification 5.6.5. | ||
* K(Z)P(Z) < | 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 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 (Fo(Z)) | |||
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN1 1 ) | |||
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 ý CYCLE 17 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 (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% 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 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 -4.10E4 Ak/k/0 F. | |||
This limit is based on a Tayg program with HFP vessel T.vg 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 16 | |||
D. C. COOK UNIT 2 CYCLE 17 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 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 Akfk/°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 -3.90E-4 Ak/k/OF 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 burnup | |||
>_0.0 MWD/MTU. | |||
Page 4 of 16 | |||
D. C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2. 1) | |||
Fc (Z) <_ -Q | |||
* K(Z) for P > 0.5 P | |||
F*.(Z) <_2 | |||
* CFQ | * CFQ | ||
* K(Z)(Z) ! | * K(Z) for P:5 0.5 F*' (Z) !_CF* | ||
* K(Z)P Fw (Z) ! | * K(Z) for P > 0.5 P | ||
Fw (Z) !_2 | |||
* CFQ | * CFQ | ||
* K(Z) | * K(Z) for P < 0.5 THERMAL POWER Where: P = RATED THERMAL POWER | ||
: d. W(Z) is provided in Table 1 for +5% AFD target band.e. F" (Z) = FC (Z) x W(Z) x Fp f. For Cycle 17, 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 Burnup (MWD/MTU)0 | : a. CFQ = 2.335 | ||
The boron concentration of 2400 ppm includes a 50 ppm conservative allowance for uncertainties. | : b. K(Z) is provided in Figure 4. | ||
Page 7 of 16 D. C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 0.5 Cb C:)V-x | : 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. | |||
F 0)CA, 0 0 0 0r | : e. F" (Z) = FC (Z) x W(Z) x Fp | ||
(2.0,0.925) 0. | : f. For Cycle 17, 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 Up Burnup Penalty (MWD/MTU) Multiplier 0 1.020 150 1.043 317 1.044 484 1.045 651 1.046 818 1.047 985 1.044 1152 1.040 Page 5 of 16 | |||
-2.56E -2.5815 -2.60E-04 4--16000 17000 18000 19000 Cycle Bumup (MWDIPMTU) | |||
MTC (AkJk/F)16000 -2.4221 E-4 17000 -2.4623E-4 18000 -2.4992E-4 19000 -2.5394E-4 20000 -2.5790E-4 Page 15 of 16 D. C. COOK UNIT 2 CYCLE 17 Revision 0 TABLE 1 D. C. Cook Unit 2 Cycle 17 W(Z) Function Node Height Bumup (MWD/MTU)PT (Ft.) 150 1000 2000 3000 4000 5000 6000 8000. 10000 12000 14000 16000 18000 20000 21000 21720 1 0.00 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 2 0.20 1.0000 1.0000 1.0000 1.0o00 1.oo00 1.0000 1.0000 1.0000 1.0000 1.0000 1.oo00 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1o.00 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 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 5 0.80 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 6 1.00 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 7 1.20 1.1069 1.1001 1.0937 1.0892 1.0870 1.0872 1.0901 1.1013 1.1143 1.1243 1.1315 1.1367 1.1408 1.1467 1.1499 1.1522 8 1.40 1.1065 1.1003 1.0944 1.0903 1.0883 1.0886 1.0913 1.1018 1.1139 1.1232 1.1298 1.1346 1.1383 1.1437 1.1467 1.1488 9 1.60 1.1058 1.1002 1.0949 1.0913 1.0895 1.0898 1.0923 1.1020 1.1131 1.1216 1.1276 1.1319 1.1352 1.1400 f.1427 1.1447 10 1.80 1.1049 1.0999 1.0952 1.0920 1.0904 1.0907 1.0931 1.1018 1.1118 1.1194 1.1247 1.1284 1.1312 1.1354 1.1378 1.1395 11 2.00 1.1036 1.0993 1.0953 1.0926 1.0913 1.0916 1.0937 1.1014 1.1101 1.1167 1.1212 1.1242 1.1265 1.1299 1.1319 1.1334 12 2.20 1.1020 , 1.0985 1.0953 1.0931 1.0921 1.0924 1.0942 1.1007 1.1080 1.1135 1.1171 1.1196 1.1212 1.1240 1.1256 1.1268 13 2.40 1.1002 1.0975 1.0950 1.0934 1.0926 1.0930 1.0945 1,0997 1.1055 .1.1098 1.1126 1.1145 1.1156 ,1.1177 1.1189 1.1198 14 2.60 1.0980 1.0962 1.0945 1.0934 1.0930 1.0933 1.0944 1.0983 1.1026 1.1057 1.1076 1.1087 1.1093 1.1106 1.1114 1.1120 15 2.80 1.0957 1.0947 1.0938 1.0932 1.0931 1.0933 1.0941 1.0966 1.0993 1.1011 1.1022 1.1027 1.1028 1.1034 1.1038 1.1041 16 3.00 1.0930 1.0929 1.0928 1.0928 1.0929 1.0931 1.0935 1.0946 1.0956 1.0962 1.0963 1.0961 1.0956 1.0955 1.0955 1.0955 17 3.20 1.0903 1.0910 1.0916 1.0921 1.0925 1.0926 .1.0926 1.0922 1,0916 1.0909 1.0903 1.0896 1.0889 1.0881 1.0878 1.0876 18 3.40 1.0883 1.0895 1.0906 1.0914 1.0919 1.0919 1.0914 1.0896 1.0877 1.0864 1.0859 1.0859 1.0863 1.0862 1.0860 1.0859 19 3.60 1.0874 1.0887 1.0899 1.0907 1.0911 1.0909 1.0901 1.0876 1.0853 1.0848 1.0859 1.0883 1.0919 1.0943 1.0952 1.0958 20 3.80 1.0868 -1.0880 1.0892 1.0900 1.0903 1.0901 1.0892 1.0864 1.0844 1.0848 1.0875 , 1.0921 1.0983 1.1028 1.1047 1.1060 21 4.00 1.0860 1.0872 1.0883 1.0891 1.0894 1.0892 1.0884 1.0861 1.0846 1.0860 1.0899 1.0960 1.1040 1.1100 1,1126 1.1144 22 4.20 1.0854 1.0863 1.0872 1.0879 1.0883 1.0883 1.0879 1.0865 1.0862 1.0887 1.0936 1.1007 1.1098 1.1169 1.1200 1.1222 23 4.40 1.0854 1.0858 1.0863 1.0868 1.0872 1.0874 1.0875 1.0876 1.0889 1.0925 1.0983 1.1059 1.1153 1.1229 1.1263 1.1288 24 4.60 1.0855 1.0853 1.0853 1.0855 1.0858 1.0862 1.0868 1.0885 1.0915 1.0963 1.1028 1.1107 1.1202 1.1283 1.1320 1.1346 25 4.80 1.0855 1.0848 1.0844 1.0843 1.0846 1.0852 1,0863 1.0893 1.0938 1.0996 1.1067 1.1149 1.1244 1.1329 1.1368 1.1396 26 5.00 1.0853 1.0842 1.0834 1.0832 1.0834 1.0843 1.0857 1.0900 1.0958 1.1025 1. | D. C. COOK UNIT 2 CYCLE 17 Revision 0 1319 1.034 1486 1.028 1653 1.023 2000 1.020 The bumup range only covers where Fp exceeds 1.02. Linear interpolation is adequate for intermediate cycle bumups. | ||
2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (em) (Specification 3.2.2) | |||
FN *H-CF. * (1 + PFk *(l-P)) | |||
THERMAL POWER Where: P = RATED THERMAL POWER | |||
: a. CFAH = 1.58 | |||
: b. PFtAH= 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 UNIT 2 CYCLE 17 Revision 0 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 _Ž 2172.4 psig + | |||
: b. Reactor Coolant System Tavg shall be _ 580.1 'F + | |||
: 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 Ta.g, and 2200 psig for Pressurizer Pressure. | |||
This concentration bounds the condition of If < 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 17 Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0 | |||
[UNACCEPTABLE OPERATION 0.5 Cb JN 0.0 ACCEPTABLE OPERATION] | |||
C:) | |||
V-x | |||
-0.5 | |||
-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 17 Revision 0 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (FOUR-LOOP OPERATION) 250 225 200 F 175 150 0) | |||
CA, 125 0 | |||
100 0 | |||
0 75 0r 50 25 0 | |||
0 10 20 30 40 50 60 70 80 90 100 POWER (% of Rated Thermal Power) | |||
Page 9 of 16 | |||
D, Q. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 90 x 80 Y.N 70 60 It 0 60 IL' 40 E | |||
E 30 20 0 | |||
10 0 | |||
FLUX DIFFERENCE (DELTA-I) | |||
-Page 10 of 16 | |||
A C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 (0.0,, 1.0) _(6.0,1.0) 1.0 (2.0,0.925) 0.8 Z | |||
z Lu w | |||
0.6 | |||
-J N | |||
0 z | |||
0.4 0.2 0 | |||
0 2 4 6 8 10 12 CORE HEIGHT (FT) | |||
Page 11 of 16 | |||
D. C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 5 (Page 2 of 2) | |||
Overpower AT Trip Setpoint Overpower AT < AT° [K4 - K5 I +S 1 1i+r*SJT-K(T-1)-f(A) | |||
Where: AT = Measured RCS AT, IF AT° Indicated AT at RATED THERMAL POWER, IF T = Average temperature, OF T" = Nominal T..g at RATED THERMAL POWER, (:5 576.0 0F) | |||
K4 _< 1.16" Ks > 0.02/°F for increasing average temperature; Ks = 0 for decreasing average temperature K6 > 0.00 197/'F for T greater than T" ; K6g=0 for T less than or equal to T" r3S I + T's The function generated by the rate lag controller for Tav. dynamic compensation t3 = Time constant utilized in the rate lag controller for T.,g; -T3 >g10 sees. | |||
1 S = Laplace transform operator, see f2 (A) = 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 17 Revision 0 FIGURE 6 Reactor Core Safety Limits U. 620 | |||
> 610 I.- | |||
U) 600 0 | |||
0 0.2 0.4 0.6 0.8 '1 1.2 Power (fraction of rated thermal power) | |||
DESCRIPTION OF SAFETY LIMITS Power Tavg Power Tavg Power Tavg Power Tavg PRESSURE (psia) (frac) ( F) (frac) (UF) (frac) (CF) (frac) ( F) 1775 0.00 615.4 0.98 583.8 1.02 580.9 1.2 558.1 2000 0.00 631.8 0.86 605.8 0.96 597.5 1.2 568.5 2100 0.00 639.1 0.82 614.0 0.96 601.6 1.2 573.A 2250 0.00 649.2 0.72 628.6 0.98 605.2 1.2 580.4 2400 0.00 659.0 0.62 642.0 1.1 599.0 1.2 588.1 UNIT 2 Reactor Core Safety Limits Page 14 of 16 | |||
D. C. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 7 Unit 2 Cycle 17 Predicted HFP ARO 300.PPM MTC Versus Burnup | |||
-2.40E -2.42E -2.44E Z-2.48E-04 - | |||
S-2.SOE S-2.52E--04 | |||
-2.56E -2.5815 -2.60E-04 4-- | |||
16000 17000 18000 19000 20000 Cycle Bumup (MWDIPMTU) | |||
Burnup (MWDIMTU) MTC (AkJk/F) 16000 -2.4221 E-4 17000 -2.4623E-4 18000 -2.4992E-4 19000 -2.5394E-4 20000 -2.5790E-4 Page 15 of 16 | |||
D. C. COOK UNIT 2 CYCLE 17 Revision 0 TABLE 1 D. C. Cook Unit 2 Cycle 17 W(Z) Function Node Height Bumup (MWD/MTU) | |||
PT (Ft.) 150 1000 2000 3000 4000 5000 6000 8000. 10000 12000 14000 16000 18000 20000 21000 21720 1 0.00 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 2 0.20 1.0000 1.0000 1.0000 1.0o00 1.oo00 1.0000 1.0000 1.0000 1.0000 1.0000 1.oo00 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1o.00 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 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 5 0.80 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 6 1.00 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 7 1.20 1.1069 1.1001 1.0937 1.0892 1.0870 1.0872 1.0901 1.1013 1.1143 1.1243 1.1315 1.1367 1.1408 1.1467 1.1499 1.1522 8 1.40 1.1065 1.1003 1.0944 1.0903 1.0883 1.0886 1.0913 1.1018 1.1139 1.1232 1.1298 1.1346 1.1383 1.1437 1.1467 1.1488 9 1.60 1.1058 1.1002 1.0949 1.0913 1.0895 1.0898 1.0923 1.1020 1.1131 1.1216 1.1276 1.1319 1.1352 1.1400 f.1427 1.1447 10 1.80 1.1049 1.0999 1.0952 1.0920 1.0904 1.0907 1.0931 1.1018 1.1118 1.1194 1.1247 1.1284 1.1312 1.1354 1.1378 1.1395 11 2.00 1.1036 1.0993 1.0953 1.0926 1.0913 1.0916 1.0937 1.1014 1.1101 1.1167 1.1212 1.1242 1.1265 1.1299 1.1319 1.1334 12 2.20 1.1020 , 1.0985 1.0953 1.0931 1.0921 1.0924 1.0942 1.1007 1.1080 1.1135 1.1171 1.1196 1.1212 1.1240 1.1256 1.1268 13 2.40 1.1002 1.0975 1.0950 1.0934 1.0926 1.0930 1.0945 1,0997 1.1055 . 1.1098 1.1126 1.1145 1.1156 ,1.1177 1.1189 1.1198 14 2.60 1.0980 1.0962 1.0945 1.0934 1.0930 1.0933 1.0944 1.0983 1.1026 1.1057 1.1076 1.1087 1.1093 1.1106 1.1114 1.1120 15 2.80 1.0957 1.0947 1.0938 1.0932 1.0931 1.0933 1.0941 1.0966 1.0993 1.1011 1.1022 1.1027 1.1028 1.1034 1.1038 1.1041 16 3.00 1.0930 1.0929 1.0928 1.0928 1.0929 1.0931 1.0935 1.0946 1.0956 1.0962 1.0963 1.0961 1.0956 1.0955 1.0955 1.0955 17 3.20 1.0903 1.0910 1.0916 1.0921 1.0925 1.0926 .1.0926 1.0922 1,0916 1.0909 1.0903 1.0896 1.0889 1.0881 1.0878 1.0876 18 3.40 1.0883 1.0895 1.0906 1.0914 1.0919 1.0919 1.0914 1.0896 1.0877 1.0864 1.0859 1.0859 1.0863 1.0862 1.0860 1.0859 19 3.60 1.0874 1.0887 1.0899 1.0907 1.0911 1.0909 1.0901 1.0876 1.0853 1.0848 1.0859 1.0883 1.0919 1.0943 1.0952 1.0958 20 3.80 1.0868 -1.0880 1.0892 1.0900 1.0903 1.0901 1.0892 1.0864 1.0844 1.0848 1.0875 , 1.0921 1.0983 1.1028 1.1047 1.1060 21 4.00 1.0860 1.0872 1.0883 1.0891 1.0894 1.0892 1.0884 1.0861 1.0846 1.0860 1.0899 1.0960 1.1040 1.1100 1,1126 1.1144 22 4.20 1.0854 1.0863 1.0872 1.0879 1.0883 1.0883 1.0879 1.0865 1.0862 1.0887 1.0936 1.1007 1.1098 1.1169 1.1200 1.1222 23 4.40 1.0854 1.0858 1.0863 1.0868 1.0872 1.0874 1.0875 1.0876 1.0889 1.0925 1.0983 1.1059 1.1153 1.1229 1.1263 1.1288 24 4.60 1.0855 1.0853 1.0853 1.0855 1.0858 1.0862 1.0868 1.0885 1.0915 1.0963 1.1028 1.1107 1.1202 1.1283 1.1320 1.1346 25 4.80 1.0855 1.0848 1.0844 1.0843 1.0846 1.0852 1,0863 1.0893 1.0938 1.0996 1.1067 1.1149 1.1244 1.1329 1.1368 1.1396 26 5.00 1.0853 1.0842 1.0834 1.0832 1.0834 1.0843 1.0857 1.0900 1.0958 1.1025 1.1I1001,1185 1.1279 1.1366 1.1407 1.1436 27 5.20 1.0849 1.0834 1.0823 1.0818 1.0820 1.0830 1.0848 1.0904 1.0974 1.1049 1,1128 1.1213 1.1306 1.1394 1,1435 1.1466 28 5.40 1.0845 1.0825 1.0809 1.0802 1.0803 1.0815 1.0837 1.0904 1,0986 1.1068 1.1150 1.1234 1.1324 1.1411 1.1454 1.1484 29 5.60 1.0837 1.0813 1.0793 1.0783 1.0784 1.0796 1M0822 1.0899 1.0992 1.1080 1.1164 1.1247 1.1332 1.1418 1.1460 1.1491 30 5.80 1.0827 1,0801 1.0778 10767 1.0767 1.0781 1.0808 1.0893 1.0992 1.1084 1.1168 1.1248 1.1329 1.1412 1.1454 1.1485 31 6.00 1.0814 1.0787 1,0764 1.0752 1.0752 1.0766 1.0795 1.0884 1.0986 1.1079 1.1161 1.1238 1.1314 1.1395 1.1436 1.1466 32 6.20 1.0798 1.0770 1.0747 1.0735 1.0735 1.0750 1.0779 1.0869 1.0973 1.1065 1.1145 1.1218 1.1289 1.1366 1.1406 1.1434 33 6,40 1.0777 1.0750 1.0726 1.0714 1.0715 1.0730 1.0759 1.0850 1.0953 1.1042 1.1119 1.1188 1.1254 1.1326 1.1364 1.1391 34 6.60 1.0752 1.0725 1.0702 1.0691 1.0691 1.0706 1.0735 1.0824 1.0925 1.1011 .1.1084 1.1148 1.1209 1.1276 1.1311 1.1337 35 6.80 1.0725 1.0697 1.0674 1.0662 1.0662 1.0675 1.0704 f.0791 1.0888 1.0970 1.1037 1.1094 1.1145 1.1205 1.1237 1.1260 36 7.00 1.0684 1.0661 1.0642 1.0632 1.0633 1.0647 1.0674 1.0755 1.0845 1,0923 1.0988 1.1044 1.1097 1.1156 1.1188 1.1210 37 7,20 1.0659 1.0634 1.0614 1.0604 1.0605 1.0619 1.0647 1.0732 1.0827 1.0908 1.0975 1.1033 1.1087 1.1149 1.1181 1.1204 38 7.40 1.0685 1.0643 1.0607 1.0585 1.0581 1.0596 1.0631 1.0742 1.0864 1.0956 1.1020 1.1063 1.1093 1.1140 1.1168 1.1188 39 7.60 1.0720 1.0677 1.0640 1.0618 1.0613 1,0627 1.0663 1.0775 1.0896 1.0985 1.1041 1,1076 1.1094 1.1133 1.1157 1.1174 40 7.80 1.0753 1.0716 1.0683 1.0664 1.0660 1.0675 1.0708 1.0810 1.0920 1.1000 1.1049. 1.1077 1.1089 1,1121 1.1141 1.1156 41 8.00 1.0784 .1.0750 1.0719 1.0702 1.0698 1.0712 1.0743 1.0840 1.0942 1.1013 1.`055 1.1075 1.1078 1,1102 1.1118 1.1129 42 8.20 1.0812 1.0781 1.0754 1.0739 1.0736 1.0749 1.0778 1.0866 1.0958 1.1021 1.1054 1.1066 1.1061 1.1077 1.1088 1.1097 43 8.40 1.0837 1.0810 1.0786 1.0773 1.0771 1.0783 1.0809 1.0889 1.0970 1.1023 .1.1047 1.1051 1.1039 1.1046 1.1053 1.1059 44 8.60 1.0858 1.0835 1.0815 1.0804 1.0803 1.0814 1.0837 1.0906 1.0976 1.1019 1.1035 1.1031 1.1010 1.1009 1.1012 1.1014 45 8.80 1.0875 1.0856 1.0840 1.0831 1.0830 1.0840 1.0861 1.0921 1.0981 1.1014 1.1023 1.1012 1.0986 1.0977 1.0976 1.0976 46 9.00 1.0889 1.0875 1.0863 1.0856 1.0857 1.0865 1.0881 1.0929 1.0977 1.1005 1.1014 1.1009 1.0992 1.0989 1.0990 1.0991 47 9.20 1.0908 1.0897 1,0888 1.0884 1.0884 1.0890 1.0903 1.0940 1.0978 1.1006 1.1022 1.1030 1.1033 1.1042 1.1049 1.1053 48 9.40 1.0945 1.0929 1.0915 1.0907 1.0905 1.0912 1.0927 1.0974 1.1022 1.1054 1.1069 1.1074 1.1069 1.1074 1.1080 1.1084 49 9.60 1.0991 1.0965 1.0942 1.0927 1.0922 1.0928 1.0947 1.1007 1.1070 1.1109 1.1125 1.1125 1.1111 1.1113 1.1117 1.1120 50 9.80 1.1035 1.1000 1.0967 1.0945 1.0936 1.0942 1.0964 1.1037 1.1113 1.1.160 1.1177 1.1172 1.1151 1.1150 1.1153 1.1156 51 10.00 1.1077 1.1030 1.0985 1.0955 1.0941 1.0946 1.0972 1.1060 1.1153 1.1208 1.1226 1.1215 1.1184 1.1178 1.1180 1.1182 52 10.20 1..11161.1057 1.1002 1.0963 1.0944 1.0949 1.0978 1.1081 1.1189 1.1251 1.1268 1.1252 1.1211 1.1200 1.1201 1.1202 53 10.40 1.1152 1.1096 1.1043 1.1006 1.0988 1.0992 i.1019 1.1117 1.1220 1.1278 1.1292 1.1273 1.1229 1.1215 1.1215 1.1215 54 10.60 1.1182 1.1117 1.1055 1.1011 1.0989 1.0992 1.1021 1.1130 1.1244 1.1309 1.1324 1.1304 1.1255 1.1240 1.1240 1.1240 55 10.80 1.1208 1.1144 1.1083 1.1041 1.1019 1.1021 1,1049 1.1153 1.1263 1,1325 1.1340 1.1320 1.1272 1.1257 1.1256 1.1256 56 11.00 L.O000 .1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 .0000 1.0000 1.0000, 1.0000 1.0000 57 11.20 1.0000 1.0000 1.0000 1.0000 1.00001.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 i.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.000 1.0000 1.0000 1.0000 59 11.60 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 60 11.80 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 61 12.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 .loOQ 1.0000 1.0000, 1,0000 1.0000. l.0000 1.0000 Top and bottom t 0% of core excluded. | |||
Page 16 of 16}} |
Latest revision as of 00:27, 23 November 2019
ML073241011 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 11/12/2007 |
From: | Peifer M Indiana Michigan Power Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
AEP:NRC:7565 | |
Download: ML073241011 (17) | |
Text
Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place Bridgman, MI 49106 POWER AEPcom A unit of American Electric Power November 12, 2007 AEP:NRC:7565 10 CFR 50.4 Docket No.: 50-316' U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 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 17 in accordance with Technical Specification 5.6.5.
Revision 0 of the Unit 2 Cycle 17 COLR is provided as an attachment to this letter.
There are no new commitments in this submittal. Should you have any questions, please contact Ms. Susan D. Simpson, Regulatory Affairs Manager, at (269) 466-2428.
Vice President - Site Support Services KAS/jen Attachment c: J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne J. T. King- MPSC MDEQ - WHMD/RPMWS NRC Resident Inspector P. S. Tam - NRC Washington DC oll 104A
ATTACHMENT TO AEP:NRC:7565 Donald C. Cook Nuclear Plant Unit 2 Cycle 17 Core Operating Limits Report Revision 0
D. C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UI'41T 2 CYCLE 17 Revision 0 Donald C. Cook Nuclear Plant Unit 2 Cycle 17 Core Operating Limits Report Revision 0 Page 1 of 16
D. C. COOK UNIT 2 CYCLE 17 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for the Donald C. Cook Nuclear Plant Unit 2 Cycle 17 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 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 (Fo(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN1 1 )
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 ý CYCLE 17 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 (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% 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 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 -4.10E4 Ak/k/0 F.
This limit is based on a Tayg program with HFP vessel T.vg 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 16
D. C. COOK UNIT 2 CYCLE 17 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 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 Akfk/°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 -3.90E-4 Ak/k/OF 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 burnup
>_0.0 MWD/MTU.
Page 4 of 16
D. C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 2.3.2 Heat Flux Hot Channel Factor (FQ(Z)) (Specification 3.2. 1)
Fc (Z) <_ -Q
- K(Z) for P > 0.5 P
F*.(Z) <_2
- CFQ
- K(Z) for P:5 0.5 F*' (Z) !_CF*
- K(Z) for P > 0.5 P
Fw (Z) !_2
- CFQ
- K(Z) for P < 0.5 THERMAL POWER Where: P = RATED THERMAL POWER
- a. CFQ = 2.335
- b. K(Z) is provided in Figure 4.
- c. 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. F" (Z) = FC (Z) x W(Z) x Fp
- f. For Cycle 17, 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 Up Burnup Penalty (MWD/MTU) Multiplier 0 1.020 150 1.043 317 1.044 484 1.045 651 1.046 818 1.047 985 1.044 1152 1.040 Page 5 of 16
D. C. COOK UNIT 2 CYCLE 17 Revision 0 1319 1.034 1486 1.028 1653 1.023 2000 1.020 The bumup range only covers where Fp exceeds 1.02. Linear interpolation is adequate for intermediate cycle bumups.
2.3.3 Nuclear Enthalpy Rise Hot Channel Factor (em) (Specification 3.2.2)
FN *H-CF. * (1 + PFk *(l-P))
THERMAL POWER Where: P = RATED THERMAL POWER
- a. CFAH = 1.58
- b. PFtAH= 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 UNIT 2 CYCLE 17 Revision 0 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 _Ž 2172.4 psig +
- b. Reactor Coolant System Tavg shall be _ 580.1 'F +
- 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 Ta.g, and 2200 psig for Pressurizer Pressure.
This concentration bounds the condition of If < 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 17 Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT (MTC) LIMITS 1.0
[UNACCEPTABLE OPERATION 0.5 Cb JN 0.0 ACCEPTABLE OPERATION]
C:)
V-x
-0.5
-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 17 Revision 0 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (FOUR-LOOP OPERATION) 250 225 200 F 175 150 0)
CA, 125 0
100 0
0 75 0r 50 25 0
0 10 20 30 40 50 60 70 80 90 100 POWER (% of Rated Thermal Power)
Page 9 of 16
D, Q. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (RTP) 100 90 x 80 Y.N 70 60 It 0 60 IL' 40 E
E 30 20 0
10 0
FLUX DIFFERENCE (DELTA-I)
-Page 10 of 16
A C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 (0.0,, 1.0) _(6.0,1.0) 1.0 (2.0,0.925) 0.8 Z
z Lu w
0.6
-J N
0 z
0.4 0.2 0
0 2 4 6 8 10 12 CORE HEIGHT (FT)
Page 11 of 16
D. C. COOK UNIT 2 CYCLE 17 Revision 0 D. C. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 5 (Page 2 of 2)
Overpower AT Trip Setpoint Overpower AT < AT° [K4 - K5 I +S 1 1i+r*SJT-K(T-1)-f(A)
Where: AT = Measured RCS AT, IF AT° Indicated AT at RATED THERMAL POWER, IF T = Average temperature, OF T" = Nominal T..g at RATED THERMAL POWER, (:5 576.0 0F)
K4 _< 1.16" Ks > 0.02/°F for increasing average temperature; Ks = 0 for decreasing average temperature K6 > 0.00 197/'F for T greater than T" ; K6g=0 for T less than or equal to T" r3S I + T's The function generated by the rate lag controller for Tav. dynamic compensation t3 = Time constant utilized in the rate lag controller for T.,g; -T3 >g10 sees.
1 S = Laplace transform operator, see f2 (A) = 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 17 Revision 0 FIGURE 6 Reactor Core Safety Limits U. 620
> 610 I.-
U) 600 0
0 0.2 0.4 0.6 0.8 '1 1.2 Power (fraction of rated thermal power)
DESCRIPTION OF SAFETY LIMITS Power Tavg Power Tavg Power Tavg Power Tavg PRESSURE (psia) (frac) ( F) (frac) (UF) (frac) (CF) (frac) ( F) 1775 0.00 615.4 0.98 583.8 1.02 580.9 1.2 558.1 2000 0.00 631.8 0.86 605.8 0.96 597.5 1.2 568.5 2100 0.00 639.1 0.82 614.0 0.96 601.6 1.2 573.A 2250 0.00 649.2 0.72 628.6 0.98 605.2 1.2 580.4 2400 0.00 659.0 0.62 642.0 1.1 599.0 1.2 588.1 UNIT 2 Reactor Core Safety Limits Page 14 of 16
D. C. COOK UNIT 2 CYCLE 17 Revision 0 FIGURE 7 Unit 2 Cycle 17 Predicted HFP ARO 300.PPM MTC Versus Burnup
-2.40E -2.42E -2.44E Z-2.48E-04 -
S-2.SOE S-2.52E--04
-2.56E -2.5815 -2.60E-04 4--
16000 17000 18000 19000 20000 Cycle Bumup (MWDIPMTU)
Burnup (MWDIMTU) MTC (AkJk/F) 16000 -2.4221 E-4 17000 -2.4623E-4 18000 -2.4992E-4 19000 -2.5394E-4 20000 -2.5790E-4 Page 15 of 16
D. C. COOK UNIT 2 CYCLE 17 Revision 0 TABLE 1 D. C. Cook Unit 2 Cycle 17 W(Z) Function Node Height Bumup (MWD/MTU)
PT (Ft.) 150 1000 2000 3000 4000 5000 6000 8000. 10000 12000 14000 16000 18000 20000 21000 21720 1 0.00 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 2 0.20 1.0000 1.0000 1.0000 1.0o00 1.oo00 1.0000 1.0000 1.0000 1.0000 1.0000 1.oo00 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1o.00 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 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 5 0.80 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 6 1.00 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 7 1.20 1.1069 1.1001 1.0937 1.0892 1.0870 1.0872 1.0901 1.1013 1.1143 1.1243 1.1315 1.1367 1.1408 1.1467 1.1499 1.1522 8 1.40 1.1065 1.1003 1.0944 1.0903 1.0883 1.0886 1.0913 1.1018 1.1139 1.1232 1.1298 1.1346 1.1383 1.1437 1.1467 1.1488 9 1.60 1.1058 1.1002 1.0949 1.0913 1.0895 1.0898 1.0923 1.1020 1.1131 1.1216 1.1276 1.1319 1.1352 1.1400 f.1427 1.1447 10 1.80 1.1049 1.0999 1.0952 1.0920 1.0904 1.0907 1.0931 1.1018 1.1118 1.1194 1.1247 1.1284 1.1312 1.1354 1.1378 1.1395 11 2.00 1.1036 1.0993 1.0953 1.0926 1.0913 1.0916 1.0937 1.1014 1.1101 1.1167 1.1212 1.1242 1.1265 1.1299 1.1319 1.1334 12 2.20 1.1020 , 1.0985 1.0953 1.0931 1.0921 1.0924 1.0942 1.1007 1.1080 1.1135 1.1171 1.1196 1.1212 1.1240 1.1256 1.1268 13 2.40 1.1002 1.0975 1.0950 1.0934 1.0926 1.0930 1.0945 1,0997 1.1055 . 1.1098 1.1126 1.1145 1.1156 ,1.1177 1.1189 1.1198 14 2.60 1.0980 1.0962 1.0945 1.0934 1.0930 1.0933 1.0944 1.0983 1.1026 1.1057 1.1076 1.1087 1.1093 1.1106 1.1114 1.1120 15 2.80 1.0957 1.0947 1.0938 1.0932 1.0931 1.0933 1.0941 1.0966 1.0993 1.1011 1.1022 1.1027 1.1028 1.1034 1.1038 1.1041 16 3.00 1.0930 1.0929 1.0928 1.0928 1.0929 1.0931 1.0935 1.0946 1.0956 1.0962 1.0963 1.0961 1.0956 1.0955 1.0955 1.0955 17 3.20 1.0903 1.0910 1.0916 1.0921 1.0925 1.0926 .1.0926 1.0922 1,0916 1.0909 1.0903 1.0896 1.0889 1.0881 1.0878 1.0876 18 3.40 1.0883 1.0895 1.0906 1.0914 1.0919 1.0919 1.0914 1.0896 1.0877 1.0864 1.0859 1.0859 1.0863 1.0862 1.0860 1.0859 19 3.60 1.0874 1.0887 1.0899 1.0907 1.0911 1.0909 1.0901 1.0876 1.0853 1.0848 1.0859 1.0883 1.0919 1.0943 1.0952 1.0958 20 3.80 1.0868 -1.0880 1.0892 1.0900 1.0903 1.0901 1.0892 1.0864 1.0844 1.0848 1.0875 , 1.0921 1.0983 1.1028 1.1047 1.1060 21 4.00 1.0860 1.0872 1.0883 1.0891 1.0894 1.0892 1.0884 1.0861 1.0846 1.0860 1.0899 1.0960 1.1040 1.1100 1,1126 1.1144 22 4.20 1.0854 1.0863 1.0872 1.0879 1.0883 1.0883 1.0879 1.0865 1.0862 1.0887 1.0936 1.1007 1.1098 1.1169 1.1200 1.1222 23 4.40 1.0854 1.0858 1.0863 1.0868 1.0872 1.0874 1.0875 1.0876 1.0889 1.0925 1.0983 1.1059 1.1153 1.1229 1.1263 1.1288 24 4.60 1.0855 1.0853 1.0853 1.0855 1.0858 1.0862 1.0868 1.0885 1.0915 1.0963 1.1028 1.1107 1.1202 1.1283 1.1320 1.1346 25 4.80 1.0855 1.0848 1.0844 1.0843 1.0846 1.0852 1,0863 1.0893 1.0938 1.0996 1.1067 1.1149 1.1244 1.1329 1.1368 1.1396 26 5.00 1.0853 1.0842 1.0834 1.0832 1.0834 1.0843 1.0857 1.0900 1.0958 1.1025 1.1I1001,1185 1.1279 1.1366 1.1407 1.1436 27 5.20 1.0849 1.0834 1.0823 1.0818 1.0820 1.0830 1.0848 1.0904 1.0974 1.1049 1,1128 1.1213 1.1306 1.1394 1,1435 1.1466 28 5.40 1.0845 1.0825 1.0809 1.0802 1.0803 1.0815 1.0837 1.0904 1,0986 1.1068 1.1150 1.1234 1.1324 1.1411 1.1454 1.1484 29 5.60 1.0837 1.0813 1.0793 1.0783 1.0784 1.0796 1M0822 1.0899 1.0992 1.1080 1.1164 1.1247 1.1332 1.1418 1.1460 1.1491 30 5.80 1.0827 1,0801 1.0778 10767 1.0767 1.0781 1.0808 1.0893 1.0992 1.1084 1.1168 1.1248 1.1329 1.1412 1.1454 1.1485 31 6.00 1.0814 1.0787 1,0764 1.0752 1.0752 1.0766 1.0795 1.0884 1.0986 1.1079 1.1161 1.1238 1.1314 1.1395 1.1436 1.1466 32 6.20 1.0798 1.0770 1.0747 1.0735 1.0735 1.0750 1.0779 1.0869 1.0973 1.1065 1.1145 1.1218 1.1289 1.1366 1.1406 1.1434 33 6,40 1.0777 1.0750 1.0726 1.0714 1.0715 1.0730 1.0759 1.0850 1.0953 1.1042 1.1119 1.1188 1.1254 1.1326 1.1364 1.1391 34 6.60 1.0752 1.0725 1.0702 1.0691 1.0691 1.0706 1.0735 1.0824 1.0925 1.1011 .1.1084 1.1148 1.1209 1.1276 1.1311 1.1337 35 6.80 1.0725 1.0697 1.0674 1.0662 1.0662 1.0675 1.0704 f.0791 1.0888 1.0970 1.1037 1.1094 1.1145 1.1205 1.1237 1.1260 36 7.00 1.0684 1.0661 1.0642 1.0632 1.0633 1.0647 1.0674 1.0755 1.0845 1,0923 1.0988 1.1044 1.1097 1.1156 1.1188 1.1210 37 7,20 1.0659 1.0634 1.0614 1.0604 1.0605 1.0619 1.0647 1.0732 1.0827 1.0908 1.0975 1.1033 1.1087 1.1149 1.1181 1.1204 38 7.40 1.0685 1.0643 1.0607 1.0585 1.0581 1.0596 1.0631 1.0742 1.0864 1.0956 1.1020 1.1063 1.1093 1.1140 1.1168 1.1188 39 7.60 1.0720 1.0677 1.0640 1.0618 1.0613 1,0627 1.0663 1.0775 1.0896 1.0985 1.1041 1,1076 1.1094 1.1133 1.1157 1.1174 40 7.80 1.0753 1.0716 1.0683 1.0664 1.0660 1.0675 1.0708 1.0810 1.0920 1.1000 1.1049. 1.1077 1.1089 1,1121 1.1141 1.1156 41 8.00 1.0784 .1.0750 1.0719 1.0702 1.0698 1.0712 1.0743 1.0840 1.0942 1.1013 1.`055 1.1075 1.1078 1,1102 1.1118 1.1129 42 8.20 1.0812 1.0781 1.0754 1.0739 1.0736 1.0749 1.0778 1.0866 1.0958 1.1021 1.1054 1.1066 1.1061 1.1077 1.1088 1.1097 43 8.40 1.0837 1.0810 1.0786 1.0773 1.0771 1.0783 1.0809 1.0889 1.0970 1.1023 .1.1047 1.1051 1.1039 1.1046 1.1053 1.1059 44 8.60 1.0858 1.0835 1.0815 1.0804 1.0803 1.0814 1.0837 1.0906 1.0976 1.1019 1.1035 1.1031 1.1010 1.1009 1.1012 1.1014 45 8.80 1.0875 1.0856 1.0840 1.0831 1.0830 1.0840 1.0861 1.0921 1.0981 1.1014 1.1023 1.1012 1.0986 1.0977 1.0976 1.0976 46 9.00 1.0889 1.0875 1.0863 1.0856 1.0857 1.0865 1.0881 1.0929 1.0977 1.1005 1.1014 1.1009 1.0992 1.0989 1.0990 1.0991 47 9.20 1.0908 1.0897 1,0888 1.0884 1.0884 1.0890 1.0903 1.0940 1.0978 1.1006 1.1022 1.1030 1.1033 1.1042 1.1049 1.1053 48 9.40 1.0945 1.0929 1.0915 1.0907 1.0905 1.0912 1.0927 1.0974 1.1022 1.1054 1.1069 1.1074 1.1069 1.1074 1.1080 1.1084 49 9.60 1.0991 1.0965 1.0942 1.0927 1.0922 1.0928 1.0947 1.1007 1.1070 1.1109 1.1125 1.1125 1.1111 1.1113 1.1117 1.1120 50 9.80 1.1035 1.1000 1.0967 1.0945 1.0936 1.0942 1.0964 1.1037 1.1113 1.1.160 1.1177 1.1172 1.1151 1.1150 1.1153 1.1156 51 10.00 1.1077 1.1030 1.0985 1.0955 1.0941 1.0946 1.0972 1.1060 1.1153 1.1208 1.1226 1.1215 1.1184 1.1178 1.1180 1.1182 52 10.20 1..11161.1057 1.1002 1.0963 1.0944 1.0949 1.0978 1.1081 1.1189 1.1251 1.1268 1.1252 1.1211 1.1200 1.1201 1.1202 53 10.40 1.1152 1.1096 1.1043 1.1006 1.0988 1.0992 i.1019 1.1117 1.1220 1.1278 1.1292 1.1273 1.1229 1.1215 1.1215 1.1215 54 10.60 1.1182 1.1117 1.1055 1.1011 1.0989 1.0992 1.1021 1.1130 1.1244 1.1309 1.1324 1.1304 1.1255 1.1240 1.1240 1.1240 55 10.80 1.1208 1.1144 1.1083 1.1041 1.1019 1.1021 1,1049 1.1153 1.1263 1,1325 1.1340 1.1320 1.1272 1.1257 1.1256 1.1256 56 11.00 L.O000 .1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 .0000 1.0000 1.0000, 1.0000 1.0000 57 11.20 1.0000 1.0000 1.0000 1.0000 1.00001.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 i.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.000 1.0000 1.0000 1.0000 59 11.60 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 60 11.80 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 61 12.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 .loOQ 1.0000 1.0000, 1,0000 1.0000. l.0000 1.0000 Top and bottom t 0% of core excluded.
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