ML21125A538
Text
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 DONALD C. COOK ICE CONDENSER ANALYSIS PARAMETERS Reactor Containment Volume (net free volume)
Upper Compartment, ft3 (1) 727,628 Ice Condenser, ft3 (1) 110,520 3 (1)
Lower Compartment (active), ft 293,801 Total Active Volume, ft3 1,131,949 Lower Compartment (dead ended), ft3 61,309 3
Total Containment Volume, ft Not Applicable Reactor Containment Air Compression Ratio 1.42 NSSS Power, MWt 3425 Design Energy Release to Containment Initial blowdown mass release, lbm 543,885 Initial blowdown energy release, Btu 338.8 x 106 Ice Condenser Parameters Weight of ice in condenser, lbm 2.20 x 106 Additional System Parameters Core Inlet Temperature (+/-5.1 oF), oF 552.5 (2)
Initial Steam Generator Steam Pressure, psia 858.2 Assumed Maximum Containment Back Pressure, psia 26.7 (1)
Reference 36 and 38 (2)
Includes +4.1°F allowance for instrument error, deadband, and +1°F for cold leg streaming.
This is information utilized in the current containment pressure analysis discussed in Section 14.3.4.1.3.1.
Unit 2 Added to Unit 2 by UCR-2138, Rev. 0
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 DECK LEAKAGE SENSITIVITY 5 ft2 Deck Leak Resultant Peak Deck Leak age Spray Flow Rate B reak Siz e Air Compression Containment Area (ft2 ) (gpm)
Peak (psig) 1 Pressure (psig)
D ouble ended 7.8 54 0 12.0 0.6 double ended 6.6 46 0 12.0 3 ft2 6.25 50 0 12.0 8-inch diameter 5.5 56 4000 12.2 8-inch diameter 5.5 35 2000 12.0 8-inch diameter 2 5.5 56 2000 11.3 6-inch diameter 5.0 56 4000 10.4 2 1/ 2-inch diameter 4.0 56 4000 8.5 1/ 2-inch diameter 3.0 50 4000 3.0 1
The current design basis value for the deck leakage is 7 sq . ft.
2 This case assumes upper compartment structural heat sink steam condensation of 8 lb/ sec and 30 percent of deck leakage is air.
Unit 2 Added to Unit 2 by UCR-2138, Rev. 0
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27 D. C. COOK NUCLEAR PLANT Table: 14.3.4-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 STRUCTURAL HEAT SINK TABLE Upper Compartment Area (ft2) Thickness (ft) Material Structure 1 29958.25 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.029741 Carbon Steel Layer 4 3.0364 Concrete Structure 2 12571.4 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.00275 Paint (Primer)
Layer 3 2.710421 Concrete Structure 3 15526.8 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.00275 Paint (Primer)
Layer 3 2.2728 Concrete Structure 4 1306.25 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.209108 Carbon Steel Structure 5 4207.55 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.064932 Carbon Steel Structure 6 22443.75 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.017572 Carbon Steel Structure 7 24149.01 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.010036 Carbon Steel Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27 D. C. COOK NUCLEAR PLANT Table: 14.3.4-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 STRUCTURAL HEAT SINK TABLE Lower Compartment Area (ft2) Thickness (ft) Material Structure 8 6734.55 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.0167 Carbon Steel Layer 4 1.0103 Concrete Structure 9 14642.35 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.00275 Paint (Primer)
Layer 3 5.8355 Concrete Structure 10 25872.3 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.00275 Paint (Primer)
Layer 3 2.699 Concrete Structure 11 3214.8 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.09286 Carbon Steel Structure 12 3499.8 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.06918 Carbon Steel Structure 13 12312.0 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.013136 Carbon Steel Structure 14 58073.355 Layer 1 0.001 Paint (Top Coat)
Layer 2 0.0005 Paint (Primer)
Layer 3 0.00952 Carbon Steel Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27 D. C. COOK NUCLEAR PLANT Table: 14.3.4-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 STRUCTURAL HEAT SINK TABLE Ice Condenser Area (ft2) Thickness (ft) Material Structure 15 180600.0 Ice Baskets Layer 1 0.00663 Steel Structure 16 76650.0 Lattice Frames Layer 1 0.0217 Steel Structure 17 28670.0 Lower Support Structure Layer 1 0.0267 Steel Structure 18 3336.0 Ice Condenser Floor Layer 1 0.00275 Paint Layer 2 0.33 Concrete Structure 19 19100.0 Containment Wall Panels and Containment Shell Layer 1 1.0 Steel and Insulation Layer 2 0.0625 Steel Shell Structure 20 13055.0 Crane Wall Panels and Crane Wall Layer 1 1.0 Steel and Insulation Layer 2 1.0 Concrete Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27 D. C. COOK NUCLEAR PLANT Table: 14.3.4-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 MATERIAL PROPERTY DATA UPPER AND LOWER COMPARTMENTS Thermal Conductivity Volumetric Heat Capacity Material (Btu/hr-ft-oF) (Btu/ft3-oF)
Paint (on concrete)
Primer 0.19 29.3 Top Coat 0.19 75.0 Concrete 0.81 30.4 Paint (on steel)
Primer 0.4 29.3 Top Coat 0.4 75.0 Steel 26.0 58.8 ICE CONDENSER COMPARTMENT Thermal Conductivity Volumetric Heat Capacity Material (Btu/hr-ft-oF) (Btu/ft3-oF)
Paint (on concrete) 0.0833 28.4 Insulation (on steel) 0.15 2.75 Insulation 0.2 3.663 Steel 26.0 56.4 Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-6A UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Table 14.3.4-6A (U2) - D. C. Cook Unit 2 DECL Minimum Containment Energy Accounting - Blowdown Approximate End of Blowdown (10.0 sec)
Ice Heat Removal 1 201.01 MBTU Structural Heat Sinks1 19.99 MBTU RHR Heat Exchanger Removal1 0.00 MBTU Spray Heat Exchanger1 0.00 MBTU Energy Content of Sump 2 204.42 MBTU Ice Melted 0.665 Mlbm 1
Integrated Energy 2
Sum of Active and Inactive Sump Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-6B UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Table 14.3.4-6B (U2) - D. C. Cook Unit 2 DECL Minimum Containment Energy Accounting - Meltout and Peak Pressure Approximate Time of Approximate Time of Ice Meltout Peak Pressure
(~ 7,85 s ec) 1 (~ 11,170 s ec) 2 Ice Heat Removal 3 576.07 M BTU 576.07 M BTU Structural Heat Sinks3 129.61 MBTU 171.86 M BTU RHR Heat Exchanger 124.91 MBTU 205.44 MBTU Removal3 Spray Heat Exchanger3 139.52 MBTU 231.11 MBTU Energy Content of Sump 4 537.44 M BTU 551.03 MBTU Ice Melted 2.20 Mlbm 2.20 Mlbm 1
Used 7 , 864.5 sec 2
Used 11, 098.0 sec 3
Integrated Energy 4
Active Sump Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-7 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 Steamline Break Mass / Energy Releases Inside Containment 102% of 358 M Wt Core Power, 1.4 Ft2 Double Ended Rupture Failure - MSIV Time (sec) Mass (lbm / sec) Energy (MBtu / sec) 0000 .0000 .0000 0.200 9,753 11.68 1.400 8,708 10.45 3.000 7,21 9.279 6.000 7,228 8.693 8.000 7,069 8.504 10.00 6,882 8.281 11.60 6,658 8.014 12.00 6,441 7.752 12.20 6,224 7.490 13.00 5,353 6.443 14.20 4,047 4.871 15.20 2,959 3.562 16.00 2,090 2.516 16.40 1,657 1.995 17.00 1,482 1.784 22.00 1,306 1.572 24.00 1,253 1.509 26.00 1,208 1.455 28.00 1,169 1.408 30.00 1,137 1.369 34.00 1,087. 1.309 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-7 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 Steamline Break Mass / Energy Releases Inside Containment 102% of 358 M Wt Core Power, 1.4 Ft2 Double Ended Rupture Failure - MSIV Time (sec) Mass (lbm / sec) Energy (MBtu / sec) 36.00 1,068. 1.285 45.00 1,006. 1.211 75.00 878.0 1.056 100.0 851.6 1.024 200.0 831.4 .9998 280.0 825.3 .9924 282.5 789.4 .9485 285.0 695.6 .8349 287.5 619.9 .7431 292.5 455.2 .5429 300.0 241.3 .2850 302.5 197.8 .2330 305.0 167.7 .1971 310.0 135.9 .1592 320.0 112.0 .1308 350.0 106.5 .1244 605.0 108.9 .1267 610.0 3.231 .0038 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-8 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 Steamline Break Mass / Energy Releases Inside Containment 102% of 358 M Wt Core Power, 0.860 Ft2 Split Break Failure - AFWRP Time (sec) Mass (lbm / sec) Energy (MBtu / sec)
.0000 .0000 .0000
.2000 1,394 1.669 5.600 1,293 1.550 7.000 1,439 1.724 10.00 1,551 1.855 13.00 1,627 1.944 13.60 1,635 1.953 14.80 1,642 1.961 15.60 1,642 1.961 16.00 1,640 1.959 18.00 1,628 1.945 20.00 1,540 1.843 21.00 1,484 1.77 22.00 1,433 1.718 23.00 1,387 1.663 24.00 1,345 1.614 26.00 1,271 1.526 30.00 1,153 1.386 35.00 1,043 1.255 40.00 958.2 1.154 45.00 892.0 1.074 50.00 839.6 1.011 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-8 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 Steamline Break Mass / Energy Releases Inside Containment 102% of 358 M Wt Core Power, 0.860 Ft2 Split Break Failure - AFWRP Time (sec) Mass (lbm / sec) Energy (MBtu / sec) 60.00 767.2 0.924 70.00 719.7 .8668 80.00 689.9 .8308 90.00 669.6 .8063 100.0 656.4 .7904 110.0 648.7 .7810 120.0 643.8 .7752 150.0 638.2 .7684 200.0 635.4 .7650 295.0 630.9 .7596 315.0 459.0 .5513 335.0 269.0 .3211 350.0 213.2 .2537 400.0 189.1 .2247 500.0 188.8 .2243 602.5 189.9 .2257 605.0 198.2 .2348 610.0 114.2 .1343 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-9 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Double-Ended Rupture Steamline Breaks 1.4 ft2 Double-Ended Steamline Breaks 1
Operating Power, % 102 70 Aux. F eed F ailure w /o w /o MSIV F ailure w w Tmax °F 323.3 323.0 Time of Tmax sec 8.01 11.96 4.6 ft2 Double-Ended Steamline Breaks 1
Operating Power, % 102 70 Aux. F eed F ailure w /o w /o MSIV F ailure w w Tmax °F 322.7 321.7 Time of Tmax sec 6.2 6.2 1
Based upon a core pow er of 3588 MW t.
Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-10 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Split Steamline Breaks Siz e of Break, ft2 0.860 0.942 0.942 1
Hot O perating Pow er % 102 30 30 Aux. F eed F ailure w w /o w MSIV F ailure w /o w w /o Tmax °F 324.7 324.1 323.7 Time of Tmax sec 72.4 70.4 101.3 1
Based upon a core pow er of 3588 MW t.
Unit 2
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-11 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 LOWER COMPARTMENT TEMPERATURE TRANSIENT CALCULATION RESULTS Maximum LC Temp Time Tmax Time Of Containment*
Case O F Sec. Spray Fan 0.6 ft2 326.1 151.39 53. 605.
0.35 ft2 325.8 322.8 59. 617.
0.1 ft2 320.7 651. 106. 663.
Hi-2 Pressure Setpoint used was 3.5 psig.
Relay time used for spray actuation after Hi-2 signal was 45 sec.
Relay time used for fan actuation after Hi-2 signal was 600 sec.
Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-12 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 0.35 FT2 SPLIT 30% POWER Time Mass Energy (sec) (lb/sec) (BTU/sec)
.1000E-01 .7970E+03 .9480E+06
.1000E+01 .7970E+03 .9480E+06
.3000E+01 .7890E+03 .9388E+06
.5000E+01 .7820E+03 .9308E+06
.7000E+01 .7760E+03 .7239E+06
.9000E+01 .7700E+03 .9169E+06
.1000E+02 .7680E+03 .9145E+06
.1300E+02 .7760E+03 .9237E+06
.1500E+02 .7800E+03 .9284E+06
.1600E+02 .8960E+03 .1066E+07
.1900E+02 .1240E+03 .1476E+07 2000E+02 .7720E+03 .9195E+06
.2500E+02 .7090E+03 .8466E+06
.3000E+02 .6630E+03 .7930E+06
.3500E+02 .6280E+03 .7520E+06
.4000E+02 .6010E+03 .7203E+06
.5000E+02 .5630E+03 .6756E+06
.6000E+02 .5350E+03 .6425E+06
.7000E+02 .5140E+03 .6176E+06
.8000E+02 .4970E+03 .5974E+06
.9000E+02 .4830E+03 .5808E+06
.1000E+03 .4700E+03 .5653E+06
.1200E+03 .4500E+03 .5415E+06
.1400E+03 .4320E+03 .5200E+06
.1600E+03 .4160E+03 .5008E+06
.1800E+03 .4020E+03 .4841E+06
.2000E+03 .3890E+03 .4685E+06
.2400E+03 .3650E+03 .4397E+06
.2800E+03 .3440E+03 .4144E+06
.3200E+03 .3240E+03 .3904E+06
.3600E+03 .3060E+03 .3687E+06
.4000E+03 .2890E+03 .3481E+06
.5000E+03 .2530E+03 .3046E+06
.6000E+03 .2230E+03 .2683E+06
.7000E+03 .1990E+03 .2392E+06
.8000E+03 .1790E+03 .2150E+06
.9000E+03 .1620E+03 .1944E+06
.1000E+04 .1480E+03 .1774E+06 Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-13 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
- 0. FT2 SPLIT 30% POWER Time Mass Energy (sec) (lb/sec) (BTU/sec)
.1000E-01 .1365E+04 .1624E+07
.1000E+01 .1365E+04 .1624E+07
.3000E+01 .1341E+04 .1596E+07
.5000E+01 .1320E+04 .1572E+07
.7000E+01 .1302E+04 .1551E+07
.8000E+01 .1293E+04 .1541E+07
.1000E+02 .1297E+04 .1545E+07
.1200E+02 .1298E+04 .1546E+07
.1300E+02 .1297E+04 .1545E+07
.1400E+02 .1268E+04 .1513E+07
.1600E+02 .1196E+04 .1429E+07
.1800E+02 .1133E+04 .1355E+07
.2000E+02 .1079E+04 .1292E+07 2200E+02 .1033E+04 .1238E+07
.2400E+02 .9940E+03 .1192E+07
.2700E+02 .9440E+03 .1133E+07
.3200E+02 .8800E+03 .1057E+07
.3600E+02 .8420E+03 .1012E+07
.4000E+02 .8110E+03 .9754E+06
.4600E+02 .7740E+03 .9313E+06
.5000E+02 .7540E+03 .9074E+06
.6000E+02 .7130E+03 .8584E+06
.7500E+02 .6680E+03 .8045E+06
.9500E+02 .6250E+03 .7529E+06
.1200E+03 .5840E+03 .7036E+06
.1400E+03 .5570E+03 .6711E+06
.1800E+03 .5110E+03 .6156E+06
.2200E+03 .4720E+03 .5685E+06
.2400E+03 .4530E+03 .5455E+06
.2600E+03 .4350E+03 .5238E+06
.3000E+03 .4020E+03 .4838E+06
.3600E+03 .3600E+03 .4330E+06
.4200E+03 .3250E+03 .3905E+06
.5000E+03 .2870E+03 .3445E+06
.5600E+03 .2680E+03 .3154E+06
.6000E+03 .2480E+03 .2972E+06
.8600E+03 .1790E+03 .2136E+06
.9600E+03 .1610E+03 .1918E+06
.9800E+03 .1580E+03 .1882E+06
.1000E+04 .1550E+03 .1846E+06 Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-14 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 KEY PARAMETERS AFFECTING SPLIT STEAM LINE BREAKS Values Used In Values for Variable LOTIC-3 Report D. C. Cook Full Load Steam Pressure (psia) 1000 820 Plant Power (Mwt) 3425 3403 Time Delay to Feedline Isolation (sec) 15 9.0 Time Delay to Steam Line Isolation (sec) 15 9.0 Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-15 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 STEAM LINE RUPTURE IN STEAM GENERATOR DOGHOUSE Mass Energy Release Rates Outlet Nozzle Break (Top Break)
Mass Flowrate (lbm/sec) Energy Flowrate (BTU/sec)
Time (Sec) x103 x106 0.0 19.421 23.110 0.042 19.421 23.110 0.043 13.830 16.458 0.2 13.430 15.982 0.45 16.630 16.239 0.75 26.430 19.040 1.05 34.630 21.428 1.9 33.350 20.358 2.9 31.680 19.395 3.5 31.000 18.678 Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-15 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 MAIN FEEDWATER LINE BREAK IN STEAM GENERATOR DOGHOUSE Mass and Energy Releases (Break at Side of Vessel)
Reverse Flow Time (seconds) Mass Flow (lbm/sec) Energy Flow (Btu/sec) 0.0 8919 4.866 x 106 20.23 8919 4.866 x 106 20.24 0 0 Forward Flow Time (seconds) Mass Flow (lbm/sec) Energy Flow (Btu/sec) 0.0 5711 2.451 x 106 5711 2.451 x 106 Total Flow Time (seconds) Mass Flow (lbm/sec) Energy Flow (Btu/sec) 0.0 14630 7.317 x 106 20.23 14630 7.317 x 106 20.24 5711 2.451 x 106 Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec)
.00000 0. 0.
.00101 1.8429935E+03 1.2012554E+06
.00201 2.0768869E+03 1.3312080E+06
.00302 2.0954232E+03 1.3410507E+06
.00401 2.0943466E+03 1.3398926E+06
.00502 2.0906198E+03 1.3372569E+06
.00600 2.0847010E+03 1.3334349E+06
.00703 2.0776894E+03 1.3290038E+06
.00800 2.0718446E+03 1.3252736E+06
.00901 2.0684832E+03 1.3229372E+06
.01000 2.0667746E+03 1.3215515E+06
.01102 2.0657651E+03 1.3205642E+06
.01200 2.0657312E+03 1.3202011E+06
.01301 2.0710642E+03 1.3227266E+06
.01400 2.0895916E+03 1.3326883E+06
.01505 2.1237904E+03 1.3513713E+06
.01605 2.1428041E+03 1.3615888E+06
.01705 2.1327342E+03 1.3556010E+06
.01804 2.1286790E+03 1.3530305E+06
.01905 2.1408255E+03 1.3594780E+06
.02004 2.1330134E+03 1.3547994E+06
.02108 2.1170413E+03 1.3456154E+06
.02207 2.1196063E+03 1.3467887E+06
.02308 2.1314002E+03 1.3530903E+06
.02400 2.1400977E+03 1.3576929E+06
.02501 2.1475536E+03 1.3615802E+06
.02602 2.1559827E+03 1.3660339E+06
.02707 2.1678910E+03 1.3724086E+06
.02804 2.1768474E+03 1.3771613E+06
.02907 2.1816274E+03 1.3795673E+06
.03009 2.1827097E+03 1.3799305E+06
.03107 2.1841837E+03 1.3805245E+06
.03212 2.1872679E+03 1.3820107E+06
.03301 2.1894643E+03 1.3830366E+06
.03411 2.1903771E+03 1.3833149E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec)
.03504 2.1897285E+03 1.3827485E+06
.03607 2.1861418E+03 1.3805329E+06
.03703 2.1786958E+03 1.3761844E+06
.03807 2.1711481E+03 1.3717868E+06
.03906 2.1650758E+03 1.3682259E+06
.04009 2.1587371E+03 1.3645103E+06
.04102 2.1527706E+03 1.3610346E+06
.04212 2.1468107E+03 1.3575467E+06
.04305 2.1432206E+03 1.3554088E+06
.04406 2.1404771E+03 1.3537320E+06
.04510 2.1384998E+03 1.3524847E+06
.04601 2.1374125E+03 1.3517571E+06
.04705 2.1369632E+03 1.3513688E+06
.04809 2.1372622E+03 1.3514036E+06
.04911 2.1379671E+03 1.3516676E+06
.05006 2.1388546E+03 1.3520428E+06
.05108 2.1400630E+03 1.3525916E+06
.05207 2.1411605E+03 1.3530872E+06
.05318 2.1418610E+03 1.3533545E+06
.05404 2.1420277E+03 1.3533548E+06
.05515 2.1419234E+03 1.3531771E+06
.05609 2.1415416E+03 1.3528611E+06
.05711 2.1410383E+03 1.3524782E+06
.05812 2.1409677E+03 1.3523442E+06
.05901 2.1414214E+03 1.3525173E+06
.06004 2.1427085E+03 1.3531458E+06
.06104 2.1448478E+03 1.3542536E+06
.06207 2.1481439E+03 1.3559989E+06
.06303 2.1514351E+03 1.3577536E+06
.06402 2.1550387E+03 1.3596806E+06
.06501 2.1585740E+03 1.3615691E+06
.06604 2.1618098E+03 1.3632912E+06
.06710 2.1647229E+03 1.3648345E+06
.06814 2.1673799E+03 1.3662365E+06
.06905 2.1694828E+03 1.3673439E+06
.07008 2.1716796E+03 1.3684953E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec)
.07111 2.1735789E+03 1.3694836E+06
.07213 2.1750499E+03 1.3702354E+06
.07317 2.1759218E+03 1.3706558E+06
.07412 2.1760897E+03 1.3706871E+06
.07523 2.1755041E+03 1.3702969E+06
.07602 2.1743802E+03 1.3696191E+06
.07705 2.1726900E+03 1.3686222E+06
.07801 2.1708169E+03 1.3675296E+06
.07902 2.1688239E+03 1.3663702E+06
.08006 2.1667850E+03 1.3651854E+06
.08100 2.1651864E+03 1.3642490E+06
.08204 2.1632686E+03 1.3631342E+06
.08306 2.1613432E+03 1.3620171E+06
.08410 2.1593726E+03 1.3608757E+06
.08504 2.1576149E+03 1.3598670E+06
.08603 2.1556593E+03 1.3587375E+06
.08708 2.1538655E+03 1.3576993E+06
.08814 2.1523767E+03 1.3568314E+06
.08915 2.1513646E+03 1.3562298E+06
.09005 2.1510544E+03 1.3560230E+06
.09115 2.1514210E+03 1.3561899E+06
.09214 2.1524508E+03 1.3567285E+06
.09307 2.1540139E+03 1.3575665E+06
.09405 2.1562098E+03 1.3587565E+06
.09504 2.1589196E+03 1.3602332E+06
.09601 2.1619926E+03 1.3619135E+06
.09712 2.1660659E+03 1.3641459E+06
.09811 2.1700593E+03 1.3663392E+06
.09910 2.1743398E+03 1.3686932E+06
.10011 2.1788810E+03 1.3711929E+06
.10505 2.1997980E+03 1.3827080E+06
.11017 2.2084042E+03 1.3873725E+06
.11511 2.1979605E+03 1.3814517E+06
.12010 2.1755220E+03 1.3688892E+06
.12501 2.1516732E+03 1.3555705E+06
.13001 2.1350205E+03 1.3462681E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec)
.13501 2.1319480E+03 1.3445234E+06
.14009 2.1415298E+03 1.3498034E+06
.14510 2.1540075E+03 1.3566900E+06
.15015 2.1608228E+03 1.3604378E+06
.15500 2.1603593E+03 1.3601520E+06
.16007 2.1547404E+03 1.3570065E+06
.16515 2.1446526E+03 1.3513889E+06
.17002 2.1327374E+03 1.3447619E+06
.17509 2.1250311E+03 1.3404793E+06
.18010 2.1255323E+03 1.3407503E+06
.18500 2.1307501E+03 1.3436315E+06
.19010 2.1359241E+03 1.3464861E+06
.19507 2.1377315E+03 1.3474736E+06
.20008 2.1357354E+03 1.3463523E+06
.21002 2.1305966E+03 1.3434798E+06
.22009 2.1455142E+03 1.3517412E+06
.23010 2.1609519E+03 1.3602792E+06
.24007 2.1500994E+03 1.3542251E+06
.25001 2.1319210E+03 1.3441210E+06
.26002 2.1212847E+03 1.3437534E+06
.27006 2.1408201E+03 1.3490219E+06
.28015 2.1382240E+03 1.3475602E+06
.29011 2.1219655E+03 1.3385282E+06
.30028 2.1125694E+03 1.3333092E+06
.31011 2.1146636E+03 1.3344534E+06
.32004 2.1134582E+03 1.3337664E+06
.33005 2.1102424E+03 1.3319670E+06
.34002 2.1162685E+03 1.3352858E+06
.35002 2.1252674E+03 1.3402496E+06
.36002 2.1249488E+03 1.3400427E+06
.37007 2.1182970E+03 1.3363273E+06
.38010 2.1179299E+03 1.3360961E+06
.39027 2.1241025E+03 1.3394390E+06
.40003 2.1244819E+03 1.3396673E+06
.41001 2.1157197E+03 1.3347842E+06
.42004 2.1079031E+03 1.3304251E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec)
.43006 2.1057949E+03 1.3292307E+06
.44011 2.1038434E+03 1.3281221E+06
.45008 2.1005501E+03 1.3262686E+06
.46002 2.1008990E+03 1.3264325E+06
.47013 2.1046381E+03 1.3284716E+06
.48001 2.1065466E+03 1.3294937E+06
.49011 2.1055653E+03 1.3289117E+06
.50010 2.1065499E+03 1.3294210E+06
.51005 2.1109307E+03 1.3318103E+06
.52014 2.1132353E+03 1.3330479E+06
.53006 2.1104929E+03 1.3314882E+06
.54010 2.1067324E+03 1.3293690E+06
.55002 2.1047031E+03 1.3282077E+06
.56003 2.1025984E+03 1.3270031E+06
.57000 2.0994619E+03 1.3252280E+06
.58000 2.0974864E+03 1.3240966E+06
.59023 2.0978998E+03 1.3242862E+06
.60010 2.0987566E+03 1.3247206E+06
.61005 2.0988030E+03 1.3247041E+06
.62019 2.0998437E+03 1.3252383E+06
.63007 2.1029363E+03 1.3269102E+06
.64009 2.1057724E+03 1.3284358E+06
.65011 2.1063355E+03 1.3287028E+06
.66008 2.1058521E+03 1.3283898E+06
.67006 2.1056166E+03 1.3282154E+06
.68003 2.1048258E+03 1.3277315E+06
.69009 2.1027606E+03 1.3265436E+06
.70006 2.1004766E+03 1.3252341E+06
.71021 2.0994186E+03 1.3246041E+06
.72013 2.0991217E+03 1.3243955E+06
.73018 2.0986674E+03 1.3240994E+06
.74006 2.0987148E+03 1.3240815E+06
.75009 2.1001279E+03 1.3248191E+06
.76008 2.1022067E+03 1.3259240E+06
.77007 2.1038110E+03 1.3267654E+06
.78001 2.1049477E+03 1.3273479E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec)
.79005 2.1060244E+03 1.3278975E+06
.80008 2.1065644E+03 1.3281484E+06
.81002 2.1059659E+03 1.3277697E+06
.82003 2.1046670E+03 1.3270043E+06
.83006 2.1036100E+03 1.3263731E+06
.84009 2.1028557E+03 1.3259083E+06
.85013 2.1019975E+03 1.3253876E+06
.86002 2.1012207E+03 1.3249123E+06
.87004 2.1011387E+03 1.3248209E+06
.88001 2.1018523E+03 1.3251709E+06
.89009 2.1029599E+03 1.3257378E+06
.90001 2.1041960E+03 1.3263762E+06
.92003 2.1066767E+03 1.3276561E+06
.93004 2.1070790E+03 1.3278333E+06
.94009 2.1068436E+03 1.3276548E+06
.95015 2.1064606E+03 1.3273966E+06
.91007 2.1055640E+03 1.3270867E+06
.96022 2.1060345E+03 1.3271155E+06
.97001 2.1052992E+03 1.3266634E+06
.98005 2.1042714E+03 1.3260489E+06
.99010 2.1033853E+03 1.3255134E+06 1.00003 2.1030192E+03 1.3252670E+06 1.00015 2.1030185E+03 1.3252660E+06 1.01010 2.1031598E+03 1.3252999E+06 1.02001 2.1036738E+03 1.3255407E+06 1.03002 2.1044850E+03 1.3259460E+06 1.04010 2.1053738E+03 1.3263933E+06 1.05011 2.1060053E+03 1.3266987E+06 1.06006 2.1063215E+03 1.3268299E+06 1.07003 2.1065103E+03 1.3268901E+06 1.08001 2.1065562E+03 1.3268717E+06 1.09002 2.1062535E+03 1.3266603E+06 1.10005 2.1054973E+03 1.3261987E+06 1.11001 2.1045159E+03 1.3256120E+06 1.12004 2.1036583E+03 1.3250948E+06 1.13020 2.1030886E+03 1.3247376E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 7 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec) 1.14007 2.1028399E+03 1.3245581E+06 1.15004 2.1028392E+03 1.3245158E+06 1.16002 2.1030452E+03 1.3245891E+06 1.17008 2.1033358E+03 1.3247086E+06 1.18009 2.1036084E+03 1.3248175E+06 1.19008 2.1038945E+03 1.3249345E+06 1.20005 2.1041572E+03 1.3250391E+06 1.21005 2.1041987E+03 1.3250213E+06 1.22004 2.1038425E+03 1.3247830E+06 1.23001 2.1031332E+03 1.3243498E+06 1.24003 2.1022976E+03 1.3238470E+06 1.25007 2.1014833E+03 1.3233569E+06 1.26010 2.1007977E+03 1.3229378E+06 1.27007 2.1002438E+03 1.3225929E+06 1.28000 2.0998158E+03 1.3223173E+06 1.29006 2.0995386E+03 1.3221250E+06 1.30006 2.0993915E+03 1.3220048E+06 1.31013 2.0994058E+03 1.3219736E+06 1.32023 2.0995298E+03 1.3220039E+06 1.33005 2.0995986E+03 1.3220040E+06 1.34003 2.0994684E+03 1.3218931E+06 1.35003 2.0990790E+03 1.3216402E+06 1.36003 2.0984545E+03 1.3212564E+06 1.37021 2.0977429E+03 1.3208245E+06 1.38008 2.0969880E+03 1.3203695E+06 1.39003 2.0962009E+03 1.3198970E+06 1.40007 2.0954355E+03 1.3194364E+06 1.41000 2.0947605E+03 1.3190272E+06 1.42008 2.0941729E+03 1.3186648E+06 1.43000 2.0937703E+03 1.3184063E+06 1.44009 2.0935338E+03 1.3182384E+06 1.45002 2.0933865E+03 1.3181211E+06 1.46007 2.0932071E+03 1.3179859E+06 1.47003 2.0929094E+03 1.3177850E+06 1.48002 2.0924851E+03 1.3175144E+06 1.49013 2.0919562E+03 1.3171856E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 8 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec) 1.50005 2.0913287E+03 1.3168027E+06 1.51010 2.0906026E+03 1.3163655E+06 1.52003 2.0897881E+03 1.3158794E+06 1.53000 2.0889400E+03 1.3153753E+06 1.54004 2.0881300E+03 1.3148919E+06 1.55003 2.0874180E+03 1.3144632E+06 1.56002 2.0868363E+03 1.3141071E+06 1.57009 2.0863657E+03 1.3138119E+06 1.58003 2.0859830E+03 1.3135658E+06 1.59008 2.0856058E+03 1.3133222E+06 1.60014 2.0852041E+03 1.3130654E+06 1.61003 2.0847664E+03 1.3127889E+06 1.62002 2.0842650E+03 1.3124767E+06 1.63000 2.0836788E+03 1.3121187E+06 1.64000 2.0829808E+03 1.3116980E+06 1.65005 2.0822069E+03 1.3112361E+06 1.66001 2.0813530E+03 1.3107288E+06 1.67010 2.0805367E+03 1.3102429E+06 1.68013 2.0797667E+03 1.3097828E+06 1.69008 2.0790890E+03 1.3093745E+06 1.70008 2.0784817E+03 1.3090042E+06 1.71005 2.0779442E+03 1.3086733E+06 1.72006 2.0774536E+03 1.3083681E+06 1.73003 2.0769919E+03 1.3080787E+06 1.74005 2.0765358E+03 1.3077923E+06 1.75017 2.0760313E+03 1.3074793E+06 1.76021 2.0754782E+03 1.3071398E+06 1.77003 2.0748364E+03 1.3067506E+06 1.78009 2.0741177E+03 1.3063189E+06 1.79004 2.0733817E+03 1.3058784E+06 1.80001 2.0725989E+03 1.3054116E+06 1.81000 2.0718428E+03 1.3049592E+06 1.82003 2.0711342E+03 1.3045334E+06 1.83004 2.0704825E+03 1.3041393E+06 1.84005 2.0698712E+03 1.3037673E+06 1.85006 2.0693256E+03 1.3034315E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 9 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec) 1.86007 2.0688391E+03 1.3031290E+06 1.87004 2.0683537E+03 1.3028266E+06 1.88007 2.0678600E+03 1.3025183E+06 1.89005 2.0673398E+03 1.3021967E+06 1.90017 2.0667719E+03 1.3018481E+06 1.91001 2.0661520E+03 1.3014713E+06 1.92008 2.0654916E+03 1.3010717E+06 1.93007 2.0647986E+03 1.3006537E+06 1.94002 2.0641131E+03 1.3002406E+06 1.95002 2.0634306E+03 1.2998286E+06 1.96004 2.0627835E+03 1.2994362E+06 1.97001 2.0621900E+03 1.2990740E+06 1.98001 2.0616378E+03 1.2987343E+06 1.99001 2.0611133E+03 1.2984091E+06 2.00006 2.0606351E+03 1.2981098E+06 2.01017 2.0601755E+03 1.2978210E+06 2.02002 2.0596908E+03 1.2975184E+06 2.03010 2.0591909E+03 1.2972067E+06 2.04002 2.0586654E+03 1.2968812E+06 2.05018 2.0581050E+03 1.2965364E+06 2.06005 2.0575012E+03 1.2961667E+06 2.07004 2.0568982E+03 1.2957985E+06 2.08009 2.0562820E+03 1.2954219E+06 2.09012 2.0556887E+03 1.2950588E+06 2.10002 2.0551138E+03 1.2947052E+06 2.11010 2.0545765E+03 1.2943725E+06 2.12013 2.0540837E+03 1.2940645E+06 2.13010 2.0536205E+03 1.2937729E+06 2.14019 2.0531798E+03 1.2934939E+06 2.15007 2.0527452E+03 1.2932172E+06 2.16008 2.0523014E+03 1.2929356E+06 2.17003 2.0518411E+03 1.2926450E+06 2.18009 2.0513588E+03 1.2923422E+06 2.19004 2.0508552E+03 1.2920279E+06 2.20009 2.0503249E+03 1.2916980E+06 2.21011 2.0497884E+03 1.2913649E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 10 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec) 2.22017 2.0492528E+03 1.2910321E+06 2.23014 2.0487253E+03 1.2907039E+06 2.24005 2.0482384E+03 1.2903987E+06 2.25001 2.0477626E+03 1.2900986E+06 2.26009 2.0473225E+03 1.2898187E+06 2.27004 2.0468923E+03 1.2895433E+06 2.28001 2.0465016E+03 1.2892908E+06 2.29005 2.0460991E+03 1.2890308E+06 2.30001 2.0456898E+03 1.2887674E+06 2.31012 2.0452463E+03 1.2884848E+06 2.32007 2.0448340E+03 1.2882196E+06 2.33014 2.0443954E+03 1.2879401E+06 2.34004 2.0439367E+03 1.2876484E+06 2.35001 2.0434889E+03 1.2873633E+06 2.36011 2.0430542E+03 1.2870850E+06 2.37008 2.0426322E+03 1.2868139E+06 2.38012 2.0422433E+03 1.2865609E+06 2.39005 2.0418693E+03 1.2863161E+06 2.40004 2.0415246E+03 1.2860877E+06 2.41008 2.0412113E+03 1.2858761E+06 2.42005 2.0408975E+03 1.2856645E+06 2.43008 2.0406149E+03 1.2854698E+06 2.44013 2.0403182E+03 1.2852674E+06 2.45001 2.0400192E+03 1.2850640E+06 2.46020 2.0397042E+03 1.2848514E+06 2.47007 2.0393890E+03 1.2846382E+06 2.48001 2.0390787E+03 1.2844277E+06 2.49005 2.0387565E+03 1.2842108E+06 2.50017 2.0384506E+03 1.2840029E+06 2.51008 2.0381551E+03 1.2838008E+06 2.52000 2.0378823E+03 1.2836107E+06 2.53003 2.0376188E+03 1.2834258E+06 2.54003 2.0373717E+03 1.2832502E+06 2.55004 2.0371414E+03 1.2830827E+06 2.56007 2.0369174E+03 1.2829200E+06 2.57007 2.0367206E+03 1.2827722E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 11 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec) 2.58005 2.0365020E+03 1.2826116E+06 2.59008 2.0362817E+03 1.2824507E+06 2.60014 2.0360644E+03 1.2822909E+06 2.61006 2.0358300E+03 1.2821214E+06 2.62001 2.0355880E+03 1.2819481E+06 2.63008 2.0353598E+03 1.2817817E+06 2.64006 2.0351206E+03 1.2816095E+06 2.65009 2.0349045E+03 1.2814499E+06 2.66003 2.0346896E+03 1.2812913E+06 2.67013 2.0344844E+03 1.2811382E+06 2.68004 2.0342912E+03 1.2809913E+06 2.69000 2.0341169E+03 1.2808550E+06 2.70009 2.0339484E+03 1.2807220E+06 2.71006 2.0337700E+03 1.2805830E+06 2.72003 2.0335952E+03 1.2804464E+06 2.73003 2.0334197E+03 1.2803093E+06 2.74018 2.0332272E+03 1.2801628E+06 2.75014 2.0330332E+03 1.2800152E+06 2.76007 2.0328279E+03 1.2798616E+06 2.77002 2.0326244E+03 1.2797091E+06 2.78002 2.0324222E+03 1.2795567E+06 2.79008 2.0322290E+03 1.2794097E+06 2.80006 2.0320428E+03 1.2792666E+06 2.81009 2.0318584E+03 1.2791244E+06 2.82006 2.0316917E+03 1.2789921E+06 2.83006 2.0315113E+03 1.2788520E+06 2.84015 2.0313383E+03 1.2787161E+06 2.85005 2.0311662E+03 1.2785814E+06 2.86003 2.0309809E+03 1.2784384E+06 2.87004 2.0307972E+03 1.2782965E+06 2.88006 2.0306091E+03 1.2781518E+06 2.89010 2.0304103E+03 1.2780018E+06 2.90019 2.0302106E+03 1.2778513E+06 2.91001 2.0299968E+03 1.2776931E+06 2.92007 2.0297956E+03 1.2775412E+06 2.93007 2.0295874E+03 1.2773863E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 12 of 12 TABLE 14.3.4-16 DOUBLE-ENDED SPRAY LINE BREAK MASS AND ENERGY RELEASES (When using this table, add 15% multiplier to mass & energy results.)
Time Mass Energy (sec) (lb/sec) (BTU/sec) 2.94014 2.0293708E+03 1.2772257E+06 2.95003 2.0291890E+03 1.2770853E+06 2.96002 2.0289876E+03 1.2769341E+06 2.97013 2.0287920E+03 1.2767858E+06 2.98010 2.0285960E+03 1.2766370E+06 2.99010 2.0283918E+03 1.2764839E+06 3.00017 2.0281887E+03 1.2763315E+06 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-17 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 FAN ROOM - BACKFLOW CONTRIBUTION Time Mass Flow Rate Energy Flow Rate (sec) 103 lb/sec 106 BTU/sec 0 7.54 8.99
.1 4.68 5.58
.2 4.48 5.34
.3 4.41 5.26
.4 4.32 5.15
.5 4.27 5.09
.6 4.15 4.95
.7 3.93 4.68
.8 3.59 4.28
.9 3.62 4.32 1.0 3.53 4.21 1.5 3.17 3.78 2.0 3.00 3.58 2.5 2.93 3.49 3.0 2.87 3.42 3.5 2.87 3.42 4.0 2.83 3.37 4.5 2.79 3.33 5.0 2.81 3.35 5.5 2.77 3.30 6.0 2.72 3.24 6.5 2.72 3.24 7.0 2.69 3.21 8.0 2.65 3.16 8.5 2.65 3.16 9.0 2.65 3.16 9.5 2.65 3.16 10.0 2.65 3.16 With 1.4 ft2 orifice in cross-connect to steam dump header; break in longest line.
Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-17 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 FAN ROOM - FORWARD FLOW CONTRIBUTION Time Mass Flow Rate Energy Flow Rate (sec) 103 lb/sec 106 BTU/sec 0 5.55 6.62
.1 4.15 4.94
.2 3.05 3.64
.4 2.95 3.52
.6 2.90 3.46
.8 2.78 3.31 1.0 2.75 3.28 1.5 2.67 3.19 2.0 3.45 3.38 2.5 9.50 5.26 3.0 9.42 5.21 3.5 9.38 5.19 4.0 9.33 5.16 4.5 9.28 5.13 5.0 9.23 5.10 5.5 9.16 5.07 6.0 9.10 5.04 6.5 9.03 5.01 7.0 8.95 4.97 7.5 8.86 4.93 8.0 8.80 4.91 8.5 8.70 4.86 9.0 8.58 4.81 9.5 8.46 4.76 10.0 8.33 4.70 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-18 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 TABLE 14.3.4-18 DOUBLE-ENDED HOT LEG BREAK MASS AND ENERGY RELEASES Time Mass Energy (sec) (lb/sec) (BTU/sec) 0.00000 0.000000+4 0.000000+6 0.00201 6.296400+4 3.616100+7 0.00401 7.377000+4 4.235700+7 0.00900 6.916800+4 3.973700+7 0.01200 7.047200+4 4.051200+7 0.01602 7.176400+4 4.127400+7 0.01800 7.220100+4 4.153500+7 0.02500 7.467100+4 4.308700+7 0.02600 9.129400+4 5.264000+7 0.03000 9.888800+4 5.705000+7 0.03100 9.359200+4 5.392400+7 0.03300 1.034800+5 5.976200+7 0.04100 9.387700+4 5.419200+7 0.04301 9.958000+4 5.748900+7 0.04500 9.310800+4 5.373800+7 0.04900 1.018200+5 5.884600+7 0.05300 9.121800+4 5.262800+7 0.05401 1.044100+5 6.038900+7 0.05501 9.202900+4 5.320000+7 0.05800 9.912800+4 5.729100+7 0.06000 9.173100+4 5.296500+7 0.06301 9.862900+4 5.702600+7 0.06400 9.010400+4 5.204400+7 0.06500 9.892900+4 5.723900+7 0.06701 9.587100+4 5.549400+7 0.06801 1.003200+5 5.805800+7 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-18 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 TABLE 14.3.4-18 DOUBLE-ENDED HOT LEG BREAK MASS AND ENERGY RELEASES Time Mass Energy (sec) (lb/sec) (BTU/sec) 0.07101 9.013600+4 5.208200+7 0.07200 9.396300+4 5.452900+7 0.07501 8.496600+4 4.913900+7 0.07600 9.286800+4 5.381600+7 0.08000 9.345900+4 5.411400+7 0.08301 9.631400+4 5.578500+7 0.08900 9.182300+4 5.321800+7 0.09401 8.716100+4 5.049300+7 0.10002 8.686700+4 5.036900+7 0.10103 8.751800+4 5.074300+7 0.10702 8.667200+4 5.026600+7 0.11702 8.066200+4 4.679300+7 0.12400 7.836000+4 4.550000+7 0.13004 7.823800+4 4.547300+7 0.19005 6.766600+4 3.960300+7 0.40013 6.328000+4 3.674300+7 0.60020 6.005400+4 3.460400+7 1.00020 5.560800+4 3.192700+7 1.52020 5.046300+4 2.929200+7 2.00020 4.687700+4 2.759500+7 3.00000 4.687700+4 2.759500+7 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-19 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 TABLE 14.3.4-19 SINGLE-ENDED COLD LEG BREAK MASS AND ENERGY RELEASES Time Mass Energy (sec) (lb/sec) (BTU/sec)
.00000 0.000000+4 0.000000+7
.00200 2.4652E+04 1.2752E+07
.00900 3.4491E+04 1.7946E+07
.01400 5.0203E+04 2.6009E+07
.02100 6.0914E+04 3.1606E+07
.03203 7.2136E+04 3.7456E+07
.04304 8.3502E+04 4.3434E+07
.05101 8.5426E+04 4.4414E+07
.06503 8.4836E+04 4.4078E+07
.08305 8.0678E+04 4.1866E+07
.09607 7.5506E+04 3.9152E+07
.11001 7.4227E+04 3.8487E+07
.13403 7.5861E+04 3.9362E+07
.14601 7.6620E+04 3.9755E+07
.16010 7.6233E+04 3.9551E+07
.18303 7.5634E+04 3.9236E+07
.19804 7.4886E+04 3.8846E+07
.21101 7.3690E+04 3.8219E+07
.23006 7.4895E+04 3.8860E+07
.24610 7.5605E+04 3.9233E+07
.25607 7.5224E+04 3.9028E+07
.26309 7.4595E+04 3.8696E+07
.28206 7.3024E+04 3.7873E+07
.30006 7.3101E+04 3.7920E+07
.31610 7.4255E+04 3.8528E+07
.33509 7.4163E+04 3.8475E+07
.35108 7.4723E+04 3.8773E+07 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-19 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 TABLE 14.3.4-19 SINGLE-ENDED COLD LEG BREAK MASS AND ENERGY RELEASES Time Mass Energy (sec) (lb/sec) (BTU/sec)
.37109 7.3988E+04 3.8382E+07
.41506 7.5856E+04 3.9368E+07
.44107 7.5568E+04 3.9214E+07
.46702 7.4918E+04 3.8871E+07
.49303 7.4959E+04 3.8896E+07
.53003 7.4459E+04 3.8635E+07
.64516 7.3810E+04 3.8313E+07
.69503 7.3409E+04 3.8118E+07
.73001 7.3524E+04 3.8194E+07
.77006 7.3550E+04 3.8224E+07
.83001 7.1814E+04 3.7342E+07
.87509 7.2210E+04 3.7577E+07
.92001 7.1425E+04 3.7191E+07
.96002 7.1669E+04 3.7344E+07 1.0400 7.0980E+04 3.7031E+07 1.1701 7.0215E+04 3.6723E+07 1.3202 6.9872E+04 3.6671E+07 1.4001 6.9903E+04 3.6760E+07 1.7002 6.5502E+04 3.4750E+07 2.0000 6.2185E+04 3.3253E+07 2.5001 5.5091E+04 2.9852E+07 3.0002 4.8491E+04 2.6562E+07 5.0000 4.8491E+04 2.6562E+07 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-20 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 TABLE 14.3.4-20 SINGLE-ENDED HOT LEG BREAK MASS AND ENERGY RELEASES Time Mass Energy (sec) (lb/sec) (BTU/sec)
.00000 0.000000+4 0.000000+7
.00100 2.986053E+04 1.811825E+07
.00301 4.343918E+04 2.634650E+07
.00501 4.292521E+04 2.602551E+07
.01001 4.446135E+04 2.695169E+07
.01400 5.141999E+04 3.123442E+07
.01700 4.673055E+04 2.831411E+07
.02200 4.933676E+04 2.992951E+07
.02700 6.370431E+04 3.867952E+07
.03301 7.988087E+04 4.855038E+07
.03901 7.280847E+04 4.417453E+07
.05001 7.321976E+04 4.444181E+07
.06002 6.824339E+04 4.137223E+07
.06503 6.529671E+04 3.957400E+07
.07204 6.781116E+04 4.112542E+07
.08003 6.387430E+04 3.870615E+07
.08701 6.107294E+04 3.699999E+07
.09200 6.153000E+04 3.728505E+07
.10101 5.928957E+04 3.591744E+07
.11003 5.571592E+04 3.374574E+07
.12001 5.454139E+04 3.303515E+07
.13202 5.230680E+04 3.168585E+07
.14102 5.268915E+04 3.193353E+07
.14802 5.253517E+04 3.184939E+07
.16105 5.355463E+04 3.248006E+07
.17003 5.336413E+04 3.235884E+07 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-20 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 TABLE 14.3.4-20 SINGLE-ENDED HOT LEG BREAK MASS AND ENERGY RELEASES Time Mass Energy (sec) (lb/sec) (BTU/sec)
.18500 5.353877E+04 3.246602E+07
.20003 5.186517E+04 3.149525E+07
.22500 4.640067E+04 2.829631E+07
.25002 4.433356E+04 2.709931E+07
.30003 4.316692E+04 2.649927E+07
.32811 4.406912E+04 2.715201E+07
.35016 4.359122E+04 2.691206E+07
.40004 4.291035E+04 2.645033E+07
.42302 4.323305E+04 2.665236E+07
.45011 4.282392E+04 2.641563E+07
.52004 4.230519E+04 2.601617E+07
.60016 4.197678E+04 2.568951E+07
.70035 4.194488E+04 2.555825E+07
.80004 4.204749E+04 2.547428E+07
.88531 4.220963E+04 2.546782E+07 1.00012 4.190713E+04 2.535124E+07 1.50000 3.994366E+04 2.439612E+07 2.00023 3.835372E+04 2.358048E+07 2.50028 3.711276E+04 2.282196E+07 3.00016 3.583929E+04 2.204359E+07 5.00000 3.583929E+04 2.204359E+07 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-21 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 TABLE 14.3.4-21 STEAM GENERATOR ENCLOSURE - TMD VOLUME INPUT TMD Node Volume (ft3) 46 4106 47 1125 48 634 49 615 50 1021 51 1076 52 669 53 661 54 998 55 3900 56 1030 57 634 58 615 59 807 60 990 61 669 62 661 63 801 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-22 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 TABLE 14.3.4-22 PRESSURIZER ENCLOSURE MODEL - TMD VOLUME INPUT TMD Node TMD Node 3 Common to Loop TMD Node Description Volume (ft ) Unique to this Subcompartment Model Model 1 Loop Compartment 2.2415E+04 No Yes 2 Loop Compartment 2.2845E+04 No Yes 3 Loop Compartment 4.1329E+04 No Yes 4 Loop Compartment 2.7398E+04 No Yes 5 Loop Compartment 2.2839E+04 No Yes 6 Loop Compartment 1.9921E+04 No Yes 7 Ice Condenser 3.5230E+03 No Yes 8 Ice Condenser 3.5230E+03 No Yes 9 Ice Condenser 3.4090E+03 No Yes 10 Ice Condenser 4.1660E+03 No Yes 11 Ice Condenser 4.1660E+03 No Yes 12 Ice Condenser 4.0330E+03 No Yes 13 Ice Condenser 8.3300E+03 No Yes 14 Ice Condenser 8.3300E+03 No Yes 15 Ice Condenser 8.0590E+03 No Yes 16 Ice Condenser 5.7680E+03 No Yes 17 Ice Condenser 5.7680E+03 No Yes 18 Ice Condenser 5.5800E+03 No Yes 19 Ice Condenser 4.4850E+03 No Yes 20 Ice Condenser 4.4850E+03 No Yes 21 Ice Condenser 4.3400E+03 No Yes 22 Ice Condenser 4.4850E+03 No Yes Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-22 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 TABLE 14.3.4-22 PRESSURIZER ENCLOSURE MODEL - TMD VOLUME INPUT TMD Node TMD Node Common to Loop TMD Node Description Volume (ft3) Unique to this Subcompartment Model Model 23 Ice Condenser 4.4850E+03 No Yes 24 Ice Condenser 4.3400E+03 No Yes 25 Upper Containment 7.3432E+05 No Yes 26 Pipe Trench 1.0435E+04 No Yes 27 Fan/Accumulator Room 2.6969E+04 No Yes 28 Pipe Trench 1.0435E+04 No Yes 29 Instrument Room 1.7479E+04 No Yes 30 Pipe Trench 1.0435E+04 No Yes 31 Fan/Accumulator Room 2.6969E+04 No Yes 32 Pipe Trench 1.0435E+04 No Yes 33 Upper Reactor Cavity 1.8012E+04 No Yes 34 Ice Condenser 5.3850E+03 No Yes 35 Ice Condenser 6.3650E+03 No Yes 36 Ice Condenser 1.2729E+04 No Yes 37 Ice Condenser 8.8130E+03 No Yes 38 Ice Condenser 6.8540E+03 No Yes 39 Ice Condenser 6.8540E+03 No Yes 40 Ice Condenser 2.8910E+03 No Yes 41 Ice Condenser 3.4180E+03 No Yes 42 Ice Condenser 6.8350E+03 No Yes 43 Ice Condenser 4.7320E+03 No Yes 44 Ice Condenser 3.6810E+03 No Yes 45 Ice Condenser 3.6810E+03 No Yes Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-22 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 TABLE 14.3.4-22 PRESSURIZER ENCLOSURE MODEL - TMD VOLUME INPUT TMD Node TMD Node Common to Loop TMD Node Description Volume (ft3) Unique to this Subcompartment Model Model 46 Pressurizer Enclosure 1.5517E+03 Yes No 47 Pressurizer Enclosure 3.0260E+02 Yes No 48 Pressurizer Enclosure 4.3106E+02 Yes No 49 Pressurizer Enclosure 3.5367E+02 Yes No Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-23 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 TABLE 14.3.4-23 FAN ACCUMULATOR ROOM MODEL - TMD VOLUME INPUT Volume TMD Node (ft3) 27 3800 54 4000 55 7800 56 4300 57 4400 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-24 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 TABLE 14.3.4-24 LOOP SUBCOMPARTMENT MODEL - TMD VOLUME INPUT TMD Node Common to TMD Node 3 Pressurizer Enclosure &
TMD Node Description Volume (ft ) Unique to this Steam Generator Model Enclosure Models 1 Loop Compartment 2.2415E+04 No Yes 2 Loop Compartment 2.2845E+04 No Yes 3 Loop Compartment 4.1329E+04 No Yes 4 Loop Compartment 2.7398E+04 No Yes 5 Loop Compartment 2.2839E+04 No Yes 6 Loop Compartment 1.9921E+04 No Yes 7 Ice Condenser 3.5230E+03 No Yes 8 Ice Condenser 3.5230E+03 No Yes 9 Ice Condenser 3.4090E+03 No Yes 10 Ice Condenser 4.1660E+03 No Yes 11 Ice Condenser 4.1660E+03 No Yes 12 Ice Condenser 4.0330E+03 No Yes 13 Ice Condenser 8.3300E+03 No Yes 14 Ice Condenser 8.3300E+03 No Yes 15 Ice Condenser 8.0590E+03 No Yes 16 Ice Condenser 5.7680E+03 No Yes 17 Ice Condenser 5.7680E+03 No Yes 18 Ice Condenser 5.5800E+03 No Yes 19 Ice Condenser 4.4850E+03 No Yes 20 Ice Condenser 4.4850E+03 No Yes 21 Ice Condenser 4.3400E+03 No Yes Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-24 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 TABLE 14.3.4-24 LOOP SUBCOMPARTMENT MODEL - TMD VOLUME INPUT TMD Node Common to TMD Node 3 Pressurizer Enclosure &
TMD Node Description Volume (ft ) Unique to this Steam Generator Model Enclosure Models 22 Ice Condenser 4.4850E+03 No Yes 23 Ice Condenser 4.4850E+03 No Yes 24 Ice Condenser 4.3400E+03 No Yes 25 Upper Containment 7.3432E+05 No Yes 26 Pipe Trench 1.0435E+04 No Yes 27 Fan/Accumulator Room 2.6969E+04 No Yes 28 Pipe Trench 1.0435E+04 No Yes 29 Instrument Room 1.7479E+04 No Yes 30 Pipe Trench 1.0435E+04 No Yes 31 Fan/Accumulator Room 2.6969E+04 No Yes 32 Pipe Trench 1.0435E+04 No Yes 33 Upper Reactor Cavity 1.8012E+04 No Yes 34 Ice Condenser 5.3850E+03 No Yes 35 Ice Condenser 6.3650E+03 No Yes 36 Ice Condenser 1.2729E+04 No Yes 37 Ice Condenser 8.8130E+03 No Yes 38 Ice Condenser 6.8540E+03 No Yes 39 Ice Condenser 6.8540E+03 No Yes 40 Ice Condenser 2.8910E+03 No Yes 41 Ice Condenser 3.4180E+03 No Yes 42 Ice Condenser 6.8350E+03 No Yes Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-24 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 TABLE 14.3.4-24 LOOP SUBCOMPARTMENT MODEL - TMD VOLUME INPUT TMD Node Common to TMD Node 3 Pressurizer Enclosure &
TMD Node Description Volume (ft ) Unique to this Steam Generator Model Enclosure Models 43 Ice Condenser 4.7320E+03 No Yes 44 Ice Condenser 3.6810E+03 No Yes 45 Ice Condenser 3.6810E+03 No Yes 46 Steam Generator 3.4040E+03 Yes No Enclosure 47 Steam Generator 3.1210E+03 Yes No Enclosure 48 Steam Generator 3.1210E+03 Yes No Enclosure 49 Steam Generator 3.4040E+03 Yes No Enclosure 50 Steam Generator 7.5010E+03 Yes No Enclosure 51 Steam Generator 6.9860E+03 Yes No Enclosure 52 Steam Generator 6.9860E+03 Yes No Enclosure 53 Steam Generator 7.5010E+03 Yes No Enclosure Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-25 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 4 TABLE 14.3.4-25 REACTOR CAVITY - TMD VOLUME INPUT MODEL TMD Node Volume (ft3)
Break Location (CPS 189) -
1 131.4 Inspection Volume Lower Reactor Cavity - Below 2 3724.9 RPV 3 Reactor Vessel Annular Region 7.2 4 Reactor Vessel Annular Region 0.6 5 Reactor Vessel Annular Region 3.5 6 Reactor Vessel Annular Region 4.1 7 Reactor Vessel Annular Region 0.6 8 Reactor Vessel Annular Region 44.8 9 Reactor Vessel Annular Region 0.6 10 Reactor Vessel Annular Region 3.4 11 Reactor Vessel Annular Region 4.0 12 Reactor Vessel Annular Region 0.5 13 Reactor Vessel Annular Region 43.8 14 Reactor Vessel Annular Region 0.6 15 Reactor Vessel Annular Region 3.4 16 Reactor Vessel Annular Region 5.6 17 Reactor Vessel Annular Region 2.7 18 Reactor Vessel Annular Region 43.8 19 Reactor Vessel Annular Region 7.7 Unit 1 Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-25 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 4 TABLE 14.3.4-25 REACTOR CAVITY - TMD VOLUME INPUT MODEL TMD Node Volume (ft3) 20 Reactor Vessel Annular Region 11.0 21 Reactor Vessel Annular Region 91.0 22 Reactor Vessel Annular Region 18.9 23 Reactor Vessel Annular Region 92.8 24 Reactor Vessel Annular Region 19.0 25 Reactor Vessel Annular Region 94.6 26 Reactor Vessel Annular Region 18.9 27 Reactor Vessel Annular Region 92.8 28 Reactor Vessel Annular Region 18.7 29 Reactor Vessel Annular Region 91.0 30 Reactor Vessel Annular Region 7.9 31 Reactor Vessel Annular Region 11.0 32 Reactor Vessel Annular Region 92.8 33 Reactor Vessel Annular Region 0.6 34 Reactor Vessel Annular Region 3.5 35 Reactor Vessel Annular Region 5.5 36 Reactor Vessel Annular Region 2.5 37 Reactor Vessel Annular Region 44.8 38 Upper Reactor Cavity 15720.9 Inspection Volume 39 135.0 (CPS 188)
Unit 1 Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-25 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 4 TABLE 14.3.4-25 REACTOR CAVITY - TMD VOLUME INPUT MODEL TMD Node Volume (ft3)
Inspection Volume 40 132.1 (CPS 187)
Inspection Volume 41 217.5 Port &Pipe Sleeve (CPS 186)
Inspection Volume 42 214.0 Port &Pipe Sleeve (CPS 185)
Inspection Volume 43 214.0 Port &Pipe Sleeve (CPS 184)
Inspection Volume 44 132.1 (CPS 183)
Inspection Volume 45 133.2 (CPS 182)
Broken Loop Pipe Sleeve 46 75.2 (CPS 189)
Unbroken Loop Pipe Sleeve 47 26.7 (CPS 188)
Unbroken Loop Pipe Sleeve 48 26.7 (CPS 187)
Unbroken Loop Pipe Sleeve 49 26.7 (CPS 183)
Unbroken Loop Pipe Sleeve 50 61.1 (CPS 182) 51 Loop Compartment 147644.0 52 Loop Compartment 147644.0 Broken Loop Inspection Port 53 46.900 (CPS 189)
Unbroken Loop Inspection Port 54 52.2 (CPS 188)
Unbroken Loop Inspection Port 55 52.2 (CPS 187)
Unbroken Loop Inspection Port 56 52.2 (CPS 183)
Unit 1 Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-25 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 4 TABLE 14.3.4-25 REACTOR CAVITY - TMD VOLUME INPUT MODEL TMD Node Volume (ft3)
Unbroken Loop Inspection Port 57 46.9 (CPS 182) 58 Instrument Tunnel 1825.9 59 Upper Containment 3934200.0 1 60 Lower RX Cavity Keyway 6547.1 61 Reactor Vessel Annular Region 0.5 Reactor Vessel Annular 62 0.5 Region 1
The upper compartment was modeled as an infinite sump.
Unit 1 Unit 2 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-26 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 TABLE 14.3.4-26 STEAM GENERATOR ENCLOSURE MODEL - TMD FLOW PATH INPUT STEAM LINE BREAK Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 46H-47 0.94 0.022 9.451 4.794 55.9 4.514 0.573 46R-48 0.673 0.022 6.590 3.538 25.4 1.948 0.290 46A-55 0.902 0.022 8.958 4.771 48.9 2.876 0.308 47H-51 0.938 0.022 9.891 4.297 50.1 5.102 0.691 47R-48 0.385 0.022 10.599 4.984 40.7 8.747 0.295 47A-56 0.765 0.022 7.776 4.976 25.5 3.065 0.352 48H-52 0.723 0.022 8.652 3.524 25.3 3.779 0.609 48R-49 0.296 0.022 13.767 5.057 41.3 12.841 0.947 48A-57 0.765 0.022 3.524 4.976 25.5 2.61 0.614 49H-53 0.757 0.022 9.229 3.744 26.712 4.375 0.662 49R-50 0.012 0.022 11.303 5.609 45.808 10.437 0.326 49A-46 0.662 0.022 7.522 3.967 28.302 2.93 0.326 50H-54 0.795 0.022 9.366 5.318 44.852 4.648 0.628 50R-47 0.677 0.022 7.590 5.079 41.48 5.008 0.295 50A-46 0.982 0.022 8.957 6.599 55.652 4.241 0.471 51H-2 1.339 0.022 8.248 4.107 46.4 3.522 0.564 51R-52 0.866 0.022 10.780 6.412 48.18 8.594 0.427 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-26 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 TABLE 14.3.4-26 STEAM GENERATOR ENCLOSURE MODEL - TMD FLOW PATH INPUT STEAM LINE BREAK Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 52H-2 0.722 0.022 10.937 7.201 49.1 8.128 0.962 52R-53 0.244 0.022 13.263 6.553 49.24 12.392 0.949 53H-1 2.100 0.022 9.453 6.272 48.212 7.392 0.963 53R-54 0.090 0.022 10.939 6.736 50.614 9.147 0.415 54H-1 0.988 0.022 6.483 3.730 39.852 3.164 0.526 54R-51 0.442 0.022 8.412 6.539 49.135 5.253 0.402 55H-56 0.703 0.022 7.977 3.765 43.90 2.775 0.470 55R-57 0.673 0.022 6.590 3.538 25.4 1.961 0.290 55A-58 0.649 0.022 7.456 3.91 27.9 2.863 0.322 56H-60 0.518 0.022 7.572 2.856 33.3 2.898 0.501 56R-57 0.373 0.022 10.568 4.972 40.6 8.713 0.291 57H-61 0.723 0.022 8.617 3.506 25.17 3.750 0.608 57R-58 0.296 0.022 13.767 5.057 41.3 12.841 0.947 58H-62 0.626 0.022 8.410 3.322 23.7 3.652 0.591 58R-59 0.015 0.022 11.778 5.609 45.644 10.611 0.429 59H-63 0.744 0.022 9.215 4.730 36.217 4.548 0.632 59R-56 0.703 0.022 7.253 3.88 31.69 4.938 0.227 59A-55 0.943 0.022 7.807 5.236 40.097 3.002 0.380 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-26 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 TABLE 14.3.4-26 STEAM GENERATOR ENCLOSURE MODEL - TMD FLOW PATH INPUT STEAM LINE BREAK Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 60H-2 1.111 0.022 7.718 3.567 40.3 3.304 0.529 60R-61 0.599 0.022 10.819 6.468 48.6 8.937 0.402 61H-2 0.857 0.022 9.837 6.292 42.9 6.169 0.839 61R-62 0.287 0.022 13.247 6.373 47.89 12.349 0.947 62H-3 2.121 0.022 9.457 6.245 48.00 8.091 1.0 62R-63 0.230 0.022 11.335 7.026 52.793 10.153 0.432 63H-3 0.820 0.022 5.494 2.564 26.517 2.727 0.412 63R-60 0.684 0.022 7.090 4.434 33.317 4.767 0.273 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-27 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 TABLE 14.3.4-27 STEAM GENERATOR ENCLOSURE MODEL - TMD FLOW PATH INPUT FEEDWATER LINE BREAK (CHANGES TO TABLE 14.3.4-26 TO CONVERT TO A FEED LINE BREAK.)
Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 46H-47 0.771 46R-48 0.612 47H-51 0.609 48H-52 0.496 49H-53 0.533 49A-46 0.701 50H-54 0.591 50A-46 0.780 55H-56 0.660 55R-57 0.613 55A-58 0.696 56H-60 0.437 57H-61 0.492 58H-62 0.476 59H-63 0.563 59A-55 0.700 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-28 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 5 TABLE 14.3.4-28 PRESSURIZER ENCLOSURE MODEL - TMD FLOW PATH INPUT 2
Flow Path K f LI (ft) DH (ft) AT (ft ) Leq (ft) AT /A 1-2 0.63 0. 18.6 1.0 635.0 0. 0.601 1-33 1.5 0. 4.23 1.0 11.9 0. 0.016 1-27 2.85 0. 3.6 1.0 21.4 0. 0.129 2-3 0.72 0. 25.0 1.0 600.0 0. 0.601 2-27 2.85 0. 5.5 1.0 85.3 0. 0.252 3-4 0.28 0. 33.5 1.0 570. 0. 0.648 3-33 1.5 0. 4.33 1.0 32.4 0. 0.021 3-27 2.85 0. 3.6 1.0 21.3 0. 0.128 4-5 0.56 0. 19.1 1.0 600.0 0. 0.601 4-33 1.5 0. 4.42 1.0 24.5 0. 0.022 4-31 2.85 0. 3.6 1.0 21.3 0. 0.128 5-6 0.63 0. 18.6 1.0 635.0 0. 0.601 5-31 2.85 0. 5.5 1.0 85.3 0. 0.129 6-1 1.45 0. 29.2 1.0 58.5 0. 0.055 6-33 1.5 0. 4.23 1.0 11.9 0. 0.014 6-31 2.85 0. 3.6 1.0 21.4 0. 0.129 7-8 0. 0.0276 12.278 0.855 112.8 16.0 0.727 8-9 0. 0.0276 12.278 0.855 112.8 16.0 0.727 9-34 0.812 0.0276 8.8558 0.855 112.8 8.0 0.727 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-28 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 5 TABLE 14.3.4-28 PRESSURIZER ENCLOSURE MODEL - TMD FLOW PATH INPUT 2
Flow Path K f LI (ft) DH (ft) AT (ft ) Leq (ft) AT /A 10-11 0. 0.0276 12.278 0.855 131.31 16.0 0.727 11-12 0. 0.0276 12.278 0.855 131.31 16.0 0.727 12-35 0.812 0.0276 8.8558 0.855 131.31 8.0 0.727 13-14 0. 0.0276 12.278 0.855 266.63 16.0 0.727 14-15 0. 0.0276 12.278 0.855 266.63 16.0 0.727 15-36 0.812 0.0276 8.8558 0.855 266.63 8.0 0.727 16-17 0. 0.0276 12.278 0.855 184.59 16.0 0.727 17-18 0. 0.0276 12.278 0.855 184.59 16.0 0.727 18-37 0.812 0.0276 8.8558 0.855 184.59 8.0 0.727 19-20 0. 0.0276 12.278 0.855 143.57 16.0 0.727 20-21 0. 0.0276 12.278 0.855 143.57 16.0 0.727 21-38 0.812 0.0276 8.8558 0.855 143.57 8.0 0.727 22-23 0. 0.0276 12.278 0.855 143.57 16.0 0.727 23-24 0. 0.0276 12.278 0.855 143.57 16.0 0.727 24-39 0.812 0.0276 8.8558 0.855 143.57 8.0 0.727 25-6 1.45 0. 6.08 1.0 2.2 0. .01 26-32 0.99 0. 64.5 1.0 17.0 0. 0.85 26-28 0.69 0. 45.8 1.0 25.0 0. 0.357 27-26 2.85 0. 8.0 1.0 55.0 0. 0.417 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-28 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 5 TABLE 14.3.4-28 PRESSURIZER ENCLOSURE MODEL - TMD FLOW PATH INPUT 2
Flow Path K f LI (ft) DH (ft) AT (ft ) Leq (ft) AT /A 27-29 2.85 0. 2.7 1.0 2.5 0. 0.008 28-3 2.6 0. 13.2 1.0 35.7 0. 0.077 28-27 2.85 0. 8.0 1.0 43.0 0. 0.254 29-28 2.85 0. 2.0 1.0 0.25 0. 0.001 29-3 2.85 0. 3.0 1.0 0.25 0. 0.002 30-28 0.99 0. 46.6 1.0 20.0 0. 1.0 30-4 2.6 0. 13.2 1.0 35.7 0. 0.106 31-30 2.85 0. 8.0 1.0 43.0 0. 0.254 31-29 2.85 0. 2.7 1.0 2.5 0. 0.007 32-30 0.69 0. 40.0 1.0 25.0 0. 0.417 32-31 2.85 0. 8.0 1.0 55.0 0. 0.331 33-2 1.5 0. 4.69 1.0 23.8 0. 0.034 33-5 1.5 0. 4.65 1.0 23.8 0. 0.034 34-25 1.45 0. 2.8 1.0 233.8 0. 0.659 35-25 1.43 0. 2.8 1.0 267.6 0. 0.65 36-25 1.43 0. 2.8 1.0 539.5 0. 0.625 37-25 1.41 0. 3.2 1.0 376.5 0. 0.636 38-25 1.44 0. 2.8 1.0 289.4 0. 0.646 39-25 1.43 0. 2.8 1.0 296.3 0. 0.646 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-28 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 5 TABLE 14.3.4-28 PRESSURIZER ENCLOSURE MODEL - TMD FLOW PATH INPUT 2
Flow Path K f LI (ft) DH (ft) AT (ft ) Leq (ft) AT /A 40-1 0.89 0. 10.36 1.0 121.9 1.0 0.225 40-7 0.227 0.01517 8.222 0.855 106.7 8.0 0.33 40-41 7.5 0. 13.8 1.0 24.7 0. 0.075 41-2 0.89 0. 10.36 1.0 144.0 1.0 0.225 41-10 0.227 0.01517 8.222 0.855 126.1 8.0 0.33 41-42 12.5 0. 22.4 1.0 24.7 0. 0.046 42-3 0.89 0. 10.36 1.0 288.0 1.0 0.225 42-13 0.227 0.01517 8.222 0.855 252.2 8.0 0.33 42-43 12.5 0. 25.3 1.0 24.7 0. 0.041 43-4 0.89 0. 10.36 1.0 199.4 1.0 0.225 43-16 0.227 0.01517 8.222 0.855 174.6 8.0 0.33 43-44 10.0 0. 18.4 1.0 24.7 0. 0.056 44-5 0.89 0. 10.36 1.0 155.1 1.0 0.225 44-19 0.227 0.01517 8.222 0.855 135.8 8.0 0.33 44-45 10.0 0. 16.1 1.0 24.7 0. 0.064 45-6 0.89 0. 10.36 1.0 155.1 1.0 0.225 45-22 0.227 0.01517 8.222 0.855 135.87 8.0 0.33 46-47 1.264 0.025 15.54 2.50 17.93 13.86 0.41 46-48 0.856 0.025 17.86 5.19 27.24 15.80 0.65 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-28 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 5 TABLE 14.3.4-28 PRESSURIZER ENCLOSURE MODEL - TMD FLOW PATH INPUT 2
Flow Path K f LI (ft) DH (ft) AT (ft ) Leq (ft) AT /A 46-49 0.788 0.025 17.43 3.66 25.14 15.40 0.60 47-4 1.91 0.025 11.69 2.50 17.93 11.69 1.00 48-4 1.665 0.025 8.87 3.84 18.93 9.22 0.73 48-49 1.268 0.025 7.883 4.50 52.61 7.883 0.47 48-47 0.888 0.025 10.302 2.50 29.23 10.302 0.26 49-4 1.291 0.025 8.80 2.66 17.60 9.05 0.72 49-47 1.064 0.025 11.793 2.50 29.23 14.99 0.26 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-29 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 TABLE 14.3.4-29 FAN / ACCUMULATOR ROOM MODEL - TMD FLOW PATH INPUT Flow Path K f LI (ft) DH (ft) AT (ft2) LE (ft) AT /A 27R-29 1.61 0. 1.66 1.0 1.0 0. 0.003 27H-28 2.17 0. 0.36 1.0 13.2 0. 0.094 27-3A 2.02 0. 0.085 1.0 0.68 0. 0.002 54H-27 0.25 0. 11.77 1.0 108 0. 0.320 54R-28 1.75 0. 4.22 1.0 21.2 0. 0.068 54A-3 2.12 0. 7.89 1.0 17.3 0. 0.075 55H-54 0.21 0. 15.84 1.0 170 0. 0.578 55A-28 2.10 0. 2.0 1.0 34.3 0. 0.110 55R-26 2.09 0. 29.91 1.0 34.7 0. 0.111 55-2R 1.86 0. 14.07 1.0 90.9 0. 0.382 55-56H 0.21 0. 16.24 1.0 170 0. 0.578 56R-26 1.89 0. 4.30 1.0 24.7 0. 0.076 56A-1 1.72 0. 5.99 1.0 14.5 0. 0.060 56-57H 0.25 0. 14.26 1.0 108 0. 0.635 57R-26 2.06 0. 0.32 1.0 17.2 0. 0.105 57A-1 2.36 0. 1.27 1.0 29.6 0. 0.068 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-30 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 6 Table 14.3.4-30 Loop Subcompartment Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 1-2 0.63 0. 18.6 1.0 635.0 0. 0.601 1-33 1.5 0. 4.23 1.0 11.9 0. 0.016 1-27 2.85 0. 3.6 1.0 21.4 0. 0.129 2-3 0.72 0. 25.0 1.0 600.0 0. 0.601 2-27 2.85 0. 5.5 1.0 85.3 0. 0.252 3-4 0.28 0. 33.5 1.0 570. 0. 0.648 3-33 1.5 0. 4.33 1.0 32.4 0. 0.021 3-27 2.85 0. 3.6 1.0 21.3 0. 0.128 4-5 0.56 0. 19.1 1.0 600.0 0. 0.601 4-33 1.5 0. 4.42 1.0 24.5 0. 0.022 4-31 2.85 0. 3.6 1.0 21.3 0. 0.128 5-6 0.63 0. 18.6 1.0 635.0 0. 0.601 5-31 2.85 0. 5.5 1.0 85.3 0. 0.129 6-1 1.45 0. 29.2 1.0 58.5 0. 0.055 6-33 1.5 0. 4.23 1.0 11.9 0. 0.014 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-30 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 6 Table 14.3.4-30 Loop Subcompartment Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 6-31 2.85 0. 3.6 1.0 21.4 0. 0.129 7-8 0. 0.0276 12.278 0.855 112.8 16.0 0.727 8-9 0. 0.0276 12.278 0.855 112.8 16.0 0.727 9-34 0.812 0.0276 8.8558 0.855 112.8 8.0 0.727 10-11 0. 0.0276 12.278 0.855 131.31 16.0 0.727 11-12 0. 0.0276 12.278 0.855 131.31 16.0 0.727 12-35 0.812 0.0276 8.8558 0.855 131.31 8.0 0.727 13-14 0. 0.0276 12.278 0.855 266.63 16.0 0.727 14-15 0. 0.0276 12.278 0.855 266.63 16.0 0.727 15-36 0.812 0.0276 8.8558 0.855 266.63 8.0 0.727 16-17 0. 0.0276 12.278 0.855 184.59 16.0 0.727 17-18 0. 0.0276 12.278 0.855 184.59 16.0 0.727 18-37 0.812 0.0276 8.8558 0.855 184.59 8.0 0.727 19-20 0. 0.0276 12.278 0.855 143.57 16.0 0.727 20-21 0. 0.0276 12.278 0.855 143.57 16.0 0.727 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-30 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 6 Table 14.3.4-30 Loop Subcompartment Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 21-38 0.812 0.0276 8.8558 0.855 143.57 8.0 0.727 22-23 0. 0.0276 12.278 0.855 143.57 16.0 0.727 23-24 0. 0.0276 12.278 0.855 143.57 16.0 0.727 24-39 0.812 0.0276 8.8558 0.855 143.57 8.0 0.727 25-6 1.45 0. 6.08 1.0 2.2 0. .01 26-32 0.99 0. 64.5 1.0 17.0 0. 0.85 26-28 0.69 0. 45.8 1.0 25.0 0. 0.357 27-26 2.85 0. 8.0 1.0 55.0 0. 0.417 27-29 2.85 0. 2.7 1.0 2.5 0. 0.008 28-3 2.6 0. 13.2 1.0 35.7 0. 0.077 28-27 2.85 0. 8.0 1.0 43.0 0. 0.254 29-28 2.85 0. 2.0 1.0 0.25 0. 0.001 29-3 2.85 0. 3.0 1.0 0.25 0. 0.002 30-28 0.99 0. 46.6 1.0 20.0 0. 1.0 30-4 2.6 0. 13.2 1.0 35.7 0. 0.106 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-30 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 6 Table 14.3.4-30 Loop Subcompartment Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 31-30 2.85 0. 8.0 1.0 43.0 0. 0.254 31-29 2.85 0. 2.7 1.0 2.5 0. 0.007 32-30 0.69 0. 40.0 1.0 25.0 0. 0.417 32-31 2.85 0. 8.0 1.0 55.0 0. 0.331 33-2 1.5 0. 4.69 1.0 23.8 0. 0.034 33-5 1.5 0. 4.65 1.0 23.8 0. 0.034 34-25 1.45 0. 2.8 1.0 233.8 0. 0.659 35-25 1.43 0. 2.8 1.0 267.6 0. 0.65 36-25 1.43 0. 2.8 1.0 539.5 0. 0.625 37-25 1.41 0. 3.2 1.0 376.5 0. 0.636 38-25 1.44 0. 2.8 1.0 289.4 0. 0.646 39-25 1.43 0. 2.8 1.0 296.3 0. 0.646 40-1 0.89 0. 10.36 1.0 121.9 1.0 0.225 40-7 0.227 0.01517 8.222 0.855 106.7 8.0 0.33 40-41 7.5 0. 13.8 1.0 24.7 0. 0.075 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-30 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 6 Table 14.3.4-30 Loop Subcompartment Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 41-2 0.89 0. 10.36 1.0 144.0 1.0 0.225 41-10 0.227 0.01517 8.222 0.855 126.1 8.0 0.33 41-42 12.5 0. 22.4 1.0 24.7 0. 0.046 42-3 0.89 0. 10.36 1.0 288.0 1.0 0.225 42-13 0.227 0.01517 8.222 0.855 252.2 8.0 0.33 42-43 12.5 0. 25.3 1.0 24.7 0. 0.041 43-4 0.89 0. 10.36 1.0 199.4 1.0 0.225 43-16 0.227 0.01517 8.222 0.855 174.6 8.0 0.33 43-44 10.0 0. 18.4 1.0 24.7 0. 0.056 44-5 0.89 0. 10.36 1.0 155.1 1.0 0.225 44-19 0.227 0.01517 8.222 0.855 135.8 8.0 0.33 44-45 10.0 0. 16.1 1.0 24.7 0. 0.064 45-6 0.89 0. 10.36 1.0 155.1 1.0 0.225 45-22 0.227 0.01517 8.222 0.855 135.87 8.0 0.33 46-1 2.09 0. 10.0 1.0 123.31 1.0 0.001 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-30 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 6 Table 14.3.4-30 Loop Subcompartment Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 46-2 2.21 0. 11.5 1.0 104.12 1.0 0.001 47-2 2.21 0. 11.5 1.0 104.12 1.0 0.001 47-3 2.09 0. 10.0 1.0 123.31 1.0 0.001 48-5 2.21 0. 11.5 1.0 104.12 1.0 0.001 48-4 2.09 0. 10.0 1.0 123.31 1.0 0.001 49-6 2.09 0. 10.0 1.0 123.31 1.0 0.001 49-5 2.21 0. 11.5 1.0 104.12 1.0 0.001 50-46 2.93 0. 17.6 1.0 121.43 1.0 0.001 50-51 0.874 0. 8.43 1.0 44.89 1.0 0.282 51-47 2.93 0. 17.6 1.0 121.43 1.0 0.001 52-48 2.93 0. 17.6 1.0 121.43 1.0 0.001 53-49 2.93 0. 17.6 1.0 121.43 1.0 0.001 53-52 0.874 0. 8.43 1.0 44.89 1.0 0.282 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-31 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 6 Table 14.3.4-31 Reactor Cavity Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 1H-3 1.312 0.021 1.895 1.338 12.570 1.130 0.463 1R-53 0.386 0.021 2.200 1.420 9.290 1.290 0.293 1A-46 0.419 0.021 7.080 1.125 5.780 6.690 0.211 2H-60 0.230 0.021 20.202 13.953 199.980 17.524 0.645 2R-32 0.969 0.021 14.211 1.082 3.488 14.071 1.000 2A-8 0.984 0.021 12.638 1.082 1.783 12.567 1.000 3H-6 0.412 0.021 2.008 0.759 1.081 0.590 0.721 3R-7 0.287 0.021 1.752 0.902 1.357 1.032 0.522 3A-11 0.403 0.021 2.026 0.759 1.081 0.617 0.738 4H-9 0.000 0.021 3.627 0.459 0.043 3.627 1.000 4R-38 0.996 0.021 0.122 0.467 0.842 0.094 1.000 4A-5 0.363 0.021 0.431 0.467 0.842 0.134 0.349 5H-10 0.000 0.021 3.539 1.349 1.305 3.539 1.000 5R-34 0.000 0.021 3.578 1.349 1.305 3.578 1.000 5A-6 0.144 0.021 1.727 0.904 1.498 1.376 1.000 6H-11 0.000 0.021 3.285 0.902 1.016 3.285 1.000 6R-35 0.499 0.021 2.661 0.902 1.016 2.361 1.000 6A-61 0.755 0.021 1.033 0.805 0.197 0.088 1.000 7H-61 0.000 0.021 2.879 0.819 0.2000 2.879 1.000 7R-36 0.411 0.021 0.942 0.681 0.314 0.702 0.231 7A-8 0.788 0.021 2.915 0.426 0.200 1.577 1.000 8H-3 0.489 0.021 8.814 0.759 1.081 3.803 0.606 8R-13 0.000 0.021 3.268 1.079 13.563 3.268 1.000 8A-37 0.000 0.021 3.304 1.079 13.563 3.304 1.000 9H-14 0.000 0.021 3.587 0.459 0.043 3.587 1.000 9R-38 0.996 0.021 0.122 0.467 0.823 0.094 1.000 9A-10 0.366 0.021 0.423 0.467 0.823 0.132 0.341 10H-15 0.000 0.021 3.500 1.349 1.305 3.500 1.000 Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-31 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 6 Table 14.3.4-31 Reactor Cavity Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 10R-11 0.144 0.021 1.727 0.904 1.466 1.376 1.000 11H-16 0.444 0.021 2.513 0.902 1.016 2.169 1.000 11R-62 0.789 0.021 1.056 0.671 0.164 0.049 1.000 12H-17 0.382 0.021 0.897 0.722 0.408 0.580 0.300 12R-3 0.287 0.021 1.752 0.902 1.357 1.032 0.522 12A-13 0.817 0.021 2.711 0.353 0.168 1.548 1.000 13H-18 0.000 0.021 3.232 1.079 13.563 3.232 1.000 13R-2 0.985 0.021 12.637 1.082 1.744 12.567 1.000 13A-3 0.479 0.021 8.983 0.759 1.081 3.984 0.620 14H-19 0.937 0.021 1.902 0.459 0.043 1.795 1.000 14R-38 0.996 0.021 0.122 0.467 0.823 0.094 1.000 14A-15 0.366 0.021 0.423 0.467 0.823 0.132 0.341 15H-19 0.001 0.021 5.057 1.349 1.305 5.150 1.000 15R-16 0.144 0.021 3.102 0.904 1.466 2.751 1.000 16H-39 0.971 0.021 0.506 1.901 4.232 0.070 0.320 16R-20 0.177 0.021 4.552 0.837 1.307 4.393 0.579 16A-17 0.361 0.021 3.748 0.647 0.515 3.648 0.351 17H-21 0.943 0.021 1.715 0.722 0.408 1.626 1.000 17R-39 0.698 0.021 0.591 2.150 4.943 0.109 0.785 17A-18 0.424 0.021 4.625 0.647 0.515 1.455 1.000 18H-21 0.097 0.021 4.634 1.079 13.563 4.530 0.909 18R-2 0.985 0.021 12.637 1.082 1.744 12.567 1.000 19H-22 0.262 0.021 4.919 1.271 1.348 4.304 1.000 19R-38 1.356 0.021 0.547 0.467 1.610 0.224 1.000 19A-20 0.144 0.021 3.160 0.904 2.866 2.775 1.000 20H-22 0.667 0.021 4.177 0.655 1.307 2.793 0.363 20R-40 0.934 0.021 0.557 1.901 4.232 0.116 0.166 20A-21 0.852 0.021 7.973 0.433 1.018 4.682 0.299 Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-31 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 6 Table 14.3.4-31 Reactor Cavity Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 21H-23 0.067 0.021 6.285 1.064 13.971 6.160 0.936 21R-40 1.042 0.021 0.484 1.599 3.677 0.073 0.021 21A-2 0.970 0.021 14.208 1.082 3.411 14.071 1.000 22H-24 0.281 0.021 6.008 1.017 2.562 5.613 0.711 22R-23 0.879 0.021 8.429 0.428 0.992 5.084 0.284 22A-38 1.401 0.021 1.727 0.467 1.647 0.503 1.000 23H-25 0.073 0.021 6.435 1.045 13.877 6.314 0.930 23R-41 1.033 0.021 0.969 1.810 4.330 0.151 0.025 23A-2 0.969 0.021 14.211 1.082 3.488 14.071 1.000 24H-26 0.281 0.021 6.008 1.017 2.562 5.613 0.711 24R-38 1.401 0.021 1.728 0.467 1.683 0.503 1.000 24A-25 0.905 0.021 8.247 0.404 0.966 5.018 0.271 25H-27 0.073 0.021 6.435 1.045 13.877 6.314 0.930 25R-42 1.044 0.021 0.850 1.392 3.330 0.112 0.019 25A-2 0.969 0.021 14.214 1.082 3.566 14.071 1.000 26H-28 0.253 0.021 5.843 1.012 2.656 5.413 0.737 26R-38 1.401 0.021 1.727 0.467 1.647 0.503 1.000 26A-27 0.879 0.021 8.429 0.428 0.992 5.084 0.284 27H-29 0.067 0.021 6.285 1.064 13.971 6.160 0.936 27R-43 1.030 0.021 1.115 2.150 4.943 0.175 0.028 27A-2 0.969 0.021 14.211 1.082 3.488 14.071 1.000 28H-30 0.260 0.021 4.969 1.271 1.348 4.369 1.000 28R-38 1.401 0.021 1.726 0.467 1.610 0.503 1.000 28A-29 0.852 0.021 8.350 0.433 1.018 4.746 0.299 29H-32 0.067 0.021 6.421 1.044 13.971 6.284 0.936 29R-43 1.029 0.021 1.115 2.150 4.943 0.175 0.029 29A-2 0.970 0.021 14.208 1.082 3.411 14.071 1.000 30H-33 0.937 0.021 1.945 0.459 0.043 1.835 1.000 Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-31 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 6 Table 14.3.4-31 Reactor Cavity Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 30R-38 1.355 0.021 0.548 0.467 1.647 0.224 1.000 30A-31 0.144 0.021 3.160 0.904 2.931 2.775 1.000 31H-35 0.214 0.021 4.778 0.832 1.213 4.701 0.538 31R-45 1.049 0.021 0.489 1.551 3.613 0.063 0.150 31A-28 0.667 0.021 4.192 0.655 1.307 2.805 0.363 32H-36 0.955 0.021 1.733 0.681 0.314 1.662 1.000 32R-31 0.879 0.021 8.070 0.428 0.992 5.027 0.284 32A-44 1.042 0.021 0.484 1.599 3.677 0.073 0.021 33H-4 0.000 0.021 3.667 0.459 0.043 3.667 1.000 33R-38 0.996 0.021 0.122 0.467 0.842 0.094 1.000 33A-34 0.363 0.021 0.431 0.467 0.842 0.134 0.349 34H-30 0.001 0.021 5.171 1.349 1.305 5.266 1.000 34R-35 0.144 0.021 3.102 0.904 1.498 2.751 1.000 35H-45 0.996 0.021 0.489 1.551 3.613 0.063 0.281 35R-36 0.373 0.021 4.946 0.635 0.483 4.700 0.322 36H-45 0.720 0.021 0.586 1.810 4.330 0.105 0.748 36R-37 0.462 0.021 4.435 0.635 0.483 1.495 1.000 37H-32 0.096 0.021 4.764 1.079 13.563 4.678 0.909 37R-2 0.984 0.021 12.638 1.082 1.783 12.567 1.000 38H-43 0.957 0.021 3.670 1.590 9.820 2.050 0.021 38R-42 0.957 0.021 3.670 1.590 9.820 2.050 0.021 38A-41 0.957 0.021 3.670 1.590 9.820 2.050 0.021 39H-20 1.033 0.021 0.506 1.901 4.232 0.070 0.166 39R-54 0.473 0.021 2.450 1.590 9.820 1.380 0.314 39A-21 1.029 0.021 0.591 2.150 4.943 0.109 0.029 40H-22 0.951 0.021 0.557 1.901 4.232 0.116 0.123 40R-55 0.473 0.021 2.450 1.590 9.820 1.380 0.314 40A-23 1.042 0.021 0.484 1.599 3.677 0.073 0.021 Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-31 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 6 Table 14.3.4-31 Reactor Cavity Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 41H-24 1.071 0.021 0.856 1.551 3.613 0.091 0.093 41R-25 1.033 0.021 1.025 1.810 4.330 0.153 0.024 41A-22 1.066 0.021 0.856 1.551 3.613 0.091 0.105 42H-26 0.982 0.021 0.922 1.551 3.613 0.147 0.105 42R-27 1.044 0.021 0.850 1.392 3.330 0.112 0.019 42A-24 0.987 0.021 0.922 1.551 3.613 0.147 0.093 43H-28 1.055 0.021 0.954 1.901 4.232 0.114 0.110 43R-52 1.407 0.021 4.500 1.095 5.938 4.500 0.0001 43A-26 1.050 0.021 0.954 1.901 4.232 0.114 0.123 44H-29 1.042 0.021 0.484 1.599 3.677 0.073 0.021 44R-31 0.930 0.021 0.557 1.901 4.232 0.116 0.176 44A-28 0.956 0.021 0.557 1.901 4.232 0.116 0.110 45H-50 0.422 0.021 6.120 1.060 5.490 5.590 0.202 45R-57 0.394 0.021 2.200 1.420 9.290 1.290 0.293 45A-32 1.033 0.021 0.586 1.810 4.330 0.105 0.025 46H-51 0.995 0.021 6.505 1.125 5.780 6.505 1.000 47H-51 0.995 0.021 2.250 1.095 5.938 2.250 1.000 47R-39 0.412 0.021 2.280 1.095 5.940 2.300 0.228 48H-51 0.995 0.021 2.250 1.095 5.938 2.250 1.000 48R-40 0.412 0.021 2.280 1.095 5.940 2.300 0.228 49H-44 0.412 0.021 2.280 1.095 5.940 2.300 0.228 49R-52 0.995 0.021 2.250 1.095 5.938 2.250 1.000 50H-51 0.995 0.021 5.560 1.058 5.493 5.560 1.000 51H-38 1.400 0.021 4.500 5.011 80.4 4.500 0.059 51R-52 0.280 0.021 33.500 1.000 570.000 0.000 0.648 51A-58 0.854 0.021 9.183 9.509 126.000 7.282 1.000 52H-42 1.417 0.021 5.860 1.058 5.493 5.860 0.0001 52R-38 1.400 0.021 4.500 5.011 80.4 4.500 0.059 Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-31 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 6 Table 14.3.4-31 Reactor Cavity Model - TMD Flow Path Input Flow Path K f LI (ft) DH (ft) AT (ft2) Leq (ft) AT /A 52A-41 1.417 0.021 5.860 1.058 5.493 5.860 0.0001 53H-38 0.958 0.021 2.236 2.400 9.710 2.086 1.000 54H-38 0.956 0.021 1.275 2.780 10.240 1.275 1.000 55H-38 0.956 0.021 1.275 2.780 10.240 1.275 1.000 56H-44 0.473 0.021 2.450 1.590 9.820 1.380 0.314 56R-38 0.956 0.021 1.275 2.780 10.240 1.275 1.000 57H-38 0.958 0.021 2.240 2.400 9.710 2.086 1.000 58H-60 0.374 0.021 9.918 9.509 126.000 7.675 0.321 59H-52 2.819 0.000 50.625 1.000 465.65 50.625 0.001 59R-51 2.819 0.000 50.625 1.000 465.65 50.625 0.001 60H-0 0.000 0.000 0.000 1.000 1.000 0.000 0.000 60R-0 0.000 0.000 0.000 1.000 1.000 0.000 0.000 60A-0 0.000 0.000 0.000 1.000 1.000 0.000 0.000 61H-3 0.307 0.021 1.623 0.902 1.240 0.903 0.478 61R-35 0.474 0.021 1.434 0.832 1.213 1.137 1.000 62H-3 0.307 0.021 1.623 0.902 1.240 0.903 0.478 62R-12 0.000 0.021 2.879 0.685 0.168 2.879 1.000 62A-16 0.438 0.021 1.329 0.902 1.240 1.056 1.000 Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-32 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT Compartment Volume and Area1 Free Volume Vent Area Compartment (ft3) (ft2)
Upper Reactor Cavity 15,720 165 Lower Reactor Cavity 14,769 172 Steam Generator Enclosure A 10,905 412 Enclosure B 10,107 330 Pressurizer 2,,639 54 Fan Accumulator Room 26,969 299 1
The volumes listed are those that were utilized for the respective subcompartment analysis.
Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-33 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PEAK DIFFERENTIAL PRESSURE (PSI)
STEAM LINE BREAK AT OUTLET NOZZLE (BOUNDING)1 Limiting Containment Conditions Across Structures: DP55-25=42.7691 PSI @ 1.210 SEC THigh/PLow DP56-25=31.1990 PSI @ 1.297 SEC THigh/PLow DP57-25=31.1953 PSI @ 1.296 SEC THigh/PLow DP58-25=31.5021 PSI @ 1.291 SEC THigh/PLow DP59-25=31.5003 PSI @ 1.292 SEC THigh/PLow DP60-25=19.3257 PSI @ 1.344 SEC THigh/PLow DP61-25=19.1868 PSI @ 1.346 SEC THigh/PLow DP62-25=19.1902 PSI @ 1.342 SEC THigh/PLow DP63-25=19.3621 PSI @ 1.340 SEC THigh/PLow DP55-46=25.7593 PSI @ .017 SEC TLow/PLow DP56-47=13.7783 PSI @ .022 SEC TLow/PLow DP57-48=12.1139 PSI @ .034 SEC TLow/PLow DP60-51=11.0594 PSI @ .038 SEC TLow/PLow DP61-52=10.0894 PSI @ .041 SEC TLow/PLow Across Steam DP56-58=-2.8489 PSI @ .024 SEC TLow/PLow Generator Vessel:
DP57-59=-3.9901 PSI @ .023 SEC TLow/PLow Node 46 Break DP60-62=2.6747 PSI @ .041 SEC TLow/PLow DP61-63=-1.9412 PSI @ .030 SEC TLow/PLow Node 46 Break 1
All breaks are in Node 55 unless otherwise noted.
Unit 2 UNIT 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-34 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PEAK DIFFERENTIAL PRESSURE (PSI)
FEEDWATER LINE BREAK AT SIDE (BOUNDING)1 Limiting Containment Conditions Across Structures: DP55-25=5.3159 PSI @ .220 SEC TLow/PLow/ICELow DP56-25=5.3788 PSI @ .217 SEC TLow/PLow/ICELow DP57-25=5.3801 PSI @ .219 SEC TLow/PLow/ICELow DP58-25=5.8566 PSI @ .222 SEC TLow/PLow/ICELow DP59-25=6.0058 PSI @ .161 SEC TLow/PLow/ICEHigh DP60-25=5.6043 PSI @ .214 SEC TLow/PLow/ICELow DP61-25=5.5785 PSI @ .212 SEC TLow/PLow/ICELow DP62-25=6.8782 PSI @ .022 SEC TLow/PLow/ICEHigh DP63-25=16.2857 PSI @ .012 SEC TLow/PLow/ICEHigh DP55-46=3.2606 PSI @ .045 SEC TLow/PLow/ICEHigh DP56-47=3.3787 PSI @ .030 SEC TLow/PLow/ICELow Node 54 Break DP57-48=2.9672 PSI @ .039 SEC TLow/PLow/ICEHigh DP60-51=5.2378 PSI @ .021 SEC TLow/PLow/ICELow Node 54 Break DP61-52=5.0053 PSI @ .027 SEC TLow/PLow/ICEHigh Across Steam DP56-58=-1.4657 PSI @ .023 SEC THigh/PLow/ICEHigh Generator Vessel:
DP57-59=-3.9920 PSI @ .015 SEC TLow/PLow/ICEHigh DP60-62=-2.2928 PSI @ .027 SEC TLow/PLow/ICEHigh DP61-63=-15.5871 PSI @ .011 SEC TLow/PLow/ICEHigh 1
All breaks are in Node 63 unless otherwise noted.
Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-35 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 ICE CONDENSER AZIMUTHAL DIFFERENTIAL PRESSURE DISTRIBUTION TMD BREAK LOCATION ELEMENTS 1 2 3 4 5 6 Ice Bays 1 Bays 2.75 Bays 7 thru Bays 12.5 Bays 18 thru Bays 20.5 thru 24 Condenser thru 2.75 thru 6 12.5 thru 17 20.5 Elements 9 12 15 18 21 24 Pressure 7.4 psid 6.1 psid 5.5 psid 5.5 psid 6.1 psid 7.4 psid Elements 8 11 14 17 20 23 Pressure 9.2 psid 7.6 psid 6.8 psid 6.8 psid 7.5 psid 9.2 psid Elements 7 10 13 16 19 22 Pressure 11.8 psid 9.8 psid 8.7 psid 8.7 psid 9.7 psid 11.8 psid Elements 40 41 42 43 44 45 Pressure 14.8 psid 12.6 psid 11.2 psid 11.2 psid 12.4 psid 14.5 psid Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-36 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 SENSITIVITY STUDIES FOR COOK NUCLEAR PLANT Change Made Change In Change In Parameter From Base Operating Peak Pressure Value Deck Dp Against The Shell Blowdown +10% +11% +12%
Blowdown -10% -10% -12%
Blowdown -20% -20% -23%
Blowdown -50% -50% -53%
Break Compartment
+10% +4% +1%
Inertial Length Break Compartment
-10% -4% -1%
Inertial Length Break Compartment
+10% -2% -1%
Volume Break Compartment
-10% +2% +1%
Volume Break Compartment
+10% -6% -5%
Vent Areas Break Compartment
-10% +8% +5%
Vent Areas Door Port Failure in one door port fails to open +1% -1%
Break Compartment Ice Mass +10% 0 0 Ice Mass -10% 0 0 Door Inertia +10% +1% 0 Door Inertia -10% -1% 0 All Inertial Lengths +10% +5% +4%
All Inertial Lengths -10% -5% -3%
Ice Bed Loss
+10% 0 0 Coefficients Ice Bed Loss
- 10% 0 0 Coefficients Entrainment Level 0% Ent -27% -11%
Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-36 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 SENSITIVITY STUDIES FOR COOK NUCLEAR PLANT Change Made Change In Change In Parameter From Base Operating Peak Pressure Value Deck Dp Against The Shell Entrainment Level 30% Ent. -19% -15%
Entrainment Level 50% Ent. -13% -12%
Entrainment Level 75% Ent. -6% -6%
Lower Compartment
+10% 0 0 Loss Coefficients Lower Compartment
-10% 0 0 Loss Coefficients Cross Flow in Lower Low estimate of 0 -7%
Plenum resistance Cross Flow in Lower High estimate of 0 -3%
Plenum resistance Ice Condenser Flow
+10% 0 -3%
Area Ice Condenser Flow
-10% 0 +4%
Area Ice Condenser +20% 0 -6%
Ice Condenser Flow
-50% 0 +8%
Area Initial Pressure in
+0.3 psi +2% +2%
Containment Initial Pressure in
-0.3 psi -2% -2%
Containment Reactor Coolant Break
-13.0% +6% +3%
Enthalpy Addition of the Compressibility Factor +4% 0 compressibility factor All values shown are to the nearest percent.
Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-37 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 1973 WALTZ MILL PRELIMINARY TEST CONDITIONS Nominal Conditions G
Test test/ (Total Energy/Ice Wt.) test/ Subcooling Varied in G
Series plant (Total Energy/Ice Wt.) plant In Piping Test Setup 37%
75%
Blowdown 100% Variable Orifice rate 100% 40oF 150% Sizes Series 10%
1.5%
Variable Blowdown 75% 150%
o Boiler Energy 100% 150% ~40 F Water Series 100% 200%
levels Blowdown 75% ~10oF Variable Conditions In Transient 75% 100% ~25oF Subcooled Leg Shape 100% ~10oF Series 100% ~25oF Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-38 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PEAK PRESSURES / DIFFERENTIALS DEHL Break DECL Break In Element #6 In Element #6 Pressure In Element #6 (Psig) 14.8 / 14.4 13.4 / 13.0 Peak Pressure In Ice 10.6 / 10.6 9.8 / 9.9 Condenser Compartments (Psig)
Peak Differential Pressure Across Operating Deck or 14.5 / 14.1 12.3 / 11.7 Lower Crane Wall (Psi)
Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-39 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 EFFECTS OF VARYING POLYTROPIC EXPONENT 5% 10% 20%
Base Case Decrease Decrease Decrease Pressure In Element #6 (Psig) 14.8 14.8 14.8 14.9 Peak Pressure In Ice Condenser 10.6 10.6 10.6 10.6 Compartment (Psig)
Peak Differential Pressure Across 14.5 14.5 14.5 14.6 Operating Deck or Lower Crane Wall (Psi)
Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-40 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 CALCULATED MAXIMUM PEAK PRESSURES COMPARED WITH DESIGN PRESSURE (HISTORICAL INFORMATION)
Type of Peak Pressure Peak Differential Pressure2 Location1 Design Break Augmented Unaugmented Augmented Unaugmented DECL Element 1 13.7 14.1 10.8 12.7 16.6 DECL Element 2 10.8 12.23 8.6 3 10.5 3 12.0 DECL Element 3 9.8 11.2 3 7.5 3 9.4 3 12.0 DECL Element 4 9.7 11.1 3 7.6 3 9.5 3 12.0 DECL Element 5 10.5 11.9 3 8.6 3 10.5 3 12.0 DECL Element 6 11.6 13.0 3 10.4 3 12.3 3 16.6 DEHL Element 1 13.3 13.7 3 13.0 3 13.5 3 16.6 DEHL Element 2 10.6 11.0 3 10.3 3 10.8 3 12.0 DEHL Element 3 8.9 9.3 3 8.3 3 8.8 3 12.0 DEHL Element 4 9.0 9.4 3 8.0 3 8.5 3 12.0 DEHL Element 5 10.5 10.9 3 10.2 3 10.7 3 12.0 DEHL Element 6 13.6 14.0 13.2 13.7 16.6 DECL Element 40 9.8 10.6 9.8 10.6 12.0 DECL Element 41 8.7 9.5 3 8.7 9.5 12.0 DECL Element 42 7.8 8.6 3 7.8 8.6 12.0 DECL Element 43 7.8 8.6 3 7.8 8.6 12.0 DECL Element 44 8.5 9.3 3 8.5 9.3 12.0 1
Element 1-6 are break locations 2
For Elements 1 through 6 the peak differential pressure is across the operating deck or the lower crane wall. For Elements 7 through 24 the peak differential pressure is across the upper crane wall. For Elements 40 through 45 the peak differential pressure is across the containment shell.
3 The unaugmented peak pressure and peak differential pressure other than Elements 1/40 (DECL) and 6/45 (DEHL) are conservatively estimated by taking the P (unaug-aug) and adding it to the augmented pressure. Elements 2 through 6 and 41 through 45 for DECL and 1 through 5 and 40 through 44 for DEHL reflect this change. In Elements 7 through 24 the P (unaug-aug) for peak pressure was used to estimate the unaugmented peak differential pressure.
Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-40 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 CALCULATED MAXIMUM PEAK PRESSURES COMPARED WITH DESIGN PRESSURE (HISTORICAL INFORMATION)
Type of Peak Pressure Peak Differential Pressure2 Location1 Design Break Augmented Unaugmented Augmented Unaugmented DECL Element 45 9.5 10.3 3 9.5 10.3 12.0 DEHL Element 40 10.7 10.8 3 10.7 10.8 12.0 DEHL Element 41 8.3 8.4 3 8.3 8.4 12.0 DEHL Element 42 7.0 8.1 3 7.0 8.1 12.0 DEHL Element 43 7.1 7.2 3 7.1 7.2 12.0 DEHL Element 44 8.4 8.5 3 8.4 8.5 12.0 DEHL Element 45 10.7 10.8 10.7 10.8 12.0 Elements DECL 6.1 6.1 6.6 3 6.6 3 12.0 7-8-9 Elements DECL 5.9 6.1 5.9 6.1 3 12.0 10-11-12 Elements DECL 5.6 6.0 5.2 5.6 3 12.0 13-14-15 Elements DECL 6.0 6.2 5.4 5.6 3 12.0 16-17-18 Elements DECL 6.7 6.7 6.0 6.0 3 12.0 19-20-21 Elements DECL 6.0 6.1 6.6 6.7 3 12.0 22-23-24 Elements DEHL 7.1 7.2 7.8 7.9 3 12.0 7-8-9 Elements DEHL 7.6 7.6 6.8 6.8 3 12.0 10-11-12 Elements DEHL 6.4 6.8 6.0 6.4 3 12.0 13-14-15 Elements DEHL 6.0 6.5 6.1 6.6 3 12.0 16-17-18 DEHL 19-20-21 6.8 6.8 6.9 6.9 3 12.0 DEHL 22-23-24 7.1 7.5 7.6 8.0 3 12.0 STEAMLINE S.G. Doghouse 20.8 20.8 20.5 20.5 26.4 STEAMLINE Fan Room 13.9 13.9 13.9 13.9 16.0 Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-40 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 CALCULATED MAXIMUM PEAK PRESSURES COMPARED WITH DESIGN PRESSURE (HISTORICAL INFORMATION)
Type of Peak Pressure Peak Differential Pressure2 Location1 Design Break Augmented Unaugmented Augmented Unaugmented Lower Rx SECL 12.2 13.8 11.4 12.3 15.0 Cavity Upper Rx SECL 40.4 47.0 36.9 44.1 48.0 Cavity Pressurizer 6" Spray Line 14.0 17.8 13.1 16.4 80.0 Enclosure Reactor Vessel LOCA 63.0 95.0 63.0 95.0 1000.0 Annulus Reactor Pipe LOCA 419.0 735.0 419.0 735.0 2000.0 Annulus Unit 2 Unit 1 Unit 2 Added to Unit 2 by UCR-2138, Rev. 0 l
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-41 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 Tab le 1 4 .3 .4 - 4 1 (U2 ) - DECL Minimum Safeguards B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 0.00 0.00 0.00 0.00 0.00 1.00 69,324.41 38,046,066.83 25,604.42 13,924,974.79 2.00 58,625.69 32,585,399.61 23,872.88 13,300,981.72 3.00 43,953.38 24,985,488.13 18,192.76 10,558,606.92 4.00 35,778.97 20,653,136.67 13,815.32 7,888,864.62 5.00 31,097.02 18,152,077.40 10,861.52 6,476,386.63 6.00 28,528.60 16,786,336.34 9,703.72 5,882,279.60 7.00 24,952.00 15,259,323.37 9,255.70 5,612,730.10 8.00 20,604.75 13,468,955.05 8,717.87 5,310,922.65 9.00 16,699.54 11,703,351.34 7,816.20 4,840,034.12 10.00 13,679.78 10,305,339.93 6,973.83 4,372,920.81 11.00 11,506.04 9,198,144.32 6,215.06 3,908,456.76 12.00 9,819.95 8,229,132.22 5,513.67 3,437,842.17 13.00 8,698.90 6,994,089.17 4,682.16 2,783,916.19 14.00 9,013.70 5,845,848.15 3,898.85 2,220,327.75 15.00 8,581.58 4,812,359.26 3,125.03 1,632,595.84 16.00 8,130.97 3,912,545.06 1,711.39 702,389.35 17.00 7,949.05 3,344,345.65 1,262.82 234,020.67 18.00 7,581.36 2,835,603.04 1,454.41 211,081.81 19.00 7,491.60 2,423,955.34 1,581.81 195,049.93 20.00 6,265.09 1,798,694.46 1,694.77 202,941.86 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-41 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 Tab le 1 4 .3 .4 - 4 1 (U2 ) - DECL Minimum Safeguards B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 21.00 5,926.23 1,456,776.38 1,783.47 216,266.04 22.00 5,603.63 1,220,355.04 1,810.69 220,164.07 23.00 5,589.36 1,064,941.06 2,031.48 266,994.55 24.00 5,758.15 985,245.44 1,775.59 230,283.74 25.00 4,684.52 743,432.80 1,919.02 235,497.51 26.00 2,230.43 363,444.17 1,592.20 172,466.25 27.00 2,498.47 359,261.62 1,590.49 146,728.09 28.00 37.31 6,477.01 1,612.44 128,216.33 29.00 37.31 6,477.01 1,329.69 99,486.91 30.00 37.31 6,477.01 1,414.50 102,275.58 31.00 37.31 6,477.01 2,048.86 148,748.81 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 30.90 0.00 0.00 0.00 0.00 31.00 37.31 6,477.00 1,570.12 123,750.70 31.90 37.31 6,477.00 1,570.12 123,750.70 32.00 37.31 6,477.00 1,505.73 121,482.70 32.90 37.31 6,477.00 1,505.73 121,482.70 33.00 37.31 6,477.00 1,505.91 118,795.40 33.90 37.31 6,477.00 1,505.91 118,795.40 34.00 2,053.52 403,268.50 711.78 174,169.60 53.90 2,053.52 403,268.50 711.78 174,169.60 54.00 226.44 149,978.90 186.94 67,790.90 73.90 226.44 149,978.90 186.94 67,790.90 74.00 70.82 56,316.40 174.93 53,965.60 93.90 70.82 56,316.40 174.93 53,965.60 94.00 142.15 93,861.50 183.26 59,139.20 113.90 142.15 93,861.50 183.26 59,139.20 114.00 264.99 133,941.10 198.97 68,564.80 133.90 264.99 133,941.10 198.97 68,564.80 134.00 504.71 185,713.30 209.65 77,838.00 153.90 504.71 185,713.30 209.65 77,838.00 154.00 721.28 221,521.60 196.68 75,330.60 173.90 721.28 221,521.60 196.68 75,330.60 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 174.00 598.87 187,240.20 198.51 68,659.10 193.90 598.87 187,240.20 198.51 68,659.10 194.00 452.54 151,643.70 195.37 63,673.30 213.90 452.54 151,643.70 195.37 63,673.30 214.00 388.28 132,983.20 193.27 60,220.70 233.90 388.28 132,983.20 193.27 60,220.70 234.00 342.34 126,452.80 196.76 63,124.60 433.90 342.34 126,452.80 196.76 63,124.60 434.00 397.67 149,608.80 203.37 71,255.10 633.90 397.67 149,608.80 203.37 71,255.10 634.00 407.13 154,358.20 205.48 73,978.10 833.90 407.13 154,358.20 205.48 73,978.10 834.00 398.29 155,105.60 215.61 80,216.10 1,033.90 398.29 155,105.60 215.61 80,216.10 1,034.00 372.93 156,797.20 239.80 97,244.50 1,233.90 372.93 156,797.20 239.80 97,244.50 1,234.00 368.03 164,336.10 256.48 107,947.30 1,433.90 368.03 164,336.10 256.48 107,947.30 1,434.00 296.60 149,678.90 324.98 124,829.60 1,633.90 296.60 149,678.90 324.98 124,829.60 1,634.00 101.73 88,253.60 322.13 110,404.00 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 1,833.90 101.73 88,253.60 322.13 110,404.00 1,834.00 62.62 62,987.70 98.93 53,973.90 2,033.90 62.62 62,987.70 98.93 53,973.90 2,034.00 56.72 51,650.30 291.13 90,744.10 2,233.90 56.72 51,650.30 291.13 90,744.10 2,234.00 48.59 44,833.40 392.80 115,795.10 2,433.90 48.59 44,833.40 392.80 115,795.10 2,434.00 32.75 32,475.70 401.76 112,649.40 2,633.90 32.75 32,475.70 401.76 112,649.40 2,634.00 25.14 22,598.30 396.48 103,254.60 2,833.90 25.14 22,598.30 396.48 103,254.60 2,834.00 36.35 23,574.70 408.65 106,412.10 3,033.90 36.35 23,574.70 408.65 106,412.10 3,034.00 41.73 20,167.10 399.94 97,820.50 3,233.90 41.73 20,167.10 399.94 97,820.50 3,234.00 10.83 11,547.30 382.98 95,454.10 3,433.90 10.83 11,547.30 382.98 95,454.10 3,434.00 43.29 15,762.60 409.16 95,211.10 3,633.90 43.29 15,762.60 409.16 95,211.10 3,634.00 67.71 18,434.80 403.23 92,426.20 3,833.90 67.71 18,434.80 403.23 92,426.20 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 3,834.00 221.83 53,491.90 293.30 62,115.40 4,033.90 221.83 53,491.90 293.30 62,115.40 4,034.00 303.47 81,818.00 69.08 7,930.90 4,233.90 303.47 81,818.00 69.08 7,930.90 4,234.00 120.19 59,411.90 36.56 4,933.70 4,433.90 120.19 59,411.90 36.56 4,933.70 4,434.00 95.34 55,403.20 34.06 4,698.70 4,633.90 95.34 55,403.20 34.06 4,698.70 4,634.00 91.96 55,617.70 32.52 4,439.10 4,833.90 91.96 55,617.70 32.52 4,439.10 4,834.00 94.18 56,229.50 32.09 4,363.50 5,033.90 94.18 56,229.50 32.09 4,363.50 5,034.00 94.96 56,353.80 32.68 4,361.70 5,233.90 94.96 56,353.80 32.68 4,361.70 5,234.00 91.44 55,324.70 33.62 4,448.00 5,433.90 91.44 55,324.70 33.62 4,448.00 5,434.00 89.52 54,376.60 32.21 4,198.40 5,633.90 89.52 54,376.60 32.21 4,198.40 5,634.00 94.45 54,613.80 32.90 4,285.40 5,833.90 94.45 54,613.80 32.90 4,285.40 5,834.00 95.51 54,028.30 33.07 4,290.10 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 6,033.90 95.51 54,028.30 33.07 4,290.10 6,034.00 90.50 52,677.20 34.89 4,490.60 6,233.90 90.50 52,677.20 34.89 4,490.60 6,234.00 90.46 52,428.40 30.70 3,805.80 6,433.90 90.46 52,428.40 30.70 3,805.80 6,434.00 94.21 52,493.40 33.95 4,382.30 6,633.90 94.21 52,493.40 33.95 4,382.30 6,634.00 93.49 51,867.00 30.88 3,884.90 6,833.90 93.49 51,867.00 30.88 3,884.90 6,834.00 94.71 51,770.40 32.94 4,211.40 7,033.90 94.71 51,770.40 32.94 4,211.40 7,034.00 94.59 51,510.60 33.57 4,244.30 7,233.90 94.59 51,510.60 33.57 4,244.30 7,234.00 88.95 49,986.70 33.38 4,258.70 7,433.90 88.95 49,986.70 33.38 4,258.70 7,434.00 92.68 50,241.20 34.27 4,437.90 7,633.90 92.68 50,241.20 34.27 4,437.90 7,634.00 94.83 50,262.90 32.88 4,269.80 7,833.90 94.83 50,262.90 32.88 4,269.80 7,834.00 95.29 49,975.50 30.74 3,988.10 8,033.90 95.29 49,975.50 30.74 3,988.10 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 8,034.00 92.18 49,103.80 36.42 4,613.60 8,233.90 92.18 49,103.80 36.42 4,613.60 8,234.00 98.61 50,118.80 32.94 4,082.40 8,433.90 98.61 50,118.80 32.94 4,082.40 8,434.00 94.08 49,050.30 32.72 4,146.70 8,633.90 94.08 49,050.30 32.72 4,146.70 8,634.00 97.80 49,412.60 33.77 4,265.50 8,833.90 97.80 49,412.60 33.77 4,265.50 8,834.00 94.12 48,424.70 33.15 4,155.90 9,033.90 94.12 48,424.70 33.15 4,155.90 9,034.00 94.99 48,448.40 32.75 4,114.70 9,233.90 94.99 48,448.40 32.75 4,114.70 9,234.00 96.81 48,542.60 33.48 4,169.20 9,433.90 96.81 48,542.60 33.48 4,169.20 9,434.00 96.55 48,157.70 32.70 4,061.90 9,633.90 96.55 48,157.70 32.70 4,061.90 9,634.00 94.78 47,623.80 34.81 4,365.20 9,833.90 94.78 47,623.80 34.81 4,365.20 9,834.00 97.02 47,967.30 31.94 3,991.90 10,033.90 97.02 47,967.30 31.94 3,991.90 10,034.00 96.90 47,658.10 29.29 3,627.30 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 7 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 10,233.90 96.90 47,658.10 29.29 3,627.30 10,234.00 95.49 47,145.90 36.11 4,431.10 10,433.90 95.49 47,145.90 36.11 4,431.10 10,434.00 96.60 47,223.10 34.92 4,282.50 10,633.90 96.60 47,223.10 34.92 4,282.50 10,634.00 101.33 47,983.40 33.09 4,060.20 10,833.90 101.33 47,983.40 33.09 4,060.20 10,834.00 93.68 46,303.10 34.13 4,202.80 11,033.90 93.68 46,303.10 34.13 4,202.80 11,034.00 97.44 46,904.30 32.64 4,005.20 11,233.90 97.44 46,904.30 32.64 4,005.20 11,234.00 97.78 46,727.70 32.38 3,894.60 11,433.90 97.78 46,727.70 32.38 3,894.60 11,434.00 97.90 46,551.90 35.15 4,270.00 11,633.90 97.90 46,551.90 35.15 4,270.00 11,634.00 98.75 46,672.40 33.49 4,095.10 11,833.90 98.75 46,672.40 33.49 4,095.10 11,834.00 96.22 45,927.00 33.71 4,120.60 12,033.90 96.22 45,927.00 33.71 4,120.60 12,034.00 100.37 46,574.20 32.77 3,984.40 12,233.90 100.37 46,574.20 32.77 3,984.40 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 8 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 12,234.00 94.58 45,307.00 33.11 4,011.80 12,433.90 94.58 45,307.00 33.11 4,011.80 12,434.00 98.32 45,745.60 33.30 4,017.70 12,633.90 98.32 45,745.60 33.30 4,017.70 12,634.00 100.24 46,076.80 31.33 3,688.30 12,833.90 100.24 46,076.80 31.33 3,688.30 12,834.00 96.54 45,142.20 34.79 4,170.10 13,033.90 96.54 45,142.20 34.79 4,170.10 13,034.00 95.18 44,877.20 32.94 3,919.00 13,233.90 95.18 44,877.20 32.94 3,919.00 13,234.00 98.31 45,168.00 33.49 4,016.50 13,433.90 98.31 45,168.00 33.49 4,016.50 13,434.00 97.64 44,889.60 33.61 4,037.90 13,633.90 97.64 44,889.60 33.61 4,037.90 13,634.00 105.27 46,604.60 33.27 3,980.40 13,833.90 105.27 46,604.60 33.27 3,980.40 13,834.00 92.04 43,404.60 32.45 3,879.80 14,033.90 92.04 43,404.60 32.45 3,879.80 14,034.00 97.53 44,291.10 33.04 3,944.20 14,233.90 97.53 44,291.10 33.04 3,944.20 14,234.00 96.02 43,869.70 34.19 4,084.50 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 9 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 14,433.90 96.02 43,869.70 34.19 4,084.50 14,434.00 101.49 44,885.40 34.09 4,075.60 14,633.90 101.49 44,885.40 34.09 4,075.60 14,634.00 96.69 43,647.50 30.80 3,590.70 14,833.90 96.69 43,647.50 30.80 3,590.70 14,834.00 97.19 43,705.40 34.20 4,062.60 15,033.90 97.19 43,705.40 34.20 4,062.60 15,034.00 96.55 43,377.10 34.24 4,069.30 15,233.90 96.55 43,377.10 34.24 4,069.30 15,234.00 97.98 43,562.70 31.86 3,708.20 15,433.90 97.98 43,562.70 31.86 3,708.20 15,434.00 99.92 43,940.90 32.25 3,767.10 15,633.90 99.92 43,940.90 32.25 3,767.10 15,634.00 96.68 43,244.30 34.66 4,096.70 15,833.90 96.68 43,244.30 34.66 4,096.70 15,834.00 97.92 43,084.20 33.67 3,970.80 16,033.90 97.92 43,084.20 33.67 3,970.80 16,034.00 100.45 43,787.70 33.09 3,893.90 16,233.90 100.45 43,787.70 33.09 3,893.90 16,234.00 101.48 43,594.10 34.05 4,021.70 16,433.90 101.48 43,594.10 34.05 4,021.70 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 10 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 16,434.00 100.76 43,456.50 32.71 3,791.30 16,633.90 100.76 43,456.50 32.71 3,791.30 16,634.00 97.35 42,846.40 33.87 3,979.80 16,833.90 97.35 42,846.40 33.87 3,979.80 16,834.00 94.49 41,848.30 34.20 4,020.80 17,033.90 94.49 41,848.30 34.20 4,020.80 17,034.00 100.64 43,365.30 33.35 3,918.40 17,233.90 100.64 43,365.30 33.35 3,918.40 17,234.00 95.22 41,964.40 33.43 3,927.60 17,433.90 95.22 41,964.40 33.43 3,927.60 17,434.00 97.48 42,341.80 32.10 3,721.30 17,633.90 97.48 42,341.80 32.10 3,721.30 17,634.00 116.53 46,664.00 33.90 3,975.30 17,833.90 116.53 46,664.00 33.90 3,975.30 17,834.00 64.38 36,510.30 34.06 3,988.60 18,033.90 64.38 36,510.30 34.06 3,988.60 18,034.00 65.90 38,757.40 33.01 3,893.80 18,233.90 65.90 38,757.40 33.01 3,893.80 18,234.00 74.85 39,517.80 37.01 4,572.20 18,433.90 74.85 39,517.80 37.01 4,572.20 18,434.00 89.20 42,182.30 35.71 4,325.70 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 11 of 11 Tab le 1 4 .3 .4 - 4 2 (U2 ) - DECL Minimum Safeguards Post- B lowdown M& E B reak Path 1 B reak Path 2 Time (sec) Flow (lb m/ s) Energy (B tu/ s) Flow (lb m/ s) Energy (B tu/ s) 18,633.90 89.20 42,182.30 35.71 4,325.70 18,634.00 88.01 41,454.30 32.50 3,816.20 18,833.90 88.01 41,454.30 32.50 3,816.20 18,834.00 101.20 43,919.00 34.87 4,171.20 19,033.90 101.20 43,919.00 34.87 4,171.20 19,034.00 96.13 42,607.50 33.68 4,024.10 19,233.90 96.13 42,607.50 33.68 4,024.10 19,234.00 84.78 39,992.80 33.42 3,981.00 19,433.90 84.78 39,992.80 33.42 3,981.00 19,434.00 97.51 42,588.10 41.87 5,855.70 19,633.90 97.51 42,588.10 41.87 5,855.70 19,634.00 100.52 43,109.70 21.59 2,267.20 19,833.90 100.52 43,109.70 21.59 2,267.20 19,834.00 111.91 43,408.65 19.59 2,004.22 40,000.00 55.58 32,378.51 75.92 7,760.90 60,568.90 35.27 27,552.45 96.23 9,828.70 60,569.00 34.60 27,028.21 96.90 9,897.25 100,000.00 19.31 22,440.43 112.19 11,440.77 150,000.00 17.14 19,913.48 114.36 11,662.56 174,651.90 16.41 19,063.81 115.09 11,737.14 174,652.00 15.85 18,420.99 115.65 11,793.56 Unit 2
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-47 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Parameters Used in Steamline B reak Mass / Energy Releases Parameter Parameter Value NSSS Power, MWt 3,608 Core Power, MWt 3,588 RCS Flow, gpm / loop 79,000 Minimum Measured Flow, gpm / loop 91,600 Core O utlet Temperature, °F 618.0 Vessel O utlet Temperature, °F 615.2 Vessel Average Temperature, °F 581.3 Vessel/ Core Inlet Temperature, °F 547.4 Steam Generator O utlet Temperature, °F 547.1 Z ero Load Temperature, °F 547.0 RCS Pressure, psia 2,250 or 2,100 Steam Pressure, psia 858.2 Steam Flow (106 lb / hr total) 16.00 Feedwater Temp., °F 449.0 SG Tube Plugging, % 0 Unit 2