Text

0 to Updated Final Safety Analysis Report, Chapter 14, Tables 14.3.1-1 to 14.3.9-23, 14.A.1-1 to 14.G-3 (Unit 1)
	ML21125A501
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Site:	Cook
Issue date:	04/19/2021
From:	; Indiana Michigan Power Co
To:	; Office of Nuclear Reactor Regulation
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ML21126A238	List: AEP-NRC-2021-19, 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary; ML21125A456; ML21125A457; ML21125A472; ML21125A473; ML21125A475; ML21125A482; ML21125A486; ML21125A487; ML21125A488; ML21125A493; ML21125A498; ML21125A499; ML21125A500; ML21125A501; ML21125A502; ML21125A503; ML21125A505; ML21125A508; ML21125A509; ML21125A510; ML21125A512; ML21125A514; ML21125A517; ML21125A518; ML21125A520; ML21125A521; ML21125A522; ML21125A524; ML21125A525; ML21125A526; ML21125A527; ML21125A529; ML21125A533; ML21125A534; ML21125A535; ML21125A537; ML21125A538; ML21125A539; ML21125A540; ML21125A542; ML21125A543; ML21125A545; ML21125A546; ML21125A547; ML21125A548; ML21125A550; ML21125A554; ML21125A557; ML21125A558; ... further results
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UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 Plant Operating Range Analyzed by the Best-Estimate Large Break LOCA Analysis for D. C. Cook Unit 1 Parameter Analyzed Value or Range 1.0 Plant Physical Description a) Dimensions Nominal b) Pressurizer location On an intact loop1 c) Hot assembly location Anywhere in core2 15x15 Upgrade Fuel with ZIRLO 3

d) Hot assembly type cladding or Optimized ZIRLO cladding, non-IFBA or IFBA e) Steam generator tube plugging level 10%

15x15 Upgrade Fuel with ZIRLO 3

f) Fuel assembly type cladding or Optimized ZIRLO cladding, non-IFBA or IFBA 2.0 Plant Initial Operating Conditions 2.1 Reactor Power a) Maximum Core power 3315 MWt b) Peak heat flux hot channel factor (FQ)3,4 2.15 1

Analyzing the pressurizer as being located on an intact loop is limiting per Westinghouse methodology.

2 44 peripheral locations will not physically be lead power assembly.

3 In the Westinghouse Reload Safety Analysis Checklist (RSAC) process, this parameter is identified as a key safety analysis parameter that could be impacted by a fuel reload.

4 Parameter values affected by evaluation described in Section 14.3.1.6.2 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 Plant Operating Range Analyzed by the Best-Estimate Large Break LOCA Analysis for D. C. Cook Unit 1 Parameter Analyzed Value or Range Peak hot rod enthalpy rise hot channel c) 1.55 factor (FH)3,4 Hot assembly radial peaking factor d) 1.55/1.04 (PHA)3,4 Hot assembly heat flux hot channel factor e) 2.15/1.04 (FQHA)4 f) Axial power distribution (PBOT, PMID)3 Figure 14.3.1-2 g) Low power region relative power (PLOW)3 0.30 PLOW 0.70 h) Hot assembly burnup 75,000 MWD/MTU, lead rod2,5 i) MTC 0 at hot full power (HFP) j) Typical cycle length 18 months k) Minimum core average burnup3 10,000 MWD/MTU l) Maximum steady state depletion, FQ3,4 1.90 2.2 Fluid Conditions a) TAVG4 553.7 - 4.1°F TAVG 575.4 + 5.1°F 2100 - 67 psia PRCS 2100 + 67 psia; b) Pressurizer pressure4 2250 - 67 psia PRCS 2250 + 67 psia c) Minimum thermal design flow 88,500 gpm/loop 5

The fuel temperature and rod internal pressure data is only provided up to 62,000 MWD/MTU. In addition, the hot assembly/ hot rod will not have a burnup this high in ASTRUM analyses.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 Plant Operating Range Analyzed by the Best-Estimate Large Break LOCA Analysis for D. C. Cook Unit 1 Parameter Analyzed Value or Range d) Upper head design THOT 56.1% of span (High TAVG) e) Pressurizer level (at hot full power)4 43.4% of span (Low TAVG) f) Accumulator temperature4 60°F TACC 120°F g) Accumulator pressure 599.7 psia PACC 672.7 psia h) Accumulator liquid volume 921 ft3 VACC 971 ft3 i) Minimum accumulator boron 2228 ppm 3.0 Accident Boundary Conditions a) Minimum safety injection flow4 Table 14.3.1-4a and 14.3.1-4b b) Safety injection temperature4 70°F SI Temp 105°F 27 seconds (with offsite power) c) Safety injection delay4 54 seconds (with LOOP)

Figures 14.3.1-3 thru 14.3.1-9 and raw 4

d) Containment modeling data in Tables 14.3.1-2, 14.3.1-3, and 14.3.1-7 e) Initial containment pressure See Table 14.3.1-2 f) Containment spray initiation delay4 See Table 14.3.1-2 g) Deck Fan initiation delay4 See Table 14.3.1-2 h) Single failure Loss of one ECCS train Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Large-Break Containment Data ( Ice Condenser Containment)

UC: 729,969 ft3 Net Free Volume Distribution Between Upper (UC), Lower (LC), Ice LC: 295,258 ft3 Condenser (IC) and Dead-Ended (DE) Compartments IC: 122,350 ft3 DE: 60,209 ft3 Initial Condition Containment Pressure 14.7 psia UC: 100°F Maximum Temperature for the LC: 120°F Upper (UC), Lower (LC) and Dead-Ended (DE) Compartments DE: 120°F Temperature Outside Containment -22°F Initial Spray Temperature at 14.7 psia 45°F1 Maximum Containment Spray Flow Rate2 3700 gpm / pump Number of Spray Pumps Operating 2 Post-Accident Initiation of Spray System2 44 sec Post-Accident Initiation of Deck Fans2 108 sec Deck Fan Flow Rate 48,000 cfm / fan Assumed Spray Efficiency of Water from Ice Condenser Drains 100%

1 Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See Section 14.3 .1.6.1 for more information.

2 Parameter values affected by the evaluation described in Section 14.3.1.6.2.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 14.3.1-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 LARGE BREAK CONTAINMENT - HEAT SINKS DATA (ICE CONDENSER CONTAINMENT)

Wall Compartment Area (ft2) Thickness (ft) Material 1 UC 24036. 0.0329 / 3.2 steel / concrete 2 UC 5993. 0.0329 / 3.7 steel / concrete 3 UC 2593. 2.1 concrete 4 UC 17742. 4.2 concrete 5 UC 4973. 0.0392 / 13.7 steel / concrete 6 UC 21305. 0.0091 steel 7 UC 18067. 0.0196 steel 8 UC 6035. 0.1070 steel 9 UC 5079. 0.2300 steel 10 UC 23429. 0.1284 steel 11 LC 2682. 0.0218 / 5.3 steel / concrete 12 LC 447. 5.3 concrete 13 LC 51219. 6.8 concrete 14 LC 15033. 0.0200 / 5.40 steel / concrete 15 LC 42353. 0.0081 steel 16 LC 16886. 0.0166 steel 17 LC 13778. 0.0644 steel 18 LC 61214. 0.1076 steel 19 LC 4529. 14.04 concrete 20 LC 3439. 0.1561 steel UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.3.1-4A UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Minimum Safety Inj ection Pump ( HHSI) and Residual Heat Remov al Pump ( RHR) Combined Inj ection Flow Original HHSI and RHR Total Adj usted HHSI and RHR Total Pressure Inj ected Flow Inj ected Flow

( psia)

( gpm) 1, 2 ( gpm) 2, 3 14.7 3219.7 3044.9 34.7 2637.8 2455.0 54.7 2009.5 1802.4 74.7 1520.6 1390.3 94.7 1188.2 1045.0 114.7 788.0 629.3 134.7 267.3 259.1 154.7 262.9 255.5 174.7 258.5 251.9 194.7 254.1 248.3 214.7 249.6 244.6 234.7 245.0 240.8 254.7 240.4 237.1 274.7 235.7 233.3 294.7 231.0 229.4 314.7 226.0 225.5 1

The original HHSI and RHR flow corresponds to the analysis results presented in the tables and figures, except for Table 14.3.1-5.

2 HHSI and RHR total injected flow values affected by the evaluation described in Section 14.3.1.6.2. See Table 14.3.1-4C.

3 The adjusted HHSI and RHR flow corresponds to the PCT results presented in the Adjusted HHSI and RHR Flow column in Table 14.3.1-5.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 14.3.1-4B UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 MINIMUM CENTRIFUGAL CHARGING PUMP (CCP) INJECTION FLOW Pressure Total CCP Injected Flow (psia) (gpm) 14.7 283.2 114.7 253.5 214.7 247.3 314.7 247.0 414.7 243.7 514.7 233.4 614.7 214.9 714.7 195.9 814.7 176.3 914.7 155.9 1014.7 134.7 1114.7 112.4 1214.7 88.9 1314.7 63.8 1414.7 36.3 1514.7 9.1 1614.7 0.0 1714.7 0.0

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.3.1-4C UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Minimum Safety Inj ection Pump ( HHSI) and Residual Heat Removal Pump ( RHR)

Combined Inj ection Flow for the Return to NOP/ NOT Eval uation HHSI and RHR Total Inj ected Flow at Pressure ( psia)

NOP/ NOT Conditions ( gpm) 15.7 3099 19.7 2997 24.7 2853 29.7 2707 34.7 2561 39.7 2412 54.7 1928 74.7 1465 94.7 1140 114.7 745 134.7 275 154.7 271 174.7 267 194.7 262 214.7 258 234.7 254 254.7 249 274.7 245 294.7 240 314.7 236 414.7 212 514.7 184 614.7 149 714.7 108 814.7 58 914.7 0 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 14.3.1-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 D. C. COOK UNIT 1 BEST-ESTIMATE LARGE BREAK LOCA RESULTS ASTRUM Result for ASTRUM Result for 10 CFR 50.46 Parameter Original HHSI and Adjusted HHSI and Acceptance RHR Injection Flow RHR Injection Flow Criteria Value Value 95th Percentile PCT at the 95-2106 2128 2200 Percent Confidence Level (°F) 95th Percentile LMO at the 95-10.0 11.1 17 Percent Confidence Level (%)

95th Percentile CWO at the 95-0.35 0.40 1 Percent Confidence Level (%)

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-6 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Peak Cladding Temperature Including All Penalties and Benefits, Best-Estimate Large Break LOCA ( BE LOCA) for D. C. Cook Unit 1 PCT for Analysis-of Record (AOR) 2128°F PCT Assessments Allocated to AOR NOP/NOT1 Design Input Changes with Respect to Plant

-489 F Operations Evaluation of Pellet Thermal Conductivity

+404 F Degradation and Peaking Factor Burndown Revised Heat Transfer Multiplier Distribution -91 F HOTSPOT Burst Strain Error +85 F Decay Group Uncertainty Factors Errors -29 F Upflow Conversion +14 F BE LBLOCA PCT 2022 F for Comparison to 10CFR50 .46 Req uirements 1

NOP/NOT refers to Unit 1 Return to Normal Operating Pressure and Temperature implemented by EC-52930 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-7 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Nitrogen Mass and Energy Release Rates1 Time ( s) Flow Rate ( lbm / s)

0. 0.

50. 0.

50.01 236.

70.01 236.

70.02 0.

1000. 0.

1 Parameter values affected by the evaluation described in Section 14.3.1.6.2. See Table 14.3.1-7A.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.3.1-7A UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Nitrogen Mass and Energy Release Rates for the Return to NOP/ NOT Ev aluation Time ( s) Flow Rate ( lbm / s) 0 0 44.3 0 44.31 254.6 64.31 254.6 64.32 0 1000.0 0 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-8 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Seq uence of Ev ents for the Limiting Case1 Ev ent Time ( sec)

Start of Transient 0.0 Safety Injection Signal 4.6 Accumulator Injection Begins 16.0 End of Blowdown 25.0 Bottom of Core Recovery 42.5 Accumulator Empty 49.3 Safety Injection Begins 58.6 PCT Occurs 247.0 End of Transient 500.0 1

The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Table 14.3.1-8A for more information.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.3.1-8A UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Seq uence of Ev ents for the Limiting Return to NOP/ NOT Ev aluation Case Ev ent Time ( sec)

Start of Transient 0.0 Safety Injection Signal 5.0 Accumulator Injection Begins 12.0 End of Blowdown 24.6 Safety Injection Begins 33.0 Bottom of Core Recovery 35.2 Accumulator Empty 46.2 PCT Occurs 272.0 End of Transient 500.0 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-1 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 2 Plant Input Parameters for Small Break Loss-of-Coolant Accident Core Rated Thermal Power-100 (MWt) 3304 Peak Linear Power, kW/ft 15.171 Fuel Type 15x15 Upgrade Fuel Total Core Peaking Factor, FQ 2.32 Hot Channel Enthalpy Rise Factor, FH 1.55 Hot Assembly Average Power Factor, PHA 1.38(4)

Thermal Design Flow, gpm/loop 83,200 Nominal Vessel Average Temperature, F 577.4(1)

Nominal Pressurizer Pressure, psia 2250(2)

Pressurizer Pressure Uncertainty (psia) 67 Minimum Auxiliary Feedwater Flow Rate, lbm/s per SG 14.68 Steam Generator Tube Plugging (Maximum), 10 Initial Accumulator Water Volume, ft3 946 Accumulator Tank Volume, ft3/tank 1350 Accumulator Water Temperature, °F 130 Minimum Accumulator Cover Gas Pressure (minus uncertainties), psia 600 Refueling Water Storage Tank Temperature, F 105 Nominal Steam Pressure, psia 848.32 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-1 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 2 of 2 Plant Input Parameters for Small Break Loss-of-Coolant Accident SI Flow Delay Time, seconds 54 Open (Injection & Cold HHSI Cross-Tie Valve Position Leg Recirculation)(3)

Open (Injection)

RHR Cross-Tie Valve Position Closed (Cold Leg Recirculation)

(1) Analysis supports operation over the range of nominal full-power Tavg values of 553.7 F - 575.4 F.

(2) Analysis supports operation at nominal initial pressurizer pressure (without uncertainties) of 2100 psia and 2250 psia.

(3) Conservatively modeled HHSI cross-tie valves closed in injection phase.

(4) Parameter value affected by the evaluation described in Section 14.3.2.4.1.2.See Table 14.3.2-1a.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 29 D. C. COOK NUCLEAR PLANT Table: 14.3.2-1a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Burnup-Dependent Hot Assembly Av erage Power Factor ( PHA) For Small Break Loss-of-Coolant Accident - Upflow Configuration Assembly Burnup ( MWD/ MTU) PHA Limit without Uncertainty 0 1.38 28,000 1.38 30,000 1.250 60,000 1.139 62,000 1.139 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Time Seq uence of Ev ents for Small Break Loss-of-Coolant Accident( 6 )

Ev ent Time ( sec) 1.5 -inch 2-inch 2.5 -inch 2.7 5 -inch 3.0-inch 3.25 -inch 3.5 -inch 3.7 5 -inch 4 .0-inch 6 .0-inch 8 .7 5 -inch Break Initiation 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Reactor Trip Signal 89.8 45.9 27.9 22.7 19.0 16.2 14.0 12.3 10.9 6.0 4.5 S-Signal 112.8 60.9 38.2 31.6 26.8 23.2 20.3 17.9 15.7 8.4 6.7 SI Flow Delivered(1) 166.8 114.9 92.2 85.6 80.8 77.2 74.3 71.9 69.7 62.4 60.7 Loop Seal Clearing(2) 2492 1341 857 628 516 445 386 390 302 146 30 Core Uncovery(4) N/A 1897 1027 1017 963 780 664 630 602 342 N/A (3)

Accumulator Injection N/A N/A 3065 2129 1707 1264 1031 940 823 345 168 RWST Volume Delivered(5) 2165.6 2157.6 2145.4 2137.8 2130.0 2120.9 2114.4 2110.2 2106.4 2042.8 1590.7 PCT Time (BOL) N/A 2284.4 2684.0 2140.6 2000.5 1483.4 1249.3 1129.8 986.2 404.1 N/A Core Recovery (4) N/A 6663 4032 4081 3977 3840 3973 4110 3404 423 N/A Notes:

(1) SI is assumed to begin 54.0 seconds (SI delay time) after the S-Signal.

(2) Loop seal clearing is assumed to occur when the steam flow through the broken loop, loop seal is sustained above 1 lbm/s.

(3) For 8.75-inch break, accumulator injection begins for Loops 2-4 only; Loop 1 (broken loop) accumulator line is the location of the break and assumed to spill to containment.

(4) The latest point of sustained core uncovery/recovery is reported.

(5) The analysis assumes minimum usable RWST volume (280,000 gal) delivered via ECCS injection and containment spray before the low level RWST water level signal for switchover to cold leg recirculation is reached.

(6) See Table 14.3.2-2a for additional evaluation results for Upflow configuration.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 29 D. C. COOK NUCLEAR PLANT Table: 14.3.2-2a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Time Seq uence of Ev ents for Small Break Loss-of-Coolant Accident - Upflow Configuration Time ( s)

Ev ent Description 2.75- inch 3.0-inch 3.25- inch 3.50- inch Break Initiation 0.0 0.0 0.0 0.0 Reactor Trip Signal 22.9 19.1 16.3 14.0 S-Signal 31.6 27.0 23.3 20.3 SI Flow Delivered(1) 85.6 81.0 77.3 74.3 (2)

Loop Seal Clearing 625 535 467 388 Core Uncovery(4) 1023 646 586 638 (3)

Accumulator Injection 2032 1475 1216 1016 PCT Time (BOL) 2051.7 1772.3 1418.3 1223.1 RWST Volume Delivered 2136.9 2126.3 2119.5 2113.7 (4)

Core Recovery 4370 4003 3786 3914 Notes:

(1) SI is assumed to begin 54.0 seconds (SI delay time) after the S-Signal (2) Loop seal clearing is assumed to occur when the steam flow through the broken loop, loop seal is sustained above 1 lbm/s (3) Applies to all 4 loops (4) The latest point of sustained core uncovery/recovery is reported.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Small Break Loss-of-Coolant Accident Calculations( 2)

Break Size ( in) 2-inch 2.5- inch 2.75- inch 3.0-inch 3.25- inch 3.5- inch 3.75- inch 4.0- inch 6.0- inch PCT ( F) 968.4 1433.4 1452.5 1584.0 1725.0 1705.3 1517.9 1411.2 670.6 PCT Time (s) 2284.4 2684.0 2140.6 2000.5 1483.4 1249.3 1129.8 986.2 404.1 PCT Elevation (ft) 11.0 11.50 11.50 11.75 11.75 11.75 11.50 11.25 11.00 Max. Local ZrO2 ( ) 0.03 0.70 0.54 1.26 2.08 1.72 0.56 0.26 0.00 Max. Local ZrO2 Elev. (ft) 11.0 11.50 11.50 11.75 11.75 11.50 11.50 11.25 11.00 Hot Rod Axial Average ZrO2 ( )(1) 0.00 0.09 0.07 0.17 0.30 0.26 0.08 0.04 0.00 Notes:

(1) The hot rod axial average ZrO2 conservatively represents the core wide average oxidation, since the core wide average ZrO2 thickness will always be less than the corresponding hot rod axial average ZrO2 thickness.

(2) See Table 14.3.2-3a for additional calculation results for Upflow configuration Unit 1

UFSAR Revision 30.0 Revised: 29 INDIANA MICHIGAN POWER Table: 14.3.2-3a D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Page: Page 1 of 1 Beginning of Life Small Break Loss-of-Coolant Accident Calculations - Upflow Configuration Item Description 2.7 5 -inch 3.0-inch 3.25 -inch 3.5 -inch PCT ( oF) 1522.9 1784.2 1771.7 1734.8 PCT Time ( s) 2051.7 1772.3 1418.3 1223.1 PCT Elev ation ( ft) 11.5 11.75 11.75 11.75 Max. L ocal Z rO2 ( % ) 1.01 2.97 2.53 1.89 Max. L ocal Z rO2 Elev . ( ft) 11.75 11.75 11.75 11.75 Hot Rod Axi al Ave rage Z rO2 ( % ) 0.14 0.40 0.35 0.28 Unit 1

UFSAR Revision 30.0 Revised: 29 INDIANA MICHIGAN POWER Table: 14.3.2-3b D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Page: Page 1 of 1 Upflow Configuration Limiting 3.0-Inch Small Break Loss-of-Coolant Accident Burnup Results Burnup (MWD/MTU) 8000 8500(1) 9000(2) 10000 15000 50000(3) 62000(4)

PCT (°F) 1761.1 1831.4 1796.2 1794.6 1801.7 1776.3 1573.0 Max. Local ZrO2 (%) 2.33 6.13 6.19 6.16 5.65 2.96 1.14 Hot Rod Axial Average 0.28 0.34 0.37 0.36 0.31 0.10 0.03 ZrO2 (%)

Total Maximum Local 4.19 8.11 8.28 8.49 9.14 14.6 15.57 Oxidation(5) (%)

Notes:

(1) The limiting PCT occurs at the incipient burst point burnup of 8500 MWD/MTU.

(2) The limiting local transient oxidation and hot rod average oxidation occur at 9000 MWD/MTU.

(3) PHA burndown would be available at the 50,000 MWD/MTU burnup; however, it is not credited.

(4) The 62,000 MWD/MTU case credits PHA burndown to meet the maximum local oxidation limit of 17%.

(5) Includes summation of transient (max. local ZrO2) and pre-transient oxidation.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 25.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-4 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 2 Safety Inj ection Flows Used in the SBLOCA Analysis - Inj ection Phase

( 1 CHG pump, 1 HHSI pump, 1 RHR pump - faulted loop inj ects to RCS pressure - 1.5 -inch through 6 -inch breaks)

Broken Loop Intact Loops ( lbm/ sec)

RCS Pressure ( lbm/ sec)

( psia)

Loop 1 Loop 2 Loop 3 Loop 4 14.7 188.63 158.38 175.00 159.93 114.7 127.20 102.43 117.32 103.38 214.7 38.89 12.50 34.37 12.50 314.7 37.49 12.21 33.10 12.21 414.7 35.93 11.90 31.73 11.90 514.7 34.30 11.57 30.26 11.57 614.7 32.56 11.23 28.64 11.23 714.7 30.73 10.88 26.98 10.88 814.7 28.80 10.54 25.22 10.54 914.7 26.74 10.18 23.35 10.18 1014.7 24.34 9.82 21.14 9.82 1114.7 21.49 9.46 18.54 9.46 1214.7 18.00 9.10 15.32 9.10 1314.7 13.03 8.70 10.73 8.70 1414.7 10.36 8.29 8.29 8.29 1514.7 9.82 7.86 7.86 7.86 1614.7 9.27 7.42 7.42 7.42 1714.7 8.72 6.98 6.98 6.98 1814.7 8.08 6.47 6.47 6.47 Unit 1 Last Revised: Revision 25.0

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 25.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-4 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 2 of 2 Safety Inj ection Flows Used in the SBLOCA Analysis - Inj ection Phase

( 1 CHG pump, 1 HHSI pump, 1 RHR pump - faulted loop inj ects to RCS pressure - 1.5 -inch through 6 -inch breaks)

Broken Loop Intact Loops ( lbm/ sec)

RCS Pressure ( lbm/ sec)

( psia)

Loop 1 Loop 2 Loop 3 Loop 4 1914.7 7.41 5.93 5.93 5.93 2014.7 6.72 5.38 5.38 5.38 2114.7 5.94 4.76 4.76 4.76 2214.7 5.02 4.01 4.01 4.01 2314.7 0 0 0 0 Unit 1 Last Revised: Revision 25.0

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 25.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-5 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 2 Safety Inj ection Flows Used in the SBLOCA Analysis - Inj ection Phase

( 1 CHG pump, 1 HHSI pump, 1 RHR pump - faulted loop CHG flow inj ects to RCS pressure and faulted loop HHSI / RHR flow spills to containment

( 0 psia) - 8 .7 5 -inch break)

Broken Loop ( lbm/ sec) Intact Loops ( lbm/ sec)

RCS Pressure

( psia) Loop 1 Loop 1 Loop 2 Loop 3 Loop 4 CHG RHR / HHSI 14.7 16.34 157.03 139.36 156.01 140.26 34.7 16.27 215.73 126.84 99.71 127.64 54.7 16.20 274.56 115.46 32.18 116.17 74.7 16.13 303.81 97.04 12.90 97.63 94.7 16.06 323.64 72.95 12.84 73.37 114.7 15.98 345.72 43.70 12.78 43.93 134.7 15.91 365.86 12.73 12.73 12.73 154.7 15.84 365.86 12.67 12.67 12.67 214.7 15.63 365.86 12.50 12.50 12.50 314.7 15.25 365.86 12.21 12.21 12.21 414.7 14.83 365.86 11.90 11.90 11.90 514.7 14.45 365.86 11.57 11.57 11.57 614.7 14.03 365.86 11.23 11.23 11.23 714.7 13.60 365.86 10.88 10.88 10.88 814.7 13.17 365.86 10.54 10.54 10.54 914.7 12.73 365.86 10.18 10.18 10.18 1014.7 12.29 365.86 9.82 9.82 9.82 1114.7 11.83 365.86 9.46 9.46 9.46 1214.7 11.38 365.86 9.10 9.10 9.10 Unit 1 Last Revised: Revision 25.0

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 25.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-5 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 2 of 2 Safety Inj ection Flows Used in the SBLOCA Analysis - Inj ection Phase

( 1 CHG pump, 1 HHSI pump, 1 RHR pump - faulted loop CHG flow inj ects to RCS pressure and faulted loop HHSI / RHR flow spills to containment

( 0 psia) - 8 .7 5 -inch break)

Broken Loop ( lbm/ sec) Intact Loops ( lbm/ sec)

RCS Pressure

( psia) Loop 1 Loop 1 Loop 2 Loop 3 Loop 4 CHG RHR / HHSI 1314.7 10.88 365.86 8.70 8.70 8.70 1414.7 10.36 365.86 8.29 8.29 8.29 1514.7 9.82 365.86 7.86 7.86 7.86 1614.7 9.27 365.86 7.42 7.42 7.42 1714.7 8.72 365.86 6.98 6.98 6.98 1814.7 8.08 365.86 6.47 6.47 6.47 1914.7 7.41 365.86 5.93 5.93 5.93 2014.7 6.72 365.86 5.38 5.38 5.38 2114.7 5.94 365.86 4.76 4.76 4.76 2214.7 5.02 365.86 4.01 4.01 4.01 2314.7 0 365.86 0 0 0 Unit 1 Last Revised: Revision 25.0

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 25.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-6 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 2 Safety Inj ection Flows Used in the SBLOCA Analysis - Recirculation Phase

( 1 CHG pump, 1 HHSI pump, 1 RHR pump - faulted loop inj ects to RCS pressure -

RHR Spray active - 1.5 - through 6- inch breaks)

Broken Loop RCS Pressure Intact Loops ( lbm/ sec)

( lbm/ sec)

( psia)

Loop 1 Loop 2 Loop 3 Loop 4 14.7 36.1 32.1 31.3 32.3 34.7 35.9 31.9 31.1 32.1 54.7 35.7 31.7 30.9 31.9 74.7 35.5 31.5 30.7 31.7 94.7 35.3 31.3 30.5 31.5 114.7 35.0 31.1 30.3 31.3 134.7 34.8 30.9 30.1 31.1 154.7 34.6 30.7 29.9 30.9 174.7 34.3 30.5 29.7 30.6 194.7 34.1 30.3 29.5 30.4 214.7 33.9 30.1 29.3 30.2 234.7 33.6 29.9 29.1 30.0 254.7 33.4 29.6 28.9 29.8 274.7 33.2 29.4 28.7 29.6 294.7 32.9 29.2 28.4 29.3 314.7 32.7 29.0 28.2 29.1 414.7 31.5 27.9 27.2 28.0 514.7 30.2 26.7 26.0 26.8 614.7 28.8 25.5 24.9 25.6 714.7 27.4 24.2 23.6 24.3 814.7 26.0 22.9 22.3 23.0 914.7 24.5 21.5 21.0 21.6 1014.7 22.6 19.9 19.4 20.0 Unit 1 Last Revised: Revision 25.0

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 25.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-6 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 2 of 2 Safety Inj ection Flows Used in the SBLOCA Analysis - Recirculation Phase

( 1 CHG pump, 1 HHSI pump, 1 RHR pump - faulted loop inj ects to RCS pressure -

RHR Spray active - 1.5 - through 6- inch breaks)

Broken Loop RCS Pressure Intact Loops ( lbm/ sec)

( lbm/ sec)

( psia)

Loop 1 Loop 2 Loop 3 Loop 4 1114.7 20.7 18.1 17.7 18.1 1214.7 18.4 15.9 15.6 16.0 1314.7 15.3 13.0 12.8 13.1 1414.7 11.4 9.4 9.3 9.4 1514.7 9.2 7.4 7.4 7.4 1614.7 8.7 7.0 7.0 7.0 1714.7 8.1 6.6 6.6 6.6 Unit 1 Last Revised: Revision 25.0

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 25.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-7 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 2 Safety Inj ection Flows Used in the SBLOCA Analysis - Recirculation Phase

( 1 CHG pump, 1 HHSI pump, 1 RHR pump -

faulted loop CHG flow inj ects to RCS pressure and faulted loop HHSI/ RHR flow spills to containment ( 0 psia) - R HR Spray active - 8. 75- inch break)

RCS Broken Loop ( lbm/ sec) Intact Loops ( lbm/ sec)

Pressure Loop 1 -

( psia) Loop 1 - CHG Loop 2 Loop 3 Loop 4 RHR/ HHSI 14.7 15.4 20.7 32.1 31.3 32.3 34.7 15.4 39.8 31.9 12.4 32.0 54.7 15.3 39.9 31.6 12.4 31.8 74.7 15.3 40.0 31.4 12.3 31.5 94.7 15.2 40.1 31.1 12.2 31.2 114.7 15.1 40.3 30.8 12.2 31.0 134.7 15.0 40.4 30.6 12.1 30.7 154.7 15.0 40.5 30.3 12.1 30.4 174.7 14.9 40.6 30.0 12.0 30.1 194.7 14.8 40.8 29.7 12.0 29.9 214.7 14.8 40.9 29.4 11.9 29.6 234.7 14.7 41.1 29.2 11.8 29.3 254.7 14.6 41.2 28.9 11.8 29.0 274.7 14.5 41.3 28.6 11.7 28.7 294.7 14.5 41.4 28.3 11.7 28.4 314.7 14.4 41.6 28.0 11.6 28.1 414.7 14.1 42.2 26.5 11.3 26.6 514.7 13.7 42.9 24.9 11.0 25.0 614.7 13.3 55.9 22.6 10.7 22.6 714.7 12.8 57.8 19.8 10.4 19.8 814.7 12.4 59.8 16.5 10.0 16.6 Unit 1 Last Revised: Revision 25.0

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 25.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-7 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 2 of 2 Safety Inj ection Flows Used in the SBLOCA Analysis - Recirculation Phase

( 1 CHG pump, 1 HHSI pump, 1 RHR pump -

faulted loop CHG flow inj ects to RCS pressure and faulted loop HHSI/ RHR flow spills to containment ( 0 psia) - R HR Spray active - 8. 75- inch break)

RCS Broken Loop ( lbm/ sec) Intact Loops ( lbm/ sec)

Pressure Loop 1 -

( psia) Loop 1 - CHG Loop 2 Loop 3 Loop 4 RHR/ HHSI 914.7 12.0 62.2 12.7 9.7 12.7 1014.7 11.6 64.3 9.3 9.3 9.3 1114.7 11.1 64.3 9.0 9.0 9.0 1214.7 10.7 64.3 8.6 8.6 8.6 1314.7 10.2 64.3 8.3 8.3 8.3 1414.7 9.8 64.3 7.9 7.9 7.9 1514.7 9.2 64.4 7.4 7.4 7.4 1614.7 8.7 64.4 7.0 7.0 7.0 1714.7 8.1 64.4 6.6 6.6 6.6 Unit 1 Last Revised: Revision 25.0

UFSAR Revision 30.0 Revised: 29 INDIANA MICHIGAN POWER Table: 14.3.2-8 D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Page: Page 1 of 1 Peak Cladding Temperature Including All Penalties and Benefits, Small Break LOCA ( SBLOCA) for D. C. Cook Unit 1 PCT for Analysis-of-Record (AOR) 1725º F PCT Assessments Allocated to AOR Upflow Conversion +107°F SBLOCA PCT for Comparison to 10 CFR 50.46 Requirements 1832º F Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 14.3.3-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 SELECTED INPUT PARAMETERS* USED FOR THE COOK NUCLEAR PLANT UNITS 1 AND 2 REDUCED TEMPERATURE AND PRESSURE AND RERATING PROGRAM LOCA FORCES ANALYSIS Input Parameter Value Steam Generator Tube Plugging Level 15% Uniform Vessel Inlet Temperature 511.7°F Vessel Outlet Temperature 582.3°F Loop Flow Rate 88,500 gpm Reactor Power 3588 MWt Reactor Coolant System Pressure 2250 psia

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.4 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 Lower Compartment (active), ft 3 (1) 293,801 Total Active Volume, ft3 1,131,949 Lower Compartment (dead ended), ft3 61,309 Total Containment Volume, ft3 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 19.2 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 Leakage Spray Flow Rate Break Size Air Compression Containment Area (ft2 ) (gpm)

Peak (psig) 1 Pressure (psig)

Double 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.

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 6 Structural Heat Sink Table Upper Compartment Area ( ft2 ) Thickness ( ft) Material Structure 1 29,958.25 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 12,571.35 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.00275 Paint (Primer)

Layer 3 2.710421 Concrete Structure 3 15,526.8 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.00275 Paint (Primer)

Layer 3 2.2728 Concrete Structure 4 1,306.25 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.0005 Paint (Primer)

Layer 3 0.209108 Carbon Steel Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 6 Structural Heat Sink Table Upper Compartment Area ( ft2 ) Thickness ( ft) Material Structure 5 4,207.55 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.0005 Paint (Primer)

Layer 3 0.064932 Carbon Steel Structure 6 22,443.75 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.0005 Paint (Primer)

Layer 3 0.017572 Carbon Steel Structure 7 24,149.01 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.0005 Paint (Primer)

Layer 3 0.010036 Carbon Steel Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 6 Structural Heat Sink Table Lower Compartment Area ( ft2 ) Thickness ( ft) Material Structure 8 6,734.55 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 14,642.35 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.00275 Paint (Primer)

Layer 3 5.8355 Concrete Structure 10 25,872.3 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.00275 Paint (Primer)

Layer 3 2.699 Concrete Structure 11 3,214.8 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.0005 Paint (Primer)

Layer 3 0.09286 Carbon Steel Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 6 Structural Heat Sink Table Lower Compartment Area ( ft2 ) Thickness ( ft) Material Structure 12 3,499.8 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.0005 Paint (Primer)

Layer 3 0.06918 Carbon Steel Structure 13 12,312.0 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.0005 Paint (Primer)

Layer 3 0.013136 Carbon Steel Structure 14 58,073.355 Layer 1 0.001 Paint (Top Coat)

Layer 2 0.0005 Paint (Primer)

Layer 3 0.00952 Carbon Steel Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 6 Structural Heat Sink Table Ice Condenser Area ( ft2 ) Thickness ( ft) Material Structure 15 149,600.0 Ice Baskets Layer 1 0.00663 Steel Structure 16 75,865.0 Lattice Frames Layer 1 0.0217 Steel Structure 17 28,670.0 Lower Support Structure Layer 1 0.0587 Steel Structure 18 3,336.0 Ice Condenser Floor Layer 1 0.00275 Paint Layer 2 0.33 Concrete Structure 19 19,100.0 Containment Wall Panels and Containment Shell Layer 1 1.0 Steel and Insulation Layer 2 0.0625 Steel Shell Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 6 Structural Heat Sink Table Ice Condenser Area ( ft2 ) Thickness ( ft) Material Structure 20 13,055.0 Crane Wall Panels and Crane Wall Layer 1 1.0 Steel and Insulation Layer 2 1.0 Concrete Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 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 Conductiv ity Volumetric Heat Capacity Material

( Btu / hr-ft - F) ( Btu / ft3 - F)

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 Conductiv ity Volumetric Heat Capacity Material

( Btu / hr-ft - F) ( Btu / ft3 - F)

Paint (on concrete) 0.0833 28.4 Insulation (on concrete) 0.2 3.663 Concrete 0.8 28.8 Insulation (on steel) 0.15 2.75 Steel 26.0 56.4 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-6A UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 D. C. Cook Unit 1 DECL Min Containment Energy Accounting -

Blowdown Approxi mate End of Blowdown

( 10.0 sec)

Ice Heat Removal1 202.99 MBTU Structural Heat Sinks1 19.96 MBTU RHR Heat Exchanger Heat Removal1 0.0 MBTU Spray Heat Exchanger1 0.0 MBTU Energy Content of Sump2 204.21 MBTU Ice Melted 0.668 Mlbm 1

Integrated Energy 2

Sum of active and inactive sump Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-6B UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 D. C. Cook Unit 1 DECL Min Containment Energy Accounting -

Melt-Out and Peak Pressure Approxi mate Time of Approxi mate Time of Ice Melt-Out Peak Pressure

( ~ 712. 9 1 sec) 1 ( ~ 10859.3 s ec) 2 Ice Heat Removal3 576.39 MBTU 576.39 MBTU Structural Heat Sinks3 123.75 MBTU 163.27 MBTU RHR Heat Exchanger Removal3 111.22 MBTU 190.47 MBTU Spray Heat Exchanger3 118.49 MBTU 204.56 MBTU Energy Content of Sump4 549.58 MBTU 560.49 MBTU Ice Melted 2.2 Mlbm 2.2 Mlbm 1

Used 7712.9 sec 2

Used 10784.2 sec 3

Integrated Energy 4

Active Sump Unit 1

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 Unit 1 Steamline Break Mass / Energy Releases Inside Containment 30% of 3327 MWt NSSS Power, 1.4 ft2 Double-Ended Rupture, Failure - MSIV Time ( sec) Mass ( lbm / sec) Energy ( Btu / sec) 0.0 0.0 0.000E+00 0.001 9,833 1.172E+07 0.2 20,092 2.396E+07 1.0 19,499 2.327E+07 2.46 18,757 2.24J E+07 2.4601 8,928 1.068E+07 4.2 8,045 9.645E+06 4.4 8,205 9.838E+06 10.0 6,741 8.105E+06 12.4 6,276 7.551E+06 12.6 1,620 1.950E+06 19.8 1,290 1.553E+06 26.2 1,093 1.316E+06 32.6 961.4 1.157E+06 39.0 881.7 1.061E+06 45.4 835.1 1.004E+06 76.4 859.3 1.034E+06 279.8 841.1 1.012E+06 281.4 826.4 9.938E+05 283.2 787.7 9.468E+05 285.0 731.1 8.783E+05 288.6 553.6 6.630E+05 Unit 1

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 Unit 1 Steamline Break Mass / Energy Releases Inside Containment 30% of 3327 MWt NSSS Power, 1.4 ft2 Double-Ended Rupture, Failure - MSIV Time ( sec) Mass ( lbm / sec) Energy ( Btu / sec) 292.2 315.1 3.744E+05 292.8 281.6 3.340E+05 293.4 259.8 3.078E+05 294.0 252.8 2.994E+05 294.8 259.5 3.075E+05 296.2 286.1 3.395E+05 296.8 291.0 3.454E+05 301.6 282.2 3.348E+05 306.8 275.9 3.272E+05 323.2 258.4 3.062E+05 329.6 247.8 2.934E+05 340.8 216.4 2.556E+05 348.0 182.5 2.149E+05 361.2 103.5 1.208E+05 385.6 56.6 6.537E+04 1,800.6 56.3 6.502E+04 1,803.2 20.6 2.374E+04 1,803.4 0.0 0.000E+00 Unit 1

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 Unit 1 Steam line Break Mass / Energy Releases Inside Containment 100.34 % of 3327 MWt NSSS Power, 0.8 6 5 ft2 Split Break, Failure - MSIV Time ( sec) Mass ( lbm / sec) Energy ( Btu / sec) 0.0 0.0 0.000E+00 0.2 1,549.0 1.851E+06 5.2 1,456.4 1.743E+06 5.4 1,523.9 1.824E+06 9.6 1,648.5 1.969E+06 11.8 1,691.6 2.019E+06 14.0 1,706.9 2.037E+06 17.8 1,694.1 2.023E+06 22.6 1,448.0 1.735E+06 25.4 1,348.9 1.618E+06 31.2 1,196.0 1.437E+06 37.0 1,083.1 1.303E+06 42.8 995.5 1.198E+06 48.6 927.2 1.116E+06 60.2 830.4 1.000E+06 71.8 769.5 9.269E+05 83.4 728.8 8.778E+05 106.6 680.9 8.200E+05 129.8 661.2 7.962E+05 223.2 653.8 7.872E+05 238.0 567.5 6.829E+05 243.6 518.9 6.241E+05 Unit 1

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 Unit 1 Steam line Break Mass / Energy Releases Inside Containment 100.34 % of 3327 MWt NSSS Power, 0.8 6 5 ft2 Split Break, Failure - MSIV Time ( sec) Mass ( lbm / sec) Energy ( Btu / sec) 249.2 451.8 5.428E+05 254.6 368.8 4.421E+05 260.2 274.5 3.279E+05 263.0 230.4 2.745E+05 265.8 192.2 2.283E+05 268.4 161.7 1.916E+05 271.2 135.3 1.599E+05 274.0 114.8 1.353E+05 276.8 99.5 1.169E+05 279.6 87.4 1.025E+05 281.0 82.5 9.666E+04 285.2 72.8 8.510E+04 293.4 61.6 7.180E+04 299.0 58.5 6.8l 5E+04 310.0 56.5 6.580E+04 1,800.8 55.9 6.504E+04 1,807.6 15.6 l.794E+04 1,807.8 0.0 0.000E+00 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-9 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Double-Ended Rupture Steamline Breaks Power Break Size Single Failure Peak Temperature @ Time Lev el 100.34% 1.4 ft2 MSIV 323.8°F @ 55.57 sec 100.34% 1.4 ft2 AFW Runout Control 323.7°F @ 54.76 sec 70% 1.4 ft2 MSIV 323.8°F @ 12.36 sec 70% 1.4 ft2 AFW Runout Control 323.8°F @ 12.36 sec 30% 1.4 ft2 MSIV 324.3°F @ 12.36 sec 30% 1.4 ft2 AFW Runout Control 324.3°F @ 12.36 sec 0% 1.4 ft2 MSIV 320.9°F @ 131.3 sec 0% 1.4 ft2 AFW Runout Control 320.4°F @ 132.8 sec 0% 1.0 ft2 MSIV 324.5°F @ 265.4 sec 0% 1.0 ft2 AFW Runout Control 324.l °F @ 140.8 sec Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.3.4-10 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Split Steamline Breaks Power Break Size Single Failure Peak Temperature @ Time Lev el 100.34% 0.865 ft2 MSIV 324.7°F @ 96.57 sec 100.34% 0.865 ft2 AFW Runout Control 324.5°F @ 95.86 sec 70% 0.857 ft2 MSIV 324.7°F @ 72.43 sec 70% 0.857 ft2 AFW Runout Control 324.5°F @ 111.4 sec 30% 0.834 ft2 MSIV 324.6°F @ 122.9 sec 30% 0.834 ft2 AFW Runout Control 324.3°F @ 116.7 sec 0% 0.808 ft2 MSIV 324.3°F @ 142.8 sec 0% 0.808 ft2 AFW Runout Control 324.5°F @ 119.7 sec Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.1 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.

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.1 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

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 14.3.4-13 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 0.6 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

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.1 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

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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)

.35108 7.4723E+04 3.8773E+07

.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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 Common to Loop TMD Node Description Volume (ft )

3 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 (ft )

3 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 (ft )

3 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 Pressurizer Enclosure &

TMD Node Description Volume (ft )

3 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 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 Pressurizer Enclosure &

TMD Node Description Volume (ft )

3 Unique to this Steam Generator Model Enclosure Models 21 Ice Condenser 4.3400E+03 No Yes 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 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 Pressurizer Enclosure &

TMD Node Description Volume (ft )

3 Unique to this Steam Generator Model Enclosure Models 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 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 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 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 Flow Path K f LI (ft) DH (ft) AT (ft2) 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 Flow Path K f LI (ft) DH (ft) AT (ft2) 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 Flow Path K f LI (ft) DH (ft) AT (ft2) 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 Flow Path K f LI (ft) DH (ft) AT (ft2) 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 19.3 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revision: 17.1 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 Test G test/ (Total Energy/Ice Wt.) test/ Subcooling Varied in Series G 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%

Boiler Energy 100% 150% ~40 F o

Water Series 100% 200%

levels Blowdown 75% ~10oF Variable Conditions In Transient 75% 100% ~25oF Subcooled Leg Shape 100% ~10oF Series 100% ~25oF Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 17.1 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 1

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Flow ( lbm/ s) Energy ( BTUs) Flow ( lbm/ s) Energy ( BTUs) 0.00 0.00 0.00 0.00 0.00 1.00 69541.05 38072128.38 25274.17 13708526.28 2.00 59082.07 32734686.00 23523.83 13033059.18 3.00 43630.13 24731959.23 18283.46 10507768.61 4.00 35614.74 20458788.80 13731.27 7728808.39 5.00 31074.76 18041086.00 10691.77 6319115.92 6.00 28747.32 16793275.59 9608.03 5772305.39 7.00 25328.05 15318005.81 9202.82 5537586.42 8.00 20584.46 13406087.99 8493.19 5173844.80 9.00 16598.22 11561693.69 7677.87 4727423.32 10.00 13878.16 10235512.37 6945.21 4311501.04 11.00 11775.93 9157678.86 6207.16 3877731.54 12.00 10082.38 8255713.00 5513.96 3444372.92 13.00 8964.29 7114235.22 4885.53 3000354.64 14.00 9167.35 5969225.12 4181.30 2473806.33 15.00 8638.11 4897363.27 3479.19 1902292.53 16.00 8235.41 4000941.83 2913.84 1407060.24 17.00 7980.17 3354039.35 1663.75 592718.07 18.00 7652.02 2907301.23 1429.69 235952.37 19.00 7517.17 2517308.71 1548.75 222953.41 20.00 6899.28 2061869.74 1646.23 213900.65 Unit 1

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Flow ( lbm/ s) Energy ( BTUs) Flow ( lbm/ s) Energy ( BTUs) 21.00 5911.31 1611796.68 1712.29 210866.49 22.00 6186.76 1456722.22 1769.97 223369.02 23.00 4915.57 1100883.69 1838.57 232658.29 24.00 2928.20 661283.58 1850.57 242488.78 25.00 1237.20 265272.72 1854.23 238119.92 26.00 259.50 60950.94 1712.71 190109.81 27.00 259.50 60950.94 1622.04 160051.49 28.00 259.50 60950.94 1625.74 156190.40 29.00 259.50 60950.94 1496.97 140730.10 30.00 259.50 60950.94 1324.40 121410.32 31.00 259.50 60950.94 1936.18 175388.25 32.00 259.50 60950.94 1717.65 168218.37 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 32.00 0.00 0.00 0.00 0.00 32.01 259.50 60950.94 1529.62 150693.05 32.99 259.50 60950.94 1529.62 150693.05 33.00 0.68 740.84 1686.47 184224.75 33.99 0.68 740.84 1686.47 184224.75 34.00 2041.99 484024.18 681.70 218031.44 53.99 2041.99 484024.18 681.70 218031.44 54.00 936.12 348048.67 228.87 126717.15 73.99 936.12 348048.67 228.87 126717.15 74.00 133.31 92740.89 169.55 60335.44 93.99 133.31 92740.89 169.55 60335.44 94.00 200.22 113509.29 185.90 63125.74 113.99 200.22 113509.29 185.90 63125.74 114.00 434.69 160224.09 193.90 69155.68 133.99 434.69 160224.09 193.90 69155.68 134.00 496.52 171162.54 194.18 69259.58 153.99 496.52 171162.54 194.18 69259.58 154.00 484.42 164758.35 188.51 66676.60 173.99 484.42 164758.35 188.51 66676.60 174.00 341.36 126112.47 187.84 60369.74 193.99 341.36 126112.47 187.84 60369.74 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 194.00 296.67 111859.40 186.23 58202.67 213.99 296.67 111859.40 186.23 58202.67 214.00 235.07 98279.71 185.46 57878.89 233.99 235.07 98279.71 185.46 57878.89 234.00 200.80 93212.45 188.90 59963.60 253.99 200.80 93212.45 188.90 59963.60 254.00 258.35 117147.14 193.93 66361.33 273.99 258.35 117147.14 193.93 66361.33 274.00 476.25 165200.81 196.59 69750.08 323.99 476.25 165200.81 196.59 69750.08 324.00 244.12 108658.64 191.40 63004.55 373.99 244.12 108658.64 191.40 63004.55 374.00 370.40 147334.73 199.45 72649.77 423.99 370.40 147334.73 199.45 72649.77 424.00 386.48 145510.06 197.08 69708.86 473.99 386.48 145510.06 197.08 69708.86 474.00 285.56 124470.10 196.96 69050.41 523.99 285.56 124470.10 196.96 69050.41 524.00 453.97 168390.65 204.79 78240.10 573.99 453.97 168390.65 204.79 78240.10 574.00 386.29 153608.64 203.96 76553.49 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 623.99 386.29 153608.64 203.96 76553.49 624.00 307.52 134565.16 200.92 73474.29 673.99 307.52 134565.16 200.92 73474.29 674.00 434.25 166350.42 208.41 80283.50 723.99 434.25 166350.42 208.41 80283.50 724.00 362.19 146367.64 204.02 75664.94 773.99 362.19 146367.64 204.02 75664.94 774.00 368.61 148685.27 207.10 77957.47 823.99 368.61 148685.27 207.10 77957.47 824.00 400.04 157351.26 209.89 80226.97 873.99 400.04 157351.26 209.89 80226.97 874.00 377.42 153664.13 213.41 82911.40 923.99 377.42 153664.13 213.41 82911.40 924.00 374.39 153418.33 218.44 86902.02 973.99 374.39 153418.33 218.44 86902.02 974.00 316.18 137637.64 214.00 82247.70 1023.99 316.18 137637.64 214.00 82247.70 1024.00 395.90 159231.26 232.11 96590.55 1073.99 395.90 159231.26 232.11 96590.55 1074.00 379.84 158622.36 226.96 93127.19 1123.99 379.84 158622.36 226.96 93127.19 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 1124.00 312.18 141775.18 229.84 93794.70 1173.99 312.18 141775.18 229.84 93794.70 1174.00 377.80 163888.46 239.14 101396.33 1223.99 377.80 163888.46 239.14 101396.33 1224.00 318.81 151447.59 249.13 106422.61 1273.99 318.81 151447.59 249.13 106422.61 1274.00 392.11 171402.74 252.48 110393.74 1323.99 392.11 171402.74 252.48 110393.74 1324.00 304.71 143861.52 245.81 104280.95 1373.99 304.71 143861.52 245.81 104280.95 1374.00 373.43 170512.87 259.92 113873.85 1423.99 373.43 170512.87 259.92 113873.85 1424.00 291.54 148783.97 266.66 113413.92 1473.99 291.54 148783.97 266.66 113413.92 1474.00 271.78 142834.55 301.32 125478.43 1523.99 271.78 142834.55 301.32 125478.43 1524.00 229.24 131923.31 367.69 135927.28 1573.99 229.24 131923.31 367.69 135927.28 1574.00 158.10 109482.96 381.65 129932.15 1623.99 158.10 109482.96 381.65 129932.15 1624.00 116.25 84640.51 439.41 135415.35 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 1673.99 116.25 84640.51 439.41 135415.35 1674.00 115.37 87695.35 463.55 137231.27 1723.99 115.37 87695.35 463.55 137231.27 1724.00 133.08 105191.32 342.94 122912.64 1773.99 133.08 105191.32 342.94 122912.64 1774.00 77.41 76446.17 174.88 84851.57 1823.99 77.41 76446.17 174.88 84851.57 1824.00 69.01 69732.06 108.91 64882.52 1873.99 69.01 69732.06 108.91 64882.52 1874.00 62.52 63595.65 101.04 59912.47 1923.99 62.52 63595.65 101.04 59912.47 1924.00 52.86 52618.60 150.11 62536.38 2123.99 52.86 52618.60 150.11 62536.38 2124.00 47.47 44916.11 353.27 109647.01 2323.99 47.47 44916.11 353.27 109647.01 2324.00 26.36 26516.93 396.35 119506.62 2523.99 26.36 26516.93 396.35 119506.62 2524.00 4.33 4793.89 397.58 120954.33 2723.99 4.33 4793.89 397.58 120954.33 2724.00 0.38 419.09 398.10 115923.21 2923.99 0.38 419.09 398.10 115923.21 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 2924.00 7.64 3014.99 395.39 110002.00 3123.99 7.64 3014.99 395.39 110002.00 3124.00 119.76 30193.40 391.10 102294.41 3323.99 119.76 30193.40 391.10 102294.41 3324.00 3.48 2944.70 386.15 105742.93 3523.99 3.48 2944.70 386.15 105742.93 3524.00 38.19 9859.87 391.32 102943.28 3723.99 38.19 9859.87 391.32 102943.28 3724.00 130.64 25508.17 369.45 92730.58 3923.99 130.64 25508.17 369.45 92730.58 3924.00 30.33 6084.03 367.85 92571.63 4123.99 30.33 6084.03 367.85 92571.63 4124.00 5.48 1045.09 335.02 96823.53 4323.99 5.48 1045.09 335.02 96823.53 4324.00 0.05 57.80 141.02 65695.50 4523.99 0.05 57.80 141.02 65695.50 4524.00 0.00 4.51 118.72 61254.09 4723.99 0.00 4.51 118.72 61254.09 4724.00 0.03 33.96 116.23 59526.42 4923.99 0.03 33.96 116.23 59526.42 4924.00 0.02 25.81 128.46 61201.15 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 5123.99 0.02 25.81 128.46 61201.15 5124.00 0.03 36.50 131.84 61294.88 5323.99 0.03 36.50 131.84 61294.88 5324.00 0.02 17.94 126.24 59042.74 5523.99 0.02 17.94 126.24 59042.74 5524.00 0.04 41.56 129.55 58830.68 5723.99 0.04 41.56 129.55 58830.68 5724.00 0.03 31.33 134.85 59411.87 5923.99 0.03 31.33 134.85 59411.87 5924.00 0.03 29.55 131.44 58352.90 6123.99 0.03 29.55 131.44 58352.90 6124.00 0.02 17.62 128.74 57416.45 6323.99 0.02 17.62 128.74 57416.45 6324.00 0.05 51.96 125.70 55976.66 6523.99 0.05 51.96 125.70 55976.66 6524.00 0.03 31.58 133.51 57429.33 6723.99 0.03 31.58 133.51 57429.33 6724.00 0.03 35.97 149.80 60217.58 6923.99 0.03 35.97 149.80 60217.58 6924.00 0.08 80.78 135.08 56705.62 7123.99 0.08 80.78 135.08 56705.62 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 7124.00 0.09 91.71 155.80 60313.85 7323.99 0.09 91.71 155.80 60313.85 7324.00 0.13 138.16 141.47 56394.37 7523.99 0.13 138.16 141.47 56394.37 7524.00 0.12 131.00 138.72 55837.43 7723.99 0.12 131.00 138.72 55837.43 7724.00 0.10 105.77 129.96 53973.77 7923.99 0.10 105.77 129.96 53973.77 7924.00 0.10 112.89 129.87 53807.18 8123.99 0.10 112.89 129.87 53807.18 8124.00 0.08 90.35 127.90 53613.33 8323.99 0.08 90.35 127.90 53613.33 8324.00 0.08 87.92 127.23 52915.15 8523.99 0.08 87.92 127.23 52915.15 8524.00 0.07 80.67 133.71 53881.36 8723.99 0.07 80.67 133.71 53881.36 8724.00 0.10 108.62 128.32 52436.24 8923.99 0.10 108.62 128.32 52436.24 8924.00 0.07 74.12 128.65 51886.80 9123.99 0.07 74.12 128.65 51886.80 9124.00 0.07 72.73 126.79 50967.27 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 9323.99 0.07 72.73 126.79 50967.27 9324.00 0.07 80.57 131.32 52068.57 9523.99 0.07 80.57 131.32 52068.57 9524.00 0.04 41.48 130.54 51729.07 9723.99 0.04 41.48 130.54 51729.07 9724.00 0.04 46.40 130.89 51085.18 9923.99 0.04 46.40 130.89 51085.18 9924.00 0.05 58.80 128.33 50241.49 10123.99 0.05 58.80 128.33 50241.49 10124.00 0.06 61.68 125.64 49433.24 10323.99 0.06 61.68 125.64 49433.24 10324.00 0.08 81.57 128.99 49735.65 10523.99 0.08 81.57 128.99 49735.65 10524.00 0.06 61.92 123.27 49377.78 10723.99 0.06 61.92 123.27 49377.78 10724.00 0.03 38.01 126.86 50355.47 10923.99 0.03 38.01 126.86 50355.47 10924.00 0.01 11.49 137.91 51858.61 11123.99 0.01 11.49 137.91 51858.61 11124.00 0.01 8.70 134.26 51017.92 11323.99 0.01 8.70 134.26 51017.92 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 11324.00 0.00 1.44 129.31 49922.57 11523.99 0.00 1.44 129.31 49922.57 11524.00 0.02 16.85 132.54 50146.44 11723.99 0.02 16.85 132.54 50146.44 11724.00 0.02 18.24 128.57 49163.67 11923.99 0.02 18.24 128.57 49163.67 11924.00 0.00 4.62 130.65 49597.79 12123.99 0.00 4.62 130.65 49597.79 12124.00 0.03 28.53 129.02 48868.44 12323.99 0.03 28.53 129.02 48868.44 12324.00 0.02 19.81 130.04 48901.11 12523.99 0.02 19.81 130.04 48901.11 12524.00 0.01 12.25 134.80 49660.73 12723.99 0.01 12.25 134.80 49660.73 12724.00 0.01 7.23 127.80 48290.41 12923.99 0.01 7.23 127.80 48290.41 12924.00 0.01 10.91 125.73 47420.18 13123.99 0.01 10.91 125.73 47420.18 13124.00 0.04 46.45 128.02 47720.36 13323.99 0.04 46.45 128.02 47720.36 13324.00 0.02 16.88 132.33 48157.60 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 13523.99 0.02 16.88 132.33 48157.60 13524.00 0.01 13.41 127.37 47643.24 13723.99 0.01 13.41 127.37 47643.24 13724.00 0.00 5.24 130.37 47699.14 13923.99 0.00 5.24 130.37 47699.14 13924.00 0.02 16.45 134.24 48251.35 14123.99 0.02 16.45 134.24 48251.35 14124.00 0.02 21.22 129.17 46980.21 14323.99 0.02 21.22 129.17 46980.21 14324.00 0.01 11.57 133.56 47728.45 14523.99 0.01 11.57 133.56 47728.45 14524.00 0.01 6.58 133.44 47914.23 14723.99 0.01 6.58 133.44 47914.23 14724.00 0.01 8.04 127.32 46612.04 14923.99 0.01 8.04 127.32 46612.04 14924.00 0.03 34.06 125.18 46638.62 15123.99 0.03 34.06 125.18 46638.62 15124.00 0.03 37.42 131.51 47737.44 15323.99 0.03 37.42 131.51 47737.44 15324.00 0.06 59.86 125.41 45532.79 15523.99 0.06 59.86 125.41 45532.79 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 15524.00 0.04 45.91 135.23 48010.88 15723.99 0.04 45.91 135.23 48010.88 15724.00 0.00 3.96 123.62 46113.24 15923.99 0.00 3.96 123.62 46113.24 15924.00 0.02 16.75 128.65 47155.70 16123.99 0.02 16.75 128.65 47155.70 16124.00 0.01 6.96 119.16 44750.70 16323.99 0.01 6.96 119.16 44750.70 16324.00 0.03 33.10 123.17 45506.51 16523.99 0.03 33.10 123.17 45506.51 16524.00 0.04 39.51 124.63 45408.22 16723.99 0.04 39.51 124.63 45408.22 16724.00 0.03 36.72 123.75 45355.16 16923.99 0.03 36.72 123.75 45355.16 16924.00 0.06 64.79 122.55 44988.95 17123.99 0.06 64.79 122.55 44988.95 17124.00 0.20 215.56 121.50 44510.42 17323.99 0.20 215.56 121.50 44510.42 17324.00 0.17 181.30 122.31 44511.93 17523.99 0.17 181.30 122.31 44511.93 17524.00 0.03 36.66 124.99 44587.89 Unit 1

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( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 17723.99 0.03 36.66 124.99 44587.89 17724.00 0.06 60.54 133.59 45884.13 17923.99 0.06 60.54 133.59 45884.13 17924.00 0.06 61.86 126.30 44629.85 18123.99 0.06 61.86 126.30 44629.85 18124.00 0.07 74.52 130.94 45415.03 18323.99 0.07 74.52 130.94 45415.03 18324.00 0.04 44.35 130.07 44954.87 18523.99 0.04 44.35 130.07 44954.87 18524.00 0.04 47.62 128.95 44951.28 18723.99 0.04 47.62 128.95 44951.28 18724.00 0.04 41.48 129.30 44821.25 18923.99 0.04 41.48 129.30 44821.25 18924.00 0.05 52.31 128.49 44598.03 19123.99 0.05 52.31 128.49 44598.03 19124.00 0.03 33.80 130.54 44857.31 19323.99 0.03 33.80 130.54 44857.31 19324.00 0.03 37.93 127.77 44246.79 19523.99 0.03 37.93 127.77 44246.79 19524.00 0.05 50.35 127.73 43920.88 19723.99 0.05 50.35 127.73 43920.88 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.3.4-42 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 14 of 14 DECL Minimum Safeguards Post-Blowdown Mass & Energy Break Path 1 Break Path 2 Time

( sec) Flow Energy Flow Energy

( lbm/ s) ( BTUs) ( lbm/ s) ( BTUs) 19724.00 0.03 31.33 130.55 44661.27 19924.00 0.03 31.33 130.55 44661.27 19924.1 0.06 11.81 130.84 44121.56 40000.0 88.46 16065.35 42.44 23087.88 60000.0 103.48 16013.02 27.42 20560.47 78272.0 108.62 14140.93 22.28 20897.30 78272.1 110.03 14323.78 20.87 19579.55 80000.0 110.34 14108.51 20.56 19650.11 89179.0 111.59 12891.10 19.31 20285.50 89179.1 111.94 12931.90 18.96 19914.41 100000.0 113.05 11415.34 17.85 20745.13 Unit 1

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 Break Mass / Energy Releases for Unit 1 Parameter1 Parameter Value NSSS Power, MWt 3,327 Core Power, MWt 3,304 RCS Flowrate (total), gpm 354,000 (Thermal Design Flow)

Pressurizer Pressure psia 2,250 Pressurizer Water Vol ume, % span 56.06 RCS Vessel Average Temperature, °F 575.4 Steam Generator2 Steam Temperature, °F 527.9 Steam Pressure, psia 870 Feedwater Temperature, °F 437.4 Water Level, % narrow-range span 43.8 Zero-Load Temperature, °F 547 1

Nominal parameters are listed in this table.

2 Steam generator performance data used in the analysis is conservatively high for steam temperature and pressure.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.3.5-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 5 Parameters Used for the Radiological Conseq uence Analysis of a Loss of Coolant Accident Parameter Value Core Power Level 3480 MWt Containment Purge Release Containment Volume 1,066,352 ft3 (minimum)

Iodine Chemical Form Elemental 4.85%

Organic 0.15%

Particulate 95%

Containment Purge Flow Rate 36,300 cfm Containment Purge Isolation time 15 seconds Containment Purge Filtration 0%

Removal by Wall Deposition None Removal by Sprays None Release Location Offsite Unit 1 Vent Onsite Unit 2 Vent Containment Leakage Release Containment Compartment Volumes(max)

Upper Containment (Sprayed) 621,968 ft3 Lower Containment (Sprayed) 103,770 ft3 Fan Rooms (Sprayed) 48,913 ft3 Upper Containment (Unsprayed) 122,600 ft3 Ice Condenser (Unsprayed) 105,577 ft3 Lower Containment (Unsprayed) 66,188 ft3 Dead-End (Unsprayed) 18,663 ft3 Containment Ventilation Flow Rates Fan Rooms to Lower Containment (Unsprayed) 14,580.5 cfm Fan Rooms to Lower Containment (Sprayed) 22,859.5 cfm Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.3.5-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 5 Parameters Used for the Radiological Conseq uence Analysis of a Loss of Coolant Accident Parameter Value Lower Containment (Unsprayed) to Dead-End 90 cfm Dead-End to Fan Rooms 90 cfm Lower Containment (Unsprayed) to Fan Rooms 1,350 cfm Lower Containment (Unsprayed) to Ice Condenser 13,140.5 cfm Lower Containment (Sprayed) to Ice Condenser 22,859.5 cfm Ice Condenser to Upper Containment (Sprayed) 30,072.3 cfm Ice Condenser to Upper Containment (Unsprayed) 5,927.7 cfm Upper Containment (Sprayed) to Fan Rooms 30,072.3 cfm Upper Containment (Unsprayed) to Fan Rooms 5,927.7 cfm Lower Containment - Sprayed to/from Unsprayed 2,206.3 cfm (spray induced circulation)

Upper Containment - Sprayed to/from Unsprayed 4,086.7 cfm (spray induced circulation)

Containment Spray Start Time 300 seconds Time that Containment Spray is Secured 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Containment Spray Flow Rate Upper Containment 1,466 gpm Lower Containment 660 gpm Fan Rooms 201 gpm Elemental Iodine Removal Coefficients Upper Containment 20 hr-1 Lower Containment 20 hr-1 Fan Rooms 20 hr-1 Time that Total Elemental DF Reaches 200 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Aerosol Spray Removal Coefficient Upper Containment 5.06 hr-1 Lower Containment 6.65 hr-1 Fan Rooms 3.03 hr-1 Time that Total Aerosol DF Reaches 50 2.32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.3.5-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 5 Parameters Used for the Radiological Conseq uence Analysis of a Loss of Coolant Accident Parameter Value Natural Deposition Elemental Iodine None Organic Iodine None Particulates 0.1 hr-1 Containment Leakage Rate 0-24 hours 0.18 %/day 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s-30 days 0.09 Containment Leakage Filtration 0%

Iodine Chemical Form Elemental 4.85%

Organic 0.15%

Particulate 95%

Iodine/Particulate Removal by Containment Sprays None Release Location Offsite Unit 1 Containment Surface Onsite Unit 2 Containment Surface ESF Leakage Release to the Aux iliary Building Containment Sump Volume 50,955 ft3 ECCS Recirculation Start Time 1,388.4 seconds Effective ESF Leakage Flow Rate 0.2 gpm ESF Leakage Flashing Fraction 10%

Auxiliary Building Ventilation Filtration 0%

Iodine Chemical Form Elemental 97%

Organic 3%

Particulate 0%

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.3.5-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 5 Parameters Used for the Radiological Conseq uence Analysis of a Loss of Coolant Accident Parameter Value Release Location Offsite Unit 1 Vent Onsite Unit 2 Vent ESF Leakage Release to the RWST Containment Sump Volume 50,955 ft3 ECCS Recirculation Start Time 1,388.4 seconds Effective ESF Leakage Flow Rate 1.0 gpm Total Iodine Mass Released into the Sump 12,035.5 grams Sump pH 7.0 Initial RWST pH 4.479 Initial RWST Liquid Volume 53,637.5 gallons Elemental Iodine Release Fraction 0.0-0.1914 Organic Iodine Release Fraction 0.0015 RWST Liquid/Vapor Iodine Partition Coefficient Elemental 31.92 - 45.41 Organic 1.0 Release Location Offsite Unit 1 RWST Onsite Unit 2 RWST Offsite Breathing Rates 0-8 hours 3.5E-04 m3/sec 8-24 hours 1.8E-04 m3/sec 24-720 hours 2.3E-04 m3/sec Control Room Parameters Volume 50,616 ft3 Normal Ventilation Makeup Flow Rate 880 cfm Emergency Ventilation Makeup Flow Rate 880 cfm Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.3.5-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 5 Parameters Used for the Radiological Conseq uence Analysis of a Loss of Coolant Accident Parameter Value Emergency Ventilation Recirculation Flow Rate 4,520 cfm 1

Emergency Ventilation Filter Efficiency Elemental Iodine 94.05%

Organic Iodine 94.05%

Particulates 98.01%

Delay to Switch to Emergency Mode 70 minutes (Safety Injection)

Unfiltered Inleakage 40 cfm Occupancy Factors 0-24 hours 1.0 24-96 hours 0.6 96-720 hours 0.4 Breathing Rate 3.5E-04 m3/sec 1

Includes 1% filter bypass leakage Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.3.9-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 D.C. COOK MAAP 14-NODE CONTAINMENT NODALIZATION Node Region 1 Cavity 2 Lower Compartment 3 Pipe Annulus Region 4 Ice Condenser 5 Ice Condenser Upper Plenum 6 Cylindrical Section of Upper Compartment 7 Lower Dome of Upper Compartment 8 Upper Dome of Upper Compartment 9 Pressurizer Enclosure 10 Steam Generator 1/4 Enclosure 11 Steam Generator 2/3 Enclosure 12 East Fan Room 13 West Fan Room 14 Instrument Room Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.3.9-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 D.C. COOK MAAP 14-NODE CONTAINMENT MODEL FLOW JUNCTIONS Junction Type Description 1 AO1 Cavity 6 Lower Compartment (Bypass Tunnel) 2 AO Cavity 6 Lower Compartment (Annular Gap)

Lower Compartment 6 Upper Cylindrical Sec. (Refueling Cavity 3 AO Drains) 4 UD2 Lower Compartment 6 Ice Condenser (Door Model) 5 AO Lower Compartment 6 Pipe Annulus (over Weir Wall) 6 UD Ice Condenser 6 Ice Upper Plenum 7 AO Lower Compartment 6 Upper Cylindrical Section (Bypass) 8 Fan Upper Cylindrical Section 6 West Fan Room (Cont. Air Recirc.)

9 OOAO3 Ice Upper Plenum 6 Upper Compartment Lower Dome 10 AO Normal Cont. Leakage (Pipe Annuls 6 Env.)

11 OOAO Cont. Failure (Pipe Annulus 6 Env.)

12 AO Lower Compartment 6 PZR Enclosure 13 AO Lower Compartment 6 SG 1/4 Enclosure 14 AO Upper Compartment Lower Dome 6 Upper Dome 15 AO Upper Cylinder Section 6 Upper Compartment Lower Dome 16 Fan PZR Enclosure 6 East Fan Room (H2 Skimmer) 1 AO Always Open - means junction is always open and flow may occur in either direction as well as counter-current natural circulation flow when applicable.

2 UD Uni-Directional - means that the junction performs like a check valve and only permits flow in one direction, as well as counter-current flow if the junction is open due to uni-directional flow.

3 OOAO Once Opened Always Open - means that once a sufficient pressure differential is developed to open the junction, it remains open thereafter regardless of the pressure differential.

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.3.9-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 D.C. COOK MAAP 14-NODE CONTAINMENT MODEL FLOW JUNCTIONS Junction Type Description 17 Fan SG 1&4 Enclosure 6 East Fan Room (H2 Skimmer) 18 Fan Upper Dome 6 East Fan Room (H2 Skimmer) 19 UD Ice Condenser 6 Lower Compartment (Flappers) 20 AO Ice Condenser 6 Lower Compartment. (Drain Line) 21 AO Lower Compartment 6 SG 2/3 Enclosure 22 Fan SG 2/3 Enclosure 6 East Fan Room (H2 Skimmer) 23 Fan Instrument Room 6 East Fan Room (H2 Skimmer) 24 Fan West Fan Room 6 East Fan Room (H2 Skimmer) 25 Fan Upper Cylinder Section 6 East Fan Room (Containment Air Recirc.)

26 Fan PZR 6 West Fan Room (H2 Skimmer) 27 Fan SG 1/4 Enclosure 6 West Fan Room (H2 Skimmer) 28 Fan SG 2/3 Enclosure 6 West Fan Room (H2 Skimmer) 29 Fan Instrument Room 6 West Fan Room (H2 Skimmer) 30 Fan Upper Dome 6 West Fan Room (H2 Skimmer) 31 Fan East Fan Room 6 West Fan Room (H2 Skimmer) 32 AO East Fan Room 6 Pipe Annulus (Floor Holes) 33 AO West Fan Room 6 Pipe Annulus (Floor Holes) 34 AO Instrument Room 6 Pipe Annulus (Floor Holes) 35 AO East Fan Room 6 Lower Compartment (Fan Windows) 36 AO West Fan Room 6 Lower Compartment (Fan Windows) 37 AO East Fan Room 6 Instrument Room (Wall Openings) 38 AO West Fan Room 6 Instrument Room (Wall Openings) 39 AO Instrument Room 6 Lower Compartment 40 AO Ice Upper Plenum 6 Upper Cylindrical Section (Bypass Area) 41 AO Ice Condenser 6 Ice Upper Plenum (Bypass Area)

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.3.9-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 D.C. COOK MAAP 14-NODE CONTAINMENT MODEL FLOW JUNCTIONS Junction Type Description 42 AO Lower Compartment 6 Pipe Annulus (Holes in Weir Wall) 43 AO Lower Compartment 6 Rx Cavity (NIS Holes) 44 AO Lower Compartment 6 Rx Cavity (NIS Holes)

Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 BOUNDING INSULATION QUANTITIES BY POTENTIAL BREAK LOCATION Transco RMI, DP RMI, Cal-Sil, Fiberglass, Marinite, Min-K, ft2 ft2 ft3 ft3 ft3 ft3 Lower Containment - Inside Crane Wall - Loop 1 -- 39,530 348 -- 2.09 --

Lower Containment - Inside Crane Wall - Loop 2 -- 42,542 326 -- 0.61 0.18 Lower Containment - Inside Crane Wall - Loop 3 -- 43,828 352 -- 7.05 0.08 Lower Containment - Inside Crane Wall - Loop 4 -- 39,443 401 -- 2.56 --

Lower Containment - Inside Crane Wall - PZR Vault area -- 19,942 121 -- -- --

Reactor Cavity 19,802 -- -- 5 -- --

Total 19,802 185,285 1,548 5 12.31 0.26 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 DEGB COATINGS DEBRIS GENERATED WITHIN ZOI Coating Type Area, ft2 Thickness, mils Volume, ft3 Density, lbs/ft3 Weight, lbs Qualified Coatings - Concrete Surfaces (ZOI - 5D) 894 12 0.894 111.6 99.8 Qualified Coatings - Steel Surfaces (ZOI - 5D) 1,007 12 1.007 111.6 112.7 Total Qualified (ZOI - 5D) 1,901 - 1.90 - 212.5 Unqualified Alkyd Coatings (ZOI - 10D) 57.7 4 0.019 98 1.9 Unqualified Epoxy Coatings (ZOI - 10D) 112.0 4 0.037 94 3.5 Total Unqualified (ZOI - 10D) 169.7 - 0.056 - 5.4 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 DGBS COATINGS DEBRIS GENERATED WITHIN ZOI Coating Type Area, ft2 Thickness, mils Volume, ft3 Density, lbs/ft3 Weight, lbs Qualified Coatings - Concrete Surfaces (ZOI - 5D) 0 12 0.0 111.6 0.0 Qualified Coatings - Steel Surfaces (ZOI - 5D) 20 12 0.02 111.6 2.2 Total Qualified (ZOI - 5D) 20 - 0.02 - 2.2 Unqualified Alkyd Coatings (ZOI - 10D) 16.9 4 0.006 98 0.6 Unqualified Epoxy Coatings (ZOI - 10D) 56.0 4 0.019 94 1.8 Total Unqualified (ZOI - 10D) 72.9 - 0.025 - 2.4 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-6 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 UNQUALIFIED COATINGS DEBRIS GENERATED OUTSIDE ZOI Area, Thickness, Volume, Density, Weight, Coating Type ft2 mils ft3 lbs/ft3 lbs Unqualified OEM Alkyd Handwheels and Limitorque Coatings outside 10D ZOI 1,429.5 4 0.48 98 47.0 Remaining Unqualified OEM Alkyd Coatings outside 10D ZOI 841.7 4 0.28 98 27.4 Remaining Unqualified OEM Epoxy Coatings outside 10D ZOI 538.0 4 0.18 94 16.9 Unqualified non-OEM Alkyd Coatings outside 10D ZOI 105.8 4 0.035 98 3.4 Unqualified non-OEM Epoxy Coatings outside 10D ZOI 991.2 4 0.33 94 31.0 Cold Galvanizing Compound 9,324.98 4 3.11 250 777.5 Total Unqualified 13,231.18 - 4.415 - 903.2 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-7 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 LATENT DEBRIS LOCATION UNIT 1 AND UNIT 2 BOUNDING VALUES Upper Loop Debris Type Pipe Annulus Ice Condenser Total Containment Compartment Latent Fiber, lbs 5.4 15.6 8.4 0.6 30 Latent Dirt/Dust, lbs 30.6 88.4 47.6 3.4 170 Electromark Labels - break in Loop 1

-- 21.8 30.48 -- 52.28 or Loop 4, ft2 Electromark Labels - break in Loop 2

-- 20.14 30.48 -- 50.62 or Loop 3, ft2 Unqualified Labels, ft2 8.77 13.62 3.55 -- 25.94 Flexible Conduit PVC Jacketing, ft2 -- 1.57 -- -- 1.57 Fire Barrier Tape, ft2 -- 708.83 -- -- 708.83 Ice Storage Bag Fibers, ft2 -- -- -- 5.0 5.0 Ice Storage Bag Liner Shards, ft2 -- -- -- 0.87 0.87 Pieces of Rubber from platform

-- -- -- 0.22 0.22 where ice bags were opened, ft2 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-8 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 CONTAINMENT MATERIALS Submerged Aluminum Metal (Below El. 614 ft) Mass, lb Area, ft2 Electrical Equipment (Limit Switches) 1.5 0.44 Fans and Motors 2.31 3.67 Radiation Detectors 0.72 0.36 Miscellaneous Components 17.72 6.46 NSSS Components (NRI-32,-36,-41A thru -44B) - Located in 244.00 83.00 Reactor Cavity TOTAL - Including Components in Reactor Cavity 266.25 93.93 TOTAL - Excluding NSSS Components in Reactor Cavity 22.25 10.93 Non-submerged Aluminum Metal (Above El. 614 ft) Mass, lb Area, ft2 Electrical Equipment 0.80 0.81 Radiation Detectors 0.03 0.06 Valve Components 8.00 2.47 Crane Components 1.05 0.72 Miscellaneous Components 22.97 9.33 NSSS Components (RCP Cooling Coils) 1,152.00 8,000.00 TOTAL 1,184.85 8,013.39 Uncoated Concrete (Exposed Concrete) Area, ft2 Submerged (Below El. 614 ft) 6,412.78 Non-submerged (Above El. 614 ft) 1,077.10 Zinc Coated Steel (Below El. 614 ft) Area, ft2 Galvanized Steel (Below El. 614 ft) 70,831.64 Cold Zinc Coated Steel (Below El. 614 ft) 330.98 Total submerged zinc coated steel 71,162.62 Zinc Coated Steel (Above 614 ft) Area, ft2 Galvanized Steel (Above El. 614 ft) 495,734.96 Cold Zinc Coated Steel (Above El. 614 ft) 8994.00 Total non-submerged zinc coated steel 504,728.96 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-9 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 MAXIMUM ECCS/CTS FLOW RATES ECCS/CTS Phase Maximum ECCS/CTS Flow Injection Phase - RWST Drawdown 15,500 gpm Recirculation Phase 14,400 gpm UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-10 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 LOOP 4 RCS CROSSOVER LEG BREAK (DEGB) DEBRIS LOADS AT THE MAIN STRAINER AND REMOTE STRAINER Debris Load at Main Strainer Overall Debris Load Overall Debris Load Debris Type at End of Pool Fill Phase at Main Strainer at Remote Strainer RMI Small Pieces, ft2 5267.52 7608.64 0 RMI Large Pieces, ft2 975.5 1560.8 0 Cal-Sil Fines, lbs 89.568 123.156 133.904 Erosion of Cal-Sil Small Pieces to fines, lbs 0 23.2 18.56 Cal-Sil Small Pieces, lbs 11.6 23.2 0 Marinite I fines, lbs 0.0448 0.0616 0.0728 Erosion of Marinite I Small Pieces to fines, lbs 0 0.005 0.004 Marinite I Small Pieces, lbs 0.0025 0.005 0 Erosion of Marinite I Large Pieces to fines, lbs 0 0.0322 0.0138 Marinite I Large Pieces, lbs 0.0092 0.0161 0 Marinite 36 fines, lbs 0.3456 0.4752 0.5616 Erosion of Marinite 36 Small Pieces to fines, lbs 0 0.036 0.0288 Marinite 36 Small Pieces, lbs 0.018 0.036 0 Erosion of Marinite 36 Large Pieces to fines, lbs 0 0.3024 0.1296 Marinite 36 Large Pieces, lbs 0.0864 0.1512 0 Min-K, lbs 0.512 0.704 0.832 Epoxy Paint (inside ZOI), lbs 69.12 95.04 112.32 Alkyd Paint (inside ZOI), lbs 0.608 0.836 0.988 Unqualified OEM Epoxy (outside ZOI), lbs 0 6.76 12.168 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-10 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 LOOP 4 RCS CROSSOVER LEG BREAK (DEGB) DEBRIS LOADS AT THE MAIN STRAINER AND REMOTE STRAINER Debris Load at Main Strainer Overall Debris Load Overall Debris Load Debris Type at End of Pool Fill Phase at Main Strainer at Remote Strainer Unqualified OEM Alkyd (outside ZOI), lbs 0 10.416 66.96 Unqualified Non-OEM Epoxy (outside ZOI), lbs 0 16.12 0 Unqualified Non-OEM Alkyd (outside ZOI), lbs 0 1.972 2.006 Unqualified Cold Galvanizing Compound, lbs 0 723.075 272.125 Dirt/Dust, lbs 40.8 88.4 95.2 Latent Fiber, ft3 3.00 6.5 7 Fire Proof Tape Fines, ft2 8.032 11.044 13.052 Fire Proof Tape Small Pieces, ft2 1.296 1.872 0 Fire Proof Tape Large Pieces, ft2 4.869 7.033 0 Ice Storage Bag Fibers, ft3 0.0117 0.01638 0.01092 Ice Storage Bag Liner Shards, ft3 0.000099 0.0001386 0.0000924 Pieces of Work Platform Rubber, ft3 0.0009 0.00126 0.00084 Electromark Label (inside ZOI), ft2 0.063 0.091 0.329 Electromark Label (outside ZOI), ft2 0 1.188 27.324 Unqualified Labels - Paper, ft2 0 0.2408 0.112 Unqualified Labels - Other, ft2 0 22.0676 10.264 Flex Conduit PVC Jacketing, ft2 0 1.57 0.471 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-11 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 LOOP 4 ALTERNATE RCS LOOP PIPING BREAK (DGBS) DEBRIS LOADS AT THE MAIN STRAINER AND REMOTE STRAINER Debris Load at Main Strainer Overall Debris Load Overall Debris Load Debris Type at End of Pool Fill Phase at Main Strainer at Remote Strainer RMI Small Pieces, ft2 2791.89 4032.73 0 RMI Large Pieces, ft2 517.05 827.28 0 Cal-Sil Fines, lbs 23.2 31.9 34.684 Erosion of Cal-Sil Small Pieces to fines, lbs 0 4.64 3.712 Cal-Sil Small Pieces, lbs 2.32 4.64 0 Marinite I fines, lbs 0 0 0 Erosion of Marinite I Small Pieces to fines, lbs 0 0 0 Marinite I Small Pieces, lbs 0 0 0 Erosion of Marinite I Large Pieces to fines, lbs 0 0 0 Marinite I Large Pieces, lbs 0 0 0 Marinite 36 fines, lbs 0.2528 0.3476 0.4108 Erosion of Marinite 36 Small Pieces to fines, lbs 0 0.03 0.024 Marinite 36 Small Pieces, lbs 0.015 0.03 0 Erosion of Marinite 36 Large Pieces to fines, lbs 0 0.2268 0.0972 Marinite 36 Large Pieces, lbs 0.0648 0.1134 0 Min-K, lbs 0 0 0 Epoxy Paint (inside ZOI), lbs 1.824 2.508 2.964 Alkyd Paint (inside ZOI), lbs 0.608 0.836 0.988 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-11 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 LOOP 4 ALTERNATE RCS LOOP PIPING BREAK (DGBS) DEBRIS LOADS AT THE MAIN STRAINER AND REMOTE STRAINER Debris Load at Main Strainer Overall Debris Load Overall Debris Load Debris Type at End of Pool Fill Phase at Main Strainer at Remote Strainer Unqualified OEM Epoxy (outside ZOI), lbs 0 6.76 12.168 Unqualified OEM Alkyd (outside ZOI), lbs 0 10.416 66.96 Unqualified Non-OEM Epoxy (outside ZOI), lbs 0 16.12 0 Unqualified Non-OEM Alkyd (outside ZOI), lbs 0 1.972 2.006 Unqualified Cold Galvanizing Compound, lbs 0 723.075 272.125 Dirt/Dust, lbs 40.8 88.4 95.2 Latent Fiber, ft3 3 6.5 7 Fire Proof Tape Fines, ft2 8.032 11.044 13.052 Fire Proof Tape Small Pieces, ft2 1.296 1.872 0 Fire Proof Tape Large Pieces, ft2 4.869 7.033 0 Ice Storage Bag Fibers, ft3 0.0117 0.01638 0.01092 Ice Storage Bag Liner Shards, ft3 0.000099 0.0001386 0.0000924 Pieces of Work Platform Rubber, ft3 0.0009 0.00126 0.00084 Electromark Label (inside ZOI), ft2 0.063 0.091 0.329 Electromark Label (outside ZOI), ft2 0 1.188 27.324 Unqualified Labels - Paper, ft2 0 0.2408 0.112 Unqualified Labels - Other, ft2 0 22.0676 10.264 Flex Conduit PVC Jacketing, ft2 0 1.57 0.471 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-12 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 QUANTITY OF DEBRIS AT MAIN STRAINER FOR LARGE SCALE TESTING FOR DEGB AND DGBS DEGB Test DGBS Test Debris Type Units Quantity Quantity RMI ft2 221.09 118.98 Cal-Sil Fines lbs 3.50 0.87 Marinite I Fines lbs 0.002 0 Marinite 36 Fines lbs 0.02 0.01 Min-K lbs 0.02 0 Epoxy Paint (inside ZOI) lbs 2.25 0.04 Alkyd Paint (inside ZOI) lbs 0.01 0.00 Unqualified OEM Epoxy (outside ZOI) lbs 0.17 0.17 Unqualified OEM Alkyd (outside ZOI) lbs 0.26 0.26 Unqualified Non-OEM Epoxy (outside ZOI) lbs 0.20 0.20 Unqualified Non-OEM Alkyd (outside ZOI) lbs 0.05 0.05 Unqualified Cold Galvanizing Compound lbs 17.64 18 Dirt/Dust lbs 2.57 2.57 Latent Fiber ft3 0.19 0.19 Fire Proof Tape Fines ft3 0.001 0.001 3

Ice Storage Bag Fibers ft 0.0004 0.0004 Ice Storage Bag Liner Shards ft3 0.0000 0.0000 3

Pieces of Work Platform Rubber ft 0.0000 0.0000 1 3 Fire Proof Tape Pieces ft 0.002 0.002 Electromark Label (inside ZOI) (1) ft2 0.003 0.003 (1) 2 Electromark Label (outside ZOI) ft 0.07 0.07 Unqualified Labels (1) ft2 0.61 0.61 Flex Conduit PVC Jacketing (1) ft2 0.04 0.04 1

These debris materials were included in the sacrificial strainer area.

UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-13 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 QUANTITY OF DEBRIS AT REMOTE STRAINER FOR LARGE SCALE TESTING FOR DEGB AND DGBS DEGB Test DGBS Test Debris Type Units Quantity Quantity RMI ft2 0 0 Cal-Sil Fines lbs 4.003 1.010 Marinite I Fines lbs 0.002 0 Marinite 36 Fines lbs 0.018 0.013 Min-K lbs 0.020 0 Epoxy Paint (inside ZOI) lbs 2.718 0.051 Alkyd Paint (inside ZOI) lbs 0.008 0.008 Unqualified OEM Epoxy (outside ZOI) lbs 0.309 0.309 Unqualified OEM Alkyd (outside ZOI) lbs 1.655 1.655 Unqualified Non-OEM Epoxy (outside ZOI) lbs 0 0 Unqualified Non-OEM Alkyd (outside ZOI) lbs 0.052 0.052 Unqualified Cold Galvanizing Compound lbs 6.637 6.637 Dirt/Dust lbs 1.783 1.783 Latent Fiber ft3 0.131 0.131 3

Fire Proof Tape Fines ft 0.001 0.001 3

Ice Storage Bag Fibers ft 0.0003 0.0003 Ice Storage Bag Liner Shards ft3 0.0000 0.0000 3

Pieces of Work Platform Rubber ft 0.0000 0.0000 Fire Proof Tape Pieces 1 ft3 0.010 0.010 Electromark Label (inside ZOI) (1) ft2 0.010 0.010 (1) 2 Electromark Label (outside ZOI) ft 0.453 0.453 Unqualified Labels (1) ft2 0.209 0.209 Flex Conduit PVC Jacketing(1) ft2 0.011 0.011 1

These debris materials were included in the sacrificial strainer area.

UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-14 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 DEBRIS QUANTITIES FOR MFTL HEAD LOSS TESTS Mass Mass Debris Type Units Test 1 (DEGB) Test 2 (DGBS)

Fibrous Debris Nukon kg 0.447 0.447 Particulate Debris RMI kg 17.590 9.466 Cal-Sil kg 3.402 0.855 Marinite I kg 0.002 0.000 Wollastonite kg 0.006 0.004 Min-K kg 0.016 0.000 Unqualified Non-OEM Epoxy kg 0.196 0.083 Unqualified Non-OEM Alkyd kg 0.049 0.249 Stone Flour kg 17.766 14.564 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-15 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 CHEMICAL QUANTITIES FOR DEGB CHEMICAL EFFECTS TESTING Mass Chemical Units DEGB Test Boric Acid kg 25.311 Sodium Tetraborate (Borax) kg 12.753 Sodium Aluminate Solution 36% kg 35.666 Calcium Chloride Solution 34% kg 39.550 Sodium Silicate Solution 38% kg 26.926 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 CHEMICAL QUANTITIES FOR DGBS CHEMICAL EFFECTS TESTING Mass Chemical Units DGBS Test Boric Acid kg 25.311 Sodium Tetraborate (Borax) kg 12.753 Sodium Aluminate Solution 36% kg 35.666 Calcium Chloride Solution 34% kg 39.550 Sodium Silicate Solution 38% kg 26.926 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-17 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 VUEZ CHEMICAL EFFECTS TESTING DEBRIS QUANTITIES Units Debris Source Plant Units Test Units Test (SI)

Latent Fiber1 6.5 ft3 0.096 lbs 43.5 g Epoxy (inside ZOI, 10 mil) 95.04 lbs 0.5873 lbs 266.4 g Epoxy (OEM, outside ZOI) 6.76 lbs 0.0418 lbs 18.96 g Epoxy (non-OEM, outside ZOI) 16.12 lbs 0.0996 lbs 45.2 g Alkyd (inside ZOI, 10 mil) 0.836 lbs 0.0052 lbs 2.359 g Alkyd (OEM, outside ZOI) 10.416 lbs 0.0644 lbs 29.2 g Alkyd (non-OEM, outside ZOI) 1.972 lbs 0.0122 lbs 5.53 g Marinite I 0.1199 lbs 0.000741 lbs 0.336 g Marinite 36 1.00 lbs 0.006185 lbs 2.805 g Min-K 0.704 lbs 0.00435 lbs 1.973 g Cal-Sil 169.56 lbs 1.048 lbs 475.4 g Dirt/Dust 88.4 lbs 0.546 lbs 247.7 g 1

(Plant fiber volume) x (2.4 lb/ft3) x (strainer scaling factor) = test fiber mass UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-18 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 VUEZ CHEMICAL EFFECTS TESTING MATERIAL QUANTITIES SUBMERGED IN CONTAINMENT SUMP Material Source Quantity Metallic Aluminum Miscellaneous Components 10.9 ft2 Galvanized Steel, Cold Zinc Coated Steel Structural Material 71,162.6 ft2 Copper Wires, tubing 1,021.6 ft2 Concrete Containment Building Structure 6,412.8 ft2 Glycol (undiluted) Cooling System 93.58 ft3 Oil Lubricant 32.76 ft3 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-19 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 VUEZ CHEMICAL EFFECTS TESTING NON-SUBMERGED MATERIAL QUANTITIES Material Source Quantity Metallic Aluminum HVAC Equipment 8,013.4 ft2 Galvanized Steel, Structural Material 504,729 ft2 Cold Zinc Coated Steel Carbon Steel Structural Material 32,666.2 ft2 Copper Wires, Tubing, HVAC Equipment 39,735.24 ft2 Concrete Containment Structure 1,077.1 ft2 Grease1 Lubricant 420.9 ft2 1

0.175 ft3 spread over the 420 ft2 area.

UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-20 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 STRAINER MINIMUM SUBMERGENCE DETERMINATION Time from Event Containment Water Minimum Water Minimum Minimum Initiation until Break Size Level at Initiation of Level During Submergence Main Submergence Remote Minimum Water Recirculation, ft Recirculation, ft Strainer, ft Strainer, ft Level, ~ hours DEGB 7.7 5.9 9.1 0.9 1.3 DGBS1 6.9 5.6 2.5 0.6 1.0 SBLOCA 6.8 5.1 9.5 0.1 0.5 (2 in) 1 This break was analyzed as occurring in the reactor cavity at the reactor vessel nozzle, resulting in 30% of the break flow going to the reactor cavity and 70% going to the loop compartment.

UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-21 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 IN-VESSEL FUEL ROD DEBRIS DEPOSITION Total Deposition Total Deposition Max Clad Scale Thickness Case Thickness Thickness Temperature

(µm)

(µm) (mils) (°F)

Unit 1 (min sump volume) 151 443 17 365.71 Unit 1 (max sump volume) 61 353 14 365.71 Unit 2 (min sump volume) 122 414 16 358.10 Unit 2 (max sump volume) 54 346 14 358.09 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-22 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 BOUNDING DEBRIS AT MAIN STRAINER FOR SACRIFICIAL STRAINER AREA CONSIDERATION FOR DEGB AND DGBS Debris Transport Debris at Debris Type Generated Fraction Strainer Electromark Labels (inside ZOI), ft2 0.7 0.13 0.091 Electromark Labels (outside ZOI), ft2 39.6 0.03 1.188 Unqualified Labels (all of containment), ft2 25.94 0.86 22.308 Fire Barrier Tape Small Pieces (< 4 in), ft2 14.4 0.13 1.872 Fire Barrier Tape Large Pieces ( 4 in), ft2 54.1 0.13 7.033 Flexible Conduit PVC Jacketing, ft2 1.57 1 1.57 Ice Storage Bag Liner Shards, ft2 0.87 0.63 0.548 Pieces of Work Platform Rubber, ft2 0.22 0.63 0.139 Total, ft2 137.4 - 34.75 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.3.9-23 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 BOUNDING DEBRIS AT REMOTE STRAINER FOR SACRIFICIAL STRAINER AREA CONSIDERATION FOR DEGB AND DGBS Debris Transport Debris at Debris Type Generated Fraction Strainer Electromark Labels (inside ZOI), ft2 0.7 0.47 0.329 Electromark Labels (outside ZOI), ft2 39.6 0.69 27.324 Unqualified Labels (all of containment), ft2 25.94 0.4 10.38 Fire Barrier Tape Small Pieces (< 4 in), ft2 14.4 0 0 Fire Barrier Tape Large Pieces ( 4 in), ft2 54.1 0 0 Flexible Conduit PVC Jacketing, ft2 1.57 0.3 0.471 Ice Storage Bag Liner Shards, ft2 0.87 0.42 0.365 Pieces of Work Platform Rubber, ft2 0.22 0.42 0.092 Total, ft2 137.4 - 38.96 UNIT 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.A.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 Core Activities for Radiological Consequence Analysis Activity Activities Nuclide Nuclide (Curies) (Curies)

Co-58 8.884E+05 Pr-143 1.398E+08 Co-60 6.796E+05 Nd-147 6.178E+07 Kr-85 1.280E+06 Np-239 2.609E+09 Kr-85m 2.364E+07 Pu-238 4.130E+05 Kr-87 4.661E+07 Pu-239 3.727E+04 Kr-88 6.222E+07 Pu-240 6.637E+04 Rb-86 2.272E+05 Pu-241 1.603E+07 Sr-89 8.677E+07 Am-241 1.707E+04 Sr-90 1.002E+07 Cm-242 7.417E+06 Sr-91 1.100E+08 Cm-244 1.838E+06 Sr-92 1.184E+08 Kr-83m 1.119E+07 Y-90 1.038E+07 Br-82 3.972E+05 Y-91 1.142E+08 Br-83 1.106E+07 Y-92 1.197E+08 Br-84 2.009E+07 Y-93 1.358E+08 Rb-89 8.303E+07 Zr-95 1.566E+08 Y-91m 6.384E+07 Zr-97 1.586E+08 Y-95 1.496E+08 Nb-95 1.578E+08 Nb-95m 1.795E+06 Mo-99 1.742E+08 Nb-97 1.596E+08 Tc-99m 1.546E+08 Rh-103m 1.849E+08 Ru-103 1.850E+08 Pd-109 5.749E+07 Ru-105 1.491E+08 Sb-124 1.434E+05 Ru-106 9.480E+07 Sb-125 1.231E+06 Rh-105 1.309E+08 Sb-126 5.873E+04 Sb-127 1.067E+07 Te-125m 2.725E+05 Sb-129 3.215E+07 Te-131 8.174E+07 Te-127 1.054E+07 Te-133 1.024E+08 Te-127m 1.841E+06 Te-133m 8.990E+07 Te-129 3.017E+07 Te-134 1.700E+08 Te-129m 5.821E+06 I-130 3.945E+06 Te-131m 2.119E+07 Xe-131m 1.385E+06 Te-132 1.374E+08 Xe-133m 6.099E+06 I-131 9.814E+07 Xe-135m 4.335E+07 I-132 1.420E+08 Xe-138 1.627E+08 I-133 1.916E+08 Cs-134m 5.865E+06 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.A.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 Core Activities for Radiological Consequence Analysis Activity Activities Nuclide Nuclide (Curies) (Curies)

I-134 2.148E+08 Cs-138 1.776E+08 I-135 1.832E+08 Ba-141 1.522E+08 Xe-133 1.919E+08 La-143 1.419E+08 Xe-135 5.900E+07 Pm-147 1.944E+07 Cs-134 2.523E+07 Pm-148 1.841E+07 Cs-136 6.388E+06 Pm-148m 4.711E+06 Cs-137 1.325E+07 Pm-149 6.245E+07 Ba-139 1.693E+08 Pm-151 2.177E+07 Ba-140 1.639E+08 Sm-153 6.797E+07 La-140 1.700E+08 Eu-154 9.557E+05 La-141 1.533E+08 Eu-155 4.427E+05 La-142 1.475E+08 Eu-156 4.798E+07 Ce-141 1.548E+08 Np-238 5.165E+07 Ce-143 1.430E+08 Pu-243 1.153E+08 Ce-144 1.296E+08 Am-242 1.148E+07 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.A.2-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 Core Activities in the Highest Discharge Assembly for Radiological Consequence Analysis Activity Activities Nuclide Nuclide (Ci) (Ci)

Co-58 7.595E+03 Pr-143 1.195E+06 Co-60 5.810E+03 Nd-147 5.282E+05 Kr-85 2.189E+04 Np-239 2.230E+07 Kr-85m 2.021E+05 Pu-238 3.531E+03 Kr-87 3.985E+05 Pu-239 3.186E+02 Kr-88 5.319E+05 Pu-240 5.674E+02 Rb-86 1.942E+03 Pu-241 1.370E+05 Sr-89 7.418E+05 Am-241 1.459E+02 Sr-90 8.566E+04 Cm-242 6.341E+04 Sr-91 9.404E+05 Cm-244 1.571E+04 Sr-92 1.012E+06 Kr-83m 9.567E+04 Y-90 8.874E+04 Br-82 3.396E+03 Y-91 9.763E+05 Br-83 9.455E+04 Y-92 1.023E+06 Br-84 1.718E+05 Y-93 1.161E+06 Rb-89 7.098E+05 Zr-95 1.339E+06 Y-91m 5.458E+05 Zr-97 1.356E+06 Y-95 1.279E+06 Nb-95 1.349E+06 Nb-95m 1.535E+04 Mo-99 1.489E+06 Nb-97 1.364E+06 Tc-99m 1.322E+06 Rh-103m 1.581E+06 Ru-103 1.582E+06 Pd-109 4.915E+05 Ru-105 1.275E+06 Sb-124 1.226E+03 Ru-106 8.105E+05 Sb-125 1.052E+04 Rh-105 1.119E+06 Sb-126 5.021E+02 Sb-127 9.122E+04 Te-125m 2.330E+03 Sb-129 2.749E+05 Te-131 6.988E+05 Te-127 9.011E+04 Te-133 8.754E+05 Te-127m 1.574E+04 Te-133m 7.686E+05 Te-129 2.574E+05 Te-134 1.453E+06 Te-129m 4.977E+04 I-130 3.373E+04 Te-131m 1.812E+05 Xe-131m 1.184E+04 Te-132 1.175E+06 Xe-133m 5.214E+04 I-131 1.342E+06 Xe-135m 3.706E+05 I-132 1.214E+06 Xe-138 1.391E+06 I-133 1.638E+06 Cs-134m 5.014E+04 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.A.2-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 Core Activities in the Highest Discharge Assembly for Radiological Consequence Analysis Activity Activities Nuclide Nuclide (Ci) (Ci)

I-134 1.836E+06 Cs-138 1.518E+06 I-135 1.566E+06 Ba-141 1.301E+06 Xe-133 1.641E+06 La-143 1.213E+06 Xe-135 5.044E+05 Pm-147 1.662E+05 Cs-134 2.157E+05 Pm-148 1.574E+05 Cs-136 5.461E+04 Pm-148m 4.028E+04 Cs-137 1.133E+05 Pm-149 5.339E+05 Ba-139 1.447E+06 Pm-151 1.861E+05 Ba-140 1.401E+06 Sm-153 5.811E+05 La-140 1.453E+06 Eu-154 8.170E+03 La-141 1.311E+06 Eu-155 3.785E+03 La-142 1.261E+06 Eu-156 4.102E+05 Ce-141 1.323E+06 Np-238 4.416E+05 Ce-143 1.223E+06 Pu-243 9.857E+05 Ce-144 1.108E+06 Am-242 9.815E+04 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.A.3-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 Parameters Used in the Calculation of Reactor Coolant Fission Product Concentrations Parameter Value Core Thermal Power 3480 MWt Fraction of Fuel Rods Containing Cladding Defects 0.01 Reactor Coolant Liquid Volume 10,309.9 ft3 Reactor Coolant Average Temperature 574°F Purification Flow Rate 75 gpm Cation Bed Flow Rate 800 gpd Boron Dilution/Makeup Flow Rate 400 gpd Fission Product Escape Rate Coefficients:

Kr, Xe 6.5E-08 I, Br, Rb, Cs 1.3E-08 Mo, Tc 2.0E-09 Te Isotopes 1.0E-09 Sr, Ba Isotopes 1.0E-11 Y, Zr, Nb, Ru, Rh, La, Ce, Pr 1.6E-12 Mixed Bed Demineralizer Decontamination Factors:

Noble Gases 1 I, Br Isotopes 10 Sr, Ba Isotopes 10 All Other Isotopes 1 Cation Bed Demineralizer Decontamination Factors:

Kr, Xe 1 Sr, Ba Isotopes 1 Rb-86, Cs-134, Cs-137 10 Rb-88, Rb-89, Cs-136, Cs-138 1 All Other Isotopes 1 Volume Control Tank Noble Gas Stripping Fractions Kr-83m 0.78 Kr-85m 0.61 Kr-85 7.3E-05 Kr-87 0.84 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.A.3-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 Parameters Used in the Calculation of Reactor Coolant Fission Product Concentrations Parameter Value Kr-88 0.71 Xe-131m 0.017 Xe-133m 0.085 Xe-133 0.037 Xe-135m 0.95 Xe-135 0.35 Xe-138 0.95 Volume Control Tank Purge Flow Rate 0 cfm Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.A.3-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Reactor Coolant Equilibrium Fission Product Concentrations Activity Activities Nuclide Nuclide

(µCi/g) (µCi/g)

Kr-85 2.385E+01 Xe-135 3.361E+00 Kr-85m 5.204E-01 Cs-134 3.327E+01 Kr-87 3.299E-01 Cs-136 2.188E+00 Kr-88 9.148E-01 Cs-137 1.852E+01 Rb-86 8.797E-02 Ba-139 1.975E-04 Sr-89 1.335E-03 Ba-140 1.940E-03 Sr-90 1.237E-04 La-140 2.878E-03 Sr-91 5.681E-04 La-141 1.301E-04 Sr-92 2.488E-04 La-142 3.346E-05 Y-90 2.152E-04 Ce-141 1.445E-02 Y-91 1.692E-02 Ce-143 6.911E-04 Y-92 3.067E-04 Ce-144 4.229E-02 Y-93 2.010E-04 Pr-143 6.713E-03 Zr-95 2.409E-02 Kr-83m 1.350E-01 Zr-97 3.920E-04 Br-82 4.641E-03 Nb-95 3.478E-02 Br-83 2.720E-02 Mo-99 2.070E+00 Br-84 1.244E-02 Tc-99m 1.980E+00 Rb-89 2.530E-02 Ru-103 1.991E-02 Y-91m 3.314E-04 Ru-105 9.723E-05 Nb-95m 1.867E-04 Ru-106 3.340E-02 Nb-97 4.900E-05 Rh-105 7.689E-04 Rh-103m 1.988E-02 Te-127 2.489E-01 Kr-83m 1.350E-01 Te-127m 2.465E-01 Te-125m 2.449E-02 Te-129 2.281E-01 Te-131 1.599E-02 Te-129m 3.463E-01 Te-133m 7.643E-03 Te-131m 5.787E-02 Te-134 1.092E-02 Te-132 9.639E-01 Xe-131m 1.600E+00 I-131 8.087E-01 Xe-133m 1.423E+00 I-132 6.411E-01 Xe-135m 2.138E-01 I-133 1.0304E+00 Xe-138 2.292E-01 I-134 1.231E-01 Cs-134m 2.031E-02 I-135 5.365E-01 Cs-138 3.420E-01 Xe-133 1.037E+02 Ba-141 4.233E-05 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.A.3-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Reactor Coolant Iodine Appearance Rates (Ci/min)

Appearance Rate Isotope (Ci/min)

I-131 0.4469 I-132 1.2307 I-133 0.7099 I-134 0.5128 I-135 0.5459 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 14.A.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 TRITIUM PRODUCTION IN THE REACTOR COOLANT (ci/yr) 1 RELEASED TO THE COOLANT Total Design Expected Tritium Source Produced Value Value Ternary Fissions 10,420 3126 104 Burnable Poison Rods (Initial Cycle) 922 277 9 Soluble Poison Boron (Initial Cycle) 378 378 378 (Equilibrium Cycle) 525 525 525 Li-7 Reaction 11 11 11 Li-6 Reaction 6 6 6 Deuterium Reaction 1 1 1 Totals Initial Cycle 11,738 3799 509 Totals Equilibrium 10,963 3669 647 1

This table was applicable at the time Unit 1 was licensed.

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 14.A.4-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 REVISED TRITIUM PRODUCTION IN THE REACTOR COOLANT 1 Expected Release to Total Produced Tritium Source Reactor Coolant (curies/yr)

(curies/yr)

Ternary Fission 10,000 1000 Burnable Poison Rods (Initial Cycle) 1420 142 Soluble Boron (Initial Cycle) 206 206 (Equilibrium Cycle) 294 294 Lithium and Deuterium Reactions 105 105 Total Initial Cycle 11,730 1453 Total Equilibrium Cycle 10,400 1400 Basis:

Release Fraction from Fuel 10%

Release Fraction from Burnable Poison Rods 10%

Burnable Poison Rod B-10 Mass 6160 gpm 1

This table was included in the Original FSAR in May, 1976.

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.A.5-1a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Volume Control Tank Activities for Offsite Dose Consequence Analysis VCT Gas Phase VCT Liquid Phase Letdown Activity Total Activity Nuclide Activity Activity (Ci) (Ci)

(Ci) (Ci)

Kr-85 2.793E+03 1.780E+02 2.231E+02 3.194E+03 Kr-85m 3.923E+01 4.484E+00 5.619E+00 4.933E+01 Kr-87 1.359E+01 2.462E+00 3.085E+00 1.913E+01 Kr-88 6.477E+01 7.334E+00 9.191E+00 8.129E+01 Xe-133 1.668E+04 1.146E+03 1.436E+03 1.926E+04 Xe-133m 2.176E+02 1.547E+01 1.939E+01 2.524E+02 Xe-135 2.779E+02 2.335E+01 2.927E+01 3.305E+02 Xe-135m 2.705E+00 1.835E+00 2.299E+00 6.837E+00 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table:14.A.5-1b UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Volume Control Tank Activities for Control Room Dose Consequence Analysis VCT Gas Phase VCT Liquid Letdown Flow Total Activity Nuclide Activity Phase Activity Activity (Ci)

(Ci) (Ci) (Ci)

Kr-85m 1.596E+02 1.021E+01 1.012E+01 1.799E+02 Kr-85 1.835E+04 4.679E+02 4.639E+02 1.929E+04 Kr-87 3.955E+01 6.472E+00 6.416E+00 5.244E+01 Kr-88 2.070E+02 1.794E+01 1.779E+01 2.427E+02 Xe-131m 8.716E+02 3.138E+01 3.111E+01 9.341E+02 Xe-133m 7.125E+02 2.791E+01 2.766E+01 7.681E+02 Xe-133 5.421E+04 2.035E+03 2.017E+03 5.826E+04 Xe-135m 5.806E+00 4.194E+00 4.158E+00 1.4160E+01 Xe-135 1.200E+03 6.593E+01 6.535E+01 1.331E+03 Xe-138 5.770E+00 4.497E+00 4.458E+00 1.473E+01 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.A.5-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Waste Gas Decay Tank Activity Total Activity Nuclide (Ci)

Kr-85m 1.433E+02 Kr-85 6.570E+03 Kr-87 9.087E+01 Kr-88 2.520E+02 Xe-131m 4.407E+02 Xe-133m 3.920E+02 Xe-133 2.857E+04 Xe-135m 5.889E+01 Xe-135 9.258E+02 Xe-138 6.314E+01 Unit 1

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 14.G-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 COMPONENTS NOMENCLATURE COMPONENT ELEMENT Vessel Supports Number 1 and 49 Barrel Flange and Hold-Down Spring Numbers 2 thru 6 Barrel Numbers 7 thru 10 Lower Core Supports Numbers 11 thru 15 Major Fuel Assemblies Even Numbers 16 thru 38 Minor Fuel Assemblies Odd Numbers 17 thru 39 Upper Internals Numbers 40 thru 48

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 14.G-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 HISTORICAL MAXIMUM DEFLECTIONS UNDER BLOWDOWN (INCHES)

(1-MILLISECOND DOUBLE-ENDED BREAK)

Seismic Maximum No Loss Component Hot Leg Cold Leg Allowable Horizontal Total Of Function Upper Barrel Radial inward 0.057 0.0 0.002 0.059 5 10 Radial outward 0.029 0.431 0.002 0.460 4.125 8.25 Upper core plant 0.015 0.016 0 0.016 0.100 1 0.150 RCC Guide Tubes (54)<Allowable 0.010 <Allowable 1.0 1.60 to 1.75 (deflection as a beam)

(2)<N.L.F. 0.010 <N.L.F. 1.0 1.60 to 1.75

>Allowable >Allowable 1.60 to 1.75 (5)>N.L.F 0.010 >N.L.F. 1.0 Fuel Assembly Thimbles 0 0 0 0 0.036 0.072 (cross-section distortion) 1 Only to assure that the plate will not touch a guide tube.

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 14.G-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 HISTORICAL

SUMMARY

OF MAXIMUM STRESS INTENSITIES (PSI)

(1-MILLISECOND PIPE BREAK AND SEISMICS)

Hot Leg Break Cold Leg Break Maximum Total Seismic Maximum Total Maximum Maximum Maximum Maximum Component Vertical Horizontal Blowdown Membrane Total Membrane Total Plus Seismic Barrel (Girth weld) 21,440 31,340 38,900 46,200 133 533 46,733 Barrel-Flange (weld) 19,820 29,720 18,430 47,700 545 800 49,045 Fuel Assembly Top Nozzle Plate 28,700 0 8,000 0 0 28,700 Fuel Assembly Bottom Nozzle Plate 38,700 40,800 533 41,333 Fuel Assembly Thimbles 6,600 6,600 2,300 2,300 6,600 Allowable Stress, Sm:

Sm at 588°F = 16,600 psi 1 Maximum Membrane Stress = Pm = 2.4 Sm = 39,800 psi Maximum Total Stress = Pm + Pb = 49,800 psi 1

Per Winter 1969 Addenda ASME Section III Code

ML21125A501

Text

SUMMARY

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