ML22340A157
Text
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 4 Plant Operating Range Analyzed by the Best-Estimate Large-Break LOCA Analysis for D. C. Cook Unit 2 ANALYZED VALUE PARAMETER OR RANGE 1.0 Plant Physical Description a) Dimensions Nominal b) Pressurizer location On an intact loop(4) c) Hot assembly location Anywhere in core(1) 17xl7 V5 Fuel with ZIRLO d) Hot assembly type(2) cladding or Optimized ZIRLO cladding, non-IFBA or IFBA e) Steam generator tube plugging level(5) 10%
17xl7 V5 Fuel with ZIRLO f) Fuel assembly type(2) cladding or Optimized ZIRLO cladding, non-IFBA or IFBA 2.0 Plant Initial Operating Conditions 2.1 Reactor Power a) Maximum Core power 3479.8 MWt b) Peak heat flux hot channel factor (F )(2)(5)
Q 2.335 Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 4 Plant Operating Range Analyzed by the Best-Estimate Large-Break LOCA Analysis for D. C. Cook Unit 2 ANALYZED VALUE PARAMETER OR RANGE c) Peak hot rod enthalpy rise hot channel factor 1.644 (FH)(2)(5) d) Hot assembly radial peaking factor (P )(2)
HA 1.644 / 1.04 e) Hot assembly heat flux hot channel factor (F )
QHA 2.335 / 1.04 f) Axial power distribution (P , P )(2) Figure 14.3.1-2 BOT MID g) Low power region relative power (P (2)
LOW) 0.20 PLOW 0.70 h) Hot assembly burn up 75,000 MWD / MTU, lead rod(1)(3) i) MTC 0 at hot full power (HFP) j) Typical cycle length 18 months k) Minimum core average burn up(2) 10,000 MWD / MTU l) Maximum steady state depletion, F (2)
Q 1.90 2.2 Fluid Conditions a) T (5) 547.6 - 5.6ºF TAVG 578.1 + 4.1ºF AVG b) Pressurizer pressure 2,100 - 63 psia PRCS 2,100 + 63 psia 2,250 - 63 psia PRCS 2,250 + 63 psia c) Minimum thermal design flow 88,500 gpm / loop Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 4 Plant Operating Range Analyzed by the Best-Estimate Large-Break LOCA Analysis for D. C. Cook Unit 2 ANALYZED VALUE PARAMETER OR RANGE d) Upper head design THOT e) Pressurizer level (at hot full power) 59.8% of span (High TAVG) 40.0% of span (Low TAVG) f) Accumulator temperature(5) 60ºF TACC 120ºF 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 flow Table 14.3.1-4a and 14.3.1-4b b) Safety injection temperature(5) 70ºF SI Temp 105ºF c) Safety injection delay(5) 27 seconds (with offsite power) 54 seconds (with LOOP)
See Figures 14.3.1-3 thru 14.3.1-9 d)
Containment modeling and raw data in Tables 14.3.1-2, 14.3.1-3, & 14.3.1-7 e) Initial containment pressure See Table 14.3.1-2 f) Containment spray initiation delay See Table 14.3.1-2 Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 4 Plant Operating Range Analyzed by the Best-Estimate Large-Break LOCA Analysis for D. C. Cook Unit 2 ANALYZED VALUE PARAMETER OR RANGE g) Deck Fan initiation delay See Table 14.3.1-2 h) Single failure Loss of one ECCS train Notes:
- 1. 44 peripheral locations will not physically be lead power assembly.
In the Westinghouse Reload Safety Analysis Checklist (RSAC) process, this parameter is identified as a 2.
key safety analysis parameter that could be impacted by a fuel reload.
The fuel temperature and rod internal pressure data is only provided up to 62,000 MWD / MTU. In 3.
addition, the hot assembly / hot rod will not have a burn up this high in ASTRUM analyses.
- 4. Analyzing the pressurizer as being located on an intact loop is limiting per Westinghouse methodology.
- 5. Parameter values affected by evaluation described in Section 14.3.1.5.1 Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-2 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT Large Break Containment Data (Ice Condenser Containment)
Net Free Volume Distribution Between UC: 729,969 ft3 Upper (UC),
LC: 295,258 ft3 Lower (LC),
IC: 122,350 ft3 Ice Condenser (IC) and, DE: 60,209 ft3 Dead-Ended (DE) Compartments Initial Condition Containment Pressure 14.7 psia Maximum Temperature for the UC: 100°F Upper (UC),
LC: 120°F Lower (LC) and, DE: 120°F Dead-Ended (DE) Compartments Minimum Temperature for the Upper (UC),
Lower (LC) and Dead-Ended (DE)
Compartments Temperature Outside Containment -22°F Initial Spray Temperature at 14.7 psia 45°F (1)
Maximum Containment Spray Flow Rate 3700 gpm / pump Number of Spray Pumps Operating 2 Post-Accident Initiation of Spray System 47 sec Post-Accident Initiation of Deck Fans 108 sec Deck Fan Flow Rate 48,000 cfm / fan Assumed Spray Efficiency of Water from Ice Condenser Drains 100%
Notes:
- 1. Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See Section 14.3.1.5 for more information.
Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-3 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT 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 599. 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 20923 0.0091 steel 7 UC 17754 0.0194 steel 8 UC 5923 0.1078 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 40784 0.0079 steel 16 LC 15792 0.0153 steel 17 LC 14566 0.0650 steel 18 LC 61214 0.1076 steel 19 LC 4529 14.04 concrete 20 LC 3439 0.1561 steel UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-4a UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT Minimum HHSI and RHR Combined Injection Flow HHSI + RHR Total Pressure Injected Flow (psia)
(gpm) 14.7 3,146.4 34.7 2,483.0 54.7 1,746.9 74.7 1,427.1 94.7 1,062.6 114.7 616.1 134.7 242.7 154.7 239.5 174.7 236.3 194.7 233.0 214.7 229.7 234.7 226.4 254.7 223.0 274.7 219.6 294.7 216.2 314.7 212.7 UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-4b UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT Minimum CHSI Injection Flow CHSI Total Pressure Injected Flow (psia)
(gpm) 14.7 267.6 114.7 260.0 214.7 252.4 314.7 244.6 414.7 236.6 514.7 228.4 614.7 220.1 714.7 211.6 814.7 202.9 914.7 194.1 1014.7 185.0 1114.7 175.3 1214.7 165.1 1314.7 154.5 1414.7 143.5 1514.7 132.0 1614.7 119.2 1714.7 104.0 UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 D. C. Cook Unit 2 Best-Estimate Large Break LOCA Results ASTRUM Result Value Criteria 95 / 95 PCT (ºF) 2107 < 2,200 95 / 95 LMO (%) 9.7 < 17 95 / 95 CWO (%) 0.55 <1 Unit 2
UFSAR Revision 31.0 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 LBLOCA) for D. C. Cook Unit 2 PCT for Analysis-of-Record (AOR) 2107ºF PCT Assessments Allocated to AOR Design Input Changes with Respect to Plant Operation -239°F Evaluation of Pellet Thermal Conductivity Degradation and
+73°F Peaking Factor Changes to Grid Blockage Ratio and Porosity +16°F Revised Heat Transfer Multiplier Distribution -3°F HOTSPOT Burst Strain Error +13°F Upflow Conversion +37°F BE LBLOCA PCT for Comparison to 10 CFR 50.46 Requirements 2004ºF Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-7 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT Nitrogen Mass and Energy Release Rates Time [s] Flow Rate [lbm / s]
0 0 50 0 50.01 247.8 70.01 247.8 70.02 0 1000 0 UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.1-8 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT Sequence of Events for the Limiting Case Event Time (sec)
Start of Transient 0.0 Safety Injection Signal 5.7 Accumulator Injection Begins 18.5 End of Blowdown 26.5 Bottom of Core Recovery 43.5 Accumulator Empty 52.2 Safety Injection Begins 59.7 PCT Occurs 315.9 End of Transient 600.0 UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-1 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT PLANT INPUT PARAMETERS FOR SMALL BREAK LOSS-OF-COOLANT ACCIDENT Core Rated Thermal Power - 100%, MWt 3600(1)
Peak Linear Power, kW / ft 12.822 Fuel Type 17 x 17 Vantage 5 Fuel Total Core Peaking Factor, FQ 2.32 Hot Channel Enthalpy Rise Factor, FH 1.62 Hot Assembly Average Power Factor, PHA 1.46 Thermal Design Flow, gpm / loop 88,500 Nominal Vessel Average Temperature, °F 578.2(2)
Nominal Pressurizer Pressure, psia 2250(3)
Minimum Auxiliary Feedwater Flow Rate, lbm / s per SG 25.78 Steam Generator Tube Plugging (Maximum), % 10 Initial Accumulator Water Volume, ft 3 946 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 120 Nominal Steam Pressure, psia 791.863 SI Flow Delay Time, seconds 54 HHSI Cross-Tie Valve Position Open Open (Injection)
RHR Cross-Tie Valve Position Closed (Recirculation)
(1) Calorimetric uncertainty of 1.0034 resulted in an analyzed core power of 3612 MWt.
(2) Analysis supports operation over the range of nominal full-power Tavg values of 547.6°F- 578.1 °F with Tavg uncertainty range of +4.1 °F / -5.6°F.
(3) Analysis supports operation at nominal initial pressurizer pressure of 2100 psia and 2250 psia with +/-62.6 psi uncertainty.
Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-2 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT Time Sequence of Events for Small Break Loss-of-Coolant Accident Event Time (sec) 1.5-inch 2-inch 3-Inch 4-Inch 6-Inch 8.75-inch Break Initiation 0.00 0.00 0.00 0.00 0.00 0.00 Reactor Trip Signal 89.72 46.48 19.17 11.02 6.09 4.83 S-Signal 108.11 59.03 27.57 17.71 9.65 7.66 SI Flow Delivered(1) 162.11 113.03 81.57 71.71 63.65 61.66 Loop Seal Clearing(2) 2630 1422 551 310 146 26 Core Uncovery(4) N/A 1726 877 602 N/A N/A Accumulator Injection N/A N/A 1800 864 352 168(3)
RWST Volume Delivered(5) 2161.88 2151.71 2115.48 2088.59 2052.49 1565.20 PCT Time (BOL) N/A 1989.1 1603.1 971.5 N/A N/A Core Recovery(4) N/A 5070 N/A(6) 2830 N/A 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 the 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) The run was successfully terminated per the NOTRUMP transient termination criteria.
UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-2a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 TIME SEQUENCE OF EVENTS FOR SMALL BREAK LOSS-OF-COOLANT ACCIDENT UPFLOW CONVERSION Event Time (sec) 4-Inch Break Initiation 0.0 Reactor Trip Signal 11.06 S-Signal 17.85 SI Flow Delivered(1) 71.85 Loop Seal Clearing(2) 313 Core Uncovery(3) 575 Accumulator Injection 830 RWST Volume Delivered(4) 2087.54 PCT Time (BOL) 969.0 Core Recovery(3) 2860 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 and the mixture level is at or below the top of the loop seal.
(3) The latest point of sustained core uncovery/recovery is reported (4) 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.
Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-3 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT Small Break Loss-of-Coolant Accident Calculations Break Size (in) 2.0 3.0 4.0 PCT (°F) 977.9 1176.5 1273.7 PCT Time (s) 1989.1 1603.1 971.5 PCT Elevation (ft) 11.00 11.25 11.25 Max. Local Zr02 (%) 0.01 0.11 0.11 Max. Local Zr02 Elev. (ft) 11.00 11.50 11.25 Hot Rod Axial Average Zr02 (%)(1) 0.00 0.02 0.02 Notes:
(1) The hot rod axial average Zr02 conservatively represents the core wide average oxidation, since the core wide average Zr02 thickness will always be less than the corresponding hot rod axial average Zr02 thickness.
UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-3a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 SMALL BREAK LOSS-OF-COOLANT ACCIDENT CALCULATIONS UPFLOW CONVERSION Break Size (in) 4.0 PCT (°F) 1348.7 PCT Time (s) 969.0 PCT Elevation (ft) 11.50 Max. Local ZrO2 (%) 0.19 Max. Local ZrO2 Elev. (ft) 11.25 Hot Rod Axial Average ZrO2 (%) 0.03 Note:
(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.
Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-4 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 2 REPORT Safety Injection Flows Used in the SBLOCA Analysis - Injection Phase (1 CBG pump, 1 HHSI pump, 1 RHR pump- faulted loop injects to RCS pressure)
(1.5-inch through 6-inch breaks)
RCS Pressure Broken Loop Intact Loops (psia) (lbm / sec) (lbm / sec)
Loop 1 Loop 2 Loop 3 Loop 4 14.7 177.8 155.5 157.6 156.5 34.7 169.2 148.1 150.0 149.0 54.7 159.3 139.5 141.2 140.4 74.7 148.1 129.8 131.2 130.6 94.7 135.8 119.1 120.3 119.8 114.7 121.5 106.7 107.7 107.4 134.7 103.3 91.0 91.5 91.5 154.7 77.0 68.1 68.2 68.4 174.7 31.3 28.5 27.6 28.4 194.7 31.1 28.3 27.4 28.2 214.7 30.9 28.1 27.2 28.0 234.7 30.6 27.9 26.9 27.8 254.7 30.4 27.6 26.7 27.6 274.7 30.1 27.4 26.5 27.4 294.7 29.9 27.2 26.3 27.1 314.7 29.7 27.0 26.1 26.9 414.7 28.4 25.8 25.0 25.8 514.7 27.2 24.7 23.9 24.6 614.7 25.8 23.4 22.7 23.4 714.7 24.4 22.1 21.5 22.1 814.7 23.0 20.8 20.2 20.8 914.7 21.4 19.3 18.8 19.3 1014.7 19.5 17.5 17.1 17.5 1114.7 17.4 15.6 15.2 15.5 1214.7 14.4 12.9 12.6 12.8 UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-4 UPDATED FINAL SAFETY ANALYSIS Page: 2 of 2 REPORT Safety Injection Flows Used in the SBLOCA Analysis - Injection Phase (1 CBG pump, 1 HHSI pump, 1 RHR pump- faulted loop injects to RCS pressure)
(1.5-inch through 6-inch breaks)
RCS Pressure Broken Loop Intact Loops (psia) (lbm / sec) (lbm / sec)
Loop 1 Loop 2 Loop 3 Loop 4 1314.7 10.1 8.8 8.8 8.7 1414.7 9.0 7.9 7.9 7.8 1514.7 8.6 7.5 7.5 7.4 1614.7 8.1 7.1 7.1 7.0 1714 7 7.6 6.6 6.6 6.5 1814.7 7.1 6.2 6.1 6.1 1914.7 5.3 4.6 4.6 4.6 2014.7 4.7 4.1 4.1 4.0 2114.7 3.9 3.5 3.4 3.4 2214.7 3.1 2.7 2.7 2.6 2314.7 0.0 0.0 0.0 0.0 2414.7 0.0 0.0 0.0 0.0 UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-5 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 2 REPORT Safety Injection Flows Used in the SBLOCA Analysis - Injection Phase (1 CHG pump, 1 HHSI pump, 1 RHR pump faulted loop CHG flow injects to RCS pressure and faulted loop HHSI / RHR flow spills to containment (0 psia) - 8.75-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 14.1 163.7 155.5 157.6 156.5 34.7 14.1 230.7 142.6 92.1 143.5 54.7 14.0 300.3 132.0 12.2 132.9 74.7 13.9 319.2 110.1 12.2 110.7 94.7 13.9 339.5 85.1 12.1 85.5 114.7 13.8 362.1 54.4 12.0 54.6 134.7 13.7 379.3 28.8 12.0 28.8 154.7 13.7 379.5 28.6 11.9 28.5 174.7 13.6 379.6 28.3 11.9 28.2 194.7 13.6 379.6 28.0 11.8 28.0 214.7 13.5 379.7 27.7 11.8 27.7 234.7 13.4 379.8 27.4 11.7 27.4 254.7 13.4 379.8 27.2 11.7 27.1 274.7 13.3 379.9 26.9 11.6. 26.8 294.7 13.2 379.9 26.6 11.5 26.5 314.7 13.2 380.0 26.3 11.5 26.2 414.7 12.8 380.3 24.7 11.2 24.7 514.7 12.5 380.6 23.1 10.9 23.1 614.7 12.2 386.8 20.8 10.6 20.7 714.7 11.8 387.8 17.6 10.3 17.6 814.7 11.5 388.9 13.9 10.0 13.8 914.7 11.1 390.1 9.7 9.7 9.5 1014.7 10.7 390.1 9.3 9.3 9.2 1114.7 10.3 390.2 9.0 9.0 8.9 Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-5 UPDATED FINAL SAFETY ANALYSIS Page: 2 of 2 REPORT Safety Injection Flows Used in the SBLOCA Analysis - Injection Phase (1 CHG pump, 1 HHSI pump, 1 RHR pump faulted loop CHG flow injects to RCS pressure and faulted loop HHSI / RHR flow spills to containment (0 psia) - 8.75-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 1214.7 9.9 390.2 8.6 8.6 8.5 1314.7 9.5 390.2 8.3 8.3 8.1 1414.7 9.0 390.2 7.9 7.9 7.8 1514.7 8.6 390.2 7.5 7.5 7.4 1614.7 8.1 390.2 7.1 7.1 7.0 1714.7 7.6 390.2 6.6 6.6 6.5 1814.7 7.1 390.2 6.2 6.1 6.1 1914.7 5.3 390.2 4.6 4.6 4.6 2014.7 4.7 390.2 4.1 4.1 4.0 2114.7 3.9 390.2 3.5 3.4 3.4 2214.7 3.1 390.2 2.7 2.7 2.6 2314.7 0.0 390.2 0.0 0.0 0.0 2414.7 0.0 390.2 0.0 0.0 0.0 Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-6 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 2 REPORT Safety Injection Flows Used in the SBLOCA Analysis- Recirculation Phase (1 CHG pump, 1 HHSI pump, 1 RHR pump faulted loop injects 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 36.3 32.1 31.0 32.2 26.7 36.3 31.9 30.8 32.2 34.7 36.2 31.8 30.7 31.9 54.7 35.9 31.6 30.5 31.8 74.7 35.8 31.5 30.4 31.6 94.7 35.5 31.2 30.1 31.4 114.7 35.4 31.1 30.0 31.2 134.7 35.1 30.8 29.7 31.0 154.7 34.8 30.7 29.6 30.8 174.7 34.5 30.5 29.4 30.7 194.7 34.4 30.1 29.2 30.4 214.7 34.1 30.0 29.0 30.1 234.7 34.0 29.7 28.8 29.9 254.7 33.6 29.6 28.6 29.7 274.7 33.4 29.4 28.5 29.6 294.7 33.2 29.2 28.2 29.3 314.7 33.0 28.9 27.9 29.2 414.7 31.6 27.9 27.0 28.1 514.7 30.4 26.6 25.7 26.7 614.7 29.2 25.5 24.6 25.6 714.7 27.8 24.2 23.4 24.4 814.7 26.3 22.8 22.2 23.0 914.7 24.8 21.6 20.9 21.6 1014.7 23.0 20.0 19.4 20.1 UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-6 UPDATED FINAL SAFETY ANALYSIS Page: 2 of 2 REPORT Safety Injection Flows Used in the SBLOCA Analysis- Recirculation Phase (1 CHG pump, 1 HHSI pump, 1 RHR pump faulted loop injects 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 21.1 18.2 17.6 18.2 1214.7 18.7 16.1 15.7 16.1 1314.7 15.6 13.2 12.8 13.2 1414.7 11.7 9.5 9.4 9.5 1514.7 9.6 7.7 7.7 7.7 1614.7 9.2 7.3 7.3 7.3 1714.7 8.7 6.9 6.9 6.9 1814.7 8.1 6.5 6.5 6.5 1914.7 7.4 5.9 5.9 5.9 2014.7 6.7 5.5 5.5 5.5 2114.7 6.0 4.9 4.9 4.9 2214.7 5.2. 4.3 4.3 4.3 2314.7 3.3 2.6 2.6 2.6 2414.7 0.0 0.0 0.0 0.0 UNIT 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-7 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 2 REPORT Safety Injection Flows Used in the SBLOCA Analysis - Recirculation Phase (1 CHG pump, 1 HHSI pump, 1 RHR pump faulted loop CHG flow injects to RCS pressure and faulted loop HHSI / RHR flow spills to containment (0 psia) - RHR Spray active - 8.75-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 15.7 20.6 32.1 31.0 32.2 26.7 15.7 39.5 31.9 12.6 32.1 34.7 15.7 39.5 31.8 12.5 31.9 54.7 15.5 39.6 31.5 12.5 31.6 74.7 15.5 39.8 31.4 12.5 31.5 94.7 15.4 39.9 31.0 12.4 31.1 114.7 15.4 40.0 30.7 12.4 31.0 134.7 15.3 40.2 30.4 12.2 30.5 154.7 15.3 40.3 30.1 12.2 30.4 174.7 15.1 40.4 30.0 12.2 30.1 194.7 15.1 40.6 29.6 12.1 29.7 214.7 15.0 40.7 29.4 12.1 29.6 234.7 15.0 40.9 29.0 12.0 29.2 254.7 14.8 41.0 28.8 12.0 28.9 274.7 14.8 41.1 28.6 12.0 28.8 294.7 14.7 41.1 28.2 l1.8 28.3 314.7 14.7 41.3 27.9 11.8 28.1 414.7 14.3 42.0 26.4 11.5 26.6 514.7 13.9 42.6 24.8 11.1 24.9 614.7 13.6 56.0 22.8 10.9 23.0 714.7 13.2 57.9 20.0 10.6 20.1 814.7 12.8 59.8 16.5 10.2 16.7 914.7 12.4 62.0 12.5 9.9 12.5 Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-7 UPDATED FINAL SAFETY ANALYSIS Page: 2 of 2 REPORT Safety Injection Flows Used in the SBLOCA Analysis - Recirculation Phase (1 CHG pump, 1 HHSI pump, 1 RHR pump faulted loop CHG flow injects to RCS pressure and faulted loop HHSI / RHR flow spills to containment (0 psia) - RHR Spray active - 8.75-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 1014.7 12.0 64.1 9.6 9.6 9.6 1114.7 11.5 64.1 9.2 9.2 9.2 1214.7 11.1 64.1 8.9 8.9 8.9 1314.7 10.6 - 8.5 8.5 8.5 1414.7 10.2 - 8.1 8.1 8.1 1514.7 9.6 - 7.7 7.7 7.7 1614.7 9.2 - 7.3 7.3 7.3 Unit 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.3.2-8 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PEAK CLADDING TEMPERATURE INCLUDING ALL PENALTIES AND BENEFITS, SMALL BREAK LOCA (SBLOCA) FOR D. C. COOK UNIT 2 PCT for Analysis-of-Record 1274F PCT Assessments Allocated to AOR
- Upflow Conversion +75F SBLOCA PCT for Comparison to 10 CFR 50.46 Requirements 1349F Unit 2