ML22340A157: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter: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%
{{#Wiki_filter: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
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)
Plant Operating Range Analyzed by the Best-Estimate Large-Break LOCA Analysis for D. C. Cook Unit 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)
PARAMETER ANALYZED VALUE OR RANGE
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:
1.0 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 t ype(2) clai oOptimized ZIRLO cladding, non-IFBA or IFBA e) Steam generator tube plugging level (5 ) 10%
 
17xl7 V5 Fuel with ZIRLO f) Fuel assembl y t ype(2) clai oOptimized ZIRLOcladding, 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 Q ) (2)(5) 2.335
 
Unit 2 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
 
PARAMETER ANALYZED VALUE OR RANGE
 
c) Peak hot rod enthalpy rise hot channel factor 1.644 (FH)(2)(5)
 
d) Hot assembly radial peaking factor (P HA ) (2) 1.644 / 1.04
 
e) Hot assembly heat flux hot channel factor (F QHA ) 2.335 / 1.04
 
f) Axial power distribution (P BOT, P MID ) (2) Figu re 14.3.1-2
 
g) Low power region relative power (P LO W ) (2) 0.20 PLO W 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 c ycle length 18 months
 
k) Minimum core average burn up (2) 10,000 MWD / MTU
 
l) Maximum steady state depletion, F Q (2) 1.90
 
2.2 Fluid Conditions
 
a) TAVG(5) 547.6 - 5.6ºF TAVG 578.1 + 4.1ºF
 
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 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
 
PARAMETER ANALYZED VALUE OR RANGE
 
d) Upper head design THOT
 
e) Pressurizer level (at hot full power) 59.8% of span (High T AVG )
40.0% of span (Low T AV G )
f) Accumulator temperature (5) 60ºF TACC 120ºF
 
g) Accumulator pressure 599.7 psia PACC 672.7 psia
 
h) Accumulator liquid volume 921 ft 3 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 S I T em p 105ºF
 
c) Safety injection delay (5) 27 seconds (with offsite power) 54 seconds (with LOOP) d) See Figures 14.3.1-3 thru 14.3.1-9 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 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
 
PARAMETER ANALYZED VALUE 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.
: 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.
: 2. 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.
key safety analysis parameter that could be impacted by a fuel reload.
: 3. 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 burn up this high in ASTRUM analyses.
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.
: 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
: 5. Parameter values affected by evaluation described in Section 14.3.1.5.1
 
Unit 2 INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT Revision: 24.0 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 ft 3 Upper (UC), LC: 295,258 ft 3 Lower (LC), IC: 122,350 ft 3 Ice Condenser (IC) and, DE: 60,209 ft 3 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


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)
Minimum Temperature for the Upper (UC),
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)
Lower (LC) and Dead-Ended (DE)
Compartments Temperature Outside Containment                                             -22°F Initial Spray Temperature at 14.7 psia                                       45°F (1)
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%
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:
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.
: 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)
Unit 2 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
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
 
Large Break Containment-Heat Sinks Data (Ice Condenser Containment)
Wall Compartment Area [ft 2] 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 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
 
Pressure HHSI + RHR Total (psia) Injected Flow (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 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
 
Pressure CHSI Total (psia) Injected Flow (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 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 (&#xba;F) 2107 < 2,200
 
95 / 95 LMO (%) 9.7 < 17
 
95 / 95 CWO (%) 0.55 < 1
 
Unit 2 INDIANAMICHIGAN 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) 2107&#xba;F
 
PCT Assessments Allocated to AOR
 
Design Input Changes with Respect to Plant Operation -239&deg;F
 
Evaluation of Pellet Thermal Conductivity Degradation and Peaking Factor +73&deg;F
 
Changes to Grid Blockage Ratio and Porosity +16&deg;F
 
Revised Heat Transfer Multiplier Distribution -3&deg;F
 
HOTSPOT Burst Strain Error +13&deg;F
 
Upflow Conversion +37&deg;F
 
BE LBLOCA PCT for Comparison to 10 CFR 50.46 Requirements 2004&#xba;F
 
Unit 2 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 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


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)
Safety Injection Begins 59.7
(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)
PCT Occurs 315.9
(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 (&#xba;F)            2107  < 2,200 95 / 95 LMO (%)              9.7    < 17 95 / 95 CWO (%)              0.55    <1 Unit 2
End of Transient 600.0


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)                                          2107&#xba;F PCT Assessments Allocated to AOR Design Input Changes with Respect to Plant Operation        -239&deg;F Evaluation of Pellet Thermal Conductivity Degradation and
UNIT 2 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
                                                                            +73&deg;F Peaking Factor Changes to Grid Blockage Ratio and Porosity                  +16&deg;F Revised Heat Transfer Multiplier Distribution                  -3&deg;F HOTSPOT Burst Strain Error                                    +13&deg;F Upflow Conversion                                            +37&deg;F BE LBLOCA PCT for Comparison to 10 CFR 50.46 Requirements                2004&#xba;F 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]
PLANT INPUT PARAMETERS FOR SMALL BREAK LOSS-OF-COOLANT ACCIDENT
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)
Core Rated Thermal Power - 100%, MWt 3600(1)
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
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, &deg;F 578.2(2)
Nominal Pressurizer Pressure, psia 2250(3)
Minimum Auxiliary Feedwater Flow Rate, lb m / 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, &deg;F 130 Minimum Accumulator Cover Gas Pressure (minus uncertainties), psia 600 Refueling Water Storage Tank Temperature, &deg;F 120 Nominal Steam Pressure, psia 791.863 SI Flow Delay Time, seconds 54 HHSI Cross-Tie Valve Position Open RHR Cross-Tie Valve Position Open (Injection)
Closed (Recirculation)


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, &deg;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, &deg;F                                                        130 Minimum Accumulator Cover Gas Pressure (minus uncertainties), psia                      600 Refueling Water Storage Tank Temperature, &deg;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.
(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&deg;F- 578.1 &deg;F with Tavg uncertainty range of +4.1 &deg;F / -5.6&deg;F.
(2) Analysis supports operation over the range of nominal full-power Tavg values of 547.6&deg;F - 578.1 &deg;F with Tavg uncertainty range of +4.1 &deg;F / - 5.6&deg;F.
(3) Analysis supports operation at nominal initial pressurizer pressure of 2100 psia and 2250 psia with +/-62.6 psi uncertainty.
(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)
Unit 2 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
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.
Time Sequence of Events for Small Break Loss-of-Coolant Accident
(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.
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 S I 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)
(4)     The latest point of sustained core uncovery/recovery is reported.
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 Recover y(4) N/A 5070 N/A(6) 2830 N/A N/A
(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.
Notes:
UNIT 2
(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 I NIN DD II AA NN AA MM II CC HH II GG AA NN PP OO WW EE RR Revision: 29.0 D.D. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT Table: 14.3.2-2a U PUP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS R ERE PP OO RR TT Page: 1 of 1


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.
TIME SEQUENCE OF EVENTS FOR SMALL BREAK LOSS -OF-COOLANT ACCIDENT UPFLOW CONVERSION
(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 (&deg;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:
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
(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 (&deg;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:
Accumulator Injection 830 RWST Volume Delivered(4) 2087.54
(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)
PCT Time (BOL) 969.0 Core Recovery(3) 2860 Notes
 
(1) S I is assumed to begin 54.0 seco nds (SI delay time) after the S -S ig n a l.
 
(2) Loop seal clearing is assumed to occur when the steam flow through the broken loop, loop seal i s sustain ed above 1 l bm/s and the mixture level i s at or below the top of the loop seal.
 
(3) The latest point of su stai ned core uncovery/recovery is reported
 
(4) The ana lys is assumes minimum usable RWST volume (280,000 gal) delivered v ia ECCS injection and containment spray before the low l evel RWST water l evel signal fo r sw itchover to c old l eg recirculation i s reached.
 
Unit 2 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 (&deg;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 M ax. 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 Zr0 2 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 I NIN DD II AA NN AA MM II CC HH II GG AA NN PP OO WW EE RR Revision: 29.0 D.D. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT Table: 14.3.2-3a U PUP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS R ERE PP OO RR TT Page: 1 of 1
 
SMALL BREAK LOSS -OF-COOLANT ACCIDENT CALCULATIONS UPFLOW CONVERSION
 
Break Size (in) 4.0 PCT ( &deg;F) 1348.7 PCT Time (s) 969.0 PCT Elevation (ft) 11.50 Max. Local ZrO 2 (%) 0.19 Max. Local ZrO 2 E lev. (ft) 11.25 Hot Rod Axial Average Z rO2 (%) 0.03 Note:
 
(1) The hot rod axial average ZrO 2 conservatively represents the core wide average oxidation, since the core wide average ZrO 2 thickness will always be less than the corresponding hot rod axial aver age ZrO 2 thickness.
 
Unit 2 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)
(1.5-inch through 6-inch breaks)
RCS Pressure Broken Loop                               Intact Loops (psia)       (lbm / sec)                           (lbm / sec)
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
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


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)
UNIT 2 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)
(1.5-inch through 6-inch breaks)
RCS Pressure Broken Loop                               Intact Loops (psia)       (lbm / sec)                           (lbm / sec)
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
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 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 - I njection 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)
RCS Pressure Broken Loop (lbm / sec) Intact Loops (lbm / sec)
(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 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 - I njection 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)
RCS Pressure Broken Loop (lbm / sec) Intact Loops (lbm / sec)
(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 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)
 
RCS Pressure Broken Loop / sec)
(psia) (lbm / sec) Intact Loops (lbm 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 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)
 
RCS Pressure Broken Loop / sec)
(psia) (lbm / sec) Intact Loops (lbm 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 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)
 
RCS Pressure Broken Loop (lb m / sec) Intact Loops (lbm / sec)
(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 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)


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)
RCS Pressure Broken Loop (lb m / sec) Intact Loops (lbm / sec)
Broken Loop (lbm / sec)                   Intact Loops (lbm / sec)
(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
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)
Unit 2 I NIN DD II AA NN AA MM II CC HH II GG AA NN PP OO WW EE RR Revision: 29.0 D.D. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT Table: 14.3.2-8 U PP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS U
Broken Loop (lbm / sec)                  Intact Loops (lbm / sec)
R ERE PP OO RR TT Page: 1 of 1
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)
PEAK CLADDING TEMPERATURE INCLUDING ALL PENALTIES AND BENEFITS, SMALL BREAK LOCA (SBLOCA) FOR D. C. COOK UNIT 2
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)
PCT for Analysis-of-Record 1274 F
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)
PCT Assessments Allocated to AOR
Broken Loop (lbm / sec)                Intact Loops (lbm / sec)
* Upflow Conversion +75F
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)
SBLOCA PCT for Comparison to 10 CFR 50.46 Requirements 1349F
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
Unit 2}}
* Upflow Conversion                                        +75F SBLOCA PCT for Comparison to 10 CFR 50.46 Requirements            1349F Unit 2}}

Latest revision as of 15:52, 15 November 2024

1 to Updated Final Safety Analysis Report, Chapter 14.3, Tables 14.3.1-1 to 14.3.2-8 (Unit 2)
ML22340A157
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 11/30/2022
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22340A137 List: ... further results
References
AEP-NRC-2022-62
Download: ML22340A157 (26)
v • d • e


Text

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

PARAMETER ANALYZED VALUE 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 t ype(2) clai oOptimized ZIRLO cladding, non-IFBA or IFBA e) Steam generator tube plugging level (5 ) 10%

17xl7 V5 Fuel with ZIRLO f) Fuel assembl y t ype(2) clai oOptimized ZIRLOcladding, 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 Q ) (2)(5) 2.335

Unit 2 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

PARAMETER ANALYZED VALUE OR RANGE

c) Peak hot rod enthalpy rise hot channel factor 1.644 (FH)(2)(5)

d) Hot assembly radial peaking factor (P HA ) (2) 1.644 / 1.04

e) Hot assembly heat flux hot channel factor (F QHA ) 2.335 / 1.04

f) Axial power distribution (P BOT, P MID ) (2) Figu re 14.3.1-2

g) Low power region relative power (P LO W ) (2) 0.20 PLO W 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 c ycle length 18 months

k) Minimum core average burn up (2) 10,000 MWD / MTU

l) Maximum steady state depletion, F Q (2) 1.90

2.2 Fluid Conditions

a) TAVG(5) 547.6 - 5.6ºF TAVG 578.1 + 4.1ºF

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 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

PARAMETER ANALYZED VALUE OR RANGE

d) Upper head design THOT

e) Pressurizer level (at hot full power) 59.8% of span (High T AVG )

40.0% of span (Low T AV G )

f) Accumulator temperature (5) 60ºF TACC 120ºF

g) Accumulator pressure 599.7 psia PACC 672.7 psia

h) Accumulator liquid volume 921 ft 3 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 S I T em p 105ºF

c) Safety injection delay (5) 27 seconds (with offsite power) 54 seconds (with LOOP) d) See Figures 14.3.1-3 thru 14.3.1-9 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 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

PARAMETER ANALYZED VALUE 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.
2. 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.
3. 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 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 INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT Revision: 24.0 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 ft 3 Upper (UC), LC: 295,258 ft 3 Lower (LC), IC: 122,350 ft 3 Ice Condenser (IC) and, DE: 60,209 ft 3 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 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 [ft 2] 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 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

Pressure HHSI + RHR Total (psia) Injected Flow (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 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

Pressure CHSI Total (psia) Injected Flow (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 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 INDIANAMICHIGAN 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 Peaking Factor +73°F

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 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 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 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, lb m / 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 RHR Cross-Tie Valve Position Open (Injection)

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 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 S I 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 Recover y(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 I NIN DD II AA NN AA MM II CC HH II GG AA NN PP OO WW EE RR Revision: 29.0 D.D. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT Table: 14.3.2-2a U PUP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS R ERE PP OO RR TT 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) S I is assumed to begin 54.0 seco nds (SI delay time) after the S -S ig n a l.

(2) Loop seal clearing is assumed to occur when the steam flow through the broken loop, loop seal i s sustain ed above 1 l bm/s and the mixture level i s at or below the top of the loop seal.

(3) The latest point of su stai ned core uncovery/recovery is reported

(4) The ana lys is assumes minimum usable RWST volume (280,000 gal) delivered v ia ECCS injection and containment spray before the low l evel RWST water l evel signal fo r sw itchover to c old l eg recirculation i s reached.

Unit 2 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 M ax. 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 Zr0 2 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 I NIN DD II AA NN AA MM II CC HH II GG AA NN PP OO WW EE RR Revision: 29.0 D.D. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT Table: 14.3.2-3a U PUP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS R ERE PP OO RR TT 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 ZrO 2 (%) 0.19 Max. Local ZrO 2 E lev. (ft) 11.25 Hot Rod Axial Average Z rO2 (%) 0.03 Note:

(1) The hot rod axial average ZrO 2 conservatively represents the core wide average oxidation, since the core wide average ZrO 2 thickness will always be less than the corresponding hot rod axial aver age ZrO 2 thickness.

Unit 2 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 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 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 - I njection 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)

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

(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 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 - I njection 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)

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

(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 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)

RCS Pressure Broken Loop / sec)

(psia) (lbm / sec) Intact Loops (lbm 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 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)

RCS Pressure Broken Loop / sec)

(psia) (lbm / sec) Intact Loops (lbm 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 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)

RCS Pressure Broken Loop (lb m / sec) Intact Loops (lbm / sec)

(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 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)

RCS Pressure Broken Loop (lb m / sec) Intact Loops (lbm / sec)

(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 I NIN DD II AA NN AA MM II CC HH II GG AA NN PP OO WW EE RR Revision: 29.0 D.D. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT Table: 14.3.2-8 U PP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS U

R ERE PP OO RR TT 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 1274 F

PCT Assessments Allocated to AOR

  • Upflow Conversion +75F

SBLOCA PCT for Comparison to 10 CFR 50.46 Requirements 1349F

Unit 2

Retrieved from "https://kanterella.com/w/index.php?title=ML22340A157&oldid=3716749"