ML21125A574
Text
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.1-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 Parameters Used for the Control Room Radiological Consequence Analysis of a Fuel Handling Accident Parameter Value Core Power Level 3480 MWt Radial Peaking Factor 1.65 Number of Damaged Assemblies 1 Decay Time 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> Core Fractions Released from Damaged Rods I-131 0.08 Other Halogens 0.05 Kr-85 0.10 Other Noble Gases 0.05 Alkali Metals 0.12 Core Release Fraction Multiplier for High Burnup 2.0 Fuel Depth of Water Above Damaged Fuel 23 ft Pool Decontamination Factors Elemental Iodine 285 Organic Iodine 1 Noble Gases 1 Particulates Infinite Release Duration 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Iodine Chemical Form Elemental 99.85%
Organic 0.15%
Particulate 0%
Fuel Handling Area Ventilation Filter Efficiency1 Elemental Iodine 89.1%
Organic Iodine 89.1%
Particulates 98.01%
Release Location Containment Offsite Unit 1 Containment Surface Containment Onsite Unit 2 Containment Closest Point Auxiliary Building Unit 1 Vent 1
Includes 1% filter bypass leakage Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.1-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 Parameters Used for the Control Room Radiological Consequence Analysis of a Fuel Handling Accident Parameter Value Offsite Breathing Rate 0 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.5E-04 m3/sec 8 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.8E-04 m3/sec 24 - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 2.3E-04 m3/sec Control Room Parameters Volume 50,616 ft3 Normal Ventilation Makeup Flow Rate 880 cfm Emergency Ventilation Makeup Flow Rate 880 cfm Emergency Ventilation Recirculation Flow 4520 cfm Rate Emergency Ventilation Filter Efficiency1 Elemental Iodine 94.05%
Organic Iodine 94.05%
Particulates 98.01%
Delay to Switch to Emergency Mode 20 minutes (manual)
Unfiltered Inleakage 40 cfm Occupancy Factors 0 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.0 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 0.6 96 - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 0.4 Breathing Rate 3.5E-04 m3/sec Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 Parameters Used for the Radiological Consequence Analysis of a Steam Generator Tube Rupture Parameter Value Core Power Level 3480 MWt Fuel Clad Failure 0%
Primary Coolant Limit for Normal Operation Iodines 1.0 Ci/gm D.E. I-131 Non-Iodines 100/E-bar (215.1 Ci/gm D.E. Xe-133 Pre-Accident Spike RCS Iodine Concentration 60.0 Ci/gm D.E. I-131 Concurrent Iodine Spike Appearance Rates Table 14.A.3-5 Appearance Rate Multiplier 335 Spike Duration 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Secondary Coolant Limit for Normal Operation 0.1 Ci/gm D.E. I-131 Primary Coolant Mass 466,141.5 lbm Secondary System Mass 97,515.7 lbm/SG (minimum) 161,000 lbm/SG (maximum)
Ruptured Tube Break Flow 146,704 lbm Duration of Ruptured Tube Break Flow 30 minutes Primary-to-Secondary Leak Rate 0.25 gpm to each steam generator Initial Intact Steam Generator Mass 0 - 30 minutes 198,515 lbm 30 min - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 314,432 lbm 2 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1,367,475 lbm 8 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1,347,000 lbm Ruptured Steam Generator Steam Release 66,171 lbm Pre-Trip Steam Flow to Condenser 17,153,800lbm/hr Time of Reactor Trip 101 seconds Break Flow Flashing Fractions Pre-Trip:
0 - 100 seconds: 19%
Post-Trip:
100-500 seconds: 8%
500-1000 seconds: 6%
1000-1800 seconds: 5.5%
Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 Parameters Used for the Radiological Consequence Analysis of a Steam Generator Tube Rupture Parameter Value Duration of Intact SG Tube Recovery After Reactor 40 minutes Trip Intact Tube Leakage Flashing Fraction During 0-100 seconds: 19%
Uncovery 100-500 seconds: 8%
500-1000 seconds: 6%
1000-1800 seconds: 5.5%
1800 seconds - 40 min.: 4%
Partition Coefficients Iodines 100 Alkali Metals 500 Noble Gases 1 Condenser (Iodines & Particulates) 100 Iodine Chemical Form Elemental 97%
Organic 3%
Particulate 0%
Release Location Offsite Pre-Trip Unit 1 Turbine Building Offsite Post-Trip Unit 1 Main Steam Enclosures Onsite Pre-Trip Unit 1 Steam Jet Air Ejector Onsite Post-Trip Unit 2 PORVs/MSSVs Offsite Breathing Rates 0-8 hours 3.5E-04 m3/sec 8-24 hours 1.8E-04 m3/sec 24-720 hours 2.3E-04 m3/sec Control Room Parameters Volume 50,616 ft3 Normal Ventilation Makeup Flow Rate 880 cfm Emergency Ventilation Makeup Flow Rate 880 cfm Emergency Ventilation Recirculation Flow 4520 cfm Rate Emergency Ventilation Filter Efficiency1 Elemental Iodine 94.05%
Organic Iodine 94.05%
Particulates 98.01%
1 Includes 1% filter bypass leakage Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 Parameters Used for the Radiological Consequence Analysis of a Steam Generator Tube Rupture Parameter Value Delay to Switch to Emergency Mode 394.74 seconds (Safety Injection)
Unfiltered Inleakage 40 cfm Occupancy Factors 0-24 hours 1.0 24-96 hours 0.6 96-720 hours 0.4 Breathing Rate 3.5E-04 m3/sec Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.2.5-1 Page: 1 of 1 UPDATED FINAL SAFETY ANALYSIS REPORT Rupture of a Steam Pipe Limiting Statepoints Time Pressure Heat Flux Inlet Temp. Flow Boron Reactivity Density sec psia Fraction Cold °F Hot °F Fraction ppm Percent gm / cc Hot zero power (double ended rupture downstream of the flow 76.2 709.49 .223 372.8 443.4 1.0 .19 .043 .848 restrictor with offsite power available)
Full power (0.89 ft2 rupture, largest 25.4 2,197.10 1,260 524.1 530.3 1.0 0.0 .011 .722 break size to trip on OPT)
Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 14.2.5-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Rupture of a Steam Pipe Time Seq uence of Events Time Case Event
( sec)
S team line rupture occurs 0.00 L ow steam line pressure reached 0.80 S teamline I solation (L oops 2, 3, and 4) 11.80 Hot Z ero Power Pressurizer empties 14.00 C riticality attained 14.20 (double ended rupture downstream of the flow restrictor with offsite power S I flow starts 27.80 available) B oron from S I reaches the core 38.40 Feedwater I solation (A ll loops) 68.80 Peak heat flux attained 72.60 C ore becomes subcritical 134.6 S team line rupture occurs 0.0 OPT rea tor trip setpoint rea e Full Power 22.6 (all loops)
(0.89 ft2 rupture, largest break s ize to Rod motion initiated 24.6 trip on OPT)
Peak core heat flux attained 25.2 M inimum D N B R occurs 25.4 Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.5-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 Parameters Used for the Radiological Consequence Analysis of a Main Steam Line Break Parameter Value Core Power Level 3480 MWt Fuel Clad Failure 0%
Primary Coolant Limit for Normal Operation Iodines 1.0 Ci/gm D.E. I-131 Non-Iodines 100/E-bar (215.1 Ci/gm D.E. Xe-133)
Pre-Accident Spike RCS Iodine Concentration 60.0 Ci/gm D.E. I-131 Concurrent Iodine Spike Appearance Rates Table 14.A.3-5 Appearance Rate Multiplier 500 Spike Duration 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Secondary Coolant Limit for Normal Operation 0.1 Ci/gm D.E. I-131 Primary Coolant Mass 466,141.5 lbm Secondary System Mass 97,515.7 lbm/SG (minimum) 161,000 lbm/SG (maximum)
Primary-to-Secondary Leak Rate 0.25 gpm to each steam generator Intact Steam Generator Steam Release 0-2 hours 456,000 lbm 2 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1,186,000 lbm 8 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1,347,000 lbm Duration of Intact SG Tube Uncovery After Reactor 40 minutes Trip Intact Tube Leakage Flashing Fraction During 0-400 seconds: 8%
Uncovery 400-900 seconds: 6%
900-1700 seconds: 5.5%
1700 seconds-40 min: 4%
Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.5-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 Parameters Used for the Radiological Consequence Analysis of a Main Steam Line Break Parameter Value Partition Coefficients Iodines 100 Alkali Metals 500 Noble Gases 1 Iodine Chemical Form Elemental 97%
Organic 3%
Particulate 0%
Release Location Offsite Unit 1 Turbine Building Onsite Faulted SG Unit 2 Turbine Building Onsite Intact SGs Unit 2 PORVs/MSSVs Offsite Breathing Rates 0-8 hours 3.5E-04 m3/sec 8-24 hours 1.8E-04 m3/sec 24-720 hours 2.3E-04 m3/sec Control Room Parameters Volume 50,616 ft3 Normal Ventilation Makeup Flow Rate 880 cfm Emergency Ventilation Makeup Flow Rate 880 cfm Emergency Ventilation Recirculation Flow 4520 cfm Rate Emergency Ventilation Filter Efficiency1 Elemental Iodine 94.05%
Organic Iodine 94.05%
Particulates 98.01%
Delay to Switch to Emergency Mode 70 seconds (Safety Injection) 1 Includes 1% filter bypass leakage Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.5-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 Parameters Used for the Radiological Consequence Analysis of a Main Steam Line Break Parameter Value Unfiltered Inleakage 40 cfm Occupancy Factors 0-24 hours 1.0 24-96 hours 0.6 96-720 hours 0.4 Breathing Rate 3.5E-04 m3/sec Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 18.1 D. C. COOK NUCLEAR PLANT Table: 14.2.6-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PARAMETERS USED IN THE ANALYSIS OF THE ROD CLUSTER CONTROL ASSEMBLY EJECTION ACCIDENT HZP HFP TIME IN LIFE HZP END HFP END BEGINNING BEGINNING Power Level (%)1 0 102 0 102 Ejected Rod Worth (%k) 0.65 0.15 0.75 0.19 Delayed Neutron Fraction (%) 0.0050 0.0050 0.0040 0.0040 Feedback Reactivity Weighting 2.071 1.30 2.755 1.30 Trip Reactivity (%k) 2. 4. 2. 4.
Fq Before Rod Ejection 2.50 2.50 2.50 2.50 Fq After Rod Ejection 12. 6.8 19. 7.1 Number of Operational Pumps 2 4. 2. 4.
Maximum Fuel Pellet Average 2764 4056 2963 3969 Temperature (oF)
Maximum Fuel Center 3120 4968 3258 4872 Temperature(ºF)
Maximum Clad Average 2130 2299 2322 2245 Temperature (ºF)
Maximum Fuel Stored 112.7 177.3 122.2 172.7 Energy (cal/gm)
Fuel Melt in Hot Pellet, % 0 <10 0 <10 1
Power level based upon a core power of 3250 MWt.
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.6-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 Parameters Used for the Radiological Consequence Analysis of a Rod Ejection Accident Parameter Value Core Power Level 3480 MWt Fuel Clad Failure 10%
Core Fuel Melt 0.25%
Core Fractions Released from Damaged Rods Iodines 0.10 Noble Gases 0.10 Alkali Metals 0.12 Fuel Rod Peaking Factor 1.65 Core Release Fraction Multiplier for High Burnup Fuel 1.0104 Release Fractions for Melted Fuel Containment Leakage Release Path Iodines 25%
Noble Gases 100%
Secondary System Release Path Iodines 50%
Noble Gases 100%
Secondary Coolant Limit for Normal Operation 0.1 µCi/gm D.E. I-131 Containment Leakage Release Path Parameters Containment Volume 1,066,352 ft3 Containment Leakage Rate 0 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.18 %/day 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> - 30 days 0.09 Containment Leakage Filtration 0%
Iodine Chemical Form Elemental 4.85%
Organic 0.15%
Particulate 95%
Natural Deposition Elemental Iodine None Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.6-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 Parameters Used for the Radiological Consequence Analysis of a Rod Ejection Accident Parameter Value Organic Iodine None Particulate 0.1 hr-1 after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Iodine/Particulate Removal by Containment Sprays None Release Location Offsite Unit 1 Containment Surface Onsite Unit 2 Containment Surface Secondary Leakage Path Parameters Primary Coolant Mass 466,141.5 lbm Secondary System Mass 97,515.7 lbm/SG (minimum) 161,000 lbm/SG (maximum)
Primary-to-Secondary Leak Rate 1 gpm to all steam generators Steam Generator Steam Release 0-2 hours 460,000 lbm 2-8 hours 1,256,000 lbm 8-24 hours 1,347,000 lbm Partition Coefficients Iodines 100 Alkali Metals 500 Noble Gases 1 Duration of Intact SG Tube Uncovery After Reactor Trip 40 minutes Intact Tube Leakage Flashing Fraction During Uncovery 0-400 seconds: 8%
400-900 seconds: 6%
900-1700 seconds: 5.5%
1700 seconds-40 min: 4%
Iodine Chemical Form Elemental 97%
Organic 3%
Particulates 0%
Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 14.2.6-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 Parameters Used for the Radiological Consequence Analysis of a Rod Ejection Accident Parameter Value Release Location Offsite Unit 1 Main Steam Enclosure Onsite Unit 2 PORVs/MSSVs Offsite Breathing Rates 0-8 hours 3.5E-04 m3/sec 8-24 hours 1.8E-04 m3/sec 24-720 hours 2.3E-04 m3/sec Control Room Parameters Volume 50,616 ft3 Normal Ventilation Makeup Flow Rate 880 cfm Emergency Ventilation Makeup Flow Rate 880 cfm Emergency Ventilation Recirculation Flow Rate 4520 cfm Emergency Ventilation Filter Efficiency1 Elemental Iodine 94.05%
Organic Iodine 94.05%
Particulates 98.01%
Delay to Switch to Emergency Mode 120 minutes (Safety Inspection)
Unfiltered Inleakage 40cfm Occupancy Factors 0-24 hours 1.0 24-96 hours 0.6 96-720 hours 0.4 Breathing Rate 3.5E-04 m3/sec 1
Includes 1% filter bypass leakage Unit 1
UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 14.2.7-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 LOSS OF A.C. POWER TO THE PLANT AUXILIARIES STEAM RELEASE 0-2 HOURS 2-8 HOURS Steam release from 4 S.G.'s, lbs 443,000 1,000,000 Feedwater flow to 4 S.G.'s, lbs 643,000 1,128,000