ML21130A078
Text
VOLUME I - USAR LIST OF TABLES Table No.
I-3-1 Documents Incorporate d Into the CNS USAR by Reference I-3-4 I-4-1 Unacceptabl e Safety Results for Station Event Categories I-4-2 I-6-1 Comparison of Nuclear System Design Characteris tics I-6-2 I-6-2 Comparison of Power Conversion System Design Characteris tics I-6-10 I-6-3 Comparison of Electrical Power Systems Design Characteris tics I-6-11 I-6-4 Comparison of Containment Design Characteris tics I-6-12 I-6-5 Comparison of Structural Design Characteris tics I-6-14 I-7-1 Cooper Nuclear Station Topical Reports Submitted to the AEC in Support of Docket I-7-2 I-7-2 Cooper Nuclear Station ACRS Concerns - Resolution I-7-5 I-7-3 Cooper Nuclear Station AEC Staff Concerns -
Resolutions I-7-7 I-7-4 AEC-ACRS Concerns on Other Related Dockets - Cooper Capability for Resolution I-7-9 02/06/01
VOLUME I - USAR LIST OF TABLES Table No.
II-2-1 Population Histories and Projections at Various Distances from Reactor Building II-2-3 II-2-2 Population Histories and Projections by Selected Counties II-2-4 II-2-3 Population Histories and Projections of Selected Cities, Towns, and Villages II-2-5 II-3-1 Annual Climatalogi cal Data - Lincoln, Nebraska II-3-4 II-3-2 Annual Climatalogi cal Data - Omaha, Nebraska II-3-6 II-4-1 Missouri River Dams II-4-2 II-4-2 Analytical Determinatio n of River-Stage Discharge II-4-4 II-4-3 Chemical Characteris tics of Missouri River Water II-4-13 II-4-4 Bacteriolog ical Characteris tics of Missouri River Water II-4-14 II-5-1 Selected Design Earthquakes II-5-6 01/16/01
VOLUME I - USAR LIST OF TABLES Table No. Title III-2-3 Summary of Leading Experience on Operating Production Fuel - Zircaloy-Clad 00 2 Pellet Fuel III-2-7 III-2-4 General Electric Developmental Irradiations -
Zircaloy-Clad 95% TD UO 2 Pellet Fuel Rods III-2-8 III-2-5 General Electric Developmental Irradiations Zircaloy-Clad 95% TD UO 2 Pellet Capsules General Electric Test Reactor III-2-9 III-3-1 Reactor Vessel Fatigue Transient Occurrences III-3-3 III-3-2 Pressure Differences Across Reactor Vessel Internals III-3-12 III-7-1 End of Life Thermal and Hydraulic Conditions III-7-10 III-10-1 Core and Channel Decay Ratio Results III-10-4 III-10-2 Coordinates of Exclusion Region Boundary III-10-4 03/14/13
VOLUME II - USAR LIST OF TABLES Table No. Title IV-2-1 Typical Reactor Vessel Data IV-2-4 IV-2-2 Reactor Pressure Vessel Materials IV-2-5 IV-2-3 Reactor Vessel Attachments IV-2-6 IV-2-4 Initial RTNDT Estimates for Cooper Vessel A508 Class 2 Forgings IV-2-13 IV-2-5 Equivalent Transverse RTNDT Values For Reactor Vessel Materials IV-2-14 IV-3-1 Reactor Recirculation System Design Characteristics IV-3-3 IV-4-1 Nuclear System Safety and Relief Valves IV-4-3 IV-4-2 Low-Low Set Safety/Relief Valve System IV-4-9 IV-4-3 Safety Valve - Scram Availability IV-4-17 IV-7-1 Reactor Core Isolation Cooling System Turbine--
Pump Design Data IV-7-2 IV-8-1 Residual Heat Removal System Equipment Design Data IV-8-4 IV-9-1 RWCU System Equipment Design Data IV-9-3 12/20/04
VOLUME II - USAR LIST OF TABLES Table No.
V-2-1 Primary Containment System Principal Design Parameters and Characteristics V-2-3 V-2-2 Containment Vessel Penetration Schedule V-2-9 V-2-3 Drywell Atmosphere Cooling Data Sheet V-2-45 V-2-5 Primary Containment Pressure Control System Instrumentation V-2-52 V-2-6 Suppression Chamber Water Level Instrumentation V-2-54 V-3-1 Maximum Elevation of Terrain Within Half-Mile Interval Radial Distances from ERP V-3-6 V-3-2 Effective ERP Height Within Half-Mile Interval Radial Distances from ERP V-3-7 03/08/01
VOLUME II - USAR LIST OF TABLES Table No.
VI-3-1 Emergency Core Cooling Systems Equipment VI-3-3 Design Data Summary VI-5-1 ECCS Performance Results VI-5-5 VI-5-2 CNS Single Failure Evaluation VI-5-6 VI-5-3 Operational Parameters for LOCA Analysis VI-5-7 VI-5-4 Plant ECCS Parameters VI-5-8 VI-5-5 Summary of Results VI-5-12 03/08/00
VOLUME III - USAR LIST OF TABLES Table No. Title VII-1-1 System and Subsystem Separation VII-1-9 VII-1-2 Reactor Protection System and Primary Containment Isolation Inputs Sensor Suffix Letters and Division Allocation VII-1-25 VII-1-3 Reactor Protection System Four Division Grouping for a Six Channel Neutron Monitoring System VII-1-26 VII-1-4 Engineered Safety Feature (ESF) Sensor Suffix Letters and Division Allocation VII-1-27 VII-1-5 System and Subsystem Separation VII-1-28 VII-1-6 Documentation of Seismic Compliance with IEE-344 VII-1-31 or GIP-3 VII-1-7 Reactor Water Level Instrumentation VII-1-32 VII-2-1 Reactor Protection System Instrumentation Environmental Conditions VII-2-15 VII-2-2 Reactor Protection System/ATWS Scram Trip Functions and Analytical Limits VII-2-22 VII-3-2 Primary Containment Isolation System Instrument Specifications VII-3-10 VII-3-6 Primary Containment Isolation System (PCIS)
Signals and Isolations VII-3-21 VII-4-1 High Pressure Coolant Injection System Instrument Specifications VII-4-5 VII-4-2 Automatic Depressurization System Instrument Specifications VII-4-12 VII-4-3 Core Spray System Instrument Specifications VII-4-16 VII-4-4 Low Pressure Coolant Injection Instrument Specifications VII-4-20 VII-5-1 SRM Trips VII-5-5 VII-5-2 IRM Trips VII-5-10 VII-5-3 LPRM Trips VII-5-13 VII-5-4 APRM Trips VII-5-17 04/06/05
VOLUME III - USAR LIST OF TABLES (CONT'D)
Table No.
VII-6-1 Refueling Interlock Effectiveness VII-6-6 VII-7-1 Reactor Manual Control System Instrument Specifications VII-7-11 VII-8-1 Reactor Vessel Instrumentation Instrument Specifications VII-8-3 VII-8-2 Reactor Vessel Level and Pressure Instrument Cross Reference VII-8-4 VII-12-1 Process Radiation Monitoring Systems Characteristics VII-12-3 VII-12-2 Process Radiation Monitoring System Environmental and Power Supply Design Conditions VII-12-6 VII-13-1 Plant and Augmented Radwaste (Drum Handling)
Area Radiation Monitoring System Environmental and Power Supply Design Conditions VII-13-2 VII-13-2 Plant and Augmented Radwaste (Drum Handling)
Area Radiation Monitoring System Channels, Ranges, Locations VII-13-4 VII-16-1 Typical Nuclear Process Monitoring Instrumentation Input Summary VII-16-3 VII-16-2 Typical PMIS Instrumentation Output Summary Signal Output Description VII-16-8 01/23/01
VOLUME IV - USAR LIST OF TABLES Table No.
VIII-1-1 List of Major Electrical Equipment Normal, Startup and Emergency AC Power Sources VIII-1-2 VIII-1-2 List of Major Electrical Equipment Auxiliary Power System VIII-1-3 VIII-1-3 List of Major Electrical Equipment 125/250 Volt DC Power Systems VIII-1-4 VIII-4-1 List of Major Loads Auxiliary Power System VIII-4-4 VIII-5-1 Diesel Generator Loading Table Standby AC Power System VIII-5-3 VIII-5-2 Standby Diesel Generator System Typical Sequential Loading of Diesel Generators VIII-5-6 VIII-5-3 Standby AC Power Source Equipment VIII-5-11 Nominal Ratings VIII-5-4 Abnormal Diesel Generator Disabling Conditions and Control Room Indication VIII-5-12 02/28/00
VOLUME IV - USAR LIST OF TABLES Table No. Title IX-4-1 Gaseous Radwaste System Data IX-4-3 IX-4-2 Noncondensible Gas Flow Rates (Lb/Hr) Entering Augmented Off-Gas Treatment System IX-4-7 IX-4-3 Stream Composition After Dilution IX-4-9 IX-4-4 Activity Profile IX-4-12 IX-4-5 Maximum Expected Activity Release to the Environment From Gland Seal Leakage IX-4-15 IX-4-6 Particulates Buildup in Environment IX-4-16 IX-4-7 System Failure Analysis IX-4-18 03/20/01
VOLUME IV - USAR LIST OF TABLES Table No.
X-5-1 Fuel Pool Cooling and Demineraliz er System - System Performance X-5-2 X-6-1 Equipment Supplied by the REC System X-6-3 X-6-2 REC System Equipment Data - No. of Subsystems - 2 X-6-4 X-7-1 Equipment Cooled by the TEC System X-7-2 X-7-2 Turbine Equipment Cooling System Equipment Data X-7-3 10/25/00
VOLUME IV - USAR LIST OF TABLES Table No. Title Page XII-2-1 Allowable Stresses for Class I Structures XII-2-12 XII-2-2 Live Vertical Loads XII-2-14 XII-2-3 Responses Obtained from Modal Analysis XII-2-24 XII-2-4 Station Structures - Damping Factor XII-2-28 XII-2-5 Jet Forces Loading on Primary Containment XII-2-32 XII-3-1 Station Shielding Design Basis Limitations XII-3-2 01/17/14
VOLUME V - USAR LIST OF TABLES Table No. Title Page XIII-3-1 Job Title Matrix XIII-3-3 XIII-5-1 Startup and Power Test Program XIII-5-3 XIII-10-2 Power Block Buildings XIII-10-5 04/08/15
VOLUME V - USAR LIST OF TABLES Table No. Title Page XIV-5-1 Input Parameters and Initial Conditions for SAR Transient Analyses for Initial Core Only XIV-5-4 XIV-5-2 Input Parameters and Initial Conditions for Transient Analyses for Reload Licensing Analysis (RLA) XIV-5-6 XIV-5-4 Conditions for ATWS Event Analyses XIV-5-48 XIV-6-1 Determination of the CRDA Source Term XIV-6-7 XIV-6-2 X/Q Values for the Exclusion Area Boundary and Low Population Zone XIV-6-9 XIV-6-3 CRDA Exclusion Area Boundary, Low Population Zone, and Control Room Radiological Dose Consequences XIV-6-10 XIV-6-4 Comparison of Cooper Containment and Bodega Bay Test Facility XIV-6-18 XIV-6-5 Input Parameters Used for OBA LOCA Primary Containment Analysis XIV-6-22 XIV-6-6 Loss-of-Coolant Accident Primary Containment Response Summary XIV-6-24 XIV-6-7 SGT System Flows and Iodine Removal Efficiencies XIV-6-32 XIV-6-8 X/Q Values for the Exclusion Area Boundary and Low Population Zone XIV-6-33 XIV-6-9 X/Q Values for the Control Room Intake XIV-6-34 XIV-6-10 Loss-of-Coolant Accident Exclusion Area Boundary, Low Population Zone, and Control Room Radiological Dose Consequences XIV-6-35 XIV-6-11 Fuel Handling Accident Secondary Containment Airborne Fission Product Inventory 24 Hours After Shutdown XIV-6-39 XIV-6-14 X/Q Values for the Exclusion Area Boundary and Low Population Zone XIV-6-42 XIV-6-15 X/Q Values for the Control Room Intake XIV-6-43 XIV-6-16 Fuel Handling Accident Exclusion Area Boundary, Low Population Zone, and Control Room Radiological Dose Consequences XIV-6-44 XIV-6-17 Plant Operational Parameters Used in Cooper SAFER/GESTR-LOCA Analysis XIV-6-47 07/14/11
VOLUME V - USAR LIST OF TABLES (CONT'D)
Table No. Title XIV-6-18 Main Steam Line Break Accident Sequence for 10CFRS0.46 and 10CFR50 Appendix K XIV-6-48 XIV-6-19 Main Steam Line Break Accident Radiological Dose Consequences XIV-6-53 XIV-6-20 Dose for Various Main Steam High Flow Settings XIV-6-55 XIV-7-1 Station Safety Analysis, Results of Abnormal Operational Transients XIV-7-3 XIV-7-2 Supplemental Reload Licensing Report Results for Cooper Nuclear Station Reload 31 Cycle 32 XIV-7-5 XIV-7-3 Station Safety Analysis, Results of Design Basis Accidents XIV-7-7 XIV-8-1 Activity, Mass Loading and Heat Loading at Various Locations for TID-14844 Release Assumptions XIV-8-3 XIV-8-2 Standby Gas Treatment System Heat Loads and Temperatures for RG 1.183 AST LOCA Release Assumptions XIV-8-4 XIV-8-3 Dose Rates and Integrated Doses for Various Equipment and Locations Based on TID-14844 Release Assumptions XIV-8-6 02/22/21
VOLUME VI - USAR LIST OF TABLES Table No. Title C-2-1 Reactor Building Foundation C-2-7 C-2-2 Reactor Building Floor System C-2-8 C-2-3 Reactor Building Concrete Walls C-2-9 C-2-4 Reactor Building Structural Steel Columns C-2-11 C-2-5 Reactor Building Steel Roof Truss-Frame Above El. 117' C-2-12 C-2-6 Drywell Shielding Concrete C-2-14 C-2-7 Reactor Concrete Pedestal C-2-16 C-2-8 Drywell Membrane Stresses C-2-19 C-2-9 Jet Impingement Force Stresses C-2-20 C-2-10 Drywell Stabilizer Shear Lugs C-2-22 C-2-11 Summary of Mark I Containment and Piping Modifications C-2-28 C-2-12 Original Tabulation of Critical Pipe Stresses Due to Dead Weight Plus Pressure, Plus Operating Basis Earthquake, Plus Thermal Loads C-2-32 C-2-13 Control Building Foundation C-2-39 C-2-14 Control Building Floor System C-2-40 C-2-15 Control Building Concrete Walls C-2-41 C-2-16 Elevated Release Point Foundations and Tower C-2-43 C-3-1 Loading Condition Probabilities C-3-4 C-3-2 Deformation Limit C-3-5 C-3-3 Primary Stress Limit C-3-6 C-3-4 Buckling Stability Limit C-3-8 C-3-5 Fatigue Limit C-3-9 C-3-6 Minimum Safety Factors C-3-10 C-3-7 Loading Criteria C-3-11 Reactor Vessel Internals and Associated Equipment C-3-11 Main Steam Piping C-3-24 Recirculation Loop Piping C-3-26 01/02/15
VOLUME VI - USAR LIST OF TABLES (CONT'D)
Table No.
C-3-7 Cont. Class IN/IS - Core Spray Discharge Piping CS-ID C-3-27 Class IN/IS - Clean-Up Recirculatio n Pump Suction Piping CU-IS C-3-28 Class IN/IS - Main Steam Piping to HPCI Turbine and Residual Heat Exchangers lA and 1B C-3-29 Class IN/IS - Reactor Feed Piping C-3-31 Class IN/IS - Residual Heat Removal Pump Suction Piping C-3-33 Class IN/IS - Residual Heat Removal Pump Discharge Piping C-3-35 Recirculatio n Pumps C-3-37 RHR Pump C-3-41 Core Spray Pump C-3-43 HPCI Pump C-3-45 RCIC Pump C-3-47 Standby Liquid Control Pump C-3-49 HPCI Turbine C-3-51 RCIC Turbine C-3-55 Main Steam Isolation Valves C-3-59 Main Steam Safety Valves C-3-62 Main Steam Relief Valves C-3-67 Recirculatio n Valves C-3-70 Standby Liquid Control Tank C-3-73 03/08/01
VOLUME VI - USAR LIST OF TABLES Table No.
D(l)-1-1 Quality Assurance Manual List of Abbreviatio ns D (1) 2 10/04/99
VOLUME VI - USAR LIST OF TABLES Table No. Page G-3-1 BWR Operating States G-3-2 G-4-1 Events Applicable in Each BWR Operating State G-4-2 10/04/99 I
VOLUME VI - USAR LIST OF TABLES Table No. Title Page K-2-1 Newly-Identifie d SSCs Requiring Aging Management K-2-35 K-4-1 Consolidated List of License Renewal Commitments K-4-2 03/04/15