ML19137A124
| ML19137A124 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/24/2019 |
| From: | Nebraska Public Power District (NPPD) |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19137A206 | List:
|
| References | |
| NLS2019023 | |
| Download: ML19137A124 (29) | |
Text
VOLUME I - USAR 02/06/01 LIST OF FIGURES (At End of Section I)
Figure No.
Title I-1-1 Reactor Heat Balance - Rated I-2-1 Relationship Between Safety Action and Protective Action I-2-2 Relationship Between Protective Functions and Protective Actions I-2-3 Relationship Between Different Types of Systems Actions and Objectives I-5-1 Relationship of Various Categories of Systems
VOLUME I - USAR 01/16/01 LIST OF FIGURES (At end of Section II)
Figure No.
Title II-1-1 Site Map Depicting Location of Nearest Airport II-2-1 Aerial Photograph of Site II-2-2 Site Location Plan II-2-3 Population Distribution (0-5 Miles Radial Distance from Site)
II-2-4 Population Distribution (5-50 Miles Radial Distance from Site)
II-2-5 Area Boundary Locations II-4-1 Location of Upstream Dams II-4-2 Missouri River Hydraulic Data, 1955-1958 II-4-3 Missouri River Hydraulic Data, 1959-1962 II-4-4 Missouri River Hydraulic Data, 1963-1966 II-4-5 Missouri River Hydraulic Data, 1967-1969 II-4-6 Flood Profiles II-4-7 Platte Plus Missouri River(s) Hydrograph II-4-8 Estimated Stage Discharge
- Relation, Missouri River at Brownville, Nebraska II-4-9 Levee System/Flood Control Project, Missouri River II-5-1 Regional Bedrock Geology and Cross-Section II-5-2 Configuration of Precambrian Surface and Principal Structural Features in Southeastern Nebraska II-5-3 Generalized Columnar Section of Rock Underlying Region II-5-4 Stratigraphic Chart of Portions of Wabaunsee Group and a Plan of its Outcroppings in Southeastern Nebraska II-5-5 Interpreted Location of Former Natural Levees II-5-6 Earthquake Epicenter Map
VOLUME I - USAR 01/16/01 LIST OF FIGURES (CONT'D)
(At end of Section II)
Figure No.
Title II-5-7 Design Acceleration Response Spectra for Maximum Probable Design Earthquake (Arithmetic Plot)
II-5-8 Design Response Spectra for Maximum Probable Design Earthquake (Four Way Logarithmic Plot)
II-5-9 Design Acceleration Response Spectra for Hypothetical Maximum Possible Design Earthquake (Arithmetic Plot)
II-5-10 Design Response Spectra for Hypothetical Maximum Possible Design Earthquake (Four Way Logarithmic Plot)
II-5-11 Comparison Between FSAR Design Acceleration Response Spectra and Average Acceleration Spectra II-5-12 Comparison of Unsmoothed Acceleration Response Spectra from Taft and El Centro Accelerograms for 2% Damping II-5-13 Comparison of Unsmoothed Acceleration Response Spectra from Taft and El Centro Accelerograms for 20% Damping
VOLUME I - USAR 02/20/17 LIST OF FIGURES (At End of Section III)
Figure No.
Title III-2-1 Typical GE BWR Fuel Assembly III-2-4 Schematic of Four Bundle Cell Arrangement III-3-1 Reactor Internals Arrangement III-3-2 Reactor Internals Flow Paths III-3-3 Axial Flow Steam Separator III-3-4 Fuel Support Pieces III-3-5 Jet Pump Assembly III-3-6 Steam Dryer III-3-7 Pressure Nodes Used for Depressurization Analysis III-3-8 Transient Pressure Differentials Following Steam Line Break at 105-Percent Rated Steam Flow III-3-9 Transient Pressure Differentials Following Steam Line Break at 20-Percent Rated Power and 110-Percent Rated Recirculation Flow III-3-10 Analytical Model of Reactor Vessel Internals III-4-1a Marathon Control Rod Assembly III-4-2 Control Rod Velocity Limiter III-5-1 Control Rod to Control Rod Drive Coupling III-5-2 Control Rod Drive Unit III-5-3 Control Rod Drive Unit (Schematic)
III-5-4 Control Rod Drive Unit (Cutaway)
III-5-8 Control Rod Drive Hydraulic Control Unit III-6-1 Generic Figure-Stuck Rod Margin as Function of Core Average Exposure
VOLUME I - USAR 08/07/08 LIST OF FIGURES (CONT'D)
(At End of Section III)
Figure No.
Title III-6-2 Generic Figure-Fractional Control Rod Density versus Average Moderator Density III-6-3 Generic Figure-Maximum Rod Worth versus Moderator Density III-6-4 Generic Figure-Maximum Rod Worth versus Power Level III-6-5 Generic Figure-Doppler Coefficient of Reactivity III-6-6 Generic Figure-Doppler Coefficient as Function of Fuel Exposure III-6-7 Generic Figure-Core Average Doppler Defect versus Core Power Level III-6-8 Generic Figure-Doppler Defect versus Fuel Temperature III-6-9 Generic Figure-Moderator Void Coefficient of Reactivity III-6-10 Generic Figure-Xenon Reactivity Buildup After Shutdown -
Beginning of Life III-6-11 Generic Figure-Relative Xenon Stability with No Flux Flattening III-6-12 Generic Figure-Effect of Power Density on Axial Xenon Stability Including Void Transport III-6-13 Generic Figure-Azimuthal Xenon Stability III-6-14 Generic Figure-Control Rod Scram Reactivity Characteristics Excursion Analysis III-6-15 Generic Figure-Scram Characteristics Assumed for Transient Analysis III-7-1a Operating Map III-7-1b Power/Flow Map - MELLL and ICF III-7-3 Gross Power Peaking versus Exposure III-7-4a Axial Power Distribution (Case 1)
III-7-4b Axial Power Distribution (Case 2)
III-8-1 Control Rod Drive Housing Support III-10-1 Power to Flow Operating Map
VOLUME II - USAR 02/22/17 LIST OF FIGURES (At end of Section IV)
Figure No.
Title IV-3-1 Recirculation System - Elevation, Isometric IV-3-4 Jet Pump - Operating Principle IV-3-5 Recirculation System Core Flooding Capability IV-3-6 Recirculation Pump Trip (RPT) Logic Configuration IV-4-2 Nuclear System Relief Valve Closed Position IV-4-3 Nuclear System Relief Valve Open Position IV-4-4a Safety Valve Sizing Transient: MSIV Closure with Flux Scram IV-4-4b MSIV Closure Transient (Flux Scram) (MELLLA, 1 SRV 00S, HBB)
IV-4-4c MSIV Closure Transient (Flux Scram) (ICF, 1 SRV OOS, HBB)
IV-4-d MSIV Closure Transient (Flux Scram) (MELLLA, 1 SRV OOS, Max SRV Setpoints)
IV-4-5 Mark I T-Quencher Discharge Device IV-6-1 Main Steam Line Isolation Valve IV-9-4 RWCU Leak Detection and Isolation
VOLUME II - USAR 05/30/00 LIST OF FIGURES (At end of Section V)
Figure No.
Title V-2-1 Primary Containment Pressure Suppression System V-2-2 Pressure Suppression Chamber V-2-3 Primary Containment High Pressure Process Line Penetration -
Type 1 V-2-4 Primary Containment Process Line Penetration - Type 2 V-2-5 Primary Containment Process Line Penetration - Type 3 V-2-6 Typical Instrument Penetration V-2-14 Containment Atmosphere Monitoring System
VOLUME II - USAR 02/11/13 LIST OF FIGURES (At end of Section VI)
Figure No.
Title VI-5-15 Minimum Containment Pressure for Operation of ECCS Pumps (0-1000 seconds)
VI-5-16 Minimum Containment Pressure for Operation of ECCS Pumps (1000-106 seconds)
VOLUME III - USAR 02/11/13 LIST OF FIGURES (At End of Section VII)
Figure No.
Title VII-1-1 Use of Protective System Control and Instrumentation Definitions VII-1-2 Single-Cycle-BWR Control System (Flow Control Section)
Functional Block Diagram VII-1-3 Reactor Protection System Scram Trip Circuits VII-1-4 ESF Separation Concept VII-1-5 Cable Separation Scheme - ESF VII-1-6 Primary Containment Isolation System Separation Concept VII-2-3 Schematic Diagram of Logics in One Trip System VII-2-4 Schematic Diagram of Actuators and Actuator Logics VII-2-5 Reactor Protection System, Scram Functions VII-2-7 Relationship Between Neutron Monitoring System and Reactor Protection System VII-2-8 Functional Control Diagram for Neutron Monitoring System Logics VII-2-9 Typical Arrangement of Channels and Logics VII-2-11 Typical Configuration for Main Steamline Isolation Scram VII-3-3 Reactor Building - Plan, Elevation 859 ft. 0 in.
VII-3-4 Reactor Building - Plan, Elevation 903 ft. 6 in.
VII-3-5 Main Steam Power Supply and Logic VII-4-9 LPCI Component Arrangement VII-4-10 Typical Emergency Core Cooling System (ECCS) Instrumentation VII-5-2a Detector Drive System VII-5-3 Functional Block Diagram of SRM Channel VII-5-5 Source Range Monitoring System Core Locations VII-5-6 Functional Block Diagram of IRM Channel VII-5-7 IRM Locations
VOLUME III - USAR 02/11/13 LIST OF FIGURES (CONT'D)
(At End of Section VII)
Figure No.
Title VII-5-8 Control Rod Withdrawal Error VII-5-9 Normalized Flux Distribution for Rod Withdrawal Error VII-5-11 LPRM Locations VII-5-13a LPRM to APRM Assignment Scheme (System A)
VII-5-13b LPRM to APRM Assignment Scheme (System B)
VII-5-14 Envelope of Maximum APRM Deviation, Reduction in Power by Flow Control VII-5-15 APRM Tracking With On-Limits Control Rod Withdrawal VII-5-16 Assignment of LPRM Assemblies to RBM's VII-5-18 Assignment of LPRM Strings to TIP Machines VII-5-19 Traversing In-Core Probe Subsystem Block Diagram VII-5-23 Ranges of Neutron Monitoring System VII-5-24 Typical IRM Circuit Arrangement for Reactor Protection System Input VII-5-25 Typical APRM Circuit Arrangement for Reactor Protection System Input VII-6-1 Refueling Interlocks VII-7-2 RBM Flow Variance Circuit, Schematic VII-7-4 Typical Process Computer Printout VII-9-1 Recirculation Flow Control, Illustration VII-9-4 Recirculation Pump Trip (RPT) Logic Configuration VII-12-2 Effluent Radiation Monitoring System VII-13-2 Area Radiation Monitoring System
VOLUME IV - USAR 02/11/13 LIST OF FIGURES (At End of Section VIII)
Figure No.
Title VIII-2-3 345 kV Switchyard One Line Diagram
VOLUME IV - USAR 02/11/13 LIST OF FIGURES (At End of Section IX)
Figure No.
Title None
VOLUME IV - USAR 02/11/13 LIST OF FIGURES (At end of Section X)
Figure No.
Title X-3-1 Fuel Cask Area Holtec Rack A Layout X-3-2 Fuel Cask Area Holtec Rack B Layout X-4-10 Horizontal Controlled Path of Spent Fuel Cask X-8-4 Water Jet Spraying System at Bottom of Intake Structure
VOLUME IV - USAR 02/11/13 LIST OF FIGURES (At End of Section XI)
Figure No.
Title None
VOLUME V - USAR 02/11/13 LIST OF FIGURES (At end of Section XII)
Figure No.
Title None
VOLUME V - USAR 12/10/14 LIST OF FIGURES (CONT'D)
(At end of Section XIII)
Figure No.
Title XIII-2-2 NPG Management Organization XIII-2-4 Construction Test XIII-2-5 Pre-Op and Startup Test XIII-5-1 Startup Test Sequence
VOLUME V - USAR 02/22/17 LIST OF FIGURES (At end of Section XIV)
Figure No.
Title XIV-4-1 Station Safety Analysis - Method for Identifying and Evaluating Abnormal Operational Transients XIV-4-2 Station Safety Analysis - Method for Identifying and Evaluating Accidents XIV-5-1 Generator Trip (Load Rejection) with Bypass XIV-5-2a Generator Trip (Load Rejection) without Bypass, BOC to MOC1 : MELLLA-HBB XIV-5-2b Generator Trip (Load Rejection) without Bypass, MOC1 to MOC2 : MELLLA-HBB XIV-5-2c Generator Trip (Load Rejection) without Bypass, MOC2 to EOC : MELLLA-HBB XIV-5-2d Generator Trip (Load Rejection) without Bypass, BOC to MOC1 : ICF-HBB XIV-5-2e Generator Trip (Load Rejection) without Bypass, MOC1 to MOC2 : ICF-HBB XIV-5-2f Generator Trip (Load Rejection) without Bypass, MOC2 to EOC : ICF-HBB XIV-5-2g Generator Trip (Load Rejection) without Bypass, EOC : MELLLA-UB XIV-5-2h Generator Trip (Load Rejection) without Bypass, EOC : ICF-UB XIV-5-3 Turbine Trip with Bypass XIV-5-4a Turbine Trip without Bypass, BOC to MOC1 : MELLLA-HBB XIV-5-4b Turbine Trip without Bypass, MOC1 to MOC2 : MELLLA-HBB XIV-5-4c Turbine Trip without Bypass, MOC2 to EOC : MELLLA-HBB XIV-5-4d Turbine Trip without Bypass, BOC to MOC1 : ICF-HBB XIV-5-4e Turbine Trip without Bypass, MOC1 to MOC2 : ICF-HBB XIV-5-4f Turbine Trip without Bypass, MOC2 to EOC : ICF-HBB XIV-5-4g Turbine Trip without Bypass, EOC : MELLLA-UB XIV-5-4h Turbine Trip without Bypass, EOC : ICF-UB XIV-5-5 Closure of One Main Steam Isolation Valve (MSIV)
XIV-5-6 Closure of All Main Steam Isolation Valves (MSIVs)
XIV-5-8 DEH Pressure Controller Output Fails High XIV-5-9 Inadvertent Opening of a Safety/Relief Valve
VOLUME V - USAR LIST OF FIGURES (CONT=D)
(At end of Section XIV)
Figure No.
Title 02/22/17 XIV-5-10 Loss of Feedwater Flow XIV-5-11 Loss of Auxiliary Power (Trip without Transfer)
XIV-5-12 Loss of Auxiliary Power (Loss of Grid Connection)
XIV-5-13 Recirculation Flow Controller Failure - Decreasing Flow XIV-5-14 Trip of One Recirculation Pump XIV-5-15 Trip of Two Recirculation Pumps XIV-5-15a Single Loop Operation Pump Seizure XIV-5-16 Recirculation Flow Controller Failure - Increasing Flow XIV-5-17 Startup of Idle Recirculation Pump XIV-5-18a Feedwater Controller Failure - Maximum Demand, BOC to MOC1 : MELLLA-HBB XIV-5-18b Feedwater Controller Failure - Maximum Demand, BOC to MOC1 : MELLLA-HBB - 1 TBVOOS XIV-5-18c Feedwater Controller Failure - Maximum Demand, MOC1 to MOC2 : MELLLA-HBB XIV-5-18d Feedwater Controller Failure - Maximum Demand, MOC2 to EOC : MELLLA-HBB XIV-5-18e Feedwater Controller Failure B Maximum Demand, MOC1 to EOC : MELLLA-HBB - 1 TBVOOS XIV-5-18f Feedwater Controller Failure - Maximum Demand, BOC to MOC1 : ICF-HBB XIV-5-18g Feedwater Controller Failure - Maximum Demand, BOC to MOC1 : ICF-HBB -1 TBVOOS XIV-5-18h Feedwater Controller Failure - Maximum Demand, MOC1 to MOC2 : ICF-HBB XIV-5-18i Feedwater Controller Failure - Maximum Demand, MOC2 to EOC : ICF-HBB XIV-5-18j Feedwater Controller Failure - Maximum Demand, MOC1 to EOC : ICF-HBB - 1 TBVOOS XIV-5-18k Feedwater Controller Failure - Maximum Demand, EOC : MELLLA-UB XIV-5-18l Feedwater Controller Failure - Maximum Demand, EOC : MELLLA-UB - 1 TBVOOS XIV-5-18m Feedwater Controller Failure - Maximum Demand, EOC : ICF-UB XIV-5-18n Feedwater Controller Failure - Maximum Demand, EOC : ICF-UB - 1 TBVOOS XIV-5-19 ATWS - MSIV Closure - with ARI XIV-5-20 ATWS - MSIV Closure - no ARI (First 100 Seconds)
XIV-5-21 ATWS - MSIV Closure - No ARI (Long Term Response)
VOLUME V - USAR LIST OF FIGURES (CONT=D)
(At end of Section XIV)
Figure No.
Title 02/22/17 XIV-5-21a ATWS - MSIV Closure, BOC, 76.8% Flow, 3 SRVOOS, MAX SRV Setpoint XIV-5-21b ATWS - MSIV Closure, BOC, 76.8% Flow, 3 SRVOOS, MAX SRV Setpoint XIV-5-22 ATWS - Turbine Trip with Bypass - with ARI XIV-5-23 ATWS - Inadvertent Opening of a Relief Valve - with ARI XIV-5-23a Transient Response of IORV at MELLL and EOC XIV-5-23b Transient Response of IORV at MELLL and EOC XIV-5-24 ATWS - Pressure Regulator Failure Open - with ARI XIV-5-24a ATWS - Pressure Regulator Failure, BOC, 76.8% Flow, 3 SRVOOS, +70 PSI SRV Setpoint XIV-5-24b ATWS - Pressure Regulator Failure, BOC, 76.8% Flow, 3 SRVOOS, +70 PSI SRV Setpoint XIV-5-25 ATWS - Loss of Normal Feedwater - with ARI XIV-5-26 ATWS - Loss of Normal AC Power - with ARI XIV-5-26a Transient Response of LOAP at MELLL and EOC XIV-5-26b Transient Response of LOAP at MELLL and EOC XIV-5-27 Station Blackout XIV-5-28a Inadvertent HPCI/L8 Turbine Trip, BOC to MOC1 : MELLLA-HBB XIV-5-28b Inadvertent HPCI/L8 Turbine Trip, BOC to MOC1 : MELLLA-HBB -
1 TBVOOS XIV-5-28c Inadvertent HPCI/L8 Turbine Trip, MOC1 to MOC2 : MELLLA-HBB XIV-5-28d Inadvertent HPCI/L8 Turbine Trip, MOC2 to EOC : MELLLA-HBB XIV-5-28e Inadvertent HPCI/L8 Turbine Trip, MOC1 to EOC : MELLLA-HBB -
1 TBVOOS XIV-5-28f Inadvertent HPCI/L8 Turbine Trip, BOC to MOC1 : ICF-HBB XIV-5-28g Inadvertent HPCI/L8 Turbine Trip, BOC to MOC1 : ICF-HBB -
1 TBVOOS XIV-5-28h Inadvertent HPCI/L8 Turbine Trip, MOC1 to MOC2 : ICF-HBB
VOLUME V - USAR LIST OF FIGURES (CONT=D)
(At end of Section XIV)
Figure No.
Title 02/22/17 XIV-5-28i Inadvertent HPCI/L8 Turbine Trip, MOC2 to EOC : ICF-HBB XIV-5-28j Inadvertent HPCI/L8 Turbine Trip, MOC1 to EOC : ICF-HBB -
1 TBVOOS XIV-5-28k Inadvertent HPCI/L8 Turbine Trip, EOC : MELLLA-UB XIV-5-28l Inadvertent HPCI/L8 Turbine Trip, EOC : MELLLA-UB - 1 TBVOOS XIV-5-28m Inadvertent HPCI/L8 Turbine Trip, EOC : ICF-UB XIV-5-28n Inadvertent HPCI/L8 Turbine Trip, EOC : ICF-UB - 1 TBVOOS XIV-6-1 Loss of Coolant Accident, Humboldt Primary Containment Pressure Response XIV-6-2 Loss of Coolant Accident, Bodega Bay Primary Containment Pressure Response XIV-6-3 Loss of Coolant Accident, Bodega Bay Primary Containment Pressure Response XIV-6-4 Loss of Coolant Accident, Comparison of Calculated and Measured Peak Drywell Pressure for Bodega Bay and Humboldt Tests XIV-6-5 Loss of Coolant Accident, Primary Containment Pressure and Temperature Response, Case A XIV-6-6 Loss of Coolant Accident, Primary Containment Pressure and Temperature Response, Case B XIV-6-7 Loss of Coolant Accident, Primary Containment Pressure and Temperature Response, Case C XIV-6-8 Loss of Coolant Accident, Primary Containment Pressure and Temperature Response, Case D XIV-6-9 Loss of Coolant Accident, Primary Containment Pressure and Temperature Response, Case E XIV-6-9a Loss of Coolant Accident, Primary Containment Pressure and Temperature Response, Case F XIV-6-10 Primary Containment Leak Rate XIV-6-11 Primary Containment Capability Index for Metal Water Reaction XIV-6-12 Main Steam Line Break Accident, Break Location XIV-6-13a Main Steam Line Break Accident, Mass of Coolant Through Break (10 Second MSIV Closure)
XIV-6-13b Steamline (Outside Containment) - DC Power Source Failure (Nominal) Break and SRV Flow Rates (5 Second MSIV Closure)
XIV-6-16 Containment Pressure
VOLUME V - USAR LIST OF FIGURES (CONT=D)
(At end of Section XIV)
Figure No.
Title 02/11/13 XIV-6-16a Containment Pressure Response XIV-6-18 DBA Containment Pressure Response - Mark I Containment Program XIV-6-19 DBA Containment Temperature Response - Mark I Containment Program XIV-6-20 Original Short-Term Primary Containment Pressure and Temperature Response Following a Loss of Coolant Accident
VOLUME VI - USAR 02/11/13 LIST OF FIGURES (At End of Appendix C)
Figure No.
Title C-2-1 Reactor Bldg. Dynamic Analysis Model C-2-2 Control Bldg. Dynamic Model C-2-12 Reactor Bldg. Total Acceleration
VOLUME VI - USAR 02/11/13 LIST OF FIGURES
[At End of Appendix D(1)]
Figure No.
Title D(1)-2-1 NPPD - QA Organization -- Cooper Nuclear Station D(1)-3-1 Stearns-Roger Quality Assurance Organization -- Cooper Nuclear Station D(1)-3-2 Document Review Log D(1)-3-3 Weld Procedure Evaluation - (two pages)
D(1)-3-4 Purchase Order and Mill Test Report Status D(1)-3-5 Shop Inspection Check List - Example: Shop Inspection of Reactor Feed Pump Turbines - (five pages)
D(1)-3-6 Inspection and Expediting Narrative Report D(1)-3-7 Inspection Punch List Report D(1)-3-8 Deviation Report D(1)-3-9 Deviation Report Log D(1)-3-10 Concrete Placement Checkout Sheet D(1)-3-11 Pipe Backfill Ticket D(1)-3-12 Electrical Installation Check-Off List D(1)-3-13 Concrete Batch Plant Inspection Report D(1)-3-14 Lab. Work Sheet and File D(1)-3-15 Lab Data D(1)-3-16 Concrete Field Inspection Report D(1)-3-17 Lab Field Data D(1)-3-18 Compression Test of Concrete D(1)-3-19 Documentation Requirements D(1)-3-20 Documentation Requirements (Electrical)
D(1)-4-1 Organization Flow Chart
VOLUME VI - USAR 02/11/13 LIST OF FIGURES (CONT'D)
[At End of Appendix D(1)]
Figure No.
Title D(1)-4-2 Engineering and Design Flow Chart D(1)-4-3 Specifications and Calculations Flow Chart D(1)-4-4 Drawings Flow Chart D(1)-4-5 Vendor and As-Built Drawings Flow Chart D(1)-5-1 Organization Chart, Cooper Nuclear Station, Woodward-Moorhouse & Associates, Inc. -- Quality Assurance Program D(1)-5-2 Flow Diagram of Laboratory Phase of Quality Control Testing of Structural and General Fills D(1)-5-3 Locations of Piezometers, Heave Points, Deep Wells, Verification Borings, and In-Situ Compaction and Structural Fill Construction Areas D(1)-5-4 Results of Observations of Excavation and Groundwater Levels in Reactor Building Area D(1)-5-5 Results of Standard Penetration Tests and Calculated Relative Densities of In-Situ Compacted Material D(1)-5-6 Representative Grain-Size Distribution Curves for Sand From Main Excavation and Dredged Sand D(1)-5-7 Liquefaction Potential for the Existing Structural Fill and Sand Stratum Beneath the Radwaste Bldg. Mat D(1)-5-8 Structural Fill Density Correlations D(1)-5-9 Histograms of Relative Density Values Obtained in Structural Fill D(1)-5-10 Results of Standard Penetration Tests in Structural Fill D(1)-5-11 Cooper Nuclear Station Interpreted Groundwater Contour Elevations, 31 March, 1970
VOLUME VI - USAR 02/11/13 LIST OF FIGURES (CONT'D)
[At End of Appendix D(1)]
Figure No.
Title D(1)-5-12 Histograms of Relative Density and Degree of Compaction Values Obtained in General Fill D(1)-5-13 Results of Standard Penetration Tests in Verification Borings D(1)-6-1 Quality System Organizational Structure Applicable Projects:
Browns Ferry, I, II, III Cooper Limerick I & II Peach Bottom II and III Pilgrim Vermont Yankee D(1)-7-1 Construction Test D(1)-7-2 Pre-Op and Start-Up Test D(1)-7-3 Pre-Operational Test Procedure Cover Sheet
VOLUME VII - USAR 02/11/13 LIST OF FIGURES (At end of Appendix G)
Figure No.
Title G-2-2 Block Diagram for Nuclear Safety Operational Analysis G-4-1 Format for Protection Sequence Diagrams - Planned Operation G-4-2 Format for Protection Sequence Diagrams - Events G-4-3 Format for Auxiliary System Diagrams G-4-4 Format for Commonality Diagrams G-5-1 Auxiliary Systems for Front-Line Systems G-5-2 Auxiliary Systems for Front-Line Systems G-5-3 Auxiliary Systems for Front-Line Systems G-5-4 Auxiliary Systems for Other Auxiliary Systems G-5-5 Commonality Diagrams G-5-6 Commonality Diagrams G-5-7 Commonality Diagrams G-5-8 Commonality Diagrams G-5-9 Commonality Diagrams G-5-10 Commonality Diagrams G-5-11 Protection Sequences for Planned Operation in State A G-5-12 Protection Sequences for Planned Operation in State B G-5-13 Protection Sequences for Planned Operation in State C G-5-14 Protection Sequences for Planned Operation in State D G-5-15 Protection Sequences for Planned Operation in States A, B, C & D G-5-16 Protection Sequences for Turbine Trip or Generator Load Rejection with Bypass G-5-17 Protection Sequences for Turbine Trip or Generator Load Rejection without Bypass G-5-18 Protection Sequences for Isolation of All Main Steam Lines G-5-19 Protection Sequences for Isolation of One Main Steam Line G-5-20 Protection Sequences for Loss of Condenser Vacuum
VOLUME VII - USAR 02/11/13 LIST OF FIGURES (CONT=D)
(At end of Appendix G)
Figure No.
Title G-5-21 Protection Sequences for Loss of Feedwater Heating G-5-22 Protection Sequences for Shutdown Cooling (RHRS)
Malfunction - Temperature Decrease G-5-23 Protection Sequences for Inadvertent HPCI Pump Start G-5-24 Protection Sequences for Control Rod Withdrawal Error G-5-25 Protection Sequences for Pressure Regulator Failure - Open G-5-26 Protection Sequences for Inadvertent Opening of a Safety or Relief Valve G-5-27 Protection Sequences for Loss of Feedwater Flow G-5-28 Protection Sequences for Loss of Off-Site Power G-5-29 Protection Sequences for Recirculation Flow Controller Failure - Decreasing Flow G-5-30 Protection Sequences for Trip of One Recirculation Pump G-5-31 Protection Sequences for Trip of Two Recirculation Pumps G-5-32 Protection Sequences for Recirculation Flow Controller Failure - Increasing Flow G-5-33 Protection Sequences for Start-Up of Idle Recirculation Pump G-5-34 Protection Sequences for Loss of Shutdown Cooling G-5-35 Protection Sequences for Feedwater Controller Failure -
Maximum Demand G-5-36 Protection Sequences for Control Rod Drop Accident G-5-37 Protection Sequences for Pipe Breaks Inside Primary Containment - Sheet 1 G-5-38 Protection Sequences for Pipe Breaks Inside Primary Containment - Sheet 2 G-5-39 Protection Sequences for Fuel Handling Accident G-5-40 Protection Sequences for Pipe Breaks Outside Primary Containment - Sheet 1 G-5-41 Protection Sequences for Pipe Breaks Outside Primary Containment - Sheet 2 G-5-42 Protection Sequences for Recirculation Pump Seizure G-5-43 Protection Sequences for Fuel Loading Error
VOLUME VII - USAR 02/11/13 LIST OF FIGURES (CONT=D)
(At end of Appendix G)
Figure No.
Title G-5-44 Protection Sequences for Shutdown From Outside the Control Room G-5-45 Protection Sequences for Shutdown Without Control Rods G-5-46 Protection Sequences for Anticipated Transients Without SCRAM G-5-47 Protection Sequences for Station Blackout
VOLUME VII - USAR 02/11/13 LIST OF FIGURES (At end of Appendix K)
Figure No.
Title None