LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 4, Reactor, and Table of Contents

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Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 4, Reactor, and Table of Contents
ML17046A309
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Issue date: 01/30/2017
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LR-N17-0034
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SECTION 4

  • REACTOR TABLE OF CONTENTS Section Title Page 4.1

SUMMARY

DESCRIPTION 4.1-1 4.1.1 Reference for Section 4.1 4.1-4 4.2 MECHANICAL DESIGN 4.2.1 Fuel 4.2-2 4.2.1.1 Design Bases 4.2-2 4.2.1.1.1 Fuel Rods 4.2-3 4.2.1.1.2 Fuel Assembly Structure 4.2-5 4.2.1.2 Design Description 4.2-8

  • 4.2.1.2.1 Fuel Rods 4.2-10 4.2.1.2.2 Fuel Assembly Structure 4.2-11 4.2.1.3 Design Evaluation 4.2-14 4.2.1.3.1 Fuel Rods 4.2-14 4.2.1.3.2 Fuel Assembly Structure 4.2-24 4.2.1.3.3 Operational Experience 4.2-28 4.2.1.3.4 Test Rod and Test Assembly Experience 4.2-28a 4.2.1.4 Testing and Inspection Plan 4.2-28a 4.2.1.4.1 Quality Assurance Program 4.2-28a 4.2.1.4.2 Quality Control 4.2-29 4.2.1.4.3 Onsite Inspection 4.2-32 4.2.2 Reactor Vessel Internals 4.2-33 4.2.2.1 Design Bases 4.2-33 4.2.2.2 Description and Drawings 4.2-34 4.2.2.3 Design Loading Conditions 4.2-40a 4.2.2.4 Design Loading Categories 4.2-42 4.2.2.5 Design Criteria Basis 4.2-43 4.2.3 Reactivity Control System 4.2-44
  • 4-i SGS-UFSAR Revision 11 July 22, 1991 Section 4.2.3.1 4.2.3.1.1 4.2.3.1.2 4.2.3.1.3 4.2.3.1.4 4.2.3.2 4.2.3.2.1 4.2.3.2.2 4.2.3.3 4.2.3.3.1 4.2.3.3.2 4.2.3.4 4.2.3.4.1 4.2.3.4.2 4.2.4 4.3 4.3.1 4.3.1.1 4.3.1.2 4.3.1.3 4.3.1.4 4.3.1.5 4.3.1.6 4.3.1. 7 4.3.2 4.3.2.1 4.3.2.2 4.3.2.2.1 4.3.2.2.2 SGS-UFS.AR TABLE OF CONTENTS (Cont) Design Bases Design Stresses Material Compatibility Reactivity Control Components Control Rod Drive Mechanisms Design Description Reactivity Control Components Control Rod Drive Mechanism Design Evaluation Reactivity Control Components Control Rod Drive Mechanism Tests, Verification, and Inspections Reactivity Control Components Control Rod Drive Mechanism References for Section 4.2 NUCLEAR DESIGN Design Bases Fuel Burnup Negative Reactivity Feedbacks (Reactivity Coefficient) Control of Power Distribution Maximum Controlled Reactivity Insertion Rate Shutdown Margins Stability Anticipated Transients Without Trip Description Nuclear Design Description Power Distribution Definitions Radial Power Distribution 4*11 4.2-44 4.2-44 4.2-45 4.2-45 4.2-48 4.2-49 4.2-51 4.2-56 4.2-63 4.2-63 4.2-73 4.2-77 4.2-77 4.2-79 4.2-81 4.3-1 4.3-1 4.3-2 4.3-3 4.3-4 4.3-6 4.3-7 4.3-8 4.3-9 4.3-10 4.3-10 4.3-13 4.3-13 4.3-16 Revision 6 February 15, 1987 * * *
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  • Section 4.3.2.2.3 4.3.2.2.4 4.3.2.2.5 4.3.2.2.6 4.3.2.2.7 4.3.2.2.8 4.3.2.2.9 4.3.2.3 4.3.2.3.1 4.3.2.3.2 4.3.2.3.3 4.3.2.3.4 4.3.2.3.5 4.3.2.4 4.3.2.4.1 4.3.2.4.2 4.3.2.4.3 4.3.2.4.4 4.3.2.4.5 4.3.2.4.6 4.3.2.4.7 4.3.2.4.8 4.3.2.4.9 4.3.2.5 4.3.2.5.1 4.3.2.5.2 4.3.2.5.3 4.3.2.5.4 4.3.2.5.5 SGS-UFSAR TABLE OF CONTENTS (Cont) Assembly Power Distribution Axial Power Distribution Deleted Limiting Power Distribution Experimental Verification of Power Distribution Analysis Testing Monitoring Instrumentation Reactivity coefficients Fuel Temperature (Doppler) Coefficient Moderator coefficients Power Coefficient comparison of Calculated and Experimental Reactivity Coefficients Reactivity Coefficients Used in Transient Analysis Control Requirements Doppler variable Average Moderator Temperature Redistribution Void content Rod Insertion Allowance Burn up Xenon and Samarium Poisoning pH Effects Experimental Confirmation control Chemical Poison Rod Cluster Control Assemblies Burnable Absorbers Peak xenon Startup Load Follow Control and Xenon control 4-iii 4.3-17 4.3-17 4.3-18 4.3-20 4.3-26 4.3-29 4.3-29 4.3-30 4.3-30 4.3-31 4.3-34 4.3-34 4.3-35 4.3-35 4.3-36 4.3-36 4.3-37 4.3-37 4.3-37 4.3-38 4.3-38 4.3-38 4.3-39 4.3-39 4.3-39 4.3-40 4.3-41 4.3-41 4.3-42 Revision 17 october 16, 1998 Section 4.3.2.5.6 4.3.2.6 4.3.2.7 4.3.2.8 4.3.2.8.1 4.3.2.8.2 4.3.2.8.3 4.3.2.8.4 4.3.2.8.5 4.3.2.8.6 4.3.2.9 4.3.3 4.3.3.1 4.3.3.2 4.3.3.3 4.3.4 4.4 4.4.1 4.4.1.1 4.4.1.2 4.4.1.3 4.4.1.4 4.4.1.5 4.4.2 4.4.2.1 4.4.2.2 4.4.2.2.1 SGS-UFSAR TABLE OF CONTENTS (Cont) Burnup 4.3-42 Control Rod Patterns and Reactivity Worth 4.3-42 Criticality of Fuel Assemblies 4.3-45 Stability 4.3-46 Introduction Stability Index Prediction of the core Stability Stability Measurements Comparison of Calculations with Measurements stability control and Protection Vessel Irradiation Analytical Methods Fuel Temperature (Doppler) Calculations Macroscopic Group Constants Spatial Few-Group Diffusion Calculation$ References for Section 4.3 THERMAL AND HYDRAULIC DESIGN Design Bases Departure From Nucleate Boiling Design Basis Fuel Temperature Design Basis core Flow Design Basis Hydrodynamic Stability Design Bases Other Considerations Description summary Comparison Fuel Cladding Temperatures (Including Densification) Uranium Dioxide Thermal Conductivity 4-iv 4.3-46 4.3-46 4.3-47 4.3-48 4.3-50 4.3-51 4.3-52 4.3-53 4.3-54 4.3-55 4.3-57 4.3-58 4.4-1 4.4-1 4.4-2 4.4-2a 4.4-3 4.4-4 4.4-4 4.4-5 4.4-5 4.4-7 4.4-9 Revision 11 July 22, 1991 * * *
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  • Section 4.4.2.2.2 4.4.2.2.3 4.4.2.2.4 4.4.2.2.5 .4. 4. 2. 3 4.4.2.3.1 4.4.2.3.2 4.4.2.3.3 4.4.2.3.4 4.4.2.3.5 4.4.2.3.6 4.4.2.4 4.4.2.5 4. 4. 2. 6 4. 4. 2. 7 4.4.2.7.1 4.4.2.7.2 4. 4. 2. 8 4.4.2.8.1 4.4.2.8.2 4.4.2.8.3 4. 4. 2. 9 4.4.2.10 4.4.2.10.1 4.4.2.10.2 4.4.2.10.3 4.4.2.10.4 SGS-UFSAR TABLE OF CONTENTS (Cent) Title Radial Power Distribution in UO Fuel Rods Gap Conductance Surface Heat Transfer Coefficients Fuel Clad Temperatures Critical Heat Flux Ratio or Departure from Nucleate Boiling Ratio and Mixing Technology Departure from Nucleate Boiling Technology Definition of Departure from Nucleate Boiling Ratio Mixing Technology Engineering Hot-Channel Factors Effects of Rod Bow on DNBR Transition Core DNB Methodology Flux Tilt Considerations Void Fraction Distribution Core Coolant Flow Distribution Core Pressure Drops and Hydraulic Loads Core Pressure Drops Hydraulic Loads Correlation and Physical Data Surface Heat Transfer Coefficients Total Core apd Vessel Pressure Drop Void Fraction Correlation Thermal Effects of Operational Transients Uncertainties in Estimates Uncertainties in Fuel and Clad Temperatures Uncertainties in Pressure Drops Uncertainties Due to Inlet Flow Maldistribution Uncertainty in DNB Correlation 4-v 4.4-10 4.4-10 4.4-12 4.4-12 4.4-13 4.4-14 4.4-lSa 4. 4-17a 4.4-19 4.4-21a 4.4-21a 4.4-22 4.4-22 4.4-23 4.4-23 4.4-23 4.4-24 4.4-25 4.4-25 .4. 4-26 4.4-27 4. 4-28 4.4-29 4.4-29 4.4-30 4.4-30 4.4-30 Revision 18 April 26, 2000 Section 4.4.2.10.5 4.4.2.10.6 4.4.2.10.7 4.4.2.10.6 4.4.2.11 . 4. 4.3 4.4.3.1 4.4.3.1.1 4.4.3.1.2 4.4.3.1.3 4.4.3.2 4.4.3.2.1 4.4.3.2.2 4.4.3.3 4.4.3.4 4.4.3.4.1 4.4.3.4.2 4.4.3.4.3 4.4.3.5 4.4.3.6 4.4.3.7 4.4.3.8 4.4.3.9 4.4.3.10 4.4.4 4.4.4.1 SGS-UFSAA TABLE OF CONTENTS (Cant) Title Uncertainties in DNBR Calculations Uncertainties in Flow Rates Uncertainties in Hydraulic Loads Uncertainty in Mixing Coefficients Plant Configuration Data Evaluation Core Hydraulics Flow Paths Considered in Core Pressure Drop and Thermal Design Inlet Flow Distributions Emprical Friction Factor Correlations Influence of Power Distribution Nuclear Enthalpy Rise Hot Channel Factor Axial Heat Flux Distributions Core Ther.mal Response Analytical Techniques Core Analysis Fuel Temperatures Hydrodynamdc Instability Hydrodynamic and Flow Power Coupled Instability Temperature Transient Effects Analysis Potentially Damaging Temperature Effects During Transients Energy Release During Fuel Element Burnout Energy Release or Rupture of Water-logged Fuel Elements Fuel Rod Behavior Effects from Coolant Flow Blockage Testing and Verification Tests Prior to Initial Criticality 4-vi 4.4-30 4.4-31 4.4-31 4.4-32 4.4-32 4.4-33 4.4-33 4.4-33 4.4-34 4.4-35 4.4-36 4.4-37 4.4-38 4.4-38 4.4-39 4.4-39 4.4-47 4.4-47 4.4-47 4.4-50 4.4-51 4.4-52 4.4-53 4.4-53 4.4-55 4.4-55 Revision 6 February 15, 1987 * * *
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  • Section 4.4.4.2 4.4.4.3 4.4.4.4 4.4.5 4.5 4.5.1 SGS-UFSAR TABLE OF CONTENTS (Cont) Title Initial Power and Plant Operation Component and Fuel Inspections Auq.mented Startup Test Program References for Section 4.4 RELOAD ANALYSIS References for Section 4.5 4-vii 4.4-55 4.4-56 4.4-56 4.4-56 4.5-1 4.5-2 Revision 17 October 16, 1998 4.1-1 4.1-2 4.1-3 4.2-l 4.2-2 4.3-1 4.3-2 4.3-3 4. 3-4 4.3-5 4.3-7 SGS-UFSAR LIST OF TABLE:S Thermal and Hydraulic Design Analytic Techniques Incore Design Design Loading Conditions for Reactor Core Components Maximum Deflections Allowed for Reactor Internal Support Structures Comparison of Single and Double Encapsulated Secondary Source Designs Reactor Core Description Nuclear Design Parameters Reactivity Requirements for Rod Cluster Control Assemblies Axial Stability Index-PWR Core With a 12-Foot Height Typical Neutron Flux Levels at Full Power Comparison of Measured and Calculated Doppler Defects Benchmark Critical Experiments 4-viii Revision 18 April 26, 2000 * * *
  • 4.3-8 4.3-9 4.3-10 4. 3-11 4.4-1 4.4-2 4.4-3
  • 4.4-4 4.5-1 4.5-2
  • SGS-UFSAR LIST OF TABLES (Cont) Saxton Core II Isotopics, Rod MY, Axial Zone 6 Critical Boron Concentrations, BOL Comparison of Measured and Calculated Rod Worth Comparison of Measured and Calculated Moderator Coefficients at HZP, BOL Reactor Thermal and Hydraulic Design Parameters (This text has been deleted) Void Fractions at Nominal Reactor Conditions With Design Hot Channel Factors Comparison of THINC-IV and THINC-I Predictions With Data From Representative Westinghouse Two and Three Loop Reactors (This text has been deleted) (This text has been deleted) 4-ix Revision 23 October 171 2007 I I Figure 4.2-1 4.2-2 4.2-2A 4.2-28 4.2-2C 4.2-3 4.2-3A 4.2-38 4.2-3C 4.2-4 4.2-5 4.2-6 4.2-7 4.2-8 4.2-9 4.2-10 4. 2-11 4.2-12 4.2-13 SGS-OFSAR LIST OF FIGURES Fuel Assembly Cross Section -17 x 17 Standard Fuel Assembly Outline -17 x 17 17 x 17 Vantage+/Vantage SH Fuel Assembly Comparison 17 x 17 Standard Robust Fuel Assembly Outline 17 x 17 RFA ZIRLOl'M+2 Outline Standard Fuel Rod Schematic 17 x 17 Vantage+/Vantage 5H Fuel Rod Comparison 17 x 17 Standard RFA Fuel Rod Schematic 17 x 17 RFA ZIRL0Ž+2 Fuel Rod Schematic Typical Clad and Pellet Dimensions as a Function of Exposure Plan View Representative Fuel Rod Internal Pressure and Linear Power Density for the Lead Burnup Rod as a Function of Time Top Grid to Nozzle Attachment Lower Core Support Assembly Elevation View, Grid to Thimble Attachment Upper Core Support Structure Guide Thimble to Bottom Nozzle Joint Plan View of Upper Core Support Structure Full Length Rod Cluster Control and Drive Rod Assembly With Interfacing Components 4-x Revision 19 November 19, 2001 * * *
  • 4.2-14 4.2-15 4.2-16 4.2-17 4.2-17A 4.2-18 4.2-19 4.2-20 4.2-21
  • 4.2-22 4.2-23 4.2-24 4.2-25 4.3-1 4.3-2 4.3-3 4.3-4
  • SGS-UFSAR LIST OF FIGURES (Cant) Title Full Length Rod Cluster Control Assembly Outline Full Length Absorber Rod Burnable Absorber Assembly Pyrex Burnable Poison Rod Cross Section WABA Rod Cross Section Primary Source Assembly Single Encapsulated Secondary Source Thimble Plug Assembly (Optional Usage} Full Length Control Rod Drive Mechanism Full Length Control Rod Drive Mechanism Schematic Nominal Latch Clearance at Minimum and Maximum Temperature Control Rod Drive Mechanism Latch Clearance Thermal Effect Schematic Representation of Reactor Core Model Production and Consumption of Higher Isotopes Boron Concentration vs Cycle Burnup (Typical) Normalized Power Density Distribution At BOL, Unrodded Core, HFP, No Xenon (Typical) Normalized Power Density, Distribution Near BOL, Unrodded Core, HFP, Equilibrium Xenon (Typical) 4-xi Revision 18 April 26, 2000 Figure 4.3-5 4.3-6 4.3-7 4.3-8 4.3-9 4.3-10 4. 3-11 4.3-12 4.3-13 4. 3-14 4.3-15 4.3-16 4.3-17 4.3-18 4.3-19 4.3-20 SGS-UFSAR LIST OF FIGURES (Cont) Normalized Power Density Distribution Near BOL, Group D Inserted, HFP, Equilibrium Xenon (Typical) Normalized Power Density Distribution Near Middle of Life, Unrodded Core, HFP, Equilibrium Xenon (Typical) Normalized Power Density Distribution Near EOL, Unrodded Core, HFP, Equilibrium Xenon (Typical) Typical Axial Power Shapes Occurring at Beginning of Life Typical Axial Power Shapes Occurring at Middle of Life Typical Axial Power Shapes Occurring at End of Life Maximum F0-Power vs Axial Height During Normal Operation Peak Power Density During Control Rod Malfunction Overpower Transients Peak Linear Power During Boration/Dilution Overpower Transients Comparison Between Calculated and Measured Relative Fuel Assembly Power Distribution Comparison of Calculated and Measured Axial Shape Measured Values of FQ for Full Power Rod Configuration Doppler Temperature Coefficient at BOL and EOL, (Typical) Doppler Power Coefficient-SOL, MOL, EOL, (Typical) Doppler Power Defect-BOL, MOL, EOL, (Typical) Moderator Temperature Coefficient-SOL, ARO (Typical) 4-xii Revision 17 October 16, 1998 * * *
  • Figure 4.3-21 4.3-22 4.3-23 4.3-24 4.3-25 4.3-26A 4.3-26B 4.3-27
  • 4.3-28 4.3-29 4.3-30 4.3-31 4.3-32 4.3-33 4.3-34
  • SGS-UFSAR LIST OF FIGURES (Cont) Title Moderator Temperature Coefficient-EOL, ARO (Typical) Moderator Temperature Coefficient as Concentration, BOL, ARO (Typical) a Function of Boron Hot Full Power Moderator Temperature Coefficient vs Cycle Burnup (Typical) Total Power Coefficient-SOL, EOL (Typical) Total Power Defect-SOL, EOL (Typical) Rod Cluster Control Assembly Pattern -Unit 1 Rod Cluster Control Assembly Pattern -Unit 2 Accidental Simultaneous Withdrawal of 2 Control Banks EOL, HZP, Banks D&B Moving in the Same Plane Design Trip Curve Normalized Rod Worth vs Percent Insertion All Rods But One Axial Offset vs Time-PWR Core With a 12-Foot Height and 121 Assemblies XY Xenon Test Thermocouple Response Quadrant Tilt Difference vs Time Calculated and Measured Doppler Defect and Coefficients at BOL, Two-Loop Plant, 121 Assemblies, 12-Foot Core Comparison of Calculated and Measured Boron Concentration for 2-Loop Plant, 121 Assemblies, 12-foot Core Comparison of Calculated and Measured CB 2-Loop with 121 Assemblies, 12-Foot Core 4-xiii Revision 17 October 16, 1998 Figure 4.3-35 4.4-1 4.4-lA 4.4-2 4 ., 4-2A 4.4-3 4. 4-4 4.4-SA 4.4-58 4.4-SC 4.4-6 4.4-7 4.4-8 SGS-UFSAR LIST OF FIGURES (Cant) Title Comparison of Calculated and Measured ce 3-Loop Plant, Assemblies, 12-Foot core 157 Peak Fuel Average and Surface Temperatures During Fuel Rod Lifetime vs Linear Power Peak Fuel Average and Surface Temperatures During Fuel Rod Lifetime vs Linear Power for Vantage-5H fuel Peak Fuel Centerline Temperature During Fuel Rod Lifetime vs Linear Power Peak Fuel Centerline Temperatures During Fuel Rod Lifetime vs Linear Power for Vantage-SH fuel Thermal Conductivity of uo2 (Data Corrected to 95% Theoretical Density) Axial Variation of Average Clad Temperature for Rod Operating at '5.43 kW/ft Comparison of Measured to Predicted 17 x 17 DNB Data Measured vs Predicted Critical Heat Flux WRB-1 Correlation Measured Critical Heat Flux -WRB-2 Correlation TDC vs Reynold's Number for 26-Inch Grid Spacing Normalized Radial Flow and Enthalpy Distribution at 4-Foot Elevation Normalized Radial Flow and Enthalpy Distribution at 8-Foot Elevation 4-xiv Revision 18 April 26, 2000 * *
  • Figure 4.4-9 4.4-10 4.4-11 4.4-12 4.4-13 4.4-14 4.4-15 4.4-16 4.4-17 4.5-1 4.5-2 4.5-3 4.5-4 SGS-UFSAR LIST OF FIGURES {Cont) Normalized Radial Flow and Enthalpy Distribution at 12-Foot Elevation (Unit 2) Void Fraction vs Thermodynamic Quality H-HSAT/Hg-HSAT PWR Natural Circulation Test Comparison of a Representative Westinghouse Two-Loop Reactor Incore Thermocouple Measurements With THINC-IV Predictions Comparison of a Representative Westinghouse Three-Loop Reactor Incore Thermocouple Measurements With THINC-IV Predictions Hanford Subchannel Temperature Data Comparison With THINC-IV Hanford Subcritical Temperature Data Comparison With THINC-IV Distribution of Incore Instrumentation -Unit 1 Distribution of Incore Instrumentation -Unit 2 Typical Salem Unit 1 Loading Pattern Typical Salem Unit 1 Burnable Absorber Configuration Typical Salem Unit 2 Loading Pattern Typical Salem Unit 2 Burnable Absorber Configuration 4-xv Revision 23 October 17, 2007
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