ML16207A542
| ML16207A542 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 04/28/2016 |
| From: | South Texas |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16207A547 | List:
|
| References | |
| NOC-AE-16003371 | |
| Download: ML16207A542 (9) | |
Text
STPEGS UFSAR TC 4-1 Revision 1 8 TABLE OF CONTENTS CHAPTER 4 REACTOR Section Title Page 4.1
SUMMARY
DESCRIPTION 4.1-1 4.2 FUEL SYSTEM DESIGN 4.2-1 4.2.1 Design Bases 4.2-1 4.2.2 Design Description 4.2-8 4.2.3 Design Evaluation 4.2-19 4.2.4 Testing and Inspection Plan 4.2-3 4 4.3 NUCLEAR DESIGN 4.3-1 4.3.l Design Bases 4.3-1 4.3.2 Description 4.3-6 4.3.3 Analytical Methods 4.3-36 4.4 THERMAL AND HYDRAULIC DESIGN 4.4-1 4.4.l Design Bases 4.4-1 4.4.2 Description 4.4-5 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System 4.4-21 4.4.4 Evaluation 4.4-23 4.4.5 Testing and Verification 4.4-35 4.4.6 Instrumentation Requirements 4.4-35 4.5 REACTOR MATERIALS 4.5-1 4.5.1 Control Rod System Structural Materials 4.5-1 4.5.2 Reactor Internals Materials 4.5-2 4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS 4.6-1 4.6.1 Information for Control Rod Drive System 4.6-1 4.6.2 Evaluation of the Control Rod Drive System 4.6-1 4.6.3 Testing and Verification of the Control Rod Drive System 4.6-1 4.6.4 Information for Combined Performance of Reactivity Systems 4.6-1 4.6.5 Evaluation of Combined Performance 4.6-2 STPEGS UFSAR LIST OF TABLES
CHAPTER 4 Table Title Page TC 4-2 Revision 1 8 4.1-1 Reactor Design Table 4.1-5 4.1-2 Analytical Techniques in Core Design 4.1-9 4.1-3 Design Loading Conditions for Reactor Core Components 4.1-11 4.2-1 Fuel Assembly Component Stresses 4.2-4 1 4.3-1 Reactor Core Description 4.3-45 4.3-2 Nuclear Design Parameters (First Cycle) 4.3-48 4.3-3 Reactivity Requirements for Rod Cluster Control Assemblies 4.3-51 4.3-4 Comparison of Reactivity Requirements 4.3-52 4.3-5 Expected Reactivity Parameter Range 4.3-53 4.3-6 Benchmark Critical Experiments 4.3-54 4.3-7 Axial Stability Index Pressurized Water Reactor Core with a 12
-Foot Height 4.3-55 4.3-8 Typical Neutron Flux Levels (n/cm 2-sec) at Full Power 4.3-56 4.3-9 Comparison of Measured and Calculated Doppler Defects 4.3-57 4.3-10 Saxton Core II Isotopics Rod MY, Axial Zone 6 4.3-58 4.3-11 Critical Boron Concentrations, HZP, BOL 4.3-59 4.3-12 Comparison of Measured and Calculated Rod Worth 4.3-60 4.3-13 Comparison of Measured and Calculated Moderator Coefficients at HZP, BOL 4.3-61 4.4-1 Thermal and Hydraulic Comparison Table (Historical) 4.4-47 4.4-4 Comparison of THINC
-IV and THINC
-I Predictions with Data from Representative Westinghouse Two and Three Loop Reactors 4.4-50 STPEGS UFSAR LIST OF FIGURES (Continued)
CHAPTER 4 Figure Number Title TC 4-3 Revision 1 8 4.2-l Fuel Assembly Cross Section l7x17 4.2-2 Fuel Assembly Outline l7xl7 XL (Conceptual) 4.2-2a Upgraded Fuel Assembly Outline 17x17 XL (Conceptual) 4.2-2B Fuel Assembly Outline 17x17 XL
- Vantage 5H (Typical - All Dimensions Ref.)
4.2.-2C Vantage + / RFA Fuel Assembly 4.2-3 Fuel Rod Schematic 4.2-4 Fuel Assembly Plan View 4.2-5 Fuel Assembly Elevation View 4.2-5A Fuel Assembly Plan View of Mid Grid to Guide Thimble Joint
-Vantage 5H/Vantage +/ RFA 4.2-5B Fuel Assembly Elevation View of Mid Grid to Guide Thimble Joint
-Vantage 5H/Vantage +/RFA 4.2-6 Standard Top Nozzle and Grid Attachment 4.2-6a Upgraded Top Nozzle and Guide Thimble Interface 4.2-7 Guide Thimble to Bottom Nozzle Joint 4.2-7A Vantage + Guide Thimble to Bottom Nozzle Joint 4.2-7B RFA Guide Thimble to Bottom Nozzle Joint 4.2-8 Rod Cluster Control and Drive Rod Assembly with Interfacing Componen ts 4.2-9 Rod Cluster Control Assembly Outline 4.2-l0 Hafnium or Silver
-Indium-Cadmium Absorber Rod 4.2-11 Burnable Absorber Assembly 4.2-11a Updated Burnable Absorber Assembly 4.2-l2 Burnable Absorber Rod
- Cross Section
STPEGS UFSAR LIST OF FIGURES (Continued)
CHAPTER 4 Figure Number Title TC 4-4 Revision 1 8 4.2-12a Updated Burnable Absorber Rod
- Cross Section 4.2-l3 Primary Source Assembly 4.2-l4 Secondary Source Assembly 4.2-l5 Thimble Plug Assembly 4.3-l Fuel Loading Arrangement 4.3-2 Production and Consumption of Higher Isotopes 4.3-3 Boron Concentration Versus First Cycle Burnup with and without Burnable Poison Rods Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-4 Burnable Poison Rod Arrangement Within an Assembly Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-4A Typical IFBA Rod Arrangements Within an Assembly 4.3-5 Burnable Poison Loading Pattern Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-6 Normalized Power Density Distribution Near Beginning of Life, Unrodded Core, Hot Full Power, No Xenon Unit 1 (Sheet 1 of 2) Unit 2 (Sheet 2 of 2) 4.3-7 Normalized Power Density Distribution Near Beginning of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-8 Normalized Power Density Distribution Near Beginning of Life, Group D 40% Inserted, Hot Full Power, Equilibrium Xenon Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2)
STPEGS UFSAR LIST OF FIGURES (Continued)
CHAPTER 4 Figure Number Title TC 4-5 Revision 1 8 4.3-9 Normalized Power Density Distribution Near Middle of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon Unit 1 (Sheet 1 of 2) Unit 2 (Sheet 2 of 2) 4.3-10 Normalized Power Density Distribution Near End of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-11 Normalized Power Density Distribution Near End of Life, Hot Full Power, Equilibrium Xenon, Group D 40% Inserted Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-12 Rodwise Power Distribution in a Typical Assembly Near Beginning of Life, Hot Full Power, Equilibrium Xenon, Unrodded Core 4.3-13 Rodwise Power Distribution in a Typical Assembly Near End of Life, Hot Full Power, Equilibrium Xenon, Unrodded Core 4.3-14 Typical Axial Power Shapes Occurring at Start of Life 4.3-15 Typical Axial Power Shapes Occurring at Middle of Life 4.3-16 Typical Axial Power Shapes Occurring at End of Life 4.3-17 Comparison of Assembly Axial Power Distribution with Core Average Axial Distribution D Bank Slightly Inserted 4.3-18 Not Used 4.3-19 Not Used 4.3-20 Not Used 4.3-21 Maximum F Qx Relative Power Versus Axial Height During Normal Operation STPEGS UFSAR LIST OF FIGURES (Continued)
CHAPTER 4 Figure Number Title TC 4-6 Revision 1 8 4.3-22 Peak Linear Power During Control Rod Malfunction Overpower Transients Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-23 Peak Linear Power During Boration/Dilution Overpower Transients Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-24 Comparison Between Calculated and Measured Relative Fuel Assembly Power Distribution 4.3-25 Comparison of Calculated and Measured Axial Shape 4.3-26 Measured Values of F Q for Full Power Rod Configurations 4.3-27 Doppler Temperature Coefficient at BOL and EOL Cycle l Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-28 Doppler Only Power Coefficient
- BOL, EOL Cycle l Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-29 Doppler Only Power Defect
- BOL, EOL Cycle l Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-30 Moderator Temperature Coefficient
- BOL, Cycle l, No Rods Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-3l Moderator Temperature Coefficient
- EOL, Cycle l Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2)
STPEGS UFSAR LIST OF FIGURES (Continued)
CHAPTER 4 Figure Number Title TC 4-7 Revision 1 8 4.3-32 Moderator Temperature Coefficient as a Function of Boron Concentration
- BOL, Cycle l, No Rods Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-33 Hot Full Power Moderator Temperature Coefficient During Cycle l for the Critical Boron Concentration Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-34 Total Power Coefficient
- BOL, EOL, Cycle l Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-35 Total Power Defect
- BOL, EOL Cycle l Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.3-36 Rod Cluster Control Assembly Pattern 4.3-37 Accidental Simultaneous Withdrawal of Two Control Banks Moving in the Same Plant (Typical) 4.3-38 Not Used 4.3-39 Not Used 4.3-40 Axial Offset Versus Time PWR Core with a l2
-Ft. Height and l2l Assemblies 4.3-4l XY Xenon Test Thermocouple Response Quadrant Tilt Difference Versus Time 4.3-42 Calculated and Measured Doppler Defect and Coefficients at BOL Two
-Loop Plant, l2l Assemblies, l2
-Foot Core STPEGS UFSAR LIST OF FIGURES (Continued)
CHAPTER 4 Figure Number Title TC 4-8 Revision 1 8 4.3-43 Comparison of Calculated and Measured Boron Concentration for 2
-Loop Plant, l2l Assemblies, l2
-Foot Core 4.3-44 Comparison of Calculated and Measured C B in 2-Loop Plant, l2l Assemblies, l2
-Foot Core 4.3-45 Comparison of Calculated and Measured C B in 3-Loop Plant, l57 Assemblies, l2
-Foot Core 4.4-l Comparison of "R" Grid Data for Typical Cell [Reference (42)]
4.4-4 TDC Versus Reynolds Number of 26" Grid Spacing 4.4-5 Normalized Radial Flow and Enthalpy Distribution at Elevation of l/3 Core Height Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.4-6 Normalized Radial Flow and Enthalpy Distribution at Elevation of 2/3 of Core Height Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.4-7 Normalized Radial Flow and Enthalpy Distribution at Core Exit Elevation Unit 1 (Sheet 1 of 2)
Unit 2 (Sheet 2 of 2) 4.4-8 Void Fraction Versus Thermodynamic Quality H
-HSAT/H 9-HSAT 4.4-9 Thermal Conductivity of UO 2 (Data Corrected to 95% Theoretical Density)
STPEGS UFSAR LIST OF FIGURES (Continued)
CHAPTER 4 Figure Number Title TC 4-9 Revision 1 8 4.4-10 l00% Power Shapes Evaluated at Conditions Representative of Loss of Flow, All Shapes Evaluated with
.52 1 H N F 4.4-11 PWR Natural Circulation Test 4.4-12 Comparison of Representative W 2
-Loop Reactor Incore Thermocouple Measurements with THINC
-IV Predictions 4.4-13 Comparison of Representative W 3
-Loop Reactor Incore Thermocouple Measurements with THINC
-IV Predictions 4.4-14 Hanford Subchannel Temperature Data Comparison with THINC
-IV 4.4-15 Hanford Subcritical Temperature Data Comparison with THINC-IV 4.4-20 Distribution of Incore Instrumentation 4.4-21 Reactor Coolant System Temperature Percent Power Map