LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems

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Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML17046A347
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Site: Salem  PSEG icon.png
Issue date: 01/30/2017
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Public Service Enterprise Group
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Office of Nuclear Reactor Regulation
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LR-N17-0034
Download: ML17046A347 (16)
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Section 5.1 5 .1.1 5 .1.2 5 .1.3 5.2 5.2.1 5.2.1.1 5.2.1.2 5.2.1.3 5.2.1.4 5.2.1.5 5.2.1.5.1 5.2.1.5.2 5.2.1.5.3 5.2.1.5.4 5.2.1.5.5 5.2.1.5.6 5.2.1.5.7 5.2.1.5.8 5.2.1.5.9 5.2.1.5.10 5.2.1.5.11 5. 2 .1.5 .12 5.2.1.5.13 SGS-UFSAR SECTION 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS TABLE OF CONTENTS

SUMMARY

DESCRIPTION Piping and Instrumentation Diagram Arrangement Drawing References for Section 5.1 INTEGRITY OF REACTOR COOLANT PRESSURE .. BOUNDARY Design of Reactor Coolant Pressure Boundary Performance Objectives Design Parameters Compliance With lOCFR50.55a Applicable Code Cases Design Transients Heatup and Cooldown Unit Loading and Unloading Step Increase and Decrease of 10 Percent 50-Percent Step Decrease in Load Loss-of-Load Loss of Power Loss of Flow Reactor Trip from Full Power Turbine Roll Test Hydrostatic Test Conditions Primary Side Leak Test Pressurizer Surge and Spray Line Connections Accident Conditions 5-i 5.1-1 5.1-8 5.1-8 5.1-8 5.2-1 5.2-1 5.2-1 5.2-2 5.2-4 5.2-4 5.2-4 5.2-5 5.2-6 5.2-7 5.2-8 5.2-8 5.2-9 5.2-9 5.2-10 5.2-10 5.2-11 5. 2-11 5.2-12 5.2-13 Revision 6 February 15, 1987 Section 5.2.1.6 5.2.1.7 5.2.1.7.1 5.2.1.7.2 5.2.1.7.3 5.2.1.7.4 5.2.1.7.5 5.2.1.7.6 5.2.1.8 5.2.1.8.1 5.2.1.8.2 5.2.2 5.2.2.1 5.2.2.2 5.2.2.3 5.2.3 5.2.3.1 5.2.3.2 5.2.3.3 5.2.3.4 5.2.3.5 5.2.4 5.2.4.1 5.2.4.2 5.2.4.3 5.2.4.3.1 5.2.4.3.2 5.2.4.3.3 SGS*UFSAR TABLE OF CONTENTS (Coot) Title Protection Against Environmental Factors Protection Against Proliferation of Dynamic Effects Criteria Dynamic Effects Barriers Restraints Supports Physical Separation Design Criteria for Vessels and Piping Load Combinations and Stress .Criteria Stress Analysis for Structural Adequacy Overpressurization Protection Pressure-Relieving Devices Report on Overpressure Protection RCS Pressure Control During Low Temperature Operation General Material Considerations Material Specifications Compatibility With Reactor Coolant Compatibility With External Insulation Chemistry of Reactor Coolant Electroslag Weld Quality Assurance Fracture Toughness Compliance With Code Requirements Acceptable Fracture Energy Levels Operating Limitations During Starting and Shutdown Maximum Heating and Cooling Rates Maximum Pressure System Minimum Operating Conditions 5-ii 5.2-15 5.2-15 5.2-15 5.2-16 5.2-16 5.2-17 5.2-17 5.2-18 5.2-18 5.2-18 5.2-21 5.2-38 5.2-38 5.2-39 5.2-39 5.2-40 5.2-41 5.2-42 5.2-42 5.2-43 5.2-43 5.2-47 5.2-47 5.2-47 5.2-48 5.2-48 5.2-48 5.2-49 Revision 6 February 15, 1987 * * *

  • section 5.2.4.4 5.2.4.4.1 5.2.4.4.2 5.2.4.5 5.2.4.6 5.2.5 5.2.6 5.2.7 5.2.7.1 5.2.7.1.1 5.2.7.1.2 5.2.7.1.3 5.2.7.1.4 5.2.7.1.5
  • 5.2.7.2 5.2.8 5.2.8.1 5.2.8.2 5.2.8.3 5.2.8.4 5.2.8.5 5.2.9 5.3 5.3.1 5.3.2 5.3.3
  • SGS-UFSAR TABLE OF CONTENTS (Cant) Title Page C.ompliance With Reactor vessel Material Surveillance Program Requirements 5.2-49 Surveillance Capsule 5.2-49 Material Properties of salem 1 and 2 Reactor Pressure Vessels 5.2-56 Pressurized Thermal Shock {PTS) 5.2-56a Charpy Upper Shelf Energy 5.2-57 Austenitic Stainless Steel 5.2-57 Pump Flywheels 5.2-63 Reactor Coolant Pressure Boundary Leakage Detection Systems 5.2-64 Leakage Detection Methods 5.2-65 Containment Air Particulate and Containment Radiogas Monitors 5.2-66 Humidity Detector 5.2-67 Liquid Inventory in the Process Systems and in the Containment Sump Condensate Measuring System Intersystem Leakage Detection Indication in Control Room Inservice Inspection Program Provisions for Access to Reactor Coolant Pressure Boundary Equipment for Inservice Inspections Recording and comparing Data Reactor Vessel Acceptance Standards Coordination of Inspection Equipment With Access Provisions Reference for Section 5.2 THERMAL HYDRAULIC SYSTEM DESIGN Analytical Methods and Data Operating Restrictions on Pumps Temperature Power Operating Map 5-iii 5.2-68 5.2-68 5.2-69 5.2-70 5.2-70 5.2-71 5.2-71 5.2-72 5.2-72 5.2-72 5.2-73 5.3-l 5.3-1 5.3-l 5.3-l Revision 19 November 19, 2001 I I Section 5.3.4 5.3.5 5.3.6 5.3.7 5.4 5.4.1 5.4.2 5.4.3 5.4.3.1 5.4.3.2 5.4.3.3 5.4.3.4 5.4.3.5 5.4.3.6 5.4.4 5.4.5 5.5 5.5.1 5.5.1.1 5.5.1.2 5.5.1.3 5.5.1.3.1 5.5.1.3.2 5.5.1.3.3 5.5.1.3.4 SGS-UFSAR TABLE OF CONTENTS (Cont) Load Following Characteristics Transient Effects Thermal and Hydraulic Characteristics Summary Table Natural Circulation Capability REACTOR VESSEL AND APPURTENANCES Design Basis Description Evaluation Compliance With lOCFRSO Appendices G and H Radiation Analysis and Neutron Dosimetry of Surveillance Capsules Neutron Transport Methodology Neutron Dosimetry Vessel Fluence Calculation for Fracture Toughness Determination for Salem Units Measurement of the Initial NOT Temperature of the Reactor Pressure Vessel Base Plate and Forging Material Tests and Inspections References for Section 5.4 COMPONENT AND SUBSYSTEM DESIGN Reactor Coolant Pumps Design Basis Design Description Design Evaluation Pump Performance Coastdown Capability Flywheel Integrity Bearing Integrity 5-iv 5.3-l 5.3-l 5.3-l 5.3-1 5.4-l 5.4-1 5.4-l 5.4-3 5.4-3 5,4-6 5.4-6 5.4-9 5.4-10b 5.4-11 5.4-13 5.4-14 5.5-l 5.5-1 5.5-l 5.5-1 5.5-4 5.5-4 5.5-5 5.5-5 5.5-5 Revision 19 November 19, 2001 * *
  • Section 5.5.1.3.5 5.5.1.3.6 5.5.1.3.7 5.5.1.3.8 5.5.1.3.9 5.5.1.3.10 5.5.1.3.11 5. 5 .1. 3.12 5.5.1.3.13 5.5.1.3.14 5.5.1.4 5.5.2 5.5.2.1 5.5.2.2 5.5.2.3 5.5.2.3.1 5.5.2.3.2 5.5.2.3.3 5.5.2.3.4 5.5.3 5.5.3.1 5.5.3.2 5.5.3.3 5.5.3.4 5.5.3.5 5.5.4 5.5.5 5 .5. 6 5.5.7 5.5.7.1 5.5.7.2 SGS-UFSAR TABLE OF CONTENTS (Cant) Locked Rotor Critical Speed Missile Generation Pump Cavitation Title Pump Overspeed Considerations Anti-Reverse Rotation Device Shaft Seal Leakage Seal Discharge Loss of Offsite AC Power Loss of Component Cooling Water Test and Inspections Steam Generators Design Bases Design Description Design Evaluation Natural Circulation Flow Secondary System Fluid Flow Instability Prevention Tube and Tube Sheet Stress Analyses Flow-Induced Vibration Reactor Coolant Piping Design Bases Design Description Design Evaluation Material Corrosion/Erosion Evaluation Tests and Inspections Main Steam Line Flow Restrictors Main Steam Line Isolation System Reactor Core Isolation Cooling System Residual Heat Removal System Design Bases System Description 5-v 5.5-6 5.5-7 5.5-7 5.5-7 5.5-8 5.5-8 5.5-9 5.5-9 5.5-9 5.5-10 5.5-10 5.5-10 5.5-10 5.5-11 5.5-13 5.5-13 5.5-13 5.5-14 5.5-14 5.5-19 5.5-19 5.5-19 5.5-23 5.5-23 5.5-24 5.5-24 5.5-24 5.5-24 5.5-24 5.5-24 5.5-26 Revision 24 May 11, 2009 5.5.7.3 5.5.7.3.1 5.5.7.3.2 5.5.7.3.3 5.5.7.3.4 5.5.7.3.5 5.5.7.4 5.5.8 5.5.9 5.5.10 5.5.10.1 5.5.10.1.1 5.5.10.1.2 5.5.10.2 5.5.10.2.1 5.5.10.2.2 5.5.10.3 5.5.10.3.1 5.5.10.3.2 5.5.10.3.3 5.5.10.3.4 5.5.10.4 5.5 .11 5.5.11.1 5.5.11.2 5.5.11.3 5.5.12 5.5.13 5.5.13.1 5.5.13.2 5.5.13.3 SGS-UFSAR TABLE OF CONTENTS (Cont) Design Evaluation Provisions RCS Isolation Provisions Failure Analysis Compliance with Branch Technical Position RSB 5-l Hydraulic Performance at Run-Out Tests and Inspections Reactor Coolant Cleanup System Main Steam Line and Feedwater Pressurizer Design Bases Pressurizer Surge Line Pressurizer Volume Design Description Pressurizer Surge Line Pressurizer Design Evaluation Pressure Control Pressurizer Level Control Pressure Setpoints Pressurizer Spray Tests and Inspections Pressurizer Relief Tank Design Bases Design Description Design Evaluation Valves and Relief Valves Design Bases Design Description Design Evaluation 5-vi 5.5-29 5.5-29 5.5-30 5.5-31 5.5-31 5.5-44 5.5-45 5.5-45 5.5-45 5.5-46 5.5-46 5.5-46 5.5-46 5.5-47 5.5-47 5.5-47 5.5-50 5.5-50 5.5-50 5.5-51 5.5-51 5.5-52 5.5-52 5.5-52 5.5-52 5.5-53 5.5-54 5.5-55 5.5-55 5.5-56 5.5-57 Revision 6 February 15, 1987 Section 5.5.14 5.5.14.1 5.5.14.2 5.5.14.3 5.5.14.4 5.5.15 5. 5.16 5.6 5.6.1 5. 6.2 5. 6.3 5. 6. 4 5.6.5 5.6.6 5.6.7 5.6.8 SGS-UFSAR TABLE OF CONTENTS (Cant) Title Reactor Coolant System Component Supports Description Fabrication Evaluation Inspection Partial RCS Loop Operation References for Section 5.5 INSTRUMENTATION APPLICATION Loop Temperature Pressurizer Temperature Pressure Pressurizer Water Level Reactor Vessel Water Level Reactor Coolant Flow Reactor Coolant Pump Motor Instrumentation Loose Parts Monitoring 5-vii 5.5-57 5.5-57 5.5-59 5.5-60 5.5-60 5.5-61 5.5-63 5.6-1 5.6-1 5.6-2 5.6-3 5.6-4 5.6-5 5.6-6a 5.6-7 5.6-8 Revision 24 May 111 2009 Table 5.1-1 5.2-l 5.2-2 5.2-3 5.2-4 5.2-5 5.2-6 5.2-7 5.2-8 5.2-9A 5.2-9B 5.2-10 5.2-11 5.2-12 5.2-13 I 5.2-14 SGS-UFSAR LIST OF TABLES System Design and Operating Parameters Reactor Coolant System Design Pressure Settings Reactor Coolant System Design Pressure Drop Reactor Vessel Design Data Pressurizer and Pressurizer Relief Tank Design Data Steam Generator Design Data Reactor Coolant Pumps Design Data Reactor Coolant Piping Design Parameters Pressurizer Valves Design Parameters Reactor Coolant System -codes -Unit 1 Reactor Coolant System -Codes -Unit 2 Design Thermal and Loading Cycles Summary of Plant Outage for Yankee Rowe (1964 to 1969) Load Combinations and Stress Limits Loading Conditions and Stress Limits: Pressure Vessels Summary of Primary Plus Secondary Stress Intensity Ranges for components of the Reactor Vessel 5-viii Revision 19 November 19, 2001 * *
  • 5.2-15 5.2-16 5. 2-17 5.2-18 5.2-19 5.2-20 5.2-21 5.2-22 5.2-23 5.2-24 SGS-UFSAR LIST OF TABLES (Cant) Summary of Cumulative Fatigue Usage Factors for Components of the Reactor Vessel Stress Due to Maximum Steam Generator Tube Sheet Pressure Differential (2485 psig) Ratio of Allowable Stress to Computed Stresses for a Steam Generator Tube Sheet Pressure Differential of 2485 psig Steam Generator Primary-Secondary Boundary Components (100-percent Load Operation) Steam Generator Primary-Secondary Components (Primary-Hydrotest) Steam Generator Primary-Secondary Boundary Components (Secondary Chamber Hydrotest) Steam Generator Primary-Secondary Boundary Components (Loss of Secondary Pressure -Faulted Condition) Model 61/19T Steam Generator Usage Factors (Individual Transients) Primary and Secondary Boundary Components Model 61/19T Steam Generator Usage Factors (Individual Transient) Center of Tube Sheet Tube Sheet Stress Analysis Results for Model 61/19T Steam Generators 5-ix Revision 24 May 11, 2009 5.2-25 5.2-26 5.2-27 5.2-28 5.2-29 5.2-30 5.2-31 5.2-32 5.2-33 5.2-34 5.2-35 5.2-36 5.2-37 5.2-38 5.2-39 5.2-40 5.2-41 5.2-42 SGS-UFSAR LIST OF TABLES (Cant} Limit Pressures, Generators and Calculation Results Fatigue Evaluations Table of for Model Strains, 61/19T Limit Steam Reactor Coolant System Quality Assurance Materials Construction of the Reactor Coolant System Reactor Coolant Water Chemistry Specification DELETED RPV Beltline Region Weld Chemistry for Salem Units 1 and 2 RPV Beltline Region Weld Mechanical Properties for Salem Units 1 and 2 RPV Beltline Region Plate Material Chemical and Mechanical Stress Results of Unit 1 Tubesheet and Shell Junctions Analysis (Model F' SG) Unit 1 SG) Unit 1 Unit 1 Salem 1 Salem 2 Salem 1 Salem 2 Salem 1 Salem 2 Secondary Shell and Transition Cone Stress Results (Model Stress Results of Tube (Model F SG) Tube Analysis for External Pressure (Model F SG) Predicted EOL RTNDT Predicted EOL RTNDT Predicted RTrrs For Predicted RTPTS For Use Projections For Use Projections For 5-x For Reactor Vessel Beltline Materials For Reactor Vessel Belt line Materials Reactor Vessel Reactor Vessel Reactor Vessel Reactor Vessel Belt line Materials Beltline Materials Beltline Materials Beltline Materials Revision 24 May 11, 2009 F
  • 5.4-l 5.4-2 5.4-3 5.4-4 5.4-5 5.4-6 5.4-7
  • 5.4-8 5.4-9 5.4-10 5.5-1 5.5-2 5.5-3
  • SGS-UFSAR LIST OF TABLES (Cent) Reactor Vessel Material Properties Reactor Vessel Material Properties -Closure Head Studs -Closure Head Nuts and Washers Deleted Deleted Deleted Nuclear Constants for Neutron Flux Monitors Contained in the Salem Unit 1 surveillance Capsules Fast Fluence (>1 MeV) for Salem 1 Reactor vessel Beltline Materials Fast Fluence (>1 MeV) for Salem 2 Reactor Vessel Beltline Materials Deleted Deleted Residual Heat Removal system Design Parameters Residual Heat Removal System Failure Analysis Salem Nuclear Generating Stations -Unit Nos. 1 and 2 -Steam Generator and Reactor Coolant Pump supports -Loading Combination and Allowable Stress Limits 5-xa Revision 19 November 19, 2001 THIS PAGE INTENTIONALLY BLANK 5-xb SGS-UFSAR Revision 7 July 22, 1987 Figure 5.1-1 5.1-2 5.1-3 5.1-3A 5.1-4 5.1-5 5.1-6A 5.1-68 5.1-6C 5.1-7 5.1-8 5.1-9 5.1-10 5.1-11 5.1-12 5.1-13 SGS-UFSAR LIST OF FIGURES Reactor Vessel Schematic Cutaway View of Pressurizer Steam Generator Unit 2 Only Steam Generator (Unit 1) Cutaway View of Reactor Coolant Pump Reactor Coolant Pump Performance Characteristics Deleted: Refer to Plant Drawing 205201 Deleted: Refer to Plant Drawing 205301 Logic Diagram, Head Vent System Unit 1 & 2 Deleted: Refer to Plant Drawing 204803 Deleted: Refer to Plant Drawing 204804 Deleted: Refer to Plant Drawing 204805 Deleted: Refer to Plant Drawing 204806 Deleted: Refer to Plant Drawing 204807 Auxiliary Building and Reactor Containment Elevation Deleted: Refer to Plant Drawing 204808 5-xi Revision 27 November 25, 2013 Figure 5.2-1 5.2.-2 5.2-3 5.2-4 5.2-5 5.2-6 5.2-7 5.2-8 5.2-9 5.2-10 5. 2-11 5.2-12 SGS-UFSAR LIST OF FIGURES (Cont) Typical Stress -Strain Curve Comparison Between Design and Collapse Conditions (0. 90 s ) y Comparison Between Design and Collapse Conditions (0.00 s ) y Reactor Vessel Stress Analysis Areas Examined Reactor Vessel Stress Analysis Details -Upper Reactor Vessel Stress Analysis Details -Lower Primary and Secondary Hydrostatic Test Stress History for the Center Hole Location Plant Heatup and Operational Loading Transients (With Steady-State Plateau) Stress History for the Hot Side Center Hole Location Large Step Load Decrease and Loss of Flow Stress History for the Hot Side Center Hole Location Primary and Secondary Boundary Components Shell Locations of Stress Investigations Reactor Coolant System Heatup Limitations for First 8 EFPY of Operation Reactor Coolant System Cooldown Limitations for First 8 EFPY of Operation 5-xii Revision 6 February 15, 1987 Figure 5.2-13 5.2-14 5.2-15 5.2-16 5.2-17 5.2-18 5.2-19 5.2-20 5.2-21 5.4-1 5.4-2 5.4-3 5.5-1 5.5-2A SGS-UFSAR LIST OF FIGURES (Cant) Deleted Typical Surveillance Capsule Elevation View Surveillance Capsule Plan View Reactor Coolant Pump Flywheel Flywheel Characteristics Curve Reactor Pressure Vessel Assembly Identification and Location of Beltline Region Material for the Salem Unit No. 1 Reactor Vessel Identification and Location of Beltline Region Material for the Salem Unit No. 2 Reactor Vessel Arrangement of Surveillance Capsules in the Reactor Pressure Vessel Salem Unit 1 Reactor Geometry Plan View of a Reactor Vessel Surveillance Capsule Capsule Y Diagram Showing Location of Specimens, Thermal Monitors, and Dosimeters Reactor Coolant Pump Deleted: Refer to Plant Drawing 205232 5-xiii Revision 27 November 25, 2013 Figure 5.5-28 5.5-3 5.5-4 5.5-5 5.5-6 5.5-7 SGS-UFSAR LIST OF FIGURES (Cant) Deleted: Refer to Plant Drawing 205332 Deleted: Refer to Plant Drawing 201194 Deleted: Refer to Plant Drawing 208903 Reactor Coolant Pump Supports Deleted: Refer to Plant Drawing 208902 Deleted: Refer to Plant Drawing 208907 5-xiv Revision 27 November 25, 2013
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