ML21278A107
Text
CHAPTER 4 REACTOR COOLANT AND ASSOCIATED SYSTEMS TABLE OF CONTENTS PAGE 4.0 REACTOR COOLANT AND ASSOCIATED SYSTEMS 4.1-1 4.1 REACTOR COOLANT SYSTEM 4.1-1 4.1.1 DESIGN BASIS 4.1-1 4.1.1.1 Effect of Steam Generator Replacement on Structural 4.1-2 Design Basis 4.1.2 SYSTEM DESCRIPTION 4.1-2 4.1.3 COMPONENT DESCRIPTION 4.1-3 4.1.3.1 Reactor Vessel 4.1-3 4.1.3.2 Steam Generator 4.1-5 4.1.3.3 Reactor Coolant Pumps 4.1-10 4.1.3.4 Reactor Coolant Piping 4.1-16 4.1.3.5 Pressurizer 4.1-17 4.1.3.6 Reactor Coolant Vent System 4.1-21 4.1.4 DESIGN EVALUATION 4.1-22 4.1.4.1 Codes 4.1-22 4.1.4.2 Materials Compatibility 4.1-22 4.1.4.3 Welding Procedures 4.1-23 4.1.4.4 Seismic Design 4.1-26 4.1.4.5 Prevention Of Brittle Fracture 4.1-26 4.1.4.6 Reactor Vessel Thermal Shock 4.1-31 4.1.5 TESTS AND INSPECTIONS 4.1-31 4.1.5.1 General 4.1-31 4.1.5.2 Surveillance Program 4.1-31 4.1.5.3 Non-destructive Tests 4.1-34 4.1.5.4 Additional Tests 4.1-35 4.1.5.5 In-Service Inspection 4.1-36 4.1.5.6 Pre-operational Vibration Test Program 4.1-38 4.1.5.7 Boric Acid Corrosion Monitoring Program 4.1-38 4.
1.6 REFERENCES
4.1-38 4.2 OVERPRESSURE PROTECTION SYSTEM 4.2-1 4.2.1 HIGH TEMPERATURE OVERPRESSURE 4.2-1 4.2.1.1 Design Basis 4.2-1 4.2.1.2 System Description 4.2-1 4.2.2 LOW TEMPERATURE OVERPRESSURE PROTECTION 4.2-3 4.2.3 REFERENCE 4.2-6 4.3 LEAK DETECTION SYSTEM 4.3-1 4.3.1 DESIGN BASIS 4.3-1 4.3.2 SYSTEM DESCRIPTION 4.3-1 4.3.3 DESIGN ANALYSIS 4.3-2 CALVERT CLIFFS UFSAR 4-i Rev. 52
CHAPTER 4 REACTOR COOLANT AND ASSOCIATED SYSTEMS TABLE OF CONTENTS PAGE 4.3.4 IDENTIFIED VERSUS UNIDENTIFIED LEAKAGE 4.3-2 4.3.5 OTHER CONSIDERATIONS 4.3-3 4.4 LOOSE PARTS DETECTION SYSTEM 4.4-1 4.4.1 DESIGN BASIS 4.4-1 4.4.2 SYSTEM DESCRIPTION 4.4-1 4.4.3 DESIGN ANALYSIS 4.4-1 4.5 COASTDOWN OPERATION AT END OF CYCLE 4.5-1 APPENDIX 4A CALVERT CLIFFS REACTOR COOLANT PUMP FLOW 4A.1-1 MEASUREMENT CALVERT CLIFFS UFSAR 4-ii Rev. 52
CHAPTER 4 REACTOR COOLANT AND ASSOCIATED SYSTEMS LIST OF TABLES TITLE PAGE 4-1 PRINCIPAL DESIGN PARAMETERS OF REACTOR COOLANT 4.1-42 SYSTEM 4-2 REACTOR VESSEL PARAMETERS 4.1-43 4-3 STEAM GENERATOR PARAMETERS 4.1-44 4-5 REACTOR COOLANT PUMP PARAMETERS 4.1-45 4-6 REACTOR COOLANT PIPING PARAMETERS 4.1-46 4-7 PRESSURIZER PARAMETERS 4.1-47 4-8 TABLE OF LOADING COMBINATIONS AND PRIMARY STRESS 4.1-48 LIMITS 4-9 REACTOR COOLANT SYSTEM CODE REQUIREMENTS 4.1-50 4-9A REACTOR COOLANT VENT VALVES 4.1-51 4-10 MATERIALS EXPOSED TO COOLANT 4.1-52 4-11 REFERENCES FOR IRRADIATED MATERIAL TEST DATA USED AS 4.1-53 BASIS FOR CE DESIGN CURVE OF FIGURE 4-12 4-11A CALVERT CLIFFS UNIT 1 REACTOR VESSEL BELTLINE MATERIAL 4.1-56 PROPERTIES 4-11B CALVERT CLIFFS UNIT 2 REACTOR VESSEL BELTLINE MATERIAL 4.1-57 PROPERTIES 4-12
SUMMARY
OF SPECIMENS PROVIDED FOR EACH EXPOSURE 4.1-58 LOCATION 4-13A UNIT 1 REACTOR VESSEL SURVEILLANCE CAPSULE REMOVAL 4.1-59 SCHEDULE 4-13B UNIT 2 REACTOR VESSEL SURVEILLANCE CAPSULE REMOVAL 4.1-60 SCHEDULE 4-13C Deleted 4-14 RCS QUALITY ASSURANCE PROGRAM 4.1-61 4-15 RCS INSPECTION CE REQUIREMENTS 4.1-63 4-16 ACTUATOR-OPERATED THROTTLING VALVE PARAMETERS 4.2-7 4-17 ACTUATOR-OPERATED STOP VALVE PARAMETERS 4.2-8 4-18 PRESSURIZER POWER-OPERATED RELIEF VALVE PARAMETERS 4.2-9 4-19 PRESSURIZER SAFETY VALVE PARAMETERS 4.2-10 4-20 Deleted 4-21 QUENCH TANK PARAMETERS 4.2-11 CALVERT CLIFFS UFSAR 4-iii Rev. 52
CHAPTER 4 REACTOR COOLANT AND ASSOCIATED SYSTEMS LIST OF FIGURES FIGURE 4-1 REACTOR COOLANT SYSTEM - UNIT 1 4-2 REACTOR VESSEL 4-3A STEAM GENERATOR PROFILE VIEW 4-3B STEAM GENERATOR PRIMARY HEAD DESIGN 4-4 REACTOR COOLANT PUMP 4-6 REACTOR COOLANT PUMP - SEAL AREA 4-6A REACTOR COOLANT PUMP - SEAL AREA 4-7 REACTOR COOLANT PUMP PERFORMANCE 4-8 PRESSURIZER 4-9 TEMPERATURE CONTROL PROGRAM 4-10 PRESSURIZER LEVEL SET POINT PROGRAM 4-11 PRESSURIZER LEVEL CONTROL PROGRAM 4-12 C-E DESIGN CURVE OF NDTT INCREASE (550F IRRADIATION) 4-13 LOCATION OF SURVEILLANCE CAPSULE ASSEMBLIES 4-14 TYPICAL SURVEILLANCE CAPSULE ASSEMBLY 4-15 TYPICAL CHARPY IMPACT COMPARTMENT ASSEMBLY 4-16 TYPICAL TENSILE - MONITOR COMPARTMENT ASSEMBLY 4-17 REACTOR COOLANT SYSTEM - UNIT 2 4-18 CALVERT CLIFFS COASTDOWN OPERATING REGION CALVERT CLIFFS UFSAR 4-iv Rev. 52
CHAPTER 4 REACTOR COOLANT AND ASSOCIATED SYSTEMS LIST OF ACRONYMS ART Adjusted Reference Temperature ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials B&PV Boiler and Pressure Vessel BGE Baltimore Gas and Electric Company BWC Babcock & Wilcox, Canada CE Combustion Engineering, Inc.
CEA Control Element Assembly CEDM Control Element Drive Mechanism CCNPP Calvert Cliffs Nuclear Power Plant CVCS Chemical and Volume Control System ECCS Emergency Core Cooling System GMA Gas Metal Arc GTA Gas Tungsten Arc HAZ Heat Affected Zone HPSI High Pressure Safety Injection HSST Heavy Section Steel Technology LOCA Loss-of-Coolant Accident LTOP Low Temperature Overpressure Protection MPT Minimum Pressurization Temperature NDTT Nil Ductility Transition Temperature NFPA National Fire Protection Association NSSS Nuclear Steam Supply System OBE Operating Basis Earthquake OSG Original Steam Generator P-T Pressure-Temperature PORV Power-Operated Relief Valve PTS Pressurized Thermal Shock PWSCC Primary Water Stress Corrosion Cracking RCP Reactor Coolant Pump RCS Reactor Coolant System RG Regulatory Guide RSG Replacement Steam Generator RVCH Reactor Vessel Closure Head SA Submerged Arc SCC Stress Corrosion Cracking SG Steam Generator SMA Shielded Metal Arc SRP Standard Review Plan SSE Safe Shutdown Earthquake CALVERT CLIFFS UFSAR 4-v Rev. 52