"Reactor Coolant System"

"Reactor Coolant System"

Revision 45—09/30/09 NAPS UFSAR 5-i Chapter 5: Reactor Coolant System Table of Contents Section Title Page 5.1 SUMMARY DESCRIPTION . 5.1-1 5.1.1 Reactor Coolant System Components . 5.1-2 5.1.1.1 Reactor Vessel . 5.1-2 5.1.1.2 Steam Generators. 5.1-2 5.1.1.3 Reactor Coolant Pumps . 5.1-2 5.1.1.4 Piping. 5.1-2 5.1.1.5 Pressurizer . 5.1-3 5.1.1.6 Pressurizer Relief Tank . 5.1-3 5.1.1.7 Safety and Relief Valves . 5.1-3 5.1.1.8 Loop Stop Valves . 5.1-3 5.1.1.9 Reactor Vessel Head Shielding . 5.1-3 5.1.2 Reactor Coolant System Performance and Safety Functions. 5.1-3 5.1.2.1 Reactor Coolant Flow . 5.1-4 5.1.2.2 Interrelated Performance and Safety Functions. 5.1-6 5.1.3 System Operation . 5.1-7 5.1.3.1 Plant Start-up . 5.1-7 5.1.3.2 Power Generation and Hot Shutdown . 5.1-8 5.1.3.3 Plant Shutdown . 5.1-9 5.1.3.4 Refueling . 5.1-10 5.1.3.5 Loss of Decay Heat Removal . 5.1-10 5.1 References . 5.1-12 5.1 Reference Drawings . 5.1-12 5.2 INTEGRITY OF THE REACTOR COOLANT SYSTEM BOUNDARY . 5.2-1 5.2.1 Design Criteria Methods and Procedures. 5.2-1 5.2.1.1 Performance Objectives and Design Conditions . 5.2-1 5.2.1.2 Design Evaluation . 5.2-9 5.2.2 Overpressurization Protection . 5.2-17 5.2.2.1 Normal Operation . 5.2-17 5.2.2.2 Start-up and Shutdown . 5.2-18 5.2.2.3 Water-Solid Protection . 5.2-20 5.2.2.4 Pressurized Thermal Shock . 5.2-20 5.2.3 Material Considerations . 5.2-21 5.2.3.1 Materials of Construction . 5.2-21 5.2.3.2 Chemistry Control . 5.2-30 Revision 45—09/30/09 NAPS UFSAR 5-ii Chapter 5: Reactor Coolant System Table of Contents (continued) Section Title Page 5.2.3.3 Fracture Prevention . 5.2-31 5.2.3.4 Cleaning and Contamination Protection . 5.2-35 5.2.4 Reactor Coolant Pressure Boundary Leakage Detection Systems . 5.2-37 5.2.4.1 Leakage to the Containment . 5.2-37 5.2.4.2 N-16 Primary to Secondary Leakage Detection System . 5.2-41 5.2.5 Inservice Inspection Programs . 5.2-42 5.2.5.1 Program . 5.2-42 5.2.5.2 Inservice Inspection Equipment . 5.2-45 5.2.5.3 Loose Parts Monitoring . 5.2-45 5.2.5.4 Vibration Monitoring. 5.2-46 5.2 References . 5.2-47 5.3 THERMAL-HYDRAULIC SYSTEM DESIGN . 5.3-1 5.4 REACTOR VESSEL AND APPURTENANCES . 5.4-1 5.4.1 Design Bases . 5.4-1 5.4.1.1 Codes and Specifications. 5.4-1 5.4.1.2 Design Transients . 5.4-1 5.4.1.3 Protection Against Nonductile Failure . 5.4-1 5.4.1.4 Inspection. 5.4-2 5.4.2 Description . 5.4-2 5.4.2.1 Fabrication Processes. 5.4-3 5.4.3 Evaluation. 5.4-4 5.4.3.1 Steady-State Stresses . 5.4-4 5.4.3.2 Fatigue Analysis Based on Transient Stresses. 5.4-4 5.4.3.3 Thermal Stresses Due to Gamma Heating. 5.4-4 5.4.3.4 Thermal Stresses Due to a LOCA . 5.4-4 5.4.3.5 Heatup and Cooldown . 5.4-4 5.4.3.6 Irradiation Surveillance Program. 5.4-4 5.4.3.7 Capability for Annealing the Reactor Vessel . 5.4-11 5.4.4 Tests and Inspections . 5.4-11 5.4.4.1 Ultrasonic Examinations . 5.4-12 5.4.4.2 Penetrant Examinations . 5.4-12 5.4.4.3 Magnetic Particle Examinations . 5.4-12 5.4.4.4 Inservice Inspection. 5.4-12 Revision 45—09/30/09 NAPS UFSAR 5-iii Chapter 5: Reactor Coolant System Table of Contents (continued) Section Title Page 5.4 References . 5.4-13 5.5 COMPONENT AND SUBSYSTEM DESIGN . 5.5-1 5.5.1 Reactor Coolant Pumps . 5.5-1 5.5.1.1 Design Bases . 5.5-1 5.5.1.2 Design Description . 5.5-1 5.5.1.3 Design Evaluation . 5.5-3 5.5.1.4 Tests and Inspections. 5.5-7 5.5.2 Steam Generator . 5.5-11 5.5.2.1 Design Bases . 5.5-11 5.5.2.2 Design Description . ..

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