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1、美国核管会，10 CFR Part 50, Appendix A，核电厂设计总则Appendix A to Part 50-General Design Criteria for Nuclear Power PlantsTable of Contents Introduction Definitionso Nuclear Power Unito Loss of Coolant Accidentso Single Failureo Anticipated Operational OccurrencesCRITERIANumberQuality Standards and Records 1Des
2、ign Bases for Protection Against Natural Phenomena2Fire Protection 3Environmental and Dynamic Effects Design Bases4I. Overall Requirements:Sharing of Structures, Systems, and Components5Reactor Design 10Reactor inherent Protection 11Suppression of Reactor Power Oscillations12Instrumentation and Cont
3、rol 13Reactor Coolant Pressure Boundary 14Reactor Coolant System Design 15II. Protection by Multiple Fission Product Barriers:Containment Design 16Electric Power Systems 17Inspection and Testing of Electric Power Systems18Control Room 19Protection System Functions 20Protection System Reliability and
4、 Testability21Protection System Independence 22Protection System Failure Modes 23Separation of Protection and Control Systems24Protection System Requirements for Reactivity Control Malfunctions25Reactivity Control System Redundancy and Capability26Combined Reactivity Control Systems Capability27Reac
5、tivity Limits 28III. Protection and Reactivity Control Systems:Protection Against Anticipated Operational Occurrences29Quality of Reactor Coolant Pressure Boundary30Fracture Prevention of Reactor Coolant Pressure Boundary31Inspection of Reactor Coolant Pressure Boundary32Reactor Coolant Makeup 33Res
6、idual Heat Removal 34Emergency Core Cooling 35Inspection of Emergency Core Cooling System36Testing of Emergency Core Cooling System37Containment Heat Removal 38IV. Fluid Systems:Inspection of Containment Heat Removal System39Testing of Containment Heat Removal System40Containment Atmosphere Cleanup
7、41Inspection of Containment Atmosphere Cleanup Systems42Testing of Containment Atmosphere Cleanup Systems43Cooling Water 44Inspection of Cooling Water System 45Testing of Cooling Water System 46Containment Design Basis 50Fracture Prevention of Containment Pressure Boundary51Capability for Containmen
8、t Leakage Rate Testing52Provisions for Containment Testing and Inspection53Systems Penetrating Containment 54Reactor Coolant Pressure Boundary Penetrating Containment55Primary Containment Isolation 56V. Reactor Containment:Closed Systems Isolation Valves 57Control of Releases of Radioactive Material
9、s to the Environment60Fuel Storage and Handling and Radioactivity Control61Prevention of Criticality in Fuel Storage and Handling62Monitoring Fuel and Waste Storage 63VI. Fuel and Radioactivity Control:Monitoring Radioactivity Releases 64IntroductionPursuant to the provisions of 50.34, an applicatio
10、n for a construction permit must include the principal design criteria for a proposed facility. The principal design criteria establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety; that is, structu
11、res, systems, and components that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public.These General Design Criteria establish minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in d
12、esign and location to plants for which construction permits have been issued by the Commission. The General Design Criteria are also considered to be generally applicable to other types of nuclear power units and are intended to provide guidance in establishing the principal design criteria for such
13、 other units.The development of these General Design Criteria is not yet complete. For example, some of the definitions need further amplification. Also, some of the specific design requirements for structures, systems, and components important to safety have not as yet been suitably defined. Their
14、omission does not relieve any applicant from considering these matters in the design of a specific facility and satisfying the necessary safety requirements. These matters include:(1) Consideration of the need to design against single failures of passive components in fluid systems important to safe
15、ty. (See Definition of Single Failure.)(2) Consideration of redundancy and diversity requirements for fluid systems important to safety. A system could consist of a number of subsystems each of which is separately capable of performing the specified system safety function. The minimum acceptable red
16、undancy and diversity of subsystems and components within a subsystem, and the required interconnection and independence of the subsystems have not yet been developed or defined. (See Criteria 34, 35, 38, 41, and 44.)(3) Consideration of the type, size, and orientation of possible breaks in components of the reactor coolant pressure boundary in determining design requirements to suitably protect against postulated loss-of-coolant accidents. (See Definition of Loss of Coolan
