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ANS-22, Nuclear Facility System Level Design Standards
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ANS-51.1-1993; R1988, Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants
Wanted: Working Group Chair and working group members
Skill Set Required: Mechanical or Safety Engineers
Scope: This standard establishes the nuclear safety criteria and functional design requirements of structures, systems, and components of stationary pressurized water reactor (PWR) power plants. Operations, maintenance, and testing requirements are covered only to the extent that they affect design provisions.
A methodology is given for classifying all equipment into one of three Safety Classes according to its importance to nuclear safety or into a Non-Nuclear Safety Class. Another methodology is given for identifying and categorizing into one of five Plant Conditions the normal operations and events for which the plant shall be designed. Acceptance criteria are given for each Plant Condition.
Specific design requirements are given for each major system in a typical plant. These requirements are related to other, more specific design standards and are intended to amplify the criteria given in the Code of Federal Regulations, Title 10, "Energy," Part 50, "Licensing of Production and Utilization Facilities," Appendix A, "General Design Criteria for Nuclear Power Plants".
ANS-52.1-1978; R1988, Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants
Wanted: Working Group Chair and working group members
Skill Set Required: mechanical or safety engineers
Scope: This standard establishes the nuclear safety criteria and functional design requirements of structures, systems, and components of stationary boiling water reactor (BWR) power plants. Operations, maintenance, and testing requirements are covered only to the extent that they affect design provisions.
A methodology is given for classifying all equipment into one of three Safety Classes according to its importance to nuclear safety or into a Non-Nuclear Safety Class. Another methodology is given for identifying and categorizing into one of five Plant Conditions the normal operations and events for which the plant shall be designed. Acceptance criteria are given for each Plant Condition.
Specific design requirements are given for each major system in a typical plant. These requirements are related to other, more specific design standards and are intended to amplify the criteria given in the Code of Federal Regulations, Title 10, "Energy," Part 50, "Licensing of Production and Utilization Facilities," Appendix A, "General Design Criteria for Nuclear Power Plants."
ANS-55.1-1992, Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants
Wanted: Working Group Chair and working group members
Skill Set Required: rad waste, health physics, mechanical of safety engineers
Scope: This standard sets forth the design, construction, and performance requirements for a solid radioactive waste processing system for light-water-cooled reactor plants. For the purposes of this standard, the solid radioactive waste processing system begins at the interface with the liquid radioactive waste processing system boundary and at the inlets to the spent resin, filter sludge, evaporator concentrate, and phase separator tanks. In addition, this standard pertains to dry active waste, mixed waste, and other solid radioactive waste forms that are generated as part of the operation and maintenance of light-water-cooled reactor plants. The system includes facilities for temporary (up to 30 days of anticipated normal waste generation) on-site storage of packaged waste but terminates at the point of loading the filled drums and other containers on a vehicle for shipping off-site to a licensed disposal site or transfer to interim (up to 5 yr.) on-site storage facilities. The solid radioactive waste processing system is not a safety-class system as defined by American National Standard Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants, ANSI/ANS-51.1-1983 (R1988) or as defined in American National Standard Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants, ANSI/ANS-52.1-1983 (R1988).
ANS-55.4-1993, Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants
Wanted: Working Group Chair and working group members
Skill Set Required: rad waste, health physics, mechanical of safety engineers
Scope: This standard sets forth minimum design, construction, and performance requirements, with due consideration for operation, for gaseous radioactive waste processing systems (GRWPS) for light water reactor (LWR) plants. It is applicable for routine operation, design basis fuel leakage, and other design basis occurrences.
ANS-55.6-1993; R1999, Liquid Radioactive Waste Processing System for Light Water Reactor Plants
Wanted: Working Group Chair and working group members
Skill Set Required: rad waste, health physics, mechanical of safety engineers
Scope: This standard sets forth minimum design, construction, and performance requirements, with due consideration for operation, of the Liquid Radioactive Waste Processing System (LRWPS) for light water reactor (LWR) plants for design basis inputs. It is applicable to routine operation, including design basis fuel leakage and other design basis occurrences.
ANS-59.3-1992, Nuclear Safety Criteria for Control Air Systems
Wanted: Working Group Chair and working group members
Skill Set Required: mechanical or design engineer, or construction experience
Scope: This standard provides criteria for the control air system that furnishes compressed air to nuclear safety-related components and other equipment that could affect any nuclear safety-related function in nuclear power plants.
This standard provides:
(1) the system nuclear safety design requirements and the non-nuclear safety design recommendations for equipment, piping, instruments, and controls that constitute the control air system; and
(2) the nuclear safety design requirements and the non-nuclear safety design recommendations to accommodate the testing and maintenance necessary to ensure adequate performance of the control air system.
This standard applies only to the control air system and does not apply to air-operated devices or the emergency diesel generator starting air system.
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Return to Volunteer Opportunities : NFSC
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