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ANS > Standards > Get Involved > Volunteer Opportunities > NFSC > ANS-22 |
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ANS-22, System Design Criteria If you are interested in participating in the following standards, complete and submit the Standards Volunteer Form. ANS-2.26, Categorization of Nuclear Facility Structures, Systems, and Components For Seismic Design  Scope: This standard provides: (a) criteria for selecting the seismic design category1) (SDC) for nuclear facility structures, systems, and components (SSCs) to achieve earthquake safety and (b) criteria and guidelines for selecting Limit States for these SSCs to govern their seismic design. The Limit States are selected to ensure the desired safety performance in an earthquake. 1) The SDCs used in this standard are not the same as the SDCs referred to in the International Building Code (IBC). ANS-51.10, Auxiliary Feedwater System for Pressurized Water Reactors Scope: This standard sets forth the nuclear safety-related functional requirements, performance requirements, design criteria, design requirements for testing and maintenance, and interfaces for the nuclear safety-related portion of the auxiliary feedwater system (AFS) of pressurized water reactor (PWR) plants. ANS-55.1, Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants 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, Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants 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, Liquid Radioactive Waste Processing System for Light Water Reactor Plants 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-58.3, Physical Protection for Nuclear Safety-Related Systems and Components Scope: This standard sets forth physical protection criteria for nuclear safety-related systems and components in stations using light water reactors (LWRs). This standard includes an identification of potential hazards to nuclear safety-related systems and components and acceptable means of ensuring the protection of this equipment from these hazards. ANS-58.8, Time Response Design Criteria for Safety-Related Operator Actions Scope: This standard establishes time response design criteria for safety-related operator actions to be used in the design of light water reactor (LWR) nuclear power plants. The criteria are used to determine the minimum response time intervals for safety-related operator actions that are taken to mitigate design basis events (DBEs) which result in an automatic reactor trip. This standard specifies time requirements that are to be met to receive credit in the safety analysis for operator actions that initiate or control safety-related functions. Specifically, the criteria provide bases:(1) For establishing certain requirements for determining whether a particular action to initiate or control a safety-related system might be accomplished by operator action or must be accomplished by an automatic action.(2) For determining when design modifications can obviate the need for automatic actions that would otherwise be required.(3) For general guidance for hardware, such as instrumentation, controls, indicators, and annunciators necessary to support safety-related operator actions. ANS-58.9, Single Failure Criteria for Light Water Reactor Safety-Related Fluid Systems Scope: This standard provides criteria for the designer which interpret the requirements of Title 10, Code of Federal Regulations, Part 50, "Licensing of Production and Utilization Facilities," Appendix A, "General Design Criteria for Nuclear Power Plants," with respect to design against single failures in safety-related Light Water Reactor (LWR) fluid systems. Means of treating both active and passive failures are addressed for safety-related fluid systems following various initiating events. Current acceptable practice is used as a basis for these criteria. ANS-58.11, Design Criteria for Safe Shutdown Following Selected Design Basis Events in Light Water Reactors Scope: This standard provides design criteria for systems that perform the safety-related functions necessary to shut down a reactor and maintain it in a safe shutdown condition for selected design basis events; i.e., any design basis events that do not require operation of engineered safety features. For design basis events that require operation of engineered safety features, this standard can be selectively applied because of plant features specifically designed for these conditions. For systems that serve multiple functions, the design criteria associated with the most limiting function shall be applied. The following safety-related functions are required for safe shutdown and are addressed in this standard: (1) Reactor core reactivity control, (2) Reactor core heat removal, (3) Reactor coolant pressure boundary integrity provided by: (a) Temperature control, (b) Pressure control, and (c) Inventory control. ANS-58.14, Safety and Pressure Integrity Classification Criteria for Light Water Reactors Scope: This standard specifies deterministic criteria for the safety classification of items (i.e., SSCs and parts (including consumables)) in a LWR NPP as either safety-related (Q), supplemented grade (S), or non-safety-related (N). Criteria provide and establish a procurement subclassification within Class Q, called commercial grade (C). In addition, pressure integrity classification criteria provide for the assignment of Classes 1 to 5 to the pressure-retaining portion of items. ANS-58.16, Safety and Pressure Integrity Classification for Non-Reactor Nuclear Facilities Scope: This standard provides guidance for the safety classification of items [structures, systems, components and parts (including consumables)] associated with nuclear safety in non-reactor nuclear facilities such as: nuclear storage and processing facilities, nuclear material and radioactive waste facilities, and nuclear fuel examination facilities. Pressure integrity classification criteria are provided for assignment of Safety Design Classes, SDC 1,2,3,4 or 5 to the nuclear safety related and pressure retaining portions of items and to include associated load criteria. Also provides allowable behavior criteria to identify Limit States A, B, C, and D that is currently defined in ANS standards for seismic loads. ANS-59.3, Nuclear Safety Criteria for Control Air Systems 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. ANS-59.51, Fuel Oil Systems for Safety-Related Emergency Diesel Generators Scope: This standard provides functional, performance, and initial design requirements for the fuel oil system for diesel generators that provide safety-related emergency onsite power for light water reactor nuclear power plants. This standard addresses the mechanical equipment associated with the fuel oil system, with the exception of the engine mounted components. These components, which are mounted directly to the engine structure itself, are excluded except to define interface requirements. It also includes the instrumentation and control functional requirements. The standard excludes motors, motor control centers, switchgear, cables, and other electrical equipment used in the operation of the fuel oil system, except to define interface requirements. ANS-59.52, Lubricating Oil Systems for Safety-Related Emergency Diesel Generators Scope: This standard provides functional, performance, and design requirements for lubricating oil systems for diesel generators that provide emergency onsite power for light water reactor nuclear power plants. The standard addresses all mechanical equipment associated with the lubricating oil system, with the exception of engine mounted components. These components, which are mounted directly to engine structure itself, are excluded, except to define interface requirements. This standard also includes the lubricating oil system instrumentation and control functional requirements. It excludes motors, motor control centers, switchgear, cables, and other electrical equipment used in the operation of the lubricating oil system, except to define interface requirements. |
