American National Standard


Book Description

This standard specifies criteria for categorization of SSCs and SACs that have a safety function based on radiological and/or chemical dose and exposure levels for the public and workers. The safety categorization leads to codes and standards that are needed for reliable design, construction, and operations commesurate with the safety categorization. The purpose of this standard is: Specify criteria for categorization of safety SSCs; Select industry codes and standards for reliable design, construction, and operations commesurate with the safety organization. To meet these objectives, the standard specifies the requirements in the following steps: identification of hazards; evaluation of hazards; selection of DBEs; unmitigated accident analysis of DBEs; identification of safety functions and categorizations; selection of safety SSCs to fulfill safety function requirements; evaluation, selection, and implmementation of applicable industry codes and standards to ensure safety SSCs are designed, constructed, and maintained to fulfill the intended safety functions.







American National Standard


Book Description

This standard specifies criteria for the safety classification of items [structures, systems, components, and parts (including consumables)] in a light water reactor nuclear power plant as either safety-related (Q), supplemented grade (S), or non-safety-related (N). Criteria are also provided to establish a procurement subclassification within Class Q, called commercial grade (C). In addition, pressure integrity classification criteria are provided for the assignment of Classes 1, 2, 3, 4, or 5 to the pressure retaining portions of items. Withdrawn as an ANSI standard, 2003.




American National Standard


Book Description

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".










American National Standard


Book Description

ANS 54.1-2020 defines safety objectives; sodium fast reactor design criteria (SFRDCs); selection criteria for licensing-basis events; and criteria for the classification of structures, systems, and components (SSCs) that can be used by designers and regulators of SFR nuclear power plants. It is intended to provide the necessary guidance to the designer in order to "bridge" the existing light water reactor-focused general design criteria (GDCs) contained in Appendix A to 10 CFR 50 and other regulatory requirements to the development of their respective principal design criteria, while retaining the underlying safety principles of the GDCs.







American National Standard


Book Description

This standard documents the criteria from which appropriate specific design requirements may be established for the reactor safety system of an individual research reactor.