The NRNF Consensus Committee is responsible for the preparation and maintenance of voluntary consensus standards for the safety analysis, design, maintenance, operator selection and training, and quality requirements for non-reactor nuclear facilities including facilities using radioactive isotopes, remote handling of radioactive materials, fuel processing, mixed oxide fuel processing and other fuel cycle facilities other than spent fuel handling and storage. The ANS Standards Committee Procedures Manual for Consensus Committees shall be used to guide the activities of this consensus committee.
Scope: This standard addresses requirements for systematically evaluating structures, systems, and components (SSCs) for extending the life of non-reactor nuclear facilities. This standard is applicable to facilities that are 15 to 30 years old and expect to operate for an additional 20 to 30 years. This standard provides a systematic process to determine the scope of the aging management/life extension program in terms of SSCs. For those SSCs, a process for the evaluation of remaining lifetime and determining the need for additional analysis, repairs, inspections, and replacements is developed.
Scope: This standard provides an ISA method consistent with 10 CFR Part 70 regulations to identify credible accident sequences that can lead to "high" or "intermediate" consequences as outlined in 10 CFR 70.61 performance requirements. The ISA also specifies items relied on for safety (IROFS) to prevent or mitigate those potential accidents and assess the likelihood that the facilities would meet the 10 CFR 70.61 performance requirements, and management measures a licensee will rely on to ensure IROFS are available to perform their function. ISAs look not just at radiological and nuclear criticality hazards, but chemical and fire risks as well.
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.
Last updated July 22, 2014, 2:55pm CDT.