The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. This standard is for the design qualification section of the program only. This is accomplished by a disciplined program of design qualification and quality more » assurance of design, production, installation, maintenance and surveillance. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. This paper briefly describes the IR and AMG processes and summarizes the unresolved technical issues identified through preparation of the documents. utilities were effective in preventing age-related degradation. With a few noted exceptions, the AMG process indicated that current aging management practices of U.S.
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The eventual use of AMGs in a future license renewal application will likely require NRC interaction at that time. Direct NRC interaction did not take place during preparation of individual AMGs due to their purely technical nature. Examples include certain issues related to fatigue, neutron irradiation embrittlement, intergranular stress corrosion cracking (IGSCC) and electrical cable equipment qualification.
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