Functional Description/Background-A brief overview of the study addresses the question of whether or not aging is a significant safety concern for the particular component or system. Source-The research reports upon which the Information is based are listed. Aging Related Issues-This section briefly describes the subcomponents most susceptible to aging, the stresses which affect the service life, and the dominant causes of failure of the component or system. Operating Experience-The failure history of the component or system Is discussed. This operating experience Is typically based on the LER and NPRDS databases, but could include plant specific data. Significant causes and effects of failure are highlighted. Research Recommendations-The largest portion of the Summary is devoted to the recommendations presented in the research reports for detecting and mitigating aging effects. Periodic testing, maintenance, continuous monitoring, and routine inspections are some of the techniques described for the specific components and systems. References-NRC documents and industry standards related to the subject are provided. The NRC doctiments include AEOD reports. Information notices, and regulatory guides, while mdustiy documents could include standards and guides from ASME, IEEE, ISA, NEMA, EPRI, and INPO. Itie "Aging Assessment Guide" Is a more concise document which provides some general observations of the effects of aging on the component or system. The Guide lists recommendations, associated with the maintenance, operations, design, and testing which the research has shown could be beneficial to understanding and managing the aging of that component or system. The statements and recommendations made in this document are based on assessments of operating experience, evaluations of materials, testing of naturally aged equipment, and identification of operating and environmental stresses. The perspectives expressed do not reflect regulatory positions or requirements. This document will be updated periodically to incorporate the results which continue to be obtained tiirough NRC sponsored research into the agtng of nuclear power plant components, systems, and structures. viii Mcifiieitiedgitients The following valuable contributions to the preparation of this document are appreciated: The technical direction from the NRC Program Manager, Mr. Satish K. A^arwal. The constructive comments provided by NRC reviewers from RES and NRR, particularly Mr. Jit Vora.

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