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Publication Information
Manuscript Completed: September 2026
Date Published: September 2026
Edited by:
Thomas G. Scarbrough
Nicholas J. Hansing
Sponsored by:
Office of Nuclear Reactor Regulation
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
American Society of Mechanical Engineers
Three Park Avenue
New York, NY 10016-5990
Abstract
The 2025 15th ASME/NRC OM Code Symposium, jointly sponsored by the American Society of Mechanical Engineers (ASME) and the U.S. Nuclear Regulatory Commission (NRC), provided a forum for exchanging information relative to the ASME Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) on technical, programmatic, and regulatory issues associated with inservice testing programs at current nuclear power plants and planned for new and advanced reactors. The symposium provided an opportunity to discuss improvements in design, operation, and testing of valves, pumps, and dynamic restraints and components that perform similar functions at new and advanced reactors. The participation of industry representatives, regulatory personnel, and consultants ensured the presentation of a broad spectrum of ideas and perspectives on improving the inservice testing programs at current nuclear power plants and planned for new and advanced reactors. The slide presentations are publicly available at NRC Agencywide Documents Access and Management System Accession No. ML26023A052, ML26028A102, ML26033A253, ML26040A100, and ML26055A163.