Status of Code Cases Related to Application of Risk-Informed Inservice Inspection in ASME Code Section XI

[+] Author and Article Information
O. F. Hedden

ABB Combustion Engineering Nuclear Power, Department 9481-1934, 2000 Day Hill Road, Windsor, CT 06095-0500

J. Pressure Vessel Technol 120(4), 438-440 (Nov 01, 1998) (3 pages) doi:10.1115/1.2842356 History: Received April 16, 1998; Revised May 21, 1998; Online February 11, 2008


ASME Code Section XI Cases N-577 and N-578, for application of risk-informed technology to examination of piping systems in nuclear power plants, are proceeding, with review and acceptance by ASME Board on Nuclear Codes and Standards and by the U.S. Nuclear Regulatory Commission remaining before implementation. Sources of support for a favorable reaction by NRC will be reviewed, starting with developmental research sponsored by NRC in the late 1980s. Extensive discussion in the engineering community as exemplified by forums presented by ASME PVP in 1994 and 1995 will be cited. Recent academic and NRC managerial support for risk-informed performance-based regulation will also be cited. The expressed need for risk neutrality will then be addressed.

Copyright © 1998 by The American Society of Mechanical Engineers
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