Reliability and Integrity Management Scoping Study

Technical Report · Tue Mar 14 04:00:00 EDT 2023

DOI:https://doi.org/10.2172/2203928· OSTI ID:2203928

Anselmi, Todd Michael ^[1]; Vetter, Daniel L ^[1]; Lawrence, Svetlana ^[1]

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1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)

The U.S. Nuclear Regulatory Commission (NRC) is developing the regulatory framework and technical expertise to support regulatory review of advanced non-light water reactor (ANLWR) designs. The NRC staff expects most of these designs to use the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) Section XI, Division 2 “Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants” for developing and implementing pre-service inspection (PSI) and in-service inspection (ISI) programs. The NRC recently endorsed ASME BPVC Section XI, Division 2 (BPV XI-2) in Regulatory Guide (RG) 1.246. This new ASME code is yet to be used in any applications submitted for NRC review. This report provides an overview of the current state of knowledge and practices within the industry for the use of BPV XI-2 for the development and implementation of a PSI and ISI program for non-light water reactors.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 2203928
• Report Number(s): INL/RPT--23-71547-Rev000
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
ASME Section XI Division 2
Reliability Target Allocation
Reliability and Integrity Management