Session: CS-07-01 Recent Developments in ASME Codes and Standards-1

Paper Number: 123483

123483 - Preservice Inspection Rules and Nuclear Safety 

Construction of nuclear sites is an important topic, as governments and utilities seek to decarbonize. The rules governing construction and preservice examination play a vital role in providing stakeholder confidence that safety-related nuclear components will perform their intended function under normal operating and accident conditions. Construction rules provide sound fabrication procedures, while preservice examination provides an important verification step prior to placing the finished component into service. This paper reviews the construction and preservice examination rules for U.S. nuclear plants and discusses their value to nuclear safety.

In the U.S., the regulations addressing construction of nuclear components are found in Title 10 of the Code of Federal Regulations, Part 50.55a (10 CFR 50.55a). The NRC incorporates by reference the ASME BPV Code Section III, “Rules for Construction of Nuclear Facility Components.” As part of the licensing process in the U.S., applicants for construction permits must establish which edition of ASME BPV Code Section III they will comply with in the design specifications. ASME BPV Code Section III is divided in several subsections, mostly corresponding to component classification:

·       Subsection NCA – General Requirements

·       Subsection NB – Class 1 Components

·       Subsection NCD – Class 2 and 3 Components

·       Subsection NE – Class MC Components

·       Subsection NF – Supports

·       Subsection NG – Core Support Structures

This paper will draw upon on the requirements of Subsections NCA and NCB to illustrate the overall process of nuclear construction according to ASME BPV Code Section III. Further, this paper will explore the preservice inspection rules of ASME BPV Code Section XI, including how they interact with the Section III construction rules and NRC regulations.

Presenting Author: Michael Benson US Nuclear Regulatory Commission

Presenting Author Biography: Michael is a Materials Engineer in NRC's Office of Nuclear Reactor Regulation. He has worked at NRC for 15 years. He is an active member on several committees supporting the development of ASME Boiler and Pressure Vessel Code, Section XI. His technical interest are in inservice inspection of safety-related nuclear components, including reactor vessel internals.

Authors:

Michael Benson US Nuclear Regulatory Commission
John Honcharik U.S. Nuclear Regulatory Commission
David Rudland U.S. Nuclear Regulatory Commission