Document: NRC Regulatory Guide
Document ID: 3b4c5897-7060-42e3-83a9-cf0790b7dc60
Document Type: regulatory_guide
Title: Acceptability of ASME Code, Section XI, Division 2, Requirements for RIM Programs for NPPs, for Non-LWRs
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2112/ML21120A185.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.246
CFR Part: 
CFR Title: 

Content:
s of boiling and pressurized water-cooled nuclear power reactors meet ASME Code Section III. Section III provides standards for the design and construction of nuclear facility components and supports. Non-LWRs are not required to meet ASME Code Section III, however, the NRC staff anticipates that most applications for construction permits or combined licenses for non-LWRs will reference a standard for design and construction—a “construction code”—such as Section III, Division 5, which the NRC staff is currently considering for endorsement for use by non-LWRs. DG-1383, Page 11 scanners. It is the NRC staff’s understanding that this is intended for volumetric examinations and is not applicable to other preservice examinations, such as visual and surface examinations. Basis for Regulatory Guidance Position 10 Areas within the 2019 Edition of ASME Code, Section XI, Division 2, that are “in the course of preparation” or otherwise under development are not being endorsed in this RG. These areas are: • examination requirements/figure number and acceptance standards for item 2.90, tubes and tubesheet, and item 2.100, tubes, in Table V-1.1-2, “Examination Category B, Pressure -Retaining Welds in Vessels Other Than Reactor Vessels,” in Mandatory Appendix V, “Catalog of NDE Requirements and Areas of Interest,” and • the following Articles in Mandatory Appendix VII, “Supplements for Types of Nuclear Plants”: o Article VII-2, “Supplement for Liquid Metal Reactor-Type Plants;” o Article VII-4, “Supplement for Molten Salt Reactor-Type Plants;” o Article VII-5, “Supplement for Generation 2 LWR Reactor-Type Plants;” and o Article VII-6, “Supplement for Fusion Machine-Type Plants.” Where ASME Code, Section XI, Division 2 states that provisions are “in the course of preparation” or otherwise under development, applicants may need to develop that information. Such information should be submitted to the NRC for review and approval in the