Document: NRC Regulatory Guide
Document ID: a81802d8-8b24-447a-bb5a-fe24b27963a8
Document Type: regulatory_guide
Title: Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0702/ML070250571.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.37
CFR Part: 
CFR Title: 

Content:
CUSSION In March 1973, the Atomic Energy Commission (AEC) issued Regulatory Guide (RG) 1.37, which generally endorsed the provisions and recommendations in American National Standards Institute (ANSI) N45.2.1-1973, “Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants.”1 This ANSI standard contained QA criteria for onsite cleaning of materials and components, cleanness control, and preoperational cleaning and layup of nuclear plant fluid systems. The AEC found that ANSI N45.2.1-1973 provided an adequate basis for complying with the pertinent QA requirements of Appendix B to 10 CFR Part 50, subject to six additional regulatory positions. In 1975, the American Society of Mechanical Engineers (ASME), Committee on Nuclear Quality Assurance (NQA), accepted the overall responsibility to develop and maintain nuclear power QA standards. Four years later, ASME issued NQA-1, “Quality Assurance Program Requirements for Nuclear Power Plants.”2 That standard was based on ANSI N45.2-1977, “Quality Assurance Program Requirements for Nuclear Facilities”; ANSI N46.2, Revision 1, “Quality Assurance Program Requirements for Post-Reactor Nuclear Fuel Cycle Facilities”; and seven other standards in ANSI N45.2. Then, in 1983, ASME issued NQA-2, “Quality Assurance Requirements for Nuclear Power Plants,” based on seven standards in ANSI N45, including ANSI N45.2.1-1980, “Cleaning of Fluid Systems and Associated Components for Nuclear Power Plants.” Six years later, ASME issued NQA-3, “Quality Assurance Program Requirements for the Collection of Scientific and Technical Information on Site Characterization of High-Level Nuclear Waste,” to expand the QA standards to address site characterization of high-level nuclear waste repositories. Then, in the 1990s, ASME restructured the NQA standards into a single, multipart document. Initially issued as NQA-1-1994, that standard included criteria and nonmandatory guidance