Document: NRC Regulatory Guide
Document ID: 7e956f4a-b0c9-415b-afb9-a187252498a6
Document Type: regulatory_guide
Title: Quality Assurance Program Requirements (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1227/ML12276A071.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.33
CFR Part: 
CFR Title: 

Content:
with them is not required. This regulatory guide contains information collection requirements covered by 10 CFR Part 50 and 10 CFR Part 52 that the Office of Management and Budget (OMB) approved under OMB control number 3150-0011 and 3150-0151, respectively. The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number. This regulatory guide is a rule as designated in the Congressional Review Act (5 U.S.C. 801–808). However, OMB has not found it to be a major rule as designated in the Congressional Review Act. B. DISCUSSION Reason for Change This revision (Revision 3) of RG 1.33 endorses ANSI/ANS 3.2-2012, “Managerial, Administrative, and Quality Assurance Controls for Operational Phase of Nuclear Power Plants,” (Ref. 4) which is an update to the standard that was endorsed in Revision 2, ANS 3.2/ANSI N18.7-1976, “Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants,” (Ref. 5). The updated standard incorporates operational experience since the original standard was developed, and is better focused on QA of plant operations because information on QA of design and construction was moved to another standard. Background Revision 2 of RG 1.33 (Ref. 6) endorsed ANS 3.2/ANSI 18.7-1976, but required numerous clarifications or modifications of the standard in the RG’s Regulatory Position section. Since then, licensees obtained NRC approval to use various alternate positions to Revision 2 of RG 1.33. In addition, the American Society of Mechanical Engineers (ASME) issued NQA-1, “Quality Assurance Program Requirements for Nuclear Power Plants,” (Ref. 7), which was focused on design and construction issues. The NRC has endorsed NQA-1 in 10 CFR 50.55a, “Codes and Standards”. The NRC revised a related RG (RG 1.28) to endorse NQA-1-2008 and the NQA-1a-2009 Addenda,