Document: NRC Regulatory Guide
Document ID: 5b36f49a-1e5b-4d3c-b352-91bfde8ef8cc
Document Type: regulatory_guide
Title: Acceptance of Commercial-Grade Design and Analysis Computer Programs Used in Safety-Related Applications for Nuclear Power Plants + HISTORY - HISTORY 04/2015 – DG-1305 , Proposed Revision 0
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1411/ML14119A286.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.231
CFR Part: 
CFR Title: 

Content:
nsiders acceptable in meeting regulatory requirements for acceptance and dedication of commercial-grade design and analysis computer programs for nuclear power plants. Applicable Rules and Regulations • Title 10 of the Code of Federal Regulations, Part 21, “Reporting of Defects and Noncompliance,” (10 CFR Part 21) (Ref. 1) establishes the framework for an acceptance process under the definition for “dedication” and this process is undertaken to provide reasonable assurance that a commercial-grade item to be used as a basic component will perform its intended safety function. Specifically, the definition for “dedication” requires that the dedication process be conducted in accordance with the applicable provisions of Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 2). • 10 CFR Part 50, Appendix B, Criterion III, “Design Control,” includes the provisions for quality assurance (QA) and quality control which are applicable to the acceptance and dedication process for commercial-grade design and analysis computer programs. Criterion III fulfills the Appendix B to 10 CFR Part 50 requirement established by the definition of “dedication” in 10 CFR Part 21 for commercial-grade design and analysis computer programs. Criterion III design control measures require, in part, for the selection and the review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems, DG-1305, Page 2 and components (SSCs), and are applicable to a commercial-grade design and analysis computer program associated with basic components. • 10 CFR 50.34(a)(7) and 10 CFR 50.34(b)(6)(ii) refer to Appendix B to 10 CFR Part 50 for establishing and implementing a QA program for the design and construction of nuclear power plants and fuel