Document: NRC Regulatory Guide
Document ID: 65325e1a-3033-4f91-a5fa-fcd1286b72ec
Document Type: regulatory_guide
Title: Dedication of Commercial-Grade Digital I&C Items for Use in Nuclear power Plants
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2200/ML22003A180.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.250
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CFR Title: 

Content:
ts for the dedication of commercial-grade digital instrumentation and control (I&C) items for use in nuclear power plant safety applications. It endorses, with clarifications, Nuclear Energy Institute (NEI) 17-06, “Guidance on Using IEC 61508 SIL Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications,” Revision 1, issued December 2021 (Ref. 1), to supplement existing guidance. Applicability This RG applies to holders of, or applicants for, a power reactor operating license or construction permit under Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 2), as well as holders of, or applicants for, a power reactor combined license under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 3). Under these 10 CFR Part 50 or 10 CFR Part 52 power reactor licenses or applications, this RG applies to dedication of commercial-grade digital I&C items pursuant to 10 CFR Part 21, “Reporting of Defects and Noncompliance” (Ref. 4). Applicable Regulations • 10 CFR Part 21 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. The definition for “dedication” requires that the dedication process be conducted in accordance DG-1402, Page 2 with the applicable provisions of Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50. • 10 CFR 50.34(a)(7) and 10 CFR 50.34(b)(6)(ii) refer to 10 CFR Part 50, Appendix B, for describing, establishing and implementing a quality assurance (QA) program for the design and construction of nuclear power plants and fuel reprocessing plants licensed or approved under 10 CFR Part 50 or 10