Document: NUREG-0800
Document ID: 5b10059e-25f6-4640-86f9-5d167b89cd39
Document Type: srp
Title: B-2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A226.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
ore, for I&C systems not a part of the protection system, but having a high degree of importance to safety, the reviewer may use the concepts of IEEE Std 279-1971 for the review of these systems. SRP, Appendix 7.1-C provides guidance for evaluating conformance to IEEE Std 603-1991. SRP Appendix 7.1-D provides guidance for evaluating conformance to the acceptance criteria contained in RG 1.152, “Criteria for Digital Computers in Safety Systems of Nuclear Power Plants,” which endorses IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” 2. SCOPE This appendix discusses the requirements of IEEE Std 279-1971 as they are used in the review of protection systems; however, it is not intended to be a stand-alone document. Each subsection of this appendix relates directly to one or more clauses of the standard. Additional background or detailed information relevant to this review can be found in the references to this appendix. A review of protection systems by the organization responsible for the review of I&Cs that follows the guidance of IEEE Std 279-1971 should be coordinated with other organizations as appropriate to address the following considerations: • Many of the auxiliary supporting features and other auxiliary features are described in Chapters 4, 5, 6, 8, 9, 10, 12, 15, 18 and 19 of the safety analysis report (SAR). The reviewers from the organization responsible for the review of I&C should coordinate with the reviewers of these SAR sections to ensure that auxiliary features are appropriately addressed by the review.