Document: NUREG-0800
Document ID: 9a64419a-34ff-49d2-87dd-c6f10c12014f
Document Type: srp
Title: or 7.3 of the SAR.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500501.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
systems). The guidance of IEEE Std 603 is also more readily adaptable for use in the review of non-safety I&C systems. Non-safety I&C systems are reviewed to ensure that they conform to the acceptance criteria and guidelines, that the controlled variables can be maintained within prescribed operating ranges, and that effects of operation or failure of these systems are bounded by the accident analyses in Chapter 15 of the SAR. This includes verification that non-safety systems are appropriately isolated from safety systems and that the quality and reliability of these systems is sufficient to minimize challenges to safety systems. Supplemental Guidance for Digital Computer-Based Safety Systems For designs that include digital computer-based I&C systems (including hardware, software and firmware), additional issues should be considered when evaluating compliance with 10 CFR 50. Appropriate references to review criteria and review procedures are also included in Appendices A, B, and C to this section. Reg. Guide 1.152, "Criteria for Digital Computers in Safety Systems of Nuclear Power Plants," which endorses IEEE Std 7-4.3.2, "IEEE Standard for Digital Computers in Safety Systems of Nuclear Power Generating Stations," SECY-91-292, "Digital Computer Systems for Advanced Light Water Reactors," and SECY-93-087 describe the additional issues involved. These issues and review criteria are summarized below. It is important to note that all criteria of 10 CFR 50 apply to safety-related digital I&C systems. The information here is intended only to clarify the application of certain of these requirements to digital systems, not to replace existing requirements or guidance. Reg. Guide 1.28, "Quality Assurance Program Requirements (Design and Construction)," endorses the 1983 edition of ASME Std NQA-1, "Quality Assurance Requirements for Nuclear Facility Applications." The 1994 edition of NQA-1 also includes the former ASME Std NQA-2a, Part 2.7 of which addresses computer