Document: NUREG-0800
Document ID: a2598df1-7ec6-43a6-9d2a-d8210d1f944f
Document Type: srp
Title: through 7.9. Additional information relevant to the review process can be found in the references in
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500461.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
of Digital System Review Topics This section provides detailed information on each of the digital system review topics identified above; information on the review of the acceptance of commercial-grade digital equipment is also provided. Where an applicant/licensee proposes a digital system that the NRC staff has previously approved, the staff review scope would be significantly reduced and would focus only on plant-specific issues associated with the modification (e.g., environmental qualification and configuration management). The staff would not review again generic aspects of the proposed design, such as the software development process, products, and documents, unless these aspects have changed or been affected by plant-specific differences. Where differences exist between prior approvals, they should be identified and the review should confirm that an adequate basis has been provided to accommodate the differences. The review should include an evaluation of differences to confirm that they are acceptable. C.3.1. Adequacy of Design Criteria and Guidance Section 7.1 discusses the general review of design criteria and guidance. For new digital systems, the applicant/licensee should have committed to the guidance in Reg. Guide 1.152, which endorses IEEE Std 7-4.3.2, "IEEE Standard for Digital Computers in Safety Systems of Nuclear Power Generating Stations," and a set of software engineering standards sufficient to describe the software development process. This should include, as a minimum, a commitment to the software engineering regulatory guides (Reg. Guide 1.168, "Verification, Validation, Reviews and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants," Reg. Guide 1.169, "Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants," Reg. Guide 1.170, "Software Test Rev. 4 — June 1997 SRP 7.0-A-9 Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power