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:
e 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 Plants," Reg. Guide 1.171, "Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants," Reg. Guide 1.172, "Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants," and Reg. Guide 1.173, "Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants") or an acceptable alternative approach. C.3.2. Identification of Review Topics The digital I&C review topics to be addressed depend upon the system under review, as outlined in Table 7.0-A-1. Table 7.0-A-1. Review Topics Depend on the System Under Review Topic Protection System (7.2–7.3) Other Safety Systems (7.4–7.6) Control System (7.7) Diverse I&C System (7.8) Data Communication System (7.9) D-in-D&D Review * * * Same review as supported system(s) Functional Requirements Review Review Limited review Review Same review as supported system(s) Development Process Review Review Limited review Review Same review as supported system(s) Process Implementation Review Review Limited review Review Same review as supported system(s) Design Outputs Review Review Limited review Review Same review as supported system(s) * While D-in-D&D analysis is not required for systems other than RTS and ESFAS, changes to other I&C systems in plants that have existing digital RTS and ESFAS should be reviewed to confirm that the proposed changes do not affect assumptions and commitments made in the existing D-in-D&D analysis. This includes ensuring compliance with the diversity requirements of 10 CFR 50.62, as discussed in Section 7.8. The level of review depends upon the importance to safety of the system under review. Control systems receive a limited review as necessary to confirm that