Document: NUREG-0800
Document ID: c3322e66-68dd-4764-910a-4a84b5bd6b8f
Document Type: srp
Title: Setpoints
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A207.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
ms. It endorses, with comments, IEEE Std 830 as describing an acceptable approach to the development of software requirements specifications. Appendix 7.1-A-33 Draft Revision 6 – August 2015 SRP BTP 7-14 describes the review of software requirements specifications. (p) RG 1.173, “Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants,” (endorses IEEE Std 1074, “IEEE Standard for Developing Software Life Cycle Processes”). Applicability - All I&C systems and components important to safety. Review Methods - RG 1.173 provides a basis for evaluating conformance to 10 CFR 50.55a(h), GDC 1, and Criteria I, II, III, VI, XV, and XVII of 10 CFR Part 50, Appendix B for computer-based systems. It endorses, with comments, IEEE Std 1074 as providing acceptable approaches to defining software development processes. SRP BTP 7-14 describes the review of software development plans and software project management plans that should outline the applicant’s or licensee’s software life cycle. SRP BTP 7-14 also describes the review of each activity group described in IEEE Std 1074. (q) RG 1.174, “An Approach for Using Probabilistic Risk Assessment Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis.” Applicability - All I&C Systems. Review Methods - RG 1.174 provides a basis for the conformance to GDC 13 as part of the evaluation of I&C surveillance test interval changes for purposes other than the accommodation of a 24 month fuel cycle change. RG 1.174 provides guidance on the use of probabilistic risk assessment (PRA) findings and risk insights in support of licensee requests for changes to a plant’s licensing basis, as in requests for licensing amendments and technical specification changes. SRP BTP 7-12 provides information concerning I&C calibration intervals. (r) RG 1.177, “An Approach for Plant-Specific, Risk-Informed Decision Making: Technical Specifications.” Applicability