Document: NUREG-0800
Document ID: 6209b3e7-917d-48d2-a299-4d1230aa5b51
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550070.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
tions. • Clause 5.4.3, "Design V&V Activity," (2) "Software Design Evaluation" - design elements shall be evaluated to ensure that performance requirements are correctly and completely included. • Clause 5.4.3, "Design V&V Activity," (5) "Component V&V Test Plan Generation and Validation" - testing shall be planned so as to validate timing criteria, performance at boundaries and interfaces, and performance under stress conditions. • Clause 5.4.4, "Implementation V&V Activity," (2) "Source Code and Source Code Evaluation Documentation" - source code elements shall be evaluated to ensure that performance requirements are correctly and completely included. • Clause 5.4.4, "Implementation V&V Activity," (7) "Component V&V Test Execution and Validation" - components shall be evaluated to assure that the implementation, including performance, satisfy the design. • Clause 5.4.5, "Test V&V Activity" - integration, system, and acceptance testing shall be carried out, including performance aspects. • Various clauses require that requirements, including performance requirements, be traced from requirements through design, implementation, and testing. BTP 7-21-5 Revision 5 - March 2007 • Annex G (informative) as modified by Regulatory Position 7 of Regulatory Guide 1.168, "Optional V&V Task Descriptions" - various tasks are described, including: – Performance monitoring - performance information is continually collected and analyzed under operational conditions to assure that system and software performance requirements are satisfied. – Sizing and timing analysis - data about the software functions and resource utilization is collected and analyzed to determine if system and software requirements for speed and capacity are satisfied. Regulatory Guide 1.105, Revision 3, "Setpoints for Safety-Related Instrumentation," endorses ISA-S67.04-1994, Part 1, "Setpoints for Nuclear Safety-Related Instrumentation," as an acceptable method for initially setting and