Document: NUREG-0800
Document ID: f50b3504-7021-4d54-93f4-9672d47bb74c
Document Type: srp
Title: B-3
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A091.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
viewed to confirm that it has the following characteristics: • Completeness - The design basis should address all system functions necessary to fulfill the system’s safety intent. The design basis for protection systems should be shown to address the requirements of 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion (GDC) 20, “Protection System Functions.” Information provided for each design basis item should be sufficient to enable the detailed design of the I&C system to be carried out. All functional requirements for the I&C system and the operational environment for the I&C system should be described. As a minimum, each of the design basis aspects identified in IEEE Std 279-1971 Clauses 3(1) through 3(9) should be addressed. • Consistency - The information provided in the design basis should be analyzed to confirm its consistency with the plant safety analysis, including the design basis event analysis of Chapter 15 of the SAR; the mechanical and electrical system designs; and other plant system designs.