Document: NUREG-0800
Document ID: 5691df7d-390d-4ce8-953e-bbdb0a812705
Document Type: srp
Title: REACTOR TRIP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B086.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
t the design meets the specific requirements of IEEE Std 279-1971 or IEEE Std 603-1991. The RTS review should address all topics identified as applicable in SRP Table 7-1. SRP Appendix 7.1-A describes review methods for each topic. Major design considerations that should be emphasized in the RTS review are identified below. A. Design basis - See SRP Appendix 7.1-B, Subsection 3 or SRP Appendix 7.1-C, Subsection 4. B. Single-failure criterion - See SRP Appendix 7.1-B, Subsection 4.2 or SRP Appendix 7.1-C, Subsection 5.1. C. Quality of components and modules - See SRP Appendix 7.1-B, Subsection 4.3 or SRP Appendix 7.1-C, Subsection 5.3. D. Independence - See SRP Appendix 7.1-B Subsections 4.6 and 4.7 or SRP Appendix 7.1-C, Subsections 5.6 and 6.3. E. Diversity and defense-in-depth - RTSs should incorporate multiple means for responding to each event discussed in the SAR Chapter 15, “Transient and Accident Analyses.” At least one pair of these means for each event should have the property of signal diversity, i.e., the use of different sensed parameters to initiate protective action, in which any of the parameters may independently 7.2-6 Draft Revision 6 – August 2015 indicate an abnormal condition, even if the other parameters are sensed incorrectly (see NUREG/CR-6303, “Method for Performing Diversity and Defense-in-Depth Analyses of Reactor Protection Systems”). The diverse means may actuate the same protective function or different protective functions, and may be automatically or manually activated, consistent with the response time requirements of the function. For digital computer-based RTSs, the applicant or licensee should have performed a defense-in-depth and diversity analysis. Additionally, for advanced reactor design under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” the design should provide for manual, system-level actuation of critical safety functions. SRP BTP 7-19 provides guidance for the review of