Document: NUREG-0800
Document ID: a8dee0cd-6529-4ac9-b659-26bda40aba48
Document Type: srp
Title: INFORMATION SYSTEMS IMPORTANT TO SAFETY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B138.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.5
CFR Part: 
CFR Title: 

Content:
ision 4. C. Emergency operating procedures (EOP) action points - A basis should be provided for EOP action points that accounts for measurement uncertainties. RG 1.105, “Setpoints for Safety-Related Instrumentation,” provides acceptable guidance for establishing these uncertainties. D. Monitoring for severe accidents - The accident monitoring instrumentation should be demonstrated to perform their intended function for severe accident protection. They need not be subject to additional 10 CFR 50.49, “Environmental Qualification of Electric Equipment Important to Safety For Nuclear Power Plants,” environmental qualification requirements. However, they should be designed so there is reasonable assurance that they will operate in the severe accident environment for which they are intended and over the time span for which they are needed. E. Performance assessment - For systems developed in accordance with the guidance of RG 1.97, Revision 4, the review should confirm that the performance 7.5-9 Draft Revision 6 – August 2015 assessment fulfils the goals outlined in Clause 5.6, “Performance Assessment Documentation,” of IEEE Std 497. Recommended review emphasis for BISI F. Scope of BISI indications - As a minimum, BISI should be provided for the following systems: - Reactor trip system (RTS) and engineered safety features actuation system (ESFAS) - See SRP Appendix 7.1-B, Subsection 4.13, “Indication of Bypasses,” and SRP Appendix 7.1-C, Subsection 5.8.3, “Indication of Bypasses.” - Interlocks for isolation of low-pressure systems from the reactor coolant system - See SRP BTP 7-1. - ECCS accumulator isolation valves - See SRP BTP 7-2. - Controls for changeover of residual heat removal from injection to recirculation mode - See SRP BTP 7-6. G. Conformance with RG 1.47, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems.” H. Independence - See SRP Appendix 7.1-B, Subsection 4.7, “Control and Protection System