Document: NUREG-0800
Document ID: 4865fc6d-b85f-4173-9bca-162fa9fe67d2
Document Type: srp
Title: Appendix 7-A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500555.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
r Protection Systems for Nuclear Power Generating Stations." Section 4.2 requires in part that "any single failure within the protection system shall not prevent proper protective action at the system level when required." 10 CFR 50.62, "Requirements for Reduction of Risk from Anticipated Transients without Scram," requires in part various diverse methods of responding to anticipated transients without scram (ATWS). 10 CFR 50 Appendix A, General Design Criterion (GDC) 21, "Protection Systems Reliability and Testability," requires in part that "no single failure results in the loss of the protection system." 10 CFR 50 Appendix A, GDC 22, "Protection System Independence," requires in part that the effects of natural phenomena, postulated accident conditions, normal operating, maintenance, and testing not result in the loss of protective function. "Design techniques, such as functional diversity or diversity in component design and principles of operation, shall be used to the extent practical to prevent loss of the protection function." 10 CFR 50 Appendix A, GDC 24, "Separation of Protection and Control Systems," requires in part that "Interaction of the protection and control systems shall be limited so as to assure that safety is not significantly impaired." Rev. 4 — June 1997 Appendix 7-A BTP HICB-19-2 10 CFR 50 Appendix A, GDC 29, "Protection Against Anticipated Operational Occurrences," requires in part defense against anticipated operational transients "to assure an extremely high probability of accomplishing . . . safety functions." 2. Relevant Guidance Reg. Guide 1.53 "Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems," clarifies the application of the single-failure criterion (GDC 21) and endorses ANSI/IEEE Std 379, "Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems," providing supplements and an interpretation. Reg. Guide 1.153 "Criteria for Power, Instrumentation,