Document: NUREG-0800
Document ID: 1add33e8-ea1c-46d8-9e11-29944f57ca8a
Document Type: srp
Title: Revision 6 – August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A184.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
fety systems. This BTP deals with the criteria and methods used to confirm that the design of isolation devices ensures that credible failures in the connected nonsafety or redundant channels will not prevent the safety systems from meeting their required functions. Guidance for other aspects of isolation-device qualification (e.g., electromagnetic compatibility, environmental and seismic qualification) may be found in SRP, Appendix 7.1-B, “Guidance for Evaluation of Conformance to IEEE Std 279,” Subsections 4.5, 4.6, and 4.7, SRP Appendix 7.1-C, “Guidance for Evaluation of Conformance to IEEE Std 603,” Subsection 5.6, and SRP Appendix 7.1-D, “Guidance for Evaluation of the Application of IEEE Std 7-4.3.2,” Subsection 5.6. The devices that provide isolation between safety and nonsafety portions of power distribution systems are addressed in SRP Chapter 8, “Electrical Power.” Communication independence between safety systems and nonsafety systems is not discussed in this BTP. Refer to SRP Appendix 7.1-C, Subsection 5.6 and SRP Appendix 7.1-D, Subsection 5.6. 1. Regulatory Basis Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(h), “Protection and Safety Systems,” requires compliance with the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the applicant or licensee may elect to comply instead with the plant-specific licensing basis. For nuclear power plants with construction permits issued between January 1, 1971, and May 13, 1999, the applicant or licensee may elect to comply instead with the requirements stated in IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” IEEE Std 603-1991, Clause 5.6, “Independence,” states in part, “No credible