Document: NUREG-0800
Document ID: 5b10059e-25f6-4640-86f9-5d167b89cd39
Document Type: srp
Title: B-2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A226.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
Draft Revision 6 – August 2015 1. AREAS OF REVIEW For nuclear power plants with construction permits issued before January 1, 1971, Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(h), “Protection and Safety Systems,” requires that protection systems must be consistent with their licensing basis or may meet the requirements of 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 after January 1, 1971, but before May 13, 1999, 10 CFR 50.55a(h) requires that protection systems meet the requirements of the IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” or IEEE Std 603-1991 and the correction sheet dated January 30, 1995. The scope of IEEE Std 279-1971 includes those systems that actuate a reactor trip, and that in the event of a serious reactor accident, actuate engineered safety features. This appendix discusses the requirements of IEEE Std 279-1971, Clauses 3 and 4, as they are used in the review of the reactor trip systems (RTS) and engineered safety features actuation systems (ESFAS) to determine that these systems meet the U.S. Nuclear Regulatory Commission (NRC) regulations. Although required by NRC regulations only for protection systems, the criteria of IEEE Std 279-1971 address considerations such as design bases, redundancy, independence, single failures, qualification, bypasses, status indication, and testing that may be used as review guidance, where appropriate, for any instrumentation and control (I&C) system, as elaborated in SRP Sections 7.2 through 7.9. Therefore, for I&C systems not a part of the protection system, but having a high degree of importance to safety, the reviewer may use the concepts of IEEE Std 279-1971 for the review of these systems. SRP,