Document: NUREG-0800
Document ID: f4b8f0c1-9a14-46be-88c9-a6cb74d64dff
Document Type: srp
Title: Rev. 4 — June 1997
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500499.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
Rev. 4 — June 1997 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission’s policy to inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission’s regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect new information and experience. Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, D.C. 20555. NUREG-0800 (Formerly NUREG-75/087) U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION NEW Appendix 7.1-C Guidance for Evaluation of Conformance to IEEE Std 603 10 CFR 50.55a(h) requires protection systems to meet the requirements of ANSI/IEEE Std 279, "Criteria for Protection Systems for Nuclear Power Generating Stations." Although required by NRC regulations only for protection systems, the criteria of ANSI/IEEE Std 279 address considerations such as design bases, redundancy, independence, single failures, qualification, bypasses, status indication, and test may be used as review guidance, where appropriate, for any instrumentation and control (I&C) system, as elaborated in Sections 7.2 through 7.9. IEEE Std 603, "Criteria for Safety Systems for Nuclear Power Generating Stations," has since superseded ANSI/IEEE Std 279. The guidance in IEEE Std