Document: NUREG-0800
Document ID: a8853b5a-7119-4e4d-8880-496c64ff5b6c
Document Type: srp
Title: INSTRUMENTATION AND CONTROLS - INTRODUCTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A050.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
gh IEEE Std 603-1991 and IEEE Std 279-1971 are not requirements for nonsafety I&C systems, these standards describe concepts that are useful in any situation in which functional reliability is a goal. 7.1-7 Revision 6 - August 2016 Consequently, although these standards are not SRP acceptance criteria for nonsafety I&C systems, they are a source of design concepts that may be useful for the reviewer to consider. The scope of IEEE Std 603-1991 is broader than that of IEEE Std 279-1971, and the guidance of IEEE Std 603-1991 is consequently readily adaptable for use in the review of nonsafety I&C systems. 3. Location of Detailed Acceptance Criteria and Review Methods • SRP Appendix 7.1-A, “Acceptance Criteria and Guidelines for Instrumentation and Controls Systems Important to Safety,” provides guidance on the applicability and review methods to be used in evaluating conformance to the regulatory requirements and SRP acceptance criteria for I&C systems important to safety. In three cases, the discussion of review methods is extensive and is located in separate appendices that are referenced by SRP Appendix 7.1-A. These appendices are: • SRP Appendix 7.1-B, “Guidance for Evaluation of Conformance to IEEE Std 279,” provides guidance for evaluating conformance to the requirements of IEEE Std 279-1971. • SRP Appendix 7.1-C, “Guidance for Evaluation of Conformance to IEEE Std 603,” provides guidance for evaluating conformance to IEEE Std 603-1991. • SRP Appendix 7.1-D, “Guidance for Evaluation of the Application of IEEE Std 7-4.3.2,” provides guidance for evaluating conformance to the acceptance criteria contained in RG 1.152, “Criteria for Use of Computers in Safety Systems of Nuclear Power Plants,” which endorses IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be