Document: NUREG-0800
Document ID: 896f0b4b-b27c-462b-aed0-872a58b455c8
Document Type: srp
Title: Revision 6 – August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A327.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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Content:
umentation and control (I&C) systems. These guidelines are based on reviews of licensee submittals and the analysis of PLC-related issues documented in NUREG/CR-6090, “The PLC and Its Application in Nuclear Reactor Protection Systems.” 1. Regulatory Basis Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” General Design Criterion (GDC) 1, “Quality Standards and Records,” requires in part that “structures, systems, and components important to safety shall be designed, fabricated, and tested to quality standards commensurate with the importance of the safety functions to be performed.” 10 CFR Part 50, Appendix A, GDC 21, “Protection System Reliability and Testability,” requires in part that “the protection system shall be designed for high functional reliability … commensurate with the safety functions to be performed.” 2. Relevant Guidance RG 1.152, “Criteria for Use of Computers in Safety Systems of Nuclear Power Plants,” provides guidance for complying with the requirements for safety systems that use digital computer systems. The guidance in RG 1.152 refers to the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” The SRP, Appendix 7.1-D, “Guidance for Evaluation of the Application,” provides additional guidance. NUREG/CR-6090 covers the application of PLCs to nuclear reactors. The guidance in this NUREG will aid the reviewer in the evaluation of an I&C system containing one or more PLCs. NUREG/CR-6463, Revision 1, “Review Guidelines on Software Languages for use in Nuclear Power Plant Safety Systems,” describes recommended practices in the use of common PLC programming languages. Electric Power Research Institute (EPRI)