Document: NRC Regulatory Guide
Document ID: 26c3e31f-c018-4aee-b926-6db849b72a5a
Document Type: regulatory_guide
Title: Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0630/ML063040591.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.209
CFR Part: 
CFR Title: 

Content:
-rm/adams.html, under Accession No. ML063040591. U.S. NUCLEAR REGULATORY COMMISSION October 2006 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 DRAFT REGULATORY GUIDE Contact: P. Kang (301) 415-6800 DRAFT REGULATORY GUIDE DG-1142 (Previously Issued as Draft Regulatory Guide DG-1077, dated September 2001) GUIDELINES FOR ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED COMPUTER-BASED INSTRUMENTATION AND CONTROL SYSTEMS IN NUCLEAR POWER PLANTS A. INTRODUCTION Title 10, Part 50, “Domestic Licensing of Production and Utilization Facilities,” of the Code of Federal Regulations (10 CFR Part 50) delineates the design- and qualification-related regulations that the U.S. Nuclear Regulatory Commission (NRC) has established for commercial nuclear power plants. In particular, General Design Criterion 4 in Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50 requires that structures, systems, and components (SSCs) important to safety shall be designed to accommodate the effects of, and to be compatible with, the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents (i.e., the equipment shall remain functional under postulated accident conditions). The following sections of 10 CFR Part 50 specify general requirements: • 10 CFR 50.55a, “Codes and Standards” • Appendix A, General Design Criteria 1, 2, 4, 13, 21, 22, and 23 • Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” specifically Criterion III, “Design Control,” Criterion XI, “Test Control,” and Criterion XVII, “Quality Assurance Records” DG-1142, Page 2 According to 10 CFR 50.55a(h)(2), protection systems shall meet the requirements set forth in the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 603-1991, “Criteria for Safety Systems for Nuclear Power Generating Stations,” and the correction sheet