Document: NRC Regulatory Guide
Document ID: 82021804-a487-471b-a76c-095315525b53
Document Type: regulatory_guide
Title: Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1628/ML16281A531.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.180
CFR Part: 
CFR Title: 

Content:
ce with the NRC’s regulations on design, installation, and testing to address the effects of electromagnetic and radio- frequency interference (EMI/RFI), power surges, and electrostatic discharge on safety-related instrumentation and control (I&C) systems. Applicability This RG applies to licensees and applicants subject to Title 10 of the Code of Federal Regulations, Part 50, “Domestic Licensing of Production and Utilization Facilities” (10 CFR Part 50) (Ref. 1), and 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants” (Ref. 2). Applicable Regulations • 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” requires that structures, systems, and components that are important to safety in a nuclear power plant must be designed to accommodate the effects of environmental conditions (i.e., remain functional under postulated design-basis events (DBEs)). o 10 CFR 50.55a(h) states that protection systems must meet the requirements of the Institute of Electrical and Electronics Engineers (IEEE) standard (Std.) 603-1991, “Criteria for Safety Systems for Nuclear Power Generating Stations” (Ref. 3), or IEEE Std. 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations” (Ref. 4), contingent on the date of construction permit issuance. The design basis criteria identified in those standards, or for plants with construction permits issued before January 1, 1971, the criteria identified in the licensing basis for such facilities, include the range DG-1333, Page 2 of transient and steady state environmental conditions during normal, abnormal, and accident conditions during which the equipment must perform its safety functions. o Criterion III, “Design Control,” Criterion XI, “Test Control,” and Criterion XVII, “Quality Assurance Records,” of Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing