Document: NRC Regulatory Guide
Document ID: 50995365-d97f-4101-970a-378af6b5374b
Document Type: regulatory_guide
Title: Qualification of Fiber-Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems for Production and Utilization Facilities (Rev. 0)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2505/ML25052A253.pdf
Revision Date: 2025-08
Chapter: 
Section ID: RG-1.257
CFR Part: 
CFR Title: 

Content:
of and apply to equipment qualified in accordance with IEEE Std. 323-1971, “IEEE Trial-Use Standard: General Guide for Qualifying Class I Electric Equipment for Nuclear Power Generating Stations” (Ref. 14), apply to nuclear power plants for RG 1.257, Rev. 0, Page 5 which the construction permit safety evaluation report was issued before July 1, 1974. For plants whose safety evaluation reports for construction permits were issued since July 1, 1974, the NRC has used RG 1.89, “Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants” (Ref. 15). • RG 1.61, “Damping Values for Seismic Design of Nuclear Power Plants,” (Ref. 16) provides guidance on damping values for use in the seismic response analysis of seismic Category I SSCs. • RG 1.63, “Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants,” (Ref. 17) describes a method acceptable to the NRC staff for complying with the regulatory requirements for the design, construction, testing, qualification, installation, and external circuit protection of electric penetration assemblies in containment structures. • RG 1.73, “Qualification of Safety-Related Actuators in Production and Utilization Facilities” (Ref. 18), describes a method acceptable to the NRC staff for use in complying with the regulatory requirements with respect to the qualification of safety-related actuators. • RG 1.89, “Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants,” describes a method acceptable to the NRC staff to meet regulatory requirements for EQ of certain electric equipment important to safety for nuclear power plants. • RG 1.97, “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants” (Ref. 19), describes a method that is acceptable to the NRC staff for use in complying with the regulatory requirements with respect to satisfying criteria for accident monitoring