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:
nal rule, the Commission (in CLI-80-21, “Petition for Emergency and Remedial Action,” dated May 23, 1980 (Ref. 10)) directed the staff to use NUREG-0588, “Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment,” Revision 1, issued July 1981 (Ref. 11), and the Division of Operating Reactors (DOR) Guidelines, “Guidelines for Evaluating Qualification of Class 1E Electrical Equipment in Operating Reactors,” dated November 13, 1979 (Ref. 12), as requirements that licensees and applicants must meet in order to satisfy the equipment qualification requirements of 10 CFR Part 50. At that time, NUREG-0588 consisted of what is now Part I of NUREG-0588 (i.e., only the “for comment version” of NUREG-0588). Upon its issuance, 10 CFR 50.49, which is based on Part I of NUREG-0588 (hereinafter “NUREG-0588”) and the DOR Guidelines, did not require requalification of electric equipment by applicants for and holders of operating licenses for nuclear power plants previously required by the NRC to qualify equipment in accordance with the DOR Guidelines or NUREG-0588 (Category I or II). According to NUREG-0588, all nuclear reactors with operating licenses as of May 23, 1980, would be evaluated by the staff against the DOR Guidelines. As the Commission stated in the 10 CFR 50.49 final rule preamble, Category I requirements of NUREG-0588, which supplement the recommendations of and apply to equipment qualified in accordance with IEEE Std. 323/323a-1974, “IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations” (Ref. 13), apply to nuclear power plants for which the construction permit safety evaluation report was issued after July 1, 1974. Category II requirements, which supplement the recommendations 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”