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:
nmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents. o General requirements associated with equipment qualification appear in GDC 1, “Quality Standards and Records”; GDC 2, “Design Bases for Protection Against Natural Phenomena”; and GDC 23, “Protection System Failure Modes,” of Appendix A to 10 CFR Part 50. o Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50 requires, in part, that the pertinent requirements of the appendix apply to all activities affecting the safety-related functions of SSCs that prevent or mitigate the consequences of postulated accidents that could cause undue risk to public health and safety. These activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling, and modifying. • 10 CFR Part 52 requires, in part, that SSCs important to safety in a nuclear power plant be designed to accommodate the effects of environmental conditions. o 10 CFR 52.47(a)(13) requires that an applicant for a certified design must provide the list of electrical equipment important to safety, as mandated by 10 CFR 50.49(d). o 10 CFR 52.79(a)(10) requires that an application for a combined license must provide a description of an EQ program for electrical equipment and its implementation, in accordance with 10 CFR 50.49(a). The applicant must also provide the list of electric equipment that is important to safety, as required by 10 CFR 50.49(d). o 10 CFR 52.97(b) requires that combined licenses must contain inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that the facility has been constructed and will be operated in accordance with the license; the Atomic Energy Act of 1954, as amended (Ref. 8); and NRC rules