Document: NRC Regulatory Guide
Document ID: c361be32-682d-4496-bb9f-6e52a80b0bd9
Document Type: regulatory_guide
Title: Instrument Sensing Lines + HISTORY –HISTORY 01/2019 – DG-1352 , Proposed Revision 2 09/2016 – Periodic Review of Revision 1 – Revise 12/2008 – DG-1178 , Proposed Revision 1 Draft IC 126-5, Proposed Revision 0, published 03/1982 (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1815/ML18158A303.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.151
CFR Part: 
CFR Title: 

Content:
tions to be performed. o GDC 22, “Protection System Independence,” requires, in part, the protection system to be designed to assure that the effects of natural phenomena, and of normal operating, maintenance, testing, and postulated accident conditions on redundant channels do not result in loss of the protection function. o GDC 24, “Separation of Protection and Control Systems,” requires, in part, the protection system to be separated from control systems to the extent that failure of any single control system component or channel, or failure or removal from service of any single protection system component or channel which is common to the control and protection systems leaves intact a system satisfying all reliability, redundancy, and independence requirements of the protection system. o GDC 55, “Reactor Coolant Pressure Boundary Penetrating Containment,” requires, in part, each line that is part of the reactor coolant pressure boundary and that penetrates the primary reactor containment to be provided with containment isolation valves, unless it can be demonstrated that the containment isolation provisions for a specific class of lines, such as instrument lines, are acceptable on some other defined basis. DG-1352, Page 3 • 10 CFR 50.55a(h) states that protection systems of nuclear power reactors of all types must meet the requirements specified in 10 CFR 50.55a(h), and each combined license for a utilization facility is subject to the conditions in 10 CFR 50.55a(h). o 10 CFR 50.55a(h)(2) addresses protection systems, and requires that, for nuclear power plants with construction permits issued after January 1, 1971, but before May 13, 1999, protection systems must meet the requirements in IEEE Std 279–1968, "Proposed IEEE Criteria for Nuclear Power Plant Protection Systems" (Ref. 4) or the requirements in IEEE Std 279–1971, "Criteria for Protection Systems for Nuclear Power Generating Stations" (Ref. 5) or the requirements in IEEE Std