Document: NRC Regulatory Guide
Document ID: 0df18aa6-42a8-4990-aa7e-3df6d0907f3f
Document Type: regulatory_guide
Title: Criteria for Safety Systems (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2511/ML25114A021.pdf
Revision Date: 2025-11
Chapter: 
Section ID: RG-1.153
CFR Part: 
CFR Title: 

Content:
U.S. NUCLEAR REGULATORY COMMISSION DRAFT REGULATORY GUIDE DG-1251, Revision 1 Proposed Revision 2 to Regulatory Guide 1.153 Issue Date: December 2025 Technical Lead: Gilberto Blas Rodriguez This RG is being issued in draft form to involve the public in the development of regulatory guidance in this area. It has not received final staff review or approval and does not represent an NRC final staff position. Public comments are being solicited on this DG and its associated regulatory analysis. Comments should be accompanied by appropriate supporting data. Comments may be submitted through the Federal rulemaking website, https://www.regulations.gov, by searching for draft regulatory guide DG-1251. Alternatively, comments may be submitted to Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, ATTN: Rulemakings and Adjudications Staff. Comments must be submitted by the date indicated in the Federal Register notice. Electronic copies of this DG, previous versions of DGs, and other recently issued guides are available through the NRC’s public website under the Regulatory Guides document collection of the NRC Library at https://nrc.gov/reading-rm/doc-collections/reg-guides. The DG is also available through the NRC’s Agencywide Documents Access and Management System (ADAMS) at https://www.nrc.gov/reading- rm/adams.html, under Accession No. ML25114A021. The regulatory analysis is associated with a rulemaking and may be found in ADAMS under Accession No. ML24353A321. GUIDANCE FOR THE POWER, INSTRUMENTATION, AND CONTROL PORTIONS OF SAFETY SYSTEMS FOR NUCLEAR POWER PLANTS A. INTRODUCTION Purpose This regulatory guide (RG) provides guidance to implement the requirements for the power, instrumentation and control (I&C) portions of safety systems for nuclear power plants as specified in Section 50.55a(h), Title 10, Part 50 of the Code of Federal Regulations (10 CFR Section 50.55a(h)) (Ref. 1), which incorporates by reference, among other