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:
�� RG 1.152, “Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants” 5.6.3.2, “Equipment in proximity” RG 1.75, “Criteria for Independence of Electrical Safety Systems” DG-1251, Page 10 Table 1. IEEE Std 603-2018 Clauses - Relevant Additional Guidance (continued) Clause Relevant Additional Guidance 5.7, “Capability for testing and calibration” RG 1.118, “Periodic Testing of Electric Power and Protection Systems” RG 1.152, “Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants” 5.8.3, “Indication of bypasses” RG 1.47, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems” 5.8.4, “Location” RG 1.97, “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants” 5.9, “Control of access” RG 1.152, “Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants” 5.13, “Multi-unit stations” RG 1.32, “Criteria for Power Systems for Nuclear Power Plants” 5.16, “Common-cause failure” RG 1.152, “Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants” Note: The NRC staff uses the guidance in the BTP 7-19 and in the DRG to evaluate the applicants’ D3 assessment using either best-estimate methods or a risk-informed approach or both, as a means to address CCFs due to latent design defects in digital safety-related systems. 6.2, “Manual control” RG 1.62, “Manual Initiation of Protective Actions” 6.8, “Setpoints” RG 1.105, “Setpoints for Safety-Related Instrumentation” 8.1, “Electrical power sources” RG 1.32, “Criteria for Power Systems for Nuclear Power Plants” 8.3, “Maintenance bypass” RG 1.32, “Criteria for Power Systems for Nuclear Power Plants” DG-1251, Page 11 D. IMPLEMENTATION Licensees generally are not required to comply with the guidance in this regulatory guide. If the NRC proposes to use this