Document: NRC Regulatory Guide
Document ID: fc586342-92f7-4c77-ae76-79e3674cf288
Document Type: regulatory_guide
Title: Criteria for Programmable Digital Devices in Safety-Related Systems of  Nuclear Power Plants + HISTORY –HISTORY 02/2023 – DG-1374, Proposed Revision 4 Prior to issuance of DG-1374, RG 1.152 was entitled, “Criteria for Use of Computers in Safety-Systems of Nuclear Power Plants” 06/2010 – DG-1249, Proposed Revision 3 – Revise 12/2004 – DG-1130, Proposed Revision 2 – Revise 05/1995 – DG-1039, Proposed Revision 1 03/1983 – DG-1130, Proposed Revision 2 – Revise (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2301/ML23012A242.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.152
CFR Part: 
CFR Title: 

Content:
ty Systems of Nuclear Power Generating Stations,” Piscataway, NJ, August 25, 2016.3 2. U.S. Code of Federal Regulations (CFR), “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy.” 3. CFR, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” Part 52, Chapter 1, Title 10, “Energy.” 4. IEEE Std 279-1968, “Proposed IEEE Criteria for Nuclear Power Plant Protection Systems,” Piscataway, NJ. 5. IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” Piscataway, NJ. 6. IEEE Std 603-1991, “IEEE Criteria for Safety Systems for Nuclear Power Generating Stations,” and the correction sheet dated January 30, 1995, Piscataway, NJ 7. U.S. Nuclear Regulatory Commission (NRC), Staff Requirements Memorandum to SECY-93-087, “SECY-93-087—Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Design,” Washington, DC, July 21, 1993. (ADAMS Accession No. ML003708056) 8. NRC, NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” Chapter 7, “Instrumentation and Controls,” Branch Technical Position 7-19, Revision 8, “Guidance for Evaluation of Defense in Depth and Diversity to Address Common-Cause Failure Due to Latent Design Defects in Digital Safety Systems,” Washington, DC, January 2021. 9. NRC, Regulatory Guide 5.71, “Cyber Security Programs for Nuclear Facilities,” Washington, DC. 10. CFR, “Physical Protection of Plants and Materials,” Part 73, Chapter 1, Titles 10, “Energy.” 11. IEEE Std 603-2009, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” Piscataway, NJ. 2 Publicly available NRC published documents are available electronically through the NRC Library on the NRC’s public Web site at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRC’s Agencywide