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
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rely on software instructions or programmable logic to accomplish a function. Examples include a computer, a programmable hardware device, or a device with firmware. 1 See the NRC Design Review Guide, “Instrumentation and Controls for Non-Light-Water Reactor (NON-LWR) Reviews,” dated October 8, 2020 (Ref. 12), for more information. DG-1374, Page 5 The I&C systems that use PDDs adopt advanced technology in both digital devices and the tools for design and development of these devices. These systems are expected to be significantly and functionally different from nondigital systems and may include the use of data communications, self- diagnostics, and integrated functions in a single system or module. Increasing use of PDDs provides potential enhancements to system reliability and performance but may present different hazards than those of safety-related systems that use analog technology. Therefore, the design and development of PDDs in safety-related systems should consider these different hazards. IEEE Std 7-4.3.2-2016 provides criteria for reasonable assurance that the hazards associated with PDDs in safety-related systems are adequately identified and controlled. This standard also provides criteria for the technical and quality characteristics that apply to these PDDs. Revision 2016 of IEEE Std 7-4.3.2 includes the following eight informative annexes: 1. Annex A, “Mapping of IEEE Std 603-2009 to IEEE Std 7-4.3.2,” maps IEEE Std 7-4.3.2-2016 to the criteria within IEEE Std 603-2009. This annex also identifies which clauses within IEEE Std 7-4.3.2-2016 contain additional requirements beyond those in IEEE Std 603-2009. This annex does not contain any guidance or requirements. 2. Annex B, “Diversity Requirements Determination,” has not received NRC endorsement. BTP 7-19 provides staff guidance for the evaluation of defense in depth and diversity to address CCF due to latent design defects in digital safety systems. 3. Annex C, “Dedication of Existing