Document: NRC Regulatory Guide
Document ID: 30e6fa68-c7c1-4266-ba45-e06d1bbc07a0
Document Type: regulatory_guide
Title: Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1708/ML17083A134.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.97
CFR Part: 
CFR Title: 

Content:
LWR Edition” (Ref. 7). o NUREG-0800, Chapter 7, “Instrumentation and Controls,” Branch Technical Position 7- 19, “Guidance for Evaluation of Diversity and Defense-in-Depth in Digital Computer- Based Instrumentation and Control Systems,” discusses the NRC’s concerns about common cause failures and provides guidance for evaluating an applicant’s diversity and defense-in-depth assessment appropriate. o NUREG-0800, Chapter 11, “Radioactive Waste Management,” identifies guidance documents the NRC staff uses to determine whether the plant’s design incorporates acceptable engineering practices and guidelines for systems containing radioactive material. o NUREG-0800, Chapter 18, “Human Factors Engineering,” identifies guidance documents the NRC staff uses to determine whether the plant’s design incorporates acceptable human factors engineering practices. • RG 1.53, “Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems” (Ref. 8), endorses IEEE Std. 379, “IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems” (Ref. 9), as an acceptable method to meet the regulations concerning the application of the single-failure criterion to the electrical power, instrumentation, and control portions of nuclear power plant safety systems. • RG 1.152, “Criteria for Use of Computers in Safety Systems of Nuclear Power Plants” (Ref. 10), endorses IEEE Std. 7-4.3.2, “Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations” (Ref. 11), as an acceptable method to meet the regulations. IEEE 7-4.3.2 provides criteria supporting the specification, design, and implementation of computers in safety systems of nuclear power generating stations. It should be used in conjunction with the he most recent version of IEEE Std. 603, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations” (Ref. 12), that is