Document: NRC Regulatory Guide
Document ID: 30181e34-3bc1-46b8-8de9-ef073c34bc13
Document Type: regulatory_guide
Title: Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems + HISTORY - HISTORY 10/2008 – DG-1205 , Proposed Revision 1 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0821/ML082140114.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.47
CFR Part: 
CFR Title: 

Content:
pdated version would include a discussion of digital computer-based I&C systems and advanced analog systems. The update would retain references to IEEE Std 279-1971, because this IEEE standard remains applicable to plants with construction permits issued after January 1, 1971, but before May 13, 1999. One benefit of this action is that it would enhance reactor safety by addressing the revised IEEE Std 603-1991 on safety systems endorsed by the NRC. Important digital computer-based I&C system issues such as single-failure criteria and communications would receive consideration. Also, the updated DG-1205, Page 8 guide would address considerations from current regulations in 10 CFR 50.55a(h), and 10 CFR 50.34(f)(2)(v). \ The impact to the NRC would be the costs associated with preparing and issuing the regulatory guide revision. The impact to the public would be the voluntary costs associated with reviewing and providing comments to NRC during the public comment period. The value to NRC staff and its applicants would be the benefits associated with enhanced efficiency and effectiveness in using a common guidance document as the technical basis for license applications and other interactions between the NRC and its regulated entities. 4. Conclusion Based on this regulatory analysis, the NRC staff recommends revision of Regulatory Guide 1.47. The staff concludes that the proposed action will enhance reactor safety by reflecting current regulations and referencing the updated IEEE Std 603-1991on safety systems endorsed by the NRC. The revised guide could also lead to cost savings for the industry, especially with regard to applications for standard plant design certifications and combined licenses. DG-1205, Page 9 REFERENCES 1. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” U.S. Nuclear Regulatory Commission, Washington, DC. 2. IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,”