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:
ystem safety functions. 6. Bypass and inoperable status indicators should be designed and installed in a manner that precludes the possibility of adverse effects on plant safety systems. The indicator system should not be used to perform functions that are essential to safety, unless it is designed in conformance with criteria established for safety systems. IMPLEMENTATION The purpose of this section is to provide information to applicants and licensees regarding the NRC’s plans for using this draft regulatory guide. The NRC does not intend or approve any imposition or backfit in connection with its issuance. The NRC has issued this draft guide to encourage public participation in its development. The NRC will consider all public comments received in development of the final guidance document. In some cases, applicants or licensees may propose an alternative or use a previously established acceptable alternative method for complying with specified portions of the NRC’s regulations. Otherwise, the methods described in this guide will be used in evaluating compliance with the applicable regulations for license applications, license amendment applications, and amendment requests. DG-1205, Page 7 REGULATORY ANALYSIS 1. Statement of the Problem The current version of Regulatory Guide 1.47 (Revision 0), dated May 1973, is based solely on IEEE Std 279-1971. Section 50.55a, “Codes and Standards,” of 10 CFR Part 50 requires that applications filed on or after May 13, 1999, for preliminary and final design approvals (Appendix O, “Standardization of Design: Staff Review of Standard Designs,” to 10 CFR Part 52 (Ref. 17), "Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants”), design certification, and construction permits, operating licenses, and combined licenses must meet the requirements for safety systems in IEEE Std 603-1991 and the correction sheet dated January 30, 1995. In addition, nuclear power plants are