Document: NRC Regulatory Guide
Document ID: dfb24267-98c5-442f-8325-3b1dee97bc46
Document Type: regulatory_guide
Title: Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Production and Utilization Facilities + HISTORY – HISTORY 08/2022 – DG-1401 , Proposed Revision 4 03/2013 – DG-1269 , Proposed Revision 3 10/2006 – DG-1155 , Proposed Revision 2 Prior to the issuance of DG-1155, RG 1.129 was entitled "Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Nuclear Power Plants" (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2202/ML22026A441.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.129
CFR Part: 
CFR Title: 

Content:
use in complying with the agency’s regulations with regard to the maintenance, testing, and replacement of vented lead-acid storage batteries in production and utilization facilities. This revision of RG 1.129 endorses (with certain clarifying regulatory positions described in Section C of this guide) Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 450-2020, “IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications” (Ref. 1). Applicability This RG applies to applicants and licensees subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 2), and 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 3). With respect to 10 CFR Part 50, this RG applies to applicants for and holders of a license, as defined in 10 CFR 50.2. With respect to 10 CFR Part 52, this RG applies to applicants for and holders of licenses, as defined in 10 CFR 52.1, standard design certifications, and standard design approvals. Applicable Regulations The General Design Criteria (GDC) in Appendix A to 10 CFR Part 50 establish minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in design and location to plants for which construction permits have been issued by the Commission. The GDC are also considered to be generally applicable to other types of nuclear power units and are intended to provide guidance in establishing the principal design criteria for such other units. The following GDCs are related to vented lead-acid storage batteries: DG-1401, Page 2 • GDC 1, “Quality Standards and Records,” requires, in part, that structures, systems, and components (SSCs) important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed.