Document: NRC Regulatory Guide
Document ID: f457ed0f-1a93-47d5-a311-511c0346447e
Document Type: regulatory_guide
Title: Sizing of Large Lead-Acid Storage Batteries (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2311/ML23118A344.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.212
CFR Part: 
CFR Title: 

Content:
g large lead-acid storage batteries for production and utilization facilities. It endorses, with some limitations and a clarification, Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 485-2020, “IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications” (Ref. 1). Applicability This RG applies to licensees and applicants 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). Under 10 CFR Part 50, this RG applies to licensees of or applicants for production and utilization facilities. Under 10 CFR Part 52, this RG applies to applicants and holders of combined licenses, standard design certifications, standard design approvals, and manufacturing licenses. Applicable Regulations • 10 CFR Part 50 provides regulations for licensing production and utilization facilities. o 10 CFR 50.55a, “Codes and standards,” requires, in part, that structures, systems, and components be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. o 10 CFR 50.63(a)(2) requires, in part, that the reactor core and associated coolant, control, and protection systems, including station batteries and any other necessary support systems, provide sufficient capacity and capability to ensure that the core is cooled, and appropriate containment integrity is maintained in the event of a station blackout for the specified duration. RG 1.212, Rev. 2, Page 2 o 10 CFR Part 50, Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion (GDC) 1, “Quality Standards and Records,” requires, in part, that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality