Document: NRC Regulatory Guide
Document ID: 7ff7fac8-958f-48d8-82dd-0c18b1b6e487
Document Type: regulatory_guide
Title: Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants + HISTORY – HISTORY 01/2024 – DG-1421 , Proposed Revision 3 10/2006 – DG-1154 , Proposed Revision 2 Prior to the issuance of DG-1154, RG 1.128 was entitled "Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants" (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2327/ML23277A276.pdf
Revision Date: 2024-01
Chapter: 
Section ID: RG-1.128
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CFR Title: 

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in part, that an onsite electric power system and an offsite electric power system be provided to permit functioning of SSCs important to safety. o GDC 18, “Inspection and testing of electric power systems,” requires that electric power systems important to safety be designed to permit appropriate periodic inspection and testing of important areas and features, such as wiring, insulation, connections, and switchboards, to assess the continuity of the systems and the condition of their components. • Nuclear power and fuel reprocessing plants include SSCs that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50 establishes quality assurance requirements for the design, manufacture, construction, and operation of those SSCs. Appendix B, Criterion III, “Design Control,” sets forth the following requirements: o Measures shall be established to assure that applicable regulatory requirements and the design basis, as defined in 10 CFR 50.2 and as specified in the license application, for those SSCs to which Appendix B applies are correctly translated into specifications, drawings, procedures, and instructions. o These measures shall include provisions to ensure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled. o The design control measures shall provide for verifying or checking the adequacy of design, such as by performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program. • 10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. The regulations specify, among other