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:
ssing Plants,” to 10 CFR Part 50, Criterion XI, “Test Control,” sets forth the following requirements. o A test program shall be established to ensure that all testing is required to demonstrate that SSCs will perform satisfactorily in service and is identified and performed in accordance with written test procedures that incorporate the requirements and acceptance limits contained in applicable design documents. o The test program shall include, as appropriate, proof tests before installation, preoperational tests, and operational tests during nuclear power plant or fuel reprocessing plant operation of SSCs. o Test procedures shall include provisions for ensuring that all prerequisites for the given test have been met, that adequate test instrumentation is available and used, and that the test is performed under suitable environmental conditions. o Test results shall be documented and evaluated to ensure that test requirements have been satisfied. • Appendix B to 10 CFR Part 50, Criterion XII, “Control of Measuring and Test Equipment,” sets forth the following requirement. o Measures shall be established to ensure that tools, gauges, instruments, and other measuring and testing devices used in activities affecting quality are properly controlled, calibrated, and adjusted at specified periods to maintain accuracy within necessary limits. DG-1401, Page 3 10 CFR Part 52 requires that SSCs important to safety in a nuclear power plant be designed to accommodate the effects of environmental conditions and that design control measures, such as testing, be used to check the adequacy of the design Related Guidance • NUREG/CR-7148, “Confirmatory Battery Testing: The Use of Float Current Monitoring to Determine Battery State-of-Charge,” issued November 2012 (Ref. 4), provides information on confirmatory battery testing; specifically, the use of float current monitoring to determine battery state-of-charge. • The Model Application for Plant-Specific