Document: NUREG-0800
Document ID: f9d2d9cb-1d13-407e-ad7a-523fff64de06
Document Type: srp
Title: DC POWER SYSTEMS (ONSITE)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100740391.pdf
Revision Date: 2023-06
Chapter: 8
Section ID: 8.3.2
CFR Part: 
CFR Title: 

Content:
ssociated with the onsite dc power system. 4. RG 1.81, as it relates to the sharing of SSCs of the dc power system. Regulatory Position C.1 states that multi-unit sites should not share dc systems. 5. RG 1.128, as it relates to the installation of vented lead-acid storage batteries in the onsite dc power system. 6. RG 1.129, as it relates to maintenance, testing, and replacement of vented lead-acid storage batteries in the onsite dc power system. 7. RG 1.118, as it relates to the capability to periodically test the onsite dc power system. 8. RG 1.153, as it relates to the design, reliability, qualification, and testability of the power, instrumentation, and control portions of safety systems of nuclear plants, including the application of the single failure criterion in the onsite dc power system. As endorsed by RG 1.153, IEEE Std. 603 provides a method acceptable to the staff to evaluate all aspects of the electrical portions of the safety-related systems, including basic criteria for addressing single failures. However, as stated in 10 CFR 55a(h), all plants are not required to comply with IEEE Std. 603. Only applications filed on or after May 13, 1999, for preliminary and final design approvals (10 CFR Part 52, Appendix O), DC, and construction permits; operating licenses and COLs that do not reference a final design approval or DC must meet the requirements for safety systems in IEEE Std. 603-1991 and the correction sheet dated January 30, 1995. Operating nuclear power plants are encouraged, but not required to, comply with IEEE Std. 603 for future system-level modifications. 9. RG 1.53, as it relates to the application of the single-failure criterion. 10. RG 1.63, as it relates to the capability of electric penetration assemblies in containment structures to withstand a loss of coolant accident without loss of mechanical integrity and the external circuit protection for such penetrations. 8.3.2-9 Revision 4 - May 2010 11. RG 1.155, as it relates to the