Document: NUREG-0800
Document ID: 9fa7092c-7628-402d-9028-6601d5f5fdfb
Document Type: srp
Title: DC POWER SYSTEMS (ONSITE)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550063.pdf
Revision Date: 2023-06
Chapter: 8
Section ID: 8.3.2
CFR Part: 
CFR Title: 

Content:
ry, battery charger, and inverter rooms. In particular, the organization responsible for the review of plant ventilation 8.3.2-5 Revision 3 - March 2007 systems determines whether the piping, ducting, and valving arrangements of redundant auxiliary supporting systems meet the single-failure criterion. 5. The organization responsible for the review of plant structures examines the physical arrangement of the dc power system and its supporting auxiliary system components and associated structures to confirm that single events and accidents will not disable redundant features, as part of its primary review responsibility for SRP Sections 3.4.1, 3.5.1.1, 3.5.2, and 3.6.1. 6. The organization responsible for the review of engineered safety feature systems identifies those system components that require electric power as a function of time for each mode of reactor operation and accident condition, as part of its primary review responsibility for SRP Sections 6.5.1, 6.7, 9.1.3, 9.1.4, 9.2.1, 9.2.2, 9.2.4, 9.2.5, 9.2.6, 9.3.1, 9.3.3, 9.4.1 through 9.4.5, 9.5.1, 10.4.5, 10.4.7, and 10.4.9. 7. The organization responsible for fire protection examines the fire detection and fire protection systems for the dc power system and its vital supporting systems to ensure that the adverse effects of fire are minimized, as part of its primary review responsibility for SRP Section 9.5.1. This review includes assessing the adequacy of protection provided for redundant safe-shutdown circuits to confirm that a single design-basis fire will not disable both redundant circuits. 8. The organization responsible for the review of reactor coolant and auxiliary process systems identifies those system components that require electric power as a function of time for each mode of reactor operation and accident condition, as part of its primary review responsibility for SRP Sections 5.4.8, 9.2.3, 9.3.2, and 9.3.4. 9. The organization responsible for the review of containment systems and severe