Document: NUREG-0800
Document ID: 81256f55-72dd-4777-9472-f373c71c4554
Document Type: srp
Title: AC POWER SYSTEMS (ONSITE)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550065.pdf
Revision Date: 2023-06
Chapter: 8
Section ID: 8.3.1
CFR Part: 
CFR Title: 

Content:
er will be provided for all facility operating modes, including transients and design basis accidents so that the safety functions required by these criteria may be performed, even in the event of any single failure. 7. Compliance with GDC 50 requires that the reactor containment structure, including access openings, penetrations, and containment heat removal systems, be designed so that the containment structure and its internal compartments can accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any LOCA. Accordingly, containment electric penetrations should be designed to accommodate, without exceeding their design leakage rate, the calculated pressure and temperature conditions resulting from a LOCA. In addition, the penetration conductors should be able to withstand all ranges of over load and short circuit currents up to the maximum fault current vs time conditions that could occur given single random failures of circuit protective devices. This criterion, as it applies to this SRP section, relates specifically to ensuring the integrity of containment electrical penetrations in the event of design basis LOCA conditions. SRP Section 8.3.1 cites Regulatory Guide 1.63 and the industry standards, IEEE Std 317 and IEEE Std 741, for electric penetration design and protection, respectively, as guidance acceptable to the staff for meeting the requirements of this criterion. Meeting the requirements of GDC 50 provides assurance that a LOCA will not cause a containment structure, including its electrical penetrations, to exceed the design leakage rate, thus limiting the consequences of a LOCA. 8.3.1-18 Revision 3 - March 2007 8. Compliance with 10 CFR 50.63 requires that each light-water-cooled nuclear power plant be able to withstand for a specified duration and recover from a station blackout. As required by 10 CFR 50.63, electrical systems that are necessary support