Document: NUREG-0800
Document ID: eb1d19c1-686c-42f5-ba0a-c417c7b12b8e
Document Type: srp
Title: DC POWER SYSTEMS (ONSITE)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070499.pdf
Revision Date: 2023-06
Chapter: 8
Section ID: 8.3.2
CFR Part: 
CFR Title: 

Content:
he calculated pressure and temperature conditions resulting from any LOCA. Containment electric penetrations must therefore be designed to accommodate, without exceeding their design leakage rate, the calculated pressure and temperature conditions resulting from a LOCA. 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 DRAFT Rev. 3 - April 1996 8.3.2-12 conditions. SRP Section 8.3.2 cites Regulatory Guide 1.63 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.80 8. Compliance with 10 CFR 50.63 requires that each light-water-cooled nuclear power plant be able to withstand and recover from a station blackout of specified duration. As required by 10 CFR 50.63, electrical systems must be of sufficient capacity and capability to ensure that the core is cooled and that appropriate containment integrity is maintained in the event of a station blackout. The capacity of any onsite dc sources required for station blackout must therefore be verified to be adequate with respect to the worst-case station blackout load profile and specified duration. Regulatory Guide 1.155 and SRP Section 8.4 (proposed) describe guidance acceptable to the staff for meeting the requirements of 10 CFR 50.63. Meeting the requirements of 10 CFR 50.63 provides assurance that nuclear power plants will be able to withstand or cope with, and recover from a station blackout by providing capability for maintaining core cooling and an appropriate level of containment integrity.81 III. REVIEW PROCEDURES The primary objective in the review of the dc power system is to determine that this system satisfies the acceptance criteria stated in