Document: NUREG-0800
Document ID: a78c6fc8-c253-4d08-bf41-f8120025f067
Document Type: srp
Title: CONTAINMENT HEAT REMOVAL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0701/ML070160661.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.2
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of containment integrity Secondary - None I. AREAS OF REVIEW The review includes the information in the application concerning containment heat removal under postaccident conditions to ensure conformance with the requirements of General Design Criteria (GDC) 38, 39, and 40 of Appendix A to 10 CFR Part 50 and 10 CFR 50.46(b)(5). The types of systems provided to remove heat from the containment include fan cooler systems, spray systems, and residual heat removal (RHR) systems. These systems remove heat from the containment atmosphere and the containment sump water for pressurized-water reactors (PWRs) or the water in the containment wetwell for boiling-water reactors (BWRs). The specific areas of review are as follows: 1. Analyses of the consequences of single component malfunctions. 2. Analyses of the available net positive suction head (NPSH) to the emergency core cooling system (ECCS) and containment heat removal system pumps. 3. Analyses of the heat removal capability of the spray water system. 4. Analyses of the heat removal capability of RHR and fan cooler heat exchangers. 6.2.2-2 Revision 5 - March 2007 5. The potential for surface fouling and flow blockage of fan cooler, recirculation, and RHR heat exchangers and the effect on heat exchanger performance. 6. The design provisions and proposed program for periodic inservice inspection and operability testing of each system or component. 7. The design of sumps and water sources for emergency core cooling and containment spray systems (CSSs). 8. The effects of accident-generated debris, including an assessment for potential loss of long-term cooling capability resulting from loss-of-coolant accident (LOCA)-generated and latent debris. Potential effects include debris screen blockage, failure of pump seals and other downstream components, and debris fouling of nuclear fuel. As of the publication date of this SRP section, the staff is working