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:
pression pools and the protective strainer assemblies is a critical element in ensuring long-term recirculation cooling capability. Therefore, adequate design consideration of (1) sump and suppression pool hydraulic performance, (2) evaluation of potential debris generation and associated effects including debris screen blockage, (3) RHR and CSS pump performance under postulated post-LOCA conditions, and (4) impacts of debris penetrating strainers on long-term coolability of the core is necessary. Regulatory Guide 1.82, Revision 3, as modified and supplemented for PWRs by the Nuclear Energy Institute (NEI) Guidance Report (GR) (Ref. 3) and the NRC safety evaluation (SE) (Ref. 4), provide guidance for PWR debris evaluations. Regulatory Guide 1.82, Revision 3, as supplemented by the NRC-approved Boiling Water Reactor Owners’ Group (BWROG) Utility Resolution Guidance (URG) (Ref. 5), provide guidance for BWR debris evaluations. 7. In meeting the requirements of GDC 39 and 40 regarding inspection and testing, the design of the containment heat removal systems should provide for periodic inspection and operability testing of the systems and system components such as pumps, valves, duct pressure-relieving devices, and spray nozzles. 8. To satisfy the system design requirements of GDC 38, instrumentation should be provided to monitor the performance of the containment heat removal system and its components under normal and accident conditions. The instrumentation should determine whether a system is performing its intended function or whether a system train or component is malfunctioning and should be isolated. This SRP section references separate guidance for PWR and BWR plants based on the design features of currently operating reactors. Advanced PWR or BWR designs may employ design features that existing NRC guidance associates with the opposite reactor design (e.g., an advanced PWR design that employs an in-containment refueling water storage tank that is similar to