Document: NUREG-0800
Document ID: a28650b3-fa03-428d-a2bd-4a27f583710b
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070484.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
coolant accidents including break size and location (Mark II containments only). 3. Suppression pool dynamic effects during a loss-of-coolant accident or following the actuation of one or more reactor coolant system safety/relief valves, including vent clearing, vent interactions, pool swell, pool stratification, and dynamic symmetrical and asymmetrical loads on suppression pool and other containment structures. 4. The consequences of a loss-of-coolant accident occurring within the containment (wetwell); i.e., outside the drywell (Mark III containments only). 5. The capability of the containment to withstand the effects of steam bypassing the suppression pool. DRAFT Rev. 7 - April 1996 6.2.1.1.C-2 6. The external pressure capability of the drywell and wetwell, and systems that may be provided to limit external pressures. 7. The effectiveness of static and active heat removal mechanisms. 8. The pressure conditions within subcompartments and acting on system components and supports due to high energy line breaks, e.g., the sacrificial shield structure. 9. The range and accuracy of instrumentation that is provided to monitor and record containment conditions during and following an accident. 10. The suppression pool temperature limit during reactor coolant system safety/relief valve operation, including the events considered in analyzing suppression pool temperature response, assumptions used for the analyses, and suppression pool temperature monitoring system. 11. The reactor coolant system safety/relief valve in-plant confirmatory test program. 12. The evaluation of analytical models used for containment analysis. Review Interfaces:4 The SCSB will coordinate other branches' evaluations that interface with the overall review of 5 6 the containment as follows: 1. The Instrumentation &and Control Systems Branch (ICSB)(HICB) , as part of its 7 8 primary responsibility for SRP Section 7.3, will evaluate the functional capability of the post-accident monitoring