Document: NUREG-0800
Document ID: 919b8fa0-8b11-41bd-9694-2c62120b843b
Document Type: srp
Title: Revision 7 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600403.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
-coolant accident or following actuation of one or more reactor coolant system safety/relief valves. The acceptability of pool dynamic loads for plants with Mark I containments is based on conformance with NRC acceptance criteria found in NUREG-0661. The acceptability of loss-of-coolant accident related pool dynamic loads for plants with Mark II containments is based on conformance with the generic loads previously reviewed and found acceptable by the NRC and NRC acceptance criteria. The loss-of-coolant accident related pool dynamic loads and criteria are as discussed in NUREG-0808, and Appendix B to this SRP section. Pool dynamic loads and criteria associated with the actuation of one or more reactor coolant system safety/relief valves are specified in Appendix A of NUREG-0802. The acceptability of pool dynamic loads for plants with Mark III containments is based on conformance with the NRC acceptance criteria identified in Appendix C of NUREG-0978. For Mark III plants at the construction permit stage, conformance with 6.2.1.1.C-6 Revision 7 - March 2007 the NRC acceptance criteria can be demonstrated if a previously analyzed Mark III plant has sufficient similarity in plant characteristics to make the analyses performed for that plant design applicable to the Mark III plant design under consideration. The acceptability of pool dynamic loads associated with the actuation of one or more reactor coolant system safety/relief valves in Mark III containment are specified in Appendix B of NUREG-0802. The acceptability of pool dynamic loads for plants with ABWR containments is based on the GE analytical model provided in Appendix 3B of the ABWR SSAR which, in part, conforms with NUREGS 0802, 0808, and 0978. This model was used in the standard plant analysis and evaluated by the NRC in the ABWR FSER . 3. In meeting the requirements of GDC 16 and 50 regarding the containment design margin for Mark III and ABWR plants, high energy lines passing through the containment should