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:
am. The SCSB verifies from the safety analysis report that the General Electric code has been utilized and that the input assumptions to the code are conservative. If analytical methods other than the General Electric model are used, the SCSB, in conjunction with its consultants, will initiate a detailed review of the methods. In this case, the SCSB73 reviews the proposed modeling, analytical methods and assumptions, correlation of results with applicable test data, and comparison with other similar analyses, to determine the acceptability of the proposed model. The SCSB reviews analyses of the drywell response to either a recirculation line rupture, or a steam line rupture, or main feedwater line break as presented in the safety analysis 74 report. The SCSB determines from the results of these analyses that the "worst" break 75 has been identified in establishing the drywell-wetwell design differential pressure as well as the design pressure for subcompartments and equipment supports. The SCSB verifies that the containment is designed to withstand either hydrogen burning or initiation of the post-accident inerting system, if installed, during an accident that releases hydrogen from a 100% fuel clad metal-water reaction as described in specific criterion II.k of this SRP section.76 6.2.1.1.C-11 DRAFT Rev. 7 - April 1996 If a post-accident inerting system is utilized, the SCSB verifies the containment is designed to withstand inadvertent actuation of this system.77 Modifications to the CONTEMPT-LT computer code have been made which provide the capability to perform confirmatory analyses of the Mark III and ABWR drywell 78 pressure response. 2. The review of the dynamic loads associated with a LOCA hashave been concluded with 79 the issuance of NUREG-0661 for Mark I plants, NUREG-0808 for Mark II plants and NUREG-0978 for Mark III plants. The review of the dynamic loads associated with the actuation of one or more primary coolant system safety/relief valves hashave