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:
s report to determine whether the acceptance criteria in Subsection II have been satisfied. 6.2.1.1.C-10 Revision 7 - March 2007 The NRC has reviewed the General Electric Mark III analytical model and have determined that the code appears to calculate the drywell pressure response for both Mark III and ABWR plants in an acceptable manner. The code has been verified by the General Electric Mark III test program. The reviewer 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 reviewer will initiate a detailed review of the methods. In this case, 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 are reviewed. The staff reviews analyses of the drywell response to a recirculation line rupture, a steam line rupture, or a main feedwater line break as presented in the safety analysis report. The reviewer determines from the results of these analyses that the "worst" break has been identified in establishing the drywell-wetwell design differential pressure as well as the design pressure for subcompartments and equipment supports. The reviewer verifies that the containment is designed to withstand hydrogen burning during an accident that releases hydrogen from a 100% fuel clad metal-water reaction as described in Acceptance Criterion II. of this SRP section. 3. The review of the dynamic loads associated with a LOCA has been concluded with 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 has been concluded with the issuance of NUREG-0661 for Mark I plants, and NUREG-0802