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:
6.2.1.1.C-10 plants. For Mark III plants, the steam line break has been determined to be the design basis loss-of-coolant accident. However, mass and energy releases from the recirculation line break will be evaluated using various flow correlations. For ABWR plants, the feedwater line break has been determined to be the design basis loss-of-coolant accident.67 The SCSB evaluates analyses of both the short-term and long-term pressure and temperature responses of Mark III and ABWR containment plants. For Mark III plants, 68 the peak containment pressure following a loss-of-coolant accident is independent of the postulated pipe break size. The SCSB reviews the containment response analysis 69 presented in the safety analysis report to determine that the acceptance criteria in subsection II have been satisfied. Design certification applicants should meet the margins for containment design pressure and containment/drywell design differential pressure specified in specific criterion “a” For Mark III plants. For BWR pressure-suppression plants at the operating license stage, the peak calculated containment pressure and differential pressure should be less than the design values. In general, it is expected that the peak calculated pressures will be about the same as at the design certification stage. However, it is possible that the margins may be affected by revised or improved analytical models, test results, or minor changes in the as-built design of the plant. 70 The SCSB and its consultants have reviewed the General Electric Mark III analytical 71 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 72 been verified by the General Electric Mark III test program. 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