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
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se. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 1. Upon request from the primary reviewer, staff reviewing an interfacing SRP section will provide input to address an area of review stated in Subsection I of this SRP section. The primary reviewer obtains and uses such input as required to assure that this review procedure is complete. 2. The staff reviews the analyses of the drywell and wetwell temperature and pressure response for BWR pressure-suppression containments. The staff performs confirmatory analyses, when necessary. Input data for the code, including mass and energy release data, are generally provided by the applicant. The staff normally analyzes only the design basis loss-of-coolant accident, which has been found from previous reviews to be the recirculation line break for Mark I and II 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. The reviewer 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, the peak containment pressure following a loss-of-coolant accident is independent of the postulated pipe break size. The staff reviews the containment response analysis presented in the safety analysis 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