Document: NUREG-0800
Document ID: 47be7233-5326-4a7d-a9c5-f3b91d565a72
Document Type: srp
Title: MINIMUM CONTAINMENT PRESSURE ANALYSIS FOR EMERGENCY CORE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070492.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1.5
CFR Part: 
CFR Title: 

Content:
formance evaluation differs from the containment functional performance analysis, in that the conservatisms and margins are taken in opposite directions in the two cases. Thus, the minimum containment pressure analysis required by the regulations for ECCS performance evaluation is not conservative with regard to peak containment pressure in the event of a loss-of-coolant accident and cannot be used to determine the containment design basis. Review Interfaces:3 The SCSB will coordinate the review with the Reactor Systems Branch (SRXBRSB ), which is 4 5 responsible for determining the acceptability of the mass and energy release data used in the minimum containment pressure analysis(see as part of its primary review responsibility for SRP Section 6.3). This information is derived from the applicant's evaluation of ECCS performance 6 capability in accordance with 10 CFR Part 50, §50.46 and Appendix K to 10 CFR Part 50 . 7 For the area of review identified above as being reviewed as part of the primary review responsibility of another branch, the acceptance criteria and their methods of application are contained in the referenced SRP section.8 II. ACCEPTANCE CRITERIA CSB acceptance criteria is based on meeting the relevant requirements of 10 CFR Part 50, §50.46 paragraph I.D.2 of Appendix K to 10 CFR Part 50 which requires that the containment pressure used to evaluate the performance capability of a PWR emergency core cooling system shall not exceed a pressure calculated conservatively for that purpose. 9 SCSB Acceptance Criteria is based on meeting the relevant requirements of 10 CFR 50, §50.46. 10 CFR 50, §50.46, allows the use of either an acceptable ECCS evaluation model that realistically describes the behavior of the reactor during loss-of-coolant accidents or an ECCS evaluation model developed in conformance with 10 CFR 50, Appendix K. SCSB accepts the analysis if either of the following requirements are met as they relate to the postulated minimum