Document: NUREG-0800
Document ID: c53cf2ef-5eb4-4449-bed4-17a9eff508e3
Document Type: srp
Title: SECONDARY CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600406.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.3
CFR Part: 
CFR Title: 

Content:
s stated in Subsection I of this SRP section. The input obtained will ensure that the review is complete. 2. Analytical models used and assumptions made in the analyses of the pressure and temperature response of the secondary containment to LOCAs in the primary containment are reviewed. In general, the reviewer determines whether the analyses conservatively predict the secondary containment pressure response by comparing them to the guidelines in Subsection III of this SRP section. For new applications, the 6.2.3-8 Revision 3 - March 2007 reviewer verifies that analyses of ability to draw a negative pressure on the secondary containment volume following a LOCA assume that all lines not receiving an isolation signal are open and that the worst-case secondary containment isolation valve fails to close. 3. If considered necessary, there will be confirmatory analyses of the pressure and temperature response of the secondary containment for LOCAs within the primary containment and for high-energy line (e.g., steam line and feedwater line) ruptures occurring within the annular region formed by the secondary containment. 4. The analysis will be based on the guidelines of Subsection III of this SRP section and code input data from the SAR. The review determines whether the secondary containment design pressure is exceeded, whether the depressurization time is consistent with that assumed in the analysis of the radiological consequences of the accident, and whether the primary containment external design pressure is exceeded. 5. The review determines whether all direct leakage paths have been identified and from the proposed leakage testing program whether design of the plant provides for measurement of the fraction of total primary containment leakage that bypasses the secondary containment. Any inadequacies in the applicant's direct leakage assumptions in the radiological analysis are noted. At the operating license stage, reviews technical specifications of surveillance