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:
ternal pressure. 4. In meeting GDC 43 and 10 CFR Part 50, Appendix J, requirements for secondary containment system testing the following criteria apply: A. The fraction of primary containment leakage bypassing the secondary containment and escaping directly to the environment should be specified. BTP 6-3 provides guidance for detecting leakage paths to the environment which may bypass the secondary containment. The periodic leakage rate testing program for measuring the fraction of primary containment leakage that may directly bypass the secondary containment and other contiguous areas served by ventilation and filtration systems should be described. Individual tests should be according to procedures from technical specifications or their bases. B. There should be provisions in the design of the secondary containment system for inspections and monitoring of the functional capability. Preoperational and periodic test programs determine the depressurization time, the secondary containment in-leakage rate, the uniformity of negative pressure throughout the secondary containment and other contiguous areas, and the potential for ex-filtration. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. GDC 4 requires that SSCs important to safety be designed to accommodate the effects of environmental conditions of normal operation, maintenance, testing, and postulated accidents (including LOCAs) and protected against dynamic effects that may result from equipment failures. The secondary containment minimizes offsite radioactive releases by confining a substantial fraction of leakage from the primary containment following a LOCA. Application of GDC 4 to the secondary containment provides assurance that the environmental conditions and equipment failures to which it may be exposed will not affect its capability to contain radioactive material