Document: NUREG-0800
Document ID: 91a12934-f0d9-4573-ad3b-553ab75dabc0
Document Type: srp
Title: FISSION PRODUCT CONTROL SYSTEMS AND STRUCTURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600408.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.3
CFR Part: 
CFR Title: 

Content:
hods of compliance with the NRC regulations. 6.5.3-5 Revision 3 - March 2007 1. Primary Containment. Primary containment design leakage rates for which credit is given should not be less than 0.1% per day due to difficulties in measuring lower leakage rates. Containment isolation methods and times must be such that the calculated radiological doses resulting from the escape of radioactive material prior to and following isolation after a LOCA do not exceed the applicable dose requirements of 10 CFR Part 100 and GDC 19. The primary reactor containment and associated systems should be designed so that periodic inspections and functional testing can be performed. 2. Secondary Containment. To be classified as a secondary containment for the purpose of fission product control, a structure or structures should completely surround the primary containment, and at least should be held at a pressure of 0.6 cm (0.25 in) (water), below adjacent regions, under all wind conditions up to the wind speed at which diffusion becomes great enough to ensure site boundary exposures less than those calculated for the design basis accidents even if exfiltration occurs. Acceptance of other fission product control structures for collection and control of postaccident releases will be determined following consultation with the organization responsible for the review of reactor accident consequence assessment, (specifically design basis containment and ventilation performance) and the organization responsible for structural design of containment and ventilation systems, on a case-by-case basis. The leakage and filtration rates of such structures are acceptable provided that the offsite doses calculated by the organization responsible for radiation protection under SRP Section 15.6.5 will meet the dose guidelines of 10 CFR Part 100 and provided that the preoperational testing and appropriate technical specifications are acceptable. Other criteria include specifications for intake and return