Document: NUREG-0800
Document ID: ff44162c-1686-4c5a-a9b2-3fa72707163c
Document Type: srp
Title: ESF ATMOSPHERE CLEANUP SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070468.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.1
CFR Part: 
CFR Title: 

Content:
ol room under accident and loss-of-coolant accident (LOCA)37 conditions. B. General Design Criterion 41 (GDC 41) as it relates to the design of systems to be used 38 for containment atmosphere cleanup following postulated accidents, and to control releases to the environment. 6.5.1-5 DRAFT Rev. 3 - April 1996 C. General Design Criterion 42 (GDC 42) and General Design Criterion 43 as theyit 39 40 relates to the inspection and testing of containment ESF atmosphere cleanup systems. D. General Design Criterion 43 (GDC 43) as it relates to the testing of containment ESF atmosphere cleanup systems.41 DE. General Design Criterion 61 (GDC 61) as it relates to the design of systems for 42 43 radioactivity control under normal and postulated accident conditions. EF. General Design Criterion 64 (GDC 64) as it relates to monitoring radioactive releases 44 under normal, anticipated operational occurrences, and postulated accident conditions from ESF atmosphere cleanup systems. Technical Rationale45 The technical rationale for application of these acceptance criteria to reviewing ESF atmosphere cleanup systems is discussed in the following paragraphs:46 1. Compliance with GDC 19 requires radiation protection of the control room to ensure that access and occupancy under accident conditions, including LOCAs, will not result in radiation exposures in excess of the specified limit. GDC 19 applies to this section because control room radiation protection under accident conditions may require an ESF atmosphere cleanup system. Meeting this criterion provides assurance that personnel needed to monitor and control an accident will be able to perform those functions effectively.47 2. Compliance with GDC 41 requires systems to control fission products that may be released into the reactor containment, thereby reducing the concentration of fission products released to the environment after an accident. GDC 41 also includes redundancy and reliability requirements for such systems. GDC 41