Document: NUREG-0800
Document ID: 216e7734-89e2-46c4-b2bc-9018045923c4
Document Type: srp
Title: through 6.5.4 and 15.0.3.  Upon request, the organization responsible for
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100700256.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.2
CFR Part: 
CFR Title: 

Content:
cleanup system may be an ESF. Meeting this criterion provides assurance that the equipment necessary to mitigate the consequences of an accident will maintain its functional capability. 4. Compliance with GDC 43 requires that containment atmosphere cleanup systems be designed to accommodate periodic pressure and functional testing. GDC 43 applies to this section because the containment atmosphere cleanup system may be an ESF. 6.5.1-7 Revision 4 - May 2010 Meeting this criterion provides assurance that the equipment necessary to mitigate an accident will maintain its functional capability. 5. Compliance with GDC 61 requires that fuel storage and handling, radioactive waste, and other systems that may contain radioactive material be designed to ensure adequate safety under normal and postulated accident conditions. These systems shall be designed with appropriate containment, confinement, and filtering systems. GDC 61 applies to this section because attainment of the objectives for postulated accident conditions may require an ESF atmosphere cleanup system. Meeting this criterion provides assurance that offsite doses of radiation resulting from accident conditions will not exceed regulatory limits. 6. Compliance with GDC 64 requires monitoring the reactor containment atmosphere, spaces containing components for recirculation of LOCA fluids, effluent discharge paths, and the plant environs to detect radioactivity that may be released from normal operations (including anticipated operational occurrences) and postulated accidents. GDC 64 applies to this section because the ESF atmosphere cleanup systems are used to control releases of radioactivity from postulated accidents. The review ensures that means are provided to monitor releases. Meeting this criterion provides assurance that offsite doses of radiation resulting from accident conditions will not exceed regulatory limits and that releases will be adequately documented. III. REVIEW PROCEDURES The reviewer will