Document: NUREG-0800
Document ID: c37e8c68-ed08-434b-b15c-438f1915858a
Document Type: srp
Title: PROCESS AND POST-ACCIDENT SAMPLING SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070526.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.2
CFR Part: 
CFR Title: 

Content:
as it relates to the process and post-accident sampling systems, enhances safety by DRAFT Rev. 3 - April 1996 9.3.2-10 providing a means in the design to control the release of radioactive material to the environment. Application of criterion 60 provides reasonable assurance that the process and post-accident sampling systems are designed, constructed, installed, and operated on a level commensurate with the need to protect the health and safety of the public and plant operating personnel. 9. GDC 63 requires that systems be provided to monitor the fuel storage and radioactive waste systems to detect conditions that may result in excessive radiation levels. The process sampling system, through sampling of the spent fuel pool water and the gaseous radwaste storage tanks, should be capable of detecting conditions that could result in excessive radiation levels and excessive personnel exposure. The process sampling system provides information necessary for the control of water chemistry to maintain the material properties of the fuel assembly cladding, structural members and cooling systems of the spent fuel pool. The process sampling system, through the ability to sample the gaseous radwaste storage tanks, is also used to detect abnormal levels of radioactivity in the radwaste processing facilities. Meeting the requirements of GDC 63, as it relates to the process sampling systems, ensures that sampling methods are available to monitor the spent fuel pool and the gaseous radwaste storage tank radioactivity levels such that personnel exposures are maintained as low as reasonably achievable. 10. GDC 64 requires means be available for monitoring the containment atmosphere, spaces containing components used for post-LOCA recirculation, effluent discharge paths and the plant environs for radioactivity that may be released during normal operations, anticipated operational occurrences, and postulated accidents. The process and post- accident sampling system designs provide the