Document: NUREG-0800
Document ID: f7c58873-6f34-4f88-8e26-90fc2e310d25
Document Type: srp
Title: PROCESS AND POST-ACCIDENT SAMPLING SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070680137.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.2
CFR Part: 
CFR Title: 

Content:
d the gaseous radwaste storage tanks, should be capable of detecting conditions that could result in excessive radiation levels and excessive personnel exposure. The PSS provides information necessary for the control of water chemistry to maintain the material properties of the fuel assembly cladding and structural members and cooling systems of the spent fuel pool. The PSS, through the ability to sample the gaseous radwaste storage tanks or offgas charcoal delay or decay beds, 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 PSS, 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 at ALARA levels. 10. GDC 64 requires that means be available for monitoring the containment atmosphere, spaces containing components used for recirculation after a loss-of-coolant accident, effluent discharge paths, and the plant environs for radioactivity that may be released during normal operations, anticipated operational occurrences, and postulated accidents. The PSS design provides the means for monitoring for radioactivity that may be released during normal operations, anticipated operational occurrences, and postulated accidents. The PSS provides information to indicate the potential for being breached or the actual breach of the barriers to fission product release (i.e., fuel cladding, primary coolant pressure boundary, and containment). The PSS provides information regarding the release of radioactive materials, which allows for early indication of the need to initiate other protective actions. Meeting the requirements of GDC 64, as it relates to the PSS, ensures that a means is provided to monitor the release of radioactive materials, giving the plant operator the indications needed to initiate actions when necessary to protect the health and safety of