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:
consequences of postulated accidents by removing from the containment atmosphere radioactive material that may be released in an accident. Meeting the requirements of GDC 41, as it relates to the PSS, ensures that sufficient sample information can be provided to verify the safety function of engineered safety features to reduce the concentration and quality of fission products that may be released to the environment following postulated accidents. 8. GDC 60 requires that means be provided to control the release of radioactive materials to the environment. The PSS contains or may contain radioactive material that must be properly controlled. Examples of the controls used to prevent release of radioactive material from the PSS to the environment include (a) redundant automatic isolation valves that will close on a containment isolation signal or safety injection signal and will fail in the closed position, (b) purging and draining the sample lines back to the system being sampled or to the radwaste treatment system, and (c) passive flow restrictions to limit reactor coolant loss from a rupture of a sample line. Meeting the requirements of GDC 60, as it relates to the PSS, enhances safety by providing a means in the design to control the release of radioactive material to the environment. Application of GDC 60 provides reasonable assurance that the PSS is designed, constructed, installed, and 9.3.2-10 Revision 3 - March 2007 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 PSS, 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 PSS provides information necessary