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:
val requirements and material compatibility requirements. In addition, the process and post-accident sampling systems are relied upon to sample and evaluate the conditions inside containment resulting from the metal-water reactions, radiolysis, and corrosion following a postulated accident. The information obtained from the process and post-accident samples are used to verify the safety functions of engineered safety features, including the atmospheric cleanup systems and the containment spray system, to mitigate the 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 process and post accident sampling systems, 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 process and post-accident sampling systems contain or may contain radioactive material that must be properly controlled. Examples of the controls used to prevent release of radioactive material from the process and post-accident sampling systems to the environment include: 1) redundant automatic isolation valves that will close on a containment isolation signal or safety injection signal and will fail in the closed position; 2) purging and draining the sample lines back to the system being sampled or to the radwaste treatment system; and 3) 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 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