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:
accordance with recognized quality standards, their failure could adversely affect the integrity of these systems, (b) during normal operation, the PSS provides information that allows the operator to assess the integrity of the fuel cladding and to recognize conditions that could jeopardize the integrity of the reactor coolant pressure boundary, (c) although the PSS does not have a specific post-accident sampling capability, its design allows for the collection and analysis of highly radioactive samples that may be present following an accident. Meeting the requirements of GDC 1 ensures that the PSSs will be designed, fabricated, erected, and tested to generally accepted and recognized codes and standards that are sufficient to ensure a quality system in keeping with the required safety functions. 3. GDC 2 requires that SSCs important to safety be designed to withstand the effects of natural phenomena without the loss of the capability to perform their safety functions. The PSS connects to systems, such as the reactor coolant pressure boundary, that are designed to seismic Category I requirements. Those portions of the PSSs or components that form interfaces between seismic Category I and nonseismic Category I features should be designed to seismic Category I requirements. Meeting the requirements of GDC 2 for those portions of the PSS that interface with seismic Category I systems will enhance plant safety by ensuring the integrity of seismic Category I systems, such as the reactor coolant pressure boundary, during the design- basis seismic event. 4. GDC 13 requires that instrumentation be provided to monitor variables and systems to ensure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, and the reactor coolant pressure boundary. The PSS is relied upon to provide water and gaseous samples from the reactor coolant system and associated auxiliary systems during all normal modes of