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:
ator to assess integrity of the fuel cladding and to recognize conditions that could jeopardize integrity of the reactor coolant pressure boundary; 3) following an accident, the post-accident sampling system provides information that allows the operator to assess the success of safety systems and systems important to safety in mitigating the consequences of the accident and to determine appropriate actions for further mitigation or recovery from the accident; and 4) the sampling systems contain or may contain radioactive material. Meeting the requirements of GDC 1 ensures that the process and post-accident sampling systems will be designed, fabricated, erected and tested to generally accepted and recognized codes and standards that are sufficient to assure a quality system in keeping with the required safety functions. 3. GDC 2 requires that structures, systems and components important to safety be designed to withstand the effects of natural phenomena without the loss of capability to perform their safety functions. The process and post-accident sampling systems connect to systems, such as the reactor coolant pressure boundary, that are designed to Seismic Category I requirements. Those portions of the process and post-accident sampling systems or components that form interfaces between Seismic Category I and non-Seismic Category I features should be designed to Seismic Category I requirements. Meeting the requirements of GDC 2 for those portions of the process and post-accident sampling systems 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 assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, and the reactor coolant pressure