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:
s that are as low as is reasonably achievable (ALARA). The radiation protection community has recognized that it is prudent to avoid unnecessary exposure to radiation and to maintain doses ALARA as it is assumed that there is a non-threshold linear relationship between dose and biological effects that is independent of the dose rate. The objective of the ALARA requirement in regard to the process and post- accident sampling systems is to ensure that licensees make every reasonable effort in planning, design and operation of the system to maintain exposures to radiation as far below the limits of 10 CFR Part 20 as is reasonably achievable. Appropriate station layout and design features should be provided to reduce the potential doses to personnel who must operate, service, or inspect the station process and post-accident sampling systems. The safety benefit of implementing radiation protection goals in regard to the process and post-accident sampling systems is to reduce doses wherever and whenever reasonably achievable, thereby reducing the risk that is assumed (for radiation protection purposes) to be proportional to the dose. 2. GDC 1 requires that structures, systems and components important to safety be designed, fabricated, erected and tested to quality standards commensurate with the importance of the safety functions to be performed. The process and post-accident sampling systems are important to safety in that: 1) through connections to systems, such as the reactor coolant system, that are designed and classified in accordance with recognized quality standards their failure could adversely affect the integrity of these systems; 2) during DRAFT Rev. 3 - April 1996 9.3.2-8 normal operation, the process sampling system provides information that allows the operator 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