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:
.0: review of Technical Specifications. 21. Chapter 17: review of quality assurance. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 20.1101(b), as it relates to providing engineering controls based upon sound radiation protection principles to achieve occupational doses and doses to members of the public as low as is reasonably achievable (ALARA). 2. General Design Criterion (GDC) 1, found in Appendix A to 10 CFR Part 50, as it relates to the design of the PSS and components in accordance with standards commensurate with the importance of their safety functions. 3. GDC 2, as it relates to the ability of the PSS to withstand the effects of natural phenomena. 4. GDC 13, as it relates to monitoring variables that can affect the fission process, the integrity of the reactor core, and the reactor coolant pressure boundary. 9.3.2-5 Revision 3 - March 2007 5. GDC 14, as it relates to assuring the integrity of the reactor coolant pressure boundary by sampling for chemical species that can affect the reactor coolant pressure boundary. 6. GDC 26, as it relates to reliably controlling the rate of reactivity changes by sampling boron concentration. 7. GDC 41, as it relates to reducing the concentration and quality of fission products released to the environment following postulated accidents by sampling the chemical additive tank for chemical additive concentrations to ensure an adequate supply of chemicals for meeting the material compatibility requirements and the elemental iodine removal requirements of the containment spray and recirculation solutions following a postulated accident. 8. GDC 60, as it relates to the capability of the PSS to control the release of radioactive materials to the environment. 9. GDC 63, as it relates to detecting conditions that may result