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:
he requirements of GDC 60 in Appendix A to 10 CFR Part 5030 to control the release of radioactive materials to the environment. The guidelines of position 2.i.(6) in Regulatory Guide 8.8 (reference 5) should be followed to 31 meet this criterion. Passive flow restrictions in the sample lines may be replaced by redundant environmentally qualified, remotely operated isolation valves to limit potential leakage from sampling lines. The automatic containment isolation valves should close on containment isolation signals or safety injection signals. 4. To meet the requirements of GDC 1 and 2, the seismic design and quality group classification of sampling lines, components and instruments for both the PSS and PAS should conform to the classification of the system to which each sampling line and component is connected (e.g., a sampling line connected to a Quality Group A and seismic Category I system should be designed to Quality Group A and seismic Category I classification), in accordance with regulatory positions C.1, C.2, and C.3 in Regulatory Guide 1.26 (reference 6) , regulatory positions C.1, C.2, C.3, and C.4 in Regulatory 32 Guide 1.29 (reference 7) , and the guidelines of Regulatory Guide 1.97 (reference 8) . 33 34 Components and piping downstream of the second isolation valve may be designed to Quality Group D and nonseismic Category I requirements, in accordance with regulatory position C.3 in Regulatory Guide 1.26 (reference 6) . 35 5. The post-accident sampling system and operational procedures should meet the guidelines of item II.B.3 in NUREG-0737 (reference 9) , and of Regulatory Guide 1.97 36 (reference 8) , and the following additional clarifications: 37 a. To meet the requirements of GDC 13 and 14 in Appendix A to 10 CFR Part 50 , 38 if chemical analyses show that chloride concentration in the reactor coolant exceeds the Technical Specification limits, then verification that the dissolved oxygen concentration is below the Technical Specification limits