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:
how 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 will be mandatory. Verification of hydrogen residual in excess of 10 cubic centimeters 9.3.2-7 DRAFT Rev. 3 - April 1996 per kilogram (at standard temperature and pressure) per kilogram of reactor 39 coolant will be acceptable in lieu of direct analysis of dissolved oxygen for 20 days. b. To meet the requirements of GDC 60 in Appendix A to 10 CFR Part 50 , if on 40 line gas chromatography is used for reactor coolant analyses, special provisions (e.g., pressure relief and purging) should be available to prevent high-pressure carrier gas from entering the reactor coolant. c. To meet the requirements of GDC 60 in Appendix A to 10 CFR Part 50 , passive 41 flow restrictions in the sampling lines may be replaced by redundant, fully qualified, remotely operated isolation valves to limit potential leakage from the sample lines. The automatic containment isolation valves should close on containment isolation signals or safety injection signals. All remotely operated valves should have assured power supplies and control so that they can be reopened after an accident without clearing the isolation signal. Valves which are inaccessible during an accident should be environmentally qualified to ensure operability under accident conditions. Technical Rationale:42 The application of the above acceptance criteria to the process and post-accident sampling systems is addressed in the following paragraphs. 1. 10 CFR Part 20, §20.1101(b) requires that licensees use, to the extent practicable, procedures and engineering controls based upon sound radiation protection principles to achieve doses 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