Document: NUREG-0800
Document ID: 307194c1-0b51-4a4d-bd65-440bb260c4bb
Document Type: srp
Title: PROCESS AND POST-ACCIDENT SAMPLING SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350552.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.2
CFR Part: 
CFR Title: 

Content:
3 and 14 in Appendix A to 10 CFR Part 50, to monitor variables which can affect the Integrity of the reactor core and the reactor coolant pressure boundary for accident conditions, and to assure a low probability of abnormal leakage, rapidly propagating failure, and gross rupture, respectively, by keeping the oxygen concentration in the reactor coolant below the technical Specification limits when the chloride concentration exceeds the Technical Specification limits or by having excessive hydrogen dissolved in the reactor coolant; and (A) the requirements of GCM 60 in Appendix A to 10 CFR Part 50 to control the 9.3.2-8 Rev. 2 - July 1981 release of radioactive materials to the environment, by preventing high- pressure carrier gas used in gas chromatographic analysis of reactor cool- ant from entering the reactor coolant, and by providing passive flow restrictions or fully qualified, remotely operated isolation valves in the sampling lines, to limit potential leakage from the sampling lines. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of con- formance with Commission regulations. . Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREG. VI. REFERENCES 1. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants." 2. Regulatory Guide 1.56, "Maintenance of Water Purity in Boiling Water Reactors." 3. ANSI N13.1-1969, "Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities," American National