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:
d for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. There documents are made availabl, to the public as part of the Commission's policy to Inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revisedperiodically, as appropriate, to accommodate comments and to reflect new informa- tion and experience. Comments end suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation. Washington, D.C. 2O1. are reviewed to determine the capability of promptly obtaining samples, under accident conditions, for chemical and radiochemical analyses. CMEB coordinates reviews related to this system that are performed by the following branches as part of their primary review responsibilities: Radiological Assessment Branch (RAB), under SRP Section 12.3, reviews the potential personal radiation exposure during post-accident sampling. Effluent Treatment Systems Branch (ETSB) reviews the ventilation systems which may be operating during post-accident sampling and the sampling and monitoring systems for radwaste processing systems under SRP Sections 11.3 and 11.5, respectively. Containment Systems Branch (CSB), under SRP Sec- tion 6.2.4, verifies that remotely operated containment isolation valves in the PSS and PAS are designed to close on a containment isolation signal (CIS) or safety injection signal (SIS). Instrumentation and Control Systems Branch (ICSB), under SRP Section 7.3,