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:
REVIEW RESPONSIBILITIES Primary - Materials and Chemical Engineering Branch (CMEBEMCB)1 Secondary - NoneEmergency Preparedness and Radiation Protection Branch (PERB) 2 - Plant Systems Branch (SPLB)3 I. AREAS OF REVIEW CMEBEMCB reviews the following information in the applicant's safety analysis report (SAR): 4 1. The design objectives and design criteria for the process sampling system (PSS) and post-accident sampling system (PAS) are reviewed at the construction permit (CP) stage. During the operating license (OL) stage of review, CMEB review consists of confirming the design accepted at the CP stage and evaluating the adequacy of the applicant's technical specifications in these areas. The review includes identification of the process streams to be sampled and the parameters to be determined through sampling (e.g., gross beta-gamma concentration, boric acid concentration). 2. The system descriptions for the PSS and PAS are reviewed at the operating license (OL) stage. The review includes (a) piping and instrumentation diagrams (P&IDs), (b) provisions for obtaining representative samples, (c) location of sampling points and sample stations, and (d) provisions for purging sampling lines. 3. The seismic design and quality group classifications of piping and equipment, and the bases for the classifications chosen are reviewed at the CP stage. At the OL stage, the DRAFT Rev. 3 - April 1996 9.3.2-2 review includes design and expected temperatures and pressures and materials of construction of components of the system. 4. The isolation provisions for the system and the means provided to limit radioactive releases by limiting reactor coolant losses are reviewed at the CP stage. 5. The design of the post-accident sampling system, the administrative program and the 5 operational procedures of post-accident sampling for the reactor coolant and containment atmosphere are reviewed to determine the capability of promptly obtaining samples, under accident conditions, for