Document: NUREG-0800
Document ID: 8536691d-4254-4c01-a5ec-aa9dee960958
Document Type: srp
Title: PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100740509.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
CFR Part: 
CFR Title: 

Content:
interpretation of results between monitoring instrumentation readouts, sample analytical results, and plant operations. 11.5-4 Revision 5 - May 2010 I. Descriptions of procedures used for calibration, maintenance, operational functional checks, and inspection of monitoring instrumentation and sampling systems. J. Layout drawings, piping and instrumentation diagrams (P&IDs), location and designation of effluent release or discharge points, and process and effluent flow diagrams. K. Monitoring systems and procedures used for the detection of radioactivity in nonradioactive systems to prevent unmonitored and uncontrolled releases of radioactive material to the environment. 3. The scope and elements of the technical specifications (TS) and standard radiological effluent controls (SREC) as they relate to the plant’s Offsite Dose Calculation Manual (ODCM), Radiological Environmental Monitoring Program (REMP), and the Process Control Program (PCP). The review evaluates the bases of limiting conditions for operations and controls for operation consistent with plant design features associated with the TS and SREC, as well as procedural details and programmatic controls of the ODCM, REMP, and PCP. 4. The quality group classifications of piping and equipment and the bases governing the classification chosen in accordance with the guidelines of Regulatory Guide (RG) 1.143. Design and expected temperatures and pressures and materials of construction of permanently installed systems and skid-mounted radiation monitoring and sampling equipment. 5. Design provisions incorporated in equipment and the facility to ease operation and maintenance in accordance with the guidelines of RG 1.143 and as referenced in topical reports, as well as previous experience with similar equipment and methods referenced in the safety analysis report (SAR) or other supporting documents. 6. Design features to reduce radioactivity levels in wastes, minimize, to the extent practicable, contamination of