Document: NUREG-0800
Document ID: 3c241845-034f-4f89-b12a-f51967895c13
Document Type: srp
Title: PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1307/ML13071A494.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
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the event of a postulated accident. These provisions should be in accordance with GDC 64 and the requirements of 10 CFR 50.34(f)(2)(viii), 10 CFR 50.34(f)(2)(xiv)(E), 10 CFR 50.34(f)(2)(xvii), 10 CFR 50.34(f)(2)(xxvi), and 10 CFR 50.34(f)(2)(xxvii), as they relate to postulated accidents and identified liquid effluent release paths. In addition, the design of the liquid waste collection and processing system should meet the guidance of SRP Sections 9.3.2, 11.2, and 13.3, as well as the following conditions: A. Administrative controls and procedures should be consistent with Acceptance Criteria 2 and 3 (above) of this SRP section in minimizing inadvertent or accidental releases of radioactive liquids. B. Liquid effluent radiological monitors should be provided for the automatic termination of releases in the event that effluent release setpoints are exceeded, as described in Acceptance Criterion 1 (above) of this SRP section, and implemented in the plant’s RETS/SREC and ODCM. 11.5-19 Draft Revision 6 – August 2014 C. When two or more radiation monitoring systems are used for accident monitoring on a single discharge point, differences in instrumentation response characteristics should be described over their overlapping operational ranges for expected radionuclide distributions and concentrations. 6. The requirements specified in 10 CFR 50.34(f)(2)(viii), 10 CFR 50.34(f)(2)(xiv)(E), 10 CFR 50.34(f)(2)(xvii), 10 CFR 50.34(f)(2)(xxvi), and 10 CFR 50.34(f)(2)(xxvii) include provisions for monitoring gaseous effluents from all potential accident release points. In examining the applicant’s system for sampling process streams and effluents under accident conditions, the reviewer considers RG 1.97 and RG 1.101, “Emergency Planning and Preparedness for Nuclear Power Reactors”; SRP Chapter 7; and BTP 7-10; NUREG-0933; NUREG-0737, Item II.B.3 (Clarification Items 1, 3, 6, and 11); Item II.E.4.2 (Clarification Items 2, 5, and 7 and Attachment 1); Item II.F.1,