Document: NUREG-0800
Document ID: 66e7af3b-21c0-444f-8737-0830bb176eba
Document Type: srp
Title: PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A182.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
CFR Part: 
CFR Title: 

Content:
P Section 11.5 and ANSI N42.18-2004. The review conducted in this SRP section, with supporting information from SRP Sections 11.2, 11.3, and 11.4, evaluates the methods and results used to demonstrate compliance with these requirements using NRC and industry guidance in developing operational programs. Meeting the above noted guidance provides reasonable assurance that the requirements of GDC 63 and GDC 64 will be met and that the levels of radioactivity in effluents from nuclear power plants will not exceed specified limits and design objectives. 7. 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 and liquid effluents from all potential accident release points. In examining the applicant’s system for sampling process streams and effluents under accident conditions, the review considers the guidance of RG 1.97; RG 1.101; SRP Chapter 7; BTP 7-10; NUREG-0933; NUREG-0737, Items 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, Attachment 1 on noble gas effluent monitors; Item III.D.1.1 (Clarification Items 1 and 3), Item III.D.3.3 (Clarification Items 1 to 4); and letter from D.G. Eisenhut, dated August 16, 1982. Using the guidance of SRP Sections 9.3.2 and 13.3, the applicant’s emergency plan and implementing procedures should address these aspects in the emergency plan and implementing procedures. For any portion of the PERMISS accident monitoring systems that supports safety-related functions, as identified by the applicant, the review of these design features is performed under SRP Chapter 7 using the guidance of RG 1.97 and BTP 7-10. The review, using RG 1.97 and RG 1.151, addresses the performance, design, qualification, display, QA, and selection of monitoring variables of radiation monitoring equipment required for accident