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
CFR Part: 
CFR Title: 

Content:
s identified in NUREG-0933, “Resolution of Generic Safety Issues” (Formerly entitled “A Prioritization of Generic Safety Issues”). 7. 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) for monitoring gaseous effluents from all potential accident release points, consistent with the requirements of GDC 63, “Monitoring Fuel and Waste Storage,” and GDC 64 in minimizing exposures to members of the public. For 10 CFR Part 50 applicants not listed in 10 CFR 50.34(f)(2), the applicable provisions of 10 CFR 50.34(f)(2) will be made a requirement during the licensing process and added as a license condition, as warranted. 11.5-13 Draft Revision 6 – August 2014 8. 10 CFR 50.36a, “Technical Specifications on Effluents from Nuclear Power Reactors,” as it relates to operating procedures and equipment installed in the radioactive waste system pursuant to 10 CFR 50.34a to ensure that releases of radioactive materials to unrestricted areas are kept ALARA. 9. 10 CFR 50.59, “Changes, Tests, and Experiments,” implemented using the guidance in RG 1.187, “Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments,” as it relates to design changes and differences in monitoring performance characteristics of PERMISS components in demonstrating compliance with effluent concentration limits of 10 CFR Part 20, Appendix B, Table 2. 10. 10 CFR 50.65(a) and 10 CFR 50.65(b) as they relate to providing reasonable assurance that SSCs important to safety, including those that are relied upon to mitigate accidents or transients or are used in plant emergency operating procedures (i.e., radiation monitors described in this SRP, or radiation protection features described in SRP Sections 12.3-12.4 and 12.5) are capable of fulfilling their intended functions. 11. 10 CFR Part 50, Appendix A, GDC 2 as it relates to the design basis of structures housing