Document: NUREG-0800
Document ID: de4e4c58-fcfd-4b28-8207-5ae6fc761ee2
Document Type: srp
Title: for the LWMS and GWMS, respectively.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A174.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
characteristics of filtration systems, ion-exchange resins, and adsorbent and stabilization media proposed to treat liquid and wet wastes. This includes removal efficiencies, decontamination factors, waste volume increase factors for stabilized wastes, and volume decrease factors for compacted wastes, taking into account the expected physical, chemical, and radiological properties of process waste and effluent streams. The review should determine whether performance meets that noted in NRC guidance, standard DCs, and industry standards, 11.4-19 Revision 4 – January 2016 or topical reports. The NRC guidance includes NUREG-0016 or NUREG-0017 and RG 1.112 (as revised as of six months before the docket date of the application), as they relate to the use of acceptable methods in calculating radionuclide concentrations in process streams and effluent releases; and RG 1.110, as it relates to performing cost- benefit analysis in reducing cumulative population doses by using available technology, unless already addressed in SRP Sections 11.2 and 11.3. 3. Compliance with GDC 60 requires that each nuclear power plant design shall include means to handle radioactive wastes produced during normal reactor operation, including AOOs. GDC 60 requires that the SWMS must provide for a holdup capacity sufficient to retain radioactive wastes, particularly where unfavorable site environmental conditions may impose unusual operational limitations on the release of effluents. Waste processing holdup times and long-term storage capacity also provide decay time for shorter-lived radionuclides before they are processed or released to the environment. Meeting the requirement of GDC 60 provides reasonable assurance that releases of radioactive materials in liquid and gaseous effluents to unrestricted areas during normal operation of the SWMS and AOOs will not result in offsite radiation doses exceeding the dose objectives specified in Appendix I to 10 CFR Part 50, or concentrations of