Document: NUREG-0800
Document ID: 2f527583-f167-477c-9a93-bc8f7db676b6
Document Type: srp
Title: for the LWMS and GWMS, respectively.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1307/ML13072A545.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
CFR 61.56 requirements for waste classification and characteristics taking into considerations the waste acceptance criteria of the chosen licensed radioactive waste disposal facility. The PCP should present the process and methods used to meet these 10 CFR Part 61 requirements and those of the disposal facility. 13. Greater-than-Class C wastes will be processed and placed in long-term onsite storage in accordance with 10 CFR 61.55 and 10 CFR 61.56 requirements for wastes with concentrations in excess of 10 CFR 61.55 (Table 1) limits as activated metals, radioactive sources, alpha emitting transuranics, and Pu-241 and Cm-242 until disposal access is gained at a facility licensed under 10 CFR Part 60 or 10 CFR Part 63. The PCP should present the process and methods used to meet these requirements, excluding spent-fuel. 14. Mixed wastes (characterized by the presence of hazardous chemicals and radioactive materials) will be processed and disposed in accordance with 10 CFR 20.2007, as it relates to compliance with other applicable Federal, State, and local regulations governing any other toxic or hazardous properties of radioactive wastes. 15. All effluent releases (gaseous and liquid) associated with the operation (normal and AOOs) of the SWMS will comply with 10 CFR Part 20 and guidance of RG 1.143, as they relate to the definition of the boundary of the SWMS beginning at the interface from plant systems, including multiunit reactor stations, to the points of controlled liquid and gaseous effluent discharges to the environment or designated onsite storage locations, as defined in the PCP or ODCM. 16. For processing systems equipped with automatic control features, the application should provide the justification for the placement of isolation valves and radiation detectors on process piping to ensure the timely closure of such valves upon the detection of elevated radioactivity levels. Other considerations may include determining whether system logic demands that a