Document: NUREG-0800
Document ID: d72c5a84-b363-4a7d-9df3-5570a5eceb2c
Document Type: srp
Title: SOLID WASTE MANAGEMENT SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350108.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.4
CFR Part: 
CFR Title: 

Content:
eing stored, the quantity of radionuclides Present, and how readily they might be transported into the environment. In general, it is preferable to store radioactive material in solid form. Under some circumstances, however, temporary storage in liquid form may be desirable or required. The specific design and operation of any storage facility will be significantly influenced by the various waste forms, consequently, this Appendix addresses wet waste, solidified wet waste and dry low level waste. Prior to acceptance of such an on-site storage facility, substantial safety review and environmental analysis must be conducted to assure adequate public health and safety, and minimal environmental impact. The acceptance criteria and performance objectives of any proposed storage facility, or area, will need to meet minimal requirements in areas of design considerations, oper- ational considerations, and safety considerations. For purposes of this appendix, the major 'emphasis will be on safety considerations in the storing, handling, and eventual disposition of the radioactive waste. Additional con- siderations for decontamination and decommissioning of the temporary storage facility also need to be integrated into the design and operation of the proposed storage facility. B. STORAGE FACILITY REQUIREMENTS 1. General Requirements (a) The following design objectives and criteria are applicable for wet, solidified (or dewatered), and low level dry radioactive waste storage facilities: (1) The quantity of radioactive material allowed and the shielding configurations will be dictated by the dose rate criteria for both the site boundary and unrestricted areas onsite. The 40 CFR Part 190 limits will restrict the annual dose from direct radiation and effluent release to the public (individual to less than 25 mrem per year to the whole body from all sources of the uranium fuel cycle; therefore, offsite doses from 11.4-A-1 Rev. 0 - July 1981 onsite storage must be sufficiently low