Regulatory Guide 3.13
| ML003740240 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1973 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| RG-3.13 | |
| Download: ML003740240 (2) | |
Octobw 1973 U.S. ATOMIC ENERGY COMMISSION
REGULATORY GUIDE
DIRECTORATE OF REGULATORY STANDARDS
REGULATORY GUIDE 213 GUIDE FOR ACCEPTABLE WASTE STORAGE METHODS
AT UF 6 PRODUCTION PLANTS
A. INTRODUCION
In 10 CFR Put 20, "Standards for Protection Against Radiation," section 20.106 "Radioactivity in Effluents to Unrestricted Areas," generally prohibits the use of licensed material In a manner which results in the release to an unrestricted area of radioactive material In
"concentrations which exceed the limits specified in Appendix B, Table U of Pat 20. Section 20.1(0),
"rpose",
states that In addition to complying with the requirements set forth in Part 20, licensees should make every reasonable effort to maintain radiation exposures and release of radioactive materials in effluents to unrestricted areas, as far below the limits specified in Part 20
as practicable.
To comply with these jequirements, licensees store many of the waste materials generated at UFo production plants onsite for various periods of time. waiting final disposal. It Is important that waste storage areas and retention systems be constructed and maintained in accordance with sound engineering principles since their purpose Is to prevent or control the releae of radioactive materials and chemicals to the environment. This regulatory guide describes design guidelines acceptable to the Regulatory staff for the safe storage of radioactive wastes from plants producing UF,; from uranium mill concentrate.
B. DISCUSSION
UFd production plants which employ the solvent extraction process for purification of urnium mill concentrate produce small amounts of solid radioactive waste which are uually disposed of by burial onsite.
Large volumes of liquid chemical waste containing concentratcldis of radioactive material dightly in excess of those specified In Table II of Appendix B of Part 20
are also generated and stored in earthen embankment retention systems. When neutralization and precipitation are successful In reducing the soluble chemical and radioactive concentrations in the liquid waste to an acceptable level, precipitated material is collected and stored in a settling basn and the liquid is released to the environment. When further treatment is required to reduce the radioactive and/or chemical concentrations to acceptable release levels, solids are collected and stored in a settling basin and liquids allowed to overflow to a retention basin for storage.
UF, production plants which employ a fluoride volatilization process for purification produce liquid waste which is handled in the same manner at liquid waste generated in the solvent extraction process.
However, the amount of solid waste produced is too great to be buried onsite. so it is stored in onsite radioactive waste storage areas until transferred to a licensed commercial radioactive waste iSpos firm.
The following definitions are used .n this guide:
1. Earthen Embankment Retention System means a watertight system -of one .or more settling and/or retention basins including their associated engineered safety features.
2.
Retention Biin means a watertight basin in which liquid wastes are held for any one or more of the following reasons: (a) anlysis to verify activity levels permdtting release, (b) evaporation, (c) recycle for treatment.
3.
Settiing Basin means a watertight basin designed for separating sludges and sediments as a layer on the bottom. The liquid Is disposed of by overflow to the environment, transfer to a retention basin, or solar evaporation.
4.
UF,; Production Plant means a plant used for the sole purpose of commercial purification and conversion Cool at ~ldS uitis low be fttairod by '.auel' bilathi r fVbW s USAEC REGULATORY GUIDES
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C. REGULATORY POSITION
Storage areas for solid radioective wafte and rctentiom basins for liquid radioactie waste should be designed to provide reasonable asasranci that the health and safety of the public is not endangered during normal operation nor as a result of credible accidents. The following guidelines are generally acceptable to the Regulatory staff for the design of storage systems for solid and liquid radioactive waste generated it UWe production plants:
I. Sold Radioactive Waste Storap a.
Except for sludges in liquid retention systems, storage of sold radioactive wastes should be in appropriate containers approved by the Department of Transportation.
b. Storage areas for solid radioactive waste should be used exclusively for storage of natural uranium waste generated at the plant, including contaminated equipment. Process operations, storage of non-uclear material, and other functions not directly a pat of normal storage operations should be kept separate from storamp areas for solid radioactive waste.
c.
Features should be provided at storap areas for solid radioactive waste to permit recovery or Impoundment of waste which may be lost from containers.
d.
Storage containers for solid radioactive waste should be marked or coded to indicate the type and amount of contained radioactive material.
e.
Materils of construction in storage area for solid radioactive waste should be fire-resistive or noncombustible to the maximum extent practicable.
Fire-suppression equipment capable of minimizing the propaption of res should be provided.
f.
Ventilation systems should be provided if the need for such equipment Is indicated.
g. Storage area for solid radioactive waste should be designed to prevent unauthorized access to and unauthorized removal fiom or diversion of stored materlal.
2.
LIquWd Radioactive Waste Stomp a.
A lined earthen embankment retention system is an acceptable liquid storage facility in regions where the evaporation rate is significantly greater than the rainfall. In other regions, the use of these systems is acceptable only for interim storage prior to treatment.
b. The site of the embankment retention system should be owned by the licensee and located by survey.
and should not occupy the channel of any permanent or Intermittent watercoune.
c.
The pertinent basic design considerations.
methods of stability analysis, and mininumn factors of safety contained in the United States Department or the Army, Corps of Enginecrs. Manual EM-1 10-1.PX1.
"Engineering and Design Stability of Earth and Roek Fill Dams," dated April I, 1970,' provide an acceptable basis for the design of a safe settling or retention basin structure.
d.
The Interior of each retention or settling basin should be lined with an essentially impervious synthetic lining -naterdal designed to prevent seepage. The number of construction joints and penetrations of the liner should be minimized, and protection from mechanical damap'should be provided.
e.
Provisions should be made to maintain a safe embankment freeboard above the liquid level hI each basin.
E
Basin embankments should be stabilized to prevent erosion. Provisions should be made to stabilize loose radioactive material produced by evaporation of liquid from the basins.
.
The site should be parmanentlyt protected apinst water runoff from surrounding drainage areas.
Grding and/or diversion channels should be provided to enhance natural dra'inge if necessary.
h. Th site should be provided with a security fence designed to restrict acces; by animals and unauthorized individuals.
The fence should. be constructed at a sufficient distance from the system to permit maintenance on the outer .dopes of embankments. Provisions should be made to discourage waterfowl from landing on the pond surfaces.
L
Underbed drainage systems, ground resistivity measurement systems, or other seepage assessment systems should be included in the design. Seepage assessment systems should be located in potential seepage zones as determined by the hydrology and geology of the area. The design of seepage assessment systems should provide protection against contamination by surface waters.
J.
The design should provide for the needs of routine system maintenance, the stabilization of the basins when manufacturing operations are terminated, and alternative methods of storage if the integrity of any basin Is determined insufficient to retain its contents safely.
IT i docummt is avahble from the Depauinw of fw Army, Olrik of the Clue of Engat Watsbion, D.C. 20314.
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