Regulatory Guide 3.13: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 14: Line 14:
| page count = 2
| page count = 2
}}
}}
{{#Wiki_filter:Octobw 1973 U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:Octobw 1973 U.S. ATOMIC ENERGY COMMISSION  
                            REGULATORY GUIDE
REGULATORY GUIDE  
                              DIRECTORATE OF REGULATORY STANDARDS
DIRECTORATE OF REGULATORY STANDARDS  
                                                                REGULATORY GUIDE 213 GUIDE FOR ACCEPTABLE WASTE STORAGE METHODS
REGULATORY GUIDE 213 GUIDE FOR ACCEPTABLE WASTE STORAGE METHODS  
                                                          AT UF 6 PRODUCTION PLANTS
AT UF 6 PRODUCTION PLANTS
                        A. INTRODUCION                                                   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 In 10 CFR Put 20, "Standards for Protection Against Radiation," section 20.106 "Radioactivity in                                     reduce the radioactive and/or chemical concentrations to acceptable release levels, solids are collected and stored Effluents to Unrestricted Areas," generally prohibits the use of licensed material In a manner which results in the                                 in a settling basin and liquids allowed to overflow to a retention basin for storage.
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.


release to an unrestricted area of radioactive material In
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.
"concentrations which exceed the limits specified in                                              UF, production plants which employ a fluoride Appendix B, Table U of Pat 20. Section 20.1(0),
                                                                                          volatilization process for purification produce liquid
"rpose", states that In addition to complying with the waste which is handled in the same manner at liquid requirements set forth in Part 20, licensees should make every reasonable effort to maintain radiation exposures                                  waste generated in the solvent extraction process.


and release of radioactive materials in effluents to                                      However, the amount of solid waste produced is too great to be buried onsite. so it is stored in onsite unrestricted areas, as far below the limits specified in radioactive waste storage areas until transferred to a Part 20 as practicable. To comply with these jequirements, licensees store many of the waste                                            licensed commercial radioactive waste iSpos firm.
==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.


materials generated at UFo production plants onsite for various periods of time. waiting final disposal. It Is                                            The following definitions are used .n this guide:
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
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                                1. Earthen Embankment Retention System means a control the releae of radioactive materials and chemicals                                  watertight system -of one .or more settling and/or to the environment. This regulatory guide describes                                        retention basins including their associated engineered design guidelines acceptable to the Regulatory staff for                                   safety features.
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.


the safe storage of radioactive wastes from plants producing UF,; from uranium mill concentrate.                                              2. Retention Biin means a watertight basin in which liquid wastes are held for any one or more of the  
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.


==B. DISCUSSION==
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.
following reasons: (a) anlysis to verify activity levels permdtting release, (b) evaporation, (c) recycle for UFd production plants which employ the solvent                                      treatment.
 
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
of= *
1gW
,.
mi Ut esym n
I,
ntmn
. 2W45 d1mied 1o*
. Awntoi Iewq Coevmlnion. Wadinston. DX.o 2054 aiietvy Guida mu laod to i*,te and make *Iable la td
,,*bC
Atemion:
lirurtr of Nowastv 8t- eo. Comwoan md W s stions for nat ec9*is to th AMC A*awkno'y sutaf WOW
hmphlltq ectle peers of l
~'madftt be asno t Secrtary tde ConwrAih's npuimtom, to hl*enan UEaklque wad by Us ptf iA
o th
* .
. Wtloqsan.
 
in.
 
oC545.
 
awietlwq Z==
nOblena-tL
aclwi*tho . or 10
l0 ldskganae 0
Am
*wOA
_W.ptom"P5f aolmlnU.ftla.~it GuiesWri Rut autl5 fair sqbtn Mn nillaU
With owan k stat acluired methoce eOW wamiutoa =
=fw frm onC ol ut in The 9jW15 aS blind in otie follawbVn on brlm d-Wleons:
Wad al b cpb fte gra eabes for thve fMding rejulste to ft
~1.


extraction process for purification of urnium mill concentrate produce small amounts of solid radioactive                                      3. Settiing Basin means a watertight basin designed for waste which are uually disposed of by burial onsite.                                        separating sludges and sediments as a layer on the Large volumes of liquid chemical waste containing                                          bottom. The liquid Is disposed of by overflow to the concentratcldis of radioactive material dightly in excess                                  environment, transfer to a retention basin, or solar of those specified In Table II of Appendix B of Part 20                                    evaporation.
Potw Reactor;
6. Prnthjcu Wa ~ ~
~
~
~
2 Renardt WWI
To"luee RADO
7.


are also generated and stored in earthen embankment retention systems. When neutralization and precipitation                                  4. UF,; Production Plant means a plant used for the are successful In reducing the soluble chemical and                                        sole purpose of commercial purification and conversion radioactive concentrations in the liquid waste to an mi        esym    by '.auel'
piricus am b th Crnwas
                                                                                                                                            I,        bilathi ntmn n Wadinston.          2W45s r fVbW
                                                                                                                                                                DX.o. 2054 USAEC REGULATORY GUIDES                                            d1mied of=*1o*
                                                                                                    at Cool  ~ldS . uitis
                                                                                                        1gW        ,.Awntoi    Ut be fttairod lowIewq    Coevmlnion.


lirurtr of Nowastv 8t- eo. Comwoan mdWs t stions                for
===3. PFolk md M ===
                                                              *Iable la td        ,,*bC  Atemion:
I I Fachilti L O
    aiietvy Guidamu laod to i*,te and make          hmphlltq ectle peers of              l                                          ~'madftt        be asno      Secrtary nat    ec9*is to th AMC A*awkno'y sutaf WOW                                      iA
ioml I"0m1h PahW shd clm wiN be awbtd erllv.
                                                                                      in.  o th oC545.                    .*                            . Wtloqsan.


tde ConwrAih's npuimtom,      to  hl*enan    UEaklque      wad  by    Us  ptf awietlwq Z==nOblena-tL                              . or 10 l0ldskganae
ean eovor.O . w toin wd
                                                  _W.ptom"P5f aclwi*tho                          *wOA 0  Am aolmlnU.ftla.~it      GuiesWri  Rut  autl5      fair sqbtn            MnnillaU
4. Envfrvontmwesfting U. Antitrust
                                                        =      =fw frm        onColut in    The 9 jW15 aS blind in otie  follawbVnon brlm d-Wleons:
.
  With owan k stat acluired methoce eOWwamiutoa for        thvefMding rejulste to Wad      al b cpb  ft      fte gra          eabes        ~1.             ~
uls*l mmawnu slid an inflect lown hfforltalln or experlanen.
                                                                                                Potw Reactor;                          6. Prnthjcu Wa ~ ~                  ~
                                piricus am b th Crnwas          ~                            2 Renardt WWI          RADO
                                                                                                              To"luee                  7.


L O        ioml I"0m1h
L. Uetalsk miW PmW Proesil"  
                                                                                              3. PFolk md M I I Fachilti
I
                                                                  .w          wd            4. Envfrvontmwesfting                      U. Antitrust uls*l PahWshd clm wiN be awbtd erllv.                eaneovor.O
                                                            .        toin Ia.  aemora L.  Uetalsk miW PmW   Proesil"
  mmawnu slid an inflect lown hfforltalln or experlanen.


of uranium mill concentrate (USOs) to uranium                        b. The site of the embankment retention system hexailuorido (UP,).                                            should be owned by the licensee and located by survey.
====a. aemora====


and should not occupy the channel of any permanent or
4 of uranium mill concentrate (USOs) to uranium hexailuorido (UP,). 


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
Intermittent watercoune.
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.


c. The pertinent basic design considerations.
d.


Storage areas for solid radioective wafte and            methods of stability analysis, and mininumn factors of rctentiom basins for liquid radioactie waste should be         safety contained in the United States Department or the designed to provide reasonable asasranci that the health        Army, Corps of Enginecrs. Manual EM-1 10-1.PX1.
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.


4 and safety of the public is not endangered during normal        "Engineering and Design Stability of Earth and Roek operation nor as a result of credible accidents. The            Fill Dams," dated April I, 1970,' provide an acceptable following guidelines are generally acceptable to the            basis for the design of a safe settling or retention basin Regulatory staff for the design of storage systems for          structure.
e.


solid and liquid radioactive waste generated it UWe                  d. The Interior of each retention or settling basin production plants:                                              should be lined with an essentially impervious synthetic lining -naterdal designed to prevent seepage. The number I.  Sold Radioactive Waste Storap                              of construction joints and penetrations of the liner should be minimized, and protection from mechanical a. Except for sludges in liquid retention systems,        damap'should be provided.
Provisions should be made to maintain a safe embankment freeboard above the liquid level hI each basin.


storage of sold radioactive wastes should be in                      e. Provisions should be made to maintain a safe appropriate containers approved by the Department of             embankment freeboard above the liquid level hI each Transportation.                                                  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.


b. Storage areas for solid radioactive waste should              E Basin embankments should be stabilized to be used exclusively for storage of natural uranium waste        prevent erosion. Provisions should be made to stabilize generated at the plant, including contaminated                  loose radioactive material produced by evaporation of equipment. Process operations, storage of non-uclear            liquid from the basins.
.
The site should be parmanentlyt protected apinst water runoff from surrounding drainage areas.


material, and other functions not directly a pat of                    . The site should be parmanentlyt protected normal storage operations should be kept separate from          apinst water runoff from surrounding drainage areas.
Grding and/or diversion channels should be provided to enhance natural dra'inge if necessary.


storamp areas for solid radioactive waste.
h. Th site should be provided with a security fence designed to restrict acces; by animals and unauthorized individuals.


c. Features should be provided at storap areas for solid radioactive waste to permit recovery or Impoundment of waste which may be lost from Grding and/or diversion channels should be provided to enhance natural dra'inge if necessary.
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.


h. Th site should be provided with a security fence designed to restrict acces; by animals and C
L
  containers.                                                    unauthorized individuals. The fence should. be d. Storage containers for solid radioactive waste          constructed at a sufficient distance from the system to should be marked or coded to indicate the type and               permit maintenance on the outer .dopes of amount of contained radioactive material.                        embankments. Provisions should be made to discourage e. Materils of construction in storage area for          waterfowl from landing on the pond surfaces.
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.


solid radioactive waste should be fire-resistive or                    L Underbed drainage systems, ground resistivity noncombustible to the maximum extent practicable.                measurement systems, or other seepage assessment Fire-suppression equipment capable of minimizing the            systems should be included in the design. Seepage propaption of res should be provided.                          assessment systems should be located in potential f. Ventilation systems should be provided if the          seepage zones as determined by the hydrology and need for such equipment Is indicated.                          geology of the area. The design of seepage assessment g. Storage area for solid radioactive waste should        systems should provide protection against contamination be designed to prevent unauthorized access to and              by surface waters.
J.


unauthorized removal fiom or diversion of stored                      J. The design should provide for the needs of materlal.                                                      routine system maintenance, the stabilization of the basins when manufacturing operations are terminated,
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.
  2. LIquWd Radioactive Waste Stomp                              and alternative methods of storage if the integrity of any basin Is determined insufficient to retain its contents a. A lined earthen embankment retention system            safely.


is an acceptable liquid storage facility in regions where the evaporation rate is significantly greater than the                IT i docummt is avahble from the Depauinw of fw rainfall. In other regions, the use of these systems is        Army, Olrik of the Clue of Engat               Watsbion, acceptable only for interim storage prior to treatment.        D.C. 20314.
IT i docummt is avahble from the Depauinw of fw Army, Olrik of the Clue of Engat Watsbion, D.C. 20314.


.13-2}}
.13-2 C}}


{{RG-Nav}}
{{RG-Nav}}

Latest revision as of 02:06, 17 January 2025

Guide for Acceptable Waste Storage Methods at UF6 Production Plants
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

of= *

1gW

,.

mi Ut esym n

I,

ntmn

. 2W45 d1mied 1o*

. Awntoi Iewq Coevmlnion. Wadinston. DX.o 2054 aiietvy Guida mu laod to i*,te and make *Iable la td

,,*bC

Atemion:

lirurtr of Nowastv 8t- eo. Comwoan md W s stions for nat ec9*is to th AMC A*awkno'y sutaf WOW

hmphlltq ectle peers of l

~'madftt be asno t Secrtary tde ConwrAih's npuimtom, to hl*enan UEaklque wad by Us ptf iA

o th

  • .

. Wtloqsan.

in.

oC545.

awietlwq Z==

nOblena-tL

aclwi*tho . or 10

l0 ldskganae 0

Am

  • wOA

_W.ptom"P5f aolmlnU.ftla.~it GuiesWri Rut autl5 fair sqbtn Mn nillaU

With owan k stat acluired methoce eOW wamiutoa =

=fw frm onC ol ut in The 9jW15 aS blind in otie follawbVn on brlm d-Wleons:

Wad al b cpb fte gra eabes for thve fMding rejulste to ft

~1.

Potw Reactor;

6. Prnthjcu Wa ~ ~

~

~

~

2 Renardt WWI

To"luee RADO

7.

piricus am b th Crnwas

3. PFolk md M

I I Fachilti L O

ioml I"0m1h PahW shd clm wiN be awbtd erllv.

ean eovor.O . w toin wd

4. Envfrvontmwesfting U. Antitrust

.

uls*l mmawnu slid an inflect lown hfforltalln or experlanen.

L. Uetalsk miW PmW Proesil"

I

a. aemora

4 of uranium mill concentrate (USOs) to uranium hexailuorido (UP,).

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.

.13-2 C