A REPORT ON THE EXAMINATION OF THE
WASTE TREATMENT AND DISPOSAL OPERATIONS
AT THE NATIONAL REACTOR TESTING STATION
IDAHO FALLS, IDAHO
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A REPORT ON THE EXAMINATION OF THE
WASTE TREATMENT AND DISPOSAL OPERATIONS
AT THE NATIONAL REACTOR TESTING STATION
IDAHO FALLS, IDAHO
United States Department of the Interior
Federal Water Pollution Control Administration, Northwest Region
501 Pittock Block
Portland, Oregon 97205
April 1970
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CONTENTS
Page
I. INTRODUCTION 1
II. SUMMARY OF REPORT 6
III. RECOMMENDATIONS FOR WATER POLLUTION
CONTROL 12
IV. HYDROLOGIC SETTING 18
V. LIQUID WASTE MANAGEMENT 21
Burial Ground 21
Central Facilities Area (CFA) 24
Experimental Breeder Reactor II Area 26
Special Power Excursion Reactor Test
Area (SPERT) 28
Chemical Processing Plant Area (CPP) 29
Test Reactor Area (TRA) 35
Test Area North (TAN) 40
Naval Reactor Facility 41
General Operati ng Procedures 45
VI. ATOMIC ENERGY COMMISSION POLLUTION CONTROL POLICY
AND OBJECTIVES AT THE NATIONAL REACTOR TESTING
STATI ON 49
VII. REFERENCES 56
APPENDIX A - Reconnaissance of the National
Reactor Testing Station, Idaho 57
APPENDIX B - Rules and Regulations for Standards
of Water Quality and for Waste Water
Treatment of Waters of the State of
Idaho 62
APPENDIX C - Excerpts from Idaho Drinking Water
Standards 70
APPENDIX D - Excerpts from Rules and Regulations for
the Control of Radiation in the State of
Idaho 87
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TABLES
Table Page
1 SEWAGE TREATMENT AND DISPOSAL SYSTEM
AT THE CENTRAL FACILITIES AREA 25
2 SEWAGE TREATMENT AND DISPOSAL SYSTEMS
AT THE SPERT AREA 30
3 SEWAGE TREATMENT AND DISPOSAL SYSTEMS
AT THE CHEMICAL PROCESSING PLANT AREA 34
4 SEWAGE TREATMENT AND DISPOSAL SYSTEMS
AT THE TEST REACTOR AREA 38
5 SEWAGE TREATMENT AND DISPOSAL SYSTEMS
AT THE TEST AREA NORTH 42
FIGURES
Figure Page
1 RELIEF MAP OF IDAHO SHOWING THE LOCATION
OF THE NRTS AND INFERRED GROUND-WATER
FLOW LINES 20
2 THE NATIONAL REACTOR TESTING STATION AND
RESEARCH AREA 22
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A REPORT ON THE EXAMINATION
OF THE WASTE TREATMENT AND DISPOSAL OPERATIONS
AT THE NATIONAL REACTOR TESTING STATION
IDAHO FALLS, IDAHO
I. INTRODUCTION
Purpose and Nature of the Examination
Representatives of the Federal Water Pollution Control
Administration and the Idaho Department of Health made an
examination of the waste treatment and disposal practices
at the National Reactor Testing Station (NRTS) near Idaho
Falls, Idaho during the period October 15 to 22, 1968. The
purpose of the examination v/as to review and evaluate the
existing waste management operations to determine whether
any additional water pollution control systems or procedures
are necessary or desirable to carry out the national
policy to improve water quality as set forth in Executive
Order 11288, "Prevention, control, and abatement of
water pollution by Federal activities."
The Federal Water Pollution Control Administration
was represented by Dr. Milton Lammering and Richard Velten
from the Technical Advisory and Investigations Office
in Cincinnati, Ohio; and Harold Geren and Jack Sceva of
the Northwest Region, Portland, Oregon. The Idaho Department
of Health was represented by Mr. Melvin D. Alsager.
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An itinerary of the reconnaisance, including the names of
those individuals with whom discussions were held, is presented as
Appendix A to this report. All operating installations were
visited except the Naval Reactors Facility. The representatives
of the Atomic Energy Commission and the site contractors provided
information on the treatment and disposal of liquid wastes and
arranged for field visits to the various installations.
General Description
The National Reactor Testing Station was established in 1949.
It consists of an 894 square miles reservation in Eastern Idaho be-
tween Idaho Falls and Arco that is used by the Atomic Energy
Commission to build, test and operate various types of nuclear re-
actors. The NRTS also has facilities for the processing of spent
reactor fuel elements and the calcining of highly radioactive liquid
waste for long term storage.
More than 40 reactors have been constructed and operated
at the NRTS during the last twenty years. Many of these have now
fulfilled their purpose and have been dismantled, transferred or
put in standby status. These reactors have been constructed and
operated by private firms under contract with the AEC. Plant
investment at the NRTS exceeds $450 million, with a replacement
value exceeding $600 million.
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The various reactor areas are widely dispersed over the
Station. This dispersal provides protection in case of an
accident, but also makes the use of a common water supply and
waste disposal system impractical. The fresh water supply is
obtained from wells located in each ,reactor facility area.
In 1966, ground water with-drawal at the NRTS was about two
billion gallons, or an average of about 5.4 million gallons
per day.
This large water use also results in a large amount of
waste water that must be discharged to the environment. Plant
wastes which are contained in the waste water are of three general
types: the radioactive waste, the chemical or industrial waste,
and the sanitary waste. Waste disposal facilities are located
at each facility area and are operated by the various AEC
contractors.
Any liquid radioactive waste that is not suitable for release
to the environment is transported to the calcining plant and
converted to a solid for long term storage. The "low-level"
radioactive waste is discharged to seepage pits, lagooons and
directly to the underlying aquifer through disposal wells. The
chemical wastes consist chiefly of brines from water-softening
plants and corrosion inhibitors from cooling water systems.
These wastes are also discharged to pits, lagoons and disposal
wells. The sanitary waste consists of the effluent from
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treatment plants and septic tanks. These wastes are dis-
charged to drainfields, sumps, lagoons and disposal wells.
Zones of perched ground water have developed beneath
some of the disposal ponds at the various facilities. These
zones are generally perched on a sedimentary interbed in the
basalt. The development of perched water zones beneath a waste
discharge facility is very desirable from the standpoint of
water pollution control, as it increases the travel time distance,
and the amount of sorption the waste will receive prior to
recharging the regional ground-water body.
The U.S. Geological Survey has been carrying on investi-
gations for the AEC at the NRTS since its inception. They have
supervised the drilling of many thousands of feet of test
wells and have provided a very valuable service in testing,
recording and evaluating geologic and hydro!ogic conditions at
the NRTS. Their reports are the chief source of information
on the effects of waste disposal on water quality at the NRTS.
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NATIONAL POLICY RELATING TO POLLUTION CAUSED BY
THE OPERATION OF FEDERAL FACILITIES
The purpose of the Federal Water Pollution Control Act
is to enhance the quality and value of our water resources
and to establish a national policy for the prevention, control-,
and abatement of water pollution. The policy for all Federal
departments, agencies, and establishments of the Executive
Branch of Government was spelled out in Executive Order 11288
"Prevention, control and abatement of water pollution by Federal
activities." This policy states that Federal establishments
shall provide leadership in a nationwide effort to improve
water quality through prevention control and abatement of water
pollution.
In order to enhance or improve water quality, it is the
responsibility of each Federal activity to establish programs
for the improvement of each waste treatment operation that
contributes waste to the Nations water resources. These
programs should provide for the best possible treatment
methods available so as to demonstrate what can be done to
enhance and improve water quality. In no event should the
operation of Federal activites cause the further degradation
of any of our water resources.
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II. SUMMARY OF REPORT
1. This report reviews and evaluates the existing waste
management operations at the NRTS to determine whether
any additional pollution control systems or procedures
are necessary or desirable to improve or protect water
quality.
2. The report is based on an examination made during October
1968 and on reports and information provided by the Atomic
Energy Commission and the U.S. Geological Survey.
3. The NRTS was established in 1949 for the purpose of testing
nuclear reactors. More than 40 reactors have been constructed
and operated since that time. The NRTS also contains a
chemical processing plant for reclaiming fuel from used
fuel elements and a calcining plant for converting highly
radioactive liquid waste to a solid for long time storage.
4. The NRTS is located near the eastern end of the Snake River
Plain in southeastern Idaho. This plain extends over 8000
square miles and was formed by a thick series of lava flows
that partially filled the ancestral Snake River Valley.
5. The Snake River Plain is underlain by the Snake River
Aquifer, one of the worlds most productive ground-water
reservoirs. This aquifer discharges some 6,000 cubic
feet per second in the Snake River Canyon at the western
end of the Plain.
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6. Recharge conies chiefly from rivers flov/ing out of the
mountains bordering the Plain on the North. These streams
sink into the porous lavas.
7. An estimated 2000 cfs of ground water moves beneath the
Station in a generally southwesterly direction. Part
of this is recharged on the Station and part is moving
through from farther up the Plain.
8. The travel time for ground water to move from the NRTS to
the discharge area in the Snake River Canyon is not known
but is estimated to exceed 100 years.
9. Ground water between the NRTS and the discharge area is
being developed. Travel time from the NRTS to areas of
potential development may be only a few years.
10. The depth to the water table generally increases in a
southwesterly direction across the Station, and ranges
from about 250 feet in the Test Area North to approxi-
mately 600 feet below land surface at the burial ground
near the southwestern corner of the Station.
11. The various reactor areas are widely dispersed over the
894 square mile Station. Each facility has its own water
supply and waste disposal system with the exception that
all high level liquid radioactive waste is processed at
the calcining plant and all solid radioactive waste is
buried in the burial ground or stored underground in
metallic containers.
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12. Liquid wastes generated at the NRTS include radioactive
wastes, chemical wastes and sanitary wastes. 'The low
level radioactive wastes are discharged to seepage pits,
lagoons and disposal wells. The chemical wastes are
discharged to pits, lagoons and disposal wells and the
sanitary wastes from sewage treatment plants are dis-
charged to drain-fields, sumps, lagoons and disposal wells.
13. The Geological Survey has been carrying on investigations
at the NRTS since its inception. They have supervised
the drilling of many thousands of feet of test wells and
have prepared numerous reports describing the geology
and hydrologic conditions at the Station. They have also
performed a valuable service in monitoring the effects of
waste disposal.
14. The National policy for water pollution control by Federal
activities calls for the best possible treatment methods
so as to demonstrate what can be done to enhance or improve
water quality.
15. The Idaho Operations Office of the Atomic Energy Commission
operates on the policy that water quality can be degraded to
the upper limits of the Public Health Standards for drinking
water at the point of first use below their operations.
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16. The burial ground for solid radioactive waste disposal is
located near the southwest corner of the Station. The
waste is deposited in trenches excavated to the top of the
lava surface and covered with silt and clay on a weekly
schedule. There are no observation wells to monitor the
effects of the burial ground on water quality.
17. Low level liquid radioactive waste is discharged to an
excavated pit in the lava at the Experimental Breeder
Reactor Area, into ponds and a shallow well at the Special
Power Excursion Reactor Test Area, directly into the ground-
water supply by a deep well at the Chemical Processing Plant
Area, into ponts at the Test Reactor Area, and the Naval
Reactors Facility, and into the ground water supply by
drilled wells at the Test Area North.
18. Chemical waste is discharged to a pond and shallow well at
the Experimental Breeder Reactor Area, into ponds and a
shallow well at the Special Power Excursion Reactor Test
at the Chemical Processing Plant Area, into a sump and
directly into the ground-water supply by a deep well at
the Test Reactor Area, into ponds at the Naval Reactors
Facility and into ground water supply by wells at the
Test Area North.
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19. Sanitary wastes are discharged to a tile drain system at
the Central Facilities Area, to a sewage treatment lagoon
at the Experimental Breeder Reactor Area, to seepage pits
and drain fields at the Special Power Excursion Reactor
Test Area, into seepage pits at the Chemical Processing
Plant Area, into a seepage pit at the Test Reactor Area,
to a lagoon at the Naval Reactors Facility and into the
ground water supply by disposal wells at the Test Area
North.
20. Chemical and radioactive wastes have degraded the ground
water beneath the NRTS. The tritium is believed to be
entirely contained beneath the Station in that it is de-
caying at a rate approximately equal to the rate of addi-
tion to the water supply. The ground-water supply beneath
the NRTS has been degraded by hexavalent chromimum and
chlorides and an increase in total dissolved solids.
21. There is no information available to show whether the waste
disposal operations at the NRTS have yet migrated beyond
the boundary of the Station.
22. The primary recommendations call for the abandonment of
the practice of burial of radioactive wastes above the
Snake Plain Aquifer, the removal of the existing buried
wastes and studies and programs by the AEC that will lead
to the elimination of the discharge of tritium to the Snake
Plain Aquifer.
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23. Recommendations for additional water pollution control
practices are made to improve and protect the water quality
in the Snake Plain Aquifer. They include elimination of
disposal wells that discharge waste directly into the
ground water supply, the elimination of the use of seepage
ponds for the disposal of chemical wastes, and the improve-
ment of some sanitary waste treatment systems.
24. It is also recommended that the Idaho Operations Office of
the AEC adopt a broader definition of pollution so as to
include any avoidable deterioration in water quality.
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III. RECOMMENDATIONS FOR HATER POLLUTION CONTROL
The National policy for water pollution control calls for
protection and enhancement of the nation's water quality. This
policy applies directly to the valuable ground-water resources
of the Snake Plain Aquifer underlying the National Reactor Testing
Station. Present waste disposal practices have resulted in
localized pollution of the Aquifer within the Station boundaries.
The Federal Water Pollution Control Administration concludes that
present disposal practices are a potential threat to the water
resources of the State of Idaho.
The FWPCA recommends that:
1. Burial Ground
a. The AEC initiate a positive comprehensive program for
abandonment of the practice of burial of radioactively
contaminated solid wastes, including removal of such wastes
presently buried at the site, to a new burial site, remote to
the NRTS, and more hydrologically isolated from any important
ground-water or surface-water resource. To provide
some measure of additional protection to the Snake Plain
Aquifer from radioactive wastes until the above recommen-
dation can be implemented, the following operating
procedures are recommended:
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i. A two to three-foot layer of clinoptilolite be
placed in the bottom of the burial trench to separ-
ate the radioactive waste from the basalt surface.
ii. The radioactive waste material be covered with soil
at the end of each day's disposal rather than on
a weekly basis.
iii. An observation well or wells be constructed in
proximity to the burial ground to monitor the effects
of the burial ground on water quality.
2. Disposal of Tritium Hastes
a. The AEC study alternate disposal methods to lead to the
termination of tritium discharges to the Snake Plain
Aquifer and to surface ponds in order to eliminate the
introduction of tritium to man's environment.
b. The AEC undertake an immediate study to determine the
hydrologic isolation of the lowest, and now unknown,
horizons of the Snake Plain Aquifer or other aquifers
and the technological suitability of these zones to
receive and store tritiated waste water.
c. After such slow-flushing zones have been defined,
that disposal of tritiated waste water into these zones be
initiated after other radionuclides and polluting materials
have been stripped from the waste fluids.
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3. Experimental Breeder Reactor II Area (EBR II)
a. The use of a drilled well for the disposal of demineral-
izer waste be discontinued and the waste discharged to
the chemical waste pond.
4. Special Power Excursion Reactor Test Area (SPERT)
a. The demineralizer waste and the "blow down" waste
at the new Power Burst Facility be discharged to
a surface pont.
b. The septic tank system at the Central Terminal be
replaced with a lagoon or new treatment plant.
5. Chemical Processing Plant (CPP)
a. The AEC expedite the installation of the ion exchange
unit that will "polish" the condensate from the
low-level evaporator.
b. The AEC follow the recommendations of the
U.S. Geological Survey in their 1966 annual report
by constructing the additional observation wells that
are needed to better understand the behavior and fate
of the wastes from the Chemical Processing Plant.
c. The use of the deep well for the disposal of radio-
active waste be discontinued, to eliminate the threat
of an accidental discharge of unacceptable waste
directly into the Snake Plain Aquifer.
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d. The discharge of the chemical waste stream directly
to the Snake Plain Aquifer by the deep disposal
well be discontinued.
Test Reactor Area (TRA)
a. A review of the radioactive liquid waste program be
initiated with emphasis placed on the development of
treatment alternatives that would significantly reduce
the release of the long-lived radionuclides, strontium-90
and cesium-137.
b. The capability to discharge the liquid radioactive
wastes from the "hot" drains directly to the retention
basin without a gross radioactivity analysis being
performed be eliminated. All rad liquid waste from
reactor experiments should be drained to catch tanks
for analysis before discharge to the retention basin.
c. Equipment be installed to reduce the hexavelent
chromium in the blowdown waste from the toxic
hexavalent form to the less toxic trivalent form, or
some less toxic corrosion inhibitor should be used
in the system.
d! The use of the well for disposal of the blowdown
waste directly to the Snake Plain Aquifer be dis-
continued.
e. The discharge of the demineralizer waste stream to
a seepage pond be discontinued.
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7. Test Area North (TAN)
a. The discharge of chemical"wastes directly into the
Snake Plain Aquifer through drilled disposal wells
be discontinued.
b. The discharge of septic tank and trickling filter
effluent directly to the Snake Plain Aquifer through
drilled disposal wells be discontinued.
8. Naval Reactors Facility (NRF)
a. At least one observation well extending to the
regional water table be located immediately
down-gradient from the disposal lagoons.
9. General
a. ID Chapter 0510-01 be modified to include the
national policy for water pollution control and the
Idaho Operations Office's definition of pollution
(ID-0510-004) be broadened to include any deterioration
in water quality as a form of water pollution.
b. The ID Manual Appendix 0510 be amended so that the
Radiation Protection Guide values (Part I) are
identified as those recommended by the Federal
Radiation Council.
c. The characterization of liquid effluents be improved
through expanded analytical analysis of monthly composite
samples to include quantitative identification of
specific radionuclides and a modification of reporting
procedures.
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d. A quality control program be established by the
Idaho Operations Office between the Analytical
Chemistry Branch, AEC Health Services Laboratory, and
the laboratories of the site contractors.
e. The Idaho Operations Office annual report on radio-
active waste disposal operations provide a
comprehensive description of disposal activities
during the year. In particular, emphasis should be
placed on providing an insight to variations in
radionuclide concentrations which occur as the result
of batch-type operations as well as annual average
concentrations.
f. The various chemical waste streams and the water
supplies from the production wells be analyzed
periodically.
g. Sewage plant operators be encouraged to voluntarily
become certified and expand the sanitary waste re-
porting to all sewage treatment installations.
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IV. HYDROLOGIC SETTING
The Snake River Plain covers over 8,000 square miles in
southeastern Idaho. It ranges up to 60 miles in width and
extends for over 200 miles in a southwesterly direction from
St. Anthony. It was formed by a series of lava flows that
partially filled the ancestral Snake River valley. The plain
is bordered on the north by several mountain ranges and inter-
montane valleys, and on the south by the Snake River. It is
an arid region that generally receives less than 10 inches of
precipitation per year and has an evaporation rate that exceeds
three feet per year.
The plain is underlain by the Snake Plain Aquifer, one of
the worlds most productive ground-water reservoirs. This aquifer
which is formed by permeable zones in the lava, discharges some
6,000 cubic feet per second (cfs) in the Snake River Canyon at
the western end of the plain. Recharge comes chiefly from the
rivers flowing out of the northern mountains and sinking into
the porous lavas. These rivers include the Big Wood, Lost River,
Little Lost, Birch Creek, and several smaller streams.
The National Reactor Testing Station is located in the
eastern end of the plain and contains the recharge areas created
by the Lost, Little Lost, and Birch Creek Sinks. Some 2,000 cfs
of ground water (1,300 million gallons per day) moves from
beneath the station in a generally south to southwesterly
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direction (Figure 1). Part of this ground water is recharged
on the Station and part is moving through from farther up the
Plain.
The travel time for ground water moving from the NRTS
to the discharge area in the Snake River Canyon is not known,
but estimates made from ground water velocity tests indicate
that the travel time will probably exceed 100 years.
Ground water between the NRTS and the discharge area is
currently being developed by wells for domestic, irrigation
and industrial supplies. Some ground water has already been
developed immediately down gradient from the NRTS boundary.
The amount of development in this area is expected to in-
crease with the population growth of the area'. The travel
time for ground water to move into these areas from the
NRTS would be only a few years.
The depth to the water table generally increases in a
southwesterly direction across the Station, and ranges from
about 250 feet in the Test Area North to approximately 600
feet below land surface at the burial ground in the south-
west part of the Station. Numerous test wells have been
constructed on the NRTS and detailed information on the
geology and occurrence and movement of ground water is avail-
able in Geological Survey reports.
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STATE OF IDAHO
0 10 20 30 miles
1 Notional Reactor Testing Slat.on
Springs
Approximate boundary of
Generalized ground-water (low
line (from Mundorff end
others, 1964)
vu%
Fig. 1 Relief map of Idaho showing the location of the NRTS (National Reactor Testing Station) and
inferred ground-water flow lines. (From USGS TID_4500)
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V. LIQUID WASTE MANAGEMENT
Each program function area at the NRTS is responsible for
the treatment and disposal of the liquid wastes generated at
the area facilities. Consequently, waste management procedures
vary from facility to facility. The one exception to this
pattern of decentralization is the management of high level
radioactive wastes (on the order of 10 uc/ml of gross beta-
gamma radioactivity). All high-level wastes are processed
in the Waste Calcining Facility at the Chemical Processing
Area.
The following sub-sections describe the current waste
treatment and disposal practices at each of the major NRTS facili-
ties and recommendations for additional water pollution control
practices to improve and protect the ground-water resources in
the Snake Plain Aquifer. Figure 2 shows the location of the
various facilities at the NRTS.
Burial Ground
Description and Operation
The burial ground for solid radioactive waste is located
southwest of the Central Facilities in an area underlain with
from five to twenty feet of silt and clay. This large
variation in thickness is due to the irregular basalt surface
that underlies this silt and clay deposit. The disposal trenches,
which are about five to six feet in width, are excavated to the
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^ v r.--
^ K \-f?^=&
•Arco VS.-.-V >^
OPAX ' "*
• EBRI
r ZPRH.AFSR
%Buriol Ground
* Atomic City
Big Southern
Butte
EIPLJNATICH
TABULATION OF FACILITIES AT THE SAIIiKAL REACTOR TESTING STATION
Kane Abbreviation
Advanced Test Reactor ATR
Argonne Fast Source Reactor AFSR
Army Reactor Area ARA
Boilinj later Reactor BORAX
Central Facililies Area CFA
Engineering Test Reactor ETR
Experimental Beryl Iiui Oxide Reactor EBOR
Experimental Organic Cooled Reactor EOCR
Experimental Breeder Reactor No I E6R-1
Experimental Breeder Reactor No. 2 E8R-S
Field Engineering Test Facility FET
(as Cooled Reactor Experiment CCRE
Name Abbreviation
Idaho cnenicsl Processing Plant ICPP
Initial Engineering Test Facility IET
loss ol Fluid Test Facility IOFT
laterials Testing Realtor KIR
Naval Reactors Facility NDF
Organic Moderated Reactor Experiment ONRE
Special Power Excursion Reactor Test SPERT
Test Area Nortb TAK
Test Reactor Area TKA
Transient Reactor Test Facility TREAT
Zero Power Reactor No. 3 2PR-III
Fig. 2 Map of the NRTS showing the locations of facilities.
(From TID 4500)
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basalt surface. The walls of the trenches stand vertical, with
little evidence of caving. The solid waste is deposited in the
trench with some waste lying directly on the basalt surface.
The waste is covered with silt and clay on a weekly schedule.
The placement of solid radioactive waste directly on the
basalt surface and the periodic covering of the waste creates
a threat to ground-water quality. Rain, which does occasionally
occur in the area (av. 8.2 inches per year), would fall directly
on the radioactive waste and then flow into the underlying lavas.
The amount of radioactivity that could be picked up by this
water is not known, but there would be little or no sorption of
the dissolved solids prior to flowing into the lavas.
The nearest observation well located down gradient from
the burial ground is some three miles away and is believed
effected by local recharge from flood control ponds and is not
considered a satisfactory well to monitor the effects of the
burial ground.
The Snake River Plain is not a desirable location for any
burial ground for radioactive (or toxic) wastes because of the
importance of the underlying ground-water supply. Even though
the burial of radioactive waste may not be causing pollution at
this time, climatic changes in the future could substantially
alter this situation (Plutonium 239 that is being buried at
the NRTS has a half-life of 24,000 years). Ideally a burial
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ground for radioactive or toxic wastes should be located some-
where in the Great Basin, in a subbasin that has little or
no surface or subsurface outflow and is underlain by fine-grained
sedimentary materials.
Recommendations
It is recommended that a layer of clinoptilolite of high
sorbic capacity be placed between the waste and the underlying
lava to permit additional sorption and that the waste bo covered
on a daily basis to prevent rainfall from falling directly on the
waste.
In order to observe whether a pollution threat is being
created by the operation of the burial ground, an observation
well should be drilled at the burial ground.
Central Facilities Area (CFA)
Radioactive Wastes
Radioactive wastes from the laundry and analytical labora-
tories of the Health Services Laboratory are discharged to the
sanitary waste system.
Sanitary Haste Treatment and Disposal System
The sanitary waste system consists of a primary settling
tank, a digester, a trickling filter, a secondary settling basin,
and an effluent chorination tank. The effluent is discharged
to a subsurface tile drain system in the gravelly soil.
A summary of the waste treatment and disposal system is
given in Table 1.
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TABLE 1
SEWAGE TREATMENT AND DISPOSAL SYSTEM
AT THE CENTRAL FACILITIES AREA
People Estimated Flow Design Capacity
(no.) (gal/day) (gal/day)
Equipment and Size
1,050
110,000
(including
laundry)
28,800 min.
122,400 avg.
302,400 max.
Digester--35,600 gal.
(4800 ft3)
Trickling Filter--
0.27 acre-feet
Primary Clarifier--
27,000 gal. (3620 ft3)
Secondary Clarifier--
27,000 gal. (3620 ft3)
Drying Beds--(3060 ft3)
Subsoil Disposal--
40,000 ft^ area
(Chlorinator)
Data Source: AEC Report IDO 12066 "Liquid Haste at the National
Reactor Testing Station, Idaho" July 1968.
Plant operation records from January through September 1968
indicate that an overall BOD reduction exceeding 80 percent is
attained. Effluent BOD, which ranged from 1.5 to 29 mg/1, was
normally around 4.0 mg/1. The plant receives some low-level radio-
active wastes which concentrate in the sludge and on the trickling
filter. The dried sludge is disposed of at the burial ground.
The effluent is sampled daily to determine the net concentration
of radioactive materials discharged to the drain field. The plant
effluent is chlorinated just prior to disposal.
No operations problems were reported at the time of the visit.
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Recommendations
The waste treatment plant at the Central Facilities Area
appears to be operating satisfactorily and no recommendations are
being made at this time except for voluntary certification of the
operator.
Experimental Breeder Reactor II Area (EBR II)
The facilities in this area include the Experimental Breeder
Reactor II {EBR II), the Transient Reactor Test Facility (TREAT),
the Zero Power Plutonium Reactor (ZPPR), and the Fuel Cycle
Faci1i ty.
Radioactive Hastes
The radioactive waste is collected in storage tanks, the
acidity is neutralized, and the waste discharged to a covered disposal
pit that has been excavated into the lava. An evaporator is main-
tained in a standby condition to handle waste that is not suitable
for discharge to the disposal pit. If the waste is not suitable for
discharge; it is concentrated by evaporation and handled as high
level waste.
Chemical Wastes
The cooling tower "blowdown" is chemically treated to reduce
the hexavalent chromium to the trivalent state. This waste stream
is discharged to a large excavated pond where it is concentrated
by natural evaporation. Plant operators at this facility reported
that the pond is effectively sealed and that there is little or no
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27
leakage to the ground. The waste stream going to this pond was very
small at the time of our visit. The Idaho Operations Office reports
that the lagoon receives approximately 85,000 gallons per week of
cooling tower blowdown waste, and 350,000 gallons per week of cool-
ing and miscellaneous waste (9). If the discharges are of this
magnitude, some of the waste must be infiltrating into the ground as
the pond is not of sufficient size for total disposal by evaporation.
The demineralizer waste is discharged to a shallow well drilled
into the lavas. Hhile his subsurface disposal of chemical waste may
bea minor threat to water quality, every waste stream that reaches
the water table contributes to ground-water degradation.
The open ditch that carries "blowdown" waste and other chemical
wastes from the EBR II facility to the evaporation pond flows adjacent
to Well No. 2. Any leakage from this ditch to the well would result
in an above-average sulfate and chromium content in the well water.
Sanitary Waste Treatment and Disposal
The EBR II facility is served by a 200 x 200 foot lagoon, and
the TREAT facility is served by two septic tanks. The lagoon receives
wastes from about 500 people. Each septic tank serves six people.
The lagoon was in excellent condition at the time of inspection.
According to the maintenance man, it does not normally overflow. It
is drawn down by discharging to a seepage area before cold weather
arrives and allowed to fill under ice-cover condition in the winter.
Recommendations
1. The use of drilled well for the disposal of the demineral-
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28
izer waste should be discontinued, and the waste discharged
to the chemical waste disposal pond. If a further study
should indicate that there is substantial subsurface leak-
age from this pond, methods of reducing the leakage should
be considered so as to prevent this pond from being a source
of ground-water pollution.
Special Power Excursion Reactor Test Area (SPERT)
The reactors in this area are the SPERT II (standby), SPERT III
(standby), SPERT IV (operating), and the Power Burst Facility (PBF)
(under construction).
Radioactive Haste
The waste at SPERT IV is filtered (microfilter), collected in
storage tanks and disposed of to a surface seepage pond. At the
PBF the radioactive waste will be collected in a storage tank and
subsequently discharged to a permeable zone in the lavas at a
depth of 74 to 104 feet.
Chemical Hastes
Demineralizer waste at SPERT IV is discharged to the radio-
active waste seepage pond. At the PBF, the cooling tower "blew/down"
will be chemically treated to reduce the hexavalent chromium to
the trivalent state. This waste stream and the demineralizer
waste will be discharged to a shallow well.
Sanitary Haste Treatment and Disposal
The sanitary waste treatment and disposal systems at the SPERT
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29
area are described on Table 2. No problems with the operation of
these treatment systems was reported, but the septic tank at the
Control Terminal and Pit Building is operated at about three times
the design capacity.
Recommendations
1. Eliminate the proposed disposal well for the demineralizer
waste at the PBF and discharge the waste to the desert
through the "blowclown" waste disposal ditch.
2. In view of the relatively high number (75) of employees at
the Control Terminal area and the fact that the septic tank
serving the area is only one-third the recommended size,
the construction of a lagoon similar to that at EBR II, or
a treatment plant should be considered to replace the tank.
Chemical Processing Plant Area (CPP)
The major facilities in this area are the Idaho Chemical
Processing Plant, the Waste Calcining Facility, and the Fuel Element
Storage Facility (water-filled basin).
Radioactive Waste
Low-level ( 10~2 uc/ml) and intermediate level (10~2 to 10^ uc/ml)
radioactive wastes generated at the CPP is processed by an evaporator.
The evaporator condensate is collected in storage tanks and dis-
charged after analysis directly to the Snake Plain Aquifer through
a 595-foot well. The radwaste is diluted with plant cooling water
just prior to disposal.
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TABLE 2
SEWAGE TREATMENT AND DISPOSAL SYSTEMS
AT THE SPERT AREA
30
People
(No.)
Estimated
Flow
(gal/day)
Design
Capaci ty
(gal/day)
Sewage Treatment Equipment & Size
75
2500
10
300
100
50
1500
16
500
Control Terminal
and Pit Building
800 Septic tanks,
seepage pit
Temporary
Engineering Office
Building
333 Septic tank
seepage pit
Spert II
415 Septic tank,
seepage pit
Spert III
415 Septic tank,
seepage pit
Spert IV
665 Septic tank,
seepage pit
Temporary
Construction Office
1000 Septic tank,
seepage pit
PER-PBF-620
(Proposed)
800 Septic tank
Two septic tanks--
600 gal.ea. Seepage
pit—3380 gal
(452 ft3)
Septic tank--500 gal
Seepage pit--
1030 gal (138 ft3)
Septic tank--625 gal
Seepage pit-1180 gal
(157 ft3)
Septic tank--625 gal
Seepage pit--
1180 gal (157 ft3)
Septic tank--! ,000
gal seepage pit--
3000 gal (401 ft3)
Septic tank--
1000 gal.
Septic tank--800
gal. Disposal to
drainfield
Data Source:
AEC Report IDO-12066 "Liquid Waste at the National
Reactor Testing Station, Idaho", July 1968.
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31
One of the reasons for utilizing deep-well disposal was re-
ported to be the fear that a perched water zone could develop from
near-surface disposal that would jeopardize the subsurface storage
tanks used for the high level liquid radioactive waste and solids
from the calciner.
There is no liquid waste stream from the Waste Calcining Plant.
Water from the storage basin at the Fuel Element Storage Facility is
continuously circulated through two clinoptilalite filters in series.
There is no direct discharge of water to the ground at this facility.
The disposal of tritium, the radionuclide accounting for approx-
imately 96 percent of the gross beta-gamma activity discharged
annually at the CPP, has received considerable attention by the AEC
and the Geological Survey as to its impact on the subsequent uses
of the Snake Plain Aquifer. For the period of 1961 through 1966, the
tritium plume remained well within the site boundaries of the NRTS--
the farthest southward progression of the estimated "zero" contour
lying in the vicinity of Highway 20. It is probable that tritium in
the regional ground water has reached a quasi-steady-state condition
with there being little likelihood for more extensive spreading of
the plume than previously observed unless tritium releases increase.
During the discussions with representatives of Idaho Nuclear
Corporation, the AEC contractor that operates the Chemical Processing
Plant, the reconnaissance team was informed that a proposal calling
for the passage of the condensate from the low-level evaporator
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32
through an ion exchange unit had been submitted to the Atomic Energy
Commission (its installation has been approved by the AEC s'-ubsequent
to our visit). If the anticipated decontamination factor of 100 is
obtained, this additional treatment should lower the effluent strontium-
90 concentration from 1 - 3 x 103 pc/1 to <100 pc/1, and the total
amount of radioactivity discharged, exluding tritium, to consider-
ably less than one curie per year. This proposal constitutes a
positive attempt aimed at minimizing the release of radioactive
materials.
The discharge of radioactive waste directly to the Snake Plain
Aquifer has not created a problem in the use of the ground-water
supply. The practice of discharging radioactive waste directly into
the water supply, however, does create a potential threat to the
valuable resource. The threat comes from continued use of the
aquifer for the disposal of radioactive wastes and from the possi-
bility of an unintentional or accidental release of unacceptable
waste to the disposal well. Such a release occurred on December 9,
1958, when waste from an unknown source in the CPP resulted in the
discharge of waste to the disposal well that had a concentration
of strontium-90 that was 225 times the maximum permissible concen-
tration (7).
Chemical Wastes
Chemical wastes at the CPP comes chiefly from the water treat-
ment plant. This waste, which is principally sodium chloride and
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33
sodium sulfate, is diluted with the plant cooling water and the
radioactive waste and is discharged to the deep disposal well. The
maximum concentration of chloride in the combined waste stream going
to the well was reported not to exceed 375 mg/1 (9), but averages
well over 200 mg/1. This discharge has caused a marked increase in
the chloride content of the ground water supply. The chloride con-
tent at the CPP Well No. 2 has increased from 10 to 42 mg/1 from
1951 to 1968, and at the Central Facilities Well No. 2, from 23 to
58 mg/1 from 1956 to 1968. The desirable limit for chloride in a
public water supply recommended by the National Technical Advisory
Committee on Public Water Supplies (10) is "less than 25 mg/1."
Sanitary Waste Treatment and Disposal
The sanitary waste treatment and disposal systems in the
Chemical Processing Plant Area are described in Table 3. The treat-
ment plant was operating satisfactorily. Records on plant opera-
tions from January through September 1968 indicate that an overall
BOD reduction of 80 percent is attained. Effluent BOD, which ranged
from 4.5 to 25 mg/1 during the period, was normally about 11 mg/1.
No operational problems were reported in either the treatment plant
or the septic tanks.
Recommendations
1. The Atomic Energy Commission should expedite the installa-
tion of the ion exchange unit which will "polish"
the condensate from the low-level waste evaporator.
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TABLE 3
SEWAGE TREATMENT AND DISPOSAL SYSTEMS
AT THE CHEMICAL PROCESS IUG PLANT AREA
34
People
(No.)
Estimated
Flow
(gal/day)
Design
Capaci ty
(gal/day)
Sewage Treatment
Equipment and Size
310 26,000 59,000 (c)
Imhoff Process,
Digester Chlorination
basin, Trickling filter
Drying Bed, and
Seepage Area (closed
underground)
<20
632 (a) Calciner Septic
Tanks plus Deep
Seepage Cesspool ,
DPP-633
575 (b) Fuel Storage Building
Septic Tank with
Open Bottom Dry well,
CPP-603
360 (b) Limited Area Control
House (CPP-609)
Septic Tank, Seepage
Cesspool
360 (b) Waste Disposal
Building, Septic Tank,
Seepage Cesspool
(a) Design V = 1125 + 0.75 (gal sewage).
(b) Sewage tanks designed to hold 1-1/2 days
(c) Imhoff retention time of 1.38 hour.
flow.
Imhoff Tank--3400 gal
(457 ft3)
Trickling Filter--
0.0678 Acre Feet
Final Settling--
2580 gal. tank
Chlorination Tank--
450 gal (60 ft3)
Modified Tank--
570 gal (77 ft3)
Seepage Area--
(5150 ft*)
Sludge Drying Beds--
730 ft3
Two Septic Tanks —
Each Tank--800 gal.
Cesspool--8' x 8' x
16' deep
Septic Tank—860 gal.
Dry well--5' Diameter
Septic tank--540 gal
Seepate Cesspool--6'
Septic Tank--540 gal
Seepage Cesspool
Data Source:
AEC Report IDO 12066, "Liquid Waste at the National
Reactor Testing Station, Idaho", July 1968.
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35
2. As suggested by the U.S. Geological Survey in their most
recent annual report (2, page 73), the additional observation
wells needed to resolve any unanswered questions regarding
the behavior and fate of wastes from the Chemical Processing
Plant should be drilled. The final complement of observa-
tion wells should be capable of accurately defining the
area! extent and depth(s) of the tritium plume.
3. To eliminate the possibility of an accidental discharge of
unacceptable radioactive waste directly to the Snake Plain
Aquifer, the use of the deep well for the disposal of radio-
active waste to the Snake Plain Aquifer should be discon-
tinued.
4. The discharge of the chemical waste directly to the Snake
Plain Aquifer through the deep disposal well should be dis-
continued.
Test Reactor Area (TRA)
The Test Reactor Area (TRA) is the world's largest and most
advance nuclear test complex containing the Materials Testing
Reactor (MRT), the Engineering Test Reactor (ETR), and the Advanced
Test Reactor (ATR).
Radioactive Waste
The radioactive wastes at the TRA are classified as "hot" or
"warm" with separate collection systems maintained for each type.
Hot wastes originate from the reactors and reactor experiments,
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36
whereas the warm wastes originate from floor drains and reactor
sumps. These radioactive wastes are transferred from collection
tanks to a concrete retention basin. The waste from the basin is
discharged to ponds excavated in the gravelly alluvium that over-
lies the lava in this area. No treatment is provided with the
exception that a waste batch can be trucked to the Waste Calcining
Facility if such action is deemed necessary.
Leakage from the disposal ponds has created an extensive
perched ground-water zone beneath the area. Recharge to the
regional water table comes from downward percolation of the perched
water. Sorption in the soil removes most of the radioactive nuclides
in the waste except for tritium. The removal of radioactive nuclides
and other ions is "temporary" in that the removal will occur only
until equilibrium is reached.
Chemical Hastes
Cooling tower "blowdown" from the large cooling towers at the
TRA is discharged directly to the Snake Plain Aquifer through a
1200-foot disposal well. This waste is the principal source of
the hexavalent chromium that is introduced into the ground water
at the NRTS. It now averages about 175 gpm and will be increased
by about 300 gpm when the new test reactor is put into operation.
The hexavelent chromium in this waste was reported to range from
about 4 to 5 mg/1. This waste stream constitutes one of the most
serious threats to ground-water quality at the NRTS. At places
around the TRA, the hexavalent-chromium in the ground water
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37
already exceeds Public Health Service standards for drinking water
(0.05 nig/1).
The deinineralizer waste is discharged to a pond excavated in
the gravelly alluvium. The waste, which is derived from sulphuric
acid, sodium hydroxide, and sodium chloride, now averages about
3,500,000 gallons per month. Total dissolved solids in the ground
water have increased from about 250 mg/1 prior to disposal, to
850 ing/1 after disposal was started. This waste stream is also a
serious source of ground-water pollution.
Sanitary Haste Treatment and Disposal
The sanitary waste treatment and disposal systems in the Test
Reactor Area are described in Table 4.
Plant operation records from January through September 1968
indicate that BOD reduction in excess of 80 percent is attained.
Effluent DOB, which ranged from 4.5 to 37 mg/1 during the period,
was normally about 14 ing/1. The treatment plant effluent is dis-
charged to two seepage ponds. The system was operating satis-
factorily when viewed and no problems were reported. A laboratory
building in the area is served by a 600-gallon septic tank.
Recommendations
In comparison to other facilities, the greatest on-site release
of radioactivity from liquid waste disposal occurs at the Test
Reactor Area. Yet the TRA has the distinction of being the only
area without treatment capabilities for liquid radioactive wastes;
other than being able to truck batches of "hot" waste to the chemi-
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38
TABLE 4
SEWAGE TREATMENT AND DISPOSAL SYSTEMS
AT THE TEST REACTOR AREA
People
(No.)
Estimated
Flow
(gal/day)
Design Capacity
(gal/day)
Equipment and Size
860
27,000
59,000 (a)
Imhoff Tank-3400 gal (457 ft3)
Trickling Filter--0.0678 Acre
Feet
Final Settling--24BO gal. tank
(331.5 ft3)
Chlorination Tank--450 gal.
(60 ft3)
Modified Tank--570 gal
(77 ft3)
Seepate Area—7750 ft2
Sludge Drying Beds--730 ft3
(a) Inihoff retention time of 1.38 hours.
Data Source: AEC Report I DO 12066, "Liquid Waste at the National
Reactor Testing Station, Idaho", July 1968.
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39
cal plant. Similarly, this is the only area in which the discharge
of chromate-bearing cooling water blowdown is still permitted.
The Naval Reactors Facility has replaced chromate with a
polyphosphate and at the Experimental Breeder Reactor II, the
hexavalent chromimum is reduced to the trivalent form.
1. A review of the radioactive liquid waste program at the
TRA should be initiated with emphasis placed on the de-
velopment of treatment alternatives that would significantly
reduce the releases of the long-lived radionuclides,
strontium-90 and cesium-137.
2. The capability to discharge radwastes from the "hot" drains
directly to the retention basin without a gross radio-
activity analysis being performed should be eliminated. All
wastes from reactor experiments should be initially drained
to catch tanks for analysis.
3. Equipment should be installed to reduce the hexavalent
chromium in the blowdown waste from the toxic hexavalent
form to the less toxic trivalent form, or some less toxic
corrosion inhibitor should be used in the system.
4. The use of the well for the disposal of the blowdown
waste directly to the Snake Plain Aquifer should be dis-
continued.
5. The discharge of the demineralizer waste stream to a seep-
age pond should be discontinued. Possibly waste reactor
heat could be utilized in an evaporation pond to increase
the evaporation rate of this waste stream.
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40
Test Area North (TAN)
The bulk of the activity at TAN occurs in the centralized
Technical Services Facility. Other testing facilities are the
Initial Engineering Test Facility (IET), The Low Power Test Facility
(LPTF), the Field Engineering Test Facility (FETF) at which the
reactor experiment, Loss-of-Fluid Test (LOFT) is scheduled for test-
ing. Each facility has independent systems for the treatment and
disposal of liquid wastes.
Radioactive Wastes
Radioactive waste at the Technical Services Facility is col-
lected, evaporated, and then discharged directly to the Snake Plain
Aquifer through a drilled disposal well. No radioactive wastes are
generated at the Initial Engineering Test Facility and the Low Power
Test Facility. Operational procedures for the handling and disposal
of liquid radioactive wastes at the LOFT site have not been estab-
lished. However, there will be at least one 100,000 gallon holding
tank provided for this purpose.
Chemical Wastes
Chemical wastes which consist chiefly of demineralizer wastes
are discharged directly to the Snake Plain Aquifer through drilled
disposal wells. A 1968 chemical analysis of ground water from
Well No. 2 by the U.S. Geological Survey in the TAN area shows the
ground water as having a phenol content five times the maximum per-
missible limit for public water supplies. The location of the waste
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41
stream or streams discharging phenols to the ground is not known.
Sanitary Waste Treatment and Disposal
Table 5 describes the sanitary waste treatment and disposal
systems at the TAN area. The disposal wells discharge the trickling
filter effluent and the effluent from the septic tanks directly into
the Snake Plain Aquifer. The reason given for the use of drilled
wells for sewage disposal is that the relatively tight soils in the
area makes the use of drain fields troublesome.
Recominendajions
1. The discharge of chemical wastes directly into the Snake
Plain Aquifer through drilled disposal wells should be
discontinued. The relatively tight soils in this area
should facilitate the construction and operation of evap-
oration ponds for these wastes.
2. The discharge of septic tank and trickling filter effluent
directly to the Snake Plain Aquifer through drilled disposal
wells should be discontinued. Lagoons, similar to the
lagoon at the EBR II should prove to be an effective sub-
stitute to well disposal.
Naval Reactors Facility (NRF)
The major installations comprising the NRF are the Submarine
Prototype (S1W), the Large Ship Reactor (AIM), the Expended Core
Facility (ECF), and the Natural Circulation Reactor (S5G). The
Expended Core Facility, operated for the Commission and the U.S.
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42
TABLE 5
SEWAGE TREATMENT AND DISPOSAL SYSTEMS
AT THE TEST AREA NORTH
People
(No.)
Estimated
Flow
(gal/day)
Design
Capaci ty
(gal/day)
Sewa ge
Treatment
Equipment
and
Size
410 16,000 (b) 59,000 (a)
TAN/TSF
Administration
Area
Imhoff Process, Chiori-
nation Basin, Trickling
Filter, Sludge Drying
Beds, Disposal Well
Imhoff Tank--3400 gal
(457 ft3)
Chlorinator--560 gal
(75 ft3)
Trickling filter--
0.067 Acre Feet Sludge
Bed—835 ft3
10
300
30
1,000
35
1,000
2,000 (b)
designed
for 50
people
4,000 (b)
designed
for 100
people
IET AREA
Septic Tank Chiorina-
tion Building, Filter
Bed, Disposal He.ll
STEP AREA
Septic Tank Chiorina-
tion Building, Dis-
posal Hell
LPT & EBOR AREAS
6,000 (b) Septic Tank Chiorina-
tion Building, Filter
Bed, Disposal Hell
(a) Imhoff retention time of 1.38 hour.
(b) 40 gallons per day per person for design capacity
(TRA'area figures).
(c) Design V = 1125 + 0.75 (gal. sewage).
Septic Tank—2800 gal
(c) Filter Bed—
265 ft3 (Sand)
Septic Tank--4200 gal
(c)
Septic Tank--5600 gal
(c) Filter Bed
735 ftj
Data Source:
AEC Report, IDO 12066, "Liquid Haste at the NRTS, Idaho",
July 1968
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43
Navy by Westinghouse Electric Corporation, handles the dismantling
and analysis of expended cores from nuclear ships preparatory to
fuel reprocessing. Consequently, this facility has the greatest
potential for the generation of liquid radioactive wastes. As the
Naval Reactors Facility was not visited during our examination,
the following information was provided by the Idaho Operations Office.
Radioactive Wastes
Liquid radioactive wastes generated at each of the three reactor
plants are normally collected, analyzed for radioactivity and discharged
to either an open or covered leaching pit. In the event of abnormally
high radioactivity levels, these wastes can be routed through a bank
of demineralizers. Liquid radioactive wastes from the ECF are
segregated and processed by evaporation or discharged to retention
basins depending on the gross radioactivity level. After sampling
and analysis the ECF wastes are pumped from the retention basins to
the leaching pits.
Preliminary work directed toward reducing the total activity
discharged to the environment was started in 1966. The changes
and/or modifications that are being made in the liquid radioactive
wastes management practices include:
1. Treatment of the ECF pit skim water to remove the radio-
activity with return of the treated water for reuse. It
is envisioned that this change will result in a major
reduction in the volume and radioactivity of the liquid
waste discharged at the NRF.
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44
2. Segregation of liquid wastes to eliminate processing
large volumes of waste. This will also prevent the
radioactive contamination of non-radioactive liquid
wastes.
3. Installation of filtration equipment to remove suspended
radioactive materials prior to discharge to the leaching
beds.
Actual work on modifying the systems at NRF in accordance with the
above is scheduled to commence early in calendar year 1970.
Although radioactivity analyses are performed on the wastes
discharged to the leaching beds, there are no observation wells
to monitor the regional ground water in the area down-gradient
from the disposal beds.
Chemical Wastes
Cooling tower blowdown, spent demineralizer regenerates, and
other miscellaneous wastes are discharged via culverts to a
drainage ditch located west and north of NRF. This ditch serves as
a seepage system. The excess flow is discharged to a depression on
the desert. A polyphosphate compound has replaced chromates as the
corrosion inhibitor in the cooling water system.
Sanitary Waste Treatment and Disposal
The 1968 compilation of liquid waste at the NRTS (9) reports
that the sanitary waste is discharged to a lagoon that has been con-
structed with an impervious bottom. The overflow from this lagoon
goes to a second lagoon for further aerobic digestion. The overflow
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45
from the second lagoon flows to a drain ditch and is discharged to
the desert.
Recommendations
1. At least one observation well extending to the regional
water table should be located immediately down-gradient
from the disposal lagoons. Periodic analysis of water from
such a well would provide information on the pollution
threat from the NRF operation.
General Operating Procedures
Analysis of Radwaste Effluents
Compliance with the concentration limits for the discharge of
liquid wastes is generally determined by obtaining a representative
sample of the batch scheduled for release and performing gross beta
and gamma analyses. Supplementing this procedure, daily proportional
samples of the effluents containing radionuclides are collected at
the Test Reactor Area, and the Chemical Processing Area. Gross beta
and gamma analyses are performed on these samples. Monthly propor-
tional composite samples are also prepared from the batch samples or
daily proportional samples. These composite samples are analyzed for
gross alpha radioactivity, gross beta-gamma radioactivity, tritium,
and the major gamma-emitting radionuclides (quantitatively).
Recommendations
1. As part of the indicated revision to be made in ID Manual
Appendix 0510, it is recommended that Radiation Protection
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46
Guide Values (Part I) be clearly defined as referring
to the concentration limits specified in Appendix B
(Table II) of AEC Regulation 10CFR20.
2. Analytical analysis of a monthly composite waste sample
should include the following:
a. Continued determination for gross alpha and beta
activity:
b. Quantitative identification of specific radio-
nuclides including tritium, manganese-54, cobalt-
58 and 60, zinc-65, strontium-89 and 90, ruthenium-
103 and 106, iodine-131, cesium-137, cerium-141 and
144, promethium-147, and those radionuclides respon-
sible for the alpha activity. It is recognized that
each of these radionuclides will not be major con-
stituents in the liquid wastes from each installation.
The decision to not conduct the analysis for a given
radionuclide should be based on analytical data which
demonstrates its absence or relative non-importance;
frequent analytical checks should be performed to
ensure the continued validity of such a decision.
In much the same manner that specific radionuclides
may be deleted from the above list to meet the
monitoring requirements at a specific installation, it
may be necessary in some cases to add other radio-
nuclides not listed (for example, iodine-129 and/or
radium-228).
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47
c. Specific conductivity, pH, and determination of
total dissolved solids;
d. Quantitative identification of the major inorganic
constituents (cations and anions).
3. Relative percentage(s), as required on the AEC Radioactive
Liquid Haste Report (form ID-111) is based on the total
activity computed by summing the activity results for the
identified radionuclides. If it is unsure that all the
radionuclides have been identified, the total so calculated
should be checked against a similar total computed from
gross counting procedures. The significance of tritium
should also be reflected in the computation of relative
percentages.
4. A quality control program should be established between the
Analytical Chemistry Branch, AEC Health Services Laboratory,
and the laboratories of the site contractors. Such a pro-
gram would appear to be essential to ensuring the procurement
of reliable data on liquid radioactive waste releases and
compliance by the contractors with established effluent
concentration limits.
5. The annual report on radioactive waste disposal operations
should present a comprehensive description of disposal
activities during the subject year. Sufficient data and
narrative should be presented so as to provide the in-
formed reader with an insight to variations in radionuclide
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48
concentrations occurring as the result of batch-type oper-
ations as well as annual average concentrations. Corres-
pondingly, the annual report should include the following
information for each area on a monthly basis.
a. Number of days of radioactive waste discharge;
b. Radioactive waste volume prior to dilution and
dilution factor if the radwaste is combined with
industrial wastes and/or sanitary sewage;
c. Total volume of combined waste (if applicable);
d. Analytical results for monthly composite sample.
6. During our survey at the NRTS it was found that there was
no chemical monitoring of the waste and no periodic moni-
toring of the water supplies except for radioactivity,
bacteria, and chromium. It appears desirable in light of
the large amount of chemical waste going to the ground that
the various chemical waste streams and water supplies be
periodically analyzed for total dissolved solids, con-
ductivity, chlorides and pH. Any material change in waste
characteristics or in water quality could probably be"
detected by these tests and could be followed by more
complete analyses if a change occurred.
7. Encourage the sewage treatment plant operators to volun-
tarily become certified and expand the sanitary waste
reporting to all sewage treatment installations.
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49
VI. ATOMIC ENERGY COMMISSION
POLLUTION CONTROL POLICY AND OBJECTIVES
AT THE NATIONAL REACTOR TESTING STATION
The policy of the Idaho Operations Office of the Atomic Energy
Commission relating to the management and control of v/aste materials
at NRTS is presented in ID Chapter 0510 a supplement to AECM Chapter
0510, "Prevention, Control5 and Abatement of Air and Water Pollution
by Federal Activities". Specific policy requirements are to (ID-
0510-02):
1. Minimize waste materials at the source by diligent and
efficient operations;
2. Disperse waste materials to the environment only when
this can be done without adverse effects and within pre-
scribed limits;
3. Stabilize and maintain control of waste material.
The Idaho Operations Office defines pollution as "the presence
in the environment of substances in quantities which are injurious
to human, plant, or animal life or to property" (ID-0510-004), and
operates Bunder the policy that chemical v/aste can be discharged to
the regional ground-water supply to the extent that the receiving
water quality, at the point of first use, does not exceed the
recommended upper limit of the drinking water standards of the
Public Health Service. Under this policy a severe deterioration in
ground-water quality beneath the NRTS and a deterioration in water
quality outside the NRTS could occur without being interpreted as
water pollution. Hexavalent chromium in the ground water near the
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Test Reactor Area (TRA) already exceeds the Public Health Service
standards for drinking water. As this ground water is not yet being
developed, there is no injury to human, plant, or animal life or to
property at this time, and therefore is not interpreted as water
pollution by the Idaho Operations Office. A 1968 chemical analysis
from the TAN shows the phenol content of water from the supply well
in that area to exceed the permissible limit for public water
supplies. Brine disposal at the NRTS has increased the chloride
concentration in the water supplies at the Central Facility Area (CFA)
and Chemical Processing Plant (CPP) above the desirable limit for
public v/ater supplies and recommended by the National Technical
Advisory Subcommittee for Public Hater Supplies (10).
Guides for the disposal of liquid radioactive wastes are pre-
sented in ID Manual Appendix 0510 (Part I, Section A). The basic
guides set the limits of radionuclide concentrations in liquid
wastes discharged to the ground or to ground water at levels such that
the subsequent concentrations in the regional ground water at any
point of use will not result in a dose to individuals in excess of
1/10 of the appropriate Radiation Protection Guide (RPG) values
recommended by .the Federal Radiation Council. Correspondingly,
specific guides in the form of effluent concentration limits at the
point of last sampling have been established for the acceptable
disposal of liquid radioactive wastes. Factored into the development
of these effluent limits are the probable reductions in concentration
which will occur as the result of physical decay, sorption, dis-
persion, and initial dilution.
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To set concentration limits for water which equate with a
radiation dose equal to the RPG for a certain body organ is
difficult because the daily intake of water is divided between fluid
water and the water content of food; not to mention the required
assumption of the total daily intake volume for the average individual.
A conservative approach is to assume the radionuclide concentrations
in drinking water and the water content of food are equal. This
approach forms the basis for the concentration limits specified in
AEC Regulation 10CFR20 (Appendix B, Table II). Thus, for the average
water intake of 2.2 liters per day, maintaining the level of radio-
activity at the 10CFR20 limits is sufficient in most cases to meet
the RPG's recommended for individuals (assuming no significant
radioactivity intake from other sources). However, limiting the
maximum individual dose via the water pathway to 1/10 of the appro-
priate RPG, further restricts the maximum concentrations in the
regional ground water to-levels within the range of 1/5 to 1/10 of
the corresponding 10CFR20 limits. Maximum concentrations corres-
ponding to the reduction factor of 1/5 would be for the case that
the radioactivity intake from the water content of food is negligible
(fluid water accounts for nearly one-half of total daily intake).
As an operational technique to be used where individual doses
are not known, the Federal Radiation Council has recommended that
the average exposure of a suitable sample of the exposed population
group should be one-third the RPG for individual members of the
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52
group. Therefore, if it would become necessary to use this technique
to meet the NRTS basic guide as it applies to individuals, maximum
radionuclide concentrations in the regional ground"water at the
point of use could not exceed levels in the range of 1/15 to 1/30 of
the corresponding 10CFR20 limits.
Regulations of the State of Idaho which are directly applicable
to the manner in which liquid wastes are disposed of at NRTS are
presented as paragraphs 5.C and 8.H of "Rules and Regulations for
Standards of Hater Quality and for Waste Hater Treatment for Waters
of the State of Idaho" (Appendix B).
"5.C. Radioactive materials or radioactivity in water which
exceeds (1) l/30th of the RCG values given in Column 2,
Table II, Appendix A, Part C, Rules and Regulations for
the Control of Radiation in the State of Idaho; (2}
exceeds concentration limits of the Idaho Drinking Water
Standards for waters used for, or likely to be used for,
domestic supplies; (3) results in accumulations of
radioactivity in edible plants and animals that present
a hazard to consumers, and/or (4) is harmful to aquatic
life.
"8.H. Waste discharges to underground waters shall receive,
prior to discharge of such wastes, such treatment as is
necessary to render them equal in quality to existing
underground waters or such treatment as is necessary
to bring such discharge into conformance with the
Idaho Drinking Water Standards. The provisions of
Paragraph 8.H will not be considered as strictly appli-
cable to the existing sink wells used exclusively for
irrigation waste-water disposal where such disposal does
not adversely affect domestic water sources. However, it
should be recognized that the long-term preservation of
Idaho's vast underground water resources is of great
importance and that every reasonable effort should be
made to reduce pollution from this source and that a long-
term research and development program should be estab-
lished that will lead to the total elimination of disposal
wells that directly affect underground aquifers that are
not subject to adequate filtration and percolation to
eliminate significant pollution.
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Further, this paragraph shall not be construed to pre-
clude the use of deep disposal wells which may be
constructed to discharge into underground water strata
whose quctlity is such that it is not likely to be used
for other beneficial purposes, provided necessary
precautions are taken to prevent contamination of usable
aquifers."
The basic and specific guides for the disposal of liquid wastes
(radioactive and non-radioactive) at NRTS are not in complete agree-
ment with the above Idaho regulations. When off-site ground water is
considered, the conflict between the basic guide and paragraph 5.C is
not great, particularly if the concept of the average exposure of a
suitable sample of the exposed population group is used. However,
there is substantial disagreement between the AEC policy for setting
effluent concentration limits and that implied in paragraph 8.H. As
previously stated the effluent concentration limits used in the day-
to-day operations of NRTS are based on maintaining acceptable water
quality at points of use; with consideration given to concentration
reductions which occur as the result of decay, sorption and dilution
during movement through the aquifer. This is in contrast to para-
graph 8.H which constitutes a strict application of the non-degradation
policy by requiring the quality of wastes discharged directly to the
aquifer to be equal to the quality of the aquifer water or of drink-
ing water quality.
The specific objectives of the pollution prevention, control
and abatement program at the NRTS are as follows (ID-0510-02):
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1. Protect the health and safety of on-site personnel and
the general public.
2. Maintain an inoffensive environment at the NRTS.
3. Protect the economic interest of the Nation, State and
local communities.
Recommendati ons
The objectives of the pollution prevention, control and abate-
ment program of the Idaho Operations Office (ID-0510-02) should be
modified to include the Federal objective of the national policy
for v/ater pollution control as set forth in Executive Order 11507:
"It is the intent of this order that the Federal Government
in the design, operation, and maintenance of its facilities
shall provide leadership in the nationwide effort to protect
and enhance the quality of our air and water resources."
and the Idaho Operations Office's definition of pollution should be
broadened to include any deterioration in water quality as a form of
water pollution similar to that adopted by the State of Idaho.
"Pollution" means such contamination or other alteration of the
physical chemical or biological properties of the public waters of the
State, including change in temperature, taste, color, turbidity or
odor of the waters, or such discharge of any liquid, gaseous, solid,
radioactive or other substance into the waters of the State which
either by itself or in connection with any other substance present,
will or can reasonably be expected to create a public nuisance or
render such waters harmful, detrimental or injurious to public
health, safety, or welfare, or to domestic, commercial, industrial,
agricultural, recreational, or other legitimate uses or to livestock,
wildlife, fish or other aquatic life or the habitat thereof."
For completeness, it is recommended that Radiation Protection
Guide values (ID Manual Appendix 0510, Part I) be identified as
those recommended by the Federal Radiation Council. Hith such a
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broader definition of pollution and with a new program objective
for water pollution control, the Idaho Operations Office could
provide Federal leadership in improving and protecting the water
quality in the Snake Plain Aquifer.
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VII. REFERENCES
1. Barraclough, J.R., H.E. Teasdale, and R.G. Jensen, Hydrology
of the National Reactor Testing Station Area,
Idaho: Annual Progress Report 1965, IDO-22048,
February 1967.
2. Barraclough, J.T., W.E. Teasdale, J.D. Robertson, and R.G.
Jensen, Hydrology of the National Reactor Testing
Station Idaho-1966. TID-4500, October 1967.
3. Mundorf, M.J., E.G. Crosthv/aite, Chabot Kilburn, Ground water
for irrigation in the Snake River Basin in Idaho,
USGS Water Supply Paper 1954; 1964.
4. 01 instead, F.H. , Chemical and physical character of ground water
in the National Reactor Testing Station, Idaho.
IDO-22043-USGS, May 1962.
5. Osloond, J.H., and D.L. Newcomb, Radioactive Waste Disposal
Data for the National Reactor Testing Station,
Idaho, AEC, I DO-12040, Supplement No. 3 (October
1968).
6. Peckham, Alan E., Investigations of underground waste disposal.
chemical processing plant area, National Reactor
Testing Station, IDO-22039-USGS, 1959.
7. Schmaltz, B.L., Interim report of liquid waste disposal in the
vicinity of the Idaho Chemical Processing Plant,
AEC, IDO-120011, June 1959.
8. Schmaltz, B.L., Haste Disposal at the NRTS Laundry—General
Description, Unpublished (1961?).
9. Schmaltz, B.L., Liquid Waste at the National Reactor Testing
Station, Idaho, ISO-12066, 1968.
10. Water Quality Criteria, Federal Water Pollution Control
Administration, 1968.
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APPENDIX A
ITINERARY FOR OCTOBER 1968
RECONNAISSANCE OF THE NATIONAL REACTOR TESTING STATION
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APPENDIX A
Itinerary for October 1968
Reconnaissance of the National Reactor Testing Station
October 15
Morning:
1. Brief meeting at the Idaho Operations Office of the Atomic
Energy Commission with Mr. William L. Ginkel, Manager, and
the following members of his staff:
Mr. Ralph V. Batie, Chief,Hazards Control Branch;
Mr. John T. Collins, Industrial Hygiene Engineer;
Dr. George L. Voelz, Director,Health Services
Laboratory.
2. Meeting in the office of Dr. Voelz (Central Facilities
Area) for the purpose of setting up a suitable itinerary.
The following members of the Health Services Laboratory
staff were in attendance:
Dr. Charles A. Pellctier, Chief, Environmental
Branch;
Mr. Bruce L. Schmalz, Radiation Soil Scientist.
Mr. J. Collins and Mr. Jack T. Barraclough, U. S.
Geological Survey, were also in attendance.
Afternoon:
1. Visit to the NRTS burial ground area;
2. Brief discussion of "Guides for Radioactive Waste Disposal"
Part 1 of ID Manual Appendix 0510, ''Prevention, Control
and Abatement of Air and Water Pollution" with Dr.
Pelletier and Mr. Schmalz;
3. Tour of Health Services Laboratory analytical laboratories
and counting facilities (Mr. Claude Sill, Chief, Analytical
Chemistry Branch);
A. Brief meeting with Mr. J. Weaver McCaslin, Manager, Health
and Safety Branch, Idaho Nuclear Corporation, and members
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of his staff for the purpose of establishing a schedule
for the Test Reactor Area, Test Area North, Chemical
Processing PlanL, and sewage treatment facility for the
Central Facilities Area.
October 16
Morning:
Visit to the Experimental Breeder Reactor No. 2 (EBR II)
operated by the University of Chicago for the Chicago
Operations Office (AEC). Met with:
Mr. Earl Graham, Health Physicist;
Mr. Joseph Auer, Plant Services Manager.
Afternoon:
Visit to the Special Power Excursion Reactor Test Area (SPERT)
operated by the Phillips Petroleum Company. Three facilities
were visited: SPERT-IV reactor, SPERT-I1I reactor, and Power
Burst Facility (PBF). The tour was conducted by Mr. Armand
Cordcs, Health Physicist.
October 17
Morning:
Visit to the Idaho Chemical Processing Plant (CPP) operated by
Idaho Nuclear Corporation. Discussions were held with Messrs.
R. E. Hayden, Health Physicist, Charles B. Amberson, and Mr.
Coward, Idaho Nuclear Corporation, and Mr. Donald Deming of
the Atoiiuc Energy Commission.
Afternoon:
1. Discussion and tour of the Waste Calcining Facility (Mr.
George Lohse);
2'. Tour of the sewage treatment facility at the Central
Facilities Area (Mr. Coward).
October 18
Morning:
Visit to the Test Reactor Area (TRA) operated by the Idaho
Nuclear Corporation. Tour and discussJon by Mr. John F.
Sommers, Radiation Supervisor.
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Afternoon:
Visit to the Ti2st Area North (TAN) which is largely the oper-
ational responsibility of the Idaho Nuclear Corporation. (The
Phillips Petroleum Company will be responsible for the Loss-of-
fluid Test which is to be conducted at the Field Engineering
Test Facility). Met with Mr. J. Sommers and Mr. Donald Reed
and several members of Mr. Reed's staff.
October 21
General discussions with the following individuals:
1. Atomic Energy Commission:
Dr. G. L. Voelz
Mr. J. T. Collins
Dr. C. A. Pelletier
Mr. B. L. Schmalz
Dr. Will Polzer, Soil Scientist
2. U. S. Gcologica.1 Survey
Mr. J. T. Barraclough, Chief, Research Project
Mr."John B. Robertson, HydrologisL
October 22
Morning:
FWPCA representatives spent the morning in the following
manner:
1. Dr. M. W. Lammering—conferred with Mr. J. Collins and
attended Health Services Laboratory seminar;
2. Mr. R. J. Velten—conferred with Mr. C. Sill on analyt-
ical methodology;
3. Mr. J. Sceva—conferred with Mr. J. Barraclough and
Mr. Robertson.
Afternoon:
Brief meeting with Mr. W. L. Cinkel and members of his staff
at the Idaho Operations Office.
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APPENDIX B
RULES AND REGULATIONS FOR STANDARDS
OF WATER QUALITY AND FOR WASTE WATER TREATMENT
FOR WATERS OF THE STATE OF IDAHO
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RULES AND REGULATIONS
FOR THE ESTABLISHMENT OF STANDARDS OF HATER QUALITY AND FOR
WASTE I'ATER TREATMENT REQUIREMENTS FOR HATERS OF THE STATE OF IDAHO
LEGAL AUTHORITY
The Idaho State Board of Health, pursuant to the authority granted in Title
39, Chapter 1, Idaho Code, sections 39-105 and 39-112, did adopt the following
Rules and Regulations for the Establishment of Standards of Water Quality and
for Waste Water Treatment Requirements for Waters of the State of Idaho while
in regular quarterly session on August 15, 1968, at Coeur d'Alene, Idaho, and
did determine the effective date to be September 4, 1968.
PREAMBLE
It shall be the policy of the State Board of Health to provide for an orderly
and economically feasible comprehensive water pollution control program, which
program shall be administered to conserve the waters of the State for all legiti-
mate beneficial uses, including uses for domestic purposes, agriculture, industry,
recreation, and fish and wildlife propagation.
The Board recognizes that the control of water pollution involves srany
factors, including multiple water uses, economic considerations and overall bene-
fits to the citizens of the Slate. It shall be the policy of the Board to carry
out such a program on a cooperative voluntary and educational oasis insofar as
such a policy is compatible i;ith statutory dutJ.es of the Board.
The Department of Health shall, on the basis of necessary technical studies,
determine waste treatuent needs throughout the State and shall establish recomncAdcd
tine tables for the provision of such treatment facilities as will be necessary to
abate pollution of the waters of the State.
These regulations are intended to be in harmony i/ith existing interstate
stream regulations and as an administrative guide for the continuation and sup-
plementation of the program previously carried out by the Board. The regulations
are general in nature and are intended for use until such time as the staff of the
Department of Health way be able to gather sufficient data to determine more
precise quality standards for such individual streams as uses iray indicate and
until such time as the staff of the Department develops the capability of initiating
A permit system as provided in the Idaho statutes.
For these reasons, paragraph 3A should be considered as the basic working
arrangement of the water pollution control program which provides, in effect,
special consideration for each and every vaste source on the basis of special
problems peculiar to that source.
DEFINITIONS
The following definitions shall apply to the interpretation and the enforce-
ment of these regulations:
"Sewage" means the wa'cei:-carried hui.:an or anivral waste from residences,
buildings, industrial establishments or other places together with such ground
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water infiltration and surface water as i.:ay be present. The admixture with s
as above defined of industrial wastes or wastes, as defined in the following
paragraphs 2 and 3, shall also be considered "sewage."
"Industrial waste" weans any liquid, gaseous, radioactive or solid waste
substance or a combination thereof resulting from any process of industry, manu-
facturing, trade or business, or from the development or recovery of any natural
resources.
"Wastes" means sewage, industrial wastes, and all other liquid, gaseous,
solid, radioactive or other substances which will or way cause pollution or tend
to cause pollution of the public waters of the State.
"Pollution" means such contamination or other alteration of the physical,
chemical or biological properties of the public waters of the State, including
change in temperature, taste, color, turoidity or odor of the waters, or such
discharge of any liquid, gaseous, solid, radioactive or other substance into the
waters of the State which either by itself or in connection with any other sub-
stance present, will or can reasonably be expected to create a public nuisance or
render sach waters harmful, detrimental or injurious to public health, safety, or
welfare, or to domestic, couancrcial, industrial, agricultural, recreaticual, or
other legi tai-.ate uses or to livestock, wildlife, fish or other aquatic life or the
habitat thereof.
"Standard" or "standards" means such wcdsuve of quality or purity in relation
to their reasonable and necessary use as may be established by the State Board of
Health.
1. WATER RIGHTS
It shall oe the policy of the State Board of Health that the adoption of
water quality standards and regulations and the enforcement of such standards
and regulations is not intended to conflict with the apportionment of water
to the State of Idaho, to any of the interstate compacts or court decrees, or
to interfere with the rights of Idaho appropriators in the utilization of
water rights.
2. HIGHEST AND BEST PRACTICABLE TREATMENT AND CONTROL REQUIRED
Notwithstanding the water quality standards contained herein, where a higher
standard can be achieved, the highest and best practicable treatment and/or
control of wastes, activities and flows shall be provided so as to maintain
dissolved oxygen at the highest desirable levels and overall water quality as
good as practicable, and water temperatures, colifor;;i bacteria concentrations,
dissolved chemical substances, toxic n>aterials, radioactivity, turbidities,
color, odor and other deleterious factors at the lowest desirable levels.
3. RESTRICTIONS ON THE DISCHARGE OF SEWAGE AND INDUSTRIAL WASTES AND HUMAN
ACTIVITIES WHICH AFFECT WATER QUALITY IN THE WATERS OF THE STATE
A. No wastes shall be discharged and n6 activities shall be conducted in
such a way that said wastes or activities either alone or in combination
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with other wastes or activities will violate or can reasonably be ex-
pected to violate the rater quality standards and/or regulations con-
tained herein.
B. It is noted that from time to Lime certain short-term activities which
are deemed necessary to accor/Modate essential activities and protect the
public interest may be specially authorized by the Department of Hoalfh
under such conditions as the Department of Health Kay prescribe even
though such activities rcay resuJt in a reduction of water quality con-
ditions below those criteria and classifications established by this
regulation.
4. MAINTENANCE OF STANDARDS OF QUALITY
A. The degree of sewage or waste treatment required to restore and/or
maintain the standards o£ quality and/or maintain existing quality shall
be determined in each instance by the State Board of Health and shall be
based upon the following:
(1) The uses which are or may likely be Made of the receiving stream.
(2) Tha size and nature of flow of the receiving stream.
(3) The quantity and quality of the sewage or wastes to be treated.
(4) The presence or absence of other sources of pollution on the same
watershed.
B. For purposes of enforcement of these standards and regulations, sampling
will be done at a point where these standards and/or regulations can be
evaluated, except for areas immediately adjacent to oatfalls. Cognizance
will be given lo the opportunity for admixture of waste effluents with
receiving waters, where such admixing is planned and carried out in a
rianner that will provide minimum degradation to receiving waters.
5. GENERAL WATER QUALITY STANDARDS FOR WATERS OF THE STATE
The following general water quality standards will apply to waters of the
State, both surface and underground, in addition to the water quality stand-
ards set forth on specifically identified waters. Waters of the State shall
not contain:
A. Toxic chemicals of other than natural origin in concentrations found to
be of public health significance or to adversely affect the use indicated.
(Guides such as the Water Qja_litv_ Criteria, published by the State of
California Water Quality Control Board (Second Edition, 1963} will be
used in evaluating the tolerances of the various toxic chemicals for
the use indicated.)
B. Deleterious substances of other than natural origin in concentrations
that cause tainting of edible species or tastes and odors to be imparted
to drinking water supplies.
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C. Radioactive rraterials or radioactivity in water which exceed (1) l/30th
of the MFC values given in Column 2, Taole I, Appendix A, Part C, Rules
and Regulations for the Control of Radiation i.n the State £f Idaho,
(2) exceeds concentration limits of the Idaho Drinking; Hater S_tanda£d£
for waters used for, or likely to be used for, domestic supplies,
(3) results in accumulations of radioactivity in edible plants and
animals that present a hazard to consumers, and/or (4) is harmful to
aquatic life.
D. Floating or submerged iratter not attributable to natural causes.
E. Excess nutrients of other than natural origin that cause visible slime
growths or other nuisance aquatic growths.
F. Visible concentrations of oil, sludge deposits, scum, foam or other
wastes that v.o.y adversely affect the use indicated.
G. Objectionable turbidity which can be traced to a point source or sources,
ON THE BASIS OF THE PRECEDING GENERAL WATER QUALITY STANDARDS, THE FOLLOWING
NUMERICAL STANDARDS, WHERE APPLICABLE, SHALL BE APPLIED, EXCEPT WHERE DIFFERENCES
OCCUR. BETWEEN NUMERICAL STANDARDS CONTAINED HEREIN AND THOSE PREVIOUSLY ADOPTED
FOR SPECIFICALLY IDENTIFIED INTERSTATE STREA11S. IN SUCH CASES, STANDARDS FOR
INTERSTATE STREAMS SHALL APPLY.
6. NO WASTES SHALL BE DISCHARGED AND NO ACTIVITIES SHALL BE CONDUCTED WHICH
EITHER ALONE OR IN COMBINATION WITH OTHER WASTES OR ACTIVITIES WILL CAUSE IN
THESE WATERS:
A. Organisms o_f the Coliform Group where Associated with Fcca 1 Sources
(MPN, equivalent liF or appropriate test using a representative niiu'ocr of
samples.) Average concentrations of coliforw bacteria to exceed 1,000
per 100 nillilitersj with 20 percent of samples not to exceed 2,400 per
100 uilliliters.
B. Dissolved Oxygen (DO)
DO to ba less than 75 percent of saturation at seasonal low or less than
100 percent saturation in spawning areas during spawning, hatching, and
fry stages of salmonid fishes.
C. Hydrogen I_on Concentration (pH)
pH values to be outside the range of 6.5 and 9.0. Induced variation not
to be more than 0.5 pH unit.
D. Temperature
Any measurable increases when stream temperatures arc 68° F. or above,
or more than 2 F. increase when stream temperatures arc 66° F. or less.
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E. Turbid:ty
Turbidity, other than of natural origin, to exceed 10 Jackson Turbidity
Units (JTU) . (This turbidity requirement shall not be deemed to rigidly
apply to streams, drain ditches, etc., receiving irrigation return flow.
However, every reasonable effort should be rnado lo prevent excessive
turbidity from such wastes.)
IN ADDITION TO THE GENERAL STANDARDS CONTAINED HEREIN, THE FOLLOWING NUMERICAL
STANDARDS SHALL APPLY TO THOSE WATERS OF THE STATE WHICH ARE PRESENTLY UPSTREAM
FROM EXISTING SIGNIFICANT WASTE SOURCES AND TO ALL LAKES AND RESERVOIRS USED
PRIMARILY FOR RECREATION, DRINKING WATER SUPPLIES, FISH AND WILDLIFE PROrOGATION
AND/OR AESTHETIC PURPOSES.
7. NO WASTES SHALL BE DISCHARGED AND NO ACTIVITY SHALL BE CONDUCTED WHICH ALONE
OR IN COMBINATION WITH OTHER WASTES WILL CAUSE IN THESE WATERS:
A. Organisms £f the Cpliform Group
Average concentration of coliforoi bacteria to exceed 240 per 100 milli-
liters with 20 percent of the samples not to exceed 1,000 per 100
milliliters and fecal coliform not to exceed 50 per 100 milliliters with
20 percent of the samples not to exceed 200 per 100 milliliters.
B. Dissolved Oxygen (DO)
DO to be less than 75 percent of saturation at seasonal low or Iocs than
100 percent saturation in spawning areas during spawning, hatchings and
fry stages of salmonid fishes.
C. Hydrogen 2_°n_ Concentration (pH)
pH values to be outside the range of 6.5 to 9.0. Induced variation not
to be more than 0.5 pH unit.
D. Temperature
Any measurable increase when stream temperatus/es arc 66° F. or above, or
more th.in 2° F. incicr.sc when stream tcmpeiatures are 64° F. or less.
E. Turbidity
Turbidity, other than of natural origin, to exceed 5 Jackson Turbidity
Units (JTU).
F. Phosphorus pjr Nitrogen Compounds
Measurable concentration of phosphorus or nitrogen compounds above those
of natural origin.
8. REGULATIONS GOVERNING WASTE DISCHARGES
A. Any person or perco.is, corporation, officers of any municipality, sever
district or association which owns or operates any facility or carries
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out any operation which results in the discharge of waste water shall
furnish to the Department of Health such infonration concerning quality
and quantity of discharged waste waters and isaintain such treatment
records as the Departrjer.t may reasonably require to evaluate the effects
on any receiving waters.
B. For the purposes of these regulations, r.un:wuu-adequate treatment for
domestic sewage or industrial wastes containing significant organic
material shall be equal to that which is coru-nonly known as secondary
treatment or the equivalent of 85 percent renoval of the biochemical
oxygen demand including adequate disinfection of any wastes which rcay
contain organisms that may produce disease in iran or animals. In
industrial processes, in-plant process controls or alterations, carried
out for the primary purpose of waste reduction, shall be considered as
a part of the treatment process. Exceptions to secondary treatment re-
quirements .vay be rade by the Department of Health when it can be
demonstrated that such exceptions will not adversely affect classified
water quality and will offer adequate protection for all beneficial uses,
Failure to provide adequate treatment shall be considered a violation
of these regulations.
C. Any person, persons, corporation or officials of a municipality or sewer
district who o\:ns or operates any scwaje or other water-borne vaste
treatment facility shall at all times operate such facility under
reasonably competent supervision and with the highest efficiency that
can reasonably be expected and shall rcaintain such facility in good
repair.
D. In cases of subsurface sewage or waste disposal, such disposal facilities
shall be so located that such sources of pollution including bacterio-
logical, organic or inorganic nutrient pollution will not or will not bz
likely to enter adjacent waters. In no case shall any portion of such
disposal system be located closer than 30 feet horizontally from the
edge of any water course, including lakes or reservoirs, as determined
from the known highest water level of such water course, lake or reser-
voir. Improperly or inadequately treated sewage shall not be allowed
to accumulate on the ground surface in such a manner that it may create
a health hazard.
E. It shall be a violation of these regulations to store, dispose of, or
allow to accumulate any dslecerious material adjacent to or in the
ir.imedi.ate vicinity of any portions of the waters of the State in such
a manner that such material will or is likely to enter the stream at
times of high water oc runoff or where drainage from such materials or
accidental failure of storage facilities may transport or allow dcle-
teriouc iratorial into the water course. Such materials shall include,
but not be lir.iif.ed to, trash, rubbish, garbage, oil, gasoline, chemicals,
sawdust and accumulations of iranure.
F. In case of accidental spills of deleterious iraterials, persons in
responsible charge shall ir
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G. Savage sludge or solid material which way contain disease-producing
organisms, when applied to lawns, rooL crop fields or fields producing
foods which nvay be consumed raw, or otherwise used in such a manner
that exposure to persons i?ay be a health hazard, shall be heated to
135 F. or higher for a period of one hour or any equivalent combination
of time and temperature approved by the Department of Health before such
use.
H. Waste discharges to underground waters shall receive, prior to discharge
of such wastes, such treatment as is necessary to render them equal in
quality to existing underground waters or such treatment as is necessary
to bring such discharge into conformance with the Idaho Drinking Water
Standards. The provisions of Paragraph 8H will not be considered as
strictly applicable to the existing sink wells used exclusively for
irrigation waste water disposal where such disposal does not adversely
affect domestic water sources. However, it should be recognized that
the long-term preservation of Idaho's vast underground rater resources
is of great importance and that every reasonable effort should be made
to reduce pollution from this source and that a long-term research and
development program should be established that will lead to the total
elimination of disposal wells that directly affect underground aquifers
that are not subject to adequate filtration and percolation to eliminate
significant pollution.
Further, this paragraph shall not be construed to preclude the use of
deep disposal "ells which may be constructed to discharge into under-
ground water strata whose quality is such that it is not likely to be
used for other beneficial purposes, provided necessary precautions
are taken to prevent contamination of usable aquifers.
I. Sewage Treatment Design Standards and Subsurface Sewage Disposal
Standards, as adopted by the Idaho Department of Health, shall be re-
vised from time to time and shall be used as a guide in the review of
plans and specifications for waste treatment facilities as required
by Section 39-112, Idaho Code.
Regulations relating to Water Pollution Control adopted by the Idaho State
Board of Health Hay 11, 1959, are hereby rescinded.
These Regulations shall be in full force and effect on and after September 4,
1968.
Section 39-112, Par. E --All plans and specifications for the construction
of new sewage systems, sewage treatment or disposal plants or systems, or other
waste treatment, or disposal facilities, or for improvement or extensions to
existing sewerage systems or sevage treatment or disposal plants, shall be sub-
mitted to and be approved by the board, heforo roiipt-viictinn Hiei/cof n'ay begin.
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APPENDIX C
EXCERPT FROM
IDAHO DRINKING WATER STANDARDS
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IDAHO DRINKING IJATER STAHDAROS
In accordance with the provisions of Idcho statutes pertrining to the protec-
tion of domestic water supplies (Sections 37-2102, 54-1213 and 39-101, as amended,
Idaho Code), the following standards for chemical, physical and bacterial purity
and standards for protection from impurities of water supplies in the state are
promulgated by the Department of Health.
Section 37-2102. (as amended) Domestic Uater to be Protected. -- Any person
or persons, corporation or corporations or officers of a municipality, ownins or
maintaining any plant or system for the supply to the inhabitants of this State,
or any part thereof, of water for domestic purposes shall protect the same and
keep it free from all impurities and all other foreign substances which tend to
injure the her-lth of the ultimate consumers of such water, v?hethcr such impurities
Oi foreign substances arc chemical or bacterial. The standards for protection
from impurities and the standards for chemical and bacterial purity in the State
of Idaho shall be promulgated annually by the Deonrtujcnt of Public Health and
shall be consistent with this section and the Drinking Water Standards of the
U. S. Public Health Service, which standards are suitable for use in evaluating
the quality and safety of water and wrter supply systems. The Department of
Public health may in its discretion issue reports and post public signs indicating
compliance with these standards.
Section 54-1210 (as amended) Public Work. -- After the first day of January,
1.940, it shall-be unlax;ful for this state, or for any county, city, village,
district, or other subdivision of the state, having power to levy taxes or assess-
ments against property situated therein, to engage in the construction of any
public work involving professional engineering unless the plans and specifications
and estimates have been prepared by, and the construction e^ocul-ed under the
direct s"pci vj «!iou of. r r^pi rofp
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Section 32-101 (as anendcd) (Paras jra-ph 4, SuWragraphs 13 A, B, and D)
State Board of Health -•- Towers and Duties, -- All of the powers and duties of
the Department of Public Health are hereby transferred to the State Board of
Health and the State Board of Health shall have all of such powers and shall have
and exercise the following powers and duties in additiona to all other powers and
duties imposed on it by law:
(13) To establish and enforce miniinui.1 sanitary standards for:
A. The col]cction4 treatment and distribution of drinking water,
including sanitrvy supervision, regulation and control of the
construction, extension, operation and maintenance of public
water supply, collection, treatment and distribution systems
and approval of pirns covering the construction and extension
of such systems.
B. The quality of water supplied to the public and as to the quality
of the effluent of sewerage system, sewage treatment plants and
discharged upon the land or into the surface or cr°und waters.
D. The protection of water sheds used for public water supplies.
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Definition of Terms -- For the purpose of these Standards the terms desig-
nated herein below shall be defined as follows:
Ad e qu a t c or o t e c t i on b^ jrui t o r a 1 ^ jig en c 1e s is rarely possible in surface waters.
It is possible in the case of ground waters and includes protection by storage
in and percolation through water-bearing materials.
Artificial treatment includes the various processes commonly used in water
treatment, Loth separately and in combination, such as storage, aeration, sedi-
mentation, coagulation, rapid or slow sand filtration, chlorinstion, and other
accepted forme of disinfection. Rapid sand filtration treatment is commonly under-
stood to include those auxiliary measures, notably coegr.lation and sedimentation,
which are essential to its proper operr.tion.
Adequate protection by artificial troatifont implies that the method and
degree of elaboration oC treatment arc appropriate to the source of supply; that
the works are of adequate capacity to support maximum demands, are ucll located,
designed, and constructed, are carefully and skillfully operated and supervised
by properly trained and qualified personnel, and are adequately protected against
floods and other sources of pollution. The evidence that the protection thus
afforded is adequate must be furnished by frequent bacteriological examinations
and other appropriate analyses showing that the purified water is of good and
reasonably uniform quality, a recognized principle being that irregularity in
quality is an indication of potential danger. A niiniuum specification o£ good
quality would be conformance to the bacteriologicel and chemical requirements
of these Standards, as indicated in Sections 3 and 4.
Sanitary defect means any faulty structural condition, whether of location,
design, or construction, treatment, or distribution works which r.\ay regularly or
occasionrlly prevent satisfactory purification of the water supply or cr.use it
to be contaminated frou extraneous sources. Amon« the extraneous sources of
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contamination of water supply arc dual supplies, bypasses, cross-connections,
inter-connections, and bad-flow connections.
Health hazard means any faulty operating condition including any device or
water treatment practice, which, when introduced into the water supply system,
creates or may create a danger to the well-being of the consumer.
Water supply sy&tc-n includes the works and auxiliaries for collection,
treatment, and distribution of the water from the source of supply to the free-
flowing outlet of the ultimate consi'i.isr.
The collform group of bacteria is defined, for the purpose of these standards,
a-s including all organisms considered in the coli-aorogenes group as set. forth
in the Stap.da.-d iicthods for the Examination of Uat?r and Sewage, current edition,
prepared, approved, and published jointly by the American Public Health Associa-
tion and the American '.later 'forUs Association, New Y.orl; City. The procedures
for the demonstration of bacteria of this croup shall be those specified herein,
for:
(A) The completed test, or
(b) The confirmed test when the liquid confirmatory modiiu.i brilliant:
green bile lactose broth, 2 percent, is used, providing the formation
of gas in any amount in this medium during 40 hours of incubation at
37° C. is considered to constitute a positive confirmed test, or
(c) Ihe confirmed test when one of the following liquid confirmatory media
is used: Crystal violet lactose bvoth, fuchsin lactose broth, or
formate ricinoleate broth. For the purpose of this test, all are
equivalent, but it is recornncnded that the laboratory worker base his
selection of any one of these confirmatory media upon correlation of
the confirmed results thus obtained with c series of completed tests,
and that he select for i-sc the liquid confirmatory Medium yielding
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results uiosl: nearly c^reein^ with the results of the completed test.
The inculation period for the selected liquid confirmatory mediui.i shall
be 4C hours at 37° C. and the -ornation of gac in any amount during this
time shall be considered to constitute a positive confirmed test.
(d) The membrane filter technique as outlined in the Standard Methods.
The Standard portion of water for the application of the bacteriolosical
test shall be ten niilli liter (10 ral.)
The standard sample fo" the bacteriological test shall consist of five (5)
standard portions of ten milliliter (10 ml.).
In any disinfected supply the se.i.r>le must be freed of any disinfecting ?scnt
x'ithin twenty (20) rainvtes of the tir.is of its collection,
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SGUilCE, :'?.CTECTlOi: AMD OPZIIATICH STA1IDAPJ3S
1.1 The water GLoVy shrll be obtained from the post desirable source which
is feasible and effort ohrll be raadc to prevent or control pollution of
the source. If the source is not adequately protected by natural means,
the supply shall be adequately protected by treatment.
1.2 Frequent sanitary surveys shall bo made by the purveyor of the water
supply systcn to locate find identify health hazards which might ei:ist in
the system. The manner rnd frequency of making these surveys ond the
rate at which discovered healuh hazards arc to be removed shnll be in
accordance with a progi'ara approved by tlie Departnent ol Health.
2. Approval of wrier supplies shall be dependent in part upon:
2.1 I'lnfcTccnont of jrulcs and regulations to prevent development of health
hazards.
2.2 Adequate protection of the We>ter quality throughout all ports of the
system, including watersheds and underground sources, as demonstrated by
frequent surveys.
2.3 Proper operation of the water si'pply system under the responsible charge
of personnel whose qualifications are acceptable to the Department of
Ileclth.
2.^ Acsquctc capacity of the system tc meet peak demands without development
of lot; pressures or other health hazards.
2.5 Satisfactory record ol laboratory examinations showing consistent couvoli-
sncc \;ith the water quality requirements of these standards.
2.6 Satisfactory submission of prescribed water treatment records to the
Dcoai tPient of Health if treatment is provided.
2.7 Subnission oiid appjoval of engineering plans ccvciing the construction
and extension of: the \:ater supply, collection, treaUacnu and distribucion
systems prior to actual construction.
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3. For the purpose of application of these standards, responsibility for
the conditions in and the operation of the water supply system shall be
considered to be held by:
3.1 The water purveyor from the source of supply to the connection to the
customer's service piping; and
3.2 The owner of the property served and the municipal, county, or other
authority having legal jurisdiction from the point of connection to the
customer's service piping to the free flowing outlet of the ultimate
consumer.
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WATER QUALITY STANDARDS
Part I. Bacteriological Quality
1.1 Sampling.
1.1.1 Compliance with the bacteriological requirements of these Standards shall
be based on examinations of samples collected at representative points
throughout the distribution system. The frequency of sampling and the
location of sampling points shall be established by the Department of
Health after investigation of the source, method of treatment, and pro-
tection of the water concerned.
1.1.2 The minimum number of samples to be collected from the distribution system
and examined each month should be in accordance with the following table:
Minimum Number of Samples
Per >fonth from the
Population Served Distribution System
3,000 and under 2
3,000 to 5,000 4
5,000 to 7,000 6
7,000 to 9,000 8
9,000 to 11,000 10
11,000 to 13,000 12
13,000 to 15,000 14
15,000 to 20,000 20
20,000 to 25,000 26
25,000 to 30,000 35
30,000 to 45,000 50
45,000 to 60,000 70
1.1.3 In determining the number of samples examined monthly, the following
samples nvy be included, provided all results arc essembled and
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available for inspection ?nd the laboratory methods and technical
competence of the laboratory personnel arc approved by the Department
of Health:
(a) Samples examined by the Department of Health.
(b) Samples examined by local government laboratories.
(c) Samples examined by the water works authority.
(d) Samples examined by commercial laboratories.
1.1.4 The laboratories in which these examinations are made and the methods
used in making them shall be subject to inspection at any time by the
designated representatives of the Department of Heolth. Compliance
with the specified procedures and the results obtained shall be used
as a basis for certification of the supply.
1.1.5 Daily samples collected following a bacteriologically unsatisfactory
sample as provided in Section 1.2.1 shall be considered as special
samples and shall not be included in the total number of cr.mplos examined.
Neither shall such special samples be used as a basis for prohibiting
the supply, provided that: (1) When waters of unknown quality arc being
examined, simultaneous tests are made on multiple portions of a geometric
series to dcternine a definitive coliforn content; (2) Immediate and
active efforts arc- made to locate the cause of pollution; (3) Immediate
action is taken to eliminate the cause; and (4) Samples taken following
such.remedial action are satisfactory.
1.2 Limits.--The presence of organisms of the coliform group as indicated
by samples examined shall not exceed the following limits:
1.2.1 When 10 ml standard portions arc examined, not more than 10 percent in
any month shall shov? the presence of the coliform group. The presence
of the colifonn group in three or more 10 ml portions of a standard
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sample shall not be allowable if this occurs:
(a) In two consecutive samples;
(b) In more than one sample per month when less than 20 are examined
per month; or
(c) In more than 5 percent of the samples when 20 or more are examined
per montho
When organisms of the coliform group occur in 3 or more of the 10 ml
portions of a single standard sample, daily samples from the same
sampling point shall be collected promptly and examined until the
results obtained from at least two consecutive samples show the water
to be of satisfactory quality.
PART T.I. Ihysical Characteristics
2.1 Sampling.--The frequency and manner of sampling shall be determined
by the Department of Health. Under normal circumstances samples should
be collected one or more times per week from representative points in
the distribution system and examined for turbidity, color, threshold,
odor, temperature and taste.
2.2 Limits.--Drinking water should contain no impurity which would cause
offense to the sense of sight, taste, or smell. Under general use,
the following limits should not be exceeded:
Turbidity 5 units
Color- ...-- 15 units
Threshold Odor Number-- — 3
Part III. Chemical Characteristics
3.1 Sampling.
3.1.1 The frequency and manner of sampling shall be determined by the
Department of Health. Under normal circumstances, analyses for
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substances listed below need be made only annually. If, however, there
is some presumption of unfitness because of the presence of undesirable
elements, compounds, or materials, periodic determinations for the sus-
pected toxicant: or material, should be made more frequently and an
exhaustive sanitary survey should be made to determine the source of
the pollution, Where the concentration of a substance is not expected
to increase in processing and distribution, available and acceptable
source water analyses performed in accordance with standard methods may
be used as evidence of compliance with these Standards.
3.1.2 Vihcre experience, examination, and available evidence indicate that
particular substances arc consistently absent from a water supply or
below levels of concern, annual examinations for those substances may
be omitted when approved by the Department of Health.
3.2 Limits. -- Drinking water shall not contain impurities in concentrations
which may be hazardous to the health of the consumers. It should not
be excessively corrosive to the water supply system. Substances used
in its treatment shall not remain in the water in concentrations greater
than required by good practice. Substances which may have deleterious
physiological effect, or for which physiological effects are not known,
shall not be introduced into the system in a manner which would permit
them to reach the consumer.
3.2.1 The following chemical substances should not be present in a water supply
in excess of the listed concentrations where, in the judgment of the
Department of Health, other more suitable supplies are or can be made
available.
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Substance Concentvation
in rag/I
Alkyl Benzene Sulfonate (ABS) — — 0.5
Arsenic (As) 0.01
Chloride (Cl) •-- 250.
Copper (Cu) 1.
Carbon Chloroform Extract (CCE) -» 0.2
Cyanide (CN) •• 0.01
Fluoride (F) ~ (See 3.2.3)
Iron (Fe) 0.3
Manganese (Mn) 0.05
Nitrate1 (N03) 45.
Phenols 0.001
Sulf-atc (S04) --- 250.
Total Dissolved Solids 500.
Zinc (Zn) 5.
1 In areas in which the nitrate content of water is known to bo in
excess of the listed concentration, the public should be warned of
the potential dangers of using the water for infant feeding.
3.2.2 The presence of the follo'-in™ substances in excess of the concentration!!
listed shall constitute grounds for rejection of the supply:
Substance Concentration
in mg/I
Arsenic (As) - 0.05
Barium (Ea) 1.0
Cadmium (Cd) 0.05
Chromium (Hcxavalent (Cr -1-6) 0.05
Cyanide (CN) 0.2
Fluoride (F) (See 3.2.3)
Lead (Pb) 0.05
Selenium (Se) 0.01
Silver (Ag) 0.05
3.2.3 Fluoride.--IJhen fluoiide is naturally present in drinking water, the
concentration should not average more than the appropriate upper limit
in Table I. Presence of fluoride in average concentrations greater
than tV7o times the optimum values in Table I shall constitute grounds
for rejection of the supply. IJhere fluoridation (supplementation of
fluoride in drinking water) is practiced, the average fluoride concen-
tration shall be kept within the upper and lower control limits in Table I.
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Tabls 1.
50.
53.
50.
63.
79.
Annual Average
Maximum Daily Air Ten
n s^ 7
r ^ai
Recommended control limits--
o£ __ Fluoride concentrations in ing/1
ciperaturesl T
Lower
__ n o
00
.__„ n 7
.___ n ft
Optimum
1.2
1.1
1.0
0.9
0.8
0.7
Upper
1.7
1.5
1.3
1.2
1.0
0.0
1 Based on temperature data obtained for a minimum of five years.
In addition to the sampling required by paragraph 3.1, fluoridated and
defluoridated supplies shall be sampled with sufficient frequency to
determine that the desired fluoride concentration is maintained.
Part IV. Radioactivity
4.1 Sampling.
4.1.1 Tne frequency of sampling and analysis for radioactivity shall be
determined by the Department of Health after consideration of the
likelihood of significant amounts being present. Where concentrations
of RaZ-° or Sr^ niay vary considerably, quarterly samples composited
over a period of three months are recommended. Samples for determina-
tion of gross activity should be taken and analyzed more frequently.
4.1.2 As indicated in paragraph 3.1, data from acceptable sources may be uccd
to indicate compliance \?ith these requirements.
4.2 Limits.
4.2.1 The effects of human radiation exposure are viewed as harmful and any
unnecessary exposure to ionizing radiation should be avoided. Approval
of water supplies containing radioactive materials shall be based upon
the judgment that the radioactivity intake from such \;ater supplies when
added to that from all other sources is not likely to result in an intake
greater than the radiation protection guidance recommended by the Federal
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Radiation Council. Uater supplies shall be approved without further
consideration of other sources of radioactivity intake of Radium-226
and Strontium-90 when the water contains these substances in amounts
not exceeding 3 and 10 PC/liter, respectively. When these concentra-
tions are exceeded, s water supply way be approved by the Department of
Health if surveillance of total intakes of radioactivity from all sources
indicates that such intakes are within the limits recommended by the
Department of Health and the Federal Radiation Council for control
action.
4.2.2 In the known absence of Strontium-SO and alpha emitters, the water supply
is acceptable when the gross beta concentrations do not exceed 1,000
PC/liter. Gross beta concentrations in excess of 1,000 PC/liter shall
bo grounds for rejection of supply except when more complete analyses
indicates that concentrations of nuclides arc not likely to cause exposure
greater than the Radiation Protection Guides.
Part V. Recommended Analytical Ilethods
5.1 Analytical methods to determine compliance with the requirements of
these Standards shall be those specified in Standard Methods for the
Examination of Water and Uastcwater, American Public Health Association,
current edition and those specified as follows.
5.2 Barium--Methods for the Collection and Analysis of Uater Samples, Uatcr
Supply Paper No. 1454, Rainwater, F. H. and Thatcher, L. L., U. S. Geo-
logical Survey, Washington, D. C.
5.3 Carbon Chloroform Extract (CCE)--i:anual for Recovery and Identification
of Organic Chemicals in Water, Middleton, F. II., Rosen, A. A., and
Burttschell, II. H. , Robert A. Taft Sanitary Engineering Center, Public
Health Service, Cincinnati, Ohio, Tentative Method for Carbon Chloroform
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Extract (CCS) in Water, J. An. Hater Works A. 54:223-227, Feb. 1962.
5.4 Radioactivity - Laboratory I-'anual of Methodology, Radionuclide Analysis
of Environmental Samples, Technical Seport R59-6, Robert A. Taft Sanitary
Engineering Center, Public Health Service, Cincinnati, Ohio; and Methods
of Radiochemical Analysis Technical Report No. 173, Report of the Joint
WHO-FAO Committee, 1959, World Health Organization.
5.5 Selenium - Suggested Modified Method for Colorimetric Determination of
Selenium in Natural Water, Hagin, G. B. Thatcher, L. L. Rattig, S.,
and Lavine, H., J. Am. Water Works Assoc. 52, 1199 (1960).
5.6 Organisms of the coliform group - All of the details of techniques in
the determination of bacteria of this group, including the selection and
preparation of apparatus and media, the collection and handling of samples
and the intervals and conditions of storage allowable between collection
and examination of the water sample, shall be in accordance with Stan-
dard Ifcthods for the Examination of Water and Wastewater, current edition,
and the procedures shall be those specified therein for:
5.6.1 The Membrane Filter Technique, Standard Test, or
5.6.2 The Completed Test, or
5.6.3 The Confirmed Test, procedure with brilliant green lactose bile broth, or
5.6.4 The Confirmed Test, procedure with Endo or eosin methylene blue agar
plates.
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PART I - SUB'ffSSIOK OF PLANS 86
1.0 GENERAL. - All reports, final plans, and s'pecifications should be sub-
mitted at least 30 days prior to the date on which action by the Idaho
Department of Health is desired. Documents submitter! for formal
approval shall include (a) general layout,, (b) detailed plans,
(c) specificationc, (d) reference to any plans and specifications
previously filed with the Idaho Department of Health pertaining to
the water supply system involved. No approval for construction can
be issued until finc.il, complete, detailed plans and specificatione
prepared by a registered professional engineer
have been submitted to the Idaho Department of Health and found to be
satisfactory.
1.1 ENGINEER'S REPORT. - The engineer's report for water works improvements
r.h.-.ll, where pertinent, present the following information:
1.1.1 General Infpj.Tip.Lion. - Describe the existing water works and sewerage
facilities, ar.d describe briefly the municipality or water district
served.
1.1.2 Extent of Uater Works System. - Describe the nature and extent of the
area to be served with water, 0nd any provisions for extending the
water works system to include additional areas, and appraise the future
requirements for service. Also, describe significant industrial develop
ments and industrial water supply needs which are to be met by "the- water-
supply system, or which are likely to bo required in the near future.
1.1.3 Al t ernat o PI PUS . •• Where two or more solutions exist for providing
public water supply facilities, each of which is feasible and practic-
able, discuss the alternate plans and give reasons for selecting the one
recommended, including financial considerations.
1.1.4 jgiJj__Gj:ojjndJTater Coiiditions,, and Foundation Problems. - Describe
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APPENDIX D
EXCERPT FROM
RULES AND REGULATIONS FOR THE CONTROL
OF RADIATION IN THE STATE OF IDAHO
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88
WASTE IJISl'OS-VL
Sec. C301 Gencial Kcquiicmcnt. No licensee shall dispose of any ladioactivc
matciinl cvccpt
(a) By tiansfei to an aulhonzcd iccipicnt as p;o\ided in Pail B, or
(b) As authoiizcd pursuant to Sections C 302, C 303, C.30-1, 01 C IOC.
Sec. C 302 Method of Obtaining Approval of 1'ioposed Disposal Prorcdiucs. Any
pcison may applj to the Roaul fo: appio\al of pio,)o->ed pioccduies to dispose of
radioacti\c nutcnal 111 a mannci not otlici wise aulhoii/^d in this pait Kach
application shall include a dcbcnpiion of the iadioacli\c malonal, inc'udmg the
quantities and kmJs of laclioacti.e mateiial and the le.cls of ladioactivily m-
\ol\ed, and the piopoacd mannci and conditions of disposal The application,
whcie appiopiipte, should also include an analjsis and equation of pcitincnl
infoimation as to the naliiie of the cn\iio»mcnl, including topogiaplucal, geo-
logical, mcteiologicpl, rncl ludiological cKuactet istics, ubagc of giound and sur-
face wati'is in the goneial aien, the natiue and location of olhci potentially af-
fected facil.ties; and pioccduics to be ob«ci\ed 10 mi'iimi/.o the lisk of unex-
pected 01 liazaidous eypo*u:es The I'.oaic! will not appio^c an> application for
a license to iccene iadioacti\c niateiial fiom other pei-ons for disposal on land
not owned bj a state 01 the Fcdcial Go\ei nincnt
Sec C 3U3 Disposal bj Hcli-ase into Sanitary Sewerage S.\stems. No licensee
shall diichaige iac!ioacti\c inaieii.il into a snnilaiy ^eweiage svslein unless
(a) It, i» icadily soluble 01 dispcisib'c in wi'ter, and,
(bj The quantity of an;, i;idioacti\e inaUiial iclcascd into the sji-lem by the
licensee in any one da\ does iiot exceed the laijjei of subpaiagiaphs (1)
or (2) of this paiagiaph
(1) The quantitj which, if diluted b\ the avciagc daily quantity of
sewpge lelcased into the «.c>\ ei bj tlic licensee, v, ill icsult in an a\ciaj:c
conccntiation not Kiealei th.Mi the limits specified in Appendix A, Table
I, Co'uion 2, of this pail; 01.
(2) Ten times the quantity of such matciiul specified in Appendix R of
this pai't, and,
(c) The quantity of an\ indioacti\c matcnal iclra^ed in any one iiionlh, if
diluted bj the a\eia^o inonthlj quantity of watci icle.'sed b> the
licensee, will not losufi in an a\ciagc conccntiat'on exceeding tho lim-
its specified in Appcriilix -\, Table I, Column 2, of this pait; and,
(d) The gioss quantity of ladioactr.p niplcnal icleascd into the se>'.eiage
system b> the IICOITJCC does not ex-ceecl one cuiic pci >C;M.
Excieta fiom indi\idu?'s uiidc1 going medical diagnosis 01 thciapj
with iadioacti\c matcnal shall be exempt fiom an\ limitations con-
tained in this section
Sec. C.301 Di<|io«.il bj Ruiinl in Soil No licensee shall dispose of iadioi?cli\c
matciinl by buiifl m soil unless
(a) The total quantity of irdiorcti\e materials buiicd at any one location
and time doeo not exceed, rt the time of bunal, 1,000 times the amount
specified in Appendix H of this pait; and,
(b) Biiiidl is at a minimum depth of foui feet; and,
(c) Successive buiials aie sepr.iated by distances of a least six feet and
not moie thrn 12 buiials aic made in any ycai
Sec. C ^05 Di^pos.il by Incinciatiun No licensee shall incinerate ladioactive ma-
teiial foi the put pose of disposal or piepaiation foi disposal except ab spccif-
icall\ appiovcd by the Boaul puisuant to Sections C106 and C.302
RECORDS, RKI'OUTS, AND NOTIFICATION
Sec. C-101 Records of Sunejs, Radiation Monitoring, and Disposal.
(a) Each licensee 01 icgistiant shall maintain iccoids showing the radia-
tion e.xposuic of all indnidua's foi whom pcisonncl monitoring is re-
quned undei Section C 202 of this pait Such lecoids shall be kept on
Dcpaitment of Health Foi in "Z", in accoi dance with the instruotions
containei.1 in thrt foi PI o: on C'.CPI and legible j-ecorcls containing all the
infoimation lequncd by Dcpaitmenl of Health Komi "7". The doses
enteicd 0:1 the foinib 01 lecoicis shall be foi pcuods of time not exceed-
ing one calendai quai tci
-------
89
(b) Each licpn.-ea 01 icgiilinnl shall maintain iccoulo in the same units
used in this pait, showing ilie icsulU of snivels icquncd by C.201(b),
and disposals made unclci Sections C 30-, C.303, and C 30-1
(c) Rocoids of individual radiation cxposme which must be maintained pui-
suant to the piovisions of pniagi?.ph (a) of th's section shall be pre-
setved until such time .as this BU.TI! may dctciminc 1O (ttccoids which
must be maintained puisuant to this pail may be maintained in the
form of miciofilm )
(d) The discontinuance of 01 cintai'ment of activities, does not iclie\e the
licensee or icgistianl of lespoiiiibilil.v foi lol.iinmg alt iccoids icquiied
by this section A licensee 01 icgisUanl may, howevei, lequest the Boaid
to accept such iccouls The acceptance of the iccoids by the Boaid ic-
licvcs the licensee 01 legis'iant of subsequent i tsponsibihty only in
respect to then picscivalion as iequi>ed by this section.
Sec. C.402 RppoiU of Theft 01 I.c^s of Source of Kadiation Each licensee or icg-
istipnl shall icpoit bv telephone and tclegiaph to the Boaid the theft 01 loss of
any souicc of ladiation immcdiateli aftei such occunoncc becomes known.
Sec. C-103 Notification of Incidents.
(a) Immediate Notification. Each licensee 01 icgisliant shall immediately
notify the Boaid by telephone and telegirph of an> incident involving
any souice of laclirlion possessed by li'iii and which may have caused or
tlneatcns to cause
(1) Exposu-.e to the vbo'e bod;, of any individual to 23 icnis o: mote of
radiation; c\posuio of the skin of the whole bodv of an> indiMdual to
150 icins 0! mote of ladialion; 01 cxpo^uic of the feet, ankles, hands,
01 foieniiMs of anv individual to 375 icm-j 01 moio of i?di?.l em-
ployed or associated vith hn-i (i e , student, ciaftsivan, etc.), shall fur-
nish to such individual a repoit of his exposuie to lad'ation as shown in
lecoids maintained puisuant to Section C.-!0(a). Such repoit shall
be fmnished within 30 days f'-om the time the leque^t is m'ado; sliall
cp\er each calendai -juritci of the individual's employment or associa-
tion in\ohine exposine to K'dif.tion, 01 such lesser peiiod as may be ic-
qucsted by the individual The ic-po:t shall also include the icsults of
'OAt any time, the Boaid ina> amend this section to assu:c the fuithei pieseiva-
tion of lecoids which it deteimines should not be destioycd
-------
90
any calculations and an.ilvscs of ladioactivc mateiial deposited in the
body of the mdr.idual and made puisiunt to the piovisiona of Section
C 107 The icpoit shall be in vuiting and contain the following state-
ment.
"This report is furnished to >ou unclei the pio\isions of the Idaho
State Boaid of He.illh legulations entitled Rules and Regulations
for the Contiol of Radiation in the State of Idaho You should pie-
scive this iepoit foi fuluic lofeiepce"
(b) The individual's request should include appiopi iatc idcntif v. ing data,
such as social sccunty mimbci and dates and locations of employment or
association.
Sec. C.-105 Reports of Overexposiirps and Kxcesshc Levels and Concentration.-..
(a) In addition to any notification icquiied bv Section C 103, each licensee 01
registiant shall make a icpoit in willing •\\ithm 30 days to the Board
of (1) each exposine of an individual to i.idia'.ion 01 concenti aliens of
radioactive material IP excess o' pny applicable limit as set foith in
this pait 01 as otheivvise approved b;. the Boa'd, (2) an\ incident for
which notuicatio'i is lequncd bv Section C-103; and (3) le\els of radia-
tion or conccnliatio'is of radioactive inateii?! (not involving e.\cessivc
c.xposme of anv indi\idual) in an umcstiictcd aiea in execs? of ten times
any applicable limit as set foith in this pail 01 as olhoiwUc appioved
by the Boaid Kach icpoit lecjuiied undci Ihis paragraph shall dosciibe
the extent of exposuie of mdiv iduals to ladiation ci to laclioaclivc inrle-
rial, le\cls of irdiation and concer.'iations of ipdionctnc rinlciial in-
vohed, the cause of the e\ijosuie, le\cls, 01 concenti ."'t ions; and conec-
ti\e steps taken or planned to assiue against a iccuncncc.
(b) In a'iy c?se \\hcie a licensee 01 icgist'an' i"; icqiiiied puisuant to the
pio\ibio;is of this section to icpoit to the Koaicl any cxposuio of an
indmdual to indiaiion 01 to ci>ncenlialion« of jad'o^ctiNC ma'ciipl, tlie
licensee 01 legislianl shall not l.uei than tlic ma'\ip£ of such icpoit to
the Boaid also »otif> such iiuli\idiinl of the naiuic- and extent of e\-
posuic Such notice shall be in anting and shall contain the following
statement-
'•This icpoit is fuinished to you undoi the p:o\i>c such individual ^annually of the individual's cxposuic to radia-
tion as shov.n in iccoids mainlainod by the licensee 01 legisliant puisuant to
Section C.-lOl(a).
Sec. C.107 Vacating Premises.
Each specific licensee shall, no less than 30 days bcfoie vacating 01 iclinquishing
possession 01 contiol of premises which mr.v have been contaminated with radio-
active material as a icsult of his activities, notifv the Coaid in wilting of intent
to vacate. The Bond may rcqiuic that tha licensee decontaminate or have decon-
taminated the locat'or> to a degiee consistent with subsequent use as an unre-
stricted aiea, the detp'is i>j be spec'fic-d in each case by the Boaid.
-------
91
PART C
Aprr.xmx A
CONCEXTIi \TIOVS IN MK VXD \VATi:K ABOVh NATUIVL RVCKGROUND
(Sec notes at end of pjipcndtx)
Table 1
I'lemcnt (Atomic Number)
Acciniun (89)
Amciiclu-i (95)
Andncn> (51)
Argon (18)
Arsenic (33)
Astatine (B5)
Barlun (56)
Bcrkclluci (97)
Bcrylllun (4)
Blsnuth (S3)
Brouiinc (35)
CsdnlLT ('.8)
Isolopci
Ac 227
Ac 228
A=i 241
An 242 n
Am 242
Aa 243
Am 244
Sb 122
So 124
Sb 125
A 17
t\ j /
A 41
As 73
As 74
As 76
As 77
Ac 211
Ba 131
Ba 140
Bk 249
Bk 250
Be 7
Bl 206
Bl 207
Bl 210
Bl 212
Br 82
Cd 109
S
I
S
I
S
I
S
I
S
I
S
I
S
I
s
I
s
I
s
I
S..U?
11 D
Sub
s
i
s
i
s
i
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
Column 1
Air
(uc/ml)
2xlO-12
3x10""
8xlO"8
2xlO"8
6xlO"12
IxlO-10
6xlO'12
3xlO-10
4x10-8
5xlO"8
6,10-J2
IxlO'10
4x10"°
2xlO"5
2xlO"7
IxlO'7
2xlO"7
SxlO'7
£v 1 ft"3
OX 1 \J
2x10'^
4<10"7
3*10
IxlO"7
IxlO'7
IxlO"7
5xlO"7
4xlO"7
3xlO"8
lxlO'5
4x10"'
IxlO"7
4xlO"8
9*10"10
IxlO"7
IxlO"7
1x10;°
Ix 10
2xlO"7
ixio";
2xlO"7
1x10"°
6x10
6xlO"9
IxlO'7
2xlO"7
1x10"'
2xlO"7
5x10'°
7xlO-8
Column ?
W ater
(uc/ml)
6<10"5
9>10'3
3>10"3
3xlO'3
1x10'*
MO'*
3-ilO"3
4x.lO'3
1x10-*
8xlO"*
IxlO"1
1x10"'
8x10"*
7x10-*
7x10-*
3xlO'3
3xlO"3
IxlO"2
1x10"'
2xlO'3
7xlO-3
6x10-*
6x10'*
2xlO"3
2xlO'3
5xlO"5
2xlO'3
SxlO"3
SxlO"3
3x10-''
7x10",
2xlO"?
2xlO"2
6xlO"3
6X10""1
5x10-'
5x10",
IxlO"3
IxlO'3
2x10"^
2x10",
IxlO"3
IxlO"3
IxlO"2
MO^2
IxlO"3
SxlO"3
SxlO"3
Table II
Column ]
Air
(uc/ml)
SxlO'1*
9xlO-13
3x10"'
6xlO-|°
2x10 ,
4xlO-|2
9xjO~12
IxlO'9
2xlQ-9
2xl°-12
IxlO-7
8x10"'
6x10"'
5x10
SxlO-9
7xlO-10
2xlO"8
9N10-,10
ivin"*
IX 1U
/.. i n~ 8
'* X 1 V
7xlO-8
IxlO"8
lxlO'8
4xlO"9
4xlO"9
2xlO"8
IxlO'8
IxlO'9
4x10-8
lxlO"8
4>10 o
IxlO"9
3x10""
4xlO"9
5xl°Is
2x-10'7
4>. 10*
6xlO"9
5xlO'9
• 9
6x10
5xlO"j°
2x10-0
2*10-1°
3\io"9
7xlO"9
4x10-8
6xlO'9
2x10"*
3xlO'9
Co1 urn n 2
\V 3:er
die/ml)
7xlO"6
3x10"*
9xlO"5
9x10-5
4xlO"6
2xlO"5
4x10-6
9x10" 5
1x10-*
1x10'*
4x10"°
3x10" *
SxlO'J
SxlO"3
3x10-5
3x10-5
2x10-5
7xlO"5
1x10'*
1x10"*
5x10'*
5x10'*
5x10-5
5xlO"5
2x10-5
2xl0'5
8x10" 5
8xlO"5
2x10'°
7xlO'5
2x10'*
2x10'*
3x10"^
2x10" 5
6x10-*
6x10'*
2x10'*
2x10'*
2xlO'3
2x 10"
4x10"^
4x10" 5
6x10" 5
6x10"'
4xlO"5
4x10"*
4»10"*
3x10'*
4x10 "'
2x10"*
2xlC"*
-------
92
CONCENTRATIONS IN -MR AMI \\.\1I.i: AHGVK N \TUlt \L BACKGROUND
(Set noti'a at end of ••ppcnilix)
Table I
Table II
KIcmrnt (Atomic Number) Isotopei
Cd 115 D
Cd 115
lolclu-i (70) Ca 45
Ca 47
laUfornlu- (98) Cf 249
Cf 250
Cf 251
Cf 25?
Cf 253
Cf 254
larbon (6) C 14
fro \
Icrlira (58) Cc HI
Cc 143
Cc 144
Icsluir, (i5) Cs 131
Cs 134 a
Cs 134
Cs 135
Cs 136
Cs 137
Ihlorlnc (17) Cl 36
Cl 38
Ihromtua (2i) Cr 51
:ob«lt (27) Co 57
Co 53 ci
Co S?
Co 60
:oppcr (29) Cu 64
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
C v
S
I
S
I
S
I
S
I
S
I
S
I
S
I
s
X
s
I
s
I
s
X
5
X
s
I
s
I
s
X
s
I
s
I
Column ]
Air
(uc/m!)
4xlO'8
4xlO'8
2x10-7
2xlO'7
3xlO"8
1x10"'
2x10"'
2x10 •'
1x10'}°
M°"I«
IxlO"10
2xlO'12
IxlO-}0
2>l° 10
Svlo"l°
6x10- }°,
5<10-
SxlO'}2
4x10""
t 1 rtO
3%iu.7
2x10-'
3x10''
2x10"'
IxlO"8
6x10"*
ixio";
3x10-*
4xlO"5
6xlO"5
4MO-8
lxlO"B
5/1 LO
9x1 O'f
4xio;5
6x10"?
1x10-.°
4x10"'
2x10"°
3x10"?
2x10^
2x10"^
3x10"?
2x10^
9xlO"§
8x10 _
SxlO"6
3xlO'7
9x10-9
2x10'°
IxlO"6
Column 2
Vinlcr
(uc/ral)
7x10-''
7x10-''
IxlO'3
IxlO"3
3x10",
5x10"
IxlO"3
IxlO"3
IxlO"4
7xl0^4
7xlO'4
BAlO"4
7xlO'4
7-10,
4x10^
6y 10
2> 10""
. 3>10-3
3xlO"3
IxlO'3
lx!o;4
3^10 ,
7x10",
3«10"
2«10"
3> 10"2
3xlO"4
IxlO'3
3x10"
7x10",
2x10
2vio"3
4x10"*
IxlO'3
2-<10",
2x10,
IxlO"2
1x10"
5vic'2
5xio";
•• 2
ixio;2
6x10"?
4x10,
3> 10' 3
J.jJQ-3
1A10~3
IxlO"2
6xIO"3
Column 1
Air
(uc/ml)
IxlO'9
IxlO'9
C\10'*
6xlO"9
IxlO'9
4xlO'9
SxlO'9
6.10'9
5x10' }4
3x10- ?
2x10; 3
3xl°!i4
3xlO"12
7xlO"J3
4xlO"1?
3ylQ-H
J^IQ-ll
2xlO-JJ
IxiO"'
i i n" ^
2xlO-J
5xlO'9
9xlO"9
7x10'*
3x10- °
2x!0;J°
1x10''
IMO'5
2x10"'
1x10 10
2x10*5
3sl°Ie
6x10"'
2*10"*
5\10"
1x10"®
CxlO"10
9x10"?
7x10",
4x10"'
6x10*
1x10''
6x10"*
6x10 ,
3x10"'
3x10"
2xlO'9
1x10"°
3*10"!°
7xlO'8
4xlO"8
Column 2
\\nlcr
(uc/ml)
3xlO'5
3xio;5
4xlO"5
9x10"'
2x10"
SxlO'5
3*10-5
4xlO"5
2xlO"5
IxlO'5
3x10-5
4xlO'6
3x10-5
2x10-5
2x10"
1> 10"4
IxlO"4
1x10"'
1x10"'
BxlO"4
9*10-5
9x10*5
4x10-5
4x10"
lx!0"5
1x10"?.
2x10'^
9x10"
6xlo"3
IxlO"3
9.-.10-*
4xlO"5
Ix'.O"
2x10*
9x10-5
6x10
2xlO"5
4xlO"5
ExlO"?
6x10 •?
^10!4
4x10 '
3xlO'3
2x10 "*
5x10"*
3xlO"3
~ 3
IxlO"4
9xlO"5
5x10-5
3xlO"5
2xlO'4
-------
CONCENTII.VIONS IN A1K AND V, ATKR AI10VK NATUKAL IUCKCKOUND
(Sec notes at end of n;>i)cnd.\)
Table I
Element (Atomic Number)
Curium (96)
Dysproslun (66)
ElnstcnUT (99)
Erblun (68)
Europiun (63)
Fermi usi (100)
Fluor me (9)
CadoliniuLi (64)
Gallluii (31)
Ceruanlun (32)
Isotopei
Cn 242
Cm 243
Cm 244
Cn 245
CD 246
Cn 247
Cm 746
Cn 249
D> 165
Dy 166
Es 753
Es 254 n
Es 254
Es 255
Br 169
Er 171
Eu 152
(T/2-9.Z hrs)
Eu 15?
(T/2-13 >is)
Eu 154
Eu 155
Fa 254
Fn 255
Fn 256
F 18
Cd 113
Gd 159
Ca 72
Ce 71
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
Column 1
Air
io-i°
2x10
6.10'17
1x10"'°
9 1 0" 1 7
lxlO-|°
[XJQ~10
5xlO"1?
JvJQ'lO
SxlO'12
IxlO'10
6xlO"13
IxlO"11
lxlO'5
3x10'*
2xlO"5
2xlO'7
2xlO'7
SxlO"10
6xlO"1"
5x10"*
6vlO
- 1 1
l*l°~10,
» i n
5x10 °
4x10 ,10
6*10"'
4x10
7^10'7
6x10",
4x10,
3x!0«
1x10"°
2x10"°
4x10"'
7x10-;!
9x10"°
7xlO-8
6x10-0
7x10'°
2x10""
_
-------
94
CONCKNTKATIONS IS AIK AND WAThli \KO\ K N VTUJ'Al. llVCKGICObNI)
(Soc no'.Ci at end of appendix)
Element (Atomic Number)
Cold (79)
llafnlun (72)
Holmlun (67)
Hydiogan (1)
Indium (49)
Iodine (53)
Irldlum (77)
Iron (26)
/•> e \
Krypton \jv)
Lanthanum (57)
Lend '(&2)
Isotopci
Au 196
Au 193
Au 199
HF 181
Ho 160
H 3
In 113 m
In 114 n
In 115 m
In 115
I 175
I 126
I 129
I 131
1 132
I 133
I 134
I 135
Ir 190
Ir 192
Ir 194
Fe 55
Fc 59
• r _ O C _
Kr co n
Kr 85
V «• C7
Kr b/
if i- ftp
Kr ou
La UiO
Pb 203
Pb 210
S
I
S
I
S
I
S
I
S
I
S
I
Cuk
auo
S
1
S
I
S
I
S
I
S
I
S
I
S
I
S
1
S
1
S
I
S
I
S
1
S
I
S
I
S
I
S
I
S
I
SL
UD
St,
LJO
S|_
UD
C.,K
dUD
S
I
S
I
s
I
Tab!
Column 1
Air
(uc/ml)
IxlO"5
6*10"7
3x10"'
2x10"'
1x10"°
6x10"'
4x10-3
7xlO"8
2xlO'7
2x10-7
SxlO"6.
5x10'°
")v i n~ 3
tX 1 U £
8vlO"6
7x10"°
1x10"'
2xlO'8
2> 10"°
2x10-°
2x10"'
3x10"°
5xlO"9
?x 10
8xlO'9
3x10"'
2x10"'
7xlO"8
9x10''
i m-7
3x 10
9x10-'
3x10'°
2xio";
5x10"'
3x10"°
ixio"'
4x10"'
IxlO'S
4x10"
K10"'
3xlO'8
2x10"'
2x10"'
9xlO"J
1x10"°
1x10"'
5x10"°
t. | A-D
DX 1U c
1 1 f\" J
£.
|| A"0
IX 1U
1. i n~ 6
_
2x10"'
ixio";
3x10"°
2x10"
1x10*
2xlO'10
e I
Column 2
Walir
(ur/ml)
SvlO"3
4x.lO"3
2xlO"3
1x10",
5-10"3
4xlO"J
2xlO"3
''xlO*3
9X10-'
IxlO'l
IxlC'1
4x10'^
JxlO"4
5x10"''
1x10'*
IxlO"2
3xlO"3
3xlO"3
4slO'5
6x10"
5x10'^
3xlO"3
6\ 10
6\ 10"
2xl0^3
2x10"*
1x10,
4X10"3
2x10
7x10-'*
2x10"^
6x10",
Jv 10
IxlO"3
IxlO'3
IxlO'3
9vio"
2x10-2
7x10",
2x10",
2xlO"3
7x10^*
1x10"^
/ v i Q~"
5xlO*3
Tnb!
Column 1
Air
(uc/ml)
4xlO"S
2xlO"8
IxlO"8
CxlO",
4xlO'8
3vlO'S
IxlO'9
3x10"'
7x10-'
6x10-'
2vlO"j
3x10''
2x10"'
7x10" 10
BxlO"8
6xlO"8
9xlO'9
1x10-'
CxlO"11
6xlO"9
9,10-J1
IxlO'8
2MO- "
2xlO'9
IxlO'10
IxlO'jj
3x10"'
3xlO"8
4x10"'°
7x10"*
6xlO"9
1x10''
1x10"^
4xlO"8
IxlO'8
4x10",.
9xlO:J°
GxlO
5x10"'
3xlO"8
3x10 ,
5x10"'
2xlO"9
i. i ft- 7
IX iU
9^ | A* 8
n
5x10-'
4x10"'
9x10-°
6x10"
4\10"
SxlO-12
c II
Column 2
\\ntcr
(uc/ml)
2xlO"4
1x10"*
5x10'*
5xlO"5
2x10"''
2x10'*
7xlO"5
7xl0'5
3x10-5
3xlO[3
Ixlo1'
2x10"'-
ZvlO"5
4x10"*
4x10"*
9x10"^
9<10"
2xlO'7
2x10'*
3x10"'
9x10-5
6x10"°
2x13";'
3x10"'
soioit
2x10
1x10"°
4x10'^
2xlO"3
6\10" '
4x!0'°
7xlO"J
2x10-'*
2x10"^
4xlO"5
4-10"*
3xlO"5
3x10"^
8x10,
2xlO"3
6xlO"5
SxlO"5
2x10*5
2xlO"r
4x10"^
4x10"*
Ix ! 0*
2x10"*
-------
95
CONCFMUATIONS IN All! ANH WATCH ABOVE N YTUKAL 11 \CKGKOUND
(fscc noies at end of ai>pcndi\)
Element (Atomic Number)
Lutecium (71)
rlnncanese (25)
Mercury (80)
Molybdcnun (42)
hcodyalu-a (60)
1,'cptuntv-ra (93)
Kickel (25)
Nioblun (Columhlu-i) (41)
Osnium (76)
Palladium (46)
Phosphorus (IS)
Platinum (7S)
Isotnpei
Pb 212
Lu 177
Mn 52
Kn 54
r-n 56
Fg 197 n
Hg 197
l<3 203
yo 99
t,d 144
Nd 147
Nd 149
Np 237
Np 239
Hi 59
M £3
Ml 65
S>> 93 a
Nb 95
Kb 97
Os 185
Os 191 n
Os 191
Os 193
Pd 103
Pd 109
P 32
Pt 191
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
5
I
S
I
S
I
S
I
S
I
Table
Column 1
Air
(uc/ml)
2>10-8
2xlO"8
6x!0'7
5xlO"7
2x10"'
IxlO"7
4xlO"7
4x10"°
8x10
5xlO"7
7x10"'
8/10
1x10'*
3x10^15
IxlO"7
?> 10~7
8xlO'U
4xlO"7
2x10
2x10'°
K10'6
4-10"12
.10
lxl°-7
7xlO"7
Sxio;7
3*10"7
9x10"'
5x10"
IxlO"7
2xlO'7
IxlO"7
6x10"°
5x10"°
SxiO'7
5xlO"8
2x10,
9x10"'
1x10-°
4x10"'
3x10"'
1x10"°
7x10"'
6xlO"7
4x10"'
7x10"°
8x10"°
8x10",
6x10"'
1
Column 2
Water
(uc/ml)
6.10'4
5x10"*
3xlO"3
3xlO'3
IxlO"3
9x10"*
3x10" 3
4xlQ-3
3x10",
C'.IO'
5xlO"3
9xlO"3
1x10-2
5x10"*
3xlO"3
5xlO'3
IxlO"3
2x!0;3
2xlo"3
2xlO"3
8xlO"3
9xlO'5
9x10"'
4xlO"j
6^1 O"3
6x10',
8MO'5
2x10"^
4x10"
3xlO'3
Kio";
1x10"^
3x 10"
3x10"
3xlfl-J
3x10"'
2xlO"3
2xlO"3
7x10',
7x10"'
5xlO"3
5x10'^
2xlO"3
2xlO"3
1x10"
8>10"3
3xlO'3
2x10",
5xlO"4
4xlO"J
Sxl'o"3
Table II
Column 1
Air
(uc/ml)
6xlO-10
7x10- 10
2x10-8
2\10"
7xlO-9
5x10"'
1x10"'
K10"'
3x10"°
2x10-3
3x10"°
3x10-°
4x10-°
2vlO"?
4x10 "'
3xlO-8
7vlO-'?
KIO'8
6x10''
6x10-'
5-10'8,
1»10"13
4x1 0"
3x10-8
7'10'g
3x10"
2x10"'
1x10'°
3xlO"8
?xlO"
4x10"'
5x10:'
3x10-'
2xlO"7
2xiO"7
2x10-3
2x10 V
6UO"7
3x10-'
4xlO-8
1x10"?
K10"°
9x10''
SxlO'8
3x 10"
2xlO"8
IxlO"6
2x10-'
3x10",
SxlOl7
2x10 °
Column 2
Water
(uc/ml)
2zlo-5
2xlO"5
1x10'*
1x10'*
3xlO"5
3x10"^
1x10"*
1x10"*
1x10"*
KIO',
2x10"*
2x10'*
3X10";1
5x10'*
_ Q
1x10"*
2x10"*
4xlO"5
7x10"*
6xlO"5
6^10~A
3x10 L
3x10"*
3xlO"6
3\ 10~
1x10'*
1x10'*
2x10'*
7xlO"3
3x10"
7x10'*
1x10
K10"
4x10'*
4X10-4
1x10'*
1<10"
9x10"*
9- 10"*
7xlO"5
7x10"^
3>10'3
2xlO"3
2x10'*
2x10'^
6x10"^
5xlO"5
3xlO:£
3x10 *
9x10" \
7x10'^
2x10"^
2x10";
1x10'*
1x10'*
-------
96
CO.NCLV.TK VTIONS IN" *11>. AM) \\.VII K MIOVE NATLIUI, IJACKGKOL.M)
(Sec nolea nt c.-d of ippindiO
Element (Atomic Number)
PlutonUT (94)
Polonium (81)
Potassium (19)
Fra5eo ID"5
2x10'*
4x10'.
-tl
8x1 °"I
7x10"
2xlO'2
8xlO"3
3xlO"3
1x10",
7x10"?,
4-10',
~ 3
9xlO"4
Tabl
Column 1
Air
(uc/ml)
2>10-7
2xlO'7
2x10"'
?xl°-8
3x 10
2xlO"8,
7x10:
ixio ;,
6x10- *
Ixl°-l4
lxl°-12
3x10"
1x10"
6x10"
IxlO'12
6x!0;|
8"10"
6x 10"
IxlO'J^
2viQ"
7X'°"02
4"10"
7xlO"9
IxlO"8
6x10-9
2x10-9
3'">"*
IxlO"8
8x10-9
6x10-
3x10 "
4xlO'14
4xlO'12
2xlO-8
6xlO"9
6x10-
BxlO''2
2x10-°
2xlO"U
3xlO"}2
2xlO-12
?<10":2
1x10':
-8
1x10
•ivi ft" 9
JX I v
SxlO'9
2xlO"8
8x10-9
3x10 '7
2x10'°
1x10"°
6x10"'
c II
Column 2
Water
(uc/ml)
IxlO"3
IxlO"3
1x10-
9x10'*
Ix 10"
1x10"^
5x10'^
3x10"?
5x10'^
3x10"^
3xlo"b
2. ID'*
IxlO"3
5x10"°
3x10"
3xl°"i
3x10'
4N 1 0"
_ 5
7xlO"7
3xlO"3
3x10"*
2x10"^
3x10" 5
SxlO'5
5x10-5
2^10'*
2x 10
4x10" 5
4xlO"5
2x10'*
2x10'*
9x10"'
"* J
1x10"*
1x10-*
7x10"
4.xlO'^
2vlO"
5\10"
3xlO"8
3x10-5
3x10",
3xlO"3
6x10'*
3x10'*
9x10":
5xlO"5
3x10",
2x10"^
6x10"^
3xlO"5
-------
97
COXCRX I'M \TIOXS IX AIR AND \VA1LK AFiOVK XATURU. R VCKCKOUND
(Sec notes at end of 3!>i>cnuiv)
Table I
Table II
Elemcit (Alo'inc Number)
Rhodlun (45)
Rubldlun (37)
Ruchcnlun (44)
Samarium (62)
Scandium (21)
Sclcnlin (3-'i)
Silicon (14)
SIKcr ('7)
Sodiura (11)
Strontium (38)
Sulfur (15)
Isotopct
Rh 103 Q
Rh 105
Rb 86
Rb 8;
Ru 97
Ru 103
Ru 105
Ru 106
Sen 147
So 151
Sn 153
Sc 1.6
Sc 47
Sc 48
Sc 75
SI 31
AC 105
Ag 110 n
Ag 111
Na 22
Na 24
Sr 85 n
Sr 85
Sr 89
Sr 90
Si 91
Sr 92
S 35
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
1
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
1
S
I
s
I
s
1
s
I
s
I
s
I
s
I
s
I
s
I
Column I
Air
(uc/ml)
8x10-5
6x10,
8x10"'
5x10"'
3x10'?
7x10 ,
5x10 „
7x10:8
2x10.,
2x10",
5x10"'
8x10"°
7x10"'
5x10"'
8xlO"8
6ylO;9j
3xl>
6x10"*
1x10"'
5x10-'
4x10''
?> 10" i
2xlO"8
6<10
5x10"'
2x10"'
l"10Ie
IxlO'J
6x10"'
1x10"?,
6x10"'
8x10"°
IxlO"8
2xlO"7
2x10-'
9x10 '
»7
1x10 '
4x10"*
3x10',
2x10
1x10"'
3x10^°
1x10"'
5x10 j
4.x 10"'
3x10",
4x10"'
3x10"
3x10''
3x10"
Column 2
Water
(uc/ml)
4X10"1
SxlO"1
4x10-3
3xlO'3
Z'lOlZ
7x10
3x10",
_ T
5x 10
1x10"
1x10",
2xlO"3
2x10",
3x10",
3x10",
4x10"?
3x10""
2xlO"3
2xlO"3
ixio";
li 10"
2xlO"3
2xlO'3
1x10",
IxlO"3
3x10",
JxlO^
SxlO
S'10"*
9x10":!
8x10",
_ t
6xlO"3
3x10"^
3^°l4
9x10"*
IxlO"3
1x10",
1-10"
9xl0^j
8x10",
2xlO^{
?•* 10"
3x10"
5xlO'3
3xlO'f
8*10*
ixio':>
1> 10"
1x10'^
2x10"
2xlO"3
2x10",
ExlO"J
Column 1
Air
(uc/ml)
3x10"!
2x10"°
3x10-8
2x10 p
1x10-8
2x10-'
2x10"°
2xlOl*
Sxioj
6x10 I
2x10"°
3ltl°s
2x10" Q
2x10 ,
3x10 in
2x10" °
?xl°-12
?x!0'9
5x10-'
2x10-°
1x10'°
Cxl°-io
6x10 1°
2xlO'8
2x10-8
6x10'*
5x10^
4x10"'
2x10''
3x10-8
2xl°"o
3x10''
7x10 ",«
3x10-1°
IxlO"8
8x10''
6xio';_
3xio:s
-9
5x10 "
IxlO'j
1x10"
8x10-'
4x10"*
3x10"!°
ixio";
3x10"
2xiO"l°
2X10'8,
9x10"
2x10"°
1x10"?
9x10
9x10
Column 2
W alcr
(uc/ml)
1x10"'
ixio";
1x10"*
1x10"*
7xlOle
2x10
1x10"
2"io:*
4x10
3xio;'
8x10**
8<10.
1x10 .
1x10"
1x10"*
IxlO"5
6xlO'5
7xlO',5
4x10-*
4x10'*
6x10'^
8x10"?
4x10"
4x10" 5
9.10"'
9X10"3
3x10"'
3x10"
3xlO-J
3x10 ^
SxlO"*
2x10"
IxlO"4
1x10^
3x10"*
4x10"^
4x1 0
4x10"^
3x10",
2x10"*
_ 5
3x10 ,
7x10",
7x10",
v ft
1x10 ,
2x10'*
3x10"^
3<10*
3x10",
4X10"3
7xlO'5
SxlO"5
7x10-5
6x10'^
6x10 "'
3x10"*
-------
98
CONCEXTK YTIONS IN AIR AND WATEI: \uovr NVTUKAL HACKGKOUND
(Sec notes at end of appendix)
Tnblc I
Table It
Elcncnl (Atomic Nu.nbcr)
Tantalu-i (73)
Tcchncciun (43)
Tellurium (5?)
Tcrblun (65)
Thai HIM (81)
Thoilura (90)
Thullu-n (69)
Tin (50)
Isotnpci
Ta 182
Tc 95 n
Tc 96
Tc 97 a
Tc 97
Tc 99 n
Tc 99
Tc 125 o
Tc 127 n
Tc 127
Tc 129 u
Tc 129
Tc 131 n
Tc 132
Tb 160
Tl 200
Tl 201
Tl 202
Tl 204
Th 228
Th 230
Th 232
Th natural
Th 234
TCI 170
Tn 1/1
Sn 113
Sn 125
S
I
S
I
S
I
S
I
S
I
s
r
s
i
s
i
s
i
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
s
I
Column 1
Air
(uc/ml)
4xlO"j;
2x10"°
3x10"?,
6x10"'
2x10"'
2x10 ,
2x10
lxlO"5
3x10"'
4x10"^
1x10
2>10;°
4xlO"7
MO"7
1x10"'
4xlO"8
2xl0'5
9>10
8xlO"8
3xlO'8
5x10"°
4-10"°
4x10"'
2x10
2x10"'
1x10-'
1x10
3xlO"5
1> 10"
2xlO'6
9x10''
8x10";
2x10"'
6x10"'
3xlO"8
9xlO"12,
6xlo; \2
2x10 ||
3x10-"
3xlO"||
•• 1 I
3x10 I;
SxlO'i1
6x10"!
3x10"°
4xlO"8
3xlO"8
1x10-'
2x10 7
4xloI8
5x10 B
IxlO'J
B^IO"8
Co'umn 2
Wnler
(uc/ml >
I/IO'3
£10;}
3^10"
S^IO"3
1x10'?
ixid":
5x10
SxlO"''
2x10"?
2x10",
8x10"'
lxlO"2
SxlO"3
5x10",
3/10 ,
2x10''
2.x 10'3
BV10
5 s 1 0" 3
1x10"^
6\ 1 0
2y 10"
2x10'^
2xlO"3
9x10"*
6 10"*
IxlO"3
IxlO"2
7xlO'3
SxlO"3
4xlO"3
2xlO"3
3xlO"3
2xlO"3
2x10^
5x10-5
5xl0'5
1x10"^
3xlO",5
3x10'*
SxlO"4
5x10^*
IxlO"3
lxlO"2
IxlO'f
7x10",
2xlO"3
5>10-*
5x10'*
Coliinin 1
Air
(uc/ml)
lxlO"9
7xlO"10
\ 1 *-6
1x10"*
2xlO"S
8xlO"9
SxlO"8
5x10",
4xlO"7
1x10"?
IxlO'6
5x10''
7xlO"8
2xlO"g
4xl0'9
5x10"
lxlO'9
6xlO"3
3» 10""
3x10"'
1x10,
2x10
1x10"'
IxlO^8
7x10"'
4x10-9
3xio;'
9>10'8
4x1 0"
7x10-3
3x10"°
3xlO'8
2x10"°
9x10-}°
3x10' 3
2x10' }3
BxlO'1*
3xlO'13
ixio'j;
1x10"
IxlO-}?
2xlO"9
lxlO'9
lxlO'9
1x10",
4x10 ^
8x10"'
1x10"
2x 1 0
4x10"'
3x10""
Colu..in 2
Wplcr
(uc/ml)
4xlO"5
4x10";
1x10":
1x10 ,
1x10"''
5xio;5
AV10
2x10'*
2xlO'3
8x10"*
6xlO"3
3xlO"3
3x10";-
2xlO'4
2xlO'6
lxlO"t
6xlO"5
5x10" 5
3x10"*
2x10"*
3X10"3
2vlO"5
8*10"*
8x10"*
6x10*5
4x10" 5
3x10"?
2> 10
4xlO"5
4x10"*
2x10",'
SxlO""1
2x10"*
1x10"*
7xlO"f
1x10"*
6xlO"5
1x10"*
2x10'°
3x10"?
2x10'°
4xlO"5
1x10"°
1x10-5
2x10";
2x10"^
5x10,
5x10";
5x10'*
5x10"*
9x10",
SxlO'j
2xlO"5
-------
99
CONCLXTK \TIONS IN AIK AND WATLK AUOVE NATL'KM. 11 \CIvCROIjND
(Sec notes at end of appendix)
Table I
Element (Mninir Number) Isotnpci
Tungsten (Wo If run) (74) V 181
Uranium (92)
Vanadlura (23)
Ynrtnn t ^/ 1
ACnCn IJHJ
Ytterbium (70)
Yttrlun (39)
Zinc (30)
Zirconium (40)
W 185
U 187
U 230
U 232
U 233
U 236
U 235
U 236
U 238
U 260
U nntural
V 43
Vet 111 n
AC 1 J I ul
Vo 111 m
AC ijj n
V» 1 1*4
f.C LJJ
V- 1 "IC
Ac 1 Jj
Yb 175
Y 90
Y 91 m
Y 91
Y 92
Y 93
Zn 65
Zn 69 m
Zn 69
Zr 93
Zr 95
Zr 97
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
c. i.
JUU
CuK
&UD
CuK
*>UD
S
i
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
S
I
Column 1
Air
(uc/ml)
2x10"*
IxlO,
8x10"'
IxlO"7
4x10"'
3x10 in
3x10--°
1x10-}°
• 10
3x1°-"
5x10
lxl°"!n
6x10 ,„
lxl(f}{}
lxlo"io
6x10 ,n
i>i°:l?
i :10
2xlO"7
2xlO"7
?Xl°-ll
2x10''
6xlO'8
1 „ 1 A" 3
IX 1 U -
1 „ 1 A" ^
ix 1U
/ . 1 A" 6
*«\ lv
7x10''
6x10,
IxlO'7
1x10''
2x10" I
2x10*5
4xlO"S
3xlO'8
4x10"'
3x10"'
2x10"'
IxlO'7
1x10"'
6xlO"8
3x10"'
7x10"*
9xlO"6
1x10"'
3x10''
1x10"'
3\10"S
IxlO'7
9xlO"8
Column 2
Water
lxlO'2
lxlO'2
3xlO"3
2xlO"3
2xlO'3
IxlO'4
1x10"^
BxlO"4
9,10"''
9xlO"4
9\10~
9\10'4
~6
exiQ-'Jl
1x10"
MO'3
1x10",
1x10,
1x10",
IxlO'3
5xlO'4
9\10-4
8^ 10'4
3xlO'3
3. 10"3
6x10'^
6x10",
1x10"}
IxlO"1
8x10"'*
8*10"4
2xlO"3
2xlO"3
8xlO'4
SxlO"4
3xlO"3
SxlO'3
2xlO"3
2xlO'3
5>10"2
2xlO'2
2x10-2
2xlO'3
2xlO"3
5x10"
5xlO"4
Table II
Column I
Air
(uc/ml)
8xlo-8
6x10-9
3xlO'|
2x10"?
1x10 11
1x10 ,J
4x10-"
3xl°-l3
2x10'"
6xlO[|2
6x10" |2
-11
6slO"12
2x10-
4x10-
3xlO'[2
5x10
8xlOq
6x10',,
3xl°-12
6\10"'
2>.lO*9
iv i n
JX 1 U
3x 1 u
^T
2x!o"3
2xlO"8
4x10-9
3x10 ,
CxlO'7
6xlO"7
1x10-'
1x10"'
1x10"'
6x10-9
5x10";
6x10 "'
2xlO"9
lxlO-8
IxlO"8
2x10''
3x10"'
4x10'*
IxlO o
4x10 o
lxlO"9
4xlO'9
3x10-9
Coluiiiii 2
Water
(uc/ml)
6xIO"4
3xlO'4
IxlO'4
7x10-5
6x10" 5
5xlO'£
5x10"°
3xlO"5
3x10"'
3x10"*
3x10"'
3x10"'
3x10"
3xlO"5
3x10",
3xlO"5
3xl0'5
4x10-?
4\10
3xlO"5
3xlQ-|
2x10 '
2xlO"5
3x10*5
3x10-5
K10"4
1x10*
2x10-5
2\10"
3x10" ;j
3\10*3
3x10-5
3x10-5
6x1 0"5
3xlO"5
3xlO"5
IxlO"4
2xlO"4
7x10-5
6x10*5
2xlO-3
2xlO"3
8xlO"4
6x10*5
6x10-5
2xlO"5
- ^
2x10 3
-------
100
CONCENTRATIONS IN AIR AND WA1T.R ABOVi: NATURAL BACKGROUND
(Sec notes at end of njtpcndiv)
Table I
Trblc II
Element (Atomic Number)
Isotopei
Column 1 Column 2
Air Water
(uc/ml) (uc/ml)
Column 1 Column 2
Air Water
(uc/ml) (uc/nl)
Any single ladiomiclidc not
listed abo\c v. ilh decay
mode othci than alpha
emission or spontaneous
fission and with
radioactive half-life
less than 2 houis.
Any single ladionuclidc
not listed abo\c with
decay mode othci than
alpha emission 01
spontaneous fission and
with irulioactne half-
life crpatci than 2
hours.
Any single indioiuichdc
not listed aho\e, \\h'di
deca>s by rlpha emission
or spontaneous fis>ion.
Sub 1x10-6
3xlO-c
3x10-9 9x10-5 1x10-1° 3x10-6
6.\10-i3 4x10-' 2x10-14
3xlO-o
iSoluble (S); Insoluble- (I)
2"Sub" means In?I \alucs given aic for submeision in a semi-spheiic?!
infinite cloud of anbomc mctenal.
-------
101
APPENDIX A
NOTE- In an\ case wheio tlieic is a nii.xtiue in an or watei of moie than one
radionuclidc, the Inviting \alucs foi pu'posca of this Appendix should be detet-
mincd as follows.
1. If the identity and conccnliation of each laclionuclidc in the mixtuie aie
known, the limilipg \alucs "should be demed ns follows Octet mine, foi each
ladioiuiclidc in the nnxtuie, tho latio between the quantity piesenl in the nnxtuie
and the limit othciuiic established in Appendix "A" foi the specific ladionuclide
when not in a rm\.tuic The sum of such intios foi all tlic ladionuclidcs in the
mi.xtiKC ma\ not exceed ''I'1 (i c., 'unit>'')
EXAMPLE If ladtonuchdoi u, b, and c aie ptcscnl in conccnli nitons Cn, Cb, and
Cc, ami if the applicable MFC's aic MPCa, and MPCb, and MPCc, lespcclucly,
then the concenti.'hons shall be limited so that the following iclationship exists1
Ca
MPCa
Cc
MPCc
z^r J
2. If cithci the identity 01 the conccnti.\tion of any i.idionuclidc in the mix-
tmc is not 1-i'own, the limiting ^luo foi puiposcs of Appendix "A" shall be.
a. Foi pin poses of Table I, Col 1 6\lO-'3
b. Foi lunposcfc of Table 1, Col 2 4\10-7
c Foi pin pose-of Tab'e II. Col I 2\10-"-
d Foi pin poses of Table II, Col 2 3\IO-^
3 If am of the conditions specified helou aic met, the conespondi'ig values
specified belov. 'nay be used in lieu of tho»a specified in piiagi.iph ? above
a If the it'ciilit> of each indionuclido in l^e mixti'ic is knoun but the
conccnti.itioii of one 01 moic of tlio indionuchdes in the nmluic is not
known, the coiicenti iilion trim foi the nnxtuic is the limit specified in
Appendix ''A'1 foi the jru'iomichrlo in tho nmluic lir\\ine the lowest con-
ccnttitliou hiiiil, 01,
b. If the identity of each i.idioiutehdc in the nti.xtuic is not l:nown, but it
is knov n that coilnin ladioiiucliries specified in Appendix "A" ate not
picscnt in the ii'ixtuie. the conccntiation linrt foi the mixluie is the
lowest conrentialion Irint '•j-ecificd in Appendix "A" foi an> i.idionuclidc
which is not Known to be ahsoitt fiom the mixtuic, or,
c
Element (atomic nnmbei) and
Isolopt
Table I
Column ] Column 2
Air Walci
(uc/ml) (uc/ml)
Table H
Column 1 Column 2
Ait Water
(uc/ml) (uc/ml)
If it is known lhat Si DO, I 12">, I J2C,
I 129, I 131, (1 113, Table II onl\),
Tb 2JO, Po 210, At 211, Ka 223, Ho 22-1,
Ka 2?G, Ac 227, Ka 225, Th 230, Pa 231,
Th 232, Th-nat, Cm 213, Cf 251 and Fm
256 aie not ptescnt
If it is known that Si 90, I 125, I 12G,
(I 131, I 133, Table II onl%),
Pb 210, PQ 210, K'a 223, Ka 22G, Ra 228,
Pa 231, Th-nat, Cm 24S, Cf 251, and
Fm 25G aie not picscnt
If it is known that Sr 90, I 129, (I 115,
I 12G, 1 131, Table II onl>), Fb 21},
Ra 226, Ra 22S, Cm 2 IS, and Cf 23-1
aic not picsent.
If it is known that (I 129, Table II only),
Ra 22G, and Ka 22S aie not piesent
9x10-5
6x10-5
3x10-6
ZxlO-s
3\10-6
CxlO-v
IxlO-?
-------
102
APPENDIX A
Table I
Table II
Element (atomic number) and
Isotope
Column 1 Column 2 Column 1 Column 2
Air Walcr Air Water
(lie/ml) (uc/ml) (lie/ml) (lie/ml)
If it is known tint ap'.Ki-cmiltcrb and
Sr 90, I 129, Pb 210, Ac 227, Ka 223,
Pa 230, Pu 211, and Bk 2-19 are not
present 3x10-9
If it is known that alpha-emittcis and
Pb 210, Ac 227, Ha 228, and Pu 2-11 aie
not piesent. 3xlO-'o
If it is known that alpha-cmillcis and
Ac 227 sue not picscnl 3x10-"
If it is known thai Ac 227, Th 230,
Pa 231, Pu 238, Pii 239, Pu 210, Pu 2 12,
Pu 2-1-1, Cm 218, Cf 2-19 and Cf 251
aic not picsenl. 3xlO-12
IxlO-'o
1x10-12
1x10-13
4. If the inixtuic of ladiorniclides consist of mamum and its daughter piod-
uct<; in 01 c dust pnor to chemicdl pioecssin;; of the uirnium ote, the \alues speci-
fied bclov,- mr.> bu used in lieu of those determined in accoid.'.ncc with pai<>giaph
1 abo\e 01 those specified in paipgipphs ? and 3 above
a. Voi puiposcs of T.ibb I, CoKi'nn ], l\10-'o uc/ml gioss alplu acti\il>,
01 25\10-n uc/ml nalm.il ui.iniuni, 01 75 micioginm^ pei cubic metei
of ail natuial uipnium
b Foi puiposcs of Table II, Column 1, 3\10-'?- uc/ml fioss alpha activ-
ity, 01 8\10-i3 uc/ml natuip] uianium, 01 3 miciogiams pci cubic meter
of ail ivituial uiar.ium.
5. For puiposes of this note, a ir.dionuclic'ic maj be consideied as not picscnl
in a niNluie if (?) the latio of the concenli.il.ion of thrl ladionuclidc in the iiiix-
tuic (Ca) to the conccnliation limit foi that ladionuclide specified in Table II of
Appondi\ "A" (MPCa) does not exceed 1/10, (i e., Ca = J_ ).
MPCa 10
and (b) the sum of such ir.tios foi all indioiniclidcs coi^ideied as not present in
the mi\tuic does not exceed \i, (i c, Ca -\- Cb -f . . . = 1 ).
MPCa lUPCb 7
-------
103
Material
Ag 105
Ag 111
As 76, As 77
An 19S
An 1S9
Ba 1-10-1- LA MO
Be 7
C 14
Ca 45
Cd 109 + Ag 109
Cc 111-l-Pi 1M
Cl 3G
Co GO
Ci 51
Cs 137H-Ba J37
Cu 01
Eu 154
F IS
Fc 55
Fc 59
Ga 72
Gc 71
II 3 (HTO 01 11320)
r 131
In 111
Ir 192
K -12
La MO
Mn 52
Mn 5G
Mo 99
Na 22
Na 21
Nb 95
N7i 59
Ni 63
P 32
PART C
APPENDIX
Micro-
curics
1
10
10
10
10
1
50
50
10
10
1
1
1
50
1
50
1
50
50
1
10
GO
2;0
10
1
10
10
10
1
50
10
10
10
10
1
1
10
U
Malciinl
Pd 103+Rh 103
Pd 109
Pm 1-17
Po 210
Pi 1-13
Pu 239
Ra 22G
Rb SO
Re ISO
Rh 105
Ru 30C-I-RH 10G
S 35
Sb 12-1
Sc -1C
Sm 133
Sn 113
Si 89
Sr 90-j- Y 90
Ta 182
Tc 9G
Tc 99
Tc 127
Tc 129
Th (nalmpl)
Tl 201
Ti ilium Sec II 3
U (naliii.il)
U 233
U 231-U 235
V -IS
W 185
Y 90
Y 91
Zn G5
Uniiicnlificd i.idioaclive
nip.lcn.ils or an> of the
above in unknown mixtures
Micro-
cm ics
50
10
10
0.1
10
1
0.1
10
10
10
1
50
1
]
30
10
1
0.1
10
1
1
10
1
50
50
250
50
1
50
1
10
1
1
10
O.I
NOTK- Foi pm poses of Sections C 203 and C301, \\heic thcie is invoked a
combination of isotopes in known amounts the Irmi foi the combination should
be dcii\ed r"; follov.s dctc;mine, foi each isotope in the combination, Hie ratio
between the quantity picsent in the combination and the limit othci\\isc estab-
lislied for the specific isotope \\hen not in comb'nation The sum of such latios
for all the isotopes in the combination may not c\cecc! "1" (i e , "unity1').
EXAMPLE- Foi pm poses of Section C 30-1, if a pailicu'.ai batch contains 2,000
uc of Au'99 and 25,000 no of C'-, it may also include not moic than 3,000 uc of
I'3i. This limit vas dctciminccl as follows:
2,000uc
lO.OOOuc"
_25,OOCIuc
SO.OOOuc
-h 3,000uc I"si =
lO.OOOuc
The dcnominatoi in each of the abo%c jatios v.?s obtained by multipljing the
figure in the table by 1,000 as piotidcd in Section C301
------- |