I

0 o•UNITED STATES 

NUCLEAR REGULATORY COMMISSION 

WASHINGTON, D. C. 20555 

April 25, 1980 

Regulatory Guide 4.14 

Revision 1 

REGULATORY GUIDE DISTRIBUTION LIST (DIVISION 4) 

SUBJECT: Regulatory Guide 4.14, Revision 1, "Radiological Effluent 

and Environmental Monitoring at Uranium Mills" 

Regulatory Guide 4.14 was originally issued for public comment in 1977. That 

version has now been revised as appropriate in response to public comments. 

In addition, the scope of the guide has been expanded to include offsite 

environmental monitoring. The environmental monitoring programs described in 

this revision were previously included in NRC publication NUREG-0511, "Draft 

Generic Environmental Impact Statement on Uranium Milling," published for 

comment in April 1979. 

The NRC staff developed the regulatory positions in this Revision 1 of 

Regulatory Guide 4.14 over a long period of time, taking into-account public input as described above. The positions are already being used by the NRC 

staff in the licensing process. However, this revision represents the first 

opportunity for public review of the staff position as a consolidated document. 

For this reason, it is being provided to all addressees on the Division 4 

distribution list. Comments on regulatory guides are encouraged at all times, 

and comments on this guide will be particularly helpful to the NRC staff in 

evaluating the need for another revision to this guide. Comments will be most 

useful if they are submitted within two months of the publication of the guide. 

'Ug"ector 

Robert B. Mino 

Office of Standards Development
Revision 1 

April 1980

U.S. NUCLEAR REGULATORY COMMISSION

REGULATORY GUIDE 

OFCE OF STANDARDS0EVE.OPMENT 

REGULATORY GUIDE 4.14 

RADIOLOGICAL EFFLUENT AND ENVIRONMENTAL MONITORING 

AT URANIUM MILLS

A. INTRODUCTION 

Uranium mill operators are required by Nuclear Regula

tory Commission (NRC) regulations and license conditions 

to conduct radiological effluent and environmental moni

toring programs. Regulations applicable to urafium milling 

are contained in 10 CFR Part 20, "Standards for Protection 

Against Radiation," and Part 40, "Domestic Licensing of 

Source Material." For example, § 40.65, "Effluent Moni

toring Reporting Requirements," of 10CFR Part40 

requires the submission to the Commission of semiannual 

reports containing information required to estimate doses 

to the public from effluent releases. 

Information on radiation doses and the radionuclides in 

a mill's effluents and environment both prior to and during 

operations is needed by the NRC staff: 

1. To estimate maximum potential annual radiation 

doses to the public resulting from effluent releases. 

2. To ascertain whether the regulatory requirements of 

the NRC (including 10 CFR Part 20 dose limits, release 

limits, and the "as low as is reasonably achievable" require

ment), mill license conditions, and the requirements of 

40 CFR Part 190, "Environmental Radiation Protection 

Standards for Nuclear Power Operations," have been met. 

3. To evaluate the performance of effluent controls, 

including stabilization of active and inactive tailings piles. 

4. To evaluate the environmental impact of milling opera

tions, both during operations and after decommissioning. 

5. To establish baseline data to aid in evaluation of 

decommissioning operations or decontamination following 

any unusual releases such as a tailings dam failure. 

The substantial number of changes In this revision ha made it 

impractical to Indicate the changes with lines in the margin.

This guide describes programs acceptable to the NRC 

staff for measuring and reporting releases of radioactive 

materials to the environment from typical uranium mills. 

The programs described in this guide are not require

ments. Licensing requirements are determined by the NRC 

staff on a case-by-case basis during individual licensing 

reviews. Individual applicants or licensees may propose 

alternatives for new or existing monitoring programs that 

need not necessarily be consistent with this guide. The 

justification for such alternatives will be reviewed by the 

NRC staff, and the acceptability of proposed alternatives 

will be determined on a case-by-case basis during individual 

licensing reviews. For example, it is anticipated that opera

tional monitoring programs that do not include at least 

three continuous air samples at the site boundary will 

include more extensive stack sampling and more sampling 

locations than are described in this guide as well as meteor

ological data and additional environmental monitoring 

requirements. 

B. DISCUSSION 

The radiation dose an individual receives can be deter

mined only if the radionuclides to which an individual is 

exposed are known. Therefore, monitoring programs should 

provide accurate information on the specific radionuclides 

in effluents from a mill, its ore piles, and its tailings reten

tion system and in the surrounding environment. 

Methods of sampling and analysis for the radionuclides 

associated with uranium milling are discussed in sources 

listed in the bibliography. The listing of these documents is 

not meant to be all inclusive, nor does it constitute an 

endorsement by the NRC staff of all of the methods in all 

of the listings. Rather, these listings are provided as sources 

of information to aid the licensee in developing a monitor

ing program. 

The sampling program described below is divided into 

two parts: preoperational monitoring and operational

USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission Washington, D.C. 20555, 

Regulatory Guides are Issued to describe and make available to the Attention: Docketlng and Service Branch. 

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Guides are not substitutes for regulations, and compilance witl• 2 Research and Test Reactors 7. Transportation them Is not required. Methods and solutions different from those set Fuels and Materials Facilities 8. Occupational Health out In the guides will be acceptable If they provide a basis for the 4. Envirormlmetai and Siting . Antitrust and Financial Review 

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Comments and suggestions for improvements In these guides are Printing Office price. A subscription service for future guides in spe encouraged at all times, and guides will be revised, as pPro riata, ~cific livisions Is available through the Government Printing Office. 

to accommodate comments and to reflect new Informat on or Information an the subscription service and current GPO prim may experience. This guide was revised as a result of substantive com- be obtained by writing the U.S. Nuclear Regulatory Commission, ments received from the public and additional staff review. Washington, D.C. 20555, Attention: Publications Sales Manager.
monitoring. Preoperational data is submitted to the NRC as 

part of the application process. Operational data is reported 

as required by § 40.65 of 10 CFR Part 40 and specific 

license conditions and at times of license renewal. 

C. REGULATORY POSITION 

I. PREOPERATIONAL MONITORING 

An acceptable preoperational monitoring program is 

described below and summarized in Table I. At least twelve 

consecutive months of data, including complete soil sam

pling, direct radiation, and radon flux data, should be sub

mitted to the NRC staff prior to any major site construc

tion. A complete preoperational report with twelve consec

utive months of data should be submitted prior to beginning 

milling operations. Prior to the start of local mining opera

tions, if possible, monitoring data, including airborne radon 

measurements, should be submitted to the NRC staff. 

Applicants may propose alternatives to this preopera

tional program. However, equivalent alternatives should be 

proposed for the operational program so that the programs 

remain compatible. 

1.1 Preoperational Sampling Program 

1.1.1 Air Samples 

Air particulate samples should be collected continuously 

at a minimum of three locations at or near the site bound

ary. If there are residences or occupiable structures within 

10 kilometers of the site, a continuous outdoor air sample 

should be collected at or near the structure with the highest 

predicted airborne radionuclide concentration due to milling 

operations and at or near at least one structure in any area 

where predicted doses exceed 5 percent of the standards in 

40 CFR Part 190. A continuous air sample should also be 

collected at a remote location that represents background 

conditions at the mill site; in general, a suitable location 

would be in the least prevalent wind direction from the site 

and unaffected by mining or other milling operations. 

Normally, filters for continuous ambient air samples are 

changed weekly or more often as required by dust loading. 

The sampling locations should be determined according 

to the projected site and milling operation. Preoperational 

sampling locations should be the same as operational 

locations. The following factors should be considered in 

determining the sampling locations: (1) average meteorolog

ical conditions (windspeed, wind direction, atmospheric 

stability), (2) prevailing wind direction, (3) site boundaries 

nearest to mill, ore piles, and tailings .piles, (4) direction of 

nearest occupiable structure (see footnotes of Tables I and 

2), and (5) location of estimated maximum concentrations 

of radioactive materials. 

Samples should be collected continuously, or for at least 

one week per month, for analysis of radon-222. The sam

pling locations should be the same as those for the continu

ous air particulate samples.

1.1.2 Water Samples

Samples of ground water should be collected quarterly 

from at least three sampling wells located hydrologically 

down gradient from the proposed tailings area, at least 

three locations near other sides of the tailings area, and one 

well located hydrologically up gradient from the tailings 

area (to serve as a background sample). The location of the 

ground-water sampling wells should be determined by 

hydrological analysis of the potential movement of seepage 

from the tailings area, and the basis for choosing these loca

tions should be presented when data is reported. Wells drilled 

close to the tailings for the specific purpose of obtaining 

representative samples of ground water that may be affect

ed by the mill tailings are preferable to existing wells. 

Ground-water samples should also be collected quarterly 

from each well within two kilometers of the proposed 

tailings area that is or could be used for drinking water, 

watering of livestock, or crop irrigation. 

Samples of surface water should be collected quarterly 

from each onsite water impoundment (such as a pond or lake) 

and any offsite water impoundment that may be subject to 

seepage from tailings, drainage from potentially contami

nated areas, or drainage from a tailings impoundment failure. 

Samples should be collected at least monthly from 

streams, rivers, any other surface waters or drainage systems 

crossing the site boundary, and any offsite surface waters 

that may be subject to drainage from potentially con

taminated areas or from a tailings impoundment failure. 

Any stream beds that are dry part of the year should be 

sampled when water is flowing. Samples should be collected 

at the site boundary or at a location immediately downstream 

of the area of potential influence. 

1.1.3 Vegetation, Food, and Fish Samples 

Forage vegetation should be sampled at least three times 

during the grazing season in grazing areas in three different 

sectors having the highest predicted airborne radionuclide 

concentration due to milling operations. 

At least three samples should be collected at time of 

harvest or slaughter or removal of animals from grazing for 

each type of crop (including vegetable gardens) or livestock 

raised within three kilometers of the mill site. 

Fish (if any) samples should be collected semiannually 

from any bodies of water that may be subject to seepage or 

surface drainage from potentially contaminated areas or 

that could be affected by a tailings impoundment failure. 

1.1.4 Soil and Sediment Samples 

Prior to initiation of mill construction (and if possible 

prior to mining), one set of soil samples should be collected 

as follows: 

a. Surface-soil samples (to a depth of five centimeters) 

should be collected using a consistent technique at 300-

4.14-2
meter intervals in each of the eight compass directions out 

to a distance of 1500 meters from the center of the milling 

area. The center is defined as the point midway between 

the proposed mill and the tailings area. 

b. Surface-soil samples should also be collected at each 

of the locations chosen for air particulate samples. 

c. Subsurface samples (to a depth of 1 meter) should be 

collected at the center of the milling area and at a distance 

of 750 meters in each of the four compass directions. 

Soil sampling should be repeated for each location 

disturbed by site excavation, leveling, or contouring. 

One set of sediment samples should be collected from the 

same surface-water locations as described in Section 1.1.2. 

For surface water passing through the site, sediment should 

be sampled upstream and downstream of the site. Samples 

should be collected following spring runoff and in late 

summer, preferably following an extended period of low flow. 

In each location, several sediment samples should be col

lected in a traverse across the body of water and composited 

for analysis. 

1.1.5 Direct Radiation 

Prior to initiation of mill construction (and if possible 

prior to mining), gamma exposure rate measurements 

should be made at 150-meter intervals in each of the eight 

compass directions out to a distance of 1500 meters from 

center of the milling S-the area. Measurements should also be 

made at the sites chosen for air particulate samples. 

Measurements should be repeated for each location 

disturbed by site excavation, leveling, or contouring. 

Gamma exposure measurements should be made with 

passive integrating devices (such as thermoluminescent 

dosimeters), pressurized ionization chambers, or properly 

calibrated portable survey instruments. 

Direct radiation measurements should be made in dry 

weather, not during periods following rainfall or when soil 

is abnormally wet. 

1.1.6 Radon Flux Measurements 

Radon-222 flux measurements should be made in three 

separate months during normal weather conditions in the 

spring through the fall when the ground is thawed. The 

measurements should be made at the center of the milling 

area and at locations 750 and 1500 meters from the center 

in each of the four compass directions. Measurements 

should not be taken when the ground is frozen or covered 

with ice or snow or following periods of rain. 

1.2 Analysis of Preoperational Samples 

Air particulate samples should be analyzed for natural 

uranium, thorium-230, radium-226, and lead-2 10.

Air samples collected for radon should be analyzed for 

radon-222. 

The results of analyses of air samples should be used to 

determine the radionuclide concentrations for the sampling 

locations. 

All ground-water samples collected near the tailings area 

should be analyzed for dissolved natural uranium, thorium

230, radium-226, polonium-210, and lead-210. Ground-water 

samples from sources that could be used as drinking water 

for humans or livestock or ctop irrigation should also be 

analyzed for suspended natural uranium, thorium-230, 

radium-226, polonium-2 10, and lead-210. 

Surface-water samples from water impoundments should 

be analyzed quarterly for natural uranium, thorium-230, and 

radium-226 and semiannually for lead-210 and polonium-2 10. 

The samples should be analyzed separately for dissolved and 

suspended radionuclides. 

Surface-water samples from flowing surface water should 

be analyzed monthly for natural uranium, thorium-230 and 

radium-226 and semiannually for lead-210 and polonium-210. 

The samples should be analyzed separately for dissolved and 

suspended radionuclides. 

The results of analyses of water samples should be used to 

determine the radionuclide concentrations for the sampling 

locations. 

Vegetation, food, and fish (edible portion) samples 

should be analyzed for natural uranium, thorium-230, 

radium-226, lead-210, and polonium-210. 

All soil samples should be analyzed for radium-226. Soil 

samples collected at air particulate sampling locations and 

ten percent of all other soil samples (including at least one sub

surface set) should be analyzed for natural uranium, thorium

230, and lead-210. Analysis of extra soil samples may be 

necessary for repeat samples collected at locations disturbed 

by site excavation, leveling, or contouring. 

Sediment samples should be analyzed for natural uranium, 

thorium-230, radium-226, and lead-210. 

2. OPERATIONAL MONITORING 

An acceptable monitoring program to be conducted during 

construction and after the beginning of milling operations 

is described below and summarized in Table 2. The results 

of this program should be summarized quarterly and sub

mitted to NRC semiannually pursuant to § 40.65 of 10 CFR 

Part 40. An acceptable reporting format is shown in Table 3. 

2.1 Operational Sampling Program 

2.1.1 Stack Sampling 

Effluents from the yellowcake dryer and packaging stack 

should be sampled at least quarterly during normal opera

tions. The sampling should be isokinetic, representative,

4.14-3
and adequate for determination of the release rates and 

concentrations of uranium. The sampling should also be 

adequate for the determination of release rates and con

centrations of thorium-230, radium-226, and lead-210 

if this data cannot be obtained from other sources. 

Other stacks should be sampled at least semiannually. 

The samples should be representative (not necessarily 

isokinetic) and adequate for the determination of the 

release rates and concentrations of uranium, thorium-230, 

radium-226, and lead-2 10. 

All stack flow rates should be measured at the time of 

sampling. 

2.1.2 Air Samples 

Air particulate samples should be collected continuously 

at (1) a minimum of three locations at or near the site 

boundary, (2) the residence or occupiable structure within 

10 kilometers of the. site with the highest predicted air

borne radionuclide conicentration, (3) at least one residence 

or occupiable structure where predicted doses exceed 5 

percent of the standards in 40 CFR Part 190, and (4) a 

remote location representing background conditions. The 

sampling locations should be the same as those for the 

preoperational air samples (see Section 1.1.1). The sampling 

should be adequate for the determination of natural ura

nium, thorium-230, radium-226, and lead-2 10. 

Normally, filters for continuous ambient air samples are 

changed weekly or more often as required by dust loading. 

Samples should be collected continuously at the same 

locations, or for at least one week per month, for analysis 

of radon-222. 

2.1.3 Water Samplea 

Samples of ground water should be collected from at 

least three sampling wells located hydrologically down 

gradient from the tailings area and from one background 

well located hydrologically up gradient. The samples should 

be collected monthly through the first year of operation 

and quarterly thereafter from the same downslope and 

background wells that were used for preoperational samples 

(see Section 1.1.2). 

Samples should be collected at least quarterly from each 

well within two kilometers of the tailings area that is or 

could be used for drinking water, watering of livestock, or 

crop irrigation. 

Samples should be collected at least quarterly from each 

onsite water impoundment (such as a pond or lake) and any 

offsite water impoundment that may be subject to seepage 

from tailings, drainage from potentially contaminated areas, 

or drainage from a tailings impoundment failure. 

Samples should be collected at least monthly from any 

surface water crossing the site boundary and offsite streams 

or rivers that may be subject to drainage from potentially 

4.14-4

contaminated areas or from a tailings impoundment failure. 

Stream beds that are dry part of the year should be sampled 

when water is flowing. Operational samples should be 

collected upstream and downstream of the area of potential 

influence. 

Any unusual releases (such as surface seepage) that are 

not part of normal operations should be sampled. 

.2.1.4 Vegetation, Food, and Fish Samples 

Where a significant pathway to man is identified in 

individual licensing cases, vegetation, food, and fish samples 

should be collected as described below. 

Forage vegetation should be sampled at least three times 

during the grazing season in grazing areas in three different 

sectors having the highest predicted airborne radionuclide 

concentration due to milling operations. 

At least three samples should be collected at the time of 

harvest or slaughter or removal of animals from grazing for 

each type of crop (including vegetable gardens) or livestock 

raised within three kilometers of. the mill site. 

Fish (if any) samples should be collected semiannually 

from any bodies of water that may be subject to seepage or 

surface drainage from potentially contaminated areas or 

that could be affected by a tailings impoundment failure. 

2.1.5 Soil and Sediment Samples 

Surface-soil samples should be collected annually using a 

consistent technique at each of the locations chosen for air 

particulate samples as described in Section 2.1.2. 

Sediment samples should be collected annually from the 

surface-water locations described in Section 2.1.3. 

2.1.6 Direct Radiation 

Gamma exposure rates should be measured quarterly at 

the sites chosen for air particulate samples as described in 

Section 2.1.2. Passive integrating devices (such as thermo

luminescent dosimeters), pressurized ionization chambers, 

or properly calibrated portable survey instruments should 

be used (see Regulatory Guide 4.13). 

2.2 Analysis of Operational Samples 

Samples from the yellowcake dryer and packaging stack 

should be analyzed for natural uranium. Samples should 

also be analyzed for thorium-230, radium-226, and lead-2 10 

if this data cannot be obtained from other sources such as 

isotopic analysis of yellowcake product. Samples from 

other stacks should be analyzed for natural uranium, 

thorium-230, radium-226, and lead-2 10. 

Air particulate samples should be analyzed for natural 

uranium, thorium-230, radium-226, and lead-2 10. 

Air samples collected for radon should be analyzed for 

radon-222.
The results of analyses of air samples should be used to 

determine the radionuclide release rates for the stacks and 

the radionuclide concentrations for the stacks and other 

-J sampling locations. 

Water samples should be analyzed for natural uranium, 

thorium-230, radium-226, polonium-210, and lead-210. 

Ground-water samples from sources not expected to be 

used as drinking water should be analyzed for dissolved 

radionuclides. Ground-water samples from sources that 

could be used as drinking water for humans or livestock and 

all surface-water samples should be analyzed separately for 

dissolved and suspended radionuclides. These results should 

be used to determine radionuclide concentrations for 

ground water and natural bodies of water. 

All vegetation, food, and fish (edible portion) samples 

should be analyzed for radium-226 and lead-210. 

All soil samples should be analyzed for natural uranium, 

radium-226, and lead-210. 

All sediment samples should be analyzed for natural 

uranium, thorium-230, radium-226, and lead-210. 

3. QUALITY OF SAMPLES 

Provisions should be made to ensure that representative 

samples are obtained by use of proper sampling equipment, 

proper locations of sampling points, and proper sampling 

procedures (see bibliography). 

Air samples may be composited for analysis if (1) they 

are collected at the same location and (2) they represent a 

sampling period of one calendar quarter or less. Air samples 

should not be composited if (1) they represent a sampling 

period of more than one calendar quarter, (2) they are from 

different sampling locations, or (3) the samples are to be 

analyzed for radon-222. 

Samples collected for analysis of radon-222 should be 

analyzed quickly enough to minimize decay losses. 

Samples other than air samples should not be composited. 

4. SOLUBILITY OF AIRBORNE RADIOACTIVE 

MATERIAL 

Table II of Appendix B, "Concentrations in Air and 

Water Above Natural Background," to 10 CFR Part 20 lists 

separate values for soluble and insoluble radioactive mate

rials in effluents. In making comparisons between airborne 

effluent concentrations and the values given in Table II of 

Appendix B to 10 CFR Part 20, the maximum permissible 

concentrations for insoluble materials should be used. 

5. LOWER LIMIT OF DETECTION

The lower limits of detection for stack effluent samples 

should be 10% of the appropriate concentration limits 

listed in Table II of Appendix B to 10 CFR Part 20.

The lower limits of detection for analysis of other 

samples should be as follows: 

U-natural, Th-230, Ra-226 in air - I x 10-16 Ci/ml 

Pb-210 in air -2 x I 0"' 5 iCi/ml 

Rn-222 - 2 x 10"1°/Ci/ml 

U-natural, Th-230, Ra-226 in - 2 x I010 0 .LCi/ml 

water 

Po-210 in water - lx 10-9j Ci/ml 

Pb-210 in water - Ix 10-9 paCi/ml 

U-natural, Th-230, Ra-226, - 2 x 10-7/ Ci/g 

Pb-210 in soil and sediment 

(dry)

U-natural, Th,230 in vegetation, 

food, and fish (wet) 

Ra-226 in vegetation, food, and 

fish (wet) 

Po-210,.Pb-210 in vegetation, 

food, and fish (wet)

- 2 x 10-7/ Ci/kg 

- 5 x 10-8/ .Ci/kg 

-I x 10 6 tCi/kg

Obviously, if the actual concentrations of radfonuqlides 

being sampled are higher than the lower limits of detection 

indicated above, the sampling and analysis procedures need 

only be adqquate to measure the actual concentrations. 

In such cases, the standard deviation estimated for random 

error of the analysis should be no greater than 10% of the 

measured value. 

An acceptable method for calculating lower limits of 

detection is described in the appendix to this guide. 

6. PRECISION AND ACCURACY OF RESULTS 

6.1 Error Estimates 

The random error associated with the analysis of samples 

should always be calculated. The calculation should take 

into account all significant random uncertainties, not 

merely counting error. 

If the analyst estimates that systematic errors associated 

with the analysis are significant relative to the random 

error, the magnitude of the systematic error should be 

estimated, 

6.2 Calibration 

Individual written procedures should be prepared and 

used for specific methods of calibrating all sampling and 

measuring equipment, including ancillary equipment. The 

procedures should ensure that the equipment will operate 

with adequate accuracy and stability over the range of its 

intended use. Calibration procedures may be compilations

4.14-5
of published standard practices, manufacturers' instructions 

that accompany purchased equipment, or procedures 

written in-house. Calibration procedures should identify the 

specific equipment or group of instruments to which the 

procedures apply. 

To the extent possible, calibration of measuring equip

ment should be performed using radionuclide standards 

certified by the National Bureau of Standards or standards 

obtained from suppliers who participate in measurement 

assurance activities with the National Bureau of Standards 

(see Regulatory Guide 4.15). 

Calibrations should be performed at regular intervals, at 

least semiannually, or at the manufacturer's suggested inter

val, whichever is more frequent. Frequency of calibration 

should be based on the stability of the system. If appro

priate, equipment may be calibrated before and after use 

instead of at arbitrarily scheduled intervals. Equipment 

should be recalibrated or replaced after any repairs or when

ever it is suspected of being out of adjustment, excessively 

worn, or otherwise damaged and -not operating properly. 

Functional tests, i.e., routine checks performed to demon

strate that a given instrument is in working condition, may 

be performed using sources that are not certified by the 

National Bureau of Standards. 

6.3 Quality of Results 

A continuous program should be prepared and imple

mented for ensuring the quality of results and for keeping 

random and systematic uncertainties to a minimum. The 

procedures should ensure that samples and measurements 

are obtained in a uniform manner and that samples are not 

changed prior to analysis because of handling or because of 

their storage environment. Tests should be applied to 

analytical processes, including duplicate analysis of selected 

effluent samples and periodic cross-check analyses with 

independent laboratories (see Regulatory Guide 4.15). 

7. RECORDING AND REPORTING RESULTS 

This section provides guidelines for recording all results. 

Reports submitted to NRC should be prepared using these 

guidelines and the format shown in Table 3 of this guide. 

7.1 Sampling and Analysis Results 

7.1.1 Air and Stack Samples 

For each air or stack sample, the following should be 

recorded: 

I. Location of sample. 

2. Dates during which sample was collected. 

3. The concentrations of natural uranium, thorium

230, radium-226, lead-210, and radon-222 for all 

samples except stack samples.

4. The cconcentration of natural uranium, thorium

230, radium-226, and lead-210 for stack effluent 

samples. 

5. The percentage of the appropriate 'concentration 

limit as shown in Table II oi Appendix B to 10 

CFR Part 20. 

6. The estimated release rate of natural uranium, 

thorium-230, radium-226, and lead-210 for stack 

effluent samples. 

7. The flow rate of each stack. 

7.1.2 Liquid Samples 

For each liquid sample, the following should be recorded: 

1. Location of sample. 

2. Type of sample (ground or surface water). 

3. Date of sample collection. 

4. The concentrations of natural uranium, thorium-230, 

radium-226, polonium-210, and lead-210. (If separate 

analyses were conducted for dissolved and suspended 

radionuclides, report each result separately.) 

7.1.3 Other Samples 

For other samples, the following should be recorded: 

1. Location of sample. 

2. Date of sample collection. 

3. Type of sample (vegetation, soil, radon-222 flux, 

gamma exposure rate, etc.). 

4. Analytical result (radionuclide concentration, gamma 

exposure rate, radon flux rate, etc.). 

7.1.4 Error Estimates 

Reported results should always include estimates of 

uncertainty. The magnitude of the random error of the 

analysis to the 95% uncertainty level should be reported for 

each result. If significant, an estimate of the magnitude of 

the systematic error should also be reported. 

7.2 Supplemental Information 

The following information should be included in each 

monitoring report submitted to NRC: 

L. Name of facility, location, docket number, and 

license number. 

2. Description of sampling equipment and discussion of 

how sampling locations were chosen.

4.14-6
3. Description of sampling procedures, including sam

pling times, rates, and volumes. 

4. Description of analytical procedures. 

5. Description of calculational methods. 

6. Discussion of random and systematic error estimates, 

including methods of calculation and sources of 

systematic error. 

7. The values of the lower limits of detection, along 

with a description of the calculation of the lower 

limit of detection. 

8. The values of maximum permissible concentration 

from Table II of Appendix B to 1 0 CFR Part 20 used 

in any calculations. 

9. Discussion of the program for ensuring the quality of 

results. 

10. Description of calibration procedures. 

II. Discussion of any unusual releases, including the 

circumstances of the release and any data available on 

the quantities of radionuclides released. 

7.3 Units 

Radionuclide quantities should be reported in curies. 

Radionuclide concentrations should be reported in micro

curies per milliliter for air and water, microcuries per gram 

-' for soil and sediment, and microcuries per kilogram for 

vegetation, food, or fish. Direct radiation exposure rates 

should be reported in milliroentgens per calendar quarter.

Radon flux rates should be reported in picocuries per 

square meter per second. Stack flow rates should be reported 

in cubic meters per second. (In the International System of 

Units, a curie equals 3.7 x 1010 becquerels, a microcurie 

equals 3.7 x 104 becquerels, and a milliliter equals 10-6 

cubic meters.) 

Estimates of random error should be reported in the 

same units as the result itself. Estimates of systematic error 

should be reported as a percentage of the result. 

Note: The Commission has discontinued the use in 10 

CFR Part 20 of the 6pecial curie definitions for natural 

uranium and natural thorium (39 FR 23990, June 28, 

1974). Reports to the Commission should use units con

sistent with this change. 

7.4 Significant Figures 

Results should not be reported with excessive significant 

figures, so that they appear more certain than they actually 

are. The reported estimate of error should contain no more 

than two significant figures. The reported result itself 

should have the same number of decimal places as the 

reported error. 

7.5 Format 

Reports should be submitted according to the format 

shown in Table 3. 

The term "not detected," "less than the lower limit of 

detection (LLD)," or similar terms should never be used. 

Each reported result should be a value and its associated 

error estimate, including values less than the lower limit 

of detection or less than zero.

4.14-7
TABLE 1 

PREOPERATIONAL RADIOLOGICAL MOITORING PROGRAM FOR URANIUM HILLS

Type of Sample Sample Collection Sample Analysis 

Type of Number Location Method Frequency Frequency Analysis 

AIR

At or near the site 

boundaries 

At or close to the 

nearest(b) residence(s) 

or occupiable offsite 

structure(s) (if with

in 10 ke of site) 

-At a control or back

ground location remote 

from site(c)

Five or Same locations as for 

more., air particulates

Continuous

COntinuous 

Continuous or 

at least one 

week per month 

representing 

about the same 

period each 

month

Weekly filter change or more frequently as required by dust 

loading 

Weekly filter change 

or more frequently as required by dust 

loading 

Weekly filter change or more frequently as required by dust • 

loading 

Continuous

Quarterly composites 

of weekly samples 

Quarterly composites 

of weekly samples 

Quarterly composites 

of weekly samples 

Each sample or continuous

Natural uranium, 

Ra-226, Th-230, 

and Pb-210 

Natural uranium, 

Ra-226, Th-230, 

and Pb-210, 

Natural urarviia, 

Ra-226, Th-230, 

and Pb-210 

Rn-222

WATER 

Ground Water(e) Six or Wells located around more future tailings dis

posal area. At least 

three wells hydrologi cally down gradient from disposal area. At 

least three located on other sides of tailings 

disposal area.(f) 

One from Wells within 2 km of 

each well tailings disposal area. 

that are or could be used 

for potable water supplies, 

watering of livestock, or crop irrigation. 

One Well located hydrologi

cally up gradient from 

tailings disposal area to serve as control or background location.

(

Grab quarterly

Grab 

Grab

Quarterly 

Quarterly

Quarterly

Quarterly 

Quarterly

Dissolved natural 

uranium, Ra-226, 

Th-230, Pb-210, 

and Po-210

Dissolved and 

suspended natural 

uranium, Ra-226, 

Th-230, Pb-210, 

and Po-210 

Dissolved natural 

uranium, Ra-226, 

Th-230, Pb-210, 

and Po-210

( (

Particulates Three

One.

One

Radon Gas(d)

3
K

TABLE 1 (Continued) 

PREOPERATIONAL RADIOLOGICAL MONITORING PROGRAM FOR URANIUM MILLS

Type of Sample Sample Collection Saple Analysis 

Type of 

.Number Location Method Frequency Frequency Analysis 

Surface Water(g) One from Large permanent onsite Grab Quarterly Quarterly Suspended and

Surface Water

* water impoundments or offsite impoundments 

that may be subject to 

direct surface drainage 

from potentially con

taminated areas or that 

could be affected by a 

tailings impoundment 

failure. 

Surface waters passing 

through the site(n) or offsite surface waters 

that may be subject to 

drainage from potentially 

contaminated areas or that 

could be affected by a tail

ings impoundment failure.

Semiannually

Grab monthly Monthly

Semiannually

aissoivea naLurat 

uranium, Ra-226 

and Th-230 

Suspended and 

dissolved Pb-210 

and Po-210 

Suspended and 

dissolved natural 

uranium, Ra-226, 

Th-230 

Suspended and 

dissolved Pb-210 

and Po-210

Three Grazing areas near the 

site in different sectors 

that will have the highest 

predicted air particulate 

concentrations during 

milling operations. 

Three of Crops, livestock, etc. 

each type raised within 3 km of 

mill site 

Each body Collection of fish (if 

of water any) from lakes, rivers, 

and streams in the site 

environs that may be 

subject to seepage or direct surface runoff 

from potentially con

taienated areas or that 

could be affected by a 

tailings impoundment 

failure

Grab 

Grab 

Grab

Three times 

during grazing season 

Time of harvest 

or slaughter 

Semiannually

each body 

of water

One from 

each body of water

'0

VEGETATION, 

FOOD, AND FISH 

Vegetation 

Food

Fish

Three times

Once 

Twice

Natural 

Ra-226, 

Pb-210, 

Po-210 

Natural 

Ra-226, 

Pb-210, 

Natural 

Ra-226, 

Pb-210,

uranium, 

Th-230, 

and 

uranfi um, 

Th-230, 

and Po-210 

urani um, 

Th-230, 

and Po-210
TABLE 1 (Continued) 

PREOPERATIONAL RADIOLOGICAL MONITORING PROGRAM FOR URANIUM MILLS 

Type of Sample Sample Collection Sample Analysis 

Type of Number Location Method Frequency Frequency Analysis

SOIL AND SEDIMENT 

Surface Sotl(k) 

Surface Soil 

Subsurfame Soil 

Profile(I) 

Sediment(O) 

DIRECT RADIATION

Grab 

Grab 

Grab

Once prior to 

site construction. 

Repeat for loca

tion disturbed by 

excavation, leveling, or contouring 

Once prior to 

site construction 

Once prior to site 

construction. 

Repeat for locations 

disturbed by con

struction. 

Once following spring 

runoff and late 

summer following 

period of extended 

low flow

Grab

Up to 300-meter intervals to a forty distance of 1500 meters in 

each of 8 directions from 

center of milling area 

Five or At same locations used more for collection of air 

particulate samples. 

Five At center reference loca

tion and at distances of 

750 meters in each of 

4 directions. 

Two from Up and downstream of sur each face waters passing through 

stream site or from offsite sur face waters that may be 

subject to direct runoff 

from potentially contami

nated areas or that 

could be affected by a tailings impoundment 

failure 

One from Onsite water impoundments each (lakes, ponds, etc), or off

water site impoundments that may impound- be subject to direct surface 

ment runoff from potentially 

.contaminated areas or that 

could be affected by tailings impoundment failure 

Up to 150-meter intervals to 

eighty a distance of'1500 meters 

in each of 8 directions 

from center of milling area or at a point equidis

tant from milling area(i) 

and tailings disposal area.

Once prior to site 

construction

Once prior to site 

construction. Repeat 

for areas disturbed 

by site preparation 

or construction.

Once All samples for 

Ra-226, 10% of 

samples natural 

uranium, Th-230, 

and Pb-210

Once 

Once

Natural uranium, 

Ra-226, Th-230, and 

Pb-210 

Ra-226 (all samples) 

Natural uranium, 

Th-230, and Pb-210 

(one set of samples)

Twice Natural uranium, 

Ra-226, Th-230, 

and Pb-210

Once Natural uranium, 

Ra-226, Th-230, 

and Pb-210

Once Gamma exposure rate, 

using passive 

integrating device 

such as TLD, pressurized 

ionization chamber, or 

properly calibrated 

portable survey 

instrument.

( (

Grab

0

(
TABLE 1 (Continued) 

PREOPERATIONAL RADIOLOGICAL MONITORING PROGRAM FOR URANIUM MILLS

Type of Sample Sample Collection Sample Analysis 

Type of 

Number Location Method Frequency Frequency Analysis 

Five or At same locations used for Once prior to Once Gamma exposure ra

RADON FLUX(n)

more collection of particulate 

samples

Up to At center reference location 

ten and at distances of 750 and 

1500 meters in each of 4 

directions.

site construction

One sample 

during each of 

three months.

Each sample

te,

using passive inte

grating device, pres

surized ionization 

chamber, or properly 

calibrated portable 

survey instrument. 

Radon-222 flux
TABLE 2 

OPERATIONAL RADIOLOGICAL MONITORING PROGRAM FOR URANIUM MILLS

Type of Sample Sample Collection Sample Analysis 

Type of 

Number Location Method Frequency Frequency Analysis 

STACKS

Particulates 

Particulates 

AIR 

Particulates

Radon Gas

WATER 

Ground Water

One for Yellowcake dryer 

each stack and packaging stack(s) 

One for Other stacks 

each stack

Locations at or near 

the site boundaries and 

in different sectors 

that have the highest 

predicted conceotra

tions of airborne 

particulates(b), 

At the nearest resi

dence(s) or occupiable 

structure(s) 

Control Location(s)(c) 

Same locations as for 

air particulates

Hydrologically down 

gradient and rela

tively close to the 

tailings impoundment f) 

Hydrologically up 

gradient (i.e., not 

influenced by seepage 

from tailings)

Isokinetic quarterly

Representa tive grab 

Continuous(a)

Semiannually

Weekly filter change, or more frequently as 

required by dust 

loading

Continuous Weekly filter change, 

or more frequently 

as required by dust 

loading 

Continuous Weekly filter change, 

or more frequently 

as required by dust 

loading 

Continuous At least one week per 

or at least calendar month repre

one week (d) senting approximately 

per month the same period each 

month

Grab 

Grab

Monthly (first year) Quarterly (after 

first year)

Quarterly

Each sample

Each sample

Quarterly composite, by location, of 

weekly samples 

Quarterly composite, 

by location, of 

weekly samples 

Quarterly composite, 

by location, of 

weekly somples 

Monthly

Monthly (first year) Quarterly (after first 

year) 

Quarterly

(

Natural uranium, Th-230, Ra-226, and 

Pb-210 if not avail

able from other sources. 

Measure stack flow rate 

semiannually. 

Natural uranium 

Th-230, Ra-226, and 

Pb-210. Measure stack 

flow.

Natural uranium, Ra-226, Th-230, 

and Pb-210 

Natural uranium, 

Ra-226, Th-230, 

and Pb-210 

Natural uranium, 

Ra-226, Th-230, 

and Pb-210 

Rn-222

Dissolved natural uranium, Ra-226, 

Th-230, Pb-210, 

and Po-210(e) 

Dissolved natural 

uranium, Ra-226, 

Th-230, Pb-210 

and Po-210

(

Three 

One or more 

One 

Five or more

Three or more

At least one con

trol sample

(

t•3
1\

TABLE 2 (Continued) 

OPERATIONAL RADIOLOGICAL MONITORING PROGRAM FOR URANIUM MILLS

Type of Sample Sample Collection Sample Analysis 

Number Type of Location Method Frequency Frequency Analysis One from Each well used for Grab Quarterly Quarterly Dissolved and each well drinkina wat r or.

Surface Water Two from 

each water 

body

4t 

w~

One from 

each water 

body

VEGETATION, FOOD, 

AND FISH 

Vegetation 

or Forage(o)

watering of live

stock or crops within 

2 km of the tailings 

impoundment 

Surface waters passing Grab 

through the m111 site or offsite surface 

waters that are suffi

ciently close to the 

site to be subject to 

surface drainage from 

potentially contami

nated areas or that 

could be influenced by 

seepage from the tail

ings disposal area. (h) 

One sample collected up

stream of mill site and one sample collected at 

the downstream site 

boundary or at a loca

tion immediately down

stream of location of 

potential influence 

Large water impound- Grab 

ments (i.e., lakes, 

reservoirs) near the 

mill site that are sufficiently close 

to the site to be sub

ject to drainage from 

potentially contaminated areas or that could be 

influenced by seepage 

from the tailings 

disposal area.

From animal grazing areas near the mill 

site in the direction of 

the highest predicted 

airborne radionuclide 

concentrations

Quarterly 

Quarterly

Grab Three times during 

grazing season

Quarterly 

Quarterly

Each sample

suspendea natural 

uranium, Ra-226, 

Th-230, Pb-210, 

and Po-210 

Dissolved and 

suspended natural 

uranium, Ra-226, 

Th-230, Pb-210, 

and Po-210(g) 

Dissolved and 

suspended natural 

uranium, Ra-226, 

Th-230, Pb-210, 

and Po-210

Ra-226.and Pb-210 Three or more
TABLE 2 (Continued) 

OPERATIONAL RADIOLOGICAL MONITORING PROGRAM FOR URANIUM MILLS

Type of Sample Sample Collection Sample Analysis 

Type of 

Number Location Method Frequency Frequency. Analysis 

Food Three of. Crops, livestock, etc. Grab Time of harvest Once Ra-226 and

each type raised within 3 km of 

mill site 

Each body Collection of fish 

of water (if any) from lakes, 

rivers, and streams 

in the site environs 

that may be subject 

to seepage or direct 

surface runoff from 

potentially contami

nated areas or that 

could be affected by a tailings impound

ment failure

or slaughter 

Grab Semiannually Twi ce

Pb-210 

Ra-226 

and Pb-210

SOIL AND SEDIMENT 

Soil

Sediment

DIRECT RADIATION

Five or more 

One or 

two from 

each water 

body 

Five or 

more

Same as for 

air partic

ulate samples"K) 

Same as surface 

water samples(m) 

Same as for air 

particulate samples

Grab 

Grab

Continuous 

passive in

tegrating 

device

Annually 

Annually

Quarterly change 

of passive dosim

eters

Annually 

Annually 

Quarterly

Natural uranium, 

Ra-226, and Pb-210 

Natural uranium, 

Th-230, Ra-226, 

and Pb-210

Gamma exposure 

rate

( (

Fish

(
Footnotes for Tables 1 and 2: 

(a) Continuous collection means continuous sampler operation with filter change weekly or as required by dust loading, whichever is more frequent. 

(b) The term "nearest" as used here means the location with the highest predicted airborne radionuclide concentrations during milling operations. 

(c) Care should be taken in selection of the control sampling location so that it is representative of the site conditions. In general, a loca

tion in the least prevalent wind direction from the site should provide a suitable location for a control sampling site. 

(d) Various methods are acceptable; for example: (1) Continuous collection of a gaseous air sample with samples being changed about every 

48 hours for a 1-week period or (2) continuous sampling. 

(e) If the sample contains appreciable suspended material, it should be filtered as soon as possible following collection through a membrane 

filter and the filtrate acidified to 1% hydrochloric acid. 

Cf) The location of the ground-water sampling wells should be determined by a hydrological analysis of the potential movement of seepage from 

the tailings disposal area. In general, the objective is to place monitor wells in all directions around the tailings area with the emphasis 

on the down gradient locations. 

(g) Surface-water samples to be analyzed for dissolved and suspended fractions should be filtered as soon as possible following collection 

through a membrane filter and the filtrate acidified to 1% hydrochloric acid. 

(h) Natural drainage systems (dry washes) that carry surface runoff from the site following a precipitation event should be sampled following 

the event but at a frequency not greater than monthly. 

(i) The milling area refers to the-area that includes ore storage pads, mill buildings, and other processing areas. 

(j) Thermoluminescent dosimeters should contain two or more chips or otherwise provide for two readings per exposure period (see Regulatory 

Guide 4.13). 

(k) Surface soil samples should be collected using a consistent technique to a depth of 5 cm. 

.(1) Subsurface soil profile samples should be collected to a depth of one meter. Samples should be divided into three equal sections for 

analysis. 

(m) Several samples should be collected at each location and composited for a representative. sample. 

(n) Radon exhalation measurements should not be taken during periods when the ground is frozen or covered with ice or snow or following 

periods of rain. It is recommended that these measurements be taken in the spring through the fall during normal weather conditions. 

(o) Vegetation or forage sampling need be carried out only if dose calculations indicate that the ingestion pathway from grazing animals is a potentially significant exposure pathway (an exposure pathway should be considered important if the predicted dose to an individual would 

exceed 5% of the applicable radiation protection standard).
TABLE 3 (a) 

SAMPLE FORMAT FOR REPORTING MONITORING DATA

1. STACK SAMPLES 

For each sample analyzed, report the

a. 

b. 

C.

following information:

Date sample was collected 

Location of sample collectjon 

Stack flow rate (mr/sec)

Cet•centration 

0(0ct/01)

Error Estimate(b) 

(jiCi/ol)

Release Rate 

(Ci/qr)

Error Estimate 

(Ci/qr)

2. AIR SAMPLES 

For each sample analyzed, report the following information: 

a. Date sample was collected 

b. Location-of sample collection

Concentration 

(peC/ml)

Error Estimate 

(cti/,1)

(a)Thls table Illustrates format only. It is not a complete list of data to be reported. (See text of guide and Tables 1 and 2.) 

(b)Error estimate should be calculated at 95% uncertainty level, based on all sources of random error, not merely counting error. 

Significant systematic error should be reported separately. See Sections 6.1, 7.1.4, and 7.3. 

(c)All calculations of lower limits of detection (LLD) and percentages of maximum permissible concentration (MPC) should be included as 

supplemental information.

( (

Radionuclide 

U-nat 

Th-230 

Ra-226 

Pb-210

LLDWc 

(Pcil/ml) % MPC(c)

Radionuclide 

U-nat 

Th-230 

Ra-226 

Pb-210 

Rn-222

LLO 

(Wci/ml) % HPC

(
I"

TABLE 3 (Continued) 

"SAMPLE FORMAT FOR REPORTING MONITORING DATA 

3. LIQUID SAMPLES 

For each sample analyzed, report the following information:

a. 

b. 

c.

Date sample was collected 

Location of sample collection 

Type of sample(for example: surface, ground, drinking, stock, or irrigation)

Radionuclide 

U-nat (dissolved) 

U-nat (suspended)(d) 

Th-230 (dissolved) 

Th-230 (suspended)(d) 

Ra-226 (dissolved) Ra-226 (suspended)(d) 

Pb-210 (dissolved) 

Pb-210 (suspended)(d) 

Po-210 (dissolved) 

Po-210 (suspended)(d)

Concentration 

. (pCi/ml)

Error Estimate 

(pCffml)

4. VEGETATION, FOOD, AND FISH SNIPLES 

For each sample analyzed, report the following Information:

a. 

b. 

c.

Date sample was collected 

Location of sample collection 

Type of sample and portion analyzed

Concentration 

(pCikg wet)

Error Estimate 

(pCi/kg)

(d)Not l1 samples must be analyzed for suspended radionuclides. See Sections 1.2 and 2.2 of this guide.

LLD 

(uci/al)

Radionuclide 

U-nat 

Th-230 

Ra-226 

Pb-210 

Po-210

LLD 

(pCi/ko)
TABLE 3 (Continued) 

SAMPLE FORMAT FOR REPORTING MONITORING DATA 

5. SOIL AND SEDIMENT SAMPLES 

For each sample analyzed, report the following information:

a. 

b. 

c.

Date sample was collected 

Location of sample collection 

Type of sample and portion analyzed 

Concentration

Radionuclide (pCi/g 

U-nat 

Th-230 

Ra-226 

Pb-210 

Po-210 

6. DIRECT RADIATION MEASUREMENTS

Error Estimate 

,(iCi/g)

For each measurement, report the dates covered by the measurement and the following information: 

Exposure Rate Error Estimate 

Location (mR/qr) (mR/qr) 

7. RADON FLUX MEASUREMENTS 

For each measurement, report the dates covered by the measurement and the following information: 

Flux Error Estimate 

Location (pCi/m 2

-sec) (pCi/m 2-sec)

( (

LLD 

(C i /q)

00

(

)
BIBLIOGRAPHY

ANSI N13.1-1969, "Guide to Sampling Airborne Radio

active Materials in Nuclear Facilities," American National 

Standards Institute, Inc., 1430 Broadway, New York, 

N.Y. 10018. 

ANSI N 13.8-1973, "Radiation Protection in Uranium Mines," 

American National Standards Institute, Inc., 1430 Broadway, 

New York, N.Y. 10018. 

ANSI N14.10-1974, "Specification and Performance of 

Onsite Instrumentation for Continuously Monitoring Radio

activity in Effluents," American National Standards Institute, 

Inc., 1430 Broadway, New York, N.Y. 10018. 

Cavallo, L.M. et al., "Needs for Radioactivity Standards and 

Measurements in Different Fields," Nuclear Instruments and 

Methods, Vol. 112, 1973, pp. 5-18. 

"Environmental Radioactivity Surveillance Guide," ORP

SID-72-2, U.S. Environmental Protection Agency, Washing

ton, D.C., 1972. 

"Environmental Surveillance for Fuel Fabrication Plants," 

BNWL-1973, Battelle Pacific Northwest Laboratories, 

Richland, Washington, 1973. 

Friedland, Stephen S. and Lyle Rathbun, "Radon Monitor

ing: Uranium Mill Field Experience with a Passive Detector," 

presented to IEEE Nuclear Science Symposium, San 

Francisco, California, October 1979. 

Fuchs, N. A., 'Sampling of Aerosols," A tmospheric Environ

ment, Vol. 9, 1975, pp. 697-707. 

George, A.C. and A.J. Breslin, "Measurements of Environ

mental Radon with Integrating Instruments," presented at 

the Atomic Industrial Forum Uranium Mill Monitoring 

Workshop, Albuquerque, N.M., 1977. 

George, A.C., A.J. Breslin, and S.F. Guggenheim, "A Cumu

lative Environmental Radon Monitor," Proceedings of Ninth 

Midyear Health Physics SymposiumDenver, Colorado, 1976. 

Gibson, W.M., The Radiochemistry for Lead, NAS-NS 3040, 

National Academy of Sciences-National Research Council, 

1961. 

Grindler, J.E., The Radlochemi.stry of Uranium, NAS-NS 

3050, National Academy of Sciences-National Research 

Council, 1962. 

"A Guide for Environmental Radiological Surveillance at 

ERDA Installations," ERDA 77-24, Department of Energy, 

Washington, D.C., 1977. 

Handbook of Radiochemical Analytical Methods, EPA-680/ 

4-75-001, USEPA, 1975.

Harley, John H., editor, HASL Procedures Manual, HASL

300, USERDA, revised annually. 

Hyde, E.K., The Radiochemistry of Thorium, NAS-NS 3004, 

National Academy of Sciences-National Research Council, 

1960. 

Instrumentation for Environmental Monitoring, Lawrence 

Berkeley Laboratory, LBL-1, Vol. 3, updated periodically, 

Berkeley, California. 

Kirby, H.W., and M.L. Salutsky, The Radiochemistry of 

Radium, NAS-NS 3057, National Academy of Sciences

National Research Council, 1964. 

May, K. R., N. P. Pomeroy, and S. Hibbs, "Sampling Tech

niques for Large Windborne Particles," Journal of Aerosol 

Science, Vol. 7, 1976, pp. 53-62. 

McCurdy, D. E., K. J. Schiager, and E. D. Flack, "Thermo

luminescent Dosimetry for Personal Monitoring of Uranium 

Miners," Health Physics, Vol. 17, 1969, pp. 415-422. 

Methods for Air Sampling and Analysis, American Public 

Health Association, Washington, D.C., 1977. 

Operational Health Physics, Proceedings of the Ninth 

Midyear Topical Symposium of the Health Physics Society, 

Central Rocky Mountain Chapter, Health Physics Society, 

P.O. Box 3229, Boulder, Colorado 80303, 1976. 

Percival, D.R., and D.B. Martin, "Sequential Determination 

of Radium-226, Radium-228, Actinium-227, and Thorium 

Isotopes in Environmental and Process Waste Samples," 

Analytical Chemistry, Vol. 46, 1974, pp. 1742-1749. 

Radioassay Procedures for Environmental Samples, 999-RH

27, U.S. Public Health Service, Washington, D.C., 1967. 

Regulatory Guide 4.5, "Measurements of Radionuclides in 

the Environment-Sampling and Analysis of Plutonium in 

Soil," USNRC, May 1974. 

Regulatory Guide 4.13, "Performance, Testing, and Pro

cedural Specifications for Thermoluminescence Dosimetry: 

Environmental Applications," USNRC, July 1977. 

Regulatory Guide 4.15, "Quality Assurance for Radiolog

ical Monitoring Programs (Normal Operations)-Effluent 

Streams and the Environment," USNRC, December 1977. 

Shearer, S.D., Jr., and C.W. Sill, "Evaluation of Atmospheric 

Radon in the Vicinity of Uranium Mill Tailings," Health 

Physics, Vol. 17, 1969, pp. 77-88. 

Sill, C.W., "An Integrating Air Sampler for Determination 

of Radon-222," Health Physics, Vol. 16, 1969, pp. 371-377.

4.14-19
Sill, C.W., "Simultaneous Determination of U-238, U-234, 

Th-230, Ra-226, and Pb-210 in Uranium Ores, Dusts, and 

Mill Tailings," Health Physics, Vol. 33, 1977, pp. 393-404. 

Sill, C.W., and C.P. Willis, "Radiochemical Determination 

of Lead-210 in Uranium Ores and Air Dusts," Analytical 

Chemistry, Vol. 49, 1977, pp. 302-306. 

Sill, C.W., "Determination of Thorium and Uranium 

Isotopes in Ores and Mill Tailings by Alpha Spectrometry," 

Analytical Chemistry, Vol. 49, 1977, pp. 618-621. 

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Soil," Analytical Chemistry, Vol. 46, 1974, pp. 1725-1737. 

Sill, C.W., and R.L. Williams, "Radiochemical Determina

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Solutions and Environmental Samples," Analytical Chemis

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Particle Collection Characteristics of Ambient Aerosol 

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on Nuclear Science, NS-22, 1975.

*UA GOVERNMENT PRINTING OFFICE: 1980 620-269/90 1-3 4.14-20
APPENDIX

LOWER LIMIT OF DETECTION

For the purposes of this guide, the Lower Limit of Detec

tion (LLD) is defined as the smallest concentration of radio

active material sampled that has a 95% probability of being 

detected, with only a 5% probability that a blank sample 

will yield a response interpreted to mean that radioactive 

material is present. (Radioactive material is "detected" if it 

yields an instrument response that leads the analyst to con

clude that activity above the system background is present.) 

For a particular measurement system (which may 

include radiochemical separation): 

4.66 Sb 

LLD= 

3.7 x 104 EVY exp(-,At) 

where 

LLD is the lower limit of detection (microcuries 

per milliliter); 

"is the standard deviation of the instrument 

background counting rate (counts per second);

3.7 x 104

E

is the number of disintegrations per second 

per microcurie; 

is the counting efficiency (counts per disin

tegration);

V 

Y

is the sample volume (milliliters); 

is the fractional radiochemical yield (when 

applicable);

is the radioactive decay constant for the 

particular radionuclide; and 

At is the elapsed time between sample collection 

and counting. 

The value of Sb used in the calculation of the LLD for a 

particular measurement system should be based on the 

actual observed variance of the instrument background 

counting rate rather than an unverified theoretically 

predicted variance. 

Since the LLD is a function of sample volume, counting 

efficiency, radiochemical yield, etc., it may vary for differ

ent sampling and analysis pr6cedures. Whenever there is a 

significant change in the parameters of the measurement 

system, the LLD should be recalculated.* 

*For a more complete discussion of the LLD, see "HASL Proce

dures Manual," John H. Harley, editor, USERDA, HASL-300 (revised 

annually) and Currie, L.A., "Limits for Qualitative Detection and 

Quantitative Determination-Application to Radlochemistry," AnaL 

Chem. 40, 1968, pp. 586-93, and Donn, J. J. and R. L. Wo0ke, "The 

Statistical Interpretation of Counting Data from Measurements of 

Low-Level Radioactivity," Health Physics, Vol. 32, 1977, pp. 1-14.

4.14-21
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