ML20247F234

Rev 1 to Reg Guide 8.22,Task OP 013-4, Bioassay at U Mills

ML20247F234
Person / Time
Issue date:	08/31/1988
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
TASK-OP-013-4, TASK-OP-13-4, TASK-RE REGGD-08.022, REGGD-8.022, NUDOCS 8907270111
Download: ML20247F234 (13)

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U.S. NUCLEAR REGULATORY COMMISSION August 1988 c @**$) REGULATORYGUIDE

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OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 0.22 (Tosk OP 0134 )

i 810 ASSAY AT URANIUM MILLS A. INTRODUCTION Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Section 20.108, " Orders Requiring Furidshing of Bio-Part 20, which provides the regulatory basis for this guide, asny Services," of 10 CFR Part 20, " Standards for Protec-The information collectbn requirements in 10 CFR Part 70 tion Against Radiation," states that, where necessary or have been cleared under OMB Clearance No. 3150-0014, desirable in order to aid in determining the extent of an individual' exposure to concentrations of radioactive mate-

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rial, the N RC may incorporate appropriate provisions in any B. DISCUSSION license directing the licensee to make available to the indi-vidual appropriate bioassay services. Parapaphs 20.103(a)(1)

This guide is based on information from the references, and 20.103(a)(2) require licensees to limit intakes of ma-public comments received on the versions published in terials such as uranium by individuals in restricted areas to July 1978 and January 1987, data submitted by the milling the limits soccified in Appendix B to 10 CFR Part 20. As industry, and an analysis by the staff of the Office of specified in paragra;h 20.103(a)(3), compliance with these N ulear lleplatory Research (NUREG-0874, " Internal l

limits must be deteanined through air sampling and, as Dosimetry Model for Applications to Dioassay at Uranium appropriate, through baoassays.

Mills," Ref 1). Informa. tion acquired in the fu:ure may result in revisions to this guide; in prticular, if bioassay Paragrapti 20.103(b)(2) permits licemees to make tesults accumulated over a sufficiently long period of time allcwance for the use of nspiratory protection equipment indicate that workers at uramum rnills are beirg adequately O

in determining the magnitude of intake provided such protected from airborne uranium by means of ventilatica j

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equipment is used as stipulated in paragraphs 20.103(c) equipment and effective air sampling programs, the guide

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through (g). *Rese paragraphs require the licensee to may be revised accordingly.

perform biossays, as appropriate, to evaluate individual exposure and to essess the protection actually provided.

Respiratory protection devices do not always offa efficient C. REGULATOP if POSITION protection. If a devin is defective, is inappropriate for the particular contamhan, involved, does not fit the wearer

1. DEFINITIONS properly, or is carelessly out in place, the wearer may unknowingly r..;eive a sigVficant inhalation exposure.

Recent solubility studies have revealed notable differ-Therefore, if Le potential in,ake was sufficiently large, ences in the dissolution rates cf yellowcake produced under bioassay proceduxs should be grformed to determiPe different thermal conditions. For the purpose of this guide, whether such devices were in fact effective.

the fellowing distinction iu made:

)

This guide describes a bioassay program acceptab?e to tue

u. Lowdited yellowcate is defined as yellowcake dried NRC stafifor uranium mills tand applicable portions of ura-at temperatures less than 400"C.

nium cortversion facilities where the possibility of exposure to ythweake dust exists), including exposure conditions

b. High-fired (calcine-d) yellowcake is defined as yellow-with and without the use of respiratory protection devices.

cake dried at temperatures of 400*C or more.

USNRC nEGULATOPY GUIDES The guides are issued in the fottowing ten broad d6visionsi Regulatory Guldes are issued to describe anJ mane availaDie to tue publ.c methods accirptable to the fiRC staff of implementing

1. Power Reactors

6. Products specific parts of the Commission's regulations, to delineate tech-

2. Research and Test Reactors

7. Transportation nl(Jes used faf the staff In evaluallt.g specific problerns or postu-

3. F uels and Matersats F acalities

8. Occupational Health lated accidents, or to Drovide guidance tu applicants. Regulatory

4. Environments) and Satina

9. Antitrust and Financial Review Guides are not substitutes f or regulations, and comphance with

5. Materials ar d plant Protection 10. General them is not required. Methods and solutions different frum those set out in the gtades will be accePteone if they provide a basis for the Copies of Ismed guldes may tse purchased from the Government findlngs reuutsste to the issuance or Continuance of a permit of Printing Of fice at the current GPO price. Information on current license by the Comr46ssion.

GPO prices may be c.?tained by contactitSg the Superintendent of j

This guide was issued after consideration of comments received from Documents, U.S. Gow enment Print.ag of fice, Post Office Dou

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I the pubhc. Comments and suggestions for improvements in tr ese 37062, Washington, DC 20013-7062, teleonone (2oa275 2060 cr guides are encourqtd at all times, and guide, wi81 be revised, as (202)275-1171.

appropriate, to accommodate comments and to refler t new inforty a-tion or expertence.

issued guides may also be purchased from the National Technical

)

WrittOn comments may be submitted to the Rules and Procedures information Server'e on a standing order basis. Details on this r

Branct, DRR

ADM, U.S.

Nuclear Regulatory Lvamission, serv 6ce may be ot,tained by writtng NTIS, 5285 Port Royal Road, a

)

Washington, Od 20555.

gfield. VA 22161.

B907270111 800831 PDR REGOD e re FM PTB J

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1 Two important areas in a uranium mill where workers (3.7 x 10-6 Bq/mL) (based on th. concentration of gross are exposed to uranium are defined as follows:'

alpha activity in air) sn a period of I calendar quarter.

.a. Ore-dust areas, under normal conditions, are defined

4. FREQUENCY as those areas beginning with the transfer of ore from j

the cre pad to the crusher through the final tincken-4,1 General Considerations ing stage of the ;eaching operation, The prescribed frequency of urinalwis and in vivo lung

b. Yellowcake areas are defined as those areas that rneasurements is a function of the dissolution n.tes of the contain uranium extracted from the ore in a solution inhaleu ole dust or yellowcake in the fungs. Workers in the form from the ion exchange or solvent extraction yellowcake concentrate areas may be exposed to transient stage through final packaging.

levels of airborne uranium that may cause chemical damage to the kidr.ey. Therefore, uritalysis should be perfcimed with

2. WORKING CONDITIONS UNDER WHICH BIOASSAYS sufficient frequency to detect such exposures before elimi-SHOULD BE PERFORMED nation from the body renders thera undetectr.ble. Guidance on selecting appropriate frequencies is available in NUREG-Routine bioassays are censidered by the NRC staff to be 0874 (Ref.1). The applicant may use the simplified system i

necessary for workers (1) routinely exposed to airborne yel-of frequencies and action levels presented in this guide.

lowceke or directly involved in maintenance tasksin s.hich yellowcake dust may be produced or (2) routinely exposed 4.2 Usinalysis for Workers from Yellowcake Areas f

to airbornt uranium ore dust. Baseline urlysis bioassays

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should be performed for each worker prior to initial assign-Specimens from workers, regardless of whether or not res-rnents for such work. Bioassays should be performedif there piratory protection devices were used, should be collected is any reason to suspect an inhalation exposure exceeding that and evaluated at least once per month, and additional resulting from exposure to an avirage yellowcake concentra-special specimens should be collected ind evaluated if for

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2 of 10'10 pCi/mL (3.7 x 10-6 Bq/mL) for a 40-hour any reason.an inhalation exposure exceeding that resulting tion workweek or to an average ore-dust concentration of 10-10 from an exposure te an average yellowcake concentration

(

pCijmL (3.7 x 10-6 Bq/mL)(based on the concentration of of 10'3 0 pCi/mL (3.7 x 10-6 Bq/mL) for a 40-hour work-gross alpha activity in air) for a period of I calendar quarter:

week is suspected or air sampling data are not available, if respiratory protection is used to maintaininhalation expcr surca belaw these quantities, bicusay should be performed 4.3 Urinalysis for Workers from Ore Dust Areas Exclusively to verify the effectiveness of the respirators.

Specimens from workers, regardless of whether or not

3. TYPES OF BIOASSAY respiratory pr:tection devices were used, should be col-lected and evrlusted at least once per month, and sddi-Urmalysis should be performed to monitor exposures to tional special opecimens should be collected and evaluated uranium in ore dust as well as in yellowcake as they clear from if for any reason an inhalation exposure exceeding that the kidney before elimination renden, them undetectable. In resulting frori an exposure to an average ore-dust concen-vivo thorax measurements should be made to detect the pres-tration of 10 pCi/mL (17 x 10 6 Bq/m L)(based on the ence of(l) the more insoluble yellowcake component and (2) concentration. of gross alpha activity in air) for a period of uranium in ore dust in the lung when air-sampling results indi-I calendar quarter is suspected.

cate an exposure exceeding that resulting from ex such materials at an average concentration of 10'8 posure to pCi/mL 4.4 In Vivo Lung (Thorax) Measurements I lf these definitions do not apply to a specffic milling operation.

The lung counting procedure should be capable of the applicant may submit different definitions for consid2 ration.

detecting (at the lower limit of detection (LL D)) 9 nCi t

(330 Bq) or less of uranium in the lungs.

"$$le When urinalysis results call for in vivo measurements (see con ist nt w t the 2 mg/ co e na ti n i it f nium in Footnote 4 of Appendix D to 10 CFR part 20 because of Section 5), they should be performed as quickly as possible the rounding off of values in Appendix B. Since the 1 x 10

to determine if corrective measures are required.

pCi/mLlimit in more restrictive, this value has been used in the cal.

culation of all the action levels (weekly and quarterly) in this guide.

I or compliance purposes, f notnote 4 to Appendix B sets the weekly When air monitoring or eyEosure calculations call forin limit for soluble uranium compounds, which can be converted to vivo measurements (see Section 3), they shout be per-radiologi::a1 units uaing the specific activity of natural uranium (6.77 formed as quickly as practicable but no later than 3 months x lod Ci/g or 2.5 x 10* Bq/g)

Jefined in 10 CFR Par'.

after such indication.

the curie of naturst uranium 4 to trom the original defini? ion in

]

ICRP-2 (Ref. 2).The present de.. tion of the curie of natural urani.

um in 10 CI~R Part 20 refers to the total activity of all uranium iso-4.5 Measurement Detection L.imits topes in the natural uranium mixture. When natural uranium is de-fined to be 0.711% by weight a s s U and the U is assumed to be in secular equilibrium with U, I Ci of naturs_t uranium is com-The measurement sensitivity for urine analyses should be posed of 0.489 Ci U, 0.022 5 Ci U, and 0.489 Ci U.

such that the LLD (for a probability of 0.051or a h pe 1 or a Actual percentages of s a s U may be 0.711 2 0.1%.

Type 11 statistical error)is. ' pg of uranium per hter of urine or 8.22-2

less (see Appendix A for an example af the determination occupancy in the mill. The 36-hour delay is necessary to of LLD). The LLD for uranium counting in vivo should be avoid uranium that is eliminated without uptake in kidney 9 nCi (330 Bq) or less of urardum in the lungs.

tissues. (flowever,1f compounds are encountered that mainly produce a very short-live d component, Morrow (Ref. 3,p. 6 f G

5. ACTION BASED ON BIOASSAY RESULTS reconunends the use of two action levels: a 1 pg/L Monday l

morning urinary excretion rate and an exposure-associated l

Bioassay results should be promptly and enefullyreviewed urinary output of 100 pg/L during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after l

by qualified personnel, and appropriate action should be the exposure. Tables 1 a ed 2 would not necessarily be taken if the results exceed preselected levels. The corret Live t.pplicable to these results.) Sufficient volume should be l

actions to be taken depend on the amount of uranium de-collected for four analyses, each of which should be capab!c l

tected. Action levels and actionsin Tcbles I and 2 are accept-of acideving a LLD of 5 pg/L(see Appendix A).

I able as a basis for a uranium null bioassay program. Proposals for other action levea e.nd actions f rom an applicant will be UrinalWs results should be available to the person considered on a specific-case bas if accompanied by a de-responuble for conducting the bioassay program within scription of how the information in NURI G-0874 (Ref.1) 20 days after specimen collection. If the urinalyses are was used to derive thase different criteria.

performed by an outside laboratory, results exceeding 35 pg/L should be reported by telephone.

It should be assumed that any confirmed positive urinaly-sis results are an indication of soluble uranium to wluch the in vivo results should be available to the person conduct-kidney has been expose 1 ing the bionssay program within 20 days after measure-ment. Results exceeding 16 nCi (590 Bq) should be re-5.1 Urinalysis for Workers from High Fired Yellowcake ported by telephone.

Areas 3

7.

PREVENTION OF SPECIMEN CONTAMINATION i

The corrective actions to be taken depend on the amount of uranium detected and are given in Table 1. Fig-7.1 Collection ure 1 and other information in NURFG-0874 (Ref.1) may be used to deterntine acceptable action levels for a single The specimens should be

?cted before the worker intake as a function of tirae for workers from high-fired-enters the work area and in an area free of uranium contam-ination. The collection may occur at an area outside the yellowcake areas.

mill specifically designated to be maintained contamination 5.2 Urinalysis for Workers from Low-Fired.Yellom.ake free. The hands should be carefully washed prior to voiding.

Areas Disposable collection containers should be used.

The corrective actions to be taken depend on the Under unusual circutustances where specimens cannot be amourst of uranium detected and are given in Table 1. Fig-collected in this manner, the worker sh ould shower immed!-

ure 2 und other information m NURI:G-0874 (Re:f.1) ately prior to voiding. hen a shower h not possible, disposa-may be used to obtain acceptable action lesels for a single ble plartic or rub 3er gloves should be worn during voiding.

intake as a function of time for workers from low-fired-yellowcake mas.

7.2 Laboratory Analysis 5.3 Urinalysis for Workers from Ore Dust Areas Exclusively All laboratory analyses should be performed in a labora-tory essentially free of uranium contamination using The corrective acticts to be taken depend on the containers and equipment essentially free of suen contami-amount of uranium detected and are given in Table 1. Fig-na. ion. Both on-site and off-site laboratories should main-ute 3 and information in NUREG 0874 (Ref.1) may be tain the quolity contrcl procedures specified in Section 8 of used to obtain acceptable action levels for a single intake this guide. Use of the laboratory, containers, and equip-as a function of time for workers from ore-dust areas.

ment for process or environmental samples should be restricted to low-level samples. (Note: The laboratory may 5.4 in Vivo be located within the restricted area provided these condi-tions are met.)

it should be assumed that positive in vivo results indicate the quantity of uranium in relatively insoluble form that 7 3 in Vivo Countiag Precautions has accumidated in the lung. Corrective action should be taken in accordance with Table 2 of this guide.

For in vivo measurements, emplo>ee and clothing con-tamination are major sources of measurement bias. Care

6. TIME OF SPECIMEN COLLECTION AND AVAIL-must be taken to minimize these factors. Only new clothing ABILITY OF RESULTS or clothing washed in a facility separate from those used for The appropriate actions specified in Table I should be taken Routine and special urine specimens foT analysis of fu any ren11 that is confirrned by a second analysis even though 9 utstdum cotnpounds pertinent to mdl operations should specimen contamination is believed to be the cause of the elevated usually be collected at least 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> after the most recent resutt.

8.22-3

potentially contaminated clothing should be worn during its own blank and standard samples along with the other the in vivo measurement. If the in vivo measurement results results reported to the mill indicate contamination, the subject should vnhower, use clean clothing, and be recounted.

8.2 In Vivo

8. QUALITY CONTROL For in vivo measurements, a quality control program using persons known to have no lung or systemic uranium A quality control program for bioassay measurements burdens and phantoms spiked with known amounts of should be incorporated in each uranium mill bionssay uranium should be used to test the counting system before program. A quality control program consistemt with that measurements on each group of employees, recommended in the draft standard ANSI /IIPS-Ni3.30 (Ref. 4) will be acceptable. Alternatively, the followmg 9.

USE OF RESPIRATORY PROTECTION DEVICES specific quality control program for bioassay at uramum mills will be acceptabit Licensees using respiratory protection devices in accor-dance with paragraph 20.103(c) of 10 CFR Part 20 are to 8.1 Urinalysis conduct bioassay programs in accordance with paragraph 20.103(c)(2) and NUREG-0041, " Manual of Respiratory Each batch of specimens sent to the laboratory for Protection Against Airborne Radioactive Materials"(Ref. 5).

analysis should be accompanied by at least two control urine specimens. When possible, these control specimens Under certain conditions, bioassay measurements should should be taken from individuals who are not and have not be performed to ensure the proper evaluation of personnel been occupationally exposed to uranium; otherwise simu-exposure and to evaluate the actual effectiveness provided l

lated controls known to contain a uranium concentration by respiratory protection devices, if a worker wearing such less than 1 pg/L may be used. Aliquots of each of these a device is subjected for a period of I week to an average control urine specimens should be taken; one should be a concentration greater than 10"8 pCi/mL (3.7 x 10*

" blank," one should be spiked with uranium to obtain a Bq/mL), as given in Table 1, Column 1, of Appendix B concentration of 10 to 20 pg/L, and one abould be spiked to 10 CFR Part 20 for soluMe natural uranium, vrinalpis to 40 to 60 pg/L, the actual spiked concentrations being should be performed to test the actual effectiveness of the recorded confidentiaSy and not available to the analytical device. This special bicassay measurement should also be laboratory. When results are received, the licensee shnuld performed if for any reason the magnitude of the exposure ensure that each reading is corrected for the reading of the that would have occurred if no respiratory protection de-corresponding blank, that the net reading of each spiked vice had been worn is unknown. The time that the sarrple sa.mple is recorded, and that an average of the percent for this special measurement was collected snould be deviation of the spiked sample net reported values from the recorded; it should be consistent with the need to relate "true" amount of spike 1 uranium sample is calculated. The bioassay results to kidney exposure (see Section 6).

percent deviation for the spiked samples accompanying each batch of urine spe:imens should be within 30% of the The appropriate urinalysis or in vivo measurement given spikud ydues. Otherwise, the most recent batch of affected in Section 3 of this guide should not be reduced bechuse of samples should be rcran, and steps should be taken to the use of respiratory protection devices.

rorrect the precertures for spiking of the procedures for laboratory analyses, or )oth.

D. IMPLEMENTATION In order to provide adequate quality control willin the The purpose of this section is to provide information to analytical laboratory as well as to provide a check on the appbcants and licensees regarding the NRC staff's plans for quality control program of the mill, the analy tical,abora-using this regulatory guide.

tory should dtplicate the analysis of 10% to 20% of the samples received, including the blanks and sp;kes received Lxcept in thoce cases in which an applicant or licensee from the mill in addition, the laboratory should measure proposes an acceptable alternative method for complying its own reagent and urine blanks and spiked standards as with specified portions of the Commission's regulations, the appropriate to check its own procedures, provide ts own method described in this guide will be used in the evalua-calibration factors, check its LLDs, and evaluate its results tion of existing bioassay programs of uranium milllicensees for each batch. The laboratory should report the results of or proposed programs of applicants for such licenses.

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1 Table 1 CORRECTIVE ACTIONS BASED ON MONTHLY URINARY URANIUM RESULTSa Urinary Uranium Concentration Interpretation Actions Less than 15 pg/L Uranium confinement and air None. Continue to review further bicassay results.

sampling programs are indicated to be adequate.b 15 ta 35 pg/L Uranium confinement and air 1.

Confinn results (repeat urinalysis).

sampling may not provide gn 2.

Identify the cause of elevated urinary uranium and initi-l adequate margin of safety.

ate additional control measures if the result is confirmed.

3.

Examine air sampling data to determine the source and

)

concentration of intake, if air sampling results are anomalous, investigate sampling procedures. Make torrec-1 tionsif necessary.

4.

Determine whether other workers could have been exposed and perform bioassay measurements for them.

5.

Consider work assignment limitations until the worker's urinary uranium concentration falls below 15 pg/L 6.

Improve uramum confinement controls or respiratory protection program as investigation indicates.

Greater than 35 pg/L Uranium confinement and 1.

Take the actions given above.

perhaps air sempling programs 2.

Continue operations only if it is virtually certain than no C

are not acceptable other worker will exceed a urinary uranium concentra-tion of 35 pg/L O

3.

Establish work restrictions for affected c:nployees or increase uranium confinement controls if ore dust or high-temperature-dried yellowcake are involved.

4.

Analyze bioassay samples weekly.

Confirmed to be greater Worker may have exceeded 1.

Take the actions given above.

than 35 pg/L for two regulatory limit on intake.

2.

llave urine specimen tested fo2 albuminuria.

consecutive specimens, 3.

Obtain an in vivo couns if worker may have been exposed confirmed to be to Class Y material or ore dust.

greater than 130 pg/L L Evaluate exposures.

for any single specimen, 5.

Establish further u;at um confinement controls or or air samt ling indica-terpiratory protection requirements es indicated.

tion of more than a 6 Conskler continued work restnetions on affected quarterly limit of emplopes until urinary concentrations are below 15 pg/L intake and laboratory tests for albuminuria are negative.

"U6e figures 1-3 to adjust action levels for other frequencies of bioassay sampling. The model used in NUREG.0874 (Ref.1) emp fractional composition values (F., F, F ) for Class D, Class W, and Class Y comp 9nena of yellowcake compounds. The aarA - ed values 2

3 specific for t, pa:11.J1cr opera, in NUREG4874 are based on data from avaliable literature. The use of alternative values of F, F,, and F3 j

tion are acceptable provided (1) de* nits regarding their determination are described arid mentroned'ln employee exposure secords (su para-graph 20.401(c)(1) of 10 CFR Part 20) and (2) the model as published in NURLO.0874 is then used in the determination of alternative urinalysis frequencies and action levels.

bliowever, if a person is exposed to uranium ore duAt or o;her material of Class W or Y alone, refer to Section 6 of MUREG 0874 about the possibility of the need for conducting in vivo lung counts on selected perr.onnel or about using alternative urine sampling times and associated action levels cornputed using NU REG-0874.

j "Unless the result was anticipated ar.d caused by conditions already corrected.

O 8.22-5

Table 2 CORRECTIVE ACTIONS BASED ON IN VIVO RESULTSa Amount of Uranium Detected interpretation Actions Below 9 nCi May be below detection limit.

Rely on urinalysis results to determine corrective actions (330 Bq)

This result does not necessarily (unless air sampling indicates quarterly intake limits are indicate that uranium confine-exceeded for ore dust).

ment and air sampling programs are validated.

9 to 16 nCi Confinement and air sampling 1.

Confirm result (repeat measurement within 6 months).

(330 to 590 Bq) programs should be examined.b Ensure that results are not caused by body surface Uranium activity in lungs activity.

could be too high.

2.

Examine air sarnpling data to determine source and concentntions ofintake. If air sampling results are anomalous, investigate air sampling procedures. Make corrections,if necessary.

3.

Identify the cause of elevated activity and inithte addi-tional uranium confinement control measures.

4.

Deteimine whether other workers could have been exposed and perform special bioassay measurements for them.

5.

Consider work assignment limitations that will permit the lung burden to be reduc"d through natural ehmination; ensure that the lung burden does not exceed 16 nCi (590 Bq).

More than 16 nCi Uranium confinement and air 1.

Within 90 days, take the actions listed above for 9 to (590 Bq) sampling probably are not 16 nCi(330 to 590 Bq).

acceptable.b 2.

Establish work restrictions for af fected workers or Uranium activity in the lungs should increased uranium confinement control measures.

be reduced by increased protection (Normally workers with a lung burden greater than 16 nCi measures for the workers involved.

(590 Bq) are not allawed by their employer to resume work in airborne activity areas until the burden is reduced te less than 9 nCi or 330 Bq.)

3.

Perform individual case studies (bioassays) for affected workers.

4 Continue operations only whtn it is virtually certain no additional workers will exceed 16 nCi(590 Bq).

l "The Inodel ased in NUREG.0874 (Ref.1) employs fractional composition values (F F nents of yellowcake compounds. The assigned values in NUREG.0874 are based on data f/o,m.,, F ) for C' ass D, Class W, and Cbss Y compo-Svairlble literature. The use of alternative values of f. F and F specific for a particular operation are receptable provided (1) details regarding their determination are described and snentloned,in emptlyce et.posure records (see paragraph 20A0,(c)(!) of 10 CEk Part 20) and (2) the model as published in hURFG.0874 is then used in the de'erndnation of alternative urinalysu frequencies and action levels, bUnters the result was anticipated and caused t>y conditions already cort sted.

O 8.224

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Figure 1 Urgnium Concentration in Urine Following Single Exposure to liigh-Fired Yellowcake (Intake = 160,000 p g U = 1 ALI)(from NUREG-0874, Ref.1)

O 8.22-7

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Figure 2 Uranium Concentration in Urine Following Single Exposure to L.ow-Fired Yellowcake (Intake = 260,000 pg U = 1 ALI)(from NUREG 0874, Ref.1)

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8.22-9 a

REFERENCES

1. Ct. E. Ale xander, R. B. Neel,.f. S. Puskin, and A. Brod-Hydrolysis Products of Uranium flexafluoride,"

sky, " Internal Dosimetry Model for Applications to NUREG/CR-2268,* U.S. Nuclear Regulatory Commis-Bioassay at Uranium M %s,"

NUREG 0874,*

U.S.

sion, Washington, DC,1982.

Nuclear Regulatory Commission, Washington, DC,1986;

2. IrJernational Commission on Radiological Protection,

4. American National Standards Institute (ANSI)/flealth "heport of ICRP Committee 11 on Permissible Dose for Physics Society (llPS), " Performance Criteria for Radio-Internal Radiation (1959), with Bibliography for Biolog-bioessay," Draft ANSI /11PS-N13.30,1987 *"

ical Mathematical and Physical Data," ICRP Publication 2," Pergamon Press, Elmsford, NY,1960.

5. J. L. Caplin. "Ma mal of Respiratory Protection Against

3. P. E. Morrow et al., "Metabohc Fate and Evaluation of Airborne Radioactive Materials," NUREG-0041,* U.S.

Injury in lats and Dogs Following Exposure to the Nuclear Regulatory Commission, Washington, DC,19 76.

BlF?LIOGRAPHY Alexander, R. E., " Applications of Bioasuy for Uranium,"

Spitz,11. B., J. C. Simpson, and T. L. Aldridge (Pacific WASil-1251,* U.S. Atomic Energy Commission, Washing-Northwest Laboratory, Battelle Memorial Institute),

ton, DC,1974,

" Analysis of Uranium Urinalysis and In iht> Measurement Resu:ts from Eleven Participating Uranium Mills,"

Atomic Energy ControlBoard, Guide to Bioassay of Uranium NUREC/CR-2955,* U.S. Nuclear Rer;.:latory Commission, at Uranium Mine-Mill Facilities," Regulatory Document R-5, Washin; ton, DC,1984.

1981. Available from the Atomic Energy Control Board, P.O.

Box 1046, Ottawa, Ontario, Canada KIP SS9.

Swaja R. E., and C. S. Siins (Oak Ridge National Lebora-tory), " Occupational Radiological Monitoring at Unmium Fisher, D. R., et al. (Pacific Northwest Laboratory, batte!!e Mills," NUREG/CR 3598,*

U.S.

Nuclear Regalatory 234U,23dU,and Commission, Washington, DC,1984.

Memorial Institute), " Measurements of 230Th in Eacreta of Uranium Mill Crushermen,"

NUREG/CR-2503,* U.S. Nuclear Regulatory Commission, U.S.

Nuclear Regulatory Commissior., "l:ealth Physics Washington, DC,1982.

Surveys at Uranium Mills," Regulatory Guide 8.3 0,*

Washington, DC, June 1983.

McGuire, S. A., "The NRC's Limit on Intake of Uranium Ore Dust," NUREG 0941,*

U.S.

Nuclear Regulatory Commission, Washington, DC,1983.

• Copics enay be purchased from the Superintendent of Docu.

"lCRP publications are available trom Pergamon Press, Fairview ments, d.S. Government Printing Office, Post Office. Dox 37082, Park,1:Imsford, NY 105 23.

• • • Available from the llcalth Physics Sowiety,1340 Old Ct.uin Washington, DC 20013 7082;or the National Technicalinformation Service, s285 Port Royal Road, Springfbld, VA 22161.

Bridge Road, Suite 300, McLean, VA 22101.

O 8.22-10 x-_-

APPENDlX A LOWER LIMIT OF DETECTION OF URANIUM For the purposes of this guide, the lower limit of detec-A

= the decay constant for the particular radio-tion (LLD) is defined as the smallest concentration of nuclide, and radioactive inaterial in u-ine that has a 95% probability the elapsed time between samlle collection (chance) of beir g det cted when 2 measurement procedures t

=

are set so that the concentration level at which detectionis and counting fm cor+ecting for radioactive considered significant produces only a 5% chance of calling decay when decay during time t is signifi-a background reading a positive sample.* Radioactive cant, but decay is negligible during the material is then called " detected" when the value obtained fluorometric measurement.

from an instrument reading is above the LLD and is thur, high enough to permit a conclusion that activity above the EXAMPLE: LLD FOR URANIUM WHEN FLUOROMET-system ba;kground is determined to be present. Thus,for a RIC ANALYSIS IS USED fluorometric me;.surement that may include a radiochemi-cal separation in which the " blank" urines fluctuate with a This example is worked in terms of micrograms of nat-standard deviation S, the LLD corresponds to an activity ural uranium per liter oi urine. The LLD could just as well b

that is defined as:

be calculated in terms of m'.crocuries or bscquerels of ura-4 nium per liter. A conversion factor of 6.77 y 10 uC/pg 4.65S (0.025 Bq/pg) for natural uranium can be used if the b

LLD =

uranum quantity is known in micrograms. The quantity of Ut K Lv Ye yaniam added to the fusion dish will be determined, and then it will be divided by the volume of urine in the ali-Wher quot taken from the told collected sample.

LLD = the lower limit of detection (gg/L or pCi/L),

First, determine the standard deviation of the back-the standard deviction of nuctuatiom. in ground measureraent (blank urine) (which will approxi-S

=

b fluorometer blank measureraents or (ount mate an er>timate of the standard error of the average of a rate (counts per second) for a specific time triplicate measurement if calculated as shawn below). In i

of measurement and speciijc aliquot volume, this example, urine samples were taken from 12 individ-uals who worked in areas of the plant where re trianium conversion or calibration factor to ccnvert exposure could have occurred. For each of these " blank" K

=

ur.its of S from instrument scale reading urines, three (triplicate) measurements were made; each b

units to raass or activity units; units of K measurement consisted of taking 0.2 mL from an individ-may be O/pg or d/sec-pCi if activity is ual urine sample and pipetting it into a platinum dish con-counted to obtain the final result (this term taining a NaF pellet, which was then fused and placed into is omitted if S is given in mict curies a fluorometer for measurement. The readings (in micro-b directly by use of a calibration standard),

amperes in this case) of the three 0.2 mL aliquots of each individual" blank" utme were then averaged.

the counting effh:iftney (counts per dismte-L

=

giatmn);it is I when a fluorometric standard The 12 tripl.: ate averages for the blank urines were:

is measured in the same geometry as the sample.

Average Fluorometer j

Readings (X;)

volume (in liters) of aliquot taken from the Sample Number,i (microamperes) v

=

urine sample and added to the flux in the

}

funon dish. Note: As long as the concentr>

1 0

tion m uranium in the aliInot is the same as 2

0.07 the concentration in the original uriat sam.

3 0.07 4

0.07 plc, the volume of the or:ginal urine simple 5

0 does not affect this calculation.

6 0

7 0 I3 the fractional radiochemical yield or recov-Y

=

ery (if applicable) h 10 0.10 0.13 1,1

' This

-J: ion of LLD was chosen to be consistent with the 3*

,9 NRC posithn oreviously stated in Tames I and 3 of Regulatory Guide 4.8,

%vironmental lechnical Specifications for Nuclear standard error of the triplicaI. (same as an estimate cf the The standard deviation S Power Mants." The definition is ahu used in other rerulatory guides.

e average) may be calculated among them 4.14, " Radiological 1:fnuent and I: environmental Monhuring at Uranium Mins" 8.14, " Personnel Neutron Dosim.

by the fellowing equation (or a computer or calculator pro-eters" and 8.w mennh rhysics surveys in Uranium Milh.-

grammed for this equation):

8.22-11

n If this is con erted to microcuries u*,ing the conversion S"[n-]

g f (X; - X) factor given bef;re, then b

I na the number of samples S'o = 0 000181 pg x 6.77 x 10-7 pCi/pg

= 1.23 x 10'3 0 pCi(4.55 x 10-6 gg)

X = the average readirig for triplicate i from sample i j

1. 9"*

~

E*

"'Y *."

X = the average of all triplicate averages

1. (The term E. is not applicable to a fluorometnc analysis.)

l

^1h aliqu t volume of 0.2 nit is used in the LLD equation l'or the data above, the standard deviation i;:

since the numerical value for each fluorescence reading is t

S=

0.0612 pA and X = 0.0725 pA related to this volume of urine. Also, for a fluorometric b

reading compared against a calibration factor, the radio-Convert S t mier gsams of uranium. On this fluorom.

chemical yield is not applicable, and Y should be set et;ual b

to 1. The exponential term for radioactive decay, extbN),

eter, samples of pure U 0, a' craging 0.012 pg added to the 3

fusion dish gave reading in the Cuorometet averaging 3.44 will also be equal to 1 since the ha'f-life of uranium is so pA. The fluorometer will thus have a calibration factor long that the aruount of decay between collection and analysis will be 5,egligible. Therefore,the LLDs in mass and of 287 pA/pg U 0. The U[6 x 8 = 128, 714/842 = 0.85).0, compound is 85% uranium by weight (238 $ 3 = 714, activity concentration units become:

3 Therefore, the fluorometer will read 338 pA/pgof elemen-4.65 x 0.000181 tal uranium (287/0.85 = 338).

LLD * ' 000'Oy - -

= 4.21 pg/L m

Now, the standard deviation in rnicrograms of urartium is c:.lculated:

4.65 x 1.?.3 x 10O LLD, = -

gg----

0.0612 pA 2.86 x 10-6 pCi/L (0.106 Bq)

=

S " 338 p A/[g = 0.000181 pgof usanium.

b O

l i

1 O

8.22-12 I

VALUE/ IMPACT STATEMENT A draft value/ impact statemen'. was published with the final guide has not been prepared. A copy of the draft Proposed Revision I to Regulatory Guide 8.22 (Task value/ impact statement is available for inspection and cory-OP 0134) when the draft revised guide was published for ing for a fee at the Commission's Public Document Room public comment in January 1987. No significant changes at 171711 Street NW., Washington, DC, undem Task OP were necessary, so a separate value/ impact statement for 013 4.

)

l t

l l0 8.22 13

PoEESI ff5 ES NUCLEAR REGULATORY OMMISSION y

WASHINGTON, D.C. 20555

. PENALTY F R RI TE E,$300 9

4 0

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