ML20217M977

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Forwards Proposed Procedure to Be Used for Compliance Determination for Environ Protection Standards for U Recovery facilities,40CFR190
ML20217M977
Person / Time
Issue date: 07/28/1980
From: Eadie G
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20217M974 List:
References
TASK-TF, TASK-URFO NUDOCS 9802270216
Download: ML20217M977 (19)


Text

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} g. NUCLEAR REGULATORY COMMISSION

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.Jtjt 2 81980 7

MEMORANDUM FOR: Distribution (See'AttachedList)l ,

THRU: .Hubert J. Miller, Section Leader j ,

Uranium Recovery Licensing Branch FROM: Gregory G. Eadie, Project Manager _

Uranium Recovery Licensing Branch .

SUBJECT:

40 CFR 190 COMPLIANCE DETERMINATION FOR URANIUM RECOVERY FACILITIES Attached is the proposed procedure to be used for compliance detennination for the Environmental Protection Standards. for uranium recovery facilities--

40 CFR 190. This proposal consists of two approaches: The ultimate goal is a program based on actual environmental measurements after monitoring programs are in place. In the interim period, we are constrained to the use of a predictive model assessment. Your review of this procedure is requested.

T,he WMUR staff is already working towards the completion of the predictive model assessment of all mills by mid-October following the approach outlined in the attached procedure. Note also that we intend to meet with the EPA, Office of Radiation Programs, within about a month to obtain their comments on this program. Therefore, your comments are requested as soon as possible. In any case, you are requested to provide any comments you may have by August 6, 1980.

[ '

Gregory G. Eadie, Project Manager Uranium Recovery Licensing Branch Division of Waste Management

Enclosure:

As stated i

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Title:

Compliance Detennination Procedures for Environmental Radiation Protection Standards for Uranium Recove'y r Facilities;- 40 CFR 190 ,

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Background ,

4 ' :ag 3 Under Title 40 Code of federal Regulations Part 190 - Subchapter F Radiation Protection Programs, the U.S. Environmental Protection Agency (EPA) promulgated " Environmental Radiation Protection Standards for Nuclear ~

Power Operations" which provides limits ,for the radiation doses received .

by members of the public in the general environment as the result of

>^ operations which are part of the nuclear fuel cycle. Effective December 1, 1980, each uranium milling facility shall conduct its operations in such a manner to assure that the annual radiation dose equivalent of 25 -

. millirems to the whole body, 75 millirems to the thyroid, and 25 millirems

'to any other organ of any member of the public is not exceeded. However, the dose from radon and its daughters is excluded from these doses. The following discussion briefly described the Nuclear Regulatory Comission's (NRC) program for compliance determination for uranium recovery facilities.

This program is also meant to serve as guidance for the Agreement States in their implementation of 40 CFR 190.

Procedure 4 The procedures for the determination of compliance to 40 CFR 190 consist of two distict approaches: one based upon actual environmental measurements 1

and the other based upon predictive models. The ultimate goal of this program is to establish a standardized procedure which will be used to determine compliance subsequent to the establishment of each licensee's Environmental Monitoring Program (EMP). Because of their complex ,

nature and the long lead times required, it will take some time before {

the actual EMP's are in place and made operational at all mill sites; but it is expected that this stage will be completed for all NRC licensed I mills by late 1981. Thereafter, actual environmental monitoring data  !

(e.g., air concentrations measured at point of receptor) will be used for dose assessment and compliance determination. However, in the interim period, the potential radiation dose received by members of the public due to current uranium recovery operations is also being evaluated through the use of predictive models (e.g., calculational dose techniques).

A. Assessment of Actual Environmental Monitoring Data 1

Figure 1 "40 CFR 190 Compliance Determination Procedure " shows a diagram of the various steps to be followed to ultimately assure l j

compliance to 40 CFR 190 for all licensing applications, i I l 1

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" 1.1 Each licensee shalliestablish~ an' Environmental Monitoring'- a

[. .(; W ' Program;(EMP)? consistent with thelrequirements'of_NRC's + :A - -

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RegulatorynGuide .4.14 " Radiological Effluent and Environmental ei',, '

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< " y , Monitoring at' Uranium Mills"i(April..1980)! a This^ document i . ,

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_provides specificidetails foribothla7p~reop,e' rational.and the. ~

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. operational monitoring'p'rograms which a're required Lto obt'ain r

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f I' the necessary information' to be"u' sed by_ the license'e toO . -

1 is estimate the maximum potential annual radiation dose to any.

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j'^ ' member of the ' general. public as a ' result'of actually measured mill effluent releases. Before the EMP.can be put.into operation, each applicant / licensee .shall be' required'to: ' . ,,

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a. Develop' an EMP, and submit the planito the NRC for._ review and approval., Such a plan lshall include specific details of the' number, . location', collection' method (i .e. , equipment),'

sampling frequency and analysis information for all sample types (e.g.', air particulate, radon /WL, stack samples, surface and ground waters, vegetation, food, fish, soil fand~ direct radiation). A site map showing each point of_ sample collection shall also be provided.

Participation' in a Quality Assurance Program (QAP) as specified in NRC's Regulatory Guide 4.15,. " Quality Assurance Programs for Radiological Monitoring Programs (Nonnal Operations) - Effluent Streams and the Environment" (February 1979) shall also be discussed in the EMP plan.

b. Upon NRC's review and approval, the EMP shall become a license condition, and any subsequent change or modification of the approved EMP shall require that a specific license amendment be initiated by the licensee.
c. The EMP plan shall provide a time schedule providing the date when each phase of the EMP will become operational.

For new license applicants, at least one year of pre-operational' monitoring shall be required. For existing facilities, a realistic time schedule shall be implemented; however, all phases of the EMP shall be operational within'120 days of NRC's approval of the EMP plan.

d. The NRC's Office of Inspection and Enforcement shall conduct periodic on-site inspections of both the actual environmental monitoring systems / locations, as well as all reports and records of such an EMP to ensure that the actual operations of the EMP'are within the approved EMP license condition.

2.. Each licensee shall provide an EMP report every six months, as required in 10 CFR 40.65, " Effluent Monitoring Reporting Requirements," which contains the specific'infgrmation as outlined in Section 7 " Recording and Reporting 1Results" of NRC's Regulatory Guide 4.14, supra.

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As a license c'ondition .each l'icenseeishall be required to .  ;-

submit,,in conjunction with its.every1six months.EMP report.

its own 40 CFR 190 compliance' assessment for,MRC raview and - '

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Such 'a'n' assessment sea'llje"b'ase(on data gathered by the'

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a-licensee from the approved EMP as discussed above. . Such

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data (i.e. ,gathering residences, shall include' grazing, water an annual wells, etc.survey)of in the land use.

area within 8 km (5 miles) of the mill. l Any difference

' in land use from that previously ' reported shall be discussed and evaluated with respect to 40 CFR.190 compliance.

In order to minimize ' records keeping and, formal reporting

- requirements, while still maintaining a reasonable and timely review of the EMP, ' annual averages based on two consecutive six month reporting periods shall be used for

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the compliance'. assessment and reporting requirements.

b. Dose evaluation using site specific input parameters shall be completed using procedures delineated in f ttachment A " Dose Calculational Guidance", which are based n NRC's draft Regulatory Guide RH#802-4, " Calculational Models for Estimating Radiation Doses to Man from Airborne Radioactive Materials Resulting from Uranium Milling Operations". These attached tables are prcvided to allow the rapid dose calculational assessment of environmental monitoring data,
c. As necessary, a licensee shall indicate in the report what corrective action is being taken if non-compliance is determined. Each licensee shall complete its initial 40 CFR 190 compliance assessment and shall submit its EMP report for NRC review and approval prior to January 1, 1982; and subsequently within 60 days after January 1 and July 1 of each year thereaf ter, so long as the license is active.
4. The NRC shall review and complete its own independent determination of each licensee's EMPR and 40 CFR 190 compliance assessment.
a. The NRC Project Manager (PM) shall review all submittals, and shall primarily be responsible .for all approvals, license amendments and verification of 40 CFR 190 c smpliance.
i. Upon determination of compliance to 40 CFR 190, the PM will document such findings via a brief Memorandum to File for the subject license by March 31 of each year.

ii. Upon determination of non-complianceito 40 CPR 190, the PM shall assure that the licensee take any

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i iii. The ,PM.shall , review any, variance request per 40 CFR 190.11,-

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  • The NRC shall issue a brief' annual ~ report summarizing' ,

'the results of the individual license compliance reviews. _This'~ report shall'also consider the -

> > . . a # cumulative'_ dose to any member of the ' population due '

' to exposure released from multiple mil _1 facilities .:

inl the ' gen,eralp' area.'

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. B. PredictiveModeling:'J[ .

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... m Figure 2 "NRC Interim.40 CFR1190 Compliance Detennination Procedure" shows a diagram of the' various s.teps to be followed by the NRC Project Manager for each licenseLin the interim period prior to the establishment of the EMPland ' subsequent 40 CFR 190 compliance assessments and documentation by the . licensee.

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.l. All existing data,"e'.g.', source term, environmental monitoring data, land use, population distribution, meteorology, etc.,

shall be gathered and reviewed by the NRC Project Manager (PM).

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2. The NRC PM shall complete an independent radiological assessment to 40 CFR 190 compliance based on predictive modeling using methodology as described in Regulatory Guide RHf802-4.

a- Upon determination by the PM that the licensee is in compliance with 40 CFR 190, the PM shall document such findings via Memorandum to File.

b. Upon determination of non-compliance, the PM shall assure that the licensee take any necessary corrective actions and shall issue specific license amendments as required.
c. The PM shall review any variance request per 40 CFR 190.11, and shall take appropriate licensing action as required.
3. The NRC shall issue a brief report providing all pertinent documentation of 40 CFR 190 compliance detenninations. In new licensing cases, this will be in the environmental assessment or the Environmental Impact Statement (EIS) prepared in connection with the licensing action. This report shall also consider the cumulative dose to any member of the population due to exposure from releases from multiple mill facilities in the general area. I q

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The dose received by any member of, the general population shall be calculated based on the applicable potential ~ exposure of the nearest-resident in the off-site area' surrounding the millisite. The total dose shall be' the sum of the external' exposure (i;e., due .to radiation

. sources outside-.the body) and of the ' internal.1 exposure (i.e., radioactive materials within'the body) as follows: ,

1. - External Radiation Exposure - ,

The direct radiation exposu're may be assumed to be equal to. ,

the actual personal or environmental dosimetric data less

- the appropriate background contribution.,

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2. . Internal Radiation Exposdre ~- s The total dose to organs (e.g. , lung, bone, whole body, etc.)

. shall be evaluated based on summing all human pathways, such as:

a. Inhalation of Airborne Particulates -

The measured airborne concentration multiplied by the dose conversion factors as given in Table A-1.

b. Ingestion of Contaminated Food and Milk -

The measured concentration in the food product multiplied by the dose conversion . factor as given in Table A-2(a) through(c).

c. Ingestion of Meat or Milk from Livestock Grazing on Contaminated Vegetation -

The measured concentration in vegetation (e.g., grasses in grazing areas) multiplied by the dose conversion factor as given in Table A-3(a) and (b).

d. Ingestion of Contaminated Water -

- The measured concentration in potable water multiplied by the dose conversion factor as given in Table A-4.

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e. Ingestion of Meat or I411k from Livestock Wafered on '

Contaminated Water The measured concentration in water used by' livestock for

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watering purposes multiplied by thc dose conversion factor as given in' Table A-5(a) and.'(b). - 'd If any.of the human exposure pathways as given above are'not in evidence at a mill site, then that dose contribution obviously does not need to be consider ' here. The total dose for each critical organ shall be obtained decay chainby seriessumming (the dose due to each radionuclide of the uranium

- and polonium-210) and through~ each pathway,1.e., innalation plus external exposure plus all ingestion pathways. .. .

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Dose ' Conversion Factors (Millirem forper thepCi/m3 Inhalatiog)*of Airborne Particulates Whole ..- . .

Radionuclide Body Bone Lung U-238 4.32 79.2 158 U-234 4.92 79.5 180 '

Th-230 166 5950 3220 Ra-226 30.9 309 6610 Pb-210 4.36 135 772 Po-210 0.47 1.92 420

  • The 50-year dose cqmriitment for each year of exposure to 1 pCi/m3 of each radionuclide for an adult breathing rate of 20 m 3/ day. Particle size of 1.55 pm AMAD (i.g., mean diameter of 1 um and density of 2.4 g/cm ) being representative of uranium ore. The Quality Factor for alpha radia-tions is 10. The total dose per organ is the summation of doses due to each radionuclide.

(Regulatory Guide RH#802-4).

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. Dose Converson' Factors forl Ingestion jof Contaminated Meat (HilliRem'per )* '

Radionuclid'e' Whole Body Bone Efiiver Kidney-U-23'8 3.55 E-03 6.01 E-02 0.0' l.37 E-02 U-234 -

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Th-230 4.46 E-03 1.61 E-01 9.16 E-03 4.42 E-02 Ra-226 3.60 E-01 3.60 E+00 4.49 E-04 1.28 E-02 _

Pb-210 4.26 E-02 1.20 E+00 '3.42'E-03 9.63 E-01 Po-210 7.01'E-03' 2.79 E-02 5.92 E-02 1.97 E-01

  • The 50-year dose commitment for each year of ingestion of contaminated' meat. The above factors correspond to an adult ingestion rate of 78.3 kg/yrofmeat(beef, poultry, pork, mutton). (Rc Julatory Guide RH#802-4).

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U-238' 2.38'E-03i.'03E-02;. [0.b ' 9.19 E-03 U-234^ 2.71'E-03 4.39 E-02 0.0~ ,

1.04 E-02 Th-230 -

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Ra-226 2.42 E-01 2.42 E500 - 3.01 E-Ol c 8.56 E-03 t.

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4 Pb-210 2.86 E-02 8.03 E-01 . 2.29 E-01 6.46 E-01 _

Po-210 4.51 E-03 1.87 E-02 . 3.97 E-02 1.30 E-01

  • The 50-year dose comitment,for_ each year of ingestion of contaminated edible vegetation; p n A factor of 50% activity reduction through food preparation was assumed, and an adult ingestion rate of 105 kg/yr total vegetable ingestion rate, as well as uniform concentration throughout all vegetable types. Should data be presented as concentration of edible above ground vegetables, C ; potatoes, C ; and other below ground vegetables, C3 ; then the fbilowing weighked concentration Cy should be used when multiplying the above dose factors:

Cy = 0.38 C) + 0.58 C2 + 0.05 C3 Table 5 of Regul'atory Guide RH#802-4 details the breakdown of vegetable consumption.

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Dose Conversion' Factors for Ingestion of Contaminated Milk - - - -

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Radionuclide; .Whole Body 7 . Bone Liver- Kidney

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U-238 5.90 E-03' 9.97 E-02 - 0. 0 . .,,E 2.28 E-02 9 U-234 6.72'E-03 ~ 1.09'E 101L " 0. 0 2.59 E-02

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Th-230- 7.41 E-03 2.68 E-Ol' 1.52 E-02 7.35 E-02 Ra-226- 5298E-01 ,

'5.98 Ef0d;[ 7.46 E-04' 2.12 E-02 m- . . 7 Pb-210 7.07 E-02 1.99 E+00 . 5.68 E-01 1.60 E+00

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Po-210 1.12 E-02; 4.63 E-02'.

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  • The 50-year commitmentif'for each year of ' ingestion of contaminated milk.

These values are based'on'an_ adult consumption rate of 130 liters / year.

Since children drink greater quantities, the resultant dose is much higher for younger people. Dose conversion factors, as before, are for adults. Proper dose conversion factors and milk consumption rates for other age groups are presented in Regulatory Guide RH#802-4.

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Dose Conversion- Factors ,for: Ingestion of Meat from Cattle.. ~

Grazing on ,Co.ntaminated . Vegetation ;

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_' Liver' Kidney U-238 6.04 E-05 1.02 E-03 0.0 ,

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6.88'E-05~ ' l.l'1 E-03' ~ 0.0 2.65 E-04 Th-230 4.46 E-05 .

1.61 E-03 9.16 E.05 4.42 E-04 .

~Ra-226 '9.18 E-03 '9.18 E-02 1.Y5 E-05 3.25 E-04 Pb-210 1.51'E-03 '4.25 E-02 1.21 E-02 3.42 E-02 Po-210 2.39 E-04 9.90 E-04 2.10 E-03 7.00 E-03

  • The 50-year dose' commitment for each year of ingestion of meat. The above values are based on the following.

i) Animal uptake of vegetation: 50 kg/ day ii) Environmental transfer coefficients:

U - 3.4 x 10-4 Th - 2.0 x 10 Ra - 5.1 x 10~4

~4 Pb - 7.1 x 10

~4 Po - 7.1 x 10 iii) Adult meat ingestion rate: 78.3 kg/ year iv) Adult ingestien dose conversion factors (see Regulatory Guide RH#802-4) l

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U-234 . 2.05 E 3.31 E-03~ 0.0 7.89 E-04 Th-230 1.85 E-06 6.70 E-05 3.80'E-06 1.84 E-05 -

1.76 E-02 1.76 ' E 2.20 E-05 6.25 E-04 Ra-226' . .

s ;

Pb-210 ' 4.'24 E 1.19 E-02-[ ~ 5.97 E-03 9.59 E-03 Po-210 6.70 E-05 2.78 E-04' . 5.90 E-04 1.97 E-03

  • The 50-year d'ose commitmint' for each year of iiigestion. of milk. The i above values are based on the following:

i) Animal uptake of vegetation: 50 kg/ day ii) Environmental transfer coefficients: IpCi/kg (pCi/ day U - 6.1 x 10-4 Th - 5.0 x 10-6 Ra - 5.9 x 10-4 Pb - 1.2 x 10-4 Po - 1.2 x 10-4 iii) Adult consumption of milk: 130 liters / year iv) Adult ingestion dose conversion facte.s (see Regulatory Guide RH#802-4)

U M' E 4,+@b4M' g4 #mM]-- _g', ggh _4 m _ . - , _

~ -

- _ _ _ ... .= ._ s._

_- 7

. - - . . . _ _. _ 1,; .__. _ .. . ,.

. u . . .-

w-_ . - - --

_ - .o

. Table A 4 . -

C

~ ~ ~

Dose Conversion Factors -for Human: Consumption - f- . - - - -

..o . of Contaminated Wateri .

(Millirem per pCi_)*;

,, -1 y 7." 4

~ '

P Radionuclide Whole Bodyrm , Bone: , _ ' .' Liver Kidney 4

~

U-238 1.68 E 2.84 E-01 0.0 6.48 E-02 U-234 1.91. E-02 ; 3.09 E-01. : 0.0' 7.36 E-02.

g-Th-230 2.11 E-02 7.62 E-01 4.33 E-02 2.09 E-01 Ra-226 1.70 E+00, 1.70 E+01 2.12 E-03 6.03 E-02 -

Pb-210 2.01 E 5.66 E+00' l.62 E+00 4.55 E+00

c.

Po-210 3.18 E-02 ' l.32 E-01 2.80 E-01 9.32 E-01

~

  • The 50-year dose commitment for each year of ingestion of contaminated water. The above values are based on an average adult consumption rate of 370 liters / year (Regulatory Guide 1.109) and adult ingestion dose conversion factors (Regulatory Guide RH#802-4).

d

-n . -. w :, . . -

-g

, ._ ; .-z . p_ . .a  ; .:  : -

=;. ,

. ~ - . a a = wc . . . ..-. m . . , . . , . - . . . ._ _.

' ^ ~

g .

. Table.A-5 _ . ,

m Dose Conversion factors for. Ingestion - ~~ ~- - '

'~ ~

of Meat, from; Cattle. Watered on. Contaminated Water. .. -

- , . . ~. .. - . . . . -. ..- ...

(Millirem per,.PCi)*

L o ;1. ,

Kidney!

~

Radionuclide > Whol e" Body' ' Bone < ~ Liver ,

U-238 6.04 E-05' l.02 E-03 0.0 2.33 E-04 U-234 6.88 E-05' l.11 E-03 0.0 , 2.65 E ' *

, ;R . .

Th-230 , 4.46 E-05 . 1.61 E-03 9.16 E-05 4.42 E-04 Ra-226 . 9.18 E-03 '9.'18 E-02' ~1.15 E-05 3.25 E Pb-210; ' '.1 '. 51 E- 03 ^ ,' ~.,4.25 E-02 1.21 E-02

. 3.42 E-02 Pb-210 ' 2. 39 E-04. _ 9.90 E-04 ' 2.10 E-03 7.00 E-03

  • The 50-year dose commitment for' each year of ingestion of meat.

The above values are based on the folloWng:

,i) Animal uptake of water: 50 liters /ciy ii) Environmental transfer coefficients: /pCi/kg _j

'pCi/ day /

U - 3.4 x 10-4 Th - 2.0 x 10-4 Ra - 5.1 x 10-4 Pb - 7.1 x 10-4 Po - 7.1 x 10-4 iii) Adult meat ingestion rate of 78.3 kg/ year iv) Adult ingestion dose conversion factors (see Regulatory Guide RH#802-4) i I

.. --- _.- - - . a a

= _

._ .:a ~- , . ~

f[,

c- ..

- . Table A-5(b) . . . '. -

~ ~

Dose Conversion Factors for Human Consumption - ~ . - --- - - .

of Milk from Dairy Cows Watered on' Contaminated Water

~

-. . ..r . . _ . . . ..: .

p (Millirem per pCi)*

1

.4

~ '

Whole Body ' Bone Liver Kidney Radionuclide ,

U-238 2.16 E-04 3.65 E-03 0.0 8.33 E-04 U-234 2.46 E-04 3.98 E-03 " 0.0~ 9.47 E-04 Th-230 2.22 E-06 8.03 E-05 4.56E-06 2.20 E-05 ..

Ra-226- 2.12 E-02 2.12 E-01 2.64 E-05 7.50 E-04 Pb-210 5.09 E-04 ' 1','43 E-02 3 4.09 E_03 1.15 E-02' Po-210 8.04 E-05 3.33 E-04 7.08 E-04 2.36 E-03

  • The 50-year dose commitment for each year of ingestion of milk.

The above values are based on the following:

i) Dairy animal intake rate: 60 liters / day ii) Adult ingestion milk rate: 130 liters / year iii) Environmental t'ransfer coefficients: [pCi/ liter pC1/ day k

. U - 6.1 x 10-4 Th - 5.0 x 10-6 ,

Ra - 5.9 x 10-4 i

Pb - 1.2 x 10-4 i'

Po - 1.2 x 10-4 iv) Adult ingestion dose conversion factors (see Regulatory Guide RHi802-4) i l

')

a

.g . m _

%. , ,  :, s _. _ y . _. _ _ . . . . ..

^=.*+. .

. .= .

J References . .. .

0 .U.S. Environmental; Protection Agency.'- Title 40. Code _of Federal Regulations . -

Part 190 - Subchapter F, " Environmental Radiation Protection Standards for > 'L-Nuclear Power _0perations'! (40 CFR 190). ,

~

O U.S. Nuclear Regulatory Commi3sion,- Regulatory Guide'I4.14, .'" Radiological.

Effluent'and Enyironmental Monitoring}at; Uranium Mills," (April.1980).

O U.S. fluclear Regulatory Comrbission - Regulatory Guide 4.15, " Quality . '

Assurance Programs.for Radiological Monitoring . Programs (Normal Operations) - .

Effluent Streams and the Environment (February 1979).

O U.S. Nuclear Regulatory Commission - Regulatory G'uide RHk802-4, '"Calcula-tional.Models.for Estimating Radiation Doses to Man from Airborne Radioactive Materials Resulting from Uranium Milling Operations" (draft, May 1979).,

0 U.S. Nuclear Regulatory Commission - Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" (Revision 1, October 1957).

l

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