ML19254B182

Responds to NRC Questions Re Sr-90 Inhalation Exposure. Provides Predicted Rates & Committed Dose Equivalents

ML19254B182
Person / Time
Site:	Crane
Issue date:	08/10/1979
From:	Dickson R ENERGY, DEPT. OF
To:	Jay Collins NRC - TMI-2 OPERATIONS/SUPPORT TASK FORCE
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ML19254B180	List: ML19254B179 ML19254B182
References
NUDOCS 7909240543
Download: ML19254B182 (7)

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{{#Wiki_filter:. 4 Department of Energy Idaho Operations Office 550 Second Street Idaho Falls, Idaho 83401 AUG 101979 ~ Mr. John T. Collins Deputy Director, TMI-2 Support US Nuclear Regulatory Commission TMI Site, Trailer #7 P. O. Box 311 Middletown, PA 17057

Dear Mr. Collins:

In response to questions arising during seve al telephone conversations with Ernie Murri of NUS Corporation, I have prepared the attached informa-tion on Sr-90 inhalation exposures. The predicted excretion rates and committed dose equivalents were obtained using computerized metabolic models. The computerized models are based on recommendations and methods developed by the International Commission on Radiological Protection. I hope that this information will help you in the design of your bioassay program. If you have any additional questions, just call me. Sincerely, ) At J C/ Richard L. Dickson, Health Physicist Environmental Sciences Branch Radiological and Environmental Sciences Laboratory

Enclosure:

As stated cc: D. R. Percival, ACB, RESL/ID Ernie Murri, NUS Corporation 992 249 ~ '90924 o d}3

Predicted Sr-90 Excretion Rates Following Acute Inhalation Exposures he committed dose equivalents and excretion rates following an acute inhalation exposure of Sr-90 were predicted using two computerized metabolic by P. Voilleque.gfor estimating the committed dose equivalents was developed models. he mod The code for estimating excretion rates was written by R. Dickson, but has not been published. ~ Se computer models are based on recommendations and methods developed by the International Commission on Radiological Protection (ICRP). The models use the revised lung model geribed in the report of the Task Group on Lung Dynamics,(2 and ICRP Publication 19 to estimate the deposition and retention of inhaled Sr-90 in the lungs. The equations used to estimate exgtion following an inhalation intake are derived in ICRP Publicati Additional metabolic data for Sr-90 is given in ICRP Publication 10.g 10A. The fractional daily systemic excretion rate was assumed to be described by the equation -3 -2 ] Y(t)=0.17exp[-g.23t]+1.6'x10-0 ]exp [-1.6 x 10 t + 2.9 x 10 exp [-1.7 x 10 t ne ratio of the urinary to fecal excretion rate was chosen to be 5:1. The fraction of strontium absorbed from the gastro-intestinal (GI) tract into the blood was 0.3, and the initial intake of Sr-90 (i.e., the amount entering the nose and mouth) was 1 pCi. We predicted excretion rates for class D, class W, and class Y aerosols are shown in Figures 1 and 2. De associated committed dose equivalent for the lung,' bone and GI tract are given in Table 1. Re above information can be used to help assess the adequacy of a screening program to detect Sr-90 intakes. If the detection limit for a urinalysis program is 3 pCi/ day, the committed dose equivalent to various body organs which would go undetected can be estimated. Estimates for sampling times of 5 and 20 days post exposure are given in Table 2. For very insoluble (class Y) forms of strontium, the fraction absorbed from the GI tract into the blood may be less than the 0.3 used in the previous calculations. If this fraction is assumed to be 0.01, the uringry excretion -0 rate at 5 and 20 days post exposure is 6.7 x 10 and 1.1 x 10-pCi/ day, respectively, he committed dose equivalent which would not be detected by the above urinalysis progran 5 days' post exposure would be 0.05 rem to the lung and 0.01 rem to the bone. At 20 days post exposure, the committed dose equivalent which would not be detected is 0.3 rem to the lung and 0.06 rem to the bone. An inhalation exposure to a insoluble form of Sr-90 (strontium titaniate - SrT'0 ) has been reported A comparison of the predicted values to the 3 measured values would seem to indicate that the fraction absorbed is between 0.01 and 0.3. 992 1 O aS

s References 1. Voilleque, P. G., " Calculation of Organ And Tissue Burdens Aat Doses Resulting From An Acute Exposure To A Radioactive Aerosol Using The ICRP Task Group Report On The Human Respiratory Tract", 1D0-12067, t August 1968. 2 Task Group on Lung Pynamics, " Deposition And Retention Models Foi Internal Dosimetry Of The Hu aan Respiratory Tract," Health Physics 12, 17;-207, 1966. s 3. International Commission On Radiological Protection, "ICRP Publication 19: The Metabolism of Compounds Of Plutonium And Other Actinides," P':rgamon Press, 1972. 4. International Commission On Radiological Protection, ICRP Publication 10A: The Assessment Of Internal Contamination Resulting From Recurrent Or Prolonged Uptakes," Pe rgamon Press, 1971. 5. International Commission On Radiological Protection, "ICRP Pub lic ation 10: Evaluation Of hadiation Doses To Body Tissues From Internal Contaminatica Due To Occupational Exposure," Pergamon Press, 1968. 6. Bradley, F. J., N. Wald, and R. L. Wechsler, " Human Internal Ccntaminat ion With Strontium-90 Titanate", Assessment of Radicactivity In Man, IAEA, Vienna, Vol. II, 401-416, 1964. s s i t s

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Table 1. Committed Dose Equivalent to Body Organs From a 1 UCi Inhalation Intake of 3r-90 ~ Aerosol Committed Dose Equivalent (rem) Cia::9 Lung Bone Lower Large Intestine D 0.012 25. 0.02 W 0.62 13. 0.05 Y 11. 10. 0.06 e a W e 992 252

Table 2. Committed Dose Equivalents That Wou.o Not Be Detectable j By A Routine Urinalysis Program Undetectable Committed Done Equivalent (rem) Aerosol 5 Days Post Exposure 20 Days Port Exposure Class Lung Bone Lung Bone D 0.000 0.002 0.0 00 0.01 W 0.000 0.003 0.001 0.02 Y 0.004 0.0 04 0.07 0.06 The detection limit for the urinalysis program is 3 pCi/ day.

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