ML20033C412
| ML20033C412 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 11/30/1981 |
| From: | Jamison J, Watson E Battelle Memorial Institute, PACIFIC NORTHWEST NATION |
| To: | |
| Shared Package | |
| ML20033C409 | List: |
| References | |
| PNL-3950, UN-41, NUDOCS 8112030134 | |
| Download: ML20033C412 (42) | |
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s il PLUT0NIUM RELEASES FROM ATOMICS INTERNATIONAL'S
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NUCLEAR MATERIALS DEVELOPMENT FACILITY (NMDF),
v SANTA SUSANA, CALIFORNIA, AS A RESULT OF SEVERE NATURAL PHENOMENA
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4' -dose equivalents a' in, Table 1.for'the maximum-exposed individual and s
the population within a j0 ' mile radiits 'okthe plant.
The maximum plutonium s
Odeposition values likely:toloccM offsite are also given in Table 1.
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I,'.1['+ m'5ximum residual plutonium contami$ation estimated to be deposited offsite s
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1the Environmenta1' protection Agency's,'( PA) proposed guideline for plutonium j
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.in,the;generalNenvironinenttof 0.2 uCi/m }, The deposition values following the c %
110-mphand_the130-mh\\ tornadoes'arebeloptheEPAproposedguideline.
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f y TABLE-l. Most Likely 50-Year Comitted Dose Equivalents
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4,c and Plutonium Deposition Values I-c Maximum Piutonium
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Organs of 50-Year Cormitted Dose Equivalent (a)
Depention Offsite Event Reference ' Population (person-rem)
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-Lungs 3.3 x 10 0.44
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Bone 2.6 x 10 0.19 j.
- (a) Translocation Class Y has been assumed.
(. b) The most likely relefse from the 110-mph tornado is insigni'icant (<10'*g).
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SUMMARY
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l INTRODUCTION l
~ 1i ENVIRONMENTAL EXPOSURE. PATHWAYS FOR PLUT0NIUM 3
5 RADIATION DOSE MODELS FOR AN ATMOSPHERIC RELEASE.
- 7 RESULTS 11 EARTHQUAKES
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HIGH WINDS 14 T0,RNAD0ES..
19 DISCUSSION-APPENDIX-A'- EVALUATION OF ENVIRONMENTAL PATHWAYS BY WHICH PLUT0i4IUM MAY REACH PEOPLE FROM AN ACCIDENTAL AIRBORNE RELEASE A-1
-APPENDIX B - DOSE FACTORS FOR INHALATION, AND DOSE CALCULATION RESULTS B-l
'FOR CLASS W PLUT0NIUM.
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D TABLES 1
Most Likely 50-Year Comitted Dose Equivalents and Plutonium Deposition Values iv 2
1980 Population. Distribution Around The Atomics International NMDF 2
3
-Estimated Quantity of Plutonium Released to the Atmosphere Following an Earthquake Exceeding 0.55 g 11 4
Isotopic Composition of the Plutonium Mixture l?
5 Fifty-Year Comitted Dose Equivalents from Inhalation Following an Earthquake 13 6
Estimated Maximum Plutonium Deposition at Significant Locations Following an Earthquake 13 7
Estimated Quantity of Plutonium Released to the Atmosphere Following a Tornado 14 8
Fifty-Year. Comitted Dose Equivalents from Inhalation Following a 110-mph Tornado 15 9
Fifty-Year Comitted Dose Equivalents from Inhalation Following a 130-mph Tornado 16 10 Flf ty-Year Comitted Dose Equivalents from Inhalation Following a 150-mph Tornado 16 11 Fifty-Yaar Comitted Dose Equivalents from Inhalation Following a 170-mph Tornado 17
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12 Estimated Maximum Plutonium Deposition at Significant Locations Following a 110-mph Tornado 17 13 Estimated Maximum Plutonium Deposition at Significant Locations Following a 130-mph Tornado 18 14 Estimated Maximum Plutonium Deposition at Significant Locations Following a 150-mph Tornado 18 15 Es'timated Maximum Plutonium Deposition at Significant Locations Following a 170-mph Tornado 18 vi
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's A.1 Fifty-Year Comitted Dose Equivalents from Inhalation 239 u Particles.
A-3 of 1 pm AMAD P
rom 50 Years' Fifty-Year Comitted Dose Equivalentg3gPu Particles A.2 Inhalation of 1 pm AMAD Resuspended A-6 239 A. 3 ' Air Submersion Doses from Exposure to Pu.
A-7 239 A.4 Fifty Years of External Exposure to Pu Deposited on the Ground.
A-8 239 A.5 Average Pu Concentration Estimated in Leafy Vegetables and Produce for a Five-Year Period A-10 A.6 Fifty-Year Comitted Dose Equivalents from 50 Years' Ingestion of Leafy Vegetables and Produce Contaminated with 239Pu A-10 239 A.7 Average Pu Concentration Estimated in Grain and Forage for a Five-Year Period A-12 A.8 Fifty-Year Comitted Dose Equivalents from 50 Years' Ingestion of Milk and Beef Contaminated with 233Pu A-12 A.9 Fifty-Year Comitted Dose Equivalents from 50 Years' Ingestior, of Animal Products Contaminated with 239 u A-15 P
Fifty-Year Comitted Dose Equivalents f 50 Years' A.10 Consumption of Water Contaminated with gPu A-16 A.ll Fifty-Year Comitted Dose Equivalents from 50 Years' Consumption of Eish Contaminated with 239Pu.
A-17 2M A.12 Fifty Years of External Exposure to Pu from Swiming A-18 239 A.13 Fifty Years of External Exposure to Pu from Boating A-18 239 A.14 Fifty Years of Shoreline Exposure to Pu A-20 A.15 Fifty-Year Comitted Dose Equivalents from an Acute Release of 239Pu to the Atmosphere A-22 B.1 Fifty-Year Committed Dose Equivalent-Factors from Acute Inhalation for Class W Material B-1 B.2 Fifty-Year Comitted Dose Equivalent Factors from Acute Inhalation for Class Y Material B-1 vit-
c B.3' Fifty-Year ' Committed Dose Equivalent Factors from One-Year Chronic. Inhalation forLClass W Material B-2 B.4 Fifty-Year Committed Dose Equivalent Factors from One-Year Chronic Inhalation for Class Y Material B-2
.B.5 Fifty-Year Committed Dose Equivalents from Inhalation Following an Earthquake B-3 B.6 Fif ty-Year Committed Dose Equivalents from Inhalation Follcwing a 110-mph Tornado B-3 I
B.7
. Fifty-Year Committed Dose Equivalents. from Inhalation Following a 130-mph Tornado B-4 B.8 Fifty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Torrado B-4 B.9 Fifty-Year Committed Dore Equivalents from Inhalation Following a 170-mph Tornado B-5 i -
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.l' Accidental Environmental Consequences Evaluation 2
2-l.
Potential Exposure Pathways for Radionuclides in the Biosphere 3
3 J3 Significant Potential Exposure Pathways Through Which People May-l Be Exposed from an Accidental Release of, Plutonium
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4 Time Dependence of the Environmental Surface Resuspension Factor.
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e INTRODUCTION This study estimates-the potential environmental consequences in terms of
. radiation' dose to people resulting from postulated plutonium releases caused by severe weather or other natural phenomena. The accident scenarios considered include earthquakes, tornadoes, and high winds. This is one in a series of reports on commercial plutonium-fabrication facilities sponsored by the U.S.
Nuclear Regulatory Commission and coordinated by Argonne National' Laboratory.
Figure 1 illustrates the information requirements for such a study and how the data are utilized to estimate dose.
The amount and form of plutonium released into the atmosphere was estimated by Mishima and Ayer (1981). The atmospheric transport and dispersal of released plutonium was estimated by Pepper (1980) for tornadoes, and by the NRC for earthquakes.(a) The site characteristics and demography around Vallecitos, California were provided by the NRC.(b) The population distribution given in Table 2 was used to calculate the population doses.
(a) Annual average atmospheric dispersion values for the Site transmitted by a letter from J. E. Carson of ANL to J. D. Jamison of PNL, June 3,1980.
(b) " Description of the Site Environment," transmitted by letter.from Leland C. Rouse of NRC to Rockwell International, Attn: -Dr. M. E. Remley, May 7, 1980.
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e RELEASE ENVIRONMENTAL ENVIRONMENTAL SITE CHARACTERIS OESCRIPTION
- TRANSPORT AND r CONTAMINATION --+ DEMOGRAPHY, AND 4
DOSE DISPERSAL LEVELS USAGE FACTORS QUANTITY
' HYDROLOGIC GROUNO SURFACE POPULATION MAX INDIVIDUALS MAX INDIVIDUAL /
DURATION SEVERE WEATHER SURFACE WATER R ESIO E NT/ F ARM POPUIATION TIME DEPENDENCE ACCIDENT DIFFUSION FOODS LAND USE
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CHARACTERISTICS DIET FACTORS ISOTOPlc COMPOSITION FIGURE 1.
Accidental Environmental Consequences Evaluation TABLE 2.
1980 Population Distribution Ar The Atomics International NMDF(oynd af Distance (mi) 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 Oirection N
0 4
690 3,642 8,694 210 1,150 535 781 304 NNE O
O 86 4,002 1,153 131 2,241 870 825 822 NE O
O 115 4,318 3,310 7,045 11.572 21,662 5,220 41,587 ENE O
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676 820 4.277 47,051 4,338 4,000 18,925 E
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892 5.613 22,408 341,737 188,251 147,971 89.996 ESE O
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72 9,644 65,555 272,816 811,904 1.C75,509 834,921 SE O
O 58 303 7,774 32,012 50,693 585,058 1,042,501 811.545
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360 2,384 10.165 0
38,612 12.422 5
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0 29 130 1,465 1,912 0
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0 2.995 3,604 2.928 0
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SW 0
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0 892 6.871 3.194 0
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35,903 19,615 37,296 0
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0 5,809 33,993 158,872 26,144 0
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2,692 4.644 1,778 11.548 22.460 24,688 13.578 NW 0
43 4,894 9,961 9,356 1,740 5,731 5,856 793 117 NNW 0
0 4,606 12,666 3,527 13 7,116 54 69 1,018
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67 10,463' 39,253 58.932 191.205 824,182 1.837,156 2,367.113 1,825,235 Total 7.153,606
{a) The population distribution around Santa Susana, California provided by the NDC was based on 1970 census data. Using county growth rate information from the Statistical Abstracts of the United States and other sources, estimates of the 1980 sector populations were made t; give a truer
. picture of dose consequences.
2
l ENVIRONMENTAL EXPOSURE PATHWAYS FOR PLUTCNIUM The potential environmental exposure pathways for radionuclides released to the atmosphere and water are shown in Figure 2.
Our experience has shown 9
that the more important pathways for exposure to atmospheric releases of plu-tonium and daughter products are inhalation, cloud submersion, ingestion, and direct ground irradiation.
For chronic atmospheric releases of plutonium, the most important of these pathways is inhalation (Selby 1975, Friedman 1976, Anspaugh et al. 1975. EPA 1977).
It can also be shown that inhalation is the only important pathway for acute atmospheric releases of plutonium (see Appendix A).
Therefore, only the radiation doses from inhalation during initial cloud passage and from inhalation of resuspended environmental resi-dual contamination are calculated.
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Potential Exposure Pathways for Radionuclides in the Biosphere 3
o For liquid releases during a flood, the important exposure pathways are aquatic food ingestion, water consumption, irrigation with curtaminated water and subsequent food ingestion, and shoreline exposure.
The significant poten-tial exposure pathways that have been discussed are shown in Figure 3.
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Significant Potential Exposure Pathways Throuoh Which People May Be Exposed from an Accidental Ralease of Plutonium 4
3
-p_DIATIONDOSEMODELSFORANATMOSPHERICRELEASE
-The equation for calculating committed radiation dose equivalents from acute inhalation is:
r ir
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the committed dose equivalent to organ r'from acute inhalation DC ir of radionuclide 1, rem the quantity of radionuclide i released to the atmosphere, pg Qg E/Q = the accident atmospheric exposure coefficient, pg sec/m3 per pg. released
'the ventilation rate of the human receptor during the exposure BR
- 3 period, m /sec (DCF)ir the acute committed dose equivalent factor, rem per pg inhaled; o
a number specific to a given nuclide i and organ r which can be used to calculate radiation dose from a given radionuclide intake.
Human ventilation rates for three time periods were derived from ICRP 3
recommendations (ICRP 1975): 3.3 x 10-4 m /sec for the period 0-8 hours; 3
2.3 x 10-4 3
m /sec for 8-24 hours; and 2.7 x 10-4 m /sec for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
-Fifty-year committed dose equivalent factors were calculated using the computer code DACRIN (Houston, Strenge and Watson 1975).
This code incor-porates the ICRP Task Group Lung Model (TGLM) to calculate the dose commit-ment to the lung and other organs of interest (ICRP 1966). The organ masses used in the code have been modified to reflect the changes reported in ICRP-23 (1975).
The translocation of americium from the blood to the organs of interest has been changed to the values suggested in ICRP-19 (1972).
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4 Fifty-year comitted dose equivalents per unit isotopic mass inhaled for particles with an AMAD(a) of one micrometer are listed in Appendix B, Tables B.1 and B.2, for each plutonium isotope and 241Am.
The organs of interest in plutonium dosimetry are the total body, kidneys, liver, bone, and lungs.
The plutonium postulated to be released to the atmosphere is assumed to be in the form of plutonium oxides (Mishima and Ayer 1981).
Lung retention, the TGLM, depends upon the chemical nature of the compound inhaled.
Compounds of plutonium largely fall into Class V (retained for ye'ars) or Class W (retained for weeks).
There is no evidence of plutonium existing in the environment as' Class D (retained for days). Actinides it. tae oxide form are currently classified as Class Y (ICRP 1972), which is assumed in this study.
00ses for plutonium as Class W material, however, are included in Appendix B.
Plutonium particulates that deposit onto the ground suiface from a plume can be resuspended to the atmosphere by natural processes, and subsequently inhaled by people. Therefore, ground contamination is an important factor-when calculating doses via inhalation. Where deposition values were not provided (distances less than 5000 meters for the 0-2 hour period following l.
an earthquake), the deposition velocity concept was used to estimate the plutonium deposition (Equation 2).
I (2) j = Q (E/Q)Vd W
where 2
the concentration of radionuclide i on the ground surface, pg/m W
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the quantity of radionuclide i released to the atmosphere, pg Q
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E/Q e the accident atmospheric exposure coefficient, pg sec/m per pg release'd particle deposition velocity, m/sec V
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(a) Activity median aerodynamic diameter 6
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e-The deposition velocity of plutonium particles cannot be specified exactly because it will vary depending on the size distribution of the particles, the nature of the surface on which deposition occurs, the wind speed, and other meteorological variables. The deposition velocity for plutonium has been reported to range from 1 x 10-4 to 3' x 10-2 m/sec (Selby et al. 1975, Cohen 1977, Baker 1977,Gudik'senetal._1976).
A value of 1 x 10-3 m/sec is used in this report (Baker 1977).
Deposition values for tornadoes were reported by Pepper (1980). The NRC estimated deposition values during earthquakes and annual average conditions.
Resuspension_ rates for material deposited on the ground are time depen-dent and tend to decrease with time after initial deposition.
Local condi-tions can be expected to strongly affect the rate, with rainfall, winds, and surface characteristics predominant. The exact relationships are not well-enough understood to account for these effects (Selby et al. 1975).
- However, the airborne concentration from resuspended material can be estimated using-a resuspension factor, K.
The resuspension factor is defined as the resus-pended air concentration divided by the surface deposition.
Values for K in the environment between 10-4 and 10-13 m-1 have been measured and reported (Selby et al. 1975, Friedman 1976, Anspaugh et al. 1975, EPA 1977, Cohen 1977, FES 1974, Bennett 1975, Hanson 1975, Martin and Bloom 1975, Sehmel 1977, Healy 1977, Anspaugh 1976).
Until a more general model is available, which considers all the important variables affecting the resuspension process, Anspaugh (1975) recommends using a simple time-dependent model to predict the average airborne concentration of a resuspended contaminant:
r
e K(t) = 10-4 exp(-0.15 th) + 10-9 (3) where L
t'e time since the' material was deposited en the ground, days
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10-4 -e resuspension factor at time t = 0, m-1 resuspension iactor after 20 years, m-1 10-9' e The second te:m in Equation 3,10-9 m-1, was added baccd on the assump-tion that there may be no further measurable decrease in the resuspension factor after 20 years. This assumption was deemed appropriate since the model was empirically derived to simulate experimental measurements out to 17 years, and contains no fundamental understanding of the resuspension proces (Anspaugh et al. 1975).
Figure 4 illustrates the time dependence of the resuspens!on factor.
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Time Dependence of the Environmental Surface Resuspension Factor 8-F-
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o Equation 3 was integrated over each year post-deposition.and divided by the integrated time period to determine the average resuspension factor for each year considered. Ninety-nine percent of the total 50-year exposure from resuspension occurs in the first 5 years. The chronic 50-year committed dose equivalent factor for inhalation remains relatively constant over this time period. Therefore, the 50-year committed dose equivalent from 50 years of exposure to resuspended plutonium can be estimated using chroni
'J-year com-mitted dose equivalent factors, and only the first 5 years of exposure to the resuspended material needs to be included. The committed dose equivalent from inhalation of resuspended material was calculated by:
DCir " Ni Y(BR)(DCF)ir(3.16x107)
(4) where the 50-year committed dose equivalent to organ r from one year DC e
ir of inhalation of radionuclide 1, rem /yr of inhalation the concentration of radionuci de i on the ground surface for Wj - e the year of consideration, pg/m2 Ye the average resuspension factor for the year of considera-tion, m-1 the ventilation rate of the human receptor (for a duration of BR e greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), m3/sec (DCF)ir chronic committed dose equivalent factor, rem /pg inhaled e
3.16 x 107 conversion factor, sec/yr e
Radiological decay of the deposited radionuclides and the buildup of 241Am from the decay of 241Pu were accounted for. Chronic 50-year committed dose equivalent factors for a one-year intake were calculated using DACRIN and are listed in Appendix B, Tables B.3 and B.4.
9
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RESULTS EARTHQUAKES Committed radiation dose equivalents to several organs of'the human body
'were calculated for three earthquake events using the source terms given in Tabl e. 3.
O TABLE 3.
Estimated Quantity _of Plutonium Released to the Atmosphere Following an Earthquake Exceeding 0.55 g(a)-
Time Quantity Released (grams)
Period Upper Bound Most Likely Lower Bound 0-2 hr 4
4 4
2-8 hr 6 x 10-2 1 x 10-4 1 x 10-4 8-24 hr 0.2 3 x 10-4 3 x 10-4 1-4 days 0.7 2 x 10-3 1 x 10-3 Total 5.0 4.0 4.0
. (a) Taken. from Mishima and Ayer (1981).
Only the quan-tity released in the respirable particle size range (less than 10 um) was used to calculate doses.
A peak ground acceleration in excess of 0.55 g was found to be necessary for substantial damage to the NMDF. At that acceleration, the exterior walls are postulated to fail causing the roof to collapse.
Significant damage was not postulated for ground acceleration less than 0.55 g (Mishima and Ayer 1981),
and no radiation doses were calculated.
The isotopic composition assumed for the plutonium mixture, given in Table 4, is from the Atomics International Environmental Impact Assessment (Rockwell International 1976).
For the 0-2 hour time period, accident at dispersion values for a 5% and 50% condition, calculated by the NRC i
.nta Susana site, were used to estimate potential committed dose equivalents to the population and a maximum individual' Annual average atmospheric dispersion and deposition values 11
t TABLE 4.
Isotopic Composition of the Plutonium Mixture Isotope Weight Percent 238Pu 1.1 239Pu 61.6 240Pu 20.9
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241 Pu 12.6 242Pu 3.8 241 Am
-(a) 100 (a)24iAm was not considered in the release.
Howgpr,thebuildup of 241Am from
'Pu in the envi-ronment is accounted for, also calculated by tne NRC were used for all other time periods.
For the 57, condition (conservative).at times greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the annual average dim:f s an and deposition values were multiplied by a factor of 4, as recommended b; Carsm..(a)
Four combinations of release and dispersion are considered: ~ most li. '1y release with most likely dispersion; most likely release with conservative dispersion; conservative release with most likely dispersion; and conservative release with conservative dispersion.
These combinations are referred to as Case I, Case II, Case III, and Case IV respectively, and are used for all of the natural phenomena scenarios. The calculated committed dose equivalents are listed in Table 5 for the Earthquake.
The estimated maximum plutonium ground depositions at the site boundary, nearest residence, and farm are listed in Table 6.
All the directions and distances given in the report are referenced to the hMDF (055 Building), the primary facility at the Santa Susana site for plutonium processing.
'(a) Letter transmitted from J. E. Carson of ANL/EIS to R. B. McPherson of -
PNL/ESD, October.24, 1978.
12
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TABLE 3.
Fifty-Year Committed Dose Equivalents from Inhalation Following an Earthquake (Class Y)
Committed Dose Equivalents for:
Organ of Population (person-rem)M/
Nearest Residence (rem)tD Cl Reference Cy e Ital Case II Case III Case IV Case I Case II Case III Case IV Total Body 1.7E+4 2.0E+5_
1.9E+4 2.1E+5 2.5E-1 1.4E+1 2.7E-1 1.4E+1 Kidneys 7.3E+4 8.8E+5 8.3E+4 9.2E+5 1.0E+0 6.0E+1 1.2E+0 6.1E+1 Liver 2'3E+5 2.7E+6 2.6E+F 2.9E+6 3.4E+0 1.9E+2 3.7E+0 1.9E+2-Bone 3.8E+5-4.5E+6 4.3E+5 4.7E+6 5.6E+0 3.lE+2 6.lE+0 3.lE+2 Lungs 2.0E+5 2.4E+6-2.3E+5 2.6E+6 3.0E+0 1.7E+2 3.3E+0 1.7E+2 (a) Popilation within a 50-mile radius of the NfdDF.
(b) Located 2000 meters SSE of the NMDF.
(c) Note that in the conservative dispersion cases (II and IV), the dose at the nearest residence is more than 50 times greater than.in the most likely dispersion cases with the same release (I and III respectively). This is the result of a comparable difference between the 5% (conservative) and 50%
(most likely) dispersion factors calculated by the NRC for the 0- to 2-hour time period, during which most of the dose conunitment at the nearest resi-dence is incurred.
(d) Case I - most likely release with most likely dispersion; Case II - most likely release with conservative dispersion; Case III - conservative release with most likely dispersion; Case IV - conservative release with conservative dispersion.
TABLE 6.
Estimated Maximum Plutonium Deposition at Significant Locations Following an Earthquake (all particle sizes) 2 Pu Deposition (uCi/m )
Locatio'n Case I Case II Case III Case IV Site Boundary (a) 3.0E+1 3.7E+2 3.2E+1 3.7E+2 Residence (b)'
5.2E-1 3.0E+1 5.8E-1 3.lE+1 Farm (c) 2.3E-1 2.8E+0 2.4E-1 2.8E+0 (a) Located 410 meters NW of the NMDF, (b) Located 2000 meters SSE of the NMDF.
(c) Located 3200 meters ENE of the NMDF.
13
i
. H}GH WINDS
-Fujita (1977) reported that the probability of a 90-mph straight win'd occurring at the NMDF site was approximately the same as for a 90-mph tornadic wind.
Below 90 mph, the probability of a straight-line wind gust is higher than for a tornado of the same speed. Above 90 mph, the probability of tor-nadic winds was judged'to exceed that of a comparable straight wind.
At 110 mph, the lowest wind speed for which a significant release is repo.rted (Mishima and Ayer,1981), the probability of a tornado is far greater than that cf a straight wind. High straight winds are therefore not considered to be a likely cause of major structural damage at the NMDF site and are not discussed further.
TORNADOES Plutonium releases following four tornadoes with maximum total wind speeds of 110 mph,130 mph,150 mph, and 170 mph were estimated by Mishima and Ayer (1981).
Releases for four time periods are presented in Table 7.
TABLE 7,.
Estimated Quantity of plutonium Released to the Atmosphere Following a Tornado Airborne Release of Pu (q) for the Follomnq %:imum total Wind $peeds:
Time Period Conservat we
_t like 6 Conservat
.% st likely Conservatt Host likely Conservat
%5t Likely 1.3E-2 SE-3 3.3E-2 2E-2 4
4 0-2 hr 3E 3 2-8 hr 9E-3 9E 3 3E-5 9E 3 IE-3 6E-2 1E-2 8-24 hr
-(a)
SE-5 BE-5 1E-3 1E 3 2E-2 3E-2 1 4 6ays 4E-4 4E-4 2E-2 2E-2 7E-1 2E,,, _
Total 1.2E-2 2.2E-2 5.5E-3 6.3E-2 4.2E-?
4.8 4.2 (a) - denotes (10*7 g released.
Atmospheric dispersion and deposition values most likely to occur during a tornado were calculated by Pepper (1980).
These values were assumed to apply during the first two hours after the ' vent.
During this time period, the tornadoes were assumed to move in a northeasterly direction. Annual aver-age atmospheric dispersion and depositi values were used for all other time 14 L
l o
periods. As recomended by Pepper (*) and Carson, the tornado dispersion values were multiplied by a factor of 10 and the. annual average atmospheric dispersion and deposition values were multiplied by a factor of 4 to represent the conserva-tive case.
Committed radiation dose equivalents are given in Tables 8 through 11 for Class Y plutonium.
The estimated maximum ground contamination levels from plutonium deposition at the significant locations are listed in Tables 12 through 15.
TABLE 8.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 110-mph Tornado (Class Y)
Consnitted Dose Ecuivalents for:
Organ of
.Poculation (person-rem)
Nearest Residence (reid)tal Reference Case 1(D) Case 11 Case Ill Case IV, Case I Case II Case Ill Case IV Total Body
-(c)-
3.4E+2 3.2E+3 5.8 E-4 5.8E-3 Kidneys 1.5E+3 1.4E+4 2.5E-3 2.5E-2 Liver 4.6E+3 4.4E+4 7.9E-3 7.9E-2 Bone 7.6E+3 7.2E+4 1.3E-2 1.3E-1 Lungs 4.lE+3 3.9E+4 7.lE-3
'7.1E-2 (a) Located 16,000 to 32,000 meters from the NMDF in the direction the tornado travels.
(b) Case.I - most likely release with most likely dispersion; case II - most likely release with conservative dispersion; Case III - conservative release with most ~
likely dispersion; case IV - conservative release with conservative dispersion.
(c) No doses calculated for Cases I and II, as most likely release is insignificant
(<10-7 g Pu).
(a) Letter transmitted from D. W. Pepper _of SRL/ETD to R. B. McPherson of PNL/ESD, February 21, 1979.
i
t e
TABLE 9.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 130-mph Tornado (Class Y)
Comitted Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (rem)(a)
Reference. Case I Case II Case III Case IV Case I Case II Case III Case IV
- Total Body-6.lE+2 6.1E+3 1.6E+3 1.6E+4 9.6E-4 9.6E-3 2.5E-3 2.5E-2
~~
Kidneys 2.7E+3 2.7E+4 7.1E+3 7.0E+4 4.2E-3 4.2E-2 1.1E-2
' l.1 E-1 Liver 8.4E+3 8.4E+4 2.2E+4 2.2E+5 1.3E-2 1.3E-1 3.4E-2 3.4E-1 Bone 1.4E+4 1.4E+5 3.6E+4 3.6E+5 2.2E-2 2.2E-1 5.6E-2 5.6E - Lun9s 7.5E+3 7.5E+4 2.0E+4 2.0E+5 1.2E-2 1.2E-1 3.1E-2 3.lE-1 (a) Located 16,000 to 32,000 meters from the NMDF in the direction the tornado travels.
TABLE 10.
Fifty-Year Committed Dose Equivalents from Inhalation
~
Following a 150-mph Tornado (Class Y)
Comitted Dose Equivalents for:
Organ of Pooulation (person-rem)
Nearest Residence (rem)(a)
Reference Case I Case II Case III Case IV _ Case I Case II Case III Case IV Total' Body 2.7E+4 2.7E+5 4.0E+4 4.0E+5 3.6E-2 3.6E-1 5.3E-2 5.3E-1 Kidneys 1.2E+5 1.2E+6 1.8E+5 1.8E+6 1.6E-1 1.6E+0 2.3E-1 2.3E+0 Liver 3.7E+5 '3.7E+6
- 5. 5E+5 -
5.5E+6 4.9E-1 4.9E+0 7.3E-1 7.3E+0
. Bone 6.0E+5 6.0E+6 9.0E+5 9.0E+G 8.0E-1 8.0E+0 1.2E+0 1.2E+1 Lungs 3.3E+5 3.3E+6 4.9E+5 4.9E+6 4dE-1 4.4E+0 6.5E-1 6.5E+0 (a) Located 16,000 to 32,000 meters from the NMDF in the direction the tornado travels.
I e
16
s.
-t TABLE 11.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 170-mph Tornado -(Class Y)
Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (rem)ta)
Reference Case I Case II Case III Case IV Case I Case II Case III Case IV
. Total Body 1.2E+4 1.1E+5 1.3E+4 1.2E+5 8.3E-3 8.3E-2 2.2E-2 8.9E-2 Kidneys 5.l E+4 ' 5.0E+5 5.8E+4 5.3E+5 3.6E-2 3.6E-1 9.6E 3.9E-1 Liver 1.6E+5 1.6E+6 1.8E+5 1.6E+6 1.lE-1 1.lE+0 3.0E-1 1.2E+0 Bone 2.6E+5 2.6E+6 3.0E+5 2.7E+6 1.9E-1 1.9E+0 5.0E-1 2.0E+0 Lungs 1.4E+5 1.4E+6 1.6E+5 1.5E+6 1.0E-1 1.0E+0 2.7E-1 1.lE+0 (a) Located 3h000 to 48,000 meters from the NMOF in the direction the tornado travels for Cases I and II; located 2000 meters SSE of the NMDF for Cases -
III and IV.
TABLE 12.
Estimated Maximum Plutonium Deposition at Significant Locations Following a 110-mph Tornado (all particle sizes) 2 Pu Deposition (uCi/m )
Location Case I Case II Case III Case IV Site Boundary (a)
-(b) 2.7E-2 6.3E-2 Residence (c) 3.4E-3 3.4E-2 Farm (c) 3.4E-3 3.4E-2 (a) located 410 meters fM of the NMDF.
(b) No deposition; Cases I and II had no significant release.
(c) Located 16,000 to 32,000 meters from the fEDF in the direction the tornado travels.
17
t
' TABLE - 13.
Estimated Maximum Plutonium Deposition at Significant Locations Following a 130-mph Tornado (all particle sizes)
Pu Deposition (uCi/m )
Location Case I Case II Case III Case IV Site Boundary (a) l.6E-3 3.6E-3 2.9E-2 6.62-2 Residence (b) 5.7E-3 5.7E-2 1.5E-2 1.5E-1 Farm (b) 5.7E-3 5.7E-2 1.5E-2 1.5E-1 f
(a) Located 410 meters NW of the NMDF.
l (b) located 16,000 to 32,000 meters from the NMDF in the direction the tornado travels.
TABLE 14.
Estimated Maximum Plutonium Deposit;on at Significant Locations following a 150-mph Tornado (all particle sizes) 2 Pu Deposition (uCi/m )
Location Case I Case II Case III Case IV I
Site Boundary (a) 6.7E-2 1.5E-1 9.lE-1 2.lE-1 Residence (b) 2.lE-1 2.lE+0 3.lE-1 3.1E+0 Farm (b) 2.lE-1 2.1E+0 3.lE-1 3.lE+0 (a) Located 410 meters 'NW of the NMDF.
(b) Located 16,000 to 32,000 meters from the NMDF in the direction the tornado travels.
i TABLE 15.
Estim6ted Maximum Plutonium Deposition at Significant Locations Following a 170-mph Tornado (all particle sizes) 2 l
Pu Deposition (uCi/m )
location Case I Case 11 Case III Case IV Site Boundary (a) 7.3E-1 2.9E+0 2.9E+0 1.2E+1 Residence (b) 4.5E-2 4.5E-1 4.5E-2 4.5E-1 Farm (b) 4.5E-2 4.5E-1 4.5E-2 4.5E-1
~
(a) located 410 meters NW of the NMDF.
(b) Located 32,000 to 48,000 meters from the NMDF in the direction the tornado travels.
18
.o DISCUSSION The calculated committed dose equivalents are based on the-ICRP Publica-tion 2-Metabolic Model, the ICRP Task Group Lung Model and standard man para-meter. values.
To the best of our knowledge, there are no reported assessments
' of the accuracy of dose calculations using these models and parameter values.
Dose results are usually presented with no indication of the error' associated with.tneir use.
Present insights into the degree'of uncertainty involved are very limited and qualitative (Hoffman 1978).
Dose results presented in this paper are probably within a factor of 10.
However, studies should be con-ducted to determine the uncertainties associated with these kinds of calculations.
The estimated average annual whole-body radiation dose from natural back-ground radiation in California is reported to be 115 mrem /yr (Klement 1972).
Therefore, an individual receives a total-body dose of about 5.8 rem from exposure to natural background radiation during a 50-year period.
The collec-tive dose equivalent from 50 years of exposure to natural background radiation to the total body of the population within a 50-mile radius of the NMDF is 7
4.1 x 10 person-rem.
The average annual dose to the total body of an indi-vidual from medical x-ray examination is about 20 mrec (United Nations 1977).
This average dose corresponds to a 50-year collective dose equivalent of 6
7.2 x 10 person-rem.
The dose contribution from fallout is negligible when compared to natural background radiation and medical x-ray exposure.
If a radiation worker was involved in an occupa:ional accident and received a maximum 239 permissible bone burden of Pu, the 50-year committed dose equivalent to the bone would be greater than 1000 rem.
As can be seen, in all cases, the calcu-i lated 50-year committed dose equivalents to the population for the severe natural phenomena scenarios considered in this report are lower than the col-lective dose equivalent from 50 years of exposure to natural background radiation and medical x-rays.
19 L
J
i Existing guidelines on' acceptable levels of soil contamination from Pu 2
- can be found to range from 0.01 pCi/m to 270 pCi/m2 (Selby et al. 1975; EPA 1977; Martin and. Bloom 1975; Healy 1977; U.S. Code 1976; Healy'1974; Guthrie and Nichols 1964; Hazie and Crist 1975; Kathren 1968; Dunster 1962).
2 The EPA'has proposed a guideline of 0.2 pCi/m for plutonium in the general-environment (EPA 1977). This guideline is based on annual doses of one mrad to the lung from inhalation' and three mrad to the bone. from ingestion.
If the broad range of current guidelines are normalized to these lung and bone doses and the same.resuspension factor is used, the guidelines are'all in 2
reasonable _ agreement with'0.2 pCi/m,
'The predicted maximum residual plutonium contamination levels on the ground following the earthquake, the 150-mph and 170-mph tornadoes are above the EPA proposed guideline at some or all of the significant locations. The estimated (most likely) contamination levels at these locations range from.
2 about 0.2 to 30 pCi/m.
The predicted ground contamination levels for the 110-mph and the 130-mph tornadoes are below the EPA proposed guideline at all significant locations.
i 5
20
.e
.t:
s
- i..
I
. APPENDIX A EVALUATION'0F ENVIRONMENTAL PATHWAYS BY WHICH PLUT0NIUM MAY REACH PEOPLE FROM AN ACCIDENTAL AIRBORNE RELEASE i
t I-l I
l e
4:
b P,b
...q 4
,;9
-g
}
y
,o e
x
.,xN
(.
f~
j,,\\ 1
.~~
6 g
,1 ;,s
,Q<4 t
g S-s.
s.w APPENDIX A~
~ '
d'
,n s; y
1,,
s s
g my s
~,
-EVALUATION OF ENVIRONMENTAL PATHWAYS'BY WHICH PL'UT'NIUM:v pW 5
O 3
- s. -
1 s
MAY REACH PEOPLE FROM AN ACCIDENTAL AIRBORNE RELEASE 3 N O N v..
?s.3 /
i
.a. \\
s j
w.
s - 5..;,
3-s Twelve environmental exposure modes for an accidental airborna rel, case
<n
~
, _. n
,,, v~ ~
are considered for evaluation. Three are from exposure to the !rt.4,fgaqt; pre s
cloud, and four result from radioactive materialdeposited on the ground. The remaining' five are via the waterborne pathway, assuiding iadioactive material V
was deposited onto a nearby surface body of water.
For the Babcock & Wilcox
\\
study, it is assumed that irrigation does not occur.
The following exposure modes are included in the study:
1.
inhalation during the initial cloud passage, 2.
inhalation of resuspended radioactive material, 3.
direct exposure from cloud submersion,
- 4. -direct exposure to radioactive material deposited on the ground, 5.
ingestion 'of leafy vegetables, bee?, milk, water and fish, 6.
direct exposure from swimming and boating in contaminated water, and I
7.
external exposure to radioactive material concentrated in the shoreline sediment.
One isotope of plutonium is considered, 239Pu, t the conclusions from this evaluation apply to most of the other isotopes, as well as a typical mixture of plutonium isotopes.
The dose models used to evaluate the exposure modes are taken from Regulatory Guide 1.109, Revision 1 (1977) and are modi-
= fied accordingly for an accidental release.
In the evaluation, doses are calculated to a hypothetical maximum adult individual for 50 years of exposure.
A-1 t'
g w
/Na, jv i'
q kWfy g%gy
,v" 3.
L U
Sy 3
$ g
' AIRBORNE PATHWAYS' n
Og g Airborne Release Assumptions and Dispersion
^
b
,\\ y A normalized plutonium release of 1 pg 239pu is-assumed, and an arbitrary'
[h-average accident exposure coefficient (E/Q) of 1 x 10-3 pg sec/m3 per pg at the location of the maximum exposed individual is chosen.
It is assumed
{<
that the particle size of the plutonium released is in the respirable range, less than 10 pm in diameter.
- _ yN.
Inhalation-4 The comitted dose equivalent from radioactive material inhaled during
,5 passage of the initial cloud is calculated by:
DC, = Q(E/Q)(DCF)$
(A-1) where DC
- committed dose equivalent to organ i (rem) j total quantity of radioactive material. released during the Q
- accident (pg)
(E/Q) e' accident atmospheric exposure coefficient (pg sec/m3 per pg) comitted dose equivalent factor for organ i (DCF)j e
3 (rem per pg sec/m )
The comitted dose equivalent factors for acute inhalatioq of 239pu were l
calculated using the computer code DACRIN (Houston et al. 1975).
This code f
incorporates the ICRP Task Group Lung Model to calculate the dose to the lungs i
and other organs of interest. The organ masses were modified to reflect the changes reported in ICRP-23 (1975).
The 50-year committed dose equivalent factors per unit mass exposure for 239Pu particles, with an activity median aerodynamic diameter (AMAD) of one micrometer, are listed in Table A.1 for the total body, lungs, bone, and the lower large intestine (GI-LLI), along with the calculated comitted dose equivalents. The translocation classes which minimize the contribut.v. from the inhalation pathway are used.
Cloud deple-tion is not considered.
The location of the maximum exposed individual would A-2
..p
'~~'
e v
~ -
.,.s.
,.,i$ si
~
4 z.7 s
+
' TABLE A.1. : Fifty-Year-Comitted Dose Equivalents from Inhalation of 11 pm AMAD. 239py. Particles.
Comitted D s$
'Comitted Dose
. Equivalent a
_ Translocation Equivalent Factors Organ.
Class
. (rem per ug sec/m3)-
(rem)
LTotal_ Body.
-Y.
5.6E-04(b) 5.6E-07~
Lungs'-
W-9.9E-04 9.9E-07
. Bone-
-Y 1.2E-02 1.2E-05
.GI-LLI.
W 7.3E-07 7.3E-10 3
.(a)At location where E/Q = l x 10-3 pg. sec/m per pg.
-(b)5.6E-04 is identical to 5.6 x-10-4
- probably be a few'hurdred' meters from the point of release, and the inclusion
.of. cloud depletion.would only lower the doses by a few percent (USNRC t-
. Guide'l.111 1977, Gudiksen1976).
Resuspension;is an important aspect to be considered when calculating
~
. the dose from inhalation os plutonium. The airborne concentration from resus-pended material can be predicted using a resuspension factor, k.
The resus-pension factor is defined as the resu; pended air concentration divided by the
. surface ' deposition. - Reasonable values for k between 10-4 m-1 and 10-13 m-1 have been measured'and reported (Anspaugh 1975, Cohen.1977, Hanson 1975, FES 1974, Selby 1975, Bennett 1975, EPA 1977, Martin and Bloom 1975,
- Sehmel 1977, Healy 1977, and Anspaugh 1976).
Until a more general model is available, which considers all the important variables affecting the resus-
+ ~
pension process, Anspaugh (1975) recomends using a simple time-dependent modelsto predict the average airborne concentration of a resuspended contami-nant:
h K(t) = 10-4 exp(-0.15t ) + 10-9
-(A-2)
.1 i
n e
?(
~
~'
l
- A-3 n
m
-4 d
^
y; l
~
.u.;
5 f
where-Ke resuspension factor (m-1) time'since-the material was deposited'on the ground (days)
' t e The'second term was added based upon the assumption that-there may be no further' measurable decrease in the resuspension process after 17 years, which 1s.the longest period post deposition _that measurements _ have been reported.
.This time-dependent model accounts for the observed decrease in air concentra-tions which has been noted'to occur in the absence of a significant net loss of the deposited contaminant.
The resuspension factor was integrated over 50 years to include the total
- potential intake from resuspended plutonium.
It was determined that 78% of the total 50-year exposure from resuspension occurs in the first year and 99%
occurs in the first five years. To simplify the calculation, it is assumed that the total 50 years of expostre to resuspended plutonium is. received during the first year, and the particle size is in the respirable range.
The
-committed dose environment factor remains relatively constant over the first five years. Thus, bringing this term out of the integral does not affect the resul ts. When Equation A-2 is integrated over 50 years, the total exposure to resuspended material is calculated to be 8.9 x 10-3 days / meter.
The committed dose equivalent from inhalation of resuspended material is calculated by:
TU DC$ = W(DCF)$(8.64 x 104) f K (t) dt (A-3) where surface concentration of radioact.ive material initially W e 2
deposited from the cloud onto the ground ( g/m )
dose commitment time (days);
T e
d d = 1.83 x 104 days '(50 years in this study)
T
.A 4 4
4
-u
-a
+--
a,--
s-.--- e ---- - -
c a
+
,7 e.
(DCF){ e 50-year committed dose equivalent factor for organ i (rem per pg.. sec/m )-
3
.S.64'.x 104 e constant which converts days to seconds (sec/ day)
The terms K and DC have already been defined.
9 The initial groun'd deposition concentration for an accidental release of
. plutonium is calculated.using the following equation:
W=EV (A-4)-
d where 3
exposure (pg sec/m ), the product of Q and E/Q as defined earlier E
- Vd.e deposition velocity (m/sec)
A deposition velocity of 1 x 10-3 m/sec was chosen as is used in the computer code FOOD (Baker 1977).
Chronic committed dose equivalent factors were calculated for one year of inhalation of 239Pu using DACRIN (Houston et al.1975).
The organ masses were modified to reflect the changes reported in ICRP-23 (1975) as before.
The 50-year committed dose equivalent factors per unit mass inhaled during the first year for. 239Pu particles with an AMAD of one micrometer are listed in Table A.2 for the total body, lungs, bone, and GI-LLI, along with the calcu-lated committed dose equivalents.
The translocation classes which minimize the contribution from inhalation are used to be consistent with-Teble A.l.
jt A-5
's TABLE A.2. IFif ty-Year Committed Dose Equivalents from 50 Years' Inhalation ii.
_ of 1 pm AMAD Resuspended 239Pu Particles Committed Dose'-
Committed D9sg Translocation Equivalent Factors
.Equivalentta)
. Organ' Class
'(rem per ug sec/m )
(rem) 3
~
Total Body
-Y' 4.6E-04 3.5E-07 Lurgs W
- 8.lE-04 6.2E-07 Bone Y.
- 9.7E-03 7.5E-06 GI-LLI
-W 5.9E-07' 4.5E-10 (a)Atthe same location where initial inhalation was calculated.
HoudSubmersion A' semi-infinite cloud model is used for calculating the external doses from cloud submersion during cloud passage.
The doses are calculated with the following equation:
$ = E (DF)$ S (A-5)-
D T
p where sum of the initial exposure from initial cloud passage and E
e T
resuspended radioactive material (pg sec/m3)
(DF)$
e' dose factor for cloud submersion for organ i (rem per pg sec/m3)
. attenuation factor which accounts for shielding provided by S
e F
residential structures (dimensionless)
The total exposure is calculated by:
Td T = E'+ W(8.64 x 104) f K(t).dt (A-6)
L E
o il-p where all-terms have already been defined.
A-6 y
e-
...wme
~
-b,~
~
=
s,-
t c
The. total exposure to the airborne particulate, E, is calculated to be T
3 1.8 x 10-3'pg-sec/m. A value of 0.70 is used for the attenuation factor, S-(USNRCGuide 1.1091977).
p Doses for submersion in a semi-infinite cloud of 239pu were calculated using. dose. factor's taken from Soldat.(1974) and converted to dose per unit mass. The calculated doses and dcre factors are given in Table A.3.
TABLE A.3,.
Air Submersicn Doses from Exposu:
to 239pu Dose F.ctor Organ (rem per ug sec/m3)
Dose (rem)
Total Body 9.6E-13 1.2E-15 Skin l '.3E-l l 1.6E-14 Ground Exposure Dose from external exposure to radioactive material deposited on the ground is calculated by:
D$ = W(DF)$ S T-(A-7) p where 2
(DF)$
dose rate factor for organ i'(rem /hr per pg/m )
e attenuation factor defined in Equation A-5 (dimensionless)
S F
timeofexposure(hours)
T
- 2 W has been defined previously (pg/m ),
' The assumption is made that the ground concentration of plutonium is constant (radiological decay is-insignificant and was ignored), and the. expo-sure time, T, is 50 years or 4.38 x 10s hours.
A value of 0.70 is used for Sp (USNRC Guide 1.1091977).
The dose rate' factors were again taken from Soldat et al. (1974).and converted to dose per unit mass. The calculated dose factors and doses are listed ~1n Table A.4.
A-7 z.--
J
_y i
n:
TABLE A.4.
Fifty Years of External Exposure to
.239Pu Deposited on the Ground Dose Rate Factor Organ (rem / hour per ug/m )
Dose (rem) 2 Total Body.-
4.9E-ll l1.5E-ll Ski'n 4.8E-10 1.5E-10 Crop Ingestion The internal comitted dose equivalent received from ingestion of contami-nated vegetation.is calculated by Equation A-8.
DCj =. Cp p (DCF)j (A-8)
U where consumption rate for vegetation (kg/yr)
U p
50-year committed dose equivalent factor for organ i from (DCF);
e chronic ingestion of 239 u (rem per pg ingested per year)
P radionuclide concentration -in the edible portion of the C
e p
vegetation (pg/kg):
2 WV r T" (8.64 x 104) exp(-A*t )
[T '*P( A s-0.15Ali)ds d
2 10-4 C
=
p
.y i
e
" exp[-A (t2 - t )]
(A-9)'
exp(A t ) - exp(A t )
+
+
i 2
i e
e e
where previously undefined symbols are defined by:
fraction of deposited radionuclide retained by the vegetation -
.r e
'(dimensionless) factor for'translocation of externally. deposited radionuclides T
e r
to -the edible parts of the vegetation '(dimensionless) l A-8
ce l'
4
' vegetation yield '(kg/m )
2
(
Y e 8.64 x 10N constant which converts days to seconds (sec/ days)-
~
A, e ' effective decay constant for removal of radionuclides on leaf or produce surfaces by weathering and radiological decay
~
(days-1) time from the accident.to the appearance of the vegetation (days) ti e
time'from the accident to harvest of the vegetation (days) t2
'the concentration of radioactive material initially deposited C
e g
2 on the vegetation (pg/m ); equals zero if the vegetation was not present at the time of the accident.
. Equation A-9 accounts for the radioactive material initially deposited on the-vegetation following the accident as well as the contribution from the deposit of resuspended environmental residual radioactive material.
The contribution from root uptake of plutonium is negligible compared to
'the _ plutonium deposited dir~ectly onto the vegetation (less than 1%), and is ignored.
It is assumed that the accident occurred a fev, days before harvest during the.beginning of the growing season.
A five-month growing season and
-a 90-day growing period for vegetation are used.
The integral was evaluated numerically.
It was determined that almost all of the plutonium deposited on the vegetation occurs during the first year.
.Therefore, the assumption was made that the total intake occurs during-the first -year.
Fifty-year committed dose equivalent factors were used to calcu-
' late the resulting committed dose equivalents.
Values for r, Y and A are taken from Regulatory Guide 1.109 as 0.2 for e
particulates, 2.0 kg/m2 for leafy vegetables and produce, and 0.0495 days-1, i
respectively.
Values of 1, for ' leafy vegetables, and 0.1, for produce,' are used for Tr (Baker et al. 1966).
Consumption rates for the maximum individual are taken from Regulatory Gaide 1.109 and adjusted for a five-month growing season. Consumption rates of 27. kg/yr, for leafy vegetables, and 217 kg/yr,
' for fruits, vegetables, and grain, were calculated'.
The average-plutonium concentrations in the edible portion of leafy vegetables and produce are pre-
~
sented in Table.A.5 for a five-year period.
A-9
- O 2h
a
^ 8
- )
. 9 TABLE A~.5.
Average. 239Pu Concentration Estimated in Leafy-Vegetables and Produce for.a Five-Year Period Plutonium Concentraf. ion (pg/ko)
Year (a)
~~ 'eafy Vegetables _
Produce L
1 4.7E-08 4.7E-09 2
9.4E-10 9.4E-ll-3 2.9E-10 2.9E-ll 4
1.2E-10 1.2E-ll 5
5.5E-11 5.5E-12 (a) Accident occurred during first year, a few days before the first harvest.
Fifty-year committed dose equivalent factors for a one-year chronic ingestion of 239Pu were taken from NUREG-0172 (Hoenes and Soldat 1977), modi-
,fied using updated organ masses from ICRP-23 (1975) and biological half-lives from ICRP-19 (1972), and converted to a unit mass intake.
Committed dose equivalent factors and committed dose equivalents were calculated and are included in Table A.6.
TABLE A.6.
Fifty-Year Committed Dose Equivalents from 50 Years' Ingestion of Leafy Vegetables and Produce Contaminated with 239Pu Committed Dose Equivalent Factor (rem /50-year per Committed Dose Organ ug ingested per year)
Equivalent (re.a)
Total Body 1.2E-03 2.8E-09 Bone 4.5E 1.lE-07 L
GI-LLI.
<4.6E-03 1.lE-08 Ingestion of Milk and Beef The internal committed dose equivalents.from the ingestion of animal
. products (milk and beef) are calculated by:
$ = )[(CQ)
S U(DCF)$
(A-10).
i DC A-10
,g i
~ ~ ~
.~..,_s._
m
.L where the summation of the product of the two terms, C and Q, represents the total radionuclide intake by the' animal from consumption of contaminated forage, feed, and water, and C e radionuclide concentration in the animal's-food, Cf(pg_per
~
~
kg. forage _or feed), or drinking water, Cg (pg per_1 iter of water).
Equation A-9 is used to determine values for C.
f Qe animals' consumption rate, Qf (kg. feed or forage / day), or.Q7 (twater/ day) animal product transfer coefficient that relates the daily S e intake rate of an~ animal to the radionuclide concentration in milk, Sd-(days /t) and beef, Sb_(days /kg)
U*
human consumption rate for milk,-Ud (t/ year), or beef, Ub (kg/ year)
(DCF)j chronic ingestion committed dose equivalent factor for. organ e
i' given in Table A.6 (rem /50-year per ug ingested per year)
The dose contribution from the ingestion of milk or beef contaminated by the animal's drinking water is addressed in the next section.
. An' eight-month grazing season is assumed for both beef cattle and milk 1
cows.
For the remaining four months, the animals are fed stored feed and grain, which were grown during the previous five-month growing season. ~ The radionuclide concentration in the grain is calculated using Equation A-9.
The same parameters used to calculate the concentration in produce are used for grain.
It is assumed that the accident occurred a few days before the harvest, during the beginning of the growing season.
A 90-day growing period is used.
To estimate the average radionuclide concentration deposited on the pasture from the initial accident and resuspended radioactive material,
. Equation A-9 was integrated with respect to t, evaluated'over the eight-month grazing season using a 30-day buildup period (USNRC Guide 1.109 1977),-and divided by the integration time period of ~30 days.
All other parameters remained unchanged, ~except that values of 1.0 (Baker et al.1966) and 2 (USNRC Guide :1.1091977) were used for T and Y, respectively.
a 0.70 kg/m r
A-11 i
~
G.
i
~4 It was determ'ined that almost all of the. plutonium deposited on theJgrain
~and pasture occurs during the first year. : Regulatory l Guide 1.109 uses a.value
- of 50- kg/ day for feed or forage consumption for both beef cattle and milk cows.
Values for S f 2.5 x 10-8; days /t for milk-and for S f 5.0 x 10-3 days /kg d
b
.for beef.are reported by Baker (1966). Values for the human consumption rates
.are taken-from Regulatory Guide 1.109 as 3101 of milk / year and 110.kg beef /
year.
The~ average plutonium concentrations in the edible. portion of the grain x
and in the fresh forage are presented in Table A.7 for. a five-year period.
TABLE A.7.
Average 239Pu Concentration Estimated in-Grain and Forage for a Five-Year Period Plutonium Concentration (ug/kg)
Year (a)
Grain Forage 1
4.7E-09 2.7E-08 2
9.5E-Il 1.4E-09 3
2.9E-ll 4.8E-10 4
1.2E-11 2.0E-10 5
5.5E-12 9.9E-ll (a) Accident occurred at beginning of first year, 90 days into the growing and grazing season.
Using the 50-year ingestion committed dose. equivalent factors given in Table A.6, committed dose equivaleats were calculated for the consumption of contaminated animal products and are presented in Table A.8.
TABLE A.8.
Fifty-Year Committed Dose Equivalents from 50 Years' Ingestion of Milk and Beef Contaminated with 239pu Committed Dose Equivalent (rem)
Organ Milk Beef Total Body 9.8E-15 6.9E-10 Bone 3.7E-13 2.6E-08 GI-LLI 3.7E-14 2.7E-09 A-12
.e p
WATERBORNE PATHWAYS To account for the contribution from radionuclides deposited onto a nearby
. surface body of water,.a small lake one meter deep is assumed.
Deposition ov'er the 1ake is assumed to occur at the same rate as over land (USNRC
~
Guide 1.111 1977). The plutonium is assumed to be soluble; however, it is most likely insoluble in water at normal pH levels.
It is assumed that the radioactive particulates are uniformly mixed in the lake upon contact. A
~four-year removal. half-life-is used (Wahlgren and Marshall 1975).
A differential equation was set up with a dynamic source term (this includes the initial deposition onto the water and.the contribution from
- deposited resuspended material) to reflect the changing water concentration.
When this equatio'n is solved for the water concentration, an expression is~
obtained similar to Equation A-9.
Due to the slower removal process (four years versus 14 days for vegetation), and since the majority of the radioactive material deposited on the lake takes place during the first year, the water concentration curve approaches a simple exponential expression. The initial water concentration can be determined by extrapolating the curve back to time zero, which yields Equation A-ll.
C, = 1.86 x 10-9 exp (-At)
(A-11) where radionuclide concentration in water.(pg/t)
C, e
removal constant for plutonium in the lake (days-1);
A e A = 0.693/1461 days-1 time since deposition onto the lake surface (days) t e extrapolated water concentration at't = 0 (pg/t) 1.86 x 10-9 e
Equation A-ll is much simpler than the complex solution obtained by
. solving the differential equation, and it only overestimates the water A-13
~
1,
- concentration by a few percent over. the' 50-year period considered.
Equation 11 was integrated ~to estimate the average radionuclide concentration in'the water for each year, Ingestion of Animal Products If the= animals' drinking water supply was to come from the lake, a small fraction of' the plutonium would eventually be transferred to the animals' milk :
or' meat' and be subsequently ingested by 'the maximum exposed individual.
Since the' potential radionuclide intake from this pathway occurs for approximately 30' years,~ ingestion committed' dose equivalent factors must be calculated to Jaccount for the decreasing comitment time as the exposure time approaches -
the'end of the 50-year exposure period. ' Committed dose. equivalent factors for chronic ingestion of radionuclides are calculated with Equation A-12.
t t+exp(-At)-exp(-AAt)}(A-12)
(DCF)g = (2.92 x 10-7) SA (F, c/m)(T2) -xt e2 e
whcre committed dose equivalent factor for organ i (rem per pg (DCF)$
e ingested per year) specific ~ activity of the radionuclide (pCi/pg)
SA e g
- fraction of the ingested radionuclide: reaching organ i F
e l
(dimensionless) l effective energy of the radionuclide in organ 1 l-c e
[(MeV/ dis)(rem / rad)]
mass of organ i (g) m o effective half-life of the radionuclide in organ i (days)
I T e l
effective decay constant in organ i (days-1); A = in 2/T_
A e
e e
duration of intake (days) ti e
L L
A-14
., ei e
te time over which the dose comitment_is calculated,: including 2
the-durationof: intake (days) 2 T)>0 at4 *~ (t ti One.through 50-year ingestion committed dose equivalent factors _were
-calculated for 239Pu using parameter values found in ICRP-2 (1959), ICRP-23
.(1975), and ICRP-19 (1972). The committed dose equivalent factor to the GI-LLI from ingestion does not change.
Committed dose _ equivalents were calcul ted using Equation A-10 for each
~
year during' the 50-year exposure period, using average yearly water concentra-tions and the appropriate dose commitment factor for that' year.
Baker (1966) and Regulatory Guide 1.109'use animal water consumption values of 60 t/ day for milk cows, and 50 t/ day for beef cattle. The total committed dose' equi-valents for the 50-year period to the maximum individual from ingestion of, animal products for this exposure pathway are presented in Table A.9.
The sum of the contributions from animal product ingestion for the airborne pathway and the waterborne pathway _is also shown in Table A.9.
TABLE A.9.
Fifty-Year Committed Dose Equivalents from 50 Years' Ingestion of Animal-Products Contaminated with 239Pu (waterborne pathway and waterborne plus air)
Total Committed Dose Committed Dose Equivalents-Equivalents'(rem) from Airborne (rem) from Waterborne Pathway-and Waterborne Pathways Organ Milk Beef-fiil k Beef Total Body 5.2E-15 3.lE-10
~ 1.5E-14
-1.0E-09 Bone 2.0E-13 1.2E-08 5.7E-13 3.8E-08 GI-LLI 2.3E-14 1.4E-09 6.0E-14 4.lE-09 Drinking Water Ingestion The committed dose equivalent from consumption cf contaminated drinking j
. ater-is calculated by:
j w
DCj = C,U,(DCF)j-( A-13)
A-15
n J
t-
'. o, s
where
('e average radionuclide concentration in water during the. year of interest (pg/t); calculated earlier
~
U e consumption rate (t/ year) g chronic' ingestion committed dose equivalent factor for organ i (DCF)$
(remperpgingested) _
~
A water consumption rate of 730 tiyear is used (USNRC Guide _1.109.1977).
Comitted dose equivalent factors were calculated using Equation ~-A-12.
The
. dose calculations'.were taken out to 28 years, a't which time the contribution-to the tot'al ' dose commitment from drinking water.'is insignificant. The resulting committed dose equivalents are listed in Table A.10.
TABLE A.10.
Fifty-Year Committed Dose Equivalents from 50 Years' Consumption of Water Contaminated with 239Pu Organ Committed Cose Equivalent (rem)
Total Body 8.3E-09 Bone-3.2E-07 GI-LLI 3.6E-08
. Fish Ingestion The equation used to estimate the dose from consumption of fish, assuming-immediate transfer and equilibrium after deposition of the radicnuclide onto the lake, is:
'(A-14)-
DCj = C, B Uf (DCFi g
.where average radionuclide concentration in the lake during the C,
e year of interest (ug/1); calculated earlier A-16
fi 4
- 6,
.r.
B -e. equilibrium bicaccumulation factor expressed.as.the ratio of
~
.the concentration in fish to the radionuclide concentration inwater(t/kg) fish consumption rate (kg/ year)
U a
f f
- (DCF)$
same committed dose equivalent-factor calculated for the e
' ingestion of animal products and' drinking water, for organ 1 (rem pe'r pg ingested)
A fish'c'onsumption rate of 21 kg/ year is used (USNRC Guide 1.109 1977) and the value for the bioaccumulation factor, B, is selected to be 3.5 t/kg (Soldat e't al.1974). The' duration of fish consumption is assumed to be-50 years.
However, the contribution from the last 22 years of fish consump-tion is' negligible.
The committed dose equivalents from fish consumption were calculated and are given in Table A.ll.
TABLE A.ll.. Fifty-Year Committed Dose Equivalents from 50 Years' Consumption of Fish Contaminated with 239pu Organ Committed Dose Equivalent (rem)
Total Bcdy 3.8E-10 Bone 3.2E-08 GI-LLI 3.6E-09 Swimming and Boating The following equation is used to calculate the dose from swimming:
( A-15) where average radionuclide concentration in the lake during the period C,
e of-exposure (pg/t); calculated (earlier
'A-17
4 v'
(DF)4; Ee ; water' immersion dose rate factor for organ i=(rem /hr per pg/1).
'U 'e': exposure rate-(hours / year)'
cT *- period of exposure (years)
The dose rate factors were-taken from Soldat et al. (1975) and converted -
to-dose per unit mass.; Equation A was integrated over a 50-year-period and divided by' 50' years < to obtain an average radionuclide concentration -in the
~
lake during the period of exposure of 2.1 x 10-10 pg/t.
Using a value of 100 hrs / year for the' exposure rate (Soldat et al. 1974), and assuming a 50-year
-exposure. time,'the doses from swimming were calculated and are listed, along with the dose rate factors, in Table A.12.
-TABLE A.12.
Fifty Years of External Exposure to 239pu from Swimming Dose Rate Factor Organ (rem / hour per ug/ liter)
Dose (rem)
Total Body 7.4E-09 7.8E-15 Skin 1.1E-07 1.2E-13 The doses received from boating are calculated using Equation 15 and by
- dividing _the dose rate factors by 2, to correct for the geometry (Soldat et al.
1974). The same values assume ' for U and T, in the dose calculations for--
swimming, are used (Soldat et al. 1974).
The doses for boating are given in Table A.13.
TABLE A.13.
Fifty Years of External Exposure to 239Pu from Boating Organ Dose (rem)
Total Body 3.9E-15 Skin 5.8E-14 i.
A-18
A
- .4
. Shoreline Exposure The doses received from exposure to shoreline ' deposits are calculated by:
Dj = U.~(DF)$ C T (A-16) s where L U
- axposure rate (hours / year) 2 (DF)$. * -dose factor for organ i given in Table 4 (rem / hour.per ug/m )
E averag'e radionuclide surface concentration in the~ top 2.5 cm e
s 2
of shoreline sediments (pg/m )
T*
period of exposure (years)
A differential equation was set up to represent the buildup of radio-nuclide concentration in the shoreline sediments from the transport of the radionuclide particulates in the water adjacent to the sediment.
The pro-cedure is similar to that discussed in Regulatory Guide 1.109, Rev.1, except that the water concentration is decreasing with time.
Assuming a sediment surface density'of 40 kg/m2 (USNRC Guide 1.109 1977) and a water-to-sediment transfer coefficient of 7.2 x 10-2 f./kg per hour (USNRC Guide 1.1091977),
ignoring radiological decay, and using Equation A-ll to predict the water concentration, the following equation for the sediment surface concentration is obtained:
C
=C
+ (1.29 x 10-7) Sg [1 - exp(-At)l/A
( A-17) s where U
'C the surface concentration of radioactive material initially deposited from the cloud onto the sediments-(pg/m ); same as 2
W defined in Equation A-4 1
A-19 6
.o' (1129 x 10-7 ei th'e. extrapolated water concentration at t = 0,1.86 x_-10-9 pg/t,
~
times the water-to-sediment' transfer coefficient, 7.2 x 10-2 2/kg :
h'r, times -the sediment surface density,.
2 2 per day) 40lkg/m,.timesL24 hr/ day-(ug/m S,
- shore-width factor that describes the geometry of the exposure (dimensionless)-
' A * - removal constant for plutonium in a lake, defined:in.
Equation A-11 (days-1) t *:Ltime since deposition.onto the lake surface (days)
A -shore-width factor of_0.3 is assumed for a lake shore (USNRC -Guide 1.109 1977).
Equation A-17 was integrated over a 50-year period and divided by
~
50 years to obtain an average radionuclide surface concentration in the-sedi-ments of 7.3 x 10-5 pg/m, during the period of exposure.
Using an exposure 2
--rate of 50 hrs / year-(Soldat et al. 1974), doses were calculated for a 50-year period and are-listed in Table A.14.
TABLE A.14.
Fifty Years of Shoreline Exposure-to 239PU Organ Dose (rem)
Total Body 8.9E-11 Skin 8.8E-10 1
i A-20
_.m
4 e-
"r-
SUMMARY
0F FIFTY-YEAR' COMMITTED DOSE EQUIVALENTS
'FROM ALL MODES OF-EXPOSURE A summary' of the 50-year committed dose equivalents from all modes of exposure is given 'in Table A.15.
The inhalation exposure mode contributes y
_ greater than.98% of the total dose to the total body, lungs, and bone. All-other exposure modes contribute less than 1%, except water consumption, which
~
~
The assumptions used for this expo-contributes 1.6% to'the total bone dose.
'sure mode were ~very conservative, and,. in reality, this mode of exposure is
" not. expected to contribute significantly. Therefore, for accidental airborne releases of plutonium, only Linhalation from initial cloud passage and resus-
. pension requires consideration.
Resuspension could contribute as much as
'39% of -the '9tal dose to the total body, lungs, and bone from inhalation, if
- all plutonium particles released and ava'ilable for resuspension are.in the respirable range.
The dose-equivalents to the skin and GI-LLI are insignificant when com-pared to the lungs and bone dose, and can be ignored. Although 239PU was the only isotope considered, these conclusions apply to most isotopes of plutonium and a typical' mixture of plutonium isotopes.
d i
I.,.
e 9
3 A-21 1
6
239
- TABLE-A.15.
Fifty-Year Committed Dose: Equivalents from an Acute Release of Pu; to the Atmosphere -
E Fifty-Year Committed-Dose. Equivalents (rem) to the Following 0rgans:'
Exposure Mode Total Body Skin Lungs Bone GI-LLI Initial Inhalation 5.6E-07.(61) 9.9E-07 (61)
Ll.2E-05 (60).
- 7.3E-10 (1.3)
~
Inhalation from Resuspension 3.5E-07 (38) 6.2E-07 (39) 7.5E-06 (38)-
4.5E-10 (0.8);
Cloud Submersion 1.2E-15 (<0.1) 1.6E-14 (<0.1) 1.2E-15 (<0.1). 1.2E-15-(<0.1)
.l. 2E-15 ; (<0.1 ) -
Ground Exposure 1.5E-ll (<0.1) 1.5E-10 (15) 1.5E-ll (<0.1) 1.5E-11 (<0.1) 1.5E-11 (<0.1)-
Crop Consunption 2.8E-09 (0.3) 1.1E-07 (0.6) 1.lE-08 (20);
~
Milk-Consumption 1.5E-14 (<0.1) 5'7E-13 (<0.1) 6.0E-14 (<0.1)
{g
- Beef. Consumption 1.0E-09 (0.1).
3.8E-08 (0.2) 14.lE-09 (7.3)
Water Consumption 8.3E-09(0.9) 3.2E-07 (1.6) 3;6E-08'-(64)
Fish Consumption 8.3E-10 (<0.1) 3.2E-08'(0.2)~
3.6E-09:(6.4)
. Swimming 7.8E-15 (<0.1) 1.2E.13~(<0.1) 7.8E-15(<0.1) 7.8E-15-(<0.1) 7.8E-15 (<0.1) '
Boating
-3.9E-15 (<0.1) 5.8E-14 (<0.1) 3.9E-15(<0.1) 3.9E-15 (<0.1) 3.9E-15 (<0.1)
Shoreline Exposure 8.9E-ll (<0.1) 8.8E-10 (85) 8.9E-ll (<0.1) 8;9E-ll (<0.1) 8.9E-ll (0.2)-
Totals 9.2E-07 (100) 1.0E-09 (100)
.l.6E-06 (100).
2.0E-05 (100) 5.6E-08 (100)
~
(
') - percent contribution of pathway to total organ dose.
=
a s
g 4
g I-
' h
x w-a _4 _:
e
^ d.!
. APPENDIX B DOSE FACTORS FOR' INHALATION, AND DOSE CALCULATION RESULTS FOR' CLASS W PLUTONIUM
- 9
+
a 4
f a v
9
+
9-r T
W-
l lis.J &c APPENDIX B TABLE B.l..
Fifty-Year Committed Dose Equivalent Factors) from Acute Inhalation for Class W Materialta (rem per ug inhaled)
- Isotope Total Body Kidneys
-Liver Bone Lungs Pu 1.2E+3(b) 4.8E+3 1.5E+4 2.4E+4 9.2E+2 238 239Pu 4'. 6E+0 '
1.9E+1 5.9E+1 9.7E+1
.3.0E+0.
240Pu 1.7E+1 6.9E+1 2.2E+2-3.6E+2 1.lE+1 241 Pu 1.3E+2-6.lE+2 1.8E+3 3.2E+3 1.8E+0 242 Pu 2.8E-1 1.lE+0 3.6E+0 5.7E+0
'1.8E-1 241 Am 2.0E+2 1.5E+3 3.2E+3-5.2E+3 1.7E+2 (a) Committed dose equivalent factors calculated using DACRIN for 1 um AMAD size particles. Organ masses are those reported in ICRP-23.
3 (b) 1.2E+3 is identical to 1.2 x 10,
TABLE B.2.. Fifty-Year Committed Dose Equivalent-Factors from Acute Inhalation for Class Y Material i
(rem per ug inhaled) l-Isotooe Total Body Kidneys.
Liver Bone Lungs 238 Pu' 4.3E+2
-1.8E+3 5.8E+3-8.9E+3 9.0E+3 239 Pu-
.l.7E+0 7.lE+0 2.3E+1 3.7E+1' 3.0E+1 240Pu
'6.3E+0 2.6E+1 I8.3E+1 1.3E+2 1.lE+2 4
l' 241 Pu 4.3E+1 2.0E+2 6.0E+2 1.lE+3 9.6E+1 242 Pu 1.0E-1 4.3E-1 1.4E+0 2.2E+0 1.8E+0 241 Am 7.8E+1 5.6E+2-1.2E+3 1.9E+3~
l.7E+3 t
4 9
4 B-1
/
.-s.
..,.M-'"'T'~""~'"~~~
' ~ "
' " ~ ~
m o
TABLE B.3.
Fifty-Year' Committed Dose Equivalent Factors from One-Year Chionic Inhalation for. Class W Material
~ (rem per ug inhaled in !first year)
- Isotope
. Total Body Kidneys Liver Bone Lungs 238Pu 1.2E+3' 4.8E+31 l'.5E+4 2.4E+4 l9.2E+2'
~
239Pu 4.5E+0 1.9E+1 5.8E+1.
' 9.7E+1 3.0E+0 240Pui
- 1. 7E+1 6.8E+1-2.2E42 3.6E+2 1.lE+1:
241 Pu~
-1.3E+2 6.lE+2 1.8E+3 3.2E+3' l.8E+0 242Pu.
2.8E-1 1.1E+0
-3.6E+0
- 5.7E+0 1.8E-1 241
~
2.0E+2 1.5E+3 3.2E+3 5.1E+3 1.7E+2 Am TABLE B.4.
' Fifty-Year Committed Dose Equivalent Factors from One-Year Chronic Inhalation for Class Y Material (rem per ug inhaled in first year)
Isotope Total Body Kidneys Liver Bone-Lungs 238Pu 4.3E+2 1.8E+3 5.7E+3 8.8E+3 9.0E+3 239 Pu 1.7E+0 7.0E+0 2.2E+1 3.6E+1 3.0E+1 240Pu 6.2E+0 2.6E+1 8.2E+1 1.3E+2 1.lE+2 241 Pu
- 4. 3E+1 2.0E+2 6.0E+2 1.0E+3 9.6E+1 242 Pu 1.0E-1 4.3E-1 1.4E+0 2.lE+0 1.8E+0 241 Am
- 7. 7E+1 5.6E+2 1.2E+3 1.9E+3 1.7E+3 w
a B-2
/
3
[
e,
- o TABLE B.5. - Fifty-Year Committed Dose Equivalents from Inhalation Following an Earthquake (Class W)
Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence W (rem)
Reference Case ItDJ Case II Case III Case IV Case I Case II Case III Case IV Total Body 4.8E+4 5.8E+5 5.5E+4 6.0E+5 7.lE-1 4.0E+1 7.8E-1 4.0E+1 Kidneys 2.lE+5 2.5E+6 2.4E+5 2.6E+6 3.lE+0 1.7E+2 3.4E+0 1.7E+2 Liver 6.5E+5 7.8E+6 7.4E+5 8.lE+6 9.6E+0 5.3E+2 1.lE+1 5.4E+2 Bone.
1.1E+6 1.3E+7 1.2E+6 1.4E+7 1.6E+1 8.9E+2.
1.8E+1 9.0E+2 Lungs 2.0E+4 2.3E+5 2.2E+4 2.5E+5 2.9E-1 1.6E+1 3.2E-1 1.6E+1
.(a) Located 2000 meters SSE of the NMDF.
(b) Case I - most likely release with most likely dispersion; Case II '- most 'likely release with conservative dispersion; Case III' _. conservative release with most likely dispersion; Case IV - conservative release with conservative dispersion.
TABLE B.6.
Fifty-Year Committed Dose Equivalents from Inhalation Following a.110-mph Tornado (Class W)
Committed Dose Equivalents -for:
Organ of Population { person-rem)
Nearest Residenceial (rem)
Reference Case I Case II Case III Case IV Case I Case II Case III Case IV Total Body
-(b) 9.7E+2 9.2E+3 1.7E-3 1.7E-2 Kidneys 4.2E+3 4.0E+4 7.2E-3 7.2E-2 Liver 1.3E+4 1.2E+5 2.2E-2 2.2E-1 Bone 2.2E+4 2.lE+5 3.7E-2 3.7E-1 Lungs 4.0E+2 3.8E+3 6.8E-4 6.8E-3 (a) Located 16,000 to 32,000 meters from the NMDF in the direction the tornado travels.
(b) No doges calculated for Cases I and II, as most likely release is insignificant
-(<10~
g Pu).
(
B-3 N
l o.
TABLE B.7.
Fifty-Year Committed Dose Equivalents from Inhalation' Following a 130-mph Tornado-(Class W)
Comitted Dose Equivalents for:
Organ _of Population (person-rem)
Nearest Residence (d> (rem)
Reference Case I Case II Case III Case IV Case I Case II Case III Case IV Total Body 1.8E+3 1.8E+4-4.6E+3 4.6E+4 2.8E-3 2.8E-2 7.2E-3 7.2E-2 Kidneys 7.7E+3 7.7E+4
~2.0E+4 2.0E+5 1.2E-2 1.2E-1 3.lE-2
' 3. l E-1 Liver 2.4E+4 2.8E+5 6.3E+4 6.2E+5 3.7E-2 3.7E-1 9.7E-2 9.7E-1
. Bone 4.0E+4 3.9E+5 1.0E+5 1.0E+6 6.2E-2 6.2E-1 1.6E-1 1.6E+0 Lungs ~
7.2E+2 7.2E+3 1.9E+3 1.9E+4 1.lE-3 1.lE-2 2.9E-3 2.9E-2
~
(a) located 16.000_to 32,000 meters from the NMDF in the direction the tornado travels.
TABLE B.8.
Fif ty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Tornado -(Class W)
Comitted Dose Eauivalents for:
Organ of Pooulation (person-rem)
Nearest Residencela)-(rem)
Reference Case I Case II Case III Case IV. Case I Case II Case III Case IV Total Body _7.7E+4 7.7E+5 1.2E+5 1.2E+6 1.0E-1 1.0E+0 1.5E-1 1.5E+0 Kidneys' 3.4E+5 3.4E+6 5.0E+5 5.0E+6 4.4E-1 4.4E+0 6.7E-1 6.7E+0 Liver 1.0E+6 1.0E+7 1.6E+6 1.6E+7 1.4E+0 1.4E+1 2.lE+0 2.lE+1 Bone 1.7E+6 1.7E+7 2.6E+6 2.6E+7 2.3E+0 2.3E+1 3.4E+0 3.4E+1 Lungs 3.lE+4 3.lE+5 4.7E+4 4.7E+5 4.2E-2 4.2E-1 6.3E-2 6.3E-1 (a) located 16,000 to 32,000 meters from the NMDF in the direction the tornado travels.
s e
B-4 t
.~+
.%%,-.e..,..
ww.
-.au-.
e_-_w;,.d.
t I
..... e TABLE B.9.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 170-mph Tornado (Class W)
Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Retidence(a) (rem)
Reference Case I Case II Case III Case IV Case I Case II Case III Case IV Total Body 3.4E+4 3.3E+5
'3.8E+4 3.5E+5 2.4E-2 2.4E-1 6.3E-2 2.5E-1 Kidneys-
-1.5E+5 1.4E+6' l.7E+5.
~1.5E+6 1.0E-1. 1.0E+0 ~ 2.8E-1 1.lE+0 Liver 4.5E+5 4.4E+6 5.2E+5' 4.7E+6 3.2E-1 3.2E+0 8.5E-1 3.4E+0 Bone-7.6E+5 7.3E+6-8.6E+5 7.8E+6 5.3E-1 5.3E+0 1.4E+0 5.7E+0 Lungs 1.4E+4 1.3E+5 1.6E+4 1.4E+5 9.7E-3 9.7E-2 2.6E-2 1.0E-1 (a) Located 32,000 to 48,000 meters from the NMDF in the direction the tornado travels for Cases I and II; located 2000 meters SSE of the NMDF for Cases III and IV.
l I
i.
O f
l.
l l
B-5 l
t 4
7 t....
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