ML19347B769
| ML19347B769 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 02/28/1980 |
| From: | Jamison J, Watson E Battelle Memorial Institute, PACIFIC NORTHWEST NATION |
| To: | |
| Shared Package | |
| ML19347B763 | List: |
| References | |
| REF-PROJ-M-3 PNL-3315, UC-20E, NUDOCS 8010150628 | |
| Download: ML19347B769 (70) | |
Text
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PNL-3315 4
UC-20e
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e 4
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i ENVIRONMENTAL CONSEQUENCES OF POSTULATED i
PLUT0NIUM RELEASES FROM EXXON NUCLEAR M0FP, RICHLAND, WASHINGTON, AS A RESULT i
0F SEVERE NATURAL PHENOMENA J. D. Jamison E. C. Watson i
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j February 1980 i
j Prepared for Division of Environmental Impact Studies Argonne National Laboratory under a Related Services Agreement with the U.S. Department of Energy Contract DE-AC06-76RL0 1830 i
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i Pacific Northwest Laboratory Richland, Washington 99352 i
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80101.50628
SUMMARY
Potential environmental consequences in terms of radiation dose to people are presented for postulated plutonium releases caused by severe natural pheno-mena at the Exxon Nuclear Company Mixed 0xide Fabrication Plant (M0FP), Richland, Washington. The severe natural phenomena considered are earthquakes, tornadoes, high straight-line winds, and floods.
Maximum,lutonium deposition values are given for significant locations around the site.
All important potential expo-sure pathways are examined. The most likely 50-year committed dosa equivalents are given in Table 1 for the maximum-exposed individual and the population within a 50-mile radius of the plant.
The maximum plutonium deposition values most likely to occur offsite are also given in Table 1.
The most likely calculated 50-year collective committed dose equivalents are all much lower than the collective dose equivalent expected from 50 years of exposure to natural background radiation and medical x-rays. The most likely maximum residual plutonium contamination estimated to be deposited offsite following Earthquake No. 2, and the 190-mph and 250-mph tornadoes are above the Environmental Protection Agency's (EPA) proposed guideline for Nutonium in the general environment of 0.2 pCi/m.
The deposition values follcaing the other 2
severe natural phenomena are below the EPA proposed guideline.
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TABLE 1.
40st Likely 50-Year Committed Dose Equivalents and Maximum Plutonium Deposition Values i
50-Year Committed i
Dose Equivalent (a)
Maximum Plutonium Organs of Population Nearest Deposition Off-site 2
Event Reference (person-rem)
Residence (rem)
(pCi/m )
Earthquake 2 Lungs 1.6 x 104 2.4 Bone 2.3 x 104 3.5 2.7 x 101 150-mph Wind Lungs 8.2 x 10-1 1.4 x 10-4 Bone 1.2 2.0 x 10-4 (b) 4 150-mph Tornado Lungs 1.7 x 103 3.4 x 10-2 l
Bone 2.5 x 10" 5.0 x 10-2 l
8.8 x 10-3
^
190-mph Tornado Lungs 3.1 x 104 5.0 x 10-1 Bone 4.5 x 10' 7.3 x 10-1 2.8 4
l 250-mph Tornado Lungs 1.9 x 104 3.7 Bone 2.8 x 104 5.4 1
6.6 Flood (c)
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4 (a)A translocation Class Y has been assumed.
(b) Insignificant.
(c)0utside probability range considered in this study.
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CONTENTS i
SUMMARY
iii INTRODUCTION 1
s ENVIRONMENTAL EXPOSURE PATHWAYS FOR PLUT0NIUM 3
RADIATION DOSE MODELS FOR AN ATMCSPHERIC RELEASE 5
RESULTS 11 s
EARTHQUAKES 11 HIGH WINDS 14 TORNAD0ES.
15 DISCUSSION 19 APPENDIX A - EVALUATION OF ENVIRONMENTAL PATHWAYS BY WHICH PLUT0NIUM MAY REACH PEOPLE FROM AN ACCIDENTAL AIRBORNE RELEASE A-1 i
1 APPENDIX B - DOSE FACTORS FOR INHALATION, AND DOSE CALCULATION RESULTS FOR CLASS W PLUT0NIUM.
B-1 l
APPENDIX C - DOSE CALCULATION RESULTS FOR 72 KG/ DAY PLANT THROUGHPUT C-1 l.
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4 TABLES 1
Most Likely 50-Year Committed Dose Equivalents and Maximum l
Plutonium Deposition Values iv f
2 Estimated Quantity of Plutonium Released to the Atmosphere Following an Earthquake 11 3
Isotopic Composition of the Plutonium Mixture 12 4
4 Fifty-Year Committed Dose Equivalents from Inhalation Following Earthquake No. 2 13 4
5 Estimated Maximum Plutonium Deposition at Significant Locations Following Earthquake No. 2 13 6
Estimated Quantity of Plutonium Released to the Atmosphere Following a 150-mph Straight-Line Wind 14 7
Fif ty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Straight-Line Wind 15 8
Estimated Quantity of Plutonium Released to the Atmosphere 15 Following a Tornado.
9 Fif ty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Tornado 16 i
10 Fifty-Year Committed Dose Equivalents from Inhalation Following a 190-mph Tornado 17 11 Fif ty-Year Committed Dose Equivalents from Inhalation Following a 250-mph Tornado 17 12 Estimated Maximum Plutonium Deposition at Significant Locations Following a 150-mph Tornado 17 13 Estimated Maximum Plutonium Deposition at Significant Locations Following a 190-mph Tornado 18 14 Estimated Maximum Plutonium Deposition at Significant Locations Following a 250-mph Tornado 18 A.1 Fifty-Year Committed Dose Equivalents from Inhalation of 1 pm AMAD 239Pu Particles A-3 A.2 Fifty-Year Committed Dose Equivalents from 50 Years' Inhalation of 1 pm AMAD Resuspended 239pu Particles A-6 vi
i A.3 Air Submersion Doses from Exposure to 239Pu A-7 A.4 Fifty Years of External Exposure to 239Pu Deposited on the Ground A-8 239Pu Concentration Estimated in Leafy Vegetables and A.5 Average Produce for a Five-Year Period A-10 A.6 Fifty-Year Committed Dose Equivalents from 50 Years' Ingestion of Leafy Vegetables and Prode e Contaminated with 239Pu A-10 A.7 Average 239Pu Corcentration Estimated in Grain and Forage for a Five-Year Period A-12 A.8 Fifty-Year Committed Dose Equivalents from 50 Years' Ingestion of Milk and Beef Contaminated with 239Pu A-12 A.9 Fifty-Year Committed Dose Equivalents from 50 Years' Ingestion of j
Animal Products Contaminated with 239Pu.
A-15 A.10 Fifty-Year Committed Dcce Equivalents from 50 Years' Consumption of Water Contaminated with 239Pu.
A-16 A.ll Fifty-Year Committed Dose Equivalents from 50 Years' Consumption of 1
Fish Contaminated with 239Pu A-17 i
A.12 Fifty Years of External Exposure to 239Pu from Swimming A-18 A.13 Fif ty Years of External Exposure to 239Pu from Boating.
A-18 A.14 Fif ty Years of Shoreline Exposure to 239Pu A-20 A.15 Fifty-Year Committed Dose Equivalents from an Acute Release of 4
239Pu to the Atmosphere A-22 B.1 Fif ty-Year Comr.:itted Dose Equivalent Factors from Acute Inhalation for Class W Material B-1 B.2 Fifty-Year Committed Dose Equivalent Factors from Acuta Inhalation for Class Y Material B-1 B.3 Fifty-Year Committed Dose Equivalent Factors from One-Year Chronic Inhalation for Class 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 Ir!,alation Following Earthquake No. 2 B-3 d
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B.6 Fifty-Year Committed Dose Equivalents from Inhalation Following i
a 150-mph Straight-Line Wind B-3 B.7 Fifty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Tornado B-4 B.8 Fifty-Year Committed Dose Equivalents from Inhalation Following a 190-mph Tornado B-4 4
B.9 Fifty-Year Committed Dose Equivalents from Inhalation Following a 250-mph Tornado B-5 C.1 Fifty-Year Committed Dose Equivalents from Inhalation Following Earthquake No. 2 for 72 kg/d;y Plant Throughput C-1 I
C.2 Fif ty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Straight-Line Wind for 72 kg/ day Plant Throughput.
C-1 C.3 Fifty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Tornado for 72 kg/ day Plant Throughput C-2 C.4 Fifty-Year Committed Dose Equivalents from Inhalation Following a 190-mph Tornado for 72 kg/ day Plant Throughput C-2 C.5 Fifty-Year Committed Dose Equivalents from Inhalation Following a 250-mph Tornado for 72 kg/ day Plant Throughput C-3 4
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INTRODUCTION j
This study estimates the potential environmental consequences in terms of radiation dose to people resulting from postulated plutonium releases caused by l
severe weather or other natural phenomena.
The accident scenarios considered i
include earthquakes, tornadoes, high winds, and floods.
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 et al. (1980) for both I
the present plant throughput of 36 kg plutonium oxide per day and the projected l
future thoughput of 72 kg/ day.
The doses presented in the text of this report were calculated using the source terms for a 36 kg/ day operation.
The doses calculated using the source terms for a 72 kg/ day operation are presented in Appendix C.
The atmospheric transport and dispersal of released plutonium was estimated by Pepper (1979) for tornadoes, by Carson for high winds,(a) and by the NRC for earthquakes.(b) The site characteristics and demography around Richland, WA were taken from the Final Environmental Statement for the Exxon Nuclear Company M0FP, (FES 1974) and from a population distribution study per-i formed previously by BNW (Yandon,1976).
(a)" Regional Demography, Topography and Land Use, Ecology, and Meteorology."
Descriptions for Westinghouse PFDL transmitted by letter from J. E. Carson of ANL/EIS to J. E. Ayer of NRC/FCMS, March 13, 1978.
(b)" Meteorological Evaluations for Nuclear Facilities at Exxon Richland, Washington." Annual average atmospheric dispersion values for the Site transmitted by a letter from L. G. Hulman of NRC/DSE to R. B. McPherson of BNW May 2, 1978.
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ENVIRONMENTAL ENVIRONMENTAL SITE CHARACTERISTICS RELEASE
- TRANSPORT AND
' CONTAMINATION 4 DEMOGRAPHY. AND DOSE DESCRIPTION DISPERSAL LEVELS USAGE FACTORS I
QUANTITY HYDROLOGIC GROUND SURFACE POPULATION MAX INDIVIDUALS MAX INDIVIDUAL /
DUR ATIO N SEVERE WEATHER SURFACE WATER RESIDENT / FARM POPULATION i
TIME DEPENDENCE ACCIDENT DIFFUSION FOODS LAND USE CHARACTERISTICS DIET FACTORS ISOTOPIC COMPOSITION FIGURE 1.
Accidental Environmental Consequences Evaluation t
)
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2
ENVIRONMENTAL EXPOSURE PATHWAYS FOR PLUT0NIUM The potential environmental exposure pathways for radionuclidas released to the atmosphere and water are shown in Figura 2.
Our experience has shown 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 atr.ospheric 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
For liquid releases during a flood, the important exposure pathways are aquatic food ingestion, water consumption, irrigation with contaminated water and subsequent food ingestion, and shoreline exposure.
The significant poten-tial exposure pathways that have been discussed are shown in Figure 3.
- However, it is estimated that any flood which would threaten the Exxon M0FP would be preceeded by a warning period of at least 30 days, during which dikes could be constructed and the plutonium inventory reiocated above the projected flood levels (FES 1974).
As a result, this release scenario will not be considered further.
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RESUSPENSION 1RRIG T N HALATION
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AQUATIC FOOD INGESTION DRINKING 1
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-FIFURE 3.
Significant Potential Exposure Pathways Through Which People May Be Exposed from an Accidental Release of Plutonium 4
RADIATION DOSE MODELS FOR AN ATM0 SPHERIC RELEASE The equation for calculating committed radiation dose equivalents from acute inhalation is:
ir
- O (E/Q)(BR)(DCF)ir II)
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where the committed dose equivalent to organ r from acute inhalation DC e
ir of radionuclide i, rem 1
the quantity of radionuclide i released to the atmosphere, pg Q
e 3
the accident atmospheric exposure coefficient, pg sec/m per E/Q e pg released i
the ventilation rate of the human receptor during the exposure BR e period, m3/sec the acute committed dose equivalent factor, rem per pg inhaled; (DCF)ir e
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 recommendations (ICRP 1975):
3.3 x 10-4 m3/sec for the period 0-8 hours; 3
2.3 x 10-4 m3/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 computercodeDACRIN(Houston,StrengeandWatson1975). 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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l Fifty-year committed 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 2uAm. The organs of interest in plutonium dosimetry are the total body, kidneys, liver, bone, and lungs.
I The plutor.ium postulated to be released to the atmosphere is assumed to be in the fora of plutonium oxides (Mishima et al. 1979).
Lung retention, as described by the TGLM, depends upon the chemical nature of the compound inhaled.
Compounds of plutonium largely fall into Class Y (retained for years) or Class W (retained for weeks).
There is no evidence of plutonium existing in the environment as Class D (retained for days). Actinides in the oxide form are currently classified as Class Y (ICRP 1972), which is assumed in this study.
Doses for plutonium as Class W material, however, are included in Appendix B.
Plutonium particulates that deposit onto the ground surface 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 an earthquake), the deposition velocity concept was used to estimate the plutonium deposition (Equation 2).
j = Q (E/Q)Vd (2)
W where the concentration of radionuclide i on the ground surface, pg/m2 W
e Qg the quantity of radionuclide i released to the atmosphere, pg the accident atmospheric exposure coefficient, pg sec/m3 E/Q
- per pg released V
e particle deposition velocity, m/sec d
hActivitymedianaerodynamicdiameter 6
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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, Gudiksen et al.1976, FES 1974). A value of 1 x 10-3 m/sec is used in this report (Baker 1977).
Deposition values for tornadoes were reported by Pepper (1979). The NRC estimated deposition values during earth-quakes and annual average conditions.(a)
During high-wind conditions, ground contamination from plurne depletion is cer.sidered to be very small.(b)
This is due to the large concentration gradi. x.
Resuspension rates for materiei deposited on the ground are time depen-dent and tend to decrease with tina 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-j 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 j
l (Selby et al.1975, Friedman 1976, Anspaugh et al.1975, EPA 1977, Cohen 1977, F.S 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:
(a)" Meteorological Evaluations for Nuclear Facilities at Exxon Richland, Washington." Transmitted by letter from L. G. Hulman of NRC/DSL to R. B. McPherson of BNW/ESD, May 2,1978.
I (b)" Regional Demography, Topography and Land Use, Ecology, and Meteorology."
Descriptions for the Westinghouse PFDL transmitted by letter from J. E. Carson of ANL/EIS to J. E. Ayer of NRC/FCMS, March 13, 1978.
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K(t) = 10-4 exp(-0.15 tb) + 10-9 (3) where time since the material was deposited on the ground, days t e 10-4 e resuspension factor at time t = 0, m-1 10-9 e resuspension factor after 20 years, m-1 The second term in Equation 3,10-9
-1, was added based on the assump-m 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 process (Anspaugh et al.1975).
Figure 4 illustrates the time dependence of the resuspension factor.
~4 10
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K 10 EXP (-0.15lh + 10 7
E J 10 NO 6 10'I 5m 10' a
10 1
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10 20 30 40 YlME SINCE DEPOSITION, YEARS FIGURE 4.
Time Dependence of the Environmental Surface Resuspension Factor 8
Equation 3 was integrated over each year post-deposition and divided by the integrated time period to determine the average resuspension factor for l
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 chronic 50-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 E(BR)(DCF)$7 (3.16 x 10 )
(4) 7 where the 50-year committed dose equivalent to organ r from one year DC o
ir of inhalation of radionuclide i, rem /yr of inhalation the concentration of radionuclide i on the ground surface for W
e 2
the year of consideration, pg/m i
the average resuspension factor for the year of considera-K e tion, m-1 l
the ventilation rate of the human receptor (for a duration of BR e 3
greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), m /sec l
(DCF)ir chronic committed dose equivalent factor, rem /pg inhaled 3.16 x 107 e conversion factor, sec/yr 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.
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RESULTS EARTHQUAKES I
Committed radiation dose equivalents to several organs of the human body were calculated for a postulated earthquake event using the source terms given in Table 2.
)
TABLE 2.
Estimated Quantity of Plutonium Releasgd to the Atmosphere Following an Earthquake (a)
Airborne Release of Plutonium (g)
Earthquake No. 2 Time Period Conservative Most Likely 0-2 hr 1.2 1.1 2-8 hr 0.6 0.4 8-24 hr 2
1 1-4 Days 7
5 Total 10.8 7.5 l
(a)Taken from Mishima et al. (1980).
Only the quantity released in the respirable particle size range (less than 10 pm) was used to cal-culate doses.
Peak ground acceleration levels from 0.3 to 1.0 g were assumed for Earthquake No. 1, and greater than 1.0 g for Earthquake No. 2.
Significant damage was not postulated for Earthquake No. 1 (Mishima et al. 1980), and no radiation doses were calculated.
The isotopic composition assumed for the plutonium mixture is based on the Final Environmental Statement for Exxon Nuclear M0FP (FES 1974).
The isotopic composition by weight percent is given in Table 3.
l For the 0-2 hour time period, accident atmospheric dispersion values for a 5% and 50% condition, calculated by the NRC for the Exxon Nuclear Site, were used to estimate potential committed dose equivalents to the population and a 11
TABLE 3.
Isotopic Composition of the Plutonium Mixture Isotope Weight Percent 238Pu 1.9 239pu 63.9 240Pu 18.8 241Pu 10.5 242Pu 3.5 241Am 1.4 100.0 4
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maximum individual. Annual average atmospheric dispersion and deposition j
values also calculated by the NRC were used for all other time periods.
For the 5% condition (conservative), the annual average dispersion and deposition l
values were multiplied by a factor of 4, as recommended by Carson.(a)
Four i
combinations of release and dispersion are considered:
most likely 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 pheno-mena scenarios. The calculated committed dose equivalents are listed in Table 4 for Earthquake No. 2.
The estimated maximum plutonium ground deposi-tions at the site boundary, nearest residence, and farm are listed in Table 5.
2 (a) Letter transmitted from J. E. Carson of ANL/EIS to R. B. McPherson of BfM/ESD, October 24, 1978.
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TABLE 4.
Fifty-Year Committed Dose Equivalents from Inhalation Following Earthquake No. 2 (Class Y) 1 Comitted Dose Equivalents for:
j Organ of Population (person-rem)tal Nearest Residence (rem)lDJ Reference Case Ilc) Case 11 Case III Case IV Case I Case II Case III Case IV Total Body 1.0E+3 6.9E+3 1.4E+3 2.4E+4 1.6E-1 1.8E+0 1.8E-1 2.0E+0 I.
Kidneys 4.7E+3 3.lE+4 6.4E+3 1.lE+5 7.lE-1 8.3E+0 8.0E-1 9.2E+0 Liver 1.4E+4 9.5E+4 2.0E+4 3.2E+5 2.2E+0 2.5E+1 2.4E+0 2.8E+1 Bone 2.3E+4 1.5E+5 3.2E+4 5.2E+5 3.5E+0 4.lE+1 3.9E+0 4.5E+1 I
Lungs 1.6E+4 1.lE+5 2.2E+4 3.6E+5 2.4E+0 2.8E+1 2.7E+0 3.lE+1 (a) Pcpulation within a 50-mile radius of the plant.
(b) Located 4150 meters SW of the plant.
(c) 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, i
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TABLE 5.
Estimated Maximum Plutonium Deposition at i
Significant Locations Following Earthquake j
No. 2 (all particle sizes) 2 Pu Deposition (pCi/m )
j Location Case I Case Il Case III Case IV l
SiteBoundary(a) 2.7E+1 2.3E+2
- 3. 2E+1 2.6E+2 Residence (b) 2.3E-1 2.7E+0 2.7E-1 3.0E+0 Farm (c) 8.8E-1 5.2E+0 1.2E+0 6.6E+0 t
i a
(a) Located 125 meters W of the plant.
(b) Located 4150 meters SW of the plant.
(c) Located 1600 meters ESE of the plant.
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HIGH WINDS A high, 150-mph straight-line wind condition was considered. The l
quantities of plutonium released to the atmosphere following a 150-mph severe j
wind were estimated by Mishima (1980) and are reported in Table 6.
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TABLE 6.
Estimated Quantity of Plutonium Released to the Atmosphere
]
Following a 150-mph Straight-Line Wind (a)
Airborne Release of Plutonium (g)
Time Period Conservative Most Likely 0-2 hr 1.0E-2 1.0E-2
~
2-8 hr 1.0E-5 1.0E-5 8-24 hr 3.0E-5 3.0E-5 1-4 Days 1.0E-4 1.0E-4 l
Total 1.0E-2 1.0E-2 l
(a)0nly the quantity released in the respirable particle size range was usM to calculate l
doses.
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For the 0- to 2-hour time period, tht: ir.0 t likely atmospheric dispersion values were calculated by Carson. The wind was assumed to blow from the westerly directions (into the NE, ENE, E, ESE, and SE sectors) (Fujita 1977).
i The 0- to 2-hour dispersion values were multiplied by a factor of 10 to represent the conservative case.(a)
Significant deposition downwind is pre-l sumed to not occur during the O-to 2-hour period.
Committed radiation dose equivalents calculated for several organs of the human body are given in Table 7.
1 (a) Letter transmitted from J. E. Carson of ANL/EIS to R. B. McPherson of BNW/ESD, October 24, 1978.
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TABLE 7.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Straight-Line Wind (Class Y)
Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (rem)(a)
Reference Case 1(b) Case 11 Case III Case IV Case I Case II Case III Case IV Total Body 5.4E-2 4.4E-1 5.4E-2 4.1E+0 9.1E-6 9.lE-5 9.lE-6 9.lE-5 Kidneys 2.4E-1 2.0E+0 2.4E-1 1.8E+1 4.1E-5 4.1E-4 4.lE-5 4.lE-4 Liver 7.4E-1 6.1E+0 7.4E-1 5.6E+1 1.2E-4 1.2E-3 1.2E-4 1.2E-3 Bone 1.2E+0 9.9E+0 1.2E+0 9.0E+1 2.0E-4 2.0E-3 2.0E-4 2.0E-3 Lungs 8.2E-1 6.8E+0 8.2E-1 6.2E+1 1.4E-4 1.4E-3 1.4E-4 1.4E-3 (a) Located 3300 meters SE of the plant.
(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.
TORNAD0ES Plutonium releases following three tornadoes with maximum total wind speeds of 150 mph,190 mph, and 250 mph were estimated by Mishima (1980).
Releases for four time periods are presented in Table 8.
TABLE 8.
Estimated Quantity of Plutonium Released to the Atmosphere Following a Tornado (a)
Airborne Release of Pu (q) for the Following Maximum Total Wind Speeds:
150 mph 190 mph 250 mph Time Period Conservative Most Likely Conservative Most Likely Conserve'.ive Most Likely 0-2 hr lE-2 lE-2 0.4 0.26 1.2 1.1 2-8 hr lE-5 1E-5 0.4 0.2 0.6 0.4 8-24 hr 3E-5 3E-5 1
0.5 2
1 1 f Days lE-4 lE-4 5
2 7
5 Total lE-2 lE-2 6.8 3.0 11.0 7.5 (a)0nly the quantity released in the respirable particle size range was used to calculate dose.'
e 15
l l
l Atmospheric dispersion and deposition values most likely to occur during l
a tornado were calculated by Pepper (1979). These values were assumed to apply during the first two hours after the event.
During this time period, the tornadoes were assumed to move in an easterly direction. Annual average atmospheric dispersion and deposition values were used for all other time periods. As recommended by Pepper (a) and Carson, the tornado dispersion values were multiplied by a factor of 10 to represent the conservative case, and the annual average atmospheric dispersion and deposition values were again multi-plied by a factor of 4.
Committed radiation dose equivalents are given in Tables 9 through 11 for Class Y plutonium. The estimated maximum ground con-tamination levels from plutonium deposition at the significant locations are listed in Tables 12 through 15.
TABLE 9.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Tornado (Class Y)
Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (rem)(a)
Reference Case 1(b) Case 11 Case III Case IV Case I Case 11 Case III Case IV Total Body 1.lE+2 1.1E+3 1.lE+2 1.lE+3 2.2E-3 2.2E-2 2.2E-3 2.2E-2 Kidneys 5.1E+2 5.lE+3 5.1E+2 5.lE+2 1.0E-2 1.0E-1 1.0E-2 1.0E-1 Liver 1.5E+3 1.5E+4 1.5E+3 1.5E+4 3.lE-2 3.iE-1 3.lE-2 3.lE-1 l
Bone 2.5E+3 2.5E+4 2.5E+3 2.5E+4 5.0E-2 5.0E-1 5.0E-2 5.0E-1 Lungs 1.7E+3 1.7E+4 1.7E+3 1.7E+4 3.4E-2 3.4E-1 3.4E-2 3.4E-1 (a) Located 16,000 to 32,000 meters from the plant in the direction the tornado travels.
(b) Case I - most likely release with most likely dispersion; Case II - most likely l
release with conservative dispersion; Case III - conservative release with most l
likely dispersion; Case IV - conservative release with conservative dispersion.
i l
(a) Letter transmitted from D. W. Pepper of SRL/ETD to R. B. McPherson of BNW/ESD, February 21, 1979.
16
I TABLE 10.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 190-mph Tornado (Class Y) i Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (rem)(a)
Reference Case I Case 11 Case III Case IV Case I Case II Case III Case IV Total Body 2.0E+3 1.8E+4 3.4E+3 2.7E+5 3.3E-2 3.3E-1 5.1E-2 5.1E-1 Kidneys 9.lE+3 8.2E+4 1.5E+4 1.2E+6 1.5E-1 1.5E+0 2.3E-1 2.3E+0 Liver 2.8E+4 2.5E e5 4.6E+4 3.8E+6 4.5E-1 4.5E+0 7.0E-1 7.0E+0 Bone 4.5E+4 4.1E+5 7.4E+4 6.lE+6 7.3E-1 7.3E+0 1.lE+0
- 1. l E+1 Lungs 3.lE+4 2.8E+5 5.lE+4 4.2E+6 5.0E-1 5.0E+0 7.8E-1 7.8E+0 (a) Located 16,000 to 32,000 meters from the plant in the direction the tornado travels.
TABLE 11.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 250-mph Tornado (Class Y)
Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (rem)(a)
Reference Case I Case 11 Case III Case IV Case I Case II Case ill Case IV Total Body 1.3E+3 8.3E+3 1.7E+3 7.5E+4 2.4E-1 2.4E+0 2.7E-1 2.7E+0 Kidneys 5.7E+3 3.7E+4 7.6E+3 3.4E+5 1.lE+0
- 1. l E+1 1.2E+0 1.2E+1 Liver 1.7E+4 1.lE+5 2.3E+4 1.0E+6 3.4E+0 3.4E+1 3.7E+o 3.7E+1 Bone 2.8E+4 1.8E+5 3.7E+4 1.7E+6 5.4E+0 5.4E+1 5.9E+0 5.9E+1 Lungs 1.9E+4 1.3E+5 2.6E+4 1.2E+6 3.7E+0 3.7E+1 4.lE+0
- 4. l E+1 (a) Located between 32,000 meters and 48,000 meters from the plant in the direction the tornado travels.
i TABLE 12.
Estimated Maximum Plutonium Deposition at Significant Locations Following a 150-mph Tornado (all particle sizes) 2 Pu Deposition (LC1/m )
location Case I Case II Case III Case IV Site Boundary (a) 1.4E-4 5.9E-4 1.4E-4 5.9E-4 Residence (b) 8.8E-3 8.8E-2 8.8E-3 8.8E-2 Farm (b) 8.8E-3 8.3E-2 8.8E-3 8.8E-2 (a) Located 125 m west of the plant.
(b) Located 16,000 to 32,000 meters from the plant in the direction the tornado travels.
17 i
- - - - ~ -
TABLE 13.
Estimated Maximum Plutonium Deposition at Significant Locations Following a 190-mph Tornado (all particle sizes)
Pu Deposition (pCi/m )
2 j
Location Case I Case II Case III Case IV l
SiteBoundary(a) 2.8E+0
- 1. l E+1 6.6E+0 2.7E+1 Residence (b) 1.3E-1 1.3E+0 2.0E-1 2.0E+0 Farm (c) 2.3E-1
- 1. 3E+0 5.4E-1 2.lE+0 4
i i
i (a) Located 125 m west of the plant.
(b) Located 16,000 to 32,000 meters from the plant in the j
direction the tornado travels.
(c) Located 1600 m ESE of the plant for cases I, III, and IV; for case II it is located 16,000 to 32,000 m from the plant in I
the direction the tornado travels.
TABLE 14.
Estimated Maximum Plutonium Deposition at Significant Locations Following a 250-mph i
Tornado (all particle sizes) 1 2
j Pu Deposition (pCi/m )
j Location Case I Case II Case III Case IV Site Boundary (a) 6.6E+0
- 2. 7E+1 9.9E+0
- 4. 0 E+1 Residence (b) 9.5E-1 9.5E+0 1.0E+0 1.0E+1 1
Farm (b) 9.5E-1 9.5E+0 1.0E+0 1.0E+1 i
(a) Located 125 meters W of the plant.
(b) Located 32,000 to 48,000 meters from the plant in the direction the tornado travels.
T i
P h.
18
DISCUSSION For the tornado, the majority of the radionuclide intake occurs after the first two hours.
At this time annual average meteorology is assumed to resume.
1 l '
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-1 meter values. To the best of our knowledge, there are no reported assessments l
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 their 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 calcu-lations.
The dose rate from natural background radiation in the vicinity of Richland, Washington is reported to be 100 mrem /yr to the total body (Houston 1979). Therefore, an individual receives a total-body dose of about 5 rem from exposure to natural background radiation during a 50-year period.
The col-lective dose equivalent from 50 years of exposure to natural background radia-tion to the total body of the population within a 50-mile radius of the Exxon Nuclear Company M0FP is 1 x 10s person-rem. The average annual dose to the total body of an individual from medical x-ray examination is about 20 mrem (United Nations 1977). This average dose corresponds to a 50-year collective dose equivalent of 2 x 105 person-rem. The dose contribution from fallout is negligible when compared to r.atural background radiation and medical x-ray exposure.
If a radiation worker was involved in an occupational accident and received a maximum permissible bone burden of 239pu, the 50-year committed dose equivalent to the bone would be greater than 1000 rem. As can be seen, except for the extreme conservative cases of the 190 mph and 250 mph tornadoes, the calculated 50-year committed dose equivalents to the population for the f
severe natural phenomena scenarios considered in this report are lower than the collective dose equivalent from 50 years of exposure to natural background l
radiation and medical x-rays.
19
Existing guidelines on acceptable levels of soil contamination from Pu 2 to 270 pCi/m2 (Selby et al. 1975; can be found to range from 0.01 pCi/m EPA 1977; Martin and Bloom 1975; Healy 1977; U.S. Code 1976; Healy 1974; Guthrie and Nichols 1964; Hazle and Crist 1975; Kathren 1968; Dunster 1962).
~
The EPA has proposed a guideline of 0.2 pCi/m2 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 190-mph and 250-mph tornadoes are above the EPA proposed guideline at some or all of the significant locations. The estimated contamination levels at these locations most likely to occur range from about 0.2 to 40 pCi/m. The predicted ground contamination levels for 2
the other severe natural phenomena are well below the EPA proposed guideline at all significant locations.
e 20 i
APPENDIX A EVALUATION OF ENVIRONMENTAL PATHWAYS BY WHICH PLUTONIUM MAY REACH PEOPLE FROM AN ACCIDENTAL AIRBORNE RELEASE f
i 9
b i
f l
h APPENDIX A EVALUATION OF ENVIRONMENTAL PATHWAYS BY WHICH PLUT0NIUM I
MAY REACH PEOPLE FROM AN ACCIDENTAL AI.tB0RNE RELEASE Twelve environmental exposure modes for an accidental airborne release are considered for evaluation.
Three are from exposure to the radioactive l
cloud, and four result from radioactive material deposited on the ground.
The remaining five are via the waterborne pathway, assuming radioactive material was deposited onto a nearby surface body of water.
The following exposure modes are included in the study:
l 1.
inhalation during the initial cloud passage, 2.
inhalation of resuspended radioactive material, l
3.
direct exposure from cloud submersion, l
4.
direct exposure to radioactive material deposited on the ground, 5.
ingestion of leafy vegetables, beef, milk, water and fish, 6.
direct exposure from swimming and boating in contaminated water, and 7.
external exposure to radioactive material concentrated in the shoreline sediment.
One isotope of plutonium is considered, 239Pu, but 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.
4 A-1
AIRBORNE PATHWAYS Airborne Release Assumptions and Dispersion A normalized plutonium release of 1 pg 239pu is assumed, and an arbitrary 3
average accident exposure coefficient (E/Q) of 1 x 10-3 pg sec/m per pg at the location of the maximum exposed ir4dividual is chosen.
It is assumed that the particle size of the plutonium released is in the respirable range, less than 10 pm in diameter.
Inhalation The committed dose equivalent from radioactive material inhaled during passage of the initial cloud is calculated by:
DCj = Q(E/Q)(DCF)$
(A-1) where DC e committed dose equivalent to organ i (rem) j Qe total quantity of radioactive material released during the accident (pg) accident atmospheric exposure coefficient (pg sec/m3 perpg)
(E/Q) e (DCF)j committed dose equivalent factor for organ i e
3 (rem per pg sec/m )
The committed dose equivalent factors for acute inhalation of 239PU were calculated using the computer code DACRIN (Houston et al. 1975).
This code incorporates the ICRP Task Group Lung Model to calculate the dose to the lungs 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 committed dose equivalents. The translocation classes which minimize the contribution from the inhalation pathway are used.
Cloud deple-tion is not considered. The location of the maximum exposed individual would l
A-2
i i
TABLE A.l.
Fifty-Year Committed Dose Equivalents from l
Inhalation of 1 pm AMAD 239Pu Particles 1
Committed Dose Committed Dose Translocation Equivalent Factors Equivalent (a)
Organ Class (rem per ug sec/m )
(rem) 3 f,
Total 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 t
3 (a)At location where E/Q = 1 x 10-3 pg sec/m per pg.
(b)5.6E-04 is identical to 5.6 x 10 4 l
probably be a few hundred meters from the point of release, and the inclusion of cloud depletion would only lower the doses by a few percent (USNRC Guide 1.111 1977, Gudiksen 1976).
Resuspension is an important aspect to be considered when calculating the dose from inhalation of plutonium.
The airborne concentration from resus-pended material can be predicted using a resuspension factor, k.
The resus-pension factor is defined as the resuspended 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) recommends using a simple time-dependent model to predict the average airborne concentration of a resuspended contami-nant:
h K(t) = 10-4 exp(-0.15t ) + 10-9 (A-2)
I A-3
where resuspension factor (m-1)
K e 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 i
is 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 i
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 l
l that the total S0 years of exposure to resuspended plutonium is received l
during the first year, and the particle size is in the respirable range.
The l
committed dose environment factor remains relatively constant over the first five years. Thus, bringing this term out of the integral does not affect the results. When Equation A-2 is integrated over 50 years, the total exposure to resusperded material is calculated to be 8.9 x 10-3 days / meter.
The committed dose equivalent from inhalation of resuspended material is calculated by:
Td
$ = W(DCF)$(8.64 x 104) f K (t) dt (A-3)
DC o
where surface concentration of radioactive material initially W
- deposited from the cloud onto the ground (pg/m )
2 dose commitment time (days);
T e
d T6 = 1.83 x 104 days (50 years in this study) l A-4
l 50-year committed dose equivalent factor for organ i l
(DCF)$
e 3
(rem per pg sec/m )
constant which converts days to seconds (sec/ day) 8.64 x 104 e The terms K and DC have already been defined.
The initial ground deposition concentration for an accidental release of plutonium is calculated using the following equation:
l l
W=EV (A-4) d where exposure (pg sec/m ), the product of Q and E/Q as defined earlier 3
E
- deposition velocity (m/sec)
V e
d i
A deposition velocity of 1 x 10-3 m/sec was chosen as is used in the i
computer code F000 (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 beforce.
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 comitted dose equivalents. The translocation classes which minimize the contribution from inhalation are used to be censistent with Table A.l.
i l
A-5
I l
TABLE A.2.
Fifty-Year Committed Dose Equivalents from 50 Years' Inhalation of 1 pm AMAD Resuspended 239Pu Particles l
Committed Dose Committed Dose l
Translocation Equivalent Factors Equivalent (a)
Organ Class (rem per pg sec/m )
(rem) 3 Total Body Y
4.6E-04 3.5E-07 l
Lungs 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)At the same location where initial inhalation was calculated.
I Cloud Submersion 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:
j = E (DF)$ S (A-5)
D T
p i
l where sum of the initial exposure from initial cloud passage and E
e T
3 resuspended radioactive material (pg sec/m )
dose factor for cloud submersion for organ i (DF)$
e (rem per pg sec/m3) attenuation factor which accounts for shielding provided by S
e p
residential structures (dimensionless)
The total exposure is calculated by:
Td ET = E + W(8.64 x l@ ) f K(t) dt (A-6) l l
i where all terms have already been defined.
I i
A-6 l
The total exposure to the airborne particulate, E, is calculated to be T
1.8 x 10-3 ug-sec/m. A value of 0.70 is used for the attenuation factor, 3
Sp (USNRC Guide 1.1091977).
Doses for submersion in a semi-infinite cloud of 239pu were calculated using dose factors taken from Soldat (1974) and converted to dose per unit mass. The calculated doses and dose factors are given in Table A.3.
l l
TABLE A.3.
Air Submersion Doses from Exposure to 239pu Dose Factor l
Organ (rem per pg sec/m3)
Dose (rem)
Total Body 9.6E-13 1.2E-15 Skin 1.3E-ll 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 dose rate factor for organ 1 (rem /hr per pg/m )
2 (DF)j e
attenuation factor defined in Equation A-5 (dimensionless)
S e
p time of exposure (hours)
T
- 2 W has been defined previously (pg/m ),
The assumptions are 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 in Table A.4.
A-7 l
.... - =
l TABLE A.4.
Fifty Years of External Exposure to 239Pu Deposited on the Ground Dose Rate Factor
(
Organ (rem / hour per pg/m )
Dose (rem) 2 l
Total Body 4.9E-ll 1.5E-ll Skin 4.8E-10 1.5E-10 Crop Ingestion The internal conunitted dose equivalent received from ingestion of contami-nated vegetation is calculated by Equation A-8.
Up (DCF)j (A-8)
DCj=Cp where consumption rate for vegetation (kg/yr)
U e
p 50-year committed dose equivalent factor for organ i from (DCF)j e
chronic ingestion of 239pu (rem per pg ingested per year) radionuclide concentration in the edible portion of the C
e p
vegetation (pg/kg):
2 l
WV r T" (8.64 x 104) exp(-A*t2I
[T '*PI A s-0.156)ds d
l C
10-4
=
p y
i e
r exp(A t ) - eXP(A t )
+
exp[-A (t2 - t )]
(A-9)
+
i 2
t y
e e
e l
where previously undefined symbols are defined by:
fraction of deposited radionuclide retained by the vegetation r e (dimensionless) j factor for translocation of externally deposited radionuclides T
e r
to the edible parts of the vegetation (dimensionless)
A-8
e 2
vegetation yield (kg/m )
Y e constant which converts days to seconds (sec/ days) 8.64 x 104 e effective decay constant for removal of radionuclides on leaf A
e e
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 C
a the concentration of radioactive mater', initially deposited g
on the vegetation (pg/m ); equals zero if the vegetation was 2
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.
1 The contribution from root uptake of plutonium is negligible compared to the plutonium deposited directly onto the vegetation (less than 1%), and is ignored.
It is assumed that the accident occurred a few 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 deposition on the vegetation occurs during the first year. Therefore, the assumption was made that the total intake occurs dur-ing the first year.
Fifty-year committed dose equivalent factors were used to calculate the resulting committed dose equivalents.
Values for r, Y and A are taken from Regulatory Guide 1.109 as 0.2 for e
l particulates, 2.0 kg/m2 for leafy vegetables and produce, and 0.0495 days-1, 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 Guide 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
.- -=
e TABLE A.S.
Average 239pu Concentration Estimated in Leafy Vegetables and Produce for a Five-Year Period Plutonium Concentration (pg/kg)
Year (a)
Leafy Vegetables Produce 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-ll 5.5E-12 (a) Accident occurred during first year, a few days before the first harvest Fifty-year comitted 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 Ye.srs' 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 (rem)
Total Body 1.2E-03 2.8E-09 Bone 4.5E-02 1.lE-07 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:
1 DC$=
E(CQ)
S U(DCF)$
(A-10) i A-10 1
)
i
where the sumation 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 l
kg forage or feed), or drinking water, Cg (pg per liter of l-water).
Equation A-9 is used to determine values for C.
f l
l Qe animals' consumption rate, Qf (kg feed or forage / day), or Q, I
(1 water / day)
I S e animal product transfer coafficient that relates the daily intake rate of an animal to the radionuclide concentration in milk, Sd (days /t) and beef, Sb (days /kg) human consumption rate for milk, Ud (t/ year), or beef, Ub U e (kg/ year) chronic ingestion committed dose equivalent factor for organ (DCF)$
e i given in Table A.6 (rem /50-year per pg 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 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 1.1091977), 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.
0.70 kg/m r
A-11
It was determined that almost all of the plutnnium deposited on the grain and pasture occurs during the first year.
Regulatory Guide 1.109 uses a value j
of 50 kg/ day for feed or forage consumption for both beef cattle and milk cows.
Values for S f 2.5 x 10-e days /t for milk and for S f 5.0 x 10-3 days /kg d
b l
for beef are reported by Baker (1966).
Values for the human consumption rates J
are taken from Regulatory Guide 1.109 as 310 t of milk / year and 110 kg beef /
year.
l The average plutonium concentrations in the edible portion of the grain and in the fresh forage are presented in Table A.7 for a five-year period.
239 u Concentratior Estimated in TABLE A.7.
Average P
Grain and Forage for a Five fear Period Plutonium Concentration (ug/kg) i Year (a)
Grain Forage 1
4.7E-09 2.7E-08 2
9.5E-ll 1.4E-09 3
2.9E-ll 4.8E-10 4
1.2E-ll 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 equivalents 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 j
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
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 over the lake is assumed to occur at the same rate as over land (USt;RC 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 equation 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-ll) where radionuclide concentration in water (pg/t)
C e
g removal constant for plutonium in the lake (days-1);
A e A = 0.693/1461 aays-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
l 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 a:>imals' -ilk or meat und 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 account for the decreasing commitment 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.
Atg i + exp(-A t ) - exp(-AAt)
(A-12)
(DCF)$ = (2.92 x 10-7) SA (F,c/m)(12) 2 e
where committed dose equivalent factor for organ i (rem per pg (DCF)$
e ingested per year) specific activity of the radionuclide (pCi/pg)
SA e fraction of the ingested radionuclide reaching organ i F
a g
(dimensionless) effective energy of the radionuclide in organ i c e
[(MeV/ dis)(rem / rad)]
mass of organ i (g) m o effective half-life of the radionuclide in organ i (days)
T
- effective decay constant in organ i (days-1); A = in 2/T A
e e
e
~
duration of intake (days) ti e
I A-14
I time over which the dose commitment is calculated, including t2 the duration of intake (days)
(t2 -t)>0 At
- i i
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 calculated using Equation A-10 fc. each j
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 l
of the contributions from animal product ingestion for the airborne pathway I
and the waterborne pathway is also shown in Table A.9.
i l
TABLE A.9.
Fifty-Year Committed Dose Equivalents from 50 Years' Ingestion of Animal Products Contaminated with 239py j
(waterborne pathway and waterborne plus air) i Total Committed Dose l
Committed Dose Equivalents Equivalents (rem) from Airborne i
(rem) from Waterborne Pathway and Waterborne Pathways I
Organ Milk Beef Milk Beef Total Body 5.2E-15 3.lE-10 1.5E-14 1.0E-09 l
Bone 2.0E-13 1.2E-08 5.7E-13 3.8E-08 GI-LLI 2.3E-14 1.4E-09 6.CE-14 4.lE-09
)
Drinking Water Ingestion The committed dose equivalent from consumption of contaminated drinking water is calculated by:
DC4=(U,(DCF)$
(A-13)
A-15
where average radionuclide concentration in water during '.he year of C,
e interest (pg/t); calculated earlier consumption rate (t/ year)
U, e
chronic ingestion comitted dose equivalent factor for organ i (DCF),
e (rem per pg ingested)
A water consumption rate of 730 t/ year is used (USNRC Guide 1.1091977).
Committed dose equivalent factors were calculated using Equation A-12.
The dose calculations were taken out to 28 years, at which time the contribution to the total 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 Dose 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 consurrption of fish, assuming immediate transfer and equilibrium after deposition of the radionuclide onto the lake, is:
DCj = C, B Uf (DCF)$
(A-14) where average radionuclide concentration in the lake during the C,
e year of. interest (pg/t); calculated earlier A-16
. _ =. _
i i
i l
-l equilibrium bicaccumulation factor expressed as the ratio of B e i,
the concentration in fish to the radionuclide concentration in water (t/kg) fish consumption rate (kg/ year)
U a
4 f
same committed dose equivalent factor calculated for the
)
(DCF)$ e j
ingestion of animal products and drinking water. For organ i 4
(rem per pg ingested) j A fish consumption rate of 21 kg/ year is used (USNRC Guide 1.1091977) and the value for the bioaccumulation factor, B, is selected to be 3.5 t/kg j
(Soldat et al. 1974).
The duration of fish consumption is assumed to be j
50 years. However, the contribution from the last 22 years of fish consump-tion is negligible.
j The committed dose equivalents from fish consumption were calculated and i
are given in Table A.ll.
l TABLE A.11.
Fifty-Year Committed Dose Equivalents from 50 Years' Consumption of Fish Contaminated with 239pu
]
Organ Committed Dose Equivalent (rem)
Total Body 3.8E-10 l
Bone 3.2E-08 GI-LLI 3.6E-09 I
J
)
Swimming and Boating 1
j The following equation is used to calculate the dose from swimming:
( A-15) where average radionuclide concentration in the lake during the period I
f e
g of exposure (pg/t); calculated earlier A-17 l
water immersion dose rate factor for organ i (rem /hr per pg/t)
(DF)$
e exposure rate (hours / year)
U e period of exposure (years)
T e The dose rate factors were taken from Soldat et al. (1975) and converted to dose per unit mass.
Equation A-11 was integrated over a 50-year period and divided by 50 years to obtain an average radionuclide concentration of 2.1 x 10-10 pg/t in the lake during the period of exposure.
Using a value of 100 hr/ 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 factor., 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 l
l Skin 1.lE-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 assumed 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.
Fif ty Years of External Exposure to 239Pu from Boating Organ Dose (rem)
Total Body 3.9E-15 Skin 5.8E-14 e
l A-18
4 Shoreline Exposure j
The doses received from exposure to shoreline deposits are calculated by:
D$ = U (DF)$ C T
( A-16) s 1
I.
where exposure rate (hours / year)
U e q
2 dose factor for organ i given in Table 4 (rem / hour per pg/m )
l (DF)$
e average radionuclide surface concentration in the top 2.5 cm C
e s
of shoreline sediments (pg/m )
2 i
period of exposure (years)
T
- l 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 q
that the water concentration is decreasing with time.
Assuming a sediment 1
2 surface density of 40 kg/m (USNRC Guide 1.1091977) and a water-to-sediment transfer coefficient of 7.2 x 10-2 t/kg per hour (USNRC Guide 1.1091977),
l ignoring radiological decay, and using Equation A-ll to predict the water l
concentration, the following equation for the sediment surface concentration is obtained:
i C
=C
+ (1.29 x 10-7) Sg [1 - exp(-At)]/A (A17) s where the surface concentration of radioactive material initially C
e 2
deposited from the cloud onto the sediments (pg/m ); same as W defined in Equation A-4 I
i.
A-19
...,n,.
i l
the extrapolated water concentration at t = 0, 1.86 x 10-9 pg/t, i
1.29 x 10-7 e times the water-to-sediment transfer coefficient, i
{
7.2 x 10-2 t/kg hr, times the sediment surface density, i
40 kg/m, times 24 hr/ day (pg/m2 per day) 2 shore-width factor that describes the geometry of the exposure S,
e (dimensionless) removal constant for plutonium in a lake, defined in A e Equation A-11 (days-1) time since deposition onto the lake surface (days) t e 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-2 ments of 7.3 x 10-5 pg/m, during the period of exposure.
Using an exposure 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 239py Organ Dose (rem)
Total Body 8.9E-ll Skin 8.8E-10 A-20
l l
SUMMARY
OF FIFTY-YEAR COMMITTED DOSE EQUIVALENTS l
FROM ALL MODES OF EXPOSURE l
l.
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 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 contributes 1.6% to the total bone dose. The assumptions used for this expo-sure mode were very conservative, and, in reality, this mode of exposure is not expected to contribute significantly. Therefore, for accidental airborne i
releases of plutonium, only inhalation from initial cloud passage and resus-pension requires consideration.
Resuspension could contribute as much as 39% of the total dose to the total body, lungs, and bone from inhalation, if all plutonium particles released and available 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.
i i
I i
l A-21 l
TABLE A.15.
Fifty-Year Committed Dose Equivalents from an Acute Release of 239Pu to the Atmosphere Fifty-Ye?.r Committed Dose Equivalents (rem) to the Following organs:
Exposure Mode Total Body Skin Lungs Bone GI-LLI Initial Inhalation 5.6E-07 (61) 9.9E-07 (61) 1.2E-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) 1.2E-15 (<0.1 )
Ground Exposure 1.5E-11 (<0.1) 1.5E-10 (15) 1.5E-ll (<0.1) 1.5E-ll (<0.1) 1.5E-ll (<0.1 )
Crop Consumption 2.8E-09 (0.3) 1.lE-07 (0.6) 1.lE-08 (20)
Milk Consumption 1.5E-14 (<0.1) 5.7E-13 (<0.1) 6.0E-14 (<0.1)
Beef Consumption 1.0E-09 (0.1) 3.8E-08 (0.2) 4.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) g 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-11 (<0.1) 8.9E-ll (0.2)
Totals 9.2E-07 (100) 1.0E-09 (100) 1.6E-06 (100) 2.0E-05 (100) 5.6E-08 (100)
(
) - percent contribution of pathway to total organ dose.
l l
l l
i
(
APPENDIX B DOSE FACTORS FOR INHALATION, AND DOSE CALCULATION RESULTS FOR CLASS W PLUT0NIUM I
t D
i l
l i
l l
m
.r..
I APPENDIX B Fifty-Year Committed Dose Equivalent Factors)
TABLE B.l.
from Acute Inhalation for Class W Material (a (rem per pg inhaled)
Isotope Total Body Kidneys Liver Bone Lungs 23ePu 1.2E+3(b) 4.8E+3 1.5E+4 2.4E+4 9.2E+2 239Pu 4.6E+0 1.9E+1 5.9E+1 9.7E+1 3.0E+0 l
240Pu 1.7E+1 6.9E+1 2.2E+2 3.EE+2 1.lE+1 l
241Pu 1.3E+2 6.lE+2 1.8E+3 3.2E+3 1.8E+0 242Pu 2.8E-1
- 1. l E+0 3.6E+0 5.7E+0 1.8E-1 241Am 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 pm AMAD size particles. Organ masses are those reported in ICRP-23.
(b)l.2E+3 is identical to 1.2 x 103 l
TABLE B.2.
Fifty-Year Committed Dose Equivalent Factors from Acute Inhalation for Class Y Material (rem per pg inhaled)
Isotope Total Body Kidneys Liver Bone Lungs 23aPu 4.3E+2 1.8E+3 5.8E+3 8.9E+3 9.0E+3 239pu l.7E+0 7.lE+0 2.3E+1 3.7E+1 3.0E+1 240Pu 6.3E+0 2.6E+1 8.3E+1 1.3E+2 1.lE+2 241Pu 4.3E+1 2.0E+2 6.0E+2 1.lE+3 9.6E+1 242Pu 1.0E-1 4.3E-1 1.4E+0 2.2E+0
'.8E+0 241Am 7.8E+1 5.6E+2 1.2E+3 1.9E+3 1.7E+3 O
B-1
m TABLE B.3.
Fifty-Year Committed Dose Equivalent Factors from One-Year Chronic Inhalation for Class W Material (rem per ug inhaled in first year)
Isotope Total Body Kidneys Liver Bone Lungs 23sPu 1.2E+3 4.8E+3 1.5E+4 2.4E+4 9.2E+2 239Pu 4.5E+0 1.9E+1 5.8E+1 9.7E+1 3.0E+0 240Pu 1.7E+1 6.8E+1 2.2E+2 3.6E+2 1.1E+1 241Pu 1.3E+2 6.lE+2 1.8E+3 3.2E+3 1.8E+0 j
242Pu 2.8E-1 1.lE+0 3.6E+0 5.7E+0 1.8E-1 241Am 2.0E+2 1.5E+3 3.2E+3 5.lE+3 1.7E+2 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 23sPu 4.3E+2 1.8E+3 5.7E+3 8.8E+3 9.0E+3 239Pu 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 241Pu 4.3E+1 2.0E+2 6.0E+2 1.0E+3 9.6E+1 242Pu 1.0E-1 4.3E-1 1.4E+0 2.lE+0 1.8E+0 241Am 7.7E+1 5.6E+2 1.2E+3 1.9E+3 1.7E+3 l
l l
l l
1 B-2
TABLE B.S.
Fifty-Year Committed Dose Equivalents from Inhalation Following Earthquake No. 2 (Class W) t Committed Dose Equivalents for:
1 Organ of Population (person-rem)
Nearest Residence (a) (rem)
Reference Case Ilb) Case II Case III Case IV Case I Case II Case III Case IV Total Body 2.9E+3 1.9E+4 4.0E+3 6.6E+4 4.4E-1 5.2E+0 5.0E-1 5.7E+0 4
Kidneys 1.3E+4 8.7E+4 1.8E+4 3.0E+5 2.0E+0 2.3E+1 2.2E+0 2.6E+1 4
Liver 3.9E+4 2.6E+5 5.4E+4 9.0E+5 6.0E+0
- 7. 0 E+1 6.8E+0 7.8E+1 Bone 6.5E+4 4.3E+5 8.9E+4 1.5E+6 9.8E+0 1.1E+2 1.1 E+1 1.3E+2 Lungs 1.6E+3 1.0E+4 2.2E+3 3.6E+4 2.4E-1 2.8E+0 2.7E-1 3.lE+0 i
(a) Located 4150 meters SW of the plant.
I (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.
1 i
f 1
~
TABLE B.6.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Straight-Line Wind (Class W)
Comitted Dose Equivalents for:
l Organ of Population (person-rem)
Nearest Residence (a) (rem)
Reference Case I Case II Case III Case IV Case I Case II Case III Case IV Total Body 1.5E-1 1.2E+0 1.5E-1 1.lE+1 2.6E-5 2.6E-4 2.6E-5 2.6Eh i
Kidneys 6.8E-1 5.6E+0 6.8E-1 5.1E+1 1.lE-4 1.1E-3 1.lE-4 1.lE-3
{
Liver 2.lE+0 1.7E+1 2.1E+0 1.5E+2 3.5E-4 3.5E-3 3.5E-4 3.5E-3
)
Bone 3.4E+0 2.8E+1 3.4E+0 2.5E+2 5.7E-4 5.7E-3 5.7E-4 5.7E-3 Lungs 8.lE-2 6.7E-1 8.lE-2 6.lE+0 1.4E-5 1.4E-4 1.4E-5 1.4E-4 l
(a) Located 3300 meters SE of the plant.
i
)
l B-3 s
I
TABLE B.7.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Tornado (Class W) f Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (a) (rem)
Reference Case I Case 11 Case III Case IV Case I Case II Case III Case IV Total Body 3.2E+2 3.2E+3 3.2E+2 3.2E+3 6.3E-3 6.3E-2 6.3E-3 6.3E-2 Kidneys 1.4E+3 1.4E+4 1.4E+3 1.4E+4 2.8E-2 2.8E-1 2.8E-2 2.8E-1 Liver 4.3E+3 4.3E+4 4.3E+3 4.3E+4 8.6E-2 8.6E-1 8.6E-2 8.6E-1 Bone 7.0E+3 7.0E+4 7.0E+3 7.0E+4 1.4E-1 1.4E+0 1.4E-1 1.4E+0 Lungs 1.7E+2 1.7E+3 1.7E+2 1.7E+3 3.4E-3 3.4E-2 3.4E-3 3.4E-2 (a) Located 16,000 to 32,000 meters from the plant in the direction the tornado travels.
TABLE B.8.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 190-mph Tornado (Class W)
^ ~ '
Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (a) (rem)
Reference Case I Case II Case III Case IV Case I Case II Case III Case IV Total Body 5.7E+3 5.lE+4 9.4E+3 7.7E+5 9.2E-2 9.2E-1 1.4E-1 1.4E+0 Kidneys 2.5E+4 2.3E+5 4.2E+4 3.5E+6 4.2E-1 4.2E+0 6.4E-1 6.4E+0 Liver 7.7E+4 7.0E+5 1.3E+5 1.0E+7 1.3E+0
- 1. 3 E+1 1.9E+0
- 1. 9 E+1 Bone 1.3E+5 1.lE+6 2.lE+5 1.7E+7 2.lE+0 2.lE+1 3.2E+0 3.2E+1 Lungs 3.lE+3 2.8E+4 5.lE+3 4.2E+5 5.0E-2 5.0E-1 7.7E+2 7.7E-1 (a) Located 16,000 to 32,000 meters from the plant in the direction the tornado travels.
o B-4
r 4
I 1
4 i
TABLE B.9.
Fifty-Year Committed Dose Equivalents from Inhalation l
Following a 250-mph Tornado (Class W) l Committed Dose Equivalents for:
1 '
Organ of Population (person-rem)
Nearest Residence (a) (rem)
Reference Case I Case II Case III Case IV Case I Case II Case III Case IV Total Body 3.6E+3 2.3E+4 4.7E+3 2.lE+5 6.8E-1 6.8E+0 7.5E-1 7.5E+0 Kidneys 1.6E+4 1.0E+5 2.lE+4 9.5E+5 3.lE+0 3.lE+1 3.4E+0 3.4 E+1 Liver 4.8E+4 3.lE+5 6.4E+4 2.9E+6 9.3E+0 9.3E+1 1.0E+1 1.0E+2 Bone 7.9E+4 5.lE+5 1.0E+5 4.7E+6 1.5E+1 1.5E+2 1.7E+1 1.7E+2 i
Lungs 1.9E+3 1.2E+4 2.5E+3 1.1E+5 3.7E-1 3.7E+0 4.0E-1 4.0E+0 (a) Located 32,000 meters to 48,000 meters from the plant in the direction the tornado travels.
I
{
l I
i 4
h 1
I i
l 4
'l t
}
i I
I i
k I
A e
l 4
i
?
l
}
i l
B-5 4
j
- -, - -__, -.~ _-.
APPENDIX C DOSE CALCULATION RESULTS F0il 72 KG/ DAY PLANT THROUGHOUT
i TABLE C.l.
Fifty-Year Committed Dose Equivalents from Inhalation Following Earthquake No. 2 for 72 kg/ day Plant Throughput (Class Y)
Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residencala) (rem)
Reference Case I Case II Casa III Case IV Case I Case II Case III Case IV Total Body 2.0E+3 1.4E+4 2.7E+3 4.5E+4 3.2E-1 3.8E+0 3.5E-1 4.lE+0 Kidneys 8.9E+3 6.2E+4 1.2E+4 2.0E+5 1.5E+0 1.7E+1 1.6E+0 1.8E+1 Liver 2.7E+4 1.9E+5 3.7E+4 6.2E+5 4.5E+0 5.3E+1 4.8E+0 5.6E+1
]
Bone 4.4E+4 3.lE+5 6.0E+4 1.0E+6 7.2E+0 8.5E+1 7.8E+0 9.0E+1 i
Lungs 3.0E+4 2.lE+5 4.2E+4 6.92+5 4.9E+0 5.8E+1 5.4E+0 6.2E+1 (a) Located 4150 meters SW at the plant.
r i
l TACLE C.2.
Fifty-Year Committed Dose Equivalent from Inhalation Following a 150-mph Tornado for 72 kg/ day Plant Throughput (Class Y)
Committed Dose Equivalents for:
Organ of Population (person-rem)
Near:st Residence (a) (rem) i Reference Case ! Case II Case III Case IV Case I Case II Case III Case IV i
Total Body 3.5E-1 3.2E+0 4.4E-1
- 3. 9 E+1 7.3E-5 7.3E-4 9.1E-5 9.lE-4 Kidneys 1.6E+0 1.4E+1 2.0E+0 1.8E+2 3.3E-4 3.3E-3 4.1E-4 4.lE-3 Liver 4.8E+0 4.4E+1 6.0E+0 5.4E+2 1.0E-3 1.0E-2 1.2E-3 1.2E-2 Bone 7.7E+0 7.lE+1 9.7E+0 8.6E+2 1.6E-3 1.6E-2 2.0E-3 2.0E-2 Lungs 5.3E+0 4.9E+1 6.7E+0 5.9E+2 1.lE-3 1.lE-2 1.4E-3 1.4E-2 (a) Located 3300 meters SE of the plant.
I-1 l
C-1
-..-.-- -,.,. -.- -,.,. ~.
i j
TABLE C.3.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 150-mph Tornado for 72 kg/ day Plant Throughput (Class Y) i Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (a) (rem)
Reference Case I Case 11 Case III Case IV Case I Case 11 Case III Case IV Total Body 9.0E+2 9.0E+3 1.lE+3 1.1E+4 1.8E-2 1.8E-1 2.2E-2 2.2E-1 Kidneys 4.0E+3 4.0E+4 5.lE+3 5.lE+4 8.lE-2 8.lE-1 1.0E-1 1.0E+0 Liver 1.2E+4 1.2E+5 1.5E+4 1.5E+5 2.5E-1 2.5E+0 3.lE-1 3.1E+0 Bone 2.0E+4 2.0E+5 2.5E+4 2.5E+5 4.0E-1 4.0E+0 5.0E-1 5.0E+0 Lungs 1.4E+4 1.4E+5 1.7E+4 1.7E+5 2.8E-1 2.8f+0 3.4E-1 3.4E+0 (a) Located 16,000 to 32,000 meters from the plant in the direction the tornado travels.
4 TABLE C.4.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 190-mph Tornado for 72 kg/ day Plant Throughput (Class Y)
Committed Dose Equivalents for:
Organ of Population (person-rem)
Nearest Residence (a) (rem)
Reference Case 1 Case II Case III Case IV Case I Case 11 Case III Case IV Total Body 5.3E+3 4.9E+4 9.3E+3 8.1E+5 8.9E-2 8.9E-1 1.5E-1 1.5E+0 Kidneys 2.4E+4 2.2E+5 4.2E+4 3.7E+6 4.0E-1 4.0E+0 6.8E-1 6.8E+0 Liver 7.3E+4 6.7E+5 1.3E+5 1.1E+7 1.2E+0 1.2E+1 2.lE+0 2.lE+1 j
i Bone 1.2E+5 1.lE+6 2.1E+5 1.8E+7 2.0E+0 2.0E+1 3.4E+0 3.4E+1 Lungs 8.2E+4 7.5E+5 1.4E+5 1.2E+7 1.4E+0 1.4E+1 2.3E+0 2.3E+1 (a) Located 16,000 to 32,000 meters from the plant in the direction the tornado travels.
l l
C-2 c -
r y.
.p_
,,..-.s._-
i i
1 TABLE C.5.
Fifty-Year Committed Dose Equivalents from Inhalation Following a 250-mph Tornado for 72 kg/ day Plant i
Throughput (Class Y) i Committed Dose Equivalents for:
j Organ of Population (person-rem)
Nearest Residencela) (rem) i Reference Case 1 Case 11 Case III Case IV Case I Case 11 Case III Case IV i
]'
Total Body 2.5E+3 1.7E+4 3.2E+3 1.5E+5 5.lE-1 5.lE+0 5.3E-1 5.3E+0 i
Kidneys 1.1E+4 7.4E+4 1.5E+4 6.7E+5 2.3E+0 2.3E+1 2.4E+0 2.4E+1 Liver 3.4 E+4 2.3E+5 4.4E+4 2.0E+6 7.0E+0 7.0E+1 7.3E+0 7.3E+1 i
Bone 5.5E+4 3.7E+5 7.lE+4
- 3. 3 E+ti
- 1. l E+1 1.lE+2 1.2E+1 1.2E+2 l
Lungs 3.8E+4 2.5E+5 4.9E+4 2.3E+6 1.8E+0 7.8E+1 8.2E+0 8.2E+1 4
l J
(a) Located 32,000 to 48,000 meters from the plant in the direction the tornado j
travels.
l 1
4 i
l l
t j
i 1
1 I
i i
f 1
5 i ~
i i
l l
1 l
C-3 i
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