ML20003G541

Environ Consequences of Postulated Pu Releases from GE Vallecitos Nuclear Ctr,Vallecitos,Ca,As Result of Severe Natural Phenomena

ML20003G541
Person / Time
Site:	07000754
Issue date:	11/30/1980
From:	Jamison J, Watson E Battelle Memorial Institute, PACIFIC NORTHWEST NATION
To:
Shared Package
ML20003G540	List: ML20003G539 ML20003G541
References
REF-PROJ-M-3 PNL-3683, UC-41, NUDOCS 8104290789
Download: ML20003G541 (66)

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.

W PNL-1633 UC-41 ENVIRONMENTAL CONSEQUENCES OF POSTULATED PLUTONIUM RELEASES FROM GENERAL ELECTRIC COMPANY VALLECITOS NUCLEAR CENTER, VALLECITOS, CALIFCRNIA, AS A RESULT OF SEVERE NATURAL PHENCMENA J. D. Jamison E. C. Watson November 1980 Prepared for Division of Environmental Impact Studies Argonne National Laboratory under a Related Services Agreement with the U.S. Department of Energy Contract DE-AC06-76RLO 1830 l

Pacific Northwest Laboratory Richland, Washington 99352 l

l B10429 0 %

o

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 General Electric Company Vallecitos Nuclear Center, Vallecitos, California. The severe natural phenomena considered are earthquakes, tornadoes, and nigh straight-line winds. Maximum plutonium deposition values are given for significant locations around the site. All important potential exposure pathways are examined. The most likely 50-year ccmmitted dose equivalents are given in Table 1 for the maximum-exposed individual and the population within a SC< mile radius of the plant. The maximum plutonium deoosition values 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 the earthquakes, and the ISO-mph and 230-mph tornadoes are above the Environmental Protection Agency's (EPA) proposed guideline for plutonium 9

in the general environment of 0.2 uCi/m. The deposition values following the 135-mph tornado are below the EPA proposed guideline.

iii l

TABLE 1.

Most Likely 50-Year Committed Case Equivalents and Maximum Plutonium Ceposition Values Maximum Plutonium Organs of 50-year Coapitted Dose Equivalent (,)

Deposition Offsite Event Reference Population (person = rem)

Nearest Residence (rem)

(yCI/m2)

Lower Bound Upper Bound Lower Bound Upper Bound Release Release Release Release 3

3.5x10'3 0.12 0.21 Earthquake #1 Lungs 7.6 1.2x10 2

Bone 11 1.8x10 5.1x10'3 0.18 3

3 Earthouake #2 Lungs 2.5x10 6.3x10 3.2 8.1 14 3

3 Bone 3.8x10 9.5x10 4.8 12 3

3 Earthquake #3 Lungs 1.4x10 3.7x10 1.6 4.1 6.9 3

3 Some 2.1x10 5.5x10 2.4 6.1 135-mph Tornado Lungs 3.2 8.1x10 5.2x10'#

6.1x10*I 6.8x10 2 2

Bone 12

~ 1.2x10 7.6x10~4 9.0x10-2 3

3 4

180-eph Tornaca lungs 7.1 x10 2.0x10 0.17 0.40 0.7 Bone 1.1x10' 3.0x10' O.26 0.59 230-aph Tornado Lungs 3.6x10 8.0x10' O.55 1.4 2.5 8

4 5

Bone 5.3x10 1.2x10 0.82 2.0 (a) Translocation Class Y has been assumed.

4

+

iv 3

l

U 6-CONTENTS

SUMMARY

iii INTRODUCTION 1-ENVIRONMENTAL EXPOSURE PATHWAYS FOR PLUTONIUM 3

RADIATION DOSE MODELS FOR AN ATMOSPHERIC RELEASE S

RESULTS 11 EARTHQUAKES 11 HIGH WINDS 14 15 TORNAD0ES.

DISCUSSION 19 APPENDIX A - EVALUATION OF ENVIRONMENTAL PATHWAYS BY WHICH PLUTONIUM MAY REACH PEOPLE FROM AN ACCIDENTAL AIRS 0RNE RELEASE A-1

' APPENDIX B - DOSE FACTORS FOR INHALATION, AND DOSE CALCULATION RESULTS FOR CLASS W PLUT0NIUM.

B-1 l

l l

l t

I v

I I

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TABLES 1

Conservative 50-Year Comitted Dose Equivalents and iv Maximum Plutonium Deposition Values 2

1980 Population Distribution Around General Electric,.

2 Vallecitos Nuclear Center 3

Estimated Quantity of Plutonium Released to the 11 Atmosphere Following an Earthquake 4

Isotopic Composition of the Plutonium Mixture 12 5

Fifty-Year Comitted Dose Equivalents from Inhalation.

13 Following Earthquake No. 1 6

Estimated Maximum Plutonium Deposition at Significant.

13 Locations Following Earthquake No. 1 7

Fifty-Year Comitted Dose Equivalents from 14 Inhalation Following Earthquake No. 2 8

Estimated Maximum Plutonium Deposition at 14 Significant Locations Following Earthquake No. 2 9

Fifty-Year Comitted Dose Equivalents from Inhalation.

15 Following Earthquake No. 3 10 Estimated Maximum Plutonium Deposition at Significant.

15 Locations Following Earthquake No. 3 11 Estimated Quantity of Plutonium Released to the 16 Atmosphere Following a Tornado 12 Fifty-Year Comitted Dose Equivalents from Inhalation.

17 Following a 135-mph Tornado 13 Fifty-Year Comitted Dose Equivalents from Inhalation.

18 Following a 180-mph Tornado i

14 Fifty-Year Committed Dose Equivalents from Inhalation.

18 Following a 230-mph Tornado 15 Estimated Maximum Plutonium Deposition at Significant.

18 Locations Following a 135-mph Tornado 16 Estimated Maximum Plutonium Deposition at Significant.

19 Locations Following a 180-mph Tornado vi

0 d

o 17 Estimated Maximum Plutonium Deposition at Significant.

19 Locations Following a 230-moh Tornado A.1 of i um AMAD $f tted Dose Equivalents from Inhalation.

Fifty-Year Com A-3 3

Pu Particles A.2 Fifty-Year Comitted Dose Equivalentg3from 50 Years' A-6 Inhalation of 1 um AMAD Resuspended Pu Particles A.3 Air Submersica Doses from Exposure to 239Pu.

A-7 A.4 Fifty Years of External Exposure to 239Pu Deposited A-8 on the Ground A.5 Average 239Pu Concentration Estimated in Leafy Vegetables A-10 and Produce for a Five-Year Period A.6 Fifty-Year Comitted Dose Equivalents from 50 Years' Ingestion A-10 of Leafy Vegetables and Produce Contaminated with 239Pu Average 239 u Concentration Estimated in Grain and Forage A-12 A.7 P

for a Five-Year Period A.8 Fifty-Year Comitted Dose Equivalents from 50 Years' Ingestion A-12 of Milk and Beef Contaminated with 233Pu A.9 Fifty-Year Comitted Dose Equivalents from 50 Years' Ingestion A-15 of Animal Products Contaminated with 239 u P

A.10 Fifty-Year Comitted Dose Equivalents from 50 Years' A-16 Consumption of Water Contaminated with 239 u P

A.11 Fifty-Year Comitted Dose Equivalents from 50 Years' A-17 Consumption of Fish Contaminated with 239 u P

A.12 Fifty Years of External Exposure to 239Pu from Swiming A-18 A.13 Fifty Years of External Exposure to 239Pu from Boating A-18 239Pu A-20 A.14 Fifty Years of Shoreline Exposure to A.15 Fifty-Year Committed Dose Equivalents from an Acute A-22

[

Release of 239Pu to the Atmosphere B.1 Fifty-Year Comitted Dose Equivalent Factors frem B-1 Acute Inhalation for Class W Material B.2 Fifty-Year Comitted Dose Equivalent Factors from Acute B-1 Inhalation for Class Y Material vii l

B.3 Fif ty-Year Committed Case Equivalent Factors from One-Year B-2 Chronic inhalation for Class W Material B.4 Fif ty-Year Committed Dose Equivalent Factors from One-Year B-2 Chronic Inhalation for Class Y Material B.5 Fifty-Year Committed Dose Equivalents from Inhalation B-2 Following Earthquake No. 1 B.6 Fifty-Year Committed Dose Equivalents from Inhalation B-3 L

Following Earthquake No. 2 B.7 Fifty-Year Committed Dose Equivalents from Inhalation B-3 Following Earthquake No. 3 B.8 Fifty-Year Ccmmitted Dose Equivalents from Inhalation B-3 Following a 155-mph Tornado B.9 Fifty-Year Committed Dose Equivalents from Inhalation B-4 Following a 180-mph Tornado B.10 Fifty-Year Committed Dose Equivalents from Inhalation B-4 Following a 230-mph Tornado a

i I

i t

6 viii

i e

flGURES 1

Accidental Environmental Consequences Evaluation 2

2 Potential Exposure Pathways for Radionuclides in the Biosphere 3

3 Significant Potential Exposure Pathways Through Which People May Be Exposed From an Accidental Release of Plutonium 4

4 Time Dependence of the Environmental Surface Resuspension Factor..

4

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1 1

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ix

v INTRODUCTION This study estimates the potential environmental consequences in terms of radiation dose to pecole 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 utili:ed to estimate dose. The amount and form of plutonium released into the atmosphere was estimated by Mishima et al. (1980). The atmospheric transport and dispersal of released plutonium was estimated by Pepper (1979) 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 distributier. given in Table 2 was used to calculate the population doses.

(a) " Meteorological Evaluations for the Nuclear Facility at Vallecitos."

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 April 21,1978.

(b) " Description of the Site Environment," transmitted by letter from Leland C. Rouse of NRC to General Electric Company, Attn: Mr. G. I.

Cunningham, January 18, 1980.

I t

s l ENVIRON M E NTAL l E NVIR O N ME NTAL l SITE CH AR ACTER'ST!CS l R ELE A S E

DEMOGRAPHY. AND DOSE

- TRANSPORT AND q C O NT AMIN ATIO N OESCRIPTION l lOISPERSAL l LEVELS lUSAGEFACTORS l

QU A NTITY HVOROLOGIC GROUNO SURFACE POPULATION M AX INOlvlOUALS MAX INOlVIOUAL/

OURATION SEVERE WEATHER SURFACE WATER R E SIDE NT/ F AR M POPULATION TIME DEPENDENCE ACC10ENT DIFFUSION FOOOS LAND USE CH AR ACTE RISTICS DIET F ACTORS ISOTOPIC COMPOSITION FIGURE 1.

Accidental Environmental Consequences Evaluation TABLE 2.

1980 Population Distributjog Around General Electric, Vallecitos Nuclear Centersa; Olstance (ml) 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 Direction N

0 O

0 1.090 209 453 1.098 61.755 451 17.276 NNE 3

0 0*

58 525 6.892 253 13.080 7.346 8.019 NE 5

0 0

35 1.035 32.289 650 1.107 112.783 111.352 ENE O

O O

14 68 16 637 21.329 22.664 17.896 E

O O

O O

55 163 728 924 3.131 150.239 ESE O

O O

7 0

25 185 0

1.444 11.781 SE 9

0 0

1 6

15 0

334 0

148

$$E O

O O

5 0

32 714 1.198 18.077 20.905 5

6 0

0 3

19 6 230,621 272.021 4.064 94.130 SSW 4

0 11 28 '

73 5.300 179.889 350,191 23.101 55.545 SW 0

4 10 57 18 50.125 96.197 115.921 1.353 367 WSW 10 0

363 17 15 35.231 76.150 230.521 8.126 0

W 5

57 102 0

51 11.797 57.495 143.530 250.850 0

WW 4

5 27 361 256 131 259.873 318.187 652.945 130.328 NW 7

7 304 331 744 2.858 4.932 276.627 258.349 94.513 NW 0

0 271 3.138 12.037 20.195 23.913 213.652 70.397 108.947 Total 53 73 1.088 5.145 15.112 165.528 941.345 2.020.377 1.435.081 822.596 Total 5,406.399 (a) The population distribution around Vallecitos. California provided by the NRC was based on 1970 census data. Usla9 county growth rate Information from the Statistical Abstracts of the United States and et*ier sources, estimates of the 1980 sector populations were made to give a truer picture of dose consequences.

2

ENVIRONMENTAL EXPOSURE PATHWAYS FOR PLUTONIUM The potential environmental exposure pathways for radionuclides released to the atmosphere and water are shown in Figure 2.

Our experience has shown that the more important pathways for expos 're to atmospheric releases of plu-tonium and daughter products are inhalation, cloud submersion, ingestion, and direct ground irradiation.

For chronlc 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 ce shown that inhalation is the cnly 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 Racionuclides in the Biosphere 3

1 P00R ORGINAL

For liquid releases curing a flood, the important exposure pathways are aquatic food ingestion, water consurrotion, 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.

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i FIGURE 3.

Significant Potential Exposure Pathways Through Which People May l

Be Exposed from an Accidental Release of Plutonium P00RDIGINE 4

.1 RADIATION COSE MODELS FOR AN ATMOSPHERIC RELEASE The equation for calculating comitted radiation dose equivalents from acute inhalation is:

ir

• N (E/Q)(BR)(DCF)ir II)

DC i

where the comitted dose equivalent to organ r from acute inhalation DC e

ir of radionuclide i, rem the quantity of radionuclide i released to the atmosphere, ug 0

4 E/Q

• the accide'1t atmospheric exposure coefficient, ug + sec/m3 per ug released the ventilation rate of the human receptor during the exposure SR

• period,m3/sec (DCF)ir the acute comitted dose equivalent factor, rem per ug inhaled; a numb 3r 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 recomendations (ICRP 1975): 3.3 x 10-4 m3/sec for the period 0-8 hours; 2.3 x 10-4 m3/sec for 8-24 hours; and 2.7 x 10-4 m3/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 comitted 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 comit-ment to the lung and other organs of interest (ICRP 1966). The organ masses used in the code have been modified to re'flect the changes reported in ICRP-23 (1975). The translocation of americium from the blood to the organs of interest has been.nanged to the values suggested in ICRP-19 (1972).

5 t

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 8.2, for each plutonium isotope and 241 Am. The organs of interest in plutonium dosimetry are the tctal body, kidneys, liver, bone, and lungs.

The plutonium postulated to be released to the atmosphere is assumed t0 be in the form of plutonium oxides (Mishima et al.1980). Lung retention, 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).

(2) j = Q (E/Q)Vd W

where 2

the concentration of radionuclide i on the ground surface, ug/m W

e j

the quantity of radionuclide i released to the atmosphere, ug Qg 3

E/Q e the accident atmospheric exposure coefficient, ug sec/m per ug released particle deposition velocity, m/sec V

a d

(a) Activity median aerodynamic diameter 6

q 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 wnich 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). 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 earthquakes and annual average conditions.(a)

Resuspe+,sion 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 Bloont1975, 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 the Nuclear Facility at Vallecitos."

Transmitted by letter from L. G. Hulman of NRC/DSE to R. B. McPherson of BNW/E30, April 21,1978.

7

X(t) = 10-' exp(-0.15 ti) + 10-3 (3) where time since the material was deposited on the ground, days t e resuspension factor at time t = 0, m-1 10-4 e resuspension factor after 20 years, m-1 10-9 e The second term in Ecuation 3, 10-9 m-1, was added based 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 process

( Anspaugh et al.1975). Figure 4 illustrates the time dependence of the resuspension factor.

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E i 10 ai2 5 10'7 5m z

$ 10' a

4 19

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f 10 20 30 40 TIME SINCE DEPOSITION, YEARS FIGURE 4.

Time Dependence of the Environmental Surface Resuspension Factor 8

t 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. flinety-nine percent of the total 50-year exposure from resuspension cccurs in the first 5 years. The chronic 50-year comitted dose equivalent factor for inhalation remains relatively constant over this time period. Therefore, the 50-year comitted 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 comitted dose equivalent from inhalation of resuspended material was calculated by:

7 DCir " Wi K(BR)(DCF)ir (3.16 x 10 )

(4) where the 50-year comitted dose equivalent to organ r from one year DC e

ir of inhalation of radionuclide i, rem /yr of inhalation the concentration of radionuclide i en the ground surface for W

e j

the year of consideration, pg/m2

~

7* 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 chronic comitted dose equivalent factor, rem /ug inhaled (DCF)ir o

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 comitted 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

RESULTS EARTHOUAKES Committed radiation dose equivalents to several organs of the human body were calculated for three earthquake events using the source terms given in Table 3.

TABLE 3.

Estimated Quantity of Plutonium Releas9d to the Atmosphere Following an Earthquaketa)

Earthouake #1 Earthquake #2 Earthquake #3 Time Lower Upper Lower Upper Lower Upper period Bound Bound Bound Bound Bound Bound 0-2 hr 8E-4 3E-2 0.8 2

0.4 1

2-8 hr lE-4 8E-4 2E-3 3E-3 SE-2 2E-2 8-24 hr 4E-4 2E-3 4E-3 8E-3 3E-3 SE-2 1-4 da

?E-3 lE-2 2E-2 4E-2 lE-2 0.2 Total 3.3E-3 4.6E-2 0.83 2.1 0.46 1.3 (a) Taken from Mishima et al. (1980). Only the quantity released in the respirable particle size range (less than 10 um) was used to calculate doses.

Peak ground acceleration levels from 0.4 to 0.8 g were assumed for Earth-quake No. 1, and greater than 0.8 g for Earthquake No. 2.

Peak ground accel-eration of 0.6 g with 1 m displacement due to a thrust fault was assumed for l

Earthquake No. 3.

Significant damage was not postulated for ground acceleration less than 0.4 g (Mishima et al.1980), and no radiation doses were calculated.

t l

The isotopic composition assumed for the plutonium mixture, given in Table 3, is the same as that used by Mishima et al. (1979) in an earlier anal-ysis of earthquake damage consequences.

For the 0-2 hour time period, accident atmospheric dispersion values for a 5% and 50% condition, calculated by the NRC for the Vallecitos Nuclear Center (VNC) site, were used to estimate potential committed dose equivalents to the population and a maximum individual. Annual average atmospheric dispersion and 11 I

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l l

TABLE 4.

Isotopic Composition of the Plutonium Mixture Isotooe Weight Percent (a) 238Pu 0.053 239Pu 87 240Pu 12 24I Pu 1.4 242Pu 0.20 241 (b)

Am 100 (a) All isotope percentages, including the sum, have been rounded to two significant figures.

(b) 241 m was not considered in the release. However, the buildup A241 m from 241Pu in the environment is accounted for, A

of deposition values also calculated by tne NRC were used for all other time periods. For the 5% condition (conservative), the annual average dispersion and deposition values were multiplied by a factor of 4, as recommended by Carson.(a) Four combinatibns of release and dispersion are consider.ed: lower bound release with most likely dispersion; lower bound release with conserva-tive dispersion; upper bound release with most likely dispersion; and upper bound 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 comitted dose equivalents are li:ted in Tables 5, 7. and 9 for Earthquakes No.1, 2, and 3 respectively.

l The corresponding estimated maximum plutonium ground ~ depositions at the site l

boundary, nearest residence, and farm are listed in Tables 6, 8, and 10. All the directions and distances given in-the report are referenced to the 102 Build-ing, which houses the Advanced Fuels Laboratory (AFL), the primary area at the VNC for plutonium processing.

I (a) Letter transmitted from J. E. Carson of ANL/EIS to R. B. McPherson of BNW/ESD, October 24, lo78.

I 12 l

TABLE 5.

Fifty-Year Comiitted Dose Equivalents frcm Inhalation Following Earthquake No. 1 (Class Y)

Co nittet ?ose Ecutvalents fer:

Organ of M;uistien i:erson-re*Hai

%earest aesice*ce dremh i lefeetace Case Iis, Case il Case iii Case Id Case I Case II Case III Case iv Total Body 5.1E-1 2.0E+0 8.2E+0 3.3E+1 2.3E-4 9.CE-4 8.4E-3 3.ZE-2 Kidneys 2.2E+0 3.7E+0 3.5E+1 1.4E+2 9.9E-4'3.8E-3 3.6E-2 1.4E-1 Liver 6.9E+0 2.7E+1 1.1E+2 4.4E+2 3.1E-3 1.2E-2 1.1E-1 4.3E-1 Scne 1.lE+1 4.5E+1 1.!E+2 7.ZI+2 5.1E-3 2.CE-2 1.!E-1 7.1E-1 Langs 7.6E*0 3.CE+1 1.2E+2 4.3E+2 3.!E-3 1.3E-2 1.ZE-1 4.7E-1 (a) Peculatien uttnin a 50-sile racius of the AFL.

(b) tocated 560 4ters WSW of the AFL.

(c) Case ! - le.er bound release witn 9 cst likely dis;ersion; Case II - Icwer bound release with ecnservative dispersion; Case III - uc;er bound release wita mest likely dispersten; Case IV - upper tound release with co.servative dispersien.

TABLE 6.

Estimated Maximum Plutonium Deposition at Significant Locations Folicwing Earthquake No. 1 (all particle sizes)-

2 Pu Decosition (uCi/m )

Location Case I Case 11 Case III Case IV Site Boundary (a) 1.0E-3 4.2E-3 3.7E-2 1.4E-1 Residence (b) 2.6E-4 1.0E-3 8.8E-3 3.4E-2 Farm (c)

-1.9E-3 5.6E-3 7.lE-2 2.lE-1 (a) located 370 meters SE of the AFL.

(b) Located 560 meters WSW of the AFL.

(c) located 240 meters WNW of the AFL.

s 13 L.

TABLE 7.

Fifty-Year Corraitted Dose Equivalents from Inhalation Following Earthquake No. 2 (Class Y)

Committed Dose Equivalents for:

Organ of Moulatten (person-renniai Nearest Resicence (rem W J 2eference Case ILC4 Case Il Case III Case IV Case I Case Il Case III Case IV Total Body 1.7E+2 7.0E+2 4.3E+2 1.7E+3 2.2E-1 8.4E-1 5.5E-1 2.1E+0 Kidneys 7.3E+2 3.CE+3 1.8E+3 7.4E+3 9.3E-1 3.6E+0 2.3E+0 8.9E+0 Liver 2.3E+3 9.4E+3 5.8E+3 2.3E+4 2.9E+0 1.1E+1 7.4E+0 2.SE+1 Bone 2.8E+3 1.5E+4 9.!E+3 3.8E+4 4.8E+0 1.9E+1 1.2E+1 4.6E+1 Lungs 2.5E+3 1.CE+4 6.3E+3 2.EE+4 3.2E+0 1.2E+1 3.1E+0 3.1E+1 (a) Population within a 50-elle radius of the AFL.

~

(b) Located 560 meters WSW of the ML.

(c) Case ! - lower bound release with most likely dispersion; Case II - lower bound release with conservative dispersion; Case I!! - upper bound release with most likely dispersion; Case IV - upper bound release with conservative dispersion.

TABLE 8.

Estimated Maximum Plutonium Deposition at Significant Locations Following Earthquake No. 2 (all particle sizes)

Pu Decosition (uCi/m )

location Case I Case II Case III Case IV Site Boundary (a) 9.8E-1 3.8E+0 2.4E+0 9.4E+0 Residence (b) 2.3E-1 8.7E-1 5.7E-1 2.2E+0 Farm (c) 1.9E+0 5.5E+0 4.7E+0 1.4E+1 (a) Located 370 meters SE of the AFL.

(b) located 560 meters WSW of the AFL.

l (c) Located 240 meters WNW of the AFL.

l i

i l

l 14

TABLE 9.

Fifty-Year Committed Dose Equivalents from Inhalation Follcuing Earthquake No. 3 (Class Y)

Comttted Cose E vivalents for Organ of Peculation < ;erson-remiise Nearest Resicence tremiWJ Refereece Case IF

• Case I ; Case III Case id Case I Case II Case III Case IV Total Sody 9.5E+1 3.3E+2 2.5E+2 1.0E+3 1.1E-1 4.2E-1 '2.8E-1 1.1E+0 Kioneys 4.0E+2 1.6E+3 1.1E+3 4.3E+3 4.7E-1 1.8E+0 1.2E+0 4.5E*0 Liver 1.3E+3 5.1E+3 3.3E+3 1.3E+4 1.5E+0 5.7E+0 3.7E+0 1.4E+1 Bone 2.1E+3 8.4E+3 5.!E+3 2.2E+4 2.4E+0 9.3E+0 6.1E+0 2.3E+1 Lungs 1.4E+3 5.6E+3 3.7E+3 1.5E+4 1.6E.0 6.2E+0 4.1E-0 1.6E+1 (a) Population witnin a 50-mile radius of the AFL.

(b) Located 560 mters WSW of the AFL.

(c) Case ! - lower tound release with most likely diseersion; Case !! - lower bound release with conservative dis:ersion; Case III - u:per cound release with nost likely disperston; Case IV - upper bound release with conservative dispersion.

TABLE 10.

Estimated Maximum Plutonium Deposition at Significant Locations Following Earthquake No. 3 (all particle sizes)

Pu Decosition (uCi/m )

Location Case I Case II Case III Case IV Site Boundary (a) 4.9E-1 1.9E+0 1.2E+0 4.8E+0 Residence (D) 1.lE-1 4.4E-1 2.9E-1 1.1E+0 Farm (c) 9.4E-1 2.8EM 2.4E+0 6.9E+0 (a) Located 370 meters SE of the AFL.

(b) Located 560 meters WSW of the AFL.

(c) Located 240 meters WNW of the AFL.

15

HIGH WINDS Fujita (1977) reported that the probability of a 100-mph straignt wind occurring at the VNC site was approximately the same' as for a 100-mph tornadic wind. Below 100 mph, the probability of a straight-line wind gust is higher than for a tornado of the same speed. Above 100 mph, the probability of tor-nadic winds was judged tn exceed that of a comparable straight wind.

Mishima (1980) reported that no significant radionuclide release was postu-lated for a maximum wind speed of 95 mph. At 135 mph, the lowest wind speed for which a significant release is reported, the probability of a tornado is far greater than that of a straight wind. High straight winds are therefore not considered to be a likely cause of major structural damage at the VNC site and are not discussed further.

TORNADOES Plutonium releases following three tornadoes with maximum total wind speeds of 135 mph,180 mph, and 230 mph were estimated by Mishima (1980). Releases for four time periods are presented in Table 11.

TABLE 11. Estimated Quantity of Plutonium Released to the Atmosphere Following a Tornado Airborne Release of Pu (4) for the Following Maximus Total Wind Speeds:

135 mon 100 mon 230 'ncn Time Period Lower Sound upper Sound Lower Bouno upper Sound Lower Sound upoer Sound 0-2 hr 7.5E-4 5.8E-2 0.32 2

0.86 3.1 2-4 hr lE-4 1E-2 6E.2 0.1, 0.2 0.2 8-24 nr 4E-4 6E-2 0.2 0.3 0.4 0.5 1-4 Days 2E-3 0.3 0.9 2

2 2

Total 3.3E-3 0.43 1.4 4.4 3.5 5.3 (a) Only tne quantity released in the respirable particle si:e range was used to calculate dose.

16

Atmospheric dispersion and deposition values most likely to occur during a tornado were calculated by Pepoer (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 a northeasterly direction. Annual aver-age 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 facter 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 12 through 14 for Clas Y plutonium. The estimated maximum ground con-tamination levels from ' plutonium deposition at the significant locations are listed in Tables 15 through 17.

TABLE 12. Fifty-Year Comitted Dose Equivalents from Inhalation Following a 135-mph Tornado (Class Y)

Consnitted Dose Ecutvaients for:

Organ of Moulation (person-rem) feearest Resteence ( rem)L*

• Refereace Case Ikee Case II Case Ill Case IV Case I Case !! Case III Case IV Total Body 5.5E-1 3.4E+0 5.5E+1 2.4E+2 3.5E-5 3.5E-4 4.1E-3 1.6E-2 Kieneys 2.4E+0 1.4E+1 2.3E+2 1.0E+3 1.!E-4 1.5E 3 1.7E-2 5.9E-2 Liver 7.4E+0 4.6E+1 7.4E+2 3.2E+3

• 4.7E-4 4.7E-3 5.5E-2 2.2E-1 Bone 1.2E+1 7.5E+1 1.2E+3 5.2E+3 7.6E-4 7.6E-3 9.0E-2 3.6E-1 Lungs 8.2E+0 5.0+1 8.1E+2 3.5E+3 5.2E-4 5.2E-3 6.1E-2 2.4E-1 (a) Located 16.000 to 32.000 meters from the plant in the direction the tornado travels for Cases I and !!. Located 560 m Wsw of tne AFL for Cases III and IV.

(b) Case ! - lower bound release most likely release with most likely dispersion; Case II - lower bound release with conservative dispersion; Case III - upper bound release with most Itkely disoersion; Case IV - ucper bound release with conservative dispersion.

l 1

(a) Letter transmitted from D. W. Pepper of SRL/ETO to R. B. McPherson of BMW/ESD, February 21, 1979.

17 i

TABLE 13.

Fifty-Year Committed Dose Equivalent from Inhalation Following a 180-mph Tornado (Class Y)

Corsnitted Cose E::uivalents for:

Organ of Peculation (person-rem Neares: aesicence frem)Lai Reference Case I Case II Case ill Case IV Case i Case II Case III Case IV Total Body 4.8E+2 3.9E+3 1.4E+3 1.2E+4 1.2E-2 8.1E-2 2.7E-2 2.5E-1 Kicnsys 2.0E+3 1.5E+4 5.8E+3 4.9E+4 5.0E-2 3.4E-1 1.1E-1 1.1E+0 Liver 6.4E+3 5.2E+4 1.8E+4 1.SE+5 1.6E-1 1.1E+0 3.6E-1 3.4E+0 Bone 1.1E+4 8.5E+4 3.0E+4 2.5E+5 2.6E-1 1.8E+0 5.9E 1 5.6E+0 Lungs 7.lE+3 5.7E-4 2.0E+4 1.7E+5 1.7E-1 1.2E4 4.CE-1 3.8E* o (a) Located 16.000 to 32,000 meters from the AFL in the direction the tornado travels for Cases II and IV; located 560 m WSW of the AFL for Cases I and TABLE 14.

Fifty-Year Committed Dose Equivalents from Inhalation Following a 230-mph Tornado (Class Y)

Coneitted Dose Eoutvalents for:

Organ of Fooulation (person-rem)

• earest aesicence irem ga#

Ueference Case I Case II Case III Case IV Case I Case II Case III Case IV Total Body 2.4E+3 2.2E+4 5.4E+3 5.2E+4 3.7E-2 3.7E-1 9.1E-2 9.1E-1 Kicneys 1.0E+4 9.4E+4 2.3E+4 2.2E+5 1.6E-1 1.6E+0 3.9E-1 3.9E+0 Liver-3.3E+4 3.0E+5 7.3E+4 5.9E+5 5.0E-1 5.CE+0 1.2E+0 1.2E+0 Sone 5.3E+4 4.9E+5 1.2E+5 1.1E+6 8.2E-1 8.2E+0 2.0E+0 2.CE+1 Lungs 3.6E+4 3.3E+5 8.CE+4 7.7E+5 5.5E 1 5.5E+0 1.4E+0 1.4E+1 (a) Located between 32,000 meters and 48,000 meters from the plant in the direction the tornado travels.

TABLE 15.

Estimated Maximum Plutonium Deposition at Significant Locations Following a 135-mph Tornado (all particle sizes)

Pu 0;oosition (t.Ct /m2) location Case I Case II Case III Case IV site Boundary *I 1.1E-4 4.2E-4 1.6E-2 5.2E 2 I

Residence (b) 9.7E-5 9.7E-4 1.4E-3 2.7E-2 IDI Fa nn 9.7E-5 9.7E-4 1.4E-3 6.2E-2 (a) located 370 m SE of the plant.

(b) Located 16,000 to 32,000 meters from tne plant in the direction the tornado travels for cases I, !!, and !!I.

For case IV the residence is located 560 m WSW of the AFL and the farm is located 240 m WNW.

18

--~' TABLE 16. Estimated Maxi um Plutonium Decosition at Significant Locations Following a 180-mch Tornado (all particle sizes)

Pu Decosition NCi/m2) location Case I Case II Case III Case IV Site Boundary (a) 4.6E-2 1.8E-1 1.0E-1 4.0E-1 U)

~

Residence 2.2E 2.2E-1 7.0E-2 7.0E-1 Farm (c) 4.8E-2 2.2E-1 1.lE-1 7.0E-1 (a) Located 370 SE of the AFL.

(b) Located 32,000 to 48,000 meters from the AFL in the-direction the tornado travels.

(c) Located 240 m Wf4W of the AFL for cases I and III; for Cases II and IV, it is located 32,000 to 48,000 m from the AFL in the direction the tornado travels.

TABLE 17.

Estimated Maximum Plutonium Deposition at Significant Locations Following a 230-eph Tornado (all particle sizes)

Pu Decositien (uCf/m2) location Case I Case II Case III Case IV Site Soundar (a) 1.lE-1 4.3E-1 1.2E-1 4.5E Residence (b)y 1.0E-l 1.0E+0 2.5E-1 2.5EH)

Fam(c) 1.2E-l 1.0E+0 2.5E-1 2.5E+0 (a) Located 370 meters SE of the AFL.

(b) Located 32,000 to 48,000 meters from the AFL in the direction the tornado travels.

(c) Located 240 m WriW of the AFL for Case I; for Cases II, III and IV, it is located 32,000 to 48,000 meters from the AFL in the direction the tornado travels.

19

DISCUSSION For the tornado, the majority of the radienuclide intake occurs after the first two hours. At this time annual meteorology is assumed to resume.

The calculated comitted 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 their use. Present insights into the degree of uncertainty involved are very limited and qualitative (Hoffman 1978). Oose 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 estimated average annual whole-body radiation dose from natural back-ground radiation in California is reported to be 115 mrem /yr (Klenunt 1972).

Therefore, an individual receives a total-body dose of about 5.8 rem from exposure to rfatural 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 Vallecitos 7

Nuclear Center is 3.1x10 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 6

equivalent of 5.4x10 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 occupational accident 239 and received a maximum permissible bone burden of Pu, the 50-year com-l mitted dose equivalent to the bone would be greater than 1000 rem. As can be seen, in all cases, the calculated 50-year comitted dose equivalents to the population for the severe natural ohenomena scenarios considered in this report are lower than the collective dose equivalent from 50 years of exposure to natural background radiation and medical x-rays.

20 l

Existing guidelines on acceptable levels of soil contamination fecm Pu 2

can be found to range frem 0.01 uCi/m to 270 uCi/m (Selby et al. 1975; EPA 1977; Martin and Bloom 1975; Healy 1977; U.S. Code 1975; Healy 1974; Guthrie and Nichols 1964; Hazie and Crist 1975; Kathren 1968; Dunster 1962).

2 The EPA has proposed a guideline of 0.2 uCi/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 uCi/m,

The predicted maximum residual plutonium contamination levels on the ground following the earthquakes, the 180-mph and 230-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 2

from about 0.2 to 14 pCi/m. The predicted ground contamination levels for the 135-mph tornado are well below the EPA proposed guideline at all signifi-cant locations.

l l

l 21 l

l

APPENDIX A EVALUATION OF ENVIRONMENTAL PATHWAYS BY WHICH PLUT0NIUM MAY REACH PEOPLE FROM AN ACCIDENTAL AIRBORNE RELEASE

APPENDIX A EVALUATION OF ENVIRONMENTAL PATHWAYS SY WHICH PLUTONIUM MAY REACH PEOPLE FRCM AN ACCIDENTAL AIRBONRE RELEASE Twelve environmental exposure modes for an accidental airborne release are considered for evaluation. Three are from exposure to the radioactive cloud, and four result from radioactive material deposited on the ground. The remaining five are via.the waterborne pathway, assuming radioactive material was depos:ted cnto 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 cicud submersion, 4.

direct exposure to radioactive material deposited on tre 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, 23?Pu, 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 i

j 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.

l r

A-1 l

w m

my 7

-y y

g-

+-.m p--

'm

AIRS 0RNE PATWAYS Airborne Release Assumptions and Discersion A normalized plutonium release of 1 ug 239Pu is assumed, and an arbitrary average accident exposure coefficient (E/Q) of 1 x 10-3 ug sec/m per ug 3

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 um in ciameter.

Inhalation The committed dose equivalent from radioactive material inhaled during passage of the initial cloud is calculated by:

DC$ = Q(E/Q)(DCF)$

(A-1) where DC e comitted dose equivalent to organ i (rem) total quantity of ra'dioactive material released during the Q

• accident (pg) accident atmospheric exposure coefficient (ug sec/m3 perug)

(E/Q)

(DCF)$

comitted dose equivalent factor for organ i e

(rem per pg sec/m3)

The comitted dose equivalent factors for acute inhalation of 239Pu were calculated using the computer code DACRIN (Houston et al. 1975). This code l

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 l

changes reported in ICRP-23 (1975). The 50-year comitted dose equivalent factors per unit mass exposure for 239pu Darticles, with an activity median i

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 contribution from the inhalation pathway are used. Cloud deple-I tion is not considered. The location of the naximum exposed individual would t

A-2 i

TABLE A.l.

Fifty-Year Comitted Case Equivalents from Inhalation of 1 um AMAD 219Pu Particles Comitted Dose Comitted C9sp Translocation Equivalent Factors Equivalenttaj 3

Organ Class (rem per ua sec/m )

(rem)

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 (a)At locution where E/Q = 1 x 10-3 ug sec/m3 per ug.

(b)5.6E-04 is identical to 5.6 x 10-4 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, Gudiksen1976).

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-i pension factor is defined as the resuspended air concentration divided by the l

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 model to predict the average airborne concentration of a resuspended contami-nant:

K(t) = 10-4 exp(-0.15t'5) + 10-9 (A-2)

A-3 I

1-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 raeasurable decrease in the resuspension process after 17 years, which 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 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 exposure to resuspended plutonium is received curing the first year, and the particle size is in the respirable range. The comitted 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 resuspended material is calculated to be 8.9 x 10-3 days / meter.

The comitted dose equivalent from inhalation of resuspended material is calculated by:

Td OCj = W(DCF)$(8.64 x 10") f K (t) dt (A-3) where I

surface concentration of radioactive material initially W e 2

deposited from the cloud onto the ground (ug/m )

d se comitment time (days);

T e

d T = 1.83 x 104 days (50 years in this study) d A-4

~

(DCF)$

50-year comitted dose equivalent factor for organ i e

(rem per pg sec/m31 8.54 x 10' e constant which converts days to seconds (sec/ day)

The terms K and DC have already been defined.

j The initial ground deposition concentration for an accidental release of plutonium is calculated using the following equation:

W=EV (A-4) d where 3

exposure (ug sec/m ), the product of Q and E/Q as defined earlier E

• deposition velocity (m/sec)

V e

d A deposition velocity of 1 x 10-3 m/sec was chosen as is used in the computer code FOOD (Baker 1977).

Chronic-::or:vnitted dose equivalent factors were cal.culated 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 boay, lungs, bone, and GI-LLI, along with the calcu-lated comitted dose equivalents. The translocation classes which minimize the contribution from irhalatfon are used to be consistent with Table A.l.

A-5

a TABLE A.2.

Fifty-Year Cer=itted Dose Ecuivaients from 50 Years' Inhalation of 1 ; AP.A0 Resuspended 233?u Particles Cem.itted Dose C0=nitted 09sa Trans1ccation Equivalent Factors Equivalentt3I Crean Class (rem ser uc sec/m3)

(rem)

Total Body Y

4.6E-04 3.5E-07 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 k

(a)At the same location where initial inhalation was calculated.

Cicud Submersion A semi-infinite cloud model is used for calculating the exter1al doses from cicud submersion during cloud passage. The doses are calculated with the follcwing etuation:

g = E (DF)g S (A-5)

O T

p where sum of the initial exposure from initial cloud passage and E

T resuspended radioactive material (ug sec/m3)

(DF)g dose factor for cloud subcersion for organ i e

3 (rem per ug sec/m )

attenuation factor which accounts for shielding provided by 5

7 residential structures (dimensionless)

The total exposure is calculated by:

d E7 = E + W(8.64 x 10") f K(t) dt (A-6) where all terms have already been defined.

A-6

The total exposure to the airborne particulate, E, is calculated to be 7

1.8 x 10-3 pg-sec/m. A value of 0.70 is used for the attenuation factor, 3

SF (USNRC Guide 1.109.1977).

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.

TABLE A.3.

Air Submersion Coses from Exposure to 233Pu Dose Factor Orcan (rem per ua sec/m3)

Dose frem)

Total Body 9.6E-13 1.2E-15 Skin 1.3E-11 1.6E-14 Ground Excosure Dose from external exposure to radioactive material deposited on the ground is calculated by:

Dj = W(DF)g S T (A-7) p where 2

dose rate factor for organ 1 (rem /hr per ug/m )

(DF)4 e

attenuation factor defir.ed in Equation A-5 (dimensionless)

S e

p time of exposure (hours)

T e 2

W has been deffr,ed previously (ug/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 1.109 1977).

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

TABLE A.4.

Fif ty Years of External. Exposure to 233Pu Deposited on the Ground Dose Rate Factor Organ (rem / hour oer uq/m2)

Dose (rem)

Total Body 4.9E-ll 1.5E-11 Skin 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.

DC9=Cp p (DCF)4 (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 239Pu (rem per ug ingested per year)

C e radionuclid concentration in the edible portion of th'e p

vegetation (pg/kg):

T2 WV r T" (8.64 x 104) exp(-A*t2I

[T '*P( A s-0.15/s)ds d

10-4 Cp=

y i

e 0

" exp[-A,(t2 - t )]

(A-9) exp(A,t)-exp(A,t)

+

+

i 2

i 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

o r

to the edible parts of the vegetation (dimensionless)

A-8

2 vegetation yield (kg/m )

Y e 8.64 x 10" e constant which converts days to seconds (sec/ days) effective decay constant for removal of radionuclides on leaf A

o e

or produce surfaces by weathering and radiological decay (days-1) t1 time from the accident to the appearance of the vegetation (days) e t2 time from the accident to harvest of the vegetation (days) e the concentration of radioactive material initially deposited C

e g

on the vegetation (pg/m2); 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 plutoniu,m 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 deposited en 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 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

TABLE A.5.

Average 23sPu Concentrution Estimated in Leafy Vegetables and Pr duce for a Five-Year Period Plutonium Concentration (uc/ka) a)

Year 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-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 23sPu 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 cormitted dose equivalents were calculated ard are included in Table A.6.

TABLE A.6.

Fifty-Year Committed Cose Equivalents from 50 Years' Ingestion of Leafy Vegetables and Produce Contaminated with 23sPu Committed Dose Equivalent Factor (rem /50-year per Connitted Dose Organ ug ingested eer year)

Ecuivalent (rem)

Total Body 1.2E-03 2.8E-09 Bone 4.5E-02 1.lE-07 GI-LLI 4.6E-03

1. l E-08 Incestion of Milk and Beef 1

The internal committed dose equivalents from the ingestion of animal products (milk and beef) are calculated by:

4=(}[(CO)' S U(DCF)$

( A-10)

DC A-10 m

w

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

• radionuclide concentration in the animal's food, Cf(ugper kg forage or feed), or drinking water, C, (;g per liter of water). Equation A-9 is used to determine values for C.

f animals' consumption rate, Qf (kg feed or forage / day), or Q, Q

e (1 water / day) animal prcduct 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) human consumption rate for milk, Ud (1/ 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 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 s,ection.

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 I

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 l

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 C;ide 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 0.70 kg/m2 (USNRC Guide 1.1091977) were used for T and Y, respectively.

r A-ll i

It was determined that almost all of the plutonium deposited on the grain and pasture occurs during the first year. Regulatory 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-e days /1 for milk and for S of 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 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-11 1.4E-09 3

2.9E-11 4.8E-10 4

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, comitted dosa equivalents were calculated for the consumption of contaminated animal products and are presented in Table A.8.

l l

TABLE A.8.

Fifty-Year Comitted Dose Equivalents from 50 Years' Ingestion of Milk and Beef Contaminated with 23sPu 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 l

WATERBORNE PATHWAYS To account for the contribution from radionuclides deposited onto a nearby surface body of water, a small lake one meter dcap is assumed. Deposition over the lake 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 witn a dynamic scurce 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 exoonential expression. The initial water concentration can be determined by extrapolating the curve back to time z'ero, which yields Equation A-11.

C,= 1.86 x 10-3 exp (-At)

(A-ll) where radionuclide concentration in water (1.:g/2)

C, e

removal constant for plutonium in the lake (days-1);

A

• A = 0.693/1461 days-1 time since depositicn onto the lake surface (days) t

• extrapolated water concentration ct t = 0 (pg/2) 1.86 x 10-9

• Equation A-ll is much simpler than the complex solution obtained by solving the differential equation, and it only overestimates the water A-13

concentration by a few percent over the 50-year period considered. Ecuation 11 was integrated to estimate the average radionuclide concentration in the water for eacn year.

Incestion of Aninal 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 comitted dose eouivalent factors must be calculated to account for the decreasing comitment time as the exposure time approaches the end of the 50-year exposure period. Comitted dose equivalent factors for chronic ingestion of radionuclides are calculated with Equation A-12.

e t + eXP(-A t ) - exp(-At.t)}

(A-12)

(CCF), = (2.92 x 10-7) SA (F, c/m)(T2) rt e2 where comitted dose equivalent factor for organ i (rem per.ug (DCF)$

e ingested per year) specific activity of the radionuclide (pCi/ug)

SA

• fraction of the ingested radionuclide reaching organ i F,

e (dimensionless) effective energy of the radionuclide in organ i c *

[(PeV/ dis)(rem / rad)]

mass of organ i (g) m o effective half-life of the radionuclide in organ 1 (days)

T

• A, effective decay constant in organ i (days-1); A, = in 2/r e

duration of intake (days) tt e

A-14

time over wnich the dose comitment is calculated, including t2 the duration of intake (days) 2-t)>0 (t

?.t e i

One-through 50-year ingestion comitted dose equivalent factors were -

calculated for 23sPu using parameter values found in ICRP-2 (1959)

ICRP-23 (1975), and ICRP-19 (1972). The comitted dose equivalent factor to the GI-LLI from ingestion does not change.

Comitted dose equivalents were calculated using Equation A-10 for each year during the 50-year exposure period, using average yearly water concentra-tions and the appropriate dose comitment 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 comitted 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 Comitted Cose Equivalents from 50 Years' Ingestion of Animal Products Contaminated with 239Pu (waterborne pathway and waterborne plus air)

Total Comitted Dose Comitted Dose Equivalents Equivalents (rem) from Airborne (rem) from Waterborne Pathway and Waterborne Pathways Organ Milk Beef tiilk Beef Total Body 5.2E-15 3.1E-10 1.5E-14 1.0E-09 Bone 2.0E-13 1.?E-08 5.7E-13 3.8E-08 GI-LLI 2.3E-14 1.4C-0S 6.0E-14 4.lE-09 Drinkina Water Ingestion The comitted dose equivalent from consumption of contaminated drinking water is calculated by:

DC$=(Ug (CCF)9

( A-13)

A-15 l

m -

where C

• average radionuclide concentration in water during the year of interest (ag/t); calculated earlier consumption rate (1/ year)

U, e

(DCF),

chronic ingestion committed dose equivalent factor for organ i e

(rem per ug ingested)

A water consumption rate of 730 t/ year is used (USNRC Guide 1.109 1977).

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 Orcan Committed Dose Ecuivalent (rem)

Total Body B.3E-09 Bone 3.2E-07 GI-LLI 3.6E-08 Fish Ingestion The eg.ation used to estimate the dose from consumption of fish, assuming immediate transfer and equilibrium after deposition of the radionuclide onto the lake, is:

DCg = C',B Uf(DCF)g (A-14) where C

e average radionuclide concentration in the lake during the year of interest (ug/1); calculated earlier A-16

B e equilibrium bicaccumulatten factor excressed as the ratio of the concentratien in fish to the radionuclide concentration in water (t/kg) fish consumption rate (kg/ year)

U e

f (DCF) same comitted dose equivalent factor calculated for the e

ingestion of animal products and drinking water, for organ i (rem per ug ingested)

A fish consumption rate of 21 kg/ year is used (USNRC Guide 1.109 1977) and the value for the bioaccumulation factor, B, is selected to be 3.51/kg (Soldat et al. 1974). The duration of fish censumption is assumed to be 50 years. However, the contribution from the last 22 years of fish consump-tion is negligible.

i The comitted dose equivalents from fish consumpt nn were calculated and are given in Table A.11.

TABLE A.ll.

Fifty-Year Comitted Dose Equivalents from 50 Years' Consumption of Fish Contaminated with 23sPu Organ Comitted Dose Ecuivalent (rem)

Total Body 3.8E-10 Bone 3.2E-08 GI-LLI 3.6E-09 Swimina and Boating The following equation is used to calculate the dose from swimming:

Dj = f,(DF), U T (A-15) where C, e average radionuclide concentration in the lake during tne period of exposure (ug/t); calculated earlier A-17

(DF)j water immersion dose rate factor for organ i (rem /hr per ug/2) e exposure rate (hours / year)

U e period of exposure (years)

T

• The dose rate factors were taken from Soldat et al. (1975) and converted to dose per unit mass. Equation A-ll 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/1. 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.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 l

Table A.13.

TABLE A.13.

Fifty Years of External Exposure to 239pu from Boating Organ Dose (rem) l Total Body 3.9E-15 Skin 5.8E-14 i

A-18 i

o 4>

Shoreline Excesure The doses received from exposure to shoreline deposits are calculated by:

Dj = U (DF)$ ET (A-16) s where exposure rate (hours / year)

U e 2

dose factor for organ i given in Table 4 (rem / hour per ug/m )

(DF),

e f

average radionuclide surface concentration in the top 2.5 cm e

3 of shoreline sediments (ug/m2) period of exposure (years)

T e A differential equation was set up to represent the buildup of radio-nuclice 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 k 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 1.1091977) and a water-to-sediment transfer coefficient of 7.2 x 10-2 1/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:

O + (1.29 x 10-7) 5, [1 - exp(-At)]/A (A-17)

C

=C s

where 0

the surface concentration of radioactive material initially C

e deposited from the cloud onto the sediments (ug/m2); same as W defined in Equation A-4 A-19 e

-,=,~n,,,,

o.

1.29 x 10-7 the extracolated water concentration at t = 0, 1.86 x 10-9 ug/t, e

times the water-to-sediment transfer coefficient, 7.2 x 10-2 1/kg hr, times the sediment surface density, 40 kg/m2, times 24 hr/ day (pg/m per day) 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-ll (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). Ecuation 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 ug/m2, 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 239Pu Organ Dose (rem)

Total Body 8.9E-11 Skin 8.8E-10 1

i i

i A-20 i

A

SUMMARY

OF FIFTY-YEAR CCMitITTED COSE EOUIVALENTS FRCM ALL MCDES OF EXPOSURE A summary of the 50-year committed <!:se equivalents frcm all modes of exposure is given in Table A.15..The inhalation exposure mode contributes greater than 93% of the total dose to tnc 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 airoorne releases of plutonium, only inhalation from initial cloud pas.eage 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 lu,ngs and bone dose, and can be ignored. Although 23sPu was the only isotope considered, these conclusions apply to most isotopes of plutonium and a typical mixture of plutonium isotopes.

i l

}

A-21

)

1 TABLE A.15.

Fif ty-Year Committed Dose Equivalents from an Acute Release of 239Pu to the Atmosphere Fifty-Year Committed Dose Equivalents (rem) to the Following Organs:

___ Total Body Skin Lungs Bone GI-LLI Exposure Mode i

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-Il (<0.1) 1.5E-10 (15) 1.5E-11 (<0.1) 1.5E-11 (<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) i 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) l

[g Swimmin9 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)

Boatin9 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-11 (<0.1) 8.8E-10 (85) 8.9E-ll (<0.1[ 8.9E-ll (<0.1) 8.9E-11 (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.

I:

APPENDIX B DOSE FACTORS FOR INHALATION, AND DOSE CALCULATION RESULTS FOR CLASS W PLUT0NIUM l

T I

i I

I

APPENDIX B TABLE B.l.

Fifty-Year Cemitted Dose Equivalent Factors) from Acute Inhalation for Class W Materialta l

(rem per uq inhaled)

Isotope Total Body Kidneys Liver Bone Lungs 238 ID)

Pu 1.2E+3 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 240Pu 1.7E+1 6.9E+1 2.2E+2 3.6E+2 1.1 E+1 241 Pu 1.3E+2 6.lE+2 1.8E+3 3.2E+3 1.8E+0 242Pu 2.8E-1 1.lE+0 3.6E+0 5.7E+0 1.8E-1 241 Am 2.0Ev2 1.5E+3 3.2E+3 5.2E+3 1.7E+2 (a) Comitted dose equivalent factors calculated using DACRIN for 1 cm 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 (rem oer ug inhaled)

Isotope Total Body Kidneys Liver Bone Lungs 238Pu 4.3E+2 1.8E+3 5.8E+3 8.9E+3 9.0E+3 239Pu 1.7E+0 7.lE+0 2.3E+1 3.7E+1 3.0E+1 240 Pu 6.3E+0 2.6E+1 8.3E+1 1.3E+2 1.lE+2 241 Pu 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 1.8E+0 241 Am 7.8E+1 5.6E+2 1.2E+3 1.9E+3 1.7E+3 B-1

a i

F TABLE B.3.

Fifty-Year Comitted Dose Equivalent Factors from One-Year Chronic Inhalation for Class W Material (rem oer ug inhaled in first year)

Isotooe Total Body Kidneys-Liver Bone Lungs 238Pu 1.2E+3 4.8E+3 1.5E+4 2.4E+4

9..' E+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.lE+1 241 Pu 1.3E+2 6.1E+2 1.8E+3 3.2E+3 1.8E+0 242Pu 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 5.1E+3 1.7E+2 TABLE B.4.

Fifty-Year Comitted Dose Equivalent Factors from One-Year Chronic Inhalation for Class Y Material (rem oer ug inhaled in first year)

Isotope Total Body Kicneys Liver Bone Lungs 238Pu 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 1.1E+2 241 Pu 4.3E+1 2.0E+2 6.0E+2 1.0E+3 9.6E+1 5

242Pu 1.0E 1 4.3E-1 1.4E+0 2.1E+0 1.8E+0 241 Am 7.7E+1 5.6E+2 1.2E+3 1.9E+3 1.7E+3 TABLE B.S.

Fifty-Year Comitted Dose Equivalents from Inhalation Following Earthquake No.1 (Class W)

Committed Dose Equivaleats for:

Organ of Population ' person-rem)

Nearest liesioencet=J tree)

Reference case 1L83 case I ; case III case IV W case 11 case III cigg_L Total Body 1.4E+0 5.6t+0 2.3E+1 9.1E+1 6.5E-4 2.5E 3 2.3E-2 8.9E-2 i

Kidneys 6.0E+0 2.4E+1 9.5E+1 3.8E+2 2.7E 3 1.0E-2 9.8E-2 3.7E-1 Liver 1.9E+1 7.4E+1 3.0E+2 1.2E+3 8.5E-3 3.3E-2 3.0E-1 1.2E+0 Sone 3.1E+1 1.2E+2 4.9E+2 2.0E+3 1.4E-2 5.4E-2 5.1E-1 1.9E+0 Lungs 7.5E-5 3.0E+0 1.2E+1 4.8E+1 3.4E-4 1.3E 3 1.2E-2 4.7E-2 (a) Located 560 m W5W of the AFL.

(b) Case ! - lower bound release with most likely dispersion; C.se !! - lower bound release with conservative dispersion; Case I!! - upper bound release with most likely dispersion; Case IV - upper bound release with conser'ative dispersion.

3 8-2

~,-,a,n,

-,n-

-,-.. -=.,+,---,,,,,,

n TABLE B.6.

Fif ty-Year Comitted Case Equivalents from Innalation Following Earthauake No. 2 (Class W)

Coreitted Cose EtJ1 vale *ts fer-Cr;an of aruisttea :ersea-r+=)

seerest iesieencei (re*)

Refeceace Case i U s e i_i Case III Case is Case I Case II Case !il Gase Id Total tody 4.SE+2 1.9E+3 1.2E+3 4.8E+3 6.1E-1 2.3E+0 1.!E+0 5.8E+0 Eteneys 2.CE+3 8.2E+3 5.0E+3 2.CE+4 2.6E+0 9.8E+0 6.4E+0 2.5E+1 Liver 6.3E+3 2.5E*4 1.6E+4 6.3E+4 8.CE+0 3.1E+1 2.CE+1 7.6E+1 gone 1.CE+4 4.2E+4 2.6E+4 1.1E+5 1.3E+1 5.1E+1 3.3E+1 1.3E+2 Lungs 2.5E+2 1.0E+3 6.3E+2 2.!E+3 3.2E-1 1.21-0 8.0E-1 3.1E+3 (a) Located $60 m W5W of the AFL.

TABLE B.7.

Fifty-Year Comitted Dose Equivalents from Inhalation Following Earthquake No. 3 (Class W)

Cosunitted Dose Eovivalents for Organ of Popviation ( ersea-rem)

%earest aestcence**d free)

Reference Case I Case II Case !!I Case Is Case I Case II Case III Case !d Total Body 2.6E+2 1.1E+3 6.9t+2 2.EE+3 3.1E-1 1.2E+0 7.7E 1 2.9E+0 tieneys 1.1E+r 4.5E+3 2.9E+3 1.2E+4 1.3E+0 4.9E*0 3.21*0 1.2E+1 Liver 3.4E+3 1.4E+4 9.1E+3 3.7E+4 4.0E+0 1.5E+1 1.0E+1 3.9E+1 Bone 3.7E*3 2.3E+4 1.5E*4 6.1E+4 6.7E-0 2.6E+1 1.7t+1 6.4E+1 Lungs 1.4E+2 5.6E+2 3.6E+2 1.!E+3 1.6E-.

6.2E 1 4.1E-1 1.5E+0 (a) located 560 s 's'5W of the AFL.

TABLE B.8.

Fifty-Year Committed Dose Equivalents from Inhalation Following a 135-mph Tornado (Class W)

Cosunttted Dose toutvatents for Organ of Populatten icerson-rem)

• iesrest ;; toeacesad (remi Refere9ce Case I Case ii Case III Case IV Case I Case II Case III Case IV Total Body 1.5E+0 9.4E+0 1.!E+2 6.5E+2 9.6E-5 9.6E-4 1.1E-2 4.5E+2 Kidneys 6 !E+0 4.0E+1 6.4E+2 2.8E+3 4.1E-4 4.1E-3 4.8E-2 1.9E-1 Liver 2.0E+1 1.2E+2 2.CE+3 8.6E+3 1.3E-3 1.3E 2 1.5E-1 5.9E-1 Bone 3.aE+1 2.1E+2 3.3E+3 1.4E+4 2.lE-3 2.1E-2 2.5E-1 9.9E-1 Lungs 8.1E-1 5.0E+0 8.CE+1 3.4E+2 5.1E-5 5.1E 4 6.0E-3 2.4E-2 (a) Located 16.000 to 32.000 s frors tre plant in the direction the tornado travels for Cases I and !!. Located 560 m WSW of the AFL for Cases III and IV.

3-3

~-

TABLE B.9.

Fifty-Year Comitted Dose Equivalents from Inhalation Following a 180-mph Tornado (Class W)

Comitted Dose Equivalents for-Organ of Population iperson-rem) mesrest aesicencek 3* trem)

Reference Case I Case II Case Ill Case IV Case I Case il Case III Case IV Total Body 6.7E+3 6.1E+4 1.5E+4 1.4E+5 1.0E-1 1.0E+0 2.5E-1 2.5E+0 Kidneys 2.8E+4 2.6E+5 6.3E+4 6.0E+5 4.4E-1 4.4E+0 1.1E+0 1.1E+1 Liver 8.::E+4 8.0E+5 2.0E+5 1.9E+6 1.4E+0 1.4E+1 3.3E+0 3.3E+1 Sone 1.5E+5 1.3E+6 3.3E+5 3.lE+6 2.3E+0 2.3E+1 5.5E+0 5.!E+1 Lungs 3.6E+3 3.2E+4 7.9E+3 7.6E+4 5.5E-2 5.5E-1 1.3E-1 1.3E4 (a) Located 16.000 meters to 32.000 meters from the plant in the direction the tornado travels for cases II and IV; located 560 m WsW of the AFL for cases I and !!!.

TABLE B.10.

Fifty-Year Comitted Dose Equivalents from Inhalation Following a 230-mph Tornado (Class W)

Ce e ttted Dose Equivalents for:

Organ of Population ' person-rem)

Nearest a sidence683 ( rem) e Reference Case I Case II Case III Case If Case I Case ll Case III Case IV Total Body 6.7E+3 6.1E+4 1.5E+4 1.4E+5 1.0E 1 1.0E+0 2.5E-1 2.5E+0 Kianeys 2.8E+4 2.6E+5 6.3E+4 6.0E+5 4.4E 1 4.4E+0 1.1E+0 1.1E+1 Liver S.8E+4 8.0E+5 2.0E+5 1.9E+6 1.4E4 1.4E+1 3.3E+0 3.3E+1 Bone 1.5E+5 1.3E+6 3.3E+5 3.1E+6 2.3E+0 2.3E+1 5.5E+0 5.5E+1 Lungs 3.6E+3 3.2E+4 7.9E+3 7.6E+4 5.5E-2 5.5E-1 1.3E-1 1.3E+0 e

(a) located 32.000 to 48.000 meters from the plant in the direction the tornado travels.

B-4

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Sources and Effects of Ionizing Radiation. New York, New York.

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)

Wahlgren, M.A., and J. S. Marshall. 1975. The Behavior _of Plutonium and Other Long-lived Radionuclides in Lake Michigan:

I.

Biological Transoort, Seasonal Cycling, and Residence Times in the Water Column.

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Ref-3

n e

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