ML20012A319

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Rev 0 to Effluent Semiannual Rept,Jul-Dec 1989,Supplemental Info.
ML20012A319
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 12/31/1989
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20012A314 List:
References
NUDOCS 9003090226
Download: ML20012A319 (19)
v • d • e


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-s 1989: Efflu nt S00icnnual R3p3rt REV. 0  :

.P;g]1 1Lcf 8  ;

"?e t en ti er. : Lifetime' ,

l EFFLUENT SEMIANNUAL REPORT I i

02-JUL-89 THROUGH 30-DEC-89 [

'i SUPPLEMENTAL INFORMATION l.

L Facility: Prairie Island Nuclear Generating Plant Licensee: Northern States Power Company i

< License' Numbers: DPR-42 & DPR-60 i

s.

A. Regulatory Limits [

1. Liquid Effluents:  ;
a. The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site shall be -

limited tot '

.for the quarter 3.0 mrem to the total body 10.0 mrem to any organ j for the. year I 6.0 mrem to the total body 20.0 mrem to any organ  ;

2' . Gaseous Effluents:

a. The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to: i noble gases (500 mrem / year. total body (3000 mrem / year skin I-131,.H-3, LLP (1500 mrem / year to any organ
b. The dose due to radioactive gaseous effluents shall be limited to:

noble gases (10 mrad / quarter gamma 420 mrad / quarter beta (20 mrad / year gamma 440 mrad / year beta I-131, H-3, LLP 415 mrem / quarter to any organ (30 mrem / year to any organ L

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7 J .' 1989 CFFLUENT SEMIANNUAL' REPORT REV. O PACE 2

[ B. Maximus Permissible Concentration f .l. Fission and activation gases in gaseous releases:

[ 10 CFR 20, Appendix B, Table 2, Column 1

2. Iodine and particulates with halflives greater than 8 days in gaseous releases:

4 10 CFR 20, Appendix B, Table 2, Column 1 j

3. Liquid effluents for radionuclides other than dissolved or entrained gases:

10 CrR 20, Appendix B, Table 2, Column 2

[

4. Liquid effluent dissolved and entrained gases:

2.0E-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regul3 tory limits.

D.. Measurements and approximations of total activity ,

1. Fission-and activation gases Total GeLi i25%

in gaseous releases: Nuclide GeLi

2. Iodines in gaseous releases: Total GeLi 125%

Nuclide GeLi  !

3. -Particulates in gaseous releases: Total GeLi 125%

Nuclide GeLi ,

4. Liquid effluents Total GeLi 125% (

Nuclide GeLi l

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-er - ---- --- - -_-_ - --_-__-- _ _- - _ - - - - - -------- - - --_- -- - - -

'h989: EFFLUENT SEMI ANNUAL itEPORT ' REV. O PAGE 3

1. 0' BATCH RELEASES (LIQUID) QTR: 03 QTR 04 1.1 NUMBER OF BATCH RELEASES 4.10E+01 4.70E+01 1.2 TOTAL TIME PERIOD (HRS) 6.55E+01 7.62E+01 1.3 MAXIMUM TIME PERIOD (HRS) 2.33E+00 4.67E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.60E+00 1.62E+00 1.5 MINIMUM TIME PERIOD (HRS) 1.20E+00 3.30E 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 6.98E+03 6.10E+03 2.0 BATCH RELEASES (GASEOUS) QTR: 03 QTR: 04 2.1 NUMBER OF BATCH RELEASES 1.10E+01 1.50E+01 2.2 TOTAL TIME PERIOD (HRS) 2.54E+02 1.33E+02 2.3 MAXIMUM TIME PERIOD (HRS) 1.39E+02- 2.40E+01 2.4 AVERAGE TIME PERIOD (HRS) 2.31E+01 8.87E+01 2.5 MINIMUM TIME PERIOD (HRS) 2.80E-01 5.00E-02 6

3.0 ABNORMAL RELEASES (LIQUID) QTR: 03 QTR: 04 3.1 NUMBER OF RELEASES 0.00E+00 0.00E+00

' 3. 2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 0.00E+00 I

4.0 ABNORMAL RELEASES (GASEOUS) QTR: 03 QTR: 04 4.1 NUMBER OF RELEASES 0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00

1989 EFFLUENT SEMIANNUAL REPORT R EV .- 0 PAGE 4 TABLE 1A ,

[ GASEOUS EFFLUENTS - SUMMATION OF ALL-RELEASES QTR: 03 QTR: 04 5.0 FISSION AND ACTIVATION GASES I 5.1 TOTAL RELEASE (CI) 2.33E+01 l 1.37E+02 5.2 AVERAGE RELEASE RATE (UCI/SEC) 2.96E+00 1.74E+01  :

5.3 GAMMA DOSE'(MRAD) 1.07E-02 5.83E-02 t

5.4 BETA DOSE (MRAD) 2.86E-02 1.60E-01 i 5.5 PERCENT OF GAMMA TECH SPEC (%) e 1.07E-01 5.83E .t 5.6 PERCENT OF BETA TECH SPEC (%) 1.43E-01 8.00E-01 6.0 IODINES 6.1 TOTAL I-131 ( CI ). 4.00E-06 0.00E+00 ,

6.2 AVERAGE RELEASE RATE (UCI/SEC) 5.09E-07 0.00E+00 7.0 PARTICULATES 7.1- TOTAL RELEASE (CI) 3.14E-06 2.86E-06 7.2 AVERAGE RELEASE RATE (UCI/SEC) 3.99E-07 3.64E-07 8.0 TRITIUM.

8.1 TOTAL RELEASE (CI) 3.20E+01 3.69E+01 8.2 AVERAGE RELEASE RATE (UCI/SEC) 4.07E+00 4.70E+00 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 4.07E+00 4.70E+00 i

10.0- DOSE (MREM) 5.84E-02 6.65E-02 11.0 PERCENT OF TECH SPEC (%) 3.89E-01 4.43E-01 12.0 GROSS ALPHA (CI) 8.60E-08 1.07E-08

i. 1989 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 5

. TABLE 1C 1

, GASEOUS EFFLUENTS - GROUND LEVEL RELEASES

~13.0 FISSION AND ACTIVATION GASES  !

CONTINUOUS MODE BATCH MODE j NUCLIDE UNITS OTR: 03 QTR 04 QTR: 03 QTR: 04 e

AR-41 CI 3.26E-02 1.88E-02 KR-85 CI- 1.61E-01 J i

KR-85M CI 2.35E-03 i XE-131M CI 1.30E-02 3.38E-03 XE-133 CI 2.26E+01 1.33E+02 6.04E-01 1.30E-02 XE-133M CI 1.56E-03 -

XE-135 CI 1.50E-02 3.62E+00 1.97E-04 4.65E-05 ,

TOTAL CI 2.26E+01 1.37E+02 6.51E-01 1.96E  !

14.0 IODINES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS OTR: 03 QTR: 04 QTR: 03 QTR: 04 I-131 CI 4.00E-06 TOTAL CI 4.00E-06 0.00E+00 0.00E+00 0.00E+00 .

15.0 PARTICULATES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 CO-60 CI 7.57E-07 CD-109 CI 2.04E-06 7.13E-06 SR-89 CI 2.04E-06 1.37E-07 1.12E-07 SR-90 CI 2.02E-07 TOTAL CI 3.00E-06 2.75E-06 1.37E-07 1.12E-07 P

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[ [1989CFFLUENTsSEMIANNUAL REPORT REY. O PAGE 6 TABLE 2A i LIQUID EFFLUENTS -' SUMMATION OP ALL RELEASES l QTRt 03 QTR: 04' 16.0 VOLUME OF WASTE PRIOR'TO DILUTION (LITERS) 2.60E+07 3.99E+07 l 1

17.0- VOLUME OF DILUTION WATER'tLITERS) 2.61E+11 1.77E+11 j i

18.0' FISSION AND ACTIVATION PRODUCTS  :

18.1- TOTAL. RELEASE W/O H-3, RADGAS, ALPHA (CI) . 4.98E 6.69E-02 j 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.91E-11 3.78E-10 19.0 TRITIUM *** SEE ATTACHED NOTE FOR ADDITIONAL TRITIUM DOSE CALCULATIONS j I

19.1 TOTAL RELEASE (CI) 1.68E+02 1.29E+02 ]

19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 6.44E-07 7.29E-07 l 20.0 DISSOLVED.AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 2.59E-03 '9.93E-03 I 20.2 AVERAGE. DILUTED CONCENTRATION (UCI/ML) 9.92E-12 5.61E-11  !

21.0- GROSS ALPHA (CI) 0.00E+00 0.00E+00  !

22.0 TOTAL TRITIUM, FISSION AND ACTIVATION ..

PRODUCTS (UCI/ML) 6.44E-07 7.29E-07 ,

- 23.0 TOTAL BODY DOSE (MREM) 3.78E-04 3.85E-04 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 3.78E-04 3.85E-04 24.2 ORGAN TTL BODY TTL BODY

. 25.0- PERCENT OF TOTAL BODY TECH SPEC LIMIT (%) 1.26E-02 1.28E-02 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%) 1.26E-02 1.28E-02 1

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-1989 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 7 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 1-131 CI 1.50E-04 8.04E-06 8.34E-05 I-133 CI 8.11E-05 AG-110M CI 1.85E-04 6.52E-03 C0-58 CI 2.10E-04 8.24E-04 CO-60 CI 3.71E-04 1.27E-03 FE-59 CI 3.72E-05 CS-137 CI 9.68E-06 MN-54 CI 5.32E-06 5.65E-05 NB-97 CI 2.77E-05 3.00E-05 SN-113 CI 6.13E-05 2.41E-04 NA-24 CI 1.16E-06 SB-124 CI 1.69E-03 4.40E-04 SB-125 CI 1.97E-03 1.54E-03 CS-138 CI 2.28E-05 TC-99M CI 9.37E-06 ZR-97 CI 2.94E-06 3.29E-04 SR-92 CI 7.40E-06 FE-55 CI 1.50E-04 5.55E-02 TOTAL CI 3.81E-04 0.00E+00 4.60E-03 6.69E-02 i

[ . .

I i, 1989 CFFLUENT SEMIANNUAL REPORT REv. O PAGE 8 j h

L 28.0 DISSOLVED AND ENTRAINED GASES ,

CONTINUOUS MODE BATCH MODE

[ NUCLIDE UNITS QTR: 03 OTR: 04 QTR: 03 QTR: 04

'XE-133 CI 2.59E-03 9.86E-03 i XE-133M CI- 4.55E-05 -

XE-135 CI 3.77E-06 2.77E-05 f TOTAL CI 2.59E-05 9.93E-03 l 6

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r-v ATTACHMENT TO THE 1989 EFFLUENT SEMIANNUAL REPORT L ,

i t Liquid Pathway Dose Calculation  !

I i Quarters 3 and 4 1 1989 l

Summary  ;

)

The total liquid doses to the critical receptor for the third and i fourth quarters of 1989 arn 0.0167 and 0.0190 mrem, respectively.

These. doses are reported in this attachment to the semiannual report.

! Background i In october, 1989 a well water sample of a residence close to PI showed  !

low levels of tritium. Initial dose calculation results showed '

estimated liquid pathway doses a hundred times higher than those '

reported in past semiannual reports. These results indicated that a new dose pathway should be considered.

~ Investigation into the.cause of the tritium contamination led to the assumption that the flow of water is from the discharge canal downhill  ;

toward the Vermilion river. The resident's well draws from the

  • groundwater between the canal and the Vermilion river.

ODCM Considerations The following calculation is independent.of the ODCM. At this time no

change will'be made to the ODCM. Efforts are currently under way to determine if the tritium levels in the well can be' reduced.by physical modifications to the discharge structures and/or adjustments to the discharge methods. Results of these efforts should be available in -

1990 and the problem will be eliminated or appropriate ODCM changes will.be made.

Dose Calculation Assumptions For the purpose of dose calculation, the dose-maximizing assumption was.made that the receptor's concentration of tritium in body water and organic molecules is equal to the average concentration in the- J discharge canal. The dose conversion factor for this assumption is taken from page 9-3 of NUREG/CR-3332. Its value is 102 mrem / year per ,

uCi/ liter of tritium in the body. When adjusted for the units ,

reported for the discharge canal concentration, the dose conversion factor is 2.55E4 mrem / quarter per uCi/ml. ,

Discussion The elevated tritium levels were found at the residence which is the .

critical receptor (0.6 miles to the SSE of the site) for Prairie I Island. Therefore, the dose calculated for waterborne tritium is added to the critical receptor's fish pathway dose. This overestimates the dose because the tritium dose from eating fish is i accounted for twice.

. Pag] 2 i It should'be noted that the total airborne dose (99% plus of which is due to tritium) is greater than the total waterborne tritium dose. I Even though the newly identified pathway delivers additional tritium to the critical receptor it is a lower concentration than that already in the body due to airborne exposure. ,

Dose calculation Average Dose Diluted Whole Fish Total '

Quarter Conversion X Tritium = Body + Pathway = Liquid  !

Factor Concentration Dose Dose Dose (mrem / quarter (uCi/ml) (mrem) (mrem) (mrem) i per uci/ml) 3 2.55E4 6.44E-7 1.64E-2 3.78E-4 1.68E-2 j 4 2.55E4 7.29E-7 1.86E-2 3.85E-4 1.90E-2  !

Dose Report LIQUID EFFLUENTS - SUMMATION OF WATERBOP.NE TRITIUM AND FISH PATHWAYS OTR: 03 QTR: 04 l TOTAL BODY DOSE (MREM) 1.68E-02 1.90E-02 i

CRITICAL ORGAN .

DOSE (MREM) 1.68E-02 1.90E-02 ORGAN TTL BODY TTL BODY PERCENT OF TOTAL BODY TECH SPEC LIMIT (%) 5.60E-01 6.33E-01 ,

PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%) 5.60E-01 6.33E-01 v

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' Retention: Lifetime PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-89 to 12-31 NORTHERN STATES POWER License No. DPR-42 I

SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments s-l 1. Solid Waste Total Volumes and Total Curie Quantities:

i V

l l l l Container l:

l l l l' Disposal .I Type-of Waste l Units i Totals l Volumes I (List) 3 347,3 1 A. Resins l ft 173 I

l l Ci l 51.426 1 135.8 I I ll L l ll B. Dry-Compacted 3 2730.1 7.5 ll ft l l I I  ;

I Ci 37.373 11.3 I l I , , ,

I I 3 54.8 96 l C. Non-Compacted I ft l I l .

I I I I l l-l l Ci 1 0.044 l l i l l I I I I I i i I

, l l

3 I D. Filter Media ft J. 461.8 l 163 l- 1 I I

I I Ci l 13.762 l 135.8 I I I

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l S. Spent Fuel I, ft p l H I I I I i l I Ci l I ,

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-89 to 12-31-89'-

NORTHERN STATES POWER License No. DPR-42

(- c SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT

. Table I: Solid Waste and Irradiated Fuel Shipments (Continued) -

2. -Principal Radionuclide Composition by Type of Waste:

Percent TYPE (From Page 1) Nuclide Abundance

,. 1

[- A CO-60 45.0

  • 11 - 3 1.1 i

t-l B

C0-60 26.3 "

  • 11 - 3 2.9 CS-134 1.3 NB-95 1.1 s

1; l * = Inferred - Not Measured on Site 1:

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-89 to 12-31-89  !

n NORTHERN STATES POWER License No. DPR-42 f

SOLID'RADI0 ACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT P Table 1: Solid Waste and Irradiated-Fuel Shipments (Continued)

Principal Radionuclide Composition.'by Type of Waste L 2.

'l (Continuation): o

l , Percent b TYPE (From Page 1) Nuclide Abundance a

C

  • 11 - 3 8.5

.C0-60 6. 4 _

2.4 AG-110M 2.0 SB-125 _ 0.8 v CO-58 0.7 CS-137 0.3

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6.4

CS 137 0.2 ,

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  • = Inferred - Not. Measured on Site IBM

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' i p t ' PRAIRIE: ISLAND NUCLEAR" GENERATING' PLANT Period: , 7-1-89 to 12-21-89 L ,

D ' NORTHERN STATES POWER License No. DPR-42

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7  ;

( SOLID RADIOACTIVE VASTE DISPOSAL SEMI-ANNUAL' REPORT Tab 1'e'I: Solid Waste and' Irradiated Fuel-Shipments (Continued) l  ;

[ -3. Solid. Waste Disposition:l L

i: Number of Shipments. Mode- -Destination l, :

s f

!," 14- Truck Richland WA ,i

(" *  !

1 Truck Barnwell' SC-- -

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p 2 Truck Oakridge.'TN t l.

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I 4. Irradiated Fuel Shipments:

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' Number of Shipments Mode Destination  ;

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-PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-89 t.o 12-31-89 i NORTHERN STATES POWER License No. DPR-42 >

SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT  !

Table I: Solid Waste and Irradiated Fuel Shipments (Continued)

}

}. 5. Shipping Container and Solidification Method: ,

i.

Disposal i

No. Volume Activity Type of Container Solidif. .

(Ft3) (Ci) Waste Code Code ,

89-16 510.0 2.55647 B L N/A 89-18 510.0 - 1.31359 B L N/A 89-19 510.0 ~ 1.20141 B L N/A 89-22 510.0 1.64668 U L N/A-l- 89-23 480.1 1.77159 B L N /A -

89-28 178.0 1.19304 A L N/A t

89-29 163.0 0.94613 D L N /A 89-31 163.0 -

0.86818 D L N/A r 89-32 135.8 45.3338 A L N/A

[ 89-34 178.0 1.39951 A L N /A  ;

89-35 105.0 _14.1488 B L N /A 89-36 178.0 2.26993 A L N/A 89-37 105.0 14.73528 B L N/A '

89-39 135.8 11.94816 D L N/A 89-40 178.0 1.22945 A L N /A 88-35 44.4 0.044 C L N/A 87-40 10.4 0.00001 C L N/A __

l l

TOTALS 17 4094.5 102.606 CONTAINEL CODES: L = LSA '

(Shipment Type) A = Type A B = Type B Q = Highway Route Controlled Quantity l

SOLIDIFICATION CODES: C = Cement i

TYPES OF WASTE: A = Resins B = Dry Compacted C = Non-Compacted D = Filter Media S = Spent Fuel IBM

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NORTNERN STATES POWER COMPANY ,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE manIATION DOSE ASSErMMENT..F9B January 1- Dec==her 31, 1989 An assessment of radiation dose due to release from the Prairie Island Nuclear Generating Plant during 1989 was performed in accordance with the Technical Specifications. Computed doses were well below the 40 CFR Part 190 Standards and 10 - CFR Part 50 Appendix I Guidelines.

Off-site dose calculation formulas and meteorological data from the off-site Dose Calculation Manual were used in making this assessment. Source terms were obtainea from the two Effluent and Waste Disposal Semiannual Reports prepared for NRC review during the year of 1989.

Off-site Doses from Gaseous Release Computed doses due to gaseous releases are reported in Table 1.  :

Critical receptor location and pathways for organ doses are i reported in Table 2. Doses, both whole body and organ, are a small '

percentage of Appendix I Guidelines.

Off-site Doses from Licruid Release Computed doses ' due to liquid releases are reported in Table 1.

Receptor information is reported in Table _2. Both whole body dose and organ dose are a small percentage of Appendix I Guidelines. ,

l

'l Doses to Individuals Due to Activities Inside the site Boundarv Occasionally sportsmen enter the Prairie ' Island site for recreational activities. These individuals are not expected to-spend more than a few hours per year within the site boundary.

Commercial and recreational river traffic exists through this area, i For purposes of estimating the dose due to recreational and river '

water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be '

received by an individual who spends a total of seven days per year on the river just off shore from the main plant buildings (ESE at i

0.2 miles) . Whole body and inhalation organ doses were calculated i for this location and occupancy time. These doses were reported in j Table 1. $

Domes to Most Ernosed Member of the General Public from Reactor Releases and Other Uranium Fuel cycle Bources

.There are no other. uranium fuel facilities in the vicinity of the Prairie Island site. The only other artificial source of exposure to the general public in addition to the plant effluent releases is from direct radiation of the reactors. This direct radiation from pressurized water-reactors has been shown to be negligible.

An array of TLD monitoring stations around the perimeter-of the site boundary has consistently indicated that plant operation in the past years has no effect on ambient gamma radiation.

Therefore, the most exposed member of the general public will not receive an annual radiation dose from reactor effluent releases and all other fuel cycle activities in excess of the sum of the liquid and gaseous whole body and organ doses reported in Table 1 for the site boundary and critical receptor, respectively. These doses are well below 40 CFR Part 190 standards of 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.

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4, TABLE 1' ,

x. OFF-SITE RADIATION DOSE-ASSESSNENT.- PRAIRIE ISLAND

-PERIOD 8 JANUARY 1 through DECEMBER 31. 1989-

, 10 CFR Part 50' Appendix I Guidelines per 2-units site per year 7

Gaseous Releases 1

Maximum ~ Site Boundary

- Gamma Air Dose:(mrad) 0.0720 20

. Maximum Site Boundary Beta Air Dose-.(mrad)' O 20 '40 Maximum Off-site Dose to Any' organ 2(mrem)*

Total 0.336 30 m' . Offshore Location (arem)

-Wholel Body

~

0.0118 10

Organ 0.0118 30

' ' Liould'ReIoases Maximum"Off-site: Dose Whole Body-(mrem) 0.0824- 6 w, . .

'a - MaximumLOff-site. Dose

- Organ,' Total 0.0824 20

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H OFF-SITE RADIATION DOSE-ASSESSMiANT -lPRAIRIETIBLAND .'

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-SUPPLEMENTAL INFORNATION' i

PERIOD (Al[RARY 1 throuch DECmg3 - 31, 1933 f>

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Gaseous Releases f i

Maximum Site' Boundary I h

' Dose Location- '

(from Building vents) o Sector WNW '

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Distance ~(miles) 0.36

, Offshore Location Within~ Site Boundary

  • Sector- ESE

~ Distance -~(miles) . -0.2

  • 4 Maximum off-site Dose Location Sect'or- SSE f Distance.(miles) O.6 Pathways Ground, '

y ' Inhalation, *

[.~ Vegetable.s ; ~j

Age' Group. Child-Organ- Whole Body- .

r W Liqui [ Releases

~ Maximum Off-site Dose i Location Downstream' {

Pathways Fish, well water  ?

Age' Croup Child ,

b> Organ Whole Body >

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1 3 .

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