ML20129A462

Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway

ML20129A462
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/11/1996
From:	PUBLIC SERVICE CO. OF COLORADO
To:
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ML20129A449	List: ML20129A443 ML20129A462
References
FSV-FRS-TBD-209, NUDOCS 9609180241
Download: ML20129A462 (47)

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1 I

SCIENTIFIC ECOLOGY GROUP, INC.

TECHNICAL BASIS DOCUMENT 1

FSV-FRS-TBD-209 REVISION 0 P.O. BOX 2530 1560 BEAR CREEK ROAD OAK RIDGE,TN 37831-2530 TITLE 1

i FORT ST. VRAIN DECOMMISSIONING PROJECT FINAL SURVEY REQUIREMENTS FOR THE LIQUID EFFLUENT PATHWAY REVIEWED BY:

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DATE APPROVED BY:

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T/"b NSIBLE SUPERVISOR DA1E APPROVED BY:

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9///[96 PIOQ RADIATION PROTECTION DA'TE 7////94 EFFECTIVE DATE 9609180241 960911 PDR ADOCK 05000267

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u FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0

1.0 INTRODUCTION

i 1.1 Scope This document describes the scope and the methods to be used by the Public Service Company of Colorado (PSCo) to demonstrate that the Fort St. Vrain (FSV) liquid effluent pathway and the surrounding open-land areas are suitable for release for unrestricted use.

This document has been used as the basis for survey design and development of final survey packages related to the liquid effluent pathway and the surrounding open-land areas.

1.2 Discussion Final survey packages are being prepared and implemented; and it is expected that survey packages will be reviewed and accepted for closure in accordance with this proposed revision.

This guidance will be used by final survey engineers as the guidance for the survey design during preparation of these survey packages, and serves as the basis for the selection of sampling and measurement locations. The specific instructions for collection of samples and exposure rate measurements are formally conveyed to the survey technician in accordance with the protocols and documentation contained in FSV-SC-FRS-I-102, " Survey Design and Package Preparation, Control, Implementation and Closure."

The final survey plan and procedures will be revised upon NRC approval of the methods to be used by PSCo for survey of the FSV liquid effluent pathway and the surrounding open-land areas.

In the event that approval is obtained prior to submittal of these final survey measurements, correspondence will accompany the submittal indicating that the measurements have been collected in accordance with the approved revision, and that the final survey plan and procedures are undergoing revision to comply'with the prdposed revision.

In the event that approval is not obtained prior to submittal of these survey measurements, correspondence will accompany the submittal indicating that the measurements have been collected in accordance with the proposed revision.

In the event that the proposed revision is modified during the approval process such that additional measurements are required, these survey packages will be re-opened and the balance of the data will be collected and included in the survey packages. If additional measurements are required, the Release Records will be similarly modified and re-submitted to the NRC.

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i FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 2.0 HISTORY AND DESCRIPTION OF THE EFFLUENT PATHWAY The Liquid Effluent Pathway (LEP) from the discharge point, is composed of the Goosequill Ditch, the Jay Thomas Ditch, the Farm Pond and the South Platte River. The Goosequill Ditch is a concrete-lined culven (ditch) approximately 7000 feet in length, which begins at the effluent discharge point west of County Road 19%, and terminates at the Jay Thomas Ditch. The Goosequill Ditch is approximately 5 feet wide at the top and one foot wide at the bottom, with sloping sides of approximately 40 inches each. The Jay Thomas Ditch is a stream bed beginning upstream of the intersection with the Goosequill Ditch and terminating at the Farm Pond. The Jay Thomas Ditch is unlined and is 3-6 feet wide,2-3 feet deep and approximately 2300 feet long. The Farm Pond covers approximately 25 acres and is 2-4 feet deep. The outfall of the pond is a stream bed that eventually terminates at the South Platte River. The LEP is illustrated in Figure 2.1.

Figure 2.1 FSV Liquid Effluent Pathway sman:maamanr.r -arsr.waramesnemmscr IMMENIP/StWW NN

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 Water from the Goosequill Ditch and the Jay Thomas Ditch was routinely diverted for agricultural irrigation of the surrounding fields and pastures.

Prior to 1994 the Goosequill Ditch was known to leak water into various adjacent soil areas which provided means for transport of radioactive materials to the surrounding soil.

In addition, the ditches were periodically cleaned of vegetation and sediment in order to maintain required flow rates and avoid overflow.

The removed material was routinely deposited on the banks immediately adjacent to the ditches.

A review of analysis results for liquid wastes released from FSV indicates that these releases have been well within the requirements of Public Service of Colorado's Offsite Dose Calculation Manual (ODCM).

Compliance with the ODCM, and the Radiological Environmental Monitoring Program (REMP) has demonstrated that the total dose from liquid effluents has been maintained at less than 3 mrem / year.

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 3.0 CONTROL AND MONITORING OF LIQUID EFFLUENTS The PSCo Offsite Dose Calculation Manual (ODCM) requires that if calculated doses from liquid effluents exceed 3 mrem /yr to the total body or 10 mrem /yr to any organ, then..."a special report should be submitted to the NRC stating the reason and corrective action to be taken." All liquid releases have been made in compliance with the ODCM and these limits have never been exceeded. The doses for 1994 and 1995 are shown in Table 3.1.

Table 3.1 ODCM Calculated Doses Year Whole Body Maximum Exposed Organ 1994 5.13E-04 mrem 3.29E-03 mrem 1995 2.40E-03 mrem 7.07E-03 mrem The PSCo ODCM also states:

6.14.3 A pre-operational environmental radiation surveillance program for the Fort St.

Vrain Station em' irons has been conductedfor Public Service Company of Colorado by Colorado State University. Continuous operation of this program since March,1%9, has provided baseline data which will be utilized as control valuesfor statistical analysis of the results of the decommissioning radiological surveillance program.

6.14.6 The results of the radiological environmental monitoring are intended to supplement the results of the radiological efuent monitoring by venfying that the measurable concentrations ofradioactive materials and levels of radiation are not higher than expected on the basis of the efuent measurements and modeling of the em'ironmental exposure pathways. Thus, the speciped environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highestpotential radiation exposures to individuals resulting from station decommissioning.

The Radiological Environmental Monitoring Program Summary Report for 1995, prepared by Colorado State University for the Fort St. Vrain Nuclear Generating Station provides the following observations and conclusions:

1.

As in every previous report, it was again apparent that for most sample types the variability observed around the mean values was great. This variability is partly due to counting statistics and methodological variation, but principally due to true em'ironmental variation (often termed sampling error). It must be recognized and accounted for in analyses of any set of environmental data before meaningfut conclusions can be drawn; 4 of 24

i FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY.

REVISION 0 l

2. Tritium was detected in the efluentpathwayperiodically through 1995. The release of I

tritium was indeed much less than in operational years. Since the tritium is released as j

tritiated water, the dilution by the surrounding hydrosphere is great and consequently the I

i mean values of downstream surface water were not statistically greater than upstream concentrations. No tritium was detected in ground water or anyfood samples; i

4

3. The Chernobyl world-widefallout has totally obscured whatfssion product debris has l

l remained in the FSV environsfrom the October 1980 Chinese atmospheric nuclear weapon

~

test. The b osphere will contain the Chernobylfallout, particularly Cs-137, for an equally i

long period. Nuclear weapon testfallout has,- since the inception of the project, been noted to be the predominant source term above natural background. The Chernobyl reactorfre debris was superimposed on the weapons test fallout from 1986 to present. It is the variation in fallout deposition, in addition to the variation in naturally occurring radionuclides, that mandates the large number of environmental samples to detect any possible radioactivity due tofacility efluents. A simple comparison ofpre-operational and operational values is oflittle value, for most sample types, because thefallout deposition i

i l

was considerably greater during the pre-operationalperiod due to world-widefallout; d

l

4. Theprompt and sensitive detection ofthe Chinese weapon testfallout and the Chernobyl fallout in the past assures that the environmental monitoring program was of adequate scope and sensitivity to detect any accidental releasesfrom the FSV decommissioning; and i

i i

5. Release of decommissioning radioactive waste was evident in the Goosequill sediment.

Since this is primarily Cs-137 in sediment, its transfer to plant and animalfood chains will be negligible.

P e

It can be concludedfrom the data collected by the environmental monitoring program that I

i.

l the radiation dose commitments calculatedfor the closest human inhabitants or otherparts ofthe nearby ecosystems due to currentfacility efluents are negligible. Natural background radiation and the dose commitmentfrom atmosphericfallout are the only known sigmpcant i

sources of radiation dose to the residents of the area.

During the current decommissioning phase of the facility it is concluded that this

+

i Radiological Environmental Monitoring Program is more than adequate to detect and i

quannfy any possible routine or accidental release of radioactivity.

I 1

1 L

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FINIL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 4.0 CHARACTERIZATION OF THE LIQUID EFFLUENT PATHWAY In late summer of 1993, ODCM calculations yielded slightly increased doses. This initial concern prompted the collection of a sediment sample from the inlet to the Farm Pond on 9/29/93. The analysis results of this sample indicated a concentration that was greater than those reported by both the Initial Radiological Site Characterization surveys performed during 1992, and by PSCo's environmental monitoring program. Although the result was below that which would impact the final survey, a potential increase in the radioactivity concentration was indicated.

Sediment and soil samples were periodically collected during 1993 and 1994 to check for buildup of radioactive materials. Between 9/29/93 and 8/25/94,69 samples were collected from the effluent discharge path. Activities of cobalt-60 ranged from non-detectable to 0.6 pCi/g. The results of these samples were not considered to be abnormally high, although the results indicated that a surveillance should be continued. On 8/25/94, two marshy areas where the goosequill ditch was known to have overflowed were selected for a more detailed evaluation. Each area was gridded and a total of 30 unbiased soil samples were collected.

Most of the samples exhibited low concentrations of detectable total activity with the maximum cobalt-60 result being 2.7 pCi/g.

On 11/16/94 two soil samples were collected from the effluent discharge path in an area where known leaks had occurred to evaluate the initial profile of the radionuclide mixture for final survey analysis. One of these sample results indicated a cobalt-60 concentration of 7.7 pCi/g, which was about 50% higher than any of the previous samples.

Between 11/26/94 and 1/20/95 sixty soil and sediment samples were collected and 60 exposure rate measurements (at 30 locations) were taken to better define the scope of the increased concentrations.

The highest concentration (41 pCi/g of cobalt-60) was from sediment which had been dredged from the effluent ditch. During this same time frame, 213 in-situ gamma spectroscopy measurements were collected along the liquid effluent 1

pathway, in agricultural dispersion areas, and'in areas aro'und and beyond the farm pond.

Indications of cobalt-60 and europium radionuclides demonstrated that these radionuclides were present at some locations.

In January 1995 a formal characterization survey plan was developed for the areas surrounding the LEP, and approximately 750 environmental (sediment and soil) samples were collected between 2/95 and 4/95. The intent of the survey was to define the bounds s

of the areas of increased concentrations within the effluent pathway and surrounding areas.

Samples were collected in accordance with approved operating procedures designed to meet fina! survey quality requirements. Final Survey Procedures were not used and statistical analyses were not perfonned on the resulting data because the samples would not represent the final condition of the pathway and this characterization survey was considered to be a part of the planning for the initial final survey.

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 The results from more than one thousand environmental samples collected over the past two years of the decommissioning as a part of the characterization and follow-up characterization surveys have shown that any increased concentrations of radioactive material are present in very localized areas, and are decreasing due to radioactive decay and the effects of weathering. The bounds of these areas are well-defined, and have been previously selected for biased sampling.

The areas of increased concentration peaked at their highest concentration at the beginning of 1995, and have been identified by the characterization to be located where:

1.

Dredged materials had been removed from the ditches and placed on the banks of the ditches; 2.

The ditches have leaked or overflowed and drained into slough or field areas, or; 3.

In the early days of the decommissioning project, irrigation may have occurred during discharges or dredging operations.

As a result of the controls described in Section 5.0 and implemented in late 1994 to reduce the quantities of radioactive materials released from FSV, the controls placed on irrigation during discharge, and the natural weathering process of radioactive materials in the environment, the residual concentrations in the effluent pathway are decreasing as indicated by the follow-up characterization survey performed in May and June of 1996.

The following is a chronological presentation of the sampling performed along the effluent discharge path and adjacent areas. For several of the initial samples, only the cobalt-60 results.are discussed because this isotope is more restrictive than cesium-137, which was also identified in increased concentrations.

9/29/93 Initial sample collected at the inlet to the farm pond. The total activity result was 3.7 pCi/g (3.05 pCi/g of cesium-137, 0.38 pCi/g of cesium-134 and 0.31 pCi/g of cobalt 60).

12/21/93 Twenty-two samples were collected. These se,7 es consisted of sediments 1

removed from the Goosequill Ditch, soil from 4@ cent " overflow" areas, and at the inlet to the farm pond. Total activity for these samples ranged from non-detectable to 3.8 pCi/g.

5/10/94 Two samples were collected which yielded total activity results of 4.8 and 5 pCi/g.

7/11/94 A sediment sample was collected adjacent to the outlet of the farm pond.

The total activity for this sample was < 1 pCi/g.

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 8/94 Thirteen samples were collected between 8/8/94 and 8/22/94. Ten of these samples were of silt and clay from the bottom of the farm pond. The remaining three samples were collected adjacent to irrigation ditches routinely used for agricultural purposes. The total activity results for these samples i

ranged from non-detectable to 1.6 pCi/g.

On 8/25/94, two marshy areas where the Goosequill Ditch was known to have overflowed or leaked were selected for a more detailed evaluation.

Each area was gridded and a total of 30 unbiased soil samples were collected.

Most of the samples exhibited low concentrations of detectable total activity with the maximum cobalt-60 result being 2.7 pCi/g.

i The ditches were inspected prior to the first release of shield water that had been stored in the Reactor Building bladder, to ensure that there were no leaks in the Goosequill Ditch and no potential for overflow during release.

11/16/94 Two samples were collected from the plant effluent discharge path to i

determine an initial profile of the radionuclide mixture. These samples were i

collected solely to develop site-specific criteria for concentrations of radioactivity in soils as a part of planning activities for the final survey. One sample result yielded a concentration of cobalt-60 at 7.7 pCi/g., which was higher than any results previously observed during SEG sampling and from Public Service of Colorado's en' vironmental sampling program. This sample result triggered more aggressive sampling of the effluent path.

11/26/94 Forty-two follow-up samples were collected of both sediments recently dredged from the ditch, as well as sediments remaining within the ditch. Soil j

samples were also collected from an agricultural dispersion area where the effluent path had been diverted in the past. The analysis results of these samples indicated increased concentrations of radioactivity sporadically along the entire discharge path and at an agricultural dispersion trench which was fed from the discharge path. The highest cdncentration (41 pCi/g of cobalt-t

60) was from sediment which had been cleared from the effluent ditch.

Concentrations in the agricultural dispersion trench ranged to less than MDA to 11.6 pCi/g of cobalt-60.

11/30/94 Six additional follow-up samples of sediment were collected from within the Goosequill Ditch directly down stream from the effluent inlet. All six of these samples had results which ranged from 5.9 pCi/g to 18.5 pCi/g of cobalt-60.

12/94 Additional soil samples and exposure-rate measurements were collected to funher define the scope of the contamination in the effluent pathway, and to provide data for planning a characterization survey plan that would j

characterize the quantities and boundaries of contamination.

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 All parties agreed that no water would be discharged unless evaluated and approved for release by the WT Project Radiation Protection Manager. It was further agreed that the effluent pathway would be inspected prior to a i

release, any necessary repairs to avoid leakage or overflow would be performed, and no irrigation would be permitted during a release or during

]

repair or dredging work.

1/95 Technical evaluation completed to det:rmine that existing quantities of chlorine-36 and other beta emitters wauld have no measurable effect on i

effluent pathway envimns. Recomaunded concentrations for discharge of 1E-07 Ci/mi for cobalt-66 Ar.d 2E-07 Ci/ml for cesium-137. Additional demineralizers and filters were installed to process water to recommended concentrations.

i Scoping survey completed and Characterization Plan initiated for LEP.

2/95 The radiological characterization of LEP was performed in February and March of 1995. The final report was issued for review in May 1995 and approved for publication on 6/14/95.

4 1995-1996 Samples were periodically collected to monitor contamination levels and prior to dredging or repair work in the ditches.

1' 5/28/%

A follow-up sampling plan for the LEP was initiated to evaluate the current radiological status of the LEP and compare the results to NUREG-1500 l

guideline values. These results indicated that NUREG-1500 values could be i

used, but extensive sampling and averaging over 100 square meters would be i

required in a limited number of areas.

i 4

07/10/ %

PSCo suspended the ODCM and REMP programs, and related implementing procedures to reflect the completion of ODCM requirements.

4 1

i 8

NRC NUREG 1500, Working Draft Regulatory Guide on Release Criteria for Decommissioning was used for the initial evaluation of the concentrations present in the liquid effluent pathway and surrounding soils.

Since that time, the RESRAD computer code has been used to define the concentration SGLV appropriate i

for FSV in consideration of future use of the site.

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l FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 i

THE LIQUID EFFLUENT PATHWAY REVISION 0 2

5.0 CONTROLS IMPLEMENTED SINCE NOVEMBER,1994 Additional water-processing equipment was installed and all discharges have been made at 1

concentrations (prior to dilution) that were below the LLD's required by the ODCM. The target concentrations for cesium-137 and cobalt-60 were 2E-07 and IE-07 pCi/ml, respectively. Results of radiological analysis were reviewed and accepted by the SEG Project Radiation Protection Manager prior to releasing water.

The Goosequill ditch was inspected for leaks and repaired where necessary. The ditch was i

walked down while in full dilution flow prior to a release to inspect for overflow and leaks.

Dredging materials from the ditch were sampled and placed in a designated storage area for control and disposition.

Irrigation from the ditches was not permitted during discharges or dredging operations.

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 6.0 CURRENT STATUS OF EFFLUENT PATHWAY The mechanism of the contamination is well understood and the boundaries of the areas of increased concentration have been well-defined as a result of the characterization and follow-up characterization surveys. As described in Section 4.0, to monitor the impact of liquid discharges and to prepare for the fm' al survey of the Fort St. Vrain liquid effluent pathway, l

a follow-up sampling plan for the liquid effluent pathway was written and implemented between May 28,1996 and June 6,1996. The purpose of implementing the plan was to further characterize and evaluate the current radiological status of the effluent pathway and to confirm our understanding of the affected locations. At that time more than 150 samples were collected within, and adjacent to the pathway. The sample locations were chosen to correspond with the sample locations identified during the characterization survey as having increased concentrations.

Each of the individual soil samples was analyzed for gamma emitting radionuclides and evaluated in terms of the nuclide specific dose conversion factors in the RESRAD model developed for FSV. None of the semple concentrations exceeded the SGLV, and only two of the individual sample concentrations exceeded 50% of the SGLV. (0.68 and 0.55) The results of the characterization survey and the follow-up sampling plan indicate that the radionuclide concentrations peaked in the November,1994 to January 1995 time frame.

The decrease in concentrations is a result of the controls that were implemented, radioactive decay, and natural weathering of the environs.

The last liquid discharge via the liquid effluent pathway was completed on 7/3/96. During the week of 7/22/96, the Goosequill was sampled for radiological and non-radiological constituents. Subsequent to collection of these samples, dilution water will be diverted from the Goosequill and the ditch will be cleaned and final survey will be performed.

Final Survey will be implemented for the balance of the effluent pathway including the surrounding open-land areas during August through September,1996.

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 7.0 SURVEY PLAN The approved FSV final survey plan requirements related to the quality elements, statistical evaluation, and comparison of results to release criteria will be implemented. The proposed changes are related to the collection of exposure rate measurements, the sampling frequency, and investigative actions.

7.1 Site-Specific Guideline Values for Surface Activity The site-specific guideline values for measurements of total and removable surface activity will be those appropriate for the balance of the site, and contained in FSV-TBD-201, Site-Specific Guideline Values for Surface Activity.

7.2 Site-Specific Guideline Values for Concentrations in Soil and Water The concentration guideline values for residual concentrations in soil are listed in Table 7.1, and were derived using the RESRAD computer code. The RESRAD model used for this derivation has been included as Attachment 1.

The concentration SGLVs for sediment collected from the Farm Pond and the Jay Thomas Ditch have also been based on these values for soil. This is a conservative approach since these locations consist of permanent surface waters, and external exposure which is the major exposure pathway, would not reasonably occur at these locations.

Table 7.1 4

Concentration SGLV in Soil / Sediment Based on the FSV RESRAD Model I

Nuclide Dose Conversion Factor SGLV (mrem /yr/pCi/g)

(pCi/g/10 mrem)

Co-60 1.79E+00 5.58E+00 Cs-134 1.27E +00 7.87E +00 i

Cs-137 5.35E-01 1.87E+01 Eu-152 7.58E-01 1.32E+01 Eu-154 8.27E-01 1.21E+01 Eu-155 2.28E-02 4.39E+02 Fe-55 4.07E-04 2.46E +04 4

H-3 1.10E-02 9.12E+02 g

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 l

The' concentration guideline values for surface water which could be used as drinking water are listed in Table 7.2, and were derived from the Allowable levels of Intake in Environmental Protection Agency Report 520 (EPA-520) in order to limit the committed effective dose equivalent (CEDE) to 10 mrem /yr. This results in a conservative estNate of the potential dose from the drinking water pathway since this water would r 9 tire purification which would remove the major contributors to exposure.

i Table 7.2 Concentration SGLV in Drinking Water Derived From EPA-520 Nuclide Dose Conversion Factor SGLV (mrem /yr/pCi/ml)

(pCi/ml/10 mrem)_

Co-60 7.28E+00 1.37E+00 i

Cs-134 5.20E+01 1.92E-01 Cs-137 3.64E+01 2.75E-01 Eu-152 4.55E+00 2.20E+00 Eu-154 7.28E+00 1.37E +00 Eu-155 9.10E-01 1.10E+01 Fe-55 4.04E-01 2.47E+01 H-3 4.55E-02 2.20E +02 o

{

7.3 Classification and Associated Sampling Frequency The basis for classification, the survey requirements, and the investigation / reclassification action levels for each classification are described in Table 7.3. Each of the areas indicated j

in Table 7.4 will be defined as a survey unit and surveyed as described, with the exception of the Goosequill Ditch, which is described in the paragraph following Table 7.4. The J

minimum survey requirements are based on the' potential for residual radioactivity, and assigned a classification of Affected Class 1, 2 or 3.

i t

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 l

THE LIQUID EFFLUENT PATHWAY REVISION 0 Table 7.3 Initial Clandfication/ Survey Requimnents and Investigation / Reclassification Action levels for Affected Open Iand Areas Class Cdteria for Survey Investigation / Reclassification Classification Requimnent Action I2 vel Affected Area where an individual 100% scan,40 biased Individual measurement in excess of j

Class 1 measurement exceeds 50%

and 10 unbiased soil the SOLV, or the average of the the SOLV, or the average samples, exposure rate measurements in excess of 75% of the of the measurements measurement at each SOLV.

exceeds 25% of the SOLV.

sampling location.

If an individual sample is verified to a

exceed the SOLV, the average I

concentration will be determined in accordance with the FSV Final Survey Plan.

Affected Area which has been 10% scan,40 biased Individual measurement in excess of Class 2 adequately characterized, and 10 unbiased soil 50% of the SOLV, or the average of and there is a high degree samples.

the measurements in excess of 25% of j

4 of certainty that individual the SOLV.

measurements are less than If an individual sample, or the average 50% of the SOLV, and the sample results, is verified to exceed average of the the reclassification action level, the measurements is less than survey unit, or portion of the survey i

25% of the SOLV.

unit, will be assigned to Class 1 and q

resurveyed.

Affected Area which has been 40 biased and 10 Individual measurement in excess of Class 3 adequately characterized, unbiased soil samples.

25% of the SOLV, or the average of l

and there is a high degree the measurements in excess of 10% of of certainty that individual the SOLV.

l measurements are less than If an individual sample, or the average 25% of the SOLV, and the sample results, is verified to exceed average of the the reclassification action level, the measurements is less than survey unit, or portion of the survey J

10% of the SOLV.

unit, will be assigned to Class 1 and resurveyed.

3 Biased samples are collected at locations of the most elevated concentrations identified during the characterization surveys, based on knowledge of the liquid effluent pathway. An additional 10 unbiased surface soil / sediment samples will be collected outside of the areas selected for biased sampling within each sutvey unit to ensure all portions of the survey unit are evaluated with a level of effort commensurate with the potential for concentrations to i

approach the SGLV. Due to the limited number of samples, these areas will not be gridded as described in the Final Survey Plan, unless an investigation is required as described in Sections 7.5 and 7.6.

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 Table 7.4 Survey Unit Design for the Effluent Pathway and Surrounding Soil Survey Unit Description Max / Avg Fraction of Class for Survey Requirements SGLV from Cher.

Final Survey Survey Goose Qudi Banks 0 07/0.01 3

40 biased,10 unbiased sod samples.

Jay 'Ihomas Ditch 0.83/0.17 1

40 biased.10 unbiased sediment samples.

Jay Thomas Banks 0.68/0.15 1

100% scan,40 biased,10 unbiased soil samples.

exposure rate at each sample.

Irngation Ditch 2. North and 0.47/0.15 1

100% scan, 40 biased,10 unbiased sod samples, 1

South Marsh 8 exposure rate at each sample.

J frngation Duches 1,3,4,5 and 6 0.11/0.06 3

40 biased.10 unbiased soil samples.

Farm Pond (sediment and water) 0.10/0.05 3

40 biased,10 unbiased sediment / surface soil and Outfall(sod) samples. 10 water samples.

i Permanent Pasture W. of Co. Rd.

0.10/0.03 3

40 biased,10 unbiased soil samples.

19 %

Permanent Pasture E. of Co.

0.10/0.03 3

40 biased,10 unbiased sod samples.

Rd.19%, and S.of road to farm house Permanent Pasture E. of Co.Rd.

0.10/0.03 3

40 biased.10 unbiased sod samples.

19%, and N. of toad to farm house Sediment Storsge Area:

100% scan. 40 soil samples each (surface and Surface 0.17/0.02 1

subsurface), exposure rate each surface sample.

Subsurface 0.44/0.09 Goose Qudi Ditch 0.38/0.07 Non-Suspect, All sediment has been removed from this area.

(Prior to Sedsment Affected

> 1000 measurements for total and removable Removal) acovity, jice below for details of survey requirements.

2 The South Marsh was combined with the North Marsh and Irrigation Ditch 2 since physical characteristics and potential for residual radioactivity are similar.

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FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209

)

THE LIQUID EFFLUENT PATHWAY REVISION 0 j

The Goosequill Ditch will be surveyed differently from the survey units described above due to the construction of the ditch which consists primarily of a concrete liner. The ditch has been cleaned to remove nearly all vegetation, sediment and debris. Once the Goosequill Ditch is reasonably dry, it will be surveyed similar to a non-suspect affected surface / structure survey unit. The f' mal configuration of the Goosequill Ditch will present only a low potential for residual activity because the activity is confined primarily to the sediment, which will be removed prior to survey Measurement locations will be selected at a minimum frequency of 1 per 20 square meters along the entire length of the ditch. At each measurement location a scan survey for total surface activity will be performed over a minimum of I square meter of the surface, concentrating on the most suspect surfaces (e.g., bottom of ditch & water lines). Locations of elevated activity will be marked on the j

surface. At each measurement location, measurements for total and removable activity will be collected at the bottom center-line of the ditch, and approximately (at the water line) one meter up each side from the bottom center-line. Additional measurements for total and removable activity will be collected at any locations where the scan survey indicates elevated activity.

The site-specific guideline values for measurements of total and removable surface activity will be those appropriate for the balance of the site, and contained in FSV-TBD-201, Site-Specific Guideline Values for Surface Activity.

For instances where the measurements for total surface activity (scan or fixed point) are verified to be elevated in excess of the SGLV, exposure rate measurements will be collected at a distance of 1 meter from the center line of the ditch bottom. Regardless of the number of elevated measurement results, the frequency for these measurements is not intended to exceed.one measurement per four square meters.

7.4 Exposure Rate Measurements The localized areas of increased concentration are currently at very low concentrations (maximum of 5-7 total pCi/g), and the background exposure rate due to natural radioactivity j

and global fallout at FSV is large and v'ariable.

Experience gained during the characterization survey (at a time when activity concentrations were higher than those anticipated to be present during the Final Survey), showed the exposure rate measurements to be of limited use in identifying areas containing increased activity concentrations, or locations that may exceed 5 R/hr above the background exposure rate due to licensed material. Consequently, additional scan surveys and fixed-point measurements for exposure i

rate are planned for only a limited number of instances. These instances are:

1.

Areas with Classification 1 will receive a 100% scan of the area using a Nal detector in the rate meter mode, and a fixed point measurement at each sampling location.

1 2.

Areas with Classification 2 will receive a 10% (minimum) scan of the area using a t

Nal detector in the rate meter mode.

16 of 24 7

w

FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 3.

A fixed point measurement will be collected at a distance of 1 meter from locations of elevated surface activity (in excess of the SGLV for total surface activity) identified during the survey for total surface activity within the concrete liner of the Goosequill Ditch.

4.

Within the open-land grids defined as a result of investigating elevated concentrations, a 100% scan of the area will be performed using a Nal detector in the rate meter mode, and a fixed point measurement will be collected at each investigation sampling location.

The scan surveys for exposure rate will be performed in accordance with the procedure FSV-SC-FRS-I-105, Final Survey of Open Land Areas.

7.5 Investigation Action Levels and Actions Farm Pond or Farm Pond Outfall If an individual sediment or water sample result from the Farm Pond or Farm Pond Outfall l

exceeds the applicable investigation action level, then 10 additional samples will be collected in the same general area (s) as the initial sample. If the sample in question is from the outfall, the additional samples will be taken upstream and downstream from the original sample within a 100 square meter area. If the sample in question is from pond sediment, the additional samples will be collected approximately equally distributed within an approximate 100 square meter area.

The results will be evaluated using applicable averaging protocols from the Final Survey Plan. If the average of these samples exceed the concentration SGLV, additional sampling or remediation will be implemented.

All Other Liauid Effluent Pathway Areas If an individual sample result (excluding Farm Pond & Farm Pond Outfall samples) exceeds the applicable investigation action level, then a 10 by 10 meter grid, centered around the sample location will be established for investigation. This grid will be divided into 9, 3.3 by 3.3 meter grids and surface soil / sediment samples will be collected from the center of the remaining (outside) grids. In addition, a subsurface sample (6-12 inch region) will be collected at the original sample location. Sample results verified to be in excess of the investigation / reclassification action level will result in the survey unit, or portion of the survey unit, as being assigned to Class 1 and resurveyed. If the sample results are found i

to be less than the investigation / reclassification action level, then the additional results will be included in the data set for statistical evaluation and reporting purposes.

If an individual sample result (excluding Farm Pond & Farm Pond Outfall samples) exceeds 100% of the concentration SGLV, then a 10 by 10 meter grid, centered around the sample location will be established for investigation.

This grid will be divided into 9 (approximately 3.3 by 3.3 meter) grids and surface soil / sediment samples collected from the center of the remaining (outside) grids. In addition a subsurface soil / sediment sample will be collected at the original sample location. The results of the surface samples will be evaluated using the averaging protocols given in the Final Survey Plan.

17 of 24

d FINAL SUkVEY REQUIREMENTS FOR FSV.FRS-TBD-209

]

THE LIQUID EFFLUENT PATHWAY REVISION 0 j

If an individual sample result (excluding Farm Pond & Farm Pond Outfall samples) exceeds j

the concentration SGLV by greater than a factor of 3, then the results and the original sample location will be investigated to determine the boundaries of the elevated concentrations and will be remediated as required. The investigation survey will consist of, i

as a minimum, a 10 by 10 meter grid, centered around the sample location. The grid will be divided into 9, 3.3 by 3.3 meter grids and surface samples collected from the center of l

the remaining (outside) grids. After any required remediation, samples will be collected in

)

the remediated areas to verify that the individual samples results are less than the i

j concentration SGLV, and that the weighted average is less than the concentration SGLV.

In implementing the investigation surveys multiple grids may overlap. Multiple samples 4

j from the same grid are not required. If a sample was previously collected in a grid it may j

satisfy the current rampling requirements regardless of the sample location within the grid.

If natural landscape prevents the establishment of a 10 by 10 meter grid, an equivalent 4

survey area will be established around the sample location based on engineering evaluation.

5 i

Gooseauill Ditch The investigation and reclassification action levels for non-suspect surfaces and structums will be implemented. The msults of these survey measurements will be evaluated in j

accordance with the Final Survey Plan and existing procedures.

c

]

7.6 Evaluation of Investigation Measurement Results The results of additional measurements collected as a result of exceeding action levels or l

concentration SGLV will be evaluated to ensure that the individual sample concentration-to-j guideline value ratio does not exceed 3; and that the sample concentration-to-guideline value

[

ratio within the localized area does not exceed (100/A)u2, where A is the area of elevated concentration in square meters. If these conditions are satisfied, the weighted mean for the 2

100m containing the area of elevated activity will be tested in accordance with Draft

]=

NUREG/CR-5849, Equation 8-10 to ensure the weighted mean does not exceed the concentration SGLV as follows:

i i

"s M

"A s

y i

X,, * ~ [ X: I~[A

+ [ yn n A

g s i=1 k =1 k =1 4

1 Where:

L weighted mean including elevated area (s),

=

number of systematic and random measurements, n,

=

i systematic and random measurements at point I, xi

=

number of elevated areas, n,

=

Ag 2

fraction of 100m occupied by clevated area k,

=

area of elevated activity in area k.

i yi

=

18 of 24 4

.._,_.o

,, - _. _ - - _ _ -. _ ~, _

I FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD 209

. THE LIQUID EFFLUENT PATHWAY REVISION 0 7.7 Basis and Assumptions Used for the FSV RESRAD Exposure Scenario

'Ihe RESRAD exposure scenario developed for the FSV Liquid Effluent Pathway is intended to provide a realistic estimate of the potential doses to the general public following decommissioning. During the development of the RESRAD exposure scenario for FSV, the i

default parameter values included in the computer code, and the parameter values included l

in NRC Policy and Guidance Directive (PG-8-08) were reviewed to determine whether these l

values were appropriate for the conditions at FSV. The parameter values provided in either the RESRAD default data, or PG-8-08 for the Resident Farmer (Scenario C) were used, i

with the following exceptions:

i Table 7.5 RESRAD Parameter Values Used at FSV Parasseter Rafarence Value Basis Area of Cont.

RESRAD Default 1.00E+04 m2 Estimate of FSV total area impacted by Zone effluents discharged through the LEP.

p p

Thickness of RESRAD Default 2.0 m Radioactivity was deposited on the

+

Cont. Zone surface, and soil has not been disturbed.

Sample results indicate that significant subsurface contaminahon does not exist.

FSV Parameter 0.15 m For instances where contamination I

exceeds action levels in surface soil, I

subsurface samples are collected.

f length Parallel RESRAD Default 1.00E+02 m The entire length of the LEP was used as 1

to Aquifer a conservative estimate of the potential.

1.

FSV Parameter 2.65E+03 m i

Basic Radiatico RESRAD Default 30 mrem /yr The limit for the TEDE from soil is l

Dose Limit contained in the FSV Final Survey Plan.

The limit for the CEDE from water was i

FSV Parameter 10 mrem /yr (TEDE soil) adopted from EPA Guidance since a limit 10 mrem /yr (CEDE water) for surface water cannot be derived by RESRAD.

Annual RESRAD Default 1.00E+00 m/yr RESRAD Manual, Figure 9.1, Precipitation Distribution of Average Annual FSV Parameter 5.00E-01 m/yr Precipitation Rates Over US.

l 1rrigation/

RESRAD Default 2.00E41 m/yr, Overhead Estimate of emount, and actual mode of 8*

FSV Parameter 1.00E+00 m/yr Ditch Onsite Fraction PG-8-08 Defsult 0.21 This owner-controlled land has of Time Indoors historically been used as permanent

]

FSV Parameter 0.00 pamure, and wwld not reasonably be used as the location of a residence.

Onsite Fraction RESRAD Default 0.55 This land is infrequently occupied for of Time short periods of duration during the Outdoors FSV Parameter 0.126 growmg -n.

19 of 24 4

t

FINhL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 The model developed for FSV includes considerations regarding the projected use of the open land where the LEP is located. Of these considerations, the Onsite Fractions are the i

most significant. The assumptions used to select reasonable parameter values for the Onsite Fractions include the following:

1.

The open land including the LEP has historically been used as permanent pasture, and it is expected that this land will continue to be used as permanent pasture. The Onsite Fraction (outdoors) has been conservatively estimated to be 0.126 (annual average) to account for the time required for seasonal agricultural activities such as

}

inspection of fence lines, irrigation, and the cultivation and harvesting of a hypothetical garden. This value is based on 10.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per day,3.5 days per week, i

l during 30.1 weeks per year (April - October).

I 2.

The characterization and follow-up surveys demonstrated that, when averaged over i

100 square meters, the average concentrations in the localized areas of increased concentration do not exceed the concentration SGLV obtained when using only l

default parameter values for Scenario C.

Additionally, the characterization and follow-up surveys demonstrated that individual concentrations from the localized i

areas do not exceed 3 times the concentration SGLV obtained when using only default parameter values for Scenario C.

3.

The majority of the residual activity was deposited in localized areas during irrigation of the permanent pasture areas adjacent to, and immediately downgrade of the LEP. The flowpath of the irrigation water was dictated by the irrigation ditches, and by local topography, resulting in well-defined areas oflocalized activity.

I As such, the residual concentrations are not present in a configuration which results in an infinite or semi-infinite source as the potential for exposure, which further supports a reduction in the Onsite Fraction (outdoors). These locations have been selected for sampling, and the results of these samples are compared to the concentration SGLV.

4.

The potential doses for consumption of fruit, vegetables, grains and aquatic food were included in this evaluation using the default parameter values (RESRAD and/or PG-8-08). Inclusion of these pathways, and the use of the default parameter values at FSV, results in a slight over-estimate of these potential doses since these is no known consumption of these foods. However, these pathways and default values were used to ensure the potential doses from these pathways have been conservatively estimated.

5.

The default parameter values for ingestion and inhalation of soil have been used for this evaluation. The presence of the permanent ground cover (grassland pasture),

i and the absence of tilling activities in this area, result in a conservative estimate of the potential exposure from the ingestion and inhalation pathways. It is unlikely that agricultural economics would warrant alternative use of this land, such as tilling 20 of 24

FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 and/or planting of row-crops, and the use of alternate irrigation methods, which could increase the potential doses, but not beyond the range of doses included in this estimate.

An additional level of confidence is afforded to these assumptions, since this land is owned and controlled by PSCo, and no plans exist for alteration.

8.0 ALARA JUSTIFICATION The Liquid Effluent Pathway and surrounding open land areas have been thoroughly characterized to the extent that the localized areas of increased concentration are well-defined, including a range of expected concentration values. In consideration of our knowledge of the Liquid Effluent Pathway, the modified approach to the survey described in the Final Survey Plan includes an adequate number of measurements and investigative actions to demonstrate attainment of the release criteria.

An evaluation of previous and expected future land use has been performed, and a reasonable scenario has been defined for the potential exposure of the general public to i

residual concentrations.

An estimate of the decommissioning exposures associated with implementation of the current Final Survey Plan requirements has been presented which indicates that the potential exposure to decommissioning workers would exceed the exposure to the general public.

An estimate of the decommissioning costs associated with implementation of the current Final Survey Plan requirements has been presented which, in consideration of the above, justifies the use of this approach for survey of the Liquid Effluent Pathway.

8.1 Existing Condition of the Liquid Effluent Pathway and Surrounding Soil The administrative controls placed on the FSV liquid discharges have been adequate l

to prevent the radionuclide concentr'ations in th'e liquid effluent pathway and surrounding soils from exceeding the concentration SGLV. This is supported by the results of the characterization and follow-up characterization surveys.

The bounds of the localized areas of increased concentration are located adjacent to the LEP and are well-defined. The combined surface area of these localized areas is small relative to the balance of the LEP and surrounding open land areas.

The follow-up characterization survey samples were collected from biased locations, and showed no individual sample results in excess of the concentration SGLV. For localized areas containing the highest concentrations, the average within the 100 square meters was only about 10% of the average concentration SGLV.

21 of 24

\\

FINAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 1

A comparison of the results from the characterization and follow-up surveys shows a decrease in the residual concentrations which can be expected to continue due to radioactive decay and the effects of environmental weathering.

The survey design requirements are adequate to confirm our understanding of the

~

residual radioactivity in these localized areas of increased concentration, and to ensure with a high degree of certainty that no undetected areas of elevated concentration exist.

8.2 Basis for the FSV RESRAD Exposure Scenario i

The model developed for FSV includes considerations regarding the historical and projected future use of the open land where the LEP is located.

1 The open land including the LEP has historically been used as permanent pasture, i

and it is expected that this land will continue to be used as permanent pasture.

i The potential doses for consumption of fruit, vegetables, grains and aquatic food were included in this evaluation using the default parameter values (RESRAD and/or PG-8-08), and results in a conservative estimate of these potential doses.

4 The characterization and follow-up surveys demonstrated that the individual and i

average concentrations in the localized areas of increased concentration do not

]

exceed the concentration SGLV.

l The residual concentrations are not pretent in a configuration which results in an infinite or semi-infinite source as the potential for exposure, and would result in an average exposure far below 10 mrem /yr.

Agricultural economics would not warrant alternative use of this land, and the absence of tilling activities in this area results in a conservative estimate of the potential exposure from the ingestion and inhalatio'n pathways.

An additional level of confidence is afforded, since this land is owned and controlled by PSCo, and no plans exist for alteration.

8.3 Decommissioning Exposures to Implement Current Survey Requirements Based on our estimate of approximately 8,000 sample locations, and assuming an average of 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per sample (gridding, collecting, etc.), the cumulative exposure 3

to decommissioning workers would be 4.5 times the average exposure to members of the public during the entire first year following decommissioning.

l 22 of 24

4 FIIVAL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0 The cumulative exposure for this proposed survey plan would be approximately 7%

of the exposure to decommissioning workers that would be required to implement 4

the survey in accordance with the Final Survey Plan.

1 j

8.4 Impact on Decommissioning Costs to Implement Current Survey Requirements In accordance with the Final Survey Plan, the effluent pathway and parts of the surrounding areas would be classified as affected areas because of known radioactive 1

' contamination in the ditches and some surrounding areas. If these areas were surveyed as required by the Final Survey Plan, approximately 8,000 sample locations i

would be required. The industry-average fee for performing standard analysis on a single soil sample is in the range of $75-$120 per sample and does not account for the time required to collect the samples. This combined with the industrial risk would far outweigh any benefit of reducing dose to the general population.

i l

l For example 8,000 samples at $80 per sample would incur a cost of $640,000 for analysis alone.

Additional costs for survey measurements, sample collection, l

preparation for analysis, and evaluation and reporting of the additional data would j

bring the costs to well over $1.0 million.

l The cost estimate includes the following:

l 1.

Gridding the designated sample areas.

l 2.

Collecting and processing samples (drying and packaging).

3.

Counting and analyzing samples.

4.

Performing data analysis on results.

j 5.

Purchasing enough additional processing equipment to increase capacity in order to complete survey in 1996.

6.

Disposing of samples after analysis.

Based on historical and survey knowledge of the liquid effluent pathway and the associated source term and its minimuin potential linpact on the general population, a modified survey should be performed for the pathway and surrounding areas as indicated in Section 7.0. The cost for this proposed survey plan is approximately

$60,000 to $70,000 and will result in a cost savings of approximately $1.0 million.

9.0 CONCLUSION

i Based on the radiological history of the liquid effluent pathway, the controls that have been implemented, the documented results of the ODCM and the REMP, the additional scoping i

and characterization surveys, the minimal risk to the general public, and cost, the proposed final survey provides a reasonable approach to demonstrate that the effluent pathway and surrounding open land areas meet the criteria for release for unrestricted use.

J 23 of 24

FIN;AL SURVEY REQUIREMENTS FOR FSV-FRS-TBD-209 THE LIQUID EFFLUENT PATHWAY REVISION 0

10.0 REFERENCES

10.1 FSV Nuclear Station Decommissioning Project, Final Survey Plan for Site Release.

10.2 NRC NUREG-1500, Working Draft Regulatory Guide on Release Criteria for Decommissioning: NRC Staff's Draft for Comment.

1 10.3 QPF number FSV-286, dated 6/29/%, " Corrective Action Associated with Effluent Pathway t

and Surrounding Soil Sample Methodology"

\\

10.4 Annual Radioactive Effluent Release Repon for the Fon St. Vrain Nuclear Station, March 21,1996, P-96016.

i 10.5 Offsite Dose Calculation Manual (ODCM), DPP 5.4.2, Issue 7, DSRC Review 10/11/95.

10.6 Radiological Environmental Monitoring Program Summary Repon,1995, CSU.

10.7 Fort St. Vrain Liquid Effluent Pathway Characterization Report, May 1995, Rev. O, Approved 6/14/95.

10.8 FSV Liquid Effluent Pathway Follow-Up Sampling, Report, July,1996 Rev 0 (DRAFT) 10.9 Limiting Values of Radionuclide Intake and Air Concentration, and Dose Conversion Factors for Inhalation, Submersion and Ingestion, U.S. Environmental Protection Agency -

EPA-520,1988.

10.10 U.S. Depanment of Energy Residual Radioactive Material Guidelines (RESRAD), Computer Code Version 5.61, 8/28/95.

10.11 NRC Policy and Guidance Directive PG-8-08, Scenarios for Assessing Potential Doses Associated With Residual Radioactivity, May'1994.

i i

i 24 of 24

ATTACIDIENT 1 FSV RESRAD MODEL Table of Contents

&ad448a&444444444 Part 1: Mixture sums and Single Radionuclide Guidelines 4444444444444444444444444444444444444444444444444444444 Dose Conversion Factor (and Related) Parameter Sumary 2

Site-Specific Parameter Sumary 4

Summary of Pathway Selections 9

Contaminated Zone and Total Dose summary...

10 Total Dose Components Time = 0.000E+00...

1 11 i

Time = 1.000E+00..

12 Time = s.000E+00

)

13 Time = 1.000E+01 14 Time. 2.000s.01 4

is Time. s.00e. 01......:.........................

14 Time = 1.000E+02

)

17 Time = 1.000E+03...

18 Dose / Source Ratios Sunened over All Pathways...

19 Single Radionuclide Soil Guidelines.....................

19 Dose Per Nuclide Summed Over All Pathways..

21 Soil Concentration Per Nuclide 22 l

i i

l of 22 4

+

~

A'ITACIBfENT 1 FSV RESRAD MODEL 1

Dose conversion Factor {and Related) Parameter Susunary Files DOSFAC. BIN Current *

• Parameter

. Menu

• Parameter

• Value

• Default

• Name Addada44daaaaaaaaaaaaaadata44aaaaaaassadadaddadadaadadadaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaadadadassaaadagataa 31 ' Dose conversion factors for inhalation, mrem /pcia 51 ' Co-60

' 2.190C 04

• 2.190E 04

• DCF2( 1) 5-1

• Cs 134

• 4.630E-05

• 4.630E-05

• DCF2( 2) 21

• Cs-137+D

' 3.190E-05

• 3.190E-05 ' DCF2 ( 3) 31

• Eu-152

• 2 210E-04

• 2.210E-04

• DCF2 ( 4) 3-1

' Eu 154

• 2.860E-04

• 2.860E-04 ' DCF2 ( 6) 51

• Eu 155

• 4.140E-05

• 4.140E-05

• DCF2 ( 7) 1

• Fe 55

• 2.690E-06

• 2.690E 06

• DCF2( 8) 5-1

• Gd 152

' 2.430E-01

• 2.430E-01

• DCF2 ( 9)

B-1

• H3

• 6.400E-08

• 6.400E-04

• DCF2 (10) 51

• Sr 90*D 1.310E-03

• 1.3108 03

• DCF2 (11) f e

e Dal

• Dose conversion factors for ingestion, mrom/pci:

D-1

• Co-60 2.690E 05

• 2.690E-05

• DCF3 ( 1)

{

D1

• Cs 134

• 7.330E-05

• 7.3305-05

• DCF3 ( 2)

D1

• Cs-137+D

' 5.000E 05

• 5.000E-05

• DCF3 ( 3)

D-1

• Bu 152

• 6.400E-06

• 6.480E 06

• DCF3( 4)

D-1

• Bu-154

• 9.550E-06

• 9.5505-06

• DCF3( 6)

D-1

• Eu 155

' 1.5308-06

• 1.5305-06

• DCF3( 7)

D-1

• Fe 55

• 6.070E-07

• 6.070E-07

• DCF3 ( 8)

Dal

• Gd-152

• 1.610E-04

• 1.610E 04

• DCF3( 9)

D1

• H-3 6.4 00E-08 ' 6.4005-08 ' DCF3 (10)

D-1

• Sr-90+D

' 1.530E-04

• 1.530E-04

• DCF3(11) e e

D-34

• Food transfer factores D-34

• Co 65

, plant / soil concentration ratio, dimensionless

• 8.000E-02

• 8.000E-02 ' RTF( 1,1)

D-34

• Co-do

, beef / livestock-intake ratio, (pC1/kg)/ (pC1/d)

' 2.0005-02

• 2.000E 02

• RTF( 1,2)

D-34

• Co 60

, allk/ livestock intake ratio, (pci/L)/ (pci/dl

• 2.000E-03

• 2.000E-03

• RTF( 1,3)

D 34

• D-34

• Cs-134

, plant / soil concentration ratio, dimensionless

• 4.000E-02

• 4.000E-02

• RTF( 2,1)

D-34

• Cs 134

, beef / livestock intake ratio, (pC1/kg)/(pC1/d)

• 3.000E-02

• 3.000E-02

• RTF( 2,2)

D-34

• Cs-134

, milk / livestock-intake ratio, (pci/L) / (pci/d)

• 8.400E-03

• 8.000E-03

• RTF( 2,3)

D 34

• D 34

• Cs-137+D, plant / soil concentration ratio, dimensionless

• 4.000E-02

• 4.000E-02

• RTF( 3.1)

D-34

• Cs-137+D, beef / livestock intake ratio, (pci/kg)/(pci/d)

• 3.000E-02

• 3.0005-02

• RTF( 3.2)

D-34

• Cs 137+D, milk / livestock-intake ratio, (pC1/L)/(pC1/d)

' O.000E-03

• 8.000E-03

• RTF( 3,3)

D 34

• D-34

• Eu-152

, plant / scil concentration ratio, dimensionless

• 2.500E-03

• 2.500E-03

• RTF( 4.1)

D-34

• Bu 152

, beef / livestock intake ratio, (pC1/kg)/ (PCi/d)

• 2.000E-03

• 2.000E-03

• RTF( 4,2)

D-34

• Eu 152

, milk / livestock-intake ratio, (PC1/L)/ (PCi/d)

• 2.000E-05

• 2.000E 05

• RTF( 4,3)

D 34

• D 34

• Eu 154

, plant / soil concentration ratio, dimensionless

• 2.5005-03

• 2.500E-03

• RTF( 6,1)

D 34

• Eu 154

, beef / livestock-intake ratio, (pC1/kg)/(pci/d)

• 2.000E 03

• 2.000E 03

• RTF( 6,2)

D-34

• Eu 154

, milk / livestock intake ratio, (pC1/L)/ (pC1/d)

• 2.000E-05

• 2.000E-05

• RTF( 6,3)

D 34

• D 34 ' Bu 155

, plant / soil concentration ratio, dimensionless

' 2.5005-03

• 2.500E-03

• RTF( 7,1)

D-34

• Eu-155

, beef / livestock-intake ratio, (pci/kg)/(pci/d)

• 2.000E-03

• 2.0005 03

• RTF( 7,2)

D 34

• Eu 155, milk / livestock-intake ratio, (pci/L)/ (pci/d)

• 2.000E-05

• 2.000E-05

• RTr( 7,3)

D 34 2 of 22

^

NITACHMENT 1 FSV RESRAD MODEL Dose Conversion Factor (and Related) Parameter Summary (continued)

Files DOSFAC.31N Current *

• Parameter leanu

• Parameter Value

• Default

• Name 444as444444444444444&a44444444444444444444444&a444444444444444a&a444444444444444444444&

D 34

• Fe 55

, plant / soil concentration ratio, dimensionless

• 1.000E 03

• 1.000E-03

• RTF( 8,1)

D 34

• Fe-55

, beef / livestock intake ratio, (pC1/kg)/(pci/dl

• 2.000E 02

• 2.000E-02

• RTF( 8,2)

D 34

• Fe-55

, milk / livestock-intake ratio, (pC1/L)/(pci/dl 3.000E-04 ' 3.000E-04

• RTF( 8,3)

D 34

• D-34

• Gd-152

, plant / scil concentration ratio, dimensionless

• 2.500E 03

• 2.500E 03

• RTF( 9,1)

D 34

• Gd 152

, beef / livestock-intake ratio, (pci/kg)/(pci/d)

• 2.000E-03

• 2.000E-03

• RTF( 9,28 D-34

• Od-152

, milk / livestock-intaxe ratio, (pC1/L)/(PC1/d)

• 2.000E-05

• 2.000E 05

• RTFI 9,3) p-34 e

e D-34

• K 3

, plant / soil concentration ratio, dimensionless

• 4.800E+00

• 4.800E+00 ' RTF(10,1)

D-34

• M 3

, beet / livestock intake ratio, (pci/kg)/IpC1/dl

• 1.200E-02

• 1.200E 02

• RTF(10,2) t D 34

• M 3

, milk / livestock-intake ratio, (pci/L)/(pci/d)

• 1.000E-02

• 1.000E-02

• RTFt10,3)

D-34 *

• +

- D-34

• St 90+D, plant / soil concentretion ratio, dimensionless

• 3.000E-01

• 3.000E 01

• RTF(11,1)

D 34

• Sr 90+D, beef / livestock-intake ratio, (pC1/kg)/(pC1/d)

• 8.0005-03

• 8.000E-03

• RTF(11,2)

D 34

• St 90+D, milk / livestock-intake ratio, (pCi/L)/(pci/d)

• 2.0005-03

• 2.000E-03

• RTF(11,3) e D5

• Bioaccumulation factors, fresh water, I./kg:

I D5

• Co 40

, fish

• 3.000E+02

• 3.000E+02

• BIDFAC( 1,1)

D-5

• Co 60

, crustacea and mollusks

• 2.000E+02

• 2.000E+02

• BIOFAct 1,2)

D-5 D-5

• Cs 134

, fish

• 2.000E+03

• 2.000Ee02

• BIOFAC( 2,1)

D-5

• Cs 134

, crustacea and mollusks

• 1.000E+02.' 1.000E+02

• BIOFACI 2,3)

D-5 D5

• Cs 137+D, fish

• 2.000E+03

• 2.000E+03

• 310 FACI 3,1)

D-5

• Cs 137+0, crustacea and mollusks

• 1.000E+02

• 1.000E+02

• BIOFAC( 3,2)

D5

• D5

• Eu-152

, fish

• 5.000E*01

• 5.000E+01

• BIOFACI 4.1)

D-5

• Bu 152

, crustacea and mollusks

• 1.000E+03

• 1.000E+03 ' 310FAC( 4,2)

D.5 j

D5 ' Eu-154

, fish

• 5.000E+01

• 5.000E+01

• 310FAC( 6,1)

I D-5

• Eu 154

, crustacea and mollusks

• 1.000E+03

• 1.000E+03

• 310FAC( 6,2) p.5 D5

• Eu 155

, fish

~

• 5.000E+01

• 5.000E+01

• BIOFAC( 7,1)

D-5

• Su-155

, crustacea and mollusks

• 1.000E+03

• 1.000E+03

• BIOFAC( 7,2) p.5 D5

• Fe 55

, fish

• 2.000E+02 ' 2.000E+02

• BIDFAct 8,1)

D5

• Fe 55

, crustacea and molluska

• 3.200E+03

• 3.200E+03

• BIOFACI 8,2)

D5

• D-5

• Gd 152

, fish

• 2.500E+01 + 2.500B+01

• BIOFACI 9.1)

D-5

• G4-152

, crustacea and mollusks

• 1.000E+03

• 1.000E+03

• BIOFAC( 9,2)

D.5 D-5

• K3

.. fish

• 1.000E+00

• 1.000E+00

• BIOFAC(10,1)

D5

• M-3

, crustacea and mollusks

• 1.000E+00

• 1.000E+00

• BIOFAC(10,2) p.5 D-5

• sr 90+D, fish

• 6.000E+01

• 6.000E+01 ' 310FAC(11,1)

D5

• Sr 90+D, crustacea and mollusks

• 1.000E+02

• 1.000E+02

• 310FAC(11,2) 3 of 22

l ATTAClutENT 1 e

FSV RESRAD MODEL e

a Site-Specific Parameter Susanary e

User Used by RESRAD

' Parameter Menu

• Parameter Inout Default

• (If different from user input)

Name 4444444a48444444448844444444444a444444845ad444444444444441444&a44diadiadidaaaadiaiaisiaideiadaiaadidi RO11

• Area of contaminated zone (m"2)

• 2.073E+05

• 1.000E+04

• ARIA R011

• Thickness of contaminated zone (m)

• 1.500E 01 ' 2.000E+00 *

• THICK 0 R011 ' Length parallel to aquifer flow (m)

• 2.650E+03

• 1.000E+02

• LCZPAQ R011

• Basic radiation dose limit (mrem /yr)

• 1.000E+01 ' 3.000E+01 *

• BRDL RO11

• Time since placement of material lyr)

• 0.000E+00

• 0.000Ee00 '

' TI Roll

• Times for calculations (yr)

• 1.000E+00

• 1.000E+00

• T( 2)

Roll ' *imes for calculations (yr)

• 5.000E+00

• 3.000E+00

• T( 3)

Roll

• Times for calculations (yr)

' 1.000E*01 ' 1.000E+01 *

• T( 4)

R011

• Times for calculations (yr)

' 3.000E+01 ' 3.000E+01

• T( 5)

Roll ' Times for calculations (yr)

• 5.000E+01

• 1.000E+02 *

• T( 6)

R011

• Times for calculations (yr)

• 1.000E+02

• 3.000E+02 *

• T( Tl Roll

• Times for calculations (yr)

• 1.000E+03

• 1.000E+03 *

• T( 8)

R011

• Times for calculations (yr)

' not used

• 0.000E+00 *

• Tt 9)

Roll

• Times for calculations (yr)

' not used

• 0.000E+00 *

• T(10) e e

e e

R012

• Initial principal radionuclide (pC1/g): Co-60

• 1.000E+00

• 0.000E+00 *

• S1( ll R012

• Initial principal radionuclide (pci/g): Cs 134

• 1.000E+00 ' 0,000E+00 *

• S1( 21 1

R012

• Initial principal radionuclide (pC1/g): Cs-137

• 1.000E+00

• 0.000E+00

• 1

• 51( 3)

]

RO12

• Initial principal radionuclide (pC1/g): Eu-152

• 1.000E+00

• 0.000E+00 *

• S1( 4)

R012

• Initial principal radionuclide (pci/g): Eu 154

• 1.000E+00

• 0.000E+00 *

• S1( 61 R012

• Initial principal radionuclide (pci/g): Eu.155 ' 1.000E+00

• 0.000E+00 *

• S11 7)

RO12

• Initial principal radionuclide (pci/g): Fe-55

• 1.000E+00

• 0.000E+00 *

• S1( ll R012

• Initial principal radionuclide (pci/g): Gd-152

• 1.000E+00

• 0.000E+00 *

• S1( 91 R012

• Initial principal radionuclide (pci/g):

H-3

• 1.000E+00 ' O.000E+00 *

• S1(101 R012

• Initial principal radionuclide (pci/g): Sr-90

' 1.000E+00

• 0.000E+00 *

• S1(111 R012

• Concentration in groundwater (pC1/L): Co-60

• not used

• 0.000E 00 *

• W1( 1)

R012

• Concentration i,n groundwater (pC1/L): Cs-134

• not used

• 0.000E+00 *

• Wit 2)

R012

• Concentration in groundwater (pC1/L): Cs-137

• not used

• 0.000E+00

• Wil 3)

RO12

• Concentration in groundwater (pC1/L): Eu-152

• not used

• 0.000E+00 *

• W1( 4)

R012

• Concentration in groundwater (pCi/L): Eu-154

• not used

• 0.000E+00 *

' W1( 6)

R012

• Concentration in groundwater (pci/L): Eu-155

• not used

• 0.000E+00 *

• W1( 7)

R012 ' Concentration in groundwater (pC1/L): Fe-55

• not used

• 0.000E+00 *

• Wil 8)

R012

• Concentration in groundwater (pci/L): Gd 152

• not used

• 0.000E+00 '

• Wil 9)

R012

• Concentration in groundwater (PCi/L):

H-3

• not used**

• O. 000E+00 "

• W1(10)

R012

• Concentration in groundwater (pci/L) : Sr.90

• not used

• 0.000E+00 *

' W1(11) e e

e e

R013

• Cover depth (m)

• 0.000E+00 ' O.000E+00 *

• COVERO RO13

• Density of cover material (g/ca"3)

' not used

• 1.500E+00 *

• DENSCV R013

• Cover depth erosion rate (m/yr)

• not used

• 1.000E-03 *

• VCV R013

• Density of contaminated mone (g/ca"3)

• 1.500E+00 ' 1.500E+00 *

• DENSCZ R013

• Contaminated zone erosion rate (m/yr)

• 1.0005-03

• 1.000E-03 *

• VCZ R013

• Contaminated zone total porosity

• 3.000E-01

• 4.000E-01 *

• TPCZ R013

• Contaminated zone effective porosity

• 2.000E-01 ' 2.000E-01 *

• EPCZ R013

• Contaminated zone hydraulic conductivity (m/yr)

• 1.000E+01

• 1.000E+01 *

• HCCZ R013

• Contaminated zone b parameter

• 5.300E+00

• 5.300E+00 *

• BCZ A013

• Humidity in air (g/ca"3)

' 8.000E+00

• 8.000E+00 *

• HUMID R013

• Evapotranspiration coefficient

• 5.0003 01

• 5.000E-01 *

' EVAPTR R013

• Precipitation (m/yr)

• 5.000E-01

• 1.000E+00 *

• PRECIP R013

• Irrigation (m/yr)

• 1.000E+00

• 2.000E-01 *

• RI R013

• Irrigation mode

• ditch

• overhead *

• IDITCH R013

• Runoff coefficient

' 2.000E-01

• 2.000E-01 *

• RUNCFF 4 of 22 i

i I

i

~.

ATTACIB1ENT 1

+

e FSV RESRAD MODEL A

?

Site-specific Parameter Summary (continued)

User Used by RESRAD

• Parameter Menu

• Parameter Input Default

• (If different from user input)

Name A444444444444444 d444444444444444444444444444444444 d 444444444444d d444444444444444444 R013

• Watershed area for neasby stream or pond (m"2)

• 1.000E+06

• 1.000E+06 *

• WAREA 2013

• Accuracy for water / soil computations

• 1.000E-03

• 1.000E-03 *

• EPS t

e e

e e

R014

• Density of saturated zone (g/cm"3)

• 1.500E+00

• 1.500E+00 *

• DENSAQ A014

• Saturated zone total porosity

• 3.000E-01

• 4.000E-01 *

• 'IPSE R014

• Saturated zone effective porosity

• 2.000E-01

• 2.000E-01 *

• EPSZ Role

• Saturated zone hydraulic conductivity (m/yr)

• 1.000E+02 ' 1.000E+02 *

• HCSZ Role

• Saturated zone hydraulic gradient

• 2.000E-02

• 2.0005-02 *

• HOWT R014

• Saturated zone b parameter

• 5.300E+00

• 5.300E+00 *

• BSZ R014

• Water table drop rate (m/yr)

• 1.0005-03

• 1.000E-03 *

• WT t

R014

• Well pump intake depth (a below water table)

• 1.000E+01

• 1.000E+01 *

• DWIBw!

Role ' Model Nondispersion (ND) or Mass Balance LMB)

• ND

• ND

• MODEL Rold

• Nell pumping rate (m"3/yr)

• 2.500E+02 ' 2.500E+02 *

• UN e

e e

e

)

e R015

• Number of unsaturatg/ h w strata

• 1

• 1

• NE I

2015

• Unsat. sone 1, thir W 1 Dl 4.000E+00

• 4.000E+00 *

• Mll) j A015

• Unsat. sone 1, soil 6 n V (g/cm"3 )

• 1.500E+00

• 1.500E+00 *

• DENSUZ(1)

)

R015

• Unsat. sone 1. totai p;.two y

• 3.0003-01

• 4.000E-01 '

2.000E-01

• 2.0005-01 *

.* TPUZ(1) 2015

• Uhsat. sone 1, offactive porosity

\\

• EPUZ(1)

ROIS

• Unset. sone 1, soil-specific b parameter

• 5.300E+00

• 5.300E+00 *

• BUZ(1)

R015

• Unsat. sone 1, hydraulic conductivity (m/yr)

• 1.000E+01

• 1.000E+01 *

• HCUE(1) e R016 ' Distribution coefficients for Co 60 R016

• Contaminated zone (ce "3/g).

• 1.000E+03

• 1.000E+03 *

• DorJCC( 1)

R016

• Unsaturated zone 1 (ca"3/g)

• 1.000E+03

• 1.000E+03 *

• DCNUCU( 1,1)

R016

• Saturated zone (ce "3/g)

• 1.000E+03

• 1.000E+03 *

• DCNUCSt 1)

R016

• Leach rate (/yr)

• 0.000E+00

• 0.000E+00

• 3.111E-03

• ALEACH( 1)

R016

• Solubility co'stant n

• 0.000E+00

• 0.000E+00

• not used

• SOLUBKt 1) e e

e R016

• Distribution coefficients for Co-134 R016

• Contaminated zone (ce " 3/g)

• 1.000E+03

• 1.000E+03 *

• DOrJCC( 2)

R016

• miseturated zone 1 (ce"3/g)

• 1.000E+03

• 1.000E+03 *

• DCNUCU( 2,1) l R016

• Saturated zone (cm**3/g)

• 1.000E+03 ' 1.000E+03 *

• DCNUCSi 2)

R016

• f4ach rate (/yr)

• 0. 000E+00 ** 0.000E+00 *

• 3.1115-03

• ALEACH( 2)

R016

• Solubility constant

• 0.000E+00

• 0.000E+00

• not used

• SOLUBK( 2) e e

e e

Rold ' Distribution coefficients for Cs 137 R016

• Contaminated zone (ce " 3/g)

• 1.000E+03

• 1.000E+03 *

• DCNUCCl 3)

A016

• Unsaturated zone 1 (ce"3/g)

• 1.000E+03 ' 1.000E+03 *

• DCNUCUt 3,1)

R016

• Saturated zone (cm**3/g)

• 1.000E+03

• 1.000E+03

• i R016

• Leach rats (/yr)

• D3UCS( 3)

• 0.000E+00

• 0.000E+00

• 3.1115 03

• ALEACH( 31 j

R016

• Solubility constant

• 0.000E+00

• 0.000E+00 not used

• SOLUBK( 3)

R016

• Distribution coefficients for Eu 152 R016

• Contaminated zone (ca"3/g)

• -1.000E+00 '.1.000E+00 '

5.756E+02 DCNUCCt 4)

R016

• Unsaturated zone 1 (ce"3/g)

• -1.000E+00

• 1.000E+00 '

5.758E.02

• DCNUCUt 4,1) 5 R016

• Saturated zone (ce"3/g)

' 1.000E+00 *-1.000E+00

• 5.758E+02

• D G UCSI 4) 1 R016

• Leach rate (/yr)

' O.000E+00

• 0.000E+00 '

5.402E 03

• ALEACH( 4)

R016

• Solubility constant

• 0.000E+00

• 0.000E+00

• not used

• SOLUBK t 4 )

1 5 of 22 4

~

ATTACHMENT 1 FSV RESRAD MODEL d

Site Specific Parameter Summary (continued) i

• User Used by RESRAD

• Parameter Menu '

Parameter Input Default IIf different from user input)

Name did a d e idid a d a d aiai aidida d ada d da&d 44444441& a 44444431444144444443 & dadad &&diadadidid iadiadisiad &&d&aadi R016

• Distribution coefficients for Eu-154 R016

• Contaminated zone (cm"3/g)

• -1.000E+00 *-1.000E+00

• 5,758E+02

' D O UCC( 6)

R016

• Unsaturated zone 1 (cm " 3/g)

• -1.000E+00 *-1.000E+01

• 5.758E+02

• DCNUCU( 6.1)

R016

• Saturated zone (cm"3/g)

'-1.000E+00 ' 1.000E+00

• 5.758E+02

• DCNUCS( 6)

R016

• Leach rate (/yr)

' O.000E+00

• 0.000E+00

• 5.402E-03

• ALEACH( El R016

• Solubility constant

• 0.000E+00 ' O.000E+00

• not used

• SOLUBK( 61 e

e e

e e

R016

• Distribution coefficients for Eu-155 R016

• Contaminated zone (em "3/g)

• -1.000E+00 *-1.000E+00

• 5.758E+02

• DCNUCCI 7)

R016

• Unsaturated zone 1 (cm**3/g)

'-1.000E+00 '-1.000E+00

• 5.758E+02

• DC38UCU( 7.1)

R016

• Saturated zone (ce"3/g)

'-1.000E+00 '-1.000E+00

• 5.758E+02

• DCNUCSI 7)

R016

• Leach rate (/yr)

• 0.000E+00

• 0.000E+00

• 5.402E-03

• ALEACH( 7)

R016

• Solubility constant

• 0.00CE+00

• 0.000E+00

• not used

• SOLUBK( 7) e e

e e

e R016

• Distribution coefficients for re 55 RQ16

• Contaminated zone (cm"3/g)

• 1.000E+03

• 1.000E+03 *

• DCNUCC( 8)

R016

• Unsaturated zone 1 (cm"3/g)

• 1.000E+03

• 1.000E+03 *

• DCNUCUt 8.1)

R016

• Saturated zone (cm "3/g)

• 1.000E+03 ' 1.000E+03 *

• DCNUCS i 8 )

R016

• Leach rate (/yr)

• 0.000E+00 ' O.000E+00

• 3.111E-03

• ALEACH( 8)

R016 ' Solubility constant

• 0.000E+00

• 0.000E+00

• not used

• SOLUBEf 81 e

e e

R016

• Distribution coefficients for Gd 152 R016

• Contaminated zone (cm"3/g)

• 1.000E+00 '-1.000E+00

• 5.758E+02

• DCNUCCI 9)

R016

• Unsaturated zone 1 (cm"3/g)

• 1.000E+00 '-1.000E+00

• 5.758E+02

• DCCCUt 9.1)

R016

• Saturated zone (cm**3/g)

• -1.000E+00 *-1.000E+00

• 5.758E+02

• DCNUCS( 9)

R016

• Leach rate (/yr)

• 0.000E+00

• 0.000E+00

• 5.402E 03

• ALEACHf 9)

R016

• Solubility constant

• 0.000E+00

• 0.000E+00

• not used

• SOLUBEt 9) e e

1 R016

• Distribution coefficients for H-3 R016

• Contaminated zone (cm**3/gl

• 0.000E+00

• 0.000E+00 '

• DCNUCC(10)

R016

• Unsaturated zone 1 (cm"3/g)

• 0.000E+00 ' O.000E+00 *

• DGUCU110.1)

R016

• Saturated zone (cm"3/g)

' O.000E+00

• 0.000E+00 *

• DCNUCS(10)

R016

• 14ach rate (/yr)

• 0.000E*00 ' O 000E+00

• 1.891E+01

• ALEACHl10)

R016

• Solubility constant

0. 000E+00 *

• 0. 000r+00 "

not used

• SOLUBE(10) e e

e e

R016

• Distribution coefficients for Sr-90 R016

• Contaminated zone (ce"3/g)

• 3.000E+01 ' 3.000E+01 *

• DCNUCC(111 R016

• Unsaturated zone 1 (ce"3/g)

• 3.000E+01

• 3.000E+01 *

• DCNUCU(11.1)

R016

• Saturated zone (ca"3/g)

• 3.000E*01

• 3.000E+01 *

• DGUCS(11)

R016

• Imach rate (/yr)

• 0.000E+00 ' O.000E+00

• 1.031E-01

• ALEACH(11)

R016

• Solubility constant

• 0.000E+00

• 0.000E+00

• not used

• SOLUBE(11) e e

e e

e R017

• Inhalation rate (m"3/yr)

• 1.051E+04

• 8.400E+03 *

• IMHALR R017

• Mass loading for inhalation (g/m"3)

' 2.000E 04 ' 2.000E-04 *

• MLINH R017

• Dilution length for airborne dust, inhalation (m)* 3.000E+00

• 3.000E+00 *

• tJ4 RO17

• Exposure duration

• 3.000E+01

• 3.000E+01 *

• ED R017

• Shielding factor, inhalation

' 5.000E-01

• 4.000E 01 *

• SHF3 R017

• Shielding factor, external gamma

' 3.3005-01

• 7.000E-01 *

• SHF1 R017

• Fraction of time spent indoors

• 0.000E+00 ' 5.000E 01 *

• FIND R017

• Fraction of time spent outdoors (on site)

• 1.260E-01

• 2.500E-01 *

• FOTD R017

• Shape factor flag, external gamma

' 1.000E+00

• 1.000E+00

• 1 shows circular AREA.

• FS 6 of 22

d A'ITACHMENT 1 i

FSV RESRAD MODEL 4

i Site-specific Parameter Summary (continued) l 5

User

• Parameter Used by RESRAD j

Menu * -

Parameter Input Default *

(If different from user input)

Name l

444444444444444444444444444444444444444444444644444444444444444aadaad adad ad&444444444444adatad &&aaaa44aa 4444444444&aaaaa 3017

• Radii of shape factor array (used if FS - 1)s l

RO17

• Outer annular radius (m), ring 1:

' not used

• 5.000E+01 *

• RAD, SHAPE ( 1) 1, R017

• 0 uter annular radius (m), ring 2n

• not used

• 7.071E*01 *

• RAD,SHAPEt 2) l Ro1?

• Outer annular radius - (m), ring 3:

• not used

• 0.000E+00 *

' RAD SHAPE ( 3)

A017

• Outer annular radius (m), ring 4:

• not used

• 0.000E,00 *

' RAD, SHAPE ( 4)

]

R017 ' - Outer annular radius (m), ring 5:

• not used

• 0.000E+00 *

• RAD, SHAPE ( 5) 4 2017

• Outer annular radius (m), ring 6:

• not used

• 0.000E+00 *

• RAD SHAPE ( 6)

[

i R017 * - Outer annular radius (m), ring 7:

• not used

• 0.000E+00 *

' RAD SHAPE ( 7) 2017

• Outer annular radius (m), ring 4:

• not used

• 0.000E+00

• d

• RAD,5HAPE( 8) i A017

• Outer annular radius (m), ring 9:

• not used

• 0.000E+00

• f

• RAD, SHAPE ( 9) 1 R017 ' Outer annular radius (m), ring los

• not used

• 0.000E+00 *

• RAD, SHAPE (10)

[

R017

• Outer annular radius (m), ring 11:

' not used

• 0.000E+00 *

• RAD, SHAPE (11)

R017

• Outer annular radius (m), ring 12:

• not used 0.000E*00 '

• RAD, SHAPE (12) e-e e

]

R017

• Fractions of annular areas within AREA:

d R017

• Ring 1

• not used

• 1.000E+00 *

• FRACA( 1) i 2017

• Ring 2

• not used

• 2.732E-01 *

• FRACA( 2)

R017

• Ring 3

• not used

• 0.000E+00 *

• FRACA( 33 l

R017

• Ring 4

• not used

• 0.000E+00 *

' FRACA( 4)

A017

• Ring 5

• not used

• 0.0005,00 *

• FRACA( 5)

Rol?

• Ring 6

• not used

• 0.000E+00 '

• FRACA( 6)

)

R017

• Ring 7

• not used

• 0.000E+00 *

• FRACA( 7) i R017

• Ring 8

' not used

• 0.000E+00 *

• FRACA( 8)

[

R017

• Ring 9

• not used

• 0.000E+00 *

• FRACA( 9)

R017

• Ring 10

• not used

• 0.000E+00 *

• FRACA(10)

Ro1?

• Ring 11

• not used

• 0.000E+00 *

' FRACA(11)

}.

R017

• Ring 12

• not used

• 0.000E+00 *

' FRACA(12) e e

e e

e R018

• Fruits, vegetables and grain consumption (kg/yr)

• 1.660E+02

• 1.600E+02 *

• DIET (1)

ROIS

• 14afy vegetable consumption (kg/yr)

• 1.100E+01

• 1.400E+01 *

• DIET (2)

RO18

• Milk consumption (L/yr)

• 1.000E+02 ' 9.200E+01 *

• DIET (3)

I R010

• Meat and poultry consumption (kg/yr)

• 6.300E+01

• 6.300E+01 *

• DIET (4) i I

2018

• Fish consumption (kg/yr)

' 5,400E+00

• 5.400E+00 *

• DIET (5) 2010

• Other seafood consumption (kg/yr)

' 9.0005-01-* 9.0005-01 *,

d

• DIET (6)

)

2018

• Soil ingestion rate (g/yr)

• 1.825E+01 ' 3.650E+01 *

• SOIL R010

• Drinking water intake (L/yr)

• 5.100E+02

• 5.100E+02

• 4

• DWI R018

• Contamination fraction of drinking water

• 1.000E+00

• 1.000E+00 *

' FDW R018

• Contamination fraction of household water

• not used

• 1.000E+00 *

• FMHN 2018

• Contamination fraction of livestock water

• 1.000E+00 ' 1.000B+00 *

' FLN R018

• Contamination fraction of irrigation water

• 1.000E+00 ' 1.000E+00 *

' FIRW R010

• Contamination fraction of aquatic food

• 5.0005-01 ' 5.000E-01 *

• FR9 a

R018 t Contamination fraction of plant food

• -1

• -1 0.500E+00

' FPLAFf 2018

• Contamination fraction of meat

'1

'-1 0.100E+01

• FMEAT A018

• Contamination fraction of allk

• -1

• 1 0.100E+01

• FMILK e

e e

l l

Rolt

• Livestock fodder intake for meet (kg/ day)

• 6.000E+01 ' 6.000E+01 *

• LFIS R019

• Livestock' fodder intake for tilk (kg/ day)

' 5.500E+01

• 5.500E+01 *

• LF16 R019

• Livestock water intake for meat (L/ day)

' 5.000E+01

• 5.000E+01 *

• LNIS j - ROIS

• Livestock water intake for milk (L/ day)

• 1.600E+02

• 1.600E+02 *

' LMI6 R019

• Livestock soil intake (kg/ day)'

' 5.000E-01

• 5.000E-01 *

• LSI R019

• Mass loading for toliar deposition (g/m"3)

• 1.0005-04

• 1.000E 04 *

• MLFD 7 of 22

ATTACIB1ENT 1 FSV RESRAD MODEL s *

• Site. Specific Parameter Summary (continued)

• User Used by RESRAD Parameter Menu '

Parameter Input

• Default * (If different from user input)

Name diaddadad484444444444dai4Adi44A444884448841448144414114444444484444844844484443444144448444444444ddi441A R019

• Depth of soil mixing layer (m)

• 1.500E-01

• 1.500E-01 *

• DM R019 ' Depth of roots (m)

• 9.000E 01

• 9.000E-01 *

• DROOT R019

• Drir. king water fraction from ground water

• 1.000E+00 ' 1.000E+00 *

• FGWDW ROIS

• Household water fraction from ground water

' 1.000&+00

• 1.000E+00 *

• FGWHH A019

• Livestock water fraction from ground water

• not used

• 1.000E 00 *

• FGWLW R019

• Irrigation fraction from ground water

• 1.000E+00

• 1.000E+00 *

• FGWIR i

C14

• C-12 concentration in water (g/cm**3)

• not used

• 2.000E-05 *

• C12WTR j

C14

• C-12 concentration in contaminated soil (g/g)

' not used

• 3.000E-02 *

• C12CZ C14

• Fraction of vegetation carbon from soil

• not used

• 2.000E-02 *

• CSCIL I

C14

• Fraction of vegetation carbon from air

• not used

• 9.0001-01 *

• CAIR C14

• C-14 evasion layer chickness in soil (m)

' not used

• 3.000E.01 *

• DMC C14

• C-14 evasion flux rate from soil (1/sec)

' not used

• 7.000E-07 *

• EVSN C14

• C.12 evasion flux rate from soil (1/sec)

' not used

• 1.000E-10 *

• REVSN C14

• Fraction of grain in beef cattle feed

• not used

• 8.000E-01 *

• AVFG4 C14

• Fraction of grain in milk cow feed

• not used

• 2.000E-01 *

• AVFC5 e

STC2

• Storage times of contaminated foodstuffs (days):

STOR

• Fruits, non leafy vegetables, and grain

• 1.400E+01

• 1.400E+01 *

• STOR T(11 STOR *

!aafy vegetables

• 1.000E+00

• 1.000E+00 *

• STOR_T(2)

STOR

• Milk

• 1.000E+00

• 1.000E+00 *

• STOR.T(3)

STOR

• Meat and poultry

• 2.000E+01 ' 2.000E+01 *

• STCR_T (4 )

STOR

• Fish

• 7.000E+00

• 7.000E+00 *

• STOR.T(5)

S'ItQ

• Crustacea and mollusks

• 7.000E+00

• 7.000E+00 *

• STOR T(6)

STOR

• Well water

• 1,000E+00

• 1.000E+00 '

• STOR,T(7)

STOR

• Surface water,

• 1.000E+00

• 1.000E+00 *

• STOR T(8)

STOR

• Livestock fodd'er

• 4.500E+01

• 4.500E+01 *

• STOR,T(9) e e

R021

• Thickness of building foundation (m)

' not used

• 1.500E-01 *

• F140R R021

• Bulk density of building foundation (g/cm**3)

• not used

• 2.400E+00 *

• DENSFL R021

• Total porosity of the cover material

• not used

• 4.000E-01 *

• TPCV R021

• Total porosity of the building foundation

• not used

• 1.000E-01 *

• TPFL R021

• Volumetric watas content of the cover material

• not used

• 5.000E-02 ' *

• PN20CV A021

• Volumetric water content of the foundation

• not used

• 3.000E-02 *

• PK20FL R021

• Diffusion coef ficient for radon gas (m/sec):

R021

• in cover material

• not used

• 2.000E-06 *

• DIFCV A021

• in foundation material

' not used

• 3.000E-07 *

• DIFFL R021

• in contaminated sono soil

• not used

• 2.000E-06 *

• DIFCZ R021

• Redon vertical dimension of mixing (m)

' not used

• 2.000E+00 *

• IMIX R021

• Average annual wind speed (m/sec)

• not used

• 2.000E+00 *

• WIND R021

• Average building air exchange rate (1/hr)

' not used

• 5.000E.01 *

• REKG R021

• Height of the building (room) is)

• not used

• 2.500E+00 *

• HRM R021

• Building interior area factor

• not used

• 0.300E+00 *

• FA1 R021

• Building depth below ground surface (m)

• not used

• -1.000E+00 *

• DMFL R021

• Eranating power of Rn-232 gas

' not used

• 2.500E-01 *

• EMANA(1) 3021

• Emanating power of Rn.220 gas

' not used

• 1.500E-01 *

• EMMIAl2) 8 of 22

1 ATTACHMENT 1 FSV RESRAD MODEL Summary of Pathway selections Pathway User Selection 544444444444444445di44444444444444444444444d44441a&

i 1 -- external gamma active f

2 -- inhalation (w/o radon)*

active 3 - plant ingestion active 4 -- meat ingestion active 5 -- milk ingestion active 6 -- aquatic foods active 7 -- drinking water active 8 -- soil ingestion active 9 -- radon suppressed 444444444444444444444444444444044444444444444444444 l

1 I

i i

9 of 22

ATTACHMENT 1 FSV RESRAD MODEL

+

Contaminated Zone Dimensions Initial Soil Concentrations, pC1/g Adaaaaaa&&daddadadadiadadada aaaaaaaaaaaadadadaaddaadadadaadada Area: 207300.00 square meters Co-60 1.000E+00 Thickness:

0.15 meters Cs-134 1.000E*00 Cover Depth:

0.00 meters Cs-137 1.000E+00 Eu 152 1.000E*00 d

Eu-154 1.000E+00 Eu-155 1.000E+00 Fe-55 1.000E+00 Gd-152 1.000E+00 H-3 1.000E+00 Sr-90 1.000E+00 Total Dose TDOSE(t), mres/yr i

Basic Radiation Dose ' Limit = 10 mrem /yr Total Mixture Sua M(t) = Fraction of Basic Dose Limit Received at Time (t) aaaaaaaaaaaaaaaaaaadidadadiaadiadadadadadadadadaadadaadaddadadadaaaaaaaaaa t (years): 0.000E+00 1,000E+00 5.000E+00 1.000E+01 3.000E+01 5.000E+01 1.000E+02 1.000E+03 TDOSE(t):

6.376E+00 5.505E+00 3.335E+00 2.021E+00 5.090E-01 2.093E-01 3.006E-02 0.000E+00 M(t): 6.376E-01 5.505E-01 3.335E-01 2.0218 01 5.090E-02 2.093E-02 3.0065-03 0.000E+00 Maximuse TDOSEtt): 6.376E+00 mres/yr at t = 0.000E+00 years i

i 1

4 4

4 f

l 10 of 22

~

ATTACHMENT 1 FSV RESRAD MODEL 1<

Total Dose Contributions TDOSEli.p,t) for Individual Radionuclides (1) and Pathways (p)

As mres/yr and Fraction of Total Dose At t = 0.000E+00 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Redon Plant Meat Milk Soil Radio-4444444444444444 4444444444444444 4444444444444ad& 44444444444444&4 &&a&&ad&&&&&&

Nuclida eres/yr fract, mres/yr fract, mrem /yr fract.

mres/yr fract.

arem/yr fract.

arem/yr fract, mres/yr fract.

I 4444444 &&&644484 88aa&4 ad&&a&aSA 4444&a 4444&dd44 444444 444444444 aMaia 444444444 444 1

Co-60 1.706t+00 0.2676 5.762E-05 0.0000 0.000E+00 0.0000 3.161E-02 0.0050 4.691E-02 0.0074 6.5785-03 0.0 C3-134 1.05CE*00 0.1647 1.218E 05 0.0000 0.000E+00 0.0000 4.277E 02 0.0067 1.2745-01 0.0200 4.999E C2 137 3.502E 01 0.0596 8.3938-06 0.0000 0.000E+00 0.0000 2.951E-02 0.0046 9.004E-02 0.0141 3.469 Eu 152 7.5168 01 0.1188 5.815E-05 0.0000 0.000E*00 0.0000 2.4235 04 0.0000 4.316E-04 0.0001 6.794E-06 Bu 154 0.258E 01 0.1295 7.525E 05 0.0000 0.000E+00 0,0000 3.568E-04 0.0001 6.350E-04 0.0001 1.001E 05 0.0000 2.196E Eu 155 2.263E 02 0.0035 1.089E-05 0.0000 0.000E+00 0.0000 5,7048 05 0.0000 1.013E 04 0.0000 1.6035-06 0.0000 3.518E-06 0.0000 FF55 0.000E+00 0.0000 7.078E-07 0.0000 0.000E+00 0.0000 9,2285-06 0.0000 3.868E 04 0.0001 9.288E-06 0.0000 1.396E-06 0.0000 1 0d-152 0.000E+00 0.0000 6,394E 02 0.0100 0.000E+00 0.0000 6.032E 03 0.0009 1.076E-02 0.0017 1.6898-04 0.0000 3.702E 04 0.0001 H3 0.000E+00 0.0000 3.073E-03 0.0006 0.000E+00 0.0000 4.5785 03 0.0007 1.2745 03 0.0002.1.2345 03 0.0002 1 Sr-90 2.9112 03 0.0005 3.447E 04 0.0001 0.000E+00 0.0000 6.765E-01 0.1061 2.997E-01 0.0470 9.9248 02.0.0156 3 4444444 444444444 444444 444444444 444444. 444444444 444444 444444444 444444 444444444 M4444 4 Tttal 4.746E+00 0.7442 6.8385-02 0.0107 0.000E+00 0.0000 7.917E-01 0.1242 5.777E 01 0.0906 1.9195-01 0.0301 1 i

Total Dose Contributions TDOSEfi.p,t) for Individual Radionuclides (i) and Pathways (p)

{

As arem/yr and Fraction of Total Dose At t = 0.000E+00 years 4

Water Dependent Pathways Nater Fish Radon Plant Meat Milk All Pathways +

Radio-Ad&&d&&&a&&&daad 6444444444444Aad 4d44444444444444 4448444444444444 dadded&d&&didaad 8 uuclide arem/yr fract.,, mrem /yr fract.

ares /yr fract.

arem/yr fract.

arem/yr fract, mrom/yr fract.

arem/yr fract.

A&&&ada &&a&aa&da && dead dadadadaa Addaad 444444444 addada adadadada &a4444 aadadadda adaad Co-60 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 i C2 134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+0 C3-131 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+0 Eu 152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+

Eu-154 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+

j Eu-155 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+07 0.0000 -0.000b 00 0.0000 0.000E+00 0.0000 2.200E 02 F3 55 0.000E+00 0.0000 0.000B+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0 Gd 152 0.000E+00 0.0000 0.000B+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.

M1 0.000E+00 0.0000 0.000B+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0 Sr 90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+0 M44444 444444444 4M444 M4444444 M4444 444444444 444444 M4444444 444444 444444444 444444 T:tal 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00s

• sue of all water independent and dependent pathways.

l f

i L

11 of 22 4

- - - ~

l ATTACIDfENT 1 l

+

FSV RESRAD MODEL

+ -

e

• Total Dose contributions TDOSEli.p,tl for Individual Radionuclides (1) and Pathways (p)

As mrem /yr and Fraction of Total Dose At t. 1.000E+00 years

{

l Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil R dio-aidadidaadaddada aaddaaaaadadiaad adidaaaadadaddad aidiadaadia& ding daadaidaaaaaaaad asaddaidadaddada aida446&&&dia&da i

nuclida nrem/yr fract.

mrem /yr fract.

nrem/yr fract.

mrem /yr fract, mrem /yr fract.

mrem /yr fract.

arem/yr fract.

4444144 144444344 adagaa daaaadada 444444 diadadaad agaian 44444444A aandad adaddaada idadas adadaAata 10 4 4144441&& dadada Co 60 1.488E+00 0.2703 5.0038-05 0.0000 0.000E+00 0.0000 2.744E-02 0.0050 4.073E 02 0.0074 5.7*.1E-03 0.0010 5.371E-05 0.0000 C3-134

7. 4 66E-01 0.13 5 6 8.620E-06 0.0000 0,000E+00 0.0000 3.026E-02 0.0055 9.015E-02 0.0164. 537E-02 0.0064 1.193E-04 0.0000 CJ-137 3.697E-01 0.0672 8.1124 06 0.0000 0.000E+00 0.0000 2.855E-02 0.0052 8.712E-02 0.0108.b356E-02 0.0061 1.1135-04 Eu 152 7.139E 01 0.1297 5.454E-05 0.0000 0.000E*00 0.0000 2.273E-04 0.0000 4.048E-04 0.0001 6.472?-04 0.0000 1.39BE-05 0.0000 Eu 154 7.5765-01 0.1376 6.872E-05 0.0003 0.000E+00 0.0000 3.258E 04 0.0001 5.798E-04 0.0001 9.141E-06 0.0000 2.005E-05 0.0000 Eu 155 1.956E 02 0.0036 9.359E-06 0.0000 0.000E+00 0.0000 4.900E 05 0.0000 8.707E-05'0.0000 1.377E-06 0.0000 3.023E-06 0.0000 Fa-55 0.000E+00 0.0000 5.422E 07 0.0000 0.000E+00 0.0000 7.069E 06 0.0000 2.9632-04 0.0001 7.115E-06 0.0000 1.069E-06 0.0000

~

0d 152 0.000E+00 0.0000 6.317E-02 0.0115 0.000E+00 0.0000 5.9602-03 0.0011 1.063E-02 0.0019 1.6695-04 0.0000 3.658E-04 0.000 H3 0.000E*00 0.0000 1.705E-15 0.0000 0.000E+00 0.0000 2,015E-15 0.0000 5.608E-16 0.0000 5.434E-16 0.0000 6.479E-20 0.0000 Sr 90 2.561E-03 0.0005 3.016E-04 0.0001 0.000E+00 0.0000 5.919E-01 0.1075 2.622E-01 0.0476

8. 6 83 E-0'2 '0. 015 8 3.078E-04 0.0001 4444444 444444444 444444 444444444 444444 444444444 444444 494444444 444444 444444444 444444 444444444 444444 44444444 Total 4.098E+00 0.7445 6.367E-02 0.0116 0.000E+00 0.0000 6.847E-01 0.1244 4.922E-01 0.0894 1.617E-01 0.02*4 9.959E-04 0.0002 i

Total Dose contributions TDosE(1,p t) for Individual Radionuclides (1) and Pathways (p) i As ares /yr and Fraction of Total Dose At t = 1.000E+00 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways

• Radio-adadaadadadadada dea 443&adadadada adadadaadidada&& adiadaadaddadada aidaisiadaadadaa idaddaddadaddeia aaaidad4&& da Nuclide arem/yr fract.

'tarem/yr fract.

ares /yr fract, erem/yr fract.

mres/yr fract.

mrom/yr fract.

ares /yr fract.

adadida addi44 dad dadaad dadadadas daddaa dadaadada Addaaa sadadadas aidada daaddassa assada ada444 dad diaded adiada44 C2-60 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E 00 0.0000 0.000E+00 0.0000 1.562E+00 0.2838 CJ-134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

9. 02 5 E -01 0.16 3 9 d

Ca-137 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 5.191E-01 0.09 Eu-152 0.000s.00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E*00 0.0000 7.146E-01 0.129 Eu 154 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00,,0,0000,0.000{+000.0000 0.000E+00 0.0000 7.586E 01 0.1378 Eu 155 0.000E,00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.971E-02 0.0036 F3-55 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 3.121E-04 0.000

^ 0d-152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 8.029E-H-3 2.353E 03 0.0004 3.010E 06 0.0000 0.000E+00 0.0000 4 196E-04 0.0001 1.833E-04 0.0000 4.150E-04 0.0001 3.374E 03 0.0006 Sr 90 0.000E.00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 9.441E-01 0.1715 4444444 444444444 444444 444444444 444444 444444444 444444 444444444 444444 444444444 444444 444444444 4444

Tatsi 2.3535-03 0.000t 3.010E-06 0.0000 0.000E+00 0.0000 4.196E-04 0.0001 1.033E-04 0.0000 4.150E-04 0.0001 5.505E+00 1.0000

• Eu2 of c11 water independent and dependent pathways.

12 of 22

l ATTACIB1ENT 1

+

FSV RESRAD MSDEL s *

• s Total Dose Contributions TDOSE(1,p.tl for Individual Radionuclides (i) and Pathways (p)

As mres/yr and Fraction of Total Dose At t = 5.000E+00 years 1

Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil R:dio-44444144di444444 adidiadidiadadia idadiad444444ada ediadadadidaaddi Adididadiaidad&& A&&id Nuclid3 mrom/yr fract.

mrem /yr fract.

mrem /yr fract.

mrem /yr fract, mrem /yr fract.

mrem /yr fract, mrem /yr fract.

aid 4444 4444H444 edidad dadaddaad addied dediadida idadde diaidaied deidad 1844418&& &&idia adidadida SHa&d adad&&a C3-60 8.607E-01 0.2581 2.842E-05 0.0000 0.000E.00 0.0000 1.559E-02 0.0047 2.313E-02 0.0069 3.244E-03 0.0010 1.050E-05 C3 134 1.908E-01 0.0572 2.159E-06 0.0000 0.000E+00 0.0000 7.580E-03 0.0023 2.258E-02 0.0068 8.861E-03 0.0027 2.988E Cs-137 3.305E-01 0.0991 7.117E-06 0.0000 0.000E+00 0.0000 2.502E 02 0.0075 7.634E-02 0.0229 2.9415-02 0.0088 9.749E-05 cu-152 5.628E-01 0.1687 4.219E-05 0.0000 0.000E+00 0.0000 1.758E-04 0.0001 3.131E-04 0.0001 4.929E-06 0.0000 1.081E-05 0.0 Eu-154 5.366E-01 0.1609 4.7765-05 0.0000 0.000E+00 0.0000 2.264E-04 0.0001 4.030E-04 0.0001 6.353E-06 0.0000 1.394E 05 0.0000 Eu 155 1.093E-02 0.0033 5.096E-06 0.0000 0.000E+00 0.0000 2.668E-05 0.0000 4.7412-05 0.0000 7.499E 07 0.0000 1.646E 06 0.0000 FJ 55 0.000E+00 0.0000 1.066E-07 0.0000 0.000E+00 0.0000 2.4335-06 0.0000 1.020E-04 0.0000 2.449E-06 0.0000 3.640E-07 0.0000 0d-152 0.000E+00 0.0000 6.016E-02 0.0140 0.000E+00 0.0000 5.676E-03 0.0017 1.012E-02 0.0030 '1.589E-08 0.0000 3.483E-04 0.0001 H3 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00'0.0000 0.000E+00 0.0000 i

St 90 1 5335 03 0.0005 1.766E 04 0.0001 0.000E+00 0.0000 3.467E 01 0.1039 1.536E-01 0.0461 5.086E-02 0.0152 1.0038-04 0.0001 4444444 444444444 4H444 444444444 444444 444444444 444444 444444444 444444 4444H444 444444 444444444 444444 H4444444 44 Titsi 2.494E+00 0.7477 6.047E 02 0.0181 0.000E+00 0.0000 4.010E 01 0.1202 2.866E-01 0.0859 9.254E-02 0.0277 7 133E-04 0.0002 Total Dose Contributions TDCSE(1,p,t) for Individual Radionuclides (1) and Pathways (p)

As mrem /yr and Fraction of Total Dose At t - 5.000E+00 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways

• Raiin. Ad&d454444444444 kiddiadidiadiada 4488448414444444 Addiddaddiaidida dad.daddadadadde adiaid&Hidadida Aaa4444444444445 Nuclide arem/yr fract.

arem/yr fract, mrom/yr fract.

mram/yr fract.

mr-m/yr fract.

mres/yr fract, arem/yr fract.

Adidiaa adiadaded addeda ida84didi 144448 diaadadad ediada diedidaad ediada auiMaadi 188844 44diadaad da&dia 444444444 441844 C3-60 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 9.027E-01 0.2707 C3 134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 2.2985-01 0.060 a

' Cs-137 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4.614E-01 0.138 Eu 152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 5.633E-01 0.168 Eu 154 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 6.000E"+00 0.0000 0.000E+00 0.0000 5.3722-01 0.161 Eu 155 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.101E-02 0.00 F3 55 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E.00 0.0000 0.000E+00 0.0000 1.074E-04 0. 0000 Od-152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 7.646E-02 0.0j H-3 3.724E 13 0.0000 4.7645 16 0.0000 0.000E+00 0.0000 6.639E 14 0.0000 2.900E 14 0.0000 6.568E-14 0.0000 5.339E-13 0.0000 Br-90 0.000E+00 0.0000 0.0008 00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 5.530E-01 0.1658 4444444 44HH444 4H444 444444444 4444H 444444H4 444444 444H4444 444444 444444444 4444H 44444H44 444444 4444444 Titti 3.724E-13 0.0000 4.764E 16 0.0000 0.000E+00 0.0000 6.639E-14 0.0000 2.900E-14 0.0000 6.568E-14 0.0000 3.335E+00 1.0000

• Sum of all water independent and dependent pathways.

13 of 22

J

~

ATTACHMENT 1 FSV RESRAD MODEL Total Dose Contributions TDOSE(1,p,t) for Individual Radionuclides (1) and Pathways (p) t As mree/yr and Fraction of Total Dose At t = 1.000E+01 years Water Independent Pathways (Inhalation excludes radont Ground Inhalation Radon Plant Meat Milk Soil Radio. 44&&4&daad&4adid da3&adadi484&d44 4888343133344318 4444343434144444 &adisia&&diadada dad 883334A3833dA 883383AAA383A Nuclide arem/yr fract, mrem /yr fract, mrom/yr fract, arem/yr fract.

mrom/yr fract, mrom/yr fract.

eres/yr fract.

8444444 4d4444444 444444 4d4444444 adidda dadididad idadia dadididia 444444 Adadid&&& 84&did &&&&&diai 444A&& Ad&ddadda 44d444 Ca 60 4.3385 01 0.2146 1.400E-05 0.0000 0.000E+00 0.0000 7.677E-03 0.0038 1.139E-02 0.0056 1.598E-03 0.0008 1.502E-05 0.0000 C3 134 3.463E-02 0.0171 3.823E-07 0.0000 0.000E+00 0.0000 1.3428-03 0.0007 3.9985-03 0.0020 1.5698-03 0.0008 5.289E-06 0.0000 CJ 137 2.871E-01 0.1421 4.027E 06 0.0000 0.000E+00 0.0000 2.1195 02 0.0105 6.466E-02 0.0320 2.491E-02 0.0123 0.256E-05 0.0000

~

Eu-152 4.177E 01 0.2067 3.057E-05 0.0000 0.000E+00 0.0000 1.2748-04 0.0001 2.269E-04 0.0001 3.5725-06 0.0000 7.834E-06 0.0000 Eu 154 3.483E-01 0.1724 3.027E-05 0.0000 0.000E+00 0.0000 1.435E-04 0.0001 2.5545 04 0.0001 4.027E-06 0.0000 0.834E-06 0.0000 Eu-155 5.200E-03 0.0026 2.381E-06 0.0000 0.000E+00 0.0000 1.247E-05 0.0000 2.216E-05 0.0000 3.504E-07 0.0000 7.6918-07 0.0000 F3-55 0.000E+00 0.0000 4.9155-08 0.0000 0.000E+00 0.0000 6.4083-07 0.0000 2.6865-05 0.0000 6.4498-07 0.0000 9.692E-08 0.0000 Od-152 0.000E 00 0.0000 5.654E-02 0.0280 0.000E+00 0.0000 5.334E-03 0.0026 9.5125-03 0.0047 1.493E-04 0.0001 3.274E-04 0.0002 N*3 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00'0.0000 0.000E+00 0.0000 Er-90 8.0745 04 0.0004 9.040E 05 0.0000 0.000E+00 0.0000 1.7743-01 0.0878 7.861E-02 0.0389 2.603E-02 0.0129 9.227E-05 0.0000 4444444 444444444 444444 444444444 444444 444444444 444444 444444444 444444 444444444 444 4 4. o. 44 W M M0000 l

Titti 1.528Ee00 0.7558 5.671E-02 0.0281 0.000E+00 0.0000 2.133E-01 0.1055 1.6875-01 0.0835 5.426E-02 0.0268 5.4005 04 0.0003 Total Dose Contributions TDOSE(i.p,t) for Individual Radionuclides (1) and Pathways (p)

As mrom/yr and Fraction of Total Dose At t = 1.000E+01 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways

• Radio-AdeadadaaAdadada 88Aa4484444444a& adidaddad84&daag osadagaga&ggagg gaggag&&gsdistad &&a4&atadaAsadaa 84444444&Adidade Nuclide. aree/yr fract.

ares /yr fract.

eres/yr fract.

ares /yr fract.

area /yr fract.

mrom/yr fract.

area /yr fract.

AddaAAA ad4&&& dad &adida 444444884 444444 adidded&& adidad 44444444a aidida ad&iaaded &&da&& &&d&&aada od&&& &&d&&d&di d&&d&&

Co-60 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4.545E-01 0.2249 C.> 134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4.154E 02 0.0206

,Cs 137 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 3.979E-01 0.1969 Eu 152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000(+000.0000 0.000E+00 0.0000 4.18 s

Eu-154 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 3.4888-01 0.1726 Eu 155 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 5.318E 03 0.0026 Fa 55 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 2.829E-05 0.0000 Od-152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 7.186E-02 0.0356 J3 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Ir-90 0.000E+00"0.C000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 jo.4m.m.m44mo..44m44.

m.4 m 4 4 44. Som.

o44. 4 44444 4 4.

o.. 4m o4 ooo otti 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 2.021E+00 1.0000

+Eun gf c11 water :ndependent and dependent pathways.

14 of 22

m

~

ATTACHMENT 1

+

FSV RESRAD MODEL Total Dose Contributions TDOSE(i.p.tl for Individual Radionuclides (i) and Pathways (p) i As mrom/yr and Fraction of Total Dose At t. 3.000E+01 years water Independent Pathways (Inhalation excludes redon) 4 Ground Inhalation Radon Plant Meat Milk Soil Rtdio. 4444444444444484 4444444444444444 4444444444444444 444444444448d444 444444&444444444 &di4444444644444 adidda Nuclide eres/yr fract.

arem/yr fract, mrom/yr fract.

ares /yr fract, mres/yr fract, mrem /yr fract, mrom/yr fract.

addaded didaddeia 4d4444 444444444 444444 444864444 444444 44444444a 4&4444 &&d444444 adadda &&Mdaddd saaded 44444

C3 60 2.771E 02 0.0544 8.125E.07 0.0000 0.000E+00 0.0000 4.4575 04 0.0009 6.615E-04 0.0013 9.275E-05 0.0002 8.722E-07 0.00 CJ 134 3.7265-05 0.0001 3.704E 10 0.0000 0.000E+00 0.0000 1.300E-06 0.0000 3.873E-06 0.0000 1.520E-06 0.0000 5.124E-09 0

~

C -137 1.6205 01 0.3182 3.058E 06 0.0000 0.000E+00 0.0000 1.075E 02 0.0211 3.281E-02 0.0645 1.2648-02 0.0248 4.189E-05 0.0 3 Bu 152 1.2568 01 0.2467 8.313E 06 0.0000 0.000E+00 0.0000 3.465E-05 0.0001 6.170E-05 0.0001 9.713E-07 0.0000 2.130E-06 0.00 Eu 154 6.1312 02 0.1205 4.819E-06 0.0000 0.000E+00 0.0000 2.285E-05 0.0000 4.067E-05 0.0001 6.411E 07 0.0000 1.406E-06 0.0000 Eu 155 2.862E 04 0.0006 1.120E-07 0.0000 0.000E+00 0.0000 5.843E-07 0.0000 1.0428-06 0.0000 1.648E-08 0.0000 3.6175-08 0.0000 Fa 55 0.000E+00 0.0000 2.3325-10 0.0000 0.000E+00 0.0000 3.040E-09 0.0000 1.274E 07 0.0000 3.060E-09 0.0000. 4.590E-10 0.0000 Gd 152 0,000E+00 0.0000 4.350E 02 0,0855 0.000E+00 0.0000 4.104E 03 0.0001 7.318E-03 0.0144,1.149E-04 0.0002 2.519E 04 0.0005 4

N3 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00,0.0000 0.000E+00 0.0000 3r 90 6.1585-05 0.0001 6.118E 06 0.0000 0.000E+00 0.0000 1.201E 02 0.0236 5.320E-03 0.0105 1.762E-03 0.0035 6.245E 06 0.0000 H44444 444444444 444444 444444444 444H8 444444444 444444 444444444 444444 44444H44 444444 H4444444 444444 444444444 H j Total 3.769E-01 0.7406 4.352E-02 0.0855 0.000E+00 0.0000 2.737E 02 0.0538 4.621E 02 0.0908 1.461E-02 0.0287 3.0455-04 0.0006 1

Total Dose Contributions 'IDOSE(1,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrom/yr and Fraction of Total Dose At t = 3.000E+01 years Water Dependent Pathways j

water Fish Radon Plant Meat Milk All Pathways

• iRafig- &a4444444444444& &&dd44ddaMdMid adidadaadadienda &&4144 add &&agada adidadadaaddagga &&&M44444444444 adidaadMadidada

!Nuclid3 mrom/yr fract.

' ares /yr fract, mrom/yr fract, mrom/yr fract.

ares /yr fract, mrom/yr fract, mrom/yr fract.

i Madded 144444444 444444 &&dadadde adMd4 Madiddad Aaaded Sada&aada adedM aded&& dad daa&de Maddiada adad&a I Co-60 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0,000E+00 0.0000 0.000E+00 0.0000 2.891E 02 0.0568 lCJ134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+

IC3 137 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.

itu-152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1 Bu-154 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00,0,0000 0.000E 00 0.0000 0.000E+00 0.0000 6.138E 02 0.1206 f

Bu-155 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 2.8795 04 0.000I F3-55 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E*00 0.0000 1.3425-07 0.0000 i

Gd 152 0.000E400 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 5.5298 02 M3 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 I St 90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.916E-02 0.037 H44444 H4444444 444444 444444444 M H44 444 H4444 4 H444 444444444 444444 444444444 444444 M44444 H 444444 44444 Tots 1 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 5.0905-01 1.000

• Sum of all water independent and dependent pathways.

i a

15 of 22 l

g -_

A'ITACHMENT 1 FSV RESRAD MODEL

+

4 s *

• e Total Dose Contributions TDOSE(1.p.t) for Individual Radionuclides (i) and Pathways (p) 1 As ares /yr and Fraction of Total Dose At t = 5.000E+01 years Water Independent Pathways (Inhalation excludes radon) l Ground Inhalation Radon Plant Meat Milk Soil E:dio-daddaddaddadaada daadadaaaaaaaa44 adad6adaadaddada addadadadaMaada aidadadad44&daad daadaddaadadaded adaaaaadadad Nuclid3 mrem /yr fract, mrem /yr fract, mrom/yr fract, mrom/yr fract, mrem /yr fract.

mrom/yr fract.

arem/yr fract, f

&&dadad deaddaada daadad aaMaaada daaaas adiadadaa 4444&& andadadad adadaa adadasada 44444 Co*60 1.733E 03 0.0083 4.586E-08 0.0000 0.000E+00 0.0000 2.515E-05 0.0001 3.733E-05 0.0002 5.2355-06 Cs-134 3.929E 00 0.0000 3.488E-13 0.0000 0.000E+00 0.0000 1.225E 09 0.0000 3.6495-09 0.0000 1.431E-09 0.0000 4.827E-12 0 C3 137 8.956E 02 0.4278 1.509E 06 0.0000 0.000E+00 0.0000 5.3035-03 0.0253 1.618E-02 0.0713 6.234E-03 0.0298 2.067E-05 0.00 Eu-152 3.6998 02 0.1767 2.198E 06 0,0000 0.000E+00 0.0000 9.160E-06 0.0000 1.631E-05 0.0001 2.568E 07 0.0000 5.632E-07 0.00 Eu 154 1.054E-02 0.0505 7.460E-07 0.0000 0.000E+00 0.0000 3.537E-06 0.0000 6.295E-06 0.0000 9.9243 08 0.0000 2.177E-07 0.00 Eu 155 1.5362 05 0.0001 5.119E-0* 0.0000 0.000E+00 0.0000 2.680E-08 0.0000 4.7635-08 0.0000 7.533E-10 0.0000 1.6535-09 0.0000 Fs 55 0.000E*00 0.0000 1.076E-12 0.0000 0.000E+00 0.0000 1.4025-11 0.0000 5.877E-10 0.0000 1.411E-11 0.0000 2.121E-12 0.0000 l Od 152 0.000E+00 0.0000 3.254E-02 0.1554 0.000E+00 0.0000 3.0705-03 0,0147 5.4745-03 0.0261.8.5943 05 0.0004 1.884E 04 0.

H-3 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0,0000 0.000E+00 0.0000 0.000E+00.0.0000 0.000E+00 0.0000 Sr 90 4.6165 06 0.0000 4.026E-07 0.0000 0.000E+00 0.0000 7.901E-04 0.0038 3.501E-04 0.0017 1.1595 04 0.0006 4.1095-07 0.0000 4444444 444444444 444444 444444444 444444 H4444444 444444 444444444 444444 444444444 444444 444444444 444444 H4 Tetal 1.3895 01 0.6634 3.254E-02 0.1554 0.000E+00 0.0000 9.201E-03 0.0440 2.2078-02 0.1054 6.4428-03 0.0300 2.1035-04 0.0010 Total Dose Contributions TDOSEli.p,t) for Individual Radionuclides (i) and Pathways (p)

As mrom/yr and Fraction of Total Dose At t = 5.000E+01 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways +

Radio-adaaaadadataadda adadadaadaddadia Madadadaadada&& dadaddaadadadada deidadaaaaaaaeda &&M aa&M addadaa Saadad Nuclid2 ares /yr fract.

mrom/yr fract.

mree/yr fract, mres/yr fract.

arem/yr fract.

erom/yr fract, mres/yr fract.

i saaaaaa aaaaaaada A44444 adadaa444 444444 444444444 Maada idsdadada adadda 444444444 444444 441444448 and Ma atadadad Co-60 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1 0013-03 0.0086 C3 134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4.560E 48 0.00 C3-137 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.1735-01 0.

Eu-152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 3.702E-02 0 Eu 154 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E*00 0.0000 0.008E+00 0.0000 0.000E+00 0.0000 1.0595-02 Eu 155 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.5445 F3 55 0.000E*00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 6.191E-10 Od 152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4.13 j

H-3 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000B+00 0i Sr-90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.262E 03 4444444 444H4444 444*44 444444444 444444 444444444 444444 H4444444 444444 H4444444 444444 444444444 444 Total 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 2.093E-01i

• Sum of all water independent and dependent pathwe g -

16 of 22

NITACHMENT 1 i

FSV RESRAD MODEL

.. +

Total Dose Contributions TDOSE(1,p,t) for Individual Radionuclides (1) and Pathways (p)

{

As arom/yr and Fraction of Total Dose At t = 1.000E 02 years Water Independent Pathways (Inhalation excludes radon) i Ground Inhalation Radon Plant Meat Milk Soil j

3 Radio- &&&d444444444444 Mdadadadaddadda 4M8444444444444 44&&d&&&d&& aid && 44444444444aAd44

! Nuclide mres/yr fract, mrom/yr fract, mrom/yr fract, mrom/yr fract.

mrom/yr fract.

aree/yr fract.

arem/yr fract.

&&&&&&& &&d&&d&&& &&&&&& &&4444&aa &&&&44 14&444444 444445 444444444 andad Aidadid&& a&&&d Co 60 1.4105 06 0.0000 2.737E 11 0.0000 0.000E+00 0.0000 1.5018-08 0.0000 2.228E-00 0.0000 3.125E-09 0.0000 2.

C3 134 1.182E-15 0.0000 7.492E-21 0.0000 0.000E+00 0.0000 2.6308 17 0.0000 7.836E 17 0.0000 3.0748 17 0.0000 4

i C3-137 1.696E-02 0.4457 2.034E*07 0.0000 0.000E+00 0.0000 7.1495-04 0.0188 2.182E-03 0.0573 8.4045-04 0.022 Eu 152 1.459E 03 0.0393 6.231E-08 0.0000 0.000E+00 0.0000 2.597E-07 0.0000 4.624E 07 0.0000 7.200E 09 0.0000 1.59'"

8 0.0000 Eu 154 1.102E 04 0.0029 5.546E 09 0.0000 0.000E 00 0.0000 2.630E-08 0.0000 4.630E-00 0.0000 7.378E-10 0.0000 1.

Eu 155 S.0545-09 0.0000 1.804E 12 0.0000 0.000E+00 0.0000 9.4475 12 0.0000 1.6795-11 0.0000 2.6555-13 0.0000 5 F3 55 0.000E+00 0.0000 1.226E 18 0.0000 0.000E+00 0.0000 1.598E-17 0.0000 6.699E-16 0.0000 1.6095 17 0.0000 2.41 4 0d 152 0.000E,00 0.0000 1.2425 02 0.3263 0.000E+00 0.0000 1.1725 03 0.0300

2. 08 9E-03 0.054 9 '3.280E-05 0.0009 7.190E-05 0.0019

M3 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00*0.0000 0 Sr 90 6.005E 09 0.0000 3.526E 10 0.0000 0.000E+00 0.0000 6.921E-07 0.0000 3.066E-07 0.0000 1.0155-07 H H444 M4444444 444444 444444444 444444 444444444 444444 444444444 444444 444444444 444444 444444 Tttal 1.893E 02 0.4870 1.2425-02 0.3263 0.000E+00 0.0000 1.887E-03 0.0496 4.2722 03 0.1122 8.733E.04 0.0229 7.4 l

4 Total Dose Contributions TDOSE(1,p,t) for Individual Radionuclides (i) and Pathways (p) 4 As mrom/yr and Fraction of Total Dose At t = 1.000E+02 years I

Water Dependent Pathways 3

j

+

Water Fish Radon Plant Meat Milk All Pathways +

Radio. &&&&&&&&&&&&&&&& (&&&&&a&&&&ead&& 4444444444444444 MadedM&Madd&& &&daadidiandadia Adda i maclide area /yr fract.

aree/yr fract.

aren/yr fract.

aree/yr fract.

arem/yr fract.

ares /yr fract.

mres/yr fract.

" &&&d&&& &&&4444&& &&d&&d 444444444 1M444 844444444 44d844 &&dadad&& ad&dM 444444444 44444 C3 60 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.45 Co 134 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.00 4

C3 137 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 Eu 152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 Eu 154 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00'*0.0000 0.000V+00 0.0000 0.000E+00 i Eu 155 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 FS-55 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 06 152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+0 H3 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.00 St-90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1,1078-06 0.0000 M H H4 4H4H H4 M4444 444444444 444444 H4444444 H4444 444H4444 444444 044444444 444444 444444 Total 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 C 0000 0.000E+00 0.0000 0.000E+00 0.0 4

• Sun sf all water independent and dependent pathways.

I 1

4 4

17 of 22

~.

ATTACHMENT 1 FSV RESRAD MODEL

+ '

4 4

+

J Total Dose Contributions TDosE(1,p.c) for Individual Radionuclides (1) and Pathways (p)

As mree/yr and Fraction of Total Dose At t. 1.000E+03 years Water Independent Parte sys (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat

tilk Soil Radie ad&&ddadadadadde adaeaaaaaaaaaada 444444444444M44 4a444444a4444144 adadaaaaaaaaaada a444444444444444 44444444a4444444 stuelide area /yr fract.

mrom/yr fract.

arem/yr fract, mres/yr fract.

arem/yr fract.

aree/yr fract.

area /yr fract.

4444444 daaddadad adadas adadadada deadas aa444adia 44aaM &ada4 Mad Maasa nadaaaga daadia Maaddada adaaas 444444444 Masaa co 40 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 CJ-134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 CJ 137 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu 152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-154 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-155 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 rd 55 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E 00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 f

Od 152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 V.000E+00 0.0000 0.000E+00 0.0000 H3 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0,0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00'0.0000 0.000E+00 0.0000 St-90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4444444 444444444 444444 H4444444 444444 444444444 444444 444H4444 444444 H4444444 444444 444444444 444444 444444444 M44H Tots!

0.0008 00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total Dose Contributions TDOSEli,p,t) for Individual Radionuclides (1) and Pathways (p)

As ares /yr and Fraction of Total Dose At t = 1.000E+03 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways

• Radio-4444444444444414 dadadadadaadaded dadadadadadaaaaa M44444444aa4444 aaaaaaa&daadadaa M44444444a&4144 Makaa&&aMadada touclide eres/yr fract.

area /yr fract.

mres/yr fract.

area /Yr fract.

mrom/yr fract.

ares /yr fract, mrom/yr fract.

adaaaaa adataaa&& addada addaadada addaaa 444444444 &&Maa 444444444 444444 adaaaaa&& 444444 Maaa&aad &&a444 M4444144 && dada C3-40 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

.cs-134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

'Cs 137 0.000R+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

.ru 152 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

Eu 154 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 t,.000E+00*0.0000 0.000 6 00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

-Eu-155 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 F3-55 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

Gd-152 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 M-3 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E*00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 lSr-90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4444444 444444444 444444 444444444 444444 H4444444 H4444 444444444 44H44 444444444 444444 H4444444 444444 444444444 444444

• Totel 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

• Sua cf c11 water independent and dependent pathways.

18 of 22

I ATTACHMENT 1 FSV RESRAD MODEL e

+.

o' ji t

Dose / Source Ratios Susened Over All Pathways t l Parent and Progeny Principal Radionuclide Contributions Indicated 1

, Parent Product Eranch DsR(j,t) (ares /yrl/ fpci/g) 1 (1)

(j)

Fraction to 0.000E+00 1.000E+00 5.000E+00 1.000E+01 3.000E+01 5.000E+01 1.000E+02 1.000E+03 l'

H Haad andaans Haaaaaad Haddadad dadaddada dadadadaa adadadada aaadaadde addadaa&& daadadaad Headdada l

Co 60 Co 60 1.000E+00 1.792E+00 1.562E+00 9.0275-01 4.545E 01 2.8915-02 1.801E-03 1.4515-06 0.000E+00 Co.134 Cs 134_ 1.000E+00 1.270E+00 9.025E-01 2.298E-01 4.1545 02 4.396E-05 4.560E-08 1.317E 15 0.000E+00 Ca 137 Cs-137 1.000E+00 5.3455 01 5.191E-01 4.6145 01 3.979E-01 2.182E-01 1.173E 01 2.070E-02 0.000E+00 Bu 152 Eu 152 7.2005 01 5.466E 01 5.1515-01 4.060E-01 3.0148-01 9.0595-02 2.668E 02 1.0525-03 0.000E+00 Eu 152 Eu-152 2.7938-01 2.117E 01 1.9955 01 1.573E-01 1.1675-01 3.5098-02 1.0348-02 4.075E-04 0.000E+00 Eu 152 0d 152 2.7925 01 0.000E+00 1.417E-16 6.0448 16 1.0055 15 1.5055-15 1.319E-15 5.409E-16 0.000E+00 Eu 152 40sR(j) 2.1175-01 1.995E'-01 1.'5735-01 1.1675-01 3.5095-02 1.0345 02 4. 075E-04 0.000E+00 4

Eu 154 Eu 154 1.000E+00 8.2698 01 7.5865-01 5.37JE 01 3.4885 01 6.138E-02 1.0598-02 1.103E-04 0.000E+00 Eu 155 Eu-155 1.000E+00 2.2005 02 1.971E-02 1.1015-02 5.3185 03 2.8795-04 1.544E-05 9.0855-09 0.000E+00 y

e j Fe 55 Fe-55 1.000E+00 4.014E 04 3.121E 04 1.074E-04 2.8295 05 1.3425 07 6.1913-10 7.056E-16 0.000E+00 Od 152 Od 152-1.000E+00 8.127E 02 0.0295 02 7.6465 02 7.1965-02 5.5295-02 4.135E-02 1.578E 02 0.000E+00 J

N3 M3 1.000E+00 1.094E 02 3.3745 03 5.3395-13 0.000h'*

dt00E+00 0.000E+00 0.000E+00 0.000E+00 4.

Er-90 ar 90 1.000E+00 1.0795+00 9.441E-01 5.530E 01 2.831E-01 1.9165 02 1.262E-03 1.1075-06 0.0aor 00 H44444 H444H 4444 H444 444444444 H44H444 4 '4444444 H4444444 H4444444 444444444 44444H44 he"eaede Branch Fr:ction is the eunulative factor for the j'th principal radionuclide daughter CUMBRF(j) = ERF (1)' mi2) *... ERF(j).

I The DSR includes contributAons from associated (half-life p 0.5 yr) daughters.

l 1

4 1

single Radionuclide soil OJidelines Ofi t) in pci/g i

k Basic Radiation Dose Limit = 10 nres/yr Nuclide (il t' O.000E+00 1.000E+00 5.000E+00 1.000E+01 3.000E+01 5.000E+01 l'.000E+02 1.000E+03 deidada adaaaaada dadaddaad daadadaad aidaaddad adadadada 44444444& addaadead adaaaaaad 0o 60.

5.5825,00 6.401E+00 1.1083 01 2.200E+01 3.4598+02 5.554E+03 6.893E+06 *1.131E+15 C3 134 7.872E+00 1.1083+01 4.351E+01 2.4075+02 2.275E+05 2.193E+08

• 1.294E+15 *1.294E+15 C3 137 1.8715+01 1.9278+01 2.1675+01 2.513E+01 4.583E+01 8.52SE*01 4.830E+02

• 8.701E+13

' Eu 152 1.3198+01 1.3995+01 1.775B+01 2.392E+01 7.957E+01 2.701E+02 6.852E+03

+1.765E+14 j

~ Eu-154 1.2095+01 1.318E+01 1.8615+01 2.8675+01 1.6295+02 9.443E+02 9.0685+04

• 2.639E*14

Eu 155 -

4.385E+02 5.072E+02 9.000E+02 1.800E+03 3.473E+04 6.477E+05 1.101E+09 '4.651E+14

• FJ 55 2.455E+04

3. 2 04 B+ 04 9.310E+04 3.535E+05 7.4515+07 1.615E+10 *2.409E+15

• 2.4095+15.

igd-152

• 2.1785+01

• 2.178E*01

• 2.178E+01 *2.178E+01

• 2.'785+01

• 2.178E+01

• 2.178E+01

• 2.1788+01

$ H-3 9.124E+02 2.9643p03 1,873E+13 *D.594E+15

• S. 594 E+15 *9.594E+15 +9.594E+15

'9.594E+15

,Sr 90 9.2675+00 1,059E+01 1.0088+01 3.533E+01 5.2185+02 7.927t+03 9.034E+06

• 1.365E+14 4H4H4 MH44H4 444444444 H44H444 444444444 44H44H4 444444444 444444444 444444444

'At specific activity limit 4

19 of 22 I

Al'l Allt\\ LENT 1 FSV RESRAD MODEL s o a.3 Sununed Dese/ Source Ratios DSR(1,t) in (mree/yr)/(pci/g) and Eingle Radionuclide Soil Guidelines O(1,t) in pC1/g at tain = time of minimum single radionuclide soil guideline and at taax = time of maximum total dose = 0.000E+00 years afuelide Initial tain DSR(1,tmin) Gll,tmin) DSR (i. tmax) G(1,tmax)

(1) pC1/g (years)

(pci/g)

(pci/g) 4441444 444444444 adadadad&Adadada 4&4444a&& adaddaa&& 444444444 eaaaaaaaa Co 60 1.000E+00 0.000E+00 1.192E+00 5.582E+00 1.192E+00 5.582E+00 Cs 134 1.000E+00 0.000E+00 1.270E*00 7.872E+00 1.270E+00 7.8725 00 Cs 137 1.000E+00 0.000E+00 6.3455-01 1.871E+01 5.345E-01 1.871E+01 Eu 152 1.000E+00 0.000E+00 7.584E 01 1.319E*01 7.584E-01 1.3195+01 Eu 154 1.000E+00 0.000E+00 8.269E-01 1.209E*01 8.2698 01 1.2095+01 Eu-155 1.000E+00 0.000E+00 2.2805 02 4.385E+02 2.280E 02 4.385E+02 Fe 55 1.000E+00 0.000E+00 4.074E 04 2.455E+04 4.074E 04 2.455E+04 0d-152 1.000E+00

,0,000E+00

,8.1275-02 *2.178E+01 0.127E-02 *2.1785+01 H3 1.000E+00 0.000E+00 1.0965 02 9.124E.02 1.096E-02 9.124E+02 8r 90 1.000E+00 0.000E*00 1.0798+00 9.2675+00 1.079E+00 9.2675+00 4444444 444444444 4444444444444444 444444444 444444444 444444444 444444444

'At specific activity limit e.

1 e

20 of 22

AITACfDIENT 1 FSV RESRAD MODEL

+.

s e e s+

1 Individual Nuclide Dose sununed over All Pathways Parent Nuclide and Branch Fraction Indicated Nuclide Parent BRF(i)

DOSE (j,t), mres/yr (j)

(1) t= 0.000E+00 1.000E+00 5.000E+00 1.000E+01 3.000E+01 5.000E+01 1.000E+02 1.000E+03 adaad&& Saadadd idaddaa&&

&adadaiaa 144445&&d aaadadaad &&dadaada aidadadia &&da&& dad dadada444 444484444 Co 60 Co 60 1.000E+00 1.792E+00 1.562E+00 9.0275-01 4.545E-01 2.891E-02 1.801E-03 1.451E-06 0.000E+00 l

I Cs-134 Cs 134 1.000E+00 1.270E+00 9.02SE 01 2.2905-01 4.154E-02 4.3968-05 4.560E-08 1.317E-15 0.000E+00 l

1 Cs 137 Cs 137 1.000E+00 5.345E 01 5.191E-01 4.614E-01 3.9798-01 2.182E-01 1.173E-01 2.070E-02 0.000E+00 Eu 152 Eu-152 7.2005-01 5.4665-01 5.1518-01 4.050E-01 3.014E-01 9.059E-02 2.6488-02 1.052E-03 0.000E+00 Eu-152 Eu 152 2.792E-01 2.117E-01 1.995E-01 1.573E 01 1.1678 01 3.5095-02 1.034E-02 4.0753 04 0.000E+00 Eu 152 6 DOSE (j):

7.5848-01 7.1465-01 5.6335 01 4..s1E-01 1.2575-01 3.702E-02 1.459E-03 0.000E+00 g

Od 152 Eu-152 2.792E-01 0.000E+00 1.417E-16 6.044E-16 1.005E-13 1.505E 15 1.3195 15 5.409E-16 0.000E+00 od 152 Od-152 1.000E+00 0.127E-02 0.0295-02 7.6465-02 7.1865-02 5.529E-02 4.1352 02 1.5785-02 0.000E+00 Gd 152 8DORE (j ) :

8.1275-02 0.029E-02 7.646E-02 7.186E-02 5.529E-02 4.135E-02 1.578E-02 0.000E+00 1

1 Eu-154 Eu-154 1.000E+00 8.269E-01 7.586E-01 5.3725-01 3.4005-01 6.1308-02 1.059E-02 1.103E-04 0.000E+00 1

Eu 155 Eu-155 1.000E+00 2.280E 02 1.9715-02 1.1015-02 5.3185 03 2.8795-04 1.544E-05 9.0058-09 0.000B+00 Fe 55 Fe 55 1.000E+00 4.0745-04 3.121E-04 1.074E-04 2.8295-05 1.3425 07 6.191E-10 7.0565-16 0.000E*00 H3 N3 1.000E+00 1.0968-02 3.3745 03 5.3395-13 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I.

Sr-90 Sr-90 1.000E+00 1.0795400 9.441E-01 5.5305-01 2.831E-01 1.9165-02 1.2625 03 1.107E 06 0.000E+00 4444444 4444444 444444444 444444444 444444444 444444444 444444444 444444444 444444444 444444444 444444444 i

BAF(i) is the branch fraction of the parent nuclide.

I 1

i 4

F 4

4 21 of 22

y ArfACIDIENT 1 FSV RESRAD MODEL 4 e e+

Individual Nuclide Soil Concentration Parent Nuclide and Branch Fraction Indicated l

Nuclide Parent BAF lil' 5(j,t), pC1/g (j)

(1)

t. 0.000E+00 1.000E+00 5.000E+00 1.000E+01 3.000E+01 5.000E*01 1.000E+02 1.000E+03 added&& &&idi&& $84488444 846486448 444444&d4 &&d&diedi ad&4&a&&& diadia&da &&idiad&S &&&464444 44848&&&&

Co-60 Co 60 1.000E+00 1.000E+00 8.741E-01 5.101E-01 2.602E-01 1.763E-02 1.1945-03 1.425E 06 0.000E+00 Cs 134 Cc-134 1.000E+00 1.000E+00 7.123E-01 1.834E-01 3.362E-02 3.800E-05 4.295E-08 1.845E-15 0.000E+00

)

Cs 137 Co.137 1.000E+00 1.000E+00 9.7415-01 8.771E-01 7.694E-01 4.555E 01 2.696E-01 7.269E 02 4.1195-12 Eu 152 Eu-152 7.2005 01 7.200E-01 6.8065-01 5.410E-01 4.060E 01 1.2888-01 4.087E-02 2.3175-03 8.4915-26 Eu 152 Eu 152 2.7925 01 2.792E-01 2.636C 01 2.095E-01 1.5738-01 4.989E-02 1.5835-02 8.9755-04 3.2895-26 Eu-152 48(j):

1.000E+0,0 9.442E 01 7.,505E-01 5.633E-01 1.787E 01 5.670E-02 3.2153-03 1.178E-25 Od-152 Eu 152 2.7925-01 0.000E,00 1.737E-15 7.679E-15 1.324E-14 2.315E-14 2.435E-14 1.997E-14 1.554E-16

)

0d 152 Gd 152 1.000E+00 1.00cE+00 9.946E-01 9.734E-01 9.474E-01 0.504E-01 7.633E-01 5.82EE-01 4.5095-03 Gd-152 68(j) :

1.000E+00 9. 94 6E-01 9.7345-01 9.474E-01 8.504E-01 7.633E-01 5. 8265-61 4.5095-03 l

Eu 154 Eu 154 1.000E+00 1.000E+00 9.193E-01 6.565E 01 4.310E-01 8.005E-02 1.487E 02 2.211E-04 3.7935-37 Eu-155 Eu-155 1.000E+00 1.000E+00 8.649E-01 4.8405-01 2.342E 01 1.285E-02 7.0495 04 4.969E-07 0.000B+00 Fe-55 Fe 55 1.000E+00 1.000E+00 1.712E-01 2.728E-01 7.440E-02 4.1188-04 2.2795-06 5.1965-12 0.000E+00 N-3 N3 1.000E*00 1.000E+00 4.432E-13 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0J 0.000E+00 Sr-90 St-90 1.000E+00 1.000E+00 8.808E-01 5.301E-01 2.810E-01 2.219E-02 1.7522 03 3.069E-06 0.000B+00 4444444 4444444 444444444 444444444 444444444 444444444 444444444 444444444 444444444 444444444 444444444 BRFli) is the branch fraction of the parent nuclide.

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