ML20091R000

Forwards Application Requesting Approval to Amend Previous Approval Granted Under 10CFR20.302(a) for Disposal of Contaminated Septic Waste,To Include Slightly Contaminated Cooling Tower Silt Matl

ML20091R000
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	08/30/1995
From:	Duffy J VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BVY-95-97, NUDOCS 9509060177
Download: ML20091R000 (28)

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VERMONT YANKEE NUCLEAR POWER CORPORATION Ferry Road, Brattleboro, VT 05301-7002

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ENGINEERING OFFICE 58C MAIN STREET BOLTON, M A 01740 (508) 779-6711 Augasi 30,1995 BVY 95 - 97 United States Nuclear Regulatory Commission Washington, DC 23555 A'ITN: Document ControlDesk

References:

(1) License No. DPR-28 (Docket No. 50-271)

(2) Letter from R. W. Capstick, Vermont Yankee, to USNRC, " Request to Routinely Dispose of Slightly Contaminated waste in Accordance with 10CFR20.302(a)", BVY 89-59, June 18,1989.

(3) Letter from M. B. Fairtile, USNRC, to L.A.Tremblay, Vermont Yankee,

" Approval Under 10 CFR 20.302(a) of Procedures for Disposal of Slightly Contaminated Septic Waste On Site at Vermont Yankee (TAC No. 73776)",

dated August 30,1989.

Subject:

Request to Amend Previous Approval Granted Under 10 CFR 20.302(a) for Disposal of Contaminated Septic Waste In accordance with the criteria of the Code of Federal Regulations, Title 10, Section 20.2002 (previously cited 10CFR20.302(a)), enclosed please find the subject application to amend the previously granted appmval(Reference 3) to dispose of slightly contaminated septic waste on site at Vermont Yankee by ex)anding the allowable waste stream to include slightly contaminated Cooling Tower silt materia..

This application specifically requests approval to dispose of Cooling Tower sih deposits, contaminated at minimallevels, which have been or might be generated through the end of station operations at the Vemient Yankee Nuclear Power Plant. The proposed silt disposal method is the same as the septic waste disposal method requested in Reference 2 and approved in Reference 3.

The disposal method utilizes on site land spreading in the same designated amas used for septic waste. Disposal of this waste in the manner proposed, rather than holding it for future disposal at a 10CFR Part 61 licensed facility when access to one becomes available, will save substantial costs and valuable disposal site space for waste of higher radioactivity levels.

A radiological assessment and proposed operational controls based on continued on site disposal of accumulated river silt removed from the basins of the plant's mechanical draft cooling towers is contained in Enclosure A. 'Ihe assessment demonstrates that the dose impact expected from the disposal of silt removed from the cooling towers during normal maintenance will not exceed the dose limits already imposed for septic waste disposal. The combined radiological impact for all on site disposal operations shall be limited to a total body or organ dose of a maximally exposed member of the public of less than one nurm/ year during the period of active Vermont Yankee control of the site, orless than five mrem / year to an inadvenent mtruder after tennination of active 1

site control. Enclosure B contains a copy of the original assessment and disposal procedures for 9509060177 950930 PDR ADOCK 05000271 i

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VERMONT YANKEE NUCLEAR POWER CORPORATION septic waste (References 2 and 3) for your use and reference in evaluating the proposed amendment.

Upon accipt of your approval, Enclosure A will be incorporated into the Vermont Yankee ODCM.

We trust that the infornution contained in the submittal is sufficient, however, should you luve any questions or require further information concerning this matter, please contact this office.

Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION fiffl60

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James J. Duffy Licensing Engineer Enclosures A & B c: USNRC Region I Administrator (letter and Encloare A)

USNRC Resident Inspector - VYNPS (Ixtter and Enclosure A)

USNRC Project Manager-VYNPS (letter and Enclosure A)

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ENCLOSURE A 4

VERMONT YANKEENUCLEAR POWER PLANT i

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ASSESSMENT OF ROUTINE DISPOSAL OF COOLING TOWER SILT IN AREAS ON SITE PREVIOUSLY DESIGNATED FOR SElrrIC WASTE DISPOSAL 3

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a Table of Contents 9

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1.0 INTRODUCTION

3 2.0 WASTE STREAM DESCRIPTION..................................

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3.0 DISPOSAL METHOD...........................................

9 3.1 Silt Disposal Procedure Requirements...............

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3.2 Administrative Procedure Requirements............... 12 l

4.0 EVALUATION OF ENVIRONMENTAL IMPACTS.....................

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4.1 Site Charac te ristics...............................

13 4.2 Radiological Impact................................. 13 5.0 RADIATION PROTECTION......................................

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6.0 CONCLUSION

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7.0 REFERENCES

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VERMONT YANKEE NUCLEAR POWER PIANT Assessment of Routine Disposal of Coolinn Tower Silt In Areas On Site Previously Desienated for Septic Waste Disposal

1.0 INTRODUCTION

Vermont Yankee Nuclear Power Corporation (Vermont Yankee) requested from the NRC in 1989 permission to routinely dispose of slightly contaminated septic waste in designated on site areas in accordance with 10CER20.302(a). The NRC responded to this request on August 30, 1989 by granting approval of the proposed procedures for on site disposal of septic waste concluding that the commitments as documented in our request were acceptable, provided that our request and analysis be permanently incorporatec* into the plant's Offsite Dose Calculation Manual (ODCM). Revision 9 to the ODCM (Appendix B) incor-porated the assessment and approval of the methods utilized for on site dis-pose of slightly contaminated sewage sludge.

In addition to the previously identified solids content of septic waste as a source of environmental low level radioactive contaminated material, cooling tower silt deposits resulting from the settling of solids from river water passing through the mechanical draft cooling tower system have been identi-fied to also contain low levels of plant specific radionuclides.

Periodic removal of the silt from the cooling tower basins is a necessary maintenance practice to insure operability of the cooling system.

However, due to the presence of by-product materials in the silt, proper disposal requirements must be applied to insure that the potential radiological impact is within acceptable limits.

This assessment of silt disposal repands the original septic waste disposal assessment to include earthen type materials (cooling tower silt deposits) while maintaining the original radiological assessment modeling and dose limit criteria that have been approved for septic waste spreading on site.

This assessment demonstrates that cooling tower silt can be disposed of in the same manner, and under the same dose limit criteria as previously ap-proved for septic waste in Appendix B to the Vermont Yankee ODCM.

Implemen-tation of the following commitments as an amendment to the original 10 CFR i

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Part 20.302(a) approval for septic waste shall be incorporated into the Vermont Yankee ODCM upon approval by the NRC.

2.0 WASTE STREAM DESCRIPTION:

The waste involved in this assessment is residual solids (silt) collected in the basins of the plant's mechanical draft cooling tower system.

silt consists of organic and inorganic sediments and earthen type materials that have settled from the cooling water flow taken from the Connecticut River as it passes through the towers. As a result of de-sludging of the tower basins in 1993, an estimated 14,000 cubic feet of silt was accumulated on site.

Clean-out operations will also occur periodically to ensure continued system operability.

Sample analysis performed to the plant's environmental lower limits of detection requirements, as contained in Technical Specifica-tion Table 4.9.3., has identified Cobalt-60 and Cesium-137 in low concentra-tions as being present in silt collected in 1993.

The cooling towers are located at the southern end of the plant facility complex, but are not directly connected to any system in the plant that contains radioactivity.

The postulated mechanism of how plant-related radionuclides have been introduced into the cooling system silt assumes that past routine effluents discharged from nearby plant gaseous release points were entrained in the large mechanically induced air flow that is pulled through the towsrs as a heat exchange medium.

The cooling water flow pro-vides a scrubbing action as it is breaks up into fine water droplets due to the splash pans of the towers.

This scrubbing action washes any airborne particulates out of the air. Over long periods of operation, any radioac-tivity removed from the air flow could buildup to measurable levels in silt that settles out in the basins at the bottom of the towers.

Table 1 lists the analyses of twenty-one samples collected from the silt pile removed from the cooling tower basins. Radioactivity measurements, averaged over all the samples, indicate that the silt material can be char-acterized as containing approximately 50 pCi/kg (dry wt.) of Cobalt-60, and 198 pCi/kg (dry wt.) Cesium-137.

Eight of the samples indicated no positive Cobalt-60 above a minimum detectable 1cvel achieved for the analysis.

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I Table 1 4

Cooling Tower Silt Radioactivity (1993 samples *)'

f Sample #

co.60-Cs.137' (pci/kg dry)

(pCi/kg dry) 5 i

G12759 53 144 C12758 72 172 f

l G12757

<14 201 G12756

<17 245

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G12755 73 206 C12754

<16 165 G12753

<27 240 i

G12752 79 181 1

G12751

<29 180 G12750 35 107-r i

G12749 59 171 G12748

<19 205 r

G12747

<38 209 G12746

<7 218 i

i G12745 50 241 l

G12744 40 220 i

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G12743 68 264 i

G12742 45 195 s

G12724 71 115 G12723 104 264 i

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G13940 126 218 Average:

50 198 i

Max.

126 264 Min.

<7 107 Standard deviation:

30 42 I

• Average wet to dry sample weight ratio equal to 1.6.

Dry weight silt j

density equal to 1.3 gm/cc.

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For the purpose of estimating the total activity in the silt pile, the less than values in Table 1 are included as positives in the calculation of the average radioactivity concentration.

Cobalt-60, due to its relatively short half life, is typically associated with plant operations when measured in the near environment.

However, Cesium-137 when measured in the environment may have a background component that is not related to power plant operations.

Past weapons testing fallout has imposed a man made background level of Cesium-137 in New England soils and sediments that can vary over several hundred pCi/kg.

The plant's Envi-ronmental Monitoring Program has shown that Connecticut River sediment in the vicinity of Vermont Yankee averages about 123 pCi/kg (dry wt.) of Cesi-um-137 (Table 2), with no plant related detectable level of Cobalt-60. The value of 123 pCi/kg may represent an estimate of the background level of Cesium-137 in sediment that would be subject to entrainment in cooling water flow that enters the plant.

In comparing the measured levels of Cesium-137 on Table 1 with the past river sediment level, the average concentration in the cooling tower silt is higher than that of the river sediment data, but does fall within the obcerved range of recorded sediment Cs-137.

The river sediment Cesium-137 concentration averages about 62% of the concentration value detected in the tower silt.

For purposes of this assessment of plant related dose impact from the on site disposal of silt material, it is con-servatively assumed that all detectable Cs-137 in cooling tower silt is directly related to plant operations. No background component is subtracted from the measured values for this case study since only a single sampling location (down stream) is included in the Environmental Monitoring Program which may not fully describe the true background levels in the region.

The total radioactivity for the current 14,000 cubic feet of silt collected on site can be estimated by multiplying this volume by its "as is" density of 2.1 gm/cc (i.e. 1.3 gm/cc dry weight density x 1.6 wet / dry weight ratio).

and then conservatively assume that the measured average dry weight radioac-tivity concentrations for Cobalt and Cesium would be the same as in the collected silt. Multiplying the average Cobalt-60 and Cesium-137 concen-tration in silt by the mass of the collected material produces estimates (Table 3) of total radioactivity that was removed from the cooling tower basin in September, 1993.

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. Table 2 f

Cesium.137 in' Connecticut River Sediments

• Date Cs-137 (pci/kg dry) 05/24/94 61 10/13/93 85 f

06/02/93 60 10/15/92 137 05/20/92 176 10/24/91 178 05/16/91 230 10/25/90 84 i

05/16/90.

62 10/04/89

<174 05/26/89 179 10/12/88 115 05/12/88 62 Average:

123 l

Max.

230 Min.

60 i

Standard deviation:

56

• Samples collected as part of the Vermont Yankee Radiological Environmen-tal Monitoring Program (REMP) for river sediment sample location SE-11.

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i Table 3 i

Estimated Total Radioactive Material for 1993 Tower clean.out Volume of Mass Average

. Total Act.

Decayed Act.

l Silt Concentration (as of (as of 11/93) 6/95) j (ft3)

(kg)

(pci/kg)

(uci)

(uCi) l l

I Co.60-14,000 8.32E+5 50 42 34 1

f ce.137 14,000 8.32E+5 198 165 159 i

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In addition to 14,000 cubic feet of silt already accumulated, it is antici-I pated that periodic maintenance work in cleaning out the cooling tower basins will generate approximately 4,000 cubic feet of new silt material over each successive 18 month operating cycle.

Assuming the same level of plant-related radioactivity concentration that was originally observed, the additional amounts of radioactivity tbst will require on site disposal following each refueling cycle can also be estimated. Table 4 lists an estimate of the total radioactivity that might be present at each 18 month clean-out cycle, i

Table 4 Estimated Total Radioactive Material for Each 18 Month Maintenance Cvele Volume of Mass Average Total Activity Silt Concentration (ft3)

(kg)

(pCi/kg)

(uci)

Co.60 4,000 2.38E+5 50 12 Cs.137 4,000 2.38E+5 198 47 8

3.0 DISPOSAL METHOD:

The method of silt disposal shall utilize a technique of land spreading in a manner consistent with the current commitments for the on site disposal of septic waste as approved by the NRC and implemented as Appendix B of the Vermont Yankee ODCM (Reference 1).

The same land areas designated and approved for septic waste disposal shall be used for the placement of silt removed from the cooling tower basins. Determination of the radiclogical dose impact shall also be made based on the same models and pathway assump-tions as indicated in Appendix B of the ODCM.

3.1 Ellt Disposal Procedure Reauirements:

Gamma isotopic analysis of silt samples shall be made prior to each disposal by obtaining representative composite samples in sufficient numbers to characterize the material removed from the cooling tower basins.

Each gamma isotopic analysis shall be required to achieve the environmental lower limits of detection as indicated for sediment on T ble 4.9.3 of the Vermont Yankee Technical Specifications.

The estimation of total radioactivity to be disposed of shall be made based on the average of all composite sample analyses. The estimation of total radioactivity and projected dose impact shall be made prior to placing the collected silt on the designated disposal plots. The dose impact from each disposal operation shall be included with all past septic waste and silt spreading operations to ensure that the appropriate dose limits are not exceeded on any waste disposal area for the combination of all past opera-tions.

The established dose criteria requires that all applications of earthen type materials within the approved designated disposal areas shall be limited to ensure that dose to a maximally exposed individual (during the Vermont Yankee control period) be maintained less than 1 mrem / year to the whole body and any organ, and the dose to an inadvertent intruder following termination of site control be maintained less than 5 mrem / year to the whole body and any organ.

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J The limits on concentrations of radionuclides as addressed in Appendix B to e

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the ODCM for septic waste (i.e. each tank of septic sludge to be disposed are limited to a combined MPC ratio of less than 0.1) were included to ensure proper control was in-place to address the situation of small quanti-ties of relatively high concentration material. This limitation does not

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directly apply to silt deposits since the slit is handled as dewatered

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sediments as opposed to liquid slurries of septic waste.

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l For dry earthen type material such as silt, a specific radionuclide concen-tration limit shall be applied in place of the of the septic waste liquid MPC ratio. No soil associated with a sample analysis that identifies a plant related radionuclide in excess of the concentration limits of Table 5 will be permitted regardless of the total pathway dose assessment determined for the quantity material under consideration.

For the case where more than one radionuclide is detected, the sum of the ratio rule will be applied.

The measured concentration of each radionuclide divided by its limiting concentration value shall be added with the sum of all fractions equal to or less than 1.

This limiting condition will prevent small volumes of rela-tively high specific radioactivity from being spread on the disposal plots, and therefore reduce the potential for creating unexpected hot spots of j

concentrated material.

1 Table 5 lists, by radionuclide, soil concentration values that would gener-ate an annual external effective dose equivalent of 25 mrem / year if it were assumed that an individual continuously stood on an infinite plane of soil contaminated to a depth of 15 cm.

The assumptions of an infinite plane and continuous occupancy are conservative for situations where the amount of contaminated soil identified would not provide for a 15 cm soil depth over an extended surface area, and where disposal site access is limited. Twen-ty-five mrem / year was selected as a reference value based on the fact that it was a suitable fraction of the NRC annual dose limit (100 mrem / year per 10 CFR Part 20.1301) applied to members of the public from all station sources. The 25 arem/ year also equals the EPA dose limit from 40 CFR Part 190 which would apply to real members of the public offsite, and allow for credit to be taken in accounting for actual usage patterns such as occupancy time. The external dose factors provided on Table 5 were derived from Table E-2 of NUREC/CR-5512 (Reference 3).

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-Table 5 I

i Dry Soil Haximum Concentration Values

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Radionuclide Soil Concentration j

pCi/kg i

(eaual to 25 aren/vr) l r

Cr-51 1.51E+05 Mn-54 5.50E+03

.Fe-59 3.83E+03.

Co-58 4.70E+03 CO-60 1.82E+03 Zn-65 7.85E+03 Zr-95 6.18E+03 l

Ag-110m-1.66E+03 I

Sb-124-2.51E+03 Cs-134 2.95E+03 Cs-137 8.13E+03 Ce-141 7.85E+04 Ce-144 8.75E+04 Assumptions include infinite planar distribution, uniform depth distribution to 15 cm, soil density at 1.625E+06 gm/m3, external direct dose pathway only with a 100% occupancy' factor.

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3.2 Administrative Procedure Reauirements:

Dry silt material shall be dispersed using typical agricultural dry bulk surface spreading practices only in approved disposal areas on site.

Complete records of each disposal will be maintained.

These records will include the concentration of radionuclides detected in the silt, an estimate of the total volume of silt disposed of, the total radioactivity in each disposal operation as well as the total accumulated on each disposal plot at the time of the spreading, the plot on which the silt was applied, and the results of any dose calculations or maximum allowable accumulated activity determinations required to demonstrate that the dose limits imposed on these land spreading operations have not been exceeded.

The determination of the total radioactivity and dose calculations shall also include all past septic waste and silt disposal operations that placed low level radioactive materi-al on the designated disposal plots.

The periodic disposal of silt on each of the approved land spreading areas will be limited to within the same established dose and radioactivity crite-ria that have been approved for septic waste disposal.

Concentration limits that are applied to the disposal of earthen type mate-rials (dry soil) shall restrict the placement of small volumes of material that have relatively high concentrations of radioactivity such that direct exposure could not exceed a small proportion (25%) of the annual dose limits to members of the public that is contained in 10 CFR Part 20.1301.

Any farmer leasing land used for the disposal of silt deposits will be notified of the applicable restrictions placed on the site due to the land spreading of low level contaminated material. These restrictions are the same as detailed for septic waste spreading as given in Reference 1.

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. 4.0. EVALUATION OF ENVIRONMENTAL IMPACTS:

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4.1 Site Characteristics 1

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The designated disposal sites consist of two fields located on the Vermont l'

Yankee Nuclear Power Plant site. Both fields are on the plant property

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within the site boundary security fence. Site A contains an approximate f

ten-acre parcel of land centered approximately 2,000 feet northwest of the j

Reactor Building.

Site B consist of approximately two acres and is centered approximately 1,500 feet south of the Reactor Building.

These are the same l

land parcels approved by.the NRC for the land disposal of septic waste, and 4

are described in detail in Reference 1 along with the boundary restrictions j

for the placement of contaminated material.

4 Radiological assessments of septic waste disposal have determined that a f

single two-acre plot would be sufficient for the routine disposal of that

. waste stream over a 20 year period without exceeding the dose criteria to a j

maximum exposed individual or inadvertent intruder. As a result, the ten-f acre field to the northwest can be divided into five disposal plots, with 4

the two-acre site at the south end of the plant site providing a sixth plot.

It is therefore concluded that there is sufficient space within the already l

approved disposal plots to accommodate additional material from the cooling j

tower basins along with the septic waste without the likelihood of exceeding i

the approved dose limit criteria.

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t Since the residual organic and inorganic solids associated with river sedi-ment (silt) are similar to the sand and residual organic material remaining after decomposition of septic waste that is removed form the plant's septic 2-tanks, the conclusions of no significant environmental (non-radiological) impact associated with the disposal of septic waste are not changed by the addition of another earthen type material, namely silt.

4.2 Radiological Imoact:

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The amount of cooling tower silt, in combination with any septic waste disposals, will be procedurally controlled to insure doses are maintained within the prior approved limits (Reference 1).

These limits are based on 13 4

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past NRC proposed guidance (described in AIF/NESP-037, August 1986). The j

dose criteria require that the maximally exposed member of the general public receive a dose less than 1 mrem / year to the whole body or any organ due to the disposed material, and less than 5 mrem / year to the whole body or i

any organ of an inadvertent intruder, i

To assess the doses received by the maximally exposed individual and insd-vertent intruder resulting from silt spreading, the same pathway modeling, assumptions, and dose calculation methodsras approved for septic disposal J

are used. These dose models implement the methodologies and dose conversion 4

factors as provided in Regulatory Guide 1.109 (Reference 2).

1 Six potential pathways have been identified and include:

l (a) Standing on contaminated ground,

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(b) Inhalation of resuspended radioactivity, (c) Ingestion of leafy vegetables, (d) Ingestion of stored vegetables, (f) Ingestion of meat, and (g) Ingestion of cow's milk i'

i Based on the septic waste evaluations, the liquid pathway was determined to be insignificant.

Both the maximum individual and inadvertent intruder are assumed to exposed l

to these pathways with difference between them related to occupancy time.

l The basic assumptions used in the radiological analyses include:

,i (a) Exposure to ground contamination and resuspended radioactivity is for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> per year during the Vermont Yankee active I

control of the disposal sites, and continuous thereafter.

The 104 hour0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> interval is representative of a farmer's time spend on a plot of land (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week for 6 months).

(b) For the purpose of projecting and illustrating the magnitude of dose impacts over the remaining life of the plant, it is assumed that the current concentration levels of activity detected in silt remain 14

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' constant. Table 1 indicates the measured radioactivity levels for l

Cobalt-60 and Cesium-137 first noted in silt material.

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'(c) The maximum radiation source corresponds to the accumulation of 1

radioactive material on a single plot (two acre) within the approved i

disposal sites over a period of 13 operating cycles. This extends over the next 18 years until after the operating license expires.in

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2012. The initial application (referenced to June, 1995) consists of l

j 14,000 cubic feet of silt collected in 1993 along with the first periodic clean out of the tower basins that adds an additional 4,000

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cubic feet. All subsequent applications of 4,000 cubic feet occur at

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18 month intervals.

i (d) For the analysis of the radiological impact during the Vermont I

Yankee active control of the disposal sites, no plowing is assumed to take place and all dispersed radioactive material remains on the l

surface, forming a source of unshielded direct radiation.

j (e) No radioactive material is dispersed directly on crops for human j

or animal consumption.

Crop contamination is only through root up-take.

I (f) The deposition on crops of suspended radioactivity is insignifi-cantly small.

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(g) Pathway data and usage factors used in the analysis are the same as those used in the plant's ODCM assessment of off-site radiological impact from routine releases, with the exception that the fraction of l

stored vegetables grown on the contaminated land was conservatively increased from 0.76 to 1.0 (at present.w vegetable crops for human consumption are grown on any of the approved disposal plots).

(h) It is conservatively assumed that Vermont Yankee relinquishes

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control of the disposal sites after the operating license expires in 2012. (i.e., the source term accumulated on a single 2 acre disposal plot applies also for the inadvertent intruder).

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(i) For the analysis of the impact after Vermont Yankee control of the site is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inches of soil; but nonetheless, undergoes resuspension in air at the same rate as the unplowed surface contamination.

For direct ground plane exposure the self shielding a

i due to the six inch plow layer reduces the surface dose rate by about a factor of four.

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The dose models and methods used to generate deposition values and accumu-lated activity over the operating life of the plant are documents in Attach-ment 2 to Reference 1. Based on the measured concentrations and silt volumes d

noted in Section 2.0 above, the total radioactivity that remains on the disposal plots after the operating license expires is estimated on Table 6.

Table 6 Projected Radioactivity Builduo Due To Silt Screading Nuclide Contribution from Accumulation from 13 Total Remaining initial 14,000 ft3 cycles at 4,000 ft3/ea.

in year 2013 (uC1)

(uci)

(uCi)

Cobalt.60 3.2 61.9 65.1 Cesium.137 104.9 500.5 605.4 The calculated potential radiation exposure following the spreading of all silt material anticipated to be generated through the remainder of the operating license on a single two acre plot is provides on Tabic 7.

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Table 7 Dose Imoact Due to Continued Soreadinc to End of License Disposal Site Access Radiation Exposure Individual /Ornan Controlled by VYNPS 0.228 mrem /yr adult /whole body (max exposed individual) 0.820 mrem /yr max.

child / bone Uncontrolled by VYNPS 1.46 mrem /yr adult /whole body (inadvertent intruder after 2.41 mrem /yr max, child / bone license termination)

The individual pathway contributions to the total dose due to continued silt spreading are shown on Table 8:

Table 8 i

Pathway-Decendent Critical Organ Doses 1

Maximally exposed Inadvertent Intruder Individual / Organ Critical Individual / Organ j

(Child / Bone)

(Child / Bone)

Pathway (mrem /vear)

(mrem /vear)

Ground Irradiation 0.0474 0.957 Inhalation 0.00814 0.685 Stored Vegetables 0.528 0.528 Leafy Vegetables 0.0265 0.0265 Milk Ingestion 0.201 0.201 Meat Ingestion 0.00833 0.00833 Total:

0.82 2.41 17

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In addition, the isotopic breakdown of the critical organ doses listed above (Table 8) for the two detected radionuclides is seen to be:

Table 9 Isotonic Breakdown of Maximum Radiation Exoosures Radioactivity Dose Percent of Descriotion Isotone (uCi/2 acres)

(arem/vr) total During control Cs-137 605.4 0.805 9 51. 2 of disposal sites Co-60 65.1 0.0144 1.8 Max. organ:

child / bone 0.82 I

Termination of Cs-137 605.4 2.12 88.0 disposal site Co-60 65.1 0.29 12.0 Max. organ:

child / bone 2.41 f

For comparison to the total dose calculated assuming the continued disposal of silt removed from the tower basins through the end of the operating license, the dose from just the original 14,000 cubic feet collected is shown on Table 10.

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x Table 10

-Dose Imonet Due to Sinnie (14.000ft3) Silt Soreadine

-Discosal Site Access Radiation Runosure Individual /Orran Controlled by VYNPS 0.064 arem/yr adult /whole' body (max exposed individual 0.219 ares /yr max.

child / bone

'in 1995)

Uncontrolled by VYNPS 0.224 mrem /yr adult /whole body (inadvertent intruder after 0.393 mrem /yr max.

child / bone license termination)

Table 10 shows that the application of the silt material initially collected-(14,000 cubic feet) accounts for about 27 percent of the maximum individual organ' dose during the control period as compared to the scenario of contin-ued periodic silt spreading over the balance of the operating license.

This illustrates that. dose impacts from the material currently collected are well below the acceptance criteria of limiting the dose from any two acre plot to no more than 1 arem/ year during the cont;ol period, and 5 arem/ year after termination of the license, and is expected to remain below the acceptance criteria throughout plant life.

If unexpected buildup of radioactivity in future silt clean out operations were to occur, the option for use of alter-nate disposal plots remains available to ensure that the impact from any single two acre plot stays within the acceptance criteria.

Also of interest. are derived dose conversion factors which provide a means l

of' ensuring that septic and silt disposal operations remain within the pre-scribed radiological guidelines noted above. The critical organ (worst case), and whole. body dose factors for all pathways on a per acre bases are 19

i given on Table 11 for periods during Vermont Yankee control of the disposal site, and on Table 12 for post centrol periods associated with the inadvert-ent intruder scenario. The dose conversion factors have been expanded to include other potential radionuclide beyond the original five that were J

l addressed in Reference 1.

This provides a means to assess other nuclides if i

future disposal operations identify additional radionuclides not previously I

observed. The development of these additional nuclide dose conversion j

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factors utilize the same modeling and pathway assumptions as used to derive i

the factors for the original five radionuclide identified in septic waste.

The models for these site and pathway specific dose factors are those in Regulatory Guide 1.109 (Reference 2), and are described in detail in Attach-ment II to Reference 1.

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Table 11 4

All-Pathway Critical Orman / Whole Body Dose Conversion Factors 4

Durine Vermont Yankee Control of Discosal Sites 6

Nuclide Individual / Organ Critical Organ Whole Body Dose Factor Dose Factor (arem/yr per uCi/ acre)

Cr-51 Teen / Lung 1.14E-05 5.76E-06 i

Mn-54 Adult /CI-LLI 3.75E-04 1.93E-04 Fe-55

_ Child / Bone 6.45E-06 1.06E-06 Fe-59 Teen / Lung 4.61E-04 2.13E-04 Co-58 Teen / lung 3.27E-04 2.01E-04

'Co-60 Teen / Lung 7.17E-04 5.31E-04 Zn-65 Child / Liver 1.64E-02 1.03E-02 g

. Zr-95 Teen / lung 4.47E-04 1.34E-04 l

Ag110m Teen /GI-LLI 1.32E-02 5.24E-04 Sb-124 Teen / Lung 8.34E 04 3.54E-04 Cs-134 Child / Liver 3.18E-03 1.28E-03 Cs-137 Child / Bone 2.66E-03 7.02E-04 l

Ce-141 Teen / Lung 1.54E-04 1.50E-05 i

Ce-144 Teen / Lung 6.00E-04 2,44E-05 4

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J Table 12 All-Pathway Critical Orann / Whole Body Dose Conversion Factors Post Vermont Yankee Control of Disoosal Sites (Inadvertent Intruder)

Nuclide Individual / Organ Critical Organ Whole Body Dose Factor Dose Factor (mrem /yr per uCi/ acre)

Cr-51 Teen / Lung 5.89E 04 1.19E-04 3

Mn-54 Teen / Lung 1.02E-02 3.12E-03 Fe-55 Teen / Lung 3.50E-04 2.27E-05 Fe-59 Teen / Lung 2.55E-02 4.43E-03 Co-58 Teen / lung 1.59E-02 3.72E-03 Co-60 Teen / Lung 3.19E-02 9.09E-03 Zn-65 Child / Liver 1.89E-02 1.25E-02 Zr-95 Teen / lung 2.93E-02 2.99E-03 Ag110m Teen / Lung 3.59E-02 9.53E-03 Sb-124 Teen / Lung 4.73E-02 7.04E-03 Cs-134 Child / Liver 1.21E-02 9.36E-03 Cs-137 Child / Bone 6.98E-03 3.85E-03 Ce-141 Teen / Lung 1.21E-02 3.44E-04 J

Ce-144 Teen / Lung 5.00E-02 1.52E-03 22

4 5.0 RADIATION PROTECTION:

The disposal operation of silt material from the cooling tower basins will follow the applicable Vermont Yankee procedures to maintain doses as low as reasonable achievable and within the specific dose criteria as previously-approved for septic waste disposal (Reference 1).

6.0 CONCLUSION

S:

Silt collected from the cooling tower basins is an earthen type material that is similar in characteristics to septic waste residual solids with re-spect to the radiological pathway behavior and modeling, and can be disposed through on site land spreading on the same disposal plots as previously evaluated and approved for septic waste disposal. The radiological assess-ment of low level contaminated silt shows that the projected dose from the on site periodic spreading of this material will have no significant dose impact to members of the public and can be maintained below the approved dose limitations already in-place for septic waste.

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7.0 REFERENCES

I (1). Vermont Yankee ODCM, Appendix B; " Approval of Criteria for Disposal of Slightly Contaminated Septic Waste On-Site at Vermont Yankee".

(Included NRC approval letter dated August 30, 1989, VY request for approval date June 28, 1989 with Attachments I and II) i-(2) USNRC Regulatory Guide 1.109, Rev. 1; " Calculation of Annual Doses to 4

Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", date October 1977.

(3) NUREG/CR-5512, Vol. 1, " Residual Radioactive Contamination From Decom-missioning", Final Report, date October, 1992.

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ENCLOSURE B Approval Under 10 CFR 20.302(a) of Procedures for the Disposal of Slightly Contaminated Septic Waste On Site at Vermont Yankee -

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i ATTACHMENT 1 VERMONT YANKEF. NUCLEAR POWER PIANT J

APPLICATION FOR APPROVAL TO ROUTINELY DISPOSE OF SEPTIC WASTE WITH MINIMAL LEVELS OF RADIOACTIVITY 4

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-RECEIVED i

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UNITED STATES I

NUCLEAR REGULATORY COMMISSION SEP - 7 @

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C WASHINGTON, D. C. 20555

,/

August 30, 1989 gree Docket No. 50-271

?e.,

Mr. L. A. Tremblay Licensing Engineering Vermont Yankee Nuclear Power Corporation Engineering Office 580 Main Street Bolton, Massachusetts 01740-1398

SUBJECT:

APPROVAL UNDER 10 CFR 20.302(a) 0F PROCEDURES FOR DISPOSAL OF SLIGHTLY CONTAMINATED SEPTIC WASTE ON SITE AT VERMONT YANKEE (TACNO.73776)

REFERENCE:

(a) June 28,1989 letter from R. W. Capstick to US HRC Document Control Desk, including Attachment I and Attachment II.

(b) Final Environmental Statement related to the operation of Vermont Yankee Nuclear. Power Station, dated July 1972.

In reference (a) Vermont Yankee Nuclear Power Corporation (Vermont Yankee, or the licensee) submitted an application toi disposal of licenseo materias on site.

This disposal was not previously considered oy the stair in 1.ne Vermoni. Yanitie Final Environmental Statement (FES), reference (b). This extensive application, prepared in accordance with 10 CFR 20.302(a), contains a detailed description of the licensed material, thoroughly analyzes and. evaluates the information pertinent to the effects on the environment of the proposed disposal of the licensed material, and commits the licensee to follow specific procedures to minimize the risk of unexpected or hazardous exposures.

In the FES, the 'fRC staff considered the potential effects on the environment of licensed material from operation of the plant and, in the assessment of the total radiological impact of the Vermont Yankee Station concluded that:

... operation of the Station will contribute only an extremely small increment to the radiation dose that area residents receive from natural background. Since fluctuations of the back-ground dose may be expected to exceed the increment contributed by the plant, the dose will be immeasurable in itself and will constitute no meaningful risk to be balanced against the benefits of the plant."

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Mr. L. A. Trenblay August 30, 1989

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9 Since the disposal proposed by the licensee involves licensed material containing less than 0.1 percent of the radioactive materials, primarily cobalt-60 and cesium-137, already considered acceptable in the FES, and involves exposure pathways much less significant than those considered in the FES, we consider the site-specific application (Reference (a)) for Vermont 2

Yankee Nuclear Power Station to have insignificant radiological impact. We accept the commitments and evaluations of the licensee, documented in reference 3

(a), as further assurance that the proposed disposal procedures will have a negligible effect c. the environment and the general population in comparison i

i to normal background radiation.

In conclusion. we find the licensee's procedures with commitments as documented L90E in reference (a) to be acceptable. orovided that reference (a) is permanentiv incorporated into the licensee's Offsite 00se Calculation Manual (00CM) as an a $5 bib -

, Appendix, and future modifications of reference (a) be reported to NRC in

.I accordance with licensee commitments regardina ODCM chances.

Pursuant to 10 CFR 51.22(c)(9), no environmental assessment is required. This l

completes our review under TAC No.73776.

Sincerely,

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%tL;n,3.%:wo Morton B. Fairtile, Project Manager Project Directorate I-3 i

Division of Reactor Projects I/II Office of Nuclear Reactor Regulation I

cc: See next page i

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1 Mr. L. A. Tremblay -

i cc:

Mr. J. Gary Weigand.

G. Dean Weyman.

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President & Chief _ Executive Officer Chairman,. Board of Selectman i

-Vermont Yankee Nuclear Power Corp.

Post Office Box 116 mH R.D. 5, Box 169 Vernon, Vermont 05354 Ferry Road

,Brattleboro, Vermont 05301 Mr. Raymond N. McCandless

'i Vermont Division of Occupational

Mr. John DeVincentis, Vice President and Radiological Health Yankee Atomic Electric Company Administration Building j

580 Main Street Montpelier, Vermont 05602

-Bolton, Massachusetts 01740-1398 i.

Honorable John J. Easton i

cNew England Coalition on Nuclear Attorney General i

Pollution State of Vermont 109 State Street j

j Hill and Dale Farm i

R.D. 2, Box 223 Montpelier, Vermont 05602 i

Putney, Vermont 05346 s

Conner & Wetterhahn, P.C.

Vermont Public Interest Research Suite 1050..

)

Group, Inc.

1747 Pennsylvania Avenue, N.W.

l 43 State-Street Washington, D.C.

20006 Montpelier, Vermont 05602 i

Diane Curran, Esq.

Regional Administrator, Region I Harmon, Curran & Tousley i

U.S. Nuclear Regulatory Comission 2001 S Street, N.W., Suite 430 475 Allendale Road Washington, D.C.

20009 l

King of Prussia, Pennsylvania 19406 David J. Mullett, Esq.

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R. K. Gad, III Special Assistant Attorney General Ropes & Gray Vermont Department of Public Service l

225 Fra.nklin Street 120 State Street Boston, Massachusetts 02110 Montpelier, Vermont 05602 l

Mr. W. P. Murphy, Vice President Jay Gutierrez j

and Manager of Operations Regional Counsel l

Vermont Yankee Nuclear Power Corporation U.S. Nuclear Regulatory Comission l

R.D. 5, Box 169 475 Allendale' Road Ferry Road King of Prussia, Pennsylvania 19406 Brattleboro, Vermont 05301 l

G. Dana Bisbee, Esq.

Mr. George-Sterzinger, Comissioner Office of the Attorney General Vermont Department of Public Service Environmental Protection Bureau l

120 State Street, 3rd Floor State House Annex

. Montpelier, Vermont' 05602 25 Capitol Street Concord, New Hampshire 03301-6397 i

Public Service Board State of' Vermont-Atomic Safety and Licensing Board l

120 State Street U.S. Nuclear Regulatory Comission Montpelier, Vermont 05602 Washington, D.C.

20555 l

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Mr. L. A. Tremblay ' -

3 CC:

Mr. Gu' stave A. Linenberger,Jr.

Administrative Judge

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Atomic Safety and Licensing Board 1

U.S. Nuclear Regulatory Comission Washington, D.C.

20555 Resident Inspector

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Vermont Yankee Nuclear Power Station U.S. Nuclear Regulatory Comission P.O. Box 176 Vernon, Vermont 05354 John Traficonte Esq.

Chief Safety Unit Office of the Attorney General One Ashburton Place,19th Floor Boston, Massachusetts 02108 9

• Geoffrey M. Huntington, Esquire Office of the Attorney General Environmental Protection Bureau State House Annex w-25 Capitol Street Concord, New Hampshire 03301-6397 i

Charles Bechhoefer, Esq.

Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comission Washington, D.C.

20555 Dr. James H. Carpenter Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comission Washington, D.C.

20555 Adjudicatory File (2) i Atomic Safety and Licensing Board

~,

Panel Docket U.S. Nuclear Regulatory Comission i

Washington, D.C. 20555 (25) f

VERMONT YANKEE NUCLEAR POWER CORPORATION eq-Ferry Road, Brattleboro, VT 05301-7002 ENGINEERING OFFICE

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58o uAIN STREET 1

June 28, 1989 soLToN.uA omo BVY 89-59 posinm u United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk

Reference:

License No. DPR-28 (Docket No. 50-271).

Subject:

Request to Routinely Dispose of Slightly Contaminated Septic Waste in Accordance with 10 CFR 20.302(a)

Dear Sir:

In accordance with the criteria of the Code of Federal Regulations, Title 10, Section 20.302(a) ( 10 CFR20.302 (a ) ), enclosed please find the subject application for the disposal of very low level radioactive vaste materials. Vermont Yenkee Nuclear Power Corporation (Vermont Yankee) hereby requests NRC approval of the proposed procedures for the disposal of slightly contaminated septic waste generated at the Vermont Yankee Nuclear Power Plant in Vernon, Vermont.

This application specifically requests approval to dispose of septic tank waste, contaminated at minimal levels, which have been or might be generated through the end of station operations at the Vermont Yankee Nuclear Power Plant. The proposed method of disposal is for the on-site land spreading in designatied areas in compliance witti State of Vermont health code requirements for septic waste. Disposal of this vaste in the manner proposed, rather than at a 10CER Part 61 licensed facility would save Vermont Yankee not only substantial cost, but also valuable disposal site space which would then be available for wastes of higher radioactivity levels. Disposal as radioactive waste would require treatment of the biological aspects of the septage and solidification to a stable vaste form, thereby increasing the volume substantially.

A radiological assessment and proposed operational controls, based upon the continued on-site disposal of septic waste as presently contained in the plant's septic tanks, are detailed in Attachments 1 and 2.

Based upon this analysis, Vermont Yankee requests approval to dispose of septic tank waste on-site by land spreading in such a manner that the radioactivity concentration limit in any batch of septage to be spred does not exceed one-tenth of the MPC values listed in 10CFR20, Appendix B Table II; and the combined radiological impact for all disposal operations shall be limited to a total body or organ dose of a maximally exposed member of the public of less than one crea/ year j

(less than 5 mrem / year to an inadvertent intruder).

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4 United States Nuclear Regulatory Commission June 28, 1989 Page 2 l

Due to our expected need to utilize the proposed methodology of land application of septic waste on-site during the spring of 1990, we request I

your review and approval of. this proposed disposci method by the end

y of the first quarter of 1990.

We trust that the information contained in the submittal is. suf ficient; however, should you have any questions or require further information concerning this matter, please contact this office 1

Very truly yours, i

VERMONT YANKEE NUCLEAR POWER CORPORATION

/

Robert W. Caps ick, Jr.

I Licensing Engineer MSS /emd 1

j Enclosures 1

cc: USNRC - Region I USNRC - Resident Inspector, VTNPS k

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ATTACHMENT 1 VERMONT YANKEE NUCLEAR POWER PLANT Application for AppInyal to Rout.inelv Dispose of Septic Waale With Minimal Levels of Radioactivity

1.0 INTRODUCTION

Vermont Yankee Nuclear Power Corporation (Vermont Yankee) requests approval, pursuant to 10CFR20.302(a), of a method proposed herein for the d

routine disposal of slightly contaminated septic tank wt ce.

Vermont Yankee proposes to dispose of this waste by spreading it on designated areas within the plant's site boundary fence. This application addresses specific information requested in 10CFR20.302(a).

2.0 WASIE_ STREAM DESCRIPTION The waste involved in this application consists of residual solids and water associated with the sewage collection system at Vermont Yankee. The plant's sewage systems are of the septic tank and disposal field type. The two systems servicing the majority of the plant's sanitary waste are identified as (1) main septic system and (2) the south sewage disposal system.

4 The main septic system (design flow capacity 4,950 gallons / day) l consists of a wastewater lift station, septic tank, and dual alternating i

disposal fields located on the north side of the plant.

This system services

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the main complex of buildings central to the plant and processes approximately 3,500 gallons of wastewater per day.

The septic tank, shown in Figure (1),

will typically contain 9,250 gallons of septage.

The south sewage disposal system is a newly-installed (January 1989) pressurized mound system, which is used in lieu of the construction office building (COB) holding tank that had previously serviced the lavatory l

facilities on the south end of the plant. The new system is composed of a septic tank (5,700 gallon capacity, see Figure 2), pumping station, and pressurized mound disposal field. When dosing the field, a force main pressurizes the disposal field's piping system with the septic tank effluent, which distributes throughout the field.

The south sewage disposal system has 1-1 6677R

4 the design flow capacity to process 4,607 gallons of wastewatec per day. The system is typically loaded at approximately 2,500 gallons per day during normal plant operations. Figure (3) indicates diagramatically the flow of both potable and wastewater throughout Vermont Yankee.

Both the main septic system and the south sewage disposal system's septic tanks collect waste from the plant's lavatories, showers, kitchens, and janitorial facilities outside the Radiological Control Area (RCA). No radioactivity is intentionally discharged to either of the septic systems.

However, plant investigations into the source of low levels of contamination found in septic waste have identified that very small quantities of radioactive materials, which are below detection limits for radioactivity releases from the RCA, are carried out of the control area on individuals and accumulate in the septic waste collection tanks by way of floor wash water, showers, and hand washing. As a means of minimizing the transport of radioactive materials into the septic collection tanks, the primary source of the radioactivity (i.e., floor wash water) is now poured through a filter bag r

to remove suspended solids and dirt before the water is released into a janitorial sink.

The majority of the radioactivity found in waste sludge has been i

associated with the main septic tank. Grab samples of sludge from the bottom of the COB and main septic tank were analyzed by gamma spectroscopy with the j

following results of plant-related radionuclides:

Activity Concentration Isotope

+1 Sigma (pci/kg Wet)

COB Sludge Cs-137 10.3 i 1.8 (June 8, 1988)

Co-60 45.4 i 3.1 Main Tank Sludge Mn-54 39.3 1 4.3 l

(June 8, 1988) 0o-60 853.0 i 12.0 In-65 52.7 i 8.2 Cs-134 13.0 1 2.2

{

Cs-137 120.7 i 5.2 I

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The principle radionuclide is Cobalt-60, which accounts for 79% of the plant related activity in the septage samples.

In comparison to in-plant smear samples taken for 10CFR61 waste characterizations, the septage sample from the main tank correlates very close with the distribution of radionuclides identified in-plant as shown below:

Relative Isotopic Distributions Jintspe In-Plant Smears tiain Tank Sludge Mn-54 3.6%

3.6%

Co-60 81.5 79.1 Zn-65 3.8 4.9 Cs-134 0.4 1.2 Cs-137 10.3 11.2 Additional analyses of the main tank septage showed that the liquid portion of the collected sample did not contain any plant-related activation or fission products, and that essentially all of the activity in the waste was I

associated with the solid sludge fraction. The average density of the collected sludge was found to be approximately equal to that of water, with a wet to dry ratio of 25.4 to 1.

I Both the liquid and solid fractions of the main tank septic waste were also analyzed for strontium with no detectable activity found.

The liquid portion of the waste cample was also analyzed'for tritium with no activity above the minimum detectable levels found. Appendix A to Attachment 2 contains the laboratory analysis reports of the samples taken from the COB and main septic tanks.

Prior to identification of the plant-related radioactivity in septage waste, the COB holding tank was being pumped on the avecage of twice per week, with the sludge and waste liquid transported off-site primarily to the Brattleboro, Vermont, sewage treatment facility. Waste from the main septic tank was being pumped and transported off-site for disposal on the average of twice per year.

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With the replacement of the COB holding tank by the new south sewage disposal system, and the requested implementation of on-site land disposal of accumulated septic waste, the frequency of collection tank pump-outs with land application of the waste is expected to be once per year. With the past pump-out f requency of the main tank being every six months, the accumulation of sludge at the bottom of the tank was well below its design capacity.

During the 1988 sample collections, it was estimated that the sludge thickness was less than 1 foot of its 6-foot depth. However, for conservatism in the l

radiological evaluations, it is assumed that the sludge layer in the main septic tank'and south disposal tank occupies 30% of their combined design volume, and that the frequency of pump-outs is semiannual as opposed to the expected annual cycle. Also, as noted above from laboratory analyses of the sludge layer take:n from the bottom of the main tank, the average density of the tank contents is approximately equal to that of water, with a wet-to-dry ratio of 25.4 to 1.

Hence, the weight of solids (W,gy) being disposed of is estimated, for purposes of this bounding dose assessment, to be approximately:

l sol = 14,950 [ gal] x 3,785.4 [cc/ gal] x 10-3 [kg/cc]

x 0.30 (solids fraction] x (1/25.4) [ dry / wet ratio}

~ 700 [kg) per pump-out of both tanks or, 1,400 kg of dry solids per year.

I 3.0 DISPOSAL METHOD 1

Approval of this application will allow Vermont Yankee to dispose of septage by utilization of a technique of land spreading or surface injection in a manner consistent with all applicabic state of Vermont health regulations regarding disposal of septic waste. Details of the chemical and biological controls necessary to satisfy state health code requirements are provided in Reference 5.

The septage will be spread or surface injected on land areas owned by Vermont Yankee and situated within the plant's site boundary. Transportution of the septage waste to the disposal areas will involve pumping from one of the septic waste collection tanks (i.e., main septic tank, COB holding tank, 1-4 1

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e new replacement COB septic tank, or from any other on-site septic waste collection point) into an enclosed truck-mounted tank.

The enclosed tank truck is used to prevent spillage while in traneit to the disposal areas. The P

septage will be transported to one of the two disposal sites designated for land application for septage from Vermont Yankee, and applied at a fixed rate 4

based on either limitations imposed by the state of Vermont for heavy metals or organic content of the waste, or on the radioactivity content such that projected maximum individual doses will not exceed established dose objectives.

4 I

3.1 Septic Waale_Diapssal Procedur.e l

Gamma isotopic analysis of septic waste shall be made prior to each disposal by obtaining a representative sample from each tank prior to pump-out. At least two septic waste samples will be collected from each tank to be pumped by taking a volumetric column of sludge and waste water which allows for analysis of the solid's distribution and content from top to bottom of each tank. The weight percent of solid content of the collected waste will be determined and applied to the gamma isotopic analysis in order to estimate the total radioactivity content of each tank to be pumped and spread on designated disposal fields.

l These gamma isotopic analyses of the representative samples will be performed at the environmental Technical Specification lower limit of detection (LLD) requirements for liquids (see Technical Specification Table 4.9.3) in order to document the estimation of radiological impact f rom septage disposal.

l The radionuclide concentrations and total radioactivity identified in the septage will be compared to the concentration and total curie limits established herein prior to disposal. The methodology and limits associated with determining compliance with the disposal dose and activity criteria are described in Attachment 2.

If the concentration and total activity limits are met, compliance with the dose assessment criteria will have been demonstrated since the radiological analysis (Section 4.5 and Attachment 2) was based on evaluating the exposure to a maximally exposed individual and inadvertent intruder af ter the accumulation of twenty years of periodic semiannual i

1-5 6677R

4 spreading of the septic waste on a single (2 acre) plot within one of the j.

designated disposal areas.

If'the activity limit per disposal area is projected to be exceeded, the appropriate exposure pathways as described in Section 4.5 will be evaluated prior to each additional application, or a separate plot within the designated disposal area will be utilized.

Annually, for years in which disposal occurs, the potential dose impact from disposal operations conducted during the year, including the impact from

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previous years, will be performed and results reported in the plant's Semiannual Radioactive Effluent Release Report which is filed af ter January 1.

All exposures will be assessed utilizing the methodology described in Attachment 2.

l The established dose criteria requires that all applications of septage within the approved designated disposal areas shall be limited to ensure the dose to a maximally-exposed individual be maintained less than 1 mres/ year to h

- the whole body and any organ, and the dose to the inadvertent intruder be maintained less than 5 mrem / year. The total activity based on the measured radionuclide distribution for any single disposal plot is not expected to J

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exceed the following:

i i

1 Maximum Accumulated Radioactivity Allowed Per Acre Isotope Qglim [ Ci]

Mn-54 1.4 Co-60 120.0 i

Zn-65 1.4 Cs-134 0.7 Cs-137 46.5 If any of the above. radionuclides are projected to exceed the indicated activity values, then dose calculations will be performed prior to spreading, in accordance with the methods detailed in Section 4.2.2 of Attachment 2, to l

make the determination that the dose limit criteria will not be exceeded.

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The concentration of radionuclides in any-tank of septic waste to be dispoced of will also be limited to a combined Maximum Permissible Concentration of Water (MPC)'(as listed in 10CFR, Part 20, Appendix B,

. Table II, Column 2) ratio of less than or equal to 0.1.

For radiological control, each application of septage will be applied on the designated land area.by approved plant procedure which adheres to the following assumptions which were used in developing the dose impact:

During surface spreading or injection, the septage, and any o

precipitation falling onto or flowing onto the disposal field, shall not overflow the perimeter of the designated area.

Septage shall not be surface spread or injected into the top 6-inch o

soil layer within 300 feet from any drinking water well supply.

Septage shall not be surface spread closer than 300 feet from the o

nearest dwelling or public building (or within 100 feet if injected into the top 6-inch surface layer).

Septage shall not be surface spread closer than 50 feet (or within o

25 feet if injected into the top 6-inch surface layer) from any roads or site boundary adjacent to land areas.

Septage shall not be surface spread within 100 feet (or within l

o 50 feet if injected into the top 6-inch surface layer) of any l

surface water (rivers, streams, drainage ditches).

Low areas of the approved fields, subject to seasonally high o

groundwater levels, are excluded from the septage application.

1 l

In' addition to the radiological controls to limit the total accumulation of radioactive materials released by septic waste spreading, state of Vermont health code requirements.will be followed to ensure the protection of the public and environment from chemical and biological hazards. The. application rate and acreage will be determined prior to each 1-7 6677R

disposal operation. This will vary with the chemical composition of the septage, the percent solids, and the radioactive concentrations.

3.2 Administrative Procedures Complete records of each disposal will be maintained.

These records will include the concentration of radionuclides in the septage, the total volume of septic waste disposed, the total activity in each batch as well as total accumulated on the disposal plot at time of spreading, the plot on which the septage was applied, and the results of any dose calculations required..

The annual disposal of septage on each of the approved plot areas will be limited to within the established dose, activity, and concentration i

criteria noted above, in addition to limitations dictated by chemical and biological conditions. Dose guidelines, and concentration and activity limits, will be maintained within the appropriate values as detailed in 5.

Any farmer using land which has been used for the disposal of septic waste will be notified of any applicable restrictions placed on the site due i

to the land spreading or injection of waste.

4.0 EVALUATION OF ENVIRONMENTAL IMPACT 4.1 Site _ Characteristics 4.1.1 Site TopograpAY The proposed disposal sites consist of two fields located on the i

Vermont Yankee Nuclear Power Plant site, which is located on the west bank of the Connecticut River in southwestern Vermont at latitude 42 degrees, 47 minutes north and longitude 72 degrees 31 minutes west. Both fields are on plant property within the site boundary and surrounded by a chain link fence.

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4 Site A contains an approximate eight-acre parcel of usable land i

centered approximately 2,200 feet..orthwest of the Reactor Building. Site B contains about two acres and is centered approximately 1,700 feet south of the l

i Reactor Building. The usable acreage of both the north and south disposal fields is restricted to those areas which have no slopes greater than five percent to limit surface runoff. A radiological assessment based on the 1988 measured radioactivity concentrations in sludge has determined that a single two-acre plot would be sufficient for the routine disposal of septage for twenty years without exceeding the dose criteria to maximum exposed individual or. inadvertent intruder. As a result, the eight-acre field to the northwest could be divided into four disposal plots, with the two-acre site at the south end of the plant site, providing a fifth plot. A portion of the United States Geological Survey topographic map (Brattleboro quadrangle),

showing the plant site, is presented in the Final Safety Analysis Report (FSAR) as Figure 2.5-1.

A plan map showing the plant site and the disposal sites is given on Figure 4.

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The sites are located along a glacial terrace on the west side of the Connecticut River. This terrace extends about 3,000 feet west rising gently and then more abruptly to a higher terrace and then to dissected uplands.

Distance to the east from the disposal sites to the river is at least 100 feet if septage is disposed of by surface spreading within the designated areas, or 50 feet if septage is injected directly into the soil.

i Relief of the proposed disposal sites is low, with elevation ranging between 250 feet and 265 feet (ms1). Mean water surface elevation of the

+

adjacent river is about 220 feet.

I The topographic character of the site and surrounding area is i

compatible with this use.

The spreading of septage at these locations will have no effect on the topography of the area.

i 1-9 6677R I

4.1.2 Site _Geningy 4

Profiles of site exploratory borings are shown in the FSAR in Figures 2.5-8 through 2.5-11.

Current site characteristics as determined from a 1

recent detailed site investigation can be found in Reference 5.

Composition of surfacial materials is compatible with the proposed use i

of the site for septic waste disposal.

i 4.2 Area _Characteristica 4.2.1 Mc129tn1Dgy The site area experiences a continental-type climate with some modification due to the marine climate which prevails at the Atlantic seacoast to the east. Annual precipitation averages 43 inches and is fairly evenly distributed in each month of the year.

Potential impacts on septic waste disposal include occasional harsh weather:

ice storms, severe thunderstorms, heavy rains due to hurricanes, the possibility of a tornado, and annual snowfall of from 30 to 118 inches per 4

year.

In addition, frozen ground can occur for up to 4 months of the year.

Septage spreading will be managed by written procedure such that material which is spread or a mix of that material with precipitation will not overflow the perimeter of the disposal site.

i i

Additional information on meteorology of the site can be found in Section 2.3 of the Final Safety Analysis Report.

4.2.2 Hydrnlagy Hydrology of the site and local area is tied closely to flow in the adjacent Connecticut River. River flow is controlled by a series of hydroelectric and flood-control dams including the Vernon Dam which is about 3,500 feet downstream of the site.

1-10 6677R 1

~

i All local streams drain to the' Connecticut River and the site is in the direct path of natural groundwater flow from the local watershed easterly toward the river. Site groundwater level is influenced by both precipitation-

]

l and changes in the level of ponding of the Connecticut River behind the Vernon Dam due to natural flow or dam operation.

Flood flows on the Connecticut are controlled by numerous dams 4

l including five upstream of the site. Elevation of the 100-year flood is about 1

228 ft (ms1); and, thus, well below the elevation of the proposed site which 3

~

ranges from about 250 to 265 feet (ms1). The 100-year flood level is based on t

I information presented in References (1) and (2).

L Septage disposal by means of land spreading on the proposed site will i'

have no adverse impact on area hydrology.

i s

i Further information about site hydrology is in Section 2.4 of the FSAR.

f l

l 1

4.3 Water Us. age l

4.3.1 Eurface Water i

The adjacent Connecticut River is used for hydroelectric power, for cooling water for the Vermont Yankee plant, as well as for a variety of recreational purposes such as fishing and boating. The Connecticut River is 4

not used as a potable water supply within 50 miles downstream of the plant.

i Locally, water from natural springs are used for domestic and farm purposes. FSAR Table 2.4.5 and Figure 2.4-2 show springs used within a 1-mile radius of the site.

FSAR Table 2.4.4 and Figure 2.4-1 show water supplies 1

with surface water sources which are within a ten-mile radius of the site.

i i

a There.will be no impact on surface water usage or quality as a result j

of'septage disposal due to the required separation distances between surface f

waters and the disposal plots.

1 i

1-11 6677R

4 i

1

)'

i 4.3.2 Groundwater Based on a review of groundwater measurements in various site borings presented in the FSAR and References 3 and 5, an upper estimate of groundwater levels at the plant is about 240 feet. Considering the proximity of the i

Connecticut River and Vernon Pond, with a mean water surface elevation of 220 feet, this estimate for the groundwater level appears to be reasonable.

Given the topography of the proposed dispoc al sites, it is highly unlikely 5

that the groundwater level will be within 3' feet of the disposal area surface l

1 elevation.

Prior to each application of septic waste to a disposal plot, the i

groundwater level in nearby test wells will be determined and no application

'will be allowed if the groundwater level in the vicinity of the disposal plot i

is found to be less than 3 feet.

i j

Groundwater provides potable water for public wells as shown in FSAR 4

j Table 2.4.5 and Figure 2.4-1.

Groundwater flow in the vicinity of the f

proposed disposal sites is towards the Connecticut River. There are no drinking-water wells located between the site and the river. Therefore, it is j

highly unlikely that any drinking water wells could be affected by septage disposal. FSAR Figure 2.4-2 and Table 2.4-5 present information on private wells near the plant.

i i

The Vermont Yankee on-site wells provide water for plant use.

This

]

I i

supply is routinely monitored for radioactive contamination.

i l

To quantify the impact of septage disposal on the Connecticut River, a i

conservative groundwater /radionuclide travel time analysis was performed. For an assumed average travel distance of 200 feet from the disposal site to the i

~

river, a groundwater travel time of 408 days was estimated from Darcy's Law.

2 This estimate is based on a permeability for the glacial till of 10 gpd/ft e

i a hydraulic gradient of 0.11 ft/ft, and a soil porosity of 0.3.

This analysis conservatively assumed that the septage placed on the ground was immediately available to the groundwater.

In practice, a minimum of 3 feet separation l

between groundwater and the surface will be required at time of application of the septic waste.

4 i

1-12 6677R 1

1

Due to ionic adsorption of the radionuclides on solid particles in the l

groundwater flow regime, most radionuclides travel at only a small fraction of the groundwater velocity.

For the radionuclides present in the sludge, retardation coefficients were developed from NUREG/CR-3130 (Reference 4).

Retardation coefficients for Co-60, Cs-137, and Cs-134 were directly obtained from NUREG/CR-3130.

The coefficients for Zn-65 and Mn-54 were conservatively estimated using NUREC/CR-3130 as a guide. The radionuclides, their half-lives, retardation coefficients, and their travel time to the river are summarized in Table 1.

i IARLE_1 Radionuclide Travel Times i

Retardation Travel Time Radionuclide Half Life Coefficient to River l

Co-60 5.3 years 860 961 years i

Cs-137 30.2 years 173 193 years Cs-134 2.1 years 173 193 years Zn-65 244 days 3

1,224 days Mn-54 312 days 3

1,224 days 1

The radiological impact on the river for the radionuclides reaching the i

river under this conservative analysis is discussed in Attachment 2.

Water usage of the Connecticut River downstream from the disposal area is limited to drinking water for dairy cows, irrigation of vegetable crops, and irrigation of cow and cattle fodder.

i Based on the assessments noted above, it is concluded that groundwater sources will not be adversely impacted as a result of septage disposal on the proposed site.

5 4.4 Land Use Both the eight-acre and two-acre sites proposed for the disposal areas are currently part of the Vermont Yankee Nuclear Power Plant Site inside the plant's site boundary which is enclosed by a chain link fence.

It is l

1-13 6677R

1 l

undeveloped except for transmission line structures which traverse a portion l

of the northern disposal area. Development potential is under the control of Vermont Yankee. At present, the eight-acre site on the north end of the plant property is used by a local farmer for the growing of feed hay for use with his dairy herd. No curtailment of this activity as a result of the low levels of radioactivity in septage will be necessary.

Utilization of the proposed sites for septic waste disposal will result in no impact on adjacent land or properties because of the separation of the disposal plots from off-site properties, the general msvement of groundwater toward the river and away from adjacent land areas, and the very low levels of radioactive materials contained in the waste. Administrative controls on spreading and the monitoring of disposal area conditions will provide added assurance that this proposed practice will not impact adjacent properties.

i 4.5 Radiological Impact 4

In addition to state of Vermont 10mits imposed on septage spreading, l

based on nutrient and heavy metal content, the amount of septage applied on each of the proposed disposal plots will also be procedurally controlled to 4

insure noses are maintained within the stated limits. These limits are based I

on NRC Nuclear Reactor Regulation (NRR) staff proposed guidance (described in AIF/NESP-037, August 1986). The proposed dose criteria require that the

)

maximally exposed member of the general public receive a dose less than 1 i

mrem / year to the whole body or any organ due to the disposal material, and less than 5 mrem / year to an inadvertent intruder.

4 To assess the doses received by the maximally-exposed individual and the inadvertent intruder, six potential pathways have been identified.

These include:

(a) Standing on contaminated ground, J

(b) Inhalation of resuspended radioactivity, 1-14 6677R

(c)- Ingestion of leafy vegetables, (d) Ingestion of stored vegetables, (f) Ingestion of meat, and (g) Ingestion of milk.

The liquid pathway was also evaluated and determined to be insignificant. Both the maximum individual and inadvertent intruder are assumed to be exposed to these pathways with difference between the two related to the occupancy time. The basic assumptions used in the radiological cnalyses include:

(a) Exposure to the ground contamination and to resuspended radioactivity is for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> per year during Vermont Yankee active control of the disposal sites, and continuous thereafter. The 104-hour interval being representative of a farmer's time on a plot of land (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week for 6 months).

(b) The septic tanks are emptied every 6 months.

(Expected practice is to pump septic tanks once per year.)

(c) The tank radioactivity remains constant at the currently determined level. To account for the uncertainty associated with the counting statistics, the measured activity concentrations listed in Section 2 were increased by 3 sigmas. That is, the activity concentrations employed in dose assessment and the total radioactivity content per pump-out (at 700 kg of solids per batch) are as follows:

i i

1-15 6677R

Upper-Bound Activity Upper-Bound Activity 1snippe Concentration IpfiLkg_sityl Content ICi/ tankful)

Mn-54 1,348 9.436E-07 Co-60 23,060 1.614E-05 Zn-65 1,620 1.134E-06 Cs-134 322 2.254E-07 Cs-137 4,100 2.870E-06 (d) The radiation source corresponds to the accumulation of radioactive material on a single plot (two-acre) within the proposed disposal sites over a period of 20 years (40 applications at 6-month intervals).

(In actuality, the proposed sites will accommodate more than one disposal plot, and, in practice, more than one plot will most probably be used with an application frequency of once per year.)

(e) For the analysis of the radiological impact during Vermont Yankee active control of the disposal sites, all dispersed radioactive material remains on the surface and forms a source of unshielded radiation.

(In practice, the septic waste will be either surface spread or directly injected within the top 6 inches of the disposal plot, in which case, the radioactive material will be mixed with the soil. This, in effect, would reduce the ground plane source of exposure by a factor of about four due to self-shielding.)

(f) No radioactive material is dispersed directly on crops for human or animal consumption, crop contamination being only through root uptake.

(g) The deposition on crops of resuspended radioactivity is insignificant 1y small.

1-16 6677R

(h) Pathway data and usage factors used in the analysis are the same as those used in the plant's ODCM assessment of the off-site radiological impact from routine releases,with the exception that I

the fraction of stored vegetables grown on the disposal plots was conservatively increased from 0.76 to 1.0 (at present no vegetable crops for direct human consumption are grown on any of the i

proposed disposal plots).

I 4

(i)

It is conservatively assumed that Vermont Yankee relinquishes control of the disposal sites after the fortieth pump-out (i.e.,

I the above source term applies also for the inadvertent intruder).

4 (j) For the analysis of the impact af ter Vermont Yankee control of the sites is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inches of soil; but, nonetheless, undergoes resuspension at the same rate as surface contamination.

From radiological impact assessments associated with the disposal of septage on different plot sizes (Attachment 2), it was determined that a single two-acre plot within the disposal sites would accommodate the 1 mrem / year prescribed dose to the critical organ of the maximally exposed individual for a period of up to 20 years, as well as the 5 mrem / year prescribed dose to the inadvertent intruder after control is assumed to be J

relinquished. The calculated potential radiation exposures following the spreading of 40 combined (main septic system and south disposal system) tankfuls (at six-month intervals) on a single two-acre plot are as follows:

ContrnLoLIlispnaal Sites Radiation Exposure Individual / Organ J

Controlled by VYNPS 0.1 mrem /yr Child /Whole Body (Maximum Exposed Individual) 0.2 mrem /yr Maximum Child / Liver

{

Uncontrolled 1.3 mrem /yr Adult /Whole Body (Inadvertent Intruder) 3.9 mrem /yr Maximum Teenager / Lung d

4 1-17 6677R

The individual pathway contributions to the total dose at the end of the 20-year accumulation of waste deposited on a single two-acre plot are as listed below:

fathway-Dspendent Critical Organ Doses Maximally Exposed Inadvertent Intruder Individual / Organ Critical Individual / Organ (Child / Liver)

(Teenager / Lung)

Eathw_ay (mrem / year)

(mrem /vear)

Ground Irradiation 0.0576 1.16 Inhalation 0.00122 2.74 Stored Vegetables 0.0913 0.00601 Leafy Vegetable 0.00467 0.00040 Milk Ingestion 0.0421 0.00229 Meat Ingestion 0.00249 0.00012 TOTAL 0.1994 3.909 In addition, an isotopic breakdown of the critical organ dose results listed above is shown in the following table:

Igninpic_ Breakdown of Maximum Radiation _ Exposures Radioactivity Exposure Dancriplinn lantope

.[yCi/2 Acresl Imrem/yrl During Vermont Yankee Mn-54 2.831 0.000436 control of the Co-60 235.3 0.0559 disposal sites.

Zn-65 2.801 0.0230 Maximally Exposed Cs-134 1.457 0.00231 Individual / Organ:

Cs-137 92.59 0.110 Child / Liver TOTAL 0.199 After Vermont Yankee Mn-54 2.831 0.0144 control of sites is Co-60 235.3 3.76 relinquished.

2n-65 2.801 0.00983

]

Inadvertent Intruder Cs-134 1.457 0.000505 l

critical Individual /

Cs-137 92.59 0.1247 1

Organ: Teenager / Lung f

1-18 6677R i

Of interest are also derived dose conversion factors which provide a means of ensuring septage disposal operations within the prescribed radiological guidelines. The critical-organ (worst-case) all-pathway values per acre are as follows:

All-Pathway Critical-Organ Dose Conversion Factors Durine Vermont Yankee Control of Disposal Siten Exposure isotope Individual / Organ Imrem/vr-uci/acrel Mn-54 Adult /GE-LLI 3.74E-4 Co-60 Teenager / Lung 7.14E-4 Zn-65 Child / Liver 1.64E-2 Cs-134 Child / Liver 3.18E-3 Cs-137 Child / Bone 2.66E-3 The calculational methodology and details of the radiological assessment and proposed operational controls on total activity and concentration of waste to be disposed are presented in Attachment 2.

5.0 RADIATION PROTECTIOR The disposal operation will follow the applicable Vermont Yankee procedures to maintain doses as low as reasonably achievable and within the specified dose and release concentration criteria.

1-19 6677R

REFERENCES 1.

Flood Insurance Study, Vernon, Vermont, Windham County, FEMA, Community

{

No. 500137, July 25, 1980.

2.

Flood Insurance Study, Town of Hinsdale, New Hampshire, Cheshire County, FEMA, Community No. 330022, October 15, 1980.

3.

Vermont Yankee Well Development Evaluation by Wagner, Heindel, and Noyes, Inc. July 10, 1986.

4.

NUREG/CR-3130 Influence of Leach Rate and Other Parameters on Groundwater Migration, by Dames & Moore, February 1983.

5.

Vermont Yankee Nuclear Power Corporation On-Site Septage Disposal Plan, by Wagner, Heindel, and Noyes, Incorporated, June 1989.

1-20 6677R

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i D

t ATTACHMENT 2 VERMONT YANKEE NUCLEAR POWER PIANT RADIOLOGICAL ASSESSMENT OF

[

ON-SITE DISPOSAL OF SEPTIC WASTE i

and PROPOSED PROCEDURAL CONTROLS TO D?SURE COMPLIANCE WITH RADIOLOGICAL LIMITS f

i i

1 i

i 6680R t

I i

TABLE OF CONTENTS Eage 2-

1.0 INTRODUCTION

2-1 2.0 SOURCE TERM AND OTHER BASIC DATA.................................

2-3 2.1 Septic Tank Specifics......................................

2-3 2.2-Measured and Adjusted Septic Waste Radioactivities.........

2-3 2.3 Limiting concentration Guidelines..........................

'2-4 2.4 Disposal Sites.............................................

'2-6 2.5 Radioactivity at Disposal Plot After 20 Years..............

2-6 2.6 Land-Spreading. Resuspension and Occupancy Factors.........

2-7 2.7-Site-Specific Pathway Data and Usage Factors...............

2-9 2.8 Liquid Pathways............................................

2-12 3.0 RADIOLOGICAL ASSESSMENT..........................................

2-15 3.1 Dose Reduction as a Result of Flowing the Radioactive Material into the So11.....................................

2-15 3.2 Data Manipulation for Use with AIN0 DOS.....................

2-17 3.2.1 Radioactivity Release Rate.........................

2-17 3.2.2 Atmospheric Dispersion.............................

2-18 3.2.3 Occupancy Factors..................................

2-19 3.3 Land-Spreading Exposure Pathways...........................

2-20 3.3.1 Impact During Vermont Yankee Control of the Disposal Sites.....................................

2-24 3.3.2 Radiological Impact Af ter Termination of Verinont Yankee Control of the Disposal Sites...............

2-26 3.3.3 Isotopic Dose Conversion Factors...................

2-27 4.0 REC 0tEENDED PROCEDURAL CONTROLS TO ENSURE COMPLIANCE WITH RADIOLOGICAL LIMITS..............................................

2-29 4.1 Total Radioactivity Dispersed per Disposal Plot............

2-29 4.2 Operational Limits.........................................

2-30 4.2.1 Maximum Activity Concentrations....................

2-30 4.2.2 Potential Radiation Exposures......................

2-31

5.0 REFERENCES

2-35

. 6680R r

= __ -.. -.- -

[

IABLE OF CONTENTS (Continued)

Eage APPENDIX A - LABORATORY ANALYSES OF SEPTIC WASTE.......................

A-1 i

j-APPENDIX B - COMPUTER CODE 0UTPUTS.....................................

B-1 B.1 ALLEGRA - Gamma Ray Spectra................................

B.1-1 4

i B.2 DIDOS-V - Dose Reduction as a Result of Plowing............

B.2-1

}

1 B.3 ATMODOS - Radiological Impact During Vermont Yankee Control I

of the Disposal Sites......................................

B.3-1 i

B.3.1 Impact due to Mn-54 in the Septage.................

B.3.1-1 i

B.3.2 Impact:due to Co-60 in the Septage.................

B.3.2-1 j

B.3.3 Impact due to Zn-65 in the Septage.................

B.3.3-1 1

B.3.4 Impact due to Cs-134 in the Septage................

B.3.4-1 B.3.5 Impact due to Cs-137 in the Septage................

B.3.5-1 4

l B.3.6 Impact due to All Nuclides in the Septage..........

B.3.6-1 B.4 ATMODOS - Radiological Impact After Termination of Vermont Yankee Control of the Disposal Sites t

e l

( A l l N uc l i d e s ).............................................

B.4-1 l

s B.5 ATMODOS - Unplowed-Land Dose Conversion Factors f

for Radiological Impact Assessment.........................

B.5-1 I

i B.5.1 Impact due to 1 uCi of Mn-54.......................

B.S.1-1 B.5.2 Impact due to 1 uCi of Co-60.......................

B.5.2-1 B.S.3 Impact due to 1 uCi of Zn-65.......................

B.5.3-1 j

B.5.4 Impact due to 1 uCi of Cs-134......................

B.5.4-1 1

B.5.5 Impact due to 1 uCi of Cs-137......................

B.S.5-1 l

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4 J

4 i

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AITAC11 MENT.2 VERMONT YANKEE NUCLEAR POWER PLANT Badigingical Assessment of On-Site Dispcsal of Septic Waste And Ernposed Procedural Controls to Rna.urg Compliance With Radiological flait.g 1.0 INIR0DUCHOR This calculation is in support of Vermont Yankee's application to the Nuclear Regulatory Commission for the on-site disposal of slightly radioactive septic waste in accordance with the provisions of 10CFR20.302 for very-low-level waste disposal. Specifically, the main purposes of the f-calculation were as follows:

(a) Determination of an optimal plot size for septage disposal (based l

on measured 1988 radioactivity concentrations in septic waste) which would accommodate both the radiological guidelines and the I

needed flexibilities for a smooth operation of the disposal l

program.

(b) Preparation of procedural controls to ensure compliance with the radiological guidelines.

Guidance for obtaining regulatory approval to dispose of very-low-level waste is presented in AIF/NESP-037 (Reference 6).

According to this

{

reference, the NRR staff personnel have proposed a number of draft dose f

guidelines regarding the impact of low-level waste disposal on the public 2

health and safety for use in the preparation of 10CFR20.302(a) requests. Of these, the following two are pertinent to the present calculation:

I (a) Doses to the total body and any body organ of a maximally exposed individual (a member of the general public or a worker who is not 2-1 6680R l

l

I

' classified as a radiation worker) from the probable pathways of exposure to the disposed material should be less than 1 mrem /vr.

(b) Doses to the total body and any body organ of an inadvertent intruder, from the probable pathways of exposure, should be less than 5 mremlyI.

j In either case, consideration should be given to all possible exposure pathways, while allowing for land-usage restrictions which may be in effect.

It is on these guidelines that the optimum disposal plot size was selected and the procedural controls prepared.

In addition to the dose guidelines listed above, the procedural controls recommended in this calculation also include MPC checks on the septage to be disposed. As stated in the above AIF report, the total activity concentration in the waste is expected to be below 50 pCi/ gram (Reference (6),

Page 4-1).

This guideline is approximately equivalent to the MPC limits specified in 10CFR20, Appendix B. Table II, Column 2, for the release of radioactive material to unrestricted areas, and to also be approximately 50 times higher than the activities measured in the Vermont Yankee septic waste in 1988. A lower MPC ratio appears to be more appropriate for better control. As a result, and in addition to the prescribed dose limits, a combined MPC ratio of less than or equal to 0.1 was also included in the procedures to regulate the disposal of septic waste. With respect to the measured septage radioactivity, spectroscopic analyses of samples taken in d

I 1988 from the Vermont Yankee main septic tank showed that the liquid portion of the collected samples did not contain any activation or fission products, and that the following plant-related radionuclides were found in the solids:

Activity Concentration Inoinpa 1 Siema Ipci/kg drvl Mn 54 1,126 1 74 Co-60 22,400 1 220 Zn-65 1,200 i 140 Cs-134 166 1 52 Cs-137 3,824 1 92 2-2 6680R

1 i

2.0 SDUEE_IERM AND OTHER_BASlC_ DATA 2.1 S.eptic Tank Specifica The effective capacity of the main septic tank, when filled to its maximum depth of 6 feet, is approximately 9,250 gallons. The south sewage disposal system is newly installed (January 1989) and replaces the construction office building (COB) holding tank that had previously serviced the lavatory facilities on the south end of the plant. This new system contains a 5,700 gallon septic tank. The total design capacity of both main system and new south system septic tanks is approximately 14,950 gallons.

Prior to 1988, the main tank was usually emptied every 6 months.

Due to this high pump-out frequency, the accumulation of sludge at the bottom is well below the design capacity of the tank. During the 1988 sample collections, it was estimated that the sludge thickness was less than 1 foot.

For conservatism in this radiological evaluation, it was assumed that the sludge occupies 30% of the design liquid volume of both the main septic tank and new south systems tank. Also, from laboratory analyses of the septic waste, the average density of the tank contents is approximately e7tal to that of water, and the wet to dry ratio of the sludge is 25.4 to 1.

Hence, the weight of solids (W, y) being disposed of is estimated for purposes of bounding dose analyses to be approximately:

8 I W

= 14,950 gal x 3,785.4 cc/ gal x 10~ kg/cc x 0.30 solids fraction x (1/25.4) dry / wet ratio

~ 700 kg 2.2 Measured and Adjusted Septic Waste Radioactivities j

Gamma spectroscopic analyses of septage samples from Vermont Yankee were carried out e.t the Yankee Environmental Laboratory in Westborough, Massachusetts (see Appendix A).

For the main septic tank, no activation er fission products were found in the liquid portion of the collected samples.

In the dry solids, on the other hand, the following man-made radionuclides were found to be statistically positive at the 99.9 percent confidence level:

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i Activity Concentration

'j Isotope 21 Sigma (oCi/)g Dry)

Mn-547 1126 i 74 Co-60 22400 1 220 1

In-65 1200 1 140' j

I Cs-134 166 i 52 I

Cs-137-3824 i 92 i

To account for the uncertainty associated with the counting statistics, the measured activity concentrations listed above were increased by 3 sigmas.

That is, the activity concentrations employed in this calculation. and the g

total radioactivity content per combined tankful'of both south and main septic l

tanks) (at approximately 700 kg of solids per batch, from Section 2.1 of 'this calculation) are as follows:

i l

Upper-Bound Activity Upper-Bound Activity Isotope Concentration (pCi/kg dry)

Content (01/ Batch) i Mn-54 1,348 9.436E-07 j

Co-60 23,060 1.614E-05 j

l Zn-65 1,620 1.134E-06 Cs-134 322 2.254E-07 Cs-137 4,100 2.870E-06 t

l 2.3 Limiting Concentration Guidelines t

The AIF Report (AIF/NESP-037) provided draft guidance on total activity t

i i

concentration in waste stating that it is expected to be below 50 pCi/ gram.

l As shown below, this guideline appears to be approximately equivalent to the MPC limits specified in 100FR20, Appendix B Table II, Column 2, for the

]

release of radioactive material to unrestricted areas.

I For the major radionuclides identified in the Vermont Yankee septic i

waste, the individual MPC limits are as follows:

i 1

1 l

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r 4

- _. ~ _ -.

e i

j Maximum Permissible Concerttrations in Water Soluble Insoluble Isotope (uci/ml) uC1/ml) i

~

Mn-54 1.0E-4 1.0E-4 Co-60 5.0E-5 3.0E-5 i

Zn-65 1.0E-4 2.0E-4 l

I Cs-134 9.0E-6 4.0E-5 Cs-137 2.0E-5 4.0E-5 l

i For a mix of radionuclides,10CFR20 specifies that, in addition to the l

j

'above individual limits, the following condition must also be met:

I

{

E (C /MPC ) 51.0 g

g where: O is the measured concentration for Isotope i, and the summation is f

g over all radionuclides in the mix.

i

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As indicated in Section 2.2, the 1988 spectroscopic analyses of Vermont l

Yankee septage samples showed that there was no radioactivity in the septic j

J i

water samples.

That is, the limits which are currently applicable are those l

listed above for insoluble compounds. Using the activity data from Section 2.2, along with the main septic tank volume of 9,250 gallons, the current upper-bound activities and MPC ratios are approximately:

l l

Upper-Bound Activity Upper-Bound Activity l

Isotope Content (Ci/tankfull Concentration (uC1/ml)

MPC Ratio 4

i j

Mn-54 9.44E-07 2.67E-08 2.67E-04 Co-60 1.61E-05 4.57E-07 1.52E-02 i

Zn-65 1.13E-06 3.21E-08 1.60E-04 i

Cs-134 2.25E-07 6.38E-09 1.59E-04

}

Cs-137 2.87E-Oh 8.13E-08 2.03E-03 TOTAL 2.13E-05 6.03E-07 1.78E-02 i

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-. i w

I It is seen that the overall MPC ratio is approximately 1.8 % of the regulatory limit, and that the total concentration is 1.2 % of the 50 pCi/g guideline. Thuc, the sludge activity concentration can be at least 50 times higher without exceeding either limit. Obviously, if the MPC ratio of 1 or the 50 pCi/g guideline are not revised, the on-site disposal of septic waste will be regulated solely by the prescribed radiation exposure limits. For better control, therefore, it ic hereby propored that, in addition to the prescribed dose limits, a combined MPC ratio of less than or equal to 0.1 be also included in the procedures to regulate the disposal of septage. Refer to Section 4 for more details.

2.4 Dispasal_Sl%2s There are two sites on Vermont Yankee site property which are currently designated for on-site septic waste disposal, as follows:

(a) Site A, a 8-acre site approximately 2,200 feet northwest of the Reactor Building.

(b) Site B, a 2-acre site approximately 1,700 feet south of the Reactor Building.

Both sites are within the plant's site boundary and surrounded by a chain link fence, and under direct control of Vermont Yankee for all access.

2.5 Radioactivity at Disposal Plot After 20 Ysara It is cicar that, due to the longevity of the two primary isotopes identified in the sludge (Co-60 and Cs-137), the amount of radioactivity at the disposal plot will be increasing with each disposal application. However, since the content of radioactivity in septic waste is very' low, and since it is neither practical nor necessary to carry out a new dose analysis prior to each disposal, the approach employed in this calculation was to assess the potential radiological impact at approximately the end of plant life.

That is, the radiation source was assumed to correspond to the accumulation of 2-6 6680R

radioactive material on a given plot within the proposed disposal sites over a period of 20 years (40 applications at an assumed 6-month interval).

Analytically, if-Q is the amount of radioactivity per batch for a 9

given isotope, then the total accumulated radioactivity Q, at the disposal plot after 40 applications is given by:

+ E ')

(2.1)

Q, = Q, (1 + E + E

+E

+E

+....

=Q (1 - E ')/(1 - E)

(2.2) g where: E = exp(-AAt)

(2.3)

A = is the decay constant for the selected isotope (1/ year) and At = time interval between applications = 0.5 year For the isotopes of interest, the results are as follows:

i 9

9 0

e lantngt Half Life (1/yr)

(Ci/ batch)

Q /Q 101)

Mn-54 312.2 d 0.8109 9.436E-7 3.000 2.831E-06 Co-60 5.272 y 0.1315 1.614E-5 14.58 2.353E-04 l

Zn-65 243.8 d 1.038 1.134E-6 2.470 2.801E-06 Cs-134 2.065 y 0.3357 2.254E-7 6.464 1.457E-06 l

t Cs-137 30.17 y 0.02297 2.870E-6 32.26 9.259E-05 r

2.6 Land-Spreading 4_AesusPension and Occupancy Factors As pointed out above, even though the proposed sites can accommodate more than one disposal plot, only a single disposal plot will be assumed in assessing the potential radiological impact.

If this plot has a surface area 1

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6680R 2

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of N acres, then the surface area deposition S (Ci/m ) following 40 disposal applications will be equal to:

2 S, = Q, (Ci)/(N (acres) x 4046.9 (m / acre))

(2.4)

The denominator of this equation is equivalent to the (D/Q) deposition factor normally employed in the impact assessment of deposited radionuclides.

That is:

2 (D/Q) = 1/(N (acres) x 4046.9 (m / acre))

= 2.471E-04/N (m~)

(2.5)

Following the application of septage on the disposal plot, some of the radioactivity may become airborne as a result of resuspension effects. The model used to estimate the radionuclide concentration in air above the disposal plot was taken from WASH-1400, Appendix VI (Reference 7).

According to that model, the relationship between the airborne concentration Ae (Ci/m ) and the surface deposition is:

A, = S, (Ci/m ) x K (1/m)

(2.6) where: K is the resuspension factor and is equal to 1.0E-05 (1/m) for semi-arid / grassland terrains (from Reference 1).

In actual practice, septage waste will be either surface spread at a controlled rate per acre, or directly injected into the top 6 inch surface soil layer, at a precalculated rate, in order to control the limiting factor.

The assumptions made for analytical purposes are as follows:

(a) For the analysis of the radiological impact during Vermont Yankee active control of the disposal sites, no injection will be assumed to take place; all dispersed radioactive material will be assumed to remain on the surface and to form a source of unshielded radiation.

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4 (b) For the analysis of the impact after Vermont Yankee control of the sites is assumed to be relinquished, the radionctive material will be assumed to be plowed under and to form a uniform mix with the top 6 inches of soil (to account for the shielding provided by the 1

soil), but, nonetheless, to undergo resuspension at the same rate as surface contamination.

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j Analysis of preliminary results, based on the measured radioactivity 4

concentration found in sludge during 1988, showed that a 2-acre disposal plot would meet the radiation criteria given in Section 2.3.

This is the plot size, therefore, used in the final analyses.

As for the occupancy factors for direct exposure to the ground deposition and for immersion in the resuspended radioactivity, 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> were l

used for the radiological impact analysis during active Vermont Yankee control 1

of the disposal sites, and continuous exposure was assumed thereafter. The 104-hour interval is expected to be an upper bound of a farmer's time spent on a plot of land, which is assumed to be 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week for 6 months while he plows, plants, and harvests his crop.

2.7 Site-Specific Pathway Data and Usaae Factors 1

The following exposure pathways were addressed in this calculation for both the maximally exposed individual (i.e., during Vermont Yankee control of the disposal sites) and for the inadvertent intruder (i.e., after control is assumed to be relinquished):

1 (a) Standing on contaminated ground.

(b) Inhalation of resuspended radioactivity.

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(c) Ingestion of leafy vegetables.

(d) Ingestion of stored vegetables.

(f) Ingestion of meat.

(g) Ingestion of milk.

(h) Liquid pathways, i

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l Radiation exposures were computed for all pathways, with one exception. As shown in Section 2.8 below, the radiological impact from the liquid pathway was determined to be insignificant without the need of a detailed analysis.

It should be noted that current agricultural activities permitted on the designated disposal sites are limited to the growing of feed crops (hay) for dairy animals. As such, the ingestion of leafy and stored vegetables are not existing exposure pathways, but have been included to demonstrate that these could al.

be accommodated within the proposed dose criteria for septic waste disposal.

Pathway data and usage factors as applicable to the area in the vicinity of the Vermont Yankee Nuclear Power Station are shown in the tables which follow. These are the same factors as used in the plant's ODCM assessment of the off-site radiological impact due to routine releases from the plant, with the following exceptions:

(a) The soil exposure time for spreading of the radioactivity content of the septage to cover each period of measured deposition was changed from a standard 15 years (given in Regulatory Guide 1.109) to 1 year.

(b) The fraction of stored vegetables grown on the contaminated land was conservatively increased f rom 0.76 to 1.0.

(c) The crop exposure time was changed from 2160 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.2188e-4 months <br /> to 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> to reflect the condition that no radioactive material will be dispersed directly on crops for human or animal consumption, the deposition on crops of resuspended radioactivity being insignificant 1y small; that is, crop contamination is only through root uptake.

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USAGE FACIQRS 1

Vegetables Leafy Veg.

Milk Meat Inhajation Individual (kg/vr)

(kg/vr)

(1/vr)

(kg/vr):

(m /vr)

' Adult

'520 64 310 110 8,000 Teen 630 42 400 65 8,000 Child 520 26 330 41 3,700 Infant 330 1,400' VEGETABLF E THWAY Etored Vegetables Leafv Vegetables Agricultural productivity (kg/m )

2.0 2.00 I

2 2

Soil surface density (kg/m )

240.0 240.0 Transport time to user (hours),

0.0 0.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours)

.0

.0 Holdup after harvest (hours) 1,440.0 24.0 Fraction of stored vegetables grown in garden 1.0 Fraction of leafy vegetables grown in garden 1.0 COWHMILK PATHWAY Pasture Feed Stored Feed

+

2

.7 2.0 Agriculturalproductivity{kg/m)

Soil surface density (kg/m )

240.0 240.0 Transport time to user (hours) 48.0 48.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours)

.0

.0 Holdup af ter harvest (hours)

.0 2,160.0 Animals daily feed (kg/ day) 50.0 50.0 Fraction of year on pastere

.5 Fraction pasture when on pasture 1.0 ME&T PATHWAY Pasture Feed Stored Feed 2

.7 2.0 Agriculturalproductivity{kg/m)

Soil surface density (kg/m )

240.0 240.0 Transport time to user (hours) 480.0 480.0

-Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours)

.0

.0 Holdup after harvest (hours)

.0 2,160.0 t

Animals daily feed (kg/ day) 50.0 50.0 Fraction of year on pasture

.5 Fraction pasture when on pasture 1.0 2-11 6680R

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2.8 : Liquid Pathway 1 There are three potential routes'through which septic waste radioactivity may enter into the liquid pathway, as follows:

(a) Surface water runoff.

4 (b) Ground water pathway.

(c) ' Accidental releases into the Connecticut River.

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5 Since'there are no potable water wells between the disposal site and l

~ the river, it is evident that the only way for septic waste radioactivity to enter the liquid pathway is via the Connecticut River.

4 Even though surface water runoff may be a credible pathway into the river, the fraction of disposed radioactivity which may thus be transported to i

the river is very small for the following reasons.

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(1) The selected disposal sites are set back from the river.

(2) Procedural controls will ensure that during surface spreading of all the septage and any precipitation falling onto or flowing onto the disposal plot will not overflow the perimeter of the disposal site.

(3) The disposal plots have slopes of 5% or less in order to limit surface runoff.

1 a

With respect to septage radionuclides reaching the Connecticut River 4

via the ground-water pathway, the critical parameter is the total transport t

time from the' field to the river.

Should this transport time (which is j

element dependent) be large in comparison to the half-life of the radionuclide of interest, then' decay in transit will remove the said radionuclide from the pathway. -For the case on hand, the conservative travel times to go an average

' 200 feet.to the river, and the fractions of land-spread radioactivity which are expected to reach-the river are as follows:

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Decay Travel Time Fraction of Constant to River (years)

Initial Activity i

lantDpn Half Life (1/vr)

IGround Water PatJd

_ Entering River Mn-54 312.2 d 0.8109 3.35 6.61E-02 Co-60 5.272 y 0.1315 961.

0.0 Zn-65 243.8 d 1.038 3.35 3.09E-02 Cs-134 2.065 y 0.3357 193.

0.0 Cs-137 30.17 y 0.02297 193.

1.19E-02 Thus, only small fractions of Mn-54, 2n-65, and Cs-137 may make it to the river via the ground-water pathway; and, since the initial activities of these isotopes are relatively insignificant, it is clear that the ground-water pathway is not a credible one.

We proceed, then, with the analysis of an accidental release of the entire contents of a septic waste spreading truck directly into the Connecticut River.

Following such an accident, the released radioactive material is expected to first mix with part of the water in Vernon Pond and to then gradually flow downstream of the Vernon Dam.

The storage volume in Vernon Pond, excluding the volume below the crest, is approximately 6.0E+9 gallons (2.3E+13 cc). Since no use is made of the river between the plant and the Vernon dam, the only potential exposure pathway is downstream of the dam; and from Reference (2), the river flow through the dam is typically 10,000 cfs, and no less than 1,200 cfs during the dry season.

As a conservative condition, assume that the septic waste mixes with just one thousandth of the Vernon pond storage volume, i.e., with 2.3E+10 cc.

This amount of water will pass through the dam in about 11 minutes if the river flow is 1,200 cfs, and in about 1.3 minutes if the flow is 10,000 cfs.

Using the upper-bound activities given in Section 2.3, the expected concentrations in the pond, and the corresponding MPCs are as follows:

Upper-Bound Activity Expected Concentration lan1 DER Content (Ci/ Batch) in Pond (uCi/ml)

MPC Ratio Mn-54 9.44E-07 4.10E-11 4.10E-07 Co-60 1.61E-05 7.02E-10 2.34E-05 Zn-65 1.13E-06 4.93E-11 2.47E-07 Cs-134 2.25E-07 9.80E-12 2.45E-07 Cs-137 2187E-01 1.25E-10 1.13E-Qh i

TOTAL 2.13E-05 9.27E-10 2.74E-05 2-13 6680R

1 It is seen that the concentrations are negligibly small to pose any radiological concern.

In summary, as demonstrated above, the liquid pathway is not credible.

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3.0 RAD 1010SlCAL_ASSESStiENI The radiological impact associated with the on-site disposal of radioactive septage at Vermont Yankee was carried out using the dose assessment models in Regulatory. Guide 1.109, and is consistent with the methodology employed by the Vermont Yankee ODCM. However, since the computer.

code used (ATMODOS; Reference (3)) is primarily for use with atmospheric releases, it was necessary to manipulate the input to obtain the desired results for direct deposition of radioactivity on soil due to land spreading of septic waste.

In particular, special consideration was given to the following:

(a) The computation of an effective shielding factor to account for the effect provided by the soil after the waste is plowed under, or if it is directly injected into the top 6 inch surface layer.

(b) The definition of an annual activity release rate, which following a year's time of continuous release, would yield _the ground deposition expected to prevail after 40 combined tank pump-outs, as calculated in Section 2.5.

(c) The definition of an effective atmospheric dispersion factor to represent the resuspended radioactivity.

(d) The proper representation of partial occupancy factors.

These are discussed in Sections 3.1 and 3.2 which follow.

The results of the radiological impact assessment are presented in Sections 3.3 and 3.4.

i i

3.1 Dose Reduction aa_a Result of Plowing the Radioactive Material into the j

Soil As pointed out in Section 2.6 of this calculation, the impact analysis after control of the disposal sites is relinquished, was based on the 2-15 6680R

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assumption that the radioactive material will be plowed to form a uniform mix l

with the top 6 inches of soil. To account for the gamma attenuation provided by the soil, it was necessary to carry out an appropriate shielding calculation. This was accomplished through use of the ALLEGRA and DIDOS-V computer codes (References 4 and 5). The ALLEGRA code was used to define the gamma spectrum (in MeV/sec) associated with the selected radionuclide mix.

i This spectrum was then entered into DIDOS-V to compute the radiation levels from the two following source / receptor geometries:

l (a) A circular disk source with a radius of 150 m (represented by a l

cylindrical volume with a height equal to 0.001 m), the receptor locatiot. being along the disk axis, 1 m from the disk.

(b) A cylindrical volume source with a radius of 150 m and a height of 0.15 m, with the receptor located along the axis, 1 m above the l

l source.

i 7n the latter case, the source density was set equal to 1.6 g/ce; this 2

l is equivalent to the Reg. Guide 1.109 value of 240 kg/m for the effective l

surface density of soil within a 15 cm plow layer. The source alli were assumed to be large so as to approximate semi-infinite conditions, thus, t

permitting a' direct comparison of the DIDOS-V and ATMODOS results for the i

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unplowed land. The source intensity (in MeV/sec-m, as required for input l

into DIDOS-V) was computed by distributing the radioactive material over a 2-acre surface, and within 0.001 m for the disk source and 0.15 m for the l

sec.ond case.

I l

Copies of the ALLEGRA and DIDOS-V outputs appear in Appendix B, which should be referred to for more details.

The DIDOS-V results are as follows:

i Dose to air from the disk source = 1.085E-06 rad /hr Dose to air from cylinder source = 2.629E-07 rad /hr Overall soil shielding factor

= 2.629E-07/1.085E-06 u 0.243 2-16 6680R

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At this point, it is of interest to compare the DIDOS-V and AIMODOS j

exposure results from standing on contaminated ground.

From the ATMODOS output in Appendix B (Section B.3.6), where the source term was the same as used in DIDOS-V, the skin dose due to exposure to contaminated ground for 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> is given as 6.78E-02 mrem. This is equivalent to a dose rate of 6.52E-4 mrem /hr, or (6.52E-4/1.11) = 5.87E-4 mrad /hr to air, 1.11 being the average ratio of tissue-to-air energy absorption coefficients (from Regulatory Guide 1.109).

It is seen that ATMODOS underestimates the dose by a factor of 2, approximately; the reason for this is the slightly outdated set of dose conversion factors in the guide, as can be verified by inspecting the data in WASH-1400, for instance.

i 3.2 Data Manipulation for Use with ATMODOS 3.2.1 Radioactivity Releaan._Rai.e There are two parameters in the input to ATMODOS which affect the T

buildup of radioactivity at an off-site location, namely, the activity release o

rate and the accumulation period. To simulate this process, and to also account for the effect of the 40 applications described earlier, the accumulation period was set equal to 1 year, and the release rate was selected to be such that, at the end of one year, the total accumulated radioactivity at the disposal plot would be equal to the Q, values given in Section 2.5.

That is, if we define by Q the activity release rate (Ci/yr) which is required as input to ATMODOS, then the relationship between this parameter and Qe is as follows:

1 i

Q, = Qr (1 - E)/A (3.1)

E = exp(-AAt)

(3.2)

A = is the decay constant for the selected isotope (1/ year) and t

)

1 yr.

At = time interval between applications

=

2-17 6680R

=...

-.. ~ _

. -..-~

i Using the information given'for Q, in Section 2.5, the desired values for

"' I 11"""*

j Qr "#*

Q, Q

Ratio of l

Isotope (Ci)

(Ci/vr)*

'iQ x 1 year)/0 r

e Ma 54 2.831E-06 4.132E-06 1.460 Co 60

.2.353E-04 2.511E-04 1.067 l

Zn 65 2.801E-06 4.502E-06 1.607 Cs 134 1.457E-06 1.715E-06 1.177 Cs?137-9.259E-05 9.366E-05 1.012 i

3

)

• For input.to ATMODOS only.

j 3.2.2. Atmospheric Dispersion i

What is of interest at this point is to provide a means of calculating the air immersion dose due to resuspension using the ATMODOS code (under the assumption that the resuspended material is due to an atmospheric release).

To accomplish this, we proceed as follows. By definition, in the analysis of releases of gaseous effluents to the atmosphere, the airborne concentration at a receptor of interest is given by:

i Qr (Ci/yr) x (X/Q) (sec/m )/3.1536E+7 (sec/yr)

(3.3)

A,

=

i Where:

(X/Q) is the atmospheric dispersion factor.

)

Combining Equations (2.4), (2.6) and (3.3), it is seen that, for long-lived radionuclides (where the total accumulated radioactivity at the end of one year is numerically equal to the annual release rate, i.e. Q, = Q x 1 year), the airborne concentration at the disposal plot due to resuspension effects can be accommodated by the following atmospheric dispersion factor:

1 2

(X/Q) = K (1/m) 3.1536E+7 (sec/yr)/(N (acres) x 4046.9 (m / acre))

l

= 7,792.6 (K/N) (sec/m <)

(3.4) 6680R i

1 1

J' t

With K =.1.0E-5'(1/m), and N = 2 acres, the last equation reduces to:

I (X/Q) = 3.896E-02 (sec/m ).

4 l

At this point it is important to note that this method of analysis is l

slightly conservative since the receptor is assumed to be immersed in a cloud of undecayed radioactivity. From the (Q /Q,) ratios given in the last table in Section 3.2.1, it is seen that inhalation exposures will be j

overestimated by the following factors:

i Inhalation Exposure 1sotope Overest4mation Factor 4

Mn-54 1.460 j

Co-60 1.067 r

Zn-65 1.607 i

Cs-1 14 1.177

{

Cs-1.,7 1.012 i

i 3.2.3 Draupancy Factors I

As indicated in Section 2.6, the occupancy factor for exposure to I

ground deposition and for immersion in the resuspended radiohetivity was set i

equal to 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> during control of the disposal sites, and was assumed to be l

continuous thereafter. Since occupancy factors cannot be entered directly l

into the AIN0 DOS code, the partial occupancy situation was accommodated as i

j follows:

i i

(1) The exposure to resuspended radioactivity was handled by multiplying the effective (X/Q), as given by Equation (3.4), by i

(104/8760), 8,760 being the number of hours in one year; this leads to a X/Q value of 4.626E-4 sec/m.

f (2) The exposure to radioactivity deposited on the ground was handled 4

i by setting the shielding correction factor equal to the occupancy j

factor (i.e., equal to 104/8760 = 0.012).

t f

It should be noted that the (X/Q) adjustment described above is appropriate in this case since radioactive material will not be dispersed on crops for human or animal consumption. The only pathway through which crop contamination can take place is through root uptake.

2-19 6680R i

i Land-S Ica511ng_Expnaure Pathways 3.3 P

1 Three sets of ATMODOS computer runs were carried out, for the following:

(a) Assessment of the radiological impact during Vermont Yankee control of the disposal sites.

(b) Assessment of the radiological impact af ter control of the sites is assumed to be re).inquished.

(c) Development of dose conversion factors providing a correlation between pathway exposures per soil activity for each isotope of interest.

The results for each case are presented in the subsections which follow.

Briefly, note that they correspond to a disposal plot size of 2 acres, which was detennined to be the appropriate size to meet both the radiation exposure criteria listed in Section 2.3, and the desired flexibilities listed in Section 2.4.

The whole body and critical-organ radiation exposures (after 40 pump-outs on the same plot at a concentration level equivalent to the measured 1988 concentrations in septic waste) are as follows:

CRnirQ1 of Dispnaal Sites Radiation Exposure Individual / Organ Controlled by VYNPS 0.1 mrem /yr Child /Whole Body (Maximum Exposed Individual) 0.2 mrem /yr Maximum Child / Liver Uncontrolled 1.3 mrem /yr Adult /Whole Body (Inadvertent Intruder) 3.9 mrem /yr Maximum Teenager / Lung The individual pathway contributions to the total dose are as follows:

2-20 6680R

fallway-Diptadent CriticaLDIgan Doses Maximally Exposed Inadvertent Intruder Individual / Organ Critical Individual / Organ (Child / Liver)

(Teenager / Lung)

Eathway (mrem / year)

(mrem /vear)

Ground Irradiation 0.0576 1.16 Inhalation 0.00122 2.74 Stored Vegetables 0.0913 0.00601 Leafy Vegetable 0.00467 0.00040 Milk Ingestion 0.0421 0.00229 Meat Ingestion 0.00249 0.00012 TOTAL 0.1994 3.909 In addition, an isotopic breakdown of the critical organ dose results listed above is shown in the following table:

Iantopic Breakdown of Maximum Radiation Exposures Radioactivity Description Isotope (uC1/2 Acreal (mrem /yr)

During Vermont Yankee Mn-54 2.831 0.000436 control of the Co-60 235.3 0.0559 disposal sites.

Zn-65 2.801 0.0230 Maximally Exposed Cs-134 1.457 0.00231 Individual / Organ:

Cs-137 92.59 0.118 Child / Liver TOTAL 0.199 After Vermont Yankee Mn-54 2.831 0.0144 control of sites is Co-60 235.3 3.76 relinquished.

2n-65 2.801 0.00983 Inadvertent Intruder Cs-134 1.457 0.000505 Critical Individual /

Cs-137 92.59 0.1247 Organ: Teenager / Lung TOTAL 3.91 As for the dose conversion factors during active plant control of the disposal sites, the critical-organ all-pathway values for a 2-acre disposal plot are:

2-21 6680R

I

)

All-Pathway Worst-Case Dose Conversion Factnra Duringl Vermont Yankee Control of Disposal Sites 4

1 i

Exposure lanippe Individual / Organ (mrem /yr-uci)

Mn-54 Adult /GE-LLI' 1.87E-4 Co-60 Teenager / Lung 3.57E-4 Zn-65 Child / Liver 8.21E-3 Cs-134 Child / Liver 1.59E-3 Cs-137 Child / Bone 1.33E-3 4

In all cases, the exposure pathways are direct shine from shielded / unshielded ground deposition, inhalation of resuspended radioactivity, and ingestion of contaminated food (stored vegetables, leafy vegetables, milk and meat); exposure to the ground deposition and to resuspended radioactivity is for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> during control of the disposal sites, and continuous thereafter. Refer to Appendix B for copies of the ATM0 DOS outputs, and to the following list of assumptions employed in the calculations.

Briefly, the following basic assumptions were used in the calculational analyses:

(a) The septic tanks are emptied every 6 months (expected future practice is to pump tanks once per year).

(b) The tank radioactivity remains constant (at the main septic tank 1988 determined level plus 3 sigma).

(c) The radiation source corresponds to the accumulation of radioactive material on a single plot within the proposed disposal sites over a period of 20 years (40 applications at 6 month intervals). (In actuality, the proposed sites will accommodate more than one disposal plot, and, in practice, more than one plot will most probably be used.)

2-22 6680R t

_~-

. - ~ -.

i (d) For the analysis'of the radiological impact during Vermont Yankee control of the disposal sites, no plowing or direct injection of j

septage takes place.and all dispersed radioactive material remains on the surface and forms a~ source of unshielded radiation. (In practice, the waste will be either surface spread or directly injected into the top 6 inch layer of the disposed plot, in which case the radioactive material will be mixed with the soil. This in effect would reduce the ground plane source of exposure by a factor of about four due to self-shielding.)

(e) No radioactive material is dispersed directly on crops for human l

or animal consumption, crop contamination being only through root 4

uptake.

l I

l (f) The deposition on crops of resuspended radioactivity is insignificant 1y small.

r s

(g)' Pathway data and usage factors used in the analysis are the same as those used in the plant's ODCM assessment of the off-site i

i radiological impact from routine releases, with the exception that the fraction of stored vegetables grown on the disposal plots was l

conservatively increased from 0.76 to 1.0.

(At present, no f

vegetable crops for direct human consumption are grown on any of the disposal sites.)

4 (h)

It is assumed that Vermont Yankee relinquishes control of the i

disposal sites after the fortieth pump-out (i.e., the above source term applies also for the inadvertent intruder).

i (1) For the analysis of the impact after Vermont Yankee control of the j

sites is relinquished, the radioactive material is plowed under and forms a uniform mix with the top 6 inches of soil, but, i

nonetheless, undergoes resuspension at the same rate as surface contamination.

i a

2-23 4

6680R

(k) Exposure to the ground deposition and to resuspended radioactivity is for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> during Vermont Yankee control of the disponal sites, and continuous thereaf ter, Se 104-hour interval being representative of a farmer's time on a plot of land (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week for 6 months).

3.3.1 JapacLDuring Vermont _ Yankee Control of the Discosal Sites The tables which follow present summaries of the ATMODOS results for the radiological impact during Vermont Yankee control of the disposal sites.

The first table presents the results for the entire mix of radionuclides, and the second table shows the contributions by each isotope.

Iotal Acc.umulated Radioactivity on 2-Acre Plot 6fler__4D_Diapnaal ApplicatiDna Isolope Curies Mn 54 2.831E-06 Co 60 2.353E-04 Zn 65 2.801E-06 Cs 134 1.457E-06 Cs 137 9.259E-05 Daar Delivercd to Each_Drgan_Erom all Radicauclides in the Mix e

and_Erom All Pathways Comhined*

(Adult. Tecnager_,J hild. and Infant)

(mrem /yr)

Hone Liler Ki_dney Lung GI-Lil Thyroid Whole Body Skin A 9.20E-02 1.13E-01 7.92E-02 8.46E-02 9.66E-02 5.76E-02 9.42E-02 6.78E-02 T 1.13E-01 1.44E-01 9.08E-02 9.90E-02 9.65E-02 5.76E-02 9.41E-02 6.78E-02 C 1.86E-01 1.99E-01 1.10E-01 9.73E-02 8.22E-02 5.76E-02 9.94E-02 6.78E-02 1 1.14E-01 1.38E-01 8.36E-02 8.08E-02 7.59E-02 5.76E-02 7.19E-02 6.78E-02

• Each pathway includes unshielded exposure to ground contamination for 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, with all radioactivity assumed to be on the surf ace of the ground; exposure to resuspended radioactivity is also for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />.

2-24 6680R

I l

Isnings-Spes111c_ContIlhutions to the Dose Delivered to Each Organ Eram__all_falhways Combingd*

(Adult. Ter r.or. Child. and Infant)

(mrem /yr) 1 Hone LiYer KidDcI Lung GI-LLI Thyroid Whale Body Skin Source:

Mn-54, 2.831E-06 Ci (2-acre plot)

A 2.13E-04 3.18E-04 2.44E-04 2.98E-04 5.30E-04 2.13E-04 2.33E-04 2.50E-04 1

T 2.13E-04 3.66E-04 2.59E-04 3.34E-04 5.25E-04 2.13E-04 2.44E-04 2.50E-04 C 2.13E-04 4.36E-04 2.76E-04 3.09E-04 4.00E-04 2.13E-04 2.73E-04 2.50E-04 I 2.13E-04 2.18E-04 2.14E-04 2.74E-04 2.15E-04 2.13E-04 2.14E-04 2.50E-04 Source:

Co-60, 2.353E-04 Ci (2-acre plot)

A 5.20E-02 5.37E-02 5.20E-02 7.40E-02 8.32E-02 5.20E-02 5.56E-02 6.12E-02 T 5.20E-02 5.44E-02 5.20E-02 8.41E-02 8.30E-02 5.20E-02 5.73E-02 6.12E-02 C 5.20E-02 5.55E-02 5.20E-02 7.80E-02 7.16E-02 5.20E-02 6.24E-02 6.12E-02 I

I 5.20E-02 5.22E-02 5.20E-02 6.86E-02 5.26E-02 5.20E-02 5.25E-02 6.12E-02 i

l i

4 Source:

Zn-65, 2.801E-06 Ci (2-acre plot) l l

A 3.43E-03' 1.06E-02 7.13E-03 2.03E-04 6.72E-03 1.46E-04 4.87E-03 1.68E-04 T 4.61E-03 1.57E-02 1.01E-02 2.28E-04 6.72E-03 1.46E-04 7.38E-03 1.68E-04 j

C 8.72E-03 2.30E-02 1.45E-02 2.11E-04 4.16E-03 1.46E-04 1.44E-02 1.68E-04 j

I 6.18E-03 2.08E-02 1.02E-02 1.88E-04 1.76E-02 1.46E-04 9.69E-03 1.68E-04 1

Source: Cs-134, 1.457E-06 C1 (2-acre plot)

A 5.89E-04 1.09E-03 5.06E-04 3.20E-04 2.42E-04 2.27E-04 9.31E-04 2.65E-04 T 7.92E-04 1.56E-03 6.50E-04 3.89E-04 2.44E-04 2.27E-04 8.44E-04 2.65E-04 C 1.50E-03 2.31E-03 8.74E-04 4.59E-04 2.38E-04 2.27E-04 6.67E-04 2.65E-04 l

I 7.74E-04 1.25E-03 4.89E-04 3.35E-04 2.30E-04 2.27E-04 3.30E-04 2.65E-04 Source: Cs-137, 9.259E-05 Ci (2-acre plot)

A 3.57E-02

4. 70E-02 1.93E-02 9.79E-03 5.86E-03 5.06E-03 3.25E-02 5.90E-03 T 5.52E-02 7.18E-02 2.78E-02 1.39E-02 6.00E-03 5.06E-03 2.83E-02 5.90E-03 C 1.23E-01 1.18E-01 4.19E-02 1.83E-02 5.76E-03 5.06E-03 2.18E-02 5.90E-03 I 5.50E-02 6.35E-02 2.07E-02 1.14E-02 5.24E-03 5.06E-03 9.20E-03 5.90E-03 i

• Each pathway includes unshielded exposure to ground contamination for 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, with all radioactivity assumed to be on the surface of the ground; exposure to resuspended radioactivity is also for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />.

1 2-25 6680R l

i

i i

3.3.2 Radiological Impact Af ter Termination of Active Control of the i

Disposal Sites l

l The table which follows presents a summary of the ATMODOS results for f

i the radiological impact af ter control of the disposal sites is assumed to be

[

relinquished'after 20 years of septic waste disposal. Tables showing the j

contributions by the variour isotopes were not prepared as they were j

' determined to be of little significance.

l IQial_ Accumulated Radioactivity on 2-Acre Pig 1 ~

f 1

j After 40 Disposal Applicationa Inniope Curies i

i j

25 Mn-54 2.831E-06 27 Co-60 2.353E-04 30 Zn-65 2.801E-06 55 Cs-134 1.457E-06 t

i 55 Cs-137 9.259E-05 l

t 1

Dose Delivered to Each Organ From all Radionuclides in the Mix gnd From all Pathways Combined *.

1 (Adult. Teenager. Child. and Infantl l

l (mrem /yr) j e

l Bont LiYRI Eidney Lung GI-LLI Thyroid Whole Body Skin 4

I A 1.25E+00 1.29E+00 1.21E+00 3.04E+00 1.29E+00 1.16E+00 1.25E+00 1.37E+00 T 1.30E+00 1.35E+00 1.23E+00 3.91E+00 1.28E+00 1.16E+00 1.24E+00 1.37E+00 i

C 1.40E+00 1.41E+00 1.25E+00 3.39E+00 1.22E+00 1.16E+00 1.23E+00 1.37E+00 l

3 I 1.28E+00 1.32E+00 1.21E+00 2.58E+00 1.19E+00.1.16E+00 1.19E+00 1.37E+00

}

l i

I i-j

• Each pathway includes continuous exposure to ground contamination (uniformly l

l distributed within a 6-inch layer of soil)

{

i i

I e

l I

i i

k I

2-26 6680R t

i I

3.3.3 luatopic Dose Conversion _fac_tnIn s

The table which follows presents isotope-dependent dose conversion factors for the various age groups.and organs.

They were computed using the ATMODOS computer code along with all the assumptions employed in the assessment of the radiological impact during Vermont Yankee control of the disposal sites. The source terms were defined using the adjustment ratio (Q

• 1 I#)/9 given in Section 3.2.1 to obtain an accumulated r

e radioactivity of 1 uCi for each isotope of interest at the end of one year.

These conversion factors form part of one of the procedural controls described in Section 4 for ensuring that the disposed contaminated septage does not lead to radiation exposures in excess of the specified limits.

2-27 6680R

~

l i

1 Dose Conversion Factors for Radioactive Material Spread over Two Acres For all Pathways Combined

• IAdult. Teenager. Child. and Infan11 (mrem /yr-uCi) l Hone Liyar Kidney Lung GI-LLI Ihyrnid Whole Body Skin l

Source: Mn-54 A 7.54E-05 1.12E-04 8.63E-05 1.05E-04 1.87E-04 7.54E-05 8.24E-05 8.84E-05 T 7.54E-05 1.29E-04 9.15E-05 1.18E-04 1.85E-04 7.54E-05 8.61E-05 8.84E-05 C 7.54E-05 1.54E-04 9.74E-05 1.09E-04 1.41E-04 7.54E-05 9.63E-05 8.84E-05 I 7.54E-05 7.71E-05 7.58E-05 9.68E-05 7.60E-05 7.54E-05 7.58E-05 8.84E-05 I

Source: Co-60 i

A 2.21E-04 2.28E-04 2.21E-04 3.14E-04 3.54E-04 2.21E-04 2.36E-04 2.60E-04 T 2.21E-04 2.31E-04 2.21E-04 3.57E-04 3.53E-04 2.21E-04 2.43E-04 2.60E-04 C 2.21E-04 2.36E-04 2.21E-04 3.32E-04 3.04E-04 2.21E-04 2.65E-04 2.60E-04 I 2.21E-04 2.22E-04 2.21E-04 2.92E-04 2.24E-04 2.21E-04 2.23E-04 2.60E-04 Source:

Zn-65 A 1.22E-03 3.78E-03 2.55E-03 7.24E-05 2.40E-03 5.20E-05 1.74E-03 5.98E-05 i

T 1.65E-03 5.59E-03 3.60E-03 8.12E-05 2.40E-03 5.20E-05 2.64E-03 5.98E-05 C 3.11E-03 8.21E-03 5.19E-03 7.55E-05 1.48E-03 5.20E-05 5.12E-03 5.98E-05 I 2.21E-03 7.44E-03 3.63E-03 6.72E-05 6.29E-03 5.20E-05 3.46E-03 5.98E-05 Source: Cs-134 i

A 4.04E-04 7.46E-04 3.47E-04 2.19E-04 1.66E-04 1.56E-04 6.39E-04 1.82E-04 T 5.44E-04 1.07E-03 4.46E-04 2.67E-04 1.67E-04 1.56E-04 5.79E-04 1.82E-04 C 1.03E-03 1.59E-03 6.00E-04 3.15E-04 1.64E-04 1.56E-04 4.58E-04 1.82E-04 I 5.31E-04 8.55E-04 3.36E-04 2.30E-04 1.58E-04 1.56E-04 2.26E-04 1.82E-04 Source: Cs-137 A 3.86E-04 5.07E-04 2.09E-04 1.06E-04 6.33E-05 5.46E-05 3.52E-04 6.37E-05 T 5.97E-04 7.75E-04 3.00E-04 1.50E-04 6.48E-05 5.46E-05 3.06E-04 6.37E-05 C 1.33E-03 1.28E-03 4.53E-04 1.98E-04 6.23E-05 5.46E-05 2.35E-04 6.37E-05 I 5.94E-04 6.86E-04 2.24E-04 1.23E-04 5.66E-05 5.46E-05 9.94E-05 6.37E-05

• Each pathway includes unshielded exposure to ground contamination for 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, with all radioactivity. assumed to be on the surface of the ground; exposure to resuspended radioactivity is also for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />.

2-28 6680R

4.0 RECOMMENDEILfEDCEQURAL CONTROLS TO ENSURE COMPLIANCE WITH RADIOLOGICAL LIMIIS Once an on-site septage disposal permit has been secured, implementation of the disposal program must be accompanied with procedural controls to ensure that the applicable radiological limits are not violated.

This section presents a list of proposed controls to this effect.

4.1 IQ1alladioactivity Dispersed pSr_DispaEal Plot As pointed out in Section 2.5, since the content of radioactivity in septic waste is very low, and since it is neither practical nor necessary to carry out a new analysis prior to each disposal, assessment of the radiological impact was based on an assumed source corresponding to the expected accumulation of radioactive material on a given 2-acre dispos' plot over a period of 20 years (40 applications at 6-month intervals). As auch, it will be necessary to keep accurate records of the time and location of septage disposal and of the ensuing buildup and decay of radioactivity on each disposal plot. The basic equation to be employed is as follows:

id Q

= Q"*" + Q exp (-A At)

(4.1)

Qf

=

total accumulated radioactivity at the selected 2-acre Where:

disposal plot after the current disposal (uCi).

Q'g'** =

radioactivity added to the plot as a result of the current disposal (uCi).

Qfd radioactivity accumulated at the selected disposal plot

=

prior to the current disposal (uC1), as determined at the time of the previous disposal.

g=

radioactive decay constant (1/ year).

A At =

time lapse since the previous disposal on the same disposal plot (years).

2-29 6680R

'I Q'g** can be calculated using the following equation:

Q"*" = 14,950 gallons x 3,785.4 cc/ gallon x 1.0E-3 kg/cc x Fs (solids fraction) x C"*

(pCi/kg wet) x 1.0E-6 (uCi/pCi) 4

= 0.0566 Fs C""

(4.2)

Where:

C""

is the measured or estimated radionuclide concentration in the septic waste on a wet basis, and Fs is the fraction of solids in i

the septage per tankful.

Fs was conservatively set equal to 0.3 in this calculation.

14,950 gallons equals the volume of both the main septic tank and the south disposal system collection tank.

4 4.2 Operational _Limila The disposal operating procedures to be established should address both the activity concentration and the potential radiation exposure. Should the activity concentration be in excess of the specified limit, then the sewage i

mix would not be suitable for on-site disposal and would have to be processed accordingly; this situation, however, is not likely to occur. On the other hand, approaching the exposure guideline is a possibility; but this can be 4

easily accommodated by switching to a different plot within the disposal sites. The subsections which follow present pertinent information recommended for inclusion in the operating procedures.

1 4.2.1 tiaximum Activity Concentrations In line with the discussion presented in Section 2.3 of this calculation, the radionuclide concentrations in the septic waste must not 1

exceed the following limits:

1 (a) One tenth of the MPC values listed in 10 CFR 20 Appendix B.

Table II, Column 2.

1 2-30 6680R l

~ _.

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

(b) An overall MPC ratio of less than or equal to 0.1.

4 For the major radionuclides identified in the Vermont Yankee septic waste, the individual MPC limits are as follows:

i Maximum Permissible Cor:gntrations in Water (10CFR20, Appendix B, Table II) f Soluble Insoluble laningn (pci/ml)

(pci/ml)

Mn 54 1.0E-4 1.0E-4 Co 60 5.0E-5 3.0E-5 Zn 65 1.0E-4 2.0E-4 Cs 134 9.0E-6 4.0E-5 Cs 137 2.0E-5 4.0E-5 For a mix of radionuclides in the sewage mix, the condition to be met is:

u I (C /MPC ) 10.1 g

g i

l Where: C is the measured concentration for Isotope 1, and the summation is g

i over all radionuclides in the mix.

From the 1988 spectroscopic analysis of septic waste samples, all radioactivity is expected to be in insoluble form, and no radioactivity is i

4 expected in the liquid above the sludge. Should the situation change, use should be made of both the soluble and insoluble MPCs listed above, as i

)

appropriate.

i 4.2.2 Entential RadiaticalEPRauIta As described in Section 2.3 of this calculation, the NRR draft guidelines for radiation exposure from all probable pathways due to the disposal of low-level waste are 1 mrem /yr to the total body and any body organ J

of a maximally exposed individual, and 5 mrem /yr to an inadvertent intruder.

The maximally exposed individual is identified as a ~ member of the general 4

public or a worker who is not classified as a radiation worker.

2-31 6680R

Since the proposed septage disposal sites are within VYNPS property and under VYNPS control, occupancy of the disposal sites by an inadvertent intruder is only possible after plant decommissioning. That is, during the on-site septic waste disposal program, only the specified exposure guideline for the maximally exposed individual would be in effect.

To ensure proper operation of the on-site disposal program, a set of checkpoints was prepared as guidance. The action levels were based on the following results from Section 3:

laotoolc Breakdown of Maximum Radiation Exposures i

Radioactivity Exposure Description lag _ tope IpCi/2 Acres) fmrem/vr)

During Vermont Yankee Mn-54 2.831 0.000436 control of the Co-60 235.3 0.0559 disposal sites.

2n-65 2.801 0.0230 i

Maximally Exposed Cs-134 1.457 0.00231 Individual / Organ:

Cs-137 92.59 0.118 Child / Liver TOTAL 0.199 After Vermont Yankee Mn-54 2.831 0.0144 control of sites is Co-60 235.3 3.76 relinquished.

Zn-65 2.801 0.00983 l

Inadvertent Intruder Cs-134 1.457 0.000505 f

Critical Individual /

Cs-137 92.59 0.1247 Organ: Teenager / Lung

}

TOTAL 3.91 It is seen that, whereas the exposure to the maximally exposed i

individual is approximately 20% of the 1 mrem / year guideline, the inadvertent i

intruder exposure is almost 80% of the 5 mrem / year limit. Thus, to ensure that both guidelines are met at all times, it is intended that the operational

]

I guideline for the maximally-exposed individual be set at 0.2 mrem / year. This

]

is a conservative approach since the likelihood of intruder occupancy of the sites coinciding with the end of the on-site disposal program is nil; substantial decay of the radioactive material is expected by the time the i

sites are released to the general public. Of course, future reassessment of this operational guideline is not precluded. However, an operational limit close to the guideline is not recommended since it eliminates all flexibilities.

f i

2-32 6680R A

- ~

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

i 4

l l

Based on the operational guideline of.0.2 mrem /yr to the maximally exposed individual, two' checkpoints were prepared which would ensure that the-l radiation exposure limit will not be exceeded.. They are as follows:

(a) Action Level 1 - Cross Radioactivity Limit i

The up-to-date total radioactivity dispersed per disposal plot (Qf)iscalculatedforeachisotopeusingEquation(4.1).

If the condition:

3 Q

<Q i

1 lim is wet for each isotope, where Qg represents the limiting

- values listed in the following table (from Section 3, rounded off to 2 significant figures), then disposal of the septic waste will' not violate the exposure limit; otherwise, proceed to Action Level 2.

Maximum Accumulated Radioactivity A: lowed i

Pyy" Acre isnt.oge Q

iuW I

g Mn-54 1.4 Co-60 120.0 Zn-65 1.4 Cs-134 0.7 i

Cs-137 46.5 (b) ~ Action Level 2 - Radiation Exposure If Action Level 1 fails, determine the potential radiation exposure using the equation:

i l

Dose (mrem /yr) = I Q DCF g

1 i

Where:. Qg is the up-to-date total radioactivity dispersed I

per disposal plot calculated for each isotope using Equation (4.1), DCFg is the dose conversion factor for isotope i, and the summation is over all the radionuclides I

in the mix. The doce conversion factors are as follows:

2-33 l

i DCF$

ImatsPS Individual / Organ (mrem / year-uci/ac t,_e.1 Mn-54 Adult /GI-LLI 3.74E-04 Co-60 Teenager / Lung 7.14E-04 Zn-65 Child / Liver 1.64E-02 Cs-134 Child / Liver 3.18E-03 Cs-137 Child / Bone 2.66E-03 The model overestimates the exposure by approximately 20% because the above DCF's correspond-to the most restrictive exposure to any individual and any organ from all pathways, independently selected for each radionuclide.

I The exposure pathways are direct shine from unshielded ground deposition, inhalation of resuspended radioactivity, and ingestion of contaminated food (stored vegetables, leafy vegetables, milk and meat); exposure to the ground l~

deposition and to resuspended radioactivity is for a period of 104 (hours / year).

1 If the calculated dose is in excess of 0.2 (mrem /yr), a different disposal plot would have to be selected.

I i

i i

l 4

i

)

2-34 6680R r

5.0 REEEEENCES 1.

U.S. Nuclear Regulatory Commission, Reactor Safety Study, Appendix VI, Calculat. inn of Reactor Accident Consequences, WASH-1400 (NUREG 75/014),

October 1975.

2.

Vermont Yankee Nuclear Power Station, FSAR, Section 2.4.4 Uses of River.

4 3.

ATMODOS, A YAEC Computer Code for the Calculation of Off-Site Doses from Iodines and Particulates Discharged to the Atmosphere in line with the Models In Regulatory Guide 1.109 4.

J. N. Hamawi, ALLEGRA - A Computer Code Making Use of the ORIGEN-2 Data llangs for the Analysia_of Radioactive Decay Chains and the Computation _of Gama_Spactra, ENTECH Engineering, Inc., Marlboro, MA, Technical Report P100-R15 (technical report in preparation).

5.

J. N. Hamawi, / DIDOS-III - A Three-Dimensional Point-Kernel Shielding Code for cylindr.iral Sources, ENTECH Engineering, Inc. Technical Report P100-R2, December 1982 (an upgraded version of the code, DIDOS-V,

^

suitable for the analysis of infinitely large cylindrical sources, is currently in preparation).

6.

Atomic Industrial Forum, National Environmental Studies Program, A Guide for Obtaining Regulatory Approval to Dispose of Very Low Level Wastes by Alternative Means, prepared by D. W. Chan, J. P. Davis & R. W. Wofford, General Physics Corporation, Columbia, Maryland. Technical Report No. AIF/NESP-037, August 1986.

2-35 6680R J

u a

wA u

eu.

,s APPENDIX A LABORATORY ANALYSES OF SEPTIC WASTE 1

l 1

h i

P 1

9 A-I t

YANKEE ATOPIC' ELECTRIC COMPANY MAILEU.

ENv1Ra nENraL u n = r ar Initial AnalYCi8 R* Port rJ Wl O n n....

Cue ont Yankee Nosionic Power Corp.

Report'Date: 06/09/88 Atte

k. N AdMNE KEECJ4 Analysis Dato 6 /8 /88 Date Received: 6 /0 /88 MR. -- "" ~~~.. DING Reference Date: 6 /8 /88 HR. STEPHEtt SKIBN10WSKY Sludge Sample Amounts 1.01 Kg.

Lab Sample No. :

c72970 Sanple submission Code: VSL 02 2388 Elapsed Time : 0.65 days other Analysis Requested:

None Comments COB TANK BOTTOM DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC a

CORRECTION

(

Pico Curie / Eilogram - WET )

35 E O Np-239 8.24E-01

(-15 +- 11 ) E o Co-57 9.98E-01

( 5 +- 9 4 ) E-2 310 E-2 Ce-144 9.98E-01

(~9 +- 73 ) E-1 240 E-1 Ce-141 9.06E-01

"( 26 +- 17 ) E-1 55 E-1 Mo-99 8.49E-01

( 11 +- 20 )Eo 65 E o Se-75 9.96E-01

(-6 +- 15 ) E-1 49 E-1 Cr-51 9.84E-01

( 41 +- 93 ) E-1 310 E-1 37 E-1 I -131 9.45E-01

-(-15 +- 11 ) E-1 De-7 9.92E-01

( 102 4-94 ) E-1 310 E-1 Ru-103 9.89E-01

(-11 +- 12 ) E-1 38 E-1 I -133 5.95E-01

( 22 += 17 ) E-1 58 E-1 Ba-140 9.65E-01

(-175 +- 68 ) E-1 230 E-1 4

CG-134 9.99E-01

( 16 +- 16 ) E-1 53 E-1 Ru-106 9.99E-01

( 4 +- 13 )EO 43 E O

• + Cs-137 1.00E 00

( 103 +- 18 ) E-1 54 E-1 Ag-110M 9.98E-01

(-2 4-19 ) E-1 64 E-1 Zr-95 9.93E-01

(-19 +- 24 ) E-1 79 E-1 Co-58 9.94E-01

( 7 +- 13 ) E-1 42 E-1 50 E-1 Mn-54 9.99E-01

(-7 +- 14 ) E-1 230 E-1

• + AcTh228 1.00E 00

( 287 +- 68 ) E-1 ToI-132 8.70E-01

( 117 +- 99 ) E-1 330 E-1 91 E-l' Fe'-5 9 9.90E-01

(-33 +- 27 ) E-1 En-65 9.98E-01

( 89 +- 36 ) E-1 120 E-1 82 E-1

• + Co-60 1.00E 00

( 4 5 4 +- 31 ) E-1 75 E 0

• + K -40 1.00E 00

( 87 +- 23 ) E O 100 E-1 Sb-124 9.92E-01

(-31 +- 31 ) E-1 Notes:Activity greater than 3* standard deviation Approved by

+

Peak is found 3.3._b_%_h _

D.E.McCurdy.

E....l.00'.iTC. 0*.U.UUU..*.*'.uio.

,,. 0C'.U,w.',*,.C. U'Ul*:.*!.

eU'%.'*.Z.

......u..

o

.o.

uu.i g.

.$p

.i........

i

{

I

)

i M NIL YANKEE ATOMIC ELECTRIC COMPANY 3V C ENVIRONMENTAL IABORATORY

.t0H 00 Ut' Initial Analysis Report YAEC Custgggg4(MrMetWannBYankee Nuclear Power Corp.

Report Date: 06/09/88 Attention:-MS. ELAINE KEEGAN Analysis Date 6 /8 /88 MR. EDWARD CUMMING-Date Received: 6 /8 /88 HR. STEPHEN SKI 8H10WSKY Reference Date 6 /8 /88 Sludge sample Amount 1.02 Kg.

Lab Sample No.:

G72971 sample Submission Code: vsL 03 2388 Elapsed Time : 0.63 days other Analysis Requested:

None Comment:

COB TANK-LIQUID i

DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC CORRECTION

(

Pico Curie / Kilogram-wg7

)

.........-7....

.......................... =

Np-239 8.29E-01

( 6 +- 10 ) EO 34 E 0 Co-57 9.98E-01

( 6 5 +- 9 3 ) E-2 310 E-2 Ce-144 9.98E-01

( 20 +- 67 ) E-1 220 E-1 r

co-141 9.87E-01

( 0 +- 16 ) E-1 52 E-1 1

Mo-99 8.54E-01

(-25 +- 19 )* E O 63 E O Se-75 9.96E-01

( 4 +- 14 ) E-1 48 E-1 290 E-1 Cr-51 9.84E-01

(.81 +- 8C ) E-1 I -131 9.47E-01

( 8 +- 11 ) E-1 38 E-1 Bd-7 9.92E-01

( 1 +- 10 ) EO 35 E O Ru-103 9.89E-01

( 17 +- 12 ) E-1 41 E-1 I -133 6.05E-01

(-1 +- 19 ) E-1 65 E-1 Ba-140 9.66E-01

( 33 +- 72 ) E-1 240 2-1 Cs-134 9.99E-01

(-17 +- 14 ) E-1 48 E-1 i

Ru-106 9.99E-01

(-1 +- 12 )EO 40 E O Cs-137 1.00E 00

(-5 +- 13 ) E-1 44 E-1 Ag-110H 9.98E-01

(-6 +- 16 ) E-1 54 E-1 Er-95 9.93E-01

( 20 +~ 22 ) E-1 75 E-1 l

Co-58 9.94E-01

( 13 +- 12 ) E-1 39 E-1 Hn-54 9.99E-01

( 11 +- 12 ) E-1 39 E-1 Aoth 228 1.00E 00

(-21 +- 66 ) E-1 260 E-1 TeI-132 8.73E-01

( 16 +- 91 ) E-1 300 E Fe-59 9.90E-01

( 8 +- 28 ) E.1 93 E-1 Zn-65 9.98E-01

( 72 +- 34 ) E-1 110 E-1 Co-60 1.00E 00

(-6 +- 18 ) E-1 76 E-1

+ K ~40 1.00E 00

( 55 += 21 ) E O 76 E O Sb-124 9.93E-01

( 6 +- 3 4 ) E-1 110 E-1 Notes

+- Peak is found Approved by

........i-.. u i.., u 4.

.....us u e

.a

{ p {*.

^

!!J:: int *:::tJ::O*::::!OJ:* i* P:0l::.'n ',:::"" l ::1%f D.E.McCurd.

'; g;,a;p*;;g;; a;;ag,l e;;a+g;j;t;;a8*jt4 jag;;*jajay;*,;~ b g....

_.. _. ~.

i a

6 YANKEE ATOMIC ELECTRIC COMPANY r

h ENVIRONMENTAL LABORATORY Initial Analysis Report

. UU 0 n..,,

CustomeY!:'dkernogt Yankee Nuclear Powcr Corp.

Report Date: 06/09/88 Attentebnd.ND\\'-}-ELAINE KEEGAN Analysis Date: 6 /8 /88 MR. EDWARD CUMMING Date Received: 6 /8 /88 n

ae

/8 /88 MR. STEPHEN SKIBNIOWSKY Sludge Sample Amounts 0.99 Kg.

Lab Sampic No.:

G72972 Sample Submission Code: VSL 04 2388 Elapsed Time : 0.59 days 0".her Analysis Requested:

None Comment:

MAIN TANK BOTTOM DECAY ACTIVITY CONC. +- 1 SIGMA HDC NUCLIDE CORRECTION

[

Pico Curie / Kilogram. WET

)

Np-239 0.40E-01

( 2 +- 21 ) E O 70 E O Co-57 F.98E-01

(-10 +- 19 ) E-1 62 E-1 g

Co-144 9.99E-01

( 11 += 14 ) E O 45 E O Ce-141 9.87E-01

(-12 += 32 ) E-1 110 E-1 Ho-99 8.63E-01

( 20 +- 38 ) EO 120 E O So-75 9.97E-01

( 34 t-29 ) E-1 97 E-1 Cr-51 9.85E-01

(-25 +- 18 )EO 61 E O I -131 9.50E-01

( 3 +- 23 ) E-1 78 E-1 Be=7 9.92E-01

(-20 +- 19 ) E O 65 E o Ru-101 9.90E-01

(-10 +- 24 ) E-1 81 E-1 I -133 6.26E-01

(-25 +- 37 ) E-1 120 E-1 Ba-140 9.68E-01

(-23 +- 11 ) EO 37 E O

• + Co-134 9.99E-01

( 130 +- 22 ) E-1 48 E-1 Ru-106 9.99E-01

(-1 +- 28 ) EO 93 E O

• + Cs-137 1.00E 00

( 1207 +- 52 ) E-1 130 E-1 Ag-110M

. 9.98E-01

(-8 +- 53 ) E-1 180 E-1 Er-95 9.94E-01

(-77 +- 59 ) E-1 200 E-1 Co-58 9.94E-01

(-11 +- 34 ) E-1 110 E-1

• + Mn-54 9.99E-01

( 393 +- 43 ) E-1 120 E-1

• + AcTh226 1.00E 00

( 39 +- 11 ) EG 32 E O TeI-132 8.81E-01

(-7 +- 2) ) EO 98 E O Fe-59 9.91E-01

( 68 +- 73 ) E-1 240 E-1

• + zn-65 9.98E-01

( 527 +- 82 ) E-1 230 E-1

• + Co-60 1.00E 00

( 853 +- 12 ) E O 14 E O

• + K -40 1.00E 00

( 223 += 35 ) E O 110 E o Sb-124 9.93E-01

(-12 +- 3 5 ) E-1 120 E-1 e

Notes:Activity greater than 3* standard deviation Approved by

+ ' Peak is found

:::..=n:::: :=.i

,n.:=. i.. n.<.4 D t h 5 :

/:.:

..:= n':

~

.U.. :=si.i.

i.. i D.E.HcCur y s.. i..

a.

.i

,U..',U..U..U$'OU.=d,.'. U7[io*.*UE..U*IN*:A' d*UU*.U.IIUf' I

m m

R

m 4

YANKEE ATOMIC ELECTRIC COMPANY gy Q,(J ENVIRONMENTAL LADORATORY Initial Analysls Report

' d-

Customer :7 Vermont, Yankee Nucicar Power Corp.

Report Date: 06/20/88 g

Attenbibn5 /MSl^'EddHE KEEGAN Analysis Date: 6 /15/88 8

MR. EDWARD CUMMING Date Received: 6 /14/88 Reference Date: 6 /8 /88 HR. STEPitEN SK1BN10WSKY Septic-Solid Lab Sample No. :

G73075 Sample Amount: 0.0G Kg.

. Sample Submission Code: VSLs04 2J88 Elapsed Time : 7.57 days other Analysis Requested:

None Station No.:

04 Main Tank Bottom DECAY ACTIVITY HUCLIDE CONC. +- 1 SIGMA MDC CORRECTION

[

Pico Curie / Kilogram

)

Np-239 1.07E-01

( 55 +- 25 ) E2 85 E 2 Co-57 9.81E-01

(-9 +- 3 0 ) EO 99 E 0 1

Ce-144 9.82E-01

( 3 +- 22 ) E1 74 E1 Ce-141 8.51E-01

( 137 +- 60 ) EO 190 E O

(,,

Mo-99 1.51E-01

(-60 +- 29 ) E2 9 7 E 1.

So-75 9.57E-01

( 8 5 +- 51 ) EO 170 E 3

' ^

Cr-51 8.27E-01

( 14 +- 36 ) E1 12e E 1 I -131 5.21E-01

.(-6 +- 74 ) EO 250 E O Be-7 9.06E-01

( 12 +- 38 ) E1 130 E 1 Ru-103 8.75E-01

(-2 +- 4 6 ) Eo 150 E O XI -133 2.49E-03 Ba-140 6.64E-01

(-86 +- 40 ) EO 130 E o

• + Cs-134 9.93E-01

( 166 +- 52 ) EO 150 E O Ru-106 9.86E-01

( 12 +- 49 ) E1 160 E1

• + Cs-137 1.00E 00

( 3824 +- 92 ) EO 200 E O Ag-110M 9.79E-01

( 7 6 +- 96 ) EO 320 E O Zr-95 9.22E-01

(-2 +- 11 ) E1 36 E 1 Co-58 9.29E-01

( 12 +- 60 ) EO 200 E O

• +.Mn-54 9.83E-01

( 1126 +- 74 ) EO 200.E O

• + AcTh228 1.00E 00

( 7 6 +- 17 ) E1 49 E 1 TeI-132 1.99E-01

(-14 +- 22 ) E2 75 E 2 Fe-59 8.90E-01

( 7 +- 14 ) E1 48 E 1

• + Zn-65 9.79E-01

( 120 +- 14 ) E1 40 E 1 4

• + Co-60 9.97E-01

( 2240 +- 22 ) E1 23 E 1

• + K -40 1.00E 00

( 472 +- 53 ) E 1 160 E 1 Sb-124 9.17E-01

( 69 +- 61 ) EO 200 E O Notes:Activity greater than 3* standard deviation Approved by

,I

+

Peak is found.

x-Decay correction less than.01 D.E.McCurdy.

4s aa m..,

.......i s 4. n

4. e........ s..a.s.m

..tl

....f em...di t i

.I. y.t.

t l...d.

de. esa... t.l at ie....

m.si,..,...,..4.,.......,_,....,...........

p......

....... _i... u...., a.. se...

e...

e

l 4

YANKEE ATOHIC ELECTRIC' COMPANY MAlWU ENv1RONnENrAL tao 0RATORY i

,10,1 2. 1 Initial Analysis Report VI.. C.

Custopprg;:yVergon(Mankee Nuclear Power Corp.

Report Date: 06/20/88 AttenElon MS. ELAINE KEEGAN Analysis Date: 6 /15/88 Date Received: 6 /14/88 MR. EDWARD CUMMING Reference Date: 6 /8 /88 HR.

STENIEN SKIBNIOWSKY Septic-Liquid Portion

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - = - -

Lab Sample No.:

G73074 Sample Amount: 1.00 Kg.

Sample Submission Code: VSL104 2388 Other Analysis Requested:

None Elapsed Time : 7.57 days Station No.:

04 Main Tank Dottom DECAY ACTIVITY CONC. +- 1 SIGMA MDC 1RfCLIDE CORRECTION

(

Pico Curie / Kilogram

)

- - = = - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _

Np-239 1.07E-01

( 142 +- 88 ) EO 290 E O Co-57 9.81E-01

(-16 +- 99 ) E-2 330 E-2 Ce-144 9.02E-01

( 60 +- 73 ) E-1 240 E-1 Ce-141 8.51E-01

( 15 +- 19 ) E-1 63 E-1 Mo-99 1.51E-01

(-123 +- 94 )EO 310 E O So-75 9.57E-01

(~6 +- 15 ) E-1 50 E-1 Cr-51 0.27E-01

( 3 +- 11 ) EO 36 E o I -131 5.21E-01

. (-6 +- 20 ) E-1 67 E-1 De-7 9.06E-01

( 37 +- 98 ) E-1 330 E-1 Ru-103 8.75E-01

(-5 +- 13 ) E-1 44 E-1 xI -133 2.48E-03 Da-140-6.64E-01

(-23 +- 23 ) E-1 77 E-1 Cs-134 9.93E-01

(-9 +- 15 ) E-1 49 E-1 Ru-106 9.86E-01

( 1 +- 12 ) EO 41 E O Cs-137 1.00E 00

( 21 +- 14 ) E-1 47 E-1 Ag-110M 9.79E-01

(-20 +- 18 ) E-1 59 E-1 Zr-95 9.22E-01

( 29 +- 23 ) E-1 75 E-1 Co-58 9.29E-01

( 2 0 +- 13 ) E-1 43 E-1 Mn-54 9.83E-01

( 3 +- 13 ) E-1 42 E-1 AcTh228 1.00E.00

( 28 +- 61 ) E-1 240 E-1 TeI-132 1.99E-01

( 2 5 +- 3 7 ) EO 120 E'O Fe-59 8.90E-01

(~1 +- 25 ) E-1 82 E-1 Zn-65 9.79E-01

( 31 +- 26 ) E-1 86 E-1 Co-60 9.97E-01

(-13 +- 22 ) E-1 86 E-1

+ K -40 1.00E 00

( 34 +- 21 ) EO 7S E O Sb-124 9.16E-01

( 68 +- 30 ) E-1 100 E-1 Notes:

+

Peak is found Approved by Decay correction less than.01 x

g m

.3-w..,

..a

-.i.

.....s i.4.

i,..i....i..:.. a

.c. t i... m..,....... 4.t im.6.. 4 6.... s......,

i

.. i s...

..., c.m... i. i. i.,...... 4 D.E.McCurdy.

,... s..

s,....,.., s.

a e s a.

i i

i l

1 l

~

YANKEE' ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY

{3 j

' Initial Analysis. Report s

l fgt p f

. Report Date: 07/11/88 i

Customer I:s/f(ggmont Yankee Nuclear' Power Corp.

5 i AtteEM4MUNIM&4T/ED&INE KEEGAN

.Date Received: 6 /14/88' 1

MR. EDWARD CUMMING i

a 4

Septic-Solid t.

~

l

. LAB. No..

DATE ACTIVITY l

SAMPLE CODE-of VOLUME NUCLIDE' CONC. +- 1 SIGMA' MDC-i REFERENCE ANALYSIS-Kg

[ Pico Curie / KC ; DRY 1

S73075:

61/8 7 /7 0.022 Sr-90

(-14 +- 37 )E O 40E O l'

VSLs04 2388 Main Tank' Bottom Sr-89

( 52 +- 46 )E 0 62E.0 1

i-L 1

i

+

i i

[

r 1

i I~

i i

L i

l i

=

i I

i

. Notes:

APPpoved by l

'.as quoted one-sigma terms tactode only counting statistice and do not represent t.. the propagation of all possible errors associated with the radioactive decay f.stimates of the additional systematic and random oncertainties ares 4

- **llbratloa curve, + 5 percent, and sample positioning, + 2 percent.

g procss a.

I

r' ~

D.E.McCurdy.

- = - _ -

- ~..

_. ~.. _...

YANKEE ATOMIC ELECTRIC COMPANY

'g'-

. ENVIRONMENTAL: LABORATORY-_

M Altt_!>

Initial. Analysis Report

gg ;g Customery.A ermont Yankee Nuclear Power Corp.

Report Date: 07/11/88

.INE;KEEGAN Date Received: 6 /14/88 AtMkORIA AL%,DWARD CUMMING.

l Septic-Liquid Portion-j 4

LAB. No.

DATE ACTIVITY SAMPLE CODE.

of VOLUME NUCLIDE CONC. +- 1-SIGMA MDC i

REFERENCE ANALYSIS Kg

-[ Pico Curie /' Kilogram']

l

'S73074 6 /8 6-/19 1.002 Sr-90

( 113 + -98 )E-2 200E-2

. -10 +- 11 )E-1 22E-1

(

VSL104-2388 Main Tank Bottom Sr-89 i

4 4-

[

i 1

1 i

i('l a

i t

P h

9

[

+'

i i

i I

s i

i Notes:

~

p AppraYed by.

= The quetsd one-slama tetus laciude only counting statistics and do not represent

{

the propag* tion of all possible errors associated with the radioactive decay procald. Satinates of the additional systeenatic and random uncertalaties aret

+

' ellibritime curve, 3 $ percent, and sample positioning,12 percent.

D.E.McCurdy.

tr YANKEE ATOMIC ELECTRIC COMPANY f.

I c~ :. 1 y, -

1 ENVIRONMENTAL LABORATORY -

- - -~

'.lOL i L'i.].

Initial Analysis

_________________' Report j

YA11C Cug,tpaggNg,EM9FFDqt Yankee Nuclear Power Corp.

Report Date: 07/11/88 t

. Attention: MS. ELAINE KEEGAN Date Received: 6 /14/88 MR. EDWARD CUMMING

?

Septic-Liquid Portion t

i t

LAB.'No.

'DATE ACTIVITY SAMPLE CODE of VOLUME NUCLIDE CONC. +- 1 SIGMA MDC i

REFERENCE ANALYSIS Kg

[ Pico Curie / Kilogram ]

[

H73074 6 /8-6 /20 0.003 H_3

( 26 +- 15 )E 1 49E 1 i

VSL104 '2388 ' Main Tank Bottom h

5 4

t a

+

i l

l f

k

(

4 L

d

[

j tt t

i, i

Notes:

t Apprpved by

- ha quoted onen(sma terms inctode only coveting statistics and do not represent

~

'. the $ropagetion of all possible errors associated with the radioactive decay groceas.. Estimates of the additional systematic and randen uncertaintles aret eglibestion curve, + 5 percent. and sample positioning. + 2 percent.

.-_.-___________a.-_

t

? -

D.E.McCurdy.

APPENDIX B Computer Code Outputs This section contains copies of the computer-code outputs employed in the calculation, as follows:

B.1 ALLEGRA - Gamma Ray Spectra B.2 DILOS-V - Dose Reduction as a Result of Plowing B.3 ATMODOS - Radiological Impact During VY Control of the Disposal Site B.3.1 Impact due to Mn-54 in the Septage B.3.2 Impact due to Co-60 in the Septage B.3.3 ~ Impact due to Zn-65 in the Septage B.3.4 Impact due to Cs-134 in the Septage B.3.5 Impact due to Cs-137 in the Septage B.3.6 Impact due to All Nuclides in the Septage B.4 ATMODOS - Radiological Impact After Termination of Vermonc Yankee Control of the Disposal Site (All Nuclides) s B.5 ATMODOS - Unplowed-Land Dose Conversion Factors for Radiological Impact Assessment B.S.1 Impact due to 1 uC1 of Mn-54 B.5.2 Impact due to 1 uCi of co-60 B.5.3 Impact due to 1 uci of In-65 B.S.4 Impact due to 1 uCi of Cs-134 B.5.5 Impact due to 1 uCi of Cs-137 B-1 6680R'

C.>.

C>g C333Q %8* g C Q O +r 93

)

1 i

'E G

A P

0 3/

4 0

/

8 8

8 8

'8

/

80 9

/

8 6

7 0

6 S

1

- 5 G

4 N

0 3

I P

D 1

M-O 70 U

H 9

F 8

7 K

=

4 N

3 A

4 T

3 C

0 N

1 4

I 40 9

R 8

E G

7 T

N 6

F I

5 A

0 R

4 E

3 Y

E T

0 N

1 I

I 50 V

G G

9 I

N N

8 T

E t

7 C

f 4

A H

S 3

2 C

I 4

D 0

E L

3 L

T E

1 N

A 1

I E

T 40 F0 A

9 D

8 7

E T

6 E

S U

5 G6 0

A F

4 A

S N

3 W

I E

0 A

1 S

T 4

30 1

646455 A

9 D

000000 D

E 8

E P

7 T

EEEEEE A

6 A

131799 T

5 N10 300053 N

4 I

0838427 E

3 M

0 A

0222198 1

1 T

R 20 N10 O

9 O

8 C

7 4

F 000001 A

0 O11 4 05477 R

4 0344333 T

3 L

000111 C

2 A

1570536 E

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p V

DIDOS-V (CTLINDRICAL RADIATION SOURCE DOSIMETRT)

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08/07/00. PAGE 3

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VT.- DISP. OF CONTAM. SEWACE - ACTIV. FROM 40 PUHPCUTSI: ACRES - UNFLOWED LAND RECEPT 0R 1 TIME (HRS) *

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88/07/02. PAGE 3

VY - DISP. OF CONTAM. StuADE - ACTIV. FROM 40 runFOUTS/2 ACRES - FLCWED LAND

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It corresponds to the i

output in Sec. B.3.6 below.

With the except,lon of the nuclide dat,a large portion of which was deleted due to space limitations, library, a 4

the listing is complete.

I The Tape 5 listings corresponding to the outputs in Sec. B.3.1 through B.3.5 are similar, except that a single isotope was analyzed in each case.

Also, the tables with the detailed pathway / isotope / organ i

exposures were excluded from the output.

i t

l 1 IVYp1 VY STANDARD PROGRAM INFORMATION FILE VY - SEWAGE CONTAM - SOLIDS 1% BY Wl' - 2 ACRES - SHIELD F = 0.012 - 104 HR 00 cup 1.

.200 44.56 FRESH.500YESNO NO 0. 012 1.NO NO NO 0.1.00 l (

--EOR--

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0 2VYGASRIDAS S1K VY 87 1 1 0 87063023:

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1 SQUERY PAT 1! WAYS: S110RE( 1, 2, 3 ), BND, ROAD, RES 1, RAD. HEAT, GOAT,00W SilORE1 YESYES SilORE2 YESYE Sil0RE3 YESYES 4

i IXXJND YESYES HOAD YESYES RES1 YESYESYESYE RADIUS YESYES 1

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GOAT YESYEYESYES YES YESYES j

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--DOR--

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4 i

d ENTECH ENGINEERING, INC.

Page B.3-1 P101-EC3

1 GVYUFNAXVY HAXIMUM INDIVIDUAL USAGE FACIORS FOR STANDNID PIORBLDfS 520.00 64.00 310.00 110.00 21.00

.00

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1 7VYGSD VY MAX INDIVIDUAL GAS SITE DATA FILE FOR STANDARD P10BLEMS 2.00 2.00

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.00

.00

.50

.00

.50

.00

.50

.00

.00

.00 1.00

.00 1.00

.00 1.00

.00 1.0 1.00

.00

.00

.00

.00

.00

.00 5.60

.00

.00

.00

.00

.00

.00

.00

-- FDi t--

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ENTECH ENGINEERING, INC.

P101-EC3 Page B.3-2

1 81STPNBLNUCLIDE LIBRARY FOR ALL IDSE PROGRM4S i

89 1

3 1.78E-090.00E+ 000.00E4 00 SOLUBLE 11 9.0E-01 9.0E-01 9.0E-01 9. 0E-01 9. 3E-01 9. 3E-01 4. 8E-00 1.0E-02 1. 2E-02 0.

1.05E-071.05E-071.05E-071.05E-071.05E-071.05E-07 0.

1. 58E-071. 58E-071. 58E-071. 58E-071. 58E-071. 58E-07 0.

1. 0G E-071. 0G E-071. 0G E-071. 0G E-071. 0G E-071. 0G E-07 0.

1. 59E-071. 59E-071. 59 E-071. 59E-071. 59E-071. 59 E-07 0.

2.03E-072.03E-072.03E-072.03E-072.03E-072.03E-07 0,

3. 04 E-073. 04 E-073. 04 E-073. 04 E-073. 04 E-073. 04 E-07 0.

3.08E-073.08E-073.08E-073.08E-073.08E-073.08E-07 0.

4.62E-074.62E-074.62E-074.62E-074.62E-074.62E-07 SOLUBLE 6 14 3.83E-12 C 4.GE403 9.1E403 4.GE403 1.8E+03 1.4E+03 1.8E+03 5.5E+00 1.2E-02 3.1E-02

2. 84 E-065. 68E-075. 68E-075. 68E-075. 68E-075. 68E-075. 68E-07 2.27E-064.2GE-074.2GE-074.2GE-074.2GE-074.2GE-074.2GE-07 4. 0G E-068.12 E-078.12 E-078.12 E-078.12 E-078.12 E-078.12 E-07 3.25E-0GG.09E-076.09E-076.09E-076.09E-076.09E-076.09E-07

1. 21 E-052. 42E-062. 4 2E-062. 42E-0G2. 4 2 E-062. 42E-0G2. 42E-06 9.70E-061.82E-061.82E-061.82E-061.82E-061.82E-0G1.82E-06 2.37E-055.0GE-0GS.0GE-065.0GE-005.0GE-005.0GE-0G5.0GE-06 1.89E-053.79E-063.79E-063.79E-063.79E-0G3.79E-063.79E-06 11 24 1.28E-052.50E-08 2.90E-08 SOLUBLE h'

h'IC (FDR A 7UTAL OF 89 NUCLIDES)

__gon__

--eof--

1 3VYXQF VY X/QFILE - SPIIIAL VALUES - SEWAGE CONTAM. PROBLD4 - 2 ACRE PIDTS FLD 0 COW MEAT 4.62GE-04 4.62GE-04 1.23GE-04 4.62GE-04

-BoR--

--EDF--

r ENTECH ENGINEERING, INC.

P101-EC3 Page B.3-3

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YANxEE ATOMIC ELECTRIC CCMFANY DEC. 1985 REV. 7 SECTOR FLD g3

=

-0 (METERS)

REGUL ATORY GJ1DE 1 10f e APPENDIE C DISTANCE 4.63E-04 (SEC/M-31 MODELS FOR CALCULATING DOSE VIA X/O

=

ADDITIONAL PATHWAYS FROM RADIO 10 DINES X/O DEFLETED = 4.63E-04 (SEC/M-3) um 1 24E-04 (1/M-2) g AND OTHER RADIONUCLIDES DISCHARGED DELTA

=

TO THE ATMOSFHERE NOV.1977 LIBRARY O

VY - SEWAGE CONTAM - SCL1DS 12 pY kT - 0 m

0.012 - 104 HR occur O

ACRES - SNIELD F

=

c*

6 FATMWAYS CONSIDERED C.

THE FOLLOWING 1 NUCLIDES WERE USED IN TH1$ CALCUL AT'!ON C

GROUND PLANE YES NUCLIDE RELEASE INNALATION YES STORED VEGETApLES TES CURIES h

30 IN 65 4.50E-06 LEAFY VEGETA?LES YES COW MILK YES COAT MILK NO g

MEAT TES 7

O

(.n e

~1 t*

O VEGETABLES COW MILK GOAT MILE MEAT STORED LEAFY FASTURE STORED PASTURE STORED PASTURE STORED VARIABLE CO '

TV AGRICULTURAL FRODUCTIVITY (K0/M-2) 2 00 2 00

.70 2 00

.70 2 00

.70 2 00 P

SOIL SURFACE DENSITY (K0/M-2) 240 00 240.00 240.00 240.00 240.00 240.00 240.00 240.00 d$

48 00 48 00 48.00 48.00 480.00 480.00 re (HRS) 8766 00 8766.00 8766 00 8766.00 8766.00 8766.00 8766.00 8766.00 A

(HRS)

T TRANSPORT TIME TO USER (HRS)

.00

.00

.00

.00

.00

.00

.00

.00 TB SOIL ExFOSURE TIME (HRS) 1440.00 24.00

.00 2160.00

.00 2160 00

.00 2160.00 TE CROP EXPOSURE TIME TO PLUME D1 TH HOLDUP AFTER HARVEST 50.00 50.00 6.00 4 00 50.00 50:00

{SC 0F ANIMALS DAILY FEED (K0/DAT)

.50

.50

.50 h3 FF FRACTION OF YEAR ON PASTURE 1 00 1 00 1 00 FS FRACTION PASTURE WHEN ON PAS'esst q) bg g (}

FG FRACTION OF STORED VE0 OROWN Id GARDEN 1 00 m,

FL FRACTION OF LEAFY VE0 OROWN IN GARDEN 1.00 gg gg FRACTION ELEMENTAL 10 DINE =

.500 FI

()

APSOLUTE HUMIDITY 3 60 (GM/M-3)

=

H (o g FRACTIONAL EQUILIBRIUM RATIO FOR C-14 = 1 000 FC y

stetssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssess l Ci DOSE DELIVERED TO EACM ORGAN e

>1 USAGE FACTORS FROM ALL FAT 8 WAYS COMPINED a

SC b1 VEG LEAFY MILK MEAT ' INHALATION b1 AGE VES s

PONE LIVER K!DNEY LUNG GI-LLI THYROID WHOLE BODY SMIN 3

e (MREM)

O ADULT $20.00 64.00 310 00 110.00 8000.00 s 3 43E-03 1 06E-02 7.13E-03 2 03E-04 6 72E-03 1 46E-04 4.87E-03 1.68E-04 s 4 pg (K0/TR) (K0/YR) (L1/YR) (K0/YR)

(M-3/YR) 9 g

TEEN 630.00 42.00 400.00 65.00 8000.00 4.61E-03 1 57E-02 1 01E-02 2 28E-04 6.72E-03 1.46E-04 7.38E-03 1 68E-04 s CHILD 520.00 26.00 330.00 41 00 3700.00 8 72C-03 2 30E-02 1 45E-02 2.11E-04 4.16E-03 1.46E-04 1 44E-02 1 68E-04 9 kg INFANT

.00

.00 330.00

.00 1400.00 a 4 18E-03 2 08E-02 1 02E-02 1.88E-04 1.76E-02 1.46E-04 9.6TE-03 1.68E-04 s g3 g) sessssssssssssssettsssssssssssssssssssssssssssssssssssssssssssssessanassasassesses La C,d :e

. c)

m1 a.'

PROGRAM ATRODOS TANKEE ATOMIC ELECTRIC COMPANY DEC. 1985 REU. 7 g3 REGULATORY GUIDE 1 109. AFFENDIX C SECTOR FLD M0!ELS FOR CALCULATING DOSE v! A DISTANCE

=

0 (METERS) 45 ADDITIONAL FATHWAYS FROM RADIO!DDINES I/O

= 4 63E-04 (SEC/M-3) 4.63E-04 (SEC/M-3)

X/O DEPLETED 6

AND OTHER RADIONUCLIDES DISCHAROED 1.24E-04 (1/M-2)

TO TME ATMOSFHERE NOVe1977 L19RARY DELTA

=

3 VY - SEWAGE CONTAM - SOLIDS 11 PY WT -2 O

ACRES - SNIELD F = 0.012 - 104 NR OCCUP 3

O f*

THE FOLLOWING 1 NJCLIDES WERE USED IN THIS CALCULATION 6 PATHWAYS CONSIDERED hh GROUND FLANE TES MUCLIDE RELEASE INMALATION YES CURIES STORED VEGETAPLES TES 55 CS 134 1 72E-06 LEAFY VECETA9LES

'YES c,

COW MILK YES o

GOAT MILK NO MEAT YES

()

m

~'

LJ Jk N.

5 UARIAPLE VE0ETAPLES COW MILM 00AT MILM MEAT

[

STORED LEAFY PASTURE STORED FASTURE STORED FASTURE STORED YV AGRICULTURAL FRODUCTIVITY (KG/M-23 2 00 2 00

.70 2.00

.70 2 00

.70 2 00 F

SOIL SURFACE DENSITY (K0/M-23 240 00 240.00 240.00 240.00 240.00 240.00 240.00 240.00 cn T

TRANSPORT TIME TO USER (HRSD 48.00 48.00 48.00 48.00 480.00 480.00 o

TB SDIL ENFOSURE TIME (HRS) 8766.00 8766.00 8766.00 8766.00 8766.00 8766.00 8766.00 8766.00 T3 h[

TE CROP EXFOSURE TIME TO FLUME CHRS)

.00

.00

.00

.00

.00

.00

.00

.00 TH HOLDUF AFTER HARVEST (HRS) 1440 00 24.00

.00 2160.00

.00 2160.00

.00 2160 00 ya bg 0F ANIMALS DAILY FEED (K0/ DAY) 50.00 30.00 6.00 6.00 50.00 50.00 G

"U gg FF FRACTION OF YEAR DN PASTURE

.50

.50

.50 FS FRACT!DN PASTURE WNEN ON PASTURE 1.00 1 00 1.00 C3 FG FRACTION OF STORED VEG OROWN IN GARDEN 1 00

"* O FL FRACTION OF LEAFY VEG OROWN IN GARDEM 1 00 1 Cl FI FRACTION ELEMENTAL 10 DINE =

.500 UU UE H

ASSOLUTC HUMIDITT = 5 60 (GM/M-3)

El 1.000 FC FRACTIONAL EQUILIBRIUM RATIO FOR C-14

=

E4 DU asssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssss Og g C3 USAGE FACTORS DOSE DELIVERED TO EACH ORCAM s

a FROM ALL FATHWAYS COMP!NED e

kg s

3g UEG LEAFT MILK MEAT IMHALAT!DN s "U bg ACE VEG s

PONE LIVER MIDNEY LUNG Of*LLI THYROID WHOLE 30DY SKIM-a b

(KO/TR) (K3/YR) (LI/YR) (KG/YR)

(M-3/YR)

(MREn)

D% pg ADULT 520.00 64.00 310 00 110.00 8000.00 s 5 89E-04 1 09E-03 5 06E-04 3 20E-04 2 42E-04 2.27E-04 9.31C-04 2 65E-04 gn Q

TEEN 630.00 42 00 400.00 65 00 8000.00 a 7.92E-04 1.56E-03 6.50E-04 3 89E-04 2.44E-04 2 27E-04 8.44E-04 2 65E-04 a CHILD 520 00 26.00 330 00 41 00 3700.00 s 1 50E-03 2 11E-03. 8.74E-04 4.59E-04 2 38E-04 2 27E-04 6.67E-04 2 65E-04 a 1

E INFANT

.00

.00 330.00

.00 1400.00 s 7.74E-04 1.25E-03 4.8?E-04 3 35E-04 2.30E-04 2.27E-04 3.30E-04 2 65E-04 a s

D3 C3 e

sesssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssses to b5":"

i t

m. C)

_4 m

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'S wi tU PROGRAM ATMODOS

~*

YANKEE ATOMIC ELECTRIC COMPANY gg DEC. 1985 REV. 7 SECTOR FLD e, -

RESULATORY GUIDE 1 109e APPENDIX C DISTANCE

=

0 (METERS)

PODELS FOR CALCULATING DOSE VIA I/O

. 4.63E-04 (SEC/n-33 ADDITIONAL PATHWAYS FROM RADIO!ODINES X/0 DEFLETED s 4.63E-04 (SE /M-31 H

1 24E-04 (1/M-23 IB AND OTHER RADIONUCLIDES DISCHARGED DELTA

=

TO THE ATMOSPHERE-Nove1977 L1DRARY C

VT - SEWAGE CONTAM - SOLIDS 12 By WT - 2 3'

ACRES - SHIELD F = 0.012 - 104 MR OCCUP (I

c*

6 FATHWAfS CONSIDERED THE FOLLOWING 1 NUCLIDES WERE USED IN THIS CALCULATION

' GROUND FLANE TES NUCLIDE RELEASE INHALATION TES'-

CURIES STORED VEGETABLES TES e,

55 CS 137 9.37E-05 LEAFT VEGETABLES TES c;

COW MILK YES GOAT MILK NO

()

MEAT TES UI M

-4 ha.

3 c*

-w.

VEDETAPLES COW MILK 00AT MILK MEAT STORED LEAFT PASTURE STORED PASTURE STORED PASTURE STORED VARIABLE TV AGRICULTURAL FRODUCTIVITT (KG/M-2) 2 00 2.00

.70 2 00

.70 2 00

.70 2 00 to P

SDIL SURFACE DENSITT (K0/M-2) 240 00 240 00 240.00 240.00 240.00 240.00 240.00 240.00 T3 T

TRANSFORT TIME TO USER (HRS) 48.00 48.00 48.00 48.00 480.00 480.00 TP SDIL EXPOSURE TIME (HRSS 8766.00 8766.00 8766.00 8766.00 8766 00 8766.00 8766 00 8766.00 h[

93 TE CROP EXPOSURE TIME TO PLUME (HRS)

.00

.00

.00

.00

.00

.00

.00

.00 74

>* bg TH HOLDUP AFTER HARVEST (HRS) 1440.00 24.00

.00 2160.00

.00 2160.00

.00 2140.00 0

CD 2g 0F ANIMALS DAILY FEED (RG/DAT) 50.00 50 00 6.00 6.00 50.00 50.00

.50

.50

.50

• • mg FP FRACTION OF TEAR ON PASTURE 1.00 1 00 1 00 I

FS FRACTION PASTURE WHEN ON PASTURE DU g FG FRACTION OF STORED VEG OROWN IN GARDEN 1 00 El FL FRACTION OF LEAFT VES OROWN IN CARDEN 1 00 DO E FI FRACTION ELEMENTAL IODINE =

.500 M

A930 LUTE HUMIDITY

• 5 60 (GM/M-3)

• 1.000 DU PC FRACTIONAL EQUILIPRtUM RATIO FOR C-14 g %

sassasssssssssssssstessssssssssssssssssssssssssssssssssssssssssssssssssssssssssss :

C)

DOSE DELIVERED TO EACM QRGAN

% >1 USAGE FACTORS FROM ALL PATHWAYS COMPINED 9

s l

h 3g

@4 bg VE0 LEAFT MILK MEAT INHALATION

• O pg AGE VEG PONE LIVER K!DNET LUNG GI-LLI TNTROID WHOLE PODY SKIN l

s (KG/TR) (K0/TRI (LI/TR) (KG/TR)

(M-3/TR) s (MREM)

ADULT 520.00 64.00 310.00 110.00 8000.00

• 3 57E-02 4.70E-02 1 93E-02 9 79E-03 5.86E-03 3.06E-03 3 20E-02 5.90E-03 :

gg TEEN 630.00 42 00 400 00 65 00 8000.00 s 5 5 E-02 7 18E-02 2 78E-02 1 39E-02 6.00E-03 0.06E-03 :.83E-0: 5 90E-03 :

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P101-EC3 '

Page B.3.G-9 t

~

B.4 ATHODOS - Radiological Impact After Termination of VY Control of the Disposal Site (All Nuclides t q

Presented below is a partial listing of the ATMODOS Tape 5 input used in this portion of the calculation.

It corresponds to the output I

which follows.

With the exception of the nuclide data library, a large 4

portion of which was deleted due to space limitations, the listing is j

complete.

1' 1 1VYPI VY STANDARD PROGRAM INFORMATION FILE VY - SEWAGE OWfAM - SOLIDS 1% BY Vf - 2 ACRES - SHIELD F = 0.242 - CONT. OCCUP 1.

.200 44.56FRESil

.500YESNO NO 0. 242 1.NO NO NO 0.1.00

--mR--

-- mF--

j 0 2VYGASRIIIAS S1K VY 87 1 1 0 87063023:

i MN54 4.132E-6 25 MN 54 0060 2.511E-4 27 00 60 ZN65 4.502E-6 30 ZN 65 CS134 1.715E-6 55 CS 134 CS137 9.366E-5 55 CS 137

(-

--mR-1

--WF--

1 SQUERY PA'111 WAYS : SIIORE(1,2,3),BND, ROAD,RES1, RAD, MEAT GOAT,00W SHORE 1 YEYES Si! ORE 2 YESYES SIIORE3 YESYES DOUND YEYES ROAD YESYE RES1 YESYESYESYES RADIUS YESYES MFAT YESYESYESYES YESYESYES GOAT YEYESYESYES YES YESYES 00W YESYESYESYESYES YESYES j

__ mg__

--EOF--

1 GVYUFMAXVY MAXIMUM INDIVIDUAL USAGE FACIORS FOR STANDARD PFORBLEMS 520.00 64.00 310.00 110.00 21.00

.00

.00 12.00

.00 8000.00 630.00 42.00 400.00 65.00 16.00

.00

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520.00 26.00 330.00 41.00 6.90

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.00

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.00

.00

.00

.00

.00 1400.00 j

--BOR--

--my--

4 ENTECH ENGINEERING, INC.

Page B.4-1 P101-EC3

1 7VYGSD VY MAX INDIVIDUAL GAS SITE DATA FILE FOR STANDARD PROBLD1S

/

2.00 2.00

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0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1440.00 24.00

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i

--BOF--

18ISTPNBLNUCLIDE LIBRARY FOR ALL DOSE PROGRAMS 89 SOLUBLE 1 3 1.78E-090.00E+000.00E400 H 9.0E-01 9.0E-01 9.0E-01 9.0E-01 9.3E-01 9.3E-01 4.8E-00 1.0E-02 1.2E-02

]

1 0.

1.05E-071.05E-071.05E-071.05E-071.05E-071.05E-07 0.

1.58E-071.58E-071.58E-071.58E-071.58E-071.58E-07 i

0.

1.0GE-071.0GE-071.0GE-071.06E-071.06E-071.0GE-07 O.

1.59E-071.59E-071.59E-071.59E-071.59E-071.59E-07 0.

2.03E-072.03E-072.03E-072.03E-072.03E-072.03E-07 1

0.

3.04E-073.04E-073.04E-073.04E-073.04E-073.04E-07 l

0.

3.08E-073.08E-073.08E-073.08E-073.08E-073.08E-07 0.

4.62E-074.62E-074.62E-074.62E-074.62E-074.62E-07

C}

SOLUBLE G 14 3.83E-12 C 4.6E+03 9.1E+03 4.6E+03 1.8E+03 1.4E+03 1.8E+03 5.5E+00 1.2E-02 3.1E-02

{

l 2.84E-065.68E-075.68E-075.68E-075.68E-075.68E-075.68E-07 l

2.27E-064.26E-074.26E-074.26E-074.26E-074.26E-074.262-07 l

4.06E-068.12E-078.12E-078.12E-078.12E-078.12E-078.12E-07 3.25E-066.09E-076.09E-076.09E-076.09E-076.09E-076.09E-07 1.21E-052.42E-062.42E-062.42E-062.42E-062.42E-062.42E-06 i

9.70E-061.82E-061.82E-061.82E-061.82E-061.82E-061.82E-06 2.37E-055.06E-0GS.0GE-065.0GE-065.06E-065.06E-065.0GE-06 1.89E-053.79E-063.79E-063.79E-063.79E-063.79E-063.79E-06 i

11 24 1.28E-052.50E-08 2.90E-08 SOLUBLE

$UC (FOR A 'IUI'AL OF 89 NUCLIDES)

__ son __

--EOF--

l 1 3VYXQF VY X/QFILE - SPECIAL VALUES - SEWAGE CONTAM. PROBLDi - 2 ACRE PIBI'S FLD 0 00W MEAT 3.896E-02 3.896E-02 1.236E-04 3.896E-02

__H)R--

--EDF-ENTECH ENGINEERING, INC.

P101-EC3 Page B.4-2 ww*

- -+

r

s

.O 3 FROGRAM Aftt0 DOS YANKEE ATOMIC ELECTRIC COMPAM" DEC. 198 REV. ?

SECTOR FLD 0

(HETERS)

REGULATORY GUIDE 1 109. AFFENDIX C DISTANCE e

3 90E-02 (SEC/M-31 MODELS FOR CALCULATING DOSE VIA X/O ADDITIONAL FATHWAYS FROM RADIO!0D*NES

/0 DEFLETED 3.90E-02 (SEC/M-33 1.24E-04 (1/M-21 AND OTHER RADIONUCLIDES DISCHARGED DELTA TO THE ATMOSFNERE NOV.1977 LIPRARY SOLIDS 1 3Y WT -

VY - SEWADE CONTAM.

ACRES - SHIELD F = 0.042 - CONT. OCCUF

& FATHWAYS CCHSIDERED THE FOLLOWING S NUCLIDES WERE USED IN THIS CALLULATION GROUhD FLANE YES NUCLIDE RELEASE INMALATION TCS CURIES STORED VEQETAPLES YES

$ MN 34 4.13E-Oe LEAFY UEGETAPLES YES 27 C5 60 2.51E-04 COW MILK YES 30 ON 63 4.00E-06 GOAT MILK NO 55 CS 134 1 72E-06 MEAT YES 03 CS 137 9.37E-0 VECETABLES COW HILK 004T MILK MEAT STORED LEAFY FASTURE STORED FASTURE STORED FASTURE STOKED VARIAPLE YV AGRICULTURAL PRODUCTIVITY tFM/M-25 2 00 2 00

.70 0 00

.70 2 00

.70 2.00 F

SOIL SURFACE DENSITY (KU/M-2)

• 40 00 240 00 240.00 240.00

.'40.00 240.00 240.00 240.00 48.00 48.00

=9.00 48.00 450.00 480.00 EHRS) 8766 00 8766.00 0766 00 8766.00 8764 00 8746.00 8766.00 8764.00 (NRS)

T TRANSFORT TIME TO USER TE CROF EEFOSURE TIME TO FLUME (HRS 3

.00

.00

.00

.00

.30

.00

.00

.00 TB SOIL EXF05URE TIME TH HOLDUP AFTER HARVEST (HRS) 1440 00 24 00

.00 2160.00

.00 2140.00

.00 2140.00 50.00 00.00 6.00 4.00 50.00 30.00 bg 0F ANIMALS DAILY FEED (KG/ DAY)

.00

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Page B.4-8 F101-EC3 i

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CHILD 0 METERS

' DOSES RECElvCD FROM FLD SECTOR AT A DISTANCE OF VARIOUS FATHWAYS (MREM)

FATHWAY DONE '

LIVER KIDNEY LUNG GI-LLI TNTROID

'WHOLE PODY SEIN COW MILE 54 MN

.00E+00 1.69E-06 4.74E-07

.00E400 1.4:E-06

.00E+00 4.00E-07 40 CO

.00E+00 9.78E-05

.00E+00

.00E400 5.4:E-04.

.00E+00 2 89E-04 '

45 2N 4.4TE-03 1.20E-02 7.04E-03

.00E+00 2 10E-03

.00E+00 7 44E-03 134 CS 3 33E-04 5.47E-04 1.etE-04 4.08E-05 2.95E-06

.00E400 1 10E-04 137 CS 3.08E-02 2 95E-02 9.61E-03 3 44E-03 1 80E-04

.00E600 4.30E-03 r

TOTAL FOR FATHWAY 3.34E-02 4 21E-02 1 73E-02 3.3:E-03; 2 83C-03

.00E+00 1 2 E*02 NEAT 54 MN

.'00E+00 6.46E-07 1 81E-07

.00E400 3 4:E-07

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.00E+00

.00E600 8.70E-04

.00E400 4 43E-04 e5 2N 4.08E-04 1 0tE-03 4.84E-04

.00E400 1.91E-04

.00E+00 6.7eE-04 134 CS 1 3eE-05 2 23E-05 6.90E-04 2 48E-06 1 20E-07

.EJE400 4.70E-06 i

137 CS 1 27E-03 1.::E-03 3.97E-04 1.43E-04 7.64E-04

.00E+00 1 80E-04 TOTAL FDR FATHWAY 1 70E-03 2 4?E-03 1.0TE-03 1 45E-04 1 07E-03

.00E+00 1.3 E-03 TOTAL ALL FATHS 2 33E-01 2.43E-01 8.54E-02 2.23E400 5 44E-02

.00E+00 1 23E+00 1 37E+00 TOTAL ALL FATHS

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ENTECH ENGINEERING, INC.

P101-EC3 Page B.4-11

2 B.5 ATMODOS - Unplowed-Land Dose Conversion Factors for Radiological Impact Assessment The Tape 5 inputs to ATHODOS for these cases are identical to the i

one shown in Attachment B.3, the only exception being the isotopic 4

I intensities in File 2.

In the current computer runs, each isotope was i

i assumed to have an annual release rate which would yield an a'ccumulated intensity of 1 pCi at the end of one year (uniformly spread over 2 acres of unplowed land).

5 l

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1 ENTECH ENGINEERING, INC.

t P101-EC3 Page B.5-1

m

.m.

fT 07 PROGRAM ATMODCS D

YANKEE ATOMIC ELECTRIC COMPANY DEC. 1985 REV. ?

SECTOR FLD REOULATORY GUIDE 1 109e AFFENDIN C a

O IMETERSD DISTANCE MODELS FOR CALCULATING DOSE VIA 4.63E-04 tSEC/M-33 X/O

=

ADDITIONAL PATHWAYS FROM RADIDIDDINES 4.63E-04 ISEC/M-3)

X/O DEFLETED

=

AND OTHER RADIONUCLIDES DISCNARGED 1.24E-04 41/M-2)

DELTA

=

TO THE ATMOSPNERE NOVe1977 LIPRARY 3

VY - SEWACE CONTAM - ASSUMED SRC - 2 ACR O

ES - SMIELD F = 0.012 - 104 MR CCCUP.

c*

6 PATHWAYS CONSIDERED Om THE FOLLOWINO 1 NUCLIDES WERE USED IN THIS CALCULATION C

GROUND PLANE YES O

NUCLIDE RELEASE INNALATION YES E'

CURIES STORED wtOETAptES YES O

25 MN 34 1 46E-06 LEAFY VEGETABLES YES COW MILK YES w

GOAT MILK NO MEAT YES cO O

9

• C 3

CU 6

VECETABLES COW MILM 00AT MILK MEAT UARIAPLE STORED LEAFY PASTURE STORED PASTURE STORED PASTORE STORED YV AGRICULTURAL PRODUCTIVITY (KO/M-2) 2 00 2.00

.70 2 00

.70 2 00

.70 2.00 P

S01t SURFACE DENSITY (K0/M-23 240 00 240.00 240.00 240.00 240.00 240.00 240.00 240.00 T

TRANSPORT TIME TO USER (HRSS 48.00 48.00 48.00 48.00 480.00 480.00 i

79 SOIL EXPOSURE TIME (HRS) 8766.00 8766.00 8766.00 8766.00 8766 00 8766.00 8764.00 8766.00 bg TE CROP EXPOSURE TIME TO PLUME (HRS)

.00

.00

.00

.00

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.00 2160.00

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.50

.50

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'* l I U)

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FI FRACTION ELEMENTAL 10 DINE =

.500

~ 0 DQ H

APSOLUTE HUMIDITY a 3.60 (GM/M-3) 1.000 UC PC FRACTIONAL EQUILISRIUM RATIO FOR C-14

=

1 C) sessssssssstatsse tt essa ssessass as ss stse sstess aast sste n s s t a s s a s s t a t s s a t s s t a a t s t a s s e DOSE DELIVERED TO EACH CRGAN I

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(K0/YR) (K0/YR) (LI/YR) EK0/YR)

(M-3/YR)

(MREMI 1

ADULT 520.00 64.00 310.00 110 00 8000.00 s 7.54E-05 1.12E-04 8 63E-05 1 05E-04 1 87C-04 7.54E-05 8.24E-05 8.84E-05 :

O TEEN 630.00 42.00 400.00 65 00 0000.00

• 7.54E-05 1 29E-04 9.15E-05 1.18E-04 1.85E-04 7.54E-05 8.61E-05 8.84E-05 e ts C)

CHILD 520.00 26.00 330.00 41 00 3700.00 e 7.54E-05 1 54E-04 9.74E-05 1.09E-04 1.41E-04 7.54E-05 9.63E-05 8.84E-05 INFANT

.00

.00 330.00

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I

7

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_c PROGRAM ATMODOS gg YANKEE ATOMIC ELECTRIC COMPANT DECe 1983 *EV.

7 (n

SECTOR FLD REGUL ATORY GUIDE 1.109. APFENDIX C

=

0 (METERS)

DJ DISTANCE MODELS FOR CALCULATINS DOSE VIA X/0

• 4.63E-04 (SEC/M*3)

ADDITIONAL FATHWATS FROM RADIC10 DINES N/0 DEFLETED = 4 43E-04 (SEC/M-3)

AND OTHER RAD 10NUCLIDES DISCMARGED bd 1 24E-04 (1/M-2)

DELTA TO THE ATMOSPMERE NOV.1977 LIPRARY B

U VY - SEWA0E CONTAM - ASSUMED SOURCE - 2 ACRES - SMIELD F = 0 012 - 104 MR OCCUP 4 FATHWAYS CONSIDERED THE FOLLOWING 1 NUCLIDES WERE USED IN THIS CALCULATION GROUND FLANE TES NUCLIDE RELEASE INHALATION YES g

CURIES STORED VEGETAptES YES 27 CD 40 1.07E-06 LEAFY VEGETAsLES TES r*

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l O

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.70 2.00

.70 2 00

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SOIL SURFACE DENSITY (MG/M-2) 240.00 240.00 240.00 240 00 240.00 240.00 240.00 240.00 t

TRANSPORT TIME TO USER (HRS) 48.00 48.00 48.00 48 00 480.00 480.00 TD S0IL EXPOSURE TIME (HRS) 8766 00 8746.00 8766.00 8766.00 8744.00 8766 00 8766.00 8766.00 TE CROP EXPOSURE TIME TO PLUME (HRS)

.00

.00

.00

.00

.00

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1 ()

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.500 C)

H ASSOLUTE MuniDITY =

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USAGE FACTORS a

3 9

s FROM ALL FATHWAYS COM91NED a

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• AGE VES e

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f00 00 (K0/YR) (K0/TR) (Lf/YR) (KS/TR)

(M-3/YR)

(MREM) yg 30 ADULT 520.00 44.00 310.00 110 00 8000.00 e 2 21E-04 2 28E-04 2.21E-04 3.14E-04 3.54E-04 2 21E-04 2.34E-04 2.40E-04 s b1 TEEN 430.00 42 00 400.00 43.00 8000.00 s 2 21E-04 2 31E-04 2 21E-04 3.37E-04 3.03C-04 2 21E-04 2 43E-04 2 40E-04 :

g It CMILD 520.00 24 00 330.00 41 00 3700 00

• 2 21E-04 2 2&E-04 2 21E-04 3.32E-04 3.04E-04 2 21E-04 2.45E-04 2 40E-04 s 03 C)

$NFANT

.00

.00 330.00

.00 1400 00 s 2 21E-04 2 22E-04 2 21E-04 2.92E-04 2 24E-04 2 21E-04 2 23E-04 2 40E-04 s a

sassasssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssses

• =

(h 3i DC we C)

n

%d CS PROGRAM ATMODOS TANKEE ATOMIC ELECTRIC COMPANY DECs 1985 REV. 7 g4 SECTOR FLD REGULATORY OUIDE 1.109, APPENDIX C O

(METERS)

DISTANCE MODELS FOR CALCULATING DOSE VIA 4.43E-04 tSEC/M-3) w.

X/O

=

ADDITIONAL PATHueTS FROM RADIO 10 DINES 4 43E-04 (SEC/M-33 g

E/0 DEPLETED

=

AND OTHER RADIONUCLIDES DISCHARDED 1.24E-04 (1/M-2) c DELTA

=

TO THE ATMOSPHERE NOV.1977 LIPRARY VY - SEWA0E CONTAM - ASSUMED SOURCE - 2 O

ACRES - SHIELD F = 0.012 - 104 MR OCCUP r*

CL 4 PATHWAYS CONSIDERED THE FOLLOWING 1 NUCLIDES WERE USED IN TMIS CALCULATION C

S GROUND PLANE TES NUCLIDE RELEASE INHALATION TES hf CURIES STORED VEGETA9LES YES 30 2N 43 1.41E-04 LEAFY VEDETAPLES YES COW MILK YES 00AT HILK NO MEAT TES c

O O

~*>

N 3

t f

VEDETABLES COW HILK 0047 MILK MEAT VARIABLE STORED LEAFY FASTURE

• TORED PASTURt STORED PASTURE STORED YV AGRICULTURAL PRODUCTIVITY (K0/M-23 2 00 2.00

.70 2.00

.70 0 00

.70 2 00 P

SOIL SURFACE DENSITY (K0/M-2) 240.00 240.00 240.00 240.00 240 00 240 00 240.00 240.00 T

TRANSFORT TIME TO USER (HRS) 48 00 48.00 48.00 48.00 480.00 480.00 79 SOIL EKFOSURE TIME (HRS) 8766 00 8764.00 8746 00 8746.00 8764 00 8744.00 8766.00 8764.00 bg TE CROP EXPOSURE TIME TO PLUME CHRS)

.00

.00

.00

.00

.00

.00

.00

.00 13 Og TH HOLDUP AFTER HARVEST (HRS) 1440.00 24.00

.00 2140.00

.00 2140.00

.00 2240.00 b*

0F ANIMALS DAILY FEED (K0/ DAY) 50 00 00.00 4 00 e.00 30.00

$0.00 CD FP FRACTION OF YEAR ON PASTURE

.50

.50

.50 mg FS FRACTION PASTURE WHEN ON PASTURE 1 00 1 00 1 00 I

FG FRACTION OF STORED VES GROWN IN GARDEN 1 00 I

O FL FRACTION OF LEAFY VES GROWN IN GARDEN 1.00

(

FI FRACTION ELEMENTAL 10 DINE *

.300 O U1 M

ASSOLUTE HUMIDITY = 5 40 (GM/M-3) 1 000 IC PC FRACTIONAL EQUILIBRIUM RATIO FOR C-14 e t C1

$ttetttttstettettatattetetteettettaatttttattletetstestStatttttstttttttattttttttlet kg DOSE DELIVERED TO EACM ORGAN 3

at USAGE FACTORS FROM ALL PATHWAYS COMBINED e

93 bg t

VE0 LEAFY MILK MEAT INHALATION t b

bg D4 gg AGE VES DONE LIVER KIDNEY LUNG 01-LLI THYROID WHOLE PODY SKIN 0

(K0/YR) (K0/YR) (LI/YR3 (K0/ YRS (M-3/YR)

(MREM)

ADULT U20.00 44 00 310.00 110.00 8000.00

• 1.2 E-03 3.78E-03 2 00E-03 7.24E-05 2 40E-03 S.20E-03 1.74E-03 5 98E-00 t Sq TEEN 430.00 42 00 400.00 63 00 8000.00 2 1.e:E-03 0 09E-03 3.40E-03 8.1:E-03 2 40E-03 5.20E-03 2.44E-03 5.99E-00 E

D3 I CHILD 520.00 24.00 330.00 41 00 3700.00 e 3.11E-03 8 21E-03 5.19E-03 7.03E-03 1.48E-03 S.20E-03 5.1:E-03 3 9eE-0: a n'

INFANT

.00

.00 330.00

.00 1400.00 e 2 21E-03 7.44E-03 3.43E-03 6.7:E-03 6.29E-03 3.20E-05 3 44E-03.5 9sE-03 2 3

t i

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FROGRAM ATMODOS gn YANK 0 ATOMIC ELECTRIC ConrauY DEC. 1980 REV. ?

26 f

REGULATORY GUIDC 1.107e AFFENDIX C SECTOR-rLD MODELS FOR CALCULA11NG DOSE VIA DISTANCE 0

(HETERS)

ADDITIONAL FATHWAYS FROM LADIO10 DINES

%/3

. 4.40E-04 (SEC/M-36 1-4 AND OTHER RADIONUCLIDE3 DISCHARGED

/0 DEFLFTFD - 4.4*E-04 (SEC/H-33 3

TO THE ATHOSFMERE NOV.19Y7 LIBRARY DEL 1A

- 1.24E-04 (1/M-2)

O 3

VY - 0FWAGE CCHTAM - ASSUMED 0005-CE. :

O ACRE: -. 3MIELD F - 0.01

- 104 HR UCCUF C'

l THE FOLLOWING 1 NUCLIDES WERE USED IN 1 MIS CALCULATION 4 FATHWAYS CONSIDERED GROUND FLANE YES NUCLIFE RELEASE INMALATIDH YES c,

CURIES TDAED VFGETABLEO YES o

CS 134 1.19E-06 LEAFY VFGCTA$LES YES COW MILK YE3 GOAT MILK NO NEAT YES C

.O O

Om he VARIAPLE VEGETABLES COW MILK GOAT MILK MEAT c3 OTORED LE AF Y FASTURE STORED FA31UEL 3TORED FASTURE STORED 45 YV AGRICULTURAL FRODJCTIVITY (KG/M-2) 2 00 2 00

.70 2 00

.70 0 00

.70 2.00 F

SOIL SURFACE DENSITY (KG/M-0) 240.00 240.00 240.00 240.00 240 00 240.00 240.00 740.00 T

TRANSFORT TIME TO USER (HRS) 48.00 48.00 48.00 48.00 490.00 480.00 TB SOIL EXFOSURE TIME (HRS) 8744.00 07&&.00 0746 00 37A4 00 8764.00 6766.00 B766.00 3746.00 DQ TE CROF EXFOSURE TIME TO FLUME (HRS)

.00

.00

.00

.00

.00

.00

.00

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.00 2160.00

.00 2140.00

.00 2160.00

{UC Or ANIMALS DAILY FEED (nd/ DAY) 50.00 30 00 4 00 6 00 50.00 50.00 FF FRACTION OF YEAR ON FASTURE

.50

.50

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FI rRACTION ELEMENTAL ICDINE =

.500 to N N

ABSOLUTE HUMIDITY =

5.60 (GM/M-3)

E FC FRACTIONAL EQUILIBRIUM RATIO FOR C-14 = 1.000 g C) toaststartsstatstattttttttttttt satttttt tttsstatst aattt atttttttttrattstatstett et st e b1 EC USAGE FACTORS DOSE DELIVERED TO EACM ORGAN 13 by 8

FROM ALL PATHWAYS Cons!NED e

t D

b5 VEG LEAFY MILK MEAT INHALATIDM t 30 ADE VEG e

PONE LIVER KIDNEY LUNG GI-LLI THYROID WHOLE PODY SKIN 71 0

(KG/YR) (Ko/YR) (LI/YR) (KG/YR)

(M-3/YR)

(MREM) hq ADULT 500.00 44.00 310.00 110.00 8000.00 t 4.04E-04 7.46E-04 3.47E-04 2.19E-04 1.4&E-04

1. Set-04 4.3?E-04 1.8:E-04 a

g TEEN 630.00 40.00 400.00 45.00 8000.00

• 5 44E-04 1 07E-03 4.46E-04 2.67E-04 1.47E-04 1.36E-04 3 7?E-04 1 8 t-04

• CHILD 5 0.00 26.00 330 00 41.00 3700.00 8 1 03C-03 1.59E-03 6.00E-04 3.15E-04 1 44E-04 1.04E-04 4.08E-04 1.t:E-04

• gn q)

(g INFANT

.00

.00 330.00

.00 1400.00 8 5 31E-04 8.53E-04 3.34E-04 2.30E-04 1.58E-04 1.36E-04 2 26E-04 1 8:E-04 a setttttttttttttttttttttttttttttttttttttttttttttttttstattttttttttstreetstastatistas b1 43 l SE

w. C)

O

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FR00 RAM ATMODOS CM YANKEE ATOMIC ELECTRIC COMPANY DECe 1985 REV. 7 CD SECTOR FLD e

0 (METERS)

REGULATORY CUIDE 1 109, APPENDIX C DISTANCE MODELS FOR CALCutATING DOSE VI A X/O

= 4 63E-04 (SEC/M-3)

= 4.43E-04 (SEC/M-3) g ADDITIONAL PATHWAYS FROM RADIOf0 DINES X/0 DEPLETED 1.24E-04 (1/M-23 g

AND OTHER RADIONUCLIDES DISCHARDED DELTA

=

TO THE ATMOSPHERE MOV.1977 LIPRARY 3

VY - SEWADE CCNTAM - ASSUMED SOURCE - 2 o.

0 012 - 104 HR OCCUP c

ACRES - SHIELD F

& FATHWAYS CONSIDERED CL C

THE FOLLOWING 1 HUCLIDES WERE USED IN THIS CALCULATION GROUND PLANE TES Q

INHALATION YES NUCLIDE RELEASE STORED VEDETAptES YES r*

LEAFY VEDETABLES YES O

CURIES 55 CS 137 1 01E-06 COW MILK YES 00AT MILK NO MEAT YES g

Q w

O

==>

Om VE0ETABLES COW MILK 00AT MILK MEAT CJ STORED LEAFY FASTURE STORED FASTURE STORED PASTURE STORED VARIABLE

-4 TV AOR! CULTURAL PRODUCTIVITY (K0/M-2) 2.00 2.00 70 2.00

.70 2 00

.70 2 00 P

SOIL SURFACE DENSITY (K0/M-23 240 00 240.00 240.00 240.00 240 00 240 00 240.00 240.00 48.00 48.00 48 00 48.00 480.00 480.00 (HRS) 8766 00 8744.00 8766.00 8766.00 8766 00 8766 00 8744.00 8766.00 (HRS)

T TRANSPORT TIME TO USER TE CROP EXPOSURE TIME TO FLUME (HRS)

.00

.00 00

.00

.00

.00

.00

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TH HOLDUP AFTER HARVEST (HRS) 1440 00 24 00

.00 2140 00

.00 2160.00

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.50

.50

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1 00 1.00 1.00 3

FF FRACTION CF YEAR ON PASTURE C3 "DQ PASTURE WHEN ON PASTURE h.

FS FRACTION i

1 C)

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FI FRACTION ELEMENTAL 10 DINE =

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H ABSOLUTE HUMIDITY a

le q

1.000 3g PC FRACTIONAL EQUILIBRIUM RATIO FOR C-14

=

assssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssssse s

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DOSE DELIVERED TO EACH ORGAN s

USAGE FACTORS s

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E I

VES LEAFY MILK MEAT INHALATION e s

PONE LIVER KIDNEY LUNG 01-LLI TNTROID WHOLE BODY SKIN l

fDU s

1 i

71 AGE VE0 (MREM)

ADULT 520.00 44.00 310.00 110.00 8000.00 s 3.8eE-04 5.07E-04 2 09E-04 1.04E-04 6.33E-05 5.46E-05 3.52E-04 4.37E-05 s 3

(K0/YR) (K0/YR) (L1/YR) (KD/YR)

(M-3/YR) 3C TEEN 630.00 42.00 400.00 65 00 8000.00 t 5 97E-04 7.75E-04 3.00E-04 1 50E-04 4.48E-05 5.44E-05 3.06C-04 6.37E-05 I

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.00

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• :st-04 2 90t-04 2.:4t-04 2 21t-04 2.23t-04 2.40C-44 FLD 0 CHILD COW Mtaf

2. lt-04 2 34t-04 2.:tt-04 3.3 t-04 3 04t-04 2.Itt-04 2.43t-04 2 40t-04 j

FLD 0 Yttu COW Mtat 2 21t-04 2.3tt=04 2.:tt-04 3 37t-04 3.33t-04 2.;tt-04 2.43t-04 2.aot-04 FLD 0 ADULY COW stat 2.

st-04 2.;pt-04

. st-04 3 34t*04 3 34t-04 2 25E-04 2.36t=04 2 40t-04 FLD 0 turaNT CCW mtet 3.3tt-04 e.tSt-04 3 34t-04 2 30t-04 1 3st=04 3 3at-04

.24t=04 1 8 t=04 FLD e CMILD COW ptat 1 03t-03 3.39t-03 4.00t-04 3.13t-04 1 44t-04 1 36t-04 4.$tt-04 1 80t-04 FLD 0 TCEN COW Mtaf S.44t-04 1 07t=03 4.46E-04

.67t-04 3 6 t-04 1 34t-04 S.79t-04 3.s:t=04 FLD 0 ADutt COW Mtaf 4.04t-04 7.44t=04 3.47t-04

.tet-04 1 46t-04 1 34t-04 a.34t-04 t.e:t-04 FLD 0 INFa47 COW mtaf 7.34t-03 7 7tt-03 7 38C-03 9.48t-03 7.60t-03

7. Sat-03 7.3st-03

8. tat-05 FLD 0 CHILD COW Mtaf 7 34t-ch 1 34t-04 9.74t-03 1 49t-04 1 41E-04 7.34t-03 9.631-03 8.04E-03 FLD

• tttu COW mtaf 7.34t-03 1 29t-04 9 13t 3 39t-04 1 0 t-04 7.34t-03 9.41t-03

e. set-05 FLD 0 ADULT COW Ptaf 7 34t-03 3.t*t-04, <9.43E-03 1 0$t-04' t.87t-04 7 34t-03 S.24t-05 S.get=05 j

Fo r 0 7ttu COW Meat 3 97t-04 7.73t-04 3 00E-04 3 30t-04 e.45t-05 3 44t-03 3.04t-04 4.37t-0S l

FLD 0 ADULT COW ataf 3.86t-04 3.07E-04 0.09t-04 1 04t-04 6.33E-05 3 44t-03 3.30t-04 6.37t=03 i

FLD 0 INFamT COW Mtaf 3.94t=04 4 84t-04 2.':4t-04 1 23t=04 3 44t-03 3.ast-03 9.94t-03 4.37t=03 j

F(9 0 CHILD COW mea 7 8 33E-03 1.:et-03 4 33E-04 3 9st=04 4 23t-03 3.44t-05 2.3 t-04 6.37t-03 FLD 0 INFANT COW Pta?

2.*3E-03 7 44t-03 3.63t-03 6 7 t-03 4.:9t-03 3 00t-03 3.46t-03 3 99t=0S FLD 0 CMILD COW MEnf 3.stt-03 s.;st-03 3.39t-03 7.331-03 3.egt=03 3.20t-03 3.t:(-03 3.99t-05 FLD 0 tttN COW mtat 3 43t-03 3.39t-03 3 60t-03 8.lat-05 2.40t-03 3.20t-03 2.44L-03 3.tet-03 g

FLD 0 ADULT COW Ptat 1.::t-03 3.7tt-03 0.33t-03 7.;4t-05 2.40E-03 3.20t-03 1.74t-03 Coest-OS i

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METERS CROUF FLD 0 CMILD C0u Mtaf 0.281-03 Ltvtt FLD 0 CMILD C0u Mtat 8.0tt-03 LivtR l

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0.:st-03 LtWit FLD 0 twFaNT C0u Mtaf 7,aat-03 Ltytt l

FLD 0 INFauf Con Mtaf

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l FLD 0 thFaNT C0u plaf 7.aat-e3 LivtR FLD 0 INFANT C0u Mtaf 4.!Tt=03 01-LLI j

6 FLD 0 INFANT C0u Mtat a.29E-03 OI-LLI FLD 0 tM8 ANT C0u Mtaf

6. TE-03 Ot-LLt FLD 0 T[Em C0u staf 5.STE-03 +Livtt FLD 0 YttM C0u Mtaf S.:Tt-03 LivtR FLD 0 fttM Cow Mta?

.37E-03 Livtt FLD 0 CMILD Cow Mtat-S.1TE-03 EtDat?

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FLD 0 CMILD C0u MEnf S.2t-03 uwp007 FLD o CHILD C0u Mtaf S.stt-03 unP0DY FLD 0 CMILD C0u MEAT 3.12E-03 wupCDT FLD e ADULT C0u Mtaf 3 70t-03 L!vtR FLD e ADULT Cow Mtaf 3.70t-03 Ltvtt rtD 0 ADULT C0u Mtaf 3.70t-03 Ltwtt FLD 0 INFANT Cou Mtaf 3 43t-03 KtDurt FLB 0 INFANT COu Mtaf 3 43t-03 RtDNt?

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FLD 0 fttN CCu Mtaf 3.40E-03 RIDNET FLD 0 TttN C0u Mtaf 3.60E-03 RfDNET FLD e TEEN CDs Mtaf 3.40E-03 KIDut?

D1 FLD 0 INFANT C0u Mtaf 3.aet-03 WMPODY 93 3R FLD 0 INFANT C0u Mtaf 3.agt=03 uneCDT

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