Text

Request for Approval of Proposed Procedures in Accordance with 10 CFR 20.2002
	ML042800489
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/16/2004
From:	Bouchard G; Connecticut Yankee Atomic Power Co
To:	; Document Control Desk, NRC/FSME
References
	-RFPFR, CY-04-168, FOIA/PA-2005-0203
	Download: ML042800489 (119)
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD

EAST HAMPN, CTOA24-3099 SEP ('J6CD204-3 CY-04-168 Docket No. 50-213 RE: 10 CFR 20.2002 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D C 20555 Haddam Neck Plant Request for Approval of Proposed Procedures in accordance with 10 CFR 20.2002 Connecticut Yankee Atomic Power Company (CYAPCO) proposes to transfer certain of its solid waste from decommissioning of the Haddam Neck Plant (HNP) facilities (e.g., structures and buildings) to a disposal facility. Specifically, CYAPCO proposes to dispose of demolition debris from decommissioning of the HNP facilities to the US Ecology Idaho Facility, located in Grand View, Idaho.

The purpose of this letter is to request NRC approval of proposed procedures for disposal of certain demolition debris in accordance with the provisions of 10 CFR 20.2002.

A description of the waste material for disposal that potentially contains licensed material is provided in Attachment 1. This description includes the physical and chemical properties important to risk evaluation and the proposed manner and conditions of waste disposal. In addition, CYAPCO has performed a conservative radiological assessment of the demolition debris material and determined that the potential dose to workers involved in the transportation and placement of the waste at the site and to members of the public after closure of the facility as a consequence of the proposed waste disposal will be no more than a few millirem per year Total Effective Dose Equivalent (TEDE) and a small fraction of NRC limits for exposure to members of the public of 25 millirem/yr TEDE.

CYAPCO hereby requests expedited review and approval of this request by December 24, 2004 to support our decommissioning activities at the HNP.

There are no regulatory commitments contained in this letter.

Document Control Desk CY-04-168 / Page 2 If you should have any questions regarding this submittal, please contact Mr. G.

P. van Noordennen at (860)-267-3938.

Sincerely,

-,X Wt ,,,i- _G __4 G. . Bochard Date Director Nuclear Safety/Regulatory Affairs Attachments: Haddam Neck Plant, Evaluation in Support of Alternate Waste Disposal Procedures in Accordance with 10 CFR 20.2002 Microshield Calculations Resident/Farmer Dose Assessment cc: S. J. Collins, NRC Region 1 Administrator T. B. Smith, NRC Project Manager, Haddam Neck Plant R. R. Bellamy, Chief, Decommissioning and Laboratory Branch, NRC Regioni E. L. Wilds, Jr., Director, CT DEP Monitoring and Radiation Division

Docket No. 50-213 CY-04-1 68 Attachment 1 Haddam Neck Plant Evaluation in Support of Alternate Waste Disposal Procedures In Accordance with 10 CFR 20.2002 September 2004

CY-04-1 68 / Page 1 Haddam Neck Plant Evaluation in Support of Alternate Waste Disposal Procedures In accordance with 10 CFR 20.2002

1. INTRODUCTION Approval of the proposed disposal procedures in accordance with the provisions of 10 CFR 20.2002 would allow Connecticut Yankee Atomic Power Company (CYAPCO) to dispose of demolition debris from the Haddam Neck Plant (HNP) decommissioning activities at the US Ecology Idaho Facility in Grand View, Idaho. This attachment provides a conservative assessment of the radiological impacts of the proposed disposal. The following Sections describe disposal site characteristics, the waste material, the radiological assessment and conclusions. The main conclusion is that the potential dose to workers involved in the transportation and placement of the waste at the site and to members of the public after closure of the facility as a consequence of the proposed waste disposal will be no more than a few millirem per year Total Effective Dose Equivalent (TEDE) and a small fraction of NRC limits for exposure to members of the public of 25 millirem/yr TEDE.

2. DISPOSAL SITE CHARACTERISTICS This section describes the features of the disposal facility of importance in radiological assessment. It describes in turn the geographical and physical environment of the facility, the engineered features, the permits under which the site operates, radioactive material disposal limits, site operations, radiation monitoring, and post-closure plans. A complete description of the site is provided in documents submitted to the State of Idaho in support of permit applications (Envirosafe 1998, Ref. 6.1; Envirosafe, 2000, Ref 6.2; CH2M Hill, 1993, Ref 6.3). A description of the key features in detail sufficient to support radiological analysis is provided herein.

2.1 ENVIRONMENT AND FACILITY DESIGN The US Ecology Idaho site is located near Grand View, Idaho in the Owyhee Desert. Grand View is approximately 40 miles south-southeast of Boise, Idaho. The disposal site is located at 10.5 miles NW on Highway 78, Lemley Road, Grand View, Idaho, 83624.

CY-04-1 68 / Page 2 The most significant natural site features that appear to limit the transport of radioactive material are the low precipitation rate and the long vertical distance to groundwater. The precipitation rate in this arid location is 0.184 meters per year (Envirosafe, 2000, Ref 6.2).

The depth to groundwater accommodates a 3.6-meter thick cover, a 33.6-meter thick disposal zone, and a 61-meter thick unsaturated zone between the base of the disposal cell and groundwater (Envirosafe, 2000, Ref 6.2; CH2M Hill, 1993, Ref 6.3).

A number of engineered features designed to enhance confinement performance have been incorporated in the facility. The most important from the standpoint of radioactive material confinement is the 3.6-meter thick, low permeability, erosion resistant cover to be constructed at cell closure. This final cover is to be constructed of compacted soil in conjunction with a 40-mil HDPE liner. The HDPE cover liner is to be integrated with a similar liner along the sides and bottom of the cell. The confinement effectiveness of the HDPE liner is ignored in this analysis to assure that projections of potential radiation dose are conservatively maximal.

Together, the low precipitation rate, the thick, low-permeability cover, and the thick unsaturated zone minimize the potential for long term infiltration, dissolution, and transport of constituents to groundwater.

The thick cover also minimizes the potential for exposure of waste material radionuclides by erosion or intrusion and minimizes release of radon gas to the atmosphere (although the dose due to the release of radon is shown to be insignificant in these analyses).

Other facility design features and operating procedures provide shorter term confinement of radioactive materials and limit the potential for radiation exposure during receipt of material and emplacement of materials in the cell. These include a closed facility with filtered ventilation exhaust for transfer of incoming waste material from the shipping conveyance to US Ecology Idaho waste transfer vehicles, mechanized equipment for disposition of waste material in the cell, and the application of an asphaltic spray (to control resuspension of the material into the air) over newly deposited material at the end of each day's operations.

The total capacity of the cell which would receive the HNP waste is approximately two million cubic yards (1.5 million cubic meters). The surface area of the cell is approximately 88,000 square meters. The material that CYAPCO proposes for disposal if occupying the full depth of this cell would have a surface area of approximately 900 square meters. This means that the HNP material would occupy approximately 1 % of the total volume of this disposal cell.

CY-04-168 / Page 3 2.2 PERMITS The US Ecology Idaho site is a Subtitle C RCRA hazardous waste disposal facility permitted under the authority of the Idaho Hazardous Waste Management Act, Chapter 44, Title 39, of the Idaho Code.

The site operates under permit IDD073 114654. A Class I Permit Modification was approved in 1999, and a Class II Permit Modification was approved in 2001. The latter permit modification also accommodates recent changes to Idaho law and regulations regarding the disposal of radioactive material, as described below. In accordance with its regulations and permit conditions, the site has been receiving certain radioactive materials exempt from Nuclear Regulatory Commission licensing requirements, including U.S.

Army Corps of Engineers formerly Utilized Sites Remedial Action Program materials, for a number of years.

Disposal of radioactive materials at the US Ecology Idaho site is regulated under the Rules of the Department of Environmental Quality, IDAPA 58.01.10, "Rules Regulating the Disposal of Radioactive Materials Not Regulated Under the Atomic Energy Act of 1954, As Amended." These regulations establish radiation protection standards and permit conditions for disposal of these materials at a permitted disposal facility under the authority of the Idaho Hazardous Waste Management Act, Chapter 44, Title 39, Idaho Code.

Under the Idaho Department of Environmental Quality general protection standards, all owners and operators disposing of radioactive materials are required to conduct operations in a manner consistent with radiation protection standards contained in 10 CFR Part 20. In addition, no owner or operator may operate in a manner such that any member of the public would receive an annual TEDE in excess of 100 millirem per year. In addition, no person may release radioactive material for unrestricted use in such a manner that the reasonable maximally exposed individual would receive an annual TEDE greater than 15 millirem per year, excluding natural background.

The facility owner or operator is also required to comply with each of the following permit conditions:

Department-approved waste acceptance criteria for radioactive material;

A Department-approved closure program that provides reasonable assurance that the radon emanation rate from the

CY-04-1 68 / Page 4 closed disposal unit will not exceed twenty (20) picocuries per square meter per second averaged across the entire area of the closed disposal unit and meets the general radiation protection standard for the public (TEDE of 15 millirem per year); and A Department-approved environmental monitoring program that monitors air, ground water, surface water and soil for radionuclides and ambient radiation levels in the environs of the facility, and which demonstrates that no member of the general public is likely to exceed a radiation dose of 100 millirem per year from operations conducted at the site.

As previously mentioned, the analysis to follow will show that the HNP material proposed for disposal at the US Ecology facility will result in doses that are a small fraction of the applicable limits.

2.3 OPERATIONS US Ecology Idaho accepts only wastes that conform to waste acceptance criteria approved by the Idaho Department of Environmental Quality, as required in IDAPA 58.01.10. This is implemented in the form of a two-step pre-acceptance protocol. In the first step, the generator prepares a chemical and physical characterization of the waste stream on a US Ecology Idaho standard form. The second step is an evaluation performed by US Ecology Idaho to determine the acceptability of the waste. No waste is shipped until the waste is determined to be acceptable by US Ecology Idaho.

Waste acceptance criteria applicable to the material intended for disposal are as follows:

1. Acceptable Dose Rate at receipt to insure that the yearly dose criteria stated in the following paragraph are maintained.

2. The sum of the concentrations of all radionuclides present in the waste does not exceed 2000 pCi/g.

US Ecology Idaho is required by condition of its Department of Environmental Quality permit to operate in a way that assures that the highest potential dose to a worker handling radioactive material is 400 millirem TEDE per year, and that assures that the highest potential dose to a member of the public is 100 millirem TEDE per year from operations or 15 millirem TEDE per year from release of radioactive materials for unrestricted use.

CY-04-1 68 / Page 5 To meet these requirements, US Ecology Idaho conducts its operations in accordance with its Radioactive Material Health and Safety Manual and other operating procedures. These procedures include measures for minimizing release of material in receipt and handling. Transfers of as-received materials from shipping conveyances to US Ecology Idaho vehicles are performed in a closed structure with bag-filtered ventilation exhaust. Workers use mechanized equipment to transfer and deposit material in the disposal cell. Materials placed in the cell are covered each day with asphaltic spray to minimize the potential for release of radioactive materials to the atmosphere.

To assist in demonstrating compliance with these requirements, US Ecology Idaho also operates a radiation monitoring program approved by the Idaho Department of Environmental Quality, as required in IDAPA 58.01.10. The program includes:

Periodic collection of grab air samples with analysis for radon progeny,

Periodic deployment and collection and analysis of passive track-etch detectors with analysis for radon concentration, and

Periodic deployment and collection of passive dosimeters at locations around the perimeter of the cell with analysis for direct radiation exposure The following samples are analyzed for Isotopic uranium and thorium, Ra-226 and Gross Alpha and Gross Beta radioactivity (The US Ecology Idaho site will soon be receiving materials from NRC Part 50 licensees. Prior to allowing shipment of any of this additional material, analyses of the following samples for gamma radionuclides will also be instituted):

Periodic collection of grab air samples during material transfer operations,

Periodic collection of continuous air samples from the admin/lab area,

Periodic collection of soil samples from locations downwind of the disposal area, and

Periodic collection of groundwater samples from two monitoring wells with analysis for gross activity.

2.4 POST-CLOSURE PLAN As required by the Idaho Department of Environmental Quality in IDAPA 58.01.10, US Ecology Idaho maintains an approved closure plan, submitted as part of its permit application (Envirosafe, 1998,

CY-04-1 68 / Page 6 Ref 6.1). The plan conforms to all standard closure and post-closure requirements applicable to RCRA disposal facilities, including post-closure monitoring and financial assurance.

The plan provides reasonable assurance that the radon emanation rate from the closed disposal unit will not exceed twenty (20) picocuries per square meter per second averaged across the entire area of the closed disposal unit and reasonable assurance that the general radiation protection standard for the public (TEDE of 15 millirem per year) will not be exceeded. It should be noted that this standard for post closure exposure to a member of the public is set below the NRC standard for unconditional release of an NRC licensed facility which is 25 millirem per year TEDE.

3. DESCRIPTION OF WASTE 3.1 Physical Properties The waste material (the demolition debris) intended for disposal includes flooring materials, concrete, rebar, roofing materials, structural steel, soils associated with digging up foundations, and concrete and/or pavement or other similar solid materials. Soils remediated for the purpose of meeting the final status survey requirements of the HNP License Termination Plan (LTP) (i.e.,

exceed the Derived Concentration Guideline Levels (DCGL) in the LTP) will not be disposed of at the US Ecology facility as the concentrations of the key gamma radionuclides at the DCGL levels are approximately an order of magnitude over the averages determined later in this evaluation. Large quantities of material at the DCGLs would therefore increase the dose to site workers.

The demolition debris proposed for disposal at the US Ecology Idaho facility will originate from the demolition and removal of structures and paved surfaces at the HNP plant site, after the structure/surface has been decontaminated to remove areas that are highly contaminated.

The physical form of this demolition debris will be that of bulk material of various sizes ranging from the size of sand grains up to occasional monoliths with a volume of several cubic feet. CYAPCO, for the purpose of calculations, assumed the material to be a homogeneous mixture with a specific density of I gram per cubic centimeter during shipment and 1.5 grams per cubic centimeter after compaction in the disposal cell at US Ecology. The material will be dry solid waste containing no absorbents or chelating agents.

CY-04-1 68 / Page 7 3.2 Estimated Waste Volume It is estimated that the mass of demolition debris originating from the decommissioning of the HNP will total approximately 100 million pounds. A breakdown of this waste by source is shown in Table 1.

With an assumed density of 1.50 grams per cubic centimeter, (after compaction at the disposal site) the estimated volume of material to be disposed of at the US Ecology Idaho facility is approximately 40,000 cubic feet. This represents approximately 9 percent of the annual volume of waste at the US Ecology Idaho facility. It will be conservatively assumed that all the HNP material is received in one year although it is anticipated that waste will be shipped to the US Ecology facility starting in 2005 through 2006.

The material will not be isolated or dedicated to a single burial cell at the US Ecology Idaho facility. Rather, it will be co-mingled with other radioactive and non radioactive waste material. The material will be covered at the end of each workday with an asphaltic spray to lockdown contamination, in accordance with US Ecology Idaho facility requirements.

3.3. Radiological Characterization of Waste 3.3.1

Background:

CYAPCO has been in the process of characterizing the radiologically contaminated buildings on site. Efforts to date have concentrated on the buildings containing the highest contamination; however, some radiological data is available on all buildings in the radiological controlled area. The demolition plans are to scabble off surface concrete where contamination levels are high and to dispose of this material at radioactive waste disposal facilities other than the US Ecology, Idaho facility. Areas of concrete where high neutron flux has caused significant activation of the concrete are also not proposed for disposal at the US Ecology Idaho facility. After dispositioning the surface contaminated material containing the highest levels of radioactivity, the remainder of the building and structures will be demolished and it is proposed that much of the debris be shipped to the US Ecology facility near Grand View, Idaho. For the purpose of determining the radioactivity level of material to be shipped to the US Ecology facility, concrete core sampling is most appropriate as these portions of the applicable buildings will be demolished in total. The demolition process results in mixing the surface and

CY-04-1 68 / Page 8 volumetric contamination with the remainder of the wall and floor material. This makes the average concentration in the total thickness of the wall or floor appropriate in determining the overall radioactivity content of the waste material.

Additional sampling will be conducted during building demolition to confirm radionuclide waste concentrations and scaling factors where currently available information is limited.

It is also appropriate to use average values as the dose limits are in terms of annual exposures. Any variation of the waste shipments would be incorporated in the average of all shipments made during a year.

Structural material other than concrete are expected to have only low levels of surface contamination and are therefore bounded by the characteristics of the concrete intended for disposal. Any rebar encased in concrete is also expected to be much less than the surface contamination levels as it is located below the depth to which most of the surface contamination is located and therefore can be treated the same as the concrete.

3.3.2 Characterization Results The portions of site buildings (including structural material after removal of contaminated system piping and components) that CYAPCO proposes to dispose of at the US Ecology Facility are as follows:

Containment Walls (including the containment liner) above elevation 17.5',

Containment Floors/Structures that are inside the containment liner,

Residual Heat Exchanger (RHR) Pit (a Portion of Auxiliary Building) Floors, RHR Pit Walls,

Waste Disposal Building Floors,

Waste Disposal Building Walls and Ceilings,

Remainder of Auxiliary Building above the RHR Pit,

Spent Fuel Pool Walls and Floor,

Remainder of Fuel Building above elevation 17.5',

Service Building above elevation 17.5', and

Other Miscellaneous Radiological Controlled Area (RCA)

Structures, Soil and Asphalt.

A breakdown of the estimated quantities of materials from the above sources is included in Table 1. The following discussion

CY-04-1 68 / Page 9 describes the operational history of the buildings that will make up the waste to be disposed at the US Ecology Idaho Facility and characterization results for the waste that will result from their demolition. In this analysis, some conservatism is applied where data gaps exist. As previously mentioned, additional sampling will be conducted as part of ongoing decommissioning activities to fill these data gaps.

Containment Walls above elevation 17.5' This portion of the Containment Building has not experienced high levels of contamination due to its location and the fact that it did not come in contact with contaminated system leakage. The concrete in this area is outside of a steel liner that covers the entire inside walls of the containment dome above elevation 17.5'. The liner itself is not expected to be highly contaminated. Four (4) Concrete Core Bores have been taken from quadrants of the containment wall at approximately elevation 4'. Twenty-Four (24) wafers cut from these cores were analyzed for gamma radionuclides, tritium and selected wafers for hard to detect radionuclides. Concrete at this elevation will not be shipped as waste but provides conservative characterization results. The containment wall at elevation 4' has been potentially exposed to more contamination than higher elevations of the wall. This elevation is below the water table and therefore subject to the diffusion of contaminated groundwater that has been present outside to the containment. The inside of containment at this elevation was exposed to standing water during the cavity seal failure event in 1984. Therefore, using the wall characterization results from elevation 4' for elevations above 17.5' is conservative. The results of these characterization samples are contained in Table 2. It should be noted that most of the sample results included in Table 2 indicated no detectable activity at the Minimum Detectable Activity (MDA) concentration. For this reason, the scaling factors determined in Table 4 for the RHR Pit Floors will be used to determine waste activities for this building area for all radionuclides except H-3, Co-60, Sr-90 and Cs-137 for which actual sample averages will be used. For C-14, the scaling factor to Co-60 from core sample # 181 taken in this area will be used.

Containment Floors and Internal Structures As described in Section 3.3.1 "Background" above, the highly contaminated surfaces and significantly activated areas of

CY-04-1 68 / Page 10 buildings will not be included as waste materials for the US Ecology facility. Therefore, the core sample results for the in core sump and the liquid sumps in containment are not applicable to the determination of average waste concentration for this area of the building. These sample results were used to determine scaling factors for radionuclides not analyzed for all of the samples. The lower area of the inside of containment experienced standing water from the cavity seal failure previously mentioned. Six (6) cores were taken from the floor in this area. Twelve wafers from these cores were analyzed for gamma and selected hard to detect radionuclides. As can be seen from Table 3, the contamination is one to two orders of magnitude higher in the first 2.5" core compared to the deeper cores. Three additional cores from the floor and walls of this area were taken in 1999.

These cores showed a similar trend. For Co-60 and Cs-137, the concentration of the resulting debris waste, Cwaste, was determined by averaging the concentration in the first 21r2 inch wafers, Cr, of the 12 cores and distributing that value over the average thickness of the containment internal floors, X(in), as follows:

C"".'e

'~C12.5 X

These characterization results will also be used for the internal structures of containment that will be disposed of at US Ecology. Using the floor samples for the internal structures is conservative as most of this material was above the cavity seal failure event and any areas of high surface contamination will be remediated and shipped to a facility other than US Ecology. Data from areas where CYAPCO has collected both floor and wall samples show the floor samples to be at least an order of magnitude higher in radioactivity content than the wall samples.

Whereas many of the samples did not show any detectable activity for most radionuclides, the average scaling factor calculated from the surface wafers will be used to calculate the average activity for all radionuclides except H-3, C-60 and Cs-137. For these radionuclides, the average of the sample results was used to characterize the waste. Only 2 samples from the highly contaminated containment sump were analyzed for tritium. These two sample results were averaged to determine the waste concentration. It is expected that when

CY-04-1 68 I Page 11 more wafers are analyzed for H-3, the average concentration will be reduced.

The characterization samples for this area show measurable levels of C-14. This radionuclide has not been detected in concrete outside of the containment liner in the containment wall or in other buildings on site. It is possible that a gaseous diffusion mechanism has resulted in the shallow permeation of C-14 into containment interior concrete. Therefore, the average sample results for C-14 inside the containment liner will be applied for all concrete inside the containment liner until additional characterization data is obtained.

Residual Heat Exchanger (RHR) Pit of the Auxiliary Building Floors The RHR Pit is one of the most contaminated areas inside buildings at the HNP site due its design and relative inaccessibility. For this reason, it was targeted for concrete characterization work. Four (4) core bores were taken from the floors in this pit. Seventeen wafers were cut from these bores and analyzed for gamma radionuclides. A subset of the wafers was also analyzed for tritium and all other hard to detect radionuclides. Table 4 details the results of the analysis performed on these core bores. As can be seen in Table 4, contamination (with the exception of Tritium) is highest in the first 2.5" wafer and drops by approximately two orders of magnitude for the second and subsequent wafers. As discussed earlier, areas of high contamination will be remediated. For conservatism, it will be assumed that no scabbling will be performed in the areas where the cores were drilled prior to demolition of the RHR Pit floors. The sumps in this building are known to be highly contaminated and will be remediated prior to demolition of the building. None of the cores were taken from sump areas. The determination of the average concentrations for Co-60 and Cs-1 37 follows the same method as is used for the containment floors above.

To determine the activity of the other radionuclides except tritium, the scaling factors to Co-60 calculated from Sample #

165 taken in this area are used to determine the average concentration. For Tritium the average concentration in all the samples will be used to characterize the waste. This is due to the fact that tritium acts as water when diffusing into the concrete.

CY-04-1 68 I Page 12 RHR Pit Walls Five (5) core bores were taken in the walls of the RHR pit.

One was taken through an internal wall at approximately elevation -17'. The other four were taken through the exterior wall of the pit at three subsurface elevations at the location adjacent to the outside location of the former Refueling Water Storage Tank. This was determined to be an area of high potential for elevated concrete contamination due to diffusion of contamination from outside of the building resulting from leakage of the Refueling Water Storage Tank (RWST) while the plant was operating. Twenty-Eight (28) wafers from the cores were analyzed for gamma radionuclides, tritium and a subset for all other hard to detect radionuclides. The results of these analyses are shown in Table 5. Surface and volumetric radioactivity levels were generally low with the exception of Tritium which was detected in moderate levels (compared with the Derived Concentration Guidelines Levels published in the HNP LTP). As contamination was seen on both end cores and on certain internal wafers, the average concentration of H-3, Co-60, Sr-90 and Cs-137 from all the cores were used in determining the waste concentration from this building area.

This approach is conservative as the highest concentrations are on the outside wafers and samples from only 15 % of the core length were analyzed. By not including results from all interior areas of the cores where lower concentrations are expected, the average concentration is higher and, therefore conservative as the average does not take credit for all the dilution that will occur when the building is demolished.

For the remaining radionuclides there were essentially no detections at the MDA concentration. For this reason and due to the relatively low levels of Co-60 for samples in this area, the scaling factors determined for the RHR Pit Floors were used to determine the waste concentrations for the remaining radionuclides.

Waste Disposal Building Walls, Ceilings and Floors above elevation 15' The current plan for the waste disposal building is to decontaminate (this waste was sent to a facility other then US Ecology) it to allow for open air demolition, demolish all of the building and dispose of this post decontamination debris as radioactive waste at US Ecology Idaho. Surveys of the building were reviewed to determine the relative contamination

CY-04-1 68 / Page 13 level of this building other than the floor areas. The result of this review is that these portions of this building had low levels of contamination, at least an order of magnitude below the levels on the RHR pit floors and somewhat lower than the levels on the RHR Pit Walls. A very small percentage of the building areas are a contaminated area. The concentrations determined for the RHR Pit Walls will be used for these areas for conservatism.

Waste Disposal Building Floors at Elevation 0' As mentioned above, the basement floor of the Waste Disposal Building will be removed in its entirety. One concrete core sample was taken from the basement floor in 1999.

Three wafers 0.5" thick were cut from the floor side of the core and analyzed for gamma radionuclides. The results for these wafers are shown on Table 6. The results show shallow contamination at levels consistent with the RHR pit floor samples. These results will be used to characterize the waste from this area along with the scaling factors determined from the RHR Pit floor samples. The tritium sample results from the RHR floors samples were used to characterize this area. A review of surveys of the area shows that the contamination levels are generally low and at least a factor of 5 below the levels on the RHR Pit floors. Only a small portion of these floors are contaminated. Using the results of the one core is therefore conservative.

Primary Auxiliary Building (PAB) other than RHR Pit All of the Primary Auxiliary Building other than the RHR Pit will be decontaminated to allow open air demolition with the scabbled material disposed of in the manner of other higher contaminated materials (not at the U. S. Ecology) The remaining material will be demolished and the debris proposed for shipment to the US Ecology facility. One concrete core was taken from the pipe trench portion of the PAB in 1999. The pipe trench portion of the PAB is the one of the most highly contaminated areas in the PAB. A review of contamination levels of other areas of the PAB shows generally low contamination levels with only a small portion of the building posted as a contaminated area. When the average contamination levels in the PAB as whole are considered, the characterization results for Co-60 and Cs-1 37 for the containment floors are conservative and will be applied to all areas of the PAB except for the RHR Pit. As with the other

CY-04-1 68 / Page 14 areas outside of the containment liner, the scaling factors to Co-60 from the RHR pit floors will be used to determine the concentrations of radionuclides other then H-3, Co-60 and Cs-137. The average concentration of H-3 for the RHR pit walls will be conservatively used for these upper areas of the Primary Auxiliary Building.

Fuel Pit Walls and Floors below elevation 17.5' The spent fuel pool in the Fuel Building is lined with stainless steel liner. The demolition plan for this building is to remove the liner after the pool is empty of fuel and all other material.

This liner will be disposed at a waste facility other than the US Ecology facility. It is known that at least a small amount of leakage past the liner has occurred. Due to concerns with the integrity of the fuel pool there has been no characterization of this area. The high concentrations measured for the RHR Pit Floors will be used to represent this area.

Remainder of Fuel Building above Elevation 17.5' The review of surveys of the remainder of the fuel building has shown low contamination levels with only a few small contaminated areas. Although the RHR Pit walls show higher levels of contamination, the concentrations for the RHR Pit walls will be used for the remainder of the Fuel Building for conservatism.

Service Building above Elevation 17.5' The Service Building has not experienced many contamination events. A review of building surveys shows only a few small contaminated areas in a Decontamination Room and the Chemistry Lab. Contaminated commodities in these areas will be removed and shipped to facilities other then the US Ecology facility. The remaining concrete, will on the average, have very low contamination levels. The expected levels are consistent with those in the Containment walls and therefore, those concentrations will be used for the service building with the exception of C-14. As there have been no detections of C-14 in concrete outside of the containment liner, the scaling factor for Co-60 determined for the RHR Pit floors will be used to determine the C-14 waste concentration in this area.

CY-04-1 68 /Page 15 Miscellaneous Structures, Soil and Asphalt There are other relatively small structures which are in the Radiological Controlled Area but have very low contamination levels. These include the Cable Vault and the Radwaste Reduction Facility. It is planned that the portions of these buildings above elevation 17.5' be disposed at the US Ecology facility. These buildings have a very low contamination history and either have very small or no contaminated areas. There will also be quantities of slightly contaminated soil that will be displaced to allow access for removal of foundations.

Quantities of slightly contaminated asphalt will be removed from the site to meet non-radioactive site closure criteria. As previously discussed, soil with radionuclide concentrations near the LTP DCGLs will not be disposed of at US Ecology, Idaho as these levels would be inconsistent with the concentrations in other type of waste proposed for disposal there. Waste concentrations determined for the containment walls are appropriate for application to this class of waste materials except as amended for C-14 as was done for the Service Building.

3.3.3 Average Concentration of Waste to be shipped to US Ecology In order to determine the average concentration of waste proposed to be disposed of at US Ecology, a weighted average of the concentrations discussed earlier is determined in Table 8. It can be seen from characterization sample results in Tables 2 thru 7 that the primary radionuclides that affect dose to personnel either transporting the waste or working with its disposal at US Ecology are C-60 and Cs-1 37.

All other gamma emitting radionuclides are present at much lower levels and therefore, need not be included in calculating worker dose. The alpha and beta emitting radionuclides are not a direct dose concern and can only be an inhalation or ingestion hazard during placement in the disposal cell. The controls, discussed earlier, present at the US Ecology facility and the relative low concentrations will preclude any significant dose from these radionuclides to the workers.

The weight of waste from each building is shown based on a recent estimate. The concentration of Co-60 and Cs-1 37 for each building area is multiplied by the estimated weight of building debris from each building, summed and the sum divided by the total waste weight to determine the weighted average. This value is shown in Table 8. These values are

CY-04-1 68 / Page 16 used later to determine expected yearly dose to transportation and US Ecology site workers involved in disposal of the HNP material.

For the purposes of determining potential dose to a member of the public after the closure of the US Ecology site, the activities of other radionuclides will be determined by the use of scaling factors based on actual HNP characterization sample data. The sample data indicates different scaling factors for inside versus outside of the containment liner. This is primarily due to the detection of C-14 in concrete inside of the containment liner. Therefore, two sets of scaling factors were used to characterize the waste. As shown on Table 8, one set of scaling factors determined from the average of sample results inside the containment liner will be applied to that area. Scaling factors determined from RHR pit floor samples will be used for concrete and other materials from outside of the containment liner. All scaling factors will be based on the ratio of the hard to detect radionuclide to Co-60.

As previously discussed, average sample results were used to characterize the proposed waste for tritium. Sr-90 samples show some limited degree of migration of this radionuclide through concrete structures in certain plant areas. As can be seen in Table 8, average sample results for Sr-90 were used when this was the case. A review of the sample data shows that the scaling factors determined are conservative as many are based on sample results that indicate no detectable activity at Minimum Detectable Activity concentration rather than actual detections. Using the above outlined protocol, Table 8 illustrates the values used to determine the average waste concentrations for the material proposed for disposal at the US Ecology facility.

4 RADIOLOGICAL ASSESSMENTS 4.1 Transport Worker Dose Assessment The Transportation Scenario Maximally Exposed Individual (MEI) dose equivalent will not exceed a few (e.g., five (5)) millirem/yr. This standard of a "few mrem/yr" to a member of the public prior to license termination is defined in NRC Regulatory Issue Summary 2004-08 Reference 6.4). The transportation workers and worker at the US Ecology site are treated as members of the public as the US Ecology site is not licensed by the NRC. Evaluations of both internal and external dose hazards to the transportation worker are discussed below.

CY-04-168 / Page 17 Each conveyance will be a strong-tight container and will be verified to be in compliance with Department of Transportation (DOT) external loose surface contamination limits prior to shipment.

Therefore, there are no internal dose hazards associated with the Transportation Scenario.

The conservative average activity concentrations discussed in Section 3.3.3 of this Attachment were used to calculate penetrating gamma dose rates external to the conveyance used to transport the material. The geometry modeled bounds any variations in the actual conveyances (e.g., intermodals) that may be used. These calculations are included as Attachment 2. The following dose receptor points were modeled.

a worst case, on-contact (i.e., one inch (1")) receptor point adjacent to the center of the side of the conveyance;

a more representative one (1) meter receptor point adjacent to the center of the side of the conveyance; and

a theoretical "driver" receptor point two (2) meters from the center of the front of the conveyance.

The resultant dose rates to each of these receptor points are 1.025 E-3 mR/hour, 6.454 E-4 mR/hour, and 2.288 E-4 mR/hour, respectively. Therefore, a worker would need to spend in excess of 4,878 hours0.0102 days 0.244 hours 0.00145 weeks 3.34079e-4 months , 7,747 hours0.00865 days 0.208 hours 0.00124 weeks 2.842335e-4 months , and 21,853 hours0.00987 days 0.237 hours 0.00141 weeks 3.245665e-4 months per year, respectively, at these points to exceed a dose equivalent of five (5) millirem per year.

It is qualitatively judged to be non-credible that the Transportation Scenario Maximum Exposed Individual (MEI) (e.g., transportation worker, or any other member of public interacting with the transportation activity) would exceed these occupancy times. When a realistic maximum occupancy time of 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months per year (50% of the normal 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months work year actually spent transporting the HNP waste) and worker location in respect to the package is used, the expected dose is less then 1 millirem/yr.

While any given conveyance, or point on the conveyance, may exhibit external dose rates in excess of the levels calculated, the average dose rate to which the MEI is exposed over the course of the year is expected to be below the value calculated. Therefore, Transportation Scenario MEI dose equivalent will not exceed a few (e.g., five (5)) millirem/yr and realistically the expected dose to the MEI is less than 1 millirem/yr.

4.2 Disposal Facility Worker Dose Assessment The Disposal Site Material Placement Scenario MEI dose equivalent will not exceed a few (e.g., five (5)) millirem/yr. The relevance of this

CY-04-1 68 / Page 18 standard is discussed previously in section 4.1. Evaluations of both internal and external dose hazards to the transportation worker are discussed below.

In support of the operating permit issued by the State of Idaho, US Ecology Idaho maintains a Radiation Protection Program including routine performance of radiation, contamination, and airborne radioactive material surveys. The facility currently conducts disposal activities involving materials similar to those described in Section 3, except that they are contaminated with source material, which has been exempted under 10CFR40. These source material isotopes (i.e., 238U and 232Th) are present in concentrations greater than, and have Derived Air Concentration (DAC) and Annual Limit on Intake (ALI) values several orders of magnitude more restrictive than the primary isotopes of concern described in Section 3.2, herein.

Despite this much larger internal dose hazard, the site has had no significant internal dose exposures. Therefore, operating experience indicates that there would be no internal dose hazards associated with the disposal activities described herein, and on-site monitoring will be used to demonstrate and control compliance with all applicable limits.

The conservative average activity concentrations discussed in Section 3.3 of this Attachment were used to calculate penetrating gamma dose rates to the worker in the vicinity of the placed material prior to it being covered. The geometry modeled assumes a dose receptor point centered 18" above a representative slab of material (i.e., after placement) and bounds any after placement scenario. It should also be noted that this calculation conservatively does not take credit for the non-radioactive material that will be co-mingled with the HNP waste. This calculation is included as Attachment 2.

The resultant dose rate to the receptor point is 1.452 E-3 mR per hour. Therefore, a worker would need to spend in excess of 3,444 hours0.00514 days 0.123 hours 7.34127e-4 weeks 1.68942e-4 months per year at this point to exceed a dose equivalent of five (5) millirem per year. It is qualitatively judged to be non-credible that the Disposal Site Material Placement Scenario MEI (e.g., disposal activity worker, or any other member of public interacting with the disposal activity) would exceed this occupancy time. When a realistic maximum occupancy time above the disposal cell of 1000 hour0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months s/yr (50% of the normal work year spent directly on the disposal cell) is used, the dose to the disposal facility worker is 1.45 millirem/yr.

CY-04-1 68 / Page 19 4.3 Resident/Farmer Dose Assessment The RESRAD computer code was used to calculate the projected effect of the proposed disposal activity on future residents at the disposal site. Each isotope of concern was included at a soil concentration of one (1) pCi/g, such that the resultant calculated dose equivalent to the maximum exposed individual (Resident Farmer) could be evaluated in terms of mrem/year per pCi/g activity concentration. A comprehensive report describing the methodology, input parameter selection, and calculation results is included as Attachment 3.

The average radionuclide concentrations in the waste proposed for disposal was determined in Section 3.3.3. It can be seen in Attachment 3 that many of the assumptions used in the RESRAD code were conservative resulting in an over estimation of post closure dose to a member of the public. The calculation of expected dose to a member of the public after closure of the facility is performed as follows: Table 9 shows the dose to the Resident Farmer for each radionuclide at a concentration of 1 pCi/g. Table 9 shows the post-closure dose to a member of the public when the dose at 1 pCi/yr for each radionuclide is scaled to the average concentrations of the HNP waste determined in Section 3.3.3. It can be seen that the total expected dose to a member of the public post closure is 1.133 millirem/yr.

In addition to other conservatism in the post-closure dose calculation discussed elsewhere in this evaluation, the values shown in Table 9 are very conservative for the following reason. It can be seen that more then 99 % of the post closure dose results from the radionuclides C-14, Nb-94, Tc-99 and Ag-108m. A review of the Attachment 3 report shows that the dose from these radionuclides results from the groundwater pathway. Further review of Attachment 3 shows that the RESRAD default distribution coefficient (Kd) for these radionuclides which was used is value of zero (0). This means that these radionuclides are assumed to have mobility in and below the disposal cell which is equivalent to water. A review of NRC guidance (NUREG/CR-6697, Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 Computer Codes, Attachment C, Table 3.9-1) shows positive Kd values for all of these radionuclides. If the NRC guidance values for Kd had been used in lieu of the RESRAD defaults, the mobility of these radionuclides would be significantly retarded and post closure dose reduced to even less significant levels.

The above discussion demonstrates that the disposal of the HNP waste materials at the average isotopic contaminant concentrations

CY-04-1 68 / Page 20 described in Section 3 will result in an insignificant dose (1.15 millirem/yr) post closure to a member of the public. This dose is a small fraction of the 25 millirem/yr NRC post closure criteria for allowable dose to a member of the public (and also the US Ecology site standard of 15 millirem/yr general radiation protection standards for the public) and is of little significance when the high factors of conservatism used in the calculation are considered.

5. Conclusions Based on the above assessment, it can be concluded that the calculated potential dose to members of the public (i.e., workers involved in the transportation to and placement of the waste and residents after closure of the site) as a consequence of the proposed waste disposal from the decommissioning activities at the HNP at the US Ecology Idaho Facility will be an insignificant fraction of the 25 millirem per year limit. Therefore, CYAPCO concludes that the proposed request for approval in accordance with 10 CFR 20.2002 will not have a significant impact on the workers, public, or the environment and that it is, therefore, acceptable.

6. References 6.1 Envirosafe, 1998. "Permit for Treatment, Storage, and Disposal of Hazardous Waste, Attachment 9: Closure and Post Closure Plans, p.36, Envirosafe Services of Idaho, Inc., 1998.

6.2 Envirosafe, 2000. "Notification of a Class I Modification, Administrative and Informational Changes to Waste Acceptance Parameters, Appendix A, ResRad Modeling of Post Closure Dose, p.2, Envirosafe Services of Idaho, Inc., 2000.

6.3 CH2M Hill, 1993. "Hydrogeological Characterization and Ground Water Monitoring Considerations for Proposed Cell 14 Expansion Area at Envirosafe Services of Idaho-Site B, pp.35-39, Envirosafe Services of Idaho, 1993.

6.4 NRC Regulatory Issue Summary 2004-08, Results of the License Termination Rule Analysis, dated May 28, 2004.

CY-04-168 / Attachment 1 / Page 21 Table i Estimated Waste Quantities Proposed for Disposal at US Ecology Idaho Source of Waste Estimated (onsWaste Weight (pounds)

Containment Walls 40,000,000 Containment Floor & Internal Structures 20,000,000 Residual Heat Exchanger(RHR) Pit Floors 1,000,000 RHR Pit Walls 2,000,000 Waste Disposal Building Walls 2,500,000 Waste Disposal Building Floors 500,000 Remainder of Auxiliary Building (w/o RHR Pit) 7,000,000 Spent Fuel Pool Walls & Floor 1,000,000 Remainder of Fuel Building above elevation 17.5' 8,000,000 Service Building above elevation 17.5' 8,000,000 Miscelaneous Structures/SoilAsphalt 10,000,000 Total 100,000,000O

CY-04-168 / Attachment 1 /Page 26 Table 6 Waste Disposal Building Basement Floors-Elevation O' GTS Sample GTS Sample GTS Sample Average over Dated 1/27/99 Dated 1/27/99 Dated 1/27/9 Total Radionuclide First 0.5 inch. 0.5 to 1 inch. I to 1.5 inch. Thickness pCi/g pCilg pCi/g pci/g Co-60 160.55 0.65 0.58 2.79 Nb-94 0.28 0.43 <MDA 0.00 Cs-134 1.30 0.18 0.54 0.02 Cs-1 37 264.00 0.72 0.52 4.59 Eu-1 54 4.05 <MD <MD 0.07 Eu-1 55 0.86 <MD <MD 0.01 Am-241 11.03 <MDA <MD 0.19 Note: 1.Sample Results in Bold Type are <Minimum Detectable Activity (MDA)

CY-04-168 / Attachement 1 I Page 27 Table 7 Primary Auxiliary Building Sample (Other then RHR Pit)

PAB Pipe Chase GTS Sample GTS Sample GTS Sample Average over Radionuclide Dated 1/27/99 Dated 1/27/99 Dated 1/27/9 Total First 0.5 inch. 0.5 to 1 inch. 1 to 1.5 inch. Thickness pci/g pCig pCi/g 9pci/

Co-60 34.10 1.00 1.00 1.42 Cs-134 5.18 0.13 0.07 0.22 Cs-1 37 74.00 0.91 0.28 3.0E Note: 1.Sample Results In Bold Type are <Minimum Detectable Activity (MDA)

CY-04-168 / Attachment 1 / Page 29 Table 9 Post Closure Dose Calculation Dose Equivilent per Concentration Weighted Post Closure Radio- of Radionuclide - Average of Dose for Avg nuclide Resident Farmer All Waste of All Waste (mremlyr per (pCilg) (mremlyr) pCilg)

H-3 1.045E-05 261.88 2.737E-03 C-14 3.060E-01 3.68 1.126E+OC Mn-54 6.286E-25 1.67E-03 1.052E-27 Fe-55 O.OOOE+00 0.14 O.OOOE+OC Co-60 1.653E-21 0.28 4.692E-22 Ni-63 O.OOOE+OI 1.69 O.OOOE+0C Sr-90 O.OOOE+OI 0.03 O.OOOE+0C Nb-94 9.961 E-01 1.25E-03 1.246E-03 c-99 2.221 E-01 6.49E-03 1.441 E-03 Ag-108m 5.764E-01 2.04E-03 1.176E-03 Cs-134 5.881E-26 4.89E-03 2.875E-28 Cs-137 6.850E-27 0.97 6.674E-27 Eu-152 1.567E-23 5.01 E-0 7.854E-26 Eu-154 5.997E-23 3.81 E-0 2.286E-25 Eu-155 O.OOOE+O 3.85E-03 O.OOOE+00 Pu-238 2.004E-06 3.69E-03 7.398E-09 Pu-239 O.OOOE+OI 1.23E-03 O.OOOE+0C Pu-241 O.OOOE+O 5.09E-0 O.OOOE+0C Am-241 O.OOOE+O 6.58E-03 O.OOOE+0C Cm-243 O.OOOE+OI 1.11 E-03 O.OOOE+OC Total Post Closure Dose (mrem/yr] 1.1 33E+00 Note: 1. Values In Bold Type are based on Minimum Detectable Activity (MDA)

(i.e. Radionuclide was not detected at the MDA concentration

Docket No. 50-213 CY-04-1 68 Attachment 2 Haddam Neck Plant Microshield Calculations September 2004

MicroShield v5.01 (5.01-00091)

Lockheed Martin Energy Systems Page : 1 File Ref: C VL iLLrL DOS File: CY-OC.MS5 Date: 51/Vq Run Date: September 8, 2004 Byh:ecedfe Run Time: 10:05:00 AM Checked: ~

Duration: 00:00:16 Case

Title:

Transport - Side OC

Description:

CY Transport - Side Dose Receptor On Contact Geometry: 13 - Rectangular Volume Source Dimensions Length 304.8 cm 10 ft 0.0 in Width 609.6 cm 20 ft 0.0 in Height 304.8 cm 10 ft 0.0 in Dose Points X y z

1 307.6575 cm 152.4 cm 304.8 cm 10 ft 1.1 in5 ft 0.0 inlO ft 0.0 in Shields Shield Name Dimension MaterialDensity Source 3.46e+06 in 3 Concretel Shield 1 .125 in Iron 7.86 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies beccuerels uCi/cm3 Bcr/cm 3 Ba-137m 5.2183e-005 1.9308e+006 9.2140e-007 3.4092e-002 Co-60 1.6084e-005 5.9511e+005 2.8400e-007 1.0508e-002 Cs-137 5.5161e-005 2.0410e+006 9.7400e-007 3.6038e-002 Buildup The material reference is : Source Integration Parameters X Direction 30 y Direction 30 z Direction 30 Results Enerav Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2 /sec MeV/cm 2 /sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.03 1.137e+05 1.282e-15 2.408e-15 1.270e-17 2.386e-17 0.04 2.684e+04 2.866e-10 7.703e-10 1.267e-12 3.407e-12 0.6 1.737e+06 6.711e-02 2.021e-01 1.310e-04 3.945e-04 1.0 5.951e+05 5.316e-02 1.331e-01 9.800e-05 2.454e-04 1.5 5.951e+05 1.043e-01 2.290e-01 1.755e-04 3.853e-04 TOTALS: 3.068e+06 2.246e-01 5.642e-01 4.045e-04 1.025e-03

MicroShield v5.01 (5.01-00091)

Lockheed Martin Energy Systems Page : 1 File Ref:

DOS File: CY-1M.MS5 Date: 4/v/

Run Date: September 8, 2004 By: 11 Run Time: 10:00:30 AM Checked: M Duration: 00:00:16 Case

Title:

Transport - Side 1M

Description:

CY Transport - Side Dose Receptor at one (1) meter Geometry: 13 - Rectangular Volume Source Dimensions

9¶**

Length 304.8 cm 10 ft 0.0 in Width 609.6 cm 20 ft 0.0 in Height 304.8 cm 10 ft 0.0 in Dose Points X y z

1 406.7175 cm 152.4 cm 304.8 cm 13 ft 4.1 in5 ft 0.0 inlO ft 0.0 in Shields Shield Name Dimension MaterialDensity Source 3.46e+06 in3 Concretel z Shield 1 .125 in Iron 7.86 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies beccruerels uCi/cm 3 Ba/cm 3 Ba-137m 5.2183e-005 1.9308e+006 9.2140e-007 3.4092e-002 Co-60 1.6084e-005 5.9511e+005 2.8400e-007 1.0508e-002 Cs-137 5.5161e-005 2.0410e+006 9.7400e-007 3.6038e-002 Buildup The material reference is : Source Integration Parameters X Direction 30 y Direction 30 z Direction 30 Results Enercrv Activitv Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2 /sec MeV/cm 2 /sec mR/hr MRLhr No Buildup With Buildup No Buildup With Buildup 0.03 1.137e+05 2.962e-15 5.467e-15 2.935e-17 5.418e-17 0.04 2.684e+04 2.613e-10 6.950e-10 1.156e-12 3.074e-12 0.6 1.737e+06 4.729e-02 1.306e-01 9.231e-05 2.550e-04 1.0 5.951e+05 3.619e-02 8.365e-02 6.670e-05 1.542e-04 1.5 5.951e+05 6.890e-02 1.404e-01 1.159e-04 2.362e-04 TOTALS: 3.068e+06 1.524e-01 3.547e-01 2.749e-04 6.454e-04

MicroShield v5.01 (5.01-00091)

Lockheed Martin Energy Systems Page : 1 File Ref: CV-U4:5Z~

DOS File: CYDRIV.MS5 Date: 9/i/l Run Date: September 8, 2004 By: ;Z Run Time: 9:33:13 AM Checked: X3 Duration: 00:00:16 /-

Case

Title:

Transport - Driver

Description:

CY Transport - Driver C 2 M Geometry: 13 - Rectangular Volume Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 304.8 cm 10 ft 0.0 in Height 304.8 cm 10 ft 0.0 in Dose Points X y z

1 815.975 cm 152.4 cm 152.4 cm 26 ft 9.3 in 5 ft 0.0 in 5 ft 0.0 in Shields Shield Name Dimension MaterialDensity Source 3.46e+06 in 3 Concretel Shield 1 .125 in Iron 7.86 Shield 2 80.0 in Air 0.00122 Shield 3 .125 in Iron 7.86 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies beccruerels uCi/cm3 Ba/cm 3 Ba-137m 5.2183e-005 1.9308e+006 9.2140e-007 3.4092e-002 Co-60 1.6084e-005 5.9511e+005 2.8400e-007 1.0508e-002 Cs-137 5.5161e-005 2.0410e+006 9.7400e-007 3.6038e-002 Buildup The material reference is : Source Integration Parameters X Direction 30 Y Direction 30 Z Direction 30 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2 /sec MeV/cm2 /sec mR/hr mR/hr No BuilduP With Buildup No Buildup With Buildup 0.03 1.137e+05 3.620e-24 7.332e-24 3.588e-26 7.266e-26 0.04 2.684e+04 2.341e-14 7.567e-14 1.036e-16 3.346e-16 0.6 1.737e+06 1.567e-02 4.625e-02 3.059e-05 9.028e-05 1.0 5.951e+05 1.232e-02 2.968e-02 2.270e-05 5.471e-05 1.5 5.951e+05 2.381e-02 4.982e-02 4.006e-05 8.382e-05

Page : 2 DOS File: CYDRIV.MS5 Run Date: September 8, 2004 Run Time: 9:33:13 AM Duration: 00:00:16 Enercrv Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2 /sec MeV/cM 2 /sec mR/hr mR/hr No Buildu= With Buildup No Buildup With Buildup TOTALS: 3.068e+06 5.180e-02 1.258e-01 9.336e-05 2.288e-04

MicroShield v5.01 (5.01-00091)

Lockheed Martin Energy Systems Page : 1 File Ref: CN-U£6 DOS File: CYUSEI.MS5 Date: YiLzd14 Run Date: September 8, 2004 By : -Ay Run Time: 9:24:49 AM Checked: Ll(

Duration: 00:00:18 O' Case

Title:

CY - USEI

Description:

CY material in USEI cell Geometry: 13 - Rectangular Volume Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+4 cm 400 ft Height 1.2e+4 cm 400 ft Dose Points x y z

1 655.32 cm 6096 cm 6096 cm 21 ft 6.0 in 200 ft 200 ft Shields Shield Name Dimension MaterialDensity Source 3.20e+06 ft3 Concretel.5 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies beccruerels uCi/cm3 Ba/cm3 Ba-137m 1.2515e-001 4.6306e+009 1.3812e-006 5.1103e-002 Co-60 3.8602e-002 1.4283e+009 4.2600e-007 1.5762e-002 Cs-137 1.3230e-001 4.8950e+009 1.4600e-006 5.4020e-002 Buildup The material reference is : Source Integration Parameters X Direction 30 y Direction 30 z Direction 30 Results Energv Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV ohotons/sec MeV/cm 2 /sec MeV/cm 2 /sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.03 2.727e+08 1.097e-05 1.464e-05 1.087e-07 1.450e-07 0.04 6.437e+07 1.264e-05 1.973e-05 5.589e-08 8.726e-08 0.6 4.167e+09 1.208e-01 2.959e-01 2.359e-04 5.776e-04 1.0 1.428e+09 8.830e-02 1.880e-01 1.628e-04 3.465e-04 1.5 1.428e+09 1.633e-01 3.139e-01 2.748e-04 5.282e-04 TOTALS: 7.361e+09 3.725e-01 7.979e-01 6.736e-04 1.452e-03

Docket No. 50-213 CY-04-1 68 Attachment 3 Haddam Neck Plant Resident/Farmer Dose Assessment September 2004

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill Prepared by:

Mark McHugh, CHP WESKEM, LLC Prepared for:

Russ Meyer, CHP US Ecology Idaho August 2004

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill TABLE OF CONTENTS Page 1.0 Purpose ................ 1 2.0 Background ................ 1 3.0 Methodology ................ 1 3.1 Isotopic Concentrations ................ 1 3.2 The Model ................ 2 4.0 Results ................ 3 5.0 Conclusion ................ 3 6.0 Appendices ................ 5 Page i of i

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill 1.0 Purpose This assessment calculates the radiological effect per given activity concentration per isotope to the future resident farmer at the US Ecology Idaho disposal facility from the alternative disposal of wastes containing residual radioactive material contamination.

These wastes are from decommissioning activities conducted at the Connecticut Yankee Haddam Neck Plant.

2.0 Background

US Ecology Idaho operates a hazardous waste landfill under a permit issued by the State of Idaho. The facility has a successful history of disposal of wastes contaminated with residual radioactive materials contaminated with source material (i.e., 238U and 232Th) that has been exempted under 10CFR40. The input parameters used herein have been used previously by US Ecology staff to evaluate the radiological effects of disposal of this exempt source material to the resident farmer as an Average Member of the Critical Group(AMCG) who might live upon the disposal facility at some time after facility closure up to 1,000 years in the future.

Connecticut Yankee (CY) is decommissioning the Haddam Neck Nuclear Power Plant (HNP) in accordance with an NRC approved License Termination Plan (LTP). Waste materials generated during the decommissioning activities vary greatly in the amount of residual radioactive material that they contain. Connecticut Yankee is seeking NRC

,approval to dispose of decommissioning materials containing very low quantities of residual radioactive material at the US Ecology Idaho landfill.

3.0 Methodology 3.1 Isotopic Concentrations The dose assessment was performed using the RESRAD 6.22 computer code. Except where specifically noted, the RESRAD default parameters were used as input parameters.

The CY License Termination Plan (LTP) identifies 20 potential isotopes of concern in the subject waste. Each of these isotopes were included in the model at a soil concentration of one (1) pCi/gram. Therefore, the dose assessment results indicate a dose equivalent per soil concentration per isotope (i.e., in mrem/year per pCilg per isotope), and are not intended to be evaluated as a direct output (i.e., isotopes may be present in less or greater concentrations than one (1) pCi/gram).

Page 1 of 5

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill Table 3-1: Isotopes of Concern

. 3H . Itc

SiMn a 55 Fe 60 63

. Co . Ni

90Sr . 94 Nb

9 9 Tc . l08mAg 134

. cs . 137cS C 15 2 Eu

154 Eu 155U

5Eu . 238U 23Pu

. 239/240pu 241pU

. 24'Am

243/240ci 3.2 The Model The RESRAD computer code is utilized to calculate doses, risks, and guidance values for residual concentrations of radionuclides in material. The code was designed by the Department of Energy (DOE) to demonstrate compliance with DOE Order 5400.5.

The radiation dose, as determined by RESRAD, is the Total Effective Dose Equivalent (TEDE) from the sum of external radiation plus the Committed Effective Dose Equivalent (CEDE) from internally deposited radionuclides. The critical population group is a relatively small, homogeneous group that is representative of those individuals in the population that could reside at the site after closure. The exposure scenario represents the reasonable maximally exposed resident farmer, who resides, works, grows crops, and raises livestock on site. The "Aquatic Foods" p'athway was suppressed due to the topography of the area around the USEI landfill (i.e., it is an arid region with the nearest surface water source two (2) miles distant).

Because this scenario is based on "prudently conservative" assumptions that tend to overestimate potential doses, use of this scenario results in estimated doses that will be greater than exposure to future residents. The highest dose per year for each isotope was used to determine the potential effects of that isotope. Copies of the graphic outputs for TEDE for each isotope at one (1) pCi/g are included in Appendix A.

RESRAD input parameters for the subject calculation, as well as their bases, are provided in Appendices B and C, and include calculations using site specific material characteristics, as determined from the site hydro-geological report(Reference 3).

Otherwise, RESRAD default parameters were used. No institutional control period was credited (i.e., the model was evaluated from the time of waste emplacement to 1,000 years thereafter).

Page 2 of 5

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill 4.0 Results The isotopes of concern can be roughly divided into four different groups for the purpose of this dose assessment. These are:

1. relatively short-lived isotopes that do not emit sufficiently penetrating gammas to penetrate the cap at the time of placement and that are not sufficiently water soluble to reach the water table prior to significant dispersion or radioactive decay (e.g., Fe, Ni, 90Sr);

2. relatively short-lived isotopes that emit sufficiently penetrating gammas to penetrate the cap at the time of placement and that are not sufficiently water soluble60 to reach the52water table prior to significant dispersion or radioactive decay (e.g., Co, 137Cs, 1 Eu);

3. water soluble isotopes that reach the water table prior to significant dispersion or radioactive decay (e.g., 108mAg, 1 4 C, 94Nb, 99 Tc, 3 H); and

4. isotopes that are sufficiently long-lived to remain in place until significant cap erosion occurs (e.g., 238Pu).

Each of these groups exhibit similar dose characteristics, although some more significant than others. The first group poses no dose hazard in the subject model (i.e., zero (0) mrem of dose equivalent from the time of placement through 1,000 years thereafter). The second poses an initial external dose hazard, although of negligible magnitude in all cases, which reduces with time through radioactive decay. The third is the primary dose hazard for the analyzed scenario. These isotopes are sufficiently water soluble to reach the water table prior to decay or dispersion, with the resultant dose equivalent peaking at

- 122 years after placement. The last group consists of 238Pu, whose progeny is sufficiently long-lived to pose Radon and direct dose hazards near the 1,000 year point (i.e., progeny in-growth coordinated with cap erosion). While this last group exhibits different dose characteristics, the actual magnitude of the associated dose hazard is negligible. Other alpha emitting radionuclides, although physically similarto 238Pu, do not include Radon as a progeny in their decay chain and therefore pose no dose hazard.

5.0 Conclusion This assessment establishes a dose equivalent per year per activity concentration to the future Resident Farmer Average Member of the Critical Group as a result of the subject disposal activities for each isotope of concern. Since, the relationship between activity concentration, for any given isotope, and resultant dose equivalent are linear, these values can be weighted by the actual isotopic concentrations in the waste stream to determine a dose equivalent estimate for the disposal activity.

Page 3 of 5

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill Table 4-1: Dose Equivalent per Concentration per Isotope Time after Dose Equivalent per Concentration at Isotope Placement to Peak Time of Peak Dose Dose (mrem/year per pCi/gram) 3H 115.2 1.045E-5 It 122.2 3.060E-1 540D O 6.286E-25 55Fe 0 0 60Co 0 1.653E-21 6 3Ni 0 0 90Sr 0 0 94Nb 122.2 9.961E-1 99Tc 122.2 2.221E-1 1OsmAg 122.2 5.764E- 1 134 Cs 0 5.881E-26 3 7 CS 0 6.850E-27 Eu 0 1.567E-23 154EU 0 5.997E-23 155EU 0 0 2 38 PU 1,000 2.004E-8 23 9 Pu 0 0 241PU 0 0 24 1Cm 0 243Cm O Page 4 of 5

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill 6.0 Appendices Appendix A: RESRAD Graphic Output for Resident Farrnd Disposal Scenario Appendix B: RESRAD Report of Input Parameters and Resultant TEDE for Resident Farmer Disposal Scenario Appendix C: Technical Bases for RESRAD Input Parameters Page 5 of 5

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill APPENDIX A RESRAD Graphic Output for Resident Farmer Scenario

DOSE: Ag-108m, All Pathways Summed 0.6 0.5 I I I. . . I .

K 0.4 -

I-s 0.3 - I I II I I I I I I I I I I E

'. I I 0.2 -

0.1 - I

)

0.0 - I 2 I 10 100 1000 Years CY_USEIC.RAD 08/30/2004 14:42 Includes All Pathways

DOSE: Am-241, All Pathways Summed 1.OOE+00 9.OOE-01 8.00E-01

-I Ias00X 7.OOE-01 6.OOE-01 I-

>1:

- 5.OOE-01 4.OOE-01 3.OOE-01 2.OOE-01 1.00E-01 Oo IL

-I)t8/

O.OOE+01 I 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Includes All Pathways

DOSE: C-14, All Pathways Summed 0.35 0.30 0.25

&. 0.20 I

E 0.15 0.10 0.05 0.00 1 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes All Pathways

DOSE: Cm-243a, All Pathways Summed 1.OOE+OO - - $X - - -

9.OOE-O1 - ,1 - _ _ _ -

8.OOE-01 -- - -

7.OOE-01 .- - - - _ _ _- -

6.OOE-01 10 1 4 5.OOE-01 -- - - - _ _ _- -

4.OOE-01 - - --

3.OOE-01 -- ___

2.OOE -_ _ -_ _ _ _ _ -

1. OOE -_ _ -_ _ _ _ - -

0.OOE+01 I 10 100 1000 Years CY_USEIC.RAD 08130/2004 14:42 Indudes All Pathways

DOSE: Cm-243b, All Pathways Summed 1.OOE+00 9.OOE-01 8.OOE-01 X Ind 7.OOE-01 6.OOE-01 L-i 5.DOE-01 E

4.OOE-01 I_ I 3.00E-01 2.OOE-01 1.00E-01 O.OOE+01 I 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes Al Pathways.

DOSE: Co-60, All Pathways Summed 1.60E-21 1.40E-21 -_ - - __ __

1.20E-21 --

1.OOE-21 -

E 8.OOE-22I 4.OOE-2 6.OOE-22 ~

O.OOE+01 - _ _ _ _ _ - I--

I 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes All Pathways

DOSE: Cs-134, All Pathways Summed 4.50E _ _ _ _ _ _

4.OOE-26 - - . _ _ _ _ __ _ _

3.50E _ _ _ _ _ _ _ _ _

3.OOE-26 - - ~ ._ _-_ _ _ ~-

2.50E-26 - _ _ _ _- - -

E2.OOE-26 -_____ ---

- I le ___ ___

1.50E I.O OE - - - - _ __ _ _

5.OOE-27 _ __ _ _-

0.OOE+01 ----

1 10 100 1000 Years CY_USEIC.RAD 08/3012004 14:42 Indudes All Pathways

DOSE: Cs-137, All Pathways Summed 7.00E-27 6.OOE-27 5.0OE-27 4.00E-27 L.

I-0 E

3.OOE-27 2.OOE-27 1.00E-27 0.OOE+01 I 10 100 1000 Years CYJUSEIC.RAD - 08/30/2004 14:42 Includes All Pathways

DOSE: Eu-152a, All Pathways Summed 1 .20E-23 1 .00E-23 8.00E-24 S-i 6.OOE-24 E

4.OOE-24 2.OOE-24 0.OOE+01 I 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes All Pathways

DOSE: Eu-152b, All Pathways Summed 4.50E 4.OOE 3.50 E-24 3.OOE -2.50E-24 E 2.OOE-24 I1.50E _ _ _ _ _ _

I.OOE 5.OOE-25 0.OOE+01 1 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes All Pathways

DOSE: Eu-154, All Pathways Summed 6.00E-23 5.00E-23 N>

I I I I _I I _ I_ I _ II_ _ I 4.00E-23 4 1 1 4 1 1 4 I i 3.00E-23 J 4 J-----4--4--4--4-4-4--4 4- .I.-4----4 4 E

2.00E-23 1.OOE-23 O.OOE+01 --

_=__ -- X__ _

1 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Includes All Pathways

DOSE: Eu-155, All Pathways Summed 1.00E+00 9.OOE-01

____ ___ __=__ __ ____ =-__ _____

8.OOE-01 ___ _=X_ __ __ _< _____

7.OOE-01 <X __ ___ __=_ _____ _____

6.OOE-01 S

ttLUL0<X L.

5.OOE-01 E

4.OOE-01 tX 3.OOE-01 2.OOE-01 1.OOE-01 0.OOE+01 I

'af if10 UtHUXf 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes All Pathways

DOSE: Fe-55, All Pathways Summed 1.OOE+OO 9.OOE-01 8.OOE-01 I 11 I1111 111 XI 7.OOE-01 6.OOE-01 I-l~ 5.OOE-OI E

4.OOE-01 5.OOE-01 3.OOE-01 =X I 2.OOE-01 :E to =E t EI/

I .OOE-01 O.OOE+01 I 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Includes All Pathways

DOSE: H-3, All Pathways Summed 1.OOE X 9.OOE-06 ---

8.OOE-06 -

7.OOE-06 --

6.OOE-06 -.-

E 4.OOE-06 3.OOE-06 -.-

2.OOE-06 - - -- Year 1.OOE-06 - - -- _

O.OOE+01 1 10 100 1000 Years CYUSEIC.RAD 0813012004 14:42 Indludes All Pathways

DOSE: Mn-54, All Pathways Summed 3.00E-25 2.50E-25 2.00E-25 a, 1.50E-25 E

1 .OOE-25 5.00E-26 0.OOE+01 1 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes All Pathways

DOSE: Nb-94, All Pathways Summed 1.0 -- _ _

0.9 . _ _ __ - -

0.8-0.7- --- ---

0.6-oo.51 1- - ram _ _5 -

0.4-0.3 --- _ _-

0.2 - -_ _ -- -- 1 0 .1 -- _ _ _ _ _ _-

0.0 -- _ _ _ _

1 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes All Pathways

DOSE: NT-63, All Pathways Summed 1 .OOE+OO 9.OOE-01 8.OOE-01 7.00E-01 X0 an E~.L 6.OOE-01 i 5.OOE-01 4.OOE-01 1~~~~

X- fi X 3.OOE-01 2.OOE-01 1 .OOE-01

_- %I I9E IX O.OOE+01 I 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes All Pathways

DOSE: Pu-238, All Pathways Summed 2.50E-06 2.OOE-06 1.50E-06 I..

E 1.OOE-06 ~~ LI ~tLX 5.OOE-07 O.OOE+01 I 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 indudes All Pathways

DOSE: Pu-239, All Pathways Summed 1.00E+00 9.OOE-01 8.OOE-01 7.OOE-01 6.OOE-01 =-~~ I==

i 5.OOE-01 4.OOE-01 3.OOE-01 E~ ~ I 2.OOE-01 1.00E-01 O.OOE+01 I 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Includes All Pathways

DOSE: Pu-241a, All Pathways Summed 1.00E+00 9.OOE-01 8.00E-01 4~II~~l

~ ~~ I1 0: 11 7.OOE-01 6.00E-01 L..

i 5.00E-01 4.00E-01 3.OOE-01 _ _=I IIID 2.00E-01 1.OOE-01 0.00EI01 1

XI 10 A 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes Al Pathways

DOSE: Pu-241b, All Pathways Summed 1.OOE+00 9.OOE-01 8.OOE-01 7.OOE-01 6.00E-01 2 5.00E-01 4.00E-01 3.OOE-01 2.00E-01 1.00E-01 lI

.~~~' aL1 O.OOE+01 I 10 100 1000 Years CYJUSEIC.RAD 08/30/2004 14:42 Includes All Pathways

DOSE: Sr-90, All Pathways Summed 1.OOE+00 9.OOE-01 8.OOE-01 7.OOE-01 S-6.OOE-01 lI l

I~~~~~'

IZZZZIIZ

- 5.OOE-01 E

4.OOE-01 3.OOE-01

~~~~IT T T0 2.OOE-01 1.00E-01 O.OOE+O1 I 10 100 1000 Years CYUSEIC.RAD 08/30/2004 14:42 Indudes All Pathways

DOSE: Tc-99, All Pathways Summed 0.25 0.20 0.15 E

0.10 0.05 0.00 I 10 100 1000 Years CY_USEIC.RAD 08/30/2004 14:42 Indudes AM Pathways

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill APPENDIX B RESRAD Report of Input Parameters and Resultant TEDE for Resident Farmer Disposal Scenario

RESRAD, Version 6.22 To Limit - 30 days 08/30/2004 14:42 Page 1 Summary : Haddam Neck Material at USEI File: CYJUSEIC.RAD Table of Contents Part I: Mixture Sums and Single Radionuclide Guidelines Dose Conversion Factor (and Related) Parameter Summary ... 2 Site-Specific Parameter Summary ..... ..................... a Summary of Pathway Selections ...... ...................... 17 Contaminated Zone and Total Dose Summary .... .............la Total Dose Components Time - O.OOOE+00 .......... .......................... 21 Time - 1.000E+C0 .......... .......................... 23 Time - 3.OOOE+00 ......... ........................... 25 Time - 1.OOOE+01 .......... .......................... 27 Time - 3.OOOE+01 .......... .......................... 29 Time - 1.000E+02 ........ ............................ 31 Time - 3.000E+02........I ...... 33 Time - 1.000E+03 ....... ............................. 35 Dose/Source Ratios Summed Over All Pathways .... ..........37 Single Radionuclide Soil Guidelines ..... .................

39 Dose Per Nuclide Summed Over All Pathways .... ............41 Soil Concentration Per Nuclide ...... ..................... 43

RESRAD, Version 6.22 T' Limit - 30 days 08/30/2004 14:42 Page 2 Summary : Haddam Neck Material at USEI File: CYUSEIC.RAD Dose Conversion Factor (and Related) Parameter Summary File: HEAST 1995 Morbidity 1 Current Parameter Menu I Parameter Value Default l Name

.1-B-1 l Dose conversion factors for inhalation, mrem/pCi:

B-1 l Ac-227+D l 6.720E+OO 6.720E+00 l DCF2( 1)

B-1 l Ag-lOBm+D l 2.830E-04 2.830E-04 l DCF2l 2)

B-1 l Ar.-241 l4.440E-Ol 4.440E-01 l DCF2( 3)

B-i l Am-243+D l 4.400E-Oi 4.400E-01 l DCF2( 4)

B-I I C-14 l 2.090E-06 2.090E-06 l DCF2) 5)

B-1 C Cm-243 l 3.070E-01 3.070E-O1 l DCF2( 6)

B-I I Co-60 l 2.190E-04 2.190E-04 l DCF2( 8)

B-1 I Cs-134 l 4.630E-05 4.630E-05 l DCF2( 9)

B-1 l Cs-137+D l 3.190E-05 3.190E-05 l DCF2 (10)

B-1 l Eu-152 l 2.21OE-04 2.210E-04 l DCF2 (11)

B-1 l Eu-154 l 2.860E-04 2.860E-04 1 DCF2 (13)

B-1 l Eu-155 l 4.14OE-05 4.140E-05 l DCF2 (14)

B-1 l Fe-55 l 2.690E-06 2.690E-06 l DCF2 (15)

B-l l Gd-152 l 2.430E-Ol 2.430E-01 l DCF2 (16)

B-l H-3 1 6.400E-08 6.400E-08 l DCF2(17)

B-1 l Hn-54 l 6.700E-06 6.700E-06 l DCF2 (18)

B-l l Nb-94 l 4.140E-04 4.140E-04 l rCF2 (19)

B-1 l Ni-63 6.290E-06 6.290E-06 l DCF2 (20)

B-i l Np-237+D 5.400E-Ol 5.400E-01 l DCF2(21)

B-i l Pa-231 l 1.280E+0O 1.280E+00 l DCF2 (22)

B-i l Pb-210+D l 1.380E-02 1.380E-02 l DCF2 (23).

B-i l Po-210 I 9.400E-03 9.400E-03 l DCF2 (24)

B-i l Pu-238 l 3.920E-O1 3.920E-01 l DCF2 (25)

B-i l Pu-239 l 4.290E-01 4.290E-01 l DCF2 (26)

B-i I Pu-241+D I 8.250E-03 8.250E-03 l DCF2 (27)

B-i l Ra-226+D l 8.600E-03 a. 600E-03 I DCF2 (29)

B-i l Sr-90+D l 1.310E-03 1.310E-03 l DCF2 (301 B-i TC-99 l 8.330E-06 8.330E-06 l DCF2 (311 B-i Th-229+D l 2.160E+00 2.160E+00 l DCF2 (32)

B-i l Th-230 l 3.260E-01 3.260E-01 l DCF2 (33)

B-1 ! U-233 l 1.350E-01 1.350E-01 l DCF2 (34)

B-1 l V-234 i 1.320E-01 1.320E-01 l DCF2 (35)

B-i l U-235+D l 1.230E-01 1.230E-01 l DCF2(36)

D-1 l Dose conversion factors for ingestion, mrem/pC':

D-1 Ac-227+D l 1.480E-02 1.480E-02 l DCF3( 1)

D-1 l Ag-108m+D l 7.620E-06 7.620E-06 l DCF3 2)

D-1 l Am-241 l 3.640E-03 3.640E-03 l DCF3( 3)

D-1 l Am-243+D 3.630E-03 3.630E-03 l DCF3( 4)

D-1 I C-14 l 2.090E-06 2.090E-06 l DCF3( 5)

D-1 I Cm-243 l 2.510E-03 2.510E-03 l DCF3( 6)

D-1 I Co-60 l 2.690E-05 2.690E-05 l DCF3( 8)

D-1 I Cs-134 l 7.330E-05 7.330E-05 l DCF3( 9)

D-1 I Cs-137+D l 5.000E-05 5.000E-05 l DCF3 (10)

D-1 I Eu-152 l 6.480E-06 6.480E-06 l DCF3(11) 0-1 I Eu-154 l 9.550E-06 9.550E-06 l DCF3 (13)

D-1 I Eu-155 l 1.530E-06 1.530E-06 l DZF3(14)

D-1 I Fe-55 l 6.070E-07 6.070E-07 l DCF3 (15)

D-1 I Gd-152 l 1.610E-04 1.610E-04 l DCF3 (16)

D-1 l H-3 l 6.400E-08 6.400E-08 l DCF3 (17)

RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 3 Summary : Haddam Neck Material at USEI File: CYUSEIC.RAD Dose Conversion Factor (and Related) Parameter Summary (continued)

File:HEAST 1995 Morbidity Current Parameter Menu I Parameter Value Default I Name l I D-1 Mn-54 2.770E-06 2.770E-06 i DCF3(18)

D-1 I Nb-94 7.140E-06 7.140E-06 ; DCF3(19)

D-1 I Ni-63 5.770E-07 5.770E-07 l DCF3(20)

D-1 N Np-237+D 4.440E-03 4.440E-03 I DCF3(21)

D-1 Pa-231 1.060E-02 1.060E-02 DCF3(22)

D-1 I Pb-210+D 5.370E-03 5.370E-03 DCF3 (23)

D-1 I Po-210 1.900E-03 1.900E-03 i DCF3(24)

D-1 I Pu-238 3.200E-03 3.200E-03 i DCF3(25)

D-1 I Pu-239 3.540E-03 3.540E-03 l DCF3(26)

D-1 I Pu-241+D 6.850E-05 6.850E-05 I DCF3(27)

D-1 I Ra-226+D 1.330E-03 1.330E-03 i DCF3(29)

D-1 I Sr-90+D 1.530E-04 1.530E-04 l DCF3(30)

D-1 i Tc-99 1.460E-06 1.460E-06 i DCF3(31)

D-1 T Sh-229+D 4.030E-03 4.030E-03 l DCF3(32)

D-1 I Th-230 5.480E-04 5.480E-04 l DCF3(33)

D-1 I U-233 2.890E-04 2.890E-04 l DCF3(34)

D-1 U U-234 2.830E-04 2.830E-04 l DCF3(35)

D-1 U U-235+D 2.670E-04 2.670E-04 DCF31(36)

D-34 Food transfer factors:

D-34 I Ac-2227+D plant/soil concentration ratio, dimensionless 2.500E-03 2.500E-03 l RTF( 141)

D-34 I Ac-2227+D beef/livestock-intake .ratio, (pCi/kg)/(pCi/d) 2.000E-05 2.000E-05 , RTF( 1,2.)

D-34 I Ac-2227+D milk/livestock-intake ratio, IpCi/L)/(pCi/d) 2.000OE-05 2.000E-05 l RTF( 1,3)

D-34 I I . I D-34 I Ag-i0)Om+DD, plant/soil concentration ratio, dimensionless I 1.500E-01 1.500E-01 l RTF( 2,1)

D-34 I Ag-lC)Bm+E , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 3.OOOE-03 3.000E-03 l RTFI 2,2)

D-34 I Ag-iC)8m+C , milk/livestock-intake ratio, (pCi/L)/(pCi/d) I 2.500E-02 2.500E-02 l RTF( 2,3)

D-34 I D-34 I Am-24L1 ,plant/soil concentration ratio, dimensionless 1.000E-03 1.OOOE-03 l RTF( 3,1)

D-34 I Am-24!1 ,beef/livestock-intake ratio, (pCi/kg)/I(p.i/d) 5.000E-05 5.000E-05 , RTF( 3,2)

D-34 Am-24 11 ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 2.000E-06 2.OOOE-06 lRTF( 3,3)

D-34 I I I D-34 Am-24!3+D ,plant/soil concentration ratio, dimensionless 1.00E-03 1.OOOE-03 , RTF( 4,1)

D-34 IA-2413+D ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 5.000E-05 I 5.000E-05 RTF( 4,2)

D-34 I Am-2413+D ,milk/livestock-intake ratio, (pCi/L)/CpCi/d) 2.000E-06 I 2.000E-06 i RTF( 4,3)

D-34 l I I D-34 I C-14 ,plant/soil concentration ratio, dimensionless 5.500E+00 5.500E+00 I RTF( 5,1)

D-34 I C-14 ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 3.100E-02 3.100E-02 l RTF( 5,2)

D-34 I C-14 ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 1.200_-02 1.200E-02 l RTF( 5,3)

D-34 I I . I D-34 Cm-2413 ,plant/soil concentration ratio, dimensionless I.OOOE-03 1.OOOE-03 I RTF( 6,1)

D-34 Cm-2413 C ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) I 2.000E-05 I 2.000E-05 i RTFI 6,2)

D-34 Cm-2413 ,milk/livestock-intake ratio, JpCi/L)/1pCi/d) 2.000E-06 2.000E-06 ilRTFI 6,3)

D-34 l I I D-34 I Co-6C ,pla'nt/soil concentration ratio, dimensionless 8.000E-02 8.000E-02 I RTFI 8,1)

D-34 I Co-6C ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 2.OOOE-02 2.000E-02 ! RTF( 8,2)

D-34 I Co-6( ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 2.OOOE-03 2.000E-03 I RTF( 8,3)

D-34 I I I D-34 C Cs-I:.34 ,plant/soil concentration ratio, dimensionless 4.OOOE-02 4.000E-02 RTF( 9,1)

D-34 I Cs-l'.34 ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 3.000E-02 3.000E-02 ' RTFI 9,2)

D-34 Cs-1i34 ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 8.000E-03 8.000E-03 I RTFI 9,3)

RESRAD, Version 6.22 Tn Limit - 30 days 08/30/2004 14:42 Page 4 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Dose Conversion Factor (and Related) Parameter Summary (continued)

File: HEAST 1995 Morbidity Current Parameter Menu I Parameter Value Default l Name l

D-34 l Cs-137?+D , plant/soil concentration ratio, dimensionless l 4.000E-0:2 1.000E-02 l RTF(10,1)

D-34 l Cs-13D1+D , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 3.000E-0: a E3.000E-02 l RTF(10,2)

D-34 l Cs-13DI+D , milk/livestock-intake ratio, (pCi/L)/(pCi/d) I 8.000E-0:3 e .OOOE-03 l RTF(10,3)

D-34 l D-34 E Eu-15 , plant/soil concentration ratio, dimensionless I 2.500E-0: 2.500E-03 l RTF(11,l)

D-34 l Eu-15i , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 2.000E-0: 2.000E-03 l RTF(11,2)

D-34 l Eu-15: , milk/livestock-intake ratio, (pCi/L)/(pCi/d) l 2.000E-0' 5 2.OOOE-05 l RTF11,3)

D-34 l D-34 l Eu-154 , plant/soil concentration ratio, dimensionless l 2.500E-0: 2.500E-03 l RTF(13,1) 3 D-34 l Eu-154 , beef/livestock-intake ratio, IpCi/kg)/(pCi/d) l 2.OOOE-0: 2.000E-03 l RTF(13,2)

D-34 l Eu-154 , milk/livestozck-intake ratio, IpCi/L)/IPCi/d) l 2.000E-Q'5 2.000E-05 l RTF113,3)

D-34 l D-34 l Eu-15'2 , plant/soil concentration ratio, dimensionless l 2.500E-0: 3 2.500E-03 l RTF(14,1)

D-34 l Eu-15'2 , beef/livestock-intake ratio, (pCi/kg)/CpCi/d) I 2.OOOE-0: 3 2.000E-03 l RTF(14,2)

D-34 l Eu-15'2 , milk/livestock-intake ratio, (pCi/L(/(pCi/d) l 2.000E-0!5 2.000E-05 l RTF(14,31 D-34 l D-34 l Fe-55 , plant/soil concentration ratio, dimensionless l l.OOOE-0: 3 1.OOOE-03 l RTF(15,l)

D-34 l Fe-55 , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 2.000E-0: 2 2.000E-02 l RTF(15,2)

D-34 l Fe-55 , milk/livestock-intake ratio, (pCi/L)/(pCi/d) l 3.OOOE-0 4 3.000E-04 l RTF(15,3)

D-34 l I D-34 l Gd-15: , plant/soil concentration ratio, dimensionless l 2.500E-0 3 2.500E-03 l RTF(1611)

D-34 l Gd-15; , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 2.000E-0 3 2.000E-03 l RTF(16,2)

D-34 l Gd-15: , milk/livestock-intake ratio, (pCi/L)/IpCi/d) l 2.000E-0 5 2.000E-05 l RTF(16,3)

D-34 l D-34 l B-3 , plant/soil concentration ratio, dimensionless 4.800E+0 0 4.800E+00 l RTF(l17,1)

D-34 l H-3 , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 1.200E-0 2 1.200E-02 l RTF(17,2)

D-34 l B-3 , milk/livestock-intake ratio, (pCi/L)/(pCi/d) l 1.000E-0 2 1.OOOE-02 l RTF(17,31 D-34 l D-34 l Mn-54 , plant/soil concentration ratio, dimensionless l 3.000E-0 1 3.000E-01 l lRTF(18,1)

D-34 l Mn-54 , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 5.000E-0 4 5.000E-04 l RTF(16,2)

D-34 l Mn-54 , milk/livestock-intake ratio, (pCi/L)/(pCi/d) l 3.000E-0 4 3.000E-04 l RTF(18,3)

D-34 l 0-34 l Nb-94 , plant/soil concentration ratio, dimensionless l 1.000E-0 2 1.000E-02 l RTF1l9,1)

D-34 l Nb-94 , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 3.000E-0 7 3.000E-07 l RTF(19,2)

D-34 l Nb-94 , milk/livestock-intake ratio, (pCi/L)/(pCi/d) 2.000E-0 6 2.000E-06 l RTF(19,3)

D-34 l D-34 l Ni-63 , plant/soil concentration ratio, dimensionless I5.000E- 2 5.000E-02 l RTF(20,1)

D-34 l Ni-63 , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 5.000E-0 3 5.000E-03 l RTF(20,2)

D-34 l Ni-63 , milk/livestock-intake ratio, (pCi/L)/(pCi/d) l 2.000E-0 2 2.000E-02 l RTF(20,31 D-34 l D-34 l Np-23 7+D , plant/soil concentration ratio, dimensionless l 2.000E-0 2 2.000E-02 l RTF(21,1)

D-34 l Np-23 7+D , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) I1.000E-0 3 1.000E-03 l RTF(21,2)

D-34 l Np-23 7+D , milk/livestock-intake ratio, (pCi/L)/(pCi/d) I5.000E-0 6 5.000E-06 l RTF(21,3)

D-34 l D-34 l Pa-23 1 , plant/soil concentration ratio, dimensionless l 1.000E-0 2 1.OOOE-02 l RTF(22,1)

D-34 l Pa-23 1 , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 5.000E-0 03 5.000E-03 l lRTF(22,2)

D-34 l Pa-23 1 , milk/livestock-intake ratio, (pCi/L)/lpCi/d) l 5.000E-0 06 5.000E-06 l RTF(22,31 D-34 l D-34 l Pb-21 O+D , plant/soil concentration ratio, dimensionless l 1.OOOE-C 12 1.OOOE-02 RTF(23,1)

D-34 l Pb-21 O+D , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l 5.000E-C04 8.000E-04 l RTF(23,2)

D-34 l Pb-21 0+0 milk/livestock-intake ratio, (pCi/L)/(pCi/d) l 3.OOOE-C 04 3.OOOE-04 RTF(23,3)

RESRAD, Version 6.22 Tn Limit - 30 days 08/30/2004 14:42 Page 5 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Dose Conversion Factor (and Related) Parameter Summary (continued)

File: HEAST 1995 Morbidity Current I I Parameter Menu I Parameter Value Default Name D-34 Po-2110 , plant/soil concentration ratio, dimensionless 1.OOOE-03 l 1.000E-03 l RTFI24,l)

D-34 l Po-2110 ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 5.000E-03 l 5.000E-03 l RTF124,2)

D-34 l Po-2110 , milk/livestock-intake ratio, (pCi/L)/(pCi/d) 3.400E-04 3.400E-04 l RTF(24,3)

D-34 l D-34 l Pu-231B ,plant/soil concentration ratio, dimensionless l.OOOE-03 1.OOOE-03 l RTF(25,1)

D-34 l Pu-231B , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 1.OOOE-04 1.OOOE-04 l RTF(25,2)

D-34 l Pu-231B ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 1.OOOE-06 l l.OOOE-06 l RTF(25,3)

D-34 l D-34 l Pu-23 9 , plant/soil concentration ratio, dimensionless 1.OOOE-03 1.OOOE-03 l RTF(26,1)

D-34 l Pu-23 9 ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 1.OOOE-04 l 1.OOOE-04 l RTFt26,2)

D-34 l Pu-23!9 ,milk/livestock-intake ratio, (pCi/L)/(pCi/dI 1.0005-06 l.OOOE-06 l RTF(26,3)

D-34 l D-34 l Pu-24:1+D ,plant/soil concentration ratio, dimensionless 1.OOOE-03 l 1.OOOE-03 l RTF(27,1)

D-34 l Pu-24:1+D ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 1.000E-04 l.OOOE-04 l RTF127,2)

D-34 l Pu-24:1+D ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 1.0005-06I l.OOOE-06 l RTF(27,3)

D-34 l D-34 l Ra-221S+D ,plant/soil concentration ratio, dimensionless 4.OOOE-02 l 4.000E-02 l RTF(29,1)

D-34 l Ra-2216+0 ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l.OOOE-061 1.OOOE-03 l l.OOOE-03 l RTF(29,2)

D-34 l Ra-22 6+D ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 1.000E-03 1.OOOE-03 l RTF(29,3)

D-34 l D-34 l Sr-90 4*D ,plant/soil concentration ratio, dimensionless 3.000E-02 l 3.000E-01 l RTF(301)

D-34 l Sr-90-4*D , beef/livestock-intake ratio, (pCi/kg)/(pCi/d) l.OOOE-03 l 8.000E-03 I RTF(30,2)

D-34 l Sr-90 #-D ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 2.OOOE-03 l 2.000E-03 l RTF(30,.3) 1.000E-04 l D-34 l D-34 l Tc-99 ,plant/soil concentration ratio, dimensionless 5.000E+00 l RTF(31,1)

D-34 l Tc-99 ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 1.000E-04 I RTF(31,2)

D-34 l Tc-99 ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 1.000E-03 l 1.000E-03 I RTF(31,3)

D-34 l D-34 l Th-22!9+D , plant/soil concentration ratio, dimensionless 1.000E-03 l 1.000E-03 l RTF(32,1)

D-34 l Th-22!9+D ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 1.0005-04 1.OOOE-04 l RTF132,2)

D-34 l Th-22.9+0 ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 5.000E+-06 5.000E-06 l RTF132,3)

D-34 l D-34 l Th-2310 ,plant/soil concentration ratio, dimensionless 1.0005-03 1.000E-03 l RTF(33,1)

D-34 l Th-2310 ,beef/livestock-intake ratio, CpCi/kg)/(pCi/d) l.OOOE-04 l 1.000E-04 l RTF(33,2) l.OOOE-04l D-34 l Ih-231 0 ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 5.OOOE-06 l 5.000E-06 RTF(33,3)

D-34 l D-34 U U-233 ,plant/soil concentration ratio, dimensionless 2.500E-03 l 2.500E-03 RTF(34,1)

D-34 U U-233 ,beef/livestock-intake ratio, (pCi/kg)/CpCi/d) 3.4005-04 3.400E-04 j RTF134,2)

D-34 U U-233 , milk/livestock-intake ratio, (pCi/L)/(pCi/d) 6.000E-04 I RTF134,3)

D-34 l D-34 U U-234 ,plant/soil concentration ratio, dimensionless 2.500E-03 2.500E-03 l RTF(35,1)

D-34 U-234 ,beef/livestock-intake ratio, CpCi/kgl/(pCi/d) 3.400E-04 3.400E-04 l RTF(35,2)

D-34 U U-234 ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 6.000E-04 l 6.000E-04 l RTF(35,3)

Z-34 D-34 U-235 +D U ,plant/soil concentration ratio, dimensionless 2.500E-03 l 2.500E-03 I RTF(36,1)

D-34 U-235 +D U ,beef/livestock-intake ratio, (pCi/kg)/(pCi/d) 3.400E-04 l 3.400E-04 l RTF(36,2)

D-34 U-235 +D U ,milk/livestock-intake ratio, (pCi/L)/(pCi/d) 6.000E-04 l 6.000E-04 I RTF(36,3)

D-5 I Bioaccumulation factors, fresh water, L/kg:

D-5 I Ac-227+D , fish 1.500E+01 l 1.500E+01 l 9IOFAC( 1,1)

D-5 I Ac-227+D , crustacea and mollusks 1.000E+03 l 1.000E+03 l BIOFAC( 1,2)

RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 6 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Dose Conversion Factor (and Related) Parameter Summary (continued)

File: HEAST 1995 Morbidity Current I Parameter Menu I Parameter Value Default Name D-5 I Ag-108m+D, fish 5.000E+00 l 5.OOOE+00 l BIOFAC( 2,1)

ID-5 I Ag-108m+D, crustacea and mollusks l 7.700E+02 l 7.700E+02 l BIOFACI 2,2)

Q-5 I I I D-5 I Am-241 , fish l 3.OOOE+01 l 3.000E+01 l BIOFAC( 3,1)

D-5 I Am-241 , crustacea and mollusks l 1.OOOE+03 l 1.000E+03 l BIOFAC( 3,2)

D-5 I I D-5 I Am-243+D , fish l 3.OOOE+01 l 3.000E+01 l BIOFAC( 4,11 D-5 I Am-243+D , crustacea and mollusks l 1.OOOE+03 l 1.000E+03 l BIOFAC( 4,2)

D-5 I I I D-5 I C-14 , fish l 5.0O0E+04 l 5.OOOE+04 l BIOFAC( 5,1)

D-5 I C-14 , crustacea and, mollusks l 9.100E+03 l 9.100E+03 l BIOFAC( 5,2)

D-5 I I I D-5 I Cm-243 , fish l 3.OOOE+01 l 3.000E+01 l BIOFAC( 6,1)

D-5 l Cm-243 , crustacea and mollusks I 1.000E+03 l 1.000E+03 l BIOFAC( 6,2)

D-5 I D-5 I Co-60 , fish l 3.OOOE+02 l 3.000E+02 l BIOFACI 8,1)

D-5 1Co-60 , crustacea and mollusks l 2.000E+02 l 2.000E+02 l BIOFAC( 8,2)

D-5 I I I

,-5 I Cs-134 , fish l 2.000E+03 l 2.000E+03 l BIOFAC( 9,1)

D-5 I Cs-134 , crustacea and mollusks I 1.000E+02 l 1.000E+02 l BIOFAC( 9,2)

D-5 I I D-5 I Cs-137+ D , fish l 2.000E+03 l 2.000E+03 l BIOFACl10,1)

D-5 I Cs-137+ D , crustacea and mollusks l 1.000E+02 l 1.000E+02 l BIOFACL10,2)

D-5 I I I D-5 I Eu-152 , fish l 5.000E+01 l 5.000E+01 l BIOFACall,l)

D-5 I Eu-152 , crustacea and mollusks l 1.000E+03 l 1.000E+03 l BIOFACC11,2)

D-5 I I I D-5 I Eu-154 , fish l 5.000E+01 l 5.000E+01 l BIOFACC13,1)

D-5 I Eu-154 , crustacea and mollusks l 1.OOOE+03 l 1.000E+03 BIOFAC(13,2)

D-5 I I I 1-D-5 I Eu-155 , fish l 5.000E+01 l 5.000E+01 l BIOFAC(14,1)

D-5 lIEa-155 , crustacea and mollusks l 1.000E+03 l 1.000E+03 l BIOFAC(14,2)

D-5 I I I D-5 I Fe-55 , fish l 2.000E+02 l 2.000E+02 l BIOFAC(15,1)

D-5 lIFe-55 , crustacea and mollusks l 3.200E+03 l 3.200E+03 l BIOFAC(15,2)

D-5 I I I 0-5 I Gd-152 f'sh l 2.500E+01 l 2.500E+01 l BIOFAC(16,1)

D-5 lIGd-152 , crustacea and mollusks l 1.000E+03 l 1.000E+03 l BIOFAC(16,2)

D-5 I I I D-5 I H-3 , fish l 1.000E+00 l 1.000E+00 l BIOFAC(17,1)

D-5 l H-3 , crustacea and mollusks l 1.000E+00 l 1.000E+00 l BIOFAC(17,2)

D-5 I I I D-5 l Mn-54 , fish l 4.000E+02 l 4.000E+02 BIOFACC18,1)

D-5 lIMn-54 , crustacea and mollusks l 9.OOOE+04 l 9.000E+04 l BIOFAC118,2)

D-5 I I .I D-5 I Nb-94 , fish l 3.000E+02 l 3.000E+02 l BIOFAC(19,1)

D-5 lINb-94 , crustacea and mollusks l 1.000E+02 l 1.000E+02 l BIOFAC(19,2)

D-5 I I I D-5 I Ni-63 , fish l 1.000E+02 l 1.000E+02 l BIOFAC(20,1)

D-5 lINi-63 , crustacea and mollusks l 1.000E+02 1.000E+02 l BIOFAC(20,2)

D-5 I I I

RESRAD, Version 6.22 T' Limit - 30 days 08/30/2004 14:42 Page 7 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Dose Conversion Factor land Related) Parameter Summary (continued)

File: HEAST 1995 Morbidity I Current I Parameter Menu I - Parameter I Value I Default I Name II i I D-5 I Np-237+D , fish l 3.000E+01 l 3.000E+01 l BIOFAC(21,1)

D-5 I Np-237+D , crust :acea and mollusks l 4.000E+02 l 4.000E+02 l BIOFAC(21,2)

D-5 I I I D-5 I Pa-231 , fish l 1.000E+01 l 1.000E+01 l BIOFAC(22,1)

D-5 I Pa-231 , crust:acea and mollusks l 1.100E+02 l 1.100E+02 l BIOFAC(22,2)

D-5 I I I D-5 I Pb-210+D , fish l3.000E+02 l 3.000E+02 l BIOFAC(23,1) 3.OOOE+02 D-5 I Pb-210+D , crustacea and mollusks l 1.000E+02 l 1.000E+02 l BIOFAC(23,2)

D-5 I D-5 I Po-210 fish 1.000E+02 l BIOFAC(24,1)

I 2.OOOE+04 I 2.000E+04 l BIOFAC(24,2)

D-5 I Po-210 , crustacea and, mollusks D-5 I D-5 I Pu-23B , fish l 3.000E+01 l 3.000E+01 l BIOFAC(25,l)

D-5 I Pu-233 , crustacea and mollusks l 2.000E+02 l 1.000E+02 l BIOFAC(25,2)

D-5 I D-5 I Pu-239 , fish l 3.000E+01 l 3.000E+01 l BIOFAC(26,1)

I I 1.000E+02 1,l 1.000E+02 l BIOFAC(26,2)

D-5 I Pu-239 , crustacea and mollusks D-5 I D-5 I Pu-241+D , fish l 3.000E+01 l 3.000E+01 l BIOFAC(27,I)

I 1.000E+02 I

l 1.000E+02 l BIOFAC(27,2)

D-5 I Pu-241+D , crustacea and mollusks D-5 I l 5.000E+01 l 5.000E+01 l BIOFAC(2.9,1)

D-5 I Ra-226+D , fish I 2.500E+02 lI 2.500E+02 l BIOFAC(29,2)

D-5 I Ra-226+D , crustacea and mollusks D-5 I D-5 I Sr-90+D , fish 6.000E+01 l 6.000E+01 l BIOFAC(30,1)

I I 2.005E+02 lI 1.000E+02 l BIOFAZ(30,2)

D-5 I Sr-90+D , crustacea and mollusks D-5 I D-5 I Tc-99 , fish l 2.000E+01 l 2.000E+01 l BIOFAC(31,1)

D-5 I Tc-99 , crustacea and mollusks I5.OOOE+00 5.000E+00 BIOFAC(31,2)

D-5 D-5 I Th-229+D , fish 1.000E+02 l 1.000E+02 l BIOFAC(32,1)

I I D-5 I Th-229+D , crustacea and mollusks l 5.000E+02 l 5.000E+02 l BIOFAC(32,2)

D-5 D-5 I Th-230 , fish l 1.000E+02 l 1.000E+02 l BIOFACC33,1)

I I D-5 I Th-230 , crustacea and mollusks l 5.000E+02 l 5.OOOE+02 l BIOFACC33,2)

D-5 I D-5 I U-233 , fish l 1.000E+01 l 1.000E+01 l BIOFAC(34,1)

I I 6.000E+01 l BIOFAC(34,2)

D-5 I U-233 ,crustacea and mollusks l 6.000E+01 l D-5 I D-5 IU-234 , fish l 1.000E+01 l 1.000E+01 l BIOFAC(35,1)

Il 6.000E+01 Il 6.000E+01 D-5 IU-234 ,crustacea and mollusks BIDFAC(35,2) l 1.000E+01 l*

D-5 I l 6.000E+01 l D-5 U-235+D , fish 1.000E+01 l BIOFAC(36,l)

D-5 U-235+D , crustacea and mollusks 6.000E+01 l BIOFACC36,2)

KSK.AU, VerSlon b.22 VI Limit - JU days 08/30/2004 14:42 Page 8 Summary : Haddam Neck Material at USEI File: CYUSEIC.RAD Site-Specific Parameter Summary User I I Used by RESRAD I Parameter Menu I Parameter Input I Default I (If different from user inpuit) l Name R011 l Area of conta-inated zone (m**2) 9.000E+02 l.000E+04 l AREA R011 l Thickness of contaminated zone (m) 3.360E+0l 2.000E+00 l THICKO Roll l Length parallel to aquifer flow (m) 3.385E+0l 1.OOOE+02 l LCZPAQ R011 l Basic radiation dose limit (mrem/yr) 5.OOOE+00 2.500E+01 l BRDL R011 l Time since placement of material (yr) O.OOOE+00 0. OOOE+00 TI R011 l Times for calculations (yr) 1.OOOE+00 l.OOOE+00 l T( 2)

Ro011 Times for calculations (yr) 3 .000E+00 3.000E+00 l T( 3)

Ro011 Times for calculations (yr) 1.OOOE+01 1.OOOE+01 l T( 4)

R011 l Times for calculations (yr) 3.000E+01 3.000E+01 T( 5)

Ro011 Times for calculations lyr) l.000E+02 1.0O0E+02 l T( 6)

Roll l Times for calculations (yrl 3.000E+02 3.000E+02 l T( 7)

Ro011 Times for calculations (yrl 1.OOOE+03 1.0OOO+03 l T( 8)

Roll l Times for calculations (yrI not used O.OOOE+00 l T( 9)

R011 l Times for calculations (yr) not used O.OOOE+00 l T(10)

R012 l Initial principal radionuclide (pCi/g) Ag-lOem 1.OOOE+00 0.OOOE+00 ___ SI1( 2)

RP012 l Initial principal radionuclide (pci/g) Am-241 1. OOOE+00 0. OOOE+00 SI1(3)

R012 l Initial principal radionuclide (pCi/g) C-14 1.000E+00 0. OOOE+00 SI1(5)

R012 l Initial principal radionuclide (pCi/g): Cr.-243 1. 000E+00 0. OOOE+00 ___

S1( 6)

R012 l Initial principal radionuclide (pCi/g): Co-60 1.OOOE+00 O.OOOE+00 ___

Si( 8)

R012 l Initial principal radionuclide (pCi/gI: Cs-134 1.000E+00 O.OOOE+00 ISI( 9)

Slaog)

R012 l Initial principal radionuclide (pCi/g) : Cs-137 1.000E+00 O.OOOE+00 I51(10)

R012 l Initial principal radionuclide (pCi/g): Eu-152 1.000E+00 0.000+OO ISlull)

R012 l Initial principal radionuclide (pCi/g): Eu-154 1.OOOE+00 0.OOOE+00 Sl(13)

R012 l Initial principal radionuclide (pCi/g) Eu-155 1.OOOE+00 0.000E+00 ___

Sl(14)

R012 l Initial principal radionuclide (pCi/g): Fe-55 1.OOOE+00 0.OOOE+00 ___

S1(15)

R012 l Initial principal radionuclide (pci/g): H-3 1.OOOE+00 0.0OOOE+00 51S(17)

Ro012 Initial principal radionuclide (pCi/g) : Mn-54 1.000E+00 0.OOOE+00 51(18)

R012 l Initial principal radionuclide (pci/g): Nb-94 1.OOOE+00 O.OOOE+00 __ _

I51119)

R012 l Initial principal radionuclide (pCi/g): Ni-63 1.OOOE+00 0.000£+00 _ __

S1(20)

R012 l Initial principal radionuclide (pCi/g): Pu-238 l.OOOE+00 0.000E+00 _ __

51(25)

R012 l Initial principal radionuclide (pCi/g): Pu-239 1.OOOE+00 O.OOOE+00 51(26)

R012 Initial principal radionuclide (pCi/g): Pu-241 1.OOOE+00 O.OOOE+OO 51(27)

R012 l Initial principal radionuclide (pci/g): Sr-90 1.000E+00 O.OOOE+00 S1(30)

R012 l Initial principal radionuclide (pci/g): Tc-99 1.OOOE+00 0.000E+00 ___

S1(31)

R012 l Concentration in groundwater (pCi/L: Ag-108m not used O.OOOE+OO W1( 2)

RP012 l Concentration in groundwater (pCi/LI: Am-241 not used 0.OOOE+00 ___

WI( 3)

R012 l Concentration in groundwater (pCi/L): C-14 not used O.OOOE+00 ___

WI( 5)

R012 Concentration in groundwater IpCi/L): Cm-243 not used O.OOOE+00 ___

Wil 6)

R012 Concentration in groundwater (pCi/L): Co-60 not used O.OOOE+00 W1( 8)

R012 l Concentration in groundwater (pCi/L): Cs-134 not used O.OOOE+00 WI( 9)

R012 l Concentration in groundwater (pCi/L): Cs-137 not used O.OOOE+00 Wl(10)

R012 l Concentration in groundwater (pCi/L) Eu-152 not used O.OOOE+00 R012 Concentration in groundwater [pCi/L) Eu-154 not used O.OOOE+00 W1(13)

R012 l Concentration in groundwater (pCi/L) Eu-155 not used O.OOOE+00 W1(14)

R012 l Concentration in groundwater (pCi /LI Fe-55 not used 0.000E+00 ___

IWlIlS)

R012 l Concentration in groundwater (pCi/L) H-3 not used 0. OOOE+00 W1(17)

R012 l Concentration in groundwater (pCi/L) Mn-54 not used 0.000E+00 W1(18)

R012 l Concentration in groundwater (pCi/L) Nb-94 not used O.OOOE+00 W1 (19)

R012 l Concentration in groundwater (pCi/L) Ni-63 not used O.OOOE+00 W1(20)

R012 l Concentration in groundwater (pCi/L) Pu-238 not used O.OOOE+00 W1(25)

r, version b..z T-r Lmit - ju aays Ue/JU/zUUq L:4z rage S Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Site-Specific Parameter Summary (continued) l l User I I Used by RESRAD l Parameter Menu l Parameter l Input l Default l (If different from user input) l Name I i g I I R012 Concentration in groundwater (pCi/L): Pu-239 l not used l 0.000E+00 l --- l W1(26)

R012 l Concentration in groundwater (pCi/L): Pu-241 not used l O.000E+00 l --- l W1(27)

R012 l Concentration in groundwater (pCi/L): Sr-90 not used l 0.000E+00 l --- l W1(30)

R012 l Concentration in groundwater (pCi/L): Tc-99 l not used l 0.000E+00 l --- l Wl(31)

R013 l Cover depth (n) l 3.600E+00 l 0.000E+00 l --- l COVERS R013 l Density of cover material 1g/c**3) l 1.780E+00 l 1.500E+00 l - DENSCV R013 l Cover depth erosion rate Cm/yr) l 1.000E-04 l 1.000E-03 --- l VCV R013 l Density of contaminated zone (g/cm**3) l 1.500E+00 1.500E+00 l --- l DENSCZ R013 l Contaminated zone erosion rate (m/yr) l 1.000E-03 l 1.000E-03 l --- l VCZ R013 l Contaminated zone total porosity l 4.000E-01 l 4.000E-01 l --- l TPCZ R013 Contaminated zone field capacity l 2.000E-01 l 2.OOOE-01 l --- l FCCZ R013 Contaminated zone hydraulic conductivity (m/yr) l 3.160E+01 l 1.000E+01 l --- l HCCZ R013 l Contaminated zone b parameter l 5.300E+00 l 5.300E+00 l --- l BCZ R013 l Average annual wind speed (m/sec) l 2.000E+00 l 2.000E+00 l - WIND R013 l Humidity in air (g/m*'3) l 8.000E+00 l 8.000E+00 l - HUMID R013 l Evapotranspiration coefficient l 7.500E-01 5.000E-01 l --- l EVAPTR R013 l Precipitation (m/yr) l 1.840E-01 l 1.000E+00 l --- l PRECIP R013 l Irrigation (m/yr) l 2.000E-01 l 2.000E-01 l - RI R013 l Irrigation mode l overhead l overhead l --- l IDITCH R013 Runoff coefficient l 2.000E-01 l 2.000E-01 l --- l RUNOFF R013 l Watershed area for nearby stream or pond (m**2) l 1.000E+06 l 1.000E+06 l --- WAREA R013 l Accuracy for water/soil computations l 1.000E-03 l 1.000E-03 l - EPS R014 Density of saturated zone (g/cm*3) l 1.500E+00 l 1.500E+00 l --- l DENSAQ R014 Saturated zone total porosity l 4.000E-01 l 4.000E-01 l --- l TPSZ R014 l Saturated zone effective porosity l 2.000E-01 l 2.000E-01 l --- l EPSZ R014 l Saturated zone field capacity l 2.000E-01 l 2.000E-01 l --- l FCSZ R014 l Saturated zone hydraulic conductivity (m/yr) l 6.700E+00 l 1.000E+02 l --- l HCSZ R014 l Saturated zone hydraulic gradient l 7.000E-03 l 2.000E-02 l --- l HGWT R014 l Saturated zone b parameter l 5.300E+00 l 5.300E+00 l --- BSZ R014 l Water table drop rate (m/yr) l 1.000E-03 l 1.000E-03 l - VWT R014 l Well pu-p intake depth (m below water table) 1.000E+01 1.000E+01 l --- l DWIBWT R014 l Model: Nondispersion (ND) or Mass-Balance (MB) l ND ND I ___ MODEL R014 l Well pumping rate Cm-*3/yr) l 2.500E+02 l 2.500E+02 l - UT I I I I R015 l Number of unsaturated zone strata I1 l 1 I ___ l NS R015 l Unsat. zone 1, thickness (m) l 6.100E+01 l 4.000E+00 l - lH1)

R015 l Unsat. zone 1, soil density (g/c-**3) l 1.500E+00 l 1.500E+00 l --- l DENSUZ(1)

R015 l Unsat. zone 1, total porosity l 4.000E-01 l 4.000E-01 l ---

l TPUZ(1)

R015 l Unsat. zone 1. effective porosity l 2.000E-01 l 2.000E-01 l --- l EPUZ(1)

R015 Unsat. zone 1, field capacity l 2.000E-01 l 2.000E-01 l --- l FCUZ(1)

R015 l Unsat. zone 1, soil-specific b parameter l 5.300E+00 l 5.300E+00 l --- l BUZ(l)

R015 l Unsat. zone 1, hydraulic conductivity (m/yr) l 1.000E+01 l 1.000E+01 l --- l HCUZ(1)

R016 l Distribution doefficients for Ag-108m I I I R016 l Contaminated zone (cnr*3/g) l 0.000E+00 l O.000E+00 l --- l DCNUCC( 2)

R016 l Unsaturated zone 1 (c=*3/g) l 0.000E+00 l 0.000E+00 l --- l DCNUCUI 2,1)

R016 l Saturated zone (cn--3/g) l 0.000E+00 l 0.000E+00 l - DCNUCS( 2)

R016 l Leach rate (/yr) l 0.000E+00 l 0.000E+00 l 9.964E-03 l ALEACH( 2)

R016 l Solubility constant l 0.000E+00 l 0.000E+00 l not used l SOLUBK( 2)

RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 10 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Site-Specific Parameter Summary Icontinued)

User Used by RESRAD lPa rame te r Menu I Parameter lInput Default (If different from user inputt ) Name I

R016 Distribution coefficients for Am-241 R016 Contaminated zone (cm -3/g) l2.000E+Ol l OOO0E+01 lDCNUCC I 3 i R016 Unsaturated zone 1 (cm -3/g) l2.000E+Ol l2.000E+Ol R016 Saturated zone (cm--3/g) l2.000E+Ol R016 Leach rate (/yr) lO.OOOE+OO l .000E+Ol e . 537E-05 lALEACH ( 3)

R016 Solubility constant lO.OOOE+OO not used lSOLUBK 3) l.

OOOOE+OO R016 Distribution coefficients for C-14 l.

OOOOE+00 R016 Contaminated zone (cm *3/g1 lDCNUCC ( 5)

R016 Unsaturated zone 1 lcmti3/g) l .OOOE+OO l.

OOOOE+OO lDCNUCU ( 5,1 L)

R016 Saeurated zone (cm--3/91 10.000E+00 lO.OOOE+OO lDCNUZS ( 5)

R016 Leach rate (/yr) lO.OOOE+OO lO.OOOE+OO 9.964E-03 lALEACH ( 5)

R016 Solubility constant not used lSOLUBK { 5) l O.OOOE+OO R016 Distribution coefficients for Cm-243 lIO.OOOE+OO R016 Contaminated zone (cm *3/g) 1.378E+03 lDCNUCC ( 6) lIO.OOOE+OO l-1.000E+OO R016 Unsaturated zone 1 (cm--3/g) 1.37BE+03 lDCNUCU ( 6,1 LI I l-1.000E+OO R016 Saturated zone Ic=-*3/g) 1.37BE+03 lDCNUCS ( 6)

I l-1.000E+OO R016 Leacn rate (/yrl 1.250E-06 lALEACH ( 6) l-1.000E+OO lOOOOE+00 R016 Solubility constant not used SOLUBK ( 6)

I_1.OOOE+OO

-1.000E+OO 1OOOOF+03 R016 Distribution coefficients for Co-60 lIO.OOOE+OO R016 Contaminated zone (cm--3/g) lDCNUCC ( SI}

I O.OOOE+OO ll.OOOE+03 Role Unsaturated zone I Icm--3/9) lDCNUZU ( 6,1 1) ll.OOOE+03 R016 Saturated zone (cm--3/g) I lDCNUCS I 8) l .OOOE+03 R016 Leach rate (/yr) lALEACH ( 8) l1.OOOE+03 l.OOOOE+OO R016 Solubility constant lSOLUBK ( 8) l1.OOOE+03 l1.OOOE+03 R016 Distribution coefficients for Cs-134 lO.OOOE+OO 1.722E-06 R016 Contaminated zone (cm--3/9) 1.000-r+03 lDCNUCC ( 9) l .OOOE+OO not used R016 Unsaturated zone I (cm**3/g) ll.OOOE+03 lDCNUCU ( 9, zI1I R016 Saturated zone (cm--3/5) l1.OOOE+03 lDCNUCS ( 9)

R016 Leach rate (/yrl l.OOOOE+OO lALEACH ( 9)

R016 Solubility constant l .OOOE+03 O.OOOE+OO lSOLUBK ( 9) l .OOOE+03 R016 Distribution coefficients for Cs-137 l .OOOE+03 1.722E-06 R016 Contaminated zone (cm -3/9) lO.OOOE+OO ll.OOOE+03 lDCNUCC (10) no: used R016 Unsaturated zone 1 (cm*-3/g) llOOOE+03 lDCNUCU (10 ,: 1 )

R016 Saturated zone ( m-*3/g) 1 O.OOOE+OO ll.OOOE+03 lDCNUZS (10)

R016 Leach rate (/yr) lALEACH {101 R016 Solubility constant l l.OOOE+03 lSOLUBK i101 1 l.OOOE+03 l O.OOOE+OO R016 Distribution coefficients for Eu-152 l l.0OOE+00 l 1.OOOE+00 R016 Coneaminated zone (cn-*3/g) l O.OOOE+OO B8.249E+02 2016 Unsaturated zone 1 (cm*-3/g) l-1.000E+OO lDCNUCU 111, I' I a8.249E+02 R016 Saturated zone (cm--3/g) lDCNUCS (11)

R016 Leach rate (/yr) lO.OOOE+OO 2.087E-06 lALEACH {11)

R016 Solubility constant lO.OOOE+OO not used lSOLUBK X111

XK.~NAD, Version 6.22 T Limit - 30 days 08/30/2004 14:42 Page 11 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Site-Specific Parameter Summary (continued)

User Ij Used by RESRAD l Parameter Menu j Parameter I Input I Default (If different from user input) j Name R016 I Distribution coefficients for Eu-154 I j I I R016 I Contaminated zone (cm=3/g) l-1.000E+00 l-1.O00E+00 I 8.249E+02 j DCNUCC(13)

R016 I Unsaturated zone 1 (cm**3/g) l-1.000E+00 l-1.OOOE+00 I E.249E+02 I DCNUCU(13,1)

R016 Saturated zone (cn*3/g) l-1.000E+00 l-1.000E+00 I 8.249E+02 DCNUCS(13)

R016 I Leach rate (/yr) I 0.000E+00 I 0.000E+00 I 2.OB7E-06 j ALEACH(13)

R016 I Solubility constant I 0.000E+00 I 0.000E+00 I not used I SOLUBK(13)

I .

R016 I Distribution coefficients for Eu-155 I j R016 I Contaminated zone (cm-*3/g) l-1.000E+00 1-1.000E+00 I 8.249E+02 DCNUCC(14)

R016 I Unsaturated zone 1 (cm*3/g) l-1.000E+00 l-1.000E+00 I 8.249E+02 I DCNUCU(14,1)

R016 I Saturated zone (cm**3/g) l-1.000E+00 I-1.000E+00 I 8.249E+02 I DCNUCS(14)

R016 l Leach rate (/yr) O l 0.000E+00 I 0.000E+00 I 2.087E-06 I ALESAH(14)

R016 j Solubility constant j 0.000E+00 I 0.OOOE+00 I not used I SOLUBK(14)

I I R016 I Distribution coefficients for Fe-55 I I I I R016 Contaminated zone (cm**3/g) 1.000E+03 I 1.000E+03 I I DCNUCC(15)

R016 I Unsaturated zone 1 (cm-*3/g) I 1.000E+03 I 1.000E+03 I --- I DCNUCU(15,1)

R016 I Saturated zone (c=-3/g) 1.000E+03 I 1.000E+03 I -- I DCNUCS(15)

R016 I Leach rate (/yr) I 0.000E+00 I 0.000E+00 I 1.722E-06 I ALEACH(15)

R016 I Solubility constant I 0.000E+00 I 0.000E+00 I not used I SOLUBK(15) l I I .I R016 j Distribution coefficients for H-3 Ij I . j R016 j Contaminated zone (=m3/g) I 0.OOOE+00 j 0.000E+00 j --- I DCNUCC(17)

R016 I Unsaturated zone 1 (=-3/g) j 0.000E+00 I 0.000E+00 I --- . DCNUCU(17,1)

R016 I Saturated zone (cm--3/g) I 0.000E+00 j 0.000E+00 j DCNUCS(17)

R016 l Leach rate (/yr) l 0.OOOE+00 l O.000E+00 l 9.964E-03 I ALEACH117)

R016 l Solubility constant I 0.000E+00 0.000E+00 I not used j SOLUBK(17)

I I I R016 I Distribution coefficients for Mn-54 I I I R016 I Contaminated zone (cm*3/g) j 2.0OOE+02 I 2.000E+02 i - DCNUCC(18)

R016 I Unsaturated zone 1 (c=**3/g) I 2.OOOE+02 I 2.000E+02 I --- I DCNUCU(18,11 R016 l Saturated zone (cm*3/g) I 2.000E+02 I 2.000E+02 I --- I CCNUCS(18)

R016 l Leach rate (/yr) I 0.000E+00 I 0.000E+00 I 6.604E-06. I ALEACH(18)

R016 I Solubility constant I 0.000E+00 I 0.000E+00 I not used I SOLUBK(18) l I .

R016 j Distribution coefficients for Nb-94 I I I R016 Contaminated zone (cm=3/g) I 0.000E+00 I 0.000E+00 --- II DCtNUCC(l9)

R016 Unsaturated zone 1 (cm--3/g) I 0.OOOE+00 I 0.OOOE+00 --- Ij DCNUCU(19,1)

R016 j Saturated zone (cm--3/g) I 0.000E+00 I 0.OOOE+00 - I DCNUCS(19)

R016 I Leach rate (/yr) I 0.000E+00 I 0.000E+00 I 9.964E-03 I ALEACH(19)

R016 I Solubility constant I 0.000E+00 I 0.000E+00 I not used I SOLUBK(19)

II I R016 Distribution coefficients for Ni-63 II I R016 I Contaminated zone (cm*3/g) I 1.OOOE+03 I 1.000E+03 --- II DCNUCC(20)

R016 I Unsaturated zone 1 (cm-3/gl I 1.000E+03 I 1.000E+03 --- II OCNUCU(20,1)

R016 I Saturated zdne (cn**3/g) I 1.000E+03 l 1.000E+03 --- II DCNUCS(20)

R016 I Leach rate (/yr) I 0.000E+00 I 0.000E+00 I 1.722E-06 I ALEACH(20)

R016 j Solubility constant j 0.OOOE+00 j 0.000E+00 not used I SOLUBK(20)

Kz.XSKAL,Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 12 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Site-Specific Parameter Summary (continued) l User I Used by RESRAD Parameter Menu l Parameter l Input l Default (If different from user input) Name R016 l Distribution coefficients for Pu-238 I I I

-R016 l Contaminated zone Icm= 3/g) l 2.000E+03 l 2.000E+03 l --- l DCNUCC(25)

R016 l Unsaturated zone 1 (cmn*3/g) l 2.OOOE+03 l 2.000E+03 l - DCNUCU(25,1)

R016 l Saturated zone I c.*3/g) l 2.000E+03 l 2.000E+03 l --- l DCNUCS(25)

R016 l Leach rate (/yr) l 0.000E+00 l 0.000E+00 8.610E-07 l ALEACH(25)

R016 l Solubility constant l 0.000E+00 l 0.000E+00 l not used l SOLUBK(25)

R016 l Distribution coefficients for Pu-239 I I I I R016 l Contaminated zone Ic**3/g) l 2.000E+03 l 2.000E+03 l --- l DCNUCC126)

R016 l Unsaturated zone 1 (cm**3/g) l 2.OOOE+03 l 2.000E+03 j -- l DCNUCU(26,1)

R016 l Saturated zone (cm**3/g) l 2.000E+03 l 2.000E+03 l --- l DCNUCS(26)

R016 l Leach rate (/yr) Il.OOOE+00 l 0.000E+00 l 8.610E-07 l ALEACH(26)

R016 l Solubility constant l 0.000E+00 j 0.000E+00 l not used l SOLUBKC26)

R016 l Distribution coefficients for Pu-241 I I I R016 l Contaminated zone (cm*3/g) l 2.000E+03 l 2.000E+03 l --- l DCNUCC(27)

R016 l Unsaturated zone 1 (c**3/g) l 2.000E+03 l 2.OOE+03 l --- l DCNUCU(27,1)

R016 l Saturated zone Icm**3/g) l 2.000E+03 l 2.000E+03 l --- l DCNUCS(271 R016 l Leach rate l/yr) l 0.000E+00 l 0.000E+00 l 8.610E-07 l ALEACH)271 R016 l Solubility constant 0.000E+00 l 0.000E+00 l not used l SOLUBK)27)

I I I.I R016 l Distribution coefficients for Sr-90 I I l ,

R016 l Contaminated zone ( =m3/g) l 3.000E+01 l 3.000E+01 l --- l DCNUCC(30)

R016 Unsaturated zone 1 (cm 3/g) 3.000E+01 3.000E+01 l - DCNUCU(30,1)

R016 l Saturated zone (c3**3/g) l 3.00OE+01 l 3.000E+01 l - DCNUCS(30)

R016 l Leach rate (/yr) j 0.000E+00 l 0.000E+00 l 5.709E-05 l ALSACH(30)

R016 l Solubility constant l 0.000E+00 l 0.000E+00 l not used l SOLUBK(30)

R016 l Distribution coefficients for Tc-99 I I I R016 l Contaminated zone (crc-3/g) l 0.000E+00 l 0.000E+00 l --- l DCNUCC(31)

R016 l Unsaturated zone 1 (cn 3/g) l 0.000E+00 l 0.OOOE+00 l --- l DNUCU(31,l)

R016 l Saturated zone (c:.*3/g) l 0.000E+00 l 0.000E+00 l -- l DCNUCS(31)

R016 l Leach rate (/yr) l 0.000E+00 l 0.000E+00 l 9.964E-03 l ALEACH(31)

R016 l Solubility constant l 0.000E+00 l 0.OOE+00 l not used l SOLUBK(31)

R016 l Distribution coefficients for daughter Ac-227 I I I R016 l Contaminated zone Ccm**3/g) l 2.OOOE+01 l 2.000E+01 l --- I DCNUCC( 1)

R016 Unsaturated zone 1 (cn**3/g) l 2.000E+01 l 2.000E+01 l --- l DCNUCU( 1,1)

R016 l Saturated zone (cm**3/g) l 2.000E+01 l 2.OOOE+0l l --- l DCNUCS( 1)

R016 l Leach rate 1/yr) l 0.000E+00 l 0.000E+00 l 8.537E-05 l ALEACH( 1)

R016 Solubility constant l 0.000E+00 l 0.000E+00 l not used l SOLUBK( 1)

R016 l Distribution coefficients for daughter Am-243 I I I R016 l Contaminated zone (cm*3/g) l 2.000E+01 l 2.000E+01 l --- l DCNUCCC 4)

R016 l Unsaturated zone 1 I a**3/g) l 2.000E+01 l 2.000E+01 l --- l DCNUCU( 4,1)

R016 l Saturated zohe (c=**3/g) l 2.000E+01 l 2.000E+01 l - DCNUCS( 4)

R016 l Leach rate l/yr) l 0.000E+00 l 0.000E+00 l 8.537E-05 l ALEADH( 4)

R016 l Solubility constant l 0.000E+00 l 0.000E+00 l not used l SOLUBK( 4)

1 MK.SAD, Version 6.22 T%s Limit - 30 days 08/30/2004 14:42 Page 13 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Site-Specific Parameter Summary (continued)

User I I Used by RESRAD I Parameter Menu I Parameter Input I Default I (If different from user input) I Name R016 l Distribution coefficients for daughter Gd-152 R016 l Contaminated zone (cm**3/g) l-1.000E+00 1-l.OOOE+00 I 8.249E+02 l DCNUCC(l6)

R016 l Unsaturated zone 1 (cn..**3/g) l-1.000E+00 1-1.000E+00 I 8.249E+02 l DCNUCU(16,1)

R016 l Saturated zone (cm**3/g) l-1.000E+00 l-1.000E+00 I 8.24 9E+02 l DCNUCS116)

R016 l Leach rate U/yr) I O.OOOE+00 I O.OOOE+00 I 2.087E-06 l ALEACHl16)

R016 l Solubility constant I0.0005+00 l 0.OOOE+OO I not used I SOLUBK(16)

I I R016 l Distribution coefficients for daughter Np-237 R016 l Contaminated zone Icm**3/gI l-1.000E+OO 1-1.000E+00 I 2.574E+02 l DCNUCCl21)

R016 l Unsaturated zone 1 Icm**3/g) I-1.000E+00 1-1.000E+00 I 2.574E+02 l DCNUCU(21,1)

R016 l Saturated zone (=c*-3/g) l-1.000E+00 1-1.000E+00 I 2.574E+02 l DCNUCS(21)

R016 I Leach rate (/yr) .*

I O.OOOE+00 I O.OOOE+00 I 6.686E-06 l ALEACH(21)

R016 I Solubility constant I O.OOOE+00 I O.OOOE+00 not used l SOLUBK(21)

I I I R016 I Distribution coefficients for daughter Pa-231 I I R016 I Contaminated zone (cm*3/g) 5.000E+01 lI5.000E+O1 I l DCNUCC(22)

R016 I Unsaturated zone 1 (cm'3/g) 5.000E+01 I 5.OOOE+01 I l DCNUCU (22,1)

R016 I Saturated zone (cm-*3/g) I 5.00DE+01 I 5.000E+01 0 l DCNUCS(22)

R016 I Leach rate C/yr) l 0.OOOE+OO I O.OOOE+00 l 3.433E-05 l ALZACH(22)

R016 I Solubility constant 0.OOOE+00 I O.OOOE+00 l not used l SOLUBK(22)

I I I R016 I Distribution coefficients for daughter Pb-210 R016 I Contaminated zone (c=*3/g) l l.000E+02 I 1.000E+02 l l DCNUCC(23)

R016 I Unsaturated zone 1 lcm**3/g) l 1.OOOE+02 I 1.000E+02 l l DCNUCU123,1)

R016 I Saturated zone (cmn'3/g) l 1.OOOE+02 I 1.000E+02 l DCNUCS123)

R016 I Leach rate (/yr) 0.0OOOE+00 I 0.000E+00 I 1.719E-05 l ALEACH(23)

R016 I Solubility constant O.OOOE+00 I O.OOOE+00 I not used SOLUBK(23)

I I I R016 I Distribution coefficients for daughter Po-210 I I R016 I Contaminated zone (cm*3/g) l 1.000E+01 I 1.000E+01 I , DCNUCC(24)

R016 I Unsaturated zone 1 (cm**3/g) l l.OOOE+01 I 1.OOOE+01 I l DCN'JCU(24,1)

R016 I Saturated zone ( cm*3/g) 1.OOOE+01 I 1.000E+01 I l DCNUCS(24)

R016 I Leach rate (/yr) I O.OOOE+00 I0.000E+00 I 1.693E-04 l ALFACH(24)

R016 I Solubility constant I 0.000E+00 I 0.000B+00 not used I SOLUBK(24)

II I

R016 I Distribution coefficients for daughter Ra-226 R016 I Contaminated zone (cr**3/g) I 7.000E+01 I 7.OOOE+01 l DCNUCC(29)

R016 I Unsaturated zone 1 (c=*3/g) l 7.000E+01 I 7.OOOE+01 l l DCNUCU(29,1)

R016 I Saturated zone (cm*'3/g) l 7.000E+Ol I 7.OOOE+01 l DCNUCS(29) l7.OOOE+OO R016 I Leach rate (/yr) 0. OOOE+0O I 6.000E+00 I 2.454E-05

ALEACH(29)

R016 I Solubility constant I0.000E+00 I 0.000E+00 l not used I SOLUBK(29)

I II R1016 l Distribution coefficients for daughter Th-229 I R016 I Contaminated zone (cm**3/g) l 6.000E+04 I 6.000E+04 l DCNUCC(32)

R016 I Unsaturated zone 1 (cm*'3/g) l 6.000E+04 I 6.O005+04 l DCNUCU(32,l)

R016 I Saturated zone (c='3/g) l 6.000E+04 I 6.OOOE+04 l DCNUCS(32)

R016 I Leach rate (/yr) l O.OODE+00 I O.OOOE+00 l 2.870E-08 l ALEACH(32)

R016 I Solubility constant l O.OOOE+00 I O.OOOE+00 I not used I SOLUBK(321

RESRAD, Version 6.22 T1/2 Limit - 30 days 08/30/2004 14:42 Page 14 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Site-Specific Parameter Summary (continued)

I User Used by RESRAD I Parameter Menu I Parameter 1 Input I Default l (If different from user inputl I Name 4- l R016 l Distribution coefficients for daughter Th-230 1 R016 Contaminated zone I=**3/g) 1 6.OOOE+04 l 6.000E+04 l ___ DCNUCC(33)

R016 l Unsaturated zone 1 Icm**3/g) 1 6.000E+04 l 6.OOOE+04 l ___

DCNUCU(33,1)

R016 l Saturated zone (c**3/g) 1 6.000E+04 l 6.000E+04 l ___

DCNUCS(33)

R016 l Leach rate C/yr) 1 0.000E+00 l 0.000E+00 l 2. 870Z-08 ALEACH(33)

R016 l Solubility constant 1 0.000E+00 l 0.000E+00 not used SOLUBKC33) 1 R016l Distribution coefficients for daughter U-233 1 R016l Contaminated zone (cm'*3/g) 1 5.000E+01 l 5.000E+01 l ___

DCNUCCZ34)

R016l Unsaturated zone 1 (=**3/g) 1 5.000E+01 l 5.OOE+01 l ___

DCNUCUC34,1)

R016l Saturated zone (cm=*3/g) 1 5.000E+01 l 5.000E+01 l ___

DCNUCS (34)

R016l Leach rate (/yr) ^ 1 0.000E+00 l 0.000E+00 l 3.433E-05 ALEACH(34)

R016l Solubility constant 1 0.000E+00 l 0.000E+00 l not used SOLU8Kl34) 1 R016l Distribution coefficients for daughter U-234 1 R016l Contaminated zone C=n*3/g) 1 5.000E+01 5.000E+01 l OCNUCC(35)

R016l Unsaturated zone 1 (=*'3/g) 1 5.OOOE+01 l 5.000E+01 l DCNUCU(35,11 R016l Saturated zone (=.**3/g) 1 5.000E+01 l 5.000E+01 l DCNUCS(35)

R016l Leach rate (/yr) 1 0.000E+00 l 0.000E+00 l ALEACH(35)

R016l Solubility constant 1 0.000E+00 l 0.000E+00 I not used SOLUBK(35) 1 R016l Distribution coefficients for daughter U-235 1 R016l Contaminated zone (cmn3/g) 1 5.000E+01 l 5.000E+01 l DCNUCC(36)

R016l Unsaturated zone 1 (c= 3/g) 1 5.000E+01 l 5. OOOE+01 DCNUCUC36,1)

R016l Saturated zone (c='3/g) 1 5.000E+01 l 5. OOOE+01 I DCN'JCS(36)

R016l Leach rate (/yr) 1 0.000E+00 l 3.433E-05 ALEACH(36)

R016l Solubility constant 1 0.OOOE+00 l O.OOOE+00 l not used SOLUBK(36) 1 . I RO17 l Inhalation rate (m**3/yr) 1 e .400E+03 l 8.400E+03 l INHALR RO17 l Mass loading for inhalation (g/r.**3) 1 1.OOOE-04 l 1.000E-04 l MLINH R017 l Exposure duration 1 3.OOOE+01 l 3.000E+01 ED R017 Shielding factor, inhalation 1 4.OOOE-01 l 4.000E-01 l SHF3 R017l Shielding factor, external gamma 1 7.000E-01 l 7.000E-01 l SHF1 R017l Fraction of time spent indoors 1 5.OOOE-01 l 5.000E-01 l FIND R017l Fraction of time spent outdoors (on site) 1 2.500E-01 l 2.500E-01 l FOTD R0 17l Shape factor flag, external gamma 1 1.000E+00 l 1.O0OE+00 l >0 shows circular M EA. FS RO17 l Radii of shape factor array (used if FS - -1): 1 RO17 l Outer annular radius (m), ring 1: 1 not used l 5.000E+01 l RADSHAPEC 1)

R017 Outer annular radius (m), ring 2: 1 not used l *7.071E+01 l RAD SHAPE( 2)

Ro17 I Outer annular radius Cm),ring 3: 1 not used I 0. OE+00 I RAD SHAPEC 3)

R0 17 I Outer annular radius Cm),ring 4: 1 not used I 0.000E+00 I RAD SHAPEC 4)

RD 17 I Outer annular radius Cm),ring 5: 1 not used I 0.000E+00 l RADSHAPES 5)

R017 I Outer annular radius (in, ring 6: 1 not used I 0.000E+00 l RAD SHAPE( 6)

R017 I Outer annular radius Cm), ring 7: 1 not used I 0.000E+00 l RAD SHAPE( 7)

RD 17 I Outer annular radius Cm),ring e: 1 not used I 0.000E+00 l RAD SHAPE( 8)

R017 I Outer annular radius Cm),ring 9: 1 not used I O.00E+00 I RAD SHAPE( 9)

R017 I Outer annular radius Cm),ring 10: 1 not used I 0.000E+00 l RADSHAPE(10)

R017 I Outer annular radius Cm),ring 11: 1 not used I 0.000E+00 I RADSHAPE(ll)

R017 I Outer annular radius Cm),ring 12: 1 not used I 0.000E+00 I RAD SHAPE(12)

I 1 I I

m&azvw version o.zz T4 Limit - JU days OU/JU/ZUU4 14:42 Lage lb Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Site-Specific Parameter Summary (continued)

User I Used by RESRAD I Parameter Menu I Parameter l Input l Default l (If different from user inpuit) l Name I

R017 I Fractions of annular areas within AREA:

R017 I Ring 1 l not used l 1.OOOE+OO l l FRACA( 1)

R017 I Ring 2 not used 2.732E-O1 l l FRACA( 2)

R017 I Ring 3 l not used l O.DOOE+OO l l FRACA( 3)

R017 I Ring 4 not used l O.OOOE+OO l l FRACA( 4)

R017 I Ring 5 lnot used I O.OOOE+DO I l FRACA( 5)

R017 I Ring 6 not used l O.OOOE+DO l l FRACA( 6)

R017 I Ring 7 l not used D.ODOE+OO l l FRACA( 7)

R017 I Ring 8 not used l O.OOOE+OO l l FRACAC 8)

R017 I Ring 9 l not used l O.OOOE+DO l l FRACAC 9)

R017 I Ring 10 not used l O.OOOE+OO l l FRACA(10)

R017 I Ring 11 not used O.OOOE+OO l l FRACAC11)

R0 17 I Ring 12 not used l O.OOOE+OO l l FRACA(12)

I ROlE I Fruits, vegetables and grain consumption (kg/yr) l 1.600E+02 l 1.600E+02 l DIESI1)

R018 I Leafy vegetable consumption (kg/yr) l 1.400E+01 l 1.400E+O1 l DIET(2)

R018 I Milk consumption (L/yr) l 9.200E+01 l 9.200E+O1 l ___

l DIEST(3)

R018 I Meat and poultry consumption (kg/yr) l 6.300E+01 l 6.300E+O1 l ___

l DIET(4)

R018 I Fish consumption (kg/yr) not used l 5.400ZE+OO l DIET(S5)

R018 I Other seafood consumption lkg/yr) l not used l 9.000E-D1 DIET(6)

R018 I Soil ingestion rate (g/yr) l 3.650E+01 l 3.650E+O1 l ___

l SOIL R018 I Drinking water intake (L/yr) l 5.100E+02 l 5.100E+02 l l DWI R018 I Contamination fraction of drinking water l 1.OOOE+OO 1.OOOE+OO l l FDW RD18 I Contamination fraction of household water l 1.0005E00 l 1.000E+00 l FHHW R018 I Contamination fraction of livestock water l 1.OOOE+00 l 1.OOOE+OO l l FLW R018 I Contamination fraction of irrigation water l l.OOOE+OO 1.OOOE+00 l l FIRW R018 I Contamination fraction of aquatic food not used l 5.000E-01 l l FR9 R018 Contamination fraction of plant food 1-1 i-I 1 0.450E+00 l FPLANT R018 Contamination fraction of meat 1-1 I-i 0. 450E-01 l FMEAT R018 l Contamination fraction of milk 0.450E-01 l FMILK R19 Livestock fodder intake for meat (kg/day) l 6.800E+01 l 6.800E+01 l LFI5 R0l9 l Livestock fodder intake for milk (kg/day) l 5.500E+01 l 5.500E+O1 l l LF16 RD19 l Livestock water intake for meat (L/day) l 5.000E+01 l 5.000E+O1 l l LWI5 R0l9 l Livestock water intake for milk (L/day) l 1.600E+02 l 1.600E+02 l l LWI6 R0l9 l Livestock soil intake (kg/day) l5.ODE-01 5.OOOE-01 lLSI RD19 Mass loading for foliar deposition (g/m**3) l l.OOOE-04 1.OOOE-04 l l YLFD RD19 l Depth of soil mixing layer (n) l 1.500E-01 l 1.500E-O1 l l DM RD19 l Depth of roots Cm) l 9.000E-01 l 9.000-E-O1 l DROOT RDl9 l Drinking water fraction from ground water ! 1.000E+00 1l.OOOE+OO l l FGWM7 R0l9 l Household water fraction from ground water l 1.000E+00 l.OOOE+OO l l FGWHH R19 l Livestock water fraction from ground water l 1.000E+00 l 1.000E+00 l FGWLW A019 l Irrigation fraction from ground water l 1.000E+00 l 1.000E+00 l FGWIR I

R19B I Wet weight crop yield for Non-Leafy (kg/m^*2) l 7.O00E-01 l 7.000E-O1 l I YV l)

R19B I Wet weight crdp yield for Leafy (kg/m-*2) l 1.500E+00 l 1.500E+00 l YV(21 R19B I Wet weight crop yield for Fodder (kg/m**2) l 1.10E+OC l 1.1OOE+OO l YV(3)

R19B Il Growing Season for Non-Leafy (years) l 1.700E-01 l 1.700E-01 l l TEQ1)

Rl9B Growing Season for Leafy (years) l 2.500E-01 l 2.500E-O1 l l TE(2)

R19B Growing Season for Fodder (years) l 8.000E-02 l 8.000E-02 l l TE(3)

R19B Translocation Factor for Non-Leafy l 1.OOE-01 l l.OOOE-0l l TIV(1)

%LZorUuw, version c.zz Tr LimIt - jU aays UV/3U/2UU4 14:42 Page 16 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Site-Specific Parameter Summary Icontinued)

User I I Used by RESRiAD Parameter Menu Parameter l Input l Default (

lIf different from u ser input) l Name I

Ri19B l Translocation Factor for Leafy l 1.OOOE+00 l 1.000E+00 l l TIV(2)

R19B l Translocation Factor for Fodder l 1.OOOE+00 l 1.000E+00 l l TIVO(3 R19E l Dry Foliar Interception Fraction for Non-Leafy l 2.500E-01 2.500E-01 l l RDRY121 R19B l Dry Foliar Interception Fraction for Leafy l 2.500E-01 l 2.500E-01 l l RDRY12)

Dry Foliar Interception Fraction for Fodder l 2.500E-01 l 2.500E-01 l l RDRY(3(

R19B Wet Foliar Interception Fraction for Non-Leafy l 2.50OE-01 2.500E-01 l l RWET111 R19B Wet Foliar Interception Fraction for Leafy l 2.500E-01 2.500E-01 l l RWET12)

R19B Wet Foliar Interception Fraction for Fodder l 2.500E-01 2.500E-01 l l RWET13)

R19B l Weathering Removal Constant for Vegetation l 2.OOOE+01 2.000E+01 i WIA I I C14 I C-12 concentration in water (g/cml*3) l 2.OOOE-05 2.000E-05 l l C12WTR C14 l C-12 concentration in coptaminated soil (g/g) l 3.000E-02 l 3.000E-02 l I C12CZ C14 l Fraction of vegetation carbon from soil l 2.000E-02 l 2.000E-02 l l CSOIL C14 l Fraction of vegetation carbon from air l 9.800E-01 1 9.800E-01 I lCAIR C14 l C-14 evasion layer thickness in soil 1m) l 3.OOOE-01 l 3.000E-01 l l DMC C14 I C-14 evasion flux rate from soil 1l/sec) l 7.000E-07 l 7.000E-07 l l EVSN C14 l C-12 evasion flux rate from soil (1/sec) l 1.000E-10 l 1.000E-10 l l REVSN C14 l Fraction of grain in beef cattle feed l 6.OOOE-01 I e.000E-01 I l AVFG4 C14 l Fraction of grain in milk cow feed 22.000E-01 l 2.000E-01 l l AVFG5 C14 D uCFcorrection factor for gaseous forms of C14 l 8.894E+01 l 8.e94E+01 l l C02F I I STOR l Storage times of contaminated foodstuffs (days): I I STORl Fruits, ncn-leafy vegetables, and grain l 1.400E+01 l 1.400E+01 l l STOR T(l)

STOR l Leafy vegetables l 1.000E+00 1.000E+00 l l STOR T(2)

STORl Milk I 1.000E+00 l 1.000E+00 l l STORPT(3)

STORl Meat and poultry l 2.000E+01 l 2.000E+01 l l STOR T(4)

STOR l Fish l 7.OOOE+00 l 7.000E+00 l STOR T(5)

STOR l Crustacea and mollusks I 7.000E+00 l 7.000E+00 l STORPT(6)

STOR l Well water l 1.000E+00 l 1.OOOE+00 l l STORT(7)

STOR I Surface water l 1.000E+00 l 1.000E+00 l l STORT(18)

STOR l Livestock fodder l 4.500E+01 l 4.500E+01 l l STOR T(9)

I I R021 Thickness of building foundation 1m) l 1.500E-01 l 1.500E-01 l l FLOOR1 R021 l Bulk density of building foundation (g/c=**3) l 2.400E+00 l 2.400E+00 l l DENSFL R021 l Total porosity of the cover material l 4.000E-01 4.000E-01 l l TPCV R021 l Total porosity of the building foundation l 1.000E-01 l 1.000E-01 l I TPFL R021 l Volumetric water content of the cover material 5.000E-02 l 5.000E-02 l l PH20-V R021 l Volumetric water content of the foundation 3.000E-02 l 3.OOOE-02 l l PH20FL R021 l Diffusion coefficient for radon gas (m/sec): I I R021 l in cover material l 2.000E-06 l 2.000E-06 l ___ l DIFCV R021 in foundation material I 3.000E-07 l 3.000E-07 l ___

l DIFFL R021 in contaminated zone soil l 2.000E-06 l 2.000E-06 l l DIFCZ R021 l Radon vertical dimension of mixing (m) l 2.000E+00 l 2.000E+00 l l HMIX R021 l Average building air exchange rate (1/hr) I 5.000E-01 l 5.000E-01 l lREXG R021 l Height of the building (rooma) m) l 2.500E+00 l 2.500E+00 l lHRM R021 l Building intefior area factor l 0.000E+00 l 0.000E+00 l codiie cosmputed (time dependent) l FAI R021 l Building depth below ground surface (m) l-1.OOOE+00 l-1.000E+00 I codie computed (time dependent) I DMFL R021 l Emanating power of Rn-222 gas l 2.500E-01 l 2.500E-01 I EMANA(1)

R021 l Emanating power of Rn-220 gas l not used l 1.500E-01 l IESMAKA(2)

I I TITL Number of graphical time points 32 ___- l NPTS TITL l Maximum number of integration points for dose 17 ___- I LYMAX

lrLbKAW, version t.ZZ TS Limit - 30 days 08/30/2004 14:42 Page 17 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Site-Specific Parameter Summary (continued)

I User I I Used by RESRRD I Parameter Menu I Parameter Input I Default I (If different from user input) I Name TITL I Maximum number of integration points for risk I 1 l --- I --- I KY.MAX I-Summary of Pathway Selections Pathway I User Selection 1 -- external gamma j active 2 -- inhalation (w/o radon)l active 3 -- plant ingestion active 4 -- meat ingestion active 5 -- milk ingestion active 6 -- aquatic foods l suppressed 7 -- drinking water active 8 -- soil ingestion l active 9 -- radon active Find peak pathway doses l active

"zbtJ, version b.ZZ T" Limit - JU aays OB/30/2004 14:42 Page 18 Surmary : Haddam Neck Material at USEI File: CY USEIC.RAD Contaminated Zone Dimensions Initial Soil Concentrations, pCi/g A-ea: 900.00 square meters Ag-108m 1.00OE+00 Thickness: 33.60 meters Am-241 1.000E+00 Cover Depth: 3.60 meters C-14 1.OOOE+00 Cm-243 1.OOOE+00 Co-60 1.000E+00 Cs-134 1.000E+00 Cs-137 1.000E+00 Eu-152 1.000E+00 Eu-154 1.OOOE+00 Eu-155 1.000E+00 Fe-55 1.000E+00 H-3 1.000E+00 Mn-54 1.000E+00 Nb-94 1.000E+00 Ni-63 1. OOOE+00 a

Pu-238 1.000E+00 Pu-239 1. OOOE+00 Pu-241 1.OOOE+00 Sr-90 1.OOOE+00 Tc-99 1. OOOE+00 Total Dose TDOSE(t), mrem/yr Basic Radiation Dose Limit - 5.OOOE+00 mre:m/yr Total Mixture Sum MHt) - Fraction of Basic Dose Limit Received at Time It) t (years): 0.000E+00 1.000E+00 3.000E+00 1.000E+01 3.000E+01 1.OOOE+02 3.000E+02 1.000E+03 TDOSEMt): 1.76BE-15 2.647E-14 3.076E-13 8.047E-12 1.893E-10 1.247E-01 2.953E-01 2.391E-04 Mlt): 3.535E-16 5.294E-15 6.153E-14 1.609E-12 3.786E-11 2.495E-02 5.905E-02 4.781E-05 Maximum TDOSE(t): 2.101E+00 mrem/yr at t - 122.1 f 0.2 years

nLzKAs, version .zz Tr Limit - 30 aays 08/30/2004 14:42 Page 19 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 1.221E+02 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Nuclide Ag-lOm 1.014E-27 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 Am-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.00 C-14 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Cm-243 O.OOOE+0O 0.0000 O.OOOE+O0 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 C.OOOE+00 0.0000 Co-60 2.080E-2E 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Cs-134 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Cs-137 5.012E-28 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-152 3.286E-26 0.0000 O.OOOE+OO 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 Eu-154 4.764E-27 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-155 0.000E+00 0.0000 C.OCOE+OC 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Fe-55 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 H-3 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Mn-54 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Nb-94 9.131E-26 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 Ni-63 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+O 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-23B 0.OOOE+00 0.0000 O.OOOE+00 0.0000 1.03aE-08 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 C.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-239 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 OOOOE+00 0.0000 O.OOOE+00 0.0000 Pu-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Tc-99 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOE+00 0.0000 Total 1.307E-25 0.0000 0.000E+00 0.0000 1.038E-08 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0000E+0 0.0000

KLDzm, version .zz Tr Limit - ju days UU/30/ZUU4 14:42 Page 20 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSEli,p,tl for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 1.221E+02 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways-Radio-Nuclide mrem/yr frac:. mrem/yr fract. mrem/yr fract. mrem/yr fract.- mrem/yr fract. mrem/yr fract. mrem/yr fract.

Nuclide Ag-108m 5.112E-01 0.2434 O.OOOE+00 0.0000 0.000E+00 0.0000 3.674E-02 0.0175 1.480E-03 0.0007 2.69BE-02 0.0128 5.764E-01 0.27.

Am-241 O.OOOE+0O 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 2.698E-01 0.1284 O.OOOE+00 0.0000 O.OOOE+00 0.0000 3.201E-02 0.0152 1.127E-03 0.0005 3.074E-03 0.0015 3.060E-01 0.1457 Co-243 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+0 0.0000 C.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Co-60 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 C.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 2.080E-28 0.0000 Cs-134 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000+OO 0.0000 0.000E+00 0.0000 Cs-137 O.OOOE+00 0.0000 0.0001F+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.0OOO+00 0.0000 5.012E-28 0.0000 Eu-152 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 C.OOOE+00 0.0000 3.286E-26 0.0000 Eu-154 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 4.764E-27 0.0000 Eu-155 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+OO O.O6oo 0.000E+00 0.0000 Fe-55 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 H-3 8.607E-06 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 9.571E-07 0.0000 1.986E-0 0.0000 5.364E-08 0.0000 9.63BE-06 0.0000 Mn-54 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Nb-94 9.315E-01 0.4434 O.OOOE+00 0.0000 O.OOOE+00 0.0000 6.459E-02 0.0308 2.689E-07 0.0000 3.927E-06 0.0000 9.961E-01 0.4742 Ni-63 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Pu-235 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 1.038E-08 0.0000 Pu-239 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+0 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 OOOOE+00 0.0000 O.OOOE+00 0.0000 Pu-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.0OOE+00 0.0000 Sr-90 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.pOOE+00 0.0000 O.OOOE+00 0.0000 Tc-99 1.912E-01 0.0910 O.OOOE+00 0.0000 O.OOOE+00 0.0000 3.047E-02 0.0145 2.032E-05 0.0000 4.257E-04 0.0002 2.221E-01 0.1057 Total 1.904E+00 0.9063 0.000E+00 0.0000 0.000E+00 0.0000 1.63BE-01 0.0780 2.62EE-03 0.0013 3.049E-02 0.0145 2.101E+00 1.0000 ISum of all water independent and dependent pathways.

rQLKVW, Version b.2Z TH Limit - JU nays 08/30/2004 14:42 Page 21 Sumnary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - O.OOOE+00 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m 5.402E-27 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.00 Am-241 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.00 C-14 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Cm-243 0.000E+00 C.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0001+00 0.0000 Co-60 1.653E-21 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Cs-134 5.8elE-26 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Cs-137 6.850E-27 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-152 1.567E-23 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-154 5.997E-23 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-155 0.000E+00 0.0000 0.DOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 C.000S+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Fe-55 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 H-3 0.OOOE+00 0.0000 0.O0OE+00 0.0000 0.000E+00 0.000C 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 Mn-54 6.286E-25 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Nb-94 2.540E-25 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Ni-63 0.OOOE+00 0.0000 C.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-238 0.0OOE+00 0.0000 C.000E+00 0.0000 1.76SE-15 1.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-239 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-241 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0,000E+00 0.0000 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Tc-99 0.000E+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 Total 1.730E-21 O.OOC0 0.000E+00 C.0000 1.768E-15 1.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

QKJ4UsL, version b.zz T4 Limit - 30 days OB/30/2004 14:42 Page 22 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSEtip,t) for Individual Radionuclides (i) and Pathways Ip)

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

Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 5.402E-27 0.00 Am-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 Cm-243 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 Co-60 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 1.653E-21 0.0000 Cs-134 O.OOO+00 0.0000 O.OOO+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+OO 0.0000 O.OOOE+00 0.0000 5.881E-26 0.0000 Cs-137 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 6.850E-27 0.0000 Eu-152 O.OOOE+00 0.0000 0.000,E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 1.567E-23 0.0000 Eu-154 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 5.997E-23 0.0000 Eu-155 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000+00 0.0000 Fe-55 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 H-3 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Mn-54 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 6.286E-25 0.0000 Nb-94 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 2.540E-25 0.0000 Ni-63 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 C.OOOE+00 0.0000 Pu-238 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOO+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 1.768E-15 1.0000 Pu-239 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 Pu-241 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOE+00 0.0000 OrOOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 O.OOOE+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 Tc-99 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.OOO O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 Total 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 1.768E-15 1.0000

'Sum of all water independent and dependent pathways.

KLSKAD, version 6.22 T1/2 Limit - 30 days 08/30/2004 14:42 Page 23 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSEfi,p,t) for Individual Radionuclides Ci) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 1.000E+OO years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Heat Milk Soil Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m 5.329E-27 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O0OE+00 0.0000 0.000E+00 0.00 APm-241 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 0.OOOE+00 O.OOCO O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000. O.OOOE+00 0.0000 Cm-243 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+OO 0.0000 Co-60 1.451E-21 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OO0E+00 0.0000 Cs-134 4.209E-26 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Cs-137 6.705E-27 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000 O.OOOE+O 0.0000 Eu-152 1.490E-23 0.0000 O.OOO,E+OO 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-154 5.550E-23 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Eu-155 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000+OO 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Fe-55 O.OOOE+00 0.0000 0.000E+00 0.0000 0.00O+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 H-3 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Mr.-54 2.800E-25 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Nb-94 2.519E-25 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Nli-63 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Pu-238 O.OOOE+00 0.0000 0.OOOE+00 0.0000 2.647E-14 1.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Pu-239 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.COOE+00 0.0000 Pu-241 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 OtOOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 O.OOOE+00 0.0000 O.OOOE+00.0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Tc-99 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 Total 1.522E-21 0.0000 O.OOOE+OO 0.0000 2.647E-14 1.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000

KQSSHAD, Version 6.22 TVi Limit - 30 days 08/30/2004 14:42 Page 24 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSEti,p,t) for Individual Radionuclides li) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 1.OOOE+00 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways*

Radio-Nuclide mrem/yr fract. rmrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr frac:. mrem/yr frac:.

Ag-108m O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 5.329E-27 0.00 A--241 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 O.OOOE+00 0.0000 O.OCOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 Cm-243 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+0O 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Co-60 0.000E+00 0.0000 C.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+0 0.0000 O.OOOE+00 0.0000 1.451E-21 0.0000 Cs-134 O.OOOE+00 0.0000 0.OOOE+00 0.0000 C.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 4.209E-26 0.0000 Cs-137 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 6.705E-27 0.0000 Eu-152 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE400 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 1.490E-23 0.0000 Eu-154 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 5.550E-23 0.0000 Eu-155 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Fe-55 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 H-3 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 Mn-54 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+0 0.0000 2.BOOE-25 0.0000 Nb-94 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 2.519E-25 0.0000 Ni-63 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+OO 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-238 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 2.647E-14 1.0000 Pu-239 O.OOOE+00 0.0000 O.OOOE+0 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 Pu-241 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O:OOOE+00 0.0000 0.OOOE+00 0.0000 Sr-90 0.OOOE+00 0.0000 O.OOOE+OO 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Tc-99 O.OOOE+00 0.0000 O.OOOE+0 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.DOOE+00 0.0000 O.OOOE+00 0.0000 Total O.OOOE+00 0.0000 0.000E+00 0.000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 2.647E-14 1.0000 ISum of all water independent and dependent pathways.

RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 25 Summary : Haddam Neck Material at USEI File: CY USEIC.PAD Total Dose Contributions TDOSEji,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 3.OOOE+00 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mren/yr fract. mrem/yr fract. mrem/yr fract. mren/yr fract.

Ag-lOEm 5.1E5E-27 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 Am-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 0.000E+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+0 0.0000 Cc-243 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Co-60 l.119E-21 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 C.OOOE+00 0.0000 Cs-134 2.156E-26 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Cs-137 6.424E-27 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Eu-152 1.347E-23 0.0000 O.o000+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-154 4.755E-23 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Eu-155 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 Fe-55 O.OOOE+00 C.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+0O 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 H-3 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Mn-54 5.55BE-26 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00. 0.0000 O.OOOE+00 0.0000 Nb-94 2.477E-25 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Ni-63 0.OOOE+00 0.0000 0.000+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Pu-238 C.OOOE+00 0.0000 O.OOOE+00 0.0000 3.076E-13 1.0000 O.OOOE+00 0.0000 O.OOOE+OO 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000

?u-239 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 OiOOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 0.OOOE+00 0.0000 0.OCOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.0OOE+00 0.0000 O.OOOE+00 0.0000 Tc-99 0.OOOE+0 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Total 1.150E-21 0.0000 O.OOOE+OO 0.0000 3.076E-13 1.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000

KLbKALU, version b.22 T' Limit - 30 days O8/30/2004 14:42 Page 26 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 3.000E+00 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways-Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+0 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 5.185E-27 0.00 An-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Cm-243 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Co-60 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 1.119E-21 0.0000 Cs-134 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 2.156E-26 0.0000 Cs-137 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 6.424E-27 0.0000 Eu-152 O.OOOE+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 1.347E-23 0.0000 Eu-154 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 C.0000 0.000+00 0.0000 0.000E+00 0.0000 4.755E-23 0.0000 Eu-155 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Fe-55 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 C.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 H-3 O.OOOE+00 0.0000 C.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.0OOE+00 0.0000 Mn-54 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 C.0000 0.000E+00 0.0000 O.OOE+00 0.0000 5.558E-26 0.0000 Nb-94 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+O 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 2.477E-25 0.0000 Ni-63 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-238 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 3.076E-13 1.0000 Pu-239 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 OOOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.QOOE+00 0.0000 O.OOOE+00 0.0000 Tc-99 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Total C.OOOE+00 0.0000 C.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 3.076E-13 1.0000

Sum of all water independent and dependent pathways.

RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 27 Su.-mary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides Ci) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 1.000E+01 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-lOBm 4.711E-27 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.00 Am-241 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.ooof+00 0.0000 0.000E+00 0.00 C-14 0.000E+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Cm-243 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Co-60 4.500E-22 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 Cs-134 2.074E-27 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Cs-137 5.530E-27 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-152 9.45BE-24 0.0000 0.00CE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-154 2.76BE-23 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-155 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Fe-55 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 H-3 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Mn-54 1.935E-28 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Nb-94 2.336E-25 0.0000 0.DOOEi00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 Ni-63 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-238 0.OOOE+00 0.0000 0.000E+00 0.0000 8.047E-12 1.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-239 0.000E+00 0.0000 0.000E+00 0.0000 O.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-241 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 02000E+00 0.0000 0.OOOE+00 0.0000 Sr-90 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 C.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Tc-99 C.OOOE+00 0.0000 0.000E+00 0.0000 O.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000.E00 0.0000 0.OOOE+00 0.0000 Total 4.874E-22 0.0000 0.000E+00 0.0000 E.047E-12 1.0000 0.000E+00 0.0000 C.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

KL KUA, Version b.22 T4 Limit - 3U aays 08/30/2004 14:42 Page 28 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - l.OOOE+01 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways' Radio-Nuclide mrem/yr fract. mrem/yr fract. mren/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 4.711E-27 0.00 Am-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 C.OOOE+O0 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Cm-243 O.OOOE+O0 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 C.OOOE+00 0.0000 Co-60 O.OOOE+OO 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 4.50OE-22 0.0000 Cs-134 0.000E+O0 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 2.074E-27 0.0000 Cs-137 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 5.530E-27 0.0000 Eu-152 O.OOOE+00 0.0000 O.OOCE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 9.45BE-24 0.0000 Eu-154 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 C.OOOE+00 0.0000 O.OOOE+00 0.0000 2.76SE-23 0.0000 Eu-155 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+OO 0.0000 Fe-55 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 H-3 O.OOOE+00 O.OOOD O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Mn-54 O.OOOE+00 0.0000 O.OOOE+OO 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 1.935E-28 0.0000 Nb-94 O.OOOE+O0 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 2.336E-25 0.0000 Ni-63 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-238 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 O.OOOQ O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 8.047E-12 1.0000 Pu-239 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+0 0.0000 Pu-241 O.OOOE+00 0.0000 0.OOOE+000.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 OaOOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 C.0000 O.OOOE+00 0.0000 Tc-99 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.00O+00 0.0000 0.000E+00 0.0000 Total O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 E.047E-12 1.0000

Sum of all water independent and dependent pathways.

HKLKHA, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 29 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSE(ipt) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 3.000E+01 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m 3.582E-27 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.00 Am-241 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.00 C-14 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Cm-243 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Co-60 3.335E-23 0.0000 C.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Cs-134 2.578E-30 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Cs-137 3.603E-27 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-152 3.444E-24 0.0000 0.0004E+00 0.0000 0.000E+00 0.0000 C.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Eu-154 5.897E-24 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00.0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.0002+00 0.0000 Eu-155 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Fe-55 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 H-3 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Mn-54 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Nb-94 1.975E-25 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Ni-63 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-238 0.000E+00 0.0000 0.000E+00 0.0000 1.893E-10 1.0000 0.0000E+0 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Pu-239 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O. 000+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Pu-241 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0:000E+00 0.0000 O.OOOE+00 0.0000 Sr-90 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 rc-99 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.ODOE+00 0.0000 0.000E+00 0.0000 0.000.E+00 0.0000 0.OOOE+OC 0.0000 Total 4.289E-23 0.000C 0.000E+00 0.0000 1.893E-10 1.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000_+00 0.0000 O.OOOE+OO O.OOOO

RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 30 Summary : Haddam Neck Material at USEI File: CYUSEIC.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mren/yr and Fraction of Total Dose At t - 3.000E+01 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways*

Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 3.582E-27 0.00 Am-241 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.00 C-14 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Cm-24 3 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Co-60 0.000E+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 3.335E-23 0.0000 Cs-134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 2.578E-30 0.0000 Cs-137 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 3.603E-27 0.0000 Eu-152 O.OOOE+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 3.444E-24 0.0000 Eu-154 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 5.897E-24 0.0000 Eu-155 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OO0E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Fe-55 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 H-3 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Mn-54 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 .0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 No-94 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 1.975E-25 0.0000 Ni-63 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.OOOC O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-238 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 1.893E-10 1.0000 Pu-239 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 Pu-241 0.000E+OC 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 OOOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.ODOE+00 0.0000 O.OOOE+00 0.0000 Tc-99 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Total O.O0OE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 1.893E-10 1.0000

'Sum of all water independent and dependent pathways.

KENRAD, Version 6.22 Ti Limit - 30 days OB/30/2004 14:42 Page 31 Surmary : Haddam Neck Material at USEI File: CYUSEIC.RAfl Total Dose Contributions TDOSEli,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - l.OOOE+02 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract. rrem/yr frac:. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr frac:.

Ag-lOSm l.373E-27 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 Am-241 O.OOOE+O0 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Cc-243 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Co-60 3.694E-27 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Cs-134 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Cs-137 B.047E-28 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Eu-152 1.004E-25 0.0000 0.00O.E+00 0.0000 C.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Eu-154 2.633E-26 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 Eu-155 O.OOOE+00 0.0000 C.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Fe-55 O.OOOE+00 0;0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 O.OOO O.OOOE+00 0.0000 0.000E+00 0.0000 H-3 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.0OOE+00 0.0000 Mn-54 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OCOE+00 0.0000 0.000E+00 0.0000 Nb-94 1.099E-25 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 N'-63 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Pu-238 O.OOOE+00 0.0000 0.OOOE+00 0.0000 5.945E-09 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-239 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Pu-241 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 C.0000 O.OOOE+00 0.0000 O.COOE+00 0.0000 O0OOOE+00 0.0000 0.OOOE+00 0.0000 Sr-90 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.0OE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Tc-99 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Total 2.425E-25 0.0000 o.OOOE+00 0.0000 5.945E-09 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000

K~rimv, version t.za ri2Limit - ju oays Ub/JUZUU4 i4:qz rage jz Summary : Haddam Neck Material at USEI File: CYIUSEIC.RAD Total Dose Contributions TDOSEUi,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 1.000E+02 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways, Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m 3.314E-02 0.2657 O.OOOE+00 0.0000 O.OOOE+00 0.0000 2.327E-03 0.0187 8.461E-05 0.0007 1.676E-03 0.0134 3.723E-02 0.29 Amn-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 1.555E-02 0.1246 O.OOOE+00 0.0000 0.000E+00 0.0000 1.78BE-03 0.0143 5.99BE-05 0.0005 1.759E-04 0.0014 1.757E-02 0.1409 Cm-243 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.0OOE+00 0.0000 O.OOE+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 Co-60 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 C.0000 C.OOOE+00 0.0000 0.000+00 0.0000 0.000E+00 0.0000 3.694E-27 0.0000 Cs-134 0.000E+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+O 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 Cs-137 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.O0OE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 8.047E-28 0.0000 Eu-152 0.000E+00 0.0000 0.000,+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000+00 0.0000 0.000E+00 0.0000 1.004E-25 0.0000 Eu-154 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 2.633E-26 0.0000 Eu-155 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Fe-55 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 H-3 1.705E-06 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.842E-07 0.0000 3.630E-09 0.0000 1.049E-08 0.0000 1.903E-06 0.0000 Mn-54 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Nb-94 5.35BE-02 0.4296 O.OOOE+00 0.0000 0.000E+00 0.0000 3.630E-03 0.0291 1.364E-08 0.0000 2.165E-07 0.0000 5.721E-02 0.4587 Ni-63 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.O0E+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 Pu-238 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+OO 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 5.945E-09 0.0000 Pu-239 0.000E+00 0.0000 O.0OOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Pu-241 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 C.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+0 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 Tc-99 1.099E-02 0.0881 C.OOOE+00 0.0000 0.OOOE+00 0.0000 1.706E-03 0.0137 2.027E-06 0.0000 2.337E-05 0.0002 1.272E-02 0.1020 Total 1.133E-01 0.9080 O.OOOE+00 0.0000 O.OOOE+00 0.0000 9.451E-03 0.0758 1.456E-04 0.0012 1.876E-03 0.0150 1.247E-01 1.0000 Sum of all water independent and dependent pathways.

RESRAD, Version 6.22 Th Limit - 30 days 08/30/2004 14:42 Page 33 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSElipt) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - 3.000E+02 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract. mrem/yr fract. nrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m 8.876E-29 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.00 Am-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.00 C-14 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Cm-243 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOO+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Co-60 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Cs-134 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Cs-137 1.110E-29 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 Eu-152 4.119E-30 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-154 O.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-155 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0M000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Fe-55 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 H-3 - 0.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Mn-54 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Nb-94 2.057E-26 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Ni-63 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+OC 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Pu-238 2.250E-30 0.0000 O.OOOE+00 0.0000 1.152E-07 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 Pu-239 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Pu-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.QOOOE+00 0.0000 O.OOOE+00 0.0000 Tc-99 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 C.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

.otal 2.067E-26 0.0000 O.OOOE+00 0.0000 1.152E-07 0.0000 O.OOOE+00 0.0000 O.0OE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000

' RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 34 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSE(ip,t) for Individual Radionuclides (i) and Pathways (p)

As nrem/yr and Fraction of Total Dose At t - 3.000E+02 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways^

Radio-Nuclide mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m 3.305E-02 0.1119 O.OOOE+00 0.0000 O.OOOE+00 0.0000 2.377E-03 0.0080 9.597E-05 0.0003 1.746£-03 0.0059 3.727E-02 0.12 Am-241 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.00 C-14 4.507E-02 0.1526 O.OOOE+00 0.0000 O.OOOE+00 0.0000 5.351E-03 0.0181 1.887E-04 0.0006 5.137E-04 0.0017 5.112E-02 0.1731 Cm-243 0.OOOE+OC 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.0OOE+00 0.0000 0.000E+00 0.0000 Co-60 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000 Cs-134 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Cs-137 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+O 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 1.110E-29 0.0000 Eu-152 O.OOOE+00 0.0000 0.000p+OO 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 4.119E-30 0.0000 Eu-154 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 Eu-155 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 Fe-55 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000 H-3 6.778E-11 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 7.542E-12 0.0000 1.567E-13 0.0000 4.225E-13 0.0000 7.590E-11 0.0000 Mn-54 0.OOOE+OO 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+OO 0.0000 0.000+00 0.0000 Nb-94 1.580E-01 0.5352 O.OOOE+00 0.0000 O.OOOE+00 0.0000 1.096E-02 0.0371 4.576E-08 0.0000 6.669E-07 0.0000 1.690E-01 0.5723 Ni-63 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-238 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 1.152E-07 0.0000 Pu-239 O.OOE+00 0.0000 O.OOOE+00 C.0000 O.OOOE+00 0.0000 O.OOOE+O 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-241 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 01000E+00 0.0000 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.OOE+00 0.0000 0.000+00 0.0000 Tc-99 3.261E-02 0.1105 O.OOOE+00 0.0000 0.000E+00 0.0000 5.200E-03 0.0176 3.476E-06 0.0000 7.269E-05 0.0002 3.789E-02 0.1283 Total 2.688E-01 0.9102 O.OOOE+00 0.0000 0.OOOE+00 0.0000 2.389E-02 0.0809 2.881E-04 0.0010 2.333E-03 0.0079 2.953E-01 1.0000

^Sum of all water independent and dependent pathways.

j RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 35 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t'- 1.OOOE+03 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract. mren/yr fract. mrem/yr fract. mrem/y- fract. mrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-lO8 0.OOOE+00 0.0000 O.0OO+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.00E+00 0.0000 0.000E+00 0.00 Xrn-241 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000 0.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Cm-243 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Co-60 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Cs-134 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Cs-137 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Eu-152 O.OOOE+00 0.0000 O.OOOE+OO 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-154 O.OOOE+00 0.0000 O.OOOE+00 C.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-155 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Fe-55 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 H-3 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000+00 0.0000 Mn-54 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOS+00 0.0000 O.OOOE+00 0.0000 0.0000E+0 0.0000 Mob-94 5.836E-29 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Ni-63 O.OOOE+00 000000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.00O+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+O0 0.0000 Pu-238 1.025E-28 0.0000 O.OOOE+00 0.0000 2.004E-06 0.0084 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 C.0000 Pu-239 O.OOOE+00 0.000C O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OCE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Pu-241 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O:OOOE+00 0.0000 O.OOOE+00 0.0000 Sr-90 0.000E+O 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+000.0000 0.000E+00 0.0000 0.000E+00 0.0000 Tc-99 C.OOCE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O. 000+00 0.0000 O.OCOE+00 0.0000 0.000E+00 0.0000 Total 1.608E-28 C.0000 O.OOOE+00 0.0000 2.004E-06 0.0084 O.OOO+00 0.0000 0.000+00 0.0000 O.OOOE+00 0.0000 0.000+00 0.0000

nQaUi version o.. 12L.Xr.m - .Ju UAyZ UO1Ua4Uw.. U~: r~vs -t

Summary : Haddam Neck Material at USEI File: CYUSEIC.RAD Total Dose Contributions TDOSE(i pt) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t - l.OOOE+03 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways, Radio-Nuclide mrem/yr fract. mrem/yr fract. nrem/yr fract. rxem/yr fract. rrem/yr fract. mrem/yr fract. mrem/yr fract.

Ag-108m 6.852E-07 0.0029 O.OOOE+00 0.0000 O.OOOE+00 0.0000 4.928E-O 0.0002 1.990E-09 0.0000 3.620E-08 0.0002 7.727E-07 0.00 Am-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.00 C-14 3.917E-05 0.1639 O.OOOE+00 0.0000 0.000E+00 0.0000 4.651E-06 0.0195 1.640E-07 0.0007 4.465E-07 0.0019 4.443E-05 0.1859 Cm-243 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 Co-60 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OGOE+00 0.0000 0.000E+00 0.0000 Cs-134 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 0.0000+00 0.0000 Cs-137 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-152 O.OOOE+DO 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 O.0000 O.OOOE+00 0.0000 O.OOE+00 0.0000 Eu-154 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Eu-155 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Fe-55 O.OOOE+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000+00 0.0000 H-3 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.OOOE+00 0.0000 Mn-54 0.00Z+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOE+00 0.0000 Nb-94 1.460E-04 0.6106 0.000E+00 0.0000 O.OOOE+00 0.0000 1.013E-05 0.0424 4.226E-11 0.0000 6.160E-10 0.0000 1.561E-04 0.6529 Ni-63 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 Pu-238 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+0 0.0000 0.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 2.004E-06 0.0064 Pu-239 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 C.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 Pu-241 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 Sr-90 O.OOOE+00 0.0000 O.OOE+00 0.0000 O.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 Tc-99 3.078E-05 0.22S8 C.000+00 0.0000 4.909E-06 0.0205 3.281E-09 0.0000 6.861E-08 0.0003 3.576E-05 0.1496 Total 2.166E-04 0.9060 O.OOOE+00 0.0000 0.000E+00 0.0000 1.974E-05 0.0826 1.693E-07 0.0007 5.519E-07 0.0023 2.391E-04 1.0000

Sum of all water independent and dependent pathways.

k; .SKKU,version e.2z TS Limit - 30 days 08/30/2004 14:42 Page 37 Summary : Haddam Neck Material at USEI File: CY USZ1C.RAD Dose/Source Ratios Summed Over All Pathways Parent and Progeny Principal Radionuclide Contributions Indicated Parent Product Branch DSR(j,t) (mrem/yrl/(pCi/g)

(i) (J) Fraction' t- O.OOE+00 l.OOOE+OO 3.0COE+00 1.OOOE+01 3.000E+01 1.OOE+02 3.000E+02 1.OOOE+03 Ag-lOm Ag-108m 1.OOOE+00 5.402E-27 5.329E-27 5.185E-27 4.711E-27 3.582E-27 3.723E-02 3.727E-02 7.727E-C Am-241 A-n-241 1.OOOE+00 O.OOOE+00 O.OOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0 .OOOE+00 0.OOOE+00 0.0002+C Am-241 Np-2 37 1.OOOE+00 5.828E-42 1.751E-41 4.095E-41 1.240E-40 3.701E-40 1.341E-39 5.295E-39 5. OOSE-t Am-2 41 U-233 1.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.0002+C Am-241 Th-229 1.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 1.401E-45 2.102E-44 8.324E-43 3.050E-41 3. 48 4E-~

Am-241 EDSR (I) 5.6282E-42 1.751E-41 4.0 95E-41 1.240E-40 3.701E-40 1.342E-39 5.325E-39 5. 35BE C-14 C-14 l.OOOE+OO O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOO+00 O.OOOE+00 1.757E-02 5.112E-02 4.443E-05 Cm-243 Ca-243 9.976E-01 8.594E-39 8.403E-39 e.048E-39 -39 4.453E-39 9.600E-40 1.198E-41 0.000E+00 crn-24 3 Pu-239 9.976E-01 O.OOOE+00 O.OOOE+00 O.OOOE+00 1.401E-45 2.803E-45 5.605E-45 9.809E-45 4.905E-44 Cm-243 U-235 9.976E-01 G.OOOE+00 O.OOOE+OO O.OOOE+00 e.OOOE+OO O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOE+00 CM-243 Pa-231 9.976E-Ol O.O0OE+OO O.OOOE+00 O.OOOE+00 O.OOO+OO O.OOOE+00 O.0OOE+00 1.401E-45 4.764E-44 Cm-243 A---227 9.976E-01 O.OOOE+00 O.0OOE+00 O.OOOE+00 O.00OE+OO 0.OOOE+00 O.OOOE+00 4.204E-45 2.522E-43 Cm-243 EDSRUj) 8.594E-39 8.40BE-39 8.048E-39 6.903E-39 4.453E-39 9.600E-40 1.199E-41 3.4e89-43 Cm-243 Cm-243 2.400E-03 2.068E-41 2.023E-41 1.936E-41 1.661E-41 1.071E-41 2.309E-42 2.803E-4 4 0. OOOE+00 Cm-243 Am-243 2.400E-03 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O. OOOE+00 0.OOOE+00 0.OOOE+00 O.0OOE+OO Cm-243 Pu-239 Z.400E-03 O.OOOE+00 O.OOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+OO O.OOOE+00 O. OOOE+OO Cm-24 3 U-235 2.400E-03 0.000+00 O.OOE+00 0.OOOE+OO O.OOOE+GO 0. OOOS+OO O.OOOE+00 O.OO0E+OO e.OOOE+OO CM-243 Pa-231 2.400E-03 O.OOOE+OO.0.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+00 O.OOOE+00 O.OOO+00 Cm-243 Ac-227 2.400E-03 O.OOOE+OO O.OOOE+OO 0.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+OO Cmn-24 3 EDSR(J) 2.06EE-41 2.023E-41 1.936E-41 1.661E-41 1.071E-41 2.309E-42 2.803E-44 O.OOOE+00 Co-60 Co-60 l.OOOE+OO 1.653E-21 1.451E-21 1.119E-21 4.500E-22 3.335E-23 3.694E-27 1.844E-38 O.OOOE+00 Cs-134 Cs-134 l.OOOE+00 5.881E-26 4.209E-26 2.156E-26 2.074E-27 2.578E-30 1.747E-40 O.OOOE+00 O.OOOE+00 Is-137 Cs-137 l.OOOE+O0 6.850E-27 6.705E-27 6.424E-27 5.530E-27 3.603E-27 8.047E-28 1.11OE-29 3.428E-36 Eu-152 Eu-152 7.208E-01 1.130E-23 1.074E-23 9.708E-24 6.817E-24 2.483E-24 7.236E-26 2.969E-30 1.401E-45 Eu-152 Eu-152 2.792E-01 4.376E-24 4.160E-24 3.761E-24 2.641E-24 9.616E-25 2.803E-26 1.150E-30 O.OOOE+00 Eu-152 Gd-152 2.792E-01 O.0OOE+00 O.0OOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OO0E+OO O.OO0E+OO Eu-152 EDSR (ii 4.376E-24 4.160E-24 3.761E-24 2.641E-24 9.616E-25 2.803E-26 1.150E-30 O.0OOE+00 Eu-154 Eu-154 1.OOOE+00 5.997E-23 5.5502-23 4.755E-23 2.768E-23 5.897E-24 2.633E-26 5.075E-33. 0.000E+00 Eu-155 Eu-155 l.OOOE+OO O.OOOE+00 O.OOOE+00 O.0OOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Fe-55 Fe-55 l.0OOE+OO O.OOE+00 C.O0OE+OO O.OOOE+OO O.0OOE+OO O.OOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 N-3 H-3 l.0OOE+OO O.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 O.0OOE+00 1.903E-06 7.590E-11 6.219E-31 An-54 Mn-54 l.0OOE+00 6.286E-25 2.800E-25 5.558E-26 1.935E-28 1.835E-35 O.OOE+00 O.OOOE+00 O.OOOE+00

RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 38 Sum ary : Haddam Neck Material at USEI File: CY USEIC.RAD Dose/Source Ratios Surmed Over All Pathways Parent and Progeny Principal Radionuclide Contributions Indicated Parent Product Branch DSR(J,t) fmrem/yr) /(pCi/g)

(i) (J) Fracti on* t- O.OOOE+00 1.000E+00 3.000E+00 1.OOOE+0l 3.000Z+01 1.000E+02 3.000E+02 1.OOOE+03 Nb-94 Nb-94 1.OOOE+00 2.540E-25 2.519E-25 2.477E-25 2.336E-25 1.975E-25 5.721E-02 1.690E-01 1.561E-04

Ni-63 Ni-63 1.OOOE+00 0.0002+00 O.OOOE+00 0.000E+00 O.OOOE+00 C.000E+00 O.OOOE+00 0.000E+00 O.OOOE+00 Pu-23B Pu-238 1. 000+00 0.OOOE+00 0.000+00 0.000E+00 0.0000E+O0 .OOOE+00 O. OOOE+00 O.OOOE+00 0. 00OE+00 Pu-238 U-234 1.000E+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 Pu-238 Th-230 1.000E+00 0.000E+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 Pu-23B Ra-226 1. OOOE+00 1.768E-15 2.647E-14 3.076E-13 8.047E-12 1.893E-10 5.945E-09 1.152E-07 2.004E-06 Pu-238 Pb-210 1.000+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0. OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 Pu-238 Po-210 1. 000E+00 0.000E+00 O.OOOE+00 2.803E-45 3.531E-43 2.527E-41 2.208E-39 9.392E-38 5.700E-36 Pu-238 ZOSR(j) 1.768E-15 2.647E-14 3.076E-13 8.047E-12 1.893E-10 5.9452-09 1. 152E-07 2.004E-06 Pu-239 Pu-239 1.000E+00 3.817E-42 3.826E-42 3.844E-42 3.907E-42 4.097E-4 2 4.839E-42 7.777E-42 4.096E-41 Pu-239 U-235 1.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 0.000E+00 0. OOOE+00 1.401E-45 1.822E-44 Pu-239 Pa-231 1.OOOE+00 0.0000E+0 O.OOOE+00 O.OOOE+00 0.000E+00 5.60SE-45 7.147E-44 9.613E-43 4.400E-41 Pu-239 Ac-227 1.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 0.000E+00 8.40BE-45 2.22BE-43 4.322E-42 2.312E-40 Pu-239 EDSR(U) 3.817E-42 3.826E-42 3.844E-42 3.907E-42 4.111E-42 5.133E-42 1.306E-41 3.162E-40 Pu-241 Pu-241 1. OOOS+00 0.000+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0. OOOE+O0 O.OOOE+00 O.OOOE+00 Pu-241 A~n-241 1,.OOO+00 0.000E+00 O.OOO+00 O.OOOE+00 O.OOOE+00 0.000+00 0.OOOE+00 O.OOOE+00 0.0002E+0 Pu-241 Np-237 1.000E+00 2.8032-45 2.102E-44 1.093E-43 8.898E-43 5.895E-42 3.592E-41 1.664E-40 1.652E-39

.Pu-241 U-233 1. 0002+00 C.OOOE+00 .0.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 0.000E+00 O.OOOE+00 0 OOE+00 Pu-241 Th-229 1.OOOZ+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 1.682E-44 8.380E-43 1,097E-40 Pu-241 ZDSR(i) 2.803E-45 2.102E-44 1.093E-43 8.89BE-43 5.895E-42 3.593E-41 1.672E-40 1.762E-39 Pu-241 Pu-24 1 2.450E-05 0. 000E+00 0.000E+0 0.000E+00 0.000E+00 0.00OE400 0.000E+00 0.000E+00 O.OOOE+00 Pu-241 Np-237 2.450E-05 0.OOOE+00 0.000E+OC 1.401E-45 2.803E-45 4.204E-45 7.006E-45 1.121E-44 5.325E-44 Pu-241 U-233 2.450E-05 0.000E+00 0.OODE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Pu-241 Th-229 2. 450E-05 0.000Z+00 0.000E+00 0.000E+00 O.OOOE+00 C.000E+00 O.OOOE+00 O.OOOE+00 7.006E-45 Pu-241 ZDSR(i) 0.0002+00 0.000E+00 1.401E-45 2.803E-45 4.204E-45 7.006E-45 1.121E-44 .6.026E-44 Sr-90 Sr-90 1.000E+00 5.327E-36 5.212E-36.4.991E-36 4.287E-36 2.7762-36 6.067E-37 7.872E-39 1.401E-45 Tc-99 Tc-99 1.000Z+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 1.272E-02 3.789E-02 3.576E-05

'Branch Fraction is the cumulative factor for the j't principal radionuclide daughter: CUMBRF(j) - BRF(1)*BRF(2)* ... BRF(j).

The DSR includes contributions from associated Ihalf-life S 30 days) daughters.

RESRAD, Version 6.22 T Limit - 30 days 08/30/2004 14:42 Page 39 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Single Radionuclide Soil Guidelines G(i,t) in pCi/g Basic Radiation Dose Limit - 5.000E+00 mrem/yr Nuclide li) t- O.OOOE+00 1.OOOE+00 3.0002+00 1.OOOE+01 3.000E+01 1.OOOE+02 3.000E+02 1.000E+03 Ag-10 m *2. 608E+13 *2. 608E+13 *2.608E+13 '2. 608E+13 *2.608E+13 1.343E+02 1.342E+02 6.471E+06 A~m-241 '3.424E+12 *3.424E+12 *3.424E+12 *3.424E+12 *3.424E+12 *3.424E+12 *3.424E+12 *3. 424E+12 C-14 *4.454E+12 *4.454E+12 *4 .454E+12 ^4.454E+12 '4.454E+12 2.845E+02 9.781E+01 1.125E+05 Cm-243 '5.159E+13 '5.159E+13 *5.159E+13 *5.159E+13 *5.159E+13 *5.159E+13 *5.159E+13 *5.159E+13 Co-60 *1.131E+15 *1.131E+15 *1.131E+15 *1.131E+15 *1.131E+15 '1. 131E+15 *1.131E+15 '1.131E+15 Cs-134 ^1.294E+15 *1.294E+15 *1.294E+15 *1.294E+15 *1.294E+15 *1.294E+15 *1.294E+15 *1.294E+15 Cs-137 'S.701E+13 *8.701E+13 *e .701E+13 *8 .701E+13 *8.701E+13 '8.701E+13 '8.701E+13 *8.701E+13 Eu-152 '1.765E+14 *1.765E+14 *1.765E+14 *1.765E+14 *1.765E+14 12.765E+14 *1.765E+14 *1.765E+14 Eu-154 *2.639E+14 *2. 639E+14 '2. 639E+14 *2.639E+14 *2.639E+14 -2.6392+14 *2.639E+14 *2.639E+14 Eu-155 4.651E+14 '4. 651E+14 *4.651E+14 '4.651E+14 '4.651E+14 '4.651E+14 *4 .651E+14 '4.651E+14 Fe-55 *2.409E+15 A2.409E+;5

2.409E+15 *2.409E+15 *2.409E+15 '2.409E+15 *2.409-+15 '2.409E+15 H-3 '9.594E+15 *9.594E+15 *9.594E+15 *9.594E+15 +9.594E+15 2.627E+06 6.588E+10 *9.594E+15 Mn-54 *7.744E+15 *7.744E+15 17.744E+15 *7.744E+15 *7.744E+15 '7.744E+15 *7.744E+15 *7.744E+15

b-94 *1.875E+ll *1. 875E+11 *1.875E+ll *1.875E+11 *1.875E+ll 8.739E+01 2.959E+01 3.203E+04 Ni-63 *5.916E+13 *5.916E+13 *5.916E+13 '5.916E+13 +5.916E+13 '5.916E+13 *5. 916E+13 5. 916E+13 Pu-238 *1.711E+13 *1.711E+13 1.625E+13 6.214E+ll 2.641E+10 8 . 411E+08 4.341E+07 2.4 95E+06 Pu-239 *6.212E+10 '6.212E+10 *6.212E+10 -6.212E+10 *6.212E+10 *6.212E+10 *6.212E+10 *6.212E+10 Pu-241 '1.03OE+14 '1.030E+14 *1.030E+14 *1.030E+14 *1.030E+14 '1.030E+14 *1.030E+14 *1.030E+14 Sr-90 *1.365E+14 *1.365E+14 *1.365E+14 *1.365E+14 *1.365E+14 '1.365E+14 *1.365E+14 '1.365E+14 Tc-99 *1.696E+10 -1.696E+10 *1.696E+10 -1.696E+10 *1.696E+10 3.930E+02 1.320E+02 1.398E+05

'At specific activity limit

RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 40 Su~mary : Haddam Neck Material at USEI File: Cv USEIC.RAD Surmed Dose/Source Ratios DSR(it) in (mrem/yr3/(pCi/g) and Single Radionuclide Soil Guidelines Glit) in pCi/g at tmin - time of minimum single radionuclide soil guideline and at tmax - time of maximum total dose - 122.1 +/- 0.2 years Nuclide Initial tnin DSR(i tminl G(itnin) DSR(itmax) G(itmax)

(i) (pCi/g) (years) (pCi/g) (pCi/g)

Ag-10 m 1.000E+00 122.2 +/- 0.2 5.763E-01 8.676E+C0 5.764E-01 B.674E+0 Am-241 1.000E+00 0.000E+00 0.000E+00 13.424E+12 0.000E+00 *3.424E+l C-14 1.00OE+00 122.2 +/- 0.2 3.060E-01 1.634E+01 3.060E-01 1.634E+01 Cm-243 1.000E+00 0.000E+00 0.000E+00 *5.159E+13 0.000E+00 *5.159E+13 Co-60 1.000E+00 0.OOOE+00 1.653E-21 *1.131E+15 2.080E-28 *1.131E+15 Cs-134 1.000E+00 0.000E+00 5.881E-26 '1.294E+15 0.000E400 1.294E+15 Cs-137 1.000E+00 0.000E+00 6.E50E-27 8.701E+13 5.012E-28 8.701E+13 Eu-152 1.OOOE+00 0.000E+00 1.567E-23 11.765E+14 3.286E-26 *1.765E+14 Eu-154 1.OOOE+00 0.000E+00 5.997E-23 -2.639E+14 4.764E-27 *2.639E+14 Eu-155 1.000E+00 0.000E+00 0.000E+00 *4.651E+14 0.000Z+00 *4.651E+14 Fe-55 1.000E+00 0.000E+00 0.000E+00 *2.409E+15 0.000E+00 *2.409E+15 F-3 1.000E+00 115.2 +/- 0.2 1.045E-05 4.784E+05 9.638E-06 5.188E+05 Mn-54 1.000E+00 0.000E+00 6.286E-25 *7.744E+15 0.000E+00 *7.744E+15 Nb-94 1.000E+00 122.2 +/- 0.2 9.960E-01 5.020E+00 9.961E-01 5.020E+00 Ni-63 1.000E+00 0.000E+00 0.000E+00 *5.916E+13 0.000E+00 *5.916E+13 Pu-238 1. 000E+00 1.000E+03 2.004E-06 2.495E+06 1.038E-08 4.816E+08 Pu-239 1.000E+00 0.OOOE+00 0.000E+00 *6.212E+l0 0.000E+00 *6.212E+10 Pu-241 1.0E+00 0.OOOE+00 0.000E+00 *1.030E+14 0.000E+00 *1.0305+14 Sr-90 1. 000E+00 0.OOOE+00 0.000E+00 *1.365E+14 O.OOOE+00 *1.365E+14 Tc-99 1.000E+00 122.2 + 0.2 2.221E-01 2.251E+01 2.221E-01 2.251E+01

At specific activity limit

f RESRAD, Version 6.22 T4 Limit - 30 days 08/30/2004 14:42 Page 41 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Individual Nuclide Dose Summed Over All Pathways Parent Nuclide and Branch Fraction Indicated Nuclide Parent BRF~i) DOSE(Jt), mrem/yr (J) Ui) t- O.OOOE+00 1.OOOE+O 3.000E+00 1.000E+01 3.OOOE+01 1.OOOE+02 3.000E+02 1.000E+03 Ag-1086m Ag-108m 1.OOOE+00 5.402E-27 5.329E-27 5.185E-27 4.711E-27 3.582E-27 3.723E-02 3.727E-02 7.727E-t An-2 41 Am-241 1.000E+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+t Am-2 41 Pu-241 1.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+t Am-241 LDOSEIj) 0.000E+00 O.OOOE+00 O.OOO+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+t Np-237 Am-241 1.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 0.OOOE+00 Np-237 Pu-241 1.OOOE+00 0.OOOE+00 O.OOOE+O O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Np-237 Pu-241 2.450E-05 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+0 O.OOOE+00 C.OOOE+00 O.OOOE+00 Np-237 EDOSECI) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.0OOE+00 A

U-233 Am-241 1.OOOE+00 O.OOOE+00 O.OOOE+0 O.OOOE+00 O.000E+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 U-233 Pu-241 1.OOOE+00 O.OOOE+00 O.OOOE+0O O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 U-233 Pu-241 2.450E-05 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 U-233 EDOSE(j) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+OO O.OOOE+00 O.0OOE+OO O.OOOE+00 O.OOOE+00 Th-229 Pm-241 1.OOOE+00 O.OOOE+00 O.OOOE+OO 0.000E+00 O.OOOE+00 O.OOOE+OO O.OOOE+00 O.OOOE+00 O.OOOE+00 Th-229 Pu-241 1.0000+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+OO O.OOOE+00 0.000E+00 O.OOOE+00 Th-229 Pu-241 2.450E-05 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+OO O.OOOE+00 0.000E+00 O.OOOE+00 Th-229 EDOSE(ij O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+O00 .000E+OO C-14 C-14 1.OOOE+00 O.OOOE+00 .OOOE+00 0.000E+00 O.OOOE+00 0.OOE+00 1.757E-02 5.112E-02 4.443E-05 Cm-243 Cm-243 9.976E-01 0.000E+00 C.000E+00 0.000E+00 O.OOOE+00 O.OOO+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Cm-243 Cm-243 2.400E-03 O.OOOE+OO O.OOOE+00 O.OOOE+00 O.0OOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 Cm-243 LMOSE j) 0.0000E+0 O.OOOE+00 0.000E+00 0.000E+00 O.OOO+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Pu-239 Cm-243 9.976E-01 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Pu-239 Cm-243 2.400E-03 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Pu-239 Pu-239 1.000E+00 O.OOOE+OO O.OOOE+00 0.000E+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Pu-239 LDOSE(J) O.OOOE+OO C.OOCE+00 0.000E+OO 0.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 C.OOOE+00 J-235 Cm-243 9.976E-01 O.OOOE+OC 0.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 U-235 Cm-243 2.400E-03 0.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 U-235 Pu-239 1.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 .OOOE+00 O.OOOE+00 O.OOE+00 O.OOOE+00 U-235 ZDOSE(C) O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 0.000E+00 O.OOOE+00 0.000E+00 Pa-231 Cm-243 9.976E-01 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+000.OOOE+00 Pa-231 Cm-243 2.400E-03 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 C.COOE+00 0.000E+00 O.OOOE+00 0.000E+00 Pa-231 Pu-239 1.OOOE+00 O.OOOE+00 O.OOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Pa-231 ZDOSE(J) O.OOOE+00 O.OOOE+00 O.OOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 Ac-227 Cn-243 9.976E-01 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOE++00 .OOOE+t Ac-227 Cm-243 2.400E-03 0.000E+00 0.000E+00 O.OOOE+00 O.0OOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+(

Ac-227 Pu-239 1.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+t Ac-2 27 EDOSE(j) O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 0.0000E+00 .OOOE+00 0.000E+00 O.OOOE+C Am-243 Cm-243 2.400E-03 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 0.0OOE+00 O.OOOE+00 O.OOOE+C

,'o -60 CO-60 1.OOOE+00 1.653E-21 1.451E-21 1.119E-21 4.500E-22 3.335E-23 3.694E-27 O.OOOE+00 O.OOOE+00

RESRAD, Version 6.22 TS Limit - 30 days 08/30/2004 14:42 Page 42 Summary : Haddam Neck Material at USEI File: CYOUSEIC.HAD Individual Nuclide Dose Summed Over All Pathways Parent Nuclide and Branch Fraction Indicated Nuclide Parent BRF(i) DOSE(J,t), mrem/yr Ii) Ui) t- O.OOOE+00 1.000E+00 3.000E+00 1.000E+01 3.000E+01 1.000E+02 3.000E+02 1.OOOE+03 Cs-134 Cs-134 1.000E+00 5.881E-26 4.209E-26 2.156E-26 2.074E-27 2.578E-30 O.OOOE+00 O.OOOE+00 0.000E+00 Cs-137 Cs-137 I.OOOE+00 6.850E-27 6.705E-27 6.424E-27 5.530E-27 3. 603E-27 8.047E-26 1.110E-29 O.OOOE+00 Eu-152 Eu-152 7.208E-01 1.130E-23 1.074E-23 9.708E-24 6.817E-24 2.483E-24 7 .236E-26 2.969E-30 O.OOOE+00 Eu-152 Eu-152 2.792E-01 4.376E-24 4.160E-24 3.761E-24 2. 641E-24 9. 616E-25 2.803E-26 1.150E-30 O.OOOE+00 Eu-152 EDOSE (C) 1.567E-23 1.490E-23 1.347E-23 9.458E-24 3.444E-24 1.004E-25 4.119E-30 O.OOOE+00 Gd-152 Eu-152 2.792E-01 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.COOE+00 0. OOOE+00 0. OOOE+00 O.OOOE+00 0.000E+00 Eu-154 Eu-154 1.000E+00 5.,997E-23 5.550E-23 4.755E-23 2.768E-23 5.897E-24 2.633E-26 O.OOOE+00 O.OOOE+00 Eu-155 Eu-155 1.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 Fe-55 Fe-55 1.000E+00 O.OOOE+00 0.000E+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 H-3 H-3 1.OOOE+00 0.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 1.903E-06 7.590E-l1 O.OOOE+00 Mn-54 Mn-54 1.OOOE+00 6.286E-25 2.800E-25 5.558E-26 1. 935E-2e 0.000Z+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Nb-94 Nb-94 l.OOOE+CO 2.54OE-25 2.519E-25 2.477E-25 2.336E-25 1.975E-25 5.721E-02 1.690E-01 1.561E-04 Ni-63 Ni-63 1.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 0000E+00

,?u-238 Pu-238 1.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0. OOOE+00 O.OOOE+00 0.000E+00 U-234 Pu-238 1.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 Th-230 Pu-238 1.000E+00 O.OOOE+00 0 .OOOE+OO O.OOOE+00 O.OOOE+00 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 Ra-226 Pu-238 l.OOOE+00 1.768E-15 2.647E-14 3.076E-13 8.047E-12 1.893E-10 5.945E-09 1.152E-07 2.004E-06 Pb-210 Pu-238 1.000E+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00 Po-210 Pu-238 l.000E+00 0.000E+00 0.000E+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+OO O.OOOE+00 O.OOOE+00 Pu-241 Pu-241 1.000E+00 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.O0OE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Pu-241 Pu-241 2.450E-05 O.OOE+00 0.000E+00 0. OOE+00 O.OOOE+OO 0.000E+00 0.000E+00 0.000E+00. 0.000E+00 Pu-241 ZDOSE(J) 0.000E+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Sr-90 Sr-90 1.OOOE+00 O.OOOE+00 O.OOOE+00 0. OOOE+00 O.OOOZ+00 O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 t'C-99 Tc-99 1.000E+00 0.000E+00 0.000E+00 O.OOOE+00 O.OOOE+000.OOOE+00 1.272E-02 3.789E-02 3.576E-05 BRF(i) is the branch'fraction of the parent nuclide.

I RES

! RESRAD, Version 6.22 Tst Limit - 30 days 08/30/2004 14:42 Page 43 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Individual Nuclide Soil Concentration Parent Nuclide and Branch Fraction Indicated Nuclide Parent BRF(i) S(J,t), pCi/g U) (i) t- O.OOOE+00 1.000E+00 3.OOOE+00 1.000E+01 3.000E+01 1.000£+02 3.000E+02 1.000E+03 Ag-108m Ag-108i 1.000E+00 1.000E+00 9.847E-01 9.548E-01 8.571E-01 6.296E-01 2.139E-01 9.78BE-03 2.006E-C Am-241 Am-241 1.000E+00 1.000E+00 9.983E-01 9.950E-01 9.E33E-01 9.507E-01 8.448E-01 6.030E-01 1.852E-C Am-241 Pu-241 1.OOOE+00 O.OOOE+00 1.562E-03 4.4 60Z-03 1.259E-02 2.463E-02 2. 883E-02 2.078E-02 6.383E-C AM-241 ES(J): 1.000E+00 9.999E-01 9.994E-01 9.959E-01 9.753E-01 8. 737E-01 6.238E-01 1.916E-C Np-237 Am-241 1.000E+00 O.OOOE+00 3.236E-07 9.692E-07 3.212E-06 9.474E-06 2.980E-05 7. 618E-05 1.558E-04 Np-237 Pu-241 1.000E+00 0.000E+00 2.550E-10 2.221E-09 2.209E-08 1.494E-07 7.969E-07 2.394E-06 5.139E-06 Np-237 Pu-241 2.450E-05 O.OOOE+OC 7.748E-12 2.217E-11 6.298Z-11 1.259E-10 1.634E-10 1.645E-10 1. 637E-10 Np-237 ES (j): O.OOOE+00 3.239E-07 9.715E-07 3.234E-06 9.624E-06 3.059E-05 7. 857E-05 1. 610E-04 U-233 Ar-241 1.000E+00 O.OOOE+00.7.078E-13 6.363E-12 7.042E-11 6.265E-10 6.690E-09 5.397E-08 4.268E-07 U-233 Pu-241 1.000E+00 0.OOOE+00 3.732E-16 9.833E-15 3.350E-13 7.271E-12 1.502E-10 1 .579E-09 1.37 4E-08 U-233 Pu-241 2. 450E-05 O.OOOE+00 1.708E-17 1.489E-16 1.4B7E-15 1.018E-14 5.713E-14 2.000E-13 6. 904E-13 U-233 ES(J) : O.OOOE+00 7.082E-13 6.373E-12 7.075E-11 6.338E-10 6.840E-09 5.555E-08 4.405E-07

.Th-229 Am-241 1. OOOE+00 O.OOOE+00 2.241E-17 6.04 4E-16 2.231E-14 5.970E-13 2.143E-11 5.301E-10 1.487E-08 Th-229 Pu-241 1.OOOE+00 O.OOOE+00 8.882E-21 7.054E-19 a. 142E-17 5.521E-15 4.171E-13 1.454E-11 4.682E-10

Th-229 Pu-241 '2.450E-05 O.OOOE+00 5.426E-22 1.431E-20 4. 88E -19 1.070E-17 2.284E-16 2.648E-15 3.136E-14 Th-229 Zs (j) : O.OOOE+00 2.242E-17 6.051E-16 2.240E-14 6.026E-13 2.184E-11 5.446E-10 1.533E-08 C-14 C-14 1.000E+00 1.000E+00C9.900E-01 9.702E-01 9.041E-01 7.389E-01 3.648E-01 4.853E-02 4:169E-05 Cn-243 Cm-243 9.976E-01 9.976E-01 9.736E-01. 9.274E-01 7.822E-01 4.8095-01 8.763E-02 6.762E-04 2.729E-11 Cr-243 Cm-243 2.400E-03 2.400E-03 2.342E-03 2.231E-03 1. 882E-03 1.157E-03 2.108E-04 1.627E-06 6.565E-14 CM-243 ES Ci): 1.000E+00 9.760E-01 9.296E-01 7.841E-01 4.821E-01 8.784E-02 6.77EE-04 2.735E-11 Pu-239 Cm-243 9.976E-01 O.OOOE+00 2.839E-05 8.313£-05 2.550E-04 6.116E-04 1.075£-03 1.172E-03 1.14SE-03 Pu-239 Cm-243 2. 400E-03 0.000E+00 3.224E-12 2.855E-11 3. OOOE-10 2.322E-09 1.657E-08 6.732E-08 2.320E-07 Pu-239 Pu-239 1.000E+00 1.000E+00 1.000E+00 9.999E-01 9.997E-01 9.991E-01 9.970E-01 9.911E-01 9.708E-01 Pu-239 ES(J): 1.000E+00 1.000E+00 1.000E+00 1.000E+00 9.997E-01 9.981E-01 9.923E-01 9.719E-01 U-235 Cm-243 9.976E-01 O.OOOE+00 1.404E-14 1.243E-13 1.307E-12 1.012E-11 7.253£-11 2.987E-10 1.082E-09 1-235 Cm-243 2.400E-03 0.000E+00 1.061E-21 2.829E-20 1.005E-1E 2.419E-17 6.356E-16 8.849E-15 1.122E-13 235 Pu-239 1.000E+00 0.000E+00 9.848E-10 2.954E-09 9.845E-09 2.952E-08 9.817E-08 2.926E-07 9.539E-07 U-235 ES (J): O.OOOE+00 9.848E-10 2.954E-09 9.847E-09 2.953E-08 9.B24E-08 2.929E-07 9.54 9E-07 Pa-231 Q. -243 9.976E-01 0.000+00 9.919E-20 2.646E-1B 9.398E-17 2.265E-15 5.964E-14 8.367E-13 1.091E-11 Pa-231 Cm--243 2.4 ODE-03 O.OOOE+00 5.617E-27 4.506E-25 5.378E-23 3.971E-21 3.694E-19 1.6E5E-17 7.660E-16 Pa-231 Pu-239 1.OOOE+00 O.OOOE+00 1.042E-14 9.376E-14 1.041E-12 9.366E-12 1.038E-10 9.266E-10 1.OO1E-08 Pa-231 ES I): O.OOOE+00 1.042E-14 9.376E-14 1.042E-12 9.368E-12 1.038E-10 9.274E-10 1.002E-08 Ac-227 CQ-243 9.976E-01 O.OOOE+00 7.853E-22 6.220E-20 7.107E-18 4.654E-16 2.989E-14 6.61SE-13 1.021E-3 Ac-227 Cm-2 43 2.400E-03 0.OOOE+00 3.560E-29 8.491E-27 3.275E-24 6.657£-22 1.574E-19 1.218E-17 6.955E-3 Ac-227 Pu-239 1. 000+00 O.OOOE+00 1.097E-16 2.915E-15 1.022E-13 2.386E-12 5.817E-11 7.520E-10 9.391E-C Ac-227 ESIj): 0.OOOE+00 1.097E-16 2.915E-15 1.023E-13 2.386E-12 5.820E-11 7.527E-10 9.401E-(

Am-243 C0-243 2.400E-03 O.OOOE+00 2.230E-07 6.529E-07 2.002E-06 4.792E-06 8.362E-06 8.853E-06 7.814E-C Co-60 C2-60 l.OOOE+OO 1.000E+00 8.768E-01 6.740E-01 2.685E-01 1.935E-02 1.945E-06 7.355E-18 0.000E+00

RESRAD, Version 6.22 T'i Limit - 30 days 08/30/2004 14: 42 Page 44 Summary : Haddam Neck Material at USEI File: CY USEIC.RAD Individual Nuclide Soil Concentration Parent Nuclide and Branch Fraction Indicated Nuclide Parent BRF() S(J,t), pCi/g Cj) (i) t- O.OOOE+O0 l.OOOE+00 3.000E+00 1.OOOE+01 3.000E+01 1.OOOE+02 3.000E+02 1.000E+03 Cs-134 Cs-134 1.OOOE+00 1.OOOE+00 7.145E-01 3.648E-01 3.468E-02 4.172E-05 2.518E-15 1.541E-44 O.OOOE+00 Cs-137 Cs-137 1.000E+00 1.000E+00 9.772E-01 9.330E-01 7.937E-01 5.000E-01 9.920E-02 9.761E-04 9.224E-11 Eu-152 Eu-152 7.208E-01 7.208E-01 6.843E-01 6.167E-01 4.285E-01 1.515E-01 3.976E-03 1.210E-07 1.879E-23 Eu-152 Eu-152 2.792E-01 2.792E-01 2.651E-01 2.389E-01 1.660E-01 5.867E-02 1.540E-03 4.686E-08 7.280E-24 Eu-152 zs(j): 1.000E+00 9.493E-01 E.556E-01 5.945E-01 2.101E-01 5.516E-03 1.67BE-07 2.607E-23

d-152 Eu-152 2.792E-C1 O.OOOE+00 1.746E-15 4.977E-15 1.397E-14 2.722E-14 3.426E-14 3.444E-14 3.439E-14

! Eu-154 Eu-154 1.OOOE+00 1.000E+00 9.243E-01 7.895E-01 4.549E-01 9.413E-02 3.794E-04 5.462E-11 6.182E-35

Eu-155 Eu-155 1.OOOE+00 1.000E+00 8.696E-01 6.575E-01 2.472E-01 1.511E-02 8.526E-07 6.198E-19 O.OOOE+00 Fe-55 Fe-55 1.000E+00 1.OOOE+00 7.736E-01 4.629E-01 7.675E-02 4.521E-04 7.090E-12 3.565E-34 0.000E+00 H-3 8-3 1.000E+00 1. OOOE+00 9.360E-01 8.201E-01 5.164E-01 1.377E-01 1.34EE-03 2.451E-09 1.985E-29 Mn-54 Mn-54 1.000E+00 1.000E+00 4.448E-01 8 .800E-02 3.03lE-04 2.7852-11 6.548E-36 O.OOOE+00 O.OOOE+00 Nb-94 Nb-94 1.OOOE+00 1.OOOE+00 9.901E-01 9.705E-01 9.049E-01 7.409E-01 3.679E-01 4.981E-02 4.548E-05 Ni-63 Ni-63 1.000E+00 1.OOOE+00 9.928E-01 9.786E-01 9.303E-01 8.052E-01 4.857E-01 1.146E-01 7.303E-04 Pu-238 Pu-238 1.OOOE+00 1. OOOE+00 9.921E-01 9.766E-01 9.24 OE-01 7.890E-01 4.538E-01 9.34E2-02 3.704E-04 J-234 Pu-238 1.OOOE+00 0.OOOE+00 2.824E-06 8.404E-06 2.725E-05 7.568E-05 1.956E-04 3.228E-04 3.472E-04 Th-230 Pu-23E 1.OOOE+00 0. OOOE+00 1.273E-11 1.139E-10 1.243E-09 1.062E-08 9. 954E-08 5.952E-07 2.764E-06 Ra-226 Pu-238 1.OOOE+00 O.OOOE+00 1.839E-15 4.944E-14 1.805E-12 4.676E-11 1.510E-09 2.894E-08 4.702E-07 Pb-210 Pu-238 1.OOOE+00

O.OOOE+00 1.421E-17 1.133E-15 1.325E-13 9.24SE-12 7 .206E-iD 2.222E-08 4.393E-07 Po-210 Pu-238 1.OOOE+00 O.OOOE+00 3.953E-18 6.252E-16 1.081E-13 8.638E-12 7.073E-10 2.211E-08 4.388E-07 Pu-241 Pu-241 1.OOOE+00 1.000E+00 9.530E-01 B. 655E-01 6.179E-01 2.360E-01 6.118E-03 5.351E-07 1.244E-21 Pu-241 Pu-241 2.450E-05 i 2.450E-05 2.335E-05 2.121E-05 1.514E-05 5.781E-06 1.989E-07 1.311E-11 3.047E-26 Pu-241 FS. 0): 1.OOOE+00 9.530E-01 8. 655E-01 6.179E-01 2.360E-01 8.119E-03 5.351E-07 1.244E-21 Sr-90 Sr-90 l.OOOE+OO *l.OOOE+00 9.764E-01 9.309E-01 7.877E-01 4.888E-01 9.200E-02 7.786E-04 4.342E-11 Tc-99 Tc-99 1.OOOE+00 1.000E+00 9.901E-01 9.705E-01 9.051E-01 7.4152-01 3.691E-01 5.028E-02 4.690E-OS 3RF(i) is the branch-fraction of the parent nuclide.

RESCALC.EXE execution time - 7.40 seconds

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill APPENDIX C Technical Bases for RESRAD Input Parameters

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill General Appendix C contains a list of all input parameters used to model the disposal of the Connecticut Yankee Haddam Neck Plant decommissioning waste at the US Ecology Landfill. Twelve (12) site specific parameters were used. All other values not specifically addressed herein are the recommended values selected by the developers of RESRAD and are discussed in the RESRAD manual [Reference 1].

References Four (4) principal references were used in developing the parameters contained in this section. These are:

1. ANL/EAD/LD-2, "Manual for Implementing Residual Radioactive Material Guidelines Using RESRAD, Version 5.0," C. Yu et al, Argonne National Laboratory, September, 1993.

2. Notification of a Class I Modification, Administrative and Informational Changes to Waste Acceptance Parameters, Appendix A, RESRAD Modeling of Post Closure Dose, Page 2, Envirosafe Services of Idaho, Inc., 2000.

3. CH2M Hill, Hydrogeologic Characterization and Ground Water Monitoring Considerations for Proposed Cell 14 Expansion Area at Envirosafe Services of Idaho - Site B, Pages 35 -39, Envirosafe Services of Idaho, 1993.

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill Parameters Specific to USEI.

1) Area of contaminated zone:

900 square meters - Estimated by the disposal facility for disposal of the anticipated volume of waste material (i.e., 1E8 pounds of waste at 1.5 g/cc density with a 33.6 m depth in a circular area).

2) Thickness of contaminated zone:

33.6 meters - Estimated by the disposal facility for designated disposal cell.

3) Length parallel to aquifer flow:

33.85 meters - the diameter of the circular area associated with the disposal volume.

4) Cover depth:

3.6 meters - designated cover depth for the disposal cell.

5) Density of cover material:

1.78 grams per cubic centimeter - compacted cover material density

[Reference 2].

6) Cover erosion rate:

1 E-4 meters per year - erosion rate for landfill area [Reference 3].

7) Contaminated zone hydraulic conductivity:

31.6 meters per year - groundwater transport rate through compacted landfill material [Reference 2].

8) Evapotranspiration coefficient:

0.75 - Evapotranspiration factor for landfill [Reference 2].

9) Precipitation 0.184 meters per year - annual rainfall for landfill area ((Reference 2].

Assessment of the Radiological Effects on Future Residents from the Alternative Disposal of the Solid Waste from the Decommissioning of the Haddam Neck Plant at the US Ecology Idaho Hazardous Waste Landfill

10) Saturated zone hydraulic conductivity:

6.7 meters per year - groundwater transport rate within the saturated zone

[Reference 2].

11) Saturated zone hydraulic gradient:

7E the groundwater gradient within the saturated zone [Reference 2].

12) Unsaturated zone thickness:

61 meters - distance between the contaminated zone (i.e., landfill material) and saturated zone (i.e., water table) [Reference 3].

CY-04-168, Request for Approval of Proposed Procedures in Accordance with 10 CFR 20.2002

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