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| author name = Dewald L | | author name = Dewald L | ||
| author affiliation = Entergy Nuclear Vermont Yankee, LLC | | author affiliation = Entergy Nuclear Vermont Yankee, LLC | ||
| addressee name = Emch R | | addressee name = Emch R | ||
| addressee affiliation = NRC/NRR/ADRO/DLR/REBB | | addressee affiliation = NRC/NRR/ADRO/DLR/REBB | ||
| docket = 05000271 | | docket = 05000271 | ||
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04/02/2007 1:36:40 PM two of two messages with attachments document. | 04/02/2007 1:36:40 PM two of two messages with attachments document. | ||
Lynn Lynn DeWald Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Road Vernon, VT 05354 802-258-5526 (phone)802-258-5865 (fax)802-380-4493 (cell) | Lynn Lynn DeWald Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Road Vernon, VT 05354 802-258-5526 (phone)802-258-5865 (fax)802-380-4493 (cell) | ||
Ic-:\ t em-,p \--G-W}O)O-0-001 .TMP PM-gel_-- eA 11 Mail Envelope Properties (46113FIC.79E | Ic-:\ t em-,p \--G-W}O)O-0-001 .TMP PM-gel_-- eA 11 Mail Envelope Properties (46113FIC.79E | ||
: 14 : 14238) | : 14 : 14238) | ||
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==Dear Sir:== | ==Dear Sir:== | ||
In accordance with the criteria of the Code of Federal Regulations, Title 10, Section 20.302(a) | In accordance with the criteria of the Code of Federal Regulations, Title 10, Section 20.302(a) | ||
(10CFR20.302(a)), enclosed please find the subject application for the disposal of very low level radioactive waste materials. | (10CFR20.302(a)), enclosed please find the subject application for the disposal of very low level radioactive waste materials. | ||
Vermont Yankee Nuclear Power Corporation (Vermont Yankee) hereby requests NRC approval of the proposed procedures for the disposal of slightly contaminated septic waste generated at the Vermont Yankee Nuclear Power Plant in Vernon, Vermont.This application specifically requests approval to dispose of septic tank waste, contaminated at minimal levels, which have been or might be generated through the end of station operations at the Vermont Yankee Nuclear Power Plant. The proposed method of disposal is for the on-site land spreading in designated areas in compliance with State of Vermont health code requirements for septic waste. Disposal of this waste in the manner proposed, rather than at a 10CFRPart 61 licensed facility would save Vermont Yankee not only substantial cost, but also valuable disposal site space which would then be available for wastes of higher radioactivity levels. Disposal as radioactive waste would require treatment of the biological aspects of the septage and solidification to a stable waste form, thereby increasing the volume substantially. | Vermont Yankee Nuclear Power Corporation (Vermont Yankee) hereby requests NRC approval of the proposed procedures for the disposal of slightly contaminated septic waste generated at the Vermont Yankee Nuclear Power Plant in Vernon, Vermont.This application specifically requests approval to dispose of septic tank waste, contaminated at minimal levels, which have been or might be generated through the end of station operations at the Vermont Yankee Nuclear Power Plant. The proposed method of disposal is for the on-site land spreading in designated areas in compliance with State of Vermont health code requirements for septic waste. Disposal of this waste in the manner proposed, rather than at a 10CFRPart 61 licensed facility would save Vermont Yankee not only substantial cost, but also valuable disposal site space which would then be available for wastes of higher radioactivity levels. Disposal as radioactive waste would require treatment of the biological aspects of the septage and solidification to a stable waste form, thereby increasing the volume substantially. | ||
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Vermont Yankee Nuclear Power Corporation (Vermont Yankee) requests approval, pursuant to lOCFR20.302(a), of a method proposed herein for the routine disposal of slightly contaminated septic tank waste. Vermont Yankee proposes to dispose of this waste by spreading it on designated areas within the plant's site boundary fence. This application addresses specific information requested in 10CFR20.302(a). | Vermont Yankee Nuclear Power Corporation (Vermont Yankee) requests approval, pursuant to lOCFR20.302(a), of a method proposed herein for the routine disposal of slightly contaminated septic tank waste. Vermont Yankee proposes to dispose of this waste by spreading it on designated areas within the plant's site boundary fence. This application addresses specific information requested in 10CFR20.302(a). | ||
2.0 WASTE STKAMDESCIpIN The waste involved in this application consists of residual solids and water associated with the sewage collection system at Vermont Yankee. The plant's sewage systems are of the septic tank and disposal field type. The two systems servicing the majority of the plant's sanitary waste are identified as (I).main septic system and (2) the south sewage disposal system.The main septic system (design flow capacity 4,950 gallons/day) consists of a wastewater lift station, septic tank, and dual alternating disposal fields located on the north side of the plant. This system services the main complex of buildings central to the plant and processes approximately 3,500 gallons of wastewater per day. The septic tank, shown in Figure (1), will typically contain 9,250 gallons of septage.The south sewage disposal system is a newly-installed (January 1989)pressurized mound system, which is used in lieu of the construction office building (COB) holding tank that had previously serviced the lavatory facilities on the south end of the plant. The new system is composed of a septic tank (5,700 gallon capacity, see Figure 2), pumping station, and pressurized mound disposal field. When dosing the field, a force main pressurizes the disposal field's piping system with the septic tank effluent, which distributes throughout the field. The south sewage disposal system has 1-1 66771( | |||
STKAMDESCIpIN The waste involved in this application consists of residual solids and water associated with the sewage collection system at Vermont Yankee. The plant's sewage systems are of the septic tank and disposal field type. The two systems servicing the majority of the plant's sanitary waste are identified as (I).main septic system and (2) the south sewage disposal system.The main septic system (design flow capacity 4,950 gallons/day) consists of a wastewater lift station, septic tank, and dual alternating disposal fields located on the north side of the plant. This system services the main complex of buildings central to the plant and processes approximately 3,500 gallons of wastewater per day. The septic tank, shown in Figure (1), will typically contain 9,250 gallons of septage.The south sewage disposal system is a newly-installed (January 1989)pressurized mound system, which is used in lieu of the construction office building (COB) holding tank that had previously serviced the lavatory facilities on the south end of the plant. The new system is composed of a septic tank (5,700 gallon capacity, see Figure 2), pumping station, and pressurized mound disposal field. When dosing the field, a force main pressurizes the disposal field's piping system with the septic tank effluent, which distributes throughout the field. The south sewage disposal system has 1-1 66771( | |||
Richard Emch -bvy 89,69.tif.__ | Richard Emch -bvy 89,69.tif.__ | ||
Pae the design flow capacity to process 4,607 gallons of wastewater per day. The system is typically loaded at approximately 2,500 gallons per day during normal plant operations. | Pae the design flow capacity to process 4,607 gallons of wastewater per day. The system is typically loaded at approximately 2,500 gallons per day during normal plant operations. | ||
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x (1/25.4) [dry/wet ratio]~ 700 [kg] per pump-out of both tanks or, 1,400 kg of dry solids per year.3.0 DISPOSAL METHOD Approval of this application will allow Vermont Yankee to dispose of septage by utilization of a technique of land spreading or surface injection in a manner consistent with all applicable state of Vermont health regulations regarding disposal of septic waste. Details of the chemical and biological controls necessary to satisfy state health code requirements are provided in Reference 5.The septage will be spread or surface injected on land areas owned by Vermont Yankee and situated within the plant's site boundary. | x (1/25.4) [dry/wet ratio]~ 700 [kg] per pump-out of both tanks or, 1,400 kg of dry solids per year.3.0 DISPOSAL METHOD Approval of this application will allow Vermont Yankee to dispose of septage by utilization of a technique of land spreading or surface injection in a manner consistent with all applicable state of Vermont health regulations regarding disposal of septic waste. Details of the chemical and biological controls necessary to satisfy state health code requirements are provided in Reference 5.The septage will be spread or surface injected on land areas owned by Vermont Yankee and situated within the plant's site boundary. | ||
Transportation of the septage waste to the disposal areas will involve pumping from one of the septic waste collection tanks (i.e., main septic tank, COB holding tank, 1-4 6677R R hadmch -bvy 8 959 tif~ aeO new replacement COB septic tank, or from any other on-site septic waste collection point) into an enclosed truck-mounted tank. The enclosed tank truck is used to prevent spillage while in transit to the disposal areas. The septage will be transported to one of the two disposal sites designated for land application for septage from Vermont Yankee, and applied at a fixed rate based on either limitations imposed by the state of Vermont for heavy metals or organic content of the waste, or on the radioactivity content such that projected maximum individual doses will not exceed established dose objectives. | Transportation of the septage waste to the disposal areas will involve pumping from one of the septic waste collection tanks (i.e., main septic tank, COB holding tank, 1-4 6677R R hadmch -bvy 8 959 tif~ aeO new replacement COB septic tank, or from any other on-site septic waste collection point) into an enclosed truck-mounted tank. The enclosed tank truck is used to prevent spillage while in transit to the disposal areas. The septage will be transported to one of the two disposal sites designated for land application for septage from Vermont Yankee, and applied at a fixed rate based on either limitations imposed by the state of Vermont for heavy metals or organic content of the waste, or on the radioactivity content such that projected maximum individual doses will not exceed established dose objectives. | ||
3.1 Seotic Was_ Disposal Procedure Gamma isotopic analysis of septic waste shall be made prior to each disposal by obtaining a representative sample from each tank prior to pump-out. | |||
Was_ Disposal Procedure Gamma isotopic analysis of septic waste shall be made prior to each disposal by obtaining a representative sample from each tank prior to pump-out. | |||
At least two septic waste samples will be collected from each tank to be pumped by taking a volumetric column of sludge and waste water which allows for analysis of the solid's distribution and content from top to bottom of each tank. The weight percent of solid content of the collected waste will be determined and applied to the gamma isotopic analysis in order to estimate the total radioactivity content of each tank to be pumped and spread on designated disposal fields.These gamma isotopic analyses of the representative samples will be performed at the environmental Technical Specification lower limit of detection (LLD) requirements for liquids (see Technical Specification Table 4.9.3) in order to document the estimation of radiological impact from septage disposal.The radionuclide concentrations and total radioactivity identified in the septage will be compared to the concentration and total curie limits established herein prior to disposal. | At least two septic waste samples will be collected from each tank to be pumped by taking a volumetric column of sludge and waste water which allows for analysis of the solid's distribution and content from top to bottom of each tank. The weight percent of solid content of the collected waste will be determined and applied to the gamma isotopic analysis in order to estimate the total radioactivity content of each tank to be pumped and spread on designated disposal fields.These gamma isotopic analyses of the representative samples will be performed at the environmental Technical Specification lower limit of detection (LLD) requirements for liquids (see Technical Specification Table 4.9.3) in order to document the estimation of radiological impact from septage disposal.The radionuclide concentrations and total radioactivity identified in the septage will be compared to the concentration and total curie limits established herein prior to disposal. | ||
The methodology and limits associated with determining compliance with the disposal dose and activity criteria are described in Attachment | The methodology and limits associated with determining compliance with the disposal dose and activity criteria are described in Attachment | ||
: 2. If the concentration and total activity limits are met, compliance with the dose assessment criteria will have been demonstrated since the radiological analysis (Section 4.5 and Attachment | : 2. If the concentration and total activity limits are met, compliance with the dose assessment criteria will have been demonstrated since the radiological analysis (Section 4.5 and Attachment | ||
: 2) was based on evaluating the exposure to a maximally exposed individual and inadvertent intruder after the accumulation of twenty years of periodic semiannual 1-5 6677R Richard E mch -.bvy89 59.tif Page' 41........... | : 2) was based on evaluating the exposure to a maximally exposed individual and inadvertent intruder after the accumulation of twenty years of periodic semiannual 1-5 6677R Richard E mch -.bvy89 59.tif Page' 41........... | ||
spreading of the septic waste on a single (2 acre) plot within one of the designated disposal areas. If the activity limit per disposal area is projected to be exceeded, the appropriate exposure pathways as described in Section 4.5 will be evaluated prior to each additional application, or a separate plot within the designated disposal area will be utilized.Annually, for years in which disposal occurs, the potential dose impact from disposal operations conducted during the year, including the impact from previous years, will be performed and results reported in the plant's Semiannual Radioactive Effluent Release Report which is filed after January 1. All exposures will be assessed utilizing the methodology described in Attachment 2.The established dose criteria requires that all applications of septage within the approved designated disposal areas shall be limited to ensure the dose to a maximally-exposed individual be maintained less than 1 mrem/year to the whole body and any organ, and the dose to the inadvertent intruder be maintained less than 5 mrem/year. | spreading of the septic waste on a single (2 acre) plot within one of the designated disposal areas. If the activity limit per disposal area is projected to be exceeded, the appropriate exposure pathways as described in Section 4.5 will be evaluated prior to each additional application, or a separate plot within the designated disposal area will be utilized.Annually, for years in which disposal occurs, the potential dose impact from disposal operations conducted during the year, including the impact from previous years, will be performed and results reported in the plant's Semiannual Radioactive Effluent Release Report which is filed after January 1. All exposures will be assessed utilizing the methodology described in Attachment 2.The established dose criteria requires that all applications of septage within the approved designated disposal areas shall be limited to ensure the dose to a maximally-exposed individual be maintained less than 1 mrem/year to the whole body and any organ, and the dose to the inadvertent intruder be maintained less than 5 mrem/year. | ||
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disposal operation. | disposal operation. | ||
This will vary with the chemical composition of the septage, the percent solids, and the radioactive concentrations. | This will vary with the chemical composition of the septage, the percent solids, and the radioactive concentrations. | ||
3.2 Administrative Procedures Complete records of each disposal will be maintained. | |||
Procedures Complete records of each disposal will be maintained. | |||
These records will include the concentration of radionuclides in the septage, the total volume of septic waste disposed, the total activity in each batch as well as total accumulated on the disposal plot at time of spreading, the plot on which the septage was applied, and the results of any dose calculations required.The annual disposal of septage on each of the approved plot areas will be limited to within the established dose, activity, and concentration criteria noted above, in addition to limitations dictated by chemical and biological conditions. | These records will include the concentration of radionuclides in the septage, the total volume of septic waste disposed, the total activity in each batch as well as total accumulated on the disposal plot at time of spreading, the plot on which the septage was applied, and the results of any dose calculations required.The annual disposal of septage on each of the approved plot areas will be limited to within the established dose, activity, and concentration criteria noted above, in addition to limitations dictated by chemical and biological conditions. | ||
Dose guidelines, and concentration and activity limits, will be maintained within the appropriate values as detailed in Attachment 2.Any farmer using land which has been used for the disposal of septic waste will be notified of any applicable restrictions placed on the site due to the land spreading or injection of waste.4.0 EVALUATION OF ENVIRONMENTAL IMPACT 4.1 Site Characte-ristics 4.1.1 5:ite Topography The proposed disposal sites consist of two fields located on the Vermont Yankee Nuclear Power Plant site, which is located on the west bank of the Connecticut River in southwestern Vermont at latitude 42 degrees, 47 minutes north and longitude 72 degrees 31 minutes west. Both fields are on plant property within the site boundary and surrounded by a chain link fence.i-8 6677R I Richard Emch -bvy 89 59.tif Pa'e 14 Site A contains an approximate eight-acre parcel of usable land centered approximately 2,200 feet northwest of the Reactor Building. | Dose guidelines, and concentration and activity limits, will be maintained within the appropriate values as detailed in Attachment 2.Any farmer using land which has been used for the disposal of septic waste will be notified of any applicable restrictions placed on the site due to the land spreading or injection of waste.4.0 EVALUATION OF ENVIRONMENTAL IMPACT 4.1 Site Characte-ristics 4.1.1 5:ite Topography The proposed disposal sites consist of two fields located on the Vermont Yankee Nuclear Power Plant site, which is located on the west bank of the Connecticut River in southwestern Vermont at latitude 42 degrees, 47 minutes north and longitude 72 degrees 31 minutes west. Both fields are on plant property within the site boundary and surrounded by a chain link fence.i-8 6677R I Richard Emch -bvy 89 59.tif Pa'e 14 Site A contains an approximate eight-acre parcel of usable land centered approximately 2,200 feet northwest of the Reactor Building. | ||
Site B contains about two acres and is centered approximately 1,700 feet south of the Reactor Building. | Site B contains about two acres and is centered approximately 1,700 feet south of the Reactor Building. | ||
The usable acreage of both the north and south disposal fields is restricted to those areas which have no slopes greater than five percent to limit surface runoff. A radiological assessment based on the 1988 measured radioactivity concentrations in sludge has determined that a single two-acre plot would be sufficient for the routine disposal of septage for twenty years without exceeding the dose criteria to maximum exposed individual or inadvertent intruder. | The usable acreage of both the north and south disposal fields is restricted to those areas which have no slopes greater than five percent to limit surface runoff. A radiological assessment based on the 1988 measured radioactivity concentrations in sludge has determined that a single two-acre plot would be sufficient for the routine disposal of septage for twenty years without exceeding the dose criteria to maximum exposed individual or inadvertent intruder. | ||
As a result, the eight-acre field to the northwest could be divided into four disposal plots, with the two-acre site at the south end of the plant site, providing a fifth plot. A portion of the United States Geological Survey topographic map (Brattleboro quadrangle), showing the plant site, is presented in the Final Safety Analysis Report (FSAR) as Figure 2.5-1. A plan map showing the plant site and the disposal sites is given on Figure 4.The sites are located along a glacial terrace on the west side of the Connecticut River. This terrace extends about 3,000 feet west rising gently and then more abruptly to a higher terrace and then to dissected uplands.Distance to the east from the disposal sites to the river is at least 100 feet if septage is disposed of by surface spreading within the designated areas, or 50 feet if septage is injected directly into the soil.Relief of the proposed disposal sites is low, with elevation ranging between 250 feet and 265 feet (msl). Mean water surface elevation of the adjacent river is about 220 feet.The topographic character of the site and surrounding area is compatible with this use. The spreading of septage at these locations will have no effect on the topography of the area.1-9 6677R Richar Emch -bvy 89 59.tifPae1 4.1.2 Site Geology Profiles of site exploratory borings are shown in the FSAR in Figures 2.5-8 through 2.5-11. Current site characteristics as determined from a recent detailed site investigation can be found in Reference 5.Composition of surfacial materials is compatible with the proposed use of the site for septic waste disposal.4.2 A haracteristics | As a result, the eight-acre field to the northwest could be divided into four disposal plots, with the two-acre site at the south end of the plant site, providing a fifth plot. A portion of the United States Geological Survey topographic map (Brattleboro quadrangle), showing the plant site, is presented in the Final Safety Analysis Report (FSAR) as Figure 2.5-1. A plan map showing the plant site and the disposal sites is given on Figure 4.The sites are located along a glacial terrace on the west side of the Connecticut River. This terrace extends about 3,000 feet west rising gently and then more abruptly to a higher terrace and then to dissected uplands.Distance to the east from the disposal sites to the river is at least 100 feet if septage is disposed of by surface spreading within the designated areas, or 50 feet if septage is injected directly into the soil.Relief of the proposed disposal sites is low, with elevation ranging between 250 feet and 265 feet (msl). Mean water surface elevation of the adjacent river is about 220 feet.The topographic character of the site and surrounding area is compatible with this use. The spreading of septage at these locations will have no effect on the topography of the area.1-9 6677R Richar Emch -bvy 89 59.tifPae1 4.1.2 Site Geology Profiles of site exploratory borings are shown in the FSAR in Figures 2.5-8 through 2.5-11. Current site characteristics as determined from a recent detailed site investigation can be found in Reference 5.Composition of surfacial materials is compatible with the proposed use of the site for septic waste disposal.4.2 A haracteristics 4.2.1 Meteorologv The site area experiences a continental-type climate with some modification due to the marine climate which prevails at the Atlantic seacoast to the east. Annual precipitation averages 43 inches and is fairly evenly distributed in each month of the year.Potential impacts on septic waste disposal include occasional harsh weather: ice storms, severe thunderstorms, heavy rains due to hurricanes, the possibility of a tornado, and annual snowfall of from 30 to 118 inches per year. In addition, frozen ground can occur for up to 4 months of the year.Septage spreading will be managed by written procedure such that material which is spread or a mix of that material with precipitation will not overflow the perimeter of the disposal site.Additional information on meteorology of the site can be found in Section 2.3 of the Final Safety Analysis Report.4.2.2 ydrolgy Hydrology of the site and local area is tied closely to flow in the adjacent Connecticut River. River flow is controlled by a series of hydroelectric and flood-control dams including the Vernon Dam which is about 3,500 feet downstream of the site.1-10 6677R | ||
The site area experiences a continental-type climate with some modification due to the marine climate which prevails at the Atlantic seacoast to the east. Annual precipitation averages 43 inches and is fairly evenly distributed in each month of the year.Potential impacts on septic waste disposal include occasional harsh weather: ice storms, severe thunderstorms, heavy rains due to hurricanes, the possibility of a tornado, and annual snowfall of from 30 to 118 inches per year. In addition, frozen ground can occur for up to 4 months of the year.Septage spreading will be managed by written procedure such that material which is spread or a mix of that material with precipitation will not overflow the perimeter of the disposal site.Additional information on meteorology of the site can be found in Section 2.3 of the Final Safety Analysis Report.4.2.2 ydrolgy Hydrology of the site and local area is tied closely to flow in the adjacent Connecticut River. River flow is controlled by a series of hydroelectric and flood-control dams including the Vernon Dam which is about 3,500 feet downstream of the site.1-10 6677R | |||
ý rich -byY89 c ,ii ii g tif Page 1 All local streams drain to the Connecticut River and the site is in the direct path of natural groundwater flow from the local watershed easterly toward the river. Site groundwater level is influenced by both precipitation and changes in the level of ponding of the Connecticut River behind the Vernon Dam due to natural flow or dam operation. | ý rich -byY89 c ,ii ii g tif Page 1 All local streams drain to the Connecticut River and the site is in the direct path of natural groundwater flow from the local watershed easterly toward the river. Site groundwater level is influenced by both precipitation and changes in the level of ponding of the Connecticut River behind the Vernon Dam due to natural flow or dam operation. | ||
Flood flows on the Connecticut are controlled by numerous dams including five upstream of the site. Elevation of the 100-year flood is about 228 ft (mel); and, thus, well below the elevation of the proposed site which ranges from about 250 to 265 feet (mal). The 100-year flood level is based on information presented in References (1) and (2).Septage disposal by means of land spreading on the proposed site will have no adverse impact on area hydrology. | Flood flows on the Connecticut are controlled by numerous dams including five upstream of the site. Elevation of the 100-year flood is about 228 ft (mel); and, thus, well below the elevation of the proposed site which ranges from about 250 to 265 feet (mal). The 100-year flood level is based on information presented in References (1) and (2).Septage disposal by means of land spreading on the proposed site will have no adverse impact on area hydrology. | ||
Further information about site hydrology is in Section 2.4 of the FSAR.4.3 Water Usage 4.3. 1 urfaeWteM r The adjacent Connecticut River is used for hydroelectric power, for cooling water for the Vermont Yankee plant, as well as for a variety of recreational purposes such as fishing and boating. The Connecticut River is not used as a potable water supply within 50 miles downstream of the plant.Locally, water from natural springs are used for domestic and farm purposes. | Further information about site hydrology is in Section 2.4 of the FSAR.4.3 Water Usage 4.3. 1 urfaeWteM r The adjacent Connecticut River is used for hydroelectric power, for cooling water for the Vermont Yankee plant, as well as for a variety of recreational purposes such as fishing and boating. The Connecticut River is not used as a potable water supply within 50 miles downstream of the plant.Locally, water from natural springs are used for domestic and farm purposes. | ||
FSAR Table 2.4.5 and Figure 2.4-2 show springs used within a 1-mile radius of the site. FSAR Table 2.4.4 and Figure 2.4-1 show water supplies with surface water sources which are within a ten-mile radius of the site.There will be no impact on surface water usage or quality as a result of septage disposal due to the required separation distances between surface waters and the disposal plots.6677R | FSAR Table 2.4.5 and Figure 2.4-2 show springs used within a 1-mile radius of the site. FSAR Table 2.4.4 and Figure 2.4-1 show water supplies with surface water sources which are within a ten-mile radius of the site.There will be no impact on surface water usage or quality as a result of septage disposal due to the required separation distances between surface waters and the disposal plots.6677R 4.3.2 Groundwater Based on a review of groundwater measurements in various site borings presented in the FSAR and References 3 and 5, an upper estimate of groundwater levels at the plant is about 240 feet. Considering the proximity of the Connecticut River and Vernon Pond, with a mean water surface elevation of 220 feet, this estimate for the groundwater level appears to be reasonable. | ||
Based on a review of groundwater measurements in various site borings presented in the FSAR and References 3 and 5, an upper estimate of groundwater levels at the plant is about 240 feet. Considering the proximity of the Connecticut River and Vernon Pond, with a mean water surface elevation of 220 feet, this estimate for the groundwater level appears to be reasonable. | |||
Given the topography of the proposed disposal sites, it is highly unlikely that the groundwater level will be within 3 feet of the disposal area surface elevation. | Given the topography of the proposed disposal sites, it is highly unlikely that the groundwater level will be within 3 feet of the disposal area surface elevation. | ||
Prior to each application of septic waste to a disposal plot, the groundwater level in nearby test wells will be determined and no application will be allowed if the groundwater level in the vicinity of the disposal plot is found to be less than 3 feet.Groundwater provides potable water for public wells as shown in FSAR Table 2.4.5 and Figure 2.4-1. Groundwater flow in the vicinity of the proposed disposal sites is towards the Connecticut River. There are no drinking-water wells located between the site and the river. Therefore, it is highly unlikely that any drinking water wells could be affected by septage disposal. | Prior to each application of septic waste to a disposal plot, the groundwater level in nearby test wells will be determined and no application will be allowed if the groundwater level in the vicinity of the disposal plot is found to be less than 3 feet.Groundwater provides potable water for public wells as shown in FSAR Table 2.4.5 and Figure 2.4-1. Groundwater flow in the vicinity of the proposed disposal sites is towards the Connecticut River. There are no drinking-water wells located between the site and the river. Therefore, it is highly unlikely that any drinking water wells could be affected by septage disposal. | ||
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In practice, a minimum of 3 feet separation between groundwater and the surface will be required at time of application of the septic waste.1-12 6677R I Richard Emch -bvy'89 59.tif'Pag 66118 1 Due to ionic adsorption of the radionuclides on solid particles in the groundwater flow regime, most radionuclides travel at only a small fraction of the groundwater velocity. | In practice, a minimum of 3 feet separation between groundwater and the surface will be required at time of application of the septic waste.1-12 6677R I Richard Emch -bvy'89 59.tif'Pag 66118 1 Due to ionic adsorption of the radionuclides on solid particles in the groundwater flow regime, most radionuclides travel at only a small fraction of the groundwater velocity. | ||
For the radionuclides present in the sludge, retardation coefficients were developed from NUREG/CR-3130 (Reference 4).Retardation coefficients for Co-60, Cs-137, and Cs-134 were directly obtained from NUREG/CR-3130. | For the radionuclides present in the sludge, retardation coefficients were developed from NUREG/CR-3130 (Reference 4).Retardation coefficients for Co-60, Cs-137, and Cs-134 were directly obtained from NUREG/CR-3130. | ||
The coefficients for Zn-65 and Mn-54 were conservatively estimated using NUREG/CR-3130 as a guide. The radionuclides, their half-lives, retardation coefficients, and their travel time to the river are summarized in Table I.TABLE I Radionuclide Travel Times Retardation Travel Time Radionuclide HafLf Coefficient to River Co-60 5.3 years 860 961 years Cs-137 30.2 years 173 193 years.Cs-134 2.1 years 173 193 years Zn-65 244 days 3 1,224 days Mn-54 312 days 3 1,224 days The radiological impact on the river for the radionuclides reaching the river under this conservative analysis is discussed in Attachment | The coefficients for Zn-65 and Mn-54 were conservatively estimated using NUREG/CR-3130 as a guide. The radionuclides, their half-lives, retardation coefficients, and their travel time to the river are summarized in Table I.TABLE I Radionuclide Travel Times Retardation Travel Time Radionuclide HafLf Coefficient to River Co-60 5.3 years 860 961 years Cs-137 30.2 years 173 193 years.Cs-134 2.1 years 173 193 years Zn-65 244 days 3 1,224 days Mn-54 312 days 3 1,224 days The radiological impact on the river for the radionuclides reaching the river under this conservative analysis is discussed in Attachment | ||
: 2. Water usage of the Connecticut River downstream from the disposal area is limited to drinking water for dairy cows, irrigation of vegetable crops, and irrigation of cow and cattle fodder.Based on the assessments noted above, it is concluded that groundwater sources will not be adversely impacted as a result of septage disposal on the proposed site.4.4 Lad s Both the eight-acre and two-acre sites proposed for the disposal areas are currently part of the Vermont Yankee Nuclear Power Plant Site inside the plant's site boundary which is enclosed by a chain link fence. It is 1-13 6677R I Richard Emch -bvy 89 59.tif Page 19[I undeveloped except for transmission line structures which traverse a portion of the northern disposal area. Development potential is under the control of Vermont Yankee. At present, the eight-acre site on the north end of the plant property is used by a local farmer for the growing of feed hay for use with his dairy herd. No curtailment of this activity as a result of the low levels of radioactivity in septage will be necessary. | : 2. Water usage of the Connecticut River downstream from the disposal area is limited to drinking water for dairy cows, irrigation of vegetable crops, and irrigation of cow and cattle fodder.Based on the assessments noted above, it is concluded that groundwater sources will not be adversely impacted as a result of septage disposal on the proposed site.4.4 Lad s Both the eight-acre and two-acre sites proposed for the disposal areas are currently part of the Vermont Yankee Nuclear Power Plant Site inside the plant's site boundary which is enclosed by a chain link fence. It is 1-13 6677R I Richard Emch -bvy 89 59.tif Page 19[I undeveloped except for transmission line structures which traverse a portion of the northern disposal area. Development potential is under the control of Vermont Yankee. At present, the eight-acre site on the north end of the plant property is used by a local farmer for the growing of feed hay for use with his dairy herd. No curtailment of this activity as a result of the low levels of radioactivity in septage will be necessary. | ||
Utilization of the proposed sites for septic waste disposal will result in no impact on adjacent land or properties because of the separation of the disposal plots from off-site properties, the general movement of groundwater toward the river and away from adjacent land areas, and the very low levels of radioactive materials contained in the waste. Administrative controls on spreading and the monitoring of disposal area conditions will provide added assurance that this proposed practice will not impact adjacent properties. | Utilization of the proposed sites for septic waste disposal will result in no impact on adjacent land or properties because of the separation of the disposal plots from off-site properties, the general movement of groundwater toward the river and away from adjacent land areas, and the very low levels of radioactive materials contained in the waste. Administrative controls on spreading and the monitoring of disposal area conditions will provide added assurance that this proposed practice will not impact adjacent properties. | ||
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These include: (a) Standing on contaminated ground, (b) Inhalation of resuspended radioactivity, 1-14 6677R I-~ichard Ernch -bvy 89 59.tit PaQe2O Richard Emch -,bvy 89 59.tif Paqe20 I Page -201 (c) Ingestion of leafy vegetables, (d) Ingestion of stored vegetables, (f) Ingestion of meat, and (g) Ingestion of milk.The liquid pathway was also evaluated and determined to be insignificant. | These include: (a) Standing on contaminated ground, (b) Inhalation of resuspended radioactivity, 1-14 6677R I-~ichard Ernch -bvy 89 59.tit PaQe2O Richard Emch -,bvy 89 59.tif Paqe20 I Page -201 (c) Ingestion of leafy vegetables, (d) Ingestion of stored vegetables, (f) Ingestion of meat, and (g) Ingestion of milk.The liquid pathway was also evaluated and determined to be insignificant. | ||
Both the maximum individual and inadvertent intruder are assumed to be exposed to these pathways with difference between the two related to the occupancy time. The basic assumptions used in the radiological analyses include: (a) Exposure to the ground contamination and to resuspended radioactivity is for a period of 104 hours per year during Vermont Yankee active control of the disposal sites, and continuous thereafter. | Both the maximum individual and inadvertent intruder are assumed to be exposed to these pathways with difference between the two related to the occupancy time. The basic assumptions used in the radiological analyses include: (a) Exposure to the ground contamination and to resuspended radioactivity is for a period of 104 hours per year during Vermont Yankee active control of the disposal sites, and continuous thereafter. | ||
The 104-hour interval being representative of a farmer's time on a plot of land (4 hours per week for 6 months).(b) The septic tanks are emptied every 6 months. (Expected practice is to pump septic tanks once per year.)(c) The tank radioactivity remains constant at the currently determined level. To account for the uncertainty associated with the counting statistics, the measured activity concentrations listed in Section 2 were increased by 3 sigmas. That is, the activity concentrations employed in dose assessment and the total radioactivity content per pump-out (at 700 kg of solids per batch)are as follows: 1-15 6677R Richard _Emch -bv'y 89 59 tifPge2 Upper-Bound Activity Upper-Bound Activity Concentration | The 104-hour interval being representative of a farmer's time on a plot of land (4 hours per week for 6 months).(b) The septic tanks are emptied every 6 months. (Expected practice is to pump septic tanks once per year.)(c) The tank radioactivity remains constant at the currently determined level. To account for the uncertainty associated with the counting statistics, the measured activity concentrations listed in Section 2 were increased by 3 sigmas. That is, the activity concentrations employed in dose assessment and the total radioactivity content per pump-out (at 700 kg of solids per batch)are as follows: 1-15 6677R Richard _Emch -bv'y 89 59 tifPge2 Upper-Bound Activity Upper-Bound Activity Concentration | ||
[pCilk2 dryl Content [Ci/tankful) | [pCilk2 dryl Content [Ci/tankful) | ||
Mn-54 1,348 9.436E-07 Co-60 23,060 1.614E-05 Zn-65 1,620 1.134E-06 Cs-134 322 2.254E-07 Cs-137 4,100 2.870E-06 (d) The radiation source corresponds to the accumulation of radioactive material on a single plot (two-acre) within the proposed disposal sites over a period of 20 years (40 applications at 6-month intervals). (In actuality, the proposed sites will accommodate more than one disposal plot, and, in practice, more than one plot will most probably be used with an application frequency of once per year.)(e) For the analysis of the radiological impact during Vermont Yankee active control of the disposal sites, all dispersed radioactive material remains on the surface and forms a source of unshielded radiation. (In practice, the septic waste will be either surface spread or directly injected within the top 6 inches of the disposal plot, in which case, the radioactive material will be mixed with the soil. This, in effect, would reduce the ground plane source of exposure by a factor of about four due to self-shielding.)(f) No radioactive material is dispersed directly on crops for human or animal consumption, crop contamination being only through root uptake.(g) The deposition on crops of resuspended radioactivity is insignificantly small.1-16 6677R | Mn-54 1,348 9.436E-07 Co-60 23,060 1.614E-05 Zn-65 1,620 1.134E-06 Cs-134 322 2.254E-07 Cs-137 4,100 2.870E-06 (d) The radiation source corresponds to the accumulation of radioactive material on a single plot (two-acre) within the proposed disposal sites over a period of 20 years (40 applications at 6-month intervals). (In actuality, the proposed sites will accommodate more than one disposal plot, and, in practice, more than one plot will most probably be used with an application frequency of once per year.)(e) For the analysis of the radiological impact during Vermont Yankee active control of the disposal sites, all dispersed radioactive material remains on the surface and forms a source of unshielded radiation. (In practice, the septic waste will be either surface spread or directly injected within the top 6 inches of the disposal plot, in which case, the radioactive material will be mixed with the soil. This, in effect, would reduce the ground plane source of exposure by a factor of about four due to self-shielding.)(f) No radioactive material is dispersed directly on crops for human or animal consumption, crop contamination being only through root uptake.(g) The deposition on crops of resuspended radioactivity is insignificantly small.1-16 6677R | ||
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-bvy 89o9.i Pag 22-(h) Pathway data and usage factors-used in the analysis are the same as those used in the plant's ODCM assessment of the off-site radiological impact from routine releases,with the exception that the fraction of stored vegetables grown on the disposal plots was conservatively increased from 0.76 to 1.0 (at present no vegetable crops for direct human consumption are grown on any of the proposed disposal plots).(1) It is conservatively assumed that Vermont Yankee relinquishes control of the disposal sites after the fortieth pump-out (i.e., the above source term applies also for the inadvertent intruder).(j) For the analysis of the impact after Vermont Yankee control of the sites is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inches of soil; but, nonetheless, undergoes resuspension at the same rate as surface contamination. | -bvy 89o9.i Pag 22-(h) Pathway data and usage factors-used in the analysis are the same as those used in the plant's ODCM assessment of the off-site radiological impact from routine releases,with the exception that the fraction of stored vegetables grown on the disposal plots was conservatively increased from 0.76 to 1.0 (at present no vegetable crops for direct human consumption are grown on any of the proposed disposal plots).(1) It is conservatively assumed that Vermont Yankee relinquishes control of the disposal sites after the fortieth pump-out (i.e., the above source term applies also for the inadvertent intruder).(j) For the analysis of the impact after Vermont Yankee control of the sites is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inches of soil; but, nonetheless, undergoes resuspension at the same rate as surface contamination. | ||
From radiological impact assessments associated with the disposal of septage on different plot sizes (Attachment 2), it was determined that a single two-acre plot within the disposal sites would accommodate the 1 mrem/year prescribed dose to the critical organ of the maximally exposed individual for a period of up to 20 years, as well as the 5 mrem/year prescribed dose to the inadvertent intruder after control is assumed to be relinquished. | From radiological impact assessments associated with the disposal of septage on different plot sizes (Attachment 2), it was determined that a single two-acre plot within the disposal sites would accommodate the 1 mrem/year prescribed dose to the critical organ of the maximally exposed individual for a period of up to 20 years, as well as the 5 mrem/year prescribed dose to the inadvertent intruder after control is assumed to be relinquished. | ||
The calculated potential radiation exposures following the spreading of 40 combined (main septic system and south disposal system)tankfuls (at six-month intervals) on a single two-acre plot are as follows:_Qolnltrl of Disposal Sites Radiation Exposure Individual/Organ Controlled by VYNPS 0.1 mrem/yr Child/Whole Body (Maximum Exposed Individual) 0.2 mrem/yr Maximum Child/Liver Uncontrolled 1.3 mrem/yr Adult/Whole Body (Inadvertent Intruder) 3.9 mrem/yr Maximum Teenager/Lung 1-17 6677R | The calculated potential radiation exposures following the spreading of 40 combined (main septic system and south disposal system)tankfuls (at six-month intervals) on a single two-acre plot are as follows:_Qolnltrl of Disposal Sites Radiation Exposure Individual/Organ Controlled by VYNPS 0.1 mrem/yr Child/Whole Body (Maximum Exposed Individual) 0.2 mrem/yr Maximum Child/Liver Uncontrolled 1.3 mrem/yr Adult/Whole Body (Inadvertent Intruder) 3.9 mrem/yr Maximum Teenager/Lung 1-17 6677R | ||
[Richard Emch " bvY 89_59.tif 23 The individual pathway contributions to the total dose at the end of the 20-year accumulation of waste deposited on a single two-acre plot are as listed below: l'athway-Dependent Critical Organn.Doje. | [Richard Emch " bvY 89_59.tif 23 The individual pathway contributions to the total dose at the end of the 20-year accumulation of waste deposited on a single two-acre plot are as listed below: l'athway-Dependent Critical Organn.Doje. | ||
Ground Irradiation Inhalation Stored Vegetables Leafy Vegetable Milk Ingestion Meat Ingestion TOTAL Maximally Exposed Individual/Organ (Child/Liver)(mremlyear) 0.0576 0.00122 0.0913 0.00467 0.0421 0.90049 0.1994 Inadvertent Intruder Critical Individual/Organ (Teenager/Lung)(mrem/year) 1.16 2.74 0.00601 0.00040 0.00229.090001 3.909 In addition, an isotopic breakdown of the critical organ dose results listed above is shown in the following table: Isotopic Breakdown of MaximuwvRa | Ground Irradiation Inhalation Stored Vegetables Leafy Vegetable Milk Ingestion Meat Ingestion TOTAL Maximally Exposed Individual/Organ (Child/Liver)(mremlyear) 0.0576 0.00122 0.0913 0.00467 0.0421 0.90049 0.1994 Inadvertent Intruder Critical Individual/Organ (Teenager/Lung)(mrem/year) 1.16 2.74 0.00601 0.00040 0.00229.090001 3.909 In addition, an isotopic breakdown of the critical organ dose results listed above is shown in the following table: Isotopic Breakdown of MaximuwvRa | ||
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Inadvertent Intruder Critical Individual/ | Inadvertent Intruder Critical Individual/ | ||
Organ: Teenager/Lung Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL 2.831 235.3 2.801 1.457 92.59 2.831 235.3 2.801 1.457 92.59 Exposure fmrem/yr]0.000436 0.0559 0.0230 0.00231 0.118 0.199 0.0144 3.76 0.00983 0.000505 3.91 1-18 6677R Richard Emch -bvy 89 59.-tifPae2 Of interest are also derived dose conversion factors which provide a means of ensuring septage disposal operations within the prescribed radiological guidelines. | Organ: Teenager/Lung Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL 2.831 235.3 2.801 1.457 92.59 2.831 235.3 2.801 1.457 92.59 Exposure fmrem/yr]0.000436 0.0559 0.0230 0.00231 0.118 0.199 0.0144 3.76 0.00983 0.000505 3.91 1-18 6677R Richard Emch -bvy 89 59.-tifPae2 Of interest are also derived dose conversion factors which provide a means of ensuring septage disposal operations within the prescribed radiological guidelines. | ||
The critical-organ (worst-case) all-pathway values per acre are as follows: All-Pathway Critical-Orsan Dose Conversion Factors During Vermont Yankee Control of Disposal Sites Exposure j .Individual/Organ | The critical-organ (worst-case) all-pathway values per acre are as follows: All-Pathway Critical-Orsan Dose Conversion Factors During Vermont Yankee Control of Disposal Sites Exposure j .Individual/Organ | ||
[mrem/yr-MCi/acre] | [mrem/yr-MCi/acre] | ||
Mn-54 Adult/GE-LLI 3.74E-4 Co-60 Teenager/Lung 7.14E-4 Zn-65 Child/Liver 1.64E-2 Cs-134 Child/Liver 3.18E-3 Cs-137 Child/Bone 2.66E-3 The calculational methodology and details of the radiological assessment and proposed operational controls on total activity and concentration of waste to be disposed are presented in Attachment 2.5.0 &ADIATION PROTECTION The disposal operation will follow the applicable Vermont Yankee procedures to maintain doses as low as reasonably achievable and within the specified dose and release concentration criteria.1-19 6677R Richard Em~c'h -b'vy 89 59.tif-Pae2 I R ic ha rd E ~ c h ........59 .t........................ | Mn-54 Adult/GE-LLI 3.74E-4 Co-60 Teenager/Lung 7.14E-4 Zn-65 Child/Liver 1.64E-2 Cs-134 Child/Liver 3.18E-3 Cs-137 Child/Bone 2.66E-3 The calculational methodology and details of the radiological assessment and proposed operational controls on total activity and concentration of waste to be disposed are presented in Attachment 2.5.0 &ADIATION PROTECTION The disposal operation will follow the applicable Vermont Yankee procedures to maintain doses as low as reasonably achievable and within the specified dose and release concentration criteria.1-19 6677R Richard Em~c'h -b'vy 89 59.tif-Pae2 I R ic ha rd E ~ c h ........59 .t........................ | ||
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Thus, the sludge activity concentration can be at least 50 times higher without exceeding either limit. Obviously, if the MPC ratio of 1 or the 50 pCi/g guideline are not revised, the on-site disposal of septic waste will be regulated solely by the prescribed radiation exposure limits. For better control, therefore, it is hereby proposed that, in addition to the prescribed dose limits, a combined MPC ratio of less than or equal to 0.1 be also included in the procedures to regulate the disposal of septage. Refer to Section 4 for more details.2.4 Dispoa~l-Sit-e-There are two sites on Vermont Yankee site property which are currently designated for on-site septic waste disposal, as follows: (a) Site A, a 8-acre site approximately 2,200 feet northwest of the Reactor Building.(b) Site B, a 2-acre site approximately 1,700 feet south of the Reactor Building.Both sites are within the plant's site boundary and surrounded by a chain link fence, and under direct control of Vermont Yankee for all access.2.5 Radioactivity at Disposal Plot After 20 Years It is clear that, due to the longevity of the two primary isotopes identified in the sludge (Co-60 and Cs-137), the amount of radioactivity at the disposal plot will be increasing with each disposal application. | Thus, the sludge activity concentration can be at least 50 times higher without exceeding either limit. Obviously, if the MPC ratio of 1 or the 50 pCi/g guideline are not revised, the on-site disposal of septic waste will be regulated solely by the prescribed radiation exposure limits. For better control, therefore, it is hereby proposed that, in addition to the prescribed dose limits, a combined MPC ratio of less than or equal to 0.1 be also included in the procedures to regulate the disposal of septage. Refer to Section 4 for more details.2.4 Dispoa~l-Sit-e-There are two sites on Vermont Yankee site property which are currently designated for on-site septic waste disposal, as follows: (a) Site A, a 8-acre site approximately 2,200 feet northwest of the Reactor Building.(b) Site B, a 2-acre site approximately 1,700 feet south of the Reactor Building.Both sites are within the plant's site boundary and surrounded by a chain link fence, and under direct control of Vermont Yankee for all access.2.5 Radioactivity at Disposal Plot After 20 Years It is clear that, due to the longevity of the two primary isotopes identified in the sludge (Co-60 and Cs-137), the amount of radioactivity at the disposal plot will be increasing with each disposal application. | ||
However, since the content of radioactivity in septic waste is very low, and since it is neither practical nor necessary to carry out a new dose analysis prior to each disposal, the approach employed in this calculation was to assess the potential radiological impact at approximately the end of plant life. That is, the radiation source was assumed to correspond to the accumulation of 2-6 6680R I Richard Emch -bvy 89 59.tif Paae 38 I L radioactive material on a given plot within the proposed disposal sites over a period of 20 years (40 applications at an assumed 6-month interval). | However, since the content of radioactivity in septic waste is very low, and since it is neither practical nor necessary to carry out a new dose analysis prior to each disposal, the approach employed in this calculation was to assess the potential radiological impact at approximately the end of plant life. That is, the radiation source was assumed to correspond to the accumulation of 2-6 6680R I Richard Emch -bvy 89 59.tif Paae 38 I L radioactive material on a given plot within the proposed disposal sites over a period of 20 years (40 applications at an assumed 6-month interval). | ||
Analytically, if Q is the amount of radioactivity per batch for a given isotope, then the total accumulated radioactivity Qe at the disposal plot after 40 applications is given by: Qe = Qo (1 + E + E 2 + E 3 + E 4 + .... +E3) (2.1)= Qo (1 -E 3 9 )l -E) (2.2)where: E = exp(-Xtt) | Analytically, if Q is the amount of radioactivity per batch for a given isotope, then the total accumulated radioactivity Qe at the disposal plot after 40 applications is given by: Qe = Qo (1 + E + E 2 + E 3 + E 4 + .... +E3) (2.1)= Qo (1 -E 3 9 )l -E) (2.2)where: E = exp(-Xtt) | ||
(2.3)= is the decay constant for the selected isotope (1/year)and At = time interval between applications | (2.3)= is the decay constant for the selected isotope (1/year)and At = time interval between applications | ||
= 0.5 year For the isotopes of interest, the results are as follows: Qo Qe 1"t2_& Half Life lr (Cibatch) | = 0.5 year For the isotopes of interest, the results are as follows: Qo Qe 1"t2_& Half Life lr (Cibatch) | ||
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4 USAGE FACTORS Vegetables Leafy Veg. Milk Meat Inhalation n (kL/yr) (kg/r) (1/y) £kgLyr) (mJ/yJ )Adult 520 64 310 110 8,000 Teen 630 42 400 65 8,000 Child 520 26 330 41 3,700 Infant --- .. 330 --- 1,400 VEGETABLE PATHWAY Stored Veaetables Leafy Vegetables Agricultural productivity (kg/m 2) 2.0 2.00 Soil surface density (kg/m 2) 240.0 240.0 Transport time to user (hours), 0.0 0.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours) .0 .0 Holdup after harvest (hours) 1,440.0 24.0 Fraction of stored vegetables grown in garden 1.0 Fraction of leafy vegetables grown in garden 1.0 COW-MILK PAINA Pasture Feed Stored Feed Agricultural productivity (kg/m 2) .7 2.0 Soil surface density (kg/m 2) 240.0 240.0 Transport time to user (hours) 48.0 48.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours) .0 .0 Holdup after harvest (hours) .0 2,160.0 Animals daily feed (kg/day) 50.0 50.0 Fraction of year on pasture .5 Fraction pasture when on pasture 1.0 MEAT PATH"WAY Pasture Feed Stored Feed Agricultural productivity (kg/m 2) .7 2.0 Soil surface density (kg/m 2) 240.0 240.0 Transport time to user (hours) 480.0 480.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours) .0 .0 Holdup after harvest (hours) .0 2,160.0 Animals daily feed (kg/day) 50.0 50.0 Fraction of year on pasture .5 Fraction pasture when on pasture 1.0 2-11 6680R Richard Emch -bvy 89 59.tif ..Page_43 2.8 LjigiLad Pathways There are three potential routes through which septic waste radioactivity may enter into the liquid pathway, as follows: (a) Surface water runoff.(b) Ground water pathway.(c) Accidental releases into the Connecticut River.Since there are no potable water wells between the disposal site and the river, it is evident that the only way for septic waste radioactivity to enter the liquid pathway is via the Connecticut River.Even though surface water runoff may be a credible pathway into the river, the fraction of disposed radioactivity which may thus be transported to the river is very small for the following reasons: (1) The selected disposal sites are set back from the river.(2) Procedural controls will ensure that during surface spreading of all the septage and any precipitation falling onto or flowing onto the disposal plot will not overflow the perimeter of the disposal site.(3) The disposal plots have slopes of 5% or less in order to limit surface runoff.With respect to septage radionuclides reaching the Connecticut River via the ground-water pathway, the critical parameter is the total transport time from the field to the river. Should this transport time (which is element dependent) be large in comparison to the half-life of the radionuclide of interest, then decay in transit will remove the said radionuclide from the pathway. For the case on hand, the conservative travel times to go an average 200 feet to the river, and the fractions of land-spread radioactivity which are expected to reach the river are as follows: 2-12 6680R I Richard Emch -bvy 89 59.tif P66e"44']Decay Constant 1Isotop (1f ie /yr)Mn-54 Co-60 Zn-65 Cs-134 Cs-137 312.2 d 5.272 y 243.8 d 2.065 y 30.17 y 0.8109 0.1315 1.038 0.3357 0.02297 Travel Time to River (years)(Ground Water Path)3.35 961.3.35 193.193.Fraction of Initial Activity_EngxJAng iver 6.61E-02 0.0 3.09E-02 0.0 I. 19E-02 Thus, only small fractions of Mn-54, Zn-65, the river via the ground-water pathway; and, since these isotopes are relatively insignificant, it is pathway is not a credible one.and Cs-137 may make it to the initial activities of clear that the ground-water We proceed, then, with the analysis of an accidental release of the entire contents of a septic waste spreading truck directly into the Connecticut River. Following such an accident, the released radioactive material is expected to first mix with part of the water in Vernon Pond and to then gradually flow downstream of the Vernon Dam. The storage volume in Vernon Pond, excluding the volume below the crest, is approximately 6.OE+9 gallons (2.3E+13 cc). Since no use is made of the river between the plant and the Vernon dam, the only potential exposure pathway is downstream of the dam;and from Reference (2), the river flow through the dam is typically 10,000 cfs, and no less than 1,200 cfs during the dry season.As a conservative condition, assume that the septic waste mixes with just one thousandth of the Vernon pond storage volume, i.e., with 2.3E+10 cc.This amount of water will pass through the dam in about 11 minutes if the river flow is 1,200 cfs, and in about 1.3 minutes if the flow is 10,000 cfs.Using the upper-bound activities given in Section 2.3, the expected concentrations in the pond, and the corresponding MPCs are as follows: Upper-Bound Activity Content (Ci/BatchL Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL 9.44E-07 1. 61E-05 1. 13E-06 2. 25 E-0 7 2. 87 EQA 2.13E-05 Expected Concentration in Pond (uCilml)4.1OE-11 7.02E-10 4.93E-11 9.80E-12 9.27E-10 4. 1OE-0 7 2.34E-05 2.47E-07 2.45E-07 3. 1E-0 2.74E-05 2-13 6680R | 4 USAGE FACTORS Vegetables Leafy Veg. Milk Meat Inhalation n (kL/yr) (kg/r) (1/y) £kgLyr) (mJ/yJ )Adult 520 64 310 110 8,000 Teen 630 42 400 65 8,000 Child 520 26 330 41 3,700 Infant --- .. 330 --- 1,400 VEGETABLE PATHWAY Stored Veaetables Leafy Vegetables Agricultural productivity (kg/m 2) 2.0 2.00 Soil surface density (kg/m 2) 240.0 240.0 Transport time to user (hours), 0.0 0.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours) .0 .0 Holdup after harvest (hours) 1,440.0 24.0 Fraction of stored vegetables grown in garden 1.0 Fraction of leafy vegetables grown in garden 1.0 COW-MILK PAINA Pasture Feed Stored Feed Agricultural productivity (kg/m 2) .7 2.0 Soil surface density (kg/m 2) 240.0 240.0 Transport time to user (hours) 48.0 48.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours) .0 .0 Holdup after harvest (hours) .0 2,160.0 Animals daily feed (kg/day) 50.0 50.0 Fraction of year on pasture .5 Fraction pasture when on pasture 1.0 MEAT PATH"WAY Pasture Feed Stored Feed Agricultural productivity (kg/m 2) .7 2.0 Soil surface density (kg/m 2) 240.0 240.0 Transport time to user (hours) 480.0 480.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours) .0 .0 Holdup after harvest (hours) .0 2,160.0 Animals daily feed (kg/day) 50.0 50.0 Fraction of year on pasture .5 Fraction pasture when on pasture 1.0 2-11 6680R Richard Emch -bvy 89 59.tif ..Page_43 2.8 LjigiLad Pathways There are three potential routes through which septic waste radioactivity may enter into the liquid pathway, as follows: (a) Surface water runoff.(b) Ground water pathway.(c) Accidental releases into the Connecticut River.Since there are no potable water wells between the disposal site and the river, it is evident that the only way for septic waste radioactivity to enter the liquid pathway is via the Connecticut River.Even though surface water runoff may be a credible pathway into the river, the fraction of disposed radioactivity which may thus be transported to the river is very small for the following reasons: (1) The selected disposal sites are set back from the river.(2) Procedural controls will ensure that during surface spreading of all the septage and any precipitation falling onto or flowing onto the disposal plot will not overflow the perimeter of the disposal site.(3) The disposal plots have slopes of 5% or less in order to limit surface runoff.With respect to septage radionuclides reaching the Connecticut River via the ground-water pathway, the critical parameter is the total transport time from the field to the river. Should this transport time (which is element dependent) be large in comparison to the half-life of the radionuclide of interest, then decay in transit will remove the said radionuclide from the pathway. For the case on hand, the conservative travel times to go an average 200 feet to the river, and the fractions of land-spread radioactivity which are expected to reach the river are as follows: 2-12 6680R I Richard Emch -bvy 89 59.tif P66e"44']Decay Constant 1Isotop (1f ie /yr)Mn-54 Co-60 Zn-65 Cs-134 Cs-137 312.2 d 5.272 y 243.8 d 2.065 y 30.17 y 0.8109 0.1315 1.038 0.3357 0.02297 Travel Time to River (years)(Ground Water Path)3.35 961.3.35 193.193.Fraction of Initial Activity_EngxJAng iver 6.61E-02 0.0 3.09E-02 0.0 I. 19E-02 Thus, only small fractions of Mn-54, Zn-65, the river via the ground-water pathway; and, since these isotopes are relatively insignificant, it is pathway is not a credible one.and Cs-137 may make it to the initial activities of clear that the ground-water We proceed, then, with the analysis of an accidental release of the entire contents of a septic waste spreading truck directly into the Connecticut River. Following such an accident, the released radioactive material is expected to first mix with part of the water in Vernon Pond and to then gradually flow downstream of the Vernon Dam. The storage volume in Vernon Pond, excluding the volume below the crest, is approximately 6.OE+9 gallons (2.3E+13 cc). Since no use is made of the river between the plant and the Vernon dam, the only potential exposure pathway is downstream of the dam;and from Reference (2), the river flow through the dam is typically 10,000 cfs, and no less than 1,200 cfs during the dry season.As a conservative condition, assume that the septic waste mixes with just one thousandth of the Vernon pond storage volume, i.e., with 2.3E+10 cc.This amount of water will pass through the dam in about 11 minutes if the river flow is 1,200 cfs, and in about 1.3 minutes if the flow is 10,000 cfs.Using the upper-bound activities given in Section 2.3, the expected concentrations in the pond, and the corresponding MPCs are as follows: Upper-Bound Activity Content (Ci/BatchL Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL 9.44E-07 1. 61E-05 1. 13E-06 2. 25 E-0 7 2. 87 EQA 2.13E-05 Expected Concentration in Pond (uCilml)4.1OE-11 7.02E-10 4.93E-11 9.80E-12 9.27E-10 4. 1OE-0 7 2.34E-05 2.47E-07 2.45E-07 3. 1E-0 2.74E-05 2-13 6680R | ||
'Richard Emch -bv-y_89 59.tifPae4 Page I A R d---A It is seen that the concentrations are negligibly small to pose any radiological concern.In sunmmary, as demonstrated above, the liquid pathway is not credible.2-14 6680R Richard Emch -bvy 89 59.tiif Page 46 1.......... | 'Richard Emch -bv-y_89 59.tifPae4 Page I A R d---A It is seen that the concentrations are negligibly small to pose any radiological concern.In sunmmary, as demonstrated above, the liquid pathway is not credible.2-14 6680R Richard Emch -bvy 89 59.tiif Page 46 1.......... | ||
3.0 RADIOLOGICAL ASSESSMENT The radiological impact associated with the on-site disposal of radioactive septage at Vermont Yankee was carried out using the dose assessment models in Regulatory Guide 1.109, and is consistent with the methodology employed by the Vermont Yankee ODCM. However, since the computer code used (ATMODOS; Reference (3)) is primarily for use with atmospheric releases, it was necessary to manipulate the input to obtain the desired results for direct deposition of radioactivity on soil due to land spreading of septic waste. In particular, special consideration was given to the following: (a) The computation of an effective shielding factor to account for the effect provided by the soil after the waste is plowed under, or if it is directly injected into the top 6 inch surface layer.(b) The definition of an annual activity release rate, which following a year's time of continuous release, would yield the ground deposition expected to prevail after 40 combined tank pump-outs, as calculated in Section 2.5.(c) The definition of an effective atmospheric dispersion factor to represent the resuspended radioactivity.(d) The proper representation of partial occupancy factors.These are discussed in Sections 3.1 and 3.2 which follow.The results of the radiological impact assessment are presented in Sections 3.3 and 3.4.3.1 as a Result of Flowing the Radioactive Material into the As pointed out in Section 2.6 of this calculation, the impact analysis after control of the disposal sites is relinquished, was based on the 2-15 6680R I Richard Emch -bvy 89 59.tif Pa6g~e -47 1------------ | |||
ASSESSMENT The radiological impact associated with the on-site disposal of radioactive septage at Vermont Yankee was carried out using the dose assessment models in Regulatory Guide 1.109, and is consistent with the methodology employed by the Vermont Yankee ODCM. However, since the computer code used (ATMODOS; Reference (3)) is primarily for use with atmospheric releases, it was necessary to manipulate the input to obtain the desired results for direct deposition of radioactivity on soil due to land spreading of septic waste. In particular, special consideration was given to the following: (a) The computation of an effective shielding factor to account for the effect provided by the soil after the waste is plowed under, or if it is directly injected into the top 6 inch surface layer.(b) The definition of an annual activity release rate, which following a year's time of continuous release, would yield the ground deposition expected to prevail after 40 combined tank pump-outs, as calculated in Section 2.5.(c) The definition of an effective atmospheric dispersion factor to represent the resuspended radioactivity.(d) The proper representation of partial occupancy factors.These are discussed in Sections 3.1 and 3.2 which follow.The results of the radiological impact assessment are presented in Sections 3.3 and 3.4.3.1 as a Result of Flowing the Radioactive Material into the As pointed out in Section 2.6 of this calculation, the impact analysis after control of the disposal sites is relinquished, was based on the 2-15 6680R I Richard Emch -bvy 89 59.tif Pa6g~e -47 1------------ | |||
assumption that the radioactive material will be plowed to form a uniform mix with the top .6 inches of soil. To account for the gamma attenuation provided by the soil, it was necessary to carry out an appropriate shielding calculation. | assumption that the radioactive material will be plowed to form a uniform mix with the top .6 inches of soil. To account for the gamma attenuation provided by the soil, it was necessary to carry out an appropriate shielding calculation. | ||
This was accomplished through use of the ALLEGRA and DIDOS-V computer codes (References 4 and 5). The ALLEGRA code was used to define the gamma spectrum (in MeV/sec) associated with the selected radionuclide mix.This spectrum was then entered into DIDOS-V to compute the radiation levels from the two following source/receptor geometries: (a) A circular disk source with a radius of 150 m (represented by a cylindrical volume with a height equal to 0.001 m), the receptor location being along the disk axis, 1 m from the disk.(b) A cylindrical volume source with a radius of 150 m and a height of 0.15 m, with the receptor located along the axis, I m above the source.In the latter case, the source density was set equal to 1.6 g/cc; this is equivalent to the Reg. Guide 1.109 value of 240 kg/m2 for the effective surface density of soil within a 15 cm plow layer. The source radii were assumed to be large so as to approximate semi-infinite conditions, thus, permitting a direct comparison of the DIDOS-V and ATMODOS results for the 3 unplowed land. The source intensity (in MeV/sec-m , as required for input into DIDOS-V) was computed by distributing the radioactive material over a 2-acre surface, and within 0.001 m for the disk source and 0.15 m for the second case.Copies of the ALLEGRA and DIDOS-V outputs appear in Appendix B, which should be referred to for more details. The DIDOS-V results are as follows: Dose to air from the disk source = 1.085E-06 rad/hr Dose to air from cylinder source = 2.629E-07 rad/hr Overall soil shielding factor = 2.629E-07/l.085E-06 | This was accomplished through use of the ALLEGRA and DIDOS-V computer codes (References 4 and 5). The ALLEGRA code was used to define the gamma spectrum (in MeV/sec) associated with the selected radionuclide mix.This spectrum was then entered into DIDOS-V to compute the radiation levels from the two following source/receptor geometries: (a) A circular disk source with a radius of 150 m (represented by a cylindrical volume with a height equal to 0.001 m), the receptor location being along the disk axis, 1 m from the disk.(b) A cylindrical volume source with a radius of 150 m and a height of 0.15 m, with the receptor located along the axis, I m above the source.In the latter case, the source density was set equal to 1.6 g/cc; this is equivalent to the Reg. Guide 1.109 value of 240 kg/m2 for the effective surface density of soil within a 15 cm plow layer. The source radii were assumed to be large so as to approximate semi-infinite conditions, thus, permitting a direct comparison of the DIDOS-V and ATMODOS results for the 3 unplowed land. The source intensity (in MeV/sec-m , as required for input into DIDOS-V) was computed by distributing the radioactive material over a 2-acre surface, and within 0.001 m for the disk source and 0.15 m for the second case.Copies of the ALLEGRA and DIDOS-V outputs appear in Appendix B, which should be referred to for more details. The DIDOS-V results are as follows: Dose to air from the disk source = 1.085E-06 rad/hr Dose to air from cylinder source = 2.629E-07 rad/hr Overall soil shielding factor = 2.629E-07/l.085E-06 | ||
= 0.243 2-16 6680R ich~rdl Ench bvy 89 59.tif .Page 48 At this point, it is of interest to compare the DIDOS-V and ATMODOS exposure results from standing on contaminated ground. From the ATMODOS output in Appendix B (Section B.3.6), where the source term was the same as used in DIDOS-V, the skin dose due to exposure to contaminated ground for 104 hours is given as 6.78E-02 mrem. This is equivalent to a dose rate of 6.52E-4 mrem/hr, or (6.52E-4/1.11) | = 0.243 2-16 6680R ich~rdl Ench bvy 89 59.tif .Page 48 At this point, it is of interest to compare the DIDOS-V and ATMODOS exposure results from standing on contaminated ground. From the ATMODOS output in Appendix B (Section B.3.6), where the source term was the same as used in DIDOS-V, the skin dose due to exposure to contaminated ground for 104 hours is given as 6.78E-02 mrem. This is equivalent to a dose rate of 6.52E-4 mrem/hr, or (6.52E-4/1.11) | ||
= 5.87E-4 mrad/hr to air, 1.11 being the average ratio of tissue-to-air energy absorption coefficients (from Regulatory Guide 1.109). It is seen that ATMODOS underestimates the dose by a factor of 2, approximately; the reason for this is the slightly outdated set of dose conversion factors in the guide, as can be verified by inspecting the data in WASH-1400, for instance.3.2 Pata o tion for Use with ATMODOS 3.2.1 Radioactivity Release Rate There are two parameters in the input to ATMODOS which affect the buildup of radioactivity at an off-site location, namely, the activity release rate and the accumulation period. To simulate this process, and to also account for the effect of the 40 applications described earlier, the accumulation period was set equal to I year, and the release rate was selected to be such that, at the end of one year, the total accumulated radioactivity at the disposal plot would be equal to the Qe values given in Section 2.5.That is, if we define by Qr the activity release rate (Ci/yr) which is required as input to ATMODOS, then the relationship between this parameter and Qe is as follows: Qe = Qr (1 -E)/)' (3.1)E = exp(-XAt) | = 5.87E-4 mrad/hr to air, 1.11 being the average ratio of tissue-to-air energy absorption coefficients (from Regulatory Guide 1.109). It is seen that ATMODOS underestimates the dose by a factor of 2, approximately; the reason for this is the slightly outdated set of dose conversion factors in the guide, as can be verified by inspecting the data in WASH-1400, for instance.3.2 Pata o tion for Use with ATMODOS 3.2.1 Radioactivity Release Rate There are two parameters in the input to ATMODOS which affect the buildup of radioactivity at an off-site location, namely, the activity release rate and the accumulation period. To simulate this process, and to also account for the effect of the 40 applications described earlier, the accumulation period was set equal to I year, and the release rate was selected to be such that, at the end of one year, the total accumulated radioactivity at the disposal plot would be equal to the Qe values given in Section 2.5.That is, if we define by Qr the activity release rate (Ci/yr) which is required as input to ATMODOS, then the relationship between this parameter and Qe is as follows: Qe = Qr (1 -E)/)' (3.1)E = exp(-XAt) | ||
(3.2)= is the decay constant for the selected isotope (I/year) and At = time interval between applications | (3.2)= is the decay constant for the selected isotope (I/year) and At = time interval between applications | ||
= 1 yr.2-17 6680R | = 1 yr.2-17 6680R | ||
| Line 281: | Line 265: | ||
Tables showing the contributions by the various isotopes were not prepared as they were determined to be of little significance. | Tables showing the contributions by the various isotopes were not prepared as they were determined to be of little significance. | ||
Total Accumulated Radioactivity on 2-Acre Plot After 40 Disposal Applications IooeCuries 25 Mn-54 2.831E-06 27 Co-60 2.353E-04 30 Zn-65 2.801E-06 55 Cs-134 1.457E-06 55 Cs-137 9.259E-05 Qose Delivered to Each Organ From all Radionuclides in the Mix a d From all Pathways Combi (Adult. Teenager. | Total Accumulated Radioactivity on 2-Acre Plot After 40 Disposal Applications IooeCuries 25 Mn-54 2.831E-06 27 Co-60 2.353E-04 30 Zn-65 2.801E-06 55 Cs-134 1.457E-06 55 Cs-137 9.259E-05 Qose Delivered to Each Organ From all Radionuclides in the Mix a d From all Pathways Combi (Adult. Teenager. | ||
Child, and Infant)(mrem/yr)DQnc Liver Kidney Lung GI-LLI Thyroid Whole Body A 1.25E+00 1.29E+00 1.21E+00 3.04E+00 1.29E+00 1.16E+00 1.25E+00 1.37E+00 T 1.30E+00 1.35E+00 1.23E+00 3.91E+00 1.28E+00 1.16E+00 1.24E+00 1.37E+00 C 1.40E+00 1.41E+00 1.25E+00 3.39E+00 1.22E+00 1.16E+00 1.23E+00 1.37E+00 I 1.28E+00 1.32E+00 1.21E+00 2.58E+00 1.19E+00 1.16E+00 1.19E+00 1.37E+00*Each pathway includes continuous exposure to ground contamination (uniformly distributed within a 6-inch layer of soil)2-26 6680R | Child, and Infant)(mrem/yr)DQnc Liver Kidney Lung GI-LLI Thyroid Whole Body A 1.25E+00 1.29E+00 1.21E+00 3.04E+00 1.29E+00 1.16E+00 1.25E+00 1.37E+00 T 1.30E+00 1.35E+00 1.23E+00 3.91E+00 1.28E+00 1.16E+00 1.24E+00 1.37E+00 C 1.40E+00 1.41E+00 1.25E+00 3.39E+00 1.22E+00 1.16E+00 1.23E+00 1.37E+00 I 1.28E+00 1.32E+00 1.21E+00 2.58E+00 1.19E+00 1.16E+00 1.19E+00 1.37E+00*Each pathway includes continuous exposure to ground contamination (uniformly distributed within a 6-inch layer of soil)2-26 6680R 3.3.3 Isotopic Dose Conversion Factors The table which follows presents isotope-dependent dose conversion factors for the various age groups and organs. They were computed using the ATMODOS computer code along with all the assumptions employed in the assessment of the radiological impact during Vermont Yankee control of the disposal sites. The source terms were defined using the adjustment ratio (Qr x 1 yr)/Qe given in Section 3.2.1 to obtain an accumulated radioactivity of 1 uCi for each isotope of interest at the end of one year.These conversion factors form part of one of the procedural controls described in Section 4 for ensuring that the disposed contaminated septage does not lead to radiation exposures in excess of the specified limits.2-27 6680R Richard ..nCh .bvy 89 59 tif a....Dose Conversion Factors For Radioactive Material Spread over Two Acres For all Pathways Combined*(Adult, Teenager. | ||
Dose Conversion Factors The table which follows presents isotope-dependent dose conversion factors for the various age groups and organs. They were computed using the ATMODOS computer code along with all the assumptions employed in the assessment of the radiological impact during Vermont Yankee control of the disposal sites. The source terms were defined using the adjustment ratio (Qr x 1 yr)/Qe given in Section 3.2.1 to obtain an accumulated radioactivity of 1 uCi for each isotope of interest at the end of one year.These conversion factors form part of one of the procedural controls described in Section 4 for ensuring that the disposed contaminated septage does not lead to radiation exposures in excess of the specified limits.2-27 6680R Richard ..nCh .bvy 89 59 tif a....Dose Conversion Factors For Radioactive Material Spread over Two Acres For all Pathways Combined*(Adult, Teenager. | |||
Child, and Infant)(mrem/yr-uCi) | Child, and Infant)(mrem/yr-uCi) | ||
BMW Liver K L= GI-LLI Thyroid Whole Body Skin Source: Mn-54 A T C I 7.54E-05 7.54E-05 7.54E-05 7.54E-05 1 .1 2E-04 1. 29E-04 1.54E-04 7. 71E-05 8.63E-05 9.15E-05 9.74E-05 7.58E-05 1.05E-04 1. 18E-04 1 .09E-04 9.68E-05 1 .87E-04 1 .85E-04 1. 41E-04 7.60E-05 7.54E-05 7.54E-05 7.54E-05 7.54E-05 8. 24E-05 8.61E-05 9.6 3E-05 7.58E-05 8.84E-05 8.84E-05 8.84E-05 8.84E-05 Source: Co-60 A T C I 2.21E-04 2.21E-04 2. 2 1E-04 2. 21E-04 2.28E-04 2. 31 E-04 2.36E-04 2.22E-04 2.21E-04 2. 21E-04 2. 21E-04 2.2 1E-04 3.14E-04 3.57E-04 3. 32E-04 2.9 2E-04 3.54E-04 3.53E-04 3.04E-04 2.24E-04 2.21E-04 2.21E-04 2-21E-04 2.21E-04 2.36E-04 2.43E-04 2.65E-04 2.23E-04 2.60E-04 2.60E-04 2.60E-04 2.60E-04 Source: Zn-65 A T C I I , 22E-03 1 .65E-03 3. 11E-03 2. 21 E-0 3 3. 78E-03 5.5 9E-03 B. 21E-03 7.44E-03 2.55E-03 3.60E-03 5.19E-03 3.63E-03 7.24E-05 8. 12E-05 7.5 5E-05 6. 72E-05 2.40E-03 2.40E-03 1. 48E-03 6. 29E-03 5. 20E-05 5. 20 E-05 5.20E-05 5. 20E-05 1. 74E-03 2.64E-03 5.12E-03 3.46E-03 5.98E-05 5.98E-05 5.98E-05 5.98E-05 Source: Cs-134 A T C I 4.04E-04 5.44E-04 1 .03E-03 5.31E-04 7.46E-04 1 .07E-0 3 1.59E-03 8.55E-04 3.47E-04 4. 46 E-04 6. OOE-04 3.36E-04 2.19E-04 2.67E-04 3.15E-04 2.30E-04 1.66E-04 1.67E-04 1. 64E-04 1 .58E-04 1.56E-04 1.56E-04 1. 56E-04 1.56E-04 6.39E-04 5. 79E-04 4.58E-04 2.26E-04 1 .82E-04 1.8 2E-04 1.82E-04 1. 82E-04 Source: Cs-137 A T C I 3.86E-04 5. 97E-04 1. 33E-03 5.94E-04 5.07E-04 7.75E-04 1. 28E-03 6.86E-04 2. 0 9E-04 3.OOE-04 4.53E-04 2.24E-04 1. 06E-04 1. 50E-04 1. 98E-04 1. 23E-04 6.33E-05 6.48E-05 6.23E-05 5.66E-05 5.46E-05 5. 46E-05 5.46E-05 5.46E-05 3.5 2E-04 3.06E-04 2.35E-04 9.94E-05 6 -37E-05 6.37E-05 6.37E-05 6.37E-05*Each pathway includes unshielded exposure to ground contamination for 104 hours, with all radioactivity assumed to be on the surface of the ground; exposure to resuspended radioactivity is also for a period of 104 hours.2-28 6680R ihard Emch -bvy 89 59.tif. Page 60 4.0 RECOMrENDED PROCEDURAL CONTROLS TO ENSURE COMPLIANCE WITH RADIOLOGICAL Once an on-site septage disposal permit has been secured, implementation of the disposal program must be accompanied with procedural controls to ensure that the applicable radiological limits are not violated.This section presents a list of proposed controls to this effect.4.1 Total Rada~ t~vity Dispersed per Disposal Plot As pointed out in Section 2.5, since the content of radioactivity in septic waste is very low, and since it is neither practical nor necessary to carry out a new analysis prior to each disposal, assessment of the radiological impact was based on an assumed source corresponding to the expected accumulation of radioactive material on a given 2-acre disposal plot over a period of 20 years (40 applications at b-month intervals). | BMW Liver K L= GI-LLI Thyroid Whole Body Skin Source: Mn-54 A T C I 7.54E-05 7.54E-05 7.54E-05 7.54E-05 1 .1 2E-04 1. 29E-04 1.54E-04 7. 71E-05 8.63E-05 9.15E-05 9.74E-05 7.58E-05 1.05E-04 1. 18E-04 1 .09E-04 9.68E-05 1 .87E-04 1 .85E-04 1. 41E-04 7.60E-05 7.54E-05 7.54E-05 7.54E-05 7.54E-05 8. 24E-05 8.61E-05 9.6 3E-05 7.58E-05 8.84E-05 8.84E-05 8.84E-05 8.84E-05 Source: Co-60 A T C I 2.21E-04 2.21E-04 2. 2 1E-04 2. 21E-04 2.28E-04 2. 31 E-04 2.36E-04 2.22E-04 2.21E-04 2. 21E-04 2. 21E-04 2.2 1E-04 3.14E-04 3.57E-04 3. 32E-04 2.9 2E-04 3.54E-04 3.53E-04 3.04E-04 2.24E-04 2.21E-04 2.21E-04 2-21E-04 2.21E-04 2.36E-04 2.43E-04 2.65E-04 2.23E-04 2.60E-04 2.60E-04 2.60E-04 2.60E-04 Source: Zn-65 A T C I I , 22E-03 1 .65E-03 3. 11E-03 2. 21 E-0 3 3. 78E-03 5.5 9E-03 B. 21E-03 7.44E-03 2.55E-03 3.60E-03 5.19E-03 3.63E-03 7.24E-05 8. 12E-05 7.5 5E-05 6. 72E-05 2.40E-03 2.40E-03 1. 48E-03 6. 29E-03 5. 20E-05 5. 20 E-05 5.20E-05 5. 20E-05 1. 74E-03 2.64E-03 5.12E-03 3.46E-03 5.98E-05 5.98E-05 5.98E-05 5.98E-05 Source: Cs-134 A T C I 4.04E-04 5.44E-04 1 .03E-03 5.31E-04 7.46E-04 1 .07E-0 3 1.59E-03 8.55E-04 3.47E-04 4. 46 E-04 6. OOE-04 3.36E-04 2.19E-04 2.67E-04 3.15E-04 2.30E-04 1.66E-04 1.67E-04 1. 64E-04 1 .58E-04 1.56E-04 1.56E-04 1. 56E-04 1.56E-04 6.39E-04 5. 79E-04 4.58E-04 2.26E-04 1 .82E-04 1.8 2E-04 1.82E-04 1. 82E-04 Source: Cs-137 A T C I 3.86E-04 5. 97E-04 1. 33E-03 5.94E-04 5.07E-04 7.75E-04 1. 28E-03 6.86E-04 2. 0 9E-04 3.OOE-04 4.53E-04 2.24E-04 1. 06E-04 1. 50E-04 1. 98E-04 1. 23E-04 6.33E-05 6.48E-05 6.23E-05 5.66E-05 5.46E-05 5. 46E-05 5.46E-05 5.46E-05 3.5 2E-04 3.06E-04 2.35E-04 9.94E-05 6 -37E-05 6.37E-05 6.37E-05 6.37E-05*Each pathway includes unshielded exposure to ground contamination for 104 hours, with all radioactivity assumed to be on the surface of the ground; exposure to resuspended radioactivity is also for a period of 104 hours.2-28 6680R ihard Emch -bvy 89 59.tif. Page 60 4.0 RECOMrENDED PROCEDURAL CONTROLS TO ENSURE COMPLIANCE WITH RADIOLOGICAL Once an on-site septage disposal permit has been secured, implementation of the disposal program must be accompanied with procedural controls to ensure that the applicable radiological limits are not violated.This section presents a list of proposed controls to this effect.4.1 Total Rada~ t~vity Dispersed per Disposal Plot As pointed out in Section 2.5, since the content of radioactivity in septic waste is very low, and since it is neither practical nor necessary to carry out a new analysis prior to each disposal, assessment of the radiological impact was based on an assumed source corresponding to the expected accumulation of radioactive material on a given 2-acre disposal plot over a period of 20 years (40 applications at b-month intervals). | ||
| Line 291: | Line 272: | ||
14,950 gallons equals the volume of both the main septic tank and the south disposal system collection tank.4.2 OperationaL_1njgij The disposal operating procedures to be established should address both the activity concentration and the potential radiation exposure. | 14,950 gallons equals the volume of both the main septic tank and the south disposal system collection tank.4.2 OperationaL_1njgij The disposal operating procedures to be established should address both the activity concentration and the potential radiation exposure. | ||
Should the activity concentration be in excess of the specified limit, then the sewage mix would not be suitable for on-site disposal and would have to be processed accordingly; this situation, however, is not likely to occur. On the other hand, approaching the exposure guideline is a possibility; but this can be easily accommodated by switching to a different plot within the disposal sites. The subsections which follow present pertinent information recommended for inclusion in the operating procedures. | Should the activity concentration be in excess of the specified limit, then the sewage mix would not be suitable for on-site disposal and would have to be processed accordingly; this situation, however, is not likely to occur. On the other hand, approaching the exposure guideline is a possibility; but this can be easily accommodated by switching to a different plot within the disposal sites. The subsections which follow present pertinent information recommended for inclusion in the operating procedures. | ||
4.2.1 1aciu Activity Concentrations In line with the discussion presented in Section 2.3 of this calculation, the radionuclide concentrations in the septic waste must not exceed the following limits: (a) One tenth of the MPC values listed in 10 CFR 20, Appendix B, Table II, Column 2.2-30 6680R Richard Emch -bvy 89 59 tif ...Page_62 (b) An overall MPC ratio of less than or equal to 0.1.For the major radionuclides identified in the Vermont Yankee septic waste, the individual MPC limits are as follows: taxim .ermissible Concentrations in Water (lOCFR20, Appendix B, Table II)Mn 54 Co 60 Zn 65 Cs 134 Cs 137 Soluble I.OE-4 5.OE-5 1.OE-4 9.0E-6 2.OE-5 Insoluble£PiilmU)I .OE-4 3.OE:-5 2. OE-.4 4. OE-.5 4.OE-5 For a mix of radionuclides in the sewage mix, the condition to be met is: E (C /MPC.) 0.1 Where: Ci is the measured concentration for Isotope i, and the summation is over all radionuclides in the mix.From the 1988 spectroscopic analysis of septic waste samples, all radioactivity is expected to be in insoluble form, and no radioactivity is expected in the liquid above the sludge. Should the situation change, use should be made of both the soluble and insoluble MPCs listed above, as appropriate. | |||
4.2.2 Potential Radiation Exposures As described in Section 2.3 of this calculation, the NRR draft guidelines for radiation exposure from all probable pathways due to the disposal of low-level waste are 1 mrem/yr to the total body and any body organ of a maximally exposed individual, and 5 mrem/yr to an inadvertent intruder.The maximally exposed individual is identified as a member of the general public or a worker who is not classified as a radiation worker.2-31 6680R Richard Emch'-bvy 89 59.tif 1-1-lI Pag 6 3.I R cha d, m c vy 9 9:tf , ............ | |||
Activity Concentrations In line with the discussion presented in Section 2.3 of this calculation, the radionuclide concentrations in the septic waste must not exceed the following limits: (a) One tenth of the MPC values listed in 10 CFR 20, Appendix B, Table II, Column 2.2-30 6680R Richard Emch -bvy 89 59 tif ...Page_62 (b) An overall MPC ratio of less than or equal to 0.1.For the major radionuclides identified in the Vermont Yankee septic waste, the individual MPC limits are as follows: taxim .ermissible Concentrations in Water (lOCFR20, Appendix B, Table II)Mn 54 Co 60 Zn 65 Cs 134 Cs 137 Soluble I.OE-4 5.OE-5 1.OE-4 9.0E-6 2.OE-5 Insoluble£PiilmU)I .OE-4 3.OE:-5 2. OE-.4 4. OE-.5 4.OE-5 For a mix of radionuclides in the sewage mix, the condition to be met is: E (C /MPC.) 0.1 Where: Ci is the measured concentration for Isotope i, and the summation is over all radionuclides in the mix.From the 1988 spectroscopic analysis of septic waste samples, all radioactivity is expected to be in insoluble form, and no radioactivity is expected in the liquid above the sludge. Should the situation change, use should be made of both the soluble and insoluble MPCs listed above, as appropriate. | |||
Radiation Exposures As described in Section 2.3 of this calculation, the NRR draft guidelines for radiation exposure from all probable pathways due to the disposal of low-level waste are 1 mrem/yr to the total body and any body organ of a maximally exposed individual, and 5 mrem/yr to an inadvertent intruder.The maximally exposed individual is identified as a member of the general public or a worker who is not classified as a radiation worker.2-31 6680R Richard Emch'-bvy 89 59.tif 1-1-lI Pag 6 3.I R cha d, m c vy 9 9:tf , ............ | |||
.."..... i ..... ...... i. ....... ... .. ii i , ii ,, .- , iiP g 6 Since the proposed septage disposal sites are within VYNPS property and under VYNPS control, occupancy of the disposal sites by an inadvertent intruder is only possible after plant decommissioning. | .."..... i ..... ...... i. ....... ... .. ii i , ii ,, .- , iiP g 6 Since the proposed septage disposal sites are within VYNPS property and under VYNPS control, occupancy of the disposal sites by an inadvertent intruder is only possible after plant decommissioning. | ||
That is, during the on-site septic waste disposal program, only the specified exposure guideline for the maximally exposed individual would be in effect.To ensure proper operation of the on-site disposal program, a set of checkpoints was prepared as guidance. | That is, during the on-site septic waste disposal program, only the specified exposure guideline for the maximally exposed individual would be in effect.To ensure proper operation of the on-site disposal program, a set of checkpoints was prepared as guidance. | ||
| Line 322: | Line 298: | ||
: 6. Atomic Industrial Forum, National Environmental Studies Program, A Guide for Obtaining Regulatory Approval to Dispose of Very Low Level Wastes by Alternative Means, prepared by D. W. Chan, J. P. Davis & R. W. Wofford, General Physics Corporation, Columbia, Maryland, Technical Report No. AIF/NESP-037, August 1986.2-35 6680R | : 6. Atomic Industrial Forum, National Environmental Studies Program, A Guide for Obtaining Regulatory Approval to Dispose of Very Low Level Wastes by Alternative Means, prepared by D. W. Chan, J. P. Davis & R. W. Wofford, General Physics Corporation, Columbia, Maryland, Technical Report No. AIF/NESP-037, August 1986.2-35 6680R | ||
'Richard Emch -bvy 89 59 tif-Page 6.7,ýAPPENDIX A LABORATORY ANALYSES OF SEPTIC WASTE A. I I Richard Emch -bvy 89 59.tif Page 68 ]MAILEU JU:-, 0o ": YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY Initial Analysis Report Custoerg Yankee Nuclear Power Corp.Atzt.W6 b&yAJk~tI*4E KEEGAN4 MR. EDWARD CUMMING MR. STEPHEN SKIBNIOWSKY Report Date: Analysis Date: Date Received: Reference Date: 06/D9/88 6 /8 /88 6 /8 /88 6 /8 /a8 Sludge Sample Amount: 1.01 Kg. Lab Sample No.: G72970 Sample Submission Code: VSL 02 2388 Elapocd Time : 0.65 days Other Analysis Requested: | 'Richard Emch -bvy 89 59 tif-Page 6.7,ýAPPENDIX A LABORATORY ANALYSES OF SEPTIC WASTE A. I I Richard Emch -bvy 89 59.tif Page 68 ]MAILEU JU:-, 0o ": YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY Initial Analysis Report Custoerg Yankee Nuclear Power Corp.Atzt.W6 b&yAJk~tI*4E KEEGAN4 MR. EDWARD CUMMING MR. STEPHEN SKIBNIOWSKY Report Date: Analysis Date: Date Received: Reference Date: 06/D9/88 6 /8 /88 6 /8 /88 6 /8 /a8 Sludge Sample Amount: 1.01 Kg. Lab Sample No.: G72970 Sample Submission Code: VSL 02 2388 Elapocd Time : 0.65 days Other Analysis Requested: | ||
None Commenti COB TANK BOTTOM DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC CORRECTION | None Commenti COB TANK BOTTOM DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC CORRECTION | ||
[ Pico Curie / Kilogram -wFT Np-239 Co-57 Ce-144 Ce-141?o-99 Se-75 Cr-51 I -131 De-7 Ru-103 1 -133 Be-140 Cs-134 Ru-106*4 Ce-137 Ag-11M Zr-95 Co-58 Mn-54*+ AcTh228 TeI-132 Te-59 Zn-65*+ Co-60*+ K -40 Sb-124 8.24E-01 9.98E-01 9.98E-01 9.86t-01 8.49E-01 9.96E-01 9.84E-01 9.45E-01 9.92E-01 9.89E-01 5.95E-01 9.65E-01 9.99E-01 9.99E-01 I.OOE 00 9.98E-01 9.93E-01 9.94E-01 9.99E-01 1.00B 00 8.70E-01 9.90E-01 9.98E-01 1.00E 00 1.00R 00 9.92E-01 (-15 +- 11 ( 5 -94 (-9 4- 73 ( 26 4- 17 ( 11 4- 20 (-6 4- 15 ( 41 4- 93 (-15 4- 11 ( 102 4- 94 (-11 4- 12 ( 22 +- 17 (-175 4- 68 ( 16 4- 16 4 4-13 103 in- 1 (-2 4- 19 (-19 4- 24 ( 7 -13 (-7 4- 14 ( 287 4- 68 ( 117 4- 99 (-33 4- 27 ( 89 4- 36 ( 454 4- 31 07+- 23 (-31 4-31 E 0 E-2 E-1 E-1 E 0 E-1 E-1 E-I E-i E-i E-i E-I E-1 E Q E-i E-I E-i E-1 E-I E-I X-1 E-i E-1 Z-i E 0 E-i 35 310 240 55 65 49 310 37 310 38 58 230 53 43 54 64 79 42 50 230 330 91 120 82 75 100 E o E-2 E-i E-I E 0 E-i E-1 E-1 E-I E-I E-i E-i E-i E 0 E-i E-i E-i E-1 E-1 E-i E-i E-1 E-i E-I E 0 E-I Notes:* Activity greater than 3*standard deviation+ Peak is found....... | [ Pico Curie / Kilogram -wFT Np-239 Co-57 Ce-144 Ce-141?o-99 Se-75 Cr-51 I -131 De-7 Ru-103 1 -133 Be-140 Cs-134 Ru-106*4 Ce-137 Ag-11M Zr-95 Co-58 Mn-54*+ AcTh228 TeI-132 Te-59 Zn-65*+ Co-60*+ K -40 Sb-124 8.24E-01 9.98E-01 9.98E-01 9.86t-01 8.49E-01 9.96E-01 9.84E-01 9.45E-01 9.92E-01 9.89E-01 5.95E-01 9.65E-01 9.99E-01 9.99E-01 I.OOE 00 9.98E-01 9.93E-01 9.94E-01 9.99E-01 1.00B 00 8.70E-01 9.90E-01 9.98E-01 1.00E 00 1.00R 00 9.92E-01 (-15 +- 11 ( 5 -94 (-9 4- 73 ( 26 4- 17 ( 11 4- 20 (-6 4- 15 ( 41 4- 93 (-15 4- 11 ( 102 4- 94 (-11 4- 12 ( 22 +- 17 (-175 4- 68 ( 16 4- 16 4 4-13 103 in- 1 (-2 4- 19 (-19 4- 24 ( 7 -13 (-7 4- 14 ( 287 4- 68 ( 117 4- 99 (-33 4- 27 ( 89 4- 36 ( 454 4- 31 07+- 23 (-31 4-31 E 0 E-2 E-1 E-1 E 0 E-1 E-1 E-I E-i E-i E-i E-I E-1 E Q E-i E-I E-i E-1 E-I E-I X-1 E-i E-1 Z-i E 0 E-i 35 310 240 55 65 49 310 37 310 38 58 230 53 43 54 64 79 42 50 230 330 91 120 82 75 100 E o E-2 E-i E-I E 0 E-i E-1 E-1 E-I E-I E-i E-i E-i E 0 E-i E-i E-i E-1 E-1 E-i E-i E-1 E-i E-I E 0 E-I Notes:* Activity greater than 3*standard deviation+ Peak is found....... | ||
..@ -. rt ........... .ttI 2 2d ..... .............. | ..@ -. rt ........... .ttI 2 2d ..... .............. | ||
| Line 346: | Line 322: | ||
None Station No.: 04 Main Tank Bottom DECAY ACTIVITY NUCLIDE CONC. +- I SIGMA MDC CORRECTOION Pico Curie / Kilogram........................................................................... | None Station No.: 04 Main Tank Bottom DECAY ACTIVITY NUCLIDE CONC. +- I SIGMA MDC CORRECTOION Pico Curie / Kilogram........................................................................... | ||
Np-239 1.O7E-O0 Co-57 9.81F-01 Ce-144 9.82E-01 Ce-141 8.51E-01 11o-99 ilo5E-01 Se-75 9.57E-01 Cr-51 8.27E-01 I -131 5.21E-01 Be-7 9.06E-01 Ru-103 8.75E-01 XI -133 2.49E-03 Ba-140 6.64E-01*+ Cs-134 9.93E-01 Ru-106 9.86E-01*+ Cs-137 1.00B 00 Ag-ISOM 9.79E-03 Zr-95 9.22E-0,1 Co-58 9.29E-01*+ Mn-54 9.83E-01*+ ACTh228 1.00E 00 Tel-132 1.99E-01 Fe-59 8.90E-01*+ Zn-65 9.79E-01*+ Co-60 9.97E-01*+ K -40 1.00E 00 Sb-124 9.17E-01 Notes:* Activity greater than 3*standa:+ Peak is found x Decay correction less than .01 55 (-9 ( 3 ( 137 (-60 ( 85 ( 14 (-6 ( 12 (-2 (-86 ( 166 ( 12 3824 ( 76 (-2 ( 12 1126 ( 76 (-14 ( 7 ( 120 2240 ( 472 ( 69 4- 25 4- 30 4- 22 4- 60+- 29 4- 51+- 36 4- 74 4- 38 4-46 4- 40 4- 52 4- 49 4- 92+- 96+- 11+- 60 4- 74 4- 17 4- 22 4- 14 4- 14 4- 22 4- 53+- 61 E 2 E 0 E 1 E 0 E 2 E 0 E 1 E 0 E 1 E 0 E 0 E 0 E I E 0 E 0 E I E 0 E 0 E I E 2 E l El1 El1 El1 EQ0 85 E 2 99 E 0 74 E 1 190 E 0 97 E 2 170 E 0 120 E 1 250 E 0 130 E 1 150 E 0 130 E 0 150 E 0 160 E 1 200 E 0 320 E 0 36 E 1 200 E 0 200 E 0 49 E 1 75 E 2 48 E 1 40 E 1 23 E 1 160 E 1 200 E 0 rd deviation Approved by D.E.McCurdy. | Np-239 1.O7E-O0 Co-57 9.81F-01 Ce-144 9.82E-01 Ce-141 8.51E-01 11o-99 ilo5E-01 Se-75 9.57E-01 Cr-51 8.27E-01 I -131 5.21E-01 Be-7 9.06E-01 Ru-103 8.75E-01 XI -133 2.49E-03 Ba-140 6.64E-01*+ Cs-134 9.93E-01 Ru-106 9.86E-01*+ Cs-137 1.00B 00 Ag-ISOM 9.79E-03 Zr-95 9.22E-0,1 Co-58 9.29E-01*+ Mn-54 9.83E-01*+ ACTh228 1.00E 00 Tel-132 1.99E-01 Fe-59 8.90E-01*+ Zn-65 9.79E-01*+ Co-60 9.97E-01*+ K -40 1.00E 00 Sb-124 9.17E-01 Notes:* Activity greater than 3*standa:+ Peak is found x Decay correction less than .01 55 (-9 ( 3 ( 137 (-60 ( 85 ( 14 (-6 ( 12 (-2 (-86 ( 166 ( 12 3824 ( 76 (-2 ( 12 1126 ( 76 (-14 ( 7 ( 120 2240 ( 472 ( 69 4- 25 4- 30 4- 22 4- 60+- 29 4- 51+- 36 4- 74 4- 38 4-46 4- 40 4- 52 4- 49 4- 92+- 96+- 11+- 60 4- 74 4- 17 4- 22 4- 14 4- 14 4- 22 4- 53+- 61 E 2 E 0 E 1 E 0 E 2 E 0 E 1 E 0 E 1 E 0 E 0 E 0 E I E 0 E 0 E I E 0 E 0 E I E 2 E l El1 El1 El1 EQ0 85 E 2 99 E 0 74 E 1 190 E 0 97 E 2 170 E 0 120 E 1 250 E 0 130 E 1 150 E 0 130 E 0 150 E 0 160 E 1 200 E 0 320 E 0 36 E 1 200 E 0 200 E 0 49 E 1 75 E 2 48 E 1 40 E 1 23 E 1 160 E 1 200 E 0 rd deviation Approved by D.E.McCurdy. | ||
... ...... ........ ..4.t b **Ch ...y 1 .,. .....p.t ......hf, 40 ..t *.44.I.. '; .a 40.J nftl'. l' Richard Emch -bvy 89 59.tif Page 72.j r\AAILLL'ii 0 YANY, E ATONI C ELECTRIC COMPANY ENVIRONMENTAL LABORATORY Initial Analysis Report CustoNFI.: | ... ...... ........ ..4.t b **Ch ...y 1 .,. .....p.t ......hf, 40 ..t *.44.I.. '; .a 40.J nftl'. l' Richard Emch -bvy 89 59.tif Page 72.j r\AAILLL'ii 0 YANY, E ATONI C ELECTRIC COMPANY ENVIRONMENTAL LABORATORY Initial Analysis Report CustoNFI.: | ||
:Yer~on..A~an1ee Nuclear Power Corp.Atten ion: "MS. ELAINXE KECGA MR. EDWARD CUMJ-IING MR. STEPHEN SKIBNIOWSKY Report Date: Analysis Date: Date Received: Reference Date: 06/20/88 6 /15/88 6 /14/88 6 /a /as Septic-Liquid Portion Sample Amount: 1.00 Kg. Lab Sample No.: G73074 Sample Submission Code: VSLI04 2388 Elapsed Time : 7.57 days Other Analysis Requested: | :Yer~on..A~an1ee Nuclear Power Corp.Atten ion: "MS. ELAINXE KECGA MR. EDWARD CUMJ-IING MR. STEPHEN SKIBNIOWSKY Report Date: Analysis Date: Date Received: Reference Date: 06/20/88 6 /15/88 6 /14/88 6 /a /as Septic-Liquid Portion Sample Amount: 1.00 Kg. Lab Sample No.: G73074 Sample Submission Code: VSLI04 2388 Elapsed Time : 7.57 days Other Analysis Requested: | ||
None Station No.: 04 Main Tank Bottom DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC CORRECTION ( Pico Curie / Kilogram I........................................................................... | None Station No.: 04 Main Tank Bottom DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC CORRECTION ( Pico Curie / Kilogram I........................................................................... | ||
| Line 356: | Line 332: | ||
Mr 1L-.: YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY | Mr 1L-.: YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY | ||
--Initial Analysis Report Customer :y/(e;mont Yankee Nuclear Power Corp.A KEEGAN MR. EDWARD CUMMING Report Date: 07/11/88 Date Received: | --Initial Analysis Report Customer :y/(e;mont Yankee Nuclear Power Corp.A KEEGAN MR. EDWARD CUMMING Report Date: 07/11/88 Date Received: | ||
6 /14/88 Septic-Solid LAB. No. DATE ACTIVITY*SAMPLE CODE of VOLUME NUCLIDE CONC. +- 1 SIGMA MDC REFERENCE ANALYSIS Kg [ Pico Curie / KC -DRY S73075 6 /8 7 /7 0.022 Sr-90 (-14 +- 37 )E 0 40E 0 VSLs04 2388 Main Tank Bottom Sr-89 ( 52 +- 46 )E 0 62E 0 Notes:.00 quoted one-n. tg terms include only counti4 statistics and do not represent the propagation of all possible error, associated vith the radioactive decay process. t. Etimtes of the additional systesatic and random uncertainties are: calibration curve, -5 percent, and ample positioninS. | 6 /14/88 Septic-Solid LAB. No. DATE ACTIVITY*SAMPLE CODE of VOLUME NUCLIDE CONC. +- 1 SIGMA MDC REFERENCE ANALYSIS Kg [ Pico Curie / KC -DRY S73075 6 /8 7 /7 0.022 Sr-90 (-14 +- 37 )E 0 40E 0 VSLs04 2388 Main Tank Bottom Sr-89 ( 52 +- 46 )E 0 62E 0 Notes:.00 quoted one-n. tg terms include only counti4 statistics and do not represent the propagation of all possible error, associated vith the radioactive decay process. t. Etimtes of the additional systesatic and random uncertainties are: calibration curve, -5 percent, and ample positioninS. | ||
: 2 percent.Apppoved by D.E.mccurdy. | : 2 percent.Apppoved by D.E.mccurdy. | ||
Richard Emch -bvy 89 59.tif Page_74.... ... ... .. ..... .. ...... ..... .. ... .. ... .... -.. ..P a e 7 4........... | Richard Emch -bvy 89 59.tif Page_74.... ... ... .. ..... .. ...... ..... .. ... .. ... .... -.. ..P a e 7 4........... | ||
| Line 381: | Line 357: | ||
-I ISOTOPE-SPECIrPC SPECTRA I RPRIUT/25 | -I ISOTOPE-SPECIrPC SPECTRA I RPRIUT/25 | ||
-I TOTAL AMNHA SPECTRA I KPRINT I TAPE II CONTENTS KRFRI ITNT? !TAPE 12 C ON1TENT " IPINTMY o INTERMEDIATE DECAY RESULTS KFIT IN T19)DATA LIPRARY SELECTION OPTION INPUT ACTIVITY UNIT CONTROLD I SA.MA SPECTRA CONTROL FLAG I 3SURCE VOLUME (CUPIC METERS) -I.ToS0EAT 3OURCE INTENSITY INPUT MULTIPLIER I I.00SE0Go0 MIM. ISOTOPIC ACTIVITY FOR INCLUSIOA IN THE OUTPUT TADLES .00GOE100 TOTAL NUMPER OF NUCLIDES IN TAE INPUT | -I TOTAL AMNHA SPECTRA I KPRINT I TAPE II CONTENTS KRFRI ITNT? !TAPE 12 C ON1TENT " IPINTMY o INTERMEDIATE DECAY RESULTS KFIT IN T19)DATA LIPRARY SELECTION OPTION INPUT ACTIVITY UNIT CONTROLD I SA.MA SPECTRA CONTROL FLAG I 3SURCE VOLUME (CUPIC METERS) -I.ToS0EAT 3OURCE INTENSITY INPUT MULTIPLIER I I.00SE0Go0 MIM. ISOTOPIC ACTIVITY FOR INCLUSIOA IN THE OUTPUT TADLES .00GOE100 TOTAL NUMPER OF NUCLIDES IN TAE INPUT | ||
* A LIST OP INPUT NUCLID'ES AND ACTIVITIES ICURIES): Z,0540 :.831E-O6 270600 7.3:;3E-04 30oaS 2.0011E-T | * A LIST OP INPUT NUCLID'ES AND ACTIVITIES ICURIES): Z,0540 :.831E-O6 270600 7.3:;3E-04 30oaS 2.0011E-T | ||
::340 I.4CE-SA o:1375 9.TE -0T Z61371 S.STE-dT THERE IS CO137 AND/OR P137M IN TUE INPUT.CHECK IF P0TH NUCLIDES ARE IN THlE INPUT A/I ; THAT THE PAI37M ACTIVITY IT D.M46 TIMES THAT OP C3137.-C(D'C,,0 VIM C) | ::340 I.4CE-SA o:1375 9.TE -0T Z61371 S.STE-dT THERE IS CO137 AND/OR P137M IN TUE INPUT.CHECK IF P0TH NUCLIDES ARE IN THlE INPUT A/I ; THAT THE PAI37M ACTIVITY IT D.M46 TIMES THAT OP C3137.-C(D'C,,0 VIM C) | ||
.OLLCOAA (RADIOACTIVITY I 064194 SPECTRA -0(10(6-2 DAT4 14ASE -(447CC4 CENGINEERING. | .OLLCOAA (RADIOACTIVITY I 064194 SPECTRA -0(10(6-2 DAT4 14ASE -(447CC4 CENGINEERING. | ||
| Line 400: | Line 376: | ||
SE.AHO -FIELD ACTIVITY AFTER 40 TANK PUMFIFGS RADIOACTIVITY TOTALS (CURIES) AS A FUO4CTION OF DECAY TIME (MRS)NUCLIDES AITT ACTIVITY> ,GTDE00 (USEE-S-PECEFEP LIMIT) AL. .UCLD.ES RENCOUTERED IN) THE ANALYSIS T(HRS) NOP. OASES HALOGENS OTNER TOTAL GIVEN F1I0 NO. OASES HALOGENS OTHER TOTAL GIVEN) YIN.0O0C.OH .0000E.00 | SE.AHO -FIELD ACTIVITY AFTER 40 TANK PUMFIFGS RADIOACTIVITY TOTALS (CURIES) AS A FUO4CTION OF DECAY TIME (MRS)NUCLIDES AITT ACTIVITY> ,GTDE00 (USEE-S-PECEFEP LIMIT) AL. .UCLD.ES RENCOUTERED IN) THE ANALYSIS T(HRS) NOP. OASES HALOGENS OTNER TOTAL GIVEN F1I0 NO. OASES HALOGENS OTHER TOTAL GIVEN) YIN.0O0C.OH .0000E.00 | ||
.00DOECOG A.2=57E-O4 4.--ZT-EGA A.:TE0 .OO0OE)00 | .00DOECOG A.2=57E-O4 4.--ZT-EGA A.:TE0 .OO0OE)00 | ||
.000E0C.00 | .000E0C.00 | ||
:T-O 4.-.2-E-04ATET NUCLIDE MIO CONSISTS or .0 Z HOPLE GASES. .0 X HALOGENS. | :T-O 4.-.2-E-04ATET NUCLIDE MIO CONSISTS or .0 Z HOPLE GASES. .0 X HALOGENS. | ||
AND 100.0 Z OTHERS hNf OLLCGOE (RADO1ACTIVITT I SAMMA SPECTRA -08R1GE-: DATA 14ASE -E(41ECH EAIWEERIGO. | AND 100.0 Z OTHERS hNf OLLCGOE (RADO1ACTIVITT I SAMMA SPECTRA -08R1GE-: DATA 14ASE -E(41ECH EAIWEERIGO. | ||
| Line 452: | Line 428: | ||
-E;TECH ENGIIJEEI4G/'YANI-EE ATOKIC 11l000 01 -10/1:;,'86 86/07/0:. | -E;TECH ENGIIJEEI4G/'YANI-EE ATOKIC 11l000 01 -10/1:;,'86 86/07/0:. | ||
PAGE INPUT 4ATA LISTI;G -TAPE 4 I. :P1 ; 3 4 6 ;"8 U34-676901 | PAGE INPUT 4ATA LISTI;G -TAPE 4 I. :P1 ; 3 4 6 ;"8 U34-676901 | ||
-:347670701 | -:347670701 | ||
:"34:6769 I: 1347670901 | :"34:6769 I: 1347670901 | ||
:347676'0 I 00 -D1St. OF COtlT-;. SEWAGE -ACTI10. rRE; 40 PUi;pOUT3'. | :347676'0 I 00 -D1St. OF COtlT-;. SEWAGE -ACTI10. rRE; 40 PUi;pOUT3'. | ||
ACRES -FLOWED LAOOP 1 0 6 1 : 1 0.0 G.0.3.E-04 3.0 70.0 3 3 1.6 1:0.0 .1: 3 1.6 1;0.0 1:;5 s.15 -1.0 C)CCD D21O$-V (CYLINDRICAL RADIATION SOURCE POSTUItRC ) -E14TECH ENk0GJJC(8NG/YAUJZLE AlN1;:C -(6OD 03 -10/1ý/A6 ) A8'07,D. PACE ImPuT DATA LISTIU0 TAPE I I CARD 1 2 3 -7 SEO. 1 :346710901 | ACRES -FLOWED LAOOP 1 0 6 1 : 1 0.0 G.0.3.E-04 3.0 70.0 3 3 1.6 1:0.0 .1: 3 1.6 1;0.0 1:;5 s.15 -1.0 C)CCD D21O$-V (CYLINDRICAL RADIATION SOURCE POSTUItRC ) -E14TECH ENk0GJJC(8NG/YAUJZLE AlN1;:C -(6OD 03 -10/1ý/A6 ) A8'07,D. PACE ImPuT DATA LISTIU0 TAPE I I CARD 1 2 3 -7 SEO. 1 :346710901 | ||
:34:91:467T2 C391 6ls 78901 :34fl7S901 234:;d7eq01 234-,67990 I VT DISPOSAL OF COI4TA11INATED SEWAGCE -FIELD (OUILIDFIUI; ACTIVITY (8;EV/SEC) 2 TIU C(MRS$ .00OOE4 3 3 a.:oE-0: 322OE-01 72.720E-CI 8.200OE-0I1.OEC E.2(0 4 7:92:2E+03 | :34:91:467T2 C391 6ls 78901 :34fl7S901 234:;d7eq01 234-,67990 I VT DISPOSAL OF COI4TA11INATED SEWAGCE -FIELD (OUILIDFIUI; ACTIVITY (8;EV/SEC) 2 TIU C(MRS$ .00OOE4 3 3 a.:oE-0: 322OE-01 72.720E-CI 8.200OE-0I1.OEC E.2(0 4 7:92:2E+03 | ||
:.33IC4CZ I2AEO I.28E80 ..1307 .076E80 C)"'I TbH C)D (o | :.33IC4CZ I2AEO I.28E80 ..1307 .076E80 C)"'I TbH C)D (o | ||
*c)(0)ay Cr1OS-V (CYLINDRICAL RADNATION SOURCE DO3IC;ETRY) | *c)(0)ay Cr1OS-V (CYLINDRICAL RADNATION SOURCE DO3IC;ETRY) | ||
| Line 506: | Line 482: | ||
* 1.000 VEGETABLES ORED LEAFP 1.00 2.00 0.00 240.00 6.00 8766.00.00 .00 0.00 24.00 COW MILK PASTURE STDRSD.70 2.00 240.00 240.00 49.00 48.00 8766.00 8766.00.00 .00.00 2160.00 50.00 50.00.50 1.00 GOAT PASTURE.70 240.00 48.00 8764.00.0O.0O 6.00.50 1.00 MILK STORED 2.00 AS. 05 48.00 8466.00.00 2160.00 4.00 MEAT PASTURE STOKED.70 2.0.40.00 240.00 480.00 480.00 9766.00 .766.00.00 20.05oo 0.00 750.00.50 (.00 ID iO 0 tAM N.j'C CO4*~to I.00 I.00 USAGE FACTORS DOE DLIAREDTO AE)) OROA FROM ALL FATUNAIS COMBINED HEX LEAPY MILK MEAT INHALATION S AGE Y50 : NONE LIVER KIDNEY LUNG GI-LLI TAYRSI0 MHOLE NOSY SKIN ISO/TRI (RO/TR) (LI/YSRI (KO/YR) (I-/YR) MNREM ADULT 520.00 64.00 3)0.00 110.00 8000.00 a 5.89E-04 1.09E-03 .-06E-04 3.20E-04 2.42E-04 2.27E-04 9.31E-04 2.6,E-04 I TEEN 630.00 42.00 400.00 650.4 8000.00 N 7.92t-04 1.OAE-03 6.501-04 38VE-0A .4-4E-04 2.27E-04 8.44E-04 '.65E-04 9 CHILD 520.00 26.00 330.00 41.00 3700.00 9 0.50S-03 !)355-03 8.74S-04 4.S9S-04 S.38E-84 2.275-ON 6,67E-04 :.AE04 INFANT .00 .00 3w0.00 .00 1400.00 9 7.74E-04 I.20E-03 4.89E-04 3.35E-OA 2.30E-04 2.27E-04 3.30E-04 2.65E-04 N.......... | * 1.000 VEGETABLES ORED LEAFP 1.00 2.00 0.00 240.00 6.00 8766.00.00 .00 0.00 24.00 COW MILK PASTURE STDRSD.70 2.00 240.00 240.00 49.00 48.00 8766.00 8766.00.00 .00.00 2160.00 50.00 50.00.50 1.00 GOAT PASTURE.70 240.00 48.00 8764.00.0O.0O 6.00.50 1.00 MILK STORED 2.00 AS. 05 48.00 8466.00.00 2160.00 4.00 MEAT PASTURE STOKED.70 2.0.40.00 240.00 480.00 480.00 9766.00 .766.00.00 20.05oo 0.00 750.00.50 (.00 ID iO 0 tAM N.j'C CO4*~to I.00 I.00 USAGE FACTORS DOE DLIAREDTO AE)) OROA FROM ALL FATUNAIS COMBINED HEX LEAPY MILK MEAT INHALATION S AGE Y50 : NONE LIVER KIDNEY LUNG GI-LLI TAYRSI0 MHOLE NOSY SKIN ISO/TRI (RO/TR) (LI/YSRI (KO/YR) (I-/YR) MNREM ADULT 520.00 64.00 3)0.00 110.00 8000.00 a 5.89E-04 1.09E-03 .-06E-04 3.20E-04 2.42E-04 2.27E-04 9.31E-04 2.6,E-04 I TEEN 630.00 42.00 400.00 650.4 8000.00 N 7.92t-04 1.OAE-03 6.501-04 38VE-0A .4-4E-04 2.27E-04 8.44E-04 '.65E-04 9 CHILD 520.00 26.00 330.00 41.00 3700.00 9 0.50S-03 !)355-03 8.74S-04 4.S9S-04 S.38E-84 2.275-ON 6,67E-04 :.AE04 INFANT .00 .00 3w0.00 .00 1400.00 9 7.74E-04 I.20E-03 4.89E-04 3.35E-OA 2.30E-04 2.27E-04 3.30E-04 2.65E-04 N.......... | ||
1-s .... ss...st..v | 1-s .... ss...st..v | ||
........... | ........... | ||
: | : | ||
1~~>f PROGRAM ATMODOS YANKEE ATOMIC ELECTRIC COMPANY DEC. 1985 REV. 7 REGULATORY GUIDE .1D09, APPENAIX C MODELS POR CALCULATING DOSE VIA ADDIITIONAL PATHUAYS FROM RADIOIODINES AN0 OTHER RA[IONUCLIDES DISCHARGES TO THE ATMOSPHERE H0V.1977 LIfRARY THE FOLLOWING I NUCLIDES WERE USED IN THIS CALCULATION NUCLIDE RELEASE CURIES 55 CS 137 9.37E-05 SECTOR FLD DISTANCE S (MT ERTS)x/a 4.63E-04 (SEC '-31 U/S DETLETET 4.AIE-04 (SEC/M-TI DELTA I.2,E-04 I1/M--1 AT -SEWUGE C01(TA0 -SOLIDS 10 TM AT -2 ACRES -SHIELD PF 0 .01. -104 MR SCCri a PATHWAYS CONSIDERED GROUND PLANE YES INHALATION YES STORED VESETAPLES YES LEAFY VESETAPLES YES COW MILK YES GoAT MILK NO MEAT YES c.)10~tat ENC)Lti 0z VARSAPLE STO YV AGRICULTURAL PRODUCTIVITY (KS/M-21 2 P SOIL SURFACE BENMITT (KR/M-2) 240 T TRANSPORT TIME TO USER (HRR)TP SOIL EXPOSURE TINE (HER) 8786 TE CROP EXPOSURE TIME TO FLUME (HRS)TA HOLDUP AFTER HARVEST (HRS) 1440 OF ANIMALS DAILY FEED (K/DATY)rP FRACTION OF TEAR ON PASTURE FS FRACTION PASTURE WHEA ON PASTURE rG FRACTION OF STORES VEG BROWN IN GARDEN I FL FRACTION Of LEAFY VEG GROWN IN GARDEN FI FRACTION ELEMENTAL IODINE -.500 A AGSOLLUT E HUMIDITY -3.60 (m/MN3)PC FRACTIONAL ESUILIPRIUIM RATIO FOR C-I4 E .000 VEGETAPLES RED LEAFY.00 2.00.00 240.00*.00 AA.0.000 74.00 COW MILK PASTURE STORED.70 2.08 240.00 248.00 G766.00 0766. 00 GAO .0.00 2160.G0 50.00 50.00 000 1.00 GOAT MILK PASTURE STORED 2.70 2.00 240.08 240.00 48.00 48.00 8766.00 87A6.O0.00 .00.80 2160.00 6.00 6.00 ,50 1G00 PASTURE.70 240.00 460.00 8766.00.00.00 50.00 1.00 STORED 2.00 240.00 450.00 8766.00.00 2160,00 50.00 MEAT TO Tn 10 C)CO 10 ITO TO.00 1.00 USAGE FACTORS P OSE DELIVERED TO EACH1 OGRAN V FROM ALL PATHAMAS COMPINED AEG LEAFY MILK MEAT INHALATION F R 0 AGE , VE a I NOME LIVER KIDNEY LUNG SI-LLI THYROID UHOLE HODY SKIN (KI/YR) (ES/SR) (LI/YT) (KS/YA) (MN-/OR) 9 (MREEN A ADUULT 520.00 64.00 310.00 110.00 800.00 A 3.57E-02 4.70E-02 1.93(-02 9.79E-03 5.06E-03 2.0AE-03 I,25RtA2 2 .M9E-03 TEEN 630.00 42.00 400.00 65.00 :GO.0 , 5.52E-0 : 7.IRE-02 2.78E-02 1.39E-02 A.0E-03 ;,06E-02 !.81E-52 5.M0E-OI S CHILD 520.00 26.00 330.00 41.00 3700.00 t 1.21E-,0 lIE-Ol 4.IOE-02 I.AE-02 S.AR-S0 S.OAE-S3 2.0RE-0l 6M'R-O0 3 INPAMO .00 .00 110.00 .00 1(00.00 A O.S0E-Ol 6.35E-02 E _.*AE2 5.224E-03 506E-03 M.2E-0'3 NO9E-03 A INFANTN .0A 30.000E-2 0tt A At "1 TVJVEE ATON10 ELECTRIC ZOTAV%DEC, 109: FLV. I REOULArOR? | 1~~>f PROGRAM ATMODOS YANKEE ATOMIC ELECTRIC COMPANY DEC. 1985 REV. 7 REGULATORY GUIDE .1D09, APPENAIX C MODELS POR CALCULATING DOSE VIA ADDIITIONAL PATHUAYS FROM RADIOIODINES AN0 OTHER RA[IONUCLIDES DISCHARGES TO THE ATMOSPHERE H0V.1977 LIfRARY THE FOLLOWING I NUCLIDES WERE USED IN THIS CALCULATION NUCLIDE RELEASE CURIES 55 CS 137 9.37E-05 SECTOR FLD DISTANCE S (MT ERTS)x/a 4.63E-04 (SEC '-31 U/S DETLETET 4.AIE-04 (SEC/M-TI DELTA I.2,E-04 I1/M--1 AT -SEWUGE C01(TA0 -SOLIDS 10 TM AT -2 ACRES -SHIELD PF 0 .01. -104 MR SCCri a PATHWAYS CONSIDERED GROUND PLANE YES INHALATION YES STORED VESETAPLES YES LEAFY VESETAPLES YES COW MILK YES GoAT MILK NO MEAT YES c.)10~tat ENC)Lti 0z VARSAPLE STO YV AGRICULTURAL PRODUCTIVITY (KS/M-21 2 P SOIL SURFACE BENMITT (KR/M-2) 240 T TRANSPORT TIME TO USER (HRR)TP SOIL EXPOSURE TINE (HER) 8786 TE CROP EXPOSURE TIME TO FLUME (HRS)TA HOLDUP AFTER HARVEST (HRS) 1440 OF ANIMALS DAILY FEED (K/DATY)rP FRACTION OF TEAR ON PASTURE FS FRACTION PASTURE WHEA ON PASTURE rG FRACTION OF STORES VEG BROWN IN GARDEN I FL FRACTION Of LEAFY VEG GROWN IN GARDEN FI FRACTION ELEMENTAL IODINE -.500 A AGSOLLUT E HUMIDITY -3.60 (m/MN3)PC FRACTIONAL ESUILIPRIUIM RATIO FOR C-I4 E .000 VEGETAPLES RED LEAFY.00 2.00.00 240.00*.00 AA.0.000 74.00 COW MILK PASTURE STORED.70 2.08 240.00 248.00 G766.00 0766. 00 GAO .0.00 2160.G0 50.00 50.00 000 1.00 GOAT MILK PASTURE STORED 2.70 2.00 240.08 240.00 48.00 48.00 8766.00 87A6.O0.00 .00.80 2160.00 6.00 6.00 ,50 1G00 PASTURE.70 240.00 460.00 8766.00.00.00 50.00 1.00 STORED 2.00 240.00 450.00 8766.00.00 2160,00 50.00 MEAT TO Tn 10 C)CO 10 ITO TO.00 1.00 USAGE FACTORS P OSE DELIVERED TO EACH1 OGRAN V FROM ALL PATHAMAS COMPINED AEG LEAFY MILK MEAT INHALATION F R 0 AGE , VE a I NOME LIVER KIDNEY LUNG SI-LLI THYROID UHOLE HODY SKIN (KI/YR) (ES/SR) (LI/YT) (KS/YA) (MN-/OR) 9 (MREEN A ADUULT 520.00 64.00 310.00 110.00 800.00 A 3.57E-02 4.70E-02 1.93(-02 9.79E-03 5.06E-03 2.0AE-03 I,25RtA2 2 .M9E-03 TEEN 630.00 42.00 400.00 65.00 :GO.0 , 5.52E-0 : 7.IRE-02 2.78E-02 1.39E-02 A.0E-03 ;,06E-02 !.81E-52 5.M0E-OI S CHILD 520.00 26.00 330.00 41.00 3700.00 t 1.21E-,0 lIE-Ol 4.IOE-02 I.AE-02 S.AR-S0 S.OAE-S3 2.0RE-0l 6M'R-O0 3 INPAMO .00 .00 110.00 .00 1(00.00 A O.S0E-Ol 6.35E-02 E _.*AE2 5.224E-03 506E-03 M.2E-0'3 NO9E-03 A INFANTN .0A 30.000E-2 0tt A At "1 TVJVEE ATON10 ELECTRIC ZOTAV%DEC, 109: FLV. I REOULArOR? | ||
| Line 534: | Line 510: | ||
.82E-06 2.37E-055 | .82E-06 2.37E-055 | ||
.06E-065.06E-065.06E-065.06E-065.06E-065 | .06E-065.06E-065.06E-065.06E-065.06E-065 | ||
.06E-06 1.89E-053.79E-063.79E-063.79E-063.79E-063.79E-063.79E-06 11 24 1.28E-052.50E-08 2.90E-08 1.0E-02 1.2E-02 SOLUBLE 1.2E-02 3.1E-02 SOLUBLE ETC (FOR A TOTAL OF 89 NUCLIDES)--EOR----EDF--I 3VYXQF VY X/QFILE -SPECIAL VALUES -SEWAGE CONTAM. PROBLEI4 -2 ACRE PLOTS FLD 0 0OW MEAT 3.896E-02 3.896E-02 1.236E-04 3.896E-02--EOR--ENTECH ENGINEERING, INC.PIOI-EC3 -Page B.4-2 PrEOPRA; YANICE ATOMIC ELECTRIZ CONPAN'" DEC, INN: ERA.7 REGULATORY GUIDE 1.109, APPENDIX C MODELS FOR CALCULATING DOSE VIA ADDITIONAL PATHWAYS PROM RADIOIODDI1ES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE NOV.1Y77 LIPRARY THE FOLLOWING S NUCLIDES WERE USED IN THIS CALCULATION AUCLIDE RELEASE CURIES:5 MN 54 4.13E-06 27 CO 2.-5E04 30 zN 65 4.0cE-06 C CS 134 I.72E-06 CS 137 9.37E-AýSECTOR FLD DISTANCE 0 tIlETERS)7/O 3.90E-02 (SEC.'N-3) 7/O DEFLETED -.90YE-O (SEC/H-3)DELTA -l.*A4E-D (1/1-2)VY -SEWAGE CONTAN. SOLITDS I' PT AT -ACRES -SHIELD F -0.242 -CONT. OCCUP A PATHWAYS CON1SIDERED GROUND PLANE YES INNALAT IDA YES STORED VEGETAPLCS YES LEAFY VEGETAPLES YES COA RILK YES GOAT NILK NO MEAT YES rb--I o 1 0 VARIAPLE STO TV AORICULTURAL PRODUCTIVITT | .06E-06 1.89E-053.79E-063.79E-063.79E-063.79E-063.79E-063.79E-06 11 24 1.28E-052.50E-08 2.90E-08 1.0E-02 1.2E-02 SOLUBLE 1.2E-02 3.1E-02 SOLUBLE ETC (FOR A TOTAL OF 89 NUCLIDES)--EOR----EDF--I 3VYXQF VY X/QFILE -SPECIAL VALUES -SEWAGE CONTAM. PROBLEI4 -2 ACRE PLOTS FLD 0 0OW MEAT 3.896E-02 3.896E-02 1.236E-04 3.896E-02--EOR--ENTECH ENGINEERING, INC.PIOI-EC3 -Page B.4-2 PrEOPRA; YANICE ATOMIC ELECTRIZ CONPAN'" DEC, INN: ERA.7 REGULATORY GUIDE 1.109, APPENDIX C MODELS FOR CALCULATING DOSE VIA ADDITIONAL PATHWAYS PROM RADIOIODDI1ES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE NOV.1Y77 LIPRARY THE FOLLOWING S NUCLIDES WERE USED IN THIS CALCULATION AUCLIDE RELEASE CURIES:5 MN 54 4.13E-06 27 CO 2.-5E04 30 zN 65 4.0cE-06 C CS 134 I.72E-06 CS 137 9.37E-AýSECTOR FLD DISTANCE 0 tIlETERS)7/O 3.90E-02 (SEC.'N-3) 7/O DEFLETED -.90YE-O (SEC/H-3)DELTA -l.*A4E-D (1/1-2)VY -SEWAGE CONTAN. SOLITDS I' PT AT -ACRES -SHIELD F -0.242 -CONT. OCCUP A PATHWAYS CON1SIDERED GROUND PLANE YES INNALAT IDA YES STORED VEGETAPLCS YES LEAFY VEGETAPLES YES COA RILK YES GOAT NILK NO MEAT YES rb--I o 1 0 VARIAPLE STO TV AORICULTURAL PRODUCTIVITT | ||
(-1/A-2T P SOIL SURFACE DENSITY (KUlE-2I 240 TRANSPORT TIME TO USER ("PS)TP DOlL EXPOSURE TIME (ANS) A76(TE CROP EXPOSURE TINE TO PLUME (IMP)TN HOLDUP AFTER HARVEST (HER) 1441 OP ANIMALS DAILY FEED (KO/DAY)FP FRACTION OF YEAR ON PASTURE FS FRACTION PASTURE WHEN ON PASTURE FO FRACTION OF STORED VEG OROWN IN GARDEN I FL FRACTION Of LEAFY VNE DROWN IN SARDEN rl FRACTION ELEMENTAL IODINE -.Z00 H ADSOLUTE HUMIDITY 3 5.60 (SH/N-3)PC FRACTIONAL EOUILIBRIUM RATIO FOR C-I4 -1.000 VEGETABLES (RED LEAFY.00 T.EN.00 240.00.00 A76A.00.00 .00.00 24.00 COW PASTURE.70.40.00 1N.00 0766.00.00.00 50.00.:0 1.00 (tILE STORED:.00.40.00 18.00 8766.00.00 2160.00"0.00 COAT NILK PASTURE STORED.70 2.00 240.00 240.00 40.00 40.00 8766.00 87A6.00.00 .00.00 2260.00 6.00 6.00 1.00 PASTURE.70 240.00 400.00 8766.00.00.00 50. 00.20 1.00 STOSED 240.00 400.00 RA66.00.00:160.00:0.00 NEAT 1.00 I-00 NNNNRNNNERNNNNNNWNRNNANANENNNWNN$NRNtNNNNNNNA0ANNSNNNNRNRNRNNRNNNINAtSNNNNNWNtNNNN USAGE FACTORS N DOSE D[ELIVERED TO EACH ORGAN NPFROM ALL PATHWAYS CONPINED *VEO LEAFY MILK NEAT INHALATIO4 N X AGE DEO N DONE LIVER KIDrNET LUNG GI-LLI THYROID WHOLE PODY SK1b (KO/TRI (KO/YRD (LI/TR) (KO/YR) (I-S/YR) H (MREA) I ADULT 520.00 64.00 310.00 110.00 OOO.00 N .TýE+O0 I.TAENOO 1.21E+O0 3.O4E400 (.TVENO0 1.16E400 I.:TEAAO 1.37E00 I TEEN 630.00 42.00 400.00 62.00 0000.00 N I.30E#O0 1.3ZEA00 I.T3EAOO 3.91C2400 ITGE+O0 1.1AE#OO I.24E400 1.37E#00 t CHILD 320.00 26.00 330.00 41.00 3700.00 a 1.4OE00 1.41E000 I.Z;EAOO 3.39E#00 1.22EA00 1.16EEO I.2SEAOO 1.37E(00 N INPANT .00 .00 330.00 .00 1400.00 N I.TSE(O0 I.3TE(00 I.:tEAOO 2.A;E+00 1.19E00 I.1AEAOD I.19HE00 1.7E.OO A.I ......$.. ....t:N ADULT DOSES RECEIVED FROM VARIOUS PATHWAYS LIVER KIDNEY LUNG FL SECTOR AT A DISTANCE OF 0 METERS PATNWAY PONE 01-LLI THYROID WHOLE BODY SKIN GROUND PLANE 04 MN 60 CO 61 ZN 134 CS£37 CI TOTAL FOR PATHWAY INHALATION 54 MN 60 CO 65 ZN 134 CS 137 CS TOTAL FOR PATHWAT STORED VEGETABLES 04 MN 60 CO 65 ON 134 CS 137 CS TOTAL FOR PATHWAY LEAFY VESETAPLES M4 MN A0 CO 65 ZN 134 CS 137 CS TOTAL FOR PATHWAY.00 +00 I. ROE-C4 7.9ME-0H!.O3E-04 5.63E-02 ,00E400:00E÷00 E. A3- 02 1.230-03 2.30E-04 1.97E-02-.12E-02.0E000.OOEOO0 1 .76R-04 2.9E-0O;2 43E-03 2.0f2-04 3.57E-03 5:74E-04£ .800-03 7.100-02 7. DOaE-SO B.NOE-02 I.:24E-03 3.I E-03.46E-04 2..6AE-02 3.27E-02 1.230-02 1.R6E-04 3.67E-OA 7.I0E-O;3.33E-03 0.020-SO.OOE+O0 3 E.3E-04 6.08E-04 2. 6NE-02 2.62E-0O:.OOECO0 2.6 !%-03 9. I1E-03 1..OE-02 3.67E-06.00E400 3..E-ED4 2 ,0 E-O 1.13E-03 7.14E-03 1.80E200 4.NOE-03 2.:OE-04 0.70E-03 I .87E#00.OOE#O0 TOE + 00* 00E 4 00 S.6lE-CO;3.0 4E-03 3. IORE-03 OCR +00.ODE+OO DOE* 400 ,.63IE- 06 3.76 E-04 3. 9E-04!.83E-02-.9OE-O4 9 .00-02 9.DOE -01 2 70E- 04 ,*..33E-02* .46E-03 9.76E-06 5,.Z[--04 3.70E-O'.93E-03 3.ý7E-04 1.24E-06.00E400.00El00.OOE000.0TE 00* TOE 400.0OE 00.00E*00 ,T[ 400.000400 ,00E400.000+00 4.30E-03 I .0+E00 2.0 4E-03 4.:8E-03 1.02E-01 1. I&E+00 3.21E-00 4.-9E-03 1,.94040..9,E-02-6,E-O2 1 .6NE-02.403..76E-03.4 7E-04 1.76E-0O 2,.36E-06 3.44R-04 7.06E-04 I.80E-O0 I. BE-03 5.020E-03 I .2.3C 00 3.30E-03:.34E-03 I. 19E-0l 1.37E400 t23 Zt.1.040-03 3.83E-04 3.39E-03 .OOE400 2.04E-03 2.640-03 4.14E-03 PA THW4JAT COW MILK 24 MN 60 CO AS ZN 134 C5 137 CS TOTAL FOR PATHWAY"EAT 54 MN 60 CO 60 ZN 134 CS 137 Cs TOTAL FOR PATHWAY TOTAL ALL PATHS TOTAL ALL PATHS INCLUDINO WNOLE POOT 0060 rPo0 00OUN9 PLANE EXPOSURE SONE.00(+00 1.490-03 9.3:E-02 7.0:E-03 8.63E-03.000400.00 400 3.66E-04 9.67E-06 8.33E-04 1.23E-03 9.000-02 1.:0EO00 LIVER 6.790-07 2.72E-0;4.740-03 1.990-04 4.6:0-03 1.460-02 7.400-07 I. 700 -04 1.230-03 2.300-0: 1.140-03 2,.6E-03 1.2E-03_6E90340 ADULT DOSE0 RECEIVED FROM 4AR20US PATHWA;S (HREM)KILNEY LUNG 2.02E-07 .000400.0000 .00400 3.17E-03 .OO04 0 6.4E0-0 2.13E-02 3.270-03 1.09E-03 6-.10-03 1.11E-03 GI-LLI:,O:E-O6 6499E-04..99E-03 3.4!E-06 I.;,E-04 3.600-03-.:7E-06 3. 00-03 7.7:0-04:..21-02 4.00E-03 1. 29E 01 1.290 400 PLO SECTOR AT A DISTANCE Or 3HTROID WHOLE SOOY.000400 1.29E-07.OOEO40 .200E-05.00O000 2.24E-03.OO0O0 1.2E2-04.E00000 6.32E-03.00t.00 B.70-E03 0 IhTEFS SKI14 2,OE-07.00!4 00 8.;22-04 3.57E-04*I.:22'-03 4.GOE-02 0.10 0E00.00E+00.00E400.000+00-.47[-06 1.31E-04 3.040400.OOEoO0.OOE 00.00E400..00E 0 0.000400.OOE O0.000400.00C.00 1.16E400 1.41E*07 3.76E-04 7.46E-04 1,70E-03 1.27-400 1.3-0400 1.:E+000 041/4071 MT TEEN DOSES REC EIVED FRO,;VAROUS PATNWAAS (MrEM)PONE LIVER KIDNEY LU14G FLO SECTOR AT A DISTANCE OF 0 METERS FATHWAY 0I-LLI THYrROID WHOLE B01DY SKIN GROUND PLANE 54 MN 60 CO 65 ,* 134 CS 137 CO TOTAL FOR PATHWAY INHALATION 54 MN 60 CO AS ZN 1 4 CS 137 CO TOTAL FoR PATHWAY STORED UEOETAPLES 54 M N 60 C0 6 5 2 N 134 CS 137 CS TOTAL FOP PATHWAY LEAPY VOOETAPLES 04 MN 60 CO A5 ZN 134 CS 137 CS TOTAL FOR PATHWAY 4 .30E-03 I. OE#O0:.94E-03!. atE-03 C .02E-01:.05K-03 5.700-03 I.,140-01 1.160+00 1.37E-00.OOr4O0 O0E $00:E14E-03 I.06-03 7.7:E-02 4.63E-03 7.4 E-O0 V,8.E-02 6A49E-05 0OE 0O0 4.00E-04 0.50-04!,G 4Eý00,0 A. v' E03 3.200-04 1.40K-0.3. IE-04 a .0E-02 E.5E-04 0.31 E -O 00 0010 00.0OE4O00.00E$00.00D400 4,290-05 A.1'E-03 3.4-,E-04 1 .1 6 -03 3 .60E -0.7.98E-02 1.06E-01 3-620-02 :.4E4o00 O.20E-02 .0GE+00 1.37E-0'.OOE MOO 1. 770-03 3.740-04 3.37E-.2 I .3E-04 1.97E-03 6.13E-03 , !E-04 4.,46E-02 4.11 E -03 OOE$OO 3.930-03 I.E0-02 ,OOE+O0 OE $+00.0OEl GO: I1.07E-G4 V.GE-03 6.70-03 6,3SE- 04.OOE400*OOE÷O0.00CE00.O OE $00.* GE +O0G-.73E-05 4.4;E-03 A.06E-03 4.I =-OA C)I z C) t lb~0q 3.57E-02 S.37E-02 1.94E-02 6.0IE-03 2.12K-02 .OOE#00 2.33E-02.000400 , 39E-04 2. +3KE-OS 5.63ER-0S 1.050-GO 1,34R-04 4.,4[-0-A,20E-0O 2.99E-03 3.12K-GA.:0':E;0040 | (-1/A-2T P SOIL SURFACE DENSITY (KUlE-2I 240 TRANSPORT TIME TO USER ("PS)TP DOlL EXPOSURE TIME (ANS) A76(TE CROP EXPOSURE TINE TO PLUME (IMP)TN HOLDUP AFTER HARVEST (HER) 1441 OP ANIMALS DAILY FEED (KO/DAY)FP FRACTION OF YEAR ON PASTURE FS FRACTION PASTURE WHEN ON PASTURE FO FRACTION OF STORED VEG OROWN IN GARDEN I FL FRACTION Of LEAFY VNE DROWN IN SARDEN rl FRACTION ELEMENTAL IODINE -.Z00 H ADSOLUTE HUMIDITY 3 5.60 (SH/N-3)PC FRACTIONAL EOUILIBRIUM RATIO FOR C-I4 -1.000 VEGETABLES (RED LEAFY.00 T.EN.00 240.00.00 A76A.00.00 .00.00 24.00 COW PASTURE.70.40.00 1N.00 0766.00.00.00 50.00.:0 1.00 (tILE STORED:.00.40.00 18.00 8766.00.00 2160.00"0.00 COAT NILK PASTURE STORED.70 2.00 240.00 240.00 40.00 40.00 8766.00 87A6.00.00 .00.00 2260.00 6.00 6.00 1.00 PASTURE.70 240.00 400.00 8766.00.00.00 50. 00.20 1.00 STOSED 240.00 400.00 RA66.00.00:160.00:0.00 NEAT 1.00 I-00 NNNNRNNNERNNNNNNWNRNNANANENNNWNN$NRNtNNNNNNNA0ANNSNNNNRNRNRNNRNNNINAtSNNNNNWNtNNNN USAGE FACTORS N DOSE D[ELIVERED TO EACH ORGAN NPFROM ALL PATHWAYS CONPINED *VEO LEAFY MILK NEAT INHALATIO4 N X AGE DEO N DONE LIVER KIDrNET LUNG GI-LLI THYROID WHOLE PODY SK1b (KO/TRI (KO/YRD (LI/TR) (KO/YR) (I-S/YR) H (MREA) I ADULT 520.00 64.00 310.00 110.00 OOO.00 N .TýE+O0 I.TAENOO 1.21E+O0 3.O4E400 (.TVENO0 1.16E400 I.:TEAAO 1.37E00 I TEEN 630.00 42.00 400.00 62.00 0000.00 N I.30E#O0 1.3ZEA00 I.T3EAOO 3.91C2400 ITGE+O0 1.1AE#OO I.24E400 1.37E#00 t CHILD 320.00 26.00 330.00 41.00 3700.00 a 1.4OE00 1.41E000 I.Z;EAOO 3.39E#00 1.22EA00 1.16EEO I.2SEAOO 1.37E(00 N INPANT .00 .00 330.00 .00 1400.00 N I.TSE(O0 I.3TE(00 I.:tEAOO 2.A;E+00 1.19E00 I.1AEAOD I.19HE00 1.7E.OO A.I ......$.. ....t:N ADULT DOSES RECEIVED FROM VARIOUS PATHWAYS LIVER KIDNEY LUNG FL SECTOR AT A DISTANCE OF 0 METERS PATNWAY PONE 01-LLI THYROID WHOLE BODY SKIN GROUND PLANE 04 MN 60 CO 61 ZN 134 CS£37 CI TOTAL FOR PATHWAY INHALATION 54 MN 60 CO 65 ZN 134 CS 137 CS TOTAL FOR PATHWAT STORED VEGETABLES 04 MN 60 CO 65 ON 134 CS 137 CS TOTAL FOR PATHWAY LEAFY VESETAPLES M4 MN A0 CO 65 ZN 134 CS 137 CS TOTAL FOR PATHWAY.00 +00 I. ROE-C4 7.9ME-0H!.O3E-04 5.63E-02 ,00E400:00E÷00 E. A3- 02 1.230-03 2.30E-04 1.97E-02-.12E-02.0E000.OOEOO0 1 .76R-04 2.9E-0O;2 43E-03 2.0f2-04 3.57E-03 5:74E-04£ .800-03 7.100-02 7. DOaE-SO B.NOE-02 I.:24E-03 3.I E-03.46E-04 2..6AE-02 3.27E-02 1.230-02 1.R6E-04 3.67E-OA 7.I0E-O;3.33E-03 0.020-SO.OOE+O0 3 E.3E-04 6.08E-04 2. 6NE-02 2.62E-0O:.OOECO0 2.6 !%-03 9. I1E-03 1..OE-02 3.67E-06.00E400 3..E-ED4 2 ,0 E-O 1.13E-03 7.14E-03 1.80E200 4.NOE-03 2.:OE-04 0.70E-03 I .87E#00.OOE#O0 TOE + 00* 00E 4 00 S.6lE-CO;3.0 4E-03 3. IORE-03 OCR +00.ODE+OO DOE* 400 ,.63IE- 06 3.76 E-04 3. 9E-04!.83E-02-.9OE-O4 9 .00-02 9.DOE -01 2 70E- 04 ,*..33E-02* .46E-03 9.76E-06 5,.Z[--04 3.70E-O'.93E-03 3.ý7E-04 1.24E-06.00E400.00El00.OOE000.0TE 00* TOE 400.0OE 00.00E*00 ,T[ 400.000400 ,00E400.000+00 4.30E-03 I .0+E00 2.0 4E-03 4.:8E-03 1.02E-01 1. I&E+00 3.21E-00 4.-9E-03 1,.94040..9,E-02-6,E-O2 1 .6NE-02.403..76E-03.4 7E-04 1.76E-0O 2,.36E-06 3.44R-04 7.06E-04 I.80E-O0 I. BE-03 5.020E-03 I .2.3C 00 3.30E-03:.34E-03 I. 19E-0l 1.37E400 t23 Zt.1.040-03 3.83E-04 3.39E-03 .OOE400 2.04E-03 2.640-03 4.14E-03 PA THW4JAT COW MILK 24 MN 60 CO AS ZN 134 C5 137 CS TOTAL FOR PATHWAY"EAT 54 MN 60 CO 60 ZN 134 CS 137 Cs TOTAL FOR PATHWAY TOTAL ALL PATHS TOTAL ALL PATHS INCLUDINO WNOLE POOT 0060 rPo0 00OUN9 PLANE EXPOSURE SONE.00(+00 1.490-03 9.3:E-02 7.0:E-03 8.63E-03.000400.00 400 3.66E-04 9.67E-06 8.33E-04 1.23E-03 9.000-02 1.:0EO00 LIVER 6.790-07 2.72E-0;4.740-03 1.990-04 4.6:0-03 1.460-02 7.400-07 I. 700 -04 1.230-03 2.300-0: 1.140-03 2,.6E-03 1.2E-03_6E90340 ADULT DOSE0 RECEIVED FROM 4AR20US PATHWA;S (HREM)KILNEY LUNG 2.02E-07 .000400.0000 .00400 3.17E-03 .OO04 0 6.4E0-0 2.13E-02 3.270-03 1.09E-03 6-.10-03 1.11E-03 GI-LLI:,O:E-O6 6499E-04..99E-03 3.4!E-06 I.;,E-04 3.600-03-.:7E-06 3. 00-03 7.7:0-04:..21-02 4.00E-03 1. 29E 01 1.290 400 PLO SECTOR AT A DISTANCE Or 3HTROID WHOLE SOOY.000400 1.29E-07.OOEO40 .200E-05.00O000 2.24E-03.OO0O0 1.2E2-04.E00000 6.32E-03.00t.00 B.70-E03 0 IhTEFS SKI14 2,OE-07.00!4 00 8.;22-04 3.57E-04*I.:22'-03 4.GOE-02 0.10 0E00.00E+00.00E400.000+00-.47[-06 1.31E-04 3.040400.OOEoO0.OOE 00.00E400..00E 0 0.000400.OOE O0.000400.00C.00 1.16E400 1.41E*07 3.76E-04 7.46E-04 1,70E-03 1.27-400 1.3-0400 1.:E+000 041/4071 MT TEEN DOSES REC EIVED FRO,;VAROUS PATNWAAS (MrEM)PONE LIVER KIDNEY LU14G FLO SECTOR AT A DISTANCE OF 0 METERS FATHWAY 0I-LLI THYrROID WHOLE B01DY SKIN GROUND PLANE 54 MN 60 CO 65 ,* 134 CS 137 CO TOTAL FOR PATHWAY INHALATION 54 MN 60 CO AS ZN 1 4 CS 137 CO TOTAL FoR PATHWAY STORED UEOETAPLES 54 M N 60 C0 6 5 2 N 134 CS 137 CS TOTAL FOP PATHWAY LEAPY VOOETAPLES 04 MN 60 CO A5 ZN 134 CS 137 CS TOTAL FOR PATHWAY 4 .30E-03 I. OE#O0:.94E-03!. atE-03 C .02E-01:.05K-03 5.700-03 I.,140-01 1.160+00 1.37E-00.OOr4O0 O0E $00:E14E-03 I.06-03 7.7:E-02 4.63E-03 7.4 E-O0 V,8.E-02 6A49E-05 0OE 0O0 4.00E-04 0.50-04!,G 4Eý00,0 A. v' E03 3.200-04 1.40K-0.3. IE-04 a .0E-02 E.5E-04 0.31 E -O 00 0010 00.0OE4O00.00E$00.00D400 4,290-05 A.1'E-03 3.4-,E-04 1 .1 6 -03 3 .60E -0.7.98E-02 1.06E-01 3-620-02 :.4E4o00 O.20E-02 .0GE+00 1.37E-0'.OOE MOO 1. 770-03 3.740-04 3.37E-.2 I .3E-04 1.97E-03 6.13E-03 , !E-04 4.,46E-02 4.11 E -03 OOE$OO 3.930-03 I.E0-02 ,OOE+O0 OE $+00.0OEl GO: I1.07E-G4 V.GE-03 6.70-03 6,3SE- 04.OOE400*OOE÷O0.00CE00.O OE $00.* GE +O0G-.73E-05 4.4;E-03 A.06E-03 4.I =-OA C)I z C) t lb~0q 3.57E-02 S.37E-02 1.94E-02 6.0IE-03 2.12K-02 .OOE#00 2.33E-02.000400 , 39E-04 2. +3KE-OS 5.63ER-0S 1.050-GO 1,34R-04 4.,4[-0-A,20E-0O 2.99E-03 3.12K-GA.:0':E;0040 | ||
: 3. 10 E-04 1.97E-Oz I. OE-O3 ,OOElO0.OOEIO0.00K +00 7.S2K-06 3.95K-G4 2..ISK-0 1.7:E-03 7.OSE-04..71E-07 4.25,E-0.00(400.00K E+00.O00rOEO0.OOE+O0.00 +000 2.07E-06 3.03[-04 2. E--04 1.040-03 2..aE-03 3.6KE-03 1.32E-03 4.020-04 2.0,K-03 .OOK400 1.60E-03 | : 3. 10 E-04 1.97E-Oz I. OE-O3 ,OOElO0.OOEIO0.00K +00 7.S2K-06 3.95K-G4 2..ISK-0 1.7:E-03 7.OSE-04..71E-07 4.25,E-0.00(400.00K E+00.O00rOEO0.OOE+O0.00 +000 2.07E-06 3.03[-04 2. E--04 1.040-03 2..aE-03 3.6KE-03 1.32E-03 4.020-04 2.0,K-03 .OOK400 1.60E-03 | ||
Revision as of 03:30, 13 July 2019
| ML070950500 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 04/02/2007 |
| From: | Dewald L Entergy Nuclear Vermont Yankee |
| To: | Emch R NRC/NRR/ADRO/DLR/REBB |
| References | |
| TAC MD2297 | |
| Download: ML070950500 (128) | |
Text
IRichard Emich -two of- wo messag'es w ith atta6hme'nts' Page1 From: To: Date:
Subject:
Here's the third"DeWald, Lynn" <Idewald@entergy.com>"Richard Emch" <RLE@nrc.gov>
04/02/2007 1:36:40 PM two of two messages with attachments document.
Lynn Lynn DeWald Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Road Vernon, VT 05354 802-258-5526 (phone)802-258-5865 (fax)802-380-4493 (cell)
Ic-:\ t em-,p \--G-W}O)O-0-001 .TMP PM-gel_-- eA 11 Mail Envelope Properties (46113FIC.79E
- 14 : 14238)
Subject:
Creation Date From: Created By: two of two messages with attachments 04/02/2007 1:36:16 PM"DeWald, Lynn" <ldewald(ientergy.com>
ldewald(ientergy.com Recipients nrc.gov OWGWPOO2.HQGWDO01 RLE (Richard Emch)Post Office OWGWPO02.HQGWDO01 Files MESSAGE TEXT.htm Mime.822 Options Expiration Date: Priority: ReplyRequested:
Return Notification:
Concealed
Subject:
Security: Route nrc.gov Size 204 3893 6719 Date & Time 04/02/2007 1:36:16 PM None Standard No None No Standard Junk Mail Handling Evaluation Results Message is eligible for Junk Mail handling This message was not classified as Junk Mail Junk Mail settings when this message was delivered Junk Mail handling disabled by User Junk Mail handling disabled by Administrator Junk List is not enabled Junk Mail using personal address books is not enabled Block List is not enabled Richard Emch -bvy 8959.tif .. .................................
Page.1.. ... ..... ....... ....Outgoing NRC Correspondence VERMONT YANKEE LICENSING CORRESPONDENCE/COMMITMENT CONTROL SHEET DESCRIPTION:
TRANSMITTAL OF VY R ET TO ROUTINELY DISPOSE OF SLIGHTLy CONTAMINATED SEPTIC WASTE IN ACCORDANCE WITH 10 CFR 20.302(a)SUMMARy: APPROVAL REQESTED BY THE END OF THE FIRST QUARTER OF 1990.7 CATEGORY:
LAI STATUS: N/A WORK ORDER: N/A DOCUMENT NUMBER(S):
NO LAI BVY 89-59 DOCUMENT DATE: 6 /28 /89 RESPONSIBILITY:
NSD , RWC , FOR DIST FINAL DUE: / I DRAFT DUE: / / LAST UPDATE: / /INTERNAL DISTRIBUTION NSD Corporate Brattleboro Additional A. C. Kadak J. G. Weigand R. McCullough J. DeVincentis D. A. Reid/W. P. Murphy R. Leach S. P. Schultz D. K. McElwee/J.
Powers E. Lindamood NSD D. McCue (I copy)
- S. Skibniowsk S. R. Miller D. Weyran J. R. Hoffman Plant P. Littlefiel R. W. Capstick J. P. Pelletier
-2 M M. J. Marian
- R. J. Wanczyk R. L. Smith R. D. Pagodin *J. G. Robinson H. M. Metell A. M. Shepard -2 D. C. Girroir Licensing File Copy (original)*
Chrono Copy B. C. Slifer A. J. Christie
- WITH ENCLOSUREES EXTERNAL DISTRIBUTION (Correspondence Only)Regulatory Affairs and Programs John Ritsher, Esq. Bruce B. Beckley Boston Edison Company Ropes & Gray Public Service of 25 Braintree Hill Office Park 225 Franklin Street New Hampshire Braintree, MA 02184 Boston, MA 02199 1000 Elm Street P.O. Box 330 Richard C. DeYoung Charles M. Rice Manchester, NH 03105 1110 Basil Drive 355 W. 14th Street New Bern, NC 28562 Idaho Falls, ID 83402 Robert G. Staker W. A. Zarbis, Fuel Licensing P.O. Box 378 Nuclear Safety & Licensing Operation Germantown, MD 20874 General Electric Company 175 Curtner Avenue G. Sterzinger, Chairman
- San Jose, CA 95125 Public Service Board 120 State Street NUS Corporation Montpelier, VT 05602 j (Plant (Plant Plant Plant (Bcatt (NSD)(NSD)*
Richard Emch -bvvy89 59tif-...... .!, r E ._ ..... .9 .i ... .........
.... .. ......VERMONT YANKEE NUCLEAR POWER CORPORATION Ferry Road, Brattleboro, VT 05301-7002 ENGINEERING OFFICE 580 MAIN STREET June 28, 1989 BOLTON. MA01740 BVY 89-59 (508) 779.6711 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Document Control Desk
Reference:
License No. DPR-28 (Docket No. 50-271).
Subject:
Request to Routinely Dispose of Slightly Contaminated Septic Waste in Accordance with 10CFR20.302(a)
Dear Sir:
In accordance with the criteria of the Code of Federal Regulations, Title 10, Section 20.302(a)
(10CFR20.302(a)), enclosed please find the subject application for the disposal of very low level radioactive waste materials.
Vermont Yankee Nuclear Power Corporation (Vermont Yankee) hereby requests NRC approval of the proposed procedures for the disposal of slightly contaminated septic waste generated at the Vermont Yankee Nuclear Power Plant in Vernon, Vermont.This application specifically requests approval to dispose of septic tank waste, contaminated at minimal levels, which have been or might be generated through the end of station operations at the Vermont Yankee Nuclear Power Plant. The proposed method of disposal is for the on-site land spreading in designated areas in compliance with State of Vermont health code requirements for septic waste. Disposal of this waste in the manner proposed, rather than at a 10CFRPart 61 licensed facility would save Vermont Yankee not only substantial cost, but also valuable disposal site space which would then be available for wastes of higher radioactivity levels. Disposal as radioactive waste would require treatment of the biological aspects of the septage and solidification to a stable waste form, thereby increasing the volume substantially.
A radiological assessment and proposed operational controls, based upon the continued on-site disposal of septic waste as presently contained in the plant's septic tanks, are detailed in Attachments 1 and 2.Based upon this analysis, Vermont Yankee requests approval to dispose of septic tank waste on-site by land spreading in such a manner that the radioactivity concentration limit in any batch of septage to be spread does not exceed one-tenth of the MPC values listed in 10CFR20, Appendix B, Table II; and the combined radiological impact for all disposal operations shall be limited to a total body or organ dose of a maximally exposed member of the public of less than one mrem/year (less than 5 mrem/year to an inadvertent intruder).
RicardErnh -bvyy89 95. tit Pge3 United States Nuclear Regulatory Commission June 28, 1989 Page 2 Due to our expected need to utilize the proposed methodology of land application of septic waste on-site during the spring of 1990, we request your review and approval of this proposed disposal method by the end of the first quarter of 1990.We trust that the information contained in the submittal is sufficient; however, should you have any questions or require further information concerning this matter, please contact this office Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION Robert W. Caps ick, Jr.Licensing Engineer MSS/emd Enclosures cc: USNRC -Region I USNRC -Resident Inspector, VTNPS
,Richard Erch -bvy 8959t91 A if Page 4'4% m~tET 1 ins ooctm~~:~
- INP(r7 $(~R~ -~ I.MuE ztf !L RE lOUt Ov ____.4. PECORD TYPE NO.ý.. Ims SUBJECT NO.6. DATE WRITTEN 7.
FORE 8. DOCUEh1ENT LOCATION 4ý3 Lsri k tTP* ..SUPPLEMENTAL INFORMATION
- 9. PALtAPY DOCtUYENT NO. // f 14. TtTME ý4W/7X7tA V> %'?J l"',....14. RE-T"EVP 1.7 URrFEFXNC DOUMENE.21.!j LOR ORDE tO.~ (CiRCLE ONE l' ADD,~ ~ ldcon '~t~'z t ~~c~xclADD.
p~CN'" rovide, document Acce c I z,, Nt=be,- r t docmn t 1"T eL-aiOi iS. 'mation an~d c~~~VA~ +/-£e'~ decur cc,~rioratox a.pi prticillar thiracte.1 1tc, -:~entry D~tELETE, provide documentA.C c'esslon r~~e am.*c~1'E Richard Emch.- bvy 89 59.tif page 5 ATTACHMENT 1 VERMONT YANKEE NUCLEAR POWER PLANT APPLICATION FOR APPROVAL TO ROUTINELY DISPOSE OF SEPTIC WASTE WITH MINIMAL LEVELS OF RADIOACTIVITY 6677R rxIt~iit~ru
~riiuri -uvy o~-i D~9.tIT P~oeR I MICHard MCH -UVY OU OU4111 Pa0p iý I I VERMONT YANKEE NUCLEAR POWER PLANT Application for Auproval to Routinely Dispose of Septic Waste With Minimal Levels of Radioactivity
1.0 INTRODUCTION
Vermont Yankee Nuclear Power Corporation (Vermont Yankee) requests approval, pursuant to lOCFR20.302(a), of a method proposed herein for the routine disposal of slightly contaminated septic tank waste. Vermont Yankee proposes to dispose of this waste by spreading it on designated areas within the plant's site boundary fence. This application addresses specific information requested in 10CFR20.302(a).
2.0 WASTE STKAMDESCIpIN The waste involved in this application consists of residual solids and water associated with the sewage collection system at Vermont Yankee. The plant's sewage systems are of the septic tank and disposal field type. The two systems servicing the majority of the plant's sanitary waste are identified as (I).main septic system and (2) the south sewage disposal system.The main septic system (design flow capacity 4,950 gallons/day) consists of a wastewater lift station, septic tank, and dual alternating disposal fields located on the north side of the plant. This system services the main complex of buildings central to the plant and processes approximately 3,500 gallons of wastewater per day. The septic tank, shown in Figure (1), will typically contain 9,250 gallons of septage.The south sewage disposal system is a newly-installed (January 1989)pressurized mound system, which is used in lieu of the construction office building (COB) holding tank that had previously serviced the lavatory facilities on the south end of the plant. The new system is composed of a septic tank (5,700 gallon capacity, see Figure 2), pumping station, and pressurized mound disposal field. When dosing the field, a force main pressurizes the disposal field's piping system with the septic tank effluent, which distributes throughout the field. The south sewage disposal system has 1-1 66771(
Richard Emch -bvy 89,69.tif.__
Pae the design flow capacity to process 4,607 gallons of wastewater per day. The system is typically loaded at approximately 2,500 gallons per day during normal plant operations.
Figure (3) indicates diagramatically the flow of both potable and wastewater throughout Vermont Yankee.Both the main septic system and the south sewage disposal system's septic tanks collect waste from the plant's lavatories, showers, kitchens, and janitorial facilities outside the Radiological Control Area (RCA). No radioactivity is intentionally discharged to either of the septic systems.However, plant investigations into the source of low levels of contamination found in septic waste have identified that very small quantities of radioactive materials, which are below detection limits for radioactivity releases from the RCA, are carried out of the control area on individuals and accumulate in the septic waste collection tanks by way of floor wash water, showers, and hand washing. As a means of minimizing the transport of radioactive materials into the septic collection tanks, the primary source of the radioactivity (i.e., floor wash water) is now poured through a filter bag to remove suspended solids and dirt before the water is released into a janitorial sink.The majority of the radioactivity found in waste sludge has been associated with the main septic tank. Grab samples of sludge from the bottom of the COB and main septic tank were analyzed by gamma spectroscopy with the following results of plant-related radionuclides:
Activity Concentration I+1 Sigma (pCi/kg Wet)COB Sludge Cs-137 10.3 +/- 1.8 (June 8, .1988) Co-60 45.4 +/- 3.1 Main Tank Sludge Mn-54 39.3 +/- 4.3 (June 8, 1988) Co-60 853.0 +/- 12.0 Zn-65 52.7 +/- 8.2 Cs-134 13.0 + 2.2 Cs-137 120.7 +/- 5.2 1-2 6677R Richard Emch -bvy 89 59*'if.Page 81 The principle radionuclide is Cobalt-60, which accounts for 79% of the plant related activity in the septage samples. In comparison to in-plant smear samples taken for 10CFR61 waste characterizations, the septage sample from the main tank correlates very close with the distribution of radionuclides identified in-plant as shown below: Relative Isotopic Distributions In-Plant Smears Main Tank Slud~e Mn-54 3.6% 3.6%Co-60 81.5 79.1 Zn-65 3.8 4.9 Cs-134 0.4 1.2 Cs-137 10.3 11.2 Additional analyses of the main tank septage showed that the liquid portion of the collected sample did not contain any plant-related activation or fission products, and that essentially all of the activity in the waste was associated with the solid sludge fraction.
The average density of the collected sludge was found to be approximately equal to that of water, with a wet to dry ratio of 25.4 to 1.Both the liquid and solid fractions of the main tank septic waste were also analyzed for strontium with no detectable activity found. The liquid portion of the waste sample was also analyzed for tritium with no activity above the minimum detectable levels found. Appendix A to Attachment 2 contains the laboratory analysis reports of the samples taken from the COB and main septic tanks.Prior to identification of the plant-related radioactivity in septage waste, the COB holding tank was being pumped on the average of twice per week, with the sludge and waste liquid transported off-site primarily to the Brattleboro, Vermont, sewage treatment facility.
Waste from the main septic tank was being pumped and transported off-site for disposal on the average of twice per year.1-3 6677R R ichar'd Emch- -bv y-8-9 5-9.ti Pag ,e .0 With the replacement of the COB holding tank by the new south sewage disposal system, and the requested implementation of on-site land disposal of accumulated septic waste, the frequency of .collection tank pump-outs with land application of the waste is expected to be once per year. With the past pump-out frequency of the main tank being every six months, the accumulation of sludge at the bottom of the tank was well below its design capacity.During the 1988 sample collections, it was estimated that the sludge thickness was less than 1 foot of its 6-foot depth. However, for conservatism in the radiological evaluations, it is assumed that the sludge layer in the main septic tank and south disposal tank occupies 30% of their combined design volume, and that the frequency of pump-outs is semiannual as opposed to the expected annual cycle. Also, as noted above from laboratory analyses of the sludge layer taken from the bottom of the main tank, the average density of the tank contents is approximately equal to that of water, with a wet-to-dry ratio of 25.4 to I. Hence, the weight of solids (W So) being disposed of is estimated, for purposes of this bounding dose assessment, to be approximately:
WSo = 14,950 [gal] x 3,785.4 [cc/gal] x 10-3 (kg/cc]x 0.30 [solids fraction]
x (1/25.4) [dry/wet ratio]~ 700 [kg] per pump-out of both tanks or, 1,400 kg of dry solids per year.3.0 DISPOSAL METHOD Approval of this application will allow Vermont Yankee to dispose of septage by utilization of a technique of land spreading or surface injection in a manner consistent with all applicable state of Vermont health regulations regarding disposal of septic waste. Details of the chemical and biological controls necessary to satisfy state health code requirements are provided in Reference 5.The septage will be spread or surface injected on land areas owned by Vermont Yankee and situated within the plant's site boundary.
Transportation of the septage waste to the disposal areas will involve pumping from one of the septic waste collection tanks (i.e., main septic tank, COB holding tank, 1-4 6677R R hadmch -bvy 8 959 tif~ aeO new replacement COB septic tank, or from any other on-site septic waste collection point) into an enclosed truck-mounted tank. The enclosed tank truck is used to prevent spillage while in transit to the disposal areas. The septage will be transported to one of the two disposal sites designated for land application for septage from Vermont Yankee, and applied at a fixed rate based on either limitations imposed by the state of Vermont for heavy metals or organic content of the waste, or on the radioactivity content such that projected maximum individual doses will not exceed established dose objectives.
3.1 Seotic Was_ Disposal Procedure Gamma isotopic analysis of septic waste shall be made prior to each disposal by obtaining a representative sample from each tank prior to pump-out.
At least two septic waste samples will be collected from each tank to be pumped by taking a volumetric column of sludge and waste water which allows for analysis of the solid's distribution and content from top to bottom of each tank. The weight percent of solid content of the collected waste will be determined and applied to the gamma isotopic analysis in order to estimate the total radioactivity content of each tank to be pumped and spread on designated disposal fields.These gamma isotopic analyses of the representative samples will be performed at the environmental Technical Specification lower limit of detection (LLD) requirements for liquids (see Technical Specification Table 4.9.3) in order to document the estimation of radiological impact from septage disposal.The radionuclide concentrations and total radioactivity identified in the septage will be compared to the concentration and total curie limits established herein prior to disposal.
The methodology and limits associated with determining compliance with the disposal dose and activity criteria are described in Attachment
- 2. If the concentration and total activity limits are met, compliance with the dose assessment criteria will have been demonstrated since the radiological analysis (Section 4.5 and Attachment
- 2) was based on evaluating the exposure to a maximally exposed individual and inadvertent intruder after the accumulation of twenty years of periodic semiannual 1-5 6677R Richard E mch -.bvy89 59.tif Page' 41...........
spreading of the septic waste on a single (2 acre) plot within one of the designated disposal areas. If the activity limit per disposal area is projected to be exceeded, the appropriate exposure pathways as described in Section 4.5 will be evaluated prior to each additional application, or a separate plot within the designated disposal area will be utilized.Annually, for years in which disposal occurs, the potential dose impact from disposal operations conducted during the year, including the impact from previous years, will be performed and results reported in the plant's Semiannual Radioactive Effluent Release Report which is filed after January 1. All exposures will be assessed utilizing the methodology described in Attachment 2.The established dose criteria requires that all applications of septage within the approved designated disposal areas shall be limited to ensure the dose to a maximally-exposed individual be maintained less than 1 mrem/year to the whole body and any organ, and the dose to the inadvertent intruder be maintained less than 5 mrem/year.
The total activity based on the measured radionuclide distribution for any single disposal plot is not expected to exceed the following:
Maximum Accumulated Radioactivity Allowed Per Acre Isotope Qilim [pCi]Mn-54 1.4 Co-60 120.0 Zn-65 1.4 Cs-134 0.7 Cs-137 46.5 If any of the above radionuclides are projected to exceed the indicated activity values, then dose calculations will be performed prior to spreading, in accordance with the methods detailed in Section 4.2.2 of Attachment 2, to make the determination that the dose limit criteria will not be exceeded.1-6 6677R Richard Emc'h"- bvy 89 69.1if--.....
Page 12;The concentration of radionuclides in any tank of septic waste to be disposed of will also be limited to a combined Maximum Permissible Concentration of Water (MPC) (as listed in 1OCFR, Part 20, Appendix B, Table II, Column 2) ratio of less than or equal to 0.1.For radiological control, each application of septage will be applied on the designated land area by approved plant procedure which adheres to the following assumptions which were used in developing the dose impact: o During surface spreading or injection, the septage, and any precipitation falling onto or flowing onto the disposal field, shall not overflow the perimeter of the designated area.o Septage shall not be surface spread or injected into the top 6-inch soil layer within 300 feet from any drinking water well supply.o Septage shall not be surface spread closer than 300 feet from the nearest dwelling or public building (or within 100 feet if injected into the top 6-inch surface layer)." Septage shall not be surface spread closer than 50 feet (or within 25 feet if injected into the top 6-inch surface layer) from any roads or site boundary adjacent to land areas." Septage shall not be surface spread within 100 feet (or within 50 feet if injected into the top 6-inch surface layer) of any surface water (rivers, streams, drainage ditches).o Low areas of the approved fields, subject to seasonally high groundwater levels, are excluded from the septage application.
In addition to the radiological controls to limit the total accumulation of radioactive materials released by septic waste spreading, state of Vermont health code requirements will be followed to ensure the protection of the public and environment from chemical and biological hazards. The application rate and acreage will be determined prior to each 1-7 6677R Richarýd Em'ch -bvy 89 59.tifPae1
-- .... .. .....~~~ ~~~. ........ ..... .. ...... ...........................
....... ..... ..... ....... ............
disposal operation.
This will vary with the chemical composition of the septage, the percent solids, and the radioactive concentrations.
3.2 Administrative Procedures Complete records of each disposal will be maintained.
These records will include the concentration of radionuclides in the septage, the total volume of septic waste disposed, the total activity in each batch as well as total accumulated on the disposal plot at time of spreading, the plot on which the septage was applied, and the results of any dose calculations required.The annual disposal of septage on each of the approved plot areas will be limited to within the established dose, activity, and concentration criteria noted above, in addition to limitations dictated by chemical and biological conditions.
Dose guidelines, and concentration and activity limits, will be maintained within the appropriate values as detailed in Attachment 2.Any farmer using land which has been used for the disposal of septic waste will be notified of any applicable restrictions placed on the site due to the land spreading or injection of waste.4.0 EVALUATION OF ENVIRONMENTAL IMPACT 4.1 Site Characte-ristics 4.1.1 5:ite Topography The proposed disposal sites consist of two fields located on the Vermont Yankee Nuclear Power Plant site, which is located on the west bank of the Connecticut River in southwestern Vermont at latitude 42 degrees, 47 minutes north and longitude 72 degrees 31 minutes west. Both fields are on plant property within the site boundary and surrounded by a chain link fence.i-8 6677R I Richard Emch -bvy 89 59.tif Pa'e 14 Site A contains an approximate eight-acre parcel of usable land centered approximately 2,200 feet northwest of the Reactor Building.
Site B contains about two acres and is centered approximately 1,700 feet south of the Reactor Building.
The usable acreage of both the north and south disposal fields is restricted to those areas which have no slopes greater than five percent to limit surface runoff. A radiological assessment based on the 1988 measured radioactivity concentrations in sludge has determined that a single two-acre plot would be sufficient for the routine disposal of septage for twenty years without exceeding the dose criteria to maximum exposed individual or inadvertent intruder.
As a result, the eight-acre field to the northwest could be divided into four disposal plots, with the two-acre site at the south end of the plant site, providing a fifth plot. A portion of the United States Geological Survey topographic map (Brattleboro quadrangle), showing the plant site, is presented in the Final Safety Analysis Report (FSAR) as Figure 2.5-1. A plan map showing the plant site and the disposal sites is given on Figure 4.The sites are located along a glacial terrace on the west side of the Connecticut River. This terrace extends about 3,000 feet west rising gently and then more abruptly to a higher terrace and then to dissected uplands.Distance to the east from the disposal sites to the river is at least 100 feet if septage is disposed of by surface spreading within the designated areas, or 50 feet if septage is injected directly into the soil.Relief of the proposed disposal sites is low, with elevation ranging between 250 feet and 265 feet (msl). Mean water surface elevation of the adjacent river is about 220 feet.The topographic character of the site and surrounding area is compatible with this use. The spreading of septage at these locations will have no effect on the topography of the area.1-9 6677R Richar Emch -bvy 89 59.tifPae1 4.1.2 Site Geology Profiles of site exploratory borings are shown in the FSAR in Figures 2.5-8 through 2.5-11. Current site characteristics as determined from a recent detailed site investigation can be found in Reference 5.Composition of surfacial materials is compatible with the proposed use of the site for septic waste disposal.4.2 A haracteristics 4.2.1 Meteorologv The site area experiences a continental-type climate with some modification due to the marine climate which prevails at the Atlantic seacoast to the east. Annual precipitation averages 43 inches and is fairly evenly distributed in each month of the year.Potential impacts on septic waste disposal include occasional harsh weather: ice storms, severe thunderstorms, heavy rains due to hurricanes, the possibility of a tornado, and annual snowfall of from 30 to 118 inches per year. In addition, frozen ground can occur for up to 4 months of the year.Septage spreading will be managed by written procedure such that material which is spread or a mix of that material with precipitation will not overflow the perimeter of the disposal site.Additional information on meteorology of the site can be found in Section 2.3 of the Final Safety Analysis Report.4.2.2 ydrolgy Hydrology of the site and local area is tied closely to flow in the adjacent Connecticut River. River flow is controlled by a series of hydroelectric and flood-control dams including the Vernon Dam which is about 3,500 feet downstream of the site.1-10 6677R
ý rich -byY89 c ,ii ii g tif Page 1 All local streams drain to the Connecticut River and the site is in the direct path of natural groundwater flow from the local watershed easterly toward the river. Site groundwater level is influenced by both precipitation and changes in the level of ponding of the Connecticut River behind the Vernon Dam due to natural flow or dam operation.
Flood flows on the Connecticut are controlled by numerous dams including five upstream of the site. Elevation of the 100-year flood is about 228 ft (mel); and, thus, well below the elevation of the proposed site which ranges from about 250 to 265 feet (mal). The 100-year flood level is based on information presented in References (1) and (2).Septage disposal by means of land spreading on the proposed site will have no adverse impact on area hydrology.
Further information about site hydrology is in Section 2.4 of the FSAR.4.3 Water Usage 4.3. 1 urfaeWteM r The adjacent Connecticut River is used for hydroelectric power, for cooling water for the Vermont Yankee plant, as well as for a variety of recreational purposes such as fishing and boating. The Connecticut River is not used as a potable water supply within 50 miles downstream of the plant.Locally, water from natural springs are used for domestic and farm purposes.
FSAR Table 2.4.5 and Figure 2.4-2 show springs used within a 1-mile radius of the site. FSAR Table 2.4.4 and Figure 2.4-1 show water supplies with surface water sources which are within a ten-mile radius of the site.There will be no impact on surface water usage or quality as a result of septage disposal due to the required separation distances between surface waters and the disposal plots.6677R 4.3.2 Groundwater Based on a review of groundwater measurements in various site borings presented in the FSAR and References 3 and 5, an upper estimate of groundwater levels at the plant is about 240 feet. Considering the proximity of the Connecticut River and Vernon Pond, with a mean water surface elevation of 220 feet, this estimate for the groundwater level appears to be reasonable.
Given the topography of the proposed disposal sites, it is highly unlikely that the groundwater level will be within 3 feet of the disposal area surface elevation.
Prior to each application of septic waste to a disposal plot, the groundwater level in nearby test wells will be determined and no application will be allowed if the groundwater level in the vicinity of the disposal plot is found to be less than 3 feet.Groundwater provides potable water for public wells as shown in FSAR Table 2.4.5 and Figure 2.4-1. Groundwater flow in the vicinity of the proposed disposal sites is towards the Connecticut River. There are no drinking-water wells located between the site and the river. Therefore, it is highly unlikely that any drinking water wells could be affected by septage disposal.
FSAR Figure 2.4-2 and Table 2.4-5 present information on private wells near the plant.The Vermont Yankee on-site wells provide water for plant use. This supply is routinely monitored for radioactive contamination.
To quantify the impact of septage disposal'on the Connecticut River, a conservative groundwater/radionuclide travel time analysis was performed.
For an assumed average travel distance of 200 feet from the disposal site to the river, a groundwater travel time of 408 days was estimated from Darcy's Law.2 This estimate is based on a permeability for the glacial till of 10 gpd/ft a hydraulic gradient of 0.11 ft/ft, and a soil porosity of 0.3. This analysis conservatively assumed that the septage placed on the ground was immediately available to the groundwater.
In practice, a minimum of 3 feet separation between groundwater and the surface will be required at time of application of the septic waste.1-12 6677R I Richard Emch -bvy'89 59.tif'Pag 66118 1 Due to ionic adsorption of the radionuclides on solid particles in the groundwater flow regime, most radionuclides travel at only a small fraction of the groundwater velocity.
For the radionuclides present in the sludge, retardation coefficients were developed from NUREG/CR-3130 (Reference 4).Retardation coefficients for Co-60, Cs-137, and Cs-134 were directly obtained from NUREG/CR-3130.
The coefficients for Zn-65 and Mn-54 were conservatively estimated using NUREG/CR-3130 as a guide. The radionuclides, their half-lives, retardation coefficients, and their travel time to the river are summarized in Table I.TABLE I Radionuclide Travel Times Retardation Travel Time Radionuclide HafLf Coefficient to River Co-60 5.3 years 860 961 years Cs-137 30.2 years 173 193 years.Cs-134 2.1 years 173 193 years Zn-65 244 days 3 1,224 days Mn-54 312 days 3 1,224 days The radiological impact on the river for the radionuclides reaching the river under this conservative analysis is discussed in Attachment
- 2. Water usage of the Connecticut River downstream from the disposal area is limited to drinking water for dairy cows, irrigation of vegetable crops, and irrigation of cow and cattle fodder.Based on the assessments noted above, it is concluded that groundwater sources will not be adversely impacted as a result of septage disposal on the proposed site.4.4 Lad s Both the eight-acre and two-acre sites proposed for the disposal areas are currently part of the Vermont Yankee Nuclear Power Plant Site inside the plant's site boundary which is enclosed by a chain link fence. It is 1-13 6677R I Richard Emch -bvy 89 59.tif Page 19[I undeveloped except for transmission line structures which traverse a portion of the northern disposal area. Development potential is under the control of Vermont Yankee. At present, the eight-acre site on the north end of the plant property is used by a local farmer for the growing of feed hay for use with his dairy herd. No curtailment of this activity as a result of the low levels of radioactivity in septage will be necessary.
Utilization of the proposed sites for septic waste disposal will result in no impact on adjacent land or properties because of the separation of the disposal plots from off-site properties, the general movement of groundwater toward the river and away from adjacent land areas, and the very low levels of radioactive materials contained in the waste. Administrative controls on spreading and the monitoring of disposal area conditions will provide added assurance that this proposed practice will not impact adjacent properties.
- 4. 5 etQQiirac In addition to state of Vermont limits imposed on septage spreading, based on nutrient and heavy metal content, the amount of septage applied on each of the proposed disposal plots will also be procedurally controlled to insure doses are maintained within the stated limits. These limits are based on NRC Nuclear Reactor Regulation (NRR) staff proposed guidance (described in AIF/NESP-037, August 1986). The proposed dose criteria require that the maximally exposed member of the general public receive a dose less than I mrem/year to the whole body or any organ due to the disposal material, and less than 5 mrem/year to an inadvertent intruder.To assess the doses received by the maximally-exposed individual and the inadvertent intruder, six potential pathways have been identified.
These include: (a) Standing on contaminated ground, (b) Inhalation of resuspended radioactivity, 1-14 6677R I-~ichard Ernch -bvy 89 59.tit PaQe2O Richard Emch -,bvy 89 59.tif Paqe20 I Page -201 (c) Ingestion of leafy vegetables, (d) Ingestion of stored vegetables, (f) Ingestion of meat, and (g) Ingestion of milk.The liquid pathway was also evaluated and determined to be insignificant.
Both the maximum individual and inadvertent intruder are assumed to be exposed to these pathways with difference between the two related to the occupancy time. The basic assumptions used in the radiological analyses include: (a) Exposure to the ground contamination and to resuspended radioactivity is for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> per year during Vermont Yankee active control of the disposal sites, and continuous thereafter.
The 104-hour interval being representative of a farmer's time on a plot of land (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week for 6 months).(b) The septic tanks are emptied every 6 months. (Expected practice is to pump septic tanks once per year.)(c) The tank radioactivity remains constant at the currently determined level. To account for the uncertainty associated with the counting statistics, the measured activity concentrations listed in Section 2 were increased by 3 sigmas. That is, the activity concentrations employed in dose assessment and the total radioactivity content per pump-out (at 700 kg of solids per batch)are as follows: 1-15 6677R Richard _Emch -bv'y 89 59 tifPge2 Upper-Bound Activity Upper-Bound Activity Concentration
[pCilk2 dryl Content [Ci/tankful)
Mn-54 1,348 9.436E-07 Co-60 23,060 1.614E-05 Zn-65 1,620 1.134E-06 Cs-134 322 2.254E-07 Cs-137 4,100 2.870E-06 (d) The radiation source corresponds to the accumulation of radioactive material on a single plot (two-acre) within the proposed disposal sites over a period of 20 years (40 applications at 6-month intervals). (In actuality, the proposed sites will accommodate more than one disposal plot, and, in practice, more than one plot will most probably be used with an application frequency of once per year.)(e) For the analysis of the radiological impact during Vermont Yankee active control of the disposal sites, all dispersed radioactive material remains on the surface and forms a source of unshielded radiation. (In practice, the septic waste will be either surface spread or directly injected within the top 6 inches of the disposal plot, in which case, the radioactive material will be mixed with the soil. This, in effect, would reduce the ground plane source of exposure by a factor of about four due to self-shielding.)(f) No radioactive material is dispersed directly on crops for human or animal consumption, crop contamination being only through root uptake.(g) The deposition on crops of resuspended radioactivity is insignificantly small.1-16 6677R
ýRiahwdLmah
-bvy 89o9.i Pag 22-(h) Pathway data and usage factors-used in the analysis are the same as those used in the plant's ODCM assessment of the off-site radiological impact from routine releases,with the exception that the fraction of stored vegetables grown on the disposal plots was conservatively increased from 0.76 to 1.0 (at present no vegetable crops for direct human consumption are grown on any of the proposed disposal plots).(1) It is conservatively assumed that Vermont Yankee relinquishes control of the disposal sites after the fortieth pump-out (i.e., the above source term applies also for the inadvertent intruder).(j) For the analysis of the impact after Vermont Yankee control of the sites is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inches of soil; but, nonetheless, undergoes resuspension at the same rate as surface contamination.
From radiological impact assessments associated with the disposal of septage on different plot sizes (Attachment 2), it was determined that a single two-acre plot within the disposal sites would accommodate the 1 mrem/year prescribed dose to the critical organ of the maximally exposed individual for a period of up to 20 years, as well as the 5 mrem/year prescribed dose to the inadvertent intruder after control is assumed to be relinquished.
The calculated potential radiation exposures following the spreading of 40 combined (main septic system and south disposal system)tankfuls (at six-month intervals) on a single two-acre plot are as follows:_Qolnltrl of Disposal Sites Radiation Exposure Individual/Organ Controlled by VYNPS 0.1 mrem/yr Child/Whole Body (Maximum Exposed Individual) 0.2 mrem/yr Maximum Child/Liver Uncontrolled 1.3 mrem/yr Adult/Whole Body (Inadvertent Intruder) 3.9 mrem/yr Maximum Teenager/Lung 1-17 6677R
[Richard Emch " bvY 89_59.tif 23 The individual pathway contributions to the total dose at the end of the 20-year accumulation of waste deposited on a single two-acre plot are as listed below: l'athway-Dependent Critical Organn.Doje.
Ground Irradiation Inhalation Stored Vegetables Leafy Vegetable Milk Ingestion Meat Ingestion TOTAL Maximally Exposed Individual/Organ (Child/Liver)(mremlyear) 0.0576 0.00122 0.0913 0.00467 0.0421 0.90049 0.1994 Inadvertent Intruder Critical Individual/Organ (Teenager/Lung)(mrem/year) 1.16 2.74 0.00601 0.00040 0.00229.090001 3.909 In addition, an isotopic breakdown of the critical organ dose results listed above is shown in the following table: Isotopic Breakdown of MaximuwvRa
' ti n xyosurP Radioactivity Istve 1A~i/2 Acres]Description During Vermont Yankee control of the disposal sites.Maximally Exposed Individual/Organ:
Child/Liver After Vermont Yankee control of sites is relinquished.
Inadvertent Intruder Critical Individual/
Organ: Teenager/Lung Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL 2.831 235.3 2.801 1.457 92.59 2.831 235.3 2.801 1.457 92.59 Exposure fmrem/yr]0.000436 0.0559 0.0230 0.00231 0.118 0.199 0.0144 3.76 0.00983 0.000505 3.91 1-18 6677R Richard Emch -bvy 89 59.-tifPae2 Of interest are also derived dose conversion factors which provide a means of ensuring septage disposal operations within the prescribed radiological guidelines.
The critical-organ (worst-case) all-pathway values per acre are as follows: All-Pathway Critical-Orsan Dose Conversion Factors During Vermont Yankee Control of Disposal Sites Exposure j .Individual/Organ
[mrem/yr-MCi/acre]
Mn-54 Adult/GE-LLI 3.74E-4 Co-60 Teenager/Lung 7.14E-4 Zn-65 Child/Liver 1.64E-2 Cs-134 Child/Liver 3.18E-3 Cs-137 Child/Bone 2.66E-3 The calculational methodology and details of the radiological assessment and proposed operational controls on total activity and concentration of waste to be disposed are presented in Attachment 2.5.0 &ADIATION PROTECTION The disposal operation will follow the applicable Vermont Yankee procedures to maintain doses as low as reasonably achievable and within the specified dose and release concentration criteria.1-19 6677R Richard Em~c'h -b'vy 89 59.tif-Pae2 I R ic ha rd E ~ c h ........59 .t........................
- i. Flood Insurance Study, Vernon, Vermont, Windham County, FEMA, Community No. 500137, July 25, 1980.2. Flood Insurance Study, Town of Hinsdale, New Hampshire, Cheshire County, FEMA, Community No. 330022, October 15, 1980.3. Vermont Yankee Well Development Evaluation by Wagner, Heindel, and Noyes, Inc. July 10, 1986.4. NUREG/CR-3130, Influence of Leach Rate and Other Parameters on Groundwater Migration, by Dames & Moore, February 1983.5. Vermont Yankee Nuclear Power Corporation On-Site Septage Disposal Plan, by Wagner, Heindel, and Noyes, Incorporated, June 1989.1-20 6677R Richard E rnch-bvy8959.tif Page 26 FIGURE I MAIN SEPTIC TANK£NLAR(4.D PLAN1 I". to'E71: QK=41 LA-tL&- -f~4 b1ODIFIC4rIO'45 70 ~Ex1,5ris5 W-Pr/C T4Nf AND CJ1AAma&R EC. LWO .~SIO vO F1EAIsc umA4 EmCrIL m (0 FIQURE 2 SOUTH DISPOSAL SYSTEM SEPTIC '2ANh-v~u~e~R ~OV7 a ?V c.¶'W~Si.J Z4 OF C AP 10 5rt TýWV1 GO7 ~I4RCC OIA sEOcTC-N Ea-F
-_ --~ -~ --~FIGURE 3 POTABLE AND WASTE WATER FLOW PW1 7 & 5 TO RAO WASTE CONSTRUCTION OFFICE)BUILDING WELL LEGEND: 0 POTABIX WA~tR MMTE SWASTE MOABLE WATER CD T\.)
0).3 (0 0-i (0ý-3EPTTC.
WASTE DlSP3-SAL AREAq Richard Emoi-. bvy89 59.tif Page 30 IALE OF CONTENTS
1.0 INTRODUCTION
.....................................................
2-1 2.0 SOURCE TERM AND OTHER BASIC DATA .................................
2-3 2.1 Septic Tank Specifics
......................................
2-3 2.2 Measured and Adjusted Septic Waste Radioactivities
.........
2-3 2.3 Limiting Concentration Guidelines
..........................
2-4 2.4 Disposal Sites .............................................
2-6 2.5 Radioactivity at Disposal Plot After 20 Years ..............
2-6 2.6 Land-Spreading, Resuspension and Occupancy Factors .........
2-7 2.7 Site-Specific Pathway Data and Usage Factors ...............
2-9 2.8 Liquid Pathways ............................................
2-12 3.0 RADIOLOGICAL ASSESSMENT..........................................
2-15 3.1 Dose Reduction as a Result of Plowing the Radioactive Material into the Soil .....................................
2-15 3.2 Data Manipulation for Use with ATMODOS .....................
2-17 3.2.1 Radioactivity Release Rate .........................
2-17 3.2.2 Atmospheric Dispersion
.............................
2-18 3.2.3 Occupancy Factors ..................................
2-19 3.3 Land-Spreading Exposure Pathways ...........................
2-20 3.3.1 Impact During Vermont Yankee Control of the Disposal Sites .....................................
2-24 3.3.2 Radiological Impact After Termination of Vermont Yankee Control of the Disposal Sites ...............
2-26 3.3.3 Isotopic Dose Conversion Factors ...................
2-27 4.0 RECOMMENDED PROCEDURAL CONTROLS TO ENSURE COMPLIANCE WITH RADIOLOGICAL LIMITS ..............................................
2-29 4.1 Total Radioactivity Dispersed per Disposal Plot ............
2-29 4.2 Operational Limits .........................................
2-30 4.2.1 Maximum Activity Concentrations
....................
2-30 4.2.2 Potential Radiation Exposures
......................
2-31
5.0 REFERENCES
.......................................................
2-35-ii-6680R Richard Emch -bvyv_ 9tf ae3[~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~~~~~~~.........
Iihr ..........
....., ....................................
TABLE OF CONTENTS (Continued)
APPENDIX A -LABORATORY ANALYSES OF SEPTIC WASTE .......................
A-I APPENDIX B -COMPUTER CODE OUTPUTS .....................................
B-I B.I ALLEGRA -Gamma Ray Spectra ................................
B.I-I B.2 DIDOS-V -Dose Reduction as a Result of Plowing ............
B.2-1 B.3 AThODOS -Radiological Impact During Vermont Yankee Control of the Disposal Sites ......................................
B.3-1 B.3.1 Impact due to Mn-54 in the Septage .................
B.3.1-1 B.3.2 Impact due to Co-60 in the Septage .................
B.3.2-1 B.3.3 Impact due to Zn-65 in the Septage .................
B.3.3-1 B.3.4 Impact due to Cs-134 in the Septage ................
B.3.4-1 B.3.5 Impact due to Cs-137 in the Septage ................
B.3.5-I B.3.6 Impact due to All Nuclides in the Septage ..........
B.3.6-I B.4 AThODOS -Radiological Impact After Termination of Vermont Yankee Control of the Disposal Sites (All Nuclides)
.............................................
B.4-1 B.5 ATMODOS -Unplowed-Land Dose Conversion Factors for Radiological Impact Assessment
.........................
B.5-1 B.5.1 Impact due to I uCi of Mn-54 .......................
B.5.1-1 B.5.2 Impact due to 1 uCi of Co-60 .......................
B.5.2-I B.5.3 Impact due to 1 uCi of Zn-65 .......................
B.5.3-1 B.5.4 Impact due to 1 uCi of Cs-134 ..........................
B.5.4-I B.5.5 Impact due to I uCi of Cs-137 ......................
B.5.5-i-iii-6680R Richard Emch -bvy 89 59.tif ......ATTACHMENT 2 VERMONT YANKEE NUCLEAR POWER PLANT Radiological Assessment of on-Site Disposal of Septic Waste aad Proposed Procedural Controls to Ensure Compliance With Radiological Limits 1.0 jTR~ODUCTIO This calculation is in support of Vermont Yankee's application to the Nuclear Regulatory Commission for the on-site disposal of slightly radioactive septic waste in accordance with the provisions of lOCFR20.302 for very-low-level waste disposal.
Specifically, the main purposes of the calculation were as follows: (a) Determination of an optimal plot size for septage disposal (based on measured 1988 radioactivity concentrations in septic waste)which would accommodate both the radiological guidelines and the needed flexibilities for a smooth operation of the disposal program.(b) Preparation of procedural controls to ensure compliance with the radiological guidelines.
Guidance for obtaining regulatory approval to dispose of very-low-level waste is presented in AIF/NESP-037 (Reference 6). According to this reference, the NRR staff personnel have proposed a number of draft dose guidelines regarding the impact of low-level waste disposal on the public health and safety for use in the preparation of IOCFR20.302(a) requests.
Of these, the following two are pertinent to the present calculation: (a) Doses to the total body and any body organ of a maximally exposed individual (a member of the general public or a worker who is not 2-1 6680R Richard Emc h bvy 60 gt'if ae3.............................................
classified as a radiation worker) from the probable pathways of exposure to the disposed material should be less than 1 mrem/yr.(b) Doses to the total body and any body organ of an inadvertent intruder, from the probable pathways of exposure, should be less than 5 mrem/yr.In either case, consideration should be given to all possible exposure pathways, while allowing for land-usage restrictions which may be in effect.It is on these guidelines that the optimum disposal plot size was selected and the procedural controls prepared.In addition to the dose guidelines listed above, the procedural controls recommended in this calculation also include MPC checks on the septage to be disposed.
As stated in the above AIF report, the total activity concentration in the waste is expected to be below 50 pCi/gram (Reference (6), Page 4-1). This guideline is approximately equivalent to the MPC limits specified in 10CFR20, Appendix B, Table II, Column 2, for the release of radioactive material to unrestricted areas, and to also be approximately 50 times higher than the activities measured in the Vermont Yankee septic waste in 1988. A lower MPC ratio appears to be more appropriate for better control. As a result, and in addition to the prescribed dose limits, a combined MPC ratio of less than or equal to 0.1 was also included in the procedures to regulate the disposal of septic waste. With respect to the measured septage radioactivity, spectroscopic analyses of samples taken in 1988 from the Vermont Yankee main septic tank showed that the liquid portion of the collected samples did not contain any activation or fission products, and that the following plant-related radionuclides were found in the solids: Activity Concentration I o+/-1 Sigma [pCi/k& dryl Mn 54 1,126 +/- 74 Co-60 22,400 +/- 220 Zn-65 1,200 +/- 140 Cs-134 166 +/- 52 Cs-137 3,824 +/- 92 2-2 6680R 0 , " A, it"", -k' , , , " -I i.Xý I I I ý 11 -11 I '."..... ' ....." I v .. .. ..J ....P ag e34. I 2.0 SOURCE TERNM-D OTHER BASIC PATA 2.1 Septic Tank Specifics The effective capacity of the main septic tank, when filled to its maximum depth of 6 feet, is approximately 9,250 gallons. The south sewage disposal system is newly installed (January 1989) and replaces the construction office building (COB) holding tank that had previously serviced the lavatory facilities on the south end of the plant. This new system contains a 5,700 gallon septic tank. The total design capacity of both main system and new south system septic tanks is approximately 14,950 gallons.Prior to 1988, the main tank was usually emptied every 6 months. Due to this high pump-out frequency, the accumulation of sludge at the bottom is well below the design capacity of the tank. During the 1988 sample collections, it was estimated that the sludge thickness was less than 1 foot.For conservatism in this radiological evaluation, it was assumed that the sludge occupies 30% of the design liquid volume of both the main septic tank and new south systems tank. Also, from laboratory analyses of the septic waste, the average density of the tank contents is approximately equal to that of water, and the wet to dry ratio of the sludge is 25.4 to I. Hence, the weight of solids (W Sol) being disposed of is estimated for purposes of bounding dose analyses to be approximately:
Wsol = 14,950 gal x 3,785.4 cc/gal x 10-3 kg/cc x 0.30 solids fraction x (1/25.4) dry/wet ratio 700 kg 2.2 Measured andAdjusted Septic Waste Radioactivitles Gamna spectroscopic analyses of septage samples from Vermont Yankee were carried out at the Yankee Environmental Laboratory in Westborough, Massachusetts (see Appendix A). For the main septic tank, no activation or fission products were found in the liquid portion of the collected samples.In the dry solids, on the other hand, the following man-made radionuclides were found to be statistically positive at the 99.9 percent confidence level: 2-3 6680R Richard Emch-,bvy89 59.tf Page.....35
-- --- ...... .......... ..................................
Mn-547 Co-60 Zn-65 Cs-134 Cs-137 Activity Concentration
+/-l Sigma (pCi/kg Dry)1126 +/- 74 22400 +/- 220 1200 +/- 140 166 +/- 52 3824 +/- 92 To account for the uncertainty associated with the counting statistics, the measured activity concentrations listed above were increased by 3 sigmas.That is, the activity concentrations employed in this calculation, and the total radioactivity content per combined tankful of both south and main septic tanks) (at approximately 700 kg of solids per batch, from Section 2.1 of this calculation) are as follows: Upper-Bound Activity Concentration (oCi/kR dry)Mn-54 Co-60 Zn-65 Cs-134 Cs-137 1,348 23,060 1,620 322 4,100 Upper-Bound Activity Content (Ci/Batch) 9.436E-07 1.614E-05 1.134E-06 2.254E-07 2.870E-06 2.3 jaiiinting Concentration Guidelines The AIF Report (AIF/NESP-037) provided draft guidance on total activity concentration in waste stating that it is expected to be below 50 pCi/gram.As shown below, this guideline appears to be approximately equivalent to the MPC limits specified in 1OCFR20, Appendix B, Table II, Column 2, for the release of radioactive material to unrestricted areas.For the major radionuclides identified in the Vermont Yankee septic waste, the individual MPC limits are as follows: 2-4 6680R I Rýqhýrq Emch -byy 89 59.tif Pag~e 36 1 I .... .. ...Ric h a rd. .... .........
..... ..... .... ... .... ... .. ... .. ..... ..... ..... ..... ..... ...b.. .. .....y.. ..... ...8 9. ...... ... ... .........
...t P a e 3 Maximum Permissible Concentrations in Water Soluble Insoluble Istp ui/m uCilml)Mn-54 Co-60 Zn-65 Cs-134 Cs-137 1 .OE-4 5.OE-5 1.OE-4 9.OE-6 2.OE-5 I.OE-4 3. OE-5 2. OE-4 4. OE-5 4.OE-5 For a mix of radionuclides, 10CFR20 specifies that, in addition to the above individual limits, the following condition must also be met: E (Ci/MPC) Si.0 where: C. is the measured concentration for Isotope i, and the summation is 1 over all radionuclides in the mix.As indicated in Section 2.2, the 1988 spectroscopic analyses of Vermont Yankee septage samples showed that there was no radioactivity in the septic water samples. That is, the limits which are currently applicable are those listed above for insoluble compounds.
Using the activity.data from Section 2.2, along with the main septic tank volume of 9,250 gallons, the current upper-bound activities and MPC ratios are approximately:
Upper-Bound Activity IContent (Ci/tankful)
Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL 9.44E-07 1.61E-05 1. 13E-06 2.25E-07 287E-06 2. 13E-05 Upper-Bound Activity Concentration (uCi/ml)2.67E-08 4.57E-07 3.21E-08 6.38E-09 6.03E-07 MPCRatio 2.6 7E-04 1.52E-02 1. 60E-04 1.59E-04 2,0~3E0 1. 78E-02 2-5 6680R Richard Emch -bvy 89 59.tif Page 37.............
It is seen that the overall MPC ratio is approximately 1.8 % of the regulatory limit, and that the total concentration is 1.2 % of the 50 pCi/g guideline.
Thus, the sludge activity concentration can be at least 50 times higher without exceeding either limit. Obviously, if the MPC ratio of 1 or the 50 pCi/g guideline are not revised, the on-site disposal of septic waste will be regulated solely by the prescribed radiation exposure limits. For better control, therefore, it is hereby proposed that, in addition to the prescribed dose limits, a combined MPC ratio of less than or equal to 0.1 be also included in the procedures to regulate the disposal of septage. Refer to Section 4 for more details.2.4 Dispoa~l-Sit-e-There are two sites on Vermont Yankee site property which are currently designated for on-site septic waste disposal, as follows: (a) Site A, a 8-acre site approximately 2,200 feet northwest of the Reactor Building.(b) Site B, a 2-acre site approximately 1,700 feet south of the Reactor Building.Both sites are within the plant's site boundary and surrounded by a chain link fence, and under direct control of Vermont Yankee for all access.2.5 Radioactivity at Disposal Plot After 20 Years It is clear that, due to the longevity of the two primary isotopes identified in the sludge (Co-60 and Cs-137), the amount of radioactivity at the disposal plot will be increasing with each disposal application.
However, since the content of radioactivity in septic waste is very low, and since it is neither practical nor necessary to carry out a new dose analysis prior to each disposal, the approach employed in this calculation was to assess the potential radiological impact at approximately the end of plant life. That is, the radiation source was assumed to correspond to the accumulation of 2-6 6680R I Richard Emch -bvy 89 59.tif Paae 38 I L radioactive material on a given plot within the proposed disposal sites over a period of 20 years (40 applications at an assumed 6-month interval).
Analytically, if Q is the amount of radioactivity per batch for a given isotope, then the total accumulated radioactivity Qe at the disposal plot after 40 applications is given by: Qe = Qo (1 + E + E 2 + E 3 + E 4 + .... +E3) (2.1)= Qo (1 -E 3 9 )l -E) (2.2)where: E = exp(-Xtt)
(2.3)= is the decay constant for the selected isotope (1/year)and At = time interval between applications
= 0.5 year For the isotopes of interest, the results are as follows: Qo Qe 1"t2_& Half Life lr (Cibatch)
QeLQo Mn-54 312.2 d 0.8109 9.436E-7 3.000 2.831E-06 Co-60 5.272 y 0.1315 1.614E-5 14.58 2.353E-04 Zn-65 243.8 d 1.038 1.134E-6 2.470 2.801E-06 Cs-134 2.065 y 0.3357 2.254E-7 6.464 1.457E-06 Cs-137 30.17 y 0.02297 2.870E-6 32.26 9.259E-05 2.6 Land-Spreading.
Resuspension and Occupancy Factors As pointed out above, even though the proposed sites can accommodate more than one disposal plot, only a single disposal plot will be assumed in assessing the potential radiological impact. If this plot has a surface area 2-7 6680R Rihr rch -bvy 8959.tif .Page39 of N acres, then the surface area deposition S (Ci/m 2) following 40 disposal applications will be equal to: Se = Qe (Ci)/(N (acres) x 4046.9 (m 2/acre)) (2.4)The denominator of this equation is equivalent to the (D/Q) deposition factor normally employed in the impact assessment of deposited radionuclides.
That is: (D/Q) = 1/(N (acres) x 4046.9 (m 2/acre))= 2.471E-04/N (m- ) (2.5)Following the application of septage on the disposal plot, some of the radioactivity may become airborne as a result of resuspension effects. The model used to estimate the radionuclide concentration in air above the disposal plot was taken from WASH-1400, Appendix VI (Reference 7). According to that model, the relationship between the airborne concentration A (Ci/m 3) and the surface deposition is: A = S (Ci/m 2) x K (1/m) (2.6)e a where: K is the resuspension factor and is equal to 1.OE-05 (1/m) for semi-arid/grassland terrains (from Reference 1).In actual practice, septage waste will be either surface spread at a controlled rate per acre, or directly injected into the top 6 inch surface soil layer, at a precalculated rate, in order to control the limiting factor.The assumptions made for analytical purposes are as follows: (a) For the analysis of the radiological impact during Vermont Yankee active control of the disposal sites, no injection will be assumed to take place; all dispersed radioactive material will be assumed to remain on the surface and to form a source of unshielded radiation.
2-8 6680R R ic'har Emch---- v'y"8 9 -59. tif Page 40j (b) For the analysis of the impact after Vermont Yankee control of the sites is assumed to be relinquished, the radioactive material will be assumed to be plowed under and to form a uniform mix with the top 6 inches of soil (to account for the shielding provided by the soil), but, nonetheless, to undergo resuspension at the same rate as surface contamination.
Analysis of preliminary results, based on the measured radioactivity concentration found in sludge during 1988, showed that a 2-acre disposal plot would meet the radiation criteria given in Section 2.3. This is the plot size, therefore, used in the final analyses.As for the occupancy factors for direct exposure to the ground deposition and for immersion in the resuspended radioactivity, 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> were used for the radiological impact analysis during active Vermont Yankee control of the disposal sites, and continuous exposure was assumed thereafter.
The 104-hour interval is expected to be an upper bound of a farmer's time spent on a plot of land, which is assumed to be 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week for 6 months while he plows, plants, and harvests his crop.2.7 -i _[iJ& Pathway Data and Usage Factors The following exposure pathways were addressed in this calculation for both the maximally exposed individual (i.e., during Vermont Yankee control of the disposal sites) and for the inadvertent intruder (i.e., after control is assumed to be relinquished): (a) Standing on contaminated ground.(b) Inhalation of resuspended radioactivity.(c) Ingestion of leafy vegetables.(d) Ingestion of stored vegetables.(f) Ingestion of meat.(g) Ingestion of milk.(h) Liquid pathways.2-9 6680R I ~L-...J r~~L L.... nr~ichardCMCH
-UV 0 Al I P7.Radiation exposures were computed for all pathways, with one exception.
As shown in Section 2.8 below, the radiological impact from the liquid pathway was determined to be insignificant without the need of a detailed analysis.
It should be noted that current agricultural activities permitted on the designated disposal sites are limited to the growing of feed crops (hay) for dairy animals. As such, the ingestion of leafy and stored vegetables are not existing exposure pathways, but have been included to demonstrate that these could also be acconmmodated within the proposed dose criteria for septic waste disposal.Pathway data and usage factors as applicable to the area in the vicinity of the Vermont Yankee Nuclear Power Station are shown in the tables which follow. These are the same factors as used in the plant's ODCM assessment of the off-site radiological impact due to routine releases from the plant, with the following exceptions: (a) The soil exposure time for spreading of the radioactivity content of the septage to cover each period of measured deposition was changed from a standard 15 years (given in Regulatory Guide 1.109)to 1 year.(b) The fraction of stored vegetables grown on the contaminated land was conservatively increased from 0.76 to 1.0.(c) The crop exposure time was changed from 2160 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.2188e-4 months <br /> to 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> to reflect the condition that no radioactive material will be dispersed directly on crops for human or animal consumption, the deposition on crops of resuspended radioactivity being insignificantly small; that is, crop contamination is only through root uptake.2-10 6680R FRichard Emch -,bvy 89 59.tif PaIg e 142[~~ ~~ ~ ~ ~~~ ~~~~ .ih r ...........
........ ....t.............................
................-
4 USAGE FACTORS Vegetables Leafy Veg. Milk Meat Inhalation n (kL/yr) (kg/r) (1/y) £kgLyr) (mJ/yJ )Adult 520 64 310 110 8,000 Teen 630 42 400 65 8,000 Child 520 26 330 41 3,700 Infant --- .. 330 --- 1,400 VEGETABLE PATHWAY Stored Veaetables Leafy Vegetables Agricultural productivity (kg/m 2) 2.0 2.00 Soil surface density (kg/m 2) 240.0 240.0 Transport time to user (hours), 0.0 0.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours) .0 .0 Holdup after harvest (hours) 1,440.0 24.0 Fraction of stored vegetables grown in garden 1.0 Fraction of leafy vegetables grown in garden 1.0 COW-MILK PAINA Pasture Feed Stored Feed Agricultural productivity (kg/m 2) .7 2.0 Soil surface density (kg/m 2) 240.0 240.0 Transport time to user (hours) 48.0 48.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours) .0 .0 Holdup after harvest (hours) .0 2,160.0 Animals daily feed (kg/day) 50.0 50.0 Fraction of year on pasture .5 Fraction pasture when on pasture 1.0 MEAT PATH"WAY Pasture Feed Stored Feed Agricultural productivity (kg/m 2) .7 2.0 Soil surface density (kg/m 2) 240.0 240.0 Transport time to user (hours) 480.0 480.0 Soil exposure time (hours) 8,766.0 8,766.0 Crop exposure time to plume (hours) .0 .0 Holdup after harvest (hours) .0 2,160.0 Animals daily feed (kg/day) 50.0 50.0 Fraction of year on pasture .5 Fraction pasture when on pasture 1.0 2-11 6680R Richard Emch -bvy 89 59.tif ..Page_43 2.8 LjigiLad Pathways There are three potential routes through which septic waste radioactivity may enter into the liquid pathway, as follows: (a) Surface water runoff.(b) Ground water pathway.(c) Accidental releases into the Connecticut River.Since there are no potable water wells between the disposal site and the river, it is evident that the only way for septic waste radioactivity to enter the liquid pathway is via the Connecticut River.Even though surface water runoff may be a credible pathway into the river, the fraction of disposed radioactivity which may thus be transported to the river is very small for the following reasons: (1) The selected disposal sites are set back from the river.(2) Procedural controls will ensure that during surface spreading of all the septage and any precipitation falling onto or flowing onto the disposal plot will not overflow the perimeter of the disposal site.(3) The disposal plots have slopes of 5% or less in order to limit surface runoff.With respect to septage radionuclides reaching the Connecticut River via the ground-water pathway, the critical parameter is the total transport time from the field to the river. Should this transport time (which is element dependent) be large in comparison to the half-life of the radionuclide of interest, then decay in transit will remove the said radionuclide from the pathway. For the case on hand, the conservative travel times to go an average 200 feet to the river, and the fractions of land-spread radioactivity which are expected to reach the river are as follows: 2-12 6680R I Richard Emch -bvy 89 59.tif P66e"44']Decay Constant 1Isotop (1f ie /yr)Mn-54 Co-60 Zn-65 Cs-134 Cs-137 312.2 d 5.272 y 243.8 d 2.065 y 30.17 y 0.8109 0.1315 1.038 0.3357 0.02297 Travel Time to River (years)(Ground Water Path)3.35 961.3.35 193.193.Fraction of Initial Activity_EngxJAng iver 6.61E-02 0.0 3.09E-02 0.0 I. 19E-02 Thus, only small fractions of Mn-54, Zn-65, the river via the ground-water pathway; and, since these isotopes are relatively insignificant, it is pathway is not a credible one.and Cs-137 may make it to the initial activities of clear that the ground-water We proceed, then, with the analysis of an accidental release of the entire contents of a septic waste spreading truck directly into the Connecticut River. Following such an accident, the released radioactive material is expected to first mix with part of the water in Vernon Pond and to then gradually flow downstream of the Vernon Dam. The storage volume in Vernon Pond, excluding the volume below the crest, is approximately 6.OE+9 gallons (2.3E+13 cc). Since no use is made of the river between the plant and the Vernon dam, the only potential exposure pathway is downstream of the dam;and from Reference (2), the river flow through the dam is typically 10,000 cfs, and no less than 1,200 cfs during the dry season.As a conservative condition, assume that the septic waste mixes with just one thousandth of the Vernon pond storage volume, i.e., with 2.3E+10 cc.This amount of water will pass through the dam in about 11 minutes if the river flow is 1,200 cfs, and in about 1.3 minutes if the flow is 10,000 cfs.Using the upper-bound activities given in Section 2.3, the expected concentrations in the pond, and the corresponding MPCs are as follows: Upper-Bound Activity Content (Ci/BatchL Mn-54 Co-60 Zn-65 Cs-134 Cs-137 TOTAL 9.44E-07 1. 61E-05 1. 13E-06 2. 25 E-0 7 2. 87 EQA 2.13E-05 Expected Concentration in Pond (uCilml)4.1OE-11 7.02E-10 4.93E-11 9.80E-12 9.27E-10 4. 1OE-0 7 2.34E-05 2.47E-07 2.45E-07 3. 1E-0 2.74E-05 2-13 6680R
'Richard Emch -bv-y_89 59.tifPae4 Page I A R d---A It is seen that the concentrations are negligibly small to pose any radiological concern.In sunmmary, as demonstrated above, the liquid pathway is not credible.2-14 6680R Richard Emch -bvy 89 59.tiif Page 46 1..........
3.0 RADIOLOGICAL ASSESSMENT The radiological impact associated with the on-site disposal of radioactive septage at Vermont Yankee was carried out using the dose assessment models in Regulatory Guide 1.109, and is consistent with the methodology employed by the Vermont Yankee ODCM. However, since the computer code used (ATMODOS; Reference (3)) is primarily for use with atmospheric releases, it was necessary to manipulate the input to obtain the desired results for direct deposition of radioactivity on soil due to land spreading of septic waste. In particular, special consideration was given to the following: (a) The computation of an effective shielding factor to account for the effect provided by the soil after the waste is plowed under, or if it is directly injected into the top 6 inch surface layer.(b) The definition of an annual activity release rate, which following a year's time of continuous release, would yield the ground deposition expected to prevail after 40 combined tank pump-outs, as calculated in Section 2.5.(c) The definition of an effective atmospheric dispersion factor to represent the resuspended radioactivity.(d) The proper representation of partial occupancy factors.These are discussed in Sections 3.1 and 3.2 which follow.The results of the radiological impact assessment are presented in Sections 3.3 and 3.4.3.1 as a Result of Flowing the Radioactive Material into the As pointed out in Section 2.6 of this calculation, the impact analysis after control of the disposal sites is relinquished, was based on the 2-15 6680R I Richard Emch -bvy 89 59.tif Pa6g~e -47 1------------
assumption that the radioactive material will be plowed to form a uniform mix with the top .6 inches of soil. To account for the gamma attenuation provided by the soil, it was necessary to carry out an appropriate shielding calculation.
This was accomplished through use of the ALLEGRA and DIDOS-V computer codes (References 4 and 5). The ALLEGRA code was used to define the gamma spectrum (in MeV/sec) associated with the selected radionuclide mix.This spectrum was then entered into DIDOS-V to compute the radiation levels from the two following source/receptor geometries: (a) A circular disk source with a radius of 150 m (represented by a cylindrical volume with a height equal to 0.001 m), the receptor location being along the disk axis, 1 m from the disk.(b) A cylindrical volume source with a radius of 150 m and a height of 0.15 m, with the receptor located along the axis, I m above the source.In the latter case, the source density was set equal to 1.6 g/cc; this is equivalent to the Reg. Guide 1.109 value of 240 kg/m2 for the effective surface density of soil within a 15 cm plow layer. The source radii were assumed to be large so as to approximate semi-infinite conditions, thus, permitting a direct comparison of the DIDOS-V and ATMODOS results for the 3 unplowed land. The source intensity (in MeV/sec-m , as required for input into DIDOS-V) was computed by distributing the radioactive material over a 2-acre surface, and within 0.001 m for the disk source and 0.15 m for the second case.Copies of the ALLEGRA and DIDOS-V outputs appear in Appendix B, which should be referred to for more details. The DIDOS-V results are as follows: Dose to air from the disk source = 1.085E-06 rad/hr Dose to air from cylinder source = 2.629E-07 rad/hr Overall soil shielding factor = 2.629E-07/l.085E-06
= 0.243 2-16 6680R ich~rdl Ench bvy 89 59.tif .Page 48 At this point, it is of interest to compare the DIDOS-V and ATMODOS exposure results from standing on contaminated ground. From the ATMODOS output in Appendix B (Section B.3.6), where the source term was the same as used in DIDOS-V, the skin dose due to exposure to contaminated ground for 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> is given as 6.78E-02 mrem. This is equivalent to a dose rate of 6.52E-4 mrem/hr, or (6.52E-4/1.11)
= 5.87E-4 mrad/hr to air, 1.11 being the average ratio of tissue-to-air energy absorption coefficients (from Regulatory Guide 1.109). It is seen that ATMODOS underestimates the dose by a factor of 2, approximately; the reason for this is the slightly outdated set of dose conversion factors in the guide, as can be verified by inspecting the data in WASH-1400, for instance.3.2 Pata o tion for Use with ATMODOS 3.2.1 Radioactivity Release Rate There are two parameters in the input to ATMODOS which affect the buildup of radioactivity at an off-site location, namely, the activity release rate and the accumulation period. To simulate this process, and to also account for the effect of the 40 applications described earlier, the accumulation period was set equal to I year, and the release rate was selected to be such that, at the end of one year, the total accumulated radioactivity at the disposal plot would be equal to the Qe values given in Section 2.5.That is, if we define by Qr the activity release rate (Ci/yr) which is required as input to ATMODOS, then the relationship between this parameter and Qe is as follows: Qe = Qr (1 -E)/)' (3.1)E = exp(-XAt)
(3.2)= is the decay constant for the selected isotope (I/year) and At = time interval between applications
= 1 yr.2-17 6680R
ýiq"rý' t:ao,_- bvy 89 59.tif Page 49 1 I-ihrdL c by-- 9hPae4 I I.............
Using the information given for Qe in Section 2.5. the desired values for Qr are as follows: Qe Qr Ratio of I o(ci) 1 o x I year)!O Mn 54 2.831E-06 4.132E-06 1.460 Co 60 2.353E-04 2.511E-04 1.067 Zn 65 2.801E-06 4.50ZE-06 1.607 Cs 134 1.457E-06 1.715E-06 1.177 Cs 137 9.259E-05 9.366E-05 1.012*For input to ATMODOS only.3.2.2 Atmospheric Dispersion What is of interest at this point is to provide a means of calculating the air immersion dose due to resuspension using the ATMODOS code (under the assumption that the resuspended material is due to an atmospheric release).To accomplish this, we proceed as follows. By definition, in the analysis of releases of gaseous effluents to the atmosphere, the airborne concentration at a receptor of interest is given by: Ae = Qr (Ci/yr) x (X/Q) (sec/m3 )/3.1536E+7 (sec/yr) (3.3)Where: (X/Q) is the atmospheric dispersion factor.Combining Equations (2.4), (2.6) and (3.3), it is seen that, for long-lived radionuclides (where the total accumulated radioactivity at the end of one year is numerically equal to the annual release rate, i.e. Qe = Qr x 1 year), the airborne concentration at the disposal plot due to resuspension effects can be accommodated by the following atmospheric dispersion factor: (X/Q) = K (1/m) 3.1536E+7 (sec/yr)/(N (acres) x 4046.9 (m2 /acre))= 7,792.6 (K/N) (sec/mi 3) (3.4)2-18 6680R Richard Emch -bvy 89 59.tif- Pag4e' -50?1 With K = 1.OE-5 (1/m), and N = 2 acres, the last equation reduces to: 3 (X/Q) = 3.896E-02 (sec/rm).At this point it is important to note that this method of analysis is slightly conservative since the receptor is assumed to be immersed in a cloud of undecayed radioactivity.
From the (Qr/Qe) ratios given in the last table in Section 3.2.1, it is seen that inhalation exposures will be overestimated by the following factors: Inhalation ExposureOverestiMation Factor Mn-54 1.460 Co-60 1.067 Zn-65 1.607 Cs-134 1.177 Cs-137 1.012 3.2.3 Occupancy Factors As indicated in Section 2.6, the occupancy factor for exposure to ground deposition and for immersion in the resuspended radioactivity was set equal to 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> during control of the disposal sites, and was assumed to be continuous thereafter.
Since occupancy factors cannot be entered directly into the ATMODOS code, the partial occupancy situation was accommodated as follows: (1) The exposure to resuspended radioactivity was handled by multiplying the effective (X/Q), as given by Equation (3.4), by (104/8760), 8,760 being the number of hours in one year; this 3 leads to a X/Q value of 4.626E-4 sec/mr (2) The exposure to radioactivity deposited on the ground was handled by setting the shielding correction factor equal to the occupancy factor (i.e., equal to 104/8760 = 0.012).It should be noted that the (X/Q) adjustment described above is appropriate in this case since radioactive material will not be dispersed on crops for human or animal consumption.
The only pathway through which crop contamination can take place is through root uptake.2-19 6680R I Richard Emch'- bVy 89 59.f Page 51 3.3 Land-Spreading Exposure Pathways Three sets of ATMODOS computer runs were carried out, for the following: (a) Assessment of the radiological impact during Vermont Yankee control of the disposal sites.(b) Assessment of the radiological impact after control of the sites is assumed to be relinquished.(c) Development of dose conversion factors providing a correlation between pathway exposures per soil activity for each isotope of interest.The results for each case are presented in the subsections which follow. Briefly, note that they correspond to a disposal plot size of 2 acres, which was determined to be the appropriate size to meet both the radiation exposure criteria listed in Section 2.3, and the desired flexibilities listed in Section 2.4. The whole body and critical-organ radiation exposures (after 40 pump-outs on the same plot at a concentration level equivalent to the measured 1988 concentrations in septic waste) are as follows: 'Control of Disposal Sites Controlled by VYNPS (Maximum Exposed Individual)
Uncontrolled (Inadvertent Intruder)Radiation Exposure 0.1 mrem/yr 0.2 mrem/yr Maximum 1.3 mrem/yr 3.9 mrem/yr Maximum Individual/Organ Child/Whole Body Child/Liver Adult/Whole Body Teenager/Lung The individual pathway contributions to the total dose are as follows: 2-20 6680R Richard Emch -bvy 89 59.tif age_52 I Pathway-Dependent Critical Organ Doses Maximally Exposed Inadvertent Intruder Individual/Organ Critical Individual/Organ (Child/Liver) (Teenager/Lung)(mremlyear) (mremlyear)
Ground Irradiation 0.0576 1.16 Inhalation 0.00122 2.74 Stored Vegetables 0.0913 0.00601 Leafy Vegetable 0.00467 0.00040 Milk Ingestion 0.0421 0.00229 Meat Ingestion 0,0249 0.00012 TOTAL 0.1994 3.909 In addition, an isotopic breakdown of the critical organ dose results listed above is shown in the following table: Isotopic Breakdown of Maximum Radiation Exposures, Radioactivity Pe cri Pt nf Istp (u2Q12 Acres) (mrem/yr)During Vermont Yankee Mn-54 2.831 0.000436 control of the Co-60 235.3 0.0559 disposal sites. Zn-65 2.801 0.0230 Maximally Exposed Cs-134 1.457 0.00231 Individual/Organ:
Cs-137 92.59 0,118 Child/Liver TOTAL 0.199 After Vermont Yankee Mn-54 2.831 0.0144 control of sites is Co-60 235.3 3.76 relinquished.
Zn-65 2.801 0.00983 Inadvertent Intruder Cs-134 1.457 0.000505 Critical Individual/
Cs-137 92.59 0.1247 Organ: Teenager/Lung TOTAL 3.91 As for the dose conversion factors during active plant control of the disposal sites, the critical-organ all-pathway values for a 2-acre disposal plot are: 2-21 6680R Rihr mich -,bvy 89 59.tifPae5 I¸~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~~....... .i..........................................................
........................
IIIIIIII iiii/ _i~ i~iiiiii iii/ I A1I7Pathway Worst-Csr__Dose Conversion Fact_-ra During Vermont Yankee Control of Disposal Sites Exposure IoQ Individual/Organ (mrem/yr-pCi)
Mn-54 Adult/GE-LLI 1.87E-4 Co-60 Teenager/Lung 3.57E-4 Zn-65 Child/Liver 8.21E-3 Cs-134 Child/Liver 1.59E-3 Cs-137 Child/Bone 1.33E-3 In all cases, the exposure pathways are direct shine from shielded/unshielded ground deposition, inhalation of resuspended radioactivity, and ingestion of contaminated food (stored vegetables, leafy vegetables, milk and meat); exposure to the ground deposition and to resuspended radioactivity is for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> during control of the disposal sites, and continuous thereafter.
Refer to Appendix B for copies of the ATMODOS outputs, and to the following list of assumptions employed in the calculations.
Briefly, the following basic assumptions were used in the calculational analyses: (a) The septic tanks are emptied every 6 months (expected future practice is to pump tanks once per year).(b) The tank radioactivity remains constant (at the main septic tank 1988 determined level plus 3 sigma).(c) The radiation source corresponds to the accumulation of radioactive material on a single plot within the proposed disposal sites over a period of 20 years (40 applications at 6 month intervals). (In actuality, the proposed sites will accommodate more than one disposal plot, and, in practice, more than one plot will most probably be used.)2-22 6680R Richard Emch -bvy 89 59.tif Page 54 (d) For the analysis of the radiological impact during Vermont Yankee control of the disposal sites, no plowing or direct injection of septage takes place and all dispersed radioactive material remains on the surface and forms a source of unshielded radiation. (In practice, the waste will be either surface spread or directly injected into the top 6 inch layer of the disposed plot, in which case the radioactive material will be mixed with the soil. This in effect would reduce the ground plane source of exposure by a factor of about four due to self-shielding.)(e) No radioactive material is dispersed directly on crops for human or animal consumption, crop contamination being only through root uptake.(f) The deposition on crops of resuspended radioactivity is insignificantly small.(g) Pathway data and usage factors used in the analysis are the same as those used in the plant's ODCM assessment of the off-site radiological impact from routine releases, with the exception that the fraction of stored vegetables grown on the disposal plots was conservatively increased from 0.76 to 1.0. (At present, no vegetable crops for direct human consumption are grown on any of the disposal sites.)(h) It is assumed that Vermont Yankee relinquishes control of the disposal sites after the fortieth pump-out (i.e., the above source term applies also for the inadvertent intruder).(i) For the analysis of the impact after Vermont Yankee control of the sites is relinquished, the radioactive material is plowed under and forms a uniform mix with the top 6 inches of soil, but, nonetheless, undergoes resuspension at the same rate as surface contamination.
2-23 6680R Rihr ErnCh -bv-y 89 69.tfifPae5 (k) Exposure to the ground deposition and to resuspended radioactivity is for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> during Vermont Yankee control of the disposal sites, and continuous thereafter, the 104-hour interval being representative of a farmer's time on a plot of land (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week for 6 months).3.3.1 Imoact During Vermont Yankee Control of the Disposal Sites The tables which follow present summaries of the ATMODOS results for the radiological impact during Vermont Yankee control of the disposal sites.The first table presents the results for the entire mix of radionuclides, and the second table shows the contributions by each isotope.Total Accumulated Radioactivity on 2-Acre Plot After 40 Disposal Auolications Ieuries Mn 54 2.831E-06 Co 60 2.353E-04 Zn 65 2.801E-06 Cs 134 1.457E-06 Cs 137 9.259E-05 Dose Delivered t Each Organ From all Radionuclides in thegmi4 ja-q Fom All Pathways Combined*(Adult. Teenager.
Child. and Infant)(mrem/yr)oAP. Kidney Lung 9IJ-4 Thyroid Whole Body SWO A 9.20E-02 1.13E-01 7.92E-02 8.46E-02 9.66E-02 5.76E-02 9.42E-02 6.78E-02 T 1.13E-01 1.44E-01 9.08E-02 9.90E-02 9.65E-02 5.76E-02 9.41E-02 6.78E-02 C 1.86E-01 1.99E-O1 1.10E-01 9.73E-02 8.22E-02 5.76E-02 9.94E-02 6.78E-02 I 1.14E-O 1.38E-01 8.36E-02 8.08E-02 7.59E-02 5.76E-02 7.19E-02 6.78E-02*Each pathway includes unshielded exposure to ground contamination for 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, with all radioactivity assumed to be on the surface of the ground;exposure to resuspended radioactivity is also for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />.2-24 6680R Richard Emch -bvy 89 59.tifP Contributions to the Dose Delivered to Each Organ From all Pathways Combined*(Adult, Teenager.
Child, and Infant)(mrem/yr)Dome Livt Kidney g =9 IU-LLJ 1hX Whole Body skin Source: Mn-54, 2.831E-06 Ci (2-acre plot)A T C I 2.13E-04 2. 13E-04 2. 13E-04 2.13E-04 3. 1BE-04 3.66E-04 4. 36 E-04 2. IBE-04 2.44E-04 2.59E-04 2. 76E-014 2.14E-04 2.98E-04 3.34E-04 3.09E-04 2. 74E-04 Source: Co-60, 2.353E-04 Ci (2-acre plot)A T C I 5.20E-02 5. 20E-02 5.20E-02 5. 20E-02 S. 37E-02 5.44E-02 5.55E-02 S. 22E-02 5.20E-02 5. 20E-0 2 5.20E-02 5. 20E-02 7.40E-02 8 .41E-02 7.80E-02 6.86E-02 5.30E-04 5.25E-04 4. OOE-04 2. 15E-04 8.32E-02 8. 30E-02 7. 16E-02 5.26E-02 6. 72E-03 6. 72E-03 4. 16E-03 1. 76E-02 Source: Zn-65, 2.801E-06 Ci (2-acre plot)A T C I 3.43E-03 4.61E-03 8.72E-03 6. 18E-03 1 .06E-02 1.57E-02 2.30E-02 2.08E-02 7. 13E-03 I.OIE-02 1.45E-02 1.02E-02 2.03E-04 2.28E-04 2. 11 E-04 1.88E-04 2. 13E-04 2.13E-04 2. 13E-04 2.13E-04 5.20E-02 5.20E-.02 5. 20E-02 5. 20E-0 2 1. 46E-04 1 .46E-04 1. 46E-04 1. 46E-04 2.27E-04 2.27E-04 2. 27E-04 2. 27E-04 5.06E-03 5.06E-03 5.06E-03 5.06E-03 2.33E-04 2.44E-04 2. 73E-04 2.14E-04 5.56E-02 5.7 3E-02 6. 24E-02 5.25E-02 4.8 7E-03 7.38E-03 1.44E-02 9.69E-03 9.31E-04 8.44E-04 6.6 7E-04 3. 30E-04 3.25E-02 2.83E-02 2. 18E-02 9.20E-03 2.50E-04 2.50E-04 2.50E-04 2.50E-04 6. 12E-02 6.12E-02 6. 12E-02 6.12E-02 1.68E-04 1.68E-04 1.68E-04 1.68E-04 2.65E-04 2.65E-04 2.65E-04 2.65E-04 5.90E-03 5. 90E-03 5.90E-03 5.90E-03 Source: Cs-134, 1.457E-06 Ci (2-acre plot)A T C I 5.89E-04 7.92E-04 1 .50E-03 7. 74E-04 1.09E-03 1 .56E-03 2.31E-03 1.25E-03 5.06E-04 6.50E-04 8.74E-04 4.89E-04 3-20E-04 3.89E-04 4.5 9E-04 3.35E-04 2.42E-04 2.44E-04 2.38E-04 2.30E-04 Source: Cs-137, 9.259E-05 Ci (2-acre plot)A T C I 3.57E-02 5.52E-02 1.23E-01 5.50E-02 4. 70E-02 7.18E-02 1.18E-01 6.35E-02 1.93E-02 2. 78E-02 4. 19E-02 2.07E-02 9.79E-03 1.39E-02 1.83E-02 1.14E-02 5.86E-03 6.OOE-03 5. 76E-03 5.24E-03*Each pathway includes unshielded exposure to ground contamination for 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, with all radioactivity assumed to be on the surface of the ground;exposure to resuspended radioactivity is also for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />.2-25 6680R I Richard Emch -bvy 89 59.tif Page 57 3.3.2 Radiological Impact After Termination of Active Control of the Disposal Sites The table which follows presents a summary of the ATMODOS results for the radiological impact after control of the disposal sites is assumed to be relinquished after 20 years of septic waste disposal.
Tables showing the contributions by the various isotopes were not prepared as they were determined to be of little significance.
Total Accumulated Radioactivity on 2-Acre Plot After 40 Disposal Applications IooeCuries 25 Mn-54 2.831E-06 27 Co-60 2.353E-04 30 Zn-65 2.801E-06 55 Cs-134 1.457E-06 55 Cs-137 9.259E-05 Qose Delivered to Each Organ From all Radionuclides in the Mix a d From all Pathways Combi (Adult. Teenager.
Child, and Infant)(mrem/yr)DQnc Liver Kidney Lung GI-LLI Thyroid Whole Body A 1.25E+00 1.29E+00 1.21E+00 3.04E+00 1.29E+00 1.16E+00 1.25E+00 1.37E+00 T 1.30E+00 1.35E+00 1.23E+00 3.91E+00 1.28E+00 1.16E+00 1.24E+00 1.37E+00 C 1.40E+00 1.41E+00 1.25E+00 3.39E+00 1.22E+00 1.16E+00 1.23E+00 1.37E+00 I 1.28E+00 1.32E+00 1.21E+00 2.58E+00 1.19E+00 1.16E+00 1.19E+00 1.37E+00*Each pathway includes continuous exposure to ground contamination (uniformly distributed within a 6-inch layer of soil)2-26 6680R 3.3.3 Isotopic Dose Conversion Factors The table which follows presents isotope-dependent dose conversion factors for the various age groups and organs. They were computed using the ATMODOS computer code along with all the assumptions employed in the assessment of the radiological impact during Vermont Yankee control of the disposal sites. The source terms were defined using the adjustment ratio (Qr x 1 yr)/Qe given in Section 3.2.1 to obtain an accumulated radioactivity of 1 uCi for each isotope of interest at the end of one year.These conversion factors form part of one of the procedural controls described in Section 4 for ensuring that the disposed contaminated septage does not lead to radiation exposures in excess of the specified limits.2-27 6680R Richard ..nCh .bvy 89 59 tif a....Dose Conversion Factors For Radioactive Material Spread over Two Acres For all Pathways Combined*(Adult, Teenager.
Child, and Infant)(mrem/yr-uCi)
BMW Liver K L= GI-LLI Thyroid Whole Body Skin Source: Mn-54 A T C I 7.54E-05 7.54E-05 7.54E-05 7.54E-05 1 .1 2E-04 1. 29E-04 1.54E-04 7. 71E-05 8.63E-05 9.15E-05 9.74E-05 7.58E-05 1.05E-04 1. 18E-04 1 .09E-04 9.68E-05 1 .87E-04 1 .85E-04 1. 41E-04 7.60E-05 7.54E-05 7.54E-05 7.54E-05 7.54E-05 8. 24E-05 8.61E-05 9.6 3E-05 7.58E-05 8.84E-05 8.84E-05 8.84E-05 8.84E-05 Source: Co-60 A T C I 2.21E-04 2.21E-04 2. 2 1E-04 2. 21E-04 2.28E-04 2. 31 E-04 2.36E-04 2.22E-04 2.21E-04 2. 21E-04 2. 21E-04 2.2 1E-04 3.14E-04 3.57E-04 3. 32E-04 2.9 2E-04 3.54E-04 3.53E-04 3.04E-04 2.24E-04 2.21E-04 2.21E-04 2-21E-04 2.21E-04 2.36E-04 2.43E-04 2.65E-04 2.23E-04 2.60E-04 2.60E-04 2.60E-04 2.60E-04 Source: Zn-65 A T C I I , 22E-03 1 .65E-03 3. 11E-03 2. 21 E-0 3 3. 78E-03 5.5 9E-03 B. 21E-03 7.44E-03 2.55E-03 3.60E-03 5.19E-03 3.63E-03 7.24E-05 8. 12E-05 7.5 5E-05 6. 72E-05 2.40E-03 2.40E-03 1. 48E-03 6. 29E-03 5. 20E-05 5. 20 E-05 5.20E-05 5. 20E-05 1. 74E-03 2.64E-03 5.12E-03 3.46E-03 5.98E-05 5.98E-05 5.98E-05 5.98E-05 Source: Cs-134 A T C I 4.04E-04 5.44E-04 1 .03E-03 5.31E-04 7.46E-04 1 .07E-0 3 1.59E-03 8.55E-04 3.47E-04 4. 46 E-04 6. OOE-04 3.36E-04 2.19E-04 2.67E-04 3.15E-04 2.30E-04 1.66E-04 1.67E-04 1. 64E-04 1 .58E-04 1.56E-04 1.56E-04 1. 56E-04 1.56E-04 6.39E-04 5. 79E-04 4.58E-04 2.26E-04 1 .82E-04 1.8 2E-04 1.82E-04 1. 82E-04 Source: Cs-137 A T C I 3.86E-04 5. 97E-04 1. 33E-03 5.94E-04 5.07E-04 7.75E-04 1. 28E-03 6.86E-04 2. 0 9E-04 3.OOE-04 4.53E-04 2.24E-04 1. 06E-04 1. 50E-04 1. 98E-04 1. 23E-04 6.33E-05 6.48E-05 6.23E-05 5.66E-05 5.46E-05 5. 46E-05 5.46E-05 5.46E-05 3.5 2E-04 3.06E-04 2.35E-04 9.94E-05 6 -37E-05 6.37E-05 6.37E-05 6.37E-05*Each pathway includes unshielded exposure to ground contamination for 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, with all radioactivity assumed to be on the surface of the ground; exposure to resuspended radioactivity is also for a period of 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />.2-28 6680R ihard Emch -bvy 89 59.tif. Page 60 4.0 RECOMrENDED PROCEDURAL CONTROLS TO ENSURE COMPLIANCE WITH RADIOLOGICAL Once an on-site septage disposal permit has been secured, implementation of the disposal program must be accompanied with procedural controls to ensure that the applicable radiological limits are not violated.This section presents a list of proposed controls to this effect.4.1 Total Rada~ t~vity Dispersed per Disposal Plot As pointed out in Section 2.5, since the content of radioactivity in septic waste is very low, and since it is neither practical nor necessary to carry out a new analysis prior to each disposal, assessment of the radiological impact was based on an assumed source corresponding to the expected accumulation of radioactive material on a given 2-acre disposal plot over a period of 20 years (40 applications at b-month intervals).
As such, it will be necessary to keep accurate records of the time and location of septage disposal and of the ensuing buildup and decay of radioactivity on each disposal plot. The basic equation to be employed is as follows: tot new old Q. + Q. exp (-ai (4.1)tot Where: Qi total accumulated radioactivity at the selected 2-acre disposal plot after the current disposal (uCi).new Q new radioactivity added to the plot as a result of the current disposal (uCi).old Qo radioactivity accumulated at the selected disposal plot prior to the current disposal (uCi), as determined at the time of the previous disposal." = radioactive decay constant (1/year).t= time lapse since the previous disposal on the same disposal plot (years).2-29 6680R 1-<ichard EmCh -bvy 89 59.tfI Page 61 1.............
Qew can be calculated using the following equation: new Qi = 14,950 gallons x 3,785.4 cc/gallon x l.0E-3 kg/cc Cwet (~/gwt x Fs (solids fraction) x C. (pci/kg wet)1 x 1.OE-6 (uCi/pCi)= 0.0566 F. C.et (4.2)i Where: C.et is the measured or estimated radionuclide concentration in 1 the septic waste on a wet basis, and Fs is the fraction of solids in the septage per tankful. Fs was conservatively set equal to 0.3 in this calculation.
14,950 gallons equals the volume of both the main septic tank and the south disposal system collection tank.4.2 OperationaL_1njgij The disposal operating procedures to be established should address both the activity concentration and the potential radiation exposure.
Should the activity concentration be in excess of the specified limit, then the sewage mix would not be suitable for on-site disposal and would have to be processed accordingly; this situation, however, is not likely to occur. On the other hand, approaching the exposure guideline is a possibility; but this can be easily accommodated by switching to a different plot within the disposal sites. The subsections which follow present pertinent information recommended for inclusion in the operating procedures.
4.2.1 1aciu Activity Concentrations In line with the discussion presented in Section 2.3 of this calculation, the radionuclide concentrations in the septic waste must not exceed the following limits: (a) One tenth of the MPC values listed in 10 CFR 20, Appendix B, Table II, Column 2.2-30 6680R Richard Emch -bvy 89 59 tif ...Page_62 (b) An overall MPC ratio of less than or equal to 0.1.For the major radionuclides identified in the Vermont Yankee septic waste, the individual MPC limits are as follows: taxim .ermissible Concentrations in Water (lOCFR20, Appendix B, Table II)Mn 54 Co 60 Zn 65 Cs 134 Cs 137 Soluble I.OE-4 5.OE-5 1.OE-4 9.0E-6 2.OE-5 Insoluble£PiilmU)I .OE-4 3.OE:-5 2. OE-.4 4. OE-.5 4.OE-5 For a mix of radionuclides in the sewage mix, the condition to be met is: E (C /MPC.) 0.1 Where: Ci is the measured concentration for Isotope i, and the summation is over all radionuclides in the mix.From the 1988 spectroscopic analysis of septic waste samples, all radioactivity is expected to be in insoluble form, and no radioactivity is expected in the liquid above the sludge. Should the situation change, use should be made of both the soluble and insoluble MPCs listed above, as appropriate.
4.2.2 Potential Radiation Exposures As described in Section 2.3 of this calculation, the NRR draft guidelines for radiation exposure from all probable pathways due to the disposal of low-level waste are 1 mrem/yr to the total body and any body organ of a maximally exposed individual, and 5 mrem/yr to an inadvertent intruder.The maximally exposed individual is identified as a member of the general public or a worker who is not classified as a radiation worker.2-31 6680R Richard Emch'-bvy 89 59.tif 1-1-lI Pag 6 3.I R cha d, m c vy 9 9:tf , ............
.."..... i ..... ...... i. ....... ... .. ii i , ii ,, .- , iiP g 6 Since the proposed septage disposal sites are within VYNPS property and under VYNPS control, occupancy of the disposal sites by an inadvertent intruder is only possible after plant decommissioning.
That is, during the on-site septic waste disposal program, only the specified exposure guideline for the maximally exposed individual would be in effect.To ensure proper operation of the on-site disposal program, a set of checkpoints was prepared as guidance.
The action levels were based on the following results from Section 3: Isotopic Breakdown of Maximum Radiation Exposures Radioactivity Exposureription Isotp (uCi/2 Acres) During Vermont Yankee Mn-54 2.831 0.000436 control of the Co-60 235.3 0.0559 disposal sites. Zn-65 2.801 0.0230 Maximally Exposed Cs-134 1.457 0.00231 Individual/Organ:
Cs-137 92.59 0_1 Child/Liver TOTAL 0.199 After Vermont Yankee Mn-54 2.831 0.0144 control of sites is Co-60 235.3 3.76 relinquished.
Zn-65 2.801 0.00983 Inadvertent Intruder Cs-134 1.457 0.000505 Critical Individual/
Cs-137 92.59 0.1247 Organ: Teenager/Lung TOTAL 3.91 It is seen that, whereas the exposure to the maximally exposed individual is approximately 20% of the 1 mrem/year guideline, the inadvertent intruder exposure is almost 80% of the 5 mrem/year limit. Thus, to ensure that both guidelines are met at all times, it is intended that the operational guideline for the maximally-exposed individual be set at 0.2 mrem/year.
This is a conservative approach since the likelihood of intruder occupancy of the sites coinciding with the end of the on-site disposal program is nil;substantial decay of the radioactive material is expected by the time the sites are released to the general public. Of course, future reassessment of this operational guideline is not precluded.
However, an operational limit close to the guideline is not recommended since it eliminates all flexibilities.
2-32 6680R Rich rd c -v Pag-e-64'Based on the operational guideline of 0.2 mremfyr to the maximally exposed individual, two checkpoints were prepared which would ensure that the radiation exposure limit will not be exceeded.
They are as follows: (a) A&tion Level 1 -Gross Radioactivity Limit The up-to-date total radioactivity dispersed per disposal plot_tot.(Qi ) is calculated for each isotope using Equation (4.1).1 If the condition:
Qtot <Q lim i 1 is met for each isotope, where Q. represents the limiting values listed in the following table (from Section 3, rounded off to 2 significant figures), then disposal of the septic waste will not violate the exposure limit; otherwise, proceed to Action Level 2.Maximum Accumulated Radioactivity AllowedAcre Is~topep 0i (uCi)Mn-54 1.4 Co-60 120.0 Zn-65 1.4 Cs-134 0.7 Cs-137 46.5 (b) Action Level 2 -Radiation Exosr If Action Level 1 fails, determine the potential radiation exposure using the equation: tot Dose (mrem/yr)
= E Qi DCF._tot Where: Qt is the up-to-date total radioactivity dispersed 1 per disposal plot calculated for each isotope using Equation (4.1), DCF. is the dose conversion factor for 1 isotope i, and the summation is over all the radionuclides in the mix. The dose conversion factors are as follows: 2-33 Richard Emch -bvy 89 59.tif Page 65 I DCFi I Individual/Organ (mrem/year-uCi/acre)
Mn-54 Adult/GI-LLI 3.74E-04 Co-60 Teenager/Lung 7.14E-04 Zn-65 Child/Liver 1.64E-02 Cs-134 Child/Liver 3.18E-03 Cs-137 Child/Bone 2.66E-03 The model overestimates the exposure by approximately 20% because the above DCF's correspond to the most restrictive exposure to any individual and any organ from all pathways, independently selected for each radionuclide.
The exposure pathways are direct shine from unshielded ground deposition, inhalation of resuspended radioactivity, and ingestion of contaminated food (stored vegetables, leafy vegetables, milk and meat); exposure to the ground deposition and to resuspended radioactivity is for a period of 104 (hours/year).
If the calculated dose is in excess of 0.2 (mrem/yr), a different disposal plot would have to be selected.2-34 6680R Richard Emch -bvy,89 59.tif Page 661 Richard~~~~ý*
0mh-by8 9tfPg 6 11..............
5.0 REFERENCES
I. U.S. Nuclear Regulatory Commission, Reactor Safety Study, Appendix VI, jv-i1ation of Reactor Accident Consequences, WASH-1400 (NUREG 75/014), October 1975.2. Vermont Yankee Nuclear Power Station, FSAR, Section 2.4.4 Uses of River.3. ATMODOS, A YAEC Computer Code for the Calculation of Off-Site Doses from Iodines and Particulates Discharged to the Atmosphere in line with the Models In Regulatory Guide 1.109 4. J. N. Hamawi, ALLEGRA -A Computer Code Making Use of the ORIGEN-2 Data Bases for the Analysis of Radioactive Decay Chains and the Computation of a ENTECH Engineering, Inc., Marlboro, MA, Technical Report PI00-RI5 (technical report in preparation).
- 5. J. N. Hamawi, /DIDOS-Ill
-A Three-Dimensional Point-Kernel Shieldina Code for Cylindrical Sources, ENTECH Engineering, Inc, Technical Report PlOO-R2, December 1982 (an upgraded version of the code, DIDOS-V, suitable for the analysis of infinitely large cylindrical sources, is currently in preparation).
- 6. Atomic Industrial Forum, National Environmental Studies Program, A Guide for Obtaining Regulatory Approval to Dispose of Very Low Level Wastes by Alternative Means, prepared by D. W. Chan, J. P. Davis & R. W. Wofford, General Physics Corporation, Columbia, Maryland, Technical Report No. AIF/NESP-037, August 1986.2-35 6680R
'Richard Emch -bvy 89 59 tif-Page 6.7,ýAPPENDIX A LABORATORY ANALYSES OF SEPTIC WASTE A. I I Richard Emch -bvy 89 59.tif Page 68 ]MAILEU JU:-, 0o ": YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY Initial Analysis Report Custoerg Yankee Nuclear Power Corp.Atzt.W6 b&yAJk~tI*4E KEEGAN4 MR. EDWARD CUMMING MR. STEPHEN SKIBNIOWSKY Report Date: Analysis Date: Date Received: Reference Date: 06/D9/88 6 /8 /88 6 /8 /88 6 /8 /a8 Sludge Sample Amount: 1.01 Kg. Lab Sample No.: G72970 Sample Submission Code: VSL 02 2388 Elapocd Time : 0.65 days Other Analysis Requested:
None Commenti COB TANK BOTTOM DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC CORRECTION
[ Pico Curie / Kilogram -wFT Np-239 Co-57 Ce-144 Ce-141?o-99 Se-75 Cr-51 I -131 De-7 Ru-103 1 -133 Be-140 Cs-134 Ru-106*4 Ce-137 Ag-11M Zr-95 Co-58 Mn-54*+ AcTh228 TeI-132 Te-59 Zn-65*+ Co-60*+ K -40 Sb-124 8.24E-01 9.98E-01 9.98E-01 9.86t-01 8.49E-01 9.96E-01 9.84E-01 9.45E-01 9.92E-01 9.89E-01 5.95E-01 9.65E-01 9.99E-01 9.99E-01 I.OOE 00 9.98E-01 9.93E-01 9.94E-01 9.99E-01 1.00B 00 8.70E-01 9.90E-01 9.98E-01 1.00E 00 1.00R 00 9.92E-01 (-15 +- 11 ( 5 -94 (-9 4- 73 ( 26 4- 17 ( 11 4- 20 (-6 4- 15 ( 41 4- 93 (-15 4- 11 ( 102 4- 94 (-11 4- 12 ( 22 +- 17 (-175 4- 68 ( 16 4- 16 4 4-13 103 in- 1 (-2 4- 19 (-19 4- 24 ( 7 -13 (-7 4- 14 ( 287 4- 68 ( 117 4- 99 (-33 4- 27 ( 89 4- 36 ( 454 4- 31 07+- 23 (-31 4-31 E 0 E-2 E-1 E-1 E 0 E-1 E-1 E-I E-i E-i E-i E-I E-1 E Q E-i E-I E-i E-1 E-I E-I X-1 E-i E-1 Z-i E 0 E-i 35 310 240 55 65 49 310 37 310 38 58 230 53 43 54 64 79 42 50 230 330 91 120 82 75 100 E o E-2 E-i E-I E 0 E-i E-1 E-1 E-I E-I E-i E-i E-i E 0 E-i E-i E-i E-1 E-1 E-i E-i E-1 E-i E-I E 0 E-I Notes:* Activity greater than 3*standard deviation+ Peak is found.......
..@ -. rt ........... .ttI 2 2d ..... ..............
Approved by D.Z .McCurdy.:
I Richard Emch -bvy 89 59.tif Pacae 69 I I MAILEU YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY ,iU;I 0,: Initial Analysis Report YAFC"Yankeo Nuclear Power Corp.A t t ention: MS. ELAINE KEEGAN MR. EDWARD CUM3ING MR. STEPHEN SKIBNIOWSKY Report Date: Analysis Date: Date Received: Reference Date: 06/09/86 6 /8 /as 6 /8 /88 6 /B /8e Sludge..............................
Sample Amount: 1.02 Kg. Lab Sample No.: G72971 Gample Submission Code: VSL 03 2388 Elapsed Time : 0.63 days Other Analysis Requested:
None Comment: COB TANK-LIQUID DECAY ACTIVITY NUCLIDE CONC. +- I SIGMA MDC CORRECTION ( Pico Curie / Kilogram-wrET
...........................................................................
Np-239 8.29E-01 Co-57 9.98E-o1 Ce-144 9.98E-O0 Ce-141 9.87E-01 Mo-99 0.54E-01 Se-75 9.96E-01 Cr-51 9.84E-01 1 -131 9.47E-01 Bd-7 9.92E-01 RU-103 9.89E-01 I -133 6.05E-01 Ba-140 9.66E-01 Ce-134 9.99E-01 RU-iO6 9.99E-01 CB-137 1.OOE 00 Ag-1iON 9.98E-01 Zr-95 9.93E-01 Co-58 9.94E-01 Mn-54 9.99E-01 AoTh228 1.00E 00 Tel-132 8.73E-01 Fe-59 9.90E-01 Zn-65 9.98E-01 CO-60 1.00E 00+ K -40 1.00E 00 sb-124 9.93E-01 Notes:+ PeaX is found (6 -10 ( 65 4- 93 ( 20 4- 67 (0 -16 (-25 +- 19 (4 -14 (. 61 4- 86 (8 -11 ( 14- 10 C 17 4- 12 (-1 4- 19 ( 33 4- 72 (-17 +- 14 (-1 +- 12 (-S -- 13 (-6 4- 16 ( 20 4- 22 ( 13 4- 12 ( 11 4- 12 (-21 4- 66 ( 16 4- 91 (a- 28 ( 72 +- 34 (-6 4- 18 ( 55 1- 21 ( 6 4- 34 E 0 E-2 E-1 E-1 E0 E-1 E-1 E-1 5 0 E-1 E-1 E-1 E-i E 0 E-I E-1 E-1 E-1 E-1 E-1 E-1 E-1 E-1 E-1 E 0 E-1 34 310 220 52 63 48 290 38 35 41 65 240 48 40 44 54 75 39 39 260 300 93 110 76 76 110 E 0 E-2 E-1 E-1 E 0 E-1 E-1 E-1 E 0 E-I E-1 E-1 E-1 E 0 E-1 E-1 t-1 X-1 E-1 E-1 X-I E-1 P-1 9 0 E-1 Approved by¶*. 4 ..l ..t .- 48 n.j .,i1$1$1*~
I *ii ,, 4' -q i% ,l.. ...~fll I .,.11. -'l Iklt** I1**111EI*1*
.III I, ll I l *l I * *, .I1 .1. .... ... ..........
..5... 0....I.. ..b.....ie i D.E.8icCurd
- 3.
Ric-hard--m ic-h- -bv'y 8- 9 5-9-.t if Page 701..............
MAILIED YA+/-*KEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY Initial Analysis Report Customelt:ýVermoPgt Yankee Nuclear Power Corp.A .nTU E KEEGAN MR. ED14ARD CUMhING MR. STEFHEH SKIBMIOWSKY Report Date: Analysis Date: Date Received: Reference Date: 06/09/88 6 /a /88 6 /S /88 6 /0 /68 Sludge Sample Amount: 0.99 Kg. Lab Sample No.: G72972 Sample Submission Code: VSL 04 2388 Elapsed Time : 0.59 days Other Analysis Requested:
None Comment: MAIN TANK BOTTON DECAY ACTIVITY NUCLIDE COliC. +- I SIGMA MDC CORRECTION Pico Curie / Kilogram -wT I Np-239 8.40E-01 ( 2 4- 21 E 0 70 E 0 Co-57 9.98E-01 (-10 +- 19 E-1 62 E-1 Ce-144 9.99E-01 ( 12 4- 14 E 0 45 E 0 Ce-141 9.87E-01 (-12 4- 32 E-I 110 E-I Mo-99 8.63E-01 ( 20 +- 38 E 0 120 E 0 Se-75 9.97E-01 ( 34 4- 29 E-1 97 E-I Cr-51 9.85Z-01 (-25 I- 1S E 0 61 E 0 I -131 9.50E-01 ( 3 +- 23 E-I 78 E-1 Be-7 9.92E-01 (-20 4- 19 E 0 65 E 0 Ru-103 9.90E-01 (-10 4- 24 E-I 81 E-1 I -133 6.26E-01 (-25 4- 37 E-1 120 E-1 Ba-140 9.6BE-01 (-23 4- 11 E 0 37 E 0*+ Ce-134 9.99E-01 ( 130 +- 22 E-1 48 E-I Ru-106 9.99E-01 (-1 4- 28 E 0 93 E 0*+ Ce-137 1.00E 00 ( 1207 4- 52 E-1 130 E-1 Ag-l10M 9.98E-01 (-8 4- 53 E-I 180 E-1 Zr-95 9.94E-01 (-77 4- 59 E-1 200 E-1 Co-58 9.94E-01 (-11 4- 34 V-1 110 E-1*+ Mn-54 9.99E-01 ( 393 4- 43 E-1 120 E-1*+ AcTh228 .I.00E 00 ( 39 1- I2 E 0 32 E 0 TeI-132 8.815-01 (-7 4- 29 E 0 99 E 0 Fe-59 9.91E-01 ( 68 4- 73 E-1 240 E-1*+ Zn-65 9.98E-01 ( 527 4- 82 E-I 230 E-1*+ Co-60 1.OOE 00 ( 853 1- 22 E 0 14 E 0*+ K -40 1.ooE 00 ( 223 4- 35 E 0 110 E 0 Sb-124 9.93E-01 (-12 4- 35 X-1 120 E-1 Notes:* Activity greater than 4 Peak is found 3*standard deviation Approved by..... .......... l.l. W e.l- ,.............D.*M.cCur~y*
Richard Emch -bvy 89 59.tif P age!1 ,10ýý-__,.-
...........
--111.1- ..........
... 1 1 .. ................
YANKEE ATOMIC ELECTRIC COMPANY EN4VIRO1MENTAL LABORATORY Initial Analysis Report Customer :",Vermont Yankee Nuclear Power Corp.Attqntioný.'MIAIEl
ýINE KEEGAN MR. ED1ARD CUMMING M1R. STEPHIEt SK]BI1IOWSKY Report Date: Analysis Date: Date Received: Reference Date: D6/20/88 6 /15/88 6 /14/88 6 /8 /88'Septic-Solid Sample Amount: 0.06 Kg. Lab Sample No.: G73075 Sample Submission Code: VSLs04 2388 Elapsed Time : ?.57 days Other Analysis Requested:
None Station No.: 04 Main Tank Bottom DECAY ACTIVITY NUCLIDE CONC. +- I SIGMA MDC CORRECTOION Pico Curie / Kilogram...........................................................................
Np-239 1.O7E-O0 Co-57 9.81F-01 Ce-144 9.82E-01 Ce-141 8.51E-01 11o-99 ilo5E-01 Se-75 9.57E-01 Cr-51 8.27E-01 I -131 5.21E-01 Be-7 9.06E-01 Ru-103 8.75E-01 XI -133 2.49E-03 Ba-140 6.64E-01*+ Cs-134 9.93E-01 Ru-106 9.86E-01*+ Cs-137 1.00B 00 Ag-ISOM 9.79E-03 Zr-95 9.22E-0,1 Co-58 9.29E-01*+ Mn-54 9.83E-01*+ ACTh228 1.00E 00 Tel-132 1.99E-01 Fe-59 8.90E-01*+ Zn-65 9.79E-01*+ Co-60 9.97E-01*+ K -40 1.00E 00 Sb-124 9.17E-01 Notes:* Activity greater than 3*standa:+ Peak is found x Decay correction less than .01 55 (-9 ( 3 ( 137 (-60 ( 85 ( 14 (-6 ( 12 (-2 (-86 ( 166 ( 12 3824 ( 76 (-2 ( 12 1126 ( 76 (-14 ( 7 ( 120 2240 ( 472 ( 69 4- 25 4- 30 4- 22 4- 60+- 29 4- 51+- 36 4- 74 4- 38 4-46 4- 40 4- 52 4- 49 4- 92+- 96+- 11+- 60 4- 74 4- 17 4- 22 4- 14 4- 14 4- 22 4- 53+- 61 E 2 E 0 E 1 E 0 E 2 E 0 E 1 E 0 E 1 E 0 E 0 E 0 E I E 0 E 0 E I E 0 E 0 E I E 2 E l El1 El1 El1 EQ0 85 E 2 99 E 0 74 E 1 190 E 0 97 E 2 170 E 0 120 E 1 250 E 0 130 E 1 150 E 0 130 E 0 150 E 0 160 E 1 200 E 0 320 E 0 36 E 1 200 E 0 200 E 0 49 E 1 75 E 2 48 E 1 40 E 1 23 E 1 160 E 1 200 E 0 rd deviation Approved by D.E.McCurdy.
... ...... ........ ..4.t b **Ch ...y 1 .,. .....p.t ......hf, 40 ..t *.44.I.. '; .a 40.J nftl'. l' Richard Emch -bvy 89 59.tif Page 72.j r\AAILLL'ii 0 YANY, E ATONI C ELECTRIC COMPANY ENVIRONMENTAL LABORATORY Initial Analysis Report CustoNFI.:
- Yer~on..A~an1ee Nuclear Power Corp.Atten ion: "MS. ELAINXE KECGA MR. EDWARD CUMJ-IING MR. STEPHEN SKIBNIOWSKY Report Date: Analysis Date: Date Received: Reference Date: 06/20/88 6 /15/88 6 /14/88 6 /a /as Septic-Liquid Portion Sample Amount: 1.00 Kg. Lab Sample No.: G73074 Sample Submission Code: VSLI04 2388 Elapsed Time : 7.57 days Other Analysis Requested:
None Station No.: 04 Main Tank Bottom DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC CORRECTION ( Pico Curie / Kilogram I...........................................................................
Np-239 1.07E-01 Co-57 9.81E-01 Ce-144 9.82E-01 Ce-141 8.51E-01 Mo-99 1.51E-01 Se-75 9.57E-01 Cr-51 8.27E-01 I -131 5.21E-01 Be-7 9.06E-01 Ru-103 8.75E-01 xI -133 2.46E-03 Ba-140 6.64E-01 Cs-134 9.93E-01 Ru-106 9.86E-O1 Cs-137 1.00E 00 Ag-I10M 9.79E-01 Zr-95 9.22E-01 Co-58 9.29E-01 Mn-54 9.83E-01 AcTh228 1.00E 00 Tel-132 1.99E-01 Fe-59 8.90E-01 Zn-65 9.79E-01 Co-60 9.97E-01+ K -40 1.O0E 00 Sb-124 9.16E-01 Notes:* Peak is found X Decay correction less than .01 ( 142 +- 88 (-16 +- 99 ( 60 +- 73 ( 15 +- 19 (-123 +- 94 (-6 +- 15 ( 3 4-- 11 (-6 1- 20 C 37 +- 98 (-S +- 13 (-23 +- 23 (-9 4- 15 ( 1 +-12 ( 21 +- 14 (-20 +- 18 29 +- 23 ( 20 +- 13 ( 3 4- 13 ( 28 4- 61 ( 25 +- 37 (-1 4- 25 ( 31 4- 26 (-13 +- 22 ( 34 ÷- 21 68 4- 30 E 0 E-2 E-1 E-1 E 0 E-1 E 0 E-1 E-1 E-1 E-1 E-1 E O E-1 E-1 E-1 E-1 E-1 E-1 E 0 E-1 E-1 E-1 E 0 E-1 290 E 0 330 E-2 240 E-1 63 E-1 310 E 0 50 E-1 36 E 0 67 E-I 330 E-i 44 E-1 77 E-1 49 E-i 41 E 0 47 E-1 59 E-I 75 E-i 43 E-1 42 E-1 240 E-I 120 E 0 82 E-i 86 E-i 86 E-I 75 E 0 100 E-1.4*..*I*t1**Lh...~.S.d,(tbCb...46...tI..d,..V
.. +/- 9. .*0 *41. f 4 9 1&t.
- I -.Approved by D.E.McCurdy.
Richard Em c h -' b-"y- 8 9-"59tif.a7
..................
Mr 1L-.: YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY
--Initial Analysis Report Customer :y/(e;mont Yankee Nuclear Power Corp.A KEEGAN MR. EDWARD CUMMING Report Date: 07/11/88 Date Received:
6 /14/88 Septic-Solid LAB. No. DATE ACTIVITY*SAMPLE CODE of VOLUME NUCLIDE CONC. +- 1 SIGMA MDC REFERENCE ANALYSIS Kg [ Pico Curie / KC -DRY S73075 6 /8 7 /7 0.022 Sr-90 (-14 +- 37 )E 0 40E 0 VSLs04 2388 Main Tank Bottom Sr-89 ( 52 +- 46 )E 0 62E 0 Notes:.00 quoted one-n. tg terms include only counti4 statistics and do not represent the propagation of all possible error, associated vith the radioactive decay process. t. Etimtes of the additional systesatic and random uncertainties are: calibration curve, -5 percent, and ample positioninS.
- 2 percent.Apppoved by D.E.mccurdy.
Richard Emch -bvy 89 59.tif Page_74.... ... ... .. ..... .. ...... ..... .. ... .. ... .... -.. ..P a e 7 4...........
Nv1A ILL YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY-Initial Analysis Report Customery-Vermont Yankee Nuclear Power Corp.Att .EARINE KEEGAN W'I~ MbWARD CUMMING Report Date: 07/11/88 Date Received:
6 /14/88 Septic-Liquid Portion LAB. No. DATE ACTIVITY SAMPLE CODE of VOLUME NUCLIDE CONC. +- 1 SIGMA MDC REFERENCE ANALYSIS Kg [ Pico Curie / Kilogram S73074 6 /8 6 /19 1.002 Sr-90 ( 113 +- 98 )E-2 200E-2 VSLI04 2388 Main Tank Bottom Sr-89 (-10 +- 11 )E-1 22E-1 Notes: AppxQayed by*e quoted onbe-sigma tern include only countingn flatiftic, and do not represent ge propagation of all possible errors *soiciated i h the rodioa.tive decay ,oe:s.. Estiate. of the additional
- yn:rtic and randoa ,ncertaijttes arec calibr-tion curve.
- S p-e1enr1 and .ample po.itioning.
-2 percet,.-----y---\-D.E.McCurdy.
Richard Ernch -bvy 89 59M Page 7f CLA, YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY-Initial Analysis Report YAU C Yankee Nuclear Power Corp.Attention:
MS. ELAINE KEEGAN MR. EDWARD CUMMING Report Date: 07/11/88 Date Received:
6 /14/88 Septic-Liquid Portion LAB. No. DATE ACTIVITY SAMPLE CODE of VOLUME NUCLIDE CONC. +- 1 SIGMA MDC REFERENCE ANALYSIS Kg C Pico Curie / Kilogram H73074 6 /8 6 /20 0.003 H-3 C 26 +- 15 )E 1 49E 1 VSLI04 2388 Main Tank Bottom Notes: Apprq9ed by -The quoted one-s ig. ter-s ijClude only co.ntift s1atilctic ad do not represe.t the propagatioi of .11 possible error- .s.ot.a.ed vith the rodi..actne decay""prooess.
Estisate.
of the additional systematic and random oncertoln ties are: oslibrotion corn.e
- 5 percent, lnd ample pos..ioning.
i 2 perce.-.r--D.E.IMc' rdy.)
Richard Emch- bvy 89 59,tifP e7 APPENDIX t Computer Code Outputs This section contains copies of the computer in the calculation, as follows: B.1 ALLEGRA -Ganma Ray Spectra B.2 DIDOS-V -Dose Reduction as a Result of B.3 ATMODOS -Radiological Impact During VY Site code outputs employed Plowing Control of the Disposal B.3. 1 B.3.2 B. 3.3 B. 3.4 B.3.5 B. 3.6 Impact Impact Impact Impact Impact Impact due due due due due due to to to to to to Mn-54 in the Septage Co-60 in the Septage Zn-65 in the Septage Cs-134 in the Septage Cs-137 in the Septage All Nuclides in the Septage B.4 ATMODOS -Radiological Impact After Termination of Vermont Yankee Control of the Disposal Site (All Nuclides)B.5 ATMODOS -Unplowed-Land Dose Conversion Factors for Radiological Impact Assessment B.5.1 B.5.2 B.5.3 B.5.4 B.5.5 Impact due Impact due Impact due Impact due to to to to 1 1 1 I 1 uCi of Mn-54 uCi of Co-60 uCi of Zn-65 uCi of Cs-134 uCi of Cs-137 Impact due to B-1 6680R w C)ALLECRA (ADIOACTIVITY CARD 3E0.3 6 7 10 0At;NA SPECTRA -0010(6-2 DATA PAS0 -E07(00;01EC iJG INC, -B;OO 01 OA/ 2,.08) 0<63.P TAPE 4 1NFUT DATA LISTING 1 2 ,4 .5 6 ."
670970 345620901fl4-62'901234S678 0 012Z34C6,70 2345;679 VY -DISFOSAL OF CONTAMINATED 00WAG0 -FIELD ACTIVITY 601t( 40 TANK ;Ur;rI;JGS o 1 1 1 1 1 6 0 2-1 1 0 0 1.0 1.0 0.0 0.0 1.0 0.02.831E-06 C060 "70600 .3;3E-04:"65 390650 .0
- fO! -O6 00134 551340 47E06 CS137 ,.130 9. 8A137M 561311 9,7Z90-05 C)0, 2 2 0, 0, e 0 C-~1 0, to, SI Ott, 0 H to, C)On->~
00 ALLEGRA (RAIIIACT;VITY I GAMMA SPECTRA -ORISEN-: DATA DASE -EATECH EuGIHEERING.
JAC. -"SI, E OA/8S) SS/06;3S.
01, 0 VT -DISPOSAL Or SEWAGE -FIELD ACTIVITY AFTER 40 TANI, FUMrINGS USER-SPEC~rIED PRINTOUT CONTROL FLAGS: AUCLIIES IN LYPRARY 1 KRRINTCIT
.o DECAY DATA IA LIDRART : PRINT(21 -GAMM SPECTRA IA LIPRARY K NPRINTT1)
'I CALCULATED ACTIVITIES I RIRINT(AI
-I ISOTOPE-SPECIrPC SPECTRA I RPRIUT/25
-I TOTAL AMNHA SPECTRA I KPRINT I TAPE II CONTENTS KRFRI ITNT? !TAPE 12 C ON1TENT " IPINTMY o INTERMEDIATE DECAY RESULTS KFIT IN T19)DATA LIPRARY SELECTION OPTION INPUT ACTIVITY UNIT CONTROLD I SA.MA SPECTRA CONTROL FLAG I 3SURCE VOLUME (CUPIC METERS) -I.ToS0EAT 3OURCE INTENSITY INPUT MULTIPLIER I I.00SE0Go0 MIM. ISOTOPIC ACTIVITY FOR INCLUSIOA IN THE OUTPUT TADLES .00GOE100 TOTAL NUMPER OF NUCLIDES IN TAE INPUT
- A LIST OP INPUT NUCLID'ES AND ACTIVITIES ICURIES): Z,0540 :.831E-O6 270600 7.3:;3E-04 30oaS 2.0011E-T
.OLLCOAA (RADIOACTIVITY I 064194 SPECTRA -0(10(6-2 DAT4 14ASE -(447CC4 CENGINEERING.
INC. -COD, 01 06e/04 6/04/30. PACC VT -DISPOSAL Or CONTAIIINATED SEWAGE -FIELD ACTIVITY AFTER 4A T5444 rUMPINOG DECAY CONSTANTS (I/(R). F 0ANCH10G F(ACTIONS AND DAUGHTER F"OUCTS -TAPC 10 PCr(AAT!01 DATE: 06/06/Z.MUCLIDE DECAY CONST REIA-0(NDI (TA-MCTA FOS-GSrN POS TA 1 SOn1ERT& 41T.. (0. 6(rl06401 S!CNY.Fis MN :4 9.24196E-05
.00000 1 Oo0E-OO .000400 OOOE-0O .0004+00 .000+O0 .000(400 CR :;4 CO 60 1.500O0-E05 I.000(E00
.0OE+400 .000+0 .000(400 .000*400 .000C00 .000(00 .00(E00 M2 60 265 1.18430-04
.000(40 .I000E40 l.O000000 .O000(00 .o000000 .0000'00 .OOO.00 .So0 Cu 65 C3134 3.93464E-03
.1000(A00 o000E(O0 .000(400 .4000400 .000(400 .O00Eo00 D050+00 .00O0(00 PA134 C5137 :.63562E-06 S..00E-02 9.460C-01
.000(400 .000(400 .000(400 .00000 .000E400 .000(.00 6A437 P4137" 4A137$ 1.6,967(+01
.00(E+00 .000 E400 .000400 .000(00 1.000(400
.000(00 .000000 .000(100 p6137 TOTAL NUMPER OF RADIONUCLIDES IN THE DATA LIBRARY 1030 t2 C)
P-tJ"8 agvd -C03-ford"DNI HM3IN3-0 1~ 'a 0 = 2 00oo oooo 0 0 000 o~o.000 oooo 0000 0000 ooo. o0000 0000 0000 ooo oo o-o.I-X oo1 0000 oo 0 00o 000o 0000 I A::' Z c 2 0 0~ C 0 0 0 0 0 '1 2 0 O C O 2-. 0 0 2 0 0 O "I 0 0 0 0 0 0 O CI C I~o 0-, 0 O 2 o o..................
...... .. .............
Q9~6 Bd -~ -~ -J! ..Aq -L4o-w'qpi2Lq3iýJ CL)cm VY -DISPOSAL OF COHTAMINATCV SE-GE -FIELD ACTIVITY ArTEP 40 TANK Pumr[mGs DECAYEDr RADIOACTIVITY AS 4FUNCTION OF TVtlE (HRSý[B NUCLIVE C0 60 2.3530E-0C CO 6Z 2. 00E-06 c0134 1.4570E-06 CS 13 9.3 900-05 P-137A 6.?7t0E-0T lb. ,
ALLECA (RADIOACTIVITY 0 GAIMMA SFECTRA -DRIGEN-:l lATA PASE E-ITECH EGJOIVERE11G.
TAC. -NOT 0T 061ZV/s/ ) 90/06/30.
FATE 6 VY -DISPOSAL Or CONTAHMTATEI.
SE.AHO -FIELD ACTIVITY AFTER 40 TANK PUMFIFGS RADIOACTIVITY TOTALS (CURIES) AS A FUO4CTION OF DECAY TIME (MRS)NUCLIDES AITT ACTIVITY> ,GTDE00 (USEE-S-PECEFEP LIMIT) AL. .UCLD.ES RENCOUTERED IN) THE ANALYSIS T(HRS) NOP. OASES HALOGENS OTNER TOTAL GIVEN F1I0 NO. OASES HALOGENS OTHER TOTAL GIVEN) YIN.0O0C.OH .0000E.00
.00DOECOG A.2=57E-O4 4.--ZT-EGA A.:TE0 .OO0OE)00
.000E0C.00
- T-O 4.-.2-E-04ATET NUCLIDE MIO CONSISTS or .0 Z HOPLE GASES. .0 X HALOGENS.
AND 100.0 Z OTHERS hNf OLLCGOE (RADO1ACTIVITT I SAMMA SPECTRA -08R1GE-: DATA 14ASE -E(41ECH EAIWEERIGO.
INC. -,101 06/1:/,B)
BB/06.30.
tAE 7 VY -DISPOAL OC CONTAMI4NATE0 SEWAGE -FIELD ACTIVITY AFTER 40 TANK PUFoPINGS IS-GPOUP GAMMA ENERGY RELEASE RATES (PEV/SEC)
AT S -.000E000 HOURS MUCLIFE ACTIVITY .0100 8EV .0220 MEW .0372 8EV .0;7: HEV .0820 R4EV .1:0 MEV (CURIES) .225 8EV .372 ME. .57, HEV .8;O MEV 1.-;0 8EV 1.720 8EV-.250 MWV 1.720 MEV 3-.00 MCV 2.000 MEV 7.000 .EV 9.000 MEV TOTAL 8104 2.831(-06 1.446E(02
.000400 O00OE+00 .0006400 .000E.00 .000+00.000(400 .O00E*00 .000(:00 0.243El04 .O000(00 .000E400.000(400 .000E400 .O00E400 .000400 OOOE O0 .000+E00 C .720(404 CO 60 2.3:3E-04
.000400 .000E00 .000E.00 .0004+00 .O00E400 .000E(00 2.000(00 2.2.:0004:10.00(40
.46 02 2.1,77(07
.000(400 2.076(E02 7.053-0l .0000400 .000(400 OOElV00 .000(400 7.177(407:N265 .8018-06 .:27E(40 .000E:00 E0 .00000 .000(400 .000(400.000E(00 1,068E00 3.E47E403 2.396VE00 2.806(404 .O00E400.000(+00 .000(+00 .000(400 .000(400 .000E400 .000(G00 6.026(404 CS134 1.4,2E-06 2.140E-01
.004E+00 1.330E401
.000(400 .000(400 .O00E400 2.753(400 2.;7E400 3.937E+04 4.042(+04 3,828E403
.000(400.OV0EVOO .000(00 000E+0 .00VEV0o .OG0EV0O .000E(40 0.373E404 C(137 9.259E-05 .O00(400 .000(+00 .O00E+00 .000E(00 .000(400 .000(400.000(400 .000+(O0 .000E(00 .006E400 .0000400 .000(400.O00E000 .000o(40 .000E400 .000(+00 .000(400 .000(400 .000(400 8437M S.?$9E-O 1.2364(02
.000E+00 7.9120403
.000(400 .O00E400 .000(400.000(400 O00(E+00 1.919EE:6
.000V00 .000(400 .000(400 000000 .0000400 .000(40 O000 000(00 .000(400 1.9:1(06 ZL Mt 0)-T--.2 VY -rtISFOSAL OF CONTAMI-TEII SEWAGE -FIELD ACTIVITY AFTER .0 TANK PUMPINGS GAMMA ENErOY RELEASE RATES (HEUV/SECI
-ALL OTHER THA14 GASES HALOGES -(0, 0. 100)As a ruwcTioN or PIECAY (HOURS) -kIGEN-7 GAMHA ENERGY GROUrS E (MEV) .0100 6.2507E+02 2500 OOOOE+O00 ,.0373 7.V--0E.03
- 0 07' .O0OE00E0 OT 0000E400* 1-50 *0000E'00.753O 4E,0O Is 0.9603E406 I.7!0"' 000, [÷:401:0, I.7:;00 OOOOE+00-,100 *1006E0020 7500 0.0000 *0000E+00 00 000 7.0000 OO000E÷O0 TOTAL 2.39.26t407 IV (b 64 00C
'o* rT ALLEGRA (RADtIOACTIVITY
£ GAMMA SPECTRA -ORIGEN-* DATA VASE -(6TCH INC. -no, 01 06/22/68) 88606/30.
VASGE VY -DISPOSAL OF CONTAMINATED SEWAGE -FIELD ACTIVITY AFTER 40 TANX F'UMP0 GS GRAND TOTAL GAMMA ENERGY RELEASE RATES (KEV/SEC)
-NOPLE GASES, HALOGENS AN14 OTHERS -(100.100.100)
AS A FUNCTION F DEECAY TItE (HOURS) -0]OK0E-2 GOA)))A ENERGY GROUPS EC(MEV) .000CE400*.0100 6.2567E402
.0-50 .0000E00.0375 7.92500403
.7057 .000oor00.0865 .OOOOEHOO.1250 .0000EAO0.2250 7.7534E400
.3750 2.3311EA02
.57,0 1.9603E4060!i.2000 2.l68EA[07 1.7z00 .0000E+00 2.250 2.07A64E402 2.7500 7.65560-01 3.5000 .OOOOE*O0 0.000 .*O0050O0 7.0000 .O:000EO0 9.0000 .OOOENO00 TOTAL 2.39'6E407 (b.or"o C)D wc ALLECEA (RADIOACTIVITY 9 GAMMA SPECTRA -ORIGEN-2 DATA PASE -(NTCH EIJGINEEI"NG.
INC.- MO 01 06/22/988 88/06/30. (AGE 10 Vy -Or CONTAMNHATED SEUAGE -FIELI ACTIVITV' AFTER 40 TAN4K FUFIAKGS GAMMA RELEASE RATES (i;[V/SEC)
-USER-SrECGFIEE
';IX -800. sAL. 0THER) -.0. .0.100.0'AS A FUNCTION Or DiECAY TIME (HOUNS) -OEIGEN-2 SuAtA [EERGY GROUPS r (MEN).0 00.0_O*.0250.0375.0275.0950.3750!.5750.8500 1: 500 (.7200 2.7500 2.5000 5.0000 7.0000 9.0000 10T41.0000 000 6. 1587[ 402 7.92ý0E+03.O000E+00.00004+00.0000(400 7,7534E400 2.3311[+0' I .YA03E+06 2. (928(007 ,0000OR $00 2. 07 ,,:.29E-01
.0000E+00 200007400.O0000(E00 2.30 00 ,.3926E+07
~tit C0 S1466 E100 OF ANALYSIS 600*84
~I 10-V CC.L114t'&ICAL RADI2ATIO S04OURCE 1.001 VI;EVIR* E;TTECH EWITE J.VLEAToVIC
-V0l. 01 -68/I5:6 007-0:. P AGE I INPUT 1.ATA LISTING -TAE 4 ARD 4 7 3 560.
I or -DIS0 .0 CONIVi;. EW44GE -ACTI. rpoM 40 PUIsPoUT0SC ACRES -UNPLOEV' LAND, 0 6 1 oo 10o0 .0 3 ..0 150O.0 0.001 or 4 00 2:0.0 0.001 C 1 .0 0 o -1 .o (0 x ato flOS-V {CYLIIlDRtCAL RADIATION
$0URCE DOSIETRV)
-EITECH I;4OlrJr.
ING"y4;Kr TOi;:C -41:0[ O0 -io/1:,'B6
,;;: GE.INPUT DATA LISTING -TorE I1 C,(1% 1 2 3 4 .- .a SE0. 12343,678901 I Vr -1IS0YOAL OF CONTAIlIN7T44D SEWAGE -riELD 0OU1L0k1UoI:
ACTIVITY (I;0vIS0CI TI2 11 CMRS0 .000E400 3.700E-02 3.7.:00-01 3.7300-01 8.300-01 1.:300400 2.230E100 4 .972:1403 1.33104 1.960E006 1.10490+ E 0.I80 C-072" f;G 2 t'2 11OS-V (CYTLINDRICAL RADIATION SOURCE VOSIY;ETRYI
-ENTECH E14GICEERIriG,.'OAIJEE 41OIr;C -4010lI -,S.RA C S0/OT,'O-".
PAGE VT -D0SP. Or CONTAH. SEWAGE -ACTOU. FROM 40 PUlCPSUTS/2 ACRES -UNCPLOWED LAND RECEPTOR S T1ME (MRS) -.00-I SOURCE DESCRIPTION UPRIGHT CIRCULAR CYLINJDER MATERIAL -RADIUS CRETERSC 1 :.600E00 HEIGHT (METERS)SSLUi;E (CUPD.;.)
-TUA6ECQI DEITT (GC/CC -r1+F10); SOURCE RCTEHOSTo FOR IV DEFElrCIENT ANA LYSIS -ZOURCE IENTEMSIT' INPUT 'IULIILIEk
-H1AN ENERGY 01Fr FOR 1141EFENl('EIT A.ALYSIS (CEECEJT)
-NI CONTAINER MATERIAL DENSITY(CG/CC)
RADIUS (H) HEIGHT (41)HOWE AIR C.000£-G3 I,-93E-03.000E 00 I. 36E-01 O00G.E 40 RID. IHICRIJESS 00 AN SHIELD SLAPS MATERIAL ANR It DOSE POINT DESCRIPTION ELEVATION RELATIVE DENSITY (O,'CC) THICKIIESS (C)I.293E-03 RECEPTOR 014 AXGS TO LOWER END OF SOURCE IC;ETERS)
-ANGLE (DEG)DELTA 2-PIIENSGIGIAL ANALTSIS I .001E400 tI~0 t'2-o 0 t62 0 1 b.q t61~tI,-Az 0 Na RESULTS O ROUH R 4 ENEROY (REV).036 2.2:r0 ADJ. INTENS (IiEV/S-1;3) 9.79.ýC:02
- 2. 681[0 A 2.4AS330400 I.Z87 E.04 2.6190)06 2.A66Ef0l SOURCE ATT COEr I1/H)3.423E-02 I. CH-02 1.0600-02 6.6870-03 7?35E-03 5.3NBE-G3 CONTAINER HUNT RAD IAL -AXI L.000 .O00.000 .000.000 .000.000 .0.0 GIG0 .000.O00 0 0OO SHIELD.000.000.000.000.O000 OVERALL PUILDUF 1.737E400 1.330E+00 I.H41E 00 1.163E 00 1.13!E.O0 I.O2E +00 INTORL VAL AITH PLDUF..443E-03..4640-03 2.400!-03 2.37,E-03 2.36:E-03:.367E-03 TOTAL DOSE TO AIR I :009E-09 9.94 10-06 6.SlE-09 9.7;3E-07 8.0520E-2 1.060E-06 MAXOIMUM PATH-LE1ATH USGD ON ANALYSIS Cl;PP) -10.0 I * .I v
- a a t .END Of PROPLEG & I .6 S a 6 ..N a: 00~cn DPOS-V ICYLINDRICAL RAOI)ATI0H SOURCE 1031i;SETRY
-E;TECH ENGIIJEEI4G/'YANI-EE ATOKIC 11l000 01 -10/1:;,'86 86/07/0:.
PAGE INPUT 4ATA LISTI;G -TAPE 4 I. :P1 ; 3 4 6 ;"8 U34-676901
-:347670701
- "34:6769 I: 1347670901
- 347676'0 I 00 -D1St. OF COtlT-;. SEWAGE -ACTI10. rRE; 40 PUi;pOUT3'.
ACRES -FLOWED LAOOP 1 0 6 1 : 1 0.0 G.0.3.E-04 3.0 70.0 3 3 1.6 1:0.0 .1: 3 1.6 1;0.0 1:;5 s.15 -1.0 C)CCD D21O$-V (CYLINDRICAL RADIATION SOURCE POSTUItRC ) -E14TECH ENk0GJJC(8NG/YAUJZLE AlN1;:C -(6OD 03 -10/1ý/A6 ) A8'07,D. PACE ImPuT DATA LISTIU0 TAPE I I CARD 1 2 3 -7 SEO. 1 :346710901
- 34:91:467T2 C391 6ls 78901 :34fl7S901 234:;d7eq01 234-,67990 I VT DISPOSAL OF COI4TA11INATED SEWAGCE -FIELD (OUILIDFIUI; ACTIVITY (8;EV/SEC) 2 TIU C(MRS$ .00OOE4 3 3 a.:oE-0: 322OE-01 72.720E-CI 8.200OE-0I1.OEC E.2(0 4 7:92:2E+03
- .33IC4CZ I2AEO I.28E80 ..1307 .076E80 C)"'I TbH C)D (o
- c)(0)ay Cr1OS-V (CYLINDRICAL RADNATION SOURCE DO3IC;ETRY)
-00TECH E0G0014ERING/';uKEE ATOf;I: -(I;OD 01 -10'15/86 3 6/00,o:. PAGE 3 UF -D1S1. Of CONTA0 .SEUWGE -ACTr1. FR09 40 rurrCGTus/:
ACRES -FLOWUD LAND RECEPTOR I TlIE (MRS) -.00-) SOURCE DESCRIPTION UFR0GHI CIRCULAR CYL1IA[COR MATERIAL -C014CRETE RADI1US (CIlETES)
-I .2000)402 HEIGHT (URTEkSl VOLUIC (CUC.I.) -1.00.0004 E)15TY (G,'CC -MINIICUM SOURCE IWTEASIT' FOR IND~fE)VEDNT A4AALYSIS SOURCE I4TEITY 114FUT IIF U LTIFLIRk -MAX ENERGY 11FF FOR IWADFENIENT AN4ALYSIS CFCYCECJT)
-2t CONTAINER MATERIAL DENSITY(G/CC)
RADIUS C);) H00GET (,C I.:ooo-ol I .600E400.0000)00 3.23-0-04 3.0GOOF)00 RAn. TAICIOAESV
'K)HONE A- SHIELD SLAPS MATERIAL DENSITYCG/CC)
TEICK;JESS IH) ANGLE IEG) DELTA AIR 1.293E-03 PS 11000 NT 0 DECRIPTION RECEPTOR OC AXIS -DIUENGIONAL ANALYSIS ELEVATION RELATIVE TO LOWER R14O OF SOURCE (ERTERS) -1.12OE0)0--I Ott'-.0 291 Ott'C)H 0'3 z C)cIY~0 AN RESULTS GAMMA GROUP ENERGY (HE)).039.37: 1.220 I r V0 ADJ. E(4NS5 (H;EV/S-)(3C
- 6. 28E900 1.200C-0I I .!200A02 1.7900+04.IGtE-O0 SOURCE ATT C0EF 'I/t))1.114.00: E+.3Z1V01 I. 10, 0) I 9.1094 00 6. 74:0)00 COI"TAIIJER MU0)RADIAL -AXIAL.000 .000.000 .000.000 .000.000 .000.000 .000.000 .000 SHIELD OUERALL sUf ,UVILDUP:000 1.2710)00*000 .0 00 .7440.000 2.0140E00 000 l :I2,O.0 00 1.7010)00 1I)GRL VOL WITH OLDUE 6.19 1-03 2.2770-0 2 9.6609-02 9.613E-0, TOTAL DOSE TO AIR l.7U10-1l 2.4A20-12 2.162-000 1.4 34009 2.390E-07 2.1790-12 2,6290-0'MACInUM FACH-LENOTH USED IA A14ALYSIS CUFF) -20.0 9 .1 * .&
- It 0A r E14D OFRCDLO9 .A A A 9 1 A
.R i.chardEm ch -..59. f .............................
I 5 B.3 ATMODOS -Radiological Impact During VY Control of the Disposal Site Presented below is a partial listing of one of the ATMODOS Tape 5 inputs used in this portion of the calculation.
It corresponds to the output in Sec. B.3.6 below. With the exception of the nuclide data library, a large portion of which was deleted due to space limitations, the listing is complete.The Tape 5 listings corresponding to the outputs in Sec. B.3.1 through B.3.5 are similar, except that a single isotope was analyzed in each case. Also, the tables with the detailed pathway/isotope/organ exposures were excluded from the output.I IVYPI VY STANDARD PROGRAM INFORMATION FILE VY -SEWAGE OONTAM -SOLIDS 1% BY WT -2 ACRES -SHIELD F = 0.012 -104 HR OCCUP 1. .200 44.56FRESH
.500YESNO NO 0..012 1.NO NO NO 0.1.00--EOR----EO)F--0 2VYGASRLGAS SIR VY 87 1 1 0 87063023: MN54 4.132E-6 25 MN 54 0060 2.511E-4 27 0X 60 ZN65 4.502E-6 30 ZN 65 CS134 1.715E-6 55 CS 134 CS137 9.366E-5 55 CS 137--EDR----EO)F--I 5QUEIY PATHWAYS:
SIIORE(1,2,3),BND,ROAD,RES1,RAD,MFAT,GOAT,COW SHOREI YESYES SHORE2 YESYES SHORE3 YESYES BOUND YESYES ROAD YESYES RES1 YESYESYESYES RADIUS YESYES MEAT YES7ESYESYES YESYESYES GOAT YESYESYFSYES YES YESYES OOW YESYESYESYESYES YESYES--EOF--ENTECH ENGINEERING, INC.P101-EC3 -Page B.3-1 Richard Emch -bvy 89 59.tif Page 94 1 6VYUFMAXVY MAXIMUM INDIVIDUAL USAGE FACTORS FOR STANDARD 520.00 64.00 310.00 110.00 21.00 .00 .00 630.00 42.00 400.00 65.00 16.00 .00 .00 520.00 26.00 330.00 41.00 6.90 .00 .00.00 .00 330.00 .00 .00 .00 .00--EOR----EOF--PFORBLENS 12.00 67.00 14.00.00.00.00.00.00 1 7VYGSD VY MAX INDIVIDUAL GAS SITE DATA 2.00 240.00.00 8766.00 0.0 1440.00.00.00.00 1.0 5.60--EOF--2.00 240.00.00 8766.00 0.0 24.00.00.00.00 1.00.00.70 240.00 48.00 8766.00 0.0.00 50.00.50 1.00.00.00 2.00 240.00 48.00 8766.00 0.0 2160.00 50.00.00.00.00.00 FILE FOR.70 240.00 48.00 8766.00 0.0.00 6.00.50 1.00.00.00 STANDARD PROBLEMIS 2.00 240.00 48.00 8766.00 0.0 2160.00 6.00.00.00.00.00.70 240.00 480.00 8766.00 0.0.00 50.00.50 1.00.00.00 8000.00 8000.00 3700.00 1400.00 2.00 240.00 480.00 8766.00 0.0 2160.00 50.00.00.00.00.00 ENTECH ENGINEERING, INC.PIOl-EC3 -Page B.3-2 I Richard Emch -bvy 89 59.tif Page 95g,...............
I 8ISTPNBLNUCLlDE LIBRAY FOR ALL DO)SE PRLMRANS 89 1 3 1.78E-090.OOE+OO0.OOE+O0 H 9 .OE-01 9.OE-O1 9.OE-01 9.OE-O1 9.3E-01 9.3E-01 4.8F-00 0. 1.05E-071.05E-071.05E-071.05E-071.05E-071.05E-07
- 0. 1.58E-071.58E-071.58E--071
.58E-071.58E-071.58E-07
- 0. 1.OGE-071.06E-071.06E-071
.06E-071.06E-071.06E-07
- 0. 1.59E-071.59E-071.59E-071.59E-071.59E-071.59E-07
- 0. 2.03E-072.03E-072.03E--072.03E--072.03E-072.03E-07
- 0. 3.04E-073.04E-073.04E-073.04E-073.04E-073.04E-07
- 0. 3.08E-073.08E-073.08E-073.08E-073.08E-073.08E-07
- 0. 4.62E-074.62E-074.62E-074.62E-074.62E-074.62E-07 6 14 3.83E-12 C 4.6E+03 9.1E+03 4.6E+03 1.8E+03 1.4E+03 1.8E+03 5.5E+00 2.84E-065.68E-075.68E--075.68E-075.68E-075.68E-075.68E-07
- 2. 27E-064 .26E-074 .26E-074 .26E-074 .26E-074 .26E-074 .26E-07 4.06E-06;8.12E-078.
12E-078. 12E-078. 12E-078. 12E-078. 12E-07 3.25E-066.09E-076.09E-076.09E-076.09E-076.09E--076.09E--07 2.ZIE-052.42E-062.42E-062.42E-062.42F-062.412E-062.42E-0G 9.70E-061
.82E-061 .82E-06! .82E-061 .82E-061 .82E-0G1 .82E-OG 2. 37E-055.06E-065.
OGE-065.OGE-065.
06 E-065.06E-065 06E-06 1. 89E-053 .79E-063 .79E-063.
79E-063. 79E-063 .79E-063 .79E-06 11 24 1.28E-052.50E-08 2.90E-08 SOLUBLE i.OE-02 1.2E-02 SOLUBLE 1.2E-02 3.1E-02 SOLUBLE ETC (FOR A TOTAL OF 89 NUCLIDES)--EODF--1 3VYXQF VY X/QFILE -SPECIAL VALUES -SEWAGE CONTAM. PROBLEI -2 ACRE PLOTS FLD 0 COW HEAT 4.626E-04 4.626E-04 1.236E-04 4.626E-04--BER----EO)F--ENTECH ENGINEERING, INC.PXOI-EC3 -Page B.3-3 F EOORAE; ATI;;T1, Th;i-E ATO;I1. ELECI&,C COIYAY PEC. C, 19B756 k .7 w (.5 REGULATORY GUIDE 1.109, APPENDIX C NODELS FOR CALCULANTXNI DOSE VIA ADDITIONAL PATHAYS FIOr RADIOISDINES AND OTHER RADIONUCLDES DISCHARGED T0 IHE ATMOSPHERE NOV,1977 LIDRARY.HE FOLLOWING I NUCLIDES WERE USED ON THIS CALCULATION TUCLIDE RELEASE CURI ES) TIN 54 4.13E-06 SECTOR FLD DISTANCE -0 :METERS)2/S0 4.63E-04 ISEC/t;-3)
- /0 DEPLETED -4.3E-Y04 SEC/I;-3)DELTA -I.24_-E0 I/I;-.)VY -SEWAGE COUaTAP; -SOLIDS iz DY AT -: A CRES -SNIELD F -0.012 -04 HE aCtUr A PATHWAYS CDUSIDEPE1 GROUND FLARE E5S ORTALATIOR4 YES STORED VEGXETALEC ,E3 LEAFY VEGET4FLES YES cow I;L; YES ZDAT "I5L A0 MEAT. YEs C.10 I 0 ,C)tit.AGIADLE STI TV AGRICULTURAL PRODUCTIVITY IRS/n-lI SOIL SURFACE DENSITY IRS/fl-l) 14 TRANSPORT TIME TO USER IN(S)Tp SOIL EXPOSURE T7l E ,NRS) 876, TE CROP EXPOSURE TIME TO FLUE INHXSI TN HOLDUP AFTER HARVEST IHESI 144, OP ANIMALS DAILT FEED (RO/DAY)PP FRACTION OF TEAR ON PASTURE PS FRACTION PASTURIE AHN ON PASTURE FP FRACTION OF STORED VEG GRORN IN GARDEN FL FRACTION OF LEAFY VYE GROAN IN GARDEN F1 FRACTION ELEMENTAL IODINE -.700 H APSOLUTt NUKTIOITy
-S.60 ION/T-3S)PC PRACTIONAL EOUILIBRIUI RATIO FOR C-14 -1.000 VEXETA DLES GRED LEAFY:.o00 .00 0.05 140.00 6.00 7A66.00.00 .00 0.00 24.00 COW MILK FA3TURE STORE70.70 2.00 240.00 240.00 46.00 40.00 8766.00 6766.00.00 .00.00 2160.00:o.oo 70. 00.70 1.00 GOT NILK PASTURE STORED.70 2.00 A40.00 140.00 40.06 4NAOS B.00 A 7 AR.00.00 .0*.00 IIA0.00 AD00 6.00 1.00 M"TE PASTURE STORED S70 2.00 240.00 240.00 480.00 460.00 NN6AS00 7A66.00.00 .00.00 2165.0o 70.00 70.00.50 1.oo0 C Cr IT En (S~0 10 TO (S 1.00 1.00 USAGE FACTORS I POSE IlLI T EACH OTRMA PROT ALL PATHWAYS CONINpREDP OVE LEAFY R ILK HEAT 1NHALATIOI4 S N AGE VES a HONE LIVER RIDPREY LUO SI-Ll THYROID WHOLE DODY StIR IR ("/TRl (EO/'RI Il/lR) (Ol/TRI Ct-i3/YRT
- A IRE;I A ADULT 710.00 64.00 310.00 1:0.00 6500.00 A 2.I3E-04 3.INE-04 2.44E04 2.98E-04 5.30E-04 Z.1JE-04 2.33E-04 2.701-0-TEEN 63:.00 40.00 HSO 5:G W7000 00.00 A 2.13E-04 3.66E:04 :.;9E-04 3.34E-04 2,I3E-04 2.44C-04 l.70E-04 CHILD 720.000 0 1 3700.00 3 E.130-04 4.36E-X4 2TA&E-0 E-4 4.00[-04 2.13E-04 2.73E-04 l.O0N04 INFANT .00 .00 330.00 .00 l400SO0 a *t3E-04 2.6E04 2.I4E-04 2.740-04 2.1-E-04 2.130-04 I.IE -04 :.;O-04 4 WN. tSA Sea WYNNa _NSA aWHY5 r.-ci CD i (D r RECAV A 5,855It;( p YAV:ZEE VYOL;IC ELECTRITC CO;I'.O.VC:. INS:ý .LO. 7 REGULATORY GUIDE 1.109, APFErDIX C MODELS FOR CALCULATING POSE VIA.DITITXONAL FAIHWAYS PROM RAIIIOItIlA4S ANV OTHER RAt-IOUCLIDES DISCHARGEr TO THE UTMOSPHERE AOV.1T77 LIbEaRE SEC70R FLD DPt31IACE
-0 (1E;TEESI-*U .63E-OA (SEC,'I;-])
8,'0 FEFLETET'
-4.630-HA (3EC'It;-)
DELTA -1.:4E-04 (1.0-)VV -SEWAGE CONTi; -SOLIDS I: 1' AT -ACRES -SNIELI F -o.01 -10 NE OCCUP STATAAYS CONSIDERED GROUND FLANE 7ES;I/HALATIOIJ
- -EO STORED VEGETA;LES "Es LEAFY OVECETALV ,E!COW 1;L K VET GO T I;ILK G MEAT EC3 THE FOLLOWING I AUCLflDES WERE USED I1 THIt C4LCAJLATIOH N4UCLIDE RELEASE CURIES
- 7 CO 60 Z.;IE-04 0 I-0~Em zt C., HARK ADLE 3TO 7V AGRICULTURAL PRODUCTIVITY IKR/Kn-)P SOIL SURFACE DENSITY (PS/H:-) R40 T TRANSPORT TINE TO USER (ME.)TM SOIL EXPOSURE TINE tARS) 6766 TE CROP EXPOSURE TIME TO PLUME (HMS)TH HOLDUP AFTER HARVEST (M .-) 1440 OF ANIMALS DAILY PEED (KGDAY)rP FRACTION OF YEAR ON PASTURE FS FRACTION PASTURE AMEN ON PASTURE FO FRACTION OF STORED VEO GROWN IN GARDEN I FL FRACTION OF LEAFY VEG OROGN IN GARDEN FI FRACTION ELEMENTAL IODINE , zOO N AVSOLUTE HUMIDITY -5.60 (GMI/-3)PC FRACTIONAL EOUILISR;IUM RATIO FOR C-I4 -1.000 USAGE FACTORS N VEG LEAFY M ILE N(AT INHALATION N AGE VEO G CRO/YE) CKR/YE) (LI/YE) CR0/"R) (9-3/TM) N ADULT T:0.00 AA.00 310.00 1)0.00 0000.00 N TEEN 630.00 4.00 400.01 65.00 000.00 N CHILD Z0.oo :6.00 330.00 41.00 3!00.0 5 INFANT .00 .00 330.oo .00 400.00 VEGETAPLES RED LEAFY.00 T.00.00 :40.00.00 9766.00*.00 4.00 CCU FASTUýE:40.00 48M.0 876.00.00 TO,00 1.00 ,o o I ILII STOVED..00:4 0.00 640.00 0766.00.00:160.00:.00 OAT SILK PASTURE 3TORED.70 :.00.40.00 ,46.00 616. 10 .461.O0 0766.00 0766.00.00 .00 0 O 160.00 6.00 6.00 1.00 OASTURE.70.40.GO 400.00 8766.00.00.o0.00 1 .00 STORED:.00:00.00.10 0 .00 6766.00.00:160.00:O .00 C-0~Tb C/S IS'0 KY 0'OY (S.00 1.00 DOSE DELIVERED TO EAC)) ORGAN FROI; ALL PATHWAYS CO; INED Ds)0E LIVER LUNG 0 1-LLI THYROID WHOLE PODO S11IN I " RE,) *....OE-02 .3!-0 T.0E-O 7.40E-70 S.3:E-02 5.:OE-O2 5.:AE-O: 6.I:E-0: s T.OE-02 !02 S.'.OE-02 8.41CE-0 .30E-02 :;.20E-0, t.73E-0 A.10 E-0".~~0E0. :.: :Z0 .E0 DM-02 7.l6E-02 :;.2VE-2 6:;E-:AI-0o 20..E-02 : .T:02 T.ZOE-O 6.UA-0 TE- 3.O-07::R02 6IE N N NO NA U A NO MU'-U 0)(0~CD Co-4 PROGRAM ATMODOS YANKEE ATOMIC ELECTRIC COMFANY DEC. 1989 REV. 7 LJ wo REGULATORY GUIDE 1.109. APPENDIX C MODELS FOR CALCULATINO DOSE VIA ADDITIONAL PATHWAYS FROM RADIDIODINES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE NOV.1977 LIBRARY SECTOR FLP DISTANCE 0 (METERS)X/0 4.63E-04 (SEE/M-3)X/O DEPLETED
- 4.63E-04 (SEC/M-3)DELTA I.24A-04 (1/N-:)VT -SEWAGE CONTAN -SOLIDS I- DY WT -ACRES -SHIELD P -0.012 -J04 HR OCCUP 6 PATHWAYS CONSIDCEGD GROUND PLANE YES INHALATION YES STOREI. VEGETABLES YES LEAFP VEGETAPLES YES CEW MILK YES GOAT MILK NO MEAT YES THE POLLOAING I NUCLIDES WERE USED IN THIS CALCULATION NUCLIDE RELEASE CURIES 30 ZN 63 4.50E-06 0 C)C)VARIAPLE STO TV AGRICULTURAL PRODUCTIVITY IKO/M-2)P SOIL SURFACE DENSITY 24)N TRANSPORT TINE TO USER (HAS)TI SOIL EXPOSURE TIME (ARS) 876)TE CROP EXPOSURE TIME TO PLUME (ARS)TA HOLDUP AFTER HARVEST (ArS) 1440 OF ANIMALS DAILY FEED (KO/DAY)FP FRACTION OF YEAR OS PASTURE PS FRACTION PASTURE WHEN ON PASTURE FG FRACTION OP STORED VES OROGN IN DARDEN FP FRACTION OP LEAFT VES OROWN IN GARDEN F1 FRACTION ELEMENTAL IODINE ..:00 A APSOLUTE HUMIDITY -0.60 (OGM/-3)PC PRACTIONAL COVILIERIUN RATIO POR C-14
- 1.000 VEGETADLES REED LEAFY.00 2.00.00 240.00 6.00 8766.00.00 .00 1.00 Z4.00 COW MOLK PASTURE STORED.70 2.00 240.00 240.00 48.00 49.00 9766.00 9766.00.00 .00.00 2160.00 00.00 50.00 5 .00 GOAT MILK PASTURE STORED.70 2.00 240.00 240.00 40.00 4*.00 8766.00 8766.00.00 .00.00 ^160.00 6.00 6.00.00 I O00 MEAT PASTURE STORED.70 2.00 240.00 240.00 490.00 490.00 9766.00 9766.00.00 .00.00 2(60.00 30.00 :0.00.50 1.00 CD OKII 1.00 1.00 USAGE PACTORS A DOSE DELIVERED TO EACH GROAN N PROM ALL PATHWAYS CONPINED VEO LEAFY MILK MEAT INHALATION A AGE Y WES S DONE LIVER KIDNEY LUNG GI-LLI THYROID WHOLE POOY SKIN N 4KO1YR) CKO/YR) (LI/YR) (PO/YR) (N-3/YR)E A)RE4M ADULT 520.00 64.00 310.00 110.00 8000.00 A 3.43E-03 1.06E-02 7.13E-03 2.03E-04 6.7.E-03 1.46E-04 4.R7E-03 1.69E-04 N TEEN 630.00 42.00 400.00 60.00 9000.00 N 4.61E-03 S.37E-O2 I-01E-02 2.29E-04 6.72E-03 1.46E-04 7.36E-03 S.6S9E04 CHILD 320.00 26.00 330.00 41.00 3700.00 N 8.72E-03 2.30-O02 1.43E-02 2.IIE-04 4.16E-03 1.46E-04 I.44E-02 1.6E-G04 N INFANT .00 .00 330.00 .00 3400.00 N 6.IRE-03 2.0RE-0E2
.02E-02 I.BNE-04 I,76E-02 1.46E-04 9.A6E-03 1.6SE-04 A.........
IN.... *...Il....l.....l l
PROGRAM ATMODOS YANKEE ATOMIC ELECTRIC COIPANY DEC, 1905 REV. 7 REGULATORT GUIDE 1.109. APPENDIX C MO10LS FOR CALCULATING DOSE VIA ADIIOIONAL FAIRWAYS FROM RADIOIODINES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE NO5.1t77 LIBRARY SHE FOLLOWING I NUCLIDES WERE USED IN THIS CALCULATION MUCLIDE RELEASE CUR IES 5. CS 134 2.72E-06 SECTOR PLD DISTANCE
- 0 (METERSS X/O 4.63E-04 (SEC/M-3)XSO DEPLETED 4 .63E-04 (SEC/N-3)DELTA I.24E-4O (1/1-2)VY -SEWAGE CONTAM -SOLIDS I1 PT 45 -I ACRES -SHIELD r -0,012 -104 HE OCCUr A PATHWAYS CONSIDERED SROUND PLANE YES INHALATION YES STORED VEGETAPLES YES LEAFY VEGETADLES YES COW MILK YES GOAT MILK NO MEAT YES C.).6 PS PS 0 C.a.C ID C t 0 0 OS VARIABLE STI TV AGRICULTURAL PRODUCTIVITY (IS/N-SC P SOIL SURFACE DENSITY (KD/M-2) I 2 I TRANSPORT TOME TO USER (HRSS TN SOIL EXPOSURE TIME (MrS) R76A TE CROP EXPOSURE TIME TO PLUME CARS)TH HOLDUP AFTER HARVEST CARS) 1441 OF ANIMALS DAILY FEED (K1/DAY)FP FRACTION OF YEAR ON PASTURE FS FRACTION PASTURE WHEN OR PASTURE PG FRACTION Or ETORED VEO GROAN IN GARDEN FL FRACTION OF LEAFY HEX GROAN IN GARDEN El FRACTION ELEMENTAL IODINE * .*OC" ABSOLUTE HUMIDITY
- 5.60 (DO/f-3)PC FRACTIONAL EOUILIBRIUM RATIO FOR C-14
- 1.000 VEGETABLES ORED LEAFP 1.00 2.00 0.00 240.00 6.00 8766.00.00 .00 0.00 24.00 COW MILK PASTURE STDRSD.70 2.00 240.00 240.00 49.00 48.00 8766.00 8766.00.00 .00.00 2160.00 50.00 50.00.50 1.00 GOAT PASTURE.70 240.00 48.00 8764.00.0O.0O 6.00.50 1.00 MILK STORED 2.00 AS. 05 48.00 8466.00.00 2160.00 4.00 MEAT PASTURE STOKED.70 2.0.40.00 240.00 480.00 480.00 9766.00 .766.00.00 20.05oo 0.00 750.00.50 (.00 ID iO 0 tAM N.j'C CO4*~to I.00 I.00 USAGE FACTORS DOE DLIAREDTO AE)) OROA FROM ALL FATUNAIS COMBINED HEX LEAPY MILK MEAT INHALATION S AGE Y50 : NONE LIVER KIDNEY LUNG GI-LLI TAYRSI0 MHOLE NOSY SKIN ISO/TRI (RO/TR) (LI/YSRI (KO/YR) (I-/YR) MNREM ADULT 520.00 64.00 3)0.00 110.00 8000.00 a 5.89E-04 1.09E-03 .-06E-04 3.20E-04 2.42E-04 2.27E-04 9.31E-04 2.6,E-04 I TEEN 630.00 42.00 400.00 650.4 8000.00 N 7.92t-04 1.OAE-03 6.501-04 38VE-0A .4-4E-04 2.27E-04 8.44E-04 '.65E-04 9 CHILD 520.00 26.00 330.00 41.00 3700.00 9 0.50S-03 !)355-03 8.74S-04 4.S9S-04 S.38E-84 2.275-ON 6,67E-04 :.AE04 INFANT .00 .00 3w0.00 .00 1400.00 9 7.74E-04 I.20E-03 4.89E-04 3.35E-OA 2.30E-04 2.27E-04 3.30E-04 2.65E-04 N..........
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1~~>f PROGRAM ATMODOS YANKEE ATOMIC ELECTRIC COMPANY DEC. 1985 REV. 7 REGULATORY GUIDE .1D09, APPENAIX C MODELS POR CALCULATING DOSE VIA ADDIITIONAL PATHUAYS FROM RADIOIODINES AN0 OTHER RA[IONUCLIDES DISCHARGES TO THE ATMOSPHERE H0V.1977 LIfRARY THE FOLLOWING I NUCLIDES WERE USED IN THIS CALCULATION NUCLIDE RELEASE CURIES 55 CS 137 9.37E-05 SECTOR FLD DISTANCE S (MT ERTS)x/a 4.63E-04 (SEC '-31 U/S DETLETET 4.AIE-04 (SEC/M-TI DELTA I.2,E-04 I1/M--1 AT -SEWUGE C01(TA0 -SOLIDS 10 TM AT -2 ACRES -SHIELD PF 0 .01. -104 MR SCCri a PATHWAYS CONSIDERED GROUND PLANE YES INHALATION YES STORED VESETAPLES YES LEAFY VESETAPLES YES COW MILK YES GoAT MILK NO MEAT YES c.)10~tat ENC)Lti 0z VARSAPLE STO YV AGRICULTURAL PRODUCTIVITY (KS/M-21 2 P SOIL SURFACE BENMITT (KR/M-2) 240 T TRANSPORT TIME TO USER (HRR)TP SOIL EXPOSURE TINE (HER) 8786 TE CROP EXPOSURE TIME TO FLUME (HRS)TA HOLDUP AFTER HARVEST (HRS) 1440 OF ANIMALS DAILY FEED (K/DATY)rP FRACTION OF TEAR ON PASTURE FS FRACTION PASTURE WHEA ON PASTURE rG FRACTION OF STORES VEG BROWN IN GARDEN I FL FRACTION Of LEAFY VEG GROWN IN GARDEN FI FRACTION ELEMENTAL IODINE -.500 A AGSOLLUT E HUMIDITY -3.60 (m/MN3)PC FRACTIONAL ESUILIPRIUIM RATIO FOR C-I4 E .000 VEGETAPLES RED LEAFY.00 2.00.00 240.00*.00 AA.0.000 74.00 COW MILK PASTURE STORED.70 2.08 240.00 248.00 G766.00 0766. 00 GAO .0.00 2160.G0 50.00 50.00 000 1.00 GOAT MILK PASTURE STORED 2.70 2.00 240.08 240.00 48.00 48.00 8766.00 87A6.O0.00 .00.80 2160.00 6.00 6.00 ,50 1G00 PASTURE.70 240.00 460.00 8766.00.00.00 50.00 1.00 STORED 2.00 240.00 450.00 8766.00.00 2160,00 50.00 MEAT TO Tn 10 C)CO 10 ITO TO.00 1.00 USAGE FACTORS P OSE DELIVERED TO EACH1 OGRAN V FROM ALL PATHAMAS COMPINED AEG LEAFY MILK MEAT INHALATION F R 0 AGE , VE a I NOME LIVER KIDNEY LUNG SI-LLI THYROID UHOLE HODY SKIN (KI/YR) (ES/SR) (LI/YT) (KS/YA) (MN-/OR) 9 (MREEN A ADUULT 520.00 64.00 310.00 110.00 800.00 A 3.57E-02 4.70E-02 1.93(-02 9.79E-03 5.06E-03 2.0AE-03 I,25RtA2 2 .M9E-03 TEEN 630.00 42.00 400.00 65.00 :GO.0 , 5.52E-0 : 7.IRE-02 2.78E-02 1.39E-02 A.0E-03 ;,06E-02 !.81E-52 5.M0E-OI S CHILD 520.00 26.00 330.00 41.00 3700.00 t 1.21E-,0 lIE-Ol 4.IOE-02 I.AE-02 S.AR-S0 S.OAE-S3 2.0RE-0l 6M'R-O0 3 INPAMO .00 .00 110.00 .00 1(00.00 A O.S0E-Ol 6.35E-02 E _.*AE2 5.224E-03 506E-03 M.2E-0'3 NO9E-03 A INFANTN .0A 30.000E-2 0tt A At "1 TVJVEE ATON10 ELECTRIC ZOTAV%DEC, 109: FLV. I REOULArOR?
GUIDE 1.10$. PFvNWDIX C MODELS FOR CALCULASONO DOSE VIA ADDITIONAL PATHWAYS FROO RAOII1ODINE3 AND OTHER RADI.AUCLISES DISCHARGED TO THE ATHSSFNEEE NOW.IV77 L.fR'.Y SECTOR FLD SISTANCE -V ;NETEKSI I/O IETLETIEI 4.63E-04 I:ELr;-31 DELTI -1.2S4-O0 VY -SEWAGE CTVTAM -SnLIVS It y AT -W ACRES -IHIELt F -0o0:- -104 OR OrCUr 6 PFATHWAYS CONSIDERED.HE FOLLOWINO SNUCLIDES WERE USED IN THIS CALCULATION NUCLIDE RELEASE CUR IES:5 HN 54 4.13E-06:7 CO 60 2.scE-04 30 ZN 65 4.00E-06 55 CO 134 1.72E-06 55 Cs 137 9.37E-05 3ROUND PLA14E INHALATION STORED VFGETTOLEq LEAFY VEEOTABLES COw MILK ODAI EALK MEAT-,'EýS YES YES NO YES toj iO 0~0 H t~C)Iz VARIAMLE ST?TV AGRICULTURAL PRODUCTIVITY (Ko/M-2)P SOIL SURFACE DENSITY IKO/M21) 240 T TRANSPORT TIME TO USER (HRST SN SOIL EXPOSURE TIME (NEST 8764 TE CROP ESPOSURE TIME TO FLUME (NRS)IH HOLDUP AFTER HARVEST (IRS) 1441 OF ANIMALS DAILY FEED (MO/t'N)FT FRACTION OF YEAR ON PASTURE FS FRACTION PASTURE WHEN ON PASTURE F0 TRACTION OF STORED VEO CROWN IN GARDEM FL TRACTION OT LEAFY VEG GROWN IN SARDEN FI FRACTION ELEMENTAL IODINE * .500 H ABSOLUTE HUMIDITY
- 3.60 (OM/M-3I PC FRACTTONAL EOUILINRIUM RATIO FOR C-14 -1.000 VEGETABLES SEED LEAFY.00 2.00 1.00 2H0.00 (.00 8766.00.0oo .oo 1.00 24.00 COV MILK PASTURE STORED.70 2.00 240.00 240.00 48.00 48,00 8766.00 8766.00.00 .00.000 2160.00 50.50 50.00.50 S.O00 GOAT MILK PASTURE STORED.70 2.00 240.00 240.00 486.00 48.700 8766.00 6?&&*:0.0*.00 .0G.00 2560.00 6.00 6.00.00 I1.00 MEAT PASTURE STORED.70 .00 240.00 240.00 480.00 400.00 8766.00 8766.00.30 1.00 1.00 1.00 USAGE FACTORS P OSE DELIVERED TO EACH ORGANN SFROM ALL TATNWAYS CODOtDNED 8 VED LEAFY MILK MEAT INOALATION N A WOE .aO 8 NONE LIVER KIDNEY LUNG 0I-LLI THYROID WHOLE DY SKINPi IS/TYR) (KS/YR) (LI/SR) IKR/YR) (M-3/Y) 8 (NREM) U ADULT 020.00 64.00 300.00 10000 8000.00 0 M.E0E-02 I.13E-01 7.92E-02 8.46[-02 9.66E-02 .76E-02 9.42E-02 6.7RE-02 2 TEEN 630.00 42.00 400.00 65.00 8000.00 8 I.13E-01 1.44E-01 9.0OE-02 9.90M-02 9.65E-02 3 .76E-02 9.41E-02 6.76E-02 *COILD 520.00 26.00 330.00 41.00 3700.00
- 1.96E-0I 1.99M-El I.IOE-01 9.73E-02 8.22E-02 5.76E-02 9.94E-02 6.78E-02 .INFANT .00 .00 330.00 .00 N I.IOE-0l I.3GE-oI 8.36E-02 9.OE-02 7.79E-02 5.76E-02 7.19E-02 6.70E-02 .8........ t ....... I ......$ ..t........
...................
-* .................
ADULT DOSES RECEIVED F0ROM VARIOUS PATHWATS PONE LIVER KIDNEY LUNG LOD SECTOR AT.A DISTANCE Or 0 NETERS PATHWAY 01-LLI THYROID WNOLE FODY SKIN GROUND PLANE 54 4N 60 Co 65 Zn 134 CS 137 CS TOTAL FOR PATHWAY INHALATION 54 MN 60 CO 134 CS 137 Cg TOTAL fOR PATHWAY STORED VEGETABLES 54 fN 60 CO 65 ZE 134 CS 137 CO TOTAL FOR PATHWAY LEAFY VEGETABLES 54 HN 6D XE 165 Z: 134 CO 137 CS TOTAL FOR PATHWAY: ..0004000*0OE+00 2.140-06 N. 3 '-0 6 6 .S E-.4 6.AVE-04 6.O69004.SOE +00.000000 1.23E-03 2.30E-04 1.97E-02 2.12E-02 0 DEN00 ,.:7E-04 2.9 60-00 2.43E-03 2.64E-03 2.400-06 4.240-0G 6.610-G6 2. IJE-0G 0.030-04 9.26A-04 a. 00-05 1.24C-03 3:90C-03 5.46E-04 2.690-02 3.27[-02 1.2*3E-05 1.S6E-04 5:67r-04 7.100-05 3.33E-G3 4.14E-03 5.96E-07 ODE0.+00 4.020-D6 7.220-06 3.0'f-04 3.16E-04 2.62E-G;.0004 00 2.610-03 1.770f04 9.1:0-03 I. 20E-02 3.67E-06.00A+G00 3.600-04 2.300-GO 1.130-03 I,24E-03 6.400-02 2.:00-40 0.7D0-05 2.400-GA I ,03E-04.OOE+ .0.0004 00.000400 3.040-03 3.10E-03.00E+00'.0t00 00 37. 63E-06 3.83E04G 3.DO0-GD 46 9E-06 1.07E-03 3.230E-06 23.6E-07 6.07-03 2.700-O4 2.336-02 2.460-03 9.060-06 0.220-04 2.660-02 3.70E-05 2.93E-03 3.270-04 1,240-06 6.440-GO 3.39E-03 GOtON00.000+00.00 00E'o0.,00[+00.OOE00.00C400.000 400.00040 0.000+00.00040 E,0.0:00+0.000+00.0OE04.00E#00 2.13E-04 1.46E-04 0.06E-03 Z.76E-02 3. 1E-07 3.07E-06 5. 06E-04 6.64E-04 1.600-00..740-03 1 .76E-03 4.471-04 1.760-02-.260-02 2.36E-06 3.440-04 S4 .46-04 2 ,60[-04 11801-03-.81E-03 2.000-04 6.1;E-02 1.6A0-04 6. ,E-O3 6.700-02 c 9 Atit iO ot0 DOSES RECEIVED FROM VARIOUS PATHWAYS CMREt)PONE LIVER KIDNEY LUNG rLp SECTOR AT A DISTANCE OC 0 METESE GI-LLI THYROID ANGLE BODY SKIN PATHWAY COW MILK PHE* .OO0 6.7 -007 2.SEC-07 OOEH+00 2.OBE-A .6OOE+O 1.'9[-07 60 C. .OOEHOO 3.71C-0a *0E400 *o00.00 A.tBt-O4 .00Eq0 0.COC-E0 63 CA 1.4.F-03 .7 E-0S 3.37E-03 !0OE C 00 A-3 :00,OOa ;:11E-S l1t CS 9.3aC-S:05 1.SC-S9 6r0 A T40E-0: 0.4A_-06 .Oacoa 1.6-C-S0 137 C7 CO.E-03 V.AE-53 3.67E-03 ,Oar-OT tRfl-CL .0a~aCS 4.TCE-O0 TOTAL FOR PATHWAY 6.63E-03 IA.46-02 6.31E-03 l.IIE-0T 3.88E-03 .00E.00 8.70E-03 MEAT T4 MN .SOCNCC 7.40E-07 .CCEE00 .O 0 C.C7E-OA .00OO(0 1.415-0S AS CO .00E400 1.7CC-I4 .00RN00 .OSEHOO 3.3CC-Si .1OE*S0 i.76-04 65 ZN 1.9SF-PA l.CiE-OT 9.3CC-CA .O0EH7E 7.7ZC-54 .OOESC' E.6E-04 134 CS 9.67E-Ce C.TOE-CS 7.4C-56 C.AE-OA 4.E'0 E7 .0OSC0N 1..E-SS I37 CS H.33iiE- 1.14E-03 3.07E-0 1..9-E_04 C.CI-0 .S SO;00 7o.A.-04 TOTAL FOR PATHWAY 1.C3E-03 2.56E-03 I.C2E-i3 1.31E-04 4.O0E-0S .S0SOCH 1.70E-03 TOTAL ALL PATHS 3.43E-CC 1lt-CC 0.1C-0C C.A9E-02 3.99E-02 .OOS+0E 9.42E-02 6.CC-SC TOTAL ALL PATHS INCLUDINO MHOLE tODY DOSE EtCH GROUND PLANE C EX OSURE 9.20E-02 1.13E-01 7.92E-02 H.ALE-S2 9.66-07 s .76C-02 9.4ZE-0,~t,a m, (b, TEEN DOSES RECEIVED FROM VARIOUS PATHWAYS NONE LIVER KIDNEY LUNG rLDt SECTOR AT A DISTANCE or 0 METERS pATHWAY GI-LLI THYROID WHOLE BODY SKIN GROUND PLANE 54 NN 60 CO 65 ZN 134 CS 137 CS TOTAL FOP PATHWAY INHALATION 54 Wm 60 CO 65 Z(134 CS 137 CS TOTAL FOR PATNWAY STORED VEGETABLES A4 PN 60 CO 65 zN 134 CS 137 CS TOTAL FOR PATHWAY LEAFY VEGETAPLES A4 MN so CO 6S ZN 134 CS 137 CS TOTAL FOR PATHWAY 2.13(-04 c.Gc-02 1,46E-04.7E-04 5.06E-03 6.I:E -07 I .6AEG04 2.6:;E-04 5.90E-03 5.76E-02 6.75E-G7* AGENDA ,00E+OO 2.15SE-06 I .6E-05 9.21E-04 3.10I-06-.57E-05 0.S2E-06 2.. 4E-0A 1.16E-03 7.71D-07 5. 70E-06 9.44E-06 N. I HE-04 1.AO[-OA 3.21E-02 a. GtE-AC 3.6WA-06 1.66E-04 A .OE-06 9.54E-04 3. OE-G6 2 ACE-0A I..16E-05.O0[÷o0.OOE400 ,OOEO00.OOE*O0.,GENA0G S,09E-07 7,31E-05 4. 12E-06 1.38E-05 4. 27-04 9.36E-04 1.26E-03 4.33[-04 3.:E-02" 9.73E-04 *OOE+0O 5.19E-04.QOEto0 AoE 40 A 1.77E-03 3.W7AD-A 3 .3CD-02 I.30E-04 1.97E-03 6.13E-03 8.=DE-04 A.4NE-02 4.011 D-05.OOctO0 3 .73E-03 2. AC-04 G.C2E-02.OOEAG0.OOE40O.07TE-04 5.90E-03 37E-02 2.60E-03 I. IOA-QC 6.3CE-04.00c#0GA.OOE400.OOE40O.0OE400 4.4ACE-03 2.73E-03 9.6E -03 4.09E-04 1 .;E-02 t"~i0l2C AlC l C)3.T7E-02 5.37E-02 1.94A-O2 6.01E-03 .9^C-02 ,OOE400 .33E-02.OGE400 1.05t-05 3.12E-06 .O0O140 2.ICD-GC OOEN0G 2.07[-06 AGOEVOG 1.3AE-04 oOD+Oo .AOE40O 1.7-E-03 GOENoG 3.03E-04 1.39E-04 4.84E-04 3.lOE-04 .O0E400 .O-04 .OOE+00 .W6E-04.W3E-A 6.20E-O- 1.97E-0A 7.52E-06 7.71E-07 GOOE+NO .88E-05 2.,4E-03 2.99E-03 I.02E-03 4.A E-OC; OOE-OO 1,04E-03 2..4E-03 3.68E-03 1.3CE-03 4.0:E-04 7.OE-G3 .OOEVOO I.60E-03 U ;EIE0S TEEN POSES RECEIV E 1 FROM VARIOUS PATHWAYS SOME LIVER KSIDEY LUNG 6L0 SECTOR AT A rISTANCE Or PATHWAY COW MILK 04 494 60 C0 6 5 Z , 134 CS 137 CS TOTAL FOR PATHWAY G0-LL2 THYROID WHOLE SOPY SKIN.00o000 ,OOE00 2.,44E-04 1.28-02 1.13E-06 4.306-OS 7.VE-03 3.40E-04 1.70 -02 3.37E-07.004+00 5.09E-03 2.086-04 0.796-03.00E 00.006c00 4.226-00 2,206-03 8.206-04 3361-603 4..3E-06* .42E~4.00E+00*00E:00.00OE400.00+00.OO6 800 2.24E-07 2.42E-04 3.226-03 1.586-04 0.9 3-03 1.52t-02 2.04E-60 2.206-02 ^.-9"-03 4.436-03.00E400 9.93E-03 MEAT 54 60 60 134 137 824 60 28 CO5 C0.00!000 00(6÷00 2.T726-04 7.69E-06 6.926-04 1.326-04 9.440-04 9.206-04 1.686-07.006400 6. 040 -04 3. 13-06 3. -236-04.00E#00-ODE 4 00.006E00 2.206-06 2. 226-04 2,266-06 4.006-04.2-E-07 2.326-02.006400.006.00.006c 400.OOE00.006 900 2.16E-07 2.98"-04 4.406-04 8.406*06 3.22E-04 TOTAL FOR PATHWAY 9.726-04 2.026-03 9.236-04 2.24E-04 2.14E-03.*22-02 0.61E-02 3.312-02 4.136-02 3.88E-02.00E#00 1.07E-03 TOTAL ALL PATHS TOTAL ALL, PATHS NG WHOLE 3001 00Do6 FROM G R00UND PLh NE.ENPOSURE 0:z To LQ.004+00 9.426-02 6.786-02 1.13E-01 1.44E-01 9.08E-O 9.900-02 9.60E-02 0.76E-02 9.416-02 m cn CHILD POSES5 RECEIVED FROM VARIOUS PATHWAYS ON RE) K DONE LIVER 0I0rI4Y LUIWS rLD SECTOR AT A DISTANCE Or 0 METERS PATHWAY 01-LLI THYROID WHOLE PODY SKIN GROUND PLANE 54 MN 60 CO AS ZN 134 Cs 137 CS TOTAL FOR PATHWAY ZIHALATION 54 NA 60 CO 63 ZN 134 CS 137 CS TOTAL FOR FATHWAY STORED WEGOTAPLES 60 CO 65 ZN 134 CS 137 CN TOTAL FOR PATHWAY LEAFY AC0ETAPLES 54 RN 60 CO 63 Z" 134 C9 137 CS TOTAL FOR PATHWAY 2.13E-04 2.50E-04 5.20E-02 6.1,E-02 1.46-0-4 1.680-04 2.271-04 2.651-0A 5.061-03 5.901-03 5.76E-02 6.780-02.O01+00 0.000400o 2.811-O0 1.641-0S E.:25-03 2. 0E-O6 4.043-03 7.470-06 1.13E-03 6.08r-07.001*00..7 1E-06 8.31E-0-3.000-04 9.551-03 2.6OE-02 4.57E-05 3. 04E-06 1.43E-04 1.39E-06 3.541-04 1.0,1-06 9.601-OS 4.97E-O6.00+C00.001600 0 00C+00.00E+00.001600 3.76E-07 8.341-05 ,.641-06 S6 :E-06 1.76E-04 1.26E-03 1.220-03 4.01[-04 2.63E-02 3.62E-04 .0OE+00 2.71E-04.00(400.0014 00 3.47E-03 1.633-04.,09-0 2 2.06:-04 3.07E-03 9.24.-03 0.420-03 7.740-0 2 5.82E-03 A,0OýE:004 4.3 90-04 2.,521-02.001#00.000E400.OOEO00.001+00'.58E-04 9.07E-03 ,.731-04 1.70E-02 1.62E-03 7.64E-06 4.840-04:OOE*O0 OOE14 0.OOE+00.00(00.000+00 5.49E-05 9.05E-03 5.7:;-03 2.991-04 1.14E-02 tao 0) 0 8.52E-02 .,130-02 3.2;0-02 9.23E-03 1,03r-02 .000400 2.660-02.000+00.001+ 00 2.051-04 4.56E-05 4.06,-03 I.171-05 1.$70-04 5.460-04 7.400-05 3.890-03 3.2Y0-06 ,00-T00O 3.:73-03.00 400 ,001400 9.321-06 4O.550-0 9.961-06 6.690-04 9.60E-05 4.03E-07 2. 430-02;.001400.00 +00.00E0 +00.OOE+O0 3.130-06 4.620-04 3.400-04 4.310-03 4.67E-03 1.64E-03 4.641-04 9,9YY-04 .000400 1.39E-03 CHILD DOSES RECKEIVED PROM VARIOUS PATHWAYS PONE LIVER KIDNEY LN9 FLO SECTOR AT A DISTANCE Or 0 METERS S1-LLI THYROID WHOLE PODY SKIN PATHWAY Cow MILK 54 MN 60 CO 1 34 CS 137 CS TOTAL FOR PATHWAY ,00E400*,00(400 3. 33E-04 3.00E-02 1.690-06 9,700-03*E70.9!30-02 4.74E-07.00 00 7.540-03 I .69C-04 9.61E-03 ,OOE40 o00(400 6.o0E-03 3.46 E-03 5.42K-O6 3. CE-0A 2.IDE-OX I a.K- -0.00K500 ,OOE400.OOE
- 00.OO E 40 0.ooE 400 4 .0E-07 E.O'E-04 7.44E-03 1.1K-n04 4.3E-0:3 3.S6E-02 4.21E-02 1.73E-02 3.52E-03 -.03K-03.00K00S 1.:KE-02 MEAT 54 60 134 137 AN CO ZN CS CS.000A*0oEc00 4.080-04 1 .36K-0S 1.27E-03 6.46E-07 1.50E-04 1.2E-03 1.:23-O3 I. AlE-07.00E400 I.A4E-04 3.97E-0O.00EV 00 00ASS00 2.48E-06.4I3K-_0 0. 70E-O I .1K-O4 1.20K-i7 7.64E-06.00EVO0.100A00.00K 400.00K r00.00K 400 1.72E-07 4.63E-04 6.76E-04 4.70E-06 1..0E-0 4 TOTAL FOR PATHWAY TOTAL ALL PATHS TOTAL ALL PATHS INECLUDING HOLE MDy DO S0 FP03 GROUND PLANE ESxPSurE 1.70K-OX 2.490-03 1.09E-03 I..*E-04 1.07E-03 1.260-01 1.420-01 S. 0E-02 3.97E-0S -.4KE-02.00E400 1.32E-03.00C.00 9.940-02 6.76[-02 1.86E-01 1199E-01 1.1OE-01 9.73E-02 1.TE-02 .i76E-02 9.94E-02 b-tA, iO 0 to.9 I5~H C., NO INFANT DOSES RECEIVED FPOM VARIOUS PATHWAYS NitRE A)PONE LIVER KIDNEY LUNG PATHWAY GROUND PLANE 54 MN 60 CO 65 ZN 134 CS 137 CS TOTAL FOR PATHWAY INHALATION 54 MN 60 CO 65 ZN 134 CO 137 Cs TOTAL FOR PATHWAY STORED VEOETAPLES 54 AN 60 CO 635 ZN 134 CS 137 CS TOTAL FOR PATHWAY LEAPT VEGOTAPLES 54 AN 60 CO 63 ZN 134 CS 137 CS TOTAL FOR PATHOAY FLO S(CTOR AT A DISTANCE OP 0 METOPO GI-LLO THYROID WHOLE POY SKIN 2.030-04 2.S0E-04 5.200-02 6.1:0-02 1.46E-04 1.&G0-04 2 .7E-04 :.67t-04 5.06C-03 5.90E-03 5.76E-02 6.780-02.*00+00 1.54E-06 3.02E-07 6.06E-O; 4.20B-07 .00EO00 3.02E-07 ,00E+00 29.SE-0 .sOOEAOO 1.66E-02 1.100-04 .00E400 4.34E-03 1.12E-06 4.13E-06 2.14E-06 4.27[-0S 3.39E-06 .OOE+00 2.05-06 9.96E-OA 1.770-OS 4.79E-06 '.00E-06 3.364-08 .O00400 1.67E-06 7.54E-04 8.40E-04 2.37E-04 9.79E-05 1.A3E-06 .00C400 6.22E-05 7.650-04 9.93E-04 2.44E-04 1.68E-02 1.23E-04 .000E00 1.l0E-O4.*00E00 .00+400 .000400 .00O400 .00c+00 .00O400 .000400.*00400 .00(400 .00E.00 .00+00 .00E400 .OoE#00 .00(O00.Oo+O .0oE0oo .oo0000 .00E+00 .00E.00 .00E400 .0oE0oo.oo00o0 .oo00O0 .0004o0 .ooE400 .OO0+00 .0o0+00 .OOE+00.00[400 .000OO0 .0O0(fO0 0OE400 .OOE+00 .000400 .O0E0O0.00OE400 .O0E400 .00E400 .000400 .000400 .0o0400 .000400.00E+00 .000400 .00E400 .000000 .00000 .00E400 .00400.OOE+O0 .OOEH00 .000400 .00(00 .4OEO0 .4OOE+0.OoEOO .000400 .0O0 O0 .00(400 .00(400 .00(400 .OOE400.OOE4O0 .00400 .000400 .00*400 .00C400 .000400 .OOE00.OOE400 .00EO0 .000400 .00400 .000400 .00E400 .000400.O0E040 .00(400 .0OE+00 .00O400 .00400 .OOE400 .000+00 to, iO (~)H'at', H z (4 WEANT ROS ECEI IVED FROM 4AR(U0S PATSUAYS PONE LIVER KIDNEY LUNG rLD SECTOR AT A DISTANCE OP 0 4ETERS GI-LLl THYROID UNGLE PODY SKIN PATHUAY COW MILK 54 iN .00(400 3.E-OA6 A.:7E-0G7
.00T400 I.IAE-0A .OOEG00 7.13E-0-AG CO .00(400 2.OOE-04 .00(400 O0C0400 .7ZE-04 .00E400 C .2T-04 63 ZN A.oE-03 .,07-02 I.,0E-02 .00400 1.7E-02 ,COEOO V.SAE-S3 134 Cs Z,37(-O4 .OOE-03 240E-04 1.0AE-04 2. 0-0A .00EECO a .01E-04 137 CS 4.92E-02 T.76A-0? I.54(-O 6.2AE-03 I.0(-04 .00(400 '.0A(03 TOTAL FOR PATNAAT Z.OTE-02 7.94AE-G 2.,?E-02 6.36E-03 I.OIE-02 .C0E-00 1.42E-02 NEAT-4 mm 60 CO AT ZN 134 CS 137 CS TOTAL FPR PATHWAY TOTAL ALL PATHS TOTAL ALL PATHS INCLUDING UNOLE pOSl Y D OSE FR 11 GRCONO PLANE EXPOSURE.00(400 .00(400 .00(400 .00(400 .00(400 .00E400 .00(400.OOEAOO .00(00 .o0E.00 .00(400 .o00 0 .00(400 .00E00.00(400 .00(400 .00(4o0 .00(400 .00(00 .0oE4oo .00(4D0 COE40 .0(40 0E40 0 .0040 0(40 0 E OESO .00400.ooE.oo .oo40o0 or 400 .0oroCoo +0 0 0 oDE+DO.00E400 .000(40 .OOE400 .00O(00 .OO(400 .OE(o00 .00ooo0.00(000 .00E400 OO0E400 .00(400 .00(400 .00(400 .00(400 5.6:E-02 B.03E-02 2.60E-0S .32E-02 1.83E-02 .O0(#00 7.19E-02 6.7N-02 1.14E-01 1I.38-0I 0.36E-02 G0.OE-02 7.5-C-02 -.76E-02 7.19-0 03 tns soq Richard Emch .- bvy 89 59.tif ----Pge --.--B.4 ATHODOS -Radiologi.cal Impact After Termination of %'Y Control of the Disposal Site (All Nuclides)Presented below is a partial listing of the ATMODOS Tape 5 input used in this portion of the calculation.
It corresponds to the outpul.which follows. With the exception of the nuclide data library, a large portion of which was deleted due to space limitations, the listing is complete.1 IVYPI VY STANDARD PROGRAM INFORMATION FILE VY -SEWAGE CONTAM -SOLIDS 1% BY WT -2 ACRES -SHIELD F = 0.242 -OONT. OCCUP 1. .200 44.56FRES)i
.500YESNO NO 0..242 1.NO NO NO 0.1.00--EOR----BO)F- -0 2VYGASRLGAS SIN VY 87 1 1 0 87063023: HN54 4.132E-6 25 MN 54 0060 2.511E-4 27 C0 60 ZN65 4.502E-6 30 ZN 65 CS134 1.715E-6 55 CS 134 CS137 9.366E-5 55 CS 137--EDF--I 5QUERY PATH1WAYS:
SIIORE(1,2,3),BND,ROAD,RESI,RAD,MFEAT,GOAT,COW SHORE1 YESYES SH{ORE2 YESYES SHORE3 YESYES BOUND YESYES ROAD YESYES R.FS I YESYES YESYES RADIUS YESYES MEAT YESYESYFSYES YESYESYES GOAT YESYESYESYES YES YESYES cow YESYESYESYESYES YESYES--)COR----EODF--1 6VYUFMAXVY MAXIMUM INDIVIDUAL USAGE FACPDRS FOR STANDARD PFORBLE2'S 520.00 64.00 310.00 110.00 21.00 .00 .00 12.00 .00 8000.00 630.00 42.00 400.00 65.00 16.00 .00 .00 67.00 .00 8000.00 520.00 26.00 330.00 41.00 6.90 .00 .00 14.00 .00 3700.00.00 .00 330.00 .00 .00 .00 .00 .00 .00 1400.00--EFOR--ENTECH ENGINEERING, INC.P101-EC3 -Page B.4-1 RiF~cha'rdEm'ch
-bvy 89 64.tfl Page 111 1 7VYGSD VY MAX INDIVIDUAL GAS SITE DATA FILE FOR STANDARD 2.00 240.00.00 8766.00 0.0 1440.00.00.00.00 1.0 5.60 2.00 240.00.00 8766.00 0.0 24.00.00.00.00 1.00.00.70 240.00 48.00 8766.00 0.0.00 50.00.50 1.00.00.00 2.00 240.00 48.00 8766.00 0.0 2160.00 50.00.00.00.00.00.70 240.00 48.00 8766.00 0.0.00 6.00.50 1.00.00.00 2.00 240.00 48.00 8766.00 0.0 2160.00 6.00.00.00.00.00 PROBLEIMS.70 2.00 240.00 240.00 480.00 480.00 8766.00 8766.00 0.0 0.0.00 2160.00 50.00 50.00.50 .00 1.00 .00.00 .00.00 .00 SOLUBLE--EOR----EDF--1 8ISTPNBLNUCLIDE LIBRARY FOR ALL DOSE PROGRAMS 89 1 3 1.78E-090.OOE+000.OOE+00 H 9.OE-01 9.0E-01 9.OE-01 9.OE-01 9.3E-01 9.3E-01 4.8E-00 0. 1.05E-071.05E-071.05E-071.05E-071.05E-071.05E-07
- 0. 1.58E-071
.58E-071.58E-071.58E-071
.58E-071.58E-07
- 0. 1.06E-071.06E-071.06E-071.06E-071.06E-071.06E-07
- 0. 1.59E-071.59E-071.59E-071.59E-071
.59E-071 .59E-07 0. 2.03E-072.03E-072.03E-072.03E-072.03E-072.03E-07
- 0. 3.04E-073.04E-073.04E-073.04E-073.04E-073.04E-07
- 0. 3.08E-073.08E-073.08E-073.08E-073.08E-073.O8E-07
- 0. 4.62E-074.62E-074.62E-074.62E-074.62E-074.62E-07 6 14 3.83E-12 C 4.6E203 9.1E+03 4.6E+03 1.8E+03 1.4E+03 1.8E+03 5.5E+00 2.84E-065.68E-075.68E-075.68E-075.68E-075.68E-075.68E-07 2.27E-064.26E-074.26E-074.26E-074.26E-074.26E-074.26E-07 4.06E-068.12E-078.12E-078.
]2E-078.12E-078.12E-078.12E-07 3.25E-066.09E-076.09E-076.09E-076
.09E-076.09E-076.09E-07 1.21E-052.42E-062.42E-062.42E-062.42E-062.42E-062.42E-06 9.70E-061.82E-061.82E-061.82E-061.82E-061.82E-061
.82E-06 2.37E-055
.06E-065.06E-065.06E-065.06E-065.06E-065
.06E-06 1.89E-053.79E-063.79E-063.79E-063.79E-063.79E-063.79E-06 11 24 1.28E-052.50E-08 2.90E-08 1.0E-02 1.2E-02 SOLUBLE 1.2E-02 3.1E-02 SOLUBLE ETC (FOR A TOTAL OF 89 NUCLIDES)--EOR----EDF--I 3VYXQF VY X/QFILE -SPECIAL VALUES -SEWAGE CONTAM. PROBLEI4 -2 ACRE PLOTS FLD 0 0OW MEAT 3.896E-02 3.896E-02 1.236E-04 3.896E-02--EOR--ENTECH ENGINEERING, INC.PIOI-EC3 -Page B.4-2 PrEOPRA; YANICE ATOMIC ELECTRIZ CONPAN'" DEC, INN: ERA.7 REGULATORY GUIDE 1.109, APPENDIX C MODELS FOR CALCULATING DOSE VIA ADDITIONAL PATHWAYS PROM RADIOIODDI1ES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE NOV.1Y77 LIPRARY THE FOLLOWING S NUCLIDES WERE USED IN THIS CALCULATION AUCLIDE RELEASE CURIES:5 MN 54 4.13E-06 27 CO 2.-5E04 30 zN 65 4.0cE-06 C CS 134 I.72E-06 CS 137 9.37E-AýSECTOR FLD DISTANCE 0 tIlETERS)7/O 3.90E-02 (SEC.'N-3) 7/O DEFLETED -.90YE-O (SEC/H-3)DELTA -l.*A4E-D (1/1-2)VY -SEWAGE CONTAN. SOLITDS I' PT AT -ACRES -SHIELD F -0.242 -CONT. OCCUP A PATHWAYS CON1SIDERED GROUND PLANE YES INNALAT IDA YES STORED VEGETAPLCS YES LEAFY VEGETAPLES YES COA RILK YES GOAT NILK NO MEAT YES rb--I o 1 0 VARIAPLE STO TV AORICULTURAL PRODUCTIVITT
(-1/A-2T P SOIL SURFACE DENSITY (KUlE-2I 240 TRANSPORT TIME TO USER ("PS)TP DOlL EXPOSURE TIME (ANS) A76(TE CROP EXPOSURE TINE TO PLUME (IMP)TN HOLDUP AFTER HARVEST (HER) 1441 OP ANIMALS DAILY FEED (KO/DAY)FP FRACTION OF YEAR ON PASTURE FS FRACTION PASTURE WHEN ON PASTURE FO FRACTION OF STORED VEG OROWN IN GARDEN I FL FRACTION Of LEAFY VNE DROWN IN SARDEN rl FRACTION ELEMENTAL IODINE -.Z00 H ADSOLUTE HUMIDITY 3 5.60 (SH/N-3)PC FRACTIONAL EOUILIBRIUM RATIO FOR C-I4 -1.000 VEGETABLES (RED LEAFY.00 T.EN.00 240.00.00 A76A.00.00 .00.00 24.00 COW PASTURE.70.40.00 1N.00 0766.00.00.00 50.00.:0 1.00 (tILE STORED:.00.40.00 18.00 8766.00.00 2160.00"0.00 COAT NILK PASTURE STORED.70 2.00 240.00 240.00 40.00 40.00 8766.00 87A6.00.00 .00.00 2260.00 6.00 6.00 1.00 PASTURE.70 240.00 400.00 8766.00.00.00 50. 00.20 1.00 STOSED 240.00 400.00 RA66.00.00:160.00:0.00 NEAT 1.00 I-00 NNNNRNNNERNNNNNNWNRNNANANENNNWNN$NRNtNNNNNNNA0ANNSNNNNRNRNRNNRNNNINAtSNNNNNWNtNNNN USAGE FACTORS N DOSE D[ELIVERED TO EACH ORGAN NPFROM ALL PATHWAYS CONPINED *VEO LEAFY MILK NEAT INHALATIO4 N X AGE DEO N DONE LIVER KIDrNET LUNG GI-LLI THYROID WHOLE PODY SK1b (KO/TRI (KO/YRD (LI/TR) (KO/YR) (I-S/YR) H (MREA) I ADULT 520.00 64.00 310.00 110.00 OOO.00 N .TýE+O0 I.TAENOO 1.21E+O0 3.O4E400 (.TVENO0 1.16E400 I.:TEAAO 1.37E00 I TEEN 630.00 42.00 400.00 62.00 0000.00 N I.30E#O0 1.3ZEA00 I.T3EAOO 3.91C2400 ITGE+O0 1.1AE#OO I.24E400 1.37E#00 t CHILD 320.00 26.00 330.00 41.00 3700.00 a 1.4OE00 1.41E000 I.Z;EAOO 3.39E#00 1.22EA00 1.16EEO I.2SEAOO 1.37E(00 N INPANT .00 .00 330.00 .00 1400.00 N I.TSE(O0 I.3TE(00 I.:tEAOO 2.A;E+00 1.19E00 I.1AEAOD I.19HE00 1.7E.OO A.I ......$.. ....t:N ADULT DOSES RECEIVED FROM VARIOUS PATHWAYS LIVER KIDNEY LUNG FL SECTOR AT A DISTANCE OF 0 METERS PATNWAY PONE 01-LLI THYROID WHOLE BODY SKIN GROUND PLANE 04 MN 60 CO 61 ZN 134 CS£37 CI TOTAL FOR PATHWAY INHALATION 54 MN 60 CO 65 ZN 134 CS 137 CS TOTAL FOR PATHWAT STORED VEGETABLES 04 MN 60 CO 65 ON 134 CS 137 CS TOTAL FOR PATHWAY LEAFY VESETAPLES M4 MN A0 CO 65 ZN 134 CS 137 CS TOTAL FOR PATHWAY.00 +00 I. ROE-C4 7.9ME-0H!.O3E-04 5.63E-02 ,00E400:00E÷00 E. A3- 02 1.230-03 2.30E-04 1.97E-02-.12E-02.0E000.OOEOO0 1 .76R-04 2.9E-0O;2 43E-03 2.0f2-04 3.57E-03 5:74E-04£ .800-03 7.100-02 7. DOaE-SO B.NOE-02 I.:24E-03 3.I E-03.46E-04 2..6AE-02 3.27E-02 1.230-02 1.R6E-04 3.67E-OA 7.I0E-O;3.33E-03 0.020-SO.OOE+O0 3 E.3E-04 6.08E-04 2. 6NE-02 2.62E-0O:.OOECO0 2.6 !%-03 9. I1E-03 1..OE-02 3.67E-06.00E400 3..E-ED4 2 ,0 E-O 1.13E-03 7.14E-03 1.80E200 4.NOE-03 2.:OE-04 0.70E-03 I .87E#00.OOE#O0 TOE + 00* 00E 4 00 S.6lE-CO;3.0 4E-03 3. IORE-03 OCR +00.ODE+OO DOE* 400 ,.63IE- 06 3.76 E-04 3. 9E-04!.83E-02-.9OE-O4 9 .00-02 9.DOE -01 2 70E- 04 ,*..33E-02* .46E-03 9.76E-06 5,.Z[--04 3.70E-O'.93E-03 3.ý7E-04 1.24E-06.00E400.00El00.OOE000.0TE 00* TOE 400.0OE 00.00E*00 ,T[ 400.000400 ,00E400.000+00 4.30E-03 I .0+E00 2.0 4E-03 4.:8E-03 1.02E-01 1. I&E+00 3.21E-00 4.-9E-03 1,.94040..9,E-02-6,E-O2 1 .6NE-02.403..76E-03.4 7E-04 1.76E-0O 2,.36E-06 3.44R-04 7.06E-04 I.80E-O0 I. BE-03 5.020E-03 I .2.3C 00 3.30E-03:.34E-03 I. 19E-0l 1.37E400 t23 Zt.1.040-03 3.83E-04 3.39E-03 .OOE400 2.04E-03 2.640-03 4.14E-03 PA THW4JAT COW MILK 24 MN 60 CO AS ZN 134 C5 137 CS TOTAL FOR PATHWAY"EAT 54 MN 60 CO 60 ZN 134 CS 137 Cs TOTAL FOR PATHWAY TOTAL ALL PATHS TOTAL ALL PATHS INCLUDINO WNOLE POOT 0060 rPo0 00OUN9 PLANE EXPOSURE SONE.00(+00 1.490-03 9.3:E-02 7.0:E-03 8.63E-03.000400.00 400 3.66E-04 9.67E-06 8.33E-04 1.23E-03 9.000-02 1.:0EO00 LIVER 6.790-07 2.72E-0;4.740-03 1.990-04 4.6:0-03 1.460-02 7.400-07 I. 700 -04 1.230-03 2.300-0: 1.140-03 2,.6E-03 1.2E-03_6E90340 ADULT DOSE0 RECEIVED FROM 4AR20US PATHWA;S (HREM)KILNEY LUNG 2.02E-07 .000400.0000 .00400 3.17E-03 .OO04 0 6.4E0-0 2.13E-02 3.270-03 1.09E-03 6-.10-03 1.11E-03 GI-LLI:,O:E-O6 6499E-04..99E-03 3.4!E-06 I.;,E-04 3.600-03-.:7E-06 3. 00-03 7.7:0-04:..21-02 4.00E-03 1. 29E 01 1.290 400 PLO SECTOR AT A DISTANCE Or 3HTROID WHOLE SOOY.000400 1.29E-07.OOEO40 .200E-05.00O000 2.24E-03.OO0O0 1.2E2-04.E00000 6.32E-03.00t.00 B.70-E03 0 IhTEFS SKI14 2,OE-07.00!4 00 8.;22-04 3.57E-04*I.:22'-03 4.GOE-02 0.10 0E00.00E+00.00E400.000+00-.47[-06 1.31E-04 3.040400.OOEoO0.OOE 00.00E400..00E 0 0.000400.OOE O0.000400.00C.00 1.16E400 1.41E*07 3.76E-04 7.46E-04 1,70E-03 1.27-400 1.3-0400 1.:E+000 041/4071 MT TEEN DOSES REC EIVED FRO,;VAROUS PATNWAAS (MrEM)PONE LIVER KIDNEY LU14G FLO SECTOR AT A DISTANCE OF 0 METERS FATHWAY 0I-LLI THYrROID WHOLE B01DY SKIN GROUND PLANE 54 MN 60 CO 65 ,* 134 CS 137 CO TOTAL FOR PATHWAY INHALATION 54 MN 60 CO AS ZN 1 4 CS 137 CO TOTAL FoR PATHWAY STORED UEOETAPLES 54 M N 60 C0 6 5 2 N 134 CS 137 CS TOTAL FOP PATHWAY LEAPY VOOETAPLES 04 MN 60 CO A5 ZN 134 CS 137 CS TOTAL FOR PATHWAY 4 .30E-03 I. OE#O0:.94E-03!. atE-03 C .02E-01:.05K-03 5.700-03 I.,140-01 1.160+00 1.37E-00.OOr4O0 O0E $00:E14E-03 I.06-03 7.7:E-02 4.63E-03 7.4 E-O0 V,8.E-02 6A49E-05 0OE 0O0 4.00E-04 0.50-04!,G 4Eý00,0 A. v' E03 3.200-04 1.40K-0.3. IE-04 a .0E-02 E.5E-04 0.31 E -O 00 0010 00.0OE4O00.00E$00.00D400 4,290-05 A.1'E-03 3.4-,E-04 1 .1 6 -03 3 .60E -0.7.98E-02 1.06E-01 3-620-02 :.4E4o00 O.20E-02 .0GE+00 1.37E-0'.OOE MOO 1. 770-03 3.740-04 3.37E-.2 I .3E-04 1.97E-03 6.13E-03 , !E-04 4.,46E-02 4.11 E -03 OOE$OO 3.930-03 I.E0-02 ,OOE+O0 OE $+00.0OEl GO: I1.07E-G4 V.GE-03 6.70-03 6,3SE- 04.OOE400*OOE÷O0.00CE00.O OE $00.* GE +O0G-.73E-05 4.4;E-03 A.06E-03 4.I =-OA C)I z C) t lb~0q 3.57E-02 S.37E-02 1.94E-02 6.0IE-03 2.12K-02 .OOE#00 2.33E-02.000400 , 39E-04 2. +3KE-OS 5.63ER-0S 1.050-GO 1,34R-04 4.,4[-0-A,20E-0O 2.99E-03 3.12K-GA.:0':E;0040
- 3. 10 E-04 1.97E-Oz I. OE-O3 ,OOElO0.OOEIO0.00K +00 7.S2K-06 3.95K-G4 2..ISK-0 1.7:E-03 7.OSE-04..71E-07 4.25,E-0.00(400.00K E+00.O00rOEO0.OOE+O0.00 +000 2.07E-06 3.03[-04 2. E--04 1.040-03 2..aE-03 3.6KE-03 1.32E-03 4.020-04 2.0,K-03 .OOK400 1.60E-03
'2 FATHWAT COWMIHLK 34 MN 60 CO 63 ZN 134 CS 137 CS TOTAL FOR PATHWAT MEAT M4 lN 60 Ca 6" 2K 134 CS 137 CS TOTAL FOR PATHWAY TOTAL ALL PATHS TOTAL ALL PATHS I NCLUSINO WHOLE POST COSE ,ROM GROUND PLANE EXPOSURE ROME* 000400.000400 1.44E-04 3.28E-02.000400?.72E-04 7.690-06 6.92E-04 9.7 11-04 1.330-01 1.30E+00 LIVER 13E30-06 6.301-03 7.,930-03 3.40E-04 1.70_-02 2,34E-02 3.63E-07 1.320-04 9.440-0 4 9,.20-04 2.010-03 1.91E-01 1.330+O0 D031S RECEIVEI PROM VA010US PAT6WEYS KIDNEY UI..3.370-07 .00E0O0.OE0000 .0E0400 ,.09E-03 .00r400 1.080-04 4.12E-03 E.790-03 E.230-O3 1.100-02 2.290-03 GI-LLI:.32E-06 8.200-04 3.36E-03 4.230-0+2.4 2-04 4.43E-03 1.160-06 1.720-03 4.000-04 1. 3 1E-03 2.14E-03 1. 2OE-O1 1 .28E0000 FLV SECTOR ,00,:00 ,OOE*00.000400.0004 00.000400.00E.00.OO400 OOE 400.OOE400.0OE400 ,000 400.OOE600 ,OOEf+O0 AT A DISTANCE OF W.OLE SOr-2.24E-07 1.420-04 3 710-03 1.390 -04 3.930-03 9.93E-03 0 SKIN 1.680-07.000E00 6.04E-04 3 E 30-04 9.23E-04 6.92E-02 1.234+00.000 4E:,00.000E4001.00E.00.200E-06 1.220-04 1.2 40-04.74E+00 3.91E400 1.1:0-07 0. B-OE 4 6.400-06 3.230-04 1.07E-03 1.:40400 1.37E000 1.24E#00 Nl-o C)t zb CHILD DOSES RECEIVED FROM VAR0GUS PATHWAYS ( "RE L)LIVER KIDNEY LUNGO rLp SECTOR AT A DISTANCE OP 0 METERS GI-LLI THYROIp WHOLE POTY SKIN PATHWAY PONE GROUND PLANE 54 mN 60 CO 60 ZN 134 CS 137 CS TOTAL FOR PATHWAY INHALATION S4 m N 60 CO 6 5 2Nm 134 CO 137 CS TOTAL FOR PATHWAY STORED VEOETAPLES 54 MN 60 Co 65 ZN 134 CS 137 CS TOTAL FOR PATHWAY LEAFY VH0ETAPLES 04 MN 60 CO 65 ZN I34 CS 137 co TOTAL FOR PATHWAY.OOE+00:.37E-04 1.38!-03 I .0E-01 1.06E-01.OOEO00 3.47C*03 8.63E-04 oSoE-o.a. :2E-G2.0000E HOG.4 6-03 4.310-03 219. E-04 4. 07-0-3 6. 30E-G4 9.754E-0.1.03E-01..06EG04 3.!7E:03 9,24E-03 1,4:E-O!7.74E-02 9 .1 3E-o'1,37E-04 0.46E-04 7,4AE-Go 3.4 6-03 4, 670-03 0 .1E-GO.00E400 I 97E-G4 3.27E-02 3.300-02 5.7E-005 4. 390G4o 43:9E-06 3. 170-GO 3.290-06 3.44 E-04 2.32E-0G 0.270-GO 1,64E-03 6.04E-03 I.1?[÷00 ,3E H03*.760-04 1.20'-00.OOEO00 ,000AO0 9.07(-03 9.:3E-03.00c + 00.04,6H0G 4.64[-04 1,17E-04-.980-02 0,030-06 4. 19E-04 3.00E-G2 O *73E-04 1.700-02 I .62E-03*.64-A06 4.84E-04 I .93E-02 9.86E-06 8.6E-04 9.600-GO 4.030-07* .430-GO 9.99E0-G OOE+00.000 HOG0.0GGE HOG0.OOE400.00E+0G.000o~ 000 0 GOEHOG0.000000.OOE400 ,OOEO00 ,O0o[lO0.00E+00.OOEOO0 ,000 HOG..OOE OG a.30E-03 1.07(000.194E-03 4.70E-03 0.020-01 1. 16t.00 4.800-05 7.02E-03 3. IE-0G 4,760E-0 1. 490 -02:.:8E-02 5.49E-05 9.00E-03 3.770-03 2.990-04 1 .14E-02 2.660-02 3.13E-06 4.6204 3.400-04 5.73E-04 1.39E-03 3.:3E000 3].38E -03 7.34E-03 I. 190E-01 I .37E0000 to, otm to,:to X7 PATHNAY COw MILK 7 4 Am iO CO 65 ZN -134 CS (37 C5 TOTAL FOR PATHWAY NEAT 34 MN 60 CO 65 E.4 134 CS 137 CS TOTAL FOR PATHWAT TOTAL ALL PATHS TOTAL ALL PATHS INCLUDING NHOLE POBT DOSE FRIM.ROUND PLANE EXPOSURE C)tn C)M4 LI,ýt PONE ,OOc4O0.OOE+00 4.49E-03*.33E-04 3.OSE-02.3.6E-0:.00(400* OO 400 4.OSE-0A 1.3 6E-0, I. 27E-03 1.70E-03..33E-01 1.40E+00 LIVER 1.69E-06I.20E-02 5.47E-04 9,E-0.6.46E-07 1. 7E-04 1.09E-03 2.23E-03 1.220-03 2.49E-03 2..43E-01 1.41E(00 CNILD DOSES RECEIVED PEON VARU10U PATHNAYS KIDNEY L"N.4.74(-07 .OOE400.0o0000 .ooEo00 7.74E-03 .OO I.69 E-04 6.0KE(-0 9.61C-03 3.46E-03 1.73E-02 3.(E-03 VI-LLI I .42E-06-.100-03* 4,.0(-04 2.83E-03 0742(-7 B,70L-04 I.91E-04 1.200-07 7.64E-04 1 .07"-03:. 46E-02 I.2.E#00 FLO SECTOR THYR0ID.00C.00*.00(+00.OOE+O 0.00[+0 00.oo00oo.,OOE O0 AT A DISTANCE OP ANOLE P00Y 0. 9E-t4 t.3E03 1.77E-O2 0 I ETERS SKIN I ,9IE-O7 6.VO-ON 6.90E-06 3.97L-04 I .091-03 8,:4E-02 1 .250;400.4oo-Oo3E-00 1. 4E-04 2.2LTE400 3.391400.OOE400.OO400.OOE-O 0.OOE400.0(40 0.00(400 ,OOr$O0 1.16E+00 1.72:-0?A. 63E-0.6.-,6E:-0 4.70E-04 1.a0v-0A I. 32E-03 1.23E400 1.37E+00 1.23E+00 INFANT DOSES 1ECEIVED rEOll VARIOUS FATOWAS(FLD SECTOR AT A DISTANCE OF o tiETE&S P ATHNWA Y GROUND PLANE S4 MN 60 CO 134 CS 137 CS TOTAL FOR PATHWAY PONE LIVER K 15(EY LUrNG lI-LLI THYREOD WHOLE PODY SKIN 4.30E-03 ,.0:E-03 1.05[400 1.23EO00 a.T4(-03 3.38E-03 4.94E-03 :4-0 0.00-01 1_1E-o01 1.16E+00 1.37E+00.00(000 1.2?9-04 2:.4E-02 0.10E-03 3.o60E-0 .OOE+00 2.24E-O0 ,OOE0O0 :.49M-03 .OOE400 1.,40:00 9.O0E-03 .O00(00 3.60E-03 1.070-04 3.490-04 l.S1(04 3.60 03 2.960-04 .00.400 I,3E-04C 5.39(-04 1.490-03 4.030-54 l.9E-04 2.630-06 .00(000 1.E5#-04 6.39E-02 7.0E0-02 4,M9E-02 8P24.-03 1.!4E-04 .00(000 5.26--03 INHALATION 54 hN 60 CO 65 ZN 134 CS 137 C.TOTAL FOR PATHWAY 6.44E-02 7.ý220-2 2.02E-02 1.4"(400 1.04E-02 .OOEN0 v.27E-03 to'Co-M'I mZ STORED VE(ETADLES 54 MN 60 CO A5 ZN 134 CS 137 CS TOTAL FOR PATHNAY LEAFY VEgETAPLES 54 MN 60 CO AS ZN 134 CS 137 CS TOTAL FOR PATHWAY.*0(0[00 .OOE(0 .00OO(0 .OOE000 .00(400 .000000 .00(400.00(400 .004000 .00(000 .0O(400 .00(00..OOE+0 .00(000 .00(EO0 .00(E40 .OE00 .00 000 .0OE+04.00(400 .00(400 .00(400 .00E000 .00E400 .00(400 .00E00.00(400 .0E+0(0 .00E0O0 .OOE400 .OOE000 .00(000 .00(000.0(0[00 .00 000 .00 .00CI00#0000 .OEOO .00E(00 ..OE00.00NOOO0 .OOEO0 .OOE00 0 .0OE-00 .00E000 .00E(00 .OOE000.OOE+00 .00(000 .OOE+00 .OOE400 .00(000 .O0E+O0 .00(E00.OE(O0 .000N00 .00(400 .00(400 .00(400 .OOEO0 .00(000.00E400 .00E(O0 OOE:00 .0000 .00(400 .00(400 .OOE400.00(400 .00000 0 .00E000 .00(400 .00(000O .0.E0400 0(0.*00(+00 OOE#00( .00(00 .0E000 .000000 .0O000 .4OOE00.00E÷00 OO0E+00 ,OOE+00 .0OE+O0 OOE+00 .00E.00 .OOE+OO PATHWAY COW FILK 34 MN 60 CO.4 ZN 134 CI 137 CS TOTAL FOR PATHWAY MEAT 54 "N 60 C0 63 ZN 134 CS 137 CS TOTAL FOR PATHWAY TOTAL ALL PATHS TOTAL ALL PATHS INCLUDING WHOLE Pony DOSE FROM GROUNO PLANE EXPOSURE PONE o00[000 6. 03(-03 5.37R-O0 4.9MZE-02.00(600.00(400.OOE+OO ,OOEO00 Q* 0E+00*OOE400.OOE0O0 1.20E-01 1. 26E+ 00 LIVER 3.14E-06 2.0E-0 4 2.07R-02 I DOER-]3.00E(-02 7.14E-02.o0(too.OOE O00.00(E00.OOE+O00.OOE+00 1.321+00 INFANT DOSES RECEIVES FROM VARIOUS IAFT6AAS'M "C r.", KIDNYT LUNG 6.97E-07 .00R40.00C40! .0000 1.0[O-02 .00(400:.20N-04 I.06'-04 I.3'(~-02 06:E-0::.7-2 6.36t-03 00 -LL I I. 16E-06 1. 73;E-o0 I.73(-02* .ZE-06 I.aoE-o4 I.OIE-O2.OOE 400*00(000* 00( 4 00 SOaR 40 0.OOE400 BSE -02 1.9 E.00 iLO SECTOR THYROID.00EQ00 OD 0(00.00E400.0OE+0( 00.0OE.0400.00o400.OOE+O0.O0E400.00(400* 00(400.00E 400.OOE400 1.16E+00 Al A DISTANCE OF WHOLE POOp 7.13E-07 A.72E-04 9.,4 E-o3 I .OE--04 1. O1- 0 I .42t02O O IETERS OR 14.OOE400*0 00E400.00(4 00.00E400.00(400.0(4O00 A.63E-02 0 0 :+ 400 SOOE 400.OOE 4 00.00(400* 00(400.0OR 4 00 1.42E +00 2..:;BE 400.00(00 ,00(400.OOE400.00(400 1.19(400 1.3?E400 1.19E400 to, I--i Ott,*-0 to)Oto~H 4 toi>2, lb H 4'-0 Ric~h~ard Emch -bvy 89 59.tif ae_2 B.5 ATMODOS -Unplowed-Land Dose Conversion Factors for Radiological Impact Assessment The Tape 5 inputs to ATMODOS for these cases are identical to the one shown in Attachment B.3, the only exception being the isotopic intensities in File 2. In the current computer runs, each isotope was assumed to have an annual release rate which would yield an accumulated intensity of 1 pCi at the end of one year (uniformly spread over 2 acres of unplowed land).ENTECH ENGINEERING, INC.Pi 01 -EC3 -Page B. 5-1 PROGRAM ATIlOVIOS YANKEE ATOlIC ELECTRIC COMPANY DEC, 1955 REV. 7 REGULATORY GUIDE 1.09. APPENDIX C NODELS FOR CALCULATING DOSE VIA ADDITIONAL PATHWAYS PROM RADIIOSDINES ANoD OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE NOV,1977 LIBRARY SECTOR FLD DISTANCE " 0 IMETERS1 X/0 4.63E-04 (SC/H-3SI x/O DEPLETED -4.63E-04 (SEC/N-SI DELTA I.24AE04 II/M-2)VY -SEWAGE CONTAM -ASSUMED 5rC -2 ACR ES SHIELD V
- 0.012 -104 HA OCCUX.A PATHWAYS CONSIDERED GROUND PLANE YES INHALATION YES STORED VAGETABLES YES LEAPY VEGETABLES YES COW MILK YES GOAT MILE NO MEAT YES LYI 0 C.C.C ID I, 0 C C)THE FOLLOWING I NUCLIDES WERE USED IA THIS CALCULATION NUCLIDE RELEASE CURE1.25 MA 54 S.46E-G6 0 G4 cISt HARIADLE STO YV AGRICULTURAL PRODUCTIVITY (KO/N-2)P SOIL SURFACE DENSITY (KO/M-2I 240 T TRANSPORT TIME TO USER E(RS)TM SOIL EXPOSURE TIME (MRS) 8766 TE CROP EXPOSURE TIME TO PLUME (ARS)TH HOLDUP AFTER HARVEST (IHRS) 1440 OF ANIMALS DAILY FEED (KO/DAT)FP FRACTION OF YEAR ON PASTURE FS FRACTION PASTURE AHEN ON PASTURE rO FRACTION OF ZTORED VEO GROAN IN GARDEN I FL FRACTION OF LEAFY VEG GROWN IN GARDEN FI FRACTION ELEMENTAL IODINE -.500 N APSOLUTE HUMIDITY -5.60 (GI/M-3I PC FRACTIONAL EGUILIPRIUN RATIO FOR C-I4 1 1.000 VEGETABLES RED LEAFY.00 2.00.00 240.00:.00 8766.0G.00 .00 P.00 24.00 COW MILK PASTURE STORED.20 2.00 240.00 240.00 49.00 4HG*O 8-6.00 0766.00* GO .00.00 2140.00.0.00 SO.GO.00 I .00 GOAT PA STUR.70 240.00 40.00 0766.00.00.00 6.00.zO 1.00 MILE S TOMED 2.00 240.00 4R.00 8766.00.00 A .00 NEAT PASTURE STORED.70 2.00 240.00 240.00 480.00 480.00 8766.00 8766:00 D.0 .00.00 2(40.oo o0.00 5o.0o.50 1.00.00 1.00 AACORAlR9CRAARXMRMCOMAMORRRARlMAIARRAKACRRP9RRRMRHR99AZACRAAAIAIASAR0KflRIAAAAIMWR USAoE FACTORS P DOSE DELIVERED TO EACH ORGAN N O P~~ROM ALL PATHWAYXSOIIE VEG LEAFY MILK MEAT INHALATION
- AGXE WED BONA LIVER KIDNEY LUNG GI-LLI THYROID WHOLE PODY S01W IRO/TRI IKO/YR) (LI/YRI (KE/YES (M-3/YR)I (NRIEMI ADULT 520.00 A 1.05 S.O00 110.00 9000.00
- 7*Z4£-GO 1.12E-04 8.63E-G0 0 .5 E04 l.97E-O4 7.SAE-0S S.24E-XO _ 4E-OS TEEN 630.00 42.00 400.00 6".00 9000.00 9 7.24E-OS 1.29E-04 9M1£E-0S I.19E-04 1.8RE-04 7.t4R-0i 8.61A-05 8.84E-t0 9 CHILD 220.00 26.00 330.00 41.00 3700.00 .7.54E-0S I-4E-04 9.74E-05 1.09E-04 1.43E-04 7.AE4-X2 9.6MAE-OS 8.R4-OS 0 INFANT .00 .00 330.00 .00 1400.00 9 7.,4E-05 7.71E-OG 7.R[E-05 9.68E-07 7.60AE-0 7.Z'E-05 7,AE-0G 8.OE-0E S 9 ....................-..........
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PROGRAM ATHODOS YANKEE ATOHIC ELECTRIC COMPANY DEC. 19:8 REV. 7 REGULATORY GUIDE 1.109. APPENDIX C MODELS POR CALCULATINO DOSE VIA ADDITIONAL PATHWAYS FROM RADIOIODINES AND OTHER RADIONUCLIDES DISCHARGED To THE ATMOSPHERE NOV.1977 LIPRARY THE PFLLOWING I NUCLIDES WERE USED IN THIS CALCULATION NUCLIDE RELEASE CURIES 27 CO 60 1.07E-o0 SECTOR PLD DISTA14CE 0 IMETERS)X/O 4.63E-04 (SEE/M-31 X/O DEPLETED 4.63E-04 (SEC/H-3)DELTA
- 1.24E-04 (IIH-I VY -SEWAGE CONTAM -ASSUHED SOURCE -2 ACRES -SHIEL P -0.012 -104 HR OCCUr 6 PATHWAYS CON4SIDERED GROUND PLANE YES INHALATION YES STORED VEGETAPLES YES LEAPT VEGETADLES YES COW MILK YES SOAT MILK NO MEAT YES r+0 0 It hI IC~t6I~0 Eat~Ic~H H 1330 U, VARIAPLE STE NV AGRICULTURAL PRODUCTIVITY (KO/M-21 P SOIL SURFACE DENSITY (K0/N-2) 240 I TRANSPORT TIME TO USER (Ers)IS SOIL EXPOSURE TIME IHRS) 876S TE CROP EXPOSURE TIRE TO PLUHE (HRS)SM HOLDUP AFTER HARVEST (HRS) 144A OF ANIMALS DAILY FEED (KR/DAY)FP FRACTION OF YEAR ON PASTURE PS PRACTION PASTURE WHEN ON PASTURE FO FRACTION OF STORED VIEG ROAN IN GARDEN PL FRACTION OF LEAFY VIO GROWN IN GARDEN FI FRACTION ELEMENTAL IODINE -.500 N APSOLUTE HUMIDITY
- 5.60 (OM/H-31 PC FRACTIONAL EOUILIPRIUM RATIO FOR C-14 -1.000 VEGETAPLES ORED LEAFY I.00 2.00 1.01 240.00..00 6766.00.00 .00 0.00 24.00 COW PASTURE.70 240.00 4 .00 6766.00.00.00 10.00.50 1.00 MILK STORED 2.00-40.00 HD.00 6746 .00.00 21o 0000 2)0.00 GOAT MILK PASTURE STORED.70 2.00 240.00 240.00 46.00 49.00 8766.00 6766.00.00 .00.00 2160.00 6.00 6.00.rO 1.00 HEAT PASTURE.70 240.00 480.00 8766,00.00.00 50.00.20 1 .00 STORED 2.00 240.00 6766.00.00 2160.00 50.05 Y)D 0 1.00 1.00 USAGE FACTORS 6 DOSE DELIVERED TO EACH ORGAN 6 FROM ALL PATHWAYS COI411NED 6 VEG LEAPT HICK MEAT INHALATION I AGE 660 a DONE LIVER KIDNEY LUNG O1-LLI THYROID WHOLE SOOY SKIN 6 (KU/YT) (KO/YR) (LI/YRT (KR/TE) (6-3/YR)* (MEEE)ADULT 520.00 64.00 310.00 110.00 8000.00 6 2.21E04 2.2"E-04 2.211-04 3.IAE-04 3.24E-04 2.21E-OA 2.361-04 2.606-04 6 TEEN 630.00 42.00 400.00 62.00 8000.00 2 2.21E-04 2.31E-04 2.21E-04 3.T7E-04 3.ý3E-04 2.21E-04 2.43E-04 2.60E-04 N CHILS 520.00 26.00 330.00 41.00 3700.00 S 2.21E-04 2.36E-04 -.21E-04 3.32E-04 3.04E-04 2.21E-04 2.6GE-04 2.6EO-04 6 INPANT .00 .00 330.00 .00 6400.00 1 2.21E-04 2.22E-O4 .E-O ,9E-04 2.4-04 2.21E-04 2.,3E-04 2.60E-04 O a N$* ~ $
&0)~1 a rn 2 C)a-'C~Co 01 Co PROGRAM ATHODOS YANKEE ATO;IC ELECTRIC COMPANY DEC. 1982 REV. 7 REGULATORY GUIDE 1.109, APPENDIX C MODELS FOR CALCULATING DOSE VIA ADDITIONAL PATHWAYS FROM RADGX00DINES AS'D OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE NOV.1977 LIPRARY THE FOLLOWING S NUCLIDES WERE USED 114 THIS CALCULATION NUCLIDE RELEASE CURIES 30 IN AS 1.61E-06 SECTOR FLD DISTANCE -0 tiIETSEOI/G 4.J3E-04 (SEC/M-J3)
N/S DEPLETED -4.63E-04 (SEC/H-3)DELTA -I.24E-04 (1/NM-)Vy -SEWAGE CONTAM -ASSUMED SOURCE -ACRES -SHIELD F -0.012 -104 NR OCCUP 6 PATHWAYS CEOISDERRE OROUND PLANE YES INHALATION YES STORED VEGETABLES YES LEAFY VEOEIABLES YES CON MILK YES GOAT MIL1 NO MEAT YES Cr r.0 0 0.C)t" I-At', iO C)1 C)'~tHI~t8'ro~h.p (-DI VARIABLE ST[TV AGRICULTURAL PRODUCTIVITY KR/N-21 2 P SOIL SURFACE DENSITY RKG/M-2) 241 T TRANSPORT TIHE TO USER (MRS?TB SOIL EXPOSURE TINE (HRO) 8764 TE CROP EXPOSURE TIME TO PLUME (NRS)TH HOLDUP AFTER HARVEST (MRS) 1441 OG ANIMALS DAILY PEED (RO/DAT)PP FRACTION Of YEAR OA FASTURE FS FRACTION PASTURE WHEN OH PASTURE FG FRACTION OF STORED VEO GROWN IN GARDEN PL FRACTION OF LEAFY VES GROWN IN GARDEN F1 FRACTION ELEHENTAL IOGINE .S2oo" ABSOLUTE HUMIDITY .r.60 (OHM/-3)PC PRACTIONAL EGUILIPRIUN RATIO FOR C-14 -1.000 VEGETABLES lEED LEAPY 2.00 2.00 0.00 240.00 6.00 8766.00.00 .00 0.00 24.00 COW PASTURE.70 240.00 40.00 0766.00.00.00 1.00 IITLK STORED.,00 24.000 48.00 076A.00.00 2160.00 20.00 GOAT PASTURE.70 240.00 49.00 8766.00.00.00 6.00.50 1.00 MILK STORED 2.00 240.00 48.00 8766.00.00 2160.00 6.00 PASTURE.70 240.00 4P0.00 8766.00.00.00:.40 00.710 1.00 STORED.,00 240.00 8766.00.00.160.00 20.00 MEAT 1.00 1.00 attet SS.* t**$ 42 gt*$*takes*$
states .2 la.Tlttttts USAGE FACTORS a BOSE ('ELIUERED TO EACH ORGAN FROM) ALL PATHWAYS COBINEpD WED LEAFY MILK HEAT INHALATION 9 AGE WOE S BONE LIVER KIDNEY LUNG OI-LLI THYROID WHOLE FODGY SKIN *(KG/YR1 (KE/TR) ILI/TR) (ES/YR) (M-3/YR) 8 -IMREM)ADULT 20.00 64.00 310.00 110.00 8000.00 I1.22E-03 3.76E-03 '.:E-03 7.24E-02 2.40E-03 .;20E-O2 1.74E-03 2.9SE-O:;TEEN 630.00 42.00 400.00 62.00 6000.00 0 1.62E-03 S.9E-03 3.60E-03 8.12E-02 2.4AE-03 S.20E-0 2.64E-03 2.98E-O H CHILD 520.00 26.00 330.00 41.00 3700.00 a 3.11E-03 6.21E-03 ,.19E-03 7.2;:.E-05 1.N8-03 5.2OE-OS r.12E-03 2.B9E-O2 a INFANT .00 .00 330.00 .00 1400.00 a 2.21E-03 7.44E-03 3.63E-03 6.7.E-05 6.29E-03 5.20E-O- 3.46E-03 2.98E-05 a 8$ i $ t t tt PROGRAM AT8;t1,OS 7A:'gZ7 4TON(C ELELCRIC LT;VoA;eY D.EC. I'0I, REV. 7 REGULCTORY 0UIDC 1.107. APrPEWDI C MODELS FOR CALCULATIIAO OSE VIA ADDITIONAL PATHMAYS FROM k.DIOIODI1JES AND OTHER KADIOGUCLIDVE DISCNARGED TO IRE ATMOSFNREr NOV.I1r7 LIBRARY THE FOLLOWIAN I NUCLIDES WERE USED IN 10I1 CALCULATI0OI MUCLIDE RELEASE CURIES:5 CS 134 I.ISE-06 SECIOR PLOT
-0 );ETEk'S LUG -4.~LIE -04 YCHI 7.'0 1IEVPLV YTI -4. ..UE-04 IYEC,'I;-31 2ELTT -IIE0 4.<VY -ZgWAtGU LOUT.AM .- ASSIKED 2nU&:CE --ACRES
- 3"IiLV FT io. 1 k , Pf1H8AYS CUNSIVDERED GROUNAD PLAN 7E3IONH 'E$S STOkED VVOIEAiLES-YES LEAVY VPOCTL-L.C YE;COW MILK -'Es GOAT ElL No0;;E111 ;Es c.6 J7 C, a 0 C VARIAPLE:TI tO Io.+TV 7V TF T 1 YE TN aP FS FO FL FP PC AGRICULTURAL PRODUCTIVITY (IRON-:)SOIL SURFACE DENSITY IEO/E-21 24'TRANSPORT TINE TO USER 'MRS)SOIL ERPOSURE TOME Itts) 8761 CROP ESPOSURE TICE[ TO PLUME INRO)HOLDUP AFTER HARVEST (IRI) 1441 ANIMALS DAILY FEED (KO/DAY)FRACTION Of YEAR ON PASTURE FRACTION PATURE WHERN ON PASTURE FRACTION OF STORED ORG ORGAN IN GARDEN FVACTION OF LEAFY YES ORGON IN GARDEN FRACTION ELEMENTAL IODINE -.100 ADSOLUTE NUMID"YY -1.60 (OM/M-31 PRACTYINAL EGUILTIRIUM RATIO FOR C-14
- 1..00 VEIOCT ALE SEED LEAFY 2.00 2-6.00 0.00 240.00.00 .00 7.00 24.00 COw P"ASTURE.70.40.00 4".00.00.00 70.00 1.00 MILK 40.00 2140 00 40.00.00 2)60.D0 70.00 GOAT F A31UEE.70:40.00 40.00 8766.00.00.00 6.00 1.00 STORED:.Do 240$ 00 40.00 V766 .00.00 2160.00 6.00 FEAT rASTURE STORED*70 2.00 240.00 740,00 400. 0 400.00 076,.00 3766.00.00 .00 2000 2160.0'0:0.0" 70.00.50 1.00 1.00 3.00 USAGE FACTORS VES LEAFY MILK MEAT AOE VYE (ES/TI (K/TYR) (L1/1t) I(0/YE)ADULT 520.00 66.10 310.00 110.00 TEEN 630.00 42.00 400.00 67.00 CHILD 720.00 26.00 330.00 41.00 INFANT .00 .00 330.00 .00/ DOSE DELIVERED TI EACH ORGAN *FROM ALL PATHAAYS COMINMED INHALATION S O S OONR LIVER K1DNEV LIMO Il-LLI THYROID WHOLE SOOT STIN CM-I/YE) I ' (nEll) E 0000.00 0 4.04E-04 7.46E-04 3.47E-04 2.19E-04 t.66'E04 1.76E-04 6.39E-0G I.OSR-G4 *8000.00 8 :.44E-04 I.07-03 4.4HE-04 2.:6E-04 1.67ER4 1.76E-04 I.7IE!04 I.02E-04 *3700.00
- lO0E-OS I.79E-07 6,OOE-04 1.17E-04 1.3EE-04 1*.6E-UA 4.SRE-OA 0.807E04 *1400.00 A 5.31E-04 0 I.S6C-04 i3.3-6f 2.260-04 1.03E i*000t 000000tO0-t~to.,.t tt)1t0000tt000000$MiS 100* *I*M010$$t Mitt tOt IWtI 0-U 03: CD PROGRAM ATHMPOS YANKEE ATOMIC ELECTRIC COMPANY DEC. 19'5 REV. 7 w1 REGULATORY GUIDE 1.109, APPENDIX C MODELS FOR CALCULATING DOSE VIA ADDITIONAL PATHUAYS FRON RADI01OVINES AND OTHEE RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE NOV.1977 LIPRARY SECTOR FLD DISTANCE -0 CMETERSI X/O 4.63E-O4 ISEC/T-31 X/I DEPLETED -4.63E-04 (SEC/M-3)DELTA
- l.24E-04 (1/M-2)AY -SEWAGE CONTAM -ASSUMED SOURCE -2 ACRES -SHIELD P -0.012 -104 AR OCCU" 6 PATHWAYS CONSIDERED GROUND PLANE YES NAMALATION YES STORED VEGEIANLES YES LEAFY VEGETAPLES YES COW SILK YES ODAT MILE NO MEAT YES THE FOLLOWINO I NUCLIDES MERE USED IN THIS CALCULATION NUCLIDE RELEASE CURIES 52 CS 137 l.0IE-O6 S 0 71 TI a S 2 7~0 It C CS hi 0 0 to N 9 (I* N 9* 12,0 50 57VARIAPLE S70 TV AGRICULTURAL PRODUCTIVITY 4RK/M-2)r SoIlL SURFACE PENSITT IKO/M-21 241 O TRANFPOET DIME TO USER (NRST I8 SOIL EXPOSURE TIME (ARSI 1764 TE CROP EXPOSURE TIME TO PLUME (4ES)TH HOLDUP AFTER HARVEST (NES) 1440 OF ANIMALS DAILY FEED (KG/DAY)PP FRACTION OF YEAR ON PASTURE FS FRACTION PASTURE WHEN ON PASTURE FO FRACTION OF STORED NED GROAN IN GARDEN FL FRACTION of LEAFY VEG GROAN IN GARDEN Fl FRACTION ELEMENTAL IODNE ..500 H APSGLUTE HUMIDITY -5.60 (GRIM-3)PC FRACTIONAL EOUIIl.rIUH RATIO FOR C-14
- 1.000 NEGETAPLES RED I LEAFY.00 2.00 O.00 240.00.00 8766.00.00 .00:.00 24.00 COW MILK PASTURE STORED.7 2.O00 240.00 240.00 40.00 48.00 8766.00 8766.00.00 .00.00 2160.00 50.00 :0.00.50 (.00 GOAT MILK PASTURE STORES.70 2.00 240.00 240.00 48.00 48.00 8766.00 9766.00.:00 .00.000 2160.00 6.00 6.00.50 1.00 PASTURr 240.00 480.00 8766.00.00.00 50.00.30 I.00 STORED 2.00 240.00 480.00 8766.00.00 2160.00 20.00 MEAT.00 1.00 ISMMtRSM(IMttASRMISSMMMRM8MIttMtt(II(MMMMMt8SIMNMSMSIMMMtItIMMt(MtMM0MtMMIIIMtMMMM USNIE FACTORS I DOSE DELIVERED TO EACH ORGAN I P ROM ALPATHWAYS CIMPINKO VES LEAFY MILE MEAT INHALATION N AGE NED I DONE LIVER SIDNEY LUNG 0I-LLI THYROID WHOLE PODY SKIN 4 (E/YET (KR0/YT) ILI/YE) (EG/YRI (M-3/tR) A (MRER)ADULT 520.00 64400 310.00 110.00 8O000.00 A86E-04 1.07E-04 2.09E-04 1.06E-04 6.33E-O3 SN46E-0S 3.22E-04 6,37E-O5 0 TEEN W30.00 42.00 400.00 63.00 8000.00 S,97E-04 7.75E-04 3.O0-O4 I*OE-04 6.-SE-0t 1ANE-OS 3,06E-04 0.37E-02 CHILD 520.00 26.00 330.00 41.00 3700.00 4 I.33E-03 1.28E053 A..3E-0 1 0,98K-O& A.23E-0O SNAR-0S 2.32K-CA 6.E-05 INFANT .00 .00 330.00 .00 1400.00
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