ML20054G301

Environ Rept for CY81 on Radiological & Nonradiological Parameters

ML20054G301
Person / Time
Site:	Battelle Memorial Institute
Issue date:	12/31/1981
From:	Robert Evans, Paulian J, Stewart D Battelle Memorial Institute, COLUMBUS LABORATORIES
To:
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ML20054G300	List: ML20054G299 ML20054G301
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NUDOCS 8206210398
Download: ML20054G301 (70)

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ENVIRONMENTAL REPORT FOR CALENDAR YEAR 1981 on RADIOLOGICAL AND NONRAD10 LOGICAL PARAMETERS to UNITED STATES DEPARTMENT OF ENERGY CHICAGO OPERATIONS OFFICE Prepared by Environmental Health Physics Nuclear Services Section Contributors:

R. G. Evans and D. G. Stewart Environmental Health Physics Nuclear Services Section J. L. Paulian Facilities Engineering and Operation Section J. E. Wissinger and E. R. Swindall, Operational Health Physics

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Nuclear Services Section J. D. Yesso, R. H. Snider and J. Justus, Radiochemistry Services Nuclaar Materials Technology Section BATTELLE Columbus Laboratories 505 King Avenue Columbus, Ohio 43201

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APPROVAL LIST

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TABLE OF CONTENTS Page FOREKARD . . . . . . . . . . . . . . . . . . . . ......... vii 1

SUMMARY

INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Si te Loca ti on a nd Env i ro nme nt . . . . . . . . . . . . . . . . . 3 King Avenue Site. . . . . . . . . . . . . . . . . . . . . . . . 3 Nuclear Science Area (West Jefferson Site). . . . . . . . . . . 3 ENVIRONMENTAL MONITORING . . . . . ............ ... 7 West s'efferson Site . . . . . ...... ......... 7 Air Radioactive. . . . . . . . . . . . . . . . . . . . . . 7 Water Radioactive. . . . . . . . . .......... 8 Water Nonradioactive . . . . . . . . . . . . . . . . . . . 9 Grass and Food Crops Radioactive . . . . . . . . . ... 10 Sediment Radioactive . . . . . . . ... ...... 10 Soil Radioactive . . ........ .. .... . Io Fish Radioactive ...... .... ... .... Il 11 Background Radiation Levels. .... .......

11 King Avenue Site. .............. ..... .

II Water Radioactive .. ...... . ....

12 EVALUATION OF DOSE TO THE PUBLIC . . . .. . .........

Estimated Radiation Doses to the Public From Emissions from the Battelle West Jefferson Site During CY-1981. . .

12 Atmospheric Discharges . . .... .. .....

12 Liquid Discharges .. ... ...... . .. 12 11

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TABLE OF CONTENTS (Continued)

Page Estimated Radiation Dose to the Public from Atmospheric Di scha rges. . . . . . . . . . . . . . . . . . . . 13 Calculation of Atmospheric Dispersion Parameters . . . . 13 Calculation of Individual and Population Group Doses . . 13 Calculation of the 50-Mile Integrated Population Annual Dose .... ................... 14 Estimated Annual Radiation Dose to the Public from E Liquid Discharges . . . . . ......... ...... 14 5 Radiation Dose from Swiming (External Whole Body) . . . 14 Annual Radiation Dose from Eating Fish . . . . . . . . . 15 "

50-Year Dose Commitment ... ... ......... 15 REFERENCES. . . . . . . . . . . . . ............... 16 Quality Assurance . . . . . . . . . . . . . . . . . . .. 17 APPENDIX ADDITIVE LEVELS DUE TO RADIDNUCLIDE MIXTURE ........ .... A-1 West Jefferson Site . . ... .............. A-2 APPLICABLE STANDARDS .. .. ....... .... .. A-2 Radioactive Standards . . . . . ....... . . A-2 Uncontrolled Area (Site Boundary) .. ........ .. A-2. A-3 Air ......... ....- - - '- #~2' #~3 l Water . .. . . .. - '- #~3 iii I

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TABLE OF CONTENTS (Continued)

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.u Mixture . . . . ...... . . . . . . . . . . A-3 Grass and Food Crops . . . . . . . . . . . . . . A-4 Y Soil and Sediment. ..... . . . . . A-4 _

Fish ....... . . . . . . . . . . . . A-4 Nonradioactive Standards (Water) . . . . . . . A-4 N External Radiation - General Public . . . A-4 2

External Distribution List . . .. . . . . . . . . A-5. A-6, A-7 M

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I' LIST OF TABLES Page Table 1. Population Distribution Within 10-Mile Radius from Site . . . . . . . . . . . . . . . . . . . . . . 18 Table 2. Sumary of Atmospheric Radioactive Emissions -

West Jefferson Site . . . . . . . . . . . . . . . . . 19 Table 3. Gama Emitting Radionuclides Identified in the JN-1 (Hot Cell Stack Particulate Emissions) . . . . . 20 Table 4. Sumary of Liquid Radioactive Emissions - West Jefferson Site (Measure of Effluent from Sanitary Sewerage System into Big Darby Creek - Figure 4 3 De s i g na ti on 010 ) . . . . . . . . . . . . . . . .... 21 g

Table 5. Nonradiological Sampling for West Jefferson Site January 1. 1980, to December 31, 1931 . . . . . . . . 22 Table 6. Summary of Grass Analyses . ............ 23 Table 7. Suma ry of Food Crop Analyses . . . . . . . . . . . . 24 Table 8. Summary of Silt Analyses ...... ....... 25 Table 9. Sumary of Soil Core Analyses . . . . . . . . . . . . 26 Table :0. Sumary of Gamma Isotopic Analysis of Soil Core Samples ...................... 27 Table 11. Sumary of Fish Analyses .............. 28 Table 12. External Background Radiation Levels Within 3/4 E Mile Radius - West Jefferson Site . . ... ... 29 g

Table 13. External Background Radiation at Perimeter Security Fence - West Jefferson Site . . . . . . . . . . . . . 30 Table 14. Concentration of Radioactivity in Liquid Discharges to Columbus Municipal Sanitary Sewerage System. . .

31 Table 15. Sumary of Site Boundary Air Sample Analyses .... 32 Table 16. Sumary of Off-Site Air Sample Analyses . .... 33 Table 17. Sumary of Environmental Water Sample Analyses. . . 34 I

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LIST OF TABLES (Continued) J. .

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Table 18. Radionuclide Composition of BCL Effluents for CY 1981 . 35 u Table 19. Summary of Maximum Annual Radiation Dose to an Individual . .. 3.

and the Nearest Population Group (Town of West . . -

Jefferson) from Atmospheric Emissions. . . . . . . . . . 36 . .,

Table 20. Estimate Annual Integrated 50-Mile Population Doses. . . 37 ' -

v Table 21. Estimated Radiation Dose to a Swimmer (External Whole Body). . . . . . . .. . . .. . .. . . 37 y.

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Table 22. Estimated Radiation Doses from Eating Fish Caught in , 1 Big Darby Creek Near the Battelle West Jefferson ' "--

Site ............... . .. .. .. 38 Table 23. 50-Year Dose Commitment for the Maximum Individual ' -

From Effluents Released During DY 1981. . . . . .

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Table 24. 50-Year Dose Canmitment for 80-Kilometer Population '

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From Liquid Effluent, Released During CY-1981 .

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Table 25. 50-Year Dose Crr.nitment for 80-Kilometer Pooulation ^ '

From Airborne Effluents Released During CY-1981 . . . . 41 '..

• i-Table 26. Parameters for West Jefferson Site Airborne Release Dose .. ,

Calculations ....... . . .

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LIST OF FIGURES I:

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Figure 1. Regional Map for King Avenue and West Jefferson Sites . . . . . . . . . . . . . . . . . . . .... . 43 Figure 2. Local Vicinity Map of King Avenue Site. . . . . . . . . 44 Figure 3. Local Vicinity Map of Nuclear Sciences Area West Jefferson Site . . . . . . . . . . . . . . . . . . 45 Figure 4. Nuclear Sciences Area West Jefferson Site . . . . . . 46 Figure 5. Map of Grass, Foodcrop and Soil Sampling Locations. . . 47 Figure 6. Map of Site Boundary Air Sampling Locations and Battelle Lake and Darby Creek Water Sampling Locations. 48 Figure 7. Battelle's Columbus Laboratories King Avenue Site . . . 49 =

Figure 8. Map of TLD Locations within 3/4 Mile Radius of the ,

Nuclear Sciences Area . . . . .... .. . .... 50 Figure 9. Map of TLD Locations at the Perimeter Security Fence. . 51 Figure 10. Map of Columbus and Vicinity Showing Off Site Air Sampling Locations. . . . . . . . .. . .... 52 Figure 11. 1981 Wind Rose Pattern for West Jefferson Site .... 53 Figure 12. 1970 Population Within 50 Miles of the West Jefferson Site. . . . . . . . .. . . . . 54 Figure 13. 1970 Population Within 10 Miles of the West .

Jefferson Site. ............... ... 55 I

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FOREWARD This report was prepared by Nuclear Service's Environmental Health Physics group. The radiological monitoring data were supplied by environmental and operational health physics staff. The nonradio-logical data were compiled by the environmental protection representative of the Facilities' Engineering and Operation Section.

The radicar.alyses of environmental air and water samples for gross radioactivity and gama isotopic determinations were perfome<2 by Radiochemistry Services, Nuclear Material Technology Section.

Radioanalyses of air, water, grass, sail, food crop and soil samples for specific radionuclides were performed by the Eberline Instrument Corporations' Radiochemistry Laboratory, Albuquerque, New Mexico.

Nonradiological analyses of environmental water samples were performed j by the Columbus Water and Chemical Testing Laboratory, Columbus, Ohio.

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SUP9%RY Environmental data collected during CY-1981 show continued compliance by Battelle Columbus Laboratories with all applicable state and federal regulations.

In addition to the routine monitoring of liquid and atmospheric emissions at the King Avenue and West Jefferson nuclear sites, data were collected for various environmental media including air, water, grass, fish, food crop, sediment and soil. These samples were taken from the area surrounding.

the West .'efferson Nuclear Site.

In general, off-site levels of radionuclides attributable to the West Jefferson nuclear operation were indistinguishable from background levels.

The data are summarized as follows.

West Jefferson nuclear operations during 1981 caused no distinguishable impact on concentrations of airborne radionuclides or on external radiation doses measured adjacent to and at distances up to 3/4 mile from the nuclear site. (See page 20. Table 3 and page 29 , Table 12).

Radionuclides observed in food crop, grass, creek bottom sediment, and soil samples were all attributed to either atmospheric nuclear tests or natural sources. (See pages 23-28.

Tables 6, 7, 8, 9,10, and 11).

Low level concentrations of a few radionuclides released to Darby Creek from the West Jefferson nuclear site were less than 1.5% of the most restrictive manual chapter guide for an individual radionuclide released to an unrestricted area. Concentrations observed at down-stream sampling l locations were indistinguishable from background levels.

! (See page 21. Table 4.)

The estimated radiological dose resulting from the nuclear operation at the West Jefferson site was calculated for the maximum individual, nearest popula-tion group, and the integrated fif ty mile population surrounding the site.

(the maximum individual is a hypothetical person situated as to receive the

, maximum radiation exposure possible.) These dose calculations take into

! account both the measurable levels of envirc rnental contaminants and the

! impact of radionuclides known to have been released but not found in l detectable concentrations during the years environmental sampling program.

l The doses are summarized as follows:

The annual whole body dose to the maximum individual during CY-1981 was calculated to be less than 3 mrem. This estimate includes contributions from airborne and aquatic recreation pathways.

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Il The maximum annual dose to a single organ received from all pathways was 9.7 mrem to the bone from eating fish. These l doses can be compared with the standards of Manual Chapter W!

0524 of 500 mrem /yr for the whole body and 3000 mrem /yr for the bone marrow. (See pages 35, 36-37, Tables 18,19-21.) '

Airborne emissions from the Wes'. Jefferson nuclear site resulted in an annual whole body dose to the population within 80-km (50 mile) radius of the nuclear site of 3 about 6.3 x 10-" person-rem. Liquid effluents during 1981 contributed very little (about 2.9 x 10-5 person-rem) to the g

total population dose. This estimate may be compared with the approximate 2.3x105 person rem /yr received annually from natural background radiation. (See page 38. Table 22.)

The maximum " fence-post" exposure rate for 1981, 0.03 mrem /hr, occurrtd just outside the security fence on the east side E of the JN-1 Hot Cell Facility. Radiation for the Hot Cell 5 radioactive waste handling facilities was primarily responsible for the slight increase in background radiation levels. 3 (See page 29. Table 12 .)

5 Releases of low-level concentrations of radioactivity to the Columbus municipal sewerage system from the Building 3 (U-235 Processing Facility) were less than 4". of the most restricted Manual Chapter guides for discharges of mixtures into sanitary sewerage systems. (See page 31 Table 14.)

The 50-year dose commitment computations for the maximum individual and the 80-km (50 mile) population have been prepared and are included in the dose evaluation section of this report. Three modes of exposure were considered in the calculations of the 50-year dose commitment:

(1) chronic inholation of radioactive mixture using an atmospheric diffusion model. (2) chronic ingestion of a radioactive mixture through terrestrial and (3) aouatic pathways.

(See pages 39-41, Tables 23-25.)

Discharces of sanitary water from the West Jefferson nuclear site into Darby Creek under the National Pollution Discharoe Elimination System (NPDES) pennit were all within the parameter limits specified in the permit. (See page 22 , Table 5.)

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-3 INTRODUCTION Site Location and Environment The activities perfonned under Contract No. W-7405-ENG-92 are conducted at BCL's King Avenue Site and the West Jefferson (Nuclear Science Area)

Site. A 50-mile area map showing both sites in presented in Figure 1.

Figsre 2 and 3 show property boundaries. Varicus NRC licensed activities are also conducted at both sites but are not addressed in this report.

However, the effluents considered in this report are a result of both contract and license activities.

King Avenue Site A local vicinity map of the King Avenue Site is shown in Figure 2. The U-235 Processing Facility, located on the first floor of Building 3, is the nuclear materials management point for all transactions involving nuclear material at the King Avenue Site. Building 3 also houses the Melting Facility, first floor south end, and the Power Metallurgy Laboratory, basement floor at the north end of the building. These are the only other areas in Building 3 utilizing contract material. Activities involving contract and license materials were very limited during 1981, tnerefore, effluent monitoring at Building 3 was limited to liquid discharges to the Columbus municipal sewerage system.

The 10-acre King Avenue Site is bounded on the north by an area of about 50 acres comprising The Ohio State University intramural sports practice field, on the west by the Olentangy River, and on the south and east by dwellings (two to four families).

Nuclear Science Area (West Jefferson Site)

A local vicinity map of the Nuclear Science Area is shown in Figure 3.

The Nuclear Science Area is located on a 1000-acre tract approximately 17 miles west of the King Avenue Laboratories as shown in Figure 1. The JN-1 Hot Cell Facility and the JN-2 Vault Facility are presently the only facilities at the Nuclear Science Area where contract material is handled.

These facilities, along with the decomissioned Research Reactor and the JN-4 Plutonium Laboratory which is, being decontaminated are located within a 10-acre fenced security area.

A 10-mile-radius circle whose center is at the site includes a small portion of Columbus having a population of about 60,000. The only other significant population center near the site is West Jefferson, Ohio, located about 2 miles from the site, with a population of 5,747.(1)

(See Table 1.)

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I Operations at the Nuclear Sciences Area include various activities such as irradiated reactor fuel element studies conducted at the JN-1 Hot Cell Facility and the materials accountability and storage operations conducted at the JN-2 Vault Facility. e There are 18 industries located within the 10-mile radius. Of these, there are only four which employ more than 100 people. These are White-Westinghouse Electric Corporation, General Motors, Janitrol Aircraft, and Capitol Mfg. Company. Each of these Is located at least 8 miles from the facility. Closest to the site are three small industries within West Jefferson which individually e.mploy less than 60 people. The primary agricultural activity in the area is raising field crops such as corn and 3 soybeans. Approximately 10% of the land area in agricultural use is devoted to pasturing beef and dairy herds.

g During the last 14 years, two major highways have been completed near the West Jeferson Site, I-70 and I-270. The junction of these highways, which occurs near the eastern edge of the 10-mile perimeter around the Nuclear Science Area, has proven to be a popular area for industrial growth.

It is estimated that the industrial population has shown an increase l equivalent to that of the general population in this area, i.e., two and 3 one-half times the 10-mile population distribution for 1970. Most of the growth has taken plats near the outer limits of Columbus; however, the larger employers, e.g., General Motors and White-Westinghouse, have actually decreased their number of employees.

The predominant geographical feature in the two-county region surrounding the West Jefferson Laboratories is Big Darby Creek which flows from north to south on the border of Madison and Franklin counties. The Nuclear Sciences Area is located about 0.42 km (1380 ft) west of Big Darby Creek g and about 1.6 km (1.0 mile ) south of I-70.

I The use of the creek is limited to fishing and occasional assumed swimming.

It is too shallow for boating and is not used as a source for drinking water. The annual average flow is 3.28 x 1011 liters. Treated sanitary and laboratory waste water from the West Jefferson Site is discharged into the creek. .The total measured volume during CY-1981 was 1.38 x 10* liters.

A 32-acre man-made lake is located just south of the Nuclear Sciences Area on Battelle property. Water in this lake is not used for consumption and the use of the lake is limited to fishing and boating.

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5 Weather conditions in the area are moderate. The average annual precipita-tion is approximately 98.8 cm (38.9 in.). Winds predominate out of the south or west except during the summer months when a high frequency is observed out of the southwest. The average annual wind speed is about 19.4 km (12.0 miles) per hour.

The impact of BCL operations on the health and safety of employees and the public is evaluated routinely at BCL by an environmental monitoring program which has been in existence since 1955. Tne basic objective of the Environmental Monitoring Program is to evaluate the effectiveness of the waste management program in maintaining the concentrations of radioactive and nonradioactive wastes so that effluent levels are main-

. tained as low as practicable and well within applicable standards. All effluents involving polluting materials are contained within the operating facilities to the extent possible and are disposed of as packaged wastes by authorizad services. Any releases of gaseous and liquid wastes to the environment are carefully controlled and dispersed to ensure that concen-trations are as low as practical within recommended standards. Radionuclides in particulate form are removed form exhaust stack effluents by the use of high-efficiency particulate air (HEPA) filters. The air effluents are filtered first at the points of operations,i.e., glove boxes, hoods, test cells, and finally at the stack release point by one or two banks of HEPA filters in series. Solid radioactive wastes are packaged and shipped off site for burial at approved burial sites. Radioactive gases i present in fuel pins under examination at the Hot Cell facility are drawn off and absorbed for subsequent disposal with solid wastes. The resideal gases trapped in the fuel matrix or otherwise released are monitored continuously by effluent monitors including a system for iodine-131 detection and diversion to a charcoal bed if warranted.

A new sanitary sewerage system, which is operated in accordance with State of Ohio regulations, handles all sanitary sewage generated on the West Jefferson Site. The liquids are first treated in a 2500-gallon septic tank and then released to a contained 2160 sq-ft sand and gravel filter bed.

From toe filter bed the effluent goes to a chlorinating system prior to release to Big Darby Creek.

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I As part of the monitoring regimen of the program, water, grass, fish, food I

crops, sediment, and soil samples are collected :outinely from the environment at distances up to 8 km (5 miles) from the West Jefferson Site boundaries.

These samples are analyzed for the specific radionuclides handled at the nuclear facilities. The sampling techniques, analyses, and counting methods are those best suited for the determination of radionuclides of interest and are capable of detecting levels as low as normal background.

The results for the analyses for calendar year 1981 are provided in this report. Error limits, when given, reflect the counting error in the data at the 95% confidence level.

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7 ENVIRONMENTAL. MONITORING West Jefferson Site Air Radioactive In-stack air samplers continuously monitor the exhaust stack effluent release from each facility to assess the effectiveness of systems con-trolling airborne emissions. Ten continuous stack monitors ensure detection of any inadvertent release of radioactive materials and provide data for the prompt assessment of the environmental impact, if any. (See Figure 4.) Particulate samples of the effluent are collected from each exhaust stack. The particulate samples are collected on two types of filter paper, GVB-60 and Type E glass fiber. The air is sampled at an average rate of 2.8 x 10 cm 3

/ min. The filters are changed weekly, which represents average sample volume of 285.5 m3 Analyses are perfomed on a weekly basis for plutonium-239 for stacks 006 through 008, gross alpha for stacks 001 through 004, 011. 013, and 014, gross beta activities for stacks 001 through 004, 012. 013, and 014. In the plutonium-239 analysis, an isotopically pure plutonium-239 source is used as an internal standard in an alpha pulse height analyzer. The results  ;

reported represent total average annual concentrations at the stack and also at the site boundary as calculated from stack sample data. The site boundary concentrations, reported in Tables 1 and 2 due to the various exhaust stack locations were calculated by dividing the individual stack concentration by the appropriate atmospheric dilution factor (ADF) which is obtained from the following equation, 8172 x 1010

• ADF = Stack vol/yr in liters.

The annual atmospheric dispersion parameters were calculated using the Air Quality Display Model computer program (See Reference 6, Page 16).

At the site boundary the weighted average concentration of plutonium-239 emitted from stacks 006 through 008 (Table 2) was less than 0.0008% of the RCG value listed for soluble material for uncontrolled areas. The RCG value for soluble plutonium-239 is applied since the solubility for the material is not known even though there is every reason to assume the material is the oxide and thus relatively inso*.able. For averaging purposes, samples below the minimum detection limit are assumed to be the value of the limit. All particulate filters are analyzed af ter a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> decay to reduce the contribution of short-lived radioactivity.

The weighted average concentration of the alpha and beta mixture, emitted from stacks 001 through 004, 012, 013, and 014 was less than 0.08%

of the RCG value at the site boundary. The results are sumarized in Table 2.

• 8172 x 1013 represents the atmospheric dilution factor at the site boundary obtained using the Air Quality Display Model computer program (See Reference 6). Tnis factor is modified based on the individual exhaust stack volume employed in the equation,

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Based on routine monthly gama ray analyses of in-line system charcoal gas sampling cartridges installed in Stacks 001 and 002, no concentration of iodine-131 was found above the minimum detectable limit. The air is monitored at a rate of 1.3 x 105 cm3/ min. This represents a weekly average sample volume of 1.3 x 103 m3 The weighted average concentration of krypton-85 released from Stack 001, 002, and 013 was 0.005% of the RCG value at the site boundary. The concentra-tions were calculated by using strip chart recorder data from the gaseous monitors on exhaust Stacks 001, 002, and 013. The results are sumarized in Table 2. (There is a discussion of RCG's in the appendix of this report.)

Identification is radionuclides in the JN-1 stack particulate emissions from Stacks 001 through 004, 013, and 014 was made by monthly gama ray analyses of weekly stack air sample filters composited over a 4-week period.

Camma ray analyses were performed using an intrinsic germanium detector coupled to a Canberra Model 8180 multi-channel analyzer. The concentrations of the radionuclides identified were all less than 1.84 x 10**% of the g applicable RCG values at the site boundary. (See Table 3.)

5 Supplementary air sampling was perfomed at four site boundary locations during 1981. (See Figure 6.) These air samples were collected continuously and analyzed on a weekly basis for mixed alpha and beta activities.

The average concentrations of activity at each of the site boundary locations were a factor of s10 higher than the average mixed alpha and beta activities found at 6 off-site background air sampling locations surveyed weekly at distances varying 5 to 44 miles from the Nuclear Sciences Area, (See page 35. Table 15.) Bervlium-7 was the primary radionuclide found in the site boundary air samples and was not attributable to stack .

releases at the nuclear site.

Water Radioactive Sampling of all liquid effluents, from the Nuclear Sciences Area, to Big Darby Creek is performed using continuous water sampling system. The liquid effluents consist of the liquid discharge from a conventional sanitary sewerage system incorporating a 2,500-gallon septic tank and a contained 2,160 -ft2 filter bed. (See Figure 4.) The effluent samples are analyzed weekly for gross alpha and beta activity is suspended and dissolved fractions. Any sampling exceeding 3 x 10~8 t.Ci/ml* receives a supplementary gamma isotopic (GeLi) analysis and/or an alpha spectrometric analysis as necessary.

The weekly samples are held, composited, and analyzed specifically for plutonium-238, iodine-129, strontium-90, radium-226, and radium-228 at the end of each month. The concentrations of gross alpha and gross beta activity in suspended and dissolved fractions as well as the concentrations of specific radionuclides identified in the sample are sumarized in Table 4. In g most cases the activity in the samples is due to a mixture of nuclides. The 5

RCG value for unidentified radionuclides in unknown concentrations released to an uncontrolled area, DOE Order 5480.1, Chapter XI, Attachment XI-1. W I

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9 The average average concentration of the mixture was 10.56% of the RCG.

concentrations of identified radionuclides in the m L iurs were 1.02% of the RCG for iodine-129, 0.001% of the RCG for plutonium-238 and plutonium-239, 0.49% of the RCG for strontium-90, 0.0002% of the RCG for cobalt-57, 0.9% of the RCG for radium-226, 1.33% of the RCG for radium-228, 0.0004%

for lead-212 and 0.012% of the RCG for uranium-235.

Supplementary water samples are collected weekly 20 yards above and 20 yards below the sanitary drain outfall at Darby Creek. Weekly water samples are also collected below the Battelle Lake dam and in the drain spillway at Darby Creek. (See Figure 6.) The supplementary water samples are analyzed weekly for mixed alpha and beta activity. The average concentration of total activity in the down stream water samples were less than 39% of the RCG (3 x 10-e uC1/ml) for release of mixed alpha and beta activity to uncontrolled areas. (See Table 17.)

Water Nonradioactive Presently, Ifquid effluents discharged from the West Jefferson Facility are subject to the restrictions of our National Pollutant Discharge Elimination .

System (NPDES) Permit which presently is being renewed under the ConsolidatedBattelle Permits Section of the Resource Conservation and Recovery Act (RCRA).

monitors and reports on a monthly basis to the Ohio Environmental Protection Agency (CEPA) and the U.S. EPA. Table 5 includes a list of the parameters for which BCL is presently required to analyze and report.

The data listed in Table 5 represent an average of the monthly data collected during tne twelve month period commencing January 1,1981, and ending December 31, 1981, and are required under the limits or restrictions set forth in BCL's NPDES Permit. The table serves to illustrate actual performance against those limits or restrictions defined in BCL's permit.

The data provided for the North Sanitary Sewer and the JN-4 storm sewer wereSince the condition obtained in accordance with the BCL NPDES Permit.

NPDES Permit were determined by the Ohio EPA following an extensive study of the Scioto River Basin, of which Battelle's West Jefferson Site is a part; and discharges are within the allowable discharge limits, the data reflect the effectiveness of BCL's waste water management.

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I 10 Grass and Food Crops Radioactive Grass and food crop samples are collected from the surrounding area. l The intent of this portion of the Environmental Monitoring Program is 5 to determine whether there is uptake and concentration of radionuclides by plant or animal life. Where possible, sampling sites are chosen at maximum deposition locations predicted by meterological studies. Grass and food crop (field corn) samples are collected at varying distances and directions within a 5-mile radius of the Nuclear Sciences Area as shown in Figure 5. Sampling locations falling into the same directional quadrant of the nuclear site are composited. The samples are analyzed for plutonium-239, plutonium-238, and strontium-90. A qualitative analysis by gamma scan (GeLi) is also perfomed. The results of the grass and food crop analyser are sumarized in Tables 6 and 7. The maximum concentration of strontium-90 detected in grass samples was 0.410.13 pC1/g. The average concentration of strontium-W in tield corn and soybean samples was 0.11 1 0.09 pCi/g and 0.003 1 0.015 pCi/g for cesium-137.

Plutonium-238 and plutonium-239 average concentrations were 0.0012 +~

0.0006 pC1/g for all samples taken of grass and food crops.

Sediment Radioactive Silt samples are collected semiannually at two locations, i.e., Darby Creek 20 yards above and 20 yards below the point of sanitary effluent release to Darby Creek. (See Figure 4.) The purpose of collecting silt samples is to estimate the inventory of certain radionuclides deposited in this waterway and document for future reference. The silt samples are analyzed for plutonium-239, plutonium-238, and strontium-90. A quantitative gamma isotopic (GeLi) analysis is also performed. The results of the analyses are summarized in Table 8. Concentrations of strontium-90 in silt samples collected above and below the effluent release point were 0.28 + 0.02 pCi/g and 0.25 + 0.02 pCi/g, respectively; for plutontun-239, 0.002 1 0.002 pCi/g, and for plutonium-238, 0.002 1 0.002 pCi/g and 0.001 1 0.002 pCi/g, respectively.

Soil Radioactive W

Soil samples are collected annually from fourteen locations at varying distances and directions within a 5-mile radius of the Nuclear Sciences Area. Locations falling into the same directional quadrant from the 3 nuclear site are composited. (See Figure 5.) The soil samples ar' analyzed for plutonium-238, plutonium-239, and strontium-90. A quali-5 tative analysis by gama scan (gel 1) is also perfomed. The results of the analyses are sumarized in Table 9. The concentration of strontium-90 in soil samples ranged from 0.16 + 0.02 to 0.47 + 0.04 pCi/g with an avercge concentration of 0.26 1 0.02 pfi/g. The average concentration of plutonium-239 was 0.002 + 0.007 pC1/g and the pluton.um-238 average concentration was 0.008 + 07009 pCi/g for all soil samples collected. Gamma

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isotopic analyses of the soil samples showed the average concentration of cesium-137 to be 0.5010.02 pCi/g ud 102 1 0.20 pCi/g for Lead-212.

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i 11 Fish Radioactive Fish samples were collected from Darby Creek and Battelle Lake over a nine month period and composited for analyses on a quarterly basis. The fish samples were analyzed for plutonium-238, plutonium-239, and strontium-90.

A quantitative gamma isotopic (Gell) analyses are also performed. The results of the analyses are summarized in Table 11. Average concentrations of plutonium-239 in fish samples taken from Darby Creek were 0.0002 1 0.0007 pCf/g and 0.0007 + 0.0010 pC1/g for plutonium-238. The average concentration of strontium-90 in fish samples taken from Darby Creek was 0.17 + 0.03 pCi/g.

and 0.047 + 0.023 pct /g for cesium-137. Fish taken from BattelTe Lake had average concentrations of plutonium-239 and plutonium-238 of 0.0008 + 0.0009 pC1/g and 0.0003 + 0.0010 pCi/g. respectively. Average concentrations of strontium-90 and cesium-137 in fish samples taken from Battelle Lake were 0.21 + 0.03 pCi/g and 0.06 + 0.03 pCi/g, respectively.

Background' Radiation Levels The external radiation background levels at the West Jefferson site are continuously monitored at 39 dosimetry stations using comercially available environmental TLD packets. (See Figure 8 and 9.) All TLD packets are changed and evaluated each calendar quarter. The annual exposure average at the site boundary for the 39 dosimeter stations was 0.13 rem or 25% of the 0.5 rem limit established for the general public. The results are sumarized in Table 12 and 13.

King Avenue Site Water Radioactive Sampling of all liquid discharges from the Building 3 (U-235 processing Facility) sump to the Columbus municipal sewerage system is performed on a monthly basis. (See Figure 7.) This discharge consists of the liquid wastes from the building laboratory drain systems. The building sump samples are routinely analyzed for gross alpha and gross beta activities.

Any sample exceeding 4 x 10-7 uC1/ml* receives a gamma isotopic (gel 1) analysis and/or an alpna spectrometric analysis as necessary.

Sample analyses are perfomed monthly on the Building 3 sump samples.

The concentrations of gross alpha and gross beta activity are summarized in Table 14. The average concentration of the mixture was less than 3.7% of the RCG for release to a public sanitary sewerage system. For averaging purposes, samples below the minimum detection limit are assumed to be the value of the limit.

Total releases of radioactivity during CY-1981 from the West Jefferson and King Avenue sites are summarized in Table 18.

• RCG value for unidentified radionuclides in unknown concentrations released to a public sanitary sewerage system. DOE Order 5480.1, Chapter XI.

Attachment XI-1.

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I 12 I

E EVALUATION OF DOSE TO THE PUBLIC Estimated Radiation Doses to the Public from Emissions from the Battelle West i

Jefferson Site During CV-1981 The BCL Environmental Monitoring Report for CY 1981 presents data which provide infomation for detemining those sources of environmental radiation resulting from past or current nuclear activities and those due to atmospheric nuclear tests or natural radioactivity. Contributions from BCL's nuclear operations were undistinguishable from other sources with only two exceptions. These include minimal airborne releases of mixed fission products from Hot Laboratory activities and very low concentrations of mixed fission products in liquid effluents at the West Jef ferson Nuclear Sciences Area. The radiological impact of BCL's nuclear activities is calculated from the quantity of radionuclides 3 measured in effluents from operating facilities in 1981, and from 5 residual radionuclides in stream sediment from past operations.

Atmospheric Discharges Measured releases and ground level annual average concentrations at the site boundary during 1981 for the West Jefferson Site are sumarized in g Table 2. The site boundary, which determines the perimeter for uncontrolled g exposure, is considered coincident with the downwind position from the facility where the annual ground level concentrations will be highest.

This point is on BCL property but cutside the security fence. Analyses of the data in Tables 2 and 3 show that the total mixed fission product (MFP) beta releases for 1981 amounted to 39.5 uti with a total average concentration at the site boundary of 1.55 x 10-16 aC1/ml. Based on isotopic analyses of the stack effluents from the JN-1 facility, the l principal radionuclides were determined to be cobalt-60, cobalt-57, g cesium-137, lead-212, cerium-141, cerium-144, strontium-90, antimony-125, cesium-134, europium-152 and uranium-235. An average composition of the effluents containing these radionuclides emitted form the five stacks of the JN-1 facility was calculated form tne isotopic 3 concentrations given in Table 3, and this was used in evaluating the dose from the MFP beta releases. The total krypton-85 emission was 7.96 Ci with a corresponding average concentration at the site boundary of 3.25 x 10-11 uCi/ml. The total plutonium-239 emissions were 0.28 uCi. Review of JN-1 facility operation for 1981 indicates that most of the gross alpha reported was due to plutonium-239. Therefore, all the alpha emissions are a considered to be plutonium-239 onip' with an annual average concentration at the site boundary of 1.68 x 10- uCi/ml. 5 Liquid Discharges Measured aqueous releases and effluent concentrations during 1981 for the West Jefferson Site are sumarized in Table 4. The concentration values apply to the water discharged into Big Darby Creek af ter passage through a conventional leaching bed. Based on knowledge gained from an isotopic I

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13 inventory of radionuclide concentrations in the leaching bed, emissions should be due to very limited elution from the leach bed of contaminants that were delivered to the bed in past years. Therefore, the alpha l

activity is considered to be primarily uranium-238 and the gross beta act.vity should contain only relatively long-lived radionuclides.

Estimated Radiation Dose to the Public from Atmospheric Discharges Calculation of Atmospheric Dispersion Parameters In all cases on-sitemeteorological data were used as input to compute the annual Display average Model computer dispersion program p@a(ameters for the 1, modified for site. The localized Air Quality applications, was used to generate the required X/Q data for calculating dose to the maximu:n individual. Thus, annual average X/Q values were developed for a series of concentric rings extending from the site boundary out to a distance of 50 miles. (Refer to Figure 1.) The annular rings were broken down into sixteen sectors corresponding to the nonnal wind rose pattern. (Refer to Figure 11.)

Calculation of Individual and Population Group Doses The annual radiation dose to persons from gaseous or particulate radio-nuclides discharged into the atmosphere was calculated for a person continuously immersed in an infinite hemispherical cloud containing the radionuclides. Table 2 lists cloud concentrations at the site boundary which were estimated from the X/Q data noted in the above paragraph. The estimated composition for the MFP source was used to specify individual nuclide concentrations, and critical organ doses were calculated assuming the more sensitive biological form (soluble or insoluble) was present.

Doses arising from the alpha activity emissions were based on plutonium-239, liberated entirely as the insoluble oxide form. The maximum dose estimate obtained for an individual and for the nearest population group are sumarized in Table 19.

The estimate off-site doses listed in the table are very low compared to the raagimum permissible exposures (MPE) which have been recommended by the ICRPbl and other groups for the general public. The MPE values recommended for an individual are: bone - 3 rem /yr, GI tract - 1.5 rem /yr, whole body -

0.5 rem /yr, skin - 3 rem /yr, thyroid - 3 rem /yr, lung - 1.5 rem /yr, and kidney - 1.5 rem /yr. The recommended values for a populaticn group are one-third of these values. Therefore, from Table 19 it may be seen that the largest fraction of MPE occurs to the skin and is 0031 of the recommended limits at the site boundary. In addition, exposure of persons to natural background radiation in the area would be less than 0.13 rem /yr as measured by TLD stations. Therefore, atmospheric emissions from the site (Table 2) led to estimated radiation doses which are approximately 0.75%

of that expected from natural background.

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I 14 Calculation of the 50-Mile Integrated Population Annual Dose The curculative population dose was determined using the individual radigtion dese, wind rose data (Figure 11), and the figures from the 1970 censustli for estimated geographic distribution of the population in the various sectors srourd the site out to a 50-mile radius (see Figure 12). Using the release data given on page 19 under " Atmospheric Discharges" and annual atmospheric dispersion around the site, the integrated population dose calculation produced the estimated 50-mile annual person-rem doses listed in Table 20. The values given in this table may be compared against the integrated person-rem /yr dose that would be expected for the population group due t0 natural background.

Since the level of natural background radiation would be essentially constant over the whole area, the corresponding person-rem /yr value is simply the product of the to;al population and the natural background radiation value.

Using a natural background of 0.13 rem /yr and a total 50-mile population figure of 1.50 x 106 produces an integrated population dose from natural background of 2.0 x 105 person-rem /yr. The total body dose caused by emissions from Battelle's West Jefferson Site is less than 3.15 x 10-7% of that due to natural background radiation.

Estimated Annual Radiation Dose to the Public from Liquid Discharges Radiation Dose from Swimming (External Whole Body)

It is not known if any of the area below the outfall on Big Darby Creek is used for swiming purposes; however, such use could be possible.

Swimmers are assumed to receive an external radiation dose from being submerged in water cantaining radionuclides which are anticipated to be W present in the liquid effluent. The treasured emissions at the outfall were summarized in Table 4. Only the beta releases were used in calculating the external rJdiation dose to potential swimmers, since the less penetrating alpha emissions do not make a significant contribution to the total body dose.

Using standard decay energy valaes, the estimated doses for a swimmer who might spenc 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in the water each week from June to September 30 were obtained a , shown in Table 21 Results are given for two cases; one where the swimmer stays in the water near the outfall (dilution factor of .10) and the other where the swimmer remains well downstream such that the discharged activities are completely mixed with the annual average stream flow of Big Darby Creek.

Radiation Dose Due to Boating and Water Skiing Big Darby Creek is too small to allow boating and other water recreation sports. Thus, there will be no dose from these activities.  ;

Radiation Dose from Drinking Water i Water from Big Darby Creek below the outfall is not used for drinking prior to its confluence with the Scioto River according to tne U. S. Geological Survey; therefore, there will be negligible dose contribution from this source.

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15 Annual Radiation Dose from Eating Fish There may be limited fishing in Battelle Lake and along Big Darby Creek but no estimate of the extent of this activity is available. Radiation dose to man can occur from eating fish which have resided in water which contains radionuclides from the liquid effluent. The concentration of an individual radionuclide in the fish (uC1/g dry wt.) is assumed to be directly related to the concentration of the radionuclidg n the water in which the fish reside multiplied by a bicaccamulation factor.t8{1 In calculating the radiation of fish per year, taken from Battelle Lake and Big Darby Creek either a short distance below the outfall (water dilution factor of 10) or well downstream where tne effluent has become completely mixed with the annual average stream flow. Internal radiatian doses were estimated on the basis of analytical data given in Table 11 for fish samples taken from Darby Creek and Battelle Lake.

Comparison of the data in Tables 21 and 22 show that fish consumption is expected to be the dominant exposure pathway for persons from liquid emissions at the Battelle West Jefferson Site. However, individuals in this area would routinely be exposed to natural background radiation at levels of about 0.13 rem /yr. Therefore, maximum doses resulting from liquid emissions from the site should have been a small fraction of that produced by natural background.

i 50-Year Dose Commitment Tables 23,24 and 25 of this report provide estimated 50-year dose commitments to the maximum individual and the 80-kilometer population from one-year of exposure. Also given for terrestrial and aquatic pathway exposures, is the estimated 50-year accumulated dose to the maximum individual (and the 80-kilometer population from 50 years of continuous exposure to the I? residual environmental contamination lef t by the one-year release. The ridionuclide composition of effluents reported for 1981 is shown in Table 25 Since these quant 1 ties of radionuclides, when dispersed in large volumes of air and water, were generally undetectable in the off-site environment, dcse models (References 10 and 11) were employed to assess the resulting radiological dose impact. Code DACRIN was used to estimate doses from chronic inhalatiun of a radioactive mixture using an atmospheric diffusion model.

Code PABLM was used to estimate doses from the chronic ingestion of a radioactive mixture through terrestrial an' '; Mic pathways.

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16 REFERENCES (1) U.S. Census,1970 Population Data. Dayton, Ohio, Standard Metropolitan Statistical Area.

(2) Operational and Environmental Safety Division. Environmental Protection.

Safety, and Health Protection Reporting Requirements DOE Order 5484.1 m U. S. Department of Energy, Washington, D.C., February 1981. g (3) Scioto River Basin Waste Load Allocation Report for the 303 (e)

Continuing Planning Process for Water Quality Management.

(4) ICRP Publication 2. " Recommendations of the International Commission on Radiological Protection, Report of Committee II on Permissible Dose for Internal Radiation." Pergamon Press,1959.

(5) Operational and Environmental Safety Division, Environmental Protection, Safety, and Health Protection Programs for DOE Operations. DOE Order 5480.1, U.S. Department of Energy, Washington, D.C. , May 1980.

(6) TRW Systems Group, " Air Quality Display Model" Report PB-189194 (Contract PH 22-68-60), November 1969.

(7) U.S. NRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man 5 From Routine Releases of Reactor Effluents for Purpose of Evaluating Compliance With 10CFR Part 50, Appendix 1."

(8) DOE /EP-0023, A Guide for Environmental Radiological Surveillance at USDOE su installations, Revised July 1981.

(9) J. R. Houston, D. L. Strenge and E. C. Watson, DACRIN - A Computer Code for Calculatinq Organ Dose From Acute or Chronic Radionuclide Innalation, BNWL-8-389, PNL, Richland WA, 99352, August 1975.

(10) B. A. Napier W. E. Kennedy, Jr. and J. K. Soldat, PABLM- A Computer Program to Calculate Accummulated Radiation Doses From Radionuclides in the Environment. PNL-3209, PNL, Richland, WA, 99352, March 1980.

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17 -

Quality Assurance Several methods are used to assure that the data collected each year are representative of acutal concentrations in the environment. Extensive environmental data are collected to eliminate an unrealistic reliance on only a few results. Newly collected data are compared with historical data for each environmental medium to assure that current values are consistent with previous results. This allows for timely investigation of any unusual results. Samples are collected using identical methods near to and far from the nuclear site, as well as upstream and downstream on Darby Creek, to provide for identification of any net differences that may be attributable to the West Jefferson nuclear operations. These prscadurcs, in ccr.juncticn with a program to demonstrate the accuracy of radiochemical analyses, assure that the data accurately represent environmental conditions.

The majority of the routine radioanalyses for the BCL environmental surveillance program are performed at the radiochemistry facility located at the West Jefferson nuclear site. Environmental samples requiring specific isotopic analysis are sent to Eberline Instrument Corporation's Albuquerque Laboratory, Albuquerque, New Mexico. Both laboratories maintain internal quality assurance programs that involve routine calibration of counting instruments, daily source and background counts, routine yield determinations of radiochemical procedures, and replicate analyses to check precision. The accuracy of radionuclide determination is assured through the use of standards traceable to the National Bureau of Standards, when available.

Assurance of the dose calculation quality is provided in the following ways.

Since doses are similar from year to year, a comparison is made against past calculated doses and any differences are validated. All computed doses are double checked by the originator and by an independent third partj who also checks all input data and assumptions used in calculation.

Information necessary to perform all of the calculations are fully documented.

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I TABLE 1. POPULATION DISTRIBUTION WITHIN 10 MILE RADIUS FROM SITE I

Distance Radius Population 1.500 feet 2.500 feet h I *II' 682 2 miles 3,000 10.000 0 i es 100.000 l

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TABLE 2. SUPNARY OF ATMOSPHERIC RADIDACTIVE EMISSIONS - WEST JEFFERSON SITE CY-1981 Stack 10-2 Number of Volume Site Percentage of Stack Stack 1030 Activity HDL Range - Stack BoundaryI ,I RCG at Site Species Locations Samples liters /yr pC1/yr 10 34 pC1/mi 10~14 pct /mi 10 14 pC1/mi 10 18 pCi/mi Boundary (a)

Gross a 001 52 3.17 0.004 0.007 <MDL-0.01 0.013 + 0.013 0.04 + 0.04 9.73 Gross e 001 52 3.17 1.59 0.004 <MDL-114.00 5.01 [ 0.06 19.42 { 0.23 Gross a 002 52 11.70 0.04 0.007 < MOL-0.34 0.033 + 0.014 0.47 + 0.20 13.84 Gross e 002 52 11.70 2.22 0.004 < MDL-18. 70 1.90 [0.05 24.2210.72 Gross a 003 52 3.63 0.004 0.007 < MDL-0.10 0.011 + 0.017 0.05 + 0.07 Gross e 003 52 3.63 0.37 0.004 < MDL-9.4 3 1.01 [0.06 4.49{0.27 2.27 Gross a 004 52 1.44 0.05 0.007 <MDL-11.70 0.358 + 0.071 0.63 + 0.12 56.75 Gross 8 004 52 1.44 9.24 0.004 < MDL-994.00 64.00 10.45 112.87[0.79 Gross a 013 52 1.11 0.002 0.007 < MDL-0.12 0.018 + 0.013 0.02 + 0.02 0.62 Gross 8 013 52 1.11 0.10 0.004 < MDL-17. 50 0.90 [0.05 1.22[0.07 g Gross a 014 52 2.02 0.003 0.007 < MDL-0.01 0.01 + 0.01 0.030 + 0.027 0.50 Gross 8 014 52 2.02 0.08 0.034 < MOL-5.02 0.0310.04 0.96 [0.10 Gross a 012 52 2.48 0.014 0.007 < MDL-1.22 0.058 + 0.012 0.17 + 0.03 0.68 Gross 8 012 52 2.48 0.114 0.004 0.16 1 2.33 0.46 [0.03 1.37[0.09 239 006 52 0.38 0.014 0.01 < MOL-3.63 0.357 1 0.065 0.17 1 0.03 0.03 Pu 239 007 26 1.51 0.062 0.01 < MDL-5.62 0.411 1 0.095 0.76 1 0.17 0.13 Pu 239 Pu 008 26 1.59 0.084 0.01 < MDL-14.10 0.530 1 0.092 1.03 1 0.18' O.17 Activity, MDL, Range, Stack Site Boundary, uC1/yr 10-s pC1/ml 10-4 pCi/ml 10-a pCf/ml 10-12 pCi/ml 85 Kr 001 (c) 3.17 1170464.40 0.30 <MDL-69.30 3.69 14.30 0.48 Kr 002 (c) 11.70 6158937.80 0.30 <MDL-26.10 5.26 75.42 2.b1 85 Kr 013 (c) 1.11 634800.00 0.30 <MDL-9.00 5.72 7.77. 0.26 (a) Site boundary concentrations calculated from stack concentration data using annual atmospheric dispersion parameters calculated using the Air Quality Display Model (see Reference 7 page (b) RCG - for mixed alpha and beta activity, 2 x 10-14 pC1/ml; esKr 3 x 10- }computerprogram. pC1/ml; 2 39Pu 6 x 10-34 pCi/ml.

(c) 85 Kr concentration calculated by evaluation of data on strip chart recorder used with gaseous stack monitor.

TABLE 3. GAMMA EMITTING RADIONUCLIDES IDENTIFIED IN THE JN-l (HOT LAB) STACK EMISSIONS CY-1981 10-6 Stack Composite Volume Site (c)

Location Percent of (d)

(a) Stack (b) 1010 Activity, MDL, Range, S ta c.k . Boundary, RCG at Species Figure 4 Samples liters /yr pC1/ml 10-15 pCi/mi 10 15 pCi/ml 10-35 pC1/ml 10-18 pC1/mi Site Boundary 144 Ce 001 12 3.17 0.05 1.45 <MDL-27.70 1.64 + 1.08 0.64 + 0.42 0.32 On2 12 11.70 0.44 1.45 <MDL-45.40 3.78 7 1.43 5.4172.05 2.70 003 12 3.63 0.07 1.45 <MDL-23.70 1.97 T 1.13 0.87 7 0.50 0.43 004 12 1.44 0.05 1.45 <MDL-28.90 3.73 7 1.87 0.66 7 0.33 0.33 013 12 1.11 0.07 1.45 <MDL-32.80 6.33 + 1.46 0.86 + 0.20 0.43 014 12 2.02 0.03 1.45 <MDL-20.50 1.71 T 1.14 0.42 T 0.28 0.21 I37 Cs 001 12 3.17 3.78 1.05 <MDL-2740.00 119.00 + 2.00 46.12 + 0.77 9.22 ~

002 12 11.70 0.48 1.05 "

<MDL-28.10 4.13 T 0.63 5.92 T 0.90 1.18 003 12 3.63 0.04 1.05 <MDL-12.60 1.05 + 0.50 0.47 + 0.22 0.09 004 12 1.44 3.13 1.05 <MDL-1480.00 217.00 7 3.00 38.27 I 0.53 7.65 013 12 1.11 0.02 1.05 <MDL-19.80 1.65[0.48 0.22[0.06 0.04 235 U 001 12 3.17 0.10 1.00 <MDL-12.50 3.20 + 0.72 1.24 + 0.28 31.00 0 02 12 11.70 0.60 1.00 <MDL-17.50 5.14 T 0.78 7.36 7 1.12 184.00 003 12 3.63 0.16 1.00 <MDL-16.50 4.49 I 0.80 1.99 I 0.36 49.75 004 12 1.44 0.04 1.00 <MDL-15.00 0.27 7 0.84 0.05 T 0.15 1.25 013 12 1.11 0.03 1.00 <MUL-8.62 2.51 7 0.65 0.34 I 0.09 8.50 014 12 2.02 0.08 1.00 <MDL-13.20 3.91[0.76 0.96[0.19 24.00 (a) Only those radionuclides which contributed to critical organ doses to the maximum individual greater than 1 x 10-7 rem /yr are listed.

(b) Identification of radionuclides in stack particulate emissions was by ganina ray analysis of stack particulate air filters.

(c) Site boundary concentrations calculated from stack concentration data using annual atmospheric dispersion parameters calculated using the Air Quality Olsplay Model (see Reference 7 page ) computer program.

I3 (d) RCG: Cs 5 x 10-10 pC1/ml; I44Ce 2 x 10-10 pC1/ml; 235U 4 x 10-12 pC1/ml.

M M M M M M M M M M M M M M M M M M M E E M

TABLE 4.

SUMMARY

OF LIQUID RADI0 ACTIVE EMISSIONS - WEST JEFFERSON SITE (MEASURE OF (FFLUENT FROM SANITARY SEWERAGE SYSTEM INTO BIG DARBY CREEK - FIGURE 4. DESIGNATION 010)(a)

CY-1981 Average Number of Activity, MDL, Range, RCG Percentage Species Samples pC1/yr 10-8 pC1/ml 10-8 pCl/ml Concentra 10-9 pCi/ml(btion } 10-8 pC1/mi of RCG Gross a 52 8.16 0.05 <MDL-2.74 5.91 1 0.02 10(c) 10.56 Gross e 52 6.42 0.09 <MDL-1.08 4.65 1 0.20 O

Sr 12 2.04 0.10 <MDL-0.29 1.48 1 0.75 30 0.49 238 Pu 12 0.08 0.009 <MDL-0.02 0.06 1 0.02 500 0.001 3 239 Pu 12 0.06 0.009 <MDL-0.01 0.04 1 0.02 500 0.0008 57 C0 12 1.20 0.1 <MDL-1.04 0.87 1 1.68 40,000 0.0002 129 1 12 0.84 0.01 <MDL-0.17 0.61 1 0.51 6 1.02 l 226 Ra 12 0.37 0.004 <MDL-0.50 0.27 1 0.11 3 0.90 228 Ra 12 0.55 0.01 <MDL-0.10 0.40 1 0.62 3 1.33 I

Pb 12 0.11 0.1 <MDL-7.74 0.08 1 0.02 2000 0.0004 235 U 12 4.86 0.01 <MDL-3.28 3.52 1 3.33 3000 0.012 (a) Annual average flow in Big Darby Creek = 429 cu ft/sec = 3.82 x 10 II liters /yr. Rate at which liquid effluents discharge = 1.38 x 106 liters /yr.

(b) Isotopic data for effluents released at this location were obtained from monthly composite samples.

(c) RCG - Mixture of alpha and beta activity; 3 x 10-e pCi/ml. (If it is known that 129g , 226Ra, and 228 Ra dre not present, the ilmiting value of i x 10-7 pCi/mi may be used.) See Appendix.

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TABLE 5. NONRAD10 LOGICAL SAMPLING FOR WEST JEFFERSON SITE January 1,1981 to December 31, 1981 Pe rmit Requirements Discharge Limitations North Sanitary System Sewer ) L ading Concentration g)

Eg/ Day JN-4 Storm Sewer (d) Kg/ Day Other Units Avg. Max. Min. Avg. Avg. Max. Hin. 30 Day Daily 30 Day Daily Flow Rate (gal / day) 4365 8640 1440 -

3120 4680 0 (b) (b)

Residual Chlorine 0.21 0.4 0.0 .0028 (a) (a) (a) -

0.5 (og/1) l pH Value (S.U.) 7.72 8.18 6.54 -

7.95 8.22 7.43 6.0 to 9.0 Rj Fecal Caliform 12.0 65.0 0.0 -

(a) (a) (a) 200 400

(#/100 ml)

Total Suspended 4.75 18.0 0.0 .1104 (a) (a) (a) 0.49 0.99 10 20 Solids (mg/1)

Temperature ( F) (a) (a) (a) -

58.5 60 57 -

90 l

1 B.O.D. (5 day)(mg/1) 3.74 4.3 1.8 .0614 (a) (a) (a) 0.49 0.99 10 20 (a) Sample analysis for this parameter was not required by our NPDES Permit.

(b) No restrictions for flow under our NPDES Permit.

] (c) Sampling site location No. 010 (d) Sampling site location No. 011.

(e) Permit requirement discharge limitations based on NPDES Permit #N404-CD.

(f) Flow rate 0.013 mgd.

I Note: Data for site No. 010 based on 8 months activity discharge that could be analyzed.

Data for site No. 011 based on 3 months activity discharge that could be analyzed.

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l 25 TABLE 8.

SUMMARY

OF SILT ANALYSES CY-1981 pCi/q dry wt.(a)

Location (b) Number 90 238 239 Figure of Samples Sr Pu Pu A (20 yd abue outfall) 2 0.28 + 0.02 0.002 + 0.002 0.002 + 0.002 B (20 yd below outfall) 2 0.25 + 0.02 0.001 + 0.002 0.002 + 0.002 Note: No standards for radionuclides in silt have been established.

90 (a) Minimum Detection Limit for Sr in silt is 0.01 pCi/g dry wt.

238 239 Minimum Detection Limit for Pu and Pu in silt is 0.002 pCi/g dry wt.

(b) The collection of silt samples at these locations, where silt deposition and accumulation should be at a maximum, was based on observatiens of the average flow pattern of Big Darby Creek in the vicinity of the outfall.

TABLE 9. SUK'iARY OF S0ll CORE ANALYSES' CV-1981 Location (a) Number of }

Composite pCi/q dry wt.

(Direction and Distanct 238 239 90 137 from the Nuclear Science Are a) Samples Pu Pu Sr Cs N5rth7uad 6.4 km (4.0 miles) 8.0 km (5.0 miles) 2 0.0010 + 0.0029 0.0020 + 0.0%4 0.16 + 0.02 0.32 + 0.03 East Quad 1.6 km (1.0 miles) 3.2 km (2.0 milc;)

6.4 km (4.0 miles) 5 0.005 1 0.011 0.019 + 0.015 0.47 + 0.04 0.62 1 0.04 7.2 km (4.5 miles) 8.0 km (5.0 miles) $

South Quad 0.8 km (0.5 miles) 3.1 km (1.9 miles) 2 0.0000 + 0.0009 0.0028 + 0.0032 0.029 + 0.008 0.29 + 0.03 West Quad 4.8 km (3.0 miles) 6.4 km (4.0 miles) 8.0 km (5.0 miles) 3 0.0033 1 0.0082 0.002 1 0.013 0.33 + 0.02 0.70 + 0.04 On Site ----------------- 2 0.0015 1 0.0042 0.018 1 0.010 0.32 1 0.02 0.59 1 0.04 Note: No standards for radionuclides in soil have been established.

The Environmental Protection Agency's proposed federal radiation protection guidance for exposures to transuranium elements in the environment has recoimiended a reference level of 0.2 pCi/m2 for soil contamination.

(a) Locations are shown in Figure 5.

(b) Minimum Detection Limit for 8

Pu and 'Pu in soil is 0.0009 pCl/g dry wt.

Minimum Detection Limit for 90 S r in soil is 0.008 pCi/g dry wt.

Minimum Detection Limit for 137Cs in soil is 0.03 pCi/g dry wt.

M M M M M W W M M M M M M E M E E E E E E E

TABLE 10.

SUMMARY

OF GAMMA ISOTOPIC ANALYSIS OF S0IL CORE SAMPLES CY 1981 Location (0irection and Distance from the Nuclear Science Area)I*I North Quad East Quad South Quad East Quad 8.0 rm (5.0 miles) 1.6 rm (1.0 miles) 0.8 kn (0.5 miles) 4.8 Km (3.0 miles) 3.2 rm (2.0 miles) 3.1 rm (1.9 miles) 0.8 Km (5.0 miles) 6.4 km (4.0 miles) 7.2 Vm (4.5 miles) On Site g_ 0.8 rpLLLO miles)

Composite Samples 1 5 2 3 2 Nuclide Average Concentration pCi/g (dry) wt. m 40 20.0 + 1.0 19.0 + 1.0 20.0 + 1.0 K 20.0 + 1.0 17.0 + 1.0 208 1.5 + 0.2 1.4 + 0.2 TL 1.4 1 0.2 1.1 + 0.2 1.4 1 0.2 214 1.2 + 0.1 0.54 + 0.04 1.0 + 0.1 Pb I.0 1 0.1 0.80 + 0.04 214 0.98 + 0.05 1.0 + 0.1 81 1.1 + 0.1 0.90 + 0.05 1.1 + 0.1 212 Pb 1.6 + 0.2 1.8 + 0.1 I.7 + 0.2 1.6 1 0.2 1.8 + 0.2 I

Cs 0.32 + 0.03 0.62 + 0.04 0.29 + 0.03 0.70 + 0.04 0.59 + 0.04 Note: No standards for radionuclides in soil have been established.

(a) Locations aie shown in Figure 5.

(b) Minimum Detection Limit for nuclides (in pC1/g dry wt.) are as follows:

40K 1.0, 2081L 0.2, 214Pb 0.04, 21481 0.05, 212Fb 0.20, 137Cs 0.03

TABLE 11. SUMPiARY OF FISH ANALYSES CY-1981 Number of pCi/g dry wt.

Period of Composite 238 239 Location [,) 137 90

, Collection Samples Pu Pu Cs Sr Darby Creek ist qtr. (c)

Battelle Lake 1st qtr. (c)

Darby Creek 2nd qtr. 1 <0.0022 <0.0022 <0.075 0.10 + 0.01 Battelle Lake 2nd qtr. I <0.0022 <0.0022 <0.075 0.10 + 0.01 Darby Creek 3rd qtr. 1 0.0004 + 0.00% 0.0008 + 0.0008 0.100 + 0.021 , 0.11 1 0.02 Battelle Lake 3rd qtr. 1 0.0003 1 0.0012 0.0003 1 0.0007 0.035 1 0.028 0.20 1 0.03 Darby Creek 4th qtr. 1 0.0000 1 0.0003 0.0007 1 0'.0014 0.025 1 0.029 0.26 1 0.03 g Battelle Lake 4th qtr. 1 0.0004 + 0.0009 0.0013 + 0.0012 0.085 + 0.026 0.23 + 0.03 Note: No standards for radionuclides in fish have been established.

(a) Fish samples were collected from various locations within Battelle lake. Fish sam es from Darby Creek were taken at various distances within 1000 f t downstream from the sanitary outfal pee tigure b).

90 (b) Hinimum Dett: tion Limit for Sr in fish was 0.01 pC1/g dry weight, 0.07 pCi/g dry weight III Cs, and 0.0003 pCi/g dry weight for 238 Pu and 239 Pu.

(c) No fish sam;les were collected during the first quarter of CY-1981.

l M M M M M M M M M M M M MM M M M M M M M M

29 TABLE 12 EXTERNAL BACKGROUND RADIATION LEVELS WITHIN 3/4-MILE RADIUS-WEST JEFFERSON SITE CY-1981 Location and Exposure to TLD in Rem Distance (a) Ist Qtr. 2nd Qtr. 3rd Qtr 4tn Qtr. Total for Year Southwest 400 ft <0.030 <0.030 <0.030 0.040 <0.130 2400 ft <0.030 <0.030 <0.030 0.030 <0.120 4050 ft <0.030 <0.030 <0.030 0.030 <0.120 West 500 ft <0.030 <0.030 <0.030 0.030 <0.120 2070 ft <0.030 <0.030 <0.030 0.030 <0.120 Southeast 1200 ft <0.030 <0.030 <0.030 0.040 <0.130 3300 ft <0.030 <0.030 <0.030 0.030 <0.120 South 1350 ft 0.030 <0.030 <0.030 0.030 <0.120 1800 ft <u.030 <0.030 <0.030 0.030 <0.120 3600 ft <0.030 <0.030 <0.030 0.030 <0.120 East 1380 ft <0.030 <0.030 <0.030 0.060 <0.150 Northeast 1200 ft <0.030 <0.030 <0.030 0.040 <0.130 Northwest 1320 ft <0.030 <0.030 <0.030 0.030 <0.120 North 1500 ft <0.030 <0.030 <0.030 0.040 <0.130 (a) Refar Figure 8. Average total for year <0.125.

l' l I

)

30 TABLE 13. EXTERNAL BACKGROUND RADIATION LEVELS AT PERIMETER SECURITY FENCE - WEST JEFFERSON SITE CY-1981 Location Distance (

d lst Qtr. 2nd Qtr.

Exposure to TLD in Rem 3rd Qtr. 4tn Qtr. Total for Year I

Southwest 100 f t JN-3 <0.030 < 0.030 < 0.030 <0.030 <0.120 150 ft JN-2 <0.030 < 0.030 < 0.030 <0.030 <0.120 175 ft JN-1 <0.030 < 0.030 < 0.030 <0.030 <0.120 West 75 f t JN-2 <0.030 < 0.030 < 0.030 <0.030 <0.120 150 ft JN-3 <0.030 < 0.030 < 0.030 <0.030 <0.120 Southeast 150 f t JN-4 (0.030 0.040 < 0.030 0.050 *0.150 200 ft JN-1 <0.030 < 0.030 < 0.030 0.030 <0.120 240 ft JN-1 0.040 < 0.030 < 0.030 0.040 *0.140 250 ft JN-1 < 0.030 0.040 < 0.030 0.040 < 0.140 South 150 f t JN-2 <0.030 < 0.030 < 0.030 0.030 <0.120 160 ft JN-1 <0.030 < 0.030 < 0.030 0.030 <0.120 3 190 f t JN-1 'O.030 < 0.030 < 0.030 0.040 < 0.130 5

East 150 f t JN-4 < 0.030 < 0.030 < 0.030 0.040 <0.130 230 ft JN-1 < 0.030 < 0.030 < 0.030 0.040 < 0.130 240 ft JN-l < 0.030 0.040 0.040 0.060 <0.170 Northeast 150 ft JN-4 <0.030 < 0.030 'O.030 0.040 50.130 225 ft JN-4 <0.030 < 0.030 <0.030 0.030 <0.120 250 f t JN-1 <0.030 0.040 <0.030 0.040 < 0.140 260 ft JN-1 <0.030 < 0.030 <0.030 0.050 <0.140 275 f t JN-3 <0.030 < 0.030 <0.030 0.030 <0.120 Northwest 200 ft JN-4 <0.030 <0.030 <0.030 0.030 <0.120 3 250 f t JN-3 <0.030 <0.030 <0.030 0.030 <0.120 5 North 150 ft JN-4 <0.030 40.030 <0.030 0.030 < 0.120 200 ft JN-4 <0.030 <0.030 <0.030 0.030 < 0.120 300 f t JN-3 <0.030 <0.030 < 0.030 0.030 <0.120 (a) Refer Figure 9. Average total for year <0.128.

I (b) TLD Unit Lost.

I

TABLE 14. CONCENTRATION OF RADI0 ACTIVITY IN LIQUl0 DISCHARGES TO COLUMBUS MUNICIPAL SANITARY SEWERAGE SYSTEM CY-1981 Concentration Location Number Activity, Range I#I Average, Nuclide Figure 7 of Samples pCi/yr 10-9 pC1/ml 10-9 pC1/ml Percent of RCG(b )

Gross a 005 12 1060.0 <MDL-25.30 8.03 3.66 Gross a 005 12 872.0 < MDL- 10. 70 6.61 M

(a) Hinimum Detection Limit (MDL) for: gross alpha: 0.5 x 10-9 pCi/ml; gross beta: 0.6 x 10-9 pC1/ml.

(b) RCG - Mixture of alpha and beta activity: 400 x 10-9 pC1/ml.

1 TABLE 15.

SUMMARY

OF SITE BOUNDARY AIR SAMPLE ANALYSES CY-1981 Location I8I 10-14 pct /ml(b)

Direction and Distance Number from Nuclear Sciences Area of Samples Gross a(c) Gross 8(C} 7Be(d)

North Quadrant Station I (450 ft. North of JN-4 Stacks) 52 0.23 + G.01 4.24 + 0.03 2.81 + 0.32 l

1 East Quadrant Station (400 ft. East of JN-1 Stacks) 52 0.40 + 0.01 7.47 + 0.04 4.04 + 0.40 I South Quadrant Station w (750 ft. South of JN-2 Stacks) 52 0.26 + 0.01 5.04 + 0.03 3.98 + 0.35 West Quadrant Station 52 0.14 + 0.01 3.28 + 0.02 2.34 + 0.25 (400 ft. West of JN-2 Stacks)

(a) Locations are shown in figure 6.

(b) Minimum Detection Limit for gross a is 7 x 10-17 pCi/mi for gross 8 4 x 10-17 pC1/ml and 1 x 10-16 pCi/ml for IBe.

l (c) The values shown for gross a and gross 8 indicate site boundary concentrations above background concentrations found at off-site air monitoring stations.

(d) Beryllum-7 was found to be a primary component in the composition of the site boundary air samples.

l i

i l

33 TABLE 16

SUMMARY

OF 0FF SITE AIR SAMPLE ANALYSES CY-1981 Location (a) 10-15 uCi/ml ID)

Direction and Distance Number

' rom Nuclear Sciences Area of-Samples Gross a Gross s Grandview (17.8 km east) 52 0.24 f; 0.02 4.36 f; 0.06 Chesapeake (24.4 km east) 52 0.26 f; 0.02 4.43 + 0.06 Fairgrounds (24.8 km northeast) 52 0.31 f;0.02 4.74 f; 0.07 Newark (70.8 km northeast) 52 0.25 + 0.02 4.26 + 0.06 Grove City (14.5 km southeast) 52 0.26 j; 0.02 4.17 + 0.06 New Rome (8.0 km east) 52 0.23 + 0.02 4.28 + 0.06 (a) locations are shown in Figure 10.

(b) Minimum Detection Limit for gross a is 7 x 10 17 uCi/mi and 4 x 10-17 uCi/mi for gross 3.

l i

f i

l i

i l

i

I I

I 34 I

TABLE lZ

SUMMARY

OF ENVIRONMENTAL WATER SAMPLE ANALYSES CY-1981 Location (a)

I Direction and Distance Number 10~9 uCi/ml(b) from Nuclear Sciences Area of Samples Gross a Gross s Darby Creek Upstream 52 5.85 + 0.32 7.24 + 0.36 (18.3 m above sanitary outfall)

Darby Creek Downstream 52 5.91 + 0.32 7.59 + 0.36 (18.3 m below sanitary outfall)

Darby Creek Downstream 52 5.21 + 0.32 5.86 + 0.38 (186.3 m below sanitary outfall)

Battelle Lake Spillway 52 5.27 + 0.32 5.69 + 0.36 (18.3 m below dam)

(a) Locations are shown in Figure 6.

(b) Minimum Detection Limit for gross a is 2 x 1010 uCi/ml and 1 x 10'10 uCi/ml for gross S.

I I

I I

I I

I I

I

35 TABLE 18 RADIONUCLIDE COMPOSITION OF BCL EFFLUENTS CY-1981 West Jefferson Site Air Activity (pCi)

Gross Alpha 0.12 Gross Beta 13.71 Plutonium-239 0.16 Cobal t-60 0.30 Cobalt-57 0.01 Strontium-90 2.99 Cesium-137 7.45 Cesium-134 2.54 Lead-212 15.60

• Lead-214 2.47

• Bismuth-214 3.14 Cerium-144 0.73 Antimony-125 8.64 Krypton-85 7964202.20 Rhodium-106 0.14 Cerium-141 0.03 Uranium-235 1.01 Europium-152 0.11

• Potassium-40 9.02 Water Activity (LCi)

Gross Alpha 8.16 Gross Beta 6.42 Iodine-129 0.84 Cobalt-57 1.20 Strontium-90 2.04 Plutonium-238 0.08 Plutonium-239 0.06 Radium-226 0.37 Radium-228 0.55 Lead-212 0.11 Uranium-235 4.86 Water Activity (LCi) l Gross Alpha 1060.0 Gross Beta 872.0

• Lead-214, bismuth-214 and potassium-40 are naturally occurring radionuclides which were part of the total effluent composition, i

i l

l l

l l

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TABLE 19.

SUMMARY

OF MAXIMUM ANNUAL RADIATION DOSE TO AN INDIVIDUAL AND THE NEAREST i POPULATION GROUP (WITHIN TWO MILES OF SITE) FROM ATMOSPHERIC EMISSIONS i CV-1981 l

Estimated Doses at Estimated Doses at Site Boundary a Radius of Two Miles from Site (,)

Critical Maximum Individual Dose, Individual Dose, Population Group Dose, Source Organ mrem /yr mrem /yr person-ren/yr

~ - ~

MfP (b) Lung 5.43 x 10 3 3.9 x 10 6 1.44 x 10 5 i MfP (b) Kidney 3.25 x 10'5 1.91 x 10 8 8.60 x 10 e ,

1 m

~ ~ ~

85 Kr Total Body 1.63 x 10 3 9.59 x 10 5 4.31 x 10 4

~

85 Kr Skin 9.75 x 10'l 5.73 x 10 4 2.58 x 10'3 239 Pu Lung 8.47 x 10 2 4.98 x 10 5 2.24 x 10

90 Sr Bone 2.30 x 10 3 1.35 x 10 6 6.09 x 10 6 (a) Two miles from site, population of 4500 and atmospheric dilution facter from site boundary of 1700.

(b) Mixed fission products.

l 1

i a

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M M K W W W W W mW W W W M M M M M M M M M

37 TABLE 20. ESTIMATED ANNUAL INTEGRATED 50-MILE POPULATION DOSES CY-1981 Critical Integrated 50-Mile Population Source Organ Dose, person-rem /yr MFP (*) Lung 3.39 x 10'5 MFP(*) Kidney 1.41 x 10*5 85 Total Body 6.30 x 10'"

Kr 85 Skin 3.75 x 10 3 Kr 239 Lung 3.26 x 10%

Pu 90 Bone 1.43 x 105 Sr (a) Mixed fission products.

TABLE 21. ESTIMATED ANNUAL RADIATION DOSE TO A SWIMMER (EXTERNAL WHOLE BODY DOSE)

CY-1981 Water Body Radiation Dose, mrem /yr Outfall Effluent 3.37 x 10 Downstream 1.22 x 10~

TABLE 22. ESTIMATED ANNUAL RADIATION DOSES FROM EATING FISI) (AUGHT IN BIG DARBY CREEK AND BATTELLE WEST JEFFERSON LAKEtas Dose (mrem /yr)(b) Dose (Person-rem /yr)IC}

Fish Taken from Darby Creek Dose (mrem /yri Fish Taken from Darby Creek Critical Near Outfall Fish Taken from B, elle Lake Downstream Nuclide Organ Adult Teen Child Adult Teen Child Adult Teen Child 137 - - -

Cs Total Body 8.87 x 10 3 4.86 x 10 3 1.83 x 10 3 3.20 x 10 2 1.7b x 10 2 6.61 x 10 3 - - -

)

90 Sr Bone 9.67 7.98 6.92 9.26 7.64 '6.62 1.13 x 10' 9.39 x 10'5 8.13 x 10 5 j _ _ , _ , . _ -. _ _ _ _ _ _ _ _ _ _ .__ _ _

1 (a) Calculation of rem dose /yr was based on guidelines set forth in U.S. NRC Regulatory Guide 1.109(8). g (b) Mrem /yr dose calculations were obtained using analytical data for fish samples taken from Darby Creek and Battelle Lake (Table 11 ).

(c) Person-rem dose calculations were obtained using radionuclide concentration in water multiplied by a bio-accumulation factor times af fected population of 1.1 x 105 mmmmmmmmW W W W W W W W W M M M M.

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TABLE 25. 50-YEAR DOSE COMMITMENT FOR 80 KILOMETER POPULATION tRUM AIRBORNE EFFLUENTS RELEASE 0 DURING CY-1981 Population Dose (person-rem) 80-Kilometer Whole Exposure Mode Popula tion Body Gl(a) Thyroid Kidneys Bone Lungs Foodstuff (ingestion) 1,5 x 106 2.50 E 6 3.60 E 9 4.00 E t2 4.10 E~7 7.80 E 6 1.20 E 7 Chronic (inhalation) 1.5 x 106 2.04 E'S 4.60 E- 1.71 E 10 5.34 E 5 3.57 E " 1.32 E~3 (b) Food stuf f (ingestion) 1.5 x 106 1.10 E 5 3.60 E 9 1.70 E 9 4.60 E-7 4.20 E 5 1.30 E 7 fI (a) Gastrointestinal tract (lower large intestine) .

(b) 50-Year Accumulated Dose.

m

I'

\

i 42 TABLE 26 PARAMETERS FOR WEST JEFFERSON SITE AIRBORNC RELEASE DOSE CALCULATIONS Facility name: JN-1 (Hot Lab)

Releases: See Table 3 Meteorological conditions: West Jeff meteorological station 1-year data (1/2-31/81), annual average Dispersion model: Gassian, 8CL parameters X/Q: Maximum individual 2.26 x 10-9 sec/m3 0122m SE 80-km population 2.46 x 10-10 sec/m3 Release height: 24.2 meters effective (18.28 meters actual stack height)

Population distribution: 1.5 x 106, see Figure Computer code: DACRIN, version 1.2, Rev. 1980 Calculated dose: Chronic inhalation, maximum individual and 80-km population, 50-year dose commitment Files addressed: Radionuclide Library, Rev. 1-15-81 Organ Data Library, Rev. 2-5-81 Computer code: , PABLM, version 2.1, Oct. 1980 Calculated dose: Chronic ingestion, maximum individual and 80-km population, 50-year dose commitment Files addressed: . Radionuclide Library, Rev.1-15-81

' Food Transfer Library, Rev. 2-27-78 Organ Data Library, Rev. 2-5-81 External Dose Factor Library.

Rev. 3-15-81 Bioaccumulation Factor Library

. _. _. . __ _ _ _ _ _ . 1

L' S 43 FIGURE 1. REGIONAL MAP FOR EtNG AVENUE ANO WEST JEFFERSON SITES

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I FIGURE 12.1970 POPULATION WITHIN 50 MILES OF THE WEST JEFFERSON SITE HARDIN "

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55 l FIGURE 13.1970 POPULATION WITHIN 10 MILES OF THE WEST JEFFERSON SITE cuuutAYtvt POPULA110N TOTALS.

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APPENDI1

APPENDIX ADDITIVE LEVELS DUE TO RADIONUCLIDE MIXTURE The " Requirements for Radiation Protection" (00E Order 548U.l. Cnapter x1) states that a radionuclide may be considered as not present in a mixture if the ratio of its concentration to its RCG is not greater than one-tenth.

Furthermore, the sum of all such excluded ratios cannot exceed one-fourth.

The summ of the ratios of the concentrations of radionuclides to their respective RCG's are listed below. The ratios are presented for maximum levels at the release point in both air and water.

West Jefferson Site Radionuclide Radionuclide Concentration  ;

RCG Air (Particulate)

Plutonium-239 7.66 x 10-2 Cobalt-60 2.19 x 10-s Co bal t-57 5.10 x 10-8 )

Cesium-134 3.65 x 10 5 Lead-212 4.56 x 10-6 Cesium-137 7.08 x 10-5 Strontium-90 6.92 x 10-3 Cerium-141 5.37 x 10-s Cerium-144 1.54 x 10-5 Antimony-125 6.46 x 10-5 Europium-152 3.35 x 10-6 Uranium-235 1.19 x 10-"

Krypton-85 1.66 x 10-1 Sum 2.50 x 10-1

I I

A-2 West Jefferson Site Radionuclide Radionuclide Concentration 3 RCG g Water Lead-212 4.00 x 10 6 Radium-228 1.33 x 10-2 Radium-226 9.00 x 10~'

E Cobalt-57 2.17 x 10 6 3 Strontium-90 4.93 x 10-3 lodine-129 1.02 x 10-2 Plutonium-238 1.20 x 10-5 Plutonium-239 8.00 x 10-6 Uranium-235 1.17 x 10~" 3 Sum 3.76 x 10-2 The data indicate that, according to the criteria of DOE Order 5480.1. Chapter XI, the sum of the above ratios does not exceed one-fourth; therefore, these nuclides are not considered as part of the mixture.

APPLICABLE STANDARDS Radioactive Standards g In conformance with Federal Radiation Council (FRC) guidelines and DOE Order 5480. i Chapter XI, " Standards for Radiation Protection," site boundary cancentrations are compared with RCG's established for uncontrolled areas.

Uncontrolled Area (31te Boundary)

Concentration, uCi/ml

• Air Plutonium-239 6 x 10~14 Krypton-85 3 x 10-7 Cobalt-60 3 x 10-10 Cobal t-57 6 x 10-9 Cesium-137 5 x 10~1' I

I I,

3 I

Il

A-3 Uncontrolled Area (Site Boundary)

Air Concentration, uCi/ml Cesium-134 4 x 10'10 Lead-212 6 x 10-10 Cerium-144 2 x 10-10 Europium-152 1 x 10-10 Strontium-90 3 x 10-11 Uranium-235 4 x 10-12 Antimony-125 9 x 10-9 Cerium-141 5 x 10~9 Water Cobalt-57 4 x 10'*

Iodine-129 6 x 10 8 Radium-226 3 x 10 8 Radium-228 3 x 10-8 Plautonium-238 5 x 10-6 Plutonium-239 5 x 10-6 S tronti um-90 3 x 10-7 Uranium-235 3 x 10~5 Lead-212 2 x 10-5 Mixture DOE Order 5480.l, Chapter XI, " Requirements for Radiation Protection," provides for the calculation of guide values in any case where there is a mixture of radionuclides in air or water. The ratio between the concentration of each radionuclide present in the mixture and its repective RCG must first be determined. The sum of these ratios for all radionuclides in the mixture should not exceed unity. A radionuclide may be considered as not present in the mixture unless the ratio of the concentration of the radionuclide to its RCG is greater than one-tenth, provided that the sum of such excluded ratios does not exceed one-fourth.

I

I I

I A-4 -

Grass and Food Crops There are no guidelines established for radionuclides in grass and food crops.

Soil and Sediment There are no guidelines established for radionuclides in soil and sediment. The Environmental Protection Agency's radiation protection requirements for exposures to transuranium elements in the environment l necessitates doses to the critical fraction of the unrestricted population 3 be less than 1 mrad /yr to the pulmonary lung and 3 mrad /yr to the bone.

Fish There are no guidelines established for radionuclides in fish.

Nonradioactive Standards (Water)

Concentrations of nonradioactive species in water are subject to the restrictions of the (NPDES) Permit as were determined by the Ohio EPA following a study of the Scioto River Basin.

External Radiation - General Public The permissible level of radiation in an uncontrolled area is that which will cause any individual to receive a dose, to the whole. body, h 5

not exceeding 0.5 rem in any period of one calendar year.

I I

I I

I I

I I

A-5 EXTERNAL DISTRIBUTION LIST This report is submitted to the Director, Contracts Management Office, U.S.

DOE. In addition, the following persons, some of whom are not a part of the DOE complex, are recipients:

Madison County Health Department Neil Bobb Sanitation Engineer Madison County London, Ohio John C. Starr, M.D.

Health Commissioner London, Ohio l

Other County and City Health Departments William Brown Health Commissioner City of Columbus State of Ohio James Wynd Engineer <in-Charge Radiological Health Unit Ohio Department of Health Dr. John Ackerman Director, Department of Health 246 N. High Street Columbus, Ohio 43215 Dr. James r.cAvoy Director Ohio EPA Ernest C. Neal, Chief District Operations Ohio EPA

l I

I A-6 State of Ohio (Continued)

I Ohio Power Siting Comission Office of Assistant Administration for Public Infomation Charles Taylor W Office of Air Pollution Ken Harsh =

Office of Emergency Response Jim Kneale Chief Office of Public Water Supply Ernie Rotering Waste Water Pollution Control Paul Flanigan, Chief Title X Ohio EFA John Donday Office of Land Pollution Control Federal EPA W. D. Rowe Deputy Assistant Administrator for Radiation Programs Office of Radiation Programs Surveillance and Inspection Division U.S. EPA Gilbert Gigliotte. Director Technical Infomation Mr. David Kee, Director Air and Hazardous Materials Divicion Outside Laboratory Samuel I. Baker =

Senior Environtrental Protection Officer Fermi National Accelerator Laboratory P.O. Box S00 Batavia, Illinois 60510 i I I'

mm I!

I

A-7 Outside Laboratory (Continued)

Jack P. Corley, C.H.P.

Staff Engineer Environmental Evaluations Section Battelle Pacific Northwest Laboratories Battelle Eoulevard Richland, Washington 99352

1 1

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a ne I Battelle g Columbus Laboratories 505 king Avenue i Columbus, Ohio 43201 Telephone (614) 424-6424 ,

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