ML20091H573

Environ Rept for CY83 on Radiological & Nonradiological Parameters to Us DOE Chicago Operations Ofc

ML20091H573
Person / Time
Site:	Battelle Memorial Institute
Issue date:	12/31/1983
From:	Robert Evans, Mckown D, Stewart D Battelle Memorial Institute, COLUMBUS LABORATORIES
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
NUDOCS 8406050212
Download: ML20091H573 (90)

Text

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ENVIRONMENTAL REPORT FOR CALENDAR YEAR 1983 ,

on RADIOLOGICAL AND NONRADIOLOGICAL 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 G. E. Kirsch and E. R. Swindall, Operational Health Physics Nuclear Services Section M. J. Stenhouse, R. H. Snider and H. R. Harris, Radiochemistry Services

' Nuclear Materials Technology Section i

BATTELLE

' Columbus Laboratories 505 King Avenue Columbus. Ohio 43291 l

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APPROVAL LIST

- APPROVED BY D - P Section Manager BCL Nuclear Services

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APPROVED BY M Project Aeninistrator N [LCA)/ /

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k TABLE OF CONTENTS I

. P, age, k- FOREWARD . . . . . . . . . . . . . . . . . . . . . . . . . . . . . viti SUPMARY ............................. 1 SITE AND FACILITY DESCRIPTION. . . . . . . . . . . . ...... 4 Si te Descri pti ons . . . . . . . . . . . . . . . . . . . . . . 4 Demography . . . . . . . . . . . . . . . . . . . . . . . 5 Climatology ...................... 5

(. Geology ........................ 6 Hydrology ....................... 7 Background Radiological Characteristics. . . . . . . . . 8 FACILITY DESCRIPTIONS. . . . . . . . . . . . . . . . . . . . . . . 8 The Ki ng Avenue Si te. . . . . . . . . . . . . . . . . . . . . 9 The West Jefferson Si te . . . . . . . . . . . . . . . . . . . 10 Radiological Waste ..................... 11 o

ENVIRONMENTAL MONITORING . . . . . . . . . . . . . . . . . . . . . 13 West Jefferson Site . . . . . . . . . . . . . . . . . . . . . 13 Ai r Radi oac ti ve . . . . . . . . . . . . . . . . . . . . . 13 Wa ter Radioactive. . . . . . . . . . . . . . . . . . . . 15 Water Nonradioactive . . . . . . . . . . . . . . . . . . 16 Grass and Food Crops Radioactive . . . . . . . . . . . . 16 Sediment Radioactive . . . . . . . . . . . . . . . . . . 17 Soil Radioactive . . . . . . . . . . . . . . . . . . . . 17 Fish Radioactive . . . . . . . . . . . . . . . . . . . . 17 Background Radiation Levels. . . . . . . . . . . . . . . 18 KING AVENUE SITE . . . . . . . . . . . . . . . . . . . . . . . . . 18 11

TABLE OF CONTENTS (Continued) -

Page Wa ter Radi oactive . . . . . . . . . . . . . . . . . . . . . . la EVALUATION OF DOSE TO THE PUBLIC . . . . . . . . . . . . . . . . . 19 Estimated Radiation Doses to the Public From Emissions from the Battelle West Jefferson Site During Cy 1983 . . . . . . . ,

19 Abnospheric Discha rges . . . . . . . . . . . . . . . . . 1g Liquid Discharges ................... 19 Estimated Radiation Dose to the Public From Atmospheric ' 1 D i s c ha rge s . . . . . . . . . . . . . . . . . . . . . . . . . . 20 f Calculation of Atmospheric Dispersion Parameters . . . . 20 Calculation of Individual and Population Group Deses . . 20 Calculation of the 50-Mile Integrated Population Annual Dose . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Estimated Annual Radiation Dose to the 'Public from Liquid D i s c ha rg es . . . . . . . . . . . . ............. 21 Radiation Dose from Swimming (External Whole Body) . . . 21 Radiation Dose Due to Boating and Water Skiing . . . . . 21 Radiation Dose from Drinking Water . . . . . . . . . . . 22 Annual Radiation Dose from Eating Fish . . . . . . . . . 22 7 70-Year Dose Commi tment. . . . . . . . . . . . . . . . . 22 Fence Pos t Dose Estima te . . . . . . . . . . . . . . . . 23 Maximum Indivudual Dose Estinate . . .. . . . . . . . . . 23 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 i I

Qual i ty Assurance . . . . . . . . . . . . . . . . . . . . . . 25 APPENDIX

' ADDITIVE LEVELS DUE TO RADIONUCLIDE MIXTURE ........... A-2 Wes t Jef ferson Si te . . . . . . . . . . . . . . . . . . . . . A-2 111

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APPLICABLE STANDARDS . . . . . . . . . . . . . . . . . . . . . . A-2 Radioactive Standards . . . . . . . . . . . . . . . . . . . . A-2 Uncontrolled Area (Site Boundary) . . . . . . . . . . . . . . A-2 Air .......................... A-3 l

Water ......................... A-3 Mixture . . . . . . . . . . . . . . . . . . . . . . . . . . . A.3 Grass and Food Crops . . . . . . . . . . . . . . . . . . A-4 Soil and Sediment. . . . . . . . . . . . . . . . . . . . A-4 Fish . . . . . . . . . . . . . . . . . . . . . . . . . . A-4 l

Nonradioactive Standards (Water) . . . . . . . . . . . . A-4 Extemal Radiation - General Public. . . . . . . . . . . A-4 EXTERNAL DISTRIBUTION LIST . . . . . . . . . . . . . . . . . . . . A-5 iv

LIST OF TABLES Page Table'l. Population Distribution Within 10-M11e Radius from Site. . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 Table 2. Sumary if Atmospheric Radioactive Emission -

= West Jefterson Site . . . . . . . . . . . . . . . . . . . . 27 Table 3. Gama Emitting Radionuclides Identified in the JN-1 (Hot Cell Stack Particulate Emissions). . . . . . . . . . . 28 Table 4. Sumary of Liquid Radioactive Emissions - West Jefferson Site (Meas are of Effluent from Sanitary Sewerage System into Big Derby Creek - Figure 4. Designation 010) . . . . . 29 Table S. Noaradiological Sampling for West Jefferson Site Jaruary 1. !983, to Decemter 31. 1983 . . . . . . . . . . . 30 Table 6. Sammary of irass Analyses . . . . . . . . . . . . . . . . . 31 Table 7. 56 mary of Food Crop Analyse . . . . . . . . . . . . . . . 32 Table 8. Sumiry of Silt Analyses ................. 33 Table 9. Sumary of Soil Core Analyses . . . . . . . . . . . . . , . 34 Table 10. Sumary of Gama Isotopic Analysis of Soil Core Samples . . 35 .

Table 11. Sumary of Fish Analyses ................. 36 Table 12. External Background Radiation Levels Within 3/4 Mile Radius -

Wes t Jefferson Si te . . . . . . . . . . . . . . . . . . . . 37 .

Table 13. External Background Radiation at Perimeter Security Fence -

Wes t Jef ferson Si te . . . . . . . . . . . . . . . . . . . . 38 Table 14. Concentration of Radioactivity in Liquid Discharges *o Columbus Municipal Sanitary Sewerage System . . . . . ... 39 Table 15. Sumery of Site Boundary Air Sample Analyses (cr Msr Radicactivity . . . . . . . . . . . . . . . . . . . . . . . 40 Table 16. Sumary of site Boundary Air Sample Analyses for ?pecific 1 Radionuclides . . . . . . . . . . . . . . . . . . . . . . . 41- '

l Table 17. Summary of Oft-Site Air Sample Analyses . . . . . . . . . . 42 Table 18. Sumary of Environmental Water Sample Analyses. ..... 43 v

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Pa.jL Table 19. Radionuclide Composition of 8CL Effluents for CY 1983 . . 44 Table 20. Summary of Annual Radiation Dose to the Maximum Individual.

Nearest Residence and Population Groups from Atmospheric Emissions of Krypton-85 During CY 1983 ......... 45 Table 21. Annual Dose to the Maximum Individual from Effluents Rel ea st s Du ri ng CY 1983 . . . . . . . . . . . . . . . . . 46 Table 22. Annual )ose to the Nearest Resident (0.75 Km NW) from Efflue'ts Released During CY 1983 . . . . . . . . . . . . 47 Table 23. Annual Dose to the Nearest Population Group (Darby Estates) from E ffluents Reinased During CY 1983. . . . . . . . . . 48 Table 24. Annual D se to the Population Group (West Jefferson) from Effluents Released During CY 1983 . . . . . . . . . . . . 49 h Table 25. 70-Year Dese Comitment for the Maximum Individual from Effluents Released During CY 1983 . . . . . . . . . . . . 50

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Table 26. 70-Year Dose Commitment for the Nearest Resident (0.75 l' Nm NW) from Effluents Released During CY 1983 . . . . . . 51 Table 27, 70-Year Dose Comitment for the Nearest Population Group (Darby Estates) from Effluent Releases During CY 1983 . . 52 Table 28. 70-Year Dose Comitment for the Population Group (West Jefferson) from Effluent Releases During CY 1983. . . . . 53 Table 29. 70-Year Dose Comitment for 80-Kilometer Population From Liquid Effluents Released During CY 1983. . . . . . . . . 54 Table 30. 70-Year Dose Comitment for 80-kilometer Population From Airborne Effluents Released During CY 1983. . . . . . . . 55 Table 31. Parameters for West Jefferson Site Airbornet Release Dose Calculations ...................... 56 Table 32. Average Annual Percent Frequency of Wind Direction and Average Wind Speed (M/S) for CY 1983. . . . . '. . . . . . 57 Table 33. 8MI King Avenue Site Population Within 'JO F iles . . . . . 58 Table 34. Annual Average Atmospheric Dispersion Archn,1 the West Jefferson Site for a 18 Meter Stack Height '(elease. . . . 59 vi

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LIST OF FIGURES Page Figure 1. Regional Map for King Avenue and West Jefferson Sites . . . . . . . . . . . . . . . . . . . .'. . . . . 60 1 Figure 2. Local Vicinity Map of King Avenue Site . . . . . . . . 61 j Figure 3. Local Vicinity Map of Nuclear Sciences Area

[ West Jefferson Site ................. 62 Figure 4. Nuclear Sciences Area West Jefferson Site . . . . . . . 63 i

Figure 5. Map of Grass. Foodcrop and Soil Sampling Locations. . . 64 Figure 6. Map of Site Boundary Air Sampling Locations and Battelle Lake and Darby Creek Water Sampling Locations. 65 Figure 7. Battelle's Columbus Laboratories King Avenue Site . . . 66 Figure 8. Map of TLD Locations Withic. 3/4 Mile Radius of the Nclear Sciences Area . . . . . . . . . . . . . . . . . 67 Figure 9. Map o' TLD Locations at the Perimeter Security Fence. . 68 Figure 10. Map'of Columbus and Vicinity Showing Off Site Air Sampling Locatiors .................. 69 Figurt 11. 1983 Wind Rose Pattern for West Jef*erson Site. . . . . 70 Figure 12. 1980 Population Within 50 Miles of the West Jefferson

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Figtre 13. 1980 Population Within 10 Mi.es of the West Jefferson Site. . . . . . . . . . . . . . . . . . . . . . . . . . 72 i

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FOREWARD i 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 radioanalyses of environmental air and water samples for gross l radioactivity and gannia isotopic deteminations were perfonned by Radiochemistry services. Nuclear Material Technology Section.

Radioanalyses of air, water. grass, soil, 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 perfonned by the Columbut Water and Chemical Testing Laboratory Columbus Ohio.

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Environmental data collected during CY-1983 show continued compliance by Battelle Columbus Laboratories with all applicable state and federal

{g regulations.

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

1 West Jefferson nuclear operations during 1983 caused no distinguishable impact on concentrations of airborne radionuclides or on external radiation doses measured

j. adjacent to the nuclear site or at the West Jefferson site boundarv.

L (See page 28. Table 3 and page 37. Table 12.)

L Radionuclides observed in food crop, grass, creek bottom 1-sediment, and soll samples were all attributed to either atmospheric nuclear tests or natural sources. (See pages 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 all less than 5.4% of the respective concentration guide for an individual radionuclide released to an unrestricted area. Concentrations observed at down-stream sampling locations were statistically indistinguishable from back .

ground levels. (See page 29. Table 4 and page 43. Table rd).

The estimated raiological dose resulting from the naclear oper West Jefferson site was calculated for the maximum rearestindividual,f a tt;n at tl{

residence and population groups, and the integrated fifty mila 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 environ-mental contaminants and the impact of radionuclides known to have been released but not found in detectable concentrations during the years environmental sampling program. The doses are summarized as follows:

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2 l The 70-year dose connitment computations for the " maximum individual, nearett resident and population groups" 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 70-year dose connitment: (1) chronic inhalation of radioactive mixture using an atmospheric diffusion model; (2) chronic ingestion of a radioactive mixture through terrestrial and (3) aquatic pathways. (See pages 50, 51, 52. 53, 54, 55 Tables 25, 26,

27. 28, 29, 30).

The whole body dose connitment for the " maximum individual" during CY 1983. was calculated to be 10.06 mrem. This estimate includes the external radiation exposure in excess of that received from normal background levels as well as contributions from airborne and aquatic recreation pathways. A discussion of how the dose commitment for maximum individual was calculated is given in the Text on page 23.

The maximum organ dnse commitment received by the maximum indi-vidual from all pathmy. was 0.059 mrem /yr to the skin from Krypton-85. These do.es can be compared with the standards given in DOE Order 5481.1 Chapter XI of 500 mrem /yr for the whole body and 3000 mrem /yr for the bone marrow. (See pages 37, 38. 50 Tables 12. 13. 25).

Airborne emissions from the West Jefferson nuclear site resulted '

in a whole body dose connitment to the Dopulation within 80 km *

(50 mile) radius of the nuclear site of about 1.3 x 10-4 person-rem. Liquid effluents during 1983 contributed approximately 6.6 x 10-4 person-rem to the total population gase. This estimate may be compared with the approximate 2.04 x 103 person rem /yr received annually from natural background radiation. (See pages 54, 55. Tables 29. 30).

The average " fence-post" exposure as measured by 'LD stations '

during 1983. was 10.0 mrem /yr (0.001 mrem /hr) above background at a location just outside the security fence on the east side of the JN 1 Hot Cell Facility. Radiation from the Hot Cell radioactive waste handling facilities was primarily responsible for the slight increa$e in background radiation levels. (See page 38. Table 13.) A discussion of how the average " fence post" exposure was obtained is given in the text on page 23.

Releases of Icw-level concentrstior.s of radioactivity to the Columbus municipal sewerage system from the Building 3 (U-235 Processing Facility) were less than 2.6% of the concentration <

guide for discharges of mixtures into sanitary sewerage systems. '

(See page 39. Tacle 14.)

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L Discharges of sanitary water from the West Jefferson nuclear site into Darby Creek under the National Pollution Discharge Eliminatian System (NPDES) permit were all within the parameter limits specified in the pemit. (Seepage 30. Table 5.)

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$1TE AND FACILITY DESCRIDTION 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-m11e area map showing both sites is presented in Figure 1.

Figure 2 and 3 show property boundaries. Various 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.

Site Descriptions The Pat King Avenue Facility is located at 39 degrees 59'N, 83 degrees 03'W in the western central portion of the city of Columbus Ohio. The ten-acre plot, accommodating twenty-one buildings, is bounded on the north by  ;

King Avenue. Perry Street to the east, Fif th Avenue to the south and the Olentangy River to the West. Figure 7 is an expanded view of the BM! King Avenue Facility. Building 3 houses the uranium processing activities at the King Avenue Facility. l The West Jefferson Site is located at 39 degrees 58'N, 83 degrees 15'W.

approximately 15 statute miles west of the BMI King Avenue Facility. The West Jefferson $tte consists of a 1.000 acre tract which accommodates the Engineerino Area in the southeastern portion, the Experimental Ecology Area in tne east central portion and the Nuclear Sciences Area in the northern portion. The northern boundary of the Site lies approximately one mile south of Interstate Highway 70 and extends from the Georgesville-Plain City j Road castward to the Big Darby Creet. The eastern boundary of the Site j roughly parallels the valley of the Big Darby Creek southward to the Conrail i tracks which constitute the soutbers boundary. The Georgesville-Plain City (

Road defines the western boundary of the Site, i The Nuclear Sciences area, the focus of interest at the West Jefferson $lte, is adjacent to the $tte's northern boundary. As illustrated in Figure 6 I it consists of a ten-acre fenced area enclosing a guardhouse, four buildings i and two other small structures on a flat bluff above Battelle Lake to the south and Big Darby Creek to the east. The eastern edge of the bluff drops rather abruptly from an average elevation of 910 feet to 870 feet msl. then <

more gradually to the 860 foot elevation of the Big Darby Creek Floodplain.

The land to the north, west, and south, to a distance of two miles, is ,

essentially cleared farmland, although there is one narrow wooded area along i the northern portion of the fence around the Nuclear Sciences Facility. 1 and another wooded area about 1.000 feet to the northeast. To the east.  !

within the Big Darby Floodplain and along the bluffs to the east of the Creek, the land is heavily vegetated with deciduous trees, scrub and high grasses. ,

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The area within a two-mile radius of the BMI King Avenu Facility to the I east and south can be characterized as. high-density residential. The Ohio State University, with a student enrollment of 53.278, is adjacent to the BMI King Avenue Facility on the north. The area west of the Olentangy River consists mainly of small business and Itght industrial f

I properties with scattered residential patches. Table 29 shows the population within a fif ty-mile radius of the King Avenue Facility.

The area immediately adjacent to the West Jefferson $tte has a low population

{ density. Figure 12 shows the population distribution, by direction and distance, within 50 miles of BMI West Jefferson. The nearest residences to ;;he Nuclear Sciences area are two houses located 2.500 feet to the north-west and southwest. respectively. A Girl Scout Camp. Camp Ken Jockety, is located on a bluff on the east side of the Big Derby Creek at a distance of 1.500 feet. Four thousand feet to the southeast, on the eastern side of l

the Big Darby Creek, the Lake Darby Estates residential subdivision (Figure 3)

J is under construction. A total of %5 single family units are planned. A L second subdivision. West Point, planned for the area east of the Lake Darby Estates and Hubbard Road is to have 1.835 housing units by 1985.

There are 18 industries located within the ten-mile radius. Of these, there are only four that employ more than 100 people. These are White.

Westinghouse Electric Corporation. General Motors. Janttrol Aircraf t, and Capttal Manufacturing Capany. Each of these is located at least 8 miles from the Facility. Closest to the site are three small industries within West Jefferson that individually uploy less than 60 people. The primary agricultural activity in the area is raising field crops such as corn and soybeans. Approxiniately 10% of the land area in agricultural use is devoted to pasturing beef and dairy herds.

During the last 16 years two major highways. I 70 and I 270 have been completed near the West Jefferson Site. The junction of these highways, which occurs near the eastern edge of the ten-mile pertteter around the Nuclear Sciences Area, has proven to be a popular area for indJstrial growth. It is estimated that the industrial population has shown an increase equivalent to that of the general population in this area; i.e.,

two and one half times the ten-mile population distribution for 1%5. Most of the growth has taken place near the outer limits of Columbus; however, the larger employers, e.g., General Motors and White-Westinghouse have actually decreased their number of employees.

Clima toloey Climatology of the south-central Ohio region may be described as continental.

temperate. As such, the region is subject to a wide seasonal range in temperature. Sumers are quite warm with the mean ter .rature for the

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months of June, July, and August being 73.30F. Teperatures of 900 F or above are expected for about 15 days during *hese months. The mean for the months of December. January, and February is 31.20F. The number of days per year wtth temperatures below 320F and below 00 F are 122 and 4 respectively. Precipitation is distributed fairly unifonely during the year although 60% falls during the spring-sumer seasons. The annual s raenthly average rainfall is about 3.5 inches and the greatest recorded

! rainfall for any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period was 3.87 inches in July of 1947.

l Changeable wind directions are characteristic of the region due to the incursion of maritime tropical air masses from the Gulf of Mexico and

!' outbreaks of continental polar air masses from Canada. Wenn air mass inversion is most comenon during the later spring and sumer and frequently results in frontal showers and thundershowers. Tropical air mass thunder-storms are also conunon during the summer and are frequently accompanied by high winds. Additionally. It is not uncomon for hot air mass thunder-storm development to be sufficiently strong to spawn tornado activity.

Cold fronts that invade the region. principally during the late fall.

winter, and early spring also bring showers and thunderstonns.

l During the late spring fast moving cold fronts, with large temperature discontinuities ahead of and behind the fruntal surface. travel through the region and are of ten acsompanied by thanderstonns and frequently by

i. terradic activity. Of the 567 tornadoes recorded within 144 miles of

l. the BMI Facilities during the period 1950-1975, one hundred sixty three j have occurred in the month of April. ,

l The regional climatological data gathered by the National Weather $ervice '

at Port Columbus, seven miles east northeast of the King Avenue Facility.

is generally representative of the local climatological conditions at the Columbus $tte. A local me*sorology station is maintained at the West ,

Jefferson $tte. The data collected by the local station are used for i long term comparison with the Port Columbus data. Table 32 summarizes the

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windspeed and direction at the West Jefferson $1te for 1983.

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Geolony 1

I The arrangement of geological strata in the tMI Facilities area consists i of glacial till and outwash wtth formations of clay, sands, and gravel.

! The sands and gravel of the outwash are found in scattered, thin, dis-continuous lenses within the till which is composed of unstratified clay I containing fragments of rock. The unglaciated basement formations in the ,

West Jefferson area, at depths of from about 80 to 100 feet, consist of -

• nearly horizontal beds of limestone, dolomite and shale several hundreds of feet thick. Surface soils consist of oatches and mixtures of Brookston $11ty '

Clay Loam. Crosby Silt Loam Lewisburg 511t Loam. Celina $11t Loam and Miamian sitt Loam. The greatest portion of the surface soils is represented by the l

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Y Brookston-Crosby association with little more than traces representing the remaining types. All of these soil types exhibtt relatively low

( permeability and all grade into till clay at depths of 55 to 60 inches where the impenneability of the near-surface geology nearly precludes further percolation.

There have been no recorded earthquakes within 50 miles of the area of interest although in 1937 a strong quake was experienced at Anna, Ohio, a little over 50 miles to the northwest of the West Jefferson Site. The Columbus-West Jefferson areas are, however, considered to be in an aseismic l region. The BMI facilities are in a Zone 1 risk area.

Hydrology

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There are two aquifers, or sources of water, in the site area. The shallow l aquifer is, of course, the dense clay till. The deep, or principal, acquifer is the limestone bedrock underlying the till. Earlier wells in the site area ranged in depth from 10 to 40 feet, which placed them in the glacial deposits. Till is not very pemeable and yields water slowly. The effective velocity of water moving through clay under a hydraulic gradient of one lk percent is reported to be less than 0.004 foot per day; for water moving l

. thruugh silt, sand, and loess under the same gradient, the rate is about 0.0042 to 0.065 foot per day. Water movement in the till at the Battelle site is probably within the range of the fomer figure, since the hydraulic gradient of the water table in the area is only slightly greater than one percent.

The present wells at the Battelle facility lie below the surface of the bedrock. The north well is 130 feet deep, the centrally located well in the Life Sciences area is 162 feet deep, and the south well is 138 feet deep. Bedrock was encountered at approximately 103 feet below the surface in drilling these wells.

A man-made hydrologic feature of the site is the artificial lake covering an area of about 25 acres that was fomed by damming Silver Ditch south of, and down gradient from, the Nuclear Sciences area. The normal surface elevation of the lake is 888 feet M$L.

• The source of ground water in the site area is local precipitation. Recharge to the shallow aquifer takes place relatively uniformly over the area.

Contours of the water table, which are about 40 feet below the surface, are a subdued replica of the surface topography. Ground water moves down.

slope at right angles to the contours and follows a path similar to surface runoff. At the Nuclear $ciences area surface runoff moves downslope into the lake, thence through the controlled dam on the site into Big Darby Creek.

All ground water in the site area, and that entering on the site, is already near its place of discharge, a

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Test borings carried out in 1970 for an addition to the Hot Laborctory reaffirmed the geology described above. Only isolated pockets of water were encountered during that boring and foundation piling excavation operations. These pockets were readily pumped rut and remained dry, }

which indicated that there is no intercornection of the pockets with the lake.

Flood hydrology calculation for the lake indicated a capacity of releasing f water that was about three times the inflow rate measured during the January 1959 floods. It can be concluded that the lake has not adversely affected the hydrology of the area.

Big Darby Creek accounts for the principal surface water flow. Normal flow at the Darbyv111e gauging station, the only continuous recording gauge on Darby Creek, 40.46 river miles south of the West Jefferson Facility, is 430 cubic feet per second (cfs),

Background Radiological Characteristics Based on aeroradioactivity measurements of the region including the BM!

surrounding BMI is 60 mm/yearl)'Ilfacilities, This numberit isisequal estimated the the natural terrestial backgrou to the average natural terrestrial backgrnund fo.* the U.S. The cosmic background for the State of Chlo is averaged to be 50 mrem / year, comt,;ted to a U.S. average g of 45 mrem / year. The estimate for natural whole body internal background is considered to be 25 mrem / year for the U.S. with only minor regional variations.ll27 Based on these figures, the total natural background near the BMI facilities is estimated to be approximately 135 mrem / year, ,

as compared with an average of 130 mrem / year for the U.S. as a whole.

Table 12 gives the local external background radiation levels measured at the West Jefferson $tte during 1983.

Facility Descriptions The center of nuclear activities at the BMI King Avenue $lte is the U 235 Processing Facility, located on the first floor of Building 3. It is the nuclear materials management point for all transactions involving nuclear material at the King Avenue Site. Figure 7 shows tPe location of Building 3 in the King Avenue Site building complex.

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At the BMI West Jefferson Nuclear Sciences Area, the major operation involvled is research on the properties of irradiated materials. This

( p work is performed in the Hot Cell Laboratory (JN 1) and involves examt-i nation and testin of irradiated reactor fuel, nuclear pressure vessel material, and fue cladding material. The experiments serve to collect f data for the development or testing of theories about material performance under irradiation conditions. Nuclear support activities are conducted in the Administrative Building (JN 2 and the retired Battelle Research Reactor (JN-3). Figure 4 shows the oCations of these nuclear facilities "

f in the Nuclear Scienc6s Area building complex.

The Kina Avenue $tte The U 235 Processing Facility is located in Building 3 of the King Avenue Site. Building 3 was constructed in the mid 50's. It served untti the l late 60's as an exclusion area specifically designed for the processing and storing of unirradiated enriched uranium utilized on various government and industrial R&D programs. Presently Building 3 is used for several activities, but access to the U 235 processing area is limited and entry doors to the area are alarmed. The vault is used for the temporary storage of limited quantities of untrradiated enriched uranium. The area is also used for the receiving, storing, waste processing and packaging for ship-I ment of source materials.

The major pfece of processing equipment located in the area is an electric calcine furnace which is used for the reduction of scrap or waste to an oxide residue suitable for shipping to either a waste disposal site or scrap reprocessor. The furnace consists of a closed system muffle and glove box combination. The exhaust system for the furnace is arranged so that room temperature air is drawn into and mixed with the hot exhaust gases within a blending box. The semi cooled exhaust gases are then drawn through a water scrubber system which is equipped with a re circulating water Jystem. Af ter passing through the scrubber, the washed enhaust Jases flow through a bank of absolute filters and are then exhausted to the outside atmosphere through a blower and duct opening on the roof.

The reduced residues and ash, af ter being burned and cooled, are dumped into plastic bags within the gove bum. This gove box is an exhausted, closed system and therefore the system operating pressure is negative to the room pressure. This prevents any problem of contamination in the surrounding area exterior to the system.

Yhts calcine system can be used for the reduction to oxide of limited quantities of untrradiated enriched uranium scrap. The removal of enriched urentum ash and residues from the glove box is accomplished by dumping the material into a hopper butit into the floor of the glove box. This hopper feeds into a pipe over which a steel can is attached. The restdae drops directly into this can which, when full, is removed and a Ild applied and sealed for snipment.

10 The area is also the central gathering and packaging spot for low level

'adioactive contaminated waste. The area also served as a receipt and shipping, sampling, and measurement area for shipr'ents of both source =

materials and small quantities of unirradiated uranium which are to be, or have been, utilized on programs being performed at the BMI King Avenue Site.

The West Jefferson Site as shown in Figure 4. there are foaar principal buildings at the West Jefferson Nuclear Sciences area: JN-1. the Mt Laboratory; JN 2. the Administrative Buildingn JN-3, a retired Reseas h Reactort JN-4. the Hazardous Material Lab (Retired Plutonium Laboratory). Each of these facilities is described in the following paragraphs.

Hot t,aboratory JN-1 This laboratory containing approximately 22.000 square feet of space. is considered to be one of the most completely es ulpped such installaticns available to the nuclear community. The Hot Laboratory is capable of providing research and technical assistance in the areas of:

o Power reactor fuel perfomance evaluations e Pressure vessel irradiation surveillance capsule examinations and evaluations e Postirradiation examinations of nuclear materials and components e Radiation source encapsulation. and e Physical and mechanical property studies of irradiated materials and structures.

The Hot Laboratory consists of a large high energy cell and connecting pool capable of handling complete power reactor fuel assemblies, five smaller cells, and supporting facilities. .Ne smaller cells are the high level and low-level cells, the two mechanical test cells, and a segmente1 alpha ganna cell. The supporting facilities include areas for cask handling, solid and liquid waste disposal, Contamination controle equipment decontaminatio1, and other miscellaneous operations.

Administrative Buildino. JN 2 This building was designed and constructed for use as a critical assembly laboratory. It was used for critical experiments from 1951 through 1963.

11nce the cessation of critical emperiments, the facility has been used for several nuclear related projects including direct conversion concepts, irradiation experiment assembly, and special nuclear materials handling.

The operating license was teminated in 1970.

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n 11 Offices and small laborateries are used by nuclear supporting services staff including $*ction Administration. Health Physics Services. Nuclear Materials Accountability Quality Assurance, and Instrument Maintenance.

I These activities are the major building activities at this time. The building also currently houses the vault, used for storage of special

[ nuclear materials. and a radicchemistry laboratory uttitzed for the I assay of routine health physics samples and low activity irradiated materials study specimens. -

Battelle Research Reactor. JN 1 l The Battelle Research Reactor began operations October 29. 1956, but thn e operations were teminated on December 31, 1974, and dismantling initia'ed.

The dismantling was completed wtthout incident during 1975 and the license changed to a possession only status. $torage of waste awaiting thtWent for burial is the only licensed activity conducted in JN 3 at this time.

Hazardous Material Laboratory. JN 4 Building JN-4 was built in 1909 to house 9Ctivities in plutonium research i

and processing. These operations were terminated in 1978 and dismantling initiated. The dismantling is nearing completion and has been conducted without incident. A hasardous materials study laboratory has teen approved for operation in JN 4. These activities involve non radioactive metertal only.

RadiolocIcal Waste The processing of liquid waste from nuclear operations at the West Jefferson site involves the collection of contaminated itquid in holding tanks and concentrating using an evaporator. All latioratory link and floor drains in the nuclear facilities are connected to holding tanks. Only office area and restream drains are connected to the santtery drain system.

Contaminated Ifquids are solidtfied and the solid waste disposed of by a licensed disposal contractor.

Therefore liquids which could potentially contain radioactive matertalt from these fact 11ttes are contained thus preventing the accidental release of radioactive materials to the santtary sewer system. Highly contaminated liquids are mixed (remotely if required) with a solidifying agent and disposed of separately rather than being permitted to mia with large volumes of mtidly contaminated Itquids in the holdup tanks.

12 1,lguid westes from the King avenue site include solutions end possibly, waste water from the U 23! pr6 assing area. All liquid waste from the U.235 processing are solijtfted for disposal. Quality assurance procedures insure that no solution is discharged to the sewer systems without approval of the Radiolog' cal Safety Comittee.

Solid radiological wastes from operations at the King Avenue site are collected, compacted if recessary. and packaged for shipment to a Itcensed disposal site. Solid waste from the West Jefferson site is from many sources. Examples of soli.1 waste are the HEPA filters and disposal cartridge water filters, the spent ion exchange resins. disposable clothing or other supplies consumed trd contaminated in the laboratories, and gloves from the gove boxes. The transpo*tation of solid waste to comercial disposal sites is serformed in accordance with 49 CFR and 10 CFR. f Any releases of gaseous wastes to the environment are carefully controlled and dispersed to ensure that concentrations are as low as practicable within recomended standards. Radionucildes in particulate fom are l removed from exhaust stack effluents by the use of high. efficiency particulate air (HEPA) filters. The air effluents are filtered first e t the points of operations, t.o., gloveboxes, hoods, test cells, and finally at the stack release point by one or two banks of HEPA filters in sortes. Radioactive gases present in fuel pins under esamination at the Hot Cell Factitty are drawn off for subsequent disposal with solid wastes. The residual gases trapped in the fuel matrin or otherwise released is monitored continuously by effluent monitors, l Constant air montters see located throughout the laboratory. They monitor

" the envirorvnental air for alpha.. beta. and garna. emitting particulate matter. These air monitors, upon detection of radiation exceedtrig a preset level will activate the alarm bell.

The hot laboratorf has two separate enhaust stack systems. One for JN.1An

, one for JN 18. There are two significant dif ferences in the two systems.

First, the JN.1A system consists of five individual stackin the JN.18 system uses only one large stack. The other difference in the two systems is that the JN.18 system contains a large !.131 charcoal trap.

For the JN.lA stacks a single AM.2 constant air monitor is used. This instrument has three channellt one monitors for alpha particulate. One for beta. game particulate, and one for gaseous effluent. Any of the tnree channels will activate the alam and shut of f the enhaust fan for the higS level. Iow level, and alpha. gamma (basenent) cells, for the JN.18 stack there are four separate CAMS. alsna particulate.

beta.gama particulate, gaseous effluent and lodine.131. Any of the four instruments will activate the alam, shut down all est aust fans for the HEC and close the butterfly valves so no more str can ao drawn from the cell, in the event that the 1 131 monitor activates the alam, two additional operations take placen an enhaust fan is started and a diversion damper opens causing any ethaust air to flow through the charcoal trap.

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13 Although the two stack monitoring and control systems operate independently, they function on a similar betit. The alarm not point of each instrument is set at a level beled upon regulatory values of RCG in DOE Order 5480.1 for various radiation species in uncontrolled areal. Alpha particulate monitors are set on the belit of LLe RCG for Pu 239 beta gamma particulate monitors. on the batit of the RCG for 1r 90. Effluent monitors are not on the batts of the RCG for Kr.85m and the I 131 monitor 18 tot on the basis for that isotope.

l For each monitor if the concentration in the stacks equals or enceeds the applicable RCG level then an alarm and corresponding action 18 taken.

Under this procedure the activity in uncontrolled arest will remain lett i

than the values in DOE Order 5480.1.

Ventilation in the JN 2 storage vault and the radiochemistry laboratory 15 provided by separate exhaust fans that are designed and coerated in a manner to maintain a negative pretture atmosphere and to provide adequate air enchange in the radiochemistry laboratory. The air enhautti for the storage vault and the radiochemistry laboratory are made up of 9.tnch diameter ducts that empty into large volume plenums to which two 24" n 12" absolute filters are sealed. The exhaust Stack for the storate vault is equipped with alarmed continuous alpha monitoring to detect the release of any radioactive matter.

ENVIRONuCNTAL WON!T0ml44 The impact of operations on the health and safety of the public 16 evtluated routinely by an environmental monitoring program which has been in esis.

tence since 1955, the basic objective of the environmental monitoring program it to evaluate the effectivenett of the wette management program in maintaining the concentrations of radioactive and non. radioactive wattet to that effluent levelt are maintained at low at reasonably 46htevable and well within applicable standards. All effluents involving polluting matertalt are contained within the operating facilittet to the entent pollible and are disposed of 48 packaged weltet by authorised services.

West Jefferson 11te Air Radioactive In=ttack air lamplert continuously monitor the ethaunt Stack ef fluent release from each facility to atlett the effectivenett of lyttoms con =

trolling strborne emtllions, tight continuous stack monttert ensure detection of any inadvertent release of redtoactive matertalt and provide

14 data for the prompt attestment of the environmental impact, if any. (See Figure 4). Particulate samples of the effluent are collected from eacn eahaust Stack. The particulate temples are collected on two types of filter paper. GVB 60 and Type E glast fiber. The air is tempted at an average rate of 2.8 a 10* cm8/ min. The filters are changed weekly, which represents average temple volume of 285.5 m8 Analyset are perforined on a weekly batts for grott alpha and grott beta for stackt 001 through 004, 006. 012. 013 and 014. The results reported represent total average annual concentrations at the Stack and also at the site boundary as calculated from Stack temple data.

The site boundary concentrations, reported in Tables 1 and 2. due to the various enhaust stack locations were calculated by dividing the individual stack concentration by the appropriate atmospheric dilution factor (ADF) which is obtained from the following equation.

ADF =

8U2 m 108 flack vol/yr In liters The annual atmospheric dispersion parametert were calculated using the Air Quality Ottolay Model computer program (see Reference 6. Page 24).

The weighted average concentration of the alpha and beta misture, emitted from stackt 001 through 004, 062. 006, 013. and 014 was lett than 0.04%

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

lated on routine monthly game rey analyses of in.line system charcoal gas tamp 1tng cartridget installed in Stackt 001 and 002, no concentration of toJine.131 was found above the minimum detectable Ilmit. The air it '

monitored at a rate of 1.3 a 105 cm8/ min. This represents a weekly average temple volume of I.3 a 10'm8 The weighted average concentration of krypton.85 released from stacht 001, 002 aid 01) was 0.0021 of the NCC value at the site boundary. The concentra.

Lions were calculated by using strip chart recorder data from the galeous monitort on enhault Stackt 001, 002 and 013. The results are sumartaed in Table 2. (there it a discullion of RCG's in the appendts of this report.)

Identification of radionuclidet in the JN.I stack particulate emittfont from Stacht 001 through 004. 013. and 014 was made by monthly game spectrometric analyset and specific radiochemittry analytes of weekly i stack air temple filtert conpoltted over a 4. week pertad. Ga ena r

'8112 s 1010 represents the mantmum ground level concentration factor used in the calculation of the ADF at the lite boundary and was obtained using the Air Qualitt Ottplay Model computer program (see Reference 6). Thil '

factor it modified based on the Individual stack volume employed in the epatten.

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15 spectrometric analyses were perfcar4d using an intrinsic germanium detector coupled to a Canberra Model 8180 multi-channel analyzer. The concentrations of the radionur.lides identified were all less than 6.1 x 10-55 of the applicable RCG values at the site boundary, (see Table 3).

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I; Supplementary during 1983, see(air Figure sampling wasairperformed 6). These at four samples were site boundary collected locations continuously and analyzed on a weekly basis for gross alpha and beta activities. The average concentrations of activity at each of the site boundary locations

/ were all lower than the average gross alpha and beta activities found at l- 6 off-site background air sampling locations surveyed weekly at distances varying 5 to 44 miles from the Nuclear Sciences Area, (see page 40, Table 15).

sam Quarterlyfor analyzed congggite Pu, gjgPu, gges from jge Sr and Cs.four The site boundary locations concentrations were all were less than 6.7 x 10-6% of the respective RCG values (see Table 16).

Water Radioactive A sanitary sewerage system, which is operated in accordance with State of Ohio regulations under NPDES pennit No. N404-CD, handles all sanitary sewerage generated on the West Jefferson Site. The liquids are first treated in a 2,500-gallon Septic tank and then released to a 2,160-sq-foot contained sand and gravel filter bed. From the filter bed the effluent goes to a chlorinating system prior to release to Dig Darby Creek.

1' Sampling of all liquid effluents, from the Nuclear Sciences Area to Big Darby Creek, is performed using a continuous water sampling system. The effluents consist of the liquid discharge from the 2,160-f t2 filter bed. .

(see Figure 4). The effluent samples are analyzed weekly for gross alpna and beta activity in suspended and dissolved fractions. Any sample exceeding 3 x 10-8 uCi/ml* receives a supplementary gamma isotopic (GeLi) analysis and/or an alpha spectrometric analysis as appropriate.

The weekly samples are held, composited, and receive gamma spectrometric analyses as well as specific analyses for plutonium-239, plutonium-238, fodine-129, strontium-90, radium-226, and radium-228 at the end of each month. The concentrations uf gross alpha and gross beta activity in suspended and dissolved fractions as well as the concentrations of specific radionuclides identified in the sample are summarized in Table 4. In most cases the activity in the samples is due to a mixture of nuclides. The average concentration of the mixture was 9.67% of the RCG. The average concentrations of identified radionuclides in the mixture were 5.38% of the RCG for iodine-129, 0.0004% of the RCG for plutonium-238, 0.0012% for e plutonium-239, 0.41% of the RCG for strontium-90, 0.002% of the RCG for cerium-141, 0.30% of the RCG for radium-226, 3.97% of the RCG for radium-228 and 0.014% for lead-212.

• RCG value for unidentified radionuclides in unknown concentrations released to an un Attachment XI-l. {ggtrolled area, DOE Order 5480.1, Chapter XI,

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16 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 at the drain spillway at Darby Creek, (see Figure 6). The supplementary water samples are analyzed weekly for mixed alpha and beta activity. The average concentrations of total activity in the down stream water samples and the below dam water samples were all less than 56% of the RCG (3 x 10-8 uC1/ml) for release of mixed alpha and beta activity to uncontrolled areas and showed no significant difference f'~un the upstream control sample, (see Table 18).

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) Water Nonradioactive Presently, liquid effluents discharged from the West Jefferson Facility are subject to the restrictions of our National Pollutant Discharge Elimination System (NPDES) Permit. Battelle monitors and reports on a monthly basis to the Ohio Environmental Protection Agency (OEPA). Table 5 includes a list of the parameters for which BCL is presently required to analyze and report.

The data listed in Table 5 represents an average of the monthly data collected daring the twelve month period comencing January 1,1983, and ending December 31, 1983, and are required under the limits or restrictions set forth in BCL's NPDES Permit. The table serves to illustrate actual performance I against those limits or restrictions defined in BCL's pemit.

he data provided for the North Sanitary Sewer were obtained in accordance f with the BCL NPDES Permit No. N404-CD. The conditions of BCL's NPDES Pemit I 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. As the discharges are within the allowable discharge limits, the data reflect the ,

effectiveness of BCL's waste water management.

Grass and Food Crops Radioactive Grass and food crop samples are collected from the surrounding area. The {

intent of this portion of the Environmental Monitoring Program is to deter- i mine whether there is uptake and concentration of radionuclides by plant i or animal life. Where possible, sampling sites are chosen at maximum i deposition locations predicted by meterological studies. Grass and food l crop (soybean or 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 i quadrant of the nuclear site are composited. The samples are analyzed I for plutonium-239, plutonium-238, and strontium-90. A qualitative analysis by gama scan (GeLi) is also performed. The results of the grass and food crop analyses are summarized in Table 6 and 7. The maxiumum concentration of strontium-90 detected in grass samples was 1

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0.7 0.3 pC1/g located in the North Quadrant. The average concentration of strontium-90 in soybean samples was 0.23 2 0.07 pCi/g and <0.2 pC1/g for cesium-137. Plutonium-238 and plutonium-239 average concentrations l were 0.012 0.01 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 Figsre 4). The purpose of collecting silt I

samples is to estimate the! indentory of certain radionuclides deposited in this waterway and document for future reference. The silt samples I are analyzed for plutonium-239, plutonium-238, and strontium-90. A quantitative ganna isotopic (gel 1) analysis is also perfnrmed. The results of the analyses are summarized in Table 8. Concen.. -tions of Strontium-90 in silt samples collected above and below the srfluent release point averaged 0.07 2 0.02 pCi/g; for pli.tonium 238, 0.01 2 0.01 pCi/g, and for plutonium-239, 0.01 2 0.01 pC1/g and 0.0 2 0.0 pCi/g, respectively. Cesium-137 averaged 1.8 2 0.2 pC1/g above and 1.6 2 0.2

.pC1/g below, h

Soil Radioactive 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 nuclear site are composited, (see Figure 5). The soil samples are analyzed for plutonium-238, plutonium-239, and strontium-90. A quali-tative analysis by gamma scan (gel 1) is also perfonned. The results of the analyses are summarized in Table 9. The concentration of strontium-90 in soil samples averaged 0.3 2 0.1 pCi/g. The average concentration af plutonium-239 was 0.01 2 0.02 pC1/g and the plutonium-238 average concentration was 0.02 t 0.04 pC1/g for all soil samples collected. Gamma isotopic analyses of the soil samples showed the average concentration of cesium-137 to be 0.2 0.1 pC1/g and 0.8 2 0.1 pCi/g for Lead-212.

Fish Radioactive Fish samples were collected from Oarby Creek and Battelle Lake over a cine 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 garmna isotopic (gel 1) analyses was also performed. The results of the analyses are summarized in Table 11. Average concentrations

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18 of plutonium-239 in fish samples taken from Darby Creek were 0.00 t 0.01 pC1/g and 0.00 t 0.01 pCi/g for plutonium-238. The average conce9tration of strontium-90 in fish samples taken from Darby Creek was 0.5 2 0.1 pC1/g. and <0.2 pC1/g for cesium-137. Fish taken from Battelle Lake had average concentrations of pluton 16:n-239 and plutonium-238 0.00 2 0.01 pCi/g and 0.01 2 0.01 pC1/g, respectively. Average concentrations of strontium-90 and cesium-137 in fish samples taken from Battelle Lake were 0.7

• 0.1 pC1/g and <0.2 pC1/g, respectively.

Backaround 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 14 parameter dosimeter stations was 0.12 rem or 24% of the 0.5 rem limit established for the general public. This value includes contributions from natural background radiation which is estimated to be approximately 0.120 rem /yr. The results are sumarized in Table 12 and 13.

KING AVENUE $1TE Water Radioactive Sampling)of Facility all liquid discharges from the Building 1 (U-235 Process 19gsump to the Columb 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 analyz d for gross alpha and gross beta activities.

Anysampleexceeding4x109 uC1/ml* receives a gama isotopic (gel 1) analysis and/or an alpha spectrometric analysis as necessary.

Sample analyses are performed monthly on the Butiding 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 2.6% 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 1983 from the West Jefferson I and King Avenue sites are sumarized in Table 18.

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

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19 EVALUATION OF DOSE TO THE pUBLIC Estimated Radiation Doses to the Public from Emissions Dom the Battelle best Jefferson Site During CY 1983 The BCL Environmental Monitoring Report for CY 1983 presents data which provide infonnation for determining 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 i

West Jefferson Nuclear Sciences Area. The radiological impact of BCL's nuclear activities is calculated from the quantity of radionuclides measured directly in effluents from operating facilities in 1991, from the annual deposition of airborne radionuclides on vegetation and food crops.

and from residual radionuclides in stream sediment from past operations.

Atmospheric Discharges h Measured releases and ground level annual average concentrations at the site boundary during 1983 for the West Jefferson Site are sumarized in Table 2. The site boundary, which determines the perimeter for uncontrolled I exposure, is censidered coincident with the downwind position from the facility where the annual ground level concentrations will be highest.

This point is on BCL property but outside the security fence. The gross beta data in Table 2 shows that the total mixed fission product releases for 1983 amounted to 13.9 uCi with a total average concentration at the site boundary of 1.70 x 10-17 uC1/ml. Based on isotopic analyses of the stack effluents from the JN-1 facility, the principal radionuclides were determined to be cobalt-60, plutonium-239. cesium-137. lead-212, cerium-144, strontium-90, antimony-125, cesium-134, and uranium-235. The total krypton-83 emission was 2.90 Ci wghpC1/ml. a corresponding average concentration The total plutonium-239 at were emissions the site boundary of 3.54 x 10-0.85 uC1. Review of JN-1 facility operation for 1983 indicates that most of the gross alpha reported was due to plutonium-239. Therefore, all the alpha emissions are considered to be plutonium-239 only,17i th an annual average concentration at the site boundary of 1.04'x 10- uCi/ml. The total isotopic composition of the effluents emitted fr.m the five stacks of the JN-1 facility was used in evaluating the off ' te dose to the public.

Liquid Discharges Measured aqueous releases and effluent concentrations during 1983 for the West Jefferson Site are summarized in Table 4. The concentration values apply to the water discharged into Big Darby Creek after passage through a conventional leaching bed. Based on knowledge gained from an isotopic

4 20 inventory of radionuclide concentrations in the leaching bed, emissions should be due to very limited c'ution from the leach bed of contaminants that were delivered to the bed f r. cast years. Therefore, the alpha -

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

Estimated Radiation Dose to the Public from A_tmospheric Discharges Calculation of Atmospheric Dispersion Parameters In all cases on-site meteorological data were used as input to compute the annual average dispersion parameters for the site. Computer Code DACRIN programad for localized applications, was used to generate the '

required X/Q data for calculating dose to the maximum individual, nearest residence and population groups. Thus, annual average X/Q values were developed for a serles of concentric rings extending from the site boundary out to a distance of 50 miles. (Refer to Figure 12.)

The .inular rinCs were broken down into sixteen sectors corresponding to the nomal wind rose pattern. (Refer to Figure 11.)

~ Computation of Maximum Ir.dividol Nearest Residence and Population

- Group Dotes The annual radiation dose from gaseous and particulate radionuclides discharged ir.to the atmosphere was computed for a person continuously immersed in an infinite hentspnerical cloud containing the radionuclides.

Tables 2 and 3 list stack concentrations used to estimate site boundary, nearest residence and population group concentrations from the X/Q data noted in the above paragraph. The radionuclide composition and concentration of the atmospheric emissions was used to compute critical organ doses 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 annual dose estimates obtained for the maximum individual, nearest resident, and ,

for population groups from both gaseous and particulate emissions are j sumarized in Tables 20, 21, 22, 23 and 24. 1 I

The estimated off-site doses listed in the tables are very low compared to the rppimum permissible exposures (MPE) which have been reco' rended by the ICRP PJ and other groups for the general public. The FiPE yst.es recommended 1 for an individual are: bone - 3 rem /yr, GI tract - 1.5 rem /ya, whole body - l 0.5 rem /yr, skin - 3 rem /yr, thyroid - 3 rem /yr, lung - 1.5 met /yr, and kidney - 1.5 rem /yr. The reccmended values for a population aroup are one-third of these values. Therefore, from T61e 20 it may be seen that

- the largest fraction of MPE occurs to the skin end is 0.01% o' the  ;

recormnended limits at the site boundary. In comoarf Jori, uporure of persons j to natural background radiation in the area would be approximately 120 mrem /yr as measured by TLD stations. Therefore, atmospheric emissions from the site (Table 19) led to maximum estimated radiation doses which are approximately 0.04% of that expected from natural background. . i I

l e

t

) < 21 Computation of the 70-Year Oose Commitment for Maximum Individual. Nearest Resident, Population Groups and Integrated 50-Mile Population The 70-year dose comitments were detemined by using computer Code DACRIN based on annual meteorlogical data (Table 30), the 1980 estimated geographic distribution of the population in the various sectors around the site out to a 50-mile radius (Figure 12) and the radionuclide release data given in Table 19. Sumaries of the 70-year dose commitment groups are given in Tables 23, 24, 25, 26. and 28. The values given in Table 28 may be compared against the integrated person-rem /yr dose that

(

would be expected for the population group due to natural background, f 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 total population and the natural background radiation value. Using a natural background of appro imately 0.120 rem /

yr and a total 50-mile population figure of 1.73 x 10 produces an integrated population dose from natursi background of 2.08 x 10 5 person-rem /yr. The total body dose commitment caused by emissions from Battelle's West Jefferson Site to the integrated 50 mile population, is less than 6.1 x 10-8% of that due to natural background radiation.

Estimated 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 De possible.

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

Using computer Code PABLfi the estimated dose to the swimer who might spend 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. Results are given for the maximum individual, nearest resident, population groups and the integrated 50-mile population in Tables 21, 22, 23, 24, and 29.

Radiation Dose Due to Boatino and Water Skiina Big,0arby Creek is too small to allow boating or other water recreation spog:5. Thus, there will be no dose from these activities.

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).

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

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 radionuclide in the water in which the fish reside multiplied by a bioaccumulation factor. (8) Computer Code PABLM was used to estimate doses from eating fish taken from Battelle Lake and Big Darby Creek to the maximum individual, nearest resident, population groups and the integrated 50-mile population. See Tables 21, 22, 23, 24 and 29, Internal radiation doses were estimated on the basis of analytical data given in Table 4 for water samples taken from liquid effluents discharged to Darby Creek.

Comparison of the data in Table 21 for the maximum, individual, show that fish consumption is expected to be the dominant exposure pathway for persons f rom 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 120 mrem /yr. Therefore, maximum doses result-ing from liquid emissions from the site should have been approximately 0.0002% of that produced by natural background.

70-Year Dose Comnitment Tables 25, 26, 27, 28, 29 and 30 of this report provide estimated 70-year dose commitments to the maximum individual, nearest resident, population groups and the 80-kilometer population from one-year of exposure. Also given for terrestrial and aquatic pathway exposures, is the estimated 70-year accumulated dose to the maximum individual (and the 80-kilometer population from 70-years of continuous exposure to the residual environ- i mental contamination lef t by the one-year release. The radionuclide i composition of effluents reported for 1983 is shown in Table 19. Since these quantities of radionuclides, when dispersed in large volumes of air and water, were generally undetectable in the off-site environment, dose models (References 9 and 10) were employed to assess the resulting )

radiological dose impact. Code OACRIN was used to estimate doses from chronic inhalation of a radioactive m1xture using an atmospheric diffusion model. Code PABLM was used to estimate doses from the chronic ingestion of a radioactive mixture through terrestrial and aquatic pa thways.

i I

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

v f

I t

23 Fence Post Dose Estimate The " fence post" dose is the maximum measured accumulative dose possible to an individual having access to an uncontrolled area, excluding ingestion i and inhalation pathways. An estimated " fence post" dose of 10 mrem for 1983 was obtained by subtracting the average TLD background reading of 120 mren (Table 12. Page 37) from the averaged annual TLD reading of 130 mrem taken from Table 13, Page 38.

l Maximum Individual Dose Estimate The total body dose comitment calculated for the " maximum individual" is estimated as 10.06 mrem for 1983 and is the sumation of the following:

(1) 10 mrem, representing the " fence post" dose discussed in the previous paragraph; (2) 6.76 x .10-9 mrem, representing the 70 year dose comitment due to the atmospheric inhalation pathway (Table 25, Page 50); (3) 2.30 x 10-7 mrem, representing the 70 year dose commitment due to the atmospheric ingestion pathway (Table 25, Page 50); (4) 3.60 x 10-3 mrem, representing the 70 year dose commitment from eating fish (Table 25

j. Page 50); (5) 1.50 x 10-9 mrem, representing the 70 year dose comitmegt 3- resulting from aquatic reaction (Table 25, Page 50) and (6) 5.90 x 10-mrem, representing the annual whole body dose from Krypton-85 (Table 20.

Page 45).

Nearest Resident and Population Group Dose Estimates

- Although radiation dose estimates were calculated for a hypothetical

" maximum individual", the probability of this dose occurring is extremely remote. To obtain more realistic dose estimates, computations of "real" doses to the nearest resident and nearest population groups were made and included in the EMR for CY 1983. See Tables 20, 22, 23, 24, 26, 27 and 28.

8" 24 REFERENCES (1) U.S. Census.1980 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 U.S. Departnent of Energy Washington, D.C.. February 1981.

(3) Scioto River Basin Waste Load Allocation Report for the 303 (e)

Continuing Plannint: Process for Water Quality Management.

(4) ICRP Publication 2. "Recomendations of the International Commission on Radiological Protection. Report of Committee 11 on Pennissible 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 1%9. [

(7) U.S. NRC Regulatory Guide 1.109. " Calculation of Annual Deses to (

Man From Routine Releases of Reactor Effluents for Purpose of Evaluating Compliance With 10 CFR Part 50. Appendix 1."

(8) 00E/EP-0023. A Guide for Environmental Radiological Surveillance at USDOE installations. Revised July 1981.

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

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

(11) Civil Effects Cperations (LEX 59.4.23) Aeroradioactivity Surveys and A Real Geology of Parts of Ohio and Indiana (ARMS-1) May 1%6.

(12) " Estimates of Ionizing Radiation Doses in the United States 1960-2000", U.S. Environment Protection Agency. ORP/CSD 72-1.

v . .

u 25 l

Quality Assurance Several methods are used to assure that the data collected each year are representative of actual concentrations in the enviroment. Extensive environmental data are collected to eliminate an unrealistic reliance on only a few results. Newly collected data are compared with historical l 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 f on Darby Creek, to provide for identification of any net differences that may be attributable to the West Jefferson nuclear operations. These procedures, in conjunction 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 perfomed 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 inaintain internal quality assurance programs that involve routine calibration of counting instruments, daily source and background counts, routine yield deteminations of radiochemical procedures, and replicate analyses to check precision. The accuracy of radionuclide detemination 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 party who also checks all input data and assumptions used in calculation.

Infomation necessary to perfom all of the calculations are fully documented.

BCL also participates in the DOE /EML Quality Assessment Program which requires the qualitative analyses of spiked air, water, soil, vegetation and tissue samples furnished by DOE /EML semiannually. The spiked media samples are analyzed by the radiochemistry facilities serving BCL and the results reported to DOE /EML for verification of accuracy.

- - _ _ _ _ - _ _ _ _ _ - _ _ . - _ _ _ - _ _ _ _ l

26 i TABLE 1. POPULATION DISTRIBUTION WITHIN 10 MILE RADIUS FROM SITE 1

Distance Radius Population

~1,500 feet 0 2,500 feet 4 I mile 700 2 miles 3.500 5 miles 10,700 10 miles' 116.330

TABLE 2. StM4ARY OF ATMOSPHERIC RADIOACTIVE EMISSIONS - WEST JEFFERSON SITE CY 1983 10-2 Stack Percentage of Site Number of Volume Range Stack BoundaryN) RCG at Site Stack 1010 Activity MDL Stack 10-1" pC1/mi 10-18 pC1/mi Boundarytai Species Locations Samples 11ters/yr pCi/yr 10-16 pC1/ml 10-14 pCi/ml i

52 3.17 0.21- 0.007 <MDL-35.60 0.66 2 0.02 2.56 2 0.08 18.22 l

Gross a 001 33.88 2 0.23 001 52 3.17 2.77 0.004 0.30-214.00 8.74 2 0.06 Gross 0 002 52 11.70 0.47 0.007 <MDL-7.15 0.40 2 0.02 5.73 1 0.29 46.49 Gross a 87.25 t 0.86 Gross s 002 52 11.70 7.13 0.004 0.34-115.00 6.09 2 0.06 003 52 3.63 0.02 0.007 <MDL-0.19 0.05 2 0.01 0.22 2 0.04 - 1 51 I

Gross a 2.80 t 0.13 003 52 3.63 0.23 0.004 0.04-1.59 0.63 2 0.03 Gross s 52 1.44 0.12 0.007 <MDL-35.80 0.81 2 0.03 1.43 2 0.05 20 91 Gross a 004 40.39 1 0.19 Gross e 004 52 1.44 3.30 0.004 <MDL-1090.00 22.90 2 0.11 ,

y G.oss a 013 52 1.11 0.008 0.007 (MDL-0.50 0.07 0.01 0.10 t 0.01 0*87 013 52 1.11 0.13 0.004 0.18-9.85 1.20 1 0.03 1.63 t 0.04 Gross e 52 2.02 0.01 0.007 <MDL-0.25 0.05 2 0.01 0.12 2 0.02 1*16 Gross a 014 2.20 2 0.07 Gross s 014 52 2.02 0.18 0.004 <MOL-5.85 0.89 2 0.03 l

Gross a 012 52 2.48 0.01 0.007 <MDL-1.29 0.05 t 0.01 0.15 2 0.03 -0*82 l

012 52 2.48 0.12 0.004 <MDL-3.63 0.49 2 0.03 1.49 2 0.09 Gross s 52 0.38 0.004 0.007 <MDL-0.33 0.10 t 0.02 0.05 2 0.01 0.21 Gross a 006 006 52 0.38 0.03 0.004 <MDL-2.03 0.80 2 0.05 0.37

• 0.02 Gross s Activity, MDL, Range. Site Boundary, pct /yr 10-s vCi/ml 10 8 pC1/mi 10 ' Stack, pCi/ml 10-12 aci/ml 3.17 2.29 x 10 5

0.02 0.02-2.02 7.22 2.80 0.09

,,Ar 001 (c) 3.27 x 10 5

0.02 0.02-5.75 2.79 4.00 0.13 Kr 002 (c) 11.70 1.11- 2.34 x 10' O.02 2.73-41.60 210.81 28.64 0.95 Kr 013 (c)

(a) Site boundary concentrations calculated from stack concentration data using annual atmospheric dispersion parameters calculatedusingtheAirQualityDisplayModel(pReferengg7Page24)computerprogram.

(b) pCi/ml; Kr 3 x 10- pCi/ml.

(c) gG-formixedalphaandbetaactivity,2.x10-Kr concentration calculated by evaluation of data on strip chart recorder used with gaseous stack moni

TABLE 3. GAPetA EMITTING RADIONUCLIDES IDENTIFIED IN THE JN-1 (HOT LAB) STACK. EMISSIONS Cy 1983 10-6 Stack Composite Volume Site (c) Percent of (d)

(a) Location Stack (b) 1010 Activity, MDL, Range, Stack , Boundary, RCG at t Species Figure 4 Samples liters /yr pCi/yr 10-15 pC1/ml 10-15 pCi/mi 10-15 pCi/mi 10-18 pCi/mi Site Boundary 60 8.06 2 1,72 Co 002 12 11.70 0.66 0.80 <MDL-36.90 5.6321.20 2.69

, 003 12 3.63 0.07 0.80 <MDL-22.20 1.85 2 1.21 0.82 2 0.54 0.27 g 004 12 1.44 1.11 0.80 <MDL-900.00 76.80 2 2.00 13.54

• 0.35 4.51 013 12 1.11 0.009 0.80 MDL-10.10 0.85 2 1.18 0.12 2 0.16 0.04 137 1.31 2 1.20 0.5120.47 0.10 Cs 001 12 3.17 0.04 1.05 <MDL-12.50 002 12 11.70 0.53 1.05 4tDL-20.20 4.5621.22 6.53 2 1.75 1.31 4 003 12 3.63 0.01 1.05 <MDL-8.65 1.2421.15 0.55 2 0.51 0.11

004 12 1.44 1.63 1.05 4tDL-1300.00113.00 2 2.00 19.93 2 0.35 3.99 m 0.03 02 -

a 013 12 1.11 0.01 1.05- < MDL-14.80 1.2321.21 0.1720.16 014 12 2.02 0.03 1.05 < MOL-20,20 1.68 t 1.20 0.41 2 0.30 0.08 235 2.11 0.3320.% 0.13 2 0.37 3.25 0 001 12 3.17 0.01 < MDL-7.19 4 002 12 11.70 0.20 2.11 < MDL-20. 30 1.69

• 2.16 2.42 23.09 60.50

! 003 12 3.63 0.04 2.11 < MOL-8.97 0.96 2 1.70 0.43 ? 0.76 10.75 004 12 1.44 0.006 2.11 <MDL-4.66 0.39 2 1.75 0.07 20.31 1.75 013 12 1.11 0.003 2.11 < MDL-3.60 0.30 21.75 0.04 20.24 1.00 (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 stacir particulate emissions was by gamma spectrometric 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 Display Model (see Reference 7, page 24) computer program.

I Cs 5 x 10*10 pCi/ml; 60Co 3 x 10-10 pC1/ml; 235U 4 x 10-12 pCi/ml.

(d) RCG i

4

TABLE 4. SlM MRY OF LIQUID RADIDACTIVE EMISSIONS - WEST JEFFERSON SITE (MEASURE OF EF(LUENT FROM l SANITARY SEWERAGE SYSTEM INTO BIG DARBY CREEK - FIGURE 4. DESIGNATION 010)(as l CY 1983 1 l

1 Average MDL, Range RCG Percentage Number of Activity, Concentratio ) 10 8 pCf/mi of RCG Samples pct /yr 10-s pCi/ml 10-8 pCi/ml 10-9 pCi/ml Species 43.40 0.05 <MDL-1.66 4.74 1 0.25 10(c) 9.67 Gross a 52 52 45.20 0.02 *MDL-1.78 4.93 0.35 Gross a 90 11.20 0.10 <MDL-0.20 1.22 0.87 30 0.41 Sr 12 p 0.17 0.009 <MDL-0.01 0.02 0.05 500 0.0004 l 238'u 12 239 0.06 0.57 500 0.001 @

Pu 12 0.52 0.009 MOL-0.005 20.00 0.1 <MDL-2.36 2.18 18.09 9000 0.002 Ce 12 129 29.60 0.02 ' <MDL-0. 70 3.23 2.14 6 5.38 1 12 226 0.79 0.009 <MDL-0.02 0.09 0.03 3 0.30 Ra 12 228 10.90 0.01 < MOL-0.3 1.19 0.94 3 3.97 Ra 12 2I2 Pb 25.00 0.1 <MDL-2.00 2.73 35.49 2000 0.014 12 (a) Annual average flow in Big Darby Creek = 429 cu f t/sec - 3.82 x 1011 li ters/yr. Rate at which liquid effluents discharge = 9.16 x 106 liters /yr.

(b) Isotopic data for effluents released at this location were obtained from monthly composite 0samples.

1 Ra, and (c) RCG - Mixture of alpha and beta activity; 3 x 10-8 p C1/ml. (if it is known that 1, Ra are not present, the limiting value of 1 x 10-7 pCi/mi may be used.) See Appendix.

f a l

I 1

TABLE 5. NONRADIOLOGICAL SAMPLING FOR WEST JEFFERSON SITE.

January 1, 1983 to December 31, 1983 Permit, Requirements Discharge Limitations North Sanitary System Sewer " Londiggy Concentration Eg/ Day Kg/ Day Other Units Avg. Max. Min. Avg. 30 Day Dailey 30 Day Dailey Flow Rate (gal / day) 7056 10,800 5472 - (b) (b)

Residual Chlorine (ag/1) 0.38 0.5 0.1 .0101 - 0.5 pH Value (S.U.) 7.48 7.79 7.24 - 6.0 to 9.0 Fecal Coliform (#/100 ml) 1.92 12.0 0.0 - 200 400 g; Total Suspended 0.42 3.0 0.0 .0091 0.49 0.99 10 20 Solids (ag/1)

Temperature ( F) (a) (a) (a) - - 90 B.O.D. (5 day) (ag/1) 4.07 4.8 3.1 .1077 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) Permit requirement discharge limitations based on hPDES Permit #404-CD.

(e) Flow rate 0.013 mgd.

JP:b 2/29/84

e TABLE 6. SupMARY OF GRASS ANALYSES CY 1983 I Number of (b) )

Location (a)

Composite (Direction and Distance 90 238 239 137 l Samples Sr- Pu Pu Cs from Nuclear Science Area)

North Quad 6.4 km (4.0 miles) 2 0.7

• 0.3 0.01 20.01 0.00 2 0.01 521 8.0 km (5.0 elles)-

East Quad 1.6 km (1.0 alles) 3.2km(2.0 miles) 0.00 2 0.01 0.320.1 w 6.4 km (4.0 miles) 5 0.3 2 0.1 0.0320.01 ~

7.2 km (4.5 miles) 8.0 km (5.0 alles)

South Quad 0.8 km (0.5 miles) 2 0.3 20.1 0.01 2 0.01 0.00 20.01 421 3.1 km (1.9 miles) j

! West Quad 4.8 km 3.0 miles) 0.03 20.01 0.00 20.01 6t1 6.4 km 4.0 miles?- 3 0.3 2 0.1 8.0 km 5.0 milesj l On Site ----------------- 2 0.3 2 0.1 0.02 20.01 0.02 20.01 42 1 Note: No standards for radionuclides in grass have been established.

(a) Locations are shown in Figure 5.

(b) Minimum Detection Limit for % S r in grass is 0.1 pC1/g dry wt.

239 Pu in grass is 0.01 pC1/g dry wt.

238 Mininium Detection Limit for Pu and II Cs in grass is 0.3 pCi/g dry wt.

Minimum Detection Limit for 93 . p ._. ,

TABLE 7. SUMARY OF FOOD CROP ANALYSES CV 1983 LocationI '} Number of Type (Distance from Composite

'90 Sr 238 239 137 of Samples- Quadrant Nuclear; Sciences Area) Samples Pu Pu Cs Soybeans West 0.74 km (2400 feet) 2 0.07 2 0.04 0.01 2 0.01 0.00 i 0.01 <0.1 West 3.2 km (2.0 miles)

Soybeans North 4.0 km 2.5 miles 2 0.23 2 0.07 0.01 1 0.01 0.00 2 0.01 <0.1 North 8.0 km 5.0 miles Soybeans South 4.0 km 1.5 miles) U South 6.4 km 4.0 miles) 3 0.0920.03 0.00 1 0.01 0.00 t 0.01 <0.2 South 8.0 km 5.0 miles)

Field Corn On Site ----------------- 1 0.02 2 0.04 0.00 2 0.01 0.00 2 0.01 <0.2 Note: No standard for radionuclides in food crops have been established.

(a) locations are shown in Figure 5.

(b) Minimum Detection Limit for Sr in food crops is 0.02 pC1/g dry wt.

238 239 Minimum Detection Limit for Pu and Pri in food crops is 0.01 pC1/g dry wt.

Minimum Detection Limit for Cs in food crops is 0.1 pCi/g dry wt.

1

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[

TABLE 8.

SUMMARY

OF SILT ANALYSES CY 1933 oCi/o dry wt.(a)

Location (b) Number 90 238 239 Figure of Samples Sr Pu Pu A (20 yd above outfall) 2 0.07 2 0.02 0.01 2 0.01 0.01 2 0.01 8 (20 yd below outfall) 2 0.07 t 0.02 0.02 2 0.02 0.08 2 0.03 Note: No standards for radionuclides in silt have been established.

90 (a) Minimum Detection Limit for Sr in silt is 0.02 pCi/g dry wt.

238 239 Pu in silt is 0.01 pCi/9 dry wt.

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

a

' a pu u u' m

TABLE 9. St# NARY OF S0ll CORE ANALYSES FOR SPECIFIC RA010NUCLIDES CY 1983 Location (a) Number of (b)

(Direction and Distance Composite 90 238Pu Sr from the Nuclear Science Area) Samples Pu North Quad 6.4 km 4.0 miles) 2 0.01 1 0.02 0.00 2 0.02 0.3 1 0.1 8.0 km 5.0 miles East Quad 1.6 km ll1.0 miles) 3.2 km 1,2.0 miles 6.4 km 4.0 miles 5 0.02 0.02 0.00 2 0.01 0.3 0.1 7.2 km i(4.5 miles 8.0 km I 5.0 miles U

South Quad 0.8 km 0.5 miles) 3.1 km 1.9 miles) 2 0.02 1 0.04 0.01 2 0.01 0.3

• 0.1 West Quad 4.8 km 3.0 miles 6.4 km 4.0 miles 8.0 km 5.0 miles 3 0.04 1 0.03 0.01 2 0.01 0.4 2 0.1.

On Site -- ------------- 2 0.02 2 0.08 0.01 2 0.02 0.3

• 0.1 Note: No standards for radionuclides in soil have been established.

' The Environmental Protection Agency's proposed federal radiation protection guidance for exposures to tbansuranium elements in the environment has reconnended a reference level of 0.2 pCi/m for soll contamination.

(a) Locations are shown in Figure 5.

8 239 Pu in soil is 0.01 pCi/g dry wt.

(b) Minimum Detection Limit for Pu and Minimum Detection Limit for Sr in soil is 0.1 pC1/g dry wt.

__ _ ___-s e

TABLE 10.

SUMMARY

OF GAM A ISOTOPIC ANALYSIS OF SOIL CORE SAMPLES.

CY 1983 -

Location (Direction and Distance from the Nuclear Science Area)(a)

North Quad East Quad South Quad idest Quad -

6.4Km(4.0 miles) 1.6 Km 1.0 elles) 0.8 Km (0.5 miles) 4.8 Km 3.0 miles 8.0 km (5.0 miles) 3.2 Km 2.0 miles) 3.1 km (1.9 miles) 6.4 Km 4.0 miles 6.4 Km 4.0 miles) 8.0 rm 5.0 miles 7.2 km 4.5alles)~ On Site l

8.0 Km (5.0 miles)

Number of Composite 2 2 5 2 3 Samples Average Concentration pCf/g (dry) wt.(b) g Nuclide 40g (c) 12.0 2 2.0 16.0 2 2.0 16.0 2 3.0 10.0 2 2.0 16.0 2 2.0 214PbICI 1.1 2 0.2 1.4 2 0.2 1.1 2 0.2 0.9 20.2 1.2 20.2 214Bi(c) 1.12 0.2 1.0 2 0.2 1.3 2 0.2 0.9 1 0.2 0.9 1 0.2 2I2 F:s 0.6 2 0.1 0.8 20.1 0.8 20.1 0.8 20.1 0.8 2 0.1 137 Cs 0.32 0.1 0.2 20.1 0.2 2 0.1 0.4 20.1 0.3 20.1 Note: No standards for radionuclides in soll have been established.

(a) locations are shown in Figure 5.

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

40K 2.0, 214Pb 0.2, 21481 0.2, 2I2Pb 0.1,137Cs 0.1 (c) Naturally occurring radionuclides.

.y

m TABLE 11. StM4ARY OF FISH ANALYSES CY 1983 r of pCi/o dry wt.(b)

Period of .Compostte LocationI 'I Collection Samples 238p , 239p , 137 Cs "Sr i Darby Creek. 1st qtr. (c)

Battelle Lake 1st qtr. (c) 2nd qtr. 0.00 2 0.01 0.00 2 0.01 <0.2 0.3 2 0.1 Darby Creek 1 2nd qtr. 0.01 2 0.01 0.00 2 0.01 <0.2 0.7 2 0.1 Battelle Lake 1 0.00 2 0.01 0.00 2 0.01 <0.2 0.7 t 0.1 Darby Creek 3rd qtr. 1 0.00 2 0.01 0.00 2 0.01 <0.2 0.3 2 0.1 Battelle Lake 3rd qtr. 1 Y

0.01 2 0.02 0.01 2 0.01 <0.2 0.5 2 0.1 Darby Creek 4th qtr. 1 0.01 2 0.01 0.00 z 0.01 <0.2 1.0 2 0.1 Battelle Lake 4th qtr. 1 Note: No standards for radionuclides in fish have been established.

(a) Fish samples were collected from various locations within Battelle lake. Fish samples from Darby Creek were taken at various distances within 1000 f t downstream from the sanitary outfall. (See Figure 6).

(b) Minimum Detection Limit for Sr in fish was 0.1 pCi/g dry weight. 0.2 pCi/g 238 dry weight I37 Cs, and 0.01 pC1/g dry weight for Pu and 239 ,,

p (c) No fish samples were collected during the first quarter of Cy 1983 i

1 l

- m J

i a

F 5

I 37 s

TABLE 12. EXTERNAL BACKGROUND RADIATION LEVELS WITHIN 3/4-MILE RADIUS-WEST JEFFERSON SITE CY 1983

[

Location qq Exposure to TLD in Rem Olstancetas 1st Qtr. 2nd Qtr. 3rd Qtr 4th Qtr. Total for Year Southwest 400 ft <0.030 <0.030 <0.030 <0.030 <0.120 2400 ft <0.030 <0.030 <0.030 <0.030 <0.120 f 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 I Southeast 1200 ft <0.030 <0.030 <0.030 <0.030 <0.120 3300 ft <0.030 <0.030 <0.030 <0.030 <0.120 Sou th 1350 ft <0.030 <0.030 <0.030 <0.030 <0.120 1800 ft <0.030 <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 <0.030 <0.120 Northeast 1200 ft <0.030 <0.030 <0.030 <0.030 <0.120 Northwest IJ13 ft <0.030 <0.030 <0.030 <0.030 <0.120 North 1500 ft <0.030 <0.030 <0.030 <0.030 <0.120 (a) Refer Figure 8. Average total for year <0.120

38 TABLE 13. EXTERNAL BACKGROUND RADIATION LEVELS AT PERIMETER SECURITY FENCE - WEST JEFFERSON SITE CY 1983 Exposure to TLD in Rem Location Distance a (af 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total fc Year Southwest 100 ft 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 ft 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 0.030 <0.130 200 f t JN-1 <0.030 <0.030 <0.030 <0.030 <0.120 240 f t JN-1 <0.030 0.030 <0.030 0.030 <0.120 250 f t JN 1 0.030 0.040 0.030 0.030 <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 so.120 190 ft JN-1 <0.030 0.040 <0.030 <0.040 <0.140 East 150 ft JN-4 <0.030 0.030 <0.030 0.030 <0.120 230 ft JN-1 0.030 0.060 0.030 0.060 0.180 240 ft JN-1 0.040 0.070 0.030 0.060 0.200 Northeast 150 ft JN-4 <0.030 <0.030 <0.030 <0.030 <0.120 225 f t JN-4 <0.030 <0.030 <0.030 <0.030 <0.120 250 ft JN-1 <0.030 0.040 <0.030 0.040 <0.140 260 ft JN-1 <0.030 0.040 0.030 0.050 <0.150 l 275 ft JN-3 <0.030 <0.030 <0.030 <0.030 <0.120 Northwest i 200 f t JN-4 <0.030 <0.030 <0.030 <0.030 <0.120 1 250 f t JN-3 <0.030 <0.030 <0.030 <0.030 <0.120 l North 150 ft JN-4 <0.030 <0.030 <0.030 <0.030 <0.120 200 ft JN-4 <0.030 <0.030 <0.030 <0.030 <0.120 l 300 ft JN-3 <0.030 <0.030 <0.030 <0.030 <0.120 I

(a) Refer rigure 9. Average total for year <0.130 '

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o; TABLE 15. SumARY OF SITE BOUNDARY AIR 54MPLE ANALYSES FOR GROSS RADIDACTIVITY CY 1983 LocationI *I 10-15 pCi/m1 IDI Direction and Distance Number from Nuclear Sciences Area of Samples Gross a ICI Gross S ICI l

North Quadrant Station 0.00

• I.64 (450 f t. North of JN-4 Stacks) 52 0.01 1 0.54 l

East Quadrant Station (400 f t. East of JN-1 Stacks) 52 0.04 2 0.54 0.13 2 1.64 1

South Quadrant Stattor:

(750 f t. South of JN-2 Stacks) 52 0.09 20.54 0.00 2 1.63 West Ouadrant Station (400 f t. West of JN-2 Stacks) 52 0.00 2 0.54 0.00 2 I.62 (a) Locations are shown in Figure 6.

(b) Minimum Detection 1imit for gross a is 1 x 10-17 6Cl/m1 and 4 x 10 C1/mi for gross 8.

(c) The values shown for gross a and gross 8 indicate site boundary concentrations above background concentrations found at off-site air monitoring stations. See Table 17.

I 1

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

TABLE 16. SUP9tARY OF SITE BOUNDARY AIR SAMPLE ANALYSES FOR SPECIFIC RADIONUCLIDES CY 1983 Location (a) 10-19 >Ci/m1(b)

Direction and Distance Number of 90 238 239 137 Composite Samples Sr Pu P4 Cs from Nuclear Sciences Area 4 0.% r 0.M 0.02 2 0.04 0.04 2 0.M 40 50 f t of 4 stacks)

I s .20 0.02 t 0. H 0.02 2 0.03 40 4 E fJ stacks) 1 South Quadrant Station 4 0.93 s 1.59 0.04 2 0.04 0.01 2 0.03 <10

(750 f t. South of JM-2 stacks) t 4 0.8520.%- 0.M r 0.03 0.01 2 0.03 <10 t! to 2 stacks)

(a) Locations are shown in Figure 6.

90 (b) Minimum detection limit for Sr is 7 x 10-2o Sci /ml. 238Pu 2 x 10 21 Sci /ml.

. 239Pu 2 x 10-2: pC1/m1. and I37 Cs 1 x 10-as Sci /mi.

l l

42 TtBLE 17. SUMMARf 0F OFF SITE AIR SAMPLE ANALYSES CY 1983 Location (a)

Direction and Distance Number 10*14 uti/ml(b) from Nuclear Sciences Area of Samples Gross a Gross a Grandview (17.8 km east) 52 0.59 2 0.06 3.68

• 0.15 Chesapeake (24.4 km east) 52 0.54 2 0.05 3.51 2 0.15 Fairgrounds (24.8 km northeast) 52 0.57

• 0.05 3.4920.16 Newark )

(70.8 km northeast 52 0.52 2 0.05 3.61 2 0.16 Grove City (14.5 km southeast) 52 0.49

• 0.05 3.36 0.15 New Rome *

(8.0 km east) 52 0.48 2 0.05 3.35 2 0.14 (a) Locations are shown in Figure 10.

(b) Minimum Detection Limit for gross = is 7 x 10*'# aci/mi and 4 x 10-l' 9C1/ml for gross 3.

i

= = . . . .

?

5 T.'

l.

r 43 I~

b.

TABLE 18.

SUMMARY

OF ENVIR0tNENTAL WATER SAMPLE ANALYSES CY 1983 l'

b Location (a)

f. Direction and Distance Number- 10-9 uC1/m1(b)

'- from Nuclear Sciences Area of Samples Gross a Gross s Darby Creek Upstream (18.3 m above sanitary outfall) 52 6.12 2 0.75 5.51 1 0.74 1.

Darby Creek Downstream (18.3 m below sanitary outfall) 52 6.46 2 1.01 5.27 2 0.96 Darby Creek Downstream (186.3 m below sanitary outfall) 52 5.09 z 0.67 '5.22 2 0.90

. Battelle Lake Spillway (18.3 m below dam) 52 4.66 2 0.63 5.84 0.91 (a) Locations are shown in Figure 6.

(b) Minimum Detection Limit for gross a is 2 x 10-10 pC1/ml and 1 x 10-10 uC1/mi for gross s.

N

_.m_.-_________.m. _ _ . . _

I

]

44

\

. TABLE 19. RADIONUCLIDE COMPOSITION OF BCL EFFLUENTS CY 1983 West Jefferson Site Air Activity (uC1)

~

- Gross Alpha 0.85 Gross Beta 13.89 Plutonium-239 0.85 Cobal t-60 1.77 Strontium-90 0.00005 Cesium-137 2.16

. Cesium-134 0.01 Lead-212 0.02

• Lead-214 0.05

- *Bismu th-214 0.70 Corium-144 0.26 Antimony-125 4.63 Krypton-85 2896000.00 Rhodium-106 0.34 d Uranium-235 0.25

• Potassium-40 7.23 Thallium-208 0.06 Water Activity (uC1)

Gross Alpha- 43.40 Gross Beta 45.20 Iodine-129 29.60 Strontium-90 11.20 Plu tonium-238 0.17 Plutonium-239 0.52

-Radium-226 0.79 Radium-228 10.90 Lead-212 25.00

• Bismuth-214 64.00 Cerium-141 20.00

• Potassium-40 1520.00 i

King Avenue Site Water Activity (uC1)

' Gross Alpha . 561.00 Gross Beta . 772.00

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

l l

d t

45 e

l' TABLE 20. Su MARY OF ANNUAL RADIATION DOSE TO THE MAXIMUM INDIVIDUAL, NEAREST RESIDENT AND POPULATION GROUPS FROM RELEASES OF KRYPTON-85 DURING CY 1983 i

' Critical Organ Dose to the Maximum Individual (0.122 Km)

. Total Body 5.90 x 10-2 mrem /jr Skin 3.54 x 10-l mrem /yr Dose to the Nearest Resident (0.750 Km NW)

Total Body 5.97 x 10-6 mrem /yr Skin 3.58 x 10-5 mrem /yr b

Dose to the Nearest Population Group (Darby Estates Population 2,000)

Total Body 2.12 x 10-3 person-rem /yr Skin 1.33 x 10-2 person-rem /yr Oose to the Population Group (West Jefferson, Population 6,000 Total Body 1.93 x 10-3 person-rem /yr Skin 1.16 x 10-2 person-rem /yr

J

. y-r TABLE 21.'ANNU'.LDOSETOTHEMAXIMUMINDIVIhuALFROM

. EFFLUENTS RELEASED DURING CV 1983 i

Dose (aren/yr)

,Whole Pathway Body Gl(a) Thyroid Kidneys Bone lungs

. Airborne (inhalation) 6.31 E-6 3.15 E-6 7.08 E-10 1.66 E-5 7.90 E-5 5.60 E-3 l.ir'ourni ((noelth) l a E-7 7.50 E-e 2.80 E-12 9.70 E-e 1.50 E-7 2.10 E-e Eating Fish 2.30 E-" 8.60 E-9 9.60 E-5 2,20 E-6 1.20 E-6 9.50 E-30 Aquatic Recreation 1.50 E-9 1.50 5,-9 1.50 E-9 1.50 E-9 1.50 E-9 1.50 E-9 (a) Gastrointestinual tract (lower large intestine),

s e .. . . . - -;..,--. .. - - .

TABLE 22. ANNUAL DOSE TO THE NEAREST RESIDENT (0.75 KM NW)

' FROM EFFLUENTS RELEASED DURING CY 1983

-l l

Dose (arem/yr)

Whole

• Pathway Body GII *I Thyroid Kidneys Bone Lungs 6.49 E-8 3.25 E a 7.31 E-12 1.71 E 7 ' 8.14 E-7 5.75 E-5 Airborne (inhalation)

Airborne (ingestion) 5.52 E-9 1.15 E-9 1.29 E-13 4.46 E-S 6.90 E-S 9.66 E-10 Eating' Fish 2.30 E-4 8.60 E-S 9.60 E-5 2.20 E-6 1.20 E-" 9.50 E-30 Aquatic Recreation 1.50 E-S .1.50 E-9 1.50 E-9 1.50 E-9 1.50 E-S 1.50 E-S l

l (a) Gastrointestinual tract (lower large intestine),

s

y 1

.c i

TABLE 23. ANNUAL DOSE TO THE NEAREST POPULATION GROUP (DARBY ESTATES)

FR(M EFFLUENTS RELEASED DURING CY 1983 -

Dose (Person-res)(b)

Whole Pathway Body GI(a) Thyroid Kidneys Bone Lungs

- 5.90 E-5 2.96 E-5 6.64 E-S 1.55 E-" 7.39 E-4 5.24 E-2 Airborne (inhalation)

Airborne (ingestion). 2.71.E-e 5.65 E-s 6.33 E-13 2.19 E-8 3.39 E-s 4.74 E-'

Eating Fish' . 4.60 E

• 1.72 E-s 1.92 E-* 4.40 E 6 2.40 E

• 1.90 E-S Aquatic Recreation 3.00 E-' 3.00 E-' 3.00 E-S 3.00 E ' 3.00 E-' 3.00 E-'

l l

-(a) . Gastrointestinual tract (lower large intestine).

l (b) Population affected: 2000

---

-- . . - -h .-_.h -_.__..m___ M_ _, _

-- ~

u. -- - .. --. . -.

~

-TABLE 24. ANNUAL DOSE TO THE POPULATION GROUP (WEST JEFFEP. SON) '

.FROM EFFLUENTS RELEASED DURING CY 1983

]

Dose (Person-ren)(b)

Whole .j GII 'I Lungs 4

Pa thway Body Thyroid Kidneys Bone. ,

8.52 E-5 4.25 E-5 9.58 E-9 2.23 E-4 1.06 E-3 7.55 E-2 Airborne (inhalation)

- Airborne (ingestion) 1.35 E 7 2.80 E-8 3.14 E-12 1.09 E-7 1.68 E-7 2.36 E-s Eating Fish 1.38 E-3 5.16 E e 5.76 E-* 1.33 E-5 7.20 E-3 5.70 E-9 Aquatic Recreation 9.00 E-S 9.00 E-9 9.00 E-9 9.00 E-9 9.00 E-9 9.00 E-S l

' (a) Gastrointestinual tract (lower large intestine).

(b) Population affected: 6000 ,

l 9

il}\l\ l l!  ;

2 e 9 9 e 9 9 E E E E E E E s

g 6 0 0 0 0 0 0 n 0 8 6 5 0 6 5 u 4 L 1 3 1 1 1 1 2 7 3 9 7, 3 9 E E E E E E E e 0 0 0 0 0 0 0 .

n 4 9 7 5 4 7 5 o 5 3 B 1 4 3 1 1 L

A U 7 9 7 6 9 D 3 6 I s - - - - - - -

V y E E E E E E E I e 0 _

D ) n 8 0 0 0 0 0 _

N r d 6 5 2 5 0 2 5 _

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n n l

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a t s

i t

t s

i t

s e

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n n r n ( r i i i

( (

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c i e (

h s

c e

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y n nr c nr c a 0 a r g i g i G 7 w o o n t o ni t h b b i a b a t r r t u r t u ) )

a i i a q i a q a b P A A E A A E A ( (

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i l l; llf ff

1 TABLE 26. 70 YEAR DOSE C0milTMENT FOR THE NEAREST RESIDENT (0.75 KM NW) FROM EFFLUENTS RELEASED DURING CY 1983 i

Dose'(arem/yr)

Ele -

Lungs Pathway Body Gl(a) Thyroid Kidneys Bone 6.95 E-6 3.33 E-s 7.31 E-12 2.76 E-5 1.44 E-4 1.09 E-4 Airborne (inhalation)

Airborne (ingestion) 9.66 E-9 1.15 E-9 1.33 E-13 6.90 E-9 2.25 E*8 1.75 E-9 Eating Fish 3.60 E-3 8.60 E-9 1.50 E-* 2.20 E-6 3.70 E-3 1.60 E-9 Aquatic Recreation 1.50 E-9 1.50 E-9 1.50 E-9 1.50 E-9 1.50 E-9 1.50 E-9 Airborne (ingestion)(b) 1.06 E-s 1.15 E-9 1,29 E-10 9.20 E-9 2.48 E 8 1.84 E-9 Eating Fish (b) 3.60 E-3 8.60 E-9 1.50 E-" 2.20 E-6 3.70 E-3 1.60 E-9 Aquatic Recreation (b) 1.50 E-9 1.50 E-9 1.50 E-9 1.50 E-9 1.50 E-9 1.50 E-9 (a) Gastrointestinual tract (lower large intestine).

(b) 70-Year Accur.nlated Dose. .

T L

- - - r

TABLE 27. 70 YEAR DOSE CONtITMENT FOR THE NEAREST POPULATION GROUP' (DARBY ESTATES) FROM EFFLUENTS RELEASED DURING CY 1983 i

Dose (Person-ren/yr)(b)'

Whole Pathway Body GI(a) Thyroid Kidneys Bone . Lungs-Airborne (inhalation) 6.33 E-6 3.03 E-s >6.64 E-12 2.51 E-5 1.31 E-4 9.90 E 5 Airborne (ingestion) '4.75 E-s 5.65 E-9 6.55 E-83 3.39 E-s 1.11 E-7 8.59 E S Eating Fish 7.20 E-3 1.72 E-s 3.00 E-" 4.40 E-6 7.40 E-3 3.20 E 9 E Aquatic Recreation 3.00 E-* 3.00 E-S 3.00 E-S 3.00 E-9 3.00 E-S 3.00 E-S Airborne (ingestion)ICI 5.20 E-s '5.65 E-S 6.33 E 4.52 E-s 1.22 E-7 9.04 E-9 Eating Fish ICI 7.20 E-3 1.72 E-s 3.00 E-4 4.40 E-6 7.40 E-3 3.20 E*S Aquatic Recreation IC 3.00 E-8 3.00 E-S 3.00 E-9 3.00 E-S 3.00 E-S 3.00 E-9 (a) Gastrointestinual tract (lower large intestine).

(b) Population affected: 2000 (c) 70-year accumulated dose.

w- -_ _r --_ - _ ' -M__ =-1 ._, __

7- ,- _

TABLE 28. 70 YEAR DOSE COMITMENT FOR THE POPULATION GROUP (WEST JEFFERSON)

FROM EFFLUENTS RELEASED DURING CY 1983 Dose (Person-ran/yr)(b)

Whole Pathway Body GI'I I Thyroid Kidneys Bone Lungs 4.36 E.s 9.59 E.12 3.61 E 5 1,89 E-" 1.42 E-"

Airborne (inhalation) 9.11 E 5 2.36 E 7 2.80 E s 3.17 E.12 1.68 E 7 5.50 E-7 4.26 E e Airborne (in9estion) '

Eating Fish 2.16 E.2 5.16 E s 9.00 E " 1,32 E 5 2.22 E.2 9.60 E ' g Aquatic Recreation 9.00 E ' 9.00 E

• 9.00 E ' '9.00 E ' 9.00 E 8 9.00 E '

Airborne (ingestion)ICI 2.58 E 7 2.80 E.s 3.14 E-' 2.24 E 7' 6.06 E 7 4.49 E.e l

Eating Fish (c) 2.16 E.2 - 5.16 E.a 9.00 E " 1,32 E 5 2.22 E.2 9.60 E-*

AquaticRecreation(c) 9.00 E

• 9.00 E ' 9.00'E-' 9.00 E-9 9.00 E ' 9.00 E-'

(a) Gastrointestinual tract (lower.large intestine).

(b) Population affected: 6000.

(c) 70-year accumalated dose.

s._. . ._. __

.il 4

,1 TA8LE 29. 70-YEAR DOSE C0fMITMENT FOR INTEGRATED 80-KILOMETER POP'JLATION FROM LIQUID EFFLUENTS RELEASED DURING CV 1983 4

i Population Dose (Person-ree)'

! Population idhole Exposure Mode Affected 8ody G1g ,) Thyroid Kidneys Bone Lungs Eating Fish 1.5 x 105 - 6.60 E-2 1.60 E-7 2.80 E-3 4.10 E-5 6.80 E-2 3.00 E-s Aquatic Recreation 1.5 x 105 8.90 E-9 8.90 E-9 8.90 E-9 8.90 E-9 8.90 E-9 8.90 E-9 Eating Fish (b) 1.5 x 105 6.60 E-2 1.60 E-7 2.80 E-3 4.10 E-5 6.80 E-2 3.90 E-a AquaticRecreation(b) 1.5 x 105 8.90 E-9 8.90 E-9 8.90 E-9 8.90 E-9 8.90 E-9 8.90 E-9 i

i

(a) Gastrointestinal tract (lower large intestine).

1 i (b) 70-Year Accumulated Dose.

] .

1 4

i i

i 1

l

-- - - - - - - - - . - - _ - . - _m , _

I ilI I

6 3 6 E E E s

g 0 8 0 n 1 7 2 u

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- e 0 7 0 n 7 3 0

- o N B 2 2 3 O )

I T

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U n P o 6 " 5 O s s - - -

P r y E E E e e R' p n 0 3 0

- E ( d 3 6 1 T i E e K 8 4 1 M3 s O8 o L9 D

. I1 K n 0 0 Y o 3 1 7 0C i d - - -

8 t i E E E G a o r

DN l 0 5 0 EI u y 6 2 5 TR p h AU o T 1 1 1 RD P G

ED 1E 6 7 6 hS - - -

tA E E E E I RL 0 7 0 OE I' 4 4 4 FR I G 1 5 1 TS NT EN ME TU )

lL F 5

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n E e t E l y 0 4 0 s EN od 2 1 3 e SR ho t OO WB 1 1 1 n DB i R

RI e AA r g E en a r

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7F oa ll x x x e iu w

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3

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( e 8 1 1 1 s E t o L c D B a A I r d T ' D I

t t

e

) ) l a n ) n a l o n n u i o i m t

s i

t

%r t s c u

e a e e c g l g t A e n a n n d i h i i r o ( n ( o a M i r e f ( f t Y e f f s -

r u c u a 0 u t i t G 7 s s n s o d o d p o r o ) )

x o h o a b E F C f ( (

i i[l l

4 56 TABLE 31 PARAMETERS FOR WEST JEFFERSON SITE AIRBORNE RELEASE DOSE CALCULATIONS Facility name: JN-1 (Hot Lab)

Releases: See Table 3 Meteorological conditions: West Jeff meteorological station 1-year data (1/2-31/83), annual average D hpersion model: Gassian, BCL parameters X/Q: Maximum individual 7.26 x 10-5 sec/m3 9122m SE 80-km population  ;

7.09 x 10-9 sec/mJ Release height: . 24.2 meters effective (18.28 meters actual stack height)

Population distribution: 1.73 x 106, see Figure Compuier code: DACRIN, version 1.2, Rev. 1980 Calculated dose: Chronic inhalation, maximum individual and 80-km population, 70-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.

70-year dose comitment 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. 3-1L-81 Bioaccumulation Factor Library 1

r-57 i

TABLE 32 AVERAGE ANNUAL PE9 CENT FREQUENCY OF WIND DIRECTION AND AVERAGE WIND SPEED (M/S) FOR CY 1983 Direction Percent Average Speed (M/S) i N 4.0 4.2 NNE 2.6 4.0 NE 4.4 3.6 ENE 4.1 3.7 E , 4.5 3.8 ESE 4.7 4.0 SE 6.6 4.6 SSE 7.4 5.2 5 9.6 5.0 SSW 6.9 4.9 SW 10.3 6.1 WSW 8.4 5.4 W 11.1 4.8 WNW 4.2 4.9 NW 4.6 4.8 NNW 4.4 4.7 CALM 1.2 ...

Total 100.0 4.6

T m l

TABLE 33. ANNUAL AVERAGE ATMOSPHERIC DISPERSION AROUND THE WEST JEFFFR50N $1TE FOR A 18 NETER STACK HEIGHT 3

l RELEASE (UNITS ARE SEC/M ) (a) l t

Range in Miles (Km)

Direction 0.5 (0.8) 1.2 (2.0) 2.5 (4.0) 3.5 (5.6) 4.5 (7.2) 7.5 (12) 15 (24) 25 (40) 35 (56) 45 (72)

N 3.5 x 10-5 7.87 x 10-6 2.24 x 10-6 1.20 x 10-6 7.79 x 10-7 3.26 x 10-7 1.05 x 10-7 4.65 x 10-8 2.71 x 10-8 1.83 x 10-8 I NME 3.68 x 10-5 8.26 x 10-6 2.35 x 10-6 1.26 x 10-6 8.18 x 10-7 3.43 x 10-7 1.10 x 10-7 4.89 x 10-8 2.84 x 10-8 j,93 x 30-8

! NE 4.09 x 10-5 9.18 x 10-6 2.61 x 10-6 1.40 x 10-6 9,09 x 30 77 3.81 x 10-7 7 I

ENE 3.98 x 10-6 8.93 x 10-6 2.54 x 10-6 1.37 x 10-6 8.84 x 10- 3.71 x 10-7 1.23 1.19 xx10-10 7 5.43 5.28 xx 10-8 10-8.3.07 x 10-8 2.14 3.16x 10-8 x 10-8 2.08 x 10-8 3.d8 x 10-5 8.70 x 10-6 2.47 x 10-6 1.33 x 10-6 7 10 7 1.16 x 10-7 5.14 x 10-8 2.99 x 10-8 2.03 x 10-8 E

l ESE 3.68 x 10-5 8.26 x 10-6 2.35 x 10-6 1.26 x 10-6 8.61 8.18 xx10-7 10-73.43 3.61x x10- 1.10 x 10-7 4.89 x 10-8 2.84 x 10-8 1.93 x 10-8 l SE 3.20 x 10-5 7.18 x 10-6 6 1,10 m 10-6 7.11 x 10-7 2.98 x 10-7 9.61 x 10-8 4.25 x 10-8 2.47 x 10-8 1.67 x 10-8 v.

2.83 x 10-5 6.36 x 10-6 2.04 1.81 x 10 6 x 10- 9.72 x 10-6 6.29 x 10-7 2.64 x 10-7

• l SSE 8.50 x 10-8 3.76 x 10-8 2.19 4 10-8 1.48 x 10-8 l

2.95 x 10-5 6.61 x 10-6 1.88 x 10-6 1.01 x 10-6 6.54 x 10 7 2.74 x 10-7 8.84 x 10-8 3.91 x 10-8 2.27 x 10-8 5 7 1.54 x 10-8 l SSW 3.01 x 10-5 6.75 x 10-6 1.92 x 10-6 1.03 x 10-b 9.02 x 10-8 3.9) x 10-8 2.32 x 10-8 1.57 x 10-8 2.41 x 10-5 5.42 x 10-6 1.54 x 10-6 8.20 x 10-7 6.67 x 10 5.36 x 10- 7 2.80 x 10-7 7

2.25 x 10 7 7.24 x 10-8 3.20 x 10-8 1.86 x 10-8 1.26 x 10-8 SW W5W 2.73 x 10-5 6.21 x 10-6 1.74 x 10-6 v.36 x 10-7 6.06 x 10-7 2.54 x 10- 8.18 x 10-8 3.62 x 10-8 . 2.10 x 10-8 1.43 x 10-8 C3 3.07 x 10-5 6.89 x 10-0 1.% x 10-60 1.05 x 10-6 6.81 x 10-7 2.86 x 10-7 9.21 x 10-8 4.07 x 10-8 2.37 x 10-8 1.60 x 10-8 WNW 3.01 x 10-5 6.75 x 10-6 1.03 x 10-6 6.67 x 10-7 2.80 x 10-7 9.02 x 10-8 3.99 x 10-8 2.32 x 10-8 1.57 x 10-8 hW 3.07 x 10-5 6.89 x 10-6 1.92 1.% xx 10-10 6 1.05 x 10-6 7 8 NNW 3.13 x 10-5 7.03 x 10-6 2.00 x 10-6 1.08 x 10-6 6.81 6.% xx10-7 10-72.92 1.86 x 10-x 10 7 9.40 9.21 xx 10-8 10-84.16 4.07x x10- 10 8 2.42 10-8 1.60 2.37xx10-8 x 10-8 1.64 x 10-8 l

(a) Calculated from meteorological data collected during the period 1-83 through 12-83.

=

TA8LE 34. BMI KING AVENUE SITE POPULATION WITHIN 50 MILES 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 Total N 1,205 4,202 8,700 7,216 8,502 26.724 7,615 11,143 15,914 24,936 116.157 2,225 8,382 10,061 9,073 36,911 8,315 9,702 8.687 13,102 116,999 NNE 10.041 2,389 8,782 7,145 9,991 .14.091 15,950 14,594 12,792 15.118 112,919 NE 12.06/

3,699 6,296 9,041 6,378 13.580 19,159 16,745 22,731 21,900 128,864 ENE 9.335 3,232 4,964 5,301 4,316 19,409 16.516 16,463 24,353 22,328 134,041 E 7.159 3,382 14.082 12.465 63,939 15.088 17,222 19,994 12,672 167,002 ESE 2.563 5.595 4,232 2,719 17.120 17,140 16,319 19,666 18,241 18,211 9,927 131,098 SE 7.523 1,679 3,685 6,098 10.100 14.492 21,466 12.312 11,862 13,044 10,022 104.760 ya SSE 5 1,346 1,797 5.940 2.969 2,229 5.673 9,019 8,323 13,122 16.497 66.915 837 1,685 6,718 9,083 4,526 17,293 10,880 8,284 10,637 14.278 84,221 SSW 2,167 5,119 15,565 15.129 11.062 14,925 7,001 9.529 11,322 93.219 SW 1.400 1,288 3,018 2.723 14.483 9.903 7,661 31,354 53,895 128,980 WSW 1.561 3.094 1,632 3,658 3,057 898 838 2,498 8,374 11,035 32,199 41,631 105,820 W

1,301 3,296 5,159 3,432 1,401 7,797 7. 951 6,477 10,379 14.358 61,551 WMW 1,150 5,720 7.371 6,565 9,288 7,062 9.984 13,974 69,601 NW 2.990 5.497 3,363 5.540 7,463 7.956 10.381 15.148 25,452 85,781 N !W 963 4.383 5.132 Total 31,141 64.886 97,172 129,896 124,957 295,273 192.917 182,196 268,078 321,412 1,707,928 Total within 50 miles = 1,707,928 s

l 60 FIGURE 1. REGIONAL MAP FOR KING AVENUE AND WEST JEFFERSON SITES t eTy y Memn O\.- )

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FIGURE 12.1980 POPULATION WITHIN 80 km OF THE WEST JEFFERSON SITE E

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$8.000 1.000 804 ***

b CLARK' **"*"* O*ON -

esonagf'ew j FRANKUN 8.700 % - 2.000 7s0 2 o PERRY MONTGOMERY MAO! SON . FAIRFI LD -

0eyton 9 145.000 31.0M 1.000

_ _2.300 Q750 300 ,,,,,,

x. i. FAY'ETTE PICKAWAY f6f]

4,4oo 2.200 2.300 40 800 i 2.000 y CirclewsNe @ Logan  !

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$ Hillsboro 640 km 1.731570 HIGHLAND LEGEND e =.,cw., se ac 4, w w=oa s4 O is 32 Scace am e

l 72 i

FIGURE 13.1980 POPULATION WITHIN 16 km OF THE WEST JEFFERSON SITE I

CUMULAnys POPULATION TOTALS:

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GiB **a

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APPENDIX t

! I i

I 6

APPENDIX ADDITIVE LEVELS DUE TO RADIONUCLIOE MIXTURE The " Requirements for Radiation Protection" (DOE Order 5480.1, Chapter XI) 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 sum of the ratios of the concentrations of radionuclides to tne1r 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 A1C Plutonium-239 5.46 x ,10-2 Cobalt-60 3,30 x 10-5 Cesium-134 1.74 x 10-6 Lead-212 2.31 x 10-6 Cesium-137 1.87 x 10-5 Strontium-90 7.22 x 10-9 Ceri um-144 6.52 x 10-6 Antimony-125 2.38 x 10-6 Uranium-235 2.97 x 10-4 Krypton-85 7.78 x 10-2 Sum 7.81 x 10-2

A-2 West Jefferson Site Radionuclide Radionuclide Concentration RCG Water Lead-212 1.37 x 10-4 Radium-228 3.97 x 10-2 Radium-226 3.00 x 10-3 Strontium-90 4.07 x 10-3 Iodine-129 5.38 x 10-2 Plutonium-238 4.00 x 10-6 Plutonium-239 1.20 x 10-5 Cerium-141 2.42 x 10-5 Sum 1.01 x 10-1 f

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; there-fore, these nuclides are not considered as part of the mixture.

APPLICABLE STANDARDS Radioactive Standards Ir. c formance with Federal Radiation Council (FRC) guidelines and 00E

- Order 5480.1 Chapter XI, " Standards for Radiation Protection," site bouncary concentrations are compared with RCG's established for un-controlled areas.

Uncontrolled Area (Site Boundary)

& Concentration, uti g Plutonium-239 6 x 10-14 Krypton-85 3 x 10-7 Cobalt-60 3 x 10-10 Cesium-137 5 x 10-10

p.

A-3 Uncontrolled Area (Site Boundary)

Air,. Concentration, uCf/ml Cesium-134 4 x 10-to Lead-212 6 x 10-10 Cerium-144 2 x 10-10 <

Strontium-90 3 x 10-11 Uraniun-235 4 x 10-12 Antimony-125 9 x 10-9 Water Iodine-129 6 x 10-8 Radium-226 3 x 10-8 Radium-228 3 x 10-8 Plutonium-238 5 x 10-6 Plu tonium-239 5 x 10-6 Strontium-90 3 x 10-7 Lead-212 2 x 10-5 Cerium-141- 9 x 10-5 Mixture DOE Order 5480.1, 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.

l A-4 Grass and Food Crops There are no guidelines established for radionuclides in grass and food crops.

Soil and Sediment i

There are no guidelines estabitshed for radionuclides in soil and sediment. The Environmental Protection Agency's radiation protection requirements for exposures to transuranium elements in the environment necessitates doses to the critical fraction of the unrestricted population 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.

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

l

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-S A-5 e

EXTERNAL DISTRIBUTION LIST This report is subnitted to the Director, Contracts Management Office U.S.

00E. In addition, the following persons, some of whom are not a part of the DOE complex, are recipients:

Madison County Health Department Tom Alexander Sanitation Engineer Madison County London, Ohio 43140 John C. Starr, M.D.

Health Commissioner London, Ohio 43140 John P. Overturf County Commissioner London, Ohio 43140 Other County and City Health Departments William C. Myers-Health Commissioner City of Columbus State of Ohio Robert M. Quilitn Radiological Health Frogram Director -

Ohio Department of Health P.O. Box 118

'246 N. High Street Columbus. Ohio 43215 Dr. James McAvoy Director Ohio EPA Ernest C. Neal, Chief Distract Operations Ohio EPA-Ohio Power Siting Commission

t A-6

- State of Ohio (Continued)

Office of Assistant Administration for Public Information Charles Taylor 0ffice 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 EPA Donald E. Day, P.E.

Chief Division.of Land Pollution Control Federal EPA W. 0. Rowe Deputy Assistant Administrator for Radiation Programs Office of Radiation Programs -

Surveillance and Inspection Division U.S. EPA

- Gilbert Gigliotte, Ofrector Technical Information 5

Mr. David Kee, Director Air and Hazardous Materials Division Outside Laboratory Samuel I. Baker Senior Environmental Protection Officer Fermi National Accelerator Laboratory P.O. Bcx 500 Batavia, Illinois 60510 ,

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Outside Laboratory (Continued)

Jack P. Corley, C.H.P.

Staff Engineer Environmental Evaluations Section Battelle Pacific Northwest Laborateries Battelle Boulevard Richland, Washington 99352

j OBallelle Columbus Laboratories 505 King Avenue Columbus, Ohio 43201 Telephone (614) 424-6424 Teles 24-5454 May 29,1984 1

Mr. Darrell G. Eisenhut Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Eisenhut:

Re: e Docket No. 50 Facility License R Retired Facility (BRR) -

Battelle Research Reactor Building JN-3 e Facility Report dated February 21, 1984 In the BRR Retired Facility Report to you dated February 21, 1984, Environ mental Survey Section, it was pointed out that the annual Environmental Monitoring Report was not complete and that a copy would be forwarded to you when complete.

The report has since been completed and a copy is enclosed for your information.

If you require additional information please call or write.

Sincerely, Y Y-Donald A. McKown

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DAM:bm

Enclosure:

Environmental Monitoring Report.

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Battelle l Columbus Laboratories

> 505 King Avenue Columbus, Ohio 43201 l Telephone (614) 424-6424 i

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