ML20010F713

Environ Rept for CY80 on Radiological & Nonradiological Parameters to Us Doe,Chicago Operations Ofc.

ML20010F713
Person / Time
Site:	Battelle Memorial Institute
Issue date:	12/30/1980
From:	Robert Evans, Heinlein J Battelle Memorial Institute, COLUMBUS LABORATORIES
To:
Shared Package
ML20010F712	List: ML20010F711 ML20010F713
References
NUDOCS 8109110227
Download: ML20010F713 (64)

Text

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I ENVIR101 ENTAL REPORT FOR CALENDAR YEAR 1980 l

on RADIOLOGICAL AND NONRADIOLOGICAL PARAMETERS to UNITED STATES DEPARTMENT OF ENERGY CHICAGO OPERATIONS OFFICE Prepared by R. G. Evans and J. C. Heinlen Environmental Health Physics Contributors:

M. D. Musick, Facilities Engineering and Operation Section D. G. Baker, Environmental Health Physics J. E. Wissinger and E. R. Swindall, Operational Health Physics J. D. Yesso, R. H. Snider and J. Justus, Radiochemistry Facility BATTELLE Columbus Laboratories 505 King Avenue Columbus, Ohio 43201 8109110227 810G11 PDR ADOCK 05000006 PDR R

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APPROVAL LIST I

Approved by hb@b h Section Mahager Nuclear Materials Technology

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" Assistant Group Manager West Jefferson Nuclear Services Approved by h9M" Pr&jects Administrator l

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TABLE OF CONTENTS Page I FOREWARD . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

SUM'iARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Site Location . . . . . . . . . . . . . . . . . . . . . . . . . . 3 L -.

King Avenue Site. 3 l . . . . . . . . . . . . . . . . . . . . . . .

Nuclear Sciences Area (West Jefferson Site) . . . . . . . . . . . 3 ENVIRONMENTAL MONITORING . . . . . . . . . . . . . . . . . . . . . . . 10 West Jefferson Site . . . . . . . . . . . . . . . . . . . . . . . 10 Air Radioactive. . . . . . . . . . . . . . . . . . . . . . . 10 Water Radioactive. . . . . . . . . . . . . . . . . . . . . . 13 Water Nonradioactive . . . . . . . . . . . . . . . . . . . . 14 Grass and Food Crops Radioactive . . . . . . . . . . . . . . 19 Sediment Radioactive . . . . . . . . . . . . . . . . . . . . 19 Soil Radioactive . . . . . . . . . . . . . . . . . . . . . . 19 Fish Radioactive . . . . . . . . . . . . . . . . . . . . . 20 Background Radiation Levels. . . . . . . . . . . . . . . . . 20 King Avenue Site. . . . . . . . . . . . . . . . . . . . . . . . . 20 Water Radioactive. . . . . . . . . . . . . . . . . . . . . . 20 I EVALUATION OF DOSE TO THE PUBLIC . . . . . . . . . . . . . . . . . . . 42 i Estin'ated Radiation Doses to the Public from Emissions from the Battelle West Jefferson Site During CY 1980. . . . . . . 42 Radioactive Emissions from the West Jefferson Site for 1980 . . . 42 Atmospheric Discharges . . . . . . . . . . . . . . . . . . . 42 Liquid Discharges. . . . . . . . . . . . . . . . . . . . . . 42 Estimated Annt;al Radiation Dose to the Public f rom Atmospheric Discharges. . . . . . . . . . . . . . . . . . . . . . 43 I

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TABLE OF CONTEtiTS (Continued)

Calculation of Atmospheric Dispersion Parameters . . . . . .

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Calculation of Individual and Population Group Doses . . . .

43 Calculation of the 50-Mile Integrated Population Annual B Dose . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 g Estimated Annual Radiation Dose to the Public from Liquid Discharges. . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 Radiation Dose from Swimming (External Whole Body) . . . . .

46 Radiation Dose Due to Boating and Water Skiing . . . . . . .

46 Radiation Dose from Drinking Water . . . . . . . . . . . . .

46 Radiation Dose from Eating Fish. . . . . . . . . . . . . . . 47 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49

. . . . . . . . . . . . . . . . . . . . . . . . . . 50 QUALITY ASSURANCE.

APPENDIX 51 ADDITIVE LEVELS DUE TO RADIONUCLIDE MIXTURE. . . . . . . . . . . . . .

52 West Jefferson Site . . . . . . . . . . . . . . . . . . . . . . .

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'..M.ICABLE STANDARDS . . . . . . . . . . . . . . . . . . . . . . . . .

52 Radioactive Standards . . . . . . . . . . . . . . . . . . . . . .

Uncontrolled Area (Site Boundary) . . . . . . . . . . . . . . . . 52 53 Air. . . . . . . . . . . . . . . . . . . . . . . . . . . . .

53 Water. . . . . . . . . . . . . . . . . . . . . . . . . . . .

53 Mixture . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Grass and Food Crops . . . . . . . . . . . . . . . . . . . . 54 54 Soil and Sediment. . . . . . . . . . . . . . . . . . . . . .

54 Fish . . . . . . . . . . . . . . . . . . . . . . . . . . . .

54 Nonradioactive Standards (Water) . . . . . . . . . . . . . .

54 External Radiation - General Public. . . . . . . . . . . . .

55 EXTERNAL DISTRIBUTION LIST . . . . . . . . . . . . . . . . . . . . . .

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LTST OF TABLES I

Page Table 1. Population Distribution Within 10-Mile Radius from Site . . . . . . . . . . . . . . . . . . . . . . . . . 7 Table 2. Summary of Atmespheric Radioactive Emissions -

Weat Jefferson Site . . . . . . . . . . . . . . . . . . . . 12 Table 3. Gamma Emitting Radionuclides Identified in the 16 JN-1 (Hot Cell Stack Particulate Emissions) . . . . . . . .

Table 4. Summary of Liquid Radioactive Emissions - West Jefferson Site (Measure of Effluent from Sanitary I Sewerage System into Big Darby Creek - Figure 4, Designation 010). . . . . . . . . . . . . . . . . . . . . . 18 Table 5. Nonradiological Sampling for West Jefferson Site January 1, 1980, to December 31, 1980 . . . . . . . . . . .

22 Table 6. Summary of Grass Analyses . . . . . . . . . . . . . . . . . 23 Table 7. Summary of Food Crop Analyses . . . . . . . . . . . . . . .

24 Table 8. Summary of Silt Analyses. . . . . . . . . . . . . . . . . .

25 Summary of Soil Core Analyses . 26 Table 9. . . . . . . . . . . . . . .

Table 10. Summary of Gamma Isotopic Analysis of Soil Core I Samples . . . . . . . . . . . . . . . . . . . . . . . . . .

27 28 Table 11. Summary of Fish Analyses. . . . . . . . . . . . . . . . . .

Table 12. External Background Radiation Levels Within 3/4 Mile Radius - West Jefferson Site . . . . . . . . . . . . . 31 I Table 13. External Background Radiation at Perimeter Security 32 Fence - West Jefferson Site . . . . . . . . . . . . . . . .

I Table 14. Concentration of Radioactivity in Liquid Discharges 33 to Columbus Municipal Sanitary Sewerage System. . . . . . .

Summary of Site Boundary Air Sample Analyses. 34 Table 15. . . . . . . .

Radionuclide Composition of BCL Effluents for CY 1980 . 40 Table 16. . .

Table 17. Summary of Maximum Radiation Dose to an Individual I and the Nearest Population Group (Town of West Jefferson) from Atmospheric Emissions . . . . . . . . . . .

44 Estimated Integrated 30-Mile Population Doses . 45 Table 18. . . . . . .

Table 19. Estimated Radiation Dese to a Swimmer (External 46 Whole Body) . . . . . . . . . . . . . . . . . . . . . . . .

Table 20. Estimated Radiation Doses from Eating Fish Caught in Big I Darby Creek Near the Battelle West Jefferson Site . . . . .

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I LIST OF FIGURE Page Figure 1. Regional Map for King Avenue and West Jefferson Sites. . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Figure 2. Local Vicinity Map of King Avenue Site . . . . . . . . . . 5 Figure 3. Local Vicinity Map of Nuclear Sciences Area West Jefferson Site. . . . . . . . . . . . . . . . . . . . 6 Figure 4. Nuclear Sciences Area West Jefferson Site. . . . . . . . . 11 Figure 5. Map of Grass, Foodcrop and Soil Sampling Locations . . . . 21 Figure 6. Map of Site Boundary Air Sampling Locations and Battelle Lake and Darby Creek Water Sampling Locations . . 29 Figure 7. Battelle's Columbus Laboratories King Avenue Site. . . . . 30 Figure 8. Map of TLD Locations within 3/4 Mile Radius of the Nuclear Sciences Area. . . . . . . . . . . . . . . . . . . 35 Figure 9. Map of TLD Locations at the Perimeter Security Fence . . . 36 Figure 10. Map of Columbus and Vicinity Showing Off Site Air Sampling Locations . . . . . . . . . . . . . . . . . . 37 Figure 11. 1980 Wind Rose Pattern for West Jef ferson Site . . . . . . 38 Figure 12. 1970 Population Within 50 Miles of the West Jefferson Site . . . . . . . . . . . . . . . . . . . . . . 39 I

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FOREWORD 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-I logical data were compiled by the environmental piotection representative of the Facilities' Engineering and Operation Section.

I The radioanalyses of environmental air and water samples for gross radioactivity and gamma isotopic determinations were performed by the BCL Section 585, West Jef ferson, radiochemistry f acility. '

I 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.

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

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I I SUM >iARY I Environmental data collected during CY-1980 show continued compliance I by Battelle Columbus Laboratories with all applicable state and federal regulations.

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

I In general, off-site levels of radionuclides attributable to the West Jef ferson nuclear operation were indistinguishable f rom background levels.

The data are summarized as follows.

West Jef ferson nt: lear operations during 1980 caused no distinguishable impact on concentratio w of airborne I radionuclides or on external radiation doses measured adjacent to and at distances up to 3/4 mile from the nuclear site. (Sec page 16 Table 3 and page 31 Table 12).

Radionuclides observed in food crop, grass, creek bottom sediment, and soil samples were all attributed to either atmospheric nuclear tests or natural sources. (See pages 23-28, I Tables 6,7,8,9,10 and 11).

I Low level concentrations of a few radionuclides released to Darby Creek from the West Jefferson nuclear site were less than 3% of the most restrictive manual chapter guide for an individual radionuclide released to an unrestricted I area. Concentrations observed at down-stream sampling locations were indistinguishable from background levels.

(See page 18 Table 4.).

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

(the maximum individual is a hypothetical person situated as to receive the These dose calculations take into I maximum radAation exposure possible.)

account both the measurable Icvels of environmental contaminates and the impact of radionuclides known to have been released but not found in I detectable concentrations during the years environmental sampling program.

The doses are summarized as follows:

I The whole body dose to the maximum individual during CY-1980 was calculated to be less than 8 mrem. This estimate includes I

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I contributions f rom airborne and aquatic recreation pathways. I The maximum annual dose to a single organ received from all E pathways was 40 mren to the skin. These doses can be compared with the standards of Manual Chapter 0524 of 500/ l mrem /yr for the whole body and 1500 mrem /yr for organs g other than the gonads and the bone marrow. (See pages 40-46, g Tables 16-19)

Airborne emissions from the West Jefferson nuclear site resulted in an annual whole body dose to the population within 80-km (50 mile) radius of the nuclear site of 3 about 0.50 person-rem. Liquid effluents during 1980 con- E tributed very little (about 6.7 x 10-4 person-rem) to the total population dose. This estimate may be compared with the approximate 2.1 x 105 person rem /yr received annually E g

f rom natural background radiation. (See page 48 Table 20).

The maximum " fence-post" exposure rate for 1980, 0.02 mrem /hr ,

occurred just outside the security fence on the east side o f the JN-1 Hot Cell Facility. Radiation from the Hot Cell g radioactive waste handling facilities was primarily responsible I for the slight increase in background radiation levels.

(See page 31 Table 12).

Releases of low level concentrations of radioactivity to the Columbus municipal sewerage system from the Building g 3 (U-235 Processing Facility) were less than 8% of the g most restricted Manual Chapter guides for discharges of mixtures into sanitary sewerage systems. (See page 33 Table 14).

The 50 year dose commitment computations for the maximum g individual and the 80-km (50 mile) population are being g prepared by Environmental Health Physics and will be forwarded under separate cover as an addendum to the g 1980 environmental report. These modes of exposure are g being considered in the calculations of the 50 year dose commitment; (1) chronic inhalation of a radioactive mixture g using an atmospheric diffusion model, (2) chronic ingestion g of a radioactive mixture through terrestrial and (3) aquatic pathways.

Discharges of sanitary water 'from ti.e West Jef ferson nuclear site into Darby Creek under the National Pollution Discharge Elimination System (NPDES) g permit were all within the parameter limits specified in the permit.

(See page 22 Table 5) 5 I

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

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

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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 res' tit of both I contract and license activities.

King Avenue Site A local vicinity map of the King Avenue Site is shown in Figure 2. The I U-235 Processing Facility, located on the first floor of Building 3, is the nuclear materials management point for all transactions involving nuclear material at the King Avenue Site. Building 3 also houses the I Melting Facility, first floor south end, and the Power Metallurgy Laboratory, basement floor at the north end of the building. These are the only other areas in Building 3 utilizing contract material. Activities I involving contract and license materials were very limited during 1980, therefore, effluent monitoring at Building 3 was limited to liquid discharges to the Columbus municipal sewerage system.

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

I Nuclear Science Area (West Jefferson Site)

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

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

I These facilities, along with the decommissioned Research Peactor and the JN-4 Plutonium Laboratory which is being decontaminated a e located within a 10-acra fenced security area.

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

(See Table 1.)

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I FIGURE 1. REGIONAL MAP FOR KING AVENUE AND WEST JEFFERSON SITES 1

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I Operations at the Nuclear Sciences Area include various activities such as irradiated reactor fuel element studies conducted at the JN-1 Hot Cell I Facility and the materials accountability and storage operations conducted s. Lhe JN-2 Vault Facility.

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

Distance Radius Population I 1,500 feet 2,500 feet 0

0 I 1 mile 2 miles 5 miles 682 3,000 10,000 10 miles 100,000 I There are 18 industries located within the 10-mile radius. Of these, there are only four which employ more than 100 people. These are White-I Westinghouse Electric Corporation, General Motors, Janitrol Aircraft, and Capitol Mfg. Company. Each of these is located at least 8 miles from the facility. Closest to the site are three small industries within West I Jefferson which individually emnloy less than 60 people. The primary agricultural activity in the area is raising field crops such as corn and soybeans. Approximately 10% of the land area in agricultural use is devoted to pasturing beef and dairy herds.

Puring the last 13 years, two major highways have been completed near the I I'est Jef ferson Site, I-70 and I-270. The j unction of these highways, which occurs near the eastern edge of the 10-mile perimeter around the Nuclear Science Area, has proven to be a popular area for industrial I growth. It is estimated that the industrial population has shown an increase equivalent to that of the general population in this area, two and one-half times the 10-mile population distribution for 1970.

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Most of the growth has taken place near the outer limits of Columbus; I however, the larger employers , e. g. , General Motors and White-Westinghouse ,

have actually decreased their numbcr of employees.

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

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

It is too shallow for boating and is not used as a source for drinking water. The annual average flow is 3.28 x 10 11 liters. Treated sanitary and laboratory waste water f rom the West Jefferson Site is discharged into the creek. The total measured volume during CY-1980 was 1.38 x 106 liters.

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

Weather conditions in the area are moderate. The average annual precipita-tion is approximately 96.5 cm (38.0 in.). Winds predominate out of the south or west except during the summer months when a high frequency is observed out of the southwest. The average annual wind speed is about 18.5 km (11.5 miles) per hour.

The impact of BCL operations on the health and safety of employees and the public is evaluated routinely at BCL by an environmental monitoring program which has been in existence since 1955. The basic objective of the Environmental Monitoring Program is to evaluate the effectiveness of the waste management program in maintaining the concentrations of radioactive and nonradioactive wastes so that effluent levels are main-tained as low as practicable and well within applicable standards. All effluents involving polluting materials are contained within the operating facilities to the extent possible and are disposed of as packaged wastes by authorized services. Any releases of gaseous and liquid wastes to the environment are carefully controlled and dispersed to ensure that concen-trations are as low as practical within recommended standards. Radionuclides l in particulate form are removed from exhaust stack effluens by the use W of high-efficiency particulate air (HEPA) filters. The air effluents are filtered first at the points of operations, i.e., glove boxes , hoods , l test cells, and finally at the stack release point by one or two banks 5 of HEPA filters in series. Solid radioactive wastes are packaged and shipped of f site for burial at approved burial sites. Radioactive gases l present in fuel pins under examination at .he Hot Cell facility are 5 drawn off and absorbed for subsequent disposal with solid wastes. The residual gases trapped in the fuel matrix or otherwise released are monitored l continuously by effluent monitors including a system for iodine-131 5 detection and diversion to a charcoal bed if warranted. During 1978, extensive modification of the Hot Cell facility exhaust ventilation system l was made in order to Improve filtration of particulate matter in W stack emissions.

A new sanitary sewerage system, which is operated in accordance with State of Ohio regulations, handles all sanitary sewage generated on the West Jefferson Site. The liquids are first treated in a 2500-gallon septic l tank and then released to a contained 2160 sq-ft sand and gravel filter bed. 5 From the filter bed the effluent goes to a chlorinating system prior to release to Big Darby Creek.

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9 I As part of the monitoring regimen of the program, water, grass, fish, food crops, seditrent , and soil samples are collected routinely f rom the environment I at distances up to 8 km (5 miles) from the West Jef ferson Site boundaries.

These samples are analyzed for the specific radionuclides handled at the I

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

The results for the analyses for calendar year 1980 are provided in this report. Error limits, wl'en given, reflect the counting error in the data at the 957. confidence level.

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I ENVIRONMENTAL MONITORING West Jefferson Site Air Radioactive In-stack air samplers continuously monitor the exhaust stack effluent release from each facility to assess the effectiveness of systems con-trolling airborne emissions. Ten continuous stack monitors ensure 3 detection of any inadvertent release of radioactive materials and E provide data for the prompt assessment of the environmental impact, if any. (See Figure 4.) Particulate samples of the effluent are g collected from each exhaust stack. The particulate samples are collected 3',

on two types of filter paper, GVB-60 and Type E glass fiber. The air is sampled at an average rate of 2.8 x 10 4 cm3/ min. The filters are changed weekly, which represents average sample volume of 285.5 m3, Analyses are performed on a weekly basis for plutonium-239 for stacks 3 006 through 009, gross alpha for stacks 001 through 004, 013, and 014, g gross beta activities for stacks 001 through 004, 013, and 014. In the plutonium-239 analysis, an isotopically pure plutonium-239 source is used B as an internal standard in an alpha pulse height analyzer. The results E reported represent total average annual concentrations at the stack and at the site boundary as calculated from stack sample data. The site g boundary concentrations, reported in Tables 1 and 2, due to the various 5 exhaust stack locations were calculated by dividing the individual stack concentration by the appropriate atmospheric dilution factor (ADF) which is obtained from the following equation, 10 8172 x 10 Stcck vol/yr in liters.

The annual atmospheric dispersion parameters were calculated using the Air Quality Display Model computer program (See Reference 7, Page 49 ).

At the site boundary the weighted average concentration of plutonium-239 g emitted from stacks 006 through 009 (Table 2) was less than 0.011% of the l RCG value listed for soluble material for uncontrolled areas. The RCG value for soluble plutonium-239 is applied since the solubility of the g material is not known even through there is e"ery reason to assume the g material is the oxide and thus relatively insoluble. For averaging purposes, samples below the minimum detection limit are assumed to be g the value of the limit. All particulate filters are analyzed after a 5 minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> decay to reduce the contribution of short-lived radioactivity.

The weighted average concentration of the alpha and beta mixture, emitted from stacks 001 throug 004, 0013, and 014 was less than 0.17%

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

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003-JN-1 HOT CELL (CONTROL ARE A) EXHAUST STACK 004-JN-1 HOT CELL (LIO WASTE EVAP) EXHAUST STACK

\ d 9

! 013-JN-1 HOT CELL IBASEMENT) EXHAUST STACK 014-JN-1 HOT CELL (MECH T C ) EXHAUST STACK SE PTIC OO6-JN-2 VAULT EXHAUST STACK TANK /

A

/

007-JN-4 OLD PLUTONIUM LAB (E AST) EXHAUST STACK ' 010 4 008-JN-4 OLD PLUTONIUfA LAB (WEST) EXHAUST STACK

/

009-JN 4 NEW PLUTONIUM LAB EXHAUST STACK FILTE R f g 010-WEST JEFFERSON SITE FILTER BED BED / N ,

011-JN-4 STORM SEWER Sediment Samphng Locations O 50 100 A-20 Y ARDS ABOVE OUTF ALL '

i B-20 YARDS BELOW OUTFALL SCALE. FEET C-STORM SEWER OUTFALL B

e TABLE 2.

SUMMARY

OF ATMOSPHERIC RADIOACTIVE EMISSIONS - WEST JEFFERSON SITE 1 CY-1980 Stack Average Concentrations 10-2 gg Volume Site Percentage of 0 "E" " "

• Stack Stack 10 Activity _""g "#7 )

Species Locations Samples liters /yr pCi/yr 10 pCi/ml 10_ pCi/ml 10_ pCi/ml 10 pCi/mi Boundary Gross a 001 53 3.20 0.02 0.007 <MDL-1.58 0.06 0.23 53 3.20 1.44 <MDL-42.80 17.62

8. %

Gross S 001 0.004 4.50 Gross a 002 53 11.83 0.01 0.007 <MDL-0.08 0.01 0.12 53 11.83 4.87 0.004 <MDL-95.60 59.79 29.86 Gross S 002 4.13 i

Gross a G03 53 3.67 0.004 0.007 < MDL-0. 0 9 0.01 0.04 0.09 0.004 0.57 Gross B 003 53 3.67 <MDL-6.31 0.24 1.08 6

Gro s s a 004 53 1.46 0.008 0.007 < MDL-0.11 0.05 0.09 Gross 6 004 53 1.46 0.12 0.004 <MDL-8.92 0.62 1.46 Gross a 013 53 1.12 0.005 0.007 <MDL-0.67 0.04 0.05

.31 Gross 8 013 53 1.12 1.19 0.004 <MDL-250.00 10.62 14.55 Gross a 014 53 2.04 0.002 0.007 <MDL-0.06 0.01 0.02 0.50 Gross 8 014 53 2.04 0.08 0.004 <MDL-6.98 0.39 0.97 ~

w 131 7 001 12- 3.20 0.17 0.01 <MDL-11.10 0.53 2.07 0.0002 i 131 002 12 11.83 0.04 0.01 < MDL-0. 2 6 0.035 0.51 0.00005 7

239 p 006 51 0.38 0.009 0.01 <MDL-0.79 0.23 0.11 0.18 239 p 007 51 4.43 0.12 0.01 <MDL-4.07 0.27 1.46 0.24 239 p 008 51 4.43 0.13 0.01 <MDL-638 0.29 1.57 0.24 239 p 009 51 10.63 0.47 0.01 <MDL-6.38 0.44 5.72 0.95 MDL, Range, Stack, Site Boundary, Activity,

-6 -6 -6 Ci/yr 10 uC1/ml 10 Ci/mi 10 u"i/ml 10' pCi/ml j 85 001 (c) 3.17 59.70 0 . 30 <MDL-1050.00 1.88 0.073 24.35 Kr 85 002 (c) 11.71 268.92 0.30 <MDL-22900.00 2.30 0. 329 109.69 Kr (a) Site boundary concentrations calculated from stack concentration data using annual atmospheric dispersion parameters calculated using the Air Quality Display Model (see Reference 7 page ) computer program.

(b) RCC - for mixed alpha and beta activity, 2 x 10-14 pCi/ml; 85Kr 3 x 10-7 pCi/ml; 1311 1 x 10 -10 C1/ml; 239 Pu 6 x 10-14 pCi/ml -

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

t

I -

13 Based on gamma ray analyses of in-line synt m charcoal cartridges installed I in Su:cks 001 and 002, the weighted average concentration of iodine-131 emitted was Ices than 3 x ltr5% of the RCG val e at the site boundary.

5 The air is monitored at a rate of 1.3 x 10 cm / min. This represents a weekly average sample volume of 1.3 x 10 3.

The weighted average concentration of krypton-85 released f ron Stack 001, and 002 was 1.3% of the RCG value at the site boundary. The concentrations were calculated by using strip chart recorder data from the gaseous monitors on exhaust Stacks 001 and 002. The rr.sults are summarized in Tabic 2. (There is a discussion of RCG's in the appendix of this report.)

Identification of radionuclides in the JN-1 stack particulate emissions f rom Stacks 001 through 004, 013, and 014 was made by monthly owna ray analysis of weekly stack air sample filters composited over a 9-week period.

Gamma ray analyses were performed using an intrinsic germanium detector I coupled to a Canberry Model 8180 multi-channel analyzer. Tha concentrations of the radionur11 des identified were all less than 4.9 x 10-7% of the applicable RCG values at the site boundary. (See Tabic 3.)

I Supplementary air sampling was performed at four site boundary locations during 1980. (See Figure 6.) These air samples were collected continuously and analyzed on a weekly basis for mixed alpha and beta actis! ties.

The average concentrations of activity at each of the site bouulary locations were less than the average mixed alpha and beta activities found on background samples obtained from 6 off site air sampling locations surveyed weekly at distances varying 5 to 44 miles from the Nuclear Sciences Area, (See Figure 10 and Table 15.)

Water Radioactive Sampling of all liquid effluents to Big Carby Creek, generated at the Nuclear Sciences Area, is performed routinely on a weekly basis. This effluent consisted of the liquid discharge from a conventional sanitary sewerage system incorporating a 2,500-gallon septic tank and a container' 2,160-ft filter bed. (See Figure 4.) The effluent samples are routinely analyzed specifically for plutonium-238, iodine-129, strontium-90, I radium-226, and radium-228 as well as for gross alpha and beta activity in suspuded and dissolved f ractions. Any sample exceeding 3 x 10-8 pCi/m1*

receives a supplemet.tary gamma isotopic (GeLi) analysis and/or an alpha spectrometric analysis as necessary.

The weekly samples are held and individually analyzed at the end of each month. The concentrations of gross alpha and gross beta activit.y in suspended and dissolved f ractions as wel! as the concentrations of specific radionuclides identified in the sample are summarized in Table 4. In most cases t he activity in the samples is due to a mixture of nuclides. The

'gg

• RCG value for unidentified radionuclides in unknown concentrations released to an uncontrolled area, DOE Appendix 0524. (2)

I

! I I

I 14 average concentration of the mixture was 1.92% of the RCG. The average concentrations of identified radionuclides in the mixture were 0.83% of the RCG for iodine-129, 0.001% of the RCG for plutonium-238 and plutonium-239, 2.33% of the RCG for strontium-90, 0.034% of the RCG for cesium-137, 2.30% of the RCG for radium-226, 1.67% of the RCG for radium-228, 0.12%

for cesium-144 and 0.004% of the RCG for uranium-235.

Supplementary water samples were collected weekly 20 yards above and 20 yards below the sanitary drain outf all at Darby Creek. Weekly water samples were also collected below the Battelle Lake dam and in the drain spillway at Darby Creek. (See Figure 6.) The supplementary water samples were analyzed for l mixed alpha and beta activity. The average concentration of net8 activity in the down stream water samples were less than the RCG (3 x 10 pCi/ml) for mixed alpha and beta activity in uncontrolled areas.

Water Nonradioactive Presently, liquid effluents discharged from the West Jef ferson Facility are subject to the restrictions of our National Pollutant Discharge Elimination System (NPDES) Permit which presently is being renewed under l the Cc,nsolidated Pemits Section of the Resource Conservation and Recovery Act (RCRA). Battelle monitors and reports on a monthly basis to the Ohio Environmental Protection Agency (OEPA) and the U.S. EPA.

Table 5 includes a list of the parameters for which BCL is presently required to analyze and report. These parameters may change or be subject to modification during 1981, The data listed in Table 5 represent an average of the monthly data collected during the twelve month period commencing January 1,1980, and ending December 31, 1980, and are required under the limits or restrictions set forth in BCL's NPDES Permit. The table serves to illustrate actual performance against those limits or restrictions defined in BCL's permit.

There are two sampling locations; the North Sanitary System Sewer (Location 010) and JN-4 Storm Sewer (Location 011) which are subject to the discharge limits on the following criteria: flow rates (gal / day) have no limitations or restrictions under the NPDES permit for either locatioa; residual chlorine is applicable to the North Sanitary, the average being 0.15 mg/1, with the allowable 0.5 mg/1; pH value (S.U.) applies to both North Sanitary, average being 5.5, and JN-4, average being 7.29, based on 5 months of actual discharges, with the allowable value not less than 6.0 or greater than 9.0; fecal coliform

(#/100 ml) applies to the North Sanitary only, average 2.33 daily, with an allowable of 400 daily; total suspended solids (mg/1) applies to the North Sanitary only, average 3.59 daily, with allowable daily of 20; temperature ( F) applies to JN-4 only, average 61.6*, based on 5 months actual discharges, with allowable 90*; finally B.O.D. (5 day)

(mg/1) applicable to the North Sanitary only, average 3.03, with allowable of 20 daily.

I I

1

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

I Since the conditions of BCL's NPDES Permit were determin ed by the Ohio EPA following an extensive study of the Scioto Ri .r Basin, of which Batte11e's West Jefferson Site is a part; and discharges are I within the allowable discharge limits, the data reflect the effectiveness of BCL's waste water management.

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l 'IABLE 3. GAMMA EMITTING RADIONUCLIDES IDENTIFIED IN Tile JN-1 (IlOT LAB) STACK EMISSIONS I

l CY-1980 1

Average Concentration -6 Stack Composit e V lume Site (c)

• Stack, h ndary, Per nt of (d)

(a) Loce. bion Stack (b) 10 Activity,

,3 "E**

RCG at

, Species Figure 4 Samples liters /yr pCi/ml 10 pc /mi 10 pCi/ml 10_ pCi /ml 10 pCi /ml Site Boundary 1

Co 001 24 3.20 4.36 1.45 <MDL-7500.00 1362.50 5 3. 35 17.78 i 002 12 11.83 0.36 1.45 <MDL-95.30 30.43 4.40 1,47 003 I? 3.67 0.008 1.45 <MDL-24.70 2.18 0.10 0.03

! 004 12 1.46 0.012 1.45 <MDL-108.00 8.22 0.15 0.05

013 12 1.12 0.025 1.45 <MDL-181.00 22. 32 0.31 0.10

! 014 12 2.04 0.014 1.45 <MDL-59.90 6.86 0.17 0.06 1

235 U 001 24 3.20 0.02 0.07 <MDL-74.40 6.25 0.24 6.12 002 12 11.83 0.16 0.07 <MDL-119.00 13.52 1.96 48.93 004 E j

12 1.46 0.002 0.07 <MDL-17.40 1.37 0.02 0.61 013 12 1.12 0.003 0.07 <MDL-18.90 2.68 0.04 0.92 i

Sb 001 24 3.20 46.65 1.14 <MDL-85300.00 14578.00 570.85 6.34 i 002 12 11.83 0.09 1.14 <MDL-68.10 7.61 1.10 0.012

' 14 12 2.04 0.02 1.14 <MDL-122.00 9.80 0.24 0.003 1

} Th 002 12 11.83 1.73 0.14 <MDL-1730.00 146.24 21.17 10580.00

?

144 Ce 001 24 3.20 0.0005 0.01 <MDL-3.33 0.15 0.006 0.003 002 12 11.83 0.45 0.05 <MPL-271.00 38.22 5.53 2.77 i 003 12 3.67 0.04 0.05 <MDL-53.50 10.93 0.49 0.25 j 004 12 1.46 0.02 0.05 <FDL-137.00 12.19 0.22 0.11 l 013 12 1.12 0.00007 0.01 <MDL-0.63 0.06 0.0008 0.0004 j 014 12 2.C4 0.05 0.05 <MDL-193.00 25.88 0.65 0.32 1

4 i

t I

TABLE 3. (Continued)

-6 l Average Concentration 10 l Volume Site (c) Percent of (d) 10 " '

c on (b 10 Activity.

RCG at Species -6 pCi /ml -6 pCi /ml Figure 4 Samples liters /yr pCi/yr 10[6pCi/ml 10 10 10- pti /ml Site Boundary I 001 24 3.20 0.1/ 0.07 <M3L-1110.00 53.12 2.08 2.08 002 '2 11.83 0.04 0.07 <MDL-26.50 3.49 0.51 0.51 013 12 1.12 0.15 0.07 <MDL-1500.00 133.93 1.84 1.84 014 12 2.04 0.24 0.07 <MDL-968.00 116.18 2.90 2.90 (a) Only thgse radionuclides which contributed to critical organ doses to the maximum individual greater than 1 x 10~ rem /yr are listed. C (b) Identification of radionuclides in stack particulate emissions was by gamma ray analysis of stack particulate air filters.

(c) Site boundary concentrations calculated from stack concentration data using annual atmospheric dispersion parameters calculated using the Air Quality Display Model (see Reference 7, page 49 ) computer program.

-10 137 -10 -13 125 -9 (d) RCC: Co 3 x 10 pCi/ml; Cs 5 x 10 Ci/ml; Th 2 x 10 uCi/ml; Sb 9 x 10 pCi/ml; I -10 -11 235 -I Ce 2 x 10 Ci/ml; I 1 x 10 pCi/ml; U 4 x 10 pCi/ml.

l t

1 i __ _ __ _ _____________ ___ ______ ___ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _

i I TABLE 4.

SUMMARY

OF LIQUID RADIOACTIVE EMISSIONS - WEST JEFFERSON SITE (MEASURE OF EFFLUENT FROM l SANITARY SEWERAGE SYSTEM INTO BIG DARBY CREEK - FIGURF 4. DESIGNATION 010) D)

CY-1980 i

Average Number of Act iv it y . ' '

Percentage l -8 -8 -8 -8

Species Sample pCi/yr 10 pCi/ml 10 pCi/ml 10 pCi/ml 10 pCi/mi o f RCG Gross a 52 7.92 0.05 <MDL-6.04 0.57 10(c) 19.58

]

Gross 8 52 19.10 0.02 <MDL-9.55 38 j 90Sr 12 9.63 0.10 <MDL-1.8 0.698 30 2.33

238Pu 12 0.07 0.001 <MDL-0.02 0.005 500 0.001 239Pu 12 0.05 0.001 <MDL-0.01 0.004 500 0.0008 l

137Cs 12 9.51 0.1 <MDL-1.0 0.689 2000 0.034

{ 129I 12 0.68 0.01 <MDL-0.2 0.050 6 0.83 H I

226 12 0.95 0.004 <MDL-0.35 0.069 3 2.30 Ra 228 12 0.68 0.01 <MDL-0.30 0.050 3 1.67 Ra l

144 Ce 12 16.60 0.1 <MDL-9.43 1.200 1000 0.12 235 U

12 1.64 0.001 <MDL-1,46 0.119 3000 0.004 11 l (a) Annual average flow in Big Darby Creek = 429 cu ft/sec = 3.82 x 10 lit ers /yr. Rate at which liquid effluents l discharge = 1. 38 x 106 lite rs /y r.

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

-8 1297 , 226Ra, and l (c) RCG - Mixture of alpha and beta activity; 3 x 10 Ci ml. (If it is known that Ra j are not present, the limiting value of 1 x 10-7 pCi/ml may be used.) See Appendix.

1 l

1 4

5 1

I mmm m .

mmmme em -

Mm

I l 19 ,

I Grass and Food Crops Radioactive 1

I Grass and food crop samples are collected from the surrounding area.

The intent of this portion of the Environmental Monitoring Program is to determine whether there is uptake and concentration of radionuclides by plant or aninal life. Where possible, sampling sites are chosen at maximum deposition locations predicted by meteorlogical studies. Grass I and food crop (field corn) samples are collected at varying distances and directions within a 5-mile radius of the Nuclear Sciences Area as shown in Figure 5. Sampling locations falling into the same directional quadrant of the nuclear site are composited. The samples are analyzed for plutonium-239, plutonium-238, and strontium-90. A qualitative analysis by gamma scan (Geni) is also performed. The results of the grass and food crop analyses are summarized in Tables 6 and 7. The maximum concentration of strontium-90 detected in grass samples was 3.7 0.2 pCi/g. The average concentration af strontium-90 in field corn was 0.07 0.05 pCi/g and 'O 14 pCi/g for cesium-137. Plutonium-238 and plutonium-239 concentrationn were less than the MDL for both plutonium isotopes (0.01 pCi/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 os sanitary effluent release to Darby Creek. (See Figure 4.) The purpo. of cualecting silt samples is to estimate the inventory of certrin radio.tuclides deposited in this waterway and document for future referei.ce. The silt samples are analyzed for plutonium-239, plutonium-238, s -d strontium-90. A quantitative gc=ta isotopic (GeLi) analysis is also performed. The results of the m 'yses are summarized in Table 8. Concentrations of strontium-90 in s u samples collected above and below the effluent release point were 0.16 0.01 pCi/e and 0.18 0.01 pCi/g respectively; for plutonium-238, 0.00 0.01 pC1/g, and for plutonium-239, 0.021 0.011 pCi/g and 0.018 t 0.010 pCi/g respectively.

I Soil Radioactive I 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 ans. lysis by gamma scan (GeLi) is also performed. The results g of the analyses are summarized in Table 9. The largest concentration of ntrontium-90 in soil samples was 0.19 t 0.01 pCi/g, found in the composite soil sample collected on site as compared to an average of 0.13 0.01 pCi/g for off site soil samples. The concentration of plutonium-239 did not exceed 0.021 0.010 pCi/g and the plutonium-238 concentration was 0.00 0.01 pCi/g for all soil samples collected.

Gam a isotopic analyses of the soil samples showed en on site concentration of cesium-137 of 0.62 0.12 pCi/g and au average off site concentration of 0.54 0.13 pCi/g.

20 I

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

A quantitative gamma isotopic (GeLi) analyses are also performed.

The results of the analyses are summarized in Table 11. Levels of plutonium-238 and pluton .um-239 in the fish samples were 0.00 i 0.01 pCi/g dry weight for plutonium-238 and plutonium-239. The maximum concentration of strontium-90 i

in fish samp?cs was 0.96 0.05 pCi/g, and the average concentration of r cesium-137 was 0.44 pCi/g.

Background Radiation Levels The external radiation background les als at the West Jef ferson site are continuously monitored at 39 dosimetry stations using commercially availabic environmental TLD packets. (See Figure 8 and 9.) All TLD packets at changed and evaluated each calendar quarter. The annual exposure average at the site boundary for the 39 dosimeter stations was 014 rem or 28% of the 0.5 rea limit established for the general public. The results are summarized in Table 12 cnd 13.

King Avenue Site Water Radioactive E g

l Sampling of all liquid discharges from the Building 3 (U-235 Processing Facility) sump to the Columbus municipal sewerage system is performed on a monthly basis. (See Figure 7.) This discharge consists of the ligt.id.

i wastes from tie building laboratory drain systems. The building sump samples are nc rmally analyzed for gross cipha and gross beta activities.

l Any sample exceeding 4 x 10-7 uCi/m1* receives a gamma isotopic (GeLi) analysis and/or an alpha spectrometric analysis as necessary.

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

The concentrations of gi ass alpha and gross beta activity are summarized in Table 14. The average concentration of the mixture was less than 7.6% of the RCG. For averaging purposes, samples below the minimum detection limit are assumed to be the value of the limit.

Total releases of radioactivity during CY 1980 f rom the West Jef ferson and King Avenue sites are summarized in Table 16.

• RCG value for unidentified radionuclides in unknown concentrations released to a public sanitary sewerage system, DOE Appendix 0524.

1

I 21 I FIGURE 5. MAP OF GRASS, FOODCROP AND SOIL l SAMPLING LOCATIONS I PRICE

' HILLIARD RD 3 ea c A SClOTO DARBY CREEK RD e

HILLIARD g ), ~

te,+

g .n. g o

.nW I ,, O >

k#

2 E

3

$- ROBERTS RO I

/

g o

g C ROBE RTS QA mC m A 9 rk e

k s& KEP pg A fr RENNER RD 1 70 E9x I $p

$3 9

t .70 C

$ e FEDER RD

1. 5 I %g= gg8

, , \

m , BAtTELLE O pgNNA R R + #-

8 '

/ # en I 3g RT 40 A S

I menson 1

/ g i2 D

se 4

I$

g Gras empi s

~ a--

C & Field Com Samples I i *

{<

l 2 '

8 v A Gard a veo* tab 8'a I 5, c I '

0 1.0 20 SCP.LE: MILES I

I I

I - ___ -. -- _- - - . - -- __ _

1 1

1 i

j TABLE 5. NONRADIOLOGICAL SAMPLING FOR WEST JEFFERSON SITE January 1, 1980, to December 31, 1980 4

}

1 j Permit Requirements (e) i Discharge Limitations

, North Sanitary System Sewer (c) Loading (f) Concentration Kg/ Day Jn-4 Storm Sewer (d) K3/ Day other Units Avg. Max. Min. Avg. Avg. Max. Min. 30 Day Daily 30 Day Daily

Flow Rate (gal / day) 2 8. 35 8640 0 (b) 1170 5040 0 (b) (b)

Residual Chlorine 0.15 0.4 0 (a) (a) (a) (b) 0.5 I (mg/1) l pH Value (S.U.) 5.5 8.38 0 (b) 7.29(g) 7.43(g) 7.19(g) 6.0 to 9.0 i

l Fecal Coliform 2.33 12.0 0 (b) (a) (a) (a) 200 400 U

l (#/100 ml)

, Total Suspended 3.59 12.0 0 (b) (a) (a) (a) 0.49 0.99 10 20 i Solids (mg/1) l 1 Temperature (*F) (a) (a) (a) 61.6*(g) 70*(g) 50 * (g) 90 B.O.D. (5 day)(mg/1) 3.03 5.4 0 (b) (a) (a) (a) 0.49 0.99 10 20 I

.l ..

i (a) Sample analysis for this parameter was not required by our NPDES Permit.

j (b) No restrictions for flow under our NPDES Pemit.

! (c) Sampling site location No. 010.

I (d) Sampling site location No. 011.

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

l, (f) Flow rate 0.013 mgd.

(g) Based on 5 months activity discharge that could be analyzed.

I

!M M MM MM M M '

M M M M MM M

i 23 1

I TABLE 6.

SUMMARY

OF GRASS ANALYSES CY-1980

i II

! Location (") Number of pCi/g dry (N.

I (Direction and Distance from Nuclear Science Area)

Composite Samples 90 Sr 238 Pu 239 Pu 137 Cs North Quad 8.0 km (5.0 miles) 2 3.7 1 0.2 0.067 1 0.100 0.17 1 0.17 <0.66 l

East Quad 3.2 km (2.0 miles )

6.4 km (4.0 miles) 6 0.57 ! 0.05 0.0094 1 0.005 3 0.052 t 0.013 <1.9 8.0 km (5.0 miles)

South Quad 0.8 km (0.5 miles)

I 3.1 Icn (1.9 miles) 2 0.55 1 0.05 0.024 0.010 0.021 1 0.009 <1.8

, West Quad 4.8 km (3.0 miles)

! 2 1.2 0.1 0.0052 0.0043 0.014 ! 0.007 <2.0 l

8 8.0 km (5.0 miles )

i

! On Site - - -

2 0.81 1 0.07 0.016 1 0.007 0.011 0.006 <2.3 Note: No standards for radionuclides in grass have been established.

(a) Locations are shown in Figure 5. l (b) Minimum Detection Limit fo r Sr in grars is 0.05 pCi/g dry wt.

Minimum Detection Limit for Pu and Pu in grass is 0.004 p/Ci/g dry wt . l Minimum Detection Limit fo r Cs in grass is 0.66 pCi/g dry wt.

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24 TABLE 7. SUFBfARY OF FOOD CROP ANALYSES I

CY-1980 I'

I Location (a) Number of pCi/gdry(N.

Type (Direction and Distance Composit 90 238 239 137 of Samples from Nuclear Sciences Area) Samples Sr Pu/ Pu Cs West 0.74 kr.; (2400 feet) E 2 0.051 0.049 0.00 0.010 <0.14 3 West 3.2 km (2.0 miles)

Field Corn North-west 6.4 km (4.0 miles) 1 0.046 0.038 0.00 0.01 <0.15 3

South 2.4 km (1.5 miles) 3

- 2 0.068 z 0.042 0.00 0.01 <0.12 South 8.0 km (5.0 miles)

East 8.0 km (5.0 miles) 1 0.089 ! 0.057 0.00 t 0.01 <0.13 North-east 8.0 km (5.0 miles) 1 0.092 ! 0.072 0.00 0.01 <0.12 North 4.0 km (2. ; miles)

- 2 0.14 0.04 0.00 ! 0.01 <0.14 North 8.0 km (5.0 miles)

South-west 6.4 km (4.0 miles) 1 0.050 ! 0.034 0.00 0.01 <0.13 On Site' ----

2 0.052 0.039 0.00 0.01 <0.15 I

Note: No standards for radionuclides in food crops have been established.

(a) Locations are shown in Figure 5.

90 (b) Minimum Detection Limit for Sr in food crops is 0.04 pCi/g dry wt.

Minimum Detection Limit for Pu and Pu in food crops is 0.01 pCi/g dry wt.

Minimum Detection Limit fo r Cs in food crops is 0.12 pCi/g dry wt.

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l

)

TABLE 8. SUmiARY OF SILT ANALYSES CY-1980 l I

PCi/gdryOh.

Location ( Number 90 Figure of Samples Sr Pu Pu I A (20 yd above outfall) 2 0.16 ! 0.01 0.000 1 0.010 0.021 1 0.011 I B (20 yd below outfall) 2 0.18 ! 0.01 0.000 0.010 0.018 1 0.010 I

I Note: No standards for radionuclides in silt have been established.

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

Minimum Detection Limit for 238 Pu and 239P u in silt is 0.01 pCi/g dry wt.

I (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.

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26 l I

TABLE 9.

SUMMARY

OF SOIL CORE ANALTor.s CY-1980 l

l Location (* Number of PCi/g dry (

(Direction and Distance Composite . I 238 Pu 239 Pu 90 from the Nuclear Science Area) Sainples Sr Cs North Quad 8.0 km (5.0 miles) 1 0.000 0.010 0.020 2 0.009 0.1320.01 0.84 ! 0.12 ,

l East Quad 3.2 km (2.0 miles) l 6.4 km (4.0 miles) 6 0.000 0.010 0.016 ! 0.008 0.17 ! 0.01 0.57 0.12 1

8.0 km (5.0 miles)

South Quad 0.8 km (0.5 miles) 3.1 km (1.9 miles) 2 0.000 0.010 0.000 0.010 0.08 0.012 0.24 2 0.11 West Quad 4.8 km (3.0 miles) 8.0 km (5.0 miles) 3 0.000 0.010 0.021 ! 0.011 0.1'. ! 0.01 0.51 t 0.18 On Site --

2 0.000 0.010 0.021 ! 0.009 0.18 0.01 0.62 ! 0.12 Note: No standards fe radionuclides in soil have been establ4.shed.

The Environmental Protection Agency's proposed federal radiation protection guidance for exposures to transuranium elements in the 3 environment has recommended a reference level of 0.2 pCi/m2 for soil contamination.

5 (a) Locations are shown in Figure 5.

239 (b) Minimum Detection Limit for Pu and Pu in soil is 0.008 pCi/g dry wt.

90 Sr in soil is 0.01 pCi/g dry wt. l Minimum Detection Limit fcr 3 Minimum Detection Limit for 137Cs in soil is 0.11 pCi/g dry wt.

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I

M WM MM M M M M M M M M M M M M MM M M TABLE 10. SUFDIARY OF GAFDtA ISOTOPIC ANALYSIS OF SOIL CORE SAMPLES (a)

Location (Direction and Distance from the Nuclear Science Area)

North Quad East Quad South Quad West Quad 8.0Km (5.0 miles) 3.2Km (2.0 miles) 0.8Em (0.5 miles) 4.8Km (3.0 miles) ,

6.4Km (4.0 miles) 3.1Km (1.9 miles) 8.0Km (5.0 miles) I l

8.0Km (5.0 miles) On Site Number of l Composite 1 6 2 3 2 Samples Nuclide Average Concentration pCi/g (dry) db 40 g 10.0 1 1.0 L7 1 1.1 8.3 1 1.1 < 5. 2 11.0 1 2.0 208 1.4 1 0.3 1.8 1 0.3 1.6 1 0.3 1.6 1 0.6 1.7 1 0.3 214  ?.9 1 0.2 2.2 1 0.2 2.0 0.2 1.9 0.4 2.3 0.3 Pb 214 * * * * * * * * *

• Bi 212 1.1 0.1 1.3 0.2 1.2  ! 0.2 1.1 0.3 1.2 0.2 Pb Cs 0.84 0.12 0.57 0.12 0.24 0.11 0.51 0.18 0.36 0.12 Note: No standards for radionuclides in soil have been established.

(a) Locations are shown in Figure 5.

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

08 TL 0.3, I'Pb 0.2, 14 Bi 0.2, Pb 0.10, Cs 0.11 K 1.0,

28 I

I TABLE 11.

SUMMARY

OF FISH ANALYSES CY-1980 I

Number of pCi/gdry(N.

Period of Composite Location (,) 238 239 137 90 Collection Samples Pu/ Pu Cs Sr Darby Creek ist qtr. (c)

Battelle Lake 1st qtr. (c)

Darby Creek 2nd q:r. 1 0.0010.01 <0.22 0,96 ! 0.05 Battelle Lake 2nd qtr. 1 0.00 0.01 <0.50 0.37 0.08 Darby Creek 3rd qtr. 1 0.00 0.01 <0.40 0.41 0.04 3rd qtr. 0,00 0.01 <0.36 0.13 0.04 I

Battelle Lake 1 Darby Creek 4th qtr. 1 0.00 0.01 <0.90 0.17 0.05 Battelle Lake 4th qtr. 1 0.00 ! 0.01 <0.27 0.20 1 0.04 I

Note: No standards for radionuclides in fish have been established.

(a) Locations are shown in Figure 6.

9 l (b) Minimum Detection Limit for Sr in fish was 0.04 pCi/g dry weight, 0.2 pCi/g dry weight Cs, and 0.01 pCi/g dry weight for Pu and Pu.

(c) No fish samples were collected during the first quarter of CY-1980.

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M M M M MM M M M M M M M i

I f

FIGURE 6. MAP OF SITE BOUNDARY AIR SAMPLING LOCATIONS AND BATTELLE LAKE AND DARBY CREEK WATER SAMPLING LOCATIONS i

i 9

l I SANITARY

.g.

,e g OUTF ALL

'l

,JN 4 ',*

. - t,

' '1' N -

NUCLEAR S,CIENCES AREA Ao ..... SPILLWAY i

(WS**'e SO ** GUARDHOUSE JN-2

/ ~ h h-h h h ]

, g L_- ---,

, ^i -p:_- -:::- -:

{:;8}q}$;,

MAIN ,,,;,;,,,,,,,

l _

l !5!!!___ OAM N[![!!!!!!!!$7:M

+: : :i' ^-:

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i5k51hisi$1 BATTELLE LAKE 1-D-$ ^ f

service - :- _7:gigigi-f g _______ --____

, ,

, 2

' y i

! A , REST ROOMS AND E d j $

l JM 1  %

SHELTER HOUSE j $ ' O g

> 5 p*

i C $

$ %1 m h

i 3 w.ier S.mpi . <s.n.n. t.*.. o rdy Cre.o 2s0 soo j  ?

SCALE FEET i

FIGURE 7. BATTELLE'S COLUMBUS LABORATORIES KING AVENUE SITE b J l JL KING AVENUE F Y 3

E V

Al I 4 __.

J, PARKING { V PARKING l PARKING 10 TI _

~

)( )(

SEVENTH AVENUE

. c -

5 J'-

l t

> l 6 i

a B 4 I

> l 7C l C

E 9 I N 6 5 i

g g

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j PARKING i

_7 7{6 7 A 11 1

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) ,

g 13 dT A  :

_ e gt 006 & ~SANIT '9 $F TO COLUM8US MUNnCIPAL SEWER  % 14 30 +

PARKING

{

$ PARKING .-

LEGEND E 2 I' -

Effluent Release Point identity g e

OOS-Uraneum Processing Bldg. 3 Sewer bw r FIFTH AVENUE O 5,0 100 SCALE. FEET )f mum uma amm aus sus sus seu ese amm num nas num een uma ens uma en mme ama mus _ _ __

sas

I 31

,E TABLE 12. EXTERNAL BACKGROUND RADIATION LEVELS WITHIN 3/4-MILE 5 RADIUS - WEST JEFFERSON SITE CY-1980 I

Exposure to TLD in Rem Location and Total Distance (a) 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. for Year I

Southwest 400 ft. 0.030 < 0. 0 30 <0.030 0.040 <0.130 2400 ft. <0.030 <0.030 <0.030 0.030 <0.120 4050 ft. 0.030 <0.030 <0.030 0.030 <0.120 West 500 ft. 0.030 < 0. 0 30 <0.030 0.030 <0.120 2070 f t. 0.0 30 <0.030 <0.030 0.030 <0.120 iI Southeast I 1200 ft.

3300 ft.

<0.030

<0.030

<0.030

<0.030

< 0. 030

<0.030 0.030 0.030

<0.120

<0.120 South 1350 ft. <0.030 <0.030 <0.030 0.030 <0.120 t 1800 ft. 0. 0 30 <0.030 <0.030 0.030 < 0.120 l 3600 ft. 0.030 <0.030 <0.030 0.030 <0.120 East 1380 ft. 0.030 <0.030 <0.030 0.060 <0.150 Northeast 1200 ft. <0.030 <0.030 <0.030 0.030 <0.120 Northwest 1320 ft. 0.030 <0.030 <0.030 0.030 <0.120 North 1500 ft. 0.030 <0.030 <0.030 0.040 <0.130 I

( } Refer Figure 8. Average total for year <0.124 E

I

I 32 TABLE 13. EXTERNAL BACKGROUND RADIATION LEVELS AT I

PERIMETER SECURITY FENCE - WEST JEFFERSON SITE CY-1980 Exposure to TLD in Rem Location and Total g Distance (a) 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. for Year 5

So uthwest 100 ft. JN-3 <0. 0 30 <0.030 <0.030 0.030 <0.120 m 150 ft. JN-2 (b) <0. 0 30 <0.030 0. 0 30 ------

175 ft. JN-1 0.030 <0.030 <0.030 0.040 <0.130 West 75 ft. JN-2 0.030 <0.030 <0.030 0.030 <0.120 g 150 f t . JN-3 (b) <0.030 <0.030 0.030 ------

3 Southeast 150 ft. JN-4 0.030 0.0 30 <0.030 0.060 <0.150 m 200 ft. JN-1 0.030 < 0. 0 30 <0. 0 30 0.040 <0.130 240 ft. JN-1 0.040 <0.030 <0.030 0.060 <0.1Q0 g 250 ft. JN-1 0.030 <0.030 0.030 0.060 <0.150 E South 150 ft. JN-2 0.030 <0.030 <0.030 0.040 <0.130 360 ft. JN-1 0.030 <0.030 <0.030 0.040 <0.130 190 ft. JN-1 0.030 <0.030 <0.030 0.060 <0.150 East 150 ft. JN-4 0.040 <0.030 <0.030 0.050 <0.150 l 230 ft. JN-1 0.050 < 0. 0 30 <0.030 0.070 <0.180 5 240 ft. JN-1 0.050 0.040 <0.030 0.080 <0.200 Nort heast 150 ft. JN-4 0.030 <0.030 <0.030 0.040 <0.130 225 f t. JN-4 0.0 30 <0.030 <0.030 0.040 <0.130 g 250 ft. JN-1 0.030 <0.030 <0.030 0.060 <0.150 5-260 ft. JN-1 0.050 0.0 30 <0.040 0.070 <0.190 275 ft. JN-3 0.030 <0.030 <0.030 0.040 <0.130 Northwest 200 ft. JN-4 0.040 <0.030 <0.030 0.040 <0.140 g 250 ft. JN-3 0.030 <0.030 <0.030 0.040 <0.130 m North 150 f t . JN-4 0.030 <0.030 <0.030 0.050 <0.140 200 ft. JN-4 (b) < 0. 0 30 < 0. 0 30 0.040 300 ft.. JN-3 0.030 <0.030 < 0. 0 30 0.040 <0.130 (a) Refer Figure 9. Average total for year <0.143 (b) TLD Unit Lost.

I I

I 33 TABLE 14. CONCENTRATION OF RADIOACTIVITY IN LIQUID DISCHARGES TO COLUMBUS MUNICIPAL SANITARY SEWERAGE SYSTEM I CY-1980 I

I Concentration

^ #

I Location Number Nuclide Figure 7 of Samples Activity, pCi/yr 10

_"E**

pC1/ml 10

^[*#*E*

9 pCi/ml o #[* b)

I Gross a 005 12 1570.0 <MDL-91.20 11.89 7.53 Gross 8 005 12 834.0 <MDL-18.90 6.32 I

I -9 (a) Minimum Detection Limit (MDL) for: gross alpha: 0.9 x 10 pCi/ml; gross beta: 2.0 x 10- pCi/ml.

(b) RCG - Mixture of alpha and beta activity. 400 x 10" pCi/ml.

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34 TABLE 15. SDNARY OF SITE BOUNDARY AIR SAMPLE ANALYSES l

CY 1980 ,

Location (a) fg (b) l Direction and Distance Number '

! from Nuclear Sciences Area of Samples Cross a (c) Gross 8 (c) Sr(c) i

-15

<2.30 x 10 -14 North quadrant Station 51 <3.40 x 10 <1.0 x 10 3 (450 ft. North of JN-4 Stacks) 5

-14 East Quadrant Station 51 <3.40 x 10~ <2.30 x 10 <1.0 x 10-(400 ft. East of JN-1 Stacks)

-15 ~I' ~

I South Quadrant Station 51 <3.40 x 10 <2.30 x 10 <1.0 x 10 ,

(750 ft. South of JN-2 Stacks)

-15 ~I' l West Quadrant Station 51 <3.40 x 10 < 2. 30 x 10 <l.0 x 10' I

(400 ft. West of JN-2 Stacks) E g,.

l (a) Locations are shown in Figure 6.

(b) Minimum Detection Limit for gross a is - x 10' pCi/m1, ,'

for gress 8 4 x 10~I7 LCi/ml, and 1 x 10-16 pCi/ml for f, . .

(c) The values shown for gross a , gross 8, and Sr, indicate average background concentrations found at of f-site air monitoring stations. Average site boundary ,

concentrations were all less than of f-site background levels.

l I: 1 l'

1 I 1

l I T I!

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I 35 I

FIGURE 8. MAP OF TLD LOCATIONS WITHIN M MILE RADIUS l OF THE NUCLEAR SCIENCES AREA E

%+p%

14 E "  %

s I -

L I ~4

%o

/..+ed MADISON CO F RANKLIN CO

.n.

G *,

g p., .p:Q(.:f M]D 'o 2#-

I:k5: ...... 0 g ,- b:,g t o ,

y p*9 9

. :. . . LAKE;

\h.g ,{:l LEGEND . h.$ -senysst.??:  ; *'c CC 8enen. Prop.rty Boundary ,' l5:h #k l

I m Nuci..r Sc nc . Area s Environen.ntal TLD St ten (:^::f :k'dh LLE PRihE'R[T f., ll.k f

' 'i' ' .;. #e

'I O

O 25 SCALE. MILES 05 S::

)5 h;

~ f.. .f . .. f1/

I

.': f:

. 'l.7:)

, iWef" i i i i i= p ' ' ' , iiii  ; , , , , . . i ' ' ' ' ' ', . ' I ,' , , ,'

1 ii'

{Iy. ';

e, I eE m Ree, MADISON CO FRANKLIN CO e,

y s

\

g /i h  ;

I '

I I

FIGURE 9. MAP OFTLD LOCATIONS ATTHE PERIMETER SECURITY FENCE

' 400 6023 6027 6028%;

60N 300' 6026 60224 GUARD

); HOUSE F

/ 6025 3;

3; 60 3 >

/ 200' PLUTOMtuM S ACiuTV b

% l /

N4 6030k.

3 I3.

ag6021

' .' I A

[ .

\ b 6031 REACTOR T ' e^a.y*'NG

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. ARE A7 _ . ,p N Y

s t , ,-

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020 . .- 6037

%q '

h : ? *- 6033 k

C3 ^ ' :J 3; SUB ...'  :) \ *y

( STATION . PAR KING .,.-

CRtinCAL ..' AREA!

- '[4 '1.-4 St, ASSEMBLY t ' '.. 6034k 6019 \ f  :

.. reuCEO .

"~ OLD . STORAGE:

,; JN 2 \

GUARD ggg

- HOT C' .L cc' W. ,

^^

' ',1

- JN 1 '

-- / ,

.%.1.4 '

M # '

6035$I

• l[ OLD WELL t

• STORAGE  ;

HOUS 50 100 )',

,,, ilii,,1 6036h LE GEMD 6018 6017 6016 SCALE FEET 6040 , ,,,,, pence m

3

,,

6039 7g s,y 6038 3- E nvd0"""**'

yg yy 3 yy yg 6037 A TLD Stateo" g T se ,

_ , , , . = * * * * * ~

FIGURE 10. MAP OF COLUMBUS AND VICINITY SHOWING OFF SITE AIR SAMPLING LOCATIONS DE LAW ARE 23 42 73 4

MARYSVILLE 33 C2b " WESTERVILLE 4 161 i3 WORTH 6NGTOD NE W ARK f

N!LLIARD 33 EA 8 EA-7

.3

, >o e v _5 -

- ," a ms

=

, . O

~

V NEW ROVE A6 142 WEST JEFFERSON g3 270 42 LONDON C 71 33 22 23 LE GE ND LANCASTE R Battelle Nuclear Sciences Area

$ OEPA Aer Samples O 44 88 - 33 f f f CIRCLEVILLE SCALE MILES 22 23

m m

m_ _

m E

T I

m S

N m O '&

S R

E F

m F e t E s E

J E m T *

\

S Er e* 1 E

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% m R w; +(

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,a m

M%

N uw L A 0 Mm m 8 C 3 R 9 E k T 1 ,i +

T '

A 4 M P

• s E **e S M O f R s D M N #

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0 s-M 8

9 9 t

c*s 1 #* M 1

1 E M R

U b k

G I

I M

F  %

M M

M

,,i;j;,l ,1 - i i. 3! !. Y , , .

M'

I 39 l FIGURE 12.1970 POPULATION WITHIN 50 MILES OF THE WEST JEFFERSON SITE I s HARDIN W NNW Kenton MARION MO 41.000 6 9""

I NW 5.120 i

3.050 O

8.210 Mt Gilead l NE l KNO^

I 8.150 LOGAN j

3.025 l

2. ' 21 l 6.030 8'

• 1 Mt Vernon IWNWl Be lefontasn 1.015 DE WAR I

U#

13.200 UNION *oeiaware .

SHELBY@

sidney _.

j 600

\{ ENE l I 7. ',10 5.080 CHAMPAIGN

@ 13.300 830 7,4 0 .110 13.919 3.135 5.600 LI KING MIAMI 590 - Ewan

,,,,gg, Troy @ '

. Columbus 43.100 6.200 B g21 um @p Q 13.000 C 890 I

g R[ 8 7 0 , g,,,,,,,n , 1 q spnngfield FRANKLIN 8.100 g 1.250 London 720 5.050 930 PERRY MONTGOMERY 30.800 SON 820 N N, O ~

e Dayton O 28.300 2.110 680 71'0 Lancaster New 3.600 IWsWI

@feif

@ FAYETTE PICKA AY Ese 1 2.130 4.320

, 40.200 y 1.140 Circieville g

\ 13.270 Washington. C H 7 CLINTON HOCKING I

7.300 6.210 3.020 sw *'"9'" 8 ROSS 2a.000 e I

i

[ 6.330 p 7.410

-N- ,,,,,3.3,,

f issWI o so i.on no

,I o do 1.254.975 s H :isboro l

I

] o so 1.488 885 l '

HIGHLAND LEGEND B Nuclea Scopaces Area West Jefferson Sete I $caio Meies I

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1 I 40 I

i TAllLE 16. RADIONUCI.IDE C0t! POSITION OF flCI. EFFLUENTS CY-1980 I

West Jefferson Site Air Activity (pC1)

Cross Alpha 0.05 Crana lleta 7.79 P l u t o ni ta-2 39 0.73 '

Cobalt-60 4.8 Cobalt-57 0.05 Tha llita-208 0.05 ,

Cealum-137 0.61  !

Nep t uni ta-2 39 8.41 Cesita-134 0.009 '

I. cad-212 0.14 Lead-214 0.23 Chromium-51 0.16 Te l l u r i ta-125m 2.03 Cerlum-134 0.02 Bismut h-214 0.56 Ce r i ta- 144 0.56 Antimony-125 46.76 Krypton-85 329000000.00 Rhod i ta- 101 0.02 Cerium-139 0.02 Actinlum-228 0.15 Ila r i ta- 133 0.02 Cerium-141 0.10 ,

Iodine-131 0.60

=

Uranium-235 0.18 Europium-154 0.0001 Tho r i ta-2 28 1.73

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I 41 .

TABLE 16. (Continued)

I I West Jefferson Site Water Activity (pCi)

Gross Alpha 7.92 I Cross Beta Iodine-129 Cesium-137 19.10 0.68 9.51 I St ro nt itn-90 Plutonium-238 Plut oni ta-2 39 9.63 0.07 0.05 I Radium-226 Radium-228 Cerium-144 0.95 0.65 16,60 Uranium-2 35 1.64

,I l King Avenue Site Water Activity (uC1) l Gross Alpha 1570.0 Gross Beta 834.0 1l l .

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42 EVALUATION OF DOSE TO THE PUBLIC Estimated Radiation Doses to the Public g from Emissions from the Battelle West 3 Jefferson Site During CY-1980 The following information is presented to report and evaluate the possible radiation dose to the public resulting from DOE contract operations at Battelle's nuclear facilities at West Jef ferson, Ohio. The procedures g used to estimate radiation doses utilized standard methods as recommended 5 by ICRP(4) or specified by DOE (5). Details concerning the calculational methodology can be found in our report for CY-1972.

Radioactive Emissions from the West Jef ferson Site for 1980 Atmospheric Discharges Measured releases and enund level annual average concentrations at the site boundary during 1980 for the West Jef ferson Site are summarized in Table 2. The site boundary, which determines the perimeter for uncontrolled g exposure, is considered coincident with the downwind position from the g facility where the annual ground level concentrations will be highest.

This point is on BCL property but outside the security fence. Analyses g of the data in Tables 2 and 3 show that the total mixed fission product 3 (MFP) beta releases for 1980 amounted to 67.9 pCi with a total average concentration at the site boundary of 1.96 x 10-16 pCi/ml. Based on g isotopic analyses of the stack ef fluents from the JN-1 facility, the 5 principal radionuclides were determined to be cobalt-60, cobalt-57, cesium-137, lead-212, neptunium-239, cerium-141, cerium-144, strontium-90, g iodine-131, thorium-228, antimony-125, acti. lum-228, cesium-134, 3 europium-154, uranium-235, and te11urium-125m. An average cor. position of the effluents containing these radionuclides emitted f rom the five stacks g of the JN-1 facility was calculated from the isotopic concentrations given 5 in Table 3, and this was used in evaluating the dose from the MFP beta releases. The total krypton-85 emmission was 3.29 x 102 Ci with a 3 corresponding average concentration at the site boundary of 2.01 x 10-9 3 pCi/ml. The total alpha activity emissions were 0.73 pCi and review of facility operation for 1980 indicates that most of this was due to g plutonium-239. Therefore, all the alpha emissions should be considered 3 to be plutonium-239 only , with an annual average concentration at the site boundary of 9.41 x 10-18 LCi/ml.

Liquid DNcharges Measured aqueous celeases and effluent concentrations during 1980 for the West Jefferson Site are summarized in Table 4. The concentration values apply to the water discharged into Big Darby Creek af ter passage through a conventional leaching bed. Based on knowledge gained from an isotopic =

1

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I 43 I

I inventory of radionuclide concentrations in the leaching bed , emissions should be due to very limited clution f rom the leach bed of contaminants that were delivered to the bed in past years. Therefore, the alpha I activity is considered to be primarily uranium-238 and the gross beta activity should contain only relatively long-lived radionuclides.

Estimated Radiation Dose to the Public from Atomospheric Discharges Calculation of Atmospheric Dispersion Parameters I In all cases Columbus Meteorological data the annual average dispersion parameters for the site. The Air Quality Display Model computer program (7), modified for localized applications, were used as input to compute I uas used to generate the required X/Q data. Thus, annual average X/Q values were developed for a series of concentric rings extending from the site boundary out to a distance of 50 miles. (Refer to Figure 1.) The I

annular rings were broken down into sixteen sectors corresponding to the normal wind rose pattern. (Refer to Figure 11.)

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

Doses arising fr om the alpha activity emissions were based on plutsnium-I 239, liberated entirely as the insoluble oxide form. The maximum dose estimate obtained for an individual and for the nearest population group are summarized in Table 17.

The estimated off site doses listed in the table are very low compared to the maximum permissible exposures (MPE) which have been recommended by the ICRP(4) and other groups for the general public. The MPE values recommended

!I for an infividual are: bone - 3 rem /yr, GI tract - 1.5 rem /yr, whole body -

0.5 rem /yr, skin - 3 rem /yr, throid - 3 rem /yr, lung - 1.5 rem /yr, and g kidney - 1.5 rem /yr. The recommended values for a population group are

g I

one-third of these values. Therefore, from Table 17 it may be seen that the brmst fraction of MPE occurs to the skin and is 1.3% of the recommended I

limits at the site boundary. In addition, exposure of persons to natural background radiation in the area would be less that 0.14 rem /yr as measured by TLD stations. Therefore, atmospheric emissions from the site .

I (Tabic 2) led to estimated radiation doses which are approximately 25%

of that expected from natural background.

I el

TABLE 17.

SUMMARY

OF MAXDfUM RADIATION DOSE TO AN INDIVIDUAL AND THE NEAREST POPULATTON GROUP (WITHIN TWO MILES OF SITE) FROM ATMOSPHERIC EMISSIONS CY-1980 Estimated Doses at Estimated Doses at Tite Boundary a Radius of Two Miles from Site ('

Critical Individual Dose, Source Organ Individual Dose, Populatior. Group Dose, rem /yr rem /yr person-rem /yr MFP Lung 2.6 x 10 '

-0 1.5 x 10 6.9 x 10 MFP Thyroid -6 ~9 3.2 x 10 1.9 x 10 8.6 x 10~

MFP Kidney -9 -12 -8

, 9.7 x 10 5.7 x 10 2.6 x 10 MFP GI Tract 1.1 x 10' 6.4 x 10-

~

2.9 x 10 85 Total Body -3 -6 -2 Kr 6.7 x 10 3.9 x 10 1.8 x 10 85 Kr Skin 4.0 x 10~ -5 ~1 2.4 x 10 1.1 x 10 239 Lung -4 2.3 x 10 1.4 x 10~ 6.2 x 10 90 Bone -5 -8 3 2.2 x 10 1.3 x 10 -5 5.8 x 10 (a) Two miles from site, population of 4500 and atmospheric dilution factor from site boundary of 1700.

M M M M M M M M M _ ___ ___ _ _ _ _ _ _ _ _ _ --- - - -

I 45 Calculation of the 50-Mile Integrated Population Annual Dose The cummulative population dose is the prgict of the individual radiation I dose and the figures from the 1970 census for the population in the various annuli around the site out to a 50-mile radius. Using the release data given on page 12, unde.r " Atmospheric Discharges" as input, the integrated I population dose calculatioi produced the estimated 50-mile annual person-rem doses listed in Table 8. The values given in this table way be compared againat the integrated person-rem /yr dose that would be expected I for the population group due to natural background. Since the level of natural background radiation would be assentially constant over the whole area, the corresponding person-rem /yr s alue is simply the product of the I total population and the natural background radiation value. Using a natural background of 0.14 rem /yr and a total 50 mile population figure of 1.50 x 106 produces an integrated population dose from natural background of 2.1 x 105 person-rem /yr. The total body dose caused by emissions f rom I Batte11e's West Jefferson Site is less than 0.0003% of that due to natural background radiation.

I TABLE 18. ESTIMATED INTEGRATED 50-MILE POPULATION DOSES CY-1980 I Critical Integrated 50-Mile Population Source Organ Dose, person-rem /yr MFP Lung 1.8 x 10-MFP Thyroid 2.2 x 10-MFP Kidney 7.4 x 10~

MFP GI Tract 7.4 x 10~

85 # Y

• Kr 85 "

• Kr 239 p Lung 1.6 x 10 90 g Bone 1.5 x 10 I

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t 46 I

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

It i' not known if any of the area below the outf all on Big Dacby Creek is ue, ror swimming purposes; however, such use could be possible.

Swimmers are assumed to receive an external radiation dosa f rom being g submerged in water cont ining radionuclides which are anticipated to be 5 present in the liquid ef fluent. The measured emissions at the outfe.11 were summarized in Table 4. Only the beta releases were used in calculating g the external radiation dose to potential swimmers, since the less penetrating g alpha emissions do not make a significant contribution tt ;he total body dose.

Using standard decay energy values, the estimated doses for a swimmer who g 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 g obtained as shown in Table 19. Results are given for two cases; one where the swimmer stays in the water near the outfall (dilution factor of 10) and g the other where the swimmer remains well downstream such that the discharged 5 activities are completely mixed with the annual average stream flow of Big Darby Creek.

TABLE 19. ESTIMATED RADIATION DOSE TO A SWIMMER (EXTERNAL WHOLE BODY DOSE)

CY-1980 Water Body Radiation Doce, rem /yr Outfall Effluent 1.7 x 10-6.2 x 10-Downstream I

Radiation Dose Due to Boating and Water Skiing Big Darby Creek is too small to allow boating and other water recreation s po rts . Thus, there will be no dose f rom these activities.

Radiation Dose from Drinking Water Water f rom Big Darby Creek below the cutf all 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.

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Radiation Dose f rom Eating Fish Ig There may be limited fishing activity along Big Darby Creek but no estimate 3 of the extent of this activity is available. Radiation dose to man can occur f rom eating fish which have resided in water which contains radio-I nuclides from the liquid effluent. The concentration of an individual radionuclide in the fish (uci/g dry wt.) is assumed to be direct v related to the concentration of the radionuclide in the water in which the fish reride I multiplied by a bioaccumelation factor.(8) dose to a human it was assumed the person consumes an average -f 4.8 kg of fish per year, taken from Big Darby Creek either a short distance In calculating the radiation ,

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I below the outf all (water dilution factor of 10) or well downs'. ream where the effluent has become completely mixed with the annual average stream flow. Internal radiation doses were estimated on the basis of the discharge I

I data .,1ven on pages 18 and 42 under Liquid Discharges, and the composition assumptions noted there.

I The doses from eating fish caught in Big Darby Creek are also representative of doses from eating fish caught in Battelle Lake because the overflow from the lake drains into Big Darby Creek and is monitored at the point of I outf all to the creek to determine the concentrations of radionuclides in the water.

I Comparison of the data in Tables 19 and 20 show that fish consumption is expected to be the dominant exposure pathway for persons from liquid emissions at the Battelle West Jef ferson Sit e. However, individuals in I this area would routinely be exposed to natural background radiation at levels of about 0.14 rem /yr. Therefore, raaximum doses resulting from liquid em1.sions from the site should have been a small fraction of that I produced by natural background.

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i TABLE 20 ESTIMATED RADIATION DOSES FROM EATING FISil CAUGHT IN BIG DARBY CREEK NEAR Tile BATTELLE WEST JEFFERSON SITE CY-1980 Radiation Dose, rem /yr #

Fish Taken Fish Taken Critical Near Outfall Downstream Nuc lide Organ Adult Teen Child Adult Teen Chrid i

-9 -9 -10 6.8 x 10 '

3.7 x 10 ' 1.4 x 10 '

Cs Total Body 3.0 x 10 1.7 x 10 6.2 x 10

-4 -9 -9 -9 Sr Bone 1.1 x 10- 9.1 x 10 ' 7.8 x 10 4.8 x 1G 4.0 x 10 3.5 x 10

-6 1.7 x 7g -6 4.5 x 10- -12 -1 Ce GI Tract 1.4 x 10 6.4 x 10 4.8 x 10 2.0 x 10-(a)

Calculation of rem dose per yr was based on guidelines set forth in U.S. NRC Regulate.cy Guide 1.109 (8).

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I 49 I L REFERENCES 6 (1) U.S. Census, 1970 Population Data, Dayton, Ohio, Standard Metropolitan Statistical Area.

(2) U.S. Energy Research and Development Administration, Manual Chapter 0524, " Standards for Radiation Protection".

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

Continuing Planning Process for Water Quality Management.

(4) IC'JP Publication 2, " Recommendations of the International Commission on Radiological Protection, Report of Committee II on Permissible Dor,e for Internal Radiation". Pergamon Press, 1959.

(5) U.S. Energy Research and Development Administration, Manual Chapter 0513, " Effluent and Environmental Monitoring and Reporting".

I (6) U.S. bather Buteau, Weather Information for Columbus, Ohio Decennial sa Census of United States Climate (1951-1960) Washington, D.C. (1963).

o E (7) TRW Systems Group , " Air Quality Display Model", Report PB-189194 (Contract PH 22-68-60), November, 1969.

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

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I 50 guality Assurance Several methods are used to assure that the data collected each year are representative of actual concentrations in the environment. Extensive environmental data are collected to eliminate an unrealistic reliance on' only a few results. Newly collected data are compared with historical data for each environmental medium to assure

• hat current values are consistant with previous results. This allows for timely investigation of any unusual results. Samples are cellected using identical methods gi near to and far from the nuclear s ce, as well as upstream and downstream on Darby Creek, to provide for identification of any net differences that I!

may be attributable to the West Jefferson nuclear operations. These p ro ced ures , 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 performed at the radiochemistry facility located I'

at the West Jefferson nuclear site. Environmental samples requiring specific isotopic analysis are sent to Eberline Instrument Corporation's Albuquercue Laboratory, Albuquerque, New Mexico. Both laboratories maintain internal quality assurance programs that involve routine <

calibration of counting instruments, daily source and background counts, routine yield determinations of radiochemical procedures, and replicate analyses to check precision. The accuracy of radionuclide determination is assured through the use of standards traceable to the Na* tonal Bureau of Standards, when available.

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

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

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I 51 I APPENDIX I ADDITIVE LEVELS DUE TO RADIONUCLIDE MIXTURE I The " Standards for Radiation Protection" (DOE Manual Chapter 0524) states that n radionuclide may be considered as not present in a mixtiire if the ratio of its concentration to its RCG is not grater 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 their respective RCG's are listed below. The ratios are presented for maximum levels at ti.e release point in both air and water.

I West Jefferson Site I Radionuclide Radionuclide Concentration RCG Air (Particulate)

-2 Plutonium-239 3.11 x 10

-5 Cobalt-60 3.82 x 10

-8 Cobalt-57 2.08 x 10

-8 Cesium-134 5.34 x 10 Lead-212 5.63 x 10~

-6 Cesium-137 2.94 x 10 Actinium-228 6.07 x 10~

-6 Neptunium 1,01 x 10 Cerium-141 4. 98 x 10-

-9 Chromium-51 4.94 x 10

-6 Tellurium-125m 1.22 x 10

-5 Iodine-131 1.44 x 10

-6 Carium-144 6.74 x 10 Antimony-125 1.24 x 10~

Europium-154 2.40 x 10'

-4 Uranium-235 1.08 x 10

-2 Thorium-228 2.07 x 10

-2 Sum 5.?0 x 10 Air (Gaseous) l Krypton-85 2.63

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West Jefferson Site Radionuclide Radionuclide Concentration RCG Water l

-5 m Cerium-144 3.97 x 10

-2 Radium-228 1.65 x 10

-2 Radium-226 2.30 x 10

-4 Cesium-137 3.44 x 10

-2 l S t rontium-90 2.33 x 10 Iodine-129 7.67 x 10-

-6 Plutonium-238 9.78 x 10

-6 Plutonium-239 7.96 x 10

-5 Uranium-235 3.97 x 10 Sum 7.21 x 10-l The data indicate that, according to the criteria of DOE Manual Chapter 0524, the sum of the above radios does not exceed one-fourth; therefore, g these nuclides are not considered as part of the mixture. 5 APPLICABLE STANDARDS Radioactive Standards l

l In conformance with Federal Radiation Council (FRC) guidelines and DOE l Manual Chapter 0524 " Standards for Radiation Protection", site boundary Concentrations are compared with RCG's established for uncontrolled areas.

Uncontrolled Area (Site Boundary)

Air Concentration, pCi/ml 6x10h Plutonium-239 Krypton-85 3x10]O -

I Cobalt-60 3 x 10,9 l Cobalt-57 6 x 10

-10 l Cesium-137 5 x 10

-10 Cesium-134 4 x 10

-10 Lead-212 6 x 10- 5

Actinium-228 6x10_f0

Neptunium-239 2 x 10 -

Cerium-144 m 2 x 10 '10 Tellurium-125m 4 x 10_8 Chromium-51 8 x 10

-10 $

m Iodine-131 1 x 10 Europium-154 1 x 10-10 I

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I 53 I Uncontrolled (Site Boundary)

Air Concentration pCi/ml Thorium-228 7 x 10~

Uranium-235 4 x 10-Antimony-125 9 x 10-Cerium-141 5 x 10~

Water Cesium-137 2 x 10-

-8 Iodine-129 6 x 10 Radium-226 3 x 10' Radium-228 3 x 10-

-6 Plutonium-238 5 x 10

-6 Plutonium-239 5 x 10 Strontium-90 3 x 10~

-5 Uranium-235 3 x 10 Cerium-144 1 x 10~

Mixture l

l I DOE Manual Chapter 0524, " Standards for Radiation Protection", provides l

I 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 respective RCG must l I 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 l

the radionuclide to its RCG is grater than one-tenth, provided that the sum of such excluded ratios does not esceed one-fourth.

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Grass and Food Crops There are no guidelines established for radionuclides in grass and food g crops. 3 Soil and Sediment There are no guidelines established for radionuclides in soil and sediment. The Environmental Protection Agency's radiation protection requirements for exposures to transuranium elements in the environment g

3 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)

I 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 permissable 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 calander year.

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I 55 EXTERNAL DISTRIBUTION LIST This report is submitted to the Director, Contracts Management Of fice, U.S.

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

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

Health Commissioner London, Ohio I Other County and City Health Departments William Brown Health Commissioner City of Columbus State of Ohio I

J James Wynd Engineer-in-Charge

Radiological Health Unit

( Ohio Department of Health Dr. Jehn Ackerman Director, Department of Health 246 N. High Street Columbus, Ohio 43215 Dr. James McAvoy Director j Ohio EPA Ernest C. Neal, Chief District Operations Ohio EPA II l

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I State of Ohio (Continued)

Ohio Power Siting Commission Of fice of Assistant Administration for Public Information Charles Taylor Office of Air Pollution Ken Harsh Office of Emergency Response Jim Kneale, Chief Of fice of Public Water Supply Ii Ernie Rotering Waste Water Pollution Control Paul Flanigan, Chief Title X Ohio EPA John Donday Office of Land Pollution Control Federal EPA W.D. Rowe Deputy Assistant Administrator for Radiation Programs l Of fice of Radiation Programs 5 Surveillance and Inspection Division U.S. EPA Gilbert Gigliotte, Director Technical Information Francis M. Middleton, MERL Mr. David Kee, Director Air and Hazardous Materials Division Outside Laboratory Samuel I. Baker Senior Environmental Protection Officer g Fermi National Accelerator Laboratory P.O. Box 500 E

Batavia, Illinois 60510 I

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Outside Laboratory (Continued)

Jack P. Corley, C.H.P.

Staff Engineer Environmental Evaluations bection II i

Battelle Pacific Northwest Laboratories Battelle Boulevard Richland, Washington 99352 1

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a w l Battelle Columbus I aboratories I.

505 King Avenue l Columbus, Ohio 4 3201 Telephone (614) 424-6424 I

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