ML20211G995
| ML20211G995 | |
| Person / Time | |
|---|---|
| Site: | 07000008 |
| Issue date: | 12/31/1985 |
| From: | Robert Evans, Stewart D, Swindall E, Swindally E Battelle Memorial Institute, COLUMBUS LABORATORIES |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 27012, BCD-5185, NUDOCS 8606200413 | |
| Download: ML20211G995 (87) | |
Text
BCD 5185 I
I ENVIRONMENTAL REPORT FOR CALENDAR YEAR 1985 on RADIOLOGICAL AND NONRADI0 LOGICAL PARAMETERS to UNITED STATES DEPARTMENT OF ENERGY CHICAGO OPERATIONS OFFICE Prepared by I
Environmental Health Physics Nuclear Serv 1t.as Section May 1,1986 I
Contributors D.G. Stewart, R.G. Evans, E.R. Swindall, G.E. Kirsch, R.H. Snider, Health Physics Services, Nuclear Services Section M.J. Stenhouse Radiochemistry Services, Nuclear Technology Section J.L.'Paulian and P.H. Gorman, Facilities Engineering and Operation Section BATTELLE Columbus Division 505 King Avenue Columbus, Ohio 43201 l
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APPROVAL LIST I
APPROVED BY M
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APPROVED
' Assistant Group Manapdr I
West Jefferson Nuclear Services APPROVED BY ag. d
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West O6fferson Nuclear Services I
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TABLE OF CONTENTS 1
Page LIST OF TABLES..........................................................
v LIST OF FIGURES.........................................................
vii FOREWORD................................................................ viii I
SUMMARY
1 SITE AND FACILITY DESCRIPTION...........................................
3 Site Descriptions..................................................
3 Demography....................................................
4 Climatology...................................................
4 Geology.......................................................
5 Hydrology.....................................................
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Background Radiological Characteristics.......................
7 FACILITY DESCRIPTIONS...................................................
7 The King Avenue Site...............................................
7 The West Jefferson Site............................................
8 Hot Laboratory, JN-1...............................................
8 Administrative Building, JN-2......................................
9 Battelle Research Reactor, JN-3....................................
9 Hazardous Material Laboratory, JN-4................................
9 Radiclogical Waste.................................................
10 ENVIRONMENTAL MONITORING................................................
11 West Jefferson Site................................................
12 1~
Air Radioactive...............................................
12 Water Radioactive.............................................
13 Water Nonradioactive..........................................
14 Grass and Food Crops Radioactive..............................
15 Sediment Radioactive..........................................
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TABLE OF CONTENTS (Continued)
I Page Soil Radioactive..............................................
16 Fish Radioactive..............................................
16 Background Radiation Levels...................................
16 KING AVENUE SITE........................................................
17 Water Radioactive..................................................
17 EVALUATION OF DOSE TO THE PUBLIC........................................
17 Estimated Radiation Doses to the Public From Emissions from the Battelle West Jefferson Site During Cy 1985....................
17 Atmospheric Discharges........................................
18 Liquid Discharges.............................................
18 Estimated Radiation Dose to the Public from Atmospheric Discharges.........................................................
18 Computation of Atmospheric Dispersion Parameters..............
18 Computation of Girl Scout Camp, Nearest Resident, and Population Group Doses....................................
19 Computation of the 70-Year Dose Connitment at tne g
Girl Scout Camp and for Nearest Resident, Population 3
Groups, and Integrated 50-Mile Population.....................
19 Estimated Annual Radiation Dose to the Public from Liquid Discharges.........................................................
20 Radiation Dose from Swimming (External Whole Body)............
20 Radiation Dose Due to Boating and Water Sk iing................
20 Radiation Dose from Drinking Water............................
20 Annual Radiation Dose from Eating Fish........................
20 70-Year Dose Commitmen,t.......................................
21 Fence Post Dose Estimate......................................
21 Maximum Organ Dose Estimate...................................
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REFERENCES..............................................................
22 Quality Assurance..................................................
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TABLE OF CONTENTS (Continued)
Page APPENDIX ADDITIVE LEVELS DUE TO RADIONUCLIDE MIXTURE.............................
A-2 West Jefferson Site................................................
A-2 APPLICABLE STANDARDS....................................................
A-3 Radioactive Standards..............................................
A-3 Uncontrolled Area (Site Boundary)..................................
A-4 Air...........................................................
A-4 Water.........................................................
A-4 Mixture............................................................
A-4 Grass and Food Crops..........................................
A-5
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Soil and Sediment.............................................
A-5 Fish..........................................................
A-5 Nonradioactive Standards (Water)..............................
A-5 External Radiation - General Public...........................
A-5 EXTERNAL DISTRIBUTION LIST..............................................
A-6 9
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LIST OF TABLES Page Table 1.
Populat' ion Distribution Within 10-Mile Radius from Site....................................................
24 Table _2.
Sumary of Atmospheric Radiative Emission -
West Jefferson Site..........................................
25 Table 3.
Gama Emitting Radionuclides Identified in the JN-1 (Hot Cell Stack Particulate Emissions).......................
26 Site (y of Liquid Radioactive Emissions - West Jefferson Sumar Table 4.
Measure of Effluent from Sanitary Sewerage System into Big Darby Creek - Figure 4, Designation 010)............
27 Table 5.
Nonradiological Sampling for West Jefferson Site January 1, 1984 to December 31, 1985.........................
28 Table 6.
Sumary of Gras s An alyses....................................
29 Table 7.
Sumary of Food Crop Analyses................................
30 Table 8.
Summary of Silt Analyses.....................................
31 Table 9.
Sumary of Soi l Core Analyses................................
32 Table 10. Sumary of Gamma Isotopic Analyses of Soil Core Samples......
33 Table 11. Sumary of F i sh An a lys i s.....................................
34 Table 12.
Integrated External Background Radiation Measurements at E
Recreation Area and Property Boundary Line -
3 West Jefferson Site.........................................
35 Table 13.
Summary of On-Site Ground Water Survey Sample Analyses..............................................
36 Table 14. Concentration of Radioactivity in Liquid Discharges to l
Columbus Municipal Sanitary Sewerage System..................
37 E
Table 15. Sumary of Site Boundary Air Sample Analyses for Gross a
Radioactivity................................................
38 E
Table 16. Sumary of Site Boundary Air Sample Analyses for Specific Radionuclides................................................
39 Table 17 Sumary of Off-Site Air Sample Analyses......................
40 Table 18 Sumary of Environmental Water Sample Analyses...............
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LIST OF TABLES Page Table 19.
Radionuclide Composition of BCL Effluents for CY 1985........
42 Table 20.
Summary of Annual Radiation Dose to the Girl Scout Camp Nearest Residence and Population Groups from Atmospheric Emissions of Krypton-85 During CY 1985.......................
43 Table 21.
Annual Dose to the Girl Scout Camp from Effluents Released During CY 1985......................................
44 Table 22.
Annual Dose to the Nearest Resident (0.75 Km NW) from Effluents Released During CY 1985............................
45 Table 23. Annual Dose to the Nearest Population Group (Darby Estates) from Effluents Released During CY 1985.......................
46 Table 24. Annual Dose to the Population Group (West Jefferson) from Effluents Released During CY 1985............................
47 Table 25. 70-Year Dose Commitment for the Girl Scout Camp from Effluents Released During CY 1985.......................
48 Table 26.
70-Year Dose Commitment for the Nearest Resident (0.75 Km NW) from Effluents Released During CY 1985..........
49 Table 27.
70-Year Dose Commitment for the Nearest Population Group (Darby Estates) from Effluent Releases During CY 1985........
50 Table 28.
70-Year Dose Commitment for the Population Group (West Jefferson) from Effluent Releases During CY 1985.............
51 Table 29. 70-Year Dose Commitment for 80-Kilometer Population from Liquid Effluents Released During CY 1985.....................
52 Table 30. 70-Year Dose Commitment for 80-Kilometer Population from Airborne Effluents Released During CY 1985...................
53 Table 31.
Parameters for West Jefferson Site Airborne Release Dose Calculations.................................................
54 Table 32. Average Annual Percent Frequency of Wind Direction and Average Wind Speed (M/S) for CY 1985.........................
55 Table 33.
BMI King Avenue Site Population Within 50 Miles..............
56 L
Table 34.
Annual Average Atmospheric Dispersion Around the West Jefferson Site for an 18 Meter Stack Height Release..........
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I LIST OF FIGURES Page Figure 1.
Regional Map for King Avenue and West Jefferson Sites.......................................................
58 Figure 2.
Local Vicinity Map of King Avenue Site......................
59 Figure 3.
Local Vicinity Map of Nuclear Sciences Area West Jeffeson Site..........................................
60 Figure 4.
Nuclear Sciences Area West Jefferson Site...................
61 Figure 5.
Map of Grass, Foodcrop and Soil Sampling Locations..........
62 Figure 6.
Map of Site Boundary Air Sampling Location and Battelle Lake and Darby Creek Water Sampling Locations...................................................
63 Figure 7.
Batte11e's Columbus Laboratories King Avenue Site............
64 Figure 8.
Map of TLD Locations Within 3/4 Mile Radius of the Nuclear Sciences Area.......................................
65 Figure 9.
Map of Columbus and Vicinity Showing Off-Site Air Sampling Locations..........................................
66 Figure 10.
1985 Wind Rose Pattern for West Jefferson Site..............
67 Figure 11.
1980 Population Within 50 Miles of the West Jefferson Site........................................................
68 Figure 12.
1980 Population Within 10 Miles of the West Jefferson Site........................................................
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FOREWORD 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 nonradiological 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 radioactivity and gamma isotopic determinations were performed by Radiochemistry services, Nuclear Services 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 performed by the Columbus Water and Chemical Testing Laboratory, Columbus, Ohio.
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SUMMARY
I Environmental data collected during CY-1985 show continued compliance by Battelle Columbus Division (BCD) with all applicable state and federal regu-lations.
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In addition to the routine monitoring of liquid and atmospheric emissions at the King Avenue and West Jefferson nuclear sites, data were collected for var-ious environmental media including air, water, grass, fish, food crop, sedi-ment and soil. These samples were taken from the area surrounding the West Jefferson Nuclear Site.
__ I In general, off-site levels of radionuclides attributable to the West Jefferson nuclear operation were indistinguishable from background levels.
The data are sumarized as follows.
West Jefferson nuclear operations during 1985 caused no distin-guishable impact on concentrations of airborne radionuclides or on external radiation doses measured adjacent to the nuclear site or
- I at the West Jefferson site boundary (see page 26, Table 3 and page 35 Table 12.)
Radionuclides observed in food crop, grass, creek bottom sediment, B
and soil samples were all attributed to either atmospheric nuclear tests or natural sources (see pa 6, 7, 8, 9, 10, and 11.) ges 31, 32, 33, 34, 35 and 36, Tables Low level concentrations of a few radionuclides released to Darby Creek from the West Jefferson nuclear site were all less than 0.23 percent of the respective concentration guide for an individual
-I radionuclide released to an unrestricted area. Concentrations observed at down-stream sampling locations were statistically indistinguishable from background levels (see page 27, Table 4 and page 41 Table 18).
The estimated radiological dose resulting from the nuclear operation at the West Jefferson site was calculated for the Girl Scout Camp, nearest residence B
and population groups, and the integrated fifty mile population surrounding the site.
(The Girl Scout Camp dose is calculated assuming a full time resi-dentcustodian.) These dose calculations take into account both the measur-I able levels of environmental contaminants and the impact of radionuclides known to have been released but not found in detectable concentrations during the year's environmental sampling program. The doses are summarized as
_B follows:
The 70-year dose commitment computations for the Girl Scout Camp nearest resident and population groups" and the 80-km (50 mile) population have been I
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 commitment:
(1) chronic inhalation of radioactive mixture using an
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atmospheric diffusion model; (2) chronic ingestion of a radioactive mixture through terrestrial and (3) aquatic pathways (see pages 48, 49, 50, 51, 52,
- 53. Tables 25,26,27,28,29,30).
The annual whole body dose at the Girl Scout Camp during CY 1985, was calcu-lated to be 0.0131 mrem. This estimate includes the external radiation exposure in excess of that re'ceived from normal background levels as well as contributions from airborne and aquatic recreation pathways.
The maximum organ dose comitment received at the Girl Scout Camp from all pathways was 0.078 mrem /yr to the skin from Krypton-85 (see page 43 Table 20). The dose can be compared with the standards given in DOE Order 5481.1 Chapter XI of 3000 mrem /yr for the skin. A discussion of how the maximum organ dose was calculated is given in the text on page 21.
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Airborne emissions from the West Jefferson nuclear site resulted in a whole body 70 year dose comitment to the population within 80-km (50-mile) radius of the nuclear site of 1.33 x 10-4 Liquid effluents during 1985 l
contributedapproximately4.4x10 gerson-rem. person-rem to the total population dose.
5 person rem /yr This estimate may be compared with the approximate 2.08 x 10 received annual from natural background radiation (see pages 52, 53, Tables 29, E
30).
5 The whole body " fence-post" exposure for external radiation at the site a
boundary line during 1985, was less than background at the Girl Scout Camp g
adjacent to the Battelle property line 0.5 km east of the nuclear site. This evaluation was verified through the use of TLDS placed at the site boundary (see page 35, Table 12). A discussion of how the " fence post" exposure was E
obtained is given in the text on page 21.
5 Releases of low-level concentrations of radioactivity to the Columbus E
municipal sewage system from the Building 3 (U-235 Processing Facility) were 5
less than 3.3 percent of the concentration guide for discharges of mixtures into sanitary sewerage systems (see page 37, Table 14).
Discharges of sanitary water from the West Jefferson nuclear site into Darby Creek under the National Pollution Discharge Elimination System (NPDES) permit were all within the parameter limits specified in Ohio EPA Permit No. N404-CD (see page 28 Table 5).
1 Any apparent increase in radioactivity concentration and resultant dose levels over last years report is a result of taking a conservative approach in the handling of data. Counting results were received in mixed form. Some results were presented with calculated values, others as less than minimum detectable activity (<MDA). Where <MDA was reported an apriori value was averaged with 3
the calculated values.
In nearly all instances calculated values were less g
than minimum detectable. While the concentrations may appear higher, no real increase to the public is evident.
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3 SITE AND FACILITY DESCRIPTION The activities performed under Contract No. W-7405-ENG-92 are conducted at BCD's King Avenue Site and the West Jefferson (Nuclear Science Area) Site. A 50-mile area map showing both sites is presented in Figure 1.
Figure 2 and 3 show property boundaries. Various Nuclear Regulatory Commission (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 BMI 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, accomodating twenty-one buildings, is bounded on the north by King Avenue, Perry Street to the east, Fifth Avenue to the south and the Olentangy River to the West. Figure 7 is an expanded view of the BMI King Avenue facility.
Building 3 houses the uranium processing activities at the King Avenue facility.
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 Site consists of a 1,000 acre tract which acconinodates the Engineer-ing Area in the southeastern portion, the Experimental Ecology Area in the east central portion and the Nuclear Sciences Area in the northern portion.
The northern boundary of the Site lies approximately one mile south of Inter-state Highway 70 extends from the Georgesville-Plain City Road eastward to the Big Darby Creek. The eastern boundary of the Site roughly parallels the valley of the Big Darby Creek southward to the Conrail tracks which constitute the southern boundary. The Georgesville-Plain City Road defines the western boundary of the Site.
For this report, the Nuclear Sciences area is the focus of interest at the
. West Jefferson Site. As illustrated in Figure 6 it consists of a ten-acre fenced area enclosing a guardhouse, four buildings and two other small struc-tures on a flat bluff above Battelle Lake to the south and Big Darby Creek to the east. The eastern edge of the bluff i aps rather abruptly from an average elevation of 910 feet to 870 feet mean sea level (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 the northern portion of the fence around the Nuclear Sciences facility, 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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l Demography The area within a two-mile radius of the BMI King Avenue facility to the 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 husiness and lig.ht industrial properties with scattered resi-dential patches. Table 34 shows the population within a fifty-mile radius of E
the King Avenue facility.
5 The area immediately adjacent to the West Jefferson Site has a low population g
density. Figure 12 shows the population distribution, by direction and dis-g tance, within 50 miles of BMI West Jefferson. The nearest residences to the i
Nuclear Sciences area are two houses located 2,500 feet to the northwest and southwest, respectively. A Girl Scout Camp, Camp Ken Jockety, is located on a E
bluff on the east side of the Big Darby Creek at a distance of 1,640 feet.
5 Four thousand feet to the southeast, on the eastern side of the Big Darby Creek, the Lake Darby Estates residential subdivision (Figure 3) is under con-struction. A total of 965 single family units have been built. A second subdivision, West Point, east of the Lake Darby Estates and Hubbard Road, has approximately 540 housing units.
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, Janitrol Aircraft, and Capital Manufac-E turing Company. Each of these is located at least 8 miles from the facility.
3 Closest to the Site are three small industries within West Jefferson that individually employ less than 60 people. The primary agricultural activity in the area is raising field crops such as corn and soybeans. Approximately 10 percent of the land area in agricultural use is devoted to pasturing beef cattle.
During the last 18 years two major highways, I-70 and I-270, have been com-pleted near the West Jefferson Site. The junction of these highways, which occurs near the eastern edge of the ten-mile perimeter around the Nuclear Sciences Area, has proven to be a popular area for industrial 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 1965. Most of the growth has taken place 3
near the outer limits of Columbus; however, the larger employers, e.g.,
E General Motors and White-Westinghouse, have actually decreased their number of employees.
Climatology 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 temperature for the months g
of June, July, and August being 73.3 F.
Temperatures of 90 F or above are g
expected for about 15 days during these months. The mean for the months of I
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5 December, January, and February is 31.2 F.
The number of days per year with temperatures below 32 F and below 0 F are 122 and 4, respectively. Precipita-
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tion is distributed fairly uniformly during the year although 60 percent falls during the spring-summer seasons. The annual monthly 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 r
was 3.87 inches in July of 1947.
Changeable wind directions are characteristic of the region due to the incur-sion of maritime tropical air masses from the Gulf of Mexico and outbreaks of t--
continental polar air masses from Canada. Warm air mass inversion is most 1
common during the later spring and sumer and frequently results in frontal showers and thundershowers. Tropical air mass thunderstorms are also comon 2
during the sumer and are frequently accompanied by high winds. Additionally, i
it is not uncommon for hot air mass thunderstorm development to be sufficiently strong to spawn tornado activity. Cold fronts that invade the region, princi-g pally during the late fall, winter, and early spring also bring showers and thunderstorms.
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During the late spring fast moving cold fronts, with large temperature discon-tinuities ahead of and behind the frontal surface, travel through the region Z
and are often accompanied by thunderstorms and frequently by tornadic activ-L_
ity. Of the 567 tornadoes recorded within 144 miles of the BMI Facilities M_
during the period 1950-1975, one hundred sixty-three have occurred in the month of April.
The regional climatological data gathered by the National Weather Service at I-
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Port Columbus, seven miles east-northeast of the King Avenue facility, is 7
generally representative of the local climatic conditions at the Columbus Site.
g A local meteorology station is maintained at the West Jefferson Site. The g
data collected by the local station are used for preparing the wind rose shown in Figure 10. Table 32 summarizes the windspeed and direction at the West Jefferson Site for 1985.
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_f Geology i
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The arrangement of geological strata in the BMI Facilities area consists of
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glacial till and outwash with formations of clay, sands, and gravel. The sands and gravel of the outwash are found in scattered, thin, discontinuous lenses within the till which is composed of unstratified clay 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 F
beads of limestone, dolomite and shale several hundreds of feet thick.
Surface soils consist of patches and mixtures of: Brookston Silty Clay Loam, Crosby Silt Loam, Lewisburg Silt Loam, Celina Silt Loam and Miamian Silt Loam.
The greatest portion of the surface soils is represented by the Brookston-
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Crosby Association with little more than traces representing the remaining A
types. All of these solid types exhibit relatively low permeability and all grade into till clay at depths of 55 to 60 inches where the impermeability of the near-surface geology nearly precludes further percolation.
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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 region. The BMI facilities are in a Zone 1 low-risk area.
Hydrology There are two aquifers, or sources of water, in the site area. The shallow aquifer is, of course, the dense clay till. The deep, or principal, aquifer g
is the limestone bedrock underlying the till.
Earlier wells in the site area g
ranged in depth from 10 to 40 feet, which placed them in the glacial deposits.
Till is not very permeable and yields water slowly. The effective velocity of water moving through clay under a hydraulic gradient of one percent is reported to be less than 0.004 foot per day; for water moving through silt, sand, and loess under the same gradient, the rate is about 0.0042 and 0.065 foot per day. Water movement in the till at the Battelle site is probably 3
within the range of the former figure, since the hydraulic gradient of the 5
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 E5 drilling these wells.
A man-made hydrologic feature of the site is the artificial lake covering an g
area of about 25 acres that was formed by damming Silver Ditch south of, and g
down gradient from, the Nuclear Sciences area. The normal surface elevation of the lake is 888 feet MSL.
The source of ground water in the site area is local precipitation. Recharge to the shallow aquifer takes place relatively uniformly over the area. Con-tours of the water table, which are about 40 feet below the surface, are a E
subdued replica of the surface topography. Ground water moves downslope at g
right angles to the contours and follows a path similar to surface runoff. At the Nuclear Sciences area surface runoff moves downslope into the lake, thence through the controlled dam on the site into Big Darby Creek.
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Test borings carried out in 1970 for an addition to the Hot Laboratory reaf-firmed the geology described above. Only isolated pockets of water were E
encountered during that boring and foundation-piling excavation operations.
E These pockets were readily pumped out and remained dry, which indicated that there is no interconnection of the pockets with the lake.
I Flood water calculation for the lake indicated a capacity of releasing water that was about three times the inflow rate measured during the January 1959 l
floods.
It can be concluded that the lake has not adversely affected the g'
l hydrology of the area.
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Big Darby Creek accounts for the principal surface water flow. Normal flow at the Darbyville 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 The external radiation backgroun'd levels at the Nuclear Science Area and the West Jefferson Site are continuously monitored at 15 dosimeter stations using commercially available type TLD-110 thermoluminescence (lithium fluoride) dosimeter packets. All TLD packets are changed and evaluated each calendar quarter. Table 12 gives the local external background radiation levels measured at the West Jefferson Site during 1985.
In comparison, 1966 aeroradioactivity measurements of the region including the BMI facilities showed that the natyrgl terrestrial background for the area 4
surrounding BMI was 60 mrem / year. p 01 This number is equal to the average natural terrestrial background for the U.S.
The cosmic background for the State of Ohio is averaged to be 50 mrem / year, compared to a U.S. average of 45 mrem / year. The estimate for natural whole-body internal background is consideredtpQe25 mrem /yearfortheU.S.withonlyminorregional variations.u21 Based on the 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.
5 FACILITY DESCRIPTIONS
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The center of nuclear activities at the BMI King Avenue Site 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 the location of Building 3 in the King Avenue Site building complex.
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r At the BMI West Jefferson Nuclear Sciences Area, the major operation involved is research on the properties of irradiated materials. This work is performed in the Hot Cell Laboratory (JN-1) and involves examination and testing of irradiated reactor fuel, nuclear pressure vessel material, and fuel cladding material. The experiments serve to collect 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 locations of these nuclear facilities in the Nuclear Sciences Area building complex.
f The King Avenue Site The U-235 Processing Facility is located in Building 3 of the King Avenue Site. This facility was constructed in the mid 50's.
It served until the late 60's as an exclusion area specifically designed for the processing and storing of unirradiated enriched uranium utilized on various government and b_
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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 tha area are alarmed. The vault is used for the temporary storage of limited quantities of unirradiated enriched uranium. The area is also used for the E
receiving, storing, waste processing and packaging for shipment of source 5
materials.
The major piece 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 repro-cessor. The furnace consists of a closed system muffle and glove box com-l bination. The exhaust system for the furnace is arranged so that room 5
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 g
scrubber system which is equipped with a re-circulating water system. After g
passing through the scrubber, the washed exhaust gases 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, after being burned and cooled, are dumped into plastic bags within the glove box. The glove box is an exhausted closed 3
system and therefore the system cperating pressure is negative to the room 3
pressure. This prevents any problem of contamination in the surrounding area exterior to the system.
This calcine system can be used for the reduction to oxide of limited quanti-ties of unirradiated enriched uranium scrap. The removal of enriched uranium ash and residues from the glove box is accomplished by dumping the material 3
into a hopper built into the floor of the glove box. This drops directly into 3
a can which, when full, is removed and a lid applied and sealed for shipment.
The area is also the central gathering and packaging spot for low-level radio-active contaminated waste. The area also served as a receipt and shipping, sampling, and measurement area for shipments of both source materials and small quantities of unirradiated uranium which are to be, or have been, g
E utilized on programs being performed at the BMI King Avenue Site.
The West Jefferson Site As shown in Figure 4, there are four principal buildings at the West Jefferson E
Nuclear Sciences area:
JN-1, the Hot Laboratory; JN-2, the Administrative 5
Bui~:Ing; JN-3, a retired Research Reactor; JN-4, the Hazardous Material Lab (Rt.tred Plutonium Laboratory). Each of these facilities is described in the following paragraphs.
Hot Laboratory, JN-1 This laboratory, containing approximately 22,000 square feet of space, is con-sidered to be one of the most completely equipped such installations available to the nuclear community. The Hot Laboratory is capable of providing research and technical assistance in the areas of:
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o Power mactor fuel performance evaluations f.
e Pressure vessel irradiatiol surveillance ca'sule
~1 examinations and evaluatier.;
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-(l e Postirradiation examinatior of nuclear materials and O'f'
,B components e Radiation source encapsulation, and
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materials and structures.
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-.' s The Hot Laboratory consists of a large high energy cell and connecting pool
" !T id capable of hardl;ng complete power reactor fuel assemblies, five smaller cells,
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- e and supporting facilities. The smaller cells are the high-;evel and low-level 1 "l."
cells, the two mechanical test cells, and a segmented alpha ganma cell.
The fjZ supporting facilities include areas for cask handling, solid and liquid-waste N-
.yl disposal, contamination control, equipment decontamination, and other miscel-
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.d laneous operations.
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Administrative Building, JN-2 Y ;5 "
.n 1jg This builoing was designed and constructed for use as a critical assembly labo-Al ratory.
It was used for critical experiments from 1957 through 1963.
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the cessation of critical experiments, the facility has been used for several 1,.i nuclear related projects including direct conversion concepts, irradiation
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experiment assembly, and special nuclear materials handling. The operating P (..
id license was terminated by Battelle in 1970 when project work was ended.
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ti Offices and small laboratories are used by nuclear supporting services staff d % :.$
JlB including Section Administration, Health Physics Services, Nuclear Materials
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Accountability, Quality Assurance, and Instrument Maintenance. These activi-H[4 4
ties are the major building activities at this time. The building also iDj currently houses the vault, used for storage of special nuclear materials, and a radiochemistry laboratory utilized for the assay of routine health physics samples and low activity irndiated materials study specimens.
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Battelle Research Reactr 4.
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The Battelle Research Reactor began operations h.tober a, 1956, but those hk ::
i operations were terminated on December 31, 1974, and dismantling initiated.
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a 42 The dismantling was cunpleted without incident during 1975 and the license Q.6 5
changed to a possession only status.
Storage of waste awaiting shipment for
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burial is the only licensed activity conducted in JN-3 at this time.
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-5l Hazardous Material Laboratory, JN-4 o4 LE h.6, Q.C
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Building JN-4 was built in 1960 to house activities in plutonium research and
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processing. These operations were terminated in 1978 and dismantling was com-g pleted in 1985.
A hazardous materials study laboratory has been approved for 9
operation in JN-4.
There activities involve non-radioactive material only.
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I 10 Radiological Waste The processing of liquid waste from nuclear operations at the West Jefferson site involves the collection of contaminated liquid in holding tanks and con-centrating it using an evaporator. All laboratory sink and floor drains in the nuclear facilities are connected to holding tanks. Only office area and restroom drains are connected to the sanitary drain system.
Contaminated liquids are solidified and the solid waste shipped to a Department of Energy 3
3 Liquids which could potentially contain radioactive materials from these facilities are contained thus preventing the accidental release of radioactive materials to the sanitary sewer system. Highly contaminated liquids are mixed (remotely if required) with a solidifying agent and disposed of separately rather than being permitted to mix with large volumes of mildly contaminated E
liquids in the holdup tanks.
E Liquid wastes from the King Avenue site include solutions and, possibly, waste E
water from the U-235 processing area. All liquid waste from the U-235 process-g ing are solidified for disposal. Quality assurance procedures insure that no solution is discharged to the sewer systems without approval of the Radiologi-cal Safety Committee.
Solid radiological wastes from operations at the King Avenue site are collected, compacted if necessary, and packaged for shipment to a DOE or DOE approved 3
disposal site. Solid waste from the West Jefferson site is from many sources.
3 Examples of solid waste are the HEPA filters and disposal cartridge water fil-ters, the spent ion-exchange resins, disposal clothing or other supplies consumed and contaminated in the laboratories, and gloves from the glove boxes. The transportation of solid waste to disposal sites is performed in accordance with 49CFR and 10CFR.
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. Radionuclides in particulate form are removed from a
exhaust stack effluents by the use of high-efficiency particulate air (HEPA)
E filters. The air effluents are filtered first at the points of operations, i.e., glove boxes, hoods, test cells, and finally at the stack release point by one or two banks of HEPA filters in series. To the extent possible, radio-E active gases present in the fuel pins under examination at the Hot Cell 5
Facility are drawn off for subsequent disposal with solid wastes. The residual gases trapped in the fuel matrix or otherwise released is monitored continuously by effluent monitors.
Continuous air monitors (CAM) are located throughout the laboratory. They monitor the environmental air for alpha, beta, and gamma-emitting E
particulate matter. For each monitor, if the concentration in the stacks 5
equals or exceeds the applicable RCG level then an alarm and corresponding action is taken. Under this procedure the activity in uncontrolled areas will a
remain less than the values in 00E Order 5480.1.
(There is a discussion of g
RCGs in the Appendix of this report.)
I B
I 11 I
The hot laboratory has two separate exhaust stack systems. One for JN-1A; one for JN-18. There are two significant differences in the two systems. First, the JN-1A system consists of six individual stacks; the JN-1B system uses only one large stack. The other difference in the two exhaust systems is that the I
JN-1B system contains a large I-131 charcoal trap.
For the JN-1A stacks each stack has a complex of separate alpha and beta-gamma I
particulate CAMS, with some having gaseous effluent and Iodi'ne-131 detectors, for each individual stack. Any of the monitors can activate an alarm and shut mechanical test cell or the alpha-gamma (gh level cell, low level cell, off the exhaust fan for the individual hibasement) cell, isolating the I
particular cell.
For the JN-1B stack there are four separate CAMS, alpha particulate, beta-gamma particulate, gaseous effluent and Iodine-131. Any of the four instru-ments will activate the alarm, shut down all exhaust fans for the High Energy Cell (HEC) and close the butterfly valves so no more air can be drawn from the I
cell.
In the event that the I-131 monitor activates the alarm, two additional operations take place; an exhaust fan is started and a diversion damper opens causing any exhaust air to flow through the charcoal trap.
Although the two stack monitoring and control systems operate independently, they function on a similar basis. The alarm set point of each instrument is set at a level based upon regulatory values of Radiological Concentration Guide (RCG)
I in DOE Order 5480.1 for various radiation species in uncontrolled areas. Refer to Derived Air Concentration as standard in App.endix A-2.
Alpha particulate monitors are set on the basis of the RCG for Pu-239, beta-gama particulate monitors, on the basis of the RCG for Sr-90.
Effluent monitors are set for the I
the Kr-85m RCG. The I-131 monitor is set on the basis for that isotope.
Ventilation in the JN-2 storage vault and the radiochemistry laboratory is I
provided by separate exhaust fans that are designed and operated to maintain a negative pressure atmosphere in the vault and to provide adequate air exchange in the radiochemistry laboratory. The air exhausts for the storage vault and the radiochemistry laboratory empty into large plenums to which I
absolute filters are sealed. The exhaust stack for the storage vault is I
i equipped with alarmed continuous alpha monitoring to detect the release of any lI radioactive matter.
ENVIRONMENTAL MONITORING I
The impact of operations on the health and safety of the public is evaluated routinely by an environmental monitoring program which has been in existence
- I since 1955. The basic objective of the environmental monitoring program is to l
evaluate the effectiveness of the waste management program of all operations.
l Concentrations of radioactive and non-radioactive wastes are controlled so that effluent levels are maintained as low as reasonably achievable and well I
within applicable standards. All effluents involving potentially polluting materials are contained within the operating facilities to the extent possible and are disposed of as packaged wastes by authorized services.
lI
l 12 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 controlling airborne emissions. Eight continuous stack monitors ensure detection of any inadver-g tent release of radioactive materials and provide data for the prompt assess-g ment of the environmental impact, if any (see Figure 4). Particulate samples of the effluent are collected from each exhaust stack. The particulate samples are collected on two types of filter paper, GVB-60 and Type E glass fiber.
E The air is sampled at an average rate of 2.8 x 104 cm3/ min. The filters are 5
changed weekly, which represents average sample volume of 285.5 m3 This volume is determined to facilitate the detection of airborne activity in concentration wel.1 below regulatory standards.
Analyses are performed.on a weekly basis for gross alpha and gross beta for stacks 001 - 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 sample data. The site boundary concentrations, reportad in Tables 2 and 3, for the various exhaust stack locations were calculated by 3
multiplying the individual stack concentration by the atmospheric dispersion 3
parameter computed for the site boundary.
The site boundary atmospheric dispersion parameter was obtained using the atmos-pheric dispersion model incorporated in computer code Dacrin (see reference 8, page 22).
The cumulative average concentration of the alpha and beta mixture, emitted from stacks 001 - 004, 012, 006, 013, and 014 was less than 0.002 percent of the RCG value at the site boundary. The results are sumarized in Table 2.
E i
Based on routine monthly gama ray analyses of in-line system charcoal gas 5';
sampling cartridges installed in stacks 001 and 002 the cumulative average, concentration of iodine-131 was less than 2 x 10-9 percent of the RCG value at E
represents a weekly average sample volume of 1.3 x 103m$. x 105 cm3 the site boundary. The air is monitored at a rate of 1 3
/
This E
This volume was determined to facilitate the detection of airborne activity in concentrations well below regulatory standards.
The cumulative average concentration of Krypton-85 released from stacks 001, 002, and 013 was less than 0.00062 percent of the RCG value at the site boundary.
l The concentrations were calculated by using strip chart recorder data from the a
gaseous monitors on exhaust stacks 001, 002 and 013. The results are summar-ized in Table 2.
Identification of radionuclides in the JN-1 stack particulate emissions from stacks 001 through 004, 013, and 014 was made by monthly gama spectrometric analyses and specific radiochemistry analyses of weekly stack air sample filters composited over a 4-week period. Gama spectrometric analyses were performed using an intrinsic germanium detector coupled to a Nuclear Data Model ND66 I
E
13 multi-channel analyzer. The concentrations of the radionuclides identified were all less-than 95 x 10-7 percent of the applicable RCG values at the site boundary (see Table 3).
Supplementary air sampling was performed at four site perimeter locations during 1985 (see Figure 6). These air samples were collected 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 statistically lower than the average gross alpha and beta activities found at 6 off-site background air sampling locations surveyed weekly at distances varying 5 to 44 miles from the Nuclear Sciences Area (see page 38, Table 15).
Quarterly composite air samples from the four site boundary locations were analyzed for 238 u, 90Sr and gama emitting radionuclides. The concentrations P
were all less than 2.8 x 10-4 percent of the respective RCG values (see Table 16).
Water Radioactive A sanitary sewage system, which is operated in accordance with State of Ohio regulations under NPDES Permit 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 7
and gravel filter bed.
From the filter bed the effluent goes to a chlorinating system prior to release to Big Darby Creek.
Sampling of all liquid effluents, from the Nuclear Sciences Area to Big Darby Creek, is performed using a continuous water samp The effluents consistoftheliquiddischargefromthe2,160-ft}ingsystem. filter bed (see Figure 4).
The effluent samples are analyzed weekly for gross alpha and betg activity in suspended and dissolved fractions. Any sample exceeding 3 x 10-o pCi/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, iodine-129, strontium-90, radium-226, and radium-228 at the end of each month.
The concentrations of gross alpha and gross beta activity in suspended and dissolved fractions as well as the concentrations of specific radionuclides identified in the sample are summarized in Table 4.
In most cases the activity in the samples is due to a mixture of nuclides. The average' con-centration of the mixture was 10.60 percent of the RCG. The average concen-trations of identified radionuclides in the mixture were 0.59 percent of the RCG for iodine-129, 0.001 percent of the RCG for plutonium-238, 0.0004 percent for plutonium-239, 0.10 percent of the RCG for strontium-90, 0.14 percent of
- RCG value for unidentified radionuclides in unknown concentrations relegged to an uncontrolled area, DOE Order 5480.1, Chapter XI, Attachment XI-1. W 1
I r
14 the RCG for cesium-137, 0.33 percent of the RCG for radium-226, 1.33 percent of the RCG for the raatum-228, 0.22 percent for lead-212, and 0.13 percent for 1
uranium-235.
Ground water samples are col?ected from a sump arrangement in JN1-B. These samples are used to assure that no leak has occurred in the spent storage pool liner and that the surrounding ground water is not being contaminated.
g Results of the collected samples (presented in Table 13) show no contribution g
from JN1 activities. This was determined to be natural contributions.
The non-community drinking water supply at the West Jefferson Site is exempt E
from radiological monitor per Ohio Evnironmental Protection Agency (0 EPA)
W review.* However, weekly tap water samples are collected at the Nuclear Sciences Area to verify compliance with applicable water quality standards for E
radioactivity in drinking water. The weekly tap water samples are composited g
and analyzed monthly for gross alpha and beta activity in suspended and dissolved fractions. Any sample exceeding 1.5 x 10-8 pC1/ml for gross alpha activity receives a supplementary gama isotopic (gel 1) analysis and/or an alpha spectrometric analysis as appropriate. The average concentrations of gross alpha and gross beta activities in the dissolved and suspended fractions for 1985 were 44 percent of the EPA standard for gross alpha particle activity in the drinking water.
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 3
than 33 percent of the RCG (3 x 10 d the below dam water samples were all le in the dcwn stream water samples an 3
o pCi/ml) for release of mixed alpha and beta activity to uncontrolled areas and showed no significant difference from the upstream control sample (see Table 18). These findings show that liquid effluent releases from the site to Derby Creek did not exceed background levels of radioactivity already-present in Darby Creek.
Water Nonradioactive i
l Presently, liquid efflients discharged from the West Jefferson Facility are a
subject to the restri.tions of our National Pollutant Discharge Elimination 5
System (NPDES) Permit.
Battelle monitors and reports on a monthly basis to the Ohio Environmental Protection Agency (0 EPA). Table 5 includes a list of the parameters for which BCD is presently required to analyze and report.
I l
l
Reference:
Letter to John Pavlian from Karen H. Cooper, OEPA, dated September 20, 1983.
I
I 15 I
The data provided for the North Sanitary Sewer were obtained in accordance with the BCD NPDES Permit No. N404-CD, application number OH0005461 issued by the OEPA. The conditions of BCD's NPDES Permit were determined by the Ohio EPA following an extensive study of the Scioto River Basin, of which I
l Battelle's West Jefferson Site is a part. As the discharges are within the allowable discharge limits, the data reflect the effectiveness of BCD's waste water management.
The data listed in Table 5 represents an average of the monthly data collected during the twelve-month period commencing January 1, 1985, and ending Decem-ber 31, 1985, and are required under the limits or restrictions set forth in I
BCD's permit. The table serves to illustrate actual performance against those limits or restrictions defined in BCD's permit. Battelle has requested a renewal of the NPDES Permit and it is anticipated that approval will be forthcoming in 1986.
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 detcrmine I
whether there is uptake and concentration of radionuclides by plant or animal life. Where possible, sampling sites are chosen at maximum deposition loca-tions predicted by meterological studies. Grass and food crop (soybean or I
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 I
strontium-90. A qualitative analysis by gamma scan (GeLi) is also performed.
The results of the grass and food crop analyses are summarized in Tables 6 and 7.
The average concentration of strontium-90 detected in grass samples was I
0.6
- 0.3 pCi/g and less than 0.32 pCi/g for cesium-137. The average concentration of strontium-90 in field corn samples was 0.26
- 0.36 pCi/g and less than 0.1 pC1/g for cesium-137. Plutonium-238 and plutonium-239 average concentrations were 0.003
- 0.057 pCi/g for all samples taken of grass and I
food crops. These findings show that effluent releases from the site did not contribute any significant activity to the surrounding area.
I Sediment Radioactive Silt samples are collected semiannually at two locations; i.e., Darby Creek I
20 yards above and 20 yards below the point of sanitary effluent release to Darby Creek (sea Figure 6). The purpose of collecting silt samples is to estimate the inventory of certain radionuclides deposited in this waterway and I
document for future reference. The silt samples are collected to a depth of 2.5 cm using a 10. cm soil plugging tool fitted with a gate valve. Prior to analysis, the samples are air dried and then blended in a pulverizing mill.
I The silt samples are analyzed for plutonium-239, plutonium-238, and strontium-90. A quantitative gamma isotopic (GeLi) analysis is also performed. The results of the analyses are summarized in Table 8.
I I
I 16 Concentrations of strontium-90 in silt samples collected above the effluent E
release point averaged 0.4 + 0.4 pCi/g and 0.2 + 0.3 pCi/g below; for 5
plutonium 238, 0.02 1 0.03 FCi/g, and 0.01 1 0.U2 pCi/g, respectively and for plutonium-239, 0.01
- 0.02 pCi/g and 0.01
- 0.01 pCi/g, respectively.
m Cesium-137 averaged 0.25 pCi/g above and 0.25 pCi/g below the release point.
5 No contribution from the site for the isotopes is detectable.
Soil Radioactive Soil samples are collected annually from fourteen locations at varying dis-g tances and directions within a 5-mile radius of the Nuclear Sciences Area.
g Locations falling into the same directional quadrant from the nuclear site are composited (see Figure 5). The soil samples are collected to a depth of 2.5 cm using a 10 cm soil plugging tool. Each soil sample consists of a composite
~
of five " plugs" of soil collected at random from an area of approximately 100 m2 Prior to analysis, the composite samples are air dried and then blended in a pulverizing mill. The soil samples are analyzed for plutonium-3 238, plutonium-239, and strontium-90. A qualitative analysis by gamma scan 5
(GeLi) is also performed. The results of the analyses are summarized in Tables 9 and 10. The concentration of strontium-90 in soil samples averaged 0.1
- 0.2 pCi/g. The average concentration of plutonium-239 was 0.01
- 0.01 pC1/g and the plutonium-238 average concentration was 0.00
- 0.01 pCi/g for all soil samples collected. Gama isotopic analyses of the soil samples showed the average concentration of cesium-137 to be 0.5 t 0.1 pCi/g.
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-128, plutonium-239, and strontium-90. A E,
quantitative gama isotopic (GeLi) analyses was also performed. The results 3
of the analyses are sumarized in Table 11. Average concentrations of plutonium-239 in fish samples taken from Darby Creek were 0.01
- 0.01 pCi/g and 0.01
- 0.01 pCi/g for plutonium-238. The average concentration of strontium-90 in fish samples taken from Darby Creek was 0.4
- 0.2 pCi/g, and
<0.2 pCi/g for cesium-137. Fish taken from Battelle Lake had average concentrations of plutonium-239 and plutonium-238 of 0.00 t 0.01 pCi/g and g1 0.01
- 0.02 pCi/g, respectively. Average concentrations of strontium-90 and 5j cesium-137 in fish samples taken from Battelle Lake were 0.5 t 0.2 pCi/g and j
<0.4 pC1/g, respectively.
Background Radiation Levels The external radiation background levels at the West Jefferson site boundary are continuously monitored at 15 dosimetry stations using comercially available environmental TLD packets (see Figure 8). All TLD packets are changed and evaluated each calendar quarter. The annual average dose at the I
I
M 17 g
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n :x:-
site boundary based on the 15 dosimeter stations was 120 1 10 mrem. The
[.E N limit established for the general public is 500 mrem. This value does not
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include contributions from natural background radiation which is estimated to
. g ;j be approximately 120 mrem /yr. The results are summarized in Table 12.
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- d. [q KING AVENUE SITE p;a -
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Water Radioactive gg
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Sampling)of all liquid discharges from the Building 3 (U-235 Processing Facility sump to the Columbus municipal sewerage system is performed on a A.r '
monthly basis (see Figure 7). This discharge consists of the liquid wastes tf from the building laboratory drain systems. The building sump samples are
.f routinely analyzed for gross alpha and gross beta activities. Any sample
.d.s.
exceeding 4 x 10-7 pCi/m1* receives a gama isotopic (GeLi) analysis and/or an
%# 1 alpha spectrometric analysis as necessary.
d
@j'lh Sample analyses are performed monthly on the Building 3 sump samples. The concentrations of gross alpha and gross beta activity are summarized in Table 14. The average concentration of the mixture was less than 3.3 percent fy of the RCG for release to a public sanitary sewerage system. For averaging Shi purposes, samples below the minimum detection limit are assumed to be the EM value of the limit.
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EVALUATION OF DOSE TO THE PUBLIC 3
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Estimated Radiation Doses to the Public M O'd from Emissions from the Battelle W
West Jefferson Site During CY 1985 M..J s.ca The BCD Environmental Monitoring Report for CY 1985 presents data which hN provide information for determining those sources of environmental radiation 44 1
resulting from past or current nuclear activities and those due to atmospheric y p_..'
nuclear tests or natural radioactivity. Contributions from BCD's nuclear 4,A
$ Yi operations were undistinguishable from other sources with only two exceptions.
t These include minimal cirborne releases of mixed fission products from Hot 4.h
%j@Y ad Laboratory activities and very low concentrations of mixed fission products in liquid effluents at the West Jefferson Nuclear Sciences Area. The radio-jf.
logical impact of BCD's nuclear activities is calculated from the quantity of
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- RCG value for unidentified radionuclides in unknown concentrations released to a public sanitary sewerage system, DOE Order 5480.1, Chapter XI.
I 18 r
radionuclides measured directly in effluents from operating facilities in 1985 m
from the annual deposition of airborne radionuclides on vegetation and food g
crops, and from residual radionuclides in stream sediment from past operations.
Atmospheric Discharges Measured releases and ground level annual average concentrations at the site g
boandary during 1985 for the West Jefferson Site are summarized in Table 2.
3 The downwind position from the facility where the annual ground level concen-trations will be highest is considered coincident with the site boundary, which determines the perimeter for uncontrolled exposure. This point is on BCD property within the site boundary line. The gross beta data in Table 2 shows that the total mixed fission product releases for 1985 amounted to 2.63 pCi with a total average concentration at the site boundary of 4.46 x 10-19 s
pCi/ml. Based on isotopic analyses of the stack effluents from the JN-1 g
facility, the principal radionuclides were determined to be plutonium-239, cesium-137, lead-212, cerium-144, strontium-90, antimony-125, and uranium-235.
The total krypton-85 emission was 11.77 Ci with 9 corresponding average concentration at the site boundary of 3.24 x 10-22 pCi/ml. The total plutonium-239 emissions were 0.39 pCi. Review of JN-1 facility operation for 1985 indicates that most of the gross alpha reported was due to plutonium-239.
5 Taking the conservative approach, all the alpha emissions are considered to be-3 plutonium-239 only, with an annual average concentration at the site boundary of 6.56 x 10-20 pCi/ml. The total isotopic composition of the effluents emitted from the five stacks of the JN-1 facility was used in evaluating the off-site dose to the public.
Liquid Discharges Measured aqueous releases and effluent concentrations during 1985 for the West a
Jefferson Site are sumarized in Table 4.
The concentration values apply to g
the water discharged into Big Darby Creek after passage through a conventional leaching bed. Based on a knowledge of the isotopic composition of radio-nuclide concentrations released to the leaching bed, emissions should be due l
to very limited elution from the leach bed of contaminants that were delivered a
to the bed in the past year and a half. Therefore, the alpha activities is considered to be primarily uranium-238 and the gross beta activity is presumed a
to contain only relatively long-lived radionuclides.
g i
Estimated Radiation Dose to the Public from Atmospheric 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 programmed for localized applications, was used to generate the required X/Q data for calculating dose to the maximum individual, nearest residence and I
1 19 population groups. Thus, annual average X/Q values were developed for a series of concentric rings extending from the site boundary out to a distance to 50 miles (refer to Figure 12). The annular rings were broken down into 2
sixteen sectors corresponding to the normal wind rosa pattern (refer to
=
Figure 11).
Ccmputation of Girl Scout Camp, Nearest Residence, and Population Group Doses The annual radiation dose from gaseous and particulate radionuclides dis-charged into the atmosphere was computed for a person continuously immersed in an infinite hemispherical cloud containing the radionuclides. Tables 2 and 3 list stack release data used to estimate the Girl Scout Camp, nearest the residence and the 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 6
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 Girl Scout Camp, the nearest resident and for population a
groups from both gaseous and particulate emissions are summarized in 15 Tables 20, 21, 22, 23, and 24.
The estimated off-site doses listed in the tables are very low compared to the
]
maximum permissible exposures (MPE) which have been recommended by the ICRPl4) and other groups for the general public. The MPE values recommended for an individual are: bone - 3 rem /yr, GI tract - 1.5 rem /yr, whole body -
3 0.5 rem /yr, skin - 3 rem /yr, thyroid - 3 rem /yr, lung - 1.5 rem /yr, and i
kidney - 1.5 rem /yr. The recomended values for a population group are one-third of these values. Therefore, from Table 20 it may been seen that the largest fraction of MPE occurs to the skin and is 0.003 percent of the recomended limits at the site boundary.
In comparison, exposure of persons to natural background radiation in the area would be approximately 120 mrem /yr as measured by TLD stations. Atmospheric emissions from the site (Table 19) led to maximum estimated whole body radiation doses which are approximately 0.01 percent of that expected from natural background. The highest single emission (Kr-85) contributed only 2.6 x 10-3 percent of Maximum Permissible Exposure for skin.
Computation of the 70-Year Dose Commitment at the Girl Scout Camp and for g
Nearest Resident, Population Groups, and Integrated 50-Mile Population The 70-year dose comitments were determined by using computer Code DACRIN based on annual meteorological data (Table 32), the 1980 estimated geographic distribution of the population in the various sectors around the site out to a 4
50-mile radius (Figure 12) and the radionuclide release data given in Table 19. Summaries of the 70-year dose commitment groups are given in Tables 25, 26, 27, 28, and 30. The values given in Table 30 may be compared against the integrated person-rem dose that would be expected for the population radiationwould be expected for the population group due to natural background. Since the level of natural background radiation would be E
I 20 essentially constant over the whole area, the corresponding person-rem value is simply the product of the total population and the natural background radiation value. Using a natural background of approximately 120 mrem /yr and a total 50-mile population figure of 1.73 x 106 produces an integrated population dose from natural background of 2.08 x 105 person-rem /yr. The total body dose comitment caused by emissions from Batte11e's West Jefferson Site to the integrated 50-mile population, is less than 6.4 x 108 percent 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 swimming purposes; however, such use could be 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 sumarized in Table 4.
Only the beta releases were used in calculating the external radiation dose to potential swimers, since the less penetrating alpha emissions do not make a significant contribution to the total body dose.
Using computer Code PABLM the estimated dose to the swimmer 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 Girl Scout Camp, nearest resident, population groups and the integrated 50-mile population in Tables 21, 22, 23, 24, and 29.
Radiation Dose Due to Boating and Wat:r Skiing Big Darby Creek is too small to allow boating or other water recreation sports. Thus, there will be no dose from these activities.
l
=
l Radiation Dose from Drinking Water Water from Big Darby Creek below the outfall is not used for drinking priur to 3
its confluence with the Scioto River according to the U.S. Geological Survey; E
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 E
no estimate of the extent of this activity is available. Radiation dose to 5
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 (pCi/g dry wt.) is assumed to be directly related to the concentration of the radionuclide in the water in which the fish reside
L.
21 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 Girl Scout Camp, nearest resident, population groups, and the inte-grated 50-mile population (see Tables 21,22,23,24,and29).
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 Girl Scout Camp, show that fish consumption is expected to be the dominant exposure pathway for persons from licuid 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 resulting from liquid emissions from the site should have been approximately 8 x 10-5 percent of that produced by natural background.
70-Year Dose Commitment Tables 25, 26, 27, 28, 29, and 30 of this report provide estimated 70-year dose commitments to the Girl Scout Camp, nearest resident, population groups
=
and the 80-kilometer population from one year of exposure. Also given for terrestrial pathway exposures is the estimated 70-year accumulated dose to the maximum individual (and the 80-kilometer population from 70-years of con-tinuous exposure to the residual environmental contaulnation left by the one-year release. The radionuclide composition of effluents reported for 1985 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 DACRIN was used to estimate doses from chronic inhalation of a radioactive mixture using an atmospheric diffusion model.
Code PABLM was used to estimate doses from the chronic ingestion of a radioactive mixture through terrestrial and aquatic pathways.
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 and inhalation pathways (Table 12, page 35). The " fence port" dose for 1985 was equal to or less than the annual average TLD background reading of 120 mrem measured at off-site background monitoring stations.
Maximum Organ Dose Estimates The maximum annual organ dose for 1985, calculated at the Girl Scout Camp, is estimated as 7.77 x 10-2 mrem to the skin from Krypton-85 (Table 20, page 44).
The maximum 70-year organ dose commitments for 1985, computed at the Girl Scout Camp, were estimated as 1.41 E-2 mrem to the Lungs from the atmospheric inhalation pathway and 3.30 E-4 mrem to the bone from eating fish (Table 25, page 49).
-mism
-ims----imme-
I 22 REFERENCES (1)
U.S. Census, 1980 Population Data, Dayton, Ohio, Standard Metropolitan Statistical Area.
(2) Operational and Environmental Safety Division, Environmental Protection, g
Safety and Health Protection Reporting Requirements, DOE Order 5484.1, B
U.S. Department of Energy, Washington, DC, February 1981.
(3) Scioto River Basin Waste Load Allocation Report for the 303 (e)
Continuing Planning Process for Water Quality Management.
(4)
ICRP Publication 2, " Recommendations of the International Commission on Radiological Protection, Report of Comittee II on Permissible Dose for Internal Radiation." Pergamon Press, 1959.
(5) Operational and Environmental Safety Division, Environmental Protection.
Safety, and Health Protection Programs for DOE Operations, DOE Order 5480.1, U.S. Department of Energy, Washington, DC, May 1980.
(6)
U.S. NRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix 1."
(7) 00E/EP-0023, A Guide for Environmental Radiological Surveillance at US00E Installations, Revised July 1981.
(8)
J. R. Houston, D. L. Strenge and E. C. Watson, DACRIN - A Computer Code for Calculating Organ Dose From Acute or Chronic Radionuclide Inhalation, BNWL-B-389, PNL, Richland, WA 99352, August 1975.
(9)
B. A. Napier, W. E. Kennedy 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.
(10) Civil Effects Operations (LEX 59.4.23) Aeroradioactivity Surveys and A Real Geology of Parts of Ohio and Indiana (ARMS-1), May 1966.
(11)
" Estimates of Ionizing Radiation Doses in the United States 1960-2000",
U.S. Environmental Protection Agency, ORP/CSD 72-1.
(12) Chapter I Environmental Protection Agency, Natural Revised Primary Drinking Water Regulations, 40CFR Part 141, Federal Register /Vol 48, No. 194, October 5, 1983.
I I
I 23 Quality Assurance Several methods are used to assure that the data collected each year are I
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 that current values are consistent with previous results. This allows for timely investigation of any unusual results. Samples are collected using identical methods near to and far from the nuclear site, as well as upstream and downstream on Darby Creek, to provide for identification of any net differences that may be attributable to the West Jefferson nuclear operations. These 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 BCD environmental surveillance program are performed at the radiochemistry facility located at the West Jefferson nuclear site. Environmental samples requiring specific isotopic analysis are sent to Eberline Instrument Corporation's Albuquerque Laboratory, Albuquerque, New Mexico. Both laboratories maintain internal I
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 I
traceable to the National 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 neces-sary to perform all of the calculations are fully documented.
BCD also participates in the DOE sponsored Quality Assessment Program which is administrated by the Environmental Measurements Laboratory (EML) and 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 BCD and the results reported to DOE /EML for verification of accuracy.
I I
I I
I 24 I
TABLE 1.
POPULATION DISTRIBUTION WITHIN 10 MILE RADIUS FROM SITE Distance Radius Population 1,500 feet 0
l 2,500 feet 4
1 mile 1,200 2 miles 4,000 5 miles 10,700 10 miles 116,330 I
I I
I I
I I
I,
~
1
TA8tE 2.
SUP9tARY OF ARMOSPHERIC RADIDACTIVE D9 TIS $10NS - WEST JEFFERSON $1TE CY 1985 Stack 10-3 Per.
Number Volume Site centage of of Stack 1010 Activity MDL Range Stack Soundary(a) RCG at Site 541/m1 10-14 p/Cl/m1 10-14 pct /ml 10-19 f t/ml Soundary(b)
Species Locations Samples liters /yr p/C1/yr 10-14 Gross a 001 52 3.86 0.10 0.15
< fel-7.41 0.27 + 0.02 1.24 + 0.08 5.18 Gross 8 001 52 3.86 0.76 0.24 0.40-71.9 1.9810.06 9.1110.29 Gross a 002 52 11.85 0.13 0.15 0.007-0.30 0.11 + 0.01 0.51 + 0.07 0.44 Gross 8 002 52 11.85 0.88 0.24 0.38-2.20 0.7410.04 3.4010.20 Gross a 003 52 3.88 0.03 0.15
< pWL-0.19 0.08 + 0.01 0.31 + 0.06 I**'
Gross 8 003 52 3.88 0.22 0.24 0.05-2.27 0.5610.02 2.5810.11 Gross a 004 52 1.69 0.04 0.15
< MDL-2.57 0.21 + 0.03 0.97 + 0.16 4.65 Gross 8 004 52 1.69 0.31 0.24 0.18-14.2 1.8110.06 8.3310.30 Gross a 013 52 1.00 0.01 0.15 0.02 - 0.37 0.12 + 0.01 0.55 + 0.04 2*32 Gross 8 013 52 1.00 0.09 0.24 0.06 - 3.23 0.8910.03 4.0910.14 Gross a 014 52 2.00 0.06 0.15
<let-9.24 0.31 + 0.02 1.43 + 0.09 3.22 Gross 8 014 52 2.00 0.22 0.24 0.11 - 10.0 1.0910.04 5.0110.20 m
vi Gross e 012 52 2.48 0.012 0.15
< pWL-0. 28 0.05 + 0.03 0.23 + 0.14 1.20 Gross 8 012 52 2.48 0.12 0.24 0.03-0.82 0.4710.03 2.1610.14 Gross a 006 52 0.38 0.005 0.15
< MDL-0.41 0.14 + 0.02 0.64 + 0.09 2.23 Gross 8 006 52 0.38 0.03 0.24 0.23-2.06 0.8310.03 3.8210.14 Stack Volvme Site Emis-1010 Activity pel Range Stack Boundary (a)
Gaseous sions liters /yr pCl/yr pCl/mi 10-5 pct /mi 10-9 pCl/e1 10-13 pCl/m3 (c) 1311 001 10Ld) 3.86 0.002 0.009x10-14
<tel
<f4DL 311 002 10i d) 11.85 0.01 0.009:10-14
< IIDL
< MDL gNr 001 el 3.86 1.29x106 0.02x10-8 0.04-3.09 33.5 15.4 85 r 002 el 11.85 9.96x106 0.02x10-8 0.02-8.09 83.7 38.5 K
85Kr 013 (ej 1.00 5.16x105 0.02x10-8 0.02-9.87 51.6 23.7 (a) Site boundary concentrations were calculated by multiplying stack concentrations by the atmospheric dispersion parameter computed for the site boundary usin computer code DACRIN (See reference 9. Page 24)0 (b). RCG - for mixed alpha and beta activity, 2 m $0-14 pCl/ml; 85 r 3 x 10-1 pCi/ml; 131g 1 x 10-1 pCi/m1, K
c Range base on monthly average, d Iwo additional months estimated at fet. based on monthly strip chart.
85 r concentration calculated by evaluation of data on strip chart recorder used with gaseous stack monitor.
(e)
K
l l
TA8LE 3.
GAfmA EMITTING RADIONUCLIDES IDENTIFIED IN THE JN-1 (HOT LAB) STACK EMISSIONS CY 1985 10-7 Percentage Stack Composite Volume Site of (d) RCG (a)
Location Stack (b) 1010 Activity IOL Range Stack Boundary (a) at Sitg Species Figure 4 Samples liters /yr pct /yr pC1/m1 p/CIMI 10-15 pCIA1 10-19 pCIAI 80undaryta) 212Pb 001 12 3.86 0.34 1.40x10-14
< MDL
< 8.75 + 1.18
< 4.03 6.71 002 12 11.85 0.95
< MDL
< 8.00 T 0.82
<0.37 0.61 003 12 3.88 0.34
<MDL
<8.87 T 1.88
< 4.08 6.80 004 12 1.69 0.09
< MDL
<5.62 I 16.6
< 2.59 4.31 013 12 1.00 0.08
<let
<8.12 7 2.08
<3.74 6.23 014 12 2.00 0.13
< MDL
- 6.5911.84
< 3.03 5.05 137 s 001 12 3.86 0.37 7.02x10-15
< MDL-9,70x10-14 < 9.56 + 2.06
< 4.40 0.68 C
002 12 11.85 0.90
< MDL-1.20x10-14 < 7.58 T 1.14
< 3.49 0.70 14 <6.12 71.06
< 2.82 0.56
< MDL-0.78x1014 < 16.5 T 4.95 003 12 3.88 0.24
- MDL-4.90ml0-
<7.59 1.52 004 12 1.69 0.28 013 12 1.00 0.05
< MDL
<5.13 7 1.30
< 2.36 0.47 014 12 2.00 0.13
- MDL-7.40ml0-15 < 6.53 7 0.94
< 3.00 0.60 2350 001 12 3.86 0.27 1.05 E-14
< MDL
< 6.92 + 0.81
< 3.18 79.6 002 12 11.85 0.70
<MDL
< 5.94 T 1.14
<2.73 68.3 003 12 3.88 0.21
<MDL
<5.54 7 1.45
< 2.55 6.37 004 12 1.69 0.14
<MDL
<8.27 T 16.7-
< 3.81 95.1 013 12 1.00 0.07
<MDL
< 7.18 T 1.18
< 3.30 82.5 014 12 2.00 0.13
<MDL
< 6.6917.41
< 3.08 76.9 144Ce 001 12 3.86 1.45 4.95x10-14
<MDL
<37.6
<17.3 8.65 002 12 11.85 4.35
<MDL
< 36.7 + 2.6
<!6.9 8.44 003 12 3.88 1.46
<MDL
<37.6 -
<17.3 8.65 004 12 1.69 C.63
<MDL
<37.5
<!8.3 8.63 013 12 1.00 0.38
<MDL
<37.5
<17.3 8.63 014 12 2.00 0.75
<MDL
<37.5
<!?.3 8.63 125Sb 001 12 3.86 1.11 1.56 E-14
<MDL-1.80x10-13 <28.7 + -0.8
<13.2 1.47 002 12 11.85 2.32
<MDL
< 19.6 -
<9.02 1.00 003 12 3.88 0.56
<MDL
<14.4
<6.63 0.74 004 12 1.69 0.25
<MDL
<l4.6
<6.72 0.75 013 12 1.00 0.42
<MDL-1.80 E-13 542.4 + 1.6
<19.5 2.17 014 12 2.00 0.34
<MDL-7.26 E-14
- 17.2 ~
- 7.91 0.88 (a) (hly those radionuclides which contributed to critical organ doses to the maximum individual greater'than 1 x 10-10 res/yr are Itsted.
r (b) Identification of radionuclides in stack particulate emissions was by gamma spectrometric analysis of stack particulate air filters.
(c) Site boundary concentrations were calculated by multiplying stack concentration by the atmospheric dispersion parameter computed for the sitt boundary using computer code DACRIN (see reference 9. page 24).
(d) RCG: 212 Pb 6 x 10-10; 137Cs 5 x 10-10 pC1/ml; 235u 4 x 10-12 pCi/m1; 144Ce 2 x 10-10 pCl/ml; 9 x 10-10 pCl/el.
E E
E E
E E
E E
E E
E E
E E
E E
E E
w-.
TABLE 4.
SupmARY OF LIQUID RADI0 ACTIVE EMISSION - WEST JEFFERSON SITE (MEASURE OF EFFLUElji FR(M SANITARY SEWERAGE SYSTEM INTO BIG DARBY CREEK - FIGURE 4. DESIGNATION 010)La)
CY 1985 Average Number of
- Activity, FM.,
Range Conctntration RCG Percentage Species Samples pCf/yr 10-o pC1/mi 10-8 pC1/mi 10-0 pCi/ml 10-8 pCf/mi of RCG Gross a 52 28.72 0.1
< MDL-1.69
< 0.43 10.06 2010(C) 10.60 Gross 8 52
-42.08 0.16
< MDL-1.02
< 0.6310.08 90 r 12 2.00 0.10
< MDL
< 0.03 10.07 30 0.10 S
238 u 12 0.33.
0.01
< MDL
<0.005 10.004 500 0.001 P
239 u 12 0.13 0.01
< MDL
< 0.002 10.004 500 0.0004 P
137 s 12 180.36 3.4
< MDL
< 2.7010.37 2000 0.14 y
C 129g 12 2.00 0.1
< MDL
< 0.03 10.14 6
0.50 226 a 12 0.67 0.01
< MDL-0.04
< 0.01 10.003 3
0.33 R
228 a 12 2.67 0.01
< MDL
< 0.04 10.05 3
1.33 R
212Pb 12 299.26 8.0
< MDL
< 4.48 10.93 2000 0.22
~
235U 12 266.53 6.0
< MDL
< 3.99 10.62 3000 0.13 (a) Annual average flow in Big Darby Creek = 429 cu ft/sec - 3.82 x 1011 11ters/yr. Total volume of liquid effluent discharge = for Cy 1985 = 6.68 x 106 liters.
(b) Isotopic data for effluents released at this location were obtained from monthly composite samples.
(c) RCG - Mixture of alpha and beta activity; 3 x 10-8 pCl/ml. (If it is known that 1291, 226 a, and 228 a are R
R not present, the Ilmiting value of 1 x 10-7 pC1/mi may be used.) See Appendix.
TABLE 5.
NONRADIOLOGICAL SAMPLING FOR WEST JEFFERSON SITE January 1,1985 to December 31, 1985 Permit Requirements (d)
Discharge Limitations North Sanitary System Sewer (c)
Loading Concentration
'Da Ko/Davle)
Other Units UK Avg.
Max.
Min.
Avg.
30 Day Daily 30 Day Daily (b)
(b)
Flow Rate (ga./ day) 4621 7200 3323 0.5 Residual Chlorine (ag/1)
.5 1.0 0.1
.0087 6.0 to 9.0 pH Value (S.U.)
/.44 8.15 7.27 200 400 Fecal Collform (#/100 ml) 219.6 2600 0
Total Suspended Solids (og/1)
.7 3.0 0.0
.0122 0.49 0.99 10 20 90 Temperature ('F)
(a)
(a)
(a) 8.0.D. (5 day) (Mg/l) 4.1 4.8 3.3
.0717 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 NPDES Permit #404-CD.
(e) Flow rate 0.013 mgd.
M M
M M
M M
M M
M M
M M
M M
M
l_
l l
l l
TABLE 6.
SUPMARY OF GRASS ANALYSES CY 1985 l
l Location (a)
Number of Direction and Distance Composite pC1/q dry wt.(b) from Nuclear Science Area)
Samples 90 r 238 u 239 u 137 s I
S P
P C
l North Quad 6.4 km (4.0 miles) 2 0.6 1 0.3 0.01 t 0.01 0.00 t 0.01 0.4 l
8.0 km (5.0 alles) l East Quad 1.6 km (1.0 elles) 3.2 km (2.0 miles) 6.4km(4.0 miles) 5 0.6 1 0.3 0.01 t 0.03 0.00 t 0.01 0.3 7.2 km (4.5 alles) 8.0 km (5.0 miles)
SouthQuad0.8kmI;0.5 miles;'
2 0.5 1 0.2 0.00 t 0.01 0.00 t 0.01 0.2 3.1 km 1,1.9 allesJ West Quad 4.8 km (3.0 miles 6.4 km 4.0 miles 3
0.9 1 0.3 0.01 1 0.02 0.01 1 0.01 0.3 8.0 km 5.0 alles 2
0.6 1 0.3 0.01 1 0.03 0.00 t 0.01 0.4 On Site Note: No standards for radionuclides in grass have been established.
(a) Locations are shown in Figure 5.
Minimum Detection Limit for 90 r in grass is 0.2 pCi/g dry wt.
(b)
S Minimum Detection Limit for 238Pu and 239Pu in grass is 0.01 pCi/g dry wt.
Minimum Detection Limit for 137 s in grass is 0.2 pCl/g dry wt.
C
TABLE 7.
SlM1ARY OF F000 CROP ANALYSES CY 1985 Type Location (a)
Number of of (Distance from Composite DC1/q dry wt.(b)
Samples Quadrant Eclear Sciences Area)
Samples 90 r 238 u 239 u 137 s S
P P
C Field Corn West 0.74 km (2400 feet) 2 0.1 + 0.2 0.00 + 0.01 0.00 + 0.01 0.1 West 3.2 km (2.0 alles)
Field Corn North 4.0km[2.5 miles 2
0.0 + 0.2 0.00 + 0.01 0.00 + 0.01 0.1 North 8.0 km (5.0 miles Field Corn South 4.0km(1.5alles) w South 6.4 km 4.0 miles 3
0.5 + 0.3 0.00 + 0.01 0.00 + 0.01 0.1 o
South 8.0 km 5.0 miles Field Corn East 8.0 km 5.0 miles 2
0.2 + 0.2 East 4.0 km 2.5 miles 0.00 + 0.01 0.00 + 0.01 0.1 Field Corn On Site 1
0.5 1 0.9 0.00 1 0.01 0.00 1 0.01 0.1 Note: No standard for radionuclides in food crops have been estabitshed.
(a) Locations are shown in Figure 5.
Minimum Detection Limit for 90 r in food crops in 0.2 pC1/g dry wt.
(b)
S 239 u in food crops in 0.01 pCl/g dry wt.
Minimum Detection Limit for 238 u and P
P Minimum Detection Limit for 137 s in food crops is 0.1 pC1/g dry wt.
C
31 I
TABLE 8.
SUMMARY
OF SILT ANALYSES CY 1985 Location (b)
Number of PCi/g dry wt.(a)
I Figure Samples 90 r 238Pu 239Pu 137Cs S
A (20 yd above 2
0.4 + 0.4 0.02 + 0.03 0.01 + 0.02 0.25 outfall) outfall) 0.01 + 0.01 0.25 B(20ydbelow 2
0.2 + 0.3 0.01 + 0.02 Note: No standards for radionuclides in silt have been established.
Minimum Detection Limit for 90 r and 137 s in silt is 0.2 pCi/g and 0.25 S
C (a) pCi/g dry wt. respectively.
239 u in silt is 0.01 pCi/g dry wt.
Minimum Detection Limit for 238 u and P
P (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.
I I
I I
TABLE 9.
SupMARY OF SOIL ANALYSES FOR SPECIFIC RADIONUCLIDES CY 1985 Location (a)
Number of (Direction and Distance from Composite pCi/a' dry wt.(b) the Nuclear Science Area)
Samples 238 u 239 u 90 r P
P S
North Quad 6.4 km 4.0 miles 8.0 km 5.0 alles 0.02 + 0.01 0.0 + 0.2 2
0.00 + 0.01 East Quad 1.6km(1.0elles) 3.2 km (2.0 alles) 6.4 km 4.0 miles 5
0.01 + 0.02 0.01 + 0.01 0.3 + 0.3 7.2 km 4.5 miles 8.0 km 5.0 alles South Quad 0.8 km (0.5 miles) 2 0.00 1 0.01 0.01 1 0.02 0.3 1 0.2 3.1 km (1.9 miles)
West Quad 4.8 km (3.0 alles) 0.0 + 0.3 6.4 km (4.0 alles 3
0.00 + 0.01 0.00 + 0.01 8.0 km (5.0 alles) 2 0.00 1 0.01 0.00 1 0.01 0.0 1 0.2 On Site Note: No standards for radionuclides in soll have been established. The Environmental Protection Agency's proposed federal radiation protection guldgnce for exposures to transuranium elements in the environment has recommended a reference level of 0.2 pC1/mi for soll contamination.
(a) Locations are shown in Figure 5.
(b) Minimum Detection Limit for 238 u and 239 u in soll is 0.01 pC1/g dry wt.
P P
Minimum Detection Limit for 90Sr in soil is 0.2 pCi/g dry wt.
TABLE 11. SIM1ARY OF FISH ANALYSES CY 1985 i
Number of Period of Composite pCi/o dry wt.(b)
Location (a)
Collection Samples 238 u 239 u
'137 s 90 r P
P C
S Darby Creek ist quarter (c)
Battelle Lake 1st quarter (c)
Darby Creek 2nd quarter 1
0.00 + 0.01 0.01 + 0.01
< 0. 2 0.6 + 0.2 Battelle Lake 2nd quarter 1
0.0110.01 0.0010.01
< 0.6 0.510.2 Darby Creek 3rd quarter 1
0.01 + 0.02 0'.00 + 0.01
< 0. 2 0.3 + 0.2 Battelle Lake 3rd quarter 1
0.0110.01 0.0010.01
< 0.2 0.410.2 Darby Creek 4th quarter 1
0.01 + 0.01 0.00 + 0.01
< 0.2 0.2 + 0.2 Battelle Lake 4th quarter 1
0.0110.01 0.0010.01 2.6 + 0.7 0.610.2 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 ft. downstream from the sanitary outfall. (See Figure 6).
(b) Minimum Detection Limit for 90Sr in fish was 0.2 pCi/g dry weight, 0.2 pCi/g dry weight 137 s, and 0.01 C
pC1/g dry weight for 238Pu and 239 Pu.
(c) No fish samples were collected during the first quarter of CY 1985.
TABLE 10. SupMARY OF GMMA ISOTOPIC ANALYSIS OF SOIL SAMPLES CY 1985 Location (Direction and Distance from the Nuclear Science Area)(a)
North Quad East Quad South Quad idest Quad 6.4 km (4.0 alles) 1.6 km (1.0 alles) 0.8 km (0.5 miles) 4.8 km (3.0 miles) 8.0km(5.0alles) 3.2 km 2.0 alles) 3.1 km (1.9 miles) 6.4km(4.0 miles) 6.4 km 4.0 miles) 8.0 km (5.0 alles) 7.2 km 4.5 miles) 8.0 km (5.0 miles)
On Site O
Number of Composite 2
5 2
3 2
Samples Nuclide Average Concentration pCi/g (dry) wt.(b) 137 s 0.4 1 0.1 0.5 1 0.1 0.4 1 0.1 0.6 1 0.1 0.4 1 0.1 C
Note: No standards for radionuclides in soll hae been established.
(a) Locations are shown in Figure 5.
(b) Minimum detection limit for 137 s (in pCi/g dry wt.) is 0.1.
C M
M M
M M
I 35 TABLE 12.
INTEGRATED EXTERNAL BACKGROUND RADIATION MEASUREMENTS AT RECREATION AREA AND PROPERTY B0UNDARY LINE -
WEST JEFFERSON SITE - CY 1985 Location and Integrated TLD Measurements in Rem Total Distance (a) 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
for Year Southwest 400 ft 0.030 0.030 0.030 0.030 0.120 I
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 I
500 ft 0.030 0.030 0.030 0.030 0.120 2070 ft 0.030 0.030 0.030 0.030 0.120 Southeast 1200 ft 0.030 0.030 0.030 0.030 0.120 3300 ft 0.030 0.030 0.030 0.030 0.120 South 1200 ft 0.030 0.030 0.030 0.030 0.120 I
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 1299 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 0.030 0.120 (a) Refer Figure 8.
Average off-site background for year 0.120 Rem.
I I
r TABLE 13. CONCENTRATION OF RADIOACTIVITY IN GROUND WATER WEST JEFFERSON SITE CY 1985 Concentration er of
- Activity, Range,(a)
- Average, Percent Nuclide Location les pCi/yr 10-8 pCi/ml 10-8 pCi/ml of RCG(b)
Gross a JN1 Sump 7
720.0 0.05-4.01 0.22 M
Gross 8 JN1 Sung 7
922.0 1.39-3.%
3.08(C)
(a) Minimum Detection Limit (MDL) for: gross alpha: 2.5 x 10-9 pCi/al; gross beta: 4.0 x 10-9 pCi/m1.
(b) RCG - Mixture of alpha and beta activity: 400 x 10-9 pCi/ml.
(c) Gamma analysis shows this to TL-208.
M M
M M
M M
M M>
M M
[ r.:.r.*
'l;. ;,,
.,x_.
J
.. ~.s
.- l (; 9 l
6.
TABLE 14. CONCENTRATION OF RADIDACTIVITY IN LIQUID DISCHARCES TO COLUM8CSi4UNICIPAL SANITARY SEWAGE SYSTEM CY 1985 Concentration Location Number of
- Activity, Range,LaJ
- Average, Percent Nuclide Figure 7 Samples pCi/yr 10-9 g41/mi 10-9 pCi/mi
.of RCG(b)
Gross a 005 12 720.0 MDL-943 3.68 1 0.22 3.25 Gross S 005 12 922.0 4.13-22.0 9.30 1 0.14 (a) Minimum Detection Limit (MDL) for: gross alpha: 2.5 x 10-9 pCi/ml; gross beta: 3.9 x 10-9 pCi/ml.
(b) RCG - Mixture of alpha and beta activity: 400 x 10-9 pCi/ml.
1 C
l l
4 38 TABLE 15.
SUMMARY
OF' SITE BOUNDARY AIR SAMPLE ANALYSES l
FOR GROSS RADIOACTIVITY - CY 1985 s
I Location (a)
Direction and Distance Number of 10-15 uCi/m1(b) from Nuclear Sciences Area Samples Gross a(c)
Gross B(c)
North Quadrant Station (450 ft. North of JN d Stacks) 52 0.00 t 0.56 0.00
- 0.87 East Quadrant Station (400 ft. East of JN-1 Stacks) 52 0.00 t 0.56 0.00 t 0.92 South Quadrant Station E
(750 ft. South of JN-2 Stacks) 52 0.00
- 0.62 0.00 t 0.87 5
West Quadrant Station (400 ft. West of JN-2 Stacks) 52 0.00 t 0.56 0.00 t 0.87 (a) Locations are shown in Figure 6.
(b) Minimum Detection Limit for gross a is 5.73 x 10-17 pCi/m1, and 4.0 x 10-1/ pC1/ml for gross B.
(c) The values shown for gross a and gross S indicate site boundary concentrations above background concentrations found at off-site air monitoring stations. See Table 17.
1 I
I I
I I
I I
i I
TABLE 16. SUPMARY OF SITE BOUNDARY AIR SAMPLE ANALYSES FOR SPECIFIC RA010NUCLIDES CY 1985 Location (a)
Number of 10-16 uC1/m1(b)
Direction and Distance Composite 90 r 238 u 239 u 137 s 144 e S
P P
C C
from Number Sciences Area.
Samples North Quadrant Station (450 ft. North of JN-4 stacks) 4 0.60 1 0.87 0.01 1 0.12 0.01 1 0.04
<MDL
< MDL l
East Quadrant Station 8
(400 ft. East of JN-1 stacks) 4 1.35 1 1.48 0.02 1 0;08 0.02 1 0.05
< MDL
< MDL South Quadrant Station (750 ft. South of JN-2 stacks) 4 0.23 1 1.16 0.04 1 0.30 0.01 1 0.29
< MDL
< MDL West Quadrant Station (400 ft. West of JN-2 stacks) 4 1.36 1 1.41 0.04 1 0.08 0.17 1 0.12
< MDL
< M)L 2
i (a) Locations are shown in Figure 6.
pCl/ml, 238 u 2 x 10-21 pC1/m1, (b) Minimum detection limit for 90 r is 7 x 10-20 P
S 144 e 2.16 x 10-15, 239 u 2 x 10-21 pCi/m1, 137 s 3.84 x 10-16 pC1/ml, and P
C C
l I
I 40 TABLE 17.
SUMMARY
OF 0FF SITE AIR SAMPLE ANALYSES E
CY 1985 W
E Location (a)
Direction and Distance Nu11ber of 10-14 uCi/m1(b) from Nuclear Sciences Area Samples Gross a Gross S Grandview (17.8 km east) 61 0.72 0.13 3.25* 0.09 Chesapeake (24.4 km east) 60 0.61 t 0.06 2.71t 0.08 Fairgrounds E
(24.8 km northeast) 61 0.78 t 0.05 2.38 t 0.07 5
Newark (70.8 km northeast 61 0.68 t 0.10 3.12 t 0.08 Grove City (14.5 km southeast) 59 0.61
- 0.05 2.95* 0.08 New Rome (8.0 km east) 59 0.59
- 0.05 2.851 0.08 (a) Locations are shown in Figure 10.
(b) Minimum De etion Limit for gross a is 8.0 x 10-17 pCi/ml and l
1.90 x 10-pCi/ml for gross S.
I I
I I
l
_I I
I
41 t
TABLE 18.
SUMMARY
OF ENVIRONMENTAL WATER SAMPLE ANALYSES CY 1985 L
tocation(a)
Direction and Distance Number of 10-9 pCi/m1(b) from Nuclear Sciences Area Samples Gross a Gross B Darby Creek Upstream l
(18.3 m above sanitary outfall) 52 14.7 1 1.68 8.31 1 1.47 Darby Creek Downstream l
(18.3 m below sanitary outfall) 52 3.27 1 0.99 6.57 1 0.50 1
Darby Creek Downstream (186.3 m below sanitary outfall) 52 3.50 1 1.05 6.41 1 0.52 L
Battelle Lake Spillway B
(18.3 m below dam) 52 2.40 + 0.88 5.77 + 0.47 (a) Locations are shown in Figure 6.
l (b) MinimumDgtectionLimitforgrossais1x10-9 pCi/ml and 1.6 x 10- pCi/mi for gross S.
!I t
i I
lI I
L
I 42 TABLE 19. RADIONUCLIDE COMPOSITION OF BCL EFFLUENTS - CY 1985 West Jefferson Site Air Activity (uCi)
Gross Alpha 0.53 Gross Beta 3.45 Plutonium-239 0.60 Strontium-90 0.35 Cesium-137 2.36 Lead-212 2.12 Lead-214*
2.33 Bismuth-214*
2.63 Cerium-144 10.10 Antimony-125 6.40 Krypton-85 11253400.00 Uranium-235 1.84 Potassium-40*
26.60 Thallium-208 3.12 Water Activity (uC1)
Gross Alpha 28.67 3
Gross Beta 42.30 g
Iodine-129 1.72 Strontium-90 1.67 Plutonium-238 0.33 Plutonium-239 0.11 Radium-226 0.67 Radium-228 2.79 E
Lead-212 299.37 5
Bismuth-214*
579.37 Potassium-40*
3287.76 Cesium-137 180.43 Lead-214*
545.95 Thallium-208 61.81 Uranium-235 266.63 King Avenue Site Water Activity (uC1)
Gross Alpha 485.76 Gross Beta 1227.6
- Lead-214, bismuth-214 and potassium-40 are naturally occurring radionuclides which were part of the total effluent composition.
I I
l O
I 43 I
I TABLE 20. SUtf4ARY OF ANNUAL RADIATION DOSE TO THE GIRL SCOUT CAMP, NEAREST RESIDENT AND POPULATION GROUPS FROM RELEASES OF KRYPTON-85 DURING CY 1985 I
Critical Dose to the Girl Scout Camp Organ (0.500kM)
Total Body 1.30 x 10-2 mrem /yr Skin 7.77 x 10-2 mrem /yr I
Dose to the Nearest Resident (0.800 Km NW)
Total Body 4.48 x 10-3 mrem /yr Skin 2.69 x 10-2 mrem /yr Dose to the Nearest Population Group (Darby Estates, Population 3,000)
Total Body 6.08 x 10-3 person-rem /yr Skin 3.64 x 10-2 person-rem /yr I
Dose to the Population Group (West Jefferson, Population 6,000 Total Body 1.11 x 10-3 person-rem /yr Skin 6.67 x 10-3 person-rem /yr I
lI I
lI
I TABLE 21. ANNUAL DOSE TO THE GIRL SCOUT CAMP FROM EFFLUENTS RELEASED DLRING CY 1985 l
Dose (ares /yr)
Whole Pathway Body Gl(a)
Thyroid Kidneys Bone Lungs Airborne (inhalation) 1.10 E-5 3.23 E-5 1.73 E-8 3.58 E-5 9.58 E-5 5.85 E-3 g
Airborne (Ingestion) 1.90 E-7 2.00 E-8 6.00 E-10 2.50 E-7 4.10 E-7 2.70 E-8 Eating Fish 9.60 E-5 2.70 E-7 6.80 E-7 6.50 E-5 9.80 E-5 1.40 E-5 Aquatic Recreation 8.60 E-10 8.60 E-10 8.60 E-10 8.60 E-10 8.60 E-10 8.60 E-10 2
j (a) Gastrointestinal tract (lower large intestine).
I i
m M
M M
M M
M M
M -M M
M M
M M
W M
M M
m WN~M M
M M
M M~
W W '
W M -~N i
TABLE 22. ANNUAL DOSE TO THE NEAREST RESIDENT (0.8 KM NW) FROM EFFLUENTS RELEASED DURING CY 1985 Dose (ares /yr) l Whole Pathway Body GI(a)
Thyroid Kidneys Bone Lungs l
Airborne (Inhalation) 3.81 E-6 1.12 E-5 5.98 E-9 1.24 E-5 3.33 E-5 2.03 E-3 Airborne (ingestion) 1.90 E-7 2.00 E-8 6.00 E-10 2.50 E-7 4.10 E-7 2.70 E-8 Eating Fish 9.60 E-5 2.70 E-7 6.80 E-7 6.50 E-5 9.80 E-5 1.40 E-5 Aquatic Recreation 8.60 E-10 8.60 E-10 8.60 E-10 8.60 E-10 8.60 E-10 8.60 E-10 (a) Gastrointestinal tract (lower large intestine).
i d
1 TABLE 23. ANNUAL DOSE TO THE NEAREST POPULATION GROUP (DARBY ESTATES)
FROM EFFLUENTS RELEASED DURING CY 1985 4
Dose (Person-res)(b)
Whole Pathway Body GI(a)
Thyroid Kidneys Bone Lungs Airborne (inhalation) 5.16 E-6 1.51 E-5 8.10 E-9 1.68 E-5 4.50 E-5 2.75 E-3 Airborne (ingestion) 5.70 E-7 6.00 E-8 1.80 E-9 7.50 E-7 1.23 E-6 8.10 E-8 Eating Fish 8.70 E-4 3.10 E-7 3.30 E-6 2.34 E-4 9.90 E-4 7.80 E-5 Aquatic Recreation 2.58 E-9 2.58 E-9 2.58 E-9 2.58 E-9 2.58 E-9 2.58 E-9 (a) Gastrointenstinal tract (10wer large intestine).
(b) Population affected: 3000.
m a
e e
M M
M M
M M
M M
M M
M W
W W
M
M M
M m
W W
W M
M W
m m
m W
-maam 1
i TA8LE 24. ANNUAL DOSE TO THE POPULATION GROUP (WEST JEFFERSON)
FROM EFFLUENTS RELEASED DURING CY 1985 Dose (Person-res)(b)
Whole Pathway Body GI(a)
Thyroid Kidneys Bone Lungs l
Airborne (inhalation) 4.83 E-7 2.77 E-6 7.41 E-10 3.11 E-6 4.26 E-6 5.16 E-4 Airborne (ingestion) 1.14 E-6 1.20 E-7 3.60 E-9 1.50 E-6 2.46 E-6 1.62 E-7 Eating Fish 5.76 E-4 1.62 E-6 4.08 E-6 3.90 E-4 5.88 E-4 8.40 E-5 Aquatic Recreation 5.16 E-9 5.16 E-9 5.16 E-9 5.16 E-9 5.16 E-9 5.16 E-9 (a) Gastrointestinal tract (lower large intestine).
(b) Population affected: 6000.
1
)
TABLE 25. 70 YEAR DOSE COMMITMENT FOR THE GIRL SCOUT CAMP FROM EFFLUENTS RELEASED DURING CY 1985 Dose (Rem)
Whole Pathway Body GI(a)
Thyroid Kidneys Bone Lungs Airborne (inhalation) 3.69 E-7 3.26 E-8 1.73 E-Il 1.41 E-6 7.46 E-6 1.41 E-5 Airborne (ingestion) 6.00 E-10 2.00 E-11 6.20 E-13 3.10 E-10 2.30 E-9 5.00 E-11 Eating Fish 2.90 E-7 2.70 E-10 1.10 E-9 7.80 E-8 3.30 E-7 2.60 E-8 Aquatic Recreation 8.60 E-13 8.60 E-13 8.60 E-13 8.60 E-13 8.60 E-13 8.60 E-13 Airborne (ingestion)(b) 3.30 E-9 2.00 E-Il 4.90 E-12 4.10 E-10 1.30 E-8 5.30 E-11 f
(a) Gastrointestinal tract (lower large intestine).
(b) 70-year accumulated dose.
M M
W M
W W
W W
W W
M M
M M
M M
W W
m
n M
M M
O Fl --
WN fU N U~
TABLE 26. 70 YEAR DOSE C091ITMENT FOR THE NEAREST RESIDENT (0.8 KM W) FROM EFFLUENTS RELEASED DURING CY 1985 l
l Dose (Rem)
Whole Pathway Body GI(a)
Thyroid Kidneys Bone Lungs Airborne (inhalation) 1.28 E-7 1.13 E-8 5.93 E-12 4.88 E-7 2.58 E-6 4.88 E-6 Airborne (ingestion) 6.00 E-10 2.00 E-Il 6.20 E-13 3.10 E-10 2.30 E-9 5.00 E-11 g Eating Fish 2.90 E-7 2.70 E-10 1.10 E-9 7.80 E-8 3.30 E-7 2.60 E-8 Aquatic Recreation 8.60 E-13 8.60 E-13 8.60 E-13 8.60 E-13 8.60 E-13 8.60 E-13 Airborne (ingestion)(b) 3.30 E-9 2.00 E-11 4.90 E-12 4.10 E-10 1.30 E-8 5.30 E-11 (a) Gastrointestinal tract (lower large intestine).
(b) 70-year accumulated dose.
l l
l l
1 l
l 4
=
TABLE 27. 70 YEAR DOSE COP 9tITMENT FOR THE NEAREST POPULATION GROUP (DARBY ESTATES) FROM EFFLUENTS RELEASED DURING CY 1985 I
I I IE I
I I
II El I II I'm i I E HI I Dose (Person-rem)(b)
Whole Pathway Body GI(a)
Thyroid Kidneys Bone Lungs Airborne (inhalation) 1.73 E-4 1.53 E-5 8.10 E-9 6.60 E-4 3.48 E-3 1.00 E-2 Airborne (ingestion) 1.80 E-6 6.00 E-8 1.86 E-9 9.30 E-7 6.80 E-6 1.50 E-7 8
Eating Fish 8.70 E-4 8.10 E-7 3.30 E-6 2.34 E-4 9.90 E-4 7.80 E-5 Aquatic Recreation 2.58 E-9 2.58 E-9 2.58 E-9 2.58 E-9 2.58 E-9 2.58 E-9 Airborne (ingestion)(c) 9.90 E-6 6,00 E-8 1.47 E-8 1.23 E-6 3.90 E-5 1.59 E-7 (a) Gastrointestinal tract (lower large intestine).
(b) Population affected: 3000.
l (c) 70-year accumulated dose.
l l
l
m m
m m
m W
W W
W W
W W
W W
W W
W M
M TABLE 28. 70 YEAR DOSE COP 91ITMENT FOR THE POPULATION GROUP (WEST JEFFERSON)
FROM EFFLUENTS RELEASED DURING CY 1985 1
Dose (Person-rem)(b)
Whole Pathway Body Gl(a)
Thyroid Kidneys Bone Lungs t
Airborne (inhalation) 1.58 E-5 2.80 E-6 7.41 E-10 1.21 E-4 3.21 E-4 1.21 E-3 Airborne (ingestion) 2.60 E-6 1.20 E-7 3.72 E-9 1.86 E-6 1.38 E-5 3.00 E-7 g
Eating Fish 1.74 E-3 1.62 E-6 6.60 E-6 4.68 E-4 1.98 E-3 1.56 E-4 Aquatic Recreation 5.16 E-9 5.16 E-9 5.16 E-9 5.16 E-9 5.16 E-9 5.16 E-9 i
Airborne (ingestion)(c) 1.98 E-5 1.20 E-7 2.94 E-8 2.46 E-6 7.80 E-5 3.18 E-7
'i l
(a) Gastrointestinal tract (lower large intestine).
.I i
(b) Population affected: 6000.
1 l
(c) 70-year accumulated dose.
l
I TABLE 29. 70-YEAR DOSE COM ITMENT FOR INTEGRATED 80-KILOMETER POPULATION FROM LIQUID EFFLUENTS RELEASED DURING CY 1985 Population Dose (Person-res)
Exposure Population mole Mode Affected Body GI(a)
Thyroid Kidneys Bone Lungs E
Eating Fish 1.5 x 105 4.40 E-2 4.00 E-5 1.60 E-4 1.20 E-2 5.00 E-2 3.90 E-3 Aquatic Recreation 1.5 x 105 1.30 E-7 1.30 E-7 1.30 E-7 1.30 E-7 1.30 E-7 1.30 E-7 4
(a) Gastrointestinal tract (lower large intestice).
l l
E E
E W
E W
M M
M W
M M
M MW W
W WM l
l TABLE 30. 70-YEAR DOSE COMITMENT FOR INTEGRATED 80 KILOMETER POPULATION FROM AIR 8ORNE EFFLUENTS RELEASED DURING CY 1985 l
Population Dose (person-rem) 80-Kilometer mole Exposure Mode Population Body GI(a)
Thyroid Kidneys Bone Lungs Foodstuff (ingestion) 1.73 x 106 2.50 E-5 8.20 E-7 2.60 E-8 1.30 E-5 9.60 E-5 2.10 E-6 0
Chronic (inhalation) 1.73 x 106 1.08 E-4 9.52 E-6 4.98 E-9 4.13 E-4 2.18 E-3 4.10 E-3 Foodstuff (ingestion)(b) 1,73 x 106 1.40 E-4 8.40 E-7 2.00 E-7 1.70 E-5 5.50 E-4 2.20 E-6 (a) Gastrointestinal tract (lower large intestine).
(b) 70-Year Accumulated Dose.
I TABLE 31. PARAMETERS FOR WEST JEFFERSON SITE AIRBORNE RELEASE DOSE CALCULATIONS El i
Facility Name:
JN-1 (Hot Lab)
Releases:
See Table 3 Meteorological Conditions:
West Jeff meteorological station 1-year data (1/1-12/31/85), annual average Dispersion Model:
Gassian, BCL parameters X/Q:
Girl Scout Camp 4.60 x 10-5 sec/m3 0 500m SE am 80-km population 7.76 x 10-9 sec/m3 g
Release Height:
24.2 meters effective (18.28 meters actual stack height) 6 1.73 x 10, see Figure 12 Population Distribution:
Computer code:
DACRIN, version 1.2, Rev. 1980 Calculated Dose:
Chror.ic inhalation, maximum individual and 80-km population, 70-year dose comitment Files addressed:
Radionuclide Library, Rev. 1-15-81 Organ Data Library, Rev. 2-5-81 l
Computer Code:
PABLM, version 2.1, Oct. 1980 Calculated Dose:
Chronic ingestion, Girl Scout Camp and 80-km l
population, 70-year dose comitment l
Files Addressed:
Radionuclide Library, Rev. 1-15-81 E
Food Transfer Library, Rev. 2-27-78 5
I Organ Data Library, Rev. 2-5-81 l
External Dose Factor Library, Rev. 3-15-81 m
Bioaccumulation Factor Library g
I I
I
55 I
TABLE 32. AVERAGE ANNUAL PERCENT FREQUENCY OF WIND DIRECTION AND AVERAGE WIND SPEED (M/S) FOR CY 1985
=
Avera e Direction Percent Speed (M/S) l N
4.1 3.8 NNE 3.6 3.5 NE 4.3 3.4 ENE 4.2 3.3 l
E 4.5 3.2 ESE 4.9 3.4 l
10.2 4.9 j
WSW 8.2 5.5 W
7.8 4.7 WNW 5.3 4.2 NW-4.4 3.9 f
NNW 4.0 3.5 CALM 2.9 Total 100.0 4.2 I
I I
I
TABLE 33. ANNUAL AVERAGE AIMOSPHERIC OISPERSION NIJND THE WEST JEFFERSON SITE FOR A 18 METER STACK HEIGHT RELEASE (UNITS ARE SEC/M3)(a)
Direc-Range in Miles (Km) tion 0.3(0.5) 0.5(0.8) 1.2(2.0) 2.5(4.0)
J.5(5.6) 4.5(7.2) 7.5(12) 15(24) 25(40) 35(56) 45(72)
N 3.88 E-5 1.76 E-5 3.64 E-6 1.06 E-6 5.91 E-7 3.85 E-7 1.68 E-7 5.51 E-8 2.44 E-8 1.43 E-8 9.71 E-9 NNE 4.21 E-5 1.91 E-5 3.95 E-6 1.15 E-6 6.42 E-7 4.18 E-7 1.82 E-7 5.98 E-8 2.65 E-8 1.56 E-8 1.05 E-8 NE 4.33 E-5 1.97 E-5 4.07 E-6 1.18 E-6 6.61 E-7 4.31 E-7 1.88 E-7 6.15 E-8 2.73 E-8 1.60 E-8 1.09 E-8 ENE 4.46 E-S 2.03 E-5 4.19 E-6 1.22 E-6 6.81 E-7 4.44 E-7 1.93 E-7 6.34 E-8 2.81 E-8 1.65 E-8 1.12 E-8 E
4.60 E-5 2.09 E-5 4.32 E-6 1.26 E-6 7.02 E-7 4.58 E-7 1.99 E-7 6.54 E-8 2.90 E-8 1.70 E-8 1.15 E-8 ESE 4.33 E-5 1.97 E-5 4.07 E-6 1.18 E-6 6.61 E-7 4.31 E-7 1.88 E-7 6.15 E-8 2.73 E-8 1.60 E-8 1.09 E-8 o,
SE 3.20 E-5 1.45 E-5 3.01 E-6 8.73 E-7 4.88 E-7 3.18 E-7 1.39 E-7 4.55 E-8 2.01 E-8 1.18 E-8 8.02 E-9 SSE 3.43 E-5 1.56 E-5 3.22 E-6 9.34 E-7 5.22 E-7 3.41 E-7 1.48 E-7 4.87 E-8 2.16 E-8 1.27 E-8 8.58 E-9 S
3.01 E-5 1.37 E-5 2.82 E-6 8.20 E-7 4.58 E-7 2.99 E-7 1.30 E-7 4.27 E-8 1.89 E-8 1.11 E-8 7.53 E-9 SSW 2.83 E-5 1.29 E-5 2.66 E-6 7.73 E-7 4.32 E-7 2.82 E-7 1.23 E-7 4.02 E-8 1.78 E-8 1.05 E-8 7.10 E-9 SW 2.41 E-5 1.10 E-S 2.27 E-6 6.59 E-7 3.68 E-7 2.40 E-7 1.05 E-7 3.43 E-8 1.52 E-8 8.93 E-9 6.05 E-9 WSW 2.68 E-5 1.22 E-5 2.52 E-6 7.31 E-7 4.08 E-7 2.66 E-7 1.16 E-7 3.80 E-8 1.68 E-8 9.90 E-9 6.71 E W 3.13 E-5 1.42 E-5 2.94 E-6 8.55 E-7 4.78 E-7 3.12 E-7 1.36 E-7 4.45 E-8 1.97 E-8 1.16 E-8 7.85 E-9 WNW 3.51 E-5 1.59 E-5 3.29 E-6 9.57 E-7 5.35 E-7 3.49 E-7 1.52 E-7 4.98 E-8 2.21 E-8 1.30 E-8 8.79 E-9 NW 3.78 E-5 1.72 E-5 3.55 E-6 1.03 E-6 5.76 E-7 3.76 E-7 1.63 E-7 5.37 E-8 2.38 E-8 1.40 E-8 9.46 E-9 NNW 4.21 E-5 1.91 E-5 3.95 E-6 1.15 E-6 6.42 E-7 4.18 E-7 1.82 E-7 5.98 E-8 2.65 E-8 1.56 E-8 1.05 E-8 l
(a) Calculated from meteorological data collected during the period 1-85 through 12-85.
l l
l l
q M
M M
M M
M M
M M
M M
M M
M M
M M
TABLE 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 NNE 2,225 8,882 10,041 0,061 9,073 36,911 8,315 9,702 8.687 13,102 116,999 NE 2,389 8,782 7;145 12,067 9,991 14,091 15,950 14,544 12,792 15,118 112,919 ENE 3,699 6,296 9.335 9,041 6,378 13,580 19,159 16,745 22,731 21,900 128,864' E
3,232 4,964 5,301 4,316 7,159 19,409 16,516 16,463 24,353 22,328 134,041 ESE 2,563 3,382 5,595 14,082 12.465 63,939 15,088 17,222 19,994 12,672 167,002 SE 4,232 2.719 7,523 17,120 17,140 16,319 19,666 18,241 18,211 9.927 131,098 SSE 1,679 3,685 6,098 10,100 14,492 21,466 12,312 11,862 13,044 10,022 104,760 S
1,346 1,797 5,940 2,%9 2,229 5,673 9,019 8,323 13,122 16,497 66,915 SSW 837 1,685 6,718 9,083 4,526 17,293 10,880 8,284 10,637 14,278 84,221 SW 1,400 2,167 5,119 15,565 15,129 11,062 14,925 7,001 9,529 11,322 93,219 WSW 1,288 3,018 1.561 3,094 2,723 14,483 9.903 7,661 31,354 53,895 128,980 W
1,632 3,658 3,057 898 838 2,498 8,374 11,035 32,199 41,631 105,820 WNW 1,301 3,296 5,159 3,432 1,401 7,797 7,951 6,477 10,379 14.358 61,551 NW 1,150 2,990 5,497 5,720 7,371 6,565 9,288 7,062 9,984 13,974 69,601 NNW 963 3,363 4.383 5,132 5,540 7,463 7,956 10,381 15,148 25,452 85,781 Total 31,141 64,886 97,172 129.8 %
124,957 295,273 192,917 182,196 268,078 321,412 1,707,928 Total within 50 miles = 1,707,928 C
I 3
se I
FIGURE 1. REGIONAL MAP FOR KING AVENUE AND WEST JEFFERSON SITES
.N i'
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FIGURE 3. LOCAL VICINITY MAP OF NUCLEAR SCIENCES AREA WEST JEFFERSON SITE g
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FIGURE 5. MAP OF GRASS, FOODCROP AND SOlt SAMPLING LOCATIONS E
l N
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E-FIGURE 6. MAP OF SITE BOUNDARY AIR SAMPLING LOCATIONS AND BATTELLE LAKE AND DARBY CREEK WATER AND SEDIMENT SAMPLING LOCATIONS r
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FIGURE 8. MAP OF TLD LOCATIONS WITHIN % MILE RADIUS OFTHE NUCLEAR SCIENCES AREA I
s.,
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FIGURE 11.1980 POPULATION WITHIN 80 km OF THE WEST JEFFERSON SITE s
I HARDIN MARION 40.000 @Marion
=
6,000 f 11.000 O yg, g
- 9 l NE l 3.200 KNOX
,,,oo j
i -
15.000
- M' V" "
LOGAN' 3.100
' 6.200 2.a00 N
I l
lWNWl gellefontaine 1.200 MMM
.b.0 UNION g
5.200 SHELBY g laware 5.200 s Oj 2.000 7.6 5.800 12.000 CHAMPAIGN 1
/
UCKING
~
1.450 14.500 3.500 MIAMI' d
650
- 3 e4,000 Newark Troy G l
0W CLARK'f3ooo
, Columbus 1
6.400 53.000 34.500-
@r
=
55.000 7s.000 I i.
.WJe"frSon e
, O.25.
80 000
!-- L-espringfield i
l FRANKUN 8.700 London 2.000 g
3.200
%d 1
p 790' 5.200 g,
24.000 f PERRY MONTGOMERY MADISON FAIRFI LD l
33,ooo l
Dayton 9 145;0,9 2.300 750 800 1.000 g
14.000 Lancaster New W
FAYETTE PICKAWAY l ESEl Xe i 400 2.200 2.300 40.800 i
2 00 Ci leville
@ Logan I
15.000 Washington, C.H' CUNTON HOCKING 7,4oo j
6.300 G Wilmington
/
SE CUMULATIVE POPULATION TOTALS ROSS 7.000
@ Chillicothe PftESENT POPULATION 0-80 km_
32 km 937.170 SSE IssWI o-4s km 1.0ss.27o gg o s4 km 1.2s1.07o S Hillsboro 0 80 km 1.731.570 HIGHLAND LEGEND E
Nuct' er Sciences Area. West Jefferson Site 8
e O
to 32 Scale: km I
I I
I G9 FIGURE 12. 1980 POPULATION WITHIN 16 km OF THE WEST JEFFERSON SITE I
CUMULATIVE POPULATION TOTALS:
M I
I 6
11.
I 8.950 5
I Amity Hilliard (,,.
i 3.040 k
10.150
$l I
l ENEl 6,150 5 i
20 660 210 f
I
,[,, *,, g 540 20.650 130 Columbus i
PlumW k
170 530
\\
10,500 h
h West Jeffersor 3
7
~
830
,, e NewYoNe
- r. /
Alton LaYayette 2,300 520 4
Galloway o e
5,400 1,720 Ch hl 110 g
160 220 610 lWSWl l ESE l MADISON COUNTY 4,150 I
. e...
3,050 I
3,040 4,100 t
g f
8 Nuclear Sciences es We f Jefferson Sete Scale am l
I I
P' I
I I
I I
I I
APPENDIX I
I
'I I.
I I
I I
E E
A-1 APPENDIX E
ADDITIVE LEVELS DUE TO RADIONUCLIDE MIXTURE The " Requirements for Radiation Protection" (D0E 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. RCGs referred to in this report are consistent with Derived Air Concentrations h
(DRC) in DOE Order 5484.1, Chapter III (DRAFT).
The sum of all excluded ratios cannot exceed one-fcurth the sum of the ratios l
of the concentrations of radionuclides to their respective RCGs are listed below. The ratios are presented for maximum levels at the release point in I
both air and water.
lI l
West Jefferson Site I
Radionuclide Radionuclide Concentration RCG Air l
Plutonium-239 3.76 x 10-2 I-131 1.75 x 10-8 l
Lead-212 1.30 x 10-5 Cesium-137 1.74 x 10-5 l
Strontium-90 4.33 x 10-6 Cerium-144 2.03 x 10-3 Antimony-125 2.62 x 10-6 I
Uranium-235 1.69 x 10-3 Krypton-85,
1.38 x 10-1 Sum 1.78 x 10-1 l
A-2 West Jefferson Site Radionuclide Radionuclide Concentration RCG Water Uranium-235 1.33 x 10-3 Lead-212 2.24 x 10-3 E
Radium-228 1.39 x 10-2 g
Radium-226 3.33 x 10-3 Strontium-90 8.33 x 10-4 Iodine-129 4.30 x 10-3 Plutonium-238 1.00 x 10-5 Plutonium-239 3.34 x 10-6 Cesium-137 1.35 x 10-3 Sum 2.73 x 10-2 The data indicate that, according to the criteria of DOE Order 5480.1, Chapter XI, the sum of the above ratios does not exceed one-fourth; therefore, these nuclides are not considered as part of the mixture.
APPLICABLE STANDARDS Radioactive Standards In conformance with Federal Radiation Council (FRC) guidelines and DOE Order 5480.1, Chapter XI, " Standards for Radiation Protection," site boundary concentrations are compared with RCGs established for uncontrolled areas.
I'
[:
A-3 Uncontrolled Area (Site Boundary)
Air Concentration. ICi/ml
(
' Plutonium-239 6 x 10-14 Krypton-85 3 x 10-7
{
Iodine-131 l'x 10-10 Cesium-137 5 x 10-10 Lead-212 6 x 10-10 Cerium-144 2 x 10-10 Strontium-90 3 x 10-10
(
Uranium-235 4 x 10-12 Antimony-125 9 x 10-9 b-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 Plutonium-239 5 x 10-6
{
Strontium-90 3 x 10-7 Lead-212 2 x 10-5 Cesium-137 2 x 10-5 Uranium-235 3 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 mix.ture and its respective 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.
E
A-4
. Grass and Food Crops 1
There are no guidlines established for radionuclides in grass and food crops.
I' Soil and Sediment There are no guideliies established for radionuclides in soil and sediment.
l 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 E
the pulmonary lung and 3 mrad /yr to the bone.
5 Fish l
There are no guidlines established for radionuclides in fish.
Nonradioactive Standards (Water)
Concentrations of nonradfoactive species in water are subject to the restric-t tions of the (NPDES) Permit as were determined by the Ohio EPA following a study of the Scioto River Basin.
I Erternal Radiation - General Public l
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 I
l I,
1 l
t
l i
A-5 EXTERNAL DISTRIBUTION LIST This report is submitted 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. Quillin Radiological Health Program Director Ohio Department of Health 1
246 N. High Street P.O. Box 118 Columbus, Ohio 43215 Dr. James McAvoy I
Ernest C. Neal, Chief District Operation Ohio EPA I
I
I A-6 State of Ohio (Continued)
Ohio Power Siting Commission Office of Assistant Administration for Public Information Charles Taylor Office of Air Pollution Ken Harsh Office of Emergency Response Jim Kneale, Chief Office of Public Water Supply Ernie Rotering Waste Water Pollution Control Paul Flanigan, Chief Title X Ohio EPA Donald E. Day, P.E.
Chief Division of Land Pollution Control Federal EPA W. D. Rowe Deputy Assistant Administrator for Radiation Programs g
Office of Radiation Programs g
Sarveillance and Inspection Division U.S. EPA Gilbert Gigliotte Director Technical Information Mr. David Kee, Director Air and Hazardous Materials Division Outside Laboratory Samuel I Baker Senior Environmental Protection Officer Fermi National Accelerator Laboratory P.O. Box 500 Batavia, Illinois 60510 I
A-7 Jack P. Corley, C.H.P.
Staff Engineer Environmental Evaluations Section Battelle l
Pacific Northwest Laboratories Battelle Boulevard Richland, Washington 99352 Department of Enerav Mr. Dana R. Dixon, Supervisor Acquisition and Assistance Unit Jerry J. Nelsen, Ph.D.
Assistant Director for Environmental Protection Operational and Environmental Safety Division Nuclear Regulatory Commission Mr. James G. Keppler, Administrator Region III Office Leland Rouse Division of Fuel Cycle and Material Safe *.y I
I
(( [
E W M TO 35 ss
~
OBallelle Columbus talxiratonn
%ikjf 503 Aing Avenue fN x
Columbus. Ohio 4 3201-2691 N
Telephone (614) 424-6424 Teles 24-5454
~
.\\J May 19,1986 MAY 27 NOOpod
- Ai s.t.
mn "h'
Leland C. Rouse, Chief Advanced Fuel and Spent V
Fuel Licensing Branch m
Division of Fuel Cycle and Material Safety US Nuclear Regulatory Commission
-Washington DC 20 555.
. i..< u ;J, -
~ ~ ' ~ ~ ~ ~ ~ ~
Dear Mr. Rouse:
. ); a.v.
, +.
i In accordance with Con 5fon 19 of our Materials License No. SNM-7 we
~
are providing you with-three*roirfW6f~Ylie~ Battel,le Columbus Division Environmental Monitoring Rep _o_rt,Jarfdalendargear 'l'985.
r
).0 1
i Sincerely
,2 4
. Fr. M i Harley L. Toy
_,,.Pov r ' Us DOE Liaison Officer
,ov u
- ghy HLT:rm t r.aD:n.
Enclosures t, N h' ' " '
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