ML20128A790

Site Environ Rept for CY91 on Radiological & Nonradiological Parameters

ML20128A790
Person / Time
Site:	07000008
Issue date:	12/31/1991
From:	Battelle Memorial Institute, COLUMBUS LABORATORIES
To:
Shared Package
ML20128A750	List: ML20128A746 ML20128A790
References
BCLDP-10192, NUDOCS 9212030453
Download: ML20128A790 (82)

Text

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D BCLOP-10192 4 D i BATTELLE COLUMBUS LABORATORIES DECOMMISSIONING PROJECT D SITE ENVIRONMENTAL REPORT FOR CALENDAR YEAR 1991 D on RADIOLOGICAL AND NONRADIOLOGICAL PARAMETERS D to UNITED STATES DEPARTMENT OF ENERGY 00E FIELD OFFICE, CillCAG0 October 1, 1992 7r Prepared by Regulatory Compliance and O Environment, Safety, and flealth Oversight Battelle Columbus Laboratories Deconmissioning Project P l es w Ballelle . Putting Technology To %rk O

) 3 J APPROVAL LIST 9 APPROVED BY [72.___. Manager, RegulatoW Compliance & Environment, Health aWd Safety Oversight [ 8I 88Wd / f^ APPROVED BY ! A Manager, Quality /ssurance A / 8 APPROVED BY je f[cF[f.2 BCLDPHythPhysicsOversightManage'r 7!21/f2 APPROVED BY BCLDP Environmental Oversight Manager D D t_--_________-_-__-__-__-_____-_____-_______________-_-________-___-____-____--___________-____.--

.m C) CONTENTS i n Page LIST OF TABLES v LIST OF FIGURES........................... vi C) FOREWORD viii

SUMMARY

I INTRODUCTION 4 C) SITE GESCRIPTIONS 4 Demography 8 Climatology........................ 11 Geology.......................... 12 Hydrology......................... 13 C) Background Radiological Characteristics.......... 14 FACILITY DESCRIPTION...................... 15 The King Avenue Site 15 The West Jefferson Site.................. 18 O COMPLIANCE

SUMMARY

20 ENVIRONMENTAL PROGRAM INFORMATION.................. 25 ENVIRONMENTAL RADIOLOGICAL MONITORING................ 26 O WEST JEFFERSON SITE 28 Air--Radioactive 28 Water Monitoring--Radioactive............... 31 Grass and Food Crops--Radioactive.............- 35 () Garden Crops--Radioactive................. 37 Sediment--Radioactive.................... 37 Soil--Radioactive..................... 42 Fish--Radioactive..................... 42 Background Radiation Levels.... 45 Fence Post Dose Estimate 45 O KING AVENUE SITE........................ 45 Air--Radioactive 45 Water--Radioactive 49 Soil--Radioactive...................... 49 C) Vegetation--Radioactive.................. _49 ENVIRONMENTAL NONRADIOLOGICAL PROGRki INFORMATION.......... 53 iii O

C1 CONTENTS (Continued) 8 Page GROUNDWATER PROTECTION S6 EVALVATION OF DOSE TO THE PUBLIC 62 ESTIMATED DOSE TO THE PUBLIC FROM WEST JEFFERSON SITE 8 EMISSIONS DURING 1991 62 Atmospheric Discharges 62 Liquid Discharges..................... 63 ESTlHATED RADIATION DOSE TO THE PUBLIC FROM ATMOSPHERIC 8' DISCHARGES........................... 63 Calculation of Atmospheric Dispersion Parameters 63 Computation of Dose Equivalent Rates to Nearby Individuals and Population Groups............. 67 9 ESTIMATED RADIATION DOSE TO THE PUBLIC FROM LIQUID DISCHARGES 67 Radiation Dcse from Swimming (External Whole Body) 67 Radiation Dose During Boating and Waterskiing....... 68 Radiation Dose from Drinking Water 68 O-QUALITY ASSURANCE.......................... 69 REFERENCES 71 APPENDIX ENVIRONMENTAL REPORT EXTERNAL DISTRIBUTION LIST...... 72 9 9 9 e iv 9

1 TABLES Page Table 1. Battelle King Avenue Site Population Within 80-km (50-mile) Radius..................... 9 Table 2. Battelle West Jefferson Site Population Within 80-km 3 (50-mile) Radius..................... 10 Table 3. Annual Radionuclide Release Inventory--West Jefferson Site--1991........................ 27 Table 4. Sumary of Atmospheric Radioactive Emissions--West [ Jefferson Site--1991................... 29 j. Table 5. Sumary of Specific Radionuclides from Stack Emissions-- West Jefferson Site--1991 30 Table 6. Sumary of Site Boundary Air Sample Analyses--West ) Jefferson Site--1991................... 33 Table 7. Summary of Liquid Radioactive Emissions--West Jefferson Site--1991.............. 34 Table 8. Sumary of Radiological Analyses of Environmental ) Water Samples--West Jefferson Site--1991......... 36 Table 9. Summary of Radiological Analyses of Grass--West Jefferson Site--1991........................ 39 Table 10. Sumary of Radiological Analyses of Food Crops--West [ Jefferson Site--1991................... 40 f Table 11. Summary of Radiological Analyses of Garden Crops-- West-Jefferson Site--1991 41 4 Table 12. Summary of Radiological Analyses of Sediment Samples-- ) West Jefferson Site--1991 43 Table 13. Summary of Soil Analyses--West Jefferson Site--1991 44 Table 14. Summary of Fish Tissue Analyses--West Jefferson Site-- 1991........................... 46 ) Table 15. Integrated External Background Radiation Measurements at Recreation Area and Property Boundary Line--West Jefferson Site--1991................... 48 Table 16. Radiological Analyses of Environmental Air Samples-- ) -King Avenue Site--1991.................. 50 v )-

C TABLES (Continued) Page Table 17. Radiological Analyses of Liquid Discharges--King Avenue Site--1991.. -..................... 51 Table 18. Aadiological Analyses of Soil Samples--aing Avenue Site--1991........................ 52 l Table 19. Radiological Analyses of Vegetation Samples-- King Avenue Site--1991.................. 54 Table 20. Nonradiological Water Effluent Analyses--West 4 Jefferson Site--1991................... 55 8-Table 21. Radiological Analyses of Groundwater--West Jefferson Site--1991........................ 60 Table 22. Nonradiological Analyses of Groundwater--West Jefferson Site--1991........................ 61 Table 23. Average Percent Frequency of Wind Direction and Average Wind Speed.................... 64 Table 24. Average Atmospheric Dispersion Around the West Jefferson Site from an 18-Meter Height Stack Release--1991..... 65 FIGURES O Figure 1. Regional Map for King Avenue and West Jefferson Sites.. 5 Figure 2. Local Vicinity Map of King Avenue Site 6 Figure 3. Local Vicinity Map of Nuclear Sciences Area--Wes? Jefferson Site 7 Figure 4. Battelle King Avenue Laboratories............ 15 Figure 5. Nuclear Sciences Area--West Jefferson Site 17 Figure 6. Map of Site Boundary Air Sampling Locations and Battelle Lake and Darby Creek Water and Sediment Sampling Locations 32 Figure 7. Map of Grass, Food Crop, and Soii Sampling Locations 38 Figure 8. Map of TLD Locations Within 3/4-Mile Radius of the 6 Nuclear Sc'ences Area.................. 47 Figure 9. North Site Groundwater Monitoring Wells......... 57 vi 9

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i e FIGURES (Continued) 4- -Q Page Figure 10. Recommended' Remedial Action for Remediated Filter Bed Area (Shaded Area).............. 58 Figure 11. Wind Rose Pattern for West Jefferson Site........ '66 'O i l i t i } }

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C FOREWORD G This report was prepared for the Battelle Columbus Laboratories Decommission-ing Project (BCLDP) by staff in the Regulatory Compliance and Environment, Safety, and Health Oversight group. The radiological monitoring data were supplied by environmental and operational health physics staff. All radio-e analyses of environmental air, water, grass, soil, sediment, and food crop samples were perfonned by the BCLDP Radioanalytical Laboratory. Nonradiolog-ical analyses of environmental water samples were performed by the Columbus Water and Chemical Testing Laboratory, Columbus, Ohio, and Kemron Environ-g- mental Services, Marietta, Ohio. 9 O P e viii 1

O SUFt4ARY <J Battelle Memorial Institute's nuclear research facilities are cur-rently being maintained under a surveillance and maintenance (S&M) mode with increasing decontamination and decommissioning (D&D) activities under Depart-ment of Energy (DOE) Contract W-4-7405-ENG-92. These activities are referred to under the Contract as the Battelle Columbus Laboratories Decommissioning Project (BCLDP). All operations referred to in this report are those activi-ties in support of S&M and D&D. Envir<cmental monitoring was continued to O demonstrate compliance by Battelle with all federal, state, and local regula-tions. The only routine nonradiological monitoring in association with the BCLDP is done for the National Pollution Discharge Elimination System (NPDES) Permit 41N00004*DD for the West Jefferson Nuclear Sciences Area, and ground-water monitoring wells at the West Jefferson site. Routine monitoring of liquid and atmospheric emissions at the King 4 Avenue and West Jefferson Nuclear Sciences Area was conducted, in addition, samples of various environmental media including air, water, grass, fish, food C crop, sediment, and soil were collected from the region surrounding the two sites and analyzed. Off-site levels of radionuclides that may be attributable to the West Jefferson nuclear operation were indistinguishable from background levels at specific locations for air, water, and direct radiation measurement. O The Annual Radionuclide Release Inventory is a list of minimum detectable quantities of isotopes suspected but not identified in samples. Suspected isotopes are those expected to be found in the residual fuel contam-ination left from previous fuel work. O The data are summarized as follows: There were slightly elevated readings of total residual chlorine and total suspended solids in a monthly sample required under the West Jeffer-son NPDES Permit. These readings were reported to Ohio Environmental Protec-O tion Agency (OPEA) and follow-up sampling has revealed no further problems. None of these conditions are directly attributable to BCLDP activities. A discussion of releases is found in the section on ENVIRONMENTAL NON-RADIOLOGICAL PROGRAM INFORMATION on page 53 of this report. O O

0 2 8 No isotopes were present above minimum detectable levels (MDL) for air releases or for liquid discharges to Darby Creek from the West Jefferson Nuclear Science Area. MDL values for specific isotopes not detected were used to determine the percentage of the respective DOE 5400.5 derived concentration guide (DCG) for an individual radionuclide released to an unrestricted area. Concentrations observed at downstream sampling locations were statistically indistinguishable from background levels. West Jefferson nuclear operations d'aring 1991 caused no distin-guishable impact on concentrations of airborne radionuclides nor on external G radiation doses measured adjacent to the West Jefferson site and the site boundary. Radionuclides detected in food crop, grass, creek bottom sediment, fish, and soil samples (e.g., Cs-137) were all attributed to previous atmo-spheric nuclear tests, Chernobyl fallout, or natural sources. The estimated dose equivalent to a nearby resident from nuclear operations at the West Jefferson site was calculated to be 0.0066 mrem /yr, with a maximum organ dose to the endosteum of 0.038 mrem /yr. These dose cal-culations assume impacts due to the presence of radionuclides at MDL levels, 9 although such radionuclides were not found in detectable concentrations during the year's environmental sampling program. The whole body " fence-post" exposure during 1991, for external radiation at the site boundary line, was at background levels at Ken Jockety 9 Camp, the Girl Scout camp adjacent to the Battelle property line 0.4 km eu t-southeast of the boundary of the nuclear site. An estimated dose of 120 mrem / yr was verified through the use of themoluminescence dosimeters (TLDs) placed at the site boundary. This is the same as the national average for total 9 background radiation. A discussion of how the " fence-post" exposure was determined is given in the text on page 45. D&D activities during the year involved site and building charac-terization at West Jefferson, and room and/or building characterization at 9 King Avenue. Some of the radioactively contaminated sump sludge waste at the King Avenue site w6s identified as TSCA or RCRA mixed waste. This waste was O 9

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f 3' removed, packaged, and shipped for disposal at a DOE facility managed by the Westinghouse Hanford Company in Richland, Washington. Additional sump sludge has undergone further characterization and its disposal is a focal point for 1992 D&D activities. 3 Building 9 was removed from the S&M program after decontamination-was completed. 3- ? i D D J

O 4 INTRODLCTION 4 Surveillance and maintenance (S&M) activities, performed under Contract No. W-7405-ENG-92, Memorandum of Understanding, August 14, 1986, were conducted at Battelle's King Avenue site and the West Jefferson Nuclear Sci-0- ence Area site. Figure 1 is a regional area map, covering an 80-km (50-mile) radius and shows both sites. Some Nuclear Regulatory Commission (NRC) licensed activitics are conducted at both sites, but are not addressed specif-ically in this report. This report makes no distinction between effluents that may result from contract or licensed activities. 51?E DESCRIPTIONS O The Battelle King Avenue facility is located at 39 59'N, 83 03'W in the western central portion of the city of Columbus, Ohio. The 10-acre plot, accommodating 21 buildings, is bounded on the north by King Avenue, Battelle Boulevard to the east, partly by Fourth Avenue and Fifth Avenue to O the south, and the Olentangy River to the west. Figure 2 shows the property boundary of the Battelle King Avenue site. It indicates the location of Building 3, which houses facilities formerly used in uranium processing. The West Jefferson site (Figu,e 3) is located at F 58'N, 9 83 15'W, approximately 15 statute miles west of the King Avenue facility. The West Jefferson site consists of a 1,000-acre tract, which accommodates the Engineering Area in the southeastern portion, the Middle Area in the east central portion, and the Nuclear Sciences Area in the northern portion. The 9 northern boundary of the site lies approximately one mile south of Interstate Highway 70 and extends from the Georgesville-Plain City Road eastwat the Big Darby Creek. The eastern boundary of the site roughly parallels the val-ley of the Big Darby Creek southward to the Conrail ti w ks, which constitute e the southern boundary. The Georgesville-Plain City Road defines the western i boundary of the site. For this report, the focus of interest is the Nuclear Sciences Area at the West Jefferson site. It is indicated by the shaded area of Fig-4 ure 3. The Nuclear Sciences Area consists of a 10-acre fenced area enclosing 9

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,) g. M acma v l 71 VE# cowww O / ~, e c.,,,, .c. p 3 CCwTy [ ....f ~ **= I '* KING AVENut SITE ,9, LEGEND J ,wro,, B wucteAs scaucts AntA (:' w' e f' c= = WEST JEFFERSON 51TI O I y n n 3 --- t am., 0 FIGURE 1. REGIONAL MAP FOR KING AVENUE AND WEST JEFFERSON SITES O

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Ol l 8 8' a guardhouse, four buildings, and two other small structure; on a flat bluff; Battelle Lake lies to the south and Big Darby Creek lies to the east. The eastern edge of the bluff drops 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. Battelle property extends to the 8 norin, west, and south. Some is leased to farmers, typically for raising fif d crops such as corn or soy beans. The site includes two narrow wooded strips, one along the northern portion of the fence around the Nuclear Sci-ences facility, and the other about 1,000 feet to the northeast of the center of the site. 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. 9 Demography The area within a two-mile radius of the Battelle King Avenue facility to the cast and south can be characterized as high-density residen-tial. The Ohio State University, with a student enrollment of approximately 60,000 and an employee staff of approximately 29,700, is adjacent to the King Avenue facility on the north. The area west of the Olentangy River consists mainly of small business and light industrial properties, with scattered resi-8 dential patches. Table 1 gives data on the population distribution within a 50-mile radius of the King Avenue facility. The area immediately adjacent to the West Jefferson site has a low population density. Table 2 gives the population distribution, by direction 9 and distance, within 50 miles of Battelle's West Jefferson site. The nearest residences to the Nuclear Sciences area are two houses located 2,500 feet to the northwest and southwest, respectively. Camp Ken Jockety, a Girl Scout camp, is located on a bluff on the east side of the Big Darby Creek at a dis-tance of 1,640 feet from the center of the site. Four thousand feet to the southeast, on the eastern side of the Big Darby Creek, the Lake Darby Estates residential subdivision (Figure 3) currently contains a total of 965 single family units. A second subdivision, West Point, east of the Lake Darby G Estates and Hubbard Road, has approximately 540 housing units. 9

TABLE 1. BATTELLE KING AVENUE SITE POPULATION WITHIN 80-KM (50-MILE) RADIUS (O Distance in km (miles) 0-1.6 1.6-3.2 3.2-4.8 4.8-6.4 6.4-8.1 8.1-16.1 16.1-32.2 32.2-48.3 48.3-64.4 64.4-80.5 (0-1) (1-2) (2-3) (3-4) (4-5) (5-10) (10-20) (20-30) (30-40) (40-50) Total N 415 7,073 4,743 9,300 6,266 41,589 17,811 24,971 10.235 50,510 172,913 NNE 2,890 12,472 12,223 9,305 9,961 69,843 32,146 7,108 9,115 12,899 177,962 NE 2.304 9,800 '4,582 12,052 10,715-33,559 19,594 8,583 11,405 26,489 139,083 ENE 1,901 2,128 5,107 3,126 6,195 2/,062 9,099 12,645 25,754 7,274 100,291 E 2,379 1,105 4,986 5,327 7,225 36,093 36,855 19,378' 46,659 11,822 171,829. ESE 1,134' 364 7,640 10,947 8,032 68,632 34,961 13,446 10,027 13,757 168.940 SE 457 428 5,398 15,858 8,735 14,322 12,705 41,722 13,018 15,378 128,021-SSE 0 1,565 2,348 8,386 4,042 21,398 8,243 10,362 7,901 4,567 68,812 u3 - i 5 0 3,513 3,573 1,168 758 2,783 5,905 15,197 6,738 43,264 82,899 SSW 0 4,735 3,973 4,015 3,088 23,462 10,011 2,354 4,402 12,858 68,898 l i SW 8 1,475 7,100 13,473 8,479 11,219 6,709 4,478 19,966 7,430 80,337 { WSW 699 41 2,991 7,369 4,328 30,307-3,473 11,698 5,024 20,726 86,656. W 1,534 2,600 1,316 2,225 2,327. 5,477 10,245 7,340 25,726-99,540 158,330 ] WNW 1,046 4,706 3,913 1,082 1,964 14,483 3,634 5,161 16,047 13,706 65,742 NW 82 3,972 4,742 5,617 6,143 18,169 9,512 15,678 4,592 18,042 86,549' i [ NNW 21 669 702 5,487 4,489 47,202 31,149 6,090 8,483 6,158 110,450 i Total 14,870 56,646-75,337 114,737 92,747 465,600 252,052 206,211 225,092 364,420 1,867,712 i k 4 i i ~

N TABLE 2. BATTELLE WEST JEFFERSON SITE POPULATION WITHIN 80-KM (50-MILE) RADIUS Distance in km (miles) 0-1.6 1.6-3.2 3.2-4.8 4.8-6.4 6.4-8.1 8.1-16.1 16.1-32.2 32.2-48.3 48.3-64.4 64.4-80.5 (0-1) (1-2) (2-3) (3-4) (4-5) (5-10) (10-20) (20-30) (30-40) (40-50) Total N 14 20 87 77 121 3,010 4,403 4,911 9,357 48,786 70,786 NNE 8 25 108 90 188 1,789 18,941 26,667 7,577 16,527 71,920 NE 10 33 48 96 139 17,835 101,970 13,351 9.652 14,445 157,589 ENE 10 39 75 192 1,239 17,796 247,639 48,962 12,038 16,592 344,582 E 150 37 56 273 912 39,983 267,165 100,498 23,451 68,444 500,969 ESE 689 166 193 121 376 38,556 62,298 24,4C5 50,876 17,140 194,821 SE 262 1,172 46 71 274 4,158 12,216 14,48. 12,904 7,876 53,468 SSE 42 257 51 52 78 3,158 10,623 4,625 13,120 42,261 74,267 g S 25 84 66 116 123 804 4,208 2.886 4,595 12,227 25,134 SSW 5 497 361 133 80 516 1,228 3,976 20,525 6,530 37,702 SW 3 323 2,867 596 51 748 978 3,650 8.110 18,019 35,345 WSW 3 25 290 236 18 951 12,858 5,606 21,156 185,260 226,403 W 6 24 104 153 110 629 5,146 68,712 50,990 80,285 206,159 WNW 9 14 23 39 67 881 3,429 16,462 6,744 7,915 35,583 NW 14 13 31 70 114 357 1,464 4,736 20,819 I?,691 40,309 l NNW 14 12 45 484 94 665 12,097 5,189 3,851 6,905 25,505 Total 1,264 2,741 4,451 2,799 3,984 131,836 766,663 349,136 275,765 561,903 2,100,542 O O O O O O O O O O O 1

O 11 Currently 18 industries are located within a 10-mile radius. Of these, only four employ more than 100 peopic. Each of these is located at least 8 miles from the facility. Closest to the site are three small indus-tries within West Jefferson that individually employ less than 60 people. The 9 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. Two major highways, I-70 and I-270, are near the West Jefferson 9 site. The junction of these highways, which lies near the eastern edge of the 10-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 3 area, i.e., two and one-half times the 10-mile population distribution for 1965. Climatology J Climatology of the south-central Ohio ngian may be described as continental-ten +, rate. As such, the region is subject to a wide seasonal range in temperature. Summers are quite warm; the mean temperature for the 3 months of June, July, and August is 73.3 F. Temperatures of 90 F or above are expected for about 15 days during these mont The mean for the months of 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. O Precipitation 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. The greatest recorded rainfall 1 for any 24-hour period was 3.87 inches in July of 1947. e Changeable wind directions are characteristic of the region because of the incursion of maritime tropical air masses from the Gulf of Mex-ico and outbreaks of continental polar air masses from Canada. Warm air mass inversion is most common during the later spring and summer and frequently e results in frontal showers and thundershowers. Tropical air mass thunder-storms are also common during the summer and are frequently accompanied by O

0 12 high winds. Additionally, it is not uncommon for hot air mass thunderstorm development to be sufficiently strong to spawn tornado activity. Cold fronts N t invade the regicn, principally during the late fall, winter, and early ,g, also bring showers and thunderstorms. During the late spring, fast-moving cold fronts, with laile tem-perature discontinuities ahead of and behind the frontal surface, travel through the region and are often accompanied by thunderstorms and frequently by tornadic activity. Of the 567 tornadoes recorded within 144 miles of the Battelle facilities during the period 1950-1975, 163 have occurred in the month of April. The regional climatological data gathered by the National Weather Service at Port Columbus, seven miles east-northeast of the King A. venue facil-ity, is generally representative of the local climatic conditions at the Columbus site. Data from Port Columbus are used to prepare wind rose patterns and tables of average wind speed and direction (see Figure 11 and Table 23 later in this report). O Geology The arrangement of geological strata underlying the Battelle facilities area consists of glacial till and outwash with formations of clay, 9 sands, and gravel. The sands and gravel of the outwash ;re found in scat-tered, thin, discontinuous lenses within the till, which is composed of unstratified clay containing fragments of rock. The unglaciated basement for-mations in the West Jeffeison area lie at depths ranging from about 80 to 9 100 feet below the surface. They consist of nearly horizontal beds of lime-stone, dolomite, and shale several hundreds of feet thick. Surface soils con-sist of patches at d mixtures of Brookston silty clay loam, Crosby silt loam, Lewisburg silt loam, Celina silt loam, and Miamian silt loam. The greatest 9 portion of the surface soils is represented by the Brookston-Crosby Associa-tion with little more than trace representing the remaining types. All of these soil types exhibit relatively low permeability; all grade into till clay at depths of 55 to 60 inches where the impermeability of the near-surface 9 geology nearly precludes further percolation. e

O_ - 13 O No recorded earthquakes have occurred within 50 miles of the area of interest, although in 1937 a strong quake was experienced at Anni., Ohio, a little over 50 miles to the northwett of the West Jefferson site. The Columbus-W6 t Jefferson areas are, however, considered to be in a nonseismic O region. The Battelle facilities are in a zone 1 low-risk area. Hydrology O Two aquifers, or underground sources of water, are located-in the site area. The shallow aquifer is in the dense clay till. The deep or prin-cipal aquifer is in the limestone bedrock underlying the till. Earlier wells in the site area ranged in cepth from 10 to 40 feet, which placed them in the O 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 it reported to be less than 0.004 foot per day; for wrter moving through silt, sand, and loess under the same gradient, the rate is between O 0.0042 and 0.065 foot per day. Water movement in the till at the Battelle site is probably withir, the range of the former figure, since the hydraulic gradient of the water table in the area is only slightly greater than one percent. O The present supply wells at the Battelle f'cility lie below the surface of the bedrock. The north well is 130 feet deep the centrally located well in the Middle area is 162 feet deep, and the South area well is 138 feet deep. Bedrock was encountered at approximately 103 feet below the 10 surface in drilling these wells. A man-made hydrologic feature of the site is the artificial lake. It covers an area of about 25 acres and was fonned by damming Silver Ditch southeast of and down gradient from the Nuclear Sciences area. The normal O surface elevation of the lake is 888 feet MSL. The source of groundwater in the site area is local precipitation. Recharge to the shallow aquifer takes place relatively uniformly over the area. Contours of the water table, which are about 40 feet below the surf ace, !O are a subdued replica of the surface topography. Groundwater moves downslope at right angles to the contours and follows a path similar to surface runoff. I 'O

O 14 At the Nuclear Sciences area surface runoff moves downslope into t:.e lake, then through the controlled dam on the site into Big Darby Creek. Test borings carried out in 1970 for an addition to the Hot Labo-ratory reaffinned the geoiogy described above. Only isolated pockets of water wer' encountared during boring and foundation 'iling excavation operations. These pockets were readily pum?ed out and remair, d dry, which indicated that there is no interconnection of the pockets with ti.e lake. Flood water calculation for the lake indicates a capacity of releasing water that is about three times the 'nflow rate measured during the January 1959 floods. It is concluded that the lake has not adversely affected the hydrolooy of the area. Big Darby Creek accounts for the principal surf ace water flow. The Darbyville gauging station is the only continuous recording gauge on Darby Creek. It is located 40.46 river miles south of the West Jefferson facility. Normal flow, recorded at Darbyville, is 430 cubic feet per second (cfs). Background F<adiologicml Characteristics 9 in 1966, ground level radiation for the region, including Battelle facilities, was measured using an aircraft equi,9ed with radiation instrumen-tation. The measurements showed that the natural terrestrial background for 9 the area surrounding Battelle was 60 mrem /yr.(2) This numbec is equal ta the average natural terrestrial background for the United States. The cosmic background for the State of Ohio is averaged to be 50 mrem /yr, compared to a U.S. average of 45 mrem /yr. TF estimate for natural whole-body internal 9 background is consid3 red to i mrem /yr for the United States with only minor regional variations.(3) '.oed on these figures, the total natural back- ,round radiation near the Battelle facilities is estimated to be approximately 130 mrem /yr. This is the same as the national average for the United States as a whole, e 9

D 15

D FACILITY DESCRIPTION The center of S&ri activities at the clattelle King Avenne site is the former U-235 Processing Facility, located on the first floor of Build-D ing 3.

It was the nuclear materials management point for all transactions involving nuclear material at the King Avenue site. Figure 4 shows the loca-tion of Building 3 in the King Avenue site building complex. At the West Jefferson Nuclear Sciences Area, the major S&M opera-D tions are the result of research and development (R&D) on the properties of irradiated materials. This work was performed in the Hot Cell Laboratory (JN-1) and involved examination and testing of irradiated reactor fuel, nuclear pressure vessel material, and fuel cladding material. Only residual D fuel contamination and small contained sources remain onsite. Nuclear support and S&M activities are conducted in the Administrative Building (JN-2) and the retired Battelle Research Reactor (JN-3). Figure 5 shows the locations of these nuclear facilities in the Nuclear Sciences Area building complex. D D&D activities during the year involved site anc building charac-terization at West Jefferson, room and/or building characterization at King Avenue, and actual D&D of Building 9. D The Kii.; Avenue Site The former U-235 Processing facility it located in Building 3 of the King Avenue site. This fr ility was constructed in the mid-1950s. It D served until the late 1960s as an exclusio;1 area specifically designed for the processing and storing of unirradiated enriched uranium utilized on various governm.it and industrial R&D programs. Presently Building 31s used for sev-erai acti:! ties, including waste storage and characterization. Access to the D ,,-235 processing area is limited and entry doors to the area are locked. A vault was used for the temporary storage of limited quantities of unirradiated enriched uranium. The U-235 area also served as a receipt and shipping, sam-pling, and measurement area for shipments of source matarials and small quan. J tities of unirradiated uranium that had been used on programs performed at the King Avenue site. D'

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O 18 The West Jefferson Site Figure 5 shows the location of the four principal buildings at tne West Jefferson Nuclear Sciences arca: JN-1, the Hot Laboratory; JN-2, the Administrative Building; JN-3, a retired Research Reactor; and JN-4, the Haz-8 ardous Material Research Facility (Decomissioned Plutonium Laboratory). Each of these facilities is described in the following paragraphs. HOT CELL LABORATORY, JH-1 8 This laboratory contains approximately 22,000 square feet of space. It was considered to be one of the most completely equipped installa-tions available to the nuclear community. The Hot Laboratory was capable of 8 providing research and technical assistance in the following areas: o Power reactor fuel performance evaluations e Pressure vessel irradiation surveiliance, and cap-g sule examinations and evaluations e Postiriadiation examinations of nuclear materials and components Radiation source encapsulation e g Pnysical and mechanical property studies of irra-a diated materials and structures. The Hot Laboratory consists of a large high-energy cell and con-g necting pool, five smaller cells, and supporting facilities. The high-energy cell and pool are capable of handling complete power reactor fuel assemblies. The smaller cells are the high-level and low-level cells, the two mechanical test cells, and a segmented alpha gamma cell. The supporting facilities e include areas for cask hand!ing, solid and liquid-waste disposal, contamina-tion control, equipment decontamination, and other miscellaneous operations. All of these operations have contributed to the need for surveillance and maintenance while awaiting deconnissioning, g-9

9 19 3 ADMlHISTRATIVE BUILDING, JN-2 This building was designed and constructed for use as a critical assembly laboratory. It was used for critical experiments from 1957 through 3 1963. Since the cessation of critical experiments, the facility has been used for several nuclear-related projects, including direct conversion concepts, irradiation experiment assembly, and special nuclear materials handling. The operating license was terminated by Battelle in 1970 when project work was ] ended. These activities have made it necessary to maintain it on the S&M schedule. Offices and small laboratories are used by nuclear supporting ser-vices staff including Section Administration, Health Physics Services, Nuclear J Materials Accountability, Quality Assurance, and Instrument Maintenance. These activities are the major building activities at this time. The building also currently houses a vault for storage of special nuclear materials and a radiochemistry laboratory for the assay of routine health physics and environ-J mental samples. RETIRED BATTELLE RESEARCH REACTOR, JN-3 J The Battelle Research Reactor began operations October 29, 1956. Operations were terminated on December 31, 1974, and dismantling was initi-ated. The dismantling was completed without incideat during 1975 and the license changed to a possession only status. Storage of waste awaiting ship-J ment for burial is the only licensed activity conducted in JN-3 at this time. DECO M ISSIONED PLUTONIUM LABORATORY, JN-4 3 Building JN-4 was built in 1960 to house activities in plutonium research and processing. These operations were terminated in 1978 and disman-tling of the laboratory portion was completed in 1985. A hazardous materials research facility now operates in JN-4. These activities involve nonradioac-e tive materials only. D

Oi l 20 COMPLIANCE SU! NARY CALENDAR YEAR 1991 8 The BCLDP continues to maintain a state of compliance with all applicable environmental statutes, regulations, or DOE orders. No fines, penalties, or administrative orders were imposed on Battelle during 1991. No lawsuits by regulatory agencies or citizen suits were brought against Battelle 8' in 1991. There were no unresolved compliance issues during 1990 that needed to be addressed in 1991. A minor viola;;on in the areas of NPDES limits was noted and has been corrected by Battelle. However, this violation was not attributed to BCLDP activities, because it was a result of other Battelle operations. Only those issues that may be related to the BCLDP are reported 8 here. Compliance Status in Specific Regulatory Areas 9 a. Comprehensive Environmental Response, Compensation and Lia-bility Act (CERCLA) No violations have occurred and no enforcement actions were taken in connection with BCLDP. e b Resource Conservation and Recovery Act (RCRA) No violations have occurred and no enforcement actions were taken in connection with the BCLDP. Battelle's Part B permit e application for waste storage and treatment at the King Avenue site was revised in response to comments made by OEPA. The revised application is being reviewed by 0 EPA; USEPA is reviewing the Corrective Action portion of the application, e c. National Environmental Policy Act (NEPA) No activities were performed during this period that would trigger noncompliance with NEPA. g-9

e 21 3 d. Clean Air Act (CAA) All requirements under the act, including the National Emis-sions Standards for Hazardous Air Pollutants (NESHAPS), were met and no citations were issued. J e. Clet.n Water Act (CWA) This act is administered in Ohio by the OEPA. The NPDES per-mit for tL.t West Jefferson facility was renewed in 1991. It 3 contained more stringent monitoring conditions than the prior penni t. The monitoring done to meet the pennit was adjusted accordingly. Three minor permit limit exceedences occurred; two of these were due to suspended solids, the other was duc J to a total residual chlorine level. No enforcement actions were taken in connection with Battelle or the BCLDP. f. Safe Drinking Water Act (SDWA) J This act is administered in Ohio by the OEPA. No violations have occurred and no enforcement actions were taken in con-nection with the BCLDP. J g. Toxic Substances Control Act (TSCA) No violations have occurred and no enforcement actions were taken in connection with the BCLDP. PCB wastes were properly stored and removed within the regulatory time limits. h. Federal insecticide, Fungicide, and Rodenticide Act_(FIFRA) This act is not applicable. No pesticides are used in BCLDP activities. J i. Endangered Species Act (ESA) This act is not applicable. No endangered species have been identified in the areas around Battelle. O g

O I 22 j. NationalllistoricPreservationAct(NilPAl O 1his act is not applicable. No areas or structures at Battelle have been identified as subject to requirements of this Act. O k. Executive Order 11988 floodplain Management" This order is not applicable. The reference is Environmental Assessment (EA) for Battelle Columbus Laboratories Deconunis-sioning Project, Table 4-5.N l. Executive Order 11990

• Protection of Wetlands" This order is not applicable.

No wetlands have been ident1-fled at Battelle. Environmental Pennits No new environmental permits were applied for under the BCLOP. OEPA did review new infonnation on a source that they had previously exempted 8 from air pennitting. The Agency confinned that no permit was required for the source. The BCLOP applied to the OEPA for two air pennits related to project activities. The OEPA determined that neither sources required air pennitting due to the insignificant impact of the releases and the short duration of the source. List of Environmental Pennits The following is a listing of all act;/e environmental pennits at Battelle Columbus Operations that may be associated with the BCLOP. Columbus laboratory a. Air (PTO: Permit to Operate) 1. Bldg. 3--Beryllium lab hood, PTO #0125040520/P002 9 2. Bldg. 5--Beryllium Machine shop, PTO #0l?5040520/P003 b. Water NPDES pennits for King Avenue arc not associated with BCLOP operations. 9 9'

0 l 23 .O c. llazardous Waste 1. Ohio Hazardous Waste Pemit #01-25-0572. 2. USEPA interim status--Part A Permit 0HD007901598. 3. Public Utilities Comission of Ohio (P.U.C.0.) hazardous 'O waste transporter--HC 18902; 310-HW. West Jefferson Laboratory a. Air O 1. Bldg. JN-1 Dollers - 0149000074/B001, on registration status with OEPA 2. Bldg. JN-2 Boiler - 0149000077/B002, on registration sta-tus with OEPA O 3. JN-1 underground sttrage tank--PTI# 0149000077/T001, on registration with OEPA. 4. Bldg. JN-3 Boiler #0149000074/B003, on registration sta-tus with OEPA. O b. Water 1. NPDE5 Permit 41N00004*DD c. Hazardous Waste 1. Hazardous waste generation identification number-- O OHT400013892. JANUARY 1, 1992 - APRIL 1, 1992 .O The BCLDP continues to maintain a state of compliance with all applicable environmental statutes, regulations, or DOE orders. No fines, penalties, administrative orders, or notices of noncompliance were imposed on Battelle during the first quarter of 1992. No lawsuits by regulatory agencies O or citizen suits were brought against Battelle during the same periods. Only those issues that may be related to the BCLOP are reported here. 'O .O

O 24 O Compliance Status in Specific Regulatory Areas a. Comprehensive Environmental Response, Compensation and Lia-bility Act (CFRCLA) No violations have occurred and no enforcement actions were e taken in connection with the BCLDP. b. Resource Conservation and Recovery Act (RCRA) No violations have occurred and no enforcement actions were g taken in connection with the DCLDP. Battelle's Part B appli-cation is being reviewed by 0 EPA: USEPA is reviewing the Cor-rective Action portion of the application. O c. National Environmental Policy Act (NEPA) No activities were performed during this period that would trigger noncompliance with NEPA. O d. Clean Air Act (CAA) All requirements under the act, including the National Emis-sions Standards for Hazardous Air Pollutants (NESHAPS), were met and no citations were issued. e. Clean Water Act (CWA) This act is administered in Ohio by the OEPA. No violations have occurred and no enforcement actions were taken. e e 9

) 25 ENVIRONMENTAL PROGRAM INFORRATION The Battelle Columbus Laboratories Decommissioning Project (BCLDP) has an Environmental Program that consists of an environmental monitoring I program, environmental compliance awareness and evaluation activities, and programs for waste minimization and pollution prevention. There is a Waste Minimization Plan for the BCLDP. The plan addresses only the minimization of radioactive waste, because the program I involves only decontamination and decommissioning (D&D) of existing contami- ~ nated (or radioactive) facilities. No other operations or activities generate waste (other than paper, which is recycled) that could be minimized. The BCLDP Waste Manager is responsible for the annual review and updating of the I Waste Minimization Plan. Waste minimization is also included in the Waste Quality Assurance (QA) Plan, Low-Level Waste (LLW) Certification Plan, Trans-uranic (TRU) Waste Certification Plan, and D&D Work Plans. A program for training employees in pollution prevention awareness is in place. The BCLDP Program Manager has issued a copy of DOE's Environmen-tal Policy Statement, and specific instructions for compliance, to all persons involved in BCLDP operations. Pollution prevention training and awareness are addressed in the Waste Minimization Plan, and pollution prevention is also included in the support / commitment and policy statements of this plan. One key element in the Pollution Prevention Awareness Program to help prevent the spread of pollution is the issuance to each employee of site-specific Emergency Plans. They address steps to take in the event of any D number of emergencies, providing information such as whom to notify for each type of emergency and which emergency teams are assigned to respond, depending on which site is involved in the emergency. They address major items such as fire and spill of hazardous and radiological materials. The Hazardous Materials Response Team is under the direction of the BC0 Environment, Health and Safety Office. The team receives training in spill control, which includes awareness of new pollutants and how to prevent their release into the environment. A separate and detailed " Emergency Plan and Procedures - West Jefferson North" notebook addresses the handling of emergencies involving the release of radiological materials from the West Jefferson North site. West D

O 26 Jefferson personnel experienced in the handling of radioactive materials are assigned to various teams to respond to potentially larger radiological haz-ards and releases to the environment. At King Avenue the 8C0 Radiological Safety Officer coordinates the response to radiological spills. The impact of operations on the health and safety of the public is evaluated routinely by an environmental monitoring program that has been in effect since 1955. The basic objective of the environmental monitoring pro-gram is tc evaluate the ef fectiveness of the waste management program of all operations. Concentrations of radioactive and nonradioactive wastes are con-trolled so that effluent levels are maintained as low as reasonably achievable and well 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. Environmental monitoring under the BCLDP is limited by the nature of the S&M and D&D activities. With few exceptions, only radiological moni-toring is being perfonned routinely under S&M. D&D operations have been lim-ited to radiclogical precharacterization and characterization of f acilities 8 and disposal of waste. Disposal of sludge waste from King Avenue sumps did require nonroutine analysis of sludge to detennine compliance with RCRA and ISCA disposal criteria. This led to the removal and packaging of 185 drums of radioactively contaminated TSCA or RCRA waste. This operation was conducted throughout the year and the material was shipped of f ite in three shipments in 1991. Nonradiological monitoring performed in conn.ction with the BCLDP is presented in a separate section following the sectica pertaining to radiologi-cal monitoring. ENVIRONMENTAL RADIOLOGICAL HONITORING An inventory of suspected radionuclides and resultant effluent releases for air and water is presented in Table 3. Both release inventories are based on minimum detectable levels (MDL) of listed isotopes.' Weekly O' 'A discussion of he,v MDLs are calculated for radionuclide analyses can be found in the Quality Assurance Section at the end of this report. 9

\\ 27 i ) TABLE 3. ANNUAL RADIONUCLIDE RELEASE INVENTORYN-- WEST.tifrERSON SITE--1991 Air Activity (pCI) ) Co-57 0.72 Co-60 1.50 Sr-90 0.13 Sb-125 3.30 Cs-134 1.05 Cs-137 1.47 ) Eu-152 2.73 Eu-154 4.20 U-235 2.93 U-238 1,73 Pu-238 0.04 Pu-239 0.01 ) Am-241 1.79 Water Activity (pCi) Co-57 106.7 Co-60 166.5 ) Sr-90 24.9 Sb-125 344.9 Cs-134 123.6 Cs-137 187.1 Eu-152 369.2 Eu-154 439.5 Ra-226 15.9 f Ra-228 13.5 1-129 135.2 U-235 993.5 U-238-6029 i Pu-238 2.7 ) Pu-239 2.5 Am-241 395.5 (a) Inventory is made up of suspected radionuclides and resultant effluent releases for air and water, based on MDL values. See Tables 5 and 7 details of West Jefferson site air and water discharge. t 1

l o 28 samples are screened for elevated levels of radioactivity by counting for gross a (alpha) and gross p-y (beta-gamma). Weekly samples are composited into monthly and quarterly samples for isotopic analysis. As a conservative measure, minimum detectable levels are assumed as positive releases for pur-poses of establishing a release inventory and estimating doses to the public. WEST JEFFERSON SITE Air--Radioactive G 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 detec-tion of any inadvertent release of radioactive materials and provide data for the prompt assessment of the environmental impact, if any (see Figure 5 for location). Particulate samples of the effluent are collected from each exhaust stack. The particulate iamples are collected on Type AE glass fiber 4 filter paper. The air is sampled at an average rate of 2.85 x 10 cc/ min. The filters are changed weekly, which represents an average sample volume of 8 287 m. This volume is selected to facilitate the detection activity in concentrations well below regulatory standards. 4 Analyses are f.erformed on filters on a weekly basis for gross a and gross for stacks 001 through 004, 006, 012, 013, and 014. The cumula-tive average concentration of the a and p mixture emitted from the stacks was many orders of magnitude below the derived concentration guide (DCG) value at the site boundary. The results are summarized in Table 4. Note 3 is implied in the table references to p. These filters are compasited on a monthly basis for gamma analysis and on a quarterly basis for radiochemical analysis. Gamma spectrometric analyses were performed using an intrinsic germanium detector 9 coupled to a Nuclear Data Model N066 multichannel analyzer. The concentra-tions of the radionuclides identified were all less than 7.1 x 10^6 percent of the applicable DCG values at the site boundary (Table 5). The results reported represent total annual average concentration at specific stacks. The 9 site boundary concentrations (see Tables 4 and 5) for the various exhaust 9

TABLE 4. StW.ARY OF ATM3 SPHERIC RADI0 ACTIVE EHISSIONS--WEST JEFFERSON SITE--1991 Number Stack Site Stack of Stack Volume Activity Stack Boundary (*) Species Locations Samples 10" L/yr Ci/yr 10'" Ci/mL 10~2' pCi/mL Gross a 001 52 2.5 0.07 0.17 i 0.11 0.17 i 0.11 Gross # 001 52 2.5 0.19 1.12 i 0.19 1.12 2 0.19 Gross a 002 52 11.1 0.26 0.11

• 0.12 0.11 1 0.12 Gross #

002 52 11.1 0.87 0.58 i 0.10 0.58 i 0.10 Gross e 003 52 4.62 0.11 0.11 = 0.12 0.11 1 0.12 Gross p 003 52 4.62 0.30 0.46 i 0.18 0.47

• 0.18 Gross a 004 52 0.84 0.02 0.13 i 0.12 0.13
• 0.12 Gross #

004 52 0.84 0.06 0.53 2 0.19 0.53 i 0.19 Gross e 013 52 0.76 0.02 0.12 i 0.12 0.12 i 0.12 Gross p 013 52 0.76 0.06 0.58

• 0.19 0.58 i 0.19 3

Gross a 014 52 1.84 0.04 0.08 i 0.11 0.08

• 0.11 Gross p 014 52 1.84 0.12 0.47 i 0.18 0.47
• 0.18 Gross a 012 51 2.48 0.06 0.12
• 0.17 0.12
• 0.17 Gross #

012 51 2.48 0.29 0.56 1 0.26 0.56 i 0.26 Gross a 006 52 0.38 0.05 0.09 i 0.08 0.09

• 0.08 l

Gross p 006 52 0.38 0.37 0.72 2 0.22 0.72 = 0.22 l l (a) Site boundary concentrations were calculated by multiplying stack l concentrations by the average atmospheric dispersion parameter (1.0 x 10-8) co6aputed for the site boundary using computer code AIRD05-EPA (see Table 24 for data sets).

C: 30 0 TABLE 5. SU N RY OF SPECIFIC RA010NUCL10ES FROM STACK DilSSIONS--WEST JEFFERSON S11E--1991 Release Site Oerived Percent of Concentration Boundar Concentration DCG at the e Activity (x10'H) (x10.rs Guide Limit (C Site Species (d pCi/yrN Ci/mL(O pCi/mL() pCi/mL Boundary Co-57 0.72 0.29 0.29 2.0 x 10 l.5 x 10'" Co-60 1.50 0.61 0.61 8.0 x 10'" 7.6 x 10 Sr-90 0.13 0.05 0.05 9.0 x 10'" 5.6 x 10 Sb-125 3.30 1.35 1.35 1.0 x 10 l.8 x 10 Cs-134 1.05 0.43 0.43 2.0 x 10'" 2.15 x 10 Cs-137 1.47 0.60 0.60 4.0 x 10'" 1.5 x 10 Eu-152 2.73 1.12 1.12 5.0 x 10'" 5.6 x 10.a Eu-154 4.20 1.71 1,71 5.0 x 10'" 3.4 x 10'8 U-235 2.93 1.20 1.20 1.0 x 10"" 1.2 x 10'8 U-238 1.73 7.06 7.06 1.0 x 10'" 7.1 x 10 e 4 Pu-238 0.04 0.01 0.01 3.0 x 10'" 3.3 x 10 4 Pu-239 0.01 <0.01 <0.01 2.0 x 10'" 2.9 x 104 Am-241 1.79 0.73 0.73 2.0 x 10'" 3.7 x 10'5 (a) Identification of radionuclides in stack particulate emissions was by ganna spectrometric analysis of stack particulate air filters comoos-ite by stack location by month. In the absence of detectable activ-ity, calculated MDL values (a posteriori) were used to establish inventory of suspected radionuclides (based on age of residual fut1 contamination). (b) Activity is the sum of isotopic results for individual stacks iden-tified in Table 5 and figure 5. (c) Release Concentration is the result of Activity divided by the total stack volume of 2.451 x 10" L/yr. (d) Site boundary concentrations were calculated by multiplying stack concentration by the average atmospheric dispersion parameter (1.0 x 10) computed for the site boundary using computer 'de AIRD05 EPA 8 (see Table 24). (e) DOE Order 5400.5, U.S. Department of Energy, Washington, D.C., February 1990. O I e

J 31 3 stack locations were calculated by multiplying the individual stack concentra-tions by the atmospheric dispersion parameter computed using the atmospheric dispersion model incorporated in computer code AIRD05-EPA (see ref erence 11). Supplementary air sampling was performed at four site perimeter D locations during 1991 (figure 6). These aie samples were collected continu-ously and analyzed on a weekly basis for gross a and B activities. The average concentrations of activity at each of these locations were all statis-tically lower than the average gross a and p activities found at six of f-site D background air sampling locations previously surveyed weekly at distances varying 5 to 44 miles f rom the Nuclear Sciences Area. Quarterly composite air samples from the four site boundary locations were analyzed for Pu-238, pu-239, Sr-90, and ganm-emitting radionuclides (lable 6). D Water Monitoring--Radioactive A sanitary sewage system, which is operated in accordance with '3 State of Ohio regulations under NPDES Permit 41N00004*DO, handles all sanitary sewerage generated on the West Jefferson north site. The liquids are first treated in a 2,500-gallon septic tank and then released to a 2,160-sq-foot contained sand and gravel filter bed (figure 5), from the filter beti the J effluent goes to a chlorinating system prior to release to Big Darby Creek. Sampling of all sanitary liquid ef fluents f rom the Nuclear Sci-ences Area to Big Darby Creek is performed using a continuous water sampling system after discharge from the chlorinating system. The effluents samples 3 are analyzed weekly for gross a and p activity in suspended and dissolved 4 fractions. Any sample exceeding 3 x 10 Ci/mL receives a supplementary gamma isotopic analysis and/or an alpha spectrometric analysis as appropriate. The weekly samples are held, composited, and subjected to gamma spectrometric e analyses as well as specific analyses for plutonium-238, plutonium-239, iodine-129, strontium-90, radium-226, and radium-228 at the end of each month. The concentrations of gross a and gross p activity in suspended and dissolved fractions as well as the concentrations of specific radionuclides ident ' 'ied e in the sample are summarized in Table 7. In most cases, the activity in the samples has beca due to a mixture of nuclides. The average concentration of 3

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) 33 ) TABLE 6. SU W RY Of Si1E BOUNDARY A WEST JEffLR$0N SITE--1991(4{R SAMPLE ANALYSES 1 0'85 pCi/mL(H ) Nuclide North East South West Gross a 1.44, 0.54 1.52 4 0.56 1.39 i 0.56 1.09. 0.47 Gross p 14.0, 1.13 15.7 4 1.21 14.4 1.19 14.0 1.12 Co-57 <l.08 cl.06 <l.06 <l.06 ) Co-60 <2.52 <2.45 <2.40 <2.44 Sr-90(d <0.44 (0.44 <0.44 c0.44 Sb-125 <4.64 (4.2t <4.28 <4.53 Cs-134 <l.76 <l.65 <l.70 cl.72 ) Cs-137 <2.21 <2.13 <2.09 <2.06 Eu-152 <4.65 (4.64 <4.59 <4.61 Eu-154 <6.96 <6.79 (6.76 <6.59 ) U-235 <4.69 <3.33 <3.33 <4.58 U-238 <25.9 <24.2 <27.4 <26.8 Pu-238(d <0.057 <0.057 <0.057 <0.057 Pu-239(d <0.057 <0.057 <0.024 <0.024 ) _ -241 <2.75 <2.64 <2.75 <2.76 Am (a) Locations are shown in figure 6. North Quadrant Station 137.2 m north of JN-4 stacks); East Quadrant Station 21.9 m east of JN-1 stacks); South Quadrant Station 228.6 m south of JN-2 stacks); West Quadrant Station ) 121.9 m west of JN-2 stacks). (b) All isotropic values represent average MOL values (aposteriori). U-235, U-238, and Am-241 associated a produce higher values than gross a and p results would indicate. Gross a MOL is 3.0 x 10'38 Ci/mL and gross

1. MDL is 6.0 x 101' Ci/mL(apriori).

) (c) Detection limit is 4.66 x standard deviation of the back-ground, divided by the efficiency, assuming a 50*5 recovery of the spike and a flow volume of 2.7 E+9 mL. ) 2 ~.

O 34 O TABLE 7. Sutt%RY Of LIQUID RADIDACTIVE EHISSION--WEST JEFFERSON 51 TEM--199J Number Average of sam. Activityl Concentration DCG Percentage g pCi/yr( yCi/mL pCi/mL of DCG Specie., pins 0.46M Gross a 52 30.9 (3.68 i 3.30) x 10'C Gross # 52 173 (2.06, 0.17) x 10 00-57 12 107 1.3 x 10 l.0 x 10" 0.02 Co 60 12 167 2.0 x 10 5.0 x 10 O.60 Sr 90 12 25 3.0 x 10 l.0 x 10 e 0.08 Sb-125 12 345 4.1 x 10e 5.0 x 10'5 0.13 Cs-134 12 124 1.5 x 10 2.0 x 10 l.20 e Cs-137 12 187 2.2 x 10 3.0 x 10-e 0.97 Eu.152 12 368 4.4 x 10 2.0 x 10'6 0.32 Eu-154 12 440 5.2 x 10 2.0 x 10 O.43 Ra-226 12 16 1.9 x 10 l.0 x 10'7 1.50 8 Ra-228 12 14 1.6 x 10 l.0 x 10'7 0.90 1-129 1: 135 1.6 x 10-e 5.0 x 107 0.98 U-235 12 994 1.2 x 10'8 6.0 x 10'7 8.89 U-238 12 30.9 3.7 x 10 6.0 x 10'7 0.62 Pu-238 12 6.0 6.8 x 10'l' 4.0 x 10-e 0.40 Pu-239 12 3.0 2.9 x 10'!' 3.0 x 10a 0.13 Am-241 12 30.9

3. 7 x 10

3.0 x 10' 0.12 0 (a) Annual average flow in Big Darby Creek = 429 cu f t/sec = 3.82 x 10" L/yr. Total volume of liquid effluent discharge ar 1991 = 8.41 x 10' li ters. See figure 5 for sample location 010. (b) Isotopic data for ef fluents released at this location were obtained from ganna and radiochemical analysis of monthly composite samples where possible. In the absence of detectable activity, calculated 9 MDL values (a posteriori) were used to establish inventory on sus-pected radionuclides. Gross a values were used for alpha emitters U-238 and Am-241 using a conservative 100% of a activity. (c) No DCG listing for mixture of gross a and Value represents percent of total activity using 10 CFR Part 20, Appendix B limit (3 x 10) for mixture, not containing Sr-90,1-129. Ra-226 and e Ra-228. O l

D 35 ) the mixture was 0.48 percent of tot: limit value given in 10 CFR Part 20, Appendix B. The maximum concentratior.s of gamma-emitter suspected radionu-clides in the mixture was 8.89 percent for the DCG for U-235 e id 0.40 percent of the DCG for Pu-238, 0.13 percent for Pu-239, 0.08 percent for Sr-90, 1.E0 percent for Ra-226, and 0.90 percent for the Ra-228. The noncommunity drinking water supply at the West Jefferson site is exempt from radio %pical monitoring per OEPA review.W Mcwever, weekly tap water samples are colletteu at the Nuclear Sciences Area to verify compli-D ance with applicable water quality standards for radioactivity in drinking water. The weekly tap water samples are composited and analyzed monthly for gross a and p activity in suspended and dissolved fractions. Any sample exceeding 15 pCi/mL for gross a activity receives a supplementary gamma D isotopic analysis and/or an alpha spectrometric analysis as appropriate. In 1991, the average concentrations of gross a wa: 5.31 i 3.04 pCi/L (soluble) and 0.86 i 1.0 pCi/L (insoluble). The average concentrations of gross p were 2.37 1 0.83 pCi/L (soluble) and 0.86 4 0.54 pCi/L (insoluble). The total O gross a activity represents about 41 percent of the EPA standard of 15 pCl/L for gross a particulate activity in drinking water. Supplementary water samples are collecteti weekly 18.29 m above and 18.29 m below the sanitary drain outfall at Darby Creek. Water samples are D also collected weekly below the Battelle Lake dam and at the drain spillway at Darby Creek (Figure 6). The supplementary water samples are analyzed monthly for mixed a and p activity. The average concentrations of total activity in the downstream water samples and below the dam water samples were less than O 7.98 x 104 Ci/mL for a and less than 12.64 x 104 pCi/mL for activity and showed no significant difference from the upstream control sample (Table 8). These findings show that liquid effluent releases from the site to Darby Creek do not exceed background levels of radioactivity already present in Darby O Creek. Grass and Food Crops--Radioactive e Grass and food crop samples are collected from the surrounding area. The intent of this portion of the Environmental Monitoring Program is O

C 36 e TABLE 8.

SUMMARY

Of RADIOLOGICAL ANALYSES Of ENVIRONMENTAL WATER SAMPLES--WEST JEFFERSON SITE--1991 10 pCi/mL ) U b Location ) g (Direction and Distance Number of Gross a Gross p from Nuclear Sciences Area) Samples 0) 2 sigma 2 sigma Darby Creek Upstream 12 4.28 i 5.82 8.12 i 2.42 (18.3 m above sanitary outf all) Darby Creek Downstream 12 7.98 4 6.98 12.64 i 2.78 e' (18.3 m below sanitary outf all) Darby Creek Downstream 12 7.41 4 6.30 7.47 > 2.32 (186.3 m below sanitary outfall) Battelic Lake Spillway 12 4.29 4 4.68 6.17 i 2.14 (18.3 m below dam) 9 (a) locations are shown in figure 6. (b) Darby Creek and Battelle Lake Spillway samples are monthly com-posite samples of weekly collections. (c) A priori minimum detection limit for gross a is 6.5 x 10 Ci/mL and 4.8 x 10 pCi/mL for gross p. e 9 O 9 9 4

'O 37 O to determine whether there is uptake and concentration of radionuclides by plant or animal life. Where possible, sampling sites are chosen at maximum deposition locations predicted by meteorological studies. Grass and food crop (soybean or field corn) samples are collected at varying distances and direc- 'O tions within a 6-mile (9.6-km) radius of the Nuclear Sciences Area as shown in figure 7. Sampling locations falling within the same sector are composited. The samples are analyzed for plutonium-238, plutonium-239, and strontium-90. A qualitative analysis by gamma scan is also performed. The results of the O grass and food crop analyses are summarized in Tables 9 and 10. In both the grass and food crops, the levels of strontium-90, plutonium-238, and plutonium-239 were below the minimum detectable level for each isotope. Cesium-137 in grass was detected in insignificant amounts in Sectors 2, 4, ,0 and 5. I Garden Crops--Radioactive O There 6re two samples collected annually to access the impact on garden crops grown at the West Jefferson site. A composite sample of various vegetables from the Battelle employee garden area is compared to a composite of garden vegetables taken from an off-site location. Figure 7 shows the- 'O locations of the on-site and off-site garden plots. A gamma isotopic and plutonium-238, plutonium-239, and strontium-90 analyses were performed. The results of the analyses are shown in Table 11. A comparison of sample loca-tions shows that there is no real difference in the data values. Therefore, 'O there is no impact to the on-site garden. Sediment--Radioactive O Sediment samples were collected at five locations, i.e., Darby Creek 18.29 m above and 18.29 m below the point of sanitary effluent release to Darby Creek, the storm sewer outfall leading to Battelle Lake, the liquid effluent discharge point into Darby Creek, and at the dam spillway to Darby 40-Creek (see Figure 6)..The-purpose of collecting sediment samples is to esti-mate the inventory of certain radionuclides deposited in this waterway and' O .--_..,--,_.-~.._,._..-,-.--.-.....,_._--...__....---...._.___,em._,,

O-38 9' q l M t-. n 7,.p4%f ,/[T{d 'N 20 j < s,/ vQ \\ x l Sector 7 /' V ~ 3y pf 'g / i v6As 4 : t \\7 - - wth i-. 7',,74 ;. y [==g[ j j Wor 6 / ( ' *Y ng s _ 1 L e.5.WJ /1 1>s i V L ;qLP gy a. ,n w (f ,,,, s g % ggu _u .7yci e 10= 5:jl i D 11 7 w O Sector 10 ., j' t fferson Sector 5 'N I pp / .f t o M.- )p;' g/2u,Ager p ,L' N-nk.n "L7 Sector 9 O I 2 b - e' ' 1% l (, m q j, /' \\ SCALE OF MILES O' legend: A Food Crop, Soil and Vegetation 9 On Sne Garden Crops E CSSne Garden Crops 9: FIGURE 7. HAP OF GRASS, FOOD CR0P, AND S0ll SAMPLING LOCATIONS

O ' ' 4 LF 0-U U U TABLE 9. SLM4ARY OF RADIOLOGICAL ANALYSES OF GRASSN --WEST JEFFERSON SITE--1991 pCi/g dry wt. Sector Sector Sector Sector Sector Sector Sector Sector Sector Sector Sector Sector Nuclide 1 2 3 4 5 6 7 8 9 10 11 12 Co-57 <0.07 <0.07 <0.08 <0.28 <0.29 <0.27 <0.08 <0.10 <0.09 <0.10 <0.12 <0.11 Co-60 <0.13 <0.12 <0.14 <0.64 <0.67 <0.61 <0.16 <0.18 <0.15 <0.19 <0.20 <0.20 S r-90 <0.06 <0.06 <0.06 4.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 Sb-125 <0.25 <0.26 <0.27 <1.17 <1.23 <1.14 <0.28 <0.30 <0.27 <0.30 <0.3" <0.35 Cs-134 <0.09 <0.09 <0.11 <0.41 <0.43 <0.39 <0.11 <0.10 <0.11 <0.14 <0.12 <0.13 Cs-137 <0.11 0.05 <0.15 0.45 0.48 <0.48 <0.12 <0.15 <0.13 <0.17 <0.19 <0.17 Eu-152 <0.27 <0.24 <0.30 <1.31 <1.38 <1.16 <0.32 <0.34 <0.32 <0.40 <0.39 <0.40 Eu-154 <0.38 <0.41 <0.39 <1.62 <1.70 <1.56 <0.47 <0.41 <0.40 <0.53 <0.60 <0.52 w U-235 <0.13 <0.13 <0.15 <0.90 <0.95 <0.85 <0.85 <0.66 <0.62 <0.85 <0.82 <0.80 U-238 <2.38 <2.53 <2.70 <11.10 <11.70 <10.50 <2.74 <3.06 <2.63 <3.29 <3.78 <3.49 Pu-238 <0.006 <0.006 <0.006 <0.006 <0.006 <0.006 <0.006 <0.006 <0.006 <0.006 <0.006 <0.006 Pu-239 <0.003 <0.003 <0.003 <0.003 <0.003 <0.003 <0.003 <0.003 <0.003 <0.003 <0.003 <0.003 Am-241

1. '7

<0.28 <0.31 <0.98 <1.03 <0.89 <0.30 <0.33 <0.34 <0.38 <0.43 <0.38 (a) Locatici,5 are shown in Figure 7.

i l TABLE 10. SUPHARY OF RADIOLOGICAL ANALYSES OF FOOD CROPS'*)--WEST JEFFERSON SITE--1991 pCi/g dry wt. Sector Sector Sector Sector Sector Sector Sector Sector Sector Sector Sector Sector Nuclide 1 2 3 4 5 6 7 8 9 10 11 12 Co-57 <0.03 <0.04 <0.04 <0.03 <0.04 <0.04 <0.04 <0.03 <0.03 <0.03 <0.03 <0.04 Co-60 <0.06 <0.08 <0.09 <0.06 <0.09 <0.08 <0.07 <0.06 <0.07 <0.05 <0.05 <0.08 Sr-90 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 ~0.11 <0.1? Sb-125 <0.01 <0.13 <D.13 <0.10 <0.15 <0.15 <0.11 <0.11 <0.12 <0.10 Cs-134 <0.04 <0.05 <0.04 <0.04 <0.05 <0.05 <0.05 <0.04 <0.04 <0.04 <0.04 <0.05 Cs-137 <0.05 <0.05 4.06 <0.05 <0.06 <0.05 <0.05 <0.04 <0.06 <D.05 <0.04 <0.06 Eu-152 <0.12 <0.13 <0.13 <0.12 <0.13 <0.15 <0.13 <0.14 <0.11 <0.12. <0.12 <0.13 Eu-154 <0.14 <0.25 <0.22 <0.16 <0.28 <0.20 <0.18 <0.16 <0.16 <0.15 <0.17 <0.22 g U-235 <0.25 <0.07 <0.27 <0.23 <0.29 <0.27 <0.27 <0.06 <0.25 <0.06 <0.24 <0.07 U-238 <1.05 <1.00 <1.00 <1.04 <0.89 <1.19 <1.22 <1.05 <1.20 <1.07 <1.01 <1.01 Pu-238 <0.006 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 <0.06 Pu-239 <0.003 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 <0.C3 Ara-241 <0.12 <0.14 <0.14 <0.12 <0.15 <0.13 <0.13 <0.12 <0.12 <0.11 <0.12 <0.13 (a) Locations are shown in Figure 7. I i I e o e e e e 0

) 41 ) TABLE 11. StM MRY OF RAQ10 LOGICAL ANALYSES Of GAR 0EN CR0PS(U--WEST JEFFERSON SITE--1991 ) pCi/g dry wt. Nuclide On-Site (b) Off-Sited) Co-57 <0.03 <0.15 Co-60 <0.07 <0.36 ) Sr-90 <0.02 <0.08 Sb-125 <0.11 <0.64 Cs-134 <0.04 <0.25 Cs-l O.05 <0.30 ) Eu-152 <0.12 <0.72 Eu-154 <0.18 <1.03 U-235 <0.06 -1). 73 U-238 <l.12 <4.58 g Pu-238 <0.009 <0.02 Pu-239 <-0.006 <0.009 Am-241 <0.12 <0.52 ) (a) Garden crops collected at the end of the (b) growing season. Locations are shown in Figure 7. U ) ? )

O. 42 document it for future reference. The sediment samples were analyzed for plutonium-238, plutonium-239, and strontium-90. A quantitative gamma isotopic analysis was also perfonned and shows a positive result of 12.5 pCi/9 of Am-241, 30.8 pCi/g of Cs-137, and 22.4 pCi/g of Co-60 at the storm sewer out-fall (ED-1 on figure 6).. The outfall area has been under study for remedia-tion. Samples taken from other points indicate the levels are at or below upstream levels. The complete results of the sediment analyses are summarized in Table 12. G' Soil--Radioactive Soil samples are collected annually from 20 locations at varying distances and directions within a 6-mile (9.6-km) radius of the Nuclear Sci-ence Area. Locations (Figure 7) falling within the same sector are compos-ited. The soil samples are collected to a depth of 10 cm using a 10-c., soil plugging tool. Each soil sample consists of a composite of five " plugs" of i soil ccliected at random from an area of approximately 1 m. Prior to anuly-sis, the composite samples are air dried and then blended in a pulverizing mill. The soil samples are analyzed for plutonium-238, plutonium-239, and strontium-90. A qualitative analysis by a gamma spectrometry scan is also performed. The results of the analyses are summarized in Table 13. Strnntium-90 and plutonium results were below the minitum detect-able level for these isotopes. Gamma isotopic analyses of the soil samples showed the maximum average concentration of cesium-l?7 to be 0.)2 pC /g. The cesium is believed to be attributable to the settling out of the atmospheric releases from off-site, and not on-site activities. Fish--Radioactive e Fish are collected on a quarterly basis from Battelle Lake and Darby Creek, as available, to determine if any radioact.ive material is getting into the food chain, fish collection in Darby Creek is limited to within a hundred yards of the liquid effluent outfall and the Battelle Lake spillway. The fish tissue is analyzed for gamma isotopes, plutonium-238, plutonium-239, e

) 43 D TABLE 12. SUHKARY OF RADIOLOGICAL ANALYSES OF SEDIMENT SAMPLES--WEST,-ffERSON SITE--1991 pCi/g dry wt.(d Avg. I Nuclide ED-1(O ED-2 ED-3 ED-4 ED-5 Co-57 <0.03 <0.02 <0.03 <0.04 .03 Co-60 22.4 <0.05 <0.05 <0.06 <0.06 Sb-125 <0.40 <0.08 <0.06 <0.09 <0.09 Cs-134 0.59 <0.03 <0.03 <0.03 <0.04 Cs-137 30.8 1.52 0.09 0.76 <0.03 Eu-152 <0.35 <0.08 <0.09 <0.10 <0.10 Eu-154 <0.29 <0.12 <0.12 <0.14 <0.15 U-235 <0.05 <0.03 <0.03 <0.03 <0.04 U-238 <1.49 <0.55 <0.52 <1.03 <1.03 Sr-90 4.1'i 0.52 <0.40 <0.40 0.80 Pu-238 1.38 0.09 0.06 0.05 0.11 Pu-239 55.90 0.04 0.04 0.03 0.05 Am-241 12.5 <0.09 <0.14 <0.12 <0.12 l (a) No standards for radionuclides in sediment have been established. (b) Location EO-1 has undergone more detailed evaluation. Results are documented in FINAL ASSESSMENT OF THE RADIOLOGICAL STATli 0F BATTELLE'S NUCLEAR SCIENCES AREA dated January 1991. See Figure 6 for locations. = I

TABLE 13. StRNARY OF S0ll ANALYSESM--WEST JEFFERSON Sisi--1991 pCi/9 dry wt. Sector Sector Sector Sector Sector Sector Sector Sector Sector Sector Sector Sector l Nuclide 1 7 3 4 5 6 7 8 9 10 11 12 Co-57 <0.03 <0.03 <0.03 <0.03 <0.04 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 (0.03 I Co-60 <0.07 <0. '17 <0.06 <0.06 <0.07 <0.06 <0.06 <0.06 <0.06 <0.05 <0.06 <0.07 Sr-90 <0.40 <0.40 <0.40 <0.40 <0.40 <0.40 <0.40 <0.40 <0.40 <0.40 <0.40 <0.40 l Sb-125 <0.11 <0.11 <0.10 <0.12 <0.12 <0.11 <0.12 <0.11 <0.13 <0.10 <0.10 <0.11 l Cs-134 <0.04 <0.04 <0.04 <0.04 <0.05 <0.04 <0.04 <G.04 <0.03 <0.04 <0.04 <0.04 Cs-137 0.25 0.20 0.11 0.44 0.72 0.62 0.40 0.31 0.59 0.30 0.36 0.26 Eu-152 <0.12 <0.11 <0.11 <0.12 <0.12 <0.10 <0.13 <0.13 <0.11 <0.10 <0.11 <0.11 Eu-154 <0.18 <0.19 <0. '. 7 <0.18 <0.19 <0.15 <0.16 <0.16 <0.17 <0.16 <0.16 <0.17 g U-235 <0.04 <0.04 <0.04 <0.04 <0.04 <0.04 <0.04 <0.07 <0.04 <0.04 <0.04 <0.04 U-238 <0.62 <0.61 <0.60 <0.061 <0.65 <0.60 <0.62 <0.01 <0.57 <0.57 <0.56 <0.57 Pu-238 <0.03 <0.03 <0.03 <0.03 <n 03 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 Pu-239 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 Am-241 <0.14 <0.15 <0.13 <0.15 <0.16 <0.13 <0.14 <0.14 <0.'2 <0 0.13 <0.15 (a) Locations are shown in Figure 7. O O O O O O O O O O O

) 45 and strontium-90. Table 14 sumarizes the 1991 data from the analyses. All of the analyses showed undetected levels except for very low levels of Cesium-137, which is believed to be from radioactive fallout not associated with the Battelle facility. No fish were collected from Darby Creek in 1991 due to D poor collection conditions. Background Radiation Levels The limit established for the general public by the Department of Energy is 100 mrem /yr.W This value does not include the contribution from natural background radiation, which, in previous years, averaged approximately 130 mrem /yr off site. Figure 8 shows tha location of the 16 dosimetry sta-D tions that continuously monitor the external radiation background levels at the West Jefferson site. The dosimetry stations are equipped with comer-cially available environmental TLD packets that are changed and evaluated each calendar quarter. Based on data provided by the 16 dosimeter stations, the D 1991 annual average dose including background at the site boundary is 120 i 10 mrem. The results are summarized in Table 15. Fence Post Duse Estimate D The " fence post" dose is the maximum measured cumulative dose pos-sible to an individual having access to an uncontrolled area. It does not include ingestion and iahalation pathways. The " fence post" dose for 1991 was D equal to or less than the annual average TLD background reading of 120 mrem measured at off-site background monitoring stations. KING AVENUE SITE D Air--Radioactive There were no radiological releases from stacks at the King Avenue f site in 1991. However, one environmental air sample was collected at the east p boundary of Battelle property along Battelle Boulevard. This sample may serve as a reference for future D&D activities and will provide evidence to the B l ~ - - -. -

O 46 O TABLE 14. Sutt4ARY OF FISH TISSUE ANALYSESN--WEST JEFFERSON SITE--1991 pCi/g raw wt. Sample Quarter 1stN 2nd 3rd 4th Avg. g Co-57 <0.51 <0.28 <0.23 <0.49 <0.38 Co-60 <l.01 <0.40 <0.36 <0.76 <0.63 Sr-90 <0.04 <0.06 <0.05 <0.08 <0.05 Sb-125 <2.07 <0.79 <0.72 <1.57 <l.29 9: Cs-134 <0.70 <0.27 <0.'8 <0.56 <0.45 c Cs-137 <0.87 0.18 <0.30 <0.63 0.49 Eu-152 <1.85 <0.77 <0.73 <0.163 <l.25 Eu-154 <2.55 <0.94 <0.96 <2.13 <1.65 U-235 <2.98 <0.49 <0.50 <l.08 <l.26 U-238 <16.00 <13.20 <4.90 <13.20 <11.83 Pu-238 <0.04 <0.02 <0.02 <0.02 <0.02 Pu-239 <0.02 <0.01 <0.01 <0.02 <0.01 Am-241 <1.92 <0.53 <0.52 <1.15 <l.03 NR = Data not received from laboratory. (a) Fish samples were collected from various locations within Battelle 9 Lake. (b) First quarter results are average for bottom and non-bottom feeders, all others are for non-bottom feeders only. G l l 0 l 9 l 9

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O 48 9 TABLE 15. INTEGRATED EXTERNAL BACKGROUND RADIATION HEASUREMENTS Af RECREATION AREA AND PROPERTY BOUNDARY LINE--WEST JEFFERSON SITE--1991 Integrated TLD Measurements in rem 9 f DistanceN lst Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Year Southwest 121.9 m 400 ft) 0.030 0.030 0.030 <0.030 <0.120 420.6 m 600 ft) 0.030 0.030 0.030 <0.030 <0.120 731.5 m 2400 ft) 0.030 0.030 <0.030 <0.030 <0.120 8 1234.5 m (4050 ft) 0.030 0.030 <0.030 <0.030 <0.120 West 152.4 m (500 ft) 0.030 0.030 0.030 <0.030 <0.120 630.9 m (2070 ft) 0.030 0.030 0.030 <0.030 <0.120 Southeast 8 T65 8 m (1200 ft) 0.030 0.030 0.030 <0.030 <0.120 1005.9 m (3300 ft) 0.030 0.030 <0.030 <0.030 <0.120 South 19E 9 m (1200 ft) 0.030 <0.030 0.030 <0.030 <0.120 411.5 m (1350 ft) 0.030 0.030 <0.030 <0.030 <0.120 e 548.6 m (1800 ft) 0.030 0.030 (0.030 <0.030 <0.120 1097.3 m (3600 ft) 0.030 0.030 0.030 <0.030 <0.120 East 420.6 m (1380 ft) 0.030 0.030 0.030 <0.030 <0.120 Northeast 9 395.9 m (1200 f t) 0.030 0.030 0.030 <0.030 <0.120 Northwest T02.3 m (1320 ft) 0.030 0.030 0.030 <0.030 <0.120 North TB D m (1500 ft) 0.030 0.030 0.030 <0.030 <0.120 (a) Refer to Figure 8. Average off-site background for year <0.120 rem. 9 9 9

D 49 O neighborhood that no radiological impact has resulted from the BCLOP opera-tions. The results in Table 16 are considered to be background levels of 1.43 x 10-" uCi/mL gross a and 1.43 x 10'" Ci/mL gross p. Table 16 also includes the res ults of the gamma spectrometry scans done for the King Avenue 3 samples. The results are all below the detection limit. Water--Radioactive 8 Sampling of liquid discharges from the Building 3 sump to the Columbus municipal sewerage system is performed on a monthly basis (Figure 4). This discharge consists of the liquid wastes from the building laboratory drain systems. The building sump samples are routinely analyzed for gross a O and gross p activities. Any sample exceeding 4 x 10'7 Ci/mL (400 pCi/L) receives a gamma isotopic analysis and/or an alpha spectrometric analysis as necessary. The concentrations of gross a and gross p activity are summarized in Table 17. The average concentrations at all discharge points were well D below NRC standards as well as the DOE's DCG for the most restrictive p activ-ity in the uranium decay chain. Soil--Radioactive O Seven soil samples were collected at various points around the King Avenue site (Figure 4). One was collected from The Ohio State University Agriculture campus north of the Battelle site as a background reference. The D same technique was used as that for soil collected for the West Jefferson off-site soil samples. The data from these collections are presented in Table 18. There was no evidence of uranium in the soil sample above detectable levels. There was, however, evidence of Cs-137 in the King Avenue site soil while none D was detected in the background sample. No cesium operations are being con-ducted at King Avenue. The cesium is in the same range as that seen in West Jefferson off-site samples. This suggests that the cesium is from fallout and not operations. D O

O 50 9 TABLE 16. RADIOLOGICAL ANALYSES OF ENVIRONMENTAL AIR SAMPLES (0--KING AVENUE SITE--1991 Average Number of Concentration e Nuclides Samples Ci/mL i 2 sigma Percent of DCG Gross a 51 1.43 i 0.58 x 10-35 ---(O Gross p 51 1.43 i 0.12 x 10-" -- CH Co-57 4 <1.06 5.3 x 10-5 en Co-60 4 <2.31 2.9 x 10-3 Sb-125 4 <4.63 4.6 x 10-' Cs-134 4 <1.71 8.6 x 10-' Cs-137 4 <2.06 5.2 x 10-4 4> Eu-152 4 <4.51 9.0 x 10-3 Eu-154 4 <6.35 1.3 x 10-2 U-235 4 <7.04 7.0 U-238 4 <27.6 27.6 Am-241 4 <2.69 13.4 (a) Sample location EA-15, identified in Figure 4. (b) DOE 5400.5 does not list DCG limits for mixed a and # activity. O' O O' 9' l e

O-51 0 TABLE 17. RADIOLOGICAgANALYSESOFLIQUID DISCHARGES (* -KING AVENUE SITE--1991 Average o Number of Concentration Sample (*) Species Samples pCi/L i 2 sigma 005(6) Gross a 12 4.0 i 4.4-Gross p 12 7.6 2 2.3 EW-6(*) Gross a 12 4.1 i 5.0 0 Gross p 12 21.4 i 3.3 EW-7 Gross a 12 5.5 i 4.8 Gross p 12 7.0 2 2.2 EW-8 Gross a 12 3.4 i 4.2 Gross p 12 10.6 2 2.5 O EW-9 Gross a 12 6.2 i 5.6 Gross p 12 18.6 i 3.2 EW-13 Gross a 12 3.2 i 3.9 Gross B 12 6.3 2 2.1 O a Locations identified in Figure 4. b Also identified as EW-14. c EW samples are supplemental samples collected from various sumps and discharge points throughout the King Avenue Site. O O O ' O O

O 52 O TABLE 18. RADIOLOGICAL ANALYSES OF SOIL SAMPLES--KING AVENUE SITE--1991 Nuclide (pCi/g) Sampie(*) U-238 U-235 Cs-137 KAES-01 <0.60 <0.04 0.97 KAEA-02 <0.57 <0.04 0.48 KAES-03 <0.60 <0.04 0.27 KAES-04 (0.60 <0.04 0.18 KAEA-05 <0.60 <0.04 0.17 KAES-05 <0.60 <0.04 0.19 KAEA-07 <0.60 <0.04 0.28 qp KAES-08 <0.61 <0.04 <0.02 (a) locations are identified in Figure 4, except KAES-08, which is an off-site sample taken from The Ohio State University Agriculture Campus. 45' db 6 4 e 9

h 53 9 Vegetation--Radioactive Eight samples of vegetation were collected at points around the King Avenue site. Seven of these samples were collected on Battelle's 8 property. See Figure 4 for exact locations. Another sample was collected from The Ohio State University Agriculture campus ncrth of the Battelle site as a background reference. The samples were analyzed for Uranium-235, Uranium-238, and Cesium-137. Data from these analyses is represented in S Table 19. There was no evidence of either uranium isotope above detectable levels in any of the samples. There were detectable levels of cesit.- in both the on-site and off-site samples. The source of cesium is believed to be from fallout and not site operations. O ENVIRONMENTAL NONRADIOLOGICAL PROGRAM INFORMATION The drinking water system at the West Jefferson site is monitored 9 under OEPA regulations, which regulate all public water supplies. As a non-community water supply, Battelle is required to perform quarterly sampling for microbiological contamination, quarterly sampling for volatile organic com-pounds (VOCs), and a nitrate analysis every three years (7) The results of 9 the quarterly tests for microbiological contamination all showed no contamina-tion (<1 colony /100 mL) and were reported as being " safe." VOC sampling showed some VOCs at just above the detection level.' The source of VOC con-tamination is believed to be sampling error rather than groundwater contamina-O tion. The suspected sources of contamination are being investigated. The last nitrate analyses were below the established Maximum Contamination Level J (MCL) value of 10 mg/L. Battelle has complied with the public notification regulations enacted to warn of the dangers of lead in drinking water. Presently, liquid effluents discharged from the West Jefferson Facility are subject to the restrictions of an NPDES Permit. Battelle moni-tors and reports on a monthly basis to the OEPA. Table 20, Nonradiological ' Total xylenes were found in the first and third quarters of a concentration of around 1 pg/L. The EPA's maximum contaminant level for drinking water is 10,000 g/L.

C 54 e TABLE 19. RADIOLOGICAL ANALYSES OF VEGETATION SAMPLES-- KING AVENUE SITE--1991 Nuclide (pCi/g) Sample (') U-238 U-235 Cs-137 KAEV-01 <7.31 <0.75 0.70 KAEV-02 <10.70 <0.87 <0.52 KAEV-03 <l.33 <l.33 <0.81 gp KAEV-04 <7.01 <0.69 <0.40 KAEV-05 <10.10 <0.82 <0.50 KAEV-06 <11.10 <0.00 <0.51 KAEV-07 <13.60 <l.11 <0,71 gp KAEV-08 <7.75 <2.07 <0.40 (a) Locations are identified in figure 4, except KAEV-08, which is an off-site sample taken from The Ohio State University Agriculture Campus. O e e e G e

l TABLE 20. NONRADI0 LOGICAL WATER EFFLUENT ANALYSES--WEST JEFFERSON SITE--1991 Permit Requirements') I North Sanitary System Sewer (*) Discharge Limitations Loading Concentration kg/ Day kg/ Day Other Units Avg. Max. Min. Avg.N 30-Day Daily 30-Day Daily Flow Rate (1/ day) W 23,041 37,415 1,340 Residual Chlorine (mg/L) 0.49 1.8 <0.1 0.01 0.5 ( pH Value (S.U.) 7.90 8.48 7.45 6.5 to 9.0 Fecal Coliform (#/100 mL) 230.2 1,150 0 1,000 2,000 Dissolved Oxygen (mg/L) 7.6 9.3 6.7 6.0 6.0 Total Suspended Solids 2.3 8.0 0.0 0.05 0.49 0.098 10 20 (mg/L) B.0.D. (5-day) (mg/L) 3.6 4.5 3.1 0.08 1.23 1.87 25 38 Ammonia (mg/L) 0.31 0.56 0.24 (a) Sampling site location is labeled 010 on Figure 5 (referred to as 001 in monthly NPDES reports). Includes discharge from Middle Area Sanitary System. (b) Based on a flow rate of 6,082 gpd. (c) Pemit requirement discharge limitations based on NPDES Pemit 41N00004*DD. (d) No restrictions for flow or ammonia under the NPDES Permit.

C< 56 9 Water Effluent Analyses--West Jefferson Site, includes a list of parameters for which Battelle is presently required to analyze and report. The data provided for the North Sanitary Sewer were ot>tained in accordance with the NPDES Permit 41N00004*DD issued by the OEPA. The conditions of Battelle's NPDES Permit were determined by the OEPA fallowing an extensive study of the Scioto River Basin,W of which Battelle's West Jeffer-son site is a part. All readings were within acceptable limits as specified in the permit for 1991, except for the total suspended solids readings in January and May, and total residual chlorine levels in July. The values listed in Table 20 represent an average of the monthly data collected during the 12-month period commencing January 1,1991, and ending December 31, 1991. The table serves to illustrate actual performance against those limits or restrictions defined in Battelle's permit. Battelle was issued a renewal to its NPDES Permit in July 1991. The new permit con-tained additional parameters to monitor in the effluent, but no substantial change to the allowable discharge limits. Additional nonradiological monitoring was done on three monitoring wells at the West Jefferson site. A discussion of the results car be found in the following section. The BCLDP does no environmental air monitoring for nonradiological parameters at either the King Avenue or West Jefferson sites. GROUNDWATER PROTECTION Groundwater monitoring has been increased at the West Jefferson site to include a total of 18 shallow and deep wells. These include three supply wells at a depth of approximately 150 feet, three wells designed for chemical monitoring at a depth of approximately 30 to 35 feet, and 13 shallow wells at a depth of approximately 10 to 15 feet. Figures 9 and 10 indicate 8 the location of shallow and chemical monitoring wells. The supply wells are l associated with facilities identified in Figures 5 and 6. Detailed chemical monitoring was performed and reported in Interim Report on Site Characteri-zation--West Jefferson North Site--Stage 1 Sampling and Analysis: Chemical O l l

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Sampling Summary Report, dated December 22, 1989. No contamination was found in grcundwater samples collected at that time. M Annual radiological monitoring results are presented in Table 21. The highest activity is shown to be in well 110, where radioactivity remains O in a former remediated filter bed. This area has been recommended for further remediation in the Final Assessment of the Radiological Status of Battelle's Nuclear Sciences Area, dated January 1991. Detailed chemical analyses were performed on groundwater samples O collected December 27, 1991, from the three chemical monitoring wells. Sam-ples from all three wells were analyzed for eight heavy metals, 27 pesticide and PCB compounds, 35 VOCs, 66 semivolatile organic compounds, oil and grease, and pH. All compounds in all of the samples were below the levels of detec-O tion or quantification, except for phenol in the sample from well C03, where the phenol concentration was 17 pg/L (Table 22). Phenol is a naturally occur-ring compound in the environment and there are no known or suspected sources of phenol at the site. Phenol concentrations will be reviewed in subsequent O samplings to determine if there are any trends. O O O O O

O. 60 0 TABLE 21. RADIOLOGICAL ANALYSES OF GROUNDWATER--WEST JEFFERSON SITE--1991 pCi/L(*) Well Number of Gross a Gross p g, Identification Samples 2 sigma 2 sigma i i JN 1 3.5 i 4.9 6.3 i 2.0 JM 1 5.1 1 5.4 4.0 i 1.8 JM-1 1 2.6 i 4.6 4.8 i 1.8 C03 1 15.0 i 9.1 11.0 i 2.5 C09 1 8.9 i 7.7 42.5 1 4.3 C16 1 2.5 i 6.0 4.8 i 2.0 101 1 70.5 i 32.7 77.4 i 9.0 gp 104 1 36.4 i 18.4 30.8 i 5.6 110 1 55.2 1 35.0 134.0 i 12.1 150 1 12.3 1 7.8 12.1 i 2.5 155 1 6.8 1 7.1 8.2 i 2.3 4D 168 1 9.7 1 7.8 20.8 1 3.1 172 1 39.8 i 18.0 46.3 1 6.5 206 1 11.1 i 8.9 20.2 i 3.2 8' 306 1 8.1 i 8.5 13.3 i 2.8 403 1 11.3 i 13.6 18.4 1 4.9 506 1 49.2 1 26.5 52.8 1 7.5 601 1 17.0 1 20.4 29.2 1 6.2 (a) Minimum Detection Limit (MDL) for gross a: 1.0 pCi/L; gross 2.9 pCi/L. O e e

D 61 ) TABLE 22. NONRAD10 LOGICAL ANALYSES OF GROUNDWATER--WEST JEFFERSON SITE--1991 -iLUnt2K.23 Chemical Parameter Well LO3 Well C09 Well C16 ) Total Metals (mg/L) As <0.04 <0.04 <0.04 Ba <1 <1 <1 Cd <0.1 <0.1 <0.1 Cr <0.2 <0.2 <0.2 Pb <2 <2 <2 ~ ) Hg <0.005 <0.005 <0.005 Se <0.04 <0.04 <0.04 Ag <0.4 <0.4 <0.4 Pesticides and PCBs (pg/L) p 27 compounds BDLN BDL BDL Volatile Organics ( g/L) 35 compounds BQL ) BQL BQL D Semivolatile D Compounds (pg/L) 66 compounds Phenol: 17 pg/L BQL BQL Others: BQL Oil and Grease (mg/L) <1 <1 <1 pH 7.1 6.9 7.2 3 (a) BDL = Below Detection Limit. l (b) BQL = Below Practicai Quantification Limit. D D

C 62 EVALVATION OF DOSE TO THE PUBLIC 8 ESTIMATED DOSE TO T!!E PUBLIC FROM WEST JEFFERSON Si1E EMISSIONS DURING 1991 O The environmental monitoring data for 1991 presents information for determining sources of environmental radiation resulting from past or current nuclear activities and from atmospheric nuclear tests or natural radi-oactivity. Contributions from Batte11e's nuclear operations were indistin, g guishable from other sources with two exceptions. These include minimal airborne releases of mixed fission products from Hot Cell Laboratory activi-ties and very low concentrations of mixed fission products in liquid effluents at the West Jefferson Nuclear Sciences Area. The radiological impact of e Battelle's nuclear activities is calculated from the quantity of radionuclide.; assumed directly in effluents from facilities operating in 1991, from the annual deposition of airborne radionuclides on vegetation and food crops, and from residual radionuclides in stream sediment associated with past g operations. Atmospheric Discharges e Calculated releases and ground level annual average concentrations at the site boundary during 1991 for the West Jefferson site are summarized in Tables 3, 4, 5, and 6. The downwind position froni the facility where the annual ground level concentrations will be highest is considered coincident a with the site bo sidary, which determines the perimeter for uncontrolled expo-sure. This point is on Battelle property within the site boundary line. The gross data in Table 4 show that the total n4xed fission product releases for 1991 amounted to E.8 Ci, with a total average concentration at the site boundary of about 1 x 10

• Ci/mL.

If all the alpha emissions are considered to be plutonium-239 only, the annual average concentration at the site bound-ary still would be less than 2 x 10

• pCi/mL.

The total isotopic composition of the efflueats assumed to be emitte: from the seven stacks of the JN-1 g 9

D 63 facility and two stacks of JN-2 war, used in evaluating the off-site dose to the public. Liquid Discharges e Measured aqueous releases and effluent concentrations during 1991 for the West Jefferson site are summarized in Table 7. The concentration val-ues apply to the water discharged into Big Darby Creek after passage through a 9 settling tank and enclosed surface sand filter. Based on a knowledge of the isotopic composition of radionuclide concentrations released to the surface sand filter, emissions should be due to very limited elution of contaminants from the surface sand filter that were delivered to the bed in the past few years. The release inventory values are based on minimum detectable limits of isotopes listed in Table 7. ESTIMATED RADIATION DOSE TO THE PUBLIC FROM ATHOSPHERIC DISCHARGES 6 Calculation of Atmospheric Dispersion Parameters Average meteorological data from the Columbus area were used as input to compute the average dispersion parameters for the site. The computer code, COMPLY,(l') was run to further establish the minimal impact of site air emissions when it became apparent that certain nuclides listed in the inven-tory were not listed in AIRDOS-PC(") nuclide library. AIRDOS-EPA,(12) pro-grammed for localized applications (see Table 23), was used to generate detailed X/Q data presented in Table 24. Thus, average X/Q values were devel-oped for a series of concentric rings extending from the site boundary out to a distance of 80 km (50 miles). The rings were broken down into sixteen sectors corresponding to the normal wind rose pattern (refer to Figure 11). 4 e l

._ ;7 _--.7 m. ~_ 3 fo; 64 -- 4 TABLE 23. AVERAGE PERCENT FREQUENCY OF WIND-DIRECTION AND-O

AVERAGE WIND SPEED y

Average-Direction Percent Speed (m/s) N 4.5 4.7. NNE 4.1-4.2' NE 4.8 .4.0 ENE 5.0 4.1 g E 5.8 4.4 ESE 4.7 3.8 SE 5.0 4.3 SSE 4.3 3.8 9-S 5.5 4.5 SSW 8.1 4.9 SW 11.5 5.5 WSW 8.3 = 5. 3 -- '8 W 7.8 5.1 WNW 6.5 4.9L NW: 6.1 4.6 - NNW 4.2 4.2 CALM. 3.8 TOTAL 100.0-4.5 O O O L l L g.

v m v m m TABLE 24. AVERAGE ATMOSPHERIC DISPERSION AROUND THE WEST JEFFERSON SITE FROM AN 18-METER HEIGHT STACK RELEASE (*)--1991 Range in km (elles) Direction-0.65 (0.4)- 1.15 (0.7) 3.0 (1.9) 4.25 (2.6) 5.05 (3.1) 6.4 (4.0) 9.6 (6.0) 18 (11.2) 32 (20) 48 (30) 64 (40) N 9.39 E-7 4.15 E-7 1.48 E-7 1.04 E-7 8.59 E-8 6.46 E-8 3.70 E-8 1.55 E-8 5.17 E-9 2.82 E-9 1.34 E-9 NME 1.38 E-6 6.09 E-7 1.91 E-7 1.29 E-7 1.06 E-7 7.87 E-8 4.48 E-8 1.88 E-8 6.69 E-9 3.70 E-9 1.93 E-9' NE 1.60 E-6 6.98 E-7 2.09 E-7 1.40 E-7 1.14 E-7 8.46 E-8 4.81 E-8 2.02 E-8 7.31 E-9 4.07 E-9 2.19 E-9 ENE 1.16 E-6 5.05 E-7 1.67 E-7 1.15 E-7 9.46 E-8 7.08 E-8 4.05 E-8 1.70 E-8 5.82 E-9 3.19 E-9 1.60 E-9 E 1.09 E-6 4.75 E-7 1.61 E-7 1.11 E-7 9.16 E-8 6.87 E-8 3.93 E-8 1.65 E-8 5.59 E-9 3.06 E-9 1.51 E-9 ESE 1.11 E-6 4.90 E-7 1.64 E-7 1.13 E-7 9.34 E-8 7.00 E-8 '4.00 E-8 1.68 E-8 5.73 E-9 3.14 E-9 1.56 E-9 SE 1.04 E-6 4.61 E-7 1.58 E-7 1.10 E-7 9.05 E-8 6.79 E-8 3.89 E-8 1.63 E-8 5.52 E-9 3.02 E-9 1.47 E-9 SSE - 7.17 E-7 3.18 E-7 1.27 E-7 9.09 E-8 7.60 E-8 5.77 E-8 3.32 E-8 1.39 E-8 4.41 E-9 2.38 E-9 1.05 E-9 5 7.68 E-7 3.40 E-7 1.32 E-7 9.37 E-8 7.82 E-8 5.92 E-8 3.40 E-8 1.43 E-8 4.58 E-9 2.47 E-9 1.11 E-9 55W 7.01 E-7 3.10 E-7 1.25 E-7 8.97 E-8 7.51 E-8 5.70 E-8 3.28 E-8 1.37 E-8 4.33 E-9 2.33 E-9 1.02 E-9 SW 1.08 T-6 4.95 E-7 1.69 E-7 1.17 E-7 9.62 E-8 7.21 E-8 4.12 E-8 1.75 E-8 6.09 E-9 3.36 E-9 1.67 E-9 WSW 8.54 E-7 3.77 E-7 1.40 E-7 9.85 E-8 8.19 E-8 6.18 E-8 3.55 E-8 1.49 E-8 4.86 E-9 2.64 E-9 1.22 E-9 W 9.91 E-7 4.38 E-7 1.53 E-7 1.07 E-7 8.82 E-8 6.62 E-8 3.79 E-8 1.59 E-B 5.34 E-9 2.92 E-9 1.41 E-9 WW 1.06 E-6 4.85 E-7 1.67 E-7 1.15 E-7 9.53 E-8 7.14 E-8 4.08 E-8 1.73 E-8 6.02 E-9 3.32 E-9 1.65 E-9 m 8.54 E-7 3.77 E-7 1.40 E-7 9.85 E-8 8.19 E-8 6.18 E-8 3.55 E-8 1.49 E-8 4.86 E-8 2.64 E-9 1.22 E-9 NW 9.70 E-7 4.46 E-7 1.58 E-7 1.10 E-7 9.11 E-8 6.84 E-8 3.92 E 1.66 E-8 5.69 E-9 3.13 E-9 1.52 E-9 (a) Units are SEC/M3. Distances are given to the center of the sector; 64 km extends to 80 km. Atmospheric dispersion table is taken from output of computer code AIRD05-EPA.W l 1 -,-n

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D 67 8 Computation of Dose Equivalent Rates to Nearby Individuals and Population Groups The annual radiation dose from particulate radionuclides assumed to be discharged into the atmosphere was computed for a person continuously immersed in an infinite hemispherical cloud containing the radionuclides. Stack release data (see Table 5) are used to estimate the nearby individual and population group concentrations using actual dispersion conditions, if known. If the conditions are unknown, worst-case data were used. The radio-nuclide composition and concentration of the atmospheric emissions was used to compute critical organ doses assuming the more sensitive biological form (sol-uble or insoluble) was present. The dose estimates obtained for the nearby individual assume a full-time resident at Camp Ken Jockety. The effective dose equivalent rate for the nearby individual was computed using AIRD05-PC following requirements of 40 CFR 61.93(a). The value at the camp is 0.0066 mrem /yr, with the highest organ dose being 0.038 to the endosteum. In comparison, exposure of persons to natural background radiation in the area would be approximately 130 mrem /yr as measured by TLD stations. The EPA has set the exposure limit to 10 mrem /yr to any member of the general public from all sources of radionuclides. O ESTIMATED RADIATION DOSE TO THE PUBLIC FROM LIQUID DISCHARGES Radiation Dose from Swiming (External Whole Body) 9 Due to the shallow nature of Big Darby Creek at the West Jefferson site, there does not appear to be a significant pathway for exposure to swim-mers. Based on previous years' releases and cciculations, it can be assumed that no measurable exposure is attributable to releases from the West Jef fer-son site. G 0

O 68 Radiation Dose During Boating and Waterskiing Big Darby Creek is ' a shallow to allow any significant boating or other water recreation sports. Ihus, no dose has been calculated for this pathway. Rad tion Dose from Drinking Water Water from Big Darby Creek below the outfall is not used for drinking prior to its confluence with the Scioto River according to the U.S. Geological Survey; therefore, the dose contribution from this source is negligible. O O O O' O O l O

) 69 ) QUALITY ASSURANCE Several methods are used to assure that the data collected each year are representative of actual concentrations in the environment. Exten- ) sive 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 pro-vide for identification of any net differences that may be attributable to the West Jefferson nuclear operat;ons. These procedures, in conjunction with a ) program to demonstrate the accuracy of radiochemical analyses, assure that the data accurately represent environmental conditions. All of the routine radioanalyses for the Battelle environmentai surveillance program are performed at the radiochemistry facility located at 3 the West Jefferson nuclear site. An outside radiochemistry laboratory was

hosen as a backup service for overflow samples, but was not used in 1991.

Both laboratories maintain internal quality assurance programs that involve routine calibration of counting instruments, daily source and background J counts, routine yield determinations of radiochemical' procedures, and repli-cate analyses to check prect 3n. The accuracy of radionuclide determination is assured through the use of standards traceable to the National Institute of Standards and Technology (NIST), formerly the National' Bureau of Standards. ) Assurance of the dose calculation quality is provided in the following ways. Since doses are similar from year to year, a comparison is made against past calculated doses and any differences are validated. All computed doses are double checked by the originator and by an independent 3 third party, who also checks all input data and assumptions used in calcula-tion. Information necemary to perform all of the calculations is fully documented. Battelle also participates in the DSE-sponsored Quality Assessment Program, which is administered by the Environmental Measurements Laboratory (EML) and requires the qualitative analyses of spiked air, water, soil, )

C 70 vegetation, and tissue samples furnished by DOE /EML semiannually. The spiked 8 media samples are analyzed by the radiochemistry facilities serving the Envi-ronmental Monitoring Program and the results reported to DOE /EML for verifica-tion of accuracy. Minimum detection levels (MDLs) for radionuclide analyses were detennined to a 95 percent confidence level. The minimum detectable level (MDL) was calculated using the Nuclear Data, Inc. ND680 Computer System. The MDL was defined by: MDL = (KI + Kil)(S)(CF) where The value of the uoper percentile of the standardized KI = normal variate corresponding to the preselected risk (5 percent) of a type I error. Kil = The value of the upper percentile of the standardized normal variate corresponding to the preselected risk (5 percent) of a type 11 error. Established standard error for the net counting rate of S = the sample. CF The conversion factor from count rate to activity. = Using a 95 percent confidence level, the MDL can be defined by: MDL = 4.66 SQRT(BCR) CF where SQRT(BCR) = The square rout of the background counting rate. The conversion factor takes many variables into account, so it is different with eo::h isotope and measurement. The correction factor accounts for total chemical yield, sample size, detector efficiency branching frac-tion, decay fraction (decay prior to analysis), unit conversion, and counting interval. The a posteriori MDL is determined by adding the 2 sigma (95 per-cent confidence level) value to the calculated e, even when it is negative.

• I 91

71 4 REFERENCES (1) U.S. Bureau of the Census, 1990 Population Data. Prepared by Ohio Department of Developtrent. E 4 (2) Civil Effects Operations (LEX 59.4.23) Aeroradioactivity Surveys and A Real Geology of Parts of Ohio and Indiana (ARMS-1), May 1966. (3) " Estimates of lonizing Radiation Doses in the United States 1960-2000", U.S. Environmental Protection Agency, ORP/CSD 72-1. G (4) Environmental Assessment for Battelle Columbus Laboratories Decommis-sioning Project, Battelle, Columbus, Ohio, 1990. (5) letter to John Paulian from Karen H. Cooper, Ohio EPA-Division of Pub-lic Water Supply, dated September 20, 1983. e (6) 0)erational and Environmental Safety Division, Radiation Protection to tie Public and the Envitonment, DOE Order 5400.5, U.S. Depertment of Energy, Washington, DC, february 1990. (7) Chapter ! Environmental Protection Agency, 'tational Revised Primary ~ Drinking Water Regulations, 40 CFR Part 141, laiy 1, 1990. 9 (8) Scioto River Basin Waste Loau Allocation Rect.,rt n r ihe 303 (e) Contin-uing Planning Process for Water Quality Mat e ment. (9) Interim Report on Site Characterization West Jt'ferson Nor' Sita Stage 1 Sampling and Analysis--Chemical Sampling Tiimmarl ~C e Battelle Columbus Operations, H. J. Stenhouse and I. C. Bt d, December 22, 1989. (10) User's Guide to the Comply Code, EPA 520/1-89-003, U.S. Environmental Protection Agency, Office of~Tadiation Programs, October 1989. 1 (11) User's Guide for AIR 005-PC, Version 3.0, USEPA, Office of Radiation ~ FFograms,LasVegasfacility, EPA /520/6-89-035(December 1989), (12) AIRDOS-EPA: A Computerized Methodology for Estimating Environmental Concentrations and Dose to Man f rom Airoorne Releases of Radir aclides, R. L. Moore, C. F. Baes, 111, L. H. McDowell-Boyer, A. P. Watson, F. 6. e Hoffman, J. C. Pleasant, C. W. liille, ORNL-5532 (June 1979). O 9

C 72 APPENDIX 9 ENVIRONMENTAL REPORT EXTERNAL DISTRIBUTION LIST Robert Dyer John Sadzewicz, Chief Sanitation D.gineer Division of Drinking ar d Ground 13 North Dak Street Waters London, Ohio 43140 Ohio EPA 1800 Watermark Drive Dr. James Herman Columbus, Ohio 43266 0149 Health Commissioner Madison County Health Department Robert Rothwell, Chief 0 13 North Dak Street Division of Water Pollution Control London, Ohio 43140 Ohio EPA 1800 Watermark Drive Michael Pompili Columbus, Ohio 43266-0149 Assistant Health Commissioner Environmental Health Mr. David Kee, Director Columbus Health Department Air and Radiation Division City of Columbus (SAR26) ltail Stop A-18J 181 Washington Boulevard U.S. EPA Columbus, Ohio 43215 77 West Jackson Boulevard Robert Owen, Chief 8 Bureau of Radiological Health Ron Yerian Ohio Department of Health Public Utilities Commission P.O. Box 118 Ohio Power Siting Board Columbus, Ohin 43266-0118 180 East Broad Street Donald R. Schregardus Director Mr. Terrance A. McLaughin, Director Ohio EPA Waste Standards and Risk Assessments 1800 Watermark Drive Branch Columbus, Ohio 43266-0149 Office of Air and Radiation Mail Stop ANR-460 Linda Welch, Chief U.S. EPA O Division of Hazardous Waste 401 M Street SW Management Washington, D.C. 20460 Ohio EPA 1800 Watermark Drive Mr. Raymond Pelletier, Director Columbus, Ohio 43266-0149 Office of En'i"onmental Guidance EH-23 8' .enny Tiell, Deputy Director U.S. Department of Energy Waste Programs 1000 Independence Avenue Ohio EPA Washington, D.C. 20585 1800 Watermark Drive Columbus, Ohio 43266-0149 0 9

) 73 a ) APPENDIX (CONTINUE 0) ENVIRONMENTAL REPORT EX1ERNAL DISTRIBUTION LIST Hr. Michael A. Kirkpatrick, Director Mr. A. Bert Davis, Administrator Ell-24 U.S. Nuclear Regulatory Commission Office of Environmental Audits Regioti !!! Office U.S. Department of Energy 799 Roosevelt Road 1000 Independence Avenue Glen Ellyn, Illinois 60137 Washington, D.C. 20585 Mr. Martin Langsam, Branch Chief Lois A. llolmes Contracts Division Manager U.S. Department of Energy Communications Chicago Operations and Regional Kl-29 Office Battelle Pacific Northwest 9800 South Cass Avenue Laboratories Argonne, Illinois 60439 D Bnttelle Boulevard Richland, Washington 99352 Mr. J. O. Nef f, Project Manager U.S. Department of Energy Charles J. Haughney, Chief (3) 505 King Avenue, 15-1131 Advanced Fuel and Spent fuel Columbus, Ohio 43201 Licensing Branch Hail Stop 6H3 Dr. J. Donald Cossairt Division of fuel Cycle and Senior Environmental Protection Material Safety Officer U.S. Nuclear Regulatory Commission fenni National Acceleration Washington, J.C. 20555 Laboratory P.O. Box 500 p Batavia, Illinois 60410 D D D D

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