ML20141F028

Addendum to Environ Rept for CY84 on Radiological & Nonradiological Parameters

ML20141F028
Person / Time
Site:	07000008
Issue date:	12/31/1984
From:	Robert Evans, Paulian J, Stewart D Battelle Memorial Institute, COLUMBUS LABORATORIES
To:
Shared Package
ML20141F017	List: ML20141F010 ML20141F028
References
BCL-5184, BCL-5184-ADD, NUDOCS 8601080499
Download: ML20141F028 (19)

Text

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BCL 5184 ADDENDUM TO THE ENVIRONMENTAL REPORT FOR CALENDAR YEAR 1984 on RADIOLOGICAL AND NONRADIOLOGICAL PARAMETERS to UNITED STATES DEPARTMENT OF ENERGY CHICAGO OPERATIONS OFFICE 0ctober 4,1985 Prepared by Environmental Health Pnysics Nuclear Services Section Contributors:

R. G. Evans and D. G. Stewart. Environmental Health Physics Nuclear Services Section J. L. Pau11an, Facilities Engineering and Operation Section G. E. Kirsch and E. R. Swindall. Operational Health Physics Nuclear Services Section M. J. Stennouse and R. H. Snider, Radiochemistry Services Nuclear Materials Technology Section BATTELLE Columbus Division 505 King Avenue Columbus. Ohio 43201 l

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APPROVAL LIST APPROVED BY i [

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00E Liaison /

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APPROVED BY [ - y w a f- ' & M

' Assistant Group Manager West Jefferson Nuclear Services APPROVED BY Ad/

Healtn FDysics Supervisor West Jefferson Nuclear Services

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i TABLE OF CONTENTS AMENDMENTS Page Foreword................................

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Sumary ( p age 2 )............................

1 Background Radiation Levels (page 18) 2

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Computation of Maximum Individual, Nearest Resident and Population Group Dose (page 20)................

3 Fence Post Dose Estimate (page 23)...................

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Maximum Individual Dose Estimate (page 23)...............

4 Nearest Resident and Population Group Dose Estimate (page 23) 4 APPENDIX External Distribution List.......................

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L LIST OF TABLES AMENDMENTS

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N Table 20.

Sumary of Annual Radiation Dose to the Maximum Individual, Nearest Resident and Population Group

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from Releases of Krypton-85 During CY 1984 (page 45)...

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Annual Dose to the Maximum Individual from Effluents Relaased During CY 1984 (page 46) 6 Table 25.

70 Year Dose Comitment for the Maximum Individual from Effluents Released During CY 1984 (page 50)......

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FOREWORD

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The external radi'ation " fence post" dose; i.e., maximum individual dose, at the site boundary, as stated in the environmental monitoring report (EMR) for CY 1984, was based on a hypothetical situation where an individual might have been continuously exposed to an average security fence-line f

dose rate of %0.0104 mr/hr (above natural background) during CY 1984.

The security fence-line was defined in 1975 as being the nuclear area site boundary because of the lack of an electronic security surveillance system and minimal security patrols at that time.

With the subsequent enhancement of the security survelliance around the nuclear site security fence-line, the site boundary has now been redefined as oeing

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the physical Battelle property line as shown in Figure 8 of the EMR. Based I

on the redefined site boundary criteria, a revision of the external radiation

" fence post" dose value was made. Since radiation dosimeters have also been routinely used at the Battelle Lake recreation areas and Battelle

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property lines, the CY 1984 data for these dosimeters were reviewed to i

determine the revised " fence post" dose. It was found that all data for-these dosimeters were comparable with natural background levels (120 mrem /yr) recorded with similar dosimeters located at off-site locations.

There are three private residences located adjacent to Batte11e's west property line each having a radiation dosimeter posted nearby. The nearest residence was selected for routine "real" dose evaluation and the results were reported in the EMR for CY 1984. Since these three private residences are the only locations on the Battelle property line where members of the public could possibly reside for any appreciable length of time, we consider the annual dose data and the 70 year dose comitment data, as reported l

in the EMR for 1984 for the nearest resident, to also represent the amended

" fence post" or maximum individual dose.

This addendum provides amendments to specified pages of the original EMR

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for Cy 1984 which are sumarized as follows:

1) Sumary, page 2.

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2) Background Radiation Levels, page 18.

3) Computation of Maximum Individual Nearest Residence and Population Group Dose; page 20.

4) Fence Post Dcse Estimate; page 23.

5) Maximum Individual Dose Estimate; page 23.

6) Nearest Resident and Population Group Dose Estimate; page 23.

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7) Table 20, Sumary of Annual Radiation Dose to the Maximum Individual.

L Nearest Resident and Population Group from Releases of Krypton-85 During Cy 1984; page 45, r

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8) Table 21, Annual Cose to the Maximum Individual from Effluents Released During Cy 1984; page 46,

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9) Table 25, 70 Year Dose Commitment for the Maximum Individual from I-Effluents Released During Cy 1984; page 50.

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L The 70-year dose commitment computations for the " maximum individual,

. nearest resident and population groups" and the 80-km (50 mile) population f

have been prepared and are included in the dose evaluation section of this report. Three modes of exposure were considered in the calculations of the 70-year dose coenitment: (1) chronic inhalation of radioactive mixturo using'an atmospheric diffusion model; (2) chronic ingestion of a l;

radioactive mixture through terrestrial and (3) aquatic pathways (se'e pages 50, 51, 52, 53, 54, 55 Tables 25,26,27,28,29,30).

The whole body dose conuittment for the " maximum individual" during CY 1934, t.

l was calculated to be 0.0024 mrem. This estimate includes the external radiation exposure in excess of that received from normal background levels as well as contributions from airborne and aquatic recreation pathways. A discussion of how the dose constitment for maximum individual was calculated l

1s given in the text on page 23.

The maximum organ dose comeitment received by the maxim m individual from g

all pathways was 0.012 mres/yr to the skin from Krypton-85. These doses I

can be compared with the standards given in DOE Order 5481.1 Chapter XI of 500 mrem /yr for the whole body and 3000 mrem /yr for the skin (see pages 37, 38, 50. Tables 12,13,25.)

Airborne emissions from the West Jefferson nuclear site resulted in a whole body dose commitment to the popylation within 80-km (50-m11e) radius of the nuclear site of about 9.1 x 10-0 person-rem. Liquid effluents during 1984 l

contributed approximately 4.8 x 10-2 person-remtothetotalpopula*5 person ton i

dose. This estimate may be compared with the approximate 2.08 x 10 res/yr received annual from natural background radiation (see pages 54, 55 Tables 29,30).

The whole body " fence-post

• exposure calculated for external radiation at the site boundary during 1984, was 0.00002 mrem /yr above background at a location adjacent to the Battelle property line 0.750 km northwest of the l.

nuclear site. This calculated value was ve-ified through the use of TLDS placed at the site boundary (see page 37. Table 12). A discussion cf how the " fence post' exposure was obtained is given in the text on page 23.

f Releases of low-level concentrations of radioactivity to the Columbus municipal sewerage system from the Building 3 (U-235 Processing Facility) were less than 3.2 ;ercent of the concentration guide for disenarges of mixtures into sanitary sewerage systems (see page 39, Table 14).

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2(18) of plutonium-239 in fish samples taken from Darby Creek were 0.00 t 0.01 pC1/g and 0.00 t 0.01 pCi/g for plutonium-238. The average concentration of strontium-90 in fish samples taken from Darby Creek was 0.04 2 0.01 pC1/g, and 0.1 PC1/g for cesium-137. Fish taken from Battelle Lake had average concentrations of plutonium-239 and plutonium-238 of 0.00 t 0.01 pC1/g and 0.00 t 0.01 pCi/g, respectively. Average concentrations of strontium-90 and cesium-137 in fish samples tat en from Battelle Lake were 0.13

• 0.01 pCi/g and 0.1 pCf/g, respectively.

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Background Radiation Levels The external radiation background levels at the West Jefferson site are continuously monitored at 40 dosi.netry stations using cocnercially f

available environmental TLD packets (see Figure 8 and 9). All TLD packets are changed and evaluated each calendar quarter. The annual average dose at the site boundary based on 15 perimeter dosimeter stations was 2.0 x 10-8 rem or 4 10- 4 of the 0.5 rem limit established for the general public.

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This value does not include contributions from natural background radiation which is estimated to be approximately 0.120 rem /yr. The results are surnarized in Table 12 and 13.

f KING AVENUE SITE Water Radioactive i

Sampling of all liquid discharges from the Building 3 (U-235 Processing i

Facility) sump to the Columbus municipal sewerage system is perfomed 09 a monthly basis (see Figure 7). This discharge consists of the liquid wastes from the building laboratory drain systems. The building sump samples are f

routinely analyzed for gross alpha and gross beta activities. Any sample exceeding 4 x 10-/ uC1/m1* receives a garna isotopic (gel 1) analysis and/or L

an alpha spectrometric analysis as necessary.

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

concentrations of gross alpha and gross beta activity are sunnarized in Table 14. The average concentrat'on of the mixture was less than 3.1 percent of the RCG for release to a public sanitary sewerage system.

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assumed to be the value of the limit.

Total releases of radioactivity during CY 1984 from the West Jefferson and r

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King Avenue sites are sunnarized in Table 18.

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

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3(20) inventory of radionuclide concentrations in the leaching bed, emissions should be due to very limited elution from the leach bed of contaminants f

that were delivered to the bed in past years. Therefore, the alpha activities is considered to be primarily uranium-238 and the gross beta activity should contain only relatively long-lived radionuclides.

Estimated Radiation Dose to the Public from Atmospheric Discharges l

Calculation of Atmospheric Dispersion Parameters In all cases on-site meteorological data were used as input to compute the annual average dispersion parameters for the site. Computer Code DACRIN l

programed for localized applications, was used to generate the required X/Q data for calculating dose to the maximum individual, nearest residence and population groups. Thus, annual average X/Q values were developed for a series of concentric rings extending from the site boundary out to a

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distance to 50 miles (refer to Figure 12). The annular rings were broken down into sixteen sectors corresponding to the normal wind rose pattern (refer to Figure 11).

Cocoutation of Maximum Individual Nearest Residence and Population Group Doses f

The annual radiation dose from gaseous and particulate radionuclides dischsrged into the atmosphere was computed for a person continuously inriersed in an infinite hemispherical cloud containing the radionuclides.

Tables 2 and 3 list stack concentrations used to estimate site boundary, nearest residence and population group concentrations from the X/Q data noted in the above paragraph. The radionuclide composition and concentration of the atmospheric emissions was used to compute critical l

organ doses assuming the more sensitive biological form (soluble or i

insoluble) was present. Doses arising from the alpha activity emissions were based on plutonium-239, liberated entirely as the insoluble oxide form. The annual dose estimates obtained for the maximum individual, l

nearest resident, and for population groups from both gaseous and I

particulate emissions are sumarized in Tables 20, 21, 22, 23, and 24.

The estimated off-site doses listed in the tables are very low compared to J

the maximum permissible exposures (MPE) which have been recomended by the L

ICRP(4) and other groups for the general public. The MPE values recommended for an individual are: bone - 3 rem /yr, GI tract - 1.5 rem /yr, whole body -0.5 rem /yr, skin - 3 rem /yr, thyroid - 3 rem /yr, lung - 1.5

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rem /yr, and kidney - 1.5 rem /yr. The recomended values for a population group are one-third of these values. Therefore, from Table 20 it may been seen thst the largest fraction of MPE occurs to tne skin and is 0.003 percent of the recomended limits at the site boundary. In comparison.

l exposure of persons to natural background radiation in the area would be approximately 120 mrem /yr as measured by TLD stations. Atmospheric emissions from the site (Table 19) led to maximum estimated whole body radiation doses which are aporoximately 0.002% of that expected from

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natural background.

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L 4(23) l Fence Post Dose Estimate

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The " fence post" dose is the maximum measured accumulativeMnal f.

radiation dose possible to an individual havieg access to an;oncontrolled An estimated " fence area, excluding ingestion and inhalation pathways.

post" dose of 0.00002 mrem for 1984 was obtained by sustracting.the average TLD background reading of.120 mrem (Table 12. Page 37) from the highest f

annual security fence-line TLD reading of 430 arem, takeri fres Table 13 Page 38, and extrapolating to the nearest pr!vate residence-gri~the Battelle

<1z property line at a distance of 0.750 km.

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Maximum Individual Dose Estimate f.

The total body dose conunitment calculated for,the "gaximum 13,ividual" is d

estimated as 0.0024 mrem for 1984 and is the sunenation of _the, f'ollowing:

(1)0.00002 mres, representing the " fence post" dose discusse4 in the previous paragraph; (2) 8.92' x 10-6 mres, representing the 7.0.-year dose consnitment due to the atmospheric inhalation pathway (Tabir 35, Page 50);

to th (3) 3.10 x 10-9 mrem, representing the 70-year dose consnilmente dg mrem,e atmospheric ingestion pathway (Table 25 Page 50)4 (4) 3.20 dp representing the 70-year dose conunf tment from eating fish,(TaSe 25, Page 50); (5) 2.10 x 10-10 mrem, representing the 70-year dose.ceenttment g

resulting from aquatic reaction (Table 25 Page 50) and (6) 2.~05 x 10-3 r

mrem, representing the annual whole body dose from Krypton-84 (Table 20, Page 45).

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Nearest Resident and Population Group Dose Estimates For purposes of estimating doses to the public.tthe " site boundary" and Batte11e's property line are synonomous therefore dose valuesg,eported for

" maximum individual" and "nearert resident" are'.the same. See Tables 20, 21, 22, 25 and 26. This can be justified based on the resuitssfor TLDs l

postedatthepropertylinewhichshowdoseratesatthese'Idc'(tfonstobe conparable to off site TLD background readings.

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Computations of doses to the nearest population groups yrylep made and included in the EMR for CY 1984 See Tables 23,- 24. F ;ast 28.;

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TABLE 20.

SUMMARY

OF ANNUAL RADIATION DOSE TO THE MAXIMUM INDIVIDUAL, NEAREST RESIDENT AND POPULATION GROUPS f

FROM RELEASES OF KRYPTON-85 DURING CY 1984 l

Critical Dose to the Maximum Organ Individual (0.750 Km NW) l Total Body 2.05 x 10-3 mrem /yr Skin 1.23 x 10-2 mrem /yr Oose to the Nearest Resident (0.750 Km W1 Total Body 2.05 x 10-3 mrem /yr Skin 1.23 x 10-2 mrem /yr Oose to the Nearest Population Group (Darby Estates, Population 2,000)

Total Body 9.70 x 10-4 person-rem /yr Skin 5.82 x 10-3 person-rem /yr Dose to the Population Group (West' Jefferson, Populatien 6,000 l

Total Body 6.71 x 10-4 person-rem /yr Skin 4.03 x 10-3 person-rem /yr l

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4 TABLE 21. ANNUAL DOSE TO THE MAXIMllM INDIVIDUAL (0.75 KN WI FROM EFFLUENTS RELEASED DURING CY 1964 Dose (area /yr)

Whole Pathway Body GI(a)

Thyroid Kidneys Bone Lungs Airborne (inhalation) 1.90 E 7 4.07 E 7 1.08 E '

3.55 E '

1.14 E '

1.63 E

• Airborne (ingestion) 1.10 E

5.40 E.12 1.10 E l' 6.60 E II 3.90 E

7.70 E 12 Eating Fish 3.20 E 5 4.70 E.s 1.90 E 7 1.40 E 5 3.10 E 5 3.10 E '

Aquatic Recreation 2.10 E l' 2.10 E I' 2.10 E

2.10 E

2.10 E

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(a) Gastrointestin.ual tract (lower large intestine).

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TABLE 25.' 70 YL%R DOSE COMITNENT FOR THE MXIftM INDIVIDUAL 4

(0.75 KM m) FROM EFFLUENTS RELEASED DURING CV 1964 i

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Dose' (Rem)

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Whole si Pathway Body' Gl(a)

Thyroid Kidneys Bue!

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Airborne (inhalation)

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4.14 E I' 1.08 E

3.49 E

• i.82 E 7 3.83 E 7

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Eating Fish 3.20 E 7 4.70 E II 3.10 E

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4.00 E 7 5.80 E-?

Aquatic Recreation 2.10 E ' '

2.10 E ' 8 2.10 E,'8 2.10 E ' 8 2.10 E ' 8 2.13 E '8 Airborne (ingestien)(b) '

3.20 E '8 5.40 E 35 2.70 E 88 2.30 E

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3.10 E I3 (a) Gastrointestinual tract (lower large intestine).

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(b) 70-year accumulated dose.

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e APPENDIX l

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I A-5 BCL 5184 EXTERNAL DISTRIBUTION LIST This report is submitted to the Director. Contracts Management Office, U.S.

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

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

Health Comissioner London, Ohio 43140 John P. Overturf County Cornissioner London, Ohio 43140 Other Ccunty and City Health Departments William C. Myers Health Comissioner City of Columbus State of Ohio Rcbert M. Quillin Radiological Health Program Director Ohio Department of Health

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P.O. Box 118

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246 N. High Street Columbus Ohio 43215

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Dr. James McAvoy l

Direc tor Ohio EPA

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Ernest C. Neal, Chief I

District Operations Ohio EPA Ohio Power Siting Comission I

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A-6 State of Ohio (Continued)

Office of Assistant Adninistration for Public Information Charles Taylor-Office of Air Pollution Ken Harsh Office of Emergency Response Jim Kneale Chief Office of Public Water Supply Ernie Rotering Waste Water Polletion Control Paul Flanigan, Chief Title X Ohio EPA

Donald E. Day, P.E.

Chief Division of Land Pollution Control Federal epa W. D. Rowe Deputy Assistant Administrator for Radiation Programs Office of Radiation Programs Surveillance and Inspection Division U.S. EPA Gilbert Gigliotte, Director Technical Information Mr. David Kee, Director Air and Hazardous Materials Division Outside Laboratory Samuel 1.-Baker l

Senior Environmental Protection Officer Fermi National Accelerator Laboratory P.O. Box 500 ~

Batavia, Illinois 60510 I

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l A-7 Outside Laboratory (Continued)

Jack P. Corley, C.H.P.

-Staff Engineer Environmental Evaluations Section Battelle Pacific N: rtnwest Laboratories Battelle Boulevard Richland, Washington 99352 Departirent of Energy Mr. Dar.a R. Dixon, Superviser Acquisition and Assistance Unit Jerry J. Nelsen, Ph.D.

Assistant Director for Environmental Protection Operational and Environmental Safety Division Nuclear Reculatory Comission Mr. Jaines G. Keppler, Administrator Region III Office Leland Rouse Division of Fuel Cycle and Material Safety i

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w BaHelle Columbus Laboratories W3 Asng Asenue Columbus, Ohio 41201-2U#1 Telephone 4614,4246824

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