ML20212K396
| ML20212K396 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/31/1984 |
| From: | TELEDYNE ISOTOPES MIDWEST LABORATORY |
| To: | |
| Shared Package | |
| ML20212K316 | List: |
| References | |
| FOIA-86-608 NUDOCS 8701290066 | |
| Download: ML20212K396 (69) | |
Text
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W TELEDYNE ISOTOPES MIDWEST LA80RATORY 1509 FRONTAGE RO.
NORTHBROOK. IL 600624197 Q12) 5644700 REPORT TO TOLEDO EDISON COMPANY TOLEDO, OHIO OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT N0. 1 OAK HARBOR, OHIO I'J ;h, ANNUAL REPORT - PART I
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SUMMARY
AND INTERPRETATION JANUARY - DECEMBER 1984 FOR SUBMITTAL TO THE NUCLEAR REGULATORY COMMISSION PREPARED AND SUBMITTED BY TELEDYNE ISOTOPES MIDWEST LABORATORY PROJECT NO. 8003 Approved by:
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1 February 1985 8701290066 870116 PDR FOIA CANNIS86-608 PDR
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PREFACE The staff of Teledyne Isotopes Midwest Laboratory was responsible for the acquisition of the data presented in this report.
Samples were collected by members of the staff of the Davis-Besse Nuclear Power Station and by local sample collectors.
The report was prepared by L. G. Huebner, General Manager, Teledyne Isotopes Midwest Laboratory.
He was assisted in this report preparation by B. Grob, Research Assistant; T. Coorlim, Counting Technician; and T. Patton-Baker and C. Carlson, Technicians.
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5 TABLE OF CONTENTS No.
Page PREFACE.......................... 3.2-11 Li st of Fi gures...................... 3.2-iv Li s t o f Ta b l e s.......................
3.2-v
1.0 INTRODUCTION
3.2-1 2.0 E X EC UT I VE S UMMAR Y.....................
3.2-2 3.0 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM.......
3.2-3 3.1. Methodology......................
3.2-3 3.1.1 The Air Program................
3.2-3 3.1.2 The Terrestrial Program............
3.2-4 3.1.3 The Aquatic Program..............
3.2-6 3.1.4 Program Execution...............
3.2-7
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3.1.5 Census of Milch Animals............
3.2-7
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3.2 Results and Discussion................
3.2-8 3.2.1 Atmospheric Nuclear Detonations........
3.2-9 3.2.2 The Air Environment....
3.2-9 3.2.3 The Terrestrial Environment.......... 3.2-10 3.2.4 The Aquatic Environment............ 3.2-13 3.2.5 Summary and Conclusions............
3.2-15 4.0 FIGURES AND TABLES..................... 3.2-16
5.0 REFERENCES
......................... 3.2-31 APPENDIX A.
Crosscheck Program Results..............
A-1 3.2-111
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LIST OF FIGURES No.
Caption Fige
'4-1 Sampling locations on the site boundary of the Davis-
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Besse Nuclear Power Station.............. 3.2-17 4-2 Sampling locations (except those on the site periphery),
Davis-Besse Nuclear Power Station...........
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O LIST OF TABLES No.
Title Page 4.1 Sampling Locations, Davis-Besse Nuclear Powe.- 5:ation, Unit No. 1......................
3.2-19 4.2 Type and Frequency of Collections.............
3.2-22 4.3 Sample Codes Used in Table 4.2...............
3.2-23 4.4 Sampling Sumary 3.2-24 4.5 Environmental Radiological Monitoring Program Sumary....
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1.0 INTRODUCTION
Bec.ause of the many potential pathways of radiation exposure to man from both natural and man-made sources, it is necessary to document levels of radio-activity and the variability of these levels which exist in an area prior to the anticipated release of any additional radioactive nuclides.
To meet this objective, an extensive preoperational environmental radiological monitoring program was initiated for the Toledo Edison Company in the vicinity
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of the Davis-Besse Nuclear Power Station site.
This program included collec-(~ S tion (both onsite and offsite) and radiometric analyses of airborne particu-7
'7 lates, dirborne iodine, ambient gama radiation, milk, groundwater, meat and wildlife, fruits and vegetables, animal and wildlife feed, soil, surface water, fish, and bottom sediments.
Approximately 5 years of preoperational monitoring were completed in April 1977 by the same laboratory that currently operates under the name Teledyne Isotopes Midwest Laboratory (TIML).
Fuel elbments were loaded in Unit 1 on 23 through 27 April 1977 and the initial criticality was achieved on 12 August 1977.
Unit 1 achieved one hundred percent of its operational capacity on 4 April 1978.
Approximately 7-1/2 years of operational monitoring was completed by the end of December 1984.
This report presents th( s w n* ~ full year of operational data for the Envi-ronmental Radiological Littor ng at the Davis-Besse Nuclear Power Station.
The program was conducted in accordance with the Davis-Besse Nuclear Power I
Station Unit No.1 Technical Specifications: Appendix B to License No. NPF-3, Section 3.2.
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2.0 EXECUTIVE
SUMMARY
Operational Nuclear Stations are required by Federal Regulations to submit Annual Operational Reports to the U.S. NRC.
The reports must also include the-results of the Radiological Environmental Monitoring Program.
This report sumarizes the results of such a program.
The program was conduc-ted in accordance with the Davis-Besse Nuclear Power Station Unit No. 1 Technical Specifications:
Appendix B to License No. NPF-3 Section 3.2.
This program included collection (both onsite and offsite) and radiometric analyses
.g of airborne particulates, airborne iodine, anbient gama radiation, milk, ground water, meat and wildlife, fruits and vegetables, animal and wildlife
's feed, soil, surface water, fish, and bottom sediments.
Results of sample analyses during the period January - December 1984 are sununarized in Table 4.5.
Tabulations of data for all samples collected during this period, additional statistical analyses of the data, and graphs of data trends are presented in a separate report to the Toledo Edison Company (TIML 1985).
Radionuclide concentrations measured at indicator locations were -compared with levels measured at control locations and in preoperational studies.
The comparisons indicate background-level radioactivities in all samples collected.
No station effect on the environment was indicated in any of the sampling media collected and analyz.ed.
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3.0 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM 3.1 Methodology The sampling locations for the Environmental Radiological Monitoring Program at the Davis-Besse Nuclear Power Station are shown in Figures 4-1 and 4-2.
Table 4.1 describes the locations, lists for each its
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direction and distance from the station, and indicates which are
' indicator and which are control locations.
The sampling program monitors the air,' terrestrial, and aquatic environ-ments.
The types of samples collected at each location and the frequen-cy of collections are presented in Table 4.2 using codes defined in Table 4.3.
The collections and analyses that comprise the program are described in the following pages.
Finally, the execution of the program in the current reporting annual period (January - Decenter 1984) is discussed.
3.1.1 The Air Program Airborne Particulates The airborne particulate samples are collected on 47m diameter membrane filters of 0.8 micron porosity at a volumetric rate of approximately one cubic foot per minute.
The filters are collected weekly from eleven locations (T-1, T-2, T-3, T-4, T-7,
.T-8, T-9, T-11, T-12, T-23, and T-27), placed in individual glassine protective envelopes, and oispatched by mail to TIML for radiometric analyses.
The filters are stored at least five days after collection to allow for decay of naturally-occurring short-lived radionuclides and then analyzed for gross beta activ-ity. The quarterly composites of all air particulate samples from indicator locations (T-1, T-2,.T-3, T-4, T-7, and T-8) and of all air particulate samples from control locations (T-9, T-11, T-12, C.r[,
T-23, and T-27) are gama-scanned and analyzed for strontium-89 and -9,0.
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Airborne Iodine Each air sampler is equipped with a charcoal trap in-line af ter the filter holder.
The charcoal trap at each location is changed at the same time as the particulate filter and analyzed for iodine-131 ininediately af ter arrival at the laboratory.
Ambient Gama Radiation The integrated gamma-ray background from natural radiation is measured with thermoluminescent dosimeters (TLD).
Monthly and quarterly TLDs are placed at thirteen (13) original locations (the eleven air sampling locations and locations T-5 and T-24).
On 1 January 1980 eighteen (18) new TLD sampling locations were added to the program.
Twelve locations (T T-49) were established at the site boundary ranging in distance from 0.5 mi to 1.2 mi from the stack.
Six locations were established at a distance of 3.7 mi to 5.0 mi from the stack.
Since about 50% of the outer 5 mi ring is over Lake Erie, only six additional locations were required to cover all sectors on the land.
Each shipment of TLDs includes in-transit TLDs which are stored in a shield at the station and returned with the field TL0s af ter their removal.
In-transit exposures are measured by the in-transit TLDs and subtracted from the field TLD measurements to obtain their net exposure.
3.1.2 The Terrestrial Program Milk Two-gallon milk samples are collected twice a month during the
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grazing period (May through October) and monthly during the rest l
of the year from two indicator locations (T-8 and T-20) and one l
control location (T-24).
The milk samples are analyzed for iodine-131, strontium-89 and -90, calcium, stable potassium, and are gama scanned.
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One-gallon well water samples are collected quarterly from two indicator locations (T-7 and T-17) and from one control location (T-27).
The gross beta activity is determined on the suspended and -dissolved solids of each sample.
The samples from control location (T-27) and composites from indicator locations- (T-7 and T-17) are also gama scanned and analyzed for strontium-89 and
-90, and tritium.
Edible Meat-i Semi-annually, domestic meat samples (chickens) are collected from one indicator location (T-32) and one control location (T-34) - and one representative species of wildlife (muskrat or-l raccoon) is collected onsite (T-31).
In addition, one Canada i
goose and one snapping turtle are collected annually onsite (T-31) or in the site vicinity (T-33).
Gamma-spectroscopic analysis is performed on the edible portions of each sample.
Fruits and Vegetables
- :. d Semi-annually, two varieties of fruits and vegetables are collec-i O'
ted from each of the two indicator locations (T-8 and T-25) and from one control location (T-34).
The edible portions are gama scanned and analyzed for strontium-89 and -90.
Green Leafy Vegetables Monthly, during the harvest season, green leafy vegetables are collected from one indicator location (T-36) and one control i
location (T-37).
The samples are analyzed for iodine-131.
Should green leafy vegetables from private gardens be unavail-able, nonedible plants with similar leaf characteristics from the same vicinity may be substituted.
Animal-Wildlife Feed Animal feed is collected semi-annually from one indicator location (T-8) and one control location (T-34).
Cattlefeed is collected during the first quarter and grass is collected during the third quarter.
Also, once a year, a sample of smartweed is collected from location T-31 (onsite).
Gama-spectroscopic analysis is performed on all samples.
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Soil Once a yea.r, soil samples are collected from all eleven air sampling locations; six indicator locations (T-1, T-2, T-3, T-4, T-7, and T-8) and five control locations (T-9, T-11, T-12, T-23.,
and T-27).
Gamma-spectroscopic analysis is performed on all samples.
3.1.3 The Aquatic Program Treated Surface Water Weekly grab samples of treated water are collected at one indica-tor location (T-28, Unit 1 treated water supply, onsite) and two control locations (T-11 and T-12, Port Clinton and Toledo filtra-tion plants).
The samples from each location are composited monthly and analyzed for gross beta activity in dissolved and suspended solids.
Quarterly composites from each location are gamma scanned and analyzed for strontium-89 and -90, and tritium.
Untreated Surface Water Weekly grab samples of untreated water from Lake Erie are collec-ted from one indicator location (T-3) and from two control locations (T-11 and T-12, Port Clinton and Toledo filtration plants, untreated water tap).
In addition, hourly grab samples are collected from one in-plant water supply (T-28, Unit 1 untreated water supply, onsite).
The samples from each location are composited monthly and analyzed for gross beta activity in dissolved and suspended solids.
Quarterly composites from each location are gamma scanned and analyzed for strontium-89 and
-90, and tritium.
Beginning in June 1984, the frequency of analysis for tritium and gama-emitting isotopes on samples from location T-12 was changed from quarterly to monthly.
Also, beginning in June 1984, samples were collected from an additional location (T-50) and analyzed monthly for tritium and gama-emltting isotopes.
3.2-6
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Fish Two species of fish are collected semi-annually from each of two locations in Lake Erie; from one indicator location in the vicinity,of the discharge (T-33) and one control location greater than 10 miles from the plant (T-35).
The flesh is separated from the bones and analyzed for gross beta and gamt-emitting isotopes.
Bottom Sediments I
Semi-annually, bottom sediments are collected from three loca-tions in Lake Erie; at two indicator locations, intake (T-29) and discharge (T-30), and at one control location about 5.3 miles WNW from the' plant (T-27).
The samples are gama scanned and analyzed for gross beta and strontium-89.ind -90.
l 3.1.4 Program Execution
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Program execution is summarized in Table a.4.
The program was executed as described in the proceding sections with the follow-ing exceptions.:
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There were no gross beta in air particulates nor airborne iodine-131 data from location T-4 for the periods ending i
9-04-84, 9-17-84, 9-24-84, 10-01-84, and 10-08-84 because the station was destroyed by vandals (twice).
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There were no gross beta in air particulate nor airborne iodine-131 data from location T-12 for the collection periods ending 7,09-84 and 7-16-84 because of loss of power.
3.
Untreated surface water from Lake Erie at site boundary (T-3) l was not collected during the months of January, February, and j
March of 1984 because the lake was frozen.
3.1.5 Census of Milch Animals In compliance with Appendix B, Section 3.2 of the Technical a
Specifications for.the Davis-Besse Nuclear Power Station, the i
annual census of milch animals was conducted on May 23, 24, and 25, 1984 by the Environmental Monitoring Group personnel, Davis-Besse Nuclear Power Station.
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.The results are shown as follows:
Distance Sector (meters)
Animals SE 18,170 Dairy goat SSE 4,000 Beef cattle 7,300 Dairy goat f
S 4,420 Beef cattle SSW 3,780 Beef cattle SW 5,050 Beef cattle 11,910 Dairy goat WSW 4,250 Dairy cows 8,560 Beef Cattle 11,100 Dairy goat W
1,700 Beef cattle 4,140 Dairy goat
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WNW 16,580 Dairy goat 3.2' Results and Discussion The results for the reporting period January to December 1984 are presen-ted in sumary form in Table 4.5.
For each type of analysis of each sampled medium, this table shows the annual mean and range for all indicator locations and for all control locations. The location with the highest annual mean and the results for this location are also given.
The discussion of the results has been divided into three broad cate-gories; the air, terrestrial, and aquatic envivironments.
Within each category, samples are discussed in the order listed in Table 4.4.
Any references to previous environmental data for the Davis-Besse Nuclear Power Station refer to data collected by TIML and Hazleton Environmental Sciences (or its predecessor companies, NALCO Environmental Sciences and Industrial BIO-TEST Laboratories, Inc.).
The tabulated results of all measurements made during 1984 are not included in this section, although references to these results are made T.
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The complete tabulation of the results is submitted to the Toledo Edison Company in a separate report.
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TABLE 2 Receptor Distance From Site (Meters)
SECTOR 7 (SE) 18170 Inhalation 1
Contaminated Ground 1
Vegetation 1
Cow Milk Goat Milk 1
Meat Animal Plume Exposure 1
SECTOR 8 (SSE) 2030 2230 4000 7300 Inhalation 1
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1 Contaminated Ground 1
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1 Vegetation 1
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Goat Milk 1
Meat Animal 1
Plume Exposure 1
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1 SECTOR 9 (S) 1130 1430 (420 4 -
Inhalation 1
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Contaminated Ground 1
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1 Cow Milk Goat Milk Heat Animal 1
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TABLE 2 Receptor Distance From Site (Meters) f c,*
SECTOR 10 (SSW) 1000 3780 Inhalation 1
1 Contaminated Ground 1
1 Vegetation 1
1 Cow Milk Goat Milk i
Meat Animal 1
Plume Exposure 1
1 SECTOR 11 (SW) 990 5050 11910 Inhalation 1
1 1
Contaminated Ground 1
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Vegetation 1
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Cow Milk u-Goat Milk 1
Meat Animal 1
Plume Exposure 1
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SECTOR 12 (WSW) 2590 4250 8560 11100 Inhalation 1
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1 Contaminated Ground 1
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1 Vegetation 1
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1 Cow Milk 1
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TABLE 2
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Receptor Distance From Site (Meters) 4 SECTOR 16 (NNW) 1250 Inhalation 1
Contaminated Ground 1
Vegetation 1
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s OITSITE DOSE CALCULATIONS MANUAL TABLE 7, APPENDIX B Controlling Receptor Location Pathways and Atmospheric Dispersion Parameters Distance Sector (meters)
Pathways Age Group X/Q D/Q r
N 890 vegetation child 9.34E-7 8.24E-9 NNE*
900 vegetation child 1.19E-6 1.39E-8 NE 900 inhalation child 1.26E-6 1.58E-8 ENE**
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8,000 cow / milk infant 3.43E-8 1.45E-10 SSE 7,300 goat / milk infant 1.07E-7 1.59E-10 S
1,430 vegetation child 1.76E-7 2.51E-9 SSW 1,000 vegetation child 1.92E-7 4.18E-9 SW 990 vegetation child 3.10E-7 5.64E-9 WSW 4,250 cow / milk infant 9.71E-8 5.36E-10 W
4,140 goat / milk infant 6.21E-7 6.89E-10 WNW 1,730 vegetation child 1.49E-7 1.75E-9 NW 1,160 vegetation child 2.40E-7 2.04E-9 NNW 1,250 vegetation child 2.51E-7 3.22E-9
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- The vegetable garden was not observed at the time of the census.
It was assumed that the garden would be planted at a later date and was therefore included in the census.
- Since these sectors are located over Lake Erie, no ingestion pathways are present.
- Default value, since no real receptors are within five miles of the site.
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3.2.1 Atmospheric Nuclear Detonations There were no reported atmospheric nuclear tests in 1934.
The last reported test was conducted by the People's Republic of China on 16 October 1980.
The reported yield was in the 200 kiloton to 1 megaton range.
3.2.2 The Air Environment Airborne Particulates Gross beta measurements yielded annual means that were nearly identical at the five control locations an the six indicator locations (0.024 pCi/m3 and 0.025 pCi/m3, drespectively).
The highest annual mean which was glmost identical to the average at other locations (0.026 pCi/mJ) was measured at two indicator locations (T-2 and T-4) and one control location (T-12).
A spring peak in beta concentration had been observed almost annually for many years (Wilson et al., 1969).
It had been attributed to fallout of nuclides from the stratosphere (Gold et 4.,
al., 1964).
It was pronounced in 1981 and occured to a lesser degree in 1982.
However, the peak did not occur in 1983 or 1984.
This was similar to the years 1976 and 1979.
Strontium-89 and strontium-90 concentrations were below their respective LL0s of 0.003 and 0.001 pCi/m3 in all samples.
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
The only gama-emitting isotope detected was beryllium-7 which is produced continously in the upper atmosphere by cosmic radiation ( Arnold and Al-Salih, 1955).
There was no indication of a station effect on the data.
Airborne Iodine Weekly levels of airborne iodice-131 were below the lower limit of detection (LLD) of 0.07 pCi/m3 in all samples with the following exceptions due to power loss: T-1 on 6-18-84 and I-12 on 7-02-84.
In these cases the LLD was <4.5 and <0.22 pCi/m3, respectively.
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Ambient Gamma Radiation At thirteen (13) regular locations the monthly TLDs measured a mean equivalent dose of 11.6 mR/91 days at the indicator locations and a mean of 13.0 mR/91 days at control locations. These results were in agreement with the values obtained by quarterly TLDs and were similar to the levels observed in -1983 (11.8 mR/91 days and 13.1 mR/91 days, respectively).
The highest annual means for monthly TLDs (16.0 mR/91 days) and for quarterly TLDs (17.9 mR/91 days) occured at indicator location T-8.
At twelve special locations established at the site boundary, the mean equivalents were essentially identical to those measured at the regular indicator locations (12.6 mR/91 days and 13.3 mR/91 days, monthly and quarterly, respectively).
Higher gamma radiation levels measured at locations away from the lake were also observed in previous years and are attributed to the higher potassium-40 content in the soil.
The annual mean dose equivalent for all locations measured by monthly and quarterly TLDs was 13.2 mR/91 days and was similar or identical to that measured in 1980 (14.5 mR/91 days), 1981 (14.8
.h mR/91 days),1982 (14.5 mR/91 days), and 1983 (13.2 mR/91 days).
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2 This is lower than the estimated average natural background radiation for Middle America,19.5 mrad / quarter which is based on data on pp.71 and 108 of the report Natural Background Radiation in the United States (National Council on Radiation Protection and Measurements, 1975).
The terrestrial absorbed dose (uncorrected for structural and body shielding) ranges from 35 to 75 mrad /y and averages 46 mrad /y for Middle America.
Cosmic radiation and cosmogenic radionuclides contribute 32 mrad /y for an average of 78 mrad /y or 19.5 mead / quarter.
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3.2.3 The Terrestrial Environment Milk A total of 54 analyses for iodine-131 in milk were performed during the reporting period.
All samples contained less than 0.9 pC1/1 of iodine-131.
Strontium-89 was below the LLD level of 2.5 pCi/l in all samples.
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.3.2-10
l-Strontium-90 activity was detected in 39 of. 54 samples analyzed and ranged from 1.0 to 2.3 pC1/1.
The annual mean value for
. strontium-90 was the same at the indicator and at the control locations (1.3 pC1/1).
The location with the-highest mean (1.5 pCi/1) was control location T-20.
The mean values were similar to those measured in 1977,1978,1979,1980,1981,1982, and 1983.
The concentrations of barium-140 and cesium-137 were below their respective LLDs in all samples collected.
Results for pctassium-40 were similar at control and indicator locations (1230 and 1360 pCi/1, respectively).
Indicator location T-20 had the highest mean (1390 pCi/1).
Since the chemistries of calcium and strontium, and potassium and cesium are.similar, organisms tend to deposit cesium-137 in muscle tissue and strontium-89 and -90 in bones.
In order to detect potential environmental accumulation of these radio-nuclides, the ratios of the strontium-90 activity to the weight of g
calcium and of the cesium-137 activity to weight of stable Cs,}
potassium were monitored in milk.
The measured concentrations of calcium and stable potassium were in agreement with previously determined values of 1.16*0.08 g/l and 1.50*0.21 g/1, respectively (National Center for Radiological Health, 1968). No statistically significant variations in the ratios were observed.
Groundwater (Well Water)
Gross beta concentrations in suspended solids were below the LLD of 0.7 pCi/1 in all samples.
Gross beta concentrations in dissolved solids averaged 3.7 pC1/1 at the indicator locations and 5.4 pC1/1 at the control location.
The location with the highest annual mean was the control location T-27 and averaged 5.4 pCi/1.
The range of gross beta concentrations were similar to those observed in 1978,~1979, 1980, 1981, 1982, and 1983.
Tritium concentration was below the LLD of 330 pC1/1 in all samples.
Strontium-89 and strontium-90 concentrations were below their respective LLDs of 1.9 pCi/1 and 0.9 pCi/1 in all samples, h
All samples were below the LLD of 10.0 pCi/1 for cesium-137 concentration.
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The activities detected in well water were not significant when compared with the LLDs and were not attributable to the station operation.
Edible Meat In the edible meat samples (chickens, muskrat, Canada goose, and snapping turtle) the mean potassium-40 concentration was 2.14 pCi/g wet weight for the inoicator locations and 1.84 pCi/g wet weight for the control location.
Cesium-137 concentration was below the LLD of 0.081 pCi/g wet weight in all samples.
Fruits and Vegetables Strontium-89 was below the LLD of 0.011 pCi/g wet weight in all samples.
Strontium-90 was detected in one of twelve samples and was 0.011 pCi/g wet weight.
The only gama-emitting isotope detected was naturally-occurring potassium-40.
The mean concentrations were 1.69 pC1/g wet weight
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for the indicator locations and 3.08 pCi/g wet weight for the r-control locations.
The concentrations detected were identical or
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similar to those detected in 1977, 1978, 1979, 1980, 1981, 1982, and 1983.
All other gama-emitting isotopes were below their respective LLDs.
Green Leafy Vegetables Green leafy vegetables (cabbage) collected during harvest season were analyzed for iodine-131.
All results were below the LLD of 0.039 pCi/g wet weight.
All gamma-emitting isotopes except potassium-40 were below their respective LLDs.
Potassium-40 concentration averaged 3.37 pCi/g wet weight and 3.38 pC1/g wet weight for indicator and control locations, respectively.
No station effect was indicated.
Animal-Wildlife Feed In grass, smartweed, and corn the only gama-emitting isotope detected was potassium-40. The annual mean K-40 concentration for the control location T-34 was 2.57 pCi/g wet weight compared to the mean value of 2.47 pCi/g wet weight for indicator locations.
All other gama-emitting isotopes were below their respective LL0s.
3.2-12
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Soil Soil samples were collected in June 1984 and analyzed for gansna-emitting isotopes.
The predominant activity was potassium-40 which had a mean value of 11.2 pCi/g dry weight at the indicator locations and 14.7 pCi/g dry weight at the control locations.
Cesium-137 concentration was below the LLD of 0.054 pC1/g in seven of the eleven samples.
The mean concentrations at the _ indicator locations were 0.21 pCi/g dry weight and 0.75 pCi/g dry weight at the control locations.
The highest cesium-137 concentration,1.19 pCi/g, was detected at the control location T-9, 6.8 miles SW of station. The level of concentrations and distribution pattern was very similar to those observed in 1978, 1979, 1980, 1981, 1982, and 1983.
3.2.4 The Aquatic Environment Water Samples - Treated In treated water samples the gross beta activity in suspended solids was below the LLD of 0.7 pCi/1 in all samples.
The mean gross beta concentration in dissolved solids was nearly identical at indicator and control locations (2. 2 pCi/1 and 2.5 pC1/1 at
- )
indicator and control locations, respectively).
The values are similar to those measured in 1975, 1976, 1977, 1978, 1979, 1980, 1981, 1982, and 1983.
Tritium activity was below the LLO of 330 pCi/1 in all samples.
Strontium-89 and strontium-90 concentrations were below the LLO levels of 4.0 pCi/1 and 1.9 pCi/1, respectively, in all samples.
Cesium-137 level was below the LLD of 10 pCi/1 in all samples.
Essentially similar results were obtained in 1979, 1980, 1981, 1982, and 1983.
Water Samples - Untreated In untreated water samples, the mean gross beta concentration in suspended solids averaged 2.0 pCi/1 at indicator locations and 1.2 pC1/1 at control locations.
In dissolved solids the mean concentration was nearly identical at both indicator and control locations (3.2 pC1/1 and 3.1 pC1/1 at indicator and control locations,respectively).
For total residue, the mean concentra-tions were 3.8 pCi/1 at indicator locations and 3.3 pCi/l at control locations.
None of these results show statistically significant differences between indicator and control locations.
'3.2-23
The tritium concentration was below LLO of 330 pC1/1 in all samples, the same as in treated water.
~
Strontium-89 and strontium-90 activities were below the LLD level of 1.9 and 1.4 pCi/1, respectively, in all samples.
Cesium-137 concentration was below the LLO of 10.0 pCi/1 for all locations. No plant effect was indicated.
Fish The m'ean gross beta concentration in fish muscle was similar for indicator and control locations (3.46 and 3.31 pCi/g wet weight, respectively).
Potassium-40 was the only gama-emitting isotope detected.
The mean potassium-40 concentration was 3.09 pCi/g wet weight for the indicator location and 2.91 pCi/g wet weight for the control location.
Cesium-137 concentration was below the LLD 1evel of 0.032 pCi/g wet weight in all samples.
The levels of concentra-
).
tions were similar to those observed in 1978, 1979, 1980, 1981,
'/
1982, and 1983. No plant effect was indicated.
Bottom Sediments The mean gross beta concentration in bottom s'ediments was 29.5 pCi/g dry weight for indicator locations and 20.0 pCi/g dry weight for the control location.
The location with the highest mean was indicator Location T-29 (31.2 pCi/g dry weight).
Indicator Location T-29 also had the highest mean potassium-40 concentration (15.4 pCi/g dry weight) which was the major contributor to the gross beta activity at all locations.
Concentrations of strontium-89 and strontium-90 were below the LLD levels of 0.32 and 0.019 pCi/g dry weight respectively, in all samples.
Cesium-137 concentration was not detected in any of the six samples above the LLD level of 0.058 pCi/g dry weight.
Similar levels, distribution, and composition of detected radionuclides were detected in 1978,1979,1980,1981,1982, and 1983.
3.2-14
\\.,
3.2.5 Sumary and Conclusions Results of sarrple analyses during the period January - Decerrter 1984 are sumarized in Table 4.5.
Tabulations of data for all samples collected during this period, additional statistical analyses of the data, and graphs of data trends are presented in a separate report to the Toledo Edison Company (TIML 1985).
Radionuclide concentrations measured at indicator locations were compared with levels measured at control locations and in pre-operational studies.
The comparisons indicate background-level radioactivities in all samples collected.
No station effect on the environment was indicated in any of the sampling media collected and analyzed.
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- Figure 4 2 33,pjg89 ocations ('XCePting those' on the sjte periphery). Davis-Besse Nuclear 1%er Station, Unit Jgo,j a'
I
b s,
~
Table 4.1 Sampling locations, Davis-Besse Nuclear Power Station, Unit No.1.
Type of Code Locationa T-1 I
Site boundary, 0.6 miles NE of station, near intake canal.
T-2 I
Site boundary 0.9 miles E of station.
T-3 I
Site boundary, 1.4 miles SE of station, near Toussaint River and storm drain.
T-4 I
Site boundary, 0.8 miles S of station, near Locust Point and Toussaint River.
T-5 I
Main entrance to site, 0.5 miles W of station.
T-7 I
Sand Beach, 0.9 miles NNW of station.
T-8 I
Earl Moore Farm, 2.7 miles WSW of station.
T-9 C
Oak Harbor, 6.8 miles SW of station.
T-il C
Port Clinton, 9.5 miles SE of station.
T-12 C
Toledo Water Treatment Station, airborne particulate and iodine collected 23.5 miles WNW of station and water sanples taken from Intake Crib 11.25 miles NW of station.
T-17 I
Irv Fick's well onsite, 0.7 miles SW of station.
T-20 I
Gaeth Farm', 5.5 miles WSW of station.
T-23 C
Put-In-Bay Lighthouse,14.3 miles ENE of station.
T-24 C
Sandusky, 24.9. miles SE of station.
T-25 I
Miller Farm, 3.7 miles S of station.
T-27 C
Magee Marsh, 5.3 miles WNW of station.
T-28 I
Unit I treated and untreated water supply, onsite.
T-29 I
Lake Erie, intake area, 1.5 miles NE of station.
T-30 I
Lake Erie, discharge area, 0.9 miles ENE of station.
p g
.3.2-19
t
-s Table 4.1 (continued)
Type of Code locationa T-31 I
Onsite.
T-32 I
Land, within 5 miles radius of station.
T-33' I
Lake Erie, within 5 miles radius of site.
T-34 C
Land, greater than 10 miles radius of site.
T-35 C
Lake Erie, greater than 10 miles radius of site.
T-36 I
The private garden or farm having the highest X/Q.
T-37 C
The farm 10 to 20 miles from the site in the least prevalent wind, direction.
T-38
_I -
Site boundary, 0.6 ENE of station near lake.
T'-39
,1 Site boundary, 1.2 miles ESE of station near ditch to
s
~
Toussaint.
-)
w.
T-40 I
Site boundary, 0.7 miles SE of station near ditch to
' Toussaint.*
T-41 1'
Site boundary, 0.6 miles SSE of station near ditch to Toussaint.
T-42 I
' Site boundary, 0.8 miles SSW of station by ECC.
~
T-43
- il Site boundary, 0.5 miles SW of station along Route 2 fence.
T-44 Site boundary 0.5 miles W of station by ratiroad tracks.
T-45 1
2 Site boundary, 0.5 miles WNW of station on access road behind cooling tower.
T-46 I
Site boundary, 0.5 miles NW of station along access road.
T-47 I
Site boundary, 0.5 miles N of station along access road by gate.
T-48 I
Site boundary. 0.5 miles NNE of station by lake.
.. j 3.2-20
s Table 4.1 (continued)
Type of Code Locationa T-49 I
Site boundary, 0.5 miles NE of station along access road by lake.
T-50 I
Erie Industrial Park, 4.5 miles ESE of station by Water Tower.
~
T-51 I
Daup Farm, 600 Tettau Road, Port Clintan, Ohio 4.5 miles SSE of the station.
T-52 I
Miller Farm,* 3.7 miles S of site on West Camp Perry Western Road.
T-53 I
Nixon Farm, 4.5 miles SSE of site on West Camp Perry Western Road.
T-54 I
M. Beier Farm, 4.8 miles WSW of site on Genzman Road C,. s
- n T-55 I
Lenke Farm, 5 miles west of site on Route 2.
a I-Indicator locations; C = Control locations.
e O
' 3.2-21 e
Table 4.2.
Type and fre y of collection.
I Sampling Location Type Weekly Monthly Quarterly Semi-Annually Annually i
t i
2 Il 3
' 50 4
I TLD TLD 7
b c
8 I
SO 9
~
C AP AI SWU SWT TLD TLD S0 II I
W a
~
20 I
M Le 23 C
24 C
TLD M*
TLD b
y 25 I
VE 27 C
SWU SWT 29 I
BS 30 I
BS 31 WL SW 32 I
ME d
33 I
F W ST b
c 34 C
ME VE g
35 C
F 36 I
GLVC 37 C
EV 38-55 I
TLD TLD En I
- Semi-monthly during the grazing season, May through October.
Two varieties from each location.
C Cattlefeed collected during the 1st quarter, grass collected during 3rd quarter.
Two species from each location.
Wb O
~
i
's _,
Table 4.3.
Sample codes used in Table 4.2.
Code Description AP Airborne Particulate AI Airborne Iodine TLD(M)
Thermoluminescent Dosimeter - Monthly TLD (Q)
Thermoluminescent Dosimeter - Quarterly
~
M Milk WW Well Water (Ground Water)
ME Domestic Meat VE Fruits and Vegetables O
GLV Green Leafy Vegetables
.. ' 2 )
~~
AF Animal Feed (silage, grain, grass)
SMW Smartweed SWT Surface Water - Treated SWU Surface Water - Untreated F
Fish BS Bottom Sediments 50 Soil WL Wildlife (muskrat or raccoon)
ST Snapping Turtle WF Waterfowl (goose) 4,
'. ^3.2-23
6 i
t Table 4.4 Sampling sunenary.
Collection Number Number of Number of Sample i
Type and of Samples' Samples a
Type Frequency Locations Collected Missed Remarks Air Environment j
C/W 11 565b 7
See text p. 3.2-7 Airborne particulates Airborne iodine C/W 11 565b 7
See text p. 3.2-7 TLDs C/M 31 372 0
C/Q 31 124 0
Terrestrial Environment i
Milk (May-Oct)
G/SM 3
36 0
(Nov-Apr)
G/M 3
18 0
Groundwater G/Q 3
12 0
Edible Meat
- a. Domestic meat G/SA 2
4 0
- b. Wildlife (two species)
G/SA 1
2 0
y
- c. Waterfowl G/A 1
1 0
l 6
- d. Snapping Turtle G/A 1
1 0
4 Fruits and VegetalDes (two G/SA 3
12 0
varieties from each location)
Green leafy vegetables (during G/M 2
6 0
harvest season)
Animal-wildlife feed
- a. Cattlefeed G/A 2
2 0
Collected 1st Q
- b. Grass or corn G/A 2
2 0
Collected 3rd Q
- c. Smartweed G/A 1
1 0
Soil G/A 11 11 0
Aquatic Environment Treated surface water G/WM 3
156b o
Untreated surface water G/WM 3
156b o
G/HM 1
52b o
j G/WMc 1
7 m
o Fish (twospecies)
G/SA 2
8 0
Bottom sediments G/SA 3
6 0
- Type of collection is coded as follows: C/ = continuous; G/ = grab. Frequency is coded as follows:
/HM = hourly grab composited monthly; /WM = weekly grab composited monthly; /W = weekly; /SM = semi-monthly; 4
/M = m nthly; /Q = quarterly, /SA = semi-annually; /A = annually.
b l
c' Samples are sent to laboratory weekly.
~
. 'ection at location T-50 started in June, 1984.
+
I E
t
",J
(
U Table 4.5 Environmental Radiological Monitoring Program Summary. -
Name of facility Davis-Besse Nuclear Power Station Docket no.
50-346 Location of facility Ottawa Ohio Reporting period January - Deceder 1984 (County, state)
Indicator Location with Highest Control Sasole Type and Locationg Annual Mean Locations hud er of Type phaber of Mean(F)
Mean(F)
Mean(F)
Non-routine Locationd Range Range Results*
(Units)
Analysesa LLDb RangeC'
~
Airborne G8 565 0.0008 0.025(288/301)
T-2, Site Boundary 0.026(52/52) 0.024(239/254) 0 Particulates (0.008-0.053) 0.9 at E (0.006-0.045)
(0.008-0.061)
(pct /mJ)
T-4. Site Boundary 0.026 (44/47) 0.8 at 5 (0.008-0.045)
T-12. Toledo 0.026(45/50) 23.5 at WNW.
(0.006-0.059)
<LLD 0
Sr-89 A
0.003 RLD (LLD 0
Sr-90 8
0.001 RLD P
E 8
Y 8e-7 0.016 0.088 (4/4)
NAf 0.064 (3/4) 0 (0.051-0.161)
(0.053-0.082)
<LLD 0
K-40 0.0089 RLD
<LLD 0
Mb-95 0.0018 RLD GLD 0
Zr-95 0.0024 RLD (LLD 0
Ru-103 0.0023 RLD (LLO O
Ru-106 0.0064 RLD GLD 0
Cs-134 0.0007 RLD (LLD 0
Ce-141 0.0036 (LLD Ce-144 0.0042 RLD (LLD 0
<LLD 0
Airborne I-131 565 0.079
<LLD lodine (pC1/m3)
TLD (Monthly)
Gamma 156 1.0 11.6 (84/84)
T-8. Earl Moore Fare 16.0 (12/12) 13.0 (72/72) 0 (sit /91 days)
(8.1-17.6) 2.7 at WSW (14.0 17.6)
(8.2-17.9)
TLD (Quarterly)
Gassna 52 1.0 13.3 (28/28)
T-8. Earl Moore Fars 18.8 (4/4) 15.0 (24/24) 0 (aft /91 days)
(8.7-21.8) 2.7 at W5W (15.0-21.8)
(19.6-21.1)
Table 4.5 (continued)
Name of Factltty Davis-Besse Nuclear Power Station Indicator Location with Highest Control Sample Type and
.Locationg Annual Mean Locations Musber of Type Number of Mean(F)
Mean(f)
Mean(F)
Non-rout ine (Units)
Analysesa LLDb Rangec Locationd Range Range Resullse TLD (Monthly)
Gamma 144 1.0 12.6 (144/144)
T-45, Site boundary 17.9 (12/12)
None 0
(mR/91 days)
(6.2-20.7) 0.5 at WW (15.9 20.7)
(Inner Ring Site Boundary)
TLD ((Narterly)
Gamma 48 1.0 13.5 (48/48)
T-45, Site boundary 19.4 (4/4)
None 0
(mR/91 days)
(7.6-21.8) 0.5 at WW (15.1-21.8)
(Inner Ring 51te 8oundary)
TLD (Monthly)
Gamma 72 1.0 14.5 (72/72)
T-50. Erte Industrial 16.2 (12/12) none 0
(mR/91 days)
(12.7-17.6)
Park, 4.5 at ESE of (14.1-18.6)
(Outer Ring, app.
Station by Water 5atdistant)
Tower F
TLD (Quarterly)
Gasuna 24 1.0 16.7(24/24)
T-50, Frie Industrial 18.3 (4/4)
None O
N (mR/91 days)
(12.4-21.6)
Park 4.5 at ESE of (14.2-21.6)
N (Outer Ring, app.
Station by Water m
5 at distant)
Tower Milk (pC1/1) 1-131 54 0.9 (LLO (LLD O
Sr-90 54 1.0 1.3(R7/36)
T-20, Gaeth Farm 1.5 (14/18) 1.3(12/18) 0 (1.0-2,3) 5.5 at WSW (1.0-2.3)
(1.1-1.6)
E M
K-40 100 1360 (36/36)
T-20. Gaeth Fars 1390 (18/18) 1230(18/18) 0 (1130-1590) 5.5 at WSW (1200-1590)
(990-1390)
<LLD 0
Ba-140 10
<tL D (LLO O
(g/l)
Ca 54 0.5 1.1 (36/36)
T-20, Gaeth Farn 1.2 (54/54) 1.1 (18/18) 0 (0.1-2.0) 5.5 at W5W (0.9-2.0)
(0.8-1.3)
K 54 0.04 1.54(36/36)
T-20, Gaeth Farm 1.551(18/18) 1.40 (18/18) 0 (stable)
(1.28-1.81) 5.5 at W5W (1.36-1.81)
(1.13-1.62)
(pC1/g)
Sr-90/Ca 54 0.5 1.1 (36/36)
T-20. Gaeth Fars 1.2 (18/18) 1.1 (18/18) 0 (0.5-1.8) 5.5 mi WSW (0.5-1.8)
(0.7-1.8)
(pct /g)
(.
..)
,m
- ;g
.t-d' N
Table 4.5 (continued)
Name of facility Davls-Besse Nuclear Power Station Indicator Location with Highest Control Saanle Type and Locatt'ong Annual Mean Locations haber of Mean(F)~
Mean(F)
Mean(F)
Non-rout ine Type Inseber of Range Locationd Range Range Resultse (thits)
Analysesa LLDb Well Water GB(55) 12 0.7 (LLD (LLD 0
G8(DS) 12 1.4 3.4(8/8)
T-7. Sand Beach 3.4 (4/4) 3.3(3/4) 0 (3.2-4.6) 0.9 at spel
( 3. 2-3. 5)
(1.9-4.2)
T-17. Erv Fick's Well 3.4(4/4) 0.7 et SW (3.2-4.6)
GB(TR).12 3.4(8/8)
T-7. Sand Beach 3.4(4/4) 3.3 (3/4) 0 (3.2-4.6) 0.9 at NNW (3.2-3.5)
(1.9-4.2)
T-17, Erv Vick's Well 3.4 (4/4) 0.7 at SW (3.2-4.6)
<tLD 0
Sr-89 8
1.9 (LLD
<LLD 0
Sr-90 8
0.9
<LLD
<tLD 0
to a
E 8
<LLD 0
Edtble Meat 65 8
K-40 0.1 2.14 (6/6)
T-31, (hstte 2.23 (2/2) 1.84 (2/2) 0 (1.92-2.34) 0.6 at NE (2.12-2.34)
(1.77-1.90)
Cs-137 0.081
<t LD (LLO O
Fruits and Sr-89 12 0.011 (LLD (LLD 0
Vegetables (pC1/gmet)
Sr-90 12 0.004 0.011 (1/8)
T-25 Miller Fara 0.011 (1/4)
(LLD 0
3.7 al 5 GS 12 K-40 0.50 1.69 (8/8)
T-34. Control location 3.08 (4/4) 3.08 (4/4) 0 (0.71-3.78) 18 at SW (1.27-5.28)
(1.27-5.28) 18-95 0.047 (LLD
<LLD 0
<tLD 0
Ce-141 0.079
<tLD
<LLD 0
Ce 144 0.20 (LLD
<LLD 0
i
0 Table 4.5 (continued)
Name of Facility Davis-Besse Nuclear Power Station Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations -
beber of Type haber of Mean(F)
Mean(F)
Mean(F)
Non-routine (thits)
Analysesa LLDb Rangec locationd Range Range Resultse Green Leafy I-131 6
0.039 GLD
<LLD 0
Veoetables (pC1/g wet)
GS 6
K-40 0.1 3.37(3/3)
T-37, Fruit Stand 3.38 (3/3) 3.38 (3/3) 0 (2.21-4.22) 12.0 al SW (3.01-4.05)
(3.01-4.05)
Zr-95 0.040 (LLD
<LLD 0
Ce-141 0.036 GLD
<LLO O
Ce-144 0.16
<LLD s
(LLD 0
Animal-Wildlife 65 5
Y Feed
.g (pCl/g wet)
Be-7 0.68
<LLD (LLD 0
K-40 0.1 2.47 (3/3)
T-31, Onsite 4.25 (1/1) 2.57 (2/2) 0 (1.17-4.25) 0.6 al NE (2.32-2.81)
Nb-95 0.25 GLD
<LLD 0
Zr-95 0.15 (LLD
<LLD 0
Ru-103 0.15
<LL D
<LLD 0
Ru-106 0.26 (LLD
<LLD 0
Cs-137 0.025
<LLD (LLO O
Ce-141 0.23 (LLD (LLO O
Ce-144 0.11 GLD
<LLD 0
Soli GS 11 8
Be-7 0.54 0.70 (1/1)
T-2. Site Boundary 0.70(1/1)
<tLD 0
0.9 al E K-40 1.0 11.2 (6/6)
T-8, Moore Farm 18.4(1/1) 14.7 (5/5) 0 (6.9-18.4) 2.7 at WSW (9.4-18.0) 2r-95 0.14 (LLD
<LLD 0
les-95 0.10
<LLD (LLD 0
'M.:Y E
,3,
..n
- ^
., - [)
y "a
1 Table 4.5 (conttaued)
Name of Facility Deuts-Besse nuclear Power Station Indicator Location with Highest Control
~
Saaple Type and Locationg Annual Mean Locations W r of Mean(F)
Mean(F)
Mean(F) non-routine Type haber of (Units)
Analysesa LLDb Range Locationd Range Range Resultse Soll Ru-103 0.074 (LLD RLD 0
(pCl/g dry)
(cont'd)
Au-106 0.48 RLD GLD 0
Cs-137 0.054 0.21 (3/6)
T-9, Oak Harbor 1.19 (1/1) 0'.75 (4/5) 0 (0.10-0.28) 6.8 at SW (0.27-1.19)
Ce-141 0.12 (LLD
<LLD 0
0' Co-144 0.33 RLD RLD 1
Treated Surface GS(SS) 36
- 0. 7
<LLD (LLD 0
Water y
(pC1/1)
GB (DS) 36 1.0 2.2 (12/12)
T-11 Port Clinton 2.8 (12/12) '
2.5 (24/24) 0 g
(1.6-3.1) 9.5 at SE (1.8-4.5)
(1.6-4.5)'
h GS(TR) 36 1.0 2.2 (12/12)
T-11 Port Citaton 2.8 (12/12) 2.5 (24/24) 0 l
]
(1.6-3.1) 9.5 at SE (1.8-4.5)
(1.6-4.5)
I Sr-89 8
4.0 (LLD
<LLD 0
Sr-90 8
1.9 RLD 2
RLD 0
GS 8
Cs-137 10.0 RLD
<LLD 0
Untreated Surface GB(SS) 45 0.7 2.0 (6/21)
T-3, Lake Erie Site 2.6 (3/9) 1.2 (4/24) 0 Water (0.7-4.3)
Soundary, 1.4 al SE (1.5-4.3)
(0.1-1~.8)
(pCl/1)
G8(DS) 45 1.0 3.2 (21/21)
T-3, Lake Erle $tte 3.3(3/9) 3.1 (24/24) 0 (2.2-4.7)
Soundary, 1.4 at SE (2.2-4.7)
(2.2-5.4)
GB (TR) 45 1.0 3.8 (21/21)
T-3, Lake Erle Site 4.2(12/12) 3.3(24/24) 0 (2.2-8.5)
Soundary, 1.4 al SE (2.2-8.5)
(2.2-5.4)
H-3 28 330 RLD RLD 0
Sr-89 8
Table 4.5 (continued)
Name of Factitty Davis-Besse Eclear Power Station Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations haber of Mean(F)
MeanU)
Mean(F)
Non-routine Type shaeer of (Units)
Analysesa
. LLDb Range Locationd Range Range Results' Untreated Serface Sr-90 8
1.4
<tL D
<LLD 0
Water (PCl/l)
GS 22 Cs-137 10
<tLD (LLO O
Fish GS 8
0.1 3.46 (4/4)
T-33, Lake Erte 3.46 (4/4) 3.31 (4/4).
0 (pC1/g wet)
(3.07-4.03) 1.5 at NE (3.07-4.03)
(2.76-3.69)
GS 8
K-40 0.1 3.09 (4/4)
T-33, Lake Erie 3.09 (4/4) 2.91 (4/4)
'O (2.62-3.67) 1.5 at NE (2.62-3.67)
(2.31-3.56)
Cs-137 0.032
<LLD
<tLD 0
to Bottom Sediments GB 6
- 1. 0 29.5(4/4)
T-29 Lake Erie 31.2 (2/2) 20.0 (2/2) 0
- m (pct /g dry)
(20.6-35.2)
Intake (30.1-32.2)
(17.9-22.0) g 1.5 at NE Sr-89 6
0.32
<LL D
<LLO O
Sr-90 E
0.019 0.034(1/4)
T-30, Lake Erie, 0.034 (1/4)
(LLO O
Discharge 0.9 et WNW GS 6
K-40 0.1 15.0(4/4)
T-29, Lake Erie 15.4 (2/2) 9.2 (2/2) 0 (11.7-17.6)
Intake (15.4-15.5)
(9.0-9.5) 1.5 at NE Cs-137 0.058 (LLD (LLO O
a sg. gross beta, GS = gamma scan, SS = suspended solids. 05 = dissolved solids, TR = total residue.
b LLD = nominal lower limit of detection based on 4.66 sigma counting error for background sample, c Mean based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (F).
d Locations are spectfted by station code (Table 4.1) and distance (miles) and direction relative to reactor site.
- Non-routine results are those which exceed ten times the control station value.
f Quarterly composites of all samples from indicator locations and all samples from control locations were gamma scanned together. Thus, the location with the highest annual mean cannot be identified.
9 Two results have been excluded in the determination of the LLD of airborne lodine-131. The elevated LLDs resulted from apparent pump malfunction or low volume.
~
e 4..
J v)
I
\\
\\
- /
0 I ~
s
5.0 REFERENCES
.Arnol d, J. R.
and H.
A.
Al-Salih.
1955.
Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
- Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn.
1964.
Measurement of Naturally Occurring Radionuclides in Air, in the Natural Radiation Environment, University of Chicago Press, Chicago, Illinois, 369-382.
Hazleton Environmental Sciences, 1979.
Operational Environmental Radio-
. 03 logical Monitoring for the Davis-Besse Nuclear Power Station, Oak
'W Harbor, Ohio, Annual Report, January-December 1978.
1980. Operational Environmental Radiological Monitoring for the Davis-Besse Nuclear Power Station, Oak Harbor, Ohio, Annual Report, January-December 1979.
1981. Operational Environmental Radiological Monitoring'for the Davis-Besse Nuclear Power Station Unit No. 1, Oak Harbor, Ohio, Final Report - Part II, Data Tabulations and Analyses.
January-December 1980.
1982. Operational Environmental Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No.1, Oak Harbor, Ohio, Final Part II,. Data Tabulations and Analyses.
January-December Report 1981.
1 l
1983. Operational Environmental Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No_.1, Oak Harbor, Ohio, Final Part II, Data Tab ~ulations and Analyses.
January-December Report 1982.
Industrial BIO-TEST Laboratories, Inc.
1976.
Preoperational and Operational Monitoring for the Davis-Besse Nuclear Power Station, Oak Harbor, Ohio, Annual Report, January - December 1975.
s f
NALCO Environmental Sciences.
1977.
Preoperational and Operational Radio-
.s i.
logical Monitoring for the Davis-Besse Nuclear Power Station, Oak Harbor, Ohio, Annual Report. January-December 1976.
l l
r3.2 31
1978.
Preoperational and Operational Radiological Monitoring for the Davis-Besse Nuclear Power Station, Oak Harbor, Ohio, Annual Report, January - December 1977.
.utional Center for Radiological Health.
1968.
Section 1.
Milk and Food.
Radiological Health Data and Reports.
Vol. 9, November 12, 730-746.
. National. Council on Radiation Protection and Measurements.
1975.
Natural Radiation Background in the United States.
NCRP Report No. 45, pp. 71 and 108.
Teledy'ne Isotopes Midwest Laboratory.
1984.
Operationa'l Environmental Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No.1, Oak Harbor, Ohio, Final Report - Part II, Data Tabulations and Analyses. January-December 1983.
1985.
Operational Environmental Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No.1, Oak Harbor, Ohio, Final Report,- Part II, Data Tabulations and Analyses. January-December 1984.
Wilson, D.
W.,
G. M. Ward, and J. E. Johnson.
1969.
In:
Environmental Contamination by Radioactive Materials, International Atomic Energy
?\\
Agency, p. 125.
)
O
==--w.--
- - - - -* =
3.2-32
- s. _.
Appendix A Crosscheck Program Results 7e j
' f "9,^
' /
O e
9 I
- (t A-1
f:
.n.
Appendix A Crosscheck Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971.
These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentratio'ns of radionuclides known to the issuing agency but not to. participant laboratories.
The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.
Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency.
Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the kncwn values or outside the control limits indicate a need to check the instruments or procedures used.
h
- Q)
The results in Table A-1 were obtained through participation in the environ-mental sample crosscheck program for milk and water samples during the period 1980 through 1984. This program has been conducted by the U. S. Environmental l
Protection Agency Intercomparison,and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
The results in Table A-2'were obtained for thermoluminescent dosimeters (TLO's) during the period 1976, 1977, 1979,1980, and 1981 through parti-cipation in the Second Third, Fourth, and Fif th International Intercomparison c
l of Environmental Dosimeters under the sponsorships listed in Table A-2; AD
[
A-2
_- s Table A-1.
U.S. Environmental Protection Agency's crosscheck program, com-parison of EPA and Teledyne Isotopes Midwest Laboratory.results for milk and water samples,.1980 through 1983a, Concentration in i)Ci/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis tasc 3o, n=1d STW-206 Water Jan. 1980 Gross Alpha 19.0t2.0 30.0t8.0 Gross Beta 48.0*2.0 45.0*5.0 STW-208 Water Jan. 1980 Sr-89 6.111.2 10.0*0.5 Sr-90 23.9tl.1 25.5tl.5 STW-209 Water Feb. 1980 Cr-51 112 14 101t5.0 Co-60 12.7t2.3 11i5.0 Zn-65 29.7t2.3 25t5.0 Ru-106 71.7tl.5 5115 Cs-134 12.0i2.0 10i5.0 Cs-137 30.0t2.7 30i5.0 STW-210 Water Feb. 1980 H-3 1800t120 1750i340 STW-211 Water March 1980 Ra-226 15.7t0.2 16.0i2.4 Ra-228 3.SiO.3 2.6i0.4 STM-217 Milk May 1980 Sr-89 4.412.69 Si5 Sr-90 10.0il.0 1211.5 STW-221 Water June 1980 Ra-226 2.0i0.0 1.7i0.8 Ra-228 1.610.1 1.7t0.8 l
STW-223 Water July 1980 Gross Alpha 3Li3.0 38*5. 0 Gross Beta 44i4 35i5.0 l
STW-224 Water July 1980 Cs-137 33.9*0.4 35i5.0 Ba-140
<12 0
<5.0 0
I STW-225 Water Aug. 1980 H-3 1280 ISO 12102329 STW-226 Water Sept. 1980 Sr-89 2211.2 24i8.6 Sr-90 1210.6 15t2.6 STW-228 Water Sept. 1980 Gross Alpha nae 32.0i8.0 Gross Beta 22.5*0.0 21.015.0
' N STW-235 Water Dec. 1980 H-3 2420t30 2240i604
'0 A-3
~
I
\\.
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis f2ac i30, n=1d STW-237 Water Jan. 1981 Sr-89 13.0 1.0 1618.7 Sr-90 24.0 0.6 34i2.9 STM-239 Milk Jan. 1981 Sr-89
<210 0
Sr-90 15.7 2.6 20i3.0 I-131 30.9t4.8 26 10.0 Cs-137 46.9 2.9 43t9.0 Ba-140
<21 0
K-40 1330153 1550t134 STW-240 Water Jan. 1981 Gross alpha 7.3t2.0 9f5.0 Gross beta 41.0 3.1 4415.0 STW-243 Water Mar. 1981 Ra-226 3.510.06 3.4 0.5
- f. ~ '.
Ra-228 6.522.3 7.311.1
(.t,s..)
~
STW-245 Water Apr. 1981 H-3 3210t115 2710t355 STW-249 Water May 1981 Sr-89 51t3.6 36i8.7 Sr-90 22.7 0.6 2212.6 STW-251 Water May 1981 Gross alpha 24.0 5.3 21i5.2 Gross beta 16.1 1.9 14t5.0 STW-252 Water Jun. 1981 H-3 2140 95 1950iS96 STW 255 Water Jul. 1981 Gross a.1pha 20tl.5 22*9.5 Gross beta 13.0t2.0 15i8.7 STW-259 Water Sep. 1981 Sr-89 16.lil.0 23t5 Sr-90 10.3i0.9 11tl.5 STW-265 Water Oct. 1981 Gross alpha 71.2i19.1 80f20 Gross beta 123.3t16.6 11115.6 Sr-89 14.9 2.0 21t5 Sr-90 13.lil.7 14.4tl.5 Ra-226 13.0i2.0 12.7tl.9 STW-269 Water Dec. 1981 H-3 2516t181 2700i355
.m
..m' s2
. A_4
N Table A-1.
(continued)
Concentration in 6C1/1b Lab
- Sample Date TIML Result EPA Result Code Type Collected Analysis tasc i3o, n=1d STW-270 Water Jan. 1982 Sr-89 24.312.0 21.Di5.0 Sr-90 9.410.5 12.0tl.5 STW-273 Water Jao. 1982 I-131 8.6:0.6 8.411.5 STW-275 Water Feb. 1982 H-3 1580 147 1820i342 STW-276 Water Feb. 1982 Cr-51
<61 0
Co-60 26.0*3.7 20t5 Zn-65
<13 15t5 Ru-106
<46 20*5 Cs-134 26.8 0.7 2215 Cs-137
- 29. 7tl.4 23t5 STW-277 Water Mar. 1982 Ra-226 11.9tl.9 11.6tl.7
- s STW-278 Water Mar. 1982 Gross alpha 15.6 1.9 19t5
- J/
Gross beta 19.2 0.4 19t5 STW-280 Water Apr. 1982 H-3 2690 80 2860i360 STW-281 Water Apr. 1982 Gross alpha 75t7.9 85i21 Gross beta 114.115.9 106t5.3 Sr-89 17.411.8 2415 Sr-90 10.5t0.6 12tl.5 Ra-226 11.412.0 10.911.5
~
<4.6 0
STW-284 Water -
May 1982 Gross alpha 31.516.5 27.5i7 Gross beta 25.9t3.4 29t5 STW-285 Water June 1982 H-3 1970i1408 1830i340 STW-286 Water June 1982 Ra-226 12.6*1.5 13.4*3.5 Ra-228 11.1*2.5 8.7*2.3 STW-287 Water June 1982 I-131 6.St0.3 4.4i0.7 STW-290 Water Aug. 1982 H-3 3210 140 2890t619 ST11-291 Water Aug. 1982 I-131 94.6t2.5 87*15 ys
' u s/
A-5
+
L.,
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis
- 2aC i30, n=1d STW-292 Water Sept 1982 Sr-89 22.7t3.8 24.5*8.7 Sr-90 10.910.3 14.Si2.6 STW-296 Water Oct. 1982 Co-60 20.0il.0 20 8.7 Zn-65 32.3t5.1 2418.7
~~
Cs-134 15.3tl.5 19.0t8.7 Cs-137 21.011.7 20.0t8.7 STW-297 Water Oct. 1982 H-3 2470i20 2560i612 STW-298 Water Oct. 1982 Gross alpha 32i30 55124 Gross beta 81.7k6.1 81i8.7 Sr-89
<2 0
Sr-90 14.1i0.9 17.222.6 Cs-134
<2 1.618.7
{. ; 7Sd Cs-137 22.710.6 20i8.7 Ra-226 13.610.3 12.513.2 Ra-228 3.9t1.0 3.6*0.9 STW-301 Water Nov. 1982 Gross alpha 12.0tl.0 19.0i8.7 Gross beta 34.0f2.7 24.0i8.7 STW-302 Water Dec. 1982 I-131 40.010.0 37.0110 STW-303 Water Dec. 1982 H-3 1940t20 1990i345 STW-304 Water Dec. 1982 Ra-226 11.710.6 l'1.0tl.7 Ra-228
<3 0
STW-306 Water Jan. 1983 Sr-89 20.0i8.7 29.2i5 Sr-90 21.7t8.4 17.2*1.5 STW-307 Water Jan. 1983 Gross alpha 29.0*4.09 29.0113 Gross beta 29.3i0.6 31.0i8.7 SfM-309 Milk Feb. 1983 Sr-89 35t2.0 37*8.7 Sr-90 13.7i0.6 1812.6 I-131 55.7i3.2 55t10.4 Cs-137 29tl.0 26t8.7 Ba-140
<27 0
K-40 1637f5.8 1512i131
- A-6
O Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis
- 2aC t30, n=1d e
STW-310 Water Feb. 1983 H-3 2470i80 2560t612 STW-311 Water March 1983 Ra-226 11.9tl.3 12.7i3.3 Ra-228
<2.7 0
STW-312 Water March 1983 Gross alpha 31.6i4.59 31i13.4 Gross beta 27.012.0 2ai8.7 STW-313 Water April 1983 H-3 3240 80 33301627 STW-316 Water May 1983 Gross alpha 94i7 64119.9 Gross beta 133 5 149t12.4 Sr-89 19t1 24i8.7 Sr-90 12i1 13i2.6 Ra-226 7.9i0.4 8.Si2.25 Co-60 30i2 30i8.7
~
Cs-134 27t2 33f8.7
. = -
Cs-137 29tl 27t8.7 STW-317 Water May 1983 Sr-89 59.7i2.1 57t8.7 Sr-90 33.7tl.5 38 i 3. 3 STW-318f Water May 1983 Gr'oss alpha 12.8tl.5 11i8.7 Gross beta
- 49.413.9 57f8.7 STM-320 - Milk June 1983 Sr-89 20f0 25*8.7
~ ~
~
Sr-90 10t1 16f2.6 I-131 30i1 30i10.4
~
Cs-137 52t2 47i8.7 K
1553tS7 1486t129 STW-321' Water June 1983 H-3 1470iS9 1529tS83 STW-322 Water June 1983 Ra-226 4.3i0.2 4.8tl.24 Ra-228
<2.5 0
STW-323 Water July 1983 Gross alpha 3t1 7i8.7 Gross beta 2110 22t8.7 STW-324 Water August 1983 I-131 13.310.6 14i10.4
.s
%:; /
~
A-7
, - ~ ~ - -
'A
(
Table A-1.
(continued)
Concentration in pCi/lb
~
Lab
' Sample Date TIML Result EPA Result' Code Type Collected Analysis 12ac i3o, n=1d STAF-326-Air August 1983 Gross beta 42 2 36t8. 7 Filter Sr-90 14t2 10t2.6 Cs-137 19t1 1518.7 STW-328 Water Sept. 1983 Gross alpha 2.3 0.6 5t8.7 Gross beta 10.7tl.2 918.7 STW-329 Water Sept. 1983 Ra-226 3.0 0.2 3.1 0.81 Ra-228 3.2 0.7 2.0i0.52 STW-331 Water Oct. 1983 H-3 1300 30 12101570 STW'-335 Water Dec. 1983 I-131 19.6 1.9 20t10.4 STW-336
. Water Dec. 1983 H-3 2870t100 23891608
..t.
STAF-337 Air Nov. 1983 Gross alpha 18.0f0.2 19i8.7 Filter Gross beta 58.6tl.2 50t8.7 Sr -90 10.9 0.1 1512.6 Cs-137 30.1 2.5 20t8.7 STW-339 Water Jan. 1984 Sr-89 47.2 1.9 36t8.7 Sr-90 22.5t4.0 24t2.6 STW-343 Water Feb. 1984 H-3 2487t76 23831607 STM-347 Milk March 1984 I-131 5.311.1 6tl.6 STW-349 Wa'ter March 1984 Ra-226 4.0t0.2 4.lil.06 Ra-228 3.6t0.3 2.0f0.52 STW-350 Water March 1984 Gross alpha 3.8tl.1 5t8.7 Gross beta 24.2i2.0 20i8.7 STW-354 Water,
April 1984 H-3 3560tS0 35081630 STW-355 Water April 1984 Gross alpha 21.0t4.1 35*15.2 Gross beta 127.814.1 147*12.7 Sr-89 29.3i2.0 2318.7 Sr-90 16.6 0.7 26i2.6 Ra-226 4.0tl.0 4.0tl.04
~
~
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 2ac i3o, n=1d S W-358 Water May 1984 Gross alpha 3.0i0.6 3i8.7 Gross beta 6.711.2 6*8.7 STM-366 Milk June 1984 Sr-89 21f3.1 2518.7 Sr-90 13t2.0 1712.6 I-131 46i5.3 43t10.4 Cs-137 3814.0 3518.7 K-40 1577t172 1496 130 STW-368 Water July 1984 Gross alpha 5.111.1 618.7 Gross beta 11.912.4 1318.7 STW-369 Water August 1984 I-131 34.315.0 34.0t10.4 STW-370 Water August 1984 H-3 3003t253 28171617 STF-371 Food July 1984 Sr-89 22.0i5.3 25.018.7 Sr-90 14.7i3.1 20.0i2.6
'.)
<172 39.0i10.4 Cs-137 24.0i5.3 25.0i8.7 K-40 2503i132 2605t226.0 STAF-372 Air August 1984 Gross alpha 15.3tl.2 1718.7 Filter Gross beta 56.0 0.0 51i8.7 Sr-90 14.311.2 1812.4 Cs-137 21.0f2.0 15i8.7 STW-375 Water Sept. 1984 Ra-226 5.110.4 4.9tl.27 Ra-228 2.210.1 2.310.60 STW-377 Water.
Sept. 1984 Gross alpha 3.3tl.2 5.0*8.7 Gross beta 12.712.3 16.0*8.7 STW-379 Water Oct.1984 H-3 2860i312 28101356 STW-380 Water Oct. 1984 Cr-51
<36 40i8.7 Co-60 20.3i1.2 20i8.7 Zn-65 150i8.1 147i8.7 Ru-106
<30 47i8.7 Cs-134 31.3t7.0 3118.7 Cs-137 26.711.2 2418.7 l
>l I
'A-9 i
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12ac i30, n=1d STM-382 Milk Oct. 1984 Sr-89 15.7i4.2 22i8.7 Sr-90 12.711.2 16t2.6 I-131 41.7*3.1 42 10.4 Cs-137 31.316.1 32 8.7 K-40 1447 66 1517t131 STW-384 Water Oct. 1984 Gross alpha 9.7tl.2 1418.7 (Blind)
Sample A Ra-226 3.310.2 3.0iO.8 Ra-228 3.4tl. 6 2.110.5 Uranium nae 5t10.4 Sample B Gross beta 48.315.0 6418.7 Sr-89 10.714.6 1118.7 Sr-90 7.3tl.2 12i2.6 Co-60 16.311.2 1418.7 75)
Cs-134
<2 218.7 Cs-137 16.7tl.2 14t8.7 STW-389 Water Dec. 1984 H-3 35831110 31821624 a
a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and~ Support Laboratory, U.S. Environmental Protection Agency, (EPA), Las Vegas, Nevada.
b All results are in pCi/1, except for elemental potassium (K) data which are in mg/1, and air filter samples which are in pCi/ filter.
C Unless otherwise indicated, the TIML results are given as the mean *2 standard
~
deviations for three determinations.
d USEPA results are presented as the known values t control limits of 3 for n=3.
- NA = Not analyzed.
Analyzed but not reported to the EPA.
9 Results after calculations corrected (error in calculations when reported to EPA).
i i
/%
' d.
O
- JA-10
Table A-2.
Crosscheck program results, thermoluminescent dosimeters (TLDs).
mR i
Teledyne Average 12o d Lab
- TLD, Result Known (all Code Type Measurement 12o a Value participants) 2nd International Intercomparisonb 115-2b CaF :Mn Gamma-Field 17.011.9 17.1c 16.417.7 2
Bulb Gama-Lab 20.814.1
3c 18.817.6 3rd International Intercomparisone CaF :Mn Gama-Fleid 30.713.2 34.914.8f 31.St3.0 115-3e 2
Bulb g
Gama-Lab 89.616.4 91.7114.6f 86.2124.0 i
4th International Intercomparison9 115-49 CaFp:Mn Gama-Field 14.111.1 14.111.4f 16.09.0 Bulb Gama-Lab (Low) 9.311.3 12.212.4f 12.017.6 i
Gama-Lab (High) 40.411.4 45.819.2f 43.9113.2 5th International Intercomparisonh 115-5Ah CaF :Mn Gamma-Field 31.411.8 30.016.01 30.2114.6 2
Bulb i
Gamma-Lab 77.415.8 75.217.61 75.8140.4 at beginning Gama-Lab 96.615.8 88.418.81 90.7131.2 at the end
_,l
I w
(.9-n v
. Table A-2.
(Continued) mR d
Teledyne Average i 20 t,lab TLD Result Known (all i
Code Type Measurement 12aa Value participants) ll5-5Bh LiF-100 Ga ma-Field 30.314.8 30.0161 30.2114.6 Chips
' Gama-Lab 81.117.4 75.217.61 75.8140.4 at beginning Gama-Lab 85.4111.7 88.418.81 90.71131.2 l
I at the end h
a Lab result given is the mean 12 standard deviations of three determinations.
b y
Second Interna.tional Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of 4
c Value determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
d Mean 12 standard deviations of results obtained by all laboratories participating in the program.
e Third International Intercomparison of Environmental Dosimeters conducted in sumer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas, f Value 12 standard deviations as determined by sponsor of the intercomparison using continuously operated pressurized ion chas er.
9 Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.
h Fifth International Intercomparison of' Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas Houston, Texas and Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.
I Value determined by sponsor of the intercomparison using continuously operated pressurized ion chaser.
e
e t
e 0
e e
N w
1 OmZ (4
C (4
1 S
9 9
e 9
4 e
4 k
(
o e
9 4
5 4 e
b g
ie'
~
- ee.
1984 Land-Use and Milk Animal Census Toledo Edison Company Davis-Besse Nuclear Power ;tation Prepared By: Gary Downing, Environmental Monitoring Group August 1984 Ch 6.,,)
Reviewed By:
J. Scott-Wasilk
~
J. Lietzow K. Nash J. Branum P. Boissoneault D. Briden R. Scott M. Horne W. Frazer L. Bonker i
t i
f 4
~. u-4
)
m
,,-,-_m.-
,y,,--r--
,,.,,,r--,,m,,c.v-,,.,_,,,,,-,-,,,.
,,w_.-cn,,
_ _ _ _ _ _ _ ~
t 1
1984 LAND-USE AND MILK ANIMAL CENSUS
..g.
5 B_ackaround and Methods Appendix I, to 10 CFR 50, states "The licensee shall establish an appropri-ate surveillance and monitoring program for evaluating doses to individu-als from principal pathways of exposure." Appendix B, Section 3.2, to the o
. Davis-Besse Technical Specifications states "an a,anual census of animals producing milk for human consumption shall be conducted at the start of c
the grazing season to determine their location and number with respect to the site."
Pathways are defined as any'means by which radionuclides can get'into the human food chain. Pathways recorded in the Land-Use and Milk
. Animal Census are residences, vegetable gardens, milk animals, and beef i
animals. ' All the pathway locations must be determined within a five-mile radius of the station. All dairy goats within a fifteen-mile radius of the station must also be located.
l.
The 1984 Land-Use and Milk Animal Census was done on May 23, 24 and 25, 1984. Local agencies, such as the Northwest Ohio Goat Dairyman Associa-tion,'Lucas County Agricultural Society and the Ottawa County, Sandusky i'
- County, and Lucas County Cooperative Extension Agencies provided informa-tion on dairy-goat owners in their areas.
L l
The Ottawa County Cooperative Extension Agency confirmed the presence of l
,A all beef cattle, milk cows, and milk goats reported within the five-mile radius of the station. The pathway distances listed below are measured 4
]
from containment.
The following changes were recorded in the 1984 census:
l N Sector -
A vegetable g'arden pathway at 890 meters has been added.
'NNE Sector -
The vegetable garden pathway at 900 meters which was present last year was not observed at the time of the census. Since no major change had occurred in the area and l
the census was taken in early spring; it was assumed that the garden would be planted at a later date and was l
included in the census.
SE Sector -
The dairy goat pathway changed from 16,090 meters to 18,170 meters (11.2 miles). This change was due to the 16,090 meter location not being on any dairy goat list provided by the agencies contacted.
SSE Sector -
the vegetable garden pathway was changed from 2,680 meters to 2,230 meters. There was also a change in the dairy goat l-pathway from 24,140 meters to 7,300 meters (4.5 miles), due t
to the fact that the 24,140 meter location was not on the 1984 dairy goat listing.
9 S Sector -
The vegetable garden pathway was changed.from 1,990 meters h /2 to 1,430 meters. A dairy goat pathway was eliminated at 25,100 meters. This was removed since it did not appear on the 1984 dairy goat list.
i
SSW Sector -
The beef cattle pathway was changed from 1,610 meters to 3,780 meters. The property owners at 1,610 meters no longer have meat animals on their property. The dairy goat located at 24,620 meters was also dropped since it is no longer on that site.
SW Sector -
The beef cattle pathway has been changed from 4,970 meters to 5,050 meters. The cattle at 4,970 meters are no longer located on the property.
WSW Sector -
A beef cattle pathway was added at 8,560 meters.
W Sector -
A dairy goat pathway has been added at 4,140 meters (2.6 miles).
The dairy goat is a 4-H project. A beef cattle pathway was added at 1,700 meters.
Results The results of the 1984 Land-Use and Milk Animal Census are presented in short form in Table 1.
The detailed receptor list in Table 2 is used to update the data file of the Semiannual Radioactive Effluent Release Report. Table 7 is the updated table for Appendix B of the Offsite Dose Calculations Manual (0DCM). The critical receptor of the 1984 Census has not changed from the 1983 report. The vegetable pathway at 900 meters in the NNE sector with X/Q value of 1.19 E-6 and D/Q value of 1.39 E-8 is g
still the most critical receptor.
~ ~..,
Acknowledaements
"~
Yv'onne Leidorf assisted in the field work, and Jane Branum assisted in writing the report.
O e
e
TABLE 2 e
Receptor Distance From Site (Meters)
~
m.
18170 g
-^1 3round 1
r 1
1
~~
-a i
1 2030 2230 4000 7300 1
1 1
1 around 1
1 1
1 0
1 1
1 1
1
-~
1 1
1 1
r 1130 1430 4420 4
1 1
1
- __
- _round 1
1 1
1 1
A.
1 1
1 1
- O]U
. TABLE 2 o
Receptor Distance From Site (Meters) 1 1
SECTOR 13 (W) 980
'1700 4140 Inhalation 1
1 1
Contaminated Ground 1
1 1
Vegetation 1
1 1
Cow Milk Goat Milk 1
-Meat Animal 1
PJume Exposure 1
1 1
SECTOR 14 (WNW) 1730 16580 Inhalation 1
1 Contaminated Ground 1
1 Vegetation 1
1 Cow Milk Goat Milk i
Meat Animal Plume Exposure 1
1 SECTOR 15 (NW) 1160 Inhalation 1
o Contaminated Ground 1
Vegetation 1
Cow Milk Goat Milk' Meat Animal Plume Exposure 1
.g c:;)
.o' TABLE 2
.p -
Receptor Distance From Site (Meters)
SECTok 16 (NNW) 1250 Inhalation 1
Contaminated Ground 1
Vegetation 1
e Cow Milk Goat Milk Meat Animal Plume Exposure 1
'.. -h r
4 f
i
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e 4
l 1
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i 1
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l
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OFFSITE DOSE CALCULATIONS ENUAL TABLE 7, APPENDIX B Controlling Receptor Location Pathways and Atmospheric Dispersion Parameters Distance Sector (meters)
Pathways Age Group X/Q D/Q y
N 890 vegetation child 9.34E-7 8.24E-9 s
NNE*
900 vegetation child 1.19E-6 1.39E-8 NE 900 inhalation child 1.26E-6 1.58E-8 ENE**
e E**
ESE**
SE***
8,000 cow / milk infant 3.43E-8 1.45E-10 SSE 7,300 goat / milk infant 1.07E-7 1.59E-10 S
1,430 vegetation child 1.76E-7 2.51E-9
)
SSW 1,000 vegetation child 1.92E-7 4.18E-9 SW 990 vegetation child 3.10E-7 5.64E-9 WSW 4,250 cow / milk infant 9.71E-8 5.36E-10 W
4,140 goat / milk infant 6.21E-7 6.89E-10 WNW 1,730 vegetation child 1.49E-7 1.75E-9 NW 1,160 vegetation child 2.40E-7 2.04E-9 NNW 1,250 vegetation child 2.51E-7 3.22E-9
- The vegetable garden was not observed at the time of the census.
It
._ s was assumed that the garden would be planted at a later date and was therefore included in the census.
- Since these sectors are located over Lake Erie, no ingestion pathways are present.
- Default value, since no real receptors are within five miles of the
- site.
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.se Sland vO<o.E I A REPORT TO THE COMMISSIONERS AND TO THE PUBLIC
~
mitchell rogovin director george t. frampton,Jr.
deputy director NUCLEAR REGULATORY COMMISSION SPECIAL INQUIRY GROUP Fora-sco-Goo OE et
1
( t.
g HEALTH EFFECTS FROM i
RADIOACTIVE RELEASES DURING THE b
j ACCIDENT, AND OCCUPATIONAL HEALTH PHYSICS AT THE SITE
(
l The effects on the population in the vicinity of Three Mile Island from radioactive releases measured during the accident, if any, will certainly be nonmeasurable and nondetectable. During the course of the accident, approximately 2.5 million curies of I
radioactive noble gases and 15 curies of radioiodines were released. These releases
(
resulted in an average dose of 1.4 mrem to the approximately two million people in the i
site area.
This average dose'is less than 1% of the annual dose from both natural background l
radiation and medical practice. The 1.4-mrem dose may also be compared to differences in annual doses in background radiation from living in a brick versus a frame house, an additional 14 mrem /yr; or living in the high altitude of Denver rather than in Harrisburg, an additional 80 mrem /yr.
The effect of this total dose, averaged over the population in the site area, will be to 1
produce between none and one additional fatal cancer, and between none and one and a half total (fatal and nonfatal) cancers, over the lifetime of the population. In comparison, approximately a half million cancers are expected to develop from all other sources during this same lifetime.
In assessing the health effects from radioactive releases, we also estimated the maximum probable dose received by any one person located off site. To calculate this figure, we assumed that an individual had been standing on the east bank of the Susquehanna across the river from the plant, near the North Gate to the site (the direction in which the maximum exposure was most likely to occur),24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day for 6 days, with no clothes on, and in the open. Our calculations estimated that such a person would have received a dose below 100 mrem. The additional lifetime fatal i
cancer risk to such an individual would have been about 1 in 100,000-compared to a l
risk of fatal cancer from all other sources that the individual would incur during his 4
lifetime of about one in seven. (The additional lifetime fatal cancer risk to the individual l
receivirig the average offsite dose,1.4 mrem, is about one in five million.)
)
We studied the monitoring efforts by Met Ed, the NRC, and others in response to the accident to determine whether it was possible or likely that the average, or maximum probable, dose was underestimated because of inadequacies in monitoring. We found l
that, although the monitoring efforts could have been better and monitoring capabilities should be improved, the monitoring of releases during the accident was adequate to ensure that the estimates of dose to the population are adequate.
l In our view, the fact that there will be no adverse radiation health effects, or very minimal effects, from the Three Mile Island accident has not been clearly understood by the public. It is clear to us that the public misconception about the risks associated with 153 g,g, g g C z.
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Proiciples and General ProccJures for flandhng Emergency and.4< cidental Espmures of IVoriers 0 08 022616 i ICRP Publication No 29 (Annals of the ICRP Vol. 2 No. 2)
Radwnuclide Release mio the Emironment:.4ssessment of Doses to Alan 0 Us 022615 %
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Supplement to Part I (Annals of the ICRP Vol. 3) 0 os 024941 s Part 2 t Annah of the ICRP Vol. 4 No. 3 4) 0 os 026s32 i Supplement to Part 2 (Annals of the ICRP Vol. 5) 0 Os 026813 i Part 3 i Annah of the ICRP Vol. 6 No. 2,3) o 03 026834 \\
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NUREG-0837 Vol. 3, No. 3 i
NRC TLD Direct Radiation Monitoring Network Progress Report July - September 1983 Manuscript Completed: March 1984 D:te Published: March 1984 F. Costello, T. Thompson, L. Cohen, M. Taylor Region i U.S. Nuclear Regulatory Commission King of Prussia, PA 19406
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DAVIS EESSE TLD DIFECT RADIATIO!i ENVIR0tlMENTAL M0tlITORING FOR THE FERIOD 830629-831104 129 DAYS FIELD TIME
$9 DAYS tlRC LOCATI0tl GROSS HET EXPOSURE RATE STATION AZIMUTH /DIST EXFOSURE(mR) mR/Std.0tr.
N0ilET; Tot.
+- Rdm (dso.)
(mi.)
+- Rdm: Tot.
Df1TA 001 50' O.6 15.2 +-
.5 ;
2.3 002 86 0.9 17.1 +-
.5 ;
2.6 N0 ilET DflTA 003 116 1.4 16.0 +-
.5 ;
2.4 NO NET Df!TA 004 172 0.8 19.6 +-
.6 ;
2.9 N0 NET DfiTA 005 200 1.5 23.2 +-
.7 ;
3.5 N0 i1ET DfiTA 006 226 1.0 20.2 +-
.6 ;. 3.0 NO NET DfiTA 007 249 1.5 21.1 +-
.6 ;
3.2 fl0 tlET DfiTA 008 267 1.8 21.8 +-
.7 ;
3.3 N0 ilET Df;TA 000 085 1.8 21.8 +-
.7 ;
3.3 N0 i1ET Df,TA 010 306 1.5 18.8 +-
.6 ;
2.S N0 11ET DfiTA 011 344 0.9 19.4 +-
.6 ;
2.9 N0 ilET DftTA 012 142 4.5 20.5 +-
.6 ;
3.1 H0 llET DfiTA 013 158 4.0 21.6 +-
.6 ;
3.2 110 tiET DfiTA 014 160 3.8 19.5 +-
.6 ;
2.9 H0 HET Df;TA 015 207 4.8 20.5 +-
.6 ;
3.1 NO HET DfiTA 016 225 4.5 r 20.7 +-
.6 ;
3.1 H0 HET DfiTA 017 254 2.7 24.8 +-
.7 ;
3.7 N0 llET DflTA 01A 069 3.0 21.4 +-
.6 ;
3.2 110 llET DfiTA 019 295 5.3 22.8 +-
.7 ;
3.4 H0 HET Df:TA 020 25 0.5 16.0 +-
.5 ;
2.4 N0 llET DfiTA 021 132 9.7 20.5 +-
.6 :
3.1 H0 llET Df:TA 022 210 6.5 MISSIllG OR Dr.MAGED DOSIMETER HO TRAllSIT DOSE CALCULATED (TLD CONTROLS MISSIllG OR OTHERW l
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'DRVIS BESSE FOR THE PERIOD 830629-831104 e
TLD DIRECT RADI ATI0ti EllVIR0 tit:EllTAL t10!11TORIl1G RZIMUTH (dag.)
RVER. EXPOSURE RATE 4 IN GROUP (mR/Std.Qtr.) t-Std.Dev.
348.75-il.25 (N)
NO DATR+-NO DATR B
11.25-33.75 (NNE) 18.1 +- B.O 1
33.75-56.25 (NE) 10.6 +- B.O 1
56.25-78.75 (ENE)
NO DRTR+-NO DATR B
78.75-101.25 (E) 11.9 +- B.O 1
101.25-123.75(ESE) it.1 +- B.O 1
123,75-146.25(SE) 14.3 +- 8.0 1
146.25-168.75(55E) 15.1 4-B.O 1
168.75-191.25(5) 13.5 +
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ISt.25-213.75(55N) 15.2 4-1.3 2
213.75-236.25(SW) 14.3 +
.2 2
236.25-258.75(W5W) 16.B +- 1.8 2
258.75-281.25(W) 15.1 +
.2 2
281.25-303. 75 ( WNW) 15.5 +
.5 2
303.75-326.25 ( NN )
l 13.1 +- B.O 1
326.25-348.75(NNN) 13.5 +- B.O 1
DISTANCE (mi) F' ROM TK REACTOR RVER. EXPOSURE RRTE 4 IN GROUP (mR/Std 0tr.) + -5t d. De v.
B-2 13.4 +- 1.8 12 2-5 14.B +- 1.2 7
>5 15.8 +- B.O 1
UPHIND CONTROL DRTR 14.3 +- B.O 1
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