ML20210B087
| ML20210B087 | |
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|---|---|
| Site: | Fermi  |
| Issue date: | 03/27/1987 |
| From: | Huebner L TELEDYNE ISOTOPES |
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Text
- __________________________ _ _ _ _ _ _ _ _ _ _
T TELEDYNE ISOTOPES MIDWEST LABORATORY 1500 FRONTAGE RD.
NORTH 8 ROOK, IL 600624197 (312)564 4700 I
i REPORT TO DETROIT EDISON COMPANY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR FERMI-2 ANNUAL REPORT JANUARY - DECEMBER 1986 l'
PREPARED AND SUBMITTED BY TELEDYNE IS0 TOPES MIDWEST LABORATORY NORTHBROOK, ILLIN0IS Reviewed and Approved by:
-2 1/2 Date J/A7/87 L. G. Huebner
/
General Manager 27 March 1987 Q[j50$$$$w 50 R
I
TABLE OF CONTENTS
)
Section Py iv List of Figures List of Tables........................
v Preface vi
1.0 INTRODUCTION
1 2.0 StM1ARY 2
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4
3.1 Program Design and Interpretation 4
3.2 Program Description 5
1 3.2.1 Airborne Particulates and Iodine-131....
6 3.2.2 Ambient Gamma Radiation (TLD) 6 3.2.3 Surface Water 6
3.2.4 Dr i n ki n g W at er...............
6 3.2.5 Milk....................
7 3.2.6 Grass 7
3.2.7 Food Crops.................
7
,/
3.2.8 Fish....................
7 j
3.2.9 Bottom Sediments..............
7 3.2.10 Fodder...................
7 p
3.3 Program Execution 8
l 3.4 Analytical Procedures 8
3.5 Radiation Measurement Instruments 12
- 3. 6 Lower Limits of Detection (LLD) 12
- 3. 7 Quality Assurance / Quality Control Program 12 4.0 RESULTS AND DISCUSSION....................
13 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents 13 4.2 Pro g r am F i n d i n g s...................
18 5.0 FIGURES AND TABLES......................
23
6.0 REFERENCES
CITED.......................
41 7.0 COMPLETE DATA TABLES, 1986..................
42 11
TABLE OF CONTENTS (continued)
Appendices Page A
Interlaboratory Comparison Program Results.......... A-1 l
B Data Reporting Conventions.................. B-1 C
1986 Land Use Census..................... C-1 D
Elevated Airborne Iodine-131 Activity Resulting from Chernobyl Nuclear Plant Accident (USSR) April 26, 1986... D-1 I
i I
iii
i LIST OF FIGURES No.
Caption Page 5.0-1 On-site Locations, Enrico Fermi Unit 2............
24 5.0-2 Locations Greater than 5 Miles, Enrico Fermi Unit 2......
25 5.0-3 TLD Locations Within a Ten Mile Radius from the Plant, En r i co Fermi Un i t 2...................
26 j.
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iv
LIST OF TABLES 4
No.
Title Page 5.0-1 Radiological Environmental Monitoring Program, Enrico Fermi Unit 2...................
27 5.0-2 Sample locations and associated media, Enrico Fermi Unit 2 28 5.0-3 Maximum values for the Lower Limits of Detection (LLD),
Enrico Fermi Uni t 2...................
33 5.0-4 Radiological Environmental Monitoring Program Summary, Enrico Fermi Unit 2...................
36 Y
\\
v
1.0 INTRODUCTION
The preoperational radiological environmental monitoring program for Fermi 2 was initiated on March 15, 1978.
Fermi 2 attained initial criticality in June, 1985 and operated at less than five percent power for testing until shutdown during October, 1985: the plant remained inoperative until the reactor was restarted in August of 1986.
For the balance of 1986, the reactor operated less than fif ty percent (50%) of the time at less than twenty percent (20%) power.
This Annual Report of Fermi 2's radiological environmental monitocing program summarizes the results of measurements and analyses of data obtained by Teledyne Isotopes for samples collected during 1986.
Fermi 2 is a boiling water reactor (BWR) designed to operate at a power level of about 1150 megawatts of electrical output with the main condenser circulating water cooled by two natural-draft, wet-type hyperbolic cooling towers.
The plant is located on approximately 1120 acres about 8 miles east-northeast of Mon roe, Michigan: 30 miles southwest of downtown Detroit, Michigan; and 25 miles northeast of downtown Toledo, Ohio.
Fermi 2, bounded on the east by Lake Erie, is situated in Frenchtown Township in Monroe County, Michigan.
1
2.0 smeE4EY The Environmental Radiological Monitoring Program required by the U.S.
Nuclear Regulatory Commission (NRC) Technical Specifications for Fermi 2 is described. Results for 1986 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of Fermi 2.
No effect on the environment due to the operation of Fermi 2 is indicated.
There was a small effect on environmental radioactivity resulting from an accident at the Chernobyl Nuclear Reactor (USSR) on April 26, 1986.
The sampling media affected were air, milk and grass.
The effect is discussed below.
Air Particulates 4
Gross beta activity in air particulates collected between May 11, 1986 and June 15,1986 had elevated levels ranging from 0.041 to 0.306 pC1/m3 and averaged 0.150 pC1/m3 for all locations.
In comparison, gross beta activity for 1986, exclusive of the period between May 11, 1986 and June 15,19Q6, averaged 0.021 pCi/m3, about the same as the average for 1985(0.022pC1/m3).
Gamma spectroscopic analyses of the second quarter composites showed the
/-
presence of three isotopes:
Ru-103, Cs-134 and Cs-137, averaging 0.011, b
0.0065 and 0.014 pCi/m3, respectively.
These isotopes were below their
'(f respective LLD levels in the first, third, and fourth quarter composites.
Airborne Iodine Iodine-131 was detected in sixteen (16) samples collected between May 11, 1986 and June 1,1986.
The activity ranged from 0.08 to 0.64 pC1/m3 and averaged 0 27 pC1/m3 for all samples.
Iodine-131 was below the LLD level of 0.07 pCi/m3 n the rest of the samples collected in 1986.
i Milk Of 68 samples analyzed, fourteen (14) samples collected between May 11, 1986 and June 22, 1986 had detectable I-131 in various concentrations. The concen-trations ranged from 0.6 to 37.5 pC1/1 and averaged 13.5 pCi/1 for all samples with detectable levels.
The I-131 concentration in the rest of the samples collected in 1986 was below the required LLD level of 1.0 pCi/1.
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Cs-137 was detected in two (2) samples collected on May 15 and June 7,1986 and measured 7.3 and 6.0 pCi/1 respectively.
In the rest of the samples collected in 1986, the Cs-137 concentration was below the required LLD level of 18 pCi/1.
Grass Of twenty-eight (28) analyses for iodine-131, four (4) samples collected between May 11 and May 25, 1986 contained I-131 concentrations ranging from 46 to 463 pCi/kg wet weight and averaged 190 pC1/kg wet weight.
The I-131 concentration in the rest of the samples collected in 1986 was below the required LLD of 60 pCi/kg wet weight.
Ru-103 was detected in two (2) samples collected June 7,1986 and measured 41 and 53 pCi/kg wet weight.
Cs-134 was also detected in two (2) samples collected June 7, 1986 and measured 34 and 58 pCi/kg wet weight.
During the period between May 25 and September 27, 1986, Cs-137 was detected in six (6) samples. The concentration ranged from 13 to 145 pCi/kg wet weight and averaged 72 pCi/kg wet weight.
No other gama-emitting isotopes except potassium-40 were detected in any grass samples.
y l
3
~
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.1 Program Design and Interpretation United States Nuclear Regulatory Commission (NRC) regulations (10 CFR 50.34) require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA).
To ensure that these criteria are met, each license authorizing reactor operation includes technical specifications (10 CFR 50.36a) governing the release of radioactive effluents.
In-plant monitoring is used to ensure that these predetermined release limits are not exceeded.
However, as a precaution against unexpected and undefined processes that might allow undue accumulation of radioactivity in any sector of man's environment, a program for monitoring the plant environs is also conducted.
The regulations governing the quantities of radioactivity in reactor effluents allow nuclear power plants to contribute, at most, only a few
' percent increase above normal background radioactivity.
Background
levels at any one location are not constant but vary with time as they are influenced by such external events as cosmic ray bombardment, weapons test fallout, and seasonal variations.
These levels also can vary spatially within relatively short distances reflecting variation in
(,
geological composition.
Because of these spatial and temporal varia-
-Y tions, the radiological surveys of the plant environs are divided into preoperational and operational phases.
The preoperational phase of the program of sampling and measuring radioactivity in various media permits a general characterization of the radiation levels and concentrations prevailing prior to plant operation, along with an indication.of the degree of natural variation to be expected. The operational phase of the program obtains data that, when considered along with the data obtained in the preceprational phase, assist in the evaluation of any radiological impact of plant operation.
\\
Implementation of the preoperational monitoring program fulfilled the following objectives:
4
e Measurement of background levels and their variations along potentially important pathways in the area surrounding the plant.
Provision of baseline data for statistical comparison with future operational analytical results.
Sampling locations were selected on the basis of local ecolcgy, meteor-ology, physical characteristics of the region, and demographic and land-use features of the site vicinity.
The preoperational program was originally designed on the basis of the NRC Branch Technical Position on radiological environmental monitoring issued by the Radiological Assessment Branch (March 1978).
When this position document was revised in November,1979, the Fermi-2 environmental monitoring program was modified accordingly.
Each year a " Land Use Census" is conducted to determine what changes, if any, have occurred in the locations of the milk animals, gardens, and residences within five (5) miles of Fermi-2.
The results of this census are analyzed to ensure that the sampling locations remain representative and that dose projections continue to be conservative.
The results of the 1986 Land Use Census are included in this report as Appendix C.
In 1986, the radiological monitoring program included the measurement of ambient gama radiation by thermoluminescent dosimetry; the determination of gama-emitters in drinking and surface water, fodder, food products, shoreline sediments, and fish; the determination of gross beta and gama-emitters in air particulates; the measurement of airborne I-131 in charcoal cartridges; the measurement of gross beta in drinking water; the determination of gama-emitters and I-131 in milk and grass; and the measurement of tritium in drinking and surface water.
- V 3.2 Program Description Fif ty-seven (57) locations within a radius of about 20 miles of the Fermi-2 site were monitored.
The number and location of monitoring points were determined by considering the locations where the highest off-site environmental concentrations were predicted utilizing plant effluent source terms, site hydrology, and site meteorological condi-tions.
Other factors considered were applicable regulations, population distribution, ease of access to sampling stations, security, and future program integrity.
The environmental radiological monitoring program for Fermi-2 is suma-rized in Table 5.0-1.
Table 5.0-2 describes sample locations, associated media, and approximate distance and direction from the site.
Figures 1 through 3 designate sampling locations by station number.
1 i
5 l
3.2.1 Airborne Particulates and Iodine-131 To monitor the air environment, airborne particulates are collected on glass fiber filters by continuous pumping at a volumetric rate of approximately one cubic foot per minute at five locations.
Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations.
Four of the five locations are indicators (F-1, F-4, F 5, F-17), and one is a control (F-7).
Filters are exchanged weekly.
Fiber filters are analyzed for gross beta activity, and charcoal filters are ana-lyzed for I-131.
Quarterly composites froa each location are analyzed for gamma-emitting iosotopes.
Data are presented in Section 7.0, Tables 3 through 9.
Additionally, monthly averages of gross beta concentrations are graphed and presented in Section 7.0, Figures 1 through 5.
3.2.2 Ambient Gamma Radiation - TLD Ambient gamma radiation is measured at forty-six (46) locations with CaSO :Dy dosimeters (Teledyne).
Forty-two (42) locations 4
are indicat6rs (F-1 through F-6, F-19. L-1 through L-8, S-1 through S-20, S-23, and S-25 through S-30), and four (4) are controls (F-7, S-21, S-22 and S-24).
Two cards, "A" and "B," each with four readout areas, are placed at each location.
They are exchanged and read quarterly.
Data are presented in two separate formats, one by location and the other by meteorological sector and distance Intervals in Section
- f l [-
7.0, Tables 1 and 2.
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3.2.3 Surface Water Monthly composite samples are collected from two (2) locations, F-12 (indicator) and F-14 (control).
The samples are analyzed monthly for gama-emitting isotopes, and then composited quarterly and analyzed for tritium.
Data are presented in Section 7.0, Tables 10 and 12.
l.
3.2.4 Drinking Water l
Monthly composite samples are collected from two (2) locations, l
F-13 (indicator) and F-15 (control).
The samples are analyzed monthly for gross beta and gamma-emitting isotopes, and then i
l composited quarterly and analyzed for tritium.
Data are presented in Section 7.0, Tables 11 and 12.
6
3.2.5 Milk Milk samples are collected semimonthly, June 15 through Octeber 15, and monthly October 15 through June 15, from five (5) loca-tions, four (4) indicator (F-19, F-20, F-31, and F-32) and one (1) control (F-7).
The samples are analyzed for iodine-131 and gamma-emitting isotopes.
Data are presented in Section 7.0, Table 14.
Effective April 1,1986, milk collection at Location F-19 was replaced with grass collection dt a to the unavailability of milk, and will continue until milk samples are again available, i
3.2.6 Grass Grass samples are collected semimonthly June 15 through October 15 and monthly October 15 through June 15 in lieu of milk from two (2) indicator locations, F-18 and F-19.
Grass samples are to be collected from any milk location when the milk sample is unavail-able to the collector.
The samples are analyzed for iodine-131 and gamma-emitting isotopes.
Data are presented in Section 7.0, Table 15. Collection of grass at location F-19 began April 1, 1986.
3.2.7 Food Crops Vegetables are collected twice during the growing season at three locations, two (2) indicator (Masserant Farm and Roland Farm) and one (1) control (Happy Farm).
Samples are analyzed for gamma-emitting isotopes.
Green leafy vegetables are analyzed for iodine-131 in addition to gamma-emitting isotopes.
Data are I
presented in Section 7.0, Table 17.
3.2.8 Fish f
j Fish are collected semiannually from two (2) locations, one
- V indicator (F-16) and one control (F-11).
The edible flesh is separated from the bone and is analyzed for gamma-emitting iso-topes.
Data are presented in Section 7.0, Table 18.
3.2.9 Bottom Sediments Sediment samples are collected semiannually from four (4) loca-tions.
Three (3) off-site (F-8, F-9, and F-10) and one (1) on-site (F-22).
The samples are analyzed for gamma-emitting isotopes.
Data are presented in Section 7.0, Table 13.
3.2.10 Fodder Fodder is collected annually when milk animals are on stored feed from five (5) locations, four (4) indicator (F-19, F-20, F-31, and F-32), and one (1) control (F-7).
The samples are analyzed for gama-emitting isotopes. No sample was available from Location F-19 because no milch animals were maintained on the farm.
Data are presented in Section 7.0, Table 16.
7
= - - - - - -
3.3 Program Execution The program was executed as described in the preceding section with the following exceptions:
1.
No grass was available for analysis from Location F-18 for the collection dates of 01-12-86 and 02-09-86.
Grass from this location was temporarily unavailable due to snow cover.
2.
No milk was available for analysis from Location F-19 for the collection dates of 01-12-86, 02-09-86 and 03-24-86.
Milk was unavailable because the goat was dry.
3.
No TLD data were available from Locations S-23 and L-2 for the first quarter of 1986 because the TLDs were lost in the field.
4.
No TLD data were available from Locations S-5, S-9, S-17, and S-26 for the third quarter of 1986 because the TLDs were lost in the field.
5.
No TLD data were available from Location S-17 for the fourth quarter of 1986 because the TLDs were lost in the field.
6.
No fodder was available for analysis from Location F-19 for the collection date of 12-14-86 because no milch animals were being maintained on the farm.
/
3.4 Analytical Procedures t
\\/
Analytical procedures used by Teledyne Isotopes Midwest Laboratory are described in detail elsewhere (Teledyne Isotopes Midwest Laboratory, 1985).
Procedures are based on those prescribed by the National Center of Radiological Health of the U. S. Public Health Service (U. S. Public Health Service, 1967) and by the Health and Safety Laboratory of the U. S. Atomic Energy Commission (U. S. Atomic Energy Commission,1972).
Following is a short description of the analytical methods used in the analyses of Fermi-2 samples.
Air Particulate Filters Gross Beta - Air particulate filters are counted in a low background gas flow proportional counter after the short-lived, naturally-occurring radon and thoron daughters have decayed.
Filters are counted long enough to obtain the required LLD.
The reporting units are 10-3 pCi/m3 8
Gamma Isotopic - Quarterly composites from each location are counted using Ge(L1) or GeHP detectors long enough to obtain the required LLD.
The report-3 ing units are 10-3 pCi/m.
Charcoal Cartridges Iodine-131 - Charcoal cartridges are mounted on the Ge(L1) or GeHP detector and counted long enough to obtain the required LLD. The equilibrium concentra-tion is calculated using the following equations:
A1 = I-131 activity (pCi/ sample) =
A (atcountingtime)
(1) 2.22 x.B Where:
A = net count rate of I-131 in the 0.36 HeV peak (cpm)
B = efficiency for the I-131 in 0.36 MeV peak (cpm /dpm)
Correction for Equilibrium (assuming constant concen-tration over the sampling period) and Decay:
Al e iti p (1-e-At )
2 Where:
. f C = equilibrium concentration of I-131 (pC1/m3)
A1 = activity of I-131 at the time of counting (pCi/ sample) e = the base of the natural logarithm ='
2.71828 A = 0.693/ half life (days) = 0.693/8.04 =
0.0862/ day t1 = elapsed time between the end of sampling and mid-counting point (in days) t2 = dyration of collection (in days)
F = m3/ day 3
The reporting units are pCi/m,
9
Water Tritium - A measured aliquot of distilled water is mixed in the vial with scintillator, temperature and dark adapted and counted in a liquid scintillation counter (refrigerated) long enough to obtain the required LLD. The reporting units are pCi/1.
Gamma Isotopic - A measured aliquot of the sample is poured into a calibrated container and gamma-scanned on either a Ge(L1) or a GeHP detector. The reporting units are pCi/1.
i Milk Iodine-131 - A measured aliquot of iodide carrier is added to a known volume of milk and the iodine is extracted by absorption on anion exchange resin.
Following a Nacl wash, the iodine is eluted with sodium hypochlorite.
Iodine in the iodate form is reduced to I2 and the elemental iodine is extracted into CCl, back-extracted into water, then finally 4
precipitated as palladium iodide.
Chemical recovery of the added carrier is determined gravimetrically from PdI.
The precipitate is counted in a low 2
background gas flow proportional counter.
The reporting units are pCi/1.
Gamma Isotopic - A measured aliquot of sample is poured into a calibrated Marinelli beaker and gama-
/
scanned on either a Ge(L1) or a GeHP detector long enough to obtain the required LLD.
The reporting units are pCi/1.
A,,
Grass Gamma Isotopic - The sample is chopped into small pieces (if needed), packed into a Marinelli beaker, weighed, and gama scanned with either a Ge(Li) or a GeHP detector long enough to obtain the required LLD.
The reporting units are pCi/kg wet weight.
1 I
10
Thermoluminescent Dosimeters (TLDs)
Ambient gamma radiation is measured by a CaSO :D.
4 y phosphor impregnated in a teflon card.
Each card has four readout areas.
The cards are annealed for one hour prior to the placement.
Upon return to the laboratory, the cards are read out using Teledyne TLD reader Model 8300.
The in-transit exposure is determined by additional "in-transit" badges and is subtracted from the total exposure.
Food Crops Gamma Isotopic - The sample is either blended or cut into very small pieces, packed into a Marinelli beaker, weighed and gama-scanned with Ge(L1) or GeHP detector long en.ough to obtain the required LLD. The reporting units are pCi/kg wet weight.
Fish Gama Isotopic - Flesh is separated from the bones, cut into small pieces, and packed into a calibrated Marinelli beaker. The sample is weighed, a few drops of formaldehyde is added to prevent spoilage, sealed and gamma-scanned with either a Ge(L1) or a GeHP detector.
The reporting units are pCi/kg wet weight.
Sediments
!'l Gamma Isotopic - ine sample is oven-dried, pulver-k ized, and sieved through a screen.
A calibrated Marinelli beaker is filled with the sample, sealed, weighed, and gama-scanned with either a Ge(L1) or a GeHP detector long enough to obtain the required LLD.
The reporting units are pCi/kg dry weight.
Fodder
~
Gama Isotopic - The sample is chopped into small pieces (if needed), packed into a Marinelli beaker, weighed and gama-scanned with either a Ge(Li) or a GeHP detector long enough to obtain the required LLD.
The reporting units are pCi/kg wet weight.
l l
11
3.5 Radiation Measurement Instruments Counting instruments are maintained in the temperature and humidity controlled counting room. A complete history file is maintained for each instrument and all calibration records are fully maintained in these files.
Calibration standards are obtained from NBS or EPA whenever possible or from other reliable suppliers.
The following standards are used for efficiency calibration:
Nuclide Standard Gross Alpha Am-241, EPA Gross Beta Sr-90 in equilibrium with Y-90, EPA l
Gamma Spectroscopy Mixed gama, Eu and Sb, NBS Ambient Gamma (TLD)
Ra-226, encapsulated in irridium needle, American Radium, calibrated by NBS Specific Isotope Specific isotope, NBS, EPA, ORNL, Amersham 3.6 Lower Limits of Detection (LLD)
Lower limits of detection are listed in Table 5.0-3.
3.7 Quality Assurance / Quality Control Program
- 7 Teledyne Isotopes Midwest Laboratory has a comprehensive quality assur-ance/ quality control program designed to assure the reliability of data obtained.
Details of TIML's QA/QC Program are presented else-where (Teledyne Isotopes Midwest Laboratory,1985).
TIML QA/QC Program includes analyses of duplicate, spiked samples and participation in the Interlaboratory Comparison Program (Crosscheck) administered by EPA.
Results obtained in crosscheck programs are presented in Appendix A.
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4.0 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Section 3.3.
All results are summarized in Table 5.0-4 in a format recommended by the Nuclear Regulatory Comission in Regulatory Guide 4.8.
For each type of analysis of each sampled medium, this table lists the mean and range of all indicator and control locations.
The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 1986.
The last reported test was conducted by the People's Republic of China on October 16, 1980.
The reported yield was in the 200 kiloton to 1 megaton range.
There was an accident at Reactor No. 4 of the Chernobyl Nuclear Plant complex in the U.S.S.R.
The accident occurred on April 26, 1986.
The f
following is a brief description of the reactor, its location, and the
.l chronology of events, i\\t Location The Chernobyl nuclear complex is located in the semirural area known as the Byelorussian-Ukrainian Woodlands on the Pripyat River in the Soviet Ukraine.
The nearest town is Pripyat, six miles away, with a population of about 25,000.
An additional 25,000 people live within twenty miles, many of them in the old town of Chernobyl.
Eighty miles to the south lies Kiev, the capital city of the Ukraine, with a population of 2.5 million.
13
Reactor 1
Reactor No. 4 is one of six similar reactors at the Chernobyl site.
It is a graphite-moderated, light-water-cooled pressure tube reactor, RBMK-1000, with 1000 MW(e) and 3200 MW(th) capacity.
Reactors No. I and 2 went into operation in 1977, and Reactors No. 3 and 4 went into opera-tion in 1983; construction of Reactors No. 5 and 6 began in 1981 but have not been completed. All four completed reactors were in operation at the time of the accident.
There are fourteen R8MK-1000 reactors and one BBMK-1500[1500 MW(e)) in operation within the Soviet Union.
Out of approximately fifty operating reactors in the U.S.S.R.
about half are graphite-moderated and half are water-moderated, similar to Western design.
In the United States, the only reactor similar to the RBlet-1000 is the graphite-moderated reactor in Hanford Washington, which is used exclusively for the production of weapons-grade plutonium. Another major difference between Western light-water-moderated power reactors and Soviet reactors is that Western reactors have a steel and concrete containment surrounding the complete reactor while Soviet reactors typically do not.
There are certain advantages and disadvantages of the Chernobyl-type reactors. The advantages are a) The absence of cumbersome pressure vessels; b) Fuel elements can F withdrawn for exchange, repair, or extraction of plutonium without necessitating reactor shutdown; and c) Only about 2% enrichment with U-235 is required, in comparison with 4% for water-moderated reactors.
/'
The disadvantages are:
i a) High sensitivity of the neutron field, requiring a com-
)p(
plicated control system in order to stabilize the power density distribution in the core; b) Complex branching of the coolant delivery and removal system for each channel, which is subject to frequent small-scale failures; l
c) A large amount of heat energy accumulating in the metal structures, fuel elements, and graphite structure, and i
slightly radioactive steam in the turbine; and d)
Inherent danger of hydrogen production when leaks or a breakdown of channels carrying hot steam and water can bring hot steam in contact with graphite, which can lead to a chemical explosion (and did),
i 14
At the time of the accident, 75% of the fuel elements were first-load bundles.
It is estimated that the reactor was in operation for about 400 to 600 days.
This means that the core had a large and nearly maximum inventory of radioactive fission products and that the accident could not have happened under worse conditions.
Chronology of Events The reactor was in the process of being shut down for the maintenance of one of two turbogenerators and to perform a test.
The test was designed to determine how long the turbogenerator could provide electrical power utilizing the mechanical energy of the rotor without steam supply.
April 25, 1986 0100 hr.: Shut down started.
1305 hr.: Turbogenerator No. 7 switched off.
Electrical needs for feed pumps and other equipment switched to turbogenerator No. 8 (to be tested).
1400 hr.: Emergency core cooling system disconnected, but unit continued to operate.
2300 hr.: Power reduction resumed.
At this time, the power level dropped to about 30 MW(th), which is an unstable condition.
The operators brought it up to 200 MW(th) by withdrawing control rods and then by reducing the cooling water flow. The reactivity increased very rapidly and the reactor started to heat up very quickly. Since all automatic controls were turned
/-
off, the reactor could not scram itself.
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\\pril 26, 1986 0123 hr.: Some of the fuel rods and water tubes burst and steam reacted with zirconium and graphite, producing large quantities of hydrogen and other gases.
There were two explosions, one after the other.
There were three stages of releases.
Stage 1 During this stage, occurring intnediately after the explosion, parts of irradiated fuel and gases escaped to the atmosphere.
Some of the burning debris fell on the adjoining buildings and started a fire.
Also, graphite which was enclosed in a stainless steel container was exposed to the atmosphere and started burning.
15
f
' Stage 2 This stage lasted from April 26,1986 to May 2,1986.
The releases of radioactivity were similar to those during Stage 1.
The temperature inside the reactor continued to rise.
Stage 3 This stage lasted from May 2,1986 to May 6,1986.
During this stage, there was a sharp increase in the rate of fission products releases due to the high temperature (2000* C) caused by burning graphite.
On May 6,1986, the reactor was sealed and releases of fission products to the atmosphere were reduced to negligible amounts.
Soviet scientists (IAEA Report, 1986) have estimated that about 50 megacuries of radio-activity (excluding noble gases) were released during these three stages and constituted about 3.5% of the total inventory of isotopes in the reactor. It should be noted that most or all of the noble gases and volatile elements (Kr, Xe, I, Te, Cs) escaped from the reactor.
The estimated releases are list'ed below.
For comparison, releases from the Three Mile Island and Windscale accidents and from a 20 KT nuclear test are also listed.
Releases (in megacuries)
Incident Noble Gas I-131 Cs-137 Sr-90 Chernobyl*
100-200 10-50 1-6 0.001-0.007 Three Mile Island 10 0.00017
<0.0001
<0.0001 Windscale 0.3-0.4 0.2 0.001 20 KT ground
\\/
atomic bomb test 5
2 0.004 0.004
- Evaluation error 50%.
Because of the high temperature, gases and aerosols went straight up and reached an estimated height of 16,000 feet.
The dispersion pattern was similar to that of a tall stack of a coal plant; it reduced local fallout while increasing deposition at distant downwind locations.
In addition to the aforementioned isotopes, the following isotopes and their total releases (from April 26 to May 6, 1986) were estimated in megacuries.
16
Total Total Release
- Release *
(Estimated (Estimated Isotope in MC1)
Isotope in MC1)
Xe-133 45 Ce-141 2.8 Ce-144 2.4 Kr-85m Kr-86 0.9 Sr-89 2.2 I-131 7.3 Sr-90 0.22 Te-132 1.3 Pu-238 0.0008 Cs-134 0.5 Pu-239 0.0007 Cs-137 1.0 Pu-240 0.0011 Mo-99 3.0 Pu-241 0.14 Zr-95
- 3. 8 Pu-242 0.000002 Ru-103 3.2 Cm-241 0.021 Ru-106 1.6 Np-239 1.2 Ba-140 4.3
- Evaluation error i 50%.
The prevailing wind direction at the time of the accident was in a northwesterly direction.
It is estimated that the radioactive cloud reached the Polish border on April 26, 1986 and arrived over Sweden in the afternoon of April 27, approximately eighteen (18) hours before it was detected at the Forsmark Nuclear Plant, located 125 miles northwest of Stockholm.
/
On May 7-8, 1986, the wind changed to a southerly direction, causing radioactive fallout in that direction.
j
'(/
The f allout from Chernobyl was extremely non-uniform and strongly depended on local rainfall during the passage of the radioactive cloud.
For example, the region just north of Stockholm, Sweden, had heavy rainfall on April 27 and 28.
Ground radiation levels varied by more than a factor of 10 over just a few tenths of a mile (C. Hohenemser, et al, 1986).
I-131 levels in milk reacned values as high as 13,500 pC1/1 at rainfall locations as far as 900 or more miles distant from Chernobyl.
Because in many cases cows were kept from open pasture, milk values show high variability (C. Hohenemser, et al,1986).
17
During the period from ten to thirty days after the accident, the fol-lowing radionuclides were identified in the close-in zone of Chernobyl's fallout trail:
Mo-99, Zr-95, Nb-95, Ce-141, Ce-144, I-131 Te-132, I-132, Ru-103, Ru-106, Ba-La-140, Cs-134, Cs-137, Sr-89, Sr-90, and Y-91.
Also, plutonium isotopes were found on the ground surface (I.A.E.C.,
1986).
In the Kiev reservoir which supplies water to the city and is located just north of Kiev, gross beta concentration during the period May 13-20, 1986 was in the range of 1,000 - 5,000 pCi/1. The highest I-131 concen-tration in the Kiev reservoir was observed on May 3,1986 and reached 28,000 pCi/l.
The highest I-131 concentration in.the Pripyat River, north of the plant, was observed on May 2, 1986 and reached 120,000 pCi/1.
In the midwestern states of the U.S.A., the radioactivity released during the accident was detected about two weeks after the accident.. Radio-nuclides detected were Ru-103, Ru-106, I-131, Cs-134, and Cs-137 in such media as air, milk, precipitation, and vegetation.
The highest level of i
I-131 in milk samples collected in the Midwest and analyzed by Teledyne Isotopes Midwest Laboratory was in a milk sample collected May 23, 1986 in Illinois (82.2 pC1/l).
From mid-June to early August, levels of I-131 (and gross beta in the air particulates) in the Midwest fell below the detection limit (I-131) or returned to the pre-Chernobyl level (gross beta).
The level of cesium isotopes decreased but was still detected sporadically in grass and milk.
i As a result of the accident (as of August,1986), thirty-one (31) people P
' \\f died, two (2) from the explosion and twenty-nine (29) from radiation sickness; two hundred ninety-nine (299) people were hospitalized; and one thousand people were injured. The long range effects of the accident are yet to be determined.
4.2 Program Findings Results obtained show background levels of radioactivity in the environ-mental samples collected in 1986, with the exception of air, milk and grass.
i There was some effect on the environmental radioactivity resulting from the nuclear accident at Chernobyl (U.S.S.R. ) on April 26, 1986.
Low levels of Ru-103, I-131, Cs-134, and Cs-137 were detected in aerosols; I-131, Cs-134, and Cs-137 were detected in milk and grass samples.
18
Airborne Particulates l
The average annual gross beta concentration in airborne particulates was similar at indicator and control locations (0.034 and 0.033 pCi/m3, respectively),and was higher than in 1985 (0.022 pC1/m3 at both loca-tions).
Two samples had elevated LLDs (<13.8 and <41.2 pC1/m3) resul-ting from low volumes due to pump malfunctions.
The increase in average gross beta activity is attributable to the nuclear accident at Chernobyl.
The radioactive debris was first detected in air particulates in samples collected on May 11, 1986 and the elevated levels continued through the collection period ending June 7,1986, with the exception of one sample from Location F-5.
Analyses of air particulates collected on June 15, 1986 showed that gross beta activity returned to the pre-Chernobyl level. Gross beta activity at Location F-5 returned to the pre-Chernobyl level on June 22, 1986.
Gross beta activity during this period ranged from 0.041 to 0.306 pC1/m3 and averaged 0.150 pCi/m3 In comparison, gross beta activity for 1986, exclusive of the period between May 11, 1986 and June 15, 1986, averaged 0.021 pC1/m3, almost identical to the average for 1985 (0.022 pCi/md).
l A spring peak in beta activity 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 al., 1964).
It was pronounced in 1981, occurred to a lesser degree iT1T82, and did not occur in 1983, o
f 1984, or 1985.
In 1986, the spring peak could not be identified because f
it was overshadowed by the releases of radioactivity from Chernobyl.
l There was a slight increase in gross beta activity in the fourth quarter as compared to the first, second, and third quarters, exclusive of the period between May 11, 1986 and June 15, 1986 Two pieces of evidence indicate conclusively that the elevated observed activity during the fourth quarter was not attributable to the Plant operation.
At first, elevated activity of similar size occurred simul-t =neously at both indicator and control locations.
Secondly, a similar pattern was observed at other nuclear power plant locations in the Midwest.
l 19
Gama spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
Beryllium-7, which is produced continously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih,1955), was detected in 16 of 20 samples.
All other gama-emitting isotopes were below their respec-tive LLD limits during the first, third, and fourth quarters.
During the second quarter of 1986, three gama-emitting isotopes (Ru-103, Cs-134 and Cs-137) were identified and averaged 0.011. 0.0065 and 0.014 pCi/m3, respectively.
It should be noted that the ratio of Cs-134 to Cs-137 in air particulates was about 1:2, the same as in the mix of gases released at the time of the accident at Chernobyl.
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m3 in 244 of 260 samples analyzed.
The LLD of 0.07 pC1/m3 could not be reached in one sample (<0.11 pCi/m3) because of a delay in counting.
Iodine-131 levels in sixteen (16) samples collected between May 11 and June 1,1986 ranged from 0.08 to 0.64 pC1/m3 and averaged 0.27 pCi/mJ for all locations.
The presence of airborne I-131 in the aerosols in May and June 1986 is attributable to the Chernobyl Accident.
Ambient Gamma Radiation (TLDs) h Ambient gama radiation averaged 14.8 mR/ quarter at indicator locations and 16.2 mR/ quarter at control locations and ranged from 8.9 to 22.6 mR/ quarter. The difference in the gama levels at indicator and control locations is not statistically significant.
Surface Water Gama-emitters were below the limit of detection on all samples; one sample had an elevated Ba-La-140 LLD of 21.3 pCi/l resulting from the delay in counting.
Tritium concentrations were below the LLD level of 310 pC1/l.
No station effect was indicated.
20
1 Drinking Water Gross beta averaged 2.4 pC1/1 and 1.9 pCi/l in indicator and control locations, respectively.
Gamma-emitters were below the limit of detec-tion in all samples; one sample had a slightly elevated Ba-La-140 LLD of 15.3 pC1/1 resulting from a delay in counting.
Tritium concen-trations were below the LLO level of 310 pC1/l.
No station effect was indicated.
Milk A total of 68 analyses for iodine-131 was performed during the reporting period.
Fifty-four (54) samples had I-131 concentrations below the LLD level of 1.0 pCi/1.
Fourteen (14) samples,. collected between May 11 and June 22, 1986, contained I-131 in various concentrations.
The level ranged from 0.6 pC1/1 to 37.5 pC1/1 and averaged 6.2 and 1.2 pCi/l for indicator and control locations respectively.
The variability in concentration of I-131 in milk depended on the local precipitation during the deposition of I-131 on the ground and the method of feeding the milch animals.
Cs-137 was detected in two (2) of sixty-eight (68) samples and averaged 6.6 pC1/1 at indicator locations only. No other gamma-emitting isotopes except potassium-40 were detected in any milk samples.
This is consis-tent with the finding of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesiura, strontium, barium, and iodine (National Center for Radiologocial Health, 1968).
- /
In summary, the milk data for 1986 show no radiological effects of the plant operation, but the presence of I-131 and Cs-137 in milk samples does exhibit the effect of the nuclear accident at Chernobyl.
Grass A total of twenty-eight (28) analyses for iodine-131 was performed during the reporting period.
Twenty-four (24) samples had I-131 concentrations below the LLD level of 60 pCi/kg wet weight.
Four (4) samples collected on May 11 and May 25, 1986 contained I-131 in various concentrations.
The level ranged from 46 to 463 pCi/kg wet weight and averaged 190 pCi/kg wet weight. The variability in concentra-tion of I-131 on grass depended on the local precipitation.
t 21 l
Ru-103 (41 and 53 pCi/kg wet weight) was detected in two (2) samples collected June 7, 1986.
Cs-134 (34 and 58 pCi/kg wet weight) was detected in two (2) samples collected June 7, 1986.
Cs-137 was detected in six (6) of twenty-eight (28) samples.
The levels ranged from 13 to 145 pC1/kg wet weight and averaged 72 pCi/kg wet weight.
No other gamma-emitting isotopes except potassium-40 were detected in any grass samples.
In sumary, the grass data for 1986 show no radiological effects of the plant operation, but the. presence of Ru-103, I-131, Cs-134 and Cs-137 in grass samples does exhibit the effect of the nuclear accident at Chernobyl.
Food Crops Gamma-emitters in food crops, except naturally-occurring bery111um-7 and potassium-40, were below their respective LLDs.
No station effect was indicated.
Fish In fish, all gamma-emitters, except for potassium-40, were below their
/'
respective LLDs. Cs-137 concentrations averaged 36.0 pCi/kg wet weight i
and 57.2 pC1/kg wet weight at indicator and control locations, respec-(,
tively. No station effect was indicated.
I Bottom Sediments l
In bottom sediments, the concentrations of Cs-134 were below the detec-tion limit of 150 pCi/kg dry weight in all samples. Cs-137 concentration l
averaged 210 pCi/kg dry.
No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any of the samples analyzed.
No station effect was indicated.
I Fodder l
Gamma-emitting
- isotopes, except naturally-occurring beryllium-7 and potassium-40, were below their respective LLDs.
No station effect was indicated.
22
5.0 FIGURES AND TABLES l
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23
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Figure 5.0-3.
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Table 5.0-1.
Radiological Environmental Monitoring Program (REMP), Fermi-2 huclear Power Plant.
Estimated Freq:;ency Number of Nw6er of Cc11ection Type of of Analy,es/
Sample Type Locations Frequency Analysis Analysis Year Remarks I.
DIRECT RADIATION TLD 38 Quarterly Gama Dose Quarterly 148 2 sets of 4 dosimeters at each location.
2.
AIRBORNE a.
Particulates 5
Weekly Gross Beta Weekly 260 On all samples.
Gama Isot.
Quarterly 20 Quarterly composites by location.
b.
Radiciodine 5
Weekly lodine-131 Weekly-260 On all samples.
3.
WATERBORNE a.
Surface Water 2
Monthly Gama Isot.
Monthly' 24 On all samples (monthly composite).
gu Tritium Quarterly 8
Quarterly composite by location, b.
Ground Water 1 or 2 Quarterly Gama Isot.
OJarterly Collect only if likely to De Tritium Quarterly affected.
c.
Drinking Water 2
Monthly Gross Beta Monthly 24 On all monthly composites.
Gama Isot.
Monthly 24 On all monthly composites.
Tritium Quarterly 8
On all quarterly composites Iodine-131 Bi-weekly If required.
d.
Snoreline Sediment 4
Semi-Annually Gamma Isot.
Semi-Annually 8
Collected second and third quarter.
3.
INGESTION a.
Milk 5
Semi-Monthly Iodine-131 Semi-Monthly 40 On all samples.
(June 15 - Oct. 15)
Gama Isot.
Semi-Monthly 40 On all samples.
5 Monthly Iodine-131 Monthly 45 On all samples.
(Oct. 15 - June 15)
Gamma Isot.
Monthly 45 On all samples.
b.
Fodder 5
Annually Gama Isot.
Annually 5
(h all samples.
c.
Vegetation-3 Twice during harvest Gama Isot.
Twice a year 6
On edible portions.
Food Products season Iodine-131 On leafy vegetables.
d.
Fish 2
Semi-Annually Gama Isot.
Semi-Annually 8
On edible portions.
(2 species)
Collected in second and third quarters.
Table 5.0-2 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Meteorological Stetion Sector / Azimuth Distance fro =
Numbar Direction Reactor (Approx)
Description Media Frequer 1
NE/38' l.4 mi, Estral Beach (community)
Direct Radia t ion O
Pole on Lckeshore, 18 Radioiodine W
Poles S. of Lakeview Particulates W
2 NNE/21' l.1 mi.
Tree at the termination Direct Radiation Q
Brancho Street (private residence) 3 N/4*
1.1 mi, Pole at NW corner of Swan Direct Radiation Q
Boat Club Fence (Community) 4 NNW/340' O.6 mi.
Site Boundary and Toll Direct Rad iation Q
Road, on Site Fence by Radioiodine W
APS #4 Particulates W
5 NW/321' O.6 mi.
Site Boundary and Toll Direct Radiation Q
Road on Site Fence by Radioiodine W
APS #5 Particulates W
6 WNW/296*
0.6 mi.
Pole NE corner of bridge Direct Radia t ion Q
over Toll Road 7*
W/269*
14.2 mi.
Pole, behind Doty Farm, Direct Radiation Q
7512 N. Custer Road Radioiodine W
(control)
Particulates W
Milk H-S Fodder A
't 3,
S-1 NW/304*
1.9 mi.
Pole NE corner Dixie Direct Rad iation Q
IY Highway and Post Road S-2 NNW/333*
1.5 mi.
Pole NW corner Trombley Direct Radiation Q
Road and Swan View Road S-3 N/6*
2.2 mi.
Pole on S side Massarant Direct Radiation Q
- 2 Poles W of Chinavarre S-4 NNE/25*
6.3 mi.
Pointe Houillee - W.
Direct Rad ia t ion Q
Jef ferson and Campau Road,
Pole on SE corner of Bridge S-5 NNE/33*
6.1 mi.
I'ointe Mouillee Game Area Direct Rad iaion Q
- Field Of fice, Pole near tree north area of parking lot-
- Indicates Control Location 28
Table 5.0-2 (continued)
Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Meteorological Station Sector / Azimuth Distance from Numbsr Direction Reactor (Approx)
Description Media Frecuenc S-6 N/357' 4.1 mi.
Labo and Dixie Highway -
Direct Radiaion Q
Pole on SW corner with light S-7 NNW/338*
4.4 mi.
Labo and Brandon - Pole Direct Radiation Q
on SE corner near RR S-8 NW/318' 3.9 mi.
Pole NW corner Newport
, Direct Radiation Q
and Brandon Roads S-9 WNW/282*
4.8 mi.
Pole on SE of War and Direct Radiation Q
Post Roads S-10 W/273*
5.2 mi.
Pole on NE corner Nadeau Direct Radiation Q
and Laprad near mobile home park a
S-11 WSW/245*
4.8 mi.
Pole on NW corner Mentel Direct Radiation Q
and Hurd S-12 SW/234' 5.0 mi.
Pole in parking lot of Direct Radiation Q
Department Natural Re-sources Office Builing -
Sterling State Park S-13 WSW/253*
2.6 mi.
Pole S side Williams Road Direct Radiation Q
- 8 Poles W of Dixie Hwy.
f (Special Area)
- ('/
S-14 WSW/237*
2.7 mi.
Pole N side of Pearl at Direct Radiation Q
Parkview - Woodland Beach (populated area)
S-15 8SE/168*
1.2 mi.
Pole N side of Point Aux Direct Rad ia tion Q
Peaux 2 Poles W of Long
]
(site boundary)
S-16 SSW/193*
1.1 mi.
Pole S side of Point Aux Direct Radiation Q
Peaux - 1 Pole W of Huron next' to vent pipe (site 4
boundary)
S-17 SW/222' l.2 mi.
Termi gate along Point Aux Direct Rad iat ion Q
Peaux Road - on fence post W of gate (site boundary) l l
29
Table 5.0-2 (continued)
Rrdiolegical Environm:ntal Manitoring Pregrtm, Fermi 2 Sample Locations and Associated Media Meteorological Station Sector / Azimuth Distance from Number Direction Reactor (Approx)
Description Media Frecuen S-18 WSW/249' l.4 mi.
Pole on Toll Road - 13 Direct Radia tion Q
Poles S of Fermi Drive S-19 WSW/258' l.1 mi.
Pole on Toll Road, 6 Poles Direct Radiation Q
S of Fermi Drive S-20 SW/223' 7.0 mi.
Pole NE corner McMillan Direct Rad iat ion Q
and East Front Street i
(Special Area)
S-21*
SW/227*
10.6 mi.
Pole SE corner of Mortar Direct Radiation Q
Creek and Laplaisance S-22*
WSW/237*
10.3 mi.
Pole E side of S. Dixie, Direct Rad iation Q
l Pole S of Albain i
S-23 WSW/247*
7.8 mi.
Pole Custer (St. Mary's)
Direct Rad iat ion Q
Park corner of N Custer and Dixie (Monroe St.)
(N side, next to river)
(Special Area)
S-24*
WSW/254*
6.9 mi.
Pole Milton " Pat" Munson Direct Radiation Q
Recreational Reserve -
N Custer Road (Control)
S-25 WNW/296*
10.3 mi.
Pole corner Stony Creek Direct Radiation Q
and Finzel Roads S-26 NW/318*
9.3 mi.
Pole U side Graf ton Road,
Direct Radiation O
3, 1 Pole N of Ash /Crafton iV intersection S-27 NNW/339' 9.7 mi.
Pole E side of Port Creek, Direct Rad ia t ion Q
1 Pole S of Will-Carlton Road S-28 N/360*
7.0 mi.
Pole en S side of S. Huron Direct Radiation Q
River Drive across from Pace St. (Special Area)
S-29 N/360*
9.2 mi.
Pole NE corner of Gibraltar Direct Radiation Q
and Cahill Roads
- Indicates Control Location l
30
Table 5.0-2 (continued)
Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Meteorological Station Sector'/ Azimuth Distance from 1
Number Direction Reactor (Approx)
Description Media Frecuer S-30 NNE/23*
9.9 mi.
Pole S corner of Adems Direct Radiation Q
and Gibraltar (across from Humbug Marina) 8 S
0.9 mi.
Point Aux Peaux, 100-300ft.
Sediment SA offshore sighting directly to land based water tower 9
E 0.2 mi.
Fermi-2 discharge, approx.
Sediment SA 200 ft. offshore 10 NE 1.1 mi.
Estral Beach, approx. 200ft. Sediment SA offshore sighting directly to land based windmill 11*
NNE 9.5 mi.
Celeron Island Fish SA 12 SSE 0.4 mi.
Fermi Unit 1 Raw Lake Water Surface Water M
Intake Structure 13 S
1.2 mi.
Monroe Water Station Drinking Water M
N side of Pointe Aux Peaux 1/2 block W of Long Rd.
14*
NE 13 mi.
Deco's Trenton Channel Surface Water M
Power Plant Intake Structure
/'
(Screenhouse #2)
(/
15*
NNE 20 mi.
Detroit (Allen Park) Water Drinking Water M
Station 14700 Moran Rd.
16 E
0.4 mi.
Fermi-2 dische.rge (approx.
Fish SA 1200 ft. offshore) 17 SW l.0 mi.
Corner of Erie Street and Radioiodine W
Point Aux Peaux Roads Particulates W
18 WSW 2.0 mi.
Residence Grass M-5 4352 Poiste Aux Peaux In lieu of milk 19 WNW/289*
1.7 mi.
Residence Milk M-E 6494 N. Dixie Hwy.
Direct Radiation Q
20 NW 5.7 mi.
Resume Farm Milk M-S 2705 East Labo Fodder A
" Indicates Control Location 31
Tablo 5.0-2 (continued)
Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Meteorological
. Station Sector / Azimuth Distance from Numb 9r Direction, Reactor (Approx)
Description Media Frecuenc>
22 W
0.5 mi.
Outlet Fermi-2 Storm Drains Sediment SA l
31 NW 4.5 mi.
Yoas Farm Milk M-SM 3239 Newport Rd.
Fodder A
32 NNE 4.0 mi.
Roland Farm Milk M-SM 9501 Turnpike Hwy.
Fodder A
W1 S
0.4 mi.
Approx. 100 ft. W of Groundwater On flow Lake, Erie, S end of reversal former plant clubhouse site W2 SSW l.0 mi.
4 ft. S of Pointe Aux Croundwater On flow Peaux (PAP) Rd. fence, reversal 427 f t. W of where PAP crosses over Stoney Point's western dike W3 SW 1.0 mi.
143 f t. W of PAP Rd.
Groundwater On flow gate, (2 f t. N of PAP reversal Rd. fer.ce W4 WNW
- 0. 6 nd.
42 f t. N of Langton Rd.,
Croundwa ter On flow 8 ft. E of Toll Rd. fence reversal L1 SSE/147' O.17 S.E. Corner Protected Direct Radiation Q
Area Fence (PAF)
.f.
r L2 SE/139' O.16 Midway along OBA - PAF Direct Radiation Q
7 L3 SE/133*
0.15 Midway between OBA Direct Radiation Q
and Shield Wall - PAF L4 SE/125' O.15 Midway along Shield Direct Radiation Q
Wall - PAF L5 ESE/ll4*
0.14 Midway between Shield Wall Direct Radiation Q
and Aux. Boilers - PAF L6 E/10l*
0.14 Opposite OSSB door - PAF Direct Radiation Q
L7 E/84*
0.16 N.E. Corner - PAF L8 ENE/71*
0.2 NE side barge slip -
Direct Radiation Q
on fence 32
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. ~ _ _ _
i i
l Table 5.0-3.
Detection Capabilities for Environmental Sample Analyses, Lower Limits of Detection a
(LLD)b,c, Radiological Environmental Monitoring Program, Enrico Fermi Unit 2 j
Detroit Edison Company.
I Airborne Water Particulate or Fish Milk Food Products Sediment l
Analysis (pCi/1)
Gas (pCi/m3)
(pC1/kg wet)
(pCi/1)
(pC1/kg wet)
(pC1/kg dry) 1
[
Gross beta 4.0 0.01 H-3 2000 l
Mn-54 15 130 Fe-59 30 260 l
5 Co-58 15 130 w
I i
Co-60 15 130 l-
}
Zn-65 30 260 1
Zr-95 15 Nb-95
- 15 4
1 J
I-131 1.0d 0.07 1.0 60e i
l Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 15 15
)
La-140 15 15 t
l I
l
Table 5.0-3.
(continued)
TABLE NOTATION I
a This list does not mean that only these nuclides will be considered.
Other peaks that are identifiable, together with those of the above nuclides, will also be analyzed and reported, b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
The LLD is defined, for purposes of these specifications, as the small-C est concentration of radioactive material in a sample that will yield a net count, above system, background, that be detected with 95% probablilty with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 sb i
LLD =
E x v x 2.22 x Y x exp (-ut) where LLD is the lower limit of detection as defined above (as pCi per unit massorvolume).
is the standard deviation of the background counting rate or of
/
sbthe counting rate of a blank sample as appropriate (as counts per (jr minute).
E is the counting efficiency (as counts per transformation).
V is the volume or mass of sample.
Y is the fractional radiochemical yield (when applicable).
A is the radioactive decay constant for the particular radionuclide.
At is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
34
-..- --: c
4 Table 5.0-3.
(continued)
TABLE NOTATIONS (continued)
The value of sb used in the calculation of the LLD for a detection system will be based on the actual observed variance of the background counting i
rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclide determined by gama-ray spectrometry, the background will include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
Occasionally background fluctuations, unavoidably small sample. sizes, the presence of interfering nuclides, or other circumstances may render these LLDs unachievable.
In such cases, the contributing factors will be identified and described in the Annual Radio-logical Environmental Operating Report.
d LLD for drinking water.
I
' For grer.n leafy vegetables.
l l/
4 i
4 4
i 35
Table 5.0-4.
Environmental Radiological Monitoring Program Sunnary.
Name of Factitty Enrico Ferst Unit 2 Docket No. 50-341 Reporting Period January - December 1986 Location of Factitty 30 miles Southwest of Detroit, Michloan (Frenchtown Township)
Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Numer of Type Number of Mean Mean Mean Non-routine (Units)
Analysesa LLDb kongeC Locatiend.
Range Range Aesultse Airborne G8 260 10.0f 34.1 (202/200)
F-4. Site Boundary 34.9 (52/52) 33.4 (52/52) 0 Particulate 1 (6.2-306.0) 0.6 al NNW (8.6-306.0)
(9.1-252.3)
(10-3pC1/mJ)
GS 20 Be-7 13.4 74.4(12/16)
F-1. Estral Beach 104.1 (3/4) 76.6 (4/4) 0 (44.5-129.1) 1.4 mi NE (73.6-129.1)
(46.8-98.7)
Cs-134 50.0 6.2(4/16)
F-4. Site Boundary 8.9 (1/4) 7.7(1/4) 0 (4.4-8.9) 0.6 mi NMW Cs-137 60.0 14.0(4/16)
F-4 Site Soundary 17.9(1/4) 12.3 (1/4) 0 (11.3 17.9) 0.6 el NNW y
Ru-103 6.5 9.9 (2/16)
F-7. Doty Fare 14.6 (1/4) 14.6 (1/4) 0 (8.1-11.7) 14.2 mi W
<LLD Other gammes 8.3 4LD Airborne I-131 260 0.079 0.27 (14/208)
F-17. Erie St. and 0.38 (3/52) 0.26 (2/52) 0 Iodine (0.08-0.64)
Point aux Peaux (0.17-0.64)
(0.17-0.34)
(pC1/m3) 1.0 mi SW Ganna Gamma dose 354 14.8 (322/322) 5-18. Pole on Toll 20.1 (8/8) 16.2 (32/32)
Background
(8.9-22.6)
Road. 13 Poles 5 (18.3-22.6)
(14.8-19.0)
(TLDs) of Ferst Drive (mR/Qtr.)
1.4 el WSW Water. Surface 65 24 (pC1/1)
(LLD 0
- 43-54 15
<LLD GLD 0
Fe-59 30 GLD
<LLD 0
Co-58 15 RLD Co-60 15 RLD
<LLD 0
RLD 0
Zr-Mb.95 15 RLD
4~
+
Table 5.0-4.
Environmental Radiological Monitoring Program Summary.
Name of Facility Enrico Feret Unit 2 Docket No. 50-341 Reporting Period January - Decee er 1986 Location of Facility 30 miles Southwest of Detroit, Michigan (Frenchtown Township) l Indicator Location with Highest Control Sample Type and Locations Annual mean Locations numer of Type numer of Mean Mean mean Non-routine (Units)
Analysesa LLDb RangeC Locationd Nange Range Results*
<LLD 0
Water Surface Cs-134 15
<LLD (pC1/1)
<LLD 0
i (continued)
Ba-La-140h 15
<LLD (LLD 0
(LLD 0
Tritium 8
310 (LLD w
- Water, G8 24 4.0 2.4(12/12)
F-13 Monroe Water 2.4 (12/12) 1.9 (12/12) 0 N
Drinking (1.8-3.2)
Station, 1.2 mi 5 (1.8-3.2)
(1.8-2.6)
(PC1/1)
GS 24
<LLD 0
- -54 15
<LLD (LLD U
Fe-59 30
<LLD
<LLD 0
Co-58 15 (LLD
<LLD 0
Co-60 15
<LLD
)
<LLD U
Zn-65 30
<LLD 1
<tLD 0
Zr-95 15
<LLD
<LLD 0
Nb-95 15
<LLD (LLD 0
Cs-134 15
<LLD (LLO O
Cs-137 18
<LLD (LLD 0
Ba-La-1408 15
<LLD i
<LLD 0
Tritium 310
<LLD 1
1
m Table 5.0-4.
Environmental Hadiological Monitoring Program Sunnary (continued)
Name of Factitty Enrico Feral Unit 2 Docket No. 50-341 Reporting Perloo January - Decenter 1986 Location of Facility 30 miles Southwest of Detrott, Michigan (Frenchtown Townsnip) 1 Indicator Location with Hignest Control Sample Type and Locations Annual Mean Locations Numoer of Type Numoer of Mean riean Mean Non-routine (Units)
Analysesa LLDb gangec Locationd Range Range Resultse 1
Milk 1-131 68 1.0 6.2(10/51)
F-32. Roland Fars 12.0 (4/17) 1.2 (4/17) 0 (pCf/1)
(0.7-37.5) 4.0 mi NNE (0.8-37.5)
(0.6-1.5) i GS 68 l
Cs-134 15 (LLD (LLO U
Cs-137 18 6.6 (2/51)
F-31, Yoas Fars 7.3 (1/17)
(LLD 0
(6.0-7.3) 4.5 mi NW 8a-La-140 15
<LLD (LLD 0
i w
i CD i
K-40 500 1280 (51/51)
F-31 Yoas Farm 1390 (17/17) 1310 (17/17) 0 (1030-1600) 4.5 at NW (1170-1580)
(1250-1430)
Grass 1-131 28 60 190 (4/28)
F-18. Residence, 254(2/14) hone 0
(pC1/kg wet)
(46-463) 4352 Pointe aux (46-463)
Peaux, 2.0 at WSW GS 28 I
Cs-134 60 46 (2/28)
F-18. Residence, 58 (1/14)
None 0
(34-58) 4352 Point aux Peaux, 2.0 at WSW Cs-137 80 72 (6/28)
F-19. Residence, 77(2/14)
None 0
(13-145) 6494 Otxte Hwy.
(61-93) l.7 at WNW 84-La-140 60
<tLD None U
K-40 500 5960 (28/28)
F-19. Restoence, 6220 (14/14)
None 0
(2680-10400) 6494 Dixie Hwy.
(3040-10400) 1.7 mi WNW l
i
Table 5.0-4.
Environmental Radiological Monitoring Program Summary (continued)
Name of Facility Enrico Ferst Unit 2 Docket No. 50-341 Reporting Period January - December 1986 Location of Fact 11ty 30 miles Southwest of Optroit. Michigan (Frenchtoun Tounship) l Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of 1
Type Number of Mean Mean Mean Non-routine (Units)
Analysesa LLDb RangeC Locationd Range Range Results*
<LLD 0
Food Products 1-131 12 60
<LLD (pC1/kg wet) 4 GS 15
<LLD 0
Cs-137 80
<LLD Se-7 497 91 (1/11)
Loc. 2. Roland 91 (1/6)
(LLD 0
Farm. 4.0 at NNE K-40 500 3470(11/11)
Loc. 1. Masserant 3510 (5/5) 2600 (4/4) 0 (1060-4880) 2.8 mi Nm (1060-4880)
(2000-3210) l 0
Fish GS 5
(pct /kg met)
(LLD 0
Mn-54 130
<LLD
<LLD 0
Fe-59 260
<LLD Co-58 130
<LLD (LLD 0
(LLD 0
Co-60 130
<LLD i,
<LLD 0
Zn-65 260
<LLD (LLD 0
Cs-134 130 (LLD Cs-137 150 36.0 (1/3)
F-11. Celeron 57.2 (2/2) 57.2(2/2) 0 Island (24.4-90.0)
(24.4-90.0) 9.5 mi NE I
K-40 500 3130(3/3)
F-11. Celeron 3290 (2/2) 3290 (2/2) 0 (2490-3600)
Island (3056-3527)
(3056-3527) i 9.5 at ME J
I l
[
Table 5.0-4.
Environmental Radiological Monitoring Program Summary (continued)
Name of Factitty Enrico Ferri Unit 2 Docket No. 50-3a1 Reporting Period January - December 1986 Location of Fact 11ty 30 miles Southwest of Detroit. Michigan (Frenchtown Township)
Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Num6er of Type Number of Mean Mean Mean Non-routine (Units)
Analysesa LL0b RangeC Locationd Range Range Nesults' Sediments GS 8
Mone 0
K-40 1000 10150 (8/8)
F-22. Outlet 16220 (2/2)
None 0
(9910-17125)
Fermi-2 (15310-17125) i O.6 at W None O
Co-58 NA
<LLD None 0
Co-60 NA
<LLD None 0
g Zn-65 NA RLD None O
Zr-Nb-95 NA
<tLD Cs-134 150 RLD None 0
i Cs-137 180 210 (3/8)
F-22. Outlet 490 (2/2)
None 0
(14-588)
Femi-2 (392-588) 0.6 at W Fodder GS 4
(pCf/kg wet)
(LLD 0
Cs-134 60 RLD Cs-137 60 26 (1/1)
F-32, Roland Fars 26 (1/1)
<LLD 0
4.0 mi NNE Be-7 164 780(3/3)
F-32, Roland Fars 1287(1/1)
GLD 0
(524-1287) 4.0 ml NNE K-40 500 6080 (3/3)
F-32, Roland Farm 9550 (1/1) 7270 (1/1) 0 (3750-9550) 4.0 mi NME G8 = gross beta; GS = gamma scan.
b LLD = nominal lower limit of detection based on 4.66 signa error for background sample.
C Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectfled locations is indicated in parentheses (F).
d* Locations are specified (1) by name and code (Table 2) and (2) distance, direction, and sector relative to reactor site.
Nonroutine results are those which exceed ten times the Control station value. If no control station value is avellable,
, the result is considered nonroutine if it exceeds ten times the preoperational value for the location.
Two higher LLDs (<13.8 and <41.2) resulting from low volumes due to pump malfunctions have been excluded from determination of LLD.
9 One higher LLD (<0.11 pC1/m3) has been excluded in the determination of the LLD of airborne lodine-131. It resulted from a delay in counting.
One higher LLD (<21.3 pCf/1) has been excluded in the determination of LLD for Be-La-140 in surface water. It resulted from a deley in counting.
One higher LLD (<15.3 pC1/1) has been excluded in the determination of LLD for Ba-La-140 in drinkag water. It resulted from a delay in counting.
6.0 REFERENCES
CITED Eisenbud, M.
1963.
Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, and 276.
Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel.
1986. Chernobyl, in Chemtech, October 1986, pp. 596-605.
Teledyne Isotopes Midwest Laboratory.
1985.
Analytical Procedures Manual, Revision 5, 7 February 1985.
1985.
Quality. Control Procedures Manual, Revision 6, 9 August 1985.
1985.
Quality Assurance Program Manual, Revision 1,15 April 1985.
U. S. Atomic Energy Commission.
1972.
HASL Procedures Manual, Health and Safety Laboratory, New York, New York.
U. S. Public Health Service.
1967.
Radioassay Procedures for Environ-mental Samples, National Center for Radiological Health, Rockville, Maryland (Public Health Service Publication No. 999-RH-27).
U.
S.
Nuclear Regulatory Connission.
1978.
"An Acceptable Radiological
/
Environmental Monitoring Program," Radiological Assessment Branch Technical Position, March, 1978 and Revision 1, September, 1979.
d U.S.S.R. State Committee on the Utilization of Atomic Energy.
The Accident at the Chernobyl Nuclear Power Plant and its Consequences.
Informa-tion compiled for the I.A.E.A. Expert's Meeting, 25 - 29 August 1986, Vienna, Austria.
41
7.0 ' COMPLETE DATA TABLES 1986
?
. '\\/
42
FERMI-2 TABLE OF CONTENTS Section P3 List of Figures iii List of Tables........................
iv
1.0 INTRODUCTION
7.0-1 u
b 7.0-11
FERMI-2 LIST OF FIGURES No.
Title Page
'l Monthly averages of airborne particulates collected weekly at F-1.....................
7.0-13 2
Monthly averages of airborne particulates collected weekly at F-4.....................
7.0-15 3
Monthly averages of airborne particulates collected weekly at F-5.....................
7.0-17 4
Monthly averages of airborne particulates collected weekly at F-7.....................
7.0-19 5
Monthly averages of airborne particulates collected weekly at F-17.....................
7.0-21
/
't 4
1 7.0-111
FERMI-2 LIST OF TABLES No.
Title Page 1
Samma Radiation, as measured by TLDs.........
7.0-2 2
Samma Radiation, as measured by TLDs, grouped by sectors...
7.0-10 3
Airborne particulates and iodine collected at Location F-1, analyses for gross beta and iodine-131 7.0-12 4
Airborne particulates and iodine collected at Location F-4, analyses for gross beta and iodine-131 7.0-14 5
Airborne particulates and iodine collected at Location F-5, analyses for gross beta and iodine-131 7.0-16 E
6 Airborne particulates and iodine collected at Location F-7, analyses for gross beta and todine-131 7.0-18 7
Airborne particulates and iodine collected at Location F-17, analyses for gross beta and iodine-131 7.0-20 8
Airborne particulates, gross beta analyses, monthly averages.
7.0-22 9
Airborne particulates, analysis for gamma-emitting isotopes 7.0-23 i[
10 Surface water, analysis for gamma-emitting isotopes 7.0-24
'(t 11 Drinking water, analysis for gross beta and gamma-emitting i
isotopes 7.0-26 12 Surface and drinking water, analysis for tritium.......
7.0-29 l
13 Shoreline sediments, analysis for gamma-emitting isotopes 7.0-30 14 Milk collected at Locations F-7, F-19, F-20, F-31, and F-32, analyses for iodine-131 and gamma-emitting isotopes...
7.0-31 15 Grass collected in lieu of milk Locations F-18 and F-19, analyses for iodine-131 and gamma-emitting isotopes...
7.0-34 16 Cattlefeed, analysis for gamma-emitting isotopes.......
7.0-35 i
i l
7.0-iv
_.. ~.... -,..
FERMI-2
' LIST OF TABLES (continued)
No.
Title
- Page, l
17 Food products, analysis for gamma-emitting isotopes
-7.0-36 18 Fish, analysis for gamma-emitting isotopes..........
7.0-37 5
h i
t 7.0-v
\\
FERMI-2
1.0 INTRODUCTION
For all gama isotopic analyses, spectrum is computer scanned from 80 to 2048 kev.
Specifically included are Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, I-131, Cs-134, Cs-137, and Ba-La-140.
Naturally occurring gamma-emitters, such as Ra daughters are frequently detected but not listed here.
Potassium-40 is listed only if detected.
Data listed as "<" are at the 4.66 sigma level, others are 2 sigma.
Unless noted otherwise, the less than value
("<") for air particulates listed under "Other Gammas" is for Nb-95 and may be higher or lower for other radionuclides.
All concentrations, except gross beta, are decay corrected to the time of collection.
v i
7.0-1
--g- - -,.,
-v
-m-
-r
--v=--
'*- " ~ "
'"-"W-''"'"'"F
FERMI-2 Table 1.
Gama Radiation, as measured by TLDs.
4 Collection:
Quarterly exchange Units: mR/ standard quarter, net exposure Date Placed:
12-29-85 Date Removed:
03-29-86 4
Days in the Field:
90 Calculated Transit Dose:
(3.8 i 0.7) mR I
Location mR/Std. Qtr.
Azimuth Distance l
Station
(*)
(miles)
A B
Mean i s.d.
% s.d.
1 38
- 1. 4 11.9tl.2 11.4*1.0 11.610.4
- 3. 0 2
21 1.1 15.310.8 15.410.9 15.410.1
- 0. 5 3
4
- 1. I 12.8i0.9 12.2*0.7 12.5*0.4
- 3. 4 4a 340
- 0. 6
- 16. 7f 2.1 16.1*2.1 16.410.4 2.6 1
5 321 0,6 15.710.8 15.510.8 15.610.1
- 0. 9 6
296
- 0. 6 11.4i0.8 11.6i0.7 11.Si0.1 1.2 7
269 14.2 16.Si0.8 16.Si0.9 16.5*0.0
- 0. 0 l
19a 289
- 1. 7 17.9i2.I 19.112.I
- 18. Si0. 8
- 4. 6 S-1 304
- 1. 9 16.910.8 15.6i0.9 16.210.9
- 5. 7 i
S-2 333
- 1. 5 13.610.8 12.3*0.8 13.Ot0.9
- 7. 0 J
S-3 6
2.2 16.710.9 16.1*0.9 16.4i0.4
- 2. 6 S-4 25
- 6. 3 12.li0.9 13.5i0.8 12.8tl.0
- 7. 6 S-5 33 6.1 13.3i0.7
- 12. Si0. 8 13.0*0.4
- 2. 7 5-6 357 4.1 15.810.8 16.3*0.8 16.Oi0.4 2.2 S-7 338
- 4. 4 15.910.7 15.6i0.9 15.8*0.2
- 1. 3 S-8 318
- 3. 9 14.8*0.8 15.3t0.9 15.Ot0.4
- 2. 4 S-9 282
- 4. 8 15.9t0.8 15.4*1.0 15.6*0.4
- 2. 3 S-10 273 5.2
- 16. Oil.0 16.Ot0.9 16.Ot0.0
- 0. O S-11 245
- 4. 8 15.010.8 15.7*0.7 15.4i0.5
- 3. 2 L,
S-12 234
- 5. 0 20,3i1.2 20.3i1.5 20.3i0.0
- 0. 0 f
S-13 253
- 2. 6
- 17. Sil. 2 17.110.7 17.3i0.3 1.6 i
?
S-14 237
- 2. 7 15.410.8 15.5i0.9 15.4i0.1
- 0. 5 k/
S-15 168
- 1. 2 14.210.9 14.5*0.9 14.410.2
- 1. 5 S-16 193 1.1 16.Ot0.8
- 16. Oil.0
- 16. Oi0. 0
- 0. O S-17 222
- 1. 2 14.2*1.2 14.7tl.0 14.4i0.4
- 2. 5 i
S-18 249 1.4 19.010.9 18.3fl.0 18.6t0.5
- 2. 7 S-19 258 1.1 19.6fl.1 19.210.8 19.410.3
- 1. 5 S-20 223
- 7. 0 13.110.9 13.3*1.1 13.2t0.1 1.1 S-21 227 10.6 15.6i0.8 15.3i0.9 15.410.2
- 1. 4 S-22 237 10.3 16.810.7 16.Si0.8 16.610.2
- 1. 3 S-23 247
- 7. 8 L0ST IN THE FIELD l
S-24 254 8.9 16.410.8 15.910.7 16.210.4
- 2. 2 S-25 296 10.3 16.Oi0.8 15.810.8 15.9*0.1
- 0. 9 1
S-26 318
- 9. 3 15.0i0.8 15.211.0 15.1i0.1
- 0. 9 i
S-27 339
- 9. 7 14.610.7 13.7tl.0 14.2i0.0 4.5 i
S-28 360
- 7. 0 15.610.8 15.2il.0 15.410.3
- 1. 8 i
S-29 36 0
- 9. 2 16.810.8 16.7*0.7 16.8t0.1
- 0. 4 l
i S-30 23
- 9. 9 16.410.8
- 16. Oi0. 8 16.210.3
- 1. 7 a Placed 02-27-86; removed 03-29-86.
i
- 7. 0- 2 l
7 FERMI-2 Table 1.
Gama Radiation, as measured by TLDs.
Collection: Quarterly exchange Units: mR/ standard qearter, net exposure, Date Placed:
12-29-85 Date Removed:
03-29-86 Days in the Field:
90 Calculated Transit Dose:
(3.6 i 0.6) mR 4
Location mR/Std. Qtr.
i Azimuth Distance Station
(*)
(miles)
A B
Mean i s.d.
% s.d.
)
L-1 147 0.17 11.110.8 11.1*0.8 11.1*0.0
- 0. O L-2 139 0.16 L0ST IN THE FIELD L-3 133 0.15
- 11. lf 0. 7 10.6t0.8 10.8i0.4
- 3. 7 L-4 125 0.15 10.7*0.7 10.7*0.7 10.7*0.0
- 0. 0 L-5 114 0.14 10.6i0.7 10.5*0.7 10.6*0.1
- 0. 7 L-6 101 0.14 10.810.7 10.510.8 10.6*0.2
- 2. 0 L-7 84 0.16 10.910.8 11.0i0.7 11.010.1
- 0. 6 L-8 71 0.2 12.7*0.6 13.210.8
- 13. Oi0. 4
- 2. 7 I
i i
,/
- f 4
i 2
4 7.0-3
FERMI-2 Table 1.
Ganna Radiation, as measured by TLDs.
Collection:
Quarterly exchange Units: mR/ standard quarter, net exposure Date Placed:
03-29-86 Date Removed:
06-29-86 Days in the Field:
92 Calculated Transit Dose:
(4.9fu.6)mR Location mR/Std. Otr.
Azimuth Distance Station
(*)
(miles)
A B
Mean i s.d.
% s.d.
1 38
- 1. 4 11.7t0.9 12.110.7 11.910.3
- 2. 5 2
21 1.1 17.310.8 16.110.7 16.7:10.8
- 4. 8 3
4 1.1 14.SiOl7 13.8i0.8 14.2t0.5
- 3. 5 4
34 0
- 0. 6 18.410.8
- 18. lil. 0 18.2*0.2 1.1 5
32 1
- 0. 6 17.910.8 17.410.9 17.610.4
- 2. 3 6
296
- 0. 6 10.310.7 10.6i0.7 10.4i0.2
- 1. 9 7
269 14.2 19.0*1.0 18.6tl.0 18.8i0.3 1.6 19 289
- 1. 7 18.910.8 17.3i0.7 18.1*1.1 6.1 S-1 304
- 1. 9
- 19. li0. 7
- 19. Si0. 9 19.3i0.3 1.6 S-2 333
- 1. 5 15.310.7 14.6i0.8 15.0i0.5
- 3. 3 S-3 6
- 2. 2 19.110.8 19.010.7
- 19. 0f 0.1
- 0. 5 S-4 25
- 6. 3 13.3i0.7 14.3*1.2 13.8f0.7 5.1 S-5 33 6.1 14.110.7 13.5i0.9 13.810.4
- 2. 9 S-6 357 4.1 18.8*1.0
- 19. 0t0. 7 18.910.1
- 0. 5 S-7 338 4.4 19.1*1.0 18.3i0.8 18.7i0.6 3.2 5-8 318
- 3. 9 16.5i0.7 16.0i0.7 16.210.4
- 2. 5 S-9 282
- 4. 8 17.410.9
- 18. lil.1 17.810.5
- 2. 8 S-10 273 5.2 17.9tl.0 18.510.8 18.210.4 2.2 S-11 245
- 4. 8 16.510.9
- 17. li0. 9 16.8i0.5
- 3. 0 S-12 234
- 5. 0 20.210.8 19.810.9 20.0i0.3
- 1. 5 S-13 253
- 2. 6 21.0i0.8 20.2*1.0 20.6i0.6
- 2. 9 L' '
S-14 237
- 2. 7 17.0fl.0 15.610.7 16.3*1.0 6.1 1
S-15 168
- 1. 2 14.910.7 14.810.7 14.8*0.1
- 0. 7
- \\/
S-16 193 1.1 18.0f0.8 18.4i0.7 18.2i0.3 1.6 S-17 222
- 1. 2 15.510.7 14.710.7 15.1*0.6
- 4. 0 S-18 249
- 1. 4 22.6i0.9 22.610.7 22.6i0.0
- 0. 0 S-19 258 1.1 20.210.8 20.410.9 20.310.1
- 0. 5 S-20 223
- 7. 0 13.510.7 13.6i0.9 13.6i0.1
- 0. 7 S-21 227 10.6 16.410.7 15.110.7 15.810.9
- 5. 7 S-22 237 10.3 17.210.9
- 16. Si0. 9
- 16. 8i0. 5
- 3. 0 S-23 247
- 7. 8 13.210.7 13.410.8 13.310.1
- 0. 8 S-24 254
- 8. 9 17.310.9 16.410.9 16.810.6
- 3. 6 S-25 296 10.3 17.310.8 16.710.7 17.010.4
- 2. 4 S-26 318
- 9. 3 15.410.8 15.410.8 15.4t0.0
- 0. 0 S-27 339
- 9. 7 15.610.9 14.610.8 15.110.7
- 4. 6 S-28 36 0
- 7. 0 20.010.6a 17.710.6a 18.8*1.6
- 8. 5 S-29 36 0
- 9. 2 16.410.7 17.411.0 16.910. 7 4.1 S-30 23
- 9. 9 17.110.8 16.510.7 16.810.4 2.4 a Original TLD lost; spare TLD placed 06-12-86, removed 06-29-86.
7.04 l
FERMI-2 Table 1.
Gama Radiation, as measured by TLDs.
Collection:
Quarterly exchange Units: mR/ standard quarter, net exposure Date Placed:
03-29-86 Date Removed:
06-29-86 Days in the Field:
90 Calculated Transit Dose:
(4.910.7)mR Location mR/Std. Qtr.
Azimuth Distance Station (I)
(miles)
A 8
Mean i s.d.
% s.d.
L-1 147 0.17 11.810.8 11.710.7 11.810.1
- 0. 6 L-2 139 0.16 12.411.1 11.810.9 12.110.4
- 3. 5 L-3 133 0.15 12.010.8 11.711.0 11.810.2
- 1. 8 L-4 125 0.15 11.610.7 12.110.8 11.8i0.4
- 3. 0 L-5 114 0.14 12.3tl.2 11.210.8 11.810.8
- 6. 6 L-6 101 0.14 11.0*0.7 11.610.8 11.310.4
- 3. 8 L-7 84 0.16
'12.211.2 11.8i0.8 12.010.3
- 2. 4 L-8 71
- 0. 2 12.410.7 12.610.8 12.510.1 1.1
/
f T/
- 7. 0- 5~
FERMI-2 Table 1.
Gamma Radiation, as measured by TLDs.
Collection: Quarterly exchange Units: mR/ standard quarter, net exposure Date Placed:
06-29-86 Date Removed:
09-28-86 Days in the Field:
91 Calculated Transit Dose:
(3.0f0.3)mR Location mR/Std. Qtr.
Azimuth Distance Station
(*)
(miles)
A B
Mean i s.d.
% s.d.
1 38
- 1. 4 9.310.5 9.310.5 9.310.0 0.0 2
21 1.1 14.310.5 15.110.9 14.710.6
- 3. 8 3
4 1.1 12.110.7 11.910.6 12.010.1
- 1. 2 4
34 0 0.6 14.8i0.4 15.6i0.8 15.210.6 3.7 5
321 0.6 15.510.5 15.210.6 15.410.2
- 1. 4 6
296
- 0. 6 9.310.4 9.810.3 9.610.4
- 3. 7 7
269 14.2 16.310.6 16.410.7 16.410.1 0.4 19 289
- 1. 7
- 15. St0. 8 15.810.7 15.6i0.2 1.4 S-1 304
- 1. 9 16.810.6 16.310.6 16.6i0.4 0.4 S-2 333
- 1. 5 13.0i0.6 12.210.5 12.610.6 4.5 S-3 6
2.2 17.010.6 16.810.5 16.910.1
- 0. 8 S-4 25 6.3 10.510.4 12.310.6 11.4fl. 3 11.1 S-5 33 6.1 NDa NDa S-6 357 4.1 15.710.7 16.410.5 16.010.5 3.1 S-7 338 4.4 16.811.3 15.810.6 16.310.7 4.3 S-8 318
- 3. 9 14.410.5 15.010.5 14.710.4 2.9 S-9 282
- 4. 8 NDa NDa S-10 273 5.2 15.910.7 15.510.6 15.7i0.3
- 1. 8 S-11 245 4.8 14.310.7 14.9i0.4 14.6i0.4
- 2. 9
- /
S-12 234
- 5. 0 18.710.5 18.610.5 18.6i0.1 0.4 j
S-13 253 2.6 17.310.5 18.110.4 17.710.6
- 3. 2 (7
S-14 237
- 2. 7 14.310.5 14.710.6 14.510.3 2.0
!v S-15 168
- 1. 2 13.313.6 13.610.5 13.410.2
- 1. 6 S-16 193 1.1 15.910.6 15.7i0.6 15.810.1 0.9 S-17 222
- 1. 2 NDa NDa S-18 249
- 1. 4 19.310.6 18.910.9 19.110.3 1.5 S-19 258 1.1 18.4i0.7 18.710.5 18.610.2 1.1 1
S-20 223
- 7. 0 11.610.4 11.610.5 11.610.0 0.0 l
S-21 227 10.6 14.810.4 15.110.6 15.010.2
- 1. 4 S-22 237 10.3 15.710.4 15.010.7 15.410.5 3.2 S-23 247
- 7. 8 11.710.5 12.110.4 11.910.3 2.4 S-24 254 8.9 14.810.4 15.210.4 15.010.3
- 1. 9 S-25 296 10.3 15.310.7 15.310.5 15.310.0 0.0 S-26 318 9.3 NDa NDa r
l S-27 339
- 9. 7 13.710.4 12.410.7 13.010.9 7.1 L
S-28 360
- 7. 0 13.910.5 13.710.6 13.810.1
- 1. 0 S-29 360
- 9. 2 15.110.5 14.810.4 15.010.2
- 1. 4 S-30 23
- 9. 9 14.910.5 14.810.5
- 14. 810.1 0.5 a ND = No data; TLD lost in the field.
7.0- 6
FERMI-2 Table 1.
Gama Radiation, as measured by TLDs.
Collection: Quarterly exchange Units: mR/ standard quarter, net exposure Date Placed:
06-29-86 Date Removed:
09-28-86 Days in the Field:
91 Calculated Transit Dose:
(3.010.3)mR Location mR/Std. Qtr.
Azimuth Distance Station
(*)
(miles)
A B
Mean i s.d.
% s.d.
L-1 147 0.17 9.310.5 9.410.5 9.4t0.1 0.8 L-2 139 0.16 9.110.5 9.410.5 9.2i0.2 2.3 L-3 133 0.15 9.110.5 8.910.4 9.010.1
- 1. 6 L-4 125 0.15 9.21 0.4 9.210.4 9.2i0.0 0.0 L-5 114 0.14 9.110.4 9.210.4 9.210.1 0.8 L-6 101 0.14 9.2t0.4 9.0f0.4 9.110.1 1.6 L-7 84 0.16 9.410.4 9.510.4 9.410.1 0.8 l
L-8 71 0.2 11.010.4 11.210.4 11.110.1
- 1. 3 l
l' r
j 7.0- 7 i
FERMI-2 Table 1.
Gamma Radiation, as measured by TLDs.
Collection: Quarterly exchange Units: mR/ standard quarter, net exposure Date Placed:
09-28-86 Date Removed:
12-29-86 Days in the. Field:
92 Calculated Transit Dose:
(2.110.6) mR Location mR/Std. Qtr.
Azimuth Distance Station
(*)
(miles)
A B
Mean i s.d.
% s.d.
1 38 1.4 11.410.9 11.6i0.7 11.510.1
- 0. 9 2
21 1.1 15.910.8 15.310.7 15.6*0.4 2.6 3
4 1.1 13.910.8 13.3*0.7 13.6i0.4 2.9 4
340 0.6 17.111.0 16.610.8 16.810.4 2.4 5
321
- 0. 6 17.0i0.8 16.810.8 16.9f0.1
- 0. 6 6
296 0.6
.11.810.7 11.910.7 11.8i0.1 0.8 7
269 14.2 17.610.7 16.810.7 17.210.6 3.5 19 289 1.7 17.3i0.9 16.210.8 16.810.8 4.8 S-1 304 1.9 17.510.7 17.6i0.9 17.6i0.1 0.6 S-2 333 1.5 15.310.7 14.710.7 15.0i0.4
- 2. 7 S-3 6
2.2 17.810.8 17.7i0.7 17.8t0.1 0.6 S-4 25 6.3 12.6t0.7 13.210.9 12.910.4 3.1 S-5 33 6.1 13.6i0.7 13.210.8 13.4i0.3 2.2 S-6 357 4.1 17.510.7 17.6i0.9 17.6i0.1 0.6 S-7 338 4.4 17.611.0
- 17. 0f 0. 9 17.3i0.4 2.3 S-8 318 3.9 16.3i0.8 15.710.8 16.010.4 2.5 S-9 282 4.8 16.111.2 16.310.8 16.2i0.1 0.6 S-10 273 5.2 16.710.7 17.210.8 17.010.4 2.4 S-11 245 4.8 15.810.9 15.910.8 15.810.1 0.6 i-S-12 234 5.0 18.710.7 18.6i0.8 18.6i0.1 0.5 l
S-13 253 2.6 19.110.8 18.6fl.0 18.8i0.4 2.1
(,
S-14 237 2.7 15.810.7 15.2i0.7 15.5i0.4 2.6 Y
S-15 168 1.2 14.li0.7 14.2i0.6 14.210.1 0.7 S-16 193 1.1 16.910.7 17.210.7 17.0*0.2 1.2 S-17 222
- 1. 2 L0ST IN THE FIELD S-18 249 1.4 20.010.7 20.010.7 20.010.0 0.0 S-19 258 1.1 18.810.9 19.410.7 19.110.4 2.1 S-20 223 7.0 13.410.6 13.410.7 13.4i0.0 0.0 S-21 227 10.6 15.810.9 14.910.8 15.410.6 3.9 S-22 237 10.3 16.3f0.8 15.910.8 16.110.3 1.9 S-23 247 7.8 12.210.7 12.7*0.7 12.4i0.4 3.2 S-24 254 8.9 16.010.8 15.610.8 15.8i0.3 1.9 S-25 296 10.3 16.510.7 16.511.0 16.510.0 0.0 S-26 318 9.3 14.410.7 14.3i0.7 14.410.1 0.7 S-27 339 9.7 14.610.8 14.li0.7 14.4fD.4 2.8 S-28 360 7.0 14.911.0 14.9tl.0 14.9i0.0 0.0 S-29 360 9.2 15.610.7 16.110.7 15.810.4 2.5 S-30 23 9.9 16.4i0.7 16.010.6 16.210.3 1.8
{
l 7.0-8 I
l
FERMI-2 Table 1.
Gamma Radiation, as measured by TLDs (continued)
Collection: Quarterly exchange Units: mR/ standard quarter, net exposure Date Placed:
09-28-86 Date Removed:
12-29-86 Days in the Field:
92 Calculated Transit Dose:
(2.1 i 0.6) mR Location mR/Std. Qtr.
Azimuth Distance Station
(*)
(miles)
A B
Mean i s.d.
% s.d.
L-1 147 0.17 11.710.7 11.410.6 11.610.2 1.7 L-2 139 0.16 11.910.6 11.410.7 11.610.4 3.4 L-3 133 0.15 12.010.7 11.710.6 11.810.2 1.7 L-4 125 0.15 11.510.7 11.710.6 11.610.1 0.9 L-5 114 0.14 11.210.7 11.010.7 11.1*0.1 0.9 L-6 101 0.14 10.710.6 11.310.7 11.010.4 3.6 L-7 84 0.16
'11.711.0 10.9i0.7 11.310.6 5.3 L-8 71 0.2 12.210.6 12.210.6 12.210.0 0.0 i
t
?
7.0- 9
4 FERMI-2 Table 2 Gamma radiation, as measured by TLDs, grouped by sectors
/
Exposure: Quarterly, 1986.
1 l
Meteorological Average Exposure Rate (mR/Std. Qtr. i s.d.)
Sector 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Annual Mean TLDs in Group N
15.411.6 17.6i2.1 14.711.8 15.9*1.7 15.912.0 3, S-3, S-6, S-28, S-29 NNE 14.411.6 15.311.6 13.611.8 14.511.5 14.Sil.7 2, S-4, S-5, S-30 NE 11.6i0.4 11.9i0.3 9.310.0 11.Si0.1 11.lil.1 1
-a ENE 13.0t0.4 12.510.1 11.110.1 12.210.0 12.210.7 L-8 E
10.810.2 11.610.5 9.3i0.2 11.2i0.4 10.7tl.0 L-6, L-7 i
ESE 10.6i0.1 11.810.8 9.210.1 11.110.1 10.611.1 L-5 j
i SE 10.810.2 11.910.3 9.210.2 11.710.2 10.9tl.2 L-2, L-3, L-4 SSE 12.711.9 13.311.8 11.412.4 12.811.5 12.611.9 S-15, L-1 i
i SSW 16.010.0 18.210.3 15.810.1 17.0f0.2 16.811.0 S-16 J
SW 15.812.9 16.1*2.6 15.1*3.2 15.812.4 15.712.6 S-12, S-17, S-20, S-21 WSW 17.0il.5 18.012.9 15.8i2.4 16.712.4 16.912.4 S-11, 5-13, S-14, 5-18, S-19 S-22, S-23, S-24 W
16.210.3 18.510.4 16.0f0.4 17.1*0.4 17.011.1 7, S-10 j
WNW 15.412.7 15.813.4 13.Si3.1 15.3i2.2 15.li2.8 6, 19 S-9, S-25
)
NW 15.5i0.6 17.2il.6 15.510.9 16.2il.3 16.111.3 5, S-1, S-8, S-26 NNW 14.8tl.5 16.811.9 14.3tl.7 15.911.4 15.4tl.8 4, S-2, S-7, S-27 i
i 1
I
FERMI-2 Dhhut Sh&
Table 2.
Gamma radiation, as measured by TLDs, grouped by see4em (continued)
Distance (Miles) from the Average Exposure Rate (mR/Std. Qtr. i s.d.)
Reactor 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Annual Mean TLDs in Group 0-2 13.912.9 14.9t3.4 12.513.4 14.2i2.9 13.913.3 1, 2, 3, 4, 5, 6, 19, S-1, S-2, S-15, S-16, S-17, 5-18, S-19 L-1, L-2, L-3, L-4, L-5, L-6, L-7, L-8 u
?
2-5 16.411.6 18.311.6 16.211.5 17.111.2 17.0tl.7 S-3, S-6, S-7, S-8, 5-9, S-11, S-12, S-13, S-14
=
>5 14.911.4 15.7i2.0 13.611.7 14.7tl.5 14.711.8 S-4, S-5, S-10, S-20, S-23, S-25, S-26, 5-27, S-28, S-29, S-30 Upwind 16.210.5 17.lil.3 15.410.6 16.110.8 16.2il.0 7, S-21, S-22, S-24 Controls 1
FERMI-2 Table 3.
Airborne particulates and iodine collected at Location F-1, analyses for gross beta and iodine-131.a Collection:
Continuous, weekly exchange Units:
10-3 pC1/m3 Date Volume Gross Beta Date Volume Gross Beta Collected (m3)
(pCi/m3)
Collected (m3)
(pCi/m3) 01-05-86 247 22.9i5.7 07-06-86 266 17.614.8 01 4.2-86 248 22.815.6 07-13-86 254 14.314.9 01-19-86 248 17.415.3 07-20-86 244 17.7i5.2 01-20-86 245 18.715.4 07-27-86 260 20.3i4.8 02-02-86 247 18.315.3 08-03-86 259 19.515.0 02-09-86 245 14.714.8 08-10-86 251 21.315.1 02-16-86 246 29.215.3 08-17-86 250 30.514.0 02-23-86 249 25.415.6 08-24-86 265 23.8i5.4 03-02-86 246 25.815.5 09-01-86 281b 12.314.7 03-09-86 250 19.215.2 09-08-86 266 23.215.2 03-16-86 252 17.715.7 09-15-86 249 22.515.4 03-24-86 276b 16.615.1 09-21-86 206d 20.316.3 03-29-86 233c 13.315.0 09-28-86 251 11.315.0 1st Qtr. mean i s.d.
20.214.7 3rd Qtr. mean i s.d.
19.615.2 04-06-86 278b 17.7i5.3 10-05-86 246 14.215.1 04-14-86 292b 11.4i4.1 10-12-86 244 15.Si5.3 04-20-86 200d
<9.8 10-19-86 247 12.014.5 04-27-86 246 26.715.4 10-26-86 245 36.416.1 05-04-86 245 14.115.0 10-31-86 170c 20.416.7
-/~
05-11-86 256 45.li6.2e 11-09-86 318f 23.7*4.4 J
05-18-86 250 203.319.7e 11-16-86 237 26.lf5.6 T/
05-25-86 250 179.419.88 11-23-86 239 32.415.9 06-01-86 251 100.4i7.2e 11-30-86 242 26.515.8 06-07-86 215d 210.9110.7e 12-07-86 239 19.215.6 06-15-86 288b 22.214.6 12-14-86 237 28.6i5.9 06-22-86 261 26.5 0.5 12-21-86 241 36.616.1 06-29-86 247 17.910.5 12-29-86 275b 41.615.9 2nd Qtr. mean i s.d.
73.0179.2 4th Qtr. mean i s.d.
25.619.3 a Iodine-131 concentrations are <0.07 pCi/m3 unless noted otherwise in Appendix D.
b Pump ran eight days.
c Fump ran five days.
d Pump ran six days.
- Elevated gross beta activity is due to fallout from the Chernobyl Nuclear Plant (USSR) accident on April 26, 1986.
f Pump ran nine days.
7.0-12
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FERMI-2 Table 4.
Airborne particulates and iodine collected at Location F-4. analyses for gross beta and iodine-131.a Collection:
Continuous, weekly exchange Units:
10-3 pCi/m3 Date Volume Gross 8 eta Date Volume Gross 8 eta Collected (m3)
(pCi/m3)
Collected (m3)
(pCi/m3) 01-05-86 250 21.3*5.6 07-06-86 244 15.015.1 01-12-86 248 20.215.5 07-13-86 251 19.2*5.1 01 '.9-86 251 20.415.3 07-20-86 238 16.9i5.3 01-26-86 247 17.115.3 07-27-86 269 22.414.8 02-02-86 249 20.9i5.4 08-03-86 263 14.714.8 02-09-86 246 19.114.9 08-10-86 249 24.715.2 02-16-86 245 28.815.3 08-17-86 248 37.314.2 02-23-86 249 27.5t5.7 08-24-86 263 22.115.3 03-02-86 246 24.415'.4 09-01-86 277b 13.614.8 03-09-86 251 21.015.3 09-08-86 253 21.615.3 03-16-86 255 11.9*5.4 09-15-86 256 23.015.3 03-24-86 284b 18.715.0 09-21-86 205d 19.416.3 03-29-86 170c 18.716.9 09-28-86 252 15.3*5.1 1st Qtr. mean i s.d.
20.814.4 3rd Qtr. mean i s.d.
20.4i6.2 i
04-06-86 288b 16.115.1 10-05-86 250 8.614.8 04-14-86 305b 9.7i3.9 10-12-86 248 19.7i5.4 04-20-86 200d 10.9i5.7 10-19-86 250 11.0i4.4 04-27-86 251 27.2i5.3 10-26-86 251 34.015.9 05-04-86 252 14.514.9 10-31-86 173c 23.116.7
- /
05-11-86 260 40.8i5.9e 11-09-86 321f 25.114.4 05-18-86 256 211.9i9.7e 11-16-86 241 24.815.5 k/
05-25-86 255 165.6i9.38 11-23-86 241 24.6*5.6 06-01-86 258 92.016.88 11-30-86 245 23.715.7 06-07-86 221d 306.0112.38 12-07-86 246 18.0i5.4 06-15-86 291b 24.814.6 12-14-86 244 26.4i5.7 06-22-86 261 23.915.0 12-21-86 247 33.7*5.9 06-29-86 247 16.415.0 12-29-86 280b 47.916.0 2nd Qtr. mean i s.d.
73.8194.9 4th Qtr. mean i s.d.
24.7110.1
- Iodine-131 concentrations are <0.07 pCi/m3 unless noted otherwise in Appendix D.
b Pump ran eight days.
c Pump ran five days.
d Pump ran six days.
e Elevated gross beta activity is due to fallout from the Chernobyl Nuclear Plant (USSR) accident on April 26, 1986.
f Pump ran nine days.
7.0-14
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FERMI-2 Table 5.
Airborne particulates and iodine collected at Location F-5, analyses for gross beta and iodine-131.a Collection:
Continuous, weekly exchar.ge Units:
10-3 pCi/m3 Date Volume Gross Beta Date Volume Gross Beta Collected (m3)
(pC1/m3)
Collected (m3)
(pC1/m3) 01-05-86 251 23.315.7 07-06-86 264 14.314.8 01-12-86 241 24.315.8 07-13-86 251 19.515.1 01-19-86 244 24.815.6 07-20-86 224 12.915.5 01-26-86 241 20.515.6 07-27-86 250 17.914.9 02-02-86 242 21.615.5 08-03-86 255 13.014.8 02-09-86 239 17.715.0 08-10-86 247 33.7*5.6 02-16-86 240 28.415.4 08-17-86 239 32.114.2 02-23-86 240 17.015.4 08-24-86 246 22.1*5.6 03-02-86 241 22.415.4 09-01-86 227b 10.2i5.6 03-09-86 246 19.315.3 09-08-86 1339
<13.8h 03-16-86 250 12.915.6 09-15-86 251
<7.3 03-24-86 279b 13.414.9 09-21-86 220d 20.316.0 03-29-86 166c 17.017.0 09-28-86 273 15.3i4.7 1st Qtr. mean i s.d.
20.214.6 3rd Qtr. mean i s.d.
19.217.7 04-06-86 282b 14.4f5.1 10-05-86 270 12.214.6 04-14-86 293b 6.213.9 10-12-86 266 15.014.9 04-20-86 201d
<9.8 10-19-86 271 12.214.1 04-27-86 247 26.515.3 10-26-86 272 44.3i5.8 05-04-86 248 12.3i4.9 10-31-86 181c 21.8i6.4 05-11-86 254 41.5i6.le 11-09-86 348i 22.214.0 05-18-86 251 194.7i9.58 11-16-86 262 24.915.1
[
05-25-86 251 164.419.4e 11-23-86 261 26.915.3 1'
06-01-86 251 99.6*7.18 11-30-86 267 24.2i5.3
\\
06-07-86 215d 206.9110.78 12-07-86 263 19.615.1 06-15-86 119f 49.2111.0e 12-14-86 260 37.0i5.8 06-22-86 223 28.115.9 12-21-86 264 41.115.8 06-29-86 245 17.415.3 12-29-86 299b 39.215.4 2nd Qtr. mean i s.d.
71.8175.2 4th Qtr. mean i s.d.
26.2110.9 a Iodine-131 concentrations are <0.07 pC1/m3 unless noted otherwise in Appendix D.
b l Pump ran eight days.
Pump ran five days.
- Pump ran six days.
Elevated gross beta activity is due to f allout from the Chernobyl Nuclear Plant (USSR) accident on April 26, 1986.
f Low volume due to pump malfunction; pump ran only 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
9 Low volume due to pump malfunction; valves replaced.
Elevated gross beta LLD due to low volume.
1 Pump ran nine days.
7.0-16
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l FERMI-2 Table 6.
Airborne particulates and iodine collected at Location F-7, analyses for gross beta and iodine-131.a Collection:
Continuous, weekly exchange Units:
10-3 pCi/m3 l
Date Volume Gross Beta Date Volume Gross Beta Collected (m3)
(pCi/m3)
Collected (m3)
(pC1/m3) 01-05-86 231 22.416.0 07-06-86 272 13.914.6 01-12-86 235 22.315.8 07-13-86 267 22.3i5.0 01-19-86 238 21.015.6 07-20-86 250 16.815.1 01-26-86 239 19.415.5 07-27-86 287 19.714.4 02-02-86 241 24.315.7 08-03-86 249 18.715.1 02-09-86 245 12.014.7 08-10-86 269 31.815.1 02-16-86 254 28.615.2 08-16-86 245d 26.9i4.0 02-23-86 256 21.815.3 08-24-86 30lb 26.914.9 03-02-86 261 23.815.2 09-01-86 259d 12.415.0 03-09-86 248 20.415.3 09-08-86 343 21.114.1 03-16-86 268 9.215.1 09-15-86 212 28.li6.4 03-24-86 300b 17.614.7 09-21-86 225d 16.515.7 03-29-86 180c 17.116.5 09-28-86 271 9.li4.5 l
1st Qtr. mean i s.d.
20.0f5.1 3rd Qtr. mean i s.d.
20.316.7 04-06-86 297b 13.214.9 10-05-86 255 12.814.9 04-14-86 310b 10.913.9 10-12-86 258 16.615.1 04-20-86 217d 11.615.3 10-19-86 268 11.614.2 04-27-86 260 22.915.0 10-26-86 254 32.915.8 05-04-86 257 16.914.9 10-31-86 183c 23.916.4 05-10-86 226d 16.515.7 11-09-86 334f 21.9i4.2 i
05-18-86 245b 252.3110.78 11-16-86 257 24.6i5.2
(/
05-24-86 245d 198.2i10.3e 11-23-86 254 27.115.4 06-01-86 283b 86.916.3e 11-30-86 248 30.515.9 06-07-86 227d 183.619.8e 12-07-86 250 19.315.4 06-15-86 283b 24.914. 8 12-14-86 242 31.515.9 06-21-86 266d 20.814.9 12-21-86 264 36.415.7 06-29-86 294b 20.514.6 12-29-86 274b 42.815.9 2nd Qtr. mean i s.d.
67.6185.5 4th Qtr. mean i s.d.
25.5i9.2 a Iodine-131 concentrations are <0.07 pCi/m3 unless noted otherwise in Appendix D.
b Pump ran eight days.
c Pump ran five days.
Pump ran six days.
- Elevated gross beta activity is due to fallout from the Chernobyl Nuclear Plant (USSR) accident on April 26, 1986.
f Pump ran nine days.
7.0-18
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FERMI-2 Table 7.
Airborne particulates and iodine collected at Location F-17, analyses for gross beta and iodine-131.a Collection:
Continuous, weekly exchange Units:
10-3 pCi/m3 Date Volume Gross Beta Date Volume Gross Beta Collected (m3)
(pC1/m3)
Collected (m3)
(pCi/m3) 01-05-86 251 19.315.5 07-06-86 274 11.814.5 01-12-86 247 20.515.5 07-13-86 258 18.215.0 01-19-86 251 20.815.3 07-20-86 244 14.215.1 01-26-86 248 15.3*5.2 07-27-86 275 31.6i5.0 02-02-86 248 18.815.3 08-03-86 252 16.015.0
^
02-09-86 247 18.6i4.9 08-10-86 255 -
27.8i5.2 02-16-86 246 32.715.4 08-17-86 252 25.213.8 02-23-86 191 18.4i6.7 08-24-86 272 20.715.1 03-02-86 43b
<41.2c 09-01-86 285d 15.014.7 03-09-86 113 21.6i10.7 09-08-86 268 24.4i5.2 03-16-86 116
<10.0 09-15-86 255 24.215.4 03-24-86 217d 9.3*3.5 09-21-86 208f 18.0i6.2 03-29-86 275e 6.514.1 09-28-86 256 13.214.9 4
1st Qtr. mean i s.d.
18.416.8 3rd Qtr. mean i s.d.
20.0i6.2 i
04-06-86 287d 13.115.0 10-05-86 257 15.114.9 04-14-86 296d 7.5*3.9 10-12-86 253 13.515.1 04-20-86 204f 15.515.8 10-19-86 253 11.314.3 04-27-86 248 19.615.1 10-26-86 254 41.3i6.0 05-04-86 250 12.8i4.9 10-31-86 1778 16.6i6.3 05-11-86 259 47.8*6.29 11-09-86 326h 24.914.4 05-18-36 254 210.619.79 11-16-86 244 25.4i5.5 05-25-86 254 184.619.89 11-23-66 246 26.8i5.6 06-01-86 257 86.3*6.79 11-30-86 248 24.815.7 k'/
06-07-86 223f 202.0i10.39 12-07-86 248 18.8i5.4 06-15-86 291d 21.li4.5 12-14-86 123b 27.7110.3 06-22-86 255 26.315.2 12-21-86 239 39.716.2 l
06-29-86 248 19.7i5.3 12-29-86 280d B.415.9 2nd Qtr. mean i s.d.
66.7i78.4 4th Qtr. mean i s.d.
25.4110.8
- Iodine-131 concentrations are <0.07 pC1/m3 unless noted otherwise in Appendix D.
b Low volume due to pump malfunction; pump was repaired.
Elevated gross beta LLD and an iodine-131 LLD of <0.12 pCi/m3 due to c
I'" V I"***
d Pump ran eight days.
e Pump ran five days.
f I
Pump ran six days.
l 9 Elevated gross beta activity is due to fallout from the Chernobyl Nuclear j
Plant (USSR) accident on April 26, 1986.
h Pump ran nine days.
7.0-20
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FERMI-2 Table 8.
Airborne particulates, analyses for gross beta, monthly averages a
of weekly collections. 1986.
Units:
10-3 pCi/m3 Collection Location Period F-1 F-4 F-5 F-7 F-17 January 23.0 20.0 22.7 21.9 18.9 February 23.8 25.0 21.4 21.6 23.2 March 15.7 17.6 15.6 16.1 14.0 April 13.6 16.0 15.7 14.6 13.9 May 103.5 105.0 102.5 114.2 108.4 June 69.4 92.8 75.4 62.4 67.3 July 17.9 17.6 15.5 18.3 18.4 August 22.0 24.4 24.5 24.5 22.2 September 19.3 19.8 17.8 18.7 20.0 October 19.7 19.3 21.1 19.6 19.6 November 27.2 24.6 24.6 26.0 25.5 December 31.5 31.5 34.2 32.5 32.6 3
kr Annual mean 32.9 34.5 32.6 32.5 32.0 a Unless specified otherwise, data from samples collected on the first, second, or third day of a month are grouped with data from the previous month.
7.0-22
FERMI-2 Table 9.
Airborne particulates, analyses for gamma-emitting isotopes Collection:
Quarterly composites (by location) of weekly collections Units:
10-3 pCi/m3 Lab Volume Other Location Code (m3)
Be-7 Cs-134 Cs-137 Gammasa i
1st Qtr., 1985 F-1 FAP-89 3232
<13.1
<1.4
<1.4
<1.8 F-4 90 3190 59.4110.1
<1.2
<1.2
<1.9 F-5 91 3120
<10.8
<1.3
<1.2
<l.8 F-7 92 3196 74.0*11.0
<1.2
<1.1
<2.0 i
F-17 93 2693
<13.4
<1.4
<1.5
<2.3 2nd Qtr., 1985 F-1 FAP-238 3279 73.6i21.0 4.411.9b 11.3tl.8b 8.1*3.0b F-4 239 3346 103.9122.7 8.9tl.3b 17.911.5b 11.713.2b F-5 240 3080 63.6i20.1 6.611.5b 12.3*1.9b
<4.3 F-7 241 3410 98.7f18.0 7.7tl.5b 12.3tl.5b 14.613.0b F-17 242 3326 44.Si26.8 5.lil.8b 14.6*3.3b
<8.3 3rd Qtr., 1985 F-1 FAP-345 3302 129.li23.4
<1.7
<l.1
<3.5 F-4 34 6 3268 59.lil7.6
<1.2
<1.8
<3.9 F-5 347 3080 42.9116.2
<1.2
<1.3
<4.0
- /^
F-7 348 3450 87.0i14.5
<1.5
<1.7
<1.9 F-17 349 3354 84.0*12.2
<1.3
<1.1
<1.5
\\ t 4th Qtr., 1985 F-1 FAP-445 3180 109.5i14.1
<2.0
<2.4
<2.6 F-4 446 3237
<10.2
<1.0
<1.0
<1.9 F-5 447 3484 55.9t11.1
<1.3
<1.6
<2.2 4
F-7 448 3341 46.8til.9
<1.4
<1.6
<1.8 l
F-17 449 3148 67.6i8.8
<1.1
<1.2
<1.6
- See Introduction.
I b Elevated activity is due to fallout from the Chernobyl Nuclear Plant (USSR) accident on April 26, 1986.
Positive value listed under "Other Gammas" is for Ru-103.
t 7.0-23 l
FERMI-2 Table 10.
Surf ace water, analyses for gama-emitting isotopes Collection: Monthly Units: pCi/1 Location Sample Description and Concentration Indicator F-12 Date Collected 01-26-86 02-23-86 03-29-86 04-27-86 Lab Code FSW-5236 FSW-5555 FSW-6113 FSW-6387 Mn-54
<5.6
<3.5
<6.7
<7.7 Fe-59
<13.9
<9.5
<18.8
<19.8 Co-58
<5.7
<3.8
<7.7
<7.8 Co-60
<7.3
<4.5
<8.1
<8.5 Zn-65
<14.9
<6.6
<14.4
<17.1 Zr-Nb-95
<5.4
<3.0
<7.0
<7.7 Cs-134
<6.2
<3.9
<7.1
<8.8 l
<5.4
<4.0
<7.1
<8.3 Ba-La-140
<7.9
<4.8
<11.4
<11.1 Date Collected 05-25-86 06-28-86 07-26-86 08-31-86 Lab Code FSW-6708 FSW-7183 FSW-7595 FSW-7912 Mn-54
<2.8
<5.5
<5.1
<6.8 Fe-59
<8.4
<18.4
<11.9
<16.0 Co-58
<3.6
<9.1
<5.4
<7.3 Co-60
<2.1
<5.1
<6.1
<6.7 Zn-65
<5.7
<14.7
<11.5
<16.9 Zr-Nb-95
<5.4
<5.5
<5.8
<9.3
/
Cs-134
<2.6
<4.9
<4.3
<7.2 Cs-137
<2.7
<5.9
<4.5
<8.4 k/
Ba-La-140
<21.3a
<10.7
<12.6
<9.2 Date C "ected 09-27-86 10-26-86 11-30-86 12-29-86 Lab Code FSW-8373 FSW-8711 FSW-9091 FSW-9385 Mn-54
<8.5
<8.9
<4.7
<3.8 Fe-59
<16.3
<16.5
<8.5
<10.7 Co-58
<8.5
<9.0
<4.2
<2.8 Co-60
<6.5
<7.2
<4.8
<4.9 Zn-65
<14.2
<16.2
<6.6
<9.3 Zr-Nb-95
<8.9
<7.2
<3.9
<4.3 Cs-134
<8.4
<8.0
<4.3
<3.9 Cs-137
<8.5
<9.2
<4.2
<5.4 Ba-La-140
<10.9
<11.0
<7.0
<8.0
" LLD could not be reached due to delay in counting; sample counted for 19.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
7.0-24
. - = _.
FERMI-2 Table 10.
Surface water, analyses for gamma-emitting isotopes (continued)
Location Sample Description and Concentration Control F-14 Date Collected 01-26-86 02-23-86 03-29-86 04-27-86 Lab Code FSW-5237 FSW-5556,7 FSW-6114,5 FSW-6388 I
t Mn-54
<5.5
<2.4
<5.2
<2.4 Fe-59
<13.9
<6.0
<18.6
<5.1 I
Co-58
<6.4
<2.5
<6.1
<2.4 L
<6.4
<2.8
<7.7
<2.4 Zn-65
<16.6
<5.2
<14.2
<5.1 Zr-Nb-95
<6.9
<2.6
<7.5
<2.5 Cs-134
<7.7
<2.6
<7.4
<2.5 Cs-137
<7.7
<2.6
<8.3
<2.6 Ba-La-140
<7.6
<3.0
<9.2
<2.9 Date Collected 05-25-86 06-28-86 07-26-86 08-31-86 Lab Code FSW-6709 FSW-7184 FSW-7596 FSW-7913 Mn-54
<1.3
<1.1
<5.8
<6.3 Fe-59
<6.2
<4.2
<14.2
<13.4 Co-58
<1.8
<1.3
<7.0
<6.2 Co-60
<1.5
<1.0
<5.0
<5.8 i
Zn-65
<3.3
<2.6
<11.7
<11.3 Zr-Nb-95
<2.3
<1.4
<7.5
<7.1
/~
Cs-134
<1.6
<1.2
<6.0
<6.0
[
<1.5
<1.2
<6.6
<5.7 y
Ba-La-140
<13.7
<6.0
<14.7
<10.3 Date Collected 09-27-86 10-26-86 11-30-86 12-29-86 Lab Code FSW-8374,5 FSW-8712 FSW-9092 FSW-9386 Mn-54
<5.5
<8.0
<3.5
<5.7 Fe-59
<11.4
<17.1
<11.9
<11.0 Co-58
<6.6
<8.4
<4.0
<5.2 Co-60
<7.0
<6.5
<6.2
<5.5 Zn-65
<12.4
<15.4
<8.1
<10.9 Zr-Nb-95
<6.8
<8.1
<4.3
<5.6 Cs-134
<4.9
<7.3
<4.5
<5.3 Cs-137
<5.7
<8.3
<6.3
<5.4 Ba-La-140
<11.2
<9.5
<9.0
<6.9 7.0-25
FERMI-2 Table 11.
Drinking water, analysis for gross beta and gansna-emitting isotopes Collection: Monthly Units: pCi/1 Location Sample Description and Concentration Indicator F-13 Date Collected 01-26-86 02-23-86 03-29-86 04-27-86 Lab Code FPW-5238 FPW-5558 FPW-6116 FPW-6389 Gross beta 2.310.4 2.910.7 3.210.6 2.210.5 Mn-54
<6.5
'<4.6
<6.0
<6.0 Fe-59
<14.4
<8.0
<11.1
<8.8 Co-58
<5.7
<4.2
<5.5
<7.1 Co-60
<6.4
<4.7
<6.6
<6.2 Zn-65
<14.0
<10.0
<11.8
<11.9 Zr-Nb-95
<6.4
<3.6
<5.8
<6.6 Cs-134
<5.6
<3.8
<6.8
<7.7 Cs-137
<6. 8
<4.2
<6.4
<6.1 Ba-La-140
<10.4
<5.8
<9.0
<13.1 Date Collected 05-25-86 06-28-86 07-26-86 08-31-86 Lab Code FPW-6710 FPW-7185 FPW-7597 FPW-7914,5 Gross beta 2.610.6 2.510.6 2.110.5 2.0i0.3
- i Mn-54
<2.3
<2.8
<6.2
<4.8 ds/
Fe-59
<8.3
<7.6
<13.6
<13.6 Co-58
<2.6
<3.3
<6.7
<4.7 Co-60
<2.2
<2.5
<5.3
<6.2 Zn-65
<4.0
<5.8
<11.3
<9.2 Zr-Nb-95
<2.5
<4.4
<7.6
<4.6 Cs-134
<2.1
<2.8
<6.4
<4.9 Cs-137
<2.0
<3.0
<6.3
<4.7 Ba-La-140
<15.0
<11.3
<12.9
<9.2 7.0-26
FERMI-2 Table 11.
Drinking water, analysis for gross beta and gamma-emitting isotopes (continued) l Location Sample Description and Concentration Indicator (continued)
F-13 Date Collected 09-27-86 10-26-86 11-30-86 12-29-86 Lab Code FPW-8376 FPW-8713 FPW-9093 FPW-9387,8 Gross beta 1.8 0.6 2.710.4 2.4t0.5 2.610.5 Mn-54
<6.0
<5.6
<6.8
<5.7 Fe-59
<18.0
<12.8
<15.9
<14.9 Co-58
<7.7
<5.2
<6.0
<5.5 Co-60
<7.2
<6.5
<8.5
<5.9 Zn-65
<15.3
<12.8
<13.0
<13.7 Zr-Nb-95
<6.4
<6.2
<7.4
<5.8 Cs-134
<5.6
<5.7
<5.8
<4.8 Cs-137
<7.0
<6.0
<6.9
<5.5 Ba-La-140
<8.8
<11.5
<9.0
<3.5 Control F-15 Date Collected 01-26-86 02-23-86 03-29-86 04-27-86 Lab Code FPW-5239 FPW-5559 FPW-6117 FPW-6390 Gross beta 2.210.4 2.610.6 2.210.6 2.210.5 k/
<6.0
<5.2
<4.2
<1.9 Fe-59
<10.0
<10.4
<10.3
<5.0 Co-58
<7.1
<5.3
<4.4
<2.2 Co-60
<5.4
<4.4
<4.2
<2.2 Zn-65
<14.2
<11.0
<9.0
<4.2 Zr-Nb-95
<7.1
<5.5
<4.5
<2.2 Cs-134
<6.8
<5.5
<3.3
<2.3 Cs-137
<6.9
<6.0
<4./
<2.4 Ba-La-140
<7.4
<6.6
<9.4
<2.6 7.0-27
FERMI-2 Table 11.
Drinking water, analysis for gross beta and gamma-emitting isotopes (continued)
Location Sample Description and Concentration Control (continued)
F-15 Date Collected 05-25-86 06-28-86 07-26-86 08-31-86 Lab Code FPW-6711 FPW-7186 FPW-7598 FPW-7916 Gross beta 1.6!0.5 1.810.5 2.510.6 1.810.4 Mn-54
<6.9
<7.4
<5.1
<8.4 Fe-59
<15.4
<14.1
<19.9
<18.7 Co-58
<7.0
<6.1
<7.0
<8.0 Co-60
<6.9
<7.5
<5.7
<6.4 Zn-65
<14.0
<12.9
<9.8
<17.7 Zr-Nb-95
<7.1
<6.7
<4.4
<9.5 Cs-134
<7.4
<6.7
<4.4
<7.3 Cs-137
<6.5
<7.3
<5.6
<8.5 Ba-La-140
<15.3a
<7.3
<13.4
<13.1 Date Collected 09-27-86 10-26-86 11-30-86 12-29-86 Lab Code FPW-8377 FPW-8714 FPW-9094 FPW-9389 Gross beta 1.810.5 1.910.5 2.110.5 2.310.6
/'
<8.0
<9.9
<6.9
<2.8 Fe-59
<20.4
<16.4
<12.1
<14.4 (f
Co-58
<8.9
<9.4
<5.4
<4.8 Co-60
<7.4
<7.9
<6.9
<5.1 Zn-65
<18.1
<18.4
<13.5
<7.5 Zr-Nb-95
<8.4
<9.8
<7.5
<3.2 Cs-134
<9.2
<7.8
<5.7
<4.7 Cs-13/
<9.7
<8.6
<6.1
<4.4 Ba-La-140
<11.8
<12.5
<12.2
<3.6 a LLD could not be reached due to delay in counting.
t 7.0-28 1
FERMI-2 l
Table 12.
Surface and drinking water, analysis for tritium Collection: Quarterly composites (by location) of monthly collections Units: pC1/1 Compcsiting Location Period Lab Code H-3 Indicator F-12, Surface 1st Qtr., 86 FSW-5979
<310 2nd Qtr., 86 7061
<310 3rd Qtr., 86 8052
<310 4th Qtr., 86 9511
<310 F-13, Drinking 1st Qtr., 86 FPW-5982
<310 2nd Qtr., 86 7063
<310 3rd Qtr., 86 8054
<310 4th Qtr., 86 9512
<310 Control F-14, Surface 1st Qtr., 86 FSW-5980,1
<310 2nd Qtr., 86 7062
<310 3rd Qtr., 86 8053
<310 4th Qtr., 86 9513
<310 j
F-15, Drinking 1st Qtr., 86 FPW-5983
<310
(/
2nd Qtr., 86 7064
<310 3rd Qtr., 86 8055
<310 4th Qtr., 86 9514
<310 7.0-29
FERMI-2 Table 13.
Shoreline sediments, analysis for gama-emitting isotopes Collection:
Semi-annually Units: pCi/kg dry weight Sample Description and Concentration Location F-8 F-9 Date Collected 05-15-86 10-23-86 05-15-86 10-23-86 Lab Code FBS-46 F8S-148 FBS-47 F8S-149 K-40 10420t160 102501419 10490t162 119901426 Mn-54
<15
<40
<16
<39 N
Co-58
<35
<67
<33
<49
?
<11
<44
<13
<51 Zn-65
<35
<109
<41
<94 Zr-Nb-95
<41
<79
<45
<72 Cs-134
<16
<38
<15
<29 Cs-137
<13
<40
<12
<33 Location F-10 F-22 Date Collected 05-15-86 10-23-86 04-24-86 09-23-86 Lab Code FBS-48 FBS-150 FBS-49,50 FBS-135 K-40 111181112 99101605 171251514 153101450 Mn-54
<8
<23
<42
<45 Co-58
<17
<41
<52
<48 Co-60
<6
<25
<48
<42 Zn-65
<22
<73
<112
<95 Zr-Nb-95
<19
<81
<49
<50 Cs-134
<8
<28
<56
<56 Cs-137 14 3
<22 392133 588133 4
FERMI-2 Table 14. Milk collected at Locations F-7, F-19, F-20, F-31, and F-32, analyses for iodine-131 and gamma-emitting isotopes.
Collection:
Semimonthly: June 15 - October 15 Monthly:
October 15 - June 15 Units: pC1/1 Collection Lab Concentration Date Code I-131 Cs-134 Cs-137 Ba-La-140 K-40 Location F-7 01-12-86 FMI-1941
<0.2
<9.2
<9.9
<9.4 1290i240 02-09-86 2002
<0.5
<7.9
<8.3
<8.8 12601140 03-24-86 2103
<0.2
<2.8
<2.6
<2.8 1380130 04-14-86 2167
<0.2
<3.2
<3.0
<2.6 1340i30 05-11-86 2253,4 0.6i0.2a
<3.2
<3.3
<4.2 1390180 05-25-86 2353 1.010.4a
<2.1
<2.3
<3.2 12901120 06-14-86 2516,7 1.Si0.2a
<5.8
<6.2
<6.7 1340180 06-22-86 2548 1.510.4a
<5.9
<7.1
<6.9 1350170 07-09-86 2681
<0.4
<4.0
<4.3
<5.0 13601100 07-20-86 2731
<0.7
<3.8
<4.1
<5.6 13401100 08-03-86 2806
<0.6
<6.4
<7.3
<6.8 12501110 08-17-86 2891
<0.3
<10.1
<10.1
<9.6 1380t150 09-15-86 3076
<0.4
<4.0
<4.4
<4.6 13901110 09-21-86 3104
<0.5
<4.4
<4.4
<5.0 14001120 10-12-86 3240
<0.3
<6.6
<8.2
<6.4 1250*80 11-09-86 3384,5
<0.7
<8.9
<8.6
<8.1 14301120 12-14-86 3471
<0.3
<6.2
<7.2
<6.9 1320*90 Location F-19b
\\'
01-12-86 NSc 02-09-86 NSc 03-24-86 NSc
" Elevated I-131 activity is due to fallout from the Chernobyl Nuclear Plant b (USSR) accident on April 26, 1986.
Effective April 1986, grass will be collected in lieu of milk at F-19.
c NS = No sample; milk from Location F-19 temporarily unavailable.
1 7.0-31
FERMI-2 Table 14. Milk collected at Locations F-7, F-19, F-20, F-31, and F-32, analyses for iodine-131 and gansna-emitting isotopes (continued)
Collection Lab Concentration Date Code I-131 Cs-134 Cs-137 Ba-La-140 K-40 Location F-20 01-12-86 FMI-1942
<0.2
<5.3
<5.6
<5.9 1460i60 02-09-86 2003
<0.4
<6.6
<6.9
<9.1 14301160 03-09-86 2083
<0.2
<2.5
<2.8
<3.1 1350160 04-14-86 2168
<0.2
<5.6
<5.4
<5.5 1320i50 05-11-86 2255 0.710.2a
<9.8
<7.6
<9.8 1290180 05-25-86 2354 1.410.3a
<2.8
<2.9
<2.6 1190i120 06-07-86 2468 1.410.4a
<3.7
<3.6
<5.3 1240160 06-22-86 2549,50 1.810.3'
<4.6
<4.9
<5.1 1130i60 07-09-86 2682
<0.5
<8.5
<9.7
<12.5 1320i140 07-20-86 2732
<0.5
<4.6
<4.5
<6.2 14001110 08-03-86 2807
<0.6
<5.5
<5.0
<4.2 1220160 08-17-86 2892
<0.3
<7.8
<7.2
<5.9 1430190 09-07-86 3046
<0.4
<7.8
<8.6
<6.1 1280i190 09-21-06 3105
<0.3
<7.1
<7.1
<7.1 1280i130 10-12-86 3241
<0.3
<9.3
<10.9
<7.9 1190i140 11-09-86 3386
<0.7
<6.1
<6.0
<7.4 1210i140 12-14-86 3472
<0.2
<6.0
<5.8
<6.8 1420i140 Location F-31 01-12-86 FMI-1943
<0.1
<7.6
<8.7
<7.7 1170i220 02-09-86 2004
<0.5
<10.3
<9.6
<9.9 1470180 03-09-86 2084
<0.2
<2.7
<3.0
<3.0 1320i60 3,
04-14-86 2169
<0.2
<4.6
<5.3
<4.8 1340190 W
05-11-86 2256
<0.4
<7.2
<8.5
<10.7 1580il50 05-25-86 2355 4.010.5a
<5.2 7.3i2.0a
<5.9 1350i50 06-07-86 2469 2.010.4a
<8.4
<8.3
<9.5 1410*140 06-22-86 2551
<0.7
<7.7
<6.9
<6.5 1570i80 07-09-86 2683
<0.4
<5.4
<5.5
<5.3 1450i80 07-20-86 2733
<0.3
<7.8
<9.3
<9.0 14001140 i
08-03-86 2808
<0.5
<4.8
<5.0
<6.0 13901120 08-17-86 2893
<0.5
<5.2
<5.2
<6.1 1330t120 09-07-86 3047
<0.3
<4.0
<4.6
<5.8 13201110 09-21-86 3106
<0.4
<9.5
<9.5
<8.8 1460i160 10-12-86 3242,3
<0.4
<5.3
<4.9
<4.1 1300180 11-09-86 3387
<0.6 (4.5
<4.5
<4.9 1450t110 12-14-86 3473
<0.3
<6.2
<6.1
<7.2 13601140 a Elevated I-131 and Cs-137 activity is due to fallout from the Chernobyl i
Nuclear Plant (USSR) accident on April 26, 1986.
7.0-32
FERMI-2 Table 14. Milk collected at Locations F-7, F-19, F-20, F-31, and F-32, analyses for iodine-131 and gamma-emitting isotopes (continued)
Collection Lab Concentration Date Code I-131 Cs-134 Cs-137 Ba-La-140 K-40 Location F-32 01-12-86 FMI-1944
<0.1
<6.8
<6.4
<9.6 11101140 02-09-86 2005
<0.7a
<7.0
<7.4
<8.8 1160i130 03-09-86 2085
<0.2
<4.1
<3.6
<4.0 1600t40 l
04-14-86 2170
<0.2
<2.8
<3.0
<4.1 1130140 05-11-86 2257 0.810.34
<8.3
<7.2
<8.1 1240t70 05-25-86 2356 37.516.2D
<7.9
<8.5
<7.9 1290160 06-07-86 2470,1 8.4i0.4b
<5.2 6.0i3.8b
<9.1 1180180 06-22-86 2552 1.410.4b
<4.4
<4.8
<3.2 1220170 07-09-86 2684
<0,3
<8.5
<9.4
<9.8 1220t140 07-20-86 2734
<0.5
<7.7
<9.3
<9.0 1140i130 1
08-03-86 2809
<0.3
<3.9
<3.8
<4.4 1190180 08-17-86 2894,5
<0.4
<5.3
<5.3
<3.1 1280170 09-07-86 3048
<0.4
<4.8
<5.4
<4.4 1030t70 09-21-86 3107
<1.0
<5.1
<5.8
<9.2 11901130 10-12-86 3244
<0.5
<4.4
<5.4
<5.5 1120160 11-09-86 3388
<0.6
<5.6
<5.2
<4.0 1120*60 12-14-86 3474
<0.3
<6.5
<5.1
<3.4 1210t70 a Part of sample ' lost in analysis.
Elevated I-131 and Cs-137 activity is due to f allout from the Chernobyl Nuclear Plant (USSR) accident on April 26, 1986.
i\\'
l 7.0-33
FERMI-2 Table 15.
Grass collected in lieu of milk at Locations F-18 and F-19, analyses for iodine-131 and gamma-emitting isotopes.
Collection:
Semi-monthly:
June 15 - October 15 j
Monthly: October 15 - June 15 Units: pCi/kg wet 1
Collection Lab Concentration Date Code I-131 Cs-134 Cs-137 Ba-La-140 K-40 i
Location F-18 01-13-86 NDa 02-09-86 NDa 03-09-86 NDa 04-14-86 FG-693,4
<47
<27
<28
<33 2,680il70 05-11-86 704,5 46114b
<7
<8
<11 6,160i280 05-25-86 711 463164b
<16 145i37b
<21 10,200t940 06-07-86 726,7c
<36 58i3b 9613
<15 4.260i130 06-22-86 737.8
<37
<21
<25
<23 5,250*320 07-09-86 766
<28
<19
<21
<17 8,240i290 07-20-86 777
<36
<32
<32
<39 6.8201670 08-03-86 792
<22
<17
<18
<17 8,5901540 08-17-86 799
<11
<8
<8
<10 5,040i280 09-21-86 814
<12
<10 2415
<8 5,0201120 09-27-%
816,7
<13
<7 1315
<7 4,2401220 10-12-86 849
<23
<20
<18
<19 4,7801410 11-09-86 860
<29
<26
<26
<42 4,7101530 12-14-86 865,6
<24
<16
<20
<21 3,920i210 Location F-19 04-14-86 FG-695
<52
<30
<29
<32 3,5301160 05-11-86 706 87118D
<16
<15
<20 5,550i410
/
05-25-86 712 164tS6b
<17 93132b
<19 9,0501830 06-07-86 728d
<44 3413b 6113b
<10 4,470170
(.-
06-22-86 739
<60
<45
<45
<24 6,0491400 07-09-86 767
<47
<28
<30
<40 7,890t740 07-20-86 778
<25
<25
<30
<17 6,8101330 08-03-86 793,4
<19
<14
<14
<18 10,400i450 08-17-86 800
<12
<10
<10
<12 4,6601320 09-21-86 815
<26
<19
<21
<11 5,7901290 09-27-86 818
<23
<16
<21
<10 3.040t160 10-12-86 850
<34
<29
<31
<37 5,9001640 11-09-86 861
<45
<32
<33
<37 6,1001630 12-14-86 867
<53
<25
<28
<29 7,8601420 a ND = No data; sample temporarily unavailable.
Elevated I-131, Cs-134, and Cs-137 activity is due to fallout from the Chernobyl Nuclear Plant (USSR) accident on April 26, 1986.
c Ru-103:
5313.
d Ru-103:
4114.
7.0-34
(
s FERMI-2 Table 16. Cattlefeed, analysis for ganna-emitting isotopes.
. Collection: Annually Units: pC1/kgwetweight(asreceived)
Date Sample Concentration j
Location Collected Type Lab Code Cs-134 cs-137 8e-7 K-40 F-7 12-14-86 Fodder FCF-26'l
<21
<22
<164 7,270t490 1
l F-19a 12-14-86 Fodder l
F-20 12-14-86 Fodder 262
<7
<9 524164 '
, 3,7501210 l
U F-31 12-14-86 Fodder 263
<17
<19
. 5301104 4,9501290.
F-32 12-14-86 Fodder 264
<18 2617 1,287192 9,5501210 a Sample was unavailable because no milch' animals were being maintained on the farm.
L 1
N.., >
FERMI-2 Table 17. Food products, analysis for gama-emitting isotopes.
Collection: Twice during growing season Units: pC1/kg wet Date Sample Lab Concentration Location Collected Type Code I-131 Cs-134 Cs-137 Be-7 K-40 Indicator Location 1 -
07-27-86 Cabbage FVe-70,1
<28
<14
<15
<171 4880t220
- 8. Masserant.
09-07-86 Rhubarb 134
<15
<7
<8
<68 4180t210 2.8 mi N-NNW 09-07-86 Cabbage 135
<44
<22
<19
<229 4820t240
- y 09-21-86 Cabbage 141
<27
<19
<14
<160 2600t170 i
j*o
<21
<20
<149 10601500 4a 09-21-86 Beets 142 c'
i Location 2 -
08-24-86 Cabbage FVe-105
<15
<7
<8
<63 1620t100 I
Roland Farm, 08-24-86 Rhubarb 106
<14
<8
<7, 91132 3130t100 4.0 mi NNE 09-07-86 Cabbage 136
<18
<10
<10
<76 20501190 09-07-86 Cabbage 138b j
09-21-86 Beets 143
<30
<29
<225 4680i420 09-21-86 Cabbage 144
<24
<17
<17
<148 4440i370 i
09-21-86 Rhubarb 145
<59
<36
<42
<350 46801630 Control Happy Farm 09-07-86 Cabbage FVe-139
<16
<10
<8
<79 20801110 09-07-86 Rhubarb 140
<33
<17
<19
<149 28601360 09-21-86 Cabbage 146
<36
<21
<26
<197 2250t390
<35
<40
<497 32101430 09-21-86 Potatoes 147
- I-131 analysis required for leafy vegetables only.
J Sample was analyzed but LLDs were high because of small sample size (49.3 g wet).
It was resampled on l
September 21, 1986 (lab code 144).
s
'.. _..h
I FERMI-2 Table 18. Fish, analysis for garina-emitting isotopes.
Collection:
Semiannually Units: pCi/kg wet weight, edible portion Location Sample Description and Concentration Indicator F-16 Date Collected 05-13-86 05-13-86 10-23-86 Lab Code FF-63 FF-64 FF-160 4
Type Walleye Bass
. alleye W
K-40 3287t77 2490i164 3600f301 Mn-54
<9
<12
<30 Fe-59
<183
<227
<80 Co-58
<28
<39
<26 Co-60
<8
<12
<30 Zn-65
<24
<36
<63 Cs-134
<9
<8
<35 Cs-137 36.0f3.1
<9
<32 Control F-11 Date Collected 05-14-86 10-23-86 Lab Code FF-62 FF-159 Type Walleye Walleye
/
<10
<27 f
Fe-59
<189
<105 Co-58
<30
<31 Co-60
<19
<24 Zn-65
<26
<73 Cs-134
<9
<28 Cs-137 90.015.0 24.4f11.5 l
l 7.0-37
Appendix A Interlaboratory Comparison Program Results l
A-1
i Appendix A Interlaboratory Comparison 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 concentrations 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 known values or outside the control limits indicate a need to check the instruments or procedures used.
The results in Table A-1 were obtained through participation in the environ-mental sample crosscheck program for milk, water, air filters, and food samples during the period May 1984 through November 1986.
This program has been conducted by the U. S. Environmental 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 c
l (TLD's) during the period 1976, 1977, 1979, 1980, aind 1981 through parti-
't' cipation in the Second, Third. Fourth, and Fifth International Intercomparison
\\
of Environmental Dosimeters under the sponsorships listed in Table A-2.
Table A-3 lists results of the analyses on in-house spiked samples.
l Table A-4 lists results of the analyses on in-house " blank" samples.
A-2
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, com-parison of EPA and Teledyne Isotopes Midwest Laboratory results for milk, water, air filters, and food samples, 1984 through 1986.a Concentration in >Ci/lb Lab Sample Date TIML Result EPA tesult Code Type Collected Analysis
- 2rc flo, n=3d STW-358 Water May 1984 Gross alpha 3.010.6 318.7 Gross beta 6.7tl.2 618.7 STM-366 Milk June 1984 Sr-89 2113.1 2518.7 Sr-90 13i2.0 1712.6 I-131 46i5.3 43110.4 Cs-137 38i4.0 35*8.7 K-40 1577i172 1496t130 STW-368 Water July 1984 Gross alpha 5.1*1.1 6*8.7 Gross beta 11.9t2.4 1318.7 STW-369 Water August 1984 I-131 34.3*5.0 34.0i10.4 STW-370 Water August 1984 H-3 3003t253 28171617 STF-371' Food July 1984 Sr-89 22.015.3 25.0*8.7 Sr-90 14.7*3.1 20.0t2.6 I-131
<172 39.0*10.4 Cs-137 24.015.3 25.0*8.7 K-40 2503i132 2605i226.0 STAF-372 Air August 1984 Gross alpha 15.3tl.2 1718.7 Filter Gross beta 56.0*0.0 51i8.7 Sr-90 14.3*1.2 18i2.4 Cs-137 21.0i2.0 1518.7 k-STW-375 Water Sept.1984 Ra-226 5.1*0.4 4.9tl.27 Ra-228 2.210.1 2.3i0.60 STW-377 Water Sept.1984 Gross alpha 3.311.2 5.0*8.7 Gross beta 12.7f2.3 16.0i8.7 STW-379 Water Oct. 1984 H-3 2860*312 2810i356 STW-380 Water Oct. 1984 Cr-51
<36 40*8.7 Co-60 20.3*1.2 20*8.7 Zn-65 150i8.1 14718.7 Ru-106
<30 47*8.7 Cs-134 31.3*7.0 31*8.7 Cs-137 26.7*1.2 24i8.7 i
i A-3 i
e
Table A-1.
(continued)
Concentration in >C1/lb Lab Sample Date TIML Result EPA tesult Code Type Collected Analysis tasc ilo,n=3d STM-382 Milk Oct. 1984 Sr-89
- 15. 7t4. 2 22*8.7 Sr-90 12.7*1.2 16*2.6 I-131 41.7*3.1 42*10.4 Cs-137 31.3*6.1 32i8.7 K-40 1447166 1517*131 STW-384 Water Oct.1984 Gross alpha 9.7tl.2 14*8.7 (811nd)
Sample A Ra-226 3.3i0.2 3.0*0.8 Ra-228 3.4*1.6 2.110.5 Uranium NA8 Si10.4 Sample 8 Gross beta 48.315.0 64*8.7 Sr-r3 10.714.6 1118.7 Sr-30 7.311.2 12*2.6 00-60 16.3*1.2 14*8.7 Cs-134
<2 2i8.7 Cs-137 16.7tl.2 14i8.7 STAF-387 Air Nov. 1984 Gross alpha 18.7tl.2 15i8.7 Filter Gross beta 59.015.3 5218.7 Sr-90 18.3tl.2 21i2.6 Cs-137 10.3i1.2 1018.7 STW-388 Water Dec. 1984 I-131 28.Di2.0 36i10.4 STW-389 Water Dec. 1984 H-3 3583t110 3182i624 r
STW-391 Water Dec. 1984 Ra-226 8.4*l.7 8.6*2.2
}j Ra-228 3.1*0.2 4.1*1.1 STW-392 Water Jan. 1985 Sr-89
<3.0 3.0i8.7 Sr-90 27.315.2 30.0*2.6 STW-393 Water Jan. 1985 Gross alpha 3.3tl.2 Si8.7 Gross beta 17.3i3.0 15t8.7 STS-395 Food Jan. 1985 Gross alpha
- 4. 7t2.3 6.0i8.7 Gross beta 11.311.2 15.018.7 Sr-89 25.316.4 34.0*8.7 Sr-90 27.018.8 26.0*2.6 I
I-131 38.0*2.0 35.0*10.4 Cs-137 32.7t2.4 29.0i8.7 K-40 1410*212 1382f208 i
A-4
. - - - - - -... - ~ ~ - - -., ~ ~., - - _ _ _, _ _, -,. -. _,. -
.----m.,..
._,,,,.,--,.--,~-- --- -
Table A-1.
(continued)
Concentration in pC1/lb Lab Sample Date TIML Result EPA tesult Code Type Collected Analysis
- 2aC ilo, n=3d STW-397 Water Feb. 1985 Cr-51
<29 48i8.7 Co-60 21.313.0 20i8.7 Zn-65 53.7*5.0 5518.7 Ru-106
<23 2518.7 Cs-134 32.3*1.2 35i8.7 Cs-137 25.3i3.0 2518.7 STW-398 Water Feb. 1985 H-3 3869i319 3796i634 STM-400 Milk March 1985 I-131 7.312.4 9.0*1.6 STW-402 Water March 1965 Ra-226 4.6i0.6 5.0il.3 Ra-228
<0.8 S.0t2.3 Reanalysis Ra-228 9.010.4 STW-404 Water March 1985 Gross alpha 4.7t2.3 6i8.7 Gross beta 11.3tl.2 15i8.7 STAF-405 Air March 1985 Gross alpha 9.3*1.0 10.018.7 Filter Gross beta 42.0*1.1 36.018.7 Sr-90 13.3*1.0 15.0*2.6 Cs-137 6.3*1.0 6.0t8.7 STW-407 Water April 1985 I-131 8.0*0. 0 -
7.Sil.3 STW-408 Water April 1985 H-3 33991150 3559i630 STW-409 Water April 1985 f
(Blind)
Gross alpha 29.7*1.8 32.018.7 I
Sample A Ra-226 4.4i0.2 4.1*1.0 Ra-228 nae 6.2il.6 Uranium nae 7 Oi10,4 t
Sample B Gross beta 74.3i11.8 72.018.7 i
Sr-89 12.3*7.6 10.0i8.7 Sr-90 14.7*2.4 15.0*2.6 Co-60 14.7*2.4 15.0i8.7 Cs-134 12.0*2.0 15.0i8.7 Cs-137 14.0*2.0 12.0i8.7 A-5
1 Table A-1.
(continued) 4 l
l Concentration in >Ci/lb Lab Sample Date TIML Result EPA tesult Code Type Collected Analysis t2cc ilo, n=3d I
STW-413 Water May 1985 Sr-89 36.0112.4 39.Qi8.7 Sr-90 14.314.2 15.0*2.6 STW-414 Water May 1985 Gross alpha 8.314.1 12.018.7 Gross beta 8.7tl.2 11.0*8.7 STW-416 Water June 1985 Cr-51 44.716.0 44.018.7 Co-60 14.3tl.2 14.018.7 Zn-65 50.3*7.0 47.0t8.7 Ru-106 55.3*5.8 62.0*8.7 Cs-134 32.711.2 35.0*8.7 Cs-137 22.7*2.4 20.0*8.7 STW-418 Water June 1985 H-3 2446*132 2416i609 STM-421 Milk June 1985 Sr-89 10.3i4.6 11.018.7 Sr-90 9.0t2.0 11.0i2.6 I-131 11.7*1.2 11.0i10.4 Cs-137 12.711.2 11.0*8.7 K-40 1512162 1525*132 STW-423 Water July 1985 Gross alpha 5.0t0.0 11.018.7 Gross beta 5.012.0 8.0i8.7 STW-4?S Water August 1985 I-131 25.713.0 33.0*10.4
/
STW-426 Water August 1985 H-3 4363*83 4480*776 STAF-427 Air August 1985 Gross alpha 11.310.6 13.018.7 Filter Gross beta 46.0tl.0 44.018.7 Sr-90 17.710.6 18.0*2.6 4
Cs-137 10.310.6 8.0*8.7 STW-429 Water Sept. 1985 Sr-89 15.710.6 20.0*8.7 Sr-90 7.0f0.0 7.012.6 STW-430 Water Sept. 1985 Ra-226 8.210.3 8.9*2.3 Ra-228 4.1*0.3 4.6*1.2 STW-431 Water Sept.1985 Gross alpha 4.710.6 8.018.7 Gross beta 4.711.2 8.018.7 I
A-6
i Table A-1.
(continued)
Concentration in aci/lb
]
Lab Sample Date TIML Result EPA tesult Code Type Collected Analysis tauc tio, n=3d STW-433 Water Oct.1985 Cr-51
<13 21.018.7 Co-60 19.30.6 20.0i8.7 Zn-65 19.710.6 19.018.7 Ru-106
<19 20.0t8.7 Cs-134 17.0tl.0 20.0t8.7 Cs-137 19.3*1.2 20.0i8.7
'STW-435 Water Oct. 1985 H-3 1957150 19741598 STW-436 Water Oct.1985 437 (Blind)
Sample A Gross alpha 53.0*1.0 52.0i22.6 Ra-226 5.9*0.1 6.3*1.6 Ra-228 8.2*0.1 10.112.6 Uranium NA*
8.0110.4 Sample 8 Gross beta 85.7*2.5 75.0i8.7 Sr-89 21.3 1.5 27.018.7 Sr-90 10.3*0.6 9.0*2.6 Co-60 18.311.2 18.018.7 Cs-134 16.311.2 18.Di8.7 Cs-137 19.011.0 18.0i8.7 STM-439 Milk Oct. 1985 Sr-89 50.3i0.6 48.0*8.7 Sr-90 23.3*0.6 26.012.6 7
I-131 45.7*3.2 42.0110.4 Cs-137 60.710.6 56.0i8.7 li'
\\
K-40 1547*29 1540i134 l
STW-441 Water Nov. 1985 Gross alpha 5.3i0.6 10.0i8.7 Gross beta 11.7tl.2 13.0i8.7 STW-443 Water Dec.1985 I-131 46.7*2.1 45.0*10.4 STW-444 Water Dec.1985 Ra-226 6.5*0.1 7.lil.9 Ra-228 6.110.1 7.3i1.9 STW-445 Water Jan. 1986 Sr-89 29.7*2.5 31.0i8.7 Sr-90 13.7*0.6 15.0*2.6 STW-446 Water Jan. 1986 Gross alpha 3.010.0 3.018.7 Gross beta 5.3i0.6 7.018.7 A-7 i
i
~ ~ - - ~ - -
-,---,----,----n.----,,.,-----,n
_,.- --,,_,,-,--,,- - -. n,-. _ n n
._-,,.n-,n
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA ksult Code Type Collected Analysis
- 2aC tio, n=3d STW-447 Food Jan. 1986 Sr-89 24.3 2.5 25.0i8.7 r
Sr-90 17.3i0.6 10.0t2.6 I-131 22.7k2.3 20.0t10.4 Cs-137 16.3t0.6 15.018.7 K-40 927*46 9501249 STW-448 Water Feb. 1986 Cr-51 45.0i3.6 38.0t8.7 Co-60 19.7*1.5 18.0i8.7 Zn-65 44.0i3.5 40.018.7 i
Ru-106
<9.0 0.018.7 Cs-134 28.3t2.3 30.0i8.7 Cs-137 23.7*0.6 22.0*8.7 STW-449 Water Feb. 1986 H-3 5176i48 52271910 l
STW-450 Water Feb. 1986 U total 8.010.0 9.0*10.4 STW-451 Milk Feb. 1986 I-131 7.010.0 9.0t10.4 STW-452 Water March 1986 Ra-226 3.8i0.1 4.lil.1 Ra-228 11.0*0.5 12.4t3.2 STW-453 Water March 1986 Gross alpha 6.7*0.6 15.018.7 i
Gross beta 7.3t0. 6 8.028.7 STW-454 Water April 1986 I-131 7.0t0.0 9.0i10.4
{/
STW-455 Water April 1986
\\
456 (Blind)
Sample A Gross alpha 15.0il.0 17.0i8.7 Ra-226 3.1*0.1 2.9i0.8 Ra-228 1.5*0.2 2.010.5 Uranium 4.7*0.6 5.0110.4 Sample B Gross beta 28.7*1.2 35.018.7 Sr-89 5.710.6 7.0i8.7 Sr-90 7.0i0.0 7.0t2.6 Co-60 10.7tl.5 10.0i8.7 Cs-134 4.0il.7 5.0*8.7 Cs-137 5.3i0.6 5.0i8.7 A-8
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA tesult Code Type Collected Analysis fasc flo, n=3d STAF-457 Air April 1986 Gross alpha 13.710.6 15.018.7 Filter Gross beta 46.3i0.6 47.018.7 Sr-90 14.7*0.6 18.0t2.6 Cs-137 10.7i0.6 10.0t8. 7 STU-458 Urine April 1986 Tritium 4313i70 4423*327 STW-459 Water May 1986 Sr-89 4.3*0.6 5.018.7 Sr-90 5.0i0.0 5.0t2.6 STW-460 Water May 1986 Gross alpha 5.3*0.6 8.018.7 Gross beta 11.3*1.2 15.018.7 STW-461 Water June 1986 Cr-51
<9.0 0.018.7 Co-60 66.011.0 66.018.7 Zn-65 87.3*1.5 86.0i8.7 Ru-106 39.7*2.5 50.0t8.7 Cs-134 49.312.5 49.0i8.7 l
Cs-137 10.311.5 10.018.7 STW-462 Water June 1986 Tritium 3427125 3125*626 STM-464 Milk June 1986 Sr-89
<1.0 0.0t8.7 Sr-90 15.3t0.6 16.0t2. 6 I-131 48.3i2.3 41.0110.4 Cs-137 43.711.5 31.018.7
/
K-40 1567*114 1600i139 (f
STW-465 Water July 1986 Gross alpha 4.710.6 6.018.7 Gross beta 18.711.2 18.0*8.7 STW-467 Water August 1986 I-131 30.3i0.6 45.0t10.4 STW-468 Water August 1986 Pu-239 11.310.6 10.1*1.8 STW-469 Water August 1986 Uranium 4.0f0.0 4.0i10.4 STAF-470 Air September 1986 Gross alpha 19.3i1.5 22.0i8.7 471 Filter Gross beta 64.0i2.6 66.0i8.7 472 Sr-90 22.0il.0 22.0*2.6 Cs-137 25.7*1.5 22.0*8.7 STW-473 Water September 1986 Ra-226 6.0i0.1 6.1*1. 6 Ra-228 8.7*1.1 9.1*2.4 A-9
Table A-1.
(continued)
Concentration in ?Ci/lb Lab Sample Date TIML Result EPA tesult Code Type Collected Analysis
- 2ac ilo, n=3d STW-474 Water September 1986 Gross alpha 16.3*3.2 15.0i8.7 Gross beta
- 9. 0*1. 0 8.0f 8. 7 STW-475 Water October 1986 Cr-51 63.3*S.5 59.018.7 Co-60 31.0f2.0 31.018.7 Zn-65 87.3t5.9 85.0i8.7 Ru-106 74.7t7.4 74.0*8.7 Cs-134 25.7t0.6 28.0i8.7 Cs-137 46.3tl.5 44.0*8.7' STW-476 Water October 1986 H-3 5918i60 5973*1035 STM-479 Milk November 1986 Sr-89
- 7. 7t]. 2 9.0i8.7 Sr-90 1.020.0 0.0f 2. 6 I-131 52.313.1 49.0110.4 Cs-137 45.7i3.1 39.0*8.7 K-40 1489i104 1565i135 STU-480 Urine November 1986 H-3 5540*26 52571912 STW-481 Water November 1986 Gross alpha 12.014.0 20.018.7 Gross beta 20.0f3.5 20.018.7 a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercom-parison and Calibration Section, Quality Assurance Branch, Environmental J
Monitoring and Support Laboratory, U.S.
Environmental Protection Agency,
,t b (EPA), Las Vegas, Nevada.
s/
All results are in pCi/1, except for elemental potassium (K) data, which are in mg/1; air filter samples, which are in pCi/ filter; and food, which is in pCi/kg.
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 i control limits of b for n = 3.
e NA = Not analyzed.
f Analyzed but not reported to the EPA.
9 Results after calculations corrected (error in calculations when reported to EPA).
A-10
,,,-,-.--,,n
---.-.,,--,.---..e
Table A-2.
Crosscheck program results, thermoluminescent dosimeters (TLDs).
i mR d
Teledyne Average *2a Lab TLD Result Known (all 1
Code Type Measurement
- 2ea valueC participants)
I 2nd International Intercomparisonb CaF :Mn Field 17.0il.9 17.1 16.4t7.7 115-2 2
BuTb Lab 20.8t4.1 21.3 18.8i7.6 4
j 3rd International Intercomparisone CaF :Mn Field 30.7i3.2 34.914.8 31.5*3.0 115-3 2
?
Bulb q
=
Lab 89.616.4 91.7114.6 86.2124.0 4th International Intercomparisonf CaF :Mn Field 14.111.1 14.111.4 16.0t9.0 115-4 2
Bulb 1
Lab (Low) 9.3i1.3 12.212.4 12.0t7.6 Lab (High) 40.4*1.4 45.8t9.2 43.9*13.2 j
i Sth International Intercomparison9 t
CaF :Mn Field 31.4tl.8 30.016.0 30.2i14.6 115-5A 2
Bulb Lab at 77.4i5.8 75.2*7.6 75.8t40.4 beginning I
Lab at 96.6t5.8 88.4*8.8 90.7131.2 the end l
i
Table A-2.
(Continued) mR d
Teledyne Average i 2e Lab TLD Result Known (all Code Type Measurement 12ba Valuec participants) 115-58 LiF-100 Field 30.314.8 30.016.0 30.2114.6 Chips Lab at 81.117.4 75.217.6 75.8140.4 beginning Lab at 85.4111.7 88.418.8 90.7131.2 the end h
l 7th International Intercomparison
?
O 115-7A LiF-100 Field 75.412.6 75.816.0 75.1129.8 Chips Lab (Co-60) 80.013.5 79.914.0 77.9127.6 Lab (Cs-137) 66.6t2.5 75.0t3.8 73.0t22.2 CaF :Mn Field 71.Si2.6 75.816.0 75.li29.8 i
115-78 2
l Bulbs Lab (Co-60) 84.816.4 79.914.0 77.9127.6 Lab (Cs-137)
/8.8tl.6 75.0t3.8 73.0222.2 115-7C CaSO :Dy Field 76.812.7 75.8i6.0 75.1129.8 4
Cards 79.914.0 77.9127.6 Lab (Co-60) 82.Si3.7 Lab (Cs-137 79.013.2 75.013.8 73.0122.2
I Table A-2.
(Continued)'
"R j
1 Teledyne Average i b d l
)
Lab TLD Result Known (all Code Type Measurement iba Valuec participants}
r 8th International Intercomparisoni 115-84 L1F-100 Field Site 1 29.Sil.4 29.7*1.5 28.9*12.4 Chips Field Site 2 11.3*0.8 10.4*0.5 10.1*9.06 i
Lab (Cs-137) 13.7*0.9 17.210.9 16.2*6.8 CaF :Hn Field Site 1 32.3tl.2 29.7*1.5 28.9t12.4 115-88 2
Bulbs Field Site 2 9.0*1.0 10.4*0.5 10.lt9.0 Lab (Cs-137) 15.8t0.9 17.2*0.9 16.2*6.8 CaSO :Dy Field Site 1 32.3*0.7 29.7tl.5 28.9t12.4 l
115-8C 4
{
Cards Field Site 2 10.6i0.6 10.4*0.5 10.119.0 Lab (Cs-137) 18.1*0.8 17.210.9 16.2*6.8 a Lab result given is the mean *2 standard deviations of three determinations.
l b Second International Intercomparisen of Environmental Dosfeeters 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 l
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.
l l
e Third International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.
f Fourth International Intercomparison of Environmental Dosimeters conducted in summer of T979 by the School of Public Health of the University of Texas. Houston, Texas.
9 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.
Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and summer of h
1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, the U.S. Nuclear Regulatory
, Commiission, and the U.S. Environmental Protection Agency. Eighth International Intercomparison j
i l
1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.
j
i Table A-3.
In-house spiked samples.
Concentration in pCi/1 Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precision 1s. n=3a 3
l QC-MI-6 Milk Feb. 1986 Sr-89 6.011.9 6.4*3.0 8.7 Sr-90 14.211.7 12.912.0 5.2 I-131 34.213.8 35.2i3.5 10.4 l
Cs-134 32.011.8 27.315.0 8.7 Cs-137 35.8t2.1 35.0*5.0 8.7 QC-W-14 Water Mar. 1986 Sr-89 1.6*0.4 1.6tl.0 7.1 Sr-90
- 2. 4*0. 2 2.4*2.0 4.2 QC-W-15 Water Apr. 1986 I-131 44.912.4 41.517.0 10.6 Co-60 10.611.7 12.lt5.0 7.lb Cs-134 30.212.4 25.818.0 7.lb 4
Cs-137 21.9tl.9 19.915.0
- 7. lb QC-MI-7 Milk Apr. 1986 I-131
- 39. 7t3.3 41.517.0 10.4 Cs-134 28.712.8 25.818.0 8.7 Cs-137 21.212.8 19.9i5.0 8.7 SPW-1 Water May 1986 Gross alpha 15.8tl.8 18.015.0 Sc i
QC-W-16 Water June 1986 Gross alpha 16.2*0.7 16.912.5 8.7 Gross beta 38.4*3.5 30.215.0 8.7
/
QC-MI-9 Milk June 1986 Sr-89
<1.0 0.0 7.lb d
Sr-90 12.611.8 13.3*3.0 4.2b 4f I-131 38.917.0 34.817.0 10.4 Cs-134 33.013.4 36.115.0 8.7 1
l Cs-137 38.Si2.8 39.015.0 8.7 j
SPW-2 Water June 1986 Gross alpha 16.8tl.8 18.015.0 Sc j
SPW-3 Water June 1986 Gross alpha 17.7t0.8 18.015.0 SC i
QC-W-18 Water Sep. 1986 Cs-134 34.7kS.6 31.3i5.0 8.7 j
Cs-137 51.117.0 43.318.0 8.7 QC-W-19 Water Sep. 1986 Sr-89 13.6t4.1 15 6*3.5 7.lb l
- 6. 4* l. 6 6.2k2.0 4.2b l
A-14 i
Table A-3.
In-house spiked samples (continued) f Concentration in pC1/1 Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precision 15, n=3a i
QC-W-21 Water Oct. 1986 Co-60 19.2*2.2 18.5*3.0 8.7 Cs-134 31.7*5.2 25.6*8.0 8.7 Cs-137 23.811.0 21.6i5.0 8.7 QC-MI-11 Milk Oct 1986 Sr-89 12.3tl.8 14.3i3.0 8.7 l
QC-W-20 Water Nov. 1986 H-3 3855i180 39601350 520b QC-W-22 Water Dec. 1986 Gross alpha 9.811.4 11.214.0
- 8. 7 Gross beta 21.712.0 23.815.0 8.7 QC-W-23 Water Jan. 1987 I-131 29.8i2.5 27.9i3.0 10.4 QO-MI-12 Milk Jan. 1987 I-131 36.5*1.3 32.6f5.0 10.4 Cs-137 32.614.2 27.418.0 8.7 1
" n=3 unless noted otherwise.
c,,2.
i n=
g, ll r
A-15
Table A-4.
In-house " blank" samples.
Concentration in pC1/1 Acceptance Lab Sample Date Results Criteria a
Code Type Collected Analysis (4.660)
(4.66o)
BL-1 D.I. Water Nov. 1985 Gross alpha
<0.1
<1 Gross beta
<0.4
<4 8L-2 D.I. Water Nov. 1985 Cs-137 (gama)
<1. 9
<10 1
1 8L-3 0.I. Water Nov. 1985 Sr-89
<0. 5
<5 Sr-90
<0.6
<1 BL-5 0.I. Water Nov. 1985 Ha-226
<0.4
<1 Ra-228
<0.4
<1 SPW-2265 D.I. Water Apr. 1985 Gross alpha
<0. 6
<1 Gross beta
<2.2
<4 Sr-89
<0. 2
<5 Sr-90
<0.4
<1 1
1-131
<0.2
<1 Cs-137 (gama)
<7.4
<10 BL-6 D.I. Water Apr. 1986 Gross alpha
<0.4
<1 BL-7 D.I. Water Apr. 1986 Gross alpha
<0.4
<1
- f.
BL-8 D.I. Water June 1986 Gross alpha
<0.4
<1 BL-9 0.I. Water June 1986 Gross alpha
<0.3
<1 i
i i
4 A-16
EPA Discussion of Results Lab Code:
STF-447 EPA Result:
10.0i2.6 Nuclide:
Sr-90 TIML Result:
17.3t0.6 Collection: January, 1986 TIML has no explanation for the high Sr-90 results in this food sample except that the sample was difficult to analyze. Special attention will be paid to this analysis when analyzing food samples in the future.
Lab Code:
STAF-457 EPA Result:
18.0t2.6 Nuclide:
Sr-90 TIML Result:
14.7t0.6 Collection:
April 1986 TIML has no explanation for the low Sr-90 results in this filter sample.
TIML's test result is only 0.7 pCi/f low of the EPA's limit of error. Addi-tional results for Sr-90 in air filters in 1986 and in the past have been in 7
good agreement.
No further action is planned.
i k'
Lab Code:
STW-461 EPA Result:
50.0*8.7 Nuclide:
Ru-106 TIML Result:
39.712.5 Collection:
June, 1986 The three results were 40, 42, and 37. One of these results was within the two sigma limit; the other two were low, resulting in a low average. Addi-tional results for Ru-106 in 1986 were in good agreement. No further action is planned.
1 I
A-17
\\
Lab Code:
STM-464 EPA Result:
31.018.7 Nuclide:
Cs-137 TIML Result:
43.7tl.5 Collection: June, 1986 TIML has no explanation for the high Cs-137 results in this sample. Additional results for Cs-137 in milk in 1986 and in the past were in good agreement.
All solid state detector were recalibrated. No further action is planned.
Lab Code:
STW-467 EPA Result:
45.0*10.4 Nuclide:
1-131 TIML Result:
30.3*0.6 Collection: August 1986 The original results listed above were decay corrected to August 11, 1986.
The correct date of collection was August 8,1986. Decay correcting to August 8,1986, the three results were 39, 39 and 40, yellding a mean i 2 s.d. of 39.311.2, which is within error of the EPA result.
l' A-18
Appendix B Data Reporting Conventions
' /*
B-1
f Data Reporting. Conventions i
1.0.
All activities are decay corrected to collection time.
2.0.
Single Measurements Each single measurement is reported as follows:
4 xis where x = value of the measurement; s = 20 counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is found to be below the lower limit of detection L it is reported as
<L where L = is the lower limit of detection based on 4.66 uncertainty for a background sample.
3.0.
Duplicate Analyses 3.1.
Individual results:
x1 i s1 x2
- 52 Reported result:
xis where x = (1/2) (x1 + x2) s=(1/2)fs2,32 3.2.
Individual results:
<L1 J
<l2
-'\\t Reported result:
<L where L = lower of L1 and L2 3.3.
Individual results:
xis
<L Reported result:
x i s if x > L; 1
<L otherwise g.2
- - -. -...-..~ -
4.0.
Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations.
The average I and standard deviations of a set of n numbers x1, x2,... x are defined as follows:
n x=fIx II*~*I2 s=
n-1 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5. In rounding off, the folfowing rules are followed:
4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged.
As an example, 11.443 is rounded off to 11.44.
4.5.2 If the figure following those to be retained is greater than 5, the figure is dropped, and the last retained figure is
.N raised by 1.
As an example,11.446 is ruunded off to 11.45.
4.5.3. If the figure following those to be retained is 5, and if there are no figures other than zeros beyond the five, the figure 5 is dropped, and the last-place figure retained is increased by one if it is an odd number or it is kept unchanged if an even number.
As an example, 11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42, 1
l 8-3 i
4
Y APPENDIX C LAND USE CENSUS 5\\
C-1
r 19M M8KIAL IAPD (EE CENKE M R FERII 2 Prepared By J.
KQ otraental t
Progra:as Coordinator
/
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Pegulatory Affairs C-2
t l
t Annual Land Use Census 8/22/86 Page 2 l
TA"' OF OXTff27FS I.1986 Iand Use Census - Bases II.1986 Land Use Census - Sumary III. Table 1 - Field Verification Results IV. Table 2 - 1986 Land Use Census Data
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V C-3
7 Annual Land Use census 8/22/86 Page 3 I.
Land Use Census - Bases A.
Title 10 of the Code of Federal Regulations. Part 50 Appendix I.Section IV.B.3 states that "The Licensee shall establich an appropriate surveillance and monitoring program to:
Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modification in monitoring i
programs for evaluating doses to individuals from principal pathways of exposure."
'B.
The following requirements are from the Fermi 2 Plant
+
Specific Technical Specifications:
1.
Section 3/(.12.1 4 Land Use Census, states that "A land use census shall be c.onducted and shall identify within a distance of 6 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearegt residenge. and the nearest garden of greater than 50 m (500 ft ) producing broad leaf vegetation."
2.
Section 4.12.2 steeds that:
.i "The land use cerdus shall be conducted during the 16 growing season atlinast once'per 12 acaths using that ff }
information that will provide the best results, such as 4
by a door-to-door survey, visual survey, serial survey.
(r or by consulting local' agriculture authorities. The results of the land use census shall be included in the Annual Radiclogical Environmental-Operating Report pursuant to Fpecification 6.9.1.7."
II.
1986 Land Use Census ' Summary J
A.
Procedure It k
l The Annual Land Use Census for Frrei 2 was conducted ir accordance.with, Regulatory Affsits Work Instruction RAWI 200 during the weeY af 11 August.31986. Personnel from Detroit Edison's Wayne-Monroe Division, who were familiar with the area, drove 3 the roadways within a five mile radius of the
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(
Annual Land Use Census 8/22/86 Page 4 Reactor Centerline. 'itey had been instructed, during a pre-census meeting, to be alert for and to note changes in land-use patterns, e.g. significant industrial activity, irrigation from surface waters, recreational patterns, etc.
They recorded 3) the garden (greater than 500 scuare feet producing broadleaf vegetation) and the residence nearest the plent within each meteorological sector, and 2) all milk anicals on current maps of apprcpriate scale (Table 2).
On 21 August,1986 the Environmental Programs Coordinator field checked all " probable" milk aniral locations noted on the census maps (Table 1).
~
B.
Results l
As a result of the 1986 Land Use Census, the following changes to the nearest garden and residence locations were recorded.
(The distance figures are in miles from the Reactor Centerline). Ib neu milk aniral locations were i
found. Ib significant changes to land-use patterns were noted.
)
SBCKR ZEE 1985 DIFm? E 1986 DISDGE CEME (In 11iles)
N Residence (R) 1.2 1.1
-0.1 Garden (G) 1.2 1.6
+0.4 k/
13 I G
1.2 1.5
+0.3 SSC R
1.0 1.1
+0.1 G
1:ene 1.2 Added S
R 0.9 1.2
+0.3 G
1.1 1.2
+0.1 SS.?
G 1.5 1.1
-0.4 137 R
1.4 1.6
+0.2 11 G
1.3 1.5
+0.2 C-5
l*
Annual Iand Use Census 8/22/06 Page 5 1
)
itM R
0.6 1.1
+0.5 l
G 1.7 1.3
-0.4
!U R
1.0 0.6
-0.4 l
l 1
4 e
\\l l
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Annual Land Use Census 8/22/86 Page 6 TIILE 1 FIIID VEPlFIGTI0ti RESOLTS*
Media Incations Cerhus observaticns verification Pindims 6550 II. Stoney Creek Goat Ib nilk animals 4861 Anteau Cow Ib milk animls 4167 Post Cow Ib milk animls 6110 Leroux Goat Ib milk animls 6170 Leroux Goat lb milk animals Results of field verification of probable milk animi locations noted during the 1986 Land Use Census.
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Annual Land Use Census 8/22/86 Page 7 TAELE 2 Fermi 2 1986 IND USE CDEDS RESOLTS 2
Meteorolog{ cal Distance Sector Item Address (Miles)
N Nearest Residence 6552 Branco 1.1 N
Nearest Garden 6080 Trombley 1.6 RE Nearest Pasidence 6754 Lakeshore 1.2 DE
! barest Garden 7195 Iakeview 1.5 4
MI Milk cou 9501 Turnpike 4.0 1E tharest Residence 6832 Lakeshore 1.4
& Garden DE-SE Lake Erie SSE Nearest Residence 4834 Long 1.1
(,<
SSE Nearest Garden 4754 Long 1.2 S
Ikarest Residence 6369 PAP 1.2
& Garden SS7 Ikarest Residence 5820 Pointe Aux Peaux 1.1 SSt?
Ikarest Garden 5823 Pointe Aux Peaux 1.1 S?
Ikarest Residence 5194 Pointe Aux Peaux 1.2 S?
Ikarest Garden 5100 Pointe Aux Peaux 1.3 1G7 Nearest Residence 4771 Pointe Aux Peaux 1.6
& Garden C-8
r Annual Land U 2 Census 8/22/66 Page 8 11 Hearest Residence 6001 Toll 1.2 11 11earest Garden 6110 Leroux 1.5 tui Nearest Residence 6374 T.eroux 1.1 1917 Nearest Garden 6170 Leroux 1.3 IU 11earest Pesidence 6200 Longton 0.6 117 11earest Garden 5195 Post 1.4 4
II l' ilk Cow 3239 Newport 4.5 1211 Nearest Residence 5701 Post 1.1
& Garden lITEM:
1.
A reteorological sector is one of 16 segments of a full circle. It includes g
that area 11 1/4 to either side of any given compass direction.
(from True North).
2.
Distance from the Reactor Centerline.
3.
All gardens listed are greater than 500 ft.2 and producing broad leaf vegetation.
4.
Currently obtaining sarples at this location.
V C-9
i 1
f 1
r Appendix D I
Elevated Airborne Iodine-131 Activity Resulting From Chernobyl Nuclear Plant Accident (USSR)
April 26, 1986 4
I IY 9
D-1
=
e ww--w,-
-,--ww,-v-g 3g e r-,m---
y - rwme r.
w*~~++--+r--wewm--
m--r---- w er m w--
-m,--rwem +- g r r-e --ro m w-e w - e wcm we erm see.
y ELEVATED AIRBORNE 10 DINE-131 ACTIVITY RESULTING FROM CHERN0BYL NUCLEAR PLANT ACCIDENT (USSR)
APRIL 26, 1986 Concentration Location Date (pCi/m3)
F-1 05-11-86 0.4210.11 F-4 05-11-86 0.2010.08 F-5 05-11-86 0.18i0.04 F-17 05-11-86 0.3210.10 F-1 05-18-86 0.5910.30 F-4 05-18-86 0.2410.05 F-5 05-18-86 0.24i0.04 F-7 05-18-86 0.34i0.06 F-17 05-18-86 0.6410.11 F-1 05-25-86 0.0810.02 F-4 05-24-86 0.09i0.03 F-5 05-24-86 0.1110.03 F-7 05-24-86 0.1710.06 F-17 05-25-86 0.17*0.03 F-1 06-01-86 0.25i0.J6 F-4 06-01-86
<0.11 F-5 06-01-86 0.2310.06
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a LLD could not be reached due to delay in counting; sample counted for 12.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i
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