ML20151V128
| ML20151V128 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/31/1987 |
| From: | Hillyer D, Miller D, Morris R ILLINOIS POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| U-60117, NUDOCS 8805020287 | |
| Download: ML20151V128 (198) | |
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ILLINOIS POWER COMPANY
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CLINTON POWER STATION E
ANNUAL RADIOLOGICAL ENVIRONMENTAL l
MONITORING REPORT I
g February 27, 1987 - December 31,1987 I
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1987 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT FOR THE CLINTON POWER STATION I
I Prepared by Radiation Protection Department I
I Reviewed by f
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Robert L. Morris, CHF Supervisor - Radiological Environmental (Acting)
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David W./ Miller, PhD I
Supervisor - Radiological Support Approved by U
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David W. Hiliyer Assistant Manager - Plant Radiation Protection
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u TABLE OF CONTENTS ITEM PAGE Table of Centents i
iii List of Figures List of Tables iv I.
Executive Summary 1
II.
Introduction 2
2 A.
Objectives B.
Characteristics of Radiation 2
C.
Sources of Radiation Exposure 4
III.
Description of the Clinton Power Station 8
A.
General Information 8
I-B.
Climatological Summary - 1987 13 C.
Nuclear Reactor Operations 13 D.
Containment of Radioactivity 14 E.
Sources of Radioactive Liquid and Gaseous Effluents 17 1
Radioactivity Re.roval from Liquid and Gaseous
- 1. 7 F.
Wastes IV.
Effluents 19 V.
Radiological Environmental Monitoring Program 21 I
A.
Program Description 21 B.
Quality Assurance Program 24 VI.
Direct Radiation Monitoring 47 I
47 A.
Description B.
Results 47 48 C.
Analysis VII.
Atmospheric Monitoring 53 A.
Sample Collection 53 B.
Results and Analysis 54 59 VIII.
Aquatic Monitoring A.
Aquatic Biota Collection 59 i
B.
Results of Aquatic Biota Samples and Analysis 60 IX.
Terrestrial Monitoring 62 A.
Sataple Collection 62 I
B.
Results of Terrestrial Monitoring and Analysis 63 X.
Ground and Surface Water Monitoring 65 A.
Sample Collection 65 B.
Results and Analysis of Drinking Water Sampling 66 C.
Results and Analysis of Surface Water Sampling 71 D.
Results and Analysis of Well Water Sampling 71 i
l l
FL TABLE OF CONTENTS (Continued)
L ITEM PAGE
[ XI.
List of References 74 Appendices XII.
A.
REMP Sampling Locations, Synopsis of the REMP, A-1 l
Sampling and Analysis Exceptions in 1987 B.
LLD Exceptions in 1987 and Required Detection B-1 Capabilities C.
Changes to REMP in 1987 C-1 D.
Determination of Investigation Levels and D-1 Subsequent Actions l
E.
1987 Quality Assurance Results E-1 F.
1987 Land Use Census F-1 G.
1987 Meteorological Summary G-1 H.
1987 REMP Sample Collection and Analysis Methods H-1 I.
1987 Data Tables (Raw Data)
I-l 11
)
L I
LIST OF FIGURES PAGE FIGURE SUBJECT 15 1
Clinton Power Station Basic Plant Schematic I
Clinton Power Station Plant Schematic 16 2
22 3
Potential Exposure Pathways of Man Due to I
Releases of Radioactive Material to the Environment 42 4
Location of REMP Stations Within 2 Miles 43 5
Location of REMP Stations From 2 - 6 Miles 44 6
Location of REMP Stations From 6 - 50 Miles 45 7
Location of REMP Stations for Aq"atic I
Monitoring 46 8
Control Location of REMP Station for Aquatic Monitoring 51 9
1987 Quarterly TLD Dose Rates (mR/QTR) 10 Historic TLD Dose Rates (mR/QTR) 52 57 11 Air Particulate Gross Beta Activity 58 12 Quarterly Gross Beta Air Particulate 67 13 1987 Surface Water Gross Beta Activity 68 14 Historic Surface Water Gross Beta 69 15 1987 Drinking Water Gross Beta 70 16 Historic Drinking Water Gross Beta 6M M
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LIST OF TABLES TABLE SUBJECT PAGE 1
Common Sources of Radiation 6
2 Climatological Data From Weather Stations 12 Surrounding the Clinton Power Station 3
Radionuclide Composition of CPS Effluents 20 in 1987 l
4 Environmental Radiological Monitoring Program 26 Annual Summary 5
1987 CPS REMP Annual TLD Results 49 6
1987 Average Gross Beta Concentration in Air 55 Particulates 7
1987 Average Monthly Gross Beta Concentrations 56 in Air Particulates from Control and Indicator Stations 8
1987 Average Tritium Concentrations in Surface, 72 Drinking and Well Water 9
1987 Average Gross Beta Concentrations in 73 Surface, Drinking and Well Water I
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I iv
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CLINTON POWER STATION OPERATIONAL RADIOLOGICAL ENVIROMMENTAL MONITORING REPORT FOR 1987 I.
EXECUTIVE
SUMMARY
The Radiological Environmental Monitoring Program was performed in 1987 as required by the Clinton Power Station Technical Specifications.
This is the first annual operating report and covers the period from initial criticality (February 27, 1987) through the end of 1987.
No increases in either the environmental radiation dose rate or the radioactive material concentration in the environment due to operation of the Clinton Power Station were detected.
A total of over eleven hundred environmental samples representing atmospheric, terrestrial, and aquatic environs, es well as Lake Clinton and public drinking water supplies were collected.
Results of the analyses showed that radioactivity levels were not significantly higher than preoperational levels.
The ambient radiation field was measured at 82 locations using Thermoluminescent Dosimeters.
The average annual dose at i
indicator locations was 78 mrem per year.
This dose was similar i
dc,.f, to the annual dose at control locations, Th" Releases of gaseous and liquid radioactive materials were accurately measured in the plant effluents.
A total of 6.8 curies of short-lived noble gases and 0.26 curies of tritium was released C
to the atmosphere.
The dominant.radionuclide in the liquid
- 4 a /;,
effluent was tritium.
A total of 1.87 curies of tritium was R
released as liquid effluent in 1987.
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The Radiological Environmental Monitoring Program samples collected during 1987 were verified to be free of any measurable I
radioactivity due to the operation of the Clinton Power Station.
This finding is consistent with known radioactive material releases.
Environmental measurements verify that operational controls on the radioactive effluent functioned as designed in 1987.
1
r II.
INTRODUCTION 14 A.
Objectives This is a report on the Radiological Environmental Monitoring Program (REMP) for the Clinton Power Station (CPS),
I covering the period from initial criticality (February 27, 1987) through the end of 1987.
The Radiological Environmental Monitoring Program is an extensive program of sampling, measurements, and analysis that was instituted to monitor the radiological impact of I
reactor operation on the environment.
Objectives of the program include:
I measurement of the amount of radiation and radioactive material in the environs surrounding the Clinton Power Station evaluation of the measurements to determine the impact of the Clinton Power Station operations on the local radiation environment demonstration of compliance with regulations and operating license requirements collection of data needed to refine environmental radiation transport models used in offsite dose calculations verification that radioactive material containment systems are functioning to minimize environmental I
releases to levels that are As Low As Reasonably Achievable (ALARA).
B.
Characteristics of Radiation The following background information regarding basic 8
radiation characteristics, plant operations, radioactive effluent controls, and environmental monitoring is provided to assist the reader in reviewing this document.
Atoms whose nuclei contain an excess of energy are called radioactive atoms.
They release this excess energy by expelling electromagnetic or particulate radiation from their atomic centers to become stable (non-radioactive).
This process is called "radioactive decay". X-rays and gamma rays are similar in many ways to visible light, microwaves, and radio-waves.
Particulate radiation may be either electrically charged such as alpha and beta particles, or have no charge, like neutrons.
The term "half-life" refers to the time it takes for half of a given amount of a 2
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radionuclide co decay.
Some radionuclides have a half-life as short as a fraction of a 'second, while' others have a I
half-life as long as millions of years.
Radionuclides may decay directly into stable elements or may undergo a series E
of decays which ultimately end up reaching a stable element.
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Radionuclides are found in nature (e.g. radioactive uranium,
and may also be produced artificially in acce:.erators and. nuclear reactors (e.g.,
The activity.of a radioactive source is the number of nuclear-I disintegrations (decays) of the source per unit of time.
The unit-of activity is the. curie.
A one curie radioactive source undergoes 2.2 trillion disintegrations per minutei but in the realm of nuclear power plant effluents and I
environmental radioactivity, this is a large. unit.
So, two fractional units, the-microcurie and the picocurie, are more commonly used.
The microcurie (uCi) is one millionth of a I
curie (Ci) and represents 2.2 million decays per minute.
The picoeurie (pCi) is one nillionth of a
microcurie and represents 2.2 decays per minute.
Another way of comparing
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the pCi and the Ci'is by analogy with distances.
A pCi would W
be the width. of a pencil mark while a curie would be 100 trips around the earth.
The mass of a radionuclide corre sponding to the curie is directly proportional to the half-life and the atomic weight of the nuclide.
For example.
Uranium-235 (U-235) with a I
half-life of 704 million years requires about 462,400 grams te obtain an activity of one curie.
But I-131 with a half-life of 8.04 days only requires about
.003 grams to produce an activity of one curie.
Any mechanism that can supply the energy necessary to ionize an atom, break a chemical bond, or alter the chemistry of a I
living cel1 is capable of producing biological damage.
Electromagnetic and particulate radiation can produce cellular damage by any of these mechanisms.
In assessing the I
biological ef fects of radiation, the type, energy, and amount of radiation must be considered.
External t o':al body radiation involves exposure of all I
organs.
Most background exposures are of this form.
When radioactive elements enter the body through inhalation or ingestion, their distribution is not uniform.
For example, I
radiciodine selectively concentrates in the thyroid gland, whereas radiocesium collects in muscle and liver tissue, and radiostrontium in mineralized bone.
The total dose to organs by a given radionuclide is also influenced by the quantity and the duration of time that the radionuclide remains in the body.
Owing to radioactive decay and me t abol ism certain radionuclides stay in the body for very short times while others remain for years.
3
The amount of radiation dose which an individual receives is expressed in rem.
Since human exposure to radiation-usually involves very small exposures, the millirem (mrem) is most commonly used.
One millirem is one thousandth of a rem.
C.
Sources of Radiation Exposure Many sources of radiation exposure exist.
The most common and least controllable source is background radiation from cosmic rays and terrestrial radioactivity which mankind has always lived with and always will.
There is no choice.
Every secoad of our lives, over seven thousand atoms undergo radioactive decay in the body of the average adult.
Radioactive elements have always been a part of our planet and everything which has come from the earth including our own bodies is, therefore, naturally radioactive.
Radioactive materials found in the earth's crust today consist of such radionuclides as Potassium-40 (K-40),
Uranium-238 (U-238),
Thorium-232 (Th-232),
Radium-226 (Ra-226),
and Radon-222 (Rn-222).
These radionuclides are introduced into the water,
- J;5 ~
rc e soil, and air by such natural processes as volcanic activity,
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weathering, erosion, and radioactive decay.
i.q Some of the naturally occurring radionuclides, such as radon, y
are a significant source of radiation exposure to the general public.
Radioactive radon is a chemically inert gas produced
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.i naturally in the ground as a part of the uranium and thorium by decay series.
Radon continues to undergo radioactive decay, 7, W ' ; '
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producing" new naturally radioactive materials called "radon daugh ters The.se new materials, which are solid particles,
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not gases, can stick to surfaces such as dust particles in
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the air.
Concentrations of radon in air are variable and Q
are affected by concentrations of uranium and thorium in soil, altitude, soil porosity, temperature, pressure, soil
$Q moisture, rainfall, snow cover, atmospheric conditions, and season.
It can move through cracks and openings into basements of buildings and become trapped in a small air volume indoors.
- Thus, indoor radon concentrations are usually higher than those found outdoors.
Building materials such as cinder blocks and concrete are radon sources.
Radon can also be dissolved in well water and contribute to airborne radon in houses when released through showers or washing.
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Dust containing radon daughter particles can be inhaled and deposited on the surface of an individual's lung.
Radon daughters emit high energy alpha radiation dose to the lung I
lining.
About three hundred cosmic rays originating from outer space l
pass through each person every second.
The interaction of cosmic rays with atoms in the earth's atmosphere produces radionuclides such as Beryllium-7 (Be-7),
Beryllium-10 (Be-10),
and Sodium-22 I
(Na-22).
Portions of these radionuclides become deposited on land or in water while the remainder stay suspended in the atmosphere.
Consequently, there are natural radioactive materials in the soil, water, air, and building materials which contribute to I
radiation doses to the human body.
Natural drinking water contains trace amounts of uranium and radiumi milk contains measurable amounts of K-40.
Sources of natural radiation and I
their average contributing radiation doses are summarized in Table 1.
Radiation exposure levels from natural radiation fluctuate with time and also can vary widely from location to location.
The average individual in the United States I
receives approximately two hundred mrem per year from natural sources.
In some areas of the country, the dose from natural radiation is significantly higher.
Residents of Colorado, I
five thousand feet above sea level, receive additional dose due to the increase in cosmic and terrestrial radiation levels.
In fact, for every one thousand feet in elevation I
above sea level, an individual will receive an additional one mrem per year from cosmic radiation.
In several areas of the l
- world, high concentrations of mineral deposits result 'in natural background radiation levels of several thousand mrem I
per year.
1
a-TABLE 1
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1 COMMON SOURCES OF RADIATION A.
Estimated Annual Effective Dose Equivalent From Natural Sources in Normal Regions Annual effective dose equivalent (mrem)
(
I External Internal hurce Irradiation Irradiation Total Cosmic 30 1.5 31.5 Terrestrial 35 132.6 167.6 I
TOTAL (Rounded) 65 134 199 I
(ICRP84)
I B.
Estimated Annual Dose to Man from Significant I
Manmade Sources of Radiation in the United States Annual effective dose equivalent I
Source (mrem)
Medical Diagnoses 100 Television Viewing 1
Airline Travel 3
Atmospheric Weapons tests (Fallout) 4 I
TOTAL 108 (NR80)
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In addition to natural background radiation, the average individual is exposed to radiation from a number of man-made I
sources.
The largest of these sources comes from medical diagnosis:
X-rays, CAT-scans, fluoroscopic examinations and radio-pharmaceuticals.
Approximately 160 million people in the United States are exposed to medical or dental X-rays in I
any given year.
The annual dose to an individual from such irradiation averages 100 mrem, approximately one half of the sum total of natural radiation.
Smaller doses from man-made I
sources come from consumer products (television, smoke detectors, fertilizer),
fallour from prior nuclear weapons tests, and production of nuclear power and its associated l
fuel cycle.
Fallout commonly refers to the radioactive debris that settles to the surface of the earth following the detonation I
of nuclear weapons.
Fallout can be washed down to the earth's surface by rain or snow and is dispersed throughout the environment.
There are approximately two hundred I
radionuclides produced in the nuclear weapon detonation processi a number of these are detected in fallout.
The radionuclides found in fallout which produce mot
and Cs-137.
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W III.
DESCRIPTION OF THE CLINTON POWER STATION L
General Information - The Clinton Power Station is located in A.
Harp Township, DeWitt County, Illinois.
It is approximately F
six miles east of the city of Clinton, Illinois.
The map coordinates for the reactor are 40' 10' 19.5" North latitude, j
and 88* 50' 3" West longitude.
The station, its V-shaped cooling lake, and the surrounding Illinois Power Company-owned land encloses about 14,182 acres.
This includes the 4,895 acre man-made cooling lake and about 90 acres of privately-owned property.
The Clinton Power Station is sited on approximately 1500 acres on the northern arm of the lake.
The cooling water discharge fiume, which discharges to the eastern arm of the lake occupies an additional 130 acres.
Although the nuclear
- reactor, supporting equipment, and associated electrical generation and distribution equipment lie in Harp Township, portions of i
the 14,182 acres lie in Wilson,
- Rutledge, DeWitt,
- Creek, I
Nixon and Santa Anna Townships.
The cooling lake was formed by constructing an earthen dam l
near the confluence of Salt Creek and the North Fork of Salt Creek.
The resulting lake has an average depth of 15.6 feet, and includes an ultimate heat sink of about 590 acre feet.
1 The ultimate heat sink provides sufficient water volume and i
cooling capacity for approximately thirty days of operation j
without makeup water.
Through arrangements with the Illinois Department of Conservation, Lake Clinton and much of the area immediately adj acent to the lake are used for public recreation activities, including swimming, boating, water skiing and fishing.
Recreational facilities exist at Lake Clinton and accommodate up to 11,460 people per day.
The outflow from Lake Clinton falls into Salt Creek and flows in a westerly direction for about 56 miles before joining the Sangamon River.
The Sangamon River drains into the Illinois River which enters the Mississippi River near Grafton, Illinois.
The nearest use of downstream water for drinking purposes is 242 river miles downstream of Lake Clinton at
- Alton, Illinois.
Although some farms in the Salt Creek drainage area downstream of Lake Clinton use irrigation, the irrigation water is drawn from wells, not from the waters of Salt Creek.
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--A
-A An estimated 810,000 individuals live within 50 miles of the Clinton Power Station.
Over half of these are located in the 7
major metropolitan centers of Bloomington-Normal (located
-'i about 23 miles north northwest), Champaign-Urbana (located g.
about 31 miles east), Decatur (located about 22 miles south southwest) and Springfield (located about 48 miles west southwest).
The nearest city is Clinton, the county seat of DeWitt County, located about 6 miles west of the station.
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The estimated population of Clinton is about 8,000 people.
Outside of the urban areas most of the land within 50 miles of the Clinton Power Station is used for farming.
The 3
principal crops are corn and soybeans.
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The climate of central Illinois is typical of the midwest, 2
with cold winters, warm summers, and frequent short-period
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fluctuations in temperature, humidity, cloudiness, and wind direction.
The variability in central Illinois climate is due to its location in a confluence zone (particularly during the cooler months) between different air masses (BR66).
The "i
specific air masses which affect central Illinois include maritime tropical air which originates in the Gulf of Mexico 0
continental tropical air which originates in Mexico and the
_g southern Rockies: Pacific air which originates in the eastern North Pacific Oceans and continental polar and continental arctic air which originates in Canada.
Monthly streamline analyses of resultant surface winds suggest that air reaching central Illinois most frequently q
originates over the Gulf of Mexico from April through August, "j
over the southeastern United States from September through
- q November, and over both the Pacific Ocean and the Gulf of a N Mexico from December through March (BR66).
3 The major factors controlling the frequency and variation of weather types in central Illinois are distinctly different during two separate periods of the year, j
During the fall, winter, and spring months, the frequency and 2"
variation of weather types are determined by the movement of storm systems which commonly follow paths along a maj or confluence zone between air masses.
The confluence zone is 4E usually oriented from southwest to northeast through the 3
region and normally shifts in latitude during this period, ranging in position from the central states to the United 1
States - Canadian border.
The average frequency of passage um of storm systems along this zone is about once every 5 to 8
,q days.
These storm systems are most frequent during the 5
winter and spring months, causing a maximum of cloudiness
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i during these seasons.
Winter is characterized by alternating periods of steady precipitation and periods ~of clear, crisp, and cold weather.
Springtime precipitation is primarily I
showery in nature.
The frequent passage of storm systems, presence of high winds, and frequent occurrence of unstable conditions caused by the close proximity between warm, moist I
air masses and cold, dry air masses, result in this season's relatively high frequency of thunderstorms.
These thunderstorms on occasion are the source of hail, damaging
- winds, and tornados.
Although storm systems also occur I
during the fall months, the frequency of occurrence during these months is less than that of the win ter or spring months.
Periods of dry weather characterize this season I
which ends rather abruptly with increasing storminess that usually begins in November.
l In
- contrast, weather during the su=mer months is characterized by weaker storm systems which tend to pass to the north of Illinois.
A major confluence zone is not I
present in the
- region, and the region's weather is characterized by much sunshine interspersed with thunderstorme.
Showers and thundersterms are usually of the air mass
- type, although occasional outbreaks of cold air I
bring precipitation and weather typical of that associated with the fronts and storm systems of the spring months.
l When southeasterly and easterly winds are present in central Illinois, they usually bring mild and wet weather.
Southerly winds are warm and showery, westerly winds are dry with I
moderate temperatures, and winds from the northwest and north are cool and dry.
The prevailing wind is southerly at the Clinton Power I
Station.
The frequency of winds from other directions is relatively well distributed.
The monthly average wind speed is lowest during late summer and highest during late winter I
and early spring.
Table 2
presents a summary of climatological data at I
meteorological stations surrounding the Clinton Power Station site.
The annual average temperature at the Clinton Power Station is about 52*F.
Monthly average temperatures in the region range from the middle twenties in January to the I
middle seventies in July.
Extreme temperatures in the region range from a
maximum of 103*F (Peoria) and
-22*F (Springfield).
Maximum temperatures in the Clinton Power I
Station region equal or exceed 90*F on an average between 17 and 28 times per year.
Minimum temperatures in this region are less than or equal to 32'F on an average between 119 and 132 times per year.
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u Humidity varies with wind direction, lower with westerly or
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northwesterly winds and higher with easterly or southerly winds.
The early morning relative humidity is highest during the late summer, with an average of 87% at both Peoria and
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Springfield.
The relative humidity is highest throughout the day during December, ranging from 831 in early morning to 72%
at noon at both Peoria and Springfield.
Heavy fog with visibility less than 1/4 mile is rare, occurring an average of 21 times per year at Peoria and 18 times per year at Springfield and occurring most frequently during the winter months.
Annual precipitation in the Clinton Power Station area averages about 35 inches per year.
On the average, about
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forty five percent of the annual precipitation in the Clinton Power Station region occurs in the 5 month period from April through August.
However, in this region no month averages r
less than 4% of the annual total.
Monthly precipitation L
totals have ranged from 0.03 to 13.09 inches (Peoria).
The maximum 24-hour nrecipitation at either station was 5.52 inches, recorded at Peoria in May 1927.
Snowfall commonly
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occurs from November through March, with an annual average of 23.4 inches at Peoria, and 22.3 inches at Springfield.
[
The monthly maximum snowfall of 18.9 inches at Peoria, and 22.7 inches at Springfield, occurred in December 1973.
The 24-hour maximum snowfall, which also occurred in :)ec ember
- 1973, was 10.2 inches at
- Peoria, and 10.9 inches at r
Springfield.
The terrain in central Illinois is relatively flat and differences in elevation have no significant impact on the general climate.
However, the low hills and river valleys I
that exist cause a small effect upon nocturnal wind drainage patterns and fog frequency.
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TABLE 2 l
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CLIMATOLOGICAL DATA FROM WEATHER STATIONS SURROUNDING THE CLINTON FOWER S,TATION STATION PARAMETER PEORIA SPRINGFIELD Temperature (F')
Annual average 50.8 52.7 Maximum 103 (July 1940) 112 (July 1954) i Minimum
-20 (Jan. 1963)
-22 (Feb. 1963)
Relative Humidity (I)
Annual average at:
6 a.m.
83 82 l
12 noon 62 60 Wind Annual average speed (mph) 10.3 11.4 Prevailing Direction S
S Fastest mile:
I Speed (mph) 75 (July 75 (June Direction NW 1953)
SW 1957)
Precipitation (in.)
Annual average 35.06 35.02 Monthly ma:<imum 13.09 (Sept. 1961) 9.91 (Apr. 1964)
I Monthly minimum 0.03 (Oct. 1964) 0.15 (Dec. 1955) 24-hour maximum 5.06 (Apr. 1950) 5.12 (Sept. 1959)
Snowfall (in.)
Annual average 23.4 22.3 Monthly maximum 18.9 (Dec. 1973) 22.7 (Dec. 1973)
Maximum 24-hour 10.2 (Dec. 1973) 10.9 (Dec. 1973)
Mean Annual (no. of days)
Precipitation
> 0.1 in.
111 112 Snow, sleet, hall
> 1.0 in.
8 8
Thunderstorms 49 50
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Heasy fog (visibility % m. or less) 21 18 Maximum temperature >90*F 17 28
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Minimum temperature 132'F 132 119 The data presented in this table is based upon ref2rence (DOC 76a) and (DOC 76b).
These statistics are based on period.= af record ranging from 17 to 39 years in length.
The ranges span the ; ears 1937 to 1976.
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B.
Climatological Summary - 1987 L
Temperatures in Decatur for the months of January, May, June, July, August and October 1987 averaged below normal, while
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temperatures for the months of
- February, March,
- April, September, November and December all averaged above normal.
Over the year, the average monthly temperature ranged from 28.2'F in January to 77.8'F in July.
The lowest hourly temperature of the year occurred on January 23 when it I
dropped to 2'F.
On June 14, 100'F was recorded, marking the year s highest hourly temperature. (IPC 87)
In Springfield a total of 29.34 (water equivalent) inches of i
precipitation fell during
- 1987, which amounts to approximately 4.44 inches below the annual average.
Monthly precipitation totals ranged from a low of 0.56 inches in May I
to a
high of 5.00 inches in December.
The largest precipitation event came on July 4th when 2.98 inches of rain fell.
The year's heaviest snowfall, measuring 8.0 inches, l
occurred on January 9th. (NWS87)
Annual Joint Frequency Tables for the Clinton Power Station are provided in Appendix G.
These were generated from I
on-site meteorological data.
C.
Nuclear Reactor Operations The fuel of a nuclear reactor is made of the element uranium in the form of uranium oxide.
The fuel produces power by the l
process called "fission".
In fission, the uranium absorbs a neutron (an atomic particle found in nature and produced by the fissioning of uranium in the reactor) and splits to I
produce fission products, heat, radiation, and free neutrons.
The free neutrons travel in the cores further absorption of neutrons by uranium permits the fission process to continue.
As the fission process continues, more fission products, I
radiation, heat, and neutrons are produced and a sustained reaction occurs.
The heat produced is extracted from the fuel to produce steam which drives a turbine generator to I
produce electricity.
The fission products are predominately radioactive they are unstable elements which emit radiation as they change from unstable to stable elements.
Neutrons which are not absorbed by the uranium fuel may be absorbed by stable atoms in the materials which make up' the components
~
and structures of the reactor.
In such cases, stable atoma often become radioactive.
This process ir called "activation" and the radioactive atoms which result are called "activation products".
The reactor at the Clinton Power Station is a boiling water reactor (BWR).
In this type of reactor the fuel is formed into small ceramic pellets which are loaded into sealed fuel rods.
The fuel rods are arranged in arrays called bundles which are supported within a massive steel reactor vessel.
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I l
The spaces between the fuel rods are filled with water.
The heat released during the fission of fuel atoms is transferred to the water surrounding the fuel rods.
A type of pump which I
contains no moving parts (a jet pump),
and recirculation pumps are used to force the water to circulate through the fuel bundles to assure even cooling of the fuel rods.
As the I
water absorbs heat from the fuel rods some of it is changed to steam.
The steam is used to drive a turbine which is i
coupled to a generator thereby completing the conversion of l
the energy released during fission to electricity.
After the steam passes through the turbine it is condensed back to water and returned to the reactor vessel to repeat I
the process.
As the water circulates through the reactor pressure vessel, corrosion allows trace quantities of the component and structure surfaces to get into the water.
The I
corroded material also contains radioactive substances known as activated corrosion products.
Radioactive fission and activation products are normally confined to the primary l
system although small leaks from the primary system may occur.
Figure 1 provides a basic plant schematic for the Clinton Power Station and shows the separation of the cooling water from plant systems.
Figure 2 shows the plant schematic I
in more detail.
D.
Containment of Radioactivity Under normal operating conditions, essentially all radioactivity is contained within the first of several l
barriers of ' the primary system which collectively prevent escape of radioactivity to the environment.
The fuel cladding (metal tubes) provides the first barrier.
I The ceramic fuel pellets are sealed within Zircaloy metal tubes.
There is a
small gap between the fuel and the 3
cladding in which the noble gases and other volatile nuclides collect.
The reactor vessel and the steel piping of the primary coolant system provide the second barrier.
The reactor pressure vessel is a seventy-foot high vessel having steel walls approximately four to seven inches thick encasing the reactor core.
This system provides containment for all radionuclides in the primary coolant.
The Containment Building provides the third barrier.
The Containment Building has steel-lined, four foot thick reinforced concrete walls which completely enclose the reactor vessel and vital auxiliary equipment.
This structure provides a third line of defense against the uncontrolled release of radioactive materials to the environment.
The massive concrete walls also serve to absorb much of the radiation released during reactor operation or from radioactive materials created during reactor operation.
14
Mhh ' M M
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i FR F1 F1 F
CCeITAINMENT BUli. DING 1
Steam M h ' D / M 4' W
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Reactor
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Fuel As?cmbles
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- ig?! h; w"
Pump Steam Derven Turbine l
l O'
l O
l d
C ndenser l
Strol Rods Q...
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I Condenser FIGURE 1:
CLIfff0N POWER STATION BASIC PLANT SCHDIATIC 1:0TE:
The condenser cooling water (lake water) is separated from the reactor plant water systems by a physical barrier
l ll I
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Collectively, these three successive barriers provide in-depth protection against unewatrolled release of radioactivity, even in instances of accident conditions I
involving loss of primary coolant.
.,)
E.
Sources of Radioactive L,iquid ar.d Gaseous Effluents
}
k '.
1 s q!
e In a normal operating nuclear power plant, most of the C
E fission products are retained within the fuel and fuel n
3 cladding.
- However, the fuel manufacturing process leaves h* *$
traces of uranium on the exterior of the fuel tubes.
Fission
- : ' t..
g products from thu eventual fission of these traces may be 14 I
released to the primary coolant, other small amounts of
- y..;
radioactive fission aroducts are able to diffuse or mi' rate lh*'
through the fuel c:. adding and into the primary cooIant.
MYN I
Trace quantities of the corrosion products from component and ym e.T[W structural surfaces which have been activated, also get into the primary coolant water.
Many soluble fission and activation products such as radioactive iodines, strontiums, A'
I
$4 purification systems.
The noble gas fission
- products,
...#4?>
activated atmospheric gases introduced with reactor 1.99 I
b (~
feedwater, and some of the volatile fission products such as 4
iodine and bromine, are carried from the reactor vessel to the condenser with the steam.
The steam jet air ejectors or pf.h I
condenser vacuum pump remove the gases from the condenser and
[.
,a
, g; /,5 transfer them to the off-gas treatment system.
In the off-gas treatment system the gases are held up, by adsorption B
on specially treated charcoal, to allow the radioactive gases
- ']
to decay before they are released through the main y
ventilation exhaust stack.
9, /
2na Small releases of radioactive liquids from valves, piping, or W%
equipment associated with the primary coolant system may y
occur in the Containment, Auxiliary, Turbine, RadWaste and o.
Fuel Buildings.
The noble gases become part of the gaseous
' p[
wastes while the remaining radioactive liquids are collected a$
~
in floor and equipment drains and sumps and are processed prior to release.
Processed primary coolant water that does
( ! ~.;
not meet chemical specifications for reuse may also become lO
'#N wasce water.
These represent the principal sources of liquid cffluents.
F.
Radioactivity Removal from Liquid and Gaseous Wastel In a normal operating nuclear power plant, radioactive liquid and gaseous wastes are collected,
- stored, and processed through processing systems to remove or reduce most of the radioactivity (exclusive of tritium) prior to reuse within the plant or discharge to the environment.
These processing systems are required by the Technical Specificttions to be installed and operable and help to ensure all releases of a
radioactive liquid and gaseous effluents are As Low As Reasonably Achievable (ALARA).
17
u The licuid waste processing system consists of
- filters, demineralizers, and evaporators so that liquid wastes are filtered, distilled, and demineralized.
The liquid waste is r
routed through the waste evaporators to degas and distill the L
waste to reduce its volume and concentrate the radioactivity.
The distillate is further processed through demineralizers and transferred to the waste evaporator condensate storage tanks.
Liquid wastes are processed through the appropriate portions of the liquid waste treatment system to provide assurance that the releases of radioactive materials in liquid effluents will be kept ALARA.
Liquid wastes are discharged into the plant cooling water stream which varies from 22,000 gallons per minute, when the plant is in cold shutdown, to 567,000 gallons per minute, when the plant is at r
L full power.
The liquid effluents are thoroughly mixed with, and diluted by, the plant cooling water as it travels the 3.4 miles of discharge canal before it enters Lake Clinton east of DeWitt County Road 14.
Federal regulations (CFR) and the Technial Specifications (NUREG86) require that liquid I
effluents shall not contain a nigher concentration of any radioisotope than that set for continuous exposure to the general public.
This condition is satisfied ac the point the liquid effluent in first introduced into the cooling water I
flow.
The dilution which occurs in the cooling water canal reduces the concentrations of radioisotopes to between 1/73 (minimum flow) and 1/1890 of their original value before the I
water enters Lake Clinton.
The concentrated radioactive solids captured in the liquid waste treatment system are solidified and shipped off-site I
for disposal at one of the icw-level waste disposal facilities.
The gaseous effluents from the main condenser are held up in the off-gas charcoal beds for at least 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br />.
This provides time for the decay of most of the radionuclides I
present since most have a half-life of less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
If-gaseous effluents in the ventilation exhaust system for the Containment Building and the Secondary Containment structure exceed conservatively set levels, they are processed through I
charcoal beds and high efficiency particulate air filters in the Standby Gas Treatment System before being discharged to the environment.
This combination of filters and charcoal I
beds is rated to be 95% efficient for removing iodines and greater than 99% efficient for removing particulate material larger than one micron (one millionth of an inch) in diameter.
95 18
I IV.
EFFLUENTS L
The Clinton Power Station releases small quantities of radioactive material in the course of normal operation.
These releases are referred to as the effluent.
Two kinds of effluent are generated, I
liquid and gasecus.
The effluent is measured by an extensive network of radiation monitoring equipment, designed and calibrated to work both during normal and accident conditions.
Both liquid and gaseous radioactive effluent released from the Clinton Power Station during 1987 are list.ed in Table 3.
These data were compiled from references CL87a and CL87b.
No release exceeded or even approached the litits specified in regulations or in the cnarating license.
The releases made to the I
environment were so smcil that they were not detectable in the environmental samples collected in the Radiological Environmantal Monitoring Program.
Radionuclides released in the gaseous effluent were predominantly noble gases with short half-lives.
A total of 6.8 Ci of noble gases were released.
Xenon-135 with a 9.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> half-life was the I
highest with 5.08 Ci released.
' Tritium was the most prominent radionuclide in the liquid effluent.
The quantity of tritium released was 1.87 curies.
I I
e 19 I
__J
M TABLE 3 l
RADIONUC'LIDE COMPOSITION OF CPS EFFLUENTS IN 1987 Radionuclide Half-Life Gaseous Effluents (C1)
Liquid Effluents (Ci)
Tritium 12.3y 2.62E-1 1.87E+0 Fission and Activation Products:
I;rypton-85m 4.Sh 5.77E-3 Xenon-133 5.2d 4.91E-1 Xenon-135 9.lh 5.08E+0 2.21E-6 Argon-41 1.8h 1.25E+0 Iodine-131 8.0d 4.08E-5 Iodine-133 20.8h 6.44E-5 Strontium-89 50.6d 6.73E-4 1.21E-4 Strontium-90 28.6y Sodium 24 15.0h 1.24E-3 5.61E-5 Ce rium-14 3 33.0h 6.32E-7 Chromium-51 27.7d 1.82E-4 1.14E-2 Manganese-54 312.7d 3.57E-5 1.47E-3 Techretium-99m 6.Oh 1.0IE-4 7.14E-5 Cesium-138 32.2m 4.11E-3 Barium-139 83.lm 2.29E-4 Yttrium-91m 49.7m 1.22E-5 Arsenic-76 23.3h 2.20E-5 3. '60 E-4 Cobalt-58 70.8d 9.73E-5 Coba1t-60 5.3y Iron-59 44.6d 1.04E-4 9.80E-4 Iron-55 2.7y
- Isotopes no* detected in effluents released from the Clinton Power Station e
20 J
m u
V.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 7
A.
Program Description The Clinton Power Station is required to maintain a
radiological environmental monitoring program in accordance with the Code of Federal Regulations (CFR) Title 10, Section 20.201 and Criterion 64 of CFR Title 10, Part 50, Appendix A.
The program was developed using the following guidance published by the United States Nuclear Regulatory Commission (USNRC):
Regulatory Guide 4.1, "Programs for Monitoring Cadioactivity in the Environs of Nuclear Power Plants" USNRC Radiological Assessment Branch Technical Position on Radiological Environmental Monitoring (1979)
The basic purpose of the program ie to assess the environmental radiological impact due to operation of the Clinton Power Station.
Implicit in this purpose is the requirement to trend and assess radiation exposure rates and radioactivity concentrations that may contribute to human radiation exposure.
The program consists of two
- phases, preoperational and operational.
The preoperational portion of the program has established the baseline for the local radiation environment.
Assessment of the operational impact of the Clinton Power Station on the radiation environment is based on data collected since the reactor started.
The operational phase includes the obj ective of making confirmatory measurements to verify the in-station controls for the release of radioactive material are functioning as designed.
Figure 3 shows the basic pathways of gaseous and I
liquid radioactive effluents to man.
Design Current regulatory guidance recommends evaluating direct pathways, or the highnet trophic level in a dietcry pathway, l
that contribute to an individual's dose.
The "important selected based primarily on how radionuclides pathways" are move through the environment and eventually expose individuals, as well as man's use of the environment.
The I
scope of the program includes the monitoring of five environmental compartments:
direct radiation, atmospheric,
- aquatic, terrestrial and groundwater.
Each pathway is I
monitored at "indicator" and "control" locations.
Indicator locations are generally within the 10-mile radius of the station.
Control locations are located at least ten miles l
from the
- plant, far enough to be unaffected by plant operations.
An increase in dose rate or radioactive material concentration at an indicator location may be due to plant I
operations.
Locations of sampling stations are shown on maps in Figures 4 through 8.
A key to the maps specifying exact locations is contained in Appendix A Table A-1.
21
WM M
M M
Miin i
U O
O V 1 I
RELEASES DILUTED BY ATMOSPHERE l
AIRBORNE RELEASES CLINTON POWER ANIMALS (MILK, MEAT)
PLUME EXP SURE STATION CGNSUMED L
BY PEOPLE
\\
lj N
RE ES
?
PEOPLE g
RELEASES
' CONSUMED DILUTED CONSUMED BY PEOPLE BY LAKE
~.
BY ANIMALS AT R B PEOPLE FISH
/
s== I-xGP e
1 FIGURE 3:
POTENTIAL EXPOSURE PATHWAYS OF MAN DUE TO RELEASES OF RADIOACTIVE MATERIAL TO THE ENVIRONMENT
m An on-site meteorological tower collects information such as
{
wind speed, wind direction and air temperature at various levels.
F Meteorological conditions are measured every ten seconds and L
averaged over a ten minute period before data is transmitted to a computer for permanent record storage.
Meteorological data are used in the atmospheric dispersion model for gaseous
[
effluents.
Table 4 provides the summary of the Clinton Power Station
[
Radiological Environmental Monitoring Program from initial criticality to.the end of 1987.
Direct Radiation Compartment
{
Radionuclides present in the air, and those deposited in or on the ground cause human exposure by immersion in the 7
atmosphere or by depositien on the ground.
In general, TLDs are used to characterize direct radiation dose due to photons and electrons.
Atmospheric Compartment E
The inhalation and ingestion of radionuclides present in the L
atmosphere is a direct exposure pathway to man.
The program monitors this pathway by maintaining a network of nine active air samplers around the Clinton Power Station.
Eight rL indicator air samplers are located in sectors around the station which can be affected by station operation.
The ninth control sampler is located' upwind, away from routine station influence.
These mechanical air samplers continuously pump a known volume of air through two filters designed to collect particulates and radiciodine present in F
the local atmosphere.
Analysis of the filters provides information regarding the concentration of radioactive material in the air.
L Aquatic Compartment Lake Clinton represents the primary pathway for radioactive material in Sater_ to expose individuals engaged in
~
recreational activities.
The exposure pathways monitored by the program are fish, aquatic organisms, periphyton, lake E
bottom
- sediment, shoreline sediment and lake water.
An indicator and control location are sampled.
Radionuclides present in lake water are concentrated by biological (fish 7
and periphyton) and physical (sediment) processes which could L
eventually cause human exposure and dose equivalent by inge s tion, immersion or ground plane exposure.
r L
m 23 r~
L
FL
[
Terrestrial Compartment In addition to the direct radiation compartment, radionuclides present in the atmosphere expose individuals when these radionuclides deposit on surfaces (such as plants and soil) and are subsequently ingested directly by man or indirectly by consumption of animal products such as meat and milk.
To monitor this food pathway, control and indicator samples of green leafy vegetables, grass, milk (control only) and meat (indicator only) are analyzed.
Surface soil samples are collected at three year intervals to monitor the potential buildup of atmospherically deposited radionuclides.
No soil surface samples were collected in 1987.
b Groundwater Compartment Well water is sampled and analyzed to monitor the
{
radionuclides being ingested by individuals consuming the water.
The wells supplying water to the Village of DeWitt and the Mascoutin recreation area were the indicator sample r
locations.
Surface water samples of the station liquid L
effluent discharge flume are obtained to monitor the quality of water being discharged to Lake Clinton.
Control samples of surface water were also obtained.
The program sampling locations and results are described in I
Appendix A.
A summary of program elements (sample types, assays performed, analysis frequen'cy) is provided in Table A-2.
B.
Quality Assurance Program To establish confidence that data developed and reported in I
the Radiological Environmental Monitoring Program are accurate and precise, all Program activities are incorporated into the Illinois Power Company quality assuranco (QA) program of audits and surveillances.
The quality assurance program requires:
The analysis laboratory to participate in intercomparison I
programs such as performance testing for TLDs with the EPA crosscheck program.
An annual audit of the analysis laboratory functions and facilitie s.
Biennial review of the Clinton Power Station procedures I
specifying sampling techniques.
That the analysis laboratory perform duplicate analysit-I of every tenth sample assayed (not including TLDs).
This requirement is to check laboratory precision.
That quality control samples be routinely counted.
Approximately ten percent of the total number of counts performed are to be quality control counts.
r
r The analytical results were routinely reviewed by the E
Radiological Environmental Group of the Radiation Protection Department to ensure the required minimum sensitivities have been achieved and the proper analyses have been performed.
Teledyne Isotopes Midwest Laboratory (TIML) participates in the Environmental Protection Agency crosscheck program.
The TIML participant code in the crosscheck program is CA.
Participation in this program provides assurance that the laboratory is capable of meeting widely-accepted criteria for I
precision and accuracy needed to perform valid environmental radioactivity analysis.
Results of the 1987 crosscheck program and other in-house quality programs are shown in I
Appendix E.
The results presented in Appendix E indicate that TIML is l
capable of routinely performing high quality analysis on environmental samples.
I I
I I
25 I
J
r
-' M M
M R
F l V I I
=
J TABLE 4 ENVIRotNENTAL RADIOLOGICAL. HONITORINC PROCRAM ANNUAL
SUMMARY
Name of Facility Clinton Power Station Docket No.
50-4o1_
1 Location of Facility Dewitt, tilinois Reporting Period February 27 - December 3*,
1987 (County, State)
Medium or Type of Lower Limit All Indicatar Location with Control Number of locations:
Nonroutine Pathway Sarepled Analysis of Locaticns:
Highest Annual Mean (Unit of Total Nasnber Detection Mean Name Mean Mean Reported Measurement)
Performed (LLD) f Distance f
f Measurements Directi on Range Range Range 19.5 (296/298)(a)(f)
CL-34 23.2 (4/4)(a) 18.8 (8/8)(a) 0 l
Direct Radiation TLD 306 NA (11.3 - 27.6) 0.8 miles WNW (18.1 - 27.6)
(11.8 - 24.0)
(nR/Otr) l 0.026 (348/352)(b)
CL-11 0.028(44/44) 0.028 (44/44) 0 Qir Pagticulates (0.008 - 0.054) 16 miles S (0.014 - 0.058) (0.014 - 0.058)
Cross Beta N
(pCl/m )
396
<n Gamma Spec 36 1
0.08 (32/32)
CL-6 0.09 (4/4) 0.08 (4/4) 0 (0.05 - 0.14) 0.8 miles WSW (0.05 - 0.12)
(0.07 - 0.09)
Be-7 K-40 0.05 0.04 (2/32)
CL-2 0.05 (1/4)
LLD 0
(0.03 - 0.05) 0.7 miles NNE Co-60 0.003 LLD LLD LLD 0
1 Radiolgdines 3%
1 (pCi/m )
' =
I t.
s
., l L
W W
W W
W M
l' f U T f
TABLE 4 ENVIRott4 ENTAL RADIOLOGICAL MONITORING PROCRAM ANNUAI SUPNARY Name of Facility Clinton Power Station Docket No.
50-461 Location of facility Dewitt. Illinois Reporting Period February 27 - December 31. 1987 (County, State)
Hediun or Type of Lower Limit A'1 Indicator Location with Control Nunber of
{
P:thway Sampled Analysis of Locations:
Highest Annual Mean Locations:
Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported f_
Measurements Measurement)
Performed (LLD) f, Distance Range Direction Range Range Surface Water Cross Beta 1.6 2.3 (52/52)
CL-93 3.0 (2/2) 2.2 (8/10) 0 (pC1/1) 62 (1.1 - 5.0) 0.4 miles SW (2.8 - 3.2)
(1.3 - 3.4)
Gross Alpha 2.0 1.4 (5/20)
CL-91 2.6 (1/10)
N/A 0
20 (1.0 - 2.6) 6.4 siles ENE y
4 Tri tiun 190 152 (1/38)
CL-93 152 (1/2)
LLD 0
0.4 miles SW 38 I-131 0.5 LLD LLD LLD C
10 Cansna Spec 62 Be-7 26.2 LLD LLD LLD 0
fe-5?
12.0 Lif LLD LLD 0
Co-58 5.0 LLD LLD 1LD 0
I i.
I
6 M
M M
M W
F f l I
TABLE 4 ENVIROPNENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
Name of Facility Clinton Pou r Station Docket No. 50-461
- ocation of facility Dewitt, Illinois Reporting ?eriod February 27 - necember 31, 1987 (County, State)
Meditan or Type of Lower Limit All Indicator Location with Control Number cf Pathway Sanpled Analysis of Locations:
Highest Annual Mean Locations:
Nonroutine (Unit of Total Ntrnber Detection Mean Name Mean_
Mean Reported Measurement)
Performed (LLD) f Distance f
f Measurements Range Direction Range Range Surface Water
(con't) (pCI/1)
l l
Drinking Water Cross Beta 0.4 1.6 (9/10)
CL-14 1.6 (9/10)
N/A 0
oo (pC1/1) 10 (0.6 - 1.9)
O miles (0.6 - 1.9) l h)
Gross Alpha 0.7 1.8 (1/10)
CL-14 1.8 (1/10)
N/A 0
0 mi'as 10 l
1 4
Canma Spec 10 Be-7 22.t LLD LLD N/A 0
Fe-59 12.0 LLD LLD N/A; O
Co-58 5.0 LLD LLD N/A 0
Zn-65 6.0 LLD LLD N/A 0
Nb-95 10.0 LLD LLD
.N/A 0
Zr-95 10.0 LLD LLD N/A 0
Cs-134 5.0 LLD LLD N/A 0
{,
f Cs-137-5.0 LLD LLD N/A 0
I i
1
~
y 3
m m
i n
FT W
R Fl J l I
TABLE 4 ENVIR0rNENTAL RADIOLOGICAL HONITORING PROCRAM ANNUAL
SUMMARY
Name of Facility Clinton Power Station Docket No.
50-461 Location of Facility Dewitt, Illinois Reporting Period February 27 - December 31, 1987 (County, State)
Medim or Type of Lower Limit All ladicator Location with Control Ntznber of Pathway Sampled Analysis of Locations:
Highest Annual Mean Locations:
Nonroutine (Unit of Total Ntsnber Detection Mean Name Mean l'.ean
, Reported Measurement)
Performed (LLD) f Distance f
f Measuranents Range Diration Range Range Drinking Water Ba-140 60.0 LLD LLD N/A 0
(con't) (pC1/1)
La-140 15.0 LLD LLD N/A 0
LLD N/A 0
Ce-144 22.1 LLD MW Well Water Cross Beta 3.8 2.5(21/34)
CL-12 (T) (c) 2.7 (7/10)
N/A 0
l (pC1/1) 34 (1.0 - 3.2) 1.6 miles E (7.3 - 3.2)
Cross Alpha 3.2 LLD LLD N/A 0
32 1-131 0.5 L1D LLD N/A 0
54 LLD N/A 0
Tritium 190 LLD 12 Camma Spec 34 Be-7 29.0 LLD LLD N/A 0
I l
Fe-59 12.0 LLD LLD N/A 0
Co-58 5.0 LLD
?.LD N/A 0
Zn-65 6.0 LLD LLD N/A 0
3 UD N/A 0
g, l Hb-95..
- 10.0 LLD 8
l 4
WM M
M M
W M
(
f l l
TABLE 4 ENVIRONMENTAL RADIOLOGICAL HONITORING PROGRAM ANNUAL
SUMMARY
Name of Facility Clinton Power Station Docket No. 50-461 l
Location of Facility Dewitt, Illinois Reporting Period February 27 - December 31, 1987 (County, State)
Medium or Type of Lower Limit All Indicator Locatio. with Control Number of Pathwsy Sampled Analysis of Locations:
Highest Annual Nean Locations:
Nonroutine*
(Unit of Total Ntznber Detection Hean Name Mean Mean Reported Measur m nt)
Performed (LLD) f, D_i_ stance f
f Measurements Range Direction Range Range Well Water Zr-95 10.0 LLD LLD N/A 0
(con't) (pC1/1)
Cs-134 5.0 LLD LLD N/A 0
Ba-140 60.0 LLD LLD N/A 0
La-140 15.0 LLD LLD N/A 0
o Ce-144 25.4 LLD LLD N/A 0
Milk (e) 1-131 0.5 N/A N/A N/A LLD 0
(pCi/1) 18 Sr-90 (d)
N/A N/A N/A 2.4 (5/5) 0 (2.3 - 2.5) 5 Cama Spec 18 Be-7 28.0 N/A N/A N/A LLD 0
K-40 N/A N/A N/A 1213 (18/18) 0 (1110 - 1290)
Fe-59 12.0 N/A N/A N/A LLD 0
Co-58 5.0 N/A N/A N/A LLD 0
Zn-65 9.7 N/A N/A N/A LLD 0
Nb-95 10.0 N/A N/A N/A LLD 0
Zr-95 10.0 N/A N/A N/A LLD 0
g i Cs-134 5.0 N/A N/A N/A LLD 0
- 'I
WW M ' ~~ ~ M M--
M MR f 1 I
TABLE 4 FNVIROt24 ENTAL RADIOLOGICA' HONITORING PROGRAM At#4UAL SUtt4ARY Name of Facility Clinton Power Station Docket No.
50-461 Location of Facility Dewitt, Illinois Reporting Period February 27 - December 31, 1987 (Cnunty, State)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sanpled Analysis of Locations:
Highest Annual Hean Locations:
Nonroutine (Unit of Total Number Detection Hean Name Mean He.n Reported Measurement)
Performed (LLD) f_
Distance f
f Heasurements Range Direction Range Range Milk Cs-137 5.0 N/A N/A N/A LLD 0
(con't) (pCl/1)
Ba-140 60.0 N/A N/A N/A LLD 0
La-140 15.0 N/A N/A N/A LLD 0
Ce-144 23.0 N/A N/A N/A LLD 0
w F*
F1sh Caarna Spec l
I (pCi/g net) 16 Be-7 0.092 LLD LLD LLD 0
K-40 2.60 (8/8)
CL-19 2.60 (8/8) 2.50 (8/8) 0 (2.24 - 2.88) 3.4 miles E (2.24 - 2.88)
(1.38 - 3.25)
Fe-59 0.048 11D LLD LLD 0
Zn-65
I Nb-95 0.018 LLD LLD
- LLD, O
La-140 0.012 LLD LLD
.LLD 0
6 f Ceg 41
5
wn m
m e
amm t
FT I
1 1
TABLE 4 ENVIR0tMENTAL RADIOLOGICAL MONITORINC DROCRAM ANNUAL SUP94/RY Name of Facility Clinton Power Station Docket No.
50-461 Location of R cility Dewitt, Illinois Reporting Period February 27 - December 31, 1987 (County, State)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analysis of Locations:
Highest Annual Mean Locations:
Noorouttrie (thit of Total Number Detection H-an Name Mean Mean Reported Measurement)
Performed (LLD) f_
Distance f
f Measurements Range Direction Range Range Fish Ce-144 0.63 LtD LLD LLD C
(con't) (pCi/g) l l
Bottom Sediment Cross Beta 18.4 (10/10)
CL-105 27.0 (2/2) 27.0 (2/2) 0 m
(pCl/g dry) 12 (9.7 - 27.9) 50 miles S (26.1 - 27.9)
(26.1 - 27.9)
Cross Alpha 6.2 (10/10)
CL-105 11.2 (2/2) 11.2 (2/2) 0 12 (2.6 - 9.0) 50 miles S (8.8 - 13.5)
(8.8 -- 13.5)
Sr-90 0.014 0.047 (6/10)
CL-89 0.060 (1/7) 0.042 (2/2) 0 12 (0.010 - 0.060) 3.6 miles NNE (0.040 - 0.044)
Cann Spec 12 l
l Be-7 0.62 0.31 (1/10)
CL-7c 0.31 (1/2)
LLD 0
1.3 miles SE K-40 13.6% (10/10)
CL-105 17.44 (2/2) 17.44 (2/2) 0 (8.17 - 17.26) 50 miles 5 (15.80 - 19.08) (15.80 - 19.08) l Mn-54 0.090 LLD LLD LLD 0
Co-60 0.039 LLD LLD LLD-0 Zn-65 0.033 LLD LID LLD 0
i Zr-95*
p s
4'
7. Fl FR TR F l R
FR. Fl F7 I l _.. FR n.
F~ l n
FT TTL,J~l
.n
.n P
I TABLE 4 ENVIRONMENTAL RADBOLOGICAL MONITORING PROCRAM Ape 1UAL SUlWARY I
{
Name of Facility Clinton Power Station Docket No.
50-461 Location of Facility Dewi tt, Illinois Reporting Period February 27 - December 31. 1987 (County, State) i Medium or Type of Lower Limit All Indicator Location with Control Number of s
l Pathway Sampled Analysis of Locations:
Highest Annual Mean Locations:
Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement)
Performed (LLD) f Distance f
f_
Measurements Range Direction Range Range LLD LtD 0
Bottom Sedfeent Cs-134 0.037 LLD (con't)
Cs-137 0.01 7 0.32 (8/10)
CL-10 0.58 (2/2) 0.$U (2/2) 0 (pCi/g dej)
(0.07 - 0.58) 5.0 miles EIE (0.58 - 0.58)
(0.40 - 0.59)
LLD LLD 0
Ba-140 0.12 LtD w
AC-228 0.061 0.95 (9/10)
C1 -10 1.33 (2/2) 1.25 (2/2) 0 (0.38 - 1.44) 5.0 mile ENE (1.22 - 1.44) (1.05 - 1.45)81-212 0.54 LtD LLD LLD 0
+
Bi-214 0.56 0.65 (8/10)
CL-10 0.83(2/2) 0.74 (2/2) 0 (0.23 - 0.93) 5.0 elles ENE (0.73 - 0.93)
(0.66 - 0.82)
Pb-212 1.04 (10/10)
CL-10 1.78 (2/2) 1.64 (2/2) 0 (0.34 - 1.85) 5.0 miles ENE (1.71 - 1.65)
(1.31 - 1.97)
Pb-214 0.67 (10/10) 0.-10 0.98 (2/2) 0.84 (2/2) 0 (0.25 - 1.09) 5.0 mile ENE (0.88 - 1.09)
(0.73 - 0.96)
Ra-226 1.64 (10/10)
CL-10 2.38 (2/2) 2.23 (2/2) 0 (0.61 - 2.48) 5.0 miles EE (2.29 - 2.48)
(1.80 - 2.66)
TI-208 0.79 (10/10)
CL-10 1.38 (2/2)
, 1.24 (2/2) 0 (0.12 - 1.45) 5.0 miles EE (1.32 - 1.45)
(0.98 -~1.50) 1 I
l.
I i.*
8
- '4-f
MM M
M M
M i
fR f~
l I
[
TABLE 4 ENVIR0tNENTAL RADIOLOGICAL MONITORING PROCRAM ANNUAL
SUMMARY
Name of Facility Citnton Power Station Docket No.
50-461 Location of Facility Dewitt, filinois Reporting Period February 27 - December 31, 1987 (County, State)
Medlun or Type of Lower Limit All Indicator Location w?th Control Number of Pat %ay Sampled Analysis of Locations:
Highest Annual Mean Locations:
Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement)
Performed (LLD) f_
Distance f
f Measurements Range Direction Range Range Shoreline Sediment Cross Beta 10.0 (12/12)
CL-89 13.1 (2/2) 9.8 (2/2) 0 l
(pC1/g dry) 14 (3.9 - 13.2) 3.6 miles NNE (13.0 - 13.2)
(9.0 - 10.6)
Cross Alpha 3.3 3.4 (6/12)
CL-7d 4.6 (1/2) 3.4 (1/2) 0 14 (2.6
- .6) 2.3 miles SE y
A Sr-90 0.017 0.010 (6/12)
CL-99 0.018 (1/2)
LLD 0
14 (0.002 - 0.018) 3.6 miles NNE l
Gama Spec 14 Be-7 0.13 0.31(1/12)
CL-89 0.31 (1/2)
LLD 0
3.6 miles NNE K-40 7.94 (12/12)
CL-89 10.34 (2/2) 8.69 (2/2) 0 (5.89 - 11.50) 3.6 miles NNE (9.19 - 11.50)
(7.23 - 10.15)
Nb-95 0.023 L1D LLD LLD 0
Cs-137 0.021 0.025 (1/12)
CL-89 0.025 (1/2)
LLD 0
I 6
i T
0
3 m
M M
1 R
R f 1 F 1 J7 f 7 f 1 T-T I-T n"
n o
m i
TABLE 4 ENVIR0tNENTAL RADIOLOGICAL MONITORINC PROGRAM ANNUAL SUPNARY Name of facility Clinton Power Station Docket No.
50-461 Location of Facility Dewitt, 111tnois Reporting Period February 27 - December 31, 1987 (County, State)
{
l Medlun or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analysis of Locations:
Highest Annual Mean locations:
Nonroutine (Unit of Total Nunber Detection Mean Name Mean Mean Reported Mea surement )
Performed (LLD) f, Distance f
f Measurements Range Direction Range Range Shoreline Sediment Ba-140 0.066 LtD LLD LLD 0
(con't)
(pCl/g dry)
Ac-228 0.098 0.26 (8/12)
CL-89 0.35 (2/2) 0.26 (1/2) 0 (0.19 - 0.36) 3.6 miles NNE (0.34 - 0.36) w t.n Bi-212 0.27 LLD LLD LLD 0
l B1-214 0.051 0.18 (6/12)
CL-89 0.28 (1/2) 0.17 (1/2) 0 (0.14 - 0.28) 3.6 alles NNE Pb-212 0.26 (12/12)
CL-S9 0.44 (2/2) 0.24 (2/2) 0 (0.13 - 0.45) 3.6 miles NNE (0.42 - 0.45)
(0.15 - 0.32)
Pb-214 0.22 (12/12)
CL-10 0.34 (2/2) 0.16 (2/2) 0 l
(0.12 - 0.45) 5.0 miles ENE (0.22 - 0.45)
(0.13 - 019)
Ra-226 0.32 0.54 (8/12)
CL-89 0.73 (2/2) 0.32 (2/2) 0 (0.39 - 0.84) 3.6 miles NNE (0.62 - 0.84)
(0.20 - 0.44)
T1-208 0.22 (12/12)
CL-89 0.36 (2/2) 0.18 (2/2) 0 (0.11 - 0.38) 3.6 miles NNE (0.34 - 0.38)
(0.13 - 0.24)
I p
s
'4
R R
R R
R.. R R
f~l.
R R
..R R
R R
R R C _...R R
. R.
TABLE 4 ENVIROWtENTAL RADIOLOGICAL JONITORING PROCRAM AleeUAL StM4ARY i
Name of Facility Clinton Power Station Docket L. 50-461 Location of Facility Dewitt,' Illinois Reporting Period February 27 - December 31, 1987 (County, State)
Medium or Type of Lower Limit All Indicator Location with Contro?
Number of Pathway Sampled Analysis of Locations:
Highest Annual Mean Locations:
Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported.
Measurement)
Performed (LLD) f Distance f
f Measurements' Range Direction Range Range t
Aquatic Vegetation Gamma Spec (pCI/g wet) 8 Be-7 0.40 0.62 *2/6)
CL-7c 0.80 (1/2) 0.38 (1/2) 0 (0.44 - 0.80) 1.3 miles SE wm K-40 1.19 (6/6)
CL-105 2.14 (2.2) 2.14 (2/2) 0 (0.58 - 2.21) 50 miles S (1.67 - 2.62)
(1.67 - 2.62)
Fe-59 0.??
Co-5E 0.048 LED LLD LLD 0
O i
Cs-137 0.058 LLD CL-105 0.034 (1/2) -
0.034 (1/2)
O.
1
~
pl 50 miles S a
}
a g
g
'M M
M M
M t
R f l I
TABLE 4 ENVIR0tNENTAL RADIOLOGICAL MONITORING PROGRAM AWUAL
SUMMARY
Name of Facility Cifnton Power Station Docket No.
50-461 Location of Facility Dewitt, Illinois Reporting Period February 27 - December 31. 1987 (County, State)
Medlun or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analysis of Locations:
Mighest Annual Mean Locations:
Nonroutine (Unit of Total Nunber Detection Mean Name Mean_
Mean Reported Measurement)
Performed (LLD) f_
Distance f
f Measurements Range Di recti on Range Range aquatic Vegetation Ba-140 0.16 LLD LLD LLD 0
(pC1/g wet)
(con't)
g J
Creen Leafy and Cross Beta 3.70 (23/23)
CL-117 5.11 (2/2) 3.89 (13/13) 0 Tuberous Vegetables 36 (1.58 - 6.64) 0.9 miles N (3.90 - 6.32)
(1.98 - 7.17)
(pci/g wet)
Camma Spec 36 Be-7 0.090 1.25 (19/23)
CL-117 3.86 (2/2) 1.16 '11/13) 0 (0.15 - 5.12) 0.9 miles N (3.66 - 4.05)
(0.21 - 4.35)
K-4 0 3.41 (23/23)
CL-18 4.44 (12/12) 3.52 (13/13) 0 (1.41 - 13.10) 1.6 miles E (2.39 - 13.10)
(2.15 - 5.71)
a LLD LLD 0
Fe-59 0.037 LLD Cc-58 0.014 LLD LLD LLD 0
]
I Zn-65 *
~s
R R
R R
R R
R..
I l R
R R
R R..
R "R
R R
R E
TABLE 4 ENVIROM9 ENTAL RADIOLOGICAL MONITORING PROGRAM AlelUAL StM4ARY
[
V.
Name of Facility Cilnton Power Station Docket No.
50-461 t
Location of Facility Dewitt. tilinois _ Reporting Period February 27 - December 31. 1987
{
(County, State) 4 i
l Medium or Type of Lower Limit All indicator Location with Control Ntsaber of Pathway Sampled Analysis of Locations:
Highest Annue! Mean
~
Locations:
Nonroutine i
(Unit of Total Number Detection Mean Name-
' Hean
- Mean, Reported l
Measurement)
Performed (LLD) f Distance f
f, Measurements Range DI Netion Range Range Green Leafy and Nb-95 0.015 LLD LLD LLD 3
Tuberous Vegetables j
(pCf/g wet)
Zr-95 0.027 Lt.D LLD LLD 0
{
(con't) jg 1-1 31 0.025 LLD LLD LLD 0
) co Cs-134 0.015 LLD LLD LLD 0
1 Cs-137 0.015 LLD CL-114 0.021 (2/13) 0.021 (2/13) 0 l
12.5 miles SSE (0.026 - 0.026) (0.016 - 0.026) l Ba-140 0.069 LLD LtD LLD 0
La-140 0.088 LtD LLD LLD
'l l
Ce-144 0.088 11D LLD LLD; O
)
}
l Crass Cansna Spec i
(pC1/g wet) 68 l
i 1
Be-7 1.89 (51/51)
CL-2 2.14 (17/17) 1.51 (17/17) 0 (0.05 - 7.58) 0.7 salles NNE (0.05 - 7.58)
(0.49 - 4.17)
J
- i. I 1
j j
s
M M
M M
M M
M l
f I f l f~
TABLE 4 ENVIROtNENTAL RADIOt0CICAL MONITORINC PROCRAM ANNUAL
SUMMARY
Name of Facility Clinton Power Station Docket No.
50-461 Location of Facility Dewitt, 1111nois Reporting Period February 27 - Decanber 31, 1987 (County, State)
(
Medium or Type of Lower Limit All Indicator Location with Control Nunber of Pathaway Sampled Analysis of Locations:
Highest Annual Mean Locations:
Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement)
Performed (LLD) f Distance f
f_
Measurements Range Direction Range Range Crass K-40 6.58 (51/51)
CL-2 6.99 (17/17) 7.01 (17/17) 0 (pC1/g wet)
(3.12 - 17.90) 0.7 miles NNE (3.88 - 17.90)
(4.75 - 14.40) 0 l
(con't)
l
~
Cs-137 0.087 LLD CL-11 0.044 (4/17) 0.044 (4/17) 0 16 miles S (0.009 - 0.069) (0.009 - 0.069)
- j. I a
- 'g g
R
.F1 f 1 1
MM M
M M
M TABLE 4 EtNIR0tNENTAL RADIOLOGICAL MONITORINC PROGRAM AtNUAL
SUMMARY
Name of Facility C'inton Power Station Docket No.
50-401 Location of Facility Dewitt, Ill inoi s Reporting Period February 27 - December 31, 1987 (County, State) i Medium or Type of Lower Limit All Indicator Location with Control N mber of Pcttweay Sampled Analysis of Locations:
Highest Annual Mean Locations:
Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Mecsurement)
Performed (LLD) f Distance f
f Mr.ssurements Range Di recti on Range Range Grass La-140 0.039 LLD LLD LLD 0
(pC1/g wet)
(con't)
$ Colen 1 Column 2 Column 3 Column 4 Column 5 Column 6 Column 7 TABLE EXPLANATIONS:
Example:
The unit of Measurement describes all the nunerical vglues for LLD, Mean and Range repogted for a particular. ample medium.
Column 1:
the Cross Beta LLD in AIR PARTICULATES is 0.010 pC1/m. Abbreviations used are pC1/m = picocurie per cubic meter of sampled air; nR/ quarter = exposure measured for calendar quarter period (3 months); pC1/L = picoeurie per liter of sample; pC1/g = picoeurie per gram of sample.
Camma Spec. = measurement of each radioisotooe in a sample using Cama Spectroscopy; The Type of Analyses are described as follows:
Col mn 2:
Cross Beta = measurement of the radioactivity in a senple by measurement of emitted betas - no determination of individual Tritium = measurement of tritium (H-3) in sample by liquid scintillation counting methods TLD = direct radioisotopes is possible; measurement of gamma exposure using thermoluminescence dosimeters.
LLD reported is the highest of those reported for each type cf analysis during the year; if all analyses reported positive values, no Colunn 3:
l LLD is reported.
j Samples taken at Indicator Locations during an operational radiological environmental monitoring program (REW) relf ebly maasure the Colunn 4:
quantities of any radioisotopes cycling through the pathways to man f rom the nuclear station. The reported values are the mean or "f" If the fraction of all the samples taken average for the year of all samples of that type which had values greater than the LLD.
at all indicator locations f or the medlun which reported values greater than the LLD. Example: 7 results greate than LLD out of 15 values of the lowest to highest sample results grester than LLD reported it samples take.. would be reported 7/15. The Range is ti.
all the indicator locations for that medlun.
Fl I 1 I
TABLE 4 (cont'd)
The Mean, f-fraction and Range along with the name of the location, distance from the CPS gaseous effluent stack in miles, and the Colunn 5:
The location with j
letter (s) name of the compass sector in the direction of the sample location from the CPS gasecus ef fluent stack.
the highest annual mean is compared to both indicator and control locations of the medium samples.
Control locations are sited in areas with low relative deposition and/or dispersion factors. Sample results are used as reference Column 6:
f or the control location.
NRC Regulations (Branch Technical Position, Rev.1, November 1979) include a table of radioisotope concentrations that, if exceeded Column 7:
Such measurements require further by confirmed sample measurements, Indicate that a Nonroutine Reported Mcasurement exists.
investigation to validate the source.
(a)
Highest quarterly mean Values excluded from mean due to incorrect sample volune due to sample pump failure (b)
(c)
Treated well water sample (d)
Analysis added to program in Oct.,1987 No indicator sample location exists, no milk producing animals within 10 miles of CPS (e)
Two analyses excluded f rom mean due to unreliable results from TLD's found on ground biasing results (f) t*
l t
i g
FIGURE 4 LOCATION OF REMP STATIONS WITHIN 2 MILES New Location 117
\\
l NNE NNW 99>
- e..,
"2 NE y,
4
/
- ~ -
$3 ~
UD).
.ys W.
ENE
.II WNW a*
n.
Wi.
u.
.3 m.:
22'(y ;
92 d""t," "
t**
~
et umW
.24 g
74 W
g
. 94
.i
/.m u.
ie.
,,,o. *'f.
25
~
a ; t, ESE wsw
')
cuseoe we SE
.g
/
\\
s
$sw
$$E 5
New Location 93 SCALE 1 WILE 42 r,
s
Im
+
FIGURE 5_-
LOCATION OF REMP STATIONS FROM 2 - 6 MILES hMW NNE
{dj i,~
78 ' ' *
- _ } /6 A. - '
NE NW 1,n 37 e se
' 78 e st, rt s e s, 73e ENE
,y,
, 79 4 81 eN 6$
s ut ett I@l
.,t
~
e-r_. _...
W 63 499 9
' S4 A.
(,#
fa e,9e et e
f *!
47e 44 43 gg, 7e ESE WSW e6mm m
- *S e so est-M d k LJ
/
.n =
,3, e se neo SE e
3, SCALE 1 WILE
$$W
\\
/
k 3
43
A
')
{
o FIGURE 6 LOCATION OF REMP STATIONS FROM 6 - 50 MILES NNE NN.
4-d-
NW *==
N
( i g
e r Vr WNW.
. c.
.I f
i e.
1.l
/
3.,
a.= t"*
E B
Camen poser sensee
~
'j8
{63 -
.N W **
, l' ai le) y v
[43 gg i
e
.e,
[ o'.
i i
1 B
FIGURE 7 LOCATION OF REMP STATIONS FOR AQUATIC MONITORING 7,,.
e
( yh }
^
ti
{
/
i
~
y J
t+;
Wii,;' -
g 1
'10
~~
{---
}vQ'*,t 75 g, i
,, J L-o Q:
b s.
S ' 88
<.)
13
'cLmTow Luz r.
45
FIGURF 8 CONTROL LOCATION OF REMr) STATION FOR AQUATIC MONITORING j
Ti N
1 74 4
=
CLfNTON 9 55 Clinton Lake
- h b
'9 3
72 ga
- L
=
.J J
f
^
I DECATUR O j.
9 SPRINGFIELO
-s 9
A
~ ~
- -m i
el Lake Shelbyville j
r-g..
{5s}
5' 105 E
f Key:
1 I -
l ILL!riO15 N
E o
w 20
~..
c '.
SCM r OF :'lLES
,f n
.y i
,n
a VI.
DIRECT RADIATION MONITORING
{
A.
Description b
TLDs (thermoluminescent dnsimeters) are used to measure the ambient gamma radiation field at many locations around the Clinton Power Station.
TLDs are crystalline devices that
[
store energy when they are exposed to radiation.
They can be processed months after exposure with minimal loss of information.
This makes them well suited for quarterly
[
environmental radiation measurements.
During processing, the stored energy is released as light and measured by a TLD reader.
The light intensity is proportional to the radiation I
dose the TLD received.
The TLDs used in monitoring around the Clinton Power Station are easily capable of measuring environmental levels of radiation, approximately 20 mrem per i
quarter.
Monitoring stations are placed near the site boundary and I
approximately five miles from the
- reactor, in locations representing the sixteen compass sectors.
Other locations are chosen to measure the radiation field at places of special interest such as nearby residences, meeting places, I
and population centers.
Control sites are located further than ten miles from the
- site, in areas that should be unaffected by plant operations.
TLD measurements register the gamma ray exposure in milliRoentge.n (mR).
For reporting purposes mR is numerically I
equivalent to mrem.
Consequently the terms are used interchangeably.
B.
Results_
Results of the annuali::ed TLD dose measurements are summarized by location in Table 5.
Appendix I,
Table I-5 breaks this down further to doce at each location during each-calendar quarter.
A total of 306 TLD measurements were made.
The average quarterly dose at indicator locations was 19.5 1.6 mrem.
This i-equie lent to 8.9 microrem per hour.
The quarterly measuremanta ranged from 11.3 0.6 mrem to 27.6 0.9 mrem.
Figure 9 shows the average cuarterly gamma dose rates for 1987 control and indicator ocations, sup2rimposed on similar
~
historic data from 1985 to 1986.
Figure 10. = hows quarterly control and indicator dose rates in historical perspective.
19.9 7 At control locations the average quarterly dose was 2.6 mrem.
In determining the average control dose for 1987,~
data from the first quarter at control site CL-11 was discarded because it was more than 5 standard deviations from the mean at the s tue location during eight prior and three subsequent quarters.
47
e am b
[
Average doses, broken down by calendar quarter, are shown below for both indicator ano control locations.
The ability to characterize the error in the actual doses is due to the limited number of control TLDs (2 control TLD locations).
{
Indicator Control
+
[,
First quarter 16.4
- 1.5 16.2 I
Second quarter 21.6
- 3.6 21.4 Third quarter 18.4
- 2.2 18.3 F
Fourth quarter 21.4 2.4 21.8 L
Site CL-34, located 0.8 miles WNW of the station, registered both the hi hest quarterly and highest annualized dose:
92.7
(
mremfor19k7.
Preoperational data indicate that the dose at this location has been among the highest measured.
Between 1980 and 1984 CL-34 registered, on the average, the highest annual dose.
In 1985 and 1986 its r'ose was in the top 20% of all locations monitoredt C.
Analysis No increase in environmental gamma radiation level resulting from operation of the Clinton Power Station in 1987 was
[
detected.
P L
L.
.~
A b
-4 E
48 F
F TABLE 5 1987 CPS REMP ANNUAL TLD RESULTS 1
Station Pode (a)
Annual Total (
2 s.d.), mR(b)
CL-1 76.9
- 3.0 CL-2 80.9 3.0 i-CL-3 82.0
- 5.0 CL-4 75.7 2.2 CL-5 73.6 2.8 i
CL-6 71.7 4.2 CL-7 79.9 2.6 CL-8 78.1 2.0 CL 11(c) 77.1 0.9 I
CL-20 75.6 3.4 CL-21 82.4 2.8 CL-22 75.9
- 3.6 i
CL-23 67.9 1.8 CL-24 67.8 3.2 CL-25 60.7 i 2.8 CL-26 67.8 i 4.2 I
CL-27 74.3 5.2 CL-28 81.9 4.2 CL-29 81.4 6.8 I
CL-30 83.8
- 8.8 CL-31 71.4 5.8 CL-32 77.1 7.2 CL=33(c) 81.2 7.6 I
CL-34 92.7 9.0 CL-35 74.3 5.6 CL-36 75.2 i 5.8 I
CL-37 80.8 6.4 CL-38 78.1 6.2 CL-39 70.4 5.4 CL-40 76.4 t 5.8 CL-41 65.6 3.4 CL-42 75.4 i 5.8 CL-43 82.2 6.0 CL-44 74.9 t 6.0 CL-45 89.6 6.2 CL-46 75.0
- 5.4 CL-47 83.9 7.6 CL-48 87.9 A 4.8 CL-49 81.5 t 7.2 CL-50 78.2
- 9.0 CL-51 81.0 * 'i.0
~
CL-52 78.4 i 7.0
~~
CL-33 73.2
- 7.2 CL-54 75.7 8.6 CL-55 75.8 5.8 CL-56 81.7 i 5.8 CL-57 81.4
- 5.4 49
TABLE 5 (continued)
I' 1987 CPS REMP ANNUAL TLD RESULTS E
I Station Code (a)
Annual Total (
2 s.d.), mR(b)
CL-58 76.7 5.6 1
CL-59 83.2
- 3.2 CL-60 86.0 i 6.2 CL-61 79.8
- 7.2 l
CL-62 81.3 12.4 CL-63 87.1 9.2 CL-64 79.3 i 7.4 CL-65 81.7 7.6 i
CL-66 72.5 6.0 CL-67 81.1 5.2 CL-68 70.4 i 6.6 i
CL-69 88.8 6.8 CL-70 79.9 7.6 CL-71 84.5 i 5.8 CL-72 75.6 2.8 I
CL '/3 84.8 6.4 CL-74 78.5
- 3.0 CL-75 80.2 3.0 1
CL-76 80.3 i 5.2 CL-77 70.0 i 2.2 CL-78 77.1
- 5.2 I
CL-79 76.6
- 6.2 CL-80 79.7 7.2 CL-81 78.8 6.2 CL-82 68.8 0.6 CL-83 82.8 t 4.8 CL-84 81.3 i 6.0 CL-85 81.5 i 4.6 i
CL-86 87.9 i 4.6 CL-87 86.9 t 5.2 CL-109 79.8 i 6.2 CL-110 77.1 t 2.2 I
CL-111 53.7 6.2 CL-112 67.6 i 2.6 CL-113 81.1 3.6 (a) - For station location description refer to Table A-1 (b) - Annual TLD results are the total of the quarterly dose at each I
station Control Station all other indicators
[~_
(c) i 1
I 50
-m m
m m
m m
m m
m m
-t F
FIGURE 9 1987 QUARTERLY TLD DOSE RATES (mR/QTR)
ALL SITE AVERAGES 26.0 24 0 22.0 -
4 20.0 -
f 18.0 -
l l
E 16.0 I
l v'
O l
d l
E 14.0
-t
!"y 12.0 -
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r ATMOSPHERIC MONITORING VIIo A
direct and important exposure pathway to man is the inhalation and ingestion of radionuclides released to the I
atmosphere.
Radioactivity in the air was measured by a network of nine continuously operating air samplers.
Eight of the air sampling stations are strategically located in l
areas which are most likely to indicate effects due to the release of radioactive effluents from the Clinton Power Station.
The control location is located approximately 16 miles south of the plant in an area which is most likely to I
be independent of station operations.
Historical meteorological data indicates the north and north-northeast sectors are the prevailing downwind directions.
No contribution to the general level of airborne particulate radioactivity could be identified as a result of station I-operations during 1987.
The radioactivity that was detected is normally found in the environment and is consistent with expected concentrations of natural radioactivity and fallout l
from prior nuclear weapons testing.
A.
Sample Collection Mechanical air samplers are used to continuously draw a known volume of air through particulate filters and charcoal cartridges.
The samplers are equipped with a
I pressure-sensing flow regulator to maintain a
constant sampling flow rate.
The air sampling equipment is maintained.
and calibrated by the Clinton Power Station personnel using standards traceable to the National Bureau of Standards as I
references.
At each sampling station, a filter paper is used to collect I
particulates and charcoal cartridges are used to collect iodines.
Air samples are collected weekly and analyzed for gross beta-emitting radioactivity and Iodine-131.
Duarterly I
all air particulate filters collected during that period are composited and counted for gamma-emitting, radioisotopes.
Since the intent of particulate sampling is to measure airborne radioactivity released from the plant, the counting of short-lived daughters produced by the decay of natural radon and thoron may mask plant contributions.
Therefore, the filters are not analyzed for at least five days after their collection to allow for the decay of the short-lived daughters, thereby reducing their contribution to the gross beta activity.
53
)
r B.
Results and Analysis
[
Results of the gross beta airborne particulate analyses
~
provided comparisons between indicator and control stations I
for the year, as well as comparisons between locations in l
relation to spatial and temporal differences.
The calculated pCi/m}averagesforindieftorandcontrolstationswere0.026 annua l
and 0.028 pCi/m respectively.
These values are consigtent with the 1982 through 1987 averages of 0.027 pCi/m for both indicator and control stations.
The station I
with the highest annual average was indicator station CL-8 located 2.2 miles east of the statiop.
This station had an average concentration of 0.027 pCi/m which is equal ec the 3
preoperational mean of 0.027 pCi/m Individual station I
averages for the year are presented in Table 6.
Fluctuations in the gross beta concentrations were noted l
throughout the year.
The general trend for average weekly gross beta concentrations in the indicator stations showed good correlation with control stations throughout the i
monitoring period.
Statistical analysis of the detectable gross beta concentrations indicated no significant difference between indicator and control stations.
Only in April were the concentrations notic 2ab ;7 different with the one control I
station higher than the incicators.
This can be attributed to statistical fluctuations.
Evidence for this fact may be seen from the similarity of the trends in the average monthly I
gross beta concentrations displayed in Figure 11.
No significant difference was indicated between individual stations.
Monthly averages for indicatcr and centrol stations for the year are presented in Table 7.
Generally, the gross beta activity for both indicator and control stations remained constant throughout the monitoring I
period.
A gradual rise occurred beginning in June and peaking in September.
The increase noted in the third quarter uas unrelated to the Clinton Power Station operations I
since both indicator and control stations were affected.
All gross beta concentrations for 1987 were within normal background levels and no increases were noted as a result of l
the operation of the Clinton Power Station.
Historical trends in gross beta activity from 1982 through 1987 are depicted in Figure 12.
Generally, the level of I
gross beta activity has remained relatively constant with time.
Trends for indicator and control stations were similar.
Analynis of particulate filters for gamma-euitting radionuclides indicated naturally occurring isotopes Be-7 and K-40 were the only nuclides detected.
I l
s.
1
E M
g TABLE 6 1987 AVERAGE GROSS BETA CONCENTRATIONS IN AIR PARTICULATES
{
AverageConcentratjon Station Dercription 2
s.d.,
pCi/m E
CL-1 (I)
Camp Quest (Birkbeck) 0.027 0.010
[
CL-2 (I)
CPS Main Access Road 0.025
- 0.012 CL-3 (I)
CPS Secondary Access Road 0.027 0.010 CL-4 (I) 0.8 Miles SW 0.026 0.010 b
CL-6 (I)
IP Recreation Area 0.027
- 0.010
~
CL-7 (I)
Mascoutin Recreation Area 0.026
- 0.010 1
CL-8 (I)
Dewitt Cemetery 0.027
- 0.012 1
CL-11 (C)
IP Substation (Argenta) 0.028 i 0.008 CL-94 (I)
Old Clinton Road (0.6 miles E) 0.025 0.012' I
Indicator Station (I)
(C) = Control Station 1
I p
55
[_
TABLE 7
[
1987 AVERAGE MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES FROM CONTROL AND INDICATOR STATIONS I
3 3
Indicator, pC1/m Control, pCi/m Month (Mean 2 s.d.)
(Mean 2 s.d.)
i March 0.022 t 0.004 0.022 0.016 April 0.022
- 0.006 0.030 0.038 I
May 0.020
.004 0.022
- 0.010 I
June 0.025
.008 0.027 t 0.008 I
July 0.027
.004 0.028 0.012 August 0.028
.007 0.030 t 0.008 September 0.036 *
.004 0.035 0.024 October 0.024
.002 0.026 t 0.012 November 0.032
.002 0.034 0.026 December 0,027
.002 0.025 0.010
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VIII.
AQUATIC MONITORING
~
The Clinton Power. Station utilizes an artificial lake as the source of cooling water and returns the used cooling water to the i
same lake while most nuclear power stations use once-through flow from a river, the ocean, or a body of water much larger than Lake Clinton.
Since the radioactive liquid effluents from the Clinton I
Power Station are discharged into the cooling water
- outfall, radioisotopes with long half-lives could build up as the same water is reused on successive trips through the plant. (This water travels from the plant, into the eastern arm of the lake, then I
into the northern arm of the lake and back into the plant.)
Although the only user of Lake Clinton as a source of drinking water is the Clinton Power
- Station, the lake is a
major I
recreational facility, used for fishing, swimming, water skiing, boating and hunting.
l Lake Clinton constitutes the prime y environmental exposure pathway for radioactive materials in liquid effluents.
Aquatic Monitoring provides for the collection of fish, shoreline and bottom sediments, and aeriphyton samples to detect the presence of any radioisotopes re:.ated to operation of the Clinton Power analyzed for naturally-occurring and Station.
These samples are man-made radioactive materials.
A.
Aquatic Biota Collection I
Samples of bottom and 1.
. Bottom and Shoreline Sediment shoreline sediment are collected from Lake Clinton and Lake Shelbyville.
These samples are collected from five locations on Lake Clinton for bottom sediment and from I
six locations on Lake C1.inton for shoreline sediment.
One bottom sediment and one shoreline sediment sample is collected from Lake Shelbyville.
Lske Shelbyville is I
about 50 miles south of the Clinton Power Station and was used as the "control" site.
These samples were collected semiannually and analyzed for gross
- alpha, I
gross beta, gamma isotopic and Sr-90.
Samples of periphyton are collected from 2.
Periphyton three locations in Lake Clinton and one location in Lake I
Shelbyville.
Periphyton (attached algae), was collected from permanently anchored buoys below the water surface.
Periphyton absorb trace elements and radionuclides I
directly from water, of ten concentrating them to levels t
much higher than the cilute concentrations that occur in the aquatic environment.
This is because algae are I
coated with a carbohydrate jelly and have a large surface to volume ratio.
Cell division usually occurs once every one or two days, and as a result, half of the cell wall is a new surface for corption.
Periphyton represent one of
u the earliest links in the food chain and provide information about the amounts of radionuclides available L
to predators further up the food chain.
These samples were collected semiannually and analyzed by gamma spectroscopy.
3.
Fish - Samples of fish are collected from Lake Clinton I
and from Lake Shelbyville.
In both lakes the samples include large mouth
- bass, white
- crappie, carp and bluegill.
These species are the most commonly harvested l
fish from the lakes by sportsfishermen.
Fish ingest sediments during bottom
- feeding, or prey on other organisms which ingest sediments or otherwise retain radionuclides.
Radiological analyses of these fish I
samples provi de s information on the potential intake of radionuclides by humans via the aquatic pathway.
These samples were collected semiannually and analyzed using I
gamma spectroscopy.
Aquatic monitoring samples are collected by the Field I
Biology Laboratory of the Environmentel Affairs Department of Illinois Power Company.
B.
Results of Aquatic Biota Samples,and Analysis Bottom and shoreline sediment samples are dried before analysis.
Results are reported in units of pCi/g.
I Naturally-occurring K-40 was reported to range between 5.89 pCi/g and 19.08 pCi/g in samples from both Lake Clinton and Lake Shelbyville.
Naturally-occurring Be-7, produced by i
cosmic radiation, was also reported to be present in one sample collected from Lake Clinton and indicated to be 0.31 pCi/g.
This is only slightly above the lower limit of l
detection.
Two fission products, Sr-90 and Cs-137, were detected in camples from Lake Clinton's bottom and shoreline sediments.
I Lake Clinton's bottom sediment concentrations for Sr-90 ranged from 0.01 to 0.06 pCi/g and Cs-137 concentrations ranged from 0.07 to 0.58 pCi/g.
Lake Shelbyville Sr-90 I
concentrations ranged from 0.04 to 0.044 pCi/g and Cs-137 concentrations ranged from 0.40 to 0.59 pCi/g.
Lake Clinton's shoreline sediment concentrations for Sr-90 I
ranged from 0.002 to 0.018 pCi/g, and only one Cs-137 sample result was reported above the lower limit of detection with a concentration of 0.025 pCi/g.
Lake Shelbyville's shoreline I
sediment results were all less than the lower limit of detection for Sr-90 and Cs-137, 60
Concerstrations reported above the lower limit of detection for bottom and shoreline sediment are not substantially different than those measured during the Preoperational Program.
Preoperational bottom sediment concentrations ranged from 0.008 to 1.39 pCi/g for Cs-137 and 0.011 to 0.056 pCi/g for Sr-90.
Shoreline sediment concentrations ranged from 0.009 to 0.087 pCi/g for Sr-90, and 0.015 to 0.045 pCi/g for Cs-137.
Gross alpha analysis results showed activities of 2.6 to 13.5 I
pCi/g in samples from both lakes.
These are attributed to naturally-occurring radium isotopes and decay products present in the soil.
These values are similar to the preoperational range of 4.4 to 14.7 pCi/g for bottom and i
shoreline sediment, and 6.2 to 10.4 pCi/g found in soil samples collected away from the lakes.
l Gross beta analysis results showed activities ranging from 3.9 to 27.9 pCi/g.
The majority of this activity is contributed by the naturally-occurring isotope K-40 (5.89 to 19.80 pCi/g).
These values compare closely with the range i
8.3 to 27.7 pCi/g established during the preoperational program for gross beta.
Six periphyton samples were collected from three locations in Lake Clinton.
Gamma isotopic analyses performed on these samples showed the presence of naturally occurring Be-7 I
concentrations in two samples which were 0.44 and 0.80 pCi/g.
Naturally-occurring K-40 concentrations were detected in all samples ranging from 0.58 to 2.21 pCi/g.
All fission I
products concentrations were less than the lower limit of detection.
Two periphyton samples were collected from one location at I
Lake Shelbyville.
Gamma isotopic analyses performed on these samples s' owed concentrations for naturally-occurring K-40 of 1.67 and 2.62 pCi/g, and one Be-7 concentration of 0.38 I
pCi/g.
One fission product Cs-137 was found in one sample at 0.034 pCi/g.
The prosence of Cs-137 is attributed to previous nuclear weapons testing and atmospheric fallout from the accident at Chernobyl in the Soviet Union in 1986.
Gamma isotopic analyses performed on fish samples showed K-40 in all samples ranging from 1.38 to 3.25 pCi/g.
All other I
results were less than the lower limit of detection for each radionuclide.
I These results reveal no measurable changes in the radioactive material concentration in the aquatic environment due to operation of the Clinton Power Station.
61 l
j
S F
IX0 TERRESTRIAL MONITORING l
Radionuclides released to the atmosphere may be deposited on soil and vegetation and become incorporated into milk or food products.
To assess the impact of dose to man via the terrestrial environment and ingestion pathway, food products (meat,
- milk, cabbage, lettuce, and swiss chard) were collected from several I
locations near the Clinton Power Station in 1987.
Surfaa vegetation samples were collected from a
number of I
locatic:w for the purpose of monitoring the potential buildup of atmospherically deposited radionuclides.
Because the radionuclides of
- interest, with respect to the Clinton Power I
Station operations, are also present in the environment as a renult of several decades of worldwide fallout or because they are naturally occurring, the.
presence of these radionuclides was I
expected to some extent in all of the samples col'ected.
Milk sam 7 es were analyzed for Sr-90, I-131 and gamma-emi,.ing isotopes 1
such as Cs-137.
Food product samples were analyzed for gross y
beta-emitting radionuclides and gamma-emitting radionuclides.
The poesible contributions of radionuclides from operation of the Clinton Power Station were assessed by comparing the results of l
samples collected in prevalent downwind locations (north to north east of the plant) with control samples and samples collected in locations generally upwind of the plant.
In addition, the results of samples collected in 1987 were compared with the results of I
samples collected during the preoperational program.
An Annual Land Use Census was performed to determine the location I
of the nearest milk cow or goat in each of the 16 geographical sections and within five miles of the station.
The results of the 1987 Land Use Census are in Appendix F.
There are currently no l
milk animals within three miles of the Clinton Power Station and only one within five miles.
The annual Land Use Census also identifies all gardens of greater than fifty square meters I
producing broad leaf vegetation within five miles of the Clinton Power Station.
Terrestrial samples collected during 1987 indicate op3 ration of the I
Clinton Power Station resulted in no apparent contribution to environmental radioactivity.
l A.
Sample Collection There is no t.nown commercial production of milk for human consumption in the immediate vicinity of the Clinton Power I
Station.
The Radiological Environmental Monitoring Program regularly collects milk samples from a dairy loccted about 14 miles west soutnwest of the station (twice a month during May I
through October and once a month during November through April).
In addition, the grass samples taken in place of l
milk samples are collected in three. sectors near the plant 62 d
7u and one control station located about 16 miles south of the plant.
Milk and grass samples are analyzed for gross I
gamma-emitting activity and for I-131 activity.
The Clinton Power Station maintains contracts with three local farmers to establish and maintain gardens of greater than fif ty square meters which cont..in cabbage, lettuce, and I
swiss chard.
These gardens apaear in Figures 4, 5 and 6 as stations CL-18, CL-114 and CL-:.15e A new sample location at CL-117 was established near the end of the growing season to l
replace CL-18.
Soil samples are collected triennially from eight stations located within three miles of the plant and one control I
station located about 16 miles from the plant.
The locations of these stations are shown in Figures 4,
5 and 6.
Soil samples are analyzed for gross beta activity and I
gamma-emitting isotopes.
As an additional check on the presence of radioactive l
materials in terrestrial exposure pathways, the Clinton Power Station collects annual samples of beef liver, beef thyroid, and ground beef from an animal raised near the plant.
These samples are analyzed for all gamma-emitting isotopes.
B.
Results of Terrestrial Monitoring and Analysis Naturally-occurring radioisotopes, Sr-90, and Cs-137, were found in a number of samples.
However, the concentrations of radionuclides in samples collected near the Clinton Power I
Station were comparable to the concentrations in samples collected at locations remote frea' the station.
The presence of these fission products are attributable to previous nuclear weapons tests and the 1986 Russian reactor accident.
During the period which began February 27, 1987 and ended December 31, 1987, 18 milk samples were collected.
These I
samples were analyzed for I-131, Sr-90 and other gamma-emitting radioisotopes.
Naturally-occurring K-40 was found in all samples analyzed with concentrations of 1110 to 1290 pCi/1.
Sr-90 analyses were added to the program in October of 1987i all 5 samples takea indicated low levels of Sr-90 at concentrations of 2.3 to 2.3 pCi/1.
In addition to the milk samples, 51 samples of grass were collected from the three sectors most likely to be affected by operation of the Clinton Power Station.
These samples were analyzed for I-131 and other gamma-emitting isotopes.
Naturally-occurring Be-7 and K-40 were found in all 51 samples.
Four samples showed Cs-137 concentrations 0.009 to 0.069 pCi/g only at the control location which is located close to a field where farming operations result in soil suspension.
The presence of these fission product radioisotopes is attributed to previous nuclear weapons testing and the 1986 Russian reactor accident.
The levels of 63
M fission products detected in 1987 samples were about the same I
as the levels reported in
- 1986, indicating these radioisotopes are from sources not related to the operation of the Clinton Power Station.
During the period February 27, 1987 through December 31, 1987, 36 samples of garden produce were collected from tbe three contracted vegetable gardens.
Gamma-isotopic analysis i
showed concentrations of naturally-occurring Be-7 and K-40 ranging from 0.15 to 5.12 pCi/g of wet sample (for Be-7) and.
1.41 to 13.10 pCi/ g of wet sample (for K-40).
Two of the I
samples showed positive results for fission product Cs-137 at the control location with results of 0.016 and 0.026 pCi/g.
Gross beta analysis of these samples showed 1.58 to 7.17 I
pCi/g of wet sample.
These results are attributed to the presence of naturally-occurring K-40 in the vegetation and in deposits on the exterior of the vegetation.
I I-131 analysis results were less than the lower limit s of detection for all samples.
I I
I I
I I
I i
64
~
u Xc Ground and Surface Water Monitoring
~
Section 2.4 of the Final Safety Analysis Report for the Clinton Power Station provides a technical du cription of the geologic and i
hydrologic conditions in the vicinity of the station, and the locau ons of public and private wells.
The most rapid vertical dif tur, ion of surface water into the sub-surface aquafer suppling l
local wells is about 10.5 feet per year.
The only identified user of water from Lake Clinton for domestic purposes is the Clinton Power Stations all others potentially exposed to any radioisotopes released into surface or groundwater would not be affected for I
several years.
The Radiological Environmental Monitoring Program provided for the I
collection of samples of raw and treated well water from 2 nearby wells.
Surface water is collected frcm seven locations and drinking water has one sample location.
Average tritium and gross I
beta concentrations in
- surface, drinking and well water are presented in Table 8 and Table 9 respectively.
A.
Sample Collection The Clinton Power Station domestic water (1)
Drinking Water system is the only known direct user of water from Lake I
Clinton for human consumption.
A composite water sampler located in the Service Building collects a small, fixed volume sample at regular intervals.
The sampler discharges I
each sample into a
common sample collection bottle.
Therefore the monthly sample analyzed by the contracted laboratory service is a composite of the individual samples I
collected throughout the month.
The monthly composite sample is analyzed for gross alpha activity, gross beta activity and specific gamma-emitting isotopes.
A portion of each monthly sample is mixed with the other monthly samples collected I
during each calendar quarter.
The quarterly composite sample is analyzed for tritium.
(2)
Surface Water - Composite water samplers have been installed east of DeWitt County Road 14, in the Plant Screen House, and at the plant end of the Discharge flume.
These compositors collect a small volume of water at regular intervals and discharge it to a large sample collection bottle.
These emptied monthly and the composite monthly sample bottles are is shipped to the contracted analysis laboratory.
Menthly grab samples are also collected from four other locations on Lake Clinton and shipped to the contracted analysis laboratory.
65
L r
L The surface water samples are analyzed for gross alpha
[
activity, gross beta activity, and specific gamma-emitting radioisotopes.
In addition, a portion of each monthly sample collected in each calendar quarter is added to portions from the other 2 months to create a quarterly composite sample.
l The quarterly composite sample is analyzed for tritium.
(3)
Wellwater Every two weeks samples are collected from the well serving the Village of Dewitt and from the well serving the Mascoutin Recreation Area.
Each sample is analyzed f or I
All the samples drawn from the same well during a particular month are combined and analyzed for gross alpha
- activity, gross beta activity and specific gamma-emitting I
radioisotopes.
In
- addition, a
portion of each monthly composite is added to the quarterly composite sample and each quarterly composite is analyzed for tritium.
B.
Results and Analysis of Drinking Water Sampling Gross alpha activity above the lower limit of detection was i
reported in one of the 10 morthly samples which showed a concentration of 1.8 pCi/1.
These results are attributed to the presence of naturally-occurring traces of
- uranium, I
thorium, and their decay products in the water.
Gross beta activities ranged from 0.6 to 1.9 pCi/1.
These I
levels are attributed to very fine particles of sediment containing K-40 which are not removed during the chlorination and filtration process.
Monthly drinking water gross beta concentrations are presented in Figure 15 and Figure 16.
Specific gamma-emitting radioisotopes were all below the lower limits of detection.
Specific searches were made for I
activated corrosion products (manganese,
The results of all analyses for tritium were less than the lower limit of detection.
The lower limit of detection ranged from 174 to 190 pCi/1.
These results show no measurable effects on drinking water resulting from operation of the Clinton Power Station in 1987.
66 a
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Results and Analysis of Surface Water Sampling f
All the various water samples were analyzed for gross alpha, gross beta, gross gamma, tritium (H-3), Iodine-131 (I-131),
{
and specific nuclear power plant related isotopes such as manganese,
- iron, cobalt and zine (released as activated corrosion products) and niobium, zirconium, cesium, barium, and lanthanum (predominant fission products).
All I-131
{
and specific gamma isotopic analyses were less than the lower limits of detection.
Gross beta analysis results ranged from 1.1 to 5.0 pCi/1.
All others were less than the lower limits
(
of detection.
The positive gross beta results are attributable to naturally-occurring K-40 included in the fine sodiment particles present in the water.
Other types of
[
samples have confirmed the presence of K-40 in Lake Clinton shoreline and bottom sediments.
Monthly surface water gross beta ccacentrations for indicator and control stations are presented in Figure 12 and Figure 13.
{
Tritium analyses perfomed on samples indicated one sample at 152 pCi/1.
All other concentrations were less than the lower
(
limit of detection which ranged from 112 to 200 pCi/1.
As noted in reference (Ei87) previous nuclear weapons testing increased the normal levels of tritium (6-24 pCi/1) by a
[
factor of approximately fifty (300-1200 pCi/1).
Since the levels of tritium reported in some samples fall in the low end of the existing, non-reactor-related, natural inventory of tritium it is considered these positive results are not
[
associated with operation of the Clinton Power Station.
Gross alpha results indicated 6 positive results ranging.from
[
1.0 to 2.6 pCi/1: the rethaining results were all less than the corresponding lower limit of detection.
The gross alpha activity in the samples was attributed to sediment particles
[
present in the sample containing naturally-occurring Uranium-238 and Radium-226, both alpha emitters.
r These results show no measurable change in radioactive L
material concentration in surface water due to operation of the Clinton Power Station in 1987, b
D.
Results and Analysis of Well Water Sampling Well water results for
- gamma, gross
- alpha, tritium and
[
Iodine-131 were all less than the corresponding lower limit of detection.
Gross beta activity of 1.0 to 3.2 pCi/1 were attributed to naturally occurring K-40 which is present in
{
fine sediment particles present in the water.
These results show no measurable change in radioactive material concentration in well water resulting from operation
[
of the Clinton Power Station in 1987.
b 71
~
W TABLE 8 EL 1987 AVERAGE TRITIUM CONCENTRATIONS E
IN SURFACE, DRINKING AND WELL WATER l
Average Concentration Station Des crip tion i 2 s.d, pCi/1 Surface Water CL-9(I)
Dewitt Road Bridge
< 190 CL-10(C)
Ill. 48 Bridge
< 190 CL-13(I)
Salt Creek (bclow dam)
< 190 CL-90(I)
CPS Discharge Flume
< 190 CL-91(I)
Parnell Boat Access
< 189 CL-92(I)
CPS Intake Screenhouse
< 189
- CL-93(I)
CPS Settling Ponds 152
- 168 I
Drinking Water CL-14(I)
CPS (Service Building)
< 190 Well Water CL-7(1)
Mascoutin Recreation Area
< 190 CL-12 Treated (I)
Dewitt Pump Station
< 189 CL-12 Untreated (I)
Dewitt Pump Station
< 189
- Station added November 1987: only 2 samples taken (C) = Control (I) = Indicator
L FL TABLE 9 1987 AVERAGE GROSS BETA CONCENTRATIONS
~
IN SURFACE, DRINKINC AND WELL WATER l
I
- Avera e Concentration Stetion Description t,
s.d, pCi/l Surface Water CL-9(I)
Dewitt Road Bridge 2.3
- 1.2 CL-10(C)
Ill. 48 Bridge 2.2 1.3 CL-13(I)
Salt Creek (below dam) 2.2 1.2 l
CL-90(I)
CPS Discharge Flume 2.9 t 2.6 CL-91(I)
Parnell Boat Access 2.0 1.2 CL-92(I)
CPS Intake Screenhouse 1.9 0.9 CPS Settling Ponds 3.0 i 0.6 I
- CL-93(I)
Drinking Water CL-14(I)
CPS (Service Building) 1.6 0.8 Well Water I
CL-7(I)
Mascoutin Recreation Area 2.5 1.3 CL-12 Treated (I)
Dewitt Pump Station 2.7 0.7 CL-12 Untreated (I)
Dewitt Pump Station 2.0 2.8
- Based on detectable activities only
- Station added November 1987: only 2 samples taken (C) = Control (I) = Indicator 73
r L
LIST OF REFERENCES
{
ANSI 75 American National Standards Institute, Inc., "Performance, Testing and Procedural Specifications for l
Thermoluminescent Dosimetry," ANSI N545-1975.
BR66 "Airmass, Streamlines and the Bored Forest," A. Bryson, Technical Report No. 24, University of Wisconsin I
Department of Meteorology: Madison, Wisconsin, 1966.
CFR Code of Federal Regulations, Title 10, Part 20, Appendix I
B, Table 11 (Nuclear Regulatory Commission).
CPS Semiannual Radioactive Effluent Release Report l
CL87a February 27, 1987 - June 30, 1987.
CL87b CPS Semiannual Radioactive Effluent Release Report July 1, 1987 - December 31, 1987.
DOC 76a "Local Climatological Data, Annual Summary' with Comparative Data, Peoria, Illinois, 1976, U.S. Department I
of Commerce, NOAA, Asheville, North Carolina.
"Local Climatological Data, Annual Summary with l
DOC 76b Comparative Data, Springfield, Illinois, 1976," U.S.
Department of Commerce, NOAA, Asheville, North Carolina.
EI87 "Environmental Radioactivity," h. Eisenbud, 1987.
EPA 72 "Natural Radiation Exposure in the United States", Donald T. Oakley, U.S. Environmental Protection Agency.
ORP/SID i
72-1, June 1972.
l FRC60 Federal Radiation Council Report No. 1, "Background Material for the Development of Radiation Protection Standards."
May 13, 1960.
FSAR Final Safety Analysis Report for Clinton Power Station, Unit 1 (and amendments), May,1986.
ICRP77 International Commission on Radiological Protection, Publication 2, "Report of Committee II on Permissible Dose for Internal Radiation (1959)," with 1962 Supplement Issued in ICRP Publication 6: Publication 9, "Recommendations on Radiation Exposure," (1965): ICRP Publication 7 (1965), amplifying specific recommendations of Publication 26 (1977).
74
ICRP84 International Commission on Radiation Protection, Publication No. 39, 1984 "Principles of Limiting Exposure to the Public to Natural Sources of Radiation".
IPC87 Illinois Power Company, North Decatur Dispatch Office, 1987.
KA84 "Radioactivity in the Environment:
Sources, Distribution and Surveillance,"
Ronald L. Kathren, 1984.
NCP87 National Council on Radiation Protection Measurements, Report No. 93, 1987 "Ionizing Radiation Exposure of the l
Population of the United States".
NCRP59 National Council on Radiation Protection and Measurements, Report No. 22, "Maximum Permissible Body Burdens and I
Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, Issued June l
1959, superseding Handbook 52).
NCRP71 National Council on Radiation Prctection and Measurements, Report No. 39, "Basic Radiation Protection Criteria,"
I January 1971.
NCRP75 National Council on Radiation Protection and Measurements, I
Report No. 44, "Krypton-85 in the Atmosphere -
Accumulation, Biological Significance, and Control Technology," July 1975.
NR80 National Research Council, 1980, Committee on Biological Effects of Ionizing Radiations, Division of Medical Services, "The Effects of Populations of Exposure to Low i
Levels of Ioni::ing Radiation:
1980".
NRC75 United States Nuclear Regulatory Commission.
Regulatory Environs of Nuclear Power Plants,"g Radioactivity in theRevision 1, April 197 Guide 4.1, "Programs for Monitorin i
NRC77a United States Nuclear Regulatory Commission.
Regulatory I
Guide 4.13 "Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry:
Environmental Applications," Revision 1, July 1977.
NRC77b Regulatory Guide 1.109, Calculation of Annual Dose to Man frem Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I.
I October 1977, Revision 1.
NRC79a United States Nuclear Regulatory Commission Branch I
Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Fevision 1, November 1979.
75 L
'D
~
L r
L NRC79b United States Nuclear Regulatory Commission.
Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Norm Operations) - Effluent Streams and the
~
Environment," Revision 1, February 1979.
l NUREG86 Tecunical Specification, Clintor. Power Station, Unit No.
1, Docket No. 50-461, Office of Nuclear Reactor Regulation, 1986.
NWS87 National Weather Service, Springfield, Illinois, 1987.
TE81 Quality Control Procedures Manual, Revision 2, May 1981:
I Teledyne Isotopes Midwest Laboratory (Northbrook, Illinois)
TE84 Analytical Procedures, Manual, Revision 4, June 1984 i
Teledyne Isotopes Midwest Laboratory (Northbrook, Illinois). 60062-4197.
I I
I I
I I
5 e
76
[
[
E
~
APPENDIX A REMP Sample Locations, Synopsis of the REMP, aad Sampling and Analysia Exceptions for 1987 I
I I
I I
I 4
e A-1
b Appendix A provides information for the REMP s ample locations, a
synopsis of the 1987 operational REMP, and any sampling and r
L analysis exceptions during the monitoring perfod.
Table A-1, REMP Sample Locations, arovides information on the E
sample medium, the station code, the map number, location azimuth, and a brief description of each location where samples are taken.
The code for each sample medium are as follows:
Air Particulate (AP), Air Iodine (AI), Thermoluminescent Dosimeter (Direct Radiation) (TLD), Milk (M), Drinking Water (DW), Surface Water (SW), Well Water (WW), Green Leafy Vegetables and Tuberous Vegetables (VE), Grass (G), Fish (F), Periphyton, Slime, Bottom Organisms and Aquatic Vegetation (SL), Bottom Sediments (BS),
Shoreline Sediments (SS), Soil (S0), and Meat (ME).
The station codes are listed by Clinton (CL) - number (location number).
The map number corresponds to the number listed on the maps provided in Figures 4 through 8.
The location listed is the distance (in I
miles) and direction each location is from the station heating, ventilation, and air conditioning stack.
l Table A-2, Synopsis of the 1987 Operational REMP for the Clinton Power Station, provides each type of sample taken, the number of locations sampled, the collection frequency, the number of I
samples collected,.the types of analysis performed, the analysis frequency and total number of analyses performed.
Table A-3, Sampling and Analysis Exceptions for 1987, provides I
infomation concerning problems encountered during the performance of the Program, including any assumptions made for that problem.
I 1
I I
l w
^~
M M
M M
M l
R
[7.
R
[7
[ l i~
TABLE A-1 RADIOLOGICAL ENVIR0t#4ENT AL HONITORING PROGRAM SAMPLE LOCATIONS Sanple Statton Map Medium Code Ns.ber iocation Azimuth DeseriptIon AP, TLD, A 1, 50, G CL-1 1
1.8 alles W 258.75 - 281.25 Near the gate to Camp Quest, south of Birkbeck AP, T LD, Al, 50, G CL-2 2
0.7 miles Ntt 11.25 - 33.75 Located on site's main access road AP, TLD, A I, 50 CL-3 3
0.7 alles NE 33.75 - 56.25 Located on site's secondary access road AP, TLD, Al, 50 CL-4 4
0.8 miles SW 213.75 - 236.25 Located on f arm left of Illinois Power Recreation Af ea TLD C1 "
S 0.7 elles t:4E 11.25 - 33.75 Located on site's main access road l
0.8 miles WSW 236.25 - 258.75 Located near the Illinois Power Recreatton Area softball fleid 8w AP, Al, TLD, 50 CL-7A 7A 2.3 miles SE 123.75 - 146.25 tocated in the Mascoutin Recreation Area 55 CL-78 7B 2.1 miles SE 123.75 - 146.25 SE of site 85, St CL-7C 7C 1.3 miles SE 123.75 - 146.25 SE of site ww, 55 CL-7D ID 2.3 miles SE 123.75 - 146.25 SE of site 1
2.2 elles C 78.75 - 101.25 Located on Old Cif nton Road in Demitt Cemetery SW CL-9 9
2.7 elles ESE 101.25 - 123.75 Located on NE side of Rt. 14 bridge l
- 5W, 85, 55, St CL-10(C) 10 5.0 miles ENE 56.25 - 78.75 Located on SE side of Rt. 48 bridge h.
a
- '4 f
b-
M M
M M
M M
M t
l'~1 m
m
. O m
m m
TAtiLE A-1 (continued)
RADl0t0CICAL DJVIRONMENTAL MONITORING PROGRAM SAMPLE LOCATIONS Sample Station Map Pedium Code Nurrber location Arimuth Description
- P, TLD, AI,50, C CL-11 (C) 11 16 elles 5 168.75 - 191.25 Located in Argenta near filinois Pow;r Substation WW CL-12 12 1.6 miles E 78.75 - 101.25 Located at the Dewitt punphouse SW, BS CL-13 13 3.6 miles Sw 213.75 - 267.25 Located near the Salt Cre.,k bridge on Rt.10 DW CL-14 at CPS Plant Service N/A Located in the Service Building Building i
VE CL-18 18 1.f alles E 78.75 - 101.25 Located at feetly residence off Old Clinton Road l
f, BS, SS, SL CL-19 19 3.4 alles E 78.75 - 101.25 E of site at end of discharge l
l fiume l
4 i
l ItD CL-20 20 12.2 miles ENE 56.25 - 78.75 Located at the Farmer City cemetery TLD CL-21 21 0.9 alles FNE
'11.25 - 33.75 Located at intersection of Rt.
54 and 1675E TLD CL-22 22 0.6 miles NE 33.75 - 56.25 Leeated on site's secondary access road TLD CL-2 3 23 0.5 miles EFE 56.25 - 78.75 Located on site's secondary access road TLD CL-24 24 0.5 alles E 78.75 - 101.25 Located on site's secondary access road f
TLD CL-25 25 0.4 elles ESE 101.25 - 123.75 Located on Restricted Area rence itD CL-26 26 0.3 elles SE 123.75 - 146.25 Located on Restricted Area Fence f
g.
l 4
7 R
R R
U I ~l O
M R
R R
R R
R R
f~~l R
R P
TABLE A-1 (continued)
RADIOLOGICAL ENVIR00 MENTAL MONITORING PROCRAM SAMPLE LOCATIONS Sample Station Map Medium cme Nunber Location Azimuth Description TLD CL-27 27 0.6 miles SSE 146.25 - 168.75 Located on Restricted Area Fence near drivoney to Met Tower TLD CL-28 28 0.5 miles 5 168.7% - 191.25 Located on Restricted Area Fence TLD CL-29 29 0.6 miles SSW 191.25 - 213.75 Located on Restricted Aree Fence TLD CL-30 30 0.7 miles SW 213.75 - 236.25 Located on Restricted Area Fence at entrance to illInots Power Recreation Area o
o 8
TLD CL-31 31 0.8 miles WSW 236.25 - 258.75 located on Restricted Area Fence near lif fnois Power Recreation Area softball fleid TLD CL-32 32 0.7 miles WSW 236.25 - 258.75 Located on Restricted Area Fence near Clinton lake TLD CL-33(C) 33 11 miles SSW 191.25 - 213.75 Located in Maroa at far fly residence TLD CL-34 34 0.8 miles WNW 281.25 - 303.75 Located at CPS Visitor Center ILD CL-35 35 0.7 slies NW 303.75 - 326.25 Located at CPS Visitor Center near Rt. 54 Bridge.
TLD CL-36 36 0.6 alles N 348.75 - 11.25 Located near Rt. 54 and Main Access Road TLD CL-37 37 3.4 miles N 348.75 - 11.25 Located in rural Birkbeck TLD j
CL-38 38 3.6 miles NNE 11.25 - 33.75 Located near oferonave tower I
north of plant p
1 s
2 g
7 p
n n
n n
n
.n n
n n
n n
m m
m r-,
m
.m TABLE A-1 (conQinued)
RADIOLOCICAL ENVIR0fMENTAL MONITORING PROGRAM SAMPLE LOCATIONS Sample Station Map Medium Code Number Location Arimuth Description TLD CL-39 39 3.8 miles NE 33.75 - 56.25 Located 2 elles N of Dewitt TLD CL-40 40 3.5 miles NE 33.75 - 56.25 Located 0.6 miles N of Domitt itD CL-41 41 2.4 miles E 78.75 - 101.25 Located at 5 Domitt city limit TLD CL-42 42 2.8 elles ESE 101.25 - 123.75 Located 5 of Rt.14 bridge TLD CL-43 43 2.8 miles SE 123.75 - 146.25 Located w Citaton Marina eccess rood TLD CL-44 44 2.3 elles SSE 146.25 - 168.75 Located near Clinton Marine Boat Sales TLD CL-45 45 2.8 elles 5 168.75 - 191.25 -
Located at Lane Day Use Area e
TLD CL-46 46 2.8 miles SSW 191.25 - 213.75 Located at Peninsula Day Use Area a
TLD CL-47 47 3.3 elles Sw 213.75 - 236.25 Located near Cifnton Lake Dam Access Road TLD CL-48 48 2.3 r211es wSw 235.25 - 258.75 Located at residence on West Side Access Road TLD CL-49 49 3.5 alles W 258.75 - 281.25 Located W of site along Rt. 54 TLD CL-50 50 3.2 miles WNN 281.25 - 303.75 Located teel of site i
l TLD CL-51 51 4.4 alles NW 303.75 - 326.25 Located NW of site TLD CL-52 52 4.3 miles NEf 326.25 - 348.75 Located NNW of site TLD CL-53 53 4.3 miles E 78.75 - 101.25 Located near Weldon Boat Access f
i a
u g
g,
6~M M
M M
M i
F7 f7 F7 F 1 fR TABLE A-1 (continued)
RADiotOCICAL DNIROf#4fNTAL MON 110RitC PROGRAM SAMPt f LOCATI0tJS Sample Station Map.
Nedium Code
- Number, Location Azimuth Description TLD CL-54 54 4.6 miles ESE 101.25 - 123.75 Located near subdivision in rural weldon TLD CL-55 55 4.1 miles SE 123.75 - 146.25 Located in rural Weldon TLD CL-56 56 4.1 miles SSE 146.25" - 168.75 Located in rural between Weldon and Lane TLD CL-57 57 4.6 miles 5 168.75 - 191.25 Located in rural Lane TLD CL-5B 58 4.3 miles 55w 191.25 - 213.75 Located in rural Lane TtD CL-59 59 3.3 miles 55w 191.25 - 213.75 Located near Lane city limit b TLD CL-60 60-4.5 miles SW 213.75 - 236.25 Located SW of Cifnton Lake dam near Salt Creek l
TLD CL-61 61 4.5 miles wsw 236.25 - 258.75 WSW of site 1
TLD CL-62 62 1.9 miles Nw 303.75 - 326.25 Located in rural Birkbeck l
TLD CL-63 63 1.3 miles NNW 326.25 - 348.75 Located at North Fork Boat Access TLD CL-64 64 2.1 miles WNm 281.25 - 303.75 Located in rural Biribeck o
o TLD CL-65 65
?.6 miles ENE
$6.25 - 78.75 Located at residence in Dewitt TLD CL-66 6
p.8 miles W5W 236.25 - 258.75 Located near the Illinois Power Recreation Area Softball Fleid TLD CL-67 4
0.7 miles SW 213.75 - 236.25 Located on f arm lef t of lilinois Power Recreation Area o
o TLD CL-C9 68 4.6 miles N 348.75 - 11.25 Located N of site
M"M M
M M
M U T I'
TABLE A-1 (continued)
RADIOt0CICAL ENVIRONMENTAL MONITORINC PROGRAM SAMPLE LOCATIONS Sample Station Map Medita Code Nintier Location Arimuth Description TLD CL-69 3
0.7 miles NE 33.75 - 56.25 Located on site secondary access road TLD CL-70 2
0.7 miles NNE 11.25 - 33.75 Located on site main access road TLD CL-71 2
0.7 elles NtE 11.25 - 33.75 Located on site main access road TLD CL-72 72 4.5 miles NNE 11.25 - 33.75 Located NNE of site l
TLD CL-73 73 5.1 alles E K 56.25 - 78.75 Located near soybean processing plant north of Rt. 48 I
I TLD CL-74 74 1.9 miles W 258.75 - 281.25 Located at Camp Quest 1
co TLD CL-75 75 0.94 alles N 348.75 - 11.25 Located N of site TLD CL-76 76 4.6 alles N 348.75 - 11.25 Located N of site TLD CL-77 72 4.5 miles NNE 11.25 - 33.75 Located NNE of site TLD CL-78 78 4.6 miles NE 33.75 - 56.25 Located NE of site TLD CL-79 79 4.5 miles ENE 56.25 - 78.75 Located ENE of site l
TLD CL-80 80 4.1 elles W 258.75 - 281.25 Located W of site 1
TLD CL-81 81 4.5 miles WNW 281.25 - 303.75 Located WNW of site TLD CL-82 82 1.4 miles W 258.75 - 281.25 Located at Illinois Power Recreation Area TLD CL-83 83 0.5 miles NME 11.25 - 33.75 Located near Old Rt. 54 TLD CL-64 94 0.6 elles E 78.75 - 101.25 Located on Old Clinton Road between Dewitt and site
- j. I 6
- '4
M M
M M
M M
M M
D1 T~
TABLE A-1 (continued)
RADIOLOGICAL DNIRONMENTAL MONITORING PROGRAM SAMPLE LOCATIONS Sample Station Map Medium Code Number Location Azimuth Description TLD CL-85 85 0.6 alles ESE 101.25 - 123.75 Located ESE of site TLD CL-86 86 0.6 alles E 78.75 - 101.25 Located on Old CIfnton Road between Dewftt and site TLD CL-87 87 0.6 alles SZ 123.75 - 146.25 Located near fiume access road SS CL-88 88 2.4 miles SE 123.75 - 146.25 Located SE of site 85, 55 CL-89 89 3.6 miles NNE 11.25 - 33.75 Located NNE of site SW CL-90 90 0.4 alles ESE 101.25 - 123.75 Located at start of discharge fiume SW CL-91 91 6.4 alles ENE 56.25 - 78.75 Located at Parnell Boat Access SW CL-92 92 0.1 miles NW 303.75 - 326.25 Located at CPS Intake Screenhouse SW CL-93 93 0.4 miles SW 213.75 - 236.25 Located at CPS Settling Pond AP, A l, 50 CL-94 94 0.6 miles E 78.75 - 101.25 Located on Old C1tnton Road between Dewitt and site l
F, SS, BS, SL CL-105 (C) 105 50.0 elles 5 168.75 - 191.25 Located at Lake Shelbyville ME CL-106 106 2.0 miles NNE 11.25 - 33.75 Located NNE of site TLD CL-109 109 0.7 miles WSW 236.25 - 258.75 Located on Restricted Area Fence near Shooting Range TLD CL-110 110 0.8 miles SW 213.75 - 236.25 Located on Restricted Area Fence TLD CL-1' i ist 0.6 miles NE 33.75 - 56.25 Located near site secondary access road I
g.
a
- 't
-M M
M M
M M
l Q
f l f
TABLE A-1 (continued)
RADIOLOGICAL DNIROtNENTAL MONITORIHC PROCRAM SAMPLE LOCATIONS Sample Station Map Nedium Code Nurnber Location Ar tmut h Description TLD CL-112 68 4.6 elles N 348.75 - 11.25 Located N of site TLD Q.-113 73 5.1 miles ENE 56.25 - 78.75 Located near soybean processing plant north of Rt. 48 VE CL-114 (C) 114 12.5 miles SSE 146.25 - 168.75 Located SSE of site l
VE CL-115 115 0.7 alles NE 33.75 - 56.25 Located NE of site M
CL-116 (C) 116 14.0 miles WSW 236.25 - 258.75 Located in rural Kenney VE CL-117 117 0.9 miles N 348.75 - 11.25 Located N of r te a
l l**
s o"
(C) Cont rol location all other locations indicator Control location for surface water only 1
i l
l f.
s
'n
'M M
M M
M M ~1 O
O O
O O
O F
TABLE A-2 SYNOPSIS OF THE 1987 OPERATIONAL RADIOLOCICAL EtNIRONMENTAL MONITORING PROGRAM l
FOR THE CLINTON l'OWER STATION Number of Number of Nusber of Sample Sampilng Collection Samples Type of Analysis Samples Type Locations Frequarcy
- Collected Analysi s frequency Analyzed
- Air Particulate 9
Weekly 3%
Cross Beta weekly 396 Cama Isotopic Quarterly Composite 36 Air lodine 9
Weekly 3%
lodine-131 weekly 396 ilD 82 Quarterly 306 Cams Exposure Ovarterly 306 (continuous) l Surface Water (e) 4 Monthly 32 Comma Isotopic Monthly 32 Tritium Quarterly Coroposite 12 y
Cross Beta Monthly 32 Tritium Monthly 2
H Surf ace Water 2
Methly 20 Cansna Isotopic Monthly 20 T ri tium Monthly 20 (Intake)
Cross Beta Monthly 20 Gross Alpha (b)
Monthly (b) 10 tell Water (a) 1 Monthly 17 Cama Isotopic Monthly 14 Cross Alpha Bimonthly 12 Gross Beta Monthly 14 Tritium Quarterly Composite 4
l l
'M'M M
M M
M M
M M
i f7 f l I
TABLE A-2 SYNOPSIS OF THE 1987 OPERATIONAL RAD 10 TOC 1 CAL ENVIR0tNENTAL MONITORING PROGRAM FOR THE CLINTON powfR STATION Nisaber of Number of Number of Sample Sampling C:llection Samples Type of Analysis Samples j
Type tocetions frequency Collected Anal ysis Frequency Analyzed
- Well Water 2
Semi-monthly 46 lodine-131 Semi-monthl y 46 Cross Alpha Monthly Composite 20 Cross Beta Monthly Camposite 20 l
Canuna Isotopic Monthly Co m site 20 l
Tritium Quarterly Composite 8
Drinking water 1
Monthly 10 Cross Alpha Monthly 10 Cross Beta Monthly 10 Carina Isotopic Mothly 10 Trf tlism Quarterly Composite 4
[
Effluent Water 1
Monthly 10 C m Isotopic Monthly 10 Cross Alpha Monthly 10 fodine-131 Monthly 10 Geoss beta Monthly 10 Tr it t isa Ouarterly Composite 4
Bottom Sediments 6
Semi-annually 12 Cross Alpha Semi-annually 12 Cross Beta Semi-annually 12 Capena Isotopic semi-annually 12
$r-90 Semi-annually 12 g.
l I
r L
M-M M
M M
R f 1 f l f
TABLE A-2 SYNOPSIS OF THE 1987 OPf PATIONAL RADIOLOGICAL DNIR0t#4 ENTAL MONITORING PROGRAM FOR THE CtlNTON POWER STATION Number of N eber of Number of
!. ample Sampling Collection Samples Type of Analysis Saspies l
"ype 1ocations Frequency Collected Analysis Frequency Analyzed
- l l
' Shoreline Sediments 7
Semi-annually 14 Cross Alpha Semi-annually 14 Cross Beta Sant annually 14 l
Camma Isotopic Seal-annually 14 l
l Sr-90 Semi-annually 14 Aquatic Sediments 4
Semi-annually 8
Cama Isotopic Sant-annually 8
l to nthly/Smi-monthly 68 Camm3 Isotopic Monthly /Sant-monthly 68 Crass 4
u (May-October)
(with lodine-131) p C
Vegetables (c) 4 Monthly (during 36 Cross Beta Monthly 36 growing season)
C m Isotopic Monthly (during growing 36 (1-131 required f or season) l green leafy vegetables)
Fish 2
Seel-annual 16 Cama Isotopic Sant-annually 16 i
1 Milk 1
Monthly / Semi-Monthly 18 Came isotopic Monthly / Semi-monthly 18 (May-October)
(with lodine-131)
Sr-90 (d)
Monthly / Semi monthly 5
)
1 s
Z S
M M
M M
M M
M 1
R f~
TAELE A-2 SYNDPSIS (# M 1987 OPERATl0NAL RADict0CICAL DWIR0rNENTAL HONITORINC PROCRAM FOR THE CLINTON p0WTR STATION I
Nurrber of Number of Nisaber of Sample Sampling Collection Samples Type of Analysis Saeples Type Locations Frequency Coll ected Analysis Frequency Analyzed
- Soli 9
Triennially 0
Comma Isotopic 0
0 Cross Alpha Cross Beta Meat 1
Annually 0
Canuma Isotopic 0
G (when available) lp 8
(a) Sample f requency changed in September 1987 to Semi-monthly, added 1-131 analysis sani-monthly, changed analyses frequency on gross beta, gross alpha, and ganna isotopic to monthly composite of semi-monthly samples. Analysis for gross alpha nas changed or. samples from second month of each u
quarter to on all monthly composites.
(b) Sanples taken at location CL-92 not analyzed for gross alpha.
(c) New sample location CL-117 and CL-18 deleted af ter the growing season.
(d) Sr-90 added to program in October,1987 (e) New sample location added in Novemter,1987 at location CL-93.
- - Number of samples analyred does not include dupilcate analysis, recounts, or reenalyses g.
t
- s i
\\
~
l l
TABLE A-3 l
SAMPLING AND ANALYSIS EXCEPTIONS FOR 1987 Dates Description I
1.
February 25 to Elapsed timers at air sample stations CL-4 April 8, 1987 and CL-6 were inoperable during this time period.
Air sampler was assumed operable during the entire time per'iod for volume I
calculations.
Inoperability was due to a failed elapsed timer and was replaced with a new timer when received.
2.
February 25 to A difference of 0.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> existed between the March 4, 1987 elapsed timer and actual time at air sample station CL-1 for this timer period.
Actual I
time was used for volume calculations.
3.
March 18, 1987 Air sample station CL-7 had a blown fuse.
I Elapsed time of 99.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> was recorded.
Fuse was replaced and normal operation resumed.
4.
March 25, 1987 Composite water samplers located at stations CL-14, CL-90 and CL-91 were inoperable during month of March.
A composite of daily grab I
samples provided samples for the month.
5.
March 25, 1987 Grass samples required at sample stations I
CL-1, CL-2, CL-8 and CL-94 were not collected due to adverse weather conditions.
6.
March 31, 1987 TLD's from stations CL-7 and CL-59 were not I
found.
This was due to vandalism of the cages which held the TLD's in place.
(See note 1 on page A-19) The calculated dose for I
the quarter at stacion CL-7 is 20.0 mR and station CL-59 is 20.8 mR.
7.
April 1 to Elapsed timer at air sample station CL-7 was I
May 27, 1987 inoperable during this time period.
Air sampler was assumed operable during the entire time period for volume calculations.
Inoperability was due to a f ailed t.imer which was replaced when a new timer was received.
8.
April 22, 1987 The bottom of the air sample station shelter at CL-4 fell out of place due to termite and/or dryrot damage causing the sampler to '~
become disconnected after 160.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of operation.
A sample flow rate of 60 scfh was assumed for volume calculation.
The shelter failure also caused the elapsed timer wiring to break.
The bottom of the sample station shelter was repaired and normal sample operation resumed later on this date.
A-15
+
FL TABLE A-3 (continued)
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SAMPLING AND ANALYSIS EXCEPTIONS FOR 1987
~
Dates Description I
9.
April 22 to Elapsed timer at air sample station CL-4 was June 10, 1987 inoperable during this time period.
Air sampler was assumed operable during the entire time period for volume calculations.
i Inoperability was due to the problem described in item 8 above.
l 10.
April 29, 1987 Composite water sampler located at station CL-91 was inoperable during the aonth of April.
A com osite of daily grab samples provided samp es for the month.
11.
May 27, 1987 Composite water sampler located at station CL-91 was inoperable during the month of May.
i A composite of daily grab samples provided samples for the month.
12.
May 27 to Particulate filter paper found damaged at air I
June 3, 1987 sample station CL-94.
Filter was damaged due to the station shelter being damaged by adverse weather.
Sample results were I
disregarded as unreliable.
The sample shelter was repaired and the station returned to normal operation.
13.
June 17, 1987 Air sample stations CL-2, CL-4 and CL 8 had blown fuses.
Elapsed times of 66.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (CL-2), 66.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (CL-4) and 148.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> I
(CL-8) were recorded.
The fuses were replaced and normal operations resumed.
CL-4 elapsed timer had been removed for I
maintenance and the sample time was assumed to be the same as CL-2.
The likely cause of I
fuse failure was severe electrical s orms which occurred at the approximate time of failures.
14 June 14, 1987 Composite water sample stations CL-91 and CL-90 were inoperable for portions of month.
Samples consisted of 19 days of daily grab samples of 250 ml and 6 days of samples co11ccred by compositor at 20 ml per hour.
15.
June 24 to Elapsed timer at air sample station CL-4 July 9, 1987 removed for maintenance during this time period.
Assumed continuous operations at the sample station for the entire time period for volume calculations.
A-16
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TABLE A-3 (continued)
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SAMPLING AND ANALYSIS EXCEPTIONS FOR 1987
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Datos Description Corn and soybean leaves were collected at 16.
June 24, 1987 sample station CL-115 instead of lettuce, r
L swiss chard and cabbage, due to poor garden conditions.
Cabbage, swiss chard and lettuce transplants were added on 6/22/87 to provide
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for further samples during growing season.
17.
June 30, 1987 TLD's from stations CL-23, CL-35 CL-41, CL-58, CL-59, CL-72, CL-74, CL-77 and CL-82 r
L were not found.
This was due to the vandalism of the cages which held the TLD's in place.
(Note 1) The calculated dose for I
the quarter at stations CL-23 is 17.0 mR, CL-35 is 18.6 mR, CL-41 is 17.4 mR, CL-58 is 19.2 mR, CL-59 is 20.8 mR, CL-72 is 18.9 mR, F
CL-74 is 19.6 mR, CL-77 is 17.5 mR and CL-82 L
is 17.2 mR.
18.
July 15, 1987 Air sample station CL-4 had a blown fuse.
p Elapsed timc of 99.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> was recorded.
y Fuse was replaced and normal operation resumed.
19.
July 22, 1987 Air sample station CL-4 had a blown fuse.
Elapsed time of 53.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> was recorded.
Fuse was replaced and normal operation resumed.
20.
July 29, 1987 Soybean leaves were collected at sample I,
stations CL-18, CL-114 and CL-115 instead of L
lettuce, due to poor growth.
In addition, corn leaves at station CL-114 were collected. Station CL-117 was added, soybean rL and corn leaves were sampled instead of the regular broad leaf vegetation.
[
21.
August 19, 1987 Air sample station CL-8 had a blown fuse.
The elapsed timer showed 101.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The fuse was replaced and normal operation resumed.
{
22.
August 26, 1987 Air sample station CL-8 had a blown fuse.
Elapsed time of 23.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> was recorded.
[
Fuse was replaced and nornal operation
],
resumed.
b
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A-17 r
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l TABLE A-3 (continued)
SAMPLING AND ANALYSIS EXCEPTIONS FOR 1987 23.
September 23, 1987 Air sample station CL-8 had a pump motor failure.
Elapsed time of 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> was recorded.
Replaced unit and normal operation resumed.
24.
September 29, 1987 TLD's from stations CL-41, CL-62, CL-72, CL-74, CL-77, CL-82 and CL-111 were not I
found.
This was due to the vandalism of the cages which held the TLD's in place.
In addition, TLD's from stations CL-23, CL-24 l
and CL-58 were found on the ground due to vandalism of cages.
Results from CL-23 and CL-58 were disregarded because moisture found in TLD cases caused biased readings (approx.
I 50% low) (Note 1).
The calculated dose for the quarter at stations CL-41 is 17.4 mR, CL-62 is 20.3 mR, CL-72 is 18.9 mR, CL-74 is I
19.6 mR, CL-77 is 17.5 mR, CL-82 is 17.2 mR, CL-23 is 17.0 mR, CL-58 is 19.2 mR, and CL-111 is 13.4 mR.
25.
September 29, 1987 TLD from station CL-45 was lost in the shipping process.
No analysis was perforued (Note 1). The calculated dose for tne quarter I
at station CL-45 is 22.4 mR.
26.
September 30, 1987 Lettuce samples were unavailable at sample stations CL-18, CL-114, CL-115 or CL-117 I
because the growing season had past.
In addition, swiss chard was unavailable at CL-115.
Soybean or corn leaves were not I
available at all sites as substitutes due to harvest.
I 27.
November 25, 1987 Insufficient sample volume collected by water compositor at sample station CL-91.
A grab sample was obtained at the location and added to the composite sample to meet required I
sample volume (approximately 501 by grab and 501 by composite).
28.
December 2, 1987 Elapsed timer at air sample station CL-3 was found inoperable.
Air sampler was assumed operable for entire week of November 25, 1982.
to December 2, 1987 and a calculated time of 168.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> was used for volume calculations.
Timer was replaced and normal operation was ' ' _
resumed.
A-18
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I l
TABLE A-3 (continued)
SAMPLING AND ANALYSIS EXCEPTIONS FOR 19E 29.
December 29, 1987 TLD's from stations CL-41, CL-76 and CL-80 '
were not found.
This was due to the vandalism of the cages which held the TLD's 1
in place.
Theft proof cages were installed at these locations to prevent recurrence.
In addition, TLD's from stations CL-30, CL-44, CL-59, CL-62 and CL-110 were found on the I
ground due to vandalism of cages.
Results from TLD's found on ground were accepted and included in this report (Note 1).
The I
calculated dose for the quarter at stations CL-41 is 17.4 mR, CL-76 is 20.1 mR and CL-80 is 19.9 rR.
I NOTE 1:
Missing TLD data or TLD data found unacceptable were calculated in the following manner.
The average quarterly dose found at I
the same location for the other quarters collected in the year (i.e., Quarter 1 missing at site x, Quarters 2, 3 and 4 had readings of 21.2 mR, 18.1 mR and 20.6 eR respectively.
I Quarter 1 = Quarter 2 + Quarter 3 + Quarter 4 divided by 3, 21.2 + 18.1 + 20.6 / 3 - 20.0 mR).
I I
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A-19 l
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APPENDIX B LLD Exceptions in 1987 rL and Required Detection Capabilities
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B-1 iniimumpin imi e i i i i
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The U.S. NRC establishes minimum acceptable detection capabilities for analyses conducted by the radiological environmental monitoring program.
This value is expressed as the Lower Limit of Detection (LLD) and corresponds to a r
level of activity concentratio1 that is practically L
achievable with a given instrument, method and type of sample.
[
Tabic B-1, Analytical Results which Failed to Meet the Required LLD during 1987, lists the exceptions to the required LLD's during the monitoring period and the reason
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the exceptions were taken.
Table B-2, Detection Capabilities for Environmental Sample fired LLD's required by the Analysis, lists the minimu:r r-L Clinton Power Station Techt Jpecifications.
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rl F w TABLE B-1 ANALYTICAL RESULTS WlIICH FAILED TO MEET THE REQUIRED LLD DURING 1987 Date Sample Medium Analysis Required LLD Obtained LLD Locatien(a)
Comments 1.
3/18/87 Air Iodine I-131 0.07 pCi/m*
0.08 pCi/m CL-7 Sampler malfunction due to blown 8
fuse reducing sample volume.
2.
7/8/87 Air Iodine
,I-131 0.07 pCi/m 0.11 pCi/m CL-2 Sampler malfunction due to blown 2
8 fuse reducing sample voIr.e.
3.
7/22/87 Air Iodine I-131 0.07 pCi/m 0.15 pCi/m CL-4 Sampler malfunctir... a to blown 3
3 fuse reducing sample volume.
4.
8/26/87 Air Iodine I-131 0.07 pCi/m*
0.09 pCi/m CL-t Sampler malfunction due to blown 2
fuse reducing sample volume.
to i
S.
9/23/87 Air Iodine I-131 0.07 pCi/m 0.80 pCi/m CL-8 Sampler malfunction due to sample 2
8 pump motor failure reducing sample volume.
6.
9/23/87 Air Particulate Gross Beta 0.01 pCi/m' O.08 pC1/m CL-8 Sampler malfunction due to sample 8
pump motor failure reducing sample volume.
(
l (a) Refer to Table A-1 for location descriptions
- 6. I s
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- M M
M M
M 1
R R
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TABLE B-2 l
DETECTICN CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (a)(b)
LOWER LIMIT OF DETECTION (LLD) l Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/1) or Gas (pC1/m )
(pCi/kg, vet)
(pCi/l)
(pCi/kg, wet)
(pCi/kg, dry) 3 Gross Beta 4
0.01 H-3 2000*
Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1**
0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 m
[
Ba-140 60 60 La-140 15 15 i
Table Notations
- If no drinking water pathway exists, a value of 3000 pci/1 may be used.
oolf no drinking water pathway exists, a value of 15 pCi/1 may be used.
(a) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported.
(b) Required detection capabilities for TLD's used for environmental measucements shall be in accordance with the recommendations of Regulatory Guide 4.13, Revision 1, July 1977.
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APPENDIX C Changes to REMP in 1987 GW e,
Ee C-1 1
E s
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The following permanent changes were made in the Radiological
{'
Environmental Monitoring Program during 1987.
V-L 1.
August, 1987 Indicator vegetation station CL-117 was initiated and the site was selected in highest D/Q sector to replace-station CL-18 L
at the end of the growing season.
2.
September, 1987 Added iodine-131 analysir, for well water
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sample station CL-7.
Collection frequency was changed from monthly samples to, monthly composites of semi-mont.hly collections.
' Analysis for gross alp'na was changed on F
L samples from second month of each quarf.er to all monthly samples.
l 3.
October, 1987 Analysis for strontium-90 added to milk sample station CL-116.
L 4.
October, 1987 Indicator vegetation station CL-18 replaced r
L by station CL-117.
r-b 5.
November, 1987 Indicator surface water station CL-93 E
initiated, bringing total number of surface L
water grab sample locations to four.
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APPENDIX D
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Detertaination of Investigation Levels and Subsequent Actions
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Data from the radiological analysis of environmental samples were routinely reviewed and evaluated by the Clinton Power Station Radiological Environmental Group.
The data was checked for LLD violations, anomalous values, Technical Specification reporting I
levels, main sample and quality control sample agreement (Appendix E) and action levels.
Action levels established in the Clinton Power Station Technical I
Specifications, are defined as the level of radioactivity resulting from plant effluents in an environmental sampling medium at a specified location is detected exceeding those I
concentrations as listed in Table D-1 when averaged over a calendar quarter or when radionuclides other than those listed in Table D-1 are detected as a result of plant effluents.
I If an action level is reached, an investigation is initiated which consists of some or all of the following actions:
1.
Examine the collection data sheets for any indication of equipment malfunctions, collection or delivery errors.
2.
Examine previous data for trends.
3.
Review control station data.
I 4.
Review quality control.- duplicate sample data.
5.
Review CPS effluent reports.
6.
Recount and/or reanalyze the sample.
7.
Collect additional samples as necessary.
The results of any investigation are documented in this report.
I During 1987 no investigations were performed as a result of reaching any technical specification action level.
Six LLD violations occurred during 1937 and are documented in Appendix B.
I All other sampling and analysis exceptions are listed in Table A-3 of Appendi:, A.
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TABLE D-1
[L CPS REMP ACTION LEVELS FOR POSITIVE RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES (a)
Fish Milk Food Products
[
Airborne Partieg) laces Water or Gases (pCi/m (pCi/kg, Wet)
(pCi/1)
(pCi/kg, wet)
Analysis (pCi/1)
H-3 20,000*
{
30,000 Mn-54 1,000 10,000 Fe-59 400 t
30,000 Co-58 1,000 Co-60 300 10,000 20,000 Zn-65 300 Zr-Mb-95 400#
3 100
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T-131 2**
0.9 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 i.
300f Ba-La-140 200f For drinking water samples. This is the 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/1 may be used.
If no drinking water pathway exists, a value of 20 pCi/l may be used.
Total for parent and daughter (a)
This list does not mean these nuclides are the only ones considered. Other nuclides identified are also analyzed and reported when applicable.
OWGuh 6
e D-3
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1 APPENDIX E 1987 Quality Assurance Results i
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The Radiological Environmental Monitoring Program includes several features that assure high qu'ality results.
One feature is the requirement that the contractdr analysis laboratory, Teledyne Isotopes Midwest Laboratory (TIML), participate in the U.S. Environmental Protection Agency laboratory crosscheck program.
Table E-1 shows the i
crosscheck results obtained between May 1984 and December 1987.
During the period 333 crosscheck analysis were reported.
Ten of the reported results (i.e. the result plus or minus 2 times the standard I
deviation of the result) fell out of the control limits.
The control limits were set at the known value plus or minus 1.7.1 times the standard deviation of the known value.
In 1987, ninety-two crosscheck None of these ninety-two fell outside the I
results were reported.
control limits.
TLD intercomparisons. are not held every year.
Pertinent data from the I
Seventh International Intercomparison (1984) and the Eighth Internati onal Intercomparison (1985-6) are presented in Table E-2.
Reasurubl e good agreement is seen in each sample.
TIML tended to overestimate the known value by about 4% (+1.3% to +8.8%).
Another aspect of quality assurance is the in-house program of testing, in which samples spiked with known amounts of radioactive I
material, or blanks containing no additional radioactive material are submitted for analysis.
Table E-3 shows the results of the in-house spiked sample program.
Good agreement between known and reported I
values was obtained, In all cases except four the error bands of the known and reported values overlapped.
In the four cases when they did not overlap, the error was due to reporting a small positive result I
when the known value-was aero.
Table E-4 presents the results of the in-house blank sample program.
The only activity expected in these samples is due to naturally-occurring and fallout-related No anomalous results were reported.
Table E-5 shows I
radionuclides.the acceptance criteria for the spiked samples program.
The results presented in these tables indicated that TIFR. is capable I
of routinely performing high quality analysis on environmental samples.
I E-2 l
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G TABLE E-1 U.S. EPA CROSSCHECK PROGRAM (a)
Concentration in pCi/1 (b)
Lab Sample Date TIML Result EPA Result (d)
I Code Type Collected Analysis 2 s.d.(c)
Is, N=1 Control Limits STW-358 Water May 1984 Gr. alpha 3.0!0.6 3 5.0 0.0-11.7 Gr. beta 6.7!1.2 6!5.0 0.0-14.7 STM-366 Milk June 1984 Sr-89 2113.1 25 5.0 16.3-33.7 Sr-90 13!2.0 17 1.5 14.4-19.6 i
I-131 46 5.3 43 6.0 32.6-53.4 Cs-137 38 4.0 35!5.0 26.3-43.7 K-40 1577!172 1496 75 1336-1626 SW-368 Water July 1984 Gr. alpha 5.1!1.1 6!5.0 0.0-14.7 Gr. beta 11.9!2.4 13!5.0 4.3-21.7 STW-369 Wster Au g. 1984 1-131,
34.3!5.0 34.0 6.0 23.6-44.4 SW-370 Water Aug. 1984 H-3 3003!253 2817!356 2200-3434 STF-371 Food July 1984 Sr-89 22.0!5.3 25.0!5.0 14.3-33.7 Sr-90 14.7 3.1 20.0!1.5 17.4-22.6 I
< 17 2 39.0!6.0 28.6-49.4 Cs-137 24.0 5.3 25.0 5.0 14.3-33.7 K-40 2503i132 2605!130 2379-2831 STAF-372 Air Aug. 1984 Gr. alpha 15.3!1.2 17!5.0 8.3-25.7 Filter Gr. beta 56.0!0.0 51t5.0 42.3-59.7 Sr-90 14.3!1.2 18!1.5 15.6-20.*
Cs-137 21.0!2.0 15!5.0 6.3-23.7 STW-375 Water Sept 1984 Ra-226 5.1!0.4 4.9!0.7 3.6-6.2 Ra-228 2.2!0.1 2.3!0.4 1.7-2.9 SW-377 Water Sept 1984 Gr. alpha 3.3 1.2 5.025.0 0.0-13.7 Gr. beta 12.7!2.3 16.0!5.0 7.3-24.7 STW-379 Water Oct 1984 H-3 2860!312 2810t205 2454-3166 STW-380 Water Oct 1984 Cr-51
< 36 40 5.0 31.3-48.7 Co-60 20.3!1.2 20!5.0 11.3-28.7 Zn-65 150t8.1 147 5.0 138.3-155.7 Ru-106
< 30 47!5.0 36.3-55.7-Cs-134 31.3t7.0 31!5.0 22.3-39.7 Cs-137 26.7 1.2 24!5.0 15.3-32.2 s.
E-3
m TABLE E-1 (continued)
U.S. EPA CROSSCHECK PROGRAM (a)
{
Concentration in pCi/1 (b)
F l
Lab Sample Date TIML Result __ EPA Result (d)
Code Type Collected Analysis 2 s.d.(c) 1s, N=1 Control Limits STM-382 Milk Oct 1984 Sr-89 15.7 4.2 22!5.0 13.3-30.7 Sr-90 12.7!1.2 16!1.5 13.4-18.6 i
I-131 41.7!3.1 42!6.0 31.6-42.4 Cs-137 31.3t6.1 32!5.0 23.3-40.7 K-40 1447!66 1517t76 1386-1648 i
STW-384 Water Oct 1984 Gr. n1pha 9.7!1.2 14!5.0 5.3-22.7 (Blind)
Sample A Ra-226 3.3!0.2 3.010.5 2.2-3.8 Ra-228 3.4 1.6 2.1!0.3 1.6-2.6 I
Uranium NA (e) 0.0-15.4 Sample B Gr. beta 48.3!5.0 64t5.0 55.3-72.7 I
Sr-89 10.7!4.6 11 5.0 2.3-19.7 Sr-90 7.3!1.2 12!1.5 9.4-14.6 Co-60 16.3!1.2 14i5.0 5.3-22.7 Cs-134
<2 2!5.0 0.0-10.7 I
Cs-137 16.7!1.2 14!5.0 5.3-22.7 STAF-387 Air Nov 1984 Gr. alpha 18.7!1.2 15!5.0 6.3-23.7 I
Filter Gr. beta 59.0!5.3 52!5.0 43.3-60.7 Sr-90 18.3 1.2 21!1.5 18.4-23.6 Cs-137 10.3 1.2 10!5.0 1.3-18.7 STW-388 Water Dec 1984 I-131 28.0!2.0 36 6.0 25.6-36.4 STW-389 Water Dec 1984 H-3 3583 110 3182 360 2558-3806 STW-391 Water Dec 1984 Ra-226 8.4!1.7 8.6!1.3 6.4-10.8 Ra-228 3.lt0.2 4.1!0.6 3.0-5.2 STW-392 Water Jan 1985 Sr-89
< 3. 0 3.0 5.0 0.0-11.7 Sr-90 27.3 5.2 30.0!1.5 27.4-32.6 STW-393 Water Jan 1985 Gr. alpha 3.3 1.2 5!5.0 0.0-13.7 Gr. beta 17.3!3.0 15!15.0 5.3-23.7 STS-395 Food Jan 1985 Gr. alpha 4.7!2.3 6.0!5.0 0.0-14.7 Gr. beta 11.311.2 15.0!5.0 6.3-23.7 Sr-89 25.3!6.4 34.0!5.0 25.3-42.8 Sr-90 27.0!8.8 26.0!1.5 23.4-28.6 I-131 38.0!2.0 35.0 6.0 24.6-45 4_
Cs-137 32.7!2.4 29.0t5.0 20.3-37,7 _
K-40 1410!212 1382 120 1174-1590 E-4
u TABLE E-1 (continued) b U.S. EPA CROSSCHECK PROGRAM (a)
~
Concentration in pCi/1 (b)
Lab Sample Date TIML Result EPA Result (d)
I Code Type Collected Analysis 2 s.d.(c)
Is, N=1 Control Limits STW-397 Water Feb 1985 Cr-51
< 29 4815.0 39.3-56.7 co-60 21.3 3.0 20!5.0 11.3-28.7 I
Zn-65 53.7!5.0 55 5.0 46.3-63.7 Ru-106
< 23 25!5.0 16.3-33.7 Cs-134 32.311.2 35 5.0 26.3-43.7 I
Cs-137 25.3 3.0 25!5.0 16.3-33.7 STW-398 Water Feb 1985 H-3 3869!19 3796!634 3162-4430 STM-400 Milk March 1985 I-131 7.312.4 9.0 0.9 7.4-10.6 STW-402 Water March 1985 Ra-226 4.610.6 5.0!0.8 3.7-6.3 i
Ra-228
<0.8 9.0!1.4 6.7-11.3 Reanalysis Ra-228 9.010.4 I
STW-404 Water March 1985 Gr. alpha 4.7 2.3 6!5.0 0.0-14.7 Gr. beta 11.3 1.2 1515.0 6.3-23.7 STAF-405 Air March 1985 Gr. alpha 9.3!1.0 10.0!5.0 1.3-18.7 I
Filter Gr. beta 42.0!1.1 36.025.0 27.3-44.7 Sr-90 13.3 1.0 15.011.5 12.4-17.6 Cs-137 6.3 1.0 6.015.0 0.0-14.7 STW-407 Water April 1985 I-131 8.010.0 7.5!0.8 6.2-8.8 STW-408 Water April 1985 H-3 3399 150 35592630 2929-4189 STW-409 Water April 1985 Gr. alpha 29.711.8 32.0!5.0 23.3-40.7 (Blind)
Ra-226 4.4 0.2 4.110.6 3.1-5.1 I
Sample A Ra-228 NA (e) 6.210.9 4.6-7.8 Uranium NA (e) 7.0!6.0 0.0-17.4 1
Sample B Cr. beta 74.3111.8 72.0t5.0 63.3-80.7 Sr-89 12.3 7.6 10.0!5.0 1.3-18.7 Sr-90 14.7t2.4 15.021.5 12.4-17.6 Co-60 14.7!2.4 15.0!5.0 6.3-23.7 Cs-134 12.0!2.0 15.0t5.0 6.3-23.7 Cs-137 14.0t2.0 12.0!5.0 3.3-20.7 -
We N@
E-5
l TABLE E-1 (continued)
U.S. EPA CROSSCHECK PROGRAM (a)
~
Concentration in pCi/1 (b)
Lab Sample Date TIML Result EPA Result (d)
I Cod e Type Collected Analysis 2 s.d. (c)
In, N=1 Control Limits STW-413 Water May 1985 Sr-89 36.0 12.4 39.0t5.0 30.3-47.7 Sr-90 14.3!4.2 15.0 1.5 12.4-17.6 STW-414 Water May 1985 Gr. alpha 8.3 4.1 12.0!5.0 3.3-20.7 Gr. beta 8.7 1.2 11.0 5.0 2.3-19.7 STW-416 Water June 1985 Cr-51 44.7!6.0 44.015.0 45.3-52.7 Co-60 14.3!1.2 14.0!5.0 5.3-22.7 I
Zn-65 50.3 7.0 47.0!5.0 38.3-55.7 Ru-106 55.3!5.8 62.0 5.0 53.3-70.7 Cs-134 32.721.2 35.0!5.0 26.3-43.7 Cs-137 22.7!2.4 20.0 5.0 11.3-28.7 STW-418 Water June 1985 H-3 2446 132 2416 351 1807-3025 I
STM-421 Milk June 1985 Sr-89 10.324.6 11.015.0 2.3-19.7 Sr-90 9.012.0 11.021.5 8.4-13.6 I-131 11.7tl.2 11.0!6.0 0.6-21.4 Cs-137 12.711.2 11.0!5.0 2.3-19.7 I
K-40.
1512!62 1525!132 1393-1657 STW-423 Water July 1985 Gr. alpha 5.020.0 11.0 5.0 2.3-19.7 I
Gr. beta 5.0!2.0 8.0!5.0 0.0-16.7 STW-425 Water August 1985 I-131 25.7!3.0 33.0 6.0 22.6-43.4 STW-426 Water August 1985 H-3 4363283 4480!447 3704-5256 STAF-427 Air August 1985 Gr. alpha 11.3!0.6 13.0!5.0 4.3-21.7 I
Filter Gr. beta 46.011.0 44.0 5.0 35.3-52.7 ^
Sr-90 17.7 0.6 18.0 1.5 15.4-20.6 Cs-137 10.310.6 8.0!5.0 0.0-16.7 STW-429 Water Sept 1985 Sr-89 15.720.6 20.0!5.0 11.3-28.7 Sr-90 7.010.0 7.0tl.5 4.4-9.6 STW-430 Water Sept 1985 Ra-226 8.2!0.3 8.9:1.3 6.6-11.1 Ra-228 4.lt0.3 4.620.7 3.4-5.8 -
STW-431 Water Sept 1985 Gr. alpha 4.720.6 8.0!5.0 0.0-16.7 Gr. beta 4.7 1.2 8.015.0 0.0-16.7.
s-e E-6
TABLE E-1 (continued)
U.S. EPA CROSSCHECK PROGRAM (a) 1
[
' Concentration in pCi/1 (b)
Imb Sample Date
'IIML Result EPA Result (d)
CRde Type Collected Analysis t2 s.d. (c) is, N=1 Control Limits STW-433 Water Oct 1985 Cr-51
<13 21.0 5.0 12.3-29.7 Co-60 19.3i0.6 20.0!5.0 11.3-28.7 Zn-65 19.710.6 19.0i5.0 10.3-27.7
(
Ru-106
<19 20.025.0 11.3-28.7 Cs-134 17.011.0 20.025.0 11.3-28.7 Cs-137 19.3 1.2 20.0 5.0 11.3-28.7 STV-435 Water Oct 1985 H-3 1957!50 19741345 1376-2572 STW-436 Water Oct 1985 b
437 (Blind)
Sample A Gr. alpha 53.0!1.0 52.0213 29.4-74.6 Ra-226 5.9i0.1 6.311.0 4.1-7.9
[L Ra-228 8.220.1 10.1 1.5 7.5-12.7 Uranium NA*
8.0210.4 0.0-18.4 b-Sample B Gr. beta 85.722.5 75.0 5.0 76.3-83.7 Sr-89 21.3!1.5 27.015.0 18.3-35.7 Sr-90 10.310.6 9.0 1.5 6.4-11.6
{
Co-60 18.311.2 18.015.0 9.3-26.7 Cs-134 16.321.2 18.0!5.0 9.3-26.7 Cs-137 19.0 1.0 18.0!5.0 9.3-26.7 SIM-439 Milk Oct 1985 Sr-89 50.3 0.6 48.0 5.0 39.3-56.7 Sr-90 23.3!O.6 26.0!1.5 23.4-28.6 I-131 45.7!3.2 42.0!6.0 31.6-52.4
[
Cs-137 60.7!0.6 56.015.0 47.3-64.7 K-40 1547!29 1540 77 1406-1674 S'1V-441 Water Nov 1935 Gr. alpha 5.3!0.6 10.0!5.0 1.3-18.7
[-
Gr. beta 11.7!1.2 13.0 5.0 4.3-21.7 STW-443 Water Dec 1985 I-131 46.7!2.1 45.0!6.0 34.6-55.4 STW-444 Water Dec 1985 Ra-226 6.5 0.1 7.121.1 5.2-9.0 Ra-228 6.1!0.1 7.3!1.1 5.4-9.2.
{
STW-445 Water Jan 1986 Sr-89 29.712.5 31.0!5.0 22.3-39.7 Sr-90 13.7!0.6 15.0 1.5
- 12. 4-17 JL.
STW-446 Water Jan 1986 Gr. alpha 3.0!0.0 3.0!5.0 0.0-11.7 Gr. beta 5.3!0.6 7.0 5.0 0.0-15.7
[
E-7 h6m a ' um '
usu' u ' '
.__m-.
N L
TABLE E-1 (continued)
F
)
U.S. EPA CROSSCHECK PROGRAM (a)
Concentration in pCi/1 (b)
Lab Sample Date TIML Result EPA Result (d)
I Code,
Type Collected Analysis 2 s.d. (c) is, N=1 Control Limits STF-447 Food Jan 1986 Sr-89 24.3.2.5 25.0 5.0 16.3-33.7 Sr-90 17.3 0.6 10.0!1.5 7.4-12.6 i
I-131 22.7 2.3 20.0 6.0 9.6-30.4 Cs-137 16.3!O.6 15.0!5.0 6.3-23.7 K-40 927!46 950!144 701-1199 STW-448 Water Feb 1986 Cr-51 45.0 3.6 38.0!5.0 29.3-46.7 Co-60 19.7 1.5 18.0!5.0 9.3-26.7 I
Zn-65 44.023.5 40.015.0 31.3-48.7 Ru-106
<9. 0 0.0!5.0 0.0-8.7 Cs-134 28.3!2.3 30.0!5.0 21.3-38.7 Cs-137 23.710.6 22.0 5.0 13.3-30.7 STW-449 Water Feb 1986 H-3 5176!48 5227 525 4317-6137 STW-450 Water Feb 1986 U total 8.0!0.0 9.0!6.0 0.0-19.4 STM-451 Milk Feb 1986 I-131 7.0!0.0 9.0!6.0 0.0-19.4 STW-452 Water March 1986 Ra-226 3.8!0.1 4.1!0.6 3.0-5.2 Ra-228 11.0!0.5 12.411.8 9.2-15.5 STW-453 Water March 1986 Gr. alpha 6.710.6 15.0!5.0 6.3-23.7 Gr. beta 7.3!0.6 8.025.0 0.0-16.7 STW-454 Water April 1986 I-131 7.0!0.0 9.0!6.0 0.0-19.4 STW-455 Water April 1986 456 (Blind)
Sample A Gr. alpha 15.0!1.0 17.0!5.0 8.3-25.7 Ra-226 3.1!0.1 2.9!0.4 2.1-3.7 Ra-228 1.5!0.2 2.0!0.3 1.5-2.5 Uranium 4.720.6 5.0!6.0 0.0-15.4 Sample B Gr. beta 28.7 1.2 35.025.0 26,3-43.7 Sr-89 5.7!O.6 7.0!5.0 0.0-15.7 Sr-90 7.0!0.0 7.0 1.5 4.4*9.6 Co-60 10.7 1.5 10.0!5.0 1.3-18.7 Cs-134 4.0!1.7 5.0!5.0 0.0-13.7 Cs-137 5.3!0.6 5.025.0 0.0-13.1__
s.
E-8
l F
~
L
{
TABLE E-1 (continued)
U.S. EPA CROSSCHECK PROGRAM (a)
Concentration in pCi/1 (b)
Lab Sample Date TIML Result EPA Result (d)
I Code Type Collected Analysis 2 s.d. (c)
Is, N=1 Control Limits l
STAF-457 Air April 1986 Gr. alpha 13.7 0.6 15.0!5.0 6.3-23.7 l
Filter Gr. beta 46.3!0.6 47.0!5.0 38.3-55.7 Sr-90 14.7!0.6 18.0 1.5 15.4-20.6 Cs-137 10.7 0.6 10.0!5.0 1.3-18.7 STU-458 Urine April 1986 Tritium 4313!70 4423t189 4096-4750 STW-459 Water May 1986 Sr-89 4.310.6 5.0 5.0 0.0-13.7 i
Sr-90 5.0 0.0 5.0 1.5 2.4-7.6 STW-460 Water May 1986 Gr. alpha 5.3!0.6 8.0 5.0 0.0-16.7 Gr. beta 11.3!1.2 15.0!5.0 6.3-23.7 STW-461 Water June 1986 Cr-51
<9.0 0.0!5.0 0.0-8.7 Co-60 66.0 1.0 66.0!5.0 57.3-74.7 I
Zn-65 87.3tl.5 86.0!5.0 77.3-94.7 Ru-106 39.7!2.5 50.0!5.0 41.3-58.7 Cs-134 49.3!2.5 49.0 5.0 40.3-57.7 Cs-137 10.3!1.5 10.0!5.0 1.3-18.7 SW-462 Water June 1986 Tritium 3427!25 3125!361 2499-3751 STM-464 Milk June 1986 Sr-89
<1.0 0.0!5.0 0.0-8.7 Sr-90 15.3!0.6 16.0 1.5 13.4-18.6 I-131 48.3!2.3 41.0t6.0 30.6-51.4 I
Cs-137 43.7 1.5 31.0!5.0 22.3-39.7 K-40 1567 114 1600!80 1461-1739 I
SW-465 Water July 1986 Gr. alpha 4.7!0.6 6.0!5.0 0.0-14.7 Gr. beta 18.7 1.2 18.0!5.0 9.3-26.7 STW-467 Water August 1986 I-131 30.3!0.6 45.0!6.0 34.4-55.4 STW-468 Water August 1986 Pu-239 11.320.6 10.1!1.0 8.3-11.9 STW-469 Water August 198^ Uranium 4.0t0.0 4.0!6.0 0.0-14.4 STAF-470 Air Sept 1986 Gr. alpha 19.3 1.5 22.0 5.0 13.3-30.7) 471 Filter Gr. beta 64.0!2.6 66.0 5.0 57.3-74.7~
I 472 Sr-90 22.0!1.0 22.0 5.0 19.4-24.6 Cs-137 25.7 1.5 22.0!5.0
- 13. 3-30_.[7],
I STW-473 Water Sept 1986 Ra-226 6.010.1 6.1 0.9 4.5-7.7 j
Ra-228 8.7 1.1 9.1 1.4 6.7-11.5 E-9
7L TABLE E-1 (continued)
{
U.S. EPA CROSSCHECK PROGRAM (a)
Conentration in pCi/1 (b)
Imb Sample Date TIML Resuit EPA Result (d) i Code Type Collected Analysis 2 s.d. (c) is, N=1 Control Limits SW-474 Water Sept 1986 Gr. alpha 16.313.2 15.025.0 6.3-23.7 I
Gr. beta 9.0!1.0 8,. 0i 5. 0 0.0-16.7 5
STW-475 Water Oct 1986 Cr-51 63.3 5.5 59.0!5.0 50.3-67.7 i
Co-60 31.0!2.0 31.015.0 22.3-39.7 Zn-65 87.325.9 85.0 5.0 76.3-93.7 Ru-106 74.7!7.4 74.0 5.0 65.3-82.7 Cs-134 25.710.6 28.0 5.0 19.3-36.7 i
Cs-137 46.321.5 44.0!5.0 35.3-52.7 STW-476 Water Oct 1986 H-3 5918t60 5973!597 4938-7008 SPW-477 Water Oct 1986 478 (Blind)
Sample A Gr. alpha 34.0!6.0 40.0t5.0 31.3-48.7 Ra-226 5.8!0.2 6.020.9 4.4-7.6 Ra-228 2.711.0 5.0!0.8 3.7-6.3 I
Uranium 11.0!0.0 10.0!6.0 0.0-20.4 Sample B Gr. beta 38.7 1.2 51.0!5.0 42.3-59.7 Sr-89 5.020.0 10.0!5.0 1.3-18.7 I
Sr-90 3.0!0.0 4.011.5 1.4-6.6 Co-60 24.711.2 24.0!5.0 15.3-32.7 Cs-134 11.0!2.0 12.025.0 3.3-20.7 I
Cs-137 9.311.2 8.0!5.0 0.0-16.7 STM-479 Milk Nov 1986 Sr-89 7.711.2 9.015.0 0.3-17.7 I
Sr-90 1.0i0.0 0.0tl.5 0.0-2.6 I-131 52.3!3.1 49.0 6.0 38.6-59.4 4
489 b4 5
h 43 7b0 STU-480 Urine Nov 1986 H-3 5540!26 52571912 4345-6169 i
SW-481 Water Nov 1986 Gr. alpha 12.024.0 20.025.0 11.3-28.7 Gr. beta 20.0!3.5 20.0t5.0 11.3-28.7 STW-482 Water Dec 1986 Ra-226 6.720.2 6.8!1.0 5.0-8.6 Ra-228 5.2!O.2 11.1!1.7 8.2-14.0_
STW-483 Water Jan 1987 Sr-89 19.7!5.0 25.0 5.0
- 16. 3-3 3 ;7 " ~
Sr-90 21.012.0 25.0!1.5 22.4-27.6
~
L m
l TABLE E-1 (continued)
U.S. EPA CROSSCHECK PROGRAM (a)
Concentration in pCi/1 (b)
I Lab Sample Date TIML Result EPA Result (d)
Code Type Collected Analysis
!2 s.d.(c)
Is, N=1 Control Limits STW-484 Water Jan 1987 Pu-239 17.0 2.3 16.7!1.7 13.8-19.6 STF-486 Food Jan 1987 Sr-90 36.0!4.0 49.0 10.0 31.7-66.3 I-131 78.0 3.4 78.0!8.0 64.1-91.9 Cs-137 89.7i3.0 84.0!5.0 75.3-92.7 K-40 942156 980t49 895-1065 STF-487 Food
'Jan 1987 Sr-90 2.0!0.0 I
(Blank)
<3 Cs-137
<2 K-40 9932102 STW-488 Water Feb 1987 Co-60 49.0!0.0 50.0t5.0 41.3-58.7 2n-65 96.0!7.2 91.0 5.0 82.3-99.7 I
Ru-106 92.0 20.2 100.0!5.0 91.3-108.7 Cs-134 53.0!3.4 59.0!5.0 50.3-67.7 Cs-137 89.3!4.6 87.015.0 78.3-95.7 STW-489 Water Feb 1987 H-3 4130!!40 4209!420 3479-4939 STW-490 Water Feb 1987 Uranium 8.3!1.2 8.0!6.0 0.0-18.4 STM-491 Milk Feb 1987 I-131 10.0 0.0 9.020.9 7.4-10.6 STW-492 Water Mar 1987 Gr. alpha 3.7!1.2 3.0 5.0 0.0-11.7 1
Gr. beta 11.321.2 13.0!5.0 4.3-21.7 STW-493 Water Mar 1987 Ra-226 7.0 0.1 7.3!1.1 5.4-9.2 Ra-228 7.1!2.3 7.521.1 5.5-9.5 STW-494 Water Apr 1987 I-131 8.0!0.0 7.0!0.7 5.8-8.2 STAF-495 Air Apr 1987 Gr. alpha 15.020.0 14.0!5.0 5.3-22.7 Filter Gr. beta 41.012.0 43.0 5.0 34.3-51.7 Sr-50 16.3!1.2 17.0!1.5 14.4-19.6 I
Cs-137 7.0!0.0 8.0!5.0 0.0-16.7 STV-496 Water Apr 1987 497 (Blind)
Sample A Gr. alpha 30.7!1.2 30.0!8.0 16.1-43.T Ra-226 3.920.2 3.9!0.6 2.9-4.9 ^~
Ra-228 4.9!0.9 4.0!0.6 3.0-5.0 Uranium 5.020.0 5.0 6.0 0.0-15.4 E-11
L
{
TABLE E-1 (continued)
U.S. EPA CROSSCHECK PROGRAM (a)
Concentration in pCi/1 (b)
Lab Sample Date TIML Result EPA Result (d)
Code Type Collected Analysis 2 s.d.(c)
Is N=1 Control Limits SW-496 Water Apr 1987 l
497 (Blind) l Sample B Gr. Beta 69.3!9.4 66.0 5.0 57.3-74.7
(
Sr-89 16.313.0 19.015.0 10.3-27.7 1
Sr-90 10.010.0 10.0!1.5 7.4-12.6 l
Co-60 8.3!3.0 8.0 5.0 0.0-16.7 Cs-134 19.012.0 20.0i5.0 11.3-28.7 l
I Cs-137 14.711.2 15.0!5.0 6.3-23.7 STU-498 Urine Apr 1987 H-3 60172494 5620 795 4647-6593 STW-499 Water May 1987 Sr-89 38.026.0 41.015.0 32.3-49.7 Sr-90 21.0 2.0 20.0!1.5 17.4-22.6 STW-500 Water May 1987 Gr. alpha 9.013.4 11.0!5.0 2.3-19.7 Gr. beta 10.3 1.2 7.0!5.0 0.0-15.7 STW-501 Water June 1987 Cr-51 40.0!8.0 41.0!5.0 32.3-49.7 Co-60 60.313.0 64.0!5.0 55.3-72.7 Zn-65 11.3 5.0 10.0!5.0 1.3-18.7 i
Ru-106 78.3!6.4 75.015.0 66.3-83.7 Cs-134 36.713.0 40.025.0 31.3-48.7 Cs-137 80.314.2 80.0 5.0 71.3-88.7 STV-502 Water June 1987 H-3 2906!86 2895 357 2277-3513 SIV-503 Water June 1987 Ra-226 6.920.1 7.321.1 5.4-9.2 Ra-228 13.3tl.0 15.2!2.3 11.2-19.2 -
SW-504 Milk June 1987 Sr-89 57.0t4.3 69.015.0 60.3-77.7 Sr-90 32.021.0 35.0!1.5 32.4-37.6 I
I-131 64.022.0 59.016.0 48.6-69.4 Cs-137 77.7!0.6 74.025.0 65.3-82.7 K
1383t17 1525176 1393-1657 I
SW-505 Water July 1987 Gr. alpha 2.310.7 5.025.0 0.0-13.7,
Gr. beta 4.011.0 5.0t5.0 0.0-13.7 STF-506 Food July 1987 I-131 82.724.6 80.0 8.0 66.1-93.9 Cs-137 53.7 3.0 50.0!5.0
- 41. 3-5 8.T K
1548!57 1680!84 1534-1826'~
SW-507 Water Aug 1987 I-131 45.7!4.2 48.0 6.0 37.6-58.4 1
1 STV-508 Water Aug 1987 Pu-239 5.8 0.2 5.3!0.5 4.4-6.2
L
~
TABLE E-1 (continued)
U.S. EPA CROSSCHECK PROGRAM (a)
Concentration in pC1/1 (b)
Lab Sample Date TIML Result _
EPA Result (d)
Code Type Collected Analysis 2 s.d. (c) is, N=1 Control Limits STV-509 Water Aug 1987 Uranium 13.3 0.3 13.0!6.0 2.6-23.4 i
STAF-510 Air Aug 1987 Gr. alpha 9.7!0.4 10.0!5.0 1.3-18.7 Filter Gr. beta 28.3!0.6 30.0!5.0 21.3-38.7 Sr-90 10.0 0.9 10.0!1.5 7.4-12.6 Cs-137 10.0 1.0 10.0!5.0 1.3-18.7 STW-511 Water Sept 1987 Ra-226 9.9!0.1 9.7 1.5 7.2-12.2 Ra-228 8.1!1.4 6.3 1.0 4.6-8.0 STV-512 Water Sept 1987 Gr. alpha 2.0!0.6 4.0!5.0 0.0-12.7 Gr. beta 11.3!1.3 12.0!5.0 3.3-20.7 STW-513 Water Oct 1987 H-3 4473!100 4492!449 3714-5270 STW-514 Water A Oct 1987 Gr. alpha 29.3 2.6 28.0!7.0 15.9-40.1 I
Ra-226 4.9!0.1 4.8!O.7 3.6-6.1 Ra-228 4.2 1.0 3.6!0.5 2.7-4.5 Uranium 3.0!0.1 3.0!6.0 0.0-13.4 SIV-515 Water B Oct 1987 Cr. beta 72.3!2.7 72.0!5.0 63.3-80.7 Sr-89 14.3 1.3 16.015.0 7.3-24.7 Sr-90 9.7!0.4 10.0!1.5 7.4-12.6 I
Co-60 16.7i3.0 16.0!5.0 7.3-24.7 Cs-134 16.7!2.3 16.0 5.0 7.3-24.7 Cs-137 24.3t3.3 24.0!5.0 15.3-32.7 STV-516 Water Oct 1987 Cr-51 80.3t17.5 70.0!5.0 61.3-78.7 Co-60 16.0!2.3 15.0 5.0 6.3-23.7 Zn-65 46.3!5.6 46.0!5.0 37.3-54.7 I
Ru-106 57.3!15.4 61.015.0 52.3-69.7 Cs-134 23.7 2.5 25.0!5.0 16.3-33.7 Cs-137 51.7!3.2 51.0!5.0 42.3-59.7 STU-517 Urine Nov 1987 H-3 7267!!00 7432!743 6145-8719 STW-519 Water Dec 1987 I-131 26.0 3.0 26.0!6.0 15.6-36.4 (c) Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the I
environmental sample crosscheck program operated by the Intercomparison and Calibration S:ction, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U..S.
Environmental Protection Agency (EPA), Las Vegas, Nevada.
_2.
I (b) All results are in the pCi/1, except for elemental potassium (K) data, which are in og/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 and expected laboratory precision '
(1s, 1 determination) and control limits as defined by EPA.
(e) NA = Not analyzed.
I E-13 1
L
~
M M
M M
M f
R
.R R
R R
R R
R R
R R
R R
.I TABLE E-2 CROSSOECK PROCRAM RESULTS. TIERMOLUMINESCENT DOSIMETERS (TLDs)
- nR Teledyne Average 12 s.d. (c) l tab TLD Result Known (all Value(b) participants)
Code Type Measurement t2 s.d. (a) 7th International Intercomparison 115-7C CaSO :Dy Field 76.812.7 75.816.0 75.1129.8 Cards Lab (Co-60) 82.513.7 79.914.0 77.9127.6 1
t1:
Lab (Cs-137) 79.0*3.2 75.013.8 73.0*22.2 es A
8th International Int ercornpari son l
115-8C CaSO :Dy Fleid Site 1 32.3t0.7 29.711.5 28.9112.4 Cards Fleid Site 2 10.610.6 10.4*0.5 10.119.0 l
l Lab (Cs-137) 18.110.8 17.2i0.9 16.216.8 (a) Lab result given is the mean 12 standard deviations of tfiree determinations.
(b) Value determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
(c) Mean 12 standard deviations of results obtained by all laboratories participating in the program.
(d) Seventh International Intercomparison of Envirorunental Dosimeters conducted in the spring and sumer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, the U.S. Nuclear Regulatory Corrinission, and the U. S. Environmental Protection Agency.
(e) Eighth International Intercomparison of Environment:21 Dostmeters conducted in the f all and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.
F a
i
- '4i
- r TABLE E-3 In-House Spiked Samples Concentration in pCi/1
~
Sample Date TIML Result Known Expected Lab.
Code Type Collected Analysis n=3 Activity Precision 1s, n=3" r
u QC-MI-6 Milk Feb. 1986 Sr-89 6.0il.9 6.4 3.0 8.7 Sr-90 14.211.7 12.922.0 5.2 i
I-131 34.213.8 35.223.5 10.4
)
Cs-134 32.0 1.8 27.325.0 8.7 y
Cs-137 35.8!2.1 35.0!5.0 8.7 QC-W-14 Water Mar. 1986 Sr-89 1.6!0.4 1.621.0 7.1 Sr-90 2.4!0.2 2.4 2.0 4.2 QC-W-15 Water Apr. 1986 I-131 44.9 2.4 41.527.0 10g Co-60 10.621.7 12.1!5.0 7.1 Cs-134 30.222.4 25.818.0 7.1(
b Cs-137 21.9il.9 19.925.0 7.1 QC-MI-7 Milk Apr. 1986 7-131 39.713.3 41.5t7.0 10.4 Cs-134 28.7 2.8 25.818.0 8.7
{
Cs-137 21.212.8 19.9!5.0 8.7 SPW-1 Water May 1986 Gross alpha 15.8 1.8 18.015.0 5("}
QC-W-16 Water June 1986 Gross alpha 16.210.7 16.922.5 8.7 l
Gross beta 38.413.5 30.2 5.0 8.7 l
F QC-MI-9 Milk June 1986 Sr-89
< 1. 0 0.0 7.1 l
Sr-90 12.621.8 13.313.0 4.2 r
I-131 38.927.0 34.817.0 10.4
)
L Cs-134 33.013.4 36.125.0 8.7 l
Cs-137 38.5!2.8 39.0i5.0 8.7 SPW-2 Water June 1986 Gross alpha 16.821.8 18.025.0 5(*)
h.
SPW-3 Water June 1986 Gross alpha 17.710.8 18.025.0 5 (*)
QC-W-18 Water Sep. 1986 Cs-134 34.725.6 31.325.0 8.7 Cs-137 51.127.0 43.3 8.0 8.7 b
QC-W-19 Water Sep. 1986 Sr-89 13.624.1 15.623.5 7.1 Sr-90 6.421.6 6~2!2.0 4.2 h
M4 E
E E-15 F
l TABLE E-3 (cont.)
In-House Spiked Samples Concentration in pCi/1 Lab Sample Date TIML Result Known Expected i
Code Type
- 11 e c t e d Analysis n=3 Activity Precision 8
1s, n=3 i
QC-W-21 Water Oct 1986 Co-60 19.2!2.2 18.523.0 8.7 Cs-134 31.7!5.2 25.6 8.0 8.7 Cs-137 23.8!1.0 21.6 5.0 8.7 QC-MI-11 Milk Oct 1986 Sr-89 12.3!1.8 14.3!3.0 8.7 QC-W-20 Water Nov 1986 H-3 3855!180 39601350 520(b)
QC-W-22 Water Dec 1986 Gross alpha 9.811.4 11.2 4.0 8.7 Gross beta 21.7!2.0 23.815.0 8.7 QC-W-23 Water Jan 1987 I-131 29.8t2.5 27.9 3.0 10.4 QC-MI-12 Milk Jan 1987 I-131 36.5!1.3 32.6!5.0 10.4 Cs-137 32.6!4.2 27.418.0 8.7 I
SPM-13 Milk Jan 1987 Sr-89 10.4!2.1 12.2 4.0 8.7 Sr-90 14.621.6 12.6!3.0 5.2 I-131 49.5 1.2 54.918.0 10.4 Cs-134
< 1.6 0.0 8.7 I
Cs-137 33.310.6 27.4!8.0 8.7 SFW-24 Water Mar 1987 St-89 24.713.6 25.9!5.0 8.7 Sr-90 23.9!3.8 22.8!8.0 5.2 SPW-25 Water Apr 1987 I-131 28.021.9 29.3t5.0 10.6 SPM-14 Milk Apr 1987 I-131 25.022.2 23.9!5.0 10.4 Cs-134
< 2.1 0.0 8.7 Cs-137 34.2!2.0 27.227.0 8.7 SPW-26 Water Jun 1987 H-3 3422 100 3362 300 520 Co-6C 24.8!1.4 26.5t7.0 8.7 Cs-134
< 2.0 0.0 8.7 I
Cs-137 21.210.5 21.6!7.0 8.7 SPW-27 Water Jun 1987 Gr. alpha 8.521.9 10.124.0 8.7 Cr. beta 22.6!1.9 21.225.0 8.7 SPW-28 Water Jun 1987 Gr. alpha 8.721.3 10.1 4.0
- 8. 7 -
Gr. beta 12.225.2 9.423.0 8.7 I
~
L_
[
TABLE E-3 (cont.)
In-House Spiked Samples Concentration in pCi/1
~
Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precisg 1s, n=3 SPW-29 Water Jun 1987 Gr. alpha 16.4!1.3 18.915.0 8.7
[
Gr. beta 15.9 4.0 11.8t4.0 8.7 SPM-15 Milk Jul 1987 Sr-89 19.4 1.6 18.8!3.5 5.2 I-131 43.5 0.7 45.3!7.0 10.4
{
Cs-134 17.9!2.2 16.0!5.3 8.7 Cs-137 25.4!1.8 22.7!5.0 8.7
[
SFW-30 Water Sep 1987 Sr-89 17.5t3.0 14.3!5.0 8.7 Sr-90 18.4!2.2 17.5 2.2 5.2 SPW-31 Water Oct 1987 H-3 2053 93 2059!306 520
{
a n=3 unless noted otherwise b n=2.
e n=1.
I I
I I
I I
e=
E6 I
l l
E-17
t I
TABLE E-4 In-House Blank Samples I
Concentration in pC1/1
]
Acceptance "j
Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 s.d.)
(4.66 s.d.)
BL-1 0.I. Water Nov 1985 Gross alpha
< 0.1 1
s Gross beta
< 0.4
< A BL-2 D.I. Water Nov 1985 Cs-137 (gama)
< 1.9
< 10 DL-3 D.I. Water Nov 1985 Sr-89
< 0.5
< 5 Sr-90
< 0.6
< 1 BL-5 D.I. Water Nov 1985 Ra-226
< 0.4
< 1 Ra-228
< 0.4
< 1 SPW-2265 D.I. Water Apr 1985 Gross alphr
< 0.6
< 1 Gross beta
< 2.2
< 4 I
Sr-89
< 0.2
< 5 Sr-90
< 0.4
< 1 I-131
< 0.2
< 1 Cs-137 (gamma)
< 7.4
< 10 BL-6 D.I. Water Apr 1986 Gross alpha
< 0.4
< 1 8L-7 D.I. Water Apr 1986 Gross alpha
< 0.4
< 1 BL-8 0.I. Water June 1986 Gross alpha
< 0.4
< 1 BL-9 D.I. Water June 1986 Gross alpha
< 0.3
< 1 1
SFW-3185 D.I. Water Jan 1987 Ra-226
< 0.1 I
1 Ra-228
< 0.9 1
SPS-3292 Milk Jan 1987 I-131
< 0.1 I
Cs-134
< 6.2
< 10 Cs-137
< 6. 4
<10 SPW-3554 D.I. Water Feb 1987 H-3
< 180
< 300 I
Gross beta
< 2.6
<4 SPS-3555 Milk Feb 1987 Sr-89
< 0.6
< 5 Sr-90 1.910.4(")
< 1 SPS-3731 Milk Mar 1987 Cs-134
< 2.2
< 10 Cs-137
< 2.5
< 10 I
l
L TABLE E-4 (cont.)
In-House Blank Samples l
l Concentration in pCi/1
__ Acceptance Lab Sample Date Results Criteria i
Code Type Collected Analysis (4.66 s.d.)
(4.66 s.d.)
)
SPS-3732 D.I. Water Mar 1987 Sr-89
< 0.9
< 5 Sr-90
< 0.8
< 1 l
< 0.3
< 1 Co-60
< 2.3
< 10 Cs-134(G)
< 2.2
< 10 Cs-137(G)
< 2.4
< 10 Ra-226
< 0.1
< 1 I
Ra-228
< 1.0
< 1 Np-237
< 0. 04
< 1 Th-230
< 0.05
< 0.1 I
<0.02
< 0.1 U-234
< 0.05
< 0.1 U-?35
< 0.03
< 0.1 U-238
< 0.03
< 0.1 SPS-4023 Milk May 1987 I-131
< 0.1
< 1 SPS-4203 D.I. Water May 1987 Gross alpha
< 0.7
< 1 Cross beta
< 1.7
< 4 I
SPS-4204 Milk May 1987 St-89
< 0.5
< 5 Sr-90 2.420.6(a)
< 1 SPS-4390 Milk Jun 1987 Cs-134
< 4.7
< 10 I
< 5.2
< 10 SPS-4391 D.I. Water Jun 1987 Sr-89
< 0.4
< 5 Sr-90
< 0.4
< 1 I-131
< 0.1
< 1 Co-60
< 3.8
< 10 Cs-137
< 5.7
< 10 I
< 0.1
< 1 Ra-228
< 0.9
< 1 SPW-4627 D.I. Water Aug 1987 Gross alpha
< 0.6
< 1 Gross beta
< 1.4
< 4 Tritium
<.150 SPS-4628 Milk Aug 1967 Sr-89
< 0.6
< 5.
Sr-90 2.4!0.6 1_
SPS-4847 Milk Sep 1987 Cs-134
< 4.4
< 10 Cs-137
< 5.3
< 10 E-19
E; TABLE E-4 (cont.)
In-House Blank Samples Concentration in pCi/1 1
4 "I
Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 s.d.)
(4.66 s.d.)
SPS-4848 0.I. Water Sep 1987 I-131
< 0.2
< 1 E
SFW-4849 D.I. Water Sep 1987 Co-60
< 4.1
< 10 Cs-134
< 4.8
< 10 Cs-137
< 4.0
< 10
{
Sr-89
< 0.7
< 5 Sr-90
< 0.7
< 1 l
h SFW-4850 D.I. Water Sep 1987
'Ih-2 28
< 0.04
< 1 Th-232
< 0.8
< 1 U-234
<0.03
< 1 U-235
<0.03
< 1
{-
<0.02
< 1 Am-241
<0.06
< 1 Cm-242
<0.04
< 1 l
p L
< 0.1
< 1 Ra-228
< 1.0
< 2
{
SPW-4859 D.I. Water Oct 1987 Fe-55
< 0.5
< 1 SPS-5348 Milk Dec 1987 Cs-134
< 2.3
< 10 Cs-137
< 2.5
< 10 SPW-5384 Water Dec 1987 Co-60
< 2.8
< 10 Cs-134
< 2.6
< 10
[
< 2.8
< 10 I-131
< 0. 2
< 1 Ra-226
< 0.1
< 1 La-228
< 1.2
<2
{
Sr-89
< 0.5
< 1 Sr-90
< 0. 4
<1
(
SFW-5385 Water Nov 1987 Gross alpha
< 0.4
<1 Gross beta
< 2. 2
<4 Fe-55
< 0. 3
<1 SPS-5386 Milk Jan 1988 I-131
< 0.1
<1 SFW-5448 "Dead" Water Jan 1988 H-3
< 177
<300.-
s (a) Low level (1-4 pCi/1) of Sr-90 concentration in milk is not unusual.
E E-20 F
~
a TABLE E-5
~
ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES (a)
Analysis Level One Standard Deviation for Single Determination
~
J Gamma Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter
> 100 pCi/ liter or kg 5% of known value Strontita-89( )
5 to 50 pCi/ liter or kg 5 pCi/ liter
> 50 pCi/ liter or kg 10% of known value Strontium-90( }
2 to 30 pCi/ liter or kg 3.0 pCi/ liter
> 30 pCi/ liter of kg 10% of known value Potassium
> 0.1 g/ liter or kg 5% of known value Gross Alpha
< 20 pCi/ liter 5 pCi/ liter
)
L
> 20 pCi/ liter 25% of known value
]
Gross Beta
< 100 pCi/ liter 5 pCi/ liter
[
> 100 pCi/ liter 5% of known value Tritium
< 4,000 pCi/ liter is = (pCi/ liter) = 0933 169.85 x (known)'
> 4,000 pCi/ liter 10% of known value Radium-226
< 0.1 pCi/ liter 15% of known value l
[
Radium-228 Plutonium 0.1 pCi/ liter, gram, 10% of known value
{
or sample Iodine-131,
< 55 pci/ liter 6 pCi/ liter Iodine-129(b)
> 55 pCi/ liter 10% of known value r
L Uranium-238,
< 35 pci/ liter 6 pCi/ liter Nickel-63(b),
> 35 pCi/ liter 15% of known value
{
Iron-55 (b) 50 to 100 pCi/ liter 10 pCi/ liter 10% of known value
[
s.
(a) From EPA publication, "Envf ronmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year 1981-1982, EPA-600/4-81-004 (b) TIML limit.
E-21 F
L L
b
[
s
[
[
irreso1x v 1987 Land Use Census I
I I
I I
I I
F-1
L The 1987 Land Use Census was conducted during the growing season period from July 22nd through August 13th.
A land use census is required at least once every 12 months to satisfy the Clinton Power Station Technical Specifications.
The land use census is performed to identify within a distance of 8 km (5 miles), the locations in each of the 16 meteorological sectors of the nearest milk animals, the nearest residence and I
the nearest garden of greater than 50 square meters producing broadleaf vegetation.
Also, the census shall identify within a I
distance of 5 km (3 miles), the location in each of the 16 meteorological sectors of all milk animals and all gardens of greater than 50 square meters producing broadleaf vegetation.
The 1987 census results are. examined to ensure that the Radiological Environmental Monitoring Program will provide representative measurements of radiation and radioactive I
materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures to the general public resulting from the operation of the Clinton Power Station.
The following changes were made as a result of the 1987 Land Use Census:
1.
A new vegetation sample site CL '17 was established in October 1987 at 0.9 miles in the north sector and sample I
site CL-18 was deleted.
2.
A new cow milk sample site was identified at 3.2 miles in the northeast sector but is unavailable for sampling.
I Samples of vegetation at sample site CL-ll5 at 0.9 miles northeast are taken due to the unavailability of milk samples.
F The results of the 198; Land Use Census are presented in tabulated form.
Table F-1 provides the nearest residence in each sector, Table F-2 provides the dairy and/or livestock results and I
Table F-3 provides the garden census results within a distance of five miles.
~
6 F-2
\\
E TABLE F-1 l
1987 ANNUAL LAND USE CENSUS l
(NEAREST RESIDENCE) l DIRECTION DISTANCE
'JAME, ADDRESS, PHONi: NUMBER (miles) l N
0.9 R
N 0.9 NNE 0.9 NE 1.2 I
ENE 2.5 ENE 2.5 E
1.1 I
ESE 2.3 ESE 3.2 SE 2.9 SSE 1.7 I
WSW l.5 W
2.0 WNW l.6 NW l.6 I
NNW l.6
- Obtained upon request from the Clinton Power Station Radiological Environmental Group I
n 1
F-3
M M
M M
M M
M M
M M
l C
TABLE F-2 1987 ANNUAL LAND USE CENSUS (DAIRY AND/OR LIVESTOCK)
DISTANCE
- NAME, (MILES)
ADDRESS NO.
NO.
AND AND PHONE NO.
COWS NO.
GOATS DAIRY GRAZING DIRECTION NUMBER BREED COWS MILKED GOATS MILKED LIVESTOCK USED PERIOD i
l 0.9/N NA 0
0 0
0 31 NA April - October 2.8/N NA 0
0 1
0 0
NA April - October 3.0/N NA 0
0 0
0 10 NA April - October 1.3/NNE NA 0
0 0
0 20 NA April - October 2.0/NNE NA 4
0 0
0 6
NA April - October NA 5
0 0
0 14 NA April - October 2.5/NNE 3.2/NNE NA 0
0 0
0 40-50 NA April - October NA 0
0 0
0 15 NA April - Octobei 2.3/NE 3.2/NE NA 39 1
0 0
102 NA April - October NA/ENE NA NA NA NA NA NA NA NA 3.1/E NA 7
0 0
0 6
NA April - October y
5.7/ESE NA 0
0 0
0 10 NA April - October
^
2.9/SE NA 25 0
0 0
25 NA April - October 2.7/SSE NA 9
0 0
0 12 NA April - October 2.8/SSE NA 3
0 0
0 8
NA April - October NA 0
0 1
0 0
NA April - October 2.8/SSE 3.0/S NA 0
0 0
0 20 NA Year Round NA 0
0 0
0 15 NA April - October 3.3/SSW NA 0
0 0
0 5
NA April - October 3.4/SSW NA 12 0
0 0
12 NA April - October i
3.7/SW 2.9/WSW NA 0
0 0
0 17 NA April - October l
NA/W NA NA NA NA tiA NA NA NA NA NA/WNW NA NA NA NA NA NA NA NA NA NA/NW NA NA NA NA NA NA NA NA NA 1.0/NNW NA 0
0 0
0 31 NA April - October l
TOTALS NA 104 2
1 0
368-378 NA Mainly April to October
- Obtained upon request from the Clinton Power Station Radiological Environmental Group
. l
's
W
~
v.
TA3LE F-3 L
1987 ANNUAL LAND USE CENSUS (GARDEN)
I
- Name, Address, Distance and Phone Type of Direction (miles)
Number Vegetation How Used N
0.9 Cabbage, Lettuce Own Use N
0.9 Cabbage Own Use i
N 1.4 Lettuce Own Use N
2.7 Cabbage Ovn Use N
2.8 Cabbage, Lattuce Own Use l
N 2.8 Lettuce Own Use.
N 3.0 Cabbage, Lettuce Own Use NNE 0.9 No Broad Leaf Own Use NUE 2.0 Cabbage, Lettuce Own Use i
NNE 2.5 Lettuce own Use NNE 2.5 Cabbage, Lettuce Owr. Use NNE 2.5 Cabbage Own Use I
NNE 2.7 Cabbage, Lettuce Own Use NNE 3.0 Cabbage, Lettuce own Use NNE 3.2 Cabbage, Lettuce Own Use I
NNE 3.4 No Broad Leaf Own Use NE 1.2 Lettuce Own Use NE 1.9 No Broad Leaf Own Use I*
.NE 3.4 Cabbage, Lettuce Own Use ENE 2.5 Cabbage, Lettuce own Use ENE 2.6 Cabbage, Lettuce own Use ENE 2.6 Cabbage, Lettuce Own Use I
ENE 2.6 Cabbage, Lettuce Own Use ENE 2.7, Cabbage, Lettuce Own Use ENE 2.7 Cabbage, Lettuce Own Use l
ENE 2.7 Cabbage, Lettuce Own Use ENE 2.7 Cabbage, Lettuce Owm Use ENE 2.7 Cabbage, Lettuce Own Use I
ENE 2.8 Lettuce, Spinach Own Use ENE 2 '. 8 Cabbage, Lettuce.
Own Use ENE 2.8 Cabbage, Lettuce Own Use ENE 2.8 Cabbage, Lettuce Own Use i
ENE 2.9 Cabbage, Lettuce Owr Use ENE 2.9 Cabbage, Lettuce Own Use E
1.1 Cabbage, Lettuce Own Use E
1.5 Cabbage, Chard, own Use Lettuce E
2.4 Cabbage own Use I
E 2.4 Cabbage, Lettuce Own Use E
2.4 Cabbage Own Use E
3.1 Lettuce Own Use ESE 3.2 Cabbage, Lettuce own Use I
SE 2.9 Lettuce Own Use SSE 2.7 Cabbage, Lettuce Own Use F-5
4 l
TABLE F-3 (continued) l 1987 ANNUAL LAND USE CENSUS l
(Garden) l I
- Name, Address, Distance and Phone Type of Direction (miles)
Number Vegetation How Used S
3.C No Broad Leaf Own Use S
3.0 Cabbage, Lettuce Own Use I
SSW 3.0 Cabbage, Lettuce Own Use SSW 3.2 Cabbage, Lettuce Own Use SSW 3.2 Cabbage, Lettuce Own Use SSW 3.3 Cabbage, Lettuce Own Use i.
SSW 3.4 Cabbage, Lettuce own Use SW 0.8 No Broad Leaf Own Use SW 3.5 No Broad Leaf Own Use l
SW 3.6 Lettuce own Use SW 3.7 Cabbage, Lettuce Own Use WSW l.5 No Broad Leaf Own Use WSW 2.3 Lettuce Own Use I
WSW 2.3 No Broad Leaf Own Use WSW 2.3 Cabbage, Lettuce Own Use WSW 3.1 Cabbage Own Use I
WSW 3.3 Cabbage, Lettuce Own Use WSW 3.7 Cabbage, Lettuce Own Use WSW 3.7 Cabbage, Lettuce Own Use W
1.4 No Broad Leaf Own Use I
W 1.7 Cabbage, Lettuce Own Use W
2.0 Cabbage, Lettuce Own Use W
2.0 Cabbage, Lettuce Own Use I
W 2.3 Cabbage, Lettuce Own Use W
2.9 Cabbage, Lettuce Own Use W
3.3 Cabbage Own Use I
WNW 1.0 Cabbage, Lettuce Own Use WNW l.6 Cabbage, Lettuce Own Use WhV 2.0 Cabbage, Lettuce Own Use WNW 2.8 Cabbage, Lettuce Own Use I
WNW 3.3 Cabbage, Lettuce Own Use WNW l.4 Cabbage, Lettuce Own Use NW l.6 Cabbage, Lettuce Own Use i
NW l7 Cabbage, Lettuce Own Use NW 2.3 Cabbage, Lettuce own Use NW 2.4 Cabbage, Lettuce Own Use NNW 1.6 No Broad Leaf Own Use I
NNW 2.3 Cabbage, Lettuce own Use NNW 2.5 Lettuce own Use 1
- Obtained upon request from Clinton Power Station Radiological i
Environmental Group 1
F-6
L r
L
[
i i
APPENDIX G 1987 Meteorological Sumary i
I I
I I
I I
I l
C-1 l
u r
L Cumulative joint frequency distribution of wind speed, wind direction and atmospheric stability for the period January 1,
[
1987 through December 31, 1987 is presented in Appendix G.
There are seven stability classes from A to G: stability Class A is the least severe and Class G most severe.
This data was derived from the data collected by the on-site meteorological tower.
I I
I I
I I
I I
I I
I I
I I
I G-2
I TABLE G-1 l
ANNUAL JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL PARAMETERS - 1987 STABILITY CLASS A I
WINO $ PEED (MPH) AT 10 NETER LEVEL i
Dir ec ti on 1-3 4-7 8-12 13-18 19 24 24 TOTAL I
N 8.00E00 2.60E01 4.00E01 6.00E00 0.00E-01 0.00E-01 8.00E01 NNE 6.00E00 2.10E01 1.80E01 4.00E00 0.0CE-01 0.00E-01 4.90E01 NE 2.60E01 6.50E01 1.60E01 6.00E00 0.00E-01 0.00E-01 1.13E02 ENE 1.40E01 3.80E01 3.60E01 8.00E00 1.00E00 2.00E00 9.90E01 1
E 2.10E01 3.70E01 2.40E01 3.00E00 0.0CE-01 0.00E-01 8.50E01 ESE 3.00E01 4.10E01 2.10E01 0.00E-01 1.00E00 0.00E-01 9.30E01 SE 1.80E01 5.20E01 1.20E01 0.00E-01 0.00E-01 0.00E-01 8.20E01 i
SSE 2.40E01 9.40E01 1.30E01 6.00E00 0.00E-01 0.00E-01 1.37E02 2.70E01 1.41E02 8.30E01 2.10E01 0.00E-01 0.00E-01 2.72E02 SSW 1.70E01 7.20E01 8.60E01 1.70E01 0.00E-01 0.00E-01 1.92E02 SW 9.00E00 5.30E01 4.80E01 1.80E01 3.00E00 0.00E-01 1.31 E02 I
WSW 7.00E00 4.10E01 3.50E01 3.60E01 1.30E01 5.00E00 1.37E02 0
9.00E00 1.50E01
'3.10E01 4.70E01 5.00E00 1.40E01 1.21E02 kW 1.30E01 2.50E01 4.60E01 3.30E01 6.00E00 3.00E00 1.26E02 I
W 1.30E01 6.60E01 3.90E01 4.20E01 1.20LO1 0.00E-01 1.72E02 NNW 5.00E00 4.50E01 3.50E01 2.30E01 2.00000 0.00E-01 1.10E02 Total 2.47E02 8.32E02 5.83E02 2.70E02 4.30E01 2.40E01 2.00E03 I
STABillTY CLASS 8 I
Vf >O SPEED (MPH) AT 10 METER LEVEL Direction 1-3 47 8-12 13 18 19-24 24 TOTAL N
0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I
NPE 0.00E-01 2.00E00 1.00E00 2.00E00 0.00E-01 0.00E-01 5.00E00 NE 0.00E 01 0.00E-01 4.00E00 4.00E00 0.00E-01 0.00E-01 8.00E00 ENE 0.00E-01 0.00E-01 4.00E00 0.00E-01 0.00E-01 0.00E-01 4.00E00 I
E 0.00E 01 4.00E00 0.00E-01 0.00E-01 0.00E-01 0.00E-01 4.00E00 ESE 0.00E-01 5.00E00 2.00E00 0.00E-01 0.00E 01 0.00E-01 7.00EDO SE 0.00E-01 7.00E00 3.00E00 0.00E 01 0.00E-01 0.00E-01 1.00E01 I
SSE 0.00E-01 2.00E00 2.00E00 0.0 0E-01 0.00E-01 0.00E-01 4.00E00 0.00E-01 4.00E00 7.00E00 6.00E00 0.00E -01 0.00E-01 1.50E01 SSW 0.00E-01 1.00 LOO 1.70E01 0.00E-01 4.00E00 0.00E-01 2.20E01 SW 0.00E-01 2.00E00 1.00E01 1,00E00
- 0. 00E-01 0.00E-01 1.30E01 I
CSW 0.0CE-01 1.00E00 1.10E01 1.20E01 0.00E 01 0.00E-01
- 2. 40E01 W
0.00E-01 2.00E00 9.00E00 4.00E00 2.00E00 0.00E-01 1.70E01 WW 0.00E-01 2.00E00 7.00E00 6.00E00 1.00E00 0.00E-01 1.60E01 W
0.00E-01 3.00E00 1.10E01 1.00E01 1.00E00 0.00E-01 2.50E01 NNW 0.00E-01 1.00E00 6.00E00 2.00E00 0.00E-01 0.2CE-01 9.0,0E_00 Total 0.00E-01 3.60E01 9.40E01 4.50E01 8.00E00 0.00E-01 1.83E02 i
G.3
4 I
TABLE G-1 ANNUAL JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL PARAMETERS - 1987 1
$TABILtTY CLASS C WIND $ PEED (FPH) AT 10 METER LEVEL I
Direction 1-3 4-7 8-12 13 18 19 24 24 TOTAL N
0.00E-01 2.00E00 3.00E00 0.00E-01 1.00E00 0.00E-01 6.00E00 tNE 0.0 0E-01 1.00E00 3.00E00 1.00E00 0.00E-01 1.00E00 6.00E00 NE 0.00E 01 3.00E00 1.10E01 0.00E-01 1.00E00 0.00E-01 1.50E01 i
ENE 0.00E-01 4.00E00 6.00E00 0.00E-01 0.00E-01 0.00E-01 1.00E01 E
0.00E-01 4.00E00 1.00E00 0.00E-01 0.00E-01 0.00E-01 5.00E00 E5E 0.00E 01 8.00E00 3.00E00 0.00E-01 0.00I-01 0.00E-01 1.10E01 I
SE 1.00E00 1.20E01 2.00E00 0.00E-01 0.00E-01 0.00E-01 1.50E01 SSE 0.00E-01 1.00E00 2.00E00 2.00E00 0.00E-01 0.00E-01 5.00E00 3
0.00E-01 4.00E00 7.00E00 3.00E00 1.00E00 0.00E-01 1.50E01 SSW 1.00E00 1.00E00 1.30E01 2.00E00 0.00E-01 0.00E-01 1.70E01 I
S4 0.00E-01 3.00E00 9.00E00 5.00E00 0.00E-01 0.00E-01 1.70E01 WSW 0.00E-01 7.00E00 8.00E00 5.00E00 0.00E-01 0.00E-01 2.00E01 O
1.00E00 2.00E00 1.30E01 6.00E00 0.00E-01 0.00E-01 2.20E01 I
Whv 1.00E00 1.00E00 2.00E00 1.20E01 0.00E-01 0.00E-01 1.60E01 NV 1.00E00 3.00E00 1.20E01 4.00E00 0.00E-01 0.00E-01 2.00E01 NNW 0.00E-01 0.00E00 8.00E00 2.00E00 0.00E-01 0.00E-01 1.00E01 Votal 5.00E00 5.60E01 1.03E02 4.20E01 3.00E00 1.00E00 2.10E02 I
STABfLtTY CLAS$ D WIND SPEED (MoH) AT 10 FETER LEVEL Direetton 1 -3 4-7 8 12 13 18 1* In 24 TOTAL N
8.00E00 2.70E01 9.50E01 2.30E01 6.00E00 1.00E00 1.60E02 NNE 8.00E00 2.70E01 3.70E01 3.60E01 1.90E01 7.00E00 1.34E02 I
tE 9.00E00 2.20E01 5.00E01 6.30E01 8.00E00 0.00E-01 1.52E02 ENE 5.00E00 1.40E01 1.00E01 0.00E-01 0.00F-01 0.00E-01 2.90E01 E
6.00E00 1.80E01 4.00E00 0.00E-01 0.00E-01 0.00E-01 2.80E01 I
ESE 7.00E00 2.70E01 2.00E01 1.50E01 1.00E00 0.00E-01 7.00E01 SE 1.00E01 5.10E01 3.80E01 1.30E01 1.00E00 0.00E-01 1.13E02
$$E 5.00E00 3.50E01 3.50E01 1.60E01 0.00E-01 0.00E-01 9.10E01' 9
5.00E00 2.10E01 7.30E01 2.00E01 1.00E00 0.0CE-01 1.20E02 I
SSW.
4.00E00 4.70E01 7.70E01 2.00E01 6.00E00 0.00E-01 1.54E02 SW 8.00E00 2.00E01 4.80E01 1.50E01 0.00E-01 0.00E-01 9.10E01 09W 2.00E00 2.90E01 2.70E01 6.00E00 0.00E-01 0.00E-01
- 6. 40E01 W
5.00E00 2.40E01 6.80E01 3.60E01 1.50E01 0.00E-01 1.48E02 WNW 3.00E00 1.70E01 8.40E01 3.90E01 8.00E00 0.00E-01 1.51E02 PM 3.00E00 2.20E01 6.80E01 2.10E01 3.00E00 0.00E-01 1.17E02 NNW 4.00E00 2.20E01 3.00E01 1.00E00 0.00E-01 0.00E-01 5.70E01 Total 9.20E01 4.23E02 7.64E02 3.24E02 6.80E01 8.00E00
- 1. 68E_03 s
G-4
4 TABLE G-1 l
ANNUAL JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL PARAMETERS - 1987 STABILITY CLASS E i
Win.1 SPEED (MPH) AT 10 METER LEVEL Dir ecti on 1 -3 4-7 8-12 13-18 19 24 24 TOTAL N
7.00E00 2.70E01 5.20E01 1.30E01 5.00E00 0.00E-01 1.04 E02 NNE 7.00E00 2.50E01 3.90E01 1.50E01 4.00E00 0.00E-01 9.00E01 NE 9.00E00 5.30E01 7.40E01 2.90E01 6.00E00 0.00E-01 1.71 E02 8.00E00 3.60E01 2.60E01 1.00E01 7.00E00 0.00E-01 8.70E01 1
ENE E
1.10E01 2.20E01 4.00E00 0.00E -01 0.00E-01 0.00E 01 3.70E01 ESE 1.80E01 7.40E01 3.60E01 5.000%
0.00E-01 0.00E-01 1.33E02 SE 1.70E01 7.20E01 2.60E01 4.00E00 0.00E-01 0.00E-01 1.19E02 i
SSE 1.50E01 7.60E01 6.50E01 4.00E00 0.00E-01 0.00E-01 1.60E02 S
1.30E01 1.09E02 1.23 E02 1.70E01 2.00E00 0.00E-01 2.64E03 SSW 9.00E00 8.10E01 1.61E02 4.40E01 2.00E00 0.00E-01 2.97E02 SW 1.40E01 2.80E01 5.80E01 2.30E01 0.00E-01 0.00E-01 1.23E02 CSW 5.00E00 3.90E01 3.40E01 4.00E00 0.00E-01 0.00E-01 8.20E01 0
1.40E01 3.10E01 7.10E01 3.40E01 3.00E00 0.00E-01 1.53E02 I
WNW 1.30E01 3.80E01 4.20E01 1.90E01 3.00E00 0.00E-01 1.15E02 PM 7.00E00 3.90E01 3.90E01 2.80E01 3.00E00 1.00E00 1.17E02 NtM 3.00E00 2.30E01 3.00E01 2.80E01 7.00E00 2.00E00 9.30E01 1.70E02 7.73 E02 8.80E02 2.77E02 4.20E01 3.00E00 2.15E03 I
T tal I
STABILITY CLASS F WIND SPEED (MPH) AT 10 METER LEVEL Direction 13 47 8-12 13-18 19-24 24 TOTAL N
1.90E01 1.70E01 7.00E00 0.00E-01 0.00E-01 0.00E -01 4.30E01 1.00E01 2.00E01 5.00E00 1.00E00 0.00E-01 0.00E-01 3.60E01 I
NNE NE 6.00E00 4.70E01 7.00E00 0.00E-01 0.00E-01 0.00E 01 6.00E01 ENE 1.00E01 3.90E01 3.30E01 4.70E01 6.00E00 0.00E 01 1.35E02 E
2.10E01 3.90E01 3.10E01 1.60E01 0.00E-01 0.00E-01 1.07E02 I
ESE 1.70E01 3.50E01 3.00E00 1.00E00 0.00E-01 0.00E-01 5.60E01 SE 1.10E01 3.90E01 2.00E00 0.00E-01 0.00E-01 0.00E-01 5.20E01
$$E 1.50E01 6.60E01 6.00E00 0.00E-01 0.00E-01 0.00E-01 8.70E01 i
S 1.10E01 8.10E01 2.70E01 2.00E00 0.00E-01 0.00E 01 1.21 E02 553 1.40E01 4.80E01 5.40E01 2.00E00 0.00E-01 0.00E-01 1.18E02 SW 1.60E01 5.80E01 5.60E01 3.00E01 0.00E-01 0.00E-01
- 60E02 CSU 1.00R01 2.50E01 2.50E01 1.70E01 4.00E00 0.00E-01 8.10E01 W
1.20E01 2.20E01 1.60E01 3.00E00 1.00E00 0.00E-01 5.40E01 WNW 1.40E01 2.70C01 6.00E00 0.00E-01
- 0. 00E-01 0.00E-01 4.70E01 tM 1.00E01 2.90E01 7.00E00 1.00E00 1.00E00 0.00E-01 4.80E01 NtM 5.00E00 7.00E00 8.00E00 6.00E00 8.00E00 5.00E00 3.90E01 Total 2.01 E02 5.99E02 2.93E02 1.26E02 2.00E01 5.00E00 1.24E03 G-5
TABLE G-1 l
Annual Joint Frequency Distribution of Meteorological Parameters - 1987 l
STABILITY CLASS C WIND SPEED (MPH) AT 10 METER LEVEL Ofrection 1-3 6-7 8-12 13-18 19 24 24 TOTAL l
N 7.00E00 5.00E00 2.00E00 0.00E-01 0.00E-01 0.00E-01 1.40E01 N.E 1.00E01 1.00E01 2.00E00 0.00E-01 0.00E-01 0.00E-01 2.20E01 NE 2.50E01 7.10E01 3.00E00 0.00E-01 0.00E 01 0.00E-01 9.90E01 ENE 1.80E01 3.10E01 9.00E00 2.00E01 2.00E00 0.00E 01 8.00E01 E
1.00E01 1.30E01 1.50E01 4.10E01 3.00E00 0.00E-01 8.20E01 ESE 1.50E01 4.00E00 0.00E-01 0.00E-01 0.00E-01 0.00E 01 1.90E01 SE 8.00E00 2.70E01 1.00E00 0.00E-01 0.00E-01 0.00E-01 3.60E01
$$E 2.10E01 2.70E01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 4.80E01 5
1.90E01 2.90E01 4,00E00 4.00E00 0.00E-01 0.00E-01 5.60E01 SSW 9.00E00 1.70E01 5.00C00 0.00E-01 0.00E-01 0.00E-01 3.10E01 SW 9.00E00 3.80E01 3.00E00 6.00E00 2.00E00 0.00Ee01 5.80E01 CSW 1.10E01 1.90E01 1.10E01 1.40E01 0.00E-01 0.00E-01 5.50E01 W
9.00EC3 7.00E00 1.00E00 0.00E-01 0.00E 01 0.00E-01 1.70E01 WNW 2.10E01 1.10E01 0.00E-01 0.00E 01 0.00E-01 0.00E-01 3.20E01 NW 1.10E01 1.00E01 1.03E00 0.00E-01 0.00E 01 0.00E-01 2.30E01 NNW 1.00E01 0.00E-01 0.00E-01 1.00E00 0.00E-01 0.00E 01 1.10E01 Votal 2.14E02 3.1SE02 5.70F.01 8.60E01 7.00E00 0.00E-01 6.83E02 PERIODS OF CALM (HOURS): 3.000E00 M)URS OF INVALID DATA : 0.000E-01 HOURS OF CD00 DATA
- 8.196E3 = 93.6% OF TOTAL HOURS G-6
[
[
TABLE G-2 CLASSIFICATION OF ATMOSPHERIC STABILITY F
Stability Pasquill 1 std. Dev.
Temperature change Classification Categories (degrees) with height ( C/100m)
Extremely unstable A
25.0
-1.9 Moderately unstable B
20.0
-1.9 to -1.7 Slightly unstable C
15.0
-1.7 to -1.5 i
Neutral D
10.0
-1.5 to -0.5 Glightly stable E
5.0
-0.5 to 1.5 Moderately stable F
2.5 1.5 to 4.0 Extremely stable G
1.7 4.0 1 Standard deviation of horizontal vind direction over a period of 15 minutes to I hour.
I The values shown are averages for each stability classification.
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APPENDIX H 1987 REMP Sample Collection and Analysis Methods r
9 6 men e
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1 l
1
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Analysis methods used to determine sample media activities are listed in Table H-1.
The pr,ocedures listed are those issued by the analysis laboratory that are reviewed and approved by the Radiological Environmental Group of the Clinton Power Station Radiation Protection Department.
Any revisions to these procedures are routed through the I
radiological environmental group prior to implementation by the analysis laboratory.
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1 H-2 I
'M M
M M
M M
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TABLE 11-1 C11NTON POWER STATION RADIOLOGICAL INVIROff4 ENTAL N0f3lTORINC PROGRAM l
StM4ARY OF SAMPt F cot 1ECTION AND ANALYSIS HETHODS 1987 l
Approximate Teledyne Sarnple Sample Size Procedure Procedure Analysis Medium Sampling Method Cn11ccted Number Abstract Cross Beta AP Continuous air 280m TIML-AP-02 Sample counted on a low level gas flow sampling through proportional counter, filter media WW Crab 3.6L TIML-W(DS)-01 Sanple evaporated on a stainless steel planchet for low-level gas flow proportional counting 3:
W SW Crab 3.6L TIML-W(DS)-01 Sagle evaporated on a stainless steel e
planchet f or low-level gas flow proportional counting SW Composite 3.8L TIML-W(DS)-01 Samle evaporated on a stainless steel planchet for low-Icvel gas flow proportional counting VE Crab 2.5k g TIML-AB-01 Sample at.ked f or low-level gas flow proportional counting BS Grab 1.5-2.Ok g TIML-AB-01 Sanple ground f or low-level gas flow proportional courting SS Crab 1.5-2.06g T IML-AB-01 Sainple ground f or low-level gas flow proportional counting F
i
O O
O O
O O
O O
O O
O O
O O
O O
O I1 I'~1 I
TABLE H-1 CLINTON POWER STATION RADIOLOGICAL ENVIR00 MENTAL MONITORING PROCRAM StBetARY OF SAfFLE COLLECTION ADO ANALYSIS ETH005 1987 Appronteate Teledyne Sample Sample Size Procedure Procedure Analysts Medlun Sampling Method Collected Mu h Abstract Camma AP Composite 3640m TIML-CS-01 Germentum gamma isotopic analysis Spectroscopy C
Crab 2.2kg T IML-CS-01 CereanIum ganuma isetopic analyais WW Crab 3.8L TIML-CS-01 Cermanium gamme isotopic analysis WW Composite 15.2L T IML-CS-01 Germentum gamme isotopic analysis I^
SW Compostte 3.8L TIML-CS-01 Germentum gamuna isotopic analysts VE Crab 2.5kg i1ML-CS-01 Cermanfisa gamma isotopic analysis BS Crab 1.5-2.0kg TIML-CS-01 Cermantisa gamene Isetopic analysis SS Crab 1.5-2.0k g TIML-CS-01 Germ elum gamme isotopic analysis l
St Crab 0.5kg T 184.-C5-01 Germanfum gamme isotopic analysts F
Crats 2.5k g TIML-05-01 Germanium gammu isotopic analysis 6
1 4
5
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M M
R R
R R
R
.R
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fl Fl f-~ l f
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TABLE H-1 CilNToft POWER STATION
{
RADIOLOGICAL ENVIR000 ENTAL MONITORING PROGRAP_
SteelARif 0F SAMPLE COLLECTION AND ANALYSIS METHODS 1987 Approntmate Teledyne Sample Sample Size.
Procedure Procedure Analysis Medium Samp1tng Method Collected Esuber Abstract M
Grab 3.8L TIML-CS-01 Germanium gasshe isotnpfc analysis TLD ID Continuous TLD TIML-TLD-01 Integration of thermally stimulated Emposure visible photons Cross Alpha SW Camposite 3.SL TIML-W(r$)-01 Sample evaporated on a stainless steel planchet f or low-level gas flow g
4 proportional counting WW Crab 3.8L TIML-W(DS)-01 Sample evaporated on a sta1niess steel planchet for low-level gas flee proportional counting WW Composite 15.2L TIML-W(DS)-01 Saaple evaporated on e sta n1ess steel a
planchet for low-Icvel gas flow proportional counting BS Crab 1.5-2.Okg TIML-A8-01 TIML-AB-01 Sample pulverized for low-level gas flow proportional counting i
1 I
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s
-' M M
M M
M M
M 1
R R
f TABLE H-1 CLINTON POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORINC PROGRAM SLNHARY OF SAMPLE COLLECTION AND ANALYSIS METH005 1987 Approximate Teledyne Sagle Sample 51ze Procedure Procedure Anolysi s Meditsn Sampling Method Collected Nurnber Abstract Cross Alpha SS Crab 1.$-2.Okg TIML-AB-01 Saaple pulverized for low-level gas flow proportional counting Sr-90 BS Grab 1.5-2.Okg T IML-SR-06 Hydrochloric acid teach and low-level gas flow proportfor.a1 counting Crab 1.5-2.Okg T IML-SR-06 Hydrochloric acid leach and low-level gas j
f1ow proportional counting y
Distillation followed by counting in a Composite 3.8L TIML-T-02 Tr Mf um WW Ifquid scintillation counter SW Composite 3.8L TIML-T-02 Distillation followed by counting in a if quid scintillation counter DW Coroposi te 3.8L TIML-T-02 Distillation followed by counting in a liquid scintillation counter
E
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APPENDIX I 1987 Data Table > (Raw Data)
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r The data tables presented in Appendix 1 represent the raw data used L
to derive the results stated in this report, The data was obtained from the final monthly progress report submitted to the Clinton Power Station by Teledyne Isotopes Midwest Laboratory.
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I I-2
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l TABLt' l-1 CRO5$ BETA AND IODINE - 131 ACTIVITY IN AIR PARTICULATES FOR 1987 (a)
(pCl/m i 1 s.d.)
Collection Period CL-1 CL-2 CL-3 CL-4
_ CL 6 2/25/87 3/4/87 0.019*0.004 0.014t0.003 0.022*0.004 0.015to.004 0.018t0.004 1
3/4/87 3/11/87 0.032*0.004 0.027*0.004 0.031:0.004 0.028*0.004 0.03120.004 3/11/87 3/18/87 0.029*0.004 0.022t0.004 0.023t0.004 0.030t0.004 0.022t0.004 3/I8/87 3/25/87 0.021*0.004 0.018t0.004 0.016*0.004 0.015*0.003 0.020*0.004 1
3/25/87-4/2/87 0.01820.004 0.015t0.004 0.019t0.004 0.015*0.0%
0.018t0.004 4/2/87 4/8/87 0.04920.005 0.036t0.004 0.041*0.005 0.027*0.004 0.032*0.004 4/8/87 4/15/87 0.016t0.004 0.012t0.005 0.014t0.004 0.012t0.004 0.019t0.004 4/15/87 4/22/87 0.014t0.004 0.012 0.003 0.016t0.004 0.018 0.004 0.017t0.0M 1
4/22/87 4/29/87 0.027t0.004 0.020*0.004 0.019*0.004 0.019*0.004 0.025to.004 4/29/87-5/6/87 0.029t0.004 C.026 0.004 0.030*0.004 0.029*0.004 0.027*0.004 5/6/87-5/13/87 0.022 0.004 0.021t0.004 0.027t0.004 0.026:0.004 0.024to.004 I
5/13/87-5/20/87 0.022t0.004 0.015t0.004 0.021 t 0.004 0.026t0.004 0.02720.004 5/20/87-5/27/87 0.015*0.004 0.014*0.004 0.013t0.004 0.008t0.003 0.016t0.004 5/27/87-6/3/87 0.018t0.005 0.015*0.004 0.022to.004 0.015t0.004 0.015t0.004 6/3/87-6/10/87 0.021:0.005 0.020*0.005 0.019t0.004 0.026*0.005 0.026 0.005 I
6/10/87-6/17/87 0.016t0.004 0.078to.011*
0.030t0.004 0.071 0,011*
0.030:0.004 6/17/87 6/24/87 0.024t0.004 0.024*0.004 0.02Rt0.004 0.024to.004 0.028*0.004 6/24/87 7/1/87 0.025t0.004 0.023 t0.004 0.027*0.004 0.036t0.004 0.030*0.004 I
7/1/87-7/6/87 0.020 0.004 0.028*0.010 0.024:0.004 0.022t0.004 0.024*0.004 7/8/87-7/15/87 0.014 0.004 0.01410.004 0.019*0.004 0.018t0.006 0.016*0.004 7/15/87-7/22/87 0.042*0.005 0.038t0.005 0.03220.004 0.018 to.010 0.036t0,005 7/22/87 7/29/87 0.033 0.004 0.035to.004 0.031:0.004 0.033to.004 0.032t0.004 I
7/29/87 8/5/87 0.033*0.004 0.028*0.004 0.030 0.004 0.033t0.004 0.033t0.004 8/5/87 8/12/87 0.02220.004 0.024to.004 0.023:0.004 0.030*0.004 0.02720.004 8/12/87-8/19/87 0.033t0.004 0.030* 0.0M 0.030*0.004 0.03260.004 0.02620.004 8/19/87 8/26/87 0.031:0,004 0.024*0.004 0.023 t o.004 0.023t0.004 0.027:0.004 8/26/87-9/2/87 0.02920.004 0.025 t 0.004 0.026t0.004 0.025t0.004 0.027 0.004 9/2/87 9/9/87 0.044*0.005 0.04020.005 0.050 0.005 0.04520.005 0.044t0.005 I
9/9/87-9/16/87 0.042k0.005 0.038to.004 0.040 0.004 0.041*0.005 0.04 5* 0. 00'r 9/16/87-9/13/87 0.023 t0.004 0.022k0.003 0.01820.003 0.020 0.003 0.019t0.003 9/23/87-9/30/87 0.04020.004 0.034*0.004 0.04020.004 0.031t0.004 0.040*0.005 9/30/87-10/7/87 0.016 0.004 0.017t0.004 0.014 t0.004 0.016*0.004 0.017t0.004 I
10/7/87 10/14/87 0.016t0.004 0.024*0.004 0.022:0.004 0.022t0.004 0.025*0.004 10/14/87-10/21/87 0.029t0.004 0.033 t0.004 0.035 t0. 004 0.033t0.004 0.039*0.004 10/21/87-10/28/87 0.023t0.004 0.023 0.004 0.025t0.004 0.021 t 0.004 0.024:0.004 1
10/28/87 11/4/87 0.04520.005 0.04820.005 0.054 t0. 005 0.044to.005 0.049t0.005 11/4/87 11/11/87 0.034t0.004 0.027:0,004 0.026*0.004 0.027ko.004 0.028 0.004 11/11/87-11/18/87 0.035t0.004
- 0. 034 t0.004 0.032t0.004 0.030t0.0J4 0.032t0.004 11/18/87 11/25/87 0.04020.004 0.03820.004 0.038t0.004 0.038*0.004 0.040*0.0M 1
11/25/87 12/2/87 0.012*0.003 0.017 t0.0 04 0.014t0.003
- 0. 014 t0.004 0.012t0.003 12/2/87 12/9/87 0.026t0.004 0.028*0.004 0.031:0.004 0.032t0.004 0.031 t0.004 12/9/87 12/16/87 0.020t0.004 0.018t0.004 0.021:0,004 0.02220.004 0.018t0.004'
~
12/16/87 12/23/87 0.032t0.004 0.032t0.004 0.036t0.004 0.030t0.004 0.032 t 0. 004 12/23/87 12/30/87 0.0 26 t0. 004 0.02710.004
- 0. 0 29t0.004 0.02410.004 0.024to.004 T-3 L
j
L H
TABLE l-1 (conti nued)
{
F L
Collection Period CL*7 CL-8 CL lif e)
CL 94
=
2/25/87 3/4/87 0.018*0.0M 0.017t0.004 0.019t0.004 0.013e0.003 3/4/87 3/11/87 0.035*0.004 0.028*0.004 0.030*0.004 0.031*0.004 3/11/87 3/18/87 0.031 t0.006 0.026*0.004 0.030t0.004 0.02710.004 3/18/87 3/25/87 0.021 t 0. 004 0.018t0.004 0.014t0.003 0.01920.0%
{
3/25/87 4/2/87 0.018 0.004 0.016*0.0 %
0.016t0.0%
0.015*0.004 4/2/87-4/8/87 0.032*0.004 0.054t0.005 0.058*0.004
- 0. 041 t 0.005 4/8/87-4/15/87 0.018*0.004 0.015*0.004 0.01840.004 0.014*0.004 4/15/87 4/22/87 0.012*0.004 0.012t0.004 0.017*0.004 0.010t0.004 4/22/87-4/29/87 0.021*0.004 0.023 t0.004 0.025t0.004 0.016*0.0 %
4/29/87 5/6/87 0.025*0.004 0.024t0.004 0.028*0.004 0.028t0.004 5/6/87 5/13/87 0.026to.004 0.021 t0.004 0.022t0.004 0.026*0.004 5/13/87-5/20/87 0.024 0.004 0.023t0.004 0.024t0.004 0.016*0.004 5/20/87 5/27/87 0.010*0.003 0.012t0.003 0.014r0.004 0.012*0.003 l
5/27/U7 6/3/87 0.009AO.005 0.013t0.004 0.020t0.004 0.005 0.004*
I 6/3/87-6/10/87 0.023t0.005 0.017t0.004 0.022*0.005 0.023 0.005 p
6/10/87 6/17/87 0.027*0.004 0.043*0.005 0.030*0.004 0.011 t 0.003 l
6/17/87 6/24/87 0.026*0.004 0.028 t0.004 0.02920.005 0.026*0.004 6/24/87 7/1/87 0.033*0.004 0.023*0.004 0.028*0.004 0.015t0.004 l
7/1/87 7/8/87 0.020*0.004 0.021*0.005 0.025*0.004 0.024 to.004 7/8/87 7/15/87 0.021*0.004 0.015t0.004 0.02220.004 0.016*0.004 I
7/15/87 7/22/87 0.03720.005 0.034*0.004 0.034t0.005 0.036*0.005 1
7/22/87 7/29/87 0.035t0.004 0.033t0.004 0.032*0.004 0.031:0.004 l
7/29/87 8/5/87 0.032to.004 0.034:0.004 0.034to.004 0.028t0.004 I
8/5/87 8/12/97 0.025t0.004 0.018*0.004 0.027*0.004 0.024*0.004 8/12/87 8/19/87 0.033t0.004 0.020t0.005 0.031:0.004 0.026t0.C04 8/19/87 8/26/&7 0.027t0.004 0.038t0.020 0.031 t 0. 004 0.029t0.004 8/26/87 9/t/87 0.028t0.004 0.026t0.0%
0.025t0.004 0.031*0.004 I
9/2/87 9/9/87 0.042 t 0.005 0.040 0.005 0.0,4*0.00S 0.039*0.005 l
9/9/87-9/16/87 0.03720.004
- 0. 04 2t0. 004 0.039t0.005 0.039 0.004 I
9/16/87 9/23/87 0.021t0.003
< 0.08 0*
0.018t0.003 0.022to.004 I
9/23/87 9/30/87 0.037t0.004 0.036t0.004 0.040t0.005 0.04220.004 9/30/87-10/7/87 0.014:0,004 0.017tc.004 0.019t0.004 0.018*0.004 l
10/7/87 10/14/87 0.023:0.004 0.023 0.004 0.024*0.004 0.022*0.004 I
10/14/87-10/21/87 0.033t0.004 0.036t0.004 0.03410.004 0.035t0.004 10/21/87 10/28/87 0.022*0.004 0.023:0.004 0.0250,004 0.023*0.004 10/28/87 11/4/87 0.048 0.005 0.043t0.004 0.04920.005 0.051t0.005 11/4/87 11/11/87 0.029t0.004 0.031t0.004 0.030 0.004 0.028t0.004 I
11/11/87 11/18/87 0.03220.004 0.036t0.004 0.031 t0.004 0.034t0.004 11/18/87-11/25/87 0.042t0.004 0.041t0.005 0.04320.004 0.033to.004 11/25/87 12/2/87 0.014t0.004 0.012:0,001 0.015 0,004 0.015t0.004 12/2/87 12/9/87 0.029t0.004 0.034t0.004 0.030t0.004 0.028t0.004 12/9/87-12/16/87 0.020*0.004 0.01920.004 0.018t0.004 0.015t0.004 12/16/87 12/23/87 0.032to.004 0.03320.004 0.028t0.004 0.030t0.004 12/23/87 12/30/87 0.025t 0.004 0.027t0.004 0.023:0.004 0.027:0,004 (a) all 1 131 activity is < 0.07 pCi/m unless otherwise noted in Teole B 1
- - unreliable results, excluded from the mean (c) control location, all other locations indicators I-4
L
?L TAett
-2 CAMMA ISOTOPIC ACTIVITY IN AIR PARTICULATES FOR 1987 (pCl/m i 1 s.d.)
r" Site isotope 1st Otr 2nd Otr 3rd Otr 4th Otr L
CL 1 Be-7 0.06*0.01 0.14*0.04 0.08*0.01 0.05*0.01 K 40
< 0.02
< 0.04
< 0. 01
< 0.01
(
< 0.002
< 0.003
< 0.001
< 0.001 Nb-95
< 0.002
< 0.002
< 0.001
< 0.001 Zr-95
< 0.002
< 0.005
< 0.002
< 0.002 Ru-103
< 0.002
< 0.004
< 0.001
< 0.001 Rv-106
< 0.010
< 0.019
< 0.007
< 0.007 Cs 134
< 0.0009
< 0.002
<0.0008
< 0.001 Cs 137
< 0.001
< 0.002
< 0.0008
< 0.007 l
p l
Ce-141
< 0.002
< 0.003
< 0.001
< 0.001 i
Ce 144
< 0.004
< 0.008
< 0.003
< 0.003 l
CL 2 Be 7 0.06i0.01 0.13*0.03 0.11*0.03 0.05t0.01 l
K-4 0
< 0.01
< 0.05 0.05*0.01
< 0.01 l
I Co-60
< 0.001
< 0.002
< 0.002
< 0.002 l
Nb-95
< 0.001
< 0.003
< 0.002
< 0.002 Zr-95
< 0.002
< 0.004
< 0.004
< 0.003 I
Ru 103
< 0.001
< 0.003
< 0.002
< 0.001 Pu 106
< 0.007
< 0.020
< 0.013
< 0.012 l
l Cs-134
< 0.0009
< 0.002
< 0.001
< 0.001 i
Cs 137
< 0.0010
< 0.002
< 0.002
< 0.001 Co 141
< 0.001
< 0.003
< 0.002
< 0.002 Co-144
< 0.003
< 0.007
< 0.007
< 0.007 I
CL 3 Be-7 0.08 0.02 0.0940.02 0.07:0.01 0.0620.02 K 40
< 0.01
<0.02
< 0.007
< 0.03 l
< 0.002
< 0.002
< 0.0008
< 0.002 Nb-95
< 0.002
<0.002
< 0.001
< 0.002 1
Zr-95
< 0.003
< 0.003
< 0.002
< 0.004-l Ru-103
<0.002
<0.002
< 0.001
< 0.002 Ru-106
< 0.01
< 0.010
< 0.007
< 0.012 Cs-134
< 0.002
<0.001
< 0.0007
< 0.001 Cs 137
< 0.002
< 0.001
< 0.0007
< 0.002 Ce-141
< 0.004
< 0.002
< 0.001
<0.002 Ce 144
< 0.008
< 0. 004
< 0.003
< 0.005 v
Ybe e-I-5
e TAELE l 2 ('.*ontinued)
~
Site isotope 1st Otr 2nd Otr 3rd Otr 4th Otr CL 4 Be 7
- 0. 08 t0.0 2 0.11to.02 0.10t0.02 0.0540.01 K 40
< 0.02
< 0.01
< 0.02
< 0.01 Co-60
< 0.002
< 0.001
< 0.002
< 0.001 Hb-95
< 0.001
< 0.002
< 0.003
< 0.002 Zr-95
< 0.002
< 0.003
< 0.003
< 0.002 Ru 103
< 0.001
< 0.001
< 0.002
< 0.001 Ru-106
< 0.008
< 0.009
< 0.012
< 0.010 Cs-134
< 0.0008
< 0.001
< 0.001
< 0.001 Cs-137
< 0.0007
< 0.001
< 0.001
< 0.001 Co 141
< 0.002
< 0.001
< 0.003
< 0.002 Ce 144
< 0.004
< 0.006
< 0.008
< 0.006 CL 6 Be-7 0.09t0.02 0.12t0.02 0.10t0.03 0.05*0.01 K-40
< 0.02
< 0.02
< 0.0s
<0.02 Co 60
< 0.002
< 0.002
<0.002
< 0.001 Nb-95
< 0.001
< 0.002
< 0.002
< 0. 001 Ir 95
< 0.003
< 0.003
<0.002
<0.002 Ru-103
< 0.002
< 0.002
< 0.003
< 0.001 Ru 106
< 0.01
< 0.02
<0.012
<0.009 Cs-134
< 0.001
< 0.001
< 0. 001
<0.001 p
< 0.001
< 0.002
<0.002
< 0.001 L
Co 141
< 0.002
< 0.003
<0.004
<0.001 Ce-144
< 0.006
< 0.009
<0.007
< 0.003
{
CL 7 Be 7 0.07*0.01 0.1 0:0.01 0.10*0.03 0.06t0.02 K-4 0
< 0.01
< 0.01
< 0.02 0.03*0.01 Co-60
< 0.002
< 0.001
< 0.002
< C.001 p
Nb-95
< 0.002
< 0.002
< 0.002
< 0.001 L
Zr-95
< 0.003
< 0.002
< 0.004
< 0.002 Ru-103
< 0.002
< 0.001
< 0.003
< 0.001-Ru-106
< 0.01
< 0.008
< 0.015
< 0.006 Cs-134
< 0.001
< 0.001
< 0.001
< 0.001 Cs 137
< 0.001
< 0.0007
< 0.001
< 0.001 te 141
< 0.003
< 0.001
< 0.004
< 0.002 C
Co-144
< 0.007
< 0.003
< 0. 008
< 0.005 e-d6 l
I-6
h
[
(
TABLE l 2 (Continued) l
[
Site isotope 1st otr 2nd Otr 3rd otr ath Ot e
[
CL 8 Be-7 0.06*0.01 0.1240.03 0.09t0.02 0.05t0.01 K 40
< 0.03
< 0.04
< 0.03
< 0.01 Co-60
< 0.002
< 0.003
< 0.001
< 0.001 Nb 95
< 0.0009
< 0.002
< 0.002
< 0.001 Zr-95
< 0.001
< 0.005
< 0.002
< 0.001 Ru-103
< 0.001
< 0.003
< 0.002
< 0.001 Ru-106
< 0.01
< 0.02
< 0.01
< 0.005 Cs 134
< 0.001
< 0.002
< 0.001
< 0.001 Cs-137
< 0.002
< 0.002
< 0.002
< 0.001 Co-141
< 0.001
< 0.003
< 0.003
< 0.001
{
Ce-I n
< 0.004
< 0.007
< 0.005
< 0.002 CL 11 Be-7 0.07t0.01 0.09to.02 0.08t0.02 0.0760.02
[
< 0.01
< 0.02
< 0.02
< 0.04 L
Co 60
< 0.001
< 0.002
< 0.002
< 0.001 Nb-95
< 0.001
< 0.003
< 0.003
< 0.002 Zr 95
< 0.002
< 0.003
< 0.004
< 0.003 Ru-103
< 0.001
< 0.002
< 0.002
< 0.002 Ru 106
< 0.006
< 0.01
< 0.01
< 0.01 Cs-134
< 0.0007
< 0.0009
< 0.001
< 0.001 Cs 137
< 0.0008
< 0.001
< 0.001
< 0.001 Ce-141
< 0.001
< 0.002
< 0.002
< 0.002 Co 1%
< 0.003
< 0.005
< 0.004
< 0.005 CL 94 Be 7 0.10t0.03 0.11*0.03 0.07*0.01 0.05to.01 K 40
< 0.03
< 0.04
<0.01
< 0.01 Co-60
< 0.002
< 0.001
< 0.001
< 0.001 Nb 95
< 0.002
< 0.002
< 0.002
< 0.001
{
Zr-95
< 0.003
<0.003
< 0.003
< 0.002 Ru 103
< 0.002
< 0.003
< 0.002
< 0.001-Ru-106
< 0.0?.
< 0.01
< 0.008
< 0.007 Cs-134
< 0.001
< 0.002
< 0.0008
< 0.001 Cs 137
< 0.002
<0.002
< 0.0009
< 0.001 Co-141
< 0.004
< 0.005
< 0.002
< 0.002 Ce 144
< 0.009
< 0.010
<0.003
< 0.005 E
c
- 2.
E E
I-7 E
7 Il O
M M
.R R
R R
f-l R
fl fl fl O
fl 1-1 f.
1 T ~1 r(
-n i
TAEF 1-3 1987 CPS apr SaMtTERLY YtD RE$ta.T5 (Dose in asem/Ouerter
- 1 s.d.)
Stotton Code 1st Ouerter 2nd Guerter 3rd Overter 4th her CL-1 17.4 t1.3 19.6e0.6 19.0e1.4 20.9ee.6
.. i a-2 18.211.1 20.0e0.4 21.211.4 21.5e1.0 n-3 17.7*0.7 22.2*0.8 19.111.1 23.0e0.8 CL-4 17.511.1 18.6e0.8 20.120.8 19.5e1.0 CL-5 18.4 A1.4 17.2*0.6 20.4*0.7 17.Geo.5 a-6 15.6*0.9 17.4e0.5 20.6et.1 18.1*0.8 CL-7 20.0
- 21.221.8 18.1*0.5 20.6e0.6 R-8 18.2*0.6 19.6e0.9 20.6e1.0 19.7tt.2 CL-11(c) 19.3
- 19.6a0.5 18.6*0.8 19.Geo.7 a-20 16.6t0.8 2C.5*0.5 18.6e0.9 19.9ee.6 CL-21 18.7t1.0 21.711.4 20.4e0.6 21.Ge1.3 a-22 16.9e0.8 19.5*0.8 18.3t1.6
'21.2*1.4 CL-23 18.411.3 17.0
- 17.0
- 15.5e0.5 a-24 15.4 e0.7 16.4ec.7 16.Sec.4 19.1 A1.0 3'
s s
g
'. 4
7 R
f~ 1 M
M R
R f~~l O
R R
R R
R f-W f7 fR f ~1 ff TABLE 1-3 (Cen11nued) 1987 CPS NDP OumtTrpLY TLD ItESULTS (Dese In adtem/Ouarter i I s.d.)
Station Code 1st Guarter 2nd Que.-ter 3rd Guarter 4th Ouerter CL-25 1d.6tt.2 16.240.5 14 A*0.5 16.5et.2 CL-26 14.0*0.4 18.7*0.9 16.9e0.5 18.2e0.9 21.21i.5 17.4al.0 20.211.3 CL-27 15.510.7 CL-28 17.7*0.7 22.410.6 20.0*0.9 21.Se0.7 a-29 16.6*0.9 23.2*0.8 18.4t0.5 23.2*1.8 CL-30 16.0t0.6 25.6*2.2 18.6*0.8 23.Geo.6
+-*
CL-31 14.410.4 19.S*0.9 16.6*0.7 20.6a1.0 e
CL-32 15.5.4.6 22.1t1.3 16.St0.4 22.6e0.7 CL-33(c) 16.211.2 23.111.0 17.Sec.6
-24.0e0.7 CL-34 18.1*0.4
'26.3*0.8 20.7*0.G 27.6e0.9 a-35 15.6*0.9 18.6
- 17.Sec.4 22.3al.5 CL-36 15.3*0.5 20.7*0.8 17,5e t.5 21.7al.4 CL-37 16.110.6 21.711.0 19.4*1.1 23.Ga1.7 CL-38 15.3*0.6 21.7e0.4 19.211.8 21.9*0.8.
- M M
M M
M M
M 7
f l f l f
TABLE l-3 (Continued) 1987 CPS REMP QUARTERLY TLD RESULTS (Dose in aRem/f' *Prter i l S.d.)
Station Code 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter CL-39 14.211.0 20.010.6 16.6tt.1 19.610.7 LL-40 15.710.9 21.1*0.7 17.711.0 21.911.2 l
CL-41 17.411.7 17.4
- 17.4
- 17.4
- CL-42 14.611.1 20.6*1.2 19.211.7 21.0 1.4 CL-43 16.411.1 22.611.9 20.210.9 23.011.3 CL-44 15.210.9 21.611.0 17.4 it.6 20.711.0 e
CL-45 18.210.8 25.7i0.9 22.4
- 23.3i0.7 H
w l
O i
CL-46 15.8tt.2 21.6i0.9 17.211.0 20.411.0 CL-47 16.710.6 24.9*0.9 19.0i0.4 23.310.8 CL-4 8 18.511.0 23.7*1.2 22.1*1.6 23.611.3 CL-49 15.810.6 23.8tl.1 18.911.6 23.0*0.9 CL-50 14.9 1.0 23.710.9 16.611.0 23.010.7 O_-51 1G.0i0.8 23.410.8 18.810.7 22.811.1 CL-52 15.810.6 23.211.0 17.SiO.4 21.910.8 l
l l
l
\\
MMM M
M M
t f l f 1 1
1 I
TABLE l-3 (Continued) 1967 CDS REMP OUARTERLY TLD RESULTS (Dose in atten;/Ouarter i i s.d.)
Station Code 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter CL 53 14.5i0.8 22.2t0.8 16.111.0 20.410.8 CL-54 14.110.4 23.411.4 16.7i0.8 21.510.8 CL-55 15.611.0 21.611.1 17.5*1.0 21.121.6 CL-56 17.311.2 24.0i0.9 19.011.2 21.410.8 CL-57 16.911.1 23.011.0 19.510.8 22.011.6 CL-58 15.711.0 19.2
- 19.2
- 22.610.9 H
20.8
- 18.910.7 22.711.2 e
CL-59 20.8
- w CL-60 17.0tt.4 24.211.4 22.311.6 22.5*1.1 W
CL-61 16.011.4 22.911.1 17.711.2 23.211.2 CL-62 11.610.8 23.7 t0.8 20.3
- 25.7i1.9 CL-63 16.2i t.1 25.910.7 19.8tl.0 25.2i1.0 CL-64 15.810.9 23.8tl.4 17.7i0.8 22.011.1 CL-65 16.310.9 23.8 0.9 18.210.5 23.411.1 CL-66 15.510.9 21.111.2 15.6i1.2 20.310.9
\\
l
E M
M M
l f I J l I
TABLE l-3 (Continued) 1987 CPS REMP QUARTERLY TLD RESULTS (Dose in sRem/ Quarter i i s.d.)
Station Code 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter CL-67 16.G10. 8 22.6*1.5 20.711.4 21.210.7 CL-68 13.610.9 20.4to.8 16.2i0.7 20.210.7 CL-69 18.5 1.4 25.311.0 20.2i0.4 24.811.3 l
CL-70 15.3it.6 23.910.9 18.5*0.6 22.2*1.5 CL-71 18.311.2 23.610.9 19.O*0.5 23.6i0.9 CL-72 17.210.8 18.9
- 18.9
- 20.6il.1 l
Q -73 18.011.2 23.310.8 19.0i0.9 24.5*1.6 s
1 W
CL-74 17.810.8 19.6
- 19.6
- 21.Si0.8 N
CL-75 18.111.0 21.311.1 19.811.6 21.010.3 CL-76 17.311.1 23.610.7 19.310.9 20.1
- CL-77 16.110.6 17.5'
- 17.5
- 18.911.1 l
CL-78 16.210.8 21.610.6 18.110.6 21.2il.1
)
CL-79 15.511.0 22.6i1.3 17.910.8 20.6i1.0 CL-80 16.311.3 24.910.9 18.6t1.5 19.9
- TABLE l-3 (Continued) 1987CPSREMPOUARTERLYTLDRESNLTS (Dose in mrem / Quarter i 1 s.d.)
Station Code 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter CL-81 16.210.4 22.111.0 18.0i0.6 22.5i1.3 CL-82 16.8*0.7 17.2
- 17.2
- 17.611.2 CL-83 17.711.2 22.811.3 19.911.4 22.411.2 f
CL-84 17.211.2 23.910.8 18.610.6 21.6i1.0 CL-85 17.611.1 22.810.7 19.511.4 21.6i1.1 CL-86 19.0i0.4 23.9tt.2 21.411.3 23.6 1.9 H
24.511.3 21.311.6 22.8i1.0 CL-87 18.3i0.4 g
l CL-109 15.510.5 22.411.6 20.410.4 21.5i1.6 V
CL-110 17.d10.8 20.510.9 19.410.6 19.410.8 CL-111 17.810.9 11.310.6 13.t
- 11.2il.0 CL-112 15.310.6 18.010.8 16.510.5 17.810.6 i
20.3i1.0 20.8tO.9 CL-113 17.910.6 22.111.2 (c} - control Station all others indicators
- TLD results missing, replace by teking average of all other quarters at ts:s location for year (a) - f or station location description refer to Table A-1 l
l
O k
TABLE l-4 CROSS BETA ACTIVITY IN SURFACE WATER FOR 1987 (pCi/m i 1 s.d.)
3.
l Station Location Date CL-9 CL-10(c)
CL-13 CL-90(a)
CL-91(b)
CL-92 CL-93 03/25/87 1.5*0.6
< 1.0 1.3i0.6 4.8 1.0 1.1*0.6 1.4*0.5 (d) 04/ 29/87 1.4i0.6 1.3*0.6 1.3*0.7 1.8*0.6 1.4*0.6 1.4*0.6 (d) 05/27/87 1.8*0.6 2.0i0.9 2.3*1.0 3.6t0.7
< 1.6 2.3*1.0 (d) 06/24/87 2.6*0.7 1.9*0.7 3.0*0.8 4.0*0.8 2.9t0.7 2.4t0.7 (d) 07/29/87
< 1.1
< 1.1 2.4*0.7 2.1 *0.7 1.810.7 1.7*0.7 (d) 08/26/87 2.3 *0.7 1.6*0.6 2.8*0.7 1.8*0.5 1.8*0.7 2.3*0.7 (d) 09/30/87 2.5i0.6 2.6*0.6 2.5to.7 5.0*0.9 2.1*0.6 2.1*0.6 (d)
I 10/28/87 3.0*0.7 2.5*0.7 2.0*0.7 2.5*0.7 2.310.7 2.0* 0.5 (d)
E25/97 2.4*0.8 2.6*0.8 1.7*0.8 1.5*0.8 2.7*0.7 2.3 i0. 8 3.2*0.9 12/30/87 3.0f0.8 3.4*0.8 2.2i0.7 2.2*0.7 2.3 *0. 8 1.210.7 2.6*0.7 a - Downstream Sample Location of Discharge Point b - Upstream Sample Locat' ion c - Control Location, all other locations indicators d..
.a,1. Lo..t.on sta,t.d. _,.,.,,8, e,
$4 w=
I-14
~
m L
b TABLE l-5 CROSS ALPHA ACTIVITY IN SURFACE WATER FOR 1987 (pCi/1il s.d.)
Date CL-90(a)
CL-91(b) 03/25/87
< 2.0
< 1. 2 04/29/87 1.0*0.7
< 0.9 05/27/87 1.3*0.8
< 1.7 1
06/24/87
< 1.3 2.6*1.1 07/29/87
< 0.8
< 0.8 08/26/87
< 0.8
< 0.9 09/30/87 1.2*0.8
< 0.8 10/28/87 1.0*0.6
< 0. 8 11/25/87
< 0.9
< 0.9 12/30/87
< 1.1
< 1.4 a - Downstream Sample Location b - Upstream Sample Location I
1 I
I i
1 4
e I-15
MMU l... I TABT l-6 CAMMA ISOTOPIC ACTIVITY IN SURFACE WATER FOR 1987 (pCi/1)
Site isotope 3/25/87 4/29/87 5/27/87 6/24/87 7/29/87 8/26/87 9/30/87 10/28/87 11/25/87 12/30/87 CL-9 Be-7
< 12.0
< 12.5
< 23.0
< 26.2
< 11.3
< 22.9
< 19.3
< 16.4
< 13.2
< 15.1 K-40
< 17.0
< 23.2
< 33.4
< 41.1
< 30.5
< 34.5
< 37.5
< 3 0. 2
< 23.8
< 3 8.5 Mn-54
< 5.0 1.5
< 2.3
< 2.6
< 1.3 2.3 2.2
< 1.7
< 1.4
< 1.8 Fe-59
< 12.0
< 3.5
< 5.7
< 6.9
< 2.5 5.4
< 5.1
< 3.5
< 3.8
< 3.6 Co-58
< 5.0
< 1.5
< 2,4
< 2.6
< 1.3
< 2.6
< 2.0
< 1.8
< 1.5
< 1.8 Co-60
< 5.0 1.5
< 2.4
< 2.6
< 1.3
< 2.7 2.3
< 1.8
< 1.5
< 1.7 Zn-65
< 6.0
< 2.8
< 4.8
< 5.2
< 3.1
< 5.3 4.8
< 3.8
< 2.8
< 4.2 Nb-95
< 10.0
< 1.6
< 2.5
< 2.7
< 1.4
< 2.5
< 2.2
< 2.0
< 1.4
< 1.9 l
Zr-95
< 10.0
< 2.6
< 4.3
< 5.0
< 2.3
< 4.3
< 4.0
< 3.4
< *i
< 3.2 l
Cs-134
< 5.0
< 1.3
< 2.2
< 2.3
< 1.4
< 2.2
< 2.1
< 1.8
< 1.2
< 1.9 l
< 5.0
< 1.7
< 2.7
< 3.0
< 1.4
< 2.6
< 2.5
< 2.0
< 1.3
< 1.9 l
Ba-140
< 60.0
< 5.8
< 13.6
< 19.1
< 6.2
< 11.2
< 8.4
< 6.9
< 9.2
< 9.3 La-140
< 15.0
< 1.6
< 3.5
< 5.0
< 1.7
< 3.0
< 1.9
< 2.0
< 2.9
< 2.8 Ce-144
< 11.0
< 12.4
< 22.6
< 25.9
< 12.0
< 23.3
< 22.4
< 18.3
< 11. 2
< 13.7 g
I l
e-.
<n C -10(c)
Be-7
< 18.0
< 16.3
< 15.3
< 18.5
< 12.3
< 16.2
< 14.9
< 15. 8
<15.8
< 15.5 K-40
< 12.0
< 37.3
< 37.8
< 40.1
< 20.7
< 39.1
< 18.9
<38.6
<41.2
< 39.6 l
< 5.0
< 1.9
< 2.0
< 2.2
< 1.3
< 1.9
< 1.8
< 1.8
< 1.9
< 1.8 Fe-59
< 12.0
< 5.0
< 4.5
< 5.6
< 3.7
< 4.0
< 3.8
< 3.6
< 3.8
< 4.1 J
Co-58
< 5.0
< 2.1
< 2.1
< 2.4
< 1.4
< 1.8
< 1.9
< 1.8
< 1.8
< 1.9
.l l
< 5.0
< 2.3
< 2.4
< 2.6
< 1.4
< 2.0
< 2.1
< 1.8
< 1.9
< 1.8 l
Zn-65
< 6.0
< 4.7
< 4.8
< 5.6
< 2.6
< 4.1
< 4.0
< 3.9
< 3.6
< 4.0 lb-95
< 10.0
< 2.3
< 2.2
< 2.6
< 1.4
< 2.0
< 1.8
< 1.8
< 1.8
< 2.0 Zr-95
< 10.0
< 3.5
< 3.5
< 4.1
< 2.2
< 3.7
< 3.2
< 3.2
< 3.2
< 3.5 Cs-134
< 5.0
< 1.8
< 1.9
< 2.2
< 1.2
< 2.1
< 1.9
< 2.0
< 1.9
< 2.1 Cs-137
< 5.0
< 2.0
< 2.1
< 2.2
< 1.5
< 2.0
< 1.9
< 1.9
< 1. 3
< 1.9 Ba-140
< 60.0
< 7.0
< 8.8
<14.0
< 6.5
< 8.7
< 6.6
< 6.4
<10.5
<10.4 Lo-140
< 15.0
< 2.6
< 3.8
< 6.4
< 1.9
< 2.7
< 2.5
< 1.8
< 3.2
< 3.3 Cc-144
< 19.0
< 13.0
< 13.2
<14.6
< 15.3
< 13.4
< 12.6
< 13.5
<13.7
<14.2 l
6.
t 6
'S C
g
M M M
M M
M l FU l i
TABLE l-6 fcontinued)
Site isotope 3/25/87 4/29/87 5/27/37 6/24/87 7/29/87 8/26/87 9/30/87 10/28/87 11/25/87 12/30/87 CL-13 Be-7
< 11.0
< 23.0
< 12.9
< 22.7
< 10.3
< 17.3
< 25.1
< 16.0
< 13.5
< 16.0 K-40
< 12.0
< 38.6
< 32.2
< 42.0
< 18.3
< 19.1
< 42.8
< 37.4
< 35.0
< 33.8 Hn-54
< 5.0
< 2.4 1.5
< 2.4
- 1. 2 2.1 2.7 1.9 1.8 2.0 Fe-59
< 12.0
< 6. 2 2.9
< 5.5
< 3.2 4.2 7.4 3.9
< 4.3 4.0 Co-58
< 5.0
< 2.5 1.5
< 2.7
< 1.2 2.1 3.0 2.0
< 1.7 1.8 Co-60
< 5.0
< 2.3 1.4
< 2.6
< 1.3 2.2 3.1 2.2
< 2.0 2.0 l
2 n-65
< 6.0
< 4.9 3.3
< 5.1
< 2.3 4.6 7.2 4.6
< 4.0 4.4 Nb-95
< 10.0
< 2.6 1.5
< 3.0
< 1.2 2.1 3.5 2.t
< 2.0 2.0 l
Zr-95
< 10.0
< 4.3 2.6
< 4.8
< 2.0 3.9 5.9 3.6
< 3.3
< 3.4 l
Cs-134
< 5.0
< 2.2 1.6
< 2.4
< 1.1 2.2 2.4 2.0
< 1.7
< 1.8 Cs-137
< 5.0
< 2.6 1.5
< 2.5
< 1.4 2.3 2.6 1.9
< 1.8
< 1.9 Ba-140
< 00.0
< 8.6 7.5
< 6.8
< 4.9 8.7 9.1 6.1
< 7.6
< 9.1 La-140
< 15.0
< 1.8 2.0
< 2.6
< 1.5 2.5 3.3 2.6
< 2.8
< 3.5 Ce-144
< 10.0
< 22.0
< 13.0
< 22.4
< 13.1
< 19.2
< 16.7
< 12.9
< 10.5
< 11.3 g
I W
I w
CL-90(a)
Be-7
< 14.0
< 13.5
< 18.6
< 20.8
< 13.8
< 14.6
< 16.7
< 21.9
< 13.6
< 24.5 K-40
< 23.0
< 36.5
< 39.5
< 48.6
< 34.9
< 36.1
< 38.7
< 39.0
< 38.3
< 39.7 Hn-54
< 5.0
< 1.6 2.1
< 2.3
< 1.7 1.8 1.6 2.5
< 1.5
< 2.4 Fe-59
< 12.0
< 3.8 4.5
< 5.0
< 3.2 3.3 3.9 4.9
< 3.2
< 5.1 Co-58
< 5.0
< 1.9 2.2 2.4
< 1.6 1.7 1.8 2.3
< 1.6
< 2.2 Co-60
< 5.0
< 1.9 2.0
< 2.0
< 1.7 1.8 1.7 2.5
< 1.6
< 2.4 Zn-65
< 6.0
< 4.1 4.7
< 5.2
< 3.5 3.9 3.8 4.4
< 3.2
< 4.7 Nb-95
< 10.0
< 2.0 2.5
< 2.5
< 1.6 1.8 2.0 2.5
< 1.7
< 2.4 Zr-95
< 10.0
< 3.1 4.2 4.1
< 2.9 3.2 3.5 3.9
< 2.7
< 4.6 Cs-134
< 5.0
< 1.6 2.2
< 2.4
< 1.7 1.9 1.8 2.2
< 1.6
< 2.3 Cs-137
< 5.0
< 1.7 2.2
< 2.4
< 1.6 1.8 1.8 2.6
< 1.6
< 2.6 Ba-140
< 60.0
< 5.7
< 12.7
< 16.4
< 6.6 6.9
< 10.6
< 12.2
< 9.6
< 9.2 La-140
< 15.0
< 2.3 3.6
< 4.5
< 2.0 2.0 3.0 2.9
< 2.7
< 1.9 Ce-144
< 13.0
< 11.1
< 19.3
< 18.6
< 11.4
< 12.1
< 13.7
< 22.6
< 12.0
< 22.7 S
i 0
l
9 R
R M
'R R
R N
D M
R R
FD ~~ I.
f TAB J t-6 (continued)
Site isotope 3/25/87 4/29/87 5/27/87 6/24/87 7/29/87 8/26/87 9/30/87 10/28/87 11/25/87 12/30/87 l
CL-91 (b)
Be-7
< 10.0
< 17.4
< 15.1
< 19.3
< 11.2
< 12.2
< 19.5
< 23.1
< 11.5
< 16.9 l
l K-40
< 21.0
< 37.1
< 27.3
< 40.4
< 32.7
< 32.1
< 40.8
< 40.6
< 30.1
< 38.3 l
Mn-54 5.0
< 1.9
< 1.9 2.4
< 1.4 1.3 2.0 2.3 1.2 1.9 l
Fe-59
< 12.0
< 4.2
< 5.0 5.4
< 2.0 2.7 4.8 5.7 2.6 3.8 l
Co-58 5.0
< 2.0
< 1.6 2.7
< 1.4 1.4 2.2 2.6 1.4 1.8 l
Co-60 5.0
< 1.9
< 1.9 2.4
< 1.4 1.3 2.0 2.1 1.2 1.9 l
Zn-65 6.0
< 3.9
< 3.3 '
5.1
< 2.8 3.4 4.4 4.6 2.8 4.0 l
Nb-95
< 10.0
< 2.2
< 2.1 2.6
< 1.4 1.4 2.5 2.3 1.4 2.1 Zr-95
< 10.0
< 3.6
< 3.2 4.1
< 2.5 2.4 4.0 4.3 2.3
< 3.6 Cs-134 5.0
< 1.9
< 1.5 2.0
< 1.4 1.6 2.2 2.2 1.4 1.9 Cs-137 5.0
< 2.0
< 2.0 2.3
< 1.4 1.6 1.9 2.6 1.3 2.1 Ba-140
< 60.0
< 6.7
< 9.4
< 16.I
< 5.9 7.1
< 16.8
< 12.6 7.6 9.8 La-140
< 15.0
< 1.9
< 2.8
< 6.2
< 1.9 1.9 4.7 3.7 2.2 2.9 Ce-144
< 11.0
< 17.4
< 15.4
< 14.6
< 9.7
< 12.7
< 14.7
< 22.4
< 10.7
< 19.0 g
l W
co CL-92 Be-7
< 17.0
< 11.0
< 22.6
< 19.8
< 14.2
< 13.0
< 14.7
< 18.3
< 14.4
< 26.2 K-40
< 18.0
< 28.4
< 37.2
< 38.8
< 34.5
< 32.9
< 31.;
< 39.3
< 38.7
< 37.6 Mn-54 5.0
< 1.1
< 2.3 1.9
< 1.7 1.4 1.5 2.0 1.6 2.4 Fe-59
< 12.0
< 2.5
< 6.2
< 4.6
< 4.0 2.8 3.3 4.3 3.5 6.3 Co-58 S.0
< 1.3
< 2.3
< 2.3
< 1.9 1.6 1.7 2.1 1.6 2.5 Co-60 5.0
< 1.0 2.4
< 2.3
< 2.1 1.5 1.4 2.0 1.7 2.4 In-65 6.0
< 2.6
< 4.9
< 4.2
< 4.6 3.4 3.4 4.2 3.7 5.2 s
Nb-95
< 10.0
< 1.4
< 2.2
< 2.7
< 1.9 1.5 1.8 2.3 1.8 2.7 Zr-95
< 10.0
< 2.1
< 4.2
< 4.2
< 3.1 2.6 2.9 4.0 3.0 4.8 Cs-134
< 5.0
< 1.2
< 2.1
< 2.2
< 1.7 1.6 1.6 2.1 1.6 2.4 Cs-137
< 5.0
< 1.2
< 2.7
< ?.0
< 1.9 1.6 1.5 2.1 1.7 2.7 Ba-140
< 60.0
< 4.5
< 12.8
< '6.1
< 7.8 7.2
< 11.7 7.6
< 10.0 9.3 La-140
< 15.0
< 1.2
< 3.0 5.G
< 2.9 1.7 2.9 2.3 3.4 1.9 Ce-144
< 19.0
< 10.4
< 21.8
< ?4.5
< 11.9
< 13.4
< 13.4
< 19.1
< 12.3
< 24.4
- j. !
'g
~
nn - m-am m
e unas '-' 1 o
o FR
_ F 1__d 1
I TABLE l-6 (continued) l i
Site isotope 11/25/87 12/30/87 CL-93( d)
Be-7
< 17.4
< 17.0 K-40
< 38.7
<41.6 Hn-54
< 1.8
< 1.9 l
I Fe-59
< 3.9
< 4.0 Co-58
< 1.9
< 1.8 Co-60
< 1.9
< 2.1 Zn-65 4.0
< 4.1 Nb-95
< 2.2
< 2.0 Zr-95
< 3.6
< 3.5 Cs-134 1.9
< 2.1 Cs-137 4: 2.0
< 2.0 Ba-140
< 6.8
< 7.3 La-140 2.1
< 2.3 Ce-144
< 18.6
< 14.8 g
i (a) - downstream sample location (b) - upstream sartple location (c) - control location, all other location Indicators (d) - new sarrple location added in November,1987 l
l l
l 5
I g,
a f
a 4
~
TABLE I-7 10 DINE-131 and TRITIUM ACTIVITY IN SURFACE k'ATER 1987 (pCi/l 2 1 s.d.)
Tritium Site Mar Apr May Jun
- Jul, Aug Sep Oct Nov Dec oCL-9
< 174
< 174
< 190 i
f
< 166 oCL-10(c) < 174 i
< 174 f
i
< 190
< 120 oCL-13
< 174
< 174
< 190
< 112 I
oCL-90(a) < 174
< 174 f
f
< 190
< 130 CL-91(b)
< 174
< 174
<148
< 152
< 16 6
< 166
< 189
< 164
< 171
< 183 CL-92
< 174
< 174
<148
< 15 2
< 166
< 166
< 189
< 164
< 171
< 12 2 CL-93(d)
(d)
(d)
(d)
(d)
(d)
(d)
(d)
(d)
< 170 152 84 Iodine-131 CL-90(a)
< 0. 5
< 0.5
< 0. 5
<0.5
< 0.2
< 0. 3
<0.2
< 0.4
< 0. 4
<0.2
- - sample analyzed only once per quarter 0- samples are quarterly compesites of monthly samples (e.) - downstream sample location, only surf ace water location for I-131 (b) - upstream sample locattrn (c) - control location, all other locations indicators (d) - new sample location added November,1987 I
I I
I 6
I I
1.x
E M M
M M
R
_ f~~
l
- f 1 f
E BLE t-8 Cama Isotopic, Cross Beta, Cross Alpha and Teltlum Activity in Drinking Water for 1987 CL-14 (pC1/1 i 1 s.d.)
Isotope 3/25/87 4/29/87 5/27/87 6/24/87 7/29/87 8/26/87 9/30/87 10/28/87 11/25/87 12/30/87 Cross alpha
< 0.7 1.810.3
< 0.5
< 0.4
< 0.5
< 0.5
< 0.4
< 0.2
< 0.5
< 0.6 Cross beta 1.310.3 1.810.3 1.710.3 1.8*0.3 1.4to.3
< 0.4 1.920.3 0.6i0.2 1.9i0.3 1.610.3 Be-7
<13.0
< 15.9
< 14.6
< 18.7
< 22.1
< 20.3
< 19.5
<14.4
< 20.5
< 17.3 K-40
<16.0
< 36.7
< 23.6
< 38.1
< 3 6.3
< 34.4
< 3 8.9
< 26.0
<42.0
<39.4 Mn-54
< 5.0
< 1.7
< 1.6
< 2.0
< 2.3
< 2.1
< 2.0
< 1.7
< 2.3
< 2.0 fe-59
<12.0
< 4.1
< 4.4
< 4.5
< 6.2
< 5.3
< 5. 0
< 4.2
< 4.7
< 4.1 Co-58
< 5.0
< 1.9
< 1.7
< 2.2
< 2.6
< 2.3
< 2.4
< 1.7
< 2.2
< 1.8 Co-60
< 5.0
< 1.8
< 1.6
< 2.0
< 2.3
< 2.5
< 2.4
< 1.8
< 2.2
< 2.0 Z n-65
< 6.0
< 3.8
< 3.3
< 4.5
< 5.0
< 4.9
< 4.9
< 3.3
< 4.6
< 4.3 Nb-95
< 10.0
< 2.2
< 1.7
< 2.3 2.6
< 2.2
< 2.8
< 1.6
< 2.8 '
< 2.3 Zr-95
<10.0
< 3.3
< 2.7
< 3.9
< 4.3
< 3.8
< 4.3
< 2.5
< 4.3
< 3.8 Cs-134
< 5.0
< 1.9
< 1.4
< 2.1 2.0
< 2.0
< 2.0
< 1.3
< 2.3
< 2.0 l
< 5.0
< 1.8
< 1.8
< 1.9 2.3
< 2.6
< 2.1
< 1.8
< 2.2
< 2.2 g
8 Ba-140
< 60.0
< 6.4
< 9.2 s 14.1
< 15.8
< 9.2
< 15.5
< 8.3
< 8.0
<10.9 s-La-140
<15.0
< 2.0
< 2.6
< 4.2
< 3.7
< 2.1
< 6.0
< 2.7
< 2.5
< 3.2 Ce-144
<12.0
< 12.4
< 14.0
< 14.0
< 2 2.1
< 21.6
< 14.2
< 1.3
<21.9
<19.7 1st Qtr 2nd Otr 3rd Otr tih Qtr T rit ius
< 174
< 174
< 190
< 190 l.
S
'4 T
i
m r
t__r r,
rm r
o ro ro i
TABLE l-9 TRITIUM AND ICOlr4E - 131 ACTIVITY IN WELL WATER FOR 1987 lodine-131 (pC1/1)
Site 3/11/87 3/25/87 3/31/87 4/15/87 4/29/67 5/13/87 5/27/87 6/10/87 6/24/87 7/8/87 7/22/87 7/29/87 CL-7(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
CL-12(t)
< 0.5
< 0.5
< 0.2
< 0.2
< 0.3
< 0.2
< 0.2
< 0.2
< 0.2
< 0.3
< 0.2
< 0.1 CL-12 (u)
< 0.5
< 0.5
< 0.3
< 0.3
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2
< 0.1 8/5/87 8/19/87 9/2/87 9/16/87 9/30/87 10/14/87 10/28/87 11/11/87 11/25/87 12/9/87 12/23/87 CL-7(a)
(a)
(a)
(a)
< 0.3
< 0.2
< 0.2
< 0.2
< 0.2
< 0.3
< 0.2
< 0.2 CL-12 (t)
< 0.2
< 0.2
< 0.5
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2 g
8 U
CL-12(u)
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2
< 0.2
< 0.4
< 0. 2
< 0.2
< 0.2 l
l TRITitN(b)
Site 1st Otr 2nd Otr 3rd Otr 4th Otr CL-7
< 174
< 17 4
< 190
< 177 CL-12(t)
<174
< 174
< 189
<177 CL-12(u)
<174
<174
< 189
< 177 (a) - Analysis added to program in September,1987 (b) quarterly composites of semi-monthly sanples (t) - Treated well water (u) - Untreated well Ster f
g, s
'4 g
l mMm
~
TABLE I-10 CROSS ALPHA. CROSS BETA. AND CAMMA ISOTOPf C ACTIVITY IN WELL W ATER AT CL-7 FOR 1987 (a) (pCf /1
- 1 s.d.)
Isotope 3/25/87 3/31/87 4/29/87 5/27/87 6/24/87 6/30/87 7/29/87
< 1.7
< 2.2
< 1.0
< 1.4
< 1.5 Cross alpha (b)
Cross beta 1.3 3.0*0.9 1.0t0.8 3.1io.8 3.0t0.9 1.6*0.9
'2.2*1.0 Be-7
< 21.0
< 15.3
<20.1
< 14.7
< 18.0
<18.8
< 14.2 K-40
< 13.0
< 22.8
<31.5
< 33.8
< 25.4
<3 6.1
< 35.8 Mn-54 5.0
<,1. 6
< 2.2
< 1.6
< 4.9
< 2.1
< 1.6 Fe-59
< 12.0
< 4.2
< 5.1
< 3.2
< 1.5
< 4.6
< 3.4 Co-58
< 5.0
< 1.6
< 1.9
< 1.6
< 1.5
< 2.1
< 1.7 Co-60 5.0
< 1.9
< 2.0
< 1.5
< 1.7
< 1.5
< 1. 7 Z n-65 6.0
< 3.5
< 4.4
< 3.7
< 3.3
< 5.2
< 3.8 Nb-95
< 10.0
< 1.6
< 1.9
< 1.7
< 1.7
< 2.2
< 1.7 Zr-95
< 10.0
< 3.2
< 3.8
< 2.8
< 2.9
< 3.8
< 3.0 Cs-134 5.0
< 1.3
< 1.9
< 1.6
< 1.6
< 2.5
< 2.0 Cs-137 5.0
< 1.7
< 2.5
< 1.6
< 2.2
< 2.2
< 1.7
[
Ba-140
< 60.0
< 5.9
< 7.4
< 9.3
< 10.6
<12.2
< 7.6 La-140
< 15.0
< 1.6
< 1.9
< 2.3
< 3.8
< 3.6
< 2.1 Ce-144
< 22.0
< 12.7
<19.6
< 14.1
< 5.0
<17.6
< 11.8
~
8/26/87 9/2/87 9/16/87 9/30/87 October November December Cross alpha (b) 1.5
< 1.3
< 1.4
< 1.2
< 1.5
<1.8
< 1.1 Cross beta 1.7t0.9 2.5i0.3 2.6to.8 3.2i0.6 2.911.0
- 2. 8tl.1 2.6i0.8 Be-7
< 13.5
< 16.4
<12.8
< 13.2
< 19.8
<17.9
< 15.4 K-40
< 45.6
< 37.6
<31.6
< 25.7
< 45.0
<28.1
< 34.0 Mn-54 1.5
< 1.8
< 1.4
< *5
< 2.1
< 1.7
< 2.1 Fe-59 4.0
< 3.8
< 2.9
< 3.9
< 4.9
< 4.3
< 4.4 rn-58 1.5 1.9
< 1.5
< 1.4
< 2.3
< 2.0 1.9 2.3 C o-60 1.5 1.6
< 1.3
< 1.6 1.9
< 2.1 s
In-65 3.3
< 3.6
< 3.2
< 2.8
< 5.0
< 4.0
< 4.5 Nb-95 1.8
< 2.1
< 1.5
< 1.5
< 2.5
< 2.1
< 2.6 Zr-95 2.5
< 3.5
< 2.5
< 2.9 h.0
< 3.6
< 3.6 Cs-134 1.3
< 1.8
< 1.6
< 1.2 2.2
< 1.7
< 2.0 Cs-137 1.6 1.8
< 1.5
< 1.8 2.1
< 2.1
< 1.9 Ba-140 6.1
< 11.9
< 7.9
< 7.6 7.4
< 6.1
< 6.4 La-140 1.8
< 3.5
< 2.2
< 2.1 2.0
< 1.8
< 2.6 Ce-144
< 15.2
< 16.4
<12.9
< 13.0
< 16.5
<14.5
< 11.9 (a) - samples changed f rcrn monthly to semi-monthly nith analysis perforced on meethly cceposites of serni-monthly'~
samples in September 1987 (b) - analysis for gross alpha changed from second month of quarter to all monthly cceposite samples 1-23
7 f7 F-~1 f~~' l n
U f~1 R
M f-~'l f-~ 1.. r7 n._
n n
o F7 I
I TABLE l-11 CROSS ALPHA. CROSS IRTA, AND CAMA ISOTOPIC ACTIVITY IN WELL WATER AT CL-12 for 1987
~
(pCf/1 i 1 s.d.)
Location isotope March April May June July August September October November December CL-12(t)
Cross alpha
< 3.0
< 2.9
< 2.9
< 3.1
< 2.0
< 2.9
< 2.9
< 1.4
< 2.8
< ' 3.2 Cross beta
< 2.6 2.3*1.4
< 2.9 2.4i1.7
< 2.2 3.2i1.7 3.0i1.6 2.7* 2.1 3.1
- 2.1 2.St1.9 Be-7
< 14.0
< 16.8
<13.8
< ?1.9
< 25.0
< 16.7
< 22.6
< 21.8
< 27.9
< 29.0.
'< 27.9
< 41.0
< 40.3
. < 3 8.4
< 39.2 K-40
< 15.0
< 36.8
< 3 2.6
< 41.4
< 51.6 Nn-54
< 5.0
< 2.1
< 1.4
< 2.4
< 2.3
< 2.3
'< 2.2
< 2.2
< 2.5
~< 2.5 Fe-59
< 12.0
< 4.8
< 3.3
< 5.E '
< 6.0
< 5.0
< 5.4
< 5.0
< 6. 0
< 6.1 Co-58
< 5.0
< 2.3
< 1.6
< 2.6
< 2.4 2.4"
< 2.5
< 2.5
< 2.6
< 2.6 Co-60
< 5.0
< 2.4
< 1.3
< 2.3
< 2.3
< 2.6
< 2.4
< 2.2
.< 2.6
< 2.4 In-65
< 6.0
< 4.9
< 3.4
< 4.8
< 5.1
< 5.4
< 4.8
< 4.6
< 4.9
< 5.6 ft>-95
< 10.0
< 2.4
< 1.8
< 2.9
< 2.6
< 2.4
'< 2.9
'< 2.2
< 4.9
< 2.8 Zr-95
< 10.0
< 3.4
< 2.8
< 4.7
< 4.9
< 3.8
< 4.6
< 4.6
< 5.0
< 5.2 Cs-134
< 5.0
< 1.9
< 1.5
< 2.3
< 2.1
< 2.0
< 2.4
< 2.2
< 2.3
< 2.5 Cs-137
< 5.0
< 2.0
< 1.5 2.4_
< 2.6
< 2.3
'< 2.3
< 2.4
'< 2.7
< 3.0 g
[
Ba-140
< 60.0
< 6.5
< 10.8
< 17.0
< 17.6
< 11.0
< 19.2
< 8.2
< 8.9
< 7.7 s
La-140
< 15.0
< 2.5
< 2.8
< 4.2
< 4.5
< 4.2
< 5.5
< 2.4
< 2.0
< 1.8 Ce-144
< 12.0
< 12.9
< 13.3
< 21.b
< 23.1
< 14.6
< 21.1
< 20.7
< 24.6
< 25.4 CL-12(u)
Cross alpha
< 3.2
< 2.9
< 1.9
< 3.0
< 2.1
< 2.9
< 1.4
< 2.6
< 2.7
< 3.0 Cross beta
< 2.9 2.011.4
< 2.4
< 3.3
< 2.2
'< 3.1
< 2.8
< 3.8
< 3.2
< 3.2 I
Be-7
< 16.0
< 13.4
< 22.2
< 17.5
< 15.2
< 18.2
< 15.9
< 17.9
<18.1
<20.0 K-40
< 24.0
< 32.8
< 40.4
< 35.9
< 28.0
< 39.1
< 19.2
< 37.4
-<41.3
< 41.1 Mn-54
< 5.0
< 1.4
< 2.3
< 1,7
< 1.6
< 2.0
< 1.8
< 2.0
< 1.8
< 2.2 i
Fe-59
< 12.0
< 3.1
< 5.3
< 4.2
< 4.3
< 4.1
< 4.1
< 4.8
< 4.4
< 4.6 Co-58
< 5.0
< 1.3
< 2:4
< 2.1
< 1.6
< 2.1
< 1.9
< 2.0
< 1.9 '
< 2.1 Co-60
< 5.0
< 1.7
< 2.2
< 1.8
< 1.7
< 1.9
< 1.9
< 2.0
< 2.0
< 2.2
)
Z n-65
< 6.0
< 3.3
< 4.9
< 4.2
< 3.3
< 4.4
< 4.3
< 4.7
< 4.2 '
< 4.8 l
Nb-95
< 10.0
< 1.7
< 2.3
< 2.1
< 1.5
'< 2.2
< 2.0
< 2.5
< 2.2-
< 2.6 l
Zr-95
< 10.0
< 2.6
< 4.1
< 3.5
< 3.5
< 3.8
< 3.6
< 4.0
< 3.5
< 4.2 I
. 5.0
< 1.5 2.";
< 2.0 1.4
< 2.4 1.7
< 2.0
< 1.9
< 2.3 l
Cs-134 l
< 5.0
< 1.5
< 2.6
< 1.8
< 1.6
< 2.0
< 1.8
< 2.0
< 2.0
< 2.3 i
Ba-140
< 60.0
< 5.2
< 1.2
< 13.2
< 11.9'
< 10.3
< 9.9
< 6.3
< 6.8
< 8.0 La-140
< 15.0
< 1.3.
< 3.3
< 3c8
< 3.6
< 3.2
< 3.6
< 2.5
< 2.3
< 2.2 Ce-144
< 14.0
< 12.8
< 22.3
< 12.7
< 16.7
< 13.9
< 11.9
< 13.5
< 4.7
< 21.9 (t) - Treated well water samples (u) - Untreated well ater saEples I~
'g g
b
~
F TABLE I-12 L
IODINE - 131 AND GAMMA ISOTOPIC ACTIVITY IN MILK FOR 1987 (a)
{
CL-116 (pci/l 1 1s.d.)
Isetope 3/25/87 4/29/87 5/6/87 5/20/87 6/3/87 b
< 0.5
< 0.5
< 0.4
< 0.3
< 0.3 K- 0 1 b50 1 b50 1 b 60 b60 12b60
[
< 5.0
< 2.1
< 2.4
< 2.4
< 2.4 Fa-59
< 12.0
< 4.8
< 6.5
< 6.0
< 6.1
[
Co-58
< 5.0
< 2.2
< 2.4
< 2.5
< 2.5 L
< 5.0
< 2.2
< 2.6
< 2.7
< 2.9 Zn-65
< 6.0
< 5.5
< 5.6
< 6.5
< 7.0 Nb-95
< 10. 0
< 2.3
< 2.5
< 2. 3
< 2.3
(-'
Zr < 10.0
< 3.9
< 4.4
< 3.8
< 4.1 Cs-134
< 5.0
< 2.1
< 2.3
< 1.9
< 2. 2 C2-137
< 5.0
< 2.1
< 2.9
< 2.1
< 2.3 B;-140
< 60. 0
< 7.7
< 9.1
< 7. 8
< 8. 5
[
La-140
< 15. 0
< 1.8
< 2.0
< 2.9
< 3. 0 Cs-144
< 14.0
<16.4
< 21. 9
<13.4
<14. 4
(
6/17/87 7/1/87 7/15/87 7/29/87 8/12/87 I-131
< 0.3
< 0.4
< 0. 3
<. 0. 2
< 0. 2 Bi-7
< 17. 0
<18.0
< 15.0
<15. 0
<13.0 K-40 1250160 1220170 1200250 1220160 1140:40 pi Mn-54
< 2.5
< 2.6
< 1.8
< 2. 3
< 1.6 L
Ts-59
< 5.9
< 6.5
< 5.4
< 5. 5
< 3. 8 Co-58
< 2.6
<. 2. 8
< 1.7
< 2. 3
< 1. 7 Co-60
< 3.2
< 3. 0
< 2.0
< 2. 6
< 1. 6
[
Zn-65
< 3.2
< 3.0
< 2.0
< 2.6
< 1. 6 Nb-95
< 7.0
< 7.1
< 4.6
< 6. 4
< 4. 4 Zr-95
< 2.6
< 2.7
< 1.8
< 2. 2
< 1. 7 Cs-134
< 2.2
< 2.1
< 1.6
< 2.0
< 1. 6
[
Co-137
< 2.4
< 2.3
< 2.2
< 2. 2
< 1. 7 t
B1-140
< 8.6
< 10. 6
< 8.1
< 8.1
< 8.0 La-140
< 3.2
< 3.7
< 1.9
< 2.9
< 1. 8
(
Ce-144
< 14. 2
< 14. 7
< 16. 7
<13.2
<13.9
(.
O%
[
M M e9 I-25 F
N F
L
[
TABLE I-12 (continued) r t
Motope 8/26/87 9/9/87 9/23/87 10/07/87 2.3 0.3 Sr-90(b)
< 0.2
< 0.5
< 0.2
< 0.4 Bi-7
<17.0
< 17. 0
<17.0
<21.0 i
K-40 1240!60 1240!60 1250!60 1200
.70 Mn-54
< 2.6
< 2.5
< 2.6
< 2.5 Fa-59
< 5.8
< 6.5
< 6.2
< 6.9 i
Co-58
< 2.6
< 2.6
< 2.6
< 2.7 Co-60
< 3.0
< 3.0
< 3.0
< 2.7 Zn-65
< 6.5
< 7.0
< 7.2
< 9. 7 Nb-95
< 2.3
< 2.6
< 2.5
< 2.8 i
Zr-95
< 4.0
< 4.2
< 4.1
< 4. 8 Ca-134
< 2.1
< 2.0
< 2.2
< 2.4 Cc-137
< 2.4
< 2.4
< 2.4
< 3.0 i
Bt-140
< 8.5
< 10. 3
<10.3
< 9. 4 L:-140
< 2.9
< 3.3
< 4.0
< 1.8 Cs-144
<14.3
< 14. 2
< 14. 4
<2 3. 0 1
10/21/87 11/04/87 11/26/87 12/29/87 Sr-90(b)
- 2. J.!0. 7 2.5 0.6 2.320.6 2.410.6 I-131 0.*
< 0.2
< 0.3
< 0. 4 Bm-7
<19.0
< 17.0
<28.0
<17.0 K-40 1210!70 1220!60 1270270 1250 70 Mn-54
< 2.5
< 2.2
< 2.9
< 2.2 Fs-59
< 6.5
< 5.3
< 8.0
< 5.4 -
Co-58
< 2. 7
< 2.2
< 3.2
< 2.2 Co-60
< 3. 2
< 2.2
< 3.7
< 2.2 Zn-65
< 7. 2
< 5.4
< 7.1
< 5.6 I
Nb-95
< 2.7 2.2
< 3.0
< 2.2 Zr-95
< 4.8
< 3.7
< 5.4
< 3.8 Cs-134
< 2.4
< 2.1
< 2.6
< 2.1 i
< 2.5
< 2.0
< 3.4
< 2.3 B:-140
< 7.7
< 7.2
< 9.6
< 10. 5.
La-140
< 2.6 1.9
< 1.8
< 2.8 Cc-144
< 15. 6
< 15.0
<18.1
<15.5
~
(a) - Milk collection semi-monthly during grazing season (May - October); conthly during I
non-grazing season (November - April)
(b) - Analysis for Sr-90 added to program in October, 1987 g
1-2e i
TABLE I-13 GAMMA ISOTOPIC ACTIVITY IN FISH FOR 1987 E
(pC1/g, wet i 1 s.d.)
L CL-19 04/15/87 04/15/87 04/15/87 04/15/87 Largemouth White
{
Isotope Carp Bluegill Bass Crappie Be-7
< 0.041
< 0.049
< 0.072
< 0.059 K-40 2.62t0.014 2.4810.13 2.82!0.22 2.4710.19
[
F6-54
< 0.005
< 0.006
< 0.012
< 0.008 Fe-59
< 0.013
< 0.015
< 0.027
< 0.023 Co-58
< 0.005
< 0.006
< 0.010
< 0.008
[
< 0.006
< 0.006
< 0.012
< 0.008 Zn-65
< 0.014
< 0.016
< 0.026
< 0.020 Nb-95
< 0.006
< 0.007
< 0.010
< 0.007
[
Zr-95
< 0.010
< 0.011
< 0.018
< 0.015 L
Ru-103
< 0.005
< 0.006
< 0.008
< 0.007 Ru-106
< 0.044
< 0.050
< 0.082
< 0.061 Cs-134
< 0.005
< 0.006
< 0.009
< 0.007 Cs-137
< 0.005
< 0.006
< 0.v10
< 0.008 Ba-140
< 0.017
< 0.020
< 0.031
< 0.025 Li-140
< 0.004
< 0.009
< 0.008
< 0.007 Ce-141
< 0006
< 0.008
< 0.009
< 0.009 Cc-144
<0.026
< 0.030
< 0.040
< 0.038 10/19/87 10/19/87 10/19/87 10/19/87 Largemouth Whita Isotope Carp Bcss Crappie Bluegill B9-7
<0.058
< 0.064
< 0.092
< 0.006 K-40 2.5720.14 1.68:0.12 2.88!0.19 2.24!0.16 Mn-54
< 0.005
< 0.005
< 0.007
< 0.006 Fe-59
< 0.022
< 0.022
< 0.030
< 0.020 0.008_
Co-58
< 0.006
< 0.008
< 0.010 Co-60
< 0. 00 6
< 0.007
< 0.007
< 0.007
[
Zn-65
< 0.014
< 0.016
< 0.020
< 0.014 Nb-95
< 0. 00 7
< 0.010
< 0.010
< 0.007 Zr-95
< 0.012
< 0.015
< 0.018
< 0.011
[
Ru-103
< 0.008
< 0.009
< 0.013
< 0.008 L
Ru-106
< 0.043
< 0.055
< 0.068
< 0.049 Cs-134
< 0.004
< 0.006
< 0.007
< 0.005-Cs-137
< 0.005
< 0.006
< 0.008
< 0.006
(
Ba-140
< 0. 017
< 0.021
< 0.028
- 0. 01'6~
Ba-140
< 0.005
< 0.005
< 0.005
< 0.004"'
Ce-141
< 0.012
< 0.017
< 0.023
< 0.012 Ce-144
< 0.030
< 0.043
< 0.056
< 0.037
{
E I-27
a Iu
{
TABLE I-13 (Continued) r CL-105(c)
L 04/14/87 04/14/87 04/14/87 04/14/87
(
White Largemouth Isotope Bluegill Crappie Bass Carp Be-7
< 0.036
< 0.071
< 0.057
< 0.074
[
K-40 1.38!0.13 3.2510.22 3.15 0.20 2.42:0.13 Mn-54
< 0.006
< 0.011
< 0.009
< 0.008 Fe-59
< 0.013
< 0.027
< 0.024
< 0.022
[
Co-58
< 0.005
< 0. 011
< 0.008
< 0.009 Co-60
< 0.006
< 0.011
< 0.010
< 0.010 Zn-65
< 0.013
< 0.026
< 0.023
< 0.019 Nb-95
< 0.006
< 0. 010
< 0.008
< 0.009
{
Zr-95
< 0.010
< 0.018
< 0.017
< 0.015 0.008
< 0.008 Ru-103
< 0.005
< 0.009 Ru-106
< 0.049
< 0.088
< 0.068
< 0.076
[.
Cs-134
< 0.005
< 0.009
< 0.008
< 0.007 0.009
< 0.009 Cc-137
< 0.006
< 0.010 0.027
< 0.030 Ba-140
< 0.020
< 0.035
{
0.007
< 0.008 La-140
< 0.006
< 0.009 0.010
< 0.015 Ce-141
< 0.006
< 0.010 0.041
< 0.059 Ce-144
< 0.026
< 0.042 10/20/87 10/20/87 10/20/87 10/20/37 Largemouth White Isotope Carp Bass Crappie Bluegill Be-7
< 0.063
< 0.070
< 0.080
< 0.014 K-40 2.3510,08 2.48!0.18 2.6920.21 2.2610.26
[
< 0.006
< 0.008
< 0.009
< 0.017 Fe-59
< 0.020
< 0.029
< 0.034
< 0.048 O
Co-58
< 0.007
< 0.010
< 0.010
< 0.018 Co-60
< 0.006
< 0.008
< 0.010
< 0.017
~
Zn-65
< 0.016
< 0.020
< 0.023
< 0.040_
Nb-95
< 0.010
< 0.009
< 0.009
< 0.018 Zr-95
< 0.015
< 0.017
< 0.018
< 0.031 Ru-103
< 0.009
< 0.011
< 0.012
< 0.017 Ru-106
< 0.054
< 0.005
< 0.072
< 0.013 Cs-134
< 0.006
< 0.006
< 0.007
< 0.013, Cs-137
< 0.006
< 0.009
< 0.009
< 0.015 Ba-140
< 0.021
< 0.024
< 0.027
< 0.032 -
La-140
< 0. 005
< 0.006
< 0.006
< 0.012 Ce-141
< 0. 018
< 0.015
< 0.015
< 0.0ff'
{
Ce-144
< 0.045
< 0.040
< 0.040
< 0.63 "~
(c) - Control Location I-28
7 R.
R R
R O
n
.. R U
.O R
D n
n R
n n
n F~
TABLE l-14 CROS*, ALPHA CROSS KTA. STRONTIUM-90 Am CAMIA ISOTOPlc ACTIVITY IN POTTOM SEClHENT FOR 1987 (pCl/q dry
- 1 s.d.)
Isstope CL-7c CL-10 CL-13 CL-19 CL-89 CL-105*
04/15/87 04/15/87 04/15/87 04/15/87 04/15/87 04/14/87 Crcss Alpha 7.9013.0 9.Oi3.2 4.1*2.4 6.4
- 2.8 5.2*1.9 13.5*4.0 Cross Beta 22.022.3 22.712.3 9.7*1.8 19.812.1 15.8*1.4 26.1*3.3 Sr-90
< 0.008 0.050*0.009
< 0.013
< 0.006
< 0.014 0.044*0.019 Be-7
< 0.13
< 0.27
< 0.12
< 0.22
< 0.13
< 0.24 K-40 14.7010.47 15.27t0.58 8.1710.38 16.1410.58 12.4510.31 19.08i0.57 Mn-54
< 0.017
< 0.034
< 0.018
< 0.029
< 0.016
< 0.032 Fe-59
< 0.041
< 0.080
< 0.044
< 0.070
< 0.039
< 0.066 Co-58
< 0.017
< 0.034
< 0.013
< 0.029
< 0.015
< 0.031 Co-60
< 0.023
< 0.039
< 0.024
< 0.039
< 0.021
< 0.038 g
In-65
< 0.052
< 0.003
< 0.051
< 0.078
< 0.040
< 0.075-Nb-95
< 0.021
< 0.038
< 0.020
< 0.031
< 0.018
< 0.032 Zr-95
< 0.032
< 0.062
< 0.030
< 0.052
< 0.031
< 0.055 Cs-134
< 0.024
< 0.C37
< 0.021
< 0.031
< 0.012
< 0.031 Cs-137 0.3210.02 0.5810.05
< 0.017 0.1210.03 0.077*0.014 -
0.59*0.05~
Ba-140
< 0.060
< 0.12
< 0.063
< 0.10
< 0.057
< 0.12 te-140
< 0.025
< 0.028
< 0.024
< 0.020
< 0.010
< 0.027 Ce-144
< 0.084
< 0.26
< 0.082
< 0.23
< 0.10
< 0.29 Ac-228 1.0710.06 1.2 2+0.14
< 0.061 0.88*0.13 0.55t0.06 1.45i0.13 81-212
< 0.20
< 0.54
< 0.22
< 0.44
< 0.28
< 0.50 B1-214 0.8010.04 0.73to.08
< 0.031 0.61to.06
< 0.056 0.82*0.07 Pb-212 1.09to.03 1.7110,07 0.3410.02 1.15*0.06 0.59*0.02 1.97*0.08 Pb-214 0.81 0.04 0.8310.07 0.25*0.02 0.7210.07 0.44*0.02 0.96*0.07 Ra-226
.i.0910.20 2.2910.46 0.6410.20 2.0610.46
. 20*0.24 2.6610.45 T1-208 1.01*0.05 1.3210.12 0.3120.04 0.1210.03 0.54*0.04 1.50*0.10 1
i' j.
r 6
}
.g g
M UT F 1 T
TABLE I-14 (Continued)
CL-7 CL-10 CL-13 CL-19 CL-89 CL-105*
Isotope 10/19/87 10/19/87 10/19/87 10/19/87 10/19/87 10/20/87 Cross Alpha 5.511.4 8.422.9 2.611.2 4.912.2 8.3i2.9 8.8i2.0 Cross Beta 10.8*1.0 25.3*2.5 9.6tl.3 20.2i2.4 27.913.4 27.911.8 l
Sr-SS 0.05 0.01 0.0610.0001 0.0510.01 0.0110.01 0.06*0.01 0.0410.01 l
l Be-7 0.31 t 0.17
<0.27
<0.10
<0.10
<0.62
< 0.27 l
K-40 14.9010.39 17.2620.43 8.3410.20 14.73i0.27 14.4910.61 15.8*0.27 r4n-54
< 0.017
< 0.027
< 0.012
<0.010
<0.030
< 0.09 l
Fe-59
< 0.046
< 0.074
< 0.033
<0.036
< 0.021
< 0.022 Co-58
< 0.018
< 0.030
< 0.012
< 0.012
< 0.054
< 0.009 l
l Co-60
< 0.020
< 0.031
< 0.015
< 0.012
< 0.032
< 0.0012 In-65
< 0.038
< 0.062
< 0.029
< 0.025
< 0.074
< 0.029 l y Nb-95
< 0.022
< 0.034
< 0.014
< 0.012
< 0.069
< 0.011 l t.s Zr-95
< 0.035
< 0.057
< 0.025
< 0.024
<0.12
< 0.016 l
Cs-134
< 0.014
< 0.015
< 0.009
< 0.007
< 0.022
< 0.014 Cs-137 0.3010.02 0.5820.04
< 0.011 0.0710.01 0.5010.04 0.4010.01 Ba-140
< 0.062
< 0.094
< 0.034
< 0.033
<0.10
< 0.033 Lo 140
< 0.011
< 0.023
< 0.007
< 0.006
< 0.019
< 0.014 Ce-144
< 0.10
< 0.13
< 0.058
< 0.053
<0.16
< 0.055 Ac-228 1.13to.09 1.4410.09 0.3810.03 0.6010.05 1.30*0.14 1.05i0.05 l
Bi-212
< 0.30
<0.40
<0.19
<0.17
<0.48
< 0.12
)
Bi-214 0.8010.05 0.P ic.05 0.2310.02 0.4010.02 0.73*0.07 0.6610.02 Pb-212 1.2010.03 1.8510.04 0.37 0.01 0.6710.02 1.4210.06 1.3110.02 Pb-214 0.94to.05 1.0h 0.05 0.2810.02 0.49to.02 0.84t0.08 0.7310.02 Ra-226 2.3410.37 2.4810.31 0.6110.11 0.9610.16 1.7210.56 1.8010.14 T1-208 1.11*0.07 1.6510,02 0.3710.02 0.56*0.01 1.1110.08 0.9810.04 1
- - Control location, all other locations indicators
W M'M M
M M
M M
M M
M 1 T- -
TABLE l-15 l
CROSS ALPHA, CROSS BETA, STPONTitH-90 Ato CAMMA ISOTOPIC ACTIVITY IN SHORELINE SEDIMENT FOR 1987 (pCf /g, dry
- i s.d.)
CL-7b CL-7d CL-10 CL-19 0.-88 CL-89 CL-105*
Isotope 04/15/87 04/15/87 04/15/07 04/15/87 04/15/87 04/13/87 04/15/87 Cross Alpha 2.712.2 4.612.6
< 3.3
< 3.1 2.612.2 3.212.3 3.4i2.1 I
Cross Beta 11.211.9 11.711.9 3.971.5 6.9il.7 10.8t1.9 13.211.9 9.011.7 Sr-90
< 0.005
< 0.004
< 0.005
< 0.007
< 0.009
< 0.006
< 0.017 Be-7
< 0.083
< 0.067
< 0.0%
< 0.076
<0.13
< 0.13
< 0.083 K-40 7.1610.26 5.9710.27 6.10*0.37 5.8510.29 7.9410.41 11.5010.55 10.1510.25 Mn-54
< 0.011
< 0.009
< 0.014
< 0.011
< 0.016
< 0.021
< 0.012 Fe-59
< 0.029
< 0.023
< 0.03%
< 0.028
< 0.034
< 0.057
< 0.026 Co-58
< 0.012
< 0.G10
< 0.014
< 0.012
< 0.015
< 0.022
< 0.011 Co-60
< 0.015
< 0.014
< 0.019
< 0.015
< 0.021
<0.032
< 0.017 7
Zn-65
< 0.034
< 0.029
< 0.041
< 0.033
< 0.037
< 0.066
< 0.031 j
Nb-95
< 0.013
< 0.011
< 0.015
< 0.012
< 0.015
< 0.023
< 0.011 Z r-95
< 0.021
< 0.018
< 0.024
< 0.019
< 0.030
< 0.035
< 0.020 Cs-134
< 0.015
< 0.011
< 0.015
< 0.012
< 0.011
< 0.023
< 0.010 Cs-137
< 0.011
< 0.008
< 0.013
< 0.010
< 0.016
< 0.021
< 0.012 Ba-140
< 0.042
< 0.033
< 0.047
< 0.039
< 0.058
<0.066
< 0.041 te-140
< 0.017
< 0.013
< 0.039
< 0.014
< 0.011
< 0.026
< 0.008 Cc-144
< 0.070
< 0.045
< 0.062
< 0.065
< 0.10
< 0.096
< 0.053 Ac-228 0.31i0.04
< 0.031
< 0.048
< 0.038
< 0.098 0.36to.06 0.26io.04 81-212
< 0.014
< 0.12
< 0.16
< 0.15
< 0.26
< 0.27
<0.16 Bi-214
< 0.020
< 0.016
< 0.022
< 0.019
< 0.051
< 0.032 0.17*0.02 Pb-212 0.27t0.02 0.1810.02 0.15ta.02 0.1310.02 0.25*0.04 0.4210.03 0.32i0.02 Pb-214 0.2510.02 0.1210.01 0.4510.08 0.1210.02 0.23*0.04 0.26to.03 0.1910.02 Ra-226 0.6910.13
< 0.15
< 0.20
< 0.19
< 0.32 0.84*0.19 0.44t0.14 T1-208 0.2710.02 0.1410.02 0.1110.03 0.1310.02 0.2310.06 0.3810.05 0.24i0.04 l.
6
'4 r
p
7 R
R R
T1 n
n n
m o
n n
n C
n n
n n
F -~
TABM I-15 (Continued)
CL-7b CL-7d CL-10 CL-19 CL-88 CL-89 CL-105*
Isotope 10/19/87 10/19/87 10/19/87 10/19/87 10/19/87 10/19/87 10/20/87 Cross Alpha
< 2.1
< 3.0
< 2.4 3.4*1.9
< 2.1 4.212.1
< 2.0 Cross Beta 11.212.0 8.412.2 13.0tt.9 10.712.0 ti.411.0 13.012.1 10.611.8 S r *>0 0.00(10.001 0.002s0.001 0.01520.007 0.016*0.010 0.00210.001 0.018t0.010
< 0.012 l
Be-7
< 0.13
< 0.08
<0.13
< 0.07
<0.10 0.3110.06
< 0.07 K-40 7.7510.24 8.05t0.27 10.5110.30 8.2510.24 7.0510.21 9.1910.27 7.2310.20 Hn-54
< 0.013
< 0.010
< 0.016
< 0.007
< 0.008
< 0.010
< 0.008 Fe-59
< 0.047
< 0.028
< C.043
< 0.029
< 0.09
< 0.040
< 0.029 Co-58
< 0.017
< 0.010
< 0.018
< 0.009
< 0.010
< 0.013
< 0.009 Co-60
< 0.017
< 0.013
< 0.020
< 0.010
<0.010
< 0.014
< 0.010 Zn-65
< 0.034
< 0.07G
< 0.040
< 0.023
< 0.021
<0.032
< 0.023 Nb-95
< 0.018
< 9.011
< C.018
< 0.014
<0.012
< 0.019
< 0.014 Zr-95
< 0.031
< 0.020
< 0.032
< 0.017
<0.020
<0.023
< 0.018 g
e Cs-134
< 0.011
< 0.008
< 0.014
< 0.009
<0.006
<0.012 0.008 I
U Cs-137
< 0.011
< 0.009
< 0.013
< 0.007
< 0.008 0.02510.006
< 0.006 Bo-140
< 0.039
< 0.034
< 0.064
< 0.024
< 0.029
< 0.030
< 0.025 I
Le-MO
< 0.009
< 0.007
< 0.013
< 0.009
< 0.005
< 0.012
< 0.010 l
Ce-144
< 0.060
< 0.048
< 0.OR5
< 0.040
< 0.0*5
< 0.042
< 0.047 Ac-228 0.21*0.04 0.2010.04 0.~810.05 0.22t0.02 0.19 J.03 0.3410.03
< 0.02 B1-212
<0.17
< 0.14
< C.20
< 0.09
<0.13
<0.12
< 0.08 Bi-214 0.16to.02 0.15*0.02 0.1810.02 0.1910.01 0.14i0.02 0.28i0.02
< 0.01 Pb-212 0.2710.02 0.1810.01 0.3810.03 0.25t0.01 0.2210.01 0.4510.02 0.1510.01 Pb-214 0.21t0.02 0.1610.32 0.2?s0.03 0.19i0.01 0.16*0.02 0.2810.01 0.1310.01 Ra-226 0.50*0.15 0.4010.15 0.5210.19 0.3910.08 0.3910.14 0.6210.09 0.2010.01 TI-TM 0.23i0.10 0.2010.03 0.2720.04 0.2310.02 0.1610.03 0.34*0.02 0.1310.31
- - Control location, all other locations indicators 5
I g
'4
,i+
hi TABLE I-16 GANMA ISOTOPIC ACTIVITY IN AQUATIC VEGETATION FOR 1987
{
(pCi/g, wet i 1 s.d.)-
CL-7C CL-10 CL-19 CL-105*
Isotope 04/14/87 04/14/87 04/14/87 04/14/87 Ba-7 0.80!0.21 0.4410.07
< 0.38 0.3810.03
[
K-40 0.79 0.45 0.5810.15 2.21 0.65 1.6710.10 Mn-54
< 0.029
< 0.014
< 0.047
< 0. 00 6 Fo-59
< 0.067
< 0.028
< 0.090
< 0.012 Co-58
< 0.028
< 0.014
< 0.046
< 0.005
{-
< 0.031
< 0.014
< 04042
< 0.006 l
Zn-65
< 0.058
< 0.033
< 0.11
< 0.016 Nb-95
< 0.030
< 0.016
< 0.050
< 0.005
(
Zr-95
< 0.054
< 0.026
< 0.079
< 0.009 l
Cs-134
< 0.025
< 0.015
< 0.048
< 0.006 Cs-137
< 0.032
< 0.013
< 0.047 0.034!0.004 Bn-140
< 0. 08 9
< 0.044
< 0.16
< 0.017 j
{
La-140
. < 0.026
< 0.013
< 0.040
< 0.007 Cs-144
< 0.13
< 0.061
< 0.27
< 0.028 h
CL-7C CL-10 CL-19 CL-105*
10/19/87 10/19/87 10/19/87 10/19/87 32-7
< 0.22
< 0.26 0.24
< 0.40 K-40 1.15:0.48 1.0610.50 1.3410.47 2.62i0.64 Mn-54
< 0.028
< 0.028 0.036
< 0.043
[
Fc-59
< 0.052
< 0.060 0.077
< 0.12 Co-58
< 0.025
< 0.028 0.C35
< 0.048 Co-60
< 0.035
< 0.028 0.031
< 0.042 Zn-65
< 0.061
< 9.055 0.070
< 0.11 Nb-95' s 0.028
< 0.023 0.033
< 0.060 Zr-95
< 0.046
< 0.050 0.056
< 0.094
- Cs-134
< 0.026
< 0.025 0.029
< 0.051 Cs-137
< 0.058
< 0.033 0.030
< 0.043 Bc-140
< 0.093
< 0.092 0.094
< 0.14 La-140
< 0.026
< 0.022 0.026
< 0.044
[
Co-144
< 0.13
< 0.18 0.11
< 0.22
- Control location, all other locations indicstors
{
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TABLE I-17 (continued)
CL-114 CL-114 CL-114 CL-114 CL-114 CL-114' Lettuce Cabbage Chard Chard Cateage Soyboen Leaves Isetope 06/24/87 06/24/87 06/24/87 07/29/87 07/29/87 07/29/87 Cress Eeta 7.1710.38 3.4510.22 2.7410.12 1.98*0.10 3.5710.15 3.1210.12 Be-7 0.3010.07
<0.058
<0.090 0.21*0.05 0.67*0.05 1.3210.16
'.-40 5.20t0.25 3.2610.25 3.6810.23 2.95*0.14 2.51*0.17 2.92*0.34 Mn-54
< 0.010
< 0.008
< 0.010 -
< 0.006
< 0.008 -
< 0.015 Fe-39
< 0.025
<0.020
< 0.024
< 0.015
< 0.020
< 0.037 co-58
< 0.006
< 0.006
< 0.009
< 0.006
< 0.007
< 0.013 g
$ Co-60
< 0.010
< 0.009
< 0.006
< 0.006
< 0.008
< 0.016 Zn-65
< 0.020
<0.022
<0.020
< 0.014
< 0.017
< 0.034 Nb-95
< 0.009
< 0.006
< 0.008
< 0.006
< 0.007
< 0.015 Zr-95
< 0.016
< 0.013
<v.015
< 0.010
< 0.014
< 0.027 I-1 31
< 0.010
< 0.015
< 0.013
< 0.010
< 0.011
< 0.020 Cs-134
< 0.007
< 0.006
' < 0.006
< 0.005
<0.006
< 0.014 Cs-137 0.02610.008
< 0.007
< 0.C99
< 0.006
<0.008
< 0.015 Ca-140
< 0.037
< 0.039
< 0.04C
< 0.028
<0.035
< 0.062 ta-140
< 0.088
< 0.011
< 0.008
< 0.001
'<0.007
< 0.021 Ce-144
< 0.058
< 0.054
< 0.070
< 0.047
< 0.061
< 0.074 gi 8
}
y g
m n
n n
M n
n n _... n n
n n
n n
a n
n n
n
.O TABtE I-17 (continued)
+
CL-114 CL-114 CL-114 CL-114 CL-114 CL-114 CL-114 Corn Leaves Chard Cabbage Soybean Leaves Corn Leaves Cabbage Swiss Chard Isotope 07/29/87 08/26/87 08/26/87 08/26/87 08/26/87 09/30/87 09/30/87 a
y Cress Beta 2.49t0.14 4.5110.16 3.1010.13 5.10*0.26 3.76*0.22 3.27*0.15 6.35*0.21 j
l
~l Be-7 1.55t0.08 0.38a0.04 0.70t0.05 4.3510.20 2.69t0.14 0.25t0.04 0.3860.05 j
K-40 2.15t 0.15 4.3510.19 2.4210.15 3.77tO.27 4.19t0.26 2.68*0.16 5.71*0.25 Mn-54
< 0.006
< 0.007
< 0.006
< 0.012
< 0.010
< 0.00J
< 0.010 l
Fe-59
< 0.016
< 0.017
< 0.014
< 0.028
< 0.026
< 0.014
< 0.023 Co-58
< 0.008
<0.007
< 0.006
< 0.011
< 0.010
< 0.006
< 0.010 Y Co-60
< 0.007
< 0.008
< 0.006
< 0.012
< 0.010
< 0.006
< 0.010 La
'l In-65
< 0.018 40.018
< 0.015
< 0.029
< 0.022
< 0.015
< 0.024 i
m-95
< 0.006
<0.006
< 0.006
< 0.011
< 0.010
' < 0.006
< 0.009 Zr-95
< 0.013
<0.013
< 0.0'1
< 0.022
< 0.018
< 0.011
< 0.017 8-131
< 0.012
<0.010
< 0.006
< 0.018
< 0.011
< 0.007
.< 0.011 Cs-134
< 0.008
<0.006
< 0.006
< 0.010
< 0.006
<0.006
< 0.009 l
l Cs-137
< 0.008
<0.007
< 0.006
< 0.013 0.016*0.010
<0.006
< 0.010 Ba-140
< 0.037
<U.030
< 0.026
< 0.054
< 0.041
< 0.024
< 0.037 l
l t.a-140
< 0.009
<0.008
< 0.006
< 0.012
< 0.010
< 0.027
< 0.009
^
Co-144
< 0.058
<0.055
< 0.036
< 0.076
< 0.084
< 0.037
< 0.072 1
?
8 j
p s
m n
n O
C O.
n n
n n
n n
r~'t n
.O n
n p
r;-
~
F TAELE l-17 (continued)
CL-115 CL-115 CL-115 CL-115 CL-115 CL-115 Corn Leaves Soybean Leaves Chord Cat 6ege.
Soybean Leeves Chord isstope 06/24/87 06/24/87 07/29/87 07/29/87 07/29/87 08/26/87 Cross Beta 1.58*0.07 2.72*0.13 3.25*0.13 2.85*0.13 6.05*0.17 3.4440.15 Be-7 0.41*0.06 0.32*0.09 0.24*0.04 0.26*0.05 1.37*0.07 0.38*0.08 K-40 1.81*0.16 2.85*0.24 2.18*0.13 1.44*0.14 1.41*0.12 2.73e0.18 Mn-54
< 0.011
< 0.010
< 0.007
< 0.006
< 0.006
<0.006' I
< 0.021 Fe-59
< 0.021
< 0.026
< 0.016
< 0.014
< 0.016 Co-58
< 0.010
< 0.010
< 0.006
< 0.006
< 0.006
< 0.000 g
a co Co-60
< 0.011
< 0.010
< 0.007
< 0.006
< 0.007
<0.006 w
< 0.023
< 0.021
< 0.015
< 0.013
< 0.017
< 0.019 Nb-95
< 0.011
< 0. 010
< 0.007
< 0.006
< 0.006
< 0.008 Zr-95
< 0.019
< 0.019
< 0.012
< 0.010
< 0.011
< 0.015 1-131
< 0.017
< 0.025
< 0.010
< 0.009
< 0.009
< 0.011 Cs-134
< 0.010
< 0.009
< 0.006
< 0.005
< 0.006
< 0.007 Cs-137
< 0.01'
< 0.011
< 0.007
< 0.006
< 0.006
<0.009 Ba-140
< 0.050
< 0.061
< 0.031
< 0.027 M 0.026
< 0.m La-140
< 0.012
< 0.013
< 0.000
< 0.007
< 0.010
< 0.007 Co-144
< 0.085
< 0.081
< 0.052
< 0.058
< 0.036
< 0.065 I
s I
- g.. I g-I t
'3 4,.
7 f-1 n
n m
n n..
O n
n n
n n
n n
m n
m O
r~- =
%^:3 hb' c
A TABLE l-17 (continued)
G.-115 CL-115 CL-115 CL-117 CL-117 i
Cabbage Soybean Leaves Cabbage Soybean Leaves Corn Leeves Isotope 08/26/87 08/26/87 09/30/87 08/26/87 08/26/87 s
Cross Beta 2.24io.12 2.9010.18 2.43*0.12 6.32*0.26 3.90*0.27 Be-7 0.5510.05 5.1210.17 0.18t0.03 3.66*0.22 4.05ee.13 1
K-40 1.77s0.13 2.06*0.20 1.85*0.11 4.58*0.32 2.53*0.19 Mn-54
< 0.007
< 0.010
< 0.005
< 0.014
<0.009 Fe-59
< 0.015
< 0.022
< 0.010
< 0.036
< 0.020 r
Co-58
< 0.007
< 0.011
< 0.005
< 0.014
< 0.010 H
s W Co-60
< 0.007
< 0.010
< 0.004
< 0.014
< 0.009 w
Zn-05
< 0.017
< 0.027
< 0.013
< 0.031
< 0.023 No-95
< 0.007
< 0.011
< 0.005
< 0.014
< 0.009 Ir-95
< 0.013
< 0.019
< 0.008
< 0.025
< 0.016 8-131
< 0.010
< 0.019
< 0.006
< 0.025
< 0.013 Cs-134
< 0.007
< 0.012
< 0.0u5
< 0.012
< 0.010 Cs-137
< 0.008
< 0.011
< 0.005 ~
< 0.015
< 0.010 Ba-140
< 0.031
< 0.056
< 0.021
< 0.069
< 0.041 La-140
< 0.006
< 0.013
< 0.005
< 0.014
^ < 0.010 Ce-144
< 0.061
< 0.088
< 0.038
< 0.011
< 0.075 (a) - collection performed monthly den available during growing season and at time of hervest, normal sample green leafy or tesborous vegetables.
I I
y g
'8; t
y
in-n n
n n
n n
n n
n n
n n
n n.
n F7
_O __
F----
i TAllt E I-18 CAMMA ISOTOPIC ACTIVITY IN CRASS FOR 1987 (pCE/g, wet) f a)
CL-1 Isotope 04/15/87 04/29/87 05/13/87 05/27/87 06/10/87 06/24/87 07/08/87 07/22/87 08-05-87 Be-7 2.5710.13 0.99*0.09 0.77*0.00 0.81 0.14 1.76i0.16 1.80A0.39 3.1710.27 1.4220.22 1.1510.08 K-40 4.80f0.28 5.39to.29 7.25*0.36 6.84*0.37 6.94to.48 5.5120.72 6.1220.51 8.59*0.47 7.30io.27 Mn-54
< 0.013
< 0.010
< 0.011
< 0.015
< 0.023
< 0.026
< 0.012
< 0.016
< 0.009 Fe-59
< 0.032
< 0.026
< 0.026
< 0.042
< 0.052
< 0.072
< 0.034
< 0.040
< 0.022 Co-58
< 0.014
< 0.011
< 0.011
< 0.014
< 0.022
< 0.025
< 0.013
< 0.016
< 0.010 Co-60
< 0.014
< 0.011
< 0.012
< 0.017
< 0.023
< 0.030
< 0.013
< 0.016
< 0.009 Zn-65
< 0.031
< 0.026
< 0.030
< 0.034
< 0.061
< 0.059
< 0.027
< 0.041
< 0.025 H
s Nb-95
< 0.015
< 0.011
< 0.012
< 0.015
< 0.023
< 0.028
< 0.012
< 0.016
< 0.010
.t.o Zr-95
< 0.025
< 0.019
< 0.019
< 0.026
< 0.035
< 0.060
< 0.024
< 0.030
< 0.016 4
1-131
< 0.023
< 0.020
< 0.012
< 0.025
< 0.027
< 0.038
< 0.019
. < 0.025
< 0.014 Cs-134
< 0.013
< 0.010
< 0.012
< 0.014
< 0.020
< 0.024
< 0.011
< 0.014
< 0.010 Cs-137
< 0.014
< 0.010
< 0.011
< 0.016
< 0.022
< 0.030
< 0.014
< 0.020
< 0.009 Ba-140
< 0.049
< 0.034
< 0.038
< 0.069
< 0.084
< 0.016
< 0.060
< 0.080
< 0.046 La-140
< 0.011
< 0.008
< 0.010
< 0.016
< 0.032
< 0.039
< 0.015
< 0.017
< 0.011 Cc-144
< 0.011
< 0.056
< 0.063
< 0.012
< 0.114
< 0.219
< 0.010
< 0.14
< 0.066 I
b i
8 I
e
m m
m m
' m _. m m
m m
m m
rm m_
m m
m m
m c,
1-TABLE l-18 (continued) 4 lectope 08/19/67 09/02/87 09/16/87 09/30/87 10/14/87 10/28/87 11/25/87 12/30/87 Be-7 1.34*0.13 1.83*0.12 1.22*0.10 1.49t0.14 2.31*0.26 3.89*0.17 3.0510.14 5.99*0.26 K-40 8.0310.36 8.6910.42 6.1910.34 6.3010.34 7.5920.63 5.5610.30 3.68*0.22 3.12*0.32 Mn-54
< 0.010
< 0.013
<0.014
< 0.014
< 0.015
<0.011
< 0.006
< 0.014 Fe-59
< 0.037
< 0.033
< 0.034
< 0.034
< 0.040
<0.030
< 0.022
< 0.034 Co-58
< 0.011
< 0.014
< 0.014
< 0.013
< 0.015
<0.011
< 0.006
< 0.015 Co-60
< 0.010
< 0.014
< 0.017
< 0.015
< 0.018
<0.011
< 0.006
< 0.016 Zn-65
< 0.031
< 0.036
< 0.039
< 0.032
< 0.043
<0.024
< 0.020
< 0.031 Nb-95
< 0.013
< 0.015
< 0.015
< 0.014
< 0.016
< 0.012
< 0.010
< 0.015 w
Zr-95
< 0.021
< 0.025
< 0.025
< 0.024
< 0.028
<0.019
< 0.016
< 0.027 1-131
< 0.017
< 0.025
< 0.018
< 0.016
< 0.022
<0.017
< 0.019
< 0.024 Cs-134
< 0.010
< 0.014
< 0.012
< 0.013
< 0.015
< 0.010
< 0.007
< 0.014 Cs-137
< 0.012
< 0.012
< 0.014
< 0.014
< 0.015
< 0.012
< 0.009
< 0.016 j
Be-140
< 0.053
< 0.070
< 0.058
< 0.052
< 0.046
<0.050
< 0.048
< 0.054 l
La-140
< 0.010
< 0.018
< 0.C
< 0.011
< 0.019
< 0.015
< 0.011
< 0.012 Ce-144
< 0.087
< 0.070
< 0.012
< 0.11
< 0.079
< 0.079
< 0.059
< 0.103 t
ri.-
t g
m m
m m
m m
m m
m m
m m
m r,
m m
m rm rp r,
ti TABLE l-18 (continued)
CL-2 lutope 04/15/87 04/29/87 05/13/87 05/27/87 06/10/87 06/24/87 07/08/87 07/22/87 08/05/87 Be-7 4.12*0.16 1.2010.06 0.53*0.06 0.89*0.18 1.34*0.19 2.42ko.34 1.84t0.11 3.77*0.34 1.51*0.23 K-40 3.8810.25 6.1510.21 5.01*0.24 10.6*0.71 6.74k0.44 8.53*0.67 5.1510.27' 17.9*0.75 7.11*0.44 Mn-54
< 0.011
<0.011
< 0.009
< 0.021
< 0.017
< 0.025
< 0.012
< 0.028
< 0.018 Fe-59
< 0.027
< 0.027
< 0.021
< 0.050
< 0.037
< 0.069
< 0.026
< 0.077
< 0.046 Co-58
< 0.012
< 0.012
< 0.009
< 0.021
< 0.016
< 0.022
< 0.012
< 0.030
< 0.018 Co-60
< 0.012
< 0.011
< 0.010
< 0.022
< 0.016
< 0.024
< 0.012
< 0.028
< 0.01d I
Zn-65
< 0.031
<0.027
< 0.025
< 0.052
< 0.040
< 0.054
< 0.031
< 0,.070
< 0.043 Y E-95
< 0.011
< 0.013
< 0.009
< 0.023
< 0.017
< 0.027
< 0.012
<, 0.028
< 0.019 4
PJ Zr-95
< 0.019
< 0.021
< 0.017
< 0.040
< 0.028
< 0.040
< 0.021
< 0.050
< 0.034 1-131
< 0.017
< 0.026
< 0.011
< 0.033
< 0.020
< 0.043
< 0.020
< 0.046
< 0.030 Cs-134
< 0.010
< 0.010
< 0.010
< 0.020
< 0.015
< 0.022
< 0.013
< 0.023
< 0.016 Cs-137
< 0.011
< 0.011
< 0.010
< 0.021
< 0.01 6
< 0.028
< 0.013
< 0.030
< 0.020 Ba-140
< 0.034
< 0.038
< 0.036
< 0.096
< 0.070
< 0.12
< 0.041
< 0.10
< 0.094 La-140
< 0.012
< 0.009
< 0.006
< 0.027
< 0.019
< 0.032
< 0.006
< 0.021
< 0.017 Cc-144
< 0.062
< 0.087
< 0.073
< 0.010
< 0.12
< 0.21
< 0.088
< 0.21
< 0.14
- I
- q
m m
m m
m m
m m
m m
m m
m rm m
m m
rm r-m c-TAfRE I-18 (continued) 08/19/87 09/02/87 09/16/87 09/30/87 10/14/87 10/28/87 11/25/87 12/30/87 Be-7 0.7e*0.10 0.82t0.09 1.3310.09 1.26i0.11 1.49*0.12 2.5610.14 2.98ko.26 7.58to.46 K-40 6.87*0.40 6.2210.33 5.8710.30 5.17t0.27 7.2210.40 6.9810.39 5.0410.34 4.3210.54 Mn-54
< 0.015
< 0.015
<0.010
< 0.009
< 0.014
<0.013
< 0.016
< 0.024 Fe-59
< 0.036
< 0.036
< 0.024
< 0.025
< 0.036
< 0.031
< 0.037
< 0.058 Co-58
< 0.015
< 0.016
< 0.010
< 0.009
< 0.014
< 0.013
<0.014
< 0.024 Co-60
< 0.016
< 0.016
< 0.011
< 0.011
< 0.015
< 0.014
<0.015
< 0.023 2n-65
< 0.038
< 0.035
< 0.027
< 0.021
< 0.036
< 0.034
< 0.034
< 0.055 H
Nb-95
< 0.016
< 0.017
< 0.011
< 0.009
< 0.015
< 0.014
< 0.014
< 0.023 w
Zr-95
< 0.028
< 0.028
<0.018
< 0.017
< 0.027
< 0.023
<0.027
< 0.045 l-131
< 0.022
< 0.029
< 0.014
< 0.010
< 0.019
< 0.021
< 0.031
< 0.041 Cs-134
< 0.015
< 0.014
< 0.012
< 0.008
< 0.014
< 0.013
< 0.013
< 0.024 Cs-137
< 0.016
< 0.016
< 0.010
< 0.010
< 0.014
< 0.014
< 0.016
< 0.027 Ba-140
< 0.069
< 0.081
< 0.046
< 0.034
< 0.047
< 0.045
< 0.059
< 0.095 La-140
< 0.020
< 0.022
< 0.011
< 0.009
< 0.012
< 0.012
< 0.013
< 0.017 Cc-144
< 0.077
< 0.12
< 0.058
< 0.058
< 0.084
< 0.081
< 0.094
< 0.21 l
l p
a 8 J_ ;
I i
1 rm r-r-
rm r-m r-m r-m rm r-n rm r-n m
r-r-
m rm r-m a
r1 TAKE l-18 (continued) 4 Ct -8 teotope 04/15/87 04/23/87 05/13/87 05/27/87 06/10/87 06/24/87 07/08/87 07/22/87 08-05-87 Be-7 0.87*0.10 0.45*0.13 0.28*0.07 0.05t0.008 0.81*0.15 0.30t0.10 1.65*0.10 0.9120.10 '
0.53*0.08.
K-40 6.10*0.26 6.88*0.33 7.03*0.31 6.92*0.26 6.2310.38 7.76*0.33 5.94*0.26 7.3220.39
'7.53*0.41 Mn-54
< 0.006
< 0.013
< 0.013
< 0.012
< 0.016
< 0.012
< 0.011
< 0.016
< 0.016 Fe-59
< 0.024
< 0.039
< 0.030
< 0.030
< 0.035
< 'O.031
< 0.026
< 0.036_
< 0.039 Co-58
< 0.006
< 0.014
< 0.013
< 0.012
< 0.016
< 0.012
< 0.012
< 0.015
< 0.016 Co-60
< 0.006
< 0.014
< 0.013
<0.012
< 0.017
< 0.012
< 0.011
< 0.019
< 0.017 Zn-65
< 0.021
< 0.032
< 0.030
< 0.033
< 0.039
< 0.032
< 0.026
< 0.042
< 0.042 H
e Nb-55
< 0.006
< 0.014
< 0.013
<0.012
< 0.016
< 0.012
< 0.012
< 0.016
< 0.015 s
A Zr-95
< 0.014
< 0.026
< 0.023
< 0.021
< 0.026
< 0.020
< 0.020
< 0.026
< 0.026 I-131
< 0.011
< 0.029
< 0.015
<0.017
< 0.022
< 0.012
< 0.018
< 0.020
< 0.021 Cs-134
< 0.007
< 0.012
< 0.012
< 0.012
< 0.014
< 0.011
< 0.010
. < 0.014
< 0.014 Cs-137
< 0.008
-< 0.014
< 0.013
< 0.012
< 0.017
< 0.016
< 0.012
< 0.014
< 0.015 Ba-140
< 0.030
< 0.049
< 0.045
< 0.054
< 0.064
< 0.043 4 0.053
< 0.064
< 0.064 La-140
< 0.007
< 0.010
< 0.011
< 0.014
< 0.017
< 0.009
< 0.014
< 0.022
< 0.023 Ce-144
< 0.050
< 0.011
< 0.097
< 0.066
< 0.121
< 0.096
< 0.065
< 0.073
< 0.075 I
gI s
- 's ;q i
r, r-r, v
w r-rm r-,
rm r-,
r-r-
rm m
m 1---,
1 TABLE I-18 (continued)
I
=1 Isatope 08/15/87 9/02/87 09/16/87 09/30/87 10/14/87 10/28/87 11/25/67 12/30/87 l
Be-7 0.6310.10 1.4710.23 1.0010.18 1.1710.10 3.1510.13 4.18t0.29 2.09*0.10 4.98*0.20
]
l K-4 0 7.8710.32 6.5810.43 4.84t0.33 5.4310.33 8.8510.32 5.9210.50 3.63*0.21 3.9310.27 l
< 0.022
< 0.020
< 0.015
< 0.012
< 0.012
< 0.010
< 0.009
< 0.014 Fe-59
< 0.052
< 0.050
< 0.036
< 0.029
< 0.026
< 0.025
< 0.024
< 0.030 Co-53
< 0.021
< 0.020
< 0.015
< 0.013
< 0.013
< 0.010
< 0.009
< 0.014 Co-60
< 0.026
< 0.018
< 0.016
< 0.014
< 0.011
< 0.010
< 0.010
< 0.015 Zn-65
< 0.059
< 0.045
< 0.033
< 0.031
< 0.031
< 0.027
< 0.024
< 0.034 g
e am m FAa-95
< 0.020
< 0.020
< 0.015
< 0.013
< 0.012
< 0.011
< 0.010
<0.015 Zr-95
< 0.034
< 0.034
< 0.026
< 0.022
<0.020
< 0.018
< 0.016
< 0.026 I
< 0.028
< 0.043
< 0.023
< 0.014
< 0.018
< 0.022
< 0.017
< 0.024 l
}
Cs-134
< 0.017
< 0.018
< 0.014
< 0.013
< 0.012
< 0.011
< 0.086
<0.014 Cs-137
< 0.020
< 0.022
< 0.015
< 0.013
< 0.013
< 0.010
< 0.087
< 0.015 Be-140
< 0.085
< 0.11
< 0.067
< 0.049
< 0.043
< 0.035
< 0.045
< 0.051 La-140
< 0.032
< 0.025
< 0.014
< 0.013
< 0.009
< 0.008
< 0.014
< 0.014 Co-144
< 0.093
< 0.16
<0.12
< 0.078
< 0.086
< 0.074
< 0.045
< 0.125 I
1 I
y s
'a t
j
r-m m
m
.m r--
m r-r-m r-
.r-m r-
.r-r-~m r-r-
c rp_
r,
- \\
o I
TAGEE l-18 (centfrued)
CL-11(c)
Isotope 04/15/87 04/29/87 05/13/87 05/27/87 06/10/87 06/24/87 07/08/87 07/22/87-.
08/05/87 Ba-7 2.36t0.36 0.76*0.10 0.83*0.13 0.65*0.12 0.81*0.006 0.49*0.15 1.98*0.15 0.67*0.08 0.58*0.07 K-40 4.75t0.21 7.60t0.27 14.40*0.73 8.74*0.36 6.84*0.32 5.54*0.34 5.84*6.28 6.03*0.31 7.73*0.36 m-54
< 0.008
< 0.009
< 0.025
< 0.012
< 0.013
< 0.016
< 0.011
< 0.010
< 0.012 re-59
< 0.012
< 0.025
< 0.059
< 0.031
< 0.031
'< 0.040
< 0.028
< 0.026
< 0.027 Co-58
<0.022
< 0.009
< 0.025
< 0.011
< 0.012
< 0.015
< 0.011
< 0.011
< 0.012 Co-60
< 0.007
< 0.006
< 0.028
< 0.013
< 0.014
< 0.016
< 0.011
< 0.011
< 0.013 Zn-65
< 0.024
< 0.022
< 0.071
< 0.028
<0.035
< 0.036
< 0.027
< 0.029
< 0.031 Nb-95
< 0.024
< 0.008
< 0.024
< 0.011
< 0.013
< 0.016
< 0.011
< 0.012
< 0.011 cn Ir-95
< 0.046
< 0.015
< 0.041
< 0.020
< 0.074
< 0.026
< 0.021
< 0.020
. < 0.020 t-131
< 0.010
< 0.015
< 0.024
< 0.015
< 0.018
< 0.029
< 0.019
< 0.016
< 0.012 Cs-134
< 0.007
< 0.007
< 0.022
< 0.010
< 0.014
< 0.014
< 0.0t-0
< 0.011
< 0.011 Cs-137 0.009t0.007
< 0.009
< 0.023 0.033*0.016 0.067*0.010 0.069*0.018
< 0.012
< 0.011
< 0.011 Be-140
< 0.025
< 0.032
< 0.074
< 0.052
< 0.C53
< 0.056
< 0.054
< 0.049
< 0.043 La-140
< 0.006 0.007
< 0.023
< 0.013
< 0.014
< 0.012
< 0.011
< 0.014
< 0.011 I
Ce-144
< 0.073
< 0.050
< 0.12
< 0.090
< 0.098
<0.12
< 0.088
< 0.059
< G.062 1
f gi s
'4, ;;
t u
m m
r-,
m r-r-
r-m r-n r-m m
r-,
r-m r-r-
r-r-
}'
1 TA8lf I-18 (centinued) isotope 08/19/87 09/02/87 09/16/87 09/30/87 10/14/87 10/28/87 11/25/87 12/30/87 Be-7 1.0710.15 1.64tc.13 1.65*0.15 2.53*0.22 1.2710.12 2.0111.06 2.23*0.11 4.17*0.14 K-40 7.00e0.37 6.24*0.34 4.86*0.33 6.46*0.45 7.7810.34 6.8910.31 6.03*0.29 6.42*0.28 Mn-54
< 0.012
< 0.015
<0.012
< 0.018
< 0.012
< 0.011
< 0.010
< 0.010 Fe-59
< 0.038
< 0.039
< 0.031
< 0.046
< 0.032
< 0.030
< 0.025
< 0.021 Co-58
< 0.012
< 0.016
<0.011
< 0.018
< 0.011
< 0.011
< 0.010
< 0.010 Co-60
< 0.013
< 0.015
< 0.013
< 0.019
< 0.013
< 0.013
< 0.011
< 0.010 Zn-65
< 0.030
< 0.038
< 0.026
< 0.039
< 0.031
< 0.031
< 0.026
< 0.024 H
I Nb-95
< 0.014
< 0.018
<0.012
< 0.01 8
< 0.011
< 0.011
< 0.012
< 0.010 4-a Zr-95
< 0.025
< 0.029
<0.020
< 0.029
< 0.018
< 0.020
< 0.019
< 0.017 1-131
< 0.017
< 0.034
< 0.016
< 0.026
< 0.01 6
< 0.01 7
< 0.023
< 0.016 Cs-134
< 0.011
< 0.015
< 0.010
< 0.014
< 0.009
< 0.010
< 0.010
< 0.010 Cs-137
< 0.014
< 0.016
< 0.014
< 0.020
< 0.012
< 0.011
< 0.011
< 0.010 Ba-140
< 0.062
< 0.089
< 0.055
< 0.076
< 0.052
< 0.033
< 0.060
< 0.033 La-140
< 0.015
< 0.022
< 0.013
< 0.018
< 0.013
< 0.010
< 0.014
< 0.006 Ce-144
< 0.094
< 0.12
< 0.093
< 0.12
< 0.071
< 0.051
< 0.006
'< 0.066 (a) grass collected in lieu of milk, Camma Isotopic analysis includes 1-131, coll'ection is samf-monthly (May - October) and monthly (November - April)
(c) control location, all other locations Indicators F
1 gI t
5 f
t 4
J
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- s o
'U-601177' L30-88(04 29)-LP
~
1A.120 ILLIN0lB POWER COMPANY cLINTON PWR'STAtl0N, P.O. BOX 678. CLINTON, ILLINOIS 61727 April 29, 1988 J
Docket No. 50-461
-Document Control Desk U.S. Nuclear Regulatory Consnission Washington, D.C.
20555
Subject:
Clinton Power Station Annual Radiological Environmental-Monitoring Report' Dear Sir Attached is the Annual Radiological Environmental Monitoring Report for Clinton Power Station for the period from initial criticality to December 31, 1987. This submittal is provided in accordance with the requirements of section 6.9.1.6 of the Clinton Power Station Technical Specifications.
If you have any questions, please contact me.
Sincerely yours.
'~~
. A. Spangenberg, III Manager - Licensing and Safety DW/krm w
s Attachment cca NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety f
// %
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