U-603607, Annual Radiological Environmental Operating Report
| ML031060463 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/07/2003 |
| From: | Polson K AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 1A.120, U-603607 | |
| Download: ML031060463 (126) | |
Text
AmerGen An Exelon/British Energy Company Clinton Power Station R.R. 3 Box 228 Clinton, IL 61727-9351 U-603607 1 A. 120 April 07, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Annual Radiological Environmental Operating Report AmerGen Energy Company, LLC (AmerGen) is submitting the 2002 Annual Radiological Environmental Operating Report for Clinton Power Station. This submittal is provided in accordance with the requirements of section 5.6.2 of the Clinton Power Station Technical Specifications. This report covers the period from January 1, 2002 through December 31, 2002.
Respectfully, Keith J. Polson Plant Manager Clinton Power Station EET/blf Attachment cc:
Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
Clinton Power Station 2002 Annual Radio logical Environmental Operating Report
t
-.--
-
I-
--
t I I7
-n-
-in Exelkn.m Nuclear 01 January 2002 - 31 December 2002 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT CLINTON POWER STATION - DOCKET NUMBER 50-461 Prepared by:
Clinton Power Station
-- page I of 119--
TABLE OF CONTENTS ITEM PAGE LIST OF TABLES 4
LIST OF FIGURES 5
I.
EXECUTIVE
SUMMARY
6 II.
INTRODUCTION A.
Characteristics of Radiation 7
B.
Sources of Radiation Exposure 8
C.
Description of the Clinton Power Station 12 D.
Nuclear Reactor Operations 13 E.
Containment of Radioactivity 16 F.
Sources of Radioactive Effluents 17 G.
Radioactive Waste Processing 17 III.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 19 A.
Program Description 19 B.
Direct Radiation Monitoring 31 C.
Atmospheric Monitoring 33 D.
Aquatic Monitoring 37 Fish 37 Shoreline Sediments 38 E.
Terrestrial Monitoring 38 Milk 39 Grass 39
- Vegetables 39 F.
Water Monitoring 40 Drinking Water 40 Surface Water 40
- Well Water 41 G.
Quality Assurance Program 43 H.
Changes to the REMP During 2002 43 IV.
2002 ANNUAL LAND USE CENSUS 44 Summary of Changes 47 V.
LIST OF REFERENCES 49
-- page 2 of 119 --
TABLE OF CONTENTS (continued)
ITEM PAGE VI.
APPENDICES A.
2002 Interlabatory Comparison Program Results 51 B.
REMP Annual Summary 69
- 1.
Sampling and Analysis Frequency Summary 70
- 2.
Radiological Environmental Monitoring Program Annual Summary 73 C.
Glossary 82 D.
Exceptions to the REMP during 2002 85 E.
CPS Radiological Environmental Monitoring Results during 2002 87
-- page 3 of 119 --
LIST OF TABLES TABLE SUBJECT PAGE 1
Common Sources of Radiation 1 1 2-A CPS Radiological Environmental Monitoring Program Sampling Locations 27 2-B CPS Radiological Monitoring Program Sampling Locations 28 3-A CPS REMP Reporting Levels for Radioactivity Concentrations in Environmental Samples 29 3-B Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection [LLD]
29 4
Average Quarterly TLD Results 32 5
Annual Average Gross Beta Concentrations in Air Particulates 35 6
Average Monthly Gross Beta Concentrations in Air Particulates 35 7
Average Gross Beta Concentrations in Drinking, Surface and Well Water 42 8
Annual Land Use Census Summary Results 46
-- page 4 of 119 --
LIST OF FIGURES FIGURE SUBJECT PAGE 1
Dose Contributions to the U. S. Population from Principal Sources of Radiation Exposure 11 2
Clinton Power Station Basic Plant Schematic 15 3
Potential Exposure Pathways of Man Due to Releases of Radioactive Material to the Environment 21 4
REMP Sample Locations within 1 Mile 23 5
REMP Sample Locations from 1 - 2 Miles 24 6
REMP Sample Locations from 2 - 5 Miles 25 7
REMP Sample Locations Greater than 5 Miles 26 8
Direct Radiation Comparison 32 9
Air Particulate Gross Beta Activity Comparison 36
-- page 5 of 119 --
EXECUTIVE
SUMMARY
- 1. EXECUTIVE
SUMMARY
This report describes the Annual Radiological Environmental Monitoring Program [REMP] conducted around the Clinton Power Station [CPS] during the 2002 calendar year. The REMP was performed as required by the CPS Operating License issued by the United States Nuclear Regulatory Commission [NRC]. The objective of the REMP is to assess the radiological impact upon the surrounding environment due to the operation of the Clinton Power Station.
During 2002, 1,461 environmental samples were collected.
These environmental samples represented; direct radiation, atmospheric, terrestrial, and aquatic environments including Clinton Lake surface water and public drinking water sampling.
Subsequently, 1,794 analyses were performed on these environmental samples.
Analytical results from these environmental samples revealed the presence of natural radioactivity and radioactivity attributed to other historical nuclear events.
The radioactivity levels detected were similar to the Pre-Operational levels found prior to the operation of CPS.
The CPS Pre-Operational REMP Report documented natural background radionuclides and man-made radioactivity in the environment surrounding CPS.
Radiological environmental measurements taken during 2002 demonstrated that both operational and engineered controls on the radioactive effluents released from the plant functioned as they were designed. Any radioactivity that was detected in the environment at Indicator Locations was appropriately compared with both the measurements at Control Locations and Pre-Operational results.
There were zero (0) radioactive liquid releases from CPS during 2002.
Releases of gaseous radioactive materials were accurately measured in plant effluents.
There was no gaseous effluent releases that approached the limits specified in the CPS Offsite Dose Calculation Manual [ODCM].
The highest calculated offsite dose received by a member of the public due to the release of gaseous effluents from Clinton Power Station was less than 0.0021 mR [milli-Roentgen].
All comparisons among Operational Data and Pre-Operational Data showed that during 2002, the operation of Clinton Power Station had no measurable effects upon the surrounding environment.
-- page 6 of 119 --
INTRODUCTION
II. INTRODUCTION The Radiological Environmental Monitoring Program [REMP] at Clinton Power Station [CPS] is designed to monitor the environment surrounding the plant for any radioactive material that may be released by CPS as a result of plant operations.
The primary concern is what impact - if any - radioactive materials released from CPS may have on the general public.
A.
CHARACTERISTICS OF RADIATION 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".
Gamma rays and X-rays are examples of electromagnetic radiation and are similar in many ways to visible light, microwaves, and radio waves. Particulate radiation may be either electrically charged such as an alpha or beta particle, or has no charge, like a neutron.
The term 'half-life' refers to the time required for half of a given amount of a radionuclide to decay. Some radionuclides have a half-life as short as a fraction of a second, while others have a half-life as long as millions of years. Radionuclides may decay directly into stable elements or may undergo a series of decays until they ultimately reach a stable element.
Radionuclides are found in nature such as radioactive uranium, thorium, carbon, and potassium, and may also be produced artificially in accelerators and nuclear reactors such as radioactive iodine, cesium, and cobalt.
wfYFICAL NATURALLY-1" c
iTYP1C"AL MAN-MADE"-
~6cciJi~ RA~o~aaJIDES A 10NC9 tt Uranium Iodine Thorium Cesium Carbon Cobalt Potassium Strontium Lead Barium The activity of a radioactive source is the average number of nuclear disintegrations [decay] of the source per unit of time. The unit of activity is called the curie.
For example, a one-curie radioactive source undergoes 2.2 trillion disintegrations per minute.
When compared against nuclear power plant effluents and environmental radioactivity however, this is a very large unit of measure.
Therefore, two sub-fractional units - the microcurie and the picocurie - are more commonly used terms.
1 curie (Ci)
= 2,220,000,000,000 disintegrations / minute 1 millicurie (mCi)
= 2,220,000,000 disintegrations / minute 1 microcurie (ktCi)
= 2,220,000 disintegrations / minute 1 nanocurie (nCi)
= 2,220 disintegrations / minute 1 picocurie (pCi)
= 2.22 disintegrations / minute
-- page 7of119 --
The microcurie [jiCi] is one millionth of a curie [Ci] and represents 2.2 million decays per minute.
The picocurie [pCi] is one millionth of a microcurie and represents 2.2 decays per minute.
Another way of comparing the pCi and the Ci is by using an analogy with distances.
A picocurie would be the width of a pencil mark while a curie would be the equivalent of 100 trips around the earth.
Radioactivity is related to the half-life and the atomic mass of a radionuclide. For example, Uranium-235 (U235) with a half-life of 704 million years requires over a half ton - 1,019 pounds - to equate to an activity of one curie. Whereas lodine-131 (1131) with a half-life of 8.04 days requires 0.0000000176 pounds to equate to 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 living cell are capable of producing biological damage.
Electromagnetic and particulate radiation can produce cellular damage in any of these ways. In assessing the biological effects of radiation, the type, energy, and amount of radiation must be considered.
External total body radiation involves exposure of all organs. Most background exposures are of this form. When radioactive elements enter the body through inhalation or ingestion, their distribution may not be uniform.
.XTAGET T0IS'SUJE0 ~'
/. NQCLID Bon&
W St ront iu
-90 (S 0
)"
fKidney
- >< *1D U11ranium'-'235'(U235)
Thyonid',
J:Y' 10oir&31 (11 1)j Musc"I aid 'LivPer Tiss Ces im"37' (Cs3 7
- G'astrointes'tlnal'Trt Cobalt-60 (Co" For example, radio-iodine selectively concentrates in the thyroid gland, whereas radio-cesium collects in muscle and liver tissue and radio-strontium collect in mineralized bone. The quantity and the duration of time that the radionuclide remains in the body also influence the total dose to organs by a given radionuclide.
When factoring radioactive decay and human metabolism factors, some radionuclides stay in the body for very short periods of time while others remain for years.
The amount of radiation dose that an individual receives is expressed in Rem.
Since human exposure to radiation typically involves very small exposures, the millirem [mRem] is the unit most commonly used.
One millirem is equal to one thousandth of a Rem.
B.
SOURCES OF RADIATION EXPOSURE Many sources of radiation exposure exist. The most common and least controllable source is natural background radiation from cosmic rays and the earth which mankind has always lived with and always will. Every
-- page 8 of 119 --
second 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 that has come from the earth - including our own body - is therefore, naturally radioactive.
Natural Radionuclides in the Earth's Crust Potassium-40 (K40)
Radium-226 (Ra226)
Uranium-238 (U238)
Radon-222 (Rn222)
Thorium-232 (Th232)
Lead-204 (Pb204)
Examples of radioactive materials found in the Earth's crust today consists of radionuclides such as Potassium-40, Uranium-238, Thorium-232, Radium-226 and Radon-222. These radionuclides are introduced into the water, soil and air by such natural processes as volcanic activity, weathering, erosion and radioactive decay.
Some of the naturally occurring radionuclides - such as radon - are a significant source of radiation exposure to the general public.
Radioactive radon is a chemically inert gas produced naturally in the ground as a part of the uranium and thorium decay series.
Radon continues to undergo radioactive
- decay, producing new naturally radioactive materials called 'radon daughter products'.
These new products - which are solid particles not gases - can adhere to surfaces such as dust particles contained in the air.
Concentrations of radon in the air vary and are affected by concentrations of uranium and thorium in the soil as well as altitude, soil porosity, temperature, pressure, soil moisture, rainfall, snow cover, atmospheric conditions and the time of the season.
Radon can move through cracks and openings into basements of buildings and become trapped in small air volumes 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.
Dust containing radon daughter particles can be inhaled and deposited on the surface of an individual's lung. Radon daughters emit a high-energy alpha radiation dose to the inner lung lining. Table 1 shows the average annual effective dose due to radon radiation exposure.
About 300 cosmic rays originating from outer space pass through each person every second.
-- page 9 of 119 --
Cosmic-Ray-Activated Radionuclides Beryllium-7 (Be7)
Tritium (H3)
Beryllium-10 (Be10)
Sodium-22 (Na22)
Carbon-14 (C04)
Phosphorus-32 (p32)
The interaction of cosmic rays with atoms in the earth's atmosphere produces radionuclides such as Beryllium-7, Beryllium-10, Carbon-14, Tritium-3, and Sodium-22.
Portions of these radionuclides become deposited on land or in water while the remainder stays suspended in the atmosphere.
Consequently, there are natural radioactive materials in the soil, water, air and building materials that contribute to radiation doses to the human body.
Natural drinking water contains trace amounts of uranium and radium while milk contains measurable amounts of Potassium-40.
Sources of natural radiation and their average contributing radiation doses are also summarized in Table 1.
Figure 1 graphically shows the percentage contribution from principal sources of radiation exposure to the general population of the United States.
Radiation exposure levels from natural radiation fluctuate with time and can also vary widely from location to location.
The average individual in the United States receives approximately 300 mRem per year, just from naturally occurring background radiation sources.
In some areas of the United States, the dose from natural radiation is significantly higher. Residents of Colorado - 5,000 feet above sea level
- will receive additional dose due to the increase of cosmic and terrestrial radiation levels. In fact, for every 1,000 feet in elevation above sea level, an individual will receive an additional one (1) mRem per year from cosmic radiation.
In several areas of the world, high concentrations of mineral deposits result in natural background radiation levels of several thousand mRem per year.
In addition to natural background radiation, the average individual is exposed to radiation from a number of man-made sources. The largest of these sources come 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 any given year. The annual dose to an individual from such irradiation averages approximately 53 mRem.
-- page 10 of 119 --
TABLE 1 COMMON SOURCES OF RADIATION A.
Average Annual Effective Dose Equivalent to the U.S. Population
- 1. Natural Sources
- a. Radon
- b. Cosmic, Terrestrial, Internal
- 2. Man-Made Sources
- a. Medical X-ray Diagnosis Nuclear Medicine
- b. Consumer Products
- c. Occupational
- d. Miscellaneous Environmental
- e. Nuclear Fuel Cycle mRem 200 100 mRem 39 14 10 1
<1
<1 Approximate Total 364 PERCENTAGE OF CONTRIBUTION Radon (55%)
Consumer Products (3%)
Nudear Medicne (4%)
DE X-ray Diagnosis (11%)
w OTHER (<1%)
- Misc. Environmental Sources
- Nuclear Fuel Cycle
- Occupational Cosmic, Terrestrial Internal (27%/6)
FIGURE 1: DOSE CONTRIBUTIONS TO THE U.S. POPULATION FROM PRINCIPAL SOURCES OF RADIATION EXPOSURE
-- page 11 of 119 --
o I
Smaller doses from man-made sources come from consumer products - such as televisions, smoke detectors, and fertilizers - as well as fallout from prior nuclear weapons testing, the production of nuclear power and its associated fuel cycle.
'Fallout' commonly refers to the radioactive debris that settles to the surface of the earth following the detonation of a nuclear weapon. Fallout is dispersed throughout the environment but can be washed down to the Earth's surface by rain or snow.
Radionuclides Found in Fallout lodine-131 (1131)
Strontium-90 (Sr90" Strontium-89 (Sr89)
Cesium-137 (Cs'3 )
There are approximately 200 radionuclides produced in the nuclear weapon detonation process with a number of these detected as fallout.
The radionuclides found in fallout that produce the majority of the fallout radiation exposures to man are lodine-131, Strontium-89, Strontium-90, and Cesium-137.
C.
DESCRIPTION OF THE CLINTON POWER STATION The Clinton Power Station [CPS] is located in Harp Township, DeWitt County, Illinois.
It is approximately six (6) miles east of Clinton, Illinois.
The station - including the V-shaped cooling lake - coupled with the surrounding AmerGen Energy Company, LLC owned land encloses approximately 13,730 acres.
This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by AmerGen. The plant is situated on approximately 150 acres on the northern arm of the lake. The cooling water discharge flume - 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 the aforementioned 13,730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa Anna Township[s].
The cooling lake was formed by constructing an earthen dam near the confluence of Salt Creek and at the North Fork of Salt Creek.
The resulting lake has an average depth of 15.6 feet which includes an ultimate heat sink of approximately 590 acre-feet. The ultimate heat sink provides for a sufficient water volume and cooling capacity for approximately 30 days of operation without any makeup water.
Through arrangements made with the Illinois Department of Conservation, Clinton Lake and much of the area immediately adjacent to the lake are used for public recreation activities including swimming, boating, water-skiing, hunting and fishing.
Recreational facilities exist at
-- page 12 of 119 --
Clinton Lake and accommodate up to 11,000 people per day during peak usage periods.
The outflow from Clinton Lake falls into Salt Creek and then flows in a westerly direction for about 56 miles before joining in with the Sangamon River. The Sangamon River drains into the Illinois River that enters the Mississippi River near Grafton, Illinois. The closest use of downstream water for drinking purposes is approximately 242 river miles downstream from Clinton Lake at Alton, Illinois as verified from the Illinois Environmental Protection Agency Public Water Service.
Although some farms throughout the Salt Creek drainage area use irrigation water downstream of Clinton Lake, this irrigation water is drawn from wells and not directly from the waters of Salt Creek.
Approximately 810,000 individuals live within 50 miles of the Clinton Power Station. Over half are located in the major metropolitan centers of Bloomington - Normal which is located approximately 23 miles to the north-northwest, Champaign - Urbana which is located approximately 31 miles towards the east, Decatur which is located approximately 22 miles to the south-southwest and Springfield which is located approximately 48 miles to the west-southwest. The nearest city is Clinton, the county seat of DeWitt County.
The estimated population of Clinton is approximately 8,000 residents. Outside of the urban areas, most of the land within 50 miles of the Clinton Power Station is used for farming. The principal crops grown are corn and soybeans.
D.
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 process called
'fission'. During fission, the uranium atom absorbs a neutron and splits to produce fission products, heat, radiation and free neutrons.
The free neutrons travel in the reactor core and further absorption of neutrons by uranium permits the fission process to continue.
As the fission process continues, more fission products, more radiation, more heat and more neutrons are produced and a sustained reaction occurs.
The heat produced is extracted from the fuel to produce steam, which subsequently drives a turbine generator to produce electricity.
The fission products are predominantly radioactive.
They are unstable elements that emit radiation as they change from unstable to stable elements.
Stable atoms in the materials that make up the components and structures of the reactor may absorb neutrons that are not absorbed by the uranium fuel. In such cases, stable atoms often become radioactive. This process is called 'activation' and the radioactive atoms, which result, are called 'activation products'.
-- page 13 of 119 --
Fission Products Activation Products Cesium-137 (Cs137)
Barium-140 (Ba140)
Cerium-144 (Ce144)
Strontium-90 (Sr90)
Cobalt-60 (Co60)
Manganese-54 (Mn54)
Iron-59 (Fe"9)
Zinc-65 (Zn65)
The reactor at the Clinton Power Station is a Boiling Water Reactor
[BWR].
Figure 2 provides a basic plant schematic for the Clinton Power Station and shows the separation of the cooling water from plant water systems.
In this type of reactor, the fuel is formed into small ceramic pellets that are loaded into sealed fuel rods.
-- page 14 of 119 --
\\
I I
\\
BUILDING3s<;\\
Pressure
- l
~~~~Fuel Assemblies lilll CGeneeasor Pum Stea Po
!mDriven Turbiebr Cotrl IC__
m Rodso Cooling7 sSystem
_Condenser FIGURE 2: CLINTON POWER STATION BASIC PLANT SCHEMATIC tD0 I
The fuel rods are arranged in arrays, called bundles, which are supported within the massive steel reactor vessel.
The voids 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 that has no moving parts - a jet pump - and recirculation water pumps are used to force the water to circulate through the fuel bundles to assure even cooling and heat removal from the fuel rods. Some of the water that absorbs heat from the fuel rods is changed to steam. The steam is used to drive a turbine that is coupled to a generator, thereby completing the conversion of nuclear energy released during fission into electricity.
After the steam passes through the turbine, it is condensed back into water and returned to the reactor vessel to repeat the cycle. As the water circulates through the reactor pressure vessel, corrosion allows trace quantities of the component and structure surfaces to mix into the water.
The corroded material also contains radioactive substances known as activated corrosion products.
Radioactive fission and activation products are normally confined to the primary coolant system although small leaks from the primary system may occur.
E.
CONTAINMENT OF RADIOACTIVITY During normal operating conditions, essentially all of the radioactivity is contained within the first of several barriers - that collectively - prevent radioactivity from escaping into our environment.
The fuel cladding - metal tubes - provides the first barrier.
The ceramic fuel pellets are sealed within zircaloy metal tubes.
There is a small gap between the fuel and the cladding where noble gases and volatile nuclides collect.
The reactor pressure vessel and the steel piping of the primary coolant system provide the second barrier. The reactor pressure vessel is a 70 foot high vessel with steel walls ranging from four (4) to seven (7) inches thick that encases the reactor core.
The reactor pressure vessel and the steel piping provide containment for all radionuclides in the primary coolant.
The Containment Building provides the third barrier.
The Containment Building has a steel-lined, four (4) foot thick reinforced concrete wall which completely enclose the reactor pressure 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 emitted during reactor operations or from radioactive materials created during reactor operations.
-- page 16 of 119 --
F.
SOURCES OF RADIOACTIVE EFFLUENTS In an operating nuclear power plant, most of the fission products are retained within the fuel and fuel cladding. However, the fuel manufacturing process leaves traces of uranium on the exterior of the fuel tubes. Fission products from the eventual fission of these traces may be released to the primary coolant. Other small amounts of radioactive fission products are able to diffuse or migrate through the fuel cladding and into the primary coolant. Trace quantities of the corrosion products from component and structural surfaces that have been activated, also get into the primary coolant.
Demineralizers from the water purification systems remove many soluble fission and activation products such as radioactive iodines, strontiums, cobalts and cesiums.
Noble gas fission products, activated atmospheric gases introduced with reactor feedwater and some of the volatile fission products such as iodine and bromine, carry over from the reactor pressure vessel to the condenser.
The steam jet air ejectors remove the gases from the condenser and transfer them to the off-gas treatment system. Within the off-gas treatment system, these gases are held up by adsorption on specially treated charcoal beds to allow radioactive gases to decay before they are released through the main ventilation exhaust stack.
Small releases of radioactive liquids from valves,
- piping, or equipment associated with the primary coolant system may occur in the Containment, Auxiliary, Turbine, Rad Waste and Fuel Buildings.
Noble gases become part of the gaseous wastes while the remaining radioactive liquids are collected in sumps and processed for reuse. Processed primary coolant water that does not meet chemical specifications for reuse may also become wastewater. These represent the principal sources of liquid effluents.
Information about radioactive effluents can be found in the Annual Radioactive Effluent Release Report.
This report contains a detailed description of all radioactive releases from CPS and the resulting radiation doses for the reporting period.
G.
RADIOACTIVE WASTE PROCESSING In a normal operating nuclear power plant, radioactive liquid and gaseous wastes are collected, stored and then processed through treatment systems to remove or reduce most of their radioactivity (excluding tritium) prior to reuse within the plant or discharged to the environment. These processing systems are required by the Clinton Power Station [CPS] Offsite Dose Calculation Manual [ODCM] to be installed and operable to help ensure all releases of radioactive liquid and gaseous effluents are As Low As Reasonably Achievable [ALARA]. As a matter of Station Policy, CPS strives to be a zero (0) liquid release plant and was able to accomplish that commitment throughout 2002.
-- page 17 of 119 --
The liquid waste treatment systems consist of filters, demineralizers and evaporators. Liquid wastes are routed through the waste evaporators to be degassed and distilled thereby reducing their volume and concentrating their radioactivity. The distillates are further treated through demineralizers and filters 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 may be discharged into the plant cooling water stream that varies from approximately 5,000 gallons per minute - when the unit is shutdown - to 567,000 gallons per minute when the unit is at full power. If a planned release were to occur, liquid effluents would be thoroughly mixed with - and diluted by - the plant cooling water as it traverses down a 3.4 mile discharge canal before entering Clinton Lake east of DeWitt County Road 14.
The Clinton Power Station Offsite Dose Calculation Manual requires that liquid effluents will not have a higher concentration of any radioisotope than which is established for continuous exposure to the general public.
This requirement is satisfied at the point in which the liquid effluent is first introduced to the cooling water flow. Thus, this additional dilution - which occurs along the 3.4 mile cooling water canal - further reduces the original concentration[s] of radioisotopes by 1/73 [at minimum flow during unit shutdown] and by 1/1890 [at maximum flow during unit operation] prior to the water entering Clinton Lake.
The concentrated radioactive solids captured from the liquid waste treatment system are processed and temporarily stored on-site until scheduled for shipment off-site for disposal at a licensed low-level waste disposal facility.
The gaseous effluents from the main condenser are held up in the off-gas charcoal beds for a minimum of 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br />.
With most of the radionuclides present having a radioactive half-life of less than eight (8) hours, this hold up process allows for their radioactive decay.
If the gaseous effluents from the ventilation exhaust system for the Containment Building and Secondary Containment structure exceed conservatively established set points, these effluents are processed through charcoal beds and High Efficiency Particulate Air [HEPA] filters within the Standby Gas Treatment System before being released to the environment.
The combination of HEPA filters and charcoal bed filtration is rated to be 95% efficient for removing iodines and greater than 99% efficient for removing any particulate material that is larger than one micron [one millionth of one inch] in diameter.
-- page 18 of 119 --
-11 RA bIOLOGICAL ENVIRONMENTAL MONITORING PROG7RAM
III. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A.
Program Description The Clinton Power Station is required to maintain a Radiological Environmental Monitoring Program [REMP] in accordance with the Code of Federal Regulations (CFR) Title 10, Section 20.1501 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 Radioactivity in the Environs of Nuclear Power Plants" USNRC Radiological Assessment Branch Technical Position on Radiological Environmental Monitoring (1979)
The REMP is an extensive program of sampling, measuring and analyzing that was instituted to monitor the radiological impact of reactor operation[s] on the surrounding environment.
Objectives of the program include the following:
identification, measurement and evaluation of existing radionuclides in the environment of the Clinton Power Station and fluctuations in radioactivity levels that may occur evaluation of the measurements to determine the impact of Clinton Power Station operations relative to the local radiation environment 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 releases to levels that are ALARA
- demonstration of compliance with regulations and the Clinton Power Station Offsite Dose Calculation Manual Implicit in these objectives are the requirements to trend and assess radiation exposure rates and radioactivity concentrations in the environment that may contribute to radiation exposure to the public. The program consists of two (2) phases, Pre-Operational
[Pre-Op] and Operational.
The Pre-Operational portion of the program was initiated in May 1980 and was completed on 27 February 1987 to establish 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 beginning of reactor operations.
The operational phase implements confirmatory measurements to verify that the in-station controls for the release of radioactive material are functioning as designed.
-- page 19 of 119 --
AmerGen Energy Company, LLC currently maintains a contract with Environmental Inc. Midwest Laboratory, for the analysis of all radiological environmental samples.
Environmental Inc. is located in Northbrook, Illinois.
Samples are currently collected by AmerGen Energy Company personnel and then shipped to the Environmental, Inc. laboratory for analysis.
After analysis, environmental samples are saved at the laboratory for a specified period of time in case any additional follow up analysis is required. Analytical results are then reported back monthly to CPS for review by the ODCM Program Owner.
Current regulatory guidance recommends evaluating direct pathways, or the highest trophic level in a dietary pathway, that contribute to an individual's dose. Figure 3 shows the basic pathways of gaseous and liquid radioactive effluents to the public.
The "important pathways" selected are based primarily on how radionuclides move through the environment that will eventually expose the public -
taking into consideration - man's use of the environment. The scope of the program includes the monitoring of five (5) environmental elements:
direct radiation atmospheric aquatic terrestrial environments ground and surface water Each pathway is monitored at "Indicator" and "Control" Locations.
Indicator Locations are generally within a ten (10) mile radius of the station that is expected to mimic station effects, if any exist. Control Locations are located greater than ten (10) miles from the plant - far enough away - so as not to be influenced by station operations.
These Control Location samples provide the basis by which to measure any fluctuations in radioactivity from Indicator Locations relative to natural phenomena and fallout.
Thus any increase in radioactive material concentration from an Indicator Location may be - due in part - to station operations.
-- page 20 of 119 --
RELEASES DILUTED BY ATMOSPHERE I C~
4 ANIMALS (MILK, MEAT)
.. I.......
.... I..:
i PLUME EXPOSURE I A 4&
AIRBORNE RELEASES I
PLUME EXPOSURE A
AND INHALATION ED
+
IF CLINTON POWER STATION CONSUME BY PEOPI 0
CONSUMED BY ANIMALS LIQUID RELEASES PEOPLE CONSUMED BY PEOPLE i
DRINKING WATERw SHORELINE
_v t
EXPOSURE RELEASES DILUTED BY LAKE I
F CONSUMED BY PEOPLE
/'
go FISH FIGURE 3:
POTENTIAL EXPOSURE PATHWAYS OF MAN DUE TO RELEASES OF RADIOACTIVE MATERIAL TO THE ENVIRONMENT
-- page 21 of 119 --
Sampling locations were established by considering site meteorology, area population distribution, site hydrology, and land use characteristics of the local area. These locations were selected primarily on the basis of where the highest predicted environmental concentrations would occur.
Locations of sampling stations are shown on maps in Figures 4 through 7. Table[s] 2-A and 2-B provide information on sample location, media sampled at each of these location[s], and a brief description of each location where samples were taken.
The location is listed according to distance (in miles) and the meteorological compass sector in relationship to the Station Heating, Ventilation, and Air Conditioning [HVAC] Stack.
-- page 22 of 119 --
FIGURE 4-REAP SAMPL E L OCA TIONS WI THIN f MILE
-- page 23 of 119 --
FIGURE 5: REMP SAMPLE L OCA TIONS FROM I - 2 IL ES
-- page 24 of 119 --
FIGURE 6:
REMP SAMPLE L OCA TIONS FROM 2 - 5 MILES
-- page 25 of 19 --
FIGURE 7. REMP SAMPLE LOCATIONS GREATER THAN 5 MILES
-- page 26 of 119 --
TABLE 2-A CPS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS TLD Sites
,Deg ription eto%
Supplemental CL-15 Control N
0.9 CL-36 Inner Ring N
0.6 CL-37 Special Interest N
3.4 CL-75 Special Interest N
0.9 CL-76 Outer Ring N
4.6 Supplemental CL-3 Control NE 0.7 CL-22 Inner Ring NE 0.6 CL-78 Outer Ring NE 4.8 Supplemental CL-2 Control NNE 0.7 CL-5 Inner Ring NNE 0.7 CL-77 Outer Ring NNE 4.5 Supplemental CL-99 Control NNE 3.5 CL-23 Inner Ring ENE 0.5 CL-65 Special Interest ENE 2.6 CL-79 Outer Ring ENE 4.5 Supplemental CL-91 Control ENE 6.1 Supplemental CL-8 Control E
2.2 CL-24 Inner Ring E
0.5 CL-41 Special Interest E
2.4 CL-53 Outer Ring E
4.3 Supplemental CL-84 Control E
0.6 CL-42 Inner Ring ESE 2.8 CL-54 Outer Ring ESE 4.6 Supplemental CL-7 Control SE 2.3 CL-43 Inner Ring SE 2.8 CL-55 Outer Ring SE 4.1 Supplemental CL-90 Control SE 0.4 its at)Iri CL-44 Inner Ring SSE 2.3 CL-56 Outer Ring SSE 4.1 Supplemental CL-114 Control SSE 12.5 CL-AI Control S
16 CL-45 Inner Ring S
2.8 CL-57 Outer Ring S
4.6 CL-46 Inner Ring SSW 2.8 CL-58 Outer Ring SSW 4.3 Supplemental CL-97 Control SSW 10.3 Supplemental CL-4 Control SW 0.8 Supplemental CL-33 Control SW 11.7 CL-47 Inner Ring SW 3.3 CL-60 Outer Ring SW 4.5 Supplemental CL-6 Control WSW 0.8 CL-48 Inner Ring WSW 2.3 CL-61 Outer Ring WSW 4.5 CL-1 Inner ring W
1.8 CL-49 Special Interest W
3.5 CL-74 Special Interest W
1.9 CL-80 Outer Ring W
4.1 CL-34 Inner Ring WNW 0.8 CL-64 Special Interest WNW 2.1 CL-81 Outer Ring WNW 4.5 CL-35 Inner Ring NW 0.7 CL-51 Outer Ring NW 4.4 CL-52 Outer Ring NNW 4.3 CL-63 Inner Ring NNW 1.3
-- page 27 of 119 --
TABLE 2-B CPS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS CL-1 Camp Quest (1.8 miles W)
CL-2 Site's main access road (0.7 miles NNE) a CL-3 Site's secondary access road (0.7 miles NE)
CL-4 Residence near recreation area (0.8 6
miles SW)
CL-6 CPS recreation area (0.8 miles WSW) 0 CL-7 Mascoutin Recreation Area (2.3 miles CLi SE)
CL-7D Mascoutin Recreation Area (2.3 miles ESE)
CL-8 DeWitt Cemetery (2.2 miles E) l CL-1 1*
Illinois Power substation (16 miles S)_
CL-12 DeWitt Pumphouse (1.6 miles E)
CL-13 Salt Creek bridge on Rt.10 (3.6 miles SW)
CL-14 Station Service Building
_a CL-15 Near residence on Rt. 900N (0.9 miles V
N)
CL-90 Start of discharge flume (0.4 miles SE)
CL-91 Parnell Boat Access (6.1 miles ENE) 1 CL-94 Old Clinton Road (0.6 miles E)
CL-99 North Fork canoe access area (3.5 miles C - 9 NNE)
CL-114*
Residence in Cisco (12.5 miles SSE) a/
CL-1 15 Site's secondary access road (0.7 miles CL15 NE)
CL-116 Pasture in rural Kenney (14 miles WSW)
=___X___X CL-117 Resident north of site (0.9 miles N)
V CL-118 Site's main access road (0.7 miles NNE)
V Ax___X Stati8n8 CL-1 CL-2 CL-7B Shoreliffe"
.ed1
'ent V
SE)
CL-8 DeWitt Cemetery (2.2 miles E)
CL-19 End of the discharge flume (3.4 miles E) 4 CL-105*
Lake Shelbyville (50 miles S) 4 CL-116 Pasture in rural Kenney (14 miles WSW) a
- Control Location V ODCM required samples
- Supplemental samples Note: Location[s] are listed by distance [in miles] along Station's HVAC stack.
with meteorological sector from the
-- page 28 of119 --
TABLE 3-A CPS REMP REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES a
If no drinking water pathway exists, a value of 30,000 pCi/I may be used.
b If no drinking water pathway exists, a value of 20 pCi/I may be used.
c Total for parent and daughter.
TABLE 3-B DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISd LOWER LIMIT OF DETECTION (LLD)
I A
1...r..
I I I,
EFio k.,ross b~eta u
_U.U I
H3 2,000e Mn 15 130 Fe59 30 260 Co5, Co 15 130 Zn65 30 260
=
Z r95 3 0 Nb 95 15 i~341f 0.07 1
60 Cs134 15 0.05 130 15 60 150 Cs140 18 0.06 150 18 80 180 Ba40 60 60 La 15 15 d
This list does not mean these nuclides are the only ones considered. Other nuclides are identified and reported when applicable.
If no drinking water pathway exists, a value of 3,000 pCi/I may be used.
If no drinking water pathway exists, a value of 15 pCi/I may be used.
e f
-- page 29 of 119 --
Sample Analysis Concentrations of radioactivity present in the environment will vary due to factors such as weather conditions, variations in the sampling collection technique and during sample analysis.
Several types of measurements may be performed to provide information about the types of radiation and radionuclides present.
Analyses that are performed on environmental samples collected for the CPS REMP include the following:
Gross alpha and beta analysis Gamma spectroscopy analysis Tritium analysis Strontium analysis Gamma dose (TLDs only)
A gross alpha and beta analysis measures the total amount of alpha and beta emitting radioactivity present in a sample. Both radiation[s] may be released by many different radionuclides. Gross activity measurements
- while useful as a general trend indicator - are not used to establish specific radionuclide concentrations. Therefore, gross activity analysis will only indicate whether the sample contains normal or abnormal concentrations of alpha or beta emitting radioactivity and serves as a precursor in which to identify samples that may require additional follow up analysis.
Samples are primarily analyzed for plant-contributed radionuclides released to the environment.
Irrespective of station operations and since naturally occurring radionuclides are abundant in all environmental samples, any positive result for a certain radionuclide, including gross alpha / beta measurements, will be discussed further in this section of the report.
-- page 30 of 119 --
B.
Direct Radiation Monitoring Radionuclides present in the air - in addition to those deposited in or on top of the ground - cause human exposure by immersion in the atmosphere or by deposition on the ground. TLDs [Thermo-Luminescent Dosimeters] are used to measure the ambient gamma radiation levels at 54 locations surrounding Clinton Power Station.
TLDs are crystalline devices that store energy when they are exposed to radiation. They can be processed months after their exposure with a minimal loss of this collected information.
This makes them well suited for quarterly environmental radiation measurements.
During TLD processing, stored energy is released as light and measured by a TLD reader.
The light intensity is proportional to the radiation dose the TLD was exposed to. The TLDs used for environmental monitoring around the Clinton Power Station are capable of measuring environmental levels of radiation as low as approximately 20 mRem per quarter.
Monitoring stations are placed near the site boundary and approximately five (5) miles from the reactor, in locations representing the 16 meteorological compass sectors.
Other locations are chosen to measure the radiation levels at places of special interest such as nearby residences, meeting places and population centers.
Control Locations are located further than ten (10) miles from the station so that they will not be influenced by station operations.
TLD measurements register the gamma ray exposure in milli-Roentgen [mR].
For reporting purposes mR is numerically equivalent to that of mRem.
Consequently, these terms are used interchangeably throughout this Annual Report.
A total of 216 TLD measurements were made throughout 2002. The average quarterly dose from our Indicator Location[s] was 21.3 mrem. At our Control Locations, the average quarterly dose was 20.8 mRem. These quarterly measurements ranged from 17.7 to 23.6 mRem for Indicator TLDs and 19.6 to 21.9 mRem for Control TLDs.
Figure 8 compares the 2002 quarterly TLD results with our Pre-Operational TLD quarterly averages.
Average doses (+/-2 standard deviations) - broken down by calendar quarter - are shown in Table 4 for both Indicator and Control Locations.
-- page 31 of 119 --
TABLE 4 AVERAGE QUARTERLY TLD RESULTS Average +/- 2a (mRem/quarter) 2no 18.4 +/- 2.9 21.9 +/- 3.8 18.8 +/- 3.2 2no 1b.8 1.-i 17.1 +/- 2.8 1.b + 1.U 21.3 +/- 3.0 18.8 +/- 3.2 3ro 1
17.3 +/- 3.3 1 [see below] A 1 19.1 +/- 4.7 4
J 17.6 +/- 3.7 24.6 +/- 4.5
[
17.8 +/- 2.2 A Clinton's 3rd Quarter ODCM REMP TLD results - both Indicator and Control - were determined to be inaccurate from our Vendor.
ODCM REMP TLD results were irradiated from an unknown external source of radiation during air transportation from California to Illinois prior to placement in the environment.
This resulted in inconsistent readings after adding this unknown exposure to their quarterly environmental exposure.
FIGURE 8: DIRECT RADIATION COMPARISON 50 l
PRE-OP
_ 25 El_ 2002 2
INDICATOR 1
v_
2002 CONTROL 1 st 2nd 3rd 4th QUARTER Given the above observations - and after factoring statistical variances - there were no significant increases in environmental gamma radiation levels resulting from station operations of the Clinton Power Station.
-- page 32 of 119 --
(*
47
C.
Atmospheric Monitoring The inhalation and ingestion of radionuclides in the air is a direct exposure pathway to man.
A network of ten (10) active Air Sampling Stations around the Clinton Power Station monitor this pathway. There are nine (9) 'Indicator' Air Sampling Stations locations strategically placed in areas that are most likely to reveal any measurable effects due to the release of radioactive effluents from the Clinton Power Station.
The
'Control' Air Sampling Station location is located approximately 16 miles south of the station in an area that is totally independent from any of the effects from station operation[s].
Historical meteorological data further supports that this 'Control' Air Sampling Station location is normally upwind from the station.
Mechanical air samplers are used to draw a continuous volume of air through a filter and charcoal cartridge collecting any particulates and radioiodines that may be present in the atmosphere. These samplers are equipped with a pressure-sensing flow regulator to maintain a constant sampling rate of air flow of about one (1) cubic foot per minute (CFM). The total volume is then calculated based upon the amount of time the air sampler was in operation coupled with this flow rate.
The air sampling equipment is maintained and calibrated by Clinton Power Station personnel using reference standards that are traceable back to the National Institute of Standards and Technology (NIST).
Air samples are collected every week and analyzed for gross beta and 113' activities. Quarterly, all air particulate filters collected throughout this period are combined and counted for gamma isotopic activity. Since the intent of particulate sampling is to measure airborne radioactivity released from the station, the counting of short-lived daughters - produced by the decay of naturally occurring radon and thoron - may otherwise mask any station contributions. Therefore, particulate filters are not analyzed for at least five (5) days after their collection. This allows for the radioactive decay of naturally occurring short-lived daughters, thus reducing their contribution interference to the overall gross beta activity.
Results from the gross beta airborne particulate analysis provides for comparisons between both Indicator and Control Locations - including those locations relative to spatial and temporal differences - throughout the year. These results are reported in units of pico-curies per cubic meter
[pCi/M3]. The calculated annual average was 0.025 pCi/m3 for all Indicator Locations and 0.026 pCi/m3 for the Control Location. These results are consistent with our Pre-Operational annual averages for both Indicator and Control Locations that were 0.027 pCi/M3.
The location with the highest calculated annual average was measured at Indicator Location CL-8 that is located 2.2 miles East of the Clinton Power Station. This location had a monthly average concentration of 0.026 pCi/m3.
Individual location averages for the 2002-year are presented in Table 5.
Minor fluctuations in the gross beta concentrations were noted throughout 2002.
The general trend for average weekly gross beta
-- page 33 of 119 --
concentrations from the Indicator Locations correlated to the trend for the Control Locations throughout the monitoring period.
This correlation is evidenced by the similarity of the trends in the average monthly gross beta concentrations contained within Figure 9.
There were no significant differences observed between these individual locations. Monthly averages for both Indicator and Control Locations for the 2002 year are presented in Table 6.
Fluctuations observed in the gross beta activity over the year can be attributed to changes in the environment, specifically during seasonal changes.
All gross beta concentrations for the 2002-year were within normal background levels and no significant increases were noted as a result of station operations.
Naturally occurring Be' [Beryllium] was the only gamma-emitting radionuclide detected in the analysis of particulate filters.
No measurable contribution to the overall level of airborne particulate radioactivity was identified as a result of station operations. The radioactivity that was detected - naturally occurring Be7 - is normally found in the environment and is consistent with the expected concentrations of natural radioactivity and fallout from prior atmospheric nuclear weapons testing.
-- page 34 of 119 --
TABLE 5 ANNUAL AVERAGE GROSS BETA CONCENTRATIONS IN AIR PARTICULATES Average +/- 2a (pCi/M3)
Station Description 2001 2002 CL-1 Camp Quest 0.025 +/- 0.009 0.025 +/- 0.010 CL-2 Site's Main Access Road 0.026 +/- 0.008 0.026 +/- 0.010 CL-3 Site's Secondary Access Road 0.026 +/- 0.010 0.026 +/- 0.011 CL-4 Residence near Recreation Area 0.025 +/- 0.009 0.025 +/- 0.010 CL-6 CPS Recreation Area 0.026 +/- 0.009 0.025 +/- 0.010 CL-7 Mascoutin Recreation Area 0.024 +/- 0.010 0.025 +/- 0.010 CL-8 DeWitt Cemetery 0.027 +/- 0.008 0.026 +/- 0.011 CL-1 1*
Illinois Power Substation 0.026 +/- 0.009 0.026 +/- 0.012 CL-15 Near Residence on Route 900N 0.025 +/- 0.013 0.025 +/- 0.011 CL-94 Old Clinton Road 0.026 +/- 0.009 0.025 +/- 0.010
- Control Station TABLE 6 AVERAGE MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES Average +/- 2a (pCi/M3)
MONTH 2001 Indicator 2002 Indicator 2001 Control 2002 Control January 0.033 +/-0.004 0.032 +/-0.003 0.033 +/-0.014 0.032 +/-0.013 February 0.029 +/-0.003 0.023 +/-0.001 0.027 +/-0.007 0.022 +/-0.014 March 0.021 +/-0.003 0.023 +/-0.003 0.022 +/-0.009 0.022 +/-0.013 April 0.022 +/-0.004 0.020 +/-0.002 0.023 +/-0.008 0.018 +/-0.009 May 0.019 +/-0.004 0.017 +/-0.002 0.019 +/-0.013 0.018 +/-0.007 June 0.021 +/-0.003 0.021 +/-0.002 0.021 +/-0.009 0.023 +/-0.010 July 0.025 +/-0.004 0.027 +/-0.004 0.026 +/-0.004 0.030 +/-0.016 August 0.026 +/-0.003 0.022 +/-0.002 0.027 +/-0.007 0.022 +/-0.013 September 0.026 +/-0.002 0.029 +/-0.004 0.026 +/-0.006 0.031 +/-0.017 October 0.022 +/-0.003 0.027 +/-0.003 0.021 +/-0.011 0.030 +/-0.015 November 0.033 +/-0.004 0.030 +/-0.003 0.033 +/-0.036 0.031 +/-0.023 December 0.029 +/-0.002 0.032 +/-0.003 0.028 +/-0.011 0.034 +/-0.017
-- page 35 of 119 --
PRE-OP (ALL SITES)
_-&onno nff)Trnl 0.052 -
IV I I.
1-0.047 -
2002 INDICATOR 0.042 0.037 CO 0.032 1 00v 0.027 p
0.022 0.017 0.012 t
is~~~~~~
0e ti Aat 9>fi0o
°D MONTH FIGURE 9: AIR PARTICULATE GROSS BETA ACTIVITY COMPARISON
-- page 36 of 119 --
D.
Aquatic Monitoring The Clinton Power Station utilizes a man-made lake as the source of cooling water and returns this cooling water back to the same lake while most nuclear power stations use once-through flow methods from a river, an ocean or body of water much larger than Clinton Lake.
If regulated radioactive liquid effluents were to be discharged from the Clinton Power Station into the cooling water outfall, long-lived radioisotopes could build up over a period time as the same water is reused on recurring trips through the station. Cooling water that exits from the plant will travel back into the eastern arm of Clinton Lake and then into the northern arm of the lake before returning back into the plant. Although the only user of Clinton Lake as a source of drinking water is CPS itself, Clinton Lake is a major recreational facility used for fishing, swimming, water skiing, boating and hunting.
Clinton Lake constitutes the primary environmental exposure pathway for radioactive materials from liquid effluents. Aquatic monitoring provides for the collection of fish and shoreline sediments to detect the presence of any radioisotopes related to the operation of the Clinton Power Station.
These samples are analyzed for naturally occurring and man-made radioactive materials.
Indicator samples were taken from various locations throughout Clinton Lake whereas the Control samples are obtained from Lake Shelbyville - approximately 50 miles south of Clinton Power Station - thus serving as an excellent data comparison to our station operations.
In addition to naturally occurring radioisotopes, Sr9O was found in one sample.
However, the overall concentration[s] of radionuclides in samples collected near the Clinton Power Station were comparable to the concentrations in samples collected from the Control Location at Lake Shelbyville.
The presence of this Sr90 fission product is attributable to previous nuclear weapons testing and fallout from the accident occurring at Chernobyl.
The operation of Clinton Power Station had no measurable contribution to the radioactive inventory towards the aquatic environment.
Fish Various samples of fish are collected from Clinton Lake and Lake Shelbyville.
From both lakes; our primary interest consists of largemouth bass, crappie, carp, and bluegill. The selections of these species are the fish most commonly harvested from the lakes by sporting fishermen.
Fish will ingest both floating sediments and during feeding - prey on other organisms - that will also ingest sediments that may otherwise retain radionuclides.
A radiological analysis from fish samples provides key information on the potential ingestion of radionuclides by humans via the aquatic pathway. These samples are collected semi-annually and analyzed by gamma spectroscopy.
The gamma spectroscopy analysis revealed that fish samples - from Clinton Lake and Lake Shelbeyville from 50 miles away - both identified the presence of naturally occurring K40 [Potassium] in all species. All other
-- page 37 of 119 --
analytical results were less than the Lower Limit of Detection (LLD) for each radionuclide of interest.
Shoreline Sediments Samples of shoreline sediments are collected at Clinton Lake.
Radiological analyses of shoreline sediments provide information on any potential shoreline exposure to humans, determining long-term trends, and the accumulation of long-lived radionuclides from our environment.
Samples are collected semi-annually and then analyzed for gross beta, gross alpha, Sr90 and gamma isotopic activities.
Shoreline sediment samples are dried prior to analysis and the results are reported in pCi/g [pico-curies per gram] dry weight. Naturally occurring radioisotopes were present in samples taken at Clinton Lake.
There was only one fission product - Sr90 - that was detected from this Indicator Location. The activity detected was well within the range from that measured during our Pre-Operational period [see below].
Pre-Op Range 2001 Range 2002 Range sotope (pCi/g dry)
(pCi/g dry)
(pCi/g dry)
Sr9o 0.011 - 0.056 0.011 - 0.027 0.013 - 0.042 E.
Terrestrial Monitoring In addition to direct radiation, radionuclides that are present in our atmosphere expose individuals when they are deposited on plant and soil surfaces.
Consuming animal products - such as meat and milk -
subsequently ingest them either directly by man or indirectly. To monitor this food ingestion pathway, samples of green leafy vegetables, grass and milk are analyzed.
Surface vegetation samples are collected monthly during the growing season from a number of locations for the purpose of monitoring the potential buildup of atmospherically deposited radionuclides. Because the radionuclides of interest - relative to Clinton Power Station operations -
are already present within our environment as a result of several decades of worldwide fallout or because they are naturally occurring, the presence of these radionuclides is anticipated from all of the samples that are collected. These samples are analyzed by gamma spectroscopy.
The gamma spectroscopy analysis revealed the presence of naturally occurring K40 [Potassium] and Be7 [Beryllium] in several samples.
All other analytical results were less than the Lower Limit of Detection (LLD) for each radionuclide. The operation of Clinton Power Station had no measurable contribution to the radioactive concentration of the terrestrial environment.
-- page 38 of 119 --
Milk There is no known commercial production of milk for human consumption within a five (5) mile radius of the Clinton Power Station.
However, milk samples are collected from a dairy located approximately 14 miles West-Southwest of the station (twice a month during May through October and once a month during November through April to coincide with the grazing seasons).
These samples are analyzed for 113', Sr90, and gamma isotopic activities.
Results from these analyses showed Sr" concentrations ranging from 0.6 to 2.0 pCi/I [pico-curies per liter of milk].
And although not a REMP Sample, the analysis of Sr90 on milk samples was added to the REMP early during the operational phase of the program and as such, no Pre-Operational data for this isotope is available [see below*]. There was no I"' detected in any of the milk samples collected.
Pre-Op Range 2001 Range 2002 Range Isotope (pCi/I)
(pCi/I)
(pCi/I)
I Sr90
- Not Available I
0.5 - 3.1 1
0.6 - 2.0 I
Grass In addition to milk samples, grass samples are also collected at three (3) Indicator Locations and at one (1) Control Location.
These samples are collected twice a month during May through October and once a month during November through April (when available). Grass samples are analyzed for gamma isotopic activity including 1131.
The results from the analyses showed only naturally occurring Be7 and K40 in these samples. There was no 1131 detected in any of the grass samples collected.
Vegetables The Clinton Power Station obtains broadleaf vegetable samples from three (3) Indicator Locations and at one (1) Control Location. The Indicator Locations are located in the meteorological sectors with the highest potential for surface deposition and the Control Location is in a meteorological sector and distance - approximately 13 miles upwind -
which is considered to be unaffected by station operations. Samples are collected once a month during the growing season (June through September) and are analyzed for gross beta and gamma isotopic activities including 1 1.
The results from the analyses identified only naturally occurring Be7 and K40 from these samples.
There was no 1131 detected in any of the vegetable samples collected.
-- page 39 of 119 --
F.
Water Monitoring Water monitoring provides for the collection of drinking water, surface water, and ground water (well water) samples to detect the presence of any radioisotopes relative to station operations at the Clinton Power Station.
The only identified user of water from Clinton Lake for domestic purposes is the Clinton Power Station.
Samples taken are analyzed for naturally occurring and man-made radioactive isotopes.
Average gross beta concentrations in surface, drinking and well water[s] are presented within Table 7 at the end of this section.
Water monitoring results show no measurable effects resulting from the operation of the Clinton Power Station.
Drinking Water A composite water sampler is located at the Station Service Building that collects a small - fixed volume - sample at hourly intervals.
The sampler discharges each sample into a common sample collection bottle.
Therefore, the monthly sample analyzed by our contracted laboratory service represents a composite of the individual samples that are collected throughout the month. This monthly composite sample is then analyzed for gross alpha, gross beta and gamma isotopic activities. A portion of each of these monthly samples is further mixed with the other monthly samples collected during each calendar quarter. This quarterly composite sample is then analyzed for H3 [Tritium].
Gross beta activity ranged from 0.8 to 2.0 pCi/l. These levels are attributed to very fine particles of sediment containing K40 that are not removed during the chlorination and filtration process.
The results from the H3 and gamma-emitting radioisotope analysis were all less than the Lower Limit of Detection (LLD).
Surface Water Composite Water Samplers are installed at three (3) locations sampling surface water from Clinton Lake.
These Composite Water Samplers collect a small volume of surface water at regular intervals and discharge the sample into a large sample collection bottle. Monthly, this water is then collected.
Two (2) of the Composite Water Samplers are located upstream from Clinton Power Station and are therefore unaffected by any plant liquid releases occurring downstream.
The third Composite Water Sampler is positioned to sample water being released from the plant at the start of the plant discharge flume.
Grab samples are also collected from one (1)
Indicator Location on Clinton Lake.
-- page 40 of 119 --
Surface water samples are analyzed for gross beta, gamma isotopic, and H3 [Tritium] activities. Additional analyses for gross alpha activity are performed on the upstream water samples as required.
Additional analyses for gross alpha activity and 1131 activity are performed on water samples taken from the discharge flume. Tritium analyses are performed quarterly from all of the monthly composites from all Water Composite Sample locations.
Results of all gross beta analyses ranged from 1.4 to 9.3 pCi/l for the composite water samples and 2.2 to 3.1 pCi/I for the grab samples.
Pre-Operational gross beta activity ranged from 1.1 to 7.6 pCi/I.
These results are attributed to naturally occurring K40 suspended as fine sediment particles in the water.
Other types of samples -
such as Shoreline Sediments - have further validated the presence of K40 in Clinton Lake All samples analyzed for H3 [Tritium] were all less than the Minimum Detectable Activity (MDA).
Pre-Operational H3 [Tritium] concentrations ranged from 220 to 330 pCi/I.
As noted in Reference E187, previous nuclear weapons testing have increased the pre-1960 levels of Tritium (6 -
24 pCi/I) by a factor of approximately 50 to 300-1,200 pCi/I.
Gamma-emitting radioisotopes were all below the Lower Limits of Detection (LLD) and there wasn't any 113' detected from any surface water sample collected.
Well Water Every quarter - both treated and untreated well water samples - are collected from the well serving the Village of DeWitt and from a well serving the Illinois Department of Conservation at the Mascoutin State Recreational Area. Samples are analyzed for I1"3, gross alpha, gross beta, H3 [Tritium]
and gamma isotopic activities as required.
Results of the gross beta analyses ranged from 1.2 to 3.4 pCi/I.
Pre-Operational gross beta activity ranged from 1.1 to 5.1 pCi/I. The gross beta activity was attributed to naturally occurring K40 suspended as fine sediment particles in water.
Gamma-emitting radioisotopes were all below the lower limits of detection (LLD) and there wasn't any 1'3' or H3 detected from any well water sample collected.
-- page 41 of 119 --
TABLE 7 AVERAGE GROSS BETA CONCENTRATIONS IN DRINKING, SURFACE AND WELL WATER Average +/-2o (pCi/I)
STATION DESCRIPTION 2001 2002 Drinking Water CL-14 Station Service Building 1.4 +/- 0.6 1.2 +/- 0.7 Surface Water CL-13 Salt Creek Bridge on Route 10 2.9 +/- 0.8 2.6 +/- 0.7 CL-90 Start of Discharge Flume 2.9 +/- 1.5 4.1 +/- 5.7 CL-91 Parnell Boat Access 2.7 +/- 0.9 2.0 +/- 0.8 CL-99 North Fork Canoe Access Area 3.4 +/- 4.2 2.4 +/- 1.7 Well Water CL-7D Mascoutin Recreation Area 2.3 +/- 0.8 2.2 +/- 2.8 CL-12(T)
DeWitt Pumphouse 2.4 +/- 0.0 2.4 +/- 0.1 CL-1 2(U)
DeWitt Pumphouse 1.9 +/- 1.3 2.7 +/- 2.0 (U) Untreated (T) Treated Fluctuations observed in the gross beta activity over the year can be attributed to changes in the environment, specifically during seasonal changes.
-- page 42 of 119 --
G.
Quality Assurance Program To establish confidence and credibility that both the data collected and reported are accurate and precise, REMP activities are incorporated into the Quality Assurance (QA) program, which includes assessments, audits, and surveillances.
The Quality Assurance program requires the following:
Participation in inter-comparison programs, such as the Environmental Resource Associates (ERA) crosscheck program.
- Audits of analysis laboratory functions and their facilities.
Periodic review of the Clinton Power Station procedures specifying sampling techniques.
Duplicate analysis of all samples received (excluding TLDs).
This requirement is to validate laboratory precision.
The routine counting of quality control samples.
The analytical results provided by the laboratory were reviewed monthly to ensure the required minimum sensitivities have been achieved and the proper analyses have been performed.
Our Vendor Environmental Inc.,
Mid-West Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of their quality control program in December 1971.
These programs are operated by agencies that supply environmental type samples -
such as milk and water -
containing concentrations of radionuclides that are only known to the issuing agency and not the participating laboratory. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and alert them to any possible problems.
Results from their 2002 Environmental Inc., Mid-West Laboratory cross-check program are shown in Appendix A of this report.
H.
Changes to the REMP During 2002 On occasion, revisions to the Radiological Environmental Monitoring Program are necessary so as to improve the monitoring of the environmental exposure pathways.
Changes may result from items identified during the performance of the Annual Land Use Census, incorporation of any revised or new regulatory requirements or from Quality Assurance Audits.
During the course of 2002, there were no changes to the REMP program as delineated within the Off-Site Dose Calculation Manual.
-- page43of119--
2002 ANNUAL LANb USE CENSUS
IV. 2002 ANNUAL LAND USE CENSUS Each year an Annual Land Use Census is conducted to ensure that changes in the use of areas - at and beyond the site boundary - are identified and that any necessary modifications to the Radiological Environmental Monitoring Program [REMP] are made.
The information gathered during the Annual Land Use Census is used for Radioactive Effluent Technical Specifications [RETS] dose assessments that feeds into the REMP ensuring that these programs accurately reflect the environment surrounding CPS.
The Annual Land Use Census is conducted during the growing season satisfying the CPS Offsite Dose Calculation Manual (ODCM) requirements.
The Annual Land Use Census is conducted to identify the nearest milk animals, the nearest residence and the nearest garden of greater than 538 square feet that produce broadleaf vegetation - all within a distance of five (5) miles - in each of the 16 meteorological sectors.
The Annual Land Use Census shall also identify - within a distance of three (3) miles - the location in each of the 16 meteorological sectors all milk animals and all gardens of greater than 538 square feet that produce broadleaf vegetation.
A detailed summary of the Annual Land Use Census is provided in a separate document that is permanently archived at CPS.
In order to assemble as much information as possible, the location of area residences, their critical age groups, milking animals, the size and vegetable content of gardens and along with livestock, were all recorded from each sector within five (5) miles, as stated above.
These land use parameters are then used in the assessment of potential radiological doses to individuals for the stated sectors. This information provides the most restrictive parameters used for dose assessments that will result in the highest calculated dose within each sector. Additional information regarding dose assessments to members of the public is provided within the 2002 CPS Annual Radioactive Effluent Release Report.
Area residents were surveyed who reside within a five (5) mile radius of the station by either direct contact, via a mail-in questionnaire, a telephone interview or direct observation within the 16 geographical sectors surrounding CPS.
The information provided within this section of the report is a summary of the 2002 results from that census. The nearest residence, garden, and milk animal in for each meteorological sector - out to a distance of five (5) miles - are illustrated in Table 8.
Data from the 2002 Annual Land Use Census was obtained using the following means:
When mail-in response[s] were ineffective, door-to-door solicitation of residences / land owners identified from the 2001 Annual Land Use Census was performed with a DeWitt County plat book available if needed.
Telephone solicitation of persons who were unavailable during the 'door-to-door' survey and who did not mail back their questionnaire.
-- page44of 119--
By direct observation of land when the aforementioned methods proved to be unsuccessful. If an individual was unable to be contacted, data from the previous year was used.
Contacted several state and local agencies.
-- page 45 of 119 --
TABLE 8 ANNUAL LAND USE CENSUS
SUMMARY
RESULTS Sector Nearest Residence Nearest Garden Nearest Milk
[miles]
[miles]
(see Note)
N 0.9 0.9 0.9 NNE 1.0 2.9 1.3 NE 1.3 2.1 3.4 ENE 1.8 1.8 N/A E
1.0 1.0 1.0 ESE 3.2 3.3 N/A SE 2.8 4.4 4.4 SSE 2.4 2.7 N/A S
3.0 4.1 N/A SSW 2.9 N/A 3.4 SW 0.7 N/A 3.6 WSW 1.6 2.3 3.4 W
1.6 2.0 2.1 WNW 1.6 1.6 N/A NW 1.6 N/A N/A NNW 1.7 1.3 1.3 N/A None identified within five (5) miles of CPS within this meteorological sector.
Note - Not used for human consumption The Annual Land Use Census results were validated to ensure that the REMP will provide representative measurements of radiation and radioactive materials from exposure pathways and for radionuclides that lead to the highest potential radiation exposure to the general public resulting from station operations.
After carefully reviewing the Annual Land Use Census results - coupled with station effluent release data provided by the CPS Chemistry Department - an evaluation is conducted to ensure current ODCM sampling location requirements are adequate.
As a result of that evaluation, no changes in REMP sampling locations were required.
-- page 46 of 119 --
Summary of Changes Identified in 2002 Annual Land Use Census Nearest Residence Changes in census locations for the nearest resident were identified in one (1) of the sixteen (16) geographical sectors and is indicated below:
2001 Census Location 1.8 miles SSE 2002 Census Location 2.4 miles SSE There were no changes or additions to the REMP as a result of the Nearest Resident Census.
Garden Census Changes in census locations for the nearest garden were identified in seven (7) of the sixteen (16) geographical sectors and are indicated below:
2001 Census Location 2.6 miles ENE 2.8 miles SSE 3.0 miles S 3.6 miles SW 2.2 miles WSW 2.9 miles NW
> 5.0 miles NNW 2002 Census Location 1.8 miles ENE 2.7 miles SSE 4.1 miles S
> 5.0 miles SW 2.3 miles WSW
> 5.0 miles NW 1.3 miles NNW There were no changes or additions to the REMP garden sampling locations as a result of the Garden Census.
Milk Animal Census Milk animals within five (5) miles were located in the sixteen (16) geographical sectors surrounding CPS. Ten (10) locations were identified within this five (5) mile radius.
Only milk animals were specifically identified for this report.
Of the livestock identified, milk animals were being raised primarily for nursing [nursing of their calves] and were being used for meat production [for both their own use and sold commercially]. There were no residents that milked their animals for any human consumption.
Other livestock raised in the area were identified, but will not be addressed within this report.
Changes in the census locations for the nearest livestock / dairy were identified in two (2) of the sixteen (16) geographical sectors and are indicated below:
2001 Census Location 4.8 miles ENE 2.4 miles NW 2002 Census Location
> 5 miles ENE
> 5 miles NW
-- page 47 of 119 --
No changes or additions to REMP milk sampling locations were made as a result of the Milk Animal Census.
-- page 48 of 119 --
LIST O REFERENCES
V. LIST OF REFERENCES American National Standards Institute, Inc., "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry,"
ANSI N545-1975.
Code of Federal Regulations, Title 10, Part 20 (Nuclear Regulatory Commission).
CPS 2001 Annual Radioactive Effluent Release Report.
"Environmental Radioactivity," M. Eisenbud, 1987 (E187).
"Natural Radon Exposure in the United States," Donald T. Oakley, U.S.
Environmental Protection Agency. ORP/SID 72-1, June 1972.
Federal Radiation Council Report No. 1, "Background Material for the Development of Radiation Protection Standards," May 13, 1960.
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).
International Commission on Radiation Protection, Publication No. 39 (1984),
"Principles of Limiting Exposure to the Public to Natural Sources of Radiation."
"Radioactivity in the Environment:
Sources, Distribution and Surveillance,"
Ronald L. Kathren, 1984.
National Council on Radiation Protection and Measurements, Report No. 22, "Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure,"
(Published as National Bureau of Standards Handbook 69, issued June 1959, superseding Handbook 52).
National Council on Radiation Protection and Measurements, Report No. 39, "Basic Radiation Protection Criteria," January 1971.
National Council on Radiation Protection and Measurements, Report No. 44, "Krypton-85 in the Atmosphere - Accumulation, Biological Significance, and Control Technology," July 1975.
National Council on Radiation Protection and Measurements, Report No. 91, "Recommendations on Limits for Exposure to Ionizing Radiation," June 1987.
National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposure of the Population of the United States,"
September 1987.
-- page 49 of 119 --
National Research Council, 1990, Committee on Biological Effects of Ionizing Radiation (BEIR V), Board on Radiation Effects Research on Life Sciences, "The Effects of Exposure to Low Levels of Ionizing Radiation".
United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.
United States Nuclear Regulatory Commission, Regulatory Guide 4.13, "Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications," Revision 1, July 1977.
United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 1977.
United States Nuclear Regulatory Commission Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
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.
Technical Specification, Clinton Power Station, Unit No. 1, Docket No. 50-461, Office of Nuclear Reactor Regulation, 1986.
Clinton Power Station, Updated Safety Analysis Report.
Clinton Power Station, Unit 1, Off-Site Dose Calculation Manual.
-- page 50 of 119 --
- ~Environmental, Inc.
Mdw est Laboratory an AJbgheny Technooges Co.
700 Landwely Road
- Noihbxock, IL 8600622 (847) 584-0700 fa, (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:
Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January, 2002 through December, 2002
-- page 51 of 119 --
Appendix A Interlaboratory Comparison Proqram Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Results of internal laboratory testing is also listed.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house 'blank" samples for the past twelve months. Data for previous years available upon request. request.
Table A-5 list results of the in-house 'duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.
Attachment A lists acceptance criteria for "spiked" samples.
Out-of-limit results are explained directly below the result.
Al
-- page 52 of II9 --
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter
> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter
> 50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter
> 30 pCi/liter or kg 10% of known value Potassium-40
> 0.1 g/liter or kg 5% of known value Gross alpha 20 pCi/liter 5.0 pCi/liter
> 20 pCi/liter 25% of known value Gross beta 100 pCi/liter 5.0 pCi/liter
> 100 pCi/liter 5% of known value Tritium 4,000 pCi/liter 1 s = (pCi/liter) =
169.85 x (known)00933
> 4,000 pCi/liter 10% of known value Radium-226,-228 0.1 pCi/liter 15% of known value Plutonium 0.1 pCi/liter, gram, or sample 10% of known value lodine-131, 55 pCi/liter 6.0 pCi/liter lodine-129b
> 55 pCi/liter 10% of known value Uranium-238, 35 pCi/liter 6.0 pCi/liter Nickel-63b
> 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter
> 100 pCi/liter 10% of known value Othersb 20% of known value a From EPA publication, 'Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
A2 A2--
page 53 of 119--
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits STW-940 STW-940 STW-942 STW-942 STW-944 STW-944 STW-944 STW-944 STW-944 STW-944 STW-944 STW-944 STW-951 STW-951 STW-951 STW-951 STW-952 STW-952 STW-952 STW-952 STW-952 STW-952 STW-953 d STW-954 STW-965 STW-965 STW-965 STW-965 STW-965 STW-965 STW-965 STW-965 STW-965 STW-965 STW-965 STW-965 STW-966 STW-966 STW-967 STW-968 STW-968 STW-968 STW-969 02/20/02 02/20/02 02120J02 02/20/02 02/20/02 02/20/02 02/20/02 02/20/02 02/20/02 02/20/02 02/20/02 02/20/02 05/22/02 05/22/02 05/22/02 05/22/02 05/22/02 05/22/02 05/22/02 05/22/02 05/22/02 05/22/02 05/22/02 05/22/02 08/21/02 08/21/02 08/21/02 08/21/02 08/21/02 08/21/02 08/21/02 08/21/02 08/21/02 08/21/02 08/21/02 08/21/02 11/20/02 11/20/02 11/20/02 11/20/02 11/20/02 11/20/02 11/20/02 Sr-89 Sr-90 Gr. Alpha Gr. Beta Ba-i 33 Co-60 Cs-134 Cs-137 Ra-226 Ra-228 Uranium Zn-65 Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-I 34 Cs-137 Gr. Beta Sr-89 Sr-90 H-3 1-131 Ba-133 Co-60 Cs-134e Cs-137 Gr. Alpha Gr. Beta Ra-226 Ra-228 Sr-89 Sr-90 Uranium Zn-65 Gr. Alpha Gr. Beta H-3 Ra-226 Ra-228 Uranium 1-131 53.0 +/- 2.5 16.6 +/-0.5 6.5 +/- 0.6 45.7 +/- 3.1 25.8 +/- 1.5 76.9 +/- 2.7 38.7 +/- 1.6 92.9 +/- 2.7 15.3 +/- 0.7 17.5 +/- 0.4 23.8 +/- 1.1 361.0 +/- 9.2 23.9 +/- 2.5 5.9 +/- 0.5 5.6 +/- 0.9 7.6 +/- 0.2 37.9 +/- 0.7 14.5 +/- 0.8 50.0 +/- 2.0 171.0 +/-2.5 28.4 +/- 4.8 32.4 +/- 3.1 13900.0 +/- 100.0 14.6 +/- 0.3 71.9 +/- 2.1 23.8 +/- 1.0 62.9 +/- 1.2 219.3 +/- 10.7 74.4 +/- 0.6 26.7 +/- 0.4 5.0 +/- 0.5 6.0 +/- 0.7 28.4 +/- 1.5 36.5 +/- 1.1 4.1 +/-0.1 92.4 +/- 2.2 9.3 +/- 0.4 44.7 +/- 1.0 10100.0 +/- 38.7 11.6 +/-0.1 16.0 +/- 1.4 15.5 +/- 0.5 6.0 +/-0.4 55.3 +/- 5.0 15.9 +/-5.0 8.0 +/- 5.0 48.3 +/- 5.0 28.9 +/- 5.0 73.4 +/- 5.0 42.1 +/-5.0 88.8 +/- 5.0 14.3 +/- 2.2 16.9 +/-4.2 28.3 +/- 3.0 359.0 +/- 35.9 22.8 +/- 5.7 6.1 +/-0.9 4.5 +/- 1.1 9.3 +/- 3.0 39.1 +/-5.0 17.1 +/-5.0 52.1 +/- 5.0 189.0 +/- 28.4 31.7 +/- 5.0 28.3 +/- 5.0 17400.0 +/- 1740.0 14.7 +/-2.0 80.0 +/- 8.0 23.3 +/- 5.0 71.7 +/- 5.0 214.0 +/- 10.7 58.8 +/- 14.7 21.9 i 2.2 5.0 +/- 0.8 4.7 +/- 1.2 29.0 +/- 5.0 36.4 +/- 5.0 5.0 +/- 3.0 95.7 +/- 9.6 12.2 +/-5.0 47.0 +/- 5.0 10200.0 +/- 1020.0 12.1 +/-1.8 15.1 +/- 3.8 19.2 +/- 3.0 6.8 +/- 2.0 46.6 - 64.0 7.2 - 24.6 0.0 - 16.7 39.6 - 57.0 20.2 - 37.6 64.7 - 82.1 33.4 - 50.8 80.1 - 97.5 10.6 - 18.0 9.6 - 24.2 23.1 - 33.5 298.0 - 420.0 13.0 - 32.6 4.5 - 7.7 2.6 - 6.5 4.1 - 14.5 30.4 - 47.8 8.4 - 25.8 43.4 - 60.8 140.0 - 238.0 23.0 - 40.4 19.6 - 37.0 14400.0 - 20400.0 11.2 - 18.2 66.4 - 93.6 14.6 - 32.0 63.0 - 80.4 195.0 - 233.0 33.5 - 84.1 13.2 - 30.6 3.7 - 6.3 2.7 - 6.7 20.3 - 37.7 27.7 - 45.1 0.0 - 10.2 79.4 - 112.0 3.5 - 20.9 38.3 - 55.7 8440.0 - 12000.0 9.0 - 15.2 8.6 - 21.6 14.0 - 24.4 3.3 - 10.2 Al -1
-- page 54 of 119 --
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits STW-970 11/20/02 Co-60 104.0 +/- 7.1 104.0 +/- 5.2 95.0 - 113.0 STW-970 11/20/02 Cs-1 34 48.2 +/- 2.3 55.5 +/- 5.0 46.8 - 64.2 STW-970 11/20/02 Cs-137 109.0 +/- 12.6 117.0 +/- 5.9 107.0 - 127.0 STW-970 11/20/02 Gr. Beta 252.0 +/- 26.8 288.0 +/- 49.5 244.0 -416.0 STW-970 11/20/02 Sr-89 43.2 +/- 0.7 47.6 +/- 5.0 38.9 - 56.3 STW-970 11/20/02 Sr-90 7.5 +/-0.2 7.6 +/-5.0 0.0 - 16.2 STW-971 11/20/02 Gr. Alpha 74.9 +/- 1.5 103.0 +/- 25.8 58.4 - 148.0 STW-971 11/20/02 Ra-226 8.9 +/-0.0 9.1 +/- 1.4 6.7-11.5 STW-971 11/20/02 Ra-228 15.3 +/-0.1 17.8 +/-4.5 10.1 -25.5 STW-971 11120/02 Uranium 51.7 +/- 1.6 61.7 +/- 6.2 51.0 - 72.4 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).
b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
d Analysis was repeated; result of reanalysis: 16114+/-487 pCi/L.
e ERA acknowledged an unacceptably high percentage of failure for Cs-1 34 and questioned its own control limits.
No problems were identified in the analysis.
A1 -2
-- page 55 of 119 --
TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLDs).
mR Lab Code TLD Type Date Measurement Known Lab Result Control Value
+/- 2 sigma Limits Environmental, Inc.
2001-1 2001-1 2001-1 2001-1 2001-1 2001 -1 2001 -1 2001-1 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 24-12-01 24-12-01 24-12-01 24-12-01 24-12-01 24-12-01 24-12-01 24-12-01 Reader 1, #1 Reader 1, #1 Reader 1, #2 Reader 1, #2 Reader 1,#3 Reader 1, #3 Reader 1, #4 Reader 1, #4 3.98 3.98 7.07 7.07 15.9 15.9 63.61 63.61 3.71 +/- 0.12 3.38 +/- 0.09 7.89 +/- 0.18 7.64 +/- 0.25 18.62 +/- 0.40 19.58 +/-0.12 78.24 +/- 1.23 79.89 +/- 2.47 2.79 - 5.17 2.79 - 5.17 4.95 - 9.19 4.95 - 9.19 11.13 - 20.67 11.13 - 20.67 44.53 - 82.69 44.53 - 82.69 Environmental, Inc.
2002-1 2002-1 2002-1 2002-1 2002-1 2002-1 2002-1 2002-1 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 28-05-02 28-05-02 28-05-02 28-05-02 28-05-02 28-05-02 28-05-02 28-05-02 Reader 1, #1 Reader 1, #1 Reader 1, #2 Reader 1, #2 Reader 1, #3 Reader 1, #3 Reader 1, #4 Reader 1, #4 4.84 4.84 8.60 8.60 19.34 19.34 77.36 77.36 4.44 +/- 0.16 4.37 +/- 0.20 9.08 +/- 0.14 8.76 +/- 0.16 22.14 +/- 0.27 24.03 +/- 0.30 92.77 +/- 0.58 85.25 +/- 0.37 3.39 - 6.29 3.39 - 6.29 6.02 - 11.18 6.02 - 11.18 13.54 - 25.14 13.54 - 25.14 54.15 - 100.57 54.15 - 100.57 Environmental. Inc.
2002-2 CaSO4: Dy Cards 13-12-02 Reader 1, 30 56.73 2002-2 CaSO4: Dy Cards 13-12-02 Reader 1,45a 25.21 a Precision of the distance (cm) measurement can significantly increase the on the table could account for the higher error.
71.61 +/- 1.79 39.71 - 73.75 33.49 +/- 1.38 17.65 - 32.77 error. The placement of the card holder 2002-2 2002-2 2002-2 2002-2 2002-2 2002-2 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 13-12-02 13-12-02 13-12-02 13-12-02 13-12-02 13-12-02 Reader 1,60 Reader 1,75 Reader 1, 90 Reader 1,120 Reader 1,135 Reader 1,150 14.18 9.08 6.30 3.55 2.80 2.28 17.37 +/- 1.24 10.65 +/- 1.02 6.37 +/- 0.54 4.60 +/- 0.41 2.51 +/- 0.23 2.22 +/- 0.28 9.93 6.36 4.41 2.49 1.96 1.60
- 18.43
- 11.80
- 8.19
- 4.62
-3.64
- 2.96 A2-1
-- page 56 of 119 --
TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1b Activity Limitsc SPW-1 1552 SPW-1 1552 SPMI-595 SPMI-595 SPMI-597 SPMI-597 SPMI-597 SPAP-594 SPW-599 SPMI-1446 SPW-1446 SPW-1446 SPMI-1448 SPVE-1444 SPAP-2078 SPW-2080 SPF-2082 SPF-2082 SPMI-2084 SPMI-2084 SPMI-2084 SPMI-2084 SPMI-2084 SPW-2115 SPW-2116 SPW-2116 SPW-2116 SPW-2116 SPW-2116 SPW-2019 SPW-2019 SPCH-3064 SPW-4682 SPAP-4685 W-71 702S W-71702S W-71702S SPVE-491 0 W-72302S W-80102S W-80102S W-80202S SPW-7188 SPW-7190 Water Water Milk Milk Milk Milk Milk Air Filter Water Milk Water Water Milk Vegetation Air Filter Water Fish Fish Milk Milk Milk Milk Milk Water Water Water Water Water Water Water Water Charcoal Water Air Filter Water Water Water Vegetation Water Water Water Water Water Water 1/7/2002 1/7/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/3112002 2/6/2002 2/19/2002 3/8/2002 3/8/2002 3/8/2002 3/8/2002 3/11/2002 4/8/2002 4/5/2002 4/5/2002 4/5/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 5/3/2002 5/3/2002 5/11/2002 7/17/2002 7/17/2002 7/17/2002 07/17/02 07/17/02 07/22/02 07/23/02 08/01/02 08/01/02 08102/02 10/25/02 10/25/02 Gr. Alpha Gr. Beta Cs-134 Cs-137 Co-60 Cs-134 Cs-1 37 Gr. Beta H-3 I-131 (G) 1-131 1-131(G) 1-131 1-131 (G)
Gr. Beta H-3 Cs-134 Cs-137 Cs-1 34 Cs-1 37 1-131 1-131 (G)
Sr-90 1-131 Co-60 Cs-134 Cs-137 1-131(G)
Sr-90 Gr. Alpha Gr. Beta 1-131 (G)
H-3 Gr. Beta Fe-55 H-3 Ni-63 Sr-90 Sr-9o Gr. Alpha Gr. Beta Tc-99 Fe-55 Ni-63 35.33 +/- 1.83 112.62 +/- 2.44 29.63 +/- 4.98 51.31 +/- 7.55 44.18 +/- 7.76 20.15 +/- 5.08 54.88 +/- 8.32 1.58 +/- 0.02 47607 +/- 595 87.84 +/- 11.47 82.98 +/- 1.20 92.75 +/- 12.87 88.00 +/- 1.13 0.39 +/- 0.04 1.43 +/- 0.01 49121 +/- 608 0.83 +/- 0.04 1.29 +/- 0.07 20.93 +/- 5.82 51.83 +/- 10.23 87.72 +/- 1.28 84.08 +/- 10.75 62.81 +/- 1.99 82.42 +/- 1.27 32.47 +/- 5.78 30.80 +/- 3.60 53.85 +/- 7.07 79.09 +/- 7.58 70.35 +/- 2.32 25.89 +/- 1.71 101.19 +/- 2.37 0.74 +/- 0.04 40856 +/- 548 1.58 +/- 0.02 10463.00 +/- 126.00 45779 +/- 583 17.02 +/- 1.50 10.22 +/- 0.80 21.43 +/- 0.97 41.25 +/- 4.58 113.66 +/- 5.30 16.39 +/- 0.72 20396 +/- 265 227.18 +/- 11.60 34.57 107.70 27.10 50.89 41.36 22.59 50.89 1.55 50189 85.20 85.20 85.20 85.20 0.42 1.55 46912 0.83 1.35 24.69 50.56 88.37 88.37 66.85 88.37 33.09 28.80 50.56 88.37 66.85 34.57 107.70 0.85 46179 1.55 12200.60 46179 17.10 9.04 26.55 34.45 107.70 14.13 22778 170.80 17.29 - 51.86 96.93 - 118.47 17.10 - 37.10 40.89 - 60.89 31.36 - 51.36 12.59 - 32.59 40.89 - 60.89 0.00 - 11.55 40151 +/-60227 75.20 - 95.20 68.16 - 102.24 75.20 - 95.20 68.16 - 102.24 0.25 - 0.58 0.00 - 11.55 37530 +/- 56294 0.50 - 1.16 0.81 - 1.89 14.69 - 34.69 40.56 - 60.56 70.70 - 106.04 78.37 - 98.37 53.48 - 80.22 70.70 - 106.04 23.09 - 43.09 18.80 - 38.80 40.56 - 60.56 78.37 - 98.37 53.48 - 80.22 17.29 - 51.86 96.93 - 118.47 0.51 - 1.18 36943 +/-55415 0.00 - 11.55 9760.48 - 14640.72 36943 +/- 55415 10.26 - 23.94 0.00 - 19.04 16.55 - 36.55 17.23 - 51.68 96.93 - 118.47 2.13 - 26.13 18222 -27334 102.48 - 239.12 A3-1
-- page 57 of 119 --
TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)
Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=lb Activity Limitsc SPW-7192 Water 10/25/02 H-3 96310 +/- 871 90963 72770 -109156 SPW-7194 Water 10/25/02 C-14 42938 +/- 167 49661 29796 - 69525 SPAP-7198 Air Filter 10/25/02 Gr. Beta 1.65 +/- 0.02 1.53 0.00 - 11.53 SPW-7335 Water 10/30/02 Co-60 39.67 +/- 7.38 37.05 27.05 - 47.05 SPW-7335 Water 10/30/02 Cs-1 34 33.09 +/- 5.96 34.11 24.11 - 44.11 SPW-7335 Water 10/30/02 Cs-1 37 46.80 +/- 10.39 49.90 39.90 - 59.90 SPMI-7336 Milk 10/30/02 Cs-134 34.40 +/- 4.99 34.11 24.11 -44.11 SPMI-7336 Milk 10/30/02 Cs-i 37 46.52 +/- 8.52 49.91 39.91 - 59.91 SPF-7340 Fish 10/30/02 Cs-1 34 0.66 +/- 0.03 0.68 0.41 - 0.95 SPF-7340 Fish 10/30/02 Cs-137 1.35 +/- 0.05 1.33 0.80 - 1.86 SPS-8102 Sediment 11/01/02 Sr-90 14.69 +/- 0.67 13.45 3.45 -23.45 a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).
b Results are based on single determinations.
c Control limits are based on Attachment A, Page A2 of this report.
NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.
A3-2
-- page 58 of 119 --
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results (4.66c)
Acceptance Type LLD Activityb Criteria (4.66 c)
SPW-1 1551 SPW-1 1551 SPAP-590 SPAP-590 SPAP-590 SPAP-590 SPMI-596 SPMI-596 SPMI-596 SPMI-596 SPW-598 SPW-598 SPW-598 SPW-600 SPMI-1447 SPVE-1443 SPW-1445 SPW-1445 SPW-1445 SPW-1445 SPW-1445 SPMI-1447 SPAP-2077 SPW-2079 SPF-2081 SPF-2081 SPMI-2083 SPMI-2083 SPMI-2083 SPMI-2083 SPW-2115 SPW-2115 SPW-2115 SPW-2115 SPW-2115 SPW-2115 SPW-2018 SPW-2018 SPch-3063 SPW-4683 W-71702 W-71702 W-71802B W-71802B water water Air Filter Air Filter Air Filter Air Filter Milk Milk Milk Milk water water water water Milk Vegetation water water water water water Milk Air Filter water Fish Fish Milk Milk Milk MWlkC water water water water water water water water Charcoal water water water water water 1/7/2002 1/7/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 3/7/2002 3/8/2002 3/8/2002 3/8/2002 3/8/2002 3/8/2002 3/8/2002 3/8/2002 4/8/2002 4/5/2002 4/5/2002 4/5/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/22/2002 4/22/2002 5/11/2002 7/17/2002 7/17/2002 7/17/2002 7/18/2002 7/18/2002 Gr. Alpha Gr. Beta Co-60 Cs-134 Cs-137 Gr. Beta Co-60 Cs-1 34 Cs-137 K-40 Co-60 Cs-134 Cs-1 37 H-3 1-131(G) 1-131 (G)
Co-60 Cs-134 Cs-137 1-131 1-131(G) 1-131 Gr. Beta H-3 Cs-1 34 Cs-1 37 Cs-134 Cs-1 37 1-131 Sr-90 Co-60 Cs-1 34 Cs-137 1-131 1-131 (G)
Sr-90 Gr. Alpha Gr. Beta 1-131 (G)
H-3 Fe-55 Ni-63 Gr. Alpha Gr. Beta 0.47 1.37 1.78 3.42 2.33 0.74 3.54 3.24 3.89 2.30 3.74 3.23 138.80 7.63 0.02 2.76 2.87 4.34 0.45 6.50 0.31 0.32 134.17 7.67 9.54 2.90 3.03 0.52 0.48 1.49 2.09 3.78 0.50 3.30 0.66 0.56 1.38 8.27 129.00 33.61 2.56 0.48 1.33 0.45 +/- 0.39 0.55 +/- 1.03
-0.096 +/- 0.38 1472.1 +/- 101.50
-96.5 +/- 63.40 0.17 +/- 0.31 0.15 +/- 0.22
-0.055 +/- 0.19 16.13 +/- 67.39
-0.38 +/- 0.34 1.29 +/- 0.36
-0.16 +/- 0.33 0.10 +/- 0.32
-0.24 +/- 0.38 3.19 +/- 1.03
-62.8 +/- 60.30
-1.72 +/- 15.63 0.71 +/- 1.37 0.31 +/- 0.36 0.9 +/- 0.95 1
3.2 100 100 100 3.2 10 10 10 0
10 10 10 200 20 20 10 10 10 0.5 20 0.5 3.2 200 100 100 10 10 0.5 1
10 10 10 0,5 20 I
1 3.2 9.6 200 1000 20 1
3.2 A4-1
-- page 59 of 119 --
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results (4.66a)
Acceptance Type LLD Activityb Criteria (4.66 a)
W-72302 water 7/23/2002 Sr-90 0.27 0.027 +/- 0.13 1
W-80202 water 8/2/2002 Tc-99 0.34
-0.051 +/- 0.16 10 SPW-7189 water 10/25/2002 Fe-55 978.21 21.77 +/- 595.33 1000 SPW-7191 water 10/25/2002 Ni-63 11.74 4.47 +/- 7.24 20 SPW-7193 water 10/25/2002 H-3 146.00
-92 +/- 65.00 200 SPAP-7199 Air Filter 10125/2002 Gr. Beta 0.00
-0.0024 +/- 0.00 3.2 SPMI-7333 Milk 10/30/2002 Cs-134 5.30 10 SPMI-7333 Milk 10/30/2002 Cs-137 4.80 10 SPW-7334 water 10/30/2002 Co-60 3.69 10 SPW-7334 water 10/30/2002 Cs-134 5.37 10 SPW-7334 water 10/30/2002 Cs-1 37 3.90 10 SPF-7339 Fish 10/30/2002 Cs-134 4.69 100 SPF-7339 Fish 10/30/2002 Cs-137 11.18 100 a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).
b The activity reported is the net activity result.
C Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCi/L) in milk is not unusual.
A4-2
-- page 60 of 119 --
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result CF-20, 21 CF-20, 21 CF-20, 21 CF-20, 21 AP-11804,11805 AP-11825,11826 AP-11846, 11847 WW-150, 151 Mi-124,125 W-172, 173 SW-11698, 11699 SW-11698, 11699 U-275, 276 LW-356, 357 LW-377, 378 SW-525, 526 SW-525, 526 DW-504, 505 Ml-649, 650 DW-697, 698 DW-927, 928 W-973, 974 W-1673, 1674 SWT-1395, 1396 Ml-1268,1269 Mi-1268, 1269 MI-1332,1333 MI-1332, 1333 Ml-1458,1459 DW-10100, 10101 DW-10111, 10112 Mi-1521, 1522 MI-1521, 1522 MI-1541, 1542 MI-1541, 1542 LW-1651, 1652 DW-10134, 10135 WW-1694, 1695 SO-1715, 1716 SO-1715, 1716 DW-10302, 10303 W-1758, 1759 W-1758, 1759 1/2/2002 1J2/2002 1/2/2002 1/2/2002 1/2/2002 1/2/2002 1/212002 1/7/2002 1/8/2002 1/8/2002 1/8/2002 1/8/2002 1110/2002 1/16/2002 1/16/2002 1/30/2002 1/30/2002 1/31/2002 2/5/2002 216/2002 2/8/2002 2/18/2002 2/25/2002 2/26/2002 2/27/2002 2/27/2002 3/5/2002 3/5/2002 3/6/2002 319/2002 3/9/2002 3/11/2002 3/11/2002 3/11/2002 3/11/2002 3/14/2002 3/16/2002 3/18/2002 3/19/2002 3119/2002 3/20/2002 3/25/2002 3/25/2002 Be-7 Gr. Beta K-40 Sr-90 Be-7 Be-7 Be-7 Gr. Beta K-40 H-3 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha K-40 Gr. Beta Sr-90 Fe-55 H-3 Gr. Beta K-40 Sr-90 K-40 Sr-90 K-40 Gr. Alpha Gr. Alpha K-40 Sr-90 K-40 Sr-90 Gr. Beta Gr. Alpha Gr. Beta Cs-137 Gr. Beta Gr. Alpha Gr. Alpha Gr. Beta 0.47 +/- 0.25 7.82 +/- 0.20 6.65 +/- 0.55 0.01 +/- 0.01 0.054 +/- 0.011 0.053 +/- 0.013 0.054 +/- 0.018 1.26 +/- 0.50 1332.30 +/- 158.90 153.00 +/- 68.00 2.51 +/- 1.36 7.68 +/- 1.33 1.40 +/- 1.00 3.47 +/- 0.65 2.75 +/- 0.68 0.56 +/- 0.35 2.29 +/- 0.41 2.30 +/- 1.70 1319.40 +/- 176.70 5.10 +/- 1.20 0.69 +/- 0.29 7.29 +/- 0.97 2640.00 +/- 155.00 2.96 +/- 0.59 1460.50 +/- 162.50 0.77 +/- 0.36 1503.00 +/- 164.00 1.35 +/- 0.38 1411.70 +/- 166.70 4.10 +/- 1.70 7.10 +/- 2.00 1270.80 +/- 103.30 1.69 +/- 0.46 1562.20 +/- 122.80 0.85 +/- 0.57 2.90 +/- 0.57 5.60 +/- 1.90 1.79 +/- 0.59 0.03 +/- 0.01 18.50 +/- 1.70 2.30 +/- 1.40 2.50 +/- 0.70 4.10 +/- 1.20 0.37 +/- 0.12 7.95 +/- 0.21 6.53 +/- 0.36 0.01 +/- 0.01 0.049 +/-0.019 0.043 +/- 0.013 0.048 +/- 0.016 1.04 +/- 0.46 1271.70 +/- 151.50 148.00 +/- 68.00 3.71 +/- 1.80 8.49 +/- 1.43 1.10 +/- 1.20 2.94 +/- 0.61 2.84 +/- 0.61 0.24 i 0.35 2.58 +/- 0.39 3.90 +/- 1.40 1210.80 +/- 118.20 4.70 +/- 1.20 0.71 +/- 0.29 6.86 +/- 0.94 2908.00 +/- 161.00 2.29 +/- 0.53 1573.00 +/- 168.00 0.95 +/- 0.40 1305.00 +/- 168.00 1.07 +/- 0.40 1390.00 +/- 172.30 1.80 +/- 1.60 8.30 +/- 2.30 1369.10 +/- 121.60 2.46 +/- 0.49 1529.30 +/- 126.10 1.48 +/- 0.43 2.57 +/- 0.56 5.40 +/- 1.60 1.53 +/- 0.50 0.02 +/- 0.01 19.10 +/- 1.70 3.30 +/- 1.60 2.30 +/- 0.60 2.50 +/- 1.10 0.42 +/- 0.14 7.89 +/- 0.14 6.59 +/- 0.33 0.01 +/- 0.00 0.052 +/- 0.011 0.048 +/- 0.009 0.051 +/- 0.012 1.15 +/- 0.34 1302.00 +/- 109.77 150.50 +/- 48.08 3.11 +/- 1.13 8.09 +/- 0.98 1.25 +/- 0.78 3.21 +/- 0.45 2.79 +/- 0.46 0.40 +/- 0.25 2.43 +/- 0.28 3.10 +/- 1.10 1265.10 +/- 106.29 4.90 +/- 0.85 0.70 +/- 0.21 7.08 i 0.68 2774.00 +/- 111.74 2.63 i 0.40 1516.75 +/- 116.87 0.86 +/- 0.27 1404.00 +/- 117.39 1.21 i0.28 1400.85 i 119.87 2.95 +/- 1.17 7.70 +/- 1.52 1319.95 +/- 79.78 2.07 +/- 0.34 1545.75 +/- 88.01 1.16 +/- 0.36 2.74 +/- 0.40 5.50 +/- 1.24 1.66 +/- 0.39 0.03 +/- 0.01 18.80 +/- 1.20 2.80 +/- 1.06 2.40 +/- 0.46 3.30 +/- 0.81 A5-1
-- page 61 of 119 --
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Ml-1926,1927 MI-1926, 1927 SWU-2010, 2011 DW-10376,10377 AP-2479, 2480 DW-10395, 10396 LW-2181, 2182 LW-2181, 2182 CW-2437, 2438 CW-2437, 2438 MI-1947,1948 AP-2458, 2459 DW-10409, 10410 MI-2052, 2053 MI-2052, 2053 AP-2711, 2712 W-938, 939 SS-2202, 2203 SS-2202, 2203 F-2307, 2308 DW-10476, 10477 W-2244, 2245 DW-10509, 10510 SW-2690, 2691 SO-2903, 2904 SO-2903, 2904 SO-2903, 2904 DW-10562,10563 DW-10578,10579 SO-2861, 2862 SO-2861, 2862 SL-2819, 2820 SL-2819, 2820 SL-2819, 2820 SL-2840, 2841 SL-2840, 2841 SL-2840, 2841 MI-2971, 2972 MI-2971, 2972 DW-10603,10604 SS-3037, 3038 Ml-3124, 3125 Ml-3208, 3209 LW-3250, 3251 3/26/2002 3/26/2002 3/26/2002 3/27/2002 3/28/2002 3/29/2002 3/31/2002 3/31/2002 3/31/2002 3/31/2002 4/1/2002 4/1/2002 4/1/2002 4/3/2002 4/3/2002 4/3/2002 4/9/2002 4/9/2002 4/9/2002 4/10/2002 4/12/2002 4/15/2002 4/17/2002 4/24/2002 4/24/2002 4/24/2002 4/24/2002 4/24/2002 4/29/2002 4/30/2002 4/30/2002 5/1/2002 5/1/2002 5/1/2002 5/1/2002 5/112002 5/1/2002 5/5/2002 5/5/2002 5/6/2002 5/9/2002 5/13/2002 5/14/2002 5/15/2002 K-40 Sr-90 Gr. Beta Gr. Beta Be-7 Gr. Alpha Gr. Beta H-3 Gr. Beta H-3 K-40 Be-7 Gr. Alpha K-40 Sr-90 Be-7 Ni-63 Gr. Beta K-40 K-40 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Be-7 Cs-137 K-40 Gr. Alpha Gr. Alpha Cs-1 37 K-40 Be-7 Gr. Beta K-40 Be-7 Gr. Beta K-40 K-40 Sr-90 Gr. Alpha K-40 K-40 K-40 Gr. Beta 1414.00 +/- 115.00 2.30 +/- 0.70 2.90 +/- 0.60 10.50 +/- 1.30 0.064 +/- 0.023 10.20 2.98 2694.43 1.09 6456.70 1421.40 0.077 39.30 1283.70 0.81 0.071 1.73 5.83 5.75 2.75 5.10 1.70 6.00 2.25 1.22 0.13 21.06 2.17 8.20 236.40 10191.00 805.70 5566.00 5524.00 1010.00 4399.00 2422.80 1338.90 0.83 6.30 11585.00 1329.50 1494.60 3.14
+/- 2.10
+/- 0.68
+/- 156.53
+/- 0.61
+/- 229.20
+/- 130.90
+/- 0.011
+/- 4.00
+/- 103.20
+/- 0.36
+/- 0.01
+/- 0.10
+/- 1.16
+/- 0.48
+/- 0.27
+/- 1.30
+/- 1.10
+/- 2.00
+/- 0.68
+/- 0.57
+/- 0.05
+/- 1.48
+/- 1.13
+/- 2.20
+/- 46.00
+/- 784.60
+/- 301.50
+/- 124.00
+/- 632.90
+/- 352.10
+/- 221.80
+/- 352.10
+/- 83.44
+/- 0.47
+/- 1.70
+/- 749.00
+/- 103.80
+/- 158.40
+/- 0.55 1316.00 2.40 2.20 10.10 0.068 14.60 1.99 2688.84 1.14 6292.80 1256.80 0.081 35.30 1434.80 0.75 0.07 1.82 5.52
+/- 128.00
+/- 0.70
+/- 0.50
+/- 1.50
+/- 0.014
+/- 2.40
+/- 0.70
+/- 156.40
+/- 0.58
+/- 226.52
+/- 104.20
+/- 0.010
+/- 3.60
+/- 147.90
+/-0.35
+/- 0.01
+/- 0.10
+/- 1.19 6.11 +/- 0.51 2.49 +/- 0.32 3.90 +/- 1.60 1.60 +/- 1.00 7.30 +/- 1.80 2.15 +/- 0.59 0.78 +/- 0.43 0.09 +/- 0.05 1365.00 +/- 86.04 2.35 +/- 0.49 2.55 +/- 0.39 10.30 +/- 0.99 0.066 +/- 0.013 12.40 +/- 1.59 2.48 +/- 0.49 2691.64 +/- 110.64 1.11 +/- 0.42 6374.75 +/- 161.12 1339.10 +/- 83.65 0.079 +/- 0.008 37.30 +/- 2.69 1359.25 +/- 90.17 0.78 +/- 0.25 0.07 +/- 0.01 1.78 +/- 0.07 5.67 +/- 0.83 5.93 +/- 0.35 2.62 +/- 0.21 4.50 +/- 1.03 1.65 +/- 0.74 6.65 +/- 1.35 2.20 +/- 0.45 1.00 +/- 0.36 0.11 +/- 0.04 20.48 +/- 0.94 2.71 +/- 0.96 7.80 +/- 1.49 218.55 +/- 34.94 10608.00 +/- 612.71 833.22 +/- 171.80 5462.50 +/- 86.98 5400.75 +/- 382.97 941.48 +/- 198.11 4496.00 +/- 177.04 2338.45 +/- 255.89 1342.35 +/- 65.47 1.24 +/- 0.33 5.90 +/- 1.17 11598.50 +/- 543.22 1351.25 +/- 74.68 1478.60 +/- 120.83 3.21 +/- 0.42 19.91 3.25 7.40 200.70 11025.00 860.73 5359.00 5277.50
+/- 1.16
+/- 1.54
+/-2.00
+/- 52.60
+/- 941.30
+/- 164.80
+/- 122.00
+/- 431.40 872.95 +/- 181.70 4593.00 +/- 276.00 2254.10 1345.80 1.65 5.50 11612.00 1373.00 1462.60 3.28
+/- 371.40
+/- 100.90
+/- 0.46
+/- 1.60
+/- 787.00
+/- 107.40
+/- 182.50
+/- 0.63 A5-2
-- page 62 of 119 --
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result CF-3292, 3293 MI-3376, 3377 MI-3418, 3419 SWT-3461, 3462 SO-3503, 3504 SO-3503, 3504 SO-3503, 3504 SL-3545, 3546 SL-3545, 3546 DW-10754, 10755 SW-3777, 3778 SW-3777, 3778 MI-3798, 3799 LW-3924, 3925 MI-3966, 3967 MI-3966, 3967 MI-3987, 3988 MI-4095, 4096 SWU-4221, 4222 LW-4179, 4180 G-4329, 4330 G-4329, 4330 G-4329, 4330 SL-4337, 4338 SL-4337, 4338 SL-4337, 4338 SL-4337, 4338 AP-4864, 4865 MI-4359, 4360 AP-4569, 4570 AP-4843, 4844 AP-4789, 4790 SWU-4810, 4811 MI-4548, 4549 DW-4737, 4738 MI-4632, 4633 MI-5054, 5055 G-5075, 5076 SWU-5124, 5125 G-5151, 5152 G-5151, 5152 MI-5103, 5104 LW-5434, 5435 MI-5215, 5216 5/20/2002 5/26/2002 5/28/2002 5/28/2002 5/29/2002 5/29/2002 5/29/2002 6/3/2002 6/3/2002 6/6/2002 6/11/2002 6/11/2002 6/11/2002 6/13/2002 6/18/2002 6/18/2002 6/19/2002 6/25/2002 6/25/2002 6/27/2002 7/1/2002 7/1/2002 7/1/2002 7/1/2002 7/1/2002 7/1/2002 7/1/2002 7/1/2002 7/2/2002 7/2/2002 7/2/2002 7/3/2002 7/3/2002 7/9/2002 7/12/2002 7/15/2002 7/30/2002 7/30/2002 7/30/2002 7/31/2002 7/31/2002 8/2/2002 8/5/2002 8/7/2002 K-40 K-40 K-40 Gr. Beta Cs-1 37 Gr. Beta K-40 Gr. Beta K-40 Sr-90 Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 Sr-90 Sr-90 K-40 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Be-7 Cs-1 37 Gr. Beta K-40 Be-7 K-40 Be-7 Be-7 Be-7 Gr. Beta K-40 1-131 K-40 K-40 Gr. Beta Gr. Beta Be-7 K-40 K-40 Gr. Beta K-40 1.33 +/- 0.99 1333.30 +/- 159.40 1423.70 +/- 121.30 2.65 +/- 0.54 0.17 +/- 0.04 27.72 +/- 2.26 20.24 +/- 1.19 4436.00 +/- 90.00 4684.20 +/- 734.40 0.50 +/- 0.30 4.42 +/- 1.50 7.57 +/- 1.22 1433.40 +/- 124.20 3.05 +/- 0.59 1245.20 +/- 109.20 2.38 +/- 0.51 0.98 +/- 0.35 1256.10 +/- 138.20 6.89 +/- 1.97 2.37 +/- 0.58 1394.80 +/- 538.40 8.10 +/- 0.27 7758.20 +/- 1100.00 1480.90 +/- 223.80 32.30 +/- 14.70 5262.40 +/- 522.10 2249.00 +/- 381.90 0.085 +/- 0.009 1390.10 +/- 168.30 0.068 +/- 0.016 0.077 +/- 0.016 0.080 +/- 0.013 2.40 +/- 0.84 1511.80 +/- 127.00 0.52 +/- 0.20 1198.40 +/- 114.10 1428.80 +/- 105.60 7.11 +/-0.07 1.75 +/- 0.84 1.82 +/- 0.30 5.13 +/- 0.66 1415.90 +/- 70.57 2.77 +/- 0.35 1361.10 +/- 111.90 1.14 +/- 0.91 1090.70 +/- 143.40 1443.30 +/- 164.30 3.28 +/- 0.60 0.18 +/- 0.05 25.45 +/- 2.03 20.54 +/- 1.24 4281.00 +/- 89.00 5242.50 +/- 884.50 0.60 +/- 0.30 2.97 +/- 1.40 6.83 +/- 1.16 1401.20 +/- 96.96 3.38 +/- 0.72 1340.20 +/- 121.90 2.63 +/- 0.52 0.97 +/- 0.35 1199.00 +/- 128.30 5.38 +/- 1.93 2.00 +/- 0.62 1098.10 +/- 437.40 8.00 8399.80 1726.40 50.97 5432.40 2989.90 0.085 1567.40 0.086 0.090 0.078
+/- 0.25
+/- 929.30
+/- 552.60
+/- 27.10
+/- 540.00
+/- 509.60
+/- 0.006
+/- 194.30
+/- 0.018
+/- 0.020
+/- 0.015 1.23 +/- 0.67 1212.00 +/- 107.21 1433.50 +/- 102.11 2.97 +/- 0.40 0.18 +/- 0.03 26.58 +/- 1.52 20.39 +/- 0.86 4358.50 +/- 63.29 4963.35 +/- 574.82 0.55 +/- 0.21 3.70 +/- 1.02 7.20 +/- 0.84 1417.30 +/- 78.78 3.21 +/- 0.46 1292.70 +/- 81.83 2.51 +/- 0.36 0.98 +/- 0.25 1227.55 +/- 94.29 6.13 +/- 1.38 2.19 +/- 0.42 1246.45 +/- 346.84 8.05 +/- 0.18 8079.00 +/- 720.00 1603.65 +/- 298.10 41.64 +/- 15.42 5347.40 +/- 375.56 2619.45 +/- 318.41 0.085 +/- 0.006 1478.75 +/- 128.53 0.077 +/- 0.012 0.084 +/- 0.013 0.079 +/- 0.010 2.43 +/- 0.61 1479.30 +/- 81.38 0.51 +/- 0.18 1284.85 +/- 93.00 1386.55 +/- 74.95 7.05 +/- 0.05 1.82 +/- 0.57 1.93 +/- 0.22 5.42 +/- 0.48 1419.85 +/- 73.61 2.52 +/- 0.25 1359.70 +/- 80.52 2.47 +/- 0.88 1446.80 +/- 101.80 0.49 +/- 0.29 1371.30 +/- 146.90 1344.30 +/- 106.40 6.99 +/- 0.07 1.90 +/- 0.78 2.05 +/- 0.32 5.72 +/- 0.70 1423.80 +/- 129.20 2.26 +/- 0.35 1358.30 +/- 115.80 A5-3
-- page 63 of 119 --
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result MI-5355, 5356 F-5413, 5414 F-5413, 5414 MI-5603, 5604 MI-5603, 5604 MI-5578, 5579 VE-5682, 5683 VE-5682, 5683 VE-5682, 5683 WW-6188, 6189 SL-5724, 5725 SL-5724, 5725 SL-5724, 5725 MI-5877, 5878 MI-6157, 6158 MI-6258, 6259 LW-6278, 6279 MI-6385, 6386 BS-6453, 6454 BS-6453, 6454 SO-6478, 6479 SO-6478, 6479 SO-6478, 6479 SO-6478, 6479 SO-6478, 6479 AP-6641, 6642 MI-6544, 6545 AP-6857, 6858 AP-6857, 6858 AP-6857, 6858 BS-6620, 6621 BS-6620, 6621 BS-6620, 6621 MI-6651, 6652 G-6760, 6761 G-6760, 6761 SWU-7054, 7055 U-7126, 7127 XW-7768, 7769 XW-7768, 7769 F-7148, 7149 BS-7337, 7338 BS-7337, 7338 BS-7337, 7338 SO-7407, 7408 SO-7407, 7408 SO-7407, 7408 8/13/2002 8/15/2002 8/15/2002 8/26/2002 8/26/2002 8/27/2002 8/28/2002 8/28/2002 8/28/2002 8/31/2002 9/3/2002 9/3/2002 9/3/2002 9/912002 9/19/2002 9/24/2002 9/3012002 10/1/2002 10/1/2002 10/1/2002 10/112002 10/1/2002 10/1/2002 10/1/2002 10/11/2002 10/1/2002 10/2/2002 10/3/2002 10/3/2002 10/3/2002 10/7/2002 10/712002 10/7/2002 10/8/2002 10/912002 10/9/2002 10/10/2002 10111/2002 10/14/2002 10/14/2002 10/15/2002 10/2312002 10/23/2002 10123/2002 10129/2002 10/29/2002 10/29/2002 K-40 Gr. Beta K-40 1-131 K-40 K-40 Be-7 Gr. Beta K-40 Gr. Beta Be-7 Cs-1 37 K-40 K-40 K-40 K-40 Gr. Beta K-40 Cs-1 37 K-40 Cs-1 37 Gr. Alpha Gr. Beta K-40 Sr-90 Be-7 K-40 Be-7 Be-7 Be-7 Co-60 Cs-1 37 K-40 K-40 Be-7 K-40 Gr. Beta Gr. Beta Cs-137 H-3.
K-40 Co-60 Cs-137 Gr. Beta Cs-1 37 Gr. Beta K-40 1405.00 +/- 165.80 2.37 +/- 0.10 1.47 +/- 0.32 0.64 +/- 0.34 1353.60 +/- 83.13 1301.50 +/- 161.70 0.29 +/- 0.10 3.79 +/- 0.08 3.06 +/- 0.29 2.70 +/- 0.57 0.92 +/- 0.19 0.05 +/- 0.02 2.09 +/- 0.31 1340.70 +/- 165.00 1372.10 +/- 115.10 1328.60 +/- 201.00 2.15 +/- 0.51 1297.10 +/- 168.90 0.43 +/- 0.03 16.50 +/- 0.51 0.074 +/- 0.016 8.01 +/- 4.36 30.41 +/- 4.07 19.82 +/- 0.53 0.087 +/- 0.017 0.070 +/- 0.016 1331.60 +/- 125.20 0.062 +/- 0.015 0.062 +/- 0.015 0.062 +/- 0.015 0.090 +/- 0.020 0.62 +/- 0.04 11.38 +/- 0.48 1565.50 +/- 141.00 2.17 +/- 0.49 6.24 +/- 1.00 3.09 +/- 0.57 2.61 +/- 1.24 2.25 +/- 0.25 2.63 +/- 0.10 2.57 +/- 0.28 0.083 +/- 0.025 0.082 +/- 0.019 12.54 +/- 2.34 0.14 +/- 0.03 16.73 +/- 2.21 12.05 +/- 0.61 1549.30 +/- 114.40 2.55 +/- 0.10 1.73 +/- 0.43 0.52 +/- 0.36 1261.40 +/- 117.80 1381.60 +/- 111.20 0.25 +/- 0.11 3.80 +/- 0.08 3.31 +/- 0.42 2.30 +/- 0.57 1.04 +/- 0.23 0.05 +/- 0.02 2.28 1168.50 1136.50 1312.60 1.70 1310.10 0.44 16.80 0.070 7.55 33.04 20.39 0.094 0.080 1326.50 0.071 0.071 0.071 0.11 0.63 10.78 1640.60 2.31 6.61 2.06 2.61
+/- 0.48
+/- 172.50
+/- 222.70
+/- 118.60
+/- 0.50
+/- 128.30
+/- 0.03
+/- 0.61
+/- 0.016
+/- 4.57
+/- 4.28
+/- 0.58
+/- 0.020
+/- 0.015
+/- 171.60
+/- 0.015
+/- 0.015
+/- 0.015
+/- 0.02
+/- 0.03
+/- 0.52
+/- 189.20
+/- 0.34
+/- 0.60
+/- 0.52
+/- 1.08 1477.15 +/- 100.72 2.46 +/- 0.07 1.60 +/- 0.27 0.58 +/- 0.25 1307.50 +/- 72.09 1341.55 +/- 98.12 0.27 +/- 0.08 3.79 +/- 0.06 3.18 +/- 0.25 2.50 +/- 0.41 0.98 +/- 0.15 0.05 +/- 0.01 2.19 +/- 0.29 1254.60 +/- 119.35 1254.30 +/- 125.34 1320.60 +/- 116.69 1.93 +/- 0.36 1303.60 +/- 106.05 0.44 +/- 0.02 16.65 +/- 0.40 0.072 +/- 0.011 7.78 +/- 3.16 31.73 +/- 2.95 20.10 +/- 0.39 0.091 +/-0.013 0.075 +/- 0.011 1329.05 +/- 106.21 0.066 +/- 0.010 0.066 +/- 0.010 0.066 +/- 0.010 0.10 +/- 0.01 0.62 +/- 0.02 11.08 +/- 0.35 1603.05 +/- 117.98 2.24 +/- 0.30 6.42 +/- 0.58 2.57 +/- 0.39 2.61 +/- 0.82 2.17 +/- 0.15 2.64 +/- 0.07 2.77 +/- 0.26 0.078 +/- 0.020 0.10 +/- 0.02 12.77 +/- 1.61 0.15 +/- 0.02 16.67 +/- 1.58 12.16 +/- 0.51 2.09 +/- 0.18 2.64 +/- 0.10 2.98 +/- 0.44 0.073 +/- 0.031 0.11 +/- 0.04 12.99 +/- 2.22 0.15 +/- 0.03 16.62 +/- 2.27 12.27 +/- 0.81 A5-4
-- page 64 of 119 --
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result MI-7428, 7429 10/29/2002 K-40 1542.60 +/- 213.00 1355.80 +/- 185.70 1449.20 +/- 141.29 pw-7621, 7622 10/30/2002 Gr. Beta 2.22 +/- 0.92 2.08 +/- 0.83 2.15 +/- 0.62 TD-7653,7654 10/31/2002 H-3 11122.00 +/- 387.00 11259.00 +/- 390.00 11190.50 +/- 274.71 SW-7569, 7570 11/5/2002 Gr. Beta 15.90 +/- 1.25 16.24 +/- 1.27 16.07 +/- 0.89 SW-7569, 7570 11/5/2002 K-40 14.79 +/- 1.48 14.79 +/- 1.48 14.79 +/- 1.05 SO-8010,8011 11/7/2002 Cs-137 0.11 +/-0.02 0.11 +/-0.03 0.11 +/-0.02 SO-8010,8011 11/7/2002 K-40 6.91 +/-0.54 7.21 +/-0.54 7.06 +/-0.38 VE-7747, 7748 11/11/2002 Gr. Beta 3.59 +/- 0.05 3.25 +/- 0.05 3.42 +/- 0:03 VE-7747, 7748 11/11/2002 K-40 3.17 +/- 0.36 3.26 +/- 0.46 3.22 +/- 0.29 MI-7789, 7790 11/13/2002 K-40 1319.30 +/- 167.60 1301.20 +/- 140.70 1310.25 +/- 109.41 DW-8082, 8083 11/29/2002 1-131 0.83 +/- 0.24 0.98 +/- 0.22 0.90 +/- 0.16 SW-8054, 8055 12/2/2002 Gr. Beta 2.60 +/- 0.46 2.21 +/- 0.39 2.41 +/- 0.30 SW-8054, 8055 12/2/2002 K-40 1.44 +/- 0.14 1.43 +/- 0.14 1.44 +/- 0.10 MI-8105, 8106 12/4/2002 K-40 1300.60 +/- 111.30 1315.40 +/- 108.90 1308.00 +/- 77.86 TD-8298, 8299 12/5/2002 H-3 355.00 +/- 94.00 469.00 +/- 99.00 412.00 +/- 68.26 MI-8396, 8397 12/17/2002 K-40 1409.20 +/- 117.30 1449.60 +/- 108.60 1429.40 +/- 79.93 SWT-8654, 8655 12/30/2002 Gr. Beta 1.63 +/- 0.50 1.40 +/- 0.47 1.51 +/- 0.34 AP-8783, 8784 12/31/2002 Be-7 0.044 +/- 0.009 0.042 +/- 0.008 0.043 +/- 0.006 Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).
A5-5
-- page 65 of 119 --
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limitsc STW-939 water 12/01/01 Am-241 1.25 +/- 0.0 1.19 +/- 0.0 0.83 - 1.6 STW-939 water 12/01/01 Co-57 138.9 +/- 0.5 143 +/- 14.3 100.1 - 185.9 STW-939 water 12/01/01 Co-60 139.1 +/- 0.5 141 +/- 14.1 98.7 - 183.3 STW-939 water 12/01/01 Cs-134 25.16 +/- 0.2 28.5 +/- 0.3 19.95 - 37.1 STW-939 water 12/01/01 Cs-1 37 279.96 +/- 0.9 286 +/- 28.6 200.2 -371.8 STW-939d water 12/01/01 Fe-55 19.68 +/- 23.2 9.2 +/-0.9 6.44 - 12.0 STW-939 water 12/01/01 Mn-54 253.64 +/-0.9 246 +/-0.2 172.2 -319.8 STW-939 water 12101/01 Ni-63 65.88 +/- 1.9 88.3 +/- 8.8 61.81 - 114.8 STW-939e water 12/01/01 Pu-238 0.060 i 0.01 0.0 +/- 0.0 STW-939 water 12/01/01 Pu-239/40 2.79 i 0.0 2.99 +/- 0.3 2.09 -3.9 STW-939 water 12/01/01 Sr-90 4.88 +/- 0.3 4.8 +/- 0.5 3.36 - 6.2 STW-939 water 12/01/01 U-233/4 0.89 +/- 0.0 0.98 +/- 0.1 0.69 - 1.3 STW-939 water 12/01/01 U-238 6.75 +/- 0.0 7.8 +/- 0.8 5.46 - 10.1 STW-939 water 12/01/01 Zn-65 70.6 +/- 1.1 67.3 +/- 6.7 47.11 - 87.5 STSO-955 soil 10/16/02 Am-241 40.54 +/- 2.7 43.5 +/- 4.4 30.45 - 56.6 STSO-955 soil 10/16/02 Co-57 210.58 +/-2.0 246 +/- 24.6 172.2 -319.8 STSO-955 soil 10/16/02 Co-60 84.38 +/- 0.9 87.5 +/- 8.8 61.25 - 113.8 STSO-955 soil 10/16/02 Cs-134 692.6 +/-2.1 862 +/- 86.0 603.4 - 1120.6 STSO-955 soil 10116/02 Cs-137 96.98 +/- 1.7 111 +/- 11.1 77.7-144.3 STSO-955 soil 10/16/02 Fe-55 1714.6 +/- 299.6 1870 +/- 187.0 1309 -2431.0 STSO-955 soil 10/16/02 Mn-54 509.74 +/- 3.4 546 +/- 54.6 382.2 -709.8 STSO-955 soil 10/16/02 Ni-63 890.6 +/- 22.4 1180 +/- 118.0 826 - 1534.0 STSO-955 soil 10/16/02 Pu-238 34.04 +/- 6.0 33.3 +/- 3.3 23.31 -43.3 STSO-955 soil 10/16/02 Pu-239/40 68.7 +/- 3.7 72.9 +/- 7.3 51.03 - 94.8 STSO-955e soil 10/16/02 Sr-90 1.5 +/-3.0 0.0 +/- 0.0 STSO-955 soil 10/16/02 U-233/4 166.33 +/- 3.8 229 +/- 22.9 160.3 -297.7 STSO-955 soil 10/16/02 U-238 169.76 +/- 3.8 220 +/- 22.0 154 -286.0 STSO-955 soil 10/16/02 Zn-65 783.59 +/- 6.4 809 +/- 80.9 566.3 - 1051.7 a Results obtained by Environmental, Inc. Midwest Laboratory as.a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b All results are in Bq/kg or Bq/L as requested by the Department of Energy.
c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.
d Known activity below the laboratory LLD. The sample was recounted for 2000 minutes; result: 11.52 +/- 5.55 Bq /L e Included in the testing series as a "false positive". No activity expected.
A6-1
-- page66of119--
TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)
Concentrationa EML Control Lab Code Type Date Analysis Laboratory results Resultb Limitsc STW-945 Water 03/01/02 Am-241 1.68 +/- 0.14 1.47 0.79 - 1.41 STW-945 Water 03/01/02 Co-60 349.20 +/- 2.60 347.33 0.80 - 1.20 STW-945 Water 03/01/02 Cs-134 3.40 +/- 0.60 3.36 0.80 - 1.30 STW-945 Water 03/01/02 Cs-137 57.20 +/- 1.70 56.07 0.80 - 1.22 STW-945 Water 03/01/02 Pu-238 0.45 +/- 0.11 0.49 0.74 - 1.20 STW-945 Water 03/01/02 Pu-239/40 4.47 +/- 0.28 4.22 0.79 - 1.20 STW-945 Water 03/01/02 Sr-90 7.40 +/- 1.30 7.58 0.69 - 1.34 STW-945 Water 03/01/02 Uranium 3.27 +/- 0.43 2.84 0.75 - 1.33 STW-946 Water 03/01/02 Gr. Alpha 265.40 +/- 7.70 375.00 0.58 - 1.29 STW-946 Water 03/01/02 Gr. Beta 930.60 +/- 12.00 1030.00 0.61 - 1.43 STW-946 Water 03101/02 H-3 226.30 +/- 32.70 283.70 0.78 - 2.45 STSO-947 Soil 03/01/02 Ac-228 55.00 +/- 5.50 51.17 0.80 - 1.38 STSO-947 Soil 03101/02 Am-241 8.30 +/- 3.30 10.93 0.65 - 2.28 STSO-947 Soil 03/01/02 Bi-212 49.20 +/- 12.40 53.43 0.50 - 1.34 STSO-947 Soil 03/01/02 Bi-214 46.60 +/- 3.10 53.93 0.78 - 1.42 STSO-947 Soil 03/01/02 Cs-137 1401.60 +/- 9.10 1326.67 0.80 - 1.25 STSO-947 Soil 03/01/02 K-40 613.10 +/- 28.10 621.67 0.80 - 1.32 STSO-947 Soil 03/01/02 Pb-212 51.60 +/- 2.60 51.10 0.78 - 1.32 STSO-947 Soil 03/01/02 Pb-214 52.00 +/- 3.60 54.37 0.76 - 1.46 STSO-947 Soil 03/01/02 Pu-239/40 14.70 +/- 3.50 19.10 0.71 - 1.30 STSO-947 Soil 03/01/02 Sr-90 52.10 +/- 6.30 53.76 0.67 -2.90 STSO-947 Soil 03/01/02 Th-234 122.40 +/- 6.30 89.30 0.63 -2.35 STSO-947 Soil 03/01/02 Uranium 143.40 +/- 9.40 194.77 0.71 - 1.32 STVE-948 Vegetation 03/01/02 Am-241 3.10 +/- 2.20 2.23 0.73 - 2.02 STVE-948 Vegetation 03/01/02 Cm-244 0.90 +/- 0.80 1.32 0.61 - 1.59 STVE-948 Vegetation 03/01/02 Co-60 13.50 +/- 2.10 11.23 0.80 - 1.44 STVE-948 Vegetation 03/01/02 Cs-137 350.40 +/- 6.30 313.67 0.80 - 1.31 STVE-948 Vegetation 03/01/02 K-40 940.80 +/- 45.60 864.33 0.79 - 1.39 STVE-948d Vegetation 03101/02 Pu-239/40 16.90 +/- 0.70 3.54 0.69 - 1.31 STVE-948 Vegetation 03/01/02 Sr-90 543.40 +/- 24.90 586.28 0.55 - 1.21 STAP-949 Air Filter 03/01/02 Am-241 0.09 +/- 0.05 0.09 0.70 - 2.34 STAP-949 Air Filter 03/01/02 Co-60 30.10 +/- 0.30 30.52 0.80 - 1.26 STAP-949 Air Filter 03/01/02 Cs-137 29.90 +/- 0.30 28.23 0.80 - 1.32 STAP-949 Air Filter 03/01/02 Mn-54 40.40 +/- 0.40 38.53 0.80 - 1.35 STAP-949 Air Filter 03/01/02 Pu-238 0.05 +/- 0.02 0.06 0.67 - 1.33 STAP-949 Air Filter 03/01/02 Pu-239/40 0.15 +/- 0.02 0.19 0.73 - 1.26 STAP-949 Air Filter 03/01/02 Sr-90 3.40 +/- 0.40 4.83 0.53 - 1.84 STAP-949 Air Filter 03/01/02 Uranium 0.80 +/- 0.20 0.61 0.79 - 2.10 STAP-950 Air Filter 03/01/02 Gr. Alpha 0.43 +/- 0.04 0.53 0.73 - 1.43 STAP-950 Air Filter 03101/02 Gr. Beta 1.34 +/- 0.05 1.30 0.76 - 1.36 STW-959 Water 09/01/02 Am-241 3.00 +/- 0.10 3.04 0.79 - 1.41 STW-959 Water 09/01/02 Co-60 258.40 +/- 2.30 268.67 0.80 - 1.20 STW-959 Water 09/01/02 Cs-134 50.80 +/- 3.30 60.20 0.80 - 1.30 STW-959 Water 09/01102 Cs-137 80.10 +/- 0.30 81.43 0.80 - 1.22 STW-959 Water 09/01/02 Cs-137 80.10 +/- 0.30 81.43 0.80 - 1.22 STW-959 Water 09/01/02 Am-241 3.00 +/- 0.10 3.04 0.79 - 1.41 A7-1
-- page 67 of 119 --
TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)a.
Concentrationb EML Control Lab Code Type Date Analysis Laboratory results Resultc Limitsd STW-959 Water 09/01/02 Am-241 3.00 +/- 0.10 3.04 0.79 - 1.41 STW-959 Water 09/01/02 Co-60 258.40 +/- 2.30 268.67 0.80 - 1.20 STW-959 Water 09/01/02 Cs-134 50.80 +/- 3.30 60.20 0.80 - 1.30 STW-959 Water 09/01/02 Cs-137 80.10 +/-0.30 81.43 0.80 - 1.22 STW-959 Water 09/01/02 H-3 271.90 +/- 20.90 227.30 0.78 - 2.45 STW-959 Water 09/01/02 Pu-238 4.40 +/- 0.20 4.33 0.74 - 1.20 STW-959 Water 09/01/02 Pu-239/40 2.10 +/- 0.10 2.07 0.79 - 1.20 STW-959 Water 09/01/02 Sr-90 9.70 +/- 0.20 8.69 0.69 - 1.34 STW-959 Water 09/01/02 Uranium 5.60 +/- 0.10 6.84 0.75 - 1.33 STW-960 Water 09/01/02 Gr. Alpha 204.90 +/- 3.20 210.00 0.58 - 1.29 STW-960 Water 09/01/02 Gr. Beta 852.00 +/- 26.50 900.00 0.61 - 1.43 STSO-961 Soil 09/01/02 Ac-228 47.60 +/- 1.90 42.30 0.80 - 1.38 STSO-961 Soil 09/01/02 Am-241 7.80 +/- 1.40 6.77 0.65 - 2.28 STSO-961 Soil 09/01/02 Bi-212 45.60 +/- 1.70 45.93 0.50 - 1.34 STSO-961e Soil 09/01/02 Bi-214 48.80 +/- 4.90 33.63 0.78 - 1.42 STSO-961 Soil 09/01/02 Cs-I 37 819.60 +/- 16.60 829.33 0.80 - 1.25 STSO-961 Soil 09/01/02 K-40 705.30 +/- 31.40 637.67 0.80 - 1.32 STSO-961 Soil 09/01/02 Pb-212 48.60 +/- 3.40 43.43 0.78 - 1.32 STSO-961 Soil 09/01/02 Pb-214 51.10 +/- 5.10 35.20 0.76 - 1.46 STSO-961' Soil 09/01/02 Pu-239/40 20.20 +/- 0.80 12.90 0.71 - 1.30 STSO-961 Soil 09/01/02 Sr-90 38.50 +/- 0.10 41.16 0.67 -2.90 STSO-961 Soil 09/01/02 Uranium 58.90 +/- 0.70 87.21 0.71 - 1.32 STVE-962 Vegetation 09/01/02 Am-241 2.10 +/- 0.30 2.25 0.73 - 2.02 STVE-962 Vegetation 09/01/02 Cm-244 1.00 +/- 0.30 1.25 0.61 - 1.59 STVE-962 Vegetation 09/01/02 Co-60 11.80 +/- 1.50 9.66 0.80 - 1.44 STVE-962 Vegetation 09/01/02 Cs-137 340.30 +/- 16.80 300.67 0.80 - 1.31 STVE-962 Vegetation 09101/02 K-40 1646.00 +/- 74.40 1480.00 0.79 - 1.39 STVE-962 Vegetation 09/01/02 Pu-239/40 3.00 +/- 0.30 3.43 0.69 - 1.31 STVE-962 Vegetation 09/01/02 Sr-90 345.60 +/- 97.80 476.26 0.55 - 1.21 STAP-9639 Air Filter 09/01/02 Am-241 0.20 +/- 0.01 0.19 0.70 - 2.34 STAP-963 Air Filter 09/01/02 Co-60 24.90 +/- 0.60 23.00 0.80 - 1.26 STAP-963 Air Filter 09/01/02 Cs-137 38.00 +/- 1.30 32.50 0.80 - 1.32 STAP-963 Air Filter 09/01/02 Mn-54 60.80 +/- 1.90 52.20 0.80 - 1.35 STAP-9639 Air Filter 09/01/02 Pu-238 0.11 +/- 0.02 0.12 0.67 - 1.33 STAP-963 9 Air Filter 09/01/02 Pu-239/40 0.21 +/- 0.01 0.21 0.73 - 1.26 STAP-963 Air Filter 09/01/02 Sr-90 5.20 +/- 0.20 5.56 0.53 - 1.84 STAP-9639 Air Filter 09/01/02 Uranium 0.41 +/- 0.04 0.47 0.79 -2.10 STAP-964 Air Filter 09/01/02 Gr. Alpha 0.40 +/- 0.10 0.29 0.73 - 1.43 STAP-964 Air Filter 09/01/02 Gr. Beta 0.80 +/- 0.10 0.87 0.76 - 1.36 a Results are reported in Bq/L with the following exceptions: Air Filters (Bq/Filter), Soil and Vegetation (Bq/kg).
b The EML result listed is the mean of replicate determinations for each nuclide +/- the standard error of the mean.
' Control limits are reported by EML as the ratio of Reported Value I EML value.
d An error was found in the conversion from pCi/g to Bqlg. Corrected result: 2.84 +/- 0.59 Bq/g.
e Naturally-occurring radium daughters are present in the shield background, and a probable cause of the higher bias seen for isotopes of lead and bismuth.
' Reporting error.The average result of the triplicate analyses was 14.1+/- 5.7 Bqlkg.
9 STAP-963, Calculations for the transuranics analyses (Am-241, Uranium, Pu-238, -239/40) were not converted to Bq/total filter.
The data listed is the result of recalculation.
A7-2
-- page 68 of 119 --
APPENDIX B REMP ANNUAL
SUMMARY
-- page 69 of 119 --
TABLE B-1 SAMPLING AND ANALYSIS FREQUENCY
SUMMARY
Number Number Number Sample of Collection of Type of Analysis of Type Sampling Frequency Samples Analysis Frequency Samples l
Locations Collected Analyzed*
Gross Weekly 520 Air Beta Particulate 10 Weekly 52 Gamma Quarterly 40 Isotopic Com posite Air Iodine 10 Weekly 520
[Iodine..
Weekly 520 Radiation 54 (continuous) 216 Exposure Quarterly 216 (TLD)
_____(otnos Gamma Monthly 12 Isotopic Surface Water 1
Monthly 12 Tritium Quarterly 4
(Grab)
Composite Gross Monthly 69 Gamma Monthly 12 Isotopic Gross Monthly 69 Surface Beta Water 1Mnhy1 (Effluent 1
Monthly 12 Gross Monthly 6j Composite)
Alpha Tritium Quarterly 4
Composite Iodine.3' Monthly 12 Number of samples analyzed does not include duplicate analysis, recounts, or reanalysis.
g Analysis for Gross Beta are not required REMP Samples and were suspended in July 2002.
Analysis for Gross Alpha are not required REMP Samples and were suspended in July 2002.
-- page 70 of 119 --
TABLE B-1 (continued)
Number Number Number Sample of Collection of Type of Analysis of Type Sampling Frequency Samples Analysis Frequency Samples lll___Locations Collected
__ll_l_Analyzed*
Gamma Monthly 24 Isotopic Surface Gross Beta Monthly 129 MonthiyMonhly22 (Upstream 2
Monthly 24 Gross Monthly Composite)
Alpha 12' Quarterly Tritium Composite 8
Iodine131 Quarterly 6'
Gross Quarterly 6'
Alpha Well Water 2h Quarterly 12 Gross Beta Quarterly Gamma Quarterly 12 Isotopic Tritium Quarterly 12 Gross Monthly 6
l Alpha l r..k llglGross Beta Monthly 12 Dienking 1
Monthly 12 Gamma Monthly 12 Isotopic Tritium Quarterly 4
l__l__l__l_______Composite Number of samples analyzed does not include duplicate analysis, recounts, or reanalysis.
g Analysis for Gross Beta are not required REMP Samples and were suspended in July 2002.
h Samples collected at CL-12 are taken prior to water treatment and after water treatment.
i Analysis for Iodine.31 is not a required REMP Sample and was suspended in July 2002.
j Analysis for Gross Alpha is not a required REMP Sample and was suspended in July 2002.
-- page 71 of 119 --
TABLE B-1 (continued)
Number Number Number Sample of Collection of Type of Analysis of Type Sampling Frequency Samples Analysis Frequency Samples lll Locations
___l Collected ll
_l_l Analyzed*
Gross Semi-2 Alpha Annually Gross Semi-2 Shoreline 1
Semi-Beta Annually Sediment Annually 2Gamma Semi-2 Isotopic Annually Sr90 Semi-2 Annually Monthly Gamma Gas4Semi-56 Isotopic Monthly 5
Gkrass 4
Mon56yk(including Semi-Monthly M o nth____
i131)
Gross Monthly 40 Monthly Beta Vegetables 4
(during 40 Gamma Monthly 40 growing Isotopic season)
(including i1131 Fish 2
Semi-1 16 Gamma Semi-l 16
_j Annually j_
__I Isotopic [
Annually Gamma Monthly!/
19 Isotopic Semi-Monthly Monthly /
Iodine131 Monthly /
19 Milk 1
Semi-19 Sedne Mi-Monthly Month lyk Sm-otl Sr90 Monthly /
o10 l __
l_
I_
I_
l_
lSemi-M onthly l
_l Number of samples analyzed does not include duplicate analysis, recounts, or reanalysis.
k Samples are collected Monthly from November through April (as delineated within the Station ODCM) and Semi-Monthly May through October.
I Analysis for Strontium90 is not a required REMP Sample and was suspended in July 2002.
-- page 72 of 119 --
TABLE B-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Name of Facility: Clinton Power Station Location of Facility: DeWitt, Illinois Reporting Period:
(county, state)
Docket No. 50-461 01 January - 31 December 2002 Medium or Type of All Location Control Pathway Analysis Indicator with Highest Locations:
Sampled Locations:
Annual Total Lower Mean Mean (f)
Number of (Unit of Number Limit of Mean (f)
Non-routine Measurement)
Performed Detection (Range)
Name (Range)
Reported (LLD)
Distance -
Measurements Direction Mean (f) -
(Range) 21.3 CL-57 20.8 Direct Gamma (150/150) 4.6 miles S (12/12)
Radiation dose 0
(mRem/qtr) 216 (17.7 -
(19.8 35.)
(19.6 -
23.6)
- 1.
58 21.9)
Gross 0.025 CL-8 0.026 0
Beta (468/468) 2.2 miles E (52/52)
(.015 -
Air 520
.035)
.026 (52/52)
(0.018 -
ala
(.017 -.033) 0.034)
Particulates Gamma (pCi/iM 3)
Spec 40 cs134 0.05
<0.0009 LLD 0
cS137 0.06
<0.0011 LLD 0
Air Iodine l
1131 0.07
<MDA LLD 0
(pCi/M 3 )
520 Note: Column explanations are at the end of Table B-2.
-- page 73 of 119 --
TABLE B-2 (continued)
Medium or Type of Lower All Location Control Number of Pathway Analysis Limit of Indicator with Highest Locations:
Non-routine Sampled Detection Locations:
Annual Reported Total (LLD)
Mean Mean (f) -
Measurements (Unit of Number Mean (f)
Measurement)
Performed (Range)
Name (Range)
Distance -
Direction Mean (f) -
l __
l (Range) ll_
l Gross Beta 4
2.6 (0/6)
CL-13 3.6 NA 0
6 (2.2 - 3.1) miles SW 2.6 (0/6)
(2.2 - 3.1)
Tritium 3,000
<169 NA 0
4 Gamma Surface Water S12ec Grab (pCi/1)
Mn54 15.0
<4.8 NA 0
Fe" 30.0
<11.6 NA 0
Co5 8
15.0
<5.6 NA 0
Co 6 0 15.0
<5.8 NA 0
Zn65 30.0
<6.3 NA 0
Nb95 15.0
<7.1 NA 0
Zr95 30.0
<12.8 NA 0
Cs134 15.0
<5.0 NA 0
Cs137 18.0
<7.1 NA 0
Ba140 60.0
<47.1 NA 0
La140 15.0
<9.5 NA 0
Note: Column explanations are at the end of Table B-2.
-- page 74 of 119 --
TABLE B-2 (continued)
Medium or Type of Lower All Location Control Number of Pathway Analysis Limit of Indicator with Highest Locations:
Non-routine Sampled
-Detection Locations:
Annual Reported Total (LLD)
Mean Mean (f) -
Measurements (Unit of Number Mean (f)
Measurement)
Performed (Range)
Name (Range)
Distance -
Direction Mean (f) -
l__
l__
l__
l_ (Range) l l
_l Gross Beta 4
2.8 (2/18)
CL-90 0.4 NA 0
18 (1.4 - 9.3)
Miles ESE 4.1 (2/6)
(1.8 -9.3)
Tritium 3,000
<169 NA 0
12 1131 15.0
<0.5 NA 0
12 Surface Water Composite Gamma (pCi/l)
Spec 36 Mn54 15.0
<5.2 NA 0
Fe59 30.0
<10.6 NA 0
Co5 8 15.0
<6.0 NA 0
Co 6
0 15.0
<6.1 NA 0
Zn65 30.0
<9.9 NA 0
Nb95 15.0
<6.9 NA 0
Zr95 30.0
<12.6 NA 0
Cs134 15.0
<6.2 NA 0
Cs13 7 18.0
<6.0 NA 0
Ba140 60.0
<46.9 NA 0
La140 15.0
<13.0 NA 0
Note: Column explanations are at the end of Table B-2.
-- page 75 of 119 --
TABLE B-2 (continued)
Medium or Type of Lower All Location Control Number of Pathway Analysis Limit of Indicator with Highest Locations:
Non-routine Sampled
-Detection Locations:
Annual Reported Total (LLD)
Mean Mean (f) -
Measurements (Unit of Number Mean (f)
Measurement)
Performed (Range)
Name (Range)
Distance -
Direction Mean (f) -
(Range)
Gross Beta 4
1.2 (0/12)
CL-14 NA 0
12 (0.8 - 2.0) 0 Miles 1.2 (0/12)
(0.8 - 2.0)
Tritium 3,000
<169 NA 0
4 Gamma Drinking Spec Water (pCi/I) 12 Mn54 l
15.0
<6.8 NA 0
Fe l
30.0
<8.2 NA 0
Co 58 15.0
<6.1 NA 0
060 15.0
<6.4 NA 0
Zn65 l
30.0
<5.8 NA 0
Nb9s 15.0
<6.2 NA 0
Zr95 30.0
<14.0 NA 0
Cs1 34 15.0
<6.8 NA 0
05137 18.0
<6.7 NA 0
Ba140 60.0
<44.6 NA 0
La140 15.0
<11.6 NA 0
Note: Column explanations are at the end of Table B-2.
-- page 76 of 119 --
TABLE B-2 (continued)
Medium or Type of Lower All Location Control Number of Pathway Analysis Limit of Indicator with Highest Locations:
Non-routine Sampled
-Detection Locations:
Annual Reported Total (LLD)
Mean Mean (f) -
Measurements (Unit of Number Mean (f)
Measurement)
Performed (Range)
Name (Range)
Distance -
Direction Mean (f) -
(Range)
Gross Beta 3.4 2.4 (0/6)
CL-12(U)
NA 0
6 (1.2 - 3.4) 1.6 Miles E 2.7 (0/2)
(2.0 - 3.4) 1131 15.0
<0.5 NA 0
6 Tritium 3,000
<162 NA 0
12 Well Water Speca (pCi/I)
Sp12 Mn54 15.0
<5.2 NA 0
Fe59 30.0
<13.4 NA 0
C 5 8 15.0
<5.4 NA 0
0060 15.0
<5.8 NA 0
Zn65 30.0
<5.1 NA 0
N b95 15.0
<4.5 NA 0
Zr95 30.0
<14.8 NA 0
Cs134 15.0
<4.4 NA 0
Cs137 18.0
<4.1 NA 0
Ba140 60.0
<53.1 NA 0
La140 15.0
<11.7 NA 0
(U) Untreated well water sample Note: Column explanations are at the end of Table B-2.
-- page 77 of 119 --
TABLE B-2 (continued)
Location with Highest Medium or Type of All Annual control Pathway Analysis Lower Indicator Mean Locations:
Number of Sampled Limit of Locations:
Name Non-routine Total Detection Distance-Mean (f) -
Reported (Unit of Number (LLD)
Mean (f)
Direction (Range)
Measurements Measurement)
Performed (Range) ---------
(Range)
Mean (f) -
(Range) 1131 1.0
<0.5 NA 0
19 Gamma Milk (pCi/l)
S1p9ec Cs'34 15.0
<7.8 NA 0
Cs'37 18.0
<7.8 NA 0
Ba'40 60.0
<31.5 NA 0
La140 15.0
<6.2 NA 0
Gamma Spec 16 Mn 54 130
<0.014 NA 0
Fish (pCi/g Fe59 260
<0.036 NA 0
wet)
Co58 130
<0.012 NA 0
Co6 0 130
<0.015 NA 0
Zn0 s 260
<0.033 NA 0
Cs'34 130
<0.019 NA 0
Cs'37 150
<0.014 NA 0
Gamma Shoreline Spec Sediments 2
(pCi/g dry)
Cs'34 150
<0.017 NA 0
Cs'37 180
<0.013 NA 0
Note: Column explanations at the end of Table B-2.
-- page 78 of 119 --
TABLE B-2 (continued)
Location with Highest Mduor Type of All Annual Control Pathway Lower Indicator Mean Locations:
Number of Sampled Limit of Locations:
Name Non-routine Total Detectionst Mean (f) -
Reported (Unit of Number (LLD)
Mean (f)
-Diro Measurements Measurement)
Performed (Range)
-(Range)
Mean (f) -
(Range)
Gamma Spec Vegetables 40 (pCi/g wet) 1131 60.0
<0.048 NA 0
CS 1 3 4 60.0
<0.025 NA 0
CS 1 3 7 80.0
<0.029 NA 0
Gamma Spec Grass (pCi/g 56 wet) i131 60.0 0.055 NA 0
cS134 60.0 0.044 NA 0
cS137 80.0 0.008 NA 0
Note: Column explanations at the end of Table B-2.
-- page 79 of 119 --
TABLE B-2 (continued)
Medium or Pathway Sampled (Unit of Measurement)
Type of Analysis Total Number Performed Lower Limit of Detection (LLD)
All Indicator Locations:
Mean (f)
(Range)
Location with Highest Annual Mean Name Distance -
Direction Mean (f) -
(Range)
Control Locations:
Mean (f) -
(Range)
Number of Non-routine Reported Measurements Column 1 Column 2 Column 3 Column 4 Column 5 Column 6 Column 7 TABLE EXPLANATIONS:
Column 1:
Column 2:
Column 3:
The Unit of Measurement describes all the numerical values for LLD, Mean and Range reported for a particular sample medium.
For example:
the Gross Beta LLD in AIR PARTICULATES is 0.010 pCi/M3. Abbreviations used are: pCi/m3 = pico-curie per cubic meter of sampled air; mRem/quarter = exposure measured for calendar quarter period; pCi/l = pico-curie per liter of sample; pCi/g = pico-curie per gram of sample.
The Types of Analyses are described as follows: Gamma Spec =
measurement of each radioisotope in a sample using Gamma Spectroscopy; Gross Betas and Gross Alphas = measurement of the radioactivity in a sample by measurement of emitted betas and alphas - no determination of individual radioisotopes is possible; Tritium = measurement of tritium (H3) in sample by liquid scintillation counting method; TLD = direct measurement of gamma exposure using thermoluminescent dosimeters.
Total number of analyses does not include duplicate analyses, recounts, or reanalysis. Only ODCM required LLDs and detectable activity (excluding some naturally occurring activity such as Bi2.. ) results are reported in this table. All sample results can be found in Appendix E of this report.
The ODCM required LLD is given when applicable. LLD reported is the highest of those reported for each of the analyses during the year; if all analyses reported positive values, no LLD is reported. It should be noted that - in most cases - the CPS REMP uses lower detection limits than required.
-- page 80 of 119 --
TABLE B-2 (continued)
Location with Type of Highest Medium or Analysis All Annual Mean Control Pathway Lower Indicator Locations:
Number of Sampled Limit of Locations:
Name Non-routine Total Detection -
-Distance Mean (f) -
Reported (Unit of Number (LLD)
Mean (f)
Direction -
-Measurements Measurement)
Performed (Range)
(Range)
Mean (f) -
(Range)
Column 1 Column 2 Column 3 l Column 4 l Column 5 l Column 6 Column 7 TABLE EXPLANATIONS (continued):
Column 4:
Column 5:
Column 6:
Column 7:
Samples taken at Indicator Locations during an operational Radiological Environmental Monitoring Program (REMP) reliably measure the quantities of any radioisotopes cycling through the pathways to man from a nuclear station. The reported values are the mean or average for the year of all samples of that type which had values greater than the LLD.
(f) is the fraction of all the samples taken at all indicator locations for the medium, which reported values greater than the LLD. Example: Seven (7) results greater than LLD out of fifteen (15) samples taken would be reported as 7/15. The Range is the values of the lowest to highest sample results greater than LLD reported at all the indictor locations for that medium.
The Mean, f-fraction and Range along with the name of the location, distance from the CPS gaseous effluent stack in miles, and the letter name corresponding to the compass sector in the direction of the sample location from the CPS HVAC gaseous effluent stack.
The location with 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 I or dispersion factors. Sample results are used as reference for the control location.
NRC Regulations [Branch Technical Position, Revision. 1, November 1979] include a table of radioisotope concentrations that, if exceeded by confirmed sample measurements, indicate that a Non-routine Reported Measurement exists. Such measurements require further investigation to validate the source.
-- page 81 of 119 --
APPENDIX C Glossary Activation - the process in which stable atoms become radioactive atoms by absorbing neutrons.
ALARA - acronym for "As Low As Reasonably Achievable" which applies to many facets of nuclear power (i.e., radiation exposure for personnel kept low, minimizes number / activity of effluent releases).
Alpha particle - a charged particle emitted from the nucleus of an atom having a mass and charge equal in magnitude to a helium nucleus which has two protons and two neutrons.
Atom - the smallest component of an element having all the properties of that element.
Comprised of protons, neutrons and electrons such that the number of protons determines the element.
Background radiation - source of radiation that mankind has no control over, such as cosmic (from the sun) and terrestrial (naturally occurring radioactive elements).
Beta particle - a charged particle equivalent to an electron if negative or a positron if positive, originating near the nucleus of an atom during radioactive decay or fission.
Control Location - a sample collection location considered to be far enough away from the Clinton Power Station so as not to be influenced by station operations.
Cosmic radiation - penetrating ionizing radiation originating from the sun and from outer space varying from altitude and latitude.
Curie (Ci) - the unit of radioactivity equal to 2.2 trillion disintegrations per minute.
Dead water - water that contains no tritium.
Dose - a quantity (total or accumulated) of ionizing radiation received.
Dose equivalent - a quantity used in radiation protection that expresses all radiations on a common scale for calculating the effective absorbed dose (the unit of dose equivalent is the rem).
Ecology - a branch of biology dealing with the relations between organisms and their environment.
Electromagnetic radiation - a traveling wave motion resulting from changing electric or magnetic fields.
Familiar sources of electromagnetic radiation range from x-rays (and gamma rays) of short wavelength, through the ultraviolet, visible and infrared regions, to radar and radio waves of relatively long wavelength. All electromagnetic radiation travels in a vacuum at the speed of light.
-- page 82 of 119 --
Element - one of 103 known chemical substances that cannot be broken down further without changing its chemical properties.
Environment - the aggregate of surrounding things, conditions, or influences.
Exposure - a measure of the ionization produced in air by x-ray or gamma radiation. Acute exposure is generally accepted to be a large exposure received over a short period of time. Chronic exposure is exposure received over a long period of time.
Fission - process by which an atomic nucleus splits into two smaller nuclei and releases neutrons and energy.
Fission products - the nuclei formed as part of the fissioning of an atomic nucleus.
Gamma rays - high energy, short wavelength electromagnetic radiation emitted from the nucleus.
Half-life - the time required for half of a given amount of a radionuclide to decay.
Indicator Location - a sample collection strategically placed to monitor dose rate or radioactive material that may be the result of Clinton Power Station operations.
Ionization - the process by which a neutral atom or molecule acquires a positive or negative charge.
Irradiation - exposure to radiation.
Lower Limit of Detection (LLD) - the smallest amount of sample activity that will give a net count for which there is a confidence at a predetermined level that the activity is actually present.
Microcurie (pCi) - one millionth of a curie and represents 2.2 million decays per minute.
Neutron - one of the three basic parts of an atom, which has no charge and is normally, found in the nucleus (center) of an atom.
Nucleus - the center of an atom containing protons and neutrons; determines the atomic weight and contributes to the net positive charge of an atom.
Nuclei (plural).
Nuclides - atoms which all have the same atomic number and mass number.
Periphyton - water plant life (i.e., algae).
Radiation - the process by which energy is emitted from a nucleus as particles (alpha, beta, and neutron) or waves (gamma).
Radionuclide - a radioactive species of an atom characterized by the constitution of its nucleus. The number of protons, number of neutrons, and energy content specify the nuclear constitution.
-- page 83 of 119 --
Rem - the unit of dose of any ionizing radiation that produces the same biological effects as a unit of absorbed dose of ordinary x-rays.
Acronym for Roentgen Equivalent Man.
Roentgen - a measure of ionization produced in air by x-ray or gamma radiation.
Site boundary - the site boundary is the line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
Statistics - the science that deals with the collection, classification, analysis and interpretation of numerical data by use of mathematical theories of probabilities.
Target tissue - any tissue or organ of the body in which radiation is absorbed.
Terrestrial radiation - source of radiation pertaining to the ground (Earth's crust).
X-rays - high energy, short wavelength electromagnetic radiation, emitted from the electron shells of an atom.
-- page 84 of 119 --
APPENDIX D Exceptions to the REMP During 2002 Data from the radiological analysis of environmental samples are routinely reviewed and evaluated by the ODCM Program Owner at the Clinton Power Station (CPS).
This data is checked for LLD compliance, anomalous values, quality control sample agreement, and any positive results which are inconsistent with expected results - or - which exceed any Offsite Dose Calculation Manual (ODCM) reporting levels. Reporting levels for radioactivity concentrations from environmental samples are required by the Station's ODCM and are listed in Table 3-A of this report.
If an inconsistent result occurs, an investigation is initiated which may consist of one, some, or all of the following actions:
Examine the collection data sheets for any indication of collection or delivery errors, tampering, vandalism, equipment calibration or any malfunction[s] as a result of electrical power failure[s], weather conditions, blown fuses, etc.
Perform statistical tests Examine previous data for trends Review other results from same sample media and different sample media Review control station data Review quality control or duplicate sample data Review CPS Radiological Effluent Release Reports If possible, recount and / or reanalyze the sample Collect additional follow-up samples as warranted During 2002, no investigations were performed as a result of reaching any ODCM reporting levels. All sample analysis required by the ODCM achieved the LLDs specified by the Station's ODCM (refer to Table 3-B of this report).
Sampling and analysis exceptions are listed in this appendix.
-- page 85 of 119 --
SAMPLING AND ANALYSIS EXCEPTIONS FOR 2002 The exceptions described below are those that are considered 'deviations' from the Radiological Environmental Monitoring Program as required by the Station's ODCM.
By definition, 'deviations' are permitted as delineated within NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and within Radiological Assessment Brach Technical Position, Revision 1, November 1979 which states.... "Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons"....
The below section addresses the reporting requirements found within Section 7.1 of the Station's ODCM.
[1]
21 June 2002
- As a result of an unusual and excessively wet spring [17.1 inches of rain vice a typical area average of 12.4 inches of rain], the planting and subsequent growing of our Broadleaf Vegetables had not yet matured for our first harvest occurring in June. As such, Broadleaf Vegetables were not sampled from ODCM Gardens CL-115 and CL-118.
[2]
24 September 2002 During the last 'end of the year' harvesting of Broadleaf Vegetables, of the three (3) different varieties that are required, we were unable to collect a minimum of two (2) pounds from this third type; lettuce. As previously illustrated in [1] above regarding the unusually wet spring that challenged our planting, any remaining lettuce was found to be either rotten or consumed by wildlife. As such, the remaining lettuce that was collected, did not satisfy the minimum two (2) pound criteria limitation from Gardens CL-115 and CL-118.
[3]
11 November 2002.
- Although our 3rd Quarter Environmental ODCM REMP TLDs were properly installed and removed after the required monitoring period for processing, our vendor reported
'abnormally high readings'.
Subsequent investigations revealed that prior to placing ODCM REMP TLDs out into the environment, Clinton's 3rd Quarter ODCM REMP, Occupational and Area TLDs were irradiated from an adjacent source during air transportation from California to Illinois. As such, Clinton's 3rd Quarter ODCM REMP TLD results were influenced from an external source -
in addition to their quarterly environmental exposure - thus resulting in inconsistent readings.
-- page 86 of 119 --
APPENDIX E CPS Radiological Environmental Monitoring Results During 2002
-- page 87 of 119 --
GROSS BETA ACTIVITY IN AIR PARTICULATES FOR 2002 (pCi/m3)
CL-2 DATE COLLECTED CL-1 CL-3 CL-4 CL-6 09-Jan-02 16-Jan-02 23-Jan-02 30-Jan-02 06-Feb-02 13-Feb-02 20-Feb-02 27-Feb-02 06-Mar-02 13-Mar-02 20-Mar-02 27-Mar-02 03-Apr-02 10-Apr-02 17-Apr-02 24-Apr-02 01-May-02 08-May-02 15-May-02 22-May-02 29-May-02 05-Jun-02 12-Jun-02 19-Jun-02 26-Jun-02 02-Jul-02 10-Jul-02 17-Jul-02 24-Jul-02 31-Jul-02 07-Aug-02 14-Aug-02 21-Aug-02 28-Aug-02 04-Sep-02 11 -Sep-02 18-Sep-02 25-Sep-02 02-Oct-02 09-Oct-02 16-Oct-02 23-Oct-02 30-Oct-02 06-Nov-02 13-Nov-02 20-Nov-02 26-Nov-02 04-Dec-02 11-Dec-02 18-Dec-02 26-Dec-02 02-Jan-03 0.040 +/- 0.005 0.030 +/- 0.004 0.029 +/- 0.004 0.028 +/- 0.004 0.027 +/- 0.004 0.026 +/- 0.003 0.019 +/- 0.004 0.018 +/- 0.003 0.029 +/- 0.004 0.025 +/- 0.004 0.015 +/- 0.004 0.024 +/- 0.003 0.023 +/- 0.004 0.023 +/- 0.004 0.022 +/- 0.003 0.013 +/- 0.003 0.015 +/- 0.003 0.019 +/- 0.003 0.016 +/- 0.003 0.014 +/- 0.003 0.018 +/- 0.003 0.027 +/- 0.003 0.015 +/- 0.003 0.019 +/- 0.004 0.026 +/- 0.003 0.019 +/- 0.004 0.029 +/- 0.003 0.030 +/- 0.004 0.024 +/- 0.003 0.019 +/- 0.004 0.023 +/- 0.004 0.020 +/- 0.003 0.016 +/- 0.003 0.022 +/- 0.004 0.028 +/- 0.004 0.033 +/- 0.004 0.032 +/- 0.004 0.017 +/- 0.003 0.041 +/- 0.005 0.023 +/- 0.003 0.034 +/- 0.004 0.026 +/- 0.003 0.026 +/- 0.004 0.028 +/- 0.004 0.042 +/- 0.004 0.021 +/- 0.004 0.018 +/- 0.004 0.024 +/- 0.003 0.037 +/- 0.005 0.039 +/- 0.004 0.020 +/- 0.003 0.036 +/- 0.004 0.044 +/- 0.005 0.026 +/- 0.004 0.032 +/- 0.004 0.037 +/- 0.003 0.028 +/- 0.004 0.027 +/- 0.003 0.020 +/- 0.004 0.018 +/- 0.003 0.031 +/- 0.004 0.030 +/- 0.004 0.015 +/- 0.004 0.027 +/- 0.004 0.018 +/- 0.003 0.025 +/- 0.004 0.026 +/- 0.004 0.017 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.003 0.023 +/- 0.004 0.012 +/- 0.003 0.017 +/- 0.003 0.022 +/- 0.003 0.018 +/- 0.004 0.020 +/- 0.004 0.024 +/- 0.003 0.025 +/- 0.004 0.029 +/- 0.003 0.028 +/- 0.004 0.022 +/- 0.003 0.022 +/- 0.004 0.026 +/- 0.004 0.023 +/- 0.003 0.015 +/- 0.003 0.024 + 0.004 0.026 +/- 0.004 0.038 + 0.004 0.031 + 0.004 0.013 +/- 0.003 0.041 +/- 0.005 0.022 +/- 0.003 0.033 +/- 0.004 0.025 +/- 0.003 0.026 + 0.004 0.035 +/- 0.004 0.042 +/- 0.004 0.023 + 0.004 0.016 + 0.004 0.025 +/- 0.003 0.037 +/- 0.005 0.041 +/- 0.004 0.025 +/- 0.004 0.039 +/- 0.004 0.040 +/- 0.004 0.021 +/- 0.004 0.034 +/- 0.004 0.034 +/- 0.004 0.026 +/- 0.003 0.028 +/- 0.004 0.020 +/- 0.004 0.016 +/- 0.003 0.026 +/- 0.004 0.027 +/- 0.004 0.013 +/- 0.004 0.022 +/- 0.003 0.019 +/- 0.004 0.023 +/- 0.004 0.023 +/- 0.004 0.020 +/- 0.003 0.017 +/- 0.003 0.020 +/- 0.003 0.017 +/- 0.003 0.014 +/- 0.003 0.017 +/- 0.003 0.026 +/- 0.003 0.017 +/- 0.004 0.017 +/- 0.004 0.023 +/- 0.003 0.023 +/- 0.004 0.033 +/- 0.003 0.034 +/- 0.004 0.025 +/- 0.003 0.022 +/- 0.004 0.027 +/- 0.004 0.025 +/- 0.003 0.014 +/- 0.003 0.027 +/- 0.004 0.027 +/- 0.004 0.035 +/- 0.004 0.026 +/- 0.004 0.018 +/- 0.003 0.044 +/- 0.005 0.025 +/- 0.004 0.039 +/- 0.004 0.027 +/- 0.003 0.021 +/- 0.004 0.034 +/- 0.004 0.050 +/- 0.004 0.023 +/- 0.004 0.020 +/- 0.004 0.027 +/- 0.003 0.036 +/- 0.005 0.040 +/- 0.004 0.025 +/- 0.004 0.037 +/- 0.004 0.044 +/- 0.005 0.027 +/- 0.004 0.030 +/- 0.004 0.035 +/- 0.004 0.025 +/- 0.004 0.028 +/- 0.003 0.015 +/- 0.003 0.018 +/- 0.003 0.027 +/- 0.004 0.031 +/- 0.004 0.014 +/- 0.004 0.025 +/- 0.004 0.020 +/- 0.003 0.023 +/- 0.004 0.026 +/- 0.004 0.018 +/- 0.003 0.015 +/- 0.003 0.020 +/- 0.003 0.015 +/- 0.003 0.013 +/- 0.003 0.016 +/- 0.003 0.026 +/- 0.003 0.014 +/- 0.003 0.018 +/- 0.003 0.028 +/- 0.004 0.025 +/- 0.004 0.030 +/- 0.003 0.024 +/- 0.004 0.021 +/- 0.003 0.023 +/- 0.004 0.026 +/- 0.004 0.022 +/- 0.003 0.017 +/- 0.003 0.020 +/- 0.004 0.024 +/- 0.004 0.032 +/- 0.004 0.026 +/- 0.004 0.016 +/- 0.003 0.034 +/- 0.004 0.023 +/- 0.003 0.030 +/- 0.004 0.024 +/- 0.003 0.023 +/- 0.004 0.033 +/- 0.004 0.049 +/- 0.005 0.022 +/- 0.004 0.019 +/- 0.004 0.024 +/- 0.003 0.035 +/- 0.004 0.042 +/- 0.004 0.019 +/- 0.003 0.033 +/- 0.004 0.042 +/- 0.005 0.026 +/- 0.004 0.029 +/- 0.004 0.030 +/- 0.004 0.026 +/- 0.003 0.023 +/- 0.003 0.019 +/- 0.004 0.018 +/- 0.003 0.028 +/- 0.004 0.030 +/- 0.004 0.015 +/- 0.004 0.025 +/- 0.004 0.021 +/- 0.004 0.023 +/- 0.004 0.022 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.003 0.013 +/- 0.003 0.017 +/- 0.003 0.024 +/- 0.004 0.015 +/- 0.003 0.015 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.004 0.032 +/- 0.003 0.030 +/- 0.004 0.025 +/- 0.003 0.025 +/- 0.004 0.029 +/- 0.004 0.023 +/- 0.003 0.015 +/- 0.003 0.024 +/- 0.004 0.026 +/- 0.004 0.037 +/- 0.004 0.035 +/- 0.004 0.017 +/- 0.003 0.041 +/- 0.005 0.023 +/- 0.003 0.033 +/- 0.004 0.026 +/- 0.003 0.026 +/- 0.004 0.032 +/- 0.004 0.045 +/- 0.004 0.022 +/- 0.004 0.017 +/- 0.004 0.025 +/- 0.003 0.033 +/- 0.004 0.037 +/- 0.004 0.022 +/- 0.003 0.035 +/- 0.004
-- page 88 of 119 --
GROSS BETA ACTIVITY IN AIR PARTICULATES FOR 2002 (continued)
DATE COLLECTED CL-7 CL-8 CL-1I CL-15 CL-94 09-Jan-02 16-Jan-02 23-Jan-02 30-Jan-02 06-Feb-02 13-Feb-02 20-Feb-02 27-Feb-02 06-Mar-02 13-Mar-02 20-Mar-02 27-Mar-02 03-Apr-02 10-Apr-02 17-Apr-02 24-Apr-02 01-May-02 08-May-02 15-May-02 22-May-02 29-May-02 05-Jun-02 12-Jun-02 19-Jun-02 26-Jun-02 02-Jul-02 10-Jul-02 17-Jul-02 24-Jul-02 31-Jul-02 07-Aug-02 14-Aug-02 21 -Aug-02 28-Aug-02 04-Sep-02 11-Sep-02 18-Sep-02 25-Sep-02 02-Oct-02 09-Oct-02 16-Oct-02 23-Oct-02 30-Oct-02 06-Nov-02 13-Nov-02 20-Nov-02 26-Nov-02 04-Dec-02 11-Dec-02 18-Dec-02 26-Dec-02 02-Jan-03 0.046 +/- 0.005 0.021 +/- 0.004 0.033 +/- 0.004 0.034 +/- 0.004 0.030 +/- 0.004 0.027 +/- 0.003 0.017 +/- 0.004 0.019 +/- 0.003 0.029 +/- 0.004 0.030 +/- 0.004 0.018 +/- 0.004 0.029 +/- 0.004 0.022 +/- 0.003 0.024 +/- 0.004 0.023 +/- 0.003 0.014 +/- 0.003 0.017 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.013 +/- 0.003 0.017 +/- 0.003 0.027 +/- 0.004 0.015 +/- 0.003 0.015 +/- 0.003 0.023 +/- 0.003 0.021 +/- 0.004 0.030 +/- 0.003 0.021 +/- 0.004 0.021 +/- 0.003 0.022 +/- 0.004 0.028 +/- 0.004 0.024 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.004 0.022 +/- 0.004 0.028 +/- 0.004 0.026 +/- 0.004 0.013 +/- 0.003 0.034 +/- 0.004 0.024 +/- 0.003 0.028 +/- 0.004 0.024 +/- 0.003 0.025 +/- 0.004 0.034 +/- 0.004 0.045 +/- 0.004 0.020 +/- 0.004 0.016 +/- 0.004 0.024 +/- 0.003 0.039 +/- 0.005 0.039 +/- 0.005 0.023 +/- 0.003 0.037 +/- 0.004 0.039 +/- 0.004 0.024 +/- 0.004 0.027 +/- 0.004 0.034 +/- 0.004 0.027 +/- 0.003 0.028 +/- 0.004 0.017 +/- 0.003 0.018 +/- 0.003 0.029 +/- 0.004 0.028 +/- 0.004 0.020 +/- 0.004 0.028 +/- 0.004 0M022 +/- 0.004 0.021 +/- 0.004 0.021 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 0.018 +/- 0.004 0.014 +/- 0.003 0.015 +/- 0.003 0.025 +/- 0.003 0.019 +/- 0.004 0.015 +/- 0.003 0.026 +/- 0.003 0.024 +/- 0.004 0.034 +/- 0.003 0.037 +/- 0.004 0.025 +/- 0.003 0.023 +/- 0.004 0.028 +/- 0.004 0.025 +/- 0.003 0.012 +/- 0.003 0.020 +/- 0.004 0.029 +/- 0.004 0.035 +/- 0.004 0.033 +/- 0.004 0.016 +/- 0.003 0.042 +/- 0.005 0.025 +/- 0.003 0.036 +/- 0.004 0.029 +/- 0.003 0.027 +/- 0.004 0.036 +/- 0.004 0.048 +/- 0.004 0.021 +/- 0.004 0.017 +/- 0.004 0.023 +/- 0.003 0.038 +/- 0.005 0.041 +/- 0.005 0.024 +/- 0.003 0.039 +/- 0.004 0.040 +/- 0.005 0.024 +/- 0.004 0.032 +/- 0.004 0.032 +/- 0.004 0.029 +/- 0.004 0.026 +/- 0.003 0.015 +/- 0.004 0.016 +/- 0.003 0.023 +/- 0.004 0.028 +/- 0.004 0.012 +/- 0.004 0.027 +/- 0.003 0.022 +/- 0.004 0.020 +/- 0.004 0.023 +/- 0.004 0.013 +/- 0.003 0.017 +/- 0.003 0.022 +/- 0.003 0.018 +/- 0.003 0.014 +/- 0.003 0.019 +/- 0.003 0.024 +/- 0.003 0.017 +/- 0.004 0.018 +/- 0.003 0.026 +/- 0.003 0.029 +/- 0.004 0.031 +/- 0.003 0.041 +/- 0.005 0.026 +/- 0.003 0.022 +/- 0.004 0.028 +/- 0.004 0.025 +/- 0.003 0.013 +/- 0.003 0.023 +/- 0.004 0.028 +/- 0.004 0.032 +/- 0.004 0.033 +/- 0.004 0.020 +/- 0.003 0.043 +/- 0.005 0.028 +/- 0.004 0.041 +/- 0.004 0.026 +/- 0.003 0.025 +/- 0.004 0.036 +/- 0.004 0.044 +/- 0.004 0.022 +/- 0.004 0.020 +/- 0.004 0.026 +/- 0.003 0.040 +/- 0.005 0.040 +/- 0.004 0.023 +/- 0.003 0.041 +/- 0.004 0.039 +/- 0.004 0.025 +/- 0.004 0.032 +/- 0.004 0.033 +/- 0.004 0.024 +/- 0.003 0.028 +/- 0.003 0.019 +/- 0.004 0.013 +/- 0.003 0.025 +/- 0.004 0.026 +/- 0.004 0.015 +/- 0.004 0.024 +/- 0.004 0.018 +/- 0.003 0.018 +/- 0.004 0.024 +/- 0.004 0.018 +/- 0.003 0.018 +/- 0.003 0.016 +/- 0.003 0.019 +/- 0.004 0.011 +/- 0.003 0.015 +/- 0.003 0.024 +/- 0.004 0.018 +/- 0.003 0.016 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.004 0.030 +/- 0.003 0.028 +/- 0.004 0.024 +/- 0.003 0.024 +/- 0.004 0.024 +/- 0.004 0.023 +/- 0.003 0.014 +/- 0.003 0.018 +/- 0.004 0.024 +/- 0.004 0.034 +/- 0.004 0.033 +/- 0.004 0.016 +/- 0.003 0.040 +/- 0.004 0.024 +/- 0.003 0.034 +/- 0.004 0.023 +/- 0.003 0.024 +/- 0.004 0.034 +/- 0.004 0.047 +/- 0.004 0.019 +/- 0.004 0.017 +/- 0.004 0.023 +/- 0.003 0.044 +/- 0.005 0.037 +/- 0.004 0.022 +/- 0.003 0.042 +/- 0.005 0.035 +/- 0.004 0.021 +/- 0.004 0.031 +/- 0.004 0.032 +/- 0.004 0.026 +/- 0.003 0.028 +/- 0.004 0.017 +/- 0.004 0.019 +/- 0.003 0.026 +/- 0.004 0.026 +/- 0.004 0.017 +/- 0.004 0.025 +/- 0.004 0.023 +/- 0.004 0.024 +/- 0.004 0.027 +/- 0.004 0.017 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.003 0.017 +/- 0.003 0.012 +/- 0.003 0.016 +/- 0.003 0.024 +/- 0.003 0.018 +/- 0.004 0.016 +/- 0.003 0.023 +/- 0.003 0.026 +/- 0.004 0.030 +/- 0.003 0.035 +/- 0.004 0.024 +/- 0.003 0.023 +/- 0.004 0.027 +/- 0.004 0.024 +/- 0.003 0.015 +/- 0.003 0.023 +/- 0.004 0.027 +/- 0.004 0.034 +/- 0.004 0.029 +/- 0.004 0.015 +/- 0.003 0.036 +/- 0.004 0.024 +/- 0.003 0.033 +/- 0.004 0.025 +/- 0.003 0.027 +/- 0.004 0.034 +/- 0.004 0.049 +/- 0.004 0.022 +/- 0.004 0.018 +/- 0.004 0.024 +/- 0.003 0.035 +/- 0.005 0.041 +/- 0.005 0.023 +/- 0.003 0.039 +/- 0.004
- Control Location, all other locations are Indicator Locations.
-- page 89 of 119 --
GAMMA ISOTOPIC ACTIVITY IN AIR PARTICULATES FOR 2002m (pCi/m 3 )
2ND QTR SITE ISOTOPE 1 ST QTR 3RD QTR 4TH QTR CL-I CL-2 Be7 K4 0 Ca6' N b95 Zr95 Ru10 3 Ru1 0 6 Cs134 cS137 Ce'4' Ce'44 Be7 K40 Co6 '
N b95 Zr95 Ru"03 Ru10 6 Cs'34 cS'37 Ce'4' Ce'44 0.067 +/- 0.017
< 0.0250
< 0.0010
< 0.0005
< 0.0011
< 0.0015
< 0.0050
< 0.0008
< 0.0006
< 0.0027
< 0.0038 0.081 +/- 0.016
< 0.0250
< 0.0009
< 0.0015
< 0.0020
< 0.0009
< 0.0027
< 0.0007
< 0.0005
< 0.0011
< 0.0067 0.070 +/- 0.020
< 0.0260
< 0.0012
< 0.0019
< 0.0009
< 0.0008
< 0.0053
< 0.0008
< 0.0009
< 0.0017
< 0.0024 0.064 +/- 0.015
< 0.0410
< 0.0013
< 0.0005
< 0.0017
< 0.0006
< 0.0062
< 0.0008
< 0.0008
< 0.0012
< 0.0036 0.081 +/- 0.016
< 0.0240
< 0.0007
< 0.0010
< 0.0023
< 0.0008
< 0.0061
< 0.0006
< 0.0006
< 0.0019
< 0.0041 0.066 +/- 0.017
< 0.0260
< 0.0007
< 0.0011
< 0.0015
< 0.0006
< 0.0045
< 0.0006
< 0.0006
< 0.0021
< 0.0038 0.053 +/- 0.011
< 0.0250
< 0.0005
< 0.0006
< 0.0009
< 0.0009
< 0.0040
< 0.0007
< 0.0004
< 0.0011
< 0.0043 0.053 +/- 0.020
< 0.0250
< 0.0005
< 0.0008
< 0.0017
< 0.0014
< 0.0055
< 0.0004
< 0.0004
< 0.0019
< 0.0064 CL-3 Be7 K 40 Co6 '
Zr95 Ru10 3 Ru'0 6 Cs'34 Cs' 37 Ce' 4' C e'44 0.071 +/- 0.015
< 0.0250
< 0.0008
< 0.0008
< 0.0022
< 0.0008
< 0.0039
< 0.0007
< 0.0005
< 0.0020
< 0.0056 0.091 +/- 0.019
< 0.0270
< 0.0013
< 0.0008
< 0.0019
< 0.0007
< 0.0097
< 0.0008
< 0.0007
< 0.0013
< 0.0039 0.072 +/- 0.019
< 0.0240
< 0.0007
< 0.0008
< 0.0022
< 0.0010
< 0.0045
< 0.0005
< 0.0003
< 0.0018
< 0.0045 0.058 +/- 0.018
< 0.0340
< 0.0005
< 0.0011
< 0.0019
< 0.0010
< 0.0071
< 0.0006
< 0.0003
< 0.0023
< 0.0048 m All 1'3' results were < 0.07 pCi/m3
-- page 90 of 119 --
GAMMA ISOTOPIC ACTIVITY IN AIR PARTICULATES FOR 2002m (continued)
SITE ISOTOPE 1ST QTR 2ND QTR 3RD QTR 4TH QTR CL-11 CL-15 Be7 K40 Coso N b95 Zr95 Ru'03 Ru 106 Cs 134 Cs'37 Ce141 Ce 144 Be7 K40 Nb9s Zr95 Ru 10 3 Ru1 06 Cs'34 Cs137 Ce141 Ce 144 0.084 +/- 0.019
- 0.0250
- 0.0008
- 0.0014
< 0.0009
< 0.0009
< 0.0049
- 0.0008
- 0.0008
- 0.0022
< 0.0035 0.064 +/- 0.018
- 0.0230
< 0.0005
- 0.0013
- 0.0016
- 0.0014
- 0.0046
- 0.0008
< 0.0007
- 0.0014
< 0.0053 0.075 +/- 0.016
< 0.0260
- 0.0013
< 0.0005
< 0.0009
< 0.0009
< 0.0080
- 0.0008
- 0.0006
< 0.0018
< 0.0062 0.062 +/- 0.017
< 0.0260
- 0.0013
< 0.0005
< 0.0009
< 0.0009
< 0.0053
< 0.0006
< 0.0005
- 0.0027
- 0.0024 0.068 +/- 0.021
- 0.0240
< 0.0008
< 0.0008
- 0.0019
< 0.0007
- 0.0032
< 0.0004
< 0.0005
- 0.0021
< 0.0042 0.074 +/- 0.018
< 0.0240
< 0.0007
- 0.0013
- 0.0015
< 0.0009
- 0.0072
< 0.0006
< 0.0005
- 0.0019
- 0.0048 0.047 +/- 0.014
- 0.0250
< 0.0005
< 0.0013
< 0.0008
< 0.0009
< 0.0045
< 0.0004
- 0.0011
- 0.0017
< 0.0045 0.045 +/- 0.015
< 0.0250
< 0.0005
< 0.0007
- 0.0008
- 0.0014
< 0.0057
< 0.0008
< 0.0005
< 0.0016
- 0.0029 CL-94 Be7 K40 Nb95 Zr95 Ru 10 3 Ru10 6 Cs134 Cs137 Ce141 Ce 144 0.037 +/- 0.015
< 0.0250
< 0.0009
< 0.0009
< 0.0031
< 0.0008
< 0.0038
< 0.0007
< 0.0003
< 0.0015
< 0.0041 0.081 +/- 0.020
< 0.0260
< 0.0013
< 0.0008
< 0.0018
< 0.0009
< 0.0066
< 0.0009
< 0.0005
< 0.0022
< 0.0030 0.070 +/- 021
< 0.0240
< 0.0008
< 0.0008
< 0.0015
< 0.0008
< 0.0041
< 0.0005
< 0.0006
< 0.0020
< 0.0045 0.057 +/- 0.013
< 0.0250
< 0.0005
< 0.0011
< 0.0008
< 0.0010
< 0.0081
< 0.0005
< 0.0006
< 0.0021
< 0.0068 Control Location, all other locations m All 1'3' results were < 0.07 pCi/m3 are Indicator Locations.
-- page 92 of 119 --
GAMMA ISOTOPIC ACTIVITY IN AIR PARTICULATES FOR 2002m (continued)
SITE ISOTOPE 1ST QTR 2ND QTR 3RD QTR 4TH QTR CL-11 CL-15 Be7 K4 0 CO6O N b9$
Zr95 Ru1 03 Ru'0 6 Cs'34 Cs'37 Ce'4' Ce'44 Be7 K4 0 0600 N b95 Zr95 Ru10 3 Ru'06 Cs'34 Cs'37 Ce'4' Ce'44 0.084 +/- 0.019
< 0.0250
< 0.0008
< 0.0014
< 0.0009
< 0.0009
< 0.0049
< 0.0008
< 0.0008
< 0.0022
< 0.0035 0.064 +/- 0.018
< 0.0230
< 0.0005
< 0.0013
< 0.0016
< 0.0014
< 0.0046
< 0.0008
< 0.0007
< 0.0014
< 0.0053 0.075 +/- 0.016
< 0.0260
< 0.0013
< 0.0005
< 0.0009
< 0.0009
< 0.0080
< 0.0008
< 0.0006
< 0.0018
< 0.0062 0.062 +/- 0.017
< 0.0260
< 0.0013
< 0.0005
< 0.0009
< 0.0009
< 0.0053
< 0.0006
< 0.0005
< 0.0027
< 0.0024 0.068 +/- 0.021
< 0.0240
< 0.0008
< 0.0008
< 0.0019
< 0.0007
< 0.0032
< 0.0004
< 0.0005
< 0.0021
< 0.0042 0.074 +/- 0.018
< 0.0240
< 0.0007
< 0.0013
< 0.0015
< 0.0009
< 0.0072
< 0.0006
< 0.0005
< 0.0019
< 0.0048 0.047 +/- 0.014
< 0.0250
< 0.0005
< 0.0013
< 0.0008
< 0.0009
< 0.0045
< 0.0004
< 0.0011
< 0.0017
< 0.0045 0.045 +/- 0.015
< 0.0250
< 0.0005
< 0.0007
< 0.0008
< 0.0014
< 0.0057
< 0.0008
< 0.0005
- 0.0016
< 0.0029 CL-94 Be7 K40 Co0 0 Nb0s Zr95 Ru10 3 Ru10 6 Cs'34 Cs'37 Ce'4' Ce'44 0.037 +/- 0.015
< 0.0250
< 0.0009
< 0.0009
< 0.0031
< 0.0008
< 0.0038
< 0.0007
< 0.0003
< 0.0015
< 0.0041 0.081 +/- 0.020
< 0.0260
< 0.0013
< 0.0008
< 0.0018
< 0.0009
< 0.0066
< 0.0009
< 0.0005
< 0.0022
< 0.0030 0.070 +/- 021
< 0.0240
< 0.0008
< 0.0008
< 0.0015
< 0.0008
< 0.0041
< 0.0005
< 0.0006
< 0.0020
< 0.0045 0.057 +/- 0.013
< 0.0250
< 0.0005
< 0.0011
< 0.0008
< 0.0010
< 0.0081
< 0.0005
< 0.0006
< 0.0021
< 0.0068 Control Location, all other locations are m All 1'3' results were < 0.07 pCi/m3 Indicator Locations.
-- page 92 of 119 --
2002 QUARTERLY TLD RESULTS (mRem I quarter net exposure)
Location 1ITQTR 2 ND QTR 3
QTR 4 TH QTR CL-1 16.8 +/- 0.2 22.5 +/- 0.1 A
22.5 +/- 0.5 CL-2 18.6 +/- 0.3 21.3 +/- 2.3 A
24.9 +/- 0.6 CL-3 18.0 +/- 0.2 20.4 +/- 2.2 A
23.6 +/- 0.6 CL-4 17.9 +/- 0.3 20.2 +/- 0.0 A
23.5 +/- 1.2 CL-5 18.4 +/- 0.4 21.8 +/- 2.4 A
24.4 +/- 2.1 CL-6 15.1 +/- 0.2 20.4 +/- 0.4 A
20.9 +/- 1.7 CL-7 17.0 +/- 0.2 22.2 +/- 2.7 A
23.2 +/- 1.6 CL-8 16.8 +/- 0.2 22.3 +/- 1.8 A
22.4 +/- 1.3 CL-11 16.0 +/- 0.2 19.4 +/- 0.8 A
23.5 +/- 1.6 CL-15 14.8 +/- 0.3 19.7 +/- 1.2 A
20.7 +/- 0.8 CL-22 15.0 +/- 0.4 20.1 +/- 1.0 A
26.0 +/-2.1 CL-23 15.0 +/- 0.3 24.0 +/- 1.5 A
24.6 +/- 1.9 CL-24 16.2 +/- 0.2 21.0 +/- 1.1 A
25.1 +/- 1.7 CL-33" 16.9 +/- 0.2 20.7 +/- 2.2 A
25.8 +/- 2.0 CL-34 18.7+/-0.4 21.3+/-1.0 A
25.4+/-1.4 CL-35 16.5+/-0.2 20.9+/-1.4 A
24.9+/-2.1 CL-36 18.3 +/- 0.4 23.3 +/- 0.1 A
25.6 +/- 1.5 CL-37 18.6 +/- 0.3 20.4 +/- 0.7 A
24.1 +/- 0.6 CL-41 19.4 +/- 0.2 24.4 +/- 2.8 A
25.5 +/- 0.3 CL-42 18.0 +/- 0.2 20.1 +/- 0.3 A
25.0 +/- 0.1 CL-43 19.0 +/- 0.3 23.5 +/- 2.2 A
26.6 +/- 1.6 CL-44 18.7 +/- 0.4 23.8 +/- 0.0 A
25.0 +/- 1.8 CL-45 19.9 +/- 0.2 21.2 +/- 0.8 A
24.8 +/- 0.6 CL-46 17.5 +/-0.2 20.4+/- 1.6 A
23.1 +/-0.1 CL-47 18.5 +/- 0.4 24.7 +/- 0.5 A
23.7 +/- 0.0 CL-48 17.2 +/- 0.2 19.7 +/- 1.8 A
23.7 +/- 0.8 CL-49 18.0 +/- 0.3 22.8 +/- 3.5 A
25.5 +/- 1.1 CL-51 17.9 +/- 0.3 25.5 +/- 2.3 A
25.2 +/- 1.4 CL-52 18.5 +/- 0.3 25.6 +/- 1.7 A
24.5 +/- 2.3 CL-53 16.2 +/- 0.2 19.3 +/- 0.0 A
23.7 +/- 2.8 CL-54 18.6 +/- 0.3 20.7 +/- 0.0 A
25.7 +/- 0.9 CL-55 19.0 +/- 0.3 20.9 +/- 0.5 A
27.9 +/- 5.3 CL-56 19.4 +/- 0.2 23.8 +/- 1.2 A
24.3 +/- 0.2 CL-57 19.8 +/- 0.2 25.2 +/- 2.3 A
25.8 +/- 0.7 CL-58 20.2 +/- 0.2 24.6 +/- 2.3 A
25.7 +/- 1.4 CL-60 18.7 +/- 0.3 21.5 +/- 2.0 A
26.4 +/- 1.6 CL-61 18.9+/-0.3 21.2+/-1.8 A
24.7+/-0.9 CL-63 19.1 +/-0.3 21.3 +/-3.0 A
23.4 +/-0.6 CL-64 18.8 +/- 0.4 24.3 +/-0.4 A
24.9 +/- 0.5 CL-65 18.9 +/- 0.2 21.8 +/- 0.5 A
24.1 +/- 0.7 CL-74 16.1 +/-0.2 19.9 +/-0.1 A
21.7 +/-0.3 CL-75 17.2 +/- 0.2 24.1 +/- 2.0 A
24.6 +/- 0.5 CL-76 17.3 +/- 0.2 21.8 +/- 2.6 A
24.9 +/- 0.7 CL-77 16.6 +/- 0.2 22.3 +/- 1.5 A
23.2 +/- 0.6 CL-78 18.1 +/- 0.2 24.4 +/- 1.1 A
24.2 +/- 0.9
- ODCM Control Location n Supplemental Control Locations A Clinton's 3rd Quarter ODCM REMP TLD results - both Indicator and Control - were determined to be inaccurate from our Vendor. ODCM REMP TLD results were irradiated from an unknown external source of radiation during air transportation from California to Illinois prior to placement in the environment.
This resulted in inconsistent readings after adding this unknown exposure to their quarterly environmental exposure.
-- page 93 of 119 --
2002 QUARTERLY TLD RESULTS (continued)
(mRem / quarter net exposure Location CL-79 CL-80 CL-81 CL-84 CL-90 CL-91 CL-97n CL-99 CL-114" 1 ST QTR 18.0 +/- 0.2 18.8 +/- 0.3 18.6 +/- 0.3 18.4 +/- 0.4 13.7 +/- 0.2 16.2 +/- 0.2 18.6 +/- 0.4 14.8 +/- 0.3 14.8 +/- 0.5 2ND QTR 23.7 +/- 2.0 20.5 +/- 2.6 20.7 +/- 0.4 23.6 +/- 2.6 17.7 +/- 0.7 20.0 +/- 1.4 22.5 +/- 0.0 19.8 +/- 1.6 22.4 +/- 1.5 3 RDQTR A
A A
A A
A A
A, A
4TH QTR 24.6 +/- 1.0 26.4 +/- 2.0 24.6 +/- 3.4 25.5 +/- 1.0 21.6 +/- 1.3 24.1 +/- 1.4 27.1 +/- 0.8 19.9 +/- 0.7 22.1 +/- 0.8 n Supplemental Control Locations A
Clinton's 3rd Quarter ODCM REMP TLD results - both Indicator and Control - were determined to be inaccurate from our Vendor. ODCM REMP TLD results were irradiated from an unknown external source of radiation during air transportation from California to Illinois prior to placement in the environment. This resulted in inconsistent readings after adding this unknown exposure to their quarterly environmental exposure.
-- page94of 119--
Date Collected Gross Beta Be7 K40 M n54 Fes9 Co05 C000 Zn65 N b95 Zr95 Cs134 Cs'3' Ba14 0 La 14 0 Ce'44 Date Collected Gross Beta Be7 K40 Mns4 Fess 0060 Zn6 5 N b95 Zr95 Cs134 Cs137 B a140 La 14 0 Ce'144 CL-13 SURFACE WATER ACTIVITY (pCiUI) 30 Jan 02 27 Feb 02 27 Mar 02 24 Apr 02 29 May 02 26 Jun 02 3.1 +/- 0.7 2.2 +/- 0.5 2.5 +/- 0.6 2.2 +/- 0.5 2.9 +/- 0.6 2.4 +/- 0.6
< 36.5
< 79.5
<4.7
<3.4
<2.5
<5.8
<3.6
<2.5
< 10.9
<2.5
<3.2
< 14.8
<3.4
<38.6
< 51.0
< 104.8
<3.8
<9.0
<5.6
<3.3
<3.8
<4.3
<7.9
<4.4
<4.8
<26.3
<8.7
< 50.8
< 22.3
< 57.2
<2.8
< 4.1
<3.2
<3.7
< 2.4
<2.5
<4.7
<2.9
<3.2
< 14.8
<5.0
< 25.3
<32.9
< 54.2
<2.3
<4.3
<2.9
<2.3
<3.9
< 1.4
<2.6
< 1.6
<2.4
<22.0
<3.2
<22.0
< 23.5
< 71.1
<2.7
<3.7
<2.0
<2.8
<3.6
< 3.5
<4.4
< 3.3
<2.4
< 33.0
<3.9
< 27.9
< 23.0
< 51.1
<2.2
<6.5
< 1.7
<2.6
<5.6
< 3.1
<5.3
<2.6
<2.0
<42.0
<4.6
< 19.9 31 Jul 02 28 Aug 02 24 Sep 02 30 Oct 02 26 Nov 02 02 Jan 03 (g)
< 25.5
< 58.9
< 2.4
<6.6
< 1.9
<2.4
<4.6
<4.2
<5.0
<2.9
<2.4
< 47.1
< 6.1
<25.8 (g)
<28.6
<81.9
< 3.0
<7.8
<2.8
<3.7
<4.0
<4.9
< 8.3
< 4.1
<4.3
< 15.4
<2.2
<40.8 (g)
<42.2
< 87.2
<3.7
<7.8
<2.9
<4.0
<6.3
<2.3
<7.6
<4.4
<3.8
< 17.7
< 5.1
<22.7 (g)
< 26.1
< 97.0
< 3.9
<8.8
<4.4
<3.3
<5.0
<3.5
< 12.8
< 2.9
<5.2
< 21.4
<7.9
< 34.2 (9)
< 38.5
< 99.9
<3.8
< 6.1
< 3.3
<4.7
<5.8
<3.7
< 5.5
<5.0
< 7.1
< 20.4
<5.3
<33.8 (g)
<47.5
< 113.4
<4.8
< 11.6
<5.5
<5.7
<5.7
< 7.1
< 11.0
<3.7
<6.9
< 32.2
<9.5
<46.7 (g)
Analysis for Gross Beta is not a required REMP analysis and was suspended in July 2002
-- page 95 of 119 --
CL-90 SURFACE WATER ACTIVITY (pCill)
Date Collected 30 Jan 02 27 Feb 02 27 Mar 02 24 Apr 02 29 May 02 26 Jun 02 Gross Alpha Gross Beta I 131 Be7 K40 Mn54 Fe59 Co60 Zn65 N b95 Zr95 Cs134 Cs'37 Ba 14 0 La14 0 Ce144 0.4 +/- 0.3 2.4 +/- 0.3
< 0.4
< 21.9
< 62.3
< 2.1
<3.0
<2.6
<2.2
<2.7
<2.7
<7.6
< 2.1
<2.9
< 13.6
<2.2
< 21.1
< 1.4 2.4 +/- 1.1
< 1.8 5.7 +/- 0.9 9.3 +/- 1.0 1.8 +/- 0.8
< 1.3
< 1.3 2.6 +/- 0.7 3.0 +/- 0.8
< 0.4
<44.6
<96.2
<5.0
< 10.6
<4.6
<5.3
<2.6
<3.9
<7.2
<4.8
<5.0
< 21.8
<3.5
< 49.3
< 0.4
<29.8
< 91.1
<5.0
<4.4
<3.8
<5.2
< 8.5
<4.8
<9.6
<2.4
< 5.1
< 15.1
<4.9
< 36.4
< 0.3
< 18.6
< 48.4
< 1.8
< 3.1
< 1.5
<2.4
<2.7
< 1.4
< 5.1
< 1.7
< 1.9
<7.9
<2.0
< 20.5
< 0.3
<48.0
<89.6
<4.7
<6.4
<3.7
<3.9
<9.9
<6.9
<5.5
<5.2
< 5.2
< 27.3
<2.9
< 48.6
< 0.4
< 23.2
< 90.9
<3.2
<6.2
< 3.1
< 4.1
<5.9
< 3.8
<8.6
<4.3
<3.7
< 12.5
<3.4
< 38.5 Date Collected Gross Alpha Gross Beta 1131 31 Jul 02 28 Aug 02 24 Sep 02 30 Oct 02 26 Nov 02 02 Jan 03 (i)
(9)
< 0.5 Be7 K4 0 Mn54 Fe 5s co 6 0 Zn65 N b95 Zr95 Cs134 Cs'37 Ba 14 0 La 140 Ce 144
<24.8
< 98.0
< 3.3
< 10.2
<4.7
<5.7
<7.3
<5.3
< 12.6
<5.5
<4.4
< 16.4
<4.4
< 38.5 (i)
(9)
< 0.4
< 16.7
<66.3
<2.7
<5.4
<3.2
<2.8
< 4.1
<2.6
<4.0
<3.2
<2.6
< 12.5
<4.3 (j)
(g)
< 0.3
< 31.5
<86.0
<2.4
<4.4
<2.5
<3.0
<2.5
< 2.1
< 3.1
<2.5
<3.4
< 11.1
< 3.1 (j)
(9)
< 0.3
< 26.3
<58.3
< 1.1
<4.9
< 1.7
<2.9
<5.0
<2.4
<2.3
<2.9
<2.9
<7.8
< 1.9 (i)
(9)
< 0.5
< 28.9
< 57.0
< 2.0
<3.5
< 1.4
<2.7
< 1.8
<3.9
<6.3
<2.5
<2.3
< 10.7
<3.3
< 33.4 (i)
(g)
< 0.4
< 20.3
< 79.1
< 3.7
<4.0
<2.7
<2.0
<2.2
<2.7
< 4.1
< 3.1
<3.3
< 17.3
<3.9
<23.3
< 32.5
< 32.7
< 24.3 (g) Analysis for Gross Beta is not a required REMP analysis and was suspended in July 2002 (j) Analysis for Gross Alpha is not a required REMP analysis and was suspended in July 2002
-- page96of119 --
CL-91 SURFACE WATER ACTIVITY (pci/I) 30 Jan 02 27 Feb 02 27 Mar 02 24 Apr 02 29 May 02 26 Jun 02 Date Collected Gross Alpha Gross Beta Be 7 K40 Mn54 Fe 5 9 0060 Zn6 5 N b95 Zr95 Cs'34 Cs' 37 Ba 140 La14 0 Ce'44
< 1.2
< 1.6 2.2 +/- 0.9 2.7 +/- 1.1
< 1.7
< 1.5 1.8 +/- 0.9
< 1.6
< 21.2
< 93.5
<2.8
<3.3
< 2.3
<4.0
<6.0
< 5.1
<9.5
<4.4
<2.6
<22.8
< 3.4
<28.9
< 43.9
< 99.2
<3.5
<6.9
<2.6
<4.4
<5.3
<3.7
<8.2
<5.0
<4.3
< 16.3
< 3.1
<52.8
<44.6
< 88.1
<4.0
<6.5
<3.0
<2.5
<5.8
<4.0
<9.2
<2.5
<4.9
< 23.7
<6.5
< 25.4
< 15.5
<64.0
<2.4
<3.9
< 2.7
<2.9
<4.3
<2.5
<3.4
<2.8
<2.2
< 14.4
<2.3
< 21.7
< 1.7 1.8 +/- 0.9
< 30.9
<62.8
< 1.7
<4.5
< 1.6
<2.4
<2.8
<3.6
<4.4
<2.7
<2.8
< 19.4
<5.9
< 28.1
< 1.8
< 1.9
< 13.2
< 32.1
< 1.0
<3.0
< 1.3
< 1.5
< 1.8
< 2.1
<3.4
< 1.9
< 1.9
< 25.5
<5.2
< 12.0 Date Collected Gross Alpha Gross Beta 31 Jul 02 28 Aug 02 24 Sep 02 30 Oct 02 26 Nov 02 02 Jan 03 (j)
(9)
(j)
(g)
(i)
(g)
(i)
(9)
(j)
(g)
(i)
(9)
Be7 K4 0 Mn 5 4 Fe 59 Co58 Co6 5 Zn6 5 Nb95 Zr95 Cs' 34 Ba140 La 140 Ce'44
< 33.3
< 69.6
< 3.1
<4.7
<2.8
<2.9
<3.3
<2.4
<6.2
<3.4
<2.5
<44.6
< 12.4
< 29.5
< 34.3
<68.8
<3.4
< 9.1
<4.7
< 3.1
<7.3
<3.7
< 7.1
<3.4
<4.5
< 26.7
<5.0
< 26.5
<35.9
< 67.7
<2.8
<4.5
< 1.8
< 3.5
<3.8
<3.4
<5.6
<3.5
< 1.8
< 16.4
< 2.1
< 27.9
< 29.8
<121.6
<4.5
< 7.8
<6.0
<5.2
<6.8
<5.0
< 10.1
<5.9
<4.7
< 30.2
<5.5
< 46.6
< 30.0
< 92.4
< 1.5
<4.5
<2.3
< 2.1
<5.8
<2.7
<4.3
< 3.1
< 3.0
< 18.8
< 2.1
< 32.1
< 46.8
< 108.7
< 3.1
<4.9
<4.4
<3.4
< 5.1
<5.9
< 11.5
<4.5
< 5.1
< 38.2
< 8.1
< 38.5 (g) Analysis for Gross Beta is not a required REMP analysis and was suspended in July 2002 U) Analysis for Gross Alpha is not a required REMP analysis and was suspended in July 2002
-- page 97 of 119 --
CL-99 SURFACE WATER ACTIVITY (pciII)
Date Collected Gross Alpha Gross Beta Be7 K40 Mn 54 Fe5s Cos$
Zn6 5 N b95 Zr95 CS1 3 4 Cs137 Ba 14 0 La 14 0 Ce144 Date Collected Gross Alpha Gross Beta Be7 K4 0 Mn 54 Fess Co 6 0 Zn6 5 N b05 Zr95 Cs134 Cs137 Ba 140 La 14 0 Ce144 30 Jan 02
< 0.8 3.2 +/- 1.3
< 53.2
< 98.6
< 4.1
< 6.4
<4.3
< 6.1
<6.5
<4.5
< 11.1
<6.2
<5.7
< 25.1
<4.9
<45.0 27 Feb 02
< 0.7 1.4 +/- 1.1
< 55.6
< 87.4
<4.9
< 8.8
<5.3
<2.8
<5.9
<4.3
<8.4
<4.6
<5.3
< 34.2
<5.4
< 35.0 27 Mar 02
< 0.9 1.7+/- 1.1
< 21.5
< 45.7
<2.4
< 3.9
<2.0
<2.3
< 3.3
< 2.4
<4.0
< 3.2
< 2.5
< 8.1
< 2.3
< 21.6 24 Apr 02
< 1.9
< 2.4
< 25.0
< 52.3
< 2.6
< 3.8
<2.6
< 1.7
< 2.4
< 4.0
<4.3
< 1.7
< 2.9
< 22.2
< 5.1
< 27.0 29 May 02
< 1.7
< 2.0
< 37.7
< 77.9
< 2.4
< 5.9
<2.9
<2.6
< 2.7
< 3.2
<7.7
< 3.6
< 3.9
< 42.5
<4.5
< 30.7 26 Jun 02
< 2.0 3.6 +/- 0.8
< 21.3
< 38.1
< 1.1
< 4.3
< 1.6
< 1.4
< 3.6
< 2.0
< 3.5
< 1.4
< 1.6
< 19.6
<5.6
< 19.6 31 Jul 02 28 Aug 02 24 Sep 02 30 Oct 02 26 Nov 02 02 Jan 03 (j)
(9)
< 40.3
< 77.3
< 1.8
<4.8
< 1.7
< 2.9
< 3.1
<4.9
< 5.3
< 2.7
< 1.7
< 46.9
< 10.7
< 29.2 (i)
(9)
< 25.1
< 68.6
<2.9
<2.3
< 3.1
<3.7
<2.6
< 2.1
<4.8
<3.3
<2.7
< 13.4
< 6.3
< 20.7 (j)
(9)
< 32.8
< 98.9
<5.2
<4.9
<2.8
<4.6
<4.0
<2.7
<6.2
< 3.6
<5.5
< 13.8
< 5.1
< 20.9 (j)
(g)
<48.8
<96.0
< 3.8
< 6.0
< 3.4
< 3.9
<5.3
<3.3
< 10.7
<4.3
<4.0
< 24.1
<7.4
< 24.9 (j)
(g)
< 29.4
< 82.2
<3.6
< 3.9
<2.9
<4.2
<4.6
<2.9
< 3.6
< 3.5
< 4.2
< 21.0
< 5.0
< 22.8 (j)
(9)
< 43.0
<109.7
< 4.2
< 9.1
<4.2
<4.4
<5.9
<6.3
< 11.6
< 3.6
< 6.0
<24.2
< 13.0
< 39.5 (g) Analysis for Gross Beta is not a required REMP analysis and was suspended in July 2002 (j) Analysis for Gross Alpha is not a required REMP analysis and was suspended in July 2002
-- page 98 of 119 --
SURFACE WATER and DRINKING WATER QUARTERLY TRITIUM COMPOSITE (pCi/I)
Quarter CI-13 CI-14 CI-90 CI-91 C I-99 1st
< 169
< 169
< 169
< 169
< 169 2nd
< 131
< 131
< 131
< 131
< 131 3rd
< 146
< 146 4th
< 162
< 162
< 146
< 146
< 146
< 162
< 162
< 162 CL-7D WELL WATER ACTIVITY (pCi/I)
Date Collected Gross Alpha Gross Beta H3 1131 Be7 K4 0 Mn 54 Fe" Gos8 Zn65 N b95 Zr95 CS 1 3 4 CS 1 3 7 Ba 14 0 La1 4 0 Ce1 4 4 27 Mar 02 26 Jun 02 24 Sep 02 02 Jan 03
< 1.0 1.2 +/- 0.8
< 89
< 0.3
<20.7
< 41.5
<2.5
<2.3
<2.0
<2.6
< 1.9
<2.8
<3.9
<2.4
<2.4
< 10.0
<3.6
< 15.5 2.2 +/- 1.5 3.2 +/- 1.3
< 131
< 0.4
< 21.1
< 33.5
< 1.9
<6.8
<2.9
< 1.9
<2.7
< 4.1
<5.7
<2.0
<3.4
<29.8
<8.5
< 16.3 (j)
(g)
< 146 (i)
<30.7
< 72.8
<2.4
<3.5
< 3.2
<2.8
<2.5
< 3.4
<4.5
<4.4
<3.4
< 13.0
< 2.1
< 29.1 (j)
(g)
< 162 (i)
<63.2
< 112.1
<5.2
< 13.4
<5.4
<5.8
< 5.1
< 4.1
< 14.8
<3.7
<2.8
< 53.1
< 11.7
<34.3 (g) Analysis for Gross Beta is not a required REMP analysis and was suspended in July 2002
()
Analysis for Gross Alpha is not a required REMP analysis and was suspended in July 2002 (i)
Analysis for 1131 is not a required REMP analysis and was suspended in July 2002
-- page 99 of 119 --
CL-12 UNTREATED WELL WATER ACTIVITY (pCiII)
Date Collected Gross Alpha Gross Beta H3 1131 Be 7 K40 Mn 54 Fess Coss 0060 Zn6 5 Nb95 Zr95 cS134 Cs137 Ba 14 0 La 14 0 Ce144 27 Mar 02 26 Jun 02 24 Sep 02 02 Jan 03 2.4 +/- 1.5 3.4 +/- 1.6
< 89
< 0.4
< 39.5
< 76.1
< 4.5
<4.0
< 1.9
<4.9
<2.4
<4.5
< 8.4
< 3.6
< 4.1
< 12.0
<4.7
< 31.1
< 1.9 2.0 +/- 1.5
< 131
< 0.5
< 23.3
< 41.8
< 1.9
< 4.9
< 1.7
< 1.7
< 3.6
<2.7
<5.2
< 1.8
< 1.9
< 26.6
< 5.1
< 19.1 (i)
(g)
< 146 (i)
<34.0
<76.2
< 1.9
<5.2
< 1.6
<2.4
<2.9
<3.8
< 6.0
< 3.3
< 2.6
< 14.4
<2.6
< 26.4 (i)
(g)
< 162 (i)
< 33.1
< 68.2
< 3.4
< 3.6
< 2.6
< 2.4
< 3.9
<4.2
<5.7
<2.9
<2.6
< 19.2
< 8.7
< 27.7 (g)
Analysis for Gross Beta is not a required REMP analysis and was suspended in July 2002 (j)
Analysis for Gross Alpha is not a required REMP analysis and was suspended in July 2002 (i) Analysis for G1'3 is not a required REMP analysis and was suspended in July 2002
-- page 100 of 119 --
CL-12 TREATED WELL WATER ACTIVITY (pCiI)
Date Collected Gross Alpha Gross Beta H3 1131 Be7 K4 0 Mn54 Fess Co60 Zn 6 5 N b9s Zr95 CS1 3 4 Cs137 Ba1 4 0 La1 4 0 Ce144 27 Mar 02 26 Jun 02 24 Sep 02 02 Jan 03 2.0 +/- 1.4
< 1.8 2.3 +/- 1.5 2.4 +/- 1.5
< 89
< 0.4
< 26.4
< 50.6
< 1.3
<2.2
< 1.4
< 2.1
<2.3
< 1.9
<4.9
<2.7
< 2.1
< 12.8
<2.3
< 26.8
< 131
< 0.4
< 16.7
< 33.8
< 1.5
<4.8
< 1.9
< 1.3
<3.0
<2.3
<4.9
< 1.2
< 1.6
<24.9
<5.3
< 18.5 (j)
(9)
< 146 (i)
<33.8
< 87.2
<2.2
<6.9
<2.5
<2.9
<5.0
<2.9
<4.5
< 3.0
<3.7
< 16.1
<4.3
< 20.0 (i)
(g)
< 162 (i)
< 27.6
< 14.6
< 2.1
<5.5
< 1.9
<2.4
< 4.1
<3.0
<4.4
< 1.5
< 1.9
< 23.4
<6.3
<23.8 (g)
Analysis for Gross Beta is not a required REMP analysis and was suspended in July 2002 (j)
Analysis for Gross Alpha is not a required REMP analysis and was suspended in July 2002 (i)
Analysis for 1131 is not a required REMP analysis and was suspended in July 2002
-- page 101 of 119 --
CL-14 DRINKING WATER ACTIVITY (pCill)
Date 30 Jan 02 27 Feb 02 27 Mar 02 24 Apr 02 29 May 02 26 Jun 02 Collected Gross Alpha
< 0.9
< 0.9 1.2 +/- 0.6
< 1.5
< 1.2
< 1.2 Gross Beta 1.3 +/- 0.5 1.1 +/- 0.5 2.0 +/- 0.5 1.6 +/- 0.6 1.3 +/- 0.5 1.4 +/- 0.6 Be7
< 23.8
< 44.1
< 22.0
< 24.4
< 25.3
< 30.8 K40
< 105.0
< 95.3
< 63.3
< 65.0
< 63.4
< 59.9 Mn54
<3.9
<3.5
<2.5
<2.5
<2.2
<2.6 Fe59
<8.0
<5.5
<4.6
<5.1
<3.1
<5.4 Co58
< 2.8
< 3.5
< 2.0
< 2.9
< 2.3
< 2.2 0o65
< 5.4
< 5.4
< 1.9
< 2.6
< 1.4
< 2.0 Zn65
< 3.7
< 5.3
< 5.6
< 4.5
< 3.0
< 5.3 Nb95
<3.4
<4.0
<2.1
<2.0
<2.5
<5.1 95
< 14.0
< 7.2
< 5.5
< 6.2
< 5.1
< 8.3 Cs'34
< 5.9
< 6.8
< 3.1
< 1.7
< 1.8
< 2.0 Cs'37
<4.6
<6.6
<2.7
< 1.9
< 3.0
< 2.5 Ba' 40
< 19.0
< 21.3
< 16.2
< 16.4
< 27.1
< 44.6 La' 40
< 3.8
< 3.2
< 4.5
< 2.7
< 5.3
< 11.6 Ce'44
< 32.0
< 52.2
< 25.2
< 29.2
< 29.0
< 29.1 Date 31 Jul 02 28 Aug 02 24 Sep 02 30 Oct 02 26 Nov 02 02 Jan 03 Collected Gross Alpha (j)
(j)
(j)
(j)
(j)
(j)
Gross Beta 1.1 +/- 0.3 0.9 +/- 0.5 1.0 +/- 0.5 1.2 +/- 0.5
< 0.8 0.9 +/- 0.5 Be7
< 40.5
< 24.0
< 45.7
< 34.2
< 19.9
< 34.6 K40
< 70.1
< 117.5
< 112.2
< 121.6
< 82.5
< 102.0 Mn54
<2.3
<3.2
<6.8
<3.9
<2.8
<3.2 Fe59
< 4.1
< 4.0
< 8.2
< 6.7
< 6.7
< 3.7 Co 058
<2.9
<2.7
<6.1
< 5.2
< 3.1
< 3.0 Co60
<2.4
<3.3
<5.1
<6.4
<2.9
<4.4 Zn65
<2.6
<5.8
< 3.5
<3.5
<3.9
<5.3 Nb95
<4.1
<2.4
<3.0
<5.8
<2.4
<6.2 Zr95
< 7.4
< 8.0
< 6.9
< 13.2
< 7.0
< 6.3 Cs'34
<3.5
<3.2
<6.4
<4.5
<2.8
<4.6 Cs137
< 1.1
< 5.1
< 6.7
< 4.3
< 2.8
< 5.9 Ba140
< 35.9
< 16.1
< 24.2
< 25.9
< 21.7
< 19.1 La140
< 9.3
<5.3
< 5.8
<4.8
< 1.8
< 8.6 Ce'44
< 21.7
< 21.6
< 49.6
< 43.9
< 34.3
< 37.9
() Analysis for Gross Alpha is not a required REMP analysis and was suspended in July 2002
-- page 102 of 119 --
CL-116 MILK ACTIVITY - (Control)
(pciIl) 31 Jan 02 27 Feb 02 27 Mar 02 24 Apr 02 Date Collected 1131 Sr90 08 May 02
< 0.5
< 0.5 1.7 +/- 0.4
< 0.4 0.6 +/- 0.3
< 0.5 1.0 +/- 0.4
< 0.3 1.0 +/- 0.4 1.7 +/- 0.4 Be7 K4 0 Mn 54 Fe 59 cose Zn65 N b95 Zr95 Cs1 3 4 Cs1 3 7 Ba 14 0 La 14 0 Ce14 4
< 68.5 1,180 + 162
< 6.5
< 8.9
<5.0
<3.7
< 13.2
<5.3
< 10.6
<5.3
<7.8
< 24.2
<6.2
< 39.0
< 54.8 1,253 +/- 156
< 4.6
< 12.2
< 3.7
< 6.1
<8.9
<5.5
< 11.8
<4.0
<5.8
< 27.4
<5.2
< 45.3
< 36.1 1,261 + 143
<5.9
< 10.0
<4.2
<4.9
<9.8
<5.2
< 8.3
<6.5
<5.5
<26.6
<5.8
< 50.6
< 44.1 1,528 +/- 145
<3.6
<8.7
< 5.1
<3.9
<7.3
< 4.1
<5.9
<4.6
<5.0
< 19.4
<2.9
<44.7
< 36.5 1,168 +/- 157
<3.8
<7.6
<4.9
< 5.1
<8.7
<3.4
<6.3
<5.4
<5.5
<22.0
<2.9
<45.2 Date Collected i131 Sr90 22 May 02 05 Jun 02 19 Jun 02 02 Jul 02 17 Jul 02
< 0.4 1.8 +/- 0.5
< 0.4 1.1 +/-0.4
< 0.5 2.0 +/- 0.5
< 0.4
< 0.4 1.0 +/- 0.4 0.7 +/- 0.3 Be7 K40 Mn564 Fe 59 Co58 Zn65 N b95 Zr95 Cs1 3 4 cS137 Ba14 0 La 14 0 Ce 14 4
< 38.0 1,300 + 181
< 5.0
< 9.1
< 3.2
< 8.0
<6.4
< 5.6
<8.2
<7.2
<5.4
< 14.5
<3.6
< 33.6
< 38.4 1,267 +/- 152
<5.3
< 11.4
<2.2
<4.7
<7.7
<4.1
< 10.4
<2.6
<5.5
< 23.3
<2.7
< 23.2
< 32.2 1,269 + 135
<5.3
<9.6
<3.9
<3.5
<6.0
< 2.1
<4.8
<3.4
<4.2
< 16.9
<2.0
< 29.1
< 29.0 1,639 +/- 177
< 6.3
< 8.3
< 5.8
< 5.5
< 11.8
< 6.2
< 12.3
< 7.8
< 4.4
< 26.7
< 4.0
< 47.6
< 49.2 1,264 +/- 169
< 4.4
< 7.1
< 5.4
< 3.8
< 10.9
< 5.0
< 9.6
< 6.2
< 3.2
< 17.4
< 4.2
< 51.7
-- page 103 of 119 --
CL-116 MILK ACTIVITY- (Control) (continued)
Date Collected i131 Sr9 '
31 Jul 02 14 Aug 02
< 0.4 (I)
< 0.4 (I) 28 Aug 02
< 0.4 (I) 11 Sep 02
< 0.3 (I) 25 Sep 02
< 0.4 (I)
Be7 K 40 Mn54 Fe"9 c0s8 C 060 Zn65 NWb9 Zr 9' cS134 CS13 7 Ba 140 La140 Ce144
< 32.4 1,330 +/- 167
<4.6
<5.7
<5.0
<4.4
< 12.3
< 3.1
< 7.9
<5.5
<5.4
< 31.5
<3.9
< 30.2
< 16.7 1,385 + 108
<3.2
< 5.1
< 2.2
<2.8
<8.6
< 2.1
<4.2
<3.3
<2.6
< 11.2
<2.5
<26.8
< 25.8 1,301 +/- 119
<3.4
<8.3
<2.8
<2.5
<5.7
<4.5
<7.6
<3.9
<3.4
< 15.5
<2.0
<34.7
< 20.5 1,297 + 106
<4.2
<6.7
<2.3
<2.9
< 7.1
< 3.1
< 3.4
< 3.1
< 4.1
< 15.4
< 1.5
< 38.1
< 39.9 1,297 +/- 113
<4.4
< 5.1
< 3.4
< 3.1
<9.0
<3.2
<4.6
< 4.1
<2.4
< 21.9
<2.9
< 36.7 Date Collected i131 Sr9" 09 Oct 02 23 Oct 02 26 Nov 02 02 Jan 03
< 0.3 (I)
< 0.4 (I)
< 0.3 (I)
< 0.4 (I)
Be7 K 40 Mn54 Fe's cose C0a0 Zn65 N b95 Zr95 cS134 05S137 Ba140 La 140 Ce'44
< 30.1 1,302 +/- 114
<2.8
< 7.1
<3.5
<3.3
<5.6
<2.4
<6.2
<2.5
< 3.1
< 19.2
< 1.3
< 35.5
<54.5 1,232 +/- 162
<5.4
< 14.8
<5.6
<4.4
<9.7
<6.2
<9.8
<7.3
<3.9
< 23.4
<4.3
<44.6
< 30.6 1,241 +/- 109
<2.0
< 7.4
<3.2
<2.5
<5.6
<3.6
< 5.1
<2.5
<4.3
< 16.9
<2.6
< 30.2
<30.
1,259 + 120
< 4.6
<7.2
< 3.1
<4.0
<7.8
<2.4
<5.5
<2.7
<2.6
< 15.9
<2.7
<33.8 (I)
Analysis for Sr" is not a required REMP analysis and was suspended in July 2002
-- page 104 of 119 --
CL-I GRASS ACTIVITY (pCi/g wet)
Date Collected 01 May 02 15 May 02 29 May 02 12 Jun 02 26 Jun 02 Be7 K4 0 Mn54 Fe59 Co 58 Zn65 N b9 5
Zr95 I 131 Cs134 cS137 Ba 140 La 14 0 Ce144 3.41 +/- 0.37 6.20 +/- 0.63
<.015
<.048
<.017
<.017
<.049
<.028
<.023
<.031
<.025
<.020
<.092
<.009
<.128 1.88 +/- 0.25 4.98 +/- 0.60
<.016
<.036
<.014
<.015
<.049
<.020
<.050
<.032
<.012
<.027
<.093
<.011
<.156 0.88 +/- 0.33 5.17 +/- 0.68
<.019
<.047
<.019
<.009
<.059
<.021
<.025
<.035
<.026
<.020
<.099
<.013
<.142 1.29 +/- 0.23 4.97 +/- 0.56
<.016
<.031
<.011
<.012
<.052
<.016
<.044
<.021
<.019
<.017
<.095
<.016
<.145 1.27 +/- 0.33 4.59 +/- 0.71
<.019
<.024
<.020
<.023
<.049
<.014
<.029
<.035
<.022
<.028
<.131
<.016
<.098 Date Collected 10 Jul 02 17 Jul 02 31 Jul 02 14 Aug 02 28 Aug 02 Be7 K40 Mn 54 Fe59 Cos8 Co60 Zn65 Nb95 Zr95 1131 Cs134 Cs137 Ba 140 La 140 Ce144 1.19 +/- 0.31 6.24 +/- 0.71
<.015
<.030
<.020
<.021
<.036
<.021
<.047
<.049
<.017
<.022
<.081
<.014
<.186 1.64 +/- 0.34 8.17 +/- 0.99
<.025
<.056
<.020
<.036
<.053
<.023
<.069
<.027
<.044
<.026
<.123
<.021
<.192 2.09 +/- 0.24 4.89 +/- 0.44
<.013
<.027
<.013
<.009
<.032
<.013
<.017
<.030
<.007
<.014
<.058
<.011
<.105 1.13 +/- 0.26 3.75 +/- 0.58
<.016
<.038
<.018
<.026
<.042
<.019
<.027
<.026
<.020
<.031
<.086
<.018
<.145 3.33 +/- 0.41 5.54 +/- 0.66
<.025
<.037
<.015
<.017
<.027
<.014
<.048
<.045
<.028
<.025
<.123
<.023
<.135
-- page 105 of 119 --
CL-I GRASS ACTIVITY (continued)
Date Collected 11 Sep 02 25 Sep 02 09 Oct 02 23 Oct 02 Be7 K4 0 Mn 54 Fe 59 Coss C00 Zn65 N b95 Zr95 131 Cs 1 3 4 Cs 13 7 Ba 140 La 14 0 Ce 14 4 4.64 +/- 0.39 5.44 +/- 0.61
<.022
<.024
<.016
<.014
<.020
<.018
<.027
<.028
<.020
<.017
<.083
<.019
<.134 3.81 +/- 0.38 4.04 +/- 0.59
<.016
<.030
<.024
<.018
<.035
<.027
<.041
<.040
<.027
<.017
<.098
<.020
<.167 1.47 +/- 0.28 5.95 +/- 0.51
<.014
<.032
<.010
<.011
<.036
<.015
<.019
<.030
<.016
<.019
<.061
<.008
<.088 1.89 +/- 0.29 6.16 +/- 0.58
<.015
<.037
<.014
<.019
<.022
<.022
<.039
<.024
<.020
<.017
<.066
<.013
<.154
-- page 106 of 119 --
CL-2 GRASS ACTIVITY (pCilg wet)
Date Collected 01 May 02 15 May 02 29 May 02 12 Jun 02 26 Jun 02 Be 7 K 40 Mn 54 Fe 59 0058 Co06 Zn65 Nb95 Zr95 1131 Cs134 C0137 Ba 14 0 La 14 0 Ce 14 4 1.09 +/- 0.23 4.85 +/- 0.60
<.008
<.038
<.019
<.016
<.044
<.018
<.031
<.015
<.019
<.018
<.039
<.015
<.082 1.62 +/- 0.25 5.29 +/- 0.62
<.012
<.038
<.018
<.014
<.028
<.016
<.038
<.038
<.019
<.020
<.066
<.014
<.107 1.47 +/- 0.26 5.78 +/- 0.63
<.026
<.042
<.017
<.018
<.042
<.016
<.037
<.023
<.025
<.013
<.080
<.016
<.133 2.16 +/- 0.32 4.81 +/- 0.62
<.019
<.036
<.017
<.022
<.052
<.011
<.023
<.027
<.014
<.018
<.109
<.016
<.089 1.85 +/- 0.39 5.07 +/- 0.74
<.032
<.037
<.023
<.018
<.054
<.019
<.047
<.049
<.015
<.038
<.118
<.015
<.213 Date Collected 10 Jul 02 17 Jul 02 31 Jul 02 14 Aug 02 28 Aug 02 Be 7 K 40 Mn 54 Fe 5 9 Zn65 Nb 9 5 Zr95 i131 Cs1 3 4 Cs 137 Ba 14 0 La 14 0 Ce 144
< 0.18 4.70 +/- 0.54
<.015
<.044
<.018
<.024
<.044
<.019
<.018
<.031
<.021
<.017
<.049
<.013
<.123
< 0.22 5.79 +/- 0.59
<.019
<.043
<.023
<.020
<.048
<.016
<.045
<.023
<.018
<.015
<.063
<.009
<.155 1.75 +/- 0.25 5.13 +/- 0.47
<.016
<.032
<.016
<.013
<.047
<.013
<.017
<.027
<.013
<.010
<.063
<.007
<.107 0.73 +/- 0.19 3.30 +/- 0.33
<.013
<.019
<.011
<.012
<.015
<.009
<.029
<.013
<.007
<.011
<.039
<.008
<.107 5.07 +/- 0.34 3.52 +/- 0.42
<.015
<.029
<.015
<.012
<.018
<.010
<.025
<.027
<.008
<.009
<.080
<.008
<.108
-- page 107 of 119 --
CL-2 GRASS ACTIVITY (continued)
Date Collected 11 Sep 02 25 Sep 02 09 Oct 02 23 Oct 02 Be7 K40 Mn 54 Fe 5 9 Co 6 0 Zn6 5 N b95 Zr95 1131 Cs13 4 Cs' 3 7 Ba'40 La 14 0 Ce'4 4 2.92 +/- 0.39 9.25 +/- 0.96
<.022
<.045
<.024
<.022
<.046
<.026
<.050
<.039
<.031
<.037
<.075
<.020
<.100 0.61 +/- 0.17 7.48 +/- 0.55
<.011
<.037
<.014
<.014
<.026
<.015
<.028
<.023
<.012
<.019
<.052
<.007
<.075 4.15 +/- 0.38 8.09 +/- 0.70
<.015
<.036
<.007
<.015
<.034
<.010
<.049
<.040
<.018
<.011
<.062
<.021
<.101 0.64 +/- 0.21 5.41 +/- 0.62
<.017
<.060
<.016
<.022
<.033
<.024
<.046
<.023
<.021
<.020
<.064
<.014
<.168
-- page 108 of 119 --
CL-8 GRASS ACTIVITY (pCilg wet)
Date Collected 01 May 02 15 May 02 29 May 02 12 Jun 02 26 Jun 02 Be7 K40 Mn 54 Fess Co6s Zn 6 5 N b95 Zr95 1131 Cs1 3 4 Cs1 3 7 Ba14 0 La14 0 Ce14 4 Date Collected 1.40 +/- 0.30 7.28 +/- 0.76
<.015
<.058
<.017
<.025
<.057
<.016
<.048
<.042
<.021
<.021
<.137
<.014
<.119 10 Jul 02 2.26 +/- 0.34 6.48 +/- 0.68
<.022
<.042
<.022
<.019
<.036
<.024
<.051
<.040
<.019
<.021
<.108
<.019
<.172 17 Jul 02 0.82 +/- 0.25 5.70 +/- 0.62
<.016
<.023
<.011
<.018
<.024
<.011
<.033
<.030
<.018
<.023
<.085
<.011
<.094 1.16 +/- 0.26 5.50 +/- 0.58
<.016
<.027
<.014
<.019
<.043
<.012
<.051
<.018
<.015
<.024
<.077
<.015
<.086 1.16 +/- 0.18 5.16 +/- 0.47
<.012
<.023
<.012
<.012
<.031
<.009
<.036
<.022
<.011
<.014
<.064
<.007
<.093 31 Jul 02 14 Aug 02 28 Aug 02 Be7 K40 Mn54 Fess C 060 Zn65 N b90 Zr95 i131 Cs13 4 Cs1 3 7 Ba 14 0 La14 0 Ce14 4 1.63 +/- 0.37 7.61 +/- 0.84
<.026
<.057
<.030
<.016
<.064
<.026
<.038
<.044
<.026
<.023
<.150
<.014
<.190 0.63 +/- 0.31 8.10 +/- 1.02
<.035
<.042
<.019
<.024
<.058
<.030
<.061
<.039
<.020
<.031
<.107
<.017
<.195 1.94 +/- 0.22 5.43 +/- 0.48
<.017
<.024
<.012
<.017
<.044
<.013
<.023
<.035
<.015
<.022
<.079
<.014
<.090 1.59 +/- 0.24 2.88 +/- 0.35
<.014
<.024
<.011
<.012
<.021
<.009
<.033
<.015
<.013
<.011
<.061
<.011
<.128 4.80 +/- 0.44 7.53 +/- 0.77
<.022
<.057
<.023
<.027
<.049
<.031
<.023
<.026
<.025
<.019
<.108
<.014
<.171
-- page 109 of 119 --
CL-8 GRASS ACTIVITY (continued)
Date Collected Be7 K4 0 Mn54 Fess Cos Co6 0 Zn65 N b9s Zr95 1131 Cs1 3 4 Cs1 3 7 Ba14 0 La 14 0 Ce 14 4 11 Sep 02 25 Sep 02 09 Oct 02 3.90 +/- 0.53 13.73 +/- 1.19
<.036
<.053
<.024
<.021
<.084
<.021
<.040
<.048
<.024
<.034
<.135
<.022
<.316 2.40 +/- 0.40 7.03 +/- 0.85
<.020
<.030
<.021
<.016
<.056
<.014
<.043
<.045
<.017
<.029
<.134
<.024
<.137 3.86 +/- 0.47 6.84 +/- 0.89
<.026
<.071
<.029
<.027
<.059
<.035
<.032
<.055
<.041
<.029
<.150
<.025
<.193 23 Oct 02 2.70 +/- 0.43 7.16 +/- 0.86
<.025
<.044
<.024
<.021
<.029
<.025
<.031
<.037
<.018
<.035
<.103
<.030
<.127
-- page 110 of 119 --
CL-116 GRASS ACTIVITY (Control)
(pCilg wet) 01 May 02 15 May 02 29 May 02 Date Collected 12 Jun 02 26 Jun 02 Be7 K40 Mn 54 Fe 59 Zn6 5 N b95 Zr95 1131 CS134 Cs1 3 7 B a140 La 14 0 Ce 14 4 2.47 +/- 0.30 6.30 +/- 0.66
<.029
<.057
<.017
<.014
<.047
<.011
<.043
<.035
<.021
<.028
<.063
<.024
<.177 2.15 +/- 0.30 4.71 +/- 0.56
<.019
<.030
<.014
<.021
<.028
<.028
<.039
<.036
<.025
<.019
<.084
<.012
<.119 2.44 +/- 0.34 6.83 +/- 0.69
<.027
<.039
<.026
<.018
<.035
<.022
<.056
<.033
<.028
<.020
<.090
<.017
<.135 1.54 +/- 0.33 4.68 +/- 0.74
<.014
<.044
<.015
<.021
<.031
<.032
<.059
<.053
<.023
<.031
<.125
<.014
<.154 1.15 +/- 0.36 4.76 +/- 0.69
<.020
<.055
<.012
<.015
<.055
<.019
<.039
<.038
<.025
<.022
<.111
<.013
<.164 Date Collected 10 Jul 02 17 Jul 02 31 Jul 02 14 Aug 02 28 Aug 02 Be7 K4 0 Mn54 Fess 0058 Co60 Zn6 5 N b95 Zr95 1131 Cs 1 3 4 cS137 Ba 14 0 La 14 0 C e 144 0.48 +/- 0.25 5.68 +/- 0.78
<.026
- <.054
<.027
<.018
<.059
<.025
<.053
<.025
<.031
<.023
<.109
<.020
<.192 0.54 +/- 0.20 7.14 +/- 0.80
<.023
<.032
<.013
<.024
<.038
<.017
<.042
<.026
<.014
<.033
<.103
<.017
<.124 3.44 +/- 0.32 5.43 +/- 0.49
<.013
<.022
<.013
<.012
<.032
<.016
<.035
<.020
<.015
<.015
<.055
<.007
<.112 0.57 +/- 0.14 3.73 +/- 0.35
<.010
<.016
<.008
<.007
<.021
<.008
<.018
<.015
<.008
<.010
<.044
<.009
<.053 2.85 +/- 0.28 4.82 +/- 0.41
<.012
<.030
<.014
<.011
<.032
<.016
<.011
<.033
<.016
<.013
<.046
<.007
<.117
-- page 111 of 119 --
CL-116 GRASS ACTIVITY (Control) (continued)
Date Collected Be7 K 40 Mn 54 Fe 59 C Oo~
Zn65 N b95 Zr95 1131 Cs1 3 4 Cs1 3 7 Ba 140 La 140 Ce 14 4 11 Sep 02 25 Sep 02 09 Oct 02 23 Oct 02 6.78 +/- 0.51 15.38 +/- 1.03
<.028
<.067
<.024
<.024
<.042
<.038
<.049
<.034
<.028
<.030
<.097
<.011
<.210 0.49 +/- 0.20 6.43 +/- 0.65
<.026
<.045
<.022
<.016
<.050
<.016
<.023
<.040
<.023
<.019
<.133
<.020
<.176 2.24 +/- 0.30 6.42 +/- 0.58
<.018
<.031
<.017
<.018
<.032
<.018
<.033
<.039
<.018
<.023
<.078
<.010
<.176 1.75 +/- 0.26 5.41 +/- 0.47
<.013
<.019
<.007
<.016
<.019
<.013
<.030
<.024
<.014
<.017
<.062
<.011
<.127
-- page 112 of 119 --
CL-114 GREEN LEAFY VEGETABLE ACTIVITY (Control)
(pCi/g wet) 26 Jun 02 26 Jun 02 26 Jun 02 31 Jul 02 31 Jul 02 31 Jul 02 Date Collected Sample Type Gross Beta Be7 K40 Mn 54 Fe 5 9 Zn65 N b95 Zr95 i131 Cs1 3 4 cS'37 Ba 14 0 La14 0 Ce14 4 Date Collected Sample Type Gross Beta Be7 K4 0 Mn 54 Fe 5s Zn 6 5 NbWs Zr95 1131 Cs1 3 4 Cs1 3 7 Ba'4 0 La14 0 Ce14 4 Kale 5.71 +/- 0.13
< 0.14 5.38 +/- 0.43
<.012
<.032
<.014
<.008
<.026
<.009
<.017
<.021
<.011
<.013
<.056
<.012
<.075 28 Aug 02 Kale Kohlrabi Cabbage Cabbage Kohlrabi 5.66 +/- 0.12
< 0.19 4.81 +/- 0.60
<.015
<.041
<.022
<.020
<.042
<.017
<.033
<.027
<.022
<.023
<.066
<.016
<.136 4.63 +/- 0.12
< 0.10 4.03 +/- 0.31
<.011
<.019
<.008
<.006
<.015
<.007
<.013
<.016
<.008
<.008
<.041
<.004
<.072 2.89 +/- 0.08
< 0.11 2.99 +/- 0.39
<.013
<.026
<.010
<.009
<.022
<.019
<.017
<.025
<.015
<.014
<.039
<.022
<.050 3.93 +/- 0.11
< 0.10 3.54 +/- 0.30
<.009
<.015
<.007
<.005
<.015
<.011
<.028
<.021
<.012
<.007
<.049
<.005
<.051 Kale 5.55 +/- 0.17
< 0.21 4.42 +/- 0.37
<.010
<.026
<.011
<.009
<.021
<.009
<.011
<.017
<.009
<.010
<.038
<.006
<.071 28 Aug 02 28 Aug 04 24 Sep 02 24 Sep 02 24 Sep 02 Cabbage Kohlrabi Cabbage Kohlrabi 5.97 +/- 0.15 0.39 +/- 0.18 3.61 +/- 0.51
<.019
<.040
<.014
<.018
<.023
<.012
<.029
<.034
<.019
<.007
<.086
<.022
<.109 3.94 +/- 0.10
< 0.16 2.35 +/- 0.44
<.016
<.032
<.011
<.008
<.029
<.020
<.037
<.038
<.013
<.016
<.075
<.012
<.049 3.79+ +/- 0.06 0.27 +/- 0.08 3.18 +/- 0.25
<.005
<.012
<.005
<.006
<.012
<.008
<.011
<.018
<.004
<.005
<.048
<.011
<.052 3.00 +/- 0.06
< 0.07 2.20 +/- 0.22
<.005
<.013
<.006
<.004
<.012
<.007
<.008
<.011
<.007
<.008
<.031
<.005
<.043 4.50 +/- 0.12 0.48 +/- 0.22 3.81 +/- 0.57
<.013
<.042
<.011
<.017
<.015
<.009
<.024
<.036
<.016
<.013
<.088
<.012
<.082 Kale 4.37 +/- 0.09 0.24 +/- 0.13 4.49 +/- 0.51
<.018
<.019
<.015
<.016
<.031
<.009
<.023
<.034
<.012
<.013
<.064
<.011
<.088
-- page 113 of 119 --
CL-1 15 GREEN LEAFY VEGETABLE ACTIVITY (pCi/g wet)
Date Collected Sample Type 31 Jul 02 31 Jul 02 Lettuce Cabbage 31 Jul 02 28 Aug 02 Kohlrabi Lettuce Gross Beta Be7 K40 Mn54 Fe 59 C0s8 co60 Zn6 s N b95 Zr96 1131 Cs'34 Cs' 37 Ba14 0 La14 0 Ce'44 Date Collected Sample Type Gross Beta Be7 K40 Mn54 Fess 0060 Zn6 5 Nb95 Zr95 cS134 cS137 Ba14 0 La'4 0 Ce'44 5.44 +/- 0.17
< 0.26 6.31 +/- 0.73
<.018
<.034
<.019
<.024
<.037
<.027
<.048
<.039
<.020
<.024
<.108
<.022
<.199 28 Aug 02 Cabbage 2.80 +/- 0.06
< 0.14 2.48 +/- 0.33
<.012
<.023
<.011
<.005
<.017
<.010
<.023
<.022
<.015
<.013
<.042
<.020
<.083 2.78 +/- 0.08
< 0.14 2.76 +/- 0.37
<.017
<.018
<.012
<.006
<.028
<.017
<.033
<.027
<.016
<.012
<.055
<.015
<.084 28 Aug 02 Kohlrabi 4.75 +/- 0.12 0.25 +/- 0.13 4.04 +/- 0.35
<.011
<.024
<.007
<.011
<.017
<.011
<.028
<.021
<.012
<.012
<.045
<.006
<.073 4.02 +/- 0.12
< 0.14 3.58 +/- 0.43
<.010
<.028
<.013
<.012
<.019
<.012
<.019
<.019
<.013
<.011
<.057
<.015
<.099 24 Sep 02 Cabbage 3.85 +/- 0.08
< 0.17 3.64 +/- 0.42
<.013
<.034
<.013
<.009
<.027
<.011
<.017
<.038
<.017
<.017
<.071
<.020
<.103 5.71 +/- 0.15 1.53 +/- 0.33 5.46 +/- 0.66
<.023
<.056
<.013
< 030
.023
<.024
< 054
< 037
<.018
<.029
<.086
<.030
<.124 24 Sep 02 Kohirabi 4.05 +/- 0.08
< 0.13 3.96 +/- 0.38
<.012
<.016
<.009
<.013
<.019
<.012
<.010
<.019
<.014
<.012
<.062
<.007
<.077
-- page 114 of 119 --
CL-117 GREEN LEAFY VEGETABLE ACTIVITY (pCi/g wet)
Date Collected Sample Type Gross Beta Be7 K4 0 Mn 54 Fess Zn 65 Nb9s Zr95 1131 Cs1 3 4 Cs137 Ba14" La 14 0 Ce'44 Date Collected Sample Type Gross Beta Be7 K4 0 Mns4 Fe 59 co 58 Zn65 N b95 Zr95 1131 Cs134 Cs'37 Ba14 0 La14 0 Ce'44 26 Jun 02 26 Jun 02 26 Jun 02 31 Jul 02 31 Jul 02 31 Jul 02 Lettuce 5.66 +/- 0.13
< 0.08 4.64 +/- 0.44
<.009
<.030
<.012
<.010
<.019
<.015
<.034
<.018
<.013
<.008
<.041
<.014
<.046 28 Aug 02 Kohlrabi 2.90 +/- 0.06 0.19 +/- 0.10 2.55 +/- 0.28
<.006
<.022
<.009
<.008
<.020
<.005
<.020
<.009
<.010
<.010
<.040
<.004
<.066 Cabbage Kohirabi Kohirabi Lettuce Cabbage 4.09 +/- 0.09
< 0.12 4.71 +/- 0.58
<.014
<.027
<.013
<.020
<.034
<.014
<.031
<.019
<.017
<.012
<.049
<.030
<.059 5.88 +/- 0.13
< 0.22 5.19 +/- 0.62
<.023
<.050
<.013
<.019
<.028
<.011
<.039
<.031
<.016
<.017
<.103
<.017
<.170 3.18 +/- 0.09
< 0.11 2.79 +/- 0.34
<.006
<.020
<.009
<.006
<.020
<.014
<.021
<.021
<.014
<.010
<.053
<.006
<.047 5.05 +/- 0.05
< 0.23 7.36 +/- 0.73
<.022
<.027
<.016
<.019
<.029
<.018
<.052
<.048
<.025
<.017
<.100
<.017
<.145 2.57 +/- 0.07 0.17 +/- 0.10 2.80 +/- 0.29
<.010
<.027
<.011
<.007
<.026
<.007
<.022
<.014
<.010
<.006
<.045
<.007
<.051 28 Aug 02 28 Aug 02 24 Sep 02 24 Sep 02 24 Sep 02 Kale 6.04 +/- 0.13 0.70 +/- 0.20 6.04 +/- 0.66
<.014
<.052
<.016
<.024
<.029
<.012
<.039
<.036
<.021
<.020
<.099
<.013
<.056 Cabbage Cabbage Kohirabi 2.73 +/- 0.06
< 0.13 2.56 +/- 0.28
<.011
<.013
<.006
<.008
<.024
<.010
<.017
<.022
<.006
<.010
<.048
<.006
<.048 4.38 +/- 0.09 0.17 +/- 0.07 2.06 +/- 0.20
<.004
<.010
<.003
<.005
<.009
<.005
<.010
<.005
<.003
<.006
<.031
<.008
<.046 4.41 +/- 0.13
< 0.21 3.76 +/- 0.49
<.013
<.011
<.010
<.009
<.036
<.009
<.032
<.027
<.013
<.013
<.065
<.011
<.094 Kale 4.31 +/- 0.10 0.32 +/- 0.16 4.06 +/- 0.45
<.010
<.038
<.013
<.014
<.026
<.015
<.015
<.021
<.012
<.010
<.063
<.010
<.097
-- page 115 of 119 --
CL-118 GREEN LEAFY VEGETABLE ACTIVITY (pCi/g wet)
Date Collected Sample Type Gross Beta Be7 K4 0 Mn 54 Fe 59 cose Zn65 N b95 Zr95 1131 cS134 Cs' 37 Ba"40 La 14 0 Ce'44 Date Collected Sample Type Gross Beta Be7 K40 Mn 54 Fe 5s Co 6
0 Zn6 5 N b95 Zr95 1131 Cs' 3 4 cS137 Ba 140 La140 Ce'4 4 31 Jul 02 Lettuce 7.39 +/- 0.23 0.35 +/- 0.16 8.49 +/- 0.64
<.022
<.038
<.018
<.019
<.035
<.009
<.036
<.025
<.013
<.017
<.088
<.009
<.134 28 Aug 02 Kohlrabi 3.74 +/- 0.08 0.43 +/- 0.15 3.30 +/- 0.46
<.013
<.035
<.011
<.010
<.038
<.011
<.040
<.029
<.016
<.011
<.082
<.011
<.061 31 Jul 02 Cabbage 5.18 +/- 0.16
< 0.09 3.82 +/- 0.29
<.007
<.014
<.008
<.010
<.016
<.007
<.011
<.015
<.010
<.009
<.034
<.011
<.041 28 Aug 02 Cabbage 1.65 +/- 0.04 0.62 +/- 0.13 2.16 +/- 0.27
<.009
<.016
<.007
<.010
<.019
<.014
<.009
<.026
<.012
<.008
<.046
<.011
<.064 31 Jul 02 Kohlrabi 3.61 +/- 0.10 0.19 +/- 0.08 3.42 +/- 0.29
<.010
<.014
<.005
<.009
<.008
<.006
<.014
<.013
<.007
<.010
<.046
<.008
<.062 24 Sep 02 Cabbage 3.73 +/- 0.08
< 0.13 3.39 +/- 0.39
<.012
<.032
<.008
<.012
<.028
<.016
<.029
<.033
<.009
<.013
<.063
<.007
<.097 28 Aug 02 Lettuce 5.58 +/- 0.14 0.56 +/- 0.14 2.86 +/- 0.30
<.008
<.013
<.008
<.008
<.020
<.010
<.015
<.020
<.008
<.008
<.058
<.009
'.064 24 Sep 02 Kohlrabi 5.01 +/- 0.13 0.37 +/- 0.14 4.44 +/- 0.40
<.009
<.020
<.009
<.013
<.014
<.009
<.019
<.023
<.006
<.008
<.043
<.007
<.092
-- page 116 of 119 --
CL-19 FISH ACTIVITY (pCi/g wet)
Date Collected Type Be7 K4 0
Mn54 Fess Zn00 N b95 Zr95 Cs1'34 Cs137 Ba'4 0 La 14 0 Ce 144 15 Apr 02 Bluegill
< 0.15 2.81 +/- 0.36
<.009
<.037
<.007
<.012
<.024
<.023
<.017
<.008
<.009
<.165
<.028
<.080 15 Apr 02 Carp
< 0.05 2.67 +/- 0.26
<.008
<.010
<.007
<.006
<.008
<.010
<.011
<.007
<.008
<.040
<.012
<.035 15 Apr 02 Largemouth Bass
< 0.10 2.93 +/- 0.31
<.009
<.026
<.014
<.007
<.018
<.009
<.020
<.012
<.009
<.070
<.041
<.052 15 Apr 02 Striped White Bass
< 0.08 2.63 +/- 0.33
<.007
<.029
<.007
<.005
<.018
<.017
<.011
<.012
<.010
<.071
<.016
<.033 Date Collected Type 14 Oct 02 Carp 14 Oct 02 Largemouth Bass 14 Oct 02 Bluegill 14 Oct 02 White Bass Be7 K 40 Mn 54 Fes9
,c 60 Co 0
Zn05 N b95 Zr95 Cs134 Cs'37 Ba' 4 0 La 14 0 Ce'44
< 0.14 2.90 +/- 0.38
<.011
<.041
<.011
<.017
<.032
<.014
<.028
<.008
<.009
<.081
<.025
<.078
< 0.08 3.10 +/- 0.38
<.012
<.013
<.008
<.007
<.011
<.008
<.020
<.006
<.012
<.104
<.017
<.040
< 0.15 2.43 +/- 0.36
<.013
<.024
<.011
<.016
<.026
<.018
<.033
<.008
<.015
<.151
<.022
<.119
< 0.11 2.83 +/- 0.47
<.009
<.047
<.016
<.008
<.022
<.011
<.026
<.011
<.017
<.108
<.018
<.047
-- page 117 of 119 --
CL-105 FISH ACTIVITY (Control)
(pCilg wet) 15 Apr 02 15 Apr 02 15 Apr 02 Bluegill Bass Carp Date Collected Type 15 Apr 02 Crappie Be7 K4 0 Mn54 Fe 59 Cosa co 6
0 Zn65 N b95 Zr95 cS134 Cs'37 Ba14 0 La14 0 Ce'44 Date Collected Type Be' K40 Mn54 Fes9 co 6
0 Zn 6 5 N b95 Zr95 Cs'34 Cs' 37 Ba14 0 La14 0 Ce'44
< 0.22 3.09 +/- 0.53
- .012
<.018
<.011
<.012
<.026
<.018
<.043
<.012
<.014
<.142
<.074
- .078 10 Oct 02 Bass
< 0.13 3.10 +/- 0.46
<.014
<.019
<.006
<.015
<.026
<.016
<.014
<.019
<.007
<.078
<.026
<.068
< 0.13 2.62 +/- 0.38
<.008
<.026
<.011
<.006
<.020
<.014
<.019
<.014
<.010
<.095
<.035
<.044 10 Oct 02 Bluegill
< 0.06 2.94 +/- 0.27
<.006
<.024
<.005
<.007
<.009
<.009
<.016
<.005
<.007
<.072
<.008
<.048
< 0.12 2.89 +/- 0.39
<.013
<.015
<.012
<.014
<.033
<.013
<.027
<.013
<.012
<.105
<.046
<.043 10 Oct 02 Crappie
< 0.10 2.09 +/- 0.38
<.011
<.026
<.010
<.006
<.010
<.008
<.022
<.011
<.012
<.059
<.015
<.065
< 0.11 2.43 +/- 0.37
<.010
<.036
<.008
<.011
<.029
<.011
<.018
<.011
<.014
<.110
<.059
<.057 10 Oct 02 Carp
< 0.12 2.86 +/- 0.39
<.007
<.027
<.010
<.014
<.008
<.010
<.015
<.006
<.008
<.071
<.020
<.072
-- page 118 of 119 --
CL-7B SHORELINE SEDIMENT ACTIVITY (pC!/g dry)
Date Collected Gross Alpha Gross Beta Sr90 15 Apr 02 10 Oct 02
< 3.0 6.7 +/- 1.2 0.042 +/- 012
< 4.8 9.4 +/- 2.8
< 0.013 Be7 K40 Mn54 Fe"9 Co6 0 Zn65 N b95 Zr00 Cs134 Cs137 Ba 14 0 La 14 0 Ce144
< 0.13 5.90 +/- 0.45
<.011
<.035
<.016
<.009
<.033
<.012
<.025
<.017
<.013
<.070
<.008
<.050
< 0.10 5.86 +/- 0.40
<.009
<.031
<.012
<.006
<.022
<.016
<.027
<.016
<.010
<.058
<.016
<.048
-- page 119 of 119 --