RNP-RA/02-0077, Radiological Environmental Operating Report for 2001

Radiological Environmental Operating Report for 2001

ML021400493
Person / Time
Site:	Robinson
Issue date:	05/15/2002
From:	Fletcher B Carolina Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/02-0077
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TS 5.6.2 SCP&L A Progress Energy Company Serial: RNP-RA/02-0077 MAY 1 5 2002 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2001 Ladies and Gentlemen:

In accordance with H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, Technical Specification, Section 5.6.2, "Annual Radiological Environmental Operating Report," Carolina Power & Light (CP&L) Company is transmitting the Radiological Environmental Operating Report - 2001. This report is for the period of January 1, 2001, through December 31, 2001.

If you have any questions concerning this report, please contact Mr. C. T. Baucom.

Sincerely, B. L. Fletcher I3I Manager - Regulatory Affairs DJS/djs

Enclosure:

Radiological Environmental Operating Report - 2001 c: Mr. L. A. Reyes, NRC, Region II NRC Resident Inspector, HBRSEP Mr. R. Subbaratnam, NRR, NRC (w/o enclosure)

Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/02-0077 Radiological Environmental Operating Report - 2001

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2001 41 ROBINSON NUCLEAR PLANT CAROLINA POWER & LIGHT

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR THE H. B. ROBINSON STEAM ELECTRIC GENERATING PLANT, UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 JANUARY 1 THROUGH DECEMBER 31, 2001 Prepared by:

Sharon P. Langdon Reviewed by:

Gregory K. Barley

TABLE OF CONTENTS Title Page Table of Contents ...........................................................................................................................

List of Figures ................................................................................................................................ n List of Tables ................................................................................................................................. iio Executive Summary ........... ........................................... 1 Introduction to Nuclear O perations ....................................................................................... 3 Benefits of N uclear Power .................................................................................................. 3 Radiation and Radioactivity ................................................................................................ 4 Radiation Interaction with M atter .................................................................................. 6 Radiation Q ualities and U nits of M easure .................................................................... 7 Sources of Radiation ...................................................................................................... 8 Health Effects of Radiation ........................................................................................... 10 General Health Risk .......................................................................................................... 11 N uclear Power Plant Operations .................................................................................. 12 Plant System s .................................................................................................................... 15 Reactor Safety ................................................................................................................... 18 Radiological Environmental Monitoring Program ............................................................ 20 Purpose and Requirements for the Radiological Monitoring Program ......................... 20 General Site Description ................................................................................................ 21 Radiological M onitoring Program Quality Assurance ............... ............................ 22 Radiological M onitoring Program General Description .............................................. 23 Sum m ary of Radiological M onitoring Program ............................................................ 28 Interpretations and Conclusions ............................................. 37 Missed Sam ples and Analyses .................................................................................... 41 Analytical Procedures .................................................................................................. 42 Land Use Census ......................................................................................................................... 48 Purpose of the Land U se Census .................................................................................. 48 M ethodology ..................................................................................................................... 49 References .................................................................................................................................... 52 i

LIST OF FIGURES Figure Page I CP&L Service Area 3 2 2001 Energy Sources 3 3 The Atom 4 4 Radioactive Decay 6 5 Ionization 6 6 Radiation Ranges & Shielding 6 7 Source of Radiation Dose (BIER V) 9 8 Man-Made Radiation (BIER V) 10 9 Nuclear Fission 13 10 Nuclear Fuel Cycle 14 11 Fuel Pellets, Rods & Assemblies 14 12 Major Plant Systems for the Pressurized Water Reactor 15 13 Reactor Vessel 16 14 Primary Containment Structure 18 15 Location of Robinson Plant 21 16 Radiological Sampling Locations (Distant from Plant) 24 17 Radiological Sampling Locations (Nearest Plant) 25 18 Plot of Air Particulate Gross Beta Activity (Locations 1 and 2) 54 19 Plot of Air Particulate Gross Beta Activity (Locations 1 and 3) 55 20 Plot of Air Particulate Gross Beta Activity (Locations 1 and 4) 56 21 Plot of Air Particulate Gross Beta Activity (Locations 1 and 5) 57 22 Plot of Air Particulate Gross Beta Activity (Locations 1 and 6) 58 23 Plot of Air Particulate Gross Beta Activity (Locations 1 and 7) 59 24 Plot of Air Particulate Gross Beta Activity (Locations 1 and 55) 60 25 Plot of Surface Water Tritium Activity (Locations 40, 41, and 57) 61 26 Plot of TLD Averages for Inner and Outer Rings 62 ii

LIST OF TABLES Page Table Quality Factors for Various Types of Radiation 8 1

12 2 Reduction In Average Life Expectancy 23 3 Media Used to Assess Exposure Pathways to Man 26 4 Radiological Monitoring Sampling Locations 30 5 Radiological Environmental Monitoring Program Data Summary 35 6 Radioactivity in Environmental Samples Attributed to Plant Operations 36 7 Reporting Levels for Radioactivity Concentrations in Environmental Samples 46 8 Typical Lower Limits of Detection (a priori) for Gamma Spectrometry 51 9 Land Use Census Comparisons (1999-2000) Nearest Pathway (miles) iii

EXECUTIVE

SUMMARY

The Robinson Nuclear Plant is operated by Carolina Power & Light (CP&L), A Progress Energy Company, under a license granted by the Nuclear Regulatory Commission (NRC). Provisions of the Nuclear Regulatory Commission's Regulatory Guide 4.8, Robinson Nuclear Plant Technical Specifications, and the Robinson Nuclear Plant Off-Site Dose Calculation Manual establish the requirements of the Radiological Environmental Monitoring Program. This report provides the results of the Radiological Environmental Monitoring program from January 1, 2001 through December 31, 2001.

The Radiological Environmental Monitoring program was established in 1973. Radiation and radioactivity in various environmental media have been monitored for more than 28 years.

Monitoring is also provided for control locations which would not be impacted by operations of the Robinson Nuclear Plant (RNP). Using these control locations and data collected prior to operation allows comparison of data collected at locations near RNP which could potentially be impacted by its operations. Radiation levels show no measurable change from pre-operational radiation levels.

Monitoring results for environmental media are summarized as follows:

results are similar or less than the concentrations of radioactivity from pre operation monitoring. These observations are also consistent with past operational data.

conducted due to the unavailability of milk samples in the monitoring has not been SMilk area since July 17, 1998 when the dairy ceased operations. Broadleaf sampling is conducted, since no milk animals are located within five miles of the plant in any sector.

Milk sampling will resume if a new sample location is identified.

broadleaf vegetation and food crops. Results indicate vegetation includesSTerrestrial detectable concentrations of Cs-137 in both the indicator and control locations for broadleaf vegetation. No other gamma activity was detected in any samples, except for K-40, which is naturally occurring. Sampling of miscellaneous food products (non-leafy) in the vicinity of the site is conducted when leafy vegetables are not being grown.

> Aquatic organism monitoring includes fish and aquatic vegetation. Results indicate detectable concentrations of Cs-137 and K-40 in both indicator and control locations for fish, while aquatic vegetation results indicate detectable concentrations of Co-58, Co-60, and Cs-137 in indicator samples.

) Surface water results indicate that the surface water from Lake Robinson shows the presence of tritium, which is attributed to plant operation.

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External radiation dose showed no measurable change from pre-operational data.

- Sediment monitoring includes both shoreline and bottom sediment. During 2001, no gamma activity associated with plant operations was detected in any shoreline sediment sample. Bottom sediment results indicated the presence of Cs-137 and Co-60. No other gamma activity was detected in any sediment sample.

The continued operation of RNP has not significantly contributed radiation or the presence of radioactivity in the environmental media monitored. The measured concentrations of radioactivity and radiation are well within applicable regulatory limits.

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INTRODUCTION TO NUCLEAR OPERATIONS Carolina Power & Light (CP&L), A Progress Energy Company, operates an integrated electrical system serving more than one million customers in North Carolina and South Carolina. A system map is provided (Figure 1) that illustrates the area served and the location of the nuclear generating units including the Harris (Blue), Brunswick (Green), and Robinson (Brown) Nuclear Plants. The service area is more than 30,000 square miles and has a population of more than 4.200.000 I I peonle.

• I- -

Figure 1: CP&L ServiceArea The energy sources (Figure 2) for electrical generation include coal, fuel oil, natural gas, hydro-power, and nuclear fuel. No one energy source is best. Each fuel source has merits and disadvantages. Fossil fuels pose issues associated with clean air including emissions of sulfur dioxide and oxides of nitrogen. Both natural gas and hydro-power are in limited supply.

Nuclear energy is a vital component in a diversified energy mix. In 2001 nuclear energy supplied 44.96% of CP&L's total electrical generation. This nuclear component was El Nuclear generated from four units including the Robinson Coal Nuclear Plant. The remaining energy sources Oil & Natural Gas were primarily from coal-fired generation, and a Hydro Power very small contribution from oil, natural gas and Figure 2: 2001 Energy Sources hydro-power.

BENEFITS OF NUCLEAR POWER Nuclear energy is a viable, clean, safe, and readily available source of energy. The operation of RNP results in a very small impact on the environment. Nuclear generation serves a vital role in the operation of the Carolina Power & Light system as well as in the nation's electrical needs.

Nuclear energy currently supplies approximately twenty percent of the nation's electrical generation. It is an important source of electrical energy now and is meeting the growing electrical needs for the future. Nuclear energy has the following advantages over other fuel sources:

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The fuel is uranium, which is relatively inexpensive when compared with the fuels of coal, natural gas, and fuel oil.

, Emissions from nuclear stations do not include sulfur dioxide, oxides of nitrogen, or carbon dioxide. Sulfur dioxide is well known as a significant contributor to acid rain leading to acidification of streams and lakes. Oxides of nitrogen play a key role in the formation of ozone, which is a significant pollutant in urbanized air quality. Finally carbon dioxide is a significant greenhouse gas.

energy is safe. Nuclear power in the United States has an excellent safety SNuclear record, starting with the first commercial nuclear plant in 1957.

To better understand this source of energy, a basic understanding of radiation, its effects, risk assessment, and reactor operation follow.

RADIATION AND RADIOACTIVITY The Atom All matter consists of atoms. An atom is the smallest units into which an element can be divided and still

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-The retain its identity as that element. An atom is made up of a number of different particles. These particles are neutrons, and electrons. Each proton is positively charged (+). Each neutron has no charge.

electron is negatively charged (-). The heavier I ' o ,particles including protons and neutrons are found in the center of the atom in a very small cluster referred to as the nucleus. (The term nuclear refers to this Figure 3: The Atom nucleus.) Nearly all the mass of the atom is found in the nucleus. Electrons orbit the nucleus. Since the atom is electrically neutral (no charge) the number of protons and electrons in the atom are equal (see Figure 3 a conceptional drawing of an atom). The electrons (red) are shown in orbit around the nucleus. The protons (green), and the neutrons (black) are shown in the nucleus at the center of the atom.

Elements, Isotopes, and Radionuclides Simple substances that cannot be decomposed in any chemical reaction are known as elements.

Hydrogen, oxygen, iron, chlorine, and uranium are examples of elements. The atoms of such elements differ in the number of protons (also know as the atomic number) in their nucleus. For example the number of protons in each example above is 1 for hydrogen, 8 for oxygen, 26 for iron, 17 for chlorine, and 92 for uranium. The number of neutrons in the nucleus may vary in atoms of the same element. Atoms that contain the same number of protons but a different number of neutrons are referred to as isotopes of that element. An example is the element hydrogen, which has three isotopes--one with no neutrons, a second with one neutron, and the 4

third with two neutrons. Isotopes can be unstable (also referred to as radioactive), which means they will readily transform to another isotope and are called radionuclides. Of more than one thousand known isotopes less than twenty-five percent are considered stable. It is important to remember that a significant number of radioactive isotopes occur naturally. When referring to isotopes of an element, it is common to refer to the element by the symbol for its name (or the name) followed by the total number of protons and neutrons, for example H-3 or hydrogen-3 describing an atom with one proton and two neutrons.

Radiation Radiation is defined as the conveyance of energy through space. This conveyance may occur in the form of particles, waves, or photons. Some common forms of radiation are sunlight, microwaves, or radio waves. These are all examples of non-ionizing radiation. Ionizing radiation differs in its interaction with matter because its energy is capable of removing an electron from the outer part of an atom resulting in the remaining atom being positively charged and a free electron. There are two types of ionizing radiation--particulate radiation and electromagnetic radiation. Particulate radiation is energetic particles which will travel in a straight line if unhindered. Three types of particulate radiation are of interest in nuclear energy, those being beta particles which are high-energy electrons (not part of an atom), neutrons, and alpha particles which consist of two protons and two neutrons. Electromagnetic Radiation is high- energy waves (or photons) which have no apparent mass (not a particle). There are two types of electromagnetic radiation of interest which are gamma rays and X-rays. Gamma rays have their origin in the nucleus of the atom. X-rays have their origin in the stored energy of the electrons orbiting the nucleus. There are many important differences in the behavior of these types of radiation which will be discussed in the later sections.

Radioactivity Radionuclides are atoms that are unstable and will eventually reach a stable state through a process know as radioactive decay. This process results in the emission of energy or energetic particles from the nucleus of the unstable atom. The process may occur in a single step or may be composed of a series of steps to various radioisotopes. When this process proceeds through a series of steps it is called a radioactive decay series.

There are at least three natural radioactive-decay series which are the thorium, neptunium, and the uranium series. These radioactive decay series as well as naturally occurring K (potassium) 40, C (carbon)-14, H (hydrogen)-3 are significant contributors to background radiation levels, which are addressed in greater detail later.

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The rate at which atoms undergo radioactive decay II varies greatly. A common expression of the tendency for radioactive decay is the half-life associated with a particular isotope. The half-life is the amount of time required for one-half of the number of atoms for an isotope to experience 1'/2 radioactive decay. The longer the half-life the less likely an atom will experience radioactive decay in 1/4 a fixed time interval. Half-lives vary from 1/8 I II extremely small fractions of a second (billionths) 1/16 to millions of years.

0 140 280 420 560 700 Figure 4 illustrates an isotope with a 140-day half Time. days life. Note that the activity decreases by half in 140 Figure 4: Radioactive Decay days, and then by half again the next 140 days and thereafter.

RADIATION INTERACTION WITH MATTER Ionization As alpha, beta, gamma, and X-ray radiation interact with matter they impart part or all of their energy to the matter in a single interaction. It may require many interactions to i. e- EJECTED ELECTRON absorb the energy of a single particle or photon of radiation. One of the most common ways energy is dissipated is ionization. As we discussed earlier this results in the creation of a positively charged atom and a free electron (see Figure 5). The positively charged atom and the free electron are referred to as a charged pair. The Figure 5: Ionization creation of the charged pair is one of the primary contributions to damage of biological systems.

Radiation Ranges Each type of radiation we have discussed interacts with the matter they travel through differently (Figure 6) because of the different characteristics of each radiation. BGph......

Alpha particles are composed of two protons and two neutrons. This is the heaviest particulate radiation with a positive charge of two (two PAPER ALUMINUM LfAD protons). The alpha particle is the slowest of the types of radiation we will review, Figure 6: Radiation Ranges & Shielding 6

with a speed of no more than 20,000 miles per second. As a result of these characteristics the alpha travels only a few centimeters (or inches) in air and is readily stopped by a sheet of paper.

The alpha leaves its energy in a short distance characterized by a great many ionizations.

Beta particles are basically a very high-energy electron. Beta particles have a negative charge. It is a very light particle, with a mass of about one two- thousandth of a proton (or about one eight thousandth of an alpha particle). Beta particles are very fast, approaching the speed of light.

Due to their speed and lower charge, the beta particles travel several meters (or yards) in air and its are readily stopped by a small piece of metal or other dense material. The beta particle leaves energy in many ionizations but with the ionizations distributed along a much longer path of travel.

Gamma rays are photons (or energy waves, not a charged particle). Like light (also a photon) it travels at a speed of approximately 186,000 miles per second. The gamma ray travels much larger distances without interacting. When the gamma ray interacts with matter it creates very high-energy electrons similar to beta particles which in turn create ionizations as their energy is dissipated. Due to these differences the gamma ray travels much greater distances before its energy is dissipated. To dissipate the energy of a gamma ray several inches of lead are required.

RADIATION QUALITIES AND UNITS OF MEASURE There are numerous qualities and units used to describe radiation and radioactivity and their effects. Those used in this report relate to activity, absorbed dose, and dose equivalent. It is also common to express numbers in scientific notation or use prefixes with the number denoting the number of zeros (0) before or after the decimal. A few examples are provided below.

Prefix Number Represented Number in Scientific Notation pico .000000000001 1x 102

.000000001 1x 10. 9 nano

.000001 1x 10-6 micro

.001 1x10-3 milli centi .01 1X10-2 1,000. Ix 103 kilo lx106 mega 1,000,000.

in a Activity is the number of radioactive transformations (decays, disintegrations) that occur as fixed time interval. The unit used to express activity is the curie. The curie is defined s-i). A curie is a unit of 37,000,000,000 disintegrations per second; (also expressed as 3.7xI10 activity, not an amount of material or the number of atoms. The amount of material or number 7

of atoms necessary to produce a curie of activity vary over a very wide range. Atoms with very long half-lives would require many more atoms to produce a curie of activity versus atoms with short half-lives.

Absorbed dose describes the energy absorbed per unit of mass of tissue. The unit used to express absorbed dose is the rad (radiation absorbed dose). One rad is an absorbed radiation dose of 100 ergs (a measure of a very small amount of energy) per gram. The rad can be used with all types of radiation including X-rays, gamma-rays, and particulate radiation. The absorbed dose can be measured with various radiation-detection instruments which allow the assessment of damage to biological systems subjected to radiation and radioactive materials.

Dose equivalent is an expression of the biological effect of the radiation on tissue. The unit used to express absorbed dose equivalent is the rem (radiation equivalent man). Dose equivalent is obtained by multiplying the absorbed dose (expressdd in rad) by a quality factor (QF) for the type of radiation being considered.

Dose equivalent = absorbed dose X quality factor Some types of radiation create more biological damage due to the extent of ionization in small areas. From our discussion of alpha particles, the intense ionizations caused by the alpha particle results in a much higher Quality Factor for this radiation. This relationship for quality factors and different types of radiation we have presented in Table 1.

Table 1 Quality Factors for Various Types of Radiation Radiation Quality Factor Gamma-rays I X-rays 1 Beta Particles 1 Alpha Particles 20 SOURCES OF RADIATION Background Radiation Radiation occurs naturally and is an everyday fact of our existence. Mankind has always lived with radiation and radioactive materials and will continue to in the future. The radiation that occurs naturally is referred to as background radiation. Mankind experiences two types of radiation dose: first is radiation that originates outside the body and is called external radiation, and the second is radiation that originates inside the body and is called internal radiation.

External radiation comes from the earth, the atmosphere, and every structure (buildings) around us as well as a source referred to as cosmic radiation which is generated in the stars throughout the galaxy including our own sun (see Figure 7).

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Cosmic radiation is composed of gamma-rays (some of very high energy) and many different types of energetic particulate radiation. Some of the particulate forms of radiation include neutrons, alpha particles, and heavy particles (including nuclei). High-energy cosmic radiation has the capability to interact with other atoms on earth and generate new isotopes. As we have already discussed, some of these may be radioactive. Common examples of radionuclides formed from cosmic radiation are carbon-14 and tritium (H-3). The atmosphere around the earth serves as an effective shield causing much of the energy of cosmic radiation to be dissipated prior to reaching the surface of the earth. However, each of us may receive a dose equivalent, due to external cosmic radiation, of 20 to 50 mrem (0.020 to 0.050 rem) annually. The actual dose is influenced by the elevation which we live. Higher elevations provide less shielding and therefore the doses are higher. A single plane flight can also contribute to our dose from cosmic radiation. The average passenger could expect to receive a dose of 2.8 mrem (0.0028 rem) per flight.

Source of Radiation Dose Another important contributor to external absorbed dose is terrestrial radiation (Figure 7). This is the radiation from the earth itself and the air around each of us. The sources of terrestrial radiation include the thorium, neptunium, and the uranium decay series as well as potassium-40. The absorbed dose varies from about 15 to 140 mnrem (0.015 to 0.140 rem) annually. However, there are a very few areas that these terrestrial absorbed doses exceed 800 mrem each year.

El Radon 0 Terrestrial 0 Cosmic U Internal One of the most important sources of dose is U Man-made that contributed by internal radiation. These radionuclides are part of our body, the air we have breathed, or the food we have consumed. Figure 7: Radiation Sources (BIER V)

One of the most significant contributors is radon (Figure 7). Radon is a radioactive gas that is part of the uranium decay series. Radon's concentration varies greatly based upon the geology of each community, but is found in soils and rock everywhere. If it is allowed to concentrate in a building, the dose from radon can be increased significantly. Normally radon does not pose a significant health threat. Since radon is an alpha particle emitter, inhaling radon gas makes the lung our greatest concern (i.e. the alpha does not travel far but has a high quality factor for the affected tissue) The health effect of breathing radon is an increased risk of lung cancer.

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Man-made Radiation Man-made radiation isimportant to completing our understanding of sources of radiation (see Figure 8).

An important aspect in discussing man-made radiation is the benefit man derives from the use of these.

Medical uses of radiation are the major contributor, including diagnostic X-ray, and nuclear medical treatment. Consumer Consumer products products such as televisions, Nuclear Medicine display screens, smoke detectors, and many other devices are the next most important class of man-made radiation. Fallout from prior weapons testing is now a small contributor to total radiation dose.

L] X-Rays U Nuclear Medicine Occupational exposure is also a 0 Consumer Products Fallout factor from the medical,

• Occupational U Misc. & Nuclear manufacturing, and nuclear Figure 8: Man-Made Radiation Sources (BIER V) industries. Finally, contributions from nuclear plant operations represent less that 1% of the man made radiation for the average member of the general public. The data presented in figure 8 illustrates the importance of the different sources of man-made radiation for the average member of the public.

HEALTH EFFECTS OF RADIATION The effects of ionizing radiation have been of concern to the scientific community for several decades. The oldest body established to study biological effects of radiation dates from at least 1928 with the establishment of the International Commission on Radiological Protection. Much of our knowledge is based upon very high doses associated with animal experiments, accidents handling radioactive materials, and war time nuclear weapons use. It has been a classical problem of how to relate doses at these levels to much lower medical use (although some treatments are designed to deliver high dose) and occupational radiation levels. Environmental levels of radiation represent even greater challenges because of the extremely low doses compared with medical and occupational levels. Experiments with animals represent additional challenges because they may not accurately represent human biological responses to radiation.

Biological effects of radiation are classified as somatic and genetic (or hereditary). Somatic effects are observed in the individual receiving the radiation dose. Genetic effects are observed in the decedents of the individual receiving the radiation dose.

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Somatic effects can be classified as acute or chronic. Acute effects occur within a short time (days) after the dose is received. Generally, acute effects require very high doses. Blood changes can be have been observed in the range of 25 to 50 rem (or 50,000 mrem). Other acute effects of nuclear expected at even higher doses. Our knowledge of this level of dose are the survivors are more than weapons, accidents, and planned nuclear medical treatments. These dose levels are not 500 times normal environmental background radiation. For this reason, these effects important to a discussion of environmental radiation.

long period of time, Chronic effects are generally used to refer to effects that are observed over a generally associated and these have also been referred to as delayed effects. The effects are also However, it is not with radiation dose received over a long period known as chronic exposure.

effect is necessary for the exposure to occur over a long period. The most significant chronic low doses (at cancer. There are numerous forms of cancer. The rate of cancer in individuals at by occupational or environmental levels) has not been observed directly. "Cancers induced existence can be radiation are indistinguishable from those occurring naturally; hence their practice inferred only on the basis of statistical excess above the natural incidence." The current cancers at that dose and then is to use observations at a much higher dose to establish the rate of a

assume that the rate of cancers must be proportional to the lower dose. This has created method over-estimates the cancer scientific disagreement because some scientists believe this Some risk from low doses of radiation. However, this appears to be a conservative assumption.

The Committee risk exists, but it is believed to be a small risk of cancer at occupational levels.

clear whether dose of the Biological Effect of Ionizing Radiation further states "It is by no means rates of gamma or X-rays of about 100 mrad per year are in any way detrimental to exposed or less as we people...". Environmental radiation levels are in the range of 100 mrad per year have discussed.

As we have Genetic radiation effects occur when radiation changes the genetic material in cells.

atom. These electrons are discussed, the process of ionization removes electrons from the the genetic sometimes necessary in the creation of chemical bonds. If the bonds are part of material (mutations). Radiation is just one material of the cell, it could result in changed genetic that occur of several agents that contribute to genetic change. Chemicals, including those levels only naturally, are a significant contributor to genetic mutations. Background radiation mutation (from all provide a minor contribution to total mutations. To double the general This is sources) rate would require a dose of 50 to 250 rem (or 50,000 to 250,000 mrem).

of about 100 mrem.

approximately 500 to 2,500 times the normal environmental background GENERAL HEALTH RISK we eat, where we Every human activity has risk associated with it. The air we breathe, the food risks is quite different live or work all have different risks. Many times our perception of these regarding the than the real risk of an activity. There was widespread fear and misunderstanding is accepted as part of fire and safety hazard from electricity early this century. Now electricity or detected by our daily existence. Radiation is unique in that it cannot be seen, felt, smelled, 11

any of the human senses. It is detected by instruments or laboratory analysis specially designed to detect radiation. Thus it is understandable to be wary of something we cannot readily sense and may not have a personal knowledge about. There are other similar hazards we tend to accept such as microwave radiation, carbon monoxide in the operation of some furnaces, and our vehicles due to our familiarity with these.

A common way of expressing risk is a reduction of life expectancy from a particular activity.

Below is Table 2 presenting common activities and the associated reduction in life expectancy.

Table 2 Reduction in Average Life Expectancy Activity Reduction in Life Expectancy Cigarette Smoking 2 Packs/Day 10 Years Cigarette Smoking 1 Pack/Day 7 Years Heart Disease 5.8 Years Living in City Versus Rural 5 Years Overweight 30 % 3.6 Years Cancer 2.7 Years Commercial Nuclear Power 12 Minutes NUCLEAR POWER PLANT OPERATIONS The primary difference between a nuclear generating station and fossil generating station is the source of heat or thermal energy. The steam turbine, condenser, condensate and feed water systems are much the same. The uranium fuel within the nuclear reactor is the source of heat or energy in the nuclear generating station.

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Nuclear Fission Certain heavy radionuclides are known to naturally undergo a special form of radioactive decay, called spontaneous fission. Spontaneous fission means the nuclei of these radioisotopes literally split into two or three new nuclei (also known as fission fragments) and a few free neutrons (not in a nucleus). The protons and neutrons are shared between these new nuclei. One isotope of uranium known a U-235 is known to undergo fission. The other more common isotope of uranium known as U-238 does not fission so easily.

Fission can also be stimulated by neutrons interacting with the nucleus of these atoms (see Figure 9). Simply stated a neutron reaches the nucleus and produces fission fragments, free neutrons, and heat. Fission of uranium produces more than one neutron per fission. Therefore, if there is enough uranium (especially U-235) present it is possible to produce more fissions and keep the process going or cause more and more fissions to occur. When the rate of fission initiated is self-sustaining or increasing, a chain reaction has been established. It is this sustained chain reaction and the energy produced that produces the heat needed to generate steam for electrical generation.

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Fission Fragment Figure 9: Nuclear Fission 13

Uranium Fuel Uranium ore is mined from the earth the same as many minerals (see Figure 10). This uranium ore is then taken to a mill to concentrate the uranium. The extraction process for uranium uses acids to dissolve the uranium and separate it from the ore. This uranium is then converted chemically to a gas uranium hexafloride (in chemical notation UF6). While in this form it is possible to separate the lighter U-235 SNUCLEAR FUEL CYCLE from the heavier U-238. This process of separation is called gaseous NC diffusion. The reason for separation is to allow more of the U-235 to be included in the fuels used in MINE MILL CONVERTER commercial reactors. We have already discussed that U-235 fissions more readily that U-238. This process that increases the amount of U-235 is also referred to as enrichment. After enrichment this gas is chemically converted to REACTOR FUEL FABRICATOR ENRICHER uranium dioxide (in chemical OIFFUSION PLANT)

(GASEOUS notation U0 2). At this point the uranium dioxide is a gray powder.

Fuel Cycle Figure 10: The Nuclear The powder is then processed under high pressure, and PELLET temperature to create a ceramic pellet of uranium dioxide.

This process is part of the fuel fabrication. The fuel fabricator also ensures that each fuel pellet also has the proper amount of U-235 and U-238. The additional U-235 added is referred to as the percent enrichment which for commercial reactors is about 5% of the total uranium in the fuel. These fuel pellets are placed into long tubes of zirconium alloy or fuel rods. These rods of uranium fuel are then placed with other such fuel rods into a fuel assembly (see Figure 11). This fuel assembly is the basic unit that is shipped to the nuclear power plant. It is important to note that the entire process of making nuclear fuel is carefully controlled to ensure the quality of the nuclear fuel.

ROD ASSEMBLY Figure 11: Fuel Pellets, Rods &

Assemblies 14

PLANT SYSTEMS System Summary There are four (4) groupings of major plant systems which are the reactor, the turbine generator, the condensate and feed water systems, and various support systems including various emergency systems (see Figure 12). The reactor, with its nuclear fuel, is the source of heat to generate high pressure steam. The turbine is a large rotating fan-like machine that the steam causes to rotate. The turbine is connected to an electrical generator which produces a rotating magnetic field. Electricity is generated in winding of metallic conductors around this magnetic field and then transmitted to the electrical transmission system, and distributed to the customers in the service area and neighboring utilities.

After the steam has spent most of its energy in the turbine, water vapor remains and must be recovered for reuse. The water vapor is recovered as water in a condenser. The condenser is a large system of tubes that are water cooled. The water used to cool the condenser is one of the most visible features at any power plant. Either large quantities of water are used or a cooling tower is used. After the steam has been recovered as water it is returned through a system of pumps, piping, and heaters to the steam generator. The process of reusing this water and steam in a continuing cycle is referred to as the steam cycle.

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Figure 12: Major Plant Systems for The Pressurized Water Reactor 15

Reactor Types and the Reactor Vessel There are more than 100 commercial nuclear reactors being used to generate electricity in the United States today. Of these, there are two basic types of reactor in use today, the cont rod drive mechanism Pressurized Water Reactor (PWR) and the irnort Boiling Water Reactor (BWR). The basic difference is the point where steam is formed. The boiling water reactor forms upper support plate steam in the reactor while the pressurized rod c

water reactor forms steam through a separate inlet nozzle c-trel rod luster heat exchanger called a steam generator.

The Robinson Plant is a Pressurized Water ppe care plate types of Reactor (PWR). There are other reactors used for research and military reactor vessel purposes.

lower core plate The collection of fuel assemblies is referred tinstrumentation thimble to as the reactor core. The Robinson Plant has 157 fuel assemblies in the reactor core.

The reactor core, the controls, Figure 13: Reactor Vessel instrumentation; as well as other components, are located in the reactor vessel (see Figure 13). The components vary greatly by reactor type. The reactor vessel is a specially designed container which supports all of the components. The reactor vessel is 9.31 inches thick of steel with a stainless steel lining.

The rate of nuclear fission is controlled by neutron absorbing materials. One of the most common materials used is an isotope of boron known as boron-10 (B-10). Also control rods are used that are made of other materials including indium and cadmium. By controlling how much of the control rods are inserted in the reactor core the rate of nuclear fission is controlled. The Robinson Plant has 20 control rods per assembly.

The boiling water reactor generates steam with a significant water fraction and this steam must have this water removed. The reactor vessel for the boiling water reactor contains a steam separator which removes most of the water fraction. After treatment by the steam separator the steam passes through a steam dryer to remove additional water. The water removed by the steam separator and dryer is returned to the water in the reactor vessel. The boiling water reactor also has a special pair of recirculating pumps that provide additional control of steam generation and reactor power.

The pressurized water reactor does not generate steam in the reactor. The reactor vessel is pressurized to prevent boiling from occurring in the reactor or the reactor vessel. Steam is generated in a heat exchanger called the steam generator. The steam and the water from which steam is generated is a separate water system from reactor water or reactor coolant. This 16

separate water system is referred to as the secondary system while the reactor's water system is referred to as the primary system. In the pressurized water reactor it is this secondary water that steam is made from and recycled through the condenser and feedwater system. This water is returned to the steam generator.

The PWR steam generators serve as the point of steam production. The reactor water of the primary system is not allowed to boil or produce steam. This primary system water (or coolant) is circulated to the steam generators and back to the reactor in a continuous cycle. While in the steam generator the primary coolant (or water) transfers some of its heat or energy to the secondary coolant (water) by heating the secondary coolant and making steam with the secondary coolant. It is important to note that there is no exchange of water between the primary coolant and the secondary coolant. This process is made possible because the pressure in the primary (reactor) systems are maintained at a point which prevents boiling in the reactor.

The pressurizer is the system that supports regulation of reactor pressure. The pressurizer is a vessel partly filled with water and is in free exchange with the water in the reactor and primary systems. The pressurizer also allows for the volumetric expansion of the primary coolant (water) as the reactor starts up, while maintaining the pressure of the reactor.

Sources of Radioactive Materials In Reactor Operation There are two primary means that radioactive materials are produced in reactor operation which are:

produces two or more fission fragments in each fission. These fission fragments become the nuclei of new atoms as fission products. As we have already discussed many atoms are radioactive as is the case with these fission fragments. Examples of these isotopes are iodine-131 (1-131), strontium-90 (Sr-90), cesium-137 (Cs-137), as well as others.

nuclei occurs in the neutron field in the reactor. This occurs of normally stable SActivation because neutrons are absorbed by the nucleus of an atom, and a new isotope of that atom is created. The new isotopes may be radioactive. Examples of these isotopes include tritium (H-3) and cobalt-60 (Co-60). These radionuclei are referred to as activation products.

The potential sources of radioactive emissions from nuclear power operations involve the treatment of water from the reactor systems, the treatment of air in the buildings that house plant systems, and the condenser vacuum system. Each of these emissions is managed to reduce the emissions to levels that are considered as low as reasonably achievable. The radiological monitoring program is designed to assess the impacts of these emissions even though they are acknowledged to be small contributors to background radiation.

17

Barriers to Release of Radioactive Materials containment structure There are several barriers to release of radioactive materials. In order these are:

> the ceramic fuel pellet itself

> the zirconium cladding of the fuel rod steam lines steam ie

> the reactor vessel and its associated gen rators t piping piigcontrol rods .W- :

> the containment building The fuel, fuel rods, and the reactor vessel have already been discussed. The containment building is illustrated in figure

14. The containment houses the reactor core, the reactor vessel and its associated piping, reactor coolant pumps and the pressurizer.

reactor core Figure 14: Primary Containment Structure REACTOR SAFETY There are several points regarding nuclear safety that are important to understand, and these are:

SCommercial nuclear generating stations can not explode like a nuclear weapon. The uranium for weapons is highly enriched and must be carefully timed and configured to create an explosion. The uranium in commercial generating stations is low enrichment and can not be configured to create a nuclear explosion.

reactor control system regulates the power output of the reactor by controlling the rate of nuclear fission. This is accomplished by inserting or withdrawing control rods or by the addition of neutron absorbing materials. A special safety system is part of the reactor control system call the reactor protection system which will cause the control rods to be quickly inserted. This insertion causes the nuclear chain reaction to stop.

There are numerous sensors that measure different plant conditions that would cause the reactor protection system to activate.

SThere that provide adequate cooling of the reactor in the are several emergency systems event of a loss of coolant. Should there be breakage of piping carrying water to the reactor, this is referred to as a Loss of Coolant. Accident systems are activated upon a 18

drop in reactor pressure or a low level of water in the reactor. The exact activation varies by reactor type. The systems that deliver this supplemental source of water to the reactor are referred to as the Emergency Core Cooling System. There are even backup systems to the individual Emergency Core Cooling Systems. This practice is referred to as a defense in depth. Safety is not dependent on any one device, but is a system of several backup devices.

The Robinson Nuclear Plant is designed to be a safe means of generating electrical power. This level of safety is further enhanced through the discipline of operation provided by a well qualified and trained staff. Ongoing training is provided to the staff to ensure a high quality performance from each member of the plant staff. Although the requirements are high for the staff, reactor operators and senior reactor operators must also pass a rigorous license examination by the Nuclear Regulatory Commission on a regular basis. These examinations test knowledge of plant systems, design, procedures, problem solving, regulatory requirements, and the ability to function as a team responding to plant conditions.

19

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PURPOSE AND REQUIREMENTS FOR THE RADIOLOGICAL MONITORING PROGRAM Although the operation of a nuclear generating station results in the raising of background radiation only a small amount, it is important to measure these emissions of radioactivity and radiation to assess their impact on the surrounding populations. The purpose of the radiological monitoring program is to measure accumulation of radioactivity in the environment, to determine whether this radioactivity is the result of operations of the Robinson Plant, and to assess the potential dose to the off-site population based on the cumulative measurements of radioactivity of plant origin. Radiological environmental monitoring programs provide an additional verification of the containment and radiological controls of nuclear generating stations.

The radiological monitoring program was established in 1973 and has continued to collect samples and evaluate them for twenty-eight (28) years.

Requirements are established for the radiological monitoring program as follows:

> Off-Site Dose Calculation Manual (ODCM)

> various procedures Additional guidance regarding the radiological monitoring program may be found in the following:

> NRC Regulatory Guide 1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I Revision 1 October 1977

> NRC Regulatory Guide 4.13 Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications Revision 1 July 1977

> NRC Regulatory Guide 4.15 Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment Revision 1 February 1979 20

General Site Description The Robinson Nuclear Plant (Unit ' , 1 No. 2) consists of a pressurized V water reactor with a design rating of 769 MWe (Mega-watts electric)

The site is shared with a pulverized j .

coal unit (Unit No.1), which established commercial operation in 1960. Commercial production was initiated by Unit No. Two on March 7, 1971. The Robinson Nuclear Plant is located in Darlington County, South Carolina. The site is along state route 151 approximately five (5) miles north west of Hartsville, , ,* '

South Carolina and is displayed on the map of northeastern South uigure 15: Location of Robinson Nuclear Plant Carolina (Figure 15). The site is also approximately twenty five (25) miles north west of Florence, South Carolina.

Lake Robinson is adjacent to the plant itself and is the source of cooling water. The lake was impounded during the construction of Robinson Unit No. 1 (coal fired). The lake is fed by Black Creek and is approximately 2,250 acres in area. The plant intake is at the southern portion of the lake near the dam. The discharge is to a canal which conveys the cooling water to a point 4.2 miles north of the plant, where it returns to Lake Robinson.

The local economy supports primarily industrial and agricultural contributions. Fishing, boating, and swimming are popular activities on Lake Robinson and other nearby lakes. These activities contribute to the radiological pathways by consumption of fish, and immersion related to swimming and boating. Consumption of milk and food crops contributes to the ingestion pathway.

21

RADIOLOGICAL MONITORING PROGRAM QUALITY ASSURANCE A required component of the environmental radiological monitoring program is the Quality Assurance Program. The standards for the quality assurance program are established in the NRC Regulatory Guide (R.G.) 4.15, "Quality Assurance for Radiological Monitoring Programs.

According to R.G. 4.15, the purpose of the quality assurance program is to "(1) to identify deficiencies in the sampling and measurement processes to those responsible for these operations so that corrective action can be taken, and (2) to obtain some measure of confidence in the results of the monitoring programs in order to assure the regulatory agencies and the public that the results are valid." NRC Regulatory Guide 4.15 B, Pg. 4.15-2. This provides the opportunity to implement corrective actions that address possible deficiencies. Examples of the activities of the quality assurance program include:

. regular review of sample collection and records 3 regular review of laboratory procedures and methods

) participation in an Environmental Interlaboratory Comparison Program, which provides an independent assessment of the quality of laboratory results.

Sthe use of known concentrations of radioactivity in test samples by the laboratory to ensure consistent quality results on an ongoing basis.

22

RADIOLOGICAL MONITORING PROGRAM GENERAL DESCRIPTION Although the contribution to background radiation is small, CP&L has established this program to measure the exposure pathways to man. An exposure pathway describes the source of the radiological exposure. The primary forms of potential radiological emissions from the plant are airborne and liquid discharge. The pathways monitored are external dose, ingestion of radioactive materials, and the inhalation of radioactive material. Specific methods and different environmental media are required to assess each pathway. Table 3 provides a list of the media used to assess each of these pathways.

Table 3 Media Used to Assess Exposure Pathways to Man Pathway of Exposure to Man Media Sampled External Dose Thermoluminescent Dosimetry(TLD)

Shoreline Sediment Ingestion Aquatic Vegetation Broadleaf Vegetation Food Crops Fish Ground Water Surface Water Inhalation Air Samples (Particulate & Radioiodine)

Sampling Locations Sampling locations are chosen based upon meteorological factors, preoperational monitoring, and results of the land use surveys. A number of locations are selected as controls. Control stations are selected because they are very unlikely to be affected by operation of the plant.

Sample locations may be seen in figures 16 and 17. A description of each sample location may be found in Table 4.

23

Figure 16: Radiological Sampling Locations (Distant from Plant) (Scale 1 inch = 2 miles)

Thermoluminescent dosimeter locations(only) are displayed in black, ingestion and waterborne pathways in blue, and inhalation or air sampling stations in red. Stations not shown include 1, 41, 47(varies), 49(varies), 52, 54, and 58(varies).

Stations 1 through 7 and 55 include air sampling and thernoluninescent dosimeters.

Samnie Tvne Sample Locations Air Cartridge & Particulate 1-7, 55 (RED)

Shoreline Sediment 44,57 Ground Water 40,42,43 (BLUE)

Broadleaf Vegetation 50, 51, 52 (BLUE)

Surface Water 40,41, 57 (BLUE)

Thermolumnescent Dosimeter 1-39, 55, 56 (BLACK EXCEPT SHARED LOCATIONS)

Fish 4547 (BLUE)

Food Products 49, 54,58 (BLUE)

Aquatic Vegetation & Bottom Sediment 41, 45, 46, 54 (BLUE) 24

Radiological Sampling Locations FIgure 17: Radiological Sampling Locations (Nearest Plant) (Scale I inch = .25 miles)

Thermnohmnescent dosimeter locations (only) am displayed in black, ingestion and waterborne patbways in blue, and inhalation or air sampling stations in red.

Stations 1 through 7 and 55 include air sampling and thermoluminescent dosimeters.

Samole Ty Sample Locations Air Cartridge & Particulate 1-7, 55 (RED)

Shoreline Sediment 44,57 Ground Water 40, 42, 43 (BLUE)

Broadieaf Vegetation 50,51,52 (BLUE)

Surface Water 40,41, 57 (BLUE)

Thermoluminescent Dosimeter 1-39, 55, 56 (BLACK, EXCEPT SHARED LOCATIONS)

Fish 45-47 (BLUE)

Food Products 49, 54, 58 (BLUE)

Aquatic Vegetation & Bottom Sediment 41, 45, 46, 54 (BLUE) 25 co ',

Table 4 Robinson Nuclear Plant Radiological Monitoring Sampling Locations Sample Type Location & Description Frequency Sample Size Analysis 3

Air Cartridge 1--26 miles ESE Florence* Weekly 800 m Iodine (AC) 2--0.2 mile S Information Center 3--0.7 mile N Microwave Tower 4--0.4 mile ESE Spillway 5--0.9 mile ENE Near Johnson's Landing 6--0.3 mile SW Near Information Center 7--6.3 miles ESE Hartsville Substation 55--0.3 mile SSE Near Site Air Particulate 1-26 miles ESE Florence* Weekly 800 m3 Gross Beta (AP) 2--0.2 mile S Information Center (Weekly) 3--0.7 mile N Microwave Tower Composite 4--0.4 mile ESE Spillway Gamma 5--0.9 mile ENE Near Johnson's Landing (Quarterly) 6--0.3 mile SW Near Information Center 7--6.3 miles ESE Hartsville Substation 55--0.3 mile SSE Near Site Fish (FI) 45--Site varies within. Lake Robinson Semiannual 500 grams Gamma 46--4.9 miles ESE Prestwood Lake (wet) (edible 47--13.0 miles NW Bee Lake or 12.5miles portions only)

NNW May Lake or Juniper Lake or Lake not influenced by plant discharge*

Broadleaf 50--0.25 mile SSE CP&L Property Monthly 500 grams Gamma Vegetation 51--0.25 mile SSW CP&L Property (As (wet) Iodine (BL) 52--10 miles W Bethune* available)

Shoreline 44--1.9 miles NNE Shady Rest Club Semiannual 500 grams Gamma Sediment (SS) 57--0.9 mile NNW Ash Pond Aquatic Veg. 46--4.9 miles ESE--Prestwood Lake Annual 500 grams Gamma (AV) & Bottom 41--7.2 miles NNW Black Creek at US-I

• Sediments (SD) 45--Site varies within Lake Robinson 54--10.1 miles E Auburndale Plantation Ground Water 40--0.6 miles ESE Black Creek at Road 16- Quarterly (as 4 liters Gamma (GW) 23 of 7/98) Tritium 42--Unit 1 Deep Well 43--Unit 2 Deep Well Surface Water 40--0.6 miles ESE Black Creek at Road 16- Monthly 4 liters Gamma (SW) 23 Composite Tritium 41--7.2 miles NNW Black Creek at US 1*

57--0.9 miles NNW Ash Pond Food Products 58--Site varies from plant At time of 500 grams Gamma (FP) 49--10.0 miles W or greater than 5 miles Harvest (edible from plant

• portions) 54--10.1 miles E Auburndale Plantation

• Control Stations 26

Table 4 (Continued)

Robinson Nuclear Plant Radiological Monitoring Sampling Locations Sample Type Location & Description Frequency Sample Analysis Size Thermoluminescent 1--10 miles ESE Florence

• Quarterly Not TLD Dosimetry (TLD) 2--0.2 mile S Information Center Applicable Reading 3--0.7 mile N Microwave Tower 4--0.4 mile ESE Spillway 5--0.9 mile ENE Near Johnson's Landing 6--0.3 mile SW Near Information Center 7--6.3 miles ESE Hartsville Substation 8--0.8 mile SSE Near Transmission Tower 9-- 1.0 mile S on Transmission Tower 10--1.0 mile WSW at Church of God Cemetery 11-- 1.0 mile SW Near Old Camden Road 12--1.2 miles SSW Intersection of Dirt Road Near Roads 16-23 and 16-413 13--1.0 mile W; 0.5 mile Down Extension of Road 16-846 14--0.9 mile WNW at Pine Ridge Church 15--1.0 mile NW Near Ash Pond 16--1.0 mile NNW Darlington Co. IC Turbine Plant 17-1.2 miles N Discharge Canal at Darlington Co. Emergency Water Pumping Station 18--0.7 miles SSE Near Old Railroad Trestle at Black Creek 19--1.0 mile E; 0.1 mile from Intersection of Road 16-23 and Road 16-39 20--1.3 miles ENE; 0.5 mile N of Intersection of Roads 16-23 and 16-39 21-1.4 miles NE Near Atkinson's Boat Landing 22-1.9 miles NNE Shady Rest Club 23-1.2 miles ESE on Road 16-39; 0.5 mile S of Intersection of Roads 16-23 and 16-39 24-5.0 miles NW; 1.5 miles from Intersection of SR 151,13-711, 13-172 25--4.6 miles NNW on Road 13-346 26--5.0 miles N, on Road 13-346 27--5.0 miles NNE Road 13-763 28--4.8 miles NE on Road 13-39 29--4. 1 miles ENE on Road 16-20 at Transmission Tower 30--4.6 miles E, Near Intersection of Roads 16-20 and 16-492 31--4.6 miles ESE on Lakeshore Drive 32--4.5 miles SE Transmission Tower at end of Kalber Drive 33--4.6 miles SSE on Road 16-493 34--4.6 miles S on Road 16-772 35--4.4 miles SSW Near Intersection of Roads 31-51 and 16-12 36--4.7 miles SW on Road 16-1127 37--5.0 miles WSW Transmission Tower Nearest Clay Road 38--4.9 miles W at Union Church Cemetery 39--5.0 miles WNW, IS mile from Intersection of Road 16-231 and 13-172 55--0.3 mile SSE Near Site Boundary 56--300 feet N of ISFSI 56--0.4 mile N of the center of the ISFSI I

• Control Station 27

SUMMARY

OF RADIOLOGICAL MONITORING PROGRAM The Radiological Environmental Monitoring Program (REMP) was conducted in accordance with the H. B. Robinson Steam Electric Plant (HBRSEP), Off-Site Dose Calculation Manual (ODCM), and approved procedures.

The purpose of the REMP is to measure accumulation of radioactivity in the environment, to determine whether this radioactivity is the result of the operations of the HBRSEP, Unit No. 2, and to assess the potential dose to the off -site population based on the cumulative measurements of radioactivity of plant origin. Approximately 1,160 samples were collected from indicator and control locations and 1,200 analyses and measurements were made during 2001. Detectable radioactivity resulting from plant operations was found in all 22 indicator samples of surface water (Table 6). Only the tritium activity in fish samples constituted a potential source of public exposure. Using the methodology of Regulatory Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, dated October 1977," the potentially most exposed individual of the public (being an adult) from the fish consumption of approximately 46 pounds (21 kg of fish per year) and assuming that tritium concentration is in equilibrium with the fish flesh is 0.006 millirem per year.

1. A statistical summary of all the data gathered in 2001 has been compiled in Table 5.

2. Radioactivity in environmental samples which could be attributed to the plant operations in 2001 is summarized in Table 6.

3. All detectable radionuclides in the environmental samples for 2001 were less than reporting levels as defined in HBRSEP ODCM. Table 7 summarizes the reportable levels.

4. Environmental sampling and analyses performed during 2001 demonstrated that the HBRSEP, Unit No. 2 continues to operate with minimum impact on the environment and minimal dose to the general public.

28

5. The following locations are used as control locations and are intended to indicate conditions away from the HBRSEP influence:

Thermoluminescent Dosimeters, Florence, S.C.

Airborne and Particulate Samples (Location 1)

Surface Water, Bottom Sediment, Black Creek at US 1 and Aquatic Vegetation (Location 41)

Fish Lake Bee or May Lake or Juniper Lake or a Lake not influenced by plant discharge (Location 47)

Broadleaf Vegetation 10 Miles W. Bethune (Location 52)

Food Products > 5 Miles from plant--Lowest D/Q (Location 49 - Bethune - site varies) 29

TABLE 5 ROBINSON NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 261 Darlington County, South Carolina Calendar Year 2001 Location w/lHighest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator Locations Name, Distance, MeanRange(2) Control Locations Number of Sampled or No. of Detection Mean Range(2) and Direction Mean Range(2) Nonroutine Measured (Unit of Measurements (LLD)() Reported Measurement) Performed Measurements Air Cartridge 1-131 0 3 All less than LLD (pCi/m ) 4181"* 2,8E-2 All less than LLI)

Air Particulate Gross Beta L.OE-3 2.15E-2 (366/371) Site Boundary 2-31E-2 (53/53) 2.39E-2 (52/53) 0 3 1.48E 4.90E-2 (pCi/m ) 418"' 4.53E 4.59E-2 0.3 mile SSE 6.23E 3.64E-2 Gamma See Table 8 All less than LLD All less than LLD 0 32 Aquatic Vegetation(5 Gamma 3.1E-2 3.98E-2 (2/3) Site Varies within 2.91E- 1 (1/1) All less than LLD 0 (pCi/g, wet) 4 7.96E 2.91 E- I Lake Robinson Single value Co-58 Co-60 3.6E-2 6.65E-2 (1/3) Prestwood Lake 6.65E-2 (1/1) All less than LLD 0 Single value 4.9 miles ESE Single value Cs-137 2.9E-2 1.75E-2 (1/3) Prestwood Lake 1.75E-2 (1/I) All less than LLD 0 Single value 4.9 miles ESE Single value Broadleaf Vegetation Gamma 6.76E-2 (3/36) CP&L Property 9.72E-2 (1/18) 1.53E-1 (10/18) 0 (pCi/g, wet) 54(3)(4) 2.9E-2 4.62E 9.72E-2 0.25 miles SSW Single value 4.89E 4.99E- I Cs- 137 30

( 1' TABLE 5 (Cont.)

ROBINSON NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 261 Calendar Year 2001 Larnington C~ounty, 00UUl ,..ar ldJl .......

Location w/Highest Annual Mean All Indicator Name, Distance, and MeanRange 2) Control Locations Number of FMedium or Pathway Type and Total Lower Limit of Detection Locations Mean Direction Mean Range(2) Nonroutine Sampled or No. of Measured (Unit of Measurements (LLD) (1) Ranget 2 ) Reported Measurement) Performed Measurements Fish Gamma 4.46E+O (4/4) Prestwood Lake 4.55E+O (2/2) 4.19E+O (2/2) 0 Fish 6 1.4E+0 3.95 E+O - 5.1OE+O 4.9 miles ESE 4.OOE+O - 5.1OE+O 3.40E+O - 4.98E+O (pCi/g, wet) K4 Bottom-Feeder K40 1.12E-1 (2/4) Prestwood Lake 1.58E-1 (1/2) All less than LLD Cs-137 7.1E+O 6.59E 1.58E-1 4.9 miles ESE Single value Fish Gamma 9.63E-2 (2/4) Prestwood Lake 9.63E-2 (2/4) 2.02E-1 (1/2) 0 7.1E-2 8.26E 1.1OE-1 4.9 miles ESE 8.26E 1.1OE-I Single value (pCi/g, wet) 6 Free-Swimmer Cs- 137 4.29E+0 (4/4) Site varies within Lake 4.87E+0 (2/2) 5.26E+0 (2/2)

K-40 1.4E+0 3.59E+0 - 4.88E+0 Robinson 4.86E+0 - 4.88E+0 4.66E+0 - 5.87E+0 31

TABLE 5 (Cont.)

ROBINSON NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 261 Darlington County, South Carolina Calendar Year 2001 Location w/Highest Annual Mean Medium or Type and Total Lower Limit of All Indicator Locations Name, Distance, and MeanRange(2) Control Number of Pathway Sampled No. of Detection Mean Range(2) Direction Locations Mean Nonroutine or Measured (Unit Measurements (LLD)(') Range(2) Reported of Measurement) Performed Measurements Food Products Gamma I E- 1 2.36E+0 (6/6) Site varies from plant 3.45E+O (1/1) 4.24E+O (6/6) 0 (pCi/g, wet) 12(3) 1.68E+0 - 3.45E+0 Single value 1.59E+0 - 7.81E+O K-40 Ground Water Gamma (pCi/l) 10 See Table 8 All less than LLD - -- -- No control 0 Tritium 3.25E+2 (10/10)(')

108 All less than LLD No control 0 Shoreline Sediment Gamma See Table 8 All less than LLD No Control 0 (pCi/g, dry) 4 32

(

TABLE 5 (Cont.)

ROBINSON NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 261 Darlington County, South Carolina Calendar Year 2001 Location w/il hest Annual Mean Medium or Pathway Sampled or TypeNo.

andofTotal Lower Limit Detection of (LLD)(n Locations Mean All Indicator Name,Direction Distance, and Mean Range(2) Mean Range12)

Control Locations Number of 2

Measured (Unit of Measurements Range" ) Nonroutine Measurement) Performed Reported Measurements Bottom Sediment(5) Gamma 3.54E-1 (1/3) Site varies within 3.54E-1 (1/1) All less than LLD (pCi/g, dry) 4 4.4E-2 Single value Lake Robinson Single value Co-60 0 1.29E+0 (2/3) Prestwood Lake 1.31E+0 (1/1) All less than LLD Cs-137 5.2E-2 1.26E+0 - 1.31E+0 4.9 miles ESE Single value Surface Water Gamma 0 (pCi/l) 34(3) See Table 8 All less than LLD All less than LLD Tritium 3.25E+2 (12/34)") 2.56E+3 (22/22) Ash Pond 2.64E+3 (10/10) 34(3) I.0E+3 (22/34)(') 1.1 8E+3 - 4.45E+3 0.9 mile NNW 1.32E+3 - 4.04E+3 All less than LLD 0 TLD TLD N/A 1.42E+l (156/160) Near Intersection of 2.11 E+1 (3/4) 1.36E+1 (3/4) 0 t6 1.91E+1 - 2.22E+1 1.26E+1 - 1.42E+1 (mR/qtr) ) 159(3) 9.10E+0 - 2.24E+1 Roads 31-51 and 16-12 4.4 miles SSW 33

FOOTNOTES TO TABLE 5

1. Lower Limit of Detection (LLD) is the smallest concentration of radioactive material in a sample that will yield a net count above system background which will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal. Due to counting statistics and varying volumes, occasionally lower LLDs are achieved.

2. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.

3. Missing samples are discussed in Missed Samples and Analyses.

4. Three types of broadleaf vegetation samples are collected monthly when available from three locations for a possible total of 108 samples.

5. Bottom sediment and aquatic vegetation sampling are not required by plant Offsite Dose Calculation Manual (ODCM). Sampling and analysis is performed to monitor any radionuclide buildup in the lake.

6. TLD exposure is reported in milliroentgen (mR) per 90-day period (quarter) beginning in 1995. This is the exposure standard used to compare data to the Nuclear Regulatory Commission (NRC).

7. Tritium LLD was lowered to 3.25 E+2 pCi/L in June 1996 for samples that typically demonstrate activity less than the LLD (groundwater and surface water control). The LLD was lowered at the request of the plants in order to maintain comparable LLD and result values with the state (N.C. and S.C.) Agencies' laboratories. Other samples that typically exhibit activity greater than the LLD have a tritium Lower Limit of Detection (LLD) of 1.0 E+3 pCi/L.

34

TABLE 6 Radioactivity in Environmental Samples Attributed to Plant Operations Average Concentration Maximum Individual Sample Media Radionuclide and Occurrence Dose Surface H-3 2.56 E+3 (pCi/1) 0.006 millirem/yr Water (22/22) (from fish) 35

TABLE 7 Reporting Levels for Radioactivity Concentrations in Environmental Samples Radionuclide Water (pCi/I) Airborne Fish (pCilkg, Milk (pCi/1) Food Products (pCi/m 3 ) - wet) (pCi/kg, wet)

H-3 3E+04 1E+03 3E+04 Mn-54 4E+02 IE+04 Fe-59 1E+03 3E+04 Co-58 3E+02 IE+04 Co-60 3E+02 2E+04 Zn-65 Zr-Nb-95 4E+02 2E+00 9E-O1 ---- 3E+00 IE+02 1-131 3E+01 IE+01 IE+03 6E+O1 IE+03 Cs-134 5E+01 2E+O1 2E+03 7E+O1 2E+03 Cs- 137 B a-La- 140 2E+02 ---- ---- 3E+02 36

INTERPRETATIONS AND CONCLUSIONS Air Sampling 3

Air samples collected during 2001 had a mean gross beta activity of 2.15 E-2 pCi/rn for the 3

indicator stations versus an average concentration of 2.39 E-2 pCi/ m for the control stations.

These data are essentially unchanged from 1999; they are consistent with preoperational data obtained for the HBRSEP Unit No. 2 (1.40 E-1 pCi! mi ), and reflect the occurrence of naturally 3

occurring radionuclides of the region. Figures 18 through 24 depict the gross beta activity in air versus the control location. The lower current value is primarily due to the reduction of worldwide fallout over that which was occurring during the preoperational years. These figures confirm that the indicator stations show no significant increase over the control samples and hence no discernible impact from the plant operations is apparent in the data.

The quarterly composite gamma analyses for air particulate samples for all quarters revealed no radionuclides typical of plant effluents.

There was no Iodine-131 (1-13 1) detected in any of the 366 air cartridge samples from the indicator stations and 52 air cartridges from the control location.

Broadleaf Vegetation Broadleaf vegetation sampling is accomplished by collecting wild cherry, wax myrtle, and sassafras leaves. Three species of samples, when available, are collected monthly at three locations (one control and two indicator locations at the site boundary selected using historical meteorology with the highest calculated annual average ground level deposition). Broadleaf sampling is conducted since no milk animals are located within a radius of approximately five miles of the plant and is used to simulate dose to an individual via the milk pathway for compliance purposes.

During 2001, 3 of 36 samples taken from the indicator site demonstrated detectable concentrations of Cs-137 for an average value of 6.76 E-2 pCi/g (wet). The control samples had detectable concentrations of Cs-137 in 10 of 18 samples with a mean concentration of 1.53 E-1 37

pCi/g (wet). Upon comparing these results, it is concluded that the indicator values reflect fallout Cs-137 contamination. Past sampling experience further supports this interpretation.

Fish Samples of free-swimming and bottom-feeding fish were taken from Lake Robinson and Prestwood Lake (the first downstream lake) and compared to similar fish from a control lake unaffected by plant operations. During 2001, 2 out of 4 bottom-feeding fish and 2 out of 4 free swimming fish (indicator sites) demonstrated detectable concentrations of Cs-137 for an average of 1.12 E-1 pCi/g (wet) and 9.63 E-2 pCi/g (wet). The control samples for free-swimming fish had detectable concentrations of Cs-137, for a single value mean concentration of 2.02 E-1 pCi/g (wet)

Ground Water No gamma or tritium activity was detected in the ten samples of ground water collected in 2001, which is consistent with the observations in previous years.

Milk Broadleaf sampling is conducted since no milk animals are located within a radius of approximately five miles of the plant in any sector and is used to simulate dose to an individual via the milk pathway for compliance purposes.

Food Crops Food products consisting of collards, cucumbers, eggplants, mustard greens, peaches, squash, tomatoes, and turnips and greens were sampled and analyzed in 2001, with no gamma activity associated with plant operations being detected in any samples.

38

Shoreline Sediment In 2001, no Cesium-137 activity was observed in the shoreline sediment indicator locations. The Cesium-137 activity seen in past years was attributed to worldwide fallout and not the plant operations, while the decreases and slight increases in radionuclide activity were likely due to the variability of bottom sediment sampling. No gamma activity associated with plant operations was detected in any sample in the semiannual shoreline sediment samples in 2001.

Bottom Sediment The 2001 data for Co-60 activity in Lake Robinson is detectable in one out of three indicator sites with a mean concentration of 3.54 E-1 pCi/g (dry).. Cs-137 activity was detectable in two of the three indicator location samples in 2001 with a mean concentration of 1.29 E+0 pCi/g (dry).

Aquatic Vegetation In 2001, gamma activity (CO-58, Co-60, and Cs-137) was detected in the annual aquatic vegetation samples. Co-58 was detected in 2 out of 3 indictor samples with an average concentration of 3.98 E-2 pCi/g (wet). Co-60 and Cs-137 were detected in one out of 3 indicator samples with average concentrations of 6.65 E-2 pCi/g (wet) and 1.75 E-2 pCi/g (wet) respectively.

Surface Water Surface waters of Lake Robinson indicated the presence of tritium which is attributed to plant operations. See Figure 25 which displays the tritium activity throughout 2001. These surface waters do not supply drinking water at any downstream location and are not used for irrigation.

Therefore, radiological dose via this pathway is limited to the consumption of fish from Lake 39

Robinson. Using the methodology of Regulatory Guide 1.109, Equation A-i, a dose of 0.006 millirem/year to the maximum exposed individual could be assigned to this pathway.

Equation A- I Raipj = Cip Uap Daipj where as:

Raipj = total body dose in mrem/yr of H-3 Cip = concentration of nuclide (H-3) in pCi/kg = pCi/l Uap = maximum exposed individual's consumption (Reg. Guide 1.109, Table E-5) (46 lbs. of fish per year = 21 kg of fish/yr.)

Daipj = ingestion dose factor for total body of individual (adult) in Uap in mrem/pCi (Reg. Guide 1.109 Table E-12)

The monthly composite gamma analyses for surface water samples revealed no radionuclides typical of plant effluents.

External Radiation Direct radiation exposure in the H. B. Robinson environs was measured by the placement of thermoluminescent dosimeters (TLDs) about the plant forming an inner ring at approximately 1 mile and an outer ring at 5 miles. The expectation would be that if a plant effect existed, the inner ring dose measurements would exceed those made in the outer ring. This condition was not observed since the outer ring was slightly higher than the inner; therefore, any direct radiation dose to the off-site population was determined to be insignificant (Figure 26).

Asiatic Clams Benthic samples from Lake Robinson during 2001 continue to confirm the absence of any substantial populations of Asiatic clams (Corbiculafluminea). The natural chemistry of the lake (i.e., low alkalinity and hardness) inhibits their proliferation.

40

MISSED SAMPLES AND ANALYSES Air Cartridges and Air Particulates No samples were available for:

"* AC/AP-6, April 16, low volume due to a blown fuse

"* AC/AP-1, May 14, low volume due to a bad sample pump cord

"* AC/AP-4, June 11, low volume due to a failed sampler

"* AC/AP-7, October 8, 22, and 29, low volume due to blown fuse and sampler pump not working correctly The above problems were addressed through the plant maintenance program.

Broadleaf Vegetation Broadleaf vegetation samples were not available during the months of January, February, March, April, October, November, and December of 2001 due to the seasonal nature of broadleaf vegetation.

Food Crops Food crop vegetation samples were not available during the months of January, February, March, April, May, June, August, September, November, and December of 2001 due to the seasonal nature of food crops. Food crop location 54 (FP-54) was not collected during 2001 due to food crops not being irrigated from downstream of the plant.

Surface Water Surface water sample 57 (SW-57, the Ash Pond) was not available for sampling in June (dry) and in November (dry) of 2001.

41

Thermoluminescent Dosimeters (TLDs)

Five of a possible 164 TLD samples were missing during 2001 due to vandalism. It was:

• First Quarter - TLD 17 was missing in the field.

• . Third Quarter - TLD 17 was missing in the field.

• Fourth Quarter - TLDs 1, 17, and 35 were missing in the field.

ANALYTICAL PROCEDURES Gross Beta Gross beta radioactivity measurements are made utilizing a Tennelec Low-Background pCi/m 3.

Alpha/Beta Counting System. The LLD for air particulates is approximately 1.0 E-3 Air particulate samples are mounted in 2-inch stainless steel planchets and counted directly for 50 minutes.

Tritium Liquid samples requiring tritium analysis are treated with a small amount of sodium hydroxide and potassium permanganate crystals and then distilled. Five milliliters of the distillate are mixed with thirteen milliliters of liquid scintillation cocktail and counted in a liquid scintillation counter for 60 minutes to achieve an LLD of approximately 1.0 E+3 pCi/L for samples that typically exhibit activity greater that the LLD. Samples that typically demonstrate activity less that the LLD are counted 500 minutes. The longer count time was necessary to achieve a lower, more compatible LLD (3.25 E+2 pCi/L) with the State Agencies reportable concentrations in the Split Sample Program Report. This change to a lower LLD was per the plants' request (see Footnotes to Table 5, Number 7).

42

Iodine-131 Iodine-131 airborne concentrations are analyzed by the intrinsic germanium (Ge) gamma spectrometry systems. The cartridges are placed on the detector and each charcoal cartridge is counted 500 seconds individually with an approximate LLD of 2.2 E-2 pCi/m .

Gamma Spectrometry Gamma spectrum analysis utilizes intrinsic germanium detectors with thin aluminum windows housed in steel and lead shields. The analyzer system is the Canberra Nuclear 9900 Gamma Spectroscopy System. Table 8 summarizes LLD values derived from instrument sensitivity based upon a blank sample background.

Air particulate filter quarterly composites are placed in a Petri dish and analyzed directly for 1,500 seconds.

Liquid samples are boiled down to reduce the volume, transferred to a PB-50 beaker, and analyzed directly for 7,000 seconds.

Shoreline and bottom sediments are dried, ground, weighed, and then analyzed in a 1-liter Marinelli beaker for 1,500 seconds.

Broadleaf and aquatic vegetation and food product samples are weighed wet and analyzed in a Marinelli beaker for 7,500 seconds.

Fish samples are cleaned, dressed (raw edible portions), and placed in a 1-liter Marinelli beaker for analysis for 1,500 seconds.

43

Thermoluminescent Dosimetry Each area monitoring station includes a TLD packet, which is a polyethylene bag containing three calcium sulfate phosphors contained in a Panasonic UD-814 badge. The TLD is light tight and the bag is weather-resistant.

Dosimeters are machine annealed before field placement. Following exposure in the field, each dosimeter is read utilizing a Panasonic TLD reader. This instrument integrates the light photons emitted from traps as the dosimeter is heated. Calibration is calculated using dosimeters irradiated to known doses for each set of dosimeters measured. Prior to the measurement of each dosimeter, the instrument is checked through use of an internal constant light source as a secondary standard.

The exposure reported is corrected for exposure received in transit and during storage through the use of control dosimeters.

Interlaboratory Comparison Program The Radiochemistry Laboratory at the Harris Energy & Environmental Center in New Hill, North Carolina, provides radioanalytical services for CP&L's nuclear plant radiological environmental surveillance programs. In fulfillment of ODCM Operational Requirements, the laboratory is a participant in the Analytics, Inc., Environmental Cross Check Program and uses its performance in this program as a major determinant of the accuracy and precision of it's analytical results.

During 2001, 106 analyses were completed on 18 samples representing five major environmental media (water, milk, air filters, soil, and air cartridges). Data on the known activities and the standard deviations for the 106 analyses have been received from Analytics, Inc. A comparison of the average of our reported values with the Analytics, Inc., known activity and its standard deviation is provided below:

44

Standard Deviation From Known Activity Percent of Analyses

< 1 Standard Deviation 59

< 2 Standard Deviation 86

< 3 Standard Deviation 97 If any Cross Check samples or checks exceed internal controls, corrective actions are taken. The analyses that exceeded the internal controls do not indicate a trend and the related environmental analyses' results were not impacted. The results that exceeded the internal controls have an evaluation performed to identify any recommended remedial actions and to reduce anomalous errors. Complete documentation on the evaluation by a condition report will be available and will be provided to the NRC upon request.

Lower Limits of Detection The samples analyzed met the LLD required by the ODCM. Typical "a priori" LLD values for the samples analyzed are listed in Table 8.

45

Table 8 Typical Lower Limits of Detection (a priori)

Gamma Spectrometry Surface Water/Groundwater Samples Isotope LLD (pCi/L)

Mn-54 6 Co-58 8 Fe-59 14 Co-60 9 Zn-65 14 Zr-Nb-95 6 1-131 1.0*

Cs-134 7 Cs-137 7 Ba-La- 140 10 Other Expected Gamma Emitters 3 to 154 Air Particulates (Quarterly Composite)

Isotope LLD (pCi/m3)

Cs- 134 0.001 Cs- 137 0.001 Other Expected Gamma Emitters 0.001 to 0.038

• Instrumental analysis of resin concentrates of samples.

46

Table 8 (cont.)

Sediments (Shoreline or Bottom)

Isotope LLD (pCi/kg, dry)

Cs-134 60 Cs-137 52 Other Expected Gamma Emitters 42 to 989 Fish Isotope LLD (pCi/kg, wet)

Mn-54 58 Co-58 38 Fe-59 116 Co-60 56 Zn-65 162 Cs-134 70 Cs- 137 71 Other Expected Gamma Emitters 29 to 1430 Food Products and Vegetation Isotope LLD (pCi/kg, wet) 1-131 38 Cs-134 41 Cs- 137 29 Other Expected Gamma Emitters 23 to 278 47

LAND USE CENSUS PURPOSE OF THE LAND USE CENSUS The land use census identifies the pathways (or routes) that radioactive material may reach the general populations near commercial nuclear generating stations. This is accomplished by completing studies that identify how the surrounding lands are used by the population. A comprehensive census of the use of the land within a five-mile distance of the plant is completed once per 24 months during the growing season. This information is used for dose assessment and to identify changes to the stations sampled and the type of samples. These results ensure that the Radiological Environmental Monitoring Program (REMP) is based upon current data regarding human activity in the vicinity of the plant. Therefore the purpose of the land-use census is both to ensure the monitoring program is current as well as provide data for the calculation of estimated radiation exposure.

The pathways that are evaluated are:

Ingestion Pathway - Results from eating food crops that may have radioactive materials deposited on them, incorporated radioactive materials from the soil or atmosphere. Another pathway is through drinking milk from local cows or goats if these are present. The grass used to feed these animals may have incorporated or had deposited on it radioactive materials that can be transferred to the milk.

"* Direct Radiation Exposure Pathway- Results from deposition of radioactive materials on the ground or from passage of these radioactive materials in the air.

"* Inhalation Pathway- Results from breathing radioactive materials transported in the air.

48

Methodology The following must be identified within the five (5) mile radius of the plant for each of the sixteen meteorological sectors (compass direction the winds may blow, for example NNE [North North East]):

"* The nearest resident

"* The nearest garden of greater that 500 square feet, producing broadleaf vegetables

", The nearest milk animal The primary method is visual inspection from roadside within the five (5) mile radius. This information is supplemented with data from aerial photographs, information from county extension agents, farm supply businesses, and knowledge of the area.

Land Use Census Results The 2000 and 1999 results of the survey for the nearest resident, garden, milk and meat animals in each sector are compared in Table 9.

The nearest resident in each sector remained the same in all but the SSW sector from 1999 to 2000. Garden locations that changed in 2000 can be seen in Table 9 for specific sector changes.

Meat animal locations have changed in the following sectors from 1999 to 2000: N, SSE, SSW, SW, and W. The single indicator milk location in the REMP went out of business as of July 17, 1998. See Table 9 for all the exact changes from 1999 to 2000.

The results of the 2000 census, 1999 meteorological data, and a review of the ten years of average meteorology for the site were compared to the 1999 data. This comparison determined that there were no significant changes in land use; therefore, there were no changes that require an ODCM change, additional dose calculations, or procedure changes. The likely most exposed individual is an adult with the estimated dose to this individual being 0.005 millirem/year whole body.

49

No milk animal was identified within five miles of the site in any sector. Sampling of miscellaneous food products (Non-leafy) in the vicinity of the site will continue until leafy vegetables are identified. Milk sampling will resume if a new sample location is identified.

Also, no garden (at the time of the census) is growing leafy vegetables. Vegetables like tomatoes, squash, okra, cucumbers, etc. are examples of the vegetables of choice for this area and are what has been sampled in the past.

50

TABLE 9 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 LAND USE CENSUS COMPARISONS (1999-2000)

NEAREST PATHWAY (MILES)

SECTOR RESIDENT GARDEN MEAT MILK 1999 2000 1999 2000 1999 2000 1999 2000 N 2.9 2.9 3.0 *3.8 2.9 *3.3 ......

NNE 1.6 1.6 2.2 *2.9 1.6 1.6 NE 1.1 1.1 1.1 1.1 1.8 1.8 ENE 0.8 0.8 1.0 1.0 2.4 2.4 -

E 0.8 0.8 1.9 1.9 3.0 3.0 ESE 0.6 0.6 1.2 1.2 0.9 0.9 SE 0.6 0.6 1.6 *1.25 1.9 1.9 SSE 0.4 0.4 2.6 2.6 --- *0.46 S 0.4 0.4 2.3 *0.85 2.3 2.3 SSW 0.4 *0.35 0.8 0.8 2.0 *0.94 SW 0.5 0.5 1.4 *2.02 4.3 *4.0 WSW 0.5 0.5 0.8 0.8 1.2 1.2 W 0.5 0.5 0.5 0.5 3.7 *1.1 WNW 0.6 0.6 0.7 0.7 4.3 4.3 NW 1.6 1.6 2.0 2.0 2.0 2.0 ......

NNW 2.1 2.1 4.0 4.0 ......

• Changes from 1999.

51

REFERENCES "Annual Radiological Environmental Operating Report," Davis -Bessie Nuclear Power Station (1994)

"Basic Radiation Protection Criteria," Report No. 39, National Council on Radiation Protection and Measurement, Washington, D.C. (January 1971)

Cember, H., "Introduction to Health Physics," Pergamon Press Inc., Elmsford, N.Y. (1969)

"Domestic Licensing of Production and Utilization Facilities," Title 10, Part 50, Code of Federal Regulations, Washington, D.C.

Eisenbud, M., "Environmental Radioactivity," Academic Press, Inc. Orlando FL. (1987)

"Environmental Radiation Protection Standard for Nuclear Power Operations," Title 40, Part 190, Code of Federal Regulations, Washington, D.C.

Evans, R., "The Atomic Nucleus," McGraw-Hill, New York, N.Y. (1967)

"Exposure of the Population in the United States and Canada from Natural Background Radiation," Report No. 94, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1987)

Grosh, D. and Hopwood, L., "Biological Effects of Radiations," Academic Press Inc., New York, N.Y. (1979)

"Health Effects of Exposure to Low Levels of Ionizing Radiation: BEIR V, "Committee on the Biological Effects of Ionizing Radiations, Board on Radiation Effects Research Commission of Life Sciences, National Research Council, National Academy Press, Washington D.C. (1990)

"Ionizing Radiation Exposure of the Population of the United States," Report No. 93, National Council on Radiation Protection and Measurements, Washington, D.C. (September 1987)

Morgan, K. & Turner, J., "Principles of Radiation Protection," John Wiley & Sons, Inc., New York, N.Y. (1968)

"Public Radiation Exposure from Nuclear Power Generation in the United States," Report No.

92, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1987)

"Sources, Effects and Risk of Ionizing Radiation," United Nations Scientific Committee on the Effects of Atomic Radiation, 1988 Report to the General Assembly, United Nations, New York, N.Y. (1988) 52

"Standard for Protection Against Radiation," Tile 10, Part 20, Code of Federal Regulations, Washington, D.C.

"The Effects on Populations of Exposure to Low Levels of Ionizing Radiation: 1980,"

Committee on the Biological Effects of Ionizing Radiations, Division of Medical Sciences, Assembly of Life Sciences, National Research Council, National Academy Press, Washington, D.C. (1980)

"Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1979) 53

Figure 18 RNP From 1/1/2001 To 12/31/2001 AIR PARTICULATE for GROSS BETA - Activity (pCi/cubic meter)

Location 1 Control Location 2 0.050 0.045 0.040 0.035 0 0.030 4:

0.025 0.020 0.015 Jan 2001 Apr Jul Oct Jan 2002 Date 54

Figure 19 RNP From 1/1/2001 To 12/31/2001 AIR PARTICULATE for GROSS BETA - Actity (pCi/cubic meter) 0.050 Location 1 Control Location 3 0.045 0,040 0.035 o0.030

-- IIIIi 0.025 0.020 0.015 IL Jan 2001 Apr Jul Oct Jan 2002 Date 55

Figure 20 RNP From 1/1/2001 To 12/31/2001 AIR PARTICULATE for GROSS BETA - Actity (pCilcubic meter)

Location 1 Control Location 4 0.050 0.045 0.040 0.035

>0.030

< 0.025 0.020 0.015 0.010 Jan 2001 Apr Jul Oct Jan 2002 Date 56

( (

Figure 21 RNP From 1/1/2001 To 12/31/2001 AIR PARTICULATE for GROSS BETA - Activity (pCi/cubic meter)

Location 1 Control Location 5 0.050 0.045 - _ _ _ _ _ _ _ _ _ _ _ _ _ _

0.040 - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

0.035

" "0 VA 0 2 I 0.0350

-0II.021 Jan 2001 Apr Jul Oct Jan 2002 Date 57

/

Figure 22 RNP From 1/1/2001 To 12/31/2001 AIR PARTICULATE for GROSS BETA - Activity (pCi/cubic meter)

W ELI Location 1 control Location 6 0.050 0.045 0.040 0.035 0.015 Jan 2001 Apr Jul Oct Jan 2002 Date 58

(

Figure 23 RNP From 1/1/2001 To 12/31/2001 AIR PARTICULATE for GROSS BETA - Activity (pCicubic meter)

Location I Control Location 7 0.050 0.045 0.040 0.035 0.030

• 0.025 0.020 0.015 0.010 0.005 Jan 2001 Apr Jul Oct Jan 2002 Date 59

(

K, (

Figure 24 RNP From 1/1/2001 To 12/31/2001 AIR PARTICULATE for GROSS BETA - Actvity (pcicubic meter)

Locatio 1 Control Location 55 0.050 01045 0.040 0.035 S0.030 L ain1 oto 0.025 0.020 0.015 0.010 0.005 Jan 2001 Apr Jul Oct Jan 2002 Date 60

Figure 25 RNP 2001 Surface Water Tritium

-- w- Location 41 (control) - Location 57 -&- Location 40 5000 4500 4000 3500 3 3000..

"*-2500-'

Ž2000 1500 1000 500 0

1/31/01 2/28/01 3/31/01 4/30/01 5/31/01 6/30/01 7/31/01 8/31/01 9/30/01 10/31/01 11/30/01 12/31/01 Dates 61

Figure 26 RNP 2001 TLD Averages for Inner and Outer Ring Locations 16 14 S12-.

S10 0

8-8 (a 6-"

4 2

0 15-Feb- 15-Feb I 5-May- 15-May- I 5-Aug- I 5-Aug- I 5-Nov- 15-Nov 01 01 01 01 01 01 01 01 Inner Outer Inner Outer Inner Outer Inner Outer Dates 62

2001 RNP A Progress Energy Company Radiological Environmental Monitoring TLD Report Comments

"* TLD #17 was missing First Quarter 2001.

"* TLD #17 was missing Third Quarter 2001.

"* TLD #1, 17, and 35 were missing Fourth Quarter 2001.

RNP RadiologicalEnvironmental Monitoring TLD Report Dose: mnRlstd. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 1 26 MI ESE - FLORENCE - CONTROL 2/15/01 14.2 2 1 26 MI ESE - FLORENCE - CONTROL 5/15/01 12.6 0.7 1 26 MI ESE - FLORENCE - CONTROL 8/15/01 13.9 2 2 0.2 MI S - INFORMATION CENTER 2/15/01 12.8 2.2 2 0.2 MI S - INFORMATION CENTER 5/15/01 11.4 0.8 2 0.2 MI S - INFORMATION CENTER 8/15/01 13.1 2 2 0.2 MI S - INFORMATION CENTER 11/15/01 12.5 0.9 3 0.7 MI N - MICROWAVE TOWER 2/15/01 15.1 2.1 3 0.7 MI N - MICROWAVE TOWER 5/15/01 13.4 0.5 3 0.7 MI N- MICROWAVE TOWER 8/15/01 15.8 1.9 3 0.7 MI N - MICROWAVE TOWER 11/15/01 13.8 1 4 0.4 MI ESE - SPILLWAY 2/15/01 12.7 2.5 4 0.4 MI ESE - SPILLWAY 5/15/01 12.4 1.3 4 0.4 MI ESE - SPILLWAY 8/15/01 12.8 1.9 4 0.4 MI ESE - SPILLWAY 11/15/01 13.2 1.3 5 0.9 MI ENE - JOHNSONS LANDING 2/15/01 16.9 2 5 0.9 MI ENE -JOHNSONS LANDING 5/15/01 13.3 2.1 5 0.9 MI ENE - JOHNSONS LANDING 8/15/01 16.5 2.1 5 0.9 MI ENE - JOHNSONS LANDING 11/15/01 13.6 2.1 6 0.3 MI SW - INFORMATION CENTER 2/15/01 13.4 2.4 6 0.3 MI SW - INFORMATION CENTER 5/15/01 12.6 0.8 6 0.3 MI SW - INFORMATION CENTER 8/15/01 13.3 1.9 Page 1 of 7

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 0.3 MI SW - INFORMATION CENTER 11/15/01 12.9 0.7 6

6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/15/01 15.4 2.1 7

5/15/01 11.4 1.3 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 8/15/01 14 2 7

6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/15/01 12.5 1.4 7

2/15/01 11.2 2.3 8 0.8 MI SSE - POWER POLES FROM HBR 0.8 MI SSE - POWER POLES FROM HBR 5/15/01 10.2 0.7 8

8/15/01 11.1 2 8 0.8 MI SSE - POWER POLES FROM HBR 11/15/01 11.4 0.9 8 0.8 MI SSE - POWER POLES FROM HBR 2/15/01 19.1 2.3 9 1.0 MI S - POWER POLE NEAR HWY 151 5/15/01 18.2 0.9 9 1.0 MI S - POWER POLE NEAR HWY 151 8/15/01 20.1 3.1 9 1.0 MI S - POWER POLE NEAR HWY 151 11/15/01 19.1 1.5 9 1.0 MI S - POWER POLE NEAR HWY 151 2/15/01 11.3 2.1 10 1.0 MI WSW - CHURCH OF GOD CEMETERY 5/15/01 11 0.6 10 1.0 MI WSW - CHURCH OF GOD CEMETERY 8/15/01 12.1 2 10 1.0 MI WSW - CHURCH OF GOD CEMETERY 11/15/01 11.6 0.7 10 1.0 MI WSW - CHURCH OF GOD CEMETERY 2/15/01 11 2.1 11 1.0 MI SW - POWER POLE AT OLD CAMDEN RD 5/15/01 10.4 0.7 11 1.0 MI SW - POWER POLE AT OLD CAMDEN RD 8/15/01 11.1 2 11 1.0 MI SW - POWER POLE AT OLD CAMDEN RD 11/15/01 10.6 0.8 11 1.0 MI SW - POWER POLE AT OLD CAMDEN RD 2/15/01 15.1 2.2 12- 1.2 MI SSW-PINE TREE AT 2ND INT DIRT RD 5/15/01 14.3 1.1 12 1.2 MI SSW-PINE TREE AT 2ND INT DIRT RD 8/15/01 15.3 2.8 12 1.2 MI SSW-PINE TREE AT 2ND INT DIRT RD Page 2 of 7

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 12 1.2 MISSW-PINE TREE AT 2ND INT DIRT RD 11/15/01 14.8 0.9 13 1.0 MI W-PINE TREE WHERE DIRT RD SPLITS 2/15/01 12 2.4 13 1.0 MI W-PINE TREE WHERE DIRT RD SPLITS 5/15/01 10.5 0.8 13 1.0 MI W-PINE TREE WHERE DIRT RD SPLITS 8/15/01 12.1 1.9 13 1.0 MI W-PINE TREE WHERE DIRT RD SPLITS 11/15/01 10.9 0.9 14 0.9 MI WNW - HWY 151 AT PINE RIDGE CH 2/15/01 16.9 2.4 14 0.9 MI WNW - HWY 151 AT PINE RIDGE CH 5/15/01 16.2 1.2 14 0.9 MI WNW - HWY 151 AT PINE RIDGE CH 8/15/01 16.7 2.5 14 0.9 MI WNW - HWY 151 AT PINE RIDGE CH 11/15/01 15.5 1.3 15 1.0 MI NW -DIRT RD NEAR ASH POND 2/15/01 11.4 2 15 1.0 MI NW -DIRT RD NEAR ASH POND 5/15/01 9.2 0.7 15 1.0OMI NW -DIRT RD NEAR ASH POND 8/15/01 11 2 15 1.0 MI NW -DIRT RD NEAR ASH POND 11/15/01 9.8 0.9 16 1.0 MI NNW - DARLINGTON IC TURBINE PLANT 2/15/01 12.2 2.3 16 1.0 MI NNW - DARLINGTON IC TURBINE PLANT 5/15/01 11.3 1 16 1.0 MI NNW - DARLINGTON IC TURBINE PLANT 8/15/01 12.7 2 16 1.0 MI NNW - DARLINGTON IC TURBINE PLANT 11/15/01 11.8 0.9 17 1.1 MI N - DIS CANAL RD AT UNIT1 WEIR 5/15/01 11.4 0.9 18 0.7 MI SE - TRAIN TRESTLE OVER BLACK CR 2/15/01 12.5 2.5 18 0.7 MI SE - TRAIN TRESTLE OVER BLACK CR 5/15/01 11.6 0.5 18 0.7 MI SE - TRAIN TRESTLE OVER BLACK CR 8/15/01 12.4 2 18 0.7 MI SE -TRAIN TRESTLE OVER BLACK CR 11/15/01 12.2 0.8 19 1.0 MI E - RD S-16-23 2/15/01 13.2 2.5 19 1.0 MI E - RD S-16-23 5/15/01 12.3 0.8 Page 3 of 7

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 19 1.0OMI E - RD S-16-23 8/15/01 13.1 2.2 19 1.0 MI E - RD S-16-23 11/15/01 12.6 1.2 20 1.3 MI ENE - RD S-16-39 NORTH 2/15/01 16 2.1 20 1.3 MI ENE -RD S-16-39 NORTH 5/15/01 12.7 0.6 20 1.3 MI ENE - RD S-16-39 NORTH 8/15/01 16.4 2 20 1.3 MI ENE -RD S-16-39 NORTH 11/15/01 12.5 1.1 21 ATKINSONS BOAT LANDING 2/15/01 16 2.9 21 ATKINSONS BOAT LANDING 5/15/01 12.6 0.5 21 ATKINSONS BOAT LANDING 8/15/01 15.3 2.3 21 ATKINSONS BOAT LANDING 11/15/01 11.9 0.6 22 1.9 MI NNE - SHADY REST NEAR DOCK 2/15/01 12 2.7 22 1.9 MI NNE - SHADY REST NEAR DOCK 5/15/01 11.3 1.1 22 1.9 MI NNE - SHADY REST NEAR DOCK 8/15/01 12.1 2.2 22 1.9 MI NNE - SHADY REST NEAR DOCK 11/15/01 11.9 1.2 23 1.2 MI ESE - INT RD 41E-5 AND S-1i6-39 2/15/01 14.5 2.3 23 1.2 MI ESE -INT RD 41E-5 AND S-16-39 5/15/01 14.2 1.6 23 1.2 MI ESE - INT RD 41E-5 AND S-16-39 8/15/01 15.8 2.5 23 1.2 MI ESE - INT RD 41E-5 AND S-16-39 11/15/01 15 1.5 24 5.0 MI NW - S-13-711 PAST PEACH FARM 2/15/01 16.2 3.1 24 5.0 MI NW - S-13-711 PAST PEACH FARM 5/15/01 15.7 0.6 24 5.0 MI NW - S-1i3-711 PAST PEACH FARM 8/15/01 16.4 2 24 5.0OMI NW - S-13-711 PAST PEACH FARM 11/15/01 16 1 25 4.6 MI NNW - RD S-13-346 OFF 151 NORTH 2/15/01 15.2 2.2 25 4.6 MI NNW - RD S-13-346OFF 151 NORTH 5/15/01 11.8 0.8 Page 4 of 7

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 25 4.6 MI NNW - RD S-13-346 OFF 151 NORTH 8/15/01 15.7 2.8 25 4.6 MI NNW - RD S-13-346 OFF 151 NORTH 11/15/01 11.8 0.9 26 5.0 MI N - RD S-13-346 2/15/01 15.2 2.6 26 5.0 MI N - RD S-1 3-346 5/15/01 14.1 1.3 5.0 MI N - RD S-13-346 8/15/01 14.8 2.6 26 5.0 MI N - RD S-13-346 11/15/01 13.6 1.9 26 5.0 MI NNE - RD S-13-763 NEAR INTER 2/15/01 12.5 2.3 27 27 5.0 MI NNE - RD S-13-763 NEAR INTER 5/15/01 11.1 0.4 27 5.0 MI NNE - RD S-13-763 NEAR INTER 8/15/01 12.3 1.9 27 5.0 MI NNE - RD S-13-763 NEAR INTER 11/15/01 11.8 0.8 28 4.8 MI NE - NEAR DUMPSTER RD S-13-39 2/15/01 17.6 2.6 28 4.8 MI NE - NEAR DUMPSTER RD S-13-39 5/15/01 17.3 0.6 28 4.8 MI NE - NEAR DUMPSTER RD S-13-39 8/15/01 17.7 2.4 28 4.8 MI NE - NEAR DUMPSTER RD S-13-39 11/15/01 17.9 1.6 29 RD S-16-20 SOUTH OF LOOKOUT TOWER 2/15/01 18.7 2 29 RD S-16-20SOUTH OF LOOKOUT TOWER 5/15/01 15.1 0.6 29 RD S-16-20SOUTH OF LOOKOUT TOWER 8/15/01 19 2.2 29 RD S-16-20 SOUTH OF LOOKOUT TOWER 11/15/01 15.8 1.1 30 4.6 MI E - RD S-16-20 JOHNSON FENCE CO 2/15/01 14.8 2.4 30 4.6 MI E - RD S-16-20 JOHNSON FENCE CO 5/15/01 12.9 0.6 8/15/01 15.3 2.6 30 4.6 MI E - RD S-16-20JOHNSON FENCE CO 30 4.6 MI E - RD S-16-20 JOHNSON FENCE CO 11/15/01 12.5 0.7 31 4.6 MI ESE - LAKESHORE DRIVE 2/15/01 17.3 2.4 31 4.6 MI ESE - LAKESHORE DRIVE 5/15/01 13.6 1 Page 5 of 7

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 31 4.6 MI ESE - LAKESHORE DRIVE 8/15/01 17.2 3.1 31 4.6 MI ESE - LAKESHORE DRIVE 11/15/01 13.7 0.7 32 4.5 MI SE - END OF KALBER DRIVE 2/15/01 13.8 2.3 32 4.5 MI SE - END OF KALBER DRIVE 5/15/01 13.3 0.4 32 4.5 MI SE - END OF KALBER DRIVE 8/15/01 14 2.1 32 4.5 MI SE - END OF KALBER DRIVE 11/15/01 13.3 0.9 33 4.6 MI SSE-RD S16-493 NEAR SEGARS ENTR 2/15/01 15.4 2.2 33 4.6 MI SSE-RD S16-493 NEAR SEGARS ENTR 5/15/01 14.3 0.7 33 4.6 MI SSE-RD S16-493 NEAR SEGARS ENTR 8/15/01 15.2 2.3 33 4.6 MI SSE-RD S16-493 NEAR SEGARS ENTR 11/15/01 13 0.6 34 4.6 MI S - RD S-16-772 2/15/01 10.3 2.3 34 4.6 MI S - RD S-16-772 5/15/01 9.4 0.9 34 4.6 MI S - RD S-16-772 8/15/01 10.4 2.3 34 4.6 MI S - RD S-16-772 11/15/01 9.1 1.5 35 4.4 MI SSW - INT RD S-31-51 & S-16-12 2/15/01 22 2.6 35 4.4 MI SSW - INT RD S-31-51 & S-16-12 5/15/01 19.1 1.1 35 4.4 MI SSW - INT RD S-31-51 & S-16-12 8/15/01 22.2 2 36 4.7 MI SW - PAVED RD OFF RD S-16-85 2/15/01 19.8 2.7 36 4.7 MI SW - PAVED RD OFF RD S-16-85 5/15/01 18 1.8 36 4.7 MI SW - PAVED RD OFF RD S-16-85 8/15/01 20.4 2.2 36 4.7 MI SW - PAVED RD OFF RD S-16-85 11/15/01 17.2 1.4 37- 5.0 MI WSW - TRANS TOWER NEAR CLAY RD 2/15/01 21.7 2.8 37 5.0 MI WSW - TRANS TOWER NEAR CLAY RD 5/15/01 17.8 2.1 5.0OMI WSW - TRANS TOWER NEAR CLAY RD 8/15/01 22.4 3 37 Page 6 of 7

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 5.0 MI WSW - TRANS TOWER NEAR CLAY RD 11/15/01 17.1 1.1 37 4.9 MI W - RD S-16-231 AT UNION CHURCH 2/15/01 17.8 2.1 38 5/15/01 16 1 38 4.9 MI W - RD S-16-231 AT UNION CHURCH 4.9 MI W - RD S-16-231 AT UNION CHURCH 8/15/01 18.6 2.3 38 4.9 MI W - RD S-16-231 AT UNION CHURCH 11/15/01 16 1.6 38 5.0 MI WNW - POWER POLE IN FIELD 2/15/01 15.3 2.1 39 5/15/01 13.2 0.9 39 5.0 MI WNW - POWER POLE IN FIELD 8/15/01 14.9 2.1 39 5.0 MI WNW - POWER POLE IN FIELD 11/15/01 12.5 1.2 39 5.0 MI WNW - POWER POLE IN FIELD 2/15/01 14.8 2.4 55 0.3 MI SSE - SITE BOUNDARY 5/15/01 14 1.4 55 0.3 MI SSE - SITE BOUNDARY 8/15/01 14.8 2 55 0.3 MI SSE - SITE BOUNDARY 11/15/01 13.1 1.3 55 0.3 MI SSE -SITE BOUNDARY 2/15/01 15.7 2.1 56 300 FT N OF ISFSI 5/15/01 13.7 0.9 56 300 FT N OF ISFSI 8/15/01 16.3 2 56 300 FT N OF ISFSI 11/15/01 13.2 1.3 56 300 FT N OF ISFSI Page 7 of 7

2001 RNP A Progress Energy Company Radiological Environmental Monitoring Analysis Report Comments

"* Efficiency values are not included for AC samples requiring radioiodine analysis (1-13 1), because gamma software does not report these values.

"* The Less than LLD (<LLD) represents that no activity was present, but lists the LLD values.

• There are no 2 sigma error values reported when activity is <LLD.

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media TApe: Air Particulate Analsis." Beta Quantity: cubic meters Concentration (Activitr.): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 1 26 MI ESE - FLORENCE - CONTROL 1/2/01 464.7 3.77E-01 2.56E-02 2.67E-03 2.24E-03 1 26 MI ESE - FLORENCE - CONTROL 1/8/01 433.6 3.62E-01 2.53E-02 2.89E-03 2.62E-03 1 26 MI ESE - FLORENCE - CONTROL 1/15/01 509.3 3.62E-01 1.77E-02 2.29E-03 2.18E-03 1 26 MI ESE - FLORENCE - CONTROL 1/22/01 513.4 3.62E-01 2.49E-02 2.55E-03 2.13E-03 1 26 MI ESE - FLORENCE - CONTROL 1/29/01 501.5 3.62E-01 2.36E-02 2.56E-03 2.25E-03 1 26 MI ESE - FLORENCE - CONTROL 2/5/01 509.8 3.62E-01 2.43E-02 2.52E-03 2.10E-03 1 26 MI ESE - FLORENCE - CONTROL 2/13/01 509.1 3.62E-01 2.13E-02 2.40E-03 2.10E-03 1 26 MI ESE - FLORENCE - CONTROL 2/19/01 509 3.62E-01 1.86E-02 2.34E-03 2.22E-03 1 26 MI ESE - FLORENCE - CONTROL 2/26/01 508.1 3.62E-01 2.40E-02 2.54E-03 2.18E-03 1 26 MI ESE - FLORENCE - CONTROL 3/5/01 508.3 3.59E-01 1.71E-02 2.27E-03 2.18E-03 1 26 MI ESE FLORENCE - CONTROL 3/12/01 500 3.59E-01 1.78E-02 2.28E-03 2.09E-03 1 26 MI ESE FLORENCE - CONTROL 3/19/01 508.6 3.59E-01 1.62E-02 2.26E-03 2.26E-03 1 26 MI ESE FLORENCE - CONTROL 3/26/01 504.6 3.59E-01 1.98E-02 2.41 E-03 2.23E-03 1 26 MI ESE - FLORENCE - CONTROL 4/2/01 497.7 3.59E-01 1.77E-02 2.31 E-03 2.20E-03 1 26 MI ESE FLORENCE - CONTROL 4/9/01 508.8 3.59E-01 2.35E-02 2.49E-03 2.04E-03 1 26 MI ESE FLORENCE - CONTROL 4/16/01 540.4 3.59E-01 2.53E-02 2.51 E-03 2.1OE-03 1 26 MI ESE - FLORENCE - CONTROL 4/23/01 504.2 3.59E-01 2.75E-02 2.67E-03 2.14E-03 1 26 MI ESE - FLORENCE - CONTROL 4/30/01 484.6 3.59E-01 2.27E-02 2.56E-03 2.24E-03 1 26 MI ESE - FLORENCE - CONTROL 5/8/01 292.7 3.59E-01 2.84E-02 3.86E-03 3.75E-03 1 26 MI ESE- FLORENCE - CONTROL 5/21/01 479 3.59E-01 2.70E-02 2.71E-03 2.14E-03 1 26 MI ESE - FLORENCE - CONTROL 5/28/01 532.5 3.59E-01 2.21 E-02 2-41 E-03 2.09E-03 1 26 MI ESE - FLORENCE - CONTROL 6/4/01 499 3.59E-01 1.94E-02 2.32E-03 2.02E-03 1 26 MI ESE - FLORENCE - CONTROL 6/11/01 517.3 3.59E-01 1.97E-02 2.36E-03 2.18E-03 1 26 MI ESE- FLORENCE- CONTROL 6/18/01 482.9 3.59E-01 2.08E-02 2.50E-03 2.27E-03 1 26 MI ESE - FLORENCE - CONTROL 6/25/01 474.4 3.59E-01 2.57E-02 2.67E-03 2.13E-03 1 26 MI ESE - FLORENCE - CONTROL 7/3/01 549.8 3.59E-01 1.70E-02 2.11 E-03 1.91 E-03 Page 1 of 17

RNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 1 26 MI ESE - FLORENCE - CONTROL 7/9/01 410.5 3.59E-01 2.17E-02 2.83E-03 2.70E-03 1 26 MI ESE - FLORENCE - CONTROL 7/16/01 479 3.59E-01 2.61 E-02 2.75E-03 2.37E-03 1 26 MI ESE - FLORENCE - CONTROL 7/23/01 477.3 3.59E-01 2.17E-02 2.55E-03 2.30E-03 1 26 MI ESE - FLORENCE - CONTROL 7/30/01 476.6 3.59E-01 1.48E-02 2.28E-03 2.38E-03 1 26 MI ESE - FLORENCE - CONTROL 8/6/01 475.7 3.59E-01 1.57E-02 2.33E-03 2.38E-03 1 26 MI ESE - FLORENCE - CONTROL 8/13/01 478.9 3.59E-01 1.82E-02 2.44E-03 2.42E-03 1 26 MI ESE - FLORENCE - CONTROL 8/20/01 497.4 3.59E-01 2.34E-02 2.59E-03 2.33E-03 1 26 MI ESE - FLORENCE - CONTROL 8/27/01 457.2 3.59E-01 3.29E-02 3.OOE-03 2.20E-03 1 26 MI ESE - FLORENCE - CONTROL 9/4/01 543.3 3.59E-01 2.93E-02 2.61 E-03 1.94E-03 1 26 MI ESE - FLORENCE - CONTROL 9/10/01 406.9 3.59E-01 2.21E-02 2.82E-03 2.62E-03 1 26 MI ESE - FLORENCE - CONTROL 9/17/01 470.9 3.59E-01 2.55E-02 2.75E-03 2.41 E-Q3 1 26 MI ESE - FLORENCE - CONTROL 9/24/01 489-9 3.59E-01 3.46E-02 2.94E-03 2.07E-03 1 26 MI ESE - FLORENCE - CONTROL 10/1/01 461.9 3.59E-01 2.33E-02 2.61 E-03 2.18E-03 1 26 MI ESE - FLORENCE - CONTROL 10/8/01 450.3 3.59E-01 3.30E-02 3.04E-03 2.25E-03 1 26 MI ESE - FLORENCE - CONTROL 10/15/01 463.6 3.59E-01 2.17E-02 2.53E-03 2.14E-03 1 26 MI ESE - FLORENCE - CONTROL 10/22/01 463.2 3.59E-01 2.69E-02 2.77E-03 2.23E-03 1 26 MI ESE - FLORENCE - CONTROL 10/29/01 465.6 3.59E-01 2.12E-02 2.56E-03 2.30E-03 1 26 MI ESE - FLORENCE - CONTROL 11/5/01 543.9 3.59E-01 4.90E-02 3.26E-03 2.06E-03 1 26 MI ESE - FLORENCE - CONTROL 11/12/01 617.8 3.59E-01 3.62E-02 2.66E-03 1.79E-03 1 26 MI ESE - FLORENCE - CONTROL 11/19/01 757.5 3.59E-01 2.65E-02 2.07E-03 1.43E-03 1 26 MI ESE - FLORENCE - CONTROL 11/26/01 757.8 3.59E-01 2.30E-02 1.95E-03 1.42E-03 1 26 MI ESE - FLORENCE - CONTROL 12/3/01 755.6 3.59E-01 2.04E-02 1.85E-03 1.38E-03 1 26 MI ESE - FLORENCE - CONTROL 12/10/01 750.2 3.59E-01 2.58E-02 2.03E-03 1.34E-03 1 26 MI ESE - FLORENCE - CONTROL 12/18/01 853.4 3.59E-01 1.98E-02 1.72E-03 1.32E-03 1 26 MI ESE - FLORENCE - CONTROL 12/24/01 659 3.59E-01 2.59E-02 2.23E-03 1.67E-03 1 26 MI ESE - FLORENCE - CONTROL 12/31/01 721.2 3.59E-01 2.92E-02 2.22E-03 1.53E-03 Page 2 of 17

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Particulate Analysis. Beta Quantity: cubic meters Concentration (Activity.): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 2 0.2 MI S -INFORMATION CENTER 1/2/01 612.2 3.77E-01 2.33E-02 2.17E-03 1.70E-03 2 0.2 MI S - INFORMATION CENTER 1/8/01 547.5 3.62E-01 2.17E-02 2.35E-03 2.08E-03 2 0.2 MI S - INFORMATION CENTER 1/15/01 630.2 3.62E-01 1.80E-02 2.00E-03 1.77E-03 2 0.2 MI S - INFORMATION CENTER 1/22/01 626 3.62E-01 2.57E-02 2.28E-03 1.75E-03 2 0.2 MI S - INFORMATION CENTER 1/29/01 620 3.62E-01 2.65E-02 2.34E-03 1.82E-03 2 0.2 MI S - INFORMATION CENTER 2/5/01 629.8 3.62E-01 2.64E-02 2.29E-03 1.70E-03 2 0.2 MI S - INFORMATION CENTER 2/13/01 732.6 3.62E-01 1.74E-02 1.77E-03 1.46E-03 2 0.2 MI S - INFORMATION CENTER 2/19/01 513.5 3.62E-01 1.92E-02 2.35E-03 2.20E-03 2 0.2 MI S - INFORMATION CENTER 2/26/01 629.3 3.62E-01 2.13E-02 2.12E-03 1.76E-03 2 0.2 MI S INFORMATION CENTER 3/5/01 613.6 3.59E-01 1.58E-02 1.95E-03 1.81E-03 2 0.2 MI S INFORMATION CENTER 3/12/01 628.8 3.59E-01 2.06E-02 2.08E-03 1.66E-03 2 0.2 MI S INFORMATION CENTER 3/19/01 621.4 3.59E-01 1.42E-02 1.89E-03 1.85E-03 2 0.2 MIS- INFORMATION CENTER 3/26/01 620.8 3.59E-01 1.75E-02 2.01E-03 1.82E-03 2 0.2 MI S - INFORMATION CENTER 4/2/01 614 3.59E-01 1.49E-02 1.90E-03 1.79E-03 2 0.2 MI S- INFORMATION CENTER 4/9/01 621.7 3.59E-01 2.36E-02 2.20E-03 1.67E-03 2 0.2 MI S - INFORMATION CENTER 4/16/01 610.6 3.59E-01 2.25E-02 2.23E-03 1.86E-03 2 0.2 MI S - INFORMATION CENTER 4/23/01 614.6 3.59E-01 2.49E-02 2.28E-03 1.75E-03 2 0.2 MI S -INFORMATION CENTER 4/30/01 611.9 3.59E-01 2.21 E-02 2.19E-03 1.77E-03 2 0.2 MI S - INFORMATION CENTER 5/8/01 706.6 3.59E-01 2.40E-02 2.07E-03 1.55E-03 2 0.2 MI S - INFORMATION CENTER 5/14/01 515.3 3.59E-01 2.50E-02 2.48E-03 1.87E-03 2 0.2 MI S - INFORMATION CENTER 5/21/01 613.5 3.59E-01 2.65E-02 2.32E-03 1.67E-03 2 0.2 MI S - INFORMATION CENTER 5/28/01 616.6 3.59E-01 2.24E-02 2.20E-03 1.81E-03 2- 0.2 MI S - INFORMATION CENTER 6/4/01 605.6 3.59E-01 2.03E-02 2.09E-03 1.66E-03 2 0.2 MI S - INFORMATION CENTER 6/11/01 608.7 3.59E-01 1.90E-02 2.1OE-03 1.85E-03 2 0.2 MI S - INFORMATION CENTER 6/18/01 527.2 3.59E-01 1.68E-02 2.19E-03 2.08E-03 2 0.2 MI S - INFORMATION CENTER 6/25/01 585.7 3.59E-01 2.20E-02 2.21 E-03 1.73E-03 Page 3 of 17

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic mete Sample Date Quantity Efficiency Activity 2 Sigma Error LLD Sample Point 3.59E-01 1.56E-02 1.80E-03 1.57E-03 7/3/01 672.1 0.2 MI S - INFORMATION CENTER 3.59E-01 1.91 E-02 2.37E-03 2.21E-03 7/9/01 502.2 0.2 MI S - INFORMATION CENTER 3.59E-01 2.76E-02 2.46E-03 1.92E-03 7/16/01 590.4 0.2 MI S - INFORMATION CENTER 3.59E-01 2.12E-02 2.20E-03 1.84E-03 7/23/01 595.2 0.2 MI S - INFORMATION CENTER 1.47E-02 1.98E-03 1.94E-03 7/30/01 583.8 3.59E-01 0.2 MI S - INFORMATION CENTER 1.53E-02 1.95E-03 1.87E-03 8/6/01 606.4 3.59E-01 0.2 MI S - INFORMATION CENTER 3.59E-01 1.71 E-02 2.12E-03 2.02E-03 8/13/01 574.1 0.2 MI S - INFORMATION CENTER 3.59E-01 2.13E-02 2.24E-03 1.96E-03 8/20/01 590 0.2 MI S - INFORMATION CENTER 3.59E-01 3.21 E-02 2.56E-03 1.71E-03 8/27/01 588.5 0.2 MI S - INFORMATION CENTER 2.66E-02 2-21 E-03 1.56E-03 9/4/01 672.8 3.59E-01 0.2 MI S - INFORMATION CENTER 2.18E-02 2.43E-03 2.09E-03 9/10/01 510 3.59E-01 0.2 MI S - INFORMATION CENTER 2.39E-02 2.33E-03 1.93E-03 9/17/01 588.5 3.59E-01 0.2 MI S - INFORMATION CENTER 3.59E-01 3.07E-02 2.47E-03 1.67E-03 9/24/01 605.8 0.2 MI S - INFORMATION CENTER 2.09E-02 2.20E-03 1.76E-03 10/1/01 570.4 3.59E-01 0.2 MI S - INFORMATION CENTER 610 3.59E-01 2.86E-02 2.39E-03 1.66E-03 10/8/01 0.2 MI S - INFORMATION CENTER 3.59E-01 1.77E-02 2.04E-03 1.72E-03 10/15/01 577.2 0.2 MI S - INFORMATION CENTER 3.59E-01 2.36E-02 2.25E-03 1.73E-03 10/22/01 596.5 0.2 MI S - INFORMATION CENTER 1.69E-02 2.OOE-03 1.78E-03 10/29/01 601.2 3.59E-01 0.2 MI S - INFORMATION CENTER 3.23E-02 2.40E-03 1.65E-03 11/5/01 681.2 3.59E-01 0.2 MI S - INFORMATION CENTER 3.59E-01 3.16E-02 2.70E-03 2.01 E-03 11/12/01 549.3 0.2 MI S - INFORMATION CENTER 3-59E-01 2.94E-02 2.47E-03 1.80E-03 11/19/01 602.7 0.2 MI S - INFORMATION CENTER 627.5 3.59E-01 2.18 E-02 2.14E-03 1.72E-03 11/26/01 0.2 MI S - INFORMATION CENTER 3.59E-01 2.14E-02 2.09E-03 1.64E-03 12/3/01 635.4 0.2 MI S - INFORMATION CENTER 3.59E-01 2.85E-02 2.39E-03 1.66E-03 12/10/01 607.2 0.2 MI S - INFORMATION CENTER 1.89E-02 1.90E-03 1.59E-03 12/18/01 710.8 3.59E-01 0.2 MI S - INFORMATION CENTER 535.6 3.59E-01 2.54E-02 2.51 E-03 2.06E-03 12/24/01 0.2 MI S - INFORMATION CENTER Page 4 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analvsis: Beta Quantity: cubic meters Concentration(Activity): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 12/31/01 632.7 3.59E-01 2.87E-02 2.38E-03 1.74E-03 2 0.2 MI S - INFORMATION CENTER 1/2/01 783.6 3.77E-01 2.17E-02 1.81 E-03 1.33E-03 3 0.7 MI N - MICROWAVE TOWER 0.7 MI N - MICROWAVE TOWER 1/8/01 711.8 3.62E-01 2.13E-02 1.98E-03 1.60E-03 3

0.7 MI N - MICROWAVE TOWER 1/15/01 786.6 3.62E-01 1.79E-02 1.73E-03 1.41E-03 3

1/22/01 798.3 3.62E-01 2.45E-02 1.94E-03 1.37E-03 3 0.7 MI N - MICROWAVE TOWER 1/29/01 796.4 3.62E-01 2.06E-02 1.82E-03 1.42E-03 3 0.7 MI N - MICROWAVE TOWER 2/5/01 804 3.62E-01 2.45E-02 1.92E-03 1.33E-03 3 0.7 MI N - MICROWAVE TOWER 0.7 MI N - MICROWAVE TOWER 2/13/01 927.3 3.62E-01 1.84E-02 1.57E-03 1.15E-03 3

2/19/01 661.4 3-62E-01 1.70E-02 1.91E-03 1.71E-03 3 0.7 MI N- MICROWAVE TOWER 2/26/01 789 3.62E-01 2.02E-02 1.81 E-03 1.40E-03 3 0-7 MI N- MICROWAVE TOWER 3/5/01 781-6 3.59E-01 1.59E-02 1.67E-03 1.42E-03 3 0.7 MI N- MICROWAVE TOWER 0.7 MI N - MICROWAVE TOWER 3/12/01 790.6 3.59E-01 1.89E-02 1.74E-03 1.32E-03 3

3/19/01 799.4 3.59E-01 1.32E-02 1.56E-03 1.44E-03 3 0.7 MI N - MICROWAVE TOWER 3/26/01 773 3.59E-01 1.72E-02 1.74E-03 1.46E-03 3 0.7 MI N - MICROWAVE TOWER 0.7 MI N - MICROWAVE TOWER 4/2/01 780 3.59E-01 1.48E-02 1.62E-03 1.41E-03 3

4/9/01 784.3 3.59E-01 2.08E-02 1.82E-03 1.33E-03 3 0.7 MI N - MICROWAVE TOWER 4/16/01 797.4 3.59E-01 2.14E-02 1.85E-03 1.42E-03 3 0.7 MI N- MICROWAVE TOWER 4/23/01 737.2 3.59E-01 2.14E-02 1.92E-03 1.46E-03 3 0.7 MI N - MICROWAVE TOWER 4/30/01 774.9 3.59E-01 2.20E-02 1.89E-03 1.40E-03 3 0.7 MI N - MICROWAVE TOWER 5/8/01 887.9 3.59E-01 2.23E-02 1.76E-03 1.24E-03 3 0.7 MI N - MICROWAVE TOWER 5/14/01 670-3 3.59E-01 2.11E-02 1.98E-03 1.44E-03 3 0.7 MI N - MICROWAVE TOWER 5/21/01 761.2 3.59E-01 2.66E-02 2.04E-03 1.35E-03 3 0.7 MI N - MICROWAVE TOWER 5/28/01 754.2 3.59E-01 2.13E-02 1.91E-03 1.48E-03 3 0.7 MI N - MICROWAVE TOWER 0.7 MI N - MICROWAVE TOWER 6/4/01 790.4 3.59E-01 1.90E-02 1.74E-03 1.27E-03 3

6/11/01 754.5 3.59E-01 1.84E-02 1.816E-03 1.49E-03 3 0.7 MI N - MICROWAVE TOWER 6/18/01 701.5 3.59E-01 1.67E-02 1.82E-03 1.56E-03 3 0.7 MI N - MICROWAVE TOWER Page 5 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration(Activity): pCi/cubicMete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 3 0.7 MI N - MICROWAVE TOWER 6/25/01 737 3.59E-01 2.07E-02 1.87E-03 1.37E-03 3 0.7 MI N - MICROWAVE TOWER 7/3/01 826.4 3.59E-01 1.49E-02 1.55E-03 1.27E-03 3 0.7 MI N - MICROWAVE TOWER 7/9/01 617.5 3.59E-01 1.76E-02 2.01 E-03 1.80E-03 3 0.7 MI N - MICROWAVE TOWER 7/16/01 727.8 3.59E-01 2.61 E-02 2.12E-03 1.56E-03 3 0.7 MI N - MICROWAVE TOWER 7/23/01 724.3 3.59E-01 2.18E-02 1.97E-03 1.51 E-03 3 0.7 MI N - MICROWAVE TOWER 7/30/01 719.4 3.59E-01 1.37E-02 1.68E-03 1.58E-03 3 0.7 MI N - MICROWAVE TOWER 8/6/01 730.6 3.59E-01 1.51 E-02 1.72E-03 1.55E-03 3 0.7 MI N - MICROWAVE TOWER 8/13/01 710.9 3.59E-01 1.78E-02 1.87E-03 1.63E-03 3 0.7 MI N - MICROWAVE TOWER 8/20/01 722.3 3.59E-01 2.30E-02 2.04E-03 1.60E-03 3 0.7 MI N - MICROWAVE TOWER 8/27/01 718.1 3.59E-01 2.81E-02 2.16E-03 1.40E-03 3 0.7 MI N - MICROWAVE TOWER 9/4/01 819.1 3.59E-01 2.66E-02 1.97E-03 1.28Eý03 3 0.7 MI N MICROWAVE TOWER 9/10/01 620.9 3.59E-01 2.08E-02 2.11E-03 1.72E-03 3 0.7 MI N MICROWAVE TOWER 9/17/01 732.7 3.59E-01 2.41 E-02 2.04E-03 1.55E-03 3 0.7 MI N - MICROWAVE TOWER 9/24/01 716.9 3.59E-01 3.19E-02 2.28E-03 1.41E-03 3 0.7 MI N MICROWAVE TOWER 10/1/01 715.7 3.59E-01 1.76E-02 1.79E-03 1.41E-03 3 0.7 MI N - MICROWAVE TOWER 10/8/01 740.4 3.59E-01 2.83E-02 2.13E-03 1.37E-03 3 0.7 MI N - MICROWAVE TOWER 10/15/01 706.9 3.59E-01 1.97E-02 1.88E-03 1.40E-03 3 0.7 MI N - MICROWAVE TOWER 10/22/01 723 3.59E-01 2.04E-02 1.89E-03 1.43E-03 3 0.7 MI N - MICROWAVE TOWER 10/29/01 732.7 3.59E-01 1.71 E-02 1.77E-03 1.46E-03 3 0.7 MI N - MICROWAVE TOWER 11/5/01 735.9 3.59E-01 2.65E-02 2.12E-03 1.52E-03 3 0.7 MI N - MICROWAVE TOWER 11/12/01 751.9 3.59E-01 2.96E-02 2.18E-03 1.47E-03 3 0.7 M1N - MICROWAVE TOWER 11/19/01 718.5 3.59E-01 3.17E-02 2.29E-03 1.51 E-03 3 0.7 MI N - MICROWAVE TOWER 11/26/01 751.8 3.59E-01 2.15E-02 1.91 E-03 1.43E-03 3 0.7 MI N - MICROWAVE TOWER 12/3/01 747.3 3.59E-01 1.90E-02 1.81 E-03 1.39E-03 3 0.7 MI N - MICROWAVE TOWER 12/10/01 744 3.59E-01 2.67E-02 2.07E-03 1.35E-03 3 0.7 MI N - MICROWAVE TOWER 12/18/01 841.4 3.59E-01 1.61 E-02 1.61E-03 1.34E-03 Page 6 of 17

RNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activih): pCi/cubicmete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 3 0.7 MI N - MICROWAVE TOWER 12/24/01 639.8 3.59E-01 2.54E-02 2.25E-03 1.72E-03 3 0.7 MI N - MICROWAVE TOWER 12/31/01 758 3.59E-01 2.92E-02 2.16E-03 1.46E-03 4 0.4 MI ESE - SPILLWAY 1/2/01 844.7 3.77E-01 2.20E-02 1.74E-03 1.23E-03 4 0.4 MI ESE - SPILLWAY 1/8/01 743.3 3.62E-01 2.14E-02 1.93E-03 1.53E-03 4 0.4 MI ESE - SPILLWAY 1/15/01 855.7 3.62E-01 1.84E-02 1.66E-03 1.30E-03 4 0.4 MI ESE - SPILLWAY 1/22/01 856.1 3.62E-01 2.53E-02 1.88E-03 1.28E-03 4 0.4 MI ESE - SPILLWAY 1/29/01 844.4 3.62E-01 2.07E-02 1.76E-03 1.34E-03 4 0.4 MI ESE - SPILLWAY 2/5/01 853.9 3.62E-01 2.52E-02 1.87E-03 1.25E-03 4 0-4 MI ESE - SPILLWAY 2/13/01 991.9 3.62E-01 1.58E-02 1.42E-03 1.08E-03 4 0.4 MI ESE - SPILLWAY 2/19/01 691.2 3.62E-01 1.78E-02 1.88E-03 1.64E-03 4 0.4 MI ESE - SPILLWAY 2/26/01 850.3 3.62E-01 1.98E-02 1.72E-03 1.30E-03 4 0.4 MI ESE - SPILLWAY 3/5/01 822 3.59E-01 1.60E-02 1.62E-03 1.35E-03 4 0.4 MI ESE - SPILLWAY 3/12/01 841.7 3.59E-01 1.86E-02 1.67E-03 1.24E-03 4 0.4 MI ESE - SPILLWAY 3/19/01 845 3.59E-01 1.32E-02 1.50E-03 1.36E-03 4 0.4 MI ESE - SPILLWAY 3/26/01 827.2 3.59E-01 1.67E-02 1.65E-03 1-36E-03 4 0.4 MI ESE - SPILLWAY 4/2/01 827.3 3.59E-01 1.49E-02 1.57E-03 1.33E-03 4 0.4 MI ESE - SPILLWAY 4/9/01 824.1 3.59E-01 2.37E-02 1.86E-03 1.26E-03 4 0.4 MI ESE - SPILLWAY 4/16/01 577.9 3.59E-01 2.25E-02 2.31 E-03 1.96E-03 4 0.4 MI ESE - SPILLWAY 4/23/01 451.9 3.59E-01 2.54E-02 2.78E-03 2.39E-03 4 0.4 MI ESE - SPILLWAY 4/30/01 487.8 3.59E-01 2.42E-02 2.61 E-03 2.22E-03 4 0.4 MI ESE - SPILLWAY 5/8/01 564.4 3.59E-01 2.53E-02 2.43E-03 1.94E-03 4 0.4 MI ESE - SPILLWAY 5/14/01 411-4 3.59E-01 2.44E-02 2.82E-03 2.34E-03 4 0.4 MI ESE - SPILLWAY 5/21/01 486.6 3.59E-01 2.86E-02 2.75E-03 2.11 E-03 4 0.4 MI ESE - SPILLWAY 5/28/01 490.5 3.59E-01 2.32E-02 2.58E-03 2.27E-03 4 0.4 MI ESE - SPILLWAY 6/4/01 488.9 3.59E-01 2.22E-02 2.47E-03 2.06E-03 4 0.4 MI ESE - SPILLWAY 6/18/01 428.2 3.59E-01 2.14E-02 2.73E-03 2.56E-03 Page 7 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Anasis." Beta Quantity: cubic meters Concentration (Activit3y): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 4 0.4 MI ESE - SPILLWAY 6/25/01 589.5 3.59E-01 2.13E-02 2.17E-03 1.72E-03 4 0.4 MI ESE - SPILLWAY 7/3/01 687.6 3.59E-01 1.58E-02 1.78E-03 1.53E-03 4 0.4 MI ESE - SPILLWAY 7/9/01 510.4 3.59E-01 2.03E-02 2.39E-03 2.17E-03 4 0.4 MI ESE - SPILLWAY 7/16/01 600 3.59E-01 2.71 E-02 2.42E-03 1,89E-03 4 0.4 MI ESE - SPILLWAY 7/23/01 597.7 3.59E-01 2.15E-02 2.20E-03 1.84E-03 4 0.4 MI ESE - SPILLWAY 7/30/01 589.8 3.59E-01 1.49E-02 1.98E-03 1.92E-03 4 0.4 MI ESE - SPILLWAY 8/6/01 593.5 3.59E-01 1.53E-02 1.98E-03 1.91 E-03 4 0.4 MI ESE - SPILLWAY 8/13/01 1028.6 3.59E-01 9.59E-03 1.18E-03 1-13E-03 4 0.4 MI ESE - SPILLWAY 8/20/01 591.1 3.59E-01 2.27E-02 2.29E-03 1.96E-03 4 0.4 MI ESE - SPILLWAY 8/27/01 588.2 3.59E-01 2.98E-02 2.48E-03 1.71 E-03 4 0.4 MI ESE - SPILLWAY 9/4/01 668.5 3.59E-01 2.86E-02 2.28E-03 1-57E-03 4 0.4 MI ESE - SPILLWAY 9/10/01 502.5 3.59E-01 2.19E-02 2.46E-03 2.12E-03 4 0.4 Mi ESE - SPILLWAY 9/17/01 588.6 3.59E-01 2.28E-02 2.29E-03 1.93E-03 4 0.4 MI ESE - SPILLWAY 9/24/01 583.5 3.59E-01 3.13E-02 2.55E-03 1.74E-03 4 0.4 MI ESE - SPILLWAY 10/1/01 573.1 3.59E-01 1.75E-02 2.05E-03 1.76E-03 4 0.4 MI ESE - SPILLWAY 10/8/01 597.7 3.59E-01 2.92E-02 2.44E-03 1.69E-03 4 0.4 MI ESE - SPILLWAY 10/15/01 569.1 3.59E-01 1.99E-02 2.15E-03 1.74E-03 4 0.4 MI ESE - SPILLWAY 10/22/01 586.3 3.59E-01 2.34E-02 2.27E-03 1.76E-03 4 0.4 MI ESE- SPILLWAY 10/29/01 592.3 3.59E-01 1.64E-02 2.00E-03 1.815E-03 4 0.4 MI ESE - SPILLWAY 11/5/01 593.9 3.59E-01 2.95E-02 2.51 E-03 1.89E-03 4 0.4 MI ESE - SPILLWAY 11/12/01 543.3 3.59E-01 3.48E-02 2.82E-03 2.03E-03 4 0.4 MI ESE - SPILLWAY 11/19/01 525.2 3.59E-01 3.34E-02 2.82E-03 2.06E-03 4 0.4 MI ESE - SPILLWAY 11/26/01 566.7 3.59E-01 2.37E-02 2.35E-03 1.90E-03 4 0.4 MI ESE - SPILLWAY 12/3/01 561 3.59E-01 2.30E-02 2.32E-03 1.85E-03 4 0.4 MI ESE - SPILLWAY 12/10/01 529.4 3.59E-01 3.1OE-02 2.69E-03 1.90E-03 4 0.4 MI ESE - SPILLWAY 12/18/01 639.6 3.59E-01 1.82E-02 2.OOE-03 1.76E-03 Page 8 of 17

RNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic mete Samnple Date Quantity Efficiency Activity 2 Sigma Error LLD Sample Point 12/24/01 481.1 3.59E-01 2.72E-02 2.76E-03 2.29E-03 4 0.4 MI ESE - SPILLWAY 12/31/01 572.6 3.59E-01 3.19E-02 2.64E-03 1.93E-03 4 0.4 MI ESE - SPILLWAY 1/2/01 518.9 3.77E-01 2.34E-02 2-41E-03 2.OOE-03 5 0.9 MI ENE - JOHNSONS LANDING 1/8/01 476.8 3.62E-01 2.17E-02 2.57E-03 2.38E-03 5 0.9 MI ENE - JOHNSONS LANDING 1/15/01 571.1 3.62E-01 1.81E-02 2.13E-03 1.95E-03 5 0.9 MI ENE - JOHNSONS LANDING 1/22/01 533.1 3.62E-01 2.57E-02 2.52E-03 2.05E-03 5 0.9 MI ENE - JOHNSONS LANDING 1/29/01 528.5 3.62E-01 2.26E-02 2.44E-03 2.14E-03 5 0.9 MI ENE - JOHNSONS LANDING 2/5/01 552.9 3.62E-01 2.55E-02 2.44E-03 1.93E-03 5 0.9 MI ENE - JOHNSONS LANDING 2/13/01 673.1 3.62E-01 1.93E-02 1.94E-03 1.59E-03 5 0.9 MI ENE - JOHNSONS LANDING 2/19/01 510.3 3.62E-01 1.65E-02 2.24E-03 2.22E-03 5 0.9 MI ENE - JOHNSONS LANDING 2/26/01 626.2 3.62E-01 2.13E-02 2.13E-03 1.77E-03 5 0.9 MI ENE -JOHNSONS LANDING 3/5/01 625.3 3.59E-01 1.57E-02 1.92E-03 1.77E-03 5 0.9 MI ENE - JOHNSONS LANDING 3/12/01 650.8 3.59E-01 1.98E-02 2.00E-03 1.61 E-03 5 0.9 MI ENE - JOHNSONS LANDING 3/19/01 672.8 3.59E-01 1.30E-02 1.74E-03 1.71 E-03 5 0.9 MI ENE - JOHNSONS LANDING 3/26/01 697 3.59E-01 1.57E-02 1.80E-03 1.62E-03 5 0.9 MI ENE - JOHNSONS LANDING 4/2/01 725.5 3.59E-01 1.29E-02 1.62E-03 1.51 E-03 5 0.9 MI ENE - JOHNSONS LANDING 4/9/01 772.4 3.59E-01 2.17E-02 1.87E-03 1.35E-03 5 0.9 MI ENE - JOHNSONS LANDING 4/16/01 798.5 3.59E-01 2.25E-02 1.89E-03 1.42E-03 5 0.9 MI ENE - JOHNSONS LANDING 4/23/01 794 3.59E-01 2.07E-02 1.82E-03 1.36E-03 5 0.9 MI ENE - JOHNSONS LANDING 4/30/01 819.6 3.59E-01 1.95E-02 1.74E-03 1.32E-03 5 0.9 MI ENE - JOHNSONS LANDING 5/8/01 990.2 3.59E-01 2.09E-02 1.60E-03 1.11 E-03 5 0.9 MI ENE - JOHNSONS LANDING 5/14/01 730.5 3.59E-01 2.03E-02 1.85E-03 1.32E-03 5 0.9 MI ENE -JOHNSONS LANDING 5/21/01 852.8 3.59E-01 2.23E-02 1.78E-03 1.20E-03 5 0.9 MI ENE - JOHNSONS LANDING 5/28/01 851.5 3.59E-01 1.76E-02 1.65E-03 1.31 E-03 5 0.9 MI ENE - JOHNSONS LANDING 6/4/01 889.6 3.59E-01 1.54E-02 1.49E-03 1.13E-03 5 0.9 MI ENE -JOHNSONS LANDING 6/11/01 906.4 3.59E-01 2.10E-02 1.70E-03 1.24E-03 5 0.9 MI ENE - JOHNSONS LANDING Page 9 of 17

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 5 0.9 MI ENE - JOHNSONS LANDING 6/18/01 542.4 3.59E-01 2.17E-02 2.35E-03 2.02E-03 5 0.9 MI ENE - JOHNSONS LANDING 6/25/01 744.4 3.59E-01 1.95E-02 1.82E-03 1.36E-03 5 0.9 MI ENE -JOHNSONS LANDING 7/3/01 913.6 3.59E-01 1.50E-02 1.46E-03 1.15E-03 7/9/01 723.1 3.59E-01 1.77E-02 1.82E-03 1.53E-03 5 0.9 MI ENE - JOHNSONS LANDING 5 0.9 MI ENE -JOHNSONS LANDING 7/16/01 881.2 3.59E-01 2.33E-02 1.81 E-03 1.29E-03 7/23/01 900.7 3.59E-01 1.89E-02 1.63E-03 1.22E-03 5 0.9 MI ENE - JOHNSONS LANDING 5 0.9 MI ENE - JOHNSONS LANDING 7/30/01 873.6 3.59E-01 1.42E-02 1.50E-03 1.30E-03 5 0.9 MI ENE - JOHNSONS LANDING 8/6/01 892.4 3.59E-01 1.32E-02 1.44E-03 1.27E-03 5 0.9 MI ENE - JOHNSONS LANDING 8/13/01 894.6 3.59E-01 1.73E-02 1.60E-03 1.29E-03 0.9 MI ENE - JOHNSONS LANDING 8/20/01 890.8 3.59E-01 2.25E-02 1.78E-03 1.30E-03 5

0.9 MI ENE -JOHNSONS LANDING 8/27/01 897.5 3.59E-01 2.79E-02 1.89E-03 1.12E-,03 5

9/4/01 1011.7 3.59E-01 2.40E-02 1.67E-03 1-04E-03 5 0.9 MI ENE- JOHNSONS LANDING 0.9 MI ENE - JOHNSONS LANDING 9/10/01 770.2 3.59E-01 2.03E-02 1.83E-03 1.38E-03 5

0.9 MI ENE - JOHNSONS LANDING 9/17/01 901.3 3.59E-01 2.12E-02 1.72E-03 1.26E-03 5

0.9 MI ENE - JOHNSONS LANDING 9/24/01 862.1 3.59E-01 2.77E-02 1.93E-03 1.17E-03 5

5 0.9 MI ENE -JOHNSONS LANDING 10/1/01 860.9 3.59E-01 1.78E-02 1.61 E-03 1.17E-03 0.9 MI ENE - JOHNSONS LANDING 10/8/01 871.6 3.59E-01 2.72E-02 1.90E-03 1.16E-03 5

0.9 MI ENE - JOHNSONS LANDING 10/15/01 848.3 3.59E-01 1.89E-02 1.65E-03 1.17E-03 5

0.9 MI ENE - JOHNSONS LANDING 10/22/01 859 3.59E-01 2.14E-02 1.74E-03 1.20E-03 5

0.9 MI ENE - JOHNSONS LANDING 10/29/01 871.7 3.59E-01 1.43E-02 1.49E-03 1.23E-03 5

0.9 MI ENE - JOHNSONS LANDING 11/5/01 956.7 3.59E-01 3.14E-02 1.95E-03 1.17E-03 5

0.9 MI ENE - JOHNSONS LANDING 11/12/01 615 3.59E-01 3.17E-02 2.52E-03 1.79E-03 5

5 0.9 MI ENE - JOHNSONS LANDING 11/19/01 700 3.59E-01 2.83E-02 2.22E-03 1.55E-03 0.9 MI ENE -JOHNSONS LANDING 11/26/01 712 3.59E-01 2.15E-02 1.97E-03 1.518E-03 5

0.9 MI ENE - JOHNSONS LANDING 12/3/01 741.4 3.59E-01 1.84E-02 1.79E-03 1.40E-03 5

12/10/01 691.8 3.59E-01 2.33E-02 2.04E-03 1.45E-03 5 0.9 MI ENE - JOHNSONS LANDING Page 10of 17

RNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type" Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activitv): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 5 0.9 MI ENE-JOHNSONS LANDING 12/18/01 812.8 3.59E-01 1.69E-02 1.67E-03 1.39E-03 5 0.9 MI ENE - JOHNSONS LANDING 12/24/01 593.6 3.59E-01 2.24E-02 2.25E-03 1.86E-03 5 0.9 MI ENE- JOHNSONS LANDING 12/31/01 691.2 3.59E-01 2.93E-02 2.28E-03 1.60E-03 6 0.3 MI SW - INFORMATION CENTER 1/2/01 578.7 3.77E-01 2.30E-02 2.23E-03 1.79E-03 6 0.3 MI SW - INFORMATION CENTER 1/8/01 519.9 3.62E-01 2.25E-02 2.46E-03 2.19E-03 6 0.3 MI SW - INFORMATION CENTER 1/15/01 604.4 3.62E-01 1.80E-02 2.05E-03 1.84E-03 6 0.3 MI SW - INFORMATION CENTER 1/22/01 607.4 3.62E-01 2.30E-02 2.23E-03 1.80E-03 6 0.3 MI SW - INFORMATION CENTER 1/29/01 594.1 3.62E-01 2.05E-02 2.18E-03 1.90E-03 6 0.3 MI SW - INFORMATION CENTER 2/5/01 607.9 3.62E-01 2.42E-02 2.26E-03 1.76E-03 6 0.3 MI SW - INFORMATION CENTER 2/13/01 709.2 3.62E-01 1.60E-02 1.76E-03 1.51E-03 6 0.3 MI SW - INFORMATION CENTER 2/19/01 499.4 3.62E-01 1.60E-02 2.25E-03 2.26E-03 6 0.3 MI SW -INFORMATION CENTER 2/26/01 609.8 3.62E-01 2.12E-02 2.16E-03 1.81 E-03 6 0.3 MI SW -INFORMATION CENTER 3/5/01 599.2 3.59E-01 1.50E-02 1.94E-03 1.85E-03 6 0.3 MI SW - INFORMATION CENTER 3/12/01 603.7 3.59E-01 1.89E-02 2.06E-03 1.73E-03 6 0.3 MI SW - INFORMATION CENTER 3/19/01 605 3.59E-01 1.20E-02 1.83E-03 1.90E-03 6 0.3 MI SW - INFORMATION CENTER 3/26/01 599.8 3.59E-01 1.45E-02 1.93E-03 1.88E-03 6 0.3 MI SW - INFORMATION CENTER 4/2/01 594.5 3.59E-01 1.44E-02 1.92E-03 1.85E-03 6 0.3 MI SW - INFORMATION CENTER 4/9/01 615.7 3.59E-01 2.13E-02 2.13E-03 1.69E-03 6 0.3 MI SW -INFORMATION CENTER 4/23/01 604.8 3.59E-01 2.15E-02 2.18E-03 1.78E-03 6 0.3 MI SW - INFORMATION CENTER 4/30/01 605.3 3.59E-01 1.88E-02 2.07E-03 1.79E-03 6 0.3 MI SW- INFORMATION CENTER 5/8/01 704.9 3.59E-01 2.07E-02 1.96E-03 1.56E-03 6 0.3 MI SW- INFORMATION CENTER 5/14/01 514.8 3.59E-01 2.09E-02 2.32E-03 1.87E-03 6 0.3 MI SW - INFORMATION CENTER 5/21/01 618.6 3.59E-01 2.44E-02 2.23E-03 1.66E-03 6 0.3 MI SW - INFORMATION CENTER 5/28/01 619 3.59E-01 2.06E-02 2.13E-03 1.80E-03 6 0.3 MI SW - INFORMATION CENTER 6/4/01 609.3 3.59E-01 1.87E-02 2.02E-03 1.65E-03 6 0.3 MI SW - INFORMATION CENTER 6/11/01 617.7 3.59E-01 1.80E-02 2.04E-03 1.83E-03 Page H1of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 6/18/01 630.8 3.59E-01 1.53E-02 1.88E-03 1.74E-03 6 0.3 MI SW - INFORMATION CENTER 6/25/01 632 3.59E-01 2.09E-02 2.07E-03 1.60E-03 6 0.3 MI SW - INFORMATION CENTER 7/3/01 725.6 3.59E-01 1.23E-02 1.57E-03 1.45E-03 6 0.3 MI SW - INFORMATION CENTER 7/9/01 541.3 3.59E-01 1.54E-02 2.10E-03 2.05E-03 6 0.3 MI SW - INFORMATION CENTER 7/16/01 637.9 3.59E-01 2.10E-02 2.12E-03 1.78E-03 6 0.3 MI SW - INFORMATION CENTER 7/23/01 640.6 3.59E-01 1.88E-02 2.01 E-03 1.71 E-03 6 0.3 MI SW - INFORMATION CENTER 7/30/01 368.5 3.59E-01 1.43E-02 2.72E-03 3.08E-03 6 0.3 MI SW - INFORMATION CENTER 8/6/01 658.4 3.59E-01 1.18E-02 1.70E-03 1.72E-03 6 0.3 MI SW - INFORMATION CENTER 8/13/01 630.3 3.59E-01 1.41 E-02 1.87E-03 1.84E-03 6 0.3 MI SW - INFORMATION CENTER 8/20/01 646.6 3.59E-01 1.79E-02 1.99E-03 1.79E-03 6 0.3 MI SW - INFORMATION CENTER 8/27/01 644.1 3.59E-01 2.51 E-02 2.19E-03 1.56E-03 6 0.3 MI SW - INFORMATION CENTER 9/4/01 734.6 3.59E-01 2.13E-02 1.92E-03 1.43E-03 6 0.3 MI SW - INFORMATION CENTER 9/10/01 555.3 3.59E-01 1.73E-02 2.12E-03 1.92E-03 6 0.3 MI SW - INFORMATION CENTER 9/17/01 634.9 3.59E-01 2.13E-02 2.13E-03 1.79E-03 6 0.3 MI SW - INFORMATION CENTER 9/24/01 658.6 3.59E-01 2.57E-02 2.19E-03 1.54E-03 6 0.3 MI SW - INFORMATION CENTER 10/1/01 607.9 3.59E-01 1.62E-02 1.92E-03 1.65E-03 6 0.3 MI SW - INFORMATION CENTER 10/8/01 654 3.59E-01 2.41 E-02 2.14E-03 1.55E-03 6 0.3 MI SW - INFORMATION CENTER 10/15/01 615.3 3.59E-01 1.90E-02 2.01 E-03 1.61 E-03 6 0.3 MI SW - INFORMATION CENTER 10/22/01 633.8 3.59E-01 1.77E-02 1.94E-03 1.63E-03 6 0.3 MI SW - INFORMATION CENTER 10/29/01 637.3 3.59E-01 1.33E-02 1.77E-03 1.68E-03 6 0.3 MI SW - INFORMATION CENTER 11/5/01 715.5 3.59E-01 2.67E-02 2.16E-03 1.57E-03 6 0.3 MI SW - INFORMATION CENTER 11/12/01 652.5 3.59E-01 3.02E-02 2.39E-03 1.69E-03 6 0.3 MI SW - INFORMATION CENTER 11/19/01 709.6 3.59E-01 3.11 E-02 2.29E-03 1.53E-03 6 0.3 MI SW - INFORMATION CENTER 11/26/01 742.9 3.59E-01 2.01E-02 1.87E-03 1.45E-03 6 0.3 MI SW - INFORMATION CENTER 12/3/01 763.6 3.59E-01 1.86E-02 1.77E-03 1.36E-03 6 0.3 MI SW - INFORMATION CENTER 12/10/01 723.2 3.59E-01 2.39E-02 2.01E-03 1.39E-03 6 0.3 MI SW - INFORMATION CENTER Page 12 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type. Air Particulate Analysis:. Beta Quantit'y: cubic meters Concentration(Activity): pCi/cubic nete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 6 0.3 MI SW - INFORMATION CENTER 12/18/01 848.2 3.59E-01 1.46E-02 1.54E-03 1.33E-03 6 0.3 MI SW - INFORMATION CENTER 12/24/01 631.9 3.59E-01 2.56E-02 2.28E-03 1.75E-03 6 0.3 MI SW - INFORMATION CENTER 12/31/01 739.6 3.59E-01 2.76E-02 2.14E-03 1.49E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 1/2/01 590.7 3.77E-01 2.33E-02 2.22E-03 1.76E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 1/8/01 510.9 3.62E-01 1.82E-02 2.32E-03 2.22E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 1/15/01 594.2 3.62E-01 1.75E-02 2.05E-03 1.87E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 1/22/01 605.9 3.62E-01 2.39E-02 2.26E-03 1.816E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 1/29/01 591.9 3.62E-01 2.06E-02 2.19E-03 1.916E-03 7 6-3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/5/01 603.5 3.62E-01 2.37E-02 2.25E-03 1.77E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/13/01 685 3.62E-01 1.73E-02 1.85E-03 1.56E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/19/01 517.7 3.62E-01 1.54E-02 2.17E-03 2.18E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/26/01 599.4 3.62E-01 1.87E-02 2.09E-03 1.85E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 3/5/01 602.7 3.59E-01 1.32E-02 1.86E-03 1.84E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 3/12/01 594.8 3.59E-01 1.90E-02 2.09E-03 1.76E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 3/19/01 609.8 3.59E-01 4.53E-03 1.44E-03 1.89E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 3/26/01 599.9 3.59E-01 1.59E-02 1.99E-03 1.88E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 4/2/01 596.6 3.59E-01 1.48E-02 1.97E-03 1.95E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 4/9/01 607.4 3.59E-01 2.12E-02 2.14E-03 1.71 E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 4/16/01 612.5 3.59E-01 2.06E-02 2.15E-03 1.85E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 4/23/01 602.1 3.59E-01 2.05E-02 2.14E-03 1.79E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 4/30/01 602.9 3.59E-01 2.21E-02 2.21 E-03 1-80E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 5/8/01 702.6 3.59E-01 2.34E-02 2.06E-03 1-56E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 5/14/01 531.9 3.59E-01 1.97E-02 2.22E-03 1.81 E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 5/21/01 596.9 3.59E-01 2.21 E-02 2.19E-03 1.72E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 5/28/01 612.9 3.59E-01 1.93E-02 2.09E-03 1.82E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 6/4/01 620.3 3.59E-01 1.66E-02 1.91 E-03 1.62E-03 Page 13 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Tvpe: Air ParticulateAalsi:et T.d AI Anal-vsis:Beta Quantity: cubic meters Concentration (Activity): pCi/cubic mete Sample Date Quantity Efficiency Activity 2 Sigma Error LLD Sample Point 6/11/01 611.4 3.59E-01 1.76E-02 2.04E-03 1.84E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 6/18/01 532 3.59E-01 1.77E-02 2.22E-03 2.06E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 6/25/01 555.1 3.59E-01 2.04E-02 2.22E-03 1.82E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 7/3/01 624.7 3.59E-01 1.47E-02 1.85E-03 1.68E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 7/9/01 463.6 3.59E-01 1.76E-02 2.44E-03 2.39E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 7/16/01 546.6 3.59E-01 2.38E-02 2.44E-03 2.07E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 7/23/01 538.2 3.59E-01 1.89E-02 2.25E-03 2.04E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 7/30/01 552.9 3.59E-01 1.31 E-02 1.98E-03 2.05E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 8/6/01 528.2 3.59E-01 1.58E-02 2.17E-03 2.15E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 8/13/01 555.9 3-59E-01 1.65E-02 2.14E-03 2.08E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 8/20/01 539.6 3.59E-01 1.98E-02 2.32E-03 2.15E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 8/27/01 540.8 3.59E-01 2.76E-02 2.53E-03 1.86E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 9/4/01 626.5 3.59E-01 2.54E-02 2.26E-03 1.68E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 9/10/01 465.3 3.59E-01 1.94E-02 2.47E-03 2.29E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 9/17/01 542.5 3.59E-01 2.58E-02 2.53E-03 2.09E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 9/24/01 534.3 3.59E-01 3.07E-02 2.66E-03 1.90E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 10/1/01 527.8 3.59E-01 1.90E-02 2.22E-03 1.91 E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 10/15/01 518.8 3.59E-01 1.916E-02 2.24E-03 1.91E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/5/01 436.3 3.59E-01 4.59E-02 3.60E-03 2.57E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/12/01 718.4 3.59E-01 2.94E-02 2.23E-03 1.54E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/19/01 700.9 3.59E-01 2.97E-02 2.27E-03 1.55E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/26/01 720.2 3.59E-01 2.33E-02 2.02E-03 1.50E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/3/01 714.1 3.59E-01 2.06E-02 1.92E-03 1.46E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/10/01 708.2 3.59E-01 2.83E-02 2.18E-03 1.42E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/18/01 797.9 3.59E-01 1.84E-02 1.75E-03 1.41 E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/24/01 599.4 3.59E-01 2.38E-02 2.29E-03 1.84E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION Page 14 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 697.5 3.59E-01 3.07E-02 2.31 E-03 1.58E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/31/01 483 3.77E-01 2.70E-02 2.66E-03 2.15E-03 1/2/01 55 0.3 MI SSE - SITE BOUNDARY 1/8/01 432 3.62E-01 2.17E-02 2.75E-03 2.63E-03 55 0.3 MI SSE - SITE BOUNDARY 508 3.62E-01 1.99E-02 2.38E-03 2.19E-03 1/15/01 55 0.3 MI SSE - SITE BOUNDARY 1/22/01 510.4 3.62E-01 2.59E-02 2.60E-03 2.14E-03 55 0.3 Ml SSE - SITE BOUNDARY 1/29/01 499 3.62E-01 2.01 E-02 2.43E-03 2.27E-03 55 0.3 MI SSE - SITE BOUNDARY 2/5/01 512.9 3.62E-01 2-54E-02 2.56E-03 2.08E-03 55 0.3 MI SSE - SITE BOUNDARY 2/13/01 597 3.62E-01 1.90E-02 2.09E-03 1.79E-03 55 0.3 MI SSE - SITE BOUNDARY 419.8 3.62E-01 1.65E-02 2.57E-03 2.69E-03 2/19/01 55 0.3 MI SSE - SITE BOUNDARY 2/26/01 515.5 3.62E-01 2.08E-02 2.39E-03 2.15E-03 55 0.3 MI SSE - SITE BOUNDARY 510 3.59E-01 1.90E-02 2.34E-03 2.18E-03 3/5/01 55 0.3 MI SSE - SITE BOUNDARY 3/12/01 502.4 3.59E-01 2.20E-02 2.45E-03 2-08E-03 55 0.3 MI SSE - SITE BOUNDARY 515.5 3.59E-01 6.23E-03 1-75E-03 2.23E-03 0.3 MI SSE - SITE BOUNDARY 3/19/01 55 3/26/01 505.1 3.59E-01 1.85E-02 2.35E-03 2.23E-03 55 0.3 MI SSE - SITE BOUNDARY 4/2/01 503 3.59E-01 1.53E-02 2.19E-03 2.18E-03 55 0.3 MI SSE - SITE BOUNDARY 4/9/01 517.6 3.59E-01 2.61 E-02 2.56E-03 2.01 E-03 55 0.3 MI SSE - SITE BOUNDARY 4/16/01 519.9 3.59E-01 2.18E-02 2.44E-03 2.18E-03 55 0.3 MI SSE - SITE BOUNDARY 4/23/01 509.5 3.59E-01 2.35E-02 2.51 E-03 2.12E-03 55 0.3 MI SSE - SITE BOUNDARY 4/30/01 512 3.59E-01 2.54E-02 2.57E-03 2.12E-03 55 0.3 MI SSE - SITE BOUNDARY 595 3.59E-01 2.44E-02 2.32E-03 1.84E-03 5/8/01 55 0.3 MI SSE - SITE BOUNDARY 456 3.59E-01 2.29E-02 2.59E-03 2.11 E-03 5/14/01 55 0.3 MI SSE - SITE BOUNDARY 5/21/01 518.1 3.59E-01 2.58E-02 2.54E-03 1.98E-03 55 0.3 MI SSE - SITE BOUNDARY 5/28/01 518.8 3.59E-01 2.09E-02 2.40E-03 2.15E-03 55 0.3 MI SSE - SITE BOUNDARY 6/4/01 517.7 3.59E-01 1.88E-02 2.24E-03 1.94E-03 55 0.3 MI SSE - SITE BOUNDARY 518.6 3.59E-01 1.91 E-02 2.33E-03 2.17E-03 6/11/01 55 0.3 MI SSE - SITE BOUNDARY 450.1 3.59E-01 2.01E-02 2.58E-03 2.44E-03 6/18/01 55 0.3 MI SSE - SITE BOUNDARY Page 15 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activit."): pCi/cubic mete Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 454.5 3.59E-01 2.48E-02 2.70E-03 2.23E-03 55 0.3 MI SSE - SITE BOUNDARY 6/25/01 7/3/01 517.9 3.59E-01 1.74E-02 2.21 E-03 2.03E-03 55 0.3 MI SSE - SITE BOUNDARY 7/9/01 383.4 3.59E-01 2.07E-02 2.92E-03 2.89E-03 55 0.3 MI SSE - SITE BOUNDARY 7/16/01 453.4 3.59E-01 2.83E-02 2.93E-03 2.50E-03 55 0.3 MI SSE - SITE BOUNDARY 7/23/01 449.9 3.59E-01 2.32E-02 2.71E-03 2.44E-03 55 0.3 MI SSE - SITE BOUNDARY 7/30/01 443-8 3.59E-01 1.58E-02 2.44E-03 2.55E-03 55 0.3 MI SSE - SITE BOUNDARY 8/6/01 460-1 3.59E-01 1.54E-02 2 37E-03 2.46E-03 55 0.3 MI SSE - SITE BOUNDARY 8/13/01 438.9 3.59E-01 1.87E-02 2.62E-03 2.64E-03 55 0.3 MI SSE - SITE BOUNDARY 8/20/01 448.3 3.59E-01 2.46E-02 2.82E-03 2.58E-03 55 0.3 MI SSE - SITE BOUNDARY 8/27/01 446.9 3.59E-01 3.12E-02 2.98E-03 2.25E-03 55 0.3 MI SSE - SITE BOUNDARY 9/4/01 508.7 3.59E-01 2.66E-02 2.61 E-03 2.07E-03 55 0.3 MI SSE - SITE BOUNDARY 9/10/01 383.9 3.59E-01 2.53E-02 3.07E-03 2.78E-03 55 0.3 MI SSE - SITE BOUNDARY 9/17/01 444.9 3.59E-01 2.45E-02 2.82E-03 2.55E-03 55 0.3 MI SSE - SITE BOUNDARY 9/24/01 435.7 3.59E-01 3.62E-02 3.22E-03 2.32E-03 55 0.3 MI SSE - SITE BOUNDARY 10/1/01 430.5 3.59E-01 2.31E-02 2.72E-03 2.34E-03 55 0.3 MI SSE - SITE BOUNDARY 10/8/01 440.6 3.59E-01 3.14E-02 3.02E-03 2.30E-03 55 0.3 MI SSE - SITE BOUNDARY 10/15/01 436.4 3.59E-01 2.06E-02 2.58E-03 2.27E-03 55 0.3 MI SSE - SITE BOUNDARY 10/22/01 436.6 3.59E-01 2.41 E-02 2.76E-03 2.37E-03 55 0.3 MI SSE - SITE BOUNDARY 10/29/01 438 3.59E-01 1.89E-02 2.56E-03 2.45E-03 55 0.3 MI SSE SITE BOUNDARY 11/5/01 442.3 3.59E-01 3.14E-02 3.08E-03 2.54E-03 55 0.3 MI SSE - SITE BOUNDARY 11/12/01 182.4 3.59E-01 3.49E-02 5.72E-03 6.05E-03 55 0.3 MI SSE - SITE BOUNDARY 11/19/01 463.7 3-59E-01 3.43E-02 3.07E-03 2.34E-03 55 0.3 MI SSE - SITE BOUNDARY 11/26/01 473.8 3.59E-01 2.34E-02 2.62E-03 2.28E-03 55 0.3 MI SSE - SITE BOUNDARY 12/3/01 477.2 3.59E-01 2.19E-02 2.52E-03 2.18E-03 55 0.3 MI SSE - SITE BOUNDARY 12/10/01 477.4 3.59E-01 2.88E-02 2.77E-03 2.11 E-03 55 0.3 MI SSE - SITE BOUNDARY 12/18/01 522.1 3.59E-01 1.80E-02 2.27E-03 2.16E-03 55 0.3 MI SSE - SITE BOUNDARY Page 16 of 17

RNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantit,: cubic meters Concentration (Activity): pCi./cubic mete Sample Date Ouantitv Efficiency Activity 2 Sigma Error LLD Sample Point 395.6 3.59 E-01 2.29E-02 2.95E-03 2.79E-03 0.3 MI SSE - SITE BOUNDARY 12/24/01 395.6 3.59E-01 2.29E-02 2.95E-03 2.79E-03 55 12/31/01 469.4 3.59E-01 3.04E-02 2.92E-03 2.35E-03 55 0.3 MI SSE - SITE BOUNDARY Page 17 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubic mneter Analysis: Iodine Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 26 MI ESE - FLORENCE - CONTROL 1/2/01 464.700 <LLD 2.07E-02 1/8/01 433.600 <LLD 3.62E-02 26 MI ESE - FLORENCE - CONTROL 1/15/01 509.300 <LLD 2.91 E-02 26 MI ESE - FLORENCE - CONTROL 1/22/01 513.400 <LLD 2.16E-02 26 MI ESE - FLORENCE - CONTROL 1/29/01 501.500 <LLD 3.03E-02 26 MI ESE - FLORENCE - CONTROL 2/5/01 509.800 <LLD 2.37E-02 26 MI ESE - FLORENCE - CONTROL 2/13/01 509.100 <LLD 2.56E-02 26 MI ESE - FLORENCE - CONTROL 2/19/01 509.000 <LLD 2.50E-02 26 MI ESE - FLORENCE - CONTROL 2/26/01 508.100 <LLD 2.31 E-02 26 MI ESE - FLORENCE - CONTROL 3/5/01 508.300 <LLD 1.30E-02 26 MI ESE - FLORENCE - CONTROL 3/12/01 500.000 <LLD 1.75E-02 26 MI ESE - FLORENCE - CONTROL 3/19/01 508.600 <LLD 3.30E-02 26 MI ESE - FLORENCE - CONTROL 3/26/01 504.600 <LLD 2.37E-02 26 MI ESE - FLORENCE - CONTROL 4/2/01 497.700 <LLD 1.88E-02 26 MI ESE - FLORENCE - CONTROL 4/9/01 508.800 <LLD 2.54E-02 26 MI ESE - FLORENCE - CONTROL 4/16/01 540.400 <LLD 2.49E-02 26 MI ESE - FLORENCE - CONTROL 4/23/01 504.200 <LLD 2.52E-02 26 MI ESE - FLORENCE - CONTROL 4/30/01 484.600 <LLD 1.94E-02 26 MI ESE - FLORENCE - CONTROL 5/8/01 292.700 <LLD 3.96E-02 26 MI ESE - FLORENCE - CONTROL 5/21/01 479.000 <LLD 2.63E-02 26 MI ESE - FLORENCE - CONTROL 5/28/01 532.500 <LLD 3.87E-02 26 MI ESE - FLORENCE - CONTROL 6/4/01 499.000 <LLD 2.33E-02 26 MI ESE - FLORENCE - CONTROL 6/11/01 517.300 <LLD 1.82E-02 26 MI ESE - FLORENCE - CONTROL 6/18/01 482.900 <LLD 2.88E-02 26 MI ESE - FLORENCE - CONTROL 6/25/01 474.400 <LLD 3.41 E-02 26 MI ESE - FLORENCE - CONTROL Page 1 of 17

RNP RadiologicalEnvironmental Monitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubic meter Analysis: Iodine Sample Date Quantity Efficiency Activity 2 Sigma Error LLD Sample Point 7/3/01 549.800 <LLD 1.68E-02 26 MI ESE - FLORENCE - CONTROL 410.500 <LLD 3.76E-02 7/9/01 26 MI ESE - FLORENCE - CONTROL 7/16/01 479.000 <LLD 2.30E-02 26 MI ESE - FLORENCE - CONTROL 7/23/01 477.300 <LLD 1.39E-02 26 MI ESE - FLORENCE - CONTROL 7/30/01 476.600 <LLD 2.66E-02 26 MI ESE - FLORENCE - CONTROL 8/6/01 475.700 <LLD 1.30E-02 26 MI ESE - FLORENCE - CONTROL 8/13/01 478.900 <LLD 1.69E-02 26 MI ESE - FLORENCE - CONTROL 8/20/01 497.400 <LLD 2.74E-02 26 MI ESE - FLORENCE - CONTROL 8/27/01 457.200 <LLD 1.33E-02 26 MI ESE - FLORENCE - CONTROL 9/4/01 543.300 <LLD 2.52E-02 26 MI ESE - FLORENCE - CONTROL 9/10/01 406.900 <LLD 2.59E-02 26 MI ESE - FLORENCE - CONTROL 9/17/01 470.900 <LLD 2.32E-02 26 MI ESE - FLORENCE - CONTROL 489.900 <LLD 3.29E-02 9/24/01 26 MI ESE - FLORENCE - CONTROL 10/1/01 461.900 <LLD 2.82E-02 26 MI ESE - FLORENCE - CONTROL 10/8/01 450.300 <LLD 2.33E-02 26 MI ESE - FLORENCE - CONTROL 10/15/01 463.600 <LLD 3.32E-02 26 MI ESE - FLORENCE - CONTROL 10/22/01 463.200 <LLD 2.09E-02 26 MI ESE - FLORENCE - CONTROL 10/29/01 465.600 <LLD 2.93E-02 26 MI ESE - FLORENCE - CONTROL 543.900 <LLD 1.93E-02 11/5/01 26 MI ESE - FLORENCE - CONTROL 11/12/01 617.800 <LLD 1.33E-02 26 MI ESE - FLORENCE - CONTROL 11/19/01 757.500 <LLD 1.75E-02 26 MI ESE - FLORENCE - CONTROL 11/26/01 757.800 <LLD 1.87E-02 26 MI ESE - FLORENCE - CONTROL 12/3/01 755.600 <LLD 2.08E-02 26 MI ESE - FLORENCE - CONTROL 12/10/01 750.200 <LLD 5.07E-02 26 MI ESE - FLORENCE - CONTROL 12/18/01 853.400 <LLD 1.14E-02 26 MI ESE - FLORENCE - CONTROL Page 2 of 17

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration(Activity): pCi/cubic ,neter Analysis: Iodine Sample Poin nt Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 12/24/01 659.000 <LLD 1.92E-02 26 MI ESE - FLORENCE - CONTROL 721.200 <LLD 4.03E-02 12/31/01 26 MI ESE - FLORENCE - CONTROL 1/2/01 612.200 <LLD 3.15E-02 2 0.2 MI S - INFORMATION CENTER 1/8/01 547.500 <LLD 2.88E-02 2 0.2 MI S - INFORMATION CENTER 1/15/01 630.200 <LLD 3.21 E-02 2 0.2 MI S - INFORMATION CENTER 626.000 <LLD 3.34E-02 1/22/01 2 0.2 MI S - INFORMATION CENTER 1/29/01 620.000 <LLD 2.34E-02 2 0.2 MI S - INFORMATION CENTER 2/5/01 629.800 <LLD 3.25E-02 2 0.2 MI S - INFORMATION CENTER 2/13/01 732.600 <LLD 2.07E-02 2 0.2 MI S - INFORMATION CENTER 2/19/01 513.500 <LLD 2.65E-02 2 0.2 MI S - INFORMATION CENTER 2/26/01 629.300 <LLD 2.64E-02 2 0.2 MI S - INFORMATION CENTER

<LLD 2.00E-02 3/5/01 613.600 2 0.2 MI S - INFORMATION CENTER 3/12/01 628.800 <LLD 1.83E-02 2 0.2 MI S - INFORMATION CENTER 3/19/01 621.400 <LLD 2.80E-02 2 0.2 MI S - INFORMATION CENTER 620.800 <LLD 1.52E-02 3/26/01 2 0.2 MI S - INFORMATION CENTER 4/2/01 614.000 <LLD 2.31 E-02 2 0.2 MI S - INFORMATION CENTER 4/9/01 621.700 <LLD 2.41 E-02 2 0.2 MI S - INFORMATION CENTER 4/16/01 610.600 <LLD 2.64E-02 2 0.2 MI S - INFORMATION CENTER 4/23/01 614.600 <LLD 2.18E-02 2 0.2 MI S - INFORMATION CENTER 4/30/01 611.900 <LLD 2.92E-02 2 0.2 MI S - INFORMATION CENTER 5/8/01 706.600 <LLD 1.48E-02 2 0.2 MI S - INFORMATION CENTER 515.300 <LLD 3.47E-02 5/14/01 2 0.2 MI S - INFORMATION CENTER 613.500 <LLD 3.33E-02 5/21/01 2 0.2 MI S - INFORMATION CENTER 616.600 <LLD 3.06E-02 5/28/01 2 0.2 MI S - INFORMATION CENTER 6/4/01 605.600 <LLD 2.36E-02 2 0.2 MI S - INFORMATION CENTER Page 3 of 17

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubic meter Analysis: Iodine Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 0.2 MI S - INFORMATION CENTER 6/11/01 608.700 <LLD 2.60E-02 6/18/01 527.200 <LLD 3.64E-02 0.2 MI S - INFORMATION CENTER 6/25/01 585.700 <LLD 2.26E-02 0.2 MI S - INFORMATION CENTER 7/3/01 672.100 <LLD 3.14E-02 0.2 MI S - INFORMATION CENTER 7/9/01 502.200 <LLD 2.55E-02 0.2 MI S - INFORMATION CENTER 7/16/01 590.400 <LLD 1.35E-02 0.2 MI S - INFORMATION CENTER 7/23/01 595.200 <LLD 3.40E-02 0.2 MI S INFORMATION CENTER 7/30/01 583.800 <LLD 1.54E-02 0.2 MI S INFORMATION CENTER 8/6/01 606.400 <LLD 2.52E-02 0.2 MI S INFORMATION CENTER 8/13/01 574.100 <LLD 2.32E-02 0.2 MI S - INFORMATION CENTER 8/20/01 590.000 <LLD 2.41 E-02 0.2 MI S - INFORMATION CENTER 8/27/01 588.500 <LLD 1.29E-02 0.2 MI S - INFORMATION CENTER 9/4/01 672.800 <LLD 3.09E-02 0.2 MI S - INFORMATION CENTER 9/10/01 510.000 <LLD 2.50E-02 0.2 MI S - INFORMATION CENTER 9/17/01 588.500 <LLD 2.56E-02 0.2 MI S - INFORMATION CENTER 9/24/01 605.800 <LLD 3.38E-02 0.2 MI S - INFORMATION CENTER 10/1/01 570.400 <LLD 2.54E-02 0.2 MI S - INFORMATION CENTER 10/8/01 610.000 <LLD 3.01E-02 0.2 MI S - INFORMATION CENTER 10/15/01 577.200 <LLD 1.33E-02 0.2 MI S - INFORMATION CENTER 10/22/01 596.500 <LLD 1.98E-02 0.2 MI S - INFORMATION CENTER 10/29/01 601.200 <LLD 3.13E-02 0.2 MI S - INFORMATION CENTER 11/5/01 681.200 <LLD 1.83E-02 0.2 MI S - INFORMATION CENTER 11/12/01 549.300 <LLD 3.03E-02 0.2 MI S - INFORMATION CENTER 11/19/01 602.700 <LLD 3.35E-02 0.2 MI S - INFORMATION CENTER 11/26/01 627.500 <LLD 2.20E-02 0.2 MI S - INFORMATION CENTER Page 4 of 17

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration(Activity): pCi/cubic meter Analysis: Iodine Sample Poin ýnt Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 12/3/01 635.400 <LLD 2.09E-02 2 0.2 MI S - INFORMATION CENTER 12/10/01 607.200 <LLD 3.18E-02 2 0.2 MI S - INFORMATION CENTER 12/18/01 710.800 <LLD 2.40E-02 2 0.2 MI S - INFORMATION CENTER 12/24/01 535.600 <LLD 3.79E-02 2 0.2 MI S - INFORMATION CENTER 12/31/01 632.700 <LLD 2.06E-02 2 0.2 MI S - INFORMATION CENTER 1/2/01 783.600 <LLD 3.09E-02 3 0.7 MI N - MICROWAVE TOWER 1/8/01 711.800 <LLD 2.74E-02 3 0.7 MI N - MICROWAVE TOWER 1/15/01 786.600 <LLD 1.86E-02 3 0.7 MI N - MICROWAVE TOWER 1/22/01 798.300 <LLD 1.88E-02 3 0.7 MI N - MICROWAVE TOWER 1/29/01 796.400 <LLD 1.16E-02 3 0.7 MI N - MICROWAVE TOWER 2/5/01 804.000 <LLD 1.93E-02 3 0.7 MI N MICROWAVE TOWER 2/13/01 927.300 <LLD 1.10E-02 3 0.7 MI N - MICROWAVE TOWER 2/19/01 661.400 <LLD 2.65E-02 3 0.7 MI N - MICROWAVE TOWER 2/26/01 789.000 <LLD 2.56E-02 3 0.7 MI N - MICROWAVE TOWER 3/5/01 781.600 <LLD 2.12E-02 3 0.7 MI N- MICROWAVE TOWER 3/12/01 790.600 <LLD 2.20E-02 3 0.7 MI N - MICROWAVE TOWER 3/19/01 799.400 <LLD 1.81 E-02 3 0.7 MI N - MICROWAVE TOWER 3/26/01 773.000 <LLD 2.47E-02 3 0.7 MI N - MICROWAVE TOWER 4/2/01 780.000 <LLD 1.92E-02 3 0.7 MI N - MICROWAVE TOWER 4/9/01 784.300 <LLD 2.13E-02 3 0.7 MI N - MICROWAVE TOWER 4/16/01 797.400 <LLD 1.50E-02 3 0.7 MI N - MICROWAVE TOWER 4/23/01 737.200 <LLD 2.12E-02 3 0.7 MI N - MICROWAVE TOWER 4/30/01 774.900 <LLD 1.86E-02 3 0.7 MI N - MICROWAVE TOWER 5/8/01 887.900 <LLD 1.69E-02 3 0.7 MI N - MICROWAVE TOWER 5/14/01 670.300 <LLD 3.10E-02 3 0.7 MI N - MICROWAVE TOWER Page 5 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubic meter Analysis. Iodine Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 761.200 <LLD 1.59E-02 5/21/01 1.59E-02 0.7 MI N - MICROWAVE TOWER <LLD 754.200 2.41 E-02 5/28/01 0.7 MI N - MICROWAVE TOWER <LLD 790.400 3.17E-02 6/4/01 <LLD 0.7 MI N - MICROWAVE TOWER 754.500 2.14E-02 6/11/01 0.7 MI N - MICROWAVE TOWER <LLD 701.500 2.39E-02 6/18/01 0.7 MI N - MICROWAVE TOWER <LLD 737.000 1.73E-02 6/25/01 0.7 MI N - MICROWAVE TOWER <LLD 7/3/01 826.400 3.24E-02 0.7 MI N - MICROWAVE TOWER <LLD 7/9/01 617.500 3.43E-02 0,7 MI N - MICROWAVE TOWER <LLD 7/16/01 727.800 1.76E-02 0.7 MI N - MICROWAVE TOWER <LLD 7/23/01 724.300 3.98E-02 0.7 MI N - MICROWAVE TOWER <LLD 7/30/01 719.400 1.42E-02 0.7 MI N - MICROWAVE TOWER <LLD 8/6/01 730.600 1.49E-02 0.7 MI N - MICROWAVE TOWER <LLD 8/13/01 710.900 2.21 E-02 0.7 MI N - MICROWAVE TOWER <LLD 8/20/01 722.300 3.27E-02 0.7 MI N - MICROWAVE TOWER <LLD 8/27/01 718.100 2.55E-02 0.7 MI N - MICROWAVE TOWER <LLD 9/4/01 819.100 2.73E-02 0.7 MI N - MICROWAVE TOWER <LLD 9/10/01 620.900 4.37E-02 0.7 MI N- MICROWAVE TOWER <LLD 732.700 2.13E-02 9/17/01 0.7 MI N - MICROWAVE TOWER <LLD 716.900 1.93E-02 9/24/01 0.7 MI N - MICROWAVE TOWER <LLD 715.700 2.37E-02 10/1/01 0.7 MI N - MICROWAVE TOWER <LLD 740.400 1.36E-02 10/8/01 0.7 MI N - MICROWAVE TOWER <LLD 706.900 3.1 OE-02 10/15/01 <LLD 0.7 MI N - MICROWAVE TOWER 10/22/01 723.000 2.12E-02 0.7 MI N - MICROWAVE TOWER <LLD 10/29/01 732.700 1.72E-02 0.7 MI N - MICROWAVE TOWER <LLD 735.900 2.92E-02 11/5/01 <LLD 0.7 MI N - MICROWAVE TOWER Page 6 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubic meter Analysis: Iodine Sample Poinnt Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 11/12/01 751.900 <LLD 3.17E-02 3 0.7 MI N - MICROWAVE TOWER 11/19/01 718.500 <LLD 1.04E-02 3 0.7 MI N - MICROWAVE TOWER 11/26/01 751.800 <LLD 1.54E-02 3 0.7 MI N - MICROWAVE TOWER 12/3/01 747.300 <LLD 1.23E-02 3 0.7 MI N - MICROWAVE TOWER 12/10/01 744.000 <LLD 1.92E-02 3 0.7 MI N - MICROWAVE TOWER 12/18/01 841.400 <LLD 1.71 E-02 3 0.7 MI N - MICROWAVE TOWER 12/24/01 639.800 <LLD 1.69E-02 3 0.7 MI N - MICROWAVE TOWER 12/31/01 758.000 <LLD 2.82E-02 3 0.7 MI N - MICROWAVE TOWER 1/2/01 844.700 <LLD 2.92E-02 4 0.4 MI ESE - SPILLWAY 1/8/01 743.300 <LLD 2.92E-02 4 0.4 MI ESE - SPILLWAY 1/15/01 855.700 <LLD 1.63E-02 4 0.4 MI ESE - SPILLWAY 1/22/01 856.100 <LLD 1.81 E-02 4 0.4 MI ESE - SPILLWAY 1/29/01 844.400 <LLD 1.58E-02 4 0.4 MI ESE - SPILLWAY 2/5/01 853.900 <LLD 1.59E-02 4 0.4 MI ESE - SPILLWAY 2/13/01 991.900 <LLD 3.07E-02 4 0.4 MI ESE - SPILLWAY 2/19/01 691.200 <LLD 2.28E-02 4 0.4 MI ESE - SPILLWAY 2/26/01 850.300 <LLD 1.75E-02 4 0.4 MI ESE - SPILLWAY 3/5/01 822.000 <LLD 1.18E-02 4 0-4 MI ESE - SPILLWAY 3/12/01 841.700 <LLD 1.08E-02 4 0.4 MI ESE - SPILLWAY 3/19/01 845.000 <LLD 1.99E-02 4 0.4 MI ESE - SPILLWAY 3/26/01 827.200 <LLD 1.10E-02 4 0.4 MI ESE - SPILLWAY 4/2/01 827.300 <LLD 1.39E-02 4 0.4 MI ESE - SPILLWAY 4/9/01 824.100 <LLD 1.67E-02 4 0.4 MI ESE - SPILLWAY 4/16/01 577.900 <LLD 2.14E-02 4 0.4 MI ESE - SPILLWAY 4/23/01 451.900 <LLD 4.50E-02 4 0.4 MI ESE - SPILLWAY Page 7 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic jmeters Concentration (Activity): i)Ci/cubic meter Analysis: Iodine Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 4/30/01 487.800 <LLD 4.45E-02 4 0.44 MI ESE - SPILLWAY 5/8/01 564.400 <LLD 4.43E-02 4 0.44 MI ESE - SPILLWAY 5/14/01 411.400 <LLD 5.28E-02 4 0.,4 MI ESE - SPILLWAY 5/21/01 486.600 <LLD 4.49E-02 4 0.44 MI ESE - SPILLWAY 5/28/01 490.500 <LLD 4.92E-02 4 0.44 MI ESE - SPILLWAY 6/4/01 488.900 <LLD 2.84E-02 4 0.44 MI ESE - SPILLWAY 6/18/01 428.200 <LLD 2.33E-02 4 0. 4 MI ESE - SPILLWAY 6/25/01 589.500 <LLD 1.93E-02 4 0. 4 MI ESE - SPILLWAY 7/3/01 687.600 <LLD 2.29E-02 4 0. 4 MI ESE - SPILLWAY 7/9/01 510.400 <LLD 2.85E-02 4 0. 4 MI ESE - SPILLWAY 7/16/01 600.000 <LLD 2.18E-02 4 0. 4 MI ESE - SPILLWAY 7/23/01 597.700 <LLD 9.86E-03 4 0. 4 MI ESE - SPILLWAY 7/30/01 589.800 <LLD 3.12E-02 4 0. 4 MI ESE - SPILLWAY 8/6/01 593.500 <LLD 2.25E-02 4 0. 4 MI ESE - SPILLWAY 8/13/01 1028.600 <LLD 1.77E-02 4 0. 4 MI ESE - SPILLWAY 8/20/01 591.100 <LLD 2.75E-02 4 0. 4 MI ESE - SPILLWAY 8/27/01 588.200 <LLD 1.54E-02 4 0..4 MI ESE - SPILLWAY 9/4/01 668.500 <LLD 3.1OE-02 4 0..4 MI ESE - SPILLWAY 9/10/01 502.500 <LLD 2.52E-02 4 0. .4 MI ESE - SPILLWAY 9/17/01 588.600 <LLD 2.66E-02 4 0. .4 MI ESE - SPILLWAY 9/24/01 583.500 <LLD 1.16E-02 4 0. .4 MI ESE - SPILLWAY 10/1/01 573.100 <LLD 1.67E-02 4 0. .4 MI ESE - SPILLWAY 10/8/01 597.700 <LLD 2.93E-02 4 0. .4 MI ESE - SPILLWAY 10/15/01 569.100 <LLD 3.57E-02 4 0. .4 MI ESE - SPILLWAY 10/22/01 586.300 <LLD 1.14E-02 4 0. .4 MI ESE - SPILLWAY Page 8 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubic meter Analysis: Iodine Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 10/29/01 592.300 <LLD 4.36E-02 0.4 Ml ESE - SPILLWAY 11/5/01 593.900 <LLD 1.77E-02 0.4 MI ESE - SPILLWAY 11/12/01 543.300 <LLD 4.36E-02 0.4 MI ESE - SPILLWAY 11/19/01 525.200 <LLD 2.40E-02 0.4 MI ESE - SPILLWAY 11/26/01 566.700 <LLD 1.69E-02 0.4 MI ESE - SPILLWAY 12/3/01 561.000 <LLD 2.20E-02 0.4 MI ESE - SPILLWAY 12/10/01 529.400 <LLD 1.88E-02 0-4 MI ESE - SPILLWAY 12/18/01 639.600 <LLD 2.40E-02 0.4 MI ESE SPILLWAY 12/24/01 481.100 <LLD 5.01 E-02 0.4 MI ESE - SPILLWAY 12/31/01 572.600 <LLD 3.16E-02 0.4 MI ESE - SPILLWAY 1/2/01 518.900 <LLD 1 .54E-02 0.9 MI ENE - JOHNSONS LANDING 1/8/01 476.800 <LLD 1.91E-02 0.9 MI ENE - JOHNSONS LANDING 1/15/01 571.100 <LLD 3.58E-02 0.9 MI ENE - JOHNSONS LANDING 1/22/01 533.100 <LLD 2.50E-02 0.9 MI ENE - JOHNSONS LANDING 1/29/01 528.500 <LLD 3.10E-02 0.9 MI ENE - JOHNSONS LANDING 2/5/01 552.900 <LLD 2.58E-02 0.9 MI ENE - JOHNSONS LANDING 2/13/01 673.100 <LLD 2.37E-02 0.9 MI ENE - JOHNSONS LANDING 2/19/01 510.300 ý.LLD 1.76E-02 0.9 MI ENE - JOHNSONS LANDING 2/26/01 626.200 <LLD 1.06E-02 0.9 MI ENE - JOHNSONS LANDING 3/5/01 625.300 <LLD 2.06E-02 0.9 MI ENE - JOHNSONS LANDING 3/12/01 650.800 <LLD 2.40E-02 0.9 Ml ENE - JOHNSONS LANDING 3/19/01 672.800 <LLD 2.16E-02 0.9 MI ENE - JOHNSONS LANDING 3/26/01 697.000 <LLD 1.86E-02 0.9 MI ENE - JOHNSONS LANDING 4/2101 725.500 <LLD 1.38E-02 0.9 MI ENE - JOHNSONS LANDING 4/9/01 772.400 <LLD 1.53E-02 0.9 MI ENE - JOHNSONS LANDING Page 9 of17

RNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubic meter Analysis: Iodine Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 0.9 MI ENE - JOHNSONS LANDING 4/16/01 798.500 <LLD 1.28E-02 0.9 MI ENE - JOHNSONS LANDING 4/23/01 794.000 "<LLD 1.89E-02 0.9 MI ENE - JOHNSONS LANDING 4/30/01 819.600 <LLD 1.78E-02 0.9 MI ENE - JOHNSONS LANDING 5/8/01 990.200 <LLD 1.35E-02 0.9 MI ENE - JOHNSONS LANDING 5/14/01 730.500 <LLD 1.75E-02 0.9 MI ENE - JOHNSONS LANDING 5/21/01 852.800 <LLD 2.48E-02 0.9 MI ENE - JOHNSONS LANDING 5/28/01 851.500 <LLD 2.37E-02 0.9 MI ENE - JOHNSONS LANDING 6/4/01 889.600 <LLD 1.31 E-02 0.9 MI ENE - JOHNSONS LANDING 6/11/01 906.400 <LLD 1 24E-02 0.9 MI ENE - JOHNSONS LANDING 6/18/01 542.400 <LLD 2.16E-02 0.9 MI ENE - JOHNSONS LANDING 6/25/01 744.400 <LLD 2.29E-02 0.9 MI ENE - JOHNSONS LANDING 7/3/01 913.600 <LLD 1.63E-02 0.9 MI ENE - JOHNSONS LANDING 7/9/01 723.100 <LLD 2.51 E-02 0.9 MI ENE - JOHNSONS LANDING 7/16/01 881.200 <LLD 1.20E-02 0.9 MI ENE - JOHNSONS LANDING 7/23/01 900.700 <LLD 1.32E-02 0.9 MI ENE - JOHNSONS LANDING 7/30/01 873.600 <LLD 1.77E-02 0.9 MI ENE - JOHNSONS LANDING 8/6/01 892.400 <LLD 1.27E-02 0.9 MI ENE - JOHNSONS LANDING 8/13/01 894 600 <LLD 1.28E-02 0.9 MI ENE - JOHNSONS LANDING 8/20/01 890.800 <LLD 1.31 E-02 0.9 MI ENE - JOHNSONS LANDING 8/27/01 897.500 <LLD 2.24E-02 0.9 MI ENE - JOHNSONS LANDING 9/4/01 1011.700 <LLD 2.08E-02 0.9 MI ENE - JOHNSONS LANDING 9/10/01 770.200 <LLD 1.84E-02 0.9 MI ENE - JOHNSONS LANDING 9/17/01 901.300 <LLD 1.69E-02 0.9 MI ENE - JOHNSONS LANDING 9/24/01 862.100 <LLD 1.69E-02 0.9 MI ENE - JOHNSONS LANDING 10/1/01 860.900 <LLD 3.10E-02 Page 10 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity. cubic meters Concentration (Activity): pCi/cubic meter Analysis: Iodine Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 10/8/01 871.600 <LLD 9.47E-03 5 0.9 MI ENE - JOHNSONS LANDING 10/15/01 848.300 <LLD 1.94E-02 5 0.9 MI ENE - JOHNSONS LANDING 10/22/01 859.000 <LLD 1.99E-02 5 0.9 MI ENE - JOHNSONS LANDING 10/29/01 871.700 <LLD 1.50E-02 5 0.9 MI ENE - JOHNSONS LANDING 11/5/01 956.700 <LLD 1.60E-02 5 0.9 MI ENE - JOHNSONS LANDING 11/12/01 615.000 <LLD 1.88E-02 5 0.9 MI ENE - JOHNSONS LANDING 11/19/01 700.000 <LLD 1.54E-02 5 0.9 MI ENE JOHNSONS LANDING 11/26/01 712.000 <LLD 2.OQE-02 5 0.9 MI ENE - JOHNSONS LANDING 12/3/01 741.400 <LLD 1.46E-02 5 0.9 MI ENE - JOHNSONS LANDING 12/10/01 691.800 <LLD 2.11E-02 5 0.9 MI ENE - JOHNSONS LANDING 12/18/01 812.800 <LLD 1.0OE-02 5 0.9 MI ENE - JOHNSONS LANDING 12/24/01 593.600 <LLD 2.65E-02 5 0.9 MI ENE - JOHNSONS LANDING 12/31/01 691.200 <LLD 4.20E-02 5 0.9 MI ENE - JOHNSONS LANDING 1/2/01 578.700 <LLD 2.52E-02 6 0.3 MI SW - INFORMATION CENTER 1/8/01 519.900 <LLD 4.25E-02 6 0.3 MI SW - INFORMATION CENTER 1/15/01 604.400 <LLD 3.26E-02 6 0.3 MI SW - INFORMATION CENTER 1/22/01 607.400 <LLD 2.46E-02 6 0.3 MI SW - INFORMATION CENTER 1/29/01 594.100 <,LLD 4.07E-02 6 0.3 MI SW - INFORMATION CENTER 2/5/01 607.900 <LLD 2.30E-02 6 0.3 MI SW - INFORMATION CENTER 2/13/01 709.200 <LLD 2.09E-02 6 0.3 MI SW - INFORMATION CENTER 2/19/01 499.400 <LLD 2.49E-02 6 0.3 MI SW - INFORMATION CENTER 2/26/01 609.800 <LLD 3.40E-02 6 0.3 MI SW - INFORMATION CENTER 3/5/01 599.200 <LLD 2.54E-02 6 0.3 MI SW - INFORMATION CENTER 3/12/01 603.700 <LLD 2.82E-02 6 0.3 MI SW - INFORMATION CENTER 3/19/01 605.000 <LLD 2.44E-02 6 0.3 MI SW - INFORMATION CENTER Page11of17

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubic meter Analysis: Iodine Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 3/26/01 599.800 <LLD 1.26E-02 6 0.3 MI SW - INFORMATION CENTER 4/2/01 594.500 <LLD 3.20E-02 6 0.3 MI SW - INFORMATION CENTER 4/9/01 615.700 <LLD 3.16E-02 6 0.3 MI SW - INFORMATION CENTER 604.800 <LLD 2.47E-02 4/23/01 6 0.3 MI SW - INFORMATION CENTER 605.300 <LLD 2.35E-02 4/30/01 6 0.3 MI SW - INFORMATION CENTER 5/8/01 704.900 <LLD 2.47E-02 6 0.3 MI SW - INFORMATION CENTER 5/14/01 514.800 <LLD 3.71 E-02 6 0.3 MI SW - INFORMATION CENTER 618.600 <LLD 2.41 E-02 5/21/01 6 0.3 MI SW - INFORMATION CENTER 5/28/01 619.000 <LLD 1.58E-02 6 0.3 MI SW - INFORMATION CENTER 6/4/01 609.300 <LLD 2.05E-02 6 0.3 MI SW - INFORMATION CENTER 617.700 <LLD 1.78E-02 6/11/01 6 0.3 MI SW - INFORMATION CENTER 6/18/01 630.800 <LLD 1.58E-02 6 0.3 MI SW - INFORMATION CENTER 632.000 <LLD 3.18E-02 6/25/01 6 0.3 MI SW - INFORMATION CENTER 7/3/01 725.600 <LLD 3.15E-02 6 0.3 MI SW - INFORMATION CENTER 7/9/01 541.300 <LLD 3.58E-02 6 0.3 MI SW - INFORMATION CENTER 7/16/01 637.900 <LLD 3.18E-02 6 0.3 MI SW - INFORMATION CENTER 7/23/01 640.600 <LLD 2.66E-02 6 0.3 MI SW - INFORMATION CENTER 7/30/01 368.500 <LLD 5.96E-02 5 0.3 MI SW - INFORMATION CENTER 8/6/01 658.400 <LLD 2.03E-02 6 0.3 MI SW - INFORMATION CENTER 8/13/01 630.300 <LLD 1.52E-02 6 0.3 MI SW - INFORMATION CENTER 646.600 <LLD 2.97E-02 6 8/20/01 0.3 MI SW - INFORMATION CENTER 644.100 <LLD 3.07E-02 6 8/27/01 0.3 MI SW - INFORMATION CENTER 9/4/01 734.600 <LLD 1.32E-02 6 0.3 MI SW - INFORMATION CENTER 9/10/01 555.300 <LLD 1.88E-02 6 0.3 MI SW - INFORMATION CENTER 9/17/01 634.900 <LLD 2.08E-02 6 0.3 MI SW - INFORMATION CENTER Page 12 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Aclivity): pCi/cubic meter Analysis: Iodine Sample Point Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 658.600 <LLD 2.15E-02 9/24/01 0.3 MI SW - INFORMATION CENTER 607.900 <LLD 2.28E-02 10/1/01 0.3 MI SW - INFORMATION CENTER 10/8/01 654.000 <LLD 3.59E-02 0.3 MI SW - INFORMATION CENTER 10/15/01 615.300 <LLD 3.92E-02 0.3 MI SW - INFORMATION CENTER 10/22/01 633.800 <LLD 2.04E-02 0.3 MI SW - INFORMATION CENTER 10/29/01 637.300 <LLD 3.31 E-02 0.3 MI SW - INFORMATION CENTER 11/5/01 715.500 <LLD 3-26E-02 0.3 MI SW - INFORMATION CENTER 11/12/01 652.500 <LLD 2.97E-02 0.3 MI SW - INFORMATION CENTER 11/19/01 709.600 <LLD 2.54E-02 0.3 MI SW - INFORMATION CENTER 11/26/01 742.900 <LLD 3.72E-02 0.3 MI SW - INFORMATION CENTER 12/3/01 763.600 <LLD 2.63E-02 0.3 MI SW - INFORMATION CENTER 12/10/01 723.200 <LLD 3.02E-02 0.3 MI SW - INFORMATION CENTER 12/18/01 848.200 <LLD 2.89E-02 0.3 MI SW - INFORMATION CENTER 631.900 <LLD 2.32E-02 12/24/01 0.3 MI SW - INFORMATION CENTER 739.600 <LLD 5.04E-02 12/31/01 0.3 MI SW - INFORMATION CENTER 1/2/01 590.700 <LLD 3.55E-02 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 1/8/01 510.900 <LLD 1.85E-02 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 1/,15/01 594.200 <LLD 2-39E-02 6.3 MI ESE - HARTSVILLE CF&L SUBSTATION 1/22/01 605.900 <LLD 3.55E-02 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 1/29/01 591.900 <LLD 1.60E-02 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/5/01 603.500 <LLD 2.25E-02 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/13/01 685.000 <LLD 3.91 E-02 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/19/01 517.700 <LLD 2.59E-02 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/26/01 599.400 <LLD 1.46E-02 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 3/5/01 602.700 <LLD 2.40E-02 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION Page 13 of 17

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubicmeter Analysis: Iodine Sample Date Quantity Efficiency Activity 2 Sigma Error LLD Sanip,de Point Samp7 3/12/01 594.800 <LLD 9.36E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 609.800 <LLD 2.05E-02 3/19/01 77 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 599.900 <LLD 2.35E-02 3/26/01 77 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 4/2/01 596.600 <LLD 1.71 E-02 77 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 4/9/01 607.400 <LLD 1.81E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 4/16/01 612.500 <LLD 2.77E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 602.100 <LLD 3.18E-02 4/23/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 602.900 <LLD 1.40E-02 4/30/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 702.600 <LLD 1.67E-02 5/8/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 531.900 <LLD 3.52E-02 5/14/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 5/21/01 596.900 <LLD 2.38E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 5/28/01 612.900 <LLD 2.90E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 620.300 <LLD 2.41 E-02 6/4/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 611.400 <LLD 1.48E-02 6/11/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 532.000 <LLD 3.49E-02 6/18/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 555.100 <LLD 3.13E-02 6/25/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 7'3/01 624.700 <LLD 3.36E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 7;9101 453.600 <LLD 1.34E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 546.600 <LLD 2.86E-02 7/16/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 538.200 <LLD 1.25E-02 7/23/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 552.900 <LLD 1.85E-02 7/30/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 528.200 <LLD 2.66E-02 8/6/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 555.900 <LLD 2.29E-02 8/13/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 539.600 <LLD 3.14E-02 8/20/01 7 6.3 Mi ESE - HARTSVILLE CP&L SUBSTATION 540.800 <LLD 3.03E-02 8/27/01 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION Page 14 of 17

RNP RadiologicalEnvironmental Monitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubicmeter Analysis.: Iodine Sample Poi nt I Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 9/4/01 625.500 <LLD 1.80E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 9/10/01 465.300 <LLD 3.19E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 9/17/01 542.500 <LLD 2.70E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 9/24/01 534.300 <LLD 3.86E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 10/1/01 527.800 <LLD 3.15E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 10/15/01 518.800 <LLD 3.33E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/5/01 436.300 <LLD 4.67E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/12/01 718.400 <LLD 2.59E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/19/01 700.900 <LLD 2.44E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/26/01 720.200 <LLD 1.99E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/3/01 714.100 <LLD 8.63E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/10/01 708.200 <LLD 2.66E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/18/01 797.900 <LLD 8.61 E-03 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/24/01 599.400 <LLD 2.16E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 12/31/01 697.500 <LLD 4.16E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 1/2/01 483.000 <LLD 5.05E-02 55 0.3 MI SSE - SITE BOUNDARY 1/8'01 432.100 <LLD 4.26E-02 55 0.3 MI SSE - SITE BOUNDARY 1)15/01 508.000 <1LLD 3.36E-02 55 0.3 MI SSE - SITE BOUNDARY 1/22/01 510.400 <LLD 2.99E-02 55 0.3 MI SSE - SITE BOUNDARY 1/29/01 499.000 <LLD 3.69E-02 55 0.3 MI SSE - SITE BOUNDARY 2/5/01 512.900 <LLD 3.36E-02 55 0.3 MI SSE - SITE BOUNDARY 2/13/01 597.000 <LLD 2.1 OE-02 55 0.3 MI SSE - SITE BOUNDARY 2/19/01 419.800 <LLD 5.82E-02 55 0.3 MI SSE - SITE BOUNDARY 2/26/01 515.500 <LLD 2.88E-02 55 0.3 MI SSE - SITE BOUNDARY 3/5/01 510.000 <LLD 3.29E-02 55 0.3 MI SSE - SITE BOUNDARY Page 15 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity. cubic meters Concentration (Activity): pCi/cubic meter Analysis: Iodine Sample Poin nt Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 3/12/01 502.400 <LLD 2.97E-02 55 0.3 MI SSE - SITE BOUNDARY 3/19/01 515.500 <LLD 3.26E-02 55 0.3 MI SSE - SITE BOUNDARY 3/26/01 505.100 <LLD 3.42E-02 55 0.3 MI SSE - SITE BOUNDARY 4/2/01 503.000 <LLD 3.46E-02 55 0.3 MI SSE - SITE BOUNDARY 4/9/01 517.600 <LLD 3.38E-02 55 0.3 MI SSE - SITE BOUNDARY 4/16/01 519.900 <LLD 1.30E-02 55 0.3 MI SSE - SITE BOUNDARY 4/23/01 509.500 <LLD 3.35E-02 55 0.3 MI SSE - SITE BOUNDARY 4/30/01 512.000 <LLD 3.06E-02 55 0.3 MI SSE - SITE BOUNDARY 5/8/01 595.000 <LLD 2.49E-02 55 0.3 MI SSE - SITE BOUNDARY 5/14/01 456.000 <LLD 3.93E-02 55 0.3 MI SSE - SITE BOUNDARY 5/21/01 518.100 <LLD 3.18E-02 55 0.3 MI SSE - SITE BOUNDARY 5/28/01 518.800 <LLD 3.65E-02 55 0.3 MI SSE - SITE BOUNDARY 6/4/01 517.700 <LLD 1.90E-02 55 0.3 MI SSE - SITE BOUNDARY 6/11/01 518.600 <LLD 2.22E-02 55 0.3 MI SSE - SITE BOUNDARY 6/18/01 450.100 <LLD 5.67E-02 55 0.3 MI SSE - SITE BOUNDARY 6/225,'01 454.500 <LLD 3.77E-02 55 0.3 MI SSE - SITE BOUNDARY 7T3'01 517.900 <LLD 1.69E-02 55 0.3 MI SSE - SITE BOUNDARY Z;9u01 383.400 <LLD 3.86E-02 55 0.3 MI SSE - SITE BOUNDARY 7/16/01 453.400 <LLD 1.96E-02 55 0.3 MI SSE - SITE BOUNDARY 7/23/01 449.900 <LLD 3.73E-02 55 0.3 MI SSE - SITE BOUNDARY 7/30/01 443.800 <LLD 3.52E-02 55 0.3 MI SSE - SITE BOUNDARY 8/6/01 460.100 <LLD 3.77E-02 55 0.3 MI SSE - SITE BOUNDARY 8/13/01 438.900 <LLD 4.14E-02 55 0.3 MI SSE - SITE BOUNDARY 8/20/01 448.300 <LLD 3.69E-02 55 0.3 MI SSE - SITE BOUNDARY 8/27/01 446.900 <LLD 2.41 E-02 55 0.3 MI SSE - SITE BOUNDARY Page 16 of 17

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Concentration (Activity): pCi/cubic meter Analysis: Iodine Sample Poinnt Sample Date Quantity Efficiency Activity 2 Sigma Error LLD 508.700 <LLD 2.57E-02 55 0.3 MI SSE - SITE BOUNDARY 9/4/01 508.700 <LLD 2.57E-02 9/10/01 383.900 55 0.3 MI SSE - SITE BOUNDARY <LLD 2.97E-02 9/17/01 444.900 2.97E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 9/24/01 435.700 5.58E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 10/1/01 430.500 3.89E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 10/8/01 440.600 5.30E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 10/15/01 436.400 2.06E-02 55 0,3 MI SSE - SITE BOUNDARY <LLD 10/22/01 436.600 5.38E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 10/29/01 438.000 3.50E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 11/5/01 442.300 4.19E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 11/12/01 182.400 5.20E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 11/19/01 463.700 4.31 E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 11/26/01 473.800 4.54E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 12/3/01 477.200 2.79E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 12/10/01 477.400 3.67E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 1218/01 522.100 3.28E-02 55 0.3 MI SSE - SITE BOUNDARY <LLD 12.'24,01 395.600 1.86E 02 55 0.3 MI SSE - SITE BOUNDARY <LLD 4 3.53E-C2 12/3 1/01 469. 00 ,,LLD 55 0.3 MI SSE - SITE BOUNDARY Page 17 of 17

RNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Groundwater Quantity: Liters Analysis. Tritium Concentration (Activity): pCi/Liter Sample Point Sample Date Efficiency Quantity Activity 2 Sigma Error LLD 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 2/15/01 0.29 0.005 <LLD 2.95E+02 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 4/30/01 0.441 0.005 <LLD 2.89E+02 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 7/3/01 0.438 0.005 <LLD 2.94E+02 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 9/24/01 0.438 0.005 <LLD 3.16E+02 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 12/18/01 0.441 0.005 <LLD 2.96E+02 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 2/15/01 0.29 0.005 <LLD 2.95E+02 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 4/30/01 0.44 0.005 <LLD 2.90E+02 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 7/3/01 0.438 0.005 <LLD 2.94E+02 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 9/24/01 0.439 0.005 <LLD 3.16E+02 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 12/18/01 0.44 0.005 <LLD 2.97E+02 Page 1 of I

RNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type: Siujac-eWater Analysis: Trititum Quantity: Liters Concentration (Actih itv): pCi/Liter Samnle Date Efficiency Quantity Activity 2 Sigma Error LLD Sample Point 2.88E+02 0.29 0.005 4.40E+03 2.04E+02 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 1/31/01 0.29 0.005 4.40E+03 4.45E+03 2.40E+02 3.01 E+02 2/28/01 0.005 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.441 3/31/01 3.26E+03 2.25E+02 3.OOE+02 0.442 0.005 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.286 2.79E+03 5.64E+02 8.39E+02 4/30/01 0.005 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 2.97E+02 5/31/01 0.442 2.55E+03 2.16E+02 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.005 0.44 2.37E+03 2.11 E+02 2.93E+02 6/30/01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.005 0.439 1.86E+03 2.05E+02 2.95E+02 7/31/01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.005 0.436 1.18E+03 1.99E+02 3.01 E+02 8/31/01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.005 9/30/01 0.288 1.76E+03 5.49E+02 8.48E+02 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.005 0.286 2.13E+03 5.60E+02 8.54E+02 10/31/01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.005 11/30/01 0.444 1.41 E+03 1.95E+02 2.87E+02 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.005 12/31/01 0.439 1.53E+03 2.OOE+02 2.92E+02 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 0.005 1/31/01 0.29 <LLD 2.88E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 2/28/01 0.441 <LLD 3.01 E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 3/31/01 0.44 <LLD 3.01 E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 4/30/01 0.44 <LLD 2.90E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 5/31/01 0.443 <LLD 2.97E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 6/30/01 0.437 <LLD 2.95E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 7/31/01 0.437 <LLD 2.96E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 8/31/01 0.435 <LLD 3.01 E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 9/30/01 0.437 <LLD 3.17E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 10/31/01 0.286 <LLD 2.99E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 11/30/01 0.441 <LLD 2.89E+02 41 7.2 MI NNW - BLACK CREEK - CONTROL 0.005 12/31/01 0.438 <LLD 2-93E+02 0.005 41 7.2 MI NNW - BLACK CREEK - CONTROL Page I of 2

RNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Surface Water Quantirv: Liters Analysis: Tritium Concentration(Activiti_): pCi/Liter

.amjnn~l Point Sample Date Efficiency Quantity Activity 2 Sigma Error LLD aumptv I utitt - -----------

57 0.9 MI NNW - ASH POND 1/31/01 0.29 0.005 4.04E+03 2.01 E+02 2.88E+02 2/28/01 0.442 0.005 3.96E+03 2.34E+02 3.OOE+02 57 0.9 MI NNW - ASH POND 3/31/01 0.442 0.005 3.40E+03 2.26E+02 2.98E+02 57 0.9 MI NNW - ASH POND 4/30/01 0.286 0.005 2.86E+03 5.65E+02 8.39E+02 57 0.9 MI NNW - ASH POND 5/31/01 0.443 0.005 2.53E+03 2.15E+02 2.97E+02 57 0.9 MI NNW - ASH POND 7/31/01 0.436 0.005 1.68E+03 2.04E+02 2.97E+02 57 0.9 MI NNW - ASH POND 8/31/01 0.436 0.005 1.32E+03 2.01 E+02 3.01E+02 57 0.9 MI NNW - ASH POND 9/30/01 0.288 0.005 2.14E+03 5.56E+02 8.48E+02 57 0.9 MI NNW - ASH POND 10/31/01 0.286 0.005 1.77E+03 5.53E+02 8.54E+02 57 0.9 MI NNW - ASH POND 12/31/01 0.44 0.005 2.71 E+03 2.15E+02 2.92E+02 57 0.9 MI NNW - ASH POND Page 2 of 2

2001 RNP A Progress Energy Company Radiological Environmental Monitoring Gamma Isotopic Report Comments

"* The Less than LLD (<LLD) represents that no activity was present, but lists the LLD values.

"* There are no 2 sigma error values reported when activity is <LLD.

"* NO-ACT refers to no detectable gamma activity being present in the samples. Refer to Table 8 for typical gamma Lower Limits of Detection for specific nuclides.

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Mediai7pe: Air Particulate Quantity: CUBIC METERS Activity: pCi/cubic meter Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 1 26 MI ESE - FLORENCE - CONTROL 2/15/01 6480 BE-7 8.45E-02 1.70E-02 1 26 MI ESE - FLORENCE - CONTROL 5/15/01 5843.8 BE-7 1.09E-01 1.76E-02 1 26 MI ESE - FLORENCE - CONTROL 5/15/01 5843.8 PB-214 1.96E-03 1.07E-03 1 26 MI ESE - FLORENCE - CONTROL 8/15/01 6213.4 BE-7 1.08E-01 2.05E-02 1 26 MI ESE - FLORENCE - CONTROL 11/15/01 8721 BE-7 1.28E-01 9.90E-03 2 0.2 MI S - INFORMATION CENTER 2/15/01 8025.7 BE-7 1.05E-01 1.81 E-02 2 0.2 MI S - INFORMATION CENTER 2/15/01 8025.7 PB-214 2.17E-03 1.20E-03 2 0.2 MI S - INFORMATION CENTER 5/15/01 7852 BE-7 1.13E-01 1.71 E-02 2 0.2 MI S - INFORMATION CENTER 5/15/01 7852 K-40 2.44E-02 1.24E-02 2 0.2 MI S - INFORMATION CENTER 8/15/01 7679.8 K-40 2.86E-02 1.12E-02 2 0.2 MI S - INFORMATION CENTER 8/15/01 7679.8 BE-7 1.17E-01 2.22E-02 2 0.2 MI S- INFORMATION CENTER 11/15/01 8537.7 BE-7 1.OOE-01 1.07E-02 3 0.7 MI N - MICROWAVE TOWER 2/15/01 10163 BE-7 9.94E-02 1.53E-02 3 0.7 MI N - MICROWAVE TOWER 5/15/01 9930.8 BE-7 1.17E-01 1.45E-02 3 0.7 MI N - MICROWAVE TOWER 8/15/01 7386.9 BE-7 1.69E-01 2.03E-02 3 0.7 MI N - MICROWAVE TOWER 11/15/01 10307.3 BI-214 1.63E-03 6.27E-04 3 0.7 MI N- MICROWAVE TOWER 11/15/01 10307.3 BE-7 1.18E-01 1.09E-02 3 0.7 MI N - MICROWAVE TOWER 11/15/01 10307.3 PB-214 1.25E-03 7.77E-04 4 0.4 MI ESE - SPILLWAY 2/15/01 10867.4 BE-7 1.01 E-01 1.49E-02 4 0.4 MI ESE - SPILLWAY 5/15/01 6638.2 BE-7 1.16E-01 1.47E-02 4 0.4 MI ESE - SPILLWAY 8/15/01 8130 BE-7 1.16E-01 1.46E-02 4 0.4 MI ESE - SPILLWAY 11/15/01 7931.3 BE-7 1.22E-01 1.09E-02 4 0.4 MI ESE - SPILLWAY 11/15/01 7931.3 PB-214 1.78E-03 6.39E-04 4 0.4 MI ESE - SPILLWAY 11/15/01 7931.3 K-40 2.15E-02 5.04E-03 4 0.4 MI ESE - SPILLWAY 11/15/01 7931.3 BI-214 1.60E-03 7.02E-04 5 0.9 MI ENE -JOHNSONS LANDING 2/15/01 7636.8 BE-7 9.28E-02 1.92E-02 Page 1 of 2

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media TIVpe: Air Particulate Quantityv: ('UBIC MFTERS Activity: pCi/cubicmeter Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 5 0.9 MI ENE- JOHNSONS LANDING 2/15/01 7636.8 K-40 3.32E-02 1.21E-02 5 0.9 MI ENE- JOHNSONS LANDING 5/15/01 10399.8 BE-7 1.13E-01 1.18E-02 5 0.9 MI ENE - JOHNSONS LANDING 8/15/01 11412.8 BE-7 9.76E-02 1.61 E-02 5 0.9 MI ENE- JOHNSONS LANDING 11/15/01 10825.6 BE-7 1.11E-01 8.90E-03 5 0.9 MI ENE - JOHNSONS LANDING 11/15/01 10825.6 PB-214 1.98E-03 6.76E-04 6 0.3 MI SW - INFORMATION CENTER 2/15/01 7738.5 BE-7 1.08E-01 1.60E-02 6 0.3 MI SW - INFORMATION CENTER 5/15/01 7468.2 BE-7 1.26E-01 1.54E-02 6 0.3 MI SW - INFORMATION CENTER 8/15/01 8076.7 BE-7 1.01 E-01 1.52E-02 6 0.3 MI SW - INFORMATION CENTER 11/15/01 9675.3 PB-214 1.64E-03 6.21E-04 6 0.3 MI SW - INFORMATION CENTER 11/15/01 9675.3 BE-7 1.21 E-01 1.05E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 2/15/01 7706.4 BE-7 9.39E-02 1.67E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 5/15/01 7784.6 BE-7 1.16E-01 1.54E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 8/15/01 7059.1 BE-7 1.06E-01 1.52E-02 7 6.3 MI ESE - HARTSVILLE CP&L SUBSTATION 11/15/01 7184.8 BE-7 1.38E-01 1.11E-02 55 0.3 MI SSE - SITE BOUNDARY 2/15/01 6510.7 K-40 2.39E-02 1.15E-02 55 0.3 MI SSE - SITE BOUNDARY 2/15/01 6510.7 BE-7 9.60E-02 1.53E-02 55 0.3 MI SSE - SITE BOUNDARY 5/15/01 6590.8 BE-7 1.16E-01 1.60E-02 55 0.3 MI SSE - SITE BOUNDARY 8/15/01 5815.8 BE-7 1.31 E-01 2.67E-02 55 0.3 MI SSE - SITE BOUNDARY 11/15/01 6086 BE-7 1.22E-01 9.80E-03 Page 2 of 2

RNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report Aledia Type: Aquatic Vegetation Quantit: (rG n *.ai (wet)

Activitw p ('i/g "l Owet Q--ID pn;jlt Samnle Date Ouantity Isotope Activity 2 Sigma Error LLD

..)UIILJitI I ULILL 575.2 TL-208 2.97E-02 1 .47E-02 5/29/01 2.97E-02 1.47E-02 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 575.2 TL-208 1-131 5/29/01 575.2 3.34E-02 41 7.2 MI NNW - BLACK CREEK - CONTROL CS-134 2.54E-02 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 575.2 CS-137 1.95E-02 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 575.2 K-40 575.2 1.19E+00 3.66E-01 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 5.84E-01 4.16E-01 RA-226 45 SITE VARIES WITHIN LAKE ROBINSON 5/29/01 625.1 CS-137 625.1 2.78E-02 45 SITE VARIES WITHIN LAKE ROBINSON 5/29/01 CS-134 2.75E-02 45 SITE VARIES WITHIN LAKE ROBINSON 5/29/01 625.1 1-131 3.OOE-02 45 SITE VARIES WITHIN LAKE ROBINSON 5/29/01 625.1 AC-228 625.1 2.08E-01 6.64E-02 45 SITE VARIES WITHIN LAKE ROBINSON 5/29/01 TL-208 4.23E-02 2.62E-02 45 SITE VARIES WITHIN LAKE ROBINSON 5/29/01 625.1 K-40 1.02E+00 2.98E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/29/01 625.1 BE-7 6.98E-01 2.08E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/29/01 625.1 CO-58 2.91E-01 3.54E-02 625.1 45 SITE VARIES WITHIN LAKE ROBINSON 5/29/01 877.1 PB-212 1.17E-01 1.67E-02 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 RA-226 2.84E-01 1.92E-01 46 4-9 MI ESE - PRESTWOOD LAKE 5/31/01 877.1 BE-7 5.28E-01 1.45E-01 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 877.1 K-40 5.13E-01 1.66E-01 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 877.1 AC-228 3.08E-01 5.83E-02 46 4-9 MI ESE - PRESTWOOD LAKE 5/31/01 877.1 CO-58 7.96E-02 1.38E-02 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 877.1 CO-60 6.65E-02 1.82E-02 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 877.1 CS-137 1.75E-02 1.20E-02 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 877.1 1-131 877.1 1-60E-02 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 1.67E-02 CS-134 46 4.9 MI ESE- PRESTWOOD LAKE 5/31/01 877.1 TL-208 877.1 3.35E-02 1.44E-02 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 K-40 8.97E-01 2.74E-01 5/30/01 785 54 10.1 MI E - AUBURNDALE PLANTATION Page 1 of 2

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report MedicTve: Aquatic Vegetation Quantity: Granms (wef)

Activityv: )Ci4/gram wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 785 CS-134 4.23E-02 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 785 1-131 3.84E-02 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 785 AC-228 1.50E+00 1.32E-01 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 785 RA-226 4.02E+00 6-64E-01 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 785 PB-214 2.95E-01 4.87E-02 54 10.1 MI E -AUBURNDALE PLANTATION 5/30/01 785 BI-214 3.57E-01 6.83E-02 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 785 TL-208 1.31 E-01 2.74E-02 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 785 CS-137 2.93E-02 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 785 BE-7 5.97E-01 1.93E-01 54 10.1 MI E- AUBURNDALE PLANTATION 5/30/01 785 PB-212 2.91 E-01 3.58E-02 Page 2 oj'2

RNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report Media Tx7pe: Bottoni Feeders Quantity: Grams (et)

Activity: p i/glram wet Sample Date Quantity Isotope Activity 2 Sigma Error LLD Sample Point 5/30/01 385.9 K-40 3.95E+00 1.70E+00 45 SITE VARIES WITHIN LAKE ROBINSON 11/13/01 574 CS-137 6.59E-02 4.33E-02 45 SITE VARIES WITHIN LAKE ROBINSON 11/13/01 574 K-40 4.76E+00 1.22E+00 45 SITE VARIES WITHIN LAKE ROBINSON 5/31/01 442.6 CS-137 1.58E-01 5.28E-02 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 442.6 K-40 5.10E+00 1.30E+00 46 4.9 MI ESE - PRESTWOOD LAKE 11/13/01 499 K-40 4.00E+00 9.91E-01 46 4.9 MI ESE - PRESTWOOD LAKE 5/29/01 306.5 K-40 3.40E+00 1.64E+00 47 13 MI NNW - LAKE BEE - CONTROL 11/12/01 462.3 TL-208 5.05E-02 4.05E-02 47 13 MI NNW - LAKE BEE - CONTROL 11/12/01 462.3 K-40 4.98E+00 1.15E+00 47 13 MI NNW - LAKE BEE - CONTROL Page 1 off!

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Medi Tape: Bottom Sediment Quantit: Granms (dryv)

Activity: pCi/granz dr)

Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 683.3 TL-208 7.40E-01 1.32E-01 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 683.3 PB-212 2.31 E+00 1,93E-01 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 683.3 BI-214 1.18E+00 2.25E-01 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 683.3 PB-214 1.53E+00 2.43E-01 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 683.3 RA-226 2.51 E+00 1.52E+00 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 683.3 AC-228 2.04E+00 3.83E-01 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/29/01 683.3 K-40 2.39E+00 8.22E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 277.7 CS-137 1.26E+00 1.65E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 277.7 K-40 2.72E+00 9.30E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 277.7 TL-208 7.32E-01 1.12E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 277.7 PB-212 2.04E+00 1.76E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 277.7 BI-214 1.63E+00 2.44E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 277.7 PB-214 1.93E+00 2.38E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 277.7 RA-226 6.41 E+00 2.40E+00 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 277.7 AC-228 2.11E+00 3.88E-01 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 277.7 CO-60 3.54E-01 1.03E-01 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 268.2 AC-228 1.21 E+00 3.98E-01 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 268.2 K-40 2.76E+00 1.33E+00 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 268.2 CS-1i37 1.31 E+00 1.74E-01 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 268.2 RA-226 7.OOE+00 2.29E+00 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 268.2 PB-214 1.69E+00 2.85E-01 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 268.2 BI-214 1.58E+00 2.80E-01 46 4.9 MI ESE-PRESTWOOD LAKE 5/31/01 268.2 PB-212 1.12E+00 1.51E-01 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 268.2 TL-208 3.27E-01 1.08E-01 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 1052.1 AC-228 1.79E+00 2.76E-01 54 10.1 MI E -AUBURNDALE PLANTATION 5/30/01 1052.1 TL-208 5.70E-01 7.68E-02 Page I of 2

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Mediac Type: Bottom Sediment Quantity: Grams (dr?')

Activityv: pCi/gram dr ISample Point Sample Date Quantit, Isotope Activity 2 Sigma Error LLD 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 1052.1 PB-212 1.46E+00 1.27E-01 5/30/01 1052.1 BI-214 1.23E+00 1.68E-01 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 1052.1 PB-214 1.49E+00 1.99E-01 54 10.1 MI E -AUBURNDALE PLANTATION 5/30/01 1052.1 RA-226 5.08E+00 1.44E+00 54 10.1 MI E - AUBURNDALE PLANTATION 5/30/01 1052.1 K-40 2.03E+00 7.11E-01 54 10.1 MI E -AUBURNDALE PLANTATION Page 2 of 2

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media *Tvpe: Broadleat Vegetation Quantity: Grams Media: Cherry Activity: pCi/gramn Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 50 SSE - CP&L PROPERTY 5/2/01 421.7 1-131 <LLD 2.07E-02 50 SSE - CP&L PROPERTY 5/2/01 421.7 CS-134 <LLD 2.62E-02 50 SSE - CP&L PROPERTY 5/2/01 421.7 CS-137 <LLD 2.35E-02 50 SSE - CP&L PROPERTY 5/2/01 421.7 K-40 3.50E+00 4.94E-01 50 SSE - CP&L PROPERTY 6/4/01 419.5 BE-7 6.65E-01 2.06E-01 50 SSE - CP&L PROPERTY 6/4/01 419.5 K-40 3.08E+00 5.94E-01 50 SSE - CP&L PROPERTY 6/4/01 419.5 1-131 <LLD 3.14E-02 50 SSE - CP&L PROPERTY 6/4/01 419.5 CS-134 <LLD 2.88E-02 50 SSE - CP&L PROPERTY 6/4/01 419.5 CS-137 <LLD 3.43E-02 50 SSE - CP&L PROPERTY 6/18/01 430.9 BE-7 3.76E-01 1.48E-01 50 SSE - CP&L PROPERTY 6/18/01 430.9 CS-137 <LLD 2.51 E-02 50 SSE - CP&L PROPERTY 6/18/01 430.9 CS-1i34 <LLD 2.44E-02 50 SSE - CP&L PROPERTY 6/18/01 430.9 1-131 <LLD 2.47E-02 50 SSE - CP&L PROPERTY 6/18/01 430.9 K-40 3.43E+00 4.79E-01 50 SSE - CP&L PROPERTY 6/18/01 430.9 PB-212 5.37E-02 2.89E-02 50 SSE - CP&L PROPERTY 7/19/01 477.2 CS-134 <LLD 3.18E-02 50 SSE - CP&L PROPERTY 7/19/01 477.2 BE-7 6.46E-01 2.13E-01 50 SSE - CP&L PROPERTY 7/19/01 477.2 K-40 2.45E+00 4.97E-01 50 SSE - CP&L PROPERTY 7/19/01 477.2 TL-208 4.20E-02 2.75E-02 50 SSE - CP&L PROPERTY 7/19/01 477.2 AC-228 1.25E-01 8.17E-02 50 SSE - CP&L PROPERTY 7/19/01 477.2 CS-137 <LLD 2.97E-02 50 SSE - CP&L PROPERTY 7/19/01 477.2 1-131 <LLD 2.31 E-02 50 SSE - CP&L PROPERTY 8/24/01 371 K-40 1.82E+00 4.31E-01 50 SSE - CP&L PROPERTY 8/24/01 371 BE-7 5.65E-01 2.68E-01 50 SSE - CP&L PROPERTY 8/24/01 371 TL-208 4.52E-02 3.87E-02 50 SSE - CP&L PROPERTY 8/24/01 371 RA-226 6.67E-01 6.06E-01 Page 1 of 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Broadleaf Vegetation Quantity: Grains Media: Cherry Activity: pCi/gram Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD SSE - CP&L PROPERTY 8/24/01 371 AC-228 2.34E-01 8.83E-02 50 50 SSE - CP&L PROPERTY 8/24/01 371 1-131 <LLD 3.87E-02 8/24/01 371 CS-134 <LLD 4.07E-02 50 SSE - CP&L PROPERTY 8/24/01 371 CS-137 <LLD 3.88E-02 50 SSE - CP&L PROPERTY 9/20/01 438.1 CS-137 <LLD 3.06E-02 50 SSE - CP&L PROPERTY SSE - CP&L PROPERTY 9/20/01 438.1 K-40 1.43E+00 4.88E-01 50 9/20/01 438.1 AC-228 2.01 E-01 1.10E-01 50 SSE - CP&L PROPERTY SSE - CP&L PROPERTY 9/20/01 438.1 CS-1i34 <LLD 3.35E-02 50 9/20/01 438.1 BE-7 6.22E-01 2.69E-01 50 SSE - CP&L PROPERTY 9/20/01 438.1 1-131 <LLD 3.47E-02 50 SSE - CP&L PROPERTY 5/2/01 426.7 1-131 <LLD 3.43E-02 51 SSW - CP&L PROPERTY 5/2/01 426.7 CS-134 <LLD 3.15E-02 51 SSW - CP&L PROPERTY 5/2/01 426.7 CS-137 <LLD 2.96E-02 51 SSW - CP&L PROPERTY SSW - CP&L PROPERTY 5/2/01 426.7 K-40 5.60E+00 5.91 E-01 51 6/4/01 365.5 CS-137 <LLD 3.82E-02 51 SSW - CP&L PROPERTY 6/4/01 365.5 BE-7 3.96E-01 2.1 OE-01 51 SSW - CP&L PROPERTY 6/4/01 365.5 CS-134 <LLD 4.26E-02 51 SSW - CP&L PROPERTY 6/4/01 365.5 1-131 <LLD 3.82E-02 51 SSW - CP&L PROPERTY 6/4/01 365.5 K-40 3.75E+00 7.32E-01 51 SSW - CP&L PROPERTY 6/18/01 452.6 BE-7 5.46E-01 1.37E-01 51 SSW - CP&L PROPERTY SSW - CP&L PROPERTY 6/18/01 452.6 CS-134 <LLD 2.63E-02 51 6/18/01 452.6 1-131 <LLD 2.29E-02 51 SSW - CP&L PROPERTY 51 SSW - CP&L PROPERTY 6/18/01 452.6 K-40 3.50E+00 4.73E-01 6/18/01 452.6 CS-1i37 <LLD 1.90E-02 51 SSW - CP&L PROPERTY 6/18/01 452.6 PB-212 3.91E-02 2.71 E-02 51 SSW - CP&L PROPERTY 7/19/01 424.3 AC-228 1.33E-01 8.11 E-02 51 SSW - CP&L PROPERTY Page 2 of 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report MediciTjpe: Broadleaf Vegetation Quantity: Grains Media: Cherry Activity: pCi/gram Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 51 SSW - CP&L PROPERTY 7/19/01 424.3 CS-137 <LLD 3.32E-02 51 SSW - CP&L PROPERTY 7/19/01 424.3 1-131 <LLD 3.83E-02 51 SSW - CP&L PROPERTY 7/19/01 424.3 K-40 2.84E+00 5.03E-01 51 SSW - CP&L PROPERTY 7/19/01 424.3 BE-7 7.18E-01 2.29E-01 51 SSW - CP&L PROPERTY 7/19/01 424.3 CS-134 <LLD 3.63E-02 51 SSW - CP&L PROPERTY 8/24/01 396.2 BE-7 4.78E-01 2.21E-01 51 SSW - CP&L PROPERTY 8/24/01 396.2 K-40 2.59E+00 5.32E-01 51 SSW - CP&L PROPERTY 8/24/01 396.2 AC-228 1.57E-01 8.79E-02 51 SSW - CP&L PROPERTY 8/24/01 396.2 CS-137 <LLD 2.86E-02 51 SSW - CP&L PROPERTY 8/24/01 396.2 CS-134 <LLD 3.27E-02 51 SSW - CP&L PROPERTY 8/24/01 396.2 1-131 <LLD 3.69E-02 51 SSW - CP&L PROPERTY 9/20/01 424.5 CS-1i37 <LLD 2.27E-02 51 SSW - CP&L PROPERTY 9/20/01 424.5 1-131 <LLD 2.72E-02 51 SSW - CP&L PROPERTY 9/20/01 424.5 RA-226 3.88E-01 2.51E-01 51 SSW - CP&L PROPERTY 9/20/01 424.5 BE-7 8.98E-01 1.75E-01 51 SSW - CP&L PROPERTY 9/20/01 424.5 K-40 2.24E+00 4.20E-01 51 SSW - CP&L PROPERTY 9/20/01 424.5 PB-212 4.20E-02 2.48E-02 51 SSW - CP&L PROPERTY 9/20/01 424.5 CS-1i34 <LLD 2.56E-02 52 10 MI W - BETHUNE - CONTROL 5/2/01 378.4 1-131 <LLD 3.93E-02 52 10 MI W - BETHUNE - CONTROL 5/2/01 378.4 K-40 4.36E+00 5-63E-01 52 10 MI W - BETHUNE - CONTROL 5/2/01 378.4 CS-137 <LLD 3.76E-02 52 10 MI W - BETHUNE - CONTROL 5/2/01 378.4 CS-134 <LLD 4.02E-02 52 10MI W - BETHUNE - CONTROL 6/4/01 421.6 1-131 <LLD 2.77E-02 52 10 MI W - BETHUNE - CONTROL 6/4/01 421.6 BE-7 5.49E-01 2.42E-01 52 10MI W - BETHUNE - CONTROL 6/4/01 421.6 CS-134 <LLD 3.06E-02 52 10 M1W - BETHUNE - CONTROL 6/4/01 421.6 CS-137 <LLD 2.97E-02 Page 3 of 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Broadleaf Vegetation Quantity: Grains Media: Cherry Activity: pCi/grain Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 52 10 MI W - BETHUNE - CONTROL 6/4/01 421.6 K-40 2.78E+00 4.79E-01 52 10 MI W - BETHUNE - CONTROL 6/18/01 509.9 K-40 4.60E+00 4.71 E-01 52 10MI W - BETHUNE - CONTROL 6/18/01 509.9 CS-137 <LLD 2.61 E-02 52 10 MI W - BETHUNE - CONTROL 6/18/01 509.9 CS-134 <LLD 2.92E-02 52 10MI W - BETHUNE -CONTROL 6/18/01 509.9 1-131 <LLD 2.44E-02 52 10 MI W - BETHUNE - CONTROL 6/18/01 509.9 BE-7 3.71 E-01 2.01E-01 52 10MI W - BETHUNE - CONTROL 7/19/01 472.1 BE-7 8.71 E-01 2.02E-01 52 10 MI W - BETHUNE - CONTROL 7/19/01 472.1 1-131 <LLD 2.75E-02 52 10 MI W - BETHUNE - CONTROL 7/19/01 472.1 CS-137 <LLD 2.11E-02 52 10MI W - BETHUNE - CONTROL 7/19/01 472.1 CS-134 <LLD 2.59E-02 52 10 MI W - BETHUNE - CONTROL 7/19/01 472.1 K-40 3.19E+00 4.37E-01 52 10 MI W - BETHUNE - CONTROL 8/24/01 532.2 BE-7 7.09E-01 1.34E-01 52 10 MI W - BETHUNE - CONTROL 8/24/01 532.2 CS-134 <LLD 2.13E-02 52 10 MI W - BETHUNE - CONTROL 8/24/01 532.2 1-131 <LLD 2.05E-02 52 10 MI W - BETHUNE - CONTROL 8/24/01 532.2 CS-137 <LLD 1.99E-02 52 10 MI W - BETHUNE - CONTROL 8/24/01 532.2 K-40 2.41 E+00 3.29E-01 52 10 MI W - BETHUNE -CONTROL 9/20/01 513 BE-7 1.24E+00 2.45E-01 52 10 MI W - BETHUNE - CONTROL 9/20/01 513 K-40 4.31E+00 4.78E-01 52 10 MI W - BETHUNE - CONTROL 9/20/01 513 1-131 <LLD 3.28E-02 52 10 MI W - BETHUNE - CONTROL 9/20/01 513 CS-134 <LLD 2.41 E-02 52 10 MI W - BETHUNE - CONTROL 9/20/01 513 CS-137 <LLD 2.60E-02 Page 4 of 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Broadleaf Vegetation Quantit-y: Grams Media: Sassafras Activity: pCi/grain Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 50 SSE - CP&L PROPERTY 5/2/01 356 K-40 3.90E+00 6.73E-01 50 SSE - CP&L PROPERTY 5/2/01 356 CS-137 5.93E-02 3.44E-02 50 SSE - CP&L PROPERTY 5/2/01 356 1-131 <LLD 3.01 E-02 50 SSE - CP&L PROPERTY 5/2/01 356 CS-134 <LLD 3.25E-02 50 SSE - CP&L PROPERTY 5/2/01 356 BE-7 5.71E-01 2.99E-01 50 SSE - CP&L PROPERTY 6/4/01 372.6 K-40 3.95E+00 5.50E-01 50 SSE - CP&L PROPERTY 6/4/01 372.6 BE-7 6.88E-01 2.16E-01 SSE - CP&L PROPERTY 6/4/01 372.6 1-131 <LLD 2.49E-02 50 SSE - CP&L PROPERTY 6/4/01 372.6 CS-134 <LLD 2.57E-02 50 SSE - CP&L PROPERTY 6/4/01 372.6 CS-137 <LLD 2.92E-02 50 50 SSE - CP&L PROPERTY 6/18/01 355.9 1-131 <LLD 2.76E-02 50 SSE - CP&L PROPERTY 6/18/01 355.9 CS-134 <LLD 3.10E-02 50 SSE - CP&L PROPERTY 6/18/01 355.9 CS-137 4.62E-02 2.33E-02 50 SSE - CP&L PROPERTY 6/18/01 355.9 K-40 3.84E+00 5.52E-01 50 SSE - CP&L PROPERTY 6/18/01 355.9 BE-7 8.28E-01 2.03E-01 50 SSE - CP&L PROPERTY 7/19/01 482.8 BE-7 1.55E+00 2,40E-01 50 SSE - CP&L PROPERTY 7/19/01 482.8 K-40 2.61 E+00 4.60E-01 50 SSE - CP&L PROPERTY 7/19/01 482.8 1-131 <LLD 2.72E-02 50 SSE - CP&L PROPERTY 7/19/01 482.8 CS-134 <LLD 2.82E-02 50 SSE - CP&L PROPERTY 7/19/01 482.8 CS-1i37 <LLD 3.20E-02 50 SSE - CP&L PROPERTY 8/24/01 360.5 K-40 2.88E+00 5.90E-01 50 SSE -CP&L PROPERTY 8/24/01 360.5 BE-7 2.40E+00 3.30E-01 50 SSE - CP&L PROPERTY 8/24/01 360.5 1-131 <LLD 4.12E-02 50 SSE - CP&L PROPERTY 8/24/01 360.5 CS-134 <LLD 3.77E-02 50 SSE - CP&L PROPERTY 8/24/01 360.5 CS-137 <LLD 3.70E-02 SSE - CP&L PROPERTY 9/20/01 408.4 CS-137 <LLD 3.20E-02 50 Page 1 of 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Mledia T 7e: Broadleaf Vegetation Quantity. Grams Media: Sassafras Activity: pCikgrau Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 50 SSE - CP&L PROPERTY 9/20/01 408.4 BE-7 1.23E+00 3.06E-01 50 SSE - CP&L PROPERTY 9/20/01 408.4 1-131 <LLD 3.77E-02 50 SSE - CP&L PROPERTY 9/20/01 408.4 K-40 2.81E+00 4.11E-01 50 SSE - CP&L PROPERTY 9/20/01 408.4 CS-1i34 <LLD 3.40E-02 51 SSW - CP&L PROPERTY 5/2/01 375.8 CS-134 <LLD 3.43E-02 51 SSW - CP&L PROPERTY 5/2/01 375.8 BE-7 4.41 E-01 2.62E-01 51 SSW - CP&L PROPERTY 5/2/01 375.8 K-40 4.01 E+00 5.75E-01 51 SSW - CP&L PROPERTY 5/2/01 375.8 BI-214 6.70E-02 5.58E-02 51 SSW - CP&L PROPERTY 5/2/01 375.8 1-131 <LLD 3.46E-02 51 SSW - CP&L PROPERTY 5/2/01 375-8 CS-137 <LLD 3.80E-02 51 SSW - CP&L PROPERTY 6/4/01 401 K-40 2.54E+00 5.20E-01 51 SSW - CP&L PROPERTY 6/4/01 401 CS-137 9.72E-02 4.11 E-02 51 SSW - CP&L PROPERTY 6/4/01 401 CS-134 <LLD 3.66E-02 51 SSW - CP&L PROPERTY 6/4/01 401 BE-7 1.04E+00 2.31 E-01 51 SSW - CP&L PROPERTY 6/4/01 401 1-131 <LLD 3.59E-02 51 SSW - CP&L PROPERTY 6/18/01 423.3 K-40 3.10E+00 4.49E-01 51 SSW - CP&L PROPERTY 6/18/01 423.3 CS-1i37 <LLD 2.46E-02 51 SSW - CP&L PROPERTY 6/18/01 423.3 CS-134 <LLD 2.38E-02 51 SSW - CP&L PROPERTY 6/18/01 423.3 1-131 <LLD 2.40E-02 51 SSW - CP&L PROPERTY 6/18/01 423.3 BE-7 1.26E+00 2.14E-01 51 SSW CP&L PROPERTY 7/19/01 517.2 CS-137 <LLD 2.68E-02 51 SSW - CP&L PROPERTY 7/19/01 517.2 K-40 4.85E+00 4.93E-01 51 SSW - CP&L PROPERTY 7/19/01 517.2 1-131 <LLD 2.98E-02 51 SSW-CP&L PROPERTY 7/19/01 517.2 CS-134 <LLD 2.61E-02 51 SSW - CP&L PROPERTY 7/19/01 517.2 BE-7 1.13E+00 2.06E-01 51 SSW - CP&L PROPERTY 8/24/01 558.2 CS-134 <LLD 2.58E-02 P'age 2 of 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Tye: Broadleaf Vegetation Quantity: Grains Media: Sassafras Activity: pCi/gram Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 51 SSW - CP&L PROPERTY 8/24/01 558.2 CS-137 <LLD 2.35E-02 51 SSW - CP&L PROPERTY 8/24/01 558.2 1-131 <LLD 2.59E-02 51 SSW - CP&L PROPERTY 8/24/01 558.2 K-40 4.63E+00 4.77E-01 51 SSW - CP&L PROPERTY 8/24/01 558.2 BE-7 7.54E-01 2.11 E-01 51 SSW - CP&L PROPERTY 9/20/01 463.6 K-40 2.92E+00 4.41 E-01 51 SSW - CP&L PROPERTY 9/20/01 463.6 1-131 <LLD 3.36E-02 51 SSW - CP&L PROPERTY 9/20/01 463.6 CS-134 <LLD 2.81E-02 51 SSW - CP&L PROPERTY 9/20/01 463.6 CS-1i37 <LLD 4.19E-02 51 SSW - CP&L PROPERTY 9/20/01 463.6 BE-7 7.59E-01 2.18E-01 52 10 MI W - BETHUNE - CONTROL 5/2/01 333.6 K-40 6.24E+00 7.25E-01 52 10 MI W - BETHUNE - CONTROL 5/2/01 333.6 1-131 <LLD 4.75E-02 52 10 MI W - BETHUNE - CONTROL 5/2/01 333.6 CS-134 <LLD 3.82E-02 52 10 MI W - BETHUNE - CONTROL 5/2/01 333.6 CS-137 <LLD 3.89E-02 52 10MI W - BETHUNE - CONTROL 6/4/01 410 CS-134 <LLD 3.71E-02 52 10 MI W - BETHUNE - CONTROL 6/4/01 410 1-131 <LLD 3.34E-02 52 10 MI W - BETHUNE - CONTROL 6/4/01 410 CS-137 8.17E-02 3.59E-02 52 10 MI W - BETHUNE - CONTROL 6/4/01 410 K-40 2.09E+00 5.28E-01 52 10 MI W - BETHUNE - CONTROL 6/4/01 410 BE-7 6.82E-01 2.14E-01 52 10 MI W - BETHUNE - CONTROL 6/18/01 478.4 K-40 2.OOE+00 3.76E-01 52 10 MI W - BETHUNE - CONTROL 6/18/01 478.4 CS-137 9.23E-02 2.59E-02 52 10 MI W - BETHUNE - CONTROL 6/18/01 478.4 CS-134 <LLD 2.68E-02 52 10 MI W - BETHUNE - CONTROL 6/18/01 478.4 BE-7 9.85E-01 2.10E-01 52 10 MI W - BETHUNE - CONTROL 6/18/01 478.4 1-131 <LLD 2.74E-02 52 10 MI W - BETHUNE - CONTROL 7/19/01 457.9 CS-137 <LLD 3.55E-02 52 10 MI W - BETHUNE - CONTROL 7/19/01 457.9 BE-7 1.92E+00 2.92E-01 52 10 MI W - BETHUNE - CONTROL 7/19/01 457.9 K-40 2.23E+00 4.95E-01 Page 3 oj 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Tipe: Broadleaf Vegetation Quantity: Grams Media: Sassafras Activity: pCi/grain Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 52 10 MI W - BETHUNE - CONTROL 7/19/01 457.9 1-131 <LLD 3.37E-02 52 10MI W - BETHUNE - CONTROL 7/19/01 457.9 CS-134 <LLD 2.71E-02 52 10 MI W - BETHUNE - CONTROL 8/24/01 492.9 CS-1i34 <LLD 2.76E-02 52 10 MI W - BETHUNE - CONTROL 8/24/01 492.9 1-131 <LLD 3.49E-02 52 10 MI W - BETHUNE - CONTROL 8/24/01 492.9 CS-137 4.89E-02 2.56E-02 52 10 MI W - BETHUNE - CONTROL 8/24/01 492.9 BE-7 1.20E+00 2.91E-01 52 10 MI W - BETHUNE - CONTROL 8/24/01 492.9 K-40 2.26E+00 4-59E-01 52 10 MI W - BETHUNE - CONTROL 9/20/01 452.8 CS-134 <LLD 3.61E-02 52 10 MI W - BETHUNE - CONTROL 9/20/01 452.8 BE-7 8.95E-01 2.32E-01 52 10 MI W - BETHUNE - CONTROL 9/20/01 452.8 K-40 3.29E+00 4.59E-01 52 10 MI W - BETHUNE - CONTROL 9/20/01 452.8 CS-137 9.80E-02 3.28E-02 52 10 MI W - BETHUNE - CONTROL 9/20/01 452.8 1-131 <LLD 3.70E-02 Page 4 of 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Broadleaf Vegetation Quantity: G(ra1lMs Media: Wax Myrtle Activit,: pCi/gram Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 50 SSE - CP&L PROPERTY 5/2/01 417.2 K-40 2.68E+00 5.22E-01 50 SSE - CP&L PROPERTY 5/2/01 417.2 1-131 <LLD 3.29E-02 50 SSE - CP&L PROPERTY 5/2/01 417.2 CS-1i34 <LLD 3.06E-02 50 SSE - CP&L PROPERTY 5/2/01 417.2 CS-1i37 <LLD 3.40E-02 50 SSE - CP&L PROPERTY 5/2/01 417.2 BE-7 7.18E-01 2.26E-01 50 SSE - CP&L PROPERTY 6/4/01 384.6 BE-7 4.35E-01 1.83E-01 50 SSE - CP&L PROPERTY 6/4/01 384.6 K-40 3.08E+00 4-63E-01 50 SSE - CP&L PROPERTY 6/4/01 384.6 1-131 <LLD 2.95E-02 50 SSE - CP&L PROPERTY 6/4/01 384.6 CS-134 <LLD 2.31E-02 50 SSE - CP&L PROPERTY 6/4/01 384.6 CS-137 <LLD 2.65E-02 50 SSE - CP&L PROPERTY 6/18/01 444.8 1-131 <LLD 2.77E-02 50 SSE - CP&L PROPERTY 6/18/01 444.8 CS-1i34 <LLD 3-43E-02 50 SSE - CP&L PROPERTY 6/18/01 444.8 K-40 2.14E+00 4.62E-01 50 SSE - CP&L PROPERTY 6/18/01 444.8 BE-7 4.55E-01 2.56E-01 50 SSE - CP&L PROPERTY 6/18/01 444.8 CS-137 <LLD 3.16E-02 50 SSE - CP&L PROPERTY 7/19/01 434 K-40 3.72E+00 5.05E-01 50 SSE - CP&L PROPERTY 7/19/01 434 TL-208 7.54E-02 2.40E-02 50 SSE - CP&L PROPERTY 7/19/01 434 1-131 <LLD 2.64E-02 50 SSE - CP&L PROPERTY 7/19/01 434 CS-134 <LLD 3.37E-02 50 SSE - CP&L PROPERTY 7/19/01 434 CS-137 <LLD 2.91E-02 50 SSE - CP&L PROPERTY 7/19/01 434 BE-7 8.20E-01 2.73E-01 50 SSE - CP&L PROPERTY 8/24/01 374.3 K-40 2.13E+00 4.77E-01 50 SSE - CP&L PROPERTY 8/24/01 374.3 BE-7 7.55E-01 2.96E-01 50 SSE - CP&L PROPERTY 8/24/01 374.3 1-131 <LLD 3.62E-02 50 SSE - CP&L PROPERTY 8/24/01 374.3 CS-134 <LLD 4.26E-02 50 SSE - CP&L PROPERTY 8/24/01 374.3 CS-137 <LLD 3.55E-02 P'age 1 of 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media/Tpe: Broadleaf Vegetation Quantit,: Grams Media: Wax Myrtle Activity: pCi/gran Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD

--- I 50 SSE - CP&L PROPERTY 9/20/01 420.1 BE-7 7.46E-01 1.82E-01 50 SSE - CP&L PROPERTY 9/20/01 420.1 CS-137 <LLD 2.46E-02 50 SSE - CP&L PROPERTY 9/20/01 420.1 CS-134 <LLD 2.26E-02 50 SSE - CP&L PROPERTY 9/20/01 420.1 1-131 <LLD 2.92E-02 50 SSE - CP&L PROPERTY 9/20/01 420.1 K-40 1.92E+00 4.02E-01 51 SSW - CP&L PROPERTY 5/2/01 496.8 CS-137 <LLD 2.62E-02 51 SSW - CP&L PROPERTY 5/2/01 496.8 RA-226 8.28E-01 3.91 E-01 51 SSW - CP&L PROPERTY 5/2/01 496.8 K-40 3.80E+00 4.50E-01 51 SSW - CP&L PROPERTY 5/2/01 496.8 1-131 <LLD 2.98E-02 51 SSW - CP&L PROPERTY 5/2/01 496.8 BE-7 8.37E-01 1.90E-01 51 SSW - CP&L PROPERTY 5/2/01 496.8 CS-134 <LLD 2.67E-02 51 SSW - CP&L PROPERTY 6/4/01 447.3 CS-137 <LLD 3.22E-02 51 SSW - CP&L PROPERTY 6/4/01 447.3 K-40 2.50E+00 5.16E-01 51 SSW - CP&L PROPERTY 6/4/01 447.3 BE-7 1.02E+00 2.41 E-01 51 SSW - CP&L PROPERTY 6/4/01 447.3 1-131 <LLD 2.99E-02 51 SSW - CP&L PROPERTY 6/4/01 447.3 AC-228 1.98E-01 1.06E-01 51 SSW - CP&L PROPERTY 6/4/01 447.3 PB-212 1.25E-01 4.26E-02 51 SSW - CP&L PROPERTY 6/4/01 447.3 TL-208 7.05E-02 2.86E-02 51 SSW - CP&L PROPERTY 6/4/01 447.3 CS-134 <LLD 3.52E-02 51 SSW - CP&L PROPERTY 6/18/01 476.9 CS-134 <LLD 3.OOE-02 51 SSW - CP&L PROPERTY 6/18/01 476.9 1-131 <LLD 2.92E-02 51 SSW - CP&L PROPERTY 6/18/01 476.9 AC-228 1.03E-01 9.20E-02 51 SSW - CP&L PROPERTY 6/18/01 476.9 K-40 3.57E+00 4.99E-01 51 SSW - CP&L PROPERTY 6/18/01 476.9 BE-7 4.82E-01 2.18E-01 51 SSW - CP&L PROPERTY 6/18/01 476.9 CS-137 <LLD 2.94E-02 51 SSW - CP&L PROPERTY 7/19/01 488.4 CS-1i34 <LLD 3.26E-02 Page 2 of 4

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: BroadleafVegetation Quantit': Grams Media: Wax Myrtle Activity: pCi/gram Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 51 SSW - CP&L PROPERTY 7/19/01 488.4 BE-7 1.10E+00 2.39E-01 51 SSW - CP&L PROPERTY 7/19/01 488.4 K-40 2.47E+00 4.88E-01 51 SSW - CP&L PROPERTY 7/19/01 488.4 1-131 <LLD 3.22E-02 51 SSW - CP&L PROPERTY 7/19/01 488.4 AC-228 2.68E-01 9.07E-02 51 SSW - CP&L PROPERTY 8/24/01 573.7 BI-214 6.13E-02 4.34E-02 51 SSW - CP&L PROPERTY 8/24/01 573.7 CS-1i37 <LLD 2.70E-02 51 SSW - CP&L PROPERTY 8/24/01 573.7 CS-1i34 <LLD 2.89E-02 51 SSW - CP&L PROPERTY 8/24/01 573.7 PB-214 6.69E-02 4.72E-02 51 SSW - CP&L PROPERTY 8/24/01 573.7 1-131 <LLD 2.85E-02 51 SSW - CP&L PROPERTY 8/24/01 573.7 K-40 2.90E+00 4.12E-01 51 SSW - CP&L PROPERTY 8/24/01 573.7 BE-7 6.92E-01 1.65E-01 51 SSW - CP&L PROPERTY 8/24/01 573.7 AC-228 2.OOE-01 7.67E-02 51 SSW - CP&L PROPERTY 9/20/01 461.3 K-40 2.63E+00 3.74E-01 51 SSW - CP&L PROPERTY 9/20/01 461.3 CS-137 <LLD 2-93E-02 51 SSW - CP&L PROPERTY 9/20/01 461.3 CS-134 <LLD 3.43E-02 51 SSW - CP&L PROPERTY 9/20/01 461.3 1-131 <LLD 3.48E-02 51 SSW - CP&L PROPERTY 9/20/01 461.3 AC-228 2.05E-01 9.69E-02 51 SSW - CP&L PROPERTY 9/20/01 461.3 BE-7 6.08E-01 1.98E-01 52 10 MI W - BETHUNE - CONTROL 5/2/01 283.3 BE-7 3.08E+00 4.96E-01 52 10 MI W - BETHUNE -CONTROL 5/2/01 283.3 CS-1i34 <LLD 4.60E-02 52 10 MI W - BETHUNE - CONTROL 5/2/01 283.3 K-40 1.99E+00 6.70E-01 52 10 MI W - BETHUNE - CONTROL 5/2/01 283.3 CS-137 9.98E-02 4.53E-02 52 10 MI W - BETHUNE - CONTROL 5/2/01 283.3 1-131 <LLD 5.50E-02 52 10 MI W - BETHUNE - CONTROL 6/4/01 360.5 BE-7 9.19E-01 2.29E-01 52 10 MI W - BETHUNE - CONTROL 6/4/01 360.5 K-40 3.56E+00 5.75E-01 52 10 MI W - BETHUNE - CONTROL 6/4/01 360.5 CS-137 2.04E-01 3.01 E-02 Page 3 of 4

RNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report edia Ty)Ie: Broadlea' Vegetation Quantity: Grams Media: Wax Myrtle Activit.: pCi/gram Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 52 10 M1W - BETHUNE -CONTROL 6/4/01 360.5 CS-1i34 <LLD 2.80E-02 52 10 MI W - BETHUNE - CONTROL 6/4/01 360.5 1-131 <LLD 2.58E-02 52 10MI W - BETHUNE - CONTROL 6/18/01 424.7 K-40 2.73E+00 4.41E-01 52 10 MI W - BETHUNE - CONTROL 6/18/01 424.7 CS-137 1.50E-01 3.62E-02 6/18/01 424.7 CS-134 <LLD 2.69E-02 52 10 MI W - BETHUNE - CONTROL 52 10 MI W - BETHUNE - CONTROL 6/18/01 424.7 BE-7 1.OOE+00 2.43E-01 52 10 MI W - BETHUNE - CONTROL 6/18/01 424.7 1-131 <LLD 2.09E-02 52 10 MI W - BETHUNE - CONTROL 7/19/01 432.9 CS-134 <LLD 3.38E-02 52 10MI W - BETHUNE - CONTROL 7/19/01 432.9 BE-7 1.82E+00 2.81E-01 7/19/01 432.9 K-40 3.47E+00 4.44E-01 52 10 MI W - BETHUNE - CONTROL 52 10 MI W - BETHUNE - CONTROL 7/19/01 432.9 CS-137 1.85E-01 3.35E-02 7/19/01 432.9 1-131 <LLD 4.18E-02 52 10 M1W - BETHUNE - CONTROL 10 MI W - BETHUNE - CONTROL 8/24/01 437.6 CS-134 <LLD 2.98E-02 52 52 10 MI W - BETHUNE - CONTROL 8/24/01 437.6 1-131 <LLD 4.18E-02 10 MI W - BETHUNE - CONTROL 8/24/01 437.6 CS-137 4.99E-01 5.31E.02 52 52 10MI W - BETHUNE - CONTROL 8/24/01 437.6 BE-7 1.13E+00 2.61E-01 52 10 MI W - BETHUNE - CONTROL 8/24/01 437.6 K-40 1.24E+00 4.51E-01 10 MI W - BETHUNE - CONTROL 9/20/01 496.8 CS-134 <LLD 2.65E-02 52 52 10 MI W - BETHUNE - CONTROL 9/20/01 496.8 BE-7 4.57E-01 2.08E-01 52 10 MI W - BETHUNE - CONTROL 9/20/01 496.8 K-40 3.04E+00 4.48E-01 52 10 MI W - BETHUNE - CONTROL 9/20/01 496.8 CS-137 7.58E-02 2.47E-02 52 10 MI W - BETHUNE - CONTROL 9/20/01 496.8 1-131 <LLD 3.13E-02 Page 4 of ,l

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Food Crop Quantity: Grams Media: Collards Activity: pCi/gram Samnlen Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD ouLLDI 2.62E-02 SITE VARIES FROM PLANT 10/31/01 508 CS-137 <LLD 2.62E-02 58 10/31/01 508 CS-134 58 SITE VARIES FROM PLANT <LLD 2.66E-02 10/31/01 508 1-131 3.26E-02 58 SITE VARIES FROM PLANT <LLD 10/31/01 508 K-40 3.45E+00 58 SITE VARIES FROM PLANT 5.1 OE-01 Page I of lI

RNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report Media Ty'pe: Food Crop Quantity: Grams Media: Cucumbers Activity, pCi/gram Sample Date Quantity Isotope Activity 2 Sigma Error LLD Sample Point 7/10/01 561.5 CS-1i37 <LLD 1.52E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 561.5 CS-1i34 <LLD 1.72E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 561.5 1-131 <LLD 1.43E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 561.5 K-40 7.81E+00 2.58E+00 49 7/16/01 716.5 CS-137 <LLD 1.41 E-02 58 SITE VARIES FROM PLANT 7/16/01 716.5 CS-134 <LLD 1.41 E-02 58 SITE VARIES FROM PLANT 7/16/01 716.5 1-131 <LLD 1.11E-02 58 SITE VARIES FROM PLANT SITE VARIES FROM PLANT 7/16/01 716.5 K-40 1.68E+00 2.96E-01 58 Page I of I

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media TYpe: Food Crop Quantity: Grams Media: Eggplant Activit,: pCi/gram Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD I

SITE VARIES FROM PLANT 10/31/01 378.3 CS-137 <LLD 3.14E-02 58 10/31/01 378.3 CS-134 <LLD 3.07E-02 58 SITE VARIES FROM PLANT 10/31/01 378.3 1-131 <LLD 3.04E-02 58 SITE VARIES FROM PLANT 10/31/01 378.3 K-40 1.75E+00 5.19E-01 58 SITE VARIES FROM PLANT Page 1 offI

RNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report Media Type: Food Crop Quantity: Grams Media: Mustard Greens Activity: pCi/gram Sample Point I

Sample Date Quantity Isotope Activity 2 Sigma Error LLD GREATER THAN 5 MI FROM SITE - CONTROL 10/31/01 440 CS-137 <LLD 3.01 E-02 49 49 GREATER THAN 5 MI FROM SITE - CONTROL 10/31/01 440 CS-134 <LLD 3.14E-02 10/31/01 440 1-131 <LLD 3.63E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 49 GREATER THAN 5 MI FROM SITE - CONTROL 10/31/01 440 K-40 5.40E+00 6.37E-01 Page 1 of 1

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Food Crop Quantity: Grams Media: Peaches Activity: pCi/gram Sample Point Sample Date QuantityI Isotope Activity 2- Sigma Error LLD

- -Z5 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 755.6 CS-1i37 <LLD 1.72E-02 49 7/10/01 755.6 CS-134 <LLD 1.77E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 755.6 1-131 <LLD 1.47E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 755.6 K-40 1.83E+00 3.23E-01 49 GREATER THAN 5 MI FROM SITE - CONTROL Page 1 of f

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Food Crop Quantity. Grams Media: Squash Activity: pCi/gram Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 547 CS-1i37 <LLD 2.50E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 547 CS-134 <LLD 2.56E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 547 1-131 <LLD 1.67E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 547 K-40 1.59E+00 3.66E-01 58 SITE VARIES FROM PLANT 7/16/01 231.7 CS-137 <LLD 1.83E-02 58 SITE VARIES FROM PLANT 7/16/01 231.7 CS-134 <LLD 1.88E-02 58 SITE VARIES FROM PLANT 7/16/01 231.7 1-131 <LLD 2.06E-02 58 SITE VARIES FROM PLANT 7/16/01 231.7 K-40 1.84E+00 3.28E-01 Page 1 of f

RNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report Media Tye: Food Crop Quanti,: (Grams Media: Tomatoes Activity: pCi/gram Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 837.9 CS-137 <LLD 1.72E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 837.9 CS-134 <LLD 1.63E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 837.9 1-131 <LLD 1.25E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 7/10/01 837.9 K-40 2.07E+00 2.94E-01 58 SITE VARIES FROM PLANT 7/16/01 768.8 CS-137 <LLD 1.97E-02 58 SITE VARIES FROM PLANT 7/16/01 768.8 CS-134 <LLD 1.86E-02 58 SITE VARIES FROM PLANT 7/16/01 768.8 1-131 <LLD 1.39E-02 58 SITE VARIES FROM PLANT 7/16/01 768.8 K-40 2.23E+00 3.47E-01 Page 1 of I

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Ty'pe: Food Crop Quantity: Grams Media: Turnips and Greens Activity: pCi/grant Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 49 GREATER THAN 5 MI FROM SITE - CONTROL 10/31/01 428.5 CS-137 <LLD 3.08E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 10/31/01 428.5 CS-134 <LLD 3.08E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 10/31/01 428.5 1-131 <LLD 2.63E-02 49 GREATER THAN 5 MI FROM SITE - CONTROL 10/31/01 428.5 K-40 6.75E+00 6.65E-01 58 SITE VARIES FROM PLANT 10/31/01 399.4 CS-1i37 <LLD 2.77E-02 58 SITE VARIES FROM PLANT 10/31/01 399.4 CS-134 <LLD 2.83E-02 58 SITE VARIES FROM PLANT 10/31/01 399.4 1-131 <LLD 2.14E-02 58 SITE VARIES FROM PLANT 10/31/01 399.4 PB-212 6.38E-02 2.82E-02 58 SITE VARIES FROM PLANT 10/31/01 399.4 K-40 3.22E+00 4.76E-01 Page 1 of ]

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Free Swimmer Quantity: Grams (wet)

Activityv: pCi/granm (wet)

Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 45 SITE VARIES WITHIN LAKE ROBINSON 5/30/01 462.9 K-40 4.88E+00 1.25E+00 45 SITE VARIES WITHIN LAKE ROBINSON 11/13/01 551.7 K-40 4.86E+00 1.14E+00 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 539.5 CS-137 8.26E-02 3.44E-02 46 4.9 MI ESE - PRESTWOOD LAKE 5/31/01 539.5 K-40 3.82E+00 1.12E+00 46 4.9 MI ESE - PRESTWOOD LAKE 11/13/01 500.1 CS-137 1.10E-01 5.68E-02 46 4.9 MI ESE - PRESTWOOD LAKE 11/13/01 500.1 K-40 3.59E+00 1.19E+00 47 13 MI NNW - LAKE BEE - CONTROL 5/29/01 334.6 CS-137 2.02E-01 9.82E-02 47 13 MI NNW - LAKE BEE - CONTROL 5/29/01 334.6 K-40 5.87E+00 1.57E+00 47 13 MI NNW - LAKE BEE - CONTROL 11/12/01 394.7 K-40 4.66E+00 1.39E+00 Page I of I

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Groundiwater Quantit-: Liters Activitn: pCi/Liter Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 5.41 E+01 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 2/15/01 K-40 157 5.41 E+01 40 4/30/01 K-40 287 8.82E+01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 7/3/01 RA-226 49.2 3.81 E+01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 9/24/01 NO-ACT 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 12/18/01 NO-ACT 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 2/15/01 PB-214 17.8 1.05E+01 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 2/15/01 BI-214 37 8.99E+00 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 4/30/01 NO-ACT 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 7/3/01 K-40 361 7.22E+01 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 9/24/01 NO-ACT 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE 12/18/01 NO-ACT 42 UNIT 1 DEEP WELL NEAR SITE ENTRANCE Page 1 of I

RNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report Media Type: Shoreline Sediment Quantity: Grams (dry)

Activity: pCi/gram (drV

,nmnile Datep Ouantitv Isotope Activity 2 Sigma Error LLD Sample Point 1622.6 PB-214 1.5--1-.5E0 44 1.9 MI NNE - SHADY REST CLUB 2/15/01 1622.6 PB-214 1.15E-01 5.45E-02 2/15/01 RA-226 4.68E-01 4.14E-01 44 1.9 MI NNE - SHADY REST CLUB 1622.6 2/15/01 TL-208 4.01 E-02 1.77E-02 44 1.9 MI NNE - SHADY REST CLUB 1622.6 7/24/01 PB-212 9.76E-02 5.59E-02 44 1.9 MI NNE - SHADY REST CLUB 1622.2 7/24/01 TL-208 3.76E-02 2.31 E-02 44 1.9 MI NNE - SHADY REST CLUB 1622.2 7/24/01 PB-214 9.35E-02 5.29E-02 44 1.9 MI NNE - SHADY REST CLUB 1622.2 2/15/01 PB-214 1.27E+00 1.61E-01 57 0.9 MI NNW - ASH POND 1187.2 2/15/01 BI-214 1.OOE+00 1.59E-01 57 0.9 MI NNW - ASH POND 1187.2 PB-212 1.49E+00 1.14E-01 2/15/01 57 0.9 MI NNW - ASH POND 1187.2 2/15/01 TL-208 5.75E-01 7.52E-02 57 0.9 MI NNW - ASH POND 1187.2 2/15/01 K-40 2.90E+00 6.78E-01 57 0.9 MI NNW - ASH POND 1187.2 2/15/01 RA-226 2.96E+00 1.16E+00 57 0.9 MI NNW - ASH POND 1187.2 7/24/01 TL-208 1.20E+00 1.61 E-01 57 0.9 MI NNW - ASH POND 1101.9 7/24/01 K-40 2.03E+01 1.63E+00 57 0.9 MI NNW - ASH POND 1101.9 7/24/01 BI-212 2.46E+00 7.03E-01 57 0.9 MI NNW - ASH POND 1101.9 7/24/01 AC-228 4.13E+00 5.18E-01 57 0.9 MI NNW - ASH POND 1101.9 7/24/01 PB-212 4.08E+00 2.04E-01 57 0.9 MI NNW - ASH POND 1101.9 7/24/01 BI-214 4.81 E+00 3.13E-01 57 0.9 MI NNW - ASH POND 1101.9 7/24/01 PB-214 5.48E+00 3.19E-01 57 0.9 MI NNW - ASH POND 1101.9 7/24/01 RA-226 1.31 E+01 2.40E+00 1101.9 57 0.9 MI NNW - ASH POND Page 1 of I

RNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report Media Type: Stuface Water Quantity: Liters Activity: pCi/Liter Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 1/31/01 1.00 NO-ACT 2/28/01 1.00 NO-ACT 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 3/31/01 1.00 NO-ACT 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 4/30/01 1.00 NO-ACT 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 5/31/01 1.00 NO-ACT 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 6/30/01 1.00 NO-ACT 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 7/31/01 1.00 K-40 1.92E+02 6.27E+01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 1.00 K-40 4.48E+02 9.01 E+01 8/31/01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 1.00 K-40 2.42E+02 7.06E+01 9/30/01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 1.00 K-40 9.73E+01 7.31 E+01 10/31/01 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 11/30/01 1.00 NO-ACT 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 12/31/01 1.00 PB-212 6.13E+00 3.29E+00 40 0.6 MI ESE-SC23 AT BLACK CR AND ART WELL 1/31/01 1.00 NO-ACT 41 7.2 MI NNW - BLACK CREEK - CONTROL 2/28/01 1.00 NO-ACT 41 7.2 MI NNW - BLACK CREEK - CONTROL 3/31/01 1.00 NO-ACT 41 7.2 MI NNW - BLACK CREEK - CONTROL 4/30/01 1.00 NO-ACT 41 7.2 MI NNW - BLACK CREEK - CONTROL 5/31/01 1.00 NO-ACT 41 7.2 MI NNW - BLACK CREEK - CONTROL 6/30/01 1.00 RA-226 6.53E+01 5.19E+01 41 7.2 MI NNW - BLACK CREEK - CONTROL 7/31/01 1.00 NO-ACT 41 7.2 MI NNW - BLACK CREEK - CONTROL 8/31/01 1.00 NO-ACT 41 7.2 MI NNW - BLACK CREEK - CONTROL 9/30/01 1.00 K-40 9.30E+01 5.70E+01 41 7.2 MI NNW - BLACK CREEK - CONTROL 10/31/01 1.00 NO-ACT 41 7.2 MI NNW - BLACK CREEK - CONTROL 11/30/01 1.00 NO-ACT 41 7.2 MI NNW - BLACK CREEK - CONTROL 12/31/01 1.00 K-40 1.06E+02 4.76E+01 41 7.2 MI NNW - BLACK CREEK - CONTROL 1/31/01 1.00 NO-ACT 57 0.9 MI NNW - ASH POND 2/28/01 1.00 NO-ACT 57 0.9 MI NNW - ASH POND Page I of 2

RNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Su face Water Quantity: Liters Activity: pCi/Liter Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error LLD 57 0.9 MI NNW - ASH POND 3/31/01 1.00 NO-ACT 57 0.9 MI NNW - ASH POND 4/30/01 1.00 NO-ACT 57 0.9 MI NNW - ASH POND 5/31/01 1.00 NO-ACT 57 0.9 MI NNW - ASH POND 7/31/01 1.00 NO-ACT 57 0.9 MI NNW - ASH POND 8/31/01 1.00 K-40 3.77E+02 9.11E+01 57 0.9 MI NNW - ASH POND 9/30/01 1.00 K-40 3.67E+02 8.12E+01 57 0.9 MI NNW - ASH POND 10/31/01 1.00 NO-ACT 57 0.9 MI NNW - ASH POND 12/31/01 1.00 PB-212 6.80E+00 3.43E+00 Page 2 of 2