HNP-02-059, Annual Radiological Environmental Operating Report for 2001

Annual Radiological Environmental Operating Report for 2001

ML021270577
Person / Time
Site:	Harris
Issue date:	04/30/2002
From:	Holt J Carolina Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-02-059
Download: ML021270577 (146)

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CP&L A Progress Energy Compavy APR 3 0 2002 SERIAL: HNP-02-059 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

Dear Sir or Madam:

In accordance with Technical Specification 6.9.1.3 for the Harris Nuclear Plant, Carolina Power

& Light Company is providing the enclosed Annual Radiological Environmental Operating Report for 2001.

If you have questions or need additional information regarding this report, please contact Mr. J. R. Caves at (919) 362-3137.

Sincerely, James Holt Manager, Support Services Harris Nuclear Plant MGW Enclosure c: Mr. J. B. Brady (NRC Senior Resident Inspector, HNP)

Mr. J. M. Goshen (NRR Project Manager, HNP)

Mr. L. A. Reyes (NRC Regional Administrator, Region II)

Harris Nuclear Plant 5L!3 Shearon Harris Road New Hill, NC27562

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2001 QkT)

HARRIS NUCLEAR PLANT CAROLINA POWER & LIGHT

HARRIS ENERGY & ENVIRONMENTAL CENTER CAROLINA POWER & LIGHT A PROGRESS ENERGY COMPANY NEW HILL, NORTH CAROLINA RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT JANUARY 1 THROUGH DECEMBER 31, 2001

TABLE OF CONTENTS Title Page Table of Contents ......................................................................................................................... i List of Figures .............................................................................................................................. ii List of Tables .............................................................................................................................. iii Executive Sum m ary .................................................................................................................... 1 Introduction to Nuclear O perations ...................................................................................... 3 Benefits of N uclear Power ................................................................................................... 3 Radiation and Radioactivity ................................................................................................. 4 Radiation Interaction with M atter ........................................................................................ 6 Radiation Qualities and U nits of M easure ............................................................................ 7 Sources of Radiation ......................................................................................................... 8 Health Effects of Radiation ................................................................................................. 10 General Health Risk ................................................................................................................ 12 Nuclear Power Plant Operations .......................................................................................... 12 Plant System s .......................................................................................................................... 15 Reactor Safety ......................................................................................................................... 19 Radiological Environmental Monitoring Program ........................................................... 20 Purpose and Requirements for the Radiological Monitoring Program ............................... 20 General Site D escription ...................................................................................................... 21 Radiological M onitoring Program Quality A ssurance ........................................................ 22 Radiological M onitoring Program General D escription ...................................................... 23 Sum m ary of Radiological M onitoring Program .................................................................. 28 Interpretations and Conclusions ...................................................................... .................... 34 M issed Sam ples and A nalyses ............................................................................................ 40 Analytical Procedures ......................................................................................................... 42 Land-Use Census ....................................................................................................................... 48 Purpose of the Land-U se Census ......................................................................................... 48 M ethodology ........................................................................................................................... 48 2001 Land-U se Census Results ..................................... ....... .......................................... 49 References .................................................................................................................................. 51 i

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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 Harris 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 5) 53 19 Plot of Air Particulate Gross Beta Activity (Locations 2 and 5) 54 20 Plot of Air Particulate Gross Beta Activity (Locations 4 and 5) 55 21 Plot of Air Particulate Gross Beta Activity (Locations 5 and 26) 56 22 Plot of Air Particulate Gross Beta Activity (Locations 5 and 47) 57 23 Plot of Drinking Water Gross Beta Activity (Locations 38 and 40) 58 24 Plot of Surface Water Gross Beta Activity (Locations 26 and 38) 59 25 Plot of Surface Water Tritium Activity (Locations 26 and 40) 60 26 Plot of TLD Averages for Inner and Outer Rings 61 ii

LIST OF TABLES Table Page 1 Quality Factors for Various Radiations 8 2 Reduction In Average Life Expectancy 12 3 Media Used to Assess Exposure Pathways to Man 23 4 Radiological Monitoring Sampling Locations 26 5 Radiological Environmental Monitoring Program Data Summary 29 6 Typical Lower Limits of Detection (a priori) Gamma Spectrometry 46 7 Land-Use Census Comparison (2000-2001) 50 iii

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• EXECUTIVE

SUMMARY

The Harris Nuclear Plant (HNP) is operated by Carolina Power & Light (CP&L), A Progress Energy Company, under a license granted by the Nuclear Regulatory Commission. Provisions of the Nuclear Regulatory Commission's Regulatory Guide 4.8, Harris Nuclear Plant Tec-nical Specifications, and the Harris Nuclear Plant Offsite Dose Calculation Manual (ODCM) establish the requirements of the Radiological Environmental Monitoring Program (REMP). 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 1982. Radiation and radioactivity in various environmental media have been monitored for more than 20 years, including 5 years prior to commencing operation. Monitoring is also provided for control locations, which would not be impacted by operations of the Harris Nuclear Plant. Using these control locations and data collected prior to operation allows comparison of data collected at locations near the Harris Nuclear Plant which could potentially be impacted by its operations.

Radiation levels show no significant change from pre-operational radiation levels.

Monitoring results for environmental media are summarized as follows:

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

> Milk and broadleaf vegetation monitoring results are similar to all the past years where no 1-131 concentrations were detected. Broadleaf vegetation is in lieu of indicator milk samples, due to no milk-producing animal within five miles of the plant.

> Terrestrial vegetation includes various crops collected during a growing season, which reveals no detectable radioactivity.

> Aquatic organism monitoring includes fish and aquatic vegetation. The fish results indicate no detectable radioactivity; however, the aquatic vegetation shows the presence of detectable radioactivity.

> Surface (and drinking) water results indicate no detectable gamma radionuclides including 1-131, which is performed by an I- 131 separation analysis.

> Surface water (non-drinking water) results from Harris Lake show the presence of tritium, which.is attributed to plant operation, but is well below the EPA reportable non-drinking water limit (30,000 pCi/Liter) and drinking water limit (20,000 pCi/Liter). Refer to the Interpretations and Conclusions section/ Surface Water.

radiation dose showedSExternal no measurable change from pre-operational data.

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The continued operation of the Harris Nuclear Plant has not contributed measurable radiation or the presence of gamma radioactivity, with the exception of Harris Lake bottom sediment and aquatic vegetation, in the environmental monitoring program. The Harris Lake Surface water samples (non-public drinking water) revealed tritium concentrations that are well within the applicable regulatory limits.

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INTRODUCTION TO NUCLEAR OPERATIONS Carolina Power & Light (CP&L), A Progress Energy RCompany, 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 people.

Figure 1: CP&L Service Area The energy sources 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 H Nuclear supplied 44.96% of CP&L's total electrical Coal generation. This nuclear component was U Oil &Naural Gas generated from four units including the Harris

• Hydro Power Nuclear Plant. The remaining energy sources were primarily from coal-fired generation, and a very small contribution from oil, natural gas and Figure 2: 2001 Energy Sources hydropower.

BENEFITS OF NUCLEAR POWER Nuclear energy is a viable, clean, safe, and readily available source of energy. The operation of the Harris Nuclear Plant 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 nations electrical needs. Nuclear energy currently supplies more than twenty percent of the nation's electrical energy. 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.

SEmissions 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 green house gas.

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

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

RADIATION AND RADIOACTIVITY The Atom All matter consists of atoms. An atom is the smallest unit into which an element can be divided and still retain its identity as that element. An atom is made up of a number of different particles. These particles are protons, neutrons, and electrons. Each proton "ispositively charged (+). Each neutron has no charge. And the electron is negatively charged (-).

The heavier particles including protons and neutrons are found in the center of the atom in a very small Figure 3: The Atom cluster referred to as the nucleus. (The term nuclear refers to this 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 I 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 it's 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 with a free electron. There are two types of ionizing radiation -- particulate radiation and electromagnetic radiation. Particulate radiations are energetic particles, which will travel in a straight line if unhindered. There are three types of particulate radiation of interest in nuclear energy. These are the 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 Radiations are high-energy waves (or photons), which have no apparent mass (not a particle).

There are two types of electromagnetic radiation of interest. These 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 radiations, 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. These are the thorium, neptunium, and the uranium series. These radioactive decay series, as well as naturally occurring K (potassium) 40, C (carbon)-14, and H (hydrogen)-3, are significant contributors to background radiation levels. These are addressed in greater detail later.

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The rate at which atoms undergo radioactive decay I 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 12 1- radioactive decay. The longer the half-life the less likely an atom will experience radioactive decay in a 1/4 fixed time interval. Half-lives vary fr~om extremely 1/8 small fractions of a second (billionths) to millions of 1/16 years. Figure 4 illustrates an isotope with a 140 0 140 280 420 day half-life. Note that the activity decreases by half Time. days in 140 days, and then by half again the next 140 Figure 4: Radioactive Decay days and so on.

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 absorb ---...-. ,

the energy of a single particle or photon of radiation. One of the most common ways energy is dissipated is ionization. As ELECTRO we discussed earlier this results in the creation of a positively charged atom and a free electron. The positively charged atom and the free electron are referred to as a charged pair.

The creation of the charged pair is one of the primary contributions to damage of biological systems. Figure 5:I onization Radiation Ranges Each type of radiation we have discussed interacts with the matter they travel through differently because of the different characteristics of each radiation.

Alpha particles are composed of two protons and two neutrons. This is the heaviest particulate radiation with a positive charge of two (two protons). The alpha particle is the slowest of the radiations, with a speed of no more than 20,000 miles per second. The alpha leaves it's Mp......

energy in a short distance characterized by a great many G~

ionizations. As a result of these characteristics the alpha travels only a few centimeters (or inches) in air and isPAE UMM I-D readily stopped by a sheet of paper. AE AuiIU¶ EA Beta particles are basically a very high-energy electron. Figure 6: Radiation Ranges & Shielding 6

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• a 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 are readily stopped by a small piece of metal or other dense material. The beta particle leaves its 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 1x1O-12 nano .000000001 1x10-9 micro .000001 1x 10 6 milli .001 1XI1- 3 centi .01 1xi1- 2 kilo 1,000. lx 10 mega 1,000,000. 1xi 06 Activity is the number of radioactive transformations (decays, disintegrations) that occur in a fixed time interval. The unit used to express activity is the curie. The curie is defined as 37,000,000,000 disintegrations per second; also expressed as 3.7x1010 s-1. A curie is a unit of activity, not an amount of material or the number of atoms. The amount of material or number of atoms necessary to produce a curie of activity vary over a very wide range. Atoms with very long half-lives would require more atoms to produce a curie of activity versus atoms with short half lives.

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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 radiations. The absorbed dose can be measured with various radiation-detection instruments, which allows 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. Dose equivalent is obtained by multiplying the absorbed dose (expressed 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 radiations we have discussed is illustrated below.

Table 1 Quality Factors for Various Radiations Radiation Quality Factor Gamma-rays I X-rays I Beta Particles I 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 live with them into 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.

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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). These high-energy cosmic radiations have 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 radiations are carbon-14 and tritium (H-3). The atmosphere around the earth serves as an effective shield causing much of the energy of cosmic radiations 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, up to 20 to 50 mrem (.020 to .050 rem) annually. The actual dose is influenced by the elevation at 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 radiations. The average passenger could expect to receive a dose of 2.8 inrern (.0028 rem) per e flight.

Another important contributor to external absorbed dose is terrestrial radiation. Thisi Source of Radiation Dose 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 about 15 to 140 inrent (.015 to. 140 rem) annually. However

• there are a very few areas that these terrestrial absorbed doses exceed 800 mrem each year.

One of the most important sources of dose is that contributed by internal radiations. These radionuclides are part of our body, the air we H Radon U Terrestrial have breathed, or the food we have consumed. U Cosmic U Internal One if the most significant contributors is U Man-made radon. Radon is a radioactive gas that is part of the uranium decay series. Radon's Figure 7: Radiation Sources (BIER V) 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 (1I1the 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 radiations are important to completing our understanding of sources of An important aspect in S 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, display Nuclear Medicine screens, smoke detectors, and many other devices are the next most important class of man-made radiations. Fallout from prior weapons testing is now a small contributor to total radiation dose.

El X-Rays U Nuclear Medicine Occupational exposure is also a consumer products Fallout factor from the medical, Occupational 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 radiations 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 radiation's biological effects 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 from animal experiments, accidents handling radioactive materials, and wartime nuclear weapons use and its survivors. It has been a classical problem of how to relate doses at these levels too 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.

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-. .61 W Radiation's biological effects 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.

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 have been observed in the range of 25 to 50 rem (or 50,000 mrem). Other acute effects can be expected at even higher doses. Our knowledge of this level of dose are the survivors of nuclear weapons, accidents, and planned medical treatments. These dose levels are more than 500 times normal environmental background radiation. For this reason, these effects are not important to a discussion of environmental radiation.

Chronic effects are generally used to refer to effects that are observed over a long period of time and have been referred to as delayed effects. The effects are also generally associated with radiation dose received over a long period. This is known as chronic exposure. However, it is not necessary for the exposure to occur over a long period. The most important chronic effect is cancer. There are numerous forms of cancer. The rate of cancer in individuals at low doses (at occupational or environmental levels) has not been observed directly. "Cancers induced by radiation are indistinguishable from those occurring naturally; hence, their existence can be inferred only on the basis of statistical excess above the natural incidence." The current practice is to use observations at a much higher dose to establish the rate of cancers a t that dose and then assume that the rate of cancers must be proportional to the lower dose. This has created a scientific disagreement, because some scientists believe this method over estimates the cancer risk from low doses of radiation. However, this appears to be a conservative assumption. Some risk exists but it is believed to be a small risk of cancer at occupational levels. The Committee of the Biological Effect of Ionizing Radiation further states, "It is by no means clear whether dose rates of gamma or X-rays of about 100 mrad per year are in any way detrimental to exposed people..." Environmental radiation levels are in the range of 100 mrad per year or less as we have discussed.

Genetic radiation effects occur when radiation changes the genetic material in cells. As we have discussed, the process of ionization removes electrons from the atom. These electrons are sometimes necessary in the creation of chemical bonds. If the bonds are part of the genetic material of the cell, it could result in changed genetic material (mutations). Radiation is just one of several agents that contribute to genetic change. Chemicals, including those thate occur naturally, are a significant contributor to genetic mutations. Background radiation levels only provide a minor contribution to total mutations. To double the general mutation (from all sources) rate would require a dose of 50 to 250 rem (or 50,000 to 250,000 mrem). This is approximately 500 to 2,500 times the normal environmental background.

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GENERAL HEALTH RISK Every human activity has risk associated with it. The air we breathe, the food we eat, and where we live or work all have different risks. Many times our perception of these risks is quite different than the real risk of an activity. There was widespread fear and misunderstanding regarding the fire and safety hazard from electricity early this century. Now electricity is accepted as part of our daily existence. Radiation is unique in that it cannot be seen, felt, smelled, or detected by any of the human senses. Instruments or laboratory analyses specially designed to detect radiation detect it. 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 radiations and 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 you will find a table of 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 a 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 as U-235, is known to undergo spontaneous 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. 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. 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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FiMion Fragment Figure 9: Nuclear Fission 13

Uranium Fuel Uranium is mined from the earth as an ore, the same as many minerals. 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 gaseous uranium hexafloride (in chemical notation UF 6 ). While in this form it is possible to separate the lighter U-235 from the heavier U-238. This process of separation is called-gaseous diffusion. The reason for separation is to allow more of the U-235 to be included in the fuels used in commercial reactors. We have SNUCLEAR FUEL CYCLE 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 MINE MILL CONVERTER gas is chemically converted to uranium dioxide (in chemical notation U0 2 ). At this point the uranium dioxide is a gray powder.

The next process takes this powder under high pressure and temperature REACTOR FUEL FABRICATOR ENRICHER to create a ceramic pellet of uranium dioxide. This process is part of the fuel fabrication. The fuel fabricator Figure 10: The Nuclear Fuel Cycle PELLET also ensures that each fuel pellet 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 6% 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. 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 and these are the reactor, the turbine generator, the condensate and feed water systems, and various support systems including various emergency systems. The reactor and 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 within the windings of metallic conductors around this magnetic field. It is then transmitted to the electrical transmission system and from there to the customers in the service area and sold to neighboring utilities.

After the steam has spent most all 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.

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

Reactor Types and the Reactor Vessel There are approximately 180 commercial nuclear reactors being used to generate electricity in the United States today. Of these, there are two basic types of reactor in i ,

nstirementanism operation, the Pressurized Water Reactor part (PWR) and the Boiling Water Reactor (BWR). The basic difference is the point where steam is formed. The boiling water upper support plate reactor forms steam in the reactor while the core barrel control rod pressurized water reactor forms steam inlet nocontrol. dri rodster duster outlet nozzle through a separate heat exchanger called a steam generator. The Harris Plant is a upper core plate Pressurized Water Reactor (PWR). There are reactor vessel other types of reactors used for research and military purposes. plat The collection of fuel assemblies is referred thimble to as the reactor core. The Harris Plant has instrumentation guides 157 fuel assemblies in the reactor core. The reactor core, the controls, and Figure 13: Reactor Vessel instrumentation, as well as other components are located in the reactor vessel. The components vary greatly by reactor type. The reactor vessel is a specially designed container, which supports all of the components. The reactor vessel varies in wall thickness from 4.87 inches of steel on the lower head to 7.75 inches of steel at the core elevation 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 into the reactor core the rate of nuclear fission is controlled. The Harris Plant has 52 control rods.

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 from the steam. 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 16

steam is generated is a separate water system from reactor water or reactor coolant. This 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, and 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 stea.rn from 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 is 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:

SFission 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 radionuclides are iodine- 131 (1-131), strontium-90 (Sr-90), and cesium- 137 (Cs- 137).

SActivation of normally stable nuclei occurs in the neutron field in the reactor. This occurs 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 radionuclides include tritium (H-3) and cobalt-60 (Co-60). These radionuclei are referred to as activation products.

The sources of radioactive emissions from nuclear power operations are the treatment of water from the reactor systems, and the treatment of air in the buildings that house plant systems. 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 steam lines rod[ enkerator'*5 r"fc:T arsteamlines control water lines

> the reactor vessel and it's associated piping

>the containment building vse 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 it's reactor core associated piping, reactor coolant pumps Figure 14: Primary Containment Structure and the pressurizer.

This containment is maintained at a pressure lower than the pressure outside the building. This is accomplished by a system of fans and filter systems that treat the air inside the secondary containment; thus, any air leakage would be into the secondary containment from the outside.

The air coming from secondary containment is all filtered and treated prior to discharge.

18

- ',aa.e.,i.e. CIt* 4C ha REACTOR SAFETY There are several points regarding nuclear safety that are important to understand:

SCommercial nuclear generating stations cannot explode as a nuclear weapon. T-he 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 cannot be configured to create a nuclear explosion.

>The 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 called 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.

>There are several emergency systems that provide adequate cooling and water to the reactor in the event these are required. Should there be breakage of piping carrying water to the reactor this is referred to as a Loss of Coolant. These systems are activated upon a drop in reactor pressure or a low level of water in the reactor. The exact activation varies by reactor type. These systems that deliver this supplemental source of water are referred to as the Emergency Core Cooling System. There are additional backup systems to the individual Emergency Core Cooling Systems. This practice is referred to as defense in depth. Safety is not dependent on any one device but is a system of several backups.

The Harris 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 plant staff to ensure a high quality performance from each member. 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.

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

The radiological monitoring program was established in 1982 and has continued to collect samples and evaluate them for over 20 years.

Requirements are established for the radiological monitoring program with the following:

) Technical Specifications SOff-Site Dose Calculation Manual (ODCM)

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

SNRC Regulatory Guide 1.109 SNRC Regulatory Guide 4.13

> NRC Regulatory Guide 4.15 20

General Site Description The Harris Nuclear Plant consists of a P 1 pressurized water reactor with a design ..

rating of 900 MWe (Mega Watts _e, electric). Commercial production was .

initiated on January 3, 1987. The Hams &&ED Nuclear Plant is located in southwest ie Wake County, North Carolina. The site ,

is along U.S. route 1 approximately / ,,-m sixteen (16) miles southwest of Raleigh, I North Carolina and is displayed on the map of central North Carolina (Figure A" 15). The site is also approximately fifteen (15) miles northeast of Sanford, North -' .

Carolina. The nearest community is New 3/4 Hill, which is north of the site. ......

• i Harris Lake is adjacent to the plant itself O ,M-i_

w *USA I and is the source of cooling tower makeup water. The lake was impounded Figure 15: Location of Harris Nuclear Plant in the construction of Harris Plant. The lake is fed by Buckhorn Creek and is approximately 4,000 acres in area. The main dam is approximately 4.7 miles south of the site. The primary discharges to Harris Lake from the plant are surface runoff, cooling tower blow down, and radiological waste process systems.

Fishing, boating, and swimming are popular activities on Harris Lake and other nearby lakes.

Carolina Power & Light encourages the recreational use of the lake, Harris Lake County Park, and the adjoining lands through a variety of agreements with state and local government. One of these agreements is the game lands agreement encouraging hunting.

Within a five mile radius most of the land is wooded with only a few residences and limited agricultural activity. There are no non-company industrial structures or residences on the plant site. The chief use of the land is for production of timber and pulp fiber.

Within a ten mile radius the area would be considered rural with significant populations in Apex, Holly Springs, and Fuquay-Varina. Currently these communities are experiencing significant growth.

21

Within a fifty-mile radius much of the land is used in agricultural production. Significant crops include corn, soybeans, and tobacco. Livestock is also an important component with significant production in cattle, hogs, poultry, and dairy products.

Consumption of drinking water, food crops, and fish are sample media that are examples of ingestion pathways for exposure.

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 4.15, "Quality Assurance for Radiological Monitoring Programs." The purpose of the quality assurance program is "(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:

Sregular review of sample collection and records Sregular review of laboratory procedures and methods Sparticipation in the Analytics, Inc. Environmental Cross-Check 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, we have established this program to measure the exposure pathways to man. An exposure pathway describes the source of the radiological exposure. The primary forms of radiological emissions from the plant are airborne and liquid discharge. The following pathways are monitored: external dose, ingestion of radioactive materials, and the inhalation of radioactive material. Specific methods and different environmental media are required to assess each pathway. Below in Table 3 is 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 Drinking Water Food Crops Fish Ground Water Milk Broadleaf Vegetation (when Milk samples are unavailable)

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 unaffected by the 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.

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Radiological Sampling Locations Figure 16: Radiological Sampling Locations (Distant from Plant) (Scale 1 inch=3.9 miles)

Thetmoluninescent dosimeter and shoreline sediment locations (only) are displayed in black, iagestion and waterborne pathways in blue, and inhalation or air sampling stations in red.

Stations I through 5, and 26 include air sampling and thermolumicrnesct dosimeters.

Samule Types Sanmile Locations Air Cartridge & Particulate 1-5, 26,47 (RED)

Shoreline Sediment 26,41 Ground Water 39,57-60 (BLUE)

Drinking Water 38,40 (BLUE)

Surface Water 26,38,40 (BLUE)

Thermoluminaescent Dosimeter 1-37, 48-50, 53, 56, 63 (BLACK EXCEPT AT SHARED LOCATIONS)

Milk 5 (BLUE) & 42 (Reference Only) (BLUE)

Fish 44,45 (BLUE)

Food Products & Broadleaf Vegetation 5,54, 55,62,64, 65,66 (BLUE)

Aquatic Vegetation & Bottom Sediment 41,45,46,52,61 24

Radiological Sampling Locations

<i* 1>

Figure 17: Radiological Sampling Locations (Nearest Plant) (Scale 1 inch =1 miles)

Thermoluminescent dosimeter and shoreline sediment locations (only) an, displayed in black, ingestin and waterborne pathways in blue, and inhalation or air sampling stations in red.

Stations 1 through 5, and 26 include air sampling and thermolummesoeat dosimeters.

Samule Types Sample Locations Air Cartridge & Particulate 1-5,26,47 (RED)

Shoreline Sediment 26,41 Ground Water 39,57-60 (BLUE)

Drinking Water 38,40 (BLUE)

Surface Water 26,38,40 (BLUE)

Thermoluminescent Dosimeter 1-37,48-50,53, 56,63 (BLACK EXCEPT SHARED LOCATION)

Milk 5 (BLUE)

Fish 44,45 (BLUE)

Food Products & Broadleaf Vegetation 5,54,55,62,64,65,66 (BLUE)

Aquatic Vegetation & Bottom Sediment 41,45,46,52,61 c-OS-25

Table 4 Harris Nuclear Plant Radiological Monitoring Sampling Locations Sample Type Location & Description Frequency Sample Size Analysis Air Cartridge 1--2.6 miles N As required by 28,000 ft3 Iodine (AC) 2--1.4 miles NNE dust loading, but (800 m3 )

4--3.1 miles NNE at least once per 7 5--13.4 miles WNW--Pittsboro* days 26--4.7 miles S 47--3.4 miles SSW Air Particulate 1--2.6 miles N As required by 28,000 ft3 Gross Beta (AP) 2--1.4 miles NNE dust loading, but (800 M3) (Weekly) 4--3.1 miles NNE at least once per 7 Composite 5--13.4 miles WNW--Pittsboro* days Gamma 26--4.7 miles S (Quarterly) 47--3.4 miles SSW Fish (FI) 44--Site varies in Harris Lake Semiannual 1 kg (wet) Gamma 45--Site varies in Cape Fear (In Season) Free Swimmers River* & Bottom Feeders Drinking 38--6.2 miles WSW* Weekly 8 liters 1-131, Gamma Water (DW) 40--17.2 miles SSE Lillington Monthly Tritium 51--Water Treatment Plant (On Composite Gross Beta Site)

Ground Water 39-.07 miles SSW Quarterly 4 liters Gamma (GW) 57--.04 miles SSW Tritium 58--.5 miles WSW 59--.5 miles NNE 60--.5 miles ESE Milk (MK) 5--18.2 miles WNW Manco Semimonthly 8 liters 1-131 Dairy* Gamma Shoreline 26--4.6 miles S Semiannual 500 grams Gamma Sediment (SS) 41--3.8 miles S Surface Water 26--4.7 miles S Weekly 8 liters 1-131, Gamma (SW) 38--6.2 miles WSW

• Monthly Tritium 40--17.2 miles SSE Lillington Composite Gross Beta Aquatic 26--4.7 miles S Annually 500 grams Gamma Vegetation 41--3.8 miles S 61--2.5 miles E Bottom 52--3.8 miles S Semiannual 500 grams Gamma Sediment (SD)

Food Products 5--18.0 miles NNW--Pittsboro* Monthly during 500 grams Gamma (FP) 54--1.7 miles NNE--Wilkins or growing season Morris when milk 55--2.0 miles NNW--L. L. samples not Goodwin performed 62--2.3 miles NE--Lee 64--1.8 miles ENE-Michael Broadleaf 65-1.36 miles S-Site Monthly when 500 grams Gamma Vegetation Boundary available (BL) 66--1.33 miles SSW-Site In lieu of Milk Boundary

• Control Stations 26

Table 4 (Continued)

Harris Nuclear Plant Radiological Monitoring Sampling Locations Sample Type Location & Description Frequency Sample Analysis I _I I Size Thermoluminescent 1-2.6 miles N Quarterly Not TLD Dosimetry (TLD) 2-1.4 miles NNE Applicable Reading 3--2.6 miles ENE 4--3.1 miles NNE 5--13.4 miles WNW--Pittsboro*

6--0.8 mile NE 7-0.7 mile E 8--0.6 mile ESE 9--2.2 miles SE 10--2.2 miles SSE 11-0.6 mile S 12--0.9 mile SSW 13--0.7 mile WSW 14--1.5 miles W 15--2.0 miles W 16-- 1.9 miles WNW 17--1.5 miles NW 18-- 1.4 miles NNW 19--5.0 miles NNE 20--4.5 miles NE 21--4.8 miles ENE 22 --4.3 miles E 23 --4.8 miles ESE 24--4.0 miles SE 25--4.7 miles SSE 26--4.7 miles S 27--4.8 miles SW 28--4.8 miles SSW 29--5.7 miles WSW 30--5.6 miles W 31--4.7 miles WNW 32--6.4 miles NNW 33--4.5 miles NNW 34--8.7 miles NE--Apex 35--6.9 miles E--Holly Springs 36--10.9 miles E 37--9.2 miles ESE--Fuquay-Varina 48--4.5 miles N 49--2.5 miles NNE 50--2.6 miles ESE 53--5.8 miles NW 56--3.0 miles WSW 63--0.6 mile S'W

• Control Stations 27

SUMMARY

OF RADIOLOGICAL MONITORING PROGRAM This report presents the results of the Radiological Environmental Monitoring Program conducted during 2001 for the Shearon Harris Nuclear Power Plant (HNP) and fulfills the reporting requirements of Technical Specifications 6.9.1.3 and ODCM E-3. The program was conducted in accordance with Operational Requirement 3.12.1 in the Off-Site Dose Calculation Manual (ODCM), and applicable procedures.

Approximately 1100 total samples of 13 different media types from approximately 880 indicator stations were compared to approximately 230 control stations. Control stations are locations that are unaffected by plant operations. In approximately 99 percent of the indicator samples there was no difference from the activities observed in the corresponding control samples.

Radioactivity in environmental samples attributed to plant operations in 2001 is as follows:

Environmental Radionuclide Location of Activity and Occurrence Maximum Media w/Highest Annual Individual Mean Dose (mrem/yr)

Surface Water H-3 Harris Lake 4,310 pCi/L No ingestion (12/12) pathway. No dose calculated.

Fish H-3 Harris Lake See above. 0.01 Assumes H-3 equilibrium between lake water and Total Body fish tissue.

The radiological environmental data indicates that HNP operations in 2001 had no significant impact on the environment or public health and safety.

A statistical summary of all the data for 2001 has been compiled and summarized in Table 5.

The plant-derived activity detected within the scope of the Radiological Environmental Monitoring Program can be seen in the Data Summary Table 5 for 2001. No detectable tritium activity was observed at Lillington, N.C., located 17 miles downstream on the Cape Fear River, which is the first public drinking water (ingestion pathway) location below the Harris Lake discharge spillway. No plant-related gamma activity has been detected in fish collected from Harris Lake or in the water samples from Lillington, N.C.

The Harris Lake Bottom Sediment and the Aquatic Vegetation pose no radiological dose to the general public via this pathway due to the fact that it is not easily assessable. These samples are for long-term trends.

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( ( (

Table 5 Shearon Harris Nuclear Plant Radiological Environmental Monitoring Program Data Summary Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 2001 Location w/Highest Annual Mean Medium or Type and Typical Lower All Indicator Name, Distance, and Mean(2 ) Control Locations Pathway Total No. of Limit of Detection Locations Mean(2 ) Direction Range Mean(2 )

Sampled or Measurements (LLD) (1) Range Range Measured (Unit Performed of Measurement) _

Air Cartridge 1-131 2.8E-2 All less than LLD All less than LLD All less than LLD (pCi/m3) 315(')

Air Particulate Gross Beta 1.OE-3 1.65E-2 (261/265) New Hill near 1st 1.74E-2 (52/53) 1.60E-2 (53/53)

(pCi/m 3 ) 314"3) 7.35E 2.87E-2 Baptist Church 9.62E 2.87E-2 4.80E 2.36E-2 3.1 miles NNE Gamma Refer to All less than LLD All less than LLD All less than LLD 24 Table 6 Drinking Water(4) 1-131 1.OE+O All less than LLD All less than LLD All less than LLD (pCi/I) 52 Gross Beta 1.0E+0 5.11 E+O (12/12) Lillington 5.11 E+O (12/12) 5.39E+O (12/12) 24 3.69E+O - 7.14E+O Cape Fear River 3.69E+O - 7.14E+O 3.42E+O - 7.45E+O 17.2 miles SSE Gamma Refer to All less than LLD All less than LLD All less than LLD 24 Table 6 Tritium 3.25E+2 All less than LLD All less than LLD All less than LLD 24 29 I.

Table 5 (cont.)

Shearon Harris Nuclear Power Plant Radiological Environmental Monitoring Program Data Summary Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 2001 Location w/Hiighest Annual Mean Medium or Type and Typical Lower All Indicator Name, Distance, and Mean(2) Control Locations Pathway Total No. of Limit of Detection Locations Mean(2) Direction Range Mean(2)

Sampled or Measurements (LLD) ) Range Range Measured (Unit Performed of Measurement) f Fish Bottom-Feeders Gamma Refer to All less than LLD All less than LLD All less than LLD (pCi/g, wet) 4 Table 6 Free-Swimmers Gamma Refer to (pCi/g, wet) 8 Table 6 All less than LLD All less than LLD All less than LLD BroadLeaf Gamma Vegetation 28(3) 2.9E-2 7.39E-2 (1/28) Site Boundary 7.39E-2 (1/10) No control (pCi/g, wet) Cs-137 Single Value 1.33 miles SSW Single Value Food Crop Gamma Refer to All less than LLD All less than LLD All less than LLD (pCi/g, wet) 30() Table 6 Aquatic Gamma Spillway on Main Vegetation 4 3. 1E-2 5.46E-2 (2/4) Reservoir 5.46E-2 (2/2) No control (pCi/g, wet) Co-58 4.2 1E 6.7 1E-2 4.7 miles S 4.2 1E 6.7 IE-2 Spillway on Main Co-60 3.6E-2 4.54E-2 (1/4) Reservoir 4.54E-2 (1/4) No control Single Value 4.7 miles S Single Value Ground Water Gamma Refer to All less than LLD All less than LLD No control (pCi/1) 20 Table 6 North Bank Tritium 3.25E+2 (20/20)(6) 7.15E+2 (4/20) ESW Intake 7.15E+2 (4/4) No control 20 6.14E+2 - 8.25E+2 0.5 mile WSW 6.14E+2 - 8.25E+2 30

( ( (

Table 5 (cont.)

Shearon Harris Nuclear Power Plant Radiological Environmental Monitoring Program Data Summary Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 2001 Location w/Highest Annual Mean Medium or Type and Typical Lower All Indicator Name, Distance, and Mean(2) Control Locations Pathway Total No. of Limit of Detection Locations Mean(2) Direction Range Mean(2)

Sampled or Measurements (LLD)(1) Range Range Measured (Unit Performed of Measurem ent) . ,_ . .. _. __.. . .. . . ... .. ..

Milk 1-131 (pCi/1) 24 1.01E+0 All less than LLD Gamma Refer to 24 Table 6 All less than LLD Shoreline Sediments Gamma Refer to All less than LLD All less than LLD No Control (pCi/g, dry) 4 Table 6 Bottom Sediment Gamma Harris Lake Cooling (pCi/g, dry) 2 4.5 E-2 1.13E-1 (1/2) Tower Mixing Zone 1.13E-1 (1/2) No Control Mn-54 Single Value 3.8 miles S Single Value Harris Lake Cooling Co-58 4.6 E-2 1.09E-1 (1/2) Tower Mixing Zone 1.09E-1 (1/2) No Control Single Value 3.8 miles S Single Value Harris Lake Cooling Co-60 4.4 E-2 6.03E+0 (2/2) Tower Mixing Zone 6.03E+0 (2/2) No Control 2.59E+O - 9.46E+O 3.8 miles S 2.59E+O - 9.46E+O Harris Lake Cooling Ag-108M 5.1E-2 4.30E+O (1/2) Tower Mixing Zone 4.30E+O (1/2) No Control Single Value 3.8 miles S Single Value 31

/i C (

Table 5 (cont.)

Shearon Harris Nuclear Power Plant Radiological Environmental Monitoring Program Data Summary Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 2001 Location w/Hieh st Annual Mean Medium or Type and Typical Lower All Indicator Name, Distance, and Mean(2) Control Locations Pathway Total No. of Limit of Detection Locations Meant 2 ) Direction Range Mean(2 )

Sampled or Measurements (LLD) (1) Range Range Measured (Unit Performed of M easurem ent) ,_ ,_.....IIII Bottom Sediment Harris Lake Cooling (pCi/g, dry) Sb-125 1.23 E-1 5.82E-1 (2/2) Tower Mixing Zone 3.8 5.82E-1 (2/2) No Control 5.54E 6.09E-I miles S 5.54E 6.09E-1 Harris Lake Cooling Cs-137 5.2 E-2 4.20E-1 (2/2) Tower Mixing Zone 3.8 4.20E-1 (2/2) No Control 4.15E 4.26E-1 miles S 4.15E 4.26E-1 Surface Water(4) 1-131 (pCi/1) 52 L.OE+0 All less than LLD All less than LLD All less than LLD Lillington Gross Beta 1.OE+0 4.17E+O (24/24) Cape Fear River 5.11 E+O (12/12) 5.39E+O (12/12) 36 2. 1OE+O - 7.14E+O 17.2 miles SSE 3.69E+O - 7.14E+O 3.42E+O - 7.45E+O Gamma Refer to All less than LLD All less than LLD All less than LLD 36 Table 6 T 3.25E+2 (24/36)(6) All less than LLD All less than LLD All less than LLD Tritium 36 1.00E+3 (12/36)(6) 4.31E+3 (12/24) Harris Lake 4.31E+3 (12/12) 3.01E+3 - 7.24E+3 4.7 miles S 3.01E+3 - 7.24E+3 Direct Fuquay Varina at Old Radiation TLD 1.16E+1 (167/168) CP&L Office 1.57E+1 (4/4) 1.50E+1 (4/4)

(mR/qtr) 171 (3) 8.70E+O- 1.63E+l 9.2 miles ESE 1.49E+l - 1.63E+1  !.44E+l - 1.57E+l 32

.*. .a,.ra1.nwa...v. .. . - -

FOOTNOTES TO TABLE 5

1. The 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 and 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 all samples with detectable activities at specific locations are indicated in parentheses.

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

4. Although quarterly composite samples are required, monthly composite samples are used to provide more frequent and sensitive analyses.

5. 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).

6. Tritium Lower Limit of Detection (LLD) was lowered to 3.25 E+2 pCi/L in June 1996 for samples that typically demonstrate activity less than the LLD. 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.

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INTERPRETATIONS AND CONCLUSIONS Air Monitoring All 315 air cartridge samples from indicator and control stations had 1-131 concentrations less than the typical LLD of 2.8E-2 pCi/mi3. 1-131 was detected in air samples for a six-week period following the Chernobyl incident in April 1986. With this exception, no 1-131 has been detected in air samples collected from 1987 through 2001, which is the entire operating history of the plant.

For the period of January 1, 2001 to December 31, 2001; the gross beta activity was detectable in all airborne particulate samples, with acceptable volumes, from the five indicator locations. The 261 indicator samples had an average concentration of 1.65E-2 pCi/m 3 , a value similar to or less than preoperational data of 2.OOE-2 pCi/m3 . Similar gross beta activities were observed at the control location in Pittsboro, which had an average concentration of 1.60E-2 pCi/mr3 in 53 control samples. Figures 18 through 22 provide a graphic representation of the gross beta activity at the indicator locations compared to the control location for the year 2001. As seen in the graphs (Figures 18-22), AP-5 (control location) on 10-8-01 exhibits an abnormally low gross beta activity (4.80E-3 pCi/mr3), which is attributed to low beta counts and normal sample volume flow. No gamma activity was observed for any air particulates during that quarter. These concentrations are typical of the natural environment and are not attributed to plant operations.

No plant-related gamma activity was detected in quarterly composite filter samples from either the indicator or control locations. Typical LLDs for air particulates are contained in Table 6.

Drinking Water The 26 drinking water samples collected at the Lillington Municipal water supply and the 26 control samples collected from the Cape Fear River above the Buckhorn Dam contained less than detectable 1-131 activity (< 1.0 E+0 pCi/L) during 2001. This has been the experience for the preoperational and operational period with the exception of 1986 when the fallout from Chernobyl was detected.

34

The average annual gross beta concentrations at the indicator and control locations were similar in concentrations of 5.1 1E+0 pCi/L and 5.39E+0 pCi/L, respectively. This is similar to the preoperational average of 4.OOE+0 pCi/IL. These concentrations are attributed to the natural environment and are not attributed to plant operations. Figure 23 provides graphic representation of the gross beta activity during 2001 for Location 40 (Lillington).

Analyses for gamma-emitting radionuclides indicated all concentrations were less than the lower limit of detection for drinking water. Table 6 contains typical LLD values for gamma-emitting radionuclides in drinking water.

Tritium concentrations in the Lillington Municipal Water Supply samples were less than the lower limit of detection (3.25 E+2 pCi/IL) (see Footnotes to Table 5, Footnote 6).

Fish Analyses for gamma-emitting radionuclides in two samples of bottom-feeding fish and in four samples of free-swimming species (sunfish and largemouth bass) from the indicator location, Harris Lake, revealed no detectable activity for 2001. This is consistent with the data for 1989 2000. During the Chernobyl period, Cs-134, 137 were detected in both control and indicator samples.

Fish are assumed to be in equilibrium with the tritium concentration in the lake. The total body/organ dose to the maximum exposed individual due to tritium was calculated using Regulatory Guide 1.109, Rev.1, October 1977, Equation A-1, to be 0.0095 - 0.01 mrem/year.

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) 35

Daipj ingestion dose factor for total body/organ of individual in Uap in mrem/pCi (Reg. Guide 1.109 Table E- 11, E-12, or E-13)

The Total Body/Organ dose is as follows:

Child Teenager Adult Consumption of fish kg/yr 6.9 16 21 Dose (Total Body/Organ) mrem/yr 0.006 0.007 0.01 The total body dose and organ dose, due to tritium in the fish, (ingestion dose factor - Reg. Guide 1.109 Table E-11, E-12, and E-13) for the maximum exposed individual being a child, a teenager, or an adult having a consumption rate of approximately 6.9 kg fish/yr. (15 lbs), 16 kg fish/yr. (35 lbs), or 21 kg fish/yr. (46 lbs) (Reg. Guide 1.109 Table E-5) calculates to be 0.006, 0.007, or 0.01 mrem/year respectively.

Milk/Broadleaf Vegetation During 2001, as in all past years with the exception of the Chernobyl period, no 1-131 concentrations were detected in milk samples. Gamma analyses revealed no detectable radioactivity from plant operations. The only detectable gamma activity identified in each milk sample was potassium-40 (K-40). This is a natural occurring nuclide in any living organism or product of. The K-40 concentrations in the milk control samples range from 1.00E+3 pCi/L 2.23E+3 pCi/L.

In May of 1997, the Maple Knoll Dairy (indicator MK located in the SSE sector) ceased operations. In lieu of the semimonthly milk samples, per HNP ODCM Table 3.12-1, broadleaf vegetation samples were collected in both the South (S) and SSW sectors.

Broadleaf sampling is conducted since no milk animals are available 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. Broadleaf vegetation sampling is accomplished by collecting monthly, three different species of samples, when available, at two off site locations (two 36

indicator locations of the highest predicted annual average ground level D/Q). The highest predicted annual average ground level D/Q (ODCM Table A-i through A-4) was at the site boundary in both the South sector at 1.36 miles (BL-65) and SSW sector at 1.33 miles (BL-66).

The gamma analyses on the broadleaf vegetation detected Cs-137 (7.39E-2 pCi/gm wet) in one out of 28 samples (Dogwood, Maple, and Sweetgum) from the indicator locations collected in 2001. Upon comparing these results, it is concluded that the indicator value reflects fallout Cs 137 contamination since no other plant-related radioactivity was detected in the broadleaf vegetation in 2001.

Surface Water Surface water samples were collected (weekly) and analyzed (bi-weekly) for 1-131. Water samples collected during 2001 contained no detectable 1-131 (LLD < 1.OE+0 pCi/L).

Average gross beta concentrations at the indicator and control locations were 4.17E+0 pCiIL and 5.39E+0 pCi/L, respectively in 2001, indicating no adverse influence from plant operations (See Figure 24).

Surface water samples were analyzed for gamma and tritium radioactivity. All concentrations of man-made gamma-emitters were less than their respective lower limits of detection (see Table 6).

The annual average tritium concentration in Harris Lake was 4.31E+3 pCi/L with minimum and maximum values of 3.01E+3 pCi/L and 7.24E+3 pCi/L, respectively (see Figure 25). The average Harris Lake tritium concentration showed an increase in tritium compared to the annual average of 3.52E+3 pCi/L in 2000. The tritium liquid release program is managed by periods of high rainfall to minimize the impact of the tritium concentration in the lake.

Ground Water Ground water samples are collected on site at HNP for gamma and tritium analysis. The measured concentrations of the gamma analyses were measured below their required Lower Limits of Detection (LLD) as specified in the Harris Plant ODCM (docket No. STN-50-400) in Table 4.12-1 titled "Detection Capabilities For Environmental Sample Analysis Lower Limit of Detection (LLD)" for the year 2001.

37

The measured tritium concentrations were below the required HNP ODCM Table 4.12-1 LLD for environmental samples. These limits are 2000 picocuries per Liter (pCi/L) for a drinking water pathway and 3000 pCi/L if no drinking water pathway exists. HNP administratively established a ground water tritium analysis LLD of 325 pCi/L, which is well below the requirements specified in the HNP ODCM.

The ground water tritium analysis for the year 2001 determined that no detectable tritium concentration was present based on the LLD specified in the HNP ODCM. However, trace levels of tritium, below the 2000 pCi/L ODCM LLD, but above the HNP administrative LLD (325 pCi/L) were detected in ground water Location 58 (0.5 mile WSW Sector N Bank ESW Intake). See Table 5 on page 30. The ground water wells, located on site at HNP, are all abandoned wells and are not a water supply for drinking or irrigation; therefore, there is no radiological dose via this pathway.

Shoreline Sediment Shoreline sediment samples were collected (1) opposite the discharge structure and (2) near the main dam in 2001. No long-term trends are readily observed in these samples.

Bottom Sediment The 2001 data shows Manganese (Mn)-54 (1.13E-1 pCi/gm dry Single Value), Cobalt (Co)-58 (1.09E-1 pCi/gm dry Single Value), Co-60 (2.59E+0 - 9.46E+0 pCi/gm dry), Silver (Ag)-108m (4.30E+0 pCi/gm dry Single Value), Antimony (Sb)-125 (5.54E 6.09E-1 pCi/gm dry), and Cesium (Cs)-137 (4.15E 4.26E-1 pCi/gm dry) activity in the indicator sample, which is sampled semiannually. The bottom sediment sample from Harris Lake poses no radiological dose to the general public via this pathway due to the fact that it is not easily assessable (i.e.

bottom sediment is approximately forty to sixty feet plus under water). These samples are for long-term trends for liquid effluents.

38

Food Crops In addition to milk sampling (or broadleaf vegetation sampling), a food product sampling program was maintained. Various crops were collected during growing season(s), which basically continued year round. The species selected were primarily broad-leaf vegetables most sensitive to direct fallout of airborne radioactive particulates. Crops sampled in 2001 included cabbage, collards, cucumbers, eggplants, mustard greens, squash, tomatoes, and turnips and greens. Gamma analyses of the food crops detected no plant-related activity in 16 samples from indicator locations and 14 samples from control locations collected in 2001.

Aquatic Vegetation The 2001 data shows Co-58 (4.21E 6.71E-2 pCi/gm wet) and Co-60 (4.54E-2 pCi/gm wet Single Value) activity in the indictor sample, which is sampled annually. There were four aquatic vegetation samples collected from Harris Lake in 2001. The aquatic vegetation samples from Harris Lake pose no radiological dose to the general public via this pathway. The samples are for long-term trends for liquid effluents.

External Radiation Exposure Thermoluminescent dosimeters (TLDs) were used to monitor ambient radiation exposures in the plant environs. The average quarterly exposure from the indicator locations was 11.6 mR and 15.0 mR from the control station. The highest indicator location was 9.2 miles ESE of the plant (Fuquay Varina at the old CP&L office) and the average was 15.7 mR/qtr. The differences among these locations are attributed to variations in soils, local geology, and are not the result of plant operations.

Comparison of the quarterly TLD exposure within approximately 2 miles (inner ring) of the plant with that at approximately 5 miles (outer ring) is presented in Figure 26. These data illustrate that the quarterly inner ring TLD exposures are slightly less than the quarterly outer ring TLD exposures (differences range from 0.21 mR to 0.50 mR).

39

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

"* AC/AP-2, August 13 - The air sampler was not working. No significant volume. Sampler was replaced and Condition Report #46603 was written to document this problem.

"* AC/AP-4, September 11 - Blown fuse, low volume. Condition Report # 47771 was written to document this problem.

"* AC/AP-26, September 11 - Blown fuse, low volume. Condition Report # 47771 was written to document this problem.

"* AP-1, September 25 - Air Sampler was malfunctioning. A low volume was obtained.

Repaired and returned to service. Condition Report # 49549 was written to document this problem.

Food Crops Food crops were not available from any garden location for sampling during March, April, and May. During the remainder of the year, January through December, at least one food crop was available from the sample locations, except for locations 62 and 64. Garden locations 62 (2.3 miles NE sector) and 64 (1.8 miles ENE Sector) did not have a garden for sampling in 2001.

Broadleaf Vegetation Broadleaf vegetation samples were not available for sampling during January,-February, March, April, November, and December of 2001.

40

TLDs One of a possible 172 TLD samples were missing during 2001. It was:

• Second Quarter - TLD 28 was missing in the field. The area around the location was searched, but the TLD could not be located. Condition Report #44773 was written to document this problem.

41

I

• 4-..... .'. . j.%.fl..e.j ANALYTICAL PROCEDURES Gross Beta Gross beta radioactivity measurements are made utilizing a Tennelec Low-Background Alpha/Beta Counting System. The LLD for air particulates is approximately 1.0E-3 pCi/m3 for HNP samples. Air particulate samples are mounted in 2-inch stainless steel planchits and counted directly.

Gross beta activity in drinking and surface waters is determined by evaporating I liter of the sample and counting a planchet on a Tennelec Low-Background Alpha/Beta Counting System for 50 minutes. Typical LLD for gross beta is 1.0E+0 pCi/L.

Tritium Liquid samples requiring tritium analysis are treated with a small amount of sodium hydroxide, 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. Samples that typically exhibit activity are counted for 60 minutes to achieve an approximate LLD of 1.0 E+3 pCi/L. Samples, which routinely demonstrate activity less than the lower limit of detection, are counted for 500 minutes with an approximate LLD of 3.25 E+2 pCi/L. The tritium LLD was lowered in 1996 at the request of the plants (see Footnotes to Table 5, Number 6).

Iodine-131 Iodine-131 airborne concentrations are analyzed by the intrinsic germanium (Ge) spectrometry systems. The cartridges are placed on the detector, and each charcoal cartridge is counted individually with an LLD 2.8 E-2 pCi/m 3 .

Iodine-131 in milk and drinking water is determined by an instrumental method. Analysis involves passing 4 liters over an anion exchange resin and direct gamma analysis of the resin 42

.stdD.DI% - .- -- & ci. .ptaA& - %dIa..a * .11.t jfl.&(g *jaz.

with an intrinsic Ge detector. The LLD using the Ge detector is approximately 1.0 E+0 pCi/L using a 25,000-second count time.

Gamma Spectrometry Gamma samples are analyzed by the 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 6 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, except milk, are boiled down to a small volume, transferred to a Poly Bottle (PB-50 beaker) and analyzed for 7,000 seconds. One-liter milk samples are analyzed in a 1-liter Marinelli beaker for 11,000 seconds.

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

Food crop, aquatic vegetation, and broadleaf vegetation samples are weighed as sampled 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 gamma analysis using a count time of 1,500 seconds.

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 43

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 its analytical results. The change in vendors for the Interlaboratory Program was due to the EPA Environmental Cross Check Program's termination for utility participation as of December 31, 1995.

During 2001, 106 analyses were completed on 18 samples representing five major environmental media (i.e., 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:

Standard Deviation From Known Activity Percent of Analyses

<*1 Standard Deviation 59

< 2 Standard Deviation 86

< 3 Standard Deviation 97 Three of 106 analyses exceeded the three-sigma action level; however, all three were well within the +/- 20% ratio to the known value. The analyses that exceed the three-sigma action level do not 44

indicate a trend and the related environmental analyses' results were not impacted. The results that lie at greater than three standard deviations from the known value have an evaluation performed to identify any recommended remedial actions and to reduce anomalous errors.

Condition report(s) (AR#43487 and AR#50067) documenting the evaluation will be available and provided to the NRC upon request.

Lower Limits of Detection All samples analyzed met the LLD required by the ODCM.

45

Table 6 Typical Lower Limits of Detection (A Priori)

Gamma Spectrometry Drinking Water/Surface Water/Ground Water Samples Isotone 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 B a-La- 140 10 Other Expected 3 to 154 Gamma Emitters Air Particulates (Quarterly Composite)

Isotope LLD (pCi/m 3) 1-131 0.038 Cs-134 0.001 Cs-137 0.001 Other Expected Gamma Emitters 0.00 1 to 0.038 Milk Isotope LLD (pCi/L) 1-131 1.0*

Cs-134 11 Cs-137 9 Other Expected Gamma Emitters 8 to 206 Sediment 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

• Instrumental analysis of resin concentrates of samples.

46

Table 6 (Cont.)

Typical Lower Limits of Detection (A Priori)

Gamma Spectrometry Food Products and Vegetation Isotope LLD (pCi/kg wet) 1-131 38 Cs-134 41 Cs-137 29 Other Expected Gamma Emitters 25 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 each year 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 during the growing season each year. 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 to ensure the monitoring program is current, as well as provide data for the calculation of estimated radiation exposure.

The pathways 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 and if not then broadleaf vegetation is collected in lieu of milk. The grass used to feed these animals may have incorporated or had deposited on it radioactive materials that can be transferred to the milk.

SDirect 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.

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]):

SThe nearest resident SThe nearest garden of greater that 500 square feet, producing broadleaf vegetables

> The nearest milk animal 48

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, and farm supply businesses.

2001 Land-Use Census Results The 2000 and 2001 results of the survey for the nearest resident, garden, milk and-meat animals in each sector are compared in Table 7.

The nearest resident in each sector remained the same from 2000 to 2001. No gardens were located within 5 miles of the plant for the E, S, and NW sectors. All the gardens located in 2001 were the same as 2000. No meat animals were found in the E, S, SSW, WNW, and NW sectors in 2001. A meat animal location was reinstated in the SSE sector at 4.2 miles The dairy in the SSE sector at 7.0 miles from the plant ceased operation in 1997 and there still remain no milk animals near the plant.

49

Table 7 Land-Use Census Comparison (2000-2001)

Nearest Pathway (Miles)

SECTOR RESIDENT GARDEN MEAT ANIMAL MILK ANIMAL 2001 2000 2001 2000 2001 2000 2001 2000 N 2.2 2.2 2.2 2.2 2.2 2.2 NNE 1.9 1.9 1.9 1.9 2.2 2.2 NE 2.3 2.3 2.3 2.3 2.3 2.3 ENE 1.6 1.6 1.8 1.8 1.8 1.8 E 1.7 1.7 ............

ESE 2.6 2.6 2.6 2.6 4.6 4.6 SE 2.6 2.6 4.1 4.1 2.6 2.6 ......

SSE 4.2 4.2 4.2 4.2 4.2* .........

S 5 .3 5 .3 ..................

SSW 3.8 3.8 3.8 3.8 ............

SW 2.9 2.9 2.9 2.9 2.9 2.9 --

WSW 4.5 4.5 4.5 4.5 4.6 4.6 ......

W 3.0 3.0 3.1 3.1 3.1 3.1 ......

WNW 2.3 2.3 2.3 2.3 ............

NW 2.4 2.4 ---............

NNW 1.6 1.6 2.0 2.0 2.0 2.0

• Represents a change from the previous year.

Sector and distance determined by Global Positioning System.

50

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) 51

• in . * .. *.. a.. .. dJCi.siUSUIdMMIUAbe' 'MJVft10 "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 ScientificCommittee on the Effects of Atomic Radiation, 1988 Report to the General Assembly, United Nations, New York, N.Y. (1988)

"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) 52

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Figure 23 HNP From 1/1/2001 To 12/31/2001 DRINKING WATER for GROSS BETA - Activity (pCi/Liter) w wF Location 38 Control Location 40 7 .0 ,,

6.5 7.0--__ _

\/ ' /

4.5 5

4.0-

-F/

Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 2002 Date 58

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Figure 24 HNP From 1/1/2001 To 12/31/2001 SURFACE WATER for GROSS BETA - Activity (pCi/Liter) wLi-Location 26 AI Location 38 control 7

6 5

5; 4

3 2

Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 2002 Date 59

pCi/Liter

-a -a -o (A

o o

0 a

0 (SI 0

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Figure 26 HNP 2001 TLD Averages for Inner and Outer Ring Locations 12.5--

A AlI 12-4 00 11.5 V C

o 11 7 P-7 o 10.5-1 10-9..5

w - i , I I t . . I I ] =

I m

-_ pJ 15-Feb-01 15-Feb-01 15-May 15-Nov 15-Nov 15-May 15-Aug-01 15-Aug-01 01 01 01 01 Inner Outer Inner Outer Inner Outer Inner Outer Dates 61

DATA REPORTS HNP RadiologicalEnvironmental Monitoring TLD Report Dose: mR/std. qtr.

TL fl TLD Location lD.esrintion Sample Date Dose 2 Sigma Error AL1 JýUuuttult AmaLa Iyt,&uff&

2/15/01 12.9 2.2 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 5/15/01 12.3 0.4 SR 1134 AT INTSR 1011 -DIXIE PIPELINE 8/15/01 13 1.6 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 11/15/01 13 1 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 2/15/01 13.5 SR 1134 5/15/01 11.9 0.7 SR 1134 8/15/01 14.2 1.6 SR 1134 11/15/01 13.7 0.7 SR 1134 2/15/01 12.1 1.2 HARRIS E&E CENTER - 2.2 MI NE 5/15/01 10.4 0.6 HARRIS E&E CENTER - 2.2 MI NE 8/15/01 12.7 0.9 HARRIS E&E CENTER - 2.2 MI NE 11/15/01 11.6 0.5 HARRIS E&E CENTER - 2.2 MI NE 2/15/01 11.8 1.1 NEW HILL NEAR 1ST BAPTIST CH 5/15/01 10.7 0.4 NEW HILL NEAR 1ST BAPTIST CH 8/15/01 11.1 0.9 NEW HILL NEAR 1ST BAPTIST CH 11/15/01 11.6 1.5 NEW HILL NEAR 1ST BAPTIST CH 2/15/01 15.4 1.2 PITTSBORO - CONTROL 5/15/01 14.4 0.4 PITTSBORO - CONTROL 8/15/01 15.7 1 PITTSBORO - CONTROL 11/15/01 14.6 1.3 PITTSBORO - CONTROL 2/15/01 11.1 0.9 INT OF SR 1134 AND 1135 PageIlof 8

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 6 INT OF SR 1134 AND 1135 5/15/01 10.2 0.5 6 INT OF SR 1134 AND 1135 8/15/01 10.8 1.1 6 INT OF SR 1134 AND 1135 11/15/01 11.5 1.4 7 HOUSE RUINS ON SR 1134 2/15/01 10.3 1.3 7 HOUSE RUINS ON SR 1134 5/15/01 9 1.1 7 HOUSE RUINS ON SR 1134 8/15/01 10.3 1 7 HOUSE RUINS ON SR 1134 11/15/01 9.9 0.8 8 DEAD END OF SR 1134 2/15/01 15.1 1.1 8 DEAD END OF SR 1134 5/15/01 11 0.6 8 DEAD END OF SR 1134 8/15/01 14.5 1 8 DEAD END OF SR 1134 11/15/01 11.8 1 9 1 MI SW OF HOLLEMANS XRDS ON SR 1130 2/15/01 9.1 0.9 9 1 MI SW OF HOLLEMANS XRDS ON SRI1130 5/15/01 9 0.9 9 1 MI SW OF HOLLEMANS XRDS ON SR 1130 8/15/01 9.3 0.8 9 1 MI SW OF HOLLEMANS XRDS ON SR 1130 11/15/01 9.7 1 10 2.0 MI SW OF HOLLEMANS XRDS ON SR 1130 2/15/01 11.2 1.3 10 2.0 MI SW OF HOLLEMANS XRDS ON SR 1130 5/15/01 10.4 0.7 10 2.0 MI SW OF HOLLEMANS XRDS ON SR 1130 8/15/01 10.9 0.8 10 2.0 MI SW OF HOLLEMANS XRDS ON SR 1130 11/15/01 11 0.5 11 EARTHEN DAM AT HARRIS PLANT 2/15/01 10.7 1.8 11 EARTHEN DAM AT tARRIS PLANT 5/15/01 9.9 0.6 11 EARTHEN DAM AT HARRIS PLANT 8/15/01 11 1.3 11 EARTHEN DAM AT HARRIS PLANT 11/15/01 11.7 0.9 12 1 MI S ON DIRT RD FROM TLD 13 2/15/01 10.6 1.7 Page 2 of8

Dose: mR/std. qtr.

Sample Date Dose 2 Sigma Error TLD TLD Location Description 5/15/01 10.4 1.4 12 1 MIS ON DIRT RD FROM TLD 13 8/15/01 10.4 1.1 12 1 MI S ON DIRT RD FROM TLD 13 11/15/01 10.5 0.6 12 1 MI S ON DIRT RD FROM TLD 13 2/15/01 11.3 2 13 DIRT RD INT BETWEEN PLANT AND AUX RES 5/15/01 10.7 0.9 13 DIRT RD INT BETWEEN PLANT AND AUX RES 8/15/01 11.2 1.5 13 DIRT RD INT BETWEEN PLANT AND AUX RES 11/15/01 11.8 0.7 13 DIRT RD INT BETWEEN PLANT AND AUX RES 2/15/01 10.8 1.4 14 DEAD END OF SR 1911 5/15/01 9.7 0.4 14 DEAD END OF SR 1911 8/15/01 10.6 1 14 DEAD END OF SR 1911 11/15/01 10.7 0.8 14 DEAD END OF SR 1911 2/15/01 10.2 1 15 CEMETERY ON SR 1911 5/15/01 10 0.9 15 CEMETERY ON SR 1911 8/15/01 10.3 1.2 15 CEMETERY ON SR 1911 11/15/01 10.9 0.9 15 CEMETERY ON SR 1911 2/15/01 12.8 1.2 16 US 1 AT CHATHAM-WAKE CO LINE 5/15/01 11.2 1 16 US 1 AT CHATHAM-WAKE CO LINE 8/15/01 12.4 1.9 16 US 1 AT CHATHAM-WAKE CO LINE 11/15/01 12.3 1.9 16 US 1 AT CHATHAM-WAKE CO LINE 2/15/01 12 1.1 17 INTOF US1 AND AUX RES 5/15/01 10.1 0.6 17 NT OF US 1 AND AUX RES 8/15/01 11.6 1.1 17 INT OF US 1 AND AUX RES 11/15/01 11.7 1.1 17 INT OF US1 AND AUX RES 2/15/01 12.2 2.8 18 0.6 MI N ON US 1 FROM TLD 17 Page3 of8

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 5/15/01 11.7 1 18 0.6 MI N ON US 1 FROM TLD 17 8/15/01 12.2 2.1 18 0.6 MI N ON US 1 FROM TLD 17 11/15/01 12.6 1.3 18 0.6 MI N ON US 1 FROM TLD 17 2/15/01 10.4 1.2 19 SR 1142-OLIVES DAIRY 5/15/01 10.2 0.4 19 SR 1142 - OLIVES DAIRY 8/15/01 10.7 1 19 SR 1142 - OLIVES DAIRY 11/15/01 11.4 0.8 19 SR 1142 - OLIVES DAIRY 2/15/01 13.7 1.3 20 INT OF SR 1149 AND US 1 5/15/01 14 1.9 20 INT OF SR 1149 AND US 1 8/15/01 14.2 1.5 20 INT OF SR 1149 AND US 1 11/15/01 14.6 0.6 20 INT OF SR 1149 AND US 1 2/15/01 12.8 0.9 21 1.3 MI ON SR 1152 FROM INT SR 1153 5/15/01 9.8 0.7 21 1.3 MI ON SR 1152 FROM INT SR 1153 8/15/01 12.7 1.3 21 1.3 MI ON SR 1152 FROM INT SR 1153 11/15/01 10.3 0.7 21 1.3 MI ON SR 1152 FROM INT SR 1153 2/15/01 10.2 1.1 22 2.0 MI E OF HOLLEMANS XRDS ON SR 1115 5/15/01 10.6 0.4 22 2.0 MI E OF HOLLEMANS XRDS ON SR 1115 8/15/01 10.1 0.8 22 2.0 MI E OF HOLLEMANS XRDS ON SR 1115 11/15/01 10.6 0.7 22 2.0MI E OF HOLLEMANS XRDS ON SR 1115 2/15/01 12.3 1.7 23 INT SR 1116 AND SR 1127 5/15/01 11 0.6 23 INT SR 1116 AND Spi1127 8/15/01 11.9 1.2 23 INT SR 1116 AND SR 1127 11/15/01 11.7 0.6 23 INT SR 1116 AND SR 1127 2/15/01 11.8 1.8 24 SWEET SPRINGS CHURCH ON SR 1116 Page 4 of8

.A.

7 Dose: mR/std. qtr.

-1 ý Sample Date Dose 2 Sigma Error I LI) ILD Location LDescriptionW 1.2 5/15/01 11 11 1.2 24 SWEET SPRINGS CHURCH ON SR 1116 8/15/01 11.5 0.9 24 SWEET SPRINGS CHURCH ON SR 1116 11/15/01 11.1 1 24 SWEET SPRINGS CHURCH ON SR 1116 2/15/01 13.7 1.8 25 0.2 MI W OF INT OF SR 1401 AND SR 1402 5/15/01 10.3 0.7 25 0.2 MI W OF INT OF SR 1401 AND SR 1402 8/15/01 13.7 2.3 25 0.2 MI W OF INT OF SR 1401 AND SR 1402 11/15/01 11.7 0.5 25 0.2 MI W OF INT OF SR 1401 AND SR 1402 2/15/01 10.8 1.7 26 SPILLWAY ON MAIN RES 5/15/01 10.4 0.5 26 SPILLWAY ON MAIN RES 8/15/01 10.7 1.7 26 SPILLWAY ON MAIN RES 11/15/01 11 0.5 26 SPILLWAY ON MAIN RES 2/15/01 9.1 1.8 27 BUCKHORN UNITED METHODIST CH ON NC 42 5/15/01 8.8 0.9 27 BUCKHORN UNITED METHODIST CH ON NC 42 8/15/01 9.2 0.9 27 BUCKHORN UNITED METHODIST CH ON NC 42 11/15/01 9.8 0.7 27 BUCKHORN UNITED METHODIST CH ON NC 42 2/15/01 11 1.3 28 0.6 MI FROM INT SR 1916 AND SR 1924 8/15/01 11 1.1 28 0.6 MI FROM INT SR 1916 AND SR 1924 11/15/01 10.5 0.7 28 0.6 MI FROM INT SR 1916 AND SR 1924 2/15/01 12.6 1.2 29 NESTE RESIN CORP ON SR 1916 5/15/01 11.2 1.1 29 NESTE RESIN CORP ON SR 1916 8/15/01 12.7 1.1 29 NESTE RESIN CORP ON SR 1916 11/15/01 12.8 0.7 29 NESTE RESIN CORP ON SR 1916 2/15/01 10.4 1.2 30 INT OF SR 1972 AND US 1 5/15/01 10.4 0.5 30 INT OF SR 1972 AND US 1 Page 5 of 8

Dose: mR/std. qtr.

TLD TLD Location Description Samp*ie Date Dose 2 Sigma Error 30 INT OF SR 1972 AND US 1 8/15/01 10.2 1.5 30 INT OF SR 1972 AND US 1 11/15/01 10.7 0.9 31 INT OF SR 1910 2/15/01 12.2 1.4 31 INT OF SR 1910 5/15/01 8.7 1 31 INT OF SR 1910 8/15/01 11.4 0.9 31 INT OF SR 1910 11/15/01 10 0.6 32 3 MI ON SR 1008. FROM INT SR 1011 2/15/01 12.1 1.4 32 3 MI ON SR 1008 FROM INTSR 1011 5/15/01 11.6 0.6 8/15/01 12.2 1 32 3 MI ON SR 1008 FROM INT SR 1011 32 3 MI ON SR 1008 FROM INT SR 1011 11/15/01 12.3 0.6 33 SR 1142 AT BARRICADE 2/15/01 10.8 0.9 33 SR 1142 AT BARRICADE 5/15/01 10 0.5 33 SR 1142 AT BARRICADE 8/15/01 10.8 0.9 33 SR 1142 AT BARRICADE 11/15/01 10.7 0.7 34 APEX AT JONES PARK 2/15/01 13.4 2.4 34 APEX AT JONES PARK 5/15/01 12.7 0.8 34 APEX AT JONES PARK 8/15/01 14.3 1.2 34 APEX AT JONES PARK 11/15/01 14.7 0.5 35 HOLLY SPRINGS ON EARP STREET 2/15/01 12.9 1.7 35 HOLLY SPRINGS ON EARP STREET 5/15/01 12.5 1 35 HOLLY SPRINGS ON EARP STREET 8/15/01 13.5 0.9 35 HOLLY SPRINGS ON EARP STREET 11/15/01 13.1 0.5 36 NT OF SR 1393 AND SR 1421 2/15/01 11.8 1 36 INT OF SR 1393 AND SR 1421 5/15/01 10.4 1.1 Page 6 of8

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 36 INT OF SR 1393 AND SR 1421 8/15/01 12.2 1.7 36 INT OF SR 1393 AND SR 1421 11/15/01 11.4 0.9 37 FUQUAY VARINA AT OLD CP&L OFFICE 2/15/01 16.3 1.5 FUQUAY VARINA AT OLD CP&L OFFICE 5/15/01 14.9 1.2 37 37 FUQUAY VARINA AT OLD CP&L OFFICE 8/15/01 16.2 1.1 37 FUQUAY VARINA AT OLD CP&L OFFICE 11/15/01 15.4 0.8 48 SR 1142 AT UNDERGROUND CABLE SIGN 2/15/01 13.7 1.2 48 SR 1142 AT UNDERGROUND CABLE SIGN 5/15/01 12.8 0.7 48 SR 1142 AT UNDERGROUND CABLE SIGN 8/15/01 13.7 1.1 48 SR 1142 AT UNDERGROUND CABLE SIGN 11/15/01 13.4 1.1 49 SR 1127 AT WAKE CO TRASH COLLECTION AREA 2/15/01 14.5 0.9 49 SR 1127 AT WAKE CO TRASH COLLECTION AREA 5/15/01 13.3 1.5 49 SR 1127 AT WAKE CO TRASH COLLECTION AREA 8/15/01 14.6 1.6 49 SR 1127 AT WAKE CO TRASH COLLECTION AREA 11/15/01 14.8 2.4 50 HOLLEMANS CROSSROADS 2/15/01 11.6 1.4 50 HOLLEMANS CROSSROADS 5/15/01 9.3 0.8 50 HOLLEMANS CROSSROADS 8/15/01 11.5 0.9 50 HOLLEMANS CROSSROADS 11/15/01 10.5 1.7 53 INTERSECTION OF SR 1972 AND SR 1907 2/15/01 10.9 1.1 53 INTERSECTION OF SR 1972 AND SR 1907 5/15/01 9.8 0.5 53 INTERSECTION OFLSR 1972 AND SR 1907 8/15/01 10.9 1.1 53 INTERSECTION OF SR 1972 AND SR 1907 11/15/01 10.7 1 56 2.8 MI WSW OF THE SITE 2/15/01 12.1 1.4 56 2.8 MI WSW OF THE SITE 5/15/01 11 0.7 Page 7 of 8

Dose: mR/std. qtr.

TLD TLD Location Description Sample Date Dose 2 Sigma Error 56 2.8 MI WSW OF THE SITE 8/15/01 12.4 0.8 56 2.8 MI WSW OF THE SITE 11/15/01 11.5 1.1 63 0.7 MI SW SECTOR ON (POWER POLE COJ85) 2/15/01 13.8 1.4 63 0.7 MI SW SECTOR ON (POWER POLE COJ85) 5/15/01 12.9 1 63 0.7 MI SW SECTOR ON (POWER POLE COJ85) 8/15/01 14 2.1 63 0.7 MI SW SECTOR ON (POWER POLE COJ85) 11/15/01 13.3 1.8 Page8 of8

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

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

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

/I-HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/1/01 711.2 1.42E-02 1.64E-03 1.46E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/8/01 612.3 8.86E-03 1.65E-03 1.86E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/15/01 613.7 1.43E-02 1.88E-03 1.81 E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/22/01 610.3 1.50E-02 1.91 E-03 1.79E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/29/01 614.2 1.64E-02 1.98E-03 1.84E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 2/5/01 613.6 1.67E-02 1.96E-03 1.74E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 2/12/01 605.5 1.31E-02 1.82E-03 1.77E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 2/19/01 606 1.1 8E-02 1.80E-03 1.87E-03 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 2/26/01 606.6 1.66E-02 1.99E-03 1.82E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 3/5/01 603.9 1.47E-02 1.92E-03 1.84E-03 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 3/12/01 601.1 1.18E-02 1.76E-03 1.74E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 3/19/01 601.7 9.30E-03 1.70E-03 1.91 E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 3/26/01 604.8 1.33E-02 1.87E-03 1.86E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/2/01 602.8 8.95E-03 1.65E-03 1.82E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/9/01 598 1.72E-02 2.OOE-03 1.74E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/16/01 594 1.89E-02 2.13E-03 1.91 E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/23/01 599.2 1.60E-02 1.97E-03 1.80E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/30/01 598 1.52E-02 1.94E-03 1.81 E-03 SR 1134 AT INTSR 1011 -DIXIE PIPELINE 5/7/01 592.1 1.73E-02 2.05E-03 1.85E-03 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 5/14/01 593.2 1.71 E-02 1.97E-03 1.63E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 5/21/01 594.1 1.71 E-02 2.OOE-03 1.73E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 5/29/01 681.4 1.63E-02 1.a4E-03 1.64E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 6/4/01 494.1 1.33E-02 2.06E-03 2.04E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 6/11/01 597.2 1.50E-02 1.96E-03 1.89E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 6/18/01 590.2 1.34E-02 1.89E-03 1.86E-03 Page) of 13

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic meter Sample Point Sample Date Ouantitv Activity 2 Sigma Error LLD 1 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 6/25/01 592.2 1.75E-02 2.01 E-03 1.71 E-03 592.4 1.25E-02 1.81 E-03 1.78E-03 1 SR 1134 AT INTSR 1011 -DIXIE PIPELINE 7/2/01 7/9/01 589.3 1.11E-02 1.79E-03 1.88E-03 1 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 7/16/01 587 1.79E-02 2.10E-03 1.93E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 7/23/01 592.8 1.58E-02 1.98E-03 1.85E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 7/30/01 585.4 1.15E-02 1.83E-03 1.94E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 8/6/01 593.4 1.18E-02 1.83E-03 1.91 E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1 2.97E-03 8/13/01 389.9 1.81 E-02 2.81 E-03 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 8/21/01 673.8 1.92E-02 1.99E-03 1.72E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 8/27/01 507.2 2.20E-02 2.41 E-03 1.98E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 9/4/01 683.5 2.17E-02 2.01 E-03 1.54E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 9/10/01 521.7 1.66E-02 2.17E-03 2.04E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 9/17/01 608.8 1.80E-02 2.06E-03 1.86E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 10/1/01 571.9 1.19E-02 1.80E-03 1.76E-03 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 1 1.71 E-03 10/8/01 593.8 2.38E-02 2.26E-03 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 1 1.72E-03 10/15/01 577.7 1.36E-02 1.86E-03 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 590.7 1.53E-02 1.93E-03 1.75E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 10/22/01 10/29/01 360 1.14E-02 2.54E-03 2.98E-03 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 622.2 2.64E-02 2.34E-03 1.80E-03 SR 1134 AT INTSR 1011 -DIXIE PIPELINE 11/5/01 11/12/01 497.4 2.51 E-02 2.62E-03 2.22E-03 SR 1134 AT INTSR 1011 - DIXIE PIPELINE 11/19/01 515.1 2.43E-02 2.52E-03 2.11 E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 11/26/01 515.3 1.66E-02 2.20E-03 2.09E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 12/3/01 512.2 1.65E-02 2.18E-03 2.03E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 12/10/01 506.8 2.42E-02 2.50E-03 1.98E-03 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 12/17/01 519.3 1.11E-02 1.97E-03 2.17E-03 SR 1134 AT INT SR 1011 ° DIXIE PIPELINE Page 2 of 13

HNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 1 SR 1134 AT INT SR 1011 -DIXIE PIPELINE 12/23/01 435.9 1.61 E-02 2.46E-03 2.53E-03 1 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 12/31/01 595.8 2.24E-02 2.25E-03 1.85E-03 2 SR 1134 1/1/01 700 1.81 E-02 1.81 E-03 1.48E-03 2 SR 1134 1/8/01 604.8 1.60E-02 1.98E-03 1.88E-03 2 SR 1134 1/15/01 626.7 1.47E-02 1.87E-03 1.77E-03 2 SR 1134 1/22/01 582.9 1.63E-02 2.02E-03 1.88E-03 2 SR 1134 1/29/01 607.7 1.38E-02 1.88E-03 1.86E-03 2 SR 1134 2/5/01 606.5 1.50E-02 1.90E-03 1.76E-03 2 SR 1134 2/12/01 599.3 1.43E-02 1.88E-03 1.78E-03 2 SR 11,34 2/19/01 602 1.28E-02 1.85E-03 1.88E-03 2 SR 1134 2/26/01 620.8 1.42E-02 1.85E-03 1.78E-03 2 SR 1134 3/5/01 601.7 1.47E-02 1.93E-03 1.84E-03 2 SR 1134 3/12/01 583.4 1.11E-02 1.76E-03 1.79E-03 2 SR 1134 3/19/01 619.6 1.04E-02 1.72E-03 1.86E-03 2 SR 1134 3/26/01 602 1.07E-02 1.75E-03 1.87E-03 2 SR 1134 4/2/01 596.8 9.29E-03 1.68E-03 1.84E-03 2 SR 1134 4/9/01 571.3 1.67E-02 2.04E-03 1.82E-03 2 SR 1134 4/16/01 588 1.76E-02 2.09E-03 1.93E-03 2 SR 1134 4/23/01 595.9 1.66E-02 2.OOE-03 1.81 E-03 2 SR 1134 4/30/01 592 1.67E-02 2.02E-03 1.83E-03 2 SR 1134 5/7/01 588.1 1.89E-02 2.12E-03 1.87E-03 2 SR 1134 5/14/01 588.3 1.55E-02 1.91 E-03 1.64E-03 2 SR 1134 5/21/01 590.2 1.74E-02 2.02E-03 1.74E-03 2 SR 1134 5/29/01 675.2 1.50E-02 1.80E-03 1.65E-03 2 SR 1134 6/4/01 765.7 1.24E-02 1.50E-03 1.31 E-03 Page 3 of 13

HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 2 SR 1134 6/11/01 495.8 1.14E-02 2.05E-03 2.27E-03 2 SR 1134 6/18/01 489.7 1.38E-02 2.16E-03 2.24E-03 2 SR 1134 6/25/01 508.7 1.45E-02 2.08E-03 1.99E-03 2 SR 1134 7/2/01 853.2 1.12E-02 1.37E-03 1.23E-03 2 SR 1134 7/9/01 882.6 1.07E-02 1.34E-03 1.26E-03 2 SR 1134 7/16/01 865.4 1.74E-02 1.63E-03 1.31 E-03 2 SR 1134 7/23/01 876.2 1.52E-02 1.52E-03 1.25E-03 2 SR 1134 7/30/01 820.4 8.66E-03 1.33E-03 1.38E-03 2 SR 1134 8/6/01 890 1.13E-02 1.37E-03 1.27E-03 2 SR 1134 8/21/01 847.3 1.78E-02 1.67E-03 1.37E-03 2 SR 1134 8/27/01 674.7 1.93E-02 1.92E-03 1.49E-03 2 SR 1134 9/4/01 908.6 1.93E-02 1.62E-03 1.16E-03 2 SR 1134 9/10/01 681.4 1.58E-02 1.80E-03 1.56E-03 2 SR 1134 9/17/01 793.8 1.57E-02 1.65E-03 1.43E-03 2 SR 1134 9/24/01 793.8 2.30E-02 1.87E-03 1.28E-03 2 SR 1134 10/1/01 813.8 1.16E-02 1.41 E-03 1.24E-03 2 SR 1134 10/8/01 799.9 2.12E-02 1.80E-03 1.27E-03 2 SR 1134 10/15/01 796.8 1.09E-02 1.39E-03 1.25E-03 2 SR 1134 10/22/01 809.3 1.50E-02 1.57E-03 1.28E-03 2 SR 1134 10/29/01 816.1 1.05E-02 1.39E-03 1.31 E-03 2 SR 1134 11/5/01 814.6 2.05E-02 1.79E-03 1.38E-03 2 SR 1134 11/12/01 802.5 2.17E-02 1.85E-03 1.37E-03 2 SR 1134 11/19/01 810.1 2.13E-02 1.82E-03 1.34E-03 2 SR 1134 11/26/01 810.4 1.36E-02 1.53E-03 1.33E-03 2 SR 1134 12/3/01 802.6 1.58E-02 1.61 E-03 1.30E-03 Page 4 of 13

HNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD SR 1134 12/10/01 795.4 2.18E-02 1.83E-03 1.26E-03 SR 1134 12/17/01 817 9.89E-03 1.38E-03 1.38E-03 SR 1134 12/23/01 690 1.72E-02 1.86E-03 1.60E-03 SR 1134 12/31/01 941.2 2.04E-02 1.64E-03 1.17E-03 NEW HILL NEAR 1ST BAPTIST CH 1/1/01 592.2 1.60E-02 1.93E-03 1.75E-03 NEW HILL NEAR 1ST BAPTIST CH 1/8/01 511.8 1.615E-02 2.23E-03 2.22E-03 NEW HILL NEAR 1ST BAPTIST CH 1/15/01 513.7 1.28E-02 2.05E-03 2.17E-03 NEW HILL NEAR 1ST BAPTIST CH 1/22/01 511.6 1.98E-02 2.36E-03 2.14E-03 NEW HILL NEAR 1ST BAPTIST CH 1/29/01 514.6 1.81 E-02 2.30E-03 2.20E-03 NEW HILL NEAR 1ST BAPTIST CH 2/5/01 514.9 1.54E-02 2.14E-03 2.08E-03 NEW HILL NEAR 1ST BAPTIST CH 2/12/01 507.6 1.28E-02 2.04E-03 2.11 E-03 NEW HILL NEAR 1ST BAPTIST CH 2/19/01 508.2 1.01 E-02 1.95E-03 2.22E-03 NEW HILL NEAR 1ST BAPTIST CH 2/26/01 510 1.95E-02 2.35E-03 2.17E-03 NEW HILL NEAR 1ST BAPTIST CH 3/5/01 506.1 1.64E-02 2.24E-03 2.19E-03 NEW HILL NEAR 1ST BAPTIST CH 3/12/01 509.8 1.38E-02 2.07E-03 2.05E-03 NEW HILL NEAR 1ST BAPTIST CH 3/19/01 505.2 1.02E-02 1.99E-03 2.28E-03 NEW HILL NEAR 1ST BAPTIST CH 3/26/01 508 1.37E-02 2.13E-03 2.22E-03 NEW HILL NEAR 1ST BAPTIST CH 4/2/01 506.1 1.01 E-02 1.93E-03 2.17E-03 NEW HILL NEAR 1ST BAPTIST CH 4/9/01 504 1.60E-02 2.18E-03 2.06E-03 NEW HILL NEAR 1ST BAPTIST CH 4/16/01 501.1 1.91 E-02 2.39E-03 2.26E-03 NEW HILL NEAR 1ST BAPTIST CH 4/23/01 505 2.03E-02 2.39E-03 2.13E-03 NT NEW HILL NEAR 1ST BAPTIST CH 4/30/01 502 1.85E-02 2.;33E-03 2.16E-03 NEW HILL NEAR 1ST BAPTIST CH 5/7101 500.1 2.26E-02 2.51 E-03 2.19E-03 NEW HILL NEAR 1ST BAPTIST CH 5/1 4/01 499.2 1.91 E-02 2.28E-03 1.93E-03 NEW HILL NEAR 1ST BAPTIST OH 5/21/01 500.3 1.82E-02 2.28E-03 2.05E-03 Page5 of 13

HNP RadiologicalEnvironmental Monitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD NEW HILL NEAR 1ST BAPTIST CH 5/29/01 571.8 1.65E-02 2.08E-03 1.95E-03 NEW HILL NEAR 1ST BAPTIST CH 6/4/01 410.2 1.57E-02 2.46E-03 2.45E-03 NEW HILL NEAR 1ST BAPTIST CH 6/11/01 501.2 1.49E-02 2.20E-03 2.25E-03 NEW HILL NEAR 1ST BAPTIST CH 6/18/01 496.7 1.24E-02 2.08E-03 2.21 E-03 NEW HILL NEAR 1ST BAPTIST CH 6/25/01 495.8 1.07E-02 1.92E-03 2.04E-03 NEW HILL NEAR 1ST BAPTIST CH 7/2/01 498.3 1.35E-02 2.09E-03 2.11E-03 NEW HILL NEAR 1ST BAPTIST CH 7/9/01 493.3 1.05E-02 2.OOE-03 2.25E-03 NEW HILL NEAR 1ST BAPTIST CH 7/16/01 493 1.85E-02 2.39E-03 2.30E-03 NEW HILL NEAR 1ST BAPTIST CH 7/23/01 497.5 1.68E-02 2.28E-03 2.21 E-03 NEW HILL NEAR 1ST BAPTIST CH 7/30/01 490.3 9.62E-03 1.98E-03 2.31 E-03 NEW HILL NEAR 1ST BAPTIST CH 8/6/01 497.7 1.25E-02 2.10E-03 2.28E-03 NEW HILL NEAR 1ST BAPTIST CH 8/13/01 496.1 1.82E-02 2.39E-03 2.33E-03 NEW HILL NEAR 1ST BAPTIST CH 8/21/01 564.6 1.89E-02 2.22E-03 2.05E-03 NEW HILL NEAR 1ST BAPTIST CH 8/27/01 422.9 2.11 E-02 2.66E-03 2.38E-03 NEW HILL NEAR 1ST BAPTIST CH 9/4/01 572.9 2.OOE-02 2.18E-03 1.84E-03 NEW HILL NEAR 1ST BAPTIST CH 9/17/01 500 2.03E-02 2.44E-03 2.27E-03 NEW HILL NEAR 1ST BAPTIST CH 9/24/01 497.5 2.85E-02 2.70E-03 2.04E-03 NEW HILL NEAR 1ST BAPTIST CH 10/1/01 504.3 1.46E-02 2.09E-03 1.99E-03 NEW HILL NEAR 1ST BAPTIST CH 10/8/01 496.5 2.60E-02 2.61 E-03 2.04E-03 NEW HILL NEAR 1ST BAPTIST CH 10/15/01 497.1 1.39E-02 2.07E-03 2.OOE-03 NEW HILL NEAR 1ST BAPTIST CH 10/22/01 501.6 1.74E-02 2.25E-03 2.06E-03 NEW HILL NEAR 1-& BAPTIST CH 10/29/01 504.5 1.47E-02 2.14E-03 2.12E-03 NEW HILL NEAR 1ST BAPTIST CH 11/5/01 508.4 2.62E-02 2.64E-03 2.21E-03 NEW HILL NEAR 1ST BAPTIST CH 11/12/01 493.3 2.83E-02 2.76E-03 2.24E-03 NEW HILL NEAR 1ST BAPTIST CH 11/19/01 502.5 2.87E-02 2.73E-03 2.16E-03 Page 6 of 13

,.1.

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic meter Sample Point Sample Sf-Date Quantity Activity 2 Sigma "r

Error LLD NEW HILL NEAR 1ST BAPTIST CH 11/26/01 501.2 1.67E-02 2.25E-03 2.15E-03 NEW HILL NEAR 1ST BAPTIST CH 12/3/01 498.7 2.12E-02 2.42E-03 2.08E-03 NEW HILL NEAR 1ST BAPTIST CH 12/10/01 493.9 2.55E-02 2.59E-03 2.04E-03 NEW HILL NEAR 1ST BAPTIST CH 12/17/01 503.6 1.10E-02 2.01 E-03 2.24E-03 NEW HILL NEAR 1ST BAPTIST CH 12/23/01 425.2 1.64E-02 2.52E-03 2.59E-03 2.38E-03 NEW HILL NEAR 1ST BAPTIST CH 12/31/01 580.4 2.50E-02 1.90E-03 PITTSBORO - CONTROL 1/1/01 690.9 1.96E-02 1.88E-03 1.50E-03 PITTSBORO - CONTROL 1/8/01 595.4 1.38E-02 1.91 E-03 1.91 E-03 PITTSBORO - CONTROL 1/15/01 595.7 1.35E-02 1.88E-03 1.87E-03 PITTSBORO - CONTROL 1/22/01 596.7 2.02E-02 2.15E-03 1.83E-03 PITTSBORO - CONTROL 1/29/01 598.6 1.70E-02 2.04E-03 1.89E-03 PITTSBORO - CONTROL 2/5/01 601.5 1.98E-02 2.11E-03 1.78E-03 PITTSBORO - CONTROL 2/12/01 589.9 1.51 E-02 1.94E-03 1.81 E-03 PITTSBORO - CONTROL 2/19/01 589 1.14E-02 1.81 E-03 1.92E-03 PITTSBORO - CONTROL 2/26/01 592.2 1.84E-02 2.09E-03 1.87E-03 PITTSBORO - CONTROL 3/5/01 590.4 1.48E-02 1.95E-03 1.88E-03 PITTSBORO - CONTROL 3/12/01 595.2 1.30E-02 1.83E-03 1.76E-03 PITTSBORO - CONTROL 3/19/01 590 9.91 E-03 1.76E-03 1.95E-03 PITTSBORO - CONTROL 3/26/01 592 1.39E-02 1.92E-03 1.90E-03 PITTSBORO - CONTROL 4/2/01 588.2 8.79E-03 1.67E-03 1.87E-03 PITTSBORO - CONTROL 4/9/01 586.3 1.92E-02 2.11 E-03 1.77E-03 PITTSBORO - CONTROL 4/16/01 585.1 1.92E-02 2..16E-03 1.94E-03 PITTSBORO - CONTROL 4/23/01 588.1 1.89E-02 2.11 E-03 1.83E-03 PITTSBORO - CONTROL 4/30/01 587.2 1.95E-02 2.14E-03 1.85E-03 PITTSBORO - CONTROL 5/7/01 584.3 1.94E-02 2.15E-03 1.88E-03 Page 7 of 13

J HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD PITTSBORO - CONTROL 5/14/01 583.1 1.84E-02 2.04E-03 1.65E-03 PITTSBORO - CONTROL 5/21/01 587.3 1.74E-02 2.03E-03 1.75E-03 PITTSBORO - CONTROL 5/29/01 659.8 1.65E-02 1.89E-03 1.69E-03 PITTSBORO - CONTROL 6/4/01 507.7 1.22E-02 1.96E-03 1.98E-03 PITTSBORO - CONTROL 6/11/01 597.1 1.53E-02 1.97E-03 1.89E-03 PITTSBORO - CONTROL 6/18/01 579.6 1.1 7E-02 1.83E-03 1.89E-03 PITTSBORO - CONTROL 6/25/01 580.7 1.83E-02 2.07E-03 1.74E-03 PITTSBORO - CONTROL 7/2/01 585.2 1.40E-02 1.90E-03 1.80E-03 PITTSBORO - CONTROL 7/9/01 586.9 1.15E-02 1.81 E-03 1.89E-03 PITTSBORO - CONTROL 7/16/01 712.2 1.79E-02 1.86E-03 1.59E-03 PITTSBORO - CONTROL 7/23/01 775.6 1.61 E-02 1.68E-03 1.41 E-03 PITTSBORO - CONTROL 7/30/01 762.9 8.42E-03 1.39E-03 1.49E-03 PITTSBORO - CONTROL 8/6/01 771.4 1.17E-02 1.52E-03 1.47E-03 PITTSBORO - CONTROL 8/13/01 585.6 1.75E-02 2.11 E-03 1.98E-03 PITTSBORO - CONTROL 8/21/01 848.6 1.79E-02 1.67E-03 1.36E-03 PITTSBORO - CONTROL 8/27/01 643.3 1.79E-02 1.92E-03 1.56E-03 PITTSBORO - CONTROL 9/4/01 873.2 1.75E-02 "1.59E-03 1.21E-03 PITTSBORO - CONTROL 9/10/01 659.2 1.68E-02 1.88E-03 1.62E-03 PITTSBORO - CONTROL 9/17/01 765.8 1.70E-02 1.74E-03 1.48E-03 PITTSBORO - CONTROL 9/24/01 769.5 2.34E-02 1.92E-03 1.32E-03 PITTSBORO - CONTROL 10/1/01 787.4 1.23E-02 1.47E-03 1.28E-03 PITTSBORO - CONWROL 10/8/01 773.5 4.80E-03 1.12E-03 1.31 E-03 PITTSBORO - CONTROL 10/15/01 767.2 1.37E-02 1.55E-03 1.29E-03 PITTSBORO - CONTROL 10/22/01 779.7 1.46E-02 1.59E-03 1.32E-03 PITTSBORO - CONTROL 10/29/01 787.6 1.34E-02 1.55E-03 1.36E-03 Page 8 of 13

HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 5 PITTSBORO - CONTROL 11/5/01 786 2.22E-02 1.89E-03 1.43E-03 5 PITTSBORO - CONTROL 11/12/01 771.1 2.31 E-02 1.94E-03 1.43E-03 5 PITTSBORO - CONTROL 11/19/01 778.6 2.36E-02 1.94E-03 1.39E-03 5 PITTSBORO - CONTROL 11/26/01 776.2 1.45E-02 1.61 E-03 1.39E-03 5 PITTSBORO - CONTROL 12/3/01 768.9 1.59E-02 1.66E-03 1.35E-03 5 PITTSBORO - CONTROL 12/10/01 768.1 2.13E-02 1.85E-03 1.31 E-03 5 PITTSBORO - CONTROL 12/17/01 799.6 1.08E-02 1.45E-03 1.41 E-03 5 PITTSBORO - CONTROL 12/23/01 659.6 1.65E-02 1.88E-03 1.67E-03 5 PITTSBORO - CONTROL 12/31/01 909.8 2.10E-02 1.69E-03 1.21 E-03 26 SPILLWAY ON MAIN RES 1/1/01 655.7 1.77E-02 1.87E-03 1.58E-03 26 SPILLWAY ON MAIN RES 1/8/01 568.3 1.48E-02 2.02E-03 2.00E-03 26 SPILLWAY ON MAIN RES 1/15/01 568 1.40E-02 1.97E-03 1.96E-03 26 SPILLWAY ON MAIN RES 1/22/01 563.5 1.76E-02 2.12E-03 1.94E-03 26 SPILLWAY ON MAIN RES 1/29/01 567.5 2.02E-02 2.24E-03 1.99E-03 26 SPILLWAY ON MAIN RES 2/5/01 570.4 1.97E-02 2.17E-03 1.87E-03 26 SPILLWAY ON MAIN RES 2/12/01 556.7 1.53E-02 2.02E-03 1.92E-03 26 SPILLWAY ON MAIN RES 2/19/01 563.6 1.23E-02 1.91 E-03 2.01 E-03 26 SPILLWAY ON MAIN RES 2/26/01 560.8 1.94E-02 2.21 E-03 1.97E-03 26 SPILLWAY ON MAIN RES 3/5/01 562.6 1.38E-02 1.97E-03 1.97E-03 26 SPILLWAY ON MAIN RES 3/12/01 564.8 1.28E-02 1.88E-03 1.85E-03 26 SPILLWAY ON MAIN RES 3/19/01 561.7 9.07E-03 1.78E-03 2.05E-03 26 SPILLWAY ON MAIN RES 3/26/01 563.8 1.46E-02 2.02E-03 2.OOE-03 26 SPILLWAY ON MAIN RES 4/2/01 488.2 7.35E-03 1.84E-03 2.25E-03 26 SPILLWAY ON MAIN RES 4/9/01 550 1.95E-02 2.21E-03 1.89E-03 26 SPILLWAY ON MAIN RES 4/16/01 552.9 1.63E-02 2.12E-03 2.05E-03 Page 9 of 13

HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity

- ---------I Activity

- - - - - , - -1 2 Sigma Error LLD 26 SPILLWAY ON MAIN RES 4/23/01 552.9 1.98E-02 2.24E-03 1.95E-03 26 SPILLWAY ON MAIN RES 4/30/01 558.2 1.95E-02 2.21 E-03 1.94E-03 26 SPILLWAY ON MAIN RES 5/7/01 551.2 2.04E-02 2.27E-03 1.99E-03 26 SPILLWAY ON MAIN RES 5/14/01 548.2 1.82E-02 2.12E-03 1.76E-03 26 SPILLWAY ON MAIN RES 5/21/01 552.1 1.87E-02 2.16E-03 1.86E-03 26 SPILLWAY ON MAIN RES 5/29/01 636.3 1.81E-02 2.OOE-03 1.75E-03 26 SPILLWAY ON MAIN RES 6/4/01 454.9 1.35E-02 2.18E-03 2.21 E-03 26 SPILLWAY ON MAIN RES 6/11/01 555.2 1.69E-02 2.14E-03 2.03E-03 26 SPILLWAY ON MAIN RES 6/18/01 162.5 1.88E-02 5.33E-03 6.75E-03 26 SPILLWAY ON MAIN RES 6/25/01 541 1.37E-02 1.96E-03 1.87E-03 26 SPILLWAY ON MAIN RES 7/2/01 547.3 1.49E-02 2.02E-03 1.92E-03 26 SPILLWAY ON MAIN RES 7/9/01 548.6 1.27E-02 1.96E-03 2.02E-03 26 SPILLWAY ON MAIN RES 7/16/01 536.6 2.15E-02 2.38E-03 2.11E-03 26 SPILLWAY ON MAIN RES 7/23/01 536.9 1.72E-02 2.18E-03 2.04E-03 26 SPILLWAY ON MAIN RES 7/30/01 541.2 9.09E-03 1.82E-03 2.09E-03 26 SPILLWAY ON MAIN RES 8/6/01 545.2 1.31 E-02 2.OOE-03 2.08E-03 26 SPILLWAY ON MAIN RES 8/13/01 326.7 1.94E-02 3.25E-03 3.54E-03 26 SPILLWAY ON MAIN RES 8/21/01 591.6 2.15E-02 2.25E-03 1.96E-03 26 SPILLWAY ON MAIN RES 8/27/01 467.3 2.38E-02 2.61 E-03 2.15E-03 26 SPILLWAY ON MAIN RES 9/4/01 628.1 2.23E-02 2.14E-03 1.68E-03 26 SPILLWAY ON MAIN RES 9/17/01 547 1.78E-02 2.20E-03 2.07E-03 26 SPILLWAY ON MAIIA RES 9/24/01 544.4 2.70E-02 2.50E-03 1.86E-03 26 SPILLWAY ON MAIN RES 10/1/01 564.8 1.36E-02 1.89E-03 1.78E-03 26 SPILLWAY ON MAIN RES 10/8/01 541 2.54E-02 2.45E-03 1.87E-03 26 SPILLWAY ON MAIN RES 10/15/01 548 1.42E-02 1.95E-03 1.81 E-03 Page 10 of 13

HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantity: cubic meters Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 26 SPILLWAY ON MAIN RES 10/22/01 550.8 1.62E-02 2.06E-03 1.88E-03 26 SPILLWAY ON MAIN RES 10/29/01 559.2 1.27E-02 1.91 E-03 1.92E-03 26 SPILLWAY ON MAIN RES 11/5/01 491.1 2.49E-02 2.65E-03 2.28E-03 26 SPILLWAY ON MAIN RES 11/12/01 557.8 2.40E-02 2.40E-03 1.98E-03 26 SPILLWAY ON MAIN RES 11/19/01 553.4 2.34E-02 2.38E-03 1.96E-03 26 SPILLWAY ON MAIN RES 11/26/01 553.8 1.23E-02 1.91 E-03 1.95E-03 26 SPILLWAY ON MAIN RES 12/3/01 547.8 1.65E-02 2.09E-03 1.90E-03 26 SPILLWAY ON MAIN RES 12/10/01 548.4 2.53E-02 2.42E-03 1.83E-03 26 SPILLWAY ON MAIN RES 12/17/01 570.1 1.10E-02 1.84E-03 1.98E-03 26 SPILLWAY ON MAIN RES 12/23/01 382.8 1.99E-02 2.88E-03 2.88E-03 26 SPILLWAY ON MAIN RES 12/31/01 650.2 1.68E-02 1.91 E-03 1.70E-03 47 SSW SECTOR 3.4 MI FROM SITE 1/1/01 671.6 1.87E-02 1.88E-03 1.55E-03 47 SSW SECTOR 3.4 MI FROM SITE 1/8/01 582.6 1.34E-02 1.92E-03 1.95E-03 47 SSW SECTOR 3.4 MI FROM SITE 1/15/01 578.9 1.70E-02 2.07E-03 1.92E-03 47 SSW SECTOR 3.4 MI FROM SITE 1/22/01 576.6 1.94E-02 2.16E-03 1.90E-03 47 SSW SECTOR 3.4 MI FROM SITE 1/29/01 580.6 1.91 E-02 2.16E-03 1.95E-03 47 SSW SECTOR 3.4 MI FROM SITE 2/5/01 580.2 2.02E-02 2.17E-03 1.84E-03 47 SSW SECTOR 3.4 MI FROM SITE 2/12/01 572.8 1.70E-02 2.06E-03 1.87E-03 47 SSW SECTOR 3.4 MI FROM SITE 2/19/01 578.7 9.03E-03 1.72E-03 1.95E-03 47 SSW SECTOR 3.4 MI FROM SITE 2/26/01 575.3 1.71 E-02 2.08E-03 1.92E-03 47 SSW SECTOR 3.4 MI FROM SITE 3/5/01 678.2 1.36E-02 1.73E-03 1.64E-03 47 SSW SECTOR 3.4 MI FROM SITE 3/12/01 682.6 1.38E-02 1.70E-03 1.53E-03 47 SSW SECTOR 3.4 MI FROM SITE 3/19/01 679.2 9.61 E-03 1.57E-03 1.70E-03 47 SSW SECTOR 3.4 MI FROM SITE 3/26/01 680.3 1.48E-02 1.79E-03 1.66E-03 47 SSW SECTOR 3.4 MI FROM SITE 4/2/01 676.3 9.54E-03 1.54E-03 1.62E-03 Page 11 of 13

HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type." Air Particulate Analysis: Beta Quantity: cubic meters Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 47 SSW SECTOR 3.4 MI FROM SITE 4/9/01 671.4 1.77E-02 1.88E-03 1.55E-03 47 SSW SECTOR 3.4 MI FROM SITE 4/16/01 669.3 1.55E-02 1.84E-03 1.69E-03 47 SSW SECTOR 3.4 MI FROM SITE 4/23/01 671.1 2.OOE-02 1.99E-03 1.61 E-03 47 SSW SECTOR 3.4 MI FROM SITE 4/30/01 673.2 1.86E-02 1.93E-03 1.61 E-03 47 SSW SECTOR 3.4 MI FROM SITE 5/7/01 667.3 1.87E-02 1.95E-03 1.64E-03 47 SSW SECTOR 3.4 MI FROM SITE 5/14/01 664.4 1.47E-02 1.73E-03 1.45E-03 47 SSW SECTOR 3.4 MI FROM SITE 5/21/01 668.2 1.73E-02 1.86E-03 1.54E-03 47 SSW SECTOR 3.4 MI FROM SITE 5/29/01 769.4 1.47E-02 1.64E-03 1.45E-03 47 SSW SECTOR 3.4 MI FROM SITE 6/4/01 548.8 1.34E-02 1.92E-03 1.83E-03 47 SSW SECTOR 3.4 MI FROM SITE 6/11/01 672.5 1.23E-02 1.69E-03 1.68E-03 47 SSW SECTOR 3.4 MI FROM SITE 6/18/01 659.1 1.39E-02 1.77E-03 1.66E-03 47 SSW SECTOR 3.4 MI FROM SITE 6/25/01 658.8 1.43E-02 1.75E-03 1.54E-03 47 SSW SECTOR 3.4 MI FROM SITE 7/2/01 661.7 1.24E-02 1.68E-03 1.59E-03 47 SSW SECTOR 3.4 MI FROM SITE 7/9/01 663.7 1.19E-02 1.68E-03 1.67E-03 47 SSW SECTOR 3.4 MI FROM SITE 7/16/01 655.2 1.74E-02 1.94E-03 1.73E-03 47 SSW SECTOR 3.4 MI FROM SITE 7/23/01 648 1.58E-02 1.87E-03 1.69E-03 47 SSW SECTOR 3.4 MI FROM SITE 7/30/01 657 8.56E-03 1.55E-03 1.73E-03 47 SSW SECTOR 3.4 MI FROM SITE 8/6/01 661.9 1.19E-02 1.70E-03 1.71 E-03 47 SSW SECTOR 3.4 MI FROM SITE 8/13/01 506.2 1.66E-02 2.28E-03 2.29E-03 47 SSW SECTOR 3.4 MI FROM SITE 8/21/01 711.5 1.44E-02 1.73E-03 1.63E-03 47 SSW SECTOR 3.4 MI FROM SITE 8/27/01 561 2.04E-02 2.20E-03 1.79E-03 47 SSW SECTOR 3.4 kI FROM SITE 9/4/01 760.1 1.98E-02 1.82E-03 1.38E-03 47 SSW SECTOR 3.4 MI FROM SITE 9/10/01 564.3 1.76E-02 2.11E-03 I 1.89E-03 47 SSW SECTOR 3.4 MI FROM SITE 9/17/01 663.6 1.49E-02 1.82E-03 1.71 E-03 47 SSW SECTOR 3.4 MI FROM SITE 9/24/01 661.7 2.45E-02 2.14E-03 1.53E-03 Page 12 of 13

,S.

HNP RadiologicalEnvironmental Monitoring Analysis Report Media Type: Air Particulate Analysis: Beta Quantit,: cubic meters Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 47 SSW SECTOR 3.4 MI FROM SITE 10/1/01 684.8 1.25E-02 1.62E-03 1.47E-03 47 SSW SECTOR 3.4 MI FROM SITE 10/8/01 657.1 2.52E-02 2.17E-03 1.54E-03 47 SSW SECTOR 3.4 MI FROM SITE 10/15/01 670.6 1.23E-02 1.63E-03 1.48E-03 47 SSW SECTOR 3.4 MI FROM SITE 10/22/01 666 1.54E-02 1.79E-03 1.55E-03 47 SSW SECTOR 3.4 MI FROM SITE 10/29/01 678.5 1.15E-02 1.62E-03 1.58E-03 47 SSW SECTOR 3.4 MI FROM SITE 11/5/01 671.1 2.48E-02 2.18E-03 1.67E-03 47 SSW SECTOR 3.4 MI FROM SITE 11/12/01 678 2.29E-02 2.09E-03 1.63E-03 47 SSW SECTOR 3.4 MI FROM SITE 11/19/01 673.9 2.40E-02 2.13E-03 1.613E-03 47 SSW SECTOR 3.4 MI FROM SITE 11/26/01 676 12.40E-02 1.74E-03 1.59E-03 47 SSW SECTOR 3.4 MI FROM SITE 12/3/01 669.4 1.41E-02 1.73E-03 1.55E-03 47 SSW SECTOR 3.4 MI FROM SITE 12/10/01 660.9 2.28E-02 2.08E-03 1.52E-03 47 SSW SECTOR 3.4 MI FROM SITE 12/17/01 691.5 1.20E-02 1.65E-03 1.63E-03 47 SSW SECTOR 3.4 MI FROM SITE 12/23/01 557.5 1.97E-02 2.23E-03 1.98E-03 47 SSW SECTOR 3.4 MI FROM SITE 12/31/01 781.4 2.24E-02 1.90E-03 1.41 E-03 Page 13 of 13

HNP RadiologicalEnvironmentalMontoring Analysis Report Media Type: Drinking Water Quantity: Liters Analysis: Beta Concentration (Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 38 CAPE FEAR PLANT INTAKE - CONTROL 1/31/01 1.00 4.49E+00 1.03E+00 1.13E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 2/28/01 1.00 4.75E+00 1.03E+00 1.09E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 3/31/01 1.00 3.42E+00 9.26E-01 1.08E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 4/30/01 1.00 4.91 E+00 9.97E-01 1.03E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 5/31/01 1.00 3.69E+00 9.74E-01 1.15E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 6/30/01 1.00 5.17E+00 1.01E+00 1.01E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 7/31/01 1.00 5.47E+00 1.06E+00 1.09E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 8/31/01 1.00 5.44E+00 1.13E+00 1.25E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 9/30/01 1.00 7.28E+00 1.13E+00 9.65E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 10/31/01 1.00 5.81 E+00 1.1OE+00 1.09E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 11/30/01 1.00 6.85E+00 1.15E+00 1.10E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 12/31/01 1.00 7.45E+00 1.19E+00 1.07E+00 40 LILLINGTON - CAPE FEAR RIVER 1/31/01 1.00 6.27E+00 1.12E+00 1.11E+00 40 LILLINGTON - CAPE FEAR RIVER 2/28/01 1.00 4.27E+00 9.73E-01 1.05E+00 40 LILLINGTON - CAPE FEAR RIVER 3/31/01 1.00 3.69E+00 9.21 E-01 1.05E+00 40 LILLINGTON - CAPE FEAR RIVER 4/30/01 1.00 4.56E+00 9.35E-01 9.67E-01 40 LILLINGTON - CAPE FEAR RIVER 5/31/01 1.00 4.15E+00 9.96E-01 1.13E+00 40 LILLINGTON - CAPE FEAR RIVER 6/30/01 1.00 4.17E+00 9.25E-01 9.80E-01 40 LILLINGTON - CAPE FEAR RIVER 7/31/01 1.00 4.86E+00 9.98E-01 1.06E+00 40 LILLINGTON - CAPE FEAR RIVER 8/31/01 1.00 3.81 E+00 9.78E-01 1.16E+00 40 LILLINGTON - CAPE FEAR RIVER 9/30/01 1.00 5.44E+00 1.OOE+00 9.38E-01 40 LILLINGTON - CAPE FEAR RIVER 10/31/01 1.00 6.37E+00 1.11E+00 1.05E+00 40 LILLINGTON - CA1PE FEAR RIVER 11/30/01 1.00 6.64E+00 1.13E+00 1.08E+00 40 LILLINGTON - CAPE FEAR RIVER 12/31/01 1.00 7.14E+00 1.16E+00 1.06E+00 51 WATER TREATMENT BLDG AT HARRIS PLANT 1/31/01 1.00 3.43E+00 8.88E-01 1.02E+00 51 WATER TREATMENT BLDG AT HARRIS PLANT 2/28/01 1.00 4.16E+00 9.21E-01 9.83E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 3/31/01 1.00 4.1 OE+00 9.49E-01 1.05E+00 Page I of 2

HNP RadiologicalEnvironmental Montoring Analysis Report Media Type: Drinking Water Quantity: Liters Analysis: Beta Concentration(Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 51 WATER TREATMENT BLDG AT HARRIS PLANT 4/30/01 1.00 3.54E+00 8.80E-01 9.83E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 5/31/01 1.00 2.74E+00 8.73E-01 1.09E+00 51 WATER TREATMENT BLDG AT HARRIS PLANT 6/30/01 1.00 3.53E+00 8.80E-01 9.76E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 7/31/01 1.00 3.22E+00 9.14E-01 1.09E+00 51 WATER TREATMENT BLDG AT HARRIS PLANT 8/31/01 1.00 2.26E+00 7.72E-01 9.94E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 9/30/01 1.00 2.84E+00 8.01 E-01 9.04E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 10/31/01 1.00 3.27E+00 8.64E-01 9.80E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 11/30/01 1.00 2.83E+00 8.31 E-01 9.89E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 12/31/01 1.00 4.14E+00 9.19E-01 9.70E-01 Page2 of 2

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Surface Water Quantity: Liters Analysis: Beta Concentration(Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 26 SPILLWAY ON MAIN RES 1/31/01 1.00 2.91 E+00 8.02E-01 9.41 E-01 26 SPILLWAY ON MAIN RES 2/28/01 1.00 3.51 E+00 8.31E-01 9.11E-01 26 SPILLWAY ON MAIN RES 3/31/01 1.00 3.16E+00 8.28E-01 9.58E-01 26 SPILLWAY ON MAIN RES 4/30/01 1.00 4.13E+00 8.71E-01 9.11E-01 26 SPILLWAY ON MAIN RES 5/31/01 1.00 4.76E+00 9.30E-01 9.79E-01 26 SPILLWAY ON MAIN RES 6/30/01 1.00 3.08E+00 7.93E-01 8.91E-01 26 SPILLWAY ON MAIN RES 7/31/01 1.00 3.20E+00 8.27E-01 9.55E-01 26 SPILLWAY ON MAIN RES 8/31/01 1.00 2.46E+00 8.11E-01 1.03E+00 26 SPILLWAY ON MAIN RES 9/30/01 1.00 3.65E+00 7.87E-01 7.98E-01 26 SPILLWAY ON MAIN RES 10/31/01 1.00 3.17E+00 7.99E-01 8.91 E-01 26 SPILLWAY ON MAIN RES 11/30/01 1.00 2.10E+00 7.30E-01 9.12E-01 26 SPILLWAY ON MAIN RES 12/31/01 1.00 2.69E+00 7.21E-01 8.19E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 1/31/01 1.00 4.49E+00 1.03E+00 1.13E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 2/28/01 1.00 4.75E+00 1.03E+00 1.09E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 3/31/01 1.00 3.42E+00 9.26E-01 1.08E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 4/30/01 1.00 4.91E+00 9.97E-01 1.03E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 5/31/01 1.00 3.69E+00 9.74E-01 1.15E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 6/30/01 1.00 5.17E+00 1.01 E+00 1.01E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 7/31/01 1.00 5.47E+00 1.06E+00 1.09E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 8/31/01 1.00 5.44E+00 1.13E+00 1.25E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 9/30/01 1.00 7.28E+00 1.13E+00 9.65E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 10/31/01 1.00 5.81E+00 1.1OE+00 1.09E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 11/30/01 1.00 6.85E+00 1.15E+00 1.10E+00 38 CAPE FEAR PLANT INTAKE - CONTROL 12/31/01 1.00 7.45E+00 1.19E+00 i 1.07E+00 40 LILLINGTON -CAPE FEAR RIVER 1/31/01 1.00 6.27E+00 1.12E+00 1.11E+00 40 LILLINGTON - CAPE FEAR RIVER 2/28/01 1.00 4.27E+00 9.73E-01 1.05E+00 Page I of 2

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Surface Water Quantity: Liters Analysis: Beta Concentration(Activity): pCi/Lier Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 40 LILLINGTON - CAPE FEAR RIVER 3/31/01 1.00 3.69E+00 9.21 E-01 1.05E+00 40 LILLINGTON - CAPE FEAR RIVER 4/30/01 1.00 4.56E+00 9.35E-01 9.67E-01 40 LILLINGTON - CAPE FEAR RIVER 5/31/01 1.00 4.15E+00 9.96E-01 1.13E+00 40 LILLINGTON - CAPE FEAR RIVER 6/30/01 1.00 4.17E+00 9.25E-01 9.80E-01 40 LILLINGTON - CAPE FEAR RIVER 7/31/01 1.00 4.86E+00 9.98E-01 1.06E+00 40 LILLINGTON - CAPE FEAR RIVER 8/31/01 1.00 3.81 E+00 9.78E-01 1.16E+00 40 LILLINGTON - CAPE FEAR RIVER 9/30/01 1.00 5.44E+00 1.OOE+00 9.38E-01 40 LILLINGTON -CAPE FEAR RIVER 10/31/01 1.00 6.37E+00 1.11E+00 1.05E+00 40 LILLINGTON- CAPE FEAR RIVER 11/30/01 1.00 6.64E+00 1.13E+00 1.08E+00 40 LILLINGTON - CAPE FEAR RIVER 12/31/01 1.00 7.14E+00 1.16E+00 1.06E+00 Page 2 of 2

,.Jr

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine

.1 Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/1/01 711.20 <LLD 1.47E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/8/01 612.30 <LLD 3.34E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/15/01 613.70 <LLD 2.99E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/22/01 610.30 <LLD 2.62E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 1/29/01 614.20 <LLD 1.29E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 2/5/01 613.60 <LLD 1.40E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 2/12/01 605.50 <LLD 1.01 E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 2/19/01 606.00 <LLD 1.59E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 2/26/01 606.60 <LLD 2.OOE-02 SR 1134 AT INTSR 1011 -DIXIE PIPELINE 3/5/01 603.90 <LLD 1.43E-02 SR 1134 AT INT SR 1011 -DIXIE PIPELINE 3/12/01 610.10 <LLD 1.75E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 3/19/01 601.70 <LLD 1.48E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 3/26/01 604.80 <LLD 1.42E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/2/01 602.80 <LLD 1.84E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/9/01 598.00 <LLD 1.03E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/16/01 594.00 <LLD 1.38E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/23/01 599.20 <LLD 1.02E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 4/30/01 598.00 <LLD 1.75E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 5/7/01 592.10 <LLD 1.57E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 5/14/01 593.20 <LLD 2.44E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 5/21/01 594.10 <LLD 2.45E-02 SR 1134 AT INT SR I011 - DIXIE PIPELINE 5/29/01 681.40 <LLD 1.59E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 6/4/01 494.10 <LLD 2.89E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 6/11/01 597.20 <LLD 2.67E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 6/18/01 590.20 <LLD 2.40E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 6/25/01 592.20 <LLD 2.47E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 7/2/01 592.40 <LLD 1.48E-02 Page 1 of 12

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD SR 1134 AT INT SR 1011 - DIXIE PIPELINE 7/9/01 589.30 <LLD 2.08E-02 SR 1134 AT INT SR 1011 -DIXIE PIPELINE 7/16/01 587.00 <LLD 2.26E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 7/23/01 592.80 <LLD 1.81 E-02 SR 1134 AT INTSR 1011 -DIXIE PIPELINE 7/30/01 585.40 <LLD 2.34E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 8/6/01 593.40 <LLD 1.66E-02 SR 1134AT INTSR 1011 - DIXIE PIPELINE 8/13/01 389.90 <LLD 2.73E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 8/21/01 673.80 <LLD 1.32E-02 SR 1134AT INT SR 1011 -°DIXIE PIPELINE 8/27/01 507.20 <LLD 2.OOE-02 SR 1134 AT INT SR 1011 -DIXIE PIPELINE 9/4/01 683.50 <LLD 1.84E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 9/10/01 521.70 <LLD 1.80E-02 SR 1134 AT INT SR 1011 -DIXIE PIPELINE 9/17/01 608.80 <LLD 1.59E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 9/24/01 160.60 <LLD 4.66E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 10/1/01 571.90 <LLD 2.OOE-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 10/8/01 593.80 <LLD 2.06E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 10/15/01 577.70 <LLD 1.68E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 10/22/01 590.70 <LLD 2.11E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 10/29/01 360.00 <LLD 3.66E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 11/5/01 622.20 <LLD 1.38E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 11/12/01 497.40 <LLD 2.45E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 11/19/01 515.10 <LLD 3.89E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 11/26/01 515.30 <LLD 2.04E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 12/3/01 512.20 <LLD 2.43E-02 SR 1134 AT INT SR 10i11 - DIXIE PIPELINE 12/10/01 506.80 <LLD 2.14E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 12/17/01 519.30 <LLD 1.65E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 12/23/01 435.90 <LLD 5.01 E-02 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 12/31/01 595.80 <LLD 2.77E-02 SR 1134 1/1/01 700.00 <LLD 1.35E-02 Page 2 of 12

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine Concentration(Activity): pCi/cubic Jneter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 2 SR 1134 1/8/01 604.80 <LLD 3.31 E-02 2 SR 1134 1/15/01 626.70 <LLD 3.11E-02 2 SR 1134 1/22/01 582.90 <LLD 3.57E-02 2 SR 1134 1/29/01 607.70 <LLD 2.44E-02 2 SR 1134 2/5/01 606.50 <LLD 1.79E-02 2 SR 1134 2/12/01 599.30 <LLD 2.56E-02 2 SR 1134 2/19/01 602.00 <LLD 2.51E-02 2 SR 1134 2/26/01 620.80 <LLD 2.74E-02 2 SR 1134 3/5/01 601.70 <LLD 3.14E-02 2 SR 1134 3/12/01 583.40 <LLD 2.84E-02 2 SR 1134 3/19/01 619.60 <LLD 1.05E-02 2 SR 1134 3/26/01 602.00 <LLD 2.17E-02 2 SR 1134 4/2/01 596.80 <LLD 2.91 E-02 2 SR 1134 4/9/01 571.30 <LLD 2.OOE-02 2 SR 1134 4/16/01 588.00 <LLD 2.30E-02 2 SR 1134 4/23/01 595.90 <LLD 2.19E-02 2 SR 1134 4/30/01 592.00 <LLD 1.19E-02 2 SR 1134 5/7/01 588.10 <LLD 2.20E-02 2 SR 1134 5/14/01 588.30 <LLD 1.57E-02 2 SR 1134 5/21/01 590.20 <LLD 3.48E-02 2 SR 1134 5/29/01 675.20 <LLD 1.76E-02 2 SR 1134 6/4/01 765.70 <LLD 2.42E-02 2 SR 1134 6/11/01 495.80 <LLD 2.58E-02 2 SR 1134 6/18/01 489.70 <LLD 1.68E-02 2 SR 1134 6/25/01 508.70 <LLD 2.97E-02 2 SR 1134 7/2/01 853.20 <LLD 2.54E-02 2 SR 1134 7/9/01 882.60 <LLD 1.74E-02 Page 3 of 12

HNP RadiologicalEnvironmental Monitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD SR 1134 7/16/01 865.40 <LLD 1.75E-02 SR 1134 7/23/01 876.60 <LLD 2.32E-02 SR 1134 7/30/01 820.40 <LLD 2.28E-02 SR 1134 8/6/01 890.00 <LLD 1.20E-02 SR 1134 8/21/01 847.30 <LLD 2.07E-02 SR 1134 8/27/01 674.70 <LLD 1.08E-02 SR 1134 9/4/01 908.60 <LLD 1.49E-02 SR 1134 9/10/01 681.40 <LLD 1.85E-02 SR 1134 9/17/01 793.80 <LLD 2.70E-02 SR 1134 9/24/01 793.80 <LLD 8.36E-03 SR 1134 10/1/01 813.80 <LLD 2.03E-02 SR 1134 10/8/01 799.90 <LLD 1.64E-02 SR 1134 10/15/01 796.80 <LLD 1.92E-02 SR 1134 10/22/01 809.30 <LLD 2.09E-02 SR 1134 10/29/01 816.10 <LLD 2.36E-02 SR 1134 11/5/01 814.60 <LLD 2.07E-02 SR 1134 11/12/01 802.50 <LLD 1.63E-02 SR 1134 11/19/01 810.10 <LLD 2.19E-02 SR 1134 11/26/01 810.40 <LLD 1.86E-02 SR 1134 12/3/01 802.60 <LLD 2.30E-02 SR 1134 12/10/01 795.40 <LLD 1.57E-02 SR 1134 12/17/01 817.00 <LLD 1.59E-02 SR 1134 12/23/01 690.00 <LLD 2.86E-02 SR 1134 12/31/01 941.20 <LLD 2.52E-02 NEW HILL NEAR 1ST BAPTIST CH 1/1/01 592.20 <LLD 3.59E-02 NEW HILL NEAR 1ST BAPTIST CH 1/8/01 511.80 <LLD 2.32E-02 NEW HILL NEAR 1ST BAPTIST CH 1/15/01 513.70 <LLD 2.83E-02 Page 4 of12

I" HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Anabysis: Iodine Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD NEW HILL NEAR 1ST BAPTIST CH 1/22/01 511.60 <LLD 3.92E-02 NEW HILL NEAR 1ST BAPTIST CH 1/29/01 514.60 <LLD 2.97E-02 2/5/01 514.90 <LLD 3.06E-02 NEW HILL NEAR 1ST BAPTIST CH NEW HILL NEAR 1ST BAPTIST CH 2/12/01 507.60 <LLD 3.93E-02 NEW HILL NEAR 1ST BAPTIST CH 2/19/01 508.20 <LLD 4.79E-02 NEW HILL NEAR 1ST BAPTIST CH 2/26/01 510.00 <LLD 3.98E-02 NEW HILL NEAR 1ST BAPTIST CH 3/5/01 506.10 <LLD 3.49E-02 NEW HILL NEAR 1ST BAPTIST CH 3/12/01 509.80 <LLD 3.56E-02 NEW HILL NEAR 1ST BAPTIST CH 3/19/01 505.20 <LLD 3.11 E-02 NEW HILL NEAR 1ST BAPTIST CH 3/26/01 508.00 <LLD 2.61 E-02 NEW HILL NEAR 1ST BAPTIST CH 4/2/01 506.10 <LLD 1.64E-02 NEW HILL NEAR 1ST BAPTIST CH 4/9/01 504.00 <LLD 2.66E-02 NEW HILL NEAR 1ST BAPTIST CH 4/16/01 501.10 <LLD 2.66E-02 NEW HILL NEAR 1ST BAPTIST CH 4/23/01 505.00 <LLD 4.01 E-02 NEW HILL NEAR 1ST BAPTIST CH 4/30/01 502.00 <LLD 4.04E-02 NEW HILL NEAR 1ST BAPTIST CH 5/7/01 500.10 <LLD 2.73E-02 NEW HILL NEAR 1ST BAPTIST CH 5/14/01 499.20 <LLD 2.48E-02 NEW HILL NEAR 1ST BAPTIST CH 5/21/01 500.30 <LLD 4.81 E-02 NEW HILL NEAR 1ST BAPTIST CH 5/29/01 571.80 <LLD 1.99E-02 NEW HILL NEAR 1ST BAPTIST CH 6/4/01 410.20 <LLD 3.20E-02 NEW HILL NEAR 1ST BAPTIST CH 6/11/01 501.20 <LLD 1.93E-02 NEW HILL NEAR 1ST BAPTIST CH 6/18/01 496.70 <LLD 3.70E-02 NEW HILL NEAR 1Sd BAPTIST CH 6/25/01 495.80 <LLD 3.09E-02 NEW HILL NEAR 1ST BAPTIST CH 7/2/01 498.30 <LLD 3.59E-02 NEW HILL NEAR 1ST BAPTIST CH 7/9/01 493.30 <LLD 2.55E-02 NEW HILL NEAR 1ST BAPTIST CH 7/16/01 493.00 <LLD 2.57E-02 NEW HILL NEAR 1ST BAPTIST CH 7/23/01 497.50 <LLD 2.02E-02 Page5 of 12

HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD NEW HILL NEAR 1ST BAPTIST CH 7/30/01 490.30 <LLD 4.05E-02 NEW HILL NEAR 1ST BAPTIST CH 8/6/01 497.70 <LLD 2.64E-02 NEW HILL NEAR 1ST BAPTIST CH 8/13/01 496.10 <LLD 3.07E-02 NEW HILL NEAR 1ST BAPTIST CH 8/21/01 564.60 <LLD 2.29E-02 NEW HILL NEAR 1ST BAPTIST CH 8/27/01 422.90 <LLD 4.95E-02 NEW HILL NEAR 1ST BAPTIST CH 9/4/01 572.90 <LLD 1.74E-02 NEW HILL NEAR 1ST BAPTIST CH 9/17/01 500.00 <LLD 2.83E-02 NEW HILL NEAR 1ST BAPTIST CH 9/24/01 497.50 <LLD 3.70E-02 NEW HILL NEAR 1ST BAPTIST CH 10/1/01 504.30 <LLD 3.83E-02 NEW HILL NEAR 1ST BAPTIST CH 10/8/01 496.50 <LLD 3.13E-02 NEW HILL NEAR 1ST BAPTIST CH 10/15/01 497.10 <LLD 3.60E-02 NEW HILL NEAR 1ST BAPTIST CH 10/22/01 501.60 <LLD 4.96E-02 NEW HILL NEAR 1ST BAPTIST CH 10/29/01 504.50 <LLD 1.94E-02 NEW HILL NEAR 1ST BAPTIST CH 11/5/01 508.40 <LLD 3.50E-02 NEW HILL NEAR 1ST BAPTIST CH 11/12/01 493.30 <LLD 3.09E-02 NEW HILL NEAR 1ST BAPTIST CH 11/19/01 502.50 <LLD 3.36E-02 NEW HILL NEAR 1ST BAPTIST CH 11/26/01 501.20 <LLD 2.48E-02 NEW HILL NEAR 1ST BAPTIST CH 12/3/01 498.70 <LLD 2.66E-02 NEW HILL NEAR 1ST BAPTIST CH 12/10/01 493.90 <LLD 2.03E-02 NEW HILL NEAR 1ST BAPTIST CH 12/17/01 503.60 <LLD 2.42E-02 NEW HILL NEAR 1ST BAPTIST CH 12/23/01 425.20 <LLD 1.82E-02 NEW HILL NEAR 1ST BAPTIST CH 12/31/01 580.40 <LLD 3.47E-02 PITTSBORO - CONTAOL 1/1/01 690.90 <LLD 2.81 E-02 PITrSBORO - CONTROL 1/8/01 595.40 <LLD 3.68E-02 PITTSBORO - CONTROL 1/15/01 595.70 <LLD 1.64E-02 PITTSBORO - CONTROL 1/22/01 596.70 <LLD 9.56E-03 PITTSBORO - CONTROL 1/29/01 598.60 <LLD 3.02E-02 Page 6 of 12 4.

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD PITTSBORO - CONTROL 2/5/01 601.50 <LLD 1.90E-02 PITTSBORO - CONTROL 2/12/01 589.90 <LLD 2.31 E-02 PITTSBORO - CONTROL 2/19/01 589.00 <LLD 3.98E-02 PITTSBORO - CONTROL 2/26/01 592.20 <LLD 1.30E-02 PITTSBORO - CONTROL 3/5/01 590.40 <LLD 3.04E-02 PITTSBORO - CONTROL 3/12101 595.20 <LLD 2.88E-02 PITTSBORO - CONTROL 3/19/01 590.00 <LLD 2.38E-02 PITTSBORO - CONTROL 3/26/01 592.00 <LLD 2.98E-02 PITTSBORO - CONTROL 4/2/01 588.20 <LLD 2.19E-02 PITTSBORO - CONTROL 4/9/01 586.30 <LLD 3.21 E-02 PITTSBORO - CONTROL 4/16/01 585.10 <LLD 3.38E-02 PITTSBORO - CONTROL 4/23/01 588.10 <LLD 2.54E-02 PITTSBORO - CONTROL 4/30/01 587.20 <LLD 2.14E-02 PITTSBORO - CONTROL 5/7/01 584.30 <LLD 1.26E-02 PITTSBORO - CONTROL 5/14/01 583.10 <LLD 3.14E-02 PITTSBORO - CONTROL 5/21/01 587.30 <LLD 2.54E-02 PITTSBORO - CONTROL 5/29/01 659.80 <LLD 3.23E-02 PITTSBORO - CONTROL 6/4/01 507.70 <LLD 3.46E-02 PITTSBORO - CONTROL 6/11/01 597.10 <LLD 1.09E-02 PITTSBORO - CONTROL 6/18/01 579.60 <LLD 2.01 E-02 PITTSBORO - CONTROL 6/25/01 580.70 <LLD 2.26E-02 PITTSBORO - CONTROL 7/2/01 585.20 <LLD 2.28E-02 PITTSBORO - CONThOL 7/9/01 587.20 <LLD 1.05E-02 PITTSBORO - CONTROL 7/16/01 712.20 <LLD 1.19E-02 PITTSBORO - CONTROL 7/23/01 775.60 <LLD 2.45E-02 PITTSBORO - CONTROL 7/30/01 762.90 <LLD 8.05E-03 PITTSBORO - CONTROL 8/6/01 771.40 <LLD 1.39E-02 Page 7 of 12

HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 5 PITTSBORO - CONTROL 8/13/01 585.60 <LLD 3.42E-02 5 PITTSBORO - CONTROL 8/21/01 848.60 <LLD 1.10E-02 5 PITTSBORO - CONTROL 8/27/01 643.30 <LLD 1.12E-02 5 PITTSBORO - CONTROL 9/4/01 873.20 <LLD 2.OOE-02 5 PITTSBORO - CONTROL 9/10/01 659.20 <LLD 3.39E-02 5 PITTSBORO - CONTROL 9/17/01 765.80 <LLD 1.13E-02 5 PITTSBORO - CONTROL 9/24/01 769.50 <LLD 8.65E-03 5 PITTSBORO - CONTROL 10/1/01 787.40 <LLD 2.10E-02 5 PITTSBORO - CONTROL 10/8/01 773.50 <LLD 1.62E-02 5 PITTSBORO - CONTROL 10/15/01 767.20 <LLD 1.70E-02 5 PITTSBORO - CONTROL 10/22/01 779.70 <LLD 1.78E-02 5 PITFSBORO - CONTROL 10/29/01 787.60 <LLD 2.18E-02 5 PITTSBORO - CONTROL 11/5/01 786.00 <LLD 1.22E-02 5 PITTSBORO - CONTROL 11/12/01 771.10 <LLD 7.88E-03 5 PITTSBORO - CONTROL 11/19/01 502.50 <LLD 3.21 E-02 5 PITTSBORO - CONTROL 11/26/01 776.20 <LLD 1.36E-02 5 PITTSBORO - CONTROL 12/3/01 768.90 <LLD 1.71 E-02 5 PITTSBORO - CONTROL 12/10/01 768.10 <LLD 8.OOE-03 5 PITTSBORO - CONTROL 12/17/01 799.60 <LLD 2.23E-02 5 PITTSBORO - CONTROL 12/23/01 659.60 <LLD 1.88E-02 5 PITTSBORO - CONTROL 12/31/01 909.80 <LLD 1.29E-02 26 SPILLWAY ON MAIN:RES 1/1/01 655.70 <LLD 2.34E-02 26 SPILLWAY ON MAINW'RES 1/8/01 568.30 <LLD 2.10E-02 26 SPILLWAY ON MAIN RES 1/15/01 568.00 <LLD 3.85E-02 26 SPILLWAY ON MAIN RES 1,/22/01 563.50 <LLD 1.80E-02 26 SPILLWAY ON MAIN RES 1/29/01 567.50 <LLD 3.30E-02 26 SPILLWAY ON MAIN RES 2/5/01 570.40 <LLD 1.91 E-02 Page 8 of 12

HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 26 SPILLWAY ON MAIN RES 2/12/01 556.70 <LLD 3.02E-02 26 SPILLWAY ON MAIN RES 2/19/01 563.60 <LLD 1.32E-02 26 SPILLWAY ON MAIN RES 2/26/01 560.80 <LLD 2.35E-02 26 SPILLWAY ON MAIN RES 3/5/01 562.60 <LLD 1.89E-02 26 SPILLWAY ON MAIN RES 3/12/01 564.80 <LLD 3.10E-02 26 SPILLWAY ON MAIN RES 3/19/01 561.70 <LLD 1.53E-02 26 SPILLWAY ON MAIN RES 3/26/01 563.80 <LLD 1.92E-02 26 SPILLWAY ON MAIN RES 4/2/01 488.20 <LLD 2.06E-02 26 SPILLWAY ON MAIN RES 4/9/01 550.00 <LLD 1.59E-02 26 SPILLWAY ON MAIN RES 4/16/01 552.90 <LLD 2.88E-02 26 SPILLWAY ON MAIN RES 4/23/01 552.90 <LLD 1.49E-02 26 SPILLWAY ON MAIN RES 4/30/01 558.20 <LLD 2.71E-02 26 SPILLWAY ON MAIN RES 5/7/01 551.20 <LLD 2.84E-02 26 SPILLWAY ON MAIN RES 5/14/01 548.20 <LLD 1.50E-02 26 SPILLWAY ON MAIN RES 5/21/01 552.10 <LLD 3.21E-02 26 SPILLWAY ON MAIN RES 5/29/01 636.30 <LLD 1.01E-02 26 SPILLWAY ON MAIN RES 6/4/01 454.90 <LLD 1.82E-02 26 SPILLWAY ON MAIN RES 6/11/01 555.20 <LLD 3.08E-02 26 SPILLWAY ON MAIN RES 6/18/01 162.50 <LLD 6.36E-02 26 SPILLWAY ON MAIN RES 6/25/01 541.00 <LLD 3.712E-02 26 SPILLWAY ON MAIN RES 7/2/01 547.30 <LLD 2.37E-02 26 SPILLWAY ON MAIN:RES 7/9/01 548.60 <LLD 4.20E-02 26 SPILLWAY ON MAIN'RES 7/16/01 536.60 <LLD 3.16E-02 26 SPILLWAY ON MAIN RES 7/23/01 536.90 <LLD 2.03E-02 26 SPILLWAY ON MAIN RES 7/30/01 541.20 <LLD 1.972-02 26 SPILLWAY ON MAIN RES 8/6/01 545.20 <LLD 3.12E-02 26 SPILLWAY ON MAIN RES 8/13/01 326.70 <LLD 4.02E-02 Page 9 of 12

I-HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 26 SPILLWAY ON MAIN RES 8/21/01 591.60 <LLD 2.66E-02 26 SPILLWAY ON MAIN RES 8/27/01 467.30 <LLD 3.80E-02 26 SPILLWAY ON MAIN RES 9/4/01 628.10 <LLD 2.52E-02 26 SPILLWAY ON MAIN RES 9/17/01 547.00 <LLD 3.11 E-02 26 SPILLWAY ON MAIN RES 9/24/01 544.40 <LLD 3.72E-02 26 SPILLWAY ON MAIN RES 10/1/01 564.80 <LLD 2.05E-02 26 SPILLWAY ON MAIN RES 10/8/01 541.00 <LLD 2.81 E-02 26 SPILLWAY ON MAIN RES 10/15/01 548.00 <LLD 2.42E-02 26 SPILLWAY ON MAIN RES 10/22/01 550.80 <LLD 2.75E-02 26 SPILLWAY ON MAIN RES 10/29/01 559.20 <LLD 1.18E-02 26 SPILLWAY ON MAIN RES 11/5/01 491.10 <LLD 2.67E-02 26 SPILLWAY ON MAIN RES 11/12/01 557.80 <LLD 4.88E-02 26 SPILLWAY ON MAIN RES 11/19/01 553.40 <LLD 3.07E-02 26 SPILLWAY ON MAIN RES 11/26/01 553.80 <LLD 3.05E-02 26 SPILLWAY ON MAIN RES 12/3/01 547.80 <LLD 3.28E-02 26 SPILLWAY ON MAIN RES 12/10/01 548.40 <LLD 2.97E-02 26 SPILLWAY ON MAIN RES 12/17/01 570.10 <LLD 3;75E-02 26 SPILLWAY ON MAIN RES 12/23/01 382.80 <LLD 2.28E-02 26 SPILLWAY ON MAIN RES 12/31/01 650.20 <LLD 2.59E-02 47 SSW SECTOR 3.4 MI FROM SITE 1/1/01 671.60 <LLD 2.45E-02 47 SSW SECTOR 3.4 MI FROM SITE 1/8/01 582.60 <LLD 3.37E-02 47 SSW SECTOR 3.4 MI:FROM SITE 1/15/01 578.90 <LLD 2.93E-02 47 SSW SECTOR 3.4 MI t FROM SITE 1/22/01 576.60 <LLD 3.20E-02 47 SSW SECTOR 3.4 MI FROM SITE 1/29/01 580.60 <LLD 3.39E-02 47 SSW SECTOR 3.4 MI FROM SITE 2/5/01 580.20 <LLD 3.45E-02 47 SSW SECTOR 3.4 MI FROM SITE 2/12/01 572.80 <LLD 2.80E-02 47 SSW SECTOR 3.4 MI FROM SITE 2/19/01 578.70 <LLD 2.26E-02 Page 10of 12 d

HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Air Cartridge Quantity: cubic meters Analysis: Iodine Concentration (Activity): pCi/cubic meter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 47 SSW SECTOR 3.4 MI FROM SITE 2/26/01 575.30 <LLD 2.29E-02 47 SSW SECTOR 3.4 MI FROM SITE 3/5/01 678.20 <LLD 1.91 E-02 47 SSW SECTOR 3.4 MI FROM SITE 3/12/01 682.60 <LLD 1.22E-02 47 SSW SECTOR 3.4 MI FROM SITE 3/19/01 679.20 <LLD 1.92E-02 47 SSW SECTOR 3.4 MI FROM SITE 3/26/01 680.30 <LLD 2.78E-02 47 SSW SECTOR 3.4 MI FROM SITE 4/2/01 676.30 <LLD 1.75E-02 47 SSW SECTOR 3.4 MI FROM SITE 4/9/01 671.40 <LLD 2.66E-02 47 SSW SECTOR 3.4 MI FROM SITE 4/16/01 669.30 <LLD 1.23E-02 47 SSW SECTOR 3.4 MI FROM SITE 4/23/01 671.10 <LLD 2.29E-02 47 SSW SECTOR 3.4 MI FROM SITE 4/30/01 673.20 <LLD 2.76E-02 47 SSW SECTOR 3.4 MI FROM SITE 5/7/01 667.30 <LLD 2.94E-02 47 SSW SECTOR 3.4 MI FROM SITE 5/14/01 664.40 <LLD 1.70E-02 47 SSW SECTOR 3.4 MI FROM SITE 5/21/01 668.20 <LLD 2.36E-02 47 SSW SECTOR 3.4 MI FROM SITE 5/29/01 769.40 <LLD 2.OOE-02 47 SSW SECTOR 3.4 MI FROM SITE 6/4/01 548.80 <LLD 1.19E-02 47 SSW SECTOR 3.4 MI FROM SITE 6/11/01 672.50 <LLD 2.66E-02 47 SSW SECTOR 3.4 MI FROM SITE 6/18/01 659.10 <LLD 2.91 E-02 47 SSW SECTOR 3.4 MI FROM SITE 6/25/01 658.80 <LLD 2.72E-02 47 SSW SECTOR 3.4 MI FROM SITE 7/2/01 661.70 <LLD 2.40E-02 47 SSW SECTOR 3.4 MI FROM SITE 7/9/01 663.70 <LLD 3.34E-02 47 SSW SECTOR 3.4 MI FROM SITE 7/16/01 655.20 <LLD 2.33E-02 47 SSW SECTOR 3.4 MI FROM SITE 7/23/01 648.00 <LLD 3.54E-02 47 SSW SECTOR 3.4 M('FROM SITE 7/30/01 657.00 <LLD 3.05E-02 47 SSW SECTOR 3.4 MI FROM SITE 8/6/01 661.90 <LLD 2.98E-02 47 SSW SECTOR 3.4 MI FROM SITE 8/13/01 506.20 <LLD 1.52E-02 47 SSW SECTOR 3.4 MI FROM SITE 8/21/01 711.50 <LLD 2.93E-02 47 SSW SECTOR 3.4 MI FROM SITE 8/27/01 561.00 <LLD 2.14E-02 Page 11 of 12 S

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Air Cartridge Quantity. cubic meters Analysis: Iodine Concentration(Activity): pCi/cubic meter Sample Date Quantity Activity- 2 Sigma Error LLD Sample Point v 47 SSW SECTOR 3.4 MI FROM SITE 9/4/01 760.10 <LLD 1.83E-02 9/10/01 564.30 <LLD 2.58E-02 47 SSW SECTOR 3.4 MI FROM SITE 9/17/01 663.60 <LLD 1.88E-02 47 SSW SECTOR 3.4 MI FROM SITE 9/24/01 661.70 <LLD 2.16E-02 47 SSW SECTOR 3.4 MI FROM SITE 10/1/01 684.80 <LLD 2.43E-02 47 SSW SECTOR 3.4 MI FROM SITE 10/8/01 657.10 <LLD 3.04E-02 47 SSW SECTOR 3.4 MI FROM SITE 10/15/01 670.60 <LLD 3.51 E-02 47 SSW SECTOR 3.4 MI FROM SITE 10/22/01 666.00 <LLD 1.93E-02 47 SSW SECTOR 3.4 MI FROM SITE 10/29/01 678.50 <LLD 3.18E-02 47 SSW SECTOR 3.4 MI FROM SITE 11/5/01 671.70 <LLD 1.31 E-02 47 SSW SECTOR 3.4 MI FROM SITE 11/12/01 678.00 <LLD 3.48E-02 47 SSW SECTOR 3.4 MI FROM SITE 11/19/01 673.90 <LLD 2.30E-02 47 SSW SECTOR 3.4 MI FROM SITE 11/26/01 676.00 <LLD 1.93E-02 47 SSW SECTOR 3.4 MI FROM SITE 12/3/01 669.40 <LLD 3.03E-02 47 SSW SECTOR 3.4 MI FROM SITE 12/10/01 660.90 <LLD 1.37E-02 47 SSW SECTOR 3.4 MI FROM SITE 12/17/01 691.50 <LLD 2.85E-02 47 SSW SECTOR 3.4 MI FROM SITE 12/23/01 557.50 <LLD 3.18E-02 47 SSW SECTOR 3.4 MI FROM SITE 12/31/01 781.40 <LLD 2.82E-02 47 SSW SECTOR 3.4 MI FROM SITE Page 12 of 12

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HNP Radiologicalenvironmental MonitoringAnalysis Report Media Type: Drinking Water Quantity: Liters Analysis: Iodine Concentration(Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 38 CAPE FEAR PLANT INTAKE - CONTROL 1/8/01 4.00 <LLD 6.48E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 1/22/01 4.00 <LLD 4.56E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 2/5/01 4.00 <LLD 6.37E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 2/19/01 4.00 <LLD 4.55E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 3/5/01 4.00 <LLD 4.78E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 3/19/01 4.00 <LLD 4.16E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 4/2/01 4.00 <LLD 4.26E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 4/16/01 4.00 <LLD 3.64E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 4/30/01 4.00 <LLD 3.58E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 5/14/01 4.00 <LLD 3.53E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 5/29/01 4.00 <LLD 4.70E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 6/11/01 4.00 <LLD 4.94E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 6/25/01 4.00 <LLD 3.59E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 7/9/01 4.00 <LLD 5.63E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 7/23/01 4.00 <LLD 3.53E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 8/6/01 4.00 <LLD 4.48E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 8/21/01 4.00 <LLD 3.73E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 9/4/01 4.00 <LLD 5.22E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 9/17/01 4.00 <LLD 3.04E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 10/1/01 4.00 <LLD 3.76E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 10/15/01 4.00 <LLD 4.62E-01 38 CAPE FEAR PLANT'INTAKE - CONTROL 10/29/01 4.00 <LLD 3.39E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 11/1 2/01 4.00 <LLD 4.85E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 11/26/01 4.00 <LLD 4.45E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 12/10/01 4.00 <LLD 3.48E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 12/23/01 4.00 <LLD 3.30E-01 PageI of 3

HNP RadiologicalenvironmentalMonitoringAnalysis Report Media Type: Drinking Water Quantity: Liters Analysis: Iodine Concentration (Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 40 LILLINGTON - CAPE FEAR RIVER 1/8/01 4.00 <LLD 6.32E-01 40 LILLINGTON - CAPE FEAR RIVER 1/22/01 4.00 <LLD 4.29E-01 40 LILLINGTON - CAPE FEAR RIVER 2/5/01 4.00 <LLD 3.86E-01 40 LILLINGTON - CAPE FEAR RIVER 2/19/01 4.00 <LLD 4.08E-01 40 LILLINGTON - CAPE FEAR RIVER 3/5/01 4.00 <LLD 4.03E-01 40 LILLINGTON - CAPE FEAR RIVER 3/19/01 4.00 <LLD 4.34E-01 40 LILLINGTON - CAPE FEAR RIVER 4/2/01 4.00 <LLD 4.84E-01 40 LILLINGTON - CAPE FEAR RIVER 4/16/01 4.00 <LLD 4.73E-01 40 LILLINGTON - CAPE FEAR RIVER 4/30/01 4.00 <LLD 4.80E-01 40 LILLINGTON - CAPE FEAR RIVER 5/14/01 4.00 <LLD 4.12E-01 40 LILLINGTON - CAPE FEAR RIVER 5/29/01 4.00 <LLD 4.31 E-01 40 LILLINGTON - CAPE FEAR RIVER 6/11/01 4.00 <LLD 4.16E-01 40 LILLINGTON - CAPE FEAR RIVER 6/25/01 4.00 <LLD 4.69E-01 40 LILLINGTON - CAPE FEAR RIVER 7/9/01 4.00 <LLD 4.75E-01 40 LILLINGTON - CAPE FEAR RIVER 7/23/01 4.00 <LLD 4.19E-01 40 LILLINGTON - CAPE FEAR RIVER 8/6/01 4.00 <LLD 4.49E-01 40 LILLINGTON - CAPE FEAR RIVER 8/21/01 4.00 <LLD 4.54E-01 40 LILLINGTON - CAPE FEAR RIVER 9/4/01 4.00 <LLD 5.08E-01 40 LILLINGTON - CAPE FEAR RIVER 9/17/01 4.00 <LLD 3.94E-01 40 LILLINGTON - CAPE FEAR RIVER 10/1/01 4.00 <LLD 4.82E-01 40 LILLINGTON - CAPE FEAR RIVER 10/15/01 4.00 <LLD 3.70E-01 40 LILLINGTON - CAPtE FEAR RIVER 10/29/01 4.00 <LLD 3.93E-01 40 LILLINGTON - CAPE FEAR RIVER 11/12/01 4.00 <LLD 6.10OE-01 40 LILLINGTON - CAPE FEAR RIVER 11/26/01 4.00 <LLD 05.13E-01 40 LILLINGTON - CAPE FEAR RIVER 12/10/01 4.00 <LLD 5.04E-01 40 LILLINGTON - CAPE FEAR RIVER 12/23/01 4.00 <LLD 3.92E-01 Page 2 of 3

HNP RadiologicalenvironmentalMonitoring Analysis Report Media Type: Drinking Water Quantity: Liters Analysis: Iodine Concentration(Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 51 WATER TREATMENT BLDG AT HARRIS PLANT 1/8/01 4.00 <LLD, 6.03E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 1/22/01 4.00 <LLD 4.83E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 2/5/01 4.00 <LLD 4.90E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 2/19/01 4.00 <LLD 3.18E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 3/5/01 4.00 <LLD 6.12E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 3/19/01 4.00 <LLD 3.73E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 4/2/01 4.00 <LLD 4.99E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 4/16/01 4.00 <LLD 4.01E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 4/30/01 4.00 <LLD 5.21 E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 5/14/01 4.00 <LLD 5.38E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 5/29/01 4.00 <LLD 4.65E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 6/11/01 4.00 <LLD 4.92E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 6/25/01 4.00 <LLD 5.26E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 7/9/01 4.00 <LLD 4.36E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 7/23/01 4.00 <LLD 4.86E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 8/6/01 4.00 <LLD 4.46E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 8/21/01 4.00 <LLD 5.47E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 9/4/01 4.00 <LLD 6.17E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 9/17/01 4.00 <LLD 4.53E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 10/1/01 4.00 <LLD 5.19E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 10/15/01 4.00 <LLD 4.96E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 10/29/01 4.00 <LLD 5.27E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 11/12/01 4.00 <LLD 4.53E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 11/26/01 4.00 <LLD 4.58E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 12/10/01 4.00 <LLD 4.02E-01 51 WATER TREATMENT BLDG AT HARRIS PLANT 12/23/01 4.00 <LLD 4.30E-01 Page3 of3

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Milk Quantity: Liters Analysis: Iodine Concentration(Activity): pCi/Lite Sample Point Sample Date Quantity Activity 2 Sigma Error LLD PITTSBORO - CONTROL 1/2/01 4.00 <LLD 4.98E-01 PITTSBORO - CONTROL 1/15/01 4.00 <LLD 5.65E-01 PITTSBORO - CONTROL 2/5/01 4.00 <LLD 3.25E-01 PITTSBORO - CONTROL 2/19/01 4.00 <LLD 4.91 E-01 PITTSBORO - CONTROL 3/5/01 4.00 <LLD 3.43E-01 PITTSBORO - CONTROL 3/19/01 4.00 <LLD 3.08E-01 PITTSBORO - CONTROL 4/2/01 4.00 <LLD 3.33E-01 PITTSBORO - CONTROL 4/16/01 4.00 <LLD 5.27E-01 PITTSBORO - CONTROL 5/8/01 4.00 <LLD 4.30E-01 PITTSBORO - CONTROL 5/21/01 4.00 <LLD 4.74E-01 PITTSBORO - CONTROL 6/4/01 4.00 <LLD 5.16E-01 PITTSBORO - CONTROL 6/18/01 4.00 <LLD 3.52E-01 PITTSBORO - CONTROL 7/2/01 4.00 <LLD 4.44E-01 PITTSBORO - CONTROL 7/16/01 4.00 <LLD 4.20E-01 PITTSBORO - CONTROL 8/6/01 4.00 <LLD 3.42E-01 PITTSBORO - CONTROL 8/20/01 4.00 <LLD 3.09E-01 PITTSBORO - CONTROL 9/4/01 4.00 <LLD 4.43E-01 PITTSBORO - CONTROL 9/17/01 4.00 <LLD 4.28E-01 PIT-SBORO - CONTROL 10/1/01 4.00 <LLD 6.07E-01 PITTSBORO - CONTROL 10/15/01 4.00 <LLD 4.29E-01 PITTSBORO - CONTROL 11/12/01 4.00 <LLD 3.46E-01 PITTSBORO - CONTROL 11/19/01 4.00 <LLD 4.39E-01 PITTSBORO - CONTROL 12/3/01 4.00 <LLD 4.48E-01 PITTSBORO - CONTROL 12/17/01 4.00 <LLD 4.47E-01 Page 1 of I

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HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Surface Water Quantity: Liters Analysis: Iodine Concentration(Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 38 CAPE FEAR PLANT INTAKE - CONTROL 1/8/01 4.00 <LLD 6.48E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 1/22/01 4.00 <LLD 4.56E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 2/5/01 4.00 <LLD 6.37E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 2/19/01 4.00 <LLD 4.55E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 3/5/01 4.00 <LLD 4.78E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 3/19/01 4.00 <LLD 4.16E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 4/2/01 4.00 <LLD 4.26E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 4/16/01 4.00 <LLD 3.64E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 4/30/01 4.00 <LLD 3.58E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 5/14/01 4.00 <LLD 3.53E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 5/29/01 4.00 <LLD 4.70E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 6/11/01 4.00 <LLD 4.94E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 6/25/01 4.00 <LLD 3.59E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 7/9/01 4.00 <LLD 5.63E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 7/23/01 4.00 <LLD 3.53E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 8/6/01 4.00 <LLD 4.48E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 8/21/01 4.00 <LLD 3.73E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 9/4/01 4.00 <LLD 5.22E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 9/17/01 4.00 <LLD 3.04E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 10/1/01 4.00 <LLD 3.76E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 10/15/01 4.00 <LLD 4.62E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 10/29/01 4.00 <LLD 3.39E-01 Page I of 3

HNP RadiologicalEnvironmental MonitoringAnalysis Report Media Type: Surface Water Quantity: Liters Analysis: Iodine Concentration(Activity): pCiliter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 38 CAPE FEAR PLANT INTAKE - CONTROL 11/12/01 4.00 <LLD 4.85E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 11/26/01 4.00 <LLD 4.45E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 12/10/01 4.00 <LLD 3.48E-01 38 CAPE FEAR PLANT INTAKE - CONTROL 12/23/01 4.00 <LLD 3.30E-01 40 LILLINGTON - CAPE FEAR RIVER 1/8/01 4.00 <LLD 6.32E-01 40 LILLINGTON - CAPE FEAR RIVER 1/22/01 4.00 <LLD 4.29E-01 40 LILLINGTON - CAPE FEAR RIVER 2/5/01 4.00 <LLD 3.86E-01 40 LILLINGTON - CAPE FEAR RIVER 2/19/01 4.00 <LLD 4.08E-01 40 LILLINGTON - CAPE FEAR RIVER 3/5/01 4.00 <LLD 4.03E-01 40 LILLINGTON - CAPE FEAR RIVER 3/19/01 4.00 <LLD 4.34E-01 40 LILLINGTON - CAPE FEAR RIVER 4/2/01 4.00 <LLD 4.84E-01 40 LILLINGTON - CAPE FEAR RIVER 4/16/01 4.00 <LLD 4.73E-01 40 LILLINGTON - CAPE FEAR RIVER 4/30/01 4.00 <LLD 4.80E-01 40 LILLINGTON - CAPE FEAR RIVER 5/14/01 4.00 <LLD 4.12E-01 40 LILLINGTON - CAPE FEAR RIVER 5/29/01 4.00 <LLD 4.31 E-01 40 LILLINGTON - CAPE FEAR RIVER 6/11/01 4.00 <LLD 4.16E-01 40 LILLINGTON - CAPE FEAR RIVER 6/25/01 4.00 <LLD 4.69E-01 40 LILLINGTON - CAPE FEAR RIVER 7/9/01 4.00 <LLD 4.75E-01 40 LILLINGTON - CAPE FEAR RIVER 7/23/01 4.00 <LLD 4.19E-01 40 LILLINGTON - CAPE FEAR RIVER 8/6/01 4.00 <LLD 4.49E-01 40 LILLINGTON - CAPE FEAR RIVER 8/21/01 4.00 <LLD 4.54E-01 40 LILLINGTON - CAPE FEAR RIVER 9/4/01 4.00 <LLD 5.08E-01 Page2 of3

7-HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Surface Water Quantity: Liters Analysis: Iodine Concentration (Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 40 LILLINGTON - CAPE FEAR RIVER 9/17/01 4.00 <LLD 3.94E-03 40 LILLINGTON - CAPE FEAR RIVER 10/1/01 4.00 <LLD 4.82E-01 40 LILLINGTON - CAPE FEAR RIVER 10/15/01 4.00 <LLD 3.70E-01 40 LILLINGTON - CAPE FEAR RIVER 10/29/01 4.00 <LLD 3.93E-01 40 LILLINGTON - CAPE FEAR RIVER 11/12/01 4.00 <LLD 6.1 OE-01 40 LILLINGTON - CAPE FEAR RIVER 11/26/01 4.00 <LLD 5.13E-01 40 LILLINGTON - CAPE FEAR RIVER 12/10/01 4.00 <LLD 5.04E-01 40 LILLINGTON - CAPE FEAR RIVER 12/23/01 4.00 <LLD 3.92E-01 I-,

Page 3 of 3

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HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Drinking Water Analysis: Tritiun Quantity: Liters Concentration(Activty): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 38 CAPE FEAR PLANT INTAKE - CONTROL 1/31/01 0.005 <LLD 3.06E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 2/28/01 0.005 <LLD 3.01 E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 3/31/01 0.005 <LLD 2.99E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 4/30/01 0.005 <LLD 2.94E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 5/31/01 0.005 <LLD 2.96E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 6/30/01 0.005 <LLD 2.95E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 7/31/01 0.005 <LLD 2.91 E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 8/31/01 0.005 <LLD 2.98E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 9/30/01 0.005 <LLD 2.93E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 10/31/01 0.005 <LLD 3.OOE+02 38 CAPE FEAR PLANT INTAKE - CONTROL 11/30/01 0.005 <LLD 2.88E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 12/31/01 0.005 <LLD 2.92E+02 40 LILLINGTON - CAPE FEAR RIVER 1/31/01 0.005 <LLD 3.07E+02 40 LILLINGTON - CAPE FEAR RIVER 2/28/01 0.005 <LLD 3.03E+02 40 LILLINGTON - CAPE FEAR RIVER 3/31/01 0.005 <LLD 2.99E+02 40 LILLINGTON - CAPE FEAR RIVER 4/30/01 0.005 <LLD 2.94E+02 40 LILLINGTON - CAPE FEAR RIVER 5/31/01 0.005 <LLD 2.98E+02 40 LILLINGTON - CAPE FEAR RIVER 6/30/01 0.005 <LLD 2.95E+02 40 LILLINGTON - CAPE FEAR RIVER 7/31/01 0.005 <LLD 2.96E+02 40 LILLINGTON - CAPE FEAR RIVER 8/31/01 0.005 <LLD 2.98E+02 40 LILLINGTON - CAPE FEAR RIVER 9/30/01 0.005 <LLD 2.94E+02 40 LILLINGTON - CAPE FE*AR RIVER 10/31/01 0.005 <LLD 3.02E+02 40 LILLINGTON - CAPE FEAR RIVER 11/30/01 0.005 <LLD 2.88E+02 40 LILLINGTON - CAPE FEAR RIVER 12/31/01 0.005 <LLD 2.91E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 1/31/01 0.005 3.15E+03 2.28E+02 3.06E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 2/28/01 0.005 3.32E+03 2.29E+02 3.04E+02 PageIof 2 j.4.

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Drinking Water Analysis: Tritium Quantity: Liters Concentration (Activty): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 51 WATER TREATMENT BLDG AT HARRIS PLANT 3/31/01 0.005 3.30E+03 2.26E+02 2.99E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 4/30/01 0.005 2.57E+03 2.14E+02 2.94E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 5/31/01 0.005 2.90E+03 2.20E+02 2.97E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 6/30/01 0.005 3.27E+03 2.24E+02 2.95E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 7/31/01 0.005 3.52E+03 2.25E+02 2.92E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 8/31/01 0.005 3.31 E+03 2.26E+02 2.98E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 9/30/01 0.005 3.69E+03 2.26E+02 2.90E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 10/31/01 0.005 5.68E+03 6.29E+02 8.65E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 11/30/01 0.005 4.90E+03 2.39E+02 2.88E+02 51 WATER TREATMENT BLDG AT HARRIS PLANT 12/31/01 0.005 5.51 E+03 2.46E+02 2.87E+02 Page2of 2

7 HNP RadiologicalEnvironmentalMonitoring Analysis Report Media Type: Groundwater Quantity: Liters Analysis: Tritium Concentration (Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LID 39 DEEP WELL NEAR DIABASE DIKES 2/21/01 0.005 <LLD 3.06E+02 39 DEEP WELL NEAR DIABASE DIKES 5/23/01 0.005 <LL) 2.94E+02 39 DEEP WELL NEAR DIABASE DIKES 8/29/01 0.005 <LLD 2.98E+02 39 DEEP WELL NEAR DIABASE DIKES 11/27/01 0.005 <LLD 2.93E+02 57 0.4 MI SSW SECTOR NDBANK ESW INTAKE 2/21/01 0.005 <LLD 3.07E+02 57 0.4 MI SSW SECTOR N BANK ESW INTAKE 5/23/01 0.005 <LLD 2.94E+02 57 0.4 MI SSW SECTOR N BANK ESW INTAKE 8/29/01 0.005 <LLD 2.99E+02 57 0.4 MI SSW SECTOR N BANK ESW INTAKE 11/27/01 0.005 <LLD 2.93E+02 58 0.5 MI WSW SECTOR N BANK ESW INTAKE 2/21/01 0.005 6.38E+02 1.95E+02 3.07E+02 58 0.5 MI WSW SECTOR N BANK ESW INTAKE 5/23/01 0.005 6.14E+02 1.90E+02 2.99E+02 58 0.5 MI WSW SECTOR N BANK ESW INTAKE 8/29/01 0.005 7.814E+02 1.93E+02 3.OOE+02 58 0.5 MI WSW SECTOR N BANK ESW INTAKE 11/27/01 0.005 8.25E+02 1.90E+02 2.92E+02 59 0.5 MI NNE SECTOR (NEAR CONSTRUCTION RD) 2/21/01 0.005 <LLD 3.07E+02 59 0.5 MI NNE SECTOR (NEAR CONSTRUCTION RD) 5/23/01 0.005 <LLD 2.95E+02 59 0.5 MI NNE SECTOR (NEAR CONSTRUCTION RD) 8/29/01 0.005 <LLD 3.019E+02 59 0.5 MI NNE SECTOR (NEAR CONSTRUCTION RD) 11/27/01 0.005 <LLD 2.93E+02 60 0.5 MI ESE SECTOR W BANK OF THOMAS CREEK 2/21/01 0.005 <LLD 3.08E+02 60 0.5 MI ESE SECTOR W BANK OF THOMAS CREEK 5/23/01 0.005 <LLD 2.94E+02 60 0.5 MI ESE SECTOR W BANK OF THOMAS CREEK 8/29/01 0.005 <LLD 3.019E+02 60 0.5 MI ESE SECTOR W BANK OF THOMAS CREEK 11/27/01 0.005 <LLD 2.93E+02 Page 1 of 1

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Surface Water Quantity: Liters Analysis: Tritium Concentration (Activity): pCi/Liter Sample Point Sample Date Quantity

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I Activity 2 Sigma Error LLD 26 SPILLWAY ON MAIN RES 1/31/01 0.005 3.78E+03 2.35E+02 3.06E+02 26 SPILLWAY ON MAIN RES 2/28/01 0.005 3.63E+03 2.32E+02 3.03E+02 26 SPILLWAY ON MAIN RES 3/31/01 0.005 3.35E+03 2.26E+02 2.99E+02 26 SPILLWAY ON MAIN RES 4/30/01 0.005 3.01 E+03 2.19E+02 2.93E+02 26 SPILLWAY ON MAIN RES 5/31/01 0.005 3.28E+03 2.25E+02 2.98E+02 26 SPILLWAY ON MAIN RES 6/30/01 0.005 3.21 E+03 2.22E+02 2.94E+02 26 SPILLWAY ON MAIN RES 7/31/01 0.005 3.68E+03 2.26E+02 2.91 E+02 26 SPILLWAY ON MAIN RES 8/31/01 0.005 3.73E+03 2.30E+02 2.97E+02 26 SPILLWAY ON MAIN RES 9/30/01 0.005 4.14E+03 2.33E+02 2.93E+02 26 SPILLWAY ON MAIN RES 10/31/01 0.005 7.24E+03 6.54E+02 8.65E+02 26 SPILLWAY ON MAIN RES 11/30/01 0.005 6.37E+03 2.56E+02 2.88E+02 26 SPILLWAY ON MAIN RES 12/31/01 0.005 6.30E+03 2.54E+02 2.87E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 1/31/01 0.005 <LLD 3.06E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 2/28/01 0.005 <LLD 3.01 E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 3/31/01 0.005 <LLD 2.99E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 4/30/01 0.005 <LLD 2.94E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 5/31/01 0.005 <LLD 2.96E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 6/30/01 0.005 <LLD 2.95E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 7/31/01 0.005 <LLD 2.91 E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 8/31/01 0.005 <LLD 2.98E+02 38 CAPE FEAR PLANT tNTAKE - CONTROL 9/30/01 0.005 <LLD 2.93E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 10/31/01 0.005 <LLD 3.OOE+02 38 CAPE FEAR PLANT INTAKE - CONTROL 11/30/01 0.005 <LLD 2.88E+02 38 CAPE FEAR PLANT INTAKE - CONTROL 12/31/01 0.005 <LLD 2.92E+02 Page I of 2

HNP RadiologicalEnvironmentalMonitoringAnalysis Report Media Type: Surface Water Quantity: Liters Analysis: Tritium Concentration(Activity): pCi/Liter Sample Point Sample Date Quantity Activity 2 Sigma Error LLD 40 LILLINGTON - CAPE FEAR RIVER 1/31/01 0.005 <LLD 3.07E+02 40 LILLINGTON - CAPE FEAR RIVER 2/28/01 0.005 <LLD 3.03E+02 40 LILLINGTON - CAPE FEAR RIVER 3/31/01 0.005 <LLD 2.99E+02 40 LILLINGTON - CAPE FEAR RIVER 4/30/01 0.005 <LLD 2.94E+02 40 LILLINGTON - CAPE FEAR RIVER 5/31/01 0.005 <LLD 2.98E+02 40 LILLINGTON - CAPE FEAR RIVER 6/30/01 0.005 <LLD 2.95E+02 40 LILLINGTON - CAPE FEAR RIVER 7/31/01 0.005 <LLD 2.96E+02 40 LILLINGTON - CAPE FEAR RIVER 8/31/01 0.005 <LLD 2.98E+02 40 LILLINGTON - CAPE FEAR RIVER 9/30/01 0.005 <LLD 2.94E+02 40 LILLINGTON - CAPE FEAR RIVER 10/31/01 0.005 <LLD 3.02E+02 40 LILLINGTON - CAPE FEAR RIVER 11/30/01 0.005 <LLD 2.88E+02 40 LILLINGTON - CAPE FEAR RIVER 12/31/01 0.005 <LLD 2.91 E+02 Page 2 of2

2001 HNP A Progress Energy Company Radiological Environmental Monitoring Gamma Isotopic Report Comments 0 NO-ACT refers to no detectable gamma activity being present in the samples. Refer to Table 6 for typical gamma Lower Limits of Detection for specific nuclides.

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Air Particulate Quantity: CUBIC METERS Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 1 SR 1134AT INT SR 1011 - DIXIE PIPELINE 2/15/01 8013.9 BE-7 7.21E-02 1.511E-02 1 SR 1134 AT INT SR 1011 -DIXIE PIPELINE 5/15/01 7726.5 BE-7 1.14E-01 1.57E-02 1 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 8/15/01 7085.8 BE-7

• 8.71 E-02 1.63E-02 1 SR 1134 AT INT SR 1011 -DIXIE PIPELINE 11/15/01 7414.1 BE-7 8.40E-02 1.13E-02 1 SR 1134 AT INT SR 1011 - DIXIE PIPELINE 11/15/01 7414.1 K-40 1.53E-02 6.63E-03 2 SR 1134 2/15/01 7957.4 BE-7 6.71 E-02 1.41 E-02 2 SR 1134 5/15/01 7645.7 BE-7 9.77E-02 1.63E-02 2 SR 1134 5/15/01 7645.7 K-40 3.45E-02 1.19E-02 2 SR 1134 8/15/01 9887.4 BE-7 8.49E-02 1.16E-02 2 SR 1134 11/15/01 11319.7 BE-7 8.03E-02 9.58E-03 4 NEW HILL NEAR 1ST BAPTIST CH 2/15/01 6713.7 BE-7 8.30E-02 1.64E-02 4 NEW HILL NEAR 1ST BAPTIST CH 5/15/01 6493.5 BE-7 8.88E-02 1.44E-02 4 NEW HILL NEAR 1ST BAPTIST CH 8/15/01 6100.1 BE-7 1.14E-01 2.07E-02 4 NEW HILL NEAR 1ST BAPTIST CH 11/15/01 7011.2 PB-214 3.78E-03 8.50E-04 4 NEW HILL NEAR 1ST BAPTIST CH 11/15/01 7011.2 BI-214 2.1OE-03 7.92E-04 4 NEW HILL NEAR 1ST BAPTIST CH 11/15/01 7011.2 BE-7 9.73E-02 1.11E-02 4 NEW HILL NEAR 1ST BAPTIST CH 11/15/01 7011.2 K-40 7.25E-03 4.77E-03 5 PITTSBORO - CONTROL 2/15/01 7817.5 BE-7 9.07E-02 1.53E-02 5 PITTSBORO - CONTROL 5/15/01 7614.5 K-40 2.50E-02 1.24E-02 5 PITTSBORO - CONTROL 5/15/01 7614.5 BE-7 9.11E-02 1.52E-02 5 PITTSBORO - CONTROL 8/15/01 9339.7 BE-7 9.17E-02 1.68E-02 5 PITTSBORO - CONTROL 8/15/01 9339.7 K-40 2.35E-02 1.14E-02 5 PITTSBORO - CONTROL 11/15/01 10913.3 BE-7 7.61 E-02 9.24E-03 26 SPILLWAY ON MAIN RES 2/15/01 7427.4 BE-7 8.90E-02 1.58E-02 Page 1 of 2

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Air Particulate Quantity: CUBIC METERS Concentration(Activity): pCi/cubic meter Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 26 SPILLWAY ON MAIN RES 5/15/01 6703.6 BE-7 9.41 E-02 1.51 E-02 26 SPILLWAY ON MAIN RES 8/15/01 6446.1 BE-7 9.58E-02 1.50E-02 26 SPILLWAY ON MAIN RES 11/15/01 7619.2 BE-7 8.23E-02 1.07E-02 47 SSW SECTOR 3.4 MI FROM SITE 2/15/01 8017.6 K-40 4.01 E-02 1.30E-02 47 SSW SECTOR 3.4 MI FROM SITE 2/15/01 8017.6 BE-7 8.12E-02 1.48E-02 47 SSW SECTOR 3.4 MI FROM SITE 5/15/01 8674.8 BE-7 1.04E-01 1.44E-02 47 SSW SECTOR 3.4 MI FROM SITE 8/15/01 8375.9 BE-7 8.82E-02 1.54E-02 47 SSW SECTOR 3.4 MI FROM SITE 11/15/01 9117.3 BE-7 8.03E-02 9.61 E-03 Page 2 of 2

1f HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Aquatic Vegetation Quantity: GRAMS (wet)

Concentration(Activity): pCi/gm wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 26 SPILLWAY ON MAIN RES 11/15/01 759.6 CO-60 4.54E-02 1.08E-02 26 SPILLWAY ON MAIN RES 11/15/01 759.6 CO-58 6.71 E-02 1.58E-02 26 SPILLWAY ON MAIN RES 11/15/01 759.6 AC-228 1.04E-01 3.49E-02 26 SPILLWAY ON MAIN RES 11/15/01 759.6 K-40 1.96E+00 2.62E-01 26 SPILLWAY ON MAIN RES 11/15/01 759.6 BE-7 3.82E-01 1.21 E-01 26 SPILLWAY ON MAIN RES 11/15/01 517.8 CO-58 4.21E-02 1.64E-02 26 SPILLWAY ON MAIN RES 11/15/01 517.8 K-40 3.47E+00 4.93E-01 41 SHORELINE OF COOLING TOWER MIXING ZONE 11/15/01 761.7 K-40 2.37E+00 3.03E-01 61 2.5 MI E SECTOR HOLLEMANS XRD BR 11/15/01 536.7 K-40 2.67E+00 4.78E-01 Page I of I

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Bottom Feeder Quantity: GRAMS (wet) Media. Catfish Concentration (Activity): pCi/gm wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 44 SITE VARIES WITHIN HARRIS LAKE 5/10/01 512.3 RA-226 6.98E-01 3.65E-01 44 SITE VARIES WITHIN HARRIS LAKE 5/10/01 512.3 K-40 1.75E+00 5.50E-01 44 SITE VARIES WITHIN HARRIS LAKE 11/15/01 388.7 PB-214 3.06E-01 1.08E-01 44 SITE VARIES WITHIN HARRIS LAKE 11/15/01 388.7 K-40 4.18E+00 1.35E+00 45 SITE VARIES ABOVE BUCKHORN DAM - CONTROL 5/10/01 665.9 K-40 3.70E+00 9.44E-01 45 SITE VARIES ABOVE BUCKHORN DAM - CONTROL 11/15/01 896.5 K-40 2.73E+00 6.82E-01 Page 1 of 1 I

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Bottom Sediment Quantity: GRAMS (dry)

Concentration(Activity): pCi/gm dry Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 52 HARRIS LAKE COOLING TOWER MIXING ZONE 1/23/01 674 TL-208 4.26E-01 1.31 E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 1/23/01 674 PB-212 9.66E-01 1.72E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 1/23/01 674 PB-214 7.63E-01 1.80E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 1/23/01 674 AC-228 9.40E-01 5.25E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 1/23/01 674 CO-60 2.59E+00 2.46E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 1/23/01 674 SB-125 5.54E-01 2.55E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 1/23/01 674 CS-137 4.26E-01 1.42E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 1/23/01 674 AG-108M 4.30E+00 9.46E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 1/23/01 674 K-40 1.02E+01 1.65E+00 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 TL-208 3.20E-01 7.23E-02 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 K-40 1.05E+01 7.80E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 CS-137 4.15E-01 7.49E-02 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 PB-212 8.44E-01 7.75E-02 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 BI-214 7.22E-01 1.32E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 PB-214 5.09E-01 9.88E-02 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 RA-226 1.58E+00 9.42E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 AC-228 8.78E-01 3.20E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 MN-54 1.13E-01 8.48E-02 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 CO-58 1.09E-01 9.52E-02 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 CO-60 9.46E+00 2.16E-01 52 HARRIS LAKE COOLING TOWER MIXING ZONE 7/2/01 601.9 SB-125 6.09E-01 1.73E-01 52 HARRIS LAKE COOWNG TOWER MIXING ZONE 7/2/01 601.9 BE-7 1.13E+00 4.50E-01 PageI of I

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Broadleaf Vegetation Quantity: GRAMS (wet) Media: Dogwood Concentration(Activity): pCi/gm wet Sample A Point Sample Date__ Quantity Isotope Activity 2 Sigma Error 332.2 PB-212 1.83E-01 5.11 E-02 65 1.36 MI S SECTOR 9/27/01 9/27/01 332.2 TL-208 1.04E-01 3.65E-02 65 1.36 MI S SECTOR 9/27/01 332.2 K-40 4.15E+00 6.OOE-01 65 1.36 MI S SECTOR 9/27/01 332.2 BE-7 1.26E+00 3.60E-01 65 1.36 MI S SECTOR 5/23/01 352.2 K-40 2.76E+00 6.15E-01 66 1.33 MI SSW SECTOR 5/23/01 352.2 BE-7 5.80E-01 2.49E-01 66 1.33 MI SSW SECTOR 6/27/01 323.8 BE-7 1.53E+00 2.65E-01 66 1.33 MI SSW SECTOR 6/27/01 323.8 K-40 3.30E+00 5.30E-01 66 1.33 MI SSW SECTOR 6/27/01 323.8 TL-208 3.25E-02 2.74E-02 66 1.33 MI SSW SECTOR 7/31/01 353.7 K-40 3.32E+00 6.05E-01 66 1.33 MI SSW SECTOR 7/31/01 353.7 BE-7 1.85E+00 2.84E-01 66 1.33 MI SSW SECTOR 8/29/01 413.3 K-40 3.09E+00 5.70E-01 66 1.33 MI SSW SECTOR 8/29/01 413.3 BI-214 5.00E-02 4.75E-02 66 1.33 MI SSW SECTOR 8/29/01 413.3 BE-7 2.59E+00 2.98E-01 66 1.33 MI SSW SECTOR 9/27/01 353.6 K-40 3.94E+00 5.22E-01 66 1.33 MI SSW SECTOR 9/27/01 353.6 BE-7 9.66E-01 2.54E-01 66 1.33 MI SSW SECTOR Page I of)I

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: BroadleafVegetation Quantity: GRAMS (wet) Media: Maple Concentration(Activity): pCi/gm wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 65 1.36 MI S SECTOR 5/23/01 307.9 K-40 1.99E+00 5.72E-01 65 1.36 MI S SECTOR 6/27/01 374.3 BE-7 1.28E+00 2.58E-01 65 1.36 MI S SECTOR 6/27/01 374.3 K-40 3.48E+00 5.91 E-01 65 1.36 MI S SECTOR 6/27/01 374.3 TL-208 3.70E-02 3.53E-02 65 1.36 MI S SECTOR 6/27/01 374.3 PB-212 6.70E-02 4.14E-02 65 1.36 MI S SECTOR 7/31/01 435.2 PB-212 1.87E-01 3.93E-02 65 1.36 MI S SECTOR 7/31/01 435.2 TL-208 6.06E-02 2.83E-02 65 1.36 MI S SECTOR 7/31/01 435.2 K-40 2.88E+00 4.28E-01 65 1.36 MI S SECTOR 7/31/01 435.2 BE-7 1.21 E+00 1.97E-01 65 1.36 MI S SECTOR 8/29/01 342.6 K-40 2.88E+00 5.83E-01 65 1.36 MI S SECTOR 8/29/01 342.6 BE-7 1.69E+00 3.05E-01 65 1.36 MI S SECTOR 9/27/01 426.5 K-40 2.26E+00 4.52E-01 65 1.36 MI S SECTOR 9/27/01 426.5 BE-7 1.05E+00 2.37E-01 66 1.33 MI SSW SECTOR 5/23/01 352.9 BE-7 4.96E-01 2.11E-01 66 1.33 MI SSW SECTOR 5/23/01 352.9 K-40 2.86E+00 5.76E-01 66 1.33 MI SSW SECTOR 6/27/01 280.3 BI-214 6.85E-02 6.41 E-02 66 1.33 MI SSW SECTOR 6/27/01 280.3 PB-212 5.34E-02 4.44E-02 66 1.33 MI SSW SECTOR 6/27/01 280.3 TL-208 3.54E-02 3.06E-02 66 1.33 MI SSW SECTOR 6/27/01 280.3 BE-7 1.04E+00 2.67E-01 66 1.33 MI SSW SECTOR 6/27/01 280.3 K-40 3.78E+00 7.OOE-01 66 1.33 MI SSW SECTOR 7/31/01 397.1 K-40 3.84E+00 4.86E-01 66 1.33 MI SSW SECTOR 7/31/01 397.1 TL-208 4.38E-02 2.08E-02 66 1.33 MI SSW SECTOR 7/31/01 397.1 PB-212 T.26E-01 5.52E-02 66 1.33 MI SSW SECTOR 7/31/01 397.1 BE-7 1.01 E+00 2.41 E-01 66 1.33 MI SSW SECTOR 8/29/01 467.5 BE-7 1.88E+00 2.67E-01 66 1.33 MI SSW SECTOR 8/29/01 467.5 K-40 3.64E+00 5.27E-01 PageI1 of 2

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: BroadleafVegetation Quantity: GRAMS (wet) Media: Maple Concentration (Activity): pCi/gm wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma ETrror 66 1.33 MI SSW SECTOR 8/29/01 467.5 PB-212 5.34E-02 2.99E-02 9/27/01 419.2 CS-137 7.39E-02 3.29E-02 66 1.33 MI SSW SECTOR 9/27/01 419.2 BE-7 1.39E+00 2.11E-01 66 1.33 MI SSW SECTOR 9/27/01 419.2 K-40 1.75E+00 3.87E-01 66 1.33 MI SSW SECTOR 9/27/01 419.2 TL-208 2.78E-02 1.95E-02 66 1.33 MI SSW SECTOR 9/27/01 419.2 BI-214 7.57E-02 4.81 E-02 66 1.33 MI SSW SECTOR 9/27/01 419.2 RA-226 7.32E-01 4.01 E-01 66 1.33 MI SSW SECTOR p

Page 2 of 2

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: BroadleafVegetation Quantity: GRAMS (wet) Media: Sweetgum Concentration(Activity): pCi/gin wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 65 1.36 MI S SECTOR 5/23/01 462.7 K-40 1.63E+00 4.81 E-01 65 1.36 MI S SECTOR 5/23/01 462.7 BE-7 5.98E-01 1.92E-01 65 1.36 MI S SECTOR 6/27/01 529.6 TL-208 5.25E-02 1.74E-02 65 1.36 MI S SECTOR 6/27/01 529.6 PB-212 1.19E-01 3.67E-02 65 1.36 MI S SECTOR 6/27/01 529.6 K-40 3.12E+00 3.99E-01 65 1.36 MI S SECTOR 6/27/01 529.6 BE-7 5.62E-01 1.70E-01 65 1.36 MI S SECTOR 7/31/01 377.8 BE-7 6.33E-01 2.87E-01 65 1.36 MI S SECTOR 7/31/01 377.8 K-40 2.56E+00 5.54E-01 65 1.36 MI S SECTOR 7/31/01 377.8 TL-208 9.33E-02 2.72E-02 65 1.36 MI S SECTOR 7/31/01 377.8 PB-212 2.29E-01 5.40E-02 65 1.36 MI S SECTOR 8/29/01 426.1 K-40 1.67E+00 5.43E-01 65 1.36 MI S SECTOR 8/29/01 426.1 BE-7 8.24E-01 2.28E-01 65 1.36 MI S SECTOR 9/27/01 458.7 BE-7 6.59E-01 1.82E-01 65 1.36 MI S SECTOR 9/27/01 458.7 K-40 1.61 E+00 3.65E-01 65 1.36 MI S SECTOR 9/27/01 458.7 TL-208 7.15E-02 2.60E-02 65 1.36 MI S SECTOR 9/27/01 458.7 PB-212 2.28E-01 3.54E-02 65 1.36 MI S SECTOR 10/31/01 333.3 BE-7 8.66E-01 2.38E-01 65 1.36 MI S SECTOR 10/31/01 333.3 K-40 2.68E+00 5.08E-01 66 1.33 MI SSW SECTOR 5/23/01 409.8 K-40 3.14E+00 5.29E-01 66 1.33 MI SSW SECTOR 5/23/01 409.8 BE-7 5.37E-01 2.48E-01 66 1.33 MI SSW SECTOR 6/27/01 493.4 TL-208 3.57E-02 2.50E-02 66 1.33 MI SSW SECTqR 6/27/01 493.4 K-40 2.31 E+00 4.29E-01 66 1.33 MI SSW SECTOR 6/27/01 493.4 BE-7 1.09E+00 2.84E-01 66 1.33 MI SSW SECTOR 7/31/01 418.6 PB-212 8.80E-02 4.18E-02 66 1.33 MI SSW SECTOR 7/31/01 418.6 K-40 1.77E+00 4.85E-01 66 1.33 MI SSW SECTOR 7/31/01 418.6 BE-7 1.45E+00 2.91 E-01 Page 1 of 2

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: BroadleafVegetation Quantity: GRAMS (wet) Media: Sweetgum Concentration(Activity): pCi/gin wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 451.4 BE-7 1.29E+00 2.45E-01 66 1.33 MI SSW SECTOR 8/29/01 8/29/01 451.4 K-40 3.27E+00 5.01 E-01 66 1.33 MI SSW SECTOR 9/27/01 530.8 BE-7 8.04E-01 1.72E-01 66 1.33 MI SSW SECTOR 9/27/01 530.8 K-40 1.46E+00 3.58E-01 66 1.33 MI SSW SECTOR 9/27/01 530.8 TL-208 5.56E-02 2.51 E-02 66 1.33 MI SSW SECTOR 9/27/01 530.8 PB-212 1.11E-01 3.45E-02 66 1.33 MI SSW SECTOR 10/31/01 362.7 K-40 2.17E+00 5.25E-01 66 1.33 MI SSW SECTOR 10/31/01 362.7 BE-7 8.54E-01 2.75E-01 66 1.33 MI SSW SECTOR Page 2 of2

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Drinking Water Quantity: Liters Concentration(Activity): pCi/L Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error CAPE FEAR PLANT INTAKE - CONTROL 1/31/01 1.0 NO-ACT 2/28/01 1.0 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 3/31/01 1.0 K-40 1.25E+02 4.63E+01 CAPE FEAR PLANT INTAKE - CONTROL 4/30/01 1.0 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 5/31/01 1.0 K-40 1.52E+02 5.36E+01 CAPE FEAR PLANT INTAKE - CONTROL 6/30/01 1.0 K-40 8.77E+01 3.94E+01 CAPE FEAR PLANT INTAKE - CONTROL 7/31/01 1.0 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 8/31/01 1.0 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 9/30/01 1.0 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 10/31/01 1.0 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 11/30/01 1.0 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 12/31/01 1.0 K-40 1.48E+02 5.76E+01 CAPE FEAR PLANT INTAKE - CONTROL 1/31/01 1.0 NO-ACT LILLINGTON - CAPE FEAR RIVER 2/28/01 1.0 NO-ACT LILLINGTON - CAPE FEAR RIVER 3/31/01 1.0 NO-ACT LILLINGTON - CAPE FEAR RIVER 4/30/01 1.0 NO-ACT LILLINGTON - CAPE FEAR RIVER 5/31/01 1.0 NO-ACT LILLINGTON - CAPE FEAR RIVER 6/30/01 1.0 NO-ACT LILLINGTON - CAPE FEAR RIVER 7/31/01 1.0 NO-ACT LILLINGTON - CAPE FEAR RIVER 8/31/01 1.0 K-40 3.17E+02 9.OOE+01 LILLINGTON - CAPE FEAR RIVER 9/30/01 1.0 K-40 1.84E+02 5.56E+01 LILLINGTON - CAPE FEAR RIVER 9/30/01 1.0 RA-226 9.75E+01 8.14E+01 LILLINGTON - CAPE FEAR RIVER 10/31/01 1.0 NO-ACT LILLINGTON - CAPE FEAR RIVER 11/30/01 1.0 K-40 1.44E+02 5.OOE+01 LILLINGTON - CAPE FEAR RIVER 12/31/01 1.0 NO-ACT LILLINGTON - CAPE FEAR RIVER 1/31/01 1.0 NO-ACT WATER TREATMENT BLDG AT HARRIS PLANT PageI of 2

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Drinking Water Quantity: Liters Concentration(Activity): pCi/L Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 51 WATER TREATMENT BLDG AT HARRIS PLANT 2/28/01 1.0 NO-ACT 51 WATER TREATMENT BLDG AT HARRIS PLANT 3/31/01 1.0 K-40 3.51 E+02 7.1OE+01 51 WATER TREATMENT BLDG AT HARRIS PLANT 4/30/01 1.0 K-40 2.85E+02 7.06E+01 51 WATER TREATMENT BLDG AT HARRIS PLANT 5/31/01 1.0 NO-ACT 51 WATER TREATMENT BLDG AT HARRIS PLANT 6/30/01 1.0 K-40 3.50E+02 7.11 E+01 51 WATER TREATMENT BLDG AT HARRIS PLANT 7/31/01 1.0 K-40 4.84E+02 9.39E+01 51 WATER TREATMENT BLDG AT HARRIS PLANT 8/31/01 1.0 NO-ACT 51 WATER TREATMENT BLDG AT HARRIS PLANT 9/30/01 1.0 RA-226 5.64E+01 4.70E+01 51 WATER TREATMENT BLDG AT HARRIS PLANT 9/30/01 1.0 PB-212 3.59E+00 3.19E+00 51 WATER TREATMENT BLDG AT HARRIS PLANT 10/31/01 1.0 NO-ACT 51 WATER TREATMENT BLDG AT HARRIS PLANT 11/30/01 1.0 K-40 2.90E+02 9.51 E+01 51 WATER TREATMENT BLDG AT HARRIS PLANT 12131/01 1.0 NO-ACT Page 2 of 2

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Food Crop Quantity: GRAMS (wet) Media: Cabbage Concentration(Activity): pCi/gm wet Sample "1

Point Sample Date Quantity Isotope Activity 2 Sigma Error 5 PITTSBORO - CONTROL 6/26/01 551.6 PB-212 4.31 E-02 2.35E-02 5 PITTSBORO - CONTROL 6/26/01 551.6 K-40 3.1 OE+00 3.80E-01 5 PITTS-BORO - CONTROL 6/26/01 551.6 BE-7 1.95E-01 1.29E-01 5 PITTSBORO - CONTROL 7/25/01 630.1 K-40 2.26E+00 3.08E-01 5 PITTSBORO - CONTROL 8/23/01 508.6 K-40 2.91 E+00 3.85E-01 5 PITTSBORO - CONTROL 8/23/01 508.6 BE-7 1.67E-01 9.09E-02 55 RD 1167 1.7 MI NNW (GOODWIN) 6/26/01 551.1 TL-208 1.92E-02 1.44E-02 55 RD 1167 1.7 MI NNW (GOODWIN) 6/26/01 551.1 K-40 4.03E+00 4.47E-01 55 RD 1167 1.7 MI NNW (GOODWIN) 7/25/01 487.9 BI-214 7.19E-02 3.88E-02 55 RD 1167 1.7 MI NNW (GOODWIN) 7/25/01 487.9 TL-208 4.11E-02 3.08E-02 55 RD 1167 1.7 MI NNW (GOODWIN) 7/25/01 487.9 K-40 4.24E+00 5.23E-01 Page I of I

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HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Food Crop Quantity: GRAMS (wet) Media: Collards Concentration(Activity): pCi/gm wet Sample Point q

Sample Date Quantity Isotope Activity 2 Sigma Error 12/13/01 529 RA-226 3.04E-01 2.63E-01 5 PITTSBORO - CONTROL 12/13/01 529 PB-212 2.04E-01 3.15E-02 5 PITTSBORO - CONTROL 12/13/01 529 TL-208 5.83E-02 1.90E-02 5 PITTSBORO - CONTROL 12/13/01 529 K-40 2.14E+00 3.53E-01 5 PITTSBORO - CONTROL 1/17/01 591 K-40 1.99E+00 3.75E-01 55 RD 1167 1.7 MI NNW (GOODWIN) 2/27/01 543.8 K-40 3.41 E+00 4.45E-01 55 RD 1167 1.7 MI NNW (GOODWIN) 9/26/01 499.9 K-40 6.65E+00 6.58E-01 55 RD 1167 1.7 MI NNW (GOODWIN) 10/25/01 632.9 TL-208 3.92E-02 1.43E-02 55 RD 1167 1.7 MI NNW (GOODWIN) 10/25/01 632.9 K-40 4.16E+00 4.29E-01 55 RD 1167 1.7 MI NNW (GOODWIN) 11/27/01 529.8 PB-212 3.93E-02 2.32E-02 55 RD 1167 1.7 MI NNW (GOODWIN) 11/27/01 529.8 K-40 2.56E+00 3.70E-01 55 RD 1167 1.7 MI NNW (GOODWIN) 12/13/01 530.1 TL-208 2.73E-02 1.74E-02 55 RD 1167 1.7 MI NNW (GOODWIN)

RD 1167 1.7 MI NNW (GOODWIN) 12/13/01 530.1 K-40 2.41 E+00 3.70E-01 55 12/13/01 530.1 BE-7 2.59E-01 1.60E-01 55 RD 1167 1.7 MI NNW (GOODWIN)

Page I of I

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Food Crop Quantity: GRAMS (wet) Media: Cucumbers Concentration(Activity): pCi/gm wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma EError 1.58E-02 PITTSBORO - CONTROL 8/23/01 625.6 TL-208 1.80E-02 1.58E-02 5

8/23/01 625.6 K-40 1.50E+00 4.05E-01 5 PITTSBORO - CONTROL Page I of I

11 HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Food Crop Quantity: GRAMS (wet) Media: Eggplant Concentration (Activity): pCi/gm wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 5 PITTSBORO - CONTROL 6/26/01 535.5 K-40 2.56E+00 3.86E-01 5 PITTSBORO - CONTROL 10/25/01 502.1 K-40 2.42E+00 4.77E-01 PageIof I

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HNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report Media Type: Food Crop Quantity: GRAMS (wet) Media: Squash Concentration(Activity): pCi/gin wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 5 PITTSBORO - CONTROL 7/25/01 688 K-40 1.90E+00 3.43E-01 54 RD 11891.7 MI NNE (WILKINS OR MORRIS) 7/25/01 735.8 K-40 1.95E+00 3.14E-01 Page 1 of I

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HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Food Crop Quantity: GRAMS (wet) Media. Tomatoes Concentration(Activity): pCi/gin wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 2.49E-01 5 PITTSBORO - CONTROL 7/25/01 1109.4 K-40 1.98E+00 8/23/01 885.8 K-40 2.66E+00 3.02E-01 5 PITTSBORO - CONTROL 7/25/01 955.1 K-40 1.67E+00 2.36E-01 54 RD 1189 1.7 MI NNE (WILKINS OR MORRIS) 7/25/01 1064.8 RA-226 2.09E-01 2.02E-01 55 RD 11671.7 MI NNW (GOODWIN) 7/25/01 1064.8 K-40 2.78E+00 2.60E-01 55 RD 11671.7 MI NNW (GOODWIN) 8/23/01 801.1 K-40 2.23E+00 2.81 E-01 55 RD 11671.7 MI NNW (GOODWIN)

Page I of I

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Food Crop Quantity: GRAMS (wet) Media: Turnips and Greens Concentration(Activity): pCi/gm wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 512.1 PB-212 1.44E-01 2.44E-02 5 PITTSBORO - CONTROL 10/25/01 10/25/01 512.1 TL-208 6.21 E-02 1.97E-02 5 PITTSBORO - CONTROL 10/25/01 512.1 K-40 4.67E+00 4.90E-01 5 PITTSBORO - CONTROL 11/27/01 508.5 PB-212 8.15E-02 3.24E-02 5 PITTSBORO - CONTROL 11/27/01 508.5 TL-208 3.44E-02 2.31 E-02 5 PITTSBORO - CONTROL 11/27/01 508.5 K-40 "; 3.63E+00 4.72E-01 5 PITTSBORO - CONTROL 11/27/01 508.5 BE-7 2.07E-01 1.44E-01 5 PITTSBORO - CONTROL 12/13/01 527.5 TL-208 4.41 E-02 2.18E-02 5 PITTSBORO - CONTROL 5 12/13/01 527.5 K-40 4.15E+00 5.27E-01 PITTSBORO - CONTROL 5 12/13/01 527.5 BE-7 3.10E-01 2.06E-01 PITTSBORO - CONTROL 54 10/25/01 571.1 K-40 3.48E+00 4.37E-01 RD 1189 1.7 MI NNE (WILKINS OR MORRIS) 54 11/27/01 579.3 K-40 3.36E+00 4.15E-01 RD 1189 1.7 MI NNE (WILKINS OR MORRIS) 54 12/13/01 480.9 K-40 2.90E+00 3.85E-01 RD 1189 1.7 MI NNE (WILKINS OR MORRIS) 54 12/13/01 480.9 BE-7 2.48E-01 1.88E-01 RD 1189 1.7 MI NNE (WILKINS OR MORRIS) 55 1/17/01 567.7 K-40 1.89E+00 4.19E-01 RD 1167 1.7 MI NNW (GOODWIN) t Page 1 of I

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Free Swimmer Quantity: GRAMS (wet) Media: Largemouth Bass Concentration(Activity): pCi/gm wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 44 SITE VARIES WITHIN HARRIS LAKE 5/10/01 502.7 K-40 3.02E+00 8.31 E-01 44 SITE VARIES WITHIN HARRIS LAKE 11/15/01 665.2 K-40 2.76E+00 8.97E-01 45 SITE VARIES ABOVE BUCKHORN DAM - CONTROL 5/10/01 532.2 K-40 2.27E+00 6.41 E-01 45 SITE VARIES ABOVE BUCKHORN DAM - CONTROL 11/15/01 442.4 K-40 4.64E+00 1.29E+00 Page I ofI

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HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Free Swimmer Quantity: GRAMS (wet) Media: Sunfish Concentration(Activity): pCi/gm wet Sample Point Sample Date Quantity Isotope Activity 2 Sigma ETrror 506.6 K-40 1.26E+00 5.89E-01 SITE VARIES WITHIN HARRIS LAKE 5/10/01 506.6 K-40 1.26E+00 5.89E-01 44 2.98E+00 1.10E+00 11/15/01 442.9 44 SITE VARIES WITHIN HARRIS LAKE K-40 510.4 2.80E+00 8.OOE-01 5/10/01 K-40 45 SITE VARIES ABOVE BUCKHORN DAM - CONTROL 9.11E-01 11/15/01 525.4 K-40 2.40E+00 45 SITE VARIES ABOVE BUCKHORN DAM - CONTROL PageI of 1

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type. Groundwater Quantity: Liters Concentration(Activity): pCi/L Sample Point Sample Date Quantity Isotope Activity 2 Sigma Ee7rror DEEP WELL NEAR DIABASE DIKES 2/21/01 NO-ACT DEEP WELL NEAR DIABASE DIKES 5/23/01 NO-ACT DEEP WELL NEAR DIABASE DIKES 8/29/01 NO-ACT DEEP WELL NEAR DIABASE DIKES 11/27/01 NO-ACT 0.4 MI SSW SECTOR N BANK ESW INTAKE 2/21/01 NO-ACT 0.4 MI SSW SECTOR N BANK ESW INTAKE 5/23/01 NO-ACT 0.4 MI SSW SECTOR N BANK ESW INTAKE 8/29/01 K-40 6.84E+01 5.49E+01 0.4 MI SSW SECTOR N BANK ESW INTAKE 11/27/01 K-40 1.70E+02 6.41 E+01 0.5 MI WSW SECTOR N BANK ESW INTAKE 2/21/01 NO-ACT 0.5 MI WSW SECTOR N BANK ESW INTAKE 6/4/01 NO-ACT 0.5 MI WSW SECTOR N BANK ESW INTAKE 8/29/01 NO-ACT 0.5 MI WSW SECTOR N BANK ESW INTAKE 11/27/01 K-40 3.22E+02 7.54E+01 0.5 MI NNE SECTOR (NEAR CONSTRUCTION RD) 2/21/01 NO-ACT 0.5 MI NNE SECTOR (NEAR CONSTRUCTION RD) 5/23/01 NO-ACT 0.5 MI NNE SECTOR (NEAR CONSTRUCTION RD) 8/29/01 K-40 2.47E+02 6.19E+01 0.5 MI NNE SECTOR (NEAR CONSTRUCTION RD) 11/27/01 NO-ACT 0.5 MI ESE SECTOR W BANK OF THOMAS CREEK 2/21/01 NO-ACT 0.5 MI ESE SECTOR W BANK OF THOMAS CREEK 5/23/01 NO-ACT 0.5 MI ESE SECTOR W BANK OF THOMAS CREEK 8/29/01 NO-ACT 0.5 MI ESE SECTOR W BANK OF THOMAS CREEK 11/27/01 NO-ACT 1"

Page 1 of I

HNP RadiologicalEnvironmental Monitoring Gamma Isotopic Report Media Type: Milk Quantity. Liters Concentration(Activity): pCiIL Sample Point Sample Date Quantity Isotope Activity 2 Sigma EError PITTSBORO - CONTROL 1/2/01 K-40 1.52E+03 1.96E+02 PITTSBORO - CONTROL 1/15/01 K-40 1.44E+03 2.04E+02 PITTSBORO - CONTROL 2/5/01 K-40 1.38E+03 1.99E+02 PIT-SBORO - CONTROL 2/19/01 K-40 1.49E+03 1.91 E+02 PITTSBORO - CONTROL 3/5/01 K-40 1.34E+03 1.98E+02 PITTSBORO - CONTROL 3/19/01 K-40 1.38E+03 1.71 E+02 PITTSBORO - CONTROL 3/19/01 PB-212 1.98E+01 1.09E+01 PITTSBORO - CONTROL 4/2/01 K-40 1.55E+03 2.10E+02 PITTSBORO - CONTROL 4/16/01 K-40 2.04E+03 1.97E+02 PITTSBORO - CONTROL 5/8/01 K-40 1.42E+03 1.98E+02 PITTSBORO - CONTROL 5/21/01 K-40 1.29E+03 2.02E+02 PITTSBORO - CONTROL 6/4/01 K-40 1.63E+03 1.80E+02 PITTSBORO - CONTROL 6/18/01 K-40 1.53E+03 1.98E+02 PITTSBORO - CONTROL 7/2/01 K-40 1.17E+03 2.03E+02 PITTSBORO - CONTROL 7/16/01 K-40 1.80E+03 1.89E+02 PITTSBORO - CONTROL 8/6/01 K-40 2.23E+03 2.00E+02 PITTSBORO - CONTROL 8/20/01 K-40 1.75E+03 1.65E+02 PITTSBORO - CONTROL 9/4/01 K-40 1.28E+03 1.96E+02 PITTSBORO - CONTROL 9/17/01 K-40 1.87E+03 1.93E+02 PITTSBORO - CONTROL 10/1/01 K-40 1.00E+03 2.03E+02 PITTSBORO - CONTROL 10/1/01 BI-214 2.82E+01 2.05E+01 PITTSBORO - CONTRIOL 10/15/01 K-40 1.28E+03 2.05E+02 PITTSBORO - CONTROL 10/15/01 BI-214 2.96E+01 1.89E+01 PITTSBORO - CONTROL 11/12/01 K-40 1.36E+03 2.03E+02 PITTSBORO - CONTROL 11/12/01 PB-212 1.37E+01 1.05E+01 PITTSBORO - CONTROL 11/12/01 BI-214 3.55E+01 2.00E+01 Page 1 of 2

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Milk Quantity: Liters Concentration(Activity): pCi/L Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 5 PITTSBORO - CONTROL 11/19/01 1 K-40 1.36E+03 1.90E+02 1

5 PITTSBORO - CONTROL 12/3/01 K-40 1.48E+03 2.07E+02 1

5 PITTSBORO - CONTROL 12/17/01 K-40 1.29E+03 2.OOE+02 Page 2 of 2

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HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Shoreline Sediment Quantity: GRAMS (dry)

Concentration (Activity): pCi/gm dry Sample Point Sample Date Quantity Isotope Activity 2 Sigma Error 26 SPILLWAY ON MAIN RES 1/23/01 1466.3 TL-208 9.29E-02 3.86E-02 26 SPILLWAY ON MAIN RES 1/23/01 1466.3 PB-214 2.04E-01 8.15E-02 26 SPILLWAY ON MAIN RES 1/23/01 1466.3 RA-226 9.49E-01 8.15E-01 26 SPILLWAY ON MAIN RES 1/23/01 1466.3 K-40 1.19E+01 1.05E+00 26 SPILLWAY ON MAIN RES 7/2/01 1127.3 PB-212 2.06E-01 7.65E-02 26 SPILLWAY ON MAIN RES 7/2/01 1127.3 TL-208 8.13E-02 3.91 E-02 26 SPILLWAY ON MAIN RES 7/2/01 1127.3 PB-214 1.92E-01 9.67E-02 26 SPILLWAY ON MAIN RES 7/2/01 1127.3 AC-228 3.18E-01 1.85E-01 26 SPILLWAY ON MAIN RES 7/2/01 1127.3 K-40 9.96E+00 1.06E+00 41 SHORELINE OF COOLING TOWER MIXING ZONE 1/23/01 1618.5 RA-226 4.07E-01 3.70E-01 41 SHORELINE OF COOLING TOWER MIXING ZONE 1/23/01 1618.5 PB-214 2.13E-01 7.58E-02 41 SHORELINE OF COOLING TOWER MIXING ZONE 1/23/01 1618.5 K-40 1.06E+01 9.20E-01 41 SHORELINE OF COOLING TOWER MIXING ZONE 7/2/01 1221 AC-228 2.95E-01 1.49E-01 41 SHORELINE OF COOLING TOWER MIXING ZONE 7/2/01 1221 K-40 1.58E+01 1.26E+00 41 SHORELINE OF COOLING TOWER MIXING ZONE 7/2/01 1221 TL-208 1.26E-01 4.16E-02 41 SHORELINE OF COOLING TOWER MIXING ZONE 7/2/01 1221 PB-212 3.06E-01 5.43E-02 41 SHORELINE OF COOLING TOWER MIXING ZONE 7/2/01 1221 PB-214 2.34E-01 9.57E-02 Page 1 of I

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type: Surface Water Quantity: Liters Concentration (Activity): pCi/L Sample Point Sample Date Quantity Isotope' Activity 2 Sigma Error NO-ACT SPILLWAY ON MAIN RES 1/31/01 NO-ACT 2128/01 NO-ACT SPILLWAY ON MAIN RES 3/31/01 PB-212 3.39E+00 SPILLWAY ON MAIN RES 6.34E+00 4/30/01 NO-ACT SPILLWAY ON MAIN RES 5/31/01 NO-ACT SPILLWAY ON MAIN RES 6/30/01 NO-ACT SPILLWAY ON MAIN RES K-40 5.75E+01 5.12E+01 7/31/01 SPILLWAY ON MAIN RES K-40 2.11E+02 4.57E+01 8/31/01 SPILLWAY ON MAIN RES 9/30/01 NO-ACT SPILLWAY ON MAIN RES 10/31/01 NO-ACT SPILLWAY ON MAIN RES PB-212 5.13E+00 3.07E+00 11/30/01 SPILLWAY ON MAIN RES 11/30/01 RA-226 6.89E+01 3.29E+01 SPILLWAY ON MAIN RES 12/31/01 NO-ACT SPILLWAY ON MAIN RES 1/31/01 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 2/28/01 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 3/31/01 K-40 1.25E+02 4.63E+01 CAPE FEAR PLANT INTAKE - CONTROL 4/30/01 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL K-40 1.52E+02 5.36E+01 5/31/01 CAPE FEAR PLANT INTAKE - CONTROL K-40 8.77E+01 3.94E+01 6/30/01 CAPE FEAR PLANT INTAKE - CONTROL 7/31/01 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 8/31/01 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 9/30/01 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 10/31/01 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL 11/30/01 NO-ACT CAPE FEAR PLANT INTAKE - CONTROL K-40 1.48E+02 5.76E+01 12/31/01 CAPE FEAR PLANT INTAKE - CONTROL 1/31/01 NO-ACT LILLINGTON - CAPE FEAR RIVER Page 1 of 2

HNP RadiologicalEnvironmentalMonitoring Gamma Isotopic Report Media Type. Surface Water Quantity: Liters Concentration(Activity): pCi/L Sample Point Sample Date Quantity Isotope Activity 2 Sigma EError 40 LILLINGTON - CAPE FEAR RIVER 2/28/01 1 NO-ACT 3/31/01 1 NO-ACT 40 LILLINGTON - CAPE FEAR RIVER 4/30/01 1 NO-ACT 40 LILLINGTON - CAPE FEAR RIVER 5/31/01 1 NO-ACT 40 LILLINGTON - CAPE FEAR RIVER 6/30/01 1 NO-ACT 40 LILLINGTON - CAPE FEAR RIVER 7/31/01 1 NO-ACT 40 LILLINGTON - CAPE FEAR RIVER 8/31/01 1 K-40 40 LILLINGTON - CAPE FEAR RIVER 3.17E+02 9.OOE+01 9/30/01 1 K-40 1.84E+02 5.56E+01 40 LILLINGTON - CAPE FEAR RIVER 9/30/01 RA-226 9.75E+01 8.14E+01 40 LILLINGTON - CAPE FEAR RIVER 10/31/01 NO-ACT 40 LILLINGTON - CAPE FEAR RIVER 11/30/01 K-40 1.44E+02 5.OOE+01 40 LILLINGTON - CAPE FEAR RIVER LILLINGTON - CAPE FEAR RIVER 12/31/01 NO-ACT 40 Page 2 of 2