ML18016A927
| ML18016A927 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/31/1998 |
| From: | Alexander D CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HNP-99-075, HNP-99-75, NUDOCS 9905040319 | |
| Download: ML18016A927 (132) | |
Text
RADIOLOGICAL ENVIRONMENTALOPERATING REPORT 199S HARRIS NUCLEAR PLANT CAROLINAPOWER 4 LIGHT
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RADIOLOGICAL ENVIRONMENTALOPERATING REPORT 1998 HARRIS NUCLEAR PLANT CAROLINAPOWER a LIGHT
Harris Energy & Environmental Center Carolina Power & Light Company New Hill, North Carolina RADIOLOGICALENVIRONMENTALOPERATING REPORT rOR THE SHEARON HARRIS NUCLEAR POWER PLANT JANUARY 1 THROUGH DECEMBER 31, 1998 Prepared by:
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Table of Contents List of Figures List of Tables nl Executive Summary Introduction to Nuclear Operations 2 Benefits of Nuclear Power 2 Radiation and Radioactivity 3 Radiation Interaction with Matter 6 Radiation Quantities and Units of Measure 7 Sources of Radiation 8 Health Effects of Radiation 10 General Health Risk -, 11 Nuclear Power Plant Operation 12 Plants Systems 14 Reactor Safety 1S Radiological Environmental Monitoring Program 19 Purpose and Requirements for the Radiological Monitoring Program 19 General Site Description 20 Radiological Monitoring Program Quality Assurance 21 Radiological Monitoring Program General Description 22 Summary of Radiological Monitoring Program 27 Interpretations and Conclusions 32 Missed Samples and Analyses 37 Analytical Procedures 39 Land-Use Census Purpose of the Land-Use Census 44 Methodology 44 1998 Land-Use Census Results 45 References 47
Figure Page CP&L Service Area 1998 Energy Sources The Atom Radioactive Decay Ionization Radiation Ranges &: Shielding Source of Radiation Dose (BIER V)
Man-Made Radiation (BIER V)
Nuclear Fission 10 Nuclear Fuel Cycle 13 Fuel Pellets, Rods dk Assemblies Major Plant Systems for the Pressurized Water Reactor 14 13 Reactor Vessel 15 Primary Containment Structure 15 Location of Harris Plant 20 Radiological Sampling Locations (Distant from Plant) 23 Radiological Sampling Locations (Nearest Plant)
Plot of Air Particulate Gross Beta Activity (Location 1) 49 19 Plot of Air Particulate Gross Beta Activity (Location 2) 50 20 Plot of Air Particulate Gross Beta Activity (Location 4)
Plot of Air Particulate Gross Beta Activity (Location 26) 52 22 Plot of Air Particulate Gross Beta Activity (Location 47) 53 23 Plot of Drinking Water Gross Beta Activity (Location 40) 54 24 Plot of Surface Water Gross Beta Activity (Location 26) 55 25 Plot of Surface Water Tritium Activity (Location 26 and 40) 26 Plot of TLD Averages for Inner and Outer Rings 57
Table 1 Quality I<'actors for Various Radiations 2 Reduction In Average Life Expectancy 3 Media Used to Assess Exposure Pathways to Man 22 4 Radiological Monitoring Sampling Locations 25 5 Radiological Environmental Monitoring Program Data Summary 28 6 Typical Lower Limits of Detection (a priori) Gamma Spectrometry 42 7 Land-Use Census Comparison (1997-1998) 46
The Harris Nuclear Plant is operated by Carolina Power & Light Company under a license granted by the Nuclear Regulatory Commission. Provisions of the Nuclear Regulatory Commission's Regulatory Guide 4.8, Harris Nuclear Plant Technical Specifications, and the Harris Nuclear Plant Offsite Dose Calculation Manual establish the requirements of the Radiological Environmental Monitoring Program. This report provides the results of the Radiological Environmental Monitoring program from January 1, 1998 through December 31, 1998.
The Radiological Environmental Monitoring program was established in 1982. Radiation and radioactivity in various environmental media have been monitored for more than 17 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 monitoring results are similar to all the past years where no I-131 concentrations were detected.
Terrestrial vegetation includes various crops collected during a growing season.
Aquatic organism monitoring includes fish and benthic organisms.
Surface (and drinking) water results indicate no detectable gamma-emitting radionuclides or I-131.
Surface water results from Harris Lake show the presence of tritium, which is attributed to plant operation.
External radiation dose showed no measurable change from pre-operational data.
The continued operation of the Harris Nuclear Plant has not significantly contributed radiation or the presence of radioactivity in the environmental media monitored. The measured concentrations of radioactivity and radiation are well within applicable regulatory limits.
~ INTRODUCTION TO NUCLEAR OPERATIONS Carolina Power & Light Company (CP&L) operates an integrated electrical system serving more than one million customers in North Carolina and South Carolina. A system map is provided (Figure 81) 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 3,500,000 Figure 1: CP&L SERVICE AREA people.
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 ~coal natural gas and hydro-power are in limited supply.
Nuclear energy is a vital component in a diversified energy mix. In 1998 nuclear energy supplied 46.0%
of CP&L's total electrical generation. This nuclear Nuclear component was generated from four units including Coal the Harris Nuclear Plant. The remaining energy Q Oil &. Natural Gas sources were primarily from coal-fired generation, Hydro Power and a very small contribution from oil, natural gas and hydro-power.
Figure 2: 1998 ENERGY SOURCES 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:
~ The fuel is uranium which is relatively jo~zozim when compared with the fuels of coal, natural gas, and fuel oil.
~ Emissions from nuclear stations do ~ 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 urbani7M air quality. Finally, carbon dioxide is a significant green house gas.
~ Nuclear energy is zing;. 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.
RADIATIONAND RADIOACTIVITY The Atom Allmatter 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 is positively 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 cluster o referred to as the nucleus. (The term nuclear refers to this nucleus.) Nearly all the mass of the atom is found Figure 3i The Atom 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 can not be decomposed in any chemical reaction are known as elements.
Hydrogen, oxygen, iron, chlorine, and uranium are examples of elements. The atoms of such
Hydrogen, oxygen, iron, chlorine, and uranium are examples of elements. The atoms of such elements differ in the number of protons (also know as the atomic number) in their nucleus. For example the number of protons in each example above is 1 for hydrogen, 8 for oxygen, 26 for iron, 17 for chlorine, and 92 for uranium. The number of neutrons in the nucleus may vary in atoms of the same element. Atoms that contain the same number of protons but a different number of neutrons are referred to as isotopes of that element. An example is the element hydrogen which has three isotopes one with no neutrons, a second with one neutron, an the 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 ifunhindered. 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 inde 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
~ ~
1/2 contributors to background radiation levels. These are addressed in greater detail later.
I/4 The rate at which atoms undergo radioactive decay l/8 varies greatly. A common expression of the l/16 tendency for radioactive decay is the half-life 0 14 0 280 420 560 700 associated with a p articular isoto p e. The half-life is Time. davs the amount of time required for one-half'of the Figure 4: Radioactive Decay number of atoms for an isotope to experience radioactive decay. The longer the half-life the less likely an atom will experience radioactive decay in a fixed time interval. Half-lives vary from extemely small fractions of a second ( billionths) to millions of years. Figure 4 illustrates an isotope with a 140-day half-life. Note that the activity decreases by half in 140 days, and then by half again the next 140 days and so on.
RADIATIONINTERACTION 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 particie or photon of radiation. One of the most common ways energy is dissipated is ionization. As KJKCTEO we discussed earlier this results in the creation of a positively ELEC tAON 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.
Radiation Ranges Figure 5: Ionization 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 I
a positive charge of two (two protons). The alpha particle is the slowest of the radiations we willreview with a speed of no more than 20,000 miles per second.,',.""--"'- PJ The alpha leaves it's energy in a short distance characterized by a great many ionizations. As a result of these characteristics the alpha travels only a few centimeters (or inches) in air and is readily stopped by a sheet of paper.
Figure 6: Radiation Ranges & Shielding Beta particles are basically a very high-energy electron.
Beta particles have a negative charge. It is a very light particle, with a mass of about one two-thousandth of a proton (or about one eight-thousandth of an alpha particle). Beta particles are very fast, approaching the speed of light. Due to their speed and lower charge, the beta particles travel several meters (or yards) in air and 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.
RADIATIONQUALITIES AND UNITS OF MEASVRE 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 lx10 "
nano .000000001 lx10 ~
micro .000001 lx10~
milli .001 centi .01 lx10'x10'x10'ega kilo 1,000.
1,000,000. lx10' 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 3.7x10. 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 many more atoms to produce a curie of activity versus atoms with short half-lives.
Absorbed dose describes the energy absorbed per unit of mass of tissue. The unit used to express absorbed dose is the rad (radiation absorbed dose). One rad is an absorbed radiation dose of 100 ergs (a measure of a very small amount of energy) per gram. The rad can be used with all types of radiation including X-rays, gamma-rays, and particulate 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.
D. i = t. bid. X~i 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 I Quality Factors for Various Radiations Radiation Quality Factor Gamma-rays X-rays Beta Particles Alpha Particles 20 SOURCES OF amnrrOX 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.
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 mrem (.0028 rem) per flight.
Another important contributor to external absorbed dose is terrestrial radiation. This is the
radiation from the earth itself, and the air around each Source of Radiation Dose of us. The sources of terrestrial radiation include the thorium, neptunium, and the uranium decay series as Radon well as potassium-40. The absorbed dose varies about 15 to 140 mrem (.015 to .140 rem) annually. However there are a very few areas that these terrestrial Manmade absorbed doses exceed 800 mrem each year. Terrestrial cosmic Internal One of the most important sources of dose is that contributed by internal radiations. These radionuclides are part of our body, the air we have breathed, or the food we have consumed. One ifthe most significant Radon Terrestrial contributors is radon. Radon is a radioactive gas that is part of the uranium decay series. Radon's Q Cosmic II internal concentration varies greatly based upon the geology of each community, but is found in soils and rock Figure 7: Radiation Sources ( BIER V) everywhere. Ifit 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 (IE the alpha does not travel far but has a high quality factor for the affected tissue). The health effect of breathing radon is an increased risk of lung cancer.
Man-made radiations are important to completing our understanding of sources of Man-made Radiation radiation. An important aspect in discussing man-made radiation is the benefit man derives from the use of these. Medical uses of X-Rays radiation are the major contributor, including diagnostic X-ray, and nuclear medical treatment. Consumer products such as televisions, display screens, smoke detectors, and many other devices are the next most important class of man-made radiations.
Consumer products Fallout from prior weapons testing is now a Nucloar Medicine small contributor to total radiation dose.
Occupational exposure is also a factor Rom the medical, manufacturing, and nuclear industries. Finally, contributions from nuclear plant operations represent less that 1% of the Q XWaye D Nuclear Medicine man-made radiations for the average member D Concumer products El Fallout of the general public. The data presented in D Occupational D Mice. tt Nuclear Figure 8 illustrates the importance of the Hgure 8: Man-Made Radiation Sources (BIER V) different sources of man-made radiation for the average member of the public.
The effects of ionizing radiation has 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 war time nuclear weapons use and its survivors. It has been a classical problem of how to relate doses at these levels to much lower medical use ( although some treatments are designed to deliver high dose) and occupational radiation levels. Environmental levels of radiation represent even greater challenges because of the extemely 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.
Radiations 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 decendents 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, 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 at that dos@ 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 10
sometimes necessary in the creation of chemical bonds. Ifthe 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 that 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 of about 100 mrem.
ezxzm,r. azar.xH aCSx Every human activity has risk associated with it. The air we breath, the food we eat, 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 can not be seen, felt, smelled, or detected by any of the human senses. It is detected by instruments or laboratory analyses specially designed to detect radiation. Thus it is understandable to be wary of something we can not readily sense and may not have a personal knowledge about. There are other similar hazards we tend to accept, such as micro-wave 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 LIVINGIN CITY VERSUS RURAL 5 YEARS OVERWEIGHT 30 % 3.6 YEARS CANCER 2.7 YEARS COMMERCIALNUCLEAR POWER 12 MINUTES 11
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.
Nuclear Fission Certain heavy radionuclides are known to naturally undergo a special form of radioactive, decay, called spontaneous fission. Spontaneous Qssion means the nuclei of these radioisotopes literally split into two or three new nuclei (also known as fission fragments) and a few free neutrons) not in a nucleus). The protons and neutrons are shared between these new nuclei. One isotope of Uranium known a U-235 is known to undergo 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; ifthere is enough uranium, especially U-235, present it is possible to produce more fissions and keep the process going. %hen the rate of fission initiated is self sustaining or increasing, a Chain reaction has been established. It is this sustained chain reaction and thc energy produced that produces the heat needed to generate steam for electrical generation.
Heat Bomberding .,
Neutron C
Atom
~0 Free Neutron
~
Fission Fragment Figure 9: Nuclear Fission 12
Vranium 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 UF6) 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 NUCLEAR FUEL CYCLE is to allow more of the U-235 to be included in the fuels used in commercial reactors. We have already discussed that U-235 fissions more readily that U-238. This process that increases the amount of U-235 is also MINE MILL CONVERTER referred to as enrichment. After enrichment this gas is chemically converted to uranium dioxide (in chemical notation UO~). At this point the uranium dioxide is a gray powder.
The next process takes this powder REACTOR FUEL FABRICATOR under high pressure and temperature (GASEOUS OlffUSIHPlNT) to create a ceramic pellet of uranium dioxide. This process is part of the Figure 10: The Nuclear Fuel Cycle fuel fabrication. The fuel fabricator also ensures that each fuel pellet has the proper amount of U-235 and U-238. The additional U-235 added is referred PBLLBT 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 13
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.
SEAM GENE AATOA
. AEAC'BOA VESSEL CONAtNMEN Figure 12: Major Plant Systems for The Pressurized Water Reactor 14
Reactor Types and the Reactor Vessel There are approximately 180 commercial nuclear reactors being used to generate control roti electricity in the United States today. Of drive mechanism these, there are two basic types of reactor in instrumentation ports operation, the Pressurized Water'Reactor (PWR) and the Boiling Water Reactor upper support plate (BWR). The basic difference is the point core barrel where steam is formed. The boiling water control rod rive shaft reactor forms steam in the reactor while the inlet noxxhs control rod duster outlet nozde pressurized water reactor forms steam through upper core plato a separate heat exchanger called a steam generator. The Harris Plant is a Pressurized reoctor vessel Water Reactor (PWR). There are other types of reactors used for research and military tower coro plato purposes.
The collection of fuel assemblies is referred to instrumentation thimble guides as the reactor core. The Harris Plant has 157 fuel assemblies in the reactor core. The Figure 13: Reactor Vessel reactor core, the controls, and 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 15
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 it's heat or energy to the secondary coolant (water) by heating the secondary coolant and making steam 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 are maintained at a point which prevents boiling in the reactor.
The pressurizer is the system that supports regulation of reactor pressure. The pressurizer is a vessel partly filled with water and is in free exchange with the water in the reactor and primary systems. The pressurizer also allows for the volumetric expansion of the primary coolant (water) as the reactor starts up, while maintaining the pressure of the reactor Sources of Radioactive Materials In Reactor Operation There are two primary means that radioactive materials are produced in reactor operation:
~ Fission produces two or more fission fragments in each fission. These fission fragments become the nuclei of new atoms as fission products. As we have already discussed, many atoms are radioactive, as is the case with these fission fragments. Examples of these isotopes are iodine-131 (I-131), strontium-90 (Sr-90), and cesium-137 (Cs-137).
~ Activation 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 isotopes 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
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 steam imes the zirconium cladding of the steam fuel rod generators water lines the reactor vessel and it' control rods associated piping pros the containment building suro vessel The fuel, fuel rods, and the reactor vessel have already been discussed. The containment building is illustrated in figure 14. The containment 4
houses the reactor core reactor core, the reactor vessel and it' 14: Primary Containment Structure
'igure associated piping, reactor coolant pumps 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 the 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.
17
REACTOR SAFETY O There are several points regarding nuclear safety that are important to understand:
Commercial nuclear generating stations can got explode as a nuclear weapon. The uranium for weapons is highly enriched and must be carefully timed and configured to create an explosion. The uranium in commercial generating stations is low enrichment and can not be configured to create a nuclear explosion.
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.
18
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 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 17 years.
Requirements are established for the radiological monitoring program with the following:
Technical Specifications Off-Site Dose Calculation Manual(ODCM)
Various procedures Additional guidance regarding the radiological monitoring program may be found in the following:
NRC Regulatory Guide 1.109 NRC Regulatory Guide 4.13 NRC Regulatory Guide 4.15 19
General Site Description P I ;Qs ta The Harris Nuclear Plant consists of a B Niney oa r~ Ches Oe4ah le%
pressurized water reactor with a design IWr'kdhlQc 1
rating of 860 MWe (Mega Watts electric). :~Nor Commercial production was initiated on ~l Ps oecsudsi January 3, 1987. The Harris Nuclear Plant ~4 Rale g i, is located in southwest Wake County, i
~~~RtAts% nal a C.
North Carolina. The site is along U.S. %ca Sm
",'.'ylr~~Rsaeckalaa txackaaaL - kEwsr Oe4
'<<O~W'
~ ~
CI QwN Wgs
-'-. 4 route 1 approximately sixteen (16) miles RysOmsiaC" >>-I w* lal southwest of Raleigh, North Carolina and Qpg
. E~dBlUS l SAT ,Orgn
' ~',
is displayed on the map of central North t ~ P'> 4 16a Carolina (Figure 15). The site is also CA approximately fifteen (15) miles northeast bsae, ". p ~ 1~
1 PM Mar tymp, e>
of Sanford, North Carolina. The nearest C~Wse&s,~ ~
community is New Hillwhich is north of Pre twd the site. i
~ Ã84 54est laac ALs RSA Harris Lake is adjacent to the plant itself and is the source of cooling tower makeup Figure 15 Location of Harris Nuclear Plant water. The lake was impounded 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 and adjoining lands through a variety of agreements with state and local goverment. One of these agreements is the gamelands 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 thc 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 signiTicant populations in Apex, Holly Springs, and Fuquay-Varina. Currently these communitics are experiencing significant growth.
Within a fiftymile radius much of the land is used in agricultural production. Significant crops include corn, soybeans, and tobacco. Livestock is also an important component with signiTicant 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.
20
RADIOI,OGICAI,MONITORINGPROGRAM QUALITYASSURANCE 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 to "(1) to identify deficiencies in the sampling and measurement processes to those responsible for these operations so that corrective action can be taken, and (2) to obtain some measure of confidence in the results of the monitoring programs in order to assure the regulatory agencies and the public that the results are valid."(NRC Regulatory Guide 4.15 B Pg. 4.15-2) This provides the opportunity to implement corrective actions that address possible deficiencies. Examples of the activities of the quality assurance program include:
regular review of sample collection and records regular review of laboratory procedures and methods participation in the Analytics, Inc. Environmental Cross-Check Program, which provides an independent assessment of the quality of laboratory results the use of know'n concentrations of radioactivity in test samples by the laboratory to ensure consistent quality results on an ongoing basis 21
RADIOLOGICALMONITORING I ROGRAM 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 Vsed 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 Surface Water Inhalation Air Samples (Particulate & Radioiodine)
Sampling Locations Sampling locations are chosen based upon meteorological factors, preoperation 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.
22
Radiological Sampling Locations 9e5no Cleek State Reeteeuon Atee ~ ' Ms, Ctoeeeeln6e Stete Reeteeuote Atee Phce6oeb v 39 5
Seefxet ge ~
~,
4 'Popter Poles. Stete Reote enon Atee e thmlode ShS Steee )1 sbprp 32 pet ~
4Eeeneur Cteote2e Steea Rteetelon Aoee 1
/
- Vina poSet stele 3teeteeuon Aeee 33 4 e8
~
19 r ~P
- 63 >rekonv Nel Ho9e Peene Ne SS e9 6h~e* 36
'4 31 4
Holly Spelnp8 35 64 19 Hanis Phm 1
Heywood ~ SO
~r45tnwls Ctotsfoadt
'e 4 23
"-Ot 18 ~
33
. 38 tatbon 4 4 42 4 "
te oP
"'l'neodaven 21$ C '2,26 9to .
4 Res See 55 4pepoo6 e's 62 4
Cokesbury 6>> 1996 DeLceene Stnet Apee USA Figure 16: Radiological Sampling Locations (Distant from Plant) (Scale 1 inch=3.9 miles) lhcrmoluminesecnt dosimeter and shorclinc sediment locations (only) are displayed in black, ingestion and watcrbornc pathways in blue, and inhalation or air sampling stations in rcd.
Stations 1 through 5, and 26 include air sampling and thcrmolumincsccnt dosimcters.
Sample 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)
Thcrmoluminesccnt Dosimeter 1-37, 48-50, 53, 56, 63 (BLACKEXCEPT AT SHARED LOCATIONS) 5 (BLUE)
Fish 44, 45 (BLUE)
Food Products & Broadleaf Vegetation 5, 54, 55, 62, 64, 65,66 (BLUE)
Aquatic Vcgctation & Bottom Sediment 41, 45, 46, 52, 61 23
Radiological Sampling Locations Figure 17 Radiological Sampling Locations (Nearest Plant) (Scale 1 inch = 1 miles)
Thermolumincsccnt dosimctcr and shorclinc scdimcnt locations (only) arc displayed in black, ingestion and waterborne pathways in blue, and inhalation or air sampling stations in rcd.
Stations 1 tlirough 5, and 26 include air sampling and thermoluminesccnt dosimeters.
Sample Types Sample Locations Air Cartridge & Particulate 1-5, 26,47 (RED)
Shoreline Scdimcnt 26,41 Ground Water 39,57-60 (BLUE)
Drinking Water 38, 40 (BLUE)
Surface Water 26, 38, 40 (BLUE)
'Ihermolumincsccnt Dosimctcr 1-37, 48-50, 53, 56, 63 (BLACKEXCEPT SHARED LOCATION)
Mlk 5 (BLUE)
Fish 44, 45 (BLUE)
Food Products & Broadleaf Vegetation 5, 54, 55, 62, 64, 65, 66 (BLUE)
Aquatic Vegetation & Bottom Scdimcnt 41,45, 46, 52, 61 24
Table 4 Harris Nudear Plant Radiological Monitoring Sampling Locations Sample Type Location & Description Frequency Sample Size Analysis Air Cartridge 1-2.6 miles N Weekly or as 28,000 Iodine (AC) 2-1.4 miles NNB required by dust m')
ft'800 load mg 4-3.1 miles NNE 5-13.4 miles WNW-Pittsboro*
26-4.7 miles S 47-3.4 miles SSW Air Particulate 1-2.6 miles N Wee Jdy or as 28,000 Gross Beta (AP) 2-1.4 miles NNE required by dust m')
fr'800 (Weekly) toadmg . omposite 4-3.1 miles NNE amma 5-13.4 miles WNW-Pittsboro* Quarterly) 26-<.7 miles S 47-3.4 miles SSW Fish (FI) 44-Site varies in Harris Lake Semiannual I kg (wct) Gamma 45-Site varies in Cape Fear River* (In Season) Free Swimniers &
Bottom 1 ccders 38-6.2 miles WSW* Weekly 8 liters 1-131, Gamma Qatcri(SW) 40-17.2 miles SSE Lillington Monthly Composite Tritium 51-Water Treatment Plant (On Site) Gross Beta Groundwater 39-.07 miles SSW -a 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 Dairy* Semimonthly 8 liters 1-131 Gamma Shoreline 26-4.6 miles S Semiannual 500 grams Gamma Sediment (SS) 41-3.8 miles S ur face Water 26-4.7 miles S Weekly 8 liters 1-131, Gamma SW) 38-6.2 miles WSW
- Monthly Composite Tritium 40-17.2 miles SSE Lillington Gross Beta quatic. 26-P.7 miles S Annually 500 grams Gamma egetation 41-3.8 miles S 61-2.5 miles B Botton 52-3.8 miles S Semiannual 500 grams Gamma Sedtmcnt (SD)
Pyd Products 5-18.0 miles NNW-Pittsbom~ Monthly during 500 gams Gamma 54-1.7 miles NNE-Witkins or Morris growtng season when milk sntnplcs not 55-2.0 miles NNW-L L Goodwin pcrfonncd 62-2.3 miles NE-Lcc 64-l.g miles ENE-Michael Brocdtcaf 65-1.36 mites S Monthly when 500 gams Gamma Vegetation (BL) nvnltnb! c 66-1.33 miles SStV
- Control Stations 25
Table 4 (Continued)
Harris Nuclear Plant Radiological Monitoring Sampling Locations Sample Type Location &: Description I<'requcncy Sample Analysis 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-'%.5 miles NE 21-4.8 miles ENE 22-A.3 miles E 23 -4.8 miles ESE 24-4.0 miles SE 25-A.7 miles SSE 26-4.7 miles S 27-A.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 ESL-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 26
SUMMARY
OF RADIOLOGICALMONITORING PROGRAM This report presents the results of the Radiological Environmental Monitoring Program conducted during 1998 for the Shearon Harris Nuclear Power Plant (SHNPP) and fulfills the reporting requirements of Technical Specifications 6.9.1.3. The program was conducted in accordance with Operational Requirement 3.12.1 in the Off-Site Dose Calculation Manual (ODCM), and applicable procedures.
Approximately 1020 samples of 13 different media types from indicator stations were compared to approximately
~O 330 control samples. 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 1998 are as follows:
Maximum Location of Individual Environmetxal, w/Highest Annual Activityand Occurrence Dose RadiodUclide Mean (mrem/yr)
Media Surface, water H-3 Harris Lake 3,270 pci/L No ingestion (12/12) pathway. No dose calculated.
Fish H-3 Harris Lake See above. 0.005 Assumes H-3 equilibrium Total Body between lake water and fish tissue.
The radiological environmental data indicates that SHNPP operations in 1998 had no significant impact on the environment or public health and safety.
A statistical summary of all the data for 1998 has been compiled and summarized in Table 5.
The plant-derived activity detected within the scope of the Radiological Environmental Monitoring Program (see Data Summary Table 5) has been tritium activity in Harris Lake water at an average concentration of 3.27 E+3 pCiiL, Harris Lake Bottom Sediment, and Aquatic Vegetation (see Data Summary Table 5) for 1998. No tritium activity was observed at Lillington, N.C., located 17 miles downstream on the Cape Fear River, which is the first public drinking water 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.
27
TABLE 5 RADIOLOGICALENVIRONMENTALMONITOMNGPROGRAM DATA
SUMMARY
Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1998 Medium or Pathway
, Type and Total No.
Measuranents of... Typical Lower Limit of Detection All Indicator Locations Meanm-Location w/Hi hest Annual Mean Direction'ontrol Name, Distance, and Locations hfean tn Sampled or Performed:: '(LLD)tn Range Range Measured (Unit of Measurement)
Air Cartridge I-131 2.4E-2 All less than LLD All less than LLD All less than LLD Cil 307tn New Hill n<<ar Air Particulate Gross Beta 1.0E-3 (255/260) Baptist ChurchI'.90E-2 1.95E-2 (51/52) 2.00E-2 (52/52)
(pCi/aP) 307tn 7.66E 4.01E-2 3.1 miles NNE 9.81F 3 - 3.66F 2 9.36E 3.65E-2 Refer to All less than LLD All less than LLD All less than LLD Table 6 Drinking Watetto 1-131 1.0E+0 All less than LLD All less than LLD All less than LLD (pCili) 104 Gross Beta 1.0E+0 4.07E+0 (12/12) Lillington 4.07E+0 (12/12) 4.21E+0 (12/12) 24 2.14E+0- 5.99E+0 Cape Fear River 2.14E+0- 5.99E+0 1.82E+0 - 6.59 E+0 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 Fish Gamma Refer to All less than LLD All less than LLD No Control Bottom-Feeders 4 Table 6 i/, wet Free-Swimmers Gamma Refer to All less than LLD All less than LLD No Control (pCi/g, wet) 8 Table6 Broadleaf Vegetation Gamma 2.9E -2 8.12E-2 (2/35) Location 66 8. 12E-2 (2/18) No Control (pCi/g, wet) 35tn 7.26F 2- 8.98E-2 1.33 miles SSW 7.26E2- 8.98F 2 Cs-137 Food Crop Gamma Refer to All less than LLD All less thin LLD All less than LLD (pCi/g, wet) Igtn Table 6 28
TABLE 5 (cont.)
RADIOLOGICALENVIRONMENTALMONITORING PROGRAM DATA
SUMMARY
Shearon Harris Nuclear Popover Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1998 Medium or Pathway Type and Typical Lower All Indicator Location w/HI hest Annual Mean Sampled or Measured Total No.'f Limit of Locations Name, Control Locations (Unit of Measurement) Measurements Detection Mean tu Distance, and Meantu Mean tu Performed LD tu Ran e Direction .Ran e e Shoreline of Aquatic Vegetation Gamma 3.1E-2 2.75E-2 (I/3) Cooling Tower 2.75E-2 (I/I)
(pCi/g, wet) 3 Single value Mixing Zone Single value No control Co8) 3.8 miles S Groundwater Gamma Refer to All less than LLD All less than LLD No control (pCi/I) 20 Table 6 Tritium 3.25E+2(3o/20)~ 5.33E+2g/20) NorthBank 5.33E+2g/4) No control 20 3.13E+2 - 6.74E+2 ESW Intake 3.13E+2 - 6.74E+2 0.5 mile WSW Milk 1-131 1.0E+0 All less than LLD (pCi/I) 24tu Refer to All less than LLD Table 6 Shoreline Sediments Gamma Refer to All less than LLD All less than LLD No control (pCi/g, dry) 8 Table 6 Harris Lake Bottom Sediment Gamma 4.2E-2 1.86E +0 (4/4) Cooling Tower 1.86E+0 (4/4) No control (pCi/g, dry) 4 4.62E -I - 2.69E +0 Mixing Zone 4.62E -I - 2.69E+0 Co60 3.8 miles S Harris Lake Sb-125 1.40E -I 7.90E-I g/4) Cooling Tower 7.90E I (3/4) No control 3.93E-I - 1.33E+0 Mixing Zone 3.93E-I - 1.33E+0 3.8 miles S Harris Lake Cs-137 4.7E -2 3.63E -I (4/4) Cooling Tower 3.63E -I (4/4) 'No control 1.13E -I - 5.23E -I Mixing Zone 1.13E -I - 5.23E -I 3.8 miles S 29
TABLE 5 (cont.)
RADIOLOGICALENVIRONMENTALMONITORING PROGRAM DATA
SUMMARY
Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1998 Type and T3'plcal Lol'ier All Indicator Location w/Hi est Annual Mean Medium or Pathlvay Total No."of - Linut'of Locations. Name, Control Locations Sampled or Measured Measuremerits Detection 'Mean tn and
'istance, hfean'+ Mean m nit of Measurement Performed LD tu Ran e Direction Ran e Ran e Surface Watefo 1-131 1.0E+0 All less than LLD All less than LLD All less than LLD (pCi/1) 104 Gross Beta 1.0E+0 3.28E+0 (24/24) Lillin8ton 4.07E+0 (12/12) 4.21E+0 (12/12) 36 1.55E+0 - 5.99E+0 Cape Fear River 2.14E+0 - 5.99E+0 1.82E+0 - 6.59E+0 17.2 miles SSE Gamma Refer to All less than LLD All less than LLD All less than LLD 36 Table 6 Tritium 3.25E+2 (34/36)" All less than LLD All less than LLD All less than LLD 36 1.00E+3(t2/36)" 3.27E+3 (12/24) Harris Lake 3.27E+3 (12/12) 1.82E+3 - 4.59E+3 4.7 miles S 1.82E+3 - 4.59E+3 Direct TLD 1.21E+1 (166/166) Fuquay Varina at 1.62E+1 (4/4) 1.63E+1 (4/4)
Radiation 170m 8.40E+0 - 1.75E+1 Old CP&L Oflice 1.49E+1 - 1.75E+1 1.50E+1 - 1.74E+1 (mR/qtr)tn 9.2 miles ESE 30
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'aboratories. 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.
31
INTERPRETATIONS AND CONCLUSIONS Air Monitorin All 307 air cartridge samples from indicator and control stations had I-131 activities which were less than the LLD of 1.5 E-2 pCi/m', I-131 was detected in air samples for a six-week period following the Chernobyl incident in April 1986. With this exception, no I-131 has been detected in air samples collected from 1987 through 1998, which is the entire operating history of the plant:"
Gross beta activity was detectable in all airborne particulate samples from the five indicator locations. The 255 samples had an average concentration of 1.90E-2 pCi/m', a value similar to preoperational data of 2.0 E-2pCi/m'. Similar gross beta activities were observed at the control location in Pittsboxo which had an average concentration of 2.00E-2 pCi/m'n 52 samples. These concentrations are typical of the natural environment and are not attributed to plant operations. Figures 18'through 22 provide a graphic representation of the gross beta activity at the indicator locations compared to the control location for the period January through December 1998.
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.
0~iI '
'None of the 52 drinking water samples collected at the Lillington Municipal water supply nor the 52 control samples collected from the Cape Fear River above the Buckhorn Dam contained detectable I-131 activity (( 1.0 E+0 pCi/L) during 1998. This has been the experience for the preoperational and operational period with the exception of 1986 when the fallout from Chernobyl was detected.
The average annual gross beta concentrations at the indicator and control locations wexe similar with activities of 4.07 E+O,pCi/L and 4.21 E+0 pCi/L, xespectively, similar to the preoperational average of 4.00 E+0 pCi/L. These activities are attributed to the natural environment and are not attributed to plant operations. Figure 23 provides graphic representation of the gross beta activity during 1998 for Location 40 (Lillington).
32
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.
'ritium concentrations in all of the Lillington Municipal Water Supply samples were less than the lower limit of detection (3.25 E+2 pCi/L) (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 1998 consistent with the data for 1989-1996.
During the Chernobyl period, Cs-134 and 137 were detected in both control and indicator samples.
Fish are considered to be in equilibrium with the tritium activity in the lake and the most exposed individual (a child residing 1.6 miles from the plant in the NNW sector) would have to consume approximately 15 pounds (lbs.) of fish a year (6.9 kg fish/yr.). The total body dose to the maximum exposed child individual due to tritium was calculated by Regulatory Guide 1.109, Rev.1, October 1977, Equation A-1, to be 0.005 mrem/year.
E uation A-1 Ratpj = Cip Uap Datp) where as:
Raipl = total body dose in mrem/yr of H-3 Cip = concentrationof nuclide(H-3) inpCi/kg = pCi/L Uap maximum exposed individual's consumption (Reg. Guide 1.109 Table E-5) (approx. 15 lbs. of fish/yr. = 6.9 kg of fish/yr.)
Datpj = ingestion dose factor for total body of individual in Uap in mrem/pCi (Reg. Guide 1.109 Table E-13)
The dose due to tritium in the fish was also calculated using the child as the maximum exposed individual with the exposure to the liver, the result was the same. The total body dose and 33
dose to the liver (ingestion dose factor - Reg. Guide 1.109 Table E-11) for the exposed individual being an adult consuming approximately 46 lbs. of fish a year (21 kg fish/yr.) Reg.
Guide 1.109 Table E-5) calculates to be 0.007 mrem/year.
Broadleaf Ve etation Broadleaf vegetation sampling is accomplished by collecting monthly three different species of samples, when available, at two off site locations (two indicator locations of the highest predicted annual average ground level D/Q). The highest predicted annual average ground level D/Q (ODCM Table A-1 through A-4) was at the site boundary in both the South sector at 1.36 miles (BL-65) and the SSW sector at 1.33 miles (BL-66). Broadleaf sampling is conducted since no milk animals are located within a radius of approximately five miles of the plant and is used to simulate dose to an individual via the milk pathway for compliance purposes.
During 1998, two of 35 samples taken from the indicator sites demonstrated detectable concentrations of Cs-137 for an average value of 8.12 E-2 pCi/g (wet). It is concluded that the indicator value reflects fallout from weapons testing from previous years (Cs-137 activity), not.
contamination attributed to plant operations. There was no detectable Cs-137 during 1998 from HNP gaseous releases.
Surface Water Surface water samples were collected and analyzed weekly for I-131. Water samples collected during 1998 contained no detectable I-131 (LLD ( 1.0E+0 pCi/L) as they have been since plant operations began in 1987.
Average gross beta concentrations at the indicator and control locations were 3.28 E+0 pCi/L and 4.21 E+0 pCi/L, respectively in 1998, indicating no adverse influence from plant operations (See Figure 24).
Surface water samples were analyzed for gamma-emitting radionuclides and tritium. All concentrations of man-made gamma-emitters were less than their respective lower limits of detection (see Table 6).
34
The annual average tritium concentration in Harris Lake was 3.27 E+3 pCi/L with minimum and maximum values of 1.82 E+3 pCi/L and 4.59 E+3 pCi/L, respectively. The Harris Lake tritium activity showed a slight decline in tritium concentration compared to 4.06 E+3 pCi/L in 1997 (see Figure 25).
Groundwater Groundwater samples are collected on site at SHNPP and analyzed for gamma-emitting radionuclides and tritium. Concentrations of the gamma radionuclides were all less than their respective lower limits of detection during 1998. Therefore, there appears to be no downwelling of activity. No tritium or gamma-emitter activity has been observed greater than the required LLD over the period from 1985-1995. Tritium activity (greater than the LLD of 3.25 E+2 pCi/L) was detected in groundwater 58 (0.5 mile WSW Sector N Bank ESW Intake) three out of four quarters in 1996, all of 1997, and three out of four quarters in 1998. No activity was observed in first quarter 1996, which had an LLD of 1.0 E+3 pCi/L. The tritium LLD activity for pre-operational samples through first quarter 1996 was 1.0 E+3 pCi/L and from second quarter (June) 1996 through present the LLD activity has been decreased to 3.25 E+2 pCi/L (see Footnotes to Table 5, footnote 6). The groundwater wells are all abandoned wells and are not a water supply for drinking or irrigation; therefore, there is no radiological dose via this pathway.
Milk During 1998 as in all past years with the exception of the Chernobyl period, no I-131 concentrations were detected in milk samples throughout the entire year. There were also no other gamma-emitting radionuclides from plant operations detected in the milk. The only detectable gamma-emitting nuclide identified in each milk sample was potassium-40 (K-40).
This is a naturally occuring nuclide in any living organism or product there of. The K-40 concentrations in milk range from 4.06E+2 pCi/L - 1.65E+3 pCi/L for the control location.
In May of 1997, the Maple Knoll Dairy (indicator Mk-42 located in the SSE sector) ceased operations. In lieu of the semimonthly milk samples, per Harris Nuclear Plant Off-Site Dose Calculation Manual (ODCM) Table 3.12-1, broadleaf vegetation samples were collected in both the South (S) and SSW sectors.
35
Shoreline Sediment Shoreline sediment samples were collected (1) opposite the discharge structure and (2) near the main dam in 1998. No plant-related radioactivity has been observed in either sample 1994-1998. No long-term trends are readily identifiable.
Bottom Sediment The 1998 data shows Cobalt-60 (4.62 E-1 to 2.69 E+0 pCi/g dry) and Cesium-137 (1.13 E-1 to 5.23 E-1 pCi/g dry) activity in the indicator sample, which is sampled quarterly. Also, Antimony(Sb)-125 was observed three out of four quarters for a range in activity of 3.93 E-1 to 1.33 E+0 pCi/g dry. 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 plus feet under water).
Food Cro s In addition to milk sampling (or broadleaf vegetation sampling), a food product sampling program was maintained. Various crops were collected during a growing season 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 1998 included turnip greens, cabbage, collards, tomatoes, and squash. Gamma spectrometry analyses of the food crops detected no plant-related activity in 16 samples from indicator locations and 2 samples from control locations collected in 1998.
A uatic Ve etation Cobalt - 60 activity (2.75 E-2 pCi/,gm wet) was detected in one of three annual aquatic vegetation samples collected from the Harris Lake in 1998 (see Table 5).
External Radiation Ex osure Thermoluminescent dosimeters (TLDs) were used to monitor ambient radiation exposures in the plant environs. The average quarterly exposure from the indicator locations was 12.1 mR and 16.3 mR from the control station. The highest indicator location was 9.2 mifes ESE of the plant (Fuquay Varina at the old CP8cL office) and averaged 16.2 mR/qtr. The differences 36
among these locations is attributed to variations in soils and 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 inner and outer rings are approximately equal.
MISSED SAMPLE~S AND ANALYSES Air Cartrid e and Air Particulates No samples were available for:
~ AC/AP-47, April 27, due to a power trip.
~ AC/AP-47, June 25, due to' power trip. See Condition Report (CR) ¹98-01758.
~ AC/AP-47, July 6, due to a power trip. See CR ¹ 98-01800.
~ ¹ AC/AP-47, July 27; low volume. See CR 98-02083.
~ AC/AP-4, August 31, breaker for motor tripped, but fan still running.
Low AC/AP Volumes for:
~ AC/AP-47, July 13, low volume.
~ AC/AP-47, July 20, due to a sampler not being able to switch back on. See CR ¹ 98-01977.
~ AC/AP-5, December 27, due to loss of power at town of Pittsboro.
I<'ood Cro s Food crops were not available for sampling during April, May, September, and October only collards.
Milks On May 19, 1997, the Maple Knoll Dairy (Mk-42 located in the SSE sector), ceased operations. In lieu of the semimonthly milk samples, per Harris Nuclear Plant Off-Site Dose 37
Calculation Manual (ODCM) Table 3.12-1, broadleaf vegetation "samples were collected in both the South (S) and SSW sectors. The broadleaf vegetation samples collected were three different kinds representative of the area. The vegetation site location will be designated BL-65 (S sector) and BL-66 (SSW sector).
Broadleaf Ve etation Broadleaf vegetation samples were not available for sampling during January, February, March, April, October, November, and December; however, during October BL-65 Poplar was available and sampled.
TLDs Two of a possible 172 TLD samples were missing during 1998. They were:
Third Quarter TLDs 9 and 32 were missing in the field. TLD 9 was missing due to the tree being cut down that the TLD was posted on. The area has been logged. TLD 32 was collected, but not processed. Radiological Services was unable to determine where it was lost.
38
ANALYTICALPROCEDURE<S 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/m'or SHNPP samples. Air particulate samples are mounted in 2-inch stainless steel planchets and counted directly.
Gross beta activity in drinking and surface waters is determined by evaporating 1 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 and potassium permanganate crystals and then distilled. Five milliliters of the distillate are mixed with thirteen milliliters of liquid scintillation cocktail and counted in a liquid scintillation counter. Samples which routinely demonstrate activity less than the lower limit of detection count for 500 minutes with an approximate LLD of 3.25 E+2 pCi/L and samples that typically exhibit activity count for 60 minutes with an approximate LLD of 1.0 E+3 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 2.2 E-2 pCi/m' 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 with an intrinsic Ge detector. The LLD using the Ge detector is less than or equal to 1.0 E+0 pCi/L using a 25,000-second count time.
39
Gamma S ectromet Gamma spectrum analysis utilizes intrinsic germanium detectors with thin aluminum windows housed in steel and lead shields. The analyzer system is the Canberra Nuclear 9900 Gamma Spectroscopy System. Table 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 PB-50 beaker and analyzed for 7,000 seconds. One-liter milk samples are analyzed in a Marinelli beaker for 11,000 seconds.
Shoreline and bottom sediments are dried, weighed, and then analyzed in a 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, and placed in a Marinelli beaker for analysis for 1,500 seconds.
Thermoluminescent Dosimetr 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 lighttight and the bag is weather-resistant.
Dosimeters are machine annealed before field placement. Following exposure in the field, each dosimeter is read utilizing a Panasonic TLD reader. This instrument integrates the light photons emitted from traps as the dosimeter is heated above 150'C. The photons from the lower-energy traps are automatically eliminated through a preheat cycle. Calibration is checked regularly using dosimeters irradiated to known doses. Prior to the measurement of each dosimeter, the instrument is checked through use of an internal constant light source as a secondary standard.
40
The exposure reported is corrected for exposure received in transit and during storage through the use of control dosimeters.
Interlaborator Com arison Pro ram The Radiochemistry Laboratory at the Harris Energy 8c Environmental Center in New Hill, North Carolina, provides radioanalytical services for CP8cL'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, 199S.
During 1998, 61 analyses were completed on 16 samples representing five major environmental media (water, milk, air filters, soil, and air cartridges). Data on the known activities and the standard deviations for the 61 analyses have been received from Analytics,Inc.. A comparison of the average of our reported values with Analytics, Inc.
known activity and standard deviation is provided below:
Standard Deviation From Known Activit Percent of Anal ses s 1 standard deviation 38 s 2 standard deviation 79 s 3 standard deviation 93 Four of 61 analyses exceeded the 3 sigma action level; however, three of these four were well within the + 20% ratio to the known value. A condition report (CR ¹ NGG 99-08644) was generated to investigate further the outliers.
Lower Limits of Detection All samples analyzed met the LLD required by the ODCM.
41
TABLE 6 TYPICALLOWER LIMITS OF DETECTION (A PRIOR/
GAMMASPECTROMETRY
" . Drinkin h,'.Wahter/Surface<Water/Grouh'nhdwatehr..Sam 'les.':.'-,:.".',.-
- Isoto'e;;. ;.'.LL'D'<<Ci/L' ..'i'.," .
Mn-54 6 Co-58 7 Fe-59 11 Co-60 9 Zn-65 16 Zr-Nb-95 6 I-131 0~
Cs-134 6 Cs-137 6 Ba-La-140 1 Other Expected 1 to 103 Gamma Emitters h
,Air Particulates ..
uarterl .'Cohmh-'ositeh "
<<I
,;-'Isot'o e . -LLD. Ci/m';
I-131 0.041 Cs-134 0.001 Cs-137 0.001 Other Ex ected Gamma Emitters 0.001 to 0.041
-'Milk
'h
'-'Isoto e:.', :.LLD'> 7 LAND-USE CENSUS COMPARISON (1997-1998)
NEAREST PATHWAY (MILES)
SE<CTOR RESIDE<NT GARDEN MEAT ANIMAL MILKANIMAL 1997 1998 1997 1998 1997 1998 1997 1998 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 2.3 2.3 2.3 2.3 2.3 2.3 ENE 1.8 1.8 1.8 1,8 1.8 1.7 1.7 2.0 2.0 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 5.3 5.3 5.3 SSW 3.8 3.8 3.8 3.8 SW 2.9 2.9 2.9 2.9 WSW 4.5 4.5 4.5 4.5 4.5 4.5 W 3.0 3.0 3.1 3.1 3.1 3.1 WNW 2.3 2.3 2.3 2.3 2.4 2.4 2.6 2.6 NNW 1.6 1.6 2.0 2.0 2.0 2.0 Sector and distance determined by Global Positioning System.
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)
I "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: HEIR 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. 93National Council on Radiation Protection and Measurements, Washington, D.C. (September 1987)
Morgan, K. & Turner, J., "Principles of Radiation Protection," John Wiley & Sons, Inc., New York, N.Y. (1968)
"Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1987)
"Sources, Effects and Risk of Ionizing Radiation," United Nations Scientific Committee on the Effects of Atomic Radiation, 1988 Report to the General Assembly, United Nations, New York, N.Y. (1988)
"Standard for Protection Against Radiation," Tile 10, Part 20, Code of Federal Regulations, Washington, D.C.
47
"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) 43
49 50 gw -~c <<2~%Mgk>~sch.,s,hgri, ~~~a, @ps~~~, m~~~4o~N >>AQ .<~+~~Q@<~<<~z ..., 4<Qpp'~z4zR+)4k@ ) f~a+i4d4~>>,, ,~4~~@~+~';..".-.~~+~Q>p NXQN pg,gp R4
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54 55 Figure 25 HNP 1998 Surface Water Tritium 7000 6000 5000 I
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Figure 26 HNP 1998 TLD Averages for Inner and Outer Ring Locations 14.5 14 13.5 13 12.5 12 11.5 11 10.5 10 9.5 8.5 CO CO CO CO 00 CO CO CO Cb I
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CPRL Radiological Environmental Monitoring Analysis Report 12/14/98
Semia nalysis Report CPRI Radiological Env ntal Monitoring Analysis Report 14/98 Plant: HNP TLD in mR/QTR
~Sam ie Point SempieDete Dose 2Si maError I - SR1134ATINTSR IOII-DIXIEPIPELINE 2/15/98 1.65E+001 2.40E+000 I 5/15/98 1.28E+001 9.00E401 2 -SR 1134 2/15/98 1.39E+001 1.00E+000 2 5/15/98 1.35E+001 7.00E401 3 - HARRIS E&ECENTER-2.2MI NE 2/15/98 I. I 8E+001 1.40E+000 3 5/15/98 1.13E+001 9.00E401 4 - NEWHILLNEARISTBAPTISTCH 2/15/98 1.17E+MI 8.00E-OOI 4 5/15/98 1.12E+001 I.OOE+OM 5 - PllTSBORO- CONTROL 2/15/98 1.74E+001 8.00E401 5 5/15/98 I.SOE+001 6.00E40I 6 - INTOFSR 1134 AND 1135 2/15/98 1.16E+001 S.OOE401 6 5/15/98 I.OIE+MI 5.00E40I 7 - HOUSERUINSONSR1134 2/15/98 I.OSE+001 I.OOE+000 7 5/15/98 I.OOE+001 6.00E401 8 - DEADENDOFSR 1134 2/15/98 I.SOE+001 1.00E+000 8 5/15/98 I. ISE+001 6.00E-OOI 9 - I Ml SWOF HOLLEMANS XRDS ON SR 1130 2/15/98 9.80E+000 1.00E+000 9 5/15/98 8.40E+000 I.OOE+000 10 - 2.0 M I SW OF HOLLEMANS XRDS ON SR 1130 2/15/98 l. IOE+001 8.00E401 10 5/15/98 1.12E+001 8.00E-OOI I I - EARTHEN DAh1 AT HARRIS PLANT 2/15/98 I.OSE+001 I.OOE+000 II 5/15/98 1.12E~I 1.30E+000 12 - I MISONDIRTRDFROMTLD13 2/15/98 I.OOE+001 I.IOE+000 12 5/15/98 1.03E+001 1.20E+000 13 - DIRTRDINTBETWEENPLANTANDAUXRES 2/15/98 1.09E+001 I.IOE+000 13 5/15/98 1.09E~I 1.30E+000 14 - DEAD ENDOFSR 1911 2/15/98 I. I 5E+001 9.00E401 14 5/15/98 1.02E+001 9.00E401 IS - CEMETERY ON SR 1911 2/15/98 I.OOE+MI 2. IOE+000 15 5/15/98 I.OOE+001 6.00E401 16 - US I ATCHATHAM-WAKECO LINE 2/15/98 1.26E+001 1.00Et000 16 5/15/98 I. 16E+001 1.80E+000 17 - INT OF US I AND AUX RES 2/15/98 1.12E+001 1.70E+000 17 5/15/98 I. I 5E+001 7.00E401 18 - 0.6MINONUS I FROMTLD17 2/15/98 1.27E+001 2.50E+000 IS 5/15/98 1.26E+001 1.20E+000 19 - SR 1142-OUVES DAIRY 2/15/98 I.OSE+001 1.80E+000 19 5/15/98 1.08E+001 I.OOE+000 20 - INT OF SR 1149 AND VS I 2/15/98 1.54E+001 1.70E+000 20 5/15/98 1.42E+001 S.OOE-OOI 21 - 1.3 Ml ON SR 1152 FROM INT SR 1153 2/15/98 1.23E+Ml I.IOE+MO
Semia nalysis Report CPRL Radiological Env ntal Monitoring Analysis Report 14/98 Plant: HNP Sam le Point Sam leDate Dose 2 S~iError 21 - 1.3 Ml ON SR 1152 FROM INTSR 1153 5/15/98 1.08E+001 9.00E-OOI 22 - 2 0 Ml E OF HOLLEMANS XRDS ON SR 1115 2/15/98 9.10E+000 1.40E+000 22 5/15/98 9.90E+000 6.00E4101 23 - INTSR 1116 ANDSR 1127 2/15/98 1.26E+001 I. IOE+000 23 5/15/98 1.24E+001 I.OOE+000 24 - SWEET SPRINGS CHURCH ON SR 1116 2/15/98 1.23E+001 9.00E-OOI 24 5/15/98 1.05E+001 7.00E4IOI 25 - 0.2 MI W OF INT OF SR 1401 AND SR 1402 2/15/98 1.50E+001 1.50E+000 25 5/15/98 1.14E+001 5.00E40I 26 - SPILLWAYON MAINRES 2/15/98 1.32E+001 8.00E-OOI 26 5/15/98 1.27E+001 2.90E+000 27 - BUCKHORN UNITED METHODIST CH ON NC 42 2/15/98 1.02E+001 1.40E+000 27 5/15/98 9.80E+000 I. IOE+000 28 - 0.6MI FROM INTSR 1916 AND SR 1924 2/15/98 I. IOE+001 8.00F 001 28 5/15/98 I.OOE+001 5.00F 001 29 - NESTE RESIN CORP ON SR 1916 2/15/98 1.33E+001 2.10E+000 29 5/15/98 1.3 I E+001 9.00E-OOI 30 - INT OF SR 1972 AND US I 2/15/98 1.06E+001 9.00F 001 30 5/15/98 1.03E+001 9.00E410l 31 - INTOFSR 1910 2/15/98 1.32E+001 1.80E+000 31 5/15/98 9.50E+000 7.00E-OO I 32 - 3MION SR 1008 FROM INTSR IOI I 2/15/98 1.12E+001 1.20E+000 32 5/15/98 1.20E+001 1.20E+000 33 - SR 1142AT BARRICADE 2/15/98 1.06E+001 1.60E+000 33 5/15/98 1.09E+001 I.OOE+000 34 - APEX AT JONES PARK 2/15/98 1.39E+001 1.70E+000 34 5/15/98 1.34E+001 7.00E4101 35 - HOLLYSPRINGSONEARPSTREET 2/15/98 1.38E+OOI 3.50E+000 35 5/15/98 1.16E+001 I.OOE+000 36 - INTOFSR 1393 AND SR 1421 2/15/98 1.14E+001 1.60E+000 36 5/15/98 I. I I E+001 1.80E+000 37 - FUQVAYVARINAAT OLD COL OFFICE 2/15/98 1.67E+001 8.00E-OOI 37 5/15/98 1.49E+001 1.60E+000 48 - SR 1142 AT UNDERGROUND CABLE SIGN 2/15/98 1.28E+001 1.50E+000 48 5/15/98 1.32E+001 9.00E410I 49 - SR 1127 AT WAKECO TRASH COLLECfION AREA 2/15/98 1.48E+001 1.80E+000 49 5/15/98 1.45E+001 1.50E+000 50 - HOLLEMANS CROSSROADS 2/15/98 1.12E+001 1.20E+000 50 5/15/98 I.OI E+001 7.00E4101 53 - INTERSECflONOFSR1972ANDSR1907 2/15/98 1.08E+001 9.00F 001 53 5/15/98 1.07E+001 1.30E+000
Semian nalysis Report CPRL Radiological Envi ntal Monitoring Analysis Report 14/98 n
~Sam io Point SamyleDate Dose 56 - 2.8MIWSWOFTHESITE 2/15/98 1.18E+001 1.50E+000 56 5/15/98 1.10E+001 1.30E+000 63 - 0.7MISWSECTORON(POWER POLECOJ85) 2/15/98 1.36E+001 I.OOE~
63 5/15/98 1.31E+001 5.00B-OOI
CP&L Radiological Environmental Monitoring Analysis Report 4/8/99
Semiann alysis Report 4/8/99 Sampie Point SampleDate Quantity Efficiency Activity 2 Si maError Plant: HNP Anal >>1st BETA MedlaT e: AIR PARTICULATE CUBIC METERS I - SR 1134 AT INTSR 1011- DIXIEPIPELINE I/5/98 1024.10000 3.78E401 1.66E402 1.39E403 1.01E403 I/12/98 895.80000 3.78E401 9.13E403 1.20E403 1.12E403 I/19/9S 911.40000 3.78E401 9.75E403 1.21E403 1.10E403 I/26/98 862.400M 3.78E401 1.29FA02 1.41E403 1.24FA03 2/2/98 867.60000 3.78E401 1.04FA02 1.31E403 1.23E403 2/9/98 850.70000 3.78FAOI 7.82E403 1.18FA03 1.19FA03 2/16/98 867.30000 3.78FA01 1.73FA02 1.52E403 1.05E403 2/23/98 91130000 3.78E401 7.66FA03 1.09E403 1.03E403 3/2/98 845.00000 3.78E401 137FA02 1.44E403 1.22FA03 3/9/98 866.80000 3.77E401 1.31FA02 1.39FA03 1.16E403 3/16/98 863.20000 3.77E401 190FA02 1.62E403 1.18FA03 3/23/98 864.80000 3.77E401 8.10FA03 1.19E403 1.19E403 3/30/98 877.80000 3.77FAOI 1.87E402 1.57E403 1.09E403 4/6/98 851.8MOO 3.77E401 9.88E403 1.27FA03 1.17FA03 4/13/98 845.30000 3.77E401 1.45E402 1.48FA03 1.21FA03 4/20/98 849.90000 3.77E401 1.54E402 1.48E403 1.10E403 4/27/98 855.00000 3.77E401 1.75E402 1.57FA03 1.16E403 5/4/98 849.40000 3.77E401 1.30E402 1.39FA03 1.13E403 5/11/98 848.90000 3.77FAOI 8.92FA03 1.25E403 1.24FA03 5/18/98 808.30000 3.77FAOI 1.40E402 1.51E403 1.29E403 5/26/98 897.90000 3.77E401 1.96E402 1.62E403 1.21E403 6/ I/98 701.30000 3.77E401 1.54FA02 1.73E403 1.55E403 6/8/98 SM.80000 3.77E401 1.69E402 1.63FA03 1.30E403 6/15/98 798.00000 3.77E401 1.40E402 1.54E403 1.36E403 6/22/98 810.70000 3.77E401 1.87E402 1.67FA03 1.27E403 6/29/98 812.90000 3.77E401 1.97E402 1.70E403 1.24E403 2 - SR 1134 I/5/98 871.90000 3.78E401 1.65E402 1.52E403 1.19E403 I/12/98 739.70000 3.78E401 1.29FA02 1.53E403 136 FA03 I/19/98 741.80000 3.78FA01 1.27E402 1.52E403 136E403 I/26/98 730.70000 3.7SE401 1.51E402 1.66E403 1.46FA03 2/2/98 729.10000 3.78E401 130FA02 1.58E403 1.47E403 2/9/98 740.50000 3.78E401 1.19FA02 1.49FA03 137E403 2/16/98 702.60000 3.78E4Q1 2.00E402 1.82E403 1.29E403 2/23/98 751.20000 3.78E401 1.03E402 1.37FA03 1.25E403 3/2/98 723.90000 3.78E401 1.95FA02 1.82E403 1.42E403 3/9/98 731.10000 3.77E401 1.30E402 1.55E403 138E403 3/16/98 703.50000 3.77E401 2.24E402 1.95FA03 1.45E403 3/23/98 771.80000 3.77E401 9.01E403 133 E403 1.33E403 3/30/98 711.10000 3.77FAOI 2.15FA02 1.89E403 1.35E403 2
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError 2 - SR 1134 4/6/98 748.90000 3.77E401 1.378402 1.55E403 1.33PA03 4/13/98 723.20000 3.778401 1.69E402 1.728403 1.42FA03 4/20/98 748.00000 3.77FAOI 1.59E402 1.62E403 1.258403 4/27/98 712.40000 3.77E401 2.038402 1.86FA03 1.40E403 5/4/98 743.8MOO 3.77E401 1.32E402 1.52FA03 1.29E403 5/I I/98 739.10000 3.77E401 9.34E403 IAOFA03 1.428403 5/18/98 761.70000 3.77FAOI IAOFA02 1.568403 1.37E403 5/26/98 863.50000 3.77PAOI 1.878402 1.63FA03 1.268403 6/ I/98 636.30000 3.77FAOI 1.82FA02 1.95E403 1.71E403 6/ $ 98 759.00000 3.77FAOI 1.71FA02 1.69E403 1.38FA03 6/15/98 813.70000 3.77E401 1.29FA02 1.47E403 1.338403 6/22/98 739.40000 3.77E401 1.888402 1.77E403 1.40E403 6/29/98 763.60000 3.77E401 2.04E402 1.79E403 1.32E403 4 - NEW HILLNEAR1ST BAPTIST CH I/5/98 891.90000 3.78FAOI 1.67FA02 1.51FA03 1.168403 I/12/98 781.80000 3.78FAOI 1.05FA02 137FA03 1.29FA03 I/19/98 793.00000 3.78FAOI 1.38E402 1.50E403 1.27E403 I/26/98 737.90000 3.78E401 1.46E402 1.638403 1.44FA03 2/2/98 757.60000 3.78E401 1.23E402 1.51E403 1.41E403 2/9/98 751.20000 3.78E401 1.04E402 1.41E403 1.358403 2/16/98 751.80000 3.78E401 1.93E402 1.738403 1.21E403 2/23/98 762.00000 3.78E401 1.048402 1.36E403 1.24E403 3/2/98 76430000 3.78PAOI 1.608402 1.638403 1.35E403 3/9/98 757.70000 3.77FAOI 1.53E402 1.61E403 1.33FA03 3/16/98 763.50000 3.77E401 1.98E402 1.778403 1.34E403 3/23/98 763.60000 3.77E401 1.03FA02 IAOE403 1.34E403 3/30/98 769.60000 3.77E401 2.02FA02 1.76E403 1.24E403 4/6/98 757.2 MOO 3.77E401 1.24E402 1.48E403 1.32E403 4/13/98 762.50000 3.778401 1.628402 1.64E403 1.35E403 4/20/98 763.20000 3.77E401 1.68FA02 1.638403 1.22E403 4/27/98 765.10000 3.77E401 1.98FA02 1.76E403 1.30E403 5/4/98 763.10000 3.77E401 1.28E402 1.48E403 1.26E403 5/11/98 761.50000 3.77E401 9.518403 1.38E403 1.38E403 5/1a98 738.60000 3.77FAOI 1.378402 1.58FA03 1.41E403 5/26/98 835.20000 3.77E401 2.17E402 1.76E403 1.30E403 6/ I/98 630.000M 3.77E401 1.86E402 1.98FA03 1.72E403 6/8/98 704.80000 3.77E401 1.95E402 1.86E403 1.48E403 6/15/98 734.60000 3.77E401 1.73E402 1.75E403 1.48FA03 6/22/98 738.70000 3.77E401 1.90E402 1.788403 1.40E403 6/29/98 728.70000 3.77E401 2.16FA02 1.888403 1.38E403 5 -PITTSBORO-COÃEOL I/5/98 872.10000 3.78E401 1.75E402 1.568403 1.198403 3
Sample Point SampleDate Quantity Efficiency Activity 2 Si maError 5 - PITISBORO ~ CONTROL I/12/98 746.10000 3.78E401 9.36E403 1.37E403 1.35E403 I/19/98 754.90000 3.78E401 1.47E402 1.58FA03 1.33E403 I/26/98 751.70000 3.78E401 1.49E402 1.62E403 1.42E403 2/268 73730000 3.78E401 1.21E402 1.53E403 1.45FA03 2/9/98 740.80000 3.78E401 9.91FA03 1.40E403 1.37E403 2/16/98 729.60000 3.78E401 2.14E402 1.83E403 1.25E403 2/23/98 740.20000 3.78E401 9.98E403 1.37FA03 1.27FA03 3/2/98 735.90000 3.78FAOI 1.57E402 1.66E403 1.40E403 3/9/98 743.90000 3.77E401 1.64E402 1.67E403 1.36E403 3/16/98 739.70000 3.77E401 2.22E402 1.89FA03 1.38E403 3/23/98 734.10000 3.77FAOI 9.80E403 1.41E403 1.40FA03 3/30/98 737.20000 3.77E401 2.28E402 1.89E403 130FA03 4/6/98 723.60000 3.77FAOI 1.17E402 1.50E403 1.38E403 4/13/98 732.60000 3.77FAOI 1.62E402 1.69E403 1.40E403 4n0/98 740.00000 3.77E401 1.84FA02 1.72FA03 1.26E403 4n7/98 736.30000 3.77E401 2.19E402 1.88E403 1.35E-003 5/4/98 737.10000 3.77E401 1.47E402 1.59E403 1.30FA03 5/I I/98 743.90000 3.77E401 1.03E402 IA4E403 1.41E403 5/18/98 729.20000 3.77E401 1.42E402 1.62E403 1.43E403 5n6/98 828.50000 3.77E401 2.07E402 1.74E403 1.31E403 6/ I/98 628.10000 3.77E401 1.75E402 1.94FA03 1.73FA03 6/8/98 729A 0000 3.77FAOI 1.66FA02 1.71E403 1.43E403 6/15/98 735.20000 3.77FAOI 1.75E402 1.75E403 1.48E403 6i22/98 742.40000 3.77E401 2.03FA02 1.83FA03 1.39E403 6/29/98 727.70000 3.77E401 2.00E402 1.82FA03 1.39E403 26 - SPILLWAYON MAINRES I/5/98 878.60000 3.78E401 1.76E402 1.55E403 1.18E403 I/12/98 744.00000 3.78E401 1.18E402 1.48E403 1.35E403 I/19/98 748.00000 3.78E401 1.05E402 1.42FA03 1.34E403 I/26/98 740.30000 3.78E401 1.22E402 1.53FA03 1.44E403 2/2/98 726.30000 3.78E401 9.06FA03 1.4IFA03 1.47E403 2/9/98 706.70000 3.78E401 8.97E403 1.40E403 1.43E403 2/16/98 727.60000 3.78E401 1.82E402 1.72E403 1.25FA03 2n3/98 734.10000 3.78FAOI 1.08E402 1.42E403 1.28FA03 3/2/98 733.50000 3.78E40) 1.77E402 1.74E403 1.40E403 3/9/98 725.60000 3.77FAOI 1.21E402 1.52E403 139 E403 3/16/98 727.60000 3.77E401 2.27E402 1.93E403 1.40FA03 3/23/98 723.90000 3.77E401 7.86E403 1.33E403 1.42FA03 3i30/98 724.20000 3.77FAOI 2.24FA02 1.90FA03 1.32E403 4/6/98 733.50000 3.77E401 1.16E402 1.48E403 1.36E403 4/13/98 720.70000 3.77E401 1.73E402 '.74E403 1.42E403 4
Sample Point SampleDate Quantity Efficiency Activity 2 Si maError 26 - SPILLWAYON MAINRES 4/2088 725.40000 3.77FAOI 1.53E402 1.62FA03 1.28E403 4/27/98 723.40000 3.77FAOI 2.13FA02 1.88FA03 1.38E403 5/4/98 737.60000 3.77E401 1.29E402 1.51E403 1.30E403 5/I I/98 726.70000 3.77FAOI 9.08E403 1.40E403 1.45E403 5/18/98 786.90000 3.77E401 136FA02 1.52E403 1.33E403 5/2688 88930000 3.77E401 1.46FA02 1.46E403 1.22E403 6/ I/98 688.00000 3.77FAOI 1.71E402 1.81FA03 1.58FA03 6/8/98 775.90000 3.77FAOI 134E402 1.52E403 1.35E403 6/15/98 788.70000 3.77FAOI 1.66FA02 1.65FA03 138FA03 6/2288 775.50000 3.77FAOI 2.02FA02 1.77E403 1.33E403 6/2988 750.40000 3.77E401 2.08E402 1.82FA03 1.34E-003 47 - SSW SECTOR 3.4 MI FROM SITE I/5/98 769.80000 3.78E401 1.77E402 1.69E403 1.35FA03 I/1288 660.20000 3.78E401 9.28E403 1.48FA03 1.52E403 I/19/98 667.90000 3.78FAOI 1.28E402 1.63E403 1.51E403 I/26/98 663 40000 3.78E401 1,29E402 1.67E403 1.61E403 2/2/98 654.90000 3.78FAOI 1.47E402 1.77FA03 1.64E403 2/988 657.20000 3.78FAOI 9.86E403 1.52FA03 1.54E403 2/16/98 651.10000 3.78FAOI 1.92E402 1.88FA03 1.40E403 2/23/98 658.70000 3.78FAOI 1.02FA02 1.49E403 1.43E403 3/2/98 658.90000 3.78FAOI 1.68E402 1.82E403 1.56FA03 3/9/98 652.10000 3.77FAOI 1.59E402 1.79E403 1.55E403 3/16/98 66230000 3.77E401 1.91E402 1.91E403 1.54E403 3/23/98 65790000 3.77E401 8.72E403 1.47FA03 1.56E403 3/30/98 659.70000 3.77E401 2.09E402 195 E403 1.45E403 4/6i98 677.40000 3.77FAOI 1.11E402 1.54E403 1.47E403 4/1388 661.80000 3.77E401 1.61E402 1.79FA03 I.SSE403 4n08s 66730000 3.77E401 1.78E402 1.81FA03 1.40E403 5/4/98 667.60000 3.77E401 1.41E402 1.67E403 1.43E403 5/I 188 662.00000 3.77FAOI 1.14E402 1.60E403 1.59E403 5/1888 635.80000 3.77FAOI 1.66E402 1.87E403 1.64E403 sn68s 720.40000 3.77E401 1.67E402 1.75E403 1.51E403 6/188 550.10000 3.77E401 1.89E-002 2.17E403 1.97FA03 6/8/98 635.40000 3.77E401 1.51E402 1.81FA03 1.64FA03 6/15/98 633.90000 3.77E4OI 1.81FA02 1.95E403 1.71E403 6/22/98 642.50000 3.77FAOI 2.08FA02 2.01FA03 1.61FA03 Piant: HNP MedlaT ei DRINKINGiYATER LITERS 38 - CAPE FEAR PLANT INTAKE- CO~iOL 101/98 1.00000 3.29FAOI 3.59E+000 8.32E401 9.02E401 2/28/98 1.00000 3.53FAOI 3.22E+000 7.29E401 7.43E401 3/3188 1.00000 3.51E401 1.82E+000 7.42E401 9.94E401 5
Sample Point Sam leDate Quantity Efficiency Activity 2 SigmaError LLD 38 - CAPE FEAR PLANT INTAKE- CONTROL 4/30/98 1.00000 3.20FAOI 2.62E+000 7.74E401 9.09FAOI 561/98 1.00000 3A8FAOI 2.43E+000 7.71E401 9.65FAOI 6/30/98 1.00000 3.24E401 3.14E+000 9.09E401 1.14EW00 40 - LILLINGTON- CAPE FEAR RIVER l/31/98 1.00000 3.27E401 4."4E+000 8.78E401 9.08FAOI 2/28/98 1.00000 3.56FAOI 3.80E+000 7.64FAOI 7.36FAOI 3/31/98 1.00000 3.45FAOI 2.14E+MO 7.75E401 1.01E&00 4/30/98 1.00000 3.30FAOI 2.65E+000 7.59FAOI 8.81FAOI 561/98 1.00000 3.41E401 2.43E+000 7.84E401 9.85E401 6/30i98 1.00000 3.24E401 3.36E+000 9.22FAOI 1.14E+000 51 - WATER TREATMENTBLDG AT HARRIS PLANT I/31/98 1.00000 e 3 30E401 2.24E+000 7.37E401 9.ME401 2/28/98 1.00000 3.44E401 3.27E+000 7.46FAOI 7.62E401 3i31/98 1.00000 3.12FAOI 1.88E+000 8.23FAOI 1.12 K~0 4/30/98 1.00000 3.21E401 2.10E+000 7.34FAOI 9.06E401 561/98 1.00000 3.22E401 2A6E+000 8.22E-001 1.04E+000 6/30/98 1.00000 3.35E401 1.77E+OM 7.98E401 1.10E+000 Plant: HNP Anal wb: BETA MedlaT e: SURFACEIVATER LITERS 26 - SPILLWAYON MAINRES I/31/98 1.00000 3.52E401 3.05E&00 7.58FAOI 8.43E401 2/28/98 1.00000 3.62E401 3.16E+000 7.13E401 7.24E401 3/31/98 1.00000 3.61E401 2.12E+000 7.45E401 9.66E401 4/30/98 1.00000 3.58E401 2.21E+000 6.83E401 8.12E401 561/98 1.00000 3.61E401 1.55E+000 6.88E401 930E401 6/30/98 1.00000 3.60E401 2.55E+000 8.01E401 1.02E+000 38 - CAPE FEAR PLANT INTAKE- CONTROL I/31/98 1.00000 3.29FAOI 3.59E&00 8.32E401 9.02E401 2/28/98 1.00000 3.53E401 3.22E+000 7.29E401 7.43E401 3/31/98 1.00000 3.51FAOI 1.82E+000 7.42E401 9.94FAOI 460/98 1.00000 3.20E401 2.62E+000 7.74FAOI 9.09E401 561/98 1.00000 3.48E401 2.43E+000 7.71FAOI 9.65E401 6/30/98 1.00000 3.24E401 3.14E+000 9.09FAOI 1.14E+000 40 - LILLINGTON- CAPE FEAR RIVER I61/98 1.00000 3.27E401 4.24E&00 8.78E401 9.08FAOI 2/28/98 1.00000 3.56E401 3.80E+000 7.64E401 7.36E401 3/31/98 1.00000 3.45FAOI 2.14E+000 7.75E401 I.0 I E+000 4/30/98 I.MOOO 3.30E401 2.65E+000 7.59FAOI 8.81E401 5/31/98 1.00000 3.41E401 2.43E+000 7.84E401 9.85E401 660/98 1.00000 3.25E401 3.35E+000 9.19E401 1.13E+000 Plant: HNP Anal wbt IODINE iltediaT e: AIRCARTRIDGE CUBICMETERS I - SR 1134 AT INT SR 1011 - DIXIEPIPELINE I/5/98 1024.10000 1.09E402 I/12/98 895.80000 1.51E402 I/19/98 91 IA0000 1.66E402
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError I - SR 1134 AT INT SR 1011 - DIXIEPIPEUNE In6/98 862.40000 1.4IE402 2/23/98 91130000 9.20FA03 2/16/98 867.30000 1.83FA02 2/9/98 850.70000 9.87FA03 2/2/98 867.60000 9.65FA03 3/2I98 845.00000 7.14FA03 3/9/98 866.80000 1.53FA02 4/20/98 849.90000 1.62FA02 3/16I98 863.20000 1.53FA02 3/23/98 864.80000 1.20FA02 3/30/98 877.80000 6.84PA03 4/6I98 851.80000 1.43FA02 4/13I98 845.30000 1.60PA02 4/27/98 855.00000 6.95FA03 6/ I/98 701.30000 1.62FA02 5/4/98 849.40000 1.45FA02 5/I I/98 848.90000 1.05FA02 5/18/98 80830000 1.47FA02 I 5/25/98 897.90000 1.19FA02 6/8/98 800.80000 1.21FA02 6/15/98 798.00000 1.05FA02 6/22/98 810.70000 1.28FA02 6/29/98 812.90000 1.04FA02 2 - SR 1134 I/5/98 871.90000 1.69FA02 I/12/98 739.70000 2.30FA02 I/19/98 741.80000 2.97FA02 In6/98 730.70000 1.69FA02 2/23/98 751.20000 2.19FA02 2/16/98 702.60000 2.17FA02 2/9/98 740.50000 2.74FA02 2/2/98 729.10000 1.80FA02 3/2/98 723.90000 2.94FA02 3/9/98 731.10000 1.99FA02 4n0/9s 748.00000 1.58FA02 I
3/16/98 703.50000 2.10E402 3/23/98 771.80000 1.54FA02 3/30/98 711.10000 1.62FA02 4/6/98 748.90000 2.16FA02 4/13I98 723.20000 2.27FA02 4/27/98 712.40000 1.81FA02 7
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError 2 - SR 1134 6/ I/98 63630000 1.80E402 5/4/98 743.80000 1.61E402 5/I I/98 739.10000 1.81E402 5/18/98 761.70000 2.28E402 5/25/98 863.50000 1.79FA02 6/198 759.00000 1.00FA02 6/15/98 813.70000 1.90FA02 6n2/98 739.40000 1.55E402 6/29/98 763.60000 1.96FA02 4 - NEW HILLNEAR1ST BAPTISTCH I/5/98 89190000 2.32E402 I/12/98 781.80000 1.69E402 I/19/98 793.00000 1.97FA02 in6/98 737.90000 2.12E402 2/9/98 751.20000 2.67FA02 2/23/98 762.00000 1.73E402 2/16/98 751.80000 1.43FA02 2/2/98 757.60000 1.73E402 3/2/98 76430000 1.74FA02 3/9/98 757.70000 9.98E402 4/20/98 763.20000 IAOE402 3/16/98 763.50000 1.41E402 3/23/98 763.60000 2.02FA02 3/30/98 769.60000 9.96FA03 4/6/98 757.20000 1.94FA02 4/13/98 762.50000 1.40FA02 4/27/98 765.10000 2.22E402 6/ I/98 630.00000 1.64FA02 5/4/98 763.10000 2A6FA02 5/11/98 761.50000 2.59FA02 5/18/98 738.60000 230FA02 sn5/98 835.20000 2.47E402 6/8/98 704.80000 1.70E402 6/15/98 734.60000 2.70E402 6/22/98 738.70000 1.79E402 6i29/98 728.70000 1.48E402 5 -PITTSBORO-CONTROL I/5/98 872.10000 9.84FA03 I/12/98 746.10000 1.61FA02 I/19/98 754.90000 1.47FA02 In6/98 751.70000 1.49E402 2/23/98 740.20000 2.17E402 8
Sample Point SampleDate Quantity Efficiency Activity 2 Si maError 5 - PITTSBORO- CONTROL 2/16/9S 729.60000 3.13E402 2/9/98 740.80000 2.55E402 2/2/98 737.30000 2.29E402 3/2/98 735.90000 1.16E402 3/9/98 743.90000 8.64E403 4/20/98 740.00000 2.37FA02 3/16/98 739.70000 1.14E402 3n3/98 734.10000 2.69FA02 3/30/98 737.20000 1.64E402 4/6/98 723.60000 1.47E402.
4/13/9S 732.60000 2.31E402 4/27/98 73630000 1.46E402 6/ I/98 628.10000 2.05FA02 5/4/98 737.10000 232 E402 5/11/98 743.90000 8.26FA03 5/18/98 729.20000 3.33E402 5n5/98 828.50000 1.56FA02 6/8/98 729 40000 1.82E402 6/15/98 735.20000 8.08E403 6/22/9S 742.40000 2.57E402 6/29/98 727.70000 2.17FA02 26 - SPILLWAYON MAINRES I/5/98 878.60000 1.64E402 I/12/98 744.00000 2.05FA02 I/19/98 748.00000 1.54FA02 In6/98 740.30000 2.16E402 2/23/98 734.10000 1.14E402 2/16/98 727.60000 8.15E403 2/9/98 706.70000 1.46FA02 2/2/98 726.30000 8.16FA03 3/2/98 733.50000 1.49E402 3/9/98 725.60000 1.63E402 4n0/98 725.40000 1.64E402 3/16/98 727.60000 1.88B402 3/23/98 723.90000 1.43E402 3/30/98 724.20000 2.26FA02 4/6/98 733.50000 1.82FA02 4/13/98 720.70000 1.65FA02 4/27/98 723.40000 8.23FA03 6/ I/98 688.00000 1.44FA02 5/4/98 737.60000 1.72E402 9
Sample Point Sam IeDate Quantity Efficiency Activity 2 Si maError 26 - SPILLWAYON MAINRES 5/I I/98 726.70000 1.86FA02 5/18/98 786.90000 1.77FA02 snses 88930000 1.90FA02 6/8/98 775.90000 2.51FA02 6/15e8 788.70000 2.18FA02 6/22e8 775.50000 2.34FA02 6/29/98 750.40000 1.78FA02 47 - SSW SECTOR 3.4 MI FROM SITE I/5/98 769.80000 2.70FA02 I/12/98 660.20000 2.231A02 I/19/98 667.90000 1.45FA02 In6es 663.40000 2.04FA02 2/23e8 658.70000 2.32FA02 2/16/98 651.10000 1.75FA02 2/9/98 657.20000 1.74EA02 2/2e8 654.90000 1.81FA02 3/2/98 658.90000 2.07E402 3/9es 652.10000 1.30FA02 4noes 667.30000 2.46FA02 3/16es 662.30000 1.47E402 3/23/98 657.90000 2.IOE402 3/30i98 659.70000 2.02FA02 4/6i98 667.40000 2.55E402 4/13/98 661.80000 1.04FA02 6/ les 550.10000 2.08FA02 5/4e8 667.60000 3.20FA02 5/11/98 662.00000 1.31FA02 5/18/98 635.80000 2.46FA02 snses 720.40000 1.73FA02 6/8/98 635.40000 1.89FA02 6/15/98 633.90000 2.31FA02 6/22/98 642.50000 1.89FA02 Plant: HNP Anal vis: IODINE Media e: DRINKINGIVATERLITERS 38 - CAPE PAR PLANT INTAKE- CONTROL I/5/98 4.00000 3.19FA01 I/12es 4.00000 5.IOE401 I/19/98 4.00000 4.56FA01 I/26e8 4.00000 4.35FA01 2/23/98 4.00000 3.19FA01 2/2/98 4.00000 4.25FA01 2/9/98 4.00000 3.41FA01 10
Sample Point SampleD ate Quantity Efficiency Activity 2 Si maError 38 - CAPE FEAR PLANT INTAKE- CONTROL 2/16/98 4.00000 3.60FAOI 3/2/98 4.00000 5.98FAOI 3/9/98 4.00000 3.26FAOI 3/16/98 4.00000 3.28FAOI 3/23/98 4.00000 4.74FAOI 3/30/98 4.00000 3.45FAOI 4/6/98 4.00000 3.31FAOI 4/13/98 4.00000 3.62FAOI 5/II/98 4.00000 4.07FAOI 5/26/98 4.00000 3.64FAOI 5/4/98 4.00000 3.50FAOI 5/18/98 4.00000 4.10FAOI 4/20/98 4.00000 3.75FAOI 4/27/98 4.00000 3.58FAOI 6/ I/98 4.00000 4.50FAOI 6/8/98 4.00000 3.49FAOI 6/15/98 4.00000 4.30FAOI 6/22/98 4.00000 3.80FAOI 6/29/98 4.00000 4.58FAOI 40 - LILLINGTON- CAPE FEAR RIVER I/5/98 4.00000 4.53FAOI I/12/98 4.00000 5.90FAOI I/19/98 4.0MOO 4.67FAOI I/26/98 4.00000 4.78FAOI 2/23/98 4.00000 4.42FAOI 2/2/98 4.00000 4.38FAOI 2/9/98 4.00000 3.92FAOI 2/16/98 4.00000 4.34FAOI 3/2/98 4.00000 4.54E401 3/9/98 4.00000 4.18FAOI 3/16/98 4.00000 5.58E401 3/23/98 4.00000 3.13FAOI 3/30/98 4.00000 4.2 IFAOI 4/6/98 4.00000 4.19FAOI 4/13/98 4.0MOO 4.16FAOI 5/11/98 4.00000 3.44FAOI 5/26/98 4.00000 4.68FAOI 5/4/98 4.00000 4.20FAOI 5/18/98 4.00000 5.01FAOI 4/20/98 4.00000 4.65FAOI 4/27/98 4.00000 4A4FAOI 11
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError 40 - LILLINGTON- CAPE FEAR RIVER 6/ I/98 4.00000 4.29FAOI 6/8/98 4.00000 4.65FAOI 6/15i98 4.00000 5.52FAOI 6/22/98 4.00000 4.40E40I 6/29/98 4.00000 3.58FAOI 51 - WATER TREATMENTBLDQ AT HARRIS PLANT I/5/98 4.00000 4.61FAOI I/1268 4.00000 3.20FAOI I/19/98 4.00000 3.12FAOI I/26/98 4.00000 3.99FAOI 2/23/98 4.00000 5.65FAOI 2/2/98 4.00000 5.40E401 2/9/98 4.00000 4.58E401 2/16/98 4.00000 4.26FAOI 3/2/98 4.00000 5.33FAOI 3/9/98 4.00000 4.29FAOI 3/16/98 4.00000 4.50E401 3/23/98 4.00000 4.22FAOI 3/30/98 4.00000 4.26FAOI 4/6/98 4.00000 4.30FAOI 4/13/98 4.00000 4.37FAOI 5/11/98 4.00000 4.19FAOI 5/26i98 4.00000 4.94FAOI 5/4/98 4.00000 4.49FAOI 5/18/98 4.00000 3.69FAOI Sn0/98 4.00000 3.93FAOI 4/27/9S 4.00000 4.55FAOI 6/ I/98 4.00000 3.65E401 6/8/98 4.00000 4.97FAOI 6/15/98 4.00000 3.80FAOI 6i22/98 4.00000 4.59E401 6i29i98 4.00000 4.52FAOI Plant: HNP Anal >is: IODINE McdiaT c: MILK LITERS 5 -PITISBORO-CONTROL I/5/98 4.00000 3.56FAOI I/19/98 4.00000 4.33FAOI 2/16/98 4.00000 5.28FAOI 2/2/98 4.00000 4.58FAOI 3/2/98 4.00000 4.74FAOI 3/16/98 4.00000 3.61E401 4/6/98 4.00000 5.70FAOI 12
Sam ie Point SampleDate Quantity Efficiency Activity 2 SigmaError 5 - PZITSBORO- CONTROL 5/4/98 4.00000 5.30E401 5/19/98 4.00000 3.93FA01 4noes 4.00000 5.09FAOI 6/ le8 4.00000 5.16FA01 6/15/98 4.00000 4.18FA01 Plant: HNP Anal ala: IODINE MedlaT e: SURFACE WATER LITERS 38 - CAPE FEAR PLANT INTAKE- CONTROL I/5e8 4.00000 3.19FA01 I/12es 4.00000 5.10FAOI I/19es 4.00000 4.56FAOI I/26e8 4.00000 4.35E401 2/23/98 4.00000 3.19FA01 2/2/98 4.00000 4.25FAOI 2/9es 4.00000 3.41FAOI 2/16es 4.00000 3.60FA01 3/2/98 4.00000 5.98E401 3/9es 4.00000 3.26FAOI 3/16es 4.00000 3.28FAOI 3n3e8 4.00000 4.74E401 3i30/98 4.00000 3.45FA01 4/6/98 4.00000 3.31E401 4/13es 4.00000 3.62FA01 sn6es 4.00000 3.64FA01 5/4e8 4.00000 3.50FA01 5/18e8 4.00000 4.10FAOI 4noes 4.00000 3.758401 4/27e8 4.00000 3.58FA01 6/ le8 4.00000 4.50FA01 6/ ses 4.00000 3 49E401 6/15es 4.00000 4.30E401 6/22/98 4.00000 3.80FAOI 6/29/98 4.00000 4.58FA01 5/11/98 4.00000 4.07FA01 40 - LILUNGTON- CAPE FEAR RIVER I/5e8 4.00000 4.53E401 I/12/98 4.00000 5.90FAOI I/19/98 4.00000 4.67FA01 I/26i98 4.00000 4.78E401 2/23/98 4.00000 4.42FA01 2/2/98 4.00000 4.38E401 2/9e8 4.00000 3.92FAOI 13
Sample Point SampleDate Quantity Efficiency Activity 2 Si maError 40 - ULUNGTON- CAPE FEAR RIVER 2/16/98 4.00000 4.34FAOI 3/2/98 4.00000 4.54E401 3/9/98 4.00000 4.18E401 3/16/98 4.00000 5.58E401 3/23/98 4.00000 3.13E401 3/30/98 4.00000 4.21E401 4/6/98 4.00000 4.19FAOI 4/13/9S 4.00000 4.16E401 5/ll/98 4.00000 3.44E401 5/26/98 4.00000 4.68E401 5/4/98 4.00000 4.20FAOI 5/18/98 4.00000 S.0 IE401 4/20/98 4.00000 4.65E401 4/27/98 4.00000 4.44E401 6/ I/98 4.00000 4.29E401 6/8/98 4.00000 4.65E401 6/15/98 4.00000 5.52FAOI 6/22/98 4.00000 4.40E401 6/29/98 4.00000 3.58FAOI Plant: HNP Anal ala: TRITIUM MedlaT et DRINKINGIVATER LITERS 38 - CAPE FEAR PLANT INTAKE- CONTROL I/31/98 .00500 2.82FAOI O.OOE+000 O.OOE+000 3.01E+002 2/28/98 .00500 2.83E401 O.OOE+000 O.OOE+000 2.94E+002 3/3168 .00500 2.83E401 O.OOE+000 O.OOE+000 2.97E&02 4/30/98 .00500 2.86E401 0.00E+000 O.OOE+000 2.90E+002 6/30/98 .00500 2.82E401 O.OOE+000 O.OOE+000 3.01E+002 5/31/98 .00500 2.84E401 O.OOE+000 O.OOE+000 2.97E+002 40 - LILUNGTON- CAPE FEAR RIVER I/31/98 .00500 2.82FAOI O.OOE+000 O.OOE+000 3.01E&02 2/28/98 .00500 2.83E401 0.00E+000 O.OOE+000 2.94E&02 3/31/98 .00500 2.83E401 O.OOE+000 O.OOE+000 2.97E&02 4/30/98 .00500 2.86E401 0.00E&00 O.OOE+000 2.90E+002 6/30/98 .00500 2.82FAOI O.OOE+000 O.OOE+000 3.01E+002 5/31/98 .00500 2.84E401 O.OOE+MO O.OOE+000 2.97E+002 51 - KVATERTREATMENTBLDG AT HARRIS PLANT Ii31/98 .00500 4.36E401 2.73E+003 3.52E+002 4.83E+002 2/28/98 .00500 2.83E401 2.31E+003 S.SSE&02 8.38E+002 3/31/98 .00500 2.83E401 2.i2E+003 S.SSE+002 8.51E+002 4/30/98 .00500 2.86E401 1.43E+003 5.36E+002 8.36E+002 6/30/9S .MSM 2.82E401 I. 17E+003 1.9IE&02 3.0IE&02 5/31/9S .00500 2.84E401 O.OOE+000 O.OOE+OM 8.67E+002 14
Sample Point SampleDate Quantity Efficiency Activity 2 Si maError Plant: HNP Anal vtst TRITIUM hfediaT e: GROUNDWATER LITERS 39 - DEEP WELLNEAR DIABASE DIKES 3/5/98 .00500 2.83E401 O.OOE+000 O.ME+000 2.98E+002 6/16/98 .00500 2.84FAOI 0.00E+000 O.OOE+000 3.00E+002 57 -0.4 MI SSW SECTOR N BANKESW INTAKE 3/5/98 .aoSoo 2.83FAOI Q.QQE+OQO Q.QQE&00 2.98E+002 6/16/98 .00500 2.84E401 Q.QOE+000 O.OOE+000 3.ME+002 58 - 0.5 Ml WSW SECTOR N BANKESW INTAKE 3/5/98 .00500 2.83E401 6.74E+002 1.86E+002 2.98E&02 6/16/98 .00500 2.84FAOI 3.13E+002 1.84E+002 3.00E+002 59 - 0.5 MI NNE SECTOR(NEAR CONSTRUCTION R 3/5/98 .00500 2.83FAOI Q.OOE+000 O.OOE+000 2.98E+OQ2 6/16/98 .00500 2.84FAOI Q.OQE+000 O.OOE+000 3.00E+002 60 -0.5 MI ESE SECTOR W BANKOFTHOMAS CREE 3/5/98 .00500 2.83FAOI Q.OOE+000 O.OOE+000 2.97E&02 6/16/98 .00500 2.$ 4FAOI O.OOE+oao O.OQE+000 3.00E+002 Plant: HNP Anal wb: TRITIUihI Media e: SURFACEIVATER LITERS 26 - SPILLWAYON MAINRES I/31/98 .00500 4.36FAOI 3.63E+003 3.69E+002 4.83E+002 2/28/98 .OOSQO 2.83FAOI 3.45E+003 5.76E+002 8.38E&02 3f31i98 .00500 2.83EAOI 3.06E+003 5.76E+002 8.5 IE+002 4f30i98 .00500 2.86FAOI 3.98E+003 5.84E+002 8.36E+002 6/30/98 .00500 2.82FAQI 2.27E+M3 5.74E+002 8.74E+002 5/31/98 .00500 2.84FAOI 2.45E+003 5.73E+002 8.67E+002 38 - CAPE FEAR PLANT INTAKE- CONTROL If31/98 .00500 2.82E401 O.OOE+000 Q.OOE+000 3.01E+002 2/28/98 .00500 2.83FAQI Q.OOE+000 O.OOE&M 2.94E+002 3/31/98 .OOSOQ 2.83FAQI O.OOE+000 O.OOE+000 2.97E+002 4i30i98 .00500 2.86FAQI Q.QQE+Ma Q.QQE+000 2.90E+002 6/30/98 .00500 2.82FAQI O.QOE+QQQ O.OQE+000 3.01E+002 5/31i98 .MSQO 2.84E4101 Q.QQE+000 O.OQE+000 2.97E+002 40 - LILLINGTON- CAPE FEAR RIVER I/31/98 .00500 2.82FAQI O.OQE+000 O.OOE+000 3.01E+002 2/28/98 .QOSQQ 2.83FAQI O.OOE+000 Q.QOE+000 2.94E+002 3f31/98 .00500 2.83FAQI Q.OOE+000 O.QOE+000 2.97E+002 4/30/98 .00500 2.86FAQI Q.QOE+000 O.OOE+000 2.90E+002 6/30/98 .MSQO 2.82E401 Q.OOE+000 O.OOE+000 3.01E+002 5/31/98 .00500 2.84FA01 O.OQE+000 O.QOE+000 2.97E+002 15
CP&I, Radiological Environmental Monitoring Isotopic Analysis Report 4/8/99
Semian Analysis Report 4/8/99 Sam le point SamplcDatc Quantity Isotope Activity 2 Si maError Plant: HNP Anal wist GAMBIA MediaT e: AIRPARTICULATE Units: CUBICMETERS I - SR 1134 AT INT SR 1011 - DIXIEPIPELINE 2/15/98 11508.20000 BE-7 8.66E402 IAOE402 5/15/98 10730.20000 BF7 1.05E401 1.35E402 2 - SR1134 2/15/98 9648.90000 BE-7 1.21E401 1.93E402 2/15/98 964890000 KAO 1.85E402 1.16E402 5/15/98 9752.60000 BF7 1.22E401 1.60E402 4 - NEW HILLNEAR IST BAPTIST CH 2/15/98 10045.90000 BE-7 9.39FA02 1.78E402 5/15/98 9683.20000 BF7 1.16E401 1.46E402 5 - PITPSBORO- COiVRROL 2/15/98 9763.50000 BE-7 1.06E401 2.08E402 5/15/98 9534.00000 e BE-7 1.25FAOI 1.44E402 26 - SPILLWAYON MAINRES 2/15/98 9640.40000 BE-7 1.14E401 1.99E402 5/15/98 9822.00000 =BE-7 1.15E401 1.50FA02 47 - SSW SECTOR 3.4 MI FROM SITE 2/15/98 8674.10000 BE-1 1.08FAOI 2.22E402 5/15/98 7238.60000 BF7 1.08E401 1.56FA02 Plant: EINP Anal ais: GAMMA Media T e: BOTTOM FEEDER Units GRAMS Media: CATFISEI 44 - SITE VARIES WITHINHARRIS LAKE 5/4/98 523.20000 KAO 4.13E+000 933 FAOI 45 - SITE VARIES ABOVE BUCKHORN DAM- CON 5/4/98 835.90000 KAO 2.49E+000 6.85E401 Plant: HNP Anal vis: GAMMA Media e: BOTTOiM SEDIMENT Units: GRAMS 52 - HARRIS LAKECOOUNG TOWER MIXINGZO I/12/98 351.40000 KAO 9.90E+000 1.63E+000 I/12/98 351.40000 TL-208 3.20E401 1.28FAOI I/1268 351.40000 PB-212 9.90E401 1.69E401 I/12/98 351.40000 BI-214 6.73E401 2.64E401 I/12/98 351.40000 PB-214 9.79E401 231E401 I/12/98 35IA0000 RA-226 1.79E+000 1.60E+000 I/1268 351.40000 AC-228 1.52E+000 5A4FAOI I/12/98 351.40000 C&60 2.69E+000 2.58FAOI I/1288 351.40000 SB-125 1.33E+000 2.96E401 I/12/98 351.40000 CS-137 5.23E401 1.09E401 5/5/98 821.90000 KAO 9.28E+000 1.31E&00 5/5/98 821.90000 TI 208 3.30E401 I.OOE401 5/5/98 821.90000 PB-212 9.18E401 1.79E401 5/5/98 821.90000 BI-214 6.68E401 1.67FAOI 5/5/98 821.90000 PB-214 7.66FAOI 1.59E401 5/5/98 821.90000 AC-228 9.74E401 4.72E401 5/5/98 821.90000 CCh60 2.17E+000 1.96E401 5/5/98 821.90000 SB-125 6.47E401 2.42E401 5/5/98 821.90000 CS-137 4.45E401 1.03E401 Plant: HNP Anal its: GAMMA MediaT e: BROADLEAFVEGETATION Units: GRAMS Media: DOGWOOD 66 - 1.33 MI SSW SECTOR 5/19/98 361.40000 BE-7 8.91E401 3.01FAOI
Sample Point SampleDate Quantity Isotope Activity 2 SigmaError 5/19/98 361.40000 KAO 2.86E+000 5.90E401 5/19/98 361.40000 I-131 3.21E402 5/19/98 361.40000 CS-134 3.56E402 5/19/98 361.40000 CS-137 3.12E402 6/17/98 370.80000 BF7 1.01E+000 2.50FAOI 6/17/98 370.80000 KAO 1.89E&00 4.58FA01 6/17/98 370.80000 CS-137 7.26FA02 2.99FA02 6/17/98 370.80000 1-131 2.44FA02 6/17/98 370.80000 CS-134 2.89FA02 Plant: HNP Anal is: GAMMA MedlaT e: BROADLEAFVEGETATION Units: GRAMS Media: hIAPLE 65 - 1.36 MI S SECTOR 5/19/98 378.70000 BE-7 8.00E401 2.22FA02 5/19/98 378.70000 KAO 3.26E+000 5.11E401 5/19/98 378.70000 TI 208 3.26E+000 5.11FAOI 5/19/98 378.70000 PB-212 1.79FAOI 4.03E402 5/19/98 378.70000 BI-214 4.31E402 4.55E402 5/19/98 378.70000 I-131 1.88E402 5/19/98 378.70000 CS-134 2.66FA02 5/19/98 378.70000 CS-137 2.43FA02 6/17/98 400.70000 BE-7 1.21E+000 2.75E401 6/17/98 400.70000 KAO 2.92E+000 5.68FA01 6/17/98 400.70000 I-131 2.82E402 6/17/98 400.70000 CS-134 3.39FAOZ 6/17/98 400.70000 CS-137 3.61E402 66 - 133MISSWSECTOR 5/19/98 483.80000 BE-7 6.41FAOI 1.55FAOI 5/19/98 483.80000 KRO 2.83E+000 4.55FA01 5/19/98 483.80000 I-131 1.85E402 5/19/98 483.80000 CS-134 2.03FA02 5/19/98 483.80000 CS-137 1.95FA02 6/17/98 46i.OOOOO BF7 5.84FAOI 2.33FA01 6/17/98 461.00000 KAO 3.50E+000 5.72E401 6/17/98 461.00000 I-131 2.71E402 6/17/98 461.00000 CS-134 3.75FAOZ 6/17/98 461.00000 CS-137 2.76E402 I
Plant: HNP Anal wisi GAiliilfA II fediaT BROADLEAFVEGETATION Units: GRAMS Medias POPLAR 65 - 1.36MISSECTOR 5/19/98 450.50000 KAO 2.88E+000 5.47FAol 5/19/98 450.50000 PB-212 7.72E402 4.19E402 5/19/98 450.50000 I-131 2.20E402 5/19/98 450.50000 CS-134 3.14E402 5/19/98 450.50000 CS-137 3.03E402
Sample Point SampleDate Quantity Isotope Activity 2 SigmaError 65 - 1.36MISSECTOR 6/17/98 515.90000 BF7 3.12FAOI 1.66FAOI 6/17/98 515.90000 KAO 2.47E+000 4.29FAOI 6/17/98 515.90000 I-131 2.14FA02 6/17/98 515.90000 CS-134 2.79FA02 6/17/98 515.90000 CS-137 2.42E402 Plant: HNP Anal sist GAMihIA htediaT e: BROADLEAFVEGETATIOiN Units: GRAMS htedia: AVEETGUM 65 - 1.36MIS SECTOR 5/19/98 513.20000 BF7 4.70FAOI 1.79FAOI 5/19/98 513.20000 KAO 1.86E+000 4.45FAOI 5/19/98 513.20000 , I-131 2.10FA02 5/19/98 513.20000 CS-134 2.80FA02 5/19/98 513.20000 CS-137 2.29FA02 6/17/98 504.50000 BE-7 6.70FAOI 1.86FA01 6/17/98 504.50000 KAO 2.15E&00 3.63FAOI 6/17/98 504.50000 1-131 1.74FA02 6/17/98 504.50000 CS-134 2.01FA02 6/17/98 504.50000 CS-137 1.70FA02 66 - 1.33 MI SSW SECTOR 5/19/98 501.80000 BE-7 6.39FAOI 1.92FAOI 5/19/98 501.80000 KAO 2.42E+000 4.09FAOI 5/19/98 501.80000 I-131 2.02FA02 5/19/98 501.80000 CS-134 2.80FA02 5/19/98 501.80000 CS-137 3.04FA02 6/17/98 501.80000 BE-7 7.68FAOI 1.69FAOI 6/17/98 501.80000 KAO 1.60E+000 3.41FAOI 6/17/98 501.80000 I-131 1.75FA02 6/17/98 501.80000 CS-134 2.22FA02 6/17/98 501.80000 CS-137 1.70FA02 Phnt: HNP Anal vis: GAhthIA htedta e: DRIiNKIiNGIVATER Units: LITERS 38 - CAPE FEAR PLANTINTAKE-CONTROL I/31/98 1.00000 NO-ACT 2/28/98 1.00000 NO-ACT 3/31/98 1.00000 NO-ACT 5/31/98 1.00000 NO-ACT 4/30/98 1.00000 NO-ACT 6f30/98 1.00000 NO-ACT 40 - LILUNGTON- CAPE FEAR RIVER I/31/98 1.00000 NO.ACT 2/28/98 1.00000 NO-ACT 3/31/98 1.00000 NO-ACT 5/31/98 1.00000 NO-ACT 4/30/98 1.00000 NO-ACT 6/30/98 1.00000 KAO 3.47E+002 7.78E+001
Sample Point Sam leDate Quantity Isotope Activity 2 Sigmamrror 51 - WATER TREATMENTBLDG AT HARRIS PLA I/31/98 1.00000 NO-ACT 2/28/98 1.00000 NO-ACT 3/31/98 1.00000 NO-ACT 5/31/98 1.00000 NO-ACT 4/30/98 1.00000 NO-ACT 6/30/98 1.00000 NO-ACT Plant:HNP Anal ls:GAMMA MedhT e: FOODCROP Units: GRAMS Media: CABBAGE 54 - RD11891.7MINNE(WILKINSORMORRIS) 6/16/98 564.10000 BE-7 2.14E401 1.45E401 6/16/98 564.10000 , KRO 5.02E+000 . 5.33FAOI 6/16/98 564.10000 1-131 t 2.09FA02 6/16/98 564.10000 CS-134 2.95E402 6/16/98 564.10000 CS-137 2.48FA02 Phnt: HNP Anal ls: GAMMA Media e: FOOD CROP Units: GRAMS Media: COLLARDS 55 - RD11671.7MINNW(GOODWIN) 3/24/98 501.10000 KAO 3.14E+000 5.05E401 3/24/98 501.10000 I-131 2.02E402 3/24/98 501.10000 CS-134 2.50FA02 3/24/98 501.10000 CS-137 2.60FA02 6/16/98 567.60000 KAO 5.15E+000 5.11E401 6/16/98 567.60000 1-131 2.17E402 6/16/98 567.60000 CS-134 2.83E402 6/16/98 567.60000 CS-137 2.72FA02 Phnt: HNP Anal vis: GAMMA MedhT e: FOOD CROP Units: GKVVS Media: S UASH 5 - PITI'SBORO- CONTROL 6/16/98 611.10000 KRO 2.20E+000 3.80FAOI 6/16/98 611.10000 1-131 1.76E402 6/16/98 611.10000 CS-134 2.30E402 6/16/98 611.10000 CS-137 2.24E402 Plant: HNP Anal sls: GAMMA MediaT e: FOODCROP Units: GRAMS Media: TVRNIPSANDGREENS 54 - RD 1189 1.7 MI NNE (WILKINSOR MORRIS) I/22/98 578.60000 KAO 2.11E+000 4.38FAOI I/22/98 578.60000 BI-214 5.52E402 4.19E402 I/22/98 578.60000 1-131 1.82E402 I/22/98 578.60000 CS-134 2.33FA02 I/2268 578.60000 CS-137 2.57E402 2/IO/98 442.50000 BF7 1.49E+000 2.52E401 2/10/98 442.50000 KAO 2.45E+000 5.57E401 2/10/98 442.50000 1-131 2.08E402 2/10/98 442.50000 CS-134 3.00E402 2/10/98 442.50000 CS-137 3.16FA02 3/24/98 528.90000 BF~7 2.06FAOI 1.08FAOI
l 0
Sample Point SampieDate Quantity Isotope Activity 2 SigmaError
$4 - RD 1189 1.7 MI NNE (WILKINSOR MORRIS) 3/24/98 52890000 KAO 3.17E+MO 3.78E401 3/24/98 528.90000 1-131 1.54FA02 3/24/98 $ 28.90000 CS-134 1.67E402 3/24/98 528.90000 CS-137 1.7IE402 62 - 2.3 MINE SECTOR(LEE) 1/22/98 $ 31.90000 BE-7 3.88FAOI 1.48E401 I/22/98 531.90000 KAO 2.50E+000 3.63E401 I/22/98 $ 31.90000 1-131 1.47E402 I/22/98 531.90000 CS-134 1.94E402 I/22/98 531.90000 CS-137 1.61E402 1
Plant: HNP Anal wfst GAhfMA Mediaj e: FREE AVIhfMER Unltst GRAhfS hfedla: LARGEMOUTHBASS 44 - SITE VARIES WITHINHARRIS LAKE 5/4/98 593.60000 K40 4.20E+000 9.91E401 45 - SITE VARIES ABOVE BUCKHORN DAM- CON 5/4/98 618.50000 KAO 3.29E+OOQ 1.21E+000 Plant: HiNP Anal sts: GAhfhfA MediaT e: FREESiVIMMER UnIts: GRAMS Media: SUNFISH 44 - SITE VARIES WITHINHARRIS LAKE 5/4/98 512.20000 KAQ 3.5 IE+OQO 1.09E+000 4$ - SITE VARIES ABOVE BUCKHORN DAM- CON 5/4/98 481 A0000 KRO 4.44E+000 1.01E&00 5/4/98 481.40000 PB-214 1.96E4QI 7.80E402 Plant: HNP Anal wist GAMMA MediaT e: GROUNDWATER Unttst LITERS 39 - DEEP WELLNEAR DIABASE DIKES 3/5/98 1.00000 NO-ACT 6/16/98 1.00000 NO-ACT 57 - 0.4 Ml SSW SECTOR N BANKESW INTAKE 3/5/98 1.00000 NO-ACT 6/16/98 1.00000 KAO 3.51E+002 7.71E&OI
$8 - 0.5 MI WSW SECTOR N BANKESW INTAKE 3/5/98 1.00000 RA-226 7.36E+QOI 6.40E+001 6/16/98 1.00000 NO-ACT 59 - 0.5 MI NNE SECTOR(NEAR CONSTRUCTION 3/ 5/98 1.00000 NO-ACT 6/16/98 1.00000 NO-ACT 60 - 0.5 MI ESE SECTOR W BANKOF THOMAS CR 3/5/98 1.00000 NO-ACT 6/16/9& I.Q0000 NO-ACT Plant: HiVP Anal vis: GAMMA MediaT e: MILK Unitst LITERS 5 - PIITSBORO- CONTROL II5/98 1.00000 K<0 1.38E&03 2.09E+002 I/19/98 1.00000 KAO 1.54E+003 2.06E+002 I 2/16/98 I.0 MOO K<0 1.31E+003 1.62E+002 2/2/98 1.00000 KAO 1.46E+OQ3 2.20Et002 2/2/98 1.00000 81-214 2.60E+001 1.68E+001 3/2/98 1.00000 KAQ 1.32E+OQ3 1.62Et002 4/20/98 1.00000 K<0 1.39E+003 1.55E+002 4/20/98 1.00000 BI-214 4.52E+001 1.64E+QOI 4/20/98 1.00000 PB-214 3.54E+001 1.52E+001 3/16/98 1.000M KAO 1.18E+003 1.97E &02
Sample Point SampleDate Quantity Isotope Activity 2 SigmaError 5 - PIITSBORO- CONTROL 4/6/98 1.00000 KAO 1.43E&03 1.81E+002 5/4/98 1.00000 KPO 1.41E+003 830E&OI 5/19/98 1.00000 KAO 1.24E+003 2.06E&02 6/15/98 1.00000 KAO 1.36E+003 1.78E+002 6/ I/9S 1.00000 KPO 1.60E&03 2.07E+002 Phnt: HNP Anal sis: GAhthIA hledlaT e: SHORELINE SEDIhIENT Units: GK41IS 26 .
- SPILLWAYONMAINRES I/12/98 1291.40000 KAO 9.04E+000 1.06E+000 I/12/98 1291.4 MOO TI 208 4.93FA02 4.16FA02 I/12/98 1291.40000 PB-212 1.09FAOI 4.62FAOI I/12/98 1291.40000 PB-214 1.53FAOI 6.85FA02 I/12/98 1291.40000 AC-228 2.14FAOI 1.01FAOI 5/5/98 1282A0000 KRO 1.20E+001 1.15E+000 5/5/98 1282.40000 TL 208 5.60FA02 3.54E402 5/5/98 1282.40000 PB-212 2.65FAOI 6.53FA02 5/5/98 1282.40000 PB-214 2.38FAOI 7.87FA02 5/5/98 1282.40000 RA-226 1.53E+000 6.80FAOI 41 - SHORELINE OF COOLING TOWER MIXINGZ I/12/98 1534.90000 KAO 1.35E+001 1.09E+000 I/12/98 1534.90000 TL208 9.01FA02 3.56FA02 I/12/98 1534.90000 PB-212 2.69FAOI 7.16FA02 I/12/98 1534.90000 BI-214 2.05E401 8.14FA02 I/12/98 1534.90000 PB-214 2.79FAOI 6.20E402 I/12/98 1534.90000 RA-226 1.10E+000 6.06E401 Sl 5/98 1407.20000 KAO 1.34E+001 1.17E+OM 5/5/98 1407.20000 TL-208 9.72FA02 4.21FA02 Sl 5/9S 1407.20000 PB-212 3.19FAOI S.SIFA02 5/5/98 1407.20000 PB-214 3.46E401 7.97FA02 Plant: HNP Anal Is: GAMMA hfedlaT e: SURFACEIVATER Units: LITERS 26 - SPILLWAYONMAINRES I/31/98 1.00000 NO-ACT 2/2I98 I.MOOO NO-ACT 3/31/98 1.00000 NO-ACT 5/31/98 1.00000 NO-ACT 4f30/98 1.00000 NO-ACT 6f30/98 1.00000 NO-ACT 38 - CAPE FEAR PLANT INTAKE- CONTROL I/31/98 1.00000 NO-ACT 1.00000 NO-ACT 3/31/98 1.00000 NO-ACT 5/31/98 1.00000 NO-ACT 4/30/98 1.00000 NO-ACT 6/30/98 1.00000 NO-ACT
Sample Point SampleDate Quantity Isotope Activity 2 SigmaError 40 - LILLINGTON-CAPE FEAR RIVER I/31/98 1.00000 NO-ACT 2/28/98 1.00000 NO-ACT 3/31/98 1.00000 NO-ACT 5/31/98 1.00000 NO-ACT 4/30/98 1.00000 NO-ACT 6/30/98 1.00000 KAO 3.47E+002 7.78E+001
CPAL Radiological Environmental Monitoring Analysis Report 4/6/99 cubi
Plant: TLD in mR/QTR Sam le Point Sam leDate Dose 2 Si maError I - SR1134ATINTSRIOII-DIXIEPIPELINE 8/15/98 1.68E+001 1.00E&00 I 11/15/98 1.29E+001 1.60E~
2 - SR1134 8/15/98 1.46E+001 1.90E+000 2 11/15/98 1.43E+001 1.10E+000 3 - HARRISEScECENTER-2.2MINE 8/15/98 1.24E+001 9.00E401 3 11/15/98 1.20E+001 1.30E+000 4 - NEWHILLNEARISTBAPTISTCH 8/15/98 1.25E+001 I.IOE~
4 11/15/98 1.15E+001 7.00E40I 5 - PHTSBORO- CONTROL 8/15/98 1.74E+001 1.40E+000 5 11/15/98 1.52E+001 8.00FA01 6 - INTOFSR1134AND1135 8/15/98 1.25E+001 130E+000 6 11/15/98 1.09E+001 1.50E+000 7 - HOUSERUINSONSR1134 8/15/98 1.09E+001 I.OOE+000 7 11/15/98 1.05E+001 1.00E+000 8 - DEADENDOFSR1134 8/15/98 1.60E+001 1.00K+000 8 11/15/98 1.21E+001 1.30E+000 9 - I MI SW OF HOLLEMANSXRDS ON SR 1130 11/15/98 9.60E+000 8.00FA01 10 - 2.0 htI SW OF HOLLEMANSXRDS ON SR 1130 8/15/98 1.21E+001 9.00E401 10 11/15/98 1.15E+001 9.00FA01 11 - EARTHEN DAMAT HARRIS PLANT 8/15/98 1.33E+001 1.10E+000 11 11/15/98 1.21E+001 I.IOE&00 12 - I MISONDIRTRDFROhfTLD13 8/15/98 1.12' 1.30E+000 12 11/15/98 1.06E+001 1.00E+000 13 - DIRT RD INT BETWEEN PLANT AND AUXRES 8/15/98 1.15E+001 1.80E&00 13 11/15/98 1.23E+001 1.20E+000 14 - DEADENDOFSR1911 8/15/98 1.17E+001 1.00E+000 14 11/15/98 1.05E~I 8.00E401 15 - CEMETERY ON SR 1911 8/15/98 1.08E+001 1.20E+000 15 11/15/98 1.09E+001 1.00E+000 16 - US I AT CHATHAM-WAKECO LINE 8/15/98 1.36E+001 9.00E401 16 11/15/98 1.29E+001 1.20E+000 17 - INTOFUS I ANDAUXRES 8/15/98 1.20E+001 1.50E+000 17 11/15/98 1.23E+001 9.00E001 18 - 0.6MINONUS I FROMTLD17 8/15/98 137E+001 1.40E~
18 11/15/98 1.33E+001 8.00E401 19 - SR 1142-OLlVES DAIRY 8/15/98 1.23E+001 1.80E&00 19 11/15/98 1.19E+001 1.50E&00 20 - INTOFSR1149ANDUS I 8/15/98 1.58E+001 1.10E+000 20 11/15/98 1.46E+001 7.00E401 21 - 1.3 hII ON SR 1152 FROM INT SR 1153 8/15/98 1.29E+001 1.00E+000
Plant: HNP TLD in mB/QTR Sam le Point Sam leDate Dose 2Si maError 21 - 1.3 MI ON SR 1152 FROM INT SR 1153 11/15/98 9.60E&00 7.00E401 22 - 2.0 MI E OF HOLLEhfANSXRDS ON SR 1115 8/15/98 1.04EtOOI 1.00E+0M 22 11/15/98 1.06E+001 1.50E+000 23 - INT SR 1116 AND SR 1127 8/15/98 1.33E+001 1.30E+000 23 11/15/98 1.24E+001 1.50E+000 24 - SWEET SPRINGS CHURCH ON SR 1116 8/15/98 1.29E+001 1.00E~
24 11/15/98 1.16E+001 1.40E+000 25 - 0.2MI WOF INTOF SR 1401 AND SR 1402 8/15/98 1.48E+001 2.00E&00 25 11/15/98 1.15E+001 8.00E401 26 - SPILLWAYON MAINRES 8/15/98 1.44E+001 2.30E+000 26 11/15/98 134 E+001 1.70E+000 27 - BUCKHORN UNITED METHODIST CH ON NC 42 8/15/98 9.80E+000 1.20E+000 27 11/15/98 9.60E+000 9.00E401 28 - 0.6 MI FROM INT SR 1916 AND SR 1924 8/15/98 I.IIE&01 9.00FA01 28 11/15/98 1.04E+001 1.90E+000 29 - NESTE RESIN CORP ON SR 1916 8/15/98 1.34E+001 9.00E401 29 11/15/98 1.34E+001 2.00E+000 30 - INT OF SR 1972 AND US I 8/15/98 1.05E+001 1.70E~
30 11/15/98 1.05E+001 I.IOE&00 31 - INT OF SR 1910 8/15/98 135E+001 1.50E+000 31 11/15/98 1.01E&OI 9.00E401 32 - 3 htl ON SR 1008 FROM INT SR 1011 11/15/98 1.23E+001 8.00E401 33 - SR 1142 AT BARRICADE 8/15/98 1.15E+001 8.00E40I 33 11/15/98 1.12E+001 9.00E401 34 - APEX AT JONES PARK 8/15/98 IA4E+001 2.50E~
34 11/15/98 1.40E&OI I.30E&00 35 - HOLLYSPRINGS ON EARP STREET 8/15/98 130E+001 8.00E001 35 11/15/98 1.2 I E+001 7.00E401 36 - INT OF SR 1393 AND SR 1421 8/15/98 1.20Et001 9.00E401 36 11/15/98 1.17EKOI 1.10E+000 37 - FUQUAYVARINAATOLDCPALOFFICE 8/15/98 1.75E+001 1.70E+000 37 11/15/98 1.57E+001 3.00E+0M 4& - SR 1142 AT UNDERGROUND CABLE SIGN 8/15/98 1.36E+001 I.OOE+0M 48 11/15/98 1.30E+001 1.20E+000 49 - SR 1127 AT WAKECO TRASH COLLECTION AREA 8/15/98 1.47E~I 1.40E+000 49 11/15/98 1.47E~I 1.20E+000 50 - HOLLEMANSCROSSROADS 8/15/98 1.18E+001 1.00E+000 50 11/15/98 1.11E+001 9.00E401 53 - INTERSECTION OF SR 1972 AND SR 1907 8/15/98 1.09E+001 1.70E+000 53 11/15/98 1.01E+001 1.80E&00
Plant: HNP TLD in mR/QTR Sam le Point Sam leDate Dose 2Sl maError 56 - 2.8MI WSWOFTHESITE 8/15/98 1.27E+001 1.10E+000 56 1 1/15/98 1.14E+001 8.00EOJI 63 - 0.7 MI SW SECTOR ON (POWER POLE COJ85) 8/15/98 1.50E+OOI 1.60E+000 63 l 1/15/98 1.31E+001 8.00EOOI
,CPAL Radiological Environmental Monitoring Analysis Report 4/8/99
Semiann alysis Report 4/ 8/99 Sample Point SampleDate Quantity Efficiency Activity 2 Si maError Phnt: EINP Anal Ia: BETA MediaT : AIR PARTICULATE CUBIC METERS I - SR 1134 AT INT SR 1011 - DIXIEPIPEUNE 7/6/98 788.00000 3.77E401 1.70E402 1.63E403 1.27FA03 7/1388 785.00000 3.77E401 2.43E402 1.88E403 1.27E403 7/20/98 790.70000 3.77E401 1.89FA02 1.67E403 1.18E403 7/27/98 784.50000 3.77E401 1.78E402 1.67E403 1.30E403 8/3i98 760.00000 3.77E401 2.11FA02 1.81E403 1.28E403 8/1088 757.50000 3.77E401 1.54FA02 1.62E403 1.36E403 8/17/98 755.90000 3.77FA01 1.89E402 1.76E403 138FA03 8/2488 760.50000 3.77E401 2.50E402 1.97E403 1.40E403 8/31/98 714.60000 3.77E401 2.80E402 2.16E403 1.57FA03 9/14/98 644.20000 3.77E401 2.48FA02 2.14E403 1.56E403 9/2188 720.90000 3.77E401 3.46E402 230E403 1.40E403 9/8/98 808.50000 3.77FAOI 3.73E402 2.23E403 1.25E403 9/28i98 738.20000 3.77E401 2.37E402 1.94E403 1.39FA03 10/12/98 803.90000 3.77FAOI 1.43E402 1.50E403 1.23E403 10/19/98 792.90000 3.77E401 2.65E402 1.94E403 1.26E403 10/26/98 753.00000 3.77E401 2.17E402 1.85FA03 134E403 11/2/98 766.30000 3.77FA01 3.58E402 2.27FA03 1.34E403 10/588 754.00000 3.77FAOI 2.12E402 1.82FA03 130E403 11/9/98 772.80000 3.77FA01 1.85E402 1.68E403 1.21E403 11/1688 775.70000 3.77E401 3.26E402 2.17E403 135 E403 11/2388 806.00000 3.77E401 3.08E402 2.04E403 1.20E403 I I/3088 750.20000 3.77E401 2.40E402 1.90E403 1.22E403 12/7/98 753.50000 3.77FA0I 2.34E402 1.90FA03 131E403 12/14/98 744.10000 3.77E401 1.94FA02 1.77FA03 1.32FA03 12/2188 759 40000 3.77E401 2.14E402 1.82FA03 1.30FA03 12/27/98 501.00000 3.77E401 2.72E402 2.63E403 2.16FA03 2 - SR 1134 7/688 783.90000 3.77E401 1.73E402 1.65E403 1.28E403 7/1388 738.20000 3.77E401 2.20FA02 1.88E403 1.35E403 7/20i98 767.00000 3.77E401 1.88FA02 1.70E403 1.21E403 7/27/98 742.10000 3.77FA01 1.75E402 1.72E403 1.38FA03 8/3/98 742.80000 3.77FAOI 1.72E402 1.69E403 131E403 8/1088 761.50000 3.77E401 1.33E402 1.53E403 135 E403 8/1788 802.80000 3.77E401 1.44E402 1.53E403 130E403 8/24/98 731.70000 3.77E401 2.48E402 2.00E403 1.45E403 8/3188 704.00000 3.77E401 2.77E402 2.16E403 1.59E403 9/14/98 634.60000 3.77M@1 2.35E402 2.11E403 1.58E403 9/2188 768.50000 3.77FAOI 2.97E402 2.08E403 1.31E403 9/888 81030000 3.77E401 3.42FA02 2.15FA03 1.25E403 9/2&/98 697.20000 3.77FAOI 2.26E402 1.97E403 1.47E403 2
Sample Point Sam pleD ate Quantity Efficiency Activity 2 Si maError 2 - SR 1134 10/12/98 718.80000 3.77E401 IA4FA02 1.62E403 138E403 10/19i98 702.00000 3.77E401 2.73FA02 2.11FA03 1.42FA03 10/2688 539.40000 3.77E401 2.26E402 2.30FA03 1.87E-003 11/2/98 688.70000 3.77FAOI 4.01E402 2.53E403 1.49E403 10/5/98 758.8MM 3.77E401 2.16E402 1.83E403 1.30E403 11/9/98 670.20000 3.77FAOI 1.91E402 1.85E403 139E403 11/16/98 687.40000 3.77FAOI 3.57FA02 2.41E403 1.52E403 11/23i98 684.80000 3.77FAOI 339FA02 2.34E403 1.41E403 11/30/98 650.50000 3.77FAOI 2.53FA02 2.11E403 1.41FA03 12/7/98 789.70000 3.77FAOI 2.35E402 1.85E403 1.25FA03 12/1488 753.80000 3.77FAOI 1.82FA02 1.7IFA03 1.30FA03 12/21/98 716.90000 3.77E401 1.58E402 1.67FA03 137FA03 12/2788 611.90000 3.77EOOI 2.22E402 2.15E403 1.76E403 4 - NEW HILLNEAR 1ST BAPTIST CH 7/6/98 733.90000 3.77E401 1.85E402 1.76E403 1.37FA03 7/13/98 738.60000 3.77E401 230 E402 1.91FA03 1.35FA03 7/20/98 744.00000 3.77E401 1.80E402 1.70FA03 1.25E403 7n788 734.20000 3.77E401 1.91E402 1.79E403 1.39E403 8/3/98 71430000 3.77E401 2.01E402 1.84E403 1.36E403 8/10/98 750.10000 3.77E401 1.26EO02 1.52E403 1.37E403 8/17/98 73390000 3.77E401 1.87E402 1.78E403 1.42E403 8/24/98 739 40000 3.77E401 2.52E402 2.00E403 1.44E403 9/14/98 630.70000 3.77E401 2.67FA02 2.23FA$ 3 1.59E403 9/21/98 739.20000 3.77FAOI 3.28FA02 2.22E403 1.36E403 9/888 815.80000 3.77E401 3.40E402 2.13E403 1.24E403 9/2888 738.10000 3.77E401 2.18E402 1.88E403 1.39E403 10/1288 740.70000 3.77E401 1.60E402 1.65E403 134EM3 10/1988 736.00000 3.77FAOI 2.68E402 2.04E403 1.35FA03 IO/2688 71930000 3.77FAOI 2.24E402 1.92E403 1.40FA03 11/2/98 731.80000 3.77FAOI 3.66E402 235 FA03 1.40E403 10/ Si98 736.40000 3.77E401 2.27E402 1.90FA03 134 E403 I I/9i98 733.90000 3.77FAOI 2.06E402 1.81FA03 1.27E403 11/1688 731.10000 3.77E401 3.38FA02 2.27FA03 1.43E403 11/23i98 766.00000 3.77E401 3.00FA02 2.08FA03 1.26FA03 11/30i98 711.60000 3.77E401 2.22FA02 1.89E403 1.29FA03 12/7/98 7333 MOO 3.77E401 2.39FA02 1.95E403 1.35FA03 12/14i98 739.90000 3.77E401 1.78E402 1.72E403 1.33E403 12/21/98 750.00000 3.77E401 1.98FA02 1.78E403 131FA03 12/27/98 622.00000 3.77E401 2.22E402 2.13E403 1.74E403 5 - PITTSBORO- CONTROL 7/6/98 72030000 3.77E401 1.98E402 1.83FA03 1.39E403 7/13/98 725.00000 3.77E401 2.30E402 1.93E403 137E403 3
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError 5 - PITTSBORO- CONTROL 7/2088 584.50000 3.77E401 1.84E402 1.99E403 1.59E403 7/2788 710.60000 3.77E401 2.13E402 1.90E403 1.44E403 8/3/98 701.30000 3.77E401 2.18E402 1.92E403 1.38FA03 8/1088 740.20000 3.77E401 1.50E402 1.63E403 1.39E403 8/1788 433.00000 3.77E401 2.33E402 2.70E403 2.41E403 8/2488 716.00000 3.77FAOI 2.57E402 2.06E403 1.48E403 8/31/98 715.40000 3.77FAOI 2.66FA02 2.11E403 1.56E403 9/14i98 616.70000 3.77FAOI 2.84E402 2.32E403 1.63E403 9/2188 718.90000 3.77FAOI 3.21E402 2.23E403 1.40E403 9/888 794.20000 3.77FAOI 3.65E402 2.23E403 1.28E403 9/28i98 741.50000 3.77E401 2.21E402 1.89E403 1.38E403 10/12/98 73030000 3.77FAOI 1.80E402 1.74E003 136E403 10/19/98 719.70000 3.77E401 2.58E402 2.03FA03 138E403 10/26/98 727.40000 3.77E401 2.12E402 1.87FA03 1.39E403 11/288 718.50000 3.77E401 3.46E402 2.31E403 1.43E403 10/5/98 706.00000 3.77E401 2.15E402 1.91E403 1.39E403 11/988 72790000 3.77E401 1.90E402 1.76E403 1.28E403 11/1688 723.60000 3.77E401 3.37E402 2.29FA03 1.44E403 11/2388 754.00000 3.77E401 2.97E402 2.09FA03 1.28E403 I li3088 68530000 3.77E401 2.16E402 1.92FA03 1.34E403 12/7/98 718.40000 3.77E401 2.09E402 1.86FA03 1.38FA03 12/14/98 741.10000 3.77E401 1.96FA02 1.78FA03 133 FA03 12/2188 753.90000 3.77E401 1.88FA02 1.73E403 1.30E403 12/27/98 291.20000 3.77FAOI 2.29E402 3.55E403 3.71E403 26 - SPILLWAYON MAINRES 7/6/98 756.40000 3.77FAOI 2.06FA02 1.80E403 1.32FA03 7/1388 741.60000 3.77E401 2.31FA02 1.91E403 1.34E403 7i20i98 760.70000 3.77FAOI 1.92E402 1.72E403 1.22E403 7/27/98 763.20000 3.77E401 1.64E402 1.65E403 1.34E403 8/3/98 728.60000 3.77E401 1.99FA02 1.81E403 1.33FA03 8/10/98 752.80000 3.77FAOI 1.33FA02 1.54E403 136FA03 8/1788 745.10000 3.77FAOI 1.70E402 1.70E403 1.40FA03 8/2488 744.80000 3.77FAOI 2.48E402 1.98E403 1.43FA03 8/31/98 709.40000 3.77FAOI 2.53E402 2.08FA03 1.58FA03 9/14i98 632.00000 3.77FAOI 2.55FA02 2.19E403 1.59E403 9/21/98 742.30000 3.77FAOI 3.03E402 2.14E403 1.36E403 9/888 815A0000 3.77E401 1.79E402 1.63FA03 1.24E403 9/28/98 74030000 3.77FAOI 2.47E402 1.98E403 139 E403 10/1288 740.50000 3.77FAOI 1.50FA02 1.61E-003 1.34E403 10/1988 725.90000 3.77E401 2.72E402 2.07E403 1.37FA03 10/26/98 741.10000 3.77FAOI 2.17E402 1.87E403 1.36FA03
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError 26 - SPILLWAYON MAINRES 11/2/98 726.60000 3.77E401 3.46E402 2.30E403 1.41E403 10/5/98 750.00000 3.77FAOI 1.97E402 1.77E403 1.31E403 11/9/98 733.80MO 3.77FAOI 2.04E402 1.80FA03 1.27E403 I I/16/98 732.10000 3.77E401 338E402 2.27E403 1.43FA03 11/2388 754.000M 3.77E401 2.89E402 2.06FA03 1.28E403 11/3088 711.30000 3.77FAOI 2.43E402 1.97E403 1.29E403 12/7/98 699.40000 3.77FAOI 2.45E402 2.02E403 1.42FA03 12/1488 691.40000 3.77FAOI 1.59E402 1.71E403 1.42E403 12/21/98 724.60000 3.77E401 1.76E402 1.73E403 1.36E403 12/27/98 603.00000 3.77E401 1.72E402 1.98E403 1.79E403 47 - SSW SECTOR 3.4 MI FROM SITE 7/13/98 562.50000 3.77FAOI 2.23E402 2.22E403 1.77E403 7/2088 656.300M 3.77FAOI 1.90E402 1.87E403 1.42FA03 8/388 730.30000 3.77E401 1.33E402 1.55E403 1.33E403 8/1088 839.60000 3.77E401 9.56E403 1.28E403 1.22&003 8/17/98 813.00000 3.77E401 1.57E402 1.57FA03 1.28E403 8/24/98 773.10000 3.77FAOI 2.33E402 1.89E403 1.37FA03
$ 31/98 706.00000 3.77E401 2.37E402 2.03FA03 1.59FA03 9/14/98 633.90000 3.77E401 2.34E402 2.11FA03 1.58E403 9/2188 741.20000 3.77FAOI 2.98FA02 2.13FA03 1.36E403 9/8/98 799.60000 3.77FAOI 2.30E402 1.83FA03 1.27E403 9/28/98 745.10000 3.77E401 2.24E402 1.89FA03 138E403 10/1288 745.70000 3.77FAOI 1.43FA02 1.57E403 1.33E403 10/19/98 740.50000 3.77FAOI 2.57E402 2.00FA03 1.35E403 10/26/98 744.80000 3.77E401 2.21E402 1.87E403 1.35E403 11/288 725.90MO 3.77FAOI 3.56FA02 2.33EO03 1.41E403 10/5/98 735.20000 3.77E401 2.07E402 1.83E403 1.34E403 11/9/98 748.50000 3.77E401 1.78E402 1.69E403 1.24E403 11/16/98 733.90000 3.77E401 3.45E402 2.29E403 1.42FA03 11/23/98 762300M 3.77E401 2.81E402 2.03E403 1.27E403 11/3088 716.00000 3.77FAOI 2.16E402 1.87E403 1.28E403 12/788 714.20000 3.77FAOI 237 E402 1.97E403 139E403 12/1488 729.50000 3.77E401 1.75E402 1.72FA03 135 E403 12/2188 719.80000 3.77E401 1.91FA02 1.80E403 1.37E403 12/278& 612.30000 3.77FAOI 2.20FA02 2.14FA03 1.76E403 Plant: HNP Anal vis: BETA MediaT t DRINKINGIYATERLITERS 38 - CAPE FEAR PLANT INTAKE- CONTROL 8/31/98 1.00000 2.99E401 4.31E+000 9.74E401 1.08E+000 9/30/98 1.00000 3.05E401 6.03E+000 1.04E&00 1.01E+000 10/31/98 1.00000 2.95FAOI 5.99E+000 1.06E+OM 1.04E+OM I I/3088 1.00000 2.95E401 6.38E&00 1.08E+OM 1.03E+000 5
Sample Point SampleDate Quantity Efficiency Activity 2 Si maError 38 - CAPE FEAR PLANT INTAKE-CONTROL 12/31/98 1.00000 2.918401 6.598~ 1.14E+000 1.158&00 701/98 1.00000 3.06E401 4.398+000 9.29E401 9.70E401 40 - LILUNGTON- CAPE FEAR RIVER 8/31/98 1.00000 3.04FAOI 4.45E+000 9.70E401 1.06E+000 9/30/98 1.00000 3.048401 5.99E+000 1.048~ 1.01E+MO 10/31/98 1.00000 3.21FAOI 4.158+000 8.95E401 9.52FAOI 11/30/98 1.00000 3.01E401 5.608+0M 1.02E+000 1.018~
12/31/98 1.00000 290 FAOI 5.53E+MO 1.098+0M 1.16840M 7/3168 1.00000 3.05FAOI 4.52E+MO 9.408401 9.738401 51 - WATER TREATMENTBLDG AT HARRIS PLANT &/31/98 1.00000 3.198401 2.26E+000 7.958401 1.01E+000 900/98 1.00000 3.21E401 2.81E+000 8.108401 9.61E401 10i31/98 1.00000 3.19E401 3.11E+000 8308401 9.58E401 11/30/98 1.00000 3.208401 2.39E+000 7.74E401 9.46FAOI 12f31/98 1.00000 3.30E401 2.38E+000 8.018401 1.02E+000 701/98 1.00000 3.29E401 2.358+000 7.47E401 9.028401 Phnt: HNP Anal <<is: BETA MedhT: SURFACE IVATER LITERS 26 - SPILLWAYON MAINRES 801/98 1.00000 3.598401 1.818&00 6.928401 8.98E401 9/30/98 I.MOOO 3.59E401 3.26E+000 7.74FAOI 8.59E401 10i31/98 1.00000 3.52E401 2.338+000 7.18E401 8.68E401 1100/98 1.00000 3.508401 2.50E+000 7.30E401 8.65E401 1201/98 1.00000 3.55FAOI 3.20E+000 $ .098401 9 468401 7/31/98 1.00000 3.588401 2.048&00 6.77E401 8.29E401 38 - CAPE FEAR PLANT INTAKE- CONTROL 8/31/98 1.00000 2.99E401 4.31E+000 9.74E401 1.08E+000 900/9$ 1.00000 3.058401 6.038+000 1.04E+000 1.018+000 10i31/98 1.00000 2.95E401 5.998+000 1.06E+000 1.04E+000 I lf30/98 1.00000 2.95E401 6.38E+000 1.08E+000 1.038+000 12/31/98 1.00000 2.918401 6.59E+000 1.14E+000 1.15E+000 7/31/98 1.00000 3.06FAOI 4.39E+000 9.29E401 9.708401 40 - ULUNGTON- CAPE FEAR RIVER 801/98 1.00000 3.04FAOI 4.458+000 9.708401 1.06E+000 9/30/98 1.000M 3.048401 5.998+000 1.04E+000 I.OIE+OM 10/31/98 1.00000 3.21FAOI 4.15E+000 8.95E401 9.52E401 11/30/98 1.00000 3.01FAOI 5.608+MS 1.028&00 1.018+000 1201/98 1.00000 290FAOI 5.538+0M 1.09E+000 1.16E+000 7i31/98 1.00000 3.05FAOI 4.528+000 9.40E401 9.738401 Plant: HNP Anal <<bt IODINE MedhT: AIRCARTRIDGE CUBICMETERS I - SR 1134 AT INT SR 1011 - DIXIEPIPEUNE 7/6/98 788.00000 2.02FA02 9/14/98 644.20000 1.72E402 7/13/98 785.00000 1.20E402 7/20/98 790.70000 2.05FA02
Sample Point SampleDate Quantity Efficiency Actmty 2 St aError I - SR 1134 AT INT SR 1011 - DIXIEPIPEUNE 7/27/98 784.50000 7.61E403 8/3/98 760.00000 8.52E403 8/10i98 757.50000 8.25FA03 8/17/98 755.90000 1.36FA02 8i24i98- 760.50000 1.35E402 8/31/98 714.60000 2.12E402 9/8/98 808.50000 1.43E402 9/21/98 720.90000 1.40E402 9/28/98 738.20000 1.82E402 10/5/98 754.00000 2.03E402 10/12/98 803.90000 7.41E403 10/19/98 792.90000 1.38E402 Io/26/98 753.00000 1.24E402 I I/2/98 766.30000 1.06FA02 11/9/98 772.80000 1.37E402 11/16/98 775.70000 1.53E402 11/23/98 806.00000 1.13E402 11/30/98 750.20000 2.08E402 12/7/98 753.50000 1.64E402 12/14/98 744.10000 1.25E402 12/21/98 759.40000 1.56FA02 12/27/98 501.00000 4.75E402 2 - SR 1134 7/6/98 783.90000 1.14FA02 9/14/98 634.60000 2.78E402 7/13/98 738.20000 2.05E402 7/20/98 767.00000 1.69E402 7/27/98 742.10000 1.25E402 8/3/98 742.80000 232 E402 8/10/98 761.50000 2.10E402 8/17/98 802.80000 1.64E402 8/24/98 731.70000 2.22E402 8/31/98 704.00000 1.88E402 9/8/98 810.30000 1.63E402 9/21/98 768.50000 1.86E402 9/28/98 697.20000 139E402 10/5/98 758.80000 1.62E402 10/12/98 718.80000 1.91E402 10/19/98 702.00000 1.64E402 10/26/98 539.40000 2.52E402 I I/2/98 688.70000 2.10E402 7
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError 2 - SR 1134 11/9/98 670.20000 1.24E402 11/16/98 687.40000 2.17E402 11/23/98 684.80000 1.248402 11/30/98 650.50000 3.47FA02 12/7/98 789.70000 2.66E402 12/14/98 753.80000 2.458402 12/21/98 71690000 1.90E402 12/27/98 611.90000 1.90E402 4 - NEW HILLNEAR1ST BAPTIST CH 7/6/98 733.90000 2.33E402 9/14/98 630.70000 2.748402 7/13/98 738.60000 2.608402 7/20i98 744.00000 1.88E402 7/27/98 734.20000 2.07E402 8/3/98 714.30000 1.39E402 8/10/98 750.10000 1.43E402 8/17/98 733.90000 1.29FA02 8/24/98 739.40000 IA4FA02 9/8/98 815.80000 2.21E402 9/21/98 739.20000 2.498402 9/2&/98 738.10000 2.84E402 10/5/98 736.40000 1.89E402 10/12/98 740.70000 1.948402 10/19/98 736.00000 1.15E402 10/26/9$ 719.30000 2.28FA02 11/2/9$ 731.80000 2.118402 11/9/98 733.90000 3.56E402 11/16/98 731.10000 1.47E402 I I/23/98 766.00000 1.89FA02 11/30/98 711.60000 1.648402 12/7/98 733.30000 2.07E402 12/14/98 739.90000 2.158402 12/21/98 750.00000 7.918403 12/27/98 622.00000 1.648402 5 - PITTSBORO- CONTROL 7/6/98 720.30000 1.81E402 9/14/98 616.70000 2.74E402 7/13/98 725.00000 2.098402 7/20/98 584.50000 1.90E402 7/27/98 710.60000 1.69E402 8/3/98 701.30000 2.94E402 8/10/98 740.20000 8.208403
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError 5 - PITTSBORO- CONTROL 8/17/98 433.00000 3.09FA02 8/24/98 716.00000 2.04FA02 8/31/98 715.40000 1.68FA02 9/8/98 794.20000 2 44FA02 9/21/98 718.90000 1.61FA02 9/2&/98 741.50000 2.42FA02 10/5/98 706.00000 2A4FA02 10/12/98 730.30000 2.46FA02 10/19/98 719.70000 1.20FA02 10/26/98 727.40000 2.89FA02 11/2/98 718.50000 2.49E402 11/9/98 727.90000 1.73FA02 11/16/98 723.60000 235FA02 11/23/98 754.00000 1.60E402 I I/30/98 685.30000 3.0IFA02 12/7/98 718.40000 1.89FA02 12/14/98 741.10000 2.0&FA02 12/21/98 753.90000 1.75E402 12/27/98 291.20000 3.99FA02 26 - SPILLWAYON MAINRES 7/6/98 756.40000 1.7IFA02 9/14/98 632.00000 2.00FA02 7/13/98 741.60000 1.80FA02 7/20/98 760.70000 1.87FA02 7/27/98 763.20000 13&FA02 8/3/98 728.60000 1.26FA02 8/10/98 752.80000 2.09FA02 8/17/98 745.10000 1.57FA02 8/24/98 744.80000 2.10FA02 8/31/98 709.40000 1.95FA02 9/ &/98 815.40000 I.&2FA02 9/21/98 742.30000 2.72FA02 9/28/98 740.30000 2.08FA02 10/5/98 750.00000 1.94FA02 10/12/98 740.50000 6.22FA03 10/19/98 725.90000 1.79FA02 IO/26/98 741.10000 1.41E402 11/2/98 726.60000 1.50FA02 11/9/98 733.80000 2.53E402 I I/16/98 732.10000 9.33E403 11/23/98 754.00000 1.07E402 9
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError 26 - SPILLWAYON MAINRES 11/30/98 711.30000 2.33E402 12/7/98 699.40000 2.08E402 12/14/98 691.40000 3.40E402 12/21/98 724.60000 2.65E402 12/27/98 603.00000 1.928402 47 - SSW SECTOR 3.4 Ml FROM SITE 9/14/98 633.90000 2.878402 7/13/98 562.50000 3.25E402 7/20/98 656.30000 2.60E402 8/3/98 730.30000 1.77E402 8/10/98 839.60000 1.41E002 8/17/98 813.00000 1.68E402 8/24/98 773.10000 1.39E402 8/31/98 706.00000 2.39E402 9/8/98 799.60000 1.92E402 9/21/98 741.20000 2.78E402 9/28/98 745.10000 2.70E402 10/5/98 735.20000 1.41E+000 10/12/98 745.70000 1.60E402 10/19i98 740.50000 2.29E402 10/26/98 744.80000 I.&IE402 11/2/98 725.90000 1.63E002 11/9/98 748.50000 2.32E402 11/16/98 733.90000 1.32E402 11/23/98 762.30000 1.29E402 11/30/98 711.60000 2.57E612 12/7/98 714.20000 1.57E402 12/14/98 729.50000 2.34E402 12/21/98 719.80000 3.37&002 12/27/98 612.30000 2.4&FA02 Plant: HNP Anal ala: IODINE Media e: DRINKINGiVATER LITERS 38 - CAPE FEAR PLANT INTAKE- CONTROL 10/5/98 4.00000 4.18E401 9/8/98 4.00000 4.11E-001 9/14/98 4.00000 3.87FASI 9/2&/98 4.00000 4.22E401 7/13i98 4.00000 3.97E401 7/20/98 4.00000 3.96E401 7/27/98 4.00000 3.93E401 8/3i98 4.00000 4.08E401 8/10/98 4.00000 3.57E401 10
Sample Point SampleD ate Quantity Efficiency Activity 2 SigmaError 38 - CAPE FEAR PLANT INTAKE- CONTROL 8/17/98 4.00000 3.55E401 8/24/98 4.00000 3.63E401 8/31/98 4.00000 3.25E401 9/2168 4.00000 6.22E401 10/12/98 4.00000 3.85E401 10/19/98 4.00000 3.53E401 10/26/98 4.00000 5.05E401 11/2/9& 4.00000 3.55E401 11/9/98 4.000M 3.71E401 I I/16/98 4.00000 3.50E401 11/30/98 4.00000 3.56E401 11/23/98 4.00000 3.86E401 12/7/98 4.00000 3.67E401 12/14/98 4.00000 6 49E401 12/21/98 4.00000 4.00E401 12/27/98 4.00000 3.9IMSI 7/6/98 4.00000 4.19FAOI 40 - LILLINGTON- CAPE FEAR RIVER 10/5/98 4.00000 5.87FA01 9/8/98 4.00000 3.56E401 9/14/98 4.00000 5.44E401 9/28/98 4.00000 6.27E401 7/13/98 4.00000 5.75E401 7/20/98 4.M000 5.72E401 7/27/98 4.00000 33IE401 8/3/98 4.00000 3.4&E401 8/10/98 4.00000 5.09E401 8/17/98 4.00000 3.30E401 8/24/98 4.00000 3.40E401 8/31/98 4.00000 4.75E401 9/21/98 4.00000 3.89E401 10/12/98 4.00000 3.40E401 10/19/98 4.000M 5.32E401 10/26/98 4.00000 6.26E401 11/2/98 4.00000 3.10E401 11/9/98 4.00000 5.65E401 11/16/98 4.00000 3.01E401 11/30/98 4.00000 5.03E401 11/23/98 4.00000 3.32E401 12/7/98 4.00000 6.07E401 12/14/98 4.00000 3.64E401 11
Sample Point SampleDate Quantity Efficiency Activity 2 Si maError 40 - LILLINGTON- CAPE FEAR RIVER 12/21/98 4.00000 3.12E401 12/27/98 4.00000 3.00FA01 7/6/98 4.00000 4.04E401 51 - WATER TREATMENTBLDG AT HARRIS PLANT 10/5/98 4.00000 632 FAOI 9/8/98 4.000M 4.86E401 9/14/98 4.00000 6.43E401 9nN98 4.00000 7.23E401 7/13/98 4.00000 5.17E401 7/20/98 4.00000 6.56FAOI 7/27/98 4.00000 4.70E401 8/3/98 4.00000 5.01E401 8/10/98 4.00000 5.86E401 8/17i98 4.00000 4.44E401 8/24/98 4.00000 4.65E401 8/31/98 4.00000 5.27E401 9/21/98 4.00000 3.67E401 10/12/98 4.00000 4.98E401 10/19/98 4.00000 5.68E401 Ion6/98 4.00000 6.37E401 I I/2/98 4.00000 4.83E401 I I/9/98 4.00000 3.42E401 11/16i98 4.00000 5.06FAOI 11/30i98 4.00000 5.89E401 11/23i98 4.MOOO 4.85E401 12/7/98 4.00000 5.68FAOI 12/14/98 4.00000 5.23FA01 12/21/98 4.00000 4.43FAOI 12/27/98 4.00000 5.25E401 7/6i98 4.00000 5.23E401 Plant: HNP Anal ala: IODINE hfeHa t hIILK LITERS 5 - PITISBORO- CONTROL 10/5i98 4.00000 3.95E401 9/ &i98 4.00000 5.78FAOI 7n0/98 4.00000 4.04E401 8/3/98 4.00000 6.21E401 8/17/98 4.00000 4.93E401 9/21/98 4.00000 5.77E401 10/19/98 4.00000 3.10E401 11/16/98 4.00000 4.52E401 11/2/98 4.00000 6.43E401 12
Sample Point SampleDate Quantity Efficiency Activity 2 Si maError 5 - PrlTSBORO- CONTROL 12l 7/98 4.00000 5.84FAOI 12/21/98 4.00000 5.54FAOI 7/6/98 6.14FAOI Plant: HNP Anal wist IODINE Medh t SURFACEiVATER LITERS 38 - CAPE FEAR PLANT INTAKE- CONTROL 10/5/98 4.00000 4.18FAOI 9/8/98 4.00000 4.11FAOI 9/14/98 4.00000 3.87EMI 9/28/98 4.000M 4.22FAOI 7/13/98 4.00000 3.97FAOI 7/20i98 4.00000 3.96FAOI 7/27/98 4.00000 3.93E4101 8/3/98 4.00000 4.08FAOI 8/10i98 4.00000 3.57FAOI 8/17/98 4.00000 3.55FAOI 8/24i98 4.00000 3.63FAOI 8/31/98 4.000M 3.25FAOI 9/21/98 4.00000 6.22EOOI 10/12i98 4.00000 3.85FAOI 10/19/98 4.00000 3.53FAOI 10/26i98 4.00000 5.05FAOI 11/2/98 4.00000 3.55FAOI 11/9/98 4.00000 3.71FAOI 11/16/98 4.00000 3.50FAOI 11/30/98 4.00000 3.56FAOI 11/23/98 4.00000 3.86FAOI 12/7/98 4.00000 3.67FAOI 12/14/98 4.00000 6.49FAOI 12/21/98 4.M000 4.00E401 12/27/98 4.00000 3.91E40I 7/6/98 4.00000 4.19E401 40 - LILLINGTON- CAPE FEAR RIVER 10/5/98 4.00000 5.87E401 9/8/98 4.00000 3.56E401 9/I4/98 4.00000 5.44E401 9i28/98 4.00000 6.27FAOI 7/13/98 4.00000 5.75FAOI 7/20/98 4.00000 5.72FAOI 7/27/98 4.00000 331FAOI 8l3/98 4.000M 3.48FAOI 8/10/98 4.00000 5.09FAOI 13
Sample Point SampleDate Quantity Efficiency Activity 2 SigmaError 40 - LILLINGTON- CAPE FEAR RIVER 8/17/98 4.00000 3.30E401 8/24/98 4.00000 3 40E401 131/98 4.00000 4.75FAOI 9/21/98 4.00000 3.89FAOI IO/12/98 4.00000 3.40E401 10/19/98 4.00000 532FAOI 10/26/98 4.00000 6.26E401 11/2/98 4.00000 3.10E401 11/9/98 4.00000 5.65E401 11/16/98 4.00000 3.01E401 I I/30/98 4.00000 5.03E401 II/23/98 4.00000 3.32E401 12/7/98 6.07FAOI 12/14/98 4.00000 3.64E401 12/21/98 4.00000 3.12E401 12/27/98 4.00000 3.00FAOI 7/6/98 4.00000 4.04FAOI Plant: HNP Anal vis TRITIUM hledia DRINKINGiVATER LITERS 38 - CAPE FEAR PLANT INTAKE- CONTROL 7/31/98 .00500 2.86E401 O.OOE+000 O.ME+MO 2.90E+M2 10/31/98 .00500 2.81E401 O.OOE+000 O.OOEt000 3.03E+M2 11/30/98 .00500 4.34FAOI O.OOE+000 0.00E+000 3.03E+002 12/31/98 .00500 4.34E401 0.00E+000 0.00E+000 3.14E+002 9/30/98 .00500 2.80E401 0.00E+000 O.OOE+MO 2.94E~2 8i31/98 .00500 2.82FAOI 0.00E+000 O.OOE+OM 3.01E+002 40 - LILLINGTON- CAPE FEAR RIVER 7/31/98 .00500 2.86E401 O.ME+MO O.OOE+OM 2.90 K&02 I I/30/98 .M500 4.34E401 O.OOE+000 O.OOE+000 3.03E+002 12/31/98 .00500 434 E401 O.OOE+OM O.OOE+000 3.14E+M2 9/30/98 .00500 2.80E401 O.OOE+000 O.OOE+000 2.94E~2 10i31/98 .M500 2.81E401 O.OOE+000 0.00E+000 3.03E+002 I31/98 .00500 2.82E401 0.00E&00 O.OOE+000 3.01E+M2 51 - WATER TREATMENTBLDG AT HARRIS PLANT 7/31/98 .M500 2.86E401 1.42E+003 5.50E+002 8.61E+002 10/31/98 .00500 2.81E401 2.84E+003 5.59E+002 8.26E+M2 11/30/98 .00500 4.34E401 2.37E+003 2.17E+002 3.03E~2 12/31/98 .00500 2.81FAOI 239 E+003 5.70E&02 8.61E+M2 9i30/98 .00500 2.80E401 2.53E+003 5.69E+002 8.56E+M2 8/31/98 .00500 2.82E401 1.79E+003 5.61E+002 8.66E+M2 Plant: HNP Anal vis: TRITIUM htedlaT: GROUNDWATER LITERS 39 - DEEP WELLNEAR DIABASE DIKES 11/19/98 .00500 2.81E401 O.OOE+000 O.OOE+000 3.07E+M2 14
Sampie Point SampleDate Quantity Efficiency Activity 2 Si maError 39 - DEEP WELLNEAR DIABASE DIKES 9/3/98 .00500 2.80E401 0.00E+000 O.OOE+000 3.00E~2 57 - 0.4 MI SSW SECTOR N BANKESW INTAKE I I/19/98 .00500 2.81E401 O.OOE+MO O.OOE+000 3.07E+002 9/3/98 .00500 2.80FAOI 0.00E+OM O.OOEt000 3.00K+M2 58 - 0.5 Ml WSW SECTOR N BANKESW INTAKE 11/19/98 .00500 2.81FAOI O.OOE+000 O.OOE+000 3.07E+M2 9/3/98 .M500 2.80FAOI 6.11E+002 1.86E&02 3.00E+002 59 - 0.5 Ml NNE SECTOR (NEAR CONSTRUCTION R 11/19/98 .00500 2.81FAOI O.OOE+OM 0.00E&00 3.07E+002 9/3/98 .00500 2.80FAOI O.ME+000 O.OOE+000 3.00E~2 60 -0.5 MI ESE SECTOR W BANKOF THOMAS CREE 11/19/98 .00500 2.81E401 0.00E+000 O.OOE&00 3.07E+002 9/3/98 .00500 2.80FAOI O.ME+000 O.OOE&00 3.00E~2 Plant: HNP Anal la: TRITIUht MedlaT e: SURFACE WATER LITERS 26 - SPILLWAYON hfAINRES 9/30/98 .M500 2.80E401 4.59K+003 6.07E+002 8.56E+002 7/31/98 .00500 2.86E401 1.82E&03 5.58K+002 8.61E+002 10i31/98 .00500 2.81FAOI 3.82E+003 5.77K+002 8.26E+002 11/30/98 .00500 4.34FAOI 3.21E+003 2.27E~2 3.03E+002 12/31/98 .00500 2.81FAOI 4.03E+003 5.99E+002 8.61E+M2 8/31/98 .00500 2.82FAOI 2.98E+003 5.83E+002 8.66E+002 38 - CAPE FEAR PLANT INTAKE- CONTROL 7/31/98 .00500 2.868401 0.00E+000 O.OOOO 2.90E+002 10/31/98 .00500 2.8IFAOI O.OOE+OM O.OOE+000 3.03E+002 I I/30/98 .00500 4.34E401 O,OOE+000 O.OOE+000 3.03E+002 12/31/98 .M500 4.34E401 O.OOE+000 O.OOE~ 3.14E+002 9/30/98 .00500 2.80E401 0.00E+000 O.OOE+000 2.94E+M2
$ 31/98 .00500 2.82E401 O.OOE+000 O.OOE+000 3.01E+002 40 - LILLINGTON- CAPE FEAR RIVER 7/31/98 .00500 2.86E401 O.OOE+000 O.OOE&00 2.90E+M2 10i31/98 .M500 2.81E401 O.OOE+000 O.OOE+000 3.03E+002 11/30/98 .00500 4.34E401 O.ME+000 O.OOE+000 3.03E+002 12/31/98 .005M 434E401 O.OOE+000 O.OOE+000 3.14E+002 9/30/98 .00500 2.80E401 O.OOE+000 O.OOE+000 2.94E+002 8i31/98 .00500 2.82E401 O.OOE&00 O.ME+000 3.01E+002 15
CP&I Radiological Environmental Monitoring Isotopic Analysis Report 4/8/99
Semiann alysis Report 4/8/99 Sam ie Point SampleDate Quantity Isotope Activity 2 SigmaError Phnt: HNP Anal Is: GAMhfA MediaT t AIR PARTICULATE Units: CUBIC METERS I - SR 1134 AT INT SR 1011- DIXIEPIPEUNE 8/15/98 9808.50000 BE-7 1.62E401 2.53FA02 11/15/98 9732.80000 BF7 1.42FAOI 2.56E402 2 - SR1134 8/15/98 9684.60000 BF7 1.27E401 2.68E402 11/15/98 8972.90000 BF7 1.45E401 2.39FA02 4 - NEW HILLNEAR IST BAPTIST CH 8/15/98 8825.90000 BF7 1.82FAOI 3.20FA02 11/15/98 9452.00000 BE-7 1.50E401 2.18E402 5 - PHTSBORO- CONTROL 8/15/98 8917.60000 BE-7 1.67E401 2.19FA02 11/15/98 8997.30000 BE-7 1.24E401 2.20E402 26 - SPILLWAYON MAINRES 8/15/98 9632.60000 BF7 1.18E401 1.73E402 11/15/98 9333.70000 BF7 1.06E401 1.87E402 47 - SSW SECTOR3.4 Ml FROM SITE 8/15/98 8004.60000 BF7 1.23E401 2.47E402 11/15/98 9428.60000 BE-7 1.23E401 2.06E402 Plant: HNP Anal vis: GAMhfA hfedia: A VATICVEGETATION Units: GRAMS 26 - SPILLWAYON MAINRES 11/6/98 594.90000 BE-7 2.16E401 1.17E401 I I/6/98 594.90000 KRO 2.28Et000 4.47E401 11/6/98 594.90000 I-131 2.85E402 I I/6/98 594.90000 CS-134 2.34E402 11/6/98 594.90000 CS-137 2.56E402 41 - SHOREUNE OF COOLING TOWER hlIXINGZ 11/12/98 708.40000 BE-7 1.52E401 1.09E40I 11/12/98 708.40000 KAO 238E+000 3.5IEOOI 11/12/98 708.40000 C&60 2.75E402 I.I IE402 11/12/98 708.40000 1-131 1.66E402 11/12/98 708 40000 CS-134 2.2IEO02 11/12/98 708.40000 CS-137 1.82E402 61 - 2.5 hfl E SECTOR HOLLEMANSXRD BR~N 11/688 647.90000 BE-7 5.92E401 1.98E401 11/6/98 647.90000 KRO 2.85E+000 3.998401 11/6/98 647.90000 PB-212 3.84E402 3.54FA02 11/6/98 647.90000 BI-214 9.21E402 3.14E402 11/6/98 647.90000 PB-214 7.72E402 3.44E402 11/6/98 647.90000 I-131 2.67E402 I I/6/98 647.90000 CS-134 2.36E402 11/6/98 647.90000 CS-137 2.22&002 Plant: HNP Anal vis: GAMhfA BOTTOhf FEEDER Units: GRAMS hfedla: CATFISH 44 - SITE VARIES WITHINHARRIS LAKE 11/11/98 512.00000 KAO 3.85E+000 1.23E+000 45 - SITE VARIES ABOVE BUCKHORN DAM- CON 11/I I/98 505.00000 KAO 4.50E+000 9.99E401 Plant: HNP Anal is: GAhfhfA MediaT: BOTTOhf SEDIMENT Units: GRAMS 52 - HARRIS LAKECOOLING TOWER hfIXINGZO 7/8/98 1068.50000 KPO 8.96E+000 9.51E401 7/8/98 1068.50000 TL.208 2.86E401 5.55E402
Sample Point SampleDate Quantity Isotope Activity 2 SigmaError 7/8/98 1068.50000 PB-212 5.62E401 1.06E401 7/8/98 1068.50000 BI-214 5.06E401 9.78E402 7/8/98 1068.50000 PB-214 5.13E401 9.03E402 7/8/98 1068.50000 RA-226 1.87E+000 8.60E401 7/ &/98 1068.50000 AC-228 7.97E401 1.76E401 7/8/98 1068.50000 CO60 4.62E401 7.55E402 7/8/98 1068.50000 CS-137 1.13~1 3.43E402 11/6/98 1027.10000 KAO 7.72E&00 1.06E&M I I/6/98 1027.10000 TI 208 2.74E401 9.74E402 11/6/98 1027.10000 PB-212 6.11E401 8.90E402 I I/6/98 1027.10000 BI-214 4.45E401 1.78E401 I I/6/98 1027.10000 PB-214 5.50E401 1.40E401 I I/6/98 1027.10000 AC-228 7.50E401 3.35E401 11/6/98 1027.10000 C&60 2.13E+000 1.66E401 11/6/98 1027.100M SB-125 3.93E401 1.66E401 11/6/98 1027.10000 CS-137 3.71E401 1.02E401 Plant: HNP Anal >is: GAMMA MedlaT: BROADLEAFVEGETATION Units: GRAMS Medias DOGWOOD 66 - 1.33htISSWSECTOR 7/29/98 428.00000 BE-7 8.17E401 1.67E401 7/29/98 428.00000 KAO 3.41E+000 4.69E401 7/29/98 428.00000 TL 208 2.77E402 2.45E402 7/29/98 428.00000 PB-212 8.45E402 2.81E402 7/29/98 428.00000 I-131 1.74E402 7n9/98 428.00000 CS-134 2.85FA02 7/29/98 428.00000 CS-137 3.26E402 8/27/98 356.70000 BE-7 1.07E+000 3.22E401 8/27/98 356.70000 KQO 1.54E+000 5.11E401 8/27/98 356.70000 TI 208 6.29FA02 3.19E402 8/27/98 356.70000 CS-137 8.98E402 3.62E-002 8/27/98 356.70000 I-131 3.27FA02 sn7/98 356.70000 CS-134 4.38FA02 9/29/98 400.20000 BF7 134 E+000 2.29E401 9/29/9& 400.20000 KAO 2.29E+OM 4.5&E401 9/29/98 4M.20000 1-131 3.16FA02 9/29/98 400.20000 CS-134 3.39E402 9/29/98 400.20000 CS-137 3.70E402 ion 8/98 390.60000 BF7 1.81E+000 2.73E401 ion N98 390.60000 KRO 2.17E+000 4.51E401 10/28/98 390.60000 TL-208 393 E402 2.02FA02 ion 8/98 390.60000 PB-212 8.84FA02 3.07E402 tons/98 390.60000 BI-214 2.52E-001 6.39FA02
Sample Point SampleDate Quantity Isotope Activity 2 SigmaError 66 - 133MISSWSECTOR ion s8s 390.60000 PB-214 230E401 5.44E402 ion 88s 390.60000 I-131 2.13E402 10/28/98 390.60000 CS-134 3.01E402 lons8s 390.60000 CS-137 2.83E402 Plant: HNP Anal vbt GAMhfA hfedlaT BROADLEAFVEGETATION Units: GRAMS hfedla: MAPLE 65 - 1.36MISSECTOR 7/2988 437.60000 BE-7 I. IOE+000 2.18E401 7/29/98 437.60000 KAO 3.85E+000 4.20E401 7/29/98 437.60000 Tl 208 5.54E402 2.10E402 7/29/98 437.60000 PB-212 8.09E402 3.22E402 7/29/98 437.60000 PB-214 6.90FA02 4.59E402 7/2988 437.60000 1-131 1.73E402 7/29/98 437.60000 CS-134 2.50E402 7/2988 437.60000 CS-137 2.15E402 8/27/98 353.90000 BF7 136E+000 2.89FA01 8/2788 353.90000 KM 2.43E+000 S.SSE401 8/2788 353.90000 I-131 3.29FA02 8/27/98 353.90000 CS-134 3.80FA02 8/2788 353.90000 CS-137 3.43E402 9/29/98 422.80000 BE-7 1.04E+000 234 E401 9/29/98 422.80000 KRO 2.63E+000 4.68E401 9/29/98 422.80000 1-131 3.14E402 9/2988 422.80000 CS-134 3.42E402 9/2988 422.80000 CS-137 2.90E402 10/28/98 374.60000 BF7 1.41E+000 2.94E401 10/2888 374.60000 KM 3.35E&00 5.86E401 lons8s 374.60000 TL 208 7.02E402 3.31E402 ion 88s 374.60000 BI-214 933 E402 6.71E402 10/28/98 374.60000 1-131 2.82E402 10/28/98 374.60000 CS-134 3.85E402 ion 88s 374.60000 CS-137 3.44E402 66 - 1.33 MI SSW SECTOR 7/2988 395.80000 BE-7 5.64E401 2.29FAOI 7/2988 395.80000 KAO 2.86E+000 5.19E401 7/2988 395.80000 PB-214 6.46FA02 4.61E402 7/2988 395.80000 I-131 2.73E402 7/29/98 395.80000 CS-134 3.38E402 7/2988 395.80000 CS-137 3.56E402 8/2788 359.40000 BE-7 6.43FAOI 2.38FAOI 8/27/98 359.40000 KAO 2.97E+000 5.46E401 8/27/98 359.40000 TI 208 4.80FA02 3.14E402 8/27/98 359A0000 I-131 3.05E402
Sample Point SampleDate Quantity Isotope Activity 2 SigmaError 66 - 1.33MISSWSECTOR 8/27/98 359.40000 CS-134 3.72FA02 8/27/98 359.40000 CS-137 3.82FA02 9/29/98 454.00000 BF7 9.69FAOI 2.83FAOI 9/29/98 454.00000 KAO 3.49E+000 5.85FAOI 9/29/98 454.00000 1-131 2.93E402 9/29/98 454.00000 CS-134 2.97FA02 9/29/98 454.00000 CS-137 3.04FA02 10/2&88 507.40000 BF7 1.38E+000 2.62FAOI 10/2&i98 507.40000 KRO 2.88E+000 5.18FAOI IO/2m98 50740000 TL-208 4.09FA02 2.45E402 10/28/98 507.40000 PB-212 638FA02 3.99FA02 IO/28/98 507.40000 BI-214 4.92FAOI 6.54E402 Ion&/98 50740000 PB-214 3.90FAOI 5.60FA02 10/28/98 507.40000 1-131 2.36FA02 IO/28/98 507.40000 CS-134 2.88FA02 IO/28/98 507.40000 CS-137 2.72E402 Plant t HNP Anal >>is: GAMhfA Media BROADLEAFVEGETATION Units: GRAMS hfediat POPLAR 65 - 1.36 MI S SECTOR 7/29/98 473.90000 BE-7 2.63FAOI 2.29FAOI 7/29/98 473.90000 K~ 1.50E+000 4.40E401 7/29/98 473.90000 ~208 4.06FA02 2.74FA02 7/29/98 47390000 PB-212 135 FAOI 4 46FA02 7/29/98 473.90000 1-131 2.39FA02 7/29/98 473.900M CS-134 3.40E402 7/29/98 473.90000 CS-137 2.87E402 8/27/98 372.80000 BF7 8.7&EOOI 2.71FAOI 8/27/98 372.800M KAO 1.95E+000 5.80FAOI 8/27/98 372.80000 TL.208 4.66FA02 3.00FA02 8/27/98 372.80000 PB-212 7.79FA02 5.27FA02 8/27/98 372.80000 1-131 3.27FA02 8/27/98 372.&00M CS-134 3.91FA02 8/27/98 372.80000 CS-137 3.42E402 9/29/98 437.50000 BF7 1.37E&00 2.89FAOI 9/29/98 437.50000 KM 2.69E+000 5.63E401 9/29/98 437.50000 1-131 3.16FA02 9/29/98 437.50000 CS-134 3.51FA02 9/29/98 437.50000 CS-137 3.08FA02 Plant: HNP Anal >>is: GAMMA MediaT e: BROADLEAFVEGETATION Units: GRAMS Media: AVEETGUM 65 - 1.36hiISSECTOR 7/29/98 338 40000 BE-7 1.12E+000 3.09E401 7/29/98 338.40000 KPO 4.71E+000 7.17E401
Sample Point SampleDate Quantity Isotope Activity 2 Sigmairror 65 - 1.36MISSECTOR 7/29/9$ 338.40000 TL-208 1.27FAOI 3.73E402 7/29/98 338.40000 PB-212 2.35E401 6.29E402 7/29/98 338.40000 1-131 3.12E402 7/29/98 338.40000 CS-134 3.43E402 7/29/9S 338A0000 CS-137 3.7&E402 8i27/9S 386.40000 BE-7 1.07E+000 2.78E401 8/27/9S 386.40000 KPO 1.86E+000 5.62FAOI 8/27/9S 386.40000 TI 208 6.09E402 3.45E402 8/27/98 386.40000 1-131 2.73FA02 8/27/98 386A0000 CS-134 3.44E402 8/27/98 386A0000 CS-137 3.34FA02 9/29/98 461.10000 BE-7 8.46FAOI 2.47E401 9/29/98 461.10000 KPO 1.5 IE+000 431E401 9/29/98 461.10000 1-131 2.66E402 9/29/98 461.10000 CS-134 332E402 9/29/98 461.10000 CS-137 2.60E402 10/28/98 471.50000 BF7 1.19E+000 1.&OE401 10/2&/98 471.50000 K40 1.86E+000 434 E401 10/2&/98 471.50000 TL 208 5.12E402 2.14E402 10/28/98 471.50000 PB-212 1.34E401 3.17E402 Ion a98 471.50000 I-131 1.87FA02 Ion&/98 471.50000 CS-134 2.22E402 Ion&/98 471.50000 CS-137 1.68E402 66 - 1.33MISSWSECTOR 7n9/98 428.10000 BE-7 5.27E401 1.93E401 7/29/98 428.10000 KAO 6.96E401 4.24FA01 7n9/98 428.10000 I-131 2.64E402 7/29/98 428.10000 CS-134 2.78E402 7/29/98 428.10000 CS-137 3.27FA02 8/27i98 417.20000 BE-7 8.31E401 2.45FAOI 8/27/98 417.20000 KPO 1.68E+000 495 E401 Sn7/98 417.20000 TL-20$ 4.69E402 2.52E402 8/27/98 417.20000 PB-212 1.09E401 4.40E402 8/27/98 417.20000 1-131 2.90E402 8/27/98 417.20000 CS-134 336 E402 8/27/98 417.20000 CS-137 3.44E402 9n9/98 457.20000 BE-7 7.83FAOI 2.22E401 9/29/98 457.20000 KRO 1.72E+000 4.20E401 9/29/98 457.20000 PB-214 6.84FA02 5.20E402 9/29/98 457.20000 I-131 3.13E402 9/29/98 457.20000 CS-134 3.42E402 9/29/98 457.20000 CS-137 2.87E402 6
Sample Point SampleDate Quantity Isotope Activity 2 Sigmamrror 66 - 1.33 MI SSW SECTOR 10/2N98 452.70000 BE-7 8.54FA01 2.25FA01 Ion 8/98 452.70000 KM 1.55E+000 4.25E401 10/28/98 452.70000 TL-208 4.21FA02 1.75FA02 tons/98 452.70000 PB-214 8.66FA02 4.86FA02 tons/98 452.70000 I-131 2.38FA02 Io/28/98 452.70000 CS-134 3.47FA02 10/28/98 452.70000 CS-137 3.03FA02 Phnt: HNP Anal vis: GAMMA MediaT: DRINKINGIVATERUnits: LITERS 38 - CAPE FEAR PLANT INTAKE- CONTROL 8/31/98 1.00000 NO-ACT 7/31/98 1.00000 KM 1.68E+002 4.66E+001 9/30/98 1.00000 NO-ACT 10/31/98 1.00000 PB-212 7.02E+000 4.79E+MO 11/30/98 1.00000 NO-ACT 1261/98 1.00000 NO-ACT 40 - LILLINGTON- CAPE FEAR RIVER 8/31/98 1.00000 NO-ACT 7/31/98 1.00000 NO-ACT 9/30/98 1.00000 NO-ACT Io/31/98 1.00000 NO-ACT I I/30/98 1.00000 KAO 1.93E+002 4.43E+001 11/30/98 1.00000 RA-226 5.49E+001 4.89E+001 12/31/98 1.00000 NO-ACT 51 - WATER TREATMENTBLDG AT HARRIS PLA 8/31/98 1.00000 NO-ACT 7/31/98 1.00000 NO-ACT 9/30/98 1.00000 NO-ACT 10/31/98 1.00000 NO-ACT 11/30/98 1.00000 NO-ACT 12/31/98 1.00000 NO-ACT Plant: HNP ~ts: GAMMA hfedlaT t FOOD CROP Units: GRAMS hfedlat CABBAGE 54 - RD 1189 1.7 hti NNE(WILKINSOR MORRIS) 7n8/98 637.20000 BF7 2.19FA01 1.33FA01 7/28/98 637.20000 KM 3.72E+000 3.42FA01 7/28/98 637.20000 I-131 1.48FA02 7/28/98 637.20000 CS-134 1.79E-002 7/28/98 637.20000 CS-137 1.90FA02 55 - RD 1167 1.7 hil NNW (GOODWIN) 12/9/98 624.50000 K@0 1.71E+000 3.17FAOI 12/9/98 624.50000 PB-212 2.97FA02 2.54FA02 12/9/98 624.50000 1-131 1.31E402 12/9/98 624.50000 CS-134 1.73E402 12/9/98 624.50000 CS-137 1.61E002 Phnt: HNP Anal sis: GAMhiA MediaT e: FOOD CROP Units: GRAhtS hfedia: COLLARDS
Sample Point SampleDate Quantity Isotope Actmty 2 Stgmaarror SS - RD 1167 1.7MINNW(GOODWIN) 9/15/98 617.70000 KM 4.81E+000 5.21EAOI 9/15/98 617.70000 I-131 1.90FA02 9/15/98 617.70000 CS-134 2.54FA02 9/15/98 617.70000 CS-137 2.15FA02 10/28/98 522.70000 KAO 2.79E+000 4.13FA01 10/2N98 522.70000 BI-214 1.20FA01 3.53FA02 Iona98 522.70000 PB-214 1.25FAOI 3.44FA02 Ionm98 522.70000 I-131 1.68E402 Ion 8/98 522.70000 CS-134 2.35E402 Ion 8/98 522.70000 CS-137 2.10FA02 11/17/98 583.50000 KM 3.18E+000 4.61EAOI 11/17/98 583.50000 I-131 1.97FA02 11/17/98 583.50000 CS-134 2.26FA02 11/17/98 583.50000 CS-137 2.41FA02 Plant: HNP Anal sist GAMMA MedhT t FOOD CROP Units: GRAMS Media: TOhfATOES 5 - PITTSBORO- CONTROL 7/2m98 658.10000 KAO 2.64E+000 3.94FAOI 7n8/98 658.10000 1-131 1.62FA02 7/28/98 658.10000 CS-134 2.27FA02 7/2I98 658.10000 CS-137 239 FA02 55 - RD 11671.7 MI NNW(GOODWIN) 7/28/98 726.10000 KAO 2.42E+000 3.68E401 7/28/98 726.10000 1-131 1.51FA02 7/28/98 726.10000 CS-134 2.01EA02 7/28/98 726.10000 CS-137 1.94EA02 Plant: HNP Anal sist GAMMA MedhT FOOD CROP Units: GRAMS hfedla: TURNIPSAND GREENS 54 - RD 1189 1.7 MI NNE (WILKINSOR MORRIS) 11/17/98 554.00000 KAO 237E+000 3.95FAOI 11/17/98 554.00000 I-131 2.00FA02 11/17/98 554.00000 CS-134 2.50E402 11/17/98 554.00000 CS-137 2.48FA02 12/9/98 554.40000 KPO 133 E+MO 3.14FAOI 12/9/98 554.40000 I-131 2.02FA02 12/9/98 554.4MOO CS-134 2.62FA02 12/9/98 554.40000 CS-137 2.14FA02 62 - 2.3 hil NE SECTOR(LEE) 12/9/98 598.30000 KRO 4.83E&00 4.96FAOI 12/9/98 598.30000 I-131 2.02FA02 12/9/98 59830000 CS-134 2.23FA02 12/9/98 598.30000 CS-137 2,00FA02 Plant: HNP Anal sis: GAMMA hfedla FREE AVIMMER Units: GRAMS hfedla: LARGEMOUTHBASS 44 - SITE VARIES WITHINHARRIS LAKE 11/11/98 506.00000 KAO 4.62E+000 9.79FAOI 45 - SITE VARIES ABOVE BUCKHORN DAM- CON 11/11/98 549.20000 KPO 2.77E+000 1.04E+000
Sample Point SampleDate (}uantity Isotope Activity 2 Sigmalrror Plant: HNP Anal wist GAhfhfA MedlaT FREE AVIhfMER Units: GRAMS hfedla: SUNFISH 44 - SITE VARIES WITHINHARRIS LAKE 11/11/98 491.80000 KRO 4.28E+000 9.03E401 45 - SITE VARIES ABOVE BUCKHORN DAM- CON 11/11/98 520.60000 KAO 4.55E+000 1.05E+000 Plants HNP Anal mls: GAMhfA Media: GROUNDWATER Units: LITERS 39 - DEEP WELLNEAR DIABASE DIKES 9/3/98 1.00000 NO-ACT 11/19/98 1.00000 NO-ACT 57 - 0.4 MI SSW SECTOR N BANKESW INTAKE 9/3/98 1.00000 KAO 1.37E+002 5.89E+001 11/19/98 1.00000 NO-ACT 58 - 0.5 MI WSW SECTOR N BANKESW INTAKE 9/3/98 1.00000 NO-ACT 11/19/98 1.00000 NO-ACT 59 - 0.5 Ml NNE SECTOR (NEAR CONSTRUCTION 9/3/98 1.00000 NO-ACT 11/19/98 1.00000 NO-ACT 60 - 0.5 MI ESE SECTOR W BANKOF THOMAS CR 9/3/98 1.00000 NO-ACT 11/19/98 1.00000 NO-ACT Plant: HNP Anal wist GAMhfA McdiaT MILK Units: LITERS 5 - PITTSBORO- CONTROL 10/5/98 1.00000 K<0 136E+003 1.80E+002 7/6/98 1.00000 KAO 1.50E+003 2.24E+002 7/20/98 1.00000 KQO 1.26E+003 1.72E+002 8/3/98 1.00000 KCO 1.63E+tN3 2.15E+002 8/17/98 1.00000 K-40 1.65E+003 2.11E+002 9/8/98 1.00000 KQO 1.50E+003 2.06E+002 9/21/98 1.00000 KRO 4.06E+002 4.&IE&OI 10/19/98 1.00000 KRO 1.46E+tN3 2.21E+002 11/16/98 1.00000 K@0 1.49E+003 2.21E&02 I I/2/98 1.00000 KAO 139 E+003 2.08E+002 11/2/98 1.00000 BI-214 4.03E+OOI 235 E+OOI 12/7/98 1.00000 K~ 1.37E+003 2.28E+002 12/21/98 1.00000 KRO 1.40E+tw3 1.68E&02 Plant: HNP Anal vis: GAMMA hfedia: SHORELINE SEDIMENT Units: GRAMS 26 - SPILLWAYON hfAINRES 7/ &/98 1254.80000 KAO 1.43E+001 1.07E+000 7/8/98 1254.80000 TI 208 9.67E402 4.03E~I 7/8/98 1254.80000 PB-212 2.62E401 5.32E402 7/8/98 1254.80000 BI-214 2.17E401 7.5&E402 7/8/98 1254.80000 PB-214 2.&OE401 7.71E402 7/8/98 1254.80000 RA-226 1.52E+000 7.27E401 7/8/98 1254.80000 AC-228 2.77E401 1.21E401 I I/6/98 1240.30000 KRO 9.65E+000 1.05E+000 11/6/98 1240.30000 TL-208 1.03E401 2.90E402
Sample Point SampleDate Quantity Isotope Activity 2 Sigmamrror 26 - SPILLWAYON MAINRES 11/6/98 1240.30000 PB-212 2.67FAOI 5.17IA02 11/6/98 1240.30000 PB-214 1.93FAOI 1.93FAOI 11/6/98 1240.30000 RA-226 9.77FAOI 5.52FAOI 41 - SHOREUNE OF COOLING TOWER MIXINGZ 7/198 1487.90000 KRO 194E+001 1.12E+000 7/8/98 1487.90000 TLr208 8.64FA02 3.76E402 7/ I98 1487.90000 PB-212 2.8IE401 5.09FA02 7/ I98 1487.90000 PB-214 1.91FAOI 4.82E402 7/8/98 1487.90000 RA-226 8.16E401 5.24FAOI I I/6/98 1495.20000 KQO 1.22E~I 1.07E+OM 11/6/98 1495.20000 TI 208 7.56FA02 3.71FA02 I I/6/98 1495.20000 PB-212 2.32FAOI 6.39FA02 I I/6/98 1495.20000 PB-214 2.36E401 6.72FA02 Plant: HNP Anal sist GAhthIA hfedlaT t SURFACEiVATER Units: LITERS 26 - SPILLWAYON MAINRES 861/98 1.00000 NO-ACT 761/98 1.00000 NO-ACT 9i30/98 1.00000 KAO 3.32E+002 3.88E~I 10i31/98 1.00000 RA-226 1.28E+002 8.90E+OOI 1160/98 1.00000 PB-214 8.93E+000 5.88E+000 1261/98 1.00000 NO-ACT 38 - CAPE FEAR PLANT INTAKE- CONTROL 8/31/98 1.00000 NO-ACT 7/31/98 1.00000 KRO 1.68E+002 4.66E+001 9/30/98 1.00000 NO-ACT 10i31/98 1.00000 PB-212 7.02E+000 4.79E+000 11/30/98 1.00000 NO-ACT 12/31/98 1.00000 NO-ACT 40 - ULUNGTON - CAPE FEAR RIVER 8/31/98 1.00000 NO-ACT 761/98 1.00000 NO-ACT 9/30/98 1.00000 NO-ACT 10/31i98 1.00000 NO-ACT 1160/98 1.00000 KQO 1.93Et002 4.43E+001 11/30/98 1.00000 RA-226 5.49E+001 4.89E+001 1261/98 1.00000 NO-ACT