ML20206N911
| ML20206N911 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 12/31/1998 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20206N877 | List: |
| References | |
| NUDOCS 9905180100 | |
| Download: ML20206N911 (103) | |
Text
O RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1998 i
O BRUNSWICK STEAM ELECTRIC PLANT CAROLINA POWER & LIGHT i
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- r1=an ::=a:m R
i CP&L ob' kl To:
Mr. Jerry W. Johnson W
From:
S. P. Langdon Date:
April 29,1999
Subject:
1998 BSEP Radiological Environmental Operating Report Attached is the original and four copies of the 1998 Radiological Environmental Operating Report (Volumes I, II, and III) for the Brunswick Steam Electric Plant. A verification and validation summary package for the report has been included as well. After the report has been routed through Regulatory Affairs and received plant approval, the original should be submitted to the following by May 15, 1999:
Document Control Desk G
USNRC O
Washington, D.C. 20555 Additional copies of the report should be provided to the NRC Regional Office in Atlanta and the plant records vault. The remaining copies of the report are for the site resident NRC inspector and your use. This will satisfy the requirements of Technical Specification 5.6.2 and Off-site Dose Calculation Manual Specifications 7.4.1 for 1998.
If you have any questions, please call me at Caronet 8-772-3201.
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SPL c:
Mr. Keith Jury O
SHEARON HARRIS ENERGY & ENVIRONMENTAL CENTER Carolina Power & Light Company New Hill, North Carolina RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR BRUNSWICK STEAM ELECTRIC PLANT JANUARY I THROUGH DECEMBER 31,1998 Prepared by:
a Reviewed by:
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1 TABLE OF CONTENTS Title Page Table of Contents i
l List of Figures ii List of Tables iii Executive Summary 1
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
l Sources of Radiation 8
Health Effects of Radiation 10 General Health Risk 11 Nuclear Power Plant Operation 12
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Plants Systems 14 l
Reactor Safety 18 Radiological Environmental Monitoring Program 19 Purpose and Requirements for the Radiological Monitoring Program 19 General Site Ikscription 20 Radiological Monitoring Program Quality Assurance 21 Radiological Monitoring Program General Description 22 Summary of Radiological Monitoring Program 27 Interpretations and Conclusions 31 Missed Samples and Analyses 35 Analytical Procedures 35 Land-Use Census Purpose of the Land Use Census 40 l
Methodology 40 l
1998 Land-Use Census Results 41 References 43 O
i L
q LIST OF FIGURES V
l Figure Page 1
CP&L Service Area 2
2 1998 Energy Sources 2
3 The Atom 3
4 Radioactive Decay 5
5 Ionization 6
6 Radiation Ranges & Shielding 6
7 Source of Radiation Dose (BIER V) 9 8
Man-Made Radiation (BIER V) 9 9
Nuclear Fission 12 10 Nuclear Fuel Cycle 13 11 Fuel Pellets, Rods & Assemblies 13 p
12 Major Plant Systems for the Boiling Water Reactor 14 13 Reactor Vessel 15 14 Prirr.ary Containmen Structure 16 15 Location of Brunswick Steam Electric Plant 20 16 Radiological Sampling Locations (Distant from Plant) 23 17 Radiological Sampling Locations (Nearest Plant) 24 18 Plot of Air Particulate Gross Beta Activity (Location 200) 45 19 Plot of Air Particulate Gross Beta Activity (Location 201) 46 20 Plot of Air Particulate Gross Beta Activity (Location 202) 47 21 Plot of Air Particulate Gross Beta Activity (Location 203) 48 22 Plot of Air Particulate Gross Beta Activity (Location 205) 49 23 Plot of Surface Water Tritium Activity (Location 401) 50 24 Plot of TLD Averages for Inner and Outer Rings 51 i
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ii
LIST OF TABLES O
Table Page Quality Ft.ctors for Various Radiations 8
2 Reduction In Average Life Expectancy 11 3
Media Used to Assess Exposure Pathways to Man 22 4
Radiological Monitoring Sampling Locations 25 5
Radiological Environmental Monitoring Program Data Summary 29 6
Gross Beta Air Particulate Activity Averages 33 7
IIIstorical TLD Results (1972-1998) 34 8
Typical Lower Limits of Detection (a priori) Gamma Spectrometry 39 9
Land Use Census Comparisons (1997-1998) Nearest Pathway (miles) 42 O
iii
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EXECUTIVE
SUMMARY
The Brunswick Steam Electric Plant (BSEP) is operated by Carolina Power & Light Company (CP&L) under a license granted by the Nuclear Regulatory Commission. Brunswick Steam Electric Plant Technical Specifications and the Brunswick Steam Electric 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 31,19c8.
The Radiological Monitoring program was established in 1973. Radiation and radioactivity in various environmental media have been monitored for more than 2.4 years, including monitoring in excess of a year prior to commencing operation. Monitoring is also provided for control locations which would not be impacted by operations of the Brunswick Steam Electric Plant. Using the data from the control locations and the historical data collected prior to operation, analyses of data from locations which could potentially be impacted by the operations of the Brunswick Steam Electric Plant were performed. Radiation levels show no measurable 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 e
pre-operation monitoring. These observations are also consistent with past operational data, except for the one air cartridge which had very small levels of activity.
Milk was unavailable due to no milk animals (goat or cow) currently identified within the e
environs of the plant; therefore, no exposure pathway exists.
Terrestrial vegetation includes broadleaf vegetation. Results indicate very small levels of e
activity in two broadleaf vegetation samples, but the levels were well below the NRC reporting criteria.
e Aquatic organism monitoring includes fish and benthic organisms (organisms that live on the bottom of the ocean). Results indicated no detectable activity.
Surface water results indicate no detectable activity.
e External radiation dose showed no measurable change from pre-operational data.
e The continued operation of the Brunswick Steam Electric Plant has not significantly contributed radiation or the presence of radioactivity in the environmental media monitored. The measured concentrations of radioactivity and radiation 1re wc!! within applicable regulatory limits.
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INTRODUCTION TO NUCLEAR OPERATIONS Carolina Power & Light Company (CP&L) operates an integrated electrical system serving more than one million
?.i customers in North Carolina and South Carolina. A system map is provided (Figure #1) that illustrates the area served y
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 j
30,(XX) square miles and has a population of more than 3,500,0(X)
Figure 1: CP&L SERVICE AREA peopic, The energy sources for electrical generation include
. I Nuclear l.
coal, fuel oil, natural gas, hydro-power, and nuclear j
fuel. No one energy source is best. Each fuel source has merits and disadvantages. Fossil fuels pose issues associated with clean air including emissions of sulfur dioxide and oxides of nitrogen. Both natural gas and hydro-power are in limited supply.
O x cie re cr8xie vit>ce-ve e ti aiveriiiea energy mix. In 1998 nuclear energy supplied 46.0%
of CP&L's total electrical generation. This nuclear Nuclear I
component was generated from four units including Coal j
the Brunswick Steam Electric Plant. The remaining Oil & Natural Gas energy sources were primarily from coal-fired Hydro Power generation, 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 Brunswick Steam Electric 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 clectrical needs for the future O
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Nuclear energy has the following advantages over other fuel sources:
V The fuel is uranium which is relatively inexnensive when compared with the fuels of coal, natural gas, and fuel oil.
Emissions from nuclear stations do anL include sulfur dioxide, oxides of nitrogen, or carbon dioxide. Sulfur dioxide is well known as a significant contributor to acid rain leading to acidification of streams and lakes. Oxides of nitrogen play a key role in the formation of ozone which is a significant pollutant in urbanized air quality. Finally carbon dioxide is a significant green-house gas.
Nuclear energy is safe. Nuclear power in the United states has an excellent safety record, starting with the first commercial nuclear plant in 1957.
To better understand this source of energy, a basic understanding of radiation, its elTects, risk assessment, and reactor operation follow.
RADIATION AND RADIOACTIVITY The Atom
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All matter consists of atoms. An atom is the smallest unit into which an element can be divided and still retain its identity as that element. An atom is q
made up of a number of di1Terent particles. These particles are protons, neutrons, and electrons. Each proton is positively charged (+). Each neutron has no
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heavier particles including protons and neutrons are
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found in the center of the atom in a very small cluster
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referred to as the nucleus. (The term nuclear refers to this nucleus.) Nearly all the mass of the atom is Figure 3: The Atom found in the nucleus. Electrons orbit the nucleus.
Since the atom is electrically neutral (no charge) the number of protons and electrons in the atom are equal. See Figure 3 a conceptional drawing of an atom. The electrons (red) are shown in orbit around the nucleus. The protons (green), and the neutrons (black) are shown in the nucleus at the center of the atom.
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Elements, Isotopes, and Radionuclides Simple substances that cannot be decomposed in any chemical reaction are known as elements.
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Hydrogen, oxygen, iron, chlorine, and uranium are examples of elements. The atoms of such
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elements differ in the number of protons (also know as the atomic number) in their nucleus. For
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example the number of protons in each example above is I for hydrogen,8 for oxygen,26 for iron,17 for chlorine, and 92 for uranium. The number of neutrons in the nucleus may vary in atoms of the same element. Atoms that contain the same number of protons but a different number of neutrons are referred to as isotopes of that element. An example is the element hydrogen which has three isotopes-one with no neutrons, a second with one neutron, 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 its name (or the name) followed by the total number of protons and neutrons; for example H-3 or hydrogen-3 describing an atom with one proton and two neutrons.
Radiation Radiation is defined as the conveyance of energy through space. This conveyance may occur in the form of particles, waves, or photons. Some common forms of radiation are sunlight, microwaves or radio waves. These are all examples of non-ionizing radiation, lonizing 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 r
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and a free electron. There are two types of ionizing radiation-first particulate radiation and electromagnetic radiation. Particulate radiations are energetic particles which will travel in a straight line if unhindered. Three types of particulate radiation of interest in nuclear energy, those being beta particles which are high-energy electrons (not part of an atom), neutrons, and alpha particles which consist of two protons and two neutrons. Electromagnetic Radiations are high-energy waves (or photons) which have no apparent mass (not a particle). There are two types of electromagnetic radiation of interest which are gamma rays and X-rays. Gamma rays have their origin in the nucleus of the atom. X-rays have their origin in the stored energy of the electrons orbiting the nucleus. There are many important differences in the behavior of these 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 which are the thorium, neptunium, and the uranium series. These radioactive-decay series as well as naturally occurring K(potassium)-
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g, 40, C(carbon)-14, ll(hydrogen)-3 are significant
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contributors to background radiation levels, which
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are addressed in greater detail later.
The rate at which atoms undergo radioactive decay 31j /2 varies greatly. A common expression of the tendency for radioactive decay is the half-life associated with a particular isotope. The half-life is 1/4 the amount of time required for one-half of the s\\
number of atoms for an isotope to experience 1/8 1/16 N
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radioactive decay. The longer the half-life the less 0
140 280 420 560 700 likely an atom will experience radioactive decay in Time. days a fixed time interval. Half-lives vary from Figure 4: Radioactive Decay extremely 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 thereafter.
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O RADIATION INTERACTION WITH MATTER Ionization As alpha, beta, gamma, and X-ray radiation interact with matter they impart part or all of their energy to the matter in a single interaction. It may require many interactions to absorb the energy of a single particle or photon of radiation. One of the most common ways energy is dissipated is ionization. As N
we discussed earlier this results in the creation of a positively D # $$
charged atom and a free electron. The positively charged atom a
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 a positive charge of two (two protons). The alpha particle is the slowest of the radiations we will review lf';;
with a speed of no more than 20,00() miles per second.
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As a result of these characteristics the alpha travels only
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a few centimeters (or inches) in air and is readily stopped by a sheet of paper. The alpha leaves its energy in a short distance characterized by a great many ionizations.
Beta particles are basically a very high-energy electron.
Beta particles have a negative charge. It is a very light particle, with a mass of about one two-thousandth of a proton (or about one eight-thousandth of an alpha particle). Beta particles are very fast, approaching the speed oflight. 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 severalinches oflead are required.
AU 6
RADIATION QUALITIES AND UNITS OF U,
MEASURE There are numerous qualities and units used to describe radiation and radioactivity and their effects. Those used in this report relate to activity, absorbed dose, and dose equivalent. It is also common to express numbers in scientific notation or use prefixes with the number denoting the number of zeros (0) before or after the decimal. A few examples are provided below.
Prefix Number Represented Number in Scientific Notation pico 000000000001 1x10a2 nano
.000000001 1x10*
micro
.000001 1x104 milli
.001 1 x 10-3 centi
.01 l x 10-2 kilo 1,000.
Ix10' mega 1,000,000.
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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 C
37,000,000,000 disintegrations per second; (also expressed as 3.7x10' s). A curie is a unit of
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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 l
assessment of damage to biological systems subjected to radiation and radioactive materials.
Dose equivalent is an expression of the biological effect of the radiation on tissue. The unit used to express absorbed dose equivalent is the rem. Dose equivalent is obtained by multiplying the absorbed dose (expressed in rad) by a quality factor (QF) for the type of radiation being considered.
Dose equivalent = nbsorbed dose X quality factor 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 f-different radiations we have discussed is illustrated below m
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Table 1 Quality Factors for Various Radiations Radiation Quality Factor Gamma-rays 1
l X-rays 1
Beta Particles 1
Alpha Particles 20 SOURCES OF RADIATION i
Background Radiation Radiation occurs naturally and is an everyday fact of our existence. Mankind has always lived I
with radiation and radioactive materials and will continue to in the future. The radiation that
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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, p
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 I
us as well as a source referred to as cosmic radiation which is generated in the stars throughout the galaxy including our own sun.
l Cosn < rmiiation 6 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, 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 O
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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 go,g 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 absorbed doses exceed 800 mrem each year.
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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 if the most significant C Redan Terrestrial contributors is radon. Radon is a radioactive gas that cosmic internat is part of the uranium decay series. Radon's
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M an-m ade concentration varies greatly based upon the geology of i
cach community, but is found in soils and rock every-Figure 7: Radiation Sources ( BIER V) where. 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 oflung cancer.
Man-niade radiations are important to O
completing our understanding of sources of V
Man-made Rad,ation radiation. An important aspect in discussing l
man-made radiation is the benefit man derives
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from the use of these. Medical uses of N""
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- l x-R.y. l 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.
Fallout from prior weapons testing is now a Nuclear Medioin small Contributor to total radiation dose.
Occupational exposure is also a factor from the medical, manufacturing, and nuclear industries. Finally, contributions from nuclear plant operations represent less that 1% of the O x air.
E Nnhar Medmine man-made radiations for the average member E con.um.r Products E Fallout of the general public. The data presented in E oc.p.ison.i E Msc. & Nuclear Plants Figure 8: Man-Made Radiation Sources (BIER V) different sources of man-made radiation for the average member of the public.
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HEALTH EFFECTS OF RADIATION I O The effects of ionizing radiation has been of concern to the scientific community for several I
decades. The oldest body established to study radiations biological effects date from at least 1928 with the establishment of the International Commission on Radiological Protection. Much of our l
knowledge is based upon very high doses from animal experiments, accidents handling l
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 extremely low doses i
compared with medical and occupational levels. Experiments with animals represent additional l
challenges because they may not accurately represent human biological responses to radiation.
Radiations biological effects are classified as somatic and genetic ( or bereditary). Somatic effects are observed in the individual receiving the radiation dose. Genetic effects are observed in the decedents of the individual receiving the radiation dose.
Somatic effects can be classified as acute or chronic. Acute effects occur within a short time (days) after the dose is received. Generally acute effects require very high doses. f jood 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 l
discussion of environmental radiation.
Chronic effects are generally used to refer to effects that are observed a long period of time and these have also been referred to as delayed effects. The effects are also generally associated with l
radiation dose received over a long period know 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 i
l 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 much higher dose to establish the rate of cancers at that dose and then assume that the rate of cancers must be proportional to the lower doze. 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.
I Genetic radiation effect 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 rN V
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sometimes necessary in the creation of chemical bonds. If the bonds are part of the genetic l O material of the cell, it could result in changed genetic material ( mutations). Radiation is just one V
of several agents that contribute to genetic change. Chemicals including those that occur l
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 l
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.
GENERAL HEALTH. RISK l
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 l
than the real risk of an activity. There was widespread fear and misunderstanding regarding the l
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 analysis 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, carbon monoxide in the operation of some fumaces and our vehicles due to our familiarity with these.
l A common was 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 s
Table 2 REDUCTION IN AVERAGE LIFE EXPECTANCY ACTIVITY REDUCTION IN LIFE EXPECTANCY CIGARETTE SMOKING 2 PACKS / DAY 10 YEARS CIGARETTE SMOKING 1 PACK / DAY 7 YEARS HEART DISEASE 5.8 YEARS LIVING IN CITY VERSUS RURAL 5 YEARS OVERWEIGHT 30 %
3.6 YEARS CANCER 2.7 YEARS COMMERCIAL NUCLEAR POWER 12 MINUTES
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O NUCLEAR POWER PLANT OPERATIONS Ac primary difference between a nuclear generating station and fossil generating station is the source of heat or thermal energy. The steam turbine, condenser, condensate and feed water systems are much the same. The uranium fuel within the nuclear reactor is the source of heat or energy in the nuclear generating station.
Nuclear Fission Certain heavy radionuclides are known to naturally undergo a special form of radioactive decay, called spontaneous fission. Spontaneous fission means the nuclei of these radioisotopes literally split into two or three new nuclei (also known a fission fragments) and a few free neutrons) not in a nucleus). The protons and neutrons are shared between these new nuclei. One isotope of Uranium known as U-235 is known to undergo fission. The other more common isotope of Uranium known as U-238 does not fission so easily.
Fission can also be stimulated by neutrons interacting with the nucleus of these atoms. Simply stated a neutron reaches the nucleus and produces fission fragments, free neutrons, and heat.
Fission of Uranium produces more than one neutron per fission. Therefore; if there is enough uranium (especially U-235) present is it possible to produce more fissions and keep the process going or cause more and more fissions to occur. When the rate of fission initiated is scif sustaining or increasing a chain reaction has been established. It is this sustained chain reaction and the energy produced that produces the heat needed to generate steam for electrical O
generation.
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Am Fission Fragment Figure 9: Nuclear Fission
l Uranium Fuel Uranium is mined from the earth the same as many minerals are as an ore. This uranium ore is then taken to a mill to concentrate the uranium. The extraction process for uranium uses acids to dissolve the uranium and separate it from the ore. This uranium is then converted chemically to a gas uranium hexafloride ( in chemical notation UF ) While in this form it is possible to 6
separate the lighter U-235 from the heavier U-238. This process of separation is called I
gaseous diffusion. The reason for NUCLEAR FUEL CYCLE separation is to allow more of the U-
,g 235 to be included in the fuels used in p l l
commercial reactors. We have already f
lH discussed that U-235 fissions more d'j y
- M readily that U-238. This process that increases the amount of U-235 is also MINE MILL CONVIRTER referred to as enrichment. After enrichment this gas is chemically V
converted to uranium dioxide ( in y
chemical notation UO ). At this point g
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,1 the uranium dioxide is a gray powder.
The next process takes this powder REACTOR FU!L FABRICATOR ENRICHER and under high pressure, and MA!!00$ 0lffU$KX 7 TANT)temperature creates a ceramic pellet of uranium dioxide. This process is part Figure 10: The Nuclear Fuel Cycle of the fuel fabrication. The fuel fabricator also ensures that each fuel pellet also has the g
proper amount of U-235 and U-238. The additional U-235 retter added is referred to as the percent enrichment which for g
r commercial reactors is about 6% of the total uranium in the Q
,Cl lh fuel. These fuel pellets are placed into long tubes of I
1 zirconium alloy or fuel rods. These rods of uranium fuel
[j are then placed with other such fuel rods into a fuel i
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assembly. This fuel assembly is the basic unit that is shipped to the nuclear power plant. It is important to note
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controlled to ensure the quality of the nuclear fuel.
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V ROD ASSEMBLY Figure 11: Fuel Pellets, Rods &
Assemblies p)
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PLANT SYSTEMS oV System Summary l
There are four (4) grouping 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 magrietic field.
Electricity is generated in winding of metallic conductors around this magnetic field and 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 w'ater 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 l
tower is used. After the steam has been recovered as water it is retumed through a system of pumps, piping and heaters to the reactor. The process of reusing this water and steam m a continuing cycle is referred to as the steam cycle.
Steam
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v water Controls ye Pump Figure 12: Major Plant Systems for The Iloiling Water Reactor 14
1 Reactor Types and the Reactor Vessel Commercial nuclear reactors are being used to generate electricity in the United States today. Of these, there are two basic types of reactor in use today, the Pressurized Water Reactor (PWR) and the Beiling Water Reactor (BWR). The i
l basic difference is the point where steam is formed. The l
boiling water reactor fonns steam in the reactor while the l
pressurized water reactor forms steam through a separate heat I
exchanger called a steam generator. The Brunswick Steam Electric Plant is a Boiling Water Reactor (BWR). There are other types of reactors used for research and military purposes.
The collection of fuel assemblies is referred to as the reactor core. The Brunswick Steam Electric Plant has 560 fuel assemblies in the reactor core. The reactor core, the controls, instrumentation as well as other components are located in the I
l reactor vessel. The components vary greatly by reactor type.
The reactor vessel is a specially designed container which I
I supports all of the components. The reactor vessel is nominally 5-9/16 inches thick of steel on the sides with a stainless steel lining.
g j
The rate of nuclear fission is controlled by neutron absorbing O
materials. One of the most common materials used is an Figure 13: Reactor Vessel isotope of boron known as boron-10 (B-10). Also control rods are used that are made of other materials including indium and cadmium. By controlling how much of the control rods are inserted in the reactor core the rate of nuclear fission is controlled.
The Brunswick Steam Electric Plant has 137 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. After treatment by the steam separator the steam passes through a steam dryer to remove additional water. The water removed by the steam separator and dryer is returned to the water in the reactor vessel. The boiling water reactor also has a special pair of recirculating pumps that provide additional control of steam generation and reactor power.
The pressurized water reactor does not generate steam in the reactor. The reactor vessel is pressurized to prevent boiling from occurring in the reactor or the reactor vessel. Steam is generated in a heat exchanger called the steam generator. The steam and the water from which steam is generated is a separate water system from reactor water or reactor coolant. This separate water system is referred to as secondary system while the reactor's water system is referred to as the primary system. In the pressurized water reactor it is this secondary water that steam is made from and recycled through the condenser and feedwater system. This water is returned to the steam generator.
g Sources of Radioactive Materials In Reactor Operation I \\J There are two primary means that radioactive materials are produced in reactor operation which are:
l e
Fission produces two or more fission fragments in each fission. These fission fragments I
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. Example of these l
isotopes are iodine-131 (I-131), strontium-90 (Sr-90), cesium-137 (Cs-137), as well as others.
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 I
tritium (H-3) and cobalt-60 (Co-60). These radio nuclei are referred to as activation products.
l The sources of radioactive emissions from nuclear power operations are the treatment of water l
from the reactor systems, the treatment of air in the buildings that house plant systems, and the condenser vacuum system. Each of these emissions is managed to reduce the emissions to levels that are considered as low as reasonably achievable. The radiological monitoring program is designed to assess the impacts of these emissions even though they are acknowledged to be small contributors to background radiation.
(3 Barriers to Release of Radioactive Materials
'W There are several barriers to release of nadioactive materials. In order these are:
e the ceramic fuel pellet itself e
the zirconium cladding of the fuel rod e
the reactor vessel and its associated piping e
the primary containment structures e
the secondary containment or
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reactor building N
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The fuel, fuel rods, and the reactor vessel
.c have already been discussed. The primary
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containment structures are illustrated in Figure 14. The containment houses the reactor core (in black) and the reactor vessel and its associated piping. The PRIMARY CONTAINMENT STRUCTURE primary containment also includes a 16 Figure 14:
[
suppression chamber partially filled with water. This suppression chamber functions to suppress the energy of the reactor in conditions in which the condenser is not available to receive the steam or energy from the reactor. The steam produced by the reactor is transferred to the suppression chamber through pressure relief valves and piping.
The secondary containment is the reactor building itself. This secondary containment is maintained at a pressure lower than the pressure outside the building. This is accomplished by a system of fans and filter systems that treat the air inside the secondary containment; thus, any air j
leakage would be into the secondary containment from the outside. The air coming from I
' secondary containment is all filtered and treated prior to discharge.
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17
o REACTOR SAFETY There are several points regarding nuclear safety that are important to understand and these are:
+
Commercial nuclear generating station can nat 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 j
rate of nuclear fission. This is accomplished by inserting or withdrawing control rods or by the addition of neutron absorbing materials. A special safety system is part of the reactor control system call the reactor protection system which will cause the control rods to be quickly inserted. This insertion causes to 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 vary by reactor type. These systems that delivery this supplemental source of water are i
referred to a the Emergency Core Cooling System. There are even backup systems to the individual Emergency Core Cooling Systems. This practice is referred to a defense in depth. Safety is not dependent on any one device but is a system of several backups.
The Brunswick Steam Electric Plant is desigacd to be a safe means of generating electrical power. This level of safety is further enhanceo through the discipline of operation provided by a j
well qualified and trained staff. Ongoing training is provided to the staff to ensure a high quality j
performance from each member of the plant staff. Although the requirements are high for the staff, reactor operators and senior reactor operators must also pass a rigorous license examination by the Nuclear Regulatory Commission on a regular basis. These examinations test knowledge of plant systems, design, procedures, problem solving, regulatory requirements, and the ability to function as a team responding to plant conditions.
O
=-
18
RADIOLOGICAL ENVIRONMENTAL gV MONITORING PROGRAM PURPOSE AND REQUIREMENTS FOR THE RADIOLOGICAL MONITORING PROGRAM Although the operation of a nuclear generating station results in the raising of background radiation only a small amount,it is important to measure these emissions of radioactivity and radiation to 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 Brunswick Steam Electric 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 containment and radiological controls of nuclear generating stations.
The radiological monitoring program was established in 1973 and continued to collect samples and evaluate them for twenty four (24) years.
Requirements are established for the radiological monitoring program as follows:
[G Technical Specifications Off-Site Dose Calculation Manual (ODCM) various procedures e
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
' O General Site Description The Brunswick Steam Electric Plant
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reactors with a design rating of 1631 Megawatts electric (Mwe)(820 and i) #
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811). Commercial production was
.w initiated by Unit Two on November 3, f,,, r e-s 1975 and by Unit One on March 18,
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~f' 1977. The Brunswick Steam Electric Plant is located in Brunswick County,
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North Carolina. The site is along state 4
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route 87 approximately two and a half (2.5) miles north of Southport and is 2,,
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,o,.7, Y. 4 North Carolina (Figure 15). The
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- The towns of Caswell Beach, Yaupon
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Beach, and Long Beach are on a barrier gure ca mn ninswie Steam Bectn. Mant c
island south of the plant. The site is also approximately sixteen (16) miles south h
of Wilmington, North Carolina.
The Cape Fear River is cast of the plant and cooling water is drawn from the river through a canal. The cooling water is discharged to the Atlantic Ocean through a canal, pumping station, and piping. The discharge point is south of the town of Caswell Beach.
The plant site varies in elevation from sea level to thirty (30) feet above mean sea level (M.S.L.).
It is surrounded by extensive marshes. The lower Cape Fear River is an important nursery area for shell fish, and other marine species.
The local economy supports significant recreational, industrial, agricuhural, and government contributions. There is well developed recreational use of the barrier islands south and cast of the site. Fishing and boating are popular activitics. Commercial fishing is also an important industry in the community. Agriculture utilizes less than half ofland within 50 miles of the site.
Agricultural activities are small truck farms, cattle, poultry, and row crops including corn, soybeans and tobacco. Industrial activity includes the Archer-Daniels-Midland Chemical Company, a manufacturer of citric acid located one and a half (1.5) miles southeast of the plant.
In conjunction with the citric acid plant is a small electrical generating station operated by Cogentrix, Inc. This coal fired station is composed of two units rated at 55 MWe each.
Transportation is a significant industry in the local economy with the Port of Wilmington north of the site. The ships channel is just cast of the site in the Cape Fear River. Also the Sunny Point Military Ocean Terminal is located approximately four and one half (4.5) miles north of the plant p
site and on the Cape Fear River.
V 20 L
e I
l I
o RADIOLOGICAls MONITORING PROGRAM QUALITY ASSURANCE A required component of the environmental radiological monitoring program is the Quality Assurance Program. The standards for the quality assurance program are established in the NRC Regulatory Guide 4.15," Quality Assurance for Radiological Monitoring Programs." The purpose of the quality assurance program is "(1) to identify deficiencies in the sampling and measurement processes to those responsible for these operations so that corrective action can be taken, and (2) to obtain some measure of confidence in the results of the monitoring programs in order to assure the regulatory agencies and the public that the results are valid" This provides the opportunity to implement corrective actions that address possible deficiencies. Examples of the activities of the quality assurance program include:
o regular review of sample collection and records e
regular review of laboratory procedures and methods participation in the Analytics, Inc., Environmental Cross-Check Program, which provides e
an independent assessment of the quality oflaboratory results.
the use of known concentrations of radioactivity in test samples by the laboratory to e
ensure consistent quality results on an ongoing basis.
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21
n RADIOLOGICAL MONITORING PROGRAM U
GENERAL DESCRIPTION Although the contribution to background radiation is small, we have established this program to measure the exposure pathways to man. An exposure pathway describes the source of the radiological exposure. The primary forms of radiological emissions from the plant are airborne and liquid discharge. The following pathways are monitored external dose, ingestion of radioactive materials, and the inhalation of radioactive material. Specific methods and different environmental media are required to assess each pathway. Below in Table 3 is a list of the media used to assess each of these pathways.
Table 3 Media Used to Assess Exposure Pathways to Man Pathway of Exposure to Man Media Sampled External Dose Thennoluminescent Dosimetry (TLD)
Shoreline Sediment Ingestion Broadleaf Vegetation Fish and Invertebrates Surface Water j
l 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 oflocations are selected as controls. Control stations are selected because they are very unlikely to be affected by operation of the plant. Sample locations may be seen in Figures 16 and 17. A description of each sample location may be found in Table 4.
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o, Radiological Sampling Locations V
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(h 204703,704705,302 NOT SHOWN
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Figure 16: Radiological Sampling Locations (Distant from Plant) (Scale 1 inch = 3.08 miles) 1 l
Thermoluminescent dosimeter locations are displayed in black, ingestion and waterborne i
pathways in blue, and the inhalation or air sampling station in red.
Stations not illustrated:
204 (Sutton Plant in Wilmington) (Control Air Station) 703,704,705 (Location not Specified in the Atlantic Ocean)(Control Fish Station) 802 (Location not specified) (Control Vegetation) l l
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Radiological Sampling Locations k,e-hay Osean TermJI Swriy Peu M
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Figure 17: Radiological Sampling Locations (Nearest Plant) (Scale 1 inch =.8 miles)
Thermoluminescent dosimeter locations are displayed in black, ingestion and waterborne pathways in blue, and inhalation or air sampling stations in red.
Stations not illustrated:
204 (Sutton Plant in Wilmington)(Control Air Station) 703,704,705 (Location not Specified in the Atlantic Ocean)(Control Fish Station) 802 (Location not specified) (Control Vegetation)
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I Table 4 l
llrunswick Steam Electric Plant r\\
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Radiological Monitoring Sampling Locations j
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Sample Type Location & Description Frequency Sample Size Analysis i
Air 200--1.0 mile SW Visitors Center R'ukly 10,000 ft' Iodine idge 201-0.6 mile NE PMAC (Highest D/Q)
(300 m )
3 202--l.0 mile S substation-construction rd.
203--2,3 miles SSW Southport substation 204--23 miles NNE Sutton Plant
- j 205--0.6 mile SSE Spoil Pond i
Air 200--l.0 mile SW Visitors Center Weekly 10,000 ft Gross Beta
)
P iculate
( p 201-0.6 mile.NE PMAC (Highest D/Q)
(300 m )
(Weekly) 2 202--l.0 mile S substation-construction rd.
r osite Ga 203--2.3 miles SSW Southport substation (Quarterly) l 204--23 miles NNE Sutton Plant
- 205--0.6 mile SSE Spoil Pond s
Fish (FI) 700-5.5 miles SSW Atlantic Ocean @
Semiannual 500 rams Gamma discharge (free-swimmers)
(In Season)
(wet 701--5.5 miles SSW Atlantic Ocean @
l discharge (bottom-feeders) l 702--5.5 miles SSW Atlantic Ocean @
discharge (invertebrates)
(
)
703--Atlantic Ocean; location not I
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specified* (free-swimmers)
{
704--Atlantic Ocean; location not specified* (bottom-feeders) 705--Atlantic Ocean; location not l
specified* (invertebrates)
Broadleaf 800--0.7 mile NE intake canal Monthly 500 grams Gamma (Bhetation801--0.6 mile SW discharge canal (As,1 ble)
V (wet) av 802 -10 miles; location not specified*
803--0.6 mile SSE Spoil Pond l
L Shoreline 500--4.9 miles SSW; beach near OD pumps Semiannual 500 grams Gamma l
Sediment l
(SS)
Surface 400--0.7 mile NE intake canal
- Control Stations I
i V
25 l
Table 4 (Continued)
Brunswick Steam Electric Plant
(
Radiological Monitoring Sampling Locations
(
Sample Type Location & Description Frequency Sample Sz Analysis Thennoluminescent i 1.1 miles E Moore St. extension Quarterly Not TLD Dosimetry (TLD) 2 1.0 mile ESE Moore St. ext.
Applicable Reading 3 0.9 mile SE Moore St. extension 4 1.1 miles SSE Moore St. ext.
5 1.1 miles S Leonard St.
6 1.0 mile SSW BEMCO Power Line 7
1.0 mile SW Hwy 87 at r.o.w.
8 1.2 miles W liwy 87 9 1.0 mile WNW Bethel Cherch Rd.
10 0.9 mile NW Bethel Church Rd.
I1 0.9 mile NNW Bethel Church Rd.
12 1.0 mile N Bethel Church Rd.
13 1.2 miles NNE Bethel Church Rd.
14 0.5 mile NE intake canal 15 0.9 mile ENE intake canal 16 1.0 mile WSW discharge canal 17 1.5 miles ESE A.D.M. property 18 1.7 miles SE A.D.M. property 20 2.0 miles S church on Stewart St.
21 2.9 miles SSW West St. Sea Captain 22 5.3 miles SW Caswell Beach Rd.
23 4.6 miles WSW near airport
(
24 3.0 miles W Hwy 211
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25 8.7 miles WNW Antioch Church 26 5.9 miles NW W. Boiling Springs Rd 27 5.0 miles NNW Hwy 133 28 4.2 miles NW South Brunswick HS 29 2.6 rniles SSW Southport Elem. School 30 2.0 miles NE Sunny Point MOT 31 2.6 miles ENE Sunny Point MOT 32 5.7 miles ENE Ft. Fisher AFB 33 4.0 miles E Ferry Slip N.H. Co.
34 5.5 miles ENE Ft. Fisher Museum 35 7.5 miles SSE Bald llead Island 36 9.3 miles NE Carolina Beach 37 5.5 miles NW Boiling Springs Lakes 38 11.0 miles W at Sunset Harbor 39 5.3 miles SW Yaupon Beach City Hall 40 6.9 miles WSW Long Beach City Hall 75 4.5 miles S Ft. Caswell Dapt. Assy.
76 4.8 miles SSW at Oswell Beach 77 5.3 miles S af Bald Head Island 78 10.0 miles NNE Hwy.133 at SR 1521 79 9.5 miles N SR 1539 at SR 1521 81 10.0 miles WNW Midway Rd. at SR 1508*
- Control Stations
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D 26
p
SUMMARY
OF RADIOLOGICAL MONITORING PROGRAM d
This report presents the results of the Radiological Environmental Monitoring Program conducted during 1998 for the Brunswick Steam Electric Plant. The program was conducted in accordance vith the Off-site Dose Calculation Manual Specifications (ODCMS), and applicable procedures.
The 1998 Annual Radiological Environmental Operating Report (REOR) has been prepared and submitted in accordance with Technical Specification 5.6.2 and ODCMS 7.4.1.
The report app'ies to both BSEP Units 1 and 2 (License Nos. DPR-71 and DPR-62, respectively).
Nearly 950 samples from six environmental media types were analyzed during the year.
Iodine (I-131) activity in an air cartridge (AC) was detected at location AC-201 (0.6 miles NE
- PMAC) in late April and in two of three broadleaf vegetation samples at location BL-800 (0.7 miles NE - Intake Canal) in early May. The activity (1-131) reported in the air cartridge (AC-201) was 1.10 E-1 pCi/m', in the broadleaf(BL-800 Wax Myrtle) was 1.33 E-1 pCi/g wet, and broadleaf (BL-800 Cherry) was 7.17 E-2 pCi/g wet. The levels detected were very small r)
(J and far below the NRC reporting criteria. However, they were unusual in that detectable I-131 is seldom seen in environmental samples. The positive I-131 results for these environmental samples were the result of increases in radioactive gaseous effluents due to a fuel defect.
These increases occurred in the weeks prior to a plant shutdown on April 24*,1998 for a Unit I refueling outage. During the outage, the defective fuel was removed and post-outage iodine releases returned to normal. These results were monitored by both CP&L and the State of North Carolina and in subsequent collections, no other anomalies were detected in CP&L samples. No other detectable radioactivity (or radioactivity which did not differ significantly from the corresponding control) was observed in any of the 780 measurements taken at indicator locations in 1998. All samples analyzed met the LLD requirements as established by ODCMS Table 7.3.15-3.
A statistical summary of all the data gathered in 1998 has been compiled in Table 5.
The radiological ew'.ronmental data indicates that BSEP operations in 1998 had no significant impact on the envicovnent or public health and safety. No measurable radiation exposure is 3
attributed to any off-sitt member of the public due to the operations of BSEP.
(V 27
l Comparison of the current data with preoperational (1973,1974) information (Tables 6 and 7) indicate that air particulate filter gross beta activity and ambient gamma radiation levels were i
lower in 1998.
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O FOOTNOTES TO TABLE 5
- 1. Lower limit of detection (LLD) is calculated based on 4.66 standard deviations above background using typical sample sizes and counting times. Due to counting statistics and varying volumes, occasionally lower LLDs are achieved. See Table 8.
2.
Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
- 3. Missing samples are discussed in Missed Samples and Analyses.
- 4. Summary of gamma analysis results in this report does not include the following naturally occurring isotopes since most environmental samples contained some or all of these: Be-7, l
K-40, T1-208, Pb-212, Bi-212, Bi-214, Pb-214, Ra-226, and Ac-228.
- 5. TLD dose is reported in milliroentgen (mR) per 904ay period (quarter) beginning in 1995.
This is the exposure standard used to compare data to the Nuclear Regulatory Commission (NRC).
The LLD was lowered at the request of the plants in order to maintain comparable LLD values with the North Carolina Division of Radiation Protection (NCDRP) and the South Carolina Department of Health and Environmental Control (SCDHEC) laboratories.
- 7. The numbers in parentheses (i.e. Row Surface Water Tritium 3.25E+2(23/24) for LLD]
indicate how many samples that specific value and column apply to in relation to the total number of samples for that column heading.
O 30
I 1
INTERPRETATIONS AND CONCLUSIONS p.
i Air Monitoring -
)
l The average gross beta concentration measured in 257 air particulate (AP) samples collected at 1
-indicator stations during 1998 was 1.83 E-2 picoeuries per cubic meter (pCi/m'). The preoperational (1973-1974) average concentration was 8.2 E-2 pCi/m, while the average 2
activity in the recent past (1993-1997) was 1.72 E-2 pCi/m' (Table 6). The airborne concentrations of gross beta activity in 1998 are indicative of natural background and do not indicate any abnormal activities originating from the nuclear operations at BSEP. Figures 18 through 22 depict the monthly variations of these values.
- Gamma analyses of the composited air particulate filters indicated that all of the radionuclides indicative _ of plant effluents were at concentrations less than their respective LLDs. All radionuclides positively identified by the radionuclide analyses were typical of naturally occurring materials.
Analyses of 257 indicator location air cartridges (AC) for the collection of radioiodines -
indicated that concentrations of those radionuclides, and particularly I-131, were less than the
' LLD, except for AC-201 (0.6 mile NE - PMAC) in late April (4/27) 1998. The I-131 activity detected was 1.10 E-1 pCi/m, which was far below the NRC reporting criteria. However, I
2 this was unusual in that detectable I-131 is seldom seen in environmental samples. The positive I-131 result for this sample was the result of increases in radioactive gaseous effluents j
due to a fuel defect. This increase occurred in the weeks prior to a plant shutdown for a Unit 1 refueling outage. During the outage, the defective fuel was removed and post-outage iodine releases returned to normal.
Milk No milk sampling locations are currently identified in the BSEP environs, and therefore no sampling of this media was available.
Vegetation
. Food crops were not grown in the vicinity of the plant in 1998 and this media was represented 31
F
,gs by indigenous vegetation samples consisting primarily of wild cherry, wax myrtle, and sweetgum leaves. Forty-two samples were collected from indicator locations and fourteen from the control location. In two of three types of broadleaf vegetation samples (wild cherry and wax myrtle) at location BL-800, which is 0.7 mile NE at the Intake Canal, I-131 activity was detected. The I-131 activity reported in the broadleaf vegetation (sampled 5/3/98); BL-800 wild cherry was 7.17 E-2 pCi/g wet and RL-800 wax myrtle was 1.33 E-1 pCi/g wet. No other anomalies were detected in any subsequent co: lections and no detectable activities relating to plant effluents were detected la any other sampling media in 1998.
Fish and Invertebrates l
Fish and invertebrate samples are collected semiannually from two locations: (1) near the Atlantic Ocean discharge pipe at Caswell Beach and (2) a control location in the Atlantic Ocean not influenced by plant operations. In all 12 samples, the radionuclide content was determined to be less than the respective LLDs for the gamma-emitting radionuclides.
Shoreline Sediments O
~
Two shoreline sediments are drawn from the beach area near the pumping station location at Caswell Beach. In both samples, the radionuclide content was determined to be less than the respective LLDs for gamma-emitting radionuclides.
l Surface Water l
Surface water is sampled monthly from the intake and discharge canal. These samples are analyzed for gamma-emitting radionuclides and for tritium. The analyses indicated that no detectable concentrations of radionuclides appeared in the 12 indicator samples. However, one tritium sample collected 2/28/98 (SW-4014.9 miles SSW at the Discharge Canal) was slightly l
above the LLD, with an activity of 336 pCi/ liter where the typical LLD is approximately 325 pCi/ liter. Figure 23 depicts the observed tritium concentrations for 1998.
External Radiation Eimmure The environmental data on external radiation exposure for 1998 was essentially unchanged from 1989-1997 with an average exposure for all indicator locations of 9.7 mR per quarter.
32
The average exposure observed over the preoperational period was 1.02 mR per week
(
observed from the fourth quarter of 1972 through the second quarter of 1975. Table 7 3
provides a comparison of recent data with the preoperational and historical data.
l The highest average exposure occurred at Caswell Beach 4.8 miles SSW. The exposure was 12.1 mR per quarter. Figure 24 depicts average inner and outer ring TLD data for each quarter of 1998. This depiction does not indicate a significant higher exposure rate for the inner versus the outer ring. This is interpreted as demonstrating that no discernible off-site exposure has occurred from plant operations.
l TABLE 6 GROSS BETA AIR PARTICULATE ACTIVITY AVERAGES Gross Beta Activity (pCi/m')
q(d Preoperational Recent Operational Location 1973 1974 1993 1994 1995 1996 1997 1998 AP-200 2.2 E-2 1.4 E-1 1.8 E-2 1.8 E-2 1.8 E-2 1.7 E-2 1.7 E-2 1.8 E-2 AP-201 3.1 E-2 1.4 E-1 1.7 E-2 1.8 E-2 1.9 E-2 1.7 E-2 1.7 E-2 1.9 E-2 AP-202 3.4 E-2 1.4 E-1 1.7 E-2 1.8 E-2 1.8 E-2 1.7 E-2 1.7 E-2 1.8 E-2 AP-203 2.4 E-2 1.3 E-1 1.7 E-2 1.9 E-2 1.9 E-2 1.7 E-2 1.7 E-2 1.9 E-2 AP-204*
2.5 E-2 1.3 E-1 1.7 E-2 1.9 E-2 1.9 E-2 1.8 E-2 1.8 E-2 1.8 E-2 AP-205 1.7 E-2 1.9 E-2 1.8 E-2 1.7 E-2 1.7 E-2 1.8 E-2 1
l
- Control location 1
33
l l
TABLE 7 i (
HISTORICAL TLD RESULTS (1972-1998)
Average Exposure of All TLD Monitoring Locations Year (mR per week) 1972 (4th Qtr.)
0.80 i
1973 1.25 l
1974 0.97 1975 (1st,2nd Qtr) 0.80 1976 0.98 1977 1.32 1978 1.24 1979 0.93 1980 0.90 1981 0.96 1982 1.18 1983 1.21 i
1984 0.98 1985 1.03 C
1986 0.89 1987 0.92 1988 0.86 1989 0.75 1990 0.76 1991 0.76 1992 0.75 1993 0.78 1994 0.77 1995 10.1 (mR per quarter)*
1996 10.1 (mR per quarter) 1997 10.1 (mR per quarter) 1998 9.7 (mR per quarter)
- TLD exposure in mR per quarter beginning in 1995. The equivalent weekly exposure is 0.78 mR.
AV l
l 34 L
i MISSED SAMPLES AND ANALYSES Air Cartridge and Air Particulates No samples were available for:
AC/AP-203, April 6, sampler burned out.
AC/AP-204, April 20, loss of power.
j AC/AP-201, June 15, blown fuse.
AC/AP-201, June 29, blown fuse.
Low AC/AP volumes for:
AC/AP-204, February 23, due to 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> power outage.
AC/AP-200, March 23, blown fuse.
AC/AP-200, March 30, short in air sampler, replaced.
1 AC/AP-201, April 6, blown fuse.
AC/AP-204, April 13, loss of power.
AC/AP-200, May 18, pump failed.
In August (8/98) some air samplers volumes were slightly reduced due to power outages caused by Hurricane Bonnie, but all were acceptable.
GV Thermoluminescent Dosimeters (TLDs)
One, of a possible 180 TLD samples, was missing during 1998 due to the tree being cut down that the TLD was attached to. The missing TLD occurred:
Fourth Quarter - TLD 12 was missing in the field and no data was available.
Note:
TLD points 41 thru 74 are not ODCMS TLD sample points and are not listed. TLD sample points 19 and 80 have been retired.
ANALYTICAL PROCEDURES Gross Beta Gross beta radioactivity measurements are made utilizing a Tennelec Low-Background Alpha / Beta Counting System. The LLD for air particulates is approximately 3.0 E-3 pCi/m.
Air particulate samples are mounted in 2-inch stainless steel planchets and counted directly for 50 minutes.
35
r
)
O I
Q
. Tritium Liquid samples requiring tritium analysis are treated with a small amount of sodium hydroxide and potassium permanganate crystals and then distilled. Five milliliters of the distillate are mixed with thirteen milliliters of liquid scintillation cocktail and counted in a liquid scintillation counter for 500 minutes. The LLD for this count time was approximately 3.25 1
l E+2 pCi/L. This lower LLD was established in June 1996 to compare our tritium LLDs and NCDRP's reportable concentrations, in the Split Sample Program's Annual Report.
Iodine-131 Iodine-131 airborne concentrations are analyzed by the intrinsic germanium (Ge) gamma spectrometry systems. The cartridges are placed on the detector and each charcoal cartridge is
- counted individually for 1,500 seconds with an approximate LLD of 3.0E-2 pCi/m'.
Gamma Spectrometry Gamma spectrum analysis utilizes intrinsic germanium detectors with thin aluminum windows housed in steel and lead shields. The analyzer system is the Canberra Nuclear 9900 Gamma l
Spectroscopy System. Table 8 summarizes LLD values derived from instrument sensitivity based upon a blank sample background.
l Air particulate filter quarterly composites are placed in a Petri dish and analyzed directly for l
7,000 seconds. The count time was increased in 1997 from 3,600 sec. to 7,000 sec. due to l
decreased sample volumes.
Liquid samples are boiled down to reduce the volume, transferred to 1000-ml Marinelli beaker, and analyzed for 10,000 seconds.
I Shoreline sediments are dried, ground, weighed, and then analyzed in a Marinelli beaker for 1,500 seconds.
l Broadleaf vegetation is weighed wet and analyzed in a Marinelli beaker for 7,500 seconds.
l Fish samples and edible portions of invertebrate organisms are cleaned, dressed, and placed in
- a Marinelli beaker for analysis for 1,500 seconds.
i Thermoluminescent Dosimetry Each area monitoring station includes a TLD packet, which is a polyethylene bag containing l
36 1
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.
l-The exposure reported is corrected for exposure received in transit and during storage through the use of control dosimeters.
l Interlaboratory Comparison Program l
l The Radiochemistry Laboratory at the Harris Energy & Environmental Center in New Hill, l
North Carolina, provides radioanalytical services for CP&L's nuclear plant radiological environmental monitoring programs. In fulfillment of ODCMS 7.3.17, the laboratory is a participant in the Analytics, Inc.'s 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 l
Environmental Cross-check Program's termination for utility participation as of December 31, 1995.
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 Activity Percent of Analyses s 1 standard deviation 38 s 2 standard deviation 79 l
s 3 standard deviation 93 l-Four of 61 analyses exceeded the 3 sigma action level; however, three of these four were well within the i 20% ratio to the known 'value. This discrepancy was entered into the Corrective 37
Action Program, reference Condition Report (CR) NGG 99-08644, for evaluation. The L
corrective action (s) to prevent reoccurrence have not been identified, but upon the completion of the action item a supplement to this page will be submitted within 30 days of the CR due date which is currently scheduled for completion on May 27,1999.
Lower Limits of Detection All samples analyzed met the LLD required by ODCMS Table 7.3.15-3. Typical "a priori" LLD values for the samples analyzed are listed in Table 8.
O l
38
1 TABLE 8 p
v TYPICAL LOWER LIMITS OF DETECTION (A PRIORI)
GAMMA SPECTROMETRY Surface Water Samples (Saline Water)
Isotope LLD (pCl/I)
Mn-54 6
CwS8 6
Fe-59 13 Co-60 7
Zn-65 14 Zr-Nb-95 8
Cs-134 8
Cs-137 7
Ba-La-140 9
Other Expected Gamma Emitters 2 to 166 Air Particulates (Quarterly Composite)
Isotope LLD (pCi/m')
l-131 0.048 Cs-134 0.002 Cs-137 0.001
[3}
Other Expected 0.001 to 0.076
'%se Gamma Emitters Shoreline Sediment Isotope LL.D (pCi/kg, dry)
Cs-134 74 Cs-137 47 Other Expected 39 to 1738 Gamma Emitters Fish Isotope LLD (pC1/kg, wet) hin-54 39 Co-58 46 Fe-59 125 Co-60 73 Zn-65 128 Cs-134 63 Cs-137 67 Other Expected 39 to 1535 Gamma Emitters Food Products and Vegetation Isotope LLD (pCi/kg, wet) 1-131 38 Cs-134 37 Cs-137 29 Other Expected 22 to 741 Gamma Emitters 39
f 1
1 LAND-USE CENSUS l
PURPOSE OF THE LAND-USE CENSUS The land-use census identifies the pathways (or routes) that radicactive material may reach the general populations near commercial nuclear gerratin;; aations. This is accomplished by completing studies each year that identify how the surrounding lands are used by the population.
A comprehensive census of the use of the land within a five mile distance of the plant is completed during the growing season each year. This information is used for dose assessment and to identify changes to the stations sampled and the type of samples. These results ensure that the Radiological Environmental Monitoring Program (REMP) is based upon current data regarding human activity in the vicinity of the plant. Therefore the purpose of the land-use census is both to ensure the monitoring program is current as well as provide data for the calculation of estimated radiation exposure.
The pathways that are evaluated are:
+
Ingestion Pathway - Results from eating food crops that may have radioactive materials 7
deposited on them, incorporated radioactive materials from the soil or atmosphere. Another (V
pathway is through drinking milk from local cows or goats if these are present. The grass used to feed these animals may have incorporated or had deposited on it radioactive materials that can be transferred to the milk,
+
Direct Radiation Exposure Pathway-Results from deposition of radioactive materials on the ground or from passage of these radioactive materials in the air.
+
Inhalation Pathway-Results from breathing radioactive materials transported in the air.
Methodology The following must be identified within the five (5) mile radius of the plant for each of the sixteen meteorological sectors (compass direction the winds may blow, for example NNE [ North North East]):
+
The nearest resident
+
The nearest garden of greater that 500 square feet, producing broadleaf vegetables
+
The nearest milk animal The primary method is visual inspection from roadside within the five (5) mile radius, with the exception of the Sunny Point Military Ocean Terminal. This information is supplemented with data from aerial photographs, information from county extension agents, and farm supply businesses.
40
i 1998 Land-Use Census Results The 1997 and 1998 results of the survey for the nearest resident, garden, milk and meat animals in each sector are compared in Table 9.
The r'esident portion of the census conducted in June of 1998 identified changes in the distances of the nearest resident from plant center in 3 sectors. The garden portion of the census identified changes in the distances of the nearest garden in an additional 3 sectors. The ODCM was updated to reflect these new locations.
l The resident and garden distance changes occurred within the base distance areas that have i
been previously evaluated in the ODCM. With the exception of the resident change in the NNE l
sector (0.9 miles to 0.8) miles, the remaining location changes were more conservative. Each l change was evaluated against the criteria in ODCMS 7.3.16. The results conclude that the changes have a calculated dose less than the values calculated by ODCMS TR 7.3.9.1 and are s 120% from the current sample locations identified in ODCMS Table 7.3.15-1. The evaluations were performed using 1998 annual source term.
Results of the 1998 Land Use and Garden Census indicate stable use of land indicate that current control locations are appropriate and no changes are needed for dose assessment and 1
environmental motoring.
I l O l
l 41
TABLE 9 LAND-USE CENSUS COMPARISONS (1997-1998) i NEAREST PATHWAY (MILES)
SECTOR RESIDENT GARDEN MILK / MEAT ANIMALS 1997 1998 1997 1998 1997 1998 N
0.9 0.9 0.9 None None None I
NNE 0.9 0.8 1.2 1.2 None None NE None None None None None None ENE None None None None None None E
None None None None None None ESE 1.5 1.5 1.5 1.5 None None SE 0.9 0.9 None None None None SSE 0.9 1.0 None None None None 1
S 1.5 1.5 1.5 1.5 None None l
SSW l.2 1.2 1.5 1.5 None None SW l.0 1.0 1.0 1.0 None None l
WSW l.0 1.2 1.2 1.2 None None W
0.8 0.8 0.8 1.2 None None WNW 0.8 0.8 0.9 1.1 None None NW 0.9 0.9 1.0 1.0 None None 1
NNW 0.8 0.8 4.4 4.4 None None l3 l U l
l l
l l
42
E 1
l REFERENCES rq i
\\,
" 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 l
Federal Regulations, Washington, D.C.
j l
Eisenbud, M., " Environmental Radioactivity," Academic Press, Inc. Orlando FL. (1987) i
" Environmental Radiation Protection Standard for Nuclear Power Operations," Title 40, l
Part 190, Code of Federal Regulations, Washington, D.C.
i Evans, R.,"The Atomic Nucleus," McGraw-Hill, New York, N.Y. (1967)
" Exposure of the Population in the United States and Canada from Natural Background Radiation," Report No. 94, National Council on Radiation Protection and Measurements,
(~'}
Washington, D.C. (December 1987)
]
U l
Grosh, D. and Hopwood, L.," Biological Effects of Radiations," Academic Press Inc., New l
York, N.Y. (1979)
" Health Effects of Exposure to Low Levels of Ionizing Radiation: BEIR V," Committee on the Biological Effects of Ionizing Radiations, Board on Radiation Effects Reasearch Comission of Life Sciences, National Reasearch Council, National Acadeny Press, Washington D.C. (1990)
" Ionizing Radiation Exposure of the Population of the United States," Report No. 93, National Council on Radiation Protection and Measurements, Washington, D.C. (Septemeber 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 (3)
York, N.Y. (1988) 43
" Standard for Protection Against Radiation," Tile 10, Part 20. Code of Federal Regulations, Washington, D.C.
"The Effects on Populations of Exposure to Low Levels of Ionizing Radiation: 1980,"
l Committee on the Biological Effects of Ionizing Radiations, Division of Medical Sciences, Assembly of Life Sciences, National Research Council, National Academy Press, Washington, l
D.C.(1980)
" Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1979) l l
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