ML20138H492

Radiological Environ Operating Rept 1996, as Vol I.Volumes II & III Are Sample Analysis Data for Jan-June 1996 & Jul- Dec 1996

ML20138H492
Person / Time
Site:	Brunswick
Issue date:	12/31/1996
From:	Langdon S, Payton W CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20138G490	List: BSEP-97-0151, Forwards Radiological Environ Operating Rept 1996, Listed as Vol I.Volumes II & III Are Sample Analysis Data for Jan- June 1996 & Jul-Dec 1996 ML20138H492
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!O RADIOLOGICAL ENVIRONMENTAL OPERATING 3

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BRUNSWICK NUCLEAR PLANT CAROLINA POWER & LIGHT 4

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SilEARON IIARRIS ENERGY & ENVIRONMENTAL CENTER b)

Carolina Power & Light Company New IIlli, North Carolina RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR BRUNSWICK STEAM ELECTRIC PLANT JANUARY 1 TIIROUGli DECEMBER 31,1996

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Prepared by:

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Reviewed by:

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o TABLE OF CONTENTS V

Title P_ age a

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List of Figures li i

List of Tables 111 l

Executive Summary 1

Introduction to Nuclear Operations 2

1 Benefits of Nuclear Power 2

Radiation and Radioactivity 3

Radiation Interaction with hiatter 6

Radiation Quantities and Units of hieasure 7

Sources of Radiation 8

IIealth Effects of Radiation 10 General Health Ris!

11 Nuclear Power Plant Operation 12 Plants Systems 14

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Reactor Safety 18 Radiological Environmental hionitoring Program 19 Purpose and Requirements for the Radiological hionitoring Program 19 General Site Description 20 Radiological hionitoring Program Quality Assurance 21 Radiological hionitoring Program General Description 22 Summary of Radiological hionitoring Program 27 Interpretations and Conclusions 30 h11ssed Samples and Analyses 34 Analytical Procedures 34 Land Use Census Purpose of the Land-Use Census 39 hiethodology 39 1996 Land Use Census Results 40 References 42 i

4 ic LIST OF FIGURES i

Figure Page 1

CP&L Service Area 2

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1996 Energy Sources 2

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3 The Atom 3

4 Radioactive Decay 5

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Ionization 6

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Radiation Ranges & Shielding 6

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Source of Radiation Dose (BIER V) 9 8

Man Made Radiation (BIER V) 9 i

9 Nuclear Fission 12 to Nuclear Fuel Cycle 13 i

l 11 Fuel Pellets, Rods & Assemblies 13 12 Major Plant Systems for the Boiling Water Reactor 14 13 Reactor Vessel 15 l

14 Primary Containment Structure 16 15 Location of Brunswick Plant 20 l

16 Radiological Sampling Locadons (Distant from Plant) 23 j

17 Radiological Sampling Locations (Nearest Plant) 24 18 Plot of Air Particulate Gross Beta Activity (Location 200) 44 19 Plot of Air Particulate Gross Beta Activity (Location 201) 45 20 Plot of Air Particulate Gross Beta Activity (Location 202) 46 21 Plot of Air Particulate Gross Beta Activity (Locdon 203) 47 22 Plot of Air Particulate Gross Beta Activity (Location 205) 48 23 Plot of Surface Water Tritium Activity (Location 401) 49 4

24 Plot of TLD Averages for Inner and Outer Rings 50 i

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LIST OF TABLES O

Table Page l

1 Quality Factors for Various Radiations 8

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Reduction in Average Life Expectancy 11 j

3 hiedia Used to Assess Exposure Pathways to hian 22 4

Radiological hionitoring Sampling Locations 25 l

5 Radiological Environmental hionitoring Program Data Summary 28 6

Gross Beta Air Particulate Activity Averages 32 l

7 Illstorical TLD Results (1972-1996) 33 8

Typical Lower Limits of Detection (a priori) Gamma Spectrometry 37 q

9 Land-Use Census Comparisons (1995-1996) Nearest Pathway (miles) 41 i

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o EXECUTIVE

SUMMARY

NJ The Brunswick 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, Brunswick Nuclear Plant Technical Specifications, and the Brunswick 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 1,1996 through December 31, 1996.

The Radiological Monitoring program was established in 1973. Radiation and radioactivity in various environmental media have been monitored for more than 24 years, including more than a year prior to commencing operaion. Monitoring is also provided for controllocations which would not be impacted by operations of the Brunswick Nuclear Plant.

Using these control locations and data collected prior to operation allows comparison of data collected at locations near the Brunswick Nuclear Plant which could potentially be impacted by its operations.

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

Monitoring results for environmental media are summarized as follows:

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.

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Milk was unavailable due to no milk animals (goat or cow) currently identified within the environs of the plant; therefore, no exposure pathway exists.

Terrestrial vegetation includes broadleaf vegetation. Results indicate no detectable activities were detected in this sampling media.

Aquatic organism monitoring includes fish and benthic organisms (organisms that live on the bottom of the ocean).

Surface water results indicate no detectable activity.

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

The continued operation of the Brunswick 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.

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O INTRODUCTION TO NUCLEAR OPERATIONS Carolina Power & Light Company (CP&L) operates an integrated electrical system serving more than one million d, y.yp customers in North Carolina and South Carolina. A system mmh map is provided (Figure #1) that illustrates the area served W

and the location of the nuclear generating units including the Harris (Blue), Brunswick (Green), and Robinson j

(Brown) Nuclear Plants. The service area is more than 30,(XX) square miles and has a population of more than 3,5(X),(XX)

Figure 1: CP&L SERVICE AREA people, The energy sources for electrical generation include I ""*' l '

coal, fuel oil, natural gas, hydro-power, and nuclear fuel. No one energy source is best. Each fuel source has merits and disadvantages. Fossil fuels pose issues associated with clean air including emissions of sulfur dioxide and oxides of nitrogen. Both natural gas and hydro-power are in limited supply.

Nuclear energy is a vital component in a diversified energy mix. In 1996 nuclear energy supplied 38% of Nuclear CP&L's total electrical generation. This nuclear Coal component was generated from four units including the Brunswick Nuclear Plant. The remaining energy Oil & Natural Gas sources were primarily from coal-fired generation, Hydro Power and a very small contribution from oil, natural gas, Figure 2: 1996 ENERGY SOURCES and hydro-power.

BENEFITS OF NUCLEAR POWER Nuclear energy is a viable, clean, safe, and readily available source of energy. The operation of the Brunswick 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 l

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l f3 Nuclear energy has the following advantages over other fuel sources:

b The fuel is uranium which is relatively inexnensive when compared with the fuels of coal, o

natural gas, and fuel oil.

Emissions from nuclear stations do act 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 strearns 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.

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

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

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and still retain its identity as that element. An atom is made up of a number of different particles. These

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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.

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

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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

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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 its name (or the name) followed by the total number of protons and neutrons; for example H-3 or hydrogen-3 describing an atom with one proton and two neutrons.

Radiation Radiation is defined as the conveyance of energy through space. This conveyance may occur in the form of particles, waves, or photons. Some common forms of radiation are sunlight, microwaves or radio waves. These are all examples of non-ionizing radiation. Ionizing radiation differs in its interaction with matter because its energy is capable of removing an

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clectron from the outer part of an atom resulting in the remaining atom being positively charged and a free electron. There are two types ofionizing radiation-first particulate radiation and electromagnetic radiation. Particulate radiations are energetic particles which will travelin 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 emis.sion 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 scrics 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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_gr 40, C(carbon)-14, H(hydrogen)-3 are significant j

contributors to background radiation levels, which are addressed in greater detail later.

The rate at which atoms undergo radioactive decay xF varies greatly. A common expression of the 31/2 tendency for radioactive decay is the half-life 4

associated with a particular isotope. The half-life is 1/4 the amount of time required for one-half of the

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number of atoms for an isotope to experience jjg 1/16 radioactive decay. The longer the half-life the less

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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

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' Figurc 4 illustrates an isotope with a 140-day half-life. Note that the activity decreases by half in j

' 140 days, and then by l'alf again the next 140 days and thereafter.

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n RADIATION INTERACTION WITH MATTER v

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 g

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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 thr,n a 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 i

O paiticle is the slowest of the radiations we will review U

with a speed of no more than 20,(XX) 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 particic, 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,(XX) 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.

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p" RADIATION QUALITIES AND UNITS OF MEASURE There are numerous qualities and units used to describe radiation and radioactivity and their l

cffects. 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

.(XXXXXXXXXX)1 1x 10-i2 4

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.(XXXXXXX)1 1x10 micro

.(XXXX)1 1 x 10-6 milli

.001 1x104 centi

.01 1x 10-2 kilo 1,(XX).

1x10' mega 1,(XX),(XX).

lx1(f 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 b

37,(XX),(X)0,(XX) disintegrations per second; (also expressed as 3.7x10"'s-'). 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 crgs (a measure of a very small amount of energy) ner gram. The rad can be used with all types of radiation including X-rays, gamma-rays, and paniculate radiations. The absorbed dose can be measured with various radiation-detection instruments which allows the assessment of damage to biological systems subjected to radiation and radioactive materials.

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

Dose equivalent = absorbed dose X anality factor Some types of radiation create more biolegical damage due to the extent of ionization in small j

areas. From our discussion of alpha particles, the intense ionizations caused by the alpha particle i

results in a much higher Quality Factor for this radiation. This relationship for quality factors and different radiations we have discussed is illustrated below 7

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V Quality Factors for Various Radiations Radiation Quality Factor Gamma-rays I

l X-rays 1

Beta Particles 1

Alpha Particles 20 SOURCES OF RADIATION Background Radiation Radiation occurs naturally and is an everyday fact of our existence. Mankind has always lived with radiation and radioactive materials and will continue to in the future. The radiation that occurs naturally is referred to as background radiation. Mankind experiences two types of radiation dose: first is radiation that originates outside the body and is called external radiation, (O

and the second is radiation that originates inside the body and is called internal radiation.

t External radiation comes from the carth, 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 carth 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 4,,,,

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.

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 Radon E Terrestrial contributors is radon. Radon is a radioactive gas that cosmic internal is part of the uranium decay series. Radon's J.

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concentration varies greatly based upon the geology of 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 j

dose from radon can be increased significantly. Normally radon does not pose a significant health 1

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 l

health effect of breathing radon is an increased risk oflung cancer.

Man made radiations are important to i O Man-made Rad. tion radiation. An important aspect in discussing completing our understanding of sources of ia man-made radiation is the benefit man derives from the use of these. Medical uses of y,

radiation are the major contributor, including

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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.

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Fallout from prior weapons testing is now a Nuclear Mediome small Contributor to total radiation dose.

Occupational exposure is also a factor from the medical, manufacturing, and nuclear mdustries. Finally, contributions from nuclear plant operations represent less that 1% of the 0 xan.

5 Nuclear Modeme man-madC radiations for the average member E consum.r er.ouci.

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of the general public. The data presented in 3 owup.t.

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Figure 8: Man Made Radiation Sources (BIER V) different sources of man-made radiation for j

the average member of the public.

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q HEALTH EFFECTS OF RADIATION D

The effects ofionizing radiation has been of concern to the scientific community for several 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 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 extremely low doses compared with medical and occupational levels. Experiments with animals represent additional challenges because they may not accurately represent human biological responses to radiation.

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 decedents of the individual receiving the radiation dose.

Somatic effects can be classified as acute or chronic. Acute effects occur within a short time (days) after the dose is received. Generally acute effects require very high doses. Blood changes have been observed in the range of 25 to 50 rem ( or 50,(XX) 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 a long period of time and these have also been referred to as delayed effects. The effects are also generally associated with 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 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 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 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 10

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l sometimes necessary in the creation of chemical bonds. If the bonds are part of the genetic material of the cell, it could result in changed genetic material ( mutations). Radiation is just ore l

of several agents that contribute to genetic change. Chemicals including those that occur i

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 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.

i GENERAL HEALTH RISK i

Every human activity has risk associated with it. The air we breath, the food we cat, 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 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, carbor. monoxide in the operation of some furnaces and our vehicles due to our familiarity witn these.

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

I Below you will fm' d a table of common activities and the associated reduction in life expectancy Table 2 i

REDUCTION IN AVERAGE LIFE EXPECTANCY ACTIVITY REDUCTION IN LIFE EXPECTANCY l

- CIGARETTE SMOKING 2 PACKS / DAY 10 YEARS CIGARETTE SMOKING 1 PACK / DAY 7 YEARS HEART DISEASE 5.8 YEARS 1

LIVING IN CITY VERSUS RURAL 5 YEARS

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OVERWEIGHT 30 %

3.6 YEARS CANCER 2.7 YEARS COMMERCIAL NUCLEAR POWER 12 MINUTES t

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NUCLEAR POWER PLANT OPERATIONS The primary difference between a nuclear generating station and fossil generating station is the source of heat or thermal energy. The steam turbine, condenser, condensate and feed water systems are much the same. The uranium fuel within the nuclear reactor is the source of heat or energy in the nuclear generating station.

l Nuclear Fission l

l 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 l

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 a U-235 is known to undergo fission. The other more common isotope of Uranium known as U-238 does not fission so easily.

Fission can also be stimulated by neutrons interacting with the nucleus of these atoms. Simply stated a neutron reaches the nucleus and produces fission fragments, free neutrons, and heat.

l 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 i

going or cause more and more fissions to occur. When the rate of fission initiated is self l

sustaining or increasing a chain reaction has been established. It is this sustained chain reaction and the energy produced that produces the heat needed to generate steam for electrical generation.

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1 Figure 9: Nuclear Fission

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i Uranium Fuel 4 o Uranium is mined from the carth the same as many minerals are as an ore. This uramum 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 " anium 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 gaseous diffusion. The reason for NUCLEAR FUEL CYCLE separation is to allow more of the U-A 235 to be included in the fuels used in h

commercial reactors. We have already J

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discussed that U-235 fissions more R

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readily that U-238. This process that m s. '

increases the amount of U-235 is also i

MINE MILL CONVERTER referred to as enrichment. After enrichment this gas is chemically converted to uranium dioxide (in g,

chemical notation UO ). At this point s

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the uranium dioxide is a gray powder.

The next process takes this powder RIACTOR FUIL FABRICATOR ENRICHIR and under high pressure, and (CASEQUIDiffV!4HLANT)temperature creates a ceramic pellet of n

uranium dioxide. This process is part

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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 mm added is referred to as the percent enrichment which for F

(p) jl It commercial reactors is about 6% of the total uranium in the fuel. These fuel pellets are placed into long tubes of l

zi tonium alloy or fuel rods. These rods of uranium fuel l

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are then placed with other such fuel rods into a fuel b

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i shipped to the nuclear power plant. It is important to note

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that the entire process of making nuclear fuel is carefully

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ROD ASSEMBLY Figure 11: Fuel Pellets, Rods &

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reactor buildmg Oy

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The fuel, fuel rods, and the reactor vessel have already been discussed. The primary

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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 f)'\\

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16 Figure 11:

j

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 leakage would be into the secondary containment from the outside. The air coming from secondary containment is all filtered and treated prior to discharge.

O 1

O n

g REACTOR SAFETY m

There are several points regarding nuclear safety that are important to understand and these are:

+

Commercial nuclear generating station can not 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 contigured 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 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 referred to a the Emergency Core Cooling System. There are even backup systems to N

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

18

' o RADIOLOGICAL ENVIRONMENTAL U

MONITORING PROGRAM PURPOSE AND REQUIREMENTS FOR THE RADIOLOGICAL MONITORING PROGRAM Although the operation of a nuclear generating station results in the raising of background ladiation 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 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:

/^T e

Technical Specifications e

Off-Site Dose Calculation Manual (ODCM) various procedures e

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

e NRC Regulatory Guide 1.109 NRC Regulatory Guide 4.13 NRC Regulatory Guide 4.15 l

I IU 19

\\

l(J' General Site Description

~~

The Brunswick Nuclear Plant consists v-- ) )(+i p r-A b, t (N

~ ~~* M y

of two (2) boiling water reactors with a l

design rating of 821 MWe (Mega Watts

{=,,,,~,,

"" %[b clectric) each. Commercial production i

v

\\

,_%4#pfD'~c.,,h'~..

a; _ I

• l was initiated by Unit Two on November d~

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3,1975 and by Unit One on March 18, p

.~ C h /-

~

1977. The Brunswick Nuclear Plant is f"**,",",,,,,,

4 I

""]

located in Brunswick County, North

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, - c~.

Carolina. The site is along state route t)M 6 go % ", p a- = = =

w 133 approximately two and a half (2.5) hMy hg\\

T miles north of Southport and is 7%

%c--

displayed on the map of southeastern

),

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'-l'.,,,Q~~k"g%

@E" Waa\\'~ "

.','L North Carolina (Figure 15). The m,@l:T ~,"

' "yff.j,,J community of Boiling Springs is about

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fQ',,

three (3) miles northwest cf the site.

The towns of Caswell Beach, Yaupon

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M '-

Beach, and Long Beach are on a barrier

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island south of the plant. The site is also Figure 15: Location of Brunswick Plant approximately sixteen (16) miles south g ~s 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 thiny (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, agricultural, and government contributions. There is well developed recreational use of the barrier islands south and east of the site. Fishing and boating are popular activities. Commercial fishing is also an important industry in the community. Agricuhure utilizes less than half ofland within 50 miles of the site.

Agricuhural 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 channelis just east of the site in the Cape Fear River. Also the Sunny Point i

Military Ocean Terminal is located approximately four and one half (4.5) miles north of the plant i

site and on the Cape Fear River.

I J

20

' o RADIOLOGICAL MONITORING PROGRAM V

l QUALITY ASSURANCE A required component of the environmental radiological monitoring program is the Quality Assurance Program. The standards for the quality assurance program are established in the NRC Regulatory Guide 4.15," Quality Assurance for Radiological Monitoring Programs." The purpose of the quality assurance program is "(1) to identify deficiencies in the sampling and measurement processes to those responsible for these operations so that corrective action can be taken, and (2) to obtain some measure of confidence in the results of the monitoring programs in order to assure the regulatory agencies and the public that the results are valid." NRC Regulatory Guide 4.15, 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 oflaboratory 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 ensure consistent quality results on an ongoing basis.

v O.

L]

21 l

l llp RADIOLOGICAL MONITORING PROGRAM V

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 cach pathway. Below in Table 3 is a list of the media used to assess each of these pathways.

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

Shoreline Sediment Ingestion Broadleaf Vegetation Fish and Invertebrates AV 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 oflocations are selected as controls. Control stations j

are selected because they are very unlikely to be affected by operation of the plant. Sample i

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

J l

22

4 Radiological Sampling Locations r _ a,{

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k* 404-e.a-ne',,',

f3 mm.mm5,W NOT SHOWN

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,u ma Figure 16: Radiological Sampling Locations (Distant from Plant) (Scale 1 inch = 3.08 nnies)

Thermoluninescent dosimeter locations are displayed in bbek, 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 SpeciEed in the Atlantic Ocean)(Control Fish Station) 802 (Location not specified) (Control Vegetation)

O 23

i Radiological Sampling Locations O

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d Figure 17: Radiological Sampling Losions (Nearest Plant) (Scale 1 inch =.8 miles)

Thermoluninescent 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 (Imcation not specified) (Control Vegetation) i v

24 1

Table 4 Brunswick Nuclear Plant Radiological Monitoring Sampling locations Sample Type Location & Description Frequency Sample Size Analysis Air 200-1.0 mile SW Visitors Center Weekly 10,000 ft' Iodine a idge 201--0.6 mile NE PMAC (300 m')

202--l.0 mile S substadon--construction rd.

203-2.3 miles SSW Southport substadon 204--23 miles NNE Sutton Plant

• 205--0.6 mile SSE Spoil Pond Air 200-1.0 mile SW Visitors Center Weekly 10,000 ft' Gross Beta 201-0.6 mile NE PMAC (300 m')

(Weekly)

Pa culate (g )

202-1.0 mile S substadon-construction rd.

${a,te i

203-2.3 miles SSW Southport substation (Quarterly) 204-23 miles NNE Sutton Plant

• 205-0.6 mile SSE Spoil Pond 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 0:can @

discharge (bottom-feeders) 702-5.5 miles SSW Atlantic Ocean @

discharge (invertebrates) 703--Atlantic Ocean; location not specified* (free-swimmers) 704-Atlantic Ocean; location not specified* (bottom-feeders) 705-Atlantic Ocean; location not specified* (invertebrates Broadleaf 800-0.7 mile NE intake canal Monthly 500 rams V

tation (wet (B[)

801-0.6 mile SW discharge canal (As,lable) avai 802-10 miles; location not specified*

803--0.6 mile SSE Spoil Pond

' Shoreline 500--4.9 miles SSW; beach near OD Semiannual 500 grams Gamma Sediment pumps (SS)

Surface 400-0.7 mile NE intake canal

• Monthly 4 liters Gamma Water (SW) 401--4.9 miles SSW discharge canal @OD composite Tridum pumps

[

• ConuW Stations

~

25

Table 4 (Continued)

Hrunswkk Nuclear liant

(

Radiological Monitoring Sampling lecathms Sample Type location & Description Fre<pwncy Sample Sz Analysis l

'Dicrmoluminescent i 1.1 miles E Moore St. extension Quarterly Not TLD l

Dosimetry (TLD) 2 1.0 mile ESE Moore St. ext.

Applicable Reading 3 0.9 nnte SE Moore St. extension 4 1.1 miles SSE Moore St. cxt.

l 5 1.1 nules S Leonard St.

l 6 1.0 mile SSW pine tree on BEMCO r.o.w.

7 1.0 mile SW Hwy 87 at r.o.w.

8 1.2 miles W liwy 87 9 1.0 mile WNW Bethel Church 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.

t 14 0.5 mile NE intake canal i

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 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 miles 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 Head 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 Bapt. Assy.

76 4.8 miles SSW at Caswell Beach 77 5.3 miles S at Bald Head Island l

78 10.0 miles NNE Hwy.133 at SR 1521 l

79 9.5 miles N SR 1539 at SR 1521 l

81 10.0 miles WNW Midway Rd. at SR 1508*

I l

' Control Stations 26 i

SUMMARY

OF RADIOLOGICAL MONITORING PROGRAM

( )/

This report presents the results of the Radiological Environmental Monitoring Piogram conducted during 1996 for the Brunswick Nuclear Plant (BNP). The program was conductec,in accordance with Technical Specification 4.12.1, the Off-site Dose Calculation Manual. and aoplicable procedures.

The 1996 Annual Radiological Environmental Operating Report (REOR) has been prepared in accordance with Technical Specification 6.9.1.7 and is being submitted in accordance with Technical Specification 6.9.1.6. The report applies to both BNP Units 1 and 2 (License Nos. DPR-071 and DPR-062, respectively).

Nearly 1,025 samples from six environmental media types were analyzed during the year. No detectable radioactivity (or radioactivity which did not differ significantly from the corresponding control) was observed in any of the 850 measurements taken at indicator locations. All samples analyzed met the LLD requirements as established by Technical Specification 6.9.1.7.h and Table 4.12.1-1.

D (O

A statistical summary of all the data gathered in 1996 has been compiled in Table 5.

The radiological environmental data indicates that BNP operations in 1996 had no significant impact on the environment or public health and safety. No measurable radiation exporare is attributed to any off-site member of the public due to the operations of BNP.

1 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 lower in 1996.

O v

27 l

l

O

(

TABLE 5 BRUNSWICK NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

Bmnswick Steam Electric Plant Docket Numbers 324 and 325 Bmnswick County, North Carolina Calendar Year 1996

' Imcatism w/Himiwat Annemi Mean Type and AE ladicator Medhne er Pathway

. Total No. of

. ImwerIJamit Imcations'* -

Centrol Locatises Sampiad er Messered Measuremments of Detecties Mene Neune, Distance.

Mean Meme -

(Unit of Meansaremment)

Perfenmed (LIB f" Ranae med Directime Ramer'*

Ramer'8 Air Cartndge 1-131 3.0E-2 AB E-ss than 11D AH less than llD AH less than LIB (pCi/m')

3IR Air Particulate Gross Beta 3.0E-3 1.72E-2 (265/265)

Visitors Center 1.74E-2 (53/53) 1.78E-2 (53/53)

(pCiW) 31R 6 74E 1 - 312E-2 10 mile SW R 47E 312E-2 R 94E 2 ME-2 Gamma'*

See Table 8 All less than 11D All less than IlD All less than 11D 24 Broadleaf Vegetation Gamma'*

(pCi/g, wet) 124 See Table 8 All less than 11D AH less than 11D All less than llD Fish and Imrrtebrates Gamma'*

See Table 8 Allless than llD Allless than 11D AH less than 11D l

1. pCi/g. wer) 12 Sediments-Shoreline Gamma'"

See Table 8 Allless than 11D Allless than llD No control (pCirg. dry) 2 Surface Water Gamma'*

See Table 8 All less than 11D All less than 11D All less than 11D (pCi/1) 24 Tritium 3.25E+2(1W24f"+

AH less than LU)

AH less than 11D All less than llD 24 I OE+NI4/24 r" TLD TU) Readout

!.01E+I (175/175)

Fort Caswell I 20E+1 (4/4) 1.14E+1 (4/4)

(mR per quartery

179 "

7.70E+0 - 1.54E+ 1 Baptist Assembly 1.05E+ 1 - 1.54E+ 1 1.00E+1 - 1.35E+1 4 5 mib S 28

1 I

l FOOTNOTES TO TABLE 5 lO t

l 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.

I 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 ve discussed in Missed Samples and Analyses.

4.

Summary of gamma analysis results in this report does not include l'ac following naturally occurring isotopes since most environmental samples contained some or all of these: Be-7, K-40, TI-208, Pb-212, Bi-212, Bi-214, Pb-214, Ra-226, Ac-228, and Th-234.

5.

TLD dose 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 1.0 E+3 pCi/L for five out of twelve months in 1996 (January-May); however, the LLD was lowered to 3.25 E+2 pCi/L in June 1996 (seven out of twelve months). The LLD was lowered at the request of the plants in order to maintain comparable LLD values with the state (N.C. and S.C.) Agencies' laboratories.

i l

lO i

29 i

i INTERPRETATIONS AND CONCLUSIONS i

I i

Air Monitorine l

l

. The average gross beta concentration measured in 265 air particulate samples collected at indicator stations during 1996 was 1.72 E-2 picoeuries per cubic meter (pCi/m'). The preoperational (1973-t 1974) average concentration was 8.2 E-2 pCi/m', while the average activity in the recent past (1992-1995) was 1.73 E-2 pCi/m'(Table 6). The airbome concentrations of gross beta activity in 1996 are indicative of natural background and do not indicate any abnormal activities originating from the I

nuclear olerations at the Brunswick Nuclear Plant (BNP). 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 265 indicator location air cartridges for the collection of radiciodines indicated that concentrations of those radionuclides, and particularly I-131, were less than the LLD.

O No milk sampling locations are currently identified in the BNP environs, and therefore no sampling of this media was available.

Veeetation l

Food crops were not grown in the vicinity of the plant in 1996 and this media was represented by l

mdigenous vegetation samples consisting primarily of wild cherry, wax myrtle, and sweetgum leaves along with fescue grass. Ninety-three samples were collected from indicator locations and 31 from the control location. No detectable activities relating to plant effluents were detected in this sampling media.

Fish and Invertebrates i

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.

30

Shoreline Sediments A

Two shoreline sediments are drawn from the beach area near the pumping station location at Caswell Beach. No detectable activities relating to plant effluents were detected in this sampling media.

Surface Water i

Surface water is sampled monthly from the intake and discharge canal. These samples are analyzed for gamma-emitting radionuclides and for tritium. Neither of these analyses indicated any detectable concentrations of radionuclides in the 12 indicator samples. Figure 23 depicts the observed tritium concentrations for 1996.

External Radiation Exposure The environmental data on external radiation exposure for 1996 was essentially unchanged from 1989-1995 with an average exposure for all indicator locations of 0.78 mR per week or 10.1 mR per quarter. 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 provides a j

comparison of recent data with the preoperational and historical data.

l The highest average exposure occurred at Fort Caswell Baptist Assembly 4.5 miles S. That dose was 12.0 mR per quarter. Figure 24 depicts average inner and outer ring TLD data for each quarter of 1996. This depiction does not indicate a signific ant higher exposure rate for the inner versus the outer ring. This is interpreted as demonstrating that no discernible off-site exposure arises from plant operations.

l O

31

TABLE 6 GROSS HETA AIR PARTICULATE ACTIVITY AVERAGES O

Gross Heta Activity (pCi/m')

Preoperational Recent Operational Location 1973 1974 1992 1993 1994 1995 1996 AP-2(X) 2.2 E-2 1.4 E-1 1.7 E-2 1.8 E-2 1.8 E-2 1.8 E-2 1.7 E-2 AP-201 3.1 E-2 1.4 E-1 1.6 E-2 1.7 E-2 1.8 E-2 1.9 E-2 1.7 E-2 AP-202 3.4 E-2 1.4 E-1 1.4 E-2 1.7 E-2 1.8 E-2 1.8 E-2 1.7 E-2 AP-203 2.4 E-2 1.3 E-1 1.3 E-2 1.7 E-2 1.9 E-2 1.9 E-2 1.7 E-2 AP-2(M*

2.5 E-2 1.3 E-1 1.6 E-2 1.7 E-2 1.9 E-2 1.9 E-2 1.8 E-2 AP-205 1.5 E-2 1.7 E-2 1.9 E-2 1 8 E-2 1.7 E-2

• Control location O

O 32

. - ~ _ _.

1 l

TABLE 7 l

HISTORICAL TLD RESULTS (1972-1996) l 1

lO i

Average Exposure of All TLD Monitoring Locations Year (mR per week) 1972 (4th Qtr.)

0.80 1973 1.25 1974 0.97 1975 (1st,2nd Qtr) 0.80 1976 0.98 1977 1.32 l

1978 1.24 1979 0.93 1980 0.90 L

1981 0.96 1

1982 1.18 i

l 1983 1.21 1984 0.98 1985 1.03 1986 0.89 1987 0.92 1988 0.86 l

1989 0.75 l

1 1990 0.76 1991 0.76 1992 0.75 1993 0.78 i

l I

1994 0.77 1995 10.1 (mR per quarter)*

1996 10.1 (mR per quarter)

• TLD exposure in mR per quarter beginning in 1995. The equivalent weekly exposure is 0.78 mR.

f 33 1

1 1

MISSED SAMPLES AND ANALYSES OO I

Thermoluminescent Dosimeters (TLDs)

Five of a possible 184 TLD samples were missing during 1996 due to vandalism. They were:

First Quarter

- TLD 72 was missing in the field.

Second Quarter

- TLD 72 was missing in the field.

Third Quarter

- TLDs 72 and 76 were missing in the field Fourth Quarter

- TLD 76 was missing in the field.

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'.

i Air particulate samples are mounted in 2-inch stainless steel planchets and counted directly for i

50 minutes.

Tritium Liquid samples requiring tritium analysis are treated with a small amount of sodium hydroxide and potassium permanganate crystals and then distilled. Five milliliters of the distillate are mixed with thirteen milliliters of liquid scintillation cocktail and counted in a liquid scintillation counter for 50 minutes. The LLD for this count time was approximately 1000 pCi/L through May 1996.

During June 1996, the sample count time was increased to 500 minutes with a LLD of approximately 325 pCi/L. This increase was established to compare our tritium LLDs and results with State Agency's reportable concentrations, in the Split Sample Program's Annual Report, as per plants' request.

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 with an approximate LLD of 3.0E-2 pCi/m'.

j Gamma Spectrometry

/

Gamma spectrum analysis utilizes intrinsic germanium detectors with thin aluminum windows l-housed in steel and lead shields. The analyzer system is the Canberra Nuclear 9900 Gamma 34

l',m Spectroscopy System. Table 8 summarizes LLD values derived from instrument sensitivity based

(]

upon a blank sample background.

Air particulate filter quarterly composites are placed in a Petri dish and analyzed directly for 3,600 seconds.

Liquid samples are boiled down to reduce the volume, transferred to 1000-ml Marinelli beaker, and analyzed for 10,000 seconds.

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

Broadleaf vegetation is weighed wet and analyzed in a Marinelli beaker for 7,500 seconds.

Fish samples and edible portions of intervebrate organisms are cleaned, dressed, and placed in a Marinelli beaker for analysis for 1,500 seconds.

Thermoluminescent Dosimetry Each area monitoring station includes a TLD packet, which is a polyethylene bag containing three calcium sulfate phosphors contained in a Panasonic UD-814 badge. The TLD is lighttight and the fs(j 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.

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

Interlaboratory Comparison Program The Radiochemistry Laboratory at the llarris Energy & Environmental Center in New Hill, North Carolina, provides radioanalytical services for CP&L's nuclear plant radiological environmental monitoring programs. In fulfillment of Technical Specification 3/4.12.3, the laboratory is a i

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 lp change in vendors for the Interlaborator) Program was due to the EPA Environmental Cross-check l

Program's termination as of December 31,1995.

t 35

l i

During 1996,81 analyses were completed on 16 samples representing five major environmental

-l media (water, milk, and air filters, soil, and air cartridges). Data on the known activities and the standard deviations for the 81 analyses have been received from Analytics,Inc.. A comparison l

of the average of our reported values with Analytics, Inc. known activity and standard deviation is provided below:

1 1

Standard Deviation From Known Activity Percent of Analyses s 1 standard deviation 61 s 2 standard deviation 85 i

s 3 standard deviation 94

)

Five of 81 analyses exceeded the 3 sigma action level. This was a gross alpha / beta in water from First Quarter 19% Gross Alpha / Beta in Water (E0658-72) and three gammas from Second Quarter 19% Gamma in Water (E0734-72) and an Air Filter gamma (E0737-72).

The gross alpha / beta results were investigated by the following means: (1) rechecked counts and efficiency used, (2) instrument efficiency was verified and checked against 1995's efficiency, (3) samples had been disposed of so a recount was unobtainable, (4) reanalyzed an aliquot of remaining original sample, and (5) spiked the sample - recovery was also high; therefore, the investigation did not determine a reason for the erroneous result. The laboratory also participates in a Radiochemistry Effluent Interlaboratory Comparison Program (vendor - Analytics, Inc.)

which checks our performance (accuracy and precision) on Gross Alpha / Beta, Sr-89/90, and Fe-

55. The Gross Alpha / Beta results for 1996 were within Analytics, Inc.'s acceptable criteria range.

The three gamma results that exceeded the three sigma value in the Second Quarter were within -

acceptable range in the Third Quarter 1996 Cross-Check sample.

Lower Limits of Detection All samples analyzed met the LLD required by Technical Specification 6.9.1.7 and Table 4.12.1-

1. Typical "a priori" LLD values for the samples analyzed are listed in Table 8.

O i

l 36

TABLE 8 I

TYPICAL LOWER LIMITS OF DETECTION (A PRIORI)

GAMMA SPECTROMETRY Surface Water Samples-:

(Saline Water)

Isotopei LLD (pCi/l)

Mn-54 7

Co-58 6

Fe-59 12 Co-60 8

Zn-65 14 Zr-Nb-95 7

Cs-134 7

Cs-137 6

Ba-La-140 8

Other Expected Gamma Emitters 4 to 409

~ Air Particulates1 (Quarterly Composite)

Isotope '

LLD (pCi/m')

I-131 0.063 Cs-134 0.002 Cs-137 0.002 Other Expected 0.001 to 0.073 Gamma Emitters LShoreline Sediment '

Isotopel

-LLD (pCi/kg, dry)'

Cs-134 69 Cs-137 71 Other Expected 41 to 1518 Gamma Emitters l

O 37

i TABLE 8 TYPICAL LOWER LIMITS OF DETECTION (A PRIORI)

GAMMA SPECTROMETRY l Fish :

~ Isotope.

LLD (pCi/kg, wet)

^

Mn-54 54 Co-58 40 Fe-59 119 i

Co-60 67 Zn-65 75 Cs-134 74 Cs-137 64 Other Expected 36 to 1429 Gamma Emitters

. Food Products and Vegetation -

-Isotope -

LLD (pCi/kg, wet)-

(O/

I-131 41 Cs-134 34 Cs-137 34 Other Expected 22 to 1811 Gamma Emitters O

38 3

q LAND-USE CENSUS C/

PURPOSE OF THE LAND-USE CENSUS The land-use census identifies the pathways (or routes) that radioactive material may reach the general populations near commercial nuclear generating stations. This is accomplished by completing studies each year that identify how the surrounding lands are used by the population.

A comprehensive census of the use of the land within a five mile distance of the plant is completed during the growing season each year. This information is used for dose assessment and to identify changes to the stations sampled and the type of samples. These results ensure that the Radiological Environmental Monitoring Program (REMP) is based upon current data regarding human activity in the vicinity of the plant. Therefore the purpose of the land-use census is 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 cating food crops that may have radioactive materials deposited on them, incorporated radioactive materials from the soil or atmosphere. Another pathway is through drinking milk from local cows or goats if these are present. The grass (w) used to feed these animals may have incorporated or had deposited on it radioactive i

\\

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 1

The following must be identified within the five (5) mile radius of the plant for each of the j

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 l

exception of the Military Ocean Terminal. This information is supplemented with data from aerial photographs, information from county extension agents, and farm supply businesses.

,O v

39

i 1996 Land-Use Census Results The 1996 and 1995 results of the survey for the nearest resident, garden, milk and meat animals l

in each sector are compared in Table 9.

There was no change in the location of the nearest resident in each sector. The following changes in the status of the gardens occurred with the addition of gardens in the NNE sector at I

1.2 miles and in the ESE sector at 1.6 miles. There is no longer a garden at 0.8 miles in the NNW sector, but one was located at 4.4 miles in this sector. Neither milk nor meat animals are located within 5 miles of the plant.

i i

+

f O

l a

40

f

(

l TAHLE9 O

LAND-USE CENSUS COMPARISONS (1995-1996)

NEAREST PATilWAY (MILES)

SECTOR RESIDENT GARDEN MILK / MEAT ANIMALS 1996 1995 1996 1995 1996 1995 l

l N

0.9 0.9 None None None None NNE 0.9 0.9 1.2 None 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 1.6 None None None SE 0.9 0.9 None None None None SSE 0.9 0.9 None None None None S

1.5 1.5 1.5 1.5 None None SSW l.2 1.2 1.5 1.5 None None SW l.0 1.0 1.0 1.0 None None WSW l.0 1.0 1.0 1.0 None None W

0.8 0.8 0.8 0.8 None None WNW 0.8 0.8 0.9 0.9 None None NW 0.9 0.9 1.0 1.0 None None NNW 0.8 0.8 4.4 0.8 None None O

l l

41

l g

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 Measuremc it, Washington, D.C. (January 1971)

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

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

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

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

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

" Exposure of the Population in the United States and Canada from Natural Background Radiation," Report No. 94, National Council on Radiation Protection and Measurements,

,/~N Washington, D.C. (December 1987)

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

" Health Effects of Exposure to Low Levels of Ionizing Radiation: BEIR V," Committee on the Biological Effects of Ionizing Radiations, Board on Radiation Effects 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 I

York, N.Y. (1988) i V

42

I i

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

l "The Effects on Populations of Exposure to Low Levels ofIonizing 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)

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(I Semiannual Analysis Report CP&L' Radiological Enviromental Monitoring Analysis Report 3/13/97 Plant: BNP TLD in mR/QTR Sample Point SampleDate Dose 2 SigmaError 1 - 1.1111 E - Ef00RE ST EXTENSION 2/15/96 9.40E+000 330E+000 1

5/15/96 9.80E+000 8.00E 001 2 - 1.0 Ell ESE-Kf00RE ST EXTENSION 2/15/96 9.60E+000 3.40E+000 2

5/15/96 1.05E+001 7.00E-001 3 - 0.9 hil SE - hf00RE ST EXTENSION 2/15/96 9.70E4000 3.40E+000 3

5/15/96 1.04E+001 1.00E+000 4 - 1.1 hil SSE-Ef00RE ST EXTENTION 2/15/96 9.90E+000 3.40E+000 4

5/15/96 9.50E+000 7.00E-00I

$ - 1.1111 S - LEONARD ST 2/15/96 9.70E+000 3.40E+000 5

5/15/96 9.90E+000 1.20E+000 6 - I.0 h!! S - BEkiCO POWER LINE 2/15/96 8.20E+000 3.50E+000 6

5/15/96 9.00E+000 7.00Eml 7

1.0 kII SW-11%T 87 AT RIGIIT-OF-WAY 2/15/96 9.60E+000 330E+000 7

5/15/96 1.03E+001 7.00E-001 8 - 1.2 ht! W-IrwT 87 2/15/96 9.40E+000 330E+000 8

5/15/96 8.70E+000 7.00E 001 9 - 1.0 hfI WNW-BETilEL CIIURCII RD 2/15/96 1.16E+001 330E+000 9

5/15/96 9.40E+000 100E+000 10 - 0.9 kilNW-BETilELCIIURCll RD 2/15/96 830E+000 3.40E+000 10 5/15/96 830E+000 9.00E-001 11 - 0.9 hil NNW-BETilEL CIIURCII RD 2/15/96 1.20E+001 3.40E+000 11 5/15/96 LOOE+001 9.00E-001 12 - 1.0 ht! N.BETl!EL CIIURCil RD 2/15/96 1.01E+001 330E+000 12 5/15/96 1.06E+001 8.00E-001 13 - 1.2 hil NNE - BETIIEL CIIURCII RD 2/15/96 7.70E+000 3.40E+000 13 5/15/96 8.90E+000 1.00E+000 14 - 0.5 h!!NE. INTAKE CANAL 2/15/96 136E+001 3.50E+000 14 5/15/96 1.20E+001 I.10E+000 15 - 0.9 htl ENE -INTAKE CANAL 2/15/96 1.08E+001 3.40E+000 15 5/15/96 1.19E+001 3.50E+000 16 - 1.0 hfi WSW-DIScilARGE CANAL 2/15/96 9.40E+000 330E+000 16 5/15/96 9.40E+000 1.00E+000 17 - 1.5 hil ESE-PFIZER PROPERTY 2/15/96 1.26E+00I 3.80E+000 17 5/15/96 1.06E+001 1.10E+000 18 - 1.7 All SE-PFlZER PROPERTY 2/15/96 1.11E+001 3.40E+000 18 5/15/96 8.60E+000 130E+000 20 - 2.0 kil S - h100RE ST 2/I5/96 8.60E+000 3.60E+000 20 5/15/96 8.40E+000 1.40E+000 21 - 2.9 h!I SSW -WEST ST AT SEA cal' FAIN 2/15/96 I.I4E+001 3.40E+000 21 5/15/96 9.20E+000 0.00E+000

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CP&L Radiological Enviromental Monitoring Analysis Report 3/13/97 Plant: BNP TLD in mR/QTR Sample Point SeinpleDate Deze 2 SignisError 22 - 53 hit SW-CASWELL BEACll MD 2/15/96 9.80E+000 3.50E+000 22 5/15/96 1.01E+001 1.40E+000 23 - 4.6111 WSW-NEAR AIRPORT 2/15/96 9.20E+000 4.20E+000 23 5/15/96' 8.40E+000 1.20E+000 24 - 3.0 ht! W-HWY 211 2/15/96 9.40E+000 330'E+000 24 i ie.M 9.20E+000 1.00E+000 25 - 8.7 ht! WNW-ANTIOCII BAPTIST CHURCil 2/13/96 1.28E+001 3.40E+000 25 5/15/96 1.05E+001 1.00E+000 26 - 5.9 hu NW-W DOfLING SPRINGS RD 2/15/96 L28E+001 3.40E+000 26 5/15/96 1.02E+001 7.00E-001 27 - 3.0 hilNNW-HWY 133 2/15/96 8.90E+000 330E+000 i

27 5/15/96 8.20E+000 130E+000 28 - 4.2 hil NW-AT SOtJTH BkUNSW1CK IIS 2/15/96 1.03E+001 3.60E+000 28 5/15/96 9.00E+000 1.20E+000 29 - 2.6 htl SSW - SOUrlIPORT ELEhtENTARY SCIIOOL 2/15/96 8.90E+000 330E+000 29 5/15/96 8.70E+0M 1.60E+000 30 - 2.0 h!I NE - SLWNY POINT htOT 2/15/96 9.40E+000 3.40E+000 30 5/15/96 1.01E+001 1.00E+000 31 - 2.6 ht! ENE-SLWNY POINT hf0T 2/15/96 1.01E+001 330E+000 31 5/15/96 1.01E+001 1.90E+000 32 - 5.7 hil ENE -IT FISHER AFB IIOUSING 2/15/96 1.07E+001 3.60E+000 32 5/15/96 1.03E+001 1.00E+000 33 - 4.0 Ell E - FERRY SLIP IN NEW IIANOVER CO 2/15/96 8.90E+000 3.40E+000 33 5/15/96 9.70E +000 1.00E+000 34 - 5.5 kH ENE-FTFISIIER EIUSEUhl 2/15/96 8.20E+000 330E+000 34 5/15/96 930E+000 1.5dE+000 35 - 7.5 ht! SSE-BALD IIEAD ISLAND 2/15/96 9.60E+000 3.40E+000 35 5/15/%

8.10E+000 9.00E-001 l

36 - 93 h11 NE-CAROLINA BEACil 2/15/96 9.50E+000 3.50E+000 36 5/15/96 9.00E4000 7.00E4)01 37 - 5.5 hl! NW-DOILING SPRINGS LAKES 2/15/96 8.20E+000 330E+000 37 5/15/96 8.40E+000 8.00E-001 38 - 11.0 ht! W-StWSETIIARDOR 2/15/96 9.10E+000 3.40E+000 38 5/15/96 830E+000 9.00E-001 39 - 53 ht! SW-YAUPON BEACll CITf IIALL 2/15/96 8.50E+000 3.40E+000 39 5/15/96 9.00E+000 1.20E +000 40 - 6.9 ht! WSW-LONG BEACH CITY llALL 2/15/96 1.05E4001 3.40E+000 40 5/15/96 8.80E+000 9.00E-001 75 - 4.5 ht! S - FT CASWELL BAPT1ST ASSEhtBLY 2/15/96 1.05E+001 330E+000 75 5/15/96 1.07E+00I 1.40E+000 f

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Semiannual Analysis Repon CP&L Radiological Enviromental Monitoring Analysis Report 3/13/97 Plant: BNP TLD inmR/QTR I

Sample Point SampleDate Dose 2 SigmaError 76 - 4 8111 SSW-CASWEll.BEACII 2/15/96 1.24E+001 3.40E+000 76 5/15/96 1.08E+001 1.40E+000 77 - 53 kilSSE-BA1.DHEADISLAND 2/15/96 1.1SE+001 330E+000 l

77 5/15/96 8.10E4400 130E+000 78 - 10.0 kli NNE-II%T 133 AT SR 152I 2/15/96 8.20E+000 330E+000 78 5/15/96 9.00E+000 1.00E+000 t

79 - 9.5 klIN-SR 1539 ATSR 1521 2/15/96 1.16E+001 330E+000 79 5/15/96 9.90E+000 6.00E-001 i

81 - 10.0111 WNW-hi!DWAY RD AT SR I$08 2/15/96 1.17E+001 3.40E+000 t

81 5/15/96 1.00E+001 130E+000

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Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/13/97 i

Sample Point SampleDate Quantity E Niciency ActMty 2 SigenaError LED Plant: RNP Asseints: RETA MeeHaTvye: AIR PARTICULATE CUMETERS 200 - I.0 kil SW-VISITORS CENTER 1f196 27030000 3.79E-001 1.69E-002 334E-003 0.00E+000 I/896 278.20000 3.79E-001 1.89E402 330E-003 0.00E+000 1/15.96 277.50000 3.79E401 238E-002 3.52E-003 0.00E+000 I/22,96 281.20000 3.79E-001 2.15E-002 3.27E-003 0.00E+000 1/29,96 279.50000 3.79E-001 2.16E-002 338E-003 0.00E+000 2'5,96 263.40000 3.79E-001 232E-002 3.50E-003 '

O.00E+000 1 12/96 l24.90000 3.79E-001 3.12E-002 6.66E-003 0.00E+000 l

2'19 96 26730000 3.79E-001 1.60E-002 3.19E-003 0.00E+000 2/26.96 296.50000 3.79E-001 1.56E-002 3.00E-003 0.00E+M0 3/4.96 279.90000 3.79E-001 2.23E-002 3.5 t E-003 0.00E+000 3/1896 239.10000 3.79E-001 1.80E-002 3.I BE-003 0.00E+000 3/18.96 278.30000 3.79E-001 1.90E-002 3.15E-003 0.00E400 3/25/96 261.50000 3.79E-001 1.26E-002 3.23E-003 0.00E+000 4'15.96 295.50000 3.79E-001 1.91E-002 3.16E-003 0.00E+000 4/896 271.80000 3.79E-001 1.78E-002 330E-003 0.00E+000 4/1.96 284.500n0 3.79E-001 1.09E-002 2.86E-003 0.00E+000 4'2196 28730000 3.79E 001 1.78E-002 3 31E-003 0.00E+000 4/29,96 278.60000 3.79E-001 1.59E-002 3.08E-003 0.00E+000 5/696 296.10000 3,79E-001 1.45 E-002 2.85E-003 0.00E+000 5/13.96 276.60000 3.79E-001 133E402 3.00E-003 0.00E+000 5/20.96 293.20000 3.79E-00I 1.60E-002 3.06E-003 0Ti B000 5/27.96 283.60000 3.79E-001 1.55E402 3.08E-003 0.00E+000 6/3 96 293.50000 3.76E-001 131E 002 2.84E-003 0.00E+000 6/10.96 287.40000 3.76E-001 1.23E-002 3.04E-003 0.00E+000 l

6'17.96 302.80000 3.76E-001 8.47E-003 2.69E-003 0.00E+000

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6/24.96 285.90000 3.76E-001 1.6IE-002 3.01E-003 0.00E+000

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201 - 0.6 hil NE - PhlAC ll I!96 264.40000 3.79E-001 1.66E-002 338E-003 0.00E+000 I/8.96 271.00000 3.79E-001 1.70E-002 3.26E-003 0.00E+000 1il$196 267.20000 3.79E-001 2.53 E-002 3.68E-003 0.00E+000 I/2196 273.10000 3.79E-001 233E-002 3.43 E-003 0.00E+000

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l'29 96 270.80000 3.79E-001 2.01 E-002 338E-003 0.00E+000 2'5.96 257.10000 3.79E-001 2.51E-002 3.65E-003 0.00E+000 2/12.96 272.20000 3.79E-001 2.00E-002 336E 003 0.00E+000 2/19,96 266.90000 3.79E-001 2.80E-002 3.80E-003 0.00E+000 2/26.96 28130000 3.79E-001 1.56E-O'02 3.IIE-003 0.00E+000 5

314 96 269.80000 3.79E-001 2.llE-002 3.54E-003 0.00E+000 3/11/96 2773 0000 3.79E-001 1.70E-002 3.22E-003 0.00E+000 3'18.96 2733 0000 3.79E-001 I.73 E-002 3.10E-003 0.00E+000

^

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Semiannual Analysis Repott -

CP&L Radiological Enviremental Monitoring Analysis Report 3/13/97 Sainple Point SanspleDate Qusatify Efficiency Actidty 2 SiganaError LIE I

201 - 0.6 h!! NE-PhiAC 3'25,96

' 272.50000 3.79E-001 1.26E-002 3.13E403 0.00E+000 4:15.96 284.10000 3.79E-001 1.46E-002 3.01E 003 0.00E+000 4' E96 260.50000 3.79E401 1.60E402 330E 003 0.00E+000 4'l.96 277.70000 3.79E-001 1.0$E-002 2.89E-003 0.00E+000 l

42196 282.20000 3.79E-001 1.79E-002 335E 003 0.00E+000 4'29.96 27330000 3.79E-001 1.47E 002 3.06E-003 0.00E+000 5/696 286.20000 3.79E-001 1.26E 002 '

2.82E-003 0.00E+000 I

5/1396 268 00000 3.79E401 1.61E 002 3.23E-003 0.00E+000

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5/2096 28630000 3.79E-001 1.74E-002 3.19E-003 0.00E+000 f

5/27.96 278.10000 3.79E 001 1.50E-002 3.10E 003 0.00E+000 6'3 96 289.00000 3.76E-001 1.14E 002 2.77E-003 0.00E+000 6/10.96 277.00000 3.76E-001 1.29E-002 3.16E-003 0.00E+000

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293.20000 3.76E-001 1.0$E 002 2.88E-003 0.00E+000 l

6/24.96 282.90000 3.76E401 1.49E 002 2.96E-003 0.00E+000 I

202 - I.0 hil S - SUBSTATION ON CONSTRUCTION R 1/l96 293.70000 3.79E401 1.56E-002 3.08E403 0.00E+000 1/896 295.20000 3.79E-001 1.65E 002 3.04E403 0 00E+000 1/15.96 299.10000 3.79E-001 2.72E402 3.50E-003 0.00E+000 I/2196 296.00000 3.79E-001 2.19E-002 3.18E 003 0.00E+000 l

It29.96 291.00000 3.79E-001 2.02E-002 3.22E 003 0.00E+000 f

2/5.96 280.60000 3.79E-001 237E-002 338E 003 0.00E+000 2/1196 286.10000 3.79E-001 2.00E-002 3.25E-003 0.00E+000 f

b 2/19 96 279.20000 3.79E-001 1.55E-002 3.06E-003 0.00E+000 2/2696 301.90000 3.79E-001 134E 007 2.83E-003 0.00E+000 1

3/4.%

287.00000 3.79E-001 2.10E-002 338E 003 0.00E+000

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3/1196 288.70000 3.79E 001 1.53E.002 3.04E 003 0.00E+000 l

3/IE96 286.20000 3.79E-001 1.70E-002 2.99E-003 0.00E+000 i

3/25.96 284.80000 3.79E-001 139E-002 3.09E-003 0.00E+000

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4'15/96 302.60000 3.79E-001 136E-002 2.81E-003 0.00E+000 i

4/8.96 279.40000 3.79E-00I 1.54E-002 3.11E-003 0.00E+000 I

4/I/96 29430000 3.79E-001 1.03E-002 2.75E-003 0.00E+000 4/22.96 295.90000 3.79E-001 1.68E-002 3.19E-003 0.00E+000 4.79.96 285.40000 3.79E-001 1.28E-002 2.86E-003 0.00E+000

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5/696 304.00000 3.79E-001 1.49E-002 2.83E-003 0.00E+000 5/I3.96 284.70000 3.79E-001 1.49E-002 3.02E-003 0.00E4000 I

t 3/20,96 302.00000 3.79E-001 137E-002 2.88E-003 0.00E+000 5

5/27,96 293.70000 3.79E-001 I.16E-002 2.78E-003 0.00E+000 i

6/396 302.20000 3.76E-001 1.09E-002 2.65E-003 0.00E+000 i

6/10 96 -

297.40000 3.76E-001 1.04E-002 2.85E-003 0.00E+000 6/1796 311.10000 3.76E-001 7.93 E-003 2.60E-003 0.00E+000 f

6'2496 29430000 3.76E-001 1.45 E-002 2.R6E.003 ~

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O Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/13/97 Sample Point SampleDate Quantity Efficiency Actidty 2 SigmaError LLD 203 - 23 hil SSW-SOUrlIPORT SUBSTATION llI/96 264.10000 3.79E-001 1.76E-002 3.43 E-003 0.00E+000 1/E96 267.20000 3.79E-001 2.09E-002 3.50E-003 0.00E+000 I fl5,96 270.10000 3.79E-001 2.89E-002 3.82E-003 0.00E+000 1/22,96 270.90000 3.79E-001 2.13EM2 334E 003 0.00E+000 179.96 271.50000 3.79E-001 230E-002 3.52E-003 0.00E+000 2!5:96 259.50000 3.79E-001 2.50E-002 3.62E403 0.00E+000 1/1296 240.50000 3.79E-001 2.2 t E-002 3.78E 003 0.00E+000 2:1996 273.10000 3.79E-001 1.78E-002 3.24E-003 0.00E+000 12696 300.00000 3.79E-001 IJ1E-002 2.83 E-003 0.00E+000 3' 4 ?6 283.80000 3.79E 001 2.12E 002 3.42E-003 0.00E+000 3'11/96 291.50000 3.79E-001 1.52E-002 3.01E 003 0.00E+000 3'IR96 285.10000 3.79E-001 1.75E 002 3.02E-003 0.00E+000 32596 285.50000 3.79E-001 1.22E-002 2.99E 003 0.00E+000 4/1596 293.80000 3.79E-001 1.59E-002 3.01E403 0.00E+000 4!8.96 276.90000 3.79E-001 1.97E 002 335E 003 0.00E+000 4'I/96 293.60000 3.79E-001 9.80E 003 2.72E 003 0.00E+000 42196 292.20000 3.79E-001 1.86E-002 331E-003 0.00E+000 4'29 96 287.90000 3.79E-001 134E-002 2.87E 003 0.00E+000

$/696 307.20000 3.79E-001 1.2tE 002 2.65 E-003 0.00E+000 5/13.96 288.20000 3.79E 001 1.06E-002 2.75E-003 0.00E+000 5/2096 306.00000 3.79E-001 1.64E 002 2.99E 003 0.001;+000 5/27,96 296.10000 3.79E-001 1.14E-002 2.75E-003 0.00E+000 6/ 3%

304.50000 3.76E-001 1.07E-002 2.62E-003 0.00E+000 6/10,96 298.20000 3.76E-001 9.00E-003 2.76E-003 0.00E+000 i

6/17.96 314.50000 3.76E-001 8.46E-003 2.61E-003 0.00E+000 6/2496 298.10000 3.76E-001 IJIE-002 2.75E-003 0.00E+000 204 - 23.0 kil NNE - SUITON PLANT (CONTROL)

I/ !!96 272.80000 3.79E-001 1.63E-002 3.28E-003 0.00E+000 1/8.96 284.10000 3.79E-001 1.92E 002 3.27E-003 0.00E+000 t/15!96 284.10000 3.79E-001 2.40E-002 3.47E-003 0.00E+000 1/22:96 28730000 3.79E-001 2.06E-002 3.18E-003 0.00E+000 1/29 96 259.40000 3.79E 001 2.03E-002 3.50E-003 0.00E+000 2/5,96 272.60000 3.79E-001 2.82E-002 3.66E-003 0.00E+000 I

2'12:96 273,60000 3.79E-001 2.45E-002 3.58E-003 0.00E+000 i

2/19.96 28230000 3.79E-001 1.70E-002 3.12E-003 0.00E+000 23696 282.60000 3.79E-001 1.43E-002 3.03E 003 0.00E+000 3/496 286.10000 3.79E-001 2.23E-002 3.45E-003 0.00E+000 3/11.96 279.7a000 3.79E-001 2.04E-002 337E-003 0.00E+000 3/18.96 28230000 3.79E-001 1.80E-002 3.07E-003 0.00E+000 l

3/25.96 280.7000G 3.79E-001 1.68E-002 3.28E-003 0.00E+000 l

4'1596 281.10000 3.79E-001

. l.87E-002 3.25E-003 0.00E+000 4

,. ~ - -

)

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Semiannual Analysis Report CP&L Radiological Environiental Monitoring Analysis Report 3/13/97 Sansple Point SampleDate Quantity Efficiency ActMty 2 SigmaError-IJD 204 - 23.0 h!! NNE-SUITON PLWT(CONTROL) 4! E96 290.90000 3.79E 001 1.78E-002 3.14E-003 0.00E+000 4/1.96 284.20000 3.79E-001 136E-002 3.02E-003 0.00E+000 4'22,96 285.40000 3.79E-001 1.79E402 333E-003 0.00E+000 40996 288.90000 3.79E401 1.78E 002 3.10E403 0.00E+000 5/696 288.00000 3.79E-001 1.57E-002 278E-003 0.00E+000 5/13.96 272.10000 3.79E-001 1.27E-002 3.00E-003 0.00E+000 5/20,96 284.80000 3.79E-001 1.99E-002 333E-003 0.00E+000 5/27.96 295.00000 3.79E-001 1.44E-002 2.93E-003 0.00E+000 6/3.96 286.80000 3.76E-001 1.15E 002 2.80E-003 0.00E+000 C1096 295.10000 3.76E-001 9.50E 003 2.82E403 0.00E+000 Cl7.96 263.70000 3.76E-001 8.54E-003 3.02E-003 0.00E+000 6/2496 291.80000 3.76E-001 134E.002 2.81E-003 0.00E+000 205 - 0.6 kll SSE-SPOIL POND 1/I96 277.40000 3.79E 001 1.29E 002 3.06E 003 0.00E+000 1/ Go 271.50000 3.*E m s 1.93E 002 338E403 0.00E+000 1/15/96 27830000 3.79E-001 2.60E-002 3.62E-003 0.00E+000 1/22.96 28230000 3.79E-001 2.16E402 3.27E-003 0.00E+000 1/29.96 282.40000 3.79E-001 1.87E-002 3.21E-003 0.00E+000 2/5/96 273.10000 3.79E-001 2.4IE-002 3.46E-003 0.00E+0CJ 2/12/96 285.10000 3.79E-001 2.26E 002 339E-003 0.00E+000 2/1996 283.10000 3.79E-001 1.66E-002 3.10E-003 0.00E+000 l'2696 293.20000 3.79E-001 1.41E-002 2.94E-003 0.00E+000 3/4 96 288.60000 3.79E-001 2.29E 002 3.46E-003 0.00E+000 3/1l>96 293.40000 3.79E 001 1.52E 002 2.99E-003 0.00E+000 3!!8.96 292.10000 3.79E-001 1.59E 002 2.88E-003 0.00E+000 i

3/25/96 2923 0000 3.79E 001 133E 002 2.99E-003 0.00E+000 4'I5/96 307.70000 3.79E-001 1.9IE 002 3.07E-003 0.00E+000 4/8.96 283.10000 3.79E-001 1.71E-002 3.17E-003 0.00E+000 4/l.96 296.40000 3.79E 001 1.05 E-002 2.75E 003 0.00E+000 40296 301.40000 3.79E-001 1.93 E-002 3.27E-003 0.00E+000 4'29 96 195.70000 3.79E-001 1.23E.002 3.77E-003 0.00E+000 5/6,96 278.90000 3.79E-001 1.45E.002 2.98E-003 0.00E+000 5/13.96 284.00000 3.79E-001 136E 002 2.%E-003 0 00E+000 5/20.96 301.00000 3.79E-001 1.60E-002 3.01E-003 0.00E+000

$!27.96 293.40000 3.79E-001 133E-002 2.88E-003 0.00E+000 6/3 96 303.70000 3.76E-001 1.22E-002 2.72E-003 0.00E+000 6/10.96 298.40000 3.76E-001 6.74E-003 2.63E-003 0.00E+000

&l7,96 313.50000 3.76E-001 8.18E-003 2.60E-003 0.00E+000 6/2496 296.40000 3.76E-001 133E-002 2.77E-003 0.00E+000 5

l l

r Semiannual Analysis Repott CP&L Radiological Enviremental Monitoring Analysis Report 3/13/97 Sample Point SampleDate Quantity Emciency ActMtv 2 SigmsError LLD Plant: BNP Anahsis: IODINE MediaTne: AIR CARTRIDGE CUMETERS 200 - 1.0 kil SW - VISITORS CENTER 1/196 2703 0000 0.00E+000 0.00E+000 3.47E402 1/E96 278.20000 0.00E+000 0.00E+000 2.68E 002 1/15.96 277.50000 0.00E+000 0.00E+000 3.70E402 1/22,96 281.20000 0.00E+000 0.00E+000 3.06E402 1/29.96 279.50000 0.00E+000 0.00E+000 2.00E402 I

2'5,96 263.40000 0.00E+000 0.00E+000 3.20E-002 2/1196 124.90000 0.00E+000 0.00E+000 6.94E 002 2.'I9,96 26730000 0.00E+000 0.00E+000 3.16E-002 2/2696 296.50000 0.00E+000 0.00E+000 2.97E-002 3/496 279.90000 0.00E+000 0.00E+000 4.20E-002 3/IE96 27830000 0.00E+000 0.00E+000 3.63E-002 3/l1,96 289.10000 0.00E+000 0.00E+000 2.98E402 3'2596 261.50000 0.00E+000 0.00E+000 2.65E-002 4'I/96 284.50000 0.00E+000 0.00E+000 2.62E-002 4/8.96 271.80000 0.00E+000 0.00E+000 3.52E-002 4/15/96 295.50000 0.00E+000 0.00E+000 236E-002 42196 28730000 0.00E+000 0.00E+000 3.08E-002 I

429.96 278.60000 0.00E6 0.00E+000 3.02E 002 5/696 266.10000 0.00E+000 0.00E+000 3.14E 002 5/13.96 276.60000 0.00E+000 0.00E+000 3.43 E-002 5/20;96 293.20000 0.00E+000 0.00E+000 3.70E-002 5/27 96 283.60000 0.00E+000 0.00E+000 3.65E 002 6/3.96 293.50000 0.00E+000 0.00E+000 3.41E 002 6/10.96 287.40000 0.00E+000 0.00E+000 3.00E 002 6/2496 285.90090 0.00E+000 0.00E+000 3.17E-002 6/1776 302.80000 0.00E+000 0.00E+000 3.23 E-002 201 - 0.6 h11 NE - PhlAC I/196 264.40000 0.00E+000 0.00E+000 235E-002 I/8.96 271.00000 0.00E+000 0.00E+000 2.97E402 I/15.96 267.20000 0.00E+000 0.00E+000 3.61E-002 1/22,96 273.10000 0.00E+000 0.00E+000 3.83E.002 1/2996 270.80000 0.00E+000 0.00E+000 2.82E-002 2/5/96 257.10000 0.00E+000 0.00E+000 2.98E-002 2/12.96 272.20000 0.00E+000 0.00E+000 3.84E 002 2/19/96 266.90000 0.00E+000 O.00E+000 3.98E-002 2/2696 28130000 0.00E+000 0.00E+000 2.64E-002 3/496 269.90000 0.00E+000 0.00E+000 2.80E402 3!!8.96 27330000 0.00$+000 0.00E+000 4.02E-002 3/I1.96 2773 0000 0.00E+000 0.00E+000 3.I7E402 3'25.96 272.50000 0.00E+000 0.00E+000

• 3.20E402 6

3 w

a

_ Semiannual Analysis Report '

CP&L Radiological Enviremental Monitoring Analysis Report 3/13/97 Sample Point SampleDate Quantity Emciency Actidty 2 SigmsError LIE '

201 - 0.6 hil NE - PP1AC 4'l.96 277.70000 0.00E+000 0.00E+000 4.16E402 4'8.96 260.80000 0.00E+000 0.00Ee 4.19E402 4'1556 284.10000 0 00E+000 0.00E+000 3.44E-002 4/2296 282.20000 0.00E+000 0.00E+000 2.44E-002 47996 27330000 0.00E+000 0.00E+000 3.99E-002 5/6.96 286.20000 0.00E+000 0.00E+000 4.04E-002 5/1396 268.00000 0.00E+000 0.00E+000 3.61E-002 5/20.96 28630000 0.00E+000 0.00E+000 4.93E-002 5/2736 278.10000 0.00E+000 0.00E+000 3.51E-002 6/3.96 289.00000 0.00E+000 0.00E+000 2.99E 002

&1096 277.00000 0.00E+000 0.00E+000 4.16E-002 6d496 282.90000 0.00E+000 0.00E+000 3.45E 002 6/1736 293.20000 0.00E+000 0.00E+000 332E402 202 - 1.0 M1 S - SUBSTATION ON CONSTRUCTION R I/2,96 293.70000 0.00E+000 0.00E+000 2.63E-002 Il196 295.20000 0.00E+000 0.00E+000 3.58E 002 1/15S 6 299.10000 0.00E+000 0.00E+000 3.58E 002 1/2266 296.00000 0.00E+000 0.00E+000 2.40E-002 1/29,96 291.00000 0.00E+000 0.00E+000 2.80E 002 2/5/96 280.60000 0.00E+000 0.00E+000 331E402 2/l256 286.10000 0.00E+000 0.00E+000.

2.68E-002 2/1956 279.20000 0.00E+000 0.00E+000 2.94E-002 2.76.96 301.90000 0.00E+000 0.00E+000 3.28E-002 3/ 4S6 287.00000 0.00E+000 0.00E+000 3.04E-002 3/l196 286.20000 0.00E+000 0.00E+000 4.19E402 3/II/96 288.70000 0.00E+000 0.00E+000 2.90E-002 3/25 S 6 284.80000 0.00E+000 0.00E+000 3.71E-002 4/ IS6 294 30000 0.00E+000 0.00E+000 3.25E-002 3

4/8.96 279.40000 0.00E+0C0 0.00E+000 2.49E 002 4'1566 302.60000 0.00E+000 0.00E+000 3.65E-002 4'22.96 295.90000 0.00E+000 0.00E+000 3.25E-002 i

4'29.96 285.40000 0.00E+000 0.00E+000 435E-002 5/6 96 304.00000 0.00E+000 0.00E+000 3.67E-002 5713 96 284.70000 0.00E+000 0.00E+000 436E-002 j

5/20 S 6 302.00000 0.00E+000 0.00E+000 3.64E-002 5/2796 293.70000 0.00E+000 0.00E+000 4.89E-002 i

6/396 302.20000 0.00E+000 0.00E+000 4.0iE402 6/1066 297.40000 0.00E+000 0.00E+000 3.74E-002 6P2496 29430000 0.00E+000 0.00E+000 3.52E-002 l

6/17/96 311.10000 0.00E+000 0.00E4000 3.83E-002 203 - 23 h11 SSW - SOUTHPORT SUBSTATION 1/296 264.10000 0.00E+000 0.00E+000 3.95E-002 7

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J Semiannual Analysh Report CP&L Radiological Enviromental Monitoring Analysis Repott 3/13/97

(

[

Sample Point SampleDate Quantity Efficiency ActMty 2 SigmaError IJD 203 - 23 kil SSW-SOLTIIPORT SUBSTATION ll8S6 267.20000 0.00E4000 0.00E+000 335E-002 I/15.96 270.10000 0.00E+000 0.00E+000 4.09E402 F

I/2296 270.90000 0.00E+000 0.00E6 3.60E 002 I/29 96 271.50000 0.00E+000 0.00E+000 4.05E 002 2/596 259.50000 0.00E+000 0.00E+000 3.81E-002 2/1296 240.50000 0.00E+000 0.00E+000 3.06E-002 2/19.96 273.10000 0.00E+000 0.00E+000 3.32E 002 226 %

300.00000 0.00E+000 0.00E+000 2.63E 002 3/ 4 %

283.80000 0.00E+000 0.00E+000 3.95 E-002 3/1896 285.10000 0.00E+000 0.00E+000 43 t E-002 3/11/96 291.50000 0.00E+000 0.00E+000 3.19E-002 3/25 S 6 285.50000 0.00E+000 0.00E+000 2.41E-002 4'1/96 293.60000 0.00E+000 0.00E+000 3.79E402 4'E96 276.90000 0.00E+000 0.00E+000 3.II E-002 i

4!15.96 293.80000 0.00E+000 0.00E+000 2.60E-002 4/22/96 292.20000 0.00E+000 0.00E+000 3.48E402 4/29/96 287.90000 0.00E+000 0.00E+000 2.60E-002 5/6S6 307.20000 0.00E+000 0.00E+000 3.19E 002 5/1396 288.80000 0.00E+000 0.00E+000 2.74E.002 5/20.96 306.00000 0.00E+000 0.00E+000 -

4.02E-002 5/27/96 296.10000 0.00E+000 0.00E+000 3.27E402 6/3.96 304.50000 0.00E+000 0.00E+000.

2.80E-002 6/10,96 298.20000 0.00E+000 0.00E+000 3.06E-002 I

6/24,96 298.10000 0.00E4000 0.00E+000 2.59E-002 6/17/96 314.50000 0.00E+000 0.00E+000 2.48E-002 204 - 23.0 h!! NNE - SUTTON PLANT (CONTROL) 1/196 272.80000 0.00E+000 0.00E+000 3.44E-002 l

1/836 284.I0000 0.00E+000 0.00E+000 3.97E-002 E

1/15/96 284.10000 0.00E+000 0.00E+000 3.66E-002 1/2296 28730000 0.00E+000 0.00E+000 3.31 E-002 1/29 96 259.40000 0.00E+000 0.00E+000 3.04E-002 I

2/536 272.60000 0.00E+000 0.00E+000 3.16E-002 i

1/1296 273.60000 0.00E+000 0.00E+000 3 63E-002 2/19.96 2823 0000 0.00E+000 0.00E+000 3.70E 002 2/2696 282.60000 0.00E+000 0.00E+000 2.79E-002 3/4 96 286.10000 0.0CE+000 0.00E+000 2.48E-002 3/l&96 28230000 0.00E+000 0.00E+000 2.63E 002 3/1IS6 279.70000 0.00E+000 0.00E+000 169E-002 j

3/25/96 280.70000 0.00E+000 0.00E+000 333E-002 4/I/96 284.20000 0.00E+000 0.00E+000 3.43E-002 4/896 290.90000 0.00E+000 0.00E+000 2.84E-002 8

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Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/13/97 t

Sample Point SampleDate Quantity Efficiency ActMty 2 SigmaError L1D 204 - 23.0 kil NNE - SLUTON PLANT (CONTROL) 4.15,96 281.10000 0.00E+000 0.00E+000 3.64E-002

[

47196 285.40000 0.00E+000 0.00E +000 2.99E-002

[

T29.96 288.90000 0.00E+000 0.00E+000 3.92E-002 5/6 96 288.00000 0.00E+000 0.00E+000 337E-002 5/1396 272.10000 0.00E+000 0.00E+000 3.08E-002

$/2096 284.80000 0.00E+000 0.00E+000 33?E-002 5/27.96 295.00000 0.00E+000 0.00E+000 2.89E-002

[

6/3 96 286.80000 0.00E+000 0.00E+000 3.00E-002

[

6/10.96 295.10000 0.00E+000 0.00E+000 2.61E-002 i

6'2496 291.80000 0.00E+000 0.00E+000 3.94E-002 6/17S6 263.70000 0.00E+000 0.00E+000 3.69E-002 205 - 0.6 hil SSE-SPOIL POND l/2.96 277.40000 0.00E+000 0.00E+000 3.5IE-002 I!896 271.50000 0.00E+000 0.00E+000 4.29E-002 t/1536 27830000 0.00E+000 0.00E+000 3.26E42

!!22.96 282.30000 0.00E+000 0.00E+000 2.61E-002 17996 282.40000 0.00E+000 0.00E+000 2.84E-002 2/5.96 273.10000 0.00E+000 0.00E+000 3.40E-002 f

2112.96 285.10000 0.00E+000 0.00E+000 2.78E402 2/19 %

283.10000 0.00E+000 0.00E+000 4.62E-002 2/2696 293.20000 0.00E+000 0.00E+000 3.05E-002 3/496 288.60000 0.00E+000 0.00E+000 2.93E-002 1

3/1896 292.10000 0.00E +000 0.00E+000 6.24E-002 3'l1.96 293.40000 0.00E+000 0.00E+000 2.97E-002 i

3'25S 6 292.30000 0.00E+000 0.00E+000 3.63E-002

[

4!I:96 296.40000 0.00E+000 0.00E+000 3.62E-002 4!896 283.10000 0.00E+000 0.00E+000 3.63E42 4/1596 307.70000 0.00E+000 0.00E+000 3.29E-002 1

4'22.96 301.40000 0.00E+000 0.00E+000 4.17E-002 I

N2996 195.70000 0.00E+000 0.00E+000 4.53E-002 I

{

5/6/96 278.90000 0.00E+000 0.00E+000 3.68E-002 5/13 S 6 284.00000 0.00E+000 0.00E+000 439E402

[

5/20,96 301.00000 0.00E+000 0.00E+000 3.83 E-002 I

5/27/96 293.40000 0.00E+000 0.00E+000 4.76E-002 6/3/96 303.70000 0.00E+000 0.00E+000 4.26E-002 6'10.96 298.40000 0.00E+000 0.00E+000 5.IIE-002 6/2496 296.40000 0.00E+000 0.00E+000 2.94E 002 6/17S6 313.50000 0.00E+000 0.00E+000 4.04E-002 Plant: BNP Anaksis:TRITIUhl MedinTne: SURFACE WATER LITERS 400 - 0.7 hil NE-INTAKE CANAL (CONTROL)

I/3IS6

.00500 2.95 E-001 9.1 I E+002

[

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O Semiannual Analysis Report CP&L Radiological Enviremental Monitoring Analysis Report 3/13/97 Sample Point SampleDate Qusatity Emciency Acthity 2 SigueError_

LID 400 - 0.7 Af1 NE -INTAKE CANAL (CONTROL) 2/29 95

.00500 2.99E-001 9.075+002 331/96

.00$00 2.91E-001 937E+002 430.96

.00$00 2.%E-001 3.96E+002 5'31/96

.00500 2.93E-001 8.98E+002 630.96

.00500 4.30E-001 2.67E+002 401 - 4.9 hil SSW-DISCllARGE CANAL I!3I/96

.00500 2.95E-001 9.1IE4002 2/29 96 00500 2.99E-001 9.07E+002 3'31,96

.00500 2.9IE-00I 937E+002 41096

.00500 2.96E-001 8.96E+002

.531/96

.00500 2.93E-001 8.99E+C42 6SO,96

.00500 4.30E-001 2.67E+002 i

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O b$- kobjr.2 2%d 96 fivt CP&L I

Radiological Environmental Monitoring Isotopic Analysis Report 1

3/18/97 l

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O Sentiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3n8/97 Sample Point SampleDate Quantity hotope Activity 2 SigmaError LLD Plant: BNP Amaissis:CAhthlA hie 41aType: AIR PARTICUIATE Units: CUhlETERS 200 - 1.0 hil SW-VISITORS CENTER 2/15.96 3447.70000 BE-7 1.29E-001 2.40E-002 0.00E+000 5/15.96 3736.80000 BE-7 1.42E-001 230E-002 0.00E+000 201 - 0.6 AII NE - PhlAC 2/1596 3516.90000 BE-7 1.65E-001 2.50E-002 0.00E+000 5/15.96 3638.80000 BE-7 1.25E-001 3.00E-002 0.00E+000 202 - 1.0 hl! S - SUBSTATION ON CONSTRUCTION 2/15.96 3769.50000 BE-7 1.13 E-001 330E 002 0.00E+000 5/15/96 3847.00000 BE-7 1.53E-001 230E-002 0.00E+000 p

203 - 23 hl! SSW - SOUI'llPORT SUBSTATION 2/15 96 3562.80000 BE-7 1.52E-001 2.60E-002 0.00E+000 5/15,96 3837.20000 BE-7 134E-001 230E-002 0.00E+000 204 - 23.0 hlI NNE - SUITON PLANT (CONTROL) 1:15.96 3627.60000 Bb7 1.42E-001 2.20E-002 0.00E+000 I

5/15 96 3707.70000 BE-7 1.290001 2.50E-002 0.00E+000 5/15,96 3707.70000 PB-214 5.54E-003 2.45E 003 0.00E+000 205 - 0.6 hil SSE-SPOIL POND 2/15 96 3692.80000 BE-7 1.40E-001 2.40E-002 0.00E+000 5/15.96 3753.60000 BL7 1.54E-001 2.80E-002 0.00E+000 Plant: BNP AnsJysis:CAhthlA hie 4EaTne: BROADLEAFVEGETATION Units: CRAhtS hie 40s: CHERRY 800 - 0.7 hl! NE -INTAKE CANAL 5/6.96 430.70000 BE-7 4.64E-001 1.78E-001 0.00E+000 5/696 430.70000 1-131 0.00E+000 0.00E+000 3.19E402 5/6.96 430.70000 CS-134 0.00E+000 0.00E+000 3.10E402

$/696 430.70000 CS-137 0.00E+000 0.00E+000 3.78E-002 f

5/696 430.70000 K-40 234E+000 4.90E-001 0.00E+000 6/4 96 439.00000 BL7 5.68E.001 236E-001 0.00E+000 614.96 439.00000 1-131 0.00E+000 0.00E+000 2.95E-002 6/496 439.00000 CS-134 0.00E+000 0.00E+000 2.71E-002 6/496 439.00000 CS-137 0.00E+000 0.00E+000 2.99E-002 i

6/4 96 439.00000 K-40 2.99E+000 5.50E-001 0.00E+000 801 - 0.6 hil SW - DISCIIARGE CANAL Si696 439.60000 K-40 5.72E+000 6.60E-001 0.00E+000 5/696 439.60000 CS-137 0.00E+000 0.00E+000 2.65E-002 5/696 439.60000 CS-134 0.00E+000 0 00E+000 3.16E-002 5/6.96 439.60000 1-131 0.00E+000 0.00E+000 3.16E-002 6/4.96 346.90000 BE-7 3.03 E-001 2.80E-001 0.00E+000 6/4.96 346.90000 RA-226 I.45E+000 8.60E-001 0.00E+000 6/4 96 346.90000 1-131 0.00E+000 0.00E+000 5.50E-002 6/496 346.90000 CS-134 0.00E+000 0.00E+000 4.88E-002 6'4.96 346.90000 CS-137 0.00E+000 0.00E+000 5.22F402 6/496 346.90000 K-40 3.88E+000 9.00E-001 0.00Z+000 802 - 10.0 kil-NOT SPECIHED(CONTROL) 5/696 484.40000 K-40 5.02E+000 5.20E-001 0.00E+000 5/6,96 484.40000 CS-134 0.00E+000 0.00E+000 2.57E 902 5/696 484 40000 CS-137 0.00E+000 0.00E+000 2.68E-002 5/696 484.40000 1-131 0.00E+000 0.00E +000 2.42E-002

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Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/18/97 Sample Point SampleDate Quantity Isotope Acthity 2 SigmaError LLD 802 - 10.0 Mi-NOT SPECIFIED(CONTROL) 6/4 96 526.20000 BE-7 3.61E 001 2.14E-001 0.00E+000 6/4 96 526.20000 PD-212 3.23E-002 2 76E-002 0.00E+000 6'4 96 526.20000 1-131 0.00E+000 0.00E+000 2.69E-002 6'4.96 526.20000 CS-134 0.00E+000 0.00E+000 2.75E-002 6'4.96 526.20000 CS-137 0.00E+000 0.00E+000 2.42E-002 6!4 96 526.20000 K-40 334E+000 4.80E-001 0.00E+000 803 - 0.6 hll SSE - SPOIL POND 5/696 503.20000 BL7 3.25E-001 I.57E-001 0.00E+000 5/696 503.20000 1-131 0.00E+000 0.00E+000 2.95E-002 5/696 503.20000 CS-134 0.00E+000 0.00E+000 2.stE-002 5'6.-96 503.20000 CS-137 0.00E+000 0.00E+000 2.75E-002 5/696 503.20000 K-40 2.80E+000 1.57E+000 0.00E+000 6/4 96 521.70000 BL7 4.16E-001 5.00E-002 0.00E+000 6/4 96 521.70000 RA-226 3.47E401 2.89E-001 0.00E+000 6/4 96 521.70000 1-131 0.00E400 0.00E+000 2.88E-002 6/4.96 521.70000 CS-134 0.00E+000 0.00E+000 3.00E-002 6/ 0 6 521.70000 CS-137 0.00E+000 0.00E+000 2.40E-002 6/496 521.70000 K-40 3.72E+000 5.00E-001 0.00E+000 Plant: BNP Anaksis:CAMMA MedleType: BROADLEAFVECETATION Units: GRAMS Media: FESCUE 800 - 0.7 MI NE-INTAKE CANAL 1/I/96 407.60000 BL7 136E+000 2.70E-001 0.00E+000 1/I/96 407.60000 1-131 0.00E+000 0.00E+000 3.14E-002 t/1/96 407.60000 CS-134 0.00E+000 0.00E+000 3.46E 002 t/ I/96 407.60000 CS-137 0.00E+000 0.00E+000 335E-002 t/ I!96 407.60000 K-40 3.5 t E+000 6.00E-001 0.00E+000 2/5s96 328.20000 K-40 7.58E+000 8.70E 001 0.00E+000 2/5.96 328.20000 1-131 0.00E+000 0.00E+000 4.08E-002 2/3/96 328.20000 CS-134 0.00E+000 0.00E+000 4.21E-002 2/5/96 328.20000 CS-137 0.00E+000 0.00E+000 3.45E-002 2/5.96 328.20000 RA-226 9.22E-001 6.56E-001 0.00E+000 3/496 351.40000 K-40 6.58E+000 7.20E-001 0.00E+000 3/496 351.40000 CS-134 0.00E+000 0.00E+000 3.92E-002 3/4 96 351.40000 CS-137 0.00E+000 0.00E+000 3.60E-002 3/496 351.40000 1-131 0.00E+000 0.00E+000 3.69E-002 4/8.96 36630000 K-40 4.99E+000 6.90E-001 0.00E+000 4/8.96 36630000 I-131 0.00E+000 0.00E+000 3.23E-002 4'8/96 3663 0000 CS-134 0.00E+000 0.00E+000 3.61 E-002 4!8,96 36630000 CS-137 0.00E+0'00 0.00E+000 330E-002 4/196 36630000 BL7 I.82E+000 3.20E-001 0.00E+000 801 - 0.6 hfl SO DISCilARGE CANAL 1/1/96 36330000 K-40 5.0lE+000 6.10E-001 0.00E+000 Il 1,96 36330000 1-131 0.00E+000 0.00E+000 4.23 E-002 I/196 36330000 CS-134 0.00E+000 0.00E+000 3.80E-002

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Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/18/97 l

Sample Point SampleDate Quantity Isotope Actidty 2 SigmaError LID 801 - 0.6 hil SW-DIScilARGE CANAL i!1%

36330000 CS-137 0.00E+000 0.00E+000 3.49 0 002 II 1;96 36330000 TI-208 4.14E402 1.94E-002 0.00E+000 2/5.96 372.40000 K-40 6.75E+000 6.80E-001 0.00E+000 F5.96 372.40000 1-131 0.00E+000 0.00E+000 3.46E-002 2/ $c96 372.40000 CS-134 0.00E+000 0.00E+000 3.56E402 F 5,96 372.40000 CS-137 0.00E+000 0.00E+000 3.45 LOO 2 2!5.96 372.40000 TI 208 3.07E-002 2.07E-002 0.00E+000 3!496 35030000 BL7 1.24E+000 3.00E-001 0.00E+000 I

3!496 3503 0000 RA-226 630E-001 4.87E-001 0.00E+000 3!4.96 35030000 I-131 0.00E+000 0.00E+000 3.55E402 3/4 96 35030000 CS-134 0.00E+000 0.00E+000 3.57E 002 3/ 4%

35030000 CS-137 0.00E+000 0.00E+000 3.49E-002 3/4 96 3503 0000 K-40 5.18E+000 7.20 0 001 0.00E+000 r

4'8 96 350.90000 BE-7 8.84E-001 2.61 6 001 0.00E+000 4'896 350.90000 1-131 0.00E+000

- 0.00E+000 3.84 6002 4'8.96 350.90000 CS-134 0.00E+000 0.00E+000

- 3.95E-002 4'8.96 350.90000 CS-137 0.00E+000 0.00E+000 4.26E-002 i

4/ E96 350.90000 K-40 4.75E+000 7.40E-001 0.00E+000 802 - 10.0 hil-NOT SPECIFIED(CONTROL) 1/1.96 47430000 BL7 230E+000 3.00E-001 0.00E+000

!!!96 47430000 1-131 0.00E+000 0.00E+000 2.8 t E-002 I/ I!96 47430000 CS-134 0.00E+000 0.00E+000 2.66E-002 t/1:96 47430000 CS-137 0.00E+000 0.00E+000 2.5 IE-002 II 1.96 4743 0000 K-40 2.56E+000 4.80E-001 0.00E+000 2/5.96 365.00000 DE-7 2.77E+000 3.50E-001 0.00E+000 2/5/96 365.00000 1-131 0.00E+000 0.00E+000 3.52E-002 2/5 96 365.00000 CS-134 0.00E+000 0.00E+000 3.42E402 2/5.96 365.00000 CS-137 0.00E+000 0.00E+000 3.46E-002 2/5.96.

365.00000 K-40 5.llE+000 7.50E-001 0.00E+000 3/4 96 357.80000 BE-7 1.78E+000 2.60E-001 0.00E+000 3/496 357.80000 RA-226 7.91 0 001 5.90E-001 0.00E+000 b

3/4.96 357.80000 1-131 0.00E+000 0.00E+000 3.57E-002 3!4.96 357.80000 CS-134 0.00E+000 0.00E+000 3.72E-002 3'496 357.80000 CS-137 0.00E+000 0.00E+000 3.04E-002 3/496 357.80000 K-40 5.17E+000 7.60E-001 0.00E+000 4'896 343.20000 BL7 1.59E+000 2.80E-001 0.00E+000 t

4'8.96 343.20000 I-131 0.00E+000 0.00E+000 3.69E-002 4/ E96 343.20000 CS-134 0.00E+000 0.00E+000 4.12E-002 4/8.96 343.20000 CS-137 0.00E+000 0.00E+000 3.73E-002 4/8.96 343.20000 K-40 4.86E+000 6.90E-001 0.00E+000 t

803 - 0.6 hil SSE - SPOIL POND 1/I!96 452.40000 EE-7 1.00E+000 1.90E-001 0.00E+000 1/1.96 452.40000 1-131 0.00E4000 0.00E+000 3.00E-002

p em x

Semiannual Analysis Report CP&L Radiological Enviremental Monitoring Analysis Report 3ns/97 Sample Point SampleDate Quantity hotope Activity 2 SigesError LLD 803 - 0.6 hIl SSE - SPOIL POND ll 1,96 452.40000 CS-134 0.00E+000 0.00E+000 2.79E-002 I!196 452.40000 CS-137 0.00E+000 0.00E+000 2.71E-002 t/ I;96 452.40000 K-40 3.05E+000 5.10E401 0.00E+000 2/5,96 460.10000 BE-7 1.10E+000 2.10E-001 0.00E+000 2'5,96 460.10000 I-131 0.00E+000 0.00E+000 2.73 E-002 2/3.96 460.10000 CS-134 0.00E+000 0.00E+000 3.28E 002 2/5,96 460.I0000 CS-137 0.00E+000 0.00E+000 2.78E-002 2/5.96 460.10000 K-40 5.29E+000 6.70E-001 0.00E+000 3/496 362.50000 BE-7 1.68E+000 2.80E-001 0.00E+000 3/4 96 362.50000 1-131 0.00E+000 0.00E+000 332E-002 3/4 96 362.50000 CS-134 0.00E+000 0.00E+000 3.49E 002 3!4.96 362.50000 CS-137 0.00E+000 0.00E+000 3.00E-002 3/4 96 362.50000 K-40 5.80E+000 8.60E-001 0.00E+000 4' E96 337.90000 BE-7 1.22E+000 2.70E-001 0.00E+000 4'8.96 337.90000 1-131 0.00E+000 0.00E+000 3.62E-002 4'8.96 337.90000 CS-134 0.00E+000 0.00E+000 4.25E-002 4/8.96 337.90000 CS-137 0.00E+000 0.00E+000 3.84E-002 4'E96 337.90000 K-40 538E+000 7.80E-001 0.00E+000 Plant: BNP Analnis:GAhthlA hiedinTrpe: BROADLEAFVEGETATION Uudes: GRAhtS hiedia: SWEETCUhl i

800 - 0.7 kil NE -INTAKE CANAL 5/696 402.50000 K-40 337E+000 5.00E-001 0.00E+000 5/696 402.50000 CS-134 0.00E+000 0.00E+000 3.6 t E-002 5/6,96 402.50000 CS-137 0.00E+000 0.00E+000 2.9 t E-002 5/6.96 402.50000 1-131 0.00E+000 0.00E+000 3.42E-002 i

6/4 96 4563 0000 BE-7 2.03E 001 1.83E-001 0.00E+000 6/496 4563 0000 PB-212 2.96E-002 2.51E-002 0.00E+000 6/496 45630000 1-131 0.00E+000 0.00E+000 2.55E 002 6/4.96 4563 0000 CS-134 0.00E+000 0.00E+000 3.14E 002 6/496 4563 0000 CS-137 0.00E+000 0.00E+000 2.52E-002 6'4.96 4563 0000 K-40 3.17E+000 4.20E-001 0.00E+000 801 - 0.6 hll SW-DISC 11ARGE CANAL 5/6.96 495.50000 K-40 1.95E+000 4.50E-001 0.00E+000 i

5/6,96 495.50000 CS-134 0.00E+000 0.00E+000 2.57E-002 5/696 495.50000 CS-137 0.00E+000 0.00E+000 2.87E-002 5!6,96 495.50000 1-131 0.00E+000 0.00E+000 239E-002

& 4 96 418.90000 BE-7 335E-001 1.99E-001 0.00E+000 6/4 96 4I8.90000 PB-212 3.4IE-002 2.69E-002 0.00E+000 6/4.96 418.90000 1-131 0.00E+000 0.00E+000 2.95 E-002 6/496 418.90000 CS-134 0.00E4000 0.00E+000 3.02E-002

1. 4.96 418.90000 CS-137 0.00E+000 0.00E+000 2.81 E-002 6/496 418.90000 K-40 3.0lE+000 4 60E-001 0.00E+000 802 - 10.0 h!I-NOT SPECIFIED(CONTROL) 5/696 498.80000 K-40 3.87E+000 5.20E-001 0.00E+000

Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/18/97 Sample Point SampleDate Quantity Isotope Actidty 2 SigninError LIE 802 - 10.0 MI-NOT SPECIFIED(CONTROL) 5/696 498.80000 I-I31 0.00E+000 0.00E+000 2.46E-002

$!696 498.80000 CS-134 0.00E+000 0.00E+000 2.67E-002 5'696 498.80000 CS-137 0.00E+000 0.00E+000 2.75E-002 5/696 498.80000 RA-226 5.41E-001 3.52E-001 0.00E+000 6/4 96 4803 0000 BE 7 4.07E-001 1.56E-001 0.00E+000 6

C4.96 4803 0000 PB-212 4.90E-002 330E-002 0.00E+000 6496 48030000 1 131 0.00E+000 0.00E+000 2.62E-002

&4.96 48030000 CS-134 0.00E+000 0.00E+000 3.06E-002 6/4 96 48030000 CS-137 0.00E+000 0.00E+000 2.35E-002 6/4 96 48030000 K-40 3.29E+000 4.70E-001 0.00E+000 803 - 0.6 hil SSE - SPOIL POND

&496 505.90000 K-40 333E'000 4.10E-001 0.00E+000 5/696 517.50000 K-40 3.49E+000 4.90E-001 0.00E+000 5/6 96 517.50000 CS-134 0.00E+000 0.00E+000 2.65 E-002 5/6.96 517.50000 CS-137 0.00E+000 0.00E+000 2.81 E-002 5/6,96 517.50000 1-131 0.00E+000 0.00E+000 238E402 6/4.96 505.90000 BE-7 4.25E-001 1.57E-001 0.00E+000 6/4.96 505.90000 PB-212 2.77E402 2.59E-002 0.00E+000 6/4.96 505.90000 I-I31 0.00E+000 0.00E+000 2.26E-002 6/496 505.90000 CS-134 0.00E+000 0.00E+000 2.54E-002 6/4.96 505.90000 CS-137 0.00E+000 0.00E+000 2.05E-002 Plant: RNP Anaksis:CA315tA MedinType: BROADLEAF VECETATION Unks: GRAMS Medle: WAX MYRTLE 800 - 0.7 hl! NE -INTAKE CANAL 1/I/96 40330000 BE-7 1.15E+000 2.60E-001 0.00E+000 1/1.96 4033 0000 E 208 2.26E-002 2.22E-002 -

0.00E+000 1/ t/96 403 3 0000 PB-212 6.65 E-002 4.08E-002 0.00E+000 III196 403 30000 1-131 0.00E+000 0.00E+000 3.22E402 1/ t/96 40330000 CS-134 0.00E+000 0.00E+000 333E-002 1/I/96 40330000 CS-137 0.00E+000 0.00E+000 3.10E-002 1/106 40330000 K-40 2.0$ E+000 4.90E-001 0.00E+000 2/3.96 382.70000 BE-7 239E+000 3.20E-001 0.00E+000 l

2/5.96 382.70000 I-131 0.00E+000 0.00E+000 3.53E-002 2'5,96 382.70000 CS-134 0.00E+000 0.00E+000 3.67E-002 2/5.96 382.70000 CS-137 0.00E+000 0.00E+000 3.78E-002 2/5/96 382.70000 K-40 1.99E+000 6.00E-001 0.00E+000 3/4.96 385.70000 DE-7 1.92E+000 3.00E-001 0.00E+000 3/4.96 385.70000 RA-226 5.44E-001 5.03E.001 0.00E+000 3/4.96 385.70000 I-131 0.00E+000 0.00E+000 331E-002 3/4.96 385.70000 CS-134 0.00E+000 0.00E+000 3.21 E-002 3/4 96 385.70000 CS-137 0.00E+000 0.00E+000' 3.29E-002 3/4 96 385.70000 K-40 1.63E+000 4.10E-001 0.00E+00Q 4/896 380.50000 BE-7 3.47E+000 3.80E-001 0.00E+000

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Semiannual Analysis Report '

CP&L Radiological Enviromental Monitoring Analysis Report 3/18/97 Sample Point SampicDate Quantity Isotope Activity 2 SigmaError LLD 800 - 0.7 MI NE-INTAKE CANAL 4'196 380.50000 I-131 0.00E+000 0.00E+000 3.24E.002 4'8.96 380.50000 CS-134 0.00E+000 0.00E+000 3.01E 002 4'E96 380.50000 CS-137 0.00E+000 0.00E+000 3.41E.002 4!8.96 380.50000 K-40 2.16E+000 530E401 0.00E+000 5/696 457.40000 K-40 2.50E+000 5.10E-00I 0.00E+000 5/696 457.40000 CS-134 0.00E+000 0.00E+000 2.53E-002 5/696 457.40000 CS-137 0.00E+000 0.00E+000 2.87E-002 5/696 457.40000 I-131 0.00E+000 0.00E+000 2.41E402 6/4 96 430.10000 BE-7 6.84E@l 1.8tE-001 0.00E+000 6/496 430.10000 I-131 0.00E+000 0.00E+000 2.72E-002 6/496 430.10000 CS-134 0.00E+000 0.00E+000 2.88E-002 6/4 96 430.10000 CS-137 0.00E+000 0.00E+000 2.88E-002 6/496 430.10000 K-40 2.5 t E+000 5.00E 001 0.00E+000 801 - 0.6 MI SW - DISCllARGE CANAL 1/I96 398.10000 BE-7 9.14E-001 235E401 0.00E+000 1/I!96 398.10000 I-131 0.00E+000 0.00E+000 337E-002 li I/96 398.10000 CS-134 0.00E+000 0.00E+000 3.01E402 1/I!96 398.10000 CS-137 0.00E+000 0.00E+000 3.19E-002 1/196 398.10000 K-40 1.52E+000 4.90E-001 0.00E+000 2/5,96 389.00000 BE-7 1.90E+000 2.70E-001 0.00E+000 2/5.96 389.00000 I-131 0.00E+000 0.00E+000 2.88E-002 2/5,96 389.00000 CS-134 0.00E+000 0.00E+000 3.22E402 1/5.96 389.00000 CS-137 0.00E+000 0.00E+000 2.91E-002 2/5.96 389.00000 K-40 2.09E+000 4.90E-001 0.00E+000 3/4 96 433.90000 BE-7 I.61E+000 2.40E-001 0.00E+000 3/496 433.90000 AC-228 136E.00I.

6.60E-002 0.00E+000 3/4.96 433.90000 I-131 0.00E+000 0.00E+000 2.89E-002 3'4.96 433.90000 CS-134 0.00E+000 0.00E+000 2.74E 002 3/496 433.90000 CS-137 0.00E+000 0.00E+000 2.74E-002 3/496 433.90000 K-40 1.22E+000 4.00E-001 0.00E+000 4'8.96 380.50000 BE-7 2.02E+000 3.00E401 0.00E+000 4/196 380.50000 1-131 0.00E+000 0.00E+000 3.23E-002 4t 8.96 3803 0000 CS-134 0.00E+000 0.00E+000 3.89E-002 4'8.96 380.50000 CS-137 0.00E+000 0.00E+000 3.18E-002 4'8.96 380.50000 K-40 1.51E+000 5.00E-001 0.00E+000 5/696 498.70000 BE-7 8.76E-001 1.68E-001 0.00E+000 5/696 498.70000 I-131 0.00E+000 0.00E+000 2.40E-002 5/696 498.70000 CS-134 0.00E+000 0'.00E+000 234E.002 5/696 498.70000 CS-137 0 00E+000 0.00E+000 236E-002 5/6.96 498.70000 K-40 2.40E+000 4.60E-001 0.00E+ 000 6/496 418.40000 DE-7 5.46E-00I 1.91 E-001 0.00E+000 6/4.96 418.40000 I-131 0.00E+000 0.00E+000 2.74E-002

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_ _ _ _ _ _ _. _. - _= _ _ _ _ _ _ - - _ _ _ - _ - - - -.

m 1

Senniannual Analysis Report CP&L Radiological Enviremental Monitoring Analysis Report 3/18/97 Sample Point SampleDate Quantity Isotope Activity 2 SiginaError LIE 801 - 0.6 kil SW-DISCILARGE CANAL 6/4 96 418.40000 CS-134 0.00E+000 0.00E+000 2.90E-002 6!4 96 418.40000 CS-137 0.00E+000 0.00E+000 2.71E 002 6/496 418.40000 K-40 2.69E+000 5.80E-001 0.00E+000 3/4 96 433.90000 PB-214 4.73E402 4.10E402 0.00E+000 802 - 10.0 kII-NOT SPECIFIED(CONTROL)

I' I/96 362.50000 BE-7 1.20E+000 2.90E401 0.00E4000 1/1.96 362.50000 PB-212 3.79E-002 2.92E-002 0.00E+000 1/196 362.50000 BI-214 1.80E-001 7.80E-002 0.00E+000 I!196 362.50000 PB-214 9.98E-002 5.27E-002 0.00E+000 I/ I 96 362.50000 I-131 0.00E+000 0.00E+000 3.56E-002 1/1.96 362.50000 CS-134 0.00E+000 0.00E+000 3.56E-002 l/196 362.50000 CS-137 0.00E+000 0.00E+000 4.03E-002 i

I/ I.96 362 50000 K-40 1.65E+000 5.60E401 0.00E+000 i

y 2I596 404.00000 K-40 2.66E4000 4.60E-001 0.00E+000 2/5.96 404.00000 CS-134 0.00E+000 0.00E+000 3.48E402 l

2/5.96 404.00000 CS-137 0.00E+000 0.00E+000 3.12E-002

[

2/5.96 404.00000 I-131 0.00E+000 0.00E+000 3.40E-002 5

3/496 429.40000 BE-7 5.64E-001 5.49E-001 0.00E+000 3/4 96 429.40000 PB-214 1.39E 001 5.20E-002 0.00E+000 3/496 429.40000 RA-226 7.66E-001 3.%E-001 0.00E+000 3/496 429.40000 I-131 0.00E+000 0 00E+000 3.07E-002 I

3/496 429.40000 CS-134 0.00E+000 0.00E+000 3.37E-002 j

3/496 429.40000 CS-137 0.00E+000 0.00E+000 2.86E-002 3/496 429.40000 K-40 2.95 E+000 4.30E-001 0.00E+000

[

4/8.96 357.80000 BE-7 1.49E+000 2.60E-001 0.00E+000 4'8.96 357.80000 "II 208 3.16E-002 -

2.13E-002 0.00E+000

[

4/ E96 357.80000 I-131 0.00E+000 0.00E+000 3.24E-002

[

4/8.96 357.80000 CS-134 0.00E+000 0.00E+000 3.87E-002 L

4/8.96 357.80000 CS-137 0.00E+000 0.00E+000 3.47E-002

[

4!8,96 357.80000 K-40 9.06E-001 5.48E-001 0.00E+000 5/696 486.70000 BE-7 3.53E-001 1.29E-001 0.00E+000

[

5/696 486.70000 I-131 0.00E+000 0.00E+000 2.62E-002 5/696 486.70000 CS-134 0.00E+000 0.00E+000 2.53E-002 t.

5/6.96 486.70000 CS-137 0.00E+000 0.00E+000 2.95E-002 I

5/696 486.70000 K-40 2.55 E+000 4.00E-00I 0.00E+000 6/496 471.10000 BE-7 7.75E-001 2.14E-001 0.00E+000 l

6/496 471.10000 I-131 0.00E+000 0.00E+000 2.66E-002 6/496 471.10000 CS-134 0.00E+000 0.00E+000 2.92E-002 I

6/496 471.10000 CS-137 0.00E+000 0.00E+000 2.61 E-002 f

6/496 471.10000 K-40 1.92E+000 3.80E-001 0.00E+000 803 - 0.6 kil SSE-SPOIL POND 1/196 352.60000 K-40 3.27E+000 5.10E-001 0.00E+000 1/196 352.60000 CS-134 0 00E+000 0.00E+000 4.13 E-002

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Sentiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/18/97 i

Sample Point SampleDate Quantity Isotope

' ActMty 2 SigusaError LLD 803 - 0.6 hil SSE - SPOIL POND 1/196 352.60000 CS-137 0.00E+000 0.00E+000 3.41E-002 2/5;96 433.70000 BE-7 137E+000 2.50E-001 0.00E+000 2/5 96 433.70000 1-131 0.00E+000 0.00E+000 2.89E-002 2/5,96 433.70000 CS-134 0.00E+000 0.00E+000 2.92E402 2/5.96 433.70000 CS-137 0.00E+000 0.00E+000 3.01E-002 3/496 446.20000 BE-7 1.73E+000 2.50E 00I 0.00E+000 3/496 446.20000 1-131 0.00E+000 0.00E+000 2.92E-002 I

3/4 96 446.20000 CS-134 0.00E+000 0.00E+000 3.07E 002 3/496 446.20000 CS-137 0.00E+000 0.00E+000 230E402 418.96 369.70000 BE-7 1.54E+000 3.00E-001 0.00E+000 4'8,96 369.70000 1-131 0.00E+000 0.00E+000 3.40E402 4/896 369.70000 CS-134 0.00E+000 0.00E+000 3.10E 002 4/8.96 369.70000 CS-137 0.00E+000 0.00E+000 3.64E 002 4/8.96 369.70000 K-40 1.77E+000 4.40E-001 0.00E+000 1/ l>96 352.60000 I-131 0.00E+000 0.00E+000 3.6t E-002 5:6 96 459.00000 BE-7 4.45E-001 1.67E-001 0.00E4000 5!6.96 459.00000 1-131 0.00E+000 0.00E'+000 2.85E-002 5/6.96 459.00000 CS-134 0.00E+000 0.00E+000 3.18E-002 5/696 459.00000 CS-137 0.00E+000 0.00E+000 2.6BE-002

$1696 459.00000 K-40 2.60E+000 4.90E-001 0.00E+000 6'4 96 51330000 BE-7 7.62E-001 1.73 E-001 0.00E+000 6/4.96 51330000 1-131 0.00E+000 0.00E+400 2.69E-002 j

6/496 513.30000 CS-134 0.00E+000 0.00E+000 234E 002 l

6/496 51330000 CS-137 0.00E+000 0.00E+000 2.60E-002 I

6/496 51330000 K-40 2.4IE+000 4.10E-001 0.00E+000 j

2/5.96 433.70000 K-40 1.21E+000 4.70E-001 0.00E+000 3!4.96 446.20000 K-40 IJ9E+000 5.00E-001 0.00E+000 I

t Plant:BNP Analvsts:CAhlalA blediaTwe: FISH ANDINVERTEBRATES Units: CRAhtS hiedia: DOTTOh! FEEDERS

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701 - 5.5 hil SSW-BOTTOh! FEEDER AT DISCIIAR

$!2496 1087.60000 K-40 2.12E+000 630E-001 0.00E+000 5/2496 1087.60000 RA-226 3.94E 001 3.08E-001 0.00E+000 704 - DOTFOhf FEEDER-ATIANTICOCEAN(CON 5'2496 666.90000 K-40 2.68E+000 7.40E 001 0.00E+000 Plant:BNP Analysis:GAhlalA blediaType: FISil ANDINVERTEBRATES Units: GRAhlS hiedia: FREE SH15thlERS 700 - 5.5 h!!SSW-FREESWIhlklERS ATDISCllARO

$/24.96 I:38.50000 K-40 3.66E+000 6.10E-00I 0.00E+000 703 - FREE SWikthlERS - ATL-\\NTIC OCEAN (CONT 5/24.96 8113 0000 K-40 2.90E+000 6.50E-00I 0.00E+000 I

t Plant: BNP Analwis: GAhlalA AlediaTrpe: INVERTEBRATES Units: GRAhlS hiedia: INVERTEBRATES

{

702 - 5.5 hit SSW-SitBO AT DISC 11ARGE 5/2496 661.00000 K-40 2.00E+000 6.00E-001 0.00E+000 705 - SIIBO-ATLANT!C OCEAN (CONTROL) 5/2496 470.00000 K-40 2.26E+000 9.50E-00I 0 00E+000 t

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U Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/18/97 i

l Sample Point SampleDate Quantity Isotope Acthity 2 SigmaError LLD Plant: BNP Analye:GAh151A hie 44eT3pe: SHORELINE SEDl%IENT Units: GRA3tS l

500 - 4.9 kilSSW-DISCIIARGE 5.2496 1199.30000 PB-212 4.56E-002 1.89E-002 0.00E+000 5/24 96 1199.30000 PB-214 1.24E-001 3.50E-002 0.00E+000 Plant: BNP Analpis: CAhl%1A hiedimType: SURFACEWATER Units: LITERS 400 - 0.7 kil NE -INTAKE CANAL (CONTROL) 1/31/96 1.00000 K-40 1.94E+002 9.60E+001 0.00E+000 22996 1.00000 K-40 9.73E+001 9.6 t E+001 0.00E+000 331.96 1.00000 K-40 5.26E+002 3.90E+001 0.00E+000 3'3196 1.00000 RA-226 1.01E+002 4.00E+001 0.00E+000 33196 1.00000 TI-208 3.02E+000 1.64E+000 0.00E+000 43096 1.00000 K-40 3.20E+002 8.90E+001 0.00E+000 53196 1.00000 K-40 7.01E+002 1.08E+002 0.00E+000 630.96 1.00000 K-40 5.6tE+002 1.07E+002 0.00E+000 600.96 1.00000 RA-226 IJ2E@2 1.03 E+002 0.00E+000

[

401

- 4.9 hl! SSW - DISCIIARGE CANAL 10196 1.00000 K-40 6.29E+002 9.70E+001 0.00E+000 i

2'29.96 1.00000 K-40 1.95E+002 8.60E+001 0.00E+000 3'31.96 1.00000 K-40 1.78E+002 1.01E+002 0.00E+000 2/29-96 1.00000 TL-208 4.95E+000 4.92E+000 0.00E+000 400.96 1.00000 K-40 6.01E+002 1.07E+002 0.00E+000 I

f 400.96 1.00000 RA-226 1.39E+002 8.80E+001 0 00E+000 50196 1.00000 K-40 3.14E+002 1.10E+002 0.00E+000 5/3196 1.00000 RA-226 1.24E+002 8.90E+001 0.00E+000 600,96 1.00000 K-40 3.IIE+002 9.20E+001 0.00E+000 I

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Plant: BNP TLD in mR/QTR Sample Point SampleDate Dose 2 SigmaError l

I - 1.I kt! E-klOORE ST EXTENSION 8/15/96 1.04E+001 8.00E-001 1

11/15/96 9.90E+000 1.10E+000 2 - I.0 ht! ESE-hlOORE ST EXTENSION 8/15/96 1.14E+001 1.50E+000 2

11/15/96 1.01E+001 1.10E+000 3 - 0.9 ht! SE-htOORE ST EXTENSION 8/15/96 1.11E+001 8.00E 001 3

11/15/96 1.00E+001 1.00E+000 4 - 1.1 kil SSE-htOORE ST EXTENTION 8/15/96 1.00E+00i 1.00E+000 4

11/15/96 9.90E+000 130E+000 5 - 1.1 ht! S-LEONARD ST 8/15/96 1.02E+001 1.40E+000 5

1I/15/96 9.80E+000 1.00E+000 6 - I.0 ht! S - BEhiCO POWER llNE 8/15/96 1.22E+001 9.00E 001 6

II/ISS6 9.40E+000 1.00E+000 7 - 1.0 kil SW-IIWY 87 AT RIGIIT-OF WAY 8/15/96 1.16E+001 1.20E+000 7

1I/15/96 1.05E+001 8.00E-001 8 - L2 ht! W-1IWY 87 8/15/96 131E+001 6.00E 002 8

11/15/96 9.50E+000 8.00E-001 9 - I.0 ht! WNW-BETIIELCIR'RCII RD 8/15/96 9.20E+000 1.50E+000 9

11/15/96 9.60E+000 130E+000 10 - 0.9 hil NW-BETIIEL CHURCll RD 8/15/96 9.60E+000 1.50E+000 10 11/15/96 8.7GE+000 130E+000 11 - 0.9 ht! NNW-BETIIEL CIIURCll RD 8/15/96 134E+001 1.30E+000 11 11/15/96 1.04E+001 9.00E 00t 12 - 1.0 ht! N-BETIIEL CI!URCII RD 8/15/96 1.11E+001 1.00E+000 12 11/15/96 1.09E+001 9.00E-001 13 - 1.2 kil NNE -BETIIEL CHURCII RD 8/15/96 1.25E+001 1.40E+000 13 11/15/96 9.10E+000 8.00E 001 14 - 0.5 hil NE -INTAKE CANAL 8/15/96 1.12E+001 9.00E-001 14 11/15/96 1.08E+001 8.00E-001 15 - 0.9 ht! ENE -INTAKE CANAL 8/l5/96 1.10E+001 1.40E+000

[

l5 11/15/96 1.1SE+001 2.40E+000 16 - 1.0 ht! WSW-DISCIIARGE CAN AL 8/15/96 9.70E+000 1.50E+000 16 11/15/96 9.90E+000 1.90E+000 I

17 - I.5 ht! ESE -PFI7ER PROPERTY 8/15/96 131E+001 1.90E+000 17 11/15/96 1.11E+001 8.00E@l 18 - 17 ht! SE - PFlZER PROPERTY 8/15/96 8.00E+000 1.00E+000 la 11/15/96 8.70E+000 1.10E+000 8.00'-001 20 - 2.0 ht! S-hlOORE ST 8/15/96 1.12E+001 E

20 11/15/96 8.10E+000 9.00E-001 21 - 2.9 h!I SSW-WEST ST AT SEA CAPTAIN 8/15/96 1.22E+001 1.00E+000 21 11/15/96 9.70E+000 8.00E-00I

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Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/18/97 Plant: BNP TLD in mR/QTR Sample Point SampleDate Dese 2 SigmaError 22 - 53 ht! SW-CASWELL BEACII RD 8/15/96 1.27E+001 1.50E+000 22 11/15/96 1.02E+001 130E+000 23 - 4.6 EIIWSW-NEAR AIRPORT 8/15/96 1.07E+001 1.40E+000 23 11/15/96 830E+000 1.50E+000 24 - 3.0 kil W-II%T 211 8/15/96 930E+000 1.10E+000 24 11/15/%

9.40E+000 7.00E-001 25 - 8.7 htI WNW - ANTIOCil BAPTIST CIIURCil 8/l5/96 1.16E+001 9.00E 001 25 11/15/96 1.09E+00 t i30E+000 l

26 - 5.9 kil NW - W BOILING SPRINGS RD 8/15/96 IJ2E+001 130E+000 26 11/15/96 1.07E+001 8.00E-001 27 - 5.0 hfI NNW-IIWY l33 8/15/96 830E+000 1.20E+000 v

27 11/15/96 830E+000 7.00E-00I 28 - 4.2 hilNW-AT SOUTil BRUNSWICK 11S 11/15/96 9.50E+000 1.20E+000 2

28 8/15/96 9.80E+000 1.00E+000 f

29 - 2.6 kil SSW-SOLTIIPORT ELEh!ENTARY SCIIOOL 11/15/96 8.70t+000 7.00E-001 29 8/15/96 7.90E+000 9.00E-001 30 - 2.0 hil NE-SUNNY POINT Ef0T 11/15/96 1.03E+001 8.00E-001 30 8/15/96 139E+001 1.50E+000 31 - 2.6 ht! ENE - SUNNY POINT htOT I1/15/96 1.03E+001 8.00E-001 31 8/15/96 1.40E+001 1.80E+000 32 - 5.7 hil ENE.FT FISilER AFB IIOUSING lI/15/96 1.19E+00 t 130E+000 32 8/15/96 1.19E+001 1.40E+000 33 - 4.0 h!! E-FERRY SLIPIN NEWIIANOVER CO 11/15/96 8.90E+000 9.00E-001 33 8/15/96 9.80E+000 130E+000 34 - 5.5 EII ENE - FT FISIIER hfUSEUht i1/15/96 9.80E+000 8.00E-001 i

34 8/15/96 1.13E+001 1.10E+000 35 - 7.5 hfI SSE - BALD llEAD ISLAND 11/15/96 8.20E+000 1.10E+000 35 8/15/96 tile +001 6.00E-001 36 - 93 kil NE-CAROLINA BEACII i1/15/96 8.90E+000 8.00E 001 36 8/15/96 9.00E+000 1.10E+000 37 - 5.5 Kf! NW-BOILING SPRINGS LAKES 11/15/96 8.80E+000 9.00E-001 5

37 8/15/96 9.40E+000 1.70E+000 38 - u.0 ktl W-SUNSETIIARBOR

-11/15/96 8.80E+000 1.20E+000 38 8/15/96 1.20E+001 1.70E+000 39 - 53 h!!SW-YAITON BEACllCITYIIALL i1/15/96 9.80E+000 1.40E+000 39 8/15/96 930E+000 130E+000 40 - 6.9 ht! WSW-LONO BEACII CITY IIALL 11/15/96 9.50E+000 9.00E-001 40 8/15/96 930E+000 8.00E-001 72 - 8.5 htI WSW-OCEAN CREST PIER 11/15/96 l.I2E+001 1.0dE+000 75 - 4.5 ht! S-rF CASWELL BAPTIST ASSEhfBLY II/15/96 1.14 E+001 1.50E+000 t

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CP&L Radiological Enviremental Monitoring Analysis Report 3/1s/97 Plant: BNP TLD in mR/QTR Sample Point SampleDate Dese 2 SignsErrw 75 - 4.5111S-FTCASWElL BAPTIST ASSEh1BLY 8/15/96 1.54E+001 6.00E-001 l

77 - 3.3 htiSSE-BALDIIEADIStAND 11/15/96 8.70E+000 1.00E+000 77 8/15/96 9.70E+000 1.70E+000 78 - 10.0 Aff NNE-IIWY 133 AT SR I521 11/15/96 9.20E+000 9.00E-001 78 8/15/96 1.18E+001 1.00'E+000 79 - 9.S hilN-SR 1539 ATSR 152I 11/15/96 9.80E+000 8.00E-001 79 8/15/96 1.15 E+001 8.00E-001

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81 - 10.0 ht! WNW-htIDWAY RD AT SR 1508 11/15/96 1.03E+001 1.00E+000 81 8/15/96 1.35E+001 1.00E+000 i

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O Sentiannual Analysis Report CP&L Radiological Envirosnental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Quantity Emciency ActMay 2 SigmaError LID Flmat: BNP Analysis: BETA MedinType: AIR PARTICULATE CUMETERS 200 - I.0 MI SW-VISITORS CENTER 7/I96 287.60000 3.76E401 2.04E402 3.29E-003 0.00E+000 7/196 297.20000

.3.76E 001 1.64E-002 3.IIE-003 0.00E+000 t

7/15,96 243.80000 3.76E-001 1.16E 002 3 IIE-003 0.00E+000 12/2,96 260.20000 3.76E-001 1.53E402 3.50E-003 4.25E-003 10/7,96 266.20000 3.76E-001 1.24E-002 3.05E-003 3.63E-003 10'14.96 26030000 3.76E-001 1.56E-002 3.26E403 3.64E403 l

10/21/96 259.50000 3.76E 001 2.69E-002 3.92E403 3.85E-003 l

10/2&96 273.70000 3.76E-001 2.18E-002 3.60E403 3.81E-003 11/496 257.80000 3.76E-001 1.88E-002 3.66E 003 4.18E-003 II/II/96 266.00000 3.76E-001 1.21E-002 3.00E 003 3.56E-003 1Iil&96 253.90000 3.76E 001 2.0I E-002 3.67E-003 4.01E-003 1I/25,96 259.10000 3.76E401 1.77E-002 3.44E 003 3.78E-003 12/9,96 2563 0000 3.76E-001 2.08E402 3.65E-003 3.87E 003 12/1696 248.70000 3.76E401 1.87E-002 3.56E,.003 3.86E-003 12.23/96 263.00000 3.76E-001 138E-002 3.20E 003 3.75E-003 12/30.96 260.80000 3.76E 001 1.49E-002 330E 003 3.83E443 7/22.96 291.50000 3.76E-001 1.29E-002 2.97E-003 0.00E+000 7/29.96 221.00000 3.76E-001 1.18E-002 334E-003 0.00E+000

[

8.'1696 288.70000 3.76E-001 2.79E-002 3.61E-003 0.00(+000 f

8/5s96 268.10000 3.76E-001 1.41E-002 2.95E 003 0.00E+000 8/12/96 297.00000 3.76E-001 1.62E-002 3.14E-003 0.00E+000 8/19-96 279.20000 3.76E-001 1.41E-002 2.94E-003 0.00E+000

{

9/2.96 284.00000 3.76E-001 2.92E-002 3.66E 003 0.00E+000 9/9.96 248.60000 3.76E-001 139E-002 3.40E 003 0.00E+000 9/1696 26430000 3.76E-001 1.19E-002 3.15E-003 0.00E+000 9/23.96 276.40000 3.76E-C01 2.07E-002 3.48E.003 0.00E+000 9/30.96 264.70000 3.76E-001 2.19E-002 3.65 E-003 0.00E+000 201 - 0.6 MI NE - PMAC 7/1.96 284.60000 3.76E-001 1.78E-002 3.18E-003 0.00E+000 I

7/8.96 290.70000 3.76E-001 I.86E-002 3.27E-003 0.00E+000 7/15.96 274 30000 3.76E-001 135E-002 2.96E-003 0.00E+000 II/I1.96 283.10000 3.76E-00I I36E-002 2.96E-003 335E-003 i

12/196 277.20000 3.76E-001 1.51E-002 333E403 3.99E-003 F

10/796 283.70000 3.76E-001 1.59E-002 3.I I E-003 3.4 t E-003 10/1496 279.20000 3.76E-001 1.46E-002 3.04E403 339E-003 10/21.96 277.80000 3.76E 001 2.8 t E-002 3.80E-003 3.59E-003 10/28.-96 290.00000 3.76E-001 2.57E-002 3.64E-003 3.59E-003 11/4,96 276.20000 3.76E-001 1.65 E-002 336E-003 3.90E-003 l

1I/I&96 271.50000 3.76E-00 t

. 2.11 E-002 3.55 E-003 3.75E-003 l

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Semiannual Analysis Rennt CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 E

Semple Point SampleDele Quantity Emciency Activity 2 SiginaError L1D 201 - 0.6 kIINE - PhlAC 11!25.96 276.80000 3.76E401 1.48E-002 3.12E 003 3.54E-003 12/9 96 275.60000 3.76E-001 1.87E-002 336E403 3.60E-003 12/1696 276.20000 3.76E-001 1.46E 002 3.08E-003 3.48E403 12'2396 273.20000 3.76E 001 139E-002 3.11E 003 3.61E 003 12/30,96 278.10000 3.76E-001 1.26E 002 3.01E-003 3.59E 003 7/22 96 284.10000 3.76E 001 1.21E-002 2.98E 003 0.00E+000 7'2996 297.70000 3.76E401 I A0E 002 2.80E 003 0.00E+000 82696 28930000 3.76E-001 2.48E-002 3.47E-003 0.00E+000 f

8/5.96 276.900M 3.76E-001 1.65E 002 3.02E-003 0.00E+000 I

8'I296 297.40000 3.76E 001 1.88E-002 3.27E-003 0.00E+000 E'19.96 290 40000 3.76E 001 1.41E 002 2.86E 003 0.00E+000

[

9'296 28030000 3.76E-001 2.66E-002 3.57E-003 0.00E+000 I

[

9/9 96 287.70000 3.76E-001 1.57E-002 3.15E-003 0.00E+000 9/16.96 285.70000 3.76E-001 1.07E-000 2.90E-003 0.00E+000 9 23.96 298.90000 3.76E-001 2.05E-002 3.29E-003 0.00E+000 930.96 281.70000 3.76E401 2.21E-002 3.50F-003 0.00E+000 I

202 - 1.0 MI S - St'B5TATION ON CONSTRtt' TION R 7/I96 298A0000 3.76E-001 1.80E 002 3.08E403 0.00E+000 7/ E96 305.40000 3.76E 001 1.76E-002 3.11E403 0.00E+000 7/13/96 287.40000 3.76E-001 1.15E-002 2.74E-003 0.00E+000 12/2.96 27030000 3.76E-001 1.68E402 3.48E-003

. 4.09E403 10/7/96 275.50000 3.76E-001 1.60E 002 3.18E-003 3.51E-003 10/1496 269.20000 3.76E-001 134E-002 3.05E-003 3.52E-003 10/2196 267 50000 3.76E-001 2.88E402 3.93E-003 3.73E-003 10/2E96 28330000 3.76E-001 2.72E-002 3.77E 003 3.68E 003 i

11/496 268.90000 3.76E-001 IS S 002 3.43E 003 4.00E 003 11/11/96 276.10000 3.76E401 I A8E 002 3.08F,003 3.43E-003 1 til8.96 265.80000 3.76E 001 1.77E 002 3 43E-003 3.83E 003 11/23 96 269.50000 3.76E-071 1.57E402 3.24E 003 3.64E 003 12f 996 26630000 3.76E-001 2.20E-002 3.61E-003 3.73E 003 I2'16.96 263.70000 3.76E-001 1.74E-002 335E-003 3 64E-003 I

12/2396 261.60000 3.76E-001 1.60E-002 333E-003 -

3.77E-003 l

12/30.96 266 70000 3.76E-001 1.53E-002 3.26E-003 3.74E-003 7/22.96 2953 0000 3.76E-001 9.90E-003 2.77E-003 0.00E+000 7/29.96 3063 0000 3.76E-001 1.53E-002 2 82E-003 0.00E+000 8/26.96 281.00000 3.76E-001 2.41E-002 3.51 E-003 0.00E+000 8/5/96 289.80000 3.76E-001 1.72E-002

~

2.97E-003 0.00E+000 i

8/12.96 290.20000 3.76E-001 1.77E-002 3.27E-003 0.00E*000 l

8719.96 284.40000 3.76E-001 137E-002 188E-003 0.00E+000 9/2.96 275.70000 3.76E-001 2.52E-002 3.54E-003 0 00E+000 9/9.96 280.70000 3.76E-00I

.1.13E-002 2.96E.003 0.00E+000 3

O pU Semiannual Analysis Report CP&L Radiological Enviremental Monitoring Analysis Report 3/17/97 i

Sample Point SampleDate Quantity Efficiency ActMay 2 SigmaError LLD 202 - 1.0 Kil S - SUBSTATION ON CONSTRUCTION R 9'l696 279.40000 3.76E-001 1.13E-002 2.98E.003 0.00E+000 9.7396 285.80000 3.76E-001 2.12E-002 3.42E-003 0.00E+000 93096 272.90000 3.76E 001 2.55E402 3.74E-003 0.00E+000 203 - 23 hil SSW-SOUTIIPORT SUBSTATION 7!l96 300.10000 3.76E-001 1.90E-002 3.12E-003 0.00E+000 7'8 96 308.70000 3.76E-001 1.68E-002 3.04E-003 0.00E+000 7/15.96 2713 0000 3.76E401 1.47E-002 3.05E403 0.00E+000 12'2.96 2723 0000 3.76E401 1.43E-002 333E403 4.06E-003 10'7 96 280.20000 3.76E-001 2.00E 002 335E.003 3.45E-003 10/14 96 274.00000 3.76E-001 132E 002 3.00E-003 3.46E-003 10'21.96 27330000 3.76E 001 2.90E-002 3.89E-003 3.65E 003 100&96 276.40000 3.76E-001 2.78E402 3.86E-003 3.77E-003 11/4 96 283.00000 3.76E-001 2.08E-002 3.52E 003 3.80E-003 11/1196 2783 0000 3.76E-001 1.67E402 3.17E-003 3.40E-003 11/1896 265.90000 3 76E-001 1.73E-002 3.41E-003 3.83E-003 11/25.96 270.50000 3.76E-001 2.15E-002 3.53E403 3.62E-003 12/9 96 268.10000 3.76E-001 2.23E-002 3.61E-003 3.70E-003 12/16.96 268.90000 3.76E 001 1.66E-002 3.26E-003 3.57E-003 12'2396 266.00000 3.76E-001 1.44E402 3.20E-003 3.7 t E-003 12'30.96 271.00000 3.76E-001 1.56E-002 3.24E-003 3.69E 003 7/2296 302.00000 3.76E 001 1.13E-002 2.81E-003 0.00E+000 7/2996 311.20000 3.76E-001 1.4IE 002 2.72E-003 0.00E+000 It"2696 283.70000 3.76E-001 2.64E-002 3.59E-003 0.00E+000 8/5,96 2953 0000 3.76E-001 1.44E-002 2.77E-003 0.00E+000 8'1196 290.20000 3.76E-001 1.78E-002 3.28E-003 0.00E+000 8/19.96 290.00000 3.76E-001 1.08E-002 2.67E 003 0.00E+000 i

9/2,96 2793 0000 3.76E-001 2.87E-002 3.68E-003 0.00E+000 9/9.96 206.60000 3.76E-001 1.54E 002 4.02E-003 0.00E+000 9/16h6 279.90000 3.76E-001 1.08E-002 2.95 E-003 0.00E+000 9'23 96 29230000 3.76E 001 2.23E-002 3.42E-003 0.00E+000 9/3096 279.20000 3.76E-001 2.19E 002 3.5 IE-003 0.00E+000 204 - 23.0 El! NME - SlJITON PIANT (CONTROL) 7/1.96 290.00000 3.76E-001 1.80E402 3.14E 003 0.00E+000 7/896 3003 0000 3.76E-00I 1.62E-002 3.07E-003 0.00E+000 7/1596 279.50000 3.76E-00I I35E 002 2.91E-003 0.00E+000 10/796 272.80000 3.76E-001 2.04E-002 3.43E-003 3.54E-003 10'14.96 270.80000 3.76E-001 1.26E402 ~

2.99E 003 3.50E-003 I

10/21.96 2763 0000 3.76E-001 2.69E-002 3.76E-003 3.61E-003 I

107896 27730000 3.76E-001 236E-002 3.65 E-003 3.76E-003 1I/496 274.40000 3.76E-001 2.03E-002 3.57E-003 3.92E-003 I1'lI 96 272.70000 3.76E-001 13IE-002 3.01 E-003 3.47E-003 11/1896 262.10000 3.76E-001 1.92E-002 3.55E-003 --

3.88E-003 4

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Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report.

3/17/97 Sample Point SampleDate Quentity Efficiency Activity 2 SiepneError LIE 204 - 23.0 hlI NNE - SUTTUN PIANT (CONTROL) 11'25.96 275.60000 3.76E-001 1.50E402 3.14E 003 3.56E403 l

11'296 270.50000 3.76E401 1.60E402 3.44E403 4.09E-003 E

12/9 96 266.50000 3.76E 001 2.14E-002 3.58E-003 3.72E-003 12/16,96 266.50000 3.76E 001 1.80E.002 335E-003 3.60E-003 12/23.96 262.60000 3.76E-001 1.95E 002 3.5 IE-003 3.76E-003 12/3096 272.90000 3.76E-001 1.62E 002 3.26E 003 3.66E-003 7/2196 288.10000 3.76E 001 1.06E-002 2.87E-003 0.00E+000 7/29 96 287.90000 3.76E-001 1.52E 002 2.94E433 0.00E+000 i

5.26.96 282.60000 3.76E-001 2.65E-002 3.60E403 0.00E+000 8/5/96 293.60000 3.76E-001 1.75E402 2.%E 003 0.00E+000 8'12.96 275.00000 3.76E-001 2.06E-002 3.55E-003 0.00E+000 8'19 96 282.80000 3.76E 001 1.2 t E-002 2.80E 003 0.00E+000 l

9/196 287.40000 3.76E-001 2.76E-002 3.56E-003 0.00E+000 9/9 96 277.50000 3.76E 001 1.23E402 3.05E-003 0.00E+000 9/16.96 275.00000 3.76 0 001 1.29E-002 3.IIE-003 0.00E+000 9/23,96 275.80000 3.76E 001 2.42E-002 3.65E 003 0.00E+000

[

9/30.96 277.80000 3.76E-001 2.07E-002 3.47E-003 0.00E+000 205 - 0.6 hII SSE. SPOIL POND 7/I/96 306.00000 3.76E 001 1.895002 3.08E-003 0.00E+000 I

7/8.96 317.90000 3.76E-001 1.73E-002 3.01E-003 0.00E+000 f

7/15.96 288 60000 3.76E-001 1.46E-002 2.91E-003 0.00E+000 10/7.96 280.90000 3.76E 001 1.700 002 3.19E-003 3.44E-003 10/1496 277.10000 3.76E 001 1.52E-002 3.09E-003 3.42E 003 103196 275.90000 3.76E 001 2.41E 002 3.64E 003 3.62 0 003

[

103196 287.40000 3.76E-001 2.40 5 002 3.58E-003 3.62E-003 l

1I/4.96 276.10000 3.76L001 I.76E-002 3.42E 003 3.90E-003 i

11/11/96 280.00000 3.76E-001 1.32E402 2.99E-003 3.48E-003 11/18.96 252.10000 3.76E-001 2.17E 002 3.77E 003 4.03 E-003 11/25,96 274.10000 3.76E-001 1.4C5 002 3.10E-003 3.57E-003 12/2.96 268.50000 3.76E-001 1.8 t E-002 3.57E-003 4.12E-003 12/996 274.20000 3.76E-001 1.83E402 335E-003 3.62E-003

[

12/1696 267.10000 3.76E-001 1.65E-002 3.27E-003 3.60E-003 12'23 96 257.70000 3.76E401 1.59E-002 3.36E 003 3.83E-003 12'30.96 275.90000 3.76E-001 1.43E.002 3.13E 003 3.62E-003 y

7/2196 301.10000 3.76E-001 1.25E-002 2.88E-003 0.00E+000 7/29 96 3I6.70000 3.76E 001 1.63E-002 2.8IE-003 0 00E+000 8'26,96 281.50000 3.76E-001 2.82E-002 3.69E-003 0.00E+000 8/596 301.90000 3.76E-001 1.62E-002 2.83E-003 0.00E+000 I

8/12 96 285.80000 3.76E-001 1.81 E-002 333E-003 0.00E+000 81996 285.80000 3.76E-001 133E-002 2.85E-003 0.00E+000 j

972.96 273.80000 3.76E-001 2.79E-002 3.68E-003 0.00E4000 l

5 i

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Sesniennual Analysis Report CP&L Radiological Enviremental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Quentity Emciency Activity 2 SiginaError IJD 205 - 0.6 hl! SSE - SPOIL POND 9/9 96 13630000 3.76E401 8.97E-003 5.20E 003 0.00E+000 9/16.96 189.50000 3.76E401 1.42E-002 4.25E-003 0.00E+000 9 ~Z396 291.50000 3.76E401 233E402 3.48E-003 0.00E+000 9/30.96 278.60000 3.76E-001 2.76E-002 3.79E 003 0.00E+000 i

Plesd: BNP Analnis: IODINE hledleType: AIRCARTRIDGE CUhlETERS 200 - 1.0 kil SW-VISITORS CENTER 7/1,96 287.60000 0.00E+000 0.00E+000 2.12E-002 71896 297.20000 0.00E+000 0.00E+000 2.70E-002 10/796 266.20000 4.10E-002 I

10:1496 26030000 4.68E-002 10'21.96 259.50000 3.53E-002 10'28.96 273.70000 4.llE 002

'I 11/496 257.80000 4.17E 002 ItilI 96 266.00000 4.17E 002 It!!896 253.90000 3.13E 002 II!25 96 259.10000 3.03E-002 12/2.96 260.20000 2.57E402 1

11'996 25630000 3.99E402 12/16.96 248.70000 4.24E-002 11'23.96 263.00000 3.08E-002 t

11'3096 260.80000 4.55E-002 l

3.50'-002 7!!$196 243.80000 0.00E+000 0.00E+000 E

7/22/96 291.50000 0.00E+000 0.00E+000 4.25E-002 7/29,96 221.00000 0.00E+000 0.00E+000 438E 002 8/5/96 268.10000 0.00E+000 0.00E+000 3.27E-002 i

8/12.96 297.00000 0.00E+000 0.00E+000 2.49E-002 8/19,96 279.20000 0.00E+000 0.00E+000 3.20E-002 I

8/26.96 288.70000 0.00E+000 0.00E+000 334E 002 9/2.96 284.00000 0.00E+000 0.00E+000 332E 002 9'9 96 248.60000 0.00E+000 0.00E+000 4.43E 002 9/1696 26430000 0.00E+000 0.00E+000 4.19E-002 9/2396 276.40000 0.00E+000 0.00E+000 4.6IE-002 9'3096 264.70000 0.00E+000 0.00E+000 3.74E 002 201 - 0 6 hil NE - PhlAC 7/I/96 284.60000 0.00E+000 0.00E+000 3.78E-002 I

7/ E96 290.70000 0.00E+000 0.00E+000 3.82E-002 10/7,96 283.70000 3.28E-002 10/14.96 279.20000 2.44E-002 10/2196 277.80000 412E-002 10;2896 290.00000 3.26E-002 III496 276.20000 4.58E-002 6

v s

i l

Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 l

H i

Saniple Point SainpleDate Quantity Efficiency ActMty 2 SigensError IJE

[

201 - 0.6 kil NE-PhlAC i1/11.96 283.10000 4.66E-002 11/1896 271.50000 337E402 11/25/96 276.80000 4.08E-002 12/196 277.20000 33IE402 12'9.96 275.60000 4.0lE 002 12/1696 276.20000 4.44E402 12/23.96 273.20000 4.00E402 1230.96 278.10000 4 63E 002 7/1596 27430000 0.00E+000 0.00E+000 4.18E-002 f

7/2196 284.10000 0.00E+000 0.00E+000 3.93E402 7/29 96 297.70000 0.00E+000 0 00E+000 3.46E402 8'596 276.90000 0.00E+000 0.00E+000 2.71E-002 i

8/12.96 297.40000 0.00E+000 0.00E+000 3.29E 002 I

8/1996 290.40000 0.00E+000 0.00E400 337E-002 I

8/26,96 28930000 0.00E+000 '

O.00E+000 3.55E-002 9/2.96 28030000 0.00E+000 0.00E+000 2.88E-002 9/9.96 287.70000 0.00E+000 0.00E+000 3.86E 002 9/16.96 285.70000 0.00E+000 0.00E+000 3.84E 002 9.23.96 298.90000 0.00E+000 0.00E+000 3.49E 002 j

930.96 281.70000 0.00E+000 0.00E+000 2.86E 002 202 - 1.0 hil S - SUBSTATION ON CONSTRUCTION R 7/1.96 298.40000 0.00E+000 0.00E+000 3.12E-002 7/ E96 305.40000 0.00E+000 0.00E+000 4.12E.002 10/7.96 275.50000 3.76E-002 10/1496 269.20000 5.08E-002 i

10/21/96 267.50000 4.03E-002 I

f 107196 28330000 4.20E 002 Iil496 268.90000 434E 002 11/11.96 276.10000 4.02E-002 I1/18.96 265.80000 5.11E-002 II/25/96 269.50000 3.49E 002 12/2.96 27030000 433E-002 12/996 26630000 2.80E-002 f

12/1696 263.70000 3.09E-002 127396 261.60000 3.79E-002 I

12/3096 266.70000 4.07E-002 7/15.96 287.40000 0.00E+000 0.00E+000 3.63 E-002 i

7/22.96 295.30000 0 00E+000 0.00E+000 3.%E-002 7/29<96 3063 0000 0.00E+000 0.00E+000 4 65E-002 I

8/5.96 289.80000 0.00E+000 0.00E+000 3.4SE-002 8/12.96 290.20000 0.00E+000 0.00E+000 4.73 E-002 7

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Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Quantity EfHelency ActMty 2 SigmaError.

LED 202 - I.0111 S - SUBSTATION ON CONSTRl'CTION R 8'19.96 284.40000 0.00E+000 0.00E+000 2.51E-002 8"2696 281.00000 0.00E+000 0.00E+000 4.03E 002 912,96 275.70000 0.00E+000 0.00E+000 4.92E-002 9/9.96 280.70000 0.00E+000 0.00E+000 4.36E402 9/1696 279.40000 0.00E+000 0.00E+000 3.41E-002 9.23,96 285.80000 0.00E+000 0.00E+000 3.18E-002 93096 272.90000 0.00E+000 0.00E+000 3.94E-002 203 - 2.3 kil SSW - SOUT11 PORT sui 3 STATION 7/I96 300.10000 0.00E+000 0.00E+000 2.50FA02 7/8.96 308.70000 0.00E+000 0.00E+000 2.93E-002 1017.96 280.20000 3.86E-002 10/I4.96 274.00000 2.97E-002 i

10121.96 27330000 3.13E-002 10/2896 276.40000 4.03E 002 II/ 4.96 283.00000 3.24E-002 11Il196 27830000 3.84E 002 IIil8.96 265.90000 2.7IE-002 11/25 96 270.50000 4.19E-002 12/2,96 27230000 3.79E 002 12/9.96 268.10000 4.92E 002 12/1696 268.90000 3.26E-002 12/2396 266.00000 431FA02 12/30.96 27I.00000 4.11E-002 7/15,96 27130000 0.00E+000 0.00E+000 3.7t E-002 r

7/22.96 302.00000 0.00E+000 0.00E+000 4.40E-002 7/29.96 311.20000 0.00E+000 0 00E+000 2.80E-002 8/5,96 295.30000 0.00E+000 0.00E+000 2.62E-002 8/12.96 3 0.70000 0.00E+000 0.00E+000 3.73E-002 E'19-96 290 00000 0.00E+000 0.00E+000 2.58E-002 f

876.96 283.70000 0.00E+000 0.00E+000 2.80FA02 9/2.96 27930000 0.00E+000 0.00E+000 1.83E 002 f

9/9.96 206.60000 0.00E+000 0.00E+000 '

4.93E-002

[

9/1696 279.90000 0.00E+000 0.00E+000 3.09E-002 9/2396 29230000 0.00E+000 0.00E*000 4.28E-002 930.96 279.20000 0.00E+000 0.00E+000 3.42E-002 I

204 - 23.0 hil NNE - SL7 TON PIANT (CONTROL) 7/ !!96 290.00000 0.00E+000 0.00E+000 2.42E 002 7/ E96-3003 0000 0.00E+000 0.00E+000 3.16E-002 10/7/76 272.80000 5.12E-002 10/1496 270.80000 3.50E-002 10/21/96 2763 0000 3.33 E-002 10'2&96 27730000 3.7I E-002 8

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Semiannisal Analysis Repen CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Sansple Point SampleDate Quantity Efficiency ActMty 2 SigmaErrw LLD 204 - 23.0 hil NNE - SUTTON PLANT (CONTROL) 1I/4 96 274.40000 3.69E-002 II/1196 272.70000 4.24E402 II/tE96 262.10000 237E402 1!!25.96 275.60000 3.02E-002 12/196 270.50000 3.92E402 I2/996 266.50000 3.6IE 002 12'l696 266.50000 3.87E 002 12/2396 262.60000 3.97E 002 12.30/96 272.90000 3.64E-002 7/15,96 279.50000 0.00E+000 0.00E+000 3.53E 002 7/2196 288.10000 0.00E+000 0.00E+000 436E 002 7/2996 287.90000 0.00E+000 0.00E+000 4.27E-002 8/5.96 293.60000 0.00E+000 0.00E+000 339tAsui l

8/12.96 275.00000 0.00E+000 0.00E+000 336E-002 8'19.96 282.80000 0.00E+000 0.00E+000 2.78E-002 8'26/96 282.60000 0.00E+000 0.00E+000 2.43E-002 9/196 287.40000 0.00E+000 0.00E+000 3.29E 002 9/9.96 277.50000 0.00E+000 0.00E+000 5.04E-002 9/1696 275.00000 0.00E+000 0.00E+000 2.73E-002 l

9'23 96 275.80000 0.00E+000 0.00E+000 3.58E-002 9.3096 277.80000 0.00E+000 0.00E+000 4.11E-002 205 - 0.6 kil SSE-SPott POND 7/196 306.60000 0.00E+000 0.00E+000 4.11E-002 7/8.96 317.90000 0.00E+000 0.00E+000 3.52E-002 I

10!7.96 280.90000 4.84E-002 10/1496 277.10000 3.54E-002

[

102196 275.90000 430E-002 f

10'2896 287.40000 430E-002 I1/496 276.10000 4.44E-002 i

11/11/96 280.00000 4.01E 002 I

II/IE96 252.10000 5.02E-002 7

II/25.96 274.10000 3.98E-002

[

12'2/96 268.50000 5.10E-002 12/9.96 274.20000 3.65E-002 12/16.96 267.10000 4.43E-002 11'2396 257.70000 3.73E-002 12'3096 275.90000 4.18E-002 f

7/15.96 288.60000 0.00E+000 0.00E+000 4.26E-002 7.2196 301.10000 0.00E+000 0.00E+000 3.95E-002

[

7/29 96 316.70000 0.00E+000 0.00E+000 3.75 E-002 8/5.96 301.90000 0.00E +000 0.00E+4 '

4.00E402 9

--=. --

p Semiannual Analysis Repen CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Sample Point SampicDate Quantity Emciency ActMey 2 SigmaError LLD 205 - 0.6111 SSE - SPOIL POND 8I296 285.80000 0.00E+000 0.00E+000 3.73E 002 8'19 96 285.80000 0.00E+000 0.00E+000 2.50E.002 126.96 281.50000 0.00EN)00 0.00E+000 3.45E402 s

9/196 273.80000 0.00E+000 0.00E+000 331E 002 9/9 96 136.30000 0.00E+000 0.00E+000 5.65E-002 9/1696 189.50000 0.00E+000 0.00E+000 4.82E402 9/23 %

291.50000 0.00E+000 0.00E+000 3.8tE-002 930.96 278.60000 0.00E+000 0.00E+000 3.63E-002 Plant: BNP Ammints: TRITIUM hiedinType: SURFACEWATER LITERS 400 - 0.7 M1 NE -INTAKE CANAL (CONTROL) 103196

.00500 2.87E-001 0.00E+000 0.00E+000 2.98E+002 11/30.96

.00500 2.87E401 0.00E+000 0.00E+000 3.10E+002 l

12/3196

.00500 2.87E-001 0.00E+000 0.00E+000 2.95E+002 73196

.00500 2.93E-001 2.93E+002 831.96

.00500 2.94E-001 2.94E+002 930.96

.00500 2.94E-001 2.99E+002 401 - 4.9 hil SSW-DISC 1LARGE CANAL 7/31/96

.00500 2.93E-001 2.93E+002 8/31/96

.00500 2.94E-001 2.94E +002 i

I 93096

.00500 2.94E 001 2.99E+002 1031S6

.00500 2.87E 001 0.00E+000 0.00E+000 2.98E+002 11/30.96

.C3500 2.87E-001 0.00E+000 0.00E+000 3.10E+002 f

12/31/96

.00$00 2.87E-001 0.00E+000 0.00E+000 2.95d+002 s

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CP&L Radiological Environmental Monitoring Isotopic Analysis Report

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Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Qusatity hotope Activity 2 SigmaError L1D Plant: BNP Anah*:CAMMA MedisType: AIR PARTICULATE Units: CUhfETERS 200 - 1.O kII SW-VISITORS CEN ER 11/1196 3385.60000 BE-7 1.24E-001 8.90E 003 8/1596 3812.20000 BE-7 131E 001 2.20E.002 0.00E+000 201 - 0.6 kil NE - FMAC 8'1196 4019.80000 RA-226 3.17E-002 2.41E-002 11/1196 3618.60000 BL7 1.22E 001 9.10E-003 11115 96 3618.60000 RA-226 8.44E-003 7.44E-003 8/15 96 4019.80000 BL7 1.13E 001 2 70E-002 0.00E+000 202 - 1.0 MI S - SUBSTATION ON CONSTRUCTION 1 t/15 96 3504.40000 BE-7 1.23E-001 6.60E 003 81596 4032.70000 BE-7 1.22E-001 230E-002 0.00E+000 203 - 23 MI SSW-SOUTitPORT SUBSTATION 1!!!$ 96 3547.90000 BE7 1.42E-001 8.90E.003 11/15 96 3547.90000 RA-226 1.07E-002 7.66E-003 81596 3989.80000 BL7 1.56E-001 2 50E-002 0.00E+000 204 - 23.0 MI NNE-SLTTON PLANT (CONTROL) 11:15 96 3521.00000 BE-7 1.21E-001 6.10E-003

&l196 397330000 BL7 1.44E-001

. 3.40E.002 0.00E+000 205 - 0 6 MI SSE. SPOIL POND 8/15 96 3855.60000 RA-226 2.25E-002 1.86E42 11/15 96 3547.00000 BL7 1.19E-001 7.70 6 003 8'15 96 3855.60000 BL7 1.28Fe001 2.60E-002 0.00E+000 Plant: BNP Anal *: GAMMA MediaT3De: BROADLEAFVEGETATION Units: GRAMS Media: CHERRY 3

800 - 0.7 M1 NE-INTAKE CANAL 7/2.96 470.40000 BE-7 8.16E-001 1.94E-001 0.00E+000

't 2.96 470.40000 TI 208 2.57E 002 1.92E 002 0.00E+000 7/2 96 470.40000 PB-212 5.18E-002 2.76E-002 0.00E+000 7/196 470.40000 1-131 0.00E+000 0.00E+000 232E-002 7/196 470.40000 CS-134 0.00E+000 0.00E+000 2.48E402 7/196 470.40000 CS-137 0.00E+000 0.00E+000 2.58E-002 f

7/ 2S6 470.40000 K-40 4.52E+000 4.80E 001 0.00E+000 9/196 468.20000 CS-134 0.00E+000 0.00E+000 2.83 E-002 12/196' 374.70000 BE-7 5.98E+000 236E+000 0.00E+000 12/196 374.70000 K-40 332E+000 6.26E-001 0.00E+000 12/196 374.70000 1-131 0.00E+000 0.00E4000 535E 002 i

12/296 374.70000 CS-134 0.00E+000 0.00E+000 3.93 E-002 12'2.96 374.70000 CS-137 0.00E+000 0.00E+000 3.45E-002 8'196 513.60000 DE-7 8.14E-001 1.93E-001 0.00E+090 8.'5 96 513.60000 1-131 0.00E+000 0.00E+000 2.25E-002 8/596 513.60000 CS-134 0.00E+000 0.00E+000 2.53E-002 8'596 513.60000 CS-137 0.00E+000 0.00E+000 2.25 E-002 8/196 513.60000 K-40 1.69E+000 3.60E-001 0.00E4000 9/196 468.20000 BL7 632E-001 1.77E-001 0.00E+000 9/196 468.20000 1-131 0.00E+000 0.00E4000 2.53E-002 9/196 468.20000 CS-137 0.00E+000 0 00E+000 2.58E-002

,3 (mNs)

A._/

(p\\

f 1

t/

Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Quantity Isotope Activity 2 SigmnError LLD 800 - 0.7 hil NE -INTAKE CANAL 9'296 468.20000 K-40 3.36E+000 4.90E-001 0.00E+000 10/196 417.10000 BE-7

!.79E+000 2.70E 001 0.00E+000 10!!96 417.10000 P3-212 5.82E-002 3.85E-002 0.00E+000 10.' t.96 417.10000 AC-228 1.64E-001 8.90E-002 0.00E+000 10/ IS6 417.10000 1-131 0.00E+000 0.00E+000 3.06E-002 107I96 417.10000 CS-134 0.00E+000 0.00E+000 2.95E-002 10/I96 417.10000 CS-137 0.00E+000 0.00E+000 3.18E-002 10'156 417.10000 K-40 1.56E+000 4.65 E-001 0.00E+000 11/4 96 428.50000 BE-7 8.94E401 2.09E-001 0.00E+000 11/4 96 428.50000 I-131 0.00E+000 0.00E+000 3.20E402 11/4 96 428.50000 CS-134 0.00E+000 0.00E+000 3.24E-002 II/ 496 428.50000 CS-137 0.00E+000 0.00E+000 4.30E-002 11/496 428.50000 K-40 2.56E+000 6.0SE-001 0.00E+000 801 - 0.6 kil SW-DISCllARGE CANAL 7/ 2S6 457.70000 BE-7 4.38E-001 1.94E-001 0.00E+000 7/ 2S6 457.70000 1-131 0.00E+000 0.00E+000 2.80E-002 7/196 457.70000 CS-134 0.00E+000 0.00E+000 2.79E-002 7/ 2S6 457.70000 CS-137 0.00E+000 0.00E+000 2.54E-002 7/196 457.70000 K-40 5.23E+000 5.4 t E-001 0.00E+000 12/256 354.60000 BE-7 1.2CE+000 3.04E-001 0.00E+000 12/2/96 354.60000 K-40 2.77E+000 5.88E-001 0.00E+000 12/236 354.60000 1-131 0.00E+000 0.00E+000 3.96E-002 12/256 354.60000 CS-134 0.00E+000 0.00E+000 3.50E-002 12/196 354.60000 CS-137 0.00E*000 0.00E+000 3.65E-002 8/5/96 459.70000 BF-7 7.53E401 2.IIE 001 0.00E+000 8/5 96 459.70000 1 131 0.00E+000, 0.00E+000 2.67E-002 8/196 459.70000 CS-134 0.00E+000 0.00E+000 2.85E 002 8/ 5<96 459.70000 CS-137 0.00E+000 0.00E+000 2.32E-002 8/ SS6 459.70000 K-40 1.86E+000 3.70E-001 0.00E+000 9/296 534.60000 BE-7 5.llE-001 1.72E-001 0.00E+000 9/ 2S6 334.60000 1-131 0.00E+000 0.00E+000 2.64E-002 9/296 534.60000 CS-134 0.00E+000 0.00E+000 2.78E-002 9/2.96 534.60000 CS-137 0.00E+000 0.00E+000 2.36E-002 9/196 534.60000 K-40 3.27E+000 4.60E401 0.00E+000 10/I/96 431.00000 BE-7 9.13E-001 2.42E-001 0.00E+000 10/ l<96 431.00000 RA-226 6.64E-001 3.59E-001 0.00E +000 10/ IS6 43I 00003 1-13I 0.00E+000 0.00E+ 000 2.45E-002 10/1/96 431.00000 CS-134 0.00E+000 0.00E+000 2.81 E-002 10/1/96 431.00000 CS-137 0.00E+000 0.00E+000 2.81E 002 10/1.96 431.00000 K-40 4 29E+000 4.89E-00!

0.00E+000 11/496 249.00000 BE-7 2.12 E+000 4.40E-001 0.00E+000 11/496 249.00000 Tir208 4 04E-002 2.60E-002 0 00E4000

O O

D Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Auntysis Report 3/17/97 i

1 Sample Point SampleDate Quantity isotope Actidty 2 SigmeError LIE 801 - 0.610 SW-DISCIIARGE CANAL i1/4.96 249.00000 1-131 0.00E+000 0.00E+000 4.78E-002 11/496 249.00000 CS-134 0.00E+000 0.00E+000 5.74E 002 i

11/496 249.00000 CS-137 0.00E+000 Dat.ao 4.63E-002 11/496 249.00000 K-40

?.Gudo 8.48E-001 0.00E+000 802 10.0 hil-NOT SPECIFIF"(CONTD8%

71::.%

314.40000 BE-7 4.94 0001 1.77E 001 0.00E+000 7/196 514.40000 AC-228 8.80 LOO 2 6.86 0 002 0.00E+000 7/196 514.40000 1-131 0.00E+000 0.00E+000 2.60E-002

[

7/196 514.40000 CS-134 0.00E+000 0.00E+000 2.65 LOO 2 7/2.96 514.40000 CS-137 0.00E+000 0.00E+000 2.46E-002 7/2.96 514.40000 RA-226 1.20E+002 5.90E+001 0.00E+000 7/196 514.40000 K-40 3.78E+000 4.70E 001 0.00E+000 12/2!96 349.80000 BE-7 1.20E+000 2.97E-001 0.00E+000 12/2/96 349.80000 K-40 3.08E+000 6.98E-001 0.00E+000 12/196 349.80000 1-131 0.00E+000 0.00E+000 4.02E-002 12'2.96 349.80000 CS-134 0.00E+000 0.00E+000 436E-002 12/196 349.80000 CS-137 0.00E+000 0.00E+000 4.23E 002 8/5,96 494.50000 BE-7

' 'E-0GI 5.90E-002 0.00E+000 I

8/596 494.50000 1-131 4/M 0.00E+000 8.890003 8/5,96 494.50000 CS-134 0.00E+000 0.00E+000 9.80E-003 875/96 494.50000 CS-137 0.00E+000 0.00E+000 9.21 E-003 8/5.96 494.50000 K-40 133E+000 1.80E 001 0.00E+000 9/2.96 497.50000 BE-7 1.09E+000 1.90E 001 0.00E+000 I

9/196 497.50000 RA-226 6.75 E-001 335E-001 0.00E+000 9/196 497.50000 1-131 0.00E+000 0.00E+000 2.54E-002 9/2,96 497.50000 CS-134 0.00E+000 0.00E+000 2.67E-002 9/2.96 497.50000 CS-137 0.00E+000 0.00E+000 2.90E-002 9/2.96 497.50000 K-40 4.26E+000 5.00E-001 0.00E+000 10/196 477.50000 BE-7 1.66E+000 2.40E-001 0.00E+000 10/!!96 477.50000 PB-212 3.89E-002 2.91 0002 0.00E+000 10/I96 477.50000 AC-228 1.76E-001 9.70E-002 0.00E+000 10/196 477.50000 1-131 0.00E+000 0.00E+000 2.18E-002 10/1.96 477.50000 CS-134 0.00E+000 0.00E+000 338E-002 10/I!96 477.50000 CS-137 0.00E+000 0.00E+000 2.82 6 002 10/196 477.50000 K 40 3.16E+000 4.29b001 0.00E+000 11/496 360.40000 BE-7 839E-001 2.81E-001 0.00E4000 11/4.96 360.40000 1-131 0.00E+000 0.00E+000 4.15 E-002 11/496 360.40000 CS-134 0.00E+000 0.00E+000 3.56E-002 11/496 360.40000 CS-137 0.00E+000 0.00E+000.

3.47E-002 11/496 360.40000 K-40 431E+000 7.49E-001 0.00E+000 803 - 0.6 kil SSE - SPOIL POND 7/2.96 510.20000 BE-7 5.61 E-001 1.680001 0 00E4 000 7!296 510.20000 I

0.00E +000

. 0.00E.+ 000 2 66E-002

-131

O O

O Se.aiannual Analysis Report '

CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Quantity hotope Actidty 2 SigmaError LIE 803 - 0.6 h!! SSE - SPOIL POND 7/296 510.20000 CS-134 0.00E+000 0.00E+000 2.27E 002 7/296 510.20000 CS-137 0.00E+000 0.00E+000 2.42E.C32 7/196 510.20000 K-40 2.90E+000

' 5.10E-001 0.00E+000 11/496 374.10000 K-40 2.78E+000 6.45EA)01 0.00E+000 12/2.96 362.60000 BE-7 8.2 t E+000 2.07E 001 0.00E+0nn 12/2S6 362.60000 K-40 2.7/E+000 5.43E-001 0.00E+000 8/SS6 507.70000 BL7 7.22E 001 1.9 t E401 0.00E+000 8/5.56 507.70000 K-40 1.94E+000 4.10E-001 0.00E+000 8/5S6 507.70000 1-131 0.00E+000 0.00E+000 2.73E-002 8/5S6 507.70000 CS-134 0.00E+000 0.00E+000 2.19E402 8/5/96 507.70000 CS-137 0.00E+000 0.00E+000 2.27E-002 9/296 432.60000 BL7 9.17E401 2.46E-001 0.00E+000 9/2.96 432.60000 1-131 0.00E+000 0.00E+000 2.85E 002 9/296 432.60000 CS-134 0.00E+000 0.00E+000 2.85E 002 9/2 96 432.60000 CS-137 0.00E+000 0.00E+000 2.70E-002 9/196 432.60000 K-40 2.57E+000 5.00E 001 0.00E+000 10/I/96 505.90000 BE-7 8.98E-001 23tE 001 0.00E+000 10/I!96 505.90000 RA-226 931E 001 4.29E401 0.00E+000 10/!!96 505.90000 1-131 0.00E+000 0 00E+000 2.60E402 10/ IS6 505.90G00 CS-134 0.00E+000 0.00E+000 2.99E-002 10/156 505.90000 CS-137 0.00E+000 0.00E+000 2.28E-002 10/I/96 505.90000 K-40 2.24E+000 5.llE 001 0.00E+000 12/2.96 362.60000 I-131 0.00E+000 0.00E+000 3.69E-002 12/296 362.60000 CS-134 0.00E+000 0.00E+000 3.65E-002 12/196 362.60000 CS-137 0.00E+000 -

0.00E+n00 333E 002 11/496 374.10000 BL7 7.68E-001 2.96E 001 0.00E+000 11/496 374.10000 TLr208 4.%E-002 2.52E-002 0.00E+000 11/496 374.10000 1-131 0.00E+000 0.00E+000 3.71E-002 l

11/496 374.10000 CS-134 0.00E+000 0.00E+000 3.89E-002 11/496 374.10000 CS-137 0.00E+000 0.00E+000 4.04E-002 Plant: BNP Analysis: GAhthlA hiediaType: BROADLEAFVEGETATION Units: GRAhtS hiedia: SWEETGUhl 800 - 0.7 hil NE -INTAKE CANAL 7/196 369.90000 DE-7 6.61 E-001 2.15E-001 0.00E+000 7/296 369.90000 1-131 0.00E+000 0.00E+000 3.20E-002 7/196 369.90000 CS-134 0.00E+000 0.00E6 3.41E-002 7/296 369.90000 CS-137 0.00E+000 0.00E+000 339E-002 I

7/ 2S6 369.90000 K-40 135E+000 3.00E-001 0.00E4000 8/5S6 478.60000 DE-7 1.15E+000 2.40E-001 0.00E+000 8/ 5S6 478.60000 1-131 0.00E+000 0.00E+000 2.74E-002 f

8'5/96 478.60000 CS-134 0.00E+000 0.00E+000 2.48E-002 8/5.96 478.60000 CS-137 0.00E+000 O A E+000 2.96E-002

~

LJ Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Quantity ism pe Actidty 2 SigmaError LLD 800 - 0.7 hil NE -INTAKE CANAL 815 96 478.60000 K-40 9.35E-001 4.42E-001 0.00E+000 8

9/196 43130000 BL7 6.89E-001 2.20E-001 0.00E+000 9/2.96 43130000 1-131 0.00E+000 0.00E+000 2.90E-002 9/196 431.30000 CS-134 0.00E+000 0.00E+000 2.90E-002 9/196 4313 0000 CS-137 0.00E+000 0.00E+000 2.89E-002 9/296 43130000 K-40 1.58E+000 -

4.80E-001 0.00E+000 i

10/1,96 501.70000 BE-7 1.29E+000 2.lCE-001 0.00E+000 10/1.96 501.70000 1-131 0.00E+000 0.00E+000 2.47E-002 10/196 501.70000 CS-134 0.00E+000 0.00E+000 2.58E-002 10/196 501.70000 CS-137 0.00E+000 0.00E+000 2.19E 002 10/196 501.70000 K-40 9.50E-001 3.63L001 0.00E+000 i

iI/ 4.96 375.80000 BE-7 1.77E+000 2.70E-001 0.00E+000 i

II/ 4.96 375.80000 1-131 0.00E+000 0.00E+000 3.18E-002 11/4 96 375.80000 CS-134

'O.00E+000 0.00E+000 3.28 0 002 11/4.96 375.80000 CS-137 0.00E+000 0.00E+000 3.26E-002

' 11! 4.96 375.80000 K-40 1.50E4400 430E-001 0.00E+000 801

- 0.61Lil SW - DISCllARGE CANAL 7/196 498.10000 BL7 2.21E 001 3.87E-001 0.00E+000 7/2/96 498.10000 1-131 0.00E+000 0.00E+000 2.63E-002 7/2.96 498.10000 CS-134 0.00E+000 0.00E+000 2.56E-002 7/2/96 498.10000 CS-137 0.00E+000 0.00E+000 234E-002 7/2.96 498.10000 K-40 134E+000 3.40E-001 0.00F 000 8/5,96 461.70000 BE-7 839E-001 2.525001 Of 'c. 400 8/196 461.70000 RA-226 4.70E-001 3.57E-001 0.00E+000 El3/96 461.70000 1-131 0.00E4000 0.00E+000 2.53E-002 8/5/96 461.70000 CS-134 0.00E+000 0.00E+000 3.00E-002

[

8/196 461.70000 CS-137 0.00E+000 0.00E+000 2.81E-002 8/5,96 461.70000 K-40 139E+000 4.20E-001 0.00E+000 9/296 488.70000 BE-7 1.37E+000 23CL001 0.00E+000 k

9/196 488.70000 PB-212 3.12E-002 2.20E-002 0.00E+000 9f 2S6 488.70000 I-131 0.00E+000 0.00E+000 2.64E-002 972.96 488.70000 CS-134 0.00E+000 0.00E+000 2.74E-002 9/2 %

488.70000 CS-137 0.00E+000 0.00E+000 2.73E-002 9/ 2?V 488.70005 K-40 2.68E+000 3.80E-001 0.00E+000

[

10/!!96 469.20000 DE-7 1.08E+000 230E-001 0.00E+000 f

10! !/96 469.20000 PD-212 3.44E-002 2.23E-002 0.00E+000 10/1/96 469.20000 RA-226 4.39E-001 338E-001 0.00E+000 10/1/96 469.20000 I-131 0.00E+dOO 0.00E+000 2.55E-002 10/I/96 469.20000 CS-134 0.00E+000 0.00E4000 2.76E-002 10/I/96 469.20000 CS-137 0.00E+000 0.00E+000 2.99E-002 10/196 469.20000 K-40 137E+000 4.80E-001 0.00E+000 I

11/496 361.00000 DE-7 1.77E+000 3.10E-001 0 00E+000

b v

semiannual Analysis Report

- CP&L Radiological Enviremental Monitorine, Analysis Report 3/17/97 l

Sample Point SampicDate Quantity Isotope ActMty 2 SiganaError LIE 801 - 0.6 hil SW-DISCIIARGE CANAL i1/4 96 361.000 %

I-131 0.00E+000 0.00E+000 3.73E-002 11/496 361.00000 CS-134 0.00E+000 0.00E+000 3.72E-002 7

11/496 361.00000 CS-137 0.00E+000 0.00E+000 330E-002 11/4 96 361.00000 K-40 236E+000 5.81E-001 0.00E+000 f

802 - 10.0 kil-NOT SPECII'IED(CONTROL) 7/2.96 515.80000 BL7 6.69E 001 2.04IX01 0.00E+000 7/2.96 515.80000 1-131 0 00E+000 0.00E+000 2.48E-002

[

7/196 515.80000 CS-134 0.00E+000 0.00E4000 3.08E-002 t

7/196 515.80000 CS-137 0.00E+000 0.00E+000 2.66E-002 I

7/2 96 515.80000 K-40 I.53E+000 5.00E-001 0.00E+000 h

8/596 492.90000 CS-134 0.00E+000 0.00E+000 2.80 0002 81596 492.90000 BE-7 9.98E-001 233E 001 0.00E+000 i

E' 5<96 492.90000 1-131 0.00E+000 0.00E+000 2.86E-002 8/5,96 492.90000 CS-137 0.00E+000 0.00E+000 2.89E-002

[

f 8/5.96 492.90000 K-40 2.09E+000 4.60E-001 0.00E +000 9/2.96 4363 0000 BL7 1.50E+000 2.70E-001 0.00E+000 9.'296 43630000 I-131 0.00E4000 0.00E+000 2.93E-002 9/2.96 4363 0000 CS-134 000E+000 0.00E+000 2.65E402

[

9/ 2S6 43630000 CS-137 0 00E+000 0.00E+000 3.24E-002 I

L 9/196 4363 0000 K-40 1.86E+000 3.90E-001 0.00E+000 10/I96 452.50000 BL7 I.16E+000 2.60E-001 0.00E+000 10/196 452.50000 Tir208 2.98E-002 2.44E-002 0.00E+000 10' t.96 452.50000 RA-226 5.88E 001 4.IOE-001 0.00E+000 10/ I<96 452.50000 1-131 0.00E+000 0.00E+000 2.90E-002 10/I96 452.50000 CS-134 0.00E+000 0.00E+000 3.26E 002

[

10!196 452.50000 CS-137 0.00E+000 0.00E+000 2.58E 002 10/I/96 452.50000 K-40 1.12E+000 4.68E 001 0.00E+000 11/496 378.90000 BL7 2.74E+000 3.60E-001 0.00E+000 11/496_

378.90000 1-131 0.00E+000 0.00E+000 3.57E-002 2

11/4.96 378.90000 CS-134 0.00E+000 0.00E+000 3.50EAN)2 11/4 96 378.90000 CS-137 0.00E+000 0.00E+000 3.84E-002 11/496 378.90000 K-40 2.18E+000 5.43E-001 0.00E+000 803 - 0.6 hC SSE-SPolL POND 7/2.96 5l0.10000 BL7 6.41 E-001 2.06E-001 0.00E+000 7/2.96 5I0.10000 1-131 0.00E+000 0.00E+000 2.66E-002 i

7/2/96 510.10000 CS-134 0.00E+000 0.00E+000 2.89E-002 7/2/96 510.10000 CS-137 0.00E+000 0.00E+000 2.41E-002 7/296 510.10000 K-40 1.72E+000 4.50E401 0.00E+000 10/1/96 50230000 K-40 138E+000 4.05E-001 0.00E+000 8'596 514.60000 BE-7 1.0gD 000 2.40E-001 0.00E+000 I

8/5/06 514.60000 RA-226 5.56E-001 3.51E 001 0.00E+000 8/5/96 514.60000 1-131 0.00E+000 0.00E+000 2.76E-002 8/5,96 514.60000 CS-134 0.00E4000 0.00E+000 2.96E-002

O O

s Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Seinple Point SampleDate Quentity Isotope Activity 2 SigniaError LLD 803 - 0.6 MI SSE - SPolt POND W 5 96 514.60000 CS-137 0.00E+000 0.00E+000 2.54E402 8/5 96 514.60000 K-40 1.95E+000 4.90E401 0.00E+000 9/2.96 531.60000 BL7 1.06E+000 2.20 0 001 0.00E+000 9/196 531.60000 1-131

' O.00E+000 0.00E+000 2.71E-002 9/296 331.60000 CS-134 0.00E+000 0.00E+000 237E-002 9'196 531.60000 CS-137 0.00E+000 0.00E+000 2.49E-002 9'196 531.60000 K-40 2.01E+000 4.40F-001 0.00E4000 la' l.96 5023 0000 BL7 1.58E+000 230E-001 0.00E+000 10/I/96 50230000 1-131 0.00E+000 0.00E+000 2.76E-002 10'I.96 5023 0000 CS-134 0.00E+000 0.00E+000 2.86E-002 10'I96 50230000 CS-137 0.00E+000 0.00E+000 2.81E-002 11'4 96 38630000 BE-7 2.50E+000 3.60E-001 0.00E+000 11/496 38630000 1-131 0.00E+000 0.00E+000 4.01E402 I

11/496 3863 0000 CS-134 0.00E+000 0.00E+000 3.43E 002 i

11/4 96 38630000 CS-137 0.00E+000 0.00E+000 3.44E402 11/4 96 3863 0000 K-40 2.02E+000 6.50L001 0.00E+000 Plant: BNP Anaheas:CAhl31A hiedleTrpe: BROADLEAFVEGETATION Unies: CR.OIS Media: WAX EnRTLE 800 - 0.7 ILII NE -INTAKE CANAL 7/2.96 385.90000 BL7 1.11E4000 2.70E-001 0.00E+000 7/2.96 3C190000 1-131 0.00E+000 0.00E+000 3.20 0002 7/296 385.90000 CS-134 0.00E+000 0.00E+000 3.860 002 h

7/196 385.90000 CS-137 0.00E+000 0.00E+000 3.22E-002 7/2.96 385.90000 K-40 4.49E+000 5.70E-001 U.00E+000 8/5/96 486.70000 BE-7 9.975 001 2.110001 0.00E+000 I

8/5/96 486.70000 1-131 0.00E+000 0.00E+000 2.22E-002 8/596 486.70000 CS-134 0.00E+000 0.00E+000 2.72 0002 8/5/96 486.70000 CS-137 0.00E+000 0.00E+000 238E402 U 5,96 486.70000 K-40 339E+000 4.50E-001 0.00E+000 9/196 502.10000 BL7 9.85E-001 2.09E-001 0.00E+000 9/196 502.10000 PB-212 2.80 LOO 2 2.10 LOO 2 0.00E+000 9'196 502.10000 1-131 0.00E+000 0.00E+000 2.44E-002 9/2.96 502.10000 CS-134 0.00E+000 0.00E+000 1.92E-002 9/2/96 502.10000 CS-137 0.00E+000 0.00E+000 2.69E-002 1

9/196 502.10000 K-40 2.47E+000 4.40E401 0.00E+000 1G' I/96 332.00000 BL7 1.53E+000 2.10E-001 0.00E+000 10/I!96 532.00000 RA-226 4.68E 001 3.99E-001 0.00E+000 10/1/96 532.00000 1-131 0 00E+000 0.00E+000 1.99&OO2 10/1.96 332.00000 CS-134 0.00E+000 0.00E+000 2.50E-002

}

10/I/96 532.00000 CS-137 0.00E+000 0.00E+000 1.90E-002 l

10/1.96 532.00000 K-40 1.05E+000 333E-001 0.00E+000 12'2.96 381.00000 BL7 1.860+000 3.04E-001 0.00E+000

O

)

Semiannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Quantity Isotope ActMty 2 SigmaEner LLII 800 - 0.7 kil NE-INTAKE CANAL-12/296 381.00000 K-40 1.64E+000 4.99E401 0.00E+000 t

11'196 381.00000 I-131 0.00E+000 0.00E+000 5.0200'?7 12/296 381.00000 CS-134 0.00E+000 0.00E+000 3.47E-%.!

12/2,96 381.00000 CS-137 0.00E+000 0.00E+000 336E402 11/4.96 348.50000 BL7 2.08E+000 3.00E 001 0.00E+000 11/496 348.50000 I-131 0.00E+000 0.00E+000 3.85E402 11/496 348.50000 CS-134 0.00E+000 0.00E+000 3.49E402 11/496 348.50000 CS-137 0.00E+000 0.00E+000 3.42 0 002 11/4 96 348.50000 K-40 1.50E+000 5.83E401 0.00E+000 801 - 0.6 hfl SW.DISCIIARGE CANAL 7/196 435.20000 BL7 7320001 1.77E401 0.00E+000 7r 196 435.20000 I-131 0.00E+000 0.00E+000 2.80E402 7/196 435.20000 CS-134 0.00E+000 0.00E+000 2.67E-002 7/2.96 435.20000 CS-137 0.00E+000 0.00E+000 2.82 LOO 2 l

7/196 435.20000 K-40 2.80E+000 4.20E-001 0.00E+000 E'596 517.90000 BL7 1.0$E+000 1.90E401 0.00E+000 8/5.96 517.90000 TI,208 1.95 LOO 2 1.71E-002 0.00E+000 l

8'5.96 517.90000 PB-212 439L002 3.15E402 0.00E+000 8'5.96 517.90000 1-131 0.00E+000 0.00E+000 2.26E-002 8/5.96 517.90000 CS-134 0.00E+000 0.00E+000 2.52E-002 El 5,96 517.90000 CS-137 0.00E+000 0.00E+000 239E-002 i

8.'5,96 517.90000 K-40 3.01E+000 4.20E-001 0.00E+000 9'196 465.60000 BE-7 8.61E-001 I 98E-001 0.00E+000 9/2.96 465.60000 1 131 0.00E+000 0.00E+000 2.98E402 9/196 465.60000 CS-134 0.00E+000 0.00E+000 2.94 LOO 2 9/196 465.60000 CS-137 0.00E+000.

0.00E+000 2.30 0002 l

9/2.96 465.60000 K-40 2.03E+000 4.00 0 001 0.00E+000 10/1/96 521.50000 BL7 I.46E+000 230E 001 0.00E+000 10/1,9'6 521.50000 1-131 0.00E+000 0.00E+000 2.14E-002 10'1,96 521.5000Q CS-134 0.00E+000 0.00E+000 2.20E 002 10/1/96 521.50000 CS-137 0.00E+000 0.00E+000 2330002 10/1.96 521.50000 K-40 139E+000 4.41E-001 0.00E+000 12/296 358.50000 BL7 1.78E+000 3.08E-001 0.00E+000 f

12'196 358.50000 K-40 2.25E+000 5.57E-001 0.00E+000

.}

11/496 345.40000 BL7 9.25L001 3.30E-001 0.00E+000 11/496 345.40000 I-131 0.00E+000 0.00E+000 3.46E402 11/496 345.40000 CS-134 0.00E+000 0.00E+000 3.65E-002 i

1114.96 345.40000 CS-137 0.00E+000 0.00E+000 2.91E-002 11/496 345.40000 K-40 2.19E+000 4.76E-001.

0.00E+000 12/196 358.50000 1-131 0.00E+000 0.00E+000 4.8 t E-002 12/196 358.50000 CS-134 0.00E+000 0.00E+000 3.99E-002 12/196 358.50000 CS-137 0.00E+000 0.00E+000 339E-002

C O

O Semir no:I Arlysis Report '

CP&L Rcdiigic I Enviromentzl M=ittring Analysis Report 3/17/97 Sample Point SampleDate Quentity Isotope ActMty 2 SigneErmr LID -

802 10.O kII-NOT SPECIFIED (CONTROL) 7/2 96 450.50000 BE-7 8.56E-001 2.08L001 0.00E+000 7/296 450.50000 I-131 0.00E+000 0.00E+000 3.75 LOO 2 7/196 450.50000 CS-134 0.00E+000 0.00E+000 2.46E402 7/2.96 450.50000 CS-137 0.00E+000 0.00E+000 2.66E402 7/2,96 450.50000 K-40 2.03 E+000 4.40L001 0.00E+000 8/5.96 510.60000 BL7 1.06E+000 2.10E-001 0.00E+000 8/5.96 510.60000 TL 208 2.61E-002 1.47L002 0.00E+000 8'5,96 510.60000 PB-212 2.76E402 1.86E-002 0.00E+000 8/596 510.60000 I-131 0.00E+000 0.00E+000 2.54E-002 l

8/596 510.60000 CS-134 0.00E+000 0.00E+000 -

2.00E-002 8/5.96 510.60000 CS-137 0.00E+000 0.00E+000 2.53E-002 8/596 510.60000 K-40 3.29E+000 4.50E-001 -

0.00E+000 9/296 523.80000 BL7 6.59 0 001 1.51 E-001 0.00E+000 9'296 523.80000 RA-226 7.51E-001 4335001 0.00E+000 9/2.96 523.80000 I-131 0.00E+000 0.00E+000 237E402 9/2.96 523.80000 CS-134 0.00E+000 0.00E+000 2.75E-002 9/296 523.80000 CS-137 0.00E+000 0.00E+000 2.66E402 9/296 523.80000 K-40 2.26E+000 4.70E-001 0.00E+000 10/1:96 454.20000 BL7 2.0$E+000 2.90 0 001 0.00E+000 10/196 454.20000 T1-208 2.77L002 1.680002 0.00E+000 10/I!96 454.20000 PB-212 3.90 LOO 2 332E-002 0.00E+000 10/I!96 454.20000 PB-214 9.72 5 002 533E-002 0.00E+000 10/ t/96 454.20000 RA-226 4.55 E-001 3.69E-001 0.00E+000 10/1:96 454.20000 AC-228 2.42 0 001 9.90 0 002 0.00E+000 10/I/96 454.20000 1-131 0.00E+000 0.00E+000 3.00E-002 10/I/96 454.20000 CS-134 0.00E+000 0.00E+000 3.46L002 10/I/96 454.20000 CS-137 0 00E+000 0.00E+000 2.79E-002 10/!!96 454.20000 K-40 3.04E+000 4.89 0 001 0.00E+000 11/496 355.90000 BL7 1.22E+000 2.94E 001 0.00E+000 11/496 355.90000 TI,208 4.18DOO2 2.56 0 002 0.00E+000 11/496 355.90000 1-131 0.00E+000 0.00E+000 3.95 E-002 11/496 355.90000 CS-134 0.00E+000 0.00E+000 3.93 E-002 11/496 355.90000 CS-137 0.00E+000 0.00E+000 3.85L002 11/496 355.90000 K-40 2.43 E+000 6.24E-001 0.00E+000 12'196 362.10000 BL7 1.97E+000 3.63E.001 0.00E+49) 12/2.96 362.10000 K-40 2.68E+000 5.88E-001 0.00E+000 12/296 362.10000 1-131 0.00E+000 0.00E+000 4.97E-002 12'2;96 362.10000 CS-134 0.00E+000 0.00E+000 3.69E-002 12/2,96 362.10000 CS-137 0.00E+000 0.00E+000 3.64E402 i

803 - 0.6 hlI SSE-SPOIL POND 7/2/96 536.80000 BL7 8.62E-001 2.29E-001 0.00E+000 7/2/96 536.80000 PB-212 2.71 E-002 2.09E402 0.00E+000

O O

O Senniannual Analysis Report CP&L Radiological Enviromental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Qusatity Isetope ActMty 2 SigmaError LID 803 - 0.6 MI SSE-SPOIL POND 7/2.96 336.80000 RA-226 3.54E.001 2.85 0 001 0.00E+000 7/2.96 336.80000 1-131 0.00E+000 0.00E+000 3.09E402 7/196 536.80000 CS-131 0.00E+000 0.00E+000 2.02E-002 7/2/96 536.80000 CS-137 0.00E+000 0.00E+000 2.2 t E-002 7/196 536.80000 K-40 3.09E+000 3.70E 001 0.00E+000 8/5/96 54330000 BE-7 8.09E-001 1.96E-001 0.00E+000 8!5.96 34330000 1-13 f 0.00E+000 0.00E+000 2.54E-002 8/5.96 54330000 CS-134 0.00E+000 0.00E+000 2.50E-002 8/ Se96 54330000 CS-137 0.00E+000 0.00E+000 235E-002 i

8'596 54330000 K-40 3.43E+000 4.050001 0.00E+000 9/2.96 51030000 BE-7 6.84E-001 2.0lE-001 0.00E+000 9/296 51030000 PB-212 4.56E-002 2.59E 002 0.00E400 9/296 51030000 I-131 0.00E+000 0.00E'+000 2.51E402 9/196 51030000 CS-134 0.00E+000 0.00E+000 2.66E-002 9/2.96 51030000 CS-137 0.00E+000 0.00s+000 230E-002 9/ 2S6 51030000 K-40 3.48E+000 4.20E401 0.00E+000 10!!!96 548.70000 BE-7 9.72E-001 2.13L001 0.00E+000 10/1.96 548.70000 1-131 0.00E+000 0.00E+000 2.66 0 002 10!!!96 548.70000 CS-134 0.00E+000 0.00E+000 2.43E-002 10/!!96 548.70000 CS-137 0.00E+000 0.00E+000 236E-002 10/I/96 548.70000 K-40 1.48E+000 3.94EA01 0.00E+000 11/4 96 374.80000 BE-7 I.81E+000 330E-001 0.00E+000 11/4.96 374.80900 1-131 0.00E+000 0.00E+000 3.86 0 002 11/496 374.80000 CS-134 0.00E+000 0.00E+000 3.47E-002 11/4 96 374.80000 CS-137 0.00E+000.

0.00E+000 3.115002 11/496 374.80000 K-40 2.63E+000 6.08 0 001 0.00E+000 12/2.96 348.20000 BE-7 1.61E+000 3.25E 001 0.00E+000 12/2,96 348.20000 K-40 2.47E+000 6.16E-001 0.00E+000 i

12/296 348.20000 1-131 0.00E+000 0.00E+000 4210002 12/196 348.20000 CS-134 0.00E+000 0.00E+000 3.74 0 002 12/2S 6 348.20000 CS-137 0.00E+000 0.00E+000 3.59E-002 Plant: BNP Analysis: GAMMA MedinType: FISII ANDINVERTEBRATES Unles: GRAMS 700 - 5.5 kil SSW-FREE SWikthlERS AT DISCllARG 10/25/96 506.40000 K-40 2.74E+000 1.53E+000 0.00E+000 701 - 5.5 MI SSW-BOTTOM FEEDER AT DISCIL-tR 10'25!96 432.90000 K-40 2.53E+000 1.76E+000 0.00E+000 703 - FREE SWIMMERS - ATLANTIC OCEAN (CONT 10'25/96 558.90000 K-40 3.82E+000 1.24E+000 0.00E+000 704 - BOTTOM FEEDER-ATLANTIC OCEAN (CON 10/25!96 422.20000 K-40 339E+000 1.09E+000 0.00E+000 Plant:BNP Analvsis: GAMMA MediaType: INVERTEBRATES Un6ts: GRAMS Media: INVERTEBRATES 702 - 5.5 MI SSW - 51i BO AT DISCIIARGE 10/25!96 577.50000 K-40 134E+000 7.10E401 0.00E+000

Semianna;.1 Asdysis Report CP&L Radiol:gical Enviromental Monitoring Analysis Report 3/17/97 Sample Point SampleDate Quantity hotope ActMty 2 SigmaError LIE 705 - SitBO-ATLANTICOCEAN(CONTROL) 10/2596 680.60000 K-40 136E+000 630E-001 0.00E+000 Plant: BNP Anahsis: GAMMA MedinType: SHOREl,1NE SEDIhlENT Unles: CRAMS 500 - 4.9 kil SSW-DISCllARGE 10/29 96 1034.40000 K-40 8.05E-001 4.74E-001 0.00E+000 1029 96 1034.40000 TI-208 7.61E-002 2.57Em 2 0.00E+000 10/2996 1034.40000 PB-212 9.06E-002 3.47E-002 0.00E+000 10.29 96 1034.40000 BI-214 4.46E-001 7.5IE-002 0.00E+000 10,2996 1034.40000 PB.214 3.69E.001 6.65E-002 0.00E+000 Plant: BNP Anahsis: GAMMA MedinType: SURFACEWATER Units: LITERS 400 - 0.7111NE-INTAKE CANAL (CONTROL) 10S 1.96 1.00000 K-40 1.97E+002 8.60E+001 0.00E+000 103196 1.00000 RA-226 1.88E+002 1.14E+002 0.00E+000 11/30.96 1.00000 K-40 1.73E +002 9.87E+001 0.00E+000 731.96 1.00000 K-40 1.45E+002 9.90E+001 0.00E+000 831,96 1.00000 K-40 5.37E+002 5.10E+001 0.00E+000 831.96 1.00000 PB-212 7.IIE+000

' 4.33E+000 0.00E+000 83196 1.00000 BI-214 1.2tE+001 5.90E+000 0.00E+000 E3196 1.00000 RA-226 6.67E+001 4.63E+001 0.00E+000 83156 1.00000 TI 208 2.22E+000 1.56E+000 0.00E+000 930.96 1.00000 K-40 7.79E+001 7.58E+001 0.00E+000 123 tS6 1.00000 K-40 13tE+002 9.60E+001 0.00E+000 12 31<96 1.00000 Tir208 6.97E+000 6.50E+000 0.00E+000 401 - 4.9 kil SSW-DISCIIARGE CANAL 9.30.96 1.00000 RA-226 1.20E+002 9.90E+001 0.00E+000 1031S6 1.00000 NO-ACT 11/3096 1.00000 K-40 2.27E+002 8.27E+001 0.00E+000 731.96 1.00000 K-40 332E+002 1.10E+002 0.00E+000 E3196 1.00000 K-40 1.65E+002 6.60E*001 0.00E+000 831/96 1.00000 RA-226 1.19E+002 5.20E+001 0.00E+000 9/30.95-1.00000 K-40 1.25E+002 9.60E+001 0.00E+000 12/31 S 6 1.00000 K-40 1.75 E+002 1.08E+002 0.00E+000 m