L-08-157, RTL A9.690E, 2007 Radioactive Effluent Release Report and 2007 Annual Radiological Environmental Operating Report, Enclosure 3

RTL A9.690E, 2007 Radioactive Effluent Release Report and 2007 Annual Radiological Environmental Operating Report, Enclosure 3

ML081290334
Person / Time
Site:	Beaver Valley
Issue date:	04/16/2008
From:	Lonnett A, Powell-Campbell J FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
L-08-157 RTL# A9.690E
Download: ML081290334 (90)

Text

RTL A9.690E Beaver Valley Power Station - Units 1 & 2 2007 Annual Radiological Environmental Operating Report FirstEnergy Nuclear Operating Company FENOC Beaver Valley Power Station - Units 1 & 2 Unit 1 License No. DPR-66 Unit 2 License No. NPF-73

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report EXECUTIVE

SUMMARY

and INDEX This document provides a detailed report of the Beaver Valley Power Station (BVPS)

Radiological Environmental Monitoring Program (REMP). During the report period, samples of air, water, shoreline sediment, milk, fish, food crops, feed crops, vegetation, and direct radiation (in the vicinity of the BVPS site) have been measured, analyzed, evaluated, and summarized.

The results of the REMP are intended to verify that BVPS effluent releases, performed in accordance with the BVPS Radiological Effluent Technical Specification (RETS) program, do not impact the environment with measurable concentration of radioactive materials and/or levels of radiation that are higher than expected.

Pre-operational REMIP (1974 - 1975):

A pre-operational REMP program was performed during the period 1974 through 1975. At that time, samples were collected and analyzed to determine the amount of radioactivity present in the environment prior to BVPS operation. The resulting values are considered a "baseline" to which current sample analyses can be compared. A summary of the pre-operational data is summarized in Table 2-3 of this report.

Operational REMP (1976 - Present):

The operational REMP program was initiated during calendar year 1976 and continued through the report period.

During the past thirty-two (32) years, radiation and radioactivity in the environment was monitored within a 10-mile radius of the site. A description of the operational REMP program is outlined in Table 2-1 of this report. In general, two (2) types of samples were collected during the report period, and are described as follows:

Control Samples: These samples are collected from areas that are beyond measurable influence of BVPS operation, and are used as reference data. Normal background radiation levels, or radiation present due to causes other than BVPS operation, can thus be compared to the environment surrounding the BVPS site. During the report period, three hundred nineteen (319) analyses were performed on samples from the control locations. In addition, eight (8) analyses were completed for TLDs at the control locations. Results of the analyses from the control locations are summarized in Table 2-2 of this report.

Indicator Samples: Indicator samples are collected to determine the radiological impact of BVPS operation in the environment. These samples are collected from various locations near the BVPS site. At a minimum, the samples are collected from areas where the BVPS contribution would indicate the most significant radiological impact. During the report period, one thousand three hundred sixty (1360) analyses were performed on samples collected from more than ninety (90) indicator locations. In addition, five hundred (500) analyses were completed for TLDs at the indicator locations. Results of the analyses from the indicator locations are also summarized in Table 2-2 of this report.

Current analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations.

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Beaver Valley Power Station RTL A9.690E I

2007 Annual Radiological Environmental Operating Report EXECUTIVE

SUMMARY

and INDEX I

Special Report Requirements:

A Special Report shall be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environmental sampling medium exceeds the limits specified in Offsite Dose Calculation Manual (ODCM) procedure 1/2-ODC-3.03, Attachment Q Table 3.12-2.

A Special Report shall also be submitted when the results of the following calculation are >1.0.

3 This calculation is performed when more than one radionuclide is detected in the sampling medium:

Concentration (1) + Concentration (2) +... > 1.0 1

Limit Level (1)

Limit Level (2) 1 Summary:

Based on the analytical results of environmental samples, the reporting levels were not exceeded during the report period.

Positive results attributable to the BVPS operation were consistent with station data of 3

authorized radioactive discharges and were within limits permitted by the NRC license and the ODCM.

Other radioactivity detected was attributable to naturally occurring radionuclides, previous nuclear weapons tests, other man-made sources, and to the normal statistical fluctuationl for activities near the Lower Limit of Detection (LLD).

During the report period, the radioactive effluent releases from the BVPS site did not exceed the limits identified in the BVPS Operating License Technical Specifications, and/or the ODCM.

The National Academy of Sciences 1990 BEIR Report shows that the typical dose to an i

individual from background (natural radiation exposure including radon) is an estimated average of 296 mrem per year. During the report period, the average individual population dose (for 4 million people) from BVPS operation was much less than <1 mrem. Therefore, the average I

individual population dose was not affected from BVPS operation.

Analytical results are divided into the following exposure pathways:

" Airborne Exposure Pathway: The airborne exposure pathway includes airborne radioiodine and airborne particulates.

The results during this report period were similar to previous years. There was no notable increase in natural products and no detectable fission products or other radionuclides in the airborne particulate media during the year.

1

" Direct Exposure Pathway: This pathway measures environmental radiation doses by use of Thermo-Luminescent Dosimeters (TLDs). The results of TLD processing have indicated a stable trend and compare well with previous years.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report EXECUTIVE

SUMMARY

and INDEX

" Ingestion Exposure Pathway: The ODCM requires this pathway to include samples of milk, fish, and foodcrops (leafy vegetables).

For milk samples, Strontium-90 (attributable to past atmospheric weapons testing), was detected at levels similar to those of previous years. The gamma spectrometry analyses only indicated positive results for naturally occurring Potassium-40 at average environmental levels. No other radionuclides were identified.

The fish samples indicated below LLD levels in each of the sample analyses.

Foodcrop (leafy vegetation) samples indicated naturally occurring Potassium-40 at average environmental levels.

" Waterborne Exposure Pathway: The ODCM requires this pathway to include samples of drinking water, ground (well) water, surface (river) water and river sediment.

Water samples were analyzed for tritium and gamma-emitting radionuclides. Tritium was not identified in any of these water samples. Iodine-131 analysis of drinking water indicated positive analyses, but the values were consistent with Iodine-131 at the upstream surface (river) water control location, and was not due to liquid effluent releases from BVPS.

Sediment samples were collected from upstream of the site, at the discharge point of BVPS liquid effluent releases, and downstream of the site. Analysis of samples indicated naturally occurring radionuclides Potassium-40, Thallium-208, Bismuth-214, Lead-212, Lead-214, Radium-226, and Actinium-228 in all results. The analyses also indicated Cesium-137, but the values were consistent with Cesium-137 at the control location, and most likely due from previous nuclear weapons tests. Cobalt-58 and Cobalt-60 were identified in some of the samples that were obtained at the shore line of the main outfall facility. This is not unusual, because the BVPS site discharges Cobalt-58 and Cobalt-60 in liquid waste effluents. The activity detected at this sample location is consistent with discharge data of authorized liquid effluent releases, and all liquid effluent releases during the report period did not exceed the release concentration limits set forth in the ODCM.

Other Exposure Pathways: In addition to the ODCM required samples collected from the exposure pathways described above, other media (i.e.; precipitation, feedstuff and soil) were also collected. Results were consistent with previous years and no degrading trends were identified.

The BVPS operational REMP program was followed throughout the report period. The results demonstrate the adequacy of radioactive effluent control at the BVPS, and that plant operation did not adversely affect the surrounding environment.

It should be noted that the REMP program includes sampling sites in addition to the required sites set forth in the ODCM. These include five (5) air sampling sites, one (1) surface water site, three (3) groundwater sites, three (3) precipitation sites, two (2) sediment sites, ten (10) soil sites, one (1) local large dairy, and one (1) milk animal feedstuff site.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environumental Operating Report EXECUTIVE

SUMMARY

and INDEX3 EXECUTIVE

SUMMARY

...............................................................1i SECTION 1 - INTRODUCTION A.

Radiation Fundamentals.......................................................

1-1 B.

Radiation and Radioactivity...................................................

1-1U C.

Units of Measurement.........................................................

1-4 D.

Lower Limit of Detection......................................................

1-4 E. Scope and Objectives of the REND Program....................................1-5 F. Description of the Beaver Valley Site..........................................

1-5 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAMI A.

Environmental Radioactivity Monitoring Program...............................2-1

1. Program Description......................................................

2-1

2.

Summary of Results.......................................................

2-5

3.

Quality Control Program..................................................

2-5

4.

Program Changes.........................................................

2-5 B.

Air Monitoring................................................................

2-23

1. Characterization of Air and Meteorology...................................

2-23

2.

Air Sampling Program and Analytical Techniques..........................

2-23

3.

Results and Conclusions...................................................2-24 C.

Monitoring of Shoreline Stream Sediments and Soil............................

2-27

1. Characterization of Shoreline Stream Sediments and Soils..................

2-27

2.

Sampling Program and Analytical Techniques..............................

2-27

3.

Results and Conclusions...................................................2-28 D.

Monitoring of Feedstuff and Foodcrops.........................................

2-33

1. Characterization of Farm Products.........................................

2-33

2.

Sampling Program and Analytical Techniques..............................

2-33I

3.

Results and Conclusions...................................................2-35 E.

Monitoring of Local Cow and Goat Milk........................................

2-38

1. Description - Milch Animal Locations.....................................

2-383

2.

Sampling Program and Analytical Techniques..............................

2-38

3.

Results and Conclusions...................................................2-40 F. Environmental Radiation Monitoring...........................................

2-443

1. Description of Regional Background Radiation and Sources.................

2-44

2.

Locations and Analytical Techniques......................................

2-44

3.

Results and Conclusions...................................................2-443 G. Monitoring, of Fish............................................................

2-49

1. Description...............................................................

2-49

2.

Sampling Program and Analytical Techniques..............................

2-49I

3.

Results and Conclusions...................................................2-49 vI

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report EXECUTIVE

SUMMARY

and INDEX TABLE OF CONTENTS (Continued)

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM (continued)

H.

Monitoring of Surface, Drinking, Ground Waters and Precipitation...............2-52

1. Description of Water Sources.......................................................

2-52

2.

Sampling and Analytical Techniques.......................................

2-53

3.

Results and Conclusions..................................................

2-55 I. Estimates of Radiation Does to Man............................................

2-62

1. Pathways to Man - Calculational Models..................................

2-62

2.

Results of Calculated Population Dose to Man - Liquid Effluent Releases..

2-62

3.

Results of Calculated Population Dose to Man - Gaseous Effluent Releases.

2-62

4.

Conclusions..............................................................

2-63 SECTION 3 - LAND USE CENSUS....................................................

3-1 SECTION 4 - SPLIT SAMPLE AND SPIKE SAMPLE, INTER-LABORATORY COMPARISON PROGRAM..................4-1 A.

Split Sample Program (Inter-Laboratory Comparison, Part 1 of 2)...............

4-1 B.

Spike Sample Program (Inter-Laboratory Comparison, Part 2 of 2)...............

4-1 C. Conclusions...................................................................

4-3 Vi

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report EXECUTIVE

SUMMARY

and INDEX3 LIST OF TABLESI Table 2-1 Operational Radiological Environmental Monitoring Program..................

2-2 Table 2-2 Environmental Monitoring Program Results....................................2-63 Table 2-3 Pre-Operational Environmental Radiological Monitoring Program Summary....2-20 Table 2-4 Comparison of Natural Background Exposure Versus Calculated Population Dose to Man - Liquid Effluent Releases......................................

2-64V Table 2-5 Comparison of Natural Background Exposure Versus Calculated Population Dose to Man - Gaseous Effluent Releases......................................2-65 Table 3-1 Location of Nearest Residents, Gardens, Dairy Cows, Doe Goats and Beef Cattle......................................................................................

3-3 Table 4-1 Inter-Laboratory Comparison Program, Spiked Samples - 1st Quarter............ 4-4 Tale4-Ite-LboatryCoprionPrgrmS Smpes-2 Qarer.........U-Table 4-2 Inter-Laboratory Comparison Program, Spiked Samples - 3nd Quarter...........

4-6 Table 4-3 Inter-Laboratory Comparison Program, Spiked Samples - 4th Quarter............ 4-6 vii

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report EXECUTIVE

SUMMARY

and INDEX LIST OF FIGURES Figure 1-1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver V alley Pow er Station........................................................................

1-3 Figure 2-1 Environmental Monitoring Locations - Air Sampling Stations........................

2-25 Figure 2-2 Graph of Annual Average Concentration: Gross Beta in Air Particulates...........

2-26 Figure 2-3 Environmental Monitoring Locations - Shoreline Sediments and Soil...............

2-30 Figure 2-4 Graph of Annual Average Concentration: Cesium-137, Cobalt-58 & 60 In S edim ent......................................................................................

2-3 1 Figure 2-5 Graph of Annual Average Concentration: Cesium-137 in Soil........................

2-32 Figure 2-6 Environmental Monitoring Locations - Feedstuff and Foodcrops....................

2-36 Figure 2-7 Graph of Annual Average Concentration: Cesium-137 in Feedstuff and F oodcrops.....................................................................................

2-37 Figure 2-8 Environmental Monitoring Locations - Milk............................................

2-42 Figure 2-9 Graph of Annual Average Concentration: Iodine-131 & Sr-90 in Milk.............. 2-43 Figure 2-10 Environmental Monitoring Locations - TLDs..........................................

2-46 Figure 2-11 Graph of Annual Average Exposure: Direct Radiation in Environment.............

2-48 Figure 2-12 Environmental Monitoring Locations - Fish.............................................

2-50 Figure 2-13 Graph of Annual Average Concentration: Cesium-137 in Fish.......................

2-51 Figure 2-14 Environmental Monitoring Locations - Ground Water, Surface Water, Drinking W ater and Precipitation.....................................................................

2-57 Figure 2-15 Graph of Annual Average Concentration: Iodine-131 in Surface Water, and D rinking W ater..............................................................................

2-58 Figure 2-16 Graph of Annual Average Concentration: Tritium in Surface Water.................

2-59 Figure 2-17 Graph of Annual Average Concentration: Tritium in Ground Water.................

2-60 Figure 2-18 Graph of Annual Average Concentration: Tritium in Drinking Water...............

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 1 - INTRODUCTION A.

Radiation Fundamentals Radiation is the conveyance of energy through space. For example, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. All matter consists of atoms, which are comprised of positively charged particles (protons), negatively charged particles (electrons), and non-charged/neutral particles (neutrons). The relatively large particles (protons and neutrons) are packed tightly together in a cluster at the center of the atom called the nucleus, while the smaller particles (electrons) orbit around the nucleus. In an electrically neutral atom, the negative charges of the electrons are balanced by the positive charges of the protons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other. This holds the atom together. Other attractive forces between the protons and neutrons keep the densely packed protons from repelling each other, and prevent the nucleus from breaking apart.

B. Radiation and Radioactivity The following provides an alphabetical glossary of terms associated with radiation, radioactivity, and the radioactive decay process. The terms discussed include Alpha Particles, Beta Particles, Gamma Rays, Genetic Effects, Half-life, Ionization, Isotopes, Neutrons, Radiation, Radioactive Decay, Radionuclides and Somatic Effects.

Alpha Particles: Particulate and electromagnetic radiation each travel through matter differently because of their different properties. Alpha particles contain 2 protons and 2 neutrons, are relatively large, and carry an electrical charge of +2. Alpha particles are ejected from the nucleus of a radioactive atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its comparatively large size, an alpha particle usually does not travel very far before it loses most of its energy through collisions and interactions with other atoms. As a result, a sheet of paper or a few centimeters of air can easily stop alpha particles.

Beta Particles: Beta Particles: Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed of light (186,000 miles per second). Beta particles have an electrical charge of either +1 or -1. Because they are so small and have a low charge, they do not collide and interact as often as alpha particles, so they can travel farther. Beta particles can usually travel through several meters of air, but may be stopped by a thin piece of metal or wood.

Gamma Rays: Gamma rays are pure energy and travel at the speed of light. They have no measurable charge or mass, and generally travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamma ray loses its energy and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions. Very high-energy gamma radiation can travel a considerable distance, where as, low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of Lead or concrete may be needed to effectively shield gamma rays.

Genetic Effects: The effects of ionizing radiation which are observed in the offspring of the exposed individual that could occur as a result of ionizing radiation interacting with the genes in the human cells.

Half-life: The length of time an atom remains radioactive is defined in terms of half-life, which is the amount of time required for a radioactive substance to lose half of its activity through the process of radioactive decay. Radionuclides that have infrequent emissions have a long half-life, where as, radionuclides that have more frequent emissions have a short half-life.

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Beaver Valley Power Station RTL A9.690E5 2007 Annual Radiological Environmental Operating Report SECTION 1 - INTRODUCTIONI Ionization: Through interactions with atoms, alpha, beta, and gamma radiation lose their energy.

When these forms of radiation interact with any form of material, the energy they impart may cause atoms in that material to become ions, or charged particles. Normially, an atom has the same number of protons as electrons, thus, the number of positive and negative charges cancel, in which the atom is electrically neutral. When one or more electrons are removed, an ion is formed.

Ionization is one of the processes that may result in damage to biological systems.

Isotopes: A group of identical atoms containing the same number of protons make up an element.3 In fact, the number of protons an atom contains determines its chemical identity. For instance, all atoms with one proton are hydrogen atoms, and all atoms with eight protons are oxygen atoms.

However, the number of neutrons in the nucleus of an element may vary. Atoms with the sameI number of protons but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical properties, and many are stable or non-radioactive. An unstable or radioactive isotope of an element is called a radioisotope, a radioactive atom, or a radionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess energy is usually due to a surplus or deficit in the number of neutrons in the nucleus. Radionuclides such as Uranium-238, Berylium-7 and Potassium-40 occur naturally. Others are man-made, such as Iodine-13 1, Cesium-137, and Cobalt-60.

Neutrons: Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within operating nuclear power reactors. However,3 neutrons are not of environmental concern since the neutron source at nuclear power stations is sealed within the containment building. Because neutrons have no charge, they are able to pass very close to the nuclei of the material through which they are traveling. As a result, neutrons may be3 captured by one of these nuclei or they may be deflected. When deflected, the neutron loses some of its energy. After a series of these deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is called a thermal neutron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel.

Fast neutrons can have from 200 thousand to 200 million times the energy of thermal neutrons.

Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron shielding materials commonly used to slow neutrons down are water or polyethylene. The shield is then completed with a material such as Cadmium, to absorb the now thermal neutrons. Concrete is also used to form an effective neutron shield because it contains water molecules and can be easilyI Radiation: This is the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation isI another type of radiation and has similar properties to those of the examples listed above. Ionizing radiation consists of both electromagnetic radiation and particulate radiation. Electromagnetic radiation is energy with no measurable mass that travels with a wave-like motion through space.

Included in this category are gamma rays and X-rays. Particulate radiation consists of tiny, fast moving particles which, if unhindered, travel in a straight line through space. The three types of particulate radiation of concern to us are alpha particles, which are made up of 2 protons and 2I neutrons; beta particles, which are essentially free electrons; and neutrons. The properties of these types of radiation will be described more fully in the Range and Shielding section.3 1-21

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 1 - INTRODUCTION Radioactive Decay: Radioactive atoms, over time, will reach a stable, non-radioactive state through a process known as radioactive decay, which is the release of energy from an atom through the emission of ionizing radiation. Radioactive atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several daughter products that eventually result in a stable atom. The loss of energy through radioactive decay may transform the atom into a chemically different element. For example, when Uranium-238 decays, it emits an alpha particle and, as a result, the atom loses 2 protons and 2 neutrons. Since the number of protons in the nucleus of an atom determines its chemical identity, then when the Uranium-238 atom loses the 2 protons and 2 neutrons, it is transformed into an atom of Thorium-234. Thorium-234 is one of the 14 successive daughter products of Uranium-238. Radon is another daughter product, and the decay series ends with stable Lead-206. The following example is part of a known radioactive decay series, called the Uranium series, which begins with Uranium-238 and ends with Lead-206. The information provided in the upper portion of each block is the isotope name, while the information provided in the lower portion of each block is the half-life.

2 3 8 U 4.5E+9 Yr 234 U

~'2.5E+5Yr 1 3

~Pa 4

J 1.2 min 1

2 34Th 24 d 2 30Th 8.OE+4 Yr 4

226 Ra 1600 Yr 42i2 RZ Beta Decay Alpha Decay 2183P0 3.05 min 2 14 p0 1.6E-4 s 2 10P0 138.4 d 214Bi

/210 Bi j,, 19.7 m in 5.01 d 2 14 Pb 26.8 min 2 1 0Pb 23 Yr 20 6Pb stable Radionucides: See description for "isotopes".

Somatic Effects: The effects of ionizing radiation which develop in the directly exposed individual, including an unborn child. Somatic effects can be divided further into acute and chronic effects.

Acute effects develop shortly after exposure to large amount of radiation. Chronic effects are a result of exposure to radiation over an extended period of time.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 1 - INTRODUCTION C. Units of Measurement 3

Activity (Curie): This relates the number of atoms in a sample that disintegrate (decay) per unit of time. Each time an atom disintegrates, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms of a radioactive I

substance are decaying. One curie indicates the disintegration of 37 billion atoms per second. A curie is a unit of activity, not a quantity of material. Thus, the amount of material required to produce one curie varies. A smaller unit of the curie is used when discussing the low concentrations of radioactivity detected in environmental samples. For instance, the picocurie (pCi) represents one trillionth of a curie.

Absorbed Dose (rad): This is a term used to describe the radiation energy absorbed by any material I

exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation.

The rad is the unit used to measure the absorbed dose. It is defined as the energy of ionizing radiation deposited per gram of absorbing material (1 rad = 100 erg/gm). The rate of absorbed dose I

is usually given in rad/hr. The rad is not used to quantify biological damage caused by ionizing radiation.

Dose Equivalent (rem): Biological damage due to alpha, beta, gamma and neutron radiation may I

result from ionizing radiation. Some types of radiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological damage for the same energy imparted as do gamma or X-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose (Rad), the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to a particular type of ionizing radiation. The I

dose equivalent is measured in rem. An example of this conversion from absorbed dose (rad) to dose equivalent (rem) uses the quality factor for alpha radiation, which is equal to 20. Thus, 1 Rad of alpha radiation = 20 rem. Since beta and gamma radiation each have a quality factor of 1, then 1 i

Rad of either beta or gamma radiation = 1 rem. Neutrons have a quality factor ranging from 2 to 10.

In terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit, the millirem, is often used, where as, one millirem (mrem) is equal to 1/1000 of a rem.

3 D. Lower Limit of Detection The Lower Limit of Detection (LLD) for environmental samples is a calculated value that represents an a-priori (before-the-fact) limit for the smallest concentration (i.e.; pCi per unit mass or volume)

I of radioactive material in a sample that will be detected with 95% probability, and with 5%

probability of falsely concluding that a blank observation represents a real signal. A calculated LLD must consider such analytical variables as standard deviation of the background counting rate, I

the counting efficiency, the sample size, the fractional radiochemical yield, the radioactive decay constant, and the elapsed time between sample collection and time of counting.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 1 - INTRODUCTION E. Scope and Objectives of the REMP Program The environmental program consists of environmental monitoring for radioactivity in the vicinity of the Beaver Valley Power Station. Environmental sampling and analyses include air, water, milk, vegetation, river sediments, fish, and ambient radiation levels in areas surrounding the site. The results of these media are assessed to determine impacts of the plant operation on the environment.

The Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the Radiological Environmental Monitoring Program (REMP) conducted by the FirstEnergy Nuclear Operating Company during the report period.

F. Description of the Beaver Valley Site The Beaver Valley Power Station is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 501 acre tract of land. The site is approximately one mile from Midland, Pennsylvania; five miles from East Liverpool, Ohio; and twenty-five miles from Pittsburgh, Pennsylvania. Figure 1-1 shows the site location in relation to the principal population centers. Population density in the immediate vicinity of the site is relatively low. The population within a five mile radius of the plant is approximately 15,493 and the only area within the radius of concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 3,321.

The site lies in a valley along the Ohio River. It extends from the river (elevation 665 feet above sea level) to a ridge along the border south of the Beaver Valley Power Station at an elevation of 1,078 feet. Plant grade level is approximately 735 feet above sea level.

The Beaver Valley Power Station is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Dam, and 19.4 miles upstream from New Cumberland Lock and Dam. The Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from the site. The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries.

During the report period, the Ohio River flow (as obtained from the Corps of Engineers - Water Resources Engineering) at the Wheeling Dam ranged from 8,900 cubic feet per second (minimum monthly average) to 113,600 cubic feet per second (maximum monthly average). The mean flow during the report period was 42,767 cubic feet per second.

Water temperature of the Ohio River typically varies from 34' Fahrenheit to 750 Fahrenheit. The minimum temperatures occur in January and/or February and maximum temperatures in July and/or August. Water quality in the Ohio River at the site location is affected primarily by the water quality of the Allegheny, Monongahela and Beaver rivers.

The climate of the area may be classified as humid continental. The predominant wind direction is typically from the southwest in summer and from the west southwest in winter. The National Climate Data Center (http://www.ncdc.noaa.gov/oa/climate/research/cag3/v4.htm]) indicates the following data for the Pittsburgh, PA area:

The total annual precipitation during the report period was 40.18 inches The average mean temperature during the report period was 52.00 Fahrenheit 1-5

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 1 - INTRODUCTION The basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below:

Beaver Valley Unit 1 2900 - megawatts thermal Beaver Valley Unit 2 2900 - megawatts thermal Licensed Power Level Type of Power No. of Reactor Coolant Loops No. of Steam Generators & Type Steam Used by Main Turbine PWR PWR 3

3 3 - Vertical Saturated 3 - Vertical Saturated The units utilize two separate systems (primary and secondary) for transferring heat from the source (the reactor) to the receiving component (turbine-generator). Because the two systems are isolated from each other, primary and secondary waters do not mix; therefore, radioactivity in the primary system water is normally isolated from the secondary system. Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps.

Heat is given up from the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed after passing through the turbine, and returned to the steam generators to begin another steam/water cycle.

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I Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 1 - INTRODUCTION Figure 1-1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver Valley Power Station RTL A9.690E

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20 MILES 40 1-7

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM A.

Environmental Radioactivity Monitoring Program

1.

Program Description The program consists of monitoring water, air, soil, river bottoms, vegetation and food crops, cow's milk, ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table 2-1. Further description of each portion of the program (Sampling Methods, Sample Analysis, Discussion and Results) are included in Sections 2-B through 2-I of this report.

2-B Air Monitoring 2-C -

Monitoring of Sediments and Soils 2-D -

Monitoring of Feedstuff and Foodcrops 2-E Monitoring of Local Cow and Goat Milk 2-F Environmental Radiation Monitoring 2-G -

Monitoring of Fish 2-H -

Monitoring of Surface Water, Drinking Water. Ground Water and Precipitation 2-I Estimates of Radiation Dose to Man 2-1

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E I

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Table 2-1 O0Derational Radiolos-ical Environmental Monitorin Program Section Type of Sample Sample Point Description Sample Sample Preparation Analysis Sample Point Frequency Analysis Frequency 113 Hookstown, PA (Old Meyer Farm)

Continuous Weekly - Air Gross Beta Particulate &

27 Aliquippa, PA (Brunton Farm)

Sampling with Particulate (b)

Radionuclide 28 Sherman Farm Sample 29B Beaver, Pa (Friendship Ridge)

Collection at least Weekly - Charcoal Iodine-131 30 Shippingport, PA (Cook's Ferry Substation) weekly 32 Midland, PA (North Substation)

Quarterly Composite Gamma Scan 46.1 Industry, PA (McKeel's Service - Rt. 68)

(c) 47 East Liverpool, OH (Water Department) 48 (a)

Weirton, WV (Water Tower - Collier Way) 1 1

51 Aliquippa, PA (Sheffield Substation) 2 Direct Radiation 10 13 14 15 27 28 29B 30 32 33-44 45 45.1 46 46.1 47 48 (a) 51 52-56 59 60 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 111-112 Shippingport, PA (Post Office)

Hookstown, PA (Old Meyer Farm)

Hookstown, PA Georgetown, PA (Post Office)

Aliquippa, PA (Brunton Farm)

Sherman Farm Beaver, PA (Friendship Ridge)

Shippingport, PA (Cook's Ferry Substation)

Midland, PA (North Substation)

BVPS Site Perimeter Locations Raccoon Township, PA (Christian House Baptist Chapel - Rt. 18)

Raccoon Township, PA (Kennedy's Corner)

Industry, PA (Midway Drive)

Industry, PA (McKeel's Service - Rt. 68)

East Liverpool, OH (Water Department)

Weirton, WV (Water Tower - Collier Way)

Aliquippa, PA (Sheffield Substation)

BVPS Site Perimeter Locations 236 Green Hill Road Georgetown, PA (444 Hill Road)

Industry, PA (236 Engle Road)

Brighton Township, PA (First Western Bank)

Ohioview, PA (Lutheran Church - Rear) 618 Squirrel Run Road Monaca, PA (37 Poplar Avenue - CCBC)

Aliquippa, PA (117 Holt Road)

Raccoon Township, PA (Elementary School)

Aliquippa, PA (3614 Green Garden Road)

Raccoon Township, PA (Municipal Building) 106 Rt. 151 - Ted McWilliams Auto Body Raccoon Township, PA (Park Office -Rt. 18)

Millcreek United Presbyterian, Church 2697 Rt. 18 735 Mill Creek Road Hancock County, WV (Senior Center) 2048 Rt. 30 East Liverpool, OH (1090 Ohio Avenue) 50103 Calcutta Smith's Ferry Road Midland, PA (110 Summit Road)

Ohioville, PA (488 Smith Ferry Road)

Midland, PA (6286 Tuscarawras Road)

Pine Grove Road & Doyle Road Georgetown, PA (Georgetown Road Substation) 104 Linden - Sunrise Hills Hookstown, PA (McCleary & Pole Cat Hollow Roads)

Hookstown, PA (832 McCLeary Road)

BVPS Site Perimeter Locations Continuous (TLD)

Quarterly (i)

Gamma Dose I

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Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 RTL A9.690E perational Radiological Environmental Monitoring Program Type of Sample Sample Point Description Sample Frequency Aalepis Analysis Section Sample Point Analysis Frequency 49a Weekly Grab 3

Surface 4a Industry, PA (Upstream of Montgomery Sample (h)

Weekly Sample from Water (a)

Dam)

Site49 only Iodine-131 Weekly Intermittent Composite Sample Monthly Composite of 2.1 Midland, PA (ATI Allegheny Ludlam)

(h)

Weekly Sample (c)

Gamma Scan Daily Grab Sample 5

East Liverpool, OH (Water Department)

Collected Weekly Quarterly Composite (c)

(h)

Tritium (H-3) 11 (a)

Shippingport, PA (Upstream)

Gamma Scan 4

Groundwater 14a Hookstown, PA (Downstream)

Semi-Annual Semi-Annual Tritium (H-3) 15b Georgetown, PA (Downstream) 5 Drinking 4

Midland, PA (Water Department)

Weekly Composite of Water 5

East Liverpool, OH (Water Department)

Intermittent (d)

Daily sample (d)

Iodine-131 Sample Collected Monthly Composite (d)

Gamma Scan Weekly Quarterly Composite (d)

Tritium (H-3) 2A BVPS Outfall Vicinity 6

Shoreline 49a Industry, PA (Upstream of Montgomery Semi-Annual Semi-Annual Gamma Scan Sediment (a)

Dam) 50 New Cumberland, WV (Upstream of Dam) 7 Milk Weekly (e)

Weekly Samples from Weekly 25 Hookstown, PA (Searight Farm)

Searight only Iodine-1 31 from Searight only 27a (k)

Aliquippa, PA (Brunton Farm) 69 (k)

Aliquippa, PA (Collins Farm)

Biweekly (f) When All other samples &

Gamma Scan 96 (a)

Burgettstown, PA (Windsheimer Farm) animals are on analyses are Biweekly Iodine-131 113 (k)

Hookstown, PA (Halstead Farm) pasture; monthly at during grazing, but Strontium-89 other times Monthly during other Strontium-90 114 (k)

Hookstown, PA (Moore Farm) times 2A BVPS Outfall Vicinity Gamma Scan 8

Fish Industry, PA (Upstream of Montgomery Semi-Annual Composite of edible on edible 49a Dam) parts by species (g) parts 10a Shippingport, PA Gamma Scan 9

Food 15a Georgetown, PA Annual at Harvest Composite of each iodine-131 on Products 46a Industry, PA if available sample species green leafy 48a Weirton, WV vegetables Feedstuff &

25 Hookstown, PA (Searight Farm)

Monthly Monthly Gamma Scan 10 Summer Forage 13a Hookstown, PA (Old Meyer Farm) 11 Soil 22 South of BVPS, Transmission Lines Every Three (3) 12 Core Samples 3" Gamma Scan 27b Aliquippa, PA (Brunton Farm)

Years Deep (2' diameter at 29A Beaver, PA (Nicol Farm)

(1997, 2000, 2003) each location approx. 10' 29A

eave, P

(Niol Frm)radius)

Shippingport, PA (Cook's Ferry 30a Substation) 32a Midland, PA (North Substation) 46b Industry, PA (Willows Inn - Rt. 68) 47a East Liverpool, OH (Water Department) 48 (a)

Weirton WV (Water Tower - Collier Way) 51a Aliguippa, PA (Sheffield Substation) 30 Shippingport, PA (Cook's Ferry Weekly grab 12 Precipitation Substation) samples when Quarterly Composite (c)

Gamma Scan 47 East Liverpool, OH (Water Department) available Tritium (H-3) 48 (a)

Weirton WV (Water Tower-Collier Way) 2-3

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 Operational Radiological Environmental Monitoring Program RTL A9.690E Notes for Table 2-1 (a)

Control Sample Station: These Locations which are presumed to be outside the influence of plant effluents.

Particulate Samples are not counted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter change. Perform Gamma (b) isotopic analysis on each sample when gross beta is greater than 10 times the yearly mean of control samples.

(c)

Long-term composite samples are obtained from short-term composite samples at the specified locations.

(d)

Composite samples are collected at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

(e)

Weekly milk sample from the Searight Dairy is analyzed for Iodine-131 only.

(f)

Milk samples are collected bi-weekly when animals are grazing. The milk samples are collected monthly at other times.

(g)

The fish samples contain whatever species are available.

IF adequate sample size is available, THEN the sample is separated according to species, and compositing will provide one sample of each species.

IF adequate sample size is not available, THEN separation by species is not practical. Therefore edible parts of all fish in the sample are mixed to provide one sample.

(h)

Composite samples are obtained by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at location 2.1. The water treatment plant operator at location 5 obtains the weekly grab sample from the daily composite grab samples. For location 49a, the weekly grab sample is obtained by a field technician.

(i)

Two (2) TLDs are collected quarterly from each monitoring location.

(k)

Offsite Dose Calculation Manual procedure 1/2-ODC-3.03, Attachment Q, Table 3.12-1 requires three (3) dairies to be selected on basis of highest potential thyroid dose using milch census data. See Section 2-E of this report (Monitoring of Local Cows Milk) for specific locations sampled.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

2. Summary of Results All results of this monitoring program are summarized in Table 2-2. This table is prepared in the format specified by the NRC via the Branch Technical Position in NUREG-1301, and in accordance with Beaver Valley Power Station Offsite Dose Calculation Manual. Summaries of results of analysis of each media are discussed in Sections 2-B through 2-H and an assessment of radiation doses are given in Section 2-I. Table 2-3 summarizes Beaver Valley Power Station pre-operational ranges for the various sampling media during the years 1974 and 1975.

Comparisons of pre-operational data with operational data indicate the ranges of values are generally in good agreement for both periods of time.

Activity detected was attributed to naturally occurring radionuclides, BVPS effluents, previous nuclear weapons tests or to the normal statistical fluctuation for activities near the Lower Limit of Detection (LLD).

The conclusion from all program data is that the operation of the Beaver Valley Power Station has resulted in no significant changes to the environment.

3. Quality Control Program The Quality Control Program implemented by the Beaver Valley Power Station to assure reliable performance by the contractor and the supporting QC data are presented and discussed in Section 4 of this report.

4. Program Changes There were no changes of significance to the sampling program during the report period.

2-5

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2007 Medium: Air Particulate and Radioiodine Unit of Measurement: (pico Curies / cubic meter)

RTL A9.690E I

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I Type and Lower Number of Total Number Limit of All Indicator Location* Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b)

Name Mean (fraction) b)

Name Mean (fraction) () Reported Performed LLD "'

Range 'b')

Distance and Direction Range (b)

Distance and Direction Range (b)

Measurements Gross Beta

< 0.004 0.029 ( 468 / 468)

No. 47 East Liverpool, OH 0,030 ( 52 / 52

) No. 48 Weirton, WV 0.030 ( 52 / 52 )

0 520 0.012 -0.055 Water Department 0.015 - 0.048 Water Tower 0.012 - 0.052 4.88 miles WNW Collier Way 16.40 miles SSW 1-131

<0.04 LLD(

0/468 LLD(

0/468 LLD(

0/52 0

520 Garmmra 40 Be-7 NA 0.089 (

36 / 36 No. 27 Alliquippa. PA 0.093 (

4 /4

) No. 48 Weirton, WV 0.090 ( 4/4 NA 0.063 - 0.114 Brunton Farm 0.067 -0.114 Water Tower 0.066 - 0,111 6.14 Miles SE Collier Way 16.40 miles SSW Co-60

< 0.0003 LLD(

0 / 36

)

LLD(

0 /36

)

LLD(

0 /4

)

0 Cs-134

<0.0004 LLD(

0 /36 LLD 0/36 )

LLD(

0/4 )

0 Cs-137

< 0.0004 LLD(

0 / 36 LLD(

0 /36

)

LLD(

0 /4

)

0 Ba-La-140

< 0.0005 LLD(

0 / 36 LLD(

0 /36

)

LL ( 0/4 )

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I Nominal Lower Limit of Detection h Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-6

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year -2007 Medium: Drinking Water Unit of Measurement: (pico Curies / liter)

RTL A9.690E Type and Lower Number of Total Number Limit of All Indicator Location., Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b)

Name Mean (fraction) (b) Name Mean (fraction) (h Reported Performed LLD (')

Range 'h' Distance and Direction Range (b)

Distance and Direction Range (b, Measurements 1-131

<0.5 0.650 (

44 / 104 )

No. 5 East Liverpool OH 0.700 ( 22 /52 No. 49 Industry, PA 0.900 ( 40 /52 )

0 156 0.200 - 1.500 Water Department 0.200 - 1.500 Upstream of 0.300 - 2.900 4.90 miles WNW Montgomery Dam 4.92 miles NE H-3

<200 LLD(

0/8

)

LLD(

0/4

)

LLD 0/4 )

0 12 Gamma 36 Mn-54

<5 LLD(

0/

24

)

LLD(

0/24

)

LLD(

0/12) 0 Fe-59

< 10 LLD 0/24

)

LLD(

0/24

)

LLD(

0/12) 0 Co-58

<5 LLD(

0/24

)

LLD(

0/24

)

LLD(

0/12) 0 Co-60

<5 LLD(

0 /24

)

LLD(

0/24

)

LLD(

0/12) 0 Zn-65

< 10 LLD (

0 /24

)

LLD (

0 /24

)

LID (

0 /12

)

0 Zr-Nb-95

< 5 LLD(

0 / 24

)

LLD(

0 /24

)

LLD(

0 /12) 0 Cs-134

< 5 LLD 0 / 24

)

LLD(

0 /24

)

LLD(

0 /12) 0 Cs-137

< 5 LLD(

0 / 24

)

LLD(

0 /24 LLD(

0 /12) 0 Ba-La-140

< 15 LLD 0 /2

)

LLD(

0/2-

)

LLD (0

/12 0

Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

'Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-7

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year -2007 Medium: Surface Water Unit of Measurement: (pico Curies / liter)

RTL A9.690E I

Type and Lower Number of Total Number Limit of AlI Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (bl Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD ")

Range (bý Distance and Direction Range (b)

Distance and Direction Range (b)

Measurements 1-131

< 0.5 No. 49 Industry, PA 0.900 ( 40 / 52 )

0 52 Upstream of 0.300 2,900 Montgomery Dam 4.92 miles NE H-3

<200 LLD (

0/8

)

LLD(

0/4 LLD(

0/4 )

0 12 Gamma 36 Mn-54

<5 LLD(

0/24

)

LLD(

0/24

)

LLD 0/12) 0 Fe-59

< 10 LLD(

0/24 )

LLD(

0/124

)

LLD(

0/12) 0 Co-58

< 5 LLD(

0 / 24)

LLD(

0 /24)

LLD(

0 /12) 0 Co-60

<5 LLD(

0/24

)

LLD(

0/24

)

LLD(

0/12) 0 Zn-65

< 10 LLD(

0/24

)

LLD(

0/24

)

LLD(

0/12) 0 Zr-Nb-95

<5 LLD(

0/24 )

LLD(

0/24 )

0LD(

0/12) 0 Cs-134

<5 LLD(

0/24 )

LLD(

0/24

)

LLD(

0/12) 0 Cs-137

< 5 LLD(

0 /24

)

LLD(

0/24

)

LLD(

0 /12) 0 Ba-La-140

< 15 LLD(

0 /2

)

LLD(

0/24 )

LLD(

0 /12) 0 Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)

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Beaver Valley Power Station 2006 Annual Radiological Enviromnental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

RTL A9.690E Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-33M / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2007 Medium: Ground Water Unit of Measurement: (pico Curies / liter)

Type and Lower Number of Total Number Limit of All Indicator Location, Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b)

Name Mean (fraction) W Name Mean (fraction) (b) Reported Performed LLD ("

Range (b)

Distance and Direction Range Distance and Direction Range (b)

Measurements H-3

< 200 LLD(

0 /4

)

LLD(

0 /4

) No. I IShippingport, PA LLD (

0 /2 0

6 Upstream 0.94 miles NE Gamia No. 11 Shippingport, PA 6

Upstream 0.94 miles NE Mn-54

<5 LLD(

0/4

)

LLD(

0/4

)

LLD(

0/2 0

Fe-59

< 10 LLD(

0/4

)

LLD(

0/4

)

LLD(

0/2 0

Co-58

<5 LLD(

0/4

)

LLD(

0/4

)

LLD(

0/2 0

Co-60

< 5 LLD(

0 /4

)

LLD(

0 /4

)

LLD(

0 /2 0

Zn-65

< 10 LLD(

0/4

)

LLD(

0/4

)

LLD(

0/2 0

Zr-Nb-95

<5 LLD(

0/4

)

LLD(

0/4

)

LLD(

0/2 0

Cs-134

<5 LLD(

0/4

)

LLD(

0/4

)

LLD(

0/2 0

Cs-137

<5 LLD(

0/4

)

LLD(

0/4

)

LLD(

0/2 0

Ba-La-140

<15 LLD(

0/4

)

LLD(

0/4

)

LLD(

0/2 0

Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 112-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-9

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2007 Medium: Precipitation Water Unit of Measurement: (pico Curies / liter)

RTL A9.690E Type and Lower Number of Total Number Limit of All Indicator Location, Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b)

Name Mean (fraction) (b)

Name Mean (fraction) (b) Reported Performed LLD (')

Range ("

Distance and Direction Range (b)

Distance and Direction Range (Wi Measurements W H-3

< 200 294 (

2 / 8

)

No. 30 Shippingport PA 294 2 /4

) No. 48 Weirton, WV LLD ( 0 / 4

)

0 12 240 - 348 Cook's Ferry Substation 240 - 348 Water Tower 0.43 miles ENE Collier Way 16.40 miles SSW Gamma 12 Mn-54

<5 LLD(

0/8

)

LLD(

0/8

)

LLD(

0/4 )

0 Fe-59

< 10 LLD(

0 /8

)

LLD(

0/8

)

LLD(

0/4 )

0 Co-58

<5 LLD(

0/8

)

LLD(

0/8

)

LLD(

0/4 )

0 Co-60

<5 LLD(

0/8

)

LLD(

0/8

)

LLD(

0/4 )

0 Zn-65

< 10 LI

(

0/8

)

LLD(

0/8

)

LLD(

0/4 )

0 Zr-Nb-95

<5 LLD(

0/8

)

LLD(

0/8

)

LLD(

0/4 )

0 Cs-134

<5 LLD 0/8

)

LLD(

0/8

)

LLD(

0/4 )

0 Cs-137

<5 LLD(

0/8

)

LLD(

0/8

)

LLD(

0/4 )

0 Ba-La-140

<15 LLD(

0/8

)

LLD(

0/8

)

LLD(

0/4 )

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' Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

SNonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-10

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 /50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2007 Medium; Milk Unit of Measurement: (pico Curies / liter)

Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction)

Name Mean (fraction) N Name Mean (fraction) (

Reported Performed LLD Range 'b' Distance and Direction Range (b)

Distance and Direction Range (bh Measurements 1-131

< 0.5 LLD(

0 /105

)

LLD(

0 / 105)

No. 96Burgettstown, PA LLD(

0 /21) 0 126 Windsheinmr Farm 10.48 miles SSW Sr-89

< 2.0 LLD(

0 / 75

)

LLD 0 /75

) No. 96Burgettstown, PA LLD(

0 /21 0

96 Windsheinmr Farm 10.48 miles SSW Sr-90

< 0.7 1.443 (

67 / 75

)

No. 69 Alliquippa, PA 2.027 ( 11 /12

) No. 96 Burgettstown, PA 1.068 ( 19 / 21 )

0 96 0.600 - 2.9 Collings Farm 1.600 - 2.900 Windsheimer Farm 0.600 - 1.600 3.55 miles SE 10.48 miles SSW Gamma 96 K-40

<NA 1415 (

75/

75

)

No 69Alliquippa, PA 1696 ( 12 / 12

) No. 96 Burgettstown. PA 1403 ( 21 /21

)

NA 1148-1831 Collings Farm 1617 -1831 Windsheimer Farm 1309 1493 3.55 miles SE 10.48 miles SSW Mn-54

< 5 LLD(

0 / 75

)

LLD(

0 /75

)

LLD(

0/21) 0 Fe-59

< 10 LLD (

0 /75

)

LLD(

0 /75

)

LLD(

0 /21) 0 Co-58

< 5 LLD(

0 / 75)

LLD(

0 /75)

LLD(

0 /21) 0 Co-60

< 5 LLD(

0 /75

)

LLD(

0 /75

)

LLD(

0 /21) 0 Zn-65

< 10 LLD(

0 /75

)

LLD(

0 /75

)

LLD(

0 /21) 0 Zr-Nb-95

< 5 LLD(

0 / 75

)

LLD(

0 /75

)

LLD(

0 /21) 0 Cs-134

< 5 LLD(

0 / 75

)

LLD(

0 /75

)

LLD(

0 /21) 0 Cs-137

< 5 LLD(

0 / 75

)

LLD(

0 /75

)

LLD(

0 /21) 0 Ba-La-140

< 15 LLD(

0 / 75

)

LLD(

0 /75

)

LLD(

0 /21) 0 Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nouroutine Reported Measurements (

Reference:

ODCM procedure 11-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-11

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2007 Medium: Fish Unit of Measurement: (pico Curies / gram) Wet RTL A9.690E U

U Type and Lower Number of Total Number Limit of AD Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b Name Mean (fraction)(b Name Mean (fraction) (b) Reported Performed LLD ")

Range Distance and Direction Range (b)

Distance and Direction Range (b)

Measurements 4.)

Gamma Mn-54

<0.05 LLD(

0 /

)

LLD (

/

)

LLD (0/

)

0 Fe-59

< 0.10 LLD(

0 /

)

LLD(

0 /

)

LD(

0/

)

0 Co-58

<0.05 LLD(

0 /

)

LD(0/

)

LLD (0/

)

0 Co-60

<0.05 LLD(

0 /

)

LLD (

/

)

LLD (

/

)

0 Zn-65

<0.10 LLD(

0/

)

LLD(

0/

)

LLD(

0/

)

0 Zr-Nb-95

<0.03 LLD(

0 /

)

LLD(

0/

)

LLD 0/

)

0 Cs-134

<0.05 LLD(

0 /

)

LLD(

0 /

)

LLD(

0 /

)

0 Cs-137

< 0.05 LLD(

0 /

)

LD(

0 /

)

LLD(

0 /

)

0 Ba-1s-140

<0.07 LLD(

0 /

)

LLD(

0 /

)

LLD(

0/

)

0 Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)

I 2-12 I1

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2007 Medium: Foodcrops Unit of Measurement: (pico Curies / gram) Wet RTL A9.690E Type and Lower Number of Total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) No Name Mean (fraction) (b)

Name Mean (fraction) ()

Reported Performed LLD "'I Range 'b' Distance and Direction Range N Distance and Direction Range W Measurements 1-131

< 0.06 LLD (

0 /4

)

LLD (

0 /4

)

LLD (

0 /1 0

5 Gamma 5

K-40 NA 2.400 (

4/ 4

)

No. 46 Industry, PA 2.710 (

1 / 1 No. 48a Weirton, WV 1.890 (

1 / 1 NA 1.980- 2.710 1801 Beaver Ave.

2.710 - 2.710 Weirton Area 1.890 - 1.890 3.39 miles NE 16.54 miles SSW Mn-54

<0.05 LLD(

0 /4 LLD(

0/4 LLD(

0/1

)

0 Fe-59

<0.10 LLD(

0 /4 LLD (0/4

)

LLD (0/1) 0 Co-58

< 0.05 LLD(

0 / 4

)

LLD(

0 /4

)

LLD(

0 / 1 )

0 Co-60

<0.05 LLD(

0/4

)

LLD(

0/4

)

LLD(

0/1

)

0 Zn-65

< 0.10 LLD(

0 /4

)

LLD(

0 /4

)

LLD(

0 / 1

)

0 Zr-Nb-95

< 0.03 LLD(

0 /4

)

LLD(

0 /4

)

LLD(

0 / 1

)

0 Cs-134

< 0.05 LLD(

0 /4

)

LLD(

0 /4

)

LLD(

0 /1

)

0 Cs-137

< 0.05 LLD(

0 /4

)

LLD(

0 /4

)

LLD(

0 /1

)

0 Ba-La-140

< 0.07 LLD(

0 /4

)

LLD(

0 /4

)

LLD(

0 /1

)

0 Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

SNonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-13

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2007 Medium: Feedstuff Unit of Measurement: (pico Curies I gram) Wet RTL A9.690E Type and Lower Number of Total Number Limit of All Indicator Locatiom Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) N Name Mean (fraction) (b) Name Mean (fraction) W Reported Performed LLD (')

Range (b)

Distance and Direction Range (b)

Distance and Direction Range Wb)

Measurements Gamma 12 Be-7

< NA 0.770(

7/

12

)

No. 25 SeanghtFarm 0.770 (

7 / 12

) No. 25 Seanight Farm 0.770 (

7 / 12 )

NA 0.350 - 1.270 948 McCleary Road 0.350 - 1.270 948 McCleary Road 0.350 - 1.270 Hookstown, PA Hookstown, PA 2.10 miles SSW 2.10 miles SSW K-40

<NA 10.83 (

12/

12

)

No. 25 Searight Farm 10.83 ( 12/

12

) No. 25 Searight Farm 10.83 ( 12 / 12 )

NA 7.97-17.13 948 McCleary Road 7.97-17.13 948 McCleary Road 7.97-17.13 Hookstown, PA Hookstown, PA 2.10 miles SSW 2.10 miles SSW Mn-54

< 0.05 LLD(

0 / 12

)

LLD(

0/12

)

LLD(

0/12) 0 Fe-59

< 0.10 LLD(

0 / 12

)

LLD(

0/12)

LLD(

0/12) 0 Co-58

< 0.05 LLD(

0 / 12 LLD(

0

/12 LLD 0/12) 0 Co-60

<0.05 LLD(

0/12

)

LLD(

0/12 LLD 0/12) 0 Zn-65

<0.10 LLD(

0/12

)

LLD(

0/12 LLD(

0/12) 0 Zr-Nb-95

< 0.03 LLD (

0 / 12

)

LLD (

0 /12

)

LLD (

0/12 )

0 Ru-103

< 0.04 LLD (

0 / 12

)

LLD(

0 /12

)

LLD(

0 / 12) 1-131

< 0.06 LLD(

0 / 12

)

LD(

0 /12

)

LLD(

0 / 12) 0 Cs-134

< 0.05 LLD(

0 / 12

)

LLD(

0 /12

)

LLD(

0 /12) 0 Cs-137

< 0.05 LLD(

0 / 12

)

LLD(

0/12

)

LLD(

0/12) 0 Ba-La-140

< 0.07 LLD(

0 / 12

)

LLD(

0/12

)

LLD(

0/12) 0 Nominal Lower Limit of Detection I

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b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-14

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2007 Medium: Sediment (page 1 of 2)

Unit of Measurement: (pico Curies / gram) Dry Type and Lower Number of Total Number Limit of All Indicator Locationi Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction)

Name Mean (fraction) (b)

Name Mean (fraction) (" Reported Performed LLD "'

Range b Distance and Direction Range Distance and Direction Range jMeasurements Gamma 6

K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nbh-95 Cs-134 Cs-137 Ba-La-140 TI-208 NA

< 0.05

< 0.10

< 0.05

< 0.05

< 0.10

< 0.03

< 0.03

< 0.05

< 0.05

< 0.07 NA 10.72(

4/4

)

7.99-14.75 LLD(

0 /4

)

LLD(

0/4

)

0,11(

1 /4

)

0.11 - 0.11 0.16 (

1 /4 0.16- 0.16

)

LLD(

LLD LLD 0/4

)

0/4 0/4

)

No. 2A BVPS Outfall Vicinity 0.31 miles WSW No. 2A BVPS Outfall Vicinity 0.31 miles WSW No. 2A BVPS Outfall Vicinity 0.31 miles WSW No. 2A BVPS Outfall Vicinity 0.31 miles WSW No. 50 New Cumberland, WV Upstream of Dam 11.77 miles WSW No. 2A BVPS Outfall Vicinity 0.31 miles WSW 0.11(

1 /2 0.11 - 0.11 0.16(

1 /2 0,16- 0.16 LLD (

0/4 13.42(

2 / 2 12,08 - 14.75 LLD(

0/4 4 LLD(

0/4 4 No. 49a Industry, PA Upstream of Montgomery Dam 4.93 miles NE LLD(

LLD(

0/4 0/4 LLD(

0/4 0.10(

4 /4 0.06- 0.13 LLD (

0 / 4 0.35 (

4 /4 0.26- 0.46 LLD (

0/4 0.13 (

2/2 0.12- 0.13 0.06 ( 2 /2 0.06- 0.06 LLD(

0/4 0.42(

2 /2 0.38 - 0.46 No. 49a Industry, PA Upstream of Montgomery Dam 4.93 miles NE No. 49a Industry, PA Upstream of Montgomery Dam 4.93 miles NE No. 49a Industry, PA Upstream of Montgomery Dam 4.93 miles NE No. 49a Industry, PA Upstream of Montgomery Dam 4.93 miles NE 10.83 (

2/2

)

9.24-12.42 LLD (

0/2 LLD (

0/2 LLD ( 0/2 )

LLD(

0/2 )

LLD(

0/2 LLD(

0/2 LLD (

0/2 LLD(

0/2 )

0.08 (

2 /2 0.07- 0.08 LLD (

0 /2 0.34 (

2 /2 0.29- 0.39

)

)

)

2-15

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-3-34 / 50413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year -2007 Medium: Sediment (page 2 of 2)

Unit of Measurement: (pico Curies / gram) Dry Type and Lower Number of Total Number Limit of All Indicator Location, Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b)

Name Mean (fraction) (b)

Name Mean (fraction) (b) Reported Performed LLD ()

Range (b*

Distance and Direction Range (b)

Distance and Direction Range (b)

Measurements (0 Bi-214 NA 0.81 (

4 / 4

)

No. 2A BVPS 0.94 ( 2 /2

) No. 49alndustry, PA 0.73 (

2 /2

)

NA 0.64- 0.96 Outfall Vicinity 0.92- 0.96 Upstream of 0.67- 0.78 0.31 miles WSW Montgomery Dam 4.93 miles NE Pb-212 NA 1.17 (

4 /4

)

No. 2A BVPS 1.49 (

2 /

2

) No. 49aIndusty, PA 0.94 ( 2/2 )

NA 0.75 - 1.52 Outfall Vicinity 1.45 - 1.52 Upstream of 0.89 - 0.99 0.31 miles WSW Montgomery Dam 5 miles NE Pb-214 NA 0.94 (

4 /4

)

No. 2A BVPS 1.09 (

2 /

2 ) No. 49aIndustry, PA 0.85 ( 2/2 )

NA 0.75 - 1,19 Outfall Vicinity 0.99-1.19 Upstream of 0.69-1.01 0.31 miles WSW Montgomery Dam 5 miles NE Ra-226 NA 1.88 (

4 /4

)

No. 2ABVPS 2.32 ( 2/2

) No. 49aIndustry, PA 1.83 ( 2/2 )

NA 1.17 - 2.48 Outfall Vicinity 2.15-2.48 Upstream of 1.50-2.15 0.31 miles WSW Montgomery Dam 5 mites NE Ac-228 NA 1.11 (

4 /4 No. 2ABVPS 1.33 ( 2/2

) No.,49alndustry, PA 1.02 ( 2/2 )

NA 0.80-1.42 Outfall Vicinity 1.24-1.42 Upstream of 0.92-1.11 0.31 miles WSW Montgomery Dam 5 miles NE I

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I Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-16 I

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver Countv. Pennsylvania Reporting Period: Calendar Year - 2007 Medium: Soil (page 1 of 2)

Unit of Measurement: (pico Curies / gram) Dry RTL A9.690E Type and Lower Number of Total Number Limit of All Indicator Location, Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) Wb)

Name Mean (fraction) (b) Name Mean (fraction) ýb) Reported Performed LLD 1Range (Distance and Direction Range W Distance and Direction Range Measurements Gamma Note: Soil Sampling performed every three (3) years. Sampling was performed in 2006, and is next due in 2009.

K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 2-17

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2007 Medium: Soil (page 2 of 2)

Unit of Measurement: (pico Curies / gram) Dry RTL A9.690E I

U I

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Type and Lower Number of Total Number Limit of All Indicator Locatiow Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b)

Name Mean (fraction) (b' Name Mean (fraction)b) Reported Performed {LLD '

Rne Distance and Direction

[Range Mb)

Distance and Direction Range W Measurements 10 Note: Soil Sampling performed every three (3) years. Sampling was performed in 2006, and is next due in 2009.

Ba-La-140 TI-208 I

Bi-214 I

Pb-212 I

Pb-214 Ra-226 3

Ac-228 Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-18 I

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Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2006 Medium: External Radiation Unit of Measurement: (mR / Quarter)

RTL A9.690E Type and Lower Number of Total Number Limit of All Indicator Locatjo, Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b)

Name Mean (fraction)

Name Mean (fraction) (b) Reported Performed LLD Range 'b)

Distance and Direction Range (b)

Distance and Direction Range (b)

Measurements Gamma 4.6 17.8(

500- 500)

No. 35BVPSSite 22.0 (

8/s

) No. 48Weirton, WV 19.3 (

8 /8 0

508 11.0 - 23.5 Perimeter 20.4-22.9 Water Tower 17.7 -20.3 Location Collier Way 16.40 miles SSW

'Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-19

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Table 2-3 Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis of Detection Mean, (f) Range (Unit of Measurement)

Performed (LLD)

Sediments Gross Alpha (0)

(pico Curie/gram) dry Gross Beta (33) 1 18 (33/33) 5 - 30 Sr-90 (0)

U-234, 235,238 (0)

Gamma (33) 13 (33/33) 2 - 30 K-40 1.5 13 (33/33) 2-30 Cs-137 0.1 0.4 (21/33) 0.1 - 0.6 Zr/Nb-95 0.05 0.8 (12/33) 0.2 - 3.2 Ce-144 0.3 0.5 (3/33) 0.4 - 0.7 Ru-106(a) 0.3 1.5 (3/33) 1.3-1.8 Others

< LLD Foodcrops Gamma (8)

(pico Curie /gram) dry K-40 1

33 (8/8) 10 - 53 Cs-137 0.1 0.2 (1/8)

Zr/Nb-95 0.05 0.2 (1/8)

Ru-106(a) 0.3 0.8 (1/8)

Others

< LLD Feedstuff Gross Beta (80) 0.05 19 (80/80) 8 - 50 (pico Curie/gram) dry Sr-89 (81) 0.025 0.2 (33/81) 0.04 - 0.93 Sr-90 (81) 0.005 0.4 (78/81) 0.02 - 0.81 Gamma (81)

K-40 1

19 (75/81) 5-46 Cs-137 0.1 0.5 (6/81) 0.2-1.6 Ce-144 0.3 1.5 (5/81) 0.9 - 2.6 Zr/Nb-95 0.05 0.8 (13/81) 0.2-1.8 Ru-106(a) 0.3 1.4 (12/81) 0.6-2.3 Others

< LLD Soil Gross Alpha (0)

- Template Samples -

Gross Beta (64) 1 22 (64/64) 14 - 32 Sr-89 (64) 0.25 0.4 (1/64)

(pico Curie /gram) dry Sr-90 (64) 0.05 0.3 (48/64) 0.1 - 1.3 U-234, 235,238 (0)

Gamma (64)

K-40 1.5 13 (63/64) 5-24 Cs-137 0.1 1.5 (56/64) 0.1 - 6.8 Ce-144 0.3 1.1 (7/64) 0.2 - 3 Zr/Nb-95 0.05 0.3 (13/64) 0.1 - 2 Ru-106(a) 0.3 1.1 (3/64) 0.5 - 2 Others

< LLD (f)

Fraction of detectable measurements at specified location.

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I 2-20

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-3 (Continued)

Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis of Detection Mean, (f) Range (Unit of Measurement)

Performed (LLD)

Soil Gross Alpha (0)

- Core Samples -

Gross Beta (8) 1 21 (8/8) 16 - 28 (pico Curie /gram) dry Sr-89 (8) 0.25

< LLD Sr-90 (8) 0.05 0.2 (5/8) 0.08 - 0.5 Gamma (8)

K-40 1.5 13 (8/8) 7-20 Cs-137 0.1 1.2 (7/8) 0.2 -2.4 Co-60 0.1 0.2 (1/8)

Others

< LLD Surface Water Gross Alpha (40) 0.3 0.75 (5/40) 0.6 - 1.1 (pico Curie / liter)

Gross Beta (120) 0.6 4.4 (120/120) 2.5 - 11.4 Gamma (1) 10-60

< LLD Tritium (121) 100 300 (120/121) 180-800 Sr-89 (0)

Sr-90 (0)

C-14 (0)

Drinking Water 1-131 (0)

(pico Curie / liter)

Gross Alpha (50) 0.3 0.6 (4/50) 0.4 - 0.8 Gross Beta (208) 0.6 3.8 (208/208) 2.3 - 6.4 Gamma (0)

Tritium (211) 100 310 (211/211) 130-1000 C-14 (0)

Sr-89 (0)

Sr-90 (0)

Ground Water Gross Alpha (19) 0.3

< LLD (pico Curie / liter)

Gross Beta (76) 0.6 2.9 (73/75)(b) 1.3 - 8.0 Tritium (81) 100 440 (77/81)80-800 Gamma (1) 10 - 60

< LLD Air Particulates Gross Alpha (188) 0.001 0.003 (35/188) 0.002 - 0.004 and Gaseous Gross Beta (927) 0.006 0.07 (927/927) 0.02 - 0.32 (pico Curie /cubic meter)

Sr-89 (0)

Sr-90 (0) 1-131 (816) 0.04 0.08 (2/816) 0.07 - 0.08 Gamma (197)

Zr/Nb-95 0.005 0.04 (122/197) 0.01 - 0.16 Ru-106 0.010 0.04 (50/197) 0.02 - 0.09 Ce-141 0.010 0.02 (3/197) 0.01 - 0.04 Ce-144 0.010 0.02 (44/197) 0.01 - 0.04 Others

< LLD (f)

Fraction of detectable measurements at specified location.

2-21

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Table 2-3 (Continued)

Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis of Detection Mean, (f) Range (Unit of Measurement)

Performed (LLD)

Milk 1-131 (91) 0.25 0.6 (4/91) 0.3-0.8 (pico Curie / liter)

Sr-89 (134) 5 7

(4/134) 6-11 Sr-90 (134) 1 5.3 (132/134) 1.5 - 12.8 Gamma (134)

Cs-137 10 13 (19/134) 11-16 Others

< LLD External Radiation y - Monthly (599) 0.5 mR*

0.20 (599/599) 0.08 - 0.51 (milli Roentgen / day) y - Quarterly (195) 0.5 mR*

0.20 (195/195) 0.11 -0.38 y - Annual (48) 0.5 mR*

0.19 (48/48) 0.11 - 0.30 Fish Gross Beta (17) 0.01 1.9 (15/17) 1.0-3.2 (pico Curie / gram) wet Sr-90 (17) 0.005 0.14 (17/17) 0.02-0.50 Gamma (17) 0.5 K-40 2.4 (17/17) 1.0-3.7 Others

< LLD LLD in units of mR - Lower end of useful integrated exposure detectability range for a passive radiation detector (TLD).

(a)

May include Ru-106, Ru-103, Be-7.

(b)

One outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample).

(f)

Fraction of detectable measurements at specified location.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM B.

Air Monitoring

1.

Characterization of Air and Meteorology The air in the vicinity of the site contains pollutants typical for an industrial area. Air flow is generally from the southwest in summer and from the northwest in the winter.

2.

Air Sampling Program and Analytical Techniques

a.

Program The air is sampled for gaseous radioiodine and radioactive particulates at each of ten (10) offsite air sampling stations. The locations of these stations are listed in Table 2-1 and shown on a map in Figure 2-1.

Samples are collected at each of these stations by continuously drawing two cubic feet per minute of atmosphere air through a glass fiber filter paper and a charcoal cartridge. The glass fiber filter paper is used for collection of airborne particulates, while the charcoal cartridge is used for collection of radioiodine. Samples are collected on a weekly basis.

The charcoal cartridge is used in the weekly analysis of airborne Iodine-131. The glass fiber filter papers are analyzed each week for gross beta, then composited by station each quarter for gamma spectrometry analysis. In order to reduce interference from short-lived naturally occurring radioactivity (e.g.; radon and thorium), the glass fiber filter papers are decayed prior to performing beta analysis in a low background counting system.

b.

Procedures Gross Beta Analysis of Filter Paper: Analysis is performed by placing the glass fiber filter paper from the weekly air sample in a 2 inch planchet and analyzing it in a low background, gas flow proportional counter.

Gamma Emitter Analysis of Filter Paper: Analysis is performed by stacking all of the glass fiber filter papers collected from each monitoring station during the quarter and scanning this composite on a high resolution germanium gamma spectrometer.

Iodine-131 Analysis of Charcoal Cartridge: Analysis is performed by a gamma scan of each charcoal cartridge.

c.

Special Evaluations An evaluation of all air sampling stations was performed in 2007 with regard to criteria for:

(1) collection of air from prevailing winds, and (2) maintenance of the area in vicinity of the equipment. The criteria was from: (1) EPA-450/4-87-009, Network Design & Optimum Site Exposure Criteria for Particulate Matter, (2) ASTM-D5111-95, Standard Guide for Choosing Location & Sampling Methods to Monitor Atmospheric Deposition at Non-Urban Locations, (3) DOE/EP-0023, A Guide for Environmental Radiological Surveillance at US DOE Installations, (4) NUREG-1301, ODCM Guidance, Standard RETS Controls for PWRs, and (5) NRC Radiological Branch Technical Position. Results of the evaluation and associated Corrective Actions are documented in CR07-22429 and SAP Order 200197646-0380.

2-23

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3.

Results and Conclusions I

A summary of data is presented in Table 2-2.

a.

Airborne Radioactive Particulates Gross Beta: A total of five-hundred-twenty (520) weekly samples from ten (10) locations were analyzed for gross beta. Results were comparable to previous years. Figure 2-2 indicates the weekly average concentration of gross beta in air particulates. The only item of note occurred during the period 10/23/07 - 10/29/07. Specifically, the Gross Beta results were unusually low for all ten (10) sample stations during this period. The results ranged from 0.13 - 0.015 pCi/cubic meter, where as the cumulative average ranged from 0.028 to 0.030 pCi/cubic meter. This issue was discussed with the REMvP Administrators at the other two FENOC sites, and they also noticed similar decreases during this period. There is no consequence to unusually low sample results and the cause is most likely due to cosmic interference. This issue is documented in SAP Order 200197646-0340.

Gamma Spectrometry: The weekly air particulate samples were composited into forty (40)

I quarterly samples which were analyzed by gamma spectrometry. Naturally occurring Beryllium-7 was identified in thirty-six of thirty-six (36 of 36) indicator samples, and four of four (4 of 4) control samples. No other radionuclides were detected. A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-2.

Deviations from Required Sampling and Analysis Schedule: There were some deviations from the required airborne particulate sampling and analysis schedule during the report period.

Specifically, continuous sampling was interrupted at the Brunton Dairy Farm (Site No. 27, U

6.16 miles SE) during the sampling period of 08/06/07 - 08/13/07 for 93 hours0.00108 days <br />0.0258 hours <br />1.537698e-4 weeks <br />3.53865e-5 months <br />, during the sampling period of 08/13/07 - 08/20/07 for 77 hours8.912037e-4 days <br />0.0214 hours <br />1.273148e-4 weeks <br />2.92985e-5 months <br />, and during the sampling period of 08/20/07 - 08/27/07 for 63 hours7.291667e-4 days <br />0.0175 hours <br />1.041667e-4 weeks <br />2.39715e-5 months <br />. All interruptions occurred during thunderstorms. To help m

prevent recurrence, the sample pump fuses were upgraded from 15 ampere to 25 ampere.

SINCE BVPS uses ten (10) airborne particulate sample stations versus five (5) required by the ODCM, THEN there was no consequence to interruption of sample collection during these periods. This condition is documented in SAP order 200197646-0330.

Summary: Based on the analytical results, the operation of BVPS did not contribute any measurable increase in air particulate radioactivity during the report period.

b.

Airborne Radioiodine Iodine-13 1: A total of five-hundred-twenty (520) weekly charcoal filter samples were analyzed for Iodine-13 1. No detectable concentrations were present at any locations.

Deviations from Required Sampling and Analysis Schedule: The deviations are the same as described above for airborne particulates.

Summary: Based on analytical results, the operation of BVPS did not contribute any measurable increase in airborne radioiodine during the report period.

2-24 I

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-1 Environmental Monitoring Locations - Air Sampling Stations Site Distance Sample Type No.

Sector (miles)

Sample Point Description 13 11-SW 1.49 Hookstown, PA (Old Meyer Farm) 27 7-SE 6.14 Aliquippa, Pa (Brunton Farm) 28 1-N 8.60 Beaver Falls, PA (Sherman Farm) 29B 3-NE 7.97 Beaver, PA (Friendship Ridge)

Air Particulate 30 4-ENE 0.43 Shippingport, PA (Cook's Ferry Substation)

& Radioiodine 32 15-NW 0.75 Midland, PA (North Substation - Rt. 68) 2-NNE 46.1 3-NE 2.28 Industry, PA (McKeels Service - Rt. 68) 47 14-WNW 4.88 East Liverpool, OH (Water Department) 48 10-SSW 16.40 Weirton, WV (Water Tower, Collier Way) 51 5-E 8.00 Aliquippa, PA (Sheffield Substation) 2-25

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-2 Graph of Annual Average Concentration: Gross Beta in Air Particulates Beaver Valley Power Station REM P Environmental Air Particulate Samples - Gross Beta 0.20, 0.181- ------------------------

E-o Average of 9 Indicator Locations S0.16 ---

...---- -- Control Location

0. 14 -- - - - -

Pre-Operational value (0.07 pai/cubic meter) w 0.12 --- -

Required LLD(0.01 pa /liter)

E 0.10.---------- -

-No Reporting Level for Gross Beta 00.06 A-

• 0.08 --- --- -

t-----.

0 0.04 -

C. 0.02 --..-

0.00 I

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2-26

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM C.

Monitoring of Shoreline Stream Sediments and Soils

1.

Characterization of Shoreline Stream Sediments and Soils The stream sediments (river bottoms) consist largely of sand and silt. Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material.

2.

Sampling Program and Analytical Techniques

a.

Program Shoreline stream sediments were collected semi-annually above the Montgomery Dam, in the vicinity of the BVPS outfall structure, and above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table 2-1 and are shown in Figure 2-3.

Although not required by the ODCM, soil samples are collected every three years. They were collected at each of ten (10) locations during 2006 and are not due to be collected again until 2009. At each location, twelve (12) core samples (3" diameter by 2" deep) are gathered at prescribed points on a 10 foot radius circle. Each location is permanently marked with reference pins. Each set of samples is systematically selected by moving along the radius in such a manner as to assure representative undisturbed samples.

Sampling locations are listed in Table 2-1 and are shown in Figure 2-3.

Shoreline stream sediments and soils are analyzed for gamma-emitting radionuclides.

b.

Analytical Procedures Gamma Emitter Analysis of Stream Sediment: Analysis is performed in a 300 ml plastic bottle, which is analyzed by gamma spectrometry.

Gamma Emitter Analysis of Soil: Although not required by the ODCM, analysis is performed in a 300 ml plastic bottle, which is analyzed by gamma spectrometry 2-27

Beaver Valley Power Station RTL A9.690E 3

2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3.

Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-4 and Figure 2-5.

I

a.

Shoreline Stream Sediment Gamma Spectrometry: A total of six (6) sediment samples were analyzed by gamma spectrometry during the report period. Naturally occurring Potassium-40, Thalium-208, Lead-212, Lead-214, Bismuth-214, Ra-226 and Ac-228, was detected in four of four (4 of

4) indicator samples and two of two (2 of 2) control samples.

Cesium-137: This radionuclide was identified in four of four (4 of 4) indicator samples and two of two (2 of 2) control samples. The results were similar to previous years (current years range = 0.06 to 0.13 pico Curie / gram), and less than the pre-operational level of 0.4 pico Curie / gram. Also, SINCE Cesium-137 was identified at the indicator locations (downstream) and at the control location (upstream), THEN it was not due to plant effluent releases and is most likely residual contamination due from previous nuclear weapons tests.

3 Cobalt-58: Radionuclide Cobalt-58 was identified in one of four (1 of 4) indicator samples and zero of two (0 of 2) control samples. The samples that indicated Cobalt-58 were obtained at the shore line of the main outfall facility. The results were similar to previous I

years (current years range = 0.11 to 0.11 pico Curie / gram), even though this data is greater than the pre-operational level of 0.098 pico Curie / gram.

Cobalt-60: Radionuclide Cobalt-60 was identified in one of four (1 of 4) indicator samples U

and zero of two (0 of 2) control samples. The samples that indicated Cobalt-60 were obtained at the shore line of the main outfall facility. The results were similar to previous years (current years range = 0.16 to 0.16 pico Curie / gram), and this data is currently less than the pre-operational level of 0.4 pico Curie / gram Deviations from Required Sampling and Analysis Schedule: There were no deviations i

from the required sediment sampling and analysis schedule during the report period.

Summary: The identification of Cobalt-58 and Cobalt-60 in the shoreline stream sediment i

near the main outfall facility is not unusual, because the plant discharges these radionuclides in liquid effluent releases. The analyses are consistent with discharge data of authorized liquid effluent releases, and all liquid effluent releases during the report I

period did not exceed the release limits set forth in the ODCM.

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I 2-28 I

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E

b.

Soil Although not required by the ODCM, soil is sampled every three years and was sampled in 2006. Soil sampling will be performed during calendar year 2009.

2-29

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-3 Environmental Monitoring Locations - Shoreline Sediments and Soil I

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Sample Site Distance Type No.

Sector (miles)

Sample Point Description 13a 11-SW 1.49 Hookstown, PA (Old Meyer Farm) 22 8-SSE 0.28 South of BVPS, Transmission Lines 27b 7-SE 6.19 Aliquippa, PA (Brunton Farm) 29A 3-NE 8.09 Beaver, PA (Nicol Farm)

Shippingport, PA (Cooks Ferry Soil 30a 4-ENE 0.43 Substation) 32a 15-NW 0.74 Midland, PA (North Substation) 46b 3-NE 2.66 Industry, PA (Willows Inn - Rt. 68) 47a 14-WNW 4.89 East Liverpool, OH (Water Department) 48 10-SSW 16.40 Weirton, WV (Collier Way Water Tower) 51a 5-E 7.99 Aliquippa, PA (Sheffield Substation) 2A 12-WSW 0.31 Shippingport, PA (BVPS Outfall Vicinity)

Sediment 49a 3-NE 4.93 Industry, PA (Upstream Montgomery Dam) 50 12-WSW 11.77 New Cumberland, WV (Upstream of Dam 2-30

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-4 Graph of Annual Average Concentration: Cesium-137, Cobalt-58 & Cobalt-60 in Sediment Beaver Valley Power Station REM P Cs-137 Sediment Trends - Outfall Vicinity I

1000.00 100.00-E 10.00 E

1.00-0 CL 0.10-0.01

---m--- Cs-137 Control Location Cs-137 Pre-Operational Cs-1 37 (0.4 pCi / gram) s,---

-- - -- -Cs-137 Required LLD (180 pCi.grr No Reporting Level for Sedirmnt o '

-"0"----

0\\

0 Ih 1111 0

--~ ~

~

~ -° -"

14A,ý,

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• 141P

140, 1441 1441 lop 1259 100.00 Beaver Valley Power Station REM P Co-58 & Co-60 Sediment Trends - Ouffall Vicinity

-11I.,

Co-58

-Unit 2 Pre-Operational Mean: Co-58 (0.098 pcVgm)

A Co-60 Unit 2 Pre-Operational Mean: Co-60 (0.40 pCigram)

No Required LLD for Co-58 or Co-60 No Reproting Linit for Co-58 or Co-60 E

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2-31

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-5 Graph of Annual Average Concentration: Cesium-137 in Soil RTL A9.690E 1.4 1.2 1.0 E

0.8 0.6 0o 0.4 0.

0.2 0.0 le If 2-32

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM D.

Monitoring of Feedstuff and Foodcrops

1.

Characterization of Farm Products According to the 2002 Census of Agriculture (, there were 645 farms in Beaver County. Total market value of production (Crops and Livestock) was $10,828,000.00. Some of the principal sources of revenue (>$50,000.00) are as follows:

Milk and Other Dairy Products from Cows

$4,719,000.00 Cattle and Calves

$1,387,000.00 Nursery, Greenhouse, Floriculture and Sod

$1,129,000.00 Other Crops and Hay

$893,000.00 Vegetables, Melons, Potatoes and Sweet Potatoes

$843,000.00 Grains, Oil Seeds, Dry Beans and Dry Peas

$567,000.00 Poultry and Eggs

$523,000.00 Cut Christmas Trees, and Short Rotation Woody Crops

$285,000.00 Fruits, Tree Nuts and Berries

$198,000.00 Other Animals and Other Animal Products

$85,000.00 Horses, Ponies, Mules, Burros, and Donkeys

$81,000.00 Sheep, Goats and their Products

$60,000.00 Hogs & Pigs Undisclosed Amount Aquaculture Undisclosed Amount

2.

Sampling Program and Analytical Techniques

a.

Program Feedstuff: Although not required by the ODCM, representative samples of Feedstuff (cattle feed) are collected monthly from the nearest dairy farm (Searight Dairy). See Figure 2-6. Each sample is analyzed by gamma spectrometry.

Foodcrops (leafy vegetables): Foodcrops are collected at garden locations during the growing season. Leafy vegetables, (e.g.; cabbage) are obtained from Shippingport, Georgetown, and Industry, Pennsylvania. Samples are also obtained from the control location in Weirton, West Virginia. All samples are analyzed for gamma emitters by gamma spectrometry. Samples are also analyzed by radiochemical analysis for Iodine-131.

(1) http://www.nass.usda.gov/census/censusO2/profiles/pa/ep42007.PDF 2-33

Beaver Valley Power Station RTL A9.690E 3

2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

b.

Procedures Gamma Emitter Analysis of Foodcrops: Analysis is performed by scanning a dried, homogenized sample with a gamma spectrometry system. A high resolution germanium detector is utilized with this system. Samples of feedstuff and foodcrops are loaded into 3

tare weight 300 or 150 ml plastic bottles or 1-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning for gamma emitters.

Gamma Emitter Analysis of Feedstuff: Although not required by the ODCM, analysis is performed by scanning a dried, homogenized sample with a gamma spectrometry system.

A high resolution germanium detector is utilized with this system. Samples of feedstuff and foodcrops are loaded into tare weight 300 or 150 ml plastic bottles or 1-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning for gamma emitters.

3 Iodine-131 Analysis of Foodcrops: Analysis is performed by radiochemistry. A stable iodide carrier is added to a chopped sample, which is then leached with a sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt is I

dissolved in water, filtered and treated with sodium hypochlorite. The iodate is then reduced to iodine with hydroxylamine hydrochloride and is extracted into toluene. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as 3

palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.

2-34

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3.

Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-7.

a.

Feedstuff Gamma Spectrometry: Although not required by the ODCM, a total of twelve (12) samples were analyzed by gamma spectrometry. Naturally occurring Potassium40 was identified in twelve of twelve (12 of 12) samples. Naturally occurring Beryllium-7 was found in seven of twelve (7 of 12) samples.

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required feedstuff sampling and analysis schedule during the report period.

Summary: The data from the feedstuff analyses was consistent with previous data. Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the feedstuff in the vicinity of the site during the report period

b.

Foodcrops Iodine-131: A total of five (5) samples were analyzed for Iodine-131. No detectable concentrations were present in the four (4) indicator samples or the one (1) control sample.

Gamma Spectrometry: A total of four (4) samples were analyzed by gamma spectrometry.

Naturally occurring Potassium-40 was identified in four of four (4 of 4) indicator samples and one of one (lof 1) control samples. No other radionuclides were identified.

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required foodstuff sampling and analysis schedule during the report period.

Summary: The data from the foodcrops analyses was consistent with previous data. Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the foodcrops in the vicinity of the site during the report period.

2-35

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Figure 2-6 Environmental Monitoring Locations - Feedstuff and Foodcrops I

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Sample Site Distance Type No.

Sector (miles)

Sample Point Description Feed 25 10-SSW 2.10 Hookstown, PA (Searight Farm) 10a 4-ENE 1.02 Shippingport, PA Food 15a 14-WNW 3.55 Georgetown, PA 46a 3-NE 3.39 Industry, PA 48a 10-SSW 16.54 Weirton, WV 2-36

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-7 Graph of Annual Average Concentration: Cesium-137 in Feedstuff and Fooderops Beaver Valley Power Station REMP Cs-i 37 Feedstuff and Foodcrops TrendsI 100 0) a.

E 0) 0 0)

C.)

0._

a-- - Cs-137 (Feedstuff)

Cs-137 (Foodcrops)

Cs-137 Pre-operational Results Cs-137 Required LLD (80 p0/kg) Wet

-No Reporting Level for Feed of Food 10 -

1 0.1 0.01 2

ý,4 14161ý 140-rc, 140) 141P 1441 1101 140" 14411, 2-37

I Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM E.

Monitoring of Local Cow and Goat Milk i

1.

Description - Milch Animal Locations Samples of fresh milk are obtained from milch animals at locations and frequencies noted in Table 2-1. The milk is analyzed for its radioiodine content, gamma emitters, strontium-89 and strontium-90.

Detailed field surveys are performed during the grazing season to locate and enumerate milch animals within a five (5) mile radius of the site. Survey data for the most recent survey conducted is shown in Section 3, Land Use Census.

2.

Sampling Program and Analytical Techniques 3

a.

Program Cow milk was collected from the two (2) reference dairy farms within a 10-mile radius of I

the BVPS. These milk samples were obtained at the Searight Dairy Farm (2.10 miles SSW) and the Brunton Dairy Farm (6.16 miles SE).

Cow milk and goat milk were collected from two (2) other dairy farms within a 10-mile radius of the BVPS site. These milk samples were obtained at the Collins Dairy Farm (3.55 miles SE) and the Halstead Dairy Farm (5.08 miles SSW), and were selected based i

on milch animal surveys and evaluations of meteorological data (i.e.; deposition parameters). They were added to the sampling program to ensure the highest potential milk pathway for radioiodine uptake is evaluated. The dairies are subject to change based3 upon availability of milk or when more recent data (milch animal census, and/or change in meteorological conditions) indicate other locations are more appropriate.

During the 2007 Land Use Census, it was determined that the heard of doe goats at the Moore Farm (2.12 miles SW) had been sold. Samples were not obtained from the Moore Farm in 2007 since the heard was sold.

3 Cow milk was also collected from the one (1) control location dairy farm outside of the 10-mile radius. These milk samples were obtained at the Windsheimer Dairy Farm (10.48 miles SSW).

The milk sample from the Searight Dairy Farm (2.10 miles SSW) is collected and analyzed weekly for Iodine-131 using a method that ensures a high sensitivity. Samples from each I

of the other dairies are collected monthly when cows are indoors and bi-weekly when cows are grazing. The monthly and/or bi-weekly sample is analyzed for principle gamma emitters (including Cesium-137 by high resolution germanium gamma spectrometry), and i

Iodine-131 high sensitivity analysis. Although not required by the ODCM, the monthly and/or bi-weekly sample is also analyzed for Strontium-89, Strontium-90 I

The location of each is shown in Figure 2-8 and described below.

2-38i

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Approximate Distance and Direction Collection Number of Animals from Midpoint between Period being Milked Unit I and Unit 2 Reactor 25 Searight Dairy 31 Cows 2.10 miles SSW January thru 948 McCleary Road December Hookstown, PA 27a Brunton Dairy 104 Cows 6.16 miles SE January thru 3681 Ridge Road December Aliquippa, PA 69*

Collins Dairy 4 Goats 3.55 miles SE April thru 289 Calhoun Road October Aliquippa, PA 96 Windsheimer Dairy 65 Cows 10.48 miles SSW January thru RD #11 December Burgettstown, PA Halstead Dairy 60 Cows 5.08 miles SSW January thru 113*

104 Tellish Drive December Hookstown, PA 114*

Moore Farm 0 Goats 2.12 miles SW No samples 982 State Route 168 Heard was sold in obtained Hookstown, PA 2007

• Highest potential pathway dairies based on evaluation of deposition parameters 2-39

I Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

b.

Procedure Iodine-131 Analysis of Milk: The milk samples are chemically prepared, and then analyzed with a low-level beta counting system.

I Gamma Emitter Analysis of Milk: This is determined by gamma spectrometry analysis of a 1 liter Marinelli container of milk.

3 Strontium-90 Analysis of Milk: Although not required by the ODCM, the milk samples are prepared by adding a stable strontium carrier and evaporating to dryness, then ashing in a muffle furnace, followed by precipitating phosphates. Strontium is purified in all samples by the Argonne method using 3 grams of extraction material in a chromatographic column.

Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for the in-growth of yttrium-90 (Y-90). Yttrium is then precipitated as hydroxide dissolved I

and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low-level beta counter to infer Strontium-90 activity.

3 Strontium-89 Analysis of Milk: Although not required by the ODCM, the Strontium-89 activity is determined by precipitating strontium carbonate (SrCO 3) from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an I

80 mg/cm 2 aluminum absorber for low level beta counting. Chemical yields of strontium and yttrium are determined by gravimetric means.

3.

Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of 1-131 and Sr-90 analyses (including the pre-operational period through the report I

period) is shown on Figure 2-9.

a.

Strontium-89: Although not required by the ODCM, a total of ninety-six (96) milk samples m

were analyzed for Strontium-89 during the report period. Strontium-89 was not detected in any of the seventy-five (75) indicator samples, nor was it detected in any of the twenty-one (21) control samples.

b.

Strontium-90: Although not required by the ODCM, a total of ninety-six (96) milk samples were analyzed for Strontium-90 during the report period. Strontium-90 was detected in I

sixty-seven of seventy-five (67 of 75) indicator samples and nineteen of twenty-one (19 of

21) control samples. The levels detected were attributable to previous nuclear weapons tests and are within the normally expected range.

I

c.

Gamma Spectrometry: A total of ninety-six (96) milk samples were analyzed by gamma spectrometry during the report period. Naturally occurring Potassium-40 was present in I

seventy-five of seventy-five (75 of 75) indicator samples and twenty-one of twenty-one (21 of 21) control samples. No other gamma-emitting radionuclides were identified during analysis.

3 2-40

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

d.

Iodine-131: A total of one hundred twenty-six (126) milk samples were analyzed for Iodine-131 during the report period. Iodine-131 was not detected in any of the one hundred five (105) indicator samples, nor was it detected in any of the twenty-one (21) control samples. All analyses were less than the 0.5 pico Curie / liter LLD value.

e.

Deviations from Required Sampling and Analysis: The Bi-weekly doe goat milk sampling was interrupted during the report period. Specifically, the doe goats ceased production of milk during the early winter months of 2007 and the late winter months of 2007, but was re-established in the spring and summer months (after breeding was completed). Although the doe goats could not be sampled during that period, the minimum Bi-weekly milk sampling requirements were still met. SINCE only four (4) Bi-weekly dairy cow locations (or doe goat locations) are required to be sampled, THEN the minimum requirements were met with the four (4) dairy cow milk samples. This condition is documented in SAP Order 200197646-0320.

f.

Summary: Based on all the analytical results and the comparison to pre-operational levels, the operation of BVPS did not contribute any measurable increase in radioactivity in the milk in the vicinity of the site during the report period.

2-41

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-8 Environmental Monitoring Locations - Milk RTL A9.690E I

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I Site Distance Sample Type No.

Sector (miles)

Sample Point Description 25 10-SSW 2.10 Hookstown, PA (Searight Farm) 27a 7-SE 6.16 Aliquippa, PA (Brunton Farm)

Milk 69*

7-SE 3.55 Aliquippa, PA (Collins Farm) 96 10-SSW 10.48 Burgettstown, PA (Windsheimer Farm) 113*

10-SSW 5.08 Hookstown, PA (Halstead Farm) 114*

11-SW 2.12 Hookstown, PA (Moore Farm)

• Dairies selected based on evaluation of deposition parameters 2-42 I

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-9 Graph of Annual Average Concentration: Iodine-131 & Sr-90 in Milk Beaver Valley Power Station REMPI 1-131 Concentrations in Milk I

14.0 12.0 10.0 C.)

0

.o 6.0 8.0 C.)

0.4.0-190sWeapons Testing Chernobyl Accident 6

Average at the Indicator Location

--- A--- Control Location Pre-Operational value (0.6 pCi / liter)

-Required LLD (1 pCi / liter)

-Reporting Level (3 pCi / liter) 2-0 0.0 -

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Avg. of 1 8

A- - - Control L Pre-Ope 6

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(d)

(:p 10 2-43

I Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM F. Environmental Radiation Monitoring i

1.

Description of Regional Background Radiation and Sources i

The terrain in the vicinity of the Beaver Valley Power Station generally consists of rough hills with altitude variations of 300-400 feet. Most of the land is wooded.

The principal geologic features of the region are nearly flat-laying sedimentary beds of the Pennsylvania Age. Beds of limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the northwest. Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major tributary streams.

Based on surveys reported in previous annual reports, exposure rates ranged from 6-12 pR/hr.

2.

Locations and Analytical Procedures I

Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLDs).

I During the report period, there were a total of sixty-four (64) environmental TLD locations.

This is comprised of forty-four (44) offsite locations, along with twenty (20) fence perimeter i

locations. The offsite TLD locations are plotted on Figure 2-10, but the fence perimeter locations are not plotted due to the large scale of the figure.

The TLDs were annealed at the Contractor Central Laboratory shortly before placing the TLDs in their field locations. The radiation dose accumulated in-transit between the Central Laboratory, the field location, and the Central Laboratory was corrected by transit controls maintained in lead shields at both the Central Laboratory and the field office. All dosimeters were exposed in the field for a calendar quarter, in a specific holder that contains two (2) TLDs at each location.

3.

Results and Conclusions A summary of the TLD results during the report period are listed in Table 2-2. A trend graph i

of analyses (including the pre-operational period through the report period) is shown on Figure 2-11.

TLD Analysis: During the report period, the average quarterly external exposure rate (as measured from TLD) was 17.8 mR at the sixty-four (64) indicator locations, and 19.3 mR at the Control location. This external exposure rate is comparable to previous years. As expected, there was some variation in external exposure rate among locations and seasons.

I 2-44 3

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM TLD Trend Evaluation: A review of the trends of the environmental TLD data during the period 2001 thru 2007 showed a small increase for the indicator locations, and a step (level) increase for the Control location. Since 2001, the Control location was consistently greater than the pre-operational value of 0.2 mrem/day. The increase was traced to a change made in late 2001 with regards to the environmental TLD field holders. Specifically, prior to 2001 all environmental TLDs were placed in a solid heavy wall plastic bottle (resembles a mason jar),

and that bottle was hung in the field. However, during 2001, all of these TLD field holders (bottles) were changed-out to an upgraded field holder that consists of a ventilated thin wall plastic mesh. In summary, the increase in TLD data is consistent at all locations (including the control location), and is most likely due to increased sensitivity to natural background beta radiation, and not a consequence of BVPS gaseous effluent releases. This issue is documented in SAP Order No. 200197646-0400.

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required sampling schedule (i.e.; TLD placement) and analysis schedule (i.e.; TLD processing) during the report period.

Summary: The quarterly TLD external exposure rates are comparable to those of previous years, except for the increase described above in the TLD Trend Evaluation. There was no evidence of anomalies that could be attributed to the operation of BVPS. It should also be noted that the average external exposure rate at the indicator locations was less than average external exposure rate at the Control location. Based on all the analytical results and the comparison to pre-operational levels, the operation of BVPS did not contribute any measurable increase in external exposure in the vicinity of the site during the report period. The TLD exposure rates also confirm that changes from natural radiation levels, if any, are negligible.

2-45

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-10 Environmental Monitoring Locations - TLDs RTL A9.690E 2-46

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-10 (Continued)

TLD Locations SOUTHEAST QUADRANT Site No.

Sector Distance (miles)i Location Site No.

Sector Distance (miles')

Location 27 7-SE 6.14 Brunton Dairy Farm Aliquippa, PA 45.1 6-ESE 1.92 Kennedy's Corners Raccoon Township, PA 51 5-E 8.00 Sheffield Substation Aliquippa, PA 59 6-ESE 0.99 236 Green Hill Road Aliquippa, PA 76 6-ESE 3.80 Raccoon Elementary School Raccoon Township, PA 77 6-ESE 5.52 3614 Green Garden Road

_ Aliquippa, PA 78 7-SE 2.72 Racoon Twsp Municipal Building Raccoon Township, PA 79 8-SSE 4.46 106 State Route 151 Ted McWilliams Auto Body 80 9-S 8.27 Park Office, State Route 18 Raccoon Township, PA 82 9-S 6.99 2697 State Route 18 Aliquippa, PA 94 8-SSE 2.25 McCleary & Pole Cat Hollow Road Hookstown, PA XnRITIW1RQT nMD RANT Site Sector Distance Location Site Sector Distance Location No.

(miles)

No.

(miles) 15 14-WNW 3.75 Post Office 87 14-7.04 50103 Calcutta Smith's Ferry Road Georgetown, PA WNW 32 15-NW 0.75 North Substation 88 15-NW 2.74 110 Summit Road Midland, PA Midland, PA 47 14-WNW 4.88 Water Department 89 15-NW 4.72 488 Smith's Ferry Road East Liverpool, OH I Ohioville, PA 60 13-W 2.51 444 Hill Road 90 16-NNW 5.20 6286 Tuscarawras Road Georgetown, PA Midland, PA 86 13-W 6.18 1090 Ohio Avenue 93 16-NNW 1.10 104 Linden - Sunrise Hills East Liverpool, OH Midland, PA NORTHEAST QUADRANT Site Sector Distance Location Site Sector Distance Location No.

(miles)

No.

(miles) 10 3-NE 0.94 Post Office 70 1-N 3.36 236 Engle Road 4-ENE Shippingport, PA Industry, PA 28 1-N 8.60 Sherman Farm 71 2-NNE 6.01 First Western Bank Beaver Falls, PA Brighton Township, PA 29B 3-NE 7.97 Friendship Ridge 72 3-NE 3.25 Ohioview Lutheran Church - Rear Beaver, PA Industry, PA 30 4-ENE 0.43 Cook's Ferry Substation 73 4-ENE 2.48 618 Squirrel Run Road Shippingport, PA Industry. PA 45 5-E 2.19 Christian House Baptist Chapel, State Rte 18 74 4-ENE 6.92 137 Poplar Avenue (CCBC)

Raccoon Township, PA Monaca. PA 46 3-NE 2.49 Midway Drive 75 5-E 4.08 117 Holt Road Industry, PA Aliquippa. PA 46.1 2-NNE 2.28 McKeel's Service, State Route 68 91 2-NNE 3.89 Pine Grove Road & Doyle Road 3-NE Industry, PA SOUTHWEST QUADRANT Site No.

Sector Distance (miles)

Location Site No.

Sector Distance (miles)

Location 13 11-SW 1.49 Old Meyer Farm Hookstown, PA 14 11-SW 2.53 Hookstown, PA 48 10-SSW 16.40 Collier Way Water Tower Weirton, WV 81 9-S 3.69 Millcreek United Presbyterian Church 83 10-SSW 4.26 735 Mill Creek Road 84 11-SW 8.35 Senior Center Hancock County, WV 85 12-5.73 2048 State Route 30 WSW 92 12-2.81 Georgetown Road Substation WSW Georgetown, PA 95 10-SSW 2.37 832 McCleary Road Hookstown, PA 2-47

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-11 Graph of Annual Average Exposure: Direct Radiation in Environment Beaver Valley Power Station REM P Environmental TLD Trends E

E 0.20 -I-0.14 Average of 63 ndicatorLocations--

Control Location (Weirton WV) 0.12 re-Operational Value (0.2 mrrem/ day) 0.10-2-48

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM G. Monitoring of Fish

1.

Description During the report period, fish collected for the radiological monitoring program included channel catfish, sucker, sauger and red horse.

2.

Sampling Program and Analytical Techniques

a.

Program Fish samples are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley effluent discharge point and upstream of the Montgomery Dam. The edible portion of each different species caught is analyzed by gamma spectroscopy. Fish sampling locations are shown in Figure 2-12.

b.

Procedure A sample is prepared in a standard tare weight 300 ml plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a high resolution germanium detector.

3.

Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-13.

Gamma Spectrometry: A total of nine (9) fish samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in any of the four (4) indicator samples, nor were they detected in any of the five (5) control samples.

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required fish sampling and analysis schedule during the report period.

Summary: Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the Ohio River fish population during the report period.

2-49

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Figure 2-12 Environmental Monitoring Locations - Fish Site Distance Sample Type No.

Sector (miles)

Sample Point Description 2A 12-WSW 0.31 BVPS Outfall Vicinity Fish 49a 3-NE 493 Industry, PA (Upstream Montgomery I_

I I

I IDam) 2-50

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-13 Graph of Annual Average Concentration: Cesium-137 in Fish RTL A9.690E Beaver Valley Power Station REM PI Cs-137 Concentrations - Fish 10000.000 1000.000 100.000 Cs-137

-?

Control Location - MVontgormery Dam 1

0 Unit2 Preoperational (0.014 pCi/gm)

E Required LLD (150 pCa / gm) 1.000 -

Reporting Level (2000 pCi / gm) o 0.100 0.010 "r-

.*o.

0,0,0,9,

0,

,*,*,0 0-

,-,4k,,

o"*o 2-51

Beaver Valley Power Station RTh A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM H. Monitoring of Surface, Drinking, Ground Waters and PrecipitationI

1. Description of Water Sources3 The Ohio River is the main body of water in the area. It is used by the Beaver Valley Power Station for plant make-up, for the cooling tower and for receiving plant liquid effluents.

Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley Power Station site. It is used by several municipalities and industries downstream of the site. The nearest user of the Ohio River as a potable water source is3 Midland Borough Municipal Water Authority. The intake of the treatment plant is approximately 1.5 miles downstream and on the opposite side of the river. The next downstream user is East Liverpool, Ohio which is approximately 6 miles downstream. The heavy industries in Midland, as well as others downstream, use river water for cooling purposes.

Groundwater occurs in large volumes in the gravel terraces which lie along the river, andU diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gpm.

In general, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year. The National Climate Data Center (http://www.ncdc.noaa.gov/oa/climate/research/cag3/v4.html) indicates the total annualI precipitation during the report period for the Pittsburgh, PA area was 40.18 inches.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

2.

Sampling and Analytical Techniques

a.

Surface (Raw River) Water The sampling program of river water includes three (3) sampling points along the Ohio River.

Raw water samples are collected daily at the East Liverpool (Ohio) Water Treatment Plant, sample location 5, [River Mile 41.2], and the made into a weekly composite sample. One automatic river water sampler is located at the ATI-Allegheny Ludlam (formerly J&L Steel) river water intake, sample location 2.1, [River Mile 36.2]. The automatic sampler takes a 20-40 ml sample every 15 minutes and samples are collected on a weekly basis.

The weekly samples are then made into a monthly composite sample for each location.

The monthly composite samples are analyzed for gamma emitters. In addition, a quarterly composite sample is prepared for each sample point from the monthly composites.

Quarterly composites are analyzed for tritium.

A weekly grab sample is taken upstream of the Montgomery Dam, sample location 49

[River Mile 29.6]. This upstream sample at the Montgomery Dam is the control sample.

The weekly grab samples upstream of the Montgomery Dam are analyzed for Iodine-131.

Weekly grab samples are then made into monthly composites are analyzed for gamma emitters. Quarterly composite are prepared from each of the monthly composites. The quarterly composites are analyzed for tritium.

Locations of each sample point are shown in Figure 2-14.

b.

Drinking Water (Public Supplies)

Drinking water (i.e.; treated water) is collected at both the Midland, PA Water Treating Plant, sample location 4, and East Liverpool, OH Water Treating Plant, sample location 5.

An automatic sampler at each location collects 20-40 ml every 20 minutes, which is then made into a weekly composite sample. The weekly composite sample from each location is analyzed for Iodine-131. Monthly composites are made from the weekly samples and are analyzed by gamma spectrometry. In addition, a quarterly composite sample is prepared for each sample point from the monthly composites. Quarterly composites are analyzed for tritium.

A weekly grab sample is taken upstream of the Montgomery Dam, sample location 49

[River Mile 29.6]. This upstream sample at the Montgomery Dam is the control sample.

The weekly grab samples upstream of the Montgomery Dam are analyzed for Iodine-131.

Weekly grab samples are then made into monthly composites are analyzed by gamma spectrometry. Quarterly composite are prepared from each of the monthly composites.

The quarterly composites are analyzed for tritium.

Locations of each sample point are shown in Figure 2-14.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

c.

Groundwater 3

Although not required by the ODCM, semi-annual grab samples were collected from three (3) locations within four (4) miles of the site (see Figure 2-14). These locations are:

i One (1) well in Shippingport, PA One (1) well in Hookstown, PA I

One (1) well in Georgetown, PA 3

Each ground water sample is analyzed for tritium and is analyzed by gamma spectrometry.

d.

Precipitation 3

Although not required by the ODCM, precipitation is collected in Shippingport PA, East Liverpool OH, and Weirton WV. Precipitation, when available, is collected each week and I

then made into quarterly composite samples from the weekly samples. The quarterly composites are analyzed for tritium and gamma emitters. Locations of each of the sample points are shown in Figure 2-14.

I

e.

Procedures Gamma Analysis of Drinking Water and Surface Water: The analysis is performed on I

water samples by placing one liter of the sample into a Marinelli container and analyzing the sample on a high resolution germanium gamma spectrometry system. Although not required by the ODCM, this analysis is also performed on Groundwater and Precipitation.

Tritium Analysis of Drinking Water and Surface Water: The tritium is determined in water samples by liquid scintillation analysis. Although not required by the ODCM, this analysis l

is also performed on Surface Water, Groundwater and Precipitation.

Iodine-131 Analysis of Drinking Water: The sample is chemically prepared and analyzed 3

with a low-level beta counting system. Although not required by the ODCM, this analysis is also performed on Surface Water.

2 U

I I

2-54 3

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3.

Results and Conclusions A summary of the analysis results of water samples (surface water, drinking water, ground water and precipitation) during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-15.

a.

Surface Water Tritium: A total of twelve (12) surface water samples were analyzed for Hydrogen-3 (Tritium) during the report period. Tritium was not detected in any of the eight (8) indicator samples, nor was it detected in any of the four (4) control samples.

Gamma Spectrometry: A total of thirty-six (36) surface water samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in any of the twenty-four (24) indicator samples, nor were they detected in any of the twelve (12) control samples.

Iodine-13 1: Although not required by the ODCM, a total of fifty-two (52) surface water control samples were analyzed for Iodine-131 using radiochemical methods during the report period. Iodine 131 was detected in forty of fifty-two (40 of 52) weekly control samples, of which one (1) analysis exceeded the reporting level of 2 pico Curie / liter. The results were similar to previous years, (current years range = 0.3 to 2.9 pico Curie / liter).

The positive results were detected at the Control location, which is five (5) miles upstream (not influenced by BVPS operation). Identification of Iodine-131 during the report period was most likely due to medical diagnostic and treatment procedures. This issue is documented in SAP Order 200197646-0430.

b.

Drinking Water Tritium: A total of twelve (12) drinking water samples were analyzed for Tritium during the report period. Tritium was not detected in any of the eight (8) indicator samples, nor was it detected in any of the four (4) control samples.

Gamma Spectrometry: A total of thirty-six (36) drinking water samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in any of the twenty-four (24) indicator samples, nor were they detected in any of the twelve (12) control samples.

Iodine-13 1: A total of one hundred-fifty-six (156) drinking water samples were analyzed for Iodine-131 (using radiochemical methods) during the report period. Iodine-131 was detected in forty-four of one hundred four (44 of 104) indicator samples and forty of fifty-two (40 of 52) control samples. Some of the positive results at the downstream location exceeded the positive results from the upstream surface water Control location, but none of these analyses exceeded the reporting level of 2 pico Curie / liter. Also, SINCE all of the liquid effluent discharges during the report period from BVPS did not have detectable Iodine-131. THEN the positive results were not influenced by BVPS operation, and were most likely due to medical diagnostic and treatment procedures.

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I Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

c.

Groundwater 3

Tritium: Although not required by ODCM, a total of six (6) groundwater samples were analyzed for Tritium during the report period. Tritium was not detected in any of the fourI (4) indicator samples, nor was it detected in any of the two (2) control samples.

Gamma Spectrometry: Although not required by ODCM, a total of six (6) groundwater 3

samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in any of the four (4) indicator samples, nor were they detected in any of the two (2) control samples.

3

d.

Precipitation Tritium: Although not required by ODCM, a total of twelve (12) precipitation samples I

were analyzed for Tritium during the report period. Tritium was detected in two of eight (2 of 8) indicator samples, but was not detected in any of the four (4) control samples.

Some of the positive results at the Cooks Ferry Substation in Shippingport, PA (current range = 240 - 348 pico Curie / liter, with an LLD of 200 pico Curie / liter), are greater than the pre-operational level of 300 pico Curie / liter, but is consistent with washout of tritium (from gaseous releases) during precipitation events. Specifically, identification of tritium I

at this location is not unusual, because the plant discharges tritium in gaseous waste effluents, and washout does occur during precipitation. Also, the liquid tritium activity is less than the tritium discharge data of authorized gaseous effluent releases. All gaseous I

effluent releases during the report period did not exceed the release limits set forth in the Offsite Dose Calculation Manual.

Gamma Spectrometry: Although not required by ODCM, a total of twelve (12) precipitation samples were analyzed by gamma spectrometry during the report period.

Gamma emitting radionuclides were not detected in any of the eight (8) indicator samples, 3

nor were they detected in any of the four (4) control samples.

e.

Deviations from Required Sampling and Analysis Schedule: During the sampling period of 07/10/07 - 07/17/07, the automatic drinking water sampler at the downstream East I

Liverpool OH Water Department (Site No. 5, 4.90 miles WNW) was interrupted for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. The problem was traced to an overnight power loss that was corrected the following day. There was no consequence to the interrupted sample, because the other downstream sampler located at the Midland PA Water Department (Site No. 4, 1.26 miles NW) was operating during this sample period. This issue is documented in SAP Order 200197646-0390.

f.

Summary: Data from the water sample analyses demonstrate that BVPS did not contribute a significant increase of radioactivity in the local river, in the drinking water, in the well I

water, or in the precipitation. The analytical results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.

I 2-56 1

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-14 Environmental Monitoring Locations -

Ground Water, Surface Water, Drinking Water and Precipitation Site Distance Sample Type No.

Sector (miles)

Sample Point Description Drinking 4

15-NW 1.26 Midland, PA (Water Department)

Water 5

14-WNW 4.90 East Liverpool, OH ( Water Department)

Surface 2.1 14-WNW 1.43 Midland, PA (ATI Allegheny Ludlam)

Water 5

14-WNW 4.90 East Liverpool, OH (Water Department) 49a 3-NE 4.93 Industry, PA (Upstream Montgomery Dam)

Ground 11 3-NE 0.94 Shippingport, PA Water 14a 11-SW 2.61 Hookstown, PA 15b 14-WNW 3.75 Georgetown, PA 30 4-ENE 0.43 Shippingport, PA (Cook's Ferry Substation)

Precipitation 47 14-WNW 4.88 East Liverpool, OH ( Water Department) 1 48 10-SSW 16.40 Weirton WV (Water Tower, Collier Way) 2-57

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-15 Graph of Annual Average Concentration: Iodine-131 in Surface Water & Drinking Water Beaver Valley Power Station REMP 1-131 Surface Water & Drinking Water Trends Z

00CL 2.5 2.0 1.5 1.0 0.5 0.0 Dow n Stream Drinldng Water - Vdiand Dow n Stream Drinidng Water - East Liverpool Control Location - Up Stream Surface Water Link 2 DVV Preoperational (0.23 pQ liter)

Required LLD (1 pCi / liter)

Reporting Level (2 pCi liter)

A\\

A, 14 14 11 40" e

l le l

14111 e

1" 149-1e e

ll 0

U I

I U

I I

I I

I I

I I

I I

2-58

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Figure 2-16 Graph of Annual Average Concentration: Tritium in Surface Water Beaver Valley Power Station REMPI Tritium Trends - Surface Water 100000 indicator Mean (pCi /1)

Control Location (pai / 1)

Pre-Operational (300 p~i/I) i-Required LLD (2,000 pCi/I) 10000 Reporting Level Surface Water (30,000 pCi/l)

(3L C.)

0 CL 0

10 40 0

N N4lo~N c

2-59

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-17 Graph of Annual Average Concentration: Tritium in Ground Water Beaver Valley Power Station REM PI Tritium Trends - Groundwater 100000

- Indicator Wean (pCi / )

A Control Location (pCi /-I) 10000

-Pre-Operational (440 pCi/i)

R equired LLD (2,000 pCi/i)

Reporting Level Groundwater (30,000 pCi/)

1000 10 2-60

Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Figure 2-18 Graph of Annual Average Concentration: Tritium in Drinking Water Beaver Valley Power Station REMPI Tritium Trends - Drinking Water 100000 9--

Indicator Mean Control Location (pai / 1)

Pre-Operational (310 pCi/I) 100001-Reequired LLD (2,000 pCO/)

,,,,,,,,-Reporting Level Drinking Water (20,000 pCVI)

C0

-0 0-It 1111 111 11111.o.O.

100 10 U*

l 41ý N01 10, 1ý o

o 4

e

§ 2-61

I Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I.

Estimates of Radiation Dose to Man

1.

Pathways to Man - Calculational Models 3

The radiation doses to man as a result of Beaver Valley operations were calculated for both gaseous and liquid effluent pathways using computer codes for the ARERAS/MIDAS computer system. These computer codes are equivalent to NRC computer codes XOQDOQ2, GASPAR, and LADTAP. Dose factors listed in the Offsite Dose Calculation Manual are used to calculate doses from radioactive noble gases in discharge plumes. Beaver Valley effluent data, based on sample analysis were used as the radionuclide activity input.

All liquid and gaseous effluent radionuclides listed in the Annual Radioactive Effluent Release Report were input as source terms to the computer codes.

All batch and continuous gaseous effluent releases were included in the dose assessment calculations. The release activities are based on laboratory analysis. Meteorological data I

collected by the Beaver Valley Power Station Meteorology System was also used as input to the computer codes. Except when more recent or specific data was available, the usage factors were obtained from the BVPS Final Environmental Statements or Regulatory Guide 1.109.

I All radioactive liquid effluents are released by batch mode after analysis by gamma spectrometry. Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River via the main outfall (River Mile 35.0). The actual data from these analyses are tabulated and used as the radionuclide source term input to the computer code. Except when more recent or specific data was available, the usage factors were obtained from the BVPS Final Environmental Statements or Regulatory Guide 1.109.

The total population doses were evaluated for all liquid and gaseous effluent pathways out to 50 miles. For these evaluations, a total population of -4 million people was used. An estimate i

of the populations are listed in the BVPS-2 UFSAR Section 2.1.3.1 for 0-10 miles and Section 2.1.3.2 for 10-50 miles.

2.

Results of Calculated Population Dose to Man -Liquid Effluent Releases During the report period, the calculated dose to the entire population within 50 miles of the plant is presented in Table 2-4 for BVPS liquid effluent releases. Also shown in this table is a comparison to natural radiation exposure.

3.

Results of Calculated Population Dose to Man - Gaseous Effluent Releases During the report period, the calculated dose to the entire population within 50 miles of the plant is presented in Table 2-5 for BVPS airborne effluent releases. Also shown in this table is a comparison to natural radiation exposure. The doses include the contribution of all pathways.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

4.

Conclusions Based upon the estimated dose to individuals from the natural background radiation exposure in Tables 2-4 and 2-5, the incremental increase in total body dose to the 50-mile population from the operation of Beaver Valley Power Station - Unit 1 and 2, is less than 0.00004% of the annual background dose.

The calculated doses to the public from the operation of Beaver Valley Power Station - Unit 1 and 2, are below BVPS annual limits and resulted in only a small incremental dose to that which area residents already received as a result of natural background. The doses constituted no meaningful risk to the public.

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Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-4 Comparison of Natural Radiation Exposure Versus Calculated Population Dose to Man - Liquid Effluent Releases RTL A9.690E TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE (a)

Ambient Gamma Radiation Radionuclides in Body Global Fallout Radon Average Individual (Total from all sources shown above) 58 millirem / year 40 millirem / year

< 1 millirem / year 198 millirem / year 296 millirem / year (a)

National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation," BEIR Report, 1990 0-50 mile Population Dose from BVPS Liquid Effluent Releases Man-millirem Largest Isotope Contributor Total Dose 241 Tritium Average Dose 0.0000603 Tritium (per Individual)

Comparison of Individual Dose BVPS Liquid Effluent Releases Versus Natural Background Radiation millirem BVPS Liquid Effluent Release Dose 0.0000603 Natural Radiation Exposure 296 2-64

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Table 2-5 Comparison of Natural Background Exposure Versus Calculated Population Dose to Man - Gaseous Effluent Releases TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE (a)

Ambient Gamma Radiation Radionuclides in Body Global Fallout Radon Average Individual (Total from all sources shown above) 58 millirem / year 40 millirem / year

< 1 millirem / year 198 millirem / year 296 millirem / year (b)

National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation," BEIR Report, 1990 0-50 mile Population Dose from BVPS Gaseous Effluent Releases Man-millirem Largest Isotope Contributor Total 243 Tritium Average 0.0000608 Tritium (per Individual)

Comparison of Individual Dose BVPS Gaseous Effluent Releases Versus Natural Background Radiation millirem BVPS Gaseous Effluent Release Dose 0.0000608 Natural Radiation Exposure 296 2-65

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 3 - LAND USE CENSUS A Land Use Census was conducted August 7 through August 23, 2007 to comply with:

" Offsite Dose Calculation Manual procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs", Attachment R, Control 3.12.2, and Surveillance Requirement 4.12.2.1

" BVPS REMP procedure 1/2-ENV-04.02, "Milch Animal Sampling Location Determination & ODCM Procedure 1/2-ODC-3.03, Control 3.12.2 Action Statements a and b Compliance Determination "

The Land Use census indicates that no changes were required in the current sampling locations, and no changes were required to the methodology used for determination of offsite dose from plant releases. A numerical summary of the Land Use Census results are provided in Table 3-1.

The following information is also provided to clarify the Land Use Census as documented in letter NPD3NRE:0460, dated August 31, 2007:

" Nearest Resident:

The current location has not changed since the previous census.

The current location is at 211 Ferry Hill Road, Shippingport, PA (0.406 miles NE).

" Nearest Garden >500 sqft:

The current location has not changed since the previous census.

The current location is at 238 State Route 168, Hookstown, PA (0.760 miles SSW).

" Nearest Dairy Cow Milked:

The current location has not changed since the previous census.

The current location is at Searight Dairy, 948 McCleary Road, RD 1, Hookstown, PA (2.097 miles SSW).

" Nearest Doe Goat Milked:

The current location has changed since the previous census.

The previous location is at 982 State Route 168, Hookstown, PA (2.120 miles SW).

The current location is 289 Calhoun Road, Aliquippa, PA (3.547 miles SE).

NOTE: this is not the nearest location, but it is the nearest location providing samples.

" Nearest Beef Cattle:

The current location has not changed since the previous census.

The current location is at 105 Shippingport Road, Shippingport, PA (1.405 miles ENE).

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Beaver Valley Power Station RTL A9.690E I

2007 Annual Radiological Environmental Operating Report SECTION 3 - LAND USE CENSUS m

" Projection for 2008 Dairy Cow Sampling Locations:

I Using a linear regression analysis of deposition parameters (D/Q), Dairy Cow sampling locations were determined to remain at the same locations used in 2007:

Searight Dairy, 948 McCleary Road, RD 1, Hookstown, PA (2.097 miles SSW)

Halstead Dairy, 104 Tellish Drive, Hookstown, PA (5.079 miles SSW)

Brunton Dairy, 3681 Ridge Road, Aliquippa, PA (6.158 miles SE) 3 Windsheimer Dairy, RD 1 Burgettstown, PA (10.476 miles SSW).

" Projection for 2008 Doe Goat Sampling Locations:

3 The linear regression analysis also indicated that there will be only one Doe Goat sampling location in 2008, because one of the two 2007 locations was removed during this census. Specifically, doe goats at 982 State Route 168, Hookstown PA, 2.120 miles SW) were sold in 2007. The Doe Goat sampling location for 2008 will be as follows:

Collins Farm, 289 Calhoun Road, Aliquippa, PA (3.547 miles, SE).

" D/O for Milch Animal Locations:

None of the 2007 milch animal sampling locations experienced a >20% increase in D/Q.

3

" D/O for Offsite Dose Determination:

There was no adverse effect on the current ODCM methodology used for offsite dose 3

determination from effluent releases. Specifically, a linear regression analysis of D/Q did not yield any valid locations where the offsite dose could have increased >20% more than the offsite dose previously calculated using current ODCM methodology.3

" D/O Historical Comparison:

There was no adverse trend in D/Q when comparing data to the ODCM default D/Q values, which validates that there was no adverse effect on the current ODCM methodology used for offsite dose determination from effluent releases. Specifically, the linear regression analysis of D/Q did not yield any valid locations where the offsite dose could have increased >20% more than the offsite dose previously calculated using current ODCM methodology. Therefore, a change in ODCM Receptor location was not required.

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Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 3 - LAND USE CENSUS Table 3-1 Location of Nearest Residents, Gardens, Dairy Cows, Doe Goats and Beef Cattle SECTOR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW w

WNW NW NNW RESIDENTS 0 to 5 miles (miles) 1.584 1.66 1 0.406 0.598 0.429 0.476 1.583 1.102 1.399 0.760 1.453 1.394 2.204 2.742 0.885 0.902 GARDENS 0 to 5 miles (miles) 2.899 None 2.7 11 1.028 1.979 1.7 13 1.802 2.127 2.276 0.760 1.453 2.832 None None 1.033 1.353 DAIRY Cows 0 to 5 miles (miles)

None None None None None None None None 3.85 1 2.097 None None 2.701 None None 2.442 DOE GOATS 0 to 5 miles (miles)

None None None None 3.402 4.285 3.547 None None 1.818 2.120 3.849 None None 5.125 None BEEF CATTLE 0 to 5 miles (miles) 3.461 3.110 4.869 1.405 2.620 2.952 1.974 4.573 2.337 1.832 1.452 1.544 3.176 None 4.277 2.416 NOTE: Distances shown in Bold print are the nearest location for that receptor 3-3

Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM A.

Split Sample Program (Inter-Laboratory Comparison, Part 1 of 2): BVPS participates in a split sample program with the Pennsylvania Department of Environmental Protection (PADEP) in support of their nuclear power plant monitoring program.

BVPS provided split samples to PADEP throughout the report period. The shared media and number of locations were typically comprised of; milk (1), surface water (3), sediment (1), fish (1), and food crops (2).

" PADEP has co-located continuous air particulate & air iodine sample stations with four (4) of the BVPS locations.

PADEP has co-located TLDs with twenty-four (24) of the BVPS TLDs.

B.

Spike Sample Program (Inter-Laboratory Comparison. Part 2 of 2): BVPS participates in a spike sample program with an Independent Laboratory. This program is used to independently verify sample analyses performed by the BVPS Contractor Laboratory.

Acceptance Criteria 1: The NRC criteria listed in NRC Inspection Procedure 84750, 12/4/90, Inspection Guidance 84750-03 is used as acceptance criteria for comparisons of results of spiked samples between the Contractor Lab and the Independent Lab. These comparisons are performed by dividing the comparison standard (Independent Lab result) by its associated uncertainty to obtain the resolution. The comparison standard value is multiplied by the ratio values obtained from the following table to find the acceptance band for the result to be compared. However, in such cases where the counting precision of the standard yields a resolution of less than 4, a valid comparison is not practical, and therefore, not performed.

NRC Criteria Resolution Ratio

<4 4-7 0.50-2.00 8-15 0.60-1.66 16-50 0.75-1.33 51-200 0.80-1.25

> 200 0.85-1.18 Acceptance Criteria 2: BVPS also has self imposed acceptance criteria. That criteria requires the percent difference between the Contractor Lab Activity and the Independent Lab Calculated Activity to agree by + 20%.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE 3

INTER-LABORATORY COMPARISON PROGRAM Participation in an Inter-Laboratory Comparison Program is required by BVPS Unit 1 and 2 1

Offsite Dose Calculation Manual procedure 1/2-ODC-3.03 Attachment S Control 3.12.3. For the report period, the requirement was met by the Contractor Lab analyzing NIST traceable 3

spiked samples supplied by an Independent Lab.

During the report period, BVPS used (Environmental, Inc., Midwest Laboratory - Northbrook, IL) as the Contractor Laboratory, and (Analytics - Atlanta, GA) as the Independent I

Laboratory.

The spiked samples included air particulate filter papers, charcoal cartridges, water samples, U

and milk samples. The samples were submitted by the Independent Laboratory to the Contractor Laboratory for analysis. The "spiked to" values were used for calculating 3

comparison Acceptance Criteria.

Spiked Milk & Water Samples: The spiked sample results (i.e.; the BVPS criteria) for 3

each calendar quarter are reported in Table 4-1 through Table 4-4, respectively. The following summary is provided:

A total of forty-eight (48) gamma spectrometry radionuclide analyses were performed by the Contractor Laboratory on four (4) milk samples.

A total of forty-eight (48) gamma spectrometry radionuclide analyses were performed by the Contractor Laboratory on four (4) water samples.

A total of four (4) chemical analyses for 1-131 were performed by the Contractor Laboratory on four (4) milk samples.

A total of four (4) chemical analyses for 1-131 analyses were performed by the Contractor Laboratory on four (4) water samples.

A total of four (4) tritium analyses were performed by the Contractor Laboratory on four (4) water samples.

Comparison of results of the spiked milk and water samples showed acceptable agreement with the NRC acceptance criteria. All one-hundred-eight (108) analyses met the NRC acceptance criteria 3

Comparison of results of the spiked milk and water samples showed acceptable agreement with BVPS acceptance criteria. All but three (3) of the one-hundred-eight 3

(108) analyses met the BVPS acceptance criteria.

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Beaver Valley Power Station RTL A9.690E 2007 Annual Radiological Environmental Operating Report SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Spiked Filter Paper and Charcoal Cartrid2e Samples: The spiked sample results for each calendar quarter are also reported in Table 4-1 through Table 4-4, respectively. The following summary is provided:

Gross Beta (Cesium-137) analyses were performed by the Contractor Laboratory on two (2) filter paper samples.

Iodine-131 analyses were performed by the Contractor Laboratory on two (2) charcoal cartridge samples.

Comparison of results of the spiked filter paper and charcoal cartridge samples showed acceptable agreement with the NRC acceptance criteria. All four (4) analyses performed by the Contractor Laboratory met the NRC acceptance criteria.

Comparison of results of the spiked filter paper and charcoal cartridge samples showed acceptable agreement with the BVPS acceptance criteria. All four (4) analyses performed by the Contractor Laboratory met the BVPS acceptance criteria C. Conclusions Results of Split Sample Program:

The split sample program is coordinated by the state, and the results are not provided with this report.

Results of Spike Sample Program:

Based on the Inter-Laboratory comparison data, BVPS considers all analyses provided throughout the report period by the Contractor Laboratory to be acceptable with respect to both accuracy and measurement. A comparison of the data, to the BVPS Acceptance Criteria, is provided in the following tables. The three samples that are not within the BVPS Acceptance Criteria are in two different sample types and of three different sample analyses. Although these sample analyses are not within the BVPS Acceptance Criteria, they are within the NRC Acceptance Criteria. The BVPS acceptance criteria are self imposed and can be considered stringent compared to the NRC acceptance criteria. Two of the deviations occurred in first quarter, one in milk of 1-131 by chemical separation (26.06%) and the other in water of Sr-90 (24.12%). The third deviation occurred in fourth quarter in milk of Sr-89 (21.77%).

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Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-1 Inter-Laboratory Comparison Program Spiked Samples - 18 Quarter Percent Difference Between Sample Type and Contractor Lab Activity and Sample Date Identification No.

Sample Analyses Independent Lab Calculated Activity (Contr. Lab - Ind. Lab) Ind. Lab Sr-89 16.64%

Sr-90 24.12%

1-131 (Chemical) 12.47%

1-131 4.45%

Ce-141 3.10%

Water Cr-51 7.51%

03/22/2007 Ind Lab: E5289-93 Cs-134

-4.12%

Con. Lab: SPW-1658 Cs-137 3.77%

Co-58

-0.93%

Mn-54 6.71%

Fe-59 6.43%

Zn-65 5.64%

Co-60

-0.38%

Water 03/22/2007 Ind. Lab: E5288-93 H-3

-7.54%

Con. Lab: SPW-1657 Sr-89

-6.28%

Sr-90 0.00%

1-131 (Chemical) 26.06%

1-131 3.29%

Milk Ce-141 2.69%

Cr-51 2.12%

03/22/2007 Ind. Lab: E5290-93 Cs-134 6.07%

Con. Lab: SPMI-1659 Cs-137 2.69%

Co-58

-1.32%

Mn-54 3.35%

Fe-59 4.91%

Zn-65 4.36%

Co-60

-0.07%

Filter Paper Cs-137 03/22/2007 Ind. Lab: E5291-93 18.01%

Con. Lab: SPAP-1660 (Gross Beta)

Charcoal Cartridge 03/22/2007 Ind. Lab: E5292-93 I-131

-2.66%

Con. Lab: SPCH-1661 I

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Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-2 Inter-Laboratory Comparison Program Spiked Samples - 2 nd Quarter Percent Difference Between Sample Type and Contractor Lab Activity and Sample Date Identification No.

Sample Analyses Independent Lab Calculated Activity (Contr. Lab - Ind. Lab) I Ind. Lab Sr-89

-11.12%

Sr-90 9.02%

1-131 (Chemical) 4.71%

1-131 2.16%

Ce-141

-2.19%

Water Cr-51 1.05%

06/14/2007 Ind. Lab: E5350-93 Cs-134

-5.36%

Cs-137 2.67%

Con. Lab: SPW -3625 C o-58 1.13%

Co-58 1,13%

Mn-54 9.17%

Fe-59 6.64%

Zn-65 8.02%

Co-60 0.63%

Water 06/14/2007 Ind. Lab: E5349-93 H-3 5.59%

Con. Lab: SPW-3624 Sr-89

-3.47%

Sr-90 7.75%

1-131 (Chemical) 8.70%

1-131

-0.71%

Milk Ce-141

-2.55%

Cr-51 0.47%

06/14/2007 Ind. Lab: E5351-93 Cs-134

-6.94%

Cs-137 1.42%

Con. Lab: SPMI-3626 Co-58 0.15%

Mn-54 7.77%

Fe-59 4.43%

Zn-65 5.39%

Co-60

-1.93%

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Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-3 Inter-Laboratory Comparison Program Spiked Samples - 3 rd Quarter Percent Difference Between Sample Type and Contractor Lab Activity and Sample Date Identification No.

Sample Analyses Independent Lab Calculated Activity (Contr. Lab - Ind. Lab) Ind. Lab Sr-89

-10.84%

Sr-90

-4.86%

1-131 (Chemical) 4.00%

1-131

-0.75%

Ce-141

-5.55%

Water Cr-51 3.73%

09/13/2007 Ind. Lab: E5505-93 Cs-134

-6.77%

Con. Lab: SPW-6056 Cs-137 7.59%

Co-58 1.63%

Mn-54 6.67%

Fe-59 4.73%

Zn-65 12.76%

Co-60 1.18%

Water 09/13/2007 Ind. Lab: E5504-93 H-3

-0.18%

Con. Lab: SPW-6055 Sr-89

-16.54%

Sr-90

-6.11%

1-131 (Chemical) 1.53%

1-131 1.29%

Ce-141

-0.90%

Milk Cr-51 3.32%

09/13/2007 Ind. Lab: E5506-93 Cs-134

-6.46%

Cs-137 4.66%

Con. Lab: SPMI-6057 C o-58 2.02%

Co-58

-2.02%

Mn-54 4.23%

Fe-59 6.04%

Zn-65 12.23%

Co-60

-0.20%

Filter Paper 09/13/2007 Ind. Lab: E5507-93 Cs-37 0.47%

Con. Lab: SPAP-6058 (Gross Beta)

Charcoal Cartridge 09/13/2007 Ind. Lab: E5508-93 1-131

-12.88%

Con. Lab: SPCH-6059 I

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Beaver Valley Power Station 2007 Annual Radiological Environmental Operating Report RTL A9.690E SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-4 Inter-Laboratory Comparison Program Spiked Samples - 4 th Quarter Percent Difference Between Sample Type and Contractor Lab Activity and Sample Date Identification No.

Sample Analyses Independent Lab Calculated Activity (Contr. Lab - Ind. Lab) Ind. Lab Sr-89

-8.64%

Sr-90 8.44%

1-131 (Chemical) 5.73%

1-131

-2.23%

Ce-141

-3.25%

Water Cr-51

-5.82%

12/06/2007 Ind. Lab: E5763-93 Cs-134

-10.46%

Cs-137 5.35%

Con. Lab: SPW-8207 Co-58

-0.15%

Mn-54 6.27%

Fe-59 3.98%

Zn-65 3.26%

Co-60

-1.27%

Water 12/06/2007 Ind. Lab: E5762-93 H-3

-0.52%

Con. Lab: SPW-8206 Sr-89

-21.77%

Sr-90

-0.66%

1-131 (Chemical) 10.20%

1-131

-3.13%

Ce-141

-0.07%

Milk Cr-51

-0.61%

12/06/2007 Ind. Lab: E5764-93 Cs-134

-8.39%

Cs-137 4.64%

Con. Lab: SPMI-8208 Co-58 0.23%

Mn-54 4.16%

Fe-59 3.65%

Zn-65 2.56%

Co-60

-2.13%

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