L-11-143, Annual Environmental and Effluent Release Report

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Annual Environmental and Effluent Release Report
ML11126A030
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 03/31/2011
From:
FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
L-11-143
Download: ML11126A030 (144)


Text

Perry Nuclear Power Plant Annual Environmental & Effluent Release Report 2010

2010 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT for the Perry Nuclear Power Plant PREPARED BY:

CHEMISTRY SECTION PERRY NUCLEAR POWER PLANT FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY, OHIO MARCH, 2011

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT TABLE OF CONTENTS EX ECU TIV E SU MM A RY ................................................................................................. 1....

Radioactive Effluent Releases ........................................................................................................ 1 Radiological Environm ental M onitoring ................................................................................... 2 Land Use Census ............................................................................................................................ 3 Clam /Mussel M onitoring ........................................................................................................ 3 Herbicide U se ................................................................................................................................. 3 Special Reports ............................................................................................................................... 3 IN TRO D UCTION ................................................................................................................... 4 Radiation Fundam entals ........................................................................................................ 4 Radiation and Radioactivity ..................................................................................................... 4 Units of M easure ............................................................................................................................ 5 Lower Limit of Detection ...................................................................................................... 6 Background radiation ..................................................................................................................... 7 RA D IO A CTIV E EFFLU EN T RELEA SES ........................................................................ 8 Introduction .................................................................................................................................... 8 Regulatory Lim its ........................................................................................................................... 8 Release Summ ary ......................................................................................................................... 10 M eteorological Data ..................................................................................................................... 17 Dose A ssessm ent .......................................................................................................................... 17 Carbon-14 Supplemental Inform ation ..................................................................................... 20 On-Site Groundwater M onitoring Program ............................................................................ 20 Abnorm al Releases ....................................................................................................................... 26 Non-Compliances ......................................................................................................................... 26 Offsite Dose Calculation M anual Changes ............................................................................... 26 Process Control Program Changes ......................................................................................... 26 RADIOLOGICAL ENVIRONMENTAL MONITORING ............................................... 27 Introduction .................................................................................................................................. 27 Sampling Locations ...................................................................................................................... 27 Sample Analysis ........................................................................................................................... 32 2010 Sampling Program ............................................................................................................... 33 Inter-Laboratory Cross-Check Comparison Program ............................................................... 42 Land Use Census .......................................................................................................................... 44 CLA M /M U SSEL M ON ITO RIN G .................................................................................... 47 Introduction .................................................................................................................................. 47 Corbicula Program ........................................................................................................................ 47 Dreissena Program ........................................................................................................................ 48 H ERBICID E A PPLICA TION S ......................................................................................... 49 SPECIA L REPO RTS ............................................................................................................. 50 Non-Compliances ......................................................................................................................... 50 Unreviewed Environm ental Questions ................................................................................... 50 APPENDICES Appendix A: 2010 Inter-Laboratory Cross Check Comparison Program Results Appendix B: 2010 KEMP Data Summary Reports Appendix C: 2010 REMP Detailed Data Report Appendix D: Corrections to Previous AEERR Table of Contents Page i

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT EXECUTIVE

SUMMARY

The Annual Environmental and Effluent Release Report (AEERR) details the results of environmental and effluent monitoring programs conducted at the Perry Nuclear Power Plant (PNPP) from January 01 through December 31, 2010. This report meets all of the requirements in PNPP Technical Specifications, the Environmental Protection Plan (EPP), and Regulatory Guide 1.21. It incorporates the requirements of the Annual Radioactive Effluent Release Report (ARERR),

the Annual Radiological Environmental Operating Report (AREOR) and the Annual Environmental Operating Report (AEOR). Report topics include radioactive effluent releases, radiological environmental monitoring, land use census, clamnmussel monitoring, herbicide use, and special reports. The results of the environmental and effluent programs for 2010 indicate that the operations of the Perry Nuclear Power Plant did not result in any significant environmental impact.

RADIOACTIVE EFFLUENT RELEASES During the normal operation of a nuclear power plant, small quantities of radioactivity may be released to the environment in liquid and gaseous effluents. Radioactive material may also be released as solid waste. PNPP maintains a comprehensive program to control and monitor the release of radioactive materials from the site in accordance with Nuclear Regulatory Commission (NRC) release regulations.

The dose to the general public from the plant's liquid and gaseous effluents was below the applicable regulatory limits. The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP liquid effluents was 1.53E-04 mrem (<0.0051 % of the applicable limit). The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents for 2010 was 1.46E-08 mrem

(<0.00000029% of the applicable limit).

In 2010, radioactivity released to the environment in the form of gaseous Carbon-14 (C-14) will be estimated. This is based on an industry initiative supported by the Nuclear Energy Institute (NEI) and the NRC. The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents for 2010, including C-14 is 2.OOE-01 (<0.00013% of the applicable limit). Refer to page 20 for additional Carbon-14 information.

The summation of the hypothetical maximum individual dose from effluents in 2010 is equivalent to

< 0.01 % of the total dose an individual living in the PNPP area receives from all sources of radiation.

Shipments of solid waste consisted of waste generated during water treatment, radioactive material generated during normal daily operations and maintenance, and irradiated components. PNPP complied with applicable regulations governing radioactive shipments in 2010, making shipments of solid radioactive waste to a licensed burial site.

An additional section covers the groundwater monitoring program. It includes a brief history of groundwater tritium issues at the Perry Plant, and results from current sampling and monitoring activities.

Executive Summary Page 1

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING The Radiological Environmental Monitoring Program (REMP) was established in 1981 to monitor the radiological conditions in the environment around PNPP. The REMP is conducted in accordance with PNPP Technical Specifications and the Offsite Dose Calculation Manual (ODCM). This program includes the collection and analysis of environmental samples and evaluation of results.

The REMP was established at PNPP six (6) years before the plant became operational. This pre-operational program was designed to provide data on background radiation and radioactivity normally present in the area. PNPP has continued to monitor the environment during plant operation by collecting and analyzing samples of air, precipitation, milk, fish, produce, water and sediment, as well as by measuring radiation directly. There were over 2600 radioactivity analyses performed on the 1325 radiological environmental samples collected in 2010. The results of the REMP program indicate adequate control of radioactivity released from PNPP plant effluents. These results also demonstrate that PNPP complies with applicable federal regulations. The REMP results are divided into four sections: atmospheric monitoring, terrestrial monitoring, aquatic monitoring, and direct radiation monitoring.

Samples of air were collected to monitor the radioactivity in the atmosphere. The 2010 results were similar to those observed for the pre-operational and operational programs from prior years. Only natural background environmental radioactivity was detected.

Terrestrial monitoring included the analysis of milk and produce. The PNPP ODCM does not require vegetation or soil samples to be included in the monitoring program. The results of the sample analyses in 2010 indicated concentrations of radioactivity similar to that found in previous years. Analyses of other terrestrial samples also detected concentrations of natural radioactivity similar to those observed in previous years, and indicated no build-up of radioactivity attributable to the operation of PNPP.

Aquatic monitoring included the collection and analyses of water, fish, and shoreline sediments. The 2010 analytical results for water and fish samples showed normal background radionuclide concentrations. The results of sediment sample analyses indicated that the annual average cesium radioactivity was similar to previous years for the control location. Cesium-137 activity was detected in five (5) of the twelve (12) samples collected. The average cesium-137 radioactivity for all locations was 375.95 pCi/kg and is within the maximum value of 864 pCi/kg established in 1981.

In 1999, a sediment sample of the Northwest Drain Impoundment (sampling location #64) was analyzed to contain 62 pCi/kg of cobalt-60. Enhanced monitoring activities continued within the boundaries of the impoundment for 2010. The cobalt-60 remains centered within the organic material located at the top of the spillway, with little or no activity found farther upstream. Sample analyses continue to identify cobalt-60 levels similar to those found in previous years. Refer to Table 17 for detailed sample results.

Direct radiation measurements showed no change from previous years. The indicator locations averaged 56.63 mrem/year and control locations averaged 54.64 mrem/year. In 2010, radiation dose in the area of PNPP was similar to the radiation dose measured at locations greater than ten (10) miles away from the Plant.

Based on these results, during 2010, the operation of the PNPP resulted in no significant increase in the radionuclide concentrations observed in the environment.

Executive Summary Page 2

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT LAND USE CENSUS In order to estimate radiation dose attributable to the operation of PNPP, the potential pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed as part of the REMP. During the census, PNPP personnel travel every public road within a five (5) mile radius of the plant to locate key radiological exposure pathways. These key pathways include the nearest resident, garden, and milk animal in each of the sixteen meteorological sectors. The information obtained from the census is entered into a computer program, which is used to assess the hypothetical dose to members of the public. In recent years, however, it has been noted that tracts of land once used for farming are now being developed as mini-industrial parks and residential housing tracts. For 2010, the predominant land use within the census area continues to be rural and/or agricultural.

CLAM/MUSSEL MONITORING Clam and mussel shells can clog plant piping and components that use water from Lake Erie. For this reason, sampling for clams and mussels has been conducted in Lake Erie in the vicinity of PNPP since 1971. The monitoring is specifically for Corbicula (Asiatic clams) since their introduction into the Great Lakes in 1981, and for Dreissena (zebra mussels) since their discovery in Lake Erie in 1989. Since no Corbicula have ever been found at PNPP, routine Corbicula monitoring will provide early detection capability when this pest species arrives at PNPP. The Dreissena program includes both monitoring and control and is directed at minimizing the mussel's impact on plant operation.

As in past years, this program has successfully prevented Dreissena from causing any significant operational problems at PNPP.

HERBICIDE USE The use of herbicides on the PNPP site is monitored to ensure compliance with Ohio Environmental Protection Agency (OEPA) requirements and to protect the site's natural areas. Based on the results of on-site herbicide applications and weekly general site inspections, herbicide use has not had a negative impact on the environment around the plant.

SPECIAL REPORTS Significant environmental events (for example, spills, releases), noncompliance with environmental regulations [e.g., OEPA discharge limits], and changes in plant design or operation that affect the environment are reported to regulatory agencies as they occur.

One special report was submitted in 2010:

0 On October 28, 2010 approximately 345 gallons of sodium hypochlorite (bleach) was discovered to have leaked to the ground through an underground piping break. The storage tank was immediately isolated and the leak stopped. Periodic sampling of groundwater monitoring wells has indicated the release has not migrated. The storage tank remains isolated during excavation and repair of the underground piping. All areas where leakage was discovered were neutralized by station personnel. All proper notifications to regulatory agencies were made as required.

Executive Summary Page 3

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT INTRODUCTION Nuclear energy provides an alternative energy source, which is readily available and has very limited impact upon the environment. To more fully understand nuclear energy as a source of generating electricity, one must understand basic radiation concepts and its occurrence in nature.

RADIATION FUNDAMENTALS Atoms are the basic building blocks of all matter. Simply described, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, respectively. The relatively large protons and neutrons are packed together in the center of the atom called the nucleus. Orbiting around the nucleus are one or more smaller electrons. In an electrically neutral atom, the positively charged protons in the nucleus balance the negatively charged electrons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other, which helps hold the atom together. Other attractive forces between the protons and neutrons keep the densely packed protons from repelling each other, and preventing the nucleus from breaking apart.

Atoms with the same number of protons in their nuclei make up an element. The number of neutrons in the nuclei of an element may vary. Atoms with the same number of protons but different numbers of neutrons are called isotopes. All 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, or radionuclide. Radionuclides contain an excess amount of energy in the nucleus, which is usually due to an excess number of neutrons.

Radioactive atoms attempt to reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release of energy from an atom's nucleus through the emission of radiation. Radionuclides vary greatly in the frequency with which their atoms release radiation. The length of time an atom remains radioactive is defined in terms of its half-life. Half-life is defined as the time required for a radioactive substance to lose half its activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years.

RADIATION AND RADIOACTIVITY Radioactive decay is a process in which the nucleus of an unstable atom becomes more stable by spontaneously emitting energy. Radiation refers to the energy that is released when radioactive decay occurs within the nucleus. This section includes a discussion on the three (3) primary forms of radiation produced by radioactive decay.

Alpha Particles Alpha particles consist of two protons and two neutrons and have a positive charge. Because of their charge and large size, alpha particles do not travel very far when released (less than 4 inches, in air).

They are unable to penetrate any solid material, such as paper or skin, to any significant depth.

However, if alpha particles are released inside the body, they can damage the soft internal tissues because they deposit all their energy in a small area.

Radiological Effluent Releases Page 4

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Beta Particles Beta particles are essentially free electrons, which usually carry a negative electrical charge. They are much smaller than alpha particles and travel at nearly the speed of light. Thus they can travel for longer distances than alpha particles. External beta radiation primarily affects the skin. Because of their electrical charge, paper, plastic or thin metals can stop beta particles.

Gamma Rays Gamma rays are bundles of electromagnetic energy, called photons, which behave as though they were particles. They are similar to visible light, but of a much higher energy. Gamma rays can travel long distances in air and are often released during radioactive decay, along with alpha and beta particles. Potassium-40 is an example of a naturally occurring radionuclide found in all humans that decays by emitting a gamma ray.

Interaction with Matter When radiation interacts with other materials, it affects the atoms of those materials principally by knocking the negatively charged electrons out of orbit. This causes an atom to lose its electrical neutrality and become positively charged. An atom that is charged, either positively or negatively, is called an ion and the radiation is called ionizing radiation.

UNITS OF MEASURE Some of the units of measure used in this report require explanation.

Activity Activity is the number of atoms in a material that decay per unit of time. Each time an atom decays, 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 are decaying. One curie of activity indicates the decay of 37 billion atoms per second. Smaller units of the curie are often used in this report. Two common units are the microcurie (jiCi), one millionth of a curie, and the picocurie (pCi), one trillionth of a curie. The mass, or weight, of radioactive material, which would result in one (1) curie of activity, depends on the disintegration rate. For example, one gram of radium-226 is equivalent to one (1) curie of activity. It would require about 1.5 million grams of natural uranium, however, to equal one (1) curie.

Dose Biological damage due to alpha, beta, and gamma radiation may result from the ionization caused by these types of radiation. Some types of radiation, especially alpha particles, which causes dense local ionization, can result in much more biological damage for the same energy imparted than does gamma or beta radiation. 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 (as measured in rads), the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any type of ionizing radiation. The dose equivalent is measured in terms of the Roentgen Equivalent Man (rem). When discussing Radiological Effluent Releases Page 5

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT environmental radiation effects, the rem is a large unit. Therefore, a smaller unit, the millirem (mrem) is often used. One mrem is equivalent to 1/1000 of a rem.

LOWER LIMIT OF DETECTION Sample results are often reported as below the Lower Limit of Detection (LLD). The LLD for an analysis is the smallest amount of radioactive material that will show a positive result for which there can be a 95% confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample analysis. When a measurement is reported as less than the LLD

(<LLD), it means that no radioactivity was detected. Had radioactivity been present at (or above) the stated LLD value, it statistically would have been detected. The NRC has established LLD values for environmental and effluent sample analyses.

Radiological Effluent Releases Page 6

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT BACKGROUND RADIATION Background radiation is a part of nature. Natural background radioactive decay occurs in the soil, water, air, and space. Common sources of radiation that contribute to the natural background radiation includes: the decay of radioactive elements in the earth's crust, a steady stream of high-energy particles from space (called cosmic radiation), naturally-occurring radioactive isotopes in the human body like potassium-40, the decay of radioisotopes used in medical procedures, man-made phosphate fertilizers (phosphates and uranium are often found together in nature), fallout from nuclear weapons testing, and even household items like smoke detectors. In the United States, a person's average annual exposure from background radiation is 360 mrem, and is due to the sources shown in Figure 1 [Source: National Council on Radiation Protection and Measurements].

Internal Terrestial 10.94%

7.95%

ledical/X-Ray 0.94 Nuclear Fuel Cycle 0.09%

Cosmic Nuclear Medicine 7.9513.98%

i 2.80% ,0 "l o

-Consumer Products M I-neu Fall-Out 10%

, - 0.26%

Other O

0.75%

Occupanal Sources 0.30%

Radon 54.69%

Figure 1: Sources of Background Radiation Many radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing. These radionuclides are expected to be present in many of the environmental samples collected in the vicinity of PNPP. Some of the radionuclides normally present include:

Beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere, Potassium-40, a naturally occurring radionuclide normally found in humans and throughout the environment, and Radionuclides from nuclear weapons testing fallout, including tritium and cesium-137. These radionuclides may also be released in minute amounts from nuclear facilities.

Beryllium-7 and potassium-40 are especially common in REMP samples. Since they are naturally occurring and are expected to be present, positive results for these radionuclides are not discussed in the section for the 2010 Sampling Program results. These radionuclides are included; however, in Appendix A, 2010 Inter-Laboratory Cross Check Comparison Program Results.

Radiological Effluent Releases Page 7

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT RADIOACTIVE EFFLUENT RELEASES INTRODUCTION The source of radioactive material in a nuclear power plant is the generation of fission products (e.g., noble gas, iodine, and particulate) or neutron activation of water and corrosion products (e.g., tritium and cobalt). The majority of the fission products generated remain within the nuclear fuel pellet and fuel cladding. Most fission products that escape from the fuel cladding, as well as the majority of the activated corrosion products, are removed by plant processing equipment.

During the normal operation of a nuclear power plant, small amounts of radioactive material are released in the form of solids, liquids, and gases. PNPP was designed, and is operated in such a manner as to control and monitor these effluent releases. Effluents are controlled to ensure any radioactivity released to the environment is minimal and within regulatory limits. Effluent release programs include the operation of monitoring systems, in-plant sampling and analysis, quality assurance, and detailed procedures covering all aspects of effluent monitoring.

The liquid and gaseous radioactive waste treatment systems at PNPP are designed to collect and process these wastes in order to remove most of the radioactivity. Effluent monitoring systems are used to provide continuous indication of the radioactivity present and are sensitive enough to measure several orders of magnitude lower than the applicable release limits. This monitoring equipment is equipped with alarms and indicators in the plant control room. The alarms are set to provide warnings to alert plant operators when radioactivity levels reach a small fraction of actual limits. The waste streams are sampled and analyzed to identify and quantify the radionuclides being released to the environment.

Gaseous effluent release data is coupled with on-site meteorological data in order to calculate the dose to the general public. Devices are maintained at various locations around PNPP to constantly sample the air in the surrounding environment. Frequent samples of other environmental media are also taken to determine if any radioactive material deposition has occurred. The Radiological Environmental Monitoring Program (REMP) is described in detail in the next section.

Generation of solid waste is carefully monitored to identify opportunities for minimization. Limiting the amount of material taken into the plant, sorting material as radioactive or non-radioactive waste, and incinerating waste once it is identified help to lower the volume of radioactive solid waste generated. Solid waste is shipped to a licensed burial site.

REGULATORY LIMITS The Nuclear Regulatory Commission has established limits for liquid and gaseous effluents that comply with:

Title 10 of the Code of Federal Regulations, Part 20 (Standards for Protection Against Radiation)

[10CFR20], Appendix B; Title 10 of the Code of Federal Regulations, Part 50 (Domestic Licensing of Production and Utilization Facilities) [10CFR50], Appendix I; and Title 40 of the Code of Federal Regulations, Part 190 (Environmental Radiation Protection Standards for Nuclear Power Plants) [40CFR190].

These limits were incorporated into the PNPP Technical Specifications, and subsequently into the PNPP Offsite Dose Calculation Manual (ODCM). The ODCM prescribes the maximum doses and Radioactive Effluent Releases Page 8

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT dose rates due to radioactive effluents resulting from the operation of PNPP. These limits are defined in several ways to limit the overall impact on persons living near the plant. Since there are no other fuel sources near the PNPP, the 40CFR190 limits, which are described below, were not exceeded in 2010.

The 40CFR190 limit for total direct-radiation dose is 25 mrem. For 2010, the total whole body dose to a member of the general public, considering all sectors, was 7.4E-01 person-Rem. This value was determined by summing the annual whole body doses from liquid and gaseous radioactive effluents, the annual gaseous and liquid organ dose (refer to Table 8) and the maximum, direct-radiation dose.

Since the direct radiation dose, as determined by TLD, was indistinguishable from natural background (refer to Figure 9), it was not included in the calculation.

Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases, as required by the ODCM. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 ýtCi/mL of total activity. These values are the maximum effluent concentrations.

The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:

During any calendar quarter:

Less than or equal to 1.5 mrem to the whole body, and Less than or equal to 5 mrem to any organ.

During any calendar year:

Less than or equal to 3 mrem to the whole body, and Less than or equal to 10 mrem to any organ.

Gaseous Effluents Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

Noble gases:

Less than or equal to 500 mrem per year to the whole body, and Less than or equal to 3000 mrem per year to any organ.

Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half lives greater than eight days:

Less than or equal to 1500 mrem per year to any organ Air dose due to noble gases to areas at, and beyond the site boundary, shall be limited to the following:

During any calendar quarter:

Less than or equal to 5 mrad for gamma radiation, and Less than or equal to 10 mrad for beta radiation.

During any calendar year:

Less than or equal to 10 mrad for gamma radiation, and Radioactive Effluent Releases Page 9

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Less than or equal to 20 mrad for beta radiation.

Dose to a member of the public from Iodine-13 1, Iodine-133, Tritium, and all radionuclides in particulate form with half lives greater than eight days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 7.5 mrem to any organ per any calendar quarter, and Less than or equal to 15 mrem to any organ per any calendar year.

The PNPP ODCM does not contain a concentration reference for gaseous effluents. For this reason, effluent concentrations are not used to calculate maximum release rates for gaseous effluents.

RELEASE

SUMMARY

Effluents are sampled and analyzed to identify both the type and quantity of radionuclides present.

This information is combined with effluent path flow measurements to determine the composition, concentration, and dose contribution of the radioactive effluents.

Liquid Effluents The PNPP liquid radioactive waste system is designed to collect and treat all radioactive liquid waste produced in the plant. The treatment process used for radioactive liquid waste depends on its physical and chemical properties. It is designed to reduce the concentration of radioactive material in the liquid by filtration to remove suspended solids and demineralization to remove dissolved solids. Normally, the effluent from the liquid radioactive waste system is returned to plant systems.

To reduce the volume of water stored in plant systems; however, the processed liquid effluent may be discharged from the plant via a controlled release. In this case, effluent activity and dose calculations are performed prior to, and after discharging this processed water to Lake Erie to ensure regulatory compliance and dose minimization principals are maintained.

Liquid radioactive waste system effluents may be intermittently released, which are considered to be "batch" releases. Table 1 provides information on the number and duration of these releases for 2010.

Table 1: Liquid Batch Releases QUARTER I QUARTER 2 QUARTER 3 QUARTER 4 ANNUAL TOTAL Number of batch releases 7 7 24 7 45 Total time period for batch releases, min 1.51E+03 1.78E+03 5.41E+03 1.56E+03 1.03E+04 Maximum time for a batch release, min 2.54E+02 3.84E+02 2.38E+02 2.32E+02 3.84E+02 Average time period for a batch release, min 2.15E+02 2.54E+02 2.25E+02 2.23E+02 2.28E+02 Minimum time for a batch release, min 6.60E+01 2.22E+02 2.15E+02 2.11E+02 6.60E+01 Average stream flow during periods of effluent 1.38E+05 2.34E+05 2.66E+05 1.32E+05 2.01E+05 release into a flowing stream, L/min Radioactive Effluent Releases Page 10

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 2 provides information on the nuclide composition for the liquid radioactive effluent system releases. If a radionuclide was not present at a level "greater than or equal to the LLD" (>LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, LLDs were met, or were below the levels required by the ODCM. Table 2a provides information specific to radioactive effluent batch releases while Table 2b provides information specific to continuous radioactive effluent releases.

Table 2: Summation of All Liquid Effluent Releases QUARTER QUARTER QUARTER QUARTER EST.

1 2 3 4 TOTAL ERRORT

(%)

A. Fission and Activation Products

1. Total Released, Ci 2.83E-04. 6.48E-03 2.47E-03 3.69E-04 1.00E+01 (excluding tritium, gases, alpha)
2. Average Diluted Concentration, VCi/mL
  • 4.53E- 11 9.1 IE-10 2.26E-10 5.31E-1 1
3. Percent of Applicable Limit, % N/A N/A N/A N/A B. Tritium
1. Total Released, Ci 2.05E+00 2.70E+00 9.97E+00 3.06E+00 1.00E+01
2. Average Diluted Concentration, jtCi/mL 3.28E-07 3.80E-07 9.11 E-07 4.41E-07
3. Percent of Applicable Limit, % 3.28E-3 3.80E-03 9.11 E-3 4.41E-3 C. Dissolved and Entrained Gases
1. Total Released, Ci <LLD <LLD <LLD <LLD 1.00E+01
2. Average Diluted Concentration, ptCi/mL <LLD <LLD <LLD <LLD
3. Percent of Applicable Limit, % N/A N/A N/A N/A D. Gross Alpha Activity, Ci <LLD <LLD <LLD <LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 9.54E+05 3.34E+06 9.41E+06 1.15E+07 1.00E+01 dilution)

F. Dilution Water Volume Used, Liters 6.25E+09 7.11E+09 1.09E+10 6.94E+09 1.00E+01

<LLD - Less than the lower limit of detection N/A - Not Applicable, the ODCM does not have a limit for fission and activationproducts.

  • Averagediluted concentrationsare based on total volume of water releasedduring quarter.

Radioactive Effluent Releases Page 11

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 2a: Summation of Batch Liquid Effluent Releases QUARTER QUARTER QUARTER QUARTER EST.

1 2 3 4 TOTAL ERROR,

(%)

A. Fission and Activation Products Total Released, Ci 2.83E-04 6.48E-03 2.47E-03 3.69E-04 l.00E+01 (excluding tritium, gases, alpha)

B. Tritium Total Released, Ci 2.05E+00 2.70E+00 9.97E+00 3.06E+00 1.00E+01 C. Dissolved and Entrained Gases Total Released, Ci <LLD <LLD <LLD <LLD 1.00E+01 D. Gross Alpha Activity, Ci <LLD <LLD <LLD <LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 9.54E+05 2.83E+06 8.09E+06 2.54E+06 1.00E+01 dilution)

LLD - Less than the lower limit of detection Table 2b: Summation of Continuous Liquid Effluent Releases QUARTER QUARTER QUARTER QUARTER EST.

1 2 3 4 TOTAL ERROR,

(%)

A. Fission and Activation Products Total Released, Ci <LLD <LLD <LLD <LLD .00E+O1 (excluding tritium, gases, alpha)

B. Tritium Total Released, Ci O.OOE+00 O.OOE+00 2.92E-6 4.33E-06 1.00E+01 C. Dissolved and Entrained Gases Total Released, Ci <LLD <LLD <LLD <LLD 1.00E+01 D. Gross Alpha Activity, Ci <LLD <LLD <LLD <LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 0.00E+00 5.05E+05 1.32E+06 8.95E+06 1.00E+01 dilution)

<LLD - Less than the lower limit of detection Radioactive Effluent Releases Page 12

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 3 lists the total number of curies (Ci) of each radionuclide present in liquid effluent releases for each quarter. If a radionuclide was not present at a level "greater than or equal to the LLD"

LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, the LLDs were either met, or were below the levels required by the ODCM.

Table 3: Radioactive Liquid Effluent Nuclide Composition - Batch QUARTER QUARTER QUARTER QUARTER ANNUAL UNIT 1 2 3 4 TOTAL Tritium Ci 2.05E+00 2.70E+00 9.97E+00 3.06E+00 1.78E+01 Chromium-51 Ci <LLD <LLD <LLD <LLD <LLD Manganese-54 Ci 3.21E-05 1.15E-03 4.89E-05 <LLD 1.23E-03 Iron-55 Ci <LLD <LLD <LLD <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD <LLD Cobalt-58 Ci <LLD 3.16E-05 4.55E-05 <LLD 7.71E-05 Cobalt-60 Ci 2.14E-04 5.30E-03 2.24E-03 3.69E-04 8.12E-03 Zinc-65 Ci <LLD <LLD <LLD <LLD <LLD Strontium-92 Ci <LLD <LLD <LLD <LLD <LLD Zirconium-95 Ci <LLD <LLD <LLD <LLD <LLD Niobium-95 Ci <LLD <LLD <LLD <LLD <LLD Technetium-99M Ci <LLD <LLD <LLD <LLD <LLD Rhuthenium-105 Ci <LLD <LLD <LLD <LLD <LLD Silver- IOin Ci <LLD <LLD 1.28E-04 <LLD 1.28E-04 Antimony- 124 Ci <LLD <LLD <LLD <LLD <LLD Antimony-125 Ci 3.70E-05 <LLD <LLD <LLD 3.70E-05 Iodine- 131 Ci <LLD <LLD <LLD <LLD <LLD Xenon-133 Ci <LLD <LLD <LLD <LLD <LLD Cesium-134 Ci <LLD <LLD <LLD <LLD <LLD Cesium-137 Ci <LLD <LLD <LLD <LLD <LLD Cesium-138 Ci <LLD <LLD <LLD <LLD <LLD Lanthanum- 140 Ci <LLD <LLD <LLD <LLD <LLD Gold-199 Ci <LLD <LLD <LLD <LLD <LLD Total for Period Ci 2.05E+00 2.71E+00 9.97E+00 3.06E+00 1.78E+01

<LLD - Less than the lower limit of detection Radioactive Effluent Releases Page 13

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Gaseous Effluents Gaseous effluents are made up of fission and activation gases, iodine and particulate releases. The fission and activation gas releases are primarily a result of containment purge operations, small steam leaks, and offgas system operation. The iodine and particulate releases are primarily a result of small steam leaks. Gaseous effluents from PNPP exit the plant via one of four effluent vents.

Each of these four effluent vents contains radiation detectors that continuously monitor the air to ensure that the levels of radioactivity released are well below regulatory limits. Samples are also collected and analyzed on a routine basis to ensure regulatory compliance and dose minimization principals are maintained. The majority of gaseous effluents released from PNPP are considered continuous and at ground level.

A summation of all gaseous radioactive effluent releases is given in Table 4. If a radionuclide was not present at a level "greater than or equal to the LLD" (>LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, the measured LLDs either met or were below the levels required by the PNPP ODCM.

Two plant vents had detectable tritium in the third quarter of 2010. A gaseous sample is obtained and analyzed for tritium once a month. The detected value for the release was conservatively considered to be the entire duration of the month. This is the reason for the elevated third quarter tritium result.

Discussion of Carbon-14 doses is listed on page 20 Carbon-14 supplemental information.

Table 4: Summation of All Gaseous Effluents QUARTER QUARTER QUARTER QUARTER EST. TOTAL 1 2 3 4 ERROR, %

A. Fission and Activation Products

1. Total Released, Ci 4.94E-02 2.52E+00 O.OOE+00 2.21 E-02 1.00E+01
2. Average Release Rate, gtCi/sec 6.36E-03 3.20E-01 O.OOE+00 2.78E-03
3. Percent of Applicable Limit, % N/A N/A N/A N/A B. Iodine I. Total Iodine-131 Released, Ci O.OOE+00 8.02E-05 O.OOE+00 1.32E-04 1.00E+01
2. Average Release Rate, pCi/sec O.OOE+00 1.02E-05 O.OOE+00 1.66E-05
3. Percent of Applicable Limit, % N/A N/A N/A N/A C. Particulates with Half-Lives > 8 days
1. Total Released, Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 L.00E+01
2. Average Release Rate, pCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
3. Percent of Applicable Limit, % N/A N/A N/A N/A D. Alpha Activity, Ci 9.72E-07 1.07E-07 2.95E-08 3.28E-07 E. Tritium I. Total Released, Ci O.OOE+00 6.06E-01 7.68E+00 9.37E-03 1.00E+01
2. Average Release Rate, VtCi/sec O.OOE+00 7.71E-02 9.66E-01 1.18E-03
3. Percent of ODCM Limit, % N/A N/A N/A N/A G. Carbon- 14 4.28E+00 4.28E+00 4.28E+00 4.28E+00 1.00E+01

<LLD - Less than the lower limit of detection N/A - Not Applicable, the ODCM does not have a limit jbrfission and activationproducts.

The radionuclide composition of all gaseous radioactive effluents for a continuous-mode, ground-level release is given in Table 5. If a radionuclide was not present at a level "greater than or equal to the LLD" (>LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, LLDs were met or were below the levels required by the ODCM.

Radioactive Effluent Releases Page 14

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 5: Radioactive Gaseous Effluent Nuclide Composition UNIT QUARTER QUARTER QUARTER QUARTER ANNUAL 1 2 3 4 TOTAL A. FISSION AND ACTIVATION GASES Tritium Ci <LLD 6.06E-0I 7.68E+00 9.37E-03 8.30E+00 Argon-41 Ci <LLD <LLD <LLD <LLD <LLD Krypton-85m Ci <LLD <LLD <LLD <LLD <LLD Krypton-85 Ci <LLD <LLD [ <LLD [ <LLD <LLD Kryton-87 Ci <LLD 3.55E-01 <LLD I <LLD 3.55E-01 Krypton-88 Ci <LLD 1.41E-02 I <LLD <LLD 1.41E-02 Xenon- 131 m Ci <LLD <LLD <LLD [ <LLD <LLD Xenon-133m Ci <LLD <LLD <LLD I <LLD <LLD Xenon-133 Ci <LLD 6.05E-03 <LLD I <LLD 6.05E-03 Xenon-135m Ci <LLD 2.90E-01 <LLD <LLD 2.09E-01 Xenon-135 Ci 4.94E-02 3.04E-01 <LLD 2.21E-02 3.76E-0I Xenon-137 Ci <LLD <LLD <LLD <LLD <LLD Xenon-138 Ci J <LLD 1.55E+00 <LLD <LLD 1.55E+00 Total for Period Ci 4.94E-02 3.13E+00 7.68E+00 3.15E-02 1.09E+01 B. IODINE Iodine- 131 Ci <LLD 8.02E-05 <LLD 1.32E-04 2.12E-04 Iodine-132 Ci <LLD <LLD <LLD <LLD <LLD Iodine- 133 Ci <LLD 9.16E-05 <LLD 6.70E-05 1.59E-04 Iodine-134 Ci <LLD <LLD <LLD I <LLD <LLD Iodine-135 Ci <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD 1.72E-04 <LLD 1.99E-04 13.71 E-04 C. PARTICULATE Chromium-51 Ci <LLD <LLD <LLD <LLD <LLD Manganese-54 Ci <LLD <LLD <LLD <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD <LLD Cobalt-58 Ci <LLD <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD <LLD <LLD <LLD <LLD Zinc-65 Ci <LLD <LLD <LLD <LLD <LLD Rubidium-88 Ci <LLD <LLD <LLD <LLD <LLD Rubidium-89 Ci <LLD <LLD <LLD <LLD <LLD Strontium-89 Ci <LLD <LLD <LLD <LLD <LLD Strontium-90 Ci <LLD <LLD <LLD <LLD <LLD Strontium-91 Ci <LLD <LLD <LLD <LLD <LLD Yttrium-91m Ci <LLD <LLD <LLD <LLD <LLD Strontium-92 Ci <LLD <LLD <LLD <LLD <LLD Zirconium-95 Ci <LLD <LLD <LLD <LLD <LLD Molybdenum-99 Ci <LLD <LLD <LLD <LLD <LLD Cesium-137 Ci <LLD <LLD <LLD <LLD <LLD Cesium-138 Ci <LLD <LLD <LLD <LLD <LLD Barium-139 Ci <LLD <LLD <LLD <LLD <LLD Barium- 140 Ci <LLD <LLD <LLD <LLD <LLD Lanthanum-140 Ci <LLD <LLD <LLD <LLD <LLD Total for Period I Ci I <LLD <LLD I <LLD <LLD [ <LLD

<LLD - Less than the lower limit of detection Radioactive Effluent Releases Page 15

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Solid Waste All solid radioactive waste from PNPP was processed and combined with waste from several other utilities by intermediate vendors (Energy Solutions, Duratek in Oak Ridge, TN and Studsvik, in Erwin, TN). This waste was ultimately sent to Clive, Utah disposal facilities for burial. The solid radioactive waste summary in Table 6 includes all PNPP shipments for 2010.

Table 6: Solid Waste Shipped Offsite for Burial or Disposal A. TYPE OF SOLID WASTE SHIPPED VOLUME ACTIVITY PERIOD EsT. TOTAL (M3) (CI) ERROR (%)

Spent resin, filter sludge, evaporator 4.42E+01 5.66E+02 1/1/2010-12/31/2010 +/-25 bottoms, etc.

Dry compressible waste, contaminated 1.0lE+03 1.16E+00 1/l/2010-12/31/2010 +/-25 equipment, etc.

Irradiated components, control rods, etc. 0 0 1/l/2010-12/31/2010 Other (Standby Liquid Control Waste 0 0 1/l/2010-12/31/2010 Water)

B. ESTIMATE OF MAJOR") NUCLIDE COMPOSITION (BY RADIONUCLIDE ABUNDANCE EST. TOTAL TYPE OF WASTE) (%) ERROR, (%)

Spent Resin, Filter Sludge, Evaporator Bottoms, etc. Mn-54 5.22 +/- 25 Fe-55 44.84 Co-60 47.0 Ni-63 0.46 Zn-65 1.59 Cs-137 0.34 Dry Compressible Waste, Contaminated Equipment, etc. Mn-54 2.60 +/- 25 Fe-55 45.19 Co-60 46.6 Ni-63 4.32 Zn-65 0.40 Irradiated Components, Control Rods, etc. None 0 Other (Standby Liquid Control Waste Water) None 0 C. DISPOSITION [ SH PETIs NUMBER OF MODE OF TRANSPORTATION I DESTINATION Solid Waste (2) 13 1 Public Highway Studsvik, Erwin, TN Solid Waste(2) j 21 I Public Highway Duratek, Oak Ridge, TN Solid Waste j 0 T Public Highway t Barnwell, Barwell, SC Irradiated Fuel Shipments I 0 1 N/A I N/A NIA -- Not Applicable

( 1 ) -- "Major"is defined as any individual radionuclide identified as >1% of the waste type abundance.

(2) -- This waste was combined with waste from other utilities and disposed of at Clive, Utah.

Radioactive Effluent Releases Page 16

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT METEOROLOGICAL DATA The Meteorological Monitoring System at PNPP consists of a 60-meter tower equipped with two independent systems for measuring wind speed, wind direction, and temperature at both 10-meter and 60-meter heights. The tower also has instrumentation to measure dew point and barometric pressure. Data is logged from the tower through separate data loggers, and transmitted to a common plant computer. This system compiles the data and calculates a variety of atmospheric parameters, communicates with the Meteorological Information Dose Assessment System (MIDAS), and sends data over communication links to the plant Control Room.

A detailed report of the monthly and annual operation of the PNPP Meteorological Monitoring Program is produced under separate cover. For the period of January 1, 2010 through December 31, 2010, the report substantiates the quality and quantity of meteorological date collected in accordance with applicable regulatory guidance.

DOSE ASSESSMENT The maximum concentration for any radioactive release is controlled by the limits set forth in Title 10 of the Code of Federal Regulations, Part 20 (10CFR20). Sampling, analyzing, processing, and monitoring the effluent stream ensures compliance with these concentration limits. Dose limit compliance is verified through periodic dose assessment calculations. Some dose calculations are conservatively performed for a hypothetical individual who is assumed to reside on the site boundary at the highest potential dose location all year. This person, called the "maximum individual", would incur the maximum potential dose from direct exposure (air plus ground plus water), inhalation, and ingestion of water, milk, vegetation, and fish. Because no one actually meets these criteria, the actual dose received by a real member of the public is significantly less than what is calculated for this hypothetical individual.

Dose calculations for this maximum individual at the site boundary are performed for two cases.

First, they are performed using data for a 3600 radius around the plant site (land and water based meteorological sectors); even though some of these sectors are over Lake Erie, which has no permanent residents. The second calculation is performed considering only those sectors around the plant in which people reside (land-based meteorological sectors).

The calculated hypothetical, maximum individual dose values at the site boundary are provided in Table 7. This table considers all meteorological sectors around PNPP and provides either the whole body or worst-case, organ dose values. If any radionuclide was not present at a level greater than the LLD, it was not used in the dose calculations.

Table 7: Maximum Individual Site Boundary Dose, Considering All Sectors TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT  % OF (MREM) LIMIT Liquid Effluent Whole body 4.49E-03 3.OE+00 1.5E-01 Liver 4.56E-03 L.OE+01 4.6E-02 Noble Gas - gamma air N/A 2.04E-03 1.OE+01 2.02E-02

- beta air N/A 1.43E-03 2.OE+01 7.2E-03 Noble Gas Whole body 1.13E-03 5.OE+00 2.3E-02 Skin 2.39E-03 1.5E+01 1.6E-02 Particulate & Iodine Thyroid 4.13E-03 1.5E+01 2.8E-02 Radioactive Effluent Releases Page 17

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT The calculated hypothetical, maximum population dose values at the site boundary are provided in Table 8. This table considers all meteorological sectors around PNPP and provides either the whole body or worst-case, organ dose values.

Table 8: Population Dose, Considering All Sectors ORGAN ESTIMATED DOSE (PERSON-REM)

Liquid Effluent Whole body 6.7E-01 Thyroid 6.6E-01 Gaseous Effluent Whole body 1.5E-03 I Thyroid 2.OE-03 Table 9 provides the calculated hypothetical maximum site boundary dose values considering only the land-based sectors. If any radionuclide was not present at a level greater than the LLD, it was not used in the dose calculations.

Table 9: Maximum Individual Site Boundary Dose, Considering Sectors on Land TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT  % OF (MREM) LIMIT Liquid Effluent Whole body 1.53E-04 3.OE+00 5.1E-03 Liver 1.56E-04 L.OE+01 1.6E-03 Noble Gas - gamma air N/A 2.63E-08 1.0E+01 2.6E-07

- beta air N/A 3.37E-08 2.OE+01 1.7E-07 Noble Gas Whole body 1.46E-08 5.OE+00 2.9E-07 Skin 3.84E-08 1.5E+01 2.6E-07 Particulate & Iodine Thyroid 4.03E-05 1.5E+01 2.7E-04 Carbon-14 Bone 2.OOE-01 1.5E+01 8.OE+00 Other dose calculations are performed for a hypothetical individual who is assumed to be inside the site boundary for some specified amount of time. This person would receive the maximum dose during the time spent inside site boundary. Because no one actually meets the criteria established for these conservative calculations, the actual dose received by a real member of the public is significantly less than what is calculated for this hypothetical individual. This dose is assessed relative to the offsite dose, and considers dilution, dispersion, and occupancy factors.

The highest hypothetical dose from liquid effluents to a member of the public inside the site boundary is to a person who is fishing on Lake Erie from the shore on PNPP property. The calculations assume that this person will spend 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year fishing, with a liquid dilution factor of 10. The ratio of the exposure pathway to the doses calculated for offsite locations yields the dose values shown in Table 10.

Radioactive Effluent Releases Page 18

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 10: Maximum Site Dose from Liquid Effluents WHOLE BODY DOSE, ORGAN DOSE, (MREM) (MREM)

First Quarter 1.6E-05 1.8E-05 Second Quarter 2.4E-04 2.8E-04 Third Quarter 1.OE-04 1.2E-04 Fourth Quarter 2.9E-05 3.4E-05 Annual 3.8E-04 4.4E-04 Although several cases were evaluated to determine the highest hypothetical dose from gaseous effluents to members of the public inside site boundary, the activity inside the site boundary with the highest dose potential is also shoreline fishing. The cases evaluated included traversing a public road within the site boundary, shoreline fishing (assuming fishing 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year), non-plant related training, car-pooling, and job interviews. The maximum on-site gaseous doses generated are shown in Table 11.

Table 11: Maximum Site Dose from Gaseous Effluents WHOLE BODY DOSE, ORGAN DOSE, (MREM) (MREM)

First Quarter 6.6E-06 1.7E-05 Second Quarter 1.2E-04 2.3E-04 Third Quarter 3.5E-04 3.5E-04 Fourth Quarter 6.2E-06 9.8E-05 Annual 3.6E-04 4.4E-04 An average whole body dose to individual members of the public at or beyond the site boundary is then determined by combining the dose from gaseous and liquid radiological effluents. The dose from gaseous radiological effluents is based upon the population that lives within 50 miles of PNPP.

The dose from liquid radiological effluents is determined for the population that receives drinking water from intakes within 50 miles of PNPP. The results of this calculation are provided in Table 12.

Table 12: Average Individual Whole Body Dose LIQUID EFFLUENTS GASEOUS EFFLUENTS (MREM) (MREM)

First Quarter 6.3E-09 9.5E- 14 Second Quarter 1.7E-08 8.3E-I I Third Quarter 2.5E-07 5.4E- 10 Fourth Quarter 9.5E-09 1.6E-12 Annual 2.8E-07 6.2E-10 Radioactive Effluent Releases Page 19

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CARBON-14 SUPPLEMENTAL INFORMATION Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. C-14 is released primarily from BWRs through the off-gas system in the form of carbon dioxide (CO 2 ). The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation.

The U.S. Nuclear Commission (NRC) is now requiring assessment of gaseous C-14 dose impact to a member of the public resulting from routine releases in radiological effluents. Prior to 2010, the industry did not estimate the dose impact of C-14 releases. Since the dose contribution had been considered negligible compared to the dose impact from effluent releases of noble gases, tritium, particulates and radioiodines. At Perry, improvements over the years in effluent management practices and fuel performance have resulted in a decrease in the concentration and changes in the distribution of gaseous radionuclides released to the environment.

Perry's 2010 Annual Environmental Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2010, and estimates of public dose resulting from the C-14 effluent.

Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste at Perry is not required. Refer to Table 4 and Table 9 for C-14 estimated release values.

Radioactive Effluent Releases Page 20

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT ON-SITE GROUNDWATER MONITORING PROGRAM Introduction History In March, 2006, a routine sample of the underdrain system at the Perry plant showed detectable tritium concentration. The underdrains are a porous pipe system which drains groundwater from the foundations of the site buildings. As such, it would not be expected to be a contaminated system. A Condition Report, 06-01477, was submitted, and a Root Cause Investigation was conducted.

Concurrently, a program of groundwater monitoring was initiated.

It was determined at that time that there was no detectable tritium beyond the boundaries of the underdrain system. Piezometer tubes located both inside and outside of the power block, (area encompassing equipment utilized for the generation of electricity) were sampled and analyzed. In 2007, Perry contracted with Environmental Resource Management (ERM) of Boston, Massachusetts to perform site hydrogeology evaluations, and to facilitate installation of additional groundwater monitoring wells, based on their findings. FirstEnergy fleet chemistry formalized the program with the issuance of fleet procedure NOP-LP-2012, "Groundwater Monitoring."

Cause The buildings at the Perry site are designed with seismic spaces between building walls. These would serve to drain plant buildings in the event of an earthquake of sufficient strength to break plant piping, minimizing the flooding of vital equipment areas, and facilitate continued safe operation, or safe shutdown, as conditions warrant.

It was surmised that these "rattle spaces" also allow the drainage from some plant systems to reach the outside. Since this discovery, the plant has developed a more rigorous stance towards plant observations, and has minimized process water intrusion into the rattle spaces.

It should be noted that no leakage was identified from either the radwaste system, or from the Spent Fuel Building.

UnderdrainSystem As mentioned earlier, the underdrain system drains water away from plant foundations. It is separate and distinct from the storm drain system, which is designed purely for rain water control. The underdrain system has a number of installed sump pumps, with the ability to gravity-drain and cascade forward should the pumps fail. There are two major branches of underdrains, one for each of the east and west sides of the power block. These branches ultimately flow into 2 underdrain manholes, designated MH-20 and MH-23, before draining to the suction bay of the Emergency Service Water (ESW) pump house. From there, the water is discharged from the plant. Refer to Figure 2 for locations of Manholes I through 23.

Sampling Locations Prior to the installation of monitoring wells, Manholes 20 and 23 were sampled to assess groundwater tritium in-leakage to the system. This continued through July 2007, and sampling frequency was established at weekly thereafter. Besides tritium, the samples were also analyzed via gamma spectroscopy to environmental lower limits of detection. No gamma activity was ever detected in any sample.

Manholes 20 and 23 were sampled daily through the middle of 2007, and weekly thereafter through the end of the year. Tritium releases from the station were documented as abnormal releases, and the Radioactive Effluent Releases Page 21

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT required dose calculations were completed per the Offsite Dose Calculation Manual (ODCM).

Overall, the released tritium represented a very small fraction of the limits prescribed in 10CFR20 Appendix B and 10CFR50.

Based on the ERM hydrogeology study, 12 wells were recommended for the site. Since most groundwater flow was anticipated to drain north, towards Lake Erie, the majority of wells are drilled there. A set of control wells was drilled in a more southerly direction, to assess what a typical groundwater profile would be.

There are 4 sets of triplet wells installed at each location. Each triplet has a shallow well (approximately 25 feet), a mid-depth well of approximately 50 feet, and a deep well of approximately 75 feet. These 3 depths are designated A, B and C, from shallowest to deepest, respectively. Refer to Figure 2 for locations of Groundwater wells IA through 4C.

Besides these wells, there are a number of plant piezometers which date back to early plant construction. Outside of the power block, these are located directionally along the 4 major compass points. There are also piezometers inside the plant buildings in numerous locations. Refer to Figure 2 for locations of Piezometers.

Radioactive Effluent Releases Page 22

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 2: Underdrain System and On-Site Groundwater Wells

  • Manholes *.............

0Piezometers

  • fl o:

Groundwater Wells

  • U
  • U
  • U
  • U
  • "UN *"

Radioactive Effluent Releases Page 23

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT State of the Program Currently, the monitoring wells are sampled twice annually, in spring and fall. The sampling is done under a controlled protocol, and is conducted by personnel from FirstEnergy's BETA Laboratories.

Selected plant piezometers are also sampled.

The samples are analyzed for shipping purposes, and are then shipped to Midwest Laboratories in Illinois. Midwest analyzes the sample for gamma isotopic and tritium. On alternate samples, Perry has also requested analysis of "hard-to-detect" isotopes such as Sr-89/90, Ni-63 and Fe-55.

Noteworthy Items Groundwater well samples for the first half of 2010 were collected the week of 4/12/10 by BETA labs. Perry warehouse and UPS contacted Chemistry on 5/19/10 to report that 3 samples were crushed in transit. CR 10-77095 generated to document the loss of the 3 samples (3C, 4A and N 83). These were resampled by BETA on 6/22/10. Groundwater well analyses are not required by the ODCM. However, sample results provide data for adequate tracking and trending of individual monitoring wells.

The tritium (H-3) value for Piezometer tube #6 collected in Spring 2010 was 2950 pCi/L vs. the threshold of 2000 pCi/ L. Back up sample results indicated a H-3 value of 2870 pCi/L and is consistent with previous sample results. No leakage was found from RWCU system or the feedwater venturis and all radwaste inventory can be accounted for. Based on the back up sample results and monitoring activities, there does not appear to be a new leak but rather a "recharge" of the previously reported leak as described in CR 06-01477. Condition Report 10-78248 was written to document actions taken. No ODCM required reporting values/limits were exceeded (20,000 pCi/L) or were any Tech Spec or ORM limits exceeded.

Radiological Environmental Monitoring Page 24

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 13: Summary of Onsite Groundwater Samples Monitoring H-3 MAX. H-3 H-3 TYPICAL REQUIRED PRE- H-3 ANALYSES NEI EPA Well (PCi/L) MIN. AVG. H-3 LLD H-3 LLD OPERATIONAL > PRE- AND REPORTING (PCI/L) (PCI/L) (PCI/L) (PCI/L) (DEVELOPED) OPERATIONAL FENOC LEVEL FOR MEAN FOR H-3 MEAN FOR H-3 LEVEL H-3 (PCIlL) FOR H-3 (PCi/L)

(PCI/L)

First Half 220+/- 87 N/A N/A < 200 < 2000 400 No 2000 20000 2010 Well IA <144 N/A N/A < 200 < 2000 400 No 2000 20000 Well 1B <144 N/A N/A < 200 < 2000 400 No 2000 20000 Well IC <144 N/A N/A < 200 < 2000 400 No 2000 20000 Well2A <144 N/A N/A < 200 < 2000 400 No 2000 20000 Well 2B <144 N/A N/A < 200 < 2000 400 No 2000 20000 Well 2C <144 N/A N/A < 200 < 2000 400 No 2000 20000 Well 3A 220+/-87 N/A N/A < 200 < 2000 400 No 2000 20000 Well 3B <144 N/A N/A < 200 < 2000 400 No 2000 20000 Well 3C <166 N/A N/A < 200 < 2000 400 No 2000 20000 Well 4A <166 N/A N/A < 200 < 2000 400 No 2000 20000 Well 4B <145 N/A N/A < 200 < 2000 400 No 2000 20000 Well 4A <145 N/A N/A < 200 < 2000 400 No 2000 20000 Second Half 2010 364+/-88 N/A N/A < 200 < 2000 400 No 2000 20000 Well LA <139 N/A N/A < 200 < 2000 400 No 2000 20000 Well 1B <139 N/A N/A < 200 < 2000 400 No 2000 20000 Well IC <139 N/A N/A < 200 < 2000 400 No 2000 20000 Well 2A <139 N/A N/A < 200 < 2000 400 No 2000 20000 Well 2B <139 N/A N/A < 200 < 2000 400 No 2000 20000 Well 2C 334+/- 89 N/A N/A < 200 < 2000 400 No 2000 20000 Well 3A 364+/- 88 N/A N/A < 200 < 2000 400 No 2000 20000 Well 3B <145 N/A N/A < 200 < 2000 400 No 2000 20000 Well 3C <145 N/A N/A < 200 < 2000 400 No 2000 20000 Well 4A <145 N/A N/A < 200 < 2000 400 No 2000 20000 Well 4B <145 N/A N/A < 200 < 2000 400 No 2000 20000 Well 4C <145 N/A N/A < 200 < 2000 400 No 2000 20000 Radiological Environmental Monitoring Page 25

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT ABNORMAL RELEASES There were no abnormal radioactive release events during 2010.

NON-COMPLIANCES There were no non-compliances to the ODCM Controls requirements in 2010.

OFFSITE DOSE CALCULATION MANUAL CHANGES During this reporting period, there was (1) revision to the Offsite Dose Calculation Manual.

Rev. 18 Revised the Master list of sampling locations per corrective action 10-81956-01:

1) Removed location 20 (not ODCM required) from both the ODCM REMP Sample Locations List (page 84) and ODCM map Figure 5.1-1
2) Removed location 34 (not ODCM required) from both the ODCM REMP Sample Locations List (page 84), ODCM map Figure 5.1-1
3) Added Location #18 to the ODCM REMP Sample Locations List (page 84) and ODCM map Figures 5.1-2.
4) Revised ODCM REMP Sample Locations List (page 84) foot note (1) Chronologically missing location numbers denote deleted or retired sampling locations" to "chronologically missing location numbers denote deleted, retired or non-ODCM required sampling locations".
5) Corrected ODCM figures per condition report 10-8 1955, revised Section 2.1, Figure 1 (page 2) to remove the incorrect notation of abandoned component. Removed revision bar on page 5 section 2.1.1.3.

This will align the ODCM with the USAR.

6) Upgraded ODCM map Figure 5.1-3 to a color copy providing better clarity.
7) Revised sections 1.0 (page 1), 4.1 (page 72), 4.2 (page 73),

3.11.4 (page 148), 4.11.4.2 (page 149) and 3/4.11.4 (page 179) to reference the onsite Independent Spent Fuel Storage Installation (ISFSI).

PROCESS CONTROL PROGRAM CHANGES During this reporting period, there was (1) revision to the Process Control Program.

Rev. 11 SCOPE OF REVISION:

1. Removed all references to Radwaste Solidification which is not used any longer at PNPP.
2. Updated procedure references.
3. Updated Section names.
4. Updated format of Controls
5. Updated references.
6. Updated Radwaste Process Flow Chart.
7. Incorporated needed corrections to the PCP as identified in CR 09-65546 Radiological Environmental Monitoring Page 26

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING INTRODUCTION The Radiological Environmental Monitoring Program (REMP) was established at PNPP for several reasons. First, it verifies the adequacy of plant design and operation to control radioactive materials and limit effluent releases. Second, it assesses the radiological impact, if any, that the plant has had on the surrounding environment. Third, it ensures compliance with regulatory guidelines. The REMP is conducted in accordance with the PNPP Operating License, Appendix B, Technical Specifications and the ODCM. The Nuclear Regulatory Commission (NRC) established the REMP requirements.

A wide variety of samples are collected as part of the PNPP REMP. The selection of sample types, sampling locations, and sample collection frequency are based on many things. Potential pathways for the transfer of radionuclides through the environment to humans, sample availability, local meteorology, population characteristics, land use and NRC requirements are all considered.

To ensure that the REMP data are meaningful and useful, detailed sampling methods and procedures are followed. This ensures that samples are collected in the same manner and from the same locations each time. All samples are packaged on site, and then shipped to an independent vendor laboratory for analysis. The vendor laboratory analyzes the samples and reports results to the PNPP Chemistry Unit staff, the Lake County General Health District, and the State of Ohio Department of Health.

The REMP began in 1981 with 24 direct radiation monitoring locations, four sediment locations, and two fish sampling locations. In 1982, collections of air, water, milk, food products, and feed/silage were added. Vegetation, precipitation and soil were added in 1985. Although the NRC did not require these last three media, they were incorporated into the program to establish baseline data. In 1993, feed/silage sampling was dropped from the program, based on ten years worth of data. For the same reason, strontium analyses were deleted from the program in 1994, gross beta and tritium were deleted from precipitation analyses in 1995, and precipitation sampling was deleted entirely in 1996.

In 1999, grass (vegetation) and soil sampling were dropped from the program.

SAMPLING LOCATIONS REMP samples are collected at numerous locations, both on site and up to 22 miles away from the plant. Sampling locations are divided into two general categories: indicator and control. Indicator locations are those which would be most likely to display effects caused by plant operation. They are relatively close to the plant. Control locations are those which are considered to be unaffected by plant operation. Typically, they are a greater distance from the plant, in the least prevalent wind directions. Data obtained from the indicator locations are compared with data from the control locations. This comparison allows naturally occurring background radiation to be taken into account when evaluating any radiological impact PNPP may have had on the environment. Table 14, Figure 3, Figure 4 and Figure 5 identify the PNPP REMP sampling locations.

Many REMP samples are collected in addition to those required by the PNPP ODCM. The ODCM requirements for each sample type are discussed in more detail below. Sample types and locations required by the ODCM are shown in Bold in Table 14.

Radiological Environmental Monitoring Page 27

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 14: REMP Sampling Locations (1)

LOCATION # DESCRIPTION MILES DIRECTION MEDIA( 2) 1 Chapel Road 3.4 ENE TLD, AlP 2 Kanda Garden 1.9 ENE Food Products 3 Meteorological Tower 1.0 SE TLD, AlP 4 Site Boundary 0.7 S TLD, AlP 5 Quincy Substation 0.6 SW TLD, AIP 6 Concord Service Center 11.0 SSW TLD, AIP 7 Site Boundary 0.6 NE TLD, AlP 8 Site Boundary 0.8 E TLD 9 Site Boundary 0.7 ESE TLD 10 Site Boundary 0.8 SSE TLD 11 Parmly Rd. 0.6 SSW TLD 12 Site Boundary 0.6 WSW TLD 13 Madison-on-the-Lake 4.7 ENE TLD 14 Hubbard Rd. 4.9 E TLD 15 Eagle St. Substation 5.1 ESE TLD 16 Eubank Garden 0.8 S Food Products 18 Kijauskas Farm (goat) 2.5 E Food Products, Milk 20 Rainbow Farms 1.9 E Food Products 21 Hardy Rd. 5.1 WSW TLD 23 High St. Substation 7.9 WSW TLD 24 St. Clair Ave. 15.1 SW TLD 25 Offshore - PNPP discharge 0.6 NNW Sediment, Fish 26 Offshore - Redbird 4.2 ENE Sediment 27 Offshore - Fairport Harbor 7.9 WSW Sediment 28 CEI Ashtabula Plant Intake 22.0 ENE Water 29 River Rd. 4.3 SSE TLD 30 Lane Rd. 4.8 SSW TLD 31 Wood and River Rd. 4.8 SE TLD 32 Offshore - Mentor 15.8 WSW Sediment, Fish 33 River Rd. 4.5 S TLD 34 PNPP Intake 0.7 NW Water 35 Site Boundary 0.6 E TLD, AIP 36 Lake County Water Plant 3.9 WSW TLD, Water 37 Gerlica Farm 1.5 ENE Food Products 41 Tuttle Farm (goat) 5.8 SSE Milk 51 Rettger Milk Farm (cow) 9.6 S Milk 53 Neff Perkins 0.5 WSW TLD 54 Hale Rd. School 4.6 SW TLD 55 Center Rd. 2.5 S TLD 56 Madison High School 4.0 ESE TLD 58 Antioch Rd. 0.8 ENE TLD 59 Lake Shoreline at Green Rd. 4.0 ENE Water 60 Lake Shoreline at Perry Park 1.0 WSW Water 61 Keller Milk Farm (goat) 7.4 SE Milk 63 Minor Stream Mouth 0.08 NNE Sediment 64 Northwest Drain Mouth 0.09 NW Sediment 65 Major Stream Mouth 0.18 W Sediment 70 H&H Farm Stand 16.2 SSW Food Products (1) Chronologicallymissing location numbers denote deleted or retired sampling locations.

(2) AlP = Air, Iodine and Particulate TLD = Thermnoluminescent Dosimeter Radiological Environmental Monitoring Page 28

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 3: REMP Sampling Locations Within Two Miles of Plant Site NNW N NNE NW NE WNW ENE W E WSW ESE SW SE SSW S SSE 1 0 12 MILES Radiological Environmental Monitoring Page 29

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 4: REMP Sampling Locations Between Two and Eight Miles of the Plant Site SW SSW S sse Se 0 1 2 3 4 5 10 MILES I-M M 11 Radiological Environmental Monitoring Page 30

ANNUAL EN-VIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 5: REMP Sampling Locations Greater Than Eight Miles from the Plant Site nw ,n fMleveland SV Hgs-n- erLcw° 20 es 15 0 Res MILE Radiological Environmental Monitoring Page 31

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT SAMPLE ANALYSIS When environmental samples are analyzed for radioactivity, several types of measurements are performed to provide information about the types of radiation and radionuclides present. The major analyses that are performed are discussed below.

Gross beta activity measures the total amount of beta-emitting radioactivity present in a sample, and acts as a tool to identify samples that may require further analysis. Beta radiation may be released by many different radionuclides. Since beta decay results in a continuous energy spectrum rather than the discrete energy levels, or "peaks", associated with gamma radiation, identification of specific beta-emitting nuclides is much more difficult. Therefore, gross beta activity only indicates whether the sample contains normal or abnormal amounts of beta-emitting radioactivity; it does not specifically identify the radionuclides present.

Gamma spectral analysis provides more specific information than does the analysis for gross beta activity. Gamma spectral analysis identifies each radionuclide, and the amount of radioactivity, present in the sample emitting gamma radiation. Each radionuclide has a very specific "fingerprint" that allows for accurate identification and quantification.

Iodine activity analysis measures the amount of radioactive iodine present in a sample. Some media (for example, air sample charcoal cartridges) are analyzed directly by gamma spectral analysis. With other media (for example, milk), the radioiodines are extracted by chemical separation before being analyzed by gamma spectral analysis.

Tritium activity analysis measures the amount of the radionuclide tritium (H-3) present in a sample.

Tritium is an isotope of hydrogen that emits low-energy beta particles. Tritium occurs naturally and is also man-made.

Gamma doses received by Thermoluminescent Dosimeters (TLD) while in the field are determined by a special laboratory procedure. Thermoluminescence is a process by which ionizing radiation interacts with the sensitive phosphor material in the TLD. Energy is trapped in the TLD material and can be stored for months or years. This capability provides an excellent method to measure the dose received over long periods of time. The amount of energy that was stored in the TLD as a result of interaction with radiation is released by a controlled heating process and measured in a calibrated reading system.

As the TLD is heated, the phosphor releases the stored energy as light. The amount of light is directly proportional to the amount of radiation to which the TLD was exposed. The reading process also zeroes the TLD and prepares it for reuse. Table 15 provides a list of the analyses performed on environmental samples collected for the PNPP REMP in 2010.

Sample results are often reported as less than the lower limit of detection (< LLD), which is defined as the smallest amount of radioactive material that will show a positive result for which there can be confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample analysis. When a measurement is reported as < LLD, it means that no radioactivity was detected at a value above, or equal to the appropriate ODCM table value. The NRC has established LLD values for REMP sample analyses. The vendor laboratory for REMP sample analyses complied with those values in 2010.

Radiological Environmental Monitoring Page 32

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 15: REMP Sample Analyses TYPE SAMPLE FREQUENCY ANALYSIS Atmospheric Monitoring Airborne Particulates Weekly & Gross Beta Activity &

Quarterly Gamma Spectral Analysis Airborne Radioiodine Weekly Iodine-131 Terrestrial Monitoring Milk Bi-Monthly Gamma Spectral Analysis &

Iodine- 131 Food Products Monthly Gamma Spectral Analysis Aquatic Monitoring Water Monthly Gross Beta Activity &

Gamma Spectral Analysis Quarterly Tritium Activity Fish Annually Gamma Spectral Analysis Sediment Biannually Gamma Spectral Analysis Direct Radiation Monitoring TLD Quarterly & Gamma Dose Annually 2010 SAMPLING PROGRAM The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the 2010 program with pre-operational data (i.e., data from before 1986),

operational data from previous years, and control location data. The results for each sample type are discussed below and compared to historical data to determine if there are any observable trends. All results are expressed as concentrations. Refer to Appendix B, 2010 REMP Data Summary Reports for a detailed listing of these results. The NRC requires special reporting whenever sample analysis results exceed set limits. No values exceeded these reporting levels in 2010.

Program Changes No REMP program changes were implemented in 2010.

Missed Samples On occasion, samples cannot be collected. This can be due to a variety of events, including equipment malfunction, animal husbandry practices, or lost shipments. Events may also occur which prevent a sample from being collected in the normal way, or prevent a complete sample from being collected.

The drying period for goats is an annual occurrence, since unlike cows, goats cannot produce milk year-round. Food products are weather dependent and are susceptible to excessive spring rains or summer drought that can significantly impact the garden harvest. Shoreline lake water samples are collected by grab sample utilizing a container and scoop. During the winter months the shoreline can become inaccessible due to ice and snow buildup, preventing the safe collection of these samples.

Shoreline sediment samples are collected with spoon and container. On occasion, the accessibility of these locations and sample collection may be impacted due to high lake levels, shifting lake bottom sediment, bluff erosion and shoreline collapse. For 2010, there was no impact to the program requirements as a result of any missed samples. Table 16 provides information on samples missed during 2010.

Radiological Environmental Monitoring Page 33

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 16: Missed REMP Samples in 2010 MEDIA LOCATION DATE REASON Air Samples #35 11/24/10 Failure to restart sampler after 11/17/10 collection. CR 10-86276 Food Products All Jan.-June, Nov.-Dec. 2010 Insufficient growth/temperature. Die-off/Frost damage.

Lake Water 59, 60 Jan., Feb., Mar. Dec. 2010 Sample unavailable due to frozen shoreline Milk 18 Jan., Feb., Mar. 2010 Drying period for goats/sample availability 41 Jan., Feb., Mar., Oct. ( 2 nd half) Drying period for goats/sample availability Nov., Dec. 2010 61 Jan., Feb., Mar., Apr., Drying period for goats/sample availability Oct. (2"d half), Nov.,

Dec. 2010 Sediment 63 May and October 2010 Location inaccessible/shoreline erosion Atmospheric Monitoring Air Air sampling is conducted to detect any increase in the concentration of airborne radionuclides. The PNPP REMP maintains an additional 2 air sampling locations above the five locations (four indicators and one control) required by the ODCM. Six (6) of these locations are within four miles of the plant site; the seventh is used as a control location and is eleven miles from PNPP. Air sampling pumps are used to draw continuous samples at a rate of approximately two cubic feet per minute. The air is drawn through glass fiber filters (to collect particulate material) and a charcoal cartridge (to adsorb iodine). The samples are collected on a weekly basis, 52 weeks a year, from each of the seven air sampling stations.

On occasion, power losses associated with storms, malfunctioning equipment or human error could affect sample collection. On 11/24/10 the air sample for location #35 (ODCM required) was not collected due to human error. The technician failed to restart the sampler after the 11/17/10 collection, which resulted in a loss of sample for the time period 11/17/10-11/24/10. Condition report 10-86276 was generated for documentation purposes.

Air samples are analyzed weekly for gross beta activity and radioiodine activity. The air samples are also analyzed by gamma spectral analysis quarterly. A total of 363 air particulate and 363 air radioiodine samples were collected and analyzed in 2010.

Gross beta activity was detected in 362 of 363 air samples and ranged up to 0.05pCi/m 3. The average gross beta activity at both indicator and control locations was 0.02 pCi/m 3 for 2010. Historically, the concentration of gross beta in air has been essentially identical at indicator and control locations.

Figure 6 reflects the average gross beta activity for 2010 and the previous years.

Except for naturally occurring beryllium-7, no radionuclides were identified in the gamma spectral analysis above the LLD values. Iodine-131 was not detected in any sample above the LLD of 0.05 pCi/m 3.

Radiological Environmental Monitoring Page 34

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 6: Annual Average Gross Beta Activity, in Air 0.05 o5.0 o 0.04 3 . . .........

A! 0.02-

  • 0.0 1 .. ....

C M\ LO) C r~

CD W 0- 0 CD J M~ U CO I- CW 0M 0 LO M~ U CD r--

to M 0) 0 co CD coo 0 c co ) 0) 0) 0) 0) 0M a) 0) 0)0 0 0 0 0 00 0 0 0

0) 0) ) 0) ) 0) 0) 0) 0) 0) 0)0) 0- 0) 0) 0)* 0 0) 0 0 0,0 0 00 0 0 0 0 Year lj Indicator N Control Terrestrial Monitoring Collecting and analyzing samples of milk and food products provides data to assess the build-up of radionuclides that may be ingested by humans. The historical data from soil and vegetation samples provides information on the atmospheric radionuclide deposition. The PNPP ODCM requires neither vegetation nor soil samples.

Milk Samples of milk are collected once each month from November through March, and twice each month from April through October. Sampling is increased during the summer because animals usually feed outside on pasture and not on stored feed. For 2010, the PNPP REMP included four (4) milk locations located 2.5, 5.8, 7.4 and 9.6 miles away from the plant.

Since the milk sampling locations do not meet the requirements of the ODCM (few milk-producing animals located within the required areas), food product sampling (discussed below) is performed.

Milk is collected from the available locations for informational purposes, even though they do not meet the ODCM requirements. If new locations that meet the ODCM requirements are identified in the future, they will be added to the program.

Milk samples are analyzed by gamma spectral analysis for radioiodines and other radionuclides. A total of fifty-nine (59) milk samples were collected in 2010. Iodine was not detected in any of the samples above the LLD of 0.75 pCi/ L. The concentrations of all radionuclides, except naturally occurring potassium-40, were below LLDs in all samples collected.

Food Products Food products can provide a direct pathway to humans by ingestion. They can absorb radionuclides from atmospheric deposition on soil or from irrigation water drawn from a lake or pond receiving airborne or liquid effluents. Also, radionuclides in the soil may be absorbed by the roots of the plants and become incorporated into the edible portions. Because there is not a sufficient number of dependable milk sampling locations, the PNPP REMP is required to include two food product indicator locations and one control location. Food products are collected monthly during the growing season from six (6) gardens in the vicinity of PNPP. The control location for food products is 16.2 miles SSW from PNPP.

Radiological Environmental Monitoring Page 35

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT A total of fifty-seven (57) food product samples were collected and analyzed by gamma spectral analysis in 2010. For the 2010 growing season, unseasonably warm spring temperatures followed by an early drought contributed to the missed samples referenced in Table 16.

Four (4) food products were collected which included: beet greens, collard greens, turnip greens and swiss chard. Beryllium-7 and potassium-40, naturally-occurring radionuclides, were found in several samples, as expected. No other radionuclides were detected above the required LLDs.

Aquatic Monitoring Radionuclides may be present in Lake Erie from many sources other than the PNPP. These sources include atmospheric deposition, run-off/soil erosion, and releases of radioactivity in liquid effluents from hospitals, universities or other industrial facilities. These sources provide two forms of potential radiation exposure, external and internal. External exposure can occur from contact with water or shoreline sediments, while internal exposure can occur from either direct ingestion of radionuclides or the transfer of radionuclides through the aquatic food chain. Direct ingestion can occur from drinking the water, while the transfer via the aquatic food chain occurs from the eventual consumption of aquatic organisms, such as fish. To monitor these pathways, PNPP samples water, shoreline sediments, and fish.

Water Water is sampled from five locations along Lake Erie in the vicinity of the PNPP as required by the PNPP ODCM. Samples from three locations are collected using composite sample pumps. The pumps are designed to collect water at regular intervals and composite it in a sample container.

Samples from the two other locations are manually collected weekly and combined. The containers are emptied monthly and the samples shipped to the vendor laboratory for analysis.

Fifty-two (52) water samples were collected and analyzed for gross beta activity and gamma spectral analysis in 2010. From these monthly samples, eighteen (18) quarterly composite samples were obtained and analyzed for tritium activity.

For 2010, gross beta activity was detected in ten (10) of the fifty-two (52) samples collected. The detectable gross beta activity was 2.87pCi/L vs. the lab LLD value of 3.00 pCi/L. Refer to Figure 7 for the annual average gross beta activity for both indicator and control locations. The significant difference between the pre-1988 data and post-1988 data has been attributed to a change in vendor laboratories in 1987/1988. A comprehensive explanation for the observed difference is provided in the 1988 Annual Environmental Operating Report.

Radiological Environmental Monitoring Page 36

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 7: Annual Average Gross Beta Activity, in Water 12 10 8

6 4

2 N,' CO) It O CO r'- C)O~ 0) C C\ C) 0 (j r- a) 0M 0D x- C'.4 C') T CL Co r'- a)00 C 0D 00 00) 0 00 a O 00 0000 0) 0) 0) 0) 0) 0) 0) 0) 0) 0 0 0 0 0 0 0 0 0 00

0) 0) 0) M 0
0) 0) ) 0M 0) 0 0 M 0) 0 0 0 0 0 0 0 0 0 0 0 r , r rr - rr ,r rr r r 'J N "' CN N'. N~ N. 04 (N (N N Year 0indicator EControl There were no radionuclides detected by gamma spectral analysis above the LLD.

Tritium was not detected above the LLD value in any of the eighteen (18) samples analyzed. These results are well within the range of those measured in previous years, which have ranged from below the LLD to 2,200 pCi/L. Refer to Table 16 for an explanation of any missed samples.

Sediment Sampling of lake bottom sediments can provide an indication of the accumulation of particulate radionuclides which may lead to internal exposure to humans through the ingestion of fish, the re-suspension into drinking water, or as an external radiation source to fishermen and swimmers from shoreline exposure. Although the PNPP ODCM requires only one location, sediment is presently sampled twice each year from six (6) locations. Beginning in 2006, access to sample location 63 was lost due to shoreline erosion which resulted in a bluff collapse. Lack of safe access continues to prevent sample collection at location #63.

Sediment samples from offshore are collected using a hand dredge. Shoreline samples are collected using a scoop.

Twelve (12) sediment samples were collected in 2010 and analyzed by gamma spectroscopy. The predominant radionuclide detected by gamma spectral analysis was naturally-occurring potassium-40.

Potassium-40 has been detected in all samples, since the program began in 1981.

Cesium-137 activity was detected in five (5) of the twelve (12) samples collected and ranged from 138.18 pCi!kg to 737.85 pCi/kg. The annual average cesium-137 activity was 169.30 pCi/kg for the indicator locations and 685.94 pCi/kg at the control location. The average cesium-137 radioactivity for all locations was 375.95 pCi/kg and is within the maximum value of 864 pCi/kg established in 1981. Year-to-year variations in lake bottom sediment sample activity is expected and beyond the control of PNPP. For example, cesium-137 activity variations (refer to Figure 8) in the control locations from year-to-year may be contributed to:

1. The movement of sediment on the lake bottom due to wave action and currents.
2. Difficulty in duplicating exact location and composition of bottom sediment sample from year to year even with assistance of GPS.

Radiological Environmental Monitoring Page 37

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 8: Annual Average Cesium-137 Concentration in Sediment 1600 1400 1200 1000 800 600 400 200 0

0) ~~-~ O 0", WN

, W' a)

WO0M W0)0)0)

M0 M- 0, M0 0) M) 0)

0) M- 0)M~ M' )00a)MtUC)C> 00CN C) C')0C0 U0IC) CDCD ) C)0) C)CD 00 0)0) 0)1 0 NO CN C N, C , N)('4l Year Indic ato r NC o ntrol Northwest Drain Impoundment In 1999, a sediment sample from location #64 (shoreline discharge point of the Northwest Drain Impoundment) was found to contain trace levels of cobalt-60. Ten (10) additional sample locations were established upstream from location #64 and within the Impoundment to identify the boundary of the cobalt-60 activity and to support supplemental monitoring activities. In recent years, the shoreline adjacent to the impoundment has experienced extensive bluff erosion and collapse, preventing access and sample collection for locations 64-4 and 64-5. Detailed maps of the impoundment, sample locations and sample results can be found in Chemistry Technical Assignment File TAF 10-001.

On 5/26/10, during spring sampling, 84 +/- 36 pCi/kg (dry) of cobalt-58 was identified at location 64-

9. Additionally, increased levels of cobalt-60 were identified at locations 64-6 and 64-9. Back-up sediment samples were collected on 7/13/10. Cobalt-58 was not identified in either sample.

Condition report 10-79628 was written to document the identification of cobalt-58 and subsequent investigation and corrective actions. The investigation identified that protected area runoff water from low level rad material movements and transport vehicles may be transported to the storm drain upstream of the Impoundment. Corrective actions directed the addition of sample location 64-11 within the impoundment and catch basins W-24 and W-25 upstream of the impoundment. Additional samples were collected at locations 64-6 thru 64-11 and W-24 and W-25 on 07/26/10 and 07/30/10 respectively. Fall sampling was performed on 10/11/10, 10/13/10 and 12/18/10 at all active locations.

For 2010, sample results for cobalt-60 from the twelve (12) active locations confirm that no activity was identified at the discharge point (Location #64), and continues to remain within the Northwest Drain Impoundment with an activity range of <4.3 pCi/kg to 3447 +/- 93 pCi/kg (Refer to Table 17).

For informational purposes, cesium-137 activity in sediment within the impoundment is also documented. Refer to Table 18 for these results.

Radiological Environmental Monitoring Page 38

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 17: Northwest Drain Impoundment Cobalt-60 Activity, pCi/kg (dry)

LOCATION 05/26/10 07/13/10 07/26/10 07/30/10 10/11/10 10/13/10 12/18/10 64 <4.3 ** ** ** <14.2 ** **

64-1 <8 ** ** ** ** <13 **

64-2 <21 ** ** ** ** <32 **

64-3 50+/-29 ** ** ** ** <24 **

64-6 2308+/-99 89+/-31 <50 ** ** <87 **

64-7 149+/-34 ** 117+/-31 ** ** 118+/-35 **

64-8 <16 ** 18+/-7 ** ** <20 **

64-9 3447+/-93 186+/- 19 314+/-38 ** ** 67+/-35 **

64-10 242+/-37 ** 116+/-32 ** ** 125+/-28 **

64-11 ** ** 100+/- 18 ** ** <20 **

W-24 ** ** ** <25.2 ** **

  • W-25 ** ** ** <7.2 ** ** <16.0
  • No sample available or insufficient sample for analysis ** No sample collected on this date Table 18: Northwest Drain Impoundment Cesium-137 Activity, pCi/kg (dry)

LOCATION 05/26/10 07/13/10 07/26/10 07/30/10 10/11/10 10/13/10 12/18/10 64 <11.0 ** ** ** <11.1 ** **

64-1 <19 ** ** ** ** <17 **

64-2 818+/-39 ** ** ** ** 534+/-68 **

64-3 168+/-36 ** ** ** ** 572+/-49 **

64-6 1486+/- 105 999+/-60 1193+/-65 ** ** 2359+/- 128 **

64-7 2860+/-81 ** 2279+/-66 ** ** 1927+/-74 **

64-8 604+/-37 ** 379 +/- 12 ** ** 283 +/-39 **

64-9 1053+/-84 1299+/-34 1286+/-47 ** ** 1234+/-59 **

64-10 1814+/-72 ** 1511 +/-63 ** ** 1823 +/-57 **

64-11 ** ** 1271 +/-43 ** ** 190+/- 18 **

W-24 ** ** ** 576+/-52.9 **

  • W-25 ** ** ** 1102 +/- 42.1 ** ** 1476 +/- 56.7 No sample available or insutticient sample tor analysis "* No sample collected on thls date Radiological Environmental Monitoring Page 39

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Fish Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondarily to serve as indicators of radioactivity in the aquatic ecosystem. Fish are collected from two locations, annually during the fishing season as required by the ODCM. An important sport or commercial species is targeted, and only the fillets are sent to the laboratory for analysis. In 2010, fish sampling was performed for PNPP by a local licensed sport fisherman.

Four fish samples including (2) Yellow Perch and (2) Freshwater Drum were collected and analyzed by gamma spectral analysis in 2010. As expected, naturally occurring potassium-40 was found in all samples. No other radionuclides were detected above the LLD.

Direct Radiation Monitoring Thermoluminescent Dosimeter (TLD)

Environmental radiation is measured directly at 28 locations around the PNPP site, two of which are control locations. The locations are positioned in two rings around the plant as well as at the site boundary. The inner ring is within a one-mile radius of the plant site; the outer ring is four miles to five miles from the plant. The control locations are over ten miles from the plant in the two least prevalent wind directions. Each location is equipped with three TLDs, two of which are changed quarterly and one is changed annually.

A total of 252 TLDs were collected and analyzed in 2010. This includes 224 collected on a quarterly basis and 28 collected annually. Annual TLDs are not required per the ODCM and are used for supplemental data only.

For 2010, the annual average dose for all indicator locations was 56.63 mrem, and 54.64 mrem for the control locations. The indicator annual average dose is believed to be influenced by location #36 (Figure 4) which has been consistently higher in dose than TLDs positioned closer to the plant (Figure 3).

Referring to Figure 9, the average quarterly dose for all indicator locations was 13.52 mrem, and 13.04 mrem for all control locations. Please refer to Appendix C, 2010 REMP Detailed Data Report for all TLD results. Prior to 1988, the TLD results were higher due to a change in the vendor laboratory services. A comprehensive explanation of this difference was provided in the 1988 Annual Environmental Operating Report.

Radiological Environmental Monitoring Page 40

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 9: Average Quarterly TLD Dose 25 20 E

15 10 a

5 0

Ye ar Oin dica tor EC on trol Conclusion Sediment samples continue to confirm cobalt-60 in the northwest drain impoundment. Additional monitoring is being performed to monitor this location. An environmental evaluation determined that there would be less impact upon the environment by leaving this material in place.

Atmospheric monitoring results were consistent with past results. The prevalent radionuclide in air was beryllium-7, which is naturally occurring.

Naturally occurring potassium-40 was detected in all terrestrial samples, as expected.

Finally, direct radiation measurements are consistent with past data.

Radiological Environmental Monitoring Page 41

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT INTER-LABORATORY CROSS-CHECK COMPARISON PROGRAM Introduction The purpose of the Inter-laboratory Cross-Check Comparison Program (ICCCP) is to provide an independent check on the vendor laboratory's analytical procedures. Samples with a known concentration of specific radionuclides are provided to the vendor laboratory. The vendor laboratory measures and reports the concentration of specified radionuclides. The known values are then compared to the vendor results. Results consistently outside established acceptance criteria indicate a need to check instruments or procedures. Regulatory Guide 4.15 specifically required that contractor laboratories that performed environmental measurement participate in the EPA's Environmental Radioactivity Laboratory Inter-Comparison Studies Program, or an equivalent program.

The EPA's program is no longer funded or offered. The reason that the EPA program was referenced in the regulatory guide is that the EPA standards were traceable to National Bureau of Standards (now known as National Institute Standard Technology). In response to this problem, Teledyne (PNPP vendor lab) incorporated a program offered by Environmental Resource Associates (ERA Company),

which covered the same analyses in the same matrix at the same frequency as the EPA program. The ERA Company has received NIST accreditation for its program, as an equivalent program. In addition to comparison cross checks performed with the ERA Company, the vendor laboratory routinely monitors the quality of their analyses by:

  • Analyzing "spiked" samples (samples with a specific quantity of radioactive material present in them) and
  • Participating in the Department of Energy's Mixed Analyte Performance Program (MAPEP).

Through 2004, Teledyne also participated in the Environmental Measurements Laboratory Quality Assessment Program (EML). This program was discontinued in 2005.

Conclusion Appendix A, 2010 Inter-Laboratory Cross-Check Comparison Program Results, includes results from both the above referenced programs and the ERA Company cross-check program.

1) Table A-i: All sample results obtained through participation in the environmental sample crosscheck program administered by Environmental Resource Associates (ERA) Interlaboratory Comparison Crosscheck Program were found to be within program control limits.
2) Table A-2: The Vendor Laboratory's Cross-Check program results for the testing of Thermoluminescent Dosimetry were found to be within the expected control limits.
3) Table A-3: Laboratory analysis results for In-House "Spike" samples were within their expected control limits.
4) Table A-4: Laboratory analysis results for In-House "Blank" samples were within their acceptance criteria.
5) Table A-5: Laboratory analysis results for all In-House "Duplicate" Samples were within the Vendor Laboratory's established acceptance criteria with the exception of sample SL-4884. The results of re-analysis of sample SL-4884 was found to be less than the sum of the errors and within the accepted criteria.

Radiological Environmental Monitoring Page 42

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT

6) Table A-6: All sample results obtained through participation in Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP) were found to be within program control limits.
7) Table A-7: All Vendor Laboratory sample results obtained through participation in Interlaboratory Comparison Crosscheck Program Environmental Resource Associates (ERA) laboratory were found to be within their control limits with the exception of soil samples STSO-1219 for (U-233/234), (U-238) and (Uranium). The initial results failed the acceptance criteria. The sample analyses were repeated using total dissolution and found to be within acceptance criteria.

Radiological Environmental Monitoring Page 43

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT LAND USE CENSUS Introduction Each year a Land Use Census, which is required by Section 5.2 of the PNPP ODCM, is conducted to identify the locations of the nearest milk animal, garden (of greater than 500 square feet), and residence in each of the meteorological sectors that is over land. Information gathered during the Land Use Census is used for off-site dose assessment and to update sampling locations for the Radiological Environmental Monitoring Program. The census is conducted by traveling all roads within a five-mile radius of the plant site, and recording and mapping the location of the nearest resident, milk animal and vegetable garden. The 2010 Land Use Census, which was conducted August 2 3rd and 24th provided the garden, residence and milk animal locations tabulated in Tables 19, 20 and 21 and depicted in Figure 10. Note that the W, WNW, NW, NNW, N, and NNE sectors extend over Lake Erie, and therefore, are not included in the survey.

Discussions and Results In general, the predominant land use within the census area continues to be rural/ agricultural. In recent years however, it has been noted that tracts of land once used for farming are now being developed as mini-industrial parks and residential housing tracts. This is reflected in the loss of available milking animals within a five mile radius of PNPP to support the Radiological Environmental Monitoring Program (REMP).

For 2010, the Land Use Survey was conducted with a new survey map produced by the Geographic Information System (GIS) Department, Lake County, Ohio. The new map provides roadway and residential information based on current county records and GPS technology. Changes to Tables 19, 20 and 21 and Figure 10 have been updated based on the 2010 survey map. These changes incorporated sector shifts of approximately 1/10 mile due to the increased accuracy of the new map.

Asterisks (*) identify the changes.

Table 19 identifies the nearest residences, by sector, to the PNPP. For 2010, there were seven (7) changes noted for the "nearest residence".

Table 19: Nearest Residence, By Sector SECTOR LOCATION ADDRESS MILES FROM X/Q VALUE, MAP LOCATOR PNPP (SEC/M3) NUMBER NE 4384 Lockwood 0.7 2.66E-06 1

  • ENE 4602 Lockwood 1.2 5.88E-07 2 E 2626 Antioch 1.1 6.77E-07 3
  • ESE 2836 Antioch 1.2 4.44E-07 4
  • SE 4495 North Ridge 1.2 3.89E-07 5
  • SSE 3119 Parnly 0.9 1.89E-06 6
  • S 3121 Center 0.9 2.25E-06 7
  • SSW 3850 Clark 0.9 1.11E-06 8
  • SW 2997 Perry Park 1.2 4.98E-07 9 WSW 3462 Parmly 1.1 8.67E-07 10 Radiological Environmental Monitoring Page 44

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 20 identifies the nearest milking animal by sector, to the PNPP. During the 2010 Land Use Census, no additional new milking animals were identified.

Table 20: Nearest Milk Animal, By Sector SECTOR LOCATION ADDRESS MILES FROM MAP LOCATOR PNPP NUMBER E 2591 McMacken Rd. 2.5 21 There were eight (8) changes for the nearest gardens identified during this year's census. Changes include the results of the new 2010 survey map, loss of the previous year's garden or addition of a new garden identified in this year's census.

Table 21 lists the nearest gardens occupying at least 500 square feet identified during the 2010 Land Use Census.

Table 21: Nearest Garden, By Sector SECTOR LOCATION ADDRESS MILES FROM D/Q VALUE, MAP LOCATOR PNPP (M-2L) NUMBER

  • NE 2330 Lakehurst 1.0 7.45E-09 11
  • ENE 4630 Lockwood 1.2 4.11E-09 12 E 2626 Antioch 1.1 5.29E-09 3
  • ESE 2836 Antioch 1.2 3.41E-09 4
  • SE 4671 North Ridge 1.3 1.01E-09 15
  • SSE 4225 Red Mill Valley 1.1 3.48E-09 16
  • S 3121 Center Rd. 0.9 1.31E-08 7
  • SW 3032 Perry Park 1.4 1.72E-09 13 WSW 2975 Perry Park 1.3 2.31E-09 14 Radiological Environmental Monitoring Page 45

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 10: Land Use Census Map Garden A% Residencef Milking Animal 5 Radiological Environmental Monitoring Page 46

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CLAM/MUSSEL MONITORING INTRODUCTION Sampling for macro-invertebrates (clams and mussels) has been conducted in Lake Erie in the vicinity of PNPP, since 1971. The clam/mussel program currently focuses on two species: Corbicula fluminea (Asiatic clam) and Dreissenapolymorpha (zebra mussel).

CORBICULA PROGRAM Monitoring specifically for Corbicula was initiated in response to a NRC bulletin and concerns of the Atomic Safety and Licensing Board. The 2010 monitoring was done as part of the Environmental Protection Plan (Operating License, Appendix B). The program consists of visually inspecting the raw water systems, when they are opened for maintenance. The purpose of this program is to detect Corbicula, should it appear at PNPP.

No Corbicula have been found in any sample collected from PNPP. Two Corbicula were found in a sample collected from the Eastlake plant in June, 1987. No Corbicula have been found in any other sample collected since that time. A more detailed program history can be found in the 1986 and 1987 PNPP Annual Environmental Operating Reports.

Monitoring In 2010, samples were collected from the Service Water (SW) and Emergency Service Water (ESW) pump houses at PNPP and examined for shells and fragments. Samples were either collected by hand scoop or scraper. In addition to sample collections, plant components that use raw water are inspected when opened for maintenance or repair. Sample collection/inspection dates are listed in Table 22.

Table 22: 2010 Corbicula Monitoring DATE SAMPLE LOCATION 2/26/10 Aux 599 Fire Protection Piping 7/12/10 Main Turbine Lube Oil cooler "B" 8/13/10 Main Turbine Lube Oil cooler "A" 8/20/10 Main Turbine Lube Oil cooler "B" 8/25/10 Service Water Traveling Screen "A" 9/12/10 HPCS Diesel Generator Jacket Water Heat Exchanger Conclusions The sample collected in June, 1987, was the only indication of Corbicula in the vicinity of PNPP.

Although the presence of Corbicula was detected at the Eastlake Power Plant, it has not been demonstrated that their presence has created any operational problems there, or at PNPP. As in the past, the 2010 monitoring program did not identify Corbicula in any sample collected.

Clam/Mussel Monitoring Page 47

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT DREISSENA PROGRAM Dreissena or Zebra mussels were first discovered at PNPP in September, 1988. The initial collection of 19 mussels was made as part of the Corbicula monitoring program. The Dreissena monitoring program began in 1989, with monitoring and testing. The current control program was designed and implemented in 1990.

Monitoring In addition to visually inspecting the plant's raw water systems when they are opened for maintenance or repair, monitoring methods include the use of commercial divers and side-stream monitors.

Commercial divers monitor mussel infestation during the inspection of forebays, basins, and the intake and discharge structures. Divers have also been used to take underwater videotapes of the water basins and intake tunnel. Side-stream monitors are flow-through containers that receive water diverted from plant systems and are set up at two in-plant locations during the mussel season. The side-stream monitors are fitted with slides and inspected for veliger settlement and growth of adult mussels.

Treatment Chemicals used for mussel control in 2010 included chlorine and a commercial molluscicide. The chlorine is intermittently injected into the plant service water, emergency service water, and circulating water systems by metering sodium hypochlorite into each system's influent. Sodium bisulfite is added at the plant discharge structure for dechlorination prior to return into Lake Erie.

The use of a commercial molluscicide has been approved by the Ohio Environmental Protection Agency (OEPA). The chemical selected for use at the PNPP in 2010 was alkyl-dimethyl-benzyl-ammonium chloride. Treatment was applied once in 2010, on August 18. The active ingredients were detoxified by adsorption using bentonite clay, prior to discharge into Lake Erie.

Results The effectiveness of the intermittent chlorination treatment has been determined in several ways.

First, visual inspections of raw water system components are conducted when systems are open during maintenance or repair. In addition, settlement monitors were inspected for new settlement. No live settlement has been found in any plant component to date.

The effectiveness of the application of the commercial molluscicide was measured by observing mortality of mussels placed in a flow-through container placed in plant service water and subjected to the chemical treatment. The observed mortality rate utilizing the flow-through container for 2010 was 98.4%.

To date, PNPP has had no significant problems related to zebra mussels.

Conclusions Perry Nuclear Power Plant has taken the approach that the best method for avoiding problems with zebra mussels is preventive treatment of plant water systems. The current program of monitoring and chemical treatment will be continued to minimize the possibility that PNPP will experience future problems due to zebra mussels.

Clam/Mussel Monitoring Page 48

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT HERBICIDE APPLICATIONS Herbicides are used sparingly on the PNPP site. A request must be made to, and approved by the PNPP Chemistry Unit prior to spraying to ensure that only approved chemicals are used, and only in approved areas.

In 2010, three (3) general and one (1) specific herbicide requests were initiated for chemical applications. Each application was in compliance with the Ohio Environmental Protection Agency's rules and regulations. There were no adverse environmental impacts observed during weekly site environmental inspections as a result of these applications. The herbicides approved for use in the Owner-Controlled Area are Round-Up, Round-Up Promax, Spyder, Polaris, Tempo Ultra, Prosecutor Pro and a mixture of Garlon4/stalker/basil oil. For each application, the type of weed to be treated dictated the herbicide and concentration to be used. Table 23 provides detailed documentation for each application in 2010. The quantity represents the amount of herbicide applied, prior to any dilution.

Table 23: 2010 Herbicide Applications DATE APPLIED LOCATION AMOUNT CHEMICAL NAME 4/5/10 Parmly road fencing 60 oz Round-up 4/27/10 Admin. Building, along main road and Parmly road. 30 oz Round-up 4/27/10 Transmission Yard 5.4 gal. Polaris 4/27/10 Transmission Yard 58 oz. Spyder 4/28/10 Admin. and Training buildings 30 oz Round-up 4/29/10 landscape beds outside protected area 4 oz Round-up 6/4/10 Security towers, booths, gravel areas and perifeld zones 3.5 oz. Tempo Ultra 6/4/10 E- field perimeter fencing 4 gal. Round-up 6/5/10 E- field perimeter fencing 4 gal. Round-up 6/21/10 Owner Controlled Area (OCA) north and northwest 5 gal. Round-up Promax 6/29/10 Environmental Air Samplers #4 and #35 1.5 gal. garlon 4/stalker/basil oil mix 7/29/10 West OCA fencing/environmental pathways 15 gal. Mojave 70EG/Prosecutor Pro 8/5/10 East OCA fencing/environmental pathways 15 gal. Mojave 70EG/Prosecutor Pro 8/13/10 Primary Access Facility (PAF), rooftops booths, towers 4 oz. Tempo Ultra 8/18/10 Northwest Drain Impoundment pathways 30 gal. Mojave 70EG/Prosecutor Pro 8/19/10 Protected area, graveled area on eastside plant 20 gal. Mojave 70EG/Prosecutor Pro 8/20/10 Hazardous Waste Storage facility and perimeter fencing 7.5 gal. Mojave 70EG/Prosecutor Pro 8/20/10 Empty Barrel Storage Area and perimeter fencing 0.5 gal. Mojave 70EG/Prosecutor Pro 9/23/10 PAF, vehicle trap, perifield zones 2.5 gms Tempo Ultra 10/11/10 Plant access road from Parmnly road to Admin. building 120 oz. Round-up Special Reports Page 49

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT SPECIAL REPORTS NON-COMPLIANCES NPDES Permit The National Pollutant Discharge Elimination System (NPDES) permit is issued by the Ohio Environmental Protection Agency (OEPA). It establishes monitoring requirements and limits for discharges from the PNPP. It also specifies the locations from which the plant is allowed to discharge.

There were no NPDES non-compliance issues identified in 2010.

Environmental Protection Plan The Environmental Protection Plan (EPP), which is Appendix B of the PNPP Operating License, requires a non-radiological environmental monitoring and reporting program be established at the PNPP.

One special report was submitted for 2010:

0 On October 28, 2010 approximately 345 gallons of sodium hypochlorite (bleach) was discovered to have leaked to the ground through an underground piping break. The storage tank was immediately isolated and the leak stopped. Periodic sampling of groundwater monitoring wells has indicated the release has not migrated. The storage tank remains isolated during excavation and repair of the underground piping. All areas where leakage was discovered were neutralized by station personnel. All proper notifications to regulatory agencies were made as required.

UNREVIEWED ENVIRONMENTAL QUESTIONS All proposed changes to the PNPP design or operation, as well as tests or experiments, must be evaluated for potential environmental impacts in accordance with the EPP and administrative quality assurance procedures. In 2010 there were no proposed changes to the facility or programs that if performed, could have resulted in an adverse environmental impact. Therefore, there were no unreviewed environmental questions identified.

Special Reports Page 50

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX A 2010 INTER-LABORATORY CROSS CHECK COMPARISON PROGRAM RESULTS

A TI Environmental, Inc.

-g-rýuM idwest Laboratory 700 Landwehr Road

  • Northbrook, IL 60062-23 10 phone (847) 564-0700
  • fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2010 through December, 2010

Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory haS participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors.

Complete analytical data for duplicate analyses is available upon request.

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.

Out-of-limit results are explained directly below the result.

Al

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter

> 50 pCi/liter or kg 10% of known value Strontium -90b 2 to 30 pCi/liter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potassium-40 > 0.1 g/liter or kg 5% of known value Gross alpha < 20 pCi/liter 5.0 pCi/liter

> 20 pCi/liter 25% of known value Gross beta -<100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium < 4,000 pCi/liter +/-la =

169.85 x (known)0'0933

> 4,000 pCi/liter 10% of known value Radium-226,-228 > 0.1 pCi/liter 15% of known value Plutonium > 0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, < 55 pCi/liter 6 pCi/liter Iodine-1 2 9 b > 55 pCi/liter 10% of known value Uranium-238, < 35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value b

Other Analyses 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 205 04/05/10 Sr-89 63.0 + 5.7 60.4 48.6 - 68.2 Pass STW-1 205 04/05/10 Sr-90 37.4 + 2.4 41.3 30.4 - 47.4 Pass STW-1206 04/05/10 Ba-133 63.6 + 3.3 65.9 54.9 - 72.5 Pass STW-1206 04/05/10 Co-60 83.3 + 2.9 84.5 76.0 - 95.3 Pass STW-1206 04/05/10 Cs-134 71.0 + 3.4 71.6 58.4 - 78.8 Pass STW-1206 04/05/10 Cs-137 145.5 + 5.1 146.0 131.0 - 163.0 Pass STW-1206 04/05/10 Zn-65 194.9 + 7.8 186.0 167.0 - 219.0 Pass STW-1207 04/05/10 Gr. Alpha 26.5 +/- 1.7 32.9 16.9 -42.6 Pass STW-1207 04/05/10 Gr. Beta 34.5 +/- 1.6 37.5 24.7 - 45.0 Pass STW-1208 04/05/10 1-131 22.7 +/- 0.8 26.4 21.9 -31.1 Pass STW-1209 04/05/10 Ra-226 15.2 + 0.7 14.6 10.9 -16.8 Pass STW-1209 04/05/10 Ra-228 15.6 +/- 1.8 15.1 10.1 -18.3 Pass STW-1209 04/05/10 Uranium 59.5 + 0.7 62.3 50.7 -69.1 Pass STW-1210 04/05/10 H-3 12955 + 332 12400.0 10800 -13600 Pass STW-1224 10/04/10 Sr-89 65.3 +/- 5.7 68.5 55.8 - 76.7 Pass STW-1224 10/04/10 Sr-90 39.9 +/- 2.3 43.0 31.7 - 49.3 Pass STW-1225 10/04/10 Ba-133 67.2 +/- 4.3 68.9 57.5 - 75.8 Pass STW-1225 10/04/10 Co-60 53.2 + 3.3 53.4 48.1 -61.3 Pass STW-1225 10/04/10 Cs-134 47.3 + 5.1 43.2 34.5 - 47.5 Pass STW-1225 10/04/10 Cs-137 118.0 + 5.9 123.0 111.0 - 138.0 Pass STW-1225 10/04/10 Zn-65 107.0 + 8.7 102.0 91.8 -122.0 Pass STW-1226 10/04/10 Gr. Alpha 30.7 +/- 2.9 42.3 21.9 -53.7 Pass STW-1226 10/04/10 Gr. Beta 32.7 +/- 0.8 36.6 24.0 - 44.2 Pass STW-1227 10/04/10 1-131 28.6 +/- 1.1 27.5 22.9 - 32.3 Pass STW-1228 10/04/10 Ra-226 11.8 +/--0.6 11.4 8.5 - 13.2 Pass STW-1228 10/04/10 Ra-228 12.0 +/- 1.8 9.9 6.4 - 12.3 Pass STW-1228 10/04/10 Uranium 34.8 +/- 0.4 36.8 29.8 -41.0 Pass STW-1229 10/04/10 H-3 13682 +/-352 12900.0 11200 -14200 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

Al-1

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO 4 : Dy Cards).

mR Lab Code Date Known Lab Result Control Description Value +/- 2 sigma Limits Acceptance Environmental, Inc.

2010-1 6/8/2010 30 cm. 75.07 90.78 +/- 3.60 52.55 - 97.59 Pass 2010-1 6/8/2010 40 cm. 42.23 50.88 +/- 3.59 29.56 - 54.90 Pass 2010-1 6/8/2010 50 cm. 27.03 32.12 +/- 1.90 18.92 -35.14 Pass 2010-1 6/8/2010 60 cm. 18.77 21.80 +/- 0.90 13.14 -24.40 Pass 2010-1 6/8/2010 70 cm. 13.79 15.38 +/- 1.39 9.65 - 17.93 Pass 2010-1 6/8/2010 75 cm. 12.01 11.30 +/- 1.07 8.41 - 15.61 Pass 2010-1 6/8/2010 80 cm. 10.56 10.90 +/- 0.61 7.39 - 13.73 Pass 2010-1 6/8/2010 90 cm. 8.34 7.84 +/- 0.83 5.84 - 10.84 Pass 2010-1 6/8/2010 100 cm. 6.76 6.61 +/- 0.52 4.73 - 8.79 Pass 2010-1 6/8/2010 110 cm. 5.58 4.29 +/- 0.55 3.91 - 7.25 Pass 2010-1 6/8/2010 120 cm. 4.69 3.64 +/- 0.33 3.28 -6.10 Pass 2010-1 6/8/2010 150 cm. 3.00 2.82 +/- 0.84 2.10 -3.90 Pass 2010-1 6/8/2010 180 cm. 2.09 1.55 +/- 0.23 1.46 -2.72 Pass Environmental, Inc.

2010-2 12/13/2010 100 cm. 4.94 4.65 +/- 0.57 3.46 - 6.42 Pass 2010-2 12/13/2010 110 cm. 4.09 3.50 +/- 0.74 2.86 - 5.32 Pass 2010-2 12/13/2010 120 cm. 3.43 2.68 +/- 0.36 2.40 -4.46 Pass 2010-2 12/13/2010 150 cm. 2.2 1.75 +/- 0.42 1.54 -2.86 Pass 2010-2 12/13/2010 180 cm. 1.53 1.32 +/- 0.52 1.07 -1.99 Pass 2010-2 12/13/2010 40 cm. 30.89 38.56 +/- 2.11 21.62 -40.16 Pass 2010-2 12/13/2010 50 cm. 19.77 23.35 +/- 1.82 13.84 - 25.70 Pass 2010-2 12/13/2010 60 cm. 13.73 14.53 +/- 1.24 9.61 - 17.85 Pass 2010-2 12/13/2010 60 cm. 13.73 15.84 +/- 1.53 9.61 - 17.85 Pass 2010-2 12/13/2010 80 cm. 7.72 8.33 +/- 0.74 5.40 -10.04 Pass 2010-2 12/13/2010 90 cm. 6.1 5.93 +/- 0.73 4.27 - 7.93 Pass A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-12648 1/20/2010 Ra-228 40.04 +/- 2.99 40.54 28.38 - 52.70 Pass SPW-279 1/27/2010 U-238 4.52 +/- 0.22 4.17 0.00 -16.17 Pass SPW-391 2/4/2010 Ni-63 179.70 +/- 2.96 209.62 146.73 - 272.51 Pass W-21210 2/12/2010 Ra-226 16.05 +/- 0.39 16.77 11.74 -21.80 Pass W-21710 2/17/2010 Gr. Alpha 17.54 +/- 0.37 20.00 10.00'- 30.00 Pass W-21710 2/17/2010 Gr. Beta 42.47 +/- 0.39 45.20 35.20 - 55.20 Pass SPAP-669 2/25/2010 Gr. Beta 45.78 +/- 0.11 49.24 29.54 - 68.94 Pass SPAP-671 2/25/2010 Cs-134 10.56 +/- 3.15 10.38 0.38 - 20.38 Pass SPAP-671 2/25/2010 Cs-137 105.36 +/- 3.15 109.20 98.28 - 120.12 Pass SPMI-674 2/25/2010 Co-60 67.38 +/- 5.65 68.79 58.79 - 78.79 Pass SPMI-674 2/25/2010 Cs-134 60.61 +/- 6.28 51.91 41.91 -61.91 Pass SPMI-674 2/25/2010 Cs-1 37 173.80 +/- 10.30 163.80 147.42 -180.18 Pass SPW-676 2/25/2010 Co-60 66.13 +/- 5.22 68.79 58.79 - 78.79 Pass SPW-676 2/25/2010 Cs-1 34 51.54 +/- 5.97 51.91 41.91 -61.91 Pass SPW-676 2/25/2010 Cs-1 37 179.30 +/- 9.95 163.80 147.42 - 180.18 Pass SPW-678 2/25/2010 H-3 59213.70 +/- 709.90 60407.70 48326.16 - 72489.24 Pass SPF-680 2/25/2010 Cs-134 402.56 +/- 22.40 415.00 373.50 - 456.50 Pass SPF-680 2/25/2010 Cs-137 2267.90 +/- 75.60 2180.00 1962.00 -2398.00 Pass SPW-682 2/25/2010 Tc-99 29.70 +/- 1.51 32.34 20.34 - 44.34 Pass SPW-2871 4/5/2010 Ra-228 33.91 +/- 2.85 36.80 25.76 - 47.84 Pass W-40510 4/5/2010 Gr. Alpha 20.65 +/- 0.42 20.00 10.00 - 30.00 Pass W-40510 4/5/2010 Gr. Beta 44.72 +/- 0.40 45.20 35.20 - 55.20 Pass SPW-2083 4/28/2010 U-238 4.20 +/- 0.32 4.17 0.00 -16.17 Pass W-51310 5/13/2010 Ra-226 17.04 +/- 0.50 16.77 11.74 -21.80 Pass SPW-3181 6/17/2010 Tc-99 29.87 +/- 1.09 32.34 20.34 - 44.34 Pass SPW-3272 6/25/2010 H-3 5489.00 +/- 224.00 5928.00 4742.40 -7113.60 Pass SPW-3278 6/25/2010 Fe-55 17054.00 +/- 348.00 19614.00 15691.20 -23536.80 Pass SPW-3280 6/25/2010 C-14 3410.60 +/- 9.75 4738.00 2842.80 - 6633.20 Pass SPAP-3270 6/28/2010 Cs-134 12.24 +/- 3.13 10.38 0.38 - 20.38 Pass SPAP-3270 6/28/2010 Cs-137 103.92 +/- 7.14 109.20 98.28 - 120.12 Pass SPW-3274 6/28/2010 Co-60 67.48 +/- 5.53 65.84 55.84 - 75.84 Pass SPW-3274 6/28/2010 Cs-134 49.55 +/- 6.11 46.38 36.38 - 56.38 Pass SPW-3274 6/28/2010 Cs-137 58.85 +/- 6.54 54.17 44.17 -64.17 Pass SPW-3274 6/28/2010 Sr-90 41.59 +/- 1.83 42.72 34.18 -51.26 Pass SPMI-3276 6/28/2010 Co-60 66.80 +/- 5.25 65.84 55.84 - 75.84 Pass SPMI-3276 6/28/2010 Cs-1 34 48.20 +/- 3.88 46.38 36.38 - 56.38 Pass SPMI-3276 6/28/2010 Cs-137 62.46 +/- 6.33 54.17 44.17 -64.17 Pass SPMI-3276 6/28/2010 Sr-90 43.32 +/- 1.63 42.72 34.18 -51.26 Pass A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 Activity Limitsc Acceptance SPW-5081 9/9/2010 Tc-99 30.22 +/- 1.06 32.34 20.34 - 44.34 Pass W-90910 9/9/2010 Gr. Alpha 20.95 +/- 0.43 20.00 10.00 - 30.00 Pass W-90910 9/9/2010 Gr. Beta 45.20 +/- 0.41 45.20 35.20 - 55.20 Pass W-91010 9/10/2010 Ra-226 17.48 +/- 0.50 16.77 11.74 -21.80 Pass SPW-2874 9/23/2010 Ra-228 34.60 +/- 2.68 36.80 25.76 - 47.84 Pass XWW-5302 10/6/2010 Ba-133 154.13 +/- 8.90 155.21 139.69 - 170.73 Pass XWW-5302 10/6/2010 Co-60 24.65 +/- 4.11 23,28 13.28 -33.28 Pass XWW-5302 10/6/2010 Cs-134 14.03 +/- 3.87 13.95 3.95 - 23.95 Pass XWW-5302 10/6/2010 Cs-137 61.16 +/- 6.08 59.22 49.22 - 69.22 Pass SPW-6035 10/21/2010 U-238 4.52 +/- 0.20 4.17 0.00 -16.17 Pass W-120110 12/1/2010 Gr. Alpha 20.27 +/- 0.41 20.00 10.00 - 30.00 Pass W-120110 12/1/2010 Gr. Beta 46.75 +/- 0.41 45.20 35.20 - 55.20 Pass W-121610 12/16/2010 Ra-226 17.99 +/- 0.43 16.77 11.74 -21.80 Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m 3 ), and solid samples (pCi/g).

b Laboratory codes as follows: W (water), Ml (milk), AP (air filter), SO (soil), VE (vegetation),

CH (charcoal canister), F (fish).

Results are based on single determinations.

d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2G.

NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.

A3-2

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis6 Laboratory results (4.66y) Acceptance Type LLD Activityc Criteria (4.66 ()

SPW-12658 Water 1/20/2010 Ra-228 0.79 0.61 +/- 0.44 2 SPW-280 Water 1/27/2010 U-238 0.18 0.07 +/- 0.13 1 SPW-392 Water 2/4/2010 Ni-63 15.90 -11.80 +/- 9.40 20 W-21210 Water 2/12/2010 Ra-226 0.03 0.06 +/- 0.02 1 W-21710 Water 2/17/2010 Gr. Alpha 0.41 0.09 +/- 0.30 3 W-21710 Water 2/17/2010 Gr. Beta 0.73 0.23 +/- 0.52 3.2 SPAP-668 Air Filter 2/25/2010 Gr. Beta 0.11 0.008 +/- 0.002 3.2 SPAP-670 Air Filter 2/25/2010 Cs-134 1.87 100 SPAP-670 Air Filter 2/25/2010 Cs-137 2.31 100 SPMI-672 Milk 2/25/2010 Cs-137 3.52 10 SPMI-672 Milk 2/25/2010 1-131(G) 6.09 20 SPW-675 Water 2/25/2010 Co-60 1.55 10 SPW-675 Water 2/25/2010 Cs-137 2.69 10 SPW-675 Water 2/25/2010 1-131(G) 5.68 20 SPF-679 Fish 2/25/2010 Cs-134 10.94 100 SPF-679 Fish 2/25/2010 Cs-137 18.37 100 SPW-681 Water 2/25/2010 Tc-99 16.11 -10.75 +/- 9.53 10 SPW-2881 Water 4/5/2010 Ra-228 0.89 0.22 +/- 0.44 2 W-40510 Water 4/5/2010 Gr. Alpha 0.40 -0.20 +/- 0.26 1 W-40510 Water 4/5/2010 Gr. Beta 0.75 -0.09 +/- 0.52 3.2 SPW-2084 Water 4/28/2010 U-238 0.14 0.03 +/- 0.10 1 W-51310 Water 5/13/2010 Ra-226 0.03 0.06 +/- 0.02 1 SPW-3271 Water 6/25/2010 H-3 151.60 -58.10 +/- 71.90 200 SPW-3278 Water 6/25/2010 Fe-55 634.50 256.80 +/- 396.40 1000 SPW-3279 water 6/25/2010 C-14 8.57 -1.84 +/- 5.18 200 SPAP-3269 Air Filter 6/28/2010 Cs-134 1.71 100 SPAP-3269 Air Filter 6/28/2010 Cs-1 37 2.42 100 SPW-3273 Water 6/28/2010 Co-60 1.64 10 SPW-3273 Water 6/28/2010 Cs-134 3.89 10 SPW-3273 Water 6/28/2010 Cs-137 4.29 10 SPW-3273 water 6/25/2010 Sr-90 0.50 -0.04 +/- 0.22 1 SPMI-3275 Milk 6/28/2010 Cs-1 34 3.33 10 SPMI-3275 Milk 6/28/2010 Cs-1 37 3.82 10 SPMI-3275 Milk 6/28/2010 1-131(G) 3.71 20 SPMI-3275 Milk 6/28/2010 Sr-90 0.58 0.81 +/- 0.36 1 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66a*) Acceptance Type LLD Activityc Criteria (4.66 o)

SPW-5080 Water 9/9/2010 Tc-99 2.15 -0.71 +/- 1.29 10 W-9091 0 Water 9/9/2010 Gr. Alpha 0.39 0.10 +/- 0.28 1 W-9091 0 Water 9/9/2010 Gr. Beta 0.78 -0.09 +/- 0.55 3.2 W-91010 Water 9/10/2010 Ra-226 0.04 0.07 +/- 0.03 1 SPW-2884 Water 9/23/2010 Ra-228 0.71 1.14 +/- 0.46 2 SPW-6036 Water 10/21/2010 U-238 0.11 0.07 +/- 0.10 1 W-120110 Water 12/1/2010 Gr. Alpha 0.43 -0.05 +/- 0.29 1 W-120110 Water 12/1/2010 Gr. Beta 0.75 -0.08 +/- 0.53 3.2 W-121610 Water 12/16/2010 Ra-226 0.03 0.04 +/- 0.02 1 BKW-120610 water 12/6/2010 Ba-133 5.66 10 BKW-120610 water 12/6/2010 Co-60 4.49 10 BKW-120610 water 12/6/2010 Cs-134 4.41 10 BKW-120610 water 12/6/2010 Cs-137 5.33 10 W-121610 Water 12/16/2010 Ra-226 0.03 0.04 +/- 0.02 1 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

b 1-131(G); iodine-131 as analyzed by gamma spectroscopy.

Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 1/4/2010 Gr. Beta 10.96 +/- 0.27 11.30 + 0.28 11.13 +/- 0.19 Pass CF-20, 21 1/4/2010 K-40 8.88 +/- 0.48 8.27 + 0.78 8.58 +/- 0.46 Pass CF-20, 21 1/4/2010 Sr-90 0.02 +/- 0.01 0.02 + 0.01 0.02 +/- 0.00 Pass CF-41, 42 1/4/2010 Be-7 0.45 +/- 0.11 0.41 + 0.14 0.43 +/- 0.09 Pass CF-41, 42 1/4/2010 Gr. Beta 3.26 +/- 0.10 3.33 + 0.11 3.30 +/- 0.07 Pass CF-41, 42 1/4/2010 K-40 2.85 +/- 0.36 3.04 + 0.22 2.95 +/- 0.21 Pass MI-111, 112 1/12/2010 K-40 1276.00 +/- 98.96 1334.80 + 105.00 1305.40 +/- 72.14 Pass DW-10010, 10011 1/13/2010 Ra-226 0.48 +/- 0.10 0.43 + 0.10 0.46 +/- 0.07 Pass DW-10010, 10011 1/13/2010 Ra-226 1.59 +/- 0.61 1.13 + 0.47 1.36 +/- 0.39 Pass WW-215, 216 1/18/2010 H-3 211.16 +/- 87.57 291.90 + 91.31 251.53 +/- 63.26 Pass DW-10022,10023 1/21/2010 Ra-226 8.57 +/- 0.91 10.20 + 1.08 9.39 +/- 0.71 Pass DW-10022,10023 1/21/2010 Ra-228 5.68 +/- 1.36 3.59 + 1.17 4.64 +/- 0.90 Pass WW-424,425 1/28/2010 H-3 422.30 +/- 95.90 484.20 + 98.50 453.25 +/- 68.74 Pass DW-10034, 10035 1/28/2010 Ra-226 0.93 +/- 0.13 0.90 + 0.11 0.92 +/- 0.09 Pass DW-10034,10035 1/28/2010 Ra-228 1.16 +/- 0.62 1.29 + 0.62 1.23 +/- 0.44 Pass SW-382, 383 2/1/2010 Gr. Beta 2.22 +/- 0.68 1.18 + 0.71 1.70 +/- 0.49 Pass DW-1 0046, 10047 2/2/2010 Ra-226 6.11 +/- 0.91 7.88 +/- 1.17 7.00 +/- 0.74 Pass DW-1 0046, 10047 2/2/2010 Ra-228 5.84 +/-+1.11 6.13 +/- 1.14 5.99 +/- 0.80 Pass WW-693, 694 2/23/2010 H-3 1458.00 + 131.00 1531.00 + 133.00 1494.50 +/- 93.34 Pass SW-782,783 3/1/2010 Gr. Beta 1.05 + 0.42 1.60 + 0.43 1.33 +/- 0.30 Pass SW-782, 783 3/1/2010 K-40 1.50 +/-+0.15 1.52 + 0.15 1.51 +/- 0.11 Pass MI-946, 947 3/9/2010 K-40 1485.00 + 109.30 1347.40 + 108.30 1416.20 +/- 76.93 Pass W-1035,1036 3/17/2010 Ra-226 11.78 +/- 1.51 9.76 +/- 1.26 10.77 +/- 0.98 Pass W-1035,1036 3/17/2010 Ra-228 5.31 +/- 2.42 8.45 + 2.78 6.88 +/- 1.84 Pass SW-1285, 1286 3/17/2010 H-3 377.60 +/- 104.50 282.70 + 100.70 330.15 +/- 72.56 Pass W-1103,1104 3/18/2010 H-3 12690 +/- 333 12679 + 333 12685 +/-235 Pass WW-1193, 1194 3/18/2010 H-3 227.38 +/- 95.19 251.81 + 96.15 239.60 +/- 67.65 Pass LW-1909,1910 3/24/2010 H-3 1529.40 +/- 144.60 1404.40 + 140.80 1466.90 +/- 100.91 Pass LW-1 909, 1910 3/25/2010 H-3 2.40 +/- 0.97 1.99 + 1.03 2.20 +/- 0.71 Pass DW-10068, 10069 3/25/2010 Gr. Alpha 1.08 +/- 1.02 1.35 + 1.05 1.22 +/- 0.73 Pass DW-10070, 10071 3/29/2010 Ra-226 1.58 +/- 0.17 1.69 + 0.16 1.64 +/- 0.12 Pass DW-10070, 10071 3/29/2010 Ra-228 1.16 +/- 0.47 1.34 + 0.49 1.25 +/- 0.34 Pass AP-1729, 1730 3/30/2010 Be-7 0.08 +/- 0.01 0.08 + 0.01 0.08 +/- 0.01 Pass AP-1782, 1783 3/30/2010 Be-7 0.08 +/- 0.01 0.09 + 0.01 0.09 +/- 0.01 Pass E-1392, 1393 4/1/2010 Gr. Beta 1.59 +/- 0.07 1.66 + 0.08 1.63 +/- 0.05 Pass E-1392, 1393 4/1/2010 K-40 902.30 +/- 179.00 1076.70 + 202.90 989.50 +/- 135.29 Pass WW-1422,1423 4/1/2010 Gr. Beta 22.23 +/- 1.58 19.42 + 1.40 20.83 +/- 1.06 Pass SW-1464,1465 4/1/2010 H-3 262.06 +/- 98.96 233.18 + 97.75 247.62 +/- 69.55 Pass XW-1666,1667 4/1/2010 Fe-55 7.05 +/- 0.71 7.25 + 0.74 7.15 +/- 0.51 Pass SG-1532, 1533 4/6/2010 Ac-228 19.45 +/- 1.14 20.07 + 1.19 19.76 +/- 0.82 Pass SG-1532,1533 4/6/2010 Pb-214 12.66 +/- 0.52 13.32 + 0.54 12.99 +/- 0.38 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SG-1506, 1507 .4/7/2010 Ac-228 1.28 +/- 0.15 1.15 +/- 0.14 1.22 +/- 0.10 Pass SG-1506, 1507 4/7/2010 Pb-214 1.24 +/- 0.10 1.22 +/- 0.09 1.23 +/- 0.07 Pass SW-1645, 1646 4/14/2010 H-3 312.00 +/- 100.00 352.00 +/- 102.00 332.00 +/- 71.42 Pass DW-10095, 10096 4/14/2010 Ra-226 4.87 +/- 0.53 5.57 +/- 0.61 5.22 +/- 0.40 Pass DW-10095, 10096 4/14/2010 Ra-228 2.49 +/- 0.56 2.76 +/- 0.60 2.63 +/- 0.41 Pass W-2013, 2014 4/16/2010 Gr. Alpha 33.45 +/- 3.98 39.11 +/- 4.54 36.28 +/- 3.02 Pass W-2013, 2014 4/16/2010 Gr. Beta 14.83 +/- 0.96 16.07 +/- 0.96 15.45 +/- 0.68 Pass WW-2431, 2432 4/19/2010 H-3 400.40 +/- 98.10 377.70 +/- 97.10 389.05 +/- 69.01 Pass SO-2037, 2038 4/22/2010 K-40 2.89 +/- 0.40 2.89 +/- 0.51 2.89 +/- 0.32 Pass W-2325, 2326 4/26/2010 H-3 399.00 +/- 92.00 429.00 +/- 94.00 414.00 +/- 65.76 Pass AP-2149, 2150 4/29/2010 Be-7 0.14 +/- 0.08 0.26 +/- 0.12 0.20 +/- 0.07 Pass LW-2191, 2192 4/29/2010 Gr. Beta 1.16 +/- 0.56 0.79 +/- 0.52 0.97 +/- 0.38 Pass G-2170, 2171 5/3/2010 Be-7 0.91 +/- 0.32 0.86 +/- 0.26 0.89 +/- 0.21 Pass G-2170, 2171 5/3/2010 Gr. Beta 8.73 +/- 0.22 9.01 +/- 0.23 8.87 +/- 0.16 Pass G-2170, 2171 5/3/2010 K-40 7.24 +/- 0.44 7.48 +/- 0.78 7.36 +/- 0.45 Pass SWT-2282, 2283 5/4/2010 Gr. Beta 0.73 +/- 0.52 1.58 +/- 0.57 1.16 +/- 0.39 Pass WW-2233, 2234 5/5/2010 Gr. Alpha 1.56 +/- 1.47 2.27 +/- 1.65 1.92 +/- 1.10 Pass WW-2233, 2234 5/5/2010 Gr. Beta 2.33 +/- 1.14 4.08 +/- 1.24 3.21 +/- 0.84 Pass TD-2410, 2411 5/10/2010 H-3 431.92 +/- 96.50 403.05 +/- 95.26 417.48 +/- 67.80 Pass SG-2347, 2348 5/13/2010 Ra-226 37.34 +/- 0.42 37.91 +/- 0.36 37.63 +/- 0.28 Pass F-2463, 2464 5/17/2010 K-40 2.69 +/- 0.56 2.65 +/- 0.38 2.67 +/- 0.34 Pass XW-2834, 2835 5/20/2010 H-3 209.53 +/- 83.34 263.11 +/- 85.95 236.32 +/- 59.86 Pass WW-2597, 2598 5/25/2010 H-3 288.10 +/- 98.20 155.80 +/- 93.40 221.95 +/- 67.76 Pass MI-2639, 2640 5/25/2010 K-40 1428.80 +/- 110.60 1408.60 +/- 107.40 1418.70 +/- 77.08 Pass SL-2771, 2772 6/1/2010 Gr. Beta 5.33 +/- 0.18 5.30 +/- 0.18 5.32 +/- 0.13 Pass SL-2771, 2772 6/1/2010 K-40 4.67 +/- 0.46 4.88 +/- 0.46 4.78 +/- 0.33 Pass SW-2879, 2880 6/1/2010 H-3 335.60 +/- 92.60 356.40 +/- 93.60 346.00 +/- 65.83 Pass SG-2904, 2905 6/7/2010 Gamma 5.20 +/- 0.20 5.50 +/- 0.10 5.35 +/- 0.11 Pass SO-3039, 3040 6/8/2010 Be-7 0.12 +/- 0.03 0.13 +/- 0.08 0.13 +/- 0.04 Pass SO-3039, 3040 6/8/2010 Cs-137 0.01 +/- 0.00 0.01 +/- 0.00 0.01 +/- 0.00 Pass SO-3039, 3040 6/8/2010 Gr. Beta 22.80 +/- 2.05 23.84 +/- 2.44 23.32 +/- 1.59 Pass SO-3039, 3040 6/8/2010 K-40 11.30 +/- 1.20 11.70 +/- 1.20 11.50 +/- 0.85 Pass SO-3039, 3040 6/8/2010 U-233/4 0.12 +/- 0.02 0.13 +/- 0.01 0.13 +/- 0.01 Pass SO-3039, 3040 6/8/2010 U-238 0.12 +/- 0.01 0.13 +/- 0.01 0.13 +/- 0.01 Pass WW-3060, 3061 6/14/2010 H-3 199.16 +/- 95.13 203.59 +/- 95.34 201.38 +/- 67.34 Pass VE-3351, 3352 6/21/2010 Be-7 1.86 +/- 0.25 1.85 +/- 0.27 1.85 +/- 0.18 Pass VE-3351, 3352 6/21/2010 K-40 6.10 +/- 0.52 6.10 +/- 0.57 6.10 +/- 0.39 Pass W-3469, 3470 6/25/2010 H-3 573.00 +/- 110.00 525.00 +/- 108.00 549.00 +/- 77.08 Pass SG-3539, 3540 6/29/2010 Ac-228 14.55 +/- 0.51 14.57 +/- 0.44 14.56 +/- 0.34 Pass SG-3539, 3540 6/29/2010 Pb-214 15.50 +/- 1.56 16.80 +/- 1.71 16.15 +/- 1.16 Pass AP-3743, 3744 6/30/2010 Be-7 0.07 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass A5-2

TABLE A-5, In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-3427, 3428 7/1/2010 Be-7 1.18 +/- 0.29 1.06 +/- 0.25 1.12 +/- 0.19 Pass G-3427, 3428 7/1/2010 K-40 8.79 +/- 0.64 7.85 +/- 0.65 8.32 +/- 0.46 Pass SW-3512, 3513 7/6/2010 H-3 441.00 +/- 103.00 423.00 +/- 102.00 432.00 +/- 72.48 Pass AP-3680, 3681 7/8/2010 Be-7 0.16 +/- 0.08 0.13 +/- 0.07 0.15 +/- 0.05 Pass VE-3791, 3792 7/12/2010 K-40 4.37 +/- 0.38 4.23 +/- 0.35 4.30 +/- 0.26 Pass WW-3934, 3935 7/12/2010 H-3 3091.00 +/- 187.00 3242.00 +/- 191.00 3166.50 +/- 133.65 Pass DW-10135, 10136 7/13/2010 Ra-226 0.18 +/- 0.07 0.26 +/- 0.07 0.22 +/- 0.05 Pass DW-10135, 10136 7/13/2010 Ra-228 0.76 +/- 0.44 0.81 +/- 0.41 0.79 +/- 0.30 Pass W-4063, 4064 7/14/2010 H-3 469.00 +/- 104.00 351.00 +/- 99.00 410.00 +/- 71.79 Pass DW-10143, 10144 7/19/2010 Gr. Alpha 2.84 +/- 0.74 2.49 +/- 0.73 2.67 +/- 0.52 Pass DW-10148, 10149 7/23/2010 Ra-226 2.08 +/- 0.39 2.97 +/- 0.55 2.53 +/- 0.34 Pass DW-10148, 10149 7/23/2010 Ra-228 1.90 +/- 0.61 2.00 +/- 0.61 1.95 +/- 0.43 Pass DW-10159, 10160 7/23/2010 Ra-226 0.91 +/- 0.14 0.79 +/- 0.21 0.85 +/- 0.13 Pass DW-10159, 10160 7/23/2010 Ra-228 1.41 +/- 0.54 1.30 +/- 0.53 1.36 +/- 0.38 Pass SL-4106, 4107 8/2/2010 Be-7 2.05 +/- 0.20 2.05 +/- 0.18 2.05 +/- 0.13 Pass SL-4106, 4107 8/2/2010 Gr. Beta 5.06 +/- 0.32 4.62 +/- 0.30 4.84 +/- 0.22 Pass SL-4106, 4107 8/2/2010 K-40 1.89 +/- 0.24 1.70 +/- 0.17 1.80 +/- 0.15 Pass SG-4085, 4086 8/3/2010 Ra-226 20.23 +/- 2.04 21.45 +/- 2.16 20.84 +/- 1.49 Pass SG-4085, 4086 8/3/2010 Ra-228 15.88 +/- 0.41 16.24 +/- 0.36 16.06 +/- 0.27 Pass SWT-4304, 4305 8/3/2010 Gr. Beta 2.08 +/- 1.07 2.44 +/- 0.98 2.26 +/- 0.73 Pass BS-4398, 4399 8/10/2010 Cs-1 37 78.80 +/- 33.50 94.30 +/- 51.90 86.55 +/- 30.89 Pass BS-4398, 4399 8/10/2010 K-40 13708 +/-795 12091 +/- 1110 12900 +/-683 Pass VE-4531, 4532 8/11/2010 Gr. Beta 36.20 +/- 0.90 35.80 +/- 0.90 36.00 +/- 0.64 Pass VE-4531, 4532 8/11/2010 K-40 27.31 +/- 0.70 27.58 +/- 0.62 27.45 +/- 0.47 Pass VE-4531, 4532 8/11/2010 U-233/4 0.014 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 Pass VE-4531, 4532 8/11/2010 U-238 0.012 +/- 0.003 0.010 +/- 0.002 0.011 +/-+0.002 Pass DW-10170, 10171 8/13/2010 Ra-226 1.32 +/- 0.14 1.26 +/- 0.14 1.29 +/- 0.10 Pass DW-10170, 10171 8/13/2010 Ra-228 2.55 +/- 0.78 1.76 +/- 0.71 2.16 +/- 0.53 Pass AP-4766, 4767 8/26/2010 Be-7 0.18 +/- 0.09 0.25 +/- 0.13 0.22 +/- 0.08 Pass DW-10182, 10183 8/27/2010 Ra-226 0.15 +/- 0.08 0.11 +/- 0.07 0.13 +/- 0.05 Pass VE-4928, 4929 9/1/2010 K-40 2.99 +/- 0.41 3.18 +/- 0.28 3.09 +/- 0.25 Pass SL-4883, 4884 9/1/2010 Gr. Beta 6.90 +/- 0.20 7.10 +/- 0.20 7.00 +/- 0.14 Pass SL-4883, 4 8 8 4 b 9/1/2010 K-40 7.15 +/- 0.99 5.07 +/- 0.51 6.11 +/- 0.56 Fail W-5135, 5136 9/6/2010 H-3 658.60 +/- 110.80 600.90 +/- 108.50 629.75 +/- 77.54 Pass SW-5071, 5072 9/13/2010 H-3 186.70 +/- 101.10 267.30 +/- 104.40 227.00 +/- 72.66 Pass XWW-5246, 5247 9/14/2010 H-3 1990.60 +/- 157.70 1986.20 +/- 157.60 1988.40 +/- 111.48 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-5114, 5115 9/9/2010 Be-7 1.14 +/- 0.35 1.48 +/- 0.26 1.31 +/- 0.22 Pass VE-5114, 5115 9/9/2010 Gr. Beta 34.72 +/- 1.29 33.38 +/- 1.23 34.05 +/- 0.89 Pass VE-5114, 5115 9/9/2010 H-3 79367 +/- 837 79421 +/-837 79394 +/- 592 Pass VE-5114, 5115 9/9/2010 K-40 22.13 +/- 0.67 21.93 +/- 0.58 22.03 +/- 0.44 Pass VE-5114, 5115 9/9/2010 U-233/4 0.08 +/- 0.01 0.06 +/- 0.01 0.07 +/- 0.01 Pass MI-5267, 5268 9/20/2010 K-40 1281.10 +/- 118.90 1218.60 +/- 110.80 1249.85 +/- 81.26 Pass SO-5357,5358 9/23/2010 K-40 10894.00 +/- 560.00 11175.00 +/- 760.00 11034.50 +/- 472.02 Pass AP-5357, 5358 9/23/2010 Be-7 0.11 +/- 0.02 0.09 +/- 0.02 0.10 +/- 0.01 Pass DW-10194, 10195 9/23/2010 Ra-226 0.40 +/- 0.10 0.20 +/- 0.10 0.30 +/- 0.07 Pass DW-10194,10195 9/23/2010 Ra-228 1.61 +/- 0.65 0.88 +/- 0.47 1.25 +/- 0.40 Pass WW-5442,5443 9/29/2010 H-3 6706.00 +/- 252.00 6510.00 +/- 249.00 6608.00 +/- 177.13 Pass VE-5469,5470 9/29/2010 K-40 2.86 +/- 0.38 2.57 +/- 0.37 2.72 +/- 0.26 Pass BS-5886, 5887 9/29/2010 Cs-137 83.36 +/- 23.31 58.97 +/- 21.16 71.17 +/- 15.74 Pass BS-5886, 5887 9/29/2010 K-40 13913.00 +/- 775.40 13582.00 +/- 710.30 13747.50 +/- 525.78 Pass G-5513,5514 10/4/2010 Be-7 6.73 +/- 0.40 6.36 + 0.41 6.55 +/- 0.29 Pass E-5492, 5493 10/4/2010 Gr. Beta 1.74 +/- 0.05 1.77 + 0.05 1.76 +/- 0.04 Pass E-5492, 5493 10/4/2010 K-40 1.57 +/- 0.17 1.55 + 0.18 1.56 +/- 0.12 Pass G-5512,5513 10/4/2010 Gr. Beta 10.86 +/- 0.44 10.39 + 0.39 10.63 +/- 0.29 Pass G-5512,5513 10/4/2010 K-40 7.10 +/- 0.54 7.41 + 0.59 7.26 +/- 0.40 Pass MI-5541, 5542 10/4/2010 K-40 1090.60 +/- 106.70 1246.10 + 102.60 1168.35 +/- 74.01 Pass MI-5541, 5542 10/4/2010 Sr-90 1.44 +/- 0.38 1.11 + 0.35 1.27 +/- 0.26 Pass F-6061, 6062 10/9/2010 H-3 7.64 +/- 0.23 7.49 + 0.23 7.57 +/- 0.16 Pass F-6061, 6062 10/9/2010 K-40 2.81 +/- 0.40 2.56 + 0.50 2.68 +/- 0.32 Pass VE-5740,5741 10/10/2010 K-40 4.92 +/- 0.53 4.61 + 0.34 4.77 +/- 0.32 Pass VE-5761, 5762 10/12/2010 Be-7 1.05 +/- 0.29 0.69 + 0.15 0.87 +/- 0.16 Pass VE-5761,5762 10/12/2010 K-40 3.45 +/- 0.45 3.34 + 0.29 3.40 +/- 0.27 Pass AP-5910, 5911 10/14/2010 Be-7 0.23 +/- 0.09 0.30 + 0.12 0.26 +/- 0.08 Pass WW-6294, 6295 10/18/2010 H-3 1681.49 +/- 146.32 1637.41 + 144.98 1659.45 +/- 102.99 Pass P-6038, 6039 10/19/2010 H-3 2131.90 +/- 159.50 2212.00 +/- 161.70 2171.95 +/- 113.56 Pass AP-6195, 6196 10/21/2010 Be-7 0.27 +/- 0.11 0.26 +/- 0.13 0.26 +/- 0.09 Pass WW-6366, 6367 10/23/2010 H-3 477.28 +/- 102.02 529.99 +/- 104.27 503.64 +/- 72.94 Pass SWU-6315,6316 10/26/2010 Gr. Beta 1.85 +/- 1.00 1.40 +/- 0.90 1.62 +/- 0.67 Pass SO-6336, 6337 10/28/2010 Cs-137 0.23 +/- 0.03 0.23 +/- 0.04 0.23 +/- 0.02 Pass SO-6336,6337 10/28/2010 Gr. Beta 26.36 +/- 1.67 24.78 +/- 1.52 25.57 +/- 1.13 Pass SO-6336, 6337 10/28/2010 K-40 13.43 +/- 0.76 13.73 +/- 0.81 13.58 +/- 0.56 Pass AP-6453, 6454 10/28/2010 Be-7 0.23 +/- 0.12 0.30 +/- 0.15 0.26 +/- 0.10 Pass BS-6475,6476 11/1/2010 Gr. Beta 13.13 +/- 1.83 12.75 +/- 1.67 12.94 +/- 1.24 Pass F-6658, 6659 11/3/2010 K-40 2.79 +/- 0.40 2.94 +/- 0.44 2.86 +/- 0.30 Pass F-6565, 6566 11/4/2010 Cs-137 0.06 +/- 0.02 0.04 +/- 0.01 0.05 +/- 0.01 Pass F-6565, 6566 11/4/2010 Gr. Beta 3.90 +/- 0.10 4.10 +/- 0.10 3.96 +/- 0.06 Pass F-6565, 6566 11/4/2010 K-40 2.63 +/- 0.45 2.57 +/- 0.35 2.60 +/- 0.29 Pass SS-5761, 5762 11/16/2010 K-40 15.42 +/- 1.57 15.87 +/- 1.21 15.65 +/- 0.99 Pass WW-7056,7057 11/30/2010 Gr. Beta 2.09 +/- 0.84 2.22 +/- 0.80 2.16 +/- 0.58 Pass A5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SO-7166, 7167 11/30/2010 Cs-137 0.12 +/- 0.04 0.11 +/- 0.03 0.11 +/- 0.03 Pass SO-7166, 7167 11/30/2010 K-40 14.93 +/-_0.88 14.49 +/-_0.86 14.71 +/-_0.61 Pass WW-7412, 7413 12/6/2010 H-3 469.78 +/- 146.32 503.57 +/- 93.96 486.68 +/- 86.94 Pass MI-7187, 7188 12/8/2010 K-40 1495.10 +/- 129.00 1398.40 +/- 109.10 1446.75 +/- 84.47 Pass MI-7187, 7188 12/8/2010 Sr-90 0.57 +/- 0.31 0.66 +/- 0.28 0.62 +/- 0.21 Pass WW-7255, 7256 12/8/2010 H-3 243.46 +/- 90.39 327.34 +/- 94.11 285.40 +/- 65.24 Pass AP-7276, 7277 12/9/2010 Be-7 0.13 +/- 0.07 0.18 +/- 0.10 0.16 +/- 0.06 Pass XWW-7297, 7298 12/9/2010 H-3 686.00 +/- 102.00 764.60 +/- 105.00 725.30 +/- 73.19 Pass AP-7344, 7345 12/16/2010 Be-7 0.16 +/- 0.09 0.17 +/- 0.09 0.16 +/- 0.06 Pass SWT-7480, 7481 12/28/2010 Gr. Beta 0.90 +/- 0.40 1.03 +/- 0.41 0.97 +/- 0.29 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

b Analysis was repeated, result of reanalysis: 4.83 +/- 0.29 pCi/L.

A5-5

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STVE-1 199 03/01/10 Co-57 0.01 +/- 0.03 0.00 Pass STVE-1 199 03/01/10 Co-60 3.39 +/- 0.12 3.27 2.29 - 4.25 Pass STVE-1 199 03/01/10 Cs-134 4.74 +/- 0.15 4.39 3.07 - 5.71 Pass STVE-1 199 03/01/10 Cs-137 3.32 +/- 0.17 3.06 2.14 -3.98 Pass STVE-1 199 03/01/10 Mn-54 0.01 +/- 0.05 0.00 Pass STVE-1 199 03/01/10 Zn-65 8.03 +/- 0.33 7.10 4.97 - 9.23 Pass STW-1200 03/01/10 Gr. Alpha 0.40 +/- 0.05 0.68 0.00 -1.35 Pass STW-1200 03/01/10 Gr. Beta 3.03 +/- 0.07 3.09 1.55 - 4.64 Pass STW-1201 03/01/10 Am-241 1.05 +/- 0.08 1.30 0.91 -1.69 Pass STW-1201 03/01/10 Co-57 28.90 +/- 0.40 28.30 19.80 -36.80 Pass STW-1201 03/01/10 Co-60 0.06 +/- 0.05 0.00 Pass STW-1201 03/01/10 Cs-1 34 -0.03 +/- 0.09 0.00 Pass STW-1201 03/01/10 Cs-1 37 60.60 +/- 0.60 60.60 42.40 -78.80 Pass STW-1201 03/01/10 Fe-55 3.00 +/- 14.40 0.00 Pass STW-1201 03/01/10 H-3 93.20 +/- 18.30 90.80 63.60 -118.00 Pass STW-1201 03/01/10 Mn-54 27.80 +/- 0.40 26.90 18.80 -35.00 Pass STW-1201 03/01/10 Ni-63 49.10 +/- 3.50 59.90 41.90 -77.90 Pass STW-1201 03/01/10 Sr-90 -0.10 +/- 0.60 0.00 Pass STW-1201 03/01/10 Tc-99 0.50 +/- 0.50 0.00 Pass STW-1201 03/01/10 U-233/4 1.21 +/- 0.05 1.22 0.85 -1.59 Pass STW-1201 03/01/10 U-238 1.20 +/- 0.05 1.25 0.88 -1.63 Pass STW-1 201 03/01/10 Zn-65 42.70 +/- 0.80 40.70 28.50 -52.90 Pass STSO-1202 03/01/10 Co-57 520.00 +/- 10.80 522.00 365.00 -679.00 Pass STSO-1202 03/01/10 Co-60 599.10 +/- 2.80 622.00 435.00 -809.00 Pass STSO-1202 03/01/10 Cs-134 666.10 +/- 4.70 733.00 513.00 -953.00 Pass STSO-1202 03/01/10 Cs-1 37 774.40 +/- 4.50 779.00 545.00 -1013.00 Pass STSO-1202 03/01/10 K-40 562.00 +/- 15.30 559.00 391.00 -727.00 Pass STSO-1202 03/01/10 Mn-54 866.20 +/- 4.60 849.00 594.00 -1104.00 Pass STSO-1 202 03/01/10 Sr-90 225.50 +/- 11.80 288.00 202.00 -374.00 Pass STSO-1202 03/01/10 U-233/4 59.90 +/- 2.50 60.00 42.00 -78.00 Pass STSO-1202 03/01/10 U-238 62.10 +/- 2.60 64.00 45.00 -83.00 Pass STSO-1202 03/01/10 Zn-65 -1.23 +/- 1.96 0.00 Pass STAP-1203 03/01/10 Am-241 0.10 +/- 0.01 0.15 0.10 -0.19 Pass STAP-1203 03/01/10 Co-57 0.01 +/- 0.02 0.00 Pass STAP-1203 03/01/10 Co-60 2.63 +/- 0.19 2.47 1.73 -3.22 Pass STAP-1203 03/01/10 Cs-134 2.21 +/- 0.34 2.13 1.49 - 2.77 Pass STAP-1203 03/01/10 Cs-137 1.66 +/- 0.22 1.53 1.07 -1.99 Pass STAP-1203 03/01/10 Mn-54 3.42 +/- 0.26 3.02 2.11 -3.93 Pass STAP-1203 03/01/10 Sr-90 0.02 +/- 0.06 0.00 Pass STAP-1203 03/01/10 Zn-65 -0.05 +/- 0.11 0.00 Pass A6-1

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

b Concentration Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STAP-1204 03101110 Gr. Alpha 0.13 +/- 0.03 0.43 0.00 - 0.85 Pass STAP-1204 03/01/10 Gr. Beta 1.46 +/- 0.07 1.29 0.65 - 1.94 Pass STW-1211 08/01/10 Am-241 0.02 +/- 0.02 0.00 Pass STW-1211 08/01/10 Co-57 36.40 +/- 4.80 36.00 25.20 - 46.80 Pass STW-1211 08/01/10 Co-60 28.30 +/- 1.00 28.30 19.80 -36.80 Pass STW-1211 08/01/10 Cs-1 34 29.30 +/- 2.10 31.40 22.00 - 40.80 Pass STW-1211 08/01/10 Cs-137 44.60 +/- 1.80 44.20 30.90 - 57.50 Pass STW-1211 08/01/10 Fe-55 48.50 +/- 20.10 60.20 42.10 -78.30 Pass STW-1211 08/01/10 H-3 503.60 +/- 12.80 453.40 317.40 -589.40 Pass STW-1211 08/01/10 K-40 38.50 +/- 2.50 38.90 27,20 - 50.60 Pass STW-1211 08/01/10 Mn-54 0.10 +/- 0.30 0.00 Pass STW-1211 08/01/10 Ni-63 49.30 +/- 3.10 56.10 39.30 - 72.90 Pass STW-1211 08/01/10 Pu-238 1.49 +/- 0.15 1.81 1.27 -2.35 Pass STW-1211 08/01/10 Pu-239/40 1.20 +/- 0.10 1.35 0.95 - 1.76 Pass STW-1211 08/01/10 Sr-90 9.20 +/- 1.30 8.30 5.80 - 10.80 Pass STW-1211 08/01/10 Tc-99 28.10 +/- 0.90 33.60 23.50 - 43.70 Pass STW-1211 08/01/10 U-233/4 2.04 +/- 0.14 2.01 1.41 - 2.61 Pass STW-1211 08/01/10 U-238 2.05 +/- 0.14 2.07 1.45 - 2.69 Pass STW-1211 08/01/10 Zn-65 32.80 +/- 3.00 31.00 21.70 -40.30 Pass STW-1212 08/01/10 Gr. Alpha 1.54 +/- 0.09 1.92 0.58 - 3.26 Pass STW-1212 08/01/10 Gr. Beta 4.13 +/- 0.15 4.39 2.20 - 6.59 Pass STVE-1213 08/01/10 Co-57 9.60 +/- 0.54 8.27 5.79 - 10.75 Pass STVE-1213 08/01/10 Co-60 0.05 +/- 0.08 0.00 Pass STVE-1213 08/01/10 Cs-134 4.83 +/- 0.26 4.79 3.35 - 6.23 Pass STVE-1213 08/01/10 Cs-137 6.45 +/- 0.66 5.88 4.12 -7.64 Pass STVE-1 213 08/01/10 Mn-54 7.12 +/- 0.66 6.29 4.40 -8.17 Pass STVE-1213 08/01/10 Zn-65 6.05 +/- 0.74 5.39 3.77 - 7.01 Pass STSO-1214 08/01/10 Co-57 0.10 +/- 1.60 0.00 Pass STSO-1214 08/01/10 Co-60 370.00 +/- 6.00 343.00 240.00 - 446.00 Pass STSO-1214 08/01/10 Cs-134 1005.00 +/- 21.00 940.00 658.00 - 1222.00 Pass STSO-1214 08/01/10 Cs-137 755.00 +/- 15.00 670.00 469.00 -871.00 Pass STSO-1214 08/01/10 K-40 783.00 +/- 54.00 699.00 489.00 - 909.00 Pass STSO-1214 08/01/10 Mn-54 942.00 +/- 15.00 820.00 574.00 - 1066.00 Pass STSO-1214 08/01/10 Pu-238 69.20 +/- 6.20 64.00 45.00 - 83.00 Pass STSO-1214 08/01/10 Pu-239/40 76.50 +/- 6.20 71.00 50.00 - 92.00 Pass STSO-1214 08/01/10 Sr-90 3.50 +/- 8.00 0.00 Pass STSO-1214 08/01/10 U-233/4 76.50 +/- 6.20 71.00 50.00 - 92.00 Pass STSO-1214 08/01/10 U-238 271.40 +/- 9.00 289.00 202.00 - 376.00 Pass STSO-1214 08/01/10 Zn-65 310.00 +/- 18.00 265.00 186.00 - 345.00 Pass A6-2

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration b Known Control Lab Code Date Analysis Laboratory result Activity Limits d Acceptance STAP-1215 08/01/10 Co-57 4.47 +/- 0.21 4.08 2.86 -5.30 Pass STAP-1215 08/01/10 Co-60 3.15 +/- 0.30 2.92 2.04 - 3.80 Pass STAP-1215 08/01/10 Cs-134 3.03 +/- 0.17 2.98 2.09 - 3.87 Pass STAP-1215 08/01/10 Cs-137 0.01 +/- 0.05 0.00 - Pass STAP-1215 08/01/10 Mn-54 3.69 +/- 0.39 3.18 2.23 -4.13 Pass STAP-1215 08/01/10 Sr-90 1.00 +/- 0.12 1.01 0.71 -1.31 Pass STAP-1215 08/01/10 Zn-65 0.03 +/- 0.15 0.00 - Pass STAP-1216 08/01/10 Gr. Alpha 0.01 +/- 0.01 0.00 - Pass STAP-1216 08/01/10 Gr. Beta 0.54 +/- 0.05 0.50 0.25 - 0.75 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP, A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

A6-3

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance STAP-1217 09/20/10 Am-241 55.6 +/- 2.9 74.1 43.3 - 102.0 Pass STAP-1217 09/20/10 Co-60 517.1 +/- 9.1 479.0 371.0 -598.0 Pass STAP-1 217 09/20/10 Cs-1 34 384.6 +/- 33.7 388.0 253.0 - 480.0 Pass STAP-1217 09/20/10 Cs-1 37 589.4 +/- 7.1 514.0 386.0 - 675.0 Pass STAP-1 217 09/20/10 Mn-54 0.0 +/- 0.0 Pass STAP-1217 09/20/10 Pu-238 76.5 +/- 4.0 72.9 50.0 - 95.8 Pass STAP-1217 09/20/10 Pu-239/40 73.0 +/- 3.8 69.6 50.5 - 90.1 Pass STAP-1217 09/20/10 Sr-90 172.9 +/- 21.3 159.0 70.0 - 247.0 Pass STAP-1217 09/20/10 U-233/234 64.9 +/- 3.9 71.8 45.2 - 106.0 Pass STAP-1217 09/20/10 U-238 68.0 +/- 4.0 71.2 45.6 -101.0 Pass STAP-1217 09/20/10 Uranium 135.5 +/- 8.7 146.0 74.6 - 232.0 Pass STAP-1217 09/20/10 Zn-65 563.1 +/- 15.3 465.0 322.0 - 644.0 Pass STAP-1218 09/20/10 Gr. Alpha 66.1 +/- 3.2 52.3 27.1 -78.7 Pass STAP-1218 09/20/10 Gr. Beta 69.9 +/- 2.5 52.7 32.5 - 77.0 Pass STSO-1219 09/20/10 Ac-228 1632.0 +/- 80.4 1830.0 1170.0 -2580.0 Pass STSO-1219 09/20/10 Am-241 1063.0 +/- 120.9 1120.0 669.0 - 1440.0 Pass STSO-1219 09/20/10 Bi-212 1752.0 +/- 255.6 2070.0 543.0 -3100.0 Pass STSO-1219 09/20/10 Bi-214 909.3 +/- 38.9 983.0 603.0 - 1410.0 Pass STSO-1219 09/20/10 Co-60 4852.0 +/- 153.5 4780.0 3480.0 - 6420.0 Pass STSO-1219 09/20/10 Cs-134 2190.0 +/- 50.7 2240.0 1440.0 - 2700.0 Pass STSO-1219 09/20/10 Cs-137 3584.0 +/- 42.5 3530.0 2700.0 - 4580.0 Pass STSO-1219 09/20/10 K-40 10017.0 + 274.5 10700.0 7760.0 - 14500.0 Pass STSO- 1219 09/20/10 Mn-54 0.0 + 0.0 Pass STSO-1219 09/20/10 Pb-212 1573.0 +/- 28.2 1640.0 1060.0 -2310.0 Pass STSO-1219 09/20/10 Pb-214 999.0 + 39.2 969.0 580.0 - 1440.0 Pass STSO-1219 09/20/10 Pu-238 1568.0 +/- 155.0 1280.0 733.0 - 1800.0 Pass STSO-1219 09/20/10 Pu-239/40 1445.0 +/- 142.9 1180.0 805.0 - 1570.0 Pass STSO-1219 09/20/10 U-233/234 599.4 +/- 69.4 1360.0 862.0 - 1690.0 Fail STSO-1219 e 09/20/10 U-238 633.8 +/- 71.3 1340.0 819.0 - 1700.0 Fail STSO-1219 e 09/20/10 Uranium 1248.0 + 152.7 2770.0 1580.0 - 3740.0 Fail STSO-1219 09/20/10 Zn-65 2447.0 +/- 60.1 2300.0 1820.0 - 3080.0 Pass STVE-1220 09/20/10 Co-60 1108.0 +/- 38.7 1010.0 683.0 - 1450.0 Pass STVE-1220 09/20/10 Cs-134 1161.0 +/- 57.3 1040.0 595.0 - 1440.0 Pass STVE-1220 09/20/10 Cs-137 1400.0 +/- 43.0 1260.0 924.0 - 1750.0 Pass STVE-1 220 09/20/10 K-40 27400.0 +/- 683.4 22600.0 16200.0 -32000.0 Pass STVE-1220 09/20/10 Mn-54 0.0 +/- 0.0 Pass A7-1

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance STVE-1220 09/20/10 Am-241 4185.0 +/- 180.0 4760.0 2710.0 - 6540.0 Pass STVE-1220 09/20/10 Cm-244 2329.0 +/- 132.5 2740.0 1350.0 -4270.0 Pass STVE-1220 09/20/10 Pu-238 4912.0 +/- 194.0 4740.0 2560.0 - 6940.0 Pass STVE-1220 09/20/10 Pu-239/40 4765.0 +/- 111.0 4470.0 2770.0 - 6100.0 Pass STVE-1220 09/20/10 Sr-90 7706.0 +/- 583.9 7810.0 4360.0 - 10400.0 Pass STVE-1220 09/20/10 U-233/234 3862.0 +/- 203.0 4010.0 2750.0 - 5320.0 Pass STVE-1220 09/20/10 U-238 3926.0 +/- 205.3 3980.0 2800.0 - 5030.0 Pass STVE-1220 09/20/10 Uranium 7671.0 +/- 201.2 8180.0 5620.0 - 10600.0 Pass STVE-1220 09/20/10 Zn-65 1443.0 +/- 81.0 1210.0 874.0 - 1650.0 Pass STW-1221 09/20/10 Am-241 127.9 +/- 4.2 176.0 120.0 - 238.0 Pass STW-1221 09/20/10 Co-60 697.8 +/- 10.4 714.0 622.0 - 844.0 Pass STW-1221 09/20/10 Cs-134 437.5 +/- 13.3 492.0 363.0 - 565.0 Pass STW-1221 09/20/10 Cs-137 612.8 +/- 11.6 625.0 531.0 - 749.0 Pass STW-1221 09/20/10 Fe-55 936.8 +/- 508.2 825.0 480.0 -1100.0 Pass STW-1221 09/20/10 Mn-54 0.0 +/- 0.0 Pass STW-1221 09/20/10 Pu-238 148.1 +/- 6.0 162.0 122.0 - 201.0 Pass STW-1221 09/20/10 Pu-239/40 154.1 +/- 6.2 148.0 114.0 - 183.0 Pass STW-1221 09/20/10 Sr-90 872.3 +/- 13.4 921.0 585.0 - 1230.0 Pass STW-1221 09/20/10 U-233/234 99.1 +/- 4.4 109.0 82.2 - 140.0 Pass STW-1221 09/20/10 U-238 103.7 +/- 4.5 108.0 82.5 - 134.0 Pass STW-1221 09/20/10 Uranium 206.5 +/- 9.8 221.0 159.0 -294.0 Pass STW-1221 09/20/10 Zn-65 489.1 +/- 16.2 489.0 414.0 - 610.0 Pass STW-1222 09/20/10 Gr. Alpha 110.6 +/-3.5 146.0 64.8 -216.0 Pass STW-1222 09/20/10 Gr. Beta 134.6 +/- 2.6 143.0 83.6 - 210.0 Pass STW-1223 09/20/10 H-3 23500.0 +/- 1438.0 21600.0 14100.0 -31900.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.

Analysis was repeated using total dissolution. Results of the reanalysis, U-233/234: 1137 +/- 254 pCi/kg, U-238: 1193 +/- 116 pCi/kg, Total Uranium: 2379 +/- 254 pCi/kg.

A7-2

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX B 2010 REMP DATA

SUMMARY

REPORTS

APPENDIX B Air Gamma Spectral Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from I Jocaijon-wilh-Hip_*hesLAnnuMaLeann -_ _ Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed and Range

-(_LLD) and Range Direction and Ranpg __ and Range Air Be-7 N/A 0.06 0.06 5 0.07 0.06 pCi/m3 28 28 / 28 24 / 24 0.60 4/ 20 4/4 0.05 - 0.08 0.05 - 0.08 SW 0.06 - 0.08 0.05 - 0.07 Air Co-58 N/A LLD pCi/m3 28 Air Co-60 N/A LLD pCi/m3 28 Air Cs-134 0.04 LLD pCi/m3 28 Air Cs-137 0.05 LLD pCi/m3 28 B-i

APPENDIX B Air Gross Beta Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from I n with Higbhet Annnal Mean* Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed and Rnnoe (LLD) I and Ran~e Direction and Ranee and Range Air Gross Beta 0.01 0.02 0.02 1 0.02 0.02 pCi/m3 363 362 / 363 310 / 311 3.40 52 / 52 52 / 52 0.01 - 0.05 0.01 - 0.05 ENE 0.01 - 0.05 0.01 - 0.04

~1 I

___________ L_________________ I ____________

B-2

APPENDIX B Air Iodine Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. 50-440/50-441 Type and Mean of Results from Mean of Results from I oc.tiqn withHighestAnnal Mean- Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Uni.t.s...... Performed (LLD) 1 and Range and Ranoe Direction and Range and Rang~e_

Air 1-131 0.05 LLD pCi/m3 363 B-3

APPENDIX B Fish Gamma Spectral Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with iJ~Iilaet Annimn Mean- Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Number Detected/Number Collected Limit Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed } (LLD) . and Rantte and Rancze Direction and Ranee I

I Direction and Range Fish Co-58 97.00 LLD pCi/kg wet 4 Fish Co-60 97.00 LLD pCi/kg wet 4 Fish Cs-134 97.00 LLD pCi/kg wet 4 Fish Cs-137 112.00 LLD pCi/kg wet 4 Fish Fe-59 195.00 LLD pCi/kg wet 4 Fish K-40 N/A 1,066.35 1,136.32 25 1,136.32 996.39 pCi/kg wet 4 4/4 2/2 0.60 2 /16 2/2 768.97- 1,350.00 922.63- 1,350.00 NNW 922.63 - 1,350.00 768.97 - 1,223.80 Fish Mn-54 97.00 LLD pCi/kg wet 4 Fish Zn-65 195.00 LLD pCi/kg wet 4 B-4

APPENDIX B Food Products Gamma Spectral Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from I nrqtion with, Highiest Annnait Me.nn Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Ranee and Range and Range and Range Food Products Be-7 N/A 591.27 562.16 2 803.85 724.38 pCi/kg wet 57 39 / 57 32 / 46 1.90 117.52 - 2,347.20 117.52 - 1,504.30 ENE 199.717 /- 63 1,504.30 324.677 -/ 2,347.20 11 Food Products Co-58 N/A LLD pCi/kg wet 57 Food Products Co-60 N/A LLD pCi/kg wet 57 Food Products Cs-134 45.00 LLD pCi/kg wet 57 Food Products Cs-137 60.00 LLD pCi/kg wet 57 Food Products 1-131 45.00 LLD pCi/kg wet 57 Food Products K-40 N/A 5,484.38 5,361.64 18 6,861.53 5,997.68 pCi/kg wet 57 57 / 57 46 / 46 2.50 9 / 63 11 / 11 3,391.75 - 8,684.00 3,391.75 - 8,684.00 E 4,919.40 - 8,684.00 3,872.90 - 8,330.60 B-5

APPENDIX B Milk Gamma Spectral Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from I e.fopith Highe"St Anning] Me~,n Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Ranee and Ranae Direction and Ranme and Ranae t_ I _ _ _ I Milk Ba-140 45.00 LLD pCi/L 59 Milk Cs-134 11.00 LLD pCi/L 59 Milk Cs-137 13.00 LLD pCi/L 59 Milk K-40 N/A 1,454.37 1,662.84 61 1,765.44 1,015.49 pCi/L 59 59 / 59 40 / 40 7.40 11 / 55 19 / 19 690.33 - 1,983.70 1,314.60 - 1,983.70 SE 1,385.50 - 1,983.70 690.33 - 1,563.20 Milk La-140 11.00 LLD pCiIL 59 B-6

APPENDIX B Milk Iodine Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Locnii nn with Hiohect An-In UM-n Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed {LLD) and Range and Range Direction and Rannge and Ranpe Milk 1-131 0.75 LLD pCi/L 59 B-7

APPENDIX B Sediment Gamma Spectral Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from i ncritiqn wvith Nighe'qt Ann~iin Menn Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected a"Al Q nn and Units ftI fl13 and Range and Ran*,e Performed (LLD' and Range I i

Sediment Co-58 50.00 LLD pCi/kg dry 12 Sediment Co-60 40.00 LLD pCi/kg dry 12 Sediment Cs-134 112.00 LLD pCi/kg dry 12 Sediment Cs-137 135.00 375.95 169.30 32 685.94 685.94 pCi/kg dry 12 5 / 12 3 / 10 15.80 2 / 10 2/2 138.18 - 737.85 138.18 - 222.23 WSW 634.02 - 737.85 634.02 - 737.85 Sediment K-40 N/A 14,174.31 12,179.87 32 24,146.50 24,146.50 pCi/kg dry 12 12 / 12 10 / 10 15.80 2 / 10 2/2 8,969.30 - 25,290.00 8,969.30 - 16,592.00 WSW 23,003.00 - 25,290.00 23,003.00 - 25,290.00 B-8

APPENDIX B TLD Gamma Dose Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from I nctntign with t-tighesLAnnnM*.ean2.... Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed ....... an........

  • d Ranj~e .... . . .... and Ran - and Range SL(LD)- Direction and Rang TLD Direct 1.00 13.36 13.37 33 17.75 13.17 mR/91 days 112 112 / 112 104 / 104 4.50 4/4 8/8 8.07 - 18.60 8.07 - 18.60 S 15.87 - 18.60 11.88 - 15.20 TLD Direct 1.00 13.60 13.66 33 17.54 12.91 mR/91 days 112 112 / 112 104 / 104 4.50 4/4 8/8 9.71 - 18.90 9.71 - 18.90 S 16.15 - 18.90 11.67 - 14.08 TLD Direct 1.00 56.48 56.63 36 71.55 54.64 mR/365 days 28 28 I 28 26 / 26 3.90 1 / 1 2/2 44.21 - 71.55 44.21 - 71.55 WSW 71.55 - 71.55 53.86 - 55.41 B-9

APPENDIX B Water Gamma Spectral Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from n with 4i~gheqt Anni*a1 Mean" Inq~notic Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range Water Ba- 140 45.00 LLD pCi/L 52 Water Co-58 11.00 LLD pCi/L 52 Water Co-60 11.00 LLD pCi/L 52 Water Cs- 134 11.00 LLD pCi/L 52 Water Cs-137 13.00 LLD pCi/L 52 Water Fe-59 22.00 LLD pCi/L 52 Water La-140 11.00 LLD pCi/L 52 Water Mn-54 11.00 LLD pCi/L 52 Water Nb-95 11.00 LLD pCi/L 52 Water Zn-65 22.00 LLD pCi/L 52 B-10

APPENDIX B Water Gamma Spectral Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from . . Iocaiton.ith Hiphti' Annuql Mean- Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range Water Zr-95 22.00 LLD pCi/L 52 B-1I

APPENDIX B Water Gross Beta Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from i LocationSI#r.catiqn with Hiphe't Annual Mean- Mean of Results from and Mean and All Control Locations and Number of Lower All Locations and All Indicator Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number 1 Collected I Number Detected/Number Collected nndu Ihinoe flirectinn anr nnoe n nd llnnoe and Units Performed (LLD) and Range and Ran-e Direction and Ran-e i and Ran-Water Gross Beta 3.00 2.87 2.93 60 3.14 2.41 pCi/L 52 10 / 52 9 /40 1.00 2/8 1 /12 1.92 - 3.41 1.92 - 3.41 WSW 3.12 - 3.16 2.41 - 2.41 B- 12

APPENDIX B Water Tritium Summary Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from . ocaticn wthIiigbaAnnua1,Mearn Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected 1 Number Detected/Number Collected and Units Performed (LLDJ - and Range and Rannge Direction and Range and Range Water H-3 1,500.00 LLD pCi/L 18 B-13

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX C 2010 REMP DETAILED DATA REPORT

APPENDIX C Air Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1 Air 3/31/2010 0.066 +/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 Air 6/30/2010 0.067 +/- 0.009 < 0.000 < 0.000 < 0.000 < 0.000 Air 9/29/2010 0.064 +/- 0.009 < 0.000 < 0.000 < 0.000 < 0.000 Air 12/29/2010 0.060 +/- 0.011 < 0.000 < 0.000 < 0.000 < 0.000 3 Air 3/31/2010 0.073 +/- 0.011 < 0.000 < 0.000 < 0.000 < 0.000 3 Air 6/30/2010 0.071 +/-/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 3 Air 9/29/2010 0.060 +/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 3 Air 12/29/2010 0.057 +/- 0.008 < 0.000 < 0.000 < 0.000 < 0.000 4 Air 3/31/2010 0.066 +/-/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 4 Air 6/30/2010 0.070 +/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 C-1

APPENDIX C Air Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs- 134 Cs-137 4 Air 9/29/2010 0.064 +/- 0.014 < 0.000 < 0.001 < 0.001 < 0.001 4 Air 12/29/2010 0.058 +/- 0.008 < 0.000 < 0.000 < 0.000 < 0.000 Air 3/31/2010 0.067 +/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 Air 6/30/2010 0.071 +/-/- 0.009 < 0.000 < 0.000 < 0.000 < 0.000 5 Air 9/29/2010 0.076 +/- 0.011 < 0.000 < 0.000 < 0.000 < 0.001 5 Air 12/29/2010 0.055 +/- 0.008 < 0.000 < 0.000 < 0.000 < 0.000 6 Air 3/31/2010 0.072 +/- 0.009 < 0.000 < 0.000 < 0.000 < 0.000 6 Air 6/30/2010 0.065 +/- 0.009 < 0.000 < 0.000 < 0.000 < 0.000 6 Air 9/29/2010 0.062 +/-/- 0.010 < 0.001 < 0.001 < 0.001 < 0.000 6 Air 12/29/2010 0.046 +/- 0.008 < 0.000 < 0.000 < 0.000 < 0.000 C-2

APPENDIX C Air Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in pCi/m3 +/- 2 Sigmaa Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 7 Air 3/31/2010 0.066 +/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 7 Air 6/30/2010 0.063 +/- 0.008 < 0.000 < 0.000 < 0.000 < 0.000 7 Air 9/29/2010 0.076 +/- 0.010 < 0.001 < 0.000 < 0.000 < 0.001 7 Air 12/29/2010 0.057 +/- 0.008 < 0.000 < 0.000 < 0.000 < 0.000 35 Air 3/31/2010 0.063 +/- 0.009 < 0.000 < 0.000 < 0.000 < 0.000 35 Air 6/30/2010 0.057 +/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 35 Air 9/29/2010 0.065 +/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 35 Air 12/29/2010 0.050 +/- 0.010 < 0.000 < 0.000 < 0.000 < 0.000 C-3

APPENDIX C Air Gross Beta Detail Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. :50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location 1 3 4 5 6 Collection Date Sample Type 7 35 1/6/2010 Air 0.016 +/- 0.003 0.017 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.002 0.017 +/- 0.002 0.015 +/- 0.003 0.018 +/- 0.002 1/13/2010 Air 0.026 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.003 0.027 +/- 0.003 0.023 +/- 0.003 0.027 +/- 0.003 0.025 +/- 0.003 1/20/2010 Air 0.040 +/- 0.003 0.038 +/- 0.003 0.040 +/- 0.003 0.037 +/- 0.003 0.037 +/- 0.003 0.039 +/- 0.003 0.038 +/- 0.003 1/27/2010 Air 0.015 +/- 0.003 0.012 +/- 0.003 0.013 +/- 0.003 0.013 +/- 0.003 0.012 +/- 0.003 0.011 +/- 0.003 0.012 +/- 0.003 2/3/2010 Air 0.024 +/- 0.003 0.025 +/- 0.003 0.026 +/- 0.003 0.023 +/- 0.003 0.023 +/- 0.003 0.022 +/- 0.003 0.024 +/- 0.003 2/10/2010 Air 0.026 +/- 0.003 0.024 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 0.023 +/- 0.003 0.023 +/- 0.003 0.025 +/- 0.003 2/17/2010 Air 0.016 +/- 0.003 0.018 +/- 0.003 0.015 +/- 0.002 0.017 +/- 0.003 0.013 +/- 0.002 0.015 +/- 0.003 0.014 +/- 0.002 2/24/2010 Air 0.022 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.021 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 3/3/2010 Air 0.014 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 3/10/2010 Air 0.029 +/- 0.003 0.030 +/- 0.003 0.030 +/-0.003 0.028 +/- 0.003 0.029 +/- 0.003 0.027 +/- 0.003 0.031 +/- 0.003 3/17/2010 Air 0.021 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 3/24/2010 Air 0.023 +/- 0.003 0.021 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 0.021 +/-0.003 0.019 +/- 0.003 0.020 +/- 0.002 3/31/2010 Air 0.021 +/- 0.003 0.020 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.017 +/- 0.003 0.020 +/- 0.002 4/7/2010 Air 0.018 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 C-4

APPENDIX C Air Gross Beta Detail Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location 1 3 4 5 6 Collection Date Sample Type 7 35 4/15/2010 Air 0.020 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 0.016 +/- 0.002 0.021 +/- 0.002 0.020 +/- 0.002 0.017 +/- 0.002 4/21/2010 Air 0.018 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.020 +/- 0.003 0.016 +/- 0.003 4/28/2010 Air 0.018 +/- 0.003 0.018 +/- 0.002 0.017 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.003 0.017 +/- 0.003 0.020 +/- 0.003 5/5/2010 Air 0.016 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.003 0.015 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 5/12/2010 Air 0.015 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.016 +/- 0.002 5/19/2010 Air 0.012 +/- 0.002 0.011 +/-0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 5/26/2010 Air 0.020 +/- 0.002 0.016 +/- 0.002 0.026 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.016 +/- 0.002 0.017 +/- 0.002 6/2/2010 Air 0.018 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.019 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.002 6/9/2010 Air 0.016 +/- 0.002 0.014 +/- 0.002 0.018 +/- 0.003 0.014 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.002 6/16/2010 Air 0.018 +/- 0.002 0.016 +/- 0.002 0.024 +/- 0.003 0.020 +/- 0.003 0.014 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 6/23/2010 Air 0.018 +/- 0.002 0.017 +/- 0.002 0.018 +/- 0.002 0.017 +/- 0.003 0.015 +/- 0.002 0.018 +/- 0.002 0.014 +/- 0.002 6/30/2010 Air 0.020 +/- 0.003 0.017 +/- 0.002 0.019 +/- 0.003 0.019 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.003 7/7/2010 Air 0.027 +/- 0.003 0.021 +/- 0.003 0.027 +/- 0.003 0.027 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 7/14/2010 Air 0.026 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 0.028 +/- 0.003 0.024 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.003 C-5

APPENDIX C Air Gross Beta Detail Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location 1 3 4 5 6 Collection Date Sample Type 7 35 7/21/2010 Air 0.027 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.003 0.030 +/- 0.003 0.027 +/- 0.003 0.024 +/- 0.003 0.026 +/- 0.003 7/28/2010 Air 0.020 +/- 0.002 0.019 +/- 0.002 0.018 +/- 0.002 0.020 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.002 8/4/2010 Air 0.025 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 0.027 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 0.024 +/- 0.003 8/11/2010 Air 0.032 +/- 0.003 0.027 +/- 0.003 0.034 +/- 0.003 0.035 +/- 0.003 0.028 +/- 0.003 0.031 +/- 0.003 0.028 +/- 0.003 8/18/2010 Air 0.026 +/- 0.003 0.024 +/- 0.003 0.026 +/- 0.003 0.026 +/- 0.003 0.028 +/- 0.003 0.026 +/- 0.003 0.025 +/- 0.003 8/25/2010 Air 0.025 +/- 0.003 0.022 +/- 0.003 0.024 +/- 0.003 0.025 +/- 0.003 0.026 +/- 0.003 0.026 +/- 0.003 0.025 +/- 0.003 9/1/2010 Air 0.030 +/- 0.003 0.025 +/- 0.003 0.030 +/- 0.003 0.031 +/- 0.003 0.027 +/- 0.003 0.031 +/- 0.003 0.029 +/- 0.003 9/8/2010 Air 0.024 +/- 0.003 0.026 +/- 0.003 0.027 +/- 0.003 0.027 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 0.024 +/- 0.003 9/15/2010 Air 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.003 0.014 +/- 0.003 0.011 +/-0.002 0.011 +/-0.002 9/22/2010 Air 0.022 +/- 0.003 0.017 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.003 9/29/2010 Air 0.019 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.003 10/6/2010 Air 0.014 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.018 +/- 0.003 0.015 +/-/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 10/13/2010 Air 0.035 +/- 0.003 0.028 +/- 0.003 0.032 +/- 0.003 0.031 +/- 0.003 0.034 +/- 0.003 0.030 +/- 0.003 0.029 +/- 0.003 10/20/2010 Air 0.020 +/- 0.003 0.018 +/- 0.003 0.016 +/- 0.002 0.018 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 C-6

APPENDIX C Air Gross Beta Detail Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location 1 3 4 5 6 Collection Date Sample Type 7 35 10/27/2010 Air 0.026 +/- 0.003 0.025 +/- 0.003 0.026 +/- 0.003 0.024 +/- 0.003 0.024 +/- 0.003 0.025 +/- 0.003 0.023 +/- 0.003 11/3/2010 Air 0.015 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 11/10/2010 Air 0.021 +/- 0.003 0.020 +/- 0.002 0.017 +/- 0.002 0.020 +/- 0.002 0.022 +/- 0.002 0.019 +/- 0.003 0.019 +/- 0.002 11/17/2010 Air 0.032 +/- 0.003 0.026 +/- 0.003 0.036 +/- 0.003 0.035 +/- 0.003 0.030 +/- 0.003 0.032 +/- 0.003 0.033 +/- 0.003 11/24/2010 Air 0.049 +/- 0.004 0.041 +/- 0.003 0.041 +/- 0.004 0.033 +/- 0.004 0.036 +/- 0.004 0.033 +/- 0.004 12/1/2010 Air 0.030 +/- 0.003 0.028 +/- 0.003 0.030 +/- 0.003 0.031 +/- 0.003 0.032 +/- 0.003 0.030 +/- 0.003 0.031 +/- 0.003 12/8/2010 Air 0.018 +/- 0.003 0.016 +/-/- 0.002 0.017 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.003 LLD 0.019 +/- 0.003 12/15/2010 Air 0.027 +/- 0.003 0.025 +/- 0.003 0.026 +/- 0.003 0.027 +/- 0.003 0.028 +/- 0.003 0.032 +/- 0.003 0.029 +/- 0.003 12/21/2010 Air 0.033 +/- 0.003 0.029 +/- 0.003 0.031 +/- 0.003 0.036 +/- 0.003 0.032 +/- 0.003 0.032 +/-0.003 0.032 +/- 0.003 12/29/2010 Air 0.011 +/-/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.009 +/- 0.002 0.011 +/-0.002 C-7

APPENDIX C Air Iodine Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 Air 1/6/2010 0.006 Air 1/13/2010 0.007 Air 1/20/2010 0.007 Air 1/27/2010 0.010 Air 2/3/2010 0.008 Air 2/10/2010 0.007 Air 2/17/2010 0.012 Air 2/24/2010 0.012 Air 3/3/2010 0.008 Air 3/10/2010 0.007 Air 3/17/2010 0.012 Air 3/24/2010 0.010 Air 3/31/2010 0.008 Air 4/7/2010 0.006 Air 4/15/2010 0.005 Air 4/21/2010 0.014 Air 4/28/2010 0.006 Air 5/5/2010 0.008 Air 5/12/2010 0.010 Air 5/19/2010 0.006 Air 5/26/2010 0.007 Air 6/2/2010 0.006 Air 6/9/2010 0.004 Air 6/16/2010 0.006 Air 6/23/2010 0.009 Air 6/30/2010 0.010 Air 7/7/2010 0.006 Air 7/14/2010 0.010 Air 7/21/2010 0.011 Air 7/28/2010 0.008 Air 8/4/2010 0.006 Air 8/11/2010 0.011 Air 8/18/2010 0.002 Air 8/25/2010 0.008 Air 9/1/2010 0.005 Air 9/8/2010 0.005 Air 9/15/2010 0.010 Air 9/22/2010 0.008 C-8

APPENDIX C Air Iodine Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 Air 9/29/2010 0.011 Air 10/6/2010 0.007 Air 10/1 3/2010 0.007 Air 10/20/2010 0.007 Air 10/27/2010 0.011 Air 11/3/2010 0.009 Air 11/10/2010 0.011 Air 11/17/2010 0.007 Air 11/24/2010 0.014 Air 12/1/2010 0.008 Air 12/8/2010 0.009 Air 12/15/2010 0.008 Air 12/21/2010 0.009 Air 12/29/2010 0.005 3 Air 1/6/2010 0.006 3 Air 1/13/2010 0.007 3 Air 1/20/2010 0.007 3 Air 1/27/2010 0.010 3 Air 2/3/2010 0.008 3 Air 2/10/2010 0.007 3 Air 2/17/2010 0.012 3 Air 2/24/2010 0.012 3 Air 3/3/2010 0.008 3 Air 3/10/2010 0.007 3 Air 3/17/2010 0.012 3 Air 3/24/2010 0.010 3 Air 3/31/2010 0.008 3 Air 4/7/2010 0.006 3 Air 4/15/2010 0.005 3 Air 4/21/2010 0.014 3 Air 4/28/2010 0.006 3 Air 5/5/2010 0.008 3 Air 5/12/2010 0.010 3 Air 5/19/2010 0.006 3 Air 5/26/2010 0.008 3 Air 6/2/2010 0.006 3 Air 6/9/2010 0.004 C-9

APPENDIX C Air Iodine Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 3 Air 6/16/2010 0.006 3 Air 6/23/2010 0.009 3 Air 6/30/2010 0.010 3 Air 7/7/2010 0.006 3 Air 7/14/2010 0.010 3 Air 7/21/2010 0.011 3 Air 7/28/2010 0.008 3 Air 8/4/2010 0.005 3 Air 8/11/2010 0.011 3 Air 8/18/2010 0.002 3 Air 8/25/2010 0.008 3 Air 9/1/2010 0.005 3 Air 9/8/2010 0.006 3 Air 9/15/2010 0.010 3 Air 9/22/2010 0.008 3 Air 9/29/2010 0.011 3 Air 10/6/2010 0.007 3 Air 10/13/2010 0.007 3 Air 10/20/2010 0.007 3 Air 10/27/2010 0.011 3 Air 11/3/2010 0.008 3 Air 11/10/2010 0.011 3 Air 11/17/2010 0.006 3 Air 11/24/2010 0.012 3 Air 12/1/2010 0.008 3 Air 12/8/2010 0.008 3 Air 12/15/2010 0.007 3 Air 12/21/2010 0.009 3 Air 12/29/2010 0.005 4 Air 1/6/2010 0.006 4 Air 1/13/2010 0.007 4 Air 1/20/2010 0.007 4 Air 1/27/2010 0.010 4 Air 2/3/2010 0.008 4 Air 2/10/2010 0.007 4 Air 2/17/2010 0.011 4 Air 2/24/2010 0.012 C-10

APPENDIX C Air Iodine Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 4 Air 3/3/2010 0.008 4 Air 3/10/2010 0.007 4 Air 3/17/2010 0.012 4 Air 3/24/2010 0.010 4 Air 3/31/2010 0.008 4 Air 4/7/2010 0.006 4 Air 4/15/2010 0.005 4 Air 4/21/2010 0.014 4 Air 4/28/2010 0.006 4 Air 5/5/2010 0.008 4 Air 5/12/2010 0.010 4 Air 5/19/2010 0.007 4 Air 5/26/2010 0.008 4 Air 6/2/2010 0.006 4 Air 6/9/2010 0.004 4 Air 6/16/2010 0.006 4 Air 6/23/2010 0.009 4 Air 6/30/2010 0.010 4 Air 7/7/2010 0.006 4 Air 7/14/2010 0.010 4 Air 7/21/2010 0.011 4 Air 7/28/2010 0.008 4 Air 8/4/2010 0.006 4 Air 8/11/2010 0.011 4 Air 8/18/2010 0.002 4 Air 8/25/2010 0.008 4 Air 9/1/2010 0.005 4 Air 9/8/2010 0.006 4 Air 9/15/2010 0.010 4 Air 9/22/2010 0.008 4 Air 9/29/2010 0.011 4 Air 10/6/2010 0.008 4 Air 10/13/2010 0.007 4 Air 10/20/2010 0.007 4 Air 10/27/2010 0.011 4 Air 11/3/2010 0.008 4 Air 11/10/2010 0.010 4 Air 11/17/2010 0.007 C-11

APPENDIX C Air Iodine Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 4 Air 11/24/2010 0.013 4 Air 12/1/2010 0.008 4 Air 12/8/2010 0.009 4 Air 12/15/2010 0.008 4 Air 12/21/2010 0.009 4 Air 12/29/2010 0.005 5 Air 1/6/2010 0.006 5 Air 1/13/2010 0.007 5 Air 1/20/2010 0.006 5 Air 1/27/2010 0.010 5 Air 2/3/2010 0.008 5 Air 2/10/2010 0.007 5 Air 2/17/2010 0.012 5 Air 2/24/2010 0.012 5 Air 3/3/2010 0.008 5 Air 3/10/2010 0.007 5 Air 3/17/2010 0.011 5 Air 3/24/2010 0.010 5 Air 3/31/2010 0.008 5 Air 4/7/2010 0.005 5 Air 4/15/2010 0.005 5 Air 4/21/2010 0.015 5 Air 4/28/2010 0.006 5 Air 5/5/2010 0.008 5 Air 5/12/2010 0.010 5 Air 5/19/2010 0.007 5 Air 5/26/2010 0.008 5 Air 6/2/2010 0.006 5 Air 6/9/2010 0.004 5 Air 6/16/2010 0.006 5 Air 6/23/2010 0.010 5 Air 6/30/2010 0.010 5 Air 7/7/2010 0.007 5 Air 7/14/2010 0.011 5 Air 7/21/2010 0.012 5 Air 7/28/2010 0.008 5 Air 8/4/2010 0.006 C-12

APPENDIX C Air Iodine Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 5 Air 8/11/2010 0.011 5 Air 8/18/2010 0.002 5 Air 8/25/2010 0.008 5 Air 9/1/2010 0.005 5 Air 9/8/2010 0.006 5 Air 9/15/2010 0.011 5 Air 9/22/2010 0.008 5 Air 9/29/2010 0.012 5 Air 10/6/2010 0.008 5 Air 10/13/2010 0.007 5 Air 10/20/2010 0.008 5 Air 10/27/2010 0.011 5 Air 11/3/2010 0.009 5 Air 11/10/2010 0.011 5 Air 11/17/2010 0.007 5 Air 11/24/2010 0.013 5 Air 12/1/2010 0.008 5 Air 12/8/2010 0.009 5 Air 12/15/2010 0.008 5 Air 12/21/2010 0.009 5 Air 12/29/2010 0.005 6 Air 1/6/2010 0.006 6 Air 1/13/2010 0.007 6 Air 1/20/2010 0.007 6 Air 1/27/2010 0.010 6 Air 2/3/2010 0.008 6 Air 2/10/2010 0.007 6 Air 2/17/2010 0.012 6 Air 2/24/2010 0.012 6 Air 3/3/2010 0.008 6 Air 3/10/2010 0.007 6 Air 3/17/2010 0.012 6 Air 3/24/2010 0.010 6 Air 3/31/2010 0.008 6 Air 4/7/2010 0.006 6 Air 4/15/2010 0.005 6 Air 4/21/2010 0.014 C-13

APPENDIX C Air Iodine Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 6 Air 4/28/2010 0.006 6 Air 5/5/2010 0.008 6 Air 5/12/2010 0.010 6 Air 5/19/2010 0.007 6 Air 5/26/2010 0.008 6 Air 6/2/2010 0.006 6 Air 6/9/2010 0.004 6 Air 6/16/2010 0.006 6 Air 6/23/2010 0.010 6 Air 6/30/2010 0.011 6 Air 7/7/2010 0.007 6 Air 7/14/2010 0.011 6 Air 7/21/2010 0.012 6 Air 7/28/2010 0.008 6 Air 8/4/2010 0.006 6 Air 8/11/2010 0.012 6 Air 8/18/2010 0.002 6 Air 8/25/2010 0.009 6 Air 9/1/2010 0.005 6 Air 9/8/2010 0.006 6 Air 9/15/2010 0.010 6 Air 9/22/2010 0.008 6 Air 9/29/2010 0.012 6 Air 10/6/2010 0.008 6 Air 10/13/2010 0.007 6 Air 10/20/2010 0.008 6 Air 10/27/2010 0.012 6 Air 11/3/2010 0.008 6 Air 11/10/2010 0.011 6 Air 11/17/2010 0.007 6 Air 11/24/2010 0.013 6 Air 12/1/2010 0.008 6 Air 12/8/2010 0.009 6 Air 12/15/2010 0.008 6 Air 12/21/2010 0.009 6 Air 12/29/2010 0.005 7 Air 1/6/2010 < 0.006 C- 14

APPENDIX C Air Iodine Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 7 Air 1/13/2010 0.007 7 Air 1/20/2010 0.007 7 Air 1/27/2010 0.010 7 Air 2/3/2010 0.008 7 Air 2/10/2010 0.008 7 Air 2/17/2010 0.012 7 Air 2/24/2010 0.013 7 Air 3/3/2010 0.008 7 Air 3/10/2010 0.008 7 Air 3/17/2010 0.012 7 Air 3/24/2010 0.011 7 Air 3/31/2010 0.009 7 Air 4/7/2010 0.006 7 Air 4/15/2010 0.005 7 Air 4/21/2010 0.014 7 Air 4/28/2010 0.006 7 Air 5/5/2010 0.008 7 Air 5/12/2010 0.010 7 Air 5/19/2010 0.007 7 Air 5/26/2010 0.008 7 Air 6/2/2010 0.006 7 Air 6/9/2010 0.005 7 Air 6/16/2010 0.006 7 Air 6/23/2010 0.009 7 Air 6/30/2010 0.010 7 Air 7/7/2010 0.006 7 Air 7/14/2010 0.011 7 Air 7/21/2010 0.012 7 Air 7/28/2010 0.008 7 Air 8/4/2010 0.006 7 Air 8/11/2010 0.011 7 Air 8/18/2010 0.002 7 Air 8/25/2010 0.009 7 Air 9/1/2010 0.005 7 Air 9/8/2010 0.006 7 Air 9/15/2010 0.010 7 Air 9/22/2010 0.008 7 Air 9/29/2010 0.012 C-15

APPENDIX C Air Iodine Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 7 Air 10/6/2010 0.008 7 Air 10/13/2010 0.007 7 Air 10/20/2010 0.008 7 Air 10/27/2010 0.011 7 Air 11/3/2010 0.009 7 Air 11/10/2010 0.012 7 Air 11/17/2010 0.007 7 Air 11/24/2010 0.013 7 Air 12/1/2010 0.008 7 Air 12/8/2010 0.009 7 Air 12/15/2010 0.008 7 Air 12/21/2010 0.010 7 Air 12/29/2010 0.005 35 Air 1/6/2010 0.008 35 Air 1/13/2010 0.011 35 Air 1/20/2010 0.008 35 Air 1/27/2010 0.007 35 Air 2/3/2010 0.005 35 Air 2/10/2010 0.008 35 Air 2/17/2010 0.010 35 Air 2/24/2010 0.005 35 Air 3/3/2010 0.010 35 Air 3/10/2010 0.012 35 Air 3/17/2010 0.015 35 Air 3/24/2010 0.013 35 Air 3/31/2010 0.009 35 Air 4/7/2010 0.010 35 Air 4/15/2010 0.013 35 Air 4/21/2010 0.013 35 Air 4/28/2010 0.008 35 Air 5/5/2010 0.006 35 Air 5/12/2010 0.006 35 Air 5/19/2010 0.007 35 Air 5/26/2010 0.007 35 Air 6/2/2010 0.005 35 Air 6/9/2010 0.010 35 Air 6/16/2010 0.010 C-16

Air Iodine Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date 1-131 35 Air 6/23/2010 0.014 35 Air 6/30/2010 0.011 35 Air 7/7/2010 0.006 35 Air 7/14/2010 0.007 35 Air 7/21/2010 0.013 35 Air 7/28/2010 0.008 35 Air 8/4/2010 0.005 35 Air 8/11/2010 0.005 35 Air 8/18/2010 0.004 35 Air 8/25/2010 0.006 35 Air 9/1/2010 0.006 35 Air 9/8/2010 0.015 35 Air 9/15/2010 0.008 35 Air 9/22/2010 0.009 35 Air 9/29/2010 0.014 35 Air 10/6/2010 0.004 35 Air 10/13/2010 0.013 35 Air 10/20/2010 0.009 35 Air 10/27/2010 0.011 35 Air 11/3/2010 0.008 35 Air 11/10/2010 0.012 35 Air 11/17/2010 0.011 35 Air 12/1/2010 0.009 35 Air 12/8/2010 0.011 35 Air 12/15/2010 0.012 35 Air 12/21/2010 0.012 35 Air 12/29/2010 0.010 C-17

APPENDIX C Fish Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Annually Results in pCi/kg wet +/- 2 Sigma Location Sample Type Collection Date Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 Mn-54 Zn-65 25 freshwater drum 9/11/2010 < 15.30 < 12.26

  • 14.36 < 10.30
  • 33.65 922.63 +/- 255.50 < 16.78
  • 24.49 1,350.00 +/- 293.40 < 7.53
  • 11.48 32 freshwater drum 9/11/2010 < 11.38 < 10.88
  • 11.28 < 10.02
  • 27.08 768.97 +/- 216.50 < 9.87
  • 11.69 < 11.13 K 47.87 1,223.80 +/- 401.50 < 9.49
  • 19.53 C-18

APPENDIX C Food Products Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/kg wet +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 2Location 2 beet greens 7/27/2010 786.25 +/- 170.70 < 14.40 < 12.55 13.90 15.54

< 24.53 7,245.90 +/-461.70 2 swiss chard 7/27/2010 383.12+/- 108.00 < 12.32 < 9.09 9.11 11.81

< 22.04 5,212.60 +/-365.10 2 turnip greens 7/27/2010 1,054.30 +/-188.30 < 9.60 < 8.61 10.44 13.66

< 21.27 5,662.00 +/-423.90 2 swiss chard 8/10/2010 < 134.98 < 13.33 < 5.47 12.72 15.54

< 18.18 6,373.40+/-428.90 2 turnip greens 8/10/2010 199.71 +/- 97.32 < 5.57 < 6.91 9.32 8.37

< 19.54 4,018.90 +/- 291.40 2 swiss chard 9/14/2010 < 126.29 < 10.81 < 10.67 12.58 11.09

< 26.82 5,606.50 +/- 403.70 2 turnip greens 9/14/2010 421.04+/- 154.80 < 11.80 < 12.47 11.16 14.01

< 26.38 5,836.60+/-447.10 2 swiss chard 10/12/2010 1,278.20 +/- 158.40 < 9.26 < 9.48 10.03 5.39

< 15.69 5,069.90 +/- 392.90 2 tumip greens 10/12/2010 1,504.30 +/- 184.90 < 8.72 < 9.54 12.51 11.67

< 24.25 5,181.80 +/- 369.30 16 collard greens 7/27/2010 374.15 +/- 150.40 < 6.84 < 11.21 < 7.20 < 8.21

< 21.08 4,629.70+/- 358.10 C-19

APPENDIX C Food Products Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/kg wet +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 16 turnip greens 7/27/2010 665.52 +/- 127.30 < 7.44 < 9.48 < 7.07 < 8.54

< 43.65 5,549.60 +/-/- 321.30 collard greens 8/10/2010 < 145.71 < 11.29 < 9.62 < 9.01 < 10.09

< 18.80 3,518.30 /-331.70 swiss chard 8/10/2010 189.07+/- 100.50 < 10.54 < 9.69 < 8.66 < 9.69

< 18.71 6,989.40 +/- 363.80 turnip greens 8/10/2010 241.00+/-98.96 < 8.26 < 10.10 < 7.97 < 8.65

< 18.13 6,601.30+/-385.10 collard greens 9/14/2010 < 129.08 < 12.89 < 9.29 < 9.92 < 11.51

< 19.51 4,313.10+/-393.70 swiss chard 9/14/2010 < 164.53 < 11.78 < 10.53 < 14.52 < 15.95

< 36.15 6,535.10+/-467.10 turnip greens 9/14/2010 369.60+/- 160.30 < 10.25 < 18.36 < 16.03 < 12.60

< 28.19 6,354.00+/-480.10 collard greens 10/12/2010 867.80 +/- 162.72 < 5.91 < 8.29 < 8.61 < 7.83

< 16.82 3,391.75 +/- 265.74 turnip greens 10/12/2010 1,003.80 +/- 127.00 < 6.36 < 5.87 < 7.98 < 8.00

< 15.85 5,628.40 +/- 329.60 18 collard greens 7/27/2010 150.16 +/- 75.03 < 5.46 < 9.11 < 7.58 < 9.62

< 17.49 4,919.40 +/- 309.50 C-20

APPENDIX C Food Products Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/kg wet +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 18 swiss chard 7/27/2010 436.97 +/- 115.00 < 10.38 < 8.91

  • 7.80
  • 11.35

< 20.92 8,684.00 +/-/- 408.40 18 collard greens 8/10/2010 < 101.41 < 13.53 < 8.90

  • 13.32
  • 9.76

< 25.09 6,160.20 /-405.90 18 swiss chard 8/10/2010 234.38 +/-110.30 < 7.78 < 7.87

  • 8.24
  • 9.34

< 12.70 8,024.50 /-420.10 18 collard greens 9/14/2010 < 146.36 < 12.54 < 14.07

  • 5.90
  • 12.30

< 29.48 5,777.50 +/- 437.80 18 swiss chard 9/14/2010 < 159.20 < 12.13 < 13.48

  • 13.57
  • 15.54

< 26.26 8,637.15 +/- 423.72 18 turnip greens 9/14/2010 416.15 +/- 165.20 < 13.15 < 15.16

  • 15.71
  • 15.13

< 32.49 7,981.40 +/- 508.10 18 swiss chard 10/12/2010 783.06 +/- 136.20 < 6.74 < 8.32

  • 9.97
  • 11.17

< 18.35 6,281.00 +/- 403.50 18 turnip greens 10/12/2010 905.36 +/- 106.50 < 7.56 < 5.89

  • 7.43
  • 7.85

< 18.31 5,288.60+/-301.00 20 turnip greens 7/27/2010 117.52 +/- 62.87 < 5.57 5.70 5.44 6.54

  • 9.94 4,096.20 +/- 293.70 20 collard greens 8/10/2010
  • 101.80 < 8.13 9.50 8.39 9.02
  • 14.98 4,567.60 +/- 354.20 C-21

APPENDIX C Food Products Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/kg wet +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 20 turnip greens 8/10/2010 206.68 +/- 102.30 < 8.02 < 6.87 7.68 11.93

< 13.05 5,234.80 +/-/- 330.00 20 collard greens 9/14/2010 < 120.68 < 9.43 < 11.20 9.79 11.71

< 25.31 4,348.50 +/-354.40 20 turnip greens 9/14/2010 357.86 +/- 165.90 < 12.85 < 14.10 9.15 19.39

< 29.36 7,579.30 +/- 509.50 20 collard greens 10/12/2010 267.12+/-97.77 < 6.76 < 11.23 8.54 8.41

< 22.60 4,374.70 +/-/- 270.90 20 turnip greens 10/12/2010 1,254.30 +/- 104.20 < 6.23 < 7.12 6.74 7.21

< 19.06 5,037.20 /-212.50 37 beet greens 7/27/2010 429.00 +/- 133.00 < 6.70 < 9.05 4.63 12.76

< 19.50 5,604.90 +/-410.10 37 swiss chard 7/27/2010 279.79 +/- 120.80 < 5.74 < 7.04 6.13 8.75

< 14.10 3,504.40 +/- 287.30 37 turnip greens 7/27/2010 375.01 +/- 139.10 < 6.05 < 12.31 10.03 12.62

< 26.15 4,668.50 /-332.70 37 collard greens 8/10/2010 < 126.36 < 7.71 < 13.17 11.68 12.25

< 16.51 3,938.20 /-338.40 37 swiss chard 8/10/2010 363.15 +/- 127.00 < 7.60 < 12.28 10.18 14.95

< 23.00 3,604.00 +/-/- 314.40 C-22

APPENDIX C Food Products Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/kg wet +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 37 turnip greens 8/10/2010 < 124.94 < 5.96 < 8.81 < 6.83 < 9.97

< 16.06 4,059.90 +/-/- 320.60 37 collard greens 9/14/2010 < 102.15 < 6.70 < 9.80 < 9.09 < 10.71

< 29.25 3,544.10 +/- 306.70 37 swiss chard 9/14/2010 237.79 +/- 96.38 < 10.13 < 7.72 < 6.62 < 11.56

< 17.01 4,825.80 +/- 327.80 37 turnip greens 9/14/2010 < 154.06 < 13.20 < 9.41 < 12.06 < 12.95

< 39.53 4,281.00 +/- 379.20 37 swiss chard 10/12/2010 867.23 +/- 115.10 < 8.48 < 6.70 < 7.88 < 7.65

< 25.44 3,711.50 /-224.00 37 turnip greens 10/12/2010 969.61 +/- 91.63 < 7.33 < 8.08 < 5.57 < 7.82

< 16.68 4,182.80+/-216.10 70 collard greens 7/27/2010 < 91.25 < 9.20 < 8.12 < 11.02 < 7.20

< 13.39 5,130.60 +/-/- 360.30 70 swiss chard 7/27/2010 324.67 +/- 184.50 < 21.68 < 15.79 < 15.74 < 10.51

< 37.78 8,330.60 +/-/- 708.00 70 turnip greens 7/27/2010 590.01 +/- 186.20 < 12.54 < 7.97 < 13.95 < 14.03

< 23.08 5,669.50 +/-/- 422.30 70 beet greens 8/10/2010 < 113.72 < 9.05 < 10.62 < 7.13 < 7.07

< 24.29 7,854.80 +/- 383.70 C-23

APPENDIX C Food Products Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/kg wet +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 70 collard greens 8/10/2010 < 73.53 < 7.67 < 8.07 < 7.89 < 9.67

< 15.03 4,179.80 +/-277.70 70 turnip greens 8/10/2010 336.50 +/- 108.80 < 8.80 < 10.31 < 11.49 < 8.15

< 14.69 5,034.20 /-371.00 70 collard greens 9/14/2010 < 104.21 < 12.79 < 9.25 < 9.14 < 12.36

< 18.77 3,872.90 /-313.40 70 swiss chard 9/14/2010 346.25 +/- 141.60 < 11.65 < 13.02 < 10.05 < 14.23

< 22.42 7,945.90 +/-442.60 70 turnip greens 9/14/2010 424.51 +/- 124.70 < 8.76 < 7.26 < 11.53 < 10.78

< 24.26 4,964.80+/-411.00 70 swiss chard 10/12/2010 701.50 +/- 110.60 < 6.39 < 8.35 < 7.36 < 9.66

< 18.33 7,664.40 +/- 335.60 70 turnip greens 10/12/2010 2,347.20 +/- 128.10 < 7.95 < 6.16 < 6.32 < 7.76

< 18.15 5,327.00 +-234.50 C-24

APPENDIX C Milk Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date Ba- 140 Cs- 134 Cs-137 K-40 La-140 I1R Milk 4/5*/20I10 < 11 < 3* < 3 1315'*+/- 104 <3 Milk 4/19/2010 < 20 < 4 < 3 1,413 +/- 115 < 3 Milk 5/3/2010 < 1t < 3 < 4 1,433 +/-/- 113 < 2 Milk 5/17/2010 < 9 < 4 < 3 1,617+/- 124 < 2 Milk 6/7/2010 < 20 < 4 < 4 1,704 +/- 125 < 4 Milk 6/21/2010 < 12 < 4 < 4 1,471 +/- 109 < 2 Milk 7/6/2010 < 23 < 3 < 2 1,490 +/- 113 < 4 Milk 7/19/2010 < 19 < 2 < 5 1,478 +/- 121 < 3 Milk 8/2/2010 < 19 < 3 < 4 1,515 +/- 121 < 2 Milk 8/16/2010 < 17 < 3 < 3 1,418 +/- 111 < 3 Milk 9/7/2010 < 27 < 4 < 4 1,506 +/- 123 < 4 C-25

APPENDIX C Milk Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date Ba-140 Cs-134 Cs-137 K-40 La-140 18 Milk 9/20/2010 < 19 < 3 < 4 1 599+/-124 < 4 18 Milk 10/4/2010 < 23 < 2 < 5 1,492 +/- 114 < 3 18 Milk 10/18/2010 < 18 < 3 < 4 1,650 +/- 123 < 2 18 Milk 11/1/2010 < 17 < 4 < 3 1,745 +/- 122 < 3 18 Milk 12/6/2010 < 16 < 3 < 4 1,728 +/- 121 < 2 41 Milk 4/5/2010 < 18 < 3 < 4 1,645 +/- 116 < 4 41 Milk 4/20/2010 < 13 < 3 < 3 1,697 +/- 127 < 2 41 Milk 5/3/2010 < 13 < 2 < 3 1,630 +/- 92 < 2 41 Milk 5/17/2010 < 13 < 3 < 4 1,665 +/- 125 < 2 41 Milk 6/7/2010 < 13 < 3 < 4 1,671 +/- 124 < 3 C-26

APPENDIX C Milk Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date Ba-140 Cs-134 Cs-137 K-40 La-140 Milk 6/21/2010 < 18 < 3 < 5 1,668 +/- 129 < 2 Milk 7/6/2010 < 20 < 3 < 4 1,658 +/- 111 < 4 Milk 7/19/2010 < 18 < 4 < 5 1,807 +/- 131 < 3 Milk 8/2/2010 < 15 < 3 < 3 1,793 +/- 115 < 4 Milk 8/16/2010 < 17 < 3 < 4 1,753 +/- 88 < 3 Milk 9/7/2010 < 30 < 3 < 4 1,912 +/- 138 < 6 Milk 9/20/2010 < 21 < 3 < 3 1,865 +/- 125 < 4 Milk 10/4/2010 < 14 < 3 < 5 1,757 +/- 127 < 2 Milk 1/4/2010 < 22 < 3 < 4 1,050 +/- 94 < 2 Milk 2/1/2010 < 12 < 3 < 4 1,183 +/- 113 < 3 C-27

APPENDIX C Milk Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date Ba-140 Cs-134 Cs-137 K-40 La-140 Milk 3/1/2010 < 14 < 3 < 3 761 +/- 90 < 2 Milk 4/5/2010 < 11 < 3 < 2 915 +/- 90 < 2 Milk 4/19/2010 < 11 < 3 < 3 913 +/- 88 < 3 Milk 5/3/2010 < 24 < 4 < 4 932-+/- 106 < 4 Milk 5/17/2010 < 11 < 2 < 3 928 +/- 87 < 2 Milk 6/7/2010 < 19 < 2 < 3 876 +/- 90 < 3 Milk 6/21/2010 < 18 < 3 < 2 1,171 +/- 104 < 3 Milk 7/6/2010 < 24 < 2 < 3 1,167 +/- 106 < 4 Milk 7/19/2010 < 15 < 3 < 3 1,069 +/- 106 < 2 Milk 8/2/2010 < 17 < 3 < 2 1,563 +/- 122 < 3 Milk 8/16/2010 < 24 < 3 < 3 1,045 +/- 87 < 6 C-28

APPENDIX C Milk Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date Ba-140 Cs-134 Cs-137 K-40 La-140 Milk 9/7/2010 < 19 < 3 < 3 927 +/- 99 < 4 Milk 9/20/2010 < 15 < 3 < 5 1,250 +/- 81 < 2 Milk 10/4/2010 < 23 < 2 < 2 892 +/- 75 < 5 Milk 10/18/2010 < 21 < 4 < 3 690 +/- 89 < 7 Milk 11/1/2010 < 14 < 3 < 3 1,127 +/- 98 < 3 Milk 12/6/2010 < 17 < 4 < 2 838+/- 101 < 3 Milk 5/3/2010 < 16 < 3 < 3 1,643 +/-90 < 3 Milk 5/17/2010 < 41 < 1 < 1 1,576+/-36 < 9 Milk 6/7/2010 < 19 < 3 < 4 1,743 +/- 115 < 2 Milk 6/21/2010 < 18 < 3 < 4 1,692 +/- 123 < 3 C-29

APPENDIX C Milk Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date Ba-140 Cs-134 Cs-137 K-40 La-140 61 Milk 7/6/2010 < 28 < 2 < 2 1,877 +/- 122 < 4 61 Milk 7/19/2010 < 18 < 4 < 4 1,903 120 1/- < 2 61 Milk 8/2/2010 < 28 < 4 < 4 1,861 +/-96 < 2 61 Milk 8/16/2010 < 27 < 4 < 4 1,984 +/- 126 < 6 61 Milk 9/7/2010 < 29 < 3 < 4 1,823 +/- 128 < 5 61 Milk 9/20/2010 < 22 < 4 < 5 1,933 +/- 134 < 3 61 Milk 10/4/2010 < 43 < 3 < 3 1,386 +/- 101 < 9 C-30

Milk Iodine Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date 1-131 18 Milk 1/4/2010 18 Milk 4/5/2010 0.32 18 Milk 4/19/2010 0.35 18 Milk 5/3/2010 0.34 18 Milk 5/17/2010 0.29 18 Milk 6/7/2010 0.21 18 Milk 6/21/2010 0.30 18 Milk 7/6/2010 0.21 18 Milk 7/19/2010 0.37 18 Milk 8/2/2010 0.24 18 Milk 8/16/2010 0.22 18 Milk 9/7/2010 0.30 18 Milk 9/20/2010 0.40 18 Milk 10/4/2010 0.17 18 Milk 10/18/2010 0.39 18 Milk 11/1/2010 0.27 18 Milk 12/6/2010 0.18 41 Milk 4/5/2010 0.34 41 Milk 4/20/2010 0.30 41 Milk 5/3/2010 0.34 41 Milk 5/17/2010 0.34 41 Milk 6/7/2010 0.22 41 Milk 6/21/2010 0.28 41 Milk 7/6/2010 0.21 41 Milk 7/19/2010 0.40 41 Milk 8/2/2010 0.27 41 Milk 8/16/2010 0.30 41 Milk 9/7/2010 0.43 41 Milk 9/20/2010 0.15 41 Milk 10/4/2010 0.50 41 Milk 10/18/2010 51 Milk 1/4/2010 0.25 51 Milk 2/1/2010 0.30 51 Milk 3/1/2010 0.41 51 Milk 4/5/2010 0.32 51 Milk 4/19/2010 0.26 C-3 1

Milk Iodine Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date 1-131 Milk 5/3/2010 0.30 Milk 5/17/2010 0.37 Milk 6/7/2010 0.29 Milk 6/21/2010 0.31 Milk 7/6/2010 0.23 Milk 7/19/2010 0.35 Milk 8/2/2010 0.20 Milk 8/16/2010 0.23 Milk 9/7/2010 0.32 Milk 9/20/2010 0.31 Milk 10/4/2010 0.28 Milk 10/18/2010 0.42 Milk 11/1/2010 0.27 Milk 12/6/2010 0.19 Milk 5/3/2010 0.35 Milk 5/17/2010 0.46 Milk 6/7/2010 0.28 Milk 6/21/2010 0.32 Milk 7/6/2010 0.32 Milk 7/19/2010 0.33 Milk 8/2/2010 0.25 Milk 8/16/2010 0.20 Milk 9/7/2010 0.40 Milk 9/20/2010 0.22 Milk 10/4/2010 0.23 Milk 10/18/2010 C-32

APPENDIX C Sediment Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Annually Results in pCi/kg dry +/- 2 Sigma Location Sample Type Collection Date Co-58 Co-60 Cs-134 Cs-137 K-40 25 Sediment 5/25/2010 < 25.79 < 16.03 < 17.24 147.48 +/- 20.85 13.586.00 +/- 585.40 25 Sediment 9/29/2010 < 29.99 < 8.82 < 18.24 LLD 11,314.00 +/- 640.30 26 Sediment 5/25/2010 < 16.76 < 7.90 < 12.46 LLD 13,459.00 +/-574.70 26 Sediment 9/29/2010 < 27.44 < 5.46 < 14.16 LLD 13,747.50 +/-525.78 27 Sediment 5/25/2010 < 20.06 < 12.27 < 12.98 138.18 +/-26.06 15,412.00 /-577.60 27 Sediment 9/29/2010 < 42.10 < 20.76 < 29.71 222.23 /-43.80 16,592.00 +/-/-800.30 32 Sediment 5/25/2010 < 42.84 < 21.29 < 26.61 737.85 +/-57.64 25,290.00 +/-915.60 32 Sediment 9/29/2010 < 44.27 < 23.74 < 26.59 634.02 +/-32.58 23,003.00 /-726.60 64 Sediment 5/26/2010 < 16.52 < 4.33 < 9.78 < 10.99 9,059.30 +/- 457.30 C-33

APPENDIX C Sediment Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Annually Results in pCi/kg dry +/- 2 Sigma Location Sample Type Collection Date Co-58 Co-60 Cs-134 Cs-137 K-40 64 Sediment 10/11/2010 < 7.81 < 14.20 < 9.20 < 11.07 8,969.30 +/- 473.80 65 Sediment 5/26/2010 < 11.62 < 12.68 < 11.28 < 11.52 9,122.60 +/- 464.30 65 Sediment 10/11/2010 < 14.37

  • 5.04 < 9.44 < 11.07 10,537.00 +/- 537.50 C-34

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in mR/91 days +/- 2 Sigma Location Sample Type Collection Period Exposure TLD 1/13/2010 4/6/2010 10.48 1.13 TLD 4/6/2010 7/15/2010 9.91 1.17 TLD 7/15/2010 10/19/2010 11.38 0.96 TLD 10/19/2010 1/5/2011 11.13 1.12 3 TLD 1/13/2010 4/6/2010 11.00 0.85 3 TLD 4/6/2010 7/15/2010 11.56 0.89 3 TLD 7/15/2010 10/19/2010 12.15 0.99 3 TLD 10/19/2010 1/5/2011 13.08 1.01 4 TLD 1/13/2010 4/6/2010 11.83 1.01 4 TLD 4/6/2010 7/15/2010 12.17 0.95 4 TLD 7/15/2010 10/19/2010 12.85 0.83 4 TLD 10/19/2010 1/5/2011 13.99 0.87 5 TLD 1/13/2010 4/6/2010 11.38 1.22 5 TLD 4/6/2010 7/15/2010 12.26 0.72 5 TLD 7/15/2010 10/19/2010 11.86 0.95 5 TLD 10/19/2010 1/5/2011 13.59 0.65 6 TLD 1/13/2010 4/6/2010 12.36 1.04 6 TLD 4/6/2010 7/15/2010 13.45 0.70 6 TLD 7/15/2010 10/19/2010 14.17 1.08 6 TLD 10/19/2010 1/5/2011 15.20 0.80 7 TLD 1/13/2010 .4/6/2010 11.07 0.83 7 TLD 4/6/2010 7/15/2010 12.85 1.01 7 TLD 7/15/2010 10/19/2010 12.87 0.64 7 TLD 10/19/2010 1/5/2011 14.64 1.00 8 TLD 1/13/2010 4/6/2010 10.93 0.81 8 TLD 4/6/2010 7/15/2010 12.11 0.53 8 TLD 7/15/2010 10/19/2010 12.28 0.74 8 TLD 10/19/2010 1/5/2011 13.23 0.62 9 TLD 1/13/2010 4/6/2010 10.50 0.80 9 TLD 4/6/2010 7/15/2010 11.70 0.82 9 TLD 7/15/2010 10/19/2010 12.23 0.67 9 TLD 10/19/2010 1/5/2011 13.32 0.88 C-35

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in mR/91 days +/- 2 Sigma Location Sample Type Collection Period Exposure 10 TLD 1/13/2010 4/6/2010 13.79 1.87 10 TLD 4/6/2010 7/15/2010 15.56 1.16 10 TLD 7/15/2010 10/19/2010 14.37 0.73 10 TLD 10/19/2010 1/5/2011 16.75 1.13 11 TLD 1/13/2010 4/6/2010 13.22 0.95 11 TLD 4/6/2010 7/15/2010 13.33 0.58 11 TLD 7/15/2010 10/19/2010 14.48 0.76 11 TLD 10/19/2010 1/5/2011 14.70 0.66 12 TLD 1/13/2010 4/6/2010 12.10 0.96 12 TLD 4/6/2010 7/15/2010 12.63 0.91 12 TLD 7/15/2010 10/19/2010 14.00 1.15 12 TLD 10/19/2010 1/5/2011 13.78 1.20 13 TLD 1/13/2010 4/6/2010 12.72 0.97 13 TLD 4/6/2010 7/15/2010 12.71 0.88 13 TLD 7/15/2010 10/19/2010 13.69 0.91 13 TLD 10/19/2010 1/5/2011 13.33 1.09 14 TLD 1/13/2010 4/6/2010 10.98 1.08 14 TLD 4/6/2010 7/15/2010 11.94 0.68 14 TLD 7/15/2010 10/19/2010 11.68 0.79 14 TLD 10/19/2010 1/5/2011 12.55 0.86 15 TLD 1/13/2010 4/6/2010 10.66 0.89 15 TLD 4/6/2010 7/15/2010 8.07 0.67 15 TLD 7/15/2010 10/19/2010 11.15 0.90 15 TLD 10/19/2010 1/5/2011 8.73 0.81 21 TLD 1/13/2010 4/6/2010 12.71 0.86 21 TLD 4/6/2010 7/15/2010 13.95 1.11 21 TLD 7/15/2010 10/19/2010 14.48 0.86 21 TLD 10/19/2010 1/5/2011 14.14 0.88 23 TLD 1/13/2010 4/6/2010 14.22 0.98 23 TLD 4/6/2010 7/15/2010 14.17 0.62 23 TLD 7/15/2010 10/19/2010 14.90 0.88 23 TLD 10/19/2010 1/5/2011 14.34 0.69 C-36

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in mRI91 days +/- 2 Sirma Location Sample Type Collection Period Exposure 24 TLD 1/13/2010 to 4/6/2010 11.88 0.86 24 TLD 4/6/2010 to 7/15/2010 12.40 0.67 24 TLD 7/15/2010 to 10/19/2010 12.56 H/- 0.68 24 TLD 10/19/2010 to 1/5/2011 13.31 0.92 29 TLD 1/13/2010 4/6/2010 15.32 1.16 29 TLD 4/6/2010 7/15/2010 16.27 0.76 29 TLD 7/15/2010 10/19/2010 16.81 1.13 29 TLD 10/19/2010 1/5/2011 16.42 1.02 30 TLD 1/13/2010 4/6/2010 14.00 1.08 30 TLD 4/6/2010 7/15/2010 15.65 0.62 30 TLD 7/15/2010 10/19/2010 15.65 0.72 30 TLD 10/19/2010 1/5/2011 15.80 0.54

+/-

31 TLD 1/13/2010 4/6/2010 14.33 1.15 31 TLD 4/6/2010 7/15/2010 17.20 0.68 31 TLD 7/15/2010 10/19/2010 16.49 0.87 31 TLD 10/19/2010 1/5/2011 17.93 1.18 33 TLD 1/13/2010 4/6/2010 15.87 1.29 33 TLD 4/6/2010 7/15/2010 18.53 0.67 33 TLD 7/15/2010 10/19/2010 17.99 1.05 33 TLD 10/19/2010 1/5/2011 18.60 0.80 35 TLD 1/13/2010 4/6/2010 11.26 0.82 35 TLD 4/6/2010 7/15/2010 12.41 0.61 35 TLD 7/15/2010 10/19/2010 12.54 0.70 35 TLD 10/19/2010 1/5/2011 12.97 0.74 36 TLD 1/13/2010 4/6/2010 14.69 1.21 36 TLD 4/6/2010 7/15/2010 16.21 0.63 36 TLD 7/15/2010 10/19/2010 16.54 1.16 36 TLD 10/19/2010 1/5/2011 17.34 0.67 53 TLD 1/13/2010 4/6/2010 12.20 0.98 53 TLD 4/6/2010 7/15/2010 13.66 1.01 53 TLD 7/15/2010 10/19/2010 13.88 1.07 C-37

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in mR/91 days +/- 2 Sigma Location Sample Type Collection Period Exposure 53 TLD 10/19/2010 to 1/5/2011 14.63 +/- 1.04 54 TLD 1/13/2010 to 4/6/2010 11.69 1.14 54 TLD 4/6/2010 to 7/15/2010 12.50 0.58 54 TLD 7/15/2010 to 10/19/2010 12.81 0.98 54 TLD 10/19/2010 to 1/5/2011 13.64 0.57 55 TLD 1/13/2010 to 4/6/2010 11.19 1.78 55 TLD 4/6/2010 to 7/15/2010 13.84 +/- 0.82 55 TLD 7/15/2010 to 10/19/2010 14.27 1.40 55 TLD 10/19/2010 to 1/5/2011 14.60 0.79 56 TLD 1/13/2010 to 4/6/2010 11.91 1.10 56 TLD 4/6/2010 to 7/15/2010 13.59 1.00 56 TLD 7/15/2010 to 10/19/2010 13.04 0.80 56 TLD 10/19/2010 to 1/5/2011 14.45 1.47 58 TLD 1/13/2010 to 4/6/2010 9.71 0.81 58 TLD 4/6/2010 to 7/15/2010 11.26 0.56 58 TLD 7/15/2010 to 10/19/2010 11.00 0.67 58 TLD 10/19/2010 to 1/5/2011 11.81 0.88 C-38

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in mR/91 days +/- 2 Sigma Location Sample Type Collection Period Exposure TLB 1/13/2010 4/6/2010 10.08 1.47 TLB 4/6/2010 7/15/2010 10.52 1.09 TLB 7/15/2010 10/19/2010 10.38 1.00 TLB 10/19/2010 1/5/2011 10.57 1.24 TLB 1/13/2010 4/6/2010 11.48 0.84 TLB 4/6/2010 7/15/2010 10.78 1.01 TLB 7/15/2010 10/19/2010 12.18 0.54 TLB 10/19/2010 1/5/2011 11.02 1.25 TLB 1/13/2010 4/6/2010 13.39 1.47 TLB 4/6/2010 7/15/2010 13.95 1.01 TLB 7/15/2010 10/19/2010 13.15 0.60 TLB 10/19/2010 1/5/2011 13.86 1.12 TLB 1/13/2010 4/6/2010 12.77 0.86 TLB 4/6/2010 7/15/2010 12.81 0.93 TLB 7/15/2010 10/19/2010 12.79 0.62 TLB 10/19/2010 1/5/2011 12.47 0.96 TLB 1/13/2010 4/6/2010 12.39 0.87 TLB 4/6/2010 7/15/2010 14.08 0.75 TLB 7/15/2010 10/19/2010 13.19 0.87 TLB 10/19/2010 1/5/2011 13.38 0.59 TLB 1/13/2010 4/6/2010 13.26 0.80 TLB 4/6/2010 7/15/2010 15.53 0.90 TLB 7/15/2010 10/19/2010 14.00 0.83 TLB 10/19/2010 1/5/2011 14.73 0.98 TLB 1/13/2010 4/6/2010 12.22 0.82 TLB 4/6/2010 7/15/2010 13.15 0.82 TLB 7/15/2010 10/19/2010 12.66 0.60 TLB 10/19/2010 1/5/2011 12.74 0.94 TLB 1/13/2010 4/6/2010 11.84 0.78 TLB 4/6/2010 7/15/2010 13.74 1.77 TLB 7/15/2010 10/19/2010 12.61 0.63 TLB 10/19/2010 1/5/2011 12.60 0.78 C-39

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in mR/91 days +/- 2 Sigma Location Sample Type Collection Period Exposure TLB 1/13/2010 4/6/2010 13.88 0.81 TLB 4/6/2010 7/15/2010 16.63 0.72 TLB 7/15/2010 10/19/2010 14.65 0.70 TLB 10/19/2010 1/5/2011 14.87 0.81 TLB 1/13/2010 4/6/2010 11.99 0.85 TLB 4/6/2010 7/15/2010 15.00 0.92 TLB 7/15/2010 10/19/2010 13.82 1.23 TLB 10/19/2010 1/5/2011 13.28 0.88 TLB 1/13/2010 4/6/2010 12.56 0.61 TLB 4/6/2010 7/15/2010 14.27 0.79 TLB 7/15/2010 10/19/2010 13.56 0.61 TLB 10/19/2010 1/5/2011 12.90 1.17 TLB 1/13/2010 4/6/2010 12.30 +/- 0.59 TLB 4/6/2010 7/15/2010 13.63 1.35 TLB 7/15/2010 10/19/2010 12.97 0.59 TLB 10/19/2010 1/5/2011 12.35 1.38 TLB 1/13/2010 4/6/2010 10.33 0.83 TLB 4/6/2010 7/15/2010 13.22 0.87 TLB 7/15/2010 10/19/2010 10.93 0.58 TLB 10/19/2010 1/5/2011 11.56 0.77 TLB 1/13/2010 4/6/2010 9.71 0.75 TLB 4/6/2010 7/15/2010 11.42 1.00 TLB 7/15/2010 10/19/2010 10.52 0.90 TLB 10/19/2010 1/5/2011 10.50 0.76 TLB 1/13/2010 4/6/2010 13.67 1.30 TLB 4/6/2010 7/15/2010 15.64 1.21 TLB 7/15/2010 10/19/2010 14.42 0.63 TLB 10/19/2010 1/5/2011 13.54 0.69 TLB 1/13/2010 4/6/2010 12.60 0.90 TLB 4/6/2010 7/15/2010 15.04 0.95 TLB 7/15/2010 10/19/2010 13.75 0.89 TLB 10/19/2010 1/5/2011 13.26 0.70 C-40

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Quarterly Results in mR/91 days +/- 2 Sigma Location Sample Type Collection Period Exposure 24 TLB 1/13/2010 to 4/6/2010 13.01 +1- 1.22 24 TLB 4/6/2010 to 7/15/2010 12.41 0.93 24 TLB 7/15/2010 to 10/19/2010 13.10 1.32 24 TLB 10/19/2010 to 1/5/2011 11.67 0.71 29 TLB 1/13/2010 to 4/6/2010 15.19 0.56 29 TLB 4/6/2010 to 7/15/2010 18.14 1.02 29 TLB 7/15/2010 to 10/19/2010 17.10 0.57 29 TLB 10/19/2010 to 1/5/2011 16.41 1.06 30 TLB 1/13/2010 to 4/6/2010 15.78 2.01 30 TLB 4/6/2010 to 7/15/2010 15.15 0.67 30 TLB 7/15/2010 to 10/19/2010 16.11 0.61 30 TLB 10/19/2010 to 1/5/2011 13.79 0.64 31 TLB 1/13/2010 4/6/2010 16.67 1.64 31 TLB 4/6/2010 7/15/2010 17.00 1.02 31 TLB 7/15/2010 10/19/2010 16.89 1.12 31 TLB 10/19/2010 1/5/2011 15.47 0.90 33 TLB 1/13/2010 4/6/2010 16.15 1.06 33 TLB 4/6/2010 7/15/2010 18.90 1.05 33 TLB 7/15/2010 10/19/2010 17.93 0.86 33 TLB 10/19/2010 1/5/2011 17.16 0.96 35 TLB 1/13/2010 4/6/2010 11.97 0.58 35 TLB 4/6/2010 7/15/2010 13.60 0.66 35 TLB 7/15/2010 10/19/2010 12.92 0.60 35 TLB 10/19/2010 1/5/2011 12.73 0.60 36 TLB 1/13/2010 4/6/2010 15.91 0.93 36 TLB 4/6/2010 7/15/2010 17.81 0.78 36 TLB 7/15/2010 10/19/2010 17.24 +1- 0.54 36 TLB 10/19/2010 1/5/2011 16.19 0.98 53 TLB 1/13/2010 4/6/2010 12.86 0.73 53 TLB 4/6/2010 7/15/2010 15.47 0.80 53 TLB 7/15/2010 10/19/2010 14.94 0.59 C-4 1

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in mR/91 days +/- 2 Sigma Location Sample Type Collection Period Exposure 53 TLB 10/19/2010 to 1/5/2011 14.16 +/- 0.86 54 TLB 1/13/2010 to 4/6/2010 14.00 1.88 54 TLB 4/6/2010 to 7/15/2010 14.33 0.71 54 TLB 7/15/2010 to 10/19/2010 13.96 0.78 54 TLB 10/19/2010 to 1/5/2011 13.47 0.65 55 TLB 1/13/2010 to 4/6/2010 13.38 1.16 55 TLB 4/6/2010 to 7/15/2010 15.22 0.91 55 TLB 7/15/2010 to 10/19/2010 14.50 0.69 55 TLB 10/19/2010 to 1/5/2011 13.94 0.99 56 TLB 1/13/2010 to 4/6/2010 13.24 0.90 56 TLB 4/6/2010 to 7/15/2010 13.91 1.39 56 TLB 7/15/2010 to 10/19/2010 13.91 0.88 56 TLB 10/19/2010 to 1/5/2011 12.85 1.25 58 TLB 1/13/2010 to 4/6/2010 10.26 0.95 58 TLB 4/6/2010 to 7/15/2010 11.40 0.71 58 TLB 7/15/2010 to 10/19/2010 11.14 0.74 58 TLB 10/19/2010 to 1/5/2011 10.93 0.58 C-42

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Annual Results in mR/365 days +/- 2 Sigma Location Sample Type Collection Period Exposure 1 TLA 1/13/2010 to 1/5/2011 44.21 +/- 1.87 3 TLA 1/13/2010 to 1/5/2011 46.69 +/- 2.26 4 TLA 1/13/2010 to 1/5/2011 52.79 +/- 2.36 5 TLA 1/13/2010 to 1/5/2011 49.31 +/- 2.58 6 TLA 1/13/2010 to 1/5/2011 53.86 +/- 1.85 7 TLA 1/13/2010 to 1/5/2011 50.86 +/- 2.71 8 TLA 1/13/2010 to 1/5/2011 51.53 +/- 1.77 9 TLA 1/13/2010 to 1/5/2011 48.35 +/- 0.97 10 TLA 1/13/2010 to 1/5/2011 59.62 +/- 2.77 11 TLA 1/13/2010 to 1/5/2011 55.08 +/- 2.27 12 TLA 1/13/2010 to 1/5/2011 55.09 +/- 1.14 13 TLA 1/13/2010 to 1/5/2011 54.04 +/- 1.89 14 TLA 1/13/2010 to 1/5/2011 50.55 +/- 2.29 15 TLA 1/13/2010 to 1/5/2011 50.59 +/- 2.81 21 TLA 1/13/2010 to 1/5/2011 62.08 +/- 4.10 23 TLA 1/13/2010 to 1/5/2011 59.62 +/- 2.39 24 TLA 1/13/2010 to 1/5/2011 55.41 +/- 3.29 29 TLA 1/13/2010 to 1/5/2011 70.25 +/- 3.73 30 TLA 1/13/2010 to 1/5/2011 65.63 +/- 2.15 C-43

TLD Gamma Dose Detail Report 2010 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Annual Results in mR/365 days +/- 2 Sigma Location Sample Type Collection Period Exposure 31 TLA 1/13/2010 to 1/5/2011 68.06 +/- 3.61 33 TLA 1/13/2010 to 1/5/2011 71.08 +/- 2.27 35 TLA 1/13/2010 to 1/5/2011 53.64 +/- 1.86 36 TLA 1/13/2010 to 1/5/2011 71.55 +/- 1.87 53 TLA 1/13/2010 to 1/5/2011 60.92 +/- 2.06 54 TLA 1/13/2010 to 1/5/2011 55.86 +/- 1.17 55 TLA 1/13/2010 to 1/5/2011 59.65 +/- 1.68 56 TLA 1/13/2010 to 1/5/2011 57.25 +/- 1.62 58 TLA 1/13/2010 to 1/5/2011 47.96 +/- 1.96 C-44

APPENDIX C Water Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Water 12/23/2009 1/28/2010 < 21.12 1.44 2.95 < 3.00 < 3.00

< 2.97 1.87 2.80 < 2.12 < 2.65

< 2.99 Water 2/25/2010 2/25/2010 < 15.37 1.25 2.03 < 2.49 < 2.42

< 2.99 1.77 1.77 < 3.28 < 2.66

< 2.43 Water 2/25/2010 3/25/2010 < 14.62 2.08 1.82 < 2.35 < 2.39

< 4.16 3.91 2.43 < 2.64 < 3.53

< 6.15 Water 3/25/2010 4/29/2010 < 10.01 2.14 1.47 < 2.16 < 2.63

< 3.93 1.90 1.79 < 3.20 < 3.61

< 3.54 Water 4/29/2010 5/27/2010 < 12.22 2.88 1.65 < 1.99 < 2.31

< 5.49 4.21 2.12 < 2.27 < 4.37

< 5.66 Water 5/27/2010 6/25/2010 < 12.80 2.39 2.66 < 3.22 < 3.05

< 2.94 1.59 2.93 < 2.10 < 6.31

< 2.87 Water 6/25/2010 7/28/2010 < 18.25 2.66 2.79 < 2.54 < 2.37

< 6.29 2.35 1.71 < 2.43 < 2.44

< 3.46 Water 7/28/2010 8/26/2010 < 24.27 2.70 1.86 < 1.93 < 2.34

< 4.65 5.56 2.56 < 4.33 < 3.53

< 2.80 Water 8/26/2010 9/30/2010 < 16.49 1.55 1.24 < 1.44 < 1.37

< 2.37 4.11 1.25 < 1.70 < 2.21

< 2.65 Water 9/30/2010 10/28/2010 < 23.18 3.63 3.77 < 3.81 < 5.26

< 5.27 < 3.18 < 3.37 < 3.64 < 6.56

< 6.47 28 Water 10/28/2010 to 11/24/2010 < 19.14 < 4.61 < 3.96 < 4.09 < 6.17

< 6.69 < 6.79 < 2.64 < 8.55 < 8.76

< 6.06 C-45

APPENDIX C Water Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 28 Water 11/24/2010 to 12/30/2010 < 20.20 < 1.61 < 2.97 < 3.36 < 3.79

< 6.02 < 4.18 < 2.36 < 2.29 < 5.17

< 4.32 34 Water 12/23/2009 to 1/28/2010 < 14.81 < 2.83 < 2.77 < 2.87 < 1.91

< 4.24 < 2.32 < 2.62 < 3.42 < 4.33

< 2.14 34 Water 1/28/2010 to 2/25/2010 < 18.97 < 2.18 < 1.75 < 2.68 < 3.07

< 4.25 < 3.34 < 2.53 < 2.73 < 1.51

< 5.63 34 Water 2/25/2010 to 3/25/2010 < 11.76 < 1.56 < 2.30 < 2.07 < 2.25

< 4.31 < 1.43 < 1.77 < 2.33 < 3.51

< 2.10 34 Water 3/25/2010 to 4/29/2010 < 17.30 < 2.32 < 1.42 < 2.58 < 2.39

< 5.76 < 2.64 < 2.16 < 2.98 < 3.13

< 4.81 Water 4/29/2010 to 5/27/2010 < 20.45 < 2.31 < 2.83 < 2.03 < 3.02

< 3.35 < 2.45 < 2.78 < 3.09 < 2.89

< 4.64 34 Water 5/27/2010 to 6/25/2010 < 15.65 < 1.92 < 2.66 < 1.82 < 3.17

< 4.28 < 2.74 < 2.13 < 2.63 < 2.41

< 3.88 34 Water 6/25/2010 to 7/28/2010 < 18.00 < 2.51 < 3.06 < 2.46 < 1.88

< 5.00 < 4.34 < 2.72 < 3.04 < 3.68

< 4.81 34 Water 8/26/2010 to 8/26/2010 < 16.39 < 1.75 < 1.88 < 1.25 < 1.13

< 4.40 < 4.23 < 1.42 < 2.28 < 2.27

< 3.89 34 Water 8/26/2010 to 9/30/2010 < 18.58 < 3.37 < 3.59 < 3.71 < 2.70

< 6.39 < 3.25 < 3.52 < 2.67 < 3.77

< 7.39 C-46

APPENDIX C Water Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 34 Water 9/30/2010 to 10/28/2010 < 13.44 < 2.16 < 2.29 < 2.48 < 2.99

< 3.88 < 4.31 < 2.49 < 3.42 < 2.83

< 3.48 34 Water 10/28/2010 to 11/24/2010 < 26.65 < 4.17 < 3.74 < 4.05 < 4.47

< 6.20 < 3.93 < 4.10 < 4.57 < 2.79

< 8.44 34 Water 11/24/2010 to 12/30/2010 < 14.77 < 2.14 < 2.07 < 2.28 < 2.54

< 2.93 < 1.25 < 2.00 < 2.21 < 4.52

< 2.84 36 Water 12/23/2009 to 1/28/2010 < 11.91 < 2.01 < 2.34 < 2.40 < 2.74

< 4.59 < 4.81 < 3.05 < 3.09 < 3.68

< 4.95 36 Water 1/28/2010 to 2/25/2010 < 12.95 < 2.03 < 2.08 < 2.56 < 3.97

< 5.80 < 2.92 < 2.89 < 1.30 < 4.50

< 5.97 36 Water 2/25/2010 to 3/25/2010 < 15.81 < 3.44 < 1.84 < 3.02 < 2.58

< 4.55 < 1.96 < 2.22 < 3.98 < 4.22

< 4.50 Water 3/25/2010 to 4/29/2010 < 11.17 < 1.50 < 1.01 < 2.58 < 1.94

< 5.39 < 3.72 < 0.92 < 3.16 < 4.19

< 4.89 36 Water 4/29/2010 to 5/27/2010 < 21.89 < 1.81 < 1.96 < 2.45 < 2.18

< 2.85 < 3.12 < 3.09 < 4.19 < 2.03

< 7.13 36 Water 5/27/2010 to 6/25/2010 < 24.89 < 2.17 < 1.96 < 1.98 < 2.79

< 2.60 < 5.24 < 2.88 < 3.48 < 3.84

< 4.98 36 Water 6/25/2010 to 7/28/2010 < 25.36 < 2.20 < 3.08 < 2.80

  • 3.60

< 3.31 < 4.29 < 2.07 < 2.63 < 4.34

< 6.18 C-47

APPENDIX C Water Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La- 140 Mn-54 Nb-95 Zn-65 Zr-95 Water 7/28/2010 to 8/26/2010 < 13.51 < 1.28 < 1.45 < 1.08 < 1.09

< 2.14 < 4.62 < 1.26 < 2.38 < 2.65

< 2.47 Water 8/26/2010 to 9/30/2010 < 21.02 < 1.51 < 1.78 < 1.73 < 1.38

< 2.73 < 6.55 < 1.67 < 3.05 < 2.37

< 2.30 Water 10/28/2010 to 10/28/2010 < 19.45 < 1.44 < 3.83 < 4.13 < 5.10

< 6.71 < 3.66 < 2.57 < 3.28 < 7.66

< 7.59 Water 10/28/2010 to 11/24/2010 < 18.61 < 3.26 < 3.97 < 2.78 < 1.47

< 5.63 < 2.95 < 2.68 < 2.80 < 6.18

< 3.39 Water 11/24/2010 to 12/30/2010 < 12.48 < 2.42 < 2.28 < 2.92 < 1.30

< 4.48 < 1.70 < 2.31 < 2.60 < 2.20

< 4.24 Water 3/25/2010 to 4/29/2010 < 18.26 < 1.98 < 2.51 < 3.40 < 2.97

< 3.16 < 3.53 < 2.76 < 3.10 < 1.76

< 4.33 Water 4/29/2010 to 5/27/2010 < 23.73 < 2.60 < 1.66 < 2.67 < 2.86

< 6.09 < 3.22 < 2.59 < 3.25 < 3.47

< 4.97 Water 5/27/2010 to 6/25/2010 < 25.67 < 2.50 < 2.01 < 2.93 < 3.58

< 3.95 < 5.37 < 2.47 < 2.52 < 2.75

< 3.94 Water 6/25/2010 to 7/28/2010 < 23.31 < 1.93 < 2.68 < 2.53 < 2.76

< 5.22 < 5.60 < 2.54 < 3.33 < 4.27

< 6.45 Water 7/28/2010 to 8/26/2010 < 16.11 < 0.91 < 1.07 < 0.93 < 1.31

  • 2.16 < 3.32 < 1.37 < 2.01 < 2.10
  • 2.03 C-48

APPENDIX C Water Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La- 140 Mn-54 Nb-95 Zn-65 Zr-95 59 Water 8/26/2010 to 9/30/2010 < 22.70 < 3.39 < 5.52 < 3.88 < 4.73

< 7.19 < 9.71 < 2.92 < 3.68 < 6.56

< 9.20 Water 9/30/2010 to 10/28/2010 < 16.92 < 2.78 < 1.71 < 2.70 < 2.84

< 3.08 < 3.68 < 2.45 < 3.94 < 2.85

< 5.26 Water 10/28/2010 to 11/24/2010 < 18.09 < 3.62 < 2.34 < 1.83 < 3.26

< 3.94 < 3.53 < 2.63 < 2.01 < 1.69

< 4.39 Water 3/25/2010 to 4/29/2010 < 20.09 < 2.23 < 1.14 < 2.75 < 3.67

< 6.40 < 3.99 < 1.72 < 4.23 < 1.43

< 5.64 Water 4/29/2010 to 5/27/2010 < 23.89 < 2.42 < 2.89 < 3.34 < 2.70

< 5.61 < 4.31 < 3.15 < 2.83 < 3.92

< 6.72 Water 5/27/2010 to 6/25/2010 < 19.78 < 2.43 < 1.64 < 2.07 < 3.25

< 5.57 < 5.86 < 2.51 < 3.55 < 4.53

< 5.52 Water 6/25/2010 to 7/28/2010 < 16.65 < 2.00 < 2.78 < 2.49 < 2.05

< 4.57 < 7.28 < 1.91 < 3.41 < 3.56

< 5.29 Water 7/28/2010 to 8/26/2010 < 19.35 < 1.36 < 1.26 < 0.85 < 1.21

< 2.27 < 5.26 < 1.17 < 2.04 < 2.02

< 2.18 Water 8/26/2010 to 9/30/2010 < 16.29 < 1.14 < 1.69 < 1.44 < 1.79

< 3.77 < 4.13 < 1.43 < 1.61 < 2.93

< 2.83 Water 9/30/2010 to 10/28/2010 < 32.75 < 3.34 < 3.09 < 2.69 < 3.64

< 6.88 < 7.91 < 2.58 < 3.99 < 5.10

< 4.34 C-49

APPENDIX C Water Gamma Spectral Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 60 Water 10/28/2010 to 11/24/2010 < 23.10 < 2.22 < 2.96 < 2.94 < 2.22

< 2.68 < 2.10 < 2.00 < 3.69 < 4.64

< 4.32 C-50

APPENDIX C Water Gross Beta Detail Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location 28 34 36 59 60 Collection Period Sample Type 12/23/2009 to 1/28/2010 Water LLD LLD LLD 1/28/2010 to 2/25/2010 Water LLD LLD 2/25/2010 to 2/25/2010 Water LLD 2/25/2010 to 3/25/2010 Water LLD LLD 3.41 +/- 1.10 3/25/2010 to 4/29/2010 Water LLD < 0.88 LLD LLD LLD 4/29/2010 to 5/27/2010 Water LLD LLD LLD LLD LLD 5/27/2010 to 6/25/2010 Water LLD LLD LLD LLD LLD 6/25/2010 to 7/28/2010 Water LLD LLD < 0.83 LLD < 0.94 7/28/2010 to 8/26/2010 Water < 1.68 < 1.62 < 1.70 < 1.75 8/26/2010 to 8/26/2010 Water LLD 8/26/2010 to 9/30/2010 Water LLD LLD LLD LLD 3.16 +/- 1.10 C-51

APPENDIX C Water Gross Beta Detail Report 2010 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location 28 34 36 59 60 Collection Period Sample Type 9/30/2010 to 10/28/2010 Water LLD 3.25 +/- 0.83 LLD LLD 10/28/2010 to 10/28/2010 Water 3.29 +/- 0.83 10/28/2010 to 11/24/2010 Water LLD LLD < 1.84 3.04 +/- 1.01 3.12 +/- 1.11 11/24/2010 to 12/30/2010 Water LLD 3.05 +/- 0.76 LLD C-52

APPENDIX C Water Tritium Detail Report 2010 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date H-3 28 Water 3/25/2010 142.48 28 Water 6/25/2010 162.92 28 Water 9/30/2010 161.35 28 Water 12/30/2010 143.84 34 Water 3/25/2010 142.48 34 Water 6/25/2010 162.92 34 Water 9/30/2010 161.35 34 Water 12/30/2010 143.84 36 Water 3/25/2010 142.48 36 Water 6/25/2010 162.92 36 Water 9/30/2010 161.35 36 Water 12/30/2010 143.84 59 Water 3/25/2010 59 Water 6/25/2010 162.92 59 Water 9/30/2010 161.35 59 Water 11/24/2010 144.65 60 Water 3/25/2010 60 Water 6/25/2010 162.92 60 Water 9/30/2010 161.35 60 Water 11/24/2010 144.65 C-53

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX D CORRECTIONS TO PREVIOUS ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORTS

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX D CORRECTIONS TO PREVIOUS ANUUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORTS:

There were no corrections identified during this reporting period to any of the previous Annual Environmental and Effluent Release Reports.

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