Text

Annual Environmental and Effluent Release Report 2011
	ML12129A308
Person / Time
Site:	Perry
Issue date:	04/30/2012
From:	; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML12129A308 (149)
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0 Perry Nuclear Power Plant Annual Environmental & Effluent Release Report 2011

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0 2011 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 APRIL, 2012

0 0ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT TABLE OF CONTENTS EXECUTIVE

SUMMARY

1 Radioactive Effluent Releases...................................................................................................

1 Radiological Environm ental Monitoring..............................................................................

2 Land Use Census........................................................................................................................

3 Clam/M ussel Monitoring......................................................................................................

3 Herbicide Use...............................................................................................................................

3 Special Reports............................................................................................................................

3 INTRO DUCTIO N..............................................................................................................

4 Radiation Fundam entals.......................................................................................................

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

4 Units of M easure..........................................................................................................................

5 Lower Lim it of Detection......................................................................................................

6 SBackground radiation..................................................................................................................

7 RA DIO ACTIVE EFFLUENT RELEASES...................................................................

8 Introduction...................................................................................................................................

8 Regulatory Lim its.........................................................................................................................

8 Release Sum m ary........................................................................

10 Meteorological Data...................................................................................................................

17 Dose Assessm ent......................................................................................................................

17 Carbon-14 Supplem ental Inform ation...............................................................................

21 O n-Site G roundwater Monitoring Program......................................................................

22 Corrections to Previous Annual Environmental and Effluent Release Reports......

27 SAbnorm al Releases...................................................................................................................

27 O DCM Non-Com pliances.................................................................................................

27 Offsite Dose Calculation M anual Changes......................................................................

27 Process Control Program Changes.................................................................................

27 RADIOLOGICAL ENVIRONMENTAL MONITORING..............................................

28 Introduction.................................................................................................................................

28 Sam pling Locations...................................................................................................................

28 Fukushim a Dai-Ichi....................................................................................................................

29 SSam ple Analysis.........................................................................................................................

34 2011 Sam pling Program....................................................................................................

35 Inter-Laboratory Cross-Check Com parison Program....................................................

44 Land Use Census......................................................................................................................

46 C LAM /M USSEL M O N ITO R ING..................................................................................

49 Introduction.................................................................................................................................

49 Corbicula Program......................................................................................................................

49 Dreissena Program....................................................................................................................

51 H ERBIC ID E A PPLICATIO NS....................................................................................

52 SPEC IAL REPO RTS......................................................................................................

53 Non-Com pliances......................................................................................................................

53 Un-Reviewed Environm ental Q uestions..........................................................................

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDICES Appendix A: 2011 Inter-Laboratory Cross Check Comparison Program Results Appendix B: 2011 REMP Data Summary Reports Appendix C: 2011 REMP Detailed Data Report Appendix D: Corrections to Previous AEERR Appendix E: Abnormal Releases Appendix F: ODCM Non-Compliances Appendix G: Changes to the Process Control Program Table of Contents Page ii 00 0

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00 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, 2011. 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

1 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, clam/mussel monitoring, herbicide use, and special reports. The results of the

1 environmental and effluent programs for 2011 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 0I 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 2.47E-03

mrem (0.082 % of the applicable limit). The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents (excluding C-14) for 2011 was 2.75E-04 mrem (0.0055% of the applicable limit).

In 2011, radioactivity released to the environment in the form of gaseous Carbon-14 (C-1 4) 0was estimated based on plant type and power production. 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 2011, including C-14 is 0.16 mrem. Refer to page 21 for additional Carbon-14 information.

The summation of the hypothetical maximum individual dose from effluents in 2011 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 0material generated during normal daily operations and maintenance, and irradiated

components.

PNPP complied with applicable regulations governing radioactive shipments in 2011, 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.

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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. 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. Over a four week period in late March to mid-April, radioactive iodine was identified on 25 of the 28 0

samples taken during that time period - both indicator and control. This radioactivity is attributed to the accident at Fukushima in Japan. Positive results were identified throughout the US. Other than these four weeks, the 2011 results were similar to those observed for the pre-operational and operational programs from prior years.

Terrestrial monitoring included the analysis of milk and produce. The results of three milk samples for mid-April and early May 2011 identified radioactive iodine. This was attributed to Fukushima. Other than these samples, the 2011 results indicated concentrations of radioactivity similar to that found in previous years. Analyses of produce samples detected only 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 2011 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 367.04 pCi/kg and is lower than the highest identified 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 2011. The cobalt-60 remains centered within 0

the organic material located at the top of the spillway, with little or no activity found farther 0

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 62.44 mrem/year and control locations averaged 60.56 mrem/year. In 0

2011, 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 2011, the operation of the PNPP resulted in no significant increase in the radionuclide concentrations observed in the environment.

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0 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT LAND USE CENSUS In order to estimate radiation dose attributable to the operation of PNPP, the potential 0

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 public roads within a five (5) mile radius of the

l plant to locate key radiological exposure pathways. These key pathways include the nearest resident, garden, and milk animal in each of the ten meteorological land sectors that surround the plant. 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.

0t 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 2011, 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 0

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.

I HERBICIDE USE

The use of herbicides on the PNPP site is monitored to ensure compliance with Ohio 0Environmental 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

D plant.

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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 2011:

On October 17, 2011 approximately 1000 gallons of a diesel/gas fuel mixture was spilled into the environment at the Fire Training facility, covering an area of 20 x 60 meters. The release entered a Class III wetlands just west of the Fire Training 0facility but did not enter Lake Erie. Clean Harbors Incorporated was contracted for

l the initial clean-up and disposal. The storage tank has been cleaned and emptied and is no longer in service. The associated underground piping has been removed.

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT All areas affected by the release have been cleaned and will be re-evaluated in the spring of 2012. Periodic sampling of piezometers and sentinel wells has indicated 0

the release has not migrated. All proper notifications to regulatory agencies were made as required.

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.

00 RADIATION FUNDAMENTALS Atoms are the basic building blocks of all matter. Simply described, atoms are made up of 0

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 0

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.

0 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 0

when radioactive decay occurs within the nucleus. This section includes a discussion on the three (3) primary forms of radiation produced by radioactive decay.

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t Alpha Particles 0I 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, 0they can damage the soft internal tissues because they deposit all their energy in a small

area.

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

l 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.

0 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.

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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.

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UNITS OF MEASURE 0I Some of the units of measure used in this report require explanation.

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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 0

used in this report. Two common units are the microcurie (pCi), 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.

0For 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.

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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 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.

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O 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 0

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 0

in Figure 1 [Source: National Council on Radiation Protection and Measurements].

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Internal Terrestial 10.94%

Nuclear Fuel Cycle 0.09%

osmic Nuclear Medicine

.959 3.98%

1 /6 Consumer Products Ilaneous 2.80%r.

Fall-Out 010%

" - t 0.26%

-Other 0.75%

0C cuional Sources 0.309/

O Radon O

54.699/6 O

Figure 1: Sources of Background Radiation Many radionuclides are present in the environment due to sources such as cosmic radiation 0

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:

O* 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 O

throughout the environment, and O

Radionuclides from nuclear weapons testing fallout, including tritium and cesium-O0 137. These radionuclides may also be released in minute amounts from nuclear a*

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 O

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT are not discussed in the section for the 2011 Sampling Program results. These radionuclides are included; however, in Appendix A, 2011 Inter-Laboratory Cross Check Comparison Program Results.

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RADIOACTIVE EFFLUENT RELEASES 0

I INTRODUCTION 0The source of radioactive material in a nuclear power plant is the generation of fission 0

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 0in 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 0D 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.

0Gaseous 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 0

samples of other environmental media are also taken to determine if any radioactive material deposition has occurred. The Radiological Environmental Monitoring Program

l (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

I radioactive solid waste generated. Solid waste is shipped to a licensed burial site.

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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) [1 OCFR20], 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].

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT These limits were incorporated into the PNPP Technical Specifications, and subsequently 0

into the PNPP Offsite Dose Calculation Manual (ODCM). The ODCM prescribes the maximum doses and 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, 0

which are described below, were not exceeded in 2011.

The 40CFR1 90 limit for total direct-radiation dose is 25 mrem. For 2011, the total whole body dose to a member of the general public, considering all sectors, was 3.8E-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) 0 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.OE-04 gCi/mil 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 0

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 SS Gaseous Effluents Dose rate due to radioactive materials released in gaseous effluents from the site to areas 0

at and beyond the site boundary shall be limited to the following:

0 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 S

greater than eight days:

0 Less than or equal to 1500 mrem per year to any organ 5

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 0

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT During any calendar year:

Less than or equal to 10 mrad for gamma radiation, and Less than or equal to 20 mrad for beta radiation Dose to a member of the public from lodine-131, Iodine-1 33, 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 limit 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 2011.

Table 1: Liquid Batch Releases QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 ANNUAL TOTAL Number of batch releases 22 72 37 16 147 Total time period for batch releases, min 4.91 +E03 1.60E+04 8.26E+03 3.55E+03 3.25E+04 Maximum time for a batch release, min 2.28E+02 3.84E+02 2.30E+02 2.27E+02 3.84E+02 Average time period for a batch release, 2.23E+02 2.23E+02 2.23E+02 2.22E+02 2.23E+02 min Minimum time for a batch release, min 2.02E+02 6.OOE+00 2.02E+02 2.05E+02 6.OOE+00 Average stream flow during periods of 1.14E+05 2.04E+05 2.33E+05 1.67E+05 1.80E+05 effluent 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

ERROR, A.

Fission and Activation Products

1. Total Released, Ci 1.43E-03 2.55E-02 5.21 E-03 5.27E-03 1..OOE+01 (excluding tritium, gases, alpha)

2. Average Diluted Concentration, 8.80E-11 8.68E-10 1.61 E-10 2.59E-10 NA gCi/mL *

3.

Percent of Applicable Limit, %

2.56E-03 2.1 OE-02 4.75E-03 8.06E-03 NA B.

Tritium

1. Total Released, Ci 1.08E+01 1.47E+01 6.33E+00 3.33E+00 1.OOE+01

2.

Average Diluted Concentration, 6.63E-07 4.99E-07 1.96E-07 1.64E-07 gCi/mL

3.

Percent of Applicable Limit, %

6.63E-02 4.99E-02 1.96E-02 1.64E-02 C.

Dissolved and Entrained Gases

1. Total Released, Ci

<LLD

<LLD 1.62E-07 1.OOE+01

2.

Average Diluted Concentration,

<LLD

<LLD 7.96E-15 NA jtCi/mL

3. Percent of Applicable Limit, %

N/A N/A N/A 3.99E-09 NA D.

Gross Alpha Activity, Ci

<LLD

<LLD 1.OOE+01 E.

Waste Volume Released, Liters (prior to 2.86E+06 8.72E+06 6.33E+06 2.74E+06 NA dilution)

F.

Dilution Water Volume Used, Liters 1.63E+10 2.94E+10 3.23E+10 2.03E+10 NA

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

Average diluted concentrations are based on total volume of water released during quarter.

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0 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 1.43E-03 2.55E-02 5.21 E-03 5.07E-03 1.O0E+O1 (excluding tritium, gases, alp ha)

B.

Tritium Total Released, Ci 11.08E+01 11.47E+01 6.33E+00 3.33E+O0 1.O0E+01 C.

Dissolved and Entrained Gases Total Released, Ci

<LLD

<LLD 1.OOE+01 D.

Gross Alpha Activity, Ci

<LLD

<LLD 1.OOE+01 E.

Waste Volume Released, Liters (prior to 2.86E+06 8.72E+06 4.80E+06 2.34E+06 NA 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 1.94E-04 1.00E+01 (excluding tritium, gases, alpha)

B. Tritium Total Released, Ci

<LLD

<LLD 1.80E-03 3.20E-03 1.OOE+01 C.

Dissolved and Entrained Gases Total Released, Ci

<LLD

<LLD 1.62E-07 1.OOE+01 D. Gross Alpha Activity, Ci

<LLD

<LLD 1.OOE+01 E. Waste Volume Released, Liters (prior to O.OOE+00 O.OOE+00 1.53E+06 4.01 E+05 NA 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 QUARTER QUARTER QUARTER QUARTER ANNUAL UNITS 1

2 3

4 TOTAL Tritium Ci 1.08E+01 1.47E+01 6.33E+00 3.33E+00 3.51 E+01 Sodium-24 Ci

<LLD

<LLD 9.25E-05 9.25E-05 Chromium-51 Ci

<LLD 2.26E-03

<LLD

<LLD 2.26E-03 Manganese-54 Ci 1.49E-04 2.76E-03 1.18E-04 9.60E-05 3.12E-03 Manganese-56 Ci

<LLD

<LLD 1.09E-06 1.09E-06 Iron-55 Ci

<LLD

<LLD Iron-59 Ci

<LLD

<LLD Cobalt-58 Ci

<LLD 7.09E-04

<LLD 3.39E-04 1.05E-03 Cobalt-60 Ci 1.23E-03 1.68E-02 4.25E-03 4.69E-03 2.69E-02 Zinc-65 Ci

<LLD 9.35E-04 2.45E-04

<LLD 1.18E-03 Zinc-69M Ci

<LLD

<LLD 2.38E-07 2.38E-07 Strontium-92 Ci

<LLD

<LLD Zirconium-95 Ci

<LLD

<LLD Niobium-95 Ci

<LLD

<LLD Technetium-99M Ci

<LLD

<LLD Rhuthenium-105 Ci

<LLD

<LLD Silver-i 1 om Ci

<LLD 1.38E-04 3.29E-04

<LLD 1.71 E-03 Antimony-124 Ci

<LLD 2.09E-04

<LLD

<LLD 2.09E-04 Antimony-125 Ci 5.30E-05 5.03E-04 2.70E-04

<LLD 8.26E-04 Iodine-1 31 Ci

<LLD

<LLD Xenon-135 Ci

<LLD

<LLD 1.62E-07 1.62E-07 Cesium-1 34 Ci

<LLD

<LLD Cesium-1 37 Ci

<LLD

<LLD 5.27E-05 5.27E-05 Cesium-138 Ci

<LLD

<LLD Lanthanum-1 40 Ci

<LLD

<LLD Gold-199 Ci

<LLD

<LLD Total for Period 1.08E+01 1.47E+01 6.34E+00 3.34E+00 3.52E+01

<LLD - Less than the lower limit of detection 0

0 0

0 S

0 0

Radioactive Effluent Releases Page 13

0 0

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 below regulatory limits. Samples are also collected and analyzed on a periodic 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" (Ž_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.

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 O.OOE+00 1.75E-01 O.OOE+00 1.19E-02 1.OOE+01

2.

Average Release Rate, iiCi/sec O.OOE+00 2.23E-02 O.OOE+00 1.50E-03

3.

Percent of Applicable Limit, %

N/A N/A N/A N/A B.

Iodine

1.

Total Iodine-131 Released, Ci O.OOE+00 1.84E-06 1.87E-05 2.11E-05 1.OOE+01

2.

Average Release Rate, gCi/sec O.OOE+00 2.34E-07 2.35E-06 2.65E-06

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 1.OOE+01

2.

Average Release Rate, jiCi/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 4.31E-07 1.16E-07 6.43E-08 6.04E-07 1.OOE+01 E.

Tritium

1.

Total Released, Ci 3.73E-01 2.17E+00 O.OOE+00 O.OOE+00 1.OOE+01

2.

Average Release Rate, gCi/sec 4.80E-02 2.76E-01 O.OOE+00 O.OOE+00

3.

Percent of Applicable Limit, %

N/A N/A N/A N/A F.

Carbon-14 4.58 1.84 4.72 3.81 1.OOE+01

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

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 3.73E-01 2.17E+00

<LLD

<LLD 2.54E+00 Argon-41 Ci

<LLD

<LLD Krypton-85m Ci

<LLD

<LLD Krypton-85 Ci

<LLD

<LLD Kryton-87 Ci

<LLD 2.21 E-02

<LLD

<LLD 2.21 E-02 Krypton-88 Ci

<LLD

<LLD Xenon-131m Ci

<LLD

<LLD Xenon-133m Ci

<LLD

<LLD Xenon-1 33 Ci

<LLD 5.44E-03

<LLD

<LLD 5.44E-03 Xenon-i 35m Ci

<LLD 3.21E-02

<LLD

<LLD 3.21E-02 Xenon-1 35 Ci

<LLD 4.04E-02

<LLD 2.57E-03 4.30E-02 Xenon-1 37 Ci

<LLD

<LLD Xenon-1 38 Ci 3.73E-01 7.54E-02

<LLD 9.34E-03 8.47E-02 Total for Period 3.73E-01 2.35E+00 O.OOE+00 1.19E-02 2.73E+00 B.

IODINE Iodine-131 Ci

<LLD 1.84E-06 1.87E-05 2.11E-05 4.16E-05 Iodine-132 Ci

<LLD

<LLD Iodine-133 Ci

<LLD 4.31 E-06 2.70E-04 1.60E-04 4.34E-04 Iodine-134 Ci

<LLD

<LLD Iodine-135 Ci

<LLD

<LLD Total for Period O.OOE+00 6.15E-06 2.89E-04 1.81 E-04 4.76E-04 C.

PARTICULATE Chromium-51 Ci

<LLD

<LLD Manganese-54 Ci

<LLD

<LLD Iron-59 Ci

<LLD

<LLD Cobalt-58 Ci

<LLD

<LLD Cobalt-60 Ci

<LLD

<LLD Zinc-65 Ci

<LLD

<LLD Rubidium-88 Ci

<LLD

<LLD Rubidium-89 Ci

<LLD

<LLD Strontium-89 Ci

<LLD

<LLD Strontium-90 Ci

<LLD

<LLD Yttrium-91m Ci

<LLD

<LLD Strontium-92 Ci

<LLD

<LLD Zirconium-95 Ci

<LLD

<LLD Molybdenum-99 Ci

<LLD

<LLD Cesium-137 Ci

<LLD

<LLD Cesium-138 Ci

<LLD

<LLD Barium-1 39 Ci

<LLD

<LLD Barium-140 Ci

<LLD

<LLD Lanthanum-140 Ci

<LLD

<LLD Total for Period

<LLD

<LLD - Less than the lower limit of detection 0

0 0

Radioactive Effluent Releases Page 15

0 0

0 S

0 0

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 2011.

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 7.36E+01 2.15 E+02 1/1/2011-

+/-25 bottoms, etc.

12/31/2011 Dry compressible waste, contaminated 1.09E+03 5.88 E+00 1/1/2011-

+/- 25 equipment, etc.

12/31/2011 Irradiated components, control rods, etc.

0 0

1/1/2011-12/31/2011 Other (Standby Liquid Control Waste 0

0 1/1/2011-Water) 12/31/2011 B.

ESTIMATE OF MAJOR 1 ) NUCLIDE COMPOSITION (BY RADIONUCLIDE ABUNDANCE EST. TOTAL TYPE OF WASTE)

(%)

ERROR, (%)

Spent Resin, Filter Sludge, Evaporator Bottoms, Mn-54 5.30

+/- 25 etc.

Fe-55 29.50 Co-60 62.02 Zn-65 1.64 Dry Compressible Waste, Contaminated Mn-54 8.01

+/- 25 Equipment, etc.

Fe-55 22.80 Co-60 66.51 Zn-65 1.12 Irradiated Components, Control Rods, etc.

None 0

Other (Standby Liquid Control Waste Water)

None 0

C.

DISPOSITION NUMBER OF MODE OF TRANSPORTATION DESTINATION SHIPMENTS Solid Waste(2) 16 Public Highway Studsvik, Erwin, TN Solid Waste(2) 27 Public Highway Energy Solutions, Bear Creek, TN Irradiated Fuel Shipments 0

N/A N/A N/A -- 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, 2011 through December 31, 2011, the report substantiates the quality and quantity of meteorological data 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 (1 OCFR20). Sampling, analyzing, 0

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 0

water, milk, vegetation, and fish. Because no one actually meets these criteria, the actual 0

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 0

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.

00 0

0 0

0 Radioactive Effluent Releases Page 17 0

0 0

0 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 7: Maximum Individual Site Boundary Dose, Considering All Sectors TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT

% OF (MREM)

LIMIT Liquid Effluent Whole body 2.47E-03 3.OE+00 8.2E-02 Liver 3.34E-03 1.OE+01 3.3E-02 Noble

- gamma air N/A 4.97E-04 1.OE+01 5.OE-03 Gas

- beta air N/A 3.37E-04 2.OE+01 1.7E-03 Noble Gas Whole body 2.75E-04 5.OE+00 5.5E-03 Skin 5.74E-04 1.5E+01 3.8E-03 Particulate & Iodine Thyroid 11.39E-04 1.5E+01 9.3E-04 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 3.8E-01 Thyroid 2.5E-01 Gaseous Effluent Whole body 3.5E-04 Thyroid 5.8E-04 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 2.47E-03 3.OE+00 8.2E-02 Liver 3.34E-03 1.OE+01 3.3E-02 Noble Gas - gamma air N/A 3.49E-05 1.OE+01 3.5E-04

-beta air N/A 2.51E-05 2.OE+01 1.3E-04 Noble Gas Whole Body 2.85E-06 5.OE+00 5.7E-05 Skin 5.56E-06 1.5E+01 3.7E-05 Particulate & Iodine Thyroid 5.11E-05 1.5E+01 3.4E-04 Carbon-14 Whole Body 1.60E-01 1.5E+01 1.1E+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 Radioactive Effluent Releases Page 18

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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 0.0167 hours 9.920635e-5 weeks 2.283e-5 months 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.

Table 10: Maximum Site Dose from Liquid Effluents WHOLE BODY DOSE, ORGAN DOSE (MREM)

(MREM)

First Quarter 1.1 E-04 1.3E-04 Second Quarter 9.3E-04 1.1 E-03 Third Quarter 2.OE-04 2.3E-04 Fourth Quarter 3.2E-04 3.8E-04 Annual 1.6E-03 1.8E-03 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 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year), non-plant related training, car-pooling, and job interviews. The maximum on-site gaseous doses generated are shown in Table 11.

0 0

S 0

0 0

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

(MREM)

First Quarter 1.4E-05 1.4E-05 Second Quarter 1.3E-04 1.6E-04 Third Quarter 2.2E-07 4.5E-05 Fourth Quarter 1.4E-06 9.5E-06 Annual 1.4E-04 2.1 E-04 Radioactive Effluent Releases Page 19

0 0

0 S

0 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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 3.8E-05 1.5E-08 Second Quarter 4.2E-05 1.3E-07 Third Quarter 2.OE-05 4.6E-1 1 Fourth Quarter 2.9E-05 3.1 E-1 0 Annual 1.6E-04 1.5E-07 Radioactive Effluent Releases Page 20

ANNUAL ENwIRONMENTAL AND EFFLUENT RELEASE REPORT CARBON-1 4 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 (C02). The quantity of gaseous C-14 released to the environment can be estimated using a C-14 source term scaling factor based on power generation.

The U.S. Nuclear Regulatory 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 2011, 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 2011 Annual Environmental Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2011, 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 21 0

0 0

0

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT

l 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

1 groundwater from the-foundations of the site buildings. As such, it would not be expected

1 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.

0)

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 SManagement (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-OP-2012, "Groundwater Monitoring."

0Cause 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 01 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 0towards 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.

Underdrain System As mentioned earlier, the underdrain system drains water away from plant foundations. It is 0separate 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

1 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 1 through

23.

0 0Sampling Locations Prior to the installation of monitoring wells, Manholes 20 and 23 were sampled to assess

I groundwater tritium in-leakage to the system. This continued through July 2007, and sampling frequency was established at weekly thereafter. Besides tritium, the samples 0*Radioactive Effluent Releases Page 22 0

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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 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 1 A 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 23 0

0 0

0

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 2: Underdrain System and On-Site Groundwater Wells Manholes 0

Piezometers SGroundwater Wells

.. aR i i iIlil.i.i.i..i.iBiB.ii B

.i.geni

li U

U UU a

(APO, h:

en, T-1 U

U U

U

£ B

U U

B B

U U

B B

IS 0

Radioactive Effluent Releases Page 24

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 additional samples, Perry has requested analysis of "hard-to-detect" isotopes such as Sr-89/90, Ni-63 and Fe-55.

Radiological Environmental Monitoring Page 25 00 0

0 0

0

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 0

0 0

Table 13: Summary of Onsite Groundwater Samples Monitoring H-3 MAX.

TYPICAL REQUIRED PRE-H-3 ANALYSES NEI EPA Well (PCI/L)

H-3 LLD H-3 LLD OPERATIONAL

> PRE-AND REPORTING (PCI/L)

(PCI/L)

(DEVELOPED)

OPERATIONAL FENOC LEVEL FOR MEAN FOR H-3 MEAN FOR H-3 LEVEL H-3 (PCI/L)

(PCI/L)

FOR H-3 (PCI/L)

First Half 2011 277

< 200

< 2000 400 No 2000 20000 Well1A

<144

<200

<2000 400 No 2000 20000 Well 1B

<144

< 200

< 2000 400 No 2000 20000 Well 10

<144

< 200

< 2000 400 No 2000 20000 Well 2A

<144

< 200

< 2000 400 No 2000 20000 Well 2B

<144

< 200

< 2000 400 No 2000 20000 Well 2C

<144

< 200

< 2000 400 No 2000 20000 Well 3A 277

< 200

< 2000 400 No 2000 20000 Well 3B

<166

< 200

< 2000 400 No 2000 20000 Well 3C

<166

< 200

< 2000 400 No 2000 20000 Well 4A

<144

< 200

< 2000 400 No 2000 20000 Well 4B

<144

< 200

< 2000 400 No 2000 20000 Well 40

<144

< 200

< 2000 400 No 2000 20000 Second Half 2011 219

< 200

< 2000 400 No 2000 20000 WelI1A

<145

< 200

< 2000 400 No 2000 20000 Well 1 B

<145

< 200

< 2000 400 No 2000 20000 Well 1C

<145

< 200

< 2000 400 No 2000 20000 Well 2A

<145

< 200

< 2000 400 No 2000 20000 Well 2B

<145

< 200

< 2000 400 No 2000 20000 Well 2C

<145

< 200

< 2000 400 No 2000 20000 Well 3A 219

< 200

< 2000 400 No 2000 20000 Well 3B

<145

< 200

< 2000 400 No 2000 20000 Well 3C

<145

< 200

< 2000 400 No 2000 20000 Well 4A 164

< 200

< 2000 400.

No 2000 20000 Well 4B

<145

< 200

< 2000 400 No 2000 20000 Well 4

<145

< 200

< 2000 400 No 2000 20000 Radiological Environmental Monitoring Page 26

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CORRECTIONS TO PREVIOUS ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORTS See Appendix D for description of corrections to previous Annual Environmental and Effluent Release Reports.

ABNORMAL RELEASES See Appendix E for description of an Abnormal Release from the Nuclear Closed Cooling (NCC) system.

ODCM NON-COMPLIANCES See Appendix F for description of ODCM Non-Compliances.

OFFSITE DOSE CALCULATION MANUAL CHANGES During this reporting period, there were no revisions to the Offsite Dose Calculation Manual.

PROCESS CONTROL PROGRAM CHANGES See Appendix G for description of changes to the Process Control Program Radiological Environmental Monitoring Page 27 00 0

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING

t 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

0impact, 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.

SA variety of samples are collected as part of the PNPP REMP. The selection of sample 0I types, locations, and 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 factors.

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. Additionally the Lake County General Health District obtains monthly "split" samples of milk, water and vegetation. This 0l permits an independent verification of Perry's radiological environmental monitoring program.

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 0were 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

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

0

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 0control.

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 01 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

I and Figure 5 identify the PNPP REMP sampling locations.

00

Radiological Environmental Monitoring Page 28 0

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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.

FUKUSHIMA DAI-ICHI During 2011, environmental milk and air particulate samples collected in late March, April and early May identified detectable concentrations of 1-131 that could be related to operation of the Perry Nuclear Power Plant. The concentrations detected were above levels historically observed. Concentrations returned to non-detectable levels after May 2.

Given the events of March 2011 at the Dai-lchi plant, Fukushima Japan and the associated airborne releases and subsequent trans-Pacific transportation, the positive results detected for these samples are reasonably attributed to the Dai-lchi releases. The detected radioactivity levels were below the ODCM reporting criteria.

Radiological Environmental Monitoring Page 29 00 0

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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, AlP 6

Concord Service Center 11.0 SSW TLD, AlP 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 0.9 S

Food Products 18 Kijauskas Farm (goat) 2.5 E

Food Products, Milk 19 Goodfield Dairy 8.7 S

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, AlP 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 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)

(2)

Missing location numbers denote deleted or retired sampling locations.

AlP = Air, Iodine and Particulate TLD =

Thermoluminescent Dosimeter Radiological Environmental Monitoring Page 30

ANNuAL EVWiRONMENTAL AND EFFLUENT RELEASE REPORT Figure 3: REMP Sampling Locations Within Two Miles of Plant Site NNW N

NNE NW WNW W

WSW SW NE ENE E

ESE SE 0

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0 SSW S

SSE 1

0 1

2 MILES Radiological Environmental Monitoring Page 31

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0 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 Radiological Environmental Monitoring Page 32

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 5: REMP Sampling Locations Greater Than Eight Miles from the Plant Site 5

0 5

10 15 20MILES l

m m

Radiological Environmental Monitoring Page 33

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.

0Gross 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 01 continuous energy spectrum rather than the discrete energy levels, or "peaks", associated

with gamma radiation, identification of specific beta-emitting nuclides is 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 0present.

0!

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.

0Some 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 a 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 0heating process and measured in a calibrated reading system. As the TLD is heated, the

t 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 2011.

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 0as 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

1 2011.

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

Gross Beta Activity &

Particulates 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 Monthly Gross Beta Activity &

Water Gamma Spectral Analysis Quarterly Tritium Activity Fish Annually Gamma Spectral Analysis Sediment Biannually Gamma Spectral Analysis Direct Radiation TLD Quarterly &

Gamma Dose Monitoring Annually 2011 SAMPLING PROGRAM The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the 2011 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, 2011 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 2011.

Program Changes Goodfield Dairy, located 8.7 miles in the South sector was added to the Milk program in August 2011.

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 do not normally 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 2011, there was no impact to the program requirements as a result of any missed samples. Table 16 provides information on samples missed during 2011.

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0 Table 16: Missed REMP Samples in 2011 MEDIA LOCATION DATE REASON Food Products All Jan.-June, Oct.-Dec. 2011 Insufficient growth/temperature. Die-off/Frost damage.

Lake Water 59, 60 Jan., Feb., Mar. 2011 Sample unavailable due to frozen shoreline Milk 18 Oct. Nov. Dec 2011 Drying period for goats/sample availability 41 Jan. - May, Oct. Nov., Dec.

Drying period for goats/sample 2011 availability 61 Jan., Feb., Mar., Jun to Drying period for goats/sample Dec. 2011 availability 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.

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 364 air particulate and 364 air radioiodine samples were collected and analyzed in 2011.

Gross beta activity was detected in 364 of 364 air samples and ranged up to 0.06 pCi/m 3.

The average gross beta activity at both indicator and control locations was 0.02 pCi/m 3 for 2011. 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 2011 and the previous years.

Except for naturally occurring beryllium-7, no radionuclides were identified in the gamma quarterly spectral analysis above the LLD values.

Iodine-131 was detected above the LLD of 0.05 pCi/m 3 on all indicator and control samples obtained from 3/23/11 to 4/13/11. The indicator sample average was 0.07 pCi/m 3 and the control sample average was 0.08 pCi/m 3. These positive results are attributed to the accident at Fukushima Dai-lchi nuclear plant in Japan.

Radiological Environmental Monitoring Page 36

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 6: Annual Average Gross Beta Activity, in Air n An 0.04

. 0.0 3 ZI 0.02 S0.0o1 09' 8

~8 888 8 8 88 8~ a Year llndcator EContml 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 2011, the PNPP REMP included five (5) milk locations located 2.5, 5.8, 7.4, 8.7 and 9.6 miles away from the plant.

Since the milk sampling locations do not meet the requirements of the ODCM (only one milk-producing animal is located within the required distance vs. two required), food product sampling (discussed below) is performed. Milk is collected from the available location to augment food product sampling. 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-four (54) milk samples were collected in 2011. Iodine was detected above the LLD of 0.75 pCi/m3 in three of the samples collected in April and May with an average value of 1.61 pCi/L. This radioactivity is attributed to the accident at the Fukushima nuclear plant in Japan. The concentrations of all other radionuclides, except naturally occurring potassium-40, were below LLDs in all samples collected. Results for samples taken after May have returned to below LLD levels.

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 Radiological Environmental Monitoring Page 37 00 0

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT

l 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.

I A total of forty-three (43) food product samples were collected and analyzed by gamma spectral analysis in 2011. For the 2011 growing season, record rainfall throughout the year contributed to the missed samples referenced in Table 16.

Four (4) food products were collected which included: beet greens, collard greens, turnip 0I greens and Swiss chard. Beryllium-7 and potassium-40, naturally-occurring radionuclides, were found in several samples, which is expected. No other radionuclides were detected

D 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.

0 Fifty-four (54) water samples were collected and analyzed for gross beta activity and gamma

spectral analysis in 2011. From these monthly samples, eighteen (18) quarterly composite samples were obtained and analyzed for tritium activity.

For 2011, gross beta activity was detected in four (4) of the fifty-four (54) samples collected.

The indicator average gross beta activity was 3.59 pCi/L and the control average gross beta

activity was 4.25 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 0comprehensive explanation for the observed difference is provided in the 1988 Annual

Environmental Operating Report.

R 0

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Radiological Environmental Monitoring Page 38 0

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

2 OD ODC D0 0C O0 0

)M a

)

D C

ý a

0 0

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a Year rindicator 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 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. Sediment is sampled twice each year from six (6) locations.

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

Twelve (12) sediment samples were collected in 2011 and analyzed by gamma spectroscopy. The predominant radionuclide detected by gamma spectral analysis was naturally occurring potassium-40.

Cesium-137 activity was detected in five (5) of the twelve (12) samples collected and ranged from 136.1 pCi/kg to 646.6 pCi/kg. The indicator average cesium-137 activity was 188.1 pCi/kg and the average control activity was 635.4 pCi/kg. The average cesium-137 radioactivity for all locations was 367.0 pCi/kg and is lower than the highest identified 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 39

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L ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 8: Annual Average Cesium-137 Concentration in Sediment Z')

1 600 1400 1 200 1 000 800 600 400 200 0

C'J C0) 1 fO Co r

00

) 0 N

MJ 'It LO (f N o

C) 0-C'l j C10 LOI (0 N 1

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) CY) 00 00000000; Ye ar 01 nd ic a to r MC on trol 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. Since then, 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.

On 5/26/10, manganese-54 and cobalt-58 (short half-life isotopes) were identified at location 64-9. Additionally, increased levels of cobalt-60 were identified at locations 64-6 and 64-9.

Identification of the short half life isotopes was documented and a subsequent investigation and corrective actions occurred. The investigation identified that contaminated runoff water from radioactive material movements and transport vehicles within the protected area probably flowed to the storm drain discharging to 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. For 2011, results from the nine (9) active impoundment sample locations shows Mn-54, Go-60 and Cs-1 37 activity. The shoreline sediment samples showed no activity other than naturally occurring potassium-40 which demonstrates that activity is staying within the site property and no longer migrating to the shoreline. The impoundment activities range from non-detectable to 872 +/- 36 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 40

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

LOCATION 6/17/11 06/21/11 10/20/11 11/02/11 12/1/11 64

< 8.8

< 10.3

< 10.3 64-1

<10

< 13 64-2

< 18

< 18 64-3 60

< 22 64-6 271 87 64-7 59 221 64-8 29 30 64-9

< 37 247 64-10

< 34 872 64-11 85

< 11 W-24 14 49.9 W-25

< 9

< 36.1

No sample available or insufficient sample for analysis

- No sample collected on this date Table 18: Northwest Drain Impoundment Cesium-137 Activity, pCi/kq (dry)

LOCATION 6/17/11 06/21/11 10/20/11 11/02/11 12/1/11 64

<6.2

<8.0 64-1

< 19

< 15 64-2 589 259 64-3 385 180 64-6 1530 2157 64-7 1704 1529 64-8 676 563 64-9 758 1070 64-10 1084 1364 64-11 977 220 W-24 351 2583 W-25 1433 3958 00 0

0 0

No sample available or insufficient sample for analysis

t No sample collected on this date Radiological Environmental Monitoring Page 41

S 0

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 2011, fish sampling was performed for PNPP by a local licensed 0I sport fisherman.

Six (6) fish samples including (2) Yellow Perch, (2) Catfish and (2) Freshwater Drum were

collected and analyzed by gamma spectral analysis in 2011. As expected, naturally occurring potassium-40 was found in all samples. No other radionuclides were detected

t above the LLD.

0 Direct Radiation Monitoring Thermoluminescent Dosimeter (TLD)

Environmental radiation is measured directly at 28 locations around the PNPP site, two of 0I 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 2011. 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 2011, the annual average dose for all indicator locations was 62.44 mrem, and 60.56 0

mrem for the control locations.

0 Referring to Figure 9, the average quarterly dose for all indicator locations was 12.96 mrem,

l and 12.55 mrem for all control locations. Please refer to Appendix C, 2011 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

D provided in the 1988 Annual Environmental Operating Report.

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

15 t

a 10 01005 0

O-O( J O*

sO.

Ofl 0" ON OD 0)0.

ON O*) 0" O

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0f C0 0- C 0)0-Y ear 0lndicator MCon tro I Conclusion Sediment samples continue to confirm manganese-54 and cobalt-60 in the northwest drain impoundment. (Cobalt-58 was not identified in 2011) 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.

Other than the activity detected that was attributed to Fukushima, 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 43 0

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INTER-LABORATORY CROSS-CHECK COMPARISON PROGRAM 0

Introduction O*

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 O0 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 0

established acceptance criteria indicate a need to check instruments or procedures.

0 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 O*

referenced in the regulatory guide is that the EPA standards were traceable to National O

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 O*

quality of their analyses by:

O*

Analyzing "spiked" samples (samples with a specific quantity of radioactive material

D present in them) and Participating in the Department of Energy's Mixed Analyte Performance Program (MAPEP).

O*

Through 2004, Teledyne also participated in the Environmental Measurements Laboratory O*

Quality Assessment Program (EML). This program was discontinued in 2005.

0 Conclusion Appendix A, 2011 Inter-Laboratory Cross-Check Comparison Program Results, includes results from both the above referenced programs and the ERA Company cross-check 0

program.

O

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 with one exception. The sample was reanalyzed and the result of the reanalysis O0 was acceptable.

O

2) Table A-2: The Vendor Laboratory's Cross-Check program results for the testing of Thermoluminescent Dosimetry were acceptable.

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3) Table A-3: Laboratory analysis results for In-House "Spike" samples were acceptable.

4) Table A-4: Laboratory analysis results for In-House "Blank" samples were acceptable.

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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.

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 with five exceptions. (1) Result of a repeat analysis was still unacceptable. ERA Crosschecks for Am-241 were acceptable but biased low. Matrix samples prepared to verify method; results were acceptable. Am-241 has been added to the internal spike and blank program for 2012. (2) An error in percent recovery was found, result of recalculation was satisfactory. (3) No errors were in calculation or procedure, results of reanalysis were satisfactory. (4) The analyses were repeated through a strontium column, mean result of triplicate analyses were satisfactory. (5) The lab does not currently analyze soil for Tc-99, but is evaluating the procedure.

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 acceptable.

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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 2011 Land Use Census, which was conducted August 2 nd and 3rd 2011 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).

Table 19 identifies the nearest residences, by sector, to the PNPP. For 2011, there were three (3) changes noted for the "nearest residence". The closest residences did not change, however with a more accurate map, the ENE, E and ESE locations were identified as being fractionally closer to the plant.

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 1.1 6.71 0E-07 2

E 2626 Antioch 1.0 1.141E-06 3

ESE 2836 Antioch 1.0 8.571 E-07 4

SE 4495 North Ridge 1.2 3.89E-07 5

SSE 3119 Parmly 0.9 1.89E-06 6

S 3121 Center 0.9 2.25E-06 7

SSW 3850 Clark 0.9 1.11 E-06 8

SW 2997 Perry Park 1.2 4.98E-07 9

WSW 3460 Parmly 1.1 8.67E-07 10 Radiological Environmental Monitoring Page 46

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 20 identifies the nearest milking animal by sector, to the PNPP. During the 2011 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 two (2) changes for the nearest gardens identified during this year's census.

Table 21 lists the nearest gardens occupying at least 500 square feet identified during the 2011 Land Use Census. The closest gardens did not change, however with a more accurate map, the E and ESE locations were identified as being fractionally closer to the plant.

Table 21: Nearest Garden, By Sector SECTOR LOCATION ADDRESS MILES FROM D/0 VALUE, MAP LOCATOR PNPP WM2)

NUMBER NE 2340 Lakehurst 1.0 7.45E-09 11 ENE 4630 Lockwood 1.2 4.11E-09 12 E

2626 Antioch 1.0 9.06E-09 3

ESE 2836 Antioch 1.0 6.78E-09 4

SE 4671 North Ridge 1.3 1.01 E-09 15 SSE 4225 Red Mill Valley 1.1 3.48E-09 16 S

3121 Center Rd.

0.9 1.31 E-08 7

SSW 3330 Ohio St.

2.3 4.65E-10 17 SW 3032 Perry Park 1.4 1.72E-09 13 WSW 2975 Perry Park 1.3 2.31 E-09 14 0

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 10: Land Use Census Map Garden*

ResidencefM Milking Animal RRadiological Environmental Monitoring Page 48

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 Dreissena polymorpha (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 2011 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 2011, 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: 2011 Corbicula Monitoring DATE SAMPLE LOCATION 2/13/2011 Service Water Pump House Intake Traveling Screen "A" 2/13/2011 Service Water Pump House Intake Traveling Screen "B" 3/22/2011 Strainer Fire Protection 4/22/2011 Auxiliary Condenser "A" 4/22/2011 Auxiliary Condenser "A" Waterbox 4/25/2011 LP Condenser Waterbox South 4/25/2011 Intermediate Condenser Waterbox South 4/25/2011 HP Condenser Waterbox South 4/26/2011 HP Condenser Waterbox North 4/26/2011 Intermediate Condenser Waterbox North 8/1/2011 Turbine Lube Oil Cooler "A" 9/2/2011 Turbine Lube Oil Cooler "B" 9/2/2011 ESW Screen Wash Pump 0

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0 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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 2011 monitoring program did not identify Corbicula in any sample collected.

Clam/Mussel Monitoring Page 50

0 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT DREISSENA PROGRAM 0

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.

0 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 0

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 2011 included chlorine and a commercial molluscicide.

0 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.

S The use of a commercial molluscicide has been approved by the Ohio Environmental 5

Protection Agency (OEPA). The chemical selected for use at the PNPP in 2011 was alkyl-dimethyl-benzyl-ammonium chloride. Treatment was applied once in 2011, on August 31.

The active ingredients were detoxified by adsorption using bentonite clay, prior to discharge into Lake Erie.

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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 S

inspected for new settlement. No live settlement has been found in any plant component to 5

date.

5 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-S through container for 2011 was 100%.

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

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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.

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 2011, four (4) general and three (3) 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, Accord, Polaris, Kingpin, Tempo Ultra, Oust, Escort, Super Signal Blue Concentrate and Razor. 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 2011. The quantity represents the amount of herbicide applied, prior to any dilution.

Table 23: 2011 Herbicide Applications DATE APPLIED LOCATION AMOUNT CHEMICAL NAME 4/7/11 Transmission Yard 800 gal.

Oust/ Escort 4/13/11 Transmission Yard 100 gal.

Oust/ Escort 5/24/11 Security Towers, Booths, PAF, Perifield Zone 2 oz.

Tempo Ultra 8/3/11 Security Towers, Booths, PAF, Periifeld Zone 10 gal.

Tempo Ultra 7/26/11 Transmission Yard 50 gal.

Razor 7/11 - 8/11 Transmission-Right-of-Ways 1,950 gal. Accord/ Polaris/ Kingpin Clam/Mussel Monitoring Page 52

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT S

SPECIAL REPORTS NON-COMPLIANCES NPDES Permit The National Pollutant Discharge Elimination System (NPDES) permit is issued by the Ohio 0

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 was no NPDES non-compliance issues identified in 2011.

Environmental Protection Plan 0

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 in 2011:

On October 17, 2011 approximately 1000 gallons of a diesel/gas fuel mixture was 0

spilled into the environment at the Fire Training facility, covering an area of 20 x 60 meters. The release entered a Class III wetlands just west of the Fire Training facility but did not enter Lake Erie. Clean Harbors Incorporated was contracted for the initial clean up and disposal. The storage tank has been cleaned and emptied and is no 5

longer in service. The associated underground piping has been removed. All areas affected by the release have been cleaned and will be re-evaluated in the spring.

Periodic sampling of piezometers and sentinel wells has indicated the release has not 0

migrated. All proper notifications to regulatory agencies were made as required.

0 UN-REVIEWED 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 2011 there were no proposed changes to the facility or programs that if performed could have resulted in an adverse environmental 5

impact. Therefore, there were no un-reviewed environmental questions identified.

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0 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX A 2011 INTER-LABORATORY CROSS CHECK COMPARISON PROGRAM RESULTS

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_0 AT Envirnmenta' Inc.

idwest Laboratory 700 Lendwehr Road

Northbrook, IL 60062-2310 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 through December, 2011

Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) 0 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 I sigma level for various analyses. The acceptance criteria 0

in Table A-3 is set at +/- 2 sigma.

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

A0 0

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0 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 Strontium-89b Strontium-90b Potassium-40 Gross alpha Gross beta 5 to 100 pCi/liter or kg

> 100 pCi/liter or kg 5 to 50 pCi/liter or kg

> 50 pCi/liter or kg 2 to 30 pCi/liter or kg

> 30 pCi/liter or kg

> 0.1 g/Iiter or kg

< 20 pCi/liter

> 20 pCi/liter

-< 100 pCi/liter

> 100 pCi/liter

< 4,000 pCi/liter Tritium 5.0 pCi/liter 5% of known value 5.0 pCi/liter 10% of known value 5.0 pCi/liter 10% of known value 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value

+/-1o =

169.85 x (known) 0 0 933 10% of known value 15% of known value 10% of known value 6 pCi/liter 10% of known value 6 pCi/liter 15% of known value 10 pCi/liter 10% of known value 20% of known value

> 4,000 pCi/liter

> 0.1 pCi/liter Radium-226,-228 Plutonium

> 0.1 pCi/liter, gram, or sample Iodine-131, Iodine-12 9 b Uranium-238, Nickel-63b Technetium-99b Iron-55b

-< 55 pCi/liter

> 55 pCi/liter

< 35 pCi/liter

> 35 pCi/liter 50 to 100 pCi/liter

> 100 pCi/liter Other Analyses b a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance STW-1243 04/04/11 Sr-89 STW-1243 04/04/11 Sr-90 STW-1244 STW-1 244 STW-1244 STW-1244 STW-1244 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 Ba-133 Co-60 Cs-1 34 Cs-137 Zn-65 68.2 +/- 5.8 44.3 +/- 2.4 69.8 +/- 3.9 87.9 +/- 3.8 69.5 +/- 3.7 77.9 +/- 5.3 105.2 +/- 8.4 63.2 42.5 75.3 88.8 72.9 77.0 98.9 50.1 49.8 27.5 12.1 11.6 39.8 STW-1245 04/04/11 Gr. Alpha 41.5 +/- 2.3 STW-1245 04/04/11 Gr. Beta 48.9 +/- 1.8 STW-1246 04/04/11 1-131 STW-1247 STW-1247 STW-1247 04/04/11 04/04/11 04/04/11 Ra-226 Ra-228 Uranium STW-1248 04/04/11 H-3 STW-1256 10/07/11 Sr-89 STW-1256 10/07/11 Sr-90 STW-1257 STW-1257 STW-1257 STW-1257 STW-1257 STW-1258 STW-1258 STW-1259 STW-1260 STW-1 260 STW-1260 STW-1261 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 Ba-1 33 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 26.6 +/- 1.7 13.2 +/- 0.6 11.2 +/-0.6 36.4 +/- 0.6 10322 +/-285 68.7 +/- 6.0 36.9 +/- 2.4 88.2 +/- 7.8 116.5 +/-7.1 38.8 +/- 8.0 45.6 +/- 7.3 84.9 +/- 15.4 35.7 +/- 3.8 36.1 +/- 3.3 25.0 +/- 1.1 12.2 +/- 0.6 11.5 +/- 1.7 46.6 +/- 0.5 17435 +/-382 69.7 41.1 10200.0 51.1 -71.2 31.3 -48.8 63.0 - 82.8 79.9 - 100.0 59.5 - 80.2 69.3 - 87.4 89.0-118.0 26.1 -62.9 33.8 - 56.9 22.9 - 32.3 9.0 - 14.0 7.6 - 14.3 32.2 - 44.4 8870 -11200 56.9 - 77.9 30.2 - 47.2 81.8 - 106.0 107.0 - 133.0 26.3 - 36.7 39.4 -51.7 68.9 - 92.5 27.8 - 66.6 30.9 - 53.1 22.9 - 32.3 8.7 -13.4 6.7 - 12.8 39.4 - 54.0 15200 - 19100 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass 0

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0 96.9 119.0 33.4 44.3 76.8 53.2 45.9 27.5 11.6 10.3 48.6 17400 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.

d The sample was reanalyzed. Result of reanalysis was acceptable, 32.9 +/- 7.4 pCi/L.

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0 TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).

mR Lab Code Date Known Lab Result Control Description Value

+/- 2 sigma Limits Acceptance Environmental, Inc.

2010-2 2010-2 2010-2 2010-2 2010-2 2010-2 2010-2 2010-2 2010-2 2010-2 2010-2 12/13/2010 12/13/2010 12/13/2010 12/13/2010 12/13/2010 12/13/2010 12/13/2010 12/13/2010 12/13/2010 12/13/2010 12/13/2010 100 cm.

110 cm.

120 cm.

150 cm.

180 cm.

40 cm.

50 cm.

60 cm.

80 cm.

90 cm.

4.94 4.09 3.43 2.2 1.53 30.89 19.77 13.73 13.73 7.72 6.1 4.65 +/- 0.57 3.50 +/- 0.74 2.68 +/- 0.36 1.75 +/- 0.42 1.32 +/- 0.52 38.56 +/- 2.11 23.35 +/- 1.82 14.53 +/- 1.24 15.84 +/- 1.53 8.33 +/- 0.74 5.93 +/- 0.73 3.46 - 6.42 2.86 - 5.32 2.40 - 4.46 1.54 -2.86 1.07-1.99 21.62 - 40.16 13.84 - 25.70 9.61 - 17.85 9.61 - 17.85 5.40 - 10.04 4.27 - 7.93 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Environmental, Inc.

2011-1 2011-1 2011-1 2011-1 2011-1 2011-1 2011-1 2011-1 2011-1 2011-1 2011-1 2011-1 7/6/2011 7/6/2011 7/6/2011 7/6/2011 7/6/2011 7/6/2011 7/6/2011 7/6/2011 7/6/2011 7/6/2011 7/6/2011 7/6/2011 100 cm.

110 cm.

120 cm.

150 cm.

180 cm.

40 cm.

45 cm.

50 cm.

60 cm.

70 cm.

80 cm.

90 cm.

6.71 5.54 4.66 2.98 2.07 41.92 33.12 26.83 18.63 13.69 10.48 8.28 5.64 +/- 0.30 4.60 +/- 0.46 4.68 +/- 0.29 2.93 +/- 0.66 2.05 +/- 0.18 52.36 +/- 3.08 41.83 +/- 3.46 28.61 +/- 2.63 21.00 +/- 1.15 13.24 +/- 1.76 12.18 +/- 0.65 7.95 +/- 0.82 4.70 - 8.72 3.88 - 7.20 3.26 - 6.06 2.09 - 3.87 1.45 -2.69 29.34 - 54.50 23.18 - 43.06 18.78 - 34.88 13.04 - 24.22 9.58 - 17.80 7.34 - 13.62 5.80 - 10.76 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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=l c Activity Limits d Acceptance SPW-202 W-20111 W-20711 W-20711 XWW-331 XWW-331 XWW-331 XWW-331 SPAP-567 SPAP-569 SPAP-569 SPAP-571 SPW-581 SPW-581 SPW-581 SPW-581 SPMI-583 SPMI-583 SPW-602 SPW-686 SPF-1113 XWW-1 602 XWW-1602 XWW-1602 XWW-1602 XWW-2537 XWW-2537 XWW-2537 XWW-2537 SPW-2877 SPMI-3167 SPMI-3167 SPMI-3167 SPMI-3167 W-52411 W-60711 W-60711 SPAP-4167 SPAP-4167 SPW-4169 SPW-4169 1/17/2011 2/1/2011 2/7/2011 2/7/2011 2/11/2011 2/11/2011 2/11/2011 2/11/2011 2/14/2011 2/14/2011 2/14/2011 2/14/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/17/2011 2/25/2011 3/17/2011 3/21/2011 3/21/2011 3/21/2011 3/21/2011 4/4/2011 4/4/2011 4/4/2011 4/4/2011 5/3/2011 5/24/2011 5/24/2011 5/24/2011 5/24/2011 5/24/2011 6/7/2011 6/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 U-238 Ra-226 Gr. Alpha Gr. Beta Ba-133 Cs-134 Cs-137 H-3 Gr. Beta Cs-1 34 Cs-1 37 H-3 Cs-1 34 Cs-137 Sr-89 Sr-90 Cs-137 Sr-90 U-238 Ni-63 Cs-1 37 Ba-1 33 Cs-1 34 Cs-1 37 H-3 Ba-1 33 Cs-1 34 Cs-137 H-3 Ra-228 Cs-1 34 Cs-1 37 Sr-89 Sr-90 Ra-226 Gr. Alpha Gr. Beta Cs-134 Cs-1 37 Cs-1 34 Cs-137 4.19 +/- 0.19 16.32 +/- 0.47 23.02 +/- 0.45 46.59 +/- 0.41 144.30 +/- 8.50 22.20 +/- 3.70 64.70 +/- 7.40 13399 +/-334 46.90 +/- 0.11 7.70 +/- 1.70 102.47 +/- 3.20 75815 +/- 542 39.91 +/- 1.38 56.28 +/- 2.28 112.92 +/- 5.61 47.80 +/- 2.02 57.04 +/- 2.76 36.27 +/- 1.47 3.98 +/- 0.19 167.41 +/- 3.05 2369 +/- 22 26.83 +/- 6.35 18.90 +/- 4.06 33.98 +/- 5.88 7348 +/- 248 43.40 +/- 4.26 13.50 +/- 2.40 68.30 +/- 5.90 7134 +/- 257 25.23 +/- 2.48 33.04 +/- 8.25 51.53 +/- 8.63 90.89 +/- 4.30 41.17 +/- 1.53 17.90 +/- 0.42 23.00 +/- 0.49 43.27 +/- 0.42 6.92 +/- 1.45 108.02 +/- 2.84

.34.52 +/- 4.79 58.29 +/- 6.19 4.17 16.77 20.00 45.20 144.40 21.50 61.00 12538 48.10 7.49 106.79 73230 37.45 53.39 121.42 42.07 53.39 42.07 4.17 208.11 2170 28.58 16.30 30.50 7617 42.70 11.90 60.70 7234 31.62 34.19 53.06 93.47 41.80 16.80 20.00 45.20 6.57 105.80 32.84 52.92 0.00 - 16.17 11.74 - 21.80 10.00 -30.00 35.20 - 55.20 129.96 - 158.84 11.50 - 31.50 51.00 -71.00 10030 - 15046 28.86 - 67.34 0.00 - 17.49 96.11 - 117.47 58584 - 87876 27.45 - 47.45 43.39 - 63.39 97.14 - 145.70 33.66 - 50.48 43.39 - 63.39 33.66 - 50.48 0.00 - 16.17 145.68 -270.54 1953 -2387 18.58 - 38.58 6.30 - 26.30 20.50 -40.50 6094 -9140 32.70 - 52.70 1.90 -21.90 50.70 - 70.70 5787 - 8681 22.13 - 41.11 24.19 - 44.19 43.06 - 63.06 74.78 -112.16 33.44 -50.16 11.76 - 21.84 10.00 -30.00 35.20 - 55.20 0.00 - 16.57 95.22 -116.38 22.84 - 42.84 42.92 - 62.92 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 0

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0 0

S 0

0 Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-4169 SPW-4169 SPW-4171 SPW-4180 SPW-41821 SPW-4241 SPW-4180 SPW-5029 SPW-5031 W-9141 I W-9141 1 SPW-91511 W-91911 W-100711 W-100711 W-101111 XWW-7220 XWW-7220 XWW-7220 W-113011 W-120111 W-120111 SPW-41823 SPMI-8906 SPMI-8906 SPW-8916 SPW-8916 SPAP-8902 SPAP-8904 SPAP-8904 SPW-8918 SPW-8922 SPW-8924 SPF-8926 SPF-8926 7/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 7/8/2011 7/29/2011 7/29/2011 9/14/2011 9/14/2011 9/15/2011 9/19/2011 10/7/2011 10/7/2011 10/11/2011 11/17/2011 11/17/2011 11/17/2011 11/30/2011 12/1/2011 12/1/2011 12/9/2011 12/22/2011 12/22/2011 12/22/2011 12/22/2011 12/23/2011 12/23/2011 12/23/2011 12/23/2011 12/23/2011 12/23/2011 12/23/2011 12/23/2011 Sr-89 Sr-90 H-3 Tc-99 Ra-228 Ni-63 Tc-99 C-14 Fe-55 Gr. Alpha Gr. Beta Tc-99 Ra-226 Gr. Alpha Gr. Beta Ra-226 Ba-1 33 Cs-134 Cs-137 Ra-226 Gr. Alpha Gr. Beta Ra-228 Cs-134 Cs-137 Cs-134 Cs-137 Gr. Beta Cs-134 Cs-137 H-3 Ni-63 Tc-99 Cs-1 34 Cs-137 66.12 +/- 4.18 41.72 +/- 1.79 70582 +/- 767 95.69 +/- 1.65 32.57 +/- 2.63 403.01 +/- 4.66 100.30 +/- 1.75 3991 +/- 17 13801 +/- 331 21.58 +/- 0.44 43.02 +/- 0.40 29.92 +/- 1.07 17.06 +/- 0.42 22.05 +/- 0.45 45.51 +/- 0.41 16.02 +/- 0.40 25.11 +/- 4.36 14.09 +/- 3.11 35.59 +/- 4.28 16.12 +/- 0.39 21.34 +/- 0.43 45.55 +/- 0.41 26.98 +/- 2.38 29.11 +/- 3.52 58.27 +/- 7.62 31.74 +/- 3.63 56.48 +/- 6.12 45.72 +/- 0.11 5.19 +/- 0.63 101.21 +/- 2.55 136759 +/- 1056 202.21 +/- 3.75 126.10 +/- 1.86 0.34 +/- 0.01 2.34 +/- 0.02 69.64 41.68 71646 97.02 30.63 415.20 97.02 4739 14895 20.00 45.20 32.34 16.80 20.00 45.20 16.80 27.47 16.60 29.98 16.80 20.00 45.20 29.40 28.14 52.36 28.14 52.36 47.11 5.63 104.71 137638 206.88 129.36 0.33 2.09 55.71 -83.57 33.34 - 50.02 57317 -85975 67.91 - 126.13 21.44 -39.82 290.64 - 539.76 67.91 -126.13 2843 - 6634 11916 -17874 10.00 - 30.00 35.20 - 55.20 20.34 - 44.34 11.76 - 21.84 10.00 -30.00 35.20 - 55.20 11.76 - 21.84 17.47 - 37.47 6.60 - 26.60 19.98 -39.98 11.76 - 21.84 10.00 -30.00 35.20 - 55.20 20.58 -38.22 18.14 - 38.14 42.36 -62.36 18.14 - 38.14 42.36 - 62.36 28.27 - 65.95 0.00 - 15.63 94.24 - 115.18 110110 - 165166 144.82 - 268.94 90.55 - 168.17 0.20 - 0.47 1.25 -2.93 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m 3), and solid samples (pCi/g).

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

CH (charcoal canister), F (fish), U (urine).

c Results are based on single determinations.

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

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)r Lab Code Sample Date Analysisb Laboratory results (4.66a)

Acceptance Type LLD Activityc Criteria (4.66 a)

SPW-202 W-20111 W-20711 W-20711 SPAP-566 SPAP-568 SPAP-568 SPAP-570 SPW-580 SPW-580 SPW-580 SPW-580 SPMI-582 SPMI-582 SPMI-582 SPMI-582 SPMI-582 SPW-601 SPW-685 SPF-1112 SPF-1112 BKW-401 11 BKW-401 11 BKW-401 11 BKW-401 11 SPW-2887 W-52411 W-60711 W-60711 SPAP-4164 SPW-4168 SPW-4168 SPW-4168 SPW-4168 SPW-4171 SPW-41811 Water Water Water Water Air Filter Air Filter Air Filter Air Filter Water Water Water Water Milk Milk Milk Milk Milk Water Water Fish Fish Water Water Water Water Water Water Water Water Air Filter Water Water Water Water Water Water 1/17/2011 2/1/2011 2/7/2011 2/7/2011 2/14/2011 2/14/2011 2/14/2011 2/14/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/17/2011 2/25/2011 3/17/2011 3/17/2011 4/1/2011 41112011 4/1/2011 4/1/2011 5/3/2011 5/24/2011 6/7/2011 6/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 U-238 Ra-226 Gr. Alpha Gr. Beta Gr. Beta Cs-1 34 Cs-1 37 H-3 Cs-1 34 Cs-1 37 Sr-89 Sr-90 Cs-134 Cs-1 37 1-131(G)

Sr-89 Sr-90 U-238 Ni-63 Cs-134 Cs-1 37 1-131 Co-60 Cs-1 34 Cs-137 Ra-228 Ra-226 Gr. Alpha Gr. Beta Gr. Beta Cs-1 34 Cs-137 Sr-89 Sr-90 H-3 Ra-228 0.10 0.04 0.44 0.75 0.64 2.34 1.56 103.20 2.68 2.84 0.73 0.57 3.49 3.54 4.14 0.71 0.55 0.20 1.61 6.74 5.45 4.16 3.11 4.73 5.04 0.72 0.04 0.51 1.58 0.72 3.41 2.45 0.72 0.51 152.00 0.77 0.12 +/- 0.12 0.05 +/- 0.03

-0.02 +/- 0.29

-0.03 +/- 0.53 2.24 +/- 0.61

-49.40 +/- 52.50 0.24 +/- 0.57 0.02 +/- 0.27 0.16 +/- 0.67 0.59 +/- 0.32 0.09 +/- 0.17 0.05 +/- 0.98 0.46 +/- 0.39 0.05 +/- 0.03 0.00 +/- 0.36 0.38 +/- 1.12 1.04 +/- 0.48 0.40 +/- 0.50

-0.19 +/- 0.21 37.10 +/- 81.80 0.51 +/- 0.42 1

3.2 3.2 100 100 200 10 10 5

1 10 10 20 5

1 1

20 100 100 10 10 10 10 2

1 1

3.2 3.2 10 10 5

1 200 2

0 0

0 A4-1

0 0

0 S

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 a)

SPW-4241 SPW-4179 SPW-5028 SPW-5031 W-91411 W-91411 SPW-91511 W-91911 W-100711 W-100711 W-101111 W-113011 W-120111 W-120111 SPW-41813 SPMI-8905 SPMI-8905 SPMI-8905 SPW-8915 SPW-8915 SPW-8915 SPAP-8901 SPAP-8903 S PAP-8903 SPW-8917 SPW-8921 SPW-8923 SPF-8925 SPF-8925 Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Milk Milk Milk Water Water Water Air Filter Air Filter Air Filter Water Water Water Fish Fish 7/7/2011 7/8/2011 7/29/2011 7/29/2011 9/14/2011 9/14/2011 9/15/2011 9/19/2011 10/7/2011 10/7/2011 10/11/2011 11/30/2011 12/1/2011 12/1/2011 12/9/2011 12/22/2011 12/22/2011 12/22/2011 12/22/2011 12/22/2011 12/22/2011 12/23/2011 12/23/2011 12/23/2011 12/23/2011 12123/2011 12/23/2011 12/23/2011 12/23/2011 Ni-63 Tc-99 C-14 Fe-55 Gr. Alpha Gr. Beta Tc-99 Ra-226 Gr. Alpha Gr. Beta Ra-226 Ra-226 Gr. Alpha Gr. Beta Ra-228 Cs-134 Cs-137 1-131(G)

Cs-134 Cs-137 1-131(G)

Gr. Beta Cs-1 34 Cs-137 H-3 Ni-63 Tc-99 Cs-1 34 Cs-1 37 1.70 1.20 109.80 140.60 0.48 0.78 1.11 0.03 0.44 0.76 0.04 0.03 0.41 0.75 0.71 3.27 3.38 2.17 3.37 3.45 3.38 0.78 1.65 2.41 150.20 16.92 5.66 7.15 9.73 0.09 +/- 1.03

-0.96 +/- 0.71 61.90 +/- 59.20 0.00 +/- 85.30

-0.06 +/- 0.33

-0.43 +/- 0.53

-0.62 +/- 0.66 0.04 +/- 0.02

-0.26 +/- 0.28

-0.43 +/- 0.52 0.05 +/- 0.03 0.04 +/- 0.02

-0.20 +/- 0.27

-0.10 +/- 0.53 0.17 +/- 0.35 0.50 +/- 0.46

-3.04 +/- 78.80

-4.60 +/- 10.16

-5.45 +/- 3.34 20 10 200 1000 1

3.2 10 1

1 3.2 1

1 1

3.2 2

10 10 20 10 10 20 3.2 100 100 200 20 10 100 100 a 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.

c 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)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 CF-20, 21 CF-20, 21 WW-65, 66 BS-165, 166 BS-165, 166 BS-165, 166 BS-176, 177 BS-176, 177 BS-197, 198 BS-197, 198 BS-197, 198 WW-358, 359 DW-20009, 20010 DW-20009, 20010 WW-337, 338 W-491, 492 W-491, 492 DW-20014, 20015 SWU-447, 448 W-694, 695 DW-20022, 20023 SW-626, 627 LW-825, 826 SWT-845, 846 MI-998, 999 W-1024, 1025 WW-1156, 1157 P-1198, 1199 SW-1434, 1435 WW-1588, 1589 SG-1714, 1715 SG-1714, 1715 AP-1862, 1863 W-2143, 2144 AP-2269, 2270 DW-20061, 20062 SWU-1455, 1456 SWU-1522, 1523 PM-1543, 1544 PM-1543, 1544 113/2011 1/3/2011 1/312011 1/6/2011 1/11/2011 1/11/2011 1/11/2011 1/11/2011 1/111/2011 1/11/2011 1/11/2011 1/11/2011 1/17/2011 1/19/2011 1/19/2011 1/25/2011 1127/2011 1/27/2011 1/28/2011 1/31/2011 2/7/2011 2/9/2011 2/16/2011 2/24/2011 3/1/2011 3/7/2011 3/7/2011 3/16/2011 3/17/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/29/2011 3/29/2011 3/29/2011 3/29/2011 Be-7 K-40 Sr-90 H-3 Cs-137 H-3 K-40 H-3 K-40 Cs-1 37 H-3 K-40 H-3 Ra-226 Ra-228 H-3 Ra-226 Ra-228 Gr. Alpha Gr. Beta H-3 Ra-228 H-3 Gr. Beta Gr. Beta K-40 H-3 Gr. Beta H-3 H-3 Gr. Beta Gr. Alpha Gr. Beta Be-7 H-3 Be-7 Gr. Alpha Gr. Beta Gr. Beta Gr. Beta Sr-90 0.24 10.37 0.01 321.91 0.13 286.00 14.11 391.00 9.06 0.14 459.00 14.40 331.44 3.66 1.51 21986 6.70 6.60 1.91 7.42 628.26 0.71 1268.17 2.65 1.11 1760.10 489.83 1.79 504.00 15523 1.81 8.82 13.78 0.09 536.40 0.07 2.82 2.50 1.36 13.81 8.12

+/- 0.14

+/- 0.43

+/- 0.01

+/- 97.19

+/- 0.02

+/- 80.00

+/- 0.52

+/- 92.00

+/- 0.44

+/- 0.03

+/- 103.00

+/- 0.77

+/- 93.05

+/- 0.57

+/- 0.64

+/- 402

+/- 0.50

+/- 1.30

+/- 0.71

+/- 1.17

+/- 104.30

+/- 0.47

+/- 129.52

+/- 0.82

+/- 0.39

+/- 127.50

+/- 101.09

+/- 0.78

+/- 133.00

+/- 359

+/- 1.23

+/- 0.81

+/- 0.65

+/- 0.02

+/- 99.37

+/- 0.01

+/- 1.33

+/- 0.75

+/- 0.87

+/- 0.26

+/- 3.20 0.34 +/- 0.17 9.76 +/- 0.68 0.01 +/- 0.01 345.76 +/- 98.16 0.15 +/- 0.02 284.00 +/- 80.00 13.79 +/- 0.60 332.00 +/- 89.00 8.28 +/- 0.81 0.15 +/- 0.04 283.00 +/- 95.00 14.16 +/- 1.23 407.65 +/- 95.91 2.74 +/- 0.43 1.36 +/- 0.60 21896 +/- 401 6.10 +/- 0.50 8.40 +/- 1.40 2.34 +/- 0.80 6.85 +/- 1.11 692.37 +/- 106.89 1.13 +/- 0.54 1144.65 +/- 125.39 2.45 +/- 0.74 0.80 +/- 0.37 1708.50 +/- 131.60 581.39 +/- 105.06 0.47 +/- 0.66 597.00 +/- 136.00 15968 +/- 364 2.81 +/- 1.38 8.58 +/- 0.74 12.76 +/- 0.58 0.08 +/- 0.02 466.79 +/- 96.46 0.08 +/- 0.01 3.89 +/- 1.26 2.75 +/- 0.83 2.14 +/- 0.96 13.67 +/- 0.27 7.71 +/- 3.25 0.29 +/- 0.11 10.07 0.01 333.83 0.14 285.00 13.95 361.50 8.67 0.15 371.00 14.28 369.55 3.20 1.44 21941 6.40 7.50 2.13 7.14 660.32

+/- 0.40

+/- 0.00

+/- 69.06

+/- 0.01

+/- 56.57

+/- 0.40

+/- 64.00

+/- 0.46

+/- 0.03

+/- 70.06

+/- 0.73

+/- 66.81

+/- 0.36

+/- 0.44

+/- 284

+/- 0.35

+/- 0.96

+/- 0.53

+/- 0.81

+/- 74.67 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 00 0

0 0

0.92 +/- 0.36 1206.41 +/- 90.14 2.55 +/- 0.55 0.96 +/- 0.27 1734.30 +/- 91.62 535.61 +/- 72.90 1.13 +/- 0.51 550.50 +/- 95.11 15746 +/-256 2.31 +/- 0.92 8.70 +/- 0.55 13.27 +/- 0.44 0.08 +/- 0.01 501.59 +/- 69.25 0.07 +/- 0.01 3.36 +/- 0.92 2.62 +/- 0.56 1.75 +/- 0.65 13.74 +/- 0.19 7.91 +/- 2.28 A5-1

TABLE A-5. In-House "Duplicate" Samples 0S 0

0 0

0 Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SWT-5885, 5886 AP-1883,1884 AP-2248, 2249 DW-20066, 20067 DW-20066, 20067 P-1567,1568 MI-1609,1610 MI-1609,1610 MI-1609,1610 S-1651, 1652 S-1651, 1652 AP-1841, 1842 AP-1841, 1842 AP-1841, 1842 S-1990,1991 S-1990,1991 WW-2552,2553 PM-1904,1905 PM-1904,1905 P-2011, 2012 WW-2053, 2054 BS-2095, 2096 DW-20099, 20100 DW-20099,20100 WW-2416,2417 P-2185, 2186 WW-2353,2354 DW-20115, 20116 DW-20115, 20116 SO-2960, 2961 MI-2657, 2658 DW-20130, 20131 DW-20130, 20131 DW-20148, 20149 DW-20148, 20149 PM-2810,2811 PM-2810,2811 PM-2810,2811 WW-3065,3066 WW-3086, 3087 3/29/2011 3/30/2011 3/30/2011 3/30/2011 3/30/2011 4/11/2011 4/4/2011 4/4/2011 4/4/2011 4/4/2011 4/4/2011 4/7/2011 4/7/2011 4/7/2011 4/7/2011 4/7/2011 4/7/2011 4/11/2011 4/11/2011 4/11/2011 4/13/2011 4/13/2011 4/13/2011 4/13/2011 4/19/2011 4/20/2011 4/20/2011 4/26/2011 4/26/2011 4/27/2011 5/2/2011 5/2/2011 5/2/2011 5/3/2011 5/3/2011 5/4/2011 5/4/2011 5/4/2011 5/16/2011 5/16/2011 Gr. Beta Be-7 Be-7 Ra-226 Ra-228 H-3 1-131 K-40 Sr-90 Ac-228 Pb-214 Be-7 Cs-1 37 1-131 (G)

Ac-228 Pb-214 H-3 K-40 Sr-90 H-3 H-3 K-40 U-233/4 U-238 H-3 H-3 H-3 U-233/4 U-238 K-40 K-40 U-233/4 U-238 U-233/4 U-238 Cs-1 34 Cs-137 K-40 H-3 H-3 1.21 +/- 0.54 0.07 +/- 0.01 0.06 +/- 0.01 2.14 +/- 0.16 2.55 +/- 0.65 289.00 +/- 103.00 0.85 +/- 0.17 1323.80 +/- 112.00 0.85 +/- 0.33 0.88 +/- 0.08 1.09 +/- 0.12 0.12 +/- 0.02 0.00 +/- 0.00 0.02 +/- 0.00 15.83 +/- 0.39 11.21 +/- 0.23 761.09 +/- 116.48 13585 +/- 611 9.94 +/- 3.05 670.00 +/- 108.00 220.20 +/- 86.50 12.88 +/- 0.72 1.64 +/- 0.40 1.49 +/- 0.39 217.10 +/- 97.00 405.00 +/- 93.00 525.54 +/- 119.74 11.94 +/- 2.34 2.70 +/- 1.15 22.63 +/- 1.36 1319.30 +/- 101.30 7.59 +/- 0.90 4.67 +/- 0.72 6.64 +/- 0.83 6.11 +/- 0.83 18.64 +/- 12.16 28.99 +/- 14.92 14368 +/- 720 280.51 +/- 86.98 341.14 +/- 85.94 0.77 0.09 0.06 2.10 1.78 296.00 0.91 1323.20 0.97 1.03 0.84 0.12 0.00 0.03 16.12 11.81 759.04 14278 5.62 619.00 246.80 13.56 1.31 1.28 184.90 504.00 399.41 10.71 3.89 22.90 1403.20 7.62 4.84 6.35 5.18 33.33 21.17 14309 179.46 377.97

+/- 0.54

+/- 0.02

+/- 0.01

+/- 0.16

+/- 0.62

+/- 103.00

+/- 0.18

+/- 96.22

+/- 0.34

+/- 0.22

+ 0.16

+/- 0.01

+/- 0.00

+/- 0.64

+/- 1.22

+/- 116.41

+/- 648

+/- 2.52

+/- 106.00

+/- 87.80

+ 1.08

+/- 0.34

+/- 0.33

+/- 95.60

+/- 98.00

+/- 115.99

+/- 1.19

+/- 0.72

+/- 0.03

+/- 131.60

+/- 0.83

+/- 0.66

+/- 0.81

+/- 0.73

+/- 11.86

+/- 12.16

+/- 638

+/- 82.83

+/- 87.43 0.99 +/- 0.38 0.08 +/- 0.01 0.06 +/- 0.01 2.12 +/- 0.11 2.17 +/- 0.45 292.50 +/- 72.83 0.88 +/- 0.13 1323.50 +/- 73.83 0.91 +/- 0.24 0.96 +/- 0.12 0.97 +/- 0.10 0.12 +/- 0.01 0.00 +/- 0.00 0.03 +/- 0.00 15.98 +/- 0.37 11.51 +/- 0.62 760.07 +/- 82.34 13932 +/-445 7.78 +/- 1.98 644.50 +/- 75.66 233.50 +/- 61.63 13.22 +/- 0.65 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 1.48 1.39 201.00 454.50 462.48 11.33 3.30 22.77 1361.25 7.61 4.76 6.50 5.65 25.99 25.08 14339 229.98 359.56

+/- 0.26

+/- 68.10

+/- 67.55

+/- 83.35

+/- 1.31

+/- 0.68

+/- 83.04

+/- 0.61

+/- 0.49

+/- 0.58

+/- 0.55

+/- 8.49

+/- 9.62

+/- 481

+/- 60.05

+/- 61.30 A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SG-3134, 3135 SG-3134, 3135 F-3221, 3222 SS-3434, 3435 AP-3329, 3330 WW-3350, 3351 G-3413, 3414 G-3413, 3414 G-3413, 3414 AP-3602, 3603 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 MI-3935, 3936 BS-4172, 4173 BS-4172, 4173 DW-20183, 20184 DW-20183, 20184 WW-4019, 4020 PM-4193, 4194 LW-4235, 4236 AP-4367, 4368 MI-4416, 4417 W-4914, 4915 MI-4438, 4439 VE-4481, 4482 AP-4677, 4678 W-5537, 5538 P-4764, 4765 WW-5211, 5212 5/16/2011 5/16/2011 5/23/2011 5/25/2011 5/26/2011 6/1/2011 6/1/2011 6/11/2011 6/1/2011 6/3/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 61812011 6/8/2011 6/20/2011 6/21/2011 6/21/2011 6/21/2011 6/21/2011 6/24/2011 6/30/2011 6/30/2011 7/7/2011 7/11/2011 7/11/2011 7/12/2011 7/13/2011 7/15/2011 7/18/2011 7/19/2011 7/24/2011 Ac-228 Pb-2114 K-40 K-40 Be-7 H-3 Be-7 Gr. Beta K-40 Be-7 Ac-228 Bi-212 Bi-214 Cs-1 37 K-40 Pb-212 Pb-2114 Th-232 U-233/4 U-238 K-40 Cs-1 37 K-40 U-233/4 U-238 Gr. Beta K-40 Gr. Beta 11.19 +/- 0.82 9.12 +/- 0.17 2.73 +/- 0.39 11533.00 +/- 563.70 0.24 +/- 0.11 235.37 +/- 83.98 0.28 +/- 0.10 11.04 +/- 0.31 6.80 +/- 0.33 0.20 +/- 0.08 0.99 +/- 0.05 1.10 +/- 0.12 0.87 +/- 0.02 0.41 +/- 0.01 16.08 +/- 0.26 0.98 +/- 0.10 0.95 +/- 0.02 0.47 +/- 0.05 0.16 +/- 0.02 0.16 +/- 0.02 12.50 +/- 0.84 9.37 +/- 0.42 2.81 +/- 0.42 11236.00 +/- 566.10 0.23 +/- 0.13 173.12 +/- 81.05 0.25 +/- 0.09 10.85 +/- 0.31 6.71 +/- 0.38 0.25 +/- 0.10 1.00 +/- 0.06 1.08 +/- 0.17 0.86 +/- 0.02 0.39 +/- 0.01 16.27 +/- 0.29 0.93 +/- 0.02 0.91 +/- 0.02 0.49 +/- 0.04 0.15 +/- 0.02 0.13 +/- 0.02 1843.10 +/- 136.50 48.57 +/- 17.06 11120.00 +/- 512.30 8.40 +/- 0.90 6.10 +/- 0.80 3.16 +/- 1.21 14660.00 +/- 750.00 2.11 +/- 0.78 0.19 +/- 0.11 1447.00 +/- 114.80 584.67 +/- 110.67 1381.20 +/- 112.70 4767.90 +/- 349.70 0.23 +/- 0.09 695.39 +/- 106.94 138.72 +/- 82.79 136.22 +/- 82.76 11.85 +/- 0.59 9.25 +/- 0.23 2.77 +/- 0.29 11384.50 +/- 399.45 0.24 +/- 0.08 204.25 +/- 58.36 0.27 +/- 0.07 10.95 +/- 0.22 6.76 +/- 0.25 0.22 +/- 0.07 1.00 +/- 0.04 1.09 +/- 0.10 0.87 +/- 0.01 0.40 +/- 0.01 16.18 +/- 0.19 0.96 +/- 0.05 0.93 +/- 0.01 0.48 +/- 0.03 0.16 +/- 0.01 0.15 +/- 0.01 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 1764.60 51.50 11730.00 10.00 6.70 3.56 14795.00 2.70 0.17 1342.40 576.36 1280.60 4452.60 0.18 650.13 179.82 191.94

+/- 119.40

+/- 23.78

+/- 679.60

+/- 1.00

+/- 0.80

+/- 1.20

+/- 759.00

+/- 0.72

+/- 0.10

+/- 91.49

+/- 110.35

+/- 107.50

+/- 332.40

+/- 0.08

+/- 105.19

+/- 84.81

+/- 85.50 1803.85 50.04 11425.00 9.20 6.40 3.36 14727.50 2.41 0.18 1394.70 580.52 1330.90 4610.25 0.20 672.76 159.27 164.08

+/- 90.68

+/- 14.63

+/- 425.53

+/- 0.67

+/- 0.57

+/- 0.85

+/- 533.52

+/- 0.53

+/- 0.07

+/- 73.40

+/- 78.14

+/- 77.87

+/- 241.24

+/- 0.06

+/- 75.00

+/- 59.26

+/- 59.50 00 0

0 0

Be-7 K-40 H-3 K-40 K-40 Be-7 H-3 H-3 H-3 A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance 0

0 0

0 S

0 0

0 VE-4998, 4999 VE-4998, 4999 DW-20258, 20259 DW-20258, 20259 DW-20258, 20259 DW-20269, 20270 DW-20269, 20270 DW-20280, 20281 DW-20280, 20281 MI-5019, 5020 W-5447, 5448 G-5124, 5125 AP-5232, 5233 SL-5169, 5170 SL-5169, 5170 SL-5169, 5170 G-5190,5191 G-5190,5191 G-5190,5191 DW-20291, 20292 DW-20291, 20292 SG-5342,5343 SG-5342, 5343 SG-5342, 5343 SG-5342, 5343 SG-5342, 5343 MI-5405, 5406 DW-20301, 20302 DW-20301, 20302 DW-5603, 5604 VE-5753, 5754 VE-5753, 5754 S-5801, 5802 S-5801, 5802 S-5801, 5802 S-5801, 5802 S-5801, 5802 S-5801, 5802 ME-5996, 5997 ME-5996, 5997 ME-5996, 5997 7/25/2011 7/25/2011 7/25/2011 7/25/2011 7/25/2011 7/25/2011 7/25/2011 7/25/2011 7/25/2011 7/26/2011 7/26/2011 7/28/2011 7/28/2011 8/1/2011 8/1/2011 8/1/2011 8/1/2011 8/1/2011 8/1/2011 8/2/2011 8/2/2011 8/5/2011 8/5/2011 8/5/2011 8/5/2011 8/5/2011 8/8/2011 8/9/2011 8/9/2011 8/16/2011 8/22/2011 8/22/2011 8/29/2011 8/29/2011 8/29/2011 8/29/2011 8/29/2011 8/29/2011 9/1/2011 9/1/2011 9/1/2011 Be-7 K-40 U-233/4 U-235 U-238 U-233/4 U-238 U-233/4 U-238 K-40 H-3 Gr. Beta Be-7 Be-7 Gr. Beta K-40 Be-7 Gr. Beta K-40 U-233/4 U-238 Ac-228 Bi-212 K-40 Pb-2114 TI-208 K-40 Gr. Alpha Gr. Beta Ra-228 Be-7 K-40 Ac-228 K-40 Pb-212 Pb-2114 TI-208 U-235 Gr. Alpha Gr. Beta K-40 543.90 2562.20 21.34 0.57 14.11 4.93 3.26 3.58 1.64 1348.50 246.31 7.48 0.15 2.37 4.74 3.12 3.14 8.07 5.51 3.24 1.59 14.41 4.14 7.67 10.72 0.96 1545.30 6.36 14.36 1.68 0.78 6.16 0.43 6.54 0.31 0.28 0.14 0.05 0.03 2.55 2.66

+/- 158.20

+/- 319.80

+/- 1.52

+/- 0.26

+/- 1.24

+/- 0.73

+/- 0.60

+/- 0.58

+/- 0.40

+/- 101.00

+/- 99.19

+/- 0.20

+/- 0.08

+/- 0.16

+/- 0.45

+/- 0.16

+/- 0.30

+/- 0.28

+/- 0.46

+/- 0.54

+/- 0.38

+/- 0.36

+/- 0.65

+/- 0.92

+/- 0.21

+/- 0.06

+/- 116.00

+/- 1.09

+/- 0.92

+/- 0.88

+/- 0.20

+/- 0.51

+/- 0.09

+/- 0.51

+/- 0.03

+/- 0.04

+/- 0.02

+/- 0.07

+/- 0.35 488.30 +/- 163.80 2414.00 +/- 350.00 24.93 +/- 2.93 0.69 +/- 0.26 15.81 +/- 1.23 4.65 +/- 0.68 2.53 +/- 0.50 3.33 +/- 0.56 2.11 +/-0.45 1347.40 +/- 109.70 241.99 +/- 99.02 7.17 +/- 0.19 0.22 +/- 0.13 2.17 +/- 0.17 3.94 +/- 0.39 2.96 +/- 0.21 3.44 +/- 0.27 7.86 +/- 0.27 5.57 +/- 0.44 2.60 +/- 0.50 2.00 +/- 0.43 14.13 +/- 0.48 4.73 +/- 1.21 7.95 +/- 1.21 10.67 +/- 0.28 1.00 +/- 0.06 1388.00 +/- 98.20 5.30 +/- 1.08 13.51 +/- 0.89 2.26 +/- 0.91 0.75 +/- 0.23 6.63 +/- 0.57 0.38 +/- 0.07 5.96 +/- 0.49 0.36 +/- 0.03 0.25 +/- 0.04 0.12 +/- 0.02 0.04 +/- 0.01 0.03 +/- 0.02 2.62 +/- 0.07 2.24 +/- 0.58 516.10 2488.10 23.14 0.63 14.96 4.79 2.90 3.46 1.88 1347.95 244.15

+/- 113.86

+/- 237.05

+/- 1.65

+/- 0.18

+/- 0.87

+/- 0.50

+/- 0.39

+/- 0.40

+/- 0.30

+/- 74.56

+/- 70.08 7.33 +/- 0.14 0.19 +/- 0.08 2.27 +/- 0.12 4.34 +/- 0.30 3.04 +/- 0.13 3.29 +/- 0.20 7.97 +/- 0.19 5.54 +/- 0.32 2.92 +/- 0.37 1.80 +/- 0.29 14.27 +/- 0.30 4.44 +/- 0.69 7.81 +/- 0.76 10.70 +/- 0.18 0.98 +/- 0.04 1466.65 +/- 75.99 5.83 +/- 0.77 13.94 +/- 0.64 1.97 +/- 0.63 0.77 +/- 0.15 6.40 +/- 0.38 0.41 +/- 0.06 6.25 +/- 0.35 0.34 +/- 0.02 0.27 +/- 0.03 0.13 +/- 0.01 0.05 +/- 0.01 0.03 +/- 0.01 2.58 +/- 0.05 2.45 +/- 0.34 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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 SL-6017, 6018 SL-6017, 6018 SL-6017, 6018 VE-6038, 6039 SW-6059, 6060 VE-6302, 6303 VE-6302, 6303 VE-6302, 6303 VE-6302, 6303 W-7098,7099 W-6407,6408 MI-6479, 6480 W-6579,6580 AP-7015, 7016 AP-6105, 6106 LW-6603, 6604 AP-7056, 7057 G-6730,6731 G-6730,6731 G-6730,6731 AP-7077, 7078 AP-7077, 7078 VE-6798, 6799 AP-6820, 6821 W-7755,7756 BS-7944,7945 BS-7944, 7945 BS-7140, 7141 AP-7168, 7169 DW-20349, 20350 DW-20349, 20350 WW-7667, 7668 WW-7381, 7382 SS-7495, 7496 W-7516,7517 VE-7537, 7538 MI-7622,7623 DW-20399, 20400 DW-20399, 20400 BS-7600, 7601 9/6/2011 9/6/2011 9/6/2011 9/7/2011 9/8/2011 9/13/2011 9/13/2011 9/13/2011 9/13/2011 9/19/2011 9/20/2011 9/27/2011 9/27/2011 9/27/2011 9/28/2011 9/28/2011 9/29/2011 10/3/2011 10/3/2011 10/3/2011 1013/2011 10/3/2011 10/4/2011 10/6/2011 10/9/2011 10/10/2011 10/10/2011 10/13/2011 10/13/2011 10/13/2011 10/13/2011 10/19/2011 10/21/2011 10/26/2011 10/27/2011 10/28/2011 10/31/2011 10/31/2011 10/31/2011 11/11/2011 Be-7 Gr. Beta K-40 Sr-90 H-3 Be-7 Gr. Beta H-3 K-40 H-3 Ra-228 K-40 H-3 Be-7 Be-7 Gr. Beta Be-7 Be-7 Gr. Beta K-40 Be-7 Be-7 K-40 Be-7 H-3 Cs-137 K-40 K-40 Be-7 U-233/4 U-238 H-3 H-3 K-40 H-3 K-40 K-40 U-233/4 U-238 Gr. Beta 0.47 +/- 0.17 4.23 +/- 0.16 4.43 +/- 0.55 1.86 +/- 0.98 219.75 +/- 97.52 0.76 +/- 0.24 27.00 +/- 1.02 6966.00 +/- 249.00 20.62 +/- 0.68 586.61 +/- 103.06 1.61 +/- 0.94 1384.10 +/- 111.10 287.97 +/- 99.68 0.08 +/- 0.02 0.11 +/- 0.02 2.15 +/- 1.04 0.08 +/- 0.02 4.24 +/- 0.36 8.27 +/- 0.33 6.46 +/- 0.56 0.08 +/- 0.01 0.08 +/- 0.01 11.76 +/- 0.65 0.22 +/- 0.08 261.92 +/- 96.52 291.17 +/- 34.00 14237.00 +/- 686.40 2.59 +/- 0.35 0.25 +/- 0.09 1.77 +/- 0.41 0.28 +/- 0.19 1049.11 +/- 116.32 1904.40 +/- 145.45 10.16 +/- 0.55 191.46 +/- 84.47 2.08 +/- 0.23 1386.20 +/- 116.80 5.70 +/- 0.70 3.10 +/- 0.50 6.83 +/- 1.44 0.51 +/- 0.19 3.94 +/- 0.15 4.24 +/- 0.53 2.30 +/- 0.92 177.41 +/- 95.76 0.85 +/- 0.20 25.50 +/- 0.95 6947.00 +/- 249.00 20.63 +/- 0.64 525.71 +/- 100.63 0.79 +/- 0.81 1411.40 +/- 105.00 285.95 +/- 99.60 0.09 +/- 0.02 0.09 +/- 0.02 1.65 +/- 0.90 0.06 +/- 0.01 4.47 +/- 0.37 7.93 +/- 0.31 5.41 +/- 0.50 0.07 +/- 0.01 0.07 +/- 0.01 11.91 +/- 0.62 0.18 +/- 0.10 221.92 +/- 94.80 330.68 +/- 36.40 15359.00 +/- 703.80 2.58 +/- 0.52 0.25 +/- 0.11 2.25 +/- 0.77 0.31 +/- 0.33 1071.39 +/- 117.10 1813.62 +/- 142.91 9.56 +/- 0.49 224.05 +/- 86.03 2.41 +/- 0.21 1407.90 +/- 116.50 5.70 +/- 0.70 3.70 +/- 0.70 5.31 +/- 1.35 0.49 +/- 0.13 4.09 +/- 0.11 4.34 +/- 0.38 2.08 +/- 0.67 198.58 +/- 68.34 0.81 +/- 0.16 26.25 +/- 0.70 6956.50 +/- 176.07 20.63 +/- 0.47 556.16 +/- 72.02 1.20 +/- 0.62 1397.75 +/- 76.43 286.96 +/- 70.45 0.08 +/- 0.01 0.10 +/- 0.01 1.90 +/- 0.69 0.07 +/- 0.01 4.36 +/- 0.26 8.10 +/- 0.23 5.94 +/- 0.38 0.07 +/- 0.01 0.07 +/- 0.01 11.84 +/- 0.45 0.20 +/- 0.06 241.92 +/- 67.65 310.93 +/- 24.90 14798.00 +/- 491.55 2.59 +/- 0.31 0.25 +/- 0.07 2.01 +/- 0.44 0.30 +/- 0.19 1060.25 +/- 82.53 1859.01 +/- 101.95 9.86 +/- 0.37 207.76 +/- 60.28 2.24 +/- 0.16 1397.05 +/- 82.48 5.70 +/- 0.49 3.40 +/- 0.43 6.07 +/- 0.98 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 0

0 0

A5-5

TABLE A-5. In-House "Duplicate" Samples 0

0 0

Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SG-8471, 8472 SG-8471, 8472 DW-20424, 20425 DW-20424, 20425 DW-20424, 20425 DW-20424, 20425 DW-20435, 20436 DW-20435, 20436 SG-7902, 7903 SG-7902, 7903 SG-7902, 7903 SG-7902, 7903 BS-8033, 8034 LW-8075, 8076 AP-8193, 8194 F-8663, 8664 F-8663, 8664 F-8663, 8664 DW-20449, 20450 DW-20449, 20450 SWU-8388, 8389 AP-8841, 8842 W-8886, 8887 W-8886, 8887 W-8886, 8887 SO-8958, 8959 AP-8907, 8908 AP-9196, 9197 LW-9091, 9092 11/1/2011 11/1/2011 11/7/2011 11/7/2011 11/7/2011 111712011 11/8/2011 11/8/2011 11/10/2011 11/10/2011 11/10/2011 11/10/2011 11/11/2011 11/16/2011 11/17/2011 11/19/2011 11/19/2011 11/19/2011 11/28/2011 11/28/2011 11/29/2011 12/15/2011 12/15/2011 12/15/2011 12/15/2011 12/21/2011 12/22/2011 12/28/2011 12/29/2011 Gr. Alpha Gr. Beta U-233/4 U-235 U-238 U-238 U-233/4 U-238 Ac-228 K-40 Pb-212 Pb-214 Cs-1 37 Gr. Beta Be-7 Cs-1 37 Gr. Beta K-40 U-233/4 U-238 Gr. Beta Be-7 Gr. Alpha Gr. Beta Ra-226 K-40 Be-7 Be-7 Gr. Beta 13.63 +/- 2.32 20.30 +/- 1.43 5.90 +/- 0.80 0.10 +/- 0.10 4.30 +/- 0.70 10.30 +/- 1.00 11.00 +/- 1.10 5.90 +/- 0.80 21.38 +/- 0.47 9.72 +/- 1.04 3.99 +/- 0.10 9.15 +/- 0.23 0.03 +/- 0.02 1.93 +/- 0.62 0.21 +/-0.11 0.03 +/- 0.02 3.55 +/- 0.10 3.04 +/- 0.42 0.70 +/- 0.20 0.60 +/- 0.20 1.66 +/- 0.57 0.23 +/- 0.12 0.83 +/- 0.81 6.80 +/- 1.25 0.23 +/- 0.15 14.58 +/- 0.86 0.15 +/- 0.06 0.06 +/- 0.01 1.97 +/- 0.63 11.13 +/- 2.00 17.65 +/- 1.42 6.10 +/- 0.80 0.30 +/- 0.20 3.70 +/- 0.60 10.10 +/- 1.00 10.60 +/- 0.80 4.90 +/- 0.60 20.48 +/- 0.52 9.53 +/- 0.92 3.99 +/- 0.10 9.14 +/- 0.21 0.03 +/- 0.02 2.55 +/- 0.64 0.26 +/- 0.13 0.03 +/- 0.02 3.71 +/- 0.10 3.05 +/- 0.35 0.80 +/- 0.20 0.60 +/- 0.20 1.65 +/- 0.59 0.19 +/- 0.09 1.58 +/- 0.99 5.94 +/- 1.22 0.41 +/- 0.16 15.07 +/- 0.87 0.11 +/-0.07 0.07 +/- 0.01 1.74 +/- 0.60 12.38 +/- 1.53 18.98 +/- 1.01 6.00 +/- 0.57 0.20 +/- 0.11 4.00 +/- 0.46 10.20 +/- 0.71 10.80 +/- 0.68 5.40 +/- 0.50 20.93 +/- 0.35 9.63 +/- 0.69 3.99 +/- 0.07 9.15 +/- 0.16 0.03 +/- 0.01 2.24 +/- 0.44 0.24 +/- 0.08 0.03 +/- 0.01 3.63 +/- 0.07 3.05 +/- 0.27 0.75 +/- 0.14 0.60 +/- 0.14 1.66 +/- 0.41 0.21 +/- 0.07 1.21 +/- 0.64 6.37 +/- 0.87 0.32 +/- 0.11 14.83 +/- 0.61 0.13 +/- 0.05 0.06 +/- 0.01 1.86 +/- 0.44 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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).

A5-6

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 STW-1237 e STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1 237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 Am-241 Co-57 Co-60 Cs-134 Cs-137 H-3 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 Zn-65 STW-1238 02/01/11 Gr. Alpha STW-1238 02/01/11 Gr. Beta STVE-1239 STVE-1239 STVE-1239 STVE-1239 STVE-1239 STVE-1239 STSO-1 240 STSO-1240 STSO-1240 STSO-1240 STSO-1240 STSO-1240 STSO-1240 STSO-1240 STSO-1240 STSO-1240 STAP-1 241 STAP-1241 STAP-1241 STAP-1241 STAP-1241 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 Ni-63 U-233/4 U-238 Zn-65 Am-241 Co-57 Co-60 Cs-134 Cs-137 0.35 +/- 0.10

< 0.2 24.10 +/- 0.40 19.80 +/- 0.40 29.40 +/- 0.50 238.90 +/- 8.80 95.40 +/- 3.10 32.50 +/- 0.60 16.30 +/- 0.60 1.11 +/- 0.12 0.88 +/- 0.12 8.70 +/- 0.70 7.60 +/- 0.60

< 0.5 0.82 +/- 0.07 2.82 +/- 0.07 11.27 +/- 0.21 4.95 +/- 0.16 5.18 +/- 0.19

< 0.09 6.91 +/- 0.25 3.10 +/- 0.32 984.10 +/- 4.10 540.70 +/- 3.00 726.70 +/- 5.92 883.10 +/- 4.70 622.70 +/- 16.70

-0.30 +/- 1.00 384.00 +/- 16.90 166.60 +/- 7.30 172.00 +/- 7.40 1671.00 +/- 13.10 0.00 +/- 0.01 3.48 +/- 0.06 0.00 +/- 0.02 3.44 +/- 0.27 2.46 +/- 0.27 1.14 2.96 9.94 4.91 5.50 0.00 6.40 2.99 0.53 0.00 24.60 21.50 29.40 243.00 91.00 31.60 18.60 1.06 0.81 8.72 8.99 0.00 0.37 - 0.69 17.20 - 32.00 15.10 - 28.00 20.60 - 38.20 170.00 - 316.00 64.00 - 118.00 22.10 - 41.10 13.00 - 24.20 0.75 - 1.38 0.57 - 1.05 6.10-11.34 6.29-11.69 0.34-1.93 1.48 - 4.44 6.96 - 12.92 3.44 - 6.38 3.85 -7.15 4.48 - 8.32 2.09 - 3.89 Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass 00 0

0 0

927.00 482.00 680.00 758.00 540.00 0.00 582.00 176.00 184.00 1359.00 0.00 3.33 0.00 3.49 2.28 649.00 - 1205.00 337.00 - 627.00 476.00 -884.00 531.00 -985.00 378.00 -702.00 407.00 - 757.00 123.00 - 229.00 129.00 -239.00 951.00 - 1767.00

-0.10 -0.10 2.33 - 4.33

-0.10 -0.10 2.44 - 4.54 1.60 - 2.96 A6-1

0 0

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 STAP-1241 STAP-1241 STAP-1241 STAP-1241 STAP-1241 STAP-1241 9 STAP-1241 STAP-1241 STAP-1241 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 Gr. Alpha Gr. Beta Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 STW-1249 08/01/11 1-129 STVE-1250 STVE-1250 STVE-1250 STVE-1250 STVE-1250 STVE-1250 STSO-1 251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1 251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1 251 STSO-1251 STAP-1252 STAP-1252 STAP-1252 STAP-1252 STAP-1252 STAP-1252 STAP-1252 STAP-1 252 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 0.39 +/- 0.05 1.54 +/- 0.07 2.90 +/- 0.10 0.07 +/- 0.02 0.06 +/- 0.02 1.89 +/- 0.15 0.13 +/- 0.02 0.14 +/- 0.02 3.80 +/- 0.18 7.32 +/- 0.30 0.01 +/- 0.02 3.57 +/- 0.13

-0.02 +/- 0.04 5.28 +/- 0.20 6.48 +/- 0.22 7.35 +/- 0.34 1333.90 +/- 4.20 701.30 +/- 3.40 0.71 +/- 1.05 1106.00 +/- 5.60 749.20 +/- 19.00 984.30 +/- 5.40 0.11 +/- 1.21 97.90 +/- 7.40 78.80 +/- 6.40 219.40 +/- 16.70 110.00 +/- 8.00 267.00 +/- 10.20 280.30 +/- 10.40 1639.90 +/- 11.40 5.06 +/- 0.08 3.13 +/- 0.09 0.01 +/- 0.03 2.61 +/- 0.09 0.01 +/- 0.03 0.13 +/- 0.02 0.15 +/- 0.02 1.65 +/- 0.16 0.66 1.32 2.64 0.10 0.08 1.36 0.18 0.19 3.18 9.50 0.00 3.38 0.00 4.71 5.71 6.39 1180.00 644.00 0.00 979.00 625.00 848.00 0.00 93.60 77.40 320.00 182.00 263.00 274.00 1560.00 5.09 3.20 0.00 2.60 0.00 0.12 0.14 1.67 0.20-1.12 0.66 - 1.99 1.85 - 3.43 0.07 -0.13 0.05 -0.10 0.95 - 1.77 0.13 -0.23 0.13 -0.24 2.23 -4.13 6.70 - 12.40 2.37 - 4.39

-0.10 -0.10 3.30 -6.12 4.00 - 7.42 4.47 - 8.31 826.00 - 1534.00 451.00 - 837.00 Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 685.00 438.00 594.00

-1273.00

-813.00

-1102.00 h

65.50 - 121.70 54.20 - 100.60 224.00 -416.00 127.00 - 237.00 184.00 - 342.00 192.00 - 356.00 1092.00 - 2028.00 3.56 - 6.62 2.24 -4.16

-0.10 -0.10 1.82 - 3.38

-0.10 -0.10 0.08 -0.15 0.10 -0.18 1.17 -2.17 A6-2

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 STAP-1252 08/01/11 U-233/4 0.17 +/- 0.02 0.16 0.11 -0.21 Pass STAP-1252 08/01/11 U-238 0.17 +/- 0.02 0.17 0.12 -0.22 Pass STAP-1252 08/01/11 Zn-65 4.46 +/- 0.23 4.11 2.88 - 5.34 Pass STW-1254 08/01/11 Co-57 37.20 +/- 0.50 36.60 25.60 - 47.60 Pass STW-1254 08/01/11 Co-60 28.80 +/- 0.40 29.30 20.50 - 38.10 Pass STW-1254 08/01/11 Cs-134 18.00 +/- 0.60 19.10 13.40 - 24.80 Pass STW-1254 08/01/11 Cs-1 37 0.06 +/- 0.13 0.00 Pass STW-1254 08/01/11 H-3 1039.90 +/- 17.90 1014.00 710.00 - 1318.00 Pass STW-1254 08/01/11 K-40 161.40 +/- 4.10 156.00 109.00 - 203.00 Pass STW-1254 08/01/11 Mn-54 25.70 +/- 0.50 25.00 17.50 - 32.50 Pass STW-1254 08/01/11 Ni-63 0.60 +/- 2.00 0.00 Pass STW-1254 08/01/11 Pu-238 0.04 +/- 0.02 0.02 0.00-1.00 Pass STW-1254 08/01/11 Pu-239/40 2.27 +/- 0.14 2.40 1.68 -3.12 Pass STW-1254 08/01/11 Sr-90 15.60 +/- 1.80 14.20 9.90 - 18.50 Pass STW-1254 08/01/11 Tc-99

-0.30 +/- 0.50 0.00 Pass STW-1254 08/01/11 U-233/4 2.78 +/- 0.20 2.78 1.95 -3.61 Pass STVV-1254 08/01/11 U-238 2.86 +/- 0.21 2.89 2.02 -3.76 Pass STW-1254 08/01/11 Zn-65 30.20 +/- 0.90 28.50 20.00 - 37.10 Pass STW-1255 08/01/11 Gr. Alpha 0.72 +/- 0.12 0.87 0.26 - 1.47 Pass STW-1255 08/01/11 Gr. Beta 4.71 +/- 0.15 4.81 2.41 -7.22 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.

e Result of a repeat analysis was still unacceptable. ERA crosschecks for Am-241 were acceptable, but biased low.

Matrix spikes were prepared, ( 5.17 and 51.7 pCi/L), to verify method; results were acceptable, 4.4 and 47.5 pCi/L.

Am-241 has been added to the internal spike and blank program for 2012.

f An error in percent recovery was found, result of recalculation, 427.3 +/- 18.8 Bq/kg dry.

9 No errors found in calculation or procedure, results of reanalysis; 1.73 Bq/filter.

h The analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bq/kg.

The lab does not currently analyze soil for Tc-99, but is evaluating the procedure. After consultation with Eichrom, the analysis was repeated using a matrix spike correction. Mean result of triplicate reanalyses; 183.3 Bq/kg.

A6-3 0

0 0

0 0

0 0

0 S

0 0

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 Am-241 Co-60 Cs-134 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 STAP-1231 03/21/11 Gr. Alpha STAP-1231 03/21/11 Gr. Beta STSO-1232 STSO-1232 STSO-1 232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1 232 STSO-1232 STSO-1232 STSO-1 232 STSO-1 232 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 Ac-228 Am-241 Bi-212 Bi-214 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 Th-234 U-233/4 U-238 Uranium Zn-65 46.0 +/- 1.8 401.2 +/- 12.1 268.2 +/- 24.8 345.3 +/- 24.9

< 1.9 76.1 +/- 3.2 70.50 +/- 3.10 208.40 +/- 18.70 56.10 +/- 2.10 58.90 +/- 2.60 118.50 +/- 5.52 312.60 +/- 23.40 88.40 +/- 3.70 85.10 +/- 2.80 1327.8 +/- 97.5 662.8 +/- 88.1 1396.2 +/- 185.3 841.1 +/- 33.2 2423.7 +/- 27.1 2481.3 +/- 42.2 2108.2 +/- 30.2 11497.3 +/- 276.6

< 17.4 994.7 +/- 30.0 918.3 +/- 42.6 1593.6 +/- 156.7 1428.9 +/- 143.4 8638.0 +/- 442.8 1350.1 +/- 180.0 748.0 +/- 94.4 909.0 +/- 104.9 1690.8 +/- 104.9 2356.2 +/- 57.1 62.5 390.0 279.0 312.0 0.0 69.0 65.5 185.0 61.5 61.0 125.0 279.0 74.3 69.5 1490.0 914.0 1400.0 725.0 2220.0 2450.0 1920.0 11500.0 0.0 1440.0 805.0 1420.0 1400.0 7590.0 962.0 972.0 962.0 1980.0 1990.0 36.6 - 85.7 302.0 - 487.0 182.0 - 345.0 234.0 - 410.0 47.4 - 90.7 47.5 - 85 81.4 -288 38.7 - 91 39.0 - 87 63.9 - 199 193.0 -386 38.5-112 42.8 - 102 958.0 - 2100.0 546.0 - 1170.0 368.0 - 2090.0 445.0 - 1040.0 1620.0 - 2980.0 1580.0 - 2950.0 1470.0 - 2490.0 8320.0 - 15600.0 931.0 - 2030.0 482.0 - 1200.0 813.0 - 2000.0 956.0 - 1860.0 2740.0 - 12400.0 305.0 - 1830.0 616.0 - 1210.0 588.0 - 1220.0 1130.0 - 2670.0 1580.0 - 2670.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A7-1

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-11233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1 234 STW-1234 STW-1234 STW-1234 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 Am-241 Cm-244 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 Am-241 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 2377.5 +/- 83.2 602.9 +/- 38.4 810.2 +/- 32.4 849.4 +/- 54.5 889.9 +/- 36.3 28146.70 +/- 698.80

< 19.3 3068.10 +/- 170.70 3180.00 +/- 88.90 8549.20 +/- 675.00 2418.60 +/- 142.50 2417.00 +/- 142.50 4929.80 +/- 142.50 962.40 +/- 62.50 100.0 +/- 6.4 401.6 +/- 7.2 222.7 +/- 12.3 410.3 +/- 9.5

< 3.0 130.9 +/- 5.5 113.0 +/-5.0 739.6 +/- 13.0 83.4 +/- 3.8 85.5 +/- 3.9 172.0 +/- 8.5 114.5 +/- 10.8 97.6 +/- 2.9 99.6 +/- 2.0 16307.0 +/- 377.0 3200.0 812.0 733.0 770.0 829.0 25800.0 0.0 2990.0 3100.0 7890.0 2610.0 2590.0 5320.0 799.0 135.0 411.0 231.0 417.0 0.0 131.0 119.0 773.0 94.3 93.5 192.0 111.0 112.0 99.8 1820.0 - 4400.0 400.0 - 1260.0 496.0 - 1050.0 441.0 - 1070.0 608.0 - 1150.0 18500.0 - 36500 1610.0 - 4380 1920.0 - 4230 4410.0 - 10500 1790.0 - 3460 1820.0 - 3270 3660.0 - 6860 577.0 - 1090 92.5 - 182.0 358.0 - 486.0 171.0 -265.0 354.0 - 500.0 99.1 - 162.0 92.1 - 147.0 491.0 - 1030.0 71.1 -122.0 71.4-116.0 138.0 - 256.0 94.1 -138.0 49.7 - 166.0 58.4 - 146.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 00 0

0 0

STW-1235 03/21/11 Gr. Alpha STW-1235 03/21/11 Gr. Beta STW-1236 03/21/11 H-3 15200.0 9900.0 -22500.0 8 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). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).

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.

A7-2

S 0

S S

S 0

S S

S ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX B 2011 REMP DATA

SUMMARY

REPORTS

Air Gamma Spectral Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Air pCi/m3 Air pCi/m3 Air pCi/m3 Air pCi/m3 Air pCi/m3 Type and Number of Analyses Performed Be-7 28 Co-58 28 Co-60 28 Cs-134 28 Cs-137 28 Mean of Results from Lower All Locations and Limit Number Detected/Number Collected (LLD) and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range 0.06 24 / 24 0.06 - 0.07 Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range 0.06 4/4 0.05 -

0.08 N/A N/A N/A 0.04 0.05 0.06 28 / 28 0.05

- 0.08 5

0.60 SW 0.06 4 /20 0.06

- 0.07 LLD LLD LLD LLD B-1

Air Gross Beta Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Air pCi/m3 Type and Number of Analyses Performed Gross Beta 364 Mean of Results from Lower All Locations and Limit Number Detected/Number Collected (LLD) and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range 0.02 312 / 312 0.01 0.06 Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range 0.03 52 I 52 0.01 0.06 0.01 0.02 364 / 364 0.01

- 0.06 6

11.00 SSW 0.03 52 I 52 0.01

- 0.06

Air Iodine Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Air pCi/m3 Type and Number of Analyses Performed 1-131 364 Mean of Results from Lower All Locations and Limit Number Detected/Number Collected (LLD) and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range 0.07 18 / 312 0.02 -

0.11 Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range 0.08 3 /52 0.04 -

0.13 0.05 0.07 21 /364 0.02 -

0.13 6

11.00 SSW 0.08 3 /52 0.04

- 0.13 B-3

Fish Gamma Spectral Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Type and Number of Analyses Performed Co-58 6

Co-60 6

Cs-134 6

Cs-137 6

Fe-59 6

K-40 6

Lower Limit (LLD) 97.00 97.00 97.00 112.00 195.00 Mean of Results from All Locations and Number Detected/Number Collected and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected I Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range LLD LLD LLD LLD LLD N/A 1,353.80 6/6 1,132.70-1,823.20 1,315.43 3/3 1,276.60 -

1,342.40 32 15.80 WSW 1,392.17 3 /24 1,132.70

- 1,823.20 1,392.17 3/3 1,132.70 -

1,823.20 Mn-54 97.00 6

LLD LLD Zn-65 6

195.00

Food Products Gamma Spectral Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Number of Analyses Performed Mean of Results from Lower All Locations and Limit Number Detected/Number Collected (LLD) and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range Sample Type and Units Food Products pCi/kg wet Food Products pCi/kg wet Food Products pCi/kg wet Food Products pCi/kg wet Food Products pCi/kg wet Food Products pCi/kg wet Food Products pCi/kg wet Be-7 43 Co-58 43 Co-60 43 Cs-134 43 Cs-137 43 1-131 43 N/A N/A N/A 45.00 60.00 45.00 651.54 28 / 43 181.11

- 1,736.70 651.58 25 I 36 181.11 1,736.70 2

1.90 ENE 909.23 6 / 63 181.11

- 1,736.70 651.17 3 /7 291.40 -

873.62 LLD LLD LLD LLD LLD K-40 43 N/A 4,825.36 43 / 43 2,654.10 - 7,399.40 4,939.90 36 / 36 2,654.10 -

7,399.40 18 2.50 E

5,577.61 8 / 56 4,898.60

- 6,791.10 4,236.29 7 /7 3,148.30 - 5,771.20 B-5

Milk Gamma Spectral Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Milk TCi/L Milk pCi/L Milk pCi/L Milk pCi/L Milk pCi/L Type and Number of Analyses Performed Cs-137 54 K-40 54 La-140 54 Ba-140 54 Cs-134 54 Mean of Results from Lower All Locations and Limit Number Detected/Number Collected (LLD) and Range..................

Mean of Results from All Indicator Locations and Number Detected/Number Collected

_ and Range Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range 13.00 LLD N/A 1,420.59 54 / 54 717.02-1,902.00 1,596.51 35 / 35 1,113.70 -

1,902.00 41 5.80 SSE 1,703.85 8 /40 1,152.90

- 1,868.00 1,096.52 19 / 19 717.02-1,844.70 11.00 45.00 11.00 LLD LLD LLD

00000¸00000000000000000000000000000000000000 Milk Iodine Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no.

50-440/50-441 Sample Type and Units Milk pCi/L Type and Number of Analyses Performed 1-131 54 Mean of Results from Lower All Locations and Limit Number Detected/Number Collected (LLD) and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range 1.61 3 /35 1.25 2.23 Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range LLD 0 / 19 0.75 1.61 3 /54 1.25

- 2.23 18 2.50 E

1.80 2 /15 1.36

- 2.23 B-7

Sediment Gamma Spectral Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Sediment pCi/kg dry Sediment pCi/kg dry Sediment pCi/kg dry Sediment pCi/kg dry Sediment pCi/kg dry Type and Number of Analyses Performed Co-58 12 Co-60 12 Cs-134 12 Cs-137 12 Mean of Results from Lower All Locations and Limit Number Detected/Number Collected (LLD) and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Ranze Mean of Results from All Control Locations and Number Detected/Number Collected and Range 50.00 40.00 112.00 135.00 LLD LLD LLD 367.04 5

12 136.09 - 646.60 188.12 3 / 10 136.09 - 291.17 32 15.80 WSW 32 15.80 WSW 635.43 2 / 10 624.25

- 646.60 635.43 2 /2 624.25 -

646.60 K-40 12 N/A 13,406.15 12 / 12 7,531.30

- 23,261.00 11,491.08 10 / 10 7,531.30 -

15,973.00 22,981.50 2 / 10 22,702.00

- 23,261.00 22,981.50 2 /2 22,702.00 - 23,261.00

TLD Gamma Dose Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Number of Analyses Performed Mean of Results from Lower All Locations and Limit Number Detected/Number Collected (LLD) and Range Sample Type and Units TLD mR/91 days TLD mR/91 days TLD mR/365 days Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range Direct 112 Direct 112 Direct 28 1.00 1.00 1.00 12.47 112 / 112 7.11 -

17.35 13.40 112 / 112 8.75 -

18.47 62.31 28 / 28 49.07 - 80.26 12.48 104 /104 7.11 17.35 13.44 104 /104 8.75 -

18.47 62.44 26 / 26 49.07 - 80.26 33 4.50 S

33 4.50 S

16.79 4/4 16.25 17.35 17.39 4/4 16.61 18.47 80.26 1 /1 80.26 - 80.26 12.29 8/8 11.62 -

12.82 12.81 8/8 11.23 -

14.32 60.56 2/2 56.45 -

64.68 B-9

Water Gamma Spectral Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type andUnits Water pCi/L Water pCiiL Water pCi/L Water pCi/L Water pCi/L Water pCi/L Water pCi/L Water pCi/L Water pCi/L Water pCi/L Water pCi/L Type and Number of Analyses Performed Ba-140 54 Co-58 54 Co-60 54 Cs-134 54 Cs-137 54 Fe-59 54 La-140 54 Mn-54 54 Nb-95 54 Zn-65 54 Zr-95 54 Lower Limit (LLD) 45.00 11.00 11.00 11.00 13.00 22.00 11.00 11.00 11.00 22.00 22.00 Mean of Results from All Locations and Number Detected/Number Collected and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range Location # and Distance and Direction Mean and Number Detected/Number Collected and Range Location with Highest Annual Mean:

Mean of Results from All Control Locations and Number Detected/Number Collected and Range LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD

Water Gross Beta Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Number of Analyses Performed Sample Type and Units Lower Limit (LLD)

Mean of Results from All Locations and Number Detected/Number Collected and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range Water pCi/L Gross Beta 3.00 54 3.76 4 /54 3.06 - 4.25 3.59 3 /42 3.06 - 4.11 28 22.00 ENE 4.25 1

12 4.25

- 4.25 4.25 1

12 4.25 - 4.25 B-11

Water Tritium Summary Report 2011 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Water pCi/L Type and Number of Analyses Performed H-3 18 Lower Limit (LLD) 1,500.00 Mean of Results from All Locations and Number Detected/Number Collected and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range Location with Highest AnnuasMean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range LLD

0 0

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX C 2011 REMP DETAILED DATA REPORT

0000000000000000000000000000000000000000000 Air Gamma Spectral Detail Report 2011 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 3/30/2011 0.057 +-0.009

< 0.000

< 0.001 1

Air 6/29/2011 0.065 +-0.009

< 0.000

< 0.001

< 0.001 Air 9/29/2011 0.062 +-0.011

< 0.000

< 0.000 1

Air 12/28/2011 0.061 +/-0.009

< 0.001

< 0.000

< 0.000 3

Air 3/30/2011 0.057 +/- 0.010

< 0.000

< 0.001 3

Air 6/29/2011 0.062 +/- 0.010

< 0.000

< 0.001

< 0.000

< 0.001 3

Air 9/29/2011

'0.059 +/-0.009

< 0.000

< 0.000 3

Air 12/28/2011 0.059 +/- 0.009

< 0.000

< 0.000 4

Air 3/30/2011 0.063 +/-0.010

< 0.000

< 0.000 4

Air 6/29/2011 0.062 +/-0.009

< 0.000

< 0.001

< 0.001 4

Air 9/29/2011 0.063 +/-0.008

< 0.001

< 0.000

< 0.000 C-1

Air Gamma Spectral Detail Report 2011 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 12/28/2011 0.064 +/- 0.012

< 0.000

< 0.000 5

Air 5

Air 6

6 Air Air Air 3/30/2011 6/29/2011 9/29/2011 12/28/2011 3/30/2011 6/29/2011 9/29/2011 12/28/2011 3/30/2011 6/29/2011 0.060 +/- 0.006 0.057 +/- 0.008 0.071 +/- 0.009 0.065 +/- 0.011 0.054 +/- 0.009 0.077 +/- 0.009 0.065 +/- 0.009 0.056 +/- 0.007 0.055 +/- 0.008 0.059 +/- 0.009

< 0.000

< 0.001

< 0.000

< 0.000 0.000 0.000

< 0.000

< 0.000 0.000 0.000 0.000 0.000

< 0.000

< 0.001

< 0.000

< 0.001

< 0.000 6

Air 7

Air

000000000000000000000000000000 Air Gamma Spectral Detail Report 2011 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 7

Air 7

Air 35 Air Collection Date 9/29/2011 12/28/2011 3/30/2011 Be-7 0.059 +/- 0.008 0.062 +/- 0.010 0.058 +/- 0.010 0.064 +/- 0.011 0.062 +/- 0.009 0.064 +/- 0.010 Co-58

< 0.000

< 0.001

< 0.000

< 0.001

< 0.000

< 0.000 Co-60

< 0.000

< 0.000 Cs-134

< 0.000

< 0.001

< 0.000

< 0.000 Cs-137

< 0.000

< 0.001

< 0.000

< 0.000 35 Air 35 Air 35 Air 6/29/2011 9/29/2011 12/28/2011 C-3

Air Gross Beta Detail Report 2011 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 1/5/2011 1/12/2011 1/19/2011 1/26/2011 Air Air Air Air 2/2/2011 2/3/2011 2/9/2011 2/16/2011 2/24/2011 3/2/2011 3/9/2011 3/16/2011 3/23/2011 3/30/2011 4/6/2011 Air Air Air Air Air Air Air Air Air Air Air 0.036 +/- 0.003 0.039 +/- 0.003 0.029 +/- 0.003 0.035 +/- 0.003 0.027 +/- 0.003 0.027 +/- 0.003 0.032 +/- 0.003 0.037 +/- 0.003 0.029 +/- 0.003 0.028 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 0.027 +/- 0.003 0.025 +/- 0.003 0.021 +/- 0.002 0.021 +/- 0.002 0.031 +/- 0.003 0.031 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.030 +/- 0.003 0.031 +/- 0.003 0.030 +/- 0.003 0.029 +/- 0.003 0.030 +/- 0.003 0.041 +/- 0.003 0.035 +/- 0.003 0.038 +/- 0.003 0.029 +/- 0.003 0.030 +/- 0.003 0.023 +/- 0.003 0.027 +/- 0.003 0.027 +/- 0.003 0.033 +/- 0.003 0.026 +/- 0.003 0.025 +/- 0.002 0.020 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.003 0.027 +/- 0.003 0.020 +/- 0.002 0.021 +/- 0.002 0.027 +/- 0.003 0.032 +/- 0.003 0.016 +/- 0.002 0.021 +/- 0.003 0.016 +/- 0.002 0.017 +/- 0.003 0.029 +/- 0.003 0.032 +/- 0.003 0.030 +/- 0.003 0.029 +/- 0.003 0.036 +/- 0.003 0.046 +/- 0.003 0.037 +/- 0.003 0.030 +/- 0.003 0.025 +/- 0.003 0.034 +/- 0.003 0.028 +/- 0.003 0.022 +/- 0.003 0.024 +/- 0.003 0.025 +/- 0.003 0.031 +/- 0.003 0.021 +/- 0.003 0.019 +/- 0.003 0.031 +/- 0.003 0.029 +/- 0.003 0.045 +/- 0.003 0.039 +/- 0.003 0.032 +/- 0.003 0.024 +/- 0.003 0.036 +/- 0.003 0.027 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 0.024 +/- 0.003 0.030 +/- 0.003 0.018 +/- 0.002 0.018 +/- 0.002 0.028 +/- 0.003 0.027 +/- 0.003 0.030 +/- 0.003 0.038 +/- 0.003 0.038 +/- 0.003 0.026 +/- 0.003 0.035 +/- 0.003 0.027 +/- 0.003 0.024 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0.031 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.003 0.027 +/- 0.003 0.029 +/- 0.003 0.039 +/- 0.003

Air Gross Beta Detail Report 2011 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 4/13/2011 4/20/2011 4/27/2011 Air Air Air 5/4/2011 5/11/2011 5/18/2011 5/26/2011 6/1/2011 6/8/2011 6/15/2011 6/22/2011 6/29/2011 7/6/2011 7/13/2011 7/20/2011 Air Air Air Air Air Air Air Air Air Air Air Air 0.017 +/- 0.003 0.018 +/- 0.003 0.024 +/- 0.003 0.025 +/- 0.003 0.015 +/- 0.003 0.009 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 0.014 +/- 0.003 0.013 +/- 0.003 0.011 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.016 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.003 0.015 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.003 0.011 +/- 0.003 0.014 +/- 0.002 0.013 +/- 0.002 0.017 +/- 0.003 0.020 +/- 0.003 0.025 +/- 0.003 0.027 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 0.019 +-0.003 0.019 +-0.003 0.022 +-0.003 0.024 +-0.003 0.013 +-0.002 0.015 +-0.003 0.015 +-0.002 0.017 +-0.002 0.013 +-0.003 0.0 14 +-0.003 0.0 14 +-0.002 0.012 +-0.002 0.012 +-0.002 0.0 14 +-0.002 0.019 +-0.003 0.020 +-0.003 0.021 +-0.003 0.022 +-0.003 0.015 +-0.002 0.015 +-0.002 0.012 +-0.003 0.012 +-0.003 0.012 +-0.002 0.012 +-0.002 0.013 +-0.002 0.016 +-0.003 0.024 +-0.003 0.025 +-0.003 0.024 +-0.003 0.024 +-0.003 0.016 +/- 0.003 0.027 +/- 0.003 0.017 +/- 0.003 0.014 +/- 0.002 0.015 +/- 0.003 0.015 +/- 0.002 0.013 +/- 0.002 0.020 +/- 0.003 0.025 +/- 0.003 0.013 +/- 0.002 0.013 +/- 0.003 0.012 +/- 0.002 0.017 +/- 0.003 0.026 +/- 0.003 0.024 +/- 0.003 0.015 +/- 0.002 0.023 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.020 +/- 0.003 0.021 +/- 0.003 0.015 +/- 0.002 0.012 +/- 0.003 0.013 +/- 0.002 0.029 +/- 0.003 0.026 +/- 0.003 0.025 +/-0.003 0.018 +/- 0.003 0.023 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.002 0.016 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.002 0.020 +/- 0.003 0.019 +/- 0.003 0.015 +/- 0.002 0.011 +/- 0.003 0.014 +/- 0.002 0.035 +/- 0.003 0.028 +/- 0.003 0.029 +/- 0.003' 0-5

Air Gross Beta Detail Report 2011 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 7/27/2011 Air 0.040 +/- 0.003 0.033 +/- 0.003 0.028 +/- 0.003 0.031 +/- 0.003 0.039 +/- 0.003 8/3/2011 8/10/2011 8/17/2011 8/24/2011 8/31/2011 9/7/2011 9/14/2011 9/21/2011 9/29/2011 10/5/2011 10/12/2011 10/19/2011 10/26/2011 11/2/2011 Air Air Air Air Air Air Air Air Air Air Air Air Air Air 0.030 +/- 0.003 0.028 +/- 0.003 0.030 +/- 0.003 0.022 +/- 0.003 0.027 +/- 0.003 0.021 +/- 0.002 0.017 +/- 0.003 0.031 +/- 0.003 0.031 +/- 0.003 0.017 +/- 0.002 0.015 +/- 0.002 0.040 +/- 0.003 0.043 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.017 +/- 0.002 0.016 +/- 0.003 0.024 +/- 0.002 0.020 +/-0.002 0.014 +/- 0.003 0.012 +/- 0.003 0.052 +/- 0.003 0.053 +/- 0.004 0.020 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.025 +/- 0.003 0.022 +/- 0.003 0.030 +/- 0.003 0.030 +/- 0.003 0.030 +/- 0.003 0.024 +/- 0.003 0.024 +/- 0.003 0.020 +/- 0.002 0.020 +/- 0.003 0.028 +/- 0.003 0.032 +/- 0.003 0.015 +/- 0.002 0.018 +/- 0.003 0.039 +/- 0.003 0.043 +/- 0.003 0.021 +/- 0.003 0.022 +/- 0.003 0.014 +/- 0.002 0.016 +/- 0.003 0.022 +/- 0.002 0.021 +/- 0.002 0.011 +/- 0.003 0.012 +/- 0.003 0.049 +/- 0.003 0.054 +/- 0.003 0.022 +/- 0.003 0.026 +/- 0.003 0.019 +/- 0.003 0.024 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0.028 +/- 0.003 0.025 +/- 0.003 0.019 +/- 0.002 0.029 +/- 0.003 0.017 +/- 0.002 0.037 +/- 0.003 0.023 +/- 0.003 0.016 +/- 0.002 0.021 +/- 0.002 0.013 +/- 0.003 0.056 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.003 0.025 +/- 0.003 0.028 +/- 0.003 0.027 +/- 0.003 0.024 +/- 0.003 0.030 +/- 0.003 0.018 +/- 0.003 0.045 +/- 0.003 0.024 +/- 0.003 0.015 +/- 0.003 0.025 +/- 0.003 0.015 +/- 0.003 0.060 +/- 0.004 0.022 +/- 0.003 0.022 +/- 0.003 0.026 +/- 0.003 0.037 +/- 0.003 0.026 +/- 0.003 0.019 +/- 0.003 0.031 +/- 0.003 0.018 +/- 0.003 0.043 +/- 0.003 0.021 +/- 0.003 0.016 +/- 0.003 0.025 +/- 0.003 0.014 +/- 0.003 0.057 +/- 0.004 0.024 +/- 0.003 0.018 +/- 0.003 0.025 +/- 0.003

0000000000000000@00o00@00000000000000000000 Air Gross Beta Detail Report 2011 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 11/8/2011 11/16/2011 11/23/2011 11/30/2011 Air Air Air Air 0.028 +/- 0.003 0.031 +/- 0.003 0.030 +/- 0.003 0.028 +/- 0.002 0.021 +/- 0.003 0.021 +/- 0.002 0.018 +/- 0.003 0.020 +/- 0.003 0.022 +/- 0.003 0.017 +/- 0.002 0.040 +/- 0.003 0.040 +/- 0.003 0.038 +/- 0.003 0.036 +/- 0.003 0.020 +/- 0.002 0.019 +/- 0.002 0.031 +-0.003 0.029 +-0.003 0.026 +-0.002 0.026 +-0.002 0.019 +-0.002 0.024 +-0.003 0.018 +-0.003 0.020 +-0.003 0.02 1 +-0.003 0.019 +-0.003 0.040 +-0.003 0.040+10.003 0.03 7 +-0.003 0.034 +-0.003 0.017 +-0.002 0.0 19 +-0.002 0.033 +/- 0.003 0.029 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.040+/- 0.003 0.035 +/- 0.003 0.018 +/- 0.002 0.032 +/- 0.003 0.030 +/- 0.003 0.019 +/- 0.003 0.028 +/- 0.005 0.022 +/- 0.003 0.046+/- 0.003 0.042 +/-0.003 0.020 +/- 0.003 0.035 +/- 0.003 0.029 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.044+/- 0.003 0.039 +/- 0.003 0.023+/- 0.003 12/7/2011 12/14/2011 12/21/2011 12/28/2011 Air Air Air Air C-7

Air Iodine Detail Report 2011 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 1/5/2011

< 0.006 Air 1/12/2011

< 0.011 Air 1/19/2011

< 0.010 Air 1/26/2011

< 0.006 Air 2/2/2011

< 0.005 Air 2/9/2011

< 0.006 Air 2/16/2011

< 0.004 1

Air 2/24/2011

< 0.011 Air 3/2/2011

< 0.014 Air 3/9/2011

< 0.009 1

Air 3/16/2011

< 0.012 Air 3/23/2011 0.063 +/- 0.012 Air 3/30/2011 LLD I

Air 4/6/2011 0.107 +/- 0.017 Air 4/13/2011

< 0.015 Air 4/20/2011

< 0.013 Air 4/27/2011

< 0.013 Air 5/4/2011

< 0.010 I

Air 5/11/2011

< 0.012 Air 5/18/2011

< 0.011 Air 5/26/2011

< 0.005 1

Air 6/1/2011

< 0.008 Air 6/8/2011

< 0.007 1

Air 6/15/2011

< 0.011 Air 6/22/2011

< 0.006 Air 6/29/2011

< 0.007 Air 7/6/2011

< 0.013 Air 7/13/2011

< 0.009 Air 7/20/2011

< 0.010 Air 7/27/2011

< 0.010 Air 8/3/2011

< 0.012 Air 8/10/2011

< 0.005 Air 8/17/2011

< 0.006 Air 8/24/2011

< 0.007 Air 8/31/2011

< 0.007 Air 9/7/2011

< 0.008 Air 9/14/2011

< 0.007 Air 9/21/2011

< 0.008 Air 9/29/2011

< 0.008 Air 10/5/2011

< 0.007 Air 10/12/2011

< 0.008

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 10/19/2011

< 0.006 Air 10/26/2011

< 0.007 Air 11/2/2011

< 0.008 Air 11/8/2011

< 0.007 1

Air 11/16/2011

< 0.011 I

Air 11/23/2011

< 0.007 1

Air 11/30/2011

< 0.005 I

Air 12/7/2011

< 0.005 I

Air 12/14/2011

< 0.012 Air 12/21/2011

< 0.013 Air 12/28/2011

< 0.005 3

Air 1/5/2011

< 0.005 3

Air 1/12/2011

< 0.010 3

Air 1/19/2011

< 0.010 3

Air 1/26/2011

< 0.006 3

Air 2/3/2011

< 0.004 3

Air 2/9/2011

< 0.006 3

Air 2/16/2011

< 0.004 3

Air 2/24/2011

< 0.010 3

Air 3/2/2011

< 0.013 3

Air 3/9/2011

< 0.008 3

Air 3/16/2011

< 0.011 3

Air 3/23/2011 0.056 +/- 0.012 3

Air 3/30/2011 LLD 3

Air 4/6/2011 0.107 +/- 0.018 3

Air 4/13/2011

< 0.013 3

Air 4/20/2011

< 0.009 3

Air 4/27/2011

< 0.012 3

Air 5/4/2011

< 0.009 3

Air 5/11/2011

< 0.011 3

Air 5/18/2011

< 0.011 3

Air 5/26/2011

< 0.005 3

Air 6/1/2011

< 0.008 3

Air 6/8/2011

< 0.007 3

Air 6/15/2011

< 0.016 3

Air 6/22/2011

< 0.006 3

Air 6/29/2011

< 0.007 3

Air 7/6/2011

< 0.012 3

Air 7/13/2011

< 0.009 3

Air 7/20/2011

< 0.010 3

Air 7/27/2011

< 0.010 0-9

Air Iodine Detail Report 2011 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 8/3/2011

< 0.012 3

Air 8/10/2011

< 0.005 3

Air 8/17/2011

< 0.006 3

Air 8/24/2011

< 0.007 3

Air 8/31/2011

< 0.007 3

Air 9/7/2011

< 0.008 3

Air 9/14/2011

< 0.007 3

Air 9/21/2011

< 0.008 3

Air 9/29/2011

< 0.008 3

Air 10/5/2011

< 0.007 3

Air 10/12/2011

< 0.008 3

Air 10/19/2011

< 0.007 3

Air 10/26/2011

< 0.007 3

Air 11/2/2011

< 0.008 3

Air 11/8/2011

< 0.007 3

Air 11/16/2011

< 0.010 3

Air 11/23/2011

< 0.010 3

Air 11/30/2011

< 0.005 3

Air 12/7/2011

< 0.005 3

Air 12/14/2011

< 0.012 3

Air 12/21/2011

< 0.013 3

Air 12/28/2011

< 0.005 4

Air 1/5/2011

< 0.006 4

Air 1/12/2011

< 0.011 4

Air 1/19/2011

< 0.010 4

Air 1/26/2011

< 0.006 4

Air 2/2/2011

< 0.005 4

Air 2/9/2011

< 0.006 4

Air 2/16/2011

< 0.004 4

Air 2/24/2011

< 0.011 4

Air 3/2/2011

< 0.013 4

Air 3/9/2011

< 0.009 4

Air 3/16/2011

< 0.012 4

Air 3/23/2011 0.082 +/- 0.017 4

Air 3/30/2011 LLD 4

Air 4/6/2011 0.113 +/- 0.016 4

Air 4/13/2011 LLD 4

Air 4/20/2011

< 0.010 4

Air 4/27/2011

< 0.013 4

Air 5/4/2011

< 0.010 4

Air 5/11/2011

< 0.011

o * *A* * * * *Io

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o ooo 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 5/18/2011

< 0.011 4

Air 5/26/2011

< 0.005 4

Air 6/1/2011

< 0.008 4

Air 6/8/2011

< 0.007 4

Air 6/15/2011

< 0.008 4

Air 6/22/2011

< 0.007 4

Air 6/29/2011

< 0.007 4

Air 7/6/2011

< 0.013 4

Air 7/13/2011

< 0.009 4

Air 7/20/2011

< 0.010 4

Air 7/27/2011

< 0.010 4

Air 8/3/2011

< 0.012 4

Air 8/10/2011

< 0.005 4

Air 8/17/2011

< 0.006 4

Air 8/24/2011

< 0.007 4

Air 8/31/2011

< 0.007 4

Air 9/7/2011

< 0.008 4

Air 9/14/2011

< 0.007 4

Air 9/21/2011

< 0.008 4

Air 9/29/2011

< 0.008 4

Air 10/5/2011

< 0.007 4

Air 10/12/2011

< 0.008 4

Air 10/19/2011

< 0.007 4

Air 10/26/2011

< 0.007 4

Air 11/2/2011

< 0.008 4

Air 11/8/2011

< 0.007 4

Air 11/16/2011

< 0.011 4

Air 11/23/2011

< 0.013 4

Air 11/30/2011

< 0.005 4

Air 12/7/2011

< 0.005 4

Air 12/14/2011

< 0.013 4

Air 12/21/2011

< 0.013 4

Air 12/28/2011

< 0.005 5

Air 1/5/2011

< 0.006 5

Air 1/12/2011

< 0.011 5

Air 1/19/2011

< 0.010 5

Air 1/26/2011

< 0.006 5

Air 2/2/2011

< 0.005 5

Air 2/9/2011

< 0.006 5

Air 2/16/2011

< 0.004 5

Air 2/24/2011

< 0.011 C-lI

Air Iodine Detail Report 2011 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 5

5 5

Sample Type Collection Date Air 3/2/2011 Air 3/9/2011 Air 3/16/2011 Air 3/23/2011 Air 3/30/2011 Air 4/6/2011 Air 4/13/2011 Air 4/20/2011 Air 4/27/2011 Air 5/4/2011 Air 5/11/2011 Air 5/18/2011 Air 5/26/2011 Air 6/1/2011 Air 6/8/2011 Air 6/15/2011 Air 6/22/2011 Air 6/29/2011 Air 7/6/2011 Air 7/13/2011 Air 7/20/2011 Air 7/27/2011 Air 8/3/2011 Air 8/10/2011 Air 8/17/2011 Air 8/24/2011 Air 8/31/2011 Air 9/7/2011 Air 9/14/2011 Air 9/21/2011 Air 9/29/2011 Air 10/5/2011 Air 10/12/2011 Air 10/19/2011 Air 10/26/2011 Air 11/2/2011 Air 11/8/2011 Air 11/16/2011 Air 11/23/2011 Air 11/30/2011 Air 12/7/2011 Air 12/14/2011 Air 12/21/2011 00 00 0 000 00 0 1-131

< 0.014

< 0.008

< 0.010 0.064 +/- 0.013 LLD 0.091 +/- 0.017

< 0.017

< 0.011

< 0.009

< 0.010

< 0.011

< 0.005

< 0.008

< 0.007

< 0.017

< 0.006

< 0.007

< 0.013

< 0.010

< 0.012

< 0.005

< 0.006

< 0.007

< 0.008

< 0.009

< 0.008

< 0.007

< 0.009

< 0.007

< 0.011

-< 0.012

0.011

< 0.006

< 0.013

< 0.014 00 we 0 00 0 000 0 000 0 00 0 0 0900 000000

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 12/28/2011

< 0.005 6

Air 1/5/2011

< 0.006 6

Air 1/12/2011

< 0.011 6

Air 1/19/2011

< 0.011 6

Air 1/26/2011

< 0.006 6

Air 2/2/2011

< 0.005 6

Air 2/9/2011

< 0.006 6

Air 2/16/2011

< 0.004 6

Air 2/24/2011

< 0.011 6

Air 3/2/2011

< 0.014 6

Air 3/9/2011

< 0.009 6

Air 3/16/2011

< 0.012 6

Air 3/23/2011 0.069 +/- 0.016 6

Air 3/30/2011 LLD 6

Air 4/6/2011 0.127 +/- 0.021 6

Air 4/13/2011 LLD 6

Air 4/20/2011

< 0.010 6

Air 4/27/2011

< 0.013 6

Air 5/4/2011

< 0.010 6

Air 5/11/2011

< 0.012 6

Air 5/18/2011

< 0.011 6

Air 5/26/2011

< 0.005 6

Air 6/1/2011

< 0.008 6

Air 6/8/2011

< 0.007 6

Air 6/15/2011

< 0.017 6

Air 6/22/2011

< 0.006 6

Air 6/29/2011

< 0.007 6

Air 7/6/2011

< 0.014 6

Air 7/13/2011

< 0.011 6

Air 7/20/2011

< 0.012 6

Air 7/27/2011

< 0.011 6

Air 8/3/2011

< 0.013 6

Air 8/10/2011

< 0.005 6

Air 8/17/2011

< 0.006 6

Air 8/24/2011

< 0.008 6

Air 8/31/2011

< 0.007 6

Air 9/7/2011

< 0.008 6

Air 9/14/2011

< 0.007 6

Air 9/21/2011

< 0.009 6

Air 9/29/2011

< 0.008 6

Air 10/5/2011

< 0.008 C-13

Air Iodine Detail Report 2011 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 10/12/2011

< 0.008 6

Air 10/19/2011

< 0.007 6

Air 10/26/2011

< 0.007 6

Air 11/2/2011

< 0.009 6

Air 11/8/2011

< 0.007 6

Air 11/16/2011

< 0.011 6

Air 11/23/2011

< 0.010 6

Air 11/30/2011

< 0.005 6

Air 12/7/2011

< 0.005 6

Air 12/14/2011

< 0.013 6

Air 12/21/2011

< 0.013 6

Air 12/28/2011

< 0.005 7

Air 1/5/2011

< 0.006 7

Air 1/12/2011

< 0.011 7

Air 1/19/2011

< 0.011 7

Air 1/26/2011

< 0.006 7

Air 2/2/2011

< 0.005 7

Air 2/9/2011

< 0.006 7

Air 2/16/2011

< 0.004 7

Air 2/24/2011

< 0.011 7

Air 3/2/2011

< 0.014 7

Air 3/9/2011

< 0.009 7

Air 3/16/2011

< 0.012 7

Air 3/23/2011 0.065 +/- 0.013 7

Air 3/30/2011 LLD 7

Air 4/6/2011 0.098 +/- 0.013 7

Air 4/13/2011 LLD 7

Air 4/20/2011

< 0.012 7

Air 4/27/2011

< 0.014 7

Air 5/4/2011

< 0.010 7

Air 5/11/2011

< 0.012 7

Air 5/18/2011

< 0.011 7

Air 5/26/2011

< 0.005 7

Air 6/1/2011

< 0.008 7

Air 6/8/2011

< 0.008 7

Air 6/15/2011

< 0.007 7

Air 6/22/2011

< 0.007 7

Air 6/29/2011

< 0.007 7

Air 7/6/2011

< 0.013 7

Air 7/13/2011

< 0.010 7

Air 7/20/2011

< 0.011

eeeeeeeeeeeeeeeeeeeeweeeeeeeeeeeeeeeeeeeee

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 7/27/2011

< 0.010 7

Air 8/3/2011

< 0.013 7

Air 8/10/2011

< 0.005 7

Air 8/17/2011

< 0.006 7

Air 8/24/2011

< 0.007 7

Air 8/31/2011

< 0.007 7

Air 9/7/2011

< 0.008 7

Air 9/14/2011

< 0.008 7

Air 9/21/2011

< 0.009 7

Air 9/29/2011

< 0.008 7

Air 10/5/2011

< 0.008 7

Air 10/12/2011

< 0.008 7

Air 10/19/2011

< 0.007 7

Air 10/26/2011

< 0.007 7

Air 11/2/2011

< 0.009 7

Air 11/8/2011

< 0.007 7

Air 11/16/2011

< 0.011 7

Air 11/23/2011

< 0.016 7

Air 11/30/2011

< 0.005 7

Air 12/7/2011

< 0.005 7

Air 12/14/2011

< 0.012 7

Air 12/21/2011

< 0.013 7

Air 12/28/2011

< 0.005 35 Air 1/5/2011

< 0.008 35 Air 1/12/2011

< 0.014 35 Air 1/19/2011

< 0.010 35 Air 1/26/2011

< 0.010 35 Air 2/2/2011

< 0.008 35 Air 2/9/2011

< 0.013 35 Air 2/16/2011

< 0.008 35 Air 2/24/2011

< 0.008 35 Air 3/2/2011

< 0.013 35 Air 3/9/2011

< 0.010 35 Air 3/16/2011

< 0.014 35 Air 3/23/2011 0.076 +/- 0.015 35 Air 3/30/2011 LLD 35 Air 4/6/2011 0.111 +/- 0.017 35 Air 4/13/2011 LLD 35 Air 4/20/2011

< 0.012 35 Air 4/27/2011

< 0.011 35 Air 5/4/2011

< 0.011 C-15

Air Iodine Detail Report 2011 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 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 Sample Type Collection Date Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air 5/11/2011 5/18/2011 5/26/2011 6/1/2011 6/8/2011 6/15/2011 6/22/2011 6/29/2011 7/6/2011 7/13/2011 7/20/2011 7/27/2011 8/3/2011 8/10/2011 8/17/2011 8/24/2011 8/31/2011 9/7/2011 9/14/2011 9/21/2011 9/29/2011 10/5/2011 10/12/2011 10/19/2011 10/26/2011 11/2/2011 11/8/2011 11/16/2011 11/23/2011 11/30/2011 12/7/2011 12/14/2011 12/21/2011 12/28/2011 1-131 0.009 0.006 0.009 0.007 0.011 0.010 0.015 0.010 0.012 0.012 0.013 0.008 0.008 0.010 0.013 0.008 0.007 0.011 0.011 0.009 0.006 0.007 0.012 0.007 0.007 0.010 0.007 0.008 0.010 0.014 0.014 0.011 0.006 0.006 000000000000000000000qvooooooooooooooooooooo

Fish Gamma Spectral Detail Report 2011 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 catfish 25 freshwater dnrm 25 yellow perch 32 catfish 32 freshwater drum 32 yellow perch 8/5/2011 8/5/2011 8/5/2011 8/5/2011 8/5/2011 8/5/2011

< 11.05 1,342.40 +/- 267.90

< 13.77 1,327.30 +/- 271.20

< 11.74 1,276.60 +/- 265.90

< 9.35 1,220.60 +/- 267.40

< 11.62 1,132.70 +/- 260.00

< 10.99 1,823.20 +/- 400.70 10.66 16.52 8.60

9.54 13.49 10.61 11.09 13.61

9.93 11.24 11.01

9.48

< 11.60

< 11.81

< 4.78

< 18.46

< 12.62

< 11.84

< 9.35

< 9.99

< 9.72

< 18.08

< 10.88

< 12.39

< 11.76

< 13.78

< 9.44

< 11.05

< 8.74

< 13.60

< 29.87

< 30.21

< 28.17

< 28.67

< 44.63

< 32.21 C-17

Location Sample Type 2

collard greens 2

swiss chard 2

turnip greens 2

beet greens 2

collard greens 2

turnip greens 2

collard greens 2

swiss chard 2

turnip greens Collection Date 7/13/2011 7/13/2011 7/13/2011 8/9/2011 8/9/2011 8/9/2011 9/13/2011 9/13/2011 9/13/2011 Food Products Gamma Spectral Detail Report 2011 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 Be-7 Co-58 Co-60 1-131 K-40

< 132.21

< 6.66

< 7.77

< 21.35 3,979.40+/- 349.90 181.11 +/- 101.20

< 8.46

< 11.45

< 21.05 4,762.60 +/- 374.70

< 132.21

< 6.66

< 7.77

< 21.35 3,979.40 +/- 349.90 679.62+/- 128.80

< 7.27

< 9.64

< 18.07 6,306.70 +/- 405.20

< 119.58

< 9.91

< 9.65

< 22.03 3,873.00 +/- 342.80 679.62+/- 128.80

< 7.27

< 9.64

< 18.07 6,306.70 +/- 405.20 749.85 +/- 136.70

< 5.68

< 7.39

< 16.29 4,645.90 +/- 333.60 1,736.70 +/- 157.30

< 6.90

< 6.30

< 16.14 7,399.40 +/- 405.90 1,428.50 +/- 155.50

< 5.80

< 5.90

< 21.65 5,660.50 +/- 359.30 Cs-134

< 10.44

< 12.26

< 10.44

< 8.68

< 9.94

< 8.68

< 10.67

< 10.07

< 7.22 Cs-137 11.43 9.27 11.43 12.95 13.31 12.95 8.11 12.88 11.79 16 16 beet greens turnip greens 7/13/2011 7/13/2011

< 155.01

< 13.23

< 155.01

< 13.23

< 7.48 6,671.60 +/- 449.80

< 7.48 6,671.60 +/- 449.80 6.34 6.34 10.67 10.67 11.59 11.59

.000000000000

Food Products Gamma Spectral Detail Report 2011 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 beet greens 8/9/2011 420.71 +/- 173.40

< 14.45

< 5.94

< 13.00

< 13.17

< 20.54 5,730.30 +/- 436.50 16 swiss chard 8/9/2011 276.92 +/- 92.77

< 12.09

< 10.11

< 9.37

< 6.97

< 11.73 4,861.30 +/-337.50 16 turnip greens 8/9/2011 420.71 +/- 173.40

< 14.45

< 5.94

< 13.00

< 13.17

< 20.54 5,730.30 +/- 436.50 16 collard greens 9/13/2011 578.34 +/- 163.60

< 8.95

< 6.52

< 8.20

< 6.90

< 19.33 3,846.60 +/- 333.20 16 swiss chard 9/13/2011 726.96 +/- 157.20

< 10.77

< 9.22

< 7.69

< 8.80

< 19.49 4,485.80 +/- 349.70 16 turnip greens 9/13/2011 746.31 +/- 122.40

< 10.45

< 6.38

< 9.23 10.19

< 18.60 4,714.30 +/341.30 18 collard greens 7/13/2011

< 124.75

< 14.54

< 10.97

< 7.95

< 16.16

< 23.55 5,515.40 +/- 433.90 18 turnip greens 7/13/2011

< 124.75

< 14.54

< 10.97

< 7.95

< 16.16

< 23.55 5,515.40 +/- 433.90 18 collard greens 8/9/2011

< 131.00

< 11.15

< 5.16

< 8.95

< 8.91

< 15.96 5,200.80 +/- 409.90 18 swiss chard 8/9/2011 427.24+/- 138.20

< 11.09

< 7.88

< 10.54

< 9.51

< 16.40 6,791.10 +/-419.40 18 turnip greens 8/9/2011

< 131.00

< 11.15

< 5.16

< 8.95

< 8.91

< 15.96 5,200.80 +/- 409.90 C-19

Location Sample Type 18 collard greens 18 swiss chard 18 turnip greens Collection Date 9/13/2011 9/13/2011 9/13/2011 Food Products Gamma Spectral Detail Report 2011 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 Be-7 Co-58 Co-60 1-131 K-40 658.25 +/o 121.20

< 5.74

< 6.37

< 20.45 4,898.60 +/- 346.90 976.78 +/- 145.50

< 8.96

< 8.84

< 14.21 6,218.70+/- 377.40 764.54 +/- 121.20

< 4.44

< 9.81

< 18.63 5,280.10 +/- 387.20 Cs-134

< 8.13

< 8.41

< 11.40 Cs-137

< 9.77

< 10.90

< 12.48 collard greens turnip greens turnip greens beet greens turnip greens collard greens swiss chard turnip greens 7/13/2011 8/9/2011 9/13/2011 7/13/2011 7/13/2011 8/9/2011 8/9/2011 8/9/2011 334.51 +/- 116.70

< 19.40 350.64 +/- 131.50

< 16.84 920.41 +/- 137.20

< 14.85 227.86 +/- 109.80

< 19.69 227.86 +/- 109.80

< 19.69

< 96.60

< 13.10 380.89 +/- 98.69

< 11.64

< 96.60

< 13.10

< 7.27 6,288.60 +/- 466.20

< 8.55 3,401.40 +/- 304.30

< 9.75 4,043.30 +/- 324.50

< 10.64 4,854.50 +/- 379.60

< 6.17 3,277.40 +/- 273.20

< 8.61 2,799.80 +/- 273.80

< 6.17 3,277.40 +/- 273.20 9.06 6.77 5.51 12.93 8.39 8.95 9.31 9.31 5.02 6.60 5.02 10.29 10.29 6.48 7.40 6.48 17.89 9.60 13.75 14.58 14.58 9.80 10.63 9.80

Food Products Gamma Spectral Detail Report 2011 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 collard greens 9/13/2011 418.19+/-96.20

< 6.24

< 6.77

< 6.49

< 8.21

< 14.28 2,744.40 +/- 246.90 37 swiss chard 9/13/2011 752.41 +/- 113.10

< 3.53

< 5.49

< 6.35

< 9.10

< 13.89 2,654.10 +/-238.20 37 turnip greens 9/13/2011 1,224.60 +/- 152.30

< 8.64

< 7.81

< 8.31

< 6.92

< 14.22 5,394.60+/- 380.00 70 collard greens 7/13/2011

< 99.52

< 7.70

< 5.53

< 9.01

< 11.70

< 14.58 4,452.60+/- 332.40 70 turnip greens 7/13/2011

< 99.52

< 7.70

< 5.53

< 9.01

< 11.70

< 14.58 4,452.60+/- 332.40 70 collard greens 8/9/2011

< 125.32

< 11.36

< 8.85

< 9.72

< 13.96

< 18.97 3,148.30 +/-402.20 70 swisschard 8/9/2011 291.40+/-95.27

< 8.37

< 6.61

< 9.89

< 13.30

< 18.87 4,643.30+/- 340.80 70 turnip greens 8/9/2011

< 125.32

< 11.36

< 8.85

< 9.72

< 13.96

< 18.97 3,148.30 +/-402.20 70 swiss chard 9/13/2011 873.62 +/- 156.60

< 10.12

< 3.80

< 9.59

< 5.47

< 23.09 5,771.20 +/-370.00 70 turnip greens 9/13/2011 788.49 +/- 134.10

< 9.15

< 8.45

< 7.50

< 10.17

< 10.94 4,037.70 +/- 329.60 C-21

Milk Gamma Spectral Detail Report 2011 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 Ba-140 Cs-134 Cs-137 Location Sample Type Collection Date K-40 La-140 18 18 18 18 Milk Milk Milk Milk 18 Milk 18 18 18 18 18 18 18 Milk Milk Milk Milk Milk Milk Milk 1/4/2011 2/7/2011 3/7/2011 4/4/2011 4/18/2011 5/2/2011 5/16/2011 6/6/2011 6/20/2011 7/5/2011 7/18/2011 8/1/2011

< 12

< 19

< 15

< 27 19

< 12

< 24

< 22

< 14

< 22

< 20

< 41

< 2

< 3

< 4

< 3

< 4

< 3

< 4

< 3

< 4

< 5

< 4

< 3

< 5

< 4

< 5

< 5 1,777 +/- 107 1,553 +/- 106 1,734 +/- 92 1,871 +/- 141 1,753 +/- 133 1,620+/- 115 1,609 +/- 119 1,762 +/- 121 1,760 +/- 113 1,607 +/- 125 1,620 +/- 130 1,683 +/- 112

< 2

< 3

< 2

< 6

< 4

< 2

< 3

< 5

< 2

< 6

Milk Gamma Spectral Detail Report 2011 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 8/15/2011

< 23

< 3

< 4 1,674+/-110

< 4 18 Milk 9/6/2011

< 27

< 4

< 4 1,902+/-140

< 2 18 Milk 9/19/2011

< 23

< 5

< 6 1,290+/-141

< 3 19 Milk 8/1/2011

< 28

< 2

< 3 1,393 +/-106

< 6 19 Milk 8/15/2011

< 17

< 3

< 3 1,436+/-97

< 3 19 Milk 9/6/2011

< 19

< 3

< 3 1,274+/-95

< 3 19 Milk 9/20/2011

< 21

< 3

< 4 1,114+/-111

< 4 19 Milk 10/3/2011

< 25

< 3

< 4 1,321+/-113

< 3 19 Milk 10/18/2011

< 23

< 4

< 4 1,293+/- 140

< 3 19 Milk 11/7/2011

< 28

< 3

< 3 1,436+/- 131

< 3 19 Milk 12/5/2011

< 14

< 3

< 2 1,244+/-87

< 2 C-23

Milk Gamma Spectral Detail Report 2011 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 Milk Milk Milk Milk Milk Milk Milk 6/6/2011 6/20/2011 7/5/2011 7/18/2011 8/1/2011 8/15/2011 9/6/2011 9/19/2011 1/4/2011 2/7/2011 3/7/2011 1,735 +/- 117 1,765 +/- 119 1,868 +/- 131 1,791 +/- 115 1,861 +/ 130 1,153 +/- 97 1,748 +/- 120 1,711 +/- 110 942 +/- 84 981 +/- 90 1,330 +/- 88

< 2

< 4

< 3

< 4

< 5

< 3

< 5

< 3

< 2

< 2 Milk Milk Milk 17 14 11 3

3 2

eeeeeeeeeeeeeeeeeeee**eeeeeeeeeeeeeee0eeee

Milk Gamma Spectral Detail Report 2011 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 51 Milk 4/4/2011

< 32

< 3

< 3 1,231+/-110

< 4 51 Milk 4/18/2011

< 19

< 3

< 4 756+/-75

< 3 51 Milk 5/2/2011

< 10

< 3

< 4 1,231+/-102

< 2 51 Milk 5/16/2011 19

< 3

< 3 1,106+/-111

< 3 51 Milk 6/6/2011 15

< 3

< 2 966+/-84

< 3 51 Milk 6/20/2011

< 22

< 3

< 4 1,334+/-118

< 3 51 Milk 7/5/2011

< 21

< 3

< 4 1,046+/- 100

< 5 51 Milk 7/18/2011

< 13

< 3

< 4 1,301+/-117

< 4 51 Milk 8/1/2011

< 26

< 3

< 3 970+/-96

< 4 51 Milk 8/15/2011

< 19

< 2

< 3 1,845+/- 116

< 4 51 Milk 9/6/2011

< 17

< 4

< 4 1,210+/-96

< 4 51 Milk 9/19/2011

< 20

< 2

< 3 1,027+/-82

< 3 C-25

Milk Gamma Spectral Detail Report 2011 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 pCiiL +/- 2 Sigma Location Sample Type 51 Milk 51 Milk 51 Milk 51 Milk 61 Milk 61 Milk 61 Milk 61 Milk Collection Date Ba-140 Cs-134 Cs-137 K-40 La-140 10/3/2011 10/18/2011 11/7/2011 12/5/2011 4/4/2011 4/18/2011 5/2/2011 5/16/2011

< 18

< 22

< 15

< 14

< 28

< 26

< 3

< 4

< 3

< 2

< 3

< 2

< 3

< 2

< 3

< 4

< 3

< 2

< 4

< 4 1,021 +/- 101 717+/-85 888 +/- 91 932+/-98 1,535 +/- 119 1,723 +/- 120 1,579 +/- 120 1,687 +/- 130

< 2

< 5

< 2

< 5

< 1

< 4

< 9

< 22

Milk Iodine Detail Report 2011 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 1/4/2011

< 0.32 18 Milk 2/7/2011

< 0.32 18 Milk 3/7/2011

< 0.37 18 Milk 4/4/2011

< 0.43 18 Milk 4/18/2011 2.23 +/- 0.27 18 Milk 5/2/2011 1.36 +/- 0.19 18 Milk 5/16/2011

< 0.38 18 Milk 6/6/2011

< 0.31 18 Milk 6/20/2011

< 0.29 18 Milk 7/5/2011

< 0.37 18 Milk 7/18/2011

< 0.23 18 Milk 8/1/2011

< 0.25 18 Milk 8/15/2011

< 0.32 18 Milk 9/6/2011

< 0.42 18 Milk 9/19/2011

< 0.42 19 Milk 8/1/2011

< 0.22 19 Milk 8/15/2011

< 0.47 19 Milk 9/6/2011

< 0.33 19 Milk 9/20/2011

< 0.27 19 Milk 10/3/2011

< 0.37 19 Milk 10/18/2011

< 0.37 19 Milk 11/7/2011

< 0.40 19 Milk 12/5/2011

< 0.31 41 Milk 6/6/2011

< 0.21 41 Milk 6/20/2011

< 0.46 41 Milk 7/5/2011

< 0.34 41 Milk 7/18/2011

< 0.22 41 Milk 8/1/2011

< 0.41 41 Milk 8/15/2011

< 0.26 41 Milk 9/6/2011

< 0.32 41 Milk 9/19/2011

< 0.42 51 Milk 1/4/2011

< 0.34 51 Milk 2/7/2011

< 0.33 51 Milk 3/7/2011

< 0.31 51 Milk 4/4/2011

< 0.47 51 Milk 4/18/2011

< 0.25 51 Milk 5/2/2011

< 0.32 51 Milk 5/16/2011

< 0.50 C-27

Milk Iodine Detail Report 2011 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 51 Milk 6/6/2011

< 0.28 51 Milk 6/20/2011

< 0.32 51 Milk 7/5/2011

< 0.32 51 Milk 7/18/2011

< 0.22 51 Milk 8/1/2011

< 0.42 51 Milk 8/15/2011

< 0.35 51 Milk 9/6/2011

< 0.35 51 Milk 9/19/2011

< 0.38 51 Milk 10/3/2011

< 0.43 51 Milk 10/18/2011

< 0.47 51 Milk 11/7/2011

< 0.36 51 Milk 12/5/2011

< 0.29 61 Milk 4/4/2011

< 0.42 61 Milk 4/18/2011 1.25 +/- 0.23 61 Milk 5/2/2011

< 0.38 61 Milk 5/16/2011

< 0.48

TLD Gamma Dose Detail Report 2011 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 TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/18/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 10.79 8.53 10.20 8.94 11.24 11.04 10.76 10.98 12.14 11.47 11.66 12.06 11.13 11.17 10.88 11.71 12.73 12.14 12.43 12.82 11.90 11.86 11.99 12.83 10.82 10.36 10.51 10.78 10.91 10.31 10.58 10.86 0.58 1.02 0.66 1.06 0.67 1.12 0.70 0.98 0.62 0.68 0.69 1.11 0.53 0.63 0.79 0.87 0.63 0.74 1.13 0.91 0.48 0.85 0.54 0.96 0.47 0.60 0.72 0.86 0.47 0.78 0.63 0.97 10 10 1/5/2011 to 4/26/2011 4/26/2011 to 7/12/2011 13.29

+/-

0.61 13.57

+/-

1.08 C-29

TLD Gamma Dose Detail Report 2011 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 TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 7/12/2011 to 0/17/2011 10/17/2011 to 1/6/2012 13.24

+/-

0.58 14.79

+/-

1.26 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/18/2011 1/5/2011 4/26/2011 7/12/2011 10/18/2011 1/5/2011 4/26/2011 7/12/2011 10/18/2011 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/18/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/18/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/18/2011 to 1/6/2012 12.93 11.80 13.13 12.33 11.93 11.23 12.32 11.19 12.74 10.94 12.21 11.64 11.17 10.69 10.77 10.41 10.80 7.63 11.15 7.11 13.10 12.37 14.00 11.94 14.05 12.50 15.12 12.46 12.28 11.62 12.68 11.65 0.67 0.65 0.98 0.82 0.67 1.08 0.77 1.16 0.52 0.92 0.62 1.08 0.61 0.83 0.62 0.91 0.75 0.81 0.72 0.85 0.59 1.06 0.78 0.88 0.51 0.70 0.60 0.80 0.53 0.75 0.75 1.21

* * * * * * * * * * * * * * * *

o*9T,,,AoPoAti,204 * * * * * * * * * * * * * * *

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 29 29 29 29 30 30 30 30 TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 15.99 14.78 16.86 15.24 14.30 13.70 15.75 13.99 0.60 0.82 0.74 0.99 0.67 0.64 0.85 0.92 0.77 0.80 0.80 14.98

+/-

15.89

+/-

16.11

+/-

10/17/2011 to 1/6/2012 16.68

+/-

1.02 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/18/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/18/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/18/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/18/2011 16.25 16.39 17.19 17.35 11.50 11.26 12.65 11.97 14.68 15.33 15.97 15.98 12.46 12.20 13.90 13.45 12.01 11.76 12.89 12.24 0.81 0.70 1.03 1.06 0.70 0.69 0.84 0.87 0.38 1.08 0.53 0.86 0.71 1.17 0.69 1.19 0.77 0.54 0.88 0.76 1.40 0.69 1.51 12.60

+/

12.52

+/

13.68

+/

C-31

TLD Gamma Dose Detail Report 2011 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 55 TLD 10/18/2011 to 1/6/2012 13.16

+/-

0.88 56 TLD 1/5/2011 to 4/26/2011 12.05

+/-

0.57 56 TLD 4/26/2011 to 7/12/2011 12.71

+/-

1.09 56 TLD 7/12/2011 to 0/17/2011 12.83

+/-

0.61 56 TLD 10/17/2011 to 1/6/2012 13.38

+/-

1.25 58 TLD 1/5/2011 to 4/26/2011 9.94

+/-

0.48 58 TLD 4/26/2011 to 7/12/2011 9.97

+/-

0.65 58 TLD 7/12/2011 to 0/17/2011 10.70

+/-

0.63 58 TLD 10/17/2011 to 1/6/2012 10.18

+/-

0.78 000000000000000000000irooooooooooooooooooooo

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 1

TLB 1/5/2011 to 4/26/2011 11.23

+/-

0.99 1

TLB 4/26/2011 to 7/12/2011 8.75

+/-

1.42 I

TLB 7/12/2011 to 0/17/2011 9.94

+/-

1.12 1

TLB 10/17/2011 to 1/6/2012 10.89

+/-

1.40 3

TLB 1/5/2011 to 4/26/2011 12.10

+/-

0.63 3

TLB 4/26/2011 to 7/12/2011 9.62

+/-

1.30 3

TLB 7/12/2011 to 0/17/2011 11.88

+/-

0.48 3

TLB 10/17/2011 to 1/6/2012 11.35

+/-

1.13 4

TLB 1/5/2011 to 4/26/2011 12.15

+/-

0.33 4

TLB 4/26/2011 to 7/12/2011 12.67

+/-

0.97 4

TLB 7/12/2011 to 0/17/2011 12.32

+/-

0.61 4

TLB 10/17/2011 to 1/6/2012 14.62

+/-

1.05 5

TLB 1/5/2011 to 4/26/2011 12.87

+/-

0.36 5

TLB 4/26/2011 to 7/12/2011 11.42

+/-

1.01 5

TLB 7/12/2011 to 0/17/2011 12.70

+/-

0.48 5

TLB 10/17/2011 to 1/6/2012 13.84

+/-

1.13 6

TLB 1/5/2011 to 4/26/2011 13.23

+/-

0.96 6

TLB 4/26/2011 to 7/12/2011 12.28

+/-

0.93 6

TLB 7/12/2011 to 0/18/2011 12.86

+/-

0.57 6

TLB 10/18/2011 to 1/6/2012 14.32

+/-

0.96 7

TLB 1/5/2011 to 4/26/2011 13.89

+/-

0.27 7

TLB 4/26/2011 to 7/12/2011 13.85

+/-

1.05 7

TLB 7/12/2011 to 0/17/2011 13.88

+/-

0.48 7

TLB 10/17/2011 to 1/6/2012 16.09

+/-

1.03 8

TLB 1/5/2011 to 4/26/2011 12.56

+/-

1.44 8

TLB 4/26/2011 to 7/12/2011 11.93

+/-

0.96 8

TLB 7/12/2011 to 0/17/2011 11.70

+/-

0.56 8

TLB 10/17/2011 to 1/6/2012 13.65

+/-

0.85 9

TLB 1/5/2011 to 4/26/2011 11.76

+/-

0.61 9

TLB 4/26/2011 to 7/12/2011 11.22

+/-

1.19 9

TLB 7/12/2011 to 0/17/2011 11.81

+/-

0.60 9

TLB 10/17/2011 to 1/6/2012 12.83

+/-

1.07 10 TLB 1/5/2011 to 4/26/2011 14.25

+/-

0.65 10 TLB 4/26/2011 to 7/12/2011 14.82

+/-

0.92 10 TLB 7/12/2011 to 0/17/2011 14.27

+/-

0.58 C-33

TLD Gamma Dose Detail Report 2011 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 TLB Collection Period 10/17/2011 to 1/6/2012 Exposure 16.13

+/-

0.89 TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/18/2011 1/5/2011 4/26/2011 7/12/2011 10/18/2011 1/5/2011 4/26/2011 7/12/2011 10/18/2011 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/18/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/18/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/18/2011 to 1/6/2012 13.24 13.00 12.88 14.59 12.89 12.62 13.02 13.98 12.50 11.83 12.54 13.40 11.71 11.39 10.96 12.54 10.61 9.90 10.54 11.61 14.15 12.76 13.63 13.59 13.48 12.96 14.08 13.97 13.24 11.23 12.93 12.36 1.21 1.22 0.68 1.05 0.31 1.22 0.48 1.29 0.33 1.37 0.47 1.66 1.02 0.96 0.64 0.93 0.78 1.09 0.61 0.97 0.28 1.15 0.57 1.02 0.70 0.93 1.02 1.28 1.51 0.78 1.28 0.83 1/5/2011 to 4/26/2011 16.28

+/-

0.48

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 29 TLB 4/26/2011 to 7/12/2011 16.16

+/-

1.34 29 TLB 7/12/2011 to 0/17/2011 16.48

+/-

0.56 29 TLB 10/17/2011 to 1/6/2012 16.86

+/-

1.33 30 TLB 1/5/2011 to 4/26/2011 14.92

+/-

0.43 30 TLB 4/26/2011 to 7/12/2011 13.64

+/-

0.84 30 TLB 7/12/2011 to 0/17/2011 15.58

+/-

0.60 30 TLB 10/17/2011 to 1/6/2012 15.03

+/-

0.76 31 TLB 1/5/2011 to 4/26/2011 15.72

+/-

0.97 31 TLB 4/26/2011 to 7/12/2011 15.49

+/-

0.98 31 TLB 7/12/2011 to 0/17/2011 16.59

+/-

0.79 31 TLB 10/17/2011 to 1/6/2012 16.64

+/-

1.16 33 TLB 1/5/2011 to 4/26/2011 16.61

+/-

0.60 33 TLB 4/26/2011 to 7/12/2011 17.07

+/-

1.09 33 TLB 7/12/2011 to 0/17/2011 17.40

+/-

0.61 33 TLB 10/17/2011 to 1/6/2012 18.47

+/-

1.40 35 TLB 1/5/2011 to 4/26/2011 12.26

+/-

0.40 35 TLB 4/26/2011 to 7/12/2011 12.08

+/-

0.77 35 TLB 7/12/2011 to 0/17/2011 12.85

+/-

0.52 35 TLB 10/17/2011 to 1/6/2012 13.70

+/-

0.74 36 TLB 1/5/2011 to 4/26/2011 15.92

+/-

0.27 36 TLB 4/26/2011 to 7/12/2011 16.41

+/-

0.95 36 TLB 7/12/2011 to 0/18/2011 16.29

+/-

0.45 36 TLB 10/18/2011 to 1/6/2012 16.62

+/-

1.15 53 TLB 1/5/2011 to 4/26/2011 13.30

+/-

0.43 53 TLB 4/26/2011 to 7/12/2011 14.11

+/-

0.72 53 TLB 7/12/2011 to 0/18/2011 14.19

+/-

0.53 53 TLB 10/17/2011 to 1/6/2012 14.25

+/-

1.15 54 TLB 1/5/2011 to 4/26/2011 12.97

+/-

0.51 54 TLB 4/26/2011 to 7/12/2011 13.54

+/-

0.78 54 TLB 7/12/2011 to 0/17/2011 13.73

+/-

0.59 54 TLB 10/17/2011 to 1/6/2012 14.24

+/-

0.77 55 TLB 1/5/2011 to 4/26/2011 13.85

+/-

1.01 55 TLB 4/26/2011 to 7/12/2011 14.61

+/-

0.84 55 TLB 7/12/2011 to 0/18/2011 14.01

+/-

0.70 55 TLB 10/18/2011 to 1/6/2012 15.05

+/-

1.18 C-35

TLD Gamma Dose Detail Report 2011 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 56 56 56 56 58 58 58 58 TLB TLB TLB TLB TLB TLB TLB TLB 1/5/2011 4/26/2011 7/12/2011 10/17/2011 1/5/2011 4/26/2011 7/12/2011 10/17/2011 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 to 4/26/2011 to 7/12/2011 to 0/17/2011 to 1/6/2012 12.88 13.73 13.49 14.16 10.24 10.90 11.00 11.45 0.63 1.34 0.75 1.26 0.47 0.81 0.79 0.79

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 I

TLA 1/5/2011 to 1/6/2012 52.01

+/-

2.40 3

TLA 1/5/2011 to 1/6/2012 50.47

+/-

1.27 4

TLA 1/5/2011 to 1/6/2012 67.14

+/-

1.41 5

TLA 1/5/2011 to 1/6/2012 54.60

+/-

1.66 6

TLA 1/5/2011 to 1/6/2012 64.68

+/-

1.22 7

TLA 1/5/2011 to 1/6/2012 53.05

+/-

1.90 8

TLA 1/5/2011 to 1/6/2012 58.35

+/-

1.93 9

TLA 1/5/2011 to 1/6/2012 52.67

+/-

3.22 10 TLA 1/5/2011 to 1/6/2012 71.70

+/-

2.45 11 TLA 1/5/2011 to 1/6/2012 66.28

+/-

4.82 12 TLA 1/5/2011 to 1/6/2012 60.77

+/-

1.97 13 TLA 1/5/2011 to 1/6/2012 60.13

+/-

2.60 14 TLA 1/5/2011 to 1/6/2012 49.07

+/-

3.21 15 TLA 1/5/2011 to 1/6/2012 51.48

+/-

2.09 21 TLA 1/5/2011 to 1/6/2012 68.33

+/-

4.52 23 TLA 1/5/2011 to 1/6/2012 61.22

+/-

2.01 24 TLA 1/5/2011 to 1/6/2012 56.45

+/-

2.88 29 TLA 1/5/2011 to 1/6/2012 72.05

+/-

1.70 30 TLA 1/5/2011 to 1/6/2012 70.42

+/-

2.10 31 TLA 1/5/2011 to 1/6/2012 77.42

+/-

2.32 33 TLA 1/5/2011 to 1/6/2012 80.26

+/-

4.82 C-37

TLD Gamma Dose Detail Report 2011 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 35 TLA 1/5/2011 to 1/6/2012 59.49

+/-

2.18 36 TLA 1/5/2011 to 1/6/2012 77.91

+/-

4.02 53 TLA 1/5/2011 to 1/6/2012 63.73

+/-

2.32 54 TLA 1/5/2011 to 1/6/2012 62.64

+/-

4.92 55 TLA 1/5/2011 to 1/6/2012 64.85

+/-

4.67 56 TLA 1/5/2011 to 1/6/2012 66.25

+/-

2.64 58 TLA 1/5/2011 to 1/6/2012 51.22

+/-

1.88

Looo*o

,oO

*

0

o*ooo*ooo*o*oo 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 C-39

Water Gamma Spectral Detail Report 2011 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 28 Water Water Water Water Water Water Water Water Water Water Water Water Collection Period 1/27/2011 to 1/27/2011 1/27/2011 to 2/24/2011 2/24/2011 to 3/31/2011 4/28/2011 to 4/28/2011 4/28/2011 to 5/26/2011 5/26/2011 to 6/30/2011 6/30/2011 to 7/29/2011 7/29/2011 to 8/25/2011 8/25/2011 to 9/28/2011 9/28/2011 to 0/27/2011 0/27/2011 to 1/30/2011 1/24/2011 to 2/29/2011 Ba-140 Fe-59 Zr-95

< 19.89

< 9.47

< 10.10

< 14.02

< 4.65

< 3.60

< 26.87

< 4.43

< 3.38

< 17.91

< 6.15

< 4.40

< 25.99

< 2.90

< 3.39

< 25.94

< 7.28

< 5.19

< 22.82

< 5.08

< 4.37

< 21.00

< 6.38

< 4.13

< 16.20

< 6.30

< 6.53

< 12.49

< 3.61

< 5.23

< 19.86

< 3.74

< 4.04

< 20.29

< 3.54

< 4.32 Co-58 La-140

< 4.23

< 7.31

< 2.70

< 1.79

< 2.49

< 4.14

< 2.49

< 6.17

< 3.61

< 8.69

< 3.93

< 6.73

< 3.12

< 7.15

< 2.44

< 2.27

< 2.82

< 3.93

< 1.88

< 2.01

< 1.03

< 4.95

< 2.12

< 6.07 Co-60 Mn-54

< 4.52

< 5.10

< 2.29

< 3.05

< 3.16

< 2.16

< 2.58

< 3.03

< 3.14

< 3.28 1.70

< 3.18 1.46

< 2.44

< 1.39

< 2.58

< 2.02

< 2.35

< 1.90

< 2.91

< 1.35

< 2.10

< 1.09

< 2.23 Cs-134 Nb-95

< 4.94

< 8.42

< 3.21

< 3.02

< 3.12

< 4.28

< 2.45

< 4.93

< 2.96

< 5.58

< 3.12

< 2.95

< 2.21

< 2.13

< 2.56

< 4.24

< 3.32

< 3.87

< 2.95

< 3.94

< 1.92

< 2.61

< 2.88

< 2.59 Cs-137 Zn-65

< 6.69

< 12.49

< 2.33

< 2.50

< 3.90

< 3.13

< 2.91

< 3.26

< 5.78

< 5.30

< 2.14

< 4.05

< 2.53

< 4.09

< 2.26

< 3.53

< 3.60

< 3.50

< 2.39

< 3.40

< 2.07

< 2.65

< 2.67

< 5.74

eeeeeeeeeeeeeeee@eeee~@@e@e@eeeeeeee@ee@@e@

Water Gamma Spectral Detail Report 2011 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 Water Water Water Water Water Water Water Water Water Water Water

.2/30/2010 to 1/27/2011 1/27/2011 to 2/24/2011 2/24/2011 to 3/31/2011 3/31/2011 to 4/28/2011 4/28/2011 to 5/26/2011 5/26/2011 to 6/30/2011 6/30/2011 to 7/29/2011 8/25/2011 to 8/25/2011 8/25/2011 to 9/28/2011 9/28/2011 to.0/27/2011

.0/27/2011 to 1/30/2011

.1/24/2011 to.2/29/2011

< 22.14

< 4.87

< 4.60 17.29

< 5.73

< 7.27

< 22.64

< 5.38

< 3.80

< 21.12

< 5.40

< 3.96

< 12.92

< 3.82

< 5.17

< 18.38

< 8.56

< 8.49

< 22.16

< 5.93

< 5.22

< 1.61

< 6.03

< 2.94

< 4.11

< 3.27

< 6.52

< 1.89

< 4.47

< 2.82

< 2.29

< 2.99

< 5.90

< 2.57

< 7.95

< 1.65

< 2.17

< 2.40

< 2.24

< 2.82

< 5.62

< 2.19

< 2.91

< 2.10

< 4.41

< 3.87

< 3.52

< 2.19

< 1.79

< 2.98

< 3.75

< 1.79

< 2.80

< 2.01

< 2.55

< 3.47

< 4.05

< 2.65

< 2.55

< 1.39

< 2.10

< 1.22

< 1.94

< 2.04

< 4.30

< 1.55

< 2.07

< 1.62

< 2.95

< 4.57

< 3.38

< 2.37

< 2.93

< 2.80

< 3.94

< 2.09

< 2.22

< 2.85

< 2.16

< 2.82

< 4.73

< 2.41

< 3.07

< 2.44

< 3.67

< 3.17

< 3.31

< 3.34

< 3.62

< 2.57

< 3.60

< 2.60

< 3.09

< 4.64

< 6.72

< 2.91

< 5.49

< 3.84

< 3.87

< 2.67 1.90

< 3.06

< 2.38

< 3.80

< 7.29

< 2.08

< 3.77

< 2.30

< 5.20

< 3.85

< 3.08

< 4.76

< 5.02

< 2.15

< 6.00

< 3.03

< 3.34 20.01 3.95 4.79

< 15.63

< 4.06

< 5.58

< 25.46

< 6.18

< 5.58 9.07 6.27 3.87

< 16.90

< 5.14

< 6.21 C-41

Water Gamma Spectral Detail Report 2011 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 Water Water

'Water Water Water Water Water Water Water Water Water

.2/30/2010 to 1/27/2011 1/27/2011 to 2/24/2011 2/24/2011 to 3/31/2011 3/31/2011 to 4/28/2011 4/28/2011 to 5/26/2011 5/26/2011 to 6/30/2011 6/30/2011 to 7/29/2011 7/29/2011 to 8/25/2011 8/25/2011 to 9/28/2011 9/28/2011 to 0/27/2011

.0/27/2011 to ý 1/30/2011 1/24/2011 to 2/29/2011

< 15.40

< 4.48

< 6.72

< 16.36

< 5.72

< 3.60

< 28.25

< 8.21

< 3.69

< 28.33

< 5.80

< 4.52

< 20.51

< 5.26

< 4.40

< 13.91

< 3.40

< 3.27

< 32.22

< 6.56

< 4.51

< 21.53

< 6.41

< 4.79

< 23.82

< 5.48

< 6.27

< 11.46

< 4.49

< 5.94

< 16.13

< 4.01

< 6.47

< 15.60

< 2.95

< 2.93

< 2.77

< 2.89

< 1.84

< 2.46

< 3.04

< 5.09

< 2.34

< 4.09

< 2.66

< 3.55

< 3.12

< 4.83

< 2.55

< 3.69

< 1.45

< 3.60

< 2.48

< 6.17

< 1.45

< 2.85

< 2.23

< 2.89

< 1.51

< 2.50

< 3.27

< 3.23

< 3.34

< 2.71

< 2.91

< 2.45

< 1.76

< 1.83

< 2.51

< 3.15

< 1.91

< 3.30

< 2.50

< 2.49

< 1.65

< 1.84

< 2.15

< 3.36

< 1.34

< 2.62

< 2.31

< 2.50

< 1.87

< 2.36

< 4.47

< 3.02

< 2.19

< 2.76

< 3.36

< 4.62

< 2.56

< 3.97

< 2.84

< 3.04

< 2.47

< 3.27

< 2.85

< 3.44

< 2.30

< 2.03

< 3.21

< 3.20

< 2.19

< 2.24

< 3.30

< 3.53

< 2.22

< 3.14

< 4.13

< 3.19

< 2.35

< 3.08

< 3.00

< 2.90

< 3.66

< 4.19

< 3.50

< 3.04

< 2.82

< 3.10

< 2.38

< 2.81

< 2.58

< 3.76

< 3.12

< 2.50

< 2.15

< 4.64

< 2.01

< 5.23

< 3.34

< 2.93

Water Gamma Spectral Detail Report 2011 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 pCiiL +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fc-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Water Water Water Water Water Water Water Water Water Water Water 4/6/2011 to 4/28/2011 4/28/2011 to 5/26/2011 5/26/2011 to 6/30/2011 6/30/2011 to 7/29/2011 7/29/2011 to 8/25/2011 8/25/2011 to 9/28/2011 9/28/2011 to.0/27/2011

.0/27/2011 to.1/30/2011 1/30/2011 to 2/29/2011 4/6/2011 to 4/28/2011 4/28/2011 to 5/26/2011

< 27.69

< 4.40

< 6.90

< 19.68

< 5.08

< 5.21

< 21.00

< 4.61

< 4.04

< 18.44

< 3.42

< 3.06

< 22.68

< 4.99

< 5.83

< 19.33

< 3.00

< 4.73

< 23.23

< 8.07

< 3.75

< 20.21

< 2.74

< 4.27

< 12.00

< 4.43

< 5.18

< 26.39

< 3.36

< 3.27

< 17.95

< 3.12

< 3.97

< 3.18

< 5.90

< 3.09

< 5.25

< 2.00

< 4.41

< 1.78

< 7.95

< 2.41

< 4.66

< 3.49

< 2.76

< 2.91

< 5.01

< 1.74

< 3.56

< 2.29

< 5.84

< 1.81

< 3.60

< 2.41

< 3.67

< 1.77

< 3.22 1.66

< 2.59

< 3.09

< 2.79

< 1.73

< 2.11

< 2.73

< 2.62 1.91 2.39

< 3.02

< 3.62

< 2.18

< 2.77 1.74

< 2.59

< 1.72

< 2.66 1.58 1.48

< 2.24

< 4.34

< 1.77

< 2.37

< 3.98

< 3.58

< 2.19

< 3.18

< 2.84

< 2.60

< 3.76

< 3.82

< 3.06

< 3.33

< 2.73

< 4.05

< 3.06

< 3.46

< 2.40

< 4.08

< 2.66

< 2.82

< 2.60

< 4.63

< 3.09

< 3.73

< 3.87

< 4.44

< 3.07 3.58

< 3.55

< 4.24

< 3.18

< 4.22

< 2.85

< 6.48

< 2.73

< 4.58

< 3.76

< 5.31

< 2.03

< 2.59

< 3.53

< 3.43 C-43

Water Gamma Spectral Detail Report 2011 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 60 60 60 60 60 60 Water Water Water Water Water Water Water 5/26/2011 to 6/30/2011 6/30/2011 to 7/29/2011 7/29/2011 to 8/25/2011 8/25/2011 to 9/28/2011 9/28/2011 to 0/27/2011 0/27/2011 to 1/30/2011

.1/30/2011 to 2/29/2011

< 14.59

< 4.70

< 3.88

< 28.06

< 3.68

< 4.64

< 22.68

< 6.97

< 3.11

< 16.34

< 4.61

< 5.35

< 2.86

< 4.52

< 2.57

< 8.31

< 3.51

< 6.50

< 3.19

< 4.30

< 2.14

< 6.79

< 1.83

< 2.59

< 1.68

< 5.43

< 1.44

< 3.31

< 1.96

< 1.53

< 2.59

< 2.15

< 1.19

< 1.69

< 1.54

< 1.81

< 1.73

< 1.18

< 1.37

< 1.79

< 2.45

< 2.93

< 2.06

< 4.06

< 2.45

< 3.17

< 2.65

< 3.21 1.91

< 3.46

< 1.86

< 1.73

< 2.10

< 3.12

< 3.34

< 2.09

< 2.55

< 4.21

< 2.72

< 3.55

< 3.39

< 3.55

< 2.53

< 3.44

< 2.42

< 2.91

< 2.98

< 4.89 17.81 4.77 4.44

< 17.83

< 5.86

< 3.19 19.71 5.73 3.71

Water Gross Beta Detail Report 2011 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 12/30/2010 to 1/27/2011 1/27/2011 to 1/27/2011 1/27/2011 to 2/24/2011 2/24/2011 to 3/31/2011 3/31/2011 to 4/28/2011 4/6/2011 to 4/28/2011 4/28/2011 to 4/28/2011 4/28/2011 to 5/26/2011 5/26/2011 to 6/30/2011 6/30/2011 to 7/29/2011 7/29/2011 to 8/25/2011 8/25/2011 to 8/25/2011 Water Water Water Water Water Water Water Water Water Water Water Water LLD LLD LLD LLD LLD LLD LLD 3.06 +/- 1.41 LLD LLD 4.11 +/- 1.53

< 2.16 4.25 +/- 1.59

< 1.88 LLD LLD LLD LLD LLD

< 0.86 LLD 1.65

< 0.88 LLD

< 1.61 LLD

< 0.87 LLD 3.61 +/- 1.49 LLD

< 1.82 LLD LLD

< 0.87 C-45

Water Gross Beta Detail Report 2011 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 8/25/2011 to 9/28/2011 Water LLD

< 0.87 LLD LLD LLD 9/28/2011 to 10/27/2011 Water LLD LLD LLD LLD LLD 10/27/2011 to 11/30/2011 Water LLD LLD LLD LLD LLD 11/24/2011 to 12/29/2011 Water LLD LLD LLD 11/30/2011 to 12/29/2011 Water LLD LLD

Water Tritium Detail Report 2011 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 28 28 28 34 34 34 34 36 36 36 36 59 59 59 60 60 60 Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water 3/31/2011 6/30/2011 9/28/2011 12/29/2011 3/31/2011 6/30/2011 9/28/2011

[2/29/2011 3/31/2011 6/30/2011 9/28/2011 12/29/2011 6/30/2011 9/28/2011 12/29/2011 6/30/2011 9/28/2011 12/29/2011 141.23 147.99 143.11 144.36 141.23 147.99 143.11 144.36 141.23 147.99 143.11 144.36 147.99 143.11 144.36 147.99 143.11 144.36 C-47

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 0

0 S

0 0

0 APPENDIX D CORRECTIONS TO PREVIOUS ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORTS 0

0 0

0

00 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 0

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

2010 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT

1 Page 12 of 2010 annual report Table 2b, Summation of Continuous Liquid Effluent Releases The value for line E, Waste Volume Released, Liters (prior to dilution) 4th quarter was incorrect. The correct value is

4.32E+05.

Page 38 of 2010 annual report 0Northwest Drain Impoundment sediment samples collected on 5/26/10 identified Co-58 at

location 64-9. Mn-54 was also identified in the sample but not reported. The value for Mn-54

)

in the 5/26/10 sample was 248 +/- pCi/kg dry.

0 0

0

0 0

0 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX E ABNORMAL RELEASES

0 0

0 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX E ABNORMAL RELEASES In November 2011, radioactivity was detected in the Nuclear Closed Cooling (NCC) system.

The source of this activity has not been identified. There is some leakage from the NCC system to Service Water and from there to the environment. Conservatively, activity calculations are done assuming that all leakage from the NCC system is going to Service Water. Daily NCC samples are being analyzed and system leakage is being tracked. The calculated activity released from NCC has been included in the total radioactivity released.

QUARTER QUARTER QUARTER QUARTER ANNUAL 1

2 3

4 TOTAL A.

Fission and Activation Products (Ci)

Na-24

<LLD

<LLD 9.25E-05 9.25E-05 Mn-54

<LLD

<LLD 1.17E-05 1.17E-05 Mn-56

<LLD

<LLD 1.09E-06 1.09E-06.

Co-58

<LLD

<LLD 3.50E-05 3.50E-05 Co-60

<LLD

<LLD 2.38E-07 2.38E-07 Zn-69m

<LLD

<LLD 1.62E-07 1.62E-07 Cs-1 37

<LLD

<LLD 5.27E-05 5.27E-05 B.

Tritium

<LLD

<LLD 3.20E-03 3.20E-03 C.

Dissolved and Entrained Gases (Ci)

Xe-135

<LLD

<LLD 1.62E-07 1.62E-07 D. Gross Alpha Activity, (Ci)

<LLD

0 0

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX F ODCM NON-COMPLIANCES

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX F ODCM NON-COMPLIANCES An Emergency Service Water sample was missed on 8/30/11 due to short duration of pump run. CR-2011-01331 The Unit 1 Plant Vent Gaseous Effluent Monitor was out of service for greater than 30 days.

The

> 30 day duration was due to being unable to obtain the needed part. Monitor was out of

service from 5/6/11 to 6/14/11. CR-G202-2011-95984

The Liquid Radwaste to Emergency Service Water Liquid Effluent Monitor was out of service for greater than 30 days. The > 30 day duration was due to parts availability issues. The monitor was out of service from 5/31/11 to 1/7/12. CR-2011-00211 The Emergency Service Water B Liquid Effluent Monitor was out of service for greater than 30 days. The > 30 day duration was due the time it took to obtain a new pump for the effluent

!I monitor. The monitor was out of service from 7/5/11 to 8/5/11. CR-2011-00227

Environmental air sampler at location #5 was found not running on 11/30/201. Sample volume collect prior to sampler stopping was sufficient to meet ODCM LLD requirements.

Sample pump was replaced. CR-2011-06114 0

S S

S 0

S S

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX G CHANGES TO PROCESS CONTROL PROGRAM

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX G CHANGES TO THE PROCESS CONTROL PROGRAM

1 During this reporting period, there was one (1) revision to the Process Control Program.

Rev. 12 SCOPE OF REVISION:

Changed section 3.1.1 to permit the use of uniquely numbered seals asa

t replacement for the clearance program for isolating tanks for processing.

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