Text

Annual Environmental and Effluent Release Report
	ML101270132
Person / Time
Site:	Perry
Issue date:	04/29/2010
From:	Bezilla M; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-10-114
	Download: ML101270132 (144)
	v • d • e

FENOC Perry Nuclear Power Station 10 Center Road FirstEnergy Nuclear Operating Company Perry, Ohio 44081 Mark B. Bezilla 440-280-5382 Vice President Fax: 440-280-8029 April 29, 2010 L-10-114 10 CFR 50.36a(a)(2)

ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440 Annual Environmental and Effluent Release Report Enclosed is the Annual Environmental and Effluent Release Report for the Perry Nuclear Power Plant (PNPP) for the period of January 1, 2009 through December 31, 2009. This document includes the radiological environmental operating report, radioactive effluent release report, and the non-radiological environmental operating report which satisfies the requirements of the PNPP Technical Specifications (TS), the PNPP Offsite Dose Calculation Manual (ODCM), and the Environmental Protection Plan, Appendix B of the PNPP Operating License.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Jeffrey Tufts, Manager-Chemistry at (440) 280-5458.

Sincerely, Mark B. Bezilla

Enclosure:

PNPP 2009 Annual Environmental and Effluent Release Report cc:

NRC Region III Administrator NRC Resident Inspector NRR Project Manager L 1Z_

Perry Nuclear Power Plant I

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-i Annual Environmental & Effluent Release Report 2009

2009 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT for the Perry Nuclear Power Plant PREPARED BY:

CHEMISTRY SECTION PERRY NUCLEAR POWER PLANT FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY, OHIO MARCH, 2010

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

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

1 Radiological Environm ental M onitoring........................................................................................

1 Land Use Census.......................................................

2 Clam/M ussel M onitoring......................................................................................................

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

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

3 IN TRO D U CTION...................................................................................................................

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

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

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

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

5 Background Radiation..........................................................................................................

6 RA D IO A CTIV E EFFLU EN T RELEA SES........................................................................

7 Introduction....................................................................................................................................

7 Regulatory Lim its...........................................................................................................................

7 Release Summ ary...........................................................................................................................

9 M eteorological Data.....................................................................................................................

16 Dose A ssessm ent..........................................................................................................................

16 On-Site Groundwater M onitoring Program............................................................................

18 Abnorm al Releases.......................................................................................................................

21 N on-Compliances.........................................................................................................................

22 Offsite Dose Calculation M anual Changes...............................................................................

23 Process Control Program Changes.........................................................................................

23 RADIOLOGICAL ENVIRONMENTAL MONITORING................................................

24 Introduction..................................................................................................................................

24 Sam pling Locations......................................................................................................................

24 Sam ple Analysis...........................................................................................................................

29 2009 Sam pling Program...............................................................................................................

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

38 Land U se Census..........................................................................................................................

40 CLA M /M U SSEL M ON ITO RIN G.................................................................................... 43 Introduction..................................................................................................................................

43 Corbicula Program........................................................................................................................

43 Conclusions.........................................................................

45 H ERBICID E A PPLICA TION S.........................................................................................

46 SPECIA L REPO RTS.........................................................................................................

48 N on-Compliances.........................................................................................................................

48 Unreviewed Environm ental Questions...................................................................................

48 APPENDICES Appendix A: 2009 Inter-Laboratory Cross Check Comparison Program Results Appendix B: 2009 REMP Data Summary Reports Appendix C: 2009 REMP Detailed Data Report Appendix D: Corrections to Previous AEERR Table of Contents Page i

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT EXECUTIVE

SUMMARY

The Annual Environmental and Effluent Release Report (AEERR) details the results of environmental and effluent monitoring programs conducted at the Perry Nuclear Power Plant (PNPP) from January 01 through December 31, 2009. This report meets all of the requirements in PNPP Technical Specifications, the Environmental Protection Plan (EPP), and Regulatory Guide 1.21. It incorporates the requirements of the Annual Radioactive Effluent Release Report (ARERR),

the Annual Radiological Environmental Operating Report (AREOR) and the Annual Environmental Operating Report (AEOR). Report topics include radioactive effluent releases, radiological environmental monitoring, land use census, clam/mussel monitoring, herbicide use, and special reports. The results of the environmental and effluent programs, for 2009 indicate that the operations of the Perry Nuclear Power Plant did not result in any significant environmental impact.

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

The dose to the general public from the plant's liquid and gaseous effluents was below the applicable regulatory limits. The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP liquid effluents was 3.5 7E-04 mrem (0.01 % of the applicable limit). The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents was 4.45E-8 mrem (<0.00000009%

of the applicable limit). The summation of the hypothetical maximum individual dose from effluents in 2009 is equivalent to < 0.01 % of the total dose an individual living in the PNPP area receives from all sources of radiation.

Shipments of solid waste consisted of waste generated during water treatment; radioactive material generated during normal daily operations and maintenance, and irradiated components. PNPP complied with applicable regulations governing radioactive shipments in 2009, 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.

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

The REMP was established at PNPP six (6) years before the plant became operational. This pre-operational program was designed to provide data on background radiation and radioactivity normally present in the area. PNPP has continued to monitor the environment during plant operation by collecting and analyzing samples of air, precipitation, milk, fish, produce, water and sediment, as well as by measuring radiation directly.

There were over 2700 radioactivity analyses performed on the 1356 radiological environmental samples collected in 2009. The results of the REMP indicate the adequacy of the control of the release of radioactivity in the effluents from PNPP. These results also demonstrate that PNPP Executive Summary Page 1

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT complies with applicable federal regulations. The REMP results are divided into four sections:

atmospheric monitoring, terrestrial monitoring, aquatic monitoring, and direct radiation monitoring.

3 Samples of air were collected to monitor the radioactivity in the atmosphere. The 2009 results were similar to those observed for the pre-operational and operational programs from prior years. Only natural background, environmental radioactivity was detected.

Terrestrial monitoring included the analysis of milk and produce. The PNPP ODCM does not require vegetation or soil samples to be included in the monitoring program. The results of the sample analyses in 2009 indicated concentrations of radioactivity similar to that found in previous I

years. Analyses of other terrestrial samples also detected concentrations of natural radioactivity similar to those observed in previous years, and indicated no build-up of radioactivity attributable to i

the operation of PNPP.

Aquatic monitoring included the collection and analyses of water, fish, and shoreline sediments. The 2009 analytical results for water and fish samples showed normal background radionuclide concentrations. The results of sediment sample analyses indicated that the annual average cesium I

radioactivity was similar to previous years for the control location. Cesium-137 activity was detected in four (4) of the eleven (11) samples collected. The average cesium-137 radioactivity for I

all locations was 505.24 pCi/kg and is within the maximum value of 864 pCi/kg established in 1981.

In 1999, a sediment sample of the northwest drain impoundment (sampling location #64) was analyzed to contain 62 pCi/kg of cobalt-60. During 2009, enhanced monitoring activities continued within the boundaries of the impoundment. The cobalt-60 remains centered within the organic I

material located at the top of the spillway, with little or no activity found farther upstream. Sample analyses continue to identify cobalt-60 levels similar to those found in previous years. Refer to, Table 17 for detailed sample results.

Direct radiation measurements showed no change from previous years. The indicator locations averaged 54.03 mrem/year and control locations averaged 50.20 mremlyear. In 2009, 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 2009, the operation of the PNPP resulted in no significant increase in the radionuclide concentrations observed in the environment.

LAND USE CENSUS In order to estimate radiation dose attributable to the operation of PNPP, the potential pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed as part of the REMP. During the census, PNPP personnel travel every public road within a five (5) mile radius of the plant to locate key radiological exposure pathways. These key pathways include the nearest resident, garden, and milk animal in each of the sixteen meteorological sectors. The information obtained from the census is entered into a computer program, which is used to assess the hypothetical dose to members of the public. In recent years, I

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 2009, the predominant land use within the census area continues to be rural and/or agricultural.

i I

Executive Summary Page 2i

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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 andmussels ha:s been conducted in Lake Erie in the vicinity of PNPP since 1971. The monitoring is specifically for Corbicula (Asiatic clams), since their introduction into the Great Lakes, in 1981, and for Dreissena (zebra mussels), since their discovery in Lake Erie, in 1989. Since no Corbicula have ever been found at PNPP, routine, Corbicula monitoring will provide early detection capability when this pest species arrives at PNPP. The Dreissena program includes both monitoring and control and is directed at minimizing the mussel's impact on plant operation. As in past years, this program has successfully prevented Dreissena from causing any significant operational problems at PNPP.

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

SPECIAL REPORTS Significant environmental events (for example, spills, releases), noncompliance with environmental regulations [e.g., Ohio Environmental Protection Agency (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 2009:

o A spill of approximately 3-5gallons of hydraulic fluid entered two storm drains that caused a sheen in the Minor Steam Impoundment on October 9, 2009. The spill was promptly cleaned up and all proper notifications were made.

Executive Summary Page 3

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT INTRODUCTION 3

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.

1 RADIATION FUNDAMENTALS Atoms are the basic building blocks of all matter. Simply described, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, i

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 I

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, I

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 i

emission of radiation. Radionuclides vary greatly in the frequency with which their atoms release radiation. The length of time an atom remains radioactive is defined in terms of its half-life. Half-life is defined as the time required for a radioactive substance to lose half its activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years.

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

radiation produced by radioactive decay.

Alpha Particles 3

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

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

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

Beta Particles i

Beta particles are essentially free electrons, which usually carry a negative electrical charge. They are much smaller than alpha particles and travel at nearly the speed of light. Thus they can travel for longer distances than alpha particles. External beta radiation primarily affects the skin. Because of I

their electrical charge, paper, plastic or thin metals can stop beta particles.

R Radiological Effluent Releases Page 4i

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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 amuch higher energy. Gamma rays can travel long distances in air and are often released during radioactive decay, along with alpha and beta particles. Potassium-40 is an example of a naturally occurring radionuclide found in all humans that decays by emitting a gamma ray.

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

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

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

Dose Biological damage due to alpha, beta, and gamma radiation may result from the ionization caused by these types of radiation. Some types of radiation, especially alpha particles, which causes dense local ionization, can result in much more biological damage for the same energy imparted than does gamma or beta radiation. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose (as measured in rads), the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any type of ionizing radiation. The dose equivalent is measured in terms of the Roentgen Equivalent Man (rem). When discussing environmental radiation effects, the rem is a large unit. Therefore, a smaller unit, the millirem (mrem) is often used. One mrem is equivalent to 1/1000 of a rem.

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

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

Radiological Effluent Releases Page 5

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT BACKGROUND RADIATION Background radiation is a part of nature. Natural background radioactive decay occurs in the soil, water, air, and space. Common sources of radiation that contribute to the natural background radiation includes: the decay of radioactive elements in the earth's crust, a steady stream of high-energy particles from space (called cosmic radiation), naturally-occurring radioactive isotopes in the U

human body like potassium-40, the decay of radioisotopes used in medical procedures, man-made phosphate fertilizers (phosphates and uranium are often found together in nature), fallout from nuclear weapons testing, and even household items like smoke detectors. In the United States, a person's average annual exposure from background radiation is 360 mrem, and is due to the sources shown in Figure I [Source: National Council on Radiation Protection and Measurements].

3 I

Internal Terrestial 10.94%

7.95%

Nuclear Fuel Cycle 0.09%

I Cosmic.

Nuclear Medicine 7.95 3.98%

Consumer Products MI Ilaneous 2.80%

Fall-Out 010

_,0 -

ther 0.75%

O ccuaonal Sources 3

0.30%

Radon 54.69%

3 Figure 1: Sources of Background Radiation 3

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

present include:

Beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere, I

Potassium-40, a naturally occurring radionuclide normally found in humans and throughout the environment, and Radionuclides from nuclear weapons testing fallout, including tritium and cesium-137. These radionuclides may also be released in minute amounts from nuclear facilities.

3 Beryllium-7 and potassium-40 are especially common in REMP samples. Since they are naturally occurring and are expected to be present, positive results for these radionuclides are not discussed in the section for the 2009 Sampling Program results. These radionuclides are included; however, in Appendix A, 2009 Inter-Laboratory Cross Check Comparison Program Results.

Radiological Effluent Releases Page 6

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

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

The liquid and gaseous radioactive waste treatment systems at PNPP are designed to collect and process these wastes in order to remove most of the radioactivity. Effluent monitoring systems are used to provide continuous indication of the radioactivity present and are sensitive enough to measure several orders of magnitude lower than the applicable release limits. This monitoring equipment is equiiped with alarms and indicators in the l11ant control room. The alarms are set to provide warnings to alert plant operators when radioactivity levels reach a small fraction of actual limits. The waste streams are sampled and analyzed to identify and quantify the radionuclides being released to the environment.

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

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

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

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

[10CFR20], Appendix B; Title 10 of the Code of Federal Regulations, Part 50 (Domestic Licensing of Production and Utilization Facilities) [10CFR50], Appendix I; and.

Title 40 of the Code of Federal Regulations, Part 190 (Environmental Radiation Protection Standards for Nuclear Power Plants) [40CFR190].

These limits were incorporated into the PNPP Technical Specifications, and subsequently into the PNPP Offsite Dose Calculation Manual (ODCM). The ODCM prescribes the maximum doses and 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 Radioactive Effluent Releases Page 7

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT i

no other fuel sources near the PNPP; the 40CFR190 limits, which are described below, were not exceeded in 2009.

3 The 40CFRI90 limit for total direct-radiation dose is 25 mrem. For 2009, the total whole body dose to a member of the general public, considering all sectors, was 3.4E-1 person-Rem. This value was determined by summing the annual whole body doses from liquid and gaseous radioactive effluents, U

the annual gaseous and liquid organ dose (refer to Table 8) and the maximum, direct-radiation dose.

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

3 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 I

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 ViCi/mL of total activity. These values are the maximum effluent concentrations.

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

During any calendar quarter:

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

3 During any calendar year:

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

Gaseous Effluents Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and i

beyond the site boundary shall be limited.to the following:

Noble gases:

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

Iodine-13 1, Iodine-133, Tritium, and'all radionuclides in particulate form with half lives greater than eight days:

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

During any calendar quarter:

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

During any calendar year:

m Less than or equal to 10 mrad for gamma radiation, and Less than or equal to 20 mrad for beta radiation.

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Radioactive Effluent Releases Pag e883a

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Dose to a member of the public from Iodine-131, Iodine-13 3, 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 toanyorgan per any calendar quarter, and Less than or equal to 15 mrem to any organ per any calendar year.

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

RELEASE

SUMMARY

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

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

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

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

Liquid radioactive waste system effluents may be intermittently released, which are considered to be "batch" releases. Table 1 provides information on the number and duration of these releases for 2009.

Table 1: Liquid Batch Releases QUARTER1 QUARTER2 QUARTER3 QUARTER4 ANNUAL TOTAL Number of batch releases 41 30 5

21 97 Total time period for batch releases, min 9.12E+03 7O01E+03 1.09E+03 5.17E+03 2.24E+04 Maximum time for a batch release, min 2.63E+02 2.42E+02 2.32E+02 2.79E+02 2.79E+02 Average time period for a batch release, min 2.22E+02 2.34E+02 2.19E+02 2.46E+02 2.30E+02 Minimum time for a batch release, min 2.OOE+02 1.92E+02 2.09E+02 1.63E+02 1.63E+02 Average stream flow during periods of effluent 1.83E+05 2.3 1E+05 2.87E+05 2.04E+05 2.08E+05 release into a flowing stream, L/min Radioactive Effluent Releases Page 9

ANNUAL ENVIRONMENTALAND 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, (M)

A.

Fission and Activation Products

1. Total Released, Ci 1.99E-02 2.55E-03 5.14E-04 7.66E-04 1.00E+01 (excluding tritium, gases, alpha)

2. Average Diluted Concentration, jACi/mL

9.92E-10 8.88E-1 1 1.43E-11 3.62E-I1

3.

Percent of Applicable Limit, %

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

Tritium

1. Total Released, Ci 1.62E+01 1.02E+01 1.55E+00 1.06E+01 1.00E+01

2.

Average Diluted Concentration, 1tCi/mL 8.08E-07 3.55E-07 4.30E-08 5.01E-07

3. Percent of Applicable Limit,%

8.08E-03 3.55E-03 4.30E-02 5.01E-03 C.

Dissolved and Entrained Gases

1. Total Released, Ci

<LLD

<LLD 1.00E+01

2. Average Diluted Concentration, ptCi/mL

<LLD

3. Percent of Applicable Limit, %

N/A N/A N/A N/A D.

Gross Alpha Activity, Ci

<LLD

<LLD 1.00E+01 E.

Waste Volume Released, Liters (prior to 5.19E+06 4.94E+06 4.94E+6 3.40E+06 1.00E+01 dilution)

I I

F.

Dilution Water Volume Used, Liters 2.0lEl I 2.76E1 1 3.60E1 I 2.12E1 I I.E+O1

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

A verage diluted concentrations are based on total volunme of water released during quarter.

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U I

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I Radioactive Effluent Releases Page 10

2. 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 1.99E-02 2.55E-03 5.14E-04 7.66E-04 1.00E+01 (excluding tritium, gases, alpha)

B.

Tritium Total Released, Ci 1.59E+01 l:02E+01 1.55E+00 1.06E+01 1.003+01 C.

Dissolved and Entrained Gases Total Released, Ci

<LLD

<LLD 1.001E+01 D.

Gross Alpha Activity, Ci

<LLD

<LLD 1.00E+01 E.

Waste Volume Released, Liters (prior to 5.19E+06 4.09E+06 6.28E+05 2.66E+06 1.00E+01 dilution)

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

1 2

3 4

TOTAL

ERROR, A.

Fission and Activation Products Total Released, Ci

<LLD

<LLD 1.00E+01 (excluding tritium, gases, alpha)

B.

Tritium Total Released, Ci 2.13E-01 3.07E-02

<LLD

<LLD 1.00E+01 C.

Dissolved and Entrained Gases Total Released, Ci

<LLD

<LLD 1.00E+01 D. Gross Alpha Activity, Ci

<LLD

<LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 5.19E+06 8.52E+05 4.3 IE+06 7.42E+05 1.00E+01 dilution)

<LLD - Less than the lower limit of detection Radioactive Effluent Releases Page 11

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"

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

Table 3: Radioactive Liquid Effluent Nuclide Composition - Batch QUARTER QUARTER QUARTER QUARTER ANNUAL UNIT 1

2 3

4 TOTAL Tritium Ci 1.59E+01 1.02E+01 1.55E+00 1.06E+01 3.83E+01 Chromium-51 Ci 9.72E-03

<LLD

<LLD 1.42E-04 9.86E-03 Manganese-54 Ci 1.28E-03 1.12E-04

<LLD 8.79E-05 1.48E-03 Iron-55 Ci

<LLD 1.96E-04

<LLD

<LLD 1.96E-04 Iron-59 Ci 5.06E-04

<LLD

<LLD 5.06E-04 Cobalt-58 Ci 2.59E-04

<LLD

<LLD 2.59E-04 Cobalt-60 Ci 7.90E-03 2.17E-03 2.61E-04 2.79E-04 1.06E-02 Zinc-65 Ci

<LLD

<LLD Strontium-92 Ci

<LLD

<LLD Zirconium-95 Ci

<LLD

<LLD Niobium-95 Ci 4.62E-05

<LLD

<LLD 4.62E-05 Technetium-99M Ci

<LLD

<LLD Rhuthenium-105 Ci

<LLD

<LLD Silver-IOm Ci

>LLD

<LLD

<LLD Antimony-124 Ci

<LLD

<LLD 1.58E-05

<LLD 1.58E-05 Antimony-125 Ci

<LLD 5.35E-05 2.37E-04

<LLD 2.9 1E-04 Iodine-131 Ci

<LLD

<LLD Xenon-133 Ci

<LLD

<LLD Cesium-134 Ci

<LLD

<LLD Cesium-137 Ci 1.80E-04

<LLD

<LLD 1.80E-04 Cesium-138 Ci

<LLD

<LLD Lanthanum-140 Ci

<LLD

<LLD Gold-199 Ci

<LLD

<LLD Total for Period Ci 1.59E+01 1.02E+01 1.55E+00 2.57E-04 2.77E+01

<LLD - Less than the lower limit of detection I

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Radioactive Effluent Releases Page 12

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

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

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

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 1.07E+00 O.OOE+00 8.67E-02 1.00E+01

2.

Average Release Rate, pCi/sec O.OOE+00 1.36E-01 O.OOE+00 1.09E-02

3.

Percent of Applicable Limit, %

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

Iodine

1.

Total Iodine-13 1. Released, Ci 1.17E-04 4.20E-05

< LLD 3.88E-05 1.00E+01

2.

Average Release Rate, plCi/sec 1.50E-05 5.34E-06 N/A 4.88E-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

<LLD

< LLD O.OOE+00 O.OOE+00 1.00E+01

2.

-Average Release Rate, pCi/sec

<LLD

< LLD

<LLD

3.

Percent of Applicable Limit, %

N/A N/A N/A N/A D.

Alpha Activity, Ci 1.25E-06 9.07E-07 3.46E-09 1.10E-07 E.

Tritium

1.

Total Released, Ci

< LLD

< LLD 1.00E+01

2.

Average Release Rate, pCi/sec N/A N/A N/A N/A

3.

Percent of ODCM Limit, %

N/A N/A N/A N/A

<LLD - Less than the lower limit of detection N/A - Not Applicable, the ODCM does not have a limitJbr 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 13

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 5: Radioactive Gaseous Effluent Nuclide Composition UNIT QUARTER QUARTER QUARTER QUARTER ANNUAL 1.2 3

4 TOTAL A.

FISSION AND ACTIVATION GASES Tritium Ci

<LLD

<LLD Argon-41 Ci

<LLD

<LLD.

<LLD

<LLD Krypton-85m Ci

<LLD 7.86E-03

<LLD

<LLD 7.86E-03 Krypton-85 Ci

<LLD

<LLD Kryton-87 Ci

<LLD 6.87E-02

<LLD 1.04E-02 7.91 E-02 Krypton-88 Ci

<LLD

<LLD 8.96E-03 8.96E-03 Xenon-131m Ci

<LLD

<LLD Xenon-133m Ci

<LLD

<LLD Xenon-133 Ci

<LLD 1.61E-02

<LLD

<LLD 1.61E-02 Xenon-135m Ci

<LLD 7.22E-02

<LLD

<LLD 7.22E-02 Xenon-135 Ci

<LLD 3.20E-01

<LLD

<LLD 3.20E-01 Xenon-137 Ci

<LLD

<LLD Xenon-138 Ci

<LLD 5.86E-01

<LLD 6.74E-02 6.53E-01 Total for Period Ci

<LLD 1.70E+00

<LLD 8.67E-02 1.16E+00 B.

IODINE Iodine-131 Ci 1.17E-04 4.20E-05

<LLD 3.88E-05 1.98E-04 Iodine-132 Ci

<LLD

<LLD.

<LLD Iodine-133 Ci

<LLD 3.56E-04

<LLD 2.51E-05 3.31E-04 Iodine-134 Ci

<LLD

<LLD Iodine-135 Ci

<LLD

<LLD Total for Period Ci 1.17E-04 3.98E-04

<LLD 6.39E-5 5.79E-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 6.62E-06

<LLD

<LLD 6.62E-06 Strontium-90 Ci

<LLD 1.09E-05

<LLD

<LLD 1.09E-05 Strontium-91 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-139 Ci

<LLD

<LLD Barium-140 Ci

<LLD

<LLD Lanthanum-140 Ci

<LLD

<LLD Total for Period Ci

<LLD 1.75E-05

<LLD

<LLD 1.75E-05

<LLD - Less than the lower limit of detection I

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Radioactive Effluent Releases Page 14

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 2009.

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 5.55E+1 1.02E+2 1/1/2009-12/31/2009

+/-25 bottoms, etc.

Dry compressible waste, contaminated 1.86E+3 7.71E+0 1/1/2009-12/31/2009

+/-25 equipment, etc.

Irradiated components, control rods, etc.

0 0

1/1/2009-12/31/2009

+/- 25 Other (Standby Liquid Control Waste 0

0 1/1/2009-12/31/2009

+/-25 Water)

B.

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

(%)

ERROR, (%)

Spent Resin, Filter Sludge, Evaporator Bottoms, etc.

Mn-54 3.60

+/- 25 Fe-55 59.0 Zn-65 3.10 Co-60 30.5 Cs-137 1.10 Dry Compressible Waste, Contaminated Equipment, etc.

Mn-54 3.90

+/- 25 Fe-55 23.3 Co-60 51.7 Ni-63 1.50 Zn-65 15.7 Cs-137 2.40 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) 14 Public Highway Studsvik, Erwin, TN Solid Waste(2) 34 Public Highway Duratek, Oak Ridge, TN Solid Waste 0

Public Highway Barnwell, Barnwell, S.C.

Irradiated Fuel Shipments 0

N/A N/A NIA -- Not Applicable

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

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

Radioactive Effluent Releases Page 15

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT METEOROLOGICAL DATA 3

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 toweralso 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, 2009 through December 31, 2009, the report substantiates the quality and quantity of meteorological date collected in accordance with applicable regulatory guidance.

DOSE ASSESSMENT I

The maximum concentration for any radioactive release is controlled by the limits set forth in Title 10 of the Code of Federal Regulations, Part 20 (10CFR20). Sampling, analyzing, processing, and monitoring the effluent stream ensures compliance with these concentration limits. Dose limit compliance is verified through periodic dose assessment calculations. Some dose calculations are conservatively performed for a hypothetical individual who is assumed to reside on the site boundary at the highest potential dose location all year. This person, called the "maximum individual", would 3

incur the maximum potential dose from direct exposure (air plus ground plus water), inhalation, and ingestion of water, milk, vegetation, and fish. Because no one actually meets these criteria, the' actual dose received by a real member of the public is significantly less than what is calculated for I

this hypothetical individual.

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

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

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

Table 7: Maximum Individual Site Boundary Dose, Considering All Sectors 3

TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT

% OF (MREM)

LIMIT Liquid Effluent Whole body 1.81E-03 3.OE+00 6.OE-02 Liver 2.48E-03 L.OE+01 2.5E-02 Noble Gas - gamma air N/A 7.36E-03 1.OE+01 7.4E-02

- beta air N/A 4.39E-03 2.OE+01 2.2E-02 Noble Gas Whole body 3.63E-06 5.OE+/-00 7.3E-05 Skin 8.17E-06 1.5E+01 5.4E-05 Particulate & Iodine Thyroid 1.90E-04 1.5E+01 1.3E-03 I

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I Radioactive Effluent Releases Page 16

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

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

Liquid Effluent Whole body 3.4E-01 Thyroid 2.IE-01 Gaseous Effluent Whole body 4.2E-05 Thyroid 8.9E-03 Table 9 provides the calculated hypothetical maximum site boundary dose values considering only the land-based sectors. If any radionuclide was not present at a level greater than the LLD, it was not used in the dose calculations.

Table 9: Maximum Individual Site Boundary Dose, Considering Sectors on Land TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT

% OF (MREM)

LIMIT Liquid Effluent Whole body 3.57E-04 3.OE+00 1.2E-02 Liver 3.61E-04 L.OE+01 3.6E-03 Noble Gas

- gamma air N/A 2.80E-05 1.OE+01 2.8E-04

- beta air N/A 1.87E-05 2.OE+01 9.4E-05 Noble Gas Whole body 4.45E-08 5.OE+00 8.9E-07 Skin 6.20E-08 1.5E+01 4.1E-07 Particulate &Iodine Thyroid 5.33E-05 1.5E+01 3.6E-04 Other dose calculations are performed for a hypothetical individual who is assumed to be inside the site boundary for some specified amount of time. This person would receive the maximum dose during the time spent inside site boundary. Because no one actually meets the criteria established for these conservative calculations, the actual dose received by a real member of the public is significantly less than what is calculated for this hypothetical individual. This dose is assessed relative to the offsite dose, and considers dilution, dispersion, and occupancy factors.

The highest hypothetical dose from liquid effluents to a member of the public inside the site boundary is to a person who is fishing on Lake Erie from the shore on PNPP property. The calculations assume that this person will spend 60 hours6.944444e-4 days 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 5.OOE-04 5.9E-04 Second Quarter 1.30E-04 1.5E-4 Third Quarter

.1OE-05 1.2E-05 Fourth Quarter 1.50E-05 1.7E-05 Annual 6.50E-04 7.7E-04 Radioactive Effluent Releases Page 17

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 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 I

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.

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

(MREM)

First Quarter O.OE+00 O.OE+00 Second Quarter 3.9E-07 8.8E-07 Third Quarter O.OE+00 O.OE+00 Fourth Quarter O.OE+00 O.OE+00 Annual 3.9E-07 8.8E-07 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 (2,420,000 people). The dose from liquid radiological effluents is determined for the population that receives drinking water from intakes within 50 miles of PNPP (1,820,000 people). 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 9.50E-8 1.40E-13 Second Quarter 1.10E-7 1.30E-1 I Third Quarter 2.30E-9 O.OOE+00 Fourth Quarter 2.20E-8 3.90E-12 Annual 1.40E-7 1.70E-I1 ON-SITE GROUNDWATER MONITORING PROGRAM Introduction History In March, 2006, a routine sample of the underdrain system at the Perry plant showed detectable tritium concentration. The underdrains are a porous pipe system which drains groundwater from the foundations of the site buildings. As such, it would not be expected to be a contaminated system. A Condition Report, 06-01477, was submitted, and a Root Cause Investigation was conducted.

Concurrently, a program of groundwater monitoring was initiated.

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

Radioactive Effluent Releases Page 18 I

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

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

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

Underdrain System As mentioned earlier, the underdrain system drains water away from plant foundations. It is separate and distinct from the storm drain system, which is designed purely for rain water control. The underdrain system has a number of installed sump pumps, with the ability to gravity-drain and cascade forward should the pumps fail. There are two major branches of underdrains, one for each of the east and west sides of the power block. These branches ultimately flow into 2 underdrain manholes, designated MH-20 and MH-23, before draining to the suction bay of the Emergency Service Water (ESW) pump house. From there, the water is discharged from the plant. Refer to Figure 2 for locations of Manholes 1 through 23.

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

Manholes 20 and 23 were sampled daily through the middle of 2007, and weekly thereafter through the end of the year. Tritium releases from the station were documented as abnormal releases, and the required dose calculations were completed per the Offsite Dose Calculation Manual (ODCM).

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

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

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

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

Radioactive Effluent Releases Page 19

M MM M

M m

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

Manholes Piezometers o

Groundwater Wells E l

[

mmmmmmmmm mmmm a a e 4p UM Ue U

)t*

m U

Ui

U Ummmmmmmmm

~

m U

U U

a_

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Radioactive Effluent Releases Page 20

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

Selected plant piezometers are also sampled.

The samples are analyzed for shipping purposes, and are then shipped to Midwest Laboratories in Illinois. Midwest analyzes the sample for gamma isotopic and tritium. On alternate samples, Perry has also requested analysis of "hard-to-detect" isotopes such as Sr-89/90, Ni-63 and Fe-55. Starting in 2010 the NRC will require additional testing for C-14.

Sample Analysis The May 2009 sample set for the 12 installed monitoring wells showed gamma isotopic activity

<LLD and tritium activity was barely over the LLD for one well site at 261 pCi/liter. The November 2009 sample set showed gamma activity <LLD and tritium activity was barely over the LLD for one well site at 313 pCi/liter. Analyses for the hard-to-detect nuclides were negative, all less than LLD.

Two samples (4A and 4B) for the November 2009 collection were lost in transit. Condition report

10-75950 was generated for documentation purposes.

Significant Items A fleet level procedure was implemented for notifications in the event that detectable tritium reaches 10% of the EPA-mandated trigger level of 20,000 pCi/liter. This formalized the protocol for any groundwater contamination issues.

A fleet self-assessment was conducted to verify alignment with NEI 07-07, the Groundwater Protection Initiative. There were minor items noted, but no substantial shortfalls in compliance with the NEI document.

Table 13: Summary of Onsite Groundwater Samples H-3 H-3 H-3 TYPICAL REQUIRED PRE-H-3 ANALYSES >

NEI EPA MAX.

MIN.

AVG.

H-3 H-3 LLD OPERATIONAL PRE-AND REPORTING (PCI/L)

(PCI/L)

LLD (PCi/L)

(DEVELOPED)

OPERATIONAL FENOC LEVEL FOR (PCI/L)

MEAN FOR H-3 MEAN FOR H-3?

LEVEL H-3 (PCI/L)

FOR H-3 (PCI/L)

(PCi/L)

First Half 261 N/A N/A

< 200

< 2000 400 No 2000 20000 2009 Second Half 313 N/A N/A

< 200

< 2000 400 No 2000 20000 2009 ABNORMAL RELEASES There was one abnormal radioactive release events during 2009. On March 10, 2009 chemistry sampled Emergency Service Water A from the hose connected to the drain of the Residual Heat Removal A heat exchanger (ESW side). When the test for tritium was complete results showed a tritium level of 4.14e-6 uCi/ml. Normal tritium activity in ESW is less than detectable. Back up Radiological Environmental Monitoring Page 21

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT sample from the same sample point but without the hose connected showed tritium results of 4.02e-6 uCi/ml. Chemistry Supervision, Operations Control Center Shift Outage Director, and Operations Shift Manager were informed. Chemistry was instructed to sample ESW Forebay (8.78E-07 uCi/ml),

Underdrain Manholes 20 (2.66E-06 uCi/ml) and 23 (1.26E-06 uCi/ml) which all had detectable' levels of Tritium. The ESW A system is to be drained to the Plant Discharge Tunnel (Normal effluent release path) and will be treated as an abnormal release and processed in accordance with chemistry effluents program to account for Doses to the Public. The out of spec tritium is believed to be from multiple Radwaste releases that occurred during Refuel Outage 12 February-May. Based on the flow, this would have equated to a release of 2.04E-01 curies.

NON-COMPLIANCES There were six non-compliances to the ODCM Controls requirements in 2009.

The Emergency Service Water Radiation Monitor was inoperable greater than 30 days. Total days inoperable (31) days.

The Emergency Service Water B Radiation Monitor, (1D17-K605) was declared inoperable on 1/26/09 due to planned maintenance. Following maintenance, the monitor failed downscale.

Troubleshooting performed by Fix It Now/ Maintenance team and reworked. The instrument was returned to service on 2/26/2009.

The Liquid Radwaste to Emergency Service Water Discharge Radiation Monitor was inoperable greater than 30 days. Total days inoperable (121) days.

The Liquid Radwaste to Emergency Service Water Discharge Radiation Monitor, (0D 17-K606) was declared inoperable on 3/2/09 due to spiking. Notification given a low priority due to competing priorities. The instrument was returned to service on 7/1/2009.

3 The Liquid Radwaste High Flow Discharge Header Flow Monitor was inoperable greater than 30 days. Total days inoperable (69) days.

The Liquid Radwaste High Flow Discharge Header Flow Monitor, (0G50-K466) was declared inoperable on 4/3/09 due to erratic readings. Previously identified problem of inaccurate and calibration deficiencies on the 0G50R087 recorder combined with failing total flow readings I

contributed to erroneous data being entered on the Liquid Radwaste Discharge SVI. Calibrations of both instruments needed prior to any future Radwaste discharges. Calibration and verification performed. The instrument was returned to service on 6/11/2009.

1 The Turbine Building Radiation Monitor Noble Gas Channel was inoperable greater than 30 days. Total days inoperable (31) days.

The Turbine Building Radiation Monitor Noble Gas Channel declared inoperable on 4/10/09 due to the alarm and alert lights not working during the performance of SVI-D17-T8000D. Returned to service and verified on 5/10/09, and the noble gas channel was declared operable on 5/11/09.

The Emergency Service Water B Radiation Monitor was inoperable greater than 30 days.

Total days inoperable (38) days.

The Emergency Service Water B Radiation Monitor, (1D17-K605) was declared inoperable on 3

4/12/09 due to spurious low flow alarms. Maintenance team replaced the annunciator card for the channel. The instrument was returned to service on 5/20/2009.

I Radiological Environmental Monitoring Page 22t

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT OFFSITE DOSE CALCULATION MANUAL CHANGES During this reporting period, there were no (0) changes to the Offsite Dose Calculation Manual.

PROCESS CONTROL PROGRAM CHANGES During this reporting period, there were no (0) changes to the Process Control Program.

Radiological Environmental Monitoring Page 23

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

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

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

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

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

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

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

Radiological Environmental Monitoring Page 24

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

)

LOCATION #

DESCRIPTION MILES DIRECTION MEDIA( 2)

I Chapel Road 3.4 ENE TLD, AlP 2

Kanda Garden 1.9 ENE Food Products 3

Meteorological Tower 1.0 SE TLD, AIP 4

Site Boundary 0.7 S

TLD, AIP 5

Quincy Substation 0.6 SW TLD, AIP 6

Concord Service Center 11.0 SSW TLD, AIP 7

Site Boundary 0.6 NE TLD, AIP 8

Site Boundary 0.8 E

TLD 9

Site Boundary 0.7 ESE TLD 10 Site Boundary 0.8 SSE TLD 11 Parmly Rd.

0.6 SSW TLD 12 Site Boundary 0.6 WSW TLD 13 Madison-on-the-Lake.

4.7 ENE TLD 14 Hubbard Rd.

4.9 E

TLD 15 Eagle St. Substation 5.1 ESE TLD 16 Eubank Garden.

0.8 S

Food Products 18 Kijauskas Farm 2.5 E

Food Products, Milk 20 Rainbow Farms 1.9 E

Food Products 21 Hardy Rd.

5.1 WSW TLD 23 High St. Substation 7.9 WSW TLD 24 St. Clair Ave.

15.1 SW TLD 25 Offshore - PNPP discharge 0.6 NNW Sediment, Fish 26 Offshore - Redbird 4.2 ENE Sediment 27 Offshore - Fairport Harbor 7!9 WSW Sediment 28 CEI Ashtabula Plant Intake 22.0

'-ENE, Water 29 River Rd.

4.3 SSE TLD 30 Lane Rd.

4.8 SSW TLD 31 Wood and River Rd.

4.8 SE TLD 32 Offshore - Mentor 15.8 WSW Sediment, Fish 33 River Rd.

4.5 S

TLD 34 PNPP Intake 0.7 NW Water 35 Site Boundary 0.6 E

TLD, AIP 36 Lake County Water Plant 3.9 WSW TLD, Water 37 Gerlica Farm 1.5 ENE Food Products 41 Tuttle Farm (goat) 5.8 SSE Milk 51 Rettger Milk Farm (cow) 9.6 S

Milk 53 Neff Perkins 0.5 WSW TLD 54 Hale Rd. School 4.6 SW TLD 55 Center Rd.

2.5 S

TLD 56 Madison High School 4.0 ESE TLD 58 Antioch Rd.

0.8 ENE TLD 59 Lake Shoreline at Green Rd.

4.0 ENE Water 60 Lake Shoreline at Perry Park 1.0 WSW Water 61 Keller Milk Farm (goat) 7.4 SE Milk 63 Minor Stream Mouth 0.08 NNE Sediment 64 Northwest Drain Mouth 0.09 NW Sediment 65 Major Stream Mouth 0.18 W

Sediment 70 H&H Farm Stand 16.2 SSW Food Products (1) chronologically missing location numbers denote deleted or retired sampling locations.

(2)

AlP = Air, Iodine and Particulate TLD = Thermoluminescent Dosimeter I

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Radiological Environmental Monitoring Page 25

ANNUAL ENVIRONMENTAL 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 SSW S

SSE 1

0 1

2 MILES Radiological Environmental Monitoring Page 26

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 27

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

0 5

10 15 20 MILES IN E E 0 E

ý10 Radiological Environmental Monitoring Page 28

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

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

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

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

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

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

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

As the TLD is heated, the phosphor releases the stored energy as light. The amount of light is directly proportional to the amount of radiation to which the TLD was exposed. The reading process also zeroes the TLD and prepares it for reuse. Table 15 provides a list of the analyses performed on environmental samples collected for the PNPP REMP in 2009.

Sample results are often reported as less than the lower limit of detection (< LLD), which is defined as the smallest amount of radioactive material that will show a positive result for which there can be confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample analysis. When a measurement is reported as < LLD, it means that no radioactivity was detected at a value above, or equal to the appropriate ODCM table value. The NRC has established LLD values for REMP sample analyses. The vendor laboratory for REMP sample analyses complied with those values in 2009.

Radiological Environmental Monitoring Page 29

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 15: REMP Sample Analyses 3

TYPE SAMPLE FREQUENCY ANALYSIS Atmospheric Monitoring Airborne Particulates Weekly &

Gross Beta Activity &

AoshrcMntrn AibrePriuae 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 t

MGross Beta Activity &

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

Gamma Dose Annually 2009 SAMPLING PROGRAM The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the 2009 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, 2009 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 2009.

Program Changes The 2008 Land Use Census identified a new milking animal (goat) location within 3 miles of PNPP.

The Kijauskas Farm (location #18) began participation in the REMP in 2009. The first milk samples were provided in April 2009. Additionally, the farm also agreed to participate in the REMP Food Products (Garden) program, providing their first food product samples in August 2009.

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

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

Shoreline sediment samples are collected with spoon and container. On occasion, the accessibility of these locations and sample collection may be impacted due to high lake levels, shifting lake bottom sediment, bluff erosion and shoreline collapse. For 2009, there was no impact to the program requirements as a result of any missed samples. Table 16 provides information on samples missed during 2009.

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I Radiological Environmental Monitoring Page 30

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 16: Missed REMP Samples in 2009 MEDIA LOCATION.

DATE REASON Air Samples N/A N/A N/A Food Products All Jan.-June, Dec. 2009 Insufficient growth/temperature. Die-off/Frost damage.

18,20,70 July Insufficient growth.

16 Nov.

Die-off/Frost damage Lake Water 59, 60 Jan., Feb., Dec. 2009 Sample unavailable due to frozen shoreline Milk

.18 Jan., Feb., March 2009 Not participating at this time.

41 Jan., Feb., Mar., Oct.; Nov.,

Drying period for goats/sample availability Dec. 2009 61 Jan., Feb., Mar., Apr., Nov.,

Drying period for goats/sample availability Dec. 2009 Sediment 63 June and September 2009 Location inaccessible 65 June 2009 Shoreline under water. Location inaccessible TLDs 7

3id quarter 2009 Annual TLD collected by mistake. Not ODCM required. CR 09-66741 Atmospheric Monitoring Air Air sampling is conducted to detect any increase in the concentration of airborne radionuclides. The PNPP REMP maintains an additional 2 air sampling locations above the five locations (four indicators and one control) required by the ODCM. Six (6) of these locations are within four miles of the plant site; the seventh is used as a control location and is eleven miles from PNPP. Air sampling pumps are used to draw continuous samples at a rate of approximately two cubic feet per minute. The air is drawn through glass fiber filters (to collect particulate material) and a charcoal cartridge (to adsorb iodine). The samples are collected on a weekly basis, 52 weeks a year, from each of the seven air sampling stations.

On occasion, air sample locations can experience power losses associated with storms and/or malfunctioning equipment. On 10/26/09, ODCM location #35 was found not running during the weekly sample collection. It was determined that the sample location had lost power due to a breaker issue on a nearby utility pole. Power was restored and the sample location returned to service the same day. The amount of continuous run time provided adequate sample for laboratory analysis, resulting in no loss of sample. Condition report 09-57750 was generated for documentation purposes.

Air samples are analyzed weekly for gross beta activity and radioiodine activity. The air samples are also analyzed by gamma, spectral analysis quarterly. A total of 364 air particulate and 364 air radioiodine samples were collected and analyzed in 2009.

Gross beta activity was detected in 363 of 364 air samples and ranged up to 0.04 pCi/m3. The average gross beta activity at both indicator and control locations was 0.02 pCi/mi3 for 2009. 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 2009 and the previous years.

Radiological Environmental Monitoring Page 31

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

Figure 6: Annual Average Gross Beta Activity, in Air 0.05

0. 04 0.03 0.01 0

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0 0 0 Year 0 Indicator EControl 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 2009, the PNPP REMP included four (4) milk locations located 2.5, 5.8, 7.4 and 9.6 miles away from the plant. The Kijauskas Farm, (location #18, 2.5 miles in the East sector) began participation in April 2009 after being identified during the 2008 Land Use Census.

Since the milk sampling locations do not meet the requirements of the ODCM (no milk-producing animals located within the required areas), food product sampling (discussed below) is performed.

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

Milk samples are analyzed by gamma spectral analysis for radioiodines and other radionuclides. A total of fifty-nine (59) milk samples were collected in 2009. Iodine was not detected in any of the samples above the LLD of 0.75 pCi/ L. The concentrations of all radionuclides, except naturally occurring potassium-40, were below LLDs in all samples collected.

Food Products Food products can provide a direct pathway to humans by ingestion. They can absorb radionuclides from atmospheric deposition on soil or from irrigation water drawn from a lake or pond receiving airborne or liquid effluents. Also, radionuclides in the soil may be absorbed by the roots of the plants and become incorporated into the edible portions. Because there is not a sufficient number of Radiological Environmental Monitoring Page 32

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT dependable milk sampling locations, the PNPP REMP is required to include two food product indicator locations and one control location. Food products are collected monthly during the growing season from six (6) gardens in the vicinity of PNPP. Location #18, Kijauskas Farm became the sixth (6) participant in August 2009. The control location for food products is 16.2 miles SSW from PNPP.

A total of sixty-six (66) food product samples were collected and analyzed by gamma spectral analysis in 2009. Limiting factors for the 2009 growing season included unseasonable temperatures and an early drought followed by excessive rain accounting for the missed samples referenced in Table 16.

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

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

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

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

Fifty-four (54) water samples were collected and analyzed for gross beta activity and gamma spectral analysis in 2009. From these monthly samples, twenty (20) quarterly composite samples were obtained and analyzed for tritium activity.

Gross beta activity was detected in two (2) of the fifty-four (54) samples collected. For 2009, the detectable gross beta activity was 3.14 pCi/L vs. the lab LLD value of 3.00 pCi/L. Refer to Figure 7 for the annual average gross beta activity for both indicator and control locations. The significant difference between the pre-1988 data and post-1988 data has been attributed to a change in vendor laboratories in 1987/1988. A comprehensive explanation for the observed difference is provided in the 1988 Annual Environmental Operating Report.

Radiological Environmental Monitoring Page 33

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

12 10 5

8 4

i 0

N4 M)

CO (D W

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0 M Cto CO 1-WO C 0 0

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Year 0 Indicator 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 twenty (20) samples analyzed. These results are well within the range of those measured in previous years, which have ranged from below the LLD to 2,200 pCi/L. Refer to Table 16 for an explanation of any missed samples.

Sediment Sampling of lake bottom sediments can provide an indication of the accumulation of particulate radionuclides which may lead to internal exposure to humans through the ingestion of fish, the re-suspension into drinking water, or as an external radiation source to fishermen and swimmers from shoreline exposure. Although the PNPP ODCM requires only one location, sediment is sampled twice each year from seven (7) locations. Two (2) of the sampling locations are also fish sampling locations. Sediment samples from offshore are collected using a hand dredge. Shoreline samples are collected using a scoop. Eleven (11) sediment samples were collected in 2009 and analyzed by gamma spectroscopy. Beginning in 2006, access to sample location 63 was lost due to shoreline erosion which resulted in a bluff collapse. Lack of safe access continues to prevent sample collection at location #63. The predominant radionuclide detected by gamma spectral analysis was naturally-occurring potassium-40. Potassium-40 has been detected in all samples, since the program began in 1981.

Cesium-137 activity was detected in four (4) of the eleven (11) samples collected and ranged from 301.33 pCi/kg to 699.30 pCi/kg. The annual average cesium-137 activity was 321.37 pCi/kg for the i

indicator locations and 689.11 pCi/kg at the control location. The average cesium-137 radioactivity for all locations was 505.24 pCi/kg and is within the maximum value of 864 pCi/kg established in 1981. Year-to-year variations in lake bottom sediment sample activity is expected and beyond the control of PNPP. For example, cesium-137 activity variations (refer to Figure 8) in the control locations from year-to-year may be contributed to:

1. The movement of sediment on the lake bottom due to wave action and currents.

2.

Difficulty in duplicating exact location and composition of bottom sediment sample from year to year even with assistance of GPS.

Radiological Environmental Monitoring Page 34

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 8: Annual Average Cesium-137 Concentration in Sediment C.)

0.

U 1600 1400 1200 1000 800 600 400 200 0

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3 Indicator 1Control In 1999, a sediment sample from location #64 (shoreline discharge point of the Northwest Drain Impoundment) was found to contain trace levels of cobalt-60. Ten (10) additional sample locations were established upstream from location #64 and within the Impoundment to identify the boundary of the cobalt-60 activity and to support supplemental monitoring activities. In recent years, the shoreline adjacent to the impoundment has experienced extensive bluff erosion and collapse, preventing access and sample collection for locations 64-4 and 64-5. For 2009, sample results for cobalt-60 from the eight (8) remaining locations confirm that no activity was identified at the discharge point (Location

64), and continues to remain within the Northwest Drain Impoundment with an activity range of <7 pCi/kg to 251 +/- 77 pCi/kg (Refer to Table 17). Additionally, Table 18 reflects Cesium-137 activity within the impoundment sediment for informational purposes.

Table 17: Northwest Drain Impoundment Cobalt-60 Activity, pCi/kg (dry)

LOCATION 06/18/09 06/29/09 9/16/09 10/13/09 64

<17

<8.7 64-1

<7

<12 64-2

<22

<18 64-3

<24

<24 64-4 64-5 64-6

<70 111 +/-38 64-7 118+/-33 251+/-77 64-8

<21 30+/- 14 64-9 210+/-77

<51 64-10 138+/-39 236+/-56 No sample available or insufficient sample.jbr analysis No sample collected on this date Radiological Environmental Monitoring Page 35

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 18: Northwest Drain Impoundment Cesium-137 Activity, pCi/kg (dry)

LOCATION 06/18/09 06/29/09 09/16/09 10/13/09

'64

<14.7

<11.4 64-1

<19 44+/- 18 64-2 494+/-46 416+/-36 64-3 71 +/-.42 145 +/-32 64-4 64-5 64-6 1638 +/- 135 2029 +/- 95 64-7 2630+/-98

.1581 +/- 137 64-8 586+/-48 776+/-34 64-9 1511 +/- 103 1478+/-100 64-10 1912+/-83 2194+/- 140 No sample available or insujficientsamplefor analysis No sample collected on this date Fish Fish are analyzed primarily to quantify the dietary radionuclide inftakeby 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 2009, fish sampling was performed for PNPP by a local licensed sport fisherman.

Eight (8) fish samples (yellow perch, white perch, white bass and walleye) were collected and analyzed by gamma spectral analysis in 2009. As expected, naturally occurring potassium-40 was found in all samples. No other radionuclides were detected above the LLD.

Direct Radiation Monitoring Thermoluminescent Dosimeter (TLD)

Environmental radiation is measured directly at twenty-eight locations around the PNPP site, two of which are control locations. The locations are positioned in two rings around the plant as well as at the site boundary. The inner ring is within a one-mile radius of the plant site; the outer ring is four 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 253 TLDs were collected and analyzed in 2009. This includes 224 collected on a quarterly basis and twenty-seven (27) of twenty-eight (28) collected annually. During the 3rd quarter 2009 collection, annual TLD for location #7 was inadvertently collected and sent for analysis. Annual TLDs are not required per the ODCM and are used for supplemental data only. Condition report 09-66741 was generated for documentation purposes.

Radiological Environmental Monitoring Page 36

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT For 2009, the annual average dose for all indicator locations was 54.03 mrem, and 50.20 mrem for the control locations. The indicator annual average dose is believed to be influenced by location #36 (Figure 4) which has been consistently higher in dose than TLDs positioned closer to the plant (Figure 3). Referring to Figure 9, the average quarterly dose for all indicator locations was 12.82 mrem, and 12.27 mrem for all control locations. Please refer to Appendix B, 2009 REMP Detailed Data Report for all TLD results. Prior to 1988, the TLD results were higher due to a change in the vendor laboratory services. A comprehensive explanation of this difference was provided in the 1988 Annual Environmental Operating Report.

Figure 9: Average Quarterly TLD Dose E

0) 0)

25 20 15 10 5

0 "o

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CD C-WM 01 00 00 Wo Wo Wo Wo Wo M M

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0 Year 01lndica tor EControl Conclusion Sediment samples continue to confirm cobalt-60 in the northwest drain impoundment. Additional monitoring is being performed to monitor this location. An environmental evaluation determined that there would be less impact upon the environment by leaving this material in place. Atmospheric monitoring results were consistent with past results. The prevalent radionuclide in air was beryllium-7, which is naturally occurring. Naturally occurring potassium-40 was detected in all terrestrial samples, as expected.

Finally, direct radiation measurements are consistent with past data.

Radiological Environmental Monitoring Page 37

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

laboratories that performed environmental measurement participate in the EPA's Environmental Radioactivity Laboratory Inter-Comparison Studies -Program, or an equivalent program.

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

I 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 I

monitors the quality of their analyses by:

Analyzing "spiked" samples (samples with a specific quantity of radioactive material present in them) and I

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

Through 2004, Teledyne also participated in the Environmental Measurements Laboratory Quality I

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

Conclusion Appendix A, 2009 Inter-Laboratory Cross-Check Comparison Program Results, includes results from both'the above referenced programs and the ERA Company cross-check program.

1) Table A-i, Environmental Resource Associates (ERA) Interlaboratory Comparison Crosscheck Program:I o

The vendor laboratory Cs-137 analysis results for water sample STW-1182 failed initially due to a deformed base of the Marinelli beaker. A new beaker (sitting directly on the detector) obtained the desired results within control limits.

Initial analysis of H-3 insample STW-1 186 failed. A reanlysis of the sample was performed I

and found to be within control limits.

2)

Table A-2, Vendor Laboratory's Cross-Check testing of Thermoluminescent Dosimetry were found to be within the expected control limits.

I

3)

Laboratory analysis results for Table A-3, In-House "Spike" Samples were within their expected control limits.

I

4) Analysis results for Table A-4, In-House "Blank" Samples were within their activity limits.

5)

Table A-5, In-House "Duplicate" Samples were within their averaged results.

I Radiological Environmental Monitoring Page 38n

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT

6) Table A-6, Department of Energy MAPEP:

o Vendor laboratory Am-241 analysis for water sample STW-1 170 initially failed. There was insufficient sample for reanalysis and no procedure or calculation errors were identified.

o Acceptable results for Am-241 in water are included in the second round of testing (sample STW-1192) and ERA studies Tables A-7.

0o Initial Am-241 results for air sample STAP-1174 failed. One determination was eliminated due to poor recovery. The average of three determinations was within the control limits.

o The analysis for Stontium 90 in air sample STAP-1174 initially failed high. No reason could be determined. Reanalysis was within the control limits.

o The initial failure of Sr-90 analysis in soil sample STSO-1188 was due to the possible incomplete separation of strontium from calcium. 'Analysis Was repeated and the results within the control limits.

7)

The vendor laboratory results for Table A-7, Interlaboratory Comparison Crosscheck Program Environmental Resource Associates (ERA) laboratory were all within their control limits.

Radiological Environmental Monitoring Page 39

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 2009 Land Use Census, Which was conducted August 10th and 11th 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 availabl e milking animals within a five mile radius of PNPP to support.the Radiological Environmental Monitoring Program (REMP). The 2009 Land Use Survey used the 1999 survey map produced by the Commercial Survey Co. of Cleveland. GPS units are also used for more accurate location identification.

Table.19 identifies the nearest residences, by sector, to the PNPP. The table is updated annually to reflect any changes identified during the annual Land Use Census. For 2009, there were no changes noted for the "nearest residence".

Table 19: Nearest Residence, By Sector SECTOR LOCATION ADDRESS MILES FROM X/Q VALUE, MAP LOCATOR PNPP (SEC/M3)

NUMBER NE 4384 Lockwood 0.7 2.66E-06 1

ENE 4412 Lockwood 0.7 1.96E-06 2

E 2626 Antioch 1.1

6.77E-07 3

ESE 2836 Antioch 1.0

'8.57E-07 4

SE 4537 North Ridge 1.3 3.44E-07 5

SSE 4225 Redmill Valley Rd.

1.1 5.52E-06 6

S, 3119 Parmly 0.9 2.25E-06 7

SSW 3121 Center 1.0 9.49E-07.

8 SW 3440 Clark 1.3 4.42E-07' 9

WSW 3462 Parirmly 1.1.

8.67E-07 10 I

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Radiological Environmental Monitoring Page 40 I

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 10: Land Use Census Map Radiological Environmental Monitoring Page 41

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 20 identifies the nearest milking animal by sector, to the PNPP. The milking animal identified during the 2008 census began program participation in April of 2009. During the 2009 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.

2.51 21 There was one (1) change in the nearest garden for the WSW sector during this year's census.

Changes can include either the loss of the previous year's garden or the addition of a new garden identified in this year's census. The garden nearest the plant in the WSW sector returned for 2009.

Table 21 lists the nearest gardens occupying at least 500 square feet identified during the 2009 Land Use Census.

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

NUMBER NE 2330 Lakehurst 0.9 8.9 1E-09 11 ENE 4630 Lockwood 1.1 4.77E-09 12 E

2626 Antioch 1.1 5.29E-09 3

ESE 2836 Antioch 1.0 3.96E-09 4

SE 3040 Antioch 1.3 1.01E-09 15 SSE 3288 Call Rd.

1.4 2.04E-09 16 S

3964 North Ridge 1.4 2.73E-09 17 SSW 3121 Center 1.0 4.66E-09 8

SW 3440 Clark 1.3 1.95E-09 9

WSW 2975 Perry Park 1.3 2.31E-09 20 Radiological Environmental Monitoring Page 42

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 2009 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 2009, 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.

Clam/Mussel Monitoring Page 43

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 22: 2009 Corbicula Monitoring DATE SAMPLE LOCATION 2/28/09 Low pressure condenser water boxes 3/1/09 Intermediate pressure condenser water boxes 3/2/09 Auxiliary condenser 'A' 3/3/09 Emergency Service Water valve P45-F572 3/3/09 Auxiliary condenser 'B' 3/4/09 Emergency Service Water 'B' discharge pipe 3/5/09 High pressure condenser water boxes 3/26/09 Emergency Service Water 'C' discharge strainer 3/26/09 Division I Emergency diesel generator jacket water heat exchanger 3/27/09 Emergency Service Water 'A' coupon assembly 3/28/09 Emergency Service Water 'A' strainer 7/30/09 Main Turbine Lube Oil cooler 'B' 8/18/09 Charcoal filter intake strainer 0P54-D0742 8/19/09 Main Turbine Lube Oil cooler 'A' 9/23/09 Fire protection system piping in building RW 602' 9/25/09 Main Turbine Lube oil coolers 10/5/09 Fire Protection system valve 0P54-F0521 10/5/09 Fire Protection system valve 0P54-F0520 10/5/09 Fire Protection system valve 0P54-F0518 10/26/09 Fire Protection system piping 12/10/09 Service Water 'A' strainer 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 2009 monitoring program did not identify Corbicula in any sample collected.

Clam/Mussel Monitoring Page 44 I

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

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

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

Treatment Chemicals used for mussel control in 2009 included chlorine and a commercial molluscicide. The chlorine is intermittently injected into the plant service water, emergency service water, and circulating water systems by metering sodium hypochlorite into each system's influent. Sodium bisulfite is added at the plant discharge structure for dechlorination prior to return into Lake Erie.

The use of a commercial molluscicide has been approved by the Ohio Environmental Protection Agency (OEPA). The chemical selected for use at the PNPP in 2009 was alkyl-dimethyl-benzyl-ammonium chloride. Treatment was applied twice in 2009, on June 2 and September 10. The active ingredients were detoxified by adsorption using bentonite clay, prior to discharge into Lake Erie.

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

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

The effectiveness of the application of the commercial molluscicide was measured by observing mortality of mussels placed in a flow-through container placed in plant service water and subjected to the chemical treatment. The observed mortality rate utilizing the flow-through container for 2009 was 50% and 99.5% respectively. It is believed that the disparity between the Spring and Fall mortality rates were the result of initial colder water temperatures in the Spring and a bias in the use of larger and more mature Zebra mussels for mortality determination. The larger and more mature mussels have the ability to detect chemical changes in the water and hold their breath longer to avoid the effects of chemical treatment. Condition report 09-60254 was generated for documentation purposes.

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

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

Clam/Mussel Monitoring Page 45

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

In 2009, three (3) general and one (1) specific herbicide requests were initiated for chemical applications. Each application was in compliance with the Ohio Environmental Protection Agency's rules and regulations. There were no adverse environmental impacts observed during weekly site environmental inspections as a result of these applications. The herbicides approved for use in the Owner-Controlled Area are Round-Up, Spyder, Karmex, Pramitol, Polaris, Tempo Ultra, and Oust.

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 2009. The quantity represents the amount of herbicide applied, prior to any dilution.

Herbicide Applications Page 46 I

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 23: 2009 Herbicide Applications DATE LOCATION AMOUNT CHEMICAL APPLIED

'_LOCATIONAMOUNTNAME 4/28/09 Admin., Training buildings and long main roads 12.0 oz Round-up 5/6/09 Admin., IPC, P&R Buildings 15.0 oz Round-up 5/12/09 Protected area landscape beds/gravel areas 12.0 oz Round-up 5/15/09 Transmission Yard 684.7 oz Polaris 5/15/09 Transmission Yard 24.3 oz Spyder 5/19/09 Admin. and Training buildings. OCA fence line.

51.0 oz Round-up 5/26/09 Protected area landscape beds/gravel areas 18.0 oz Round-up 5/27/09 Admin., Training, WHSE, IPC Buildings 54.0 oz Round-up 5/28/09 OCA perimeter, Admin. building, and contractor parking lot 300.0 oz Round-up 6/4/09 Admin., Training, WHSE, IPC, P&R Buildings and Hydrogen/gravel 240.0 oz Round-up area 6/5/09 Fire training grounds, contractor park lot, and firing range 300.0 oz Round-up 6/9/09 Security towers, booths and perifeld zones 50 gins Tempo Ultra 6/11/09 Transformer Yard 330.0 oz Round-up 6/16/09 OCA environmental pathways 9.0 oz Round-up 6/26/09 Protected area perimeter and transformer yard 2760.0 oz Round-up 6/29/09 North end of OCA 237.0 oz Round-up 6/30/09 Training building 24.0 oz Round-up 7/13/09 Admin., IPC, Training Buildings 300.0 oz Round-up 7/14/09 WHSE building and contractor parking lot 12.0 oz Round-up 7/21/09 Waste accumulation facility 90.0 oz Round-up 7/27/09 Hydrogen/Gravel Area and Admin. building 600.0 oz Round-up 8/6/09 Gravel areas on East and North side of plant 300.0 oz Round-up 8/11/09 OCA perimeter and Training building 27.0 oz Round-up 8/18/09 Transformer alleyway 90.0 oz Round-up 8/25/09 Admin., Training, and IPC Buildings 30.0 oz Round-up 9/1/09 General Protected area 18.0 oz Round-up 9/2/09 Security towers, booths and perifeld zones 25 gins Tempo Ultra 9/4/09 Protected area NE, NW, SE, SW quadrants 450.0 oz Round-up 9/9/09 Admin., Training, and 1PC Buildings 21.0 oz Round-up Herbicide Applications Page 47

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

One special report was submitted for 2009:

On October 09, 2009, the Perry Plant reported a non-compliance to the Ohio EPA due to a spill of approximately 3-5gallons of hydraulic fluid that entered two storm drains and caused an oil sheen in the Minor steam impoundment. The spill was promptly cleaned up and all proper notifications were made.

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

One special report was submitted for 2009:

0 On October 09, 2009, the Perry Plant reported a non-compliance to the NRC due to a spill of approximately 3-5gallons of hydraulic fluid that entered two storm drains and caused an oil sheen in the Minor steam impoundment. The spill was promptly cleaned up and all proper notifications were made.

UNREVIEWED ENVIRONMENTAL QUESTIONS All proposed changes to the PNPP design or operation, as well as tests or experiments, must be evaluated for potential environmental impacts in accordance with the EPP and administrative quality assurance procedures. In 2009 there were no proposed changes to the facility or programs that if performed, could have resulted in an adverse environmental impact. Therefore, there were no unreviewed environmental questions identified.

Special Reports Page 48 I

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX A 2009 INTER-LABORATORY CROSS CHECK COMPARISON PROGRAM RESULTS

Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

Northbrook, IL 60062-2310 ph. (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, 2009 through December, 2009

l Appendix A n

Interlaboratory Comparison Program Results 3

Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck)

I 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 I

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 3

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.

I 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 ayailable 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.

3 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.

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

Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria i

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

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

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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/liter or kg

< 20 pCi/liter

> 20 pCi/liter

-< 100 pCi/liter

.> 100 pCi/liter Tritium 5 4,000 pCi/liter

> 4,000 pCi/liter

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

> 0.1 pCi/liter, gram, or sample Iodine-131, Iodine-1 2 9 b Uranium-238, Nickel-63b Technetium-99b 5 55 pCi/liter

> 55 pCi/liter

~~35 pCi/liter Iron-55b 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.~~

A2

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

~~tConcentration (pCi/L)~~

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 181 STW-1 181 STW-1 182 STW-1 182 STW-1 182 STW-1182 a STW-1182 STW-1 183 STW-1 183 STW-1 184 STW-1185 STW-1 185 STW-1 185 STW-1186 STW-1193 STW-1 193 STW-1 194 STW-194 STW-194 STW-1194 STW-1 194 STW-1 195 STW-1 195 STW-1196 STW-1197 STW-1 197 STW-1197 STW-1 198 04/06/09 04/06/09 04/06/09 04/06/09 04/06109 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 41.0 +/- 5.8 32.4 +/- 2.4 44.6 +/- 3.1 81.0 +/- 3.1 65.6 +/- 5.2 147.7 +/- 5.3 79.8+/- 7.5 47.6 +/-2.1 38.5 +/- 1.3 24.4 +/- 2.5 14.0 +/- 0.7 14.3 +/- 2.1 25.0 +/- 0.2 22819.0 +/- 453.0 48.3 31.4 52.7 88.9 72.9 168.0 84.4 54.2 43.5 26.1 15.1 13.6 25.7 37.8 - 55.7 22.9 - 36.4 43.4 - 58.3 80.0 - 100.0 59.5 - 80.2 151.0 - 187.0 76.0 -101.0 28.3 - 67.7 29.1 - 50.8 21.7 -30.8 11.2-17.3 9.0 - 16.6 20.6 - 28.8 Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Fail 20300.0 17800.0.- 22300.0 53.0 31.1 82.5 116.8 78.8 54.2 102.5 20.3 23.7 22.4 15.0 17.4 32.5

~~+/- 6.0~~

~~+/- 2.2~~

~~+/- 3.5~~

~~+/- 3.3~~

~~+/-5.7~~

~~+/- 3.7~~

~~+/-6.2~~

~~+/- 2.0~~

~~+/- 1.4~~

~~+/- 0.7~~

~~+/- 2.0~~

+/- 0.4 62.2 30.7 92.9 117.0 78.8 54.6 99.5 23.2 26.0 22.2 13.9 14.9 33.8 16400.0 50.2 - 70.1 22.4 - 35.6 78.3 - 102.0 105.0 - 131.0 65.0 - 87.3 49.1 -62.9 89.6-119.0 11.6 -31.1 16.2 - 33.9 18.4 -26.5 10.4-16.0 10.0 - 18.0.

~~27.3 - 37.8 14300.0.- 18000.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass U~~

~~I I~~

~~i I~~

~~U I~~

~~I I~~

~~I i~~

~~I I~~

I 17228.0 +/- 694.0 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.~~

All gamma -emitters showed a low bias. A large plastic burr found on the base of the Marinelli kept the beaker from sitting directly on the detector. Result of recount in a different beaker, Cs-1 37, 155.33 +/- 14.55 pCi/L.

~~e Samples were recounted and also reanalyzed. A recount of the original vials averaged 23,009 pCi/L.~~

~~Reanalysis results were acceptable, 19,170 pCi/L.~~

~~Al-1~~

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

~~mR' Lab Code Date Known Lab Result Control Description Value~~

~~+/- 2 sigma Limits Acceptance Environmental, Inc.~~

~~2009-1 2009-1 2009-1 2009-1 2009-1 2009-1 2009-1 2009-1 2009-1 2009-1 7/6/2009 7/6/2009 7/6/2009 7/6/2009 7/6/2009 7/6/2009 7/6/2009 7/6/2009 7/6/2009 7/6/2009 40 cm.~~

~~41.82 50 cm.~~

~~60 cm.~~

~~70 cm.~~

~~90 cm.~~

~~100 cm.~~

~~110 cm.~~

~~120 cm, 150 cm.~~

26.76 18.58 13.65 8.26 8.26 6.69 5.53 4.65 2.97 45.43 +/- 3.66 32.17 +/- 1.52 20.23 +/- 1.60 15.28 +/- 0.79 7.97 +/- 0.40 7.37 +/- 0.49 6.16 +/- 0.64 4.38 +/- 0.24 4.34 +/- 0.23 2.92 +/- 0.25 29.27 -54.37 18.73 -34.79 13.01 -24.15 9.56 -17.75 5.78 -10.74 5.78 -10.74 4.68 - 8.70 3.87 -7.19 3.26 - 6.05 2.08 - 3.86 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Environmental, Inc.

2009-2 2009-2 2009-2 2009-2 2009-2 2009-2 2009-2 2009-2 2009-2 2009-2 2009-2 2009-2 2009-2 12/27/2009 12/27/2009 12/27/2009 12/2712009 12/27/2009 12/27/2009 12/27/2009 12/27/2009 12/27/2009 12/27/2009 12/27/2009 12/27/2009 12/27/2009 40 cm.

~~50 cm.~~

~~60 cm.~~

~~75 cm.~~

~~90 cm.~~

~~100 cm.~~

~~120 cm.~~

~~150 cm.~~

~~180 cm.~~

44.83 28.69 19.92 19.92 12.75 8.85 8.85 7.17 4.98 4.98 3.19 2.21 2.21 51.38 + 2.69 31.65 +/- 2.81 21.38 + 1.19 22.30 +0.50 13.48 +/- 1.02 9.62 + 0.74 8.39 +/- 0.86 6.65 +/- 0.96 4.89 +/- 0.53 4.92 +/- 0.58 2.74 +/- 0.39 1.65 +/- 0.33 2.12 +/- 0.69 31.38 -58.28 20.08 - 37.30 13.94 -25.90 13.94 - 25.90 8.93 - 16.58 6.20 - 11.51 6.20 -11.51 5.02 - 9.32 3.49 - 6.47 3.49 - 6.47 2.23 -4.15 1.55 -2.87 1.55 -2.87 Pass 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=1 c Activity Limits d Acceptance W-1 2009 W-12009 W-12709 SPW-5553 SPW-217 SPW-539 SPW-718 SPMI-814 SPMI-814 SPMI-814 SPMI-815 SPMI-815 SPW-817 SPW-817 SPW-818 SPW-818 SPW-818 SPW-818 SPAP-903 SPAP-903 SPCH-916 SPVE-888 SPF-820 W-40909 W-40909 SPW-12641 SPW-1267 TWW-2124 W-42809 SPMI-2186 SPMI-2186 SPMI-2186 SPMI-2186 SPMI-2186 SPW-2497 SPW-3448 SPW-3497 SPW-3499 SPMI-3582 SPMI-3582 SPAP-3595 SPAP-3595 1/20/2009 1/27/2009 1/27/2009 1/27/2009 1/29/2009 2/24/2009 3/6/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/23/2009 3/23/2009 3/24/2009 4/1/2009 4/7/2009 4/9/2009 4/9/2009 4/10/2009 4/10/2009 4/21/2009 4/28/2009 5/12/2009 5/12/2009 5/12/2009 5/12/2009 5/12/2009 5/27/2009 7/14/2009 7/15/2009 7/15/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 Ra-226 Gr. Alpha Gr. Beta Ra-228 U-238 Ni-63 C-14 Cs-134 Cs-137 Sr-90 1-131

~~-1 31(G) 1-131 1-131(G)~~

~~Co-60 Cs-1 34 Cs-137 Sr-90 Cs-134 Cs-137 1-131(G) 1-131(G)~~

~~Cs-134 Gr. Alpha Gr. Beta Ra-228 U-238 H-3 Ra-226 Cs-1 34 Cs-137 1-131 1-131(G)~~

Sr-90 Fe-55 Cs-137 Ni-63 Tc-99 Cs-134 Cs-137 Cs-134 Cs-137 12.88 +/- 0.41 20.20 +/- 0.40 46.26 +/- 0.42 29.11 +/- 2.53 44.98 +/- 2.30 167.93 +/-.3.79 4893.50 +/- 21.69 34.91 +/- 3.85 59.17 +/-+6.70 40.82 +/- 1.59 70.99 +/- 0.62 63.08 +/- 7.12 62.11 +/- 0.59 64.55 +/- 8.32 50.84 +/- 4.70 33.78 +/-.3.42 61.27 +/- 7.18 47.26 +/- 1.89 13.29 +/- 2.89 103.24 +/- 7:54 0.22 +/- 0;02 0.40 +/- 0.08 0.58 +/- 0.02 19.26 +/- 0.40 48.04 +/- 0.42 40.06 +/- 2.79 41.71 +/- 2.25 7932.00 +/- 279.00 14.49 +/- 0.53 32.55 +/- 1.26 54.27 +/- 2.60 60.81 +/- 0.63 56.89 +/- 2.56 43.88 +/- 1.68 2472.37..+/- 10.76 171.06 +/- 9.21 179.99 +/- 3.06 29.61 +/- 0.81 32.86 +/- 3.72 182.49 +/- 10.54 13.01 +/- 3.00 110.63 +/- 6.58 12.69 20.08 45.60 28.66 41.70 211.00 4740.20 35.70 55.60 44.07 69.60 69.60 69.60 69.60 51.99 35.70 55.64 44.07 14.19 111.23 0.22 0.35 0.56 20.08 45.60 40.54 41.70 7063.00 16.78 33.89 55.60 52.40 52.40 52.40 2106.35 166.10 210.40 32.34 31.89 166.10 12.75 110.73 8.88 - 16.50 10.04 - 30.12 35.60 -55.60 20.06 - 37.26 29.19 - 54.21 147.70 - 274.30 2844.12 - 6636.28 25.70 - 45.70 45.60 -65.60 35.26 - 52.88 55.68 - 83.52 59.60 - 79.60 55.68 - 83.52 59.60 - 79.60 41.99 - 61.99 25.70 - 45.70 45.64 - 65.64 35.26 - 52.88 4.19 - 24.19 100.11 - 122.35 0.13 -0.31 0.21 - 0.49 0.34 - 0.78 10.04 -30.12 35.60 - 55.60 28.38 - 52.70 29.19 - 54.21 5650.40 - 8475.60 11.75 - 21.81 23.89 - 43.89 45.60 - 65.60 40.40 - 64.40 42.40 - 62.40 41.92 - 62.88 1685.08 -2527.62 149.49 - 182.71 147.28 - 273.52 20.34 - 44.34 21.89 - 41.89 149.49 - 182.71 2.75 - 22.75 99.66 - 121.80 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass I

~~I I~~

~~I Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A3-1 I~~

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 Activity Limitsc Acceptance SPF-3597 SPF-3597 SPW-3599 SPW-12643 W-80709 W-81009 W-81009 W-100109 W-102709 W-102709 SPW-5964 SPW-12647 SPAP-6769 SPAP-6774 SPAP-6774 SPF-6776 SPF-6776 SPW-6780 SPMI-6782 SPMI-6782 SPMI-6782 SPW-6784 SPW-6784 SPW-6784 7/17/2009 7/17/2009 7/17/2009 8/3/2009 8/7/2009 8/10/2009 8/10/2009 10/1/2009 10/27/2009 10/27/2009 10/28/2009 11/6/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 Cs-134 Cs-137 H-3 Ra-228 Ra-226 Gr. Alpha Gr. Beta Ra-226 Gr. Alpha Gr. Beta U-238 Ra-228 Gr. Beta Cs-134 Cs-137 Cs-1 34 Cs-137 Tc-99

'Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 0.53 +/- 0.03 2.43 +/- 0.05 63246.00 +/- 725.00 38.18 +/- 2.72 16.28 +/- 0.41 20.58 +/- 0.44 44.44 +/- 0.40 15.68 +/- 0.41 21.50 +/- 0.43 44.83 +/- 0.40 40.20 +/- 1.87 44.49 +/- 3.33 45.43 +/- 0.11 10.32 +/- 0.83 106.58 +/- 2.51 0.43 +/- 0.02 2.33 +/- 0.05 30.71 +/- 1.09 74.30 +/- 5.41 58.82 +/- 3.75 178.18 +/- 9.68 74.03 +/- 4.64 54.84 +/- 3.83 180.06 +/- 8181 0.51 2.22 62495.00 40.54 16.77 20.08 45.60 16.77 20.08 45.60 41.70 40.54 49.48 11.11 109.70 0.44 2.19 32.34 72.81 55.54 164.55 72.81 55.54 164.55 0.31 - 0.71 1.33 -3.10 49996.00 - 74994.00 28.38 - 52.70 11.74 - 21.80 10.04 -30.12 35.60 - 55.60 11.74 - 21.80 10.04 - 30.12 35.60 - 55.60 29.19 - 54.21 28.38 - 52.70 29.69 - 69.27 1.11-21.11 98.73 - 120.67 0.26 - 0.62 1.31 -3.07 20.34 - 44.34 62.81 -82.81 45.54 - 65.54 148.10 - 181.01 62.81 -82.81 45.54 - 65.54 148.10 - 181.01 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/rn 3), and solid samples (pCi/g).

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

~~CH (charcoal canister), F (fish).~~

~~c Results are based on single determinations.~~

~~Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 20.~~

~~e Control limits based on the laboratory limit, Attachment A ("Other Analyses").~~

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

~~A3-2~~

~~TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code.~~

~~Sample Date Analysisb Laboratory results (4.66(r)~~

~~Acceptance Type LLD Activityc Criteria (4.66 a)~~

W-12009 SPW-5554 W-12709 W-12709 SPW-218 SPW-538 SPW-717 SPMI-816 SPMI-816 SPMI-816 SPMI-816 SPMI-816 SPW-819 SPW-819 SPW-819 SPW-819 SPW-819 SPW-819 SPAP-902 SPAP-904 SPAP-904 SPW-32709 SPF-821 SPF-821 W-40909 W-40909 SPW-12651 SPW-1268 W-42809 SPMI-2186 SPMI-2187 SPMI-2187 SPMI-2187 SPMI-2187 SPW-2498 Water Water Water Water Water Water Water Milk Milk Milk Milk Milk Water Water Water Water Water Water Air Filter Air Filter Air Filter Water Fish Fish Water Water Water Water Water Milk Milk Milk Milk Milk Water 1/20/2009 1/27/2009 1/27/2009 1/27/2009 1/29/2009 2/24/2009 316/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/23/2009 3/23/2009 3/23/2009 3/23/2009 41712009 4/7/2009 4/9/2009 419/2009 4/10/2009 4/10/2009 4/28/2009 5/12/2009 5/12/2009 5/12/2009 5/12/2009 5/12/2009 5/27/2009 Ra-226 Ra-228 Gr. Alpha Gr. Beta U-238 Ni-63 C-14 Cs-1 34 Cs-137 1-131 1-131(G)

~~Sr-90 Co-60 Cs-134 Cs-137 1-131 1-131(G)~~

~~Sr-90 Gr. Beta Cs-134 Cs-1 37 Ni-63 Cs-134 Cs-137 Gr. Alpha Gr. Beta Ra-228 U-238 Ra-226 Sr-90 Cs-134 Cs-137 1-131 1-131(G)~~

Ni-63 0.05 0.08 0.35 0.74 0.19 7.91 7.66 3.24 3.38 0.31 3.65 0.48 3.02 2.25 2.03 0.42 3.02 1.10 0.003 1.68 2.62 2.84 3.12 3.93 0.40 0.77 0.77 0.11 0.04 0.43 3.61 3.13 0.15 3.77 1.60 0.06 +/- 0.04 0.17 +/- 0.40 0.22 +/- 0.27

~~-0.08 +/- 0.51~~

~~-0.06 +/- 0.09 4.96 +/- 4.93 3.03 +/- 4.71 0.04 +/- 0.17 0.41 +/- 0.27~~

~~-0.06 +/- 0.19~~

~~-0.63 +/- 0.44 0.006 +/- 0.002 1.37 + 1.75~~

~~-0.25 +/- 0.26~~

~~-0.30 +/- 0.53 0.77 +/- 0.45 0.24 +/- 0.17 0.09 +/- 0.04 0.52 +/- 0.26~~

~~-0.02 +/- 0.10 0.00 +/- 0.97 1~~

~~2 1~~

~~3.2 1~~

~~20 200 10 10 0.5 20 1~~

~~10 10 10 0.5 20 1~~

~~3.2 100 100 20 100 100 1~~

~~3.2 2~~

~~1 1~~

~~1 10 10 0.5 20 20 U~~

~~IR I~~

~~I I~~

~~I I,~~

~~I U~~

~~I I~~

~~A4-1~~

~~TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results (4.66a)~~

~~Acceptance Type LLD Activityc Criteria (4.66 a)~~

SPW-3497 SPW-3500 SPMI-3589 SPAP-3594 SPAP-3594 SPF-3596 SPF-3596 SPF-3596 SPW-3598 SPW-12653 W-80709 W-81009 W-81009 W-100109 W-102709 W-102709 SPW-5965 SPW-12657 SPAP-6769 SPAP-6773 SPF-6775 SPF-6775 SPW-6777 SPW-6779 SPMI-6781 SPMI-6781 SPMI-6781 SPW-6783 SPW-6783 SPW-6783 Water Water Milk Air Filter Air Filter Fish Fish Fish Water Water Water Water Water Water Water Water Water Water Air Filter Air Filter Fish Fish Water Water Milk Milk Milk Water Water Water 7/15/2009 7/15/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 8/3/2009 8/7/2009 8/10/2009 8/10/2009 10/1/2009 10/27/2009 10/27/2009 10/28/2009 11/6/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 1.2/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 Ni-63 Tc-99 1-131(G)

~~Cs-134 Cs-137 Co-60 Cs-1 34 Cs-137 H-3 Ra-228 Ra-226, Gr. Alpha Gr. Beta Ra-226 Gr. Alpha Gr. Beta U-238 Ra-228 Gr. Beta Cs-137 Cs-134 Cs-137 Ni-63 Tc-99 Cs-134 Cs-1 37 1-131(G)~~

~~Cs-134 Cs-137 1-131(G) 1.55 0.90 5.75 1.14 2.47 5.00 8.00 11.50 148.40 0.76 0.04 0.44 0.75 0.04 0.38 0.81 0.15 0.86 0.003 1.31 5.70 4.18 2.29 1.16 2.62 3.29 2.65 2.18 2.90 2.30~~

~~-0.24 t 0.94~~

~~-1.71 +/- 0.53 0.69 +/- 73.60 1.46 +/- 0.51 0.08 +/- 0.03 0.08 +/- 0.31~~

~~-0.31 +/- 0.52 0.09 +/- 0.03 0.33 +/- 0.30~~

~~-0.59 +/- 0.55 0.09 +/- 0.13 0.80 +/- 0.50 0.010 +/- 0.002 0.25 +/- 1.38~~

~~-0.98 +/- 0.69 20 10.~~

~~20 100 100 100:~~

~~100 100 200 2~~

~~1 1~~

~~3.2 1~~

~~1 3.2 1~~

~~2 3.2 100 100 100 20 10 10 10 20 10 10 20 8 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)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-7464, 7465 E-20, 21 CF-67, 68 CF-67, 68 CF-67, 68 DW-90010, 90011 DW-90010, 90011 SG-198, 199 SG-198, 199 SW-308, 309 LW-330, 331 SW-308, 309 DW-375, 376 SWU-606, 607 U-651, 652 U-651, 652 SG-739, 740 MI-875, 876 MI-875, 876 WW-970, 971 XWW-980,981 AP-1441, 1442 SWT-1123, 1124 WW-11102, 1103 XWW-1174, 1175 AP-1462, 1463 SL-2024, 2025 SL-2024, 2025 SL-2024, 2025 SO-2045, 2046 SO-2045, 2046 SO-2045, 2046 mi-2251, 2252 mi-2381, 2382 SWT-2534, 2535 G-2626, 2627 G-2626, 2627 WW-2732, 2733 1/1/2009 1/5/2009 1/5/2009 1/5/2009 1/5/2009 1/9/2009 1/9/2009 1/23/2009 1/23/2009 1/27/2009 1/27/2009 1/29/2009 2/4/2009 2/24/2009 2/27/2009 2/27/2009 3/2/2009 3/17/2009 3/17/2009 3/24/2009 3/24/2009 3/30/2009 3/31/2009 4/1/2009 4/1/2009 4/2/2009 5/4/2009 5/4/2009 5/4/2009 5/4/2009 5/4/2009 5/4/2009 5/14/2009 5/19/2009 5/26/2009 5/28/2009 5/28/2009 6/1/2009 Be-7 K-40 Be-7 Gr. Beta K-40 Ra-226 Ra-228 Gr. Alpha Gr. Beta Gr. Beta Gr. Beta Gr. Beta Gr. Beta Gr. Beta Beta-K40 H-3 Ra-226 K-40 Sr-90 Gr. Beta H-3 Be-7 Gr. Beta Gr. Beta H-3 Be-7 Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta Sr-90 K-40 K-40 Gr. Beta Gr. Beta K-40 H-3 0.063 +/- 0.0.12 1.34 +/- 0.21 0.34 +/- 0.12 4.34 +/- 0.11 3.16 +/- 0.26 2.97 +/- 0.22 3.13 +/- 0.71 101.90 +/- 6.50 97.80 +/- 3.50 1.43 +/- 0.58 2.09 +/- 0.58 1.51 +/- 0.56 2.72 +/- 0.65 2.66 +/- 0.68 3.90 +/- 2.30 597.00 +/- 292.00 8.20 +/-0.20 1286.50 +/- 111.60 0.67 +/- 0.31 13.59 +/- 2.32 7143.00 +/- 262.00 0.076 +/- 0.012 1.40 +/- 0.55 2.13 +/- 1.34 2814 +/- 176 0.085 +/- 0.014 0.80 +/- 0.18 2.41 +/- 0.19 1.20 +/- 0.21 6.22 +/- 2.87 28.85 +/- 3.15 0.036 +/- 0.010 1220.60 +/- 155.10 1472.50 +/- 122.90 1.12 +/- 0.57 6.32 +/- 0.19 4.13 +/- 0.35 240.73 +/- 93.21 0.065 +/- 0.010 1.13 +/- 0.13 0.39 +/- 0.08 4.38 +/- 0.12 3.00 +/- 0.16 2.76 +/- 0.21 3.55 +/- 0.81 101.70 +/- 6.10 94.00 +/- 3.20 1.41 +/- 0.54 2.33 +/- 0.63 1.61 +/- 0.57 3.06 +/- 0.69 2.16 +/- 0.67 1.70 +/- 2.50 607.00 +/- 288.00 8.30 +/- 0.20 1471.70 +/- 111.50 0.36 +/- 0.36 17.33 +/- 2.69 7262.00 +/- 264.00 0.075 +/- 0.014 1.86 +/- 0.62 2.30 +/- 1.32 2787 +/- 176 0.10 +/- 0.016 0.82 +/- 0.13 2.68 +/- 0.21 1.30 +/-0.15 6.50 +/- 3.26 30.39 +/- 3.34 0.024 +/- 0.010 1455.50 +/- 118.20 1412.80 +/- 117.40 1.66 +/- 0.58 6.18 +/- 0.19 4.05 +/- 0.34 190.39 +/- 90.81 0.064 +/- 0.008 1.24 +/- 0.12 0.37 +/- 0.07 4.36 +/- 0.08 3.08 +/- 0.15 2.87 +/- 0.15 3.34 +/- 0.54 101.80 +/- 4.46 95.90 +/- 2.37 1.42 +/- 0.40 2.21 +/- 0.43 1.56 +/- 0.40 2.89 +/- 0.47 2.41 +/- 0.48 2.80 +/- 1.70 552.00 +/- 205.07 8.25.+/- 0.14 1379.10 +/- 78.88 0.52 +/- 0.24 15.46 +/- 1.78 7202.50.+/- 185.97 0.076 +/- 0.009 1.63 +/- 0.41 2.22 +/- 0.94 2801 +/- 124 0.091 +/- 0.011 0.81 +/- 0.11 2.55 +/- 0.14 1.25+/- 0.13 6.36 +/- 2.17 29.62 +/- 2.30 0.030 +/- 0.007 1338.05 +/- 97.50 1442.65 +/- 84.98 1.39 +/- 0.41 6.25 +/- 0.13 4.09 +/- 0.24 215.56 +/- 65.07 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass U

~~I I~~

~~I U~~

~~I I~~

~~I i,~~

~~I I~~

~~i I~~

~~I Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 2J I'I A5-1~~

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SG-3187, 3188 SG-3187, 3188 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/25/2009 6/25/2009 SL-3297, 3298 7/1/2009 SL-3297, 3298 7/1/2009 SL-3297, 3298 7/1/2009 AP-3944, 3945 7/1/2009 DW-90222, 90223 7/15/2009 DW-90222, 90223 7/15/2009 DW-90237, 90238 7/17/2009 F-3790, 3791 7/21/2009 DW-90250, 90251 7/22/2009 DW-90250, 90251 7/22/2009 VE-3965, 3966 7/28/2009 VE-4098, 4099 8/3/2009 VE-4098, 4099 8/3/2009 VE-4098, 4099 8/3/2009 SO-4325, 4326 8/14/2009 SO-4325, 4326 8/14/2009 SO-4325, 4326 8/14/2009 SG-4283, 4284 8/17/2009 SG-4283, 4284 8/17/2009 VE4436, 4437 8/25/2009 SL-4589, 4590 9/1/2009 SL-4589, 4590 9/1/2009 AV-4882, 4883 9/8/2009 AV-4882, 4883 9/8/2009 Ac-228 Be-7 Bi-212 Bi-214 Cs-137 Pb-212 Pb-214 Pu-239/40 Th-232 TI-208 U-233/4 U-238 Ac-228 Pb-214 Be-7 Gr. Beta K-40 Be-7 Ra-226 Ra-228 Gr. Alpha K-40 Ra-226 Ra-228 K-40 Be-7 Gr. Beta K-40 Be-7 Cs-137 K-40 Ac-228 Pb-214 K-40 Be-7 K-40 Be-7 K-40 1.07 +/- 0.06 0.55 +/-0.14 1.16 +/- 0.17 0.96 +/- 0.03 0.72 +/- 0.07 1.00 +/- 0.02 1.01 +/- 0.03 0.022 +/- 0.008 0.51 +/- 0.04 0.35 +/- 0.02 0.16 +/- 0.02 0.14 +/- 0.02 11.07 +/- 0.33 26.54 +/- 0.23 1.15 +/- 0.13 3.38 +/- 0.23 1.43 +/- 0.18 0.064 +/- 0.009 5.36 +/- 0.60 2.91 +/- 0.73 3.54 +/- 0.99 1.10 +/- 0.35 14.58 +/- 0.39 6.71 +/- 1.05 1.48 +/- 0.16 0.54 +/- 0.16 5.15 +/-0.17 4.91 +/- 0.49 0.59 +/- 0.21 0.29 +/- 0.05 13.41 +/-0.77 7.16 +/-*0.28 6.27 +/- 0.13 2.28 x 0.28 1.25 +/- 0.22 2.96 +/- 0.30 0.93 +/- 0.18 2.50 +/- 0.26 1.06 +/- 0.05 0.62 +/- 0.08 1.14 +/- 0.16 1.01 +/- 0.03 0.76 +/- 0.08 1.03 +/- 0.02 1.04 +/- 0.03 0.030 +/- 0.009 0.48 +/- 0.05 0.36 +/- 0.02 0.18 +/- 0.02 0.18 +/- 0.03 10.88 +/- 0.33 26.17 +/- 0.25 1.15 +/- 0.12 3.37 +/- 0.12 1.50 +/- 0.19 0.068 +/- 0.010 4.62 +/- 0.51 2.80 +/- 0.70 4.22 +/- 1.09 1.41 +/- 0.44 15.13 +/- 0.40 6.10 +/- 1.01 1.56 +/- 0.19 0.58 +/- 0.16 5.07 +/- 0.18 5.17 +/- 0.15 0.68 +/- 0.28 0.28 +/- 0.05 13.46 +/- 0.80 7.10 +/- 0.26 6.21 +/- 0.13 2.67 +/- 0.26 1.25 +/- 0.16 2.70 +/- 0.27 0.95 +/- 0.17 2.47 +/- 0.29 1.07 +/- 0.04 0.59 +/- 0.08 1.15 +/- 0.12 0.99 +/- 0.02 0.74 +/- 0.05 1.02 +/- 0.01 1.03 +/- 0.02 0.026 +/- 0.006 0.50 +/- 0.03 0.36 +/- 0.01 0.17 +/- 0.01 0.16 +/- 0.02 10.97 +/- 0.24 26.36 +/- 0.17 1.15 +/- 0.09 3.38 +/- 0.13 1.47 +/- 0.13 0.066 +/- 0.007 4.99 +/- 0.39 2.86 +/- 0.51 3.88 +/- 0.74 1.26 +/- 0.28 14.86 +/- 0.28 6.41 +/- 0.73 1.52 +/- 0.13 0.56 +/-0.11 5.11 +/- 0.12 5.04 +/- 0.26 0.64 +/- 0.18 0.28 +/- 0.03 13.43 +/- 0.56 7.13 +/- 0.19 6.24 +/- 0.09 2.48 +/- 0.19 1.25 +/- 0.14 2.83 +/- 0.20 0.94 +/- 0.12 2.49 +/- 0.20 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 A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance WW-4721,4722 WW-4903, 4904 BS-5119, 5120 BS-5119, 5120 BS-5119, 5120 SS-5188, 5189 SS-5188, 5189 AP-3944, 3945 E-5251, 5252 E-5251, 5252 G-5272, 5273 G-5272, 5273 G-5272, 5273 F-5690, 5691 F-5690, 5691 DW-90396, 90397 DW-90396, 90397 DW-90408, 90409 DW-90408, 90409 DW-90420, 90421 DW-90420, 90421 SG-5962, 5963 SG-5962, 5963 DW-90423, 90424 ME-6116, 6117 ME-6116, 6117 F-6567, 6568 F-6567, 6568 W-6495,6496 WW-6313, 6314 SWU-6611, 6612 DW-90446, 90447 DW-90446, 90447 9/9/2009 9/11/2009 9/16/2009 9/16/2009 9/16/2009 9/23/2009 9/23/2009 9/29/2009 10/1/2009 10/1/2009 10/1/2009 10/1/2009 10/1/2009 10/15/2009 10/15/2009 10/16/2009 10/16/2009 10/19/2009 10/19/2009 10/21/2009 10/21/2009 10/22/2009 10/22/2009 10/27/2009 11/3/2009 11/3/2009 11/6/2009 11/6/2009 11/8/2009 11/9/2009 11/24/2009 12/30/2009 12/30/2009 H-3 H-3 Be-7 Cs-137 K-40 Be-7 K-40 Be-7 Gr. Beta K-40 Be-7 Gr. Alpha K-40 H-3 K-40 Ra-226 Ra-228 Ra-226 Ra-228 Ra-226 Ra-228 Ac-228 Pb-214 Gr. Alpha Gr. Beta K-40 Gr. Beta Sr-90 H-3 H-3 Gr. Beta Ra-226 Ra-228 19191.00 +/- 404.00 1075.00 +/- 130.00 2067.50 +/- 327.90 86.24 +/- 35.40 16.85 +/- 0.90 1.02 +/- 0.31 10.21 +/- 0.65 0.09 +/- 0.02 2.30 +/- 0.10 1.18 +/- 0.24 3.31 +/- 0.29 19.81 +/- 0.80 16.47 +/- 0.75 8895.00 +/- 250.00 3.62 +/- 0.40 0.54 +/- 0.09 1.44 +/- 0.56 0.99 +/- 0.12 2.76 +/- 0.66 1.95 +/- 0.17ý 3.10 +/- 0.73 16.39 +/- 0.79 18.03 +/- 0.41 12.04 +/- 1.68 0.86 +/- 0.03 2.57 +/- 0.08 2.72 +/- 1.05 0.09 +/- 0.03 2638.00 +/- 173.00 1514.00 +/- 137.00 1.88 +/- 0.60 0.30 +/- 0.10 2.60 +/- 0.64 18677.00 +/- 399.00 1281.00 +/- 136.00 2225.40 +/- 371.10 145.10 +/- 31.54 17.27 +/- 0.79 1.04 +/- 0.43 9.94 +/- 0.93 0.09 +/- 0.02 2.10 +/- 0.10 1.15 +/- 0.18 3.60 +/- 0.26 21.10 +/- 0.74 17.00 +/- 0.74 9051.00 +/- 252.00 3.09 +/- 0.48 0.42 +/- 0.08 0.94 +/- 0.51 1.10 +/- 0.14 1.38 +/- 0.92 1.77 +/- 0.15 3.32 +/- 0.80 16.51 +/- 0.63 17.74 +/- 0.42 15.28 +/- 1.97 0.83 +/- 0.03 2.65 +/- 0.08 3.04 +/- 0.92 0.12 +/- 0.04 2451.00 +/- 168.00 1483.00 +/- 136.00 1.67 +/- 0.59 0.54 +/- 0.14 2.65 +/- 0.65 18934.00 +/- 283.91 1178.00 +/- 94.07 2146.45 +/- 247.61 115.67 +/- 23.71 17.06 +/- 0.60 1.03 +/- 0.26 10.07 +/- 0.57 0.09 +/- 0.01 2.20 +/- 0.07 1.17 +/- 0.15 3.46 +/- 0.19 20.46 +/- 0.54 16.74 +/- 0.53 8973.00 +/- 177.49 3.36 +/- 0.31 0.48 +/- 0.06 1.19 +/- 0.38 1.05 +/- 0.09 2.07 +/- 0.57 1.86 -+0.11 3.21 + 0.54 16.45 +/- 0.51 17.89 +/- 0.29 13.66 +/- 1.29 0.85 +/- 0.02 2.61 +/- 0.06 2.88 + 0.70 0.11 +/-0.02 2544.50 +/- 120.57 1498.50 + 96.52 1.78 + 0.42 0.42 +/- 0.09 2.63 + 0.46 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 3

~~I I~~

~~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).~~

~~A5-3~~

~~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-1170' STW-1170 STW-1170 STW-1170 STW-l 170 e STW-1170 STW-1170 STW-1170 STW-1 170 STW-1 170 STW-1 170 STW-1170 STW-1170 STW-1 170 STW-1170 STW-1170 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Am-241 Co-57 Co-60 Cs-134 Cs-137 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 1.15 +/- 0.06 19.60 +/- 0.40 16.60 +/- 0.30 20.40 +/- 0.50 0.10 +/- 0.20 51.60 +/- 20.60 359.90 +/- 33.90.

~~15.00 +/- 0.40 50.50 +/- 3.25.~~

~~1.17 +/- 0.04 0.74 +/- 0.03 7.87 +/- 1.39 12.70 +/- 0.80 2.78 +/- 0.07 2.87 +/- 0.07 14.00 +/- 0.70 0.56 +/- 0.06 1.29 +/- 0.05 0.00 +/- 0.00 458.60 +/- 7.40 0.64 18.90~~

.17.21 22.50 0.00 48.20 330.90 14.66 53.50 1.18 0.85 7.21 14.46 2.77 2.88 13.60 0.64 1.27 0.00 467.00 605.00 570.00 307.00 25.30 0.00 257.00 149.00 155.00 242.00 0.45 - 0.83 13.20 - 24.60 12.05 - 22.37 15.80 - 29.30 0.00 - 1.00 33.70 - 62.70 231.60 -430.20 10.26 - 19.06 37.45 - 69.55 0.83 - 1.53 0.60 -1.11 5.05 - 9.37 10.12 - 18.80 1.94 - 3.60 2.02 - 3.74 9.50 - 17.70 0.00 - 1.27 0.64 -1.91 0.00 - 1.00 327.00 - 607.00 424.00 - 787.00 360.40 - 669.40 215.00 - 399.00 17.70 - 32.90 0.00-1.00 180.00 - 334.00 104.00 - 194.00 109.00 - 202.00 169.00 - 315.00 STW-1171 01/01/09 Gr. Alpha STW-1171 01/01/09 Gr. Beta 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 Pass Pass Pass Pass Pass Pass Pass STSO-1172 e STSO-1 172 STSO-1 172 STSO-1172 STSO-1 172 STSO-1 172 STSO-1172 e STSO-1 172 STSO-1 172 STSO-1 172 STSO-1 172 STVE-1 173 STVE-1173 e STVE-1 173 STVE-1 173 STVE-1 173 STVE-1 173 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Co-57 Cs-134 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 652.30 636.40 346.40 28.60 0.50 180.60 152.20 154.90 268.30

~~+/- 3.50~~

~~+/- 9.50~~

~~+/- 3.10~~

~~+/- 2.20~~

~~+/- 0.40~~

~~+/- 12.10~~

~~+/- 4.30~~

~~+/- 4.40~~

~~+/- 4.00 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 2.75 0.06 3.49 1.01 2.52 1.52~~

~~+/- 0.11~~

~~+/- 0.09~~

~~+/- 0.22~~

~~+/- 0.11~~

~~+/- 0.14~~

~~+/- 0.18 2.36 0.00 3.40 0.93 2.30 1.35 1.65 - 3.07 0.00- 1.00 2.38 - 4.42 0.65 -1.21 1.61 -2.99 0.95 - 1.76~~

)

~~A6-1~~

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

~~Concentration b Known Control Lab Code '~~

Date Analysis Laboratory result Activity Limits d Acceptance STAP-1174 g STAP-1 174 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1174 h STAP-1 174 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Am-241 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 0.29 +/- 0.03 1.25 +/- 0.05 1.17 +/- 0.06 2.67 +/- 0.14 1.53 +/- 0.08 2.34 +/- 0.09 0.93 +/- 0.14 1.44 +/- 0.14 0.22 +/- 0.03 0.36 +/- 0.04 0.21 1.30 1.22 2.93 1.52 2.27 0.64 1.36 0.35 0.28 0.14 -0.27 0.91 - 1.69 0.85 - 1.59 2.05 -3.81 1.06-1.98 1.59 -2.95 0.45 - 0.83 0.95 - 1.77 0.00 -0.70 0.14 -0.42 STAP-1175 01/01/09 Gr. Alpha STAP-1175 01/01/09 Gr. Beta STSO-1 188 STSO-1188 STSO-1188 STSO-1 188 STSO-1 188 STSO-1188 STSO-1 188 STSO-1 188 STSO-1188' STSO-1 188 STSO-1 188 STSO-1 188 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 674.60 +/- 9.00 356.40 +/- 6.30 0.20 +/- 1.90 767.50 +/- 12.00 433.00 +/- 37.20 931.60 +/- 14.10 53.10 +/- 9.00 107.10 +/- 12.60 310.50 +/- 12.20 188.20 +/- 11.90 197.40 +/- 12.20 1433.90 +/- 25.20 586.00 327.00 0.00 669.00 375.00 796.00 63.20 116.30 455.00 209.00 217.00 1178.00 410.00 -762.00 229.00 -425.00 0.00 -.1.00 468.00 - 870.00 263.00 - 488.00 557.00 - 1035.00 44.20 -82.20 81.40 -151.20 319.00 -592.00 146.00 -272.00 152.00 -282.00 825.00 - 1531.00 Fail Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass 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 U

~~I I~~

~~i I~~

~~I I~~

I STAP-1189 07/01/09 Gr. Alpha STAP-1189 07/01/09 Gr. Beta STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STVE-1190 STVE-1190 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1190 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Am-241 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 0.33 +/- 0.04 1.57 + 0.07 0.01 +/- 0,02 6.78 +/- 0.27 1.06 +/- 0.18 0.01 +/- 0.06 1.49 +/- 0.27 6.00 +/- 0.45 0.79 +/- 0.13 4.55 +/- 0.66 8.90 +/- 0.60 2.50 +/- 0.36 0.01 +/- 0.11 2.42 +/- 0.16 8.35 +/- 0.70 0.01 +/- 0.26 0.66 1.32 0.00 6.48 1.03 0.00 1.40 5.49 0.84 3.93 8.00 2.57 0.00 2.43 7.90 0.00 0.00 - 1.32 0.66 - 1.98 0.01 - 0.05 4.54 - 8.42 0.72 -1.34 0.01 - 0.05 0.98 - 1.82 3.84 -7.14 0.59 - 1.09 2.75 -5.11 5.60 - 10.40 1.80 -3.34 0.00 -0.10 1.70 -3.16 5.50 - 10.30 0.00 -0.10 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 STW-1191 07/01/09 Gr. Alpha 0.88 +/- 0.07 1.05 0.00 -2.09 Pass STW-1191 07/01/09 Gr. Beta 7.29 +/- 0.10 7.53 3.77 -11.30 Pass STW-1192 07/01/09 Am-241 0.88 +/- 0.08 1.04 0.73-1.35 Pass STW-1192 07/01/09 Co-57 37.20 +/- 1.50 36.60 25.60 - 47.60 Pass STW-1192 07/01/09 Co-60*

~~15.10 +/- 0.90 15.40 10.80 - 20.00 Pass STW-1192 07/01/09 Cs-134~~

.30.30 +/- 2.10 32.20 22.50 - 41.90 Pass STW-1192 07/01/09 Cs-137 41.90 +/- 1.80 41.20 28.80 - 53.60 Pass STW-1192 07/01/09 Fe-55 54.50 +/- 15.50 60.80 42.60 - 79.00 Pass STW-1192 07/01/09 H-3 680.30 +/- 33.60 634.10 443.90 - 824.30 Pass STW-1192e 07/01/09 Mn-54 0.01 +/- 0.26 0.00 0.00-1.00 Pass STW-1192 07/01/09 Ni-63 38.70 +/- 2.60 44.20 30.90 - 57.50 Pass STW-1192 07101109 Pu-238 0.02 +/- 0.01 0.02 0.00 -0.05 Pass STW-1192 07/01/09 Pu-239/40 1.70 +/- 0.10 1.64 1.15 -2.13 Pass STW-1192 07/01/09 Sr-90 12.90 +/- 1.70 12.99 9.09 - 16.89 Pass STW-1192 07/01/09 Tc-99 7.60 +/- 0.40 10.00 7.00 -13.00 Pass STW-1192 07/01/09 Tc-99 7.60 +/- 0.40 10.00 7.00 -13.00 Pass STW-1192 07/01/09

.U-233/4 2.90 +/- 0.10 2.96 2.07 -3.85 Pass STW-1192 07/01/09 U-238 3.00 +/- 0.10 3.03 2.12 -3.94 Pass STW-1192 07/01/09 Zn-65 28.50 +/- 2.40 26.90 18.80 - 35.00 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).~~

~~MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.~~

~~e Included in the testing series as a "false positive".~~

f No errors were found in procedure or 6alculation. There was not enough sample for a reanalysis. Americium-241 in water was included in the ERA studies (Tbl. A-7) and also in the second round of MAPEP testing. Both analysis results were acceptable.

~~§ One determination was eliminated from the average, due to poor recovery. Average of three determinations, 0.25 + 0.03 pCi/filter.~~

~~h No reason was determined for the initial high results. The analysis was repeated; result of reanalysis; 0.54 + 0.12 Bq/filter.~~

Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity. The analysis was repeated; result of reanalysis 363.3 +/- 28.6 Bq/kg.

)

~~A6-3~~

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

~~Concentration (pCi/L)~~

Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance STAP-1176 STAP-1 176 STAP-1 176 STAP-1 176 STAP-1176 e STAP-1 176 STAP-1 176 STAP-1 176 STAP-1 176 STAP-1 176 STAP-1 176 STAP-1 176 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 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 47.20 +/- 3.10 543.60 +/- 8.90 941.30 +/- 30.70 850.60 +/- 19.40 0.00 +/- 0.00 64.50 +/- 3.60 88.50 +/- 4.20 93.90 +/- 10.00 50.00 +/- 2.47 50.40 +/- 2.48 101.60 +/- 5.30 237.30 +/- 23.70 76.30 +/- 3.47 98.50 +/- 3.04 55.4 490.0 865.0 724.0 0.0 57.4 78.2 95.3 53.5 53.1 109.0 185.0 63.8 80.7 32.4 - 76.0 379.0 - 612.0 563.0 - 1070.0 544.0 - 951.0 0.0-0.0 39.4 - 75.5 56.7 - 101.0 41.9-148.0 33.7 - 79.3 34.0 - 75.4 55.7 - 173.0 128.0 - 256.0 33.1 - 96.0 49.7 - 118.0 Pass Pass Pass.
Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 3
I I
I I
I I
3 I
I I
I I
I I
STAP-1 177 03/23/09 Gr. Alpha STAP-1 177 03/23/09 Gr. Beta STSO-1178 STSO-1 178 STSO-1178 STSO-1 178 STSO-1178 STSO-1 178 STSO-1 178 STSO-1 178 STSO-1178 STSO-1178 STSO-1 178 STSO-1 178 STSO-1178 STSO-1178 STSO-1178 STSO-1 178 STSO-1178 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 Ac-228 Am-241 Bi-212 Bi-214 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 U-233/4 Uranium Zn-65 1370.00 +/- 121.00 1853.00 +/- 185.50 1449.00 +/- 308.80 1355.00 +/- 66.20 7475.00 +/- 46.40 5073.00 +/- 74.70 5040.00 +/- 49.70 10884.00 +/- 292.70 0.00 +/- 0.00 1259.00 +/- 28.40 1464.00 +/- 56.80 1853.00 +/- 185.50 1516.50 +/- 168.30 5270.90 +/- 290.20 1452.30 +/- 114.40 3013.70 +/- 131.10 2083.00 +/- 59.00 1330.0 1660.0 1550.0 1420.0 7520.0 5170.0 4970.0 11200.0 0.0 1260.0 1510.0 1590.0 1360.0 5750.0 1600.0 3270.0 1940.0 860.0 - 1880.0 992.0 -2130.0 406.0 -2310.0 872.0 -2050.0 5470.0 -10100.0 3330.0 -6220.0 3800.0 - 6460.0 8060.0 -15100.0 0.0 -20.0 820.0 - 1780.0 902.0 - 2260.0 910.0 - 2240.0 928.0 - 1800.0 2080.0 - 9380.0 1010.0 -1990.0 1860.0 -4410.0 1540.0 - 2600.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
)
I I
I A7-1
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L) b Lab Code Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STW-1180 STW-1180 STW-1 180 STW-1 180 STW-1 180 STW-1180 STW-1180 STW-1 180 STW-1180 STW-1 180 STW-1 180 STW-1 180 STW-1180 03/23/09 03/23/09 03/23/09 03/23/09 03/23109 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 Am-241 Cm-244 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Sr-90 U-233/4 U-238 Uranium Zn-65 Am-241 Co-60 Cs-1 34 Cs-137 Fe-55 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 2849.70 +237.60 808.00 +/- 85.70 1546.80 +/- 31.60 1706.00 +/- 59.20 1940.50 +/- 44.80 30107.30 +/- 598.00 0.00 +/- 0.00 6604.80 +/- 440,10 1718.00 +/- 128.90 1718.30 +/- 128.80 3499.40 +/- 371.00 869.40 +/- 63.60 127.50 +/- 5.10 1174.10 +/- 11.70 742.20 +/- 18.30 887.50 +/- 14.00 323.00 +/- 362.00 0.00 +/- 0.00 96.60 +/- 2.20 89.50 +/- 2.10 763.20 +/- 12.90 95.00 +/- 1.80 97.40 +/- 1.80 195.50 +/- 3.70 653.10 +/- 24.10 3660.0 954.0 1710.0 1880.0 1800.0 30800.0 0.0 8860.0 2040.0 2020.0 4150.0 878.0 132.0 1230.0 790.0 913.0 492.0 0.0 108.0 86.3 834.0 96.6 95.8 197.0 631.0 2090.0 - 5030.0 470.0 - 1480.0 1160.0 -2460.0 1080.0 - 2600.0 1320.0 - 2500.0 22300.0 - 43700.0 0.0 - 0.0 4950.0 - 11800.0 1400.0 - 2710.0 1420.0 - 2550.0 2850.0 - 5360.0 634.0 - 1200.0 90.4 - 178.0 1070.0 - 1450.0 584.0 - 907.0 776.0 - 1090.0 286.0 - 657.0 0.0 - 0.0 81.7 -134.0 66.8 - 107.0 530.0 -1120.0 72.8 - 124.0 73.2 -119.0 142.0 -262.0 535.0 - 786.0 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 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
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 Included in the testing series as a "false positive". No activity expected.
f The analysis was repeated by leaching and total dissolution methods. Total dissolution yielded results within expected range.
Results of the reanalysis: U-233,4, 1655 +/- 95 pCi/kg. U-238 1805 +/- 97 pCi/kg.
A7-2
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX B 2009 REMP DATA
~~SUMMARY~~
REPORTS
APPENDIX B Air Gamma Spectral Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range Air pCi/m3 Air pCi/m3 Air pCi/m3 Air pCi/m3 Air pCi/m3 Be-7 28 Co-58 28 Co-60 28 Cs-134 28 Cs-137 28 N/A N/A N/A 0.04 0.05 0.07 28 / 28 0.05 - 0.08 LLD LLD LLD LLD 0.07 24 / 24 0.05 - 0.08 1
3.40 ENE 0.07 4 /20 0.06
- 0.07 0.07 4/4 0.06 - 0.08 B-i
APPENDIX B Air Gross Beta Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range Air pCi/m3 Gross Beta 364 0.01 0.02 363 / 364 0.01
- 0.04 0.02 311 / 312 0.01
- 0.04 35 0.60 E
0.02 51 / 52 0.01
- 0.03 0.02 52 / 52 0.01
- 0.04 so lo MR
am
-n W on,oam M mm
-m-a M I'M, waM
- M -ot mM s APPENDIX B Air Iodine Summary Report 2009 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 # and Distance and Direction Location with Highest Annual Mean:
Mean and Number Detected/Number Collected and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range I
I I
F I
+
I Air pCi/m3 1-131 364 0.05 LLD B-3
APPENDIX B Fish Gamma Spectral Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range 97.00 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 Co-58 8
Co-60 8
Cs-134 8
Cs-137 8
Fe-59 8
K-40 8
Mn-54 8
Zn-65 8
97.00 97.00 112.00 195.00 N/A 97.00 195.00 LLD LLD LLD LLD LLD 1,297.49 8/8 846.93 1,637.30 LLD LLD 1,330.10 4 /4 846.93 - 1,637.30 25 0.60 NNW 1,330.10 4 / 32 846.93
- 1,637.30 1,264.88 4 /4 1,056.50 - 1,559.70 m~V, M
"- Vi 'N ON 'g.- M".
N 1
APPENDIX B Food Products Gamma Spectral Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake CQ,.unty Ohio Docket no. : 50-440/50-441 Type and Number of Anal-yses Performed 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 Lower Limit (LLD)
Mean of Results from All Locations and Number DetectedlNumber Collected and Range Mean of Results from All Indicator Locations and Number Detected/Number Collected and Range Location # and Distance and Direction Location with Highest Annual Mean:
+
i-i 4
i I
Be-7 66 Co-58 66 Co-60 66 Cs-134 66 Cs-137 66 1-131 66 K-40 66 N/A N/A N/A 45.00 60.00 45.00 N/A 571.73 52 / 66 131.24-1,600.70 LLD LLD LLD LLD LLD 5,699.12 66 / 66 3,043.25 - 10,368.00 541.05 41 / 54 131.24-1,600.70 5,644.35 54 / 54 3,043.25 10,368.00 20 1.90 E
18 2.50 E
Mean and Number DetectedfNumber Collected and Range 809.10 4 /28 395.95 1,301.60 6,644.13 11 / 77 4,589.20
- 10,368.00 Mean of Results from All Control Locations and Number Detected/Number Collected and Range 686.08 11 / 12 232.78 -
1,461.80 5,945.58 12 / 12 3,466.80 - 9,186.10 B-5
APPENDIX B Milk Gamma Spectral Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mer De d
All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range Milk pCi/L Milk pCi/L Milk pCi/L Milk pCi/L Milk pCi/L Ba-140 59 Cs-134 59 Cs-137 59 K-40 59 La-140 59 45.00 11.00 13.00 N/A 11.00 LLD LLD LLD 1,639.67 59 / 59 565.39 - 2,095.10 LLD 1,834.74 40 / 40 1,470.60 - 2,095.10 61 7.40 SE 1,871.13 13 / 65 1,673.40
- 2,043.50 1,228.99 19 / 19 565.39 -
1,438.70
-0 M00M1 0WIA M
-M W -0
~,
-~ -
~
~
m -
APPENDIX B Milk Iodine Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range Milk pCi/L 1-131 59 0.75 LLD B-7
APPENDIX B Sediment Gamma Spectral Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and RanRe Sediment pCi/kg dry Sediment pCi/kg dry Sediment pCi/kg dry Sediment pCi/kg dry Sediment pCi/kg dry Co-58 11 Co-60 11 Cs-134 11 Cs-137 11 K-40 11 50.00 40.00 112.00 135.00 N/A LLD LLD LLD 505.24 4 / 11 301.33 -
699.30 15,255.95 11 / 11 7,208.50 - 24,592.00 321.37 2 /9 301.33 -
341.42 13,268.38 9 /9 7,208.50 - 23,037.00 32 15.80 WSW 32 15.80 WSW 689.11 2 / 10 678.91
- 699.30 24,200.00 2 / 10 23,808.00
- 24,592.00 689.11 2 /2 678.91
- 699.30 24,200.00 2 /2 23,808.00
- 24,592.00
-m
-0 n
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-Mo~in APPENDIX B TLD Gamma Dose Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range TLD mR/91 days TLD mR/91 days TLD mR/365 days Direct 112 Direct 112 Direct 27 1.00 1.00 1.00 12.75 112 / 112 8.26 -
17.48 12.80 112 / 112 9.31 17.53 53.75 27 / 27 41.66 - 70.94 12.78 104 / 104 8.26 -
17.48 12.86 104 / 104 9.31 17.53 54.03 25 / 25 41.66 - 70.94 33 4.50 S
33 4.50 S
33 4.50 S
16.73 4/4 15.42
- 17.48 16.48 4/4 14.74
- 17.36 70.94 1 / 1 70.94 - 70.94 12.47 8/8 11.62 -
13.40 12.07 8/8 10.74 -
13.33 50.20 2/2 45.94 -
54.45 B-9
APPENDIX B Water Gamma Spectral Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perr-i Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range Water 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 Water pCi!L 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 45.00 11.00 11.00 11.00 13.00 22.00 11.00 11.00 11.00 22.00 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD O
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MrI, 'a Radiological Environmental Monitoring Program Data Summary APPENDIX B 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 # and Distance and Direction Location with Highest Annual Mean-Mean and Number Detected/Number Collected and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range F
+
+
F
+/-
Water pCi/L Zr-95 54 22.00 LLD B-11
APPENDIX B Water Gross Beta Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range Water pCi/L Gross Beta 54 3.00 3.14 2 /54 3.09 - 3.19 3.09 1 /42 3.09 -
3.09 28 22.00 ENE 3.19 1 /12 3.19
- 3.19 3.19 1 /12 3.19 - 3.19 o
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"I oýqý-aA APPENDIX B Water Tritium Summary Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Mean of Results from Mean of Results from Location with Highest Annual Mean:
Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Sample Type Analyses Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected and Units Performed (LLD) and Range and Range Direction and Range and Range Water pCi/L H-3 20 1,500.00 LLD B-13
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX C 2009 REMP DETAILED DATA REPORT
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Air Gamma Spectral Detail Report 2009 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 I
Air 4/1/2009 0.074 +/--0.008
< 0.000
< 0.000
< 0.000
< 0.000 1
Air 7/1/2009 0.070 +-0.008
< 0.001
< 0.000
< 0.000
< 0.000 1
Air 9/30/2009 0.073 +-0.010
< 0.001
< 0.000
< 0.000
< 0.000 Air 12/30/2009 0.059 +-0.010
< 0.000
< 0.001
< 0.000
< 0.000 3
Air 4/1/2009 0.074 +-0.006
< 0.000
< 0.000
< 0.000
< 0.000 3
Air 7/1/2009 0.071 +/-0.011
< 0.000
< 0.000
< 0.000
< 0.000 3
Air 9/30/2009 0.055 +-0.009
< 0.001
< 0.001
< 0.000
< 0.000 3
Air 12/30/2009 0.061 +/-0.008
< 0.000
< 0.000
< 0.000
< 0.000 4
Air 4/1/2009 0.061 +/-0.007
< 0.000
< 0.000
< 0.000
< 0.000 4
Air 7/1/2009 0.066 +/-0.008
< 0.000
< 0.000
< 0.000
< 0.000 C-1
APPENDIX C Air Gamma Spectral Detail Report 2009 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
4 Air Air 9/30/2009 12/30/2009 0.069 +/- 0.008 0.069 +/- 0.009
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000 Air Air Air Air 4/1/2009 7/1/2009 9/30/2009 12/30/2009 0.072 +/- 0.007 0.064 +/- 0.010 0.062 +/- 0.008 0.062 +/- 0.007 0.080 +/-/- 0.009 0.061 +/- 0.009 0.063 +/-/- 0.008 0.063 +/- 0.006
< 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
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000
< 0.000 Air Air Air Air 4/1/2009 7/1/2009 9/30/2009 12/30/2009
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APE I CAir Gamma Spectral Detail Report 2009 APPENDIX C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in pCi/m3 +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 7
7 7
7 Air Air Air Air 4/1/2009 7/1/2009 9/30/2009 12/30/2009 0.073 +/- 0.011 0.077 +/- 0.010 0.067 +/- 0.007 0.048 +/- 0.007
< 0.000
< 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
< 0.000
< 0.000 35 35 35 35 Air Air Air Air 4/1/2009 7/1/2009 9/30/2009 12/30/2009 0.077 +/- 0.010 0.066 +/-/- 0.007 0.069 +/- 0.009 0.057 +/- 0.006
< 0.000
< 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
< 0.000
< 0.000 C-3
APPENDIX C Air Gross Beta Detail Report 2009 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 1/7/2009 1/14/2009 1/21/2009 1/28/2009 Air Air Air Air 2/4/2009 2/11/2009 2/18/2009 2/25/2009 3/4/2009 3/11/2009 3/18/2009 3/25/2009 4/1/2009 4/8/2009 Air Air Air Air Air Air Air Air Air Air 0.029 +/- 0.003 0.030 +/- 0.003 0.031 +/- 0.003 0.028 +/- 0.003 0.036 +/- 0.003 0.035 +/- 0.003 0.033 +/- 0.003 0.032 +/- 0.003 0.031 +/- 0.003 0.031 +/- 0.003 0.034 +/- 0.003 0.033 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.022 +/- 0.003 0.025 +/- 0.003 0.028 +/- 0.003 0.029 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.003 0.032 +/- 0.003 0.035 +/- 0.003 0.024 +/-0.003 0.025 +/- 0.003 0.016 +/- 0.003 0.019 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.027 +/- 0.003 0.029 +/- 0.003 0.029 +/- 0.003 0.031 +/- 0.003 0.034 +/- 0.003 0.032 +/- 0.003 0.035 +/- 0.003 0.034 +/- 0.003 0.032 +/- 0.003 0.030 +/- 0.003 0.032 +/- 0.003 0.034 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.003 0.028 +/- 0.003 0.027 +/- 0.003 0.023 +/- 0.003 0.026 +/- 0.003 0.031 +/-0.003 0.032 +/- 0.003 0.024 +/- 0.003 0.023 +/- 0.003 0.016 +/- 0.003 0.019 +/- 0.003 0.014 +/- 0.003 0.017 +/- 0.003 0.027 +/- 0.003 0.025 +/- 0.003 0.033 +/- 0.003 0.026 +/- 0.003 0.030 -/- 0.003 0.029 +/- 0.003 0.018 +/- 0.003 0.023 +/- 0.003 0.028 +/- 0.003 0.023 +/- 0.003 0.029 +/- 0.003 0.025 +/- 0.003 0.016 +/- 0.002 0.013 +/- 0.002 0.030 +/- 0.003 0.032 /-0.003 0.034 +/- 0.003 0.033 +/- 0.003 0.034 +/- 0.003 0.034 +/- 0.003 0.021 +/- 0.003 0.023 +/- 0.003 0.027 +/- 0.003 0.025 +/- 0.003 0.032 +/- 0.003 0.026 +/- 0.003 0.017 +/- 0.003 0.015 +/- 0.002 0.026 +/- 0.003 0.033 +/- 0.003 0.034 +/- 0.003 0.034 +/- 0.003 0.027 +/- 0.003 0.032 +/- 0.003 0.021 +/- 0.003 0.023 +/- 0.003 0.027 +/- 0.003 0.023 +/- 0.003 0.029 +/- 0.003 0.023 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.003 0--,."
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4Wn APPENDIX C Air Gross Beta Detail Report 2009 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 Sigma Location 1
3 4
5 6
Collection Date Sample Type 7
35 4/15/2009 4/22/2009 4/29/2009 Air Air Air 5/6/2009 5/13/2009 5/20/2009 5/27/2009 6/3/2009 6/10/2009 6/17/2009 6/24/2009 7/1/2009 7/8/2009 7/15/2009 Air Air Air Air Air Air Air Air Air Air Air 0.019 +/- 0.003 0.023 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.002 0.021 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.002 0.019 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.002 0.021 +/- 0.003 0.015 +/- 0.002 0.013 +/- 0.003 0.016 +/- 0.002 0.023 +/- 0.003 0.015 +/- 0.002 0.015 +/- 0.002 0.008 +/- 0.002 0.010 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.022 +/- 0.003 0.024 +/- 0.003 0.019 +/- 0.003 0.026 +/- 0.005 0.021 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.002 0.019 +/- 0.002 0.016 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.003 0.021 +/- 0.002 0.020 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.002 0.018 +/- 0.002 0.031 +/-0.003 0.015 +/- 0.002 0.015 +/- 0.002 0.009 +/- 0.002 LLD 0.016 +/- 0.002 0.014 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.025 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.002 0.019 +/- 0.003 0.018 +/- 0.002 0.017 +/- 0.003 0.021 +/- 0.003 0.012 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.002 0.010 +/- 0.002 0.017 +/- 0.002 0.010 +/- 0.002 0.013 +/- 0.002 0.022 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.002 0.019 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.021 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 0.009 +/- 0.002 0.016 +/- 0.002 0.010 +/- 0.002 0.013 +/- 0.002 0.021 +/- 0.003 0.020 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 0.016 +/- 0.002 0.018 +/- 0.003 0.021 +/- 0.003 0.013 +/- 0.002 0.018 +/- 0.003 0.017 +/- 0.003 0.009 +/- 0.002 0.016 +/- 0.002 0.011 +/-0.002 0.016 +/- 0.003 C-5
APPENDIX C Air Gross Beta Detail Report 2009 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 7/22/2009 7/29/2009 Air Air 8/5/2009 8/12/2009 8/19/2009 8/26/2009 9/2/2009 9/9/2009 9/16/2009 9/23/2009 9/30/2009 10/7/2009 10/14/2009 10/21/2009 Air Air Air Air Air Air Air Air Air Air Air Air 0.014 +/- 0.002 0.012 +/- 0.002 0.023 +/- 0.003 0.020 +/- 0.002 0.022 +/- 0.003 0.020 +/- 0.003 0.023 +/- 0.003 0.021 +/- 0.003 0.033 +/- 0.003 0.034 +/- 0.003 0.018 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.002 0.014 +/- 0.002 0.028 +/- 0.003 0.026 +/- 0.003 0.036 +/- 0.003 0.030 +/- 0.003 0.021 +/- 0.003 0.019 +/- 0.002 0.017 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.017 +/- 0.002 0.014 +/- 0.002 0.020 +/- 0.003 0.017 +/- 0.003 0.015 +/- 0.002 0.014 +/- 0.002 0.023 +/- 0.003 0.023 +/- 0.003 0.030 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.003 0.033 +/- 0.003 0.035 +/- 0.003 0.018 +/- 0.002 0.016 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.026 +/- 0.003 0.030 +/- 0.003 0.029 +/- 0.003 0.033 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.002 0.017 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.003 0.016 +/- 0.002 0.014 +/- 0.002 0.023 +/- 0.003 0.027 +/- 0.003 0.021 +/-0.003 0.031 +/- 0.003 0.015 +/- 0.002 0.015 +/- 0.002 0.029 +/- 0.003 0.033 +/- 0.003 0.021 +/- 0.003 0.015 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.003 0.015 +/- 0.002 0.021 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.032 +/- 0.003 0.017 +/- 0.002 0.015 +/- 0.002 0.026 +/- 0.003 0.030 +/- 0.003 0.021 +/- 0.002 0.017 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.002 0:015 +/- 0.003 0.024 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 0.035 +/- 0.003 0.015 +/-0.002 0.016 +/- 0.003 0.029 +/- 0.003 0.035 +/- 0.003 0.023 +/- 0.003 0.017 +/- 0.002 0.010 +/- 0.002 0.014 +/- 0.002 0.018 +/- 0.003 aw Aw No Invil"M an ANN a--W
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Air Gross Beta Detail Report 2009 APPENDIX C Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. 50-440/50-441 Sample Frequency is: Weekly Results in pCi/m3 +/-
2 Sigma Location 1
3 4
5 6
Collection Date Sample Type 7
35 10/28/2009 Air 0.023 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 11/4/2009 11/11/2009 11/18/2009 11/25/2009 12/2/2009 12/9/2009 12/16/2009 12/23/2009 12/30/2009 Air Air Air Air Air Air Air Air Air 0.017 +/- 0.003 0.018 +/- 0.003 0.014 +/- 0.002 0.034 +/- 0.003 0.030 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.003 0.033 +/- 0.003 0.033 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.003 0.021 +/-0.003 0.020 +/- 0.003 0.031 +/- 0.003 0.029 +/- 0.003 0.032 +/- 0.003 0.032 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.020 +~0. 003, 0.0 15 +-0.002 9.916 +-0.003 0.033 +/--0.003 0.032 +-0.003 0.022 +-0.003 0.022 +/m. 0.002 0.032 +-0:'003 0.033 +-0.003 0.026 +-0.003 0.022 +-0.002 0.025 +-0.003 0.022 +-0.002 0.034 +-0.003 0.033 +-0.003 0.035 +-0.003 0.034 +-0.003 0.018 +-0.003 0.016 +-0.002 0.016 +/- 0.002 0.030 +/- 0.003 0.020 +/- 0.003 0.033 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.027 +/- 0.003 0.031 +/- 0.003 0.020 +/- 0.003 0.015 +/- 0.002 0.031 +/- 0.003 0.021 +/- 0.003 0.035 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.003 0.031 +/- 0.003 0.033 +/- 0.003 0.019 +/- 0.002 0.017 +/- 0.002 0.032 +/- 0.003 0.024 +/- 0.003 0.035 +/- 0.003 0.025 +/- 0.003 0.026 +/- 0.003 0.032 +/- 0.003 0.031 +/- 0.003 0.021 +/- 0.003 C-7
APPENDIX C Air Iodine Detail Report 2009 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 11-131 1
1 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 1/7/2009 1/14/2009 1/21/2009 1/28/2009 2/4/2009 2/11/2009 2/18/2009 2/25/2009 3/4/2009 3/11/2009 3/18/2009 3/25/2009 4/1/2009 4/8/2009 4/15/2009
.4/22/2009 4/29/2009 5/,6/2009 5/13/2009 5/20/2009 5/37/2009 6/3/2009 6/10/2009 6/17/2009 6/24/2009 7/8/2009 7/8/2009 7/15/2009 7/22/2009 7/29/2009 8/5/2009 8/12/2009 8/19/2009 8/26/2009
< 0.008
< 0.006
< 0.009
< 0.009
< 0.004
< 0.010
< 0.004
< 0.006
< 0.005
< 0.008
< 0.008
< 0.006
< 0.005
< 0.007
< 0.009
< 0.004
< 0.004
< 0.006
< 0.006
< 0.004
< 0.005
< 0.004
< 0.007
< 0.005
~~0.007~~
< 0.008
< 0.005
< 0.006
< 0.008
< 0.004
< 0.007
< 0.005
< 0.009
< 0.005 S*"W Af 10, AM OW -if 1-1 t"
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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 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 9/2/2009 9/9/2009 9/16/2009 9/23/2009 9/30/2009 10/7/2009 10/14/2009 10/21/2009 10/28/2009 11/4/2009 11/11/2009 11/18/2009 11/25/2009 12/2/2009 12/9/2009 12/16/2009 12/23/2009 12/30/2009 1/7/2009 1/14/2009 1/21/2009 1/28/2009 2/4/2009 2/11/2009 2/18/2009 2/25/2009 3/4/2009 3/11/2009 3/18/2009 3/25/2009 4/1/2009 4/8/2009 4/15/2009 0.011 0.008 0.007 0.009 0.006 0.009 0.012 0.009 0.009 0.009 0.006 0.007 0.005 0.006 0.005 0.008 0.006 0.008 0.007 0.005 0.008 0.008 0.003 0.009 0.004 0.005 0.005 0.008 0.008 0.005 0.005 0.007 0.008 C-9
APPENDIX C Air Iodine Detail Report 2009 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 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
Sample Type 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 Air Collection Date 1-13 1 4/22/2009 4/29/2009 5/6/2009 5/13/2009 5/20/2009 5/27/2009 6/3/2009 6/10/2009 6/17/2009 6/24/2009 7/1/2009 7/8/2009 7/15/2009 7/22/2009 7/29/2009 8/5/2009 8/12/2009 8/19/2009 8/26/2009 9/2/2009 9/9/2009 9/16/2009 9/23/2009 9/30/2009 10/7/2009 10/14/2009 10/21/2009 10/28/2009 11/4/2009 11/11/2009 11/18/2009 11/25/2009 12/2/2009 12/9/2009 12/16/2009 0
< 0.005
< 0.004
< 0.006
< 0.006
< 0.004
< 0.005
< 0.004
< 0.007
< 0.005
< 0.007
< 0.007
< 0.005
< 0.006
< 0.008
< 0.004
< 0.007
< 0.005
< 0.009
< 0.005
< 0.012
< 0.008
< 0.007
< 0.009
< 0.006
< 0.009
< 0.012
< 0.008
< 0.009
< 0.009
< 0.006
< 0.007
< 0.005
< 0.006
< 0.005
< 0.008 M
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-Air Iodine Detail Rej~hrt 2009 APPENIX CRadiological Environmental Monitoring Program Detail D APPNDI CPerry Nuclear Power Plant, Lake County Ohio Docket no.: 50.
Sample Frequency is: Weekly Results in pCi/m3 +/- 2 S a-" I m
M W
m Location Sample Type Collection Date 1-13 1 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 12/23/2009 12/30/2009 1/7/2009 1/14/2009 1/21/2009 1/28/2009 2/4/2009 2/11/2009 2/18/2009 2/25/2009 3/4/2009 3/11/2009 3/18/2009 3/25/2009 4/1/2009 4/8/2009 4/15/2009 4/22/2009 4/29/2009 5/6/2009 5/13/2009 5/20/2009 5/27/2009 6/3/2009 6/10/2009 6/17/2009 6/24/2009 7/1/2009 7/8/2009 7/15/2009 7/22/2009 7/29/2009 8/5/2009
< 0.006
< 0.008 0.007 0.005 0.008 0.008 0.004 0.009 0.004 0.005 0.005 0.007 0.0018 0.005 0.005 0.007 0.008 0.004 0.004 0.006 0.006 0.004 0.005 0.004 0.007 0.005 0.007 0.008 0.005 0.007 0.008 0.004 0.007 C-1Il
APPENDIX C Air Iodine Detail Report 2009 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 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
Sample Type Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Collection Date 8/12/2009 8/19/2009 8/26/2009 9/2/2009 9/9/2009 9/16/2009 9/23/2009 9/30/2009 10/7/2009 10/14/2009 10/21/2009 10/28/2009 11/4/2009 11/11/2009 11/18/2009 11/25/2009 12/2/2009 12/9/2009 12/16/2009 12/23/2009 12/30/2009 1-131 0.005 0.009 0.005 0.012 0.009 0.007 0.009 0.006 0.009 0.012 0.009 0.009 0.009 0.006 0.007 0.005 0.006 0.005 0.008 0.006 0.008 0.007 0.005 0.008 0.008 0.003 0.009 0.004 0.005 0.005 0.007 0.008 0.005 0.005 5
5 5
5 5
5 5
5 5
5 5
5 5
Air Air Air Air Air Air Air Air Air Air Air Air Air 1/7/2009 1/14/2009 1/21/2009 1/28/2009 2/4/2009 2/11/2009 2/18/2009 2/25/2009 3/4/2009 3/11/2009 3/18/2009 3/25/2009 4/1/2009 K
=
-ý i-
-m NO AM-M
=
M M
M
=
M APPENDIX C M
M M
M Air Iodine Detail Report 2009 Radiological Environmental Monitoring Program Detail E Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50 Sample Frequency is: Weekly Results in pCi/m3 +/- 2 S
=
M M
=
=
m Location 5
5
.5 5
5 5
5 5
5 5
5 5
5 5
5 5
5 5
5 5
5 5
5 5
5 5
5 5,
5 5
5 5
5 5
Sample Type Collection Date 1-131 Air Air Air Air Air Air Air Air Air Air Air Ai-ý Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air 4/8/2009 4/15/2009 4/22/2009 4/29/2009 5/6/2009 5/13/2009 5/20/2009 5/27/2009 6/3/2009 6/10/2009 6/17/2009 6/24/2009 7/1/2009 7/8/2009 7/15/2009 7/22/2009 7/29/2009 8/5/2009 8/12/2009 8/19/2009 8/26/2009 9/2/2009 9/9/2009 9/16/2009 9/23/2009 9/30/2009 10/7/2009 10/14/2009 10/21/2009 10/28/2009 11/4/2009 11/11/2009 11/18/2009 11/25/2009 0.006 0.008 0.004 0.004 0.006 0.006 0.004 0.005 0.004 0.007 0.005 0.006 0.007 0.005 0.006 0.008 0.004 0.006 0.005 0.009 0.005 0.011 0.008 0.007 0.008 0.005 0.008 0.011 0.008 0.009 0.009 0.006 0.008 0.005 C-13
APPENDIX C Air Iodine Detail Report 2009 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
5 5
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 Sample Type 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 Collection Date 12/2/2009 12/9/2009 12/16/2009 12/23/2009 12/30/2009 1-131 0.006 0.005 0.008 0.006 0.008 1/7/2009 1/14/2009 1/21/2009 1/28/2009 2/4/2009 2/11/2009 2/18/2009 2/25/2009 3/4/2009 3/11/2009 3/18/2009 3/25/2009 4/1/2009 4/8/2009 4/15/2009 4/22/2009 4/29/2009 5/6/2009 5/13/2009 5/20/2009 5/27/2009 6/3/2009 6/10/2009 6/17/2009 6/24/2009 7/1/2009 7/8/2009 7/15/2009 7/22/2009 0.008 0.005 0.009 0.008 0.004 0.010 0.004 0.006 0.005 0.008 0.008 0.006 0.006 0.007 0.009 0.005 0.004 0.006 0.007 0.005 0.006 0.004 0.008 0.005 0.007 0.008 0.006 0.007 0.009
=
=
M m=
=
=
=
m m
m
-=
=
m
APPENDIX C Air Iodine Detail Report 2009 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
=
M M
=
Location Sample Type Collection Date 1-131 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 7/29/2009 8/5/2009 8/12/2009 8/19/2009 8/26/2009 9/2/2009 9/9/2009 9/16/2009 9/23/2009 9/30/2009 10/7/2009 10/14/2009 10/21/2009 10/28/2009 11/4/2009 11/11/2009 11/18/2009 11/25/2009 12/2/2009 12/9/2009 12/16/2009 12/23/2009 12/30/2009 1/7/2009 1/14/2009 1/21/2009 1/28/2009 2/4/2009 2/11/2009 2/18/2009 2/25/2009 3/4/2009 3/11/2009 0.004 0.007 0.006 0.009 0.005 0.012 0.009 0.007 0.009 0.006 0.009 0.012 0.009 0.009 0.009 0.006 0.008 0.005 0.006 0.005 0.008 0.006 0.008 0.008 0.005 0.009 0.008 0.004 0.010 0.004 0.006 0.005 0.008 C-15
APPENDIX C Air Iodine Detail Report 2009 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 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 3/18/2009 3/25/2009 4/1/2009 4/8/2009 4/15/2009 4/22/2009 4/29/2009 5/6/2009 5/13/2009 5/20/2009 5/27/2009 6/3/2009 6/10/2009 6/17/2009 6/24/2009 7/1/2009 7/8/2009 7/15/2009 7/22/2009 7/29/2009 8/5/2009 8/12/2009 8/19/2009 8/26/2009 9/2/2009 9/9/2009 9/16/2009 9/23/2009 9/30/2009 10/7/2009 10/14/2009 10/21/2009 10/28/2009 11/4/2009 11/11/2009 0.008 0.006 0.005 0.007 0.009 0.005 0.004 0.006 0.007 0.005 0.006 0.004 0.008 0.005 0.007 0.008 0.005 0.006 0.008 0.004 0.006 0.005 0.009 0.005 0.011 0.008 0.007 0.008 0.005 0.008 0.012 0.008 0.009 0.009 0.006
=
M
=-
=
=
M=
=-
mmm
Air Iodine Detail Report 2009 Radiological Environmental Monitoring Program Detail Data APPENDIX C 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 11/18/2009
< 0.008 7
Air 11/25/2009
< 0.005 7
Air 12/2/2009
< 0.006 7
Air 12/9/2009
< 0.005 7
Air 12/16/2009
< 0.008 7
Air 12/23/2009
< 0.006 7
Air 12/30/2009
< 0.008 35 Air 1/7/2009
< 0.009 35 Air 1/14/2009
< 0.010 35 Air 1/21/2009
< 0.009 35 Air 1/28/2009
< 0.009 35 Air 2/4/2009
< 0.005 35 Air 2/11/2009
< 0.006 35 Air 2/18/2009
< 0.007 35 Air 2/25/2009
< 0.004 35 Air 3/4/2009
< 0.005 35 Air 3/11/2009
< 0.011 35 Air 3/18/2009
< 0.007 35 Air 3/25/2009
< 0.008 35 Air 4/1/2009
< 0.008 35 Air 4/8/2009
< 0.010 35 Air 4/15/2009
< 0.009 35 Air 4/22/2009
< 0.021 35 Air 4/29/2009
< 0.007 35 Air 5/6/2009
< 0.009 35 Air 5/13/2009
< 0.011 35 Air 5/20/2009
< 0.010 35 Air 5/27/2009
< 0.013 35 Air 6/3/2009
< 0.010 35 Air 6/10/2009
< 0.006 35 Air 6/17/2009
< 0.008 35 Air 6/24/2009
< 0.006 35 Air 7/1/2009
< 0.010 C-17
APPENDIX C Air Iodine Detail Report 2009 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 Sample Type 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 Collection Date 7/8/2009 7/15/2009 7/22/2009 7/29/2009 8/5/2009 8/12/2009 8/19/2009 8/26/2009 9/2/2009 9/9/2009 9/16/2009 9/23/2009 9/30/2009 10/7/2009 10/14/2009 10/21/2009 10/28/2009 11/4/2009 11/11/2009 11/18/2009 11/25/2009 12/2/2009 12/9/2009 12/16/2009 12/23/2009 12/30/2009 1-131 0.011 0.012 0.005 0.008 0.008 0.011 0.014 0.010 0.010 0.012 0.014 0.006 0.008 0.008 0.010 0.006 0.006 0.010 0.006 0.006 0.015 0.009 0.007 0.006 0.008 0.009 M mmnm Mm M
M MI" m M
M M-mm M
M
SM M m =
m- =
Mm
=
=
=
=
n APPENDIX C Fish Gamma Spectral Detail Report 2009 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 smallmouth bass 7/21/2009
< 16.17 12.68
< 20.61
< 20.18
< 57.79 25 white bass 25 white perch 25 yellow perch 32 smallmouth bass 32 white bass 32 white perch 32 yellow perch 7/21/2009 7/21/2009 7/21/2009 7/21/2009 7/21/2009 7/21/2009 7/21/2009 1,637.30 +/- 462.90
< 4.79 846.93 +/- 284.90
< 14.31 1,251.45 +/-/- 280.67
< 6.49 1,584.70 +/- 289.50
< 22.35 1,246.00 +/- 372.10
< 11.85 1,197.30 +/-/- 287.40
< 8.63 1,559.70 +/-/- 316.60
< 23.64 1,056.50 +/-/- 426.70
< 18.66 13.68 13.46
< 8.54
< 20.09
< 10.26
< 13.14
< 12.96
< 18.72
< 14.36
< 9.76
< 11.21
< 16.06
< 12.58
< 14.46
< 24.20 18.28 10.60 19.72
< 31.20 11.24
< 20.66 18.24 19.83 13.45
< 36.15
< 11.49
< 22.33 17.34
< 31.52
< 20.30
< 21.13
< 9.42
< 20.14 15.94 14.77 17.73
< 11.69
< 40.02
< 11.56
< 39.59
< 31.87
< 25.48
< 22.57 C-19
APPENDIX C Location Sample Type Collection Date 2
collard greens kale swiss chard turnip greens kale swiss chard turnip greens collard greens swiss chard turnip greens kale 7/8/2009 8/6/2009 8/6/2009 8/6/2009 9/14/2009 9/14/2009 9/14/2009 10/13/2009 10/13/2009 10/13/2009 11/10/2009 Food Products Gamma Spectral Detail Report 2009 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
< 71.74
< 5.93
< 4.87
< 14.75 4,687.90 +/- 293.10
< 126.01
< 7.67
< 8.48
< 14.84 4,706.60 +/- 332.20 199.97 +/- 118.20 11.51
< 7.93
< 17.84 5,744.90 +/- 495.10 315.66 +/-113.90
< 8.59
< 7.92
< 11.41 5,772.30 +/- 368.30
< 107.99
< 5.59
< 9.35
< 17.74 4,730.80 +/- 343.70 251.01 +/- 102.80
< 6.61.
< 8.53
< 13.33 5,152.70+/-347.70 201.01 +/- 98.54
< 9.67
< 9.57
< 16.79 4,937.20 +/- 338.40 529.71 +/- 136.10
< 12.05
< 8.32
< 25.64 4,615.40 +/- 353.40 551.51 +/- 123.20
< 9.17
< 10.20
< 19.84 6,013.30+/-386.40 1,600.70+/- 160.10
< 5.14
< 7.41
< 15.76 6,135.70+/- 363.70 271.26+/- 101.20
< 6.48
< 6.41
< 14.62 4,594.90 +/- 296.90 m -
-m m m
m
[
Cs-134 Cs-137
< 558
< 798
< 8.07
< 8.81
< 9.03
< 9.31
< 9.13
< 7.66 12.51 11.32 10.16
~~7.17~~
< 8.58 16.71 12.21 10.08
< 8.46 12.35 11.53 13.12 10.00 8.22 M
m =
=
=
U m
m m
=m
=
=
=
M
=
=
-=
=
=
=
=
=
=
=
=
=
Food Products Gamma Spectral Detail Report 2009 APPENDIX C 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 2
swiss chard 11/10/2009 530.50 +/-119.10
< 9.68
< 7.18
< 7.94
< 9.57
< 18.64 6,382.60+/-336.10 16 beet greens 7/8/2009 131.24+/-76.63
< 9.21
< 5.98
< 8.17
< 10.04
< 17.05 5,756.80++/-- 362.10 16 swiss chard 7/8/2009
< 83.96
< 6.72
< 6.35
< 7.42
< 8.57
< 13.58 5,596.50 +/- 363.70 16 turnip greens 7/8/2009
< 107.15 10.19
< 4.91
< 9.36
< 7.74
< 18.00 5,521.30+/- 354.90 16 collard greens 8/6/2009
< 69.89
< 8.60
< 7.14
< 8.16
< 7.77
< 18.69 4,206.70 +/- 292.90 16 swisschard 8/6/2009 475.00+/- 151.10 13.41
< 15.12
< 11.76 11.72
< 13.24 6,022.80 +/- 535.30 16 turnip greens 8/6/2009 433.41 +/- 105.30
< 4.33
< 6.81
< 7.44
< 6.28
< 13.76 4,784.00 +/- 334.40 16 beet greens 9/14/2009 348.28 +/- 116.20
< 7.93
< 8.45
< 8.42 11.70 16.91 5,821.70 +/- 369.40 16 collardgreens 9/14/2009
< 97.21
< 10.19
< 6.60
< 10.57 12.02 K
16.87 4,641.70 +/-388.10 16 swisschard 9/14/2009 251.13+/- 145.70
< 6.42
< 11.80
< 13.48 13.11
< 24.75 5,115.40 +/- 389.30 C-21
APPENDIX C Location Sample Type Collection Date 16 16 16 beet greens swiss chard turnip greens 10/13/2009 10/13/2009 10/13/2009 18 18 18 18 18 18 18 beet greens turnip greens beet greens collard greens swiss chard beet greens collard greens 8/6/2009 8/6/2009 9/14/2009 9/14/2009 9/14/2009 10/13/2009 10/13/2009 Food Products Gamma Spectral Detail Report 2009 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 pCilkg wet +/- 2 Sigma Be-7 Co-58 Co-60 1-131 K-40 966.20+/- 155.40
< 6.71
< 8.19
< 17.72 7,260.20 +/- 441.90 432.12+/- 107.10
< 2.64
< 10.99
< 15.39 5,379.60 /-357.70 1,421.80+/- 195.60
< 7.11
< 12.82
< 22.13 6,758.70 +/-409.00 434.62+/- 133.60
< 11.96
< 5.38
< 12.98 8,648.60 +/-472.60 510.99+/- 152.30
< 8.88
< 11.85
< 15.48 5,426.50 /-377.30 446.75 +/- 164.90
< 13.79
< 13.38
< 23.68 10,368.00 +/- 491.20
< 81.25
< 7.45
< 8.27
< 14.98 5,554.40 +/- 313.20
< 171.06
< 7.63
< 6.01
< 13.58 8,768.80+/-381.09 953.93+/- 177.10
< 5.75
< 7.35
< 22.13 7,361.70 +/- 457.80 366.95 +/- 143.10
< 10.85
< 14.27
< 24.90 4,589.20 +/- 366.80 7.23 7.25 11.96 Cs-134 Cs-137 10.92 7.86 12.20
< 12.37
< 12.24
< 9.93
< 7.59
< 10.59
< 8.91
< 10.35 10.23
< 11.77
< 13.23 8.58 10.85 12.41 12.30
==
=
mmmim mmm==
=
=
W
=
=
M
=
=
=
=
=
M Min mDi A D Food Products Gamma Spectral Detail Report 2009 APPENDIXC Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/kg wet +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 18 swiss chard 10/13/2009 519.45+/- 133.50
< 12.67
< 7.22
< 9.76
< 11.51
< "17.43 5,730.80 +/- 405.30 18 collard greens 11/10/2009 277.90+/- 82.58
< 7.87
< 7.74
< 9.98
< 10.22
< 15.03 4,810.90+/- 307.60 18 swiss chard 11/10/2009 421.49+/-117.10
< 9.00
< 11.74
< 7.61
< 9.13
< 13.81 6,967.00 +/- 390.70 18 turnip greens 11/10/2009 639.27 +/- 123.30
< 4.67
< 6.16
< 8.11
< 11.34
< 19.01 4,859.50 +/- 329.60 20 tumrip greens 8/6/2009 395.95 +/-124.00
< 9.59
< 6.14
< 10.15
< 13.69
< 14.47 6,082.90 +/- 367.80 20 turnip greens 9/14/2009 402.35 +/- 107.00
< 7.33
< 8.82
< 9.33
< 9.55
< 18.56 5,284.70 +/- 347.30 20 turnip greens 10/13/2009 1,136.50 +/- 143.60
< 9.70
< 6.75
< 8.65
< 11.60
< 21.82 5,541.90 +/-371.20 20 turnip greens 11/10/2009 1,301.60 +/- 148.90
< 4.83
< 6.80
< 8.02
< 11.60
< 14.74 4,953.90 +/-331.00 37 beetgreens 7/8/2009
< 110.43
< 8.86
<. 11.86
< 10.80
< 10.11
< 15.28 7,335.10+/-419.40 37 collard greens 7/8/2009
< 98.01
< 5.01
< 5.82
< 7.06
< 9.79
< 15.09 4,023.40 +/- 286.20 C-23
APPENDIX C Location Sample Type turnip greens beet greens collard greens swiss chard beet greens swiss chard turnip greens beet greens collard greens swiss chard collard greens Collection Date 7/8/2009 8/6/2009 8/6/2009 8/6/2009 9/14/2009 9/14/2009 9/14/2009 10/13/2009 10/13/2009 10/13/2009 11/10/2009 Food Products Gamma Spectral Detail Report 2009 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-40 144.69+/- 71.55
< 8.91
< 4.33
< 16.46 5,838.70 +/-330.30 265.40+/- 131.40
< 7.97
< 12.23
< 11.86 5,325.30 +/-361.80
< 85.51
< 4.81
< 9.36
< 11.00 3,724.30 +/- 322.50 215.31 +/- 128.70
< 5.33
< 6.34
< 13.49 6,465.40+/- 386.70 375.37+/- 109.40
< 10.06
< 11.16
< 17.49 5,961.00 /-341.60 347.57+/- 124.10
< 5.92
< 10.41
< 19.07 5,801.20+/-405.00 463.36+/- 159.40
< 11.42
< 11.62
< 24.55 6,006.70 +/-405.90 774.79+/
153.90
< 10.60
< 7.14
< 12.94 5,023.70+/- 367.10 256.99+/- 100.60
< 8.13
< 6.01
< 14.24 3,120.70 +/- 270.00 623.25+/- 144.10
< 11.59
< 15.56
< 19.45 6,435.90 /-424.30
< 120.48
< 8.20
< 5.33
< 12.74 3,043.25+/- 186.11 Cs-134 Cs-137
< 7.98
< 9.48
< 10.21
< 7.44
< 9.57
< 9.45
< 10.53
< 8.12
< 7.86
< 14.56
< 5.27
< 7.19
< 8.40
< 9.01
< 9.50 10.64 15.01
< 14.05
< 9.18
< 10.51
< 8.25
< 9.37
=
=
=
APPENDIX C Food Products Gamma Spectral Detail Report 2009 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 swiss chard 11/10/2009 685.06 +/-105.30
< 8.52
< 9.92
< 9.87
< 9.95
< 10.21 6,531.00 -363.10 37 turnip greens 11/10/2009 1,313.10 +/- 148.70
< 11.84
< 9.95
< 8.38
< 9.90
< 14.16 4,870.50+/-337.30 70 beet greens 8/6/2009 365.69 +/- 87.96
< 6.83
< 8.83
< 5.91
< 10.48
~~7.64 5,988.50/- 321.20 70 collard greens 8/6/2009~~
< 66.96
< 3.85
< 7.11
< 8.89
< 10.18
~~17.82 3,943.50+/- 338.50 70 turnip greens 8/6/2009 963.97 +1/- 139.80~~
< 1131
< 12.54
< 6.76
< 10.66
< 12.06 5,214.40 +/- 353.50 70 beet greens 9/14/2009 636.67 +/- 127.20
< 8.39
< 7.37
< 7.91
< 10.95
< 15.03 9,186.10+/-436.70 70 collard greens 9/14/2009 232.78 +/- 119.80
< 4.73
< 6.95
< 10.02
< 11.69
< 21.37 4,131.60 +/- 328.10 70 swiss chard 9/14/2009 350.48 +/- 112.20
< 7.70
< 8.43
< 9.68
< 9.74 16.41 7,690.70 +/- 396.80 70 collard greens 10/13/2009 607.41 +/- 138.99
< 9.53
< 7.72
< 7.01 10.72
< 14.27 4,495.80 +/- 335.84 70 swiss chard 10/13/2009 570.71 +/- 164.70 10.80
< 15.73
< 13.35 16.68
< 27.15.
8,332.20 +/- 490.50 C-25
APPENDIX C Location Sample Type Food Products Gamma Spectral Detail Report 2009 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 Collection Date Be-7 1-131 Co-58 K-40 70 tumip greens 70 collard greens 70 swiss chard 70 turnip greens 10/13/2009 11/10/2009 11/10/2009 11/10/2009 1,461.80 +/- 205.80
< 24.10 332.88 +/- 153.20 18.83 585.94 +/- 104.30 15.84 1,438.50 +/- 167.80
< 20.29 13.33 5,118.10 +/- 383.50
< 8.19 3,466.80 +/- 299.50
< 9.07 9,161.60 +/-415.90
< 8.05 4,617.70 +/- 386.90 Co-60
< 6.12
< 6.05
< 9.12
< 11.88 Cs-134 12.19 11.47
< 7.49
< 10.70 Cs-137
< 11.48
< 7.06 10.00
< 8.00 m
-n
-m----n m,!mnn
mB m
nm B/Rm II m
Milk Gamma Spectral Detail Report 2009 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 19 Milk 4/6r/2f009 15 4
4 1 750+/- 112 3
Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk 4/20/2009 5/4/2009 5/18/2009 6/1/2009 6/16/2009 7/6/2009 7/20/2009 8/3/2009 8/17/2009 9/8/2009
< 12
< 15
< 15
< 19
< 19
< 13
< 18
< 12
< 17
< 11
< 3
< 3
< 2
< 4
< 3
< 3
< 4
< 4
< 3
< 4
< 4
< 4
< 2
< 4
< 3
< 4
< 3
< 5
< 4
< 4 1,775 +/-/- 126 1,909 +/- 121 1,831 +/- 131 1,873 +/- 133 1,786+/- 125 1,728 +/- 133 1,875 +/-/- 125 1,982 +/- 140 2,058 +/- 138 1,950+/- 130
< 2
< 3
< 2
< 4
< 2
< 3
< 3
< 3
< 3
< 2 C-27
APPENDIX C Milk Gamma Spectral Detail Report 2009 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 18 18 18 18 Milk Milk Milk Milk Milk 9/21/2009 10/5/2009 10/19/2009 11/2/2009 12/7/2009 16
< 24 10 19 15
< 4
< 3
< 3
< 3
< 3 1,987 +/- 137 1,924 +/- 134 2,095 +/- 136 1.782 +/- 125 1,471 +/- 115 41 41 41 41 41 Milk Milk Milk Milk Milk 4/6/2009 4/20/2009 5/4/2009 5/18/2009 6/1/2009 11 14 12 21 18
< 2
< 2
< 3
< 4
< 4
< 3
< 3
< 2
< 4
< 3 1,552 +/- 81 1,795 +/- 112 1.741 +/- 119 1,709 +/- 113 1,809 +/- 138
< 3
< 4
< 2
< 5
< 6
=
M W
=
W
=
W M
M W
M W
Milk Gamma Spectral Detail Report 2009 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 41 Milk 6/16/2009
< 17
< 3
< 4 1,882+/-127
< 2 41 Milk 7/6/2009
< 19
< 3
< 4 1,729 +/-129
< 4 41 Milk 7/20/2009
< 15
< 2
< 4 1,661 +/-107
< 2 41 Milk 8/3/2009
< 20
< 3
< 3 1,954 +/- 130
< 5 41
-Milk 8/17/2009
< 11
< 3
< 3 1,752+/- 129
< 4 41 Milk 9/8/2009
< 21
< 2
< 4 1,703 +/- 130
< 4 51 Milk 1/5/2009
< 22
< 4
< 4 1,331 +/-117
< 5 51 Milk 2/2/2009
< 20
< 5
< 7 565+/-114
< 4 51 Milk 3/2/2009
< 13
< 3
< 4 1,322+/-115
< 2 51 Milk 4/6/2009 18
< 3
< 4 1,217+/-106
< 3 C-29
APPENDIX C Milk Gamma Spectral Detail Report 2009 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 4/20/2009 15
< 4
< 5 1439+/-119
< 4 Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk 5/4/2009 5/18/2009 6/1/2009 6/16/2009 7/6/2009 7/20/2009 8/3/2009 8/17/2009 9/8/2009 9/21/2009
< 13
< 30
< 19
< 12
< 17
< 16
< 10
< 14
< 15
< 13
< 2
< 5
< 2
< 2
< 2
< 3
< 2
< 3
< 3
< 3
< 3
< 4
< 3
< 3
< 3
< 4
< 3
< 3
< 2
.< 2 1,322 +/-/- 103 1,375 +/- 119 1,406 +/-/- 118 1,404 +/-/- 105 1,244 +/- 92 1,354 +/- 110 967 +/- 95 930 +/-85 1,332 +/- 113 1,269 +/- 109
< 2
< 7
< 2
< 4
< 2
< 3
< 3
< 4
< 2
< 2 m
m-mm m
-_mi m
n m mm
=
W M
W M
m
=
=
M M
M W
W
=
m APPENDIX C Milk Gamma Spectral Detail Report 2009 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 10/5/2009 11
< 3
< 4 1328R/- 104
< 3 51 51 51 Milk Milk Milk 10/19/2009 11/2/2009 12/7/2009 12 21 13
< 3
< 3
< 4
< 4
< 3
< 3 1,133 +/- 90 1,150 +/- 99 1,266 +/- 108 3
4 3
61 61 61 61 61 61 Milk Milk Milk Milk Milk Milk 5/4/2009 5/18/2009 6/1/2009 6/16/2009 7/7/2009 7/20/2009
< 10
< 24
< 17
< 3
< 5
< 4
< 4
< 4
< 4
< 4
< 4
< 4 1,679+/- 116 1,747 +/- 126 1,673 +/- 130 1,844 +/- 125 1,899 +/- 127 1,855 +/- 128
< 2
< 4
< 3
< 3
< 3
< 4 20 21 27 4
3 3
C-31
APPENDIX C Milk Gamma Spectral Detail Report 2009 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 8/3/2009 8/17/2009 9/8/2009 9/21/2009 10/5/2009 10/19/2009 11/2/2009 16
< 25 19 17
< 24 18
< 25
< 3
< 2
< 3
< 3
< 3
< 3
< 2
< 4
< 5
< 3
< 3
< 5
< 4
< 4 1,956 +/- 99 2,044 +/- 139 1,980 +/- 138 1,928 +/- 127 1,979 +/- 128 1,997 +/- 137 1,744 +/- 124
< 3
< 4
< 3
< 2
< 3
< 2
< 2 m
-mNpIl oin rmil...
m m-
=nii M
s M
M M
i, M
M M
APPENDIX C Milk Iodine Detail Report 2009 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 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 41 41 41 41 41 41 41 41 41 41 41 41 41 41 51 51 Sample Type Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Collection Date 4/6/2009 4/20/2009 5/4/2009 5/18/2009 6/1/2009 6/16/2009 7/6/2009 7/20/2009 8/3/2009 8/17/2009 9/8/2009 9/21/2009 10/5/2009 10/19/2009 11/2/2009 12/7/2009 1-131 Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk 1/5/2009 2/2/2009 3/2/2009 4/6/2009 4/20/2009 5/4/2009 5/18/2009 6/1/2009 6/16/2009 7/6/2009 7/20/2009 8/3/2009 8/17/2009 9/8/2009 1/5/2009 2/2/2009
< 0.42
< 0.23
< 0.36
< 0.47
< 0.38
< 0.31
< 0.34
< 0.37
< 0.32
< 0.46
< 0.29
< 0.24
< 0.21
< 0.30
< 0.32
< 0.25
< 0.35
< 0.36
< 0.36
< 0.38
< 0.34
< 0.28
< 0.34
< 0.39
< 0.32
< 0.44
< 0.35
< 0.38
< 0.33 C-33
APPENDIX C Milk Iodine Detail Report 2009 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 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk 3/2/2009 4/6/2009 4/20/2009 5/4/2009 5/18/2009 6/1/2009 6/16/2009 7/6/2009 7/20/2009 8/3/2009 8/17/2009 9/8/2009 9/21/2009 10/5/2009 10/19/2009 11/2/2009 12/7/2009
< 0.30
< 0.27
< 0.26
< 0.37
< 0.39
< 0.29
< 0.31
< 0.40
< 0.33
< 0.37
< 0.44
< 0.39
< 0.29
< 0.33
< 0.32
< 0.47
< 0.25 61 Milk 1/5/2009 61 Milk 2/2/2009 61 Milk 3/2/2009 61 Milk 4/6/2009 61 Milk 4/20/2009 61 Milk 5/4/2009
< 0.36 61 Milk 5/18/2009
< 0.36 61 Milk 6/1/2009
< 0.44 61 Milk 6/16/2009
< 0.28 61 Milk 7/7/2009
< 0.30 61 Milk 7/20/2009
< 0.32 61 Milk 8/3/2009
< 0.42 61 Milk 8/17/2009
< 0.36 61 Milk 9/8/2009
< 0.37 61 Milk 9/21/2009
< 0.32 61 Milk 10/5/2009
< 0.22 61 Milk 10/19/2009
< 0.30
MiMk Iodine Detail Report 2009 Radiological Environmental Monitoring Program Detail Data APPENDIX C 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 61 Milk 11/2/2009
< 0.31 C-35
APPENDIX C Sediment Gamma Spectral Detail Report 2009 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Annually Results in pCi/kg dry +/-
2 Sigma Location Sample Type Collection Date Co-58 Co-60 Cs-134 Cs-137 K-40 25 25 Sediment Sediment 6/15/2009 10/6/2009 23.72 20.87
< 16.60
< 6.31 17.18 10.51 LLD 301.33 +/- 19.50 11,058.00+!- 609.30 16,865.00 +/- 442.25 26 26 Sediment Sediment 6/15/2009 10/6/2009 19.84 25.10 13.78 14.63 15.97 15.76 LLD LLD 13,355.00 +/-/- 751.30 14,895.00 +/- 698.50 27 27 32 32 Sediment Sediment Sediment Sediment 6/15/2009 10/6/2009 6/15/2009 10/6/2009 27.60 27.48 38.12 35.04
< 20.38
< 16.12
< 36.50
< 36.90
< 23.28
< 22.86
< 44.08
< 34.66 LLD 341.42 +/- 51.27 678.91 +/- 68.42 699.30 +/- 65.48 15,120.00 +/- 799.20 23,037.00 +/- 922.80 24,592.00 +/- 1,294.00 23,808.00 +/- 1,195.00 64 Sediment 6/18/2009 18.85
< 17.01
< 21.12
< 14.71 8,974.80 +/- 642.40 ml ini lm n
mmm u
-m -
-W W m0 M
M W M m
M M
M M
m W, M 0- MW APPENDIX C Sediment Gamma Spectral Detail Report 2009 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Annually Results in pCi/kg dry +/- 2 Sigma Location Sample Type Collection Date Co-58 Co-60 Cs-134 Cs-137 K-40 64 Sediment 10/13/2009 11.73
< 8.65
< 7.70
< 11.39 7,208.50+/-438.70 65 Sediment 10/13/2009
< 8.72
< 9.83
< 9.22
< 14.89 8,902.10 +/- 490.40 C-37
APPENDIX C TLD Gamma Dose Detail Report 2009 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 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 10.92
+/-
0.69 9.56
+/-
0.80 11.16
+/-
0.76 9.88
+/-
1.04 11.21
+/-
0.63 10.39
+/-
1.02 11.72
+/-
0.67 11.25
+/-
0.59 11.86
+/-
0.51 12.03
+/-
0.61 12.38
+/-
0.55 12.03
+/-
0.57 10.76
+/-
0.46 11.34
+/-
0.56 11.74
+/-
1.10 11.96
+/-
0.75 12.23
+/-
0.56 12.99
+/-
0.55 13.40
+/-
0.85 13.07
+/-
0.61 11.89
+/-
0.55 11.97
+/-
0.64 12.99
+/-
0.70 12.87
+/-
0.69 10.87
+/-
0.73 11.89
+/-
0.84 11.53
+/-
0.72 12.01
+/-
0.52 10.43
+/-
0.43 M
0 M
W m
m M w W
M M
M am s M
t M-
~~aw M~~
M sm-TLlamma~ose Detal Repo"09 W
W W
I W
W Radiological Environmental Monitoring Program Detail Data APPENDIX C 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 9
9 9
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 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10.73
+/-
0.62 11.43
+/-
0.45 11.31
+/-
0.59 13.61
+/-
1.53 14.48
+/-
0.76 14.29
+/-
0.47 14.46
+/-
0.83 12.95
+/-
0.55 12.73
+/-
0.54 14.12
+/-
0.67 12.86
+/-
0.57 11.77
+/-
0.57 11.71
+/-
0.73 12.91
+/-
0.70 12.74
+/-
0.79 12.53
+/-
0.49 12.08
+/-
0.98 12.75
+/-
0.74 12.52
+/-
0.85 10.76
+/-
0.57 11.28
+/-
0.62 11.63
+/-
0.57 11.58
+/-
0.63 10.33
+/-
0.65 8.27
+/-
1.29 11.00
+/-
0.51 8.26
+/-
0.62 12.49
+/-
0.62 13.16
+/-
0.78 14.00
+/-
0.52 C-39
APPENDIX C TLD Gamma Dose Detail Report 2009 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 21 TLD 10/8/2009 to 1/13/2010 13.42
+/-
0.67 23 23 23 23 24 24 24 24 29 29 29 29 30 30 30 30 31 31 31 31 33 33 33 33 35 35 35 35 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 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to
. 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 13.59 13.57 15.01 14.16 11.62 11.87 12.11 12.50 15.02 15.90 16.57 15.52 13.61 14.67 15.11 14.73 13.99 15.96 15.56 16.08 15.42 17.48 17.19 16.84 11.01 11.59 12.35 11.76
+/-/-
0.68
+/-
0.70
+/-
0.54
+/-
0.98
+/-
0.64
+/-
0.82
+/-
0.64
+/-
0.68
+/-
0.74
+/-
0.57
+/-
0.59
+/-
0.66
+/-
0.71
+/-
0.51
+/-
0.64
+/-
0.60
+/-
0.62
+/-
0.56
+/-
0.87
+/-
0.65
+/-
0.82
+/-
0.72
+/-
0.73
+/-
0.52
+/-
0.56
+/-
0.51
+/-
0.63
+/-
0.60 m I M M W
=
I WM m
so m
m M
STL"Gamm~a Dose Detail Report 2009 Radiological Environmental Monitoring Program Detail Data APPENDIX C 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 36 36 36 36 TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 14.50
+/-
0.75 15.96
+/-
0.66 16.62
+/-
0.80 15.42
+/-
0.51 11.63
+/-
0.57 13.56
+/-
1.66 13.80
+/-
0.58 13.36
+/-
0.69 11.59
+/-
0.76 12.28
+/-
0.54 12.82
+/-
0.89 12.26
+/-
0.56 12.12
+/-
1.42 13.67
+/-
1.10 14.11
+/-
1.41 13.45
+/-
1.09 11.73
+/-
0.61 13.42
+/-
0.83 13.12
+/-
0.58 13.08
+/-
0.94 9.67
+/-
0.53 11.06
+/-
0.62 10.84
+/-
0.52 11.12
+/-
0.73 C-41
APPENDIX C TLD Gamma Dose Detail Report 2009 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 mRP91 days +/- 2 Sigma Location Sample Type Collection Period Exposure 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 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 9.31
+/- 0.66 10.03
+/-
0.85 10.64
+/-
0.91 10.60
+/-
1.22 10.13
+/-
0.56 9.81
+/-
0.78 12.06
+/-
0.54 11.03
+/-
0.92 10.88 12.27 12.84 13.41 10.98 11.31 12.55 12.38 10.74 12.17 13.03 13.33 11.50 13.29 13.36 14.17 10.51 11.91 12.21 12.64 0.50 0.73 0.57 0.75 0.59 0.92 0.59 0.85 0.58 0.75 0.52 0.81 0.66 0.71 0.61 1.35 0.63 0.60 0.47 0.77 0.58 0.75 10.07
+/-
10.88
+/-
,m-Mm M
M M -*
mm M M
mm M
mm-m m m
mm a
TLD Gamma Dose Detail Report 2009 Radiological Environmental Monitoring Program Detail Data APPENDIX C 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 9
9 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 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 1/6/2009 to 4/10/2009 to 7/1/2009 to 10/8/2009 to 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/20.10 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 4/10/2009 7/1/2009 10/8/2009 1/13/2010 12.21
+/-
0.61 12.36
+/-
1.23 12.12
+/-
0.50 14.37
+/-
0.73 15.22
+/-
0.60 15.21
+/-
0.94 11.14
+/-
1.22 13.23
+/-
0.84 13.78
+/-
1.33 13.60
+/-
0.86 10.92
+/-
0.47 12.05
+/-
0.59 13.38
+/-
0.53 13.02
+/-
0.77 11.08
+/-
0.51 11.73
+/-
1.07 12.56
+/-
0.48 12.52
+/-
1.04 9.64
+/-/-
0.75 11.64
+/-
0.79 11.20
+/-
0.67 11.81
+/-
0.78 9.45
+/-
0.65 10.03
+/-
0.82 10.76
+/- 0.71 10.79
+/-
1.11 12.18
+/-
0.59 13.41
+/-
1.01 14.64
+/-
0.67 13.97
+/-
0.81 C-43
APPENDIX C TLD Gamma Dose Detail Report 2009 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Results in mR/91 days +/-
2 Sigma Location Sample Type Collection Period Exposure TLB 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 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 11.57
+/-
0.76 13.23
+/-
0.95 13.68
+/-
0.66 13.52
+/-
0.78 11.70
+/-
1.26 11.05
+/-
0.66 12.91
+/-
1.09 11.60
+/-
0.67 14.58
+/-
0.54 16.26
+/-
1.03 16.75
+/-
0.44 16.25
+/7 1.01 13.65
+/-
0.80 14.17
+/-
0.58 15.80
+/-
0.74 14.00
+/-
0.79 13.95
+/-
0.92 15.67
+/-
0.96 16.42
+/-
1.20 15.73
+/-
0.91 14.74
+/-
0.82 16.70
+/-
0.84 17.36
+/-
0.72 17.11
+/-
0.91 11.65
+/-
0.84 11.66
+/-
0.51 12.45
+/-
0.54 12.57
+/-
0.67 14.48
+/-
0.77
~
TL mmaDose Detail Report 2009 Radiological Environmental Monitoring Program Detail Data APPENDIX C 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 36 36 36 TLB.
TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 1/6/2009 to 4/10/2009 4/10/2009 to 7/1/2009 7/1/2009 to 10/8/2009 10/8/2009 to 1/13/2010 15.16
+/-
0.62 17.53
+/-
0.67 16.24
+/-
0.74 12.42
+/-
0.58 13.01
+/-
0.60 14.76
+/-
0.61 14.36
+/-
0.91 12.64
+/-
0.84 12.58
+/-
0.64 13.70
+/-
0.79 13.09
+/-
0.72 12.65
+/-
0.61 13.57
+/-
0.75 14.75
+/-
0.55 13.88
+/-
0.83 12.41
+/-
0.73 11.67
+/-
1.26 13.88
+/-
0.57 12.68
+/-
1.21 9.70
+/-
0.72 10.04
+/-
0.55 10.94
+/-
0.75 11.03
+/-
0.72 C-45
TLD Gamma Dose Detail Report 2009 Radiological Environmental Monitoring Program Detail Data APPENDIX C 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 1/6/2009 to 1/13/2010 44.10
+/-
1.90 3
TLA 1/6/2009 to 1/13/2010 42.30
+/-
1.44 4
TLA 1/6/2009 to 1/13/2010 55.08
+/-
2.01 5
TLA 1/6/2009 to 1/13/2010 45.70
+/-
1.99 6
TLA 1/6/2009 to 1/13/2010 54.45
+/-
1.25 7
TLA 1/6/2009 to 1/13/2010 8
TLA 1/6/2009 to 1/13/2010 50.66
+/- 2.01 9
TLA 1/6/2009 to 1/13/2010 45.40
+/-
2.71 10 TLA 1/6/2009 to 1/13/2010 63.99
+/-
2.52 11 TLA 1/6/2009 to 1/13/2010 57.95
+/-
5.29 12 TLA 1/6/2009 to 1/13/2010 52.76
+/-
1.75 13 TLA 1/6/2009 to 1/13/2010 51.94
+/-
2.91 14 TLA 1/6/2009 to 1/13/2010 41.66
+/-
2.60 15 TLA 1/6/2009 to 1/13/2010 43.14
+/-
2.06 21 TLA 1/6/2009 to 1/13/2010 59.20
+/-
5.12 23 TLA 1/6/2009 to 1/13/2010 52.79
+/-
1.62 24 TLA 1/6/2009 to 1/13/2010 45.94
+/-
1.83 29 TLA 1/6/2009 to 1/13/2010 61.59
+/-
1.65 30 TLA 1/6/2009 to 1/13/2010 59.57
+/-
1.63 lo WI i
I1W-M
TLD Gamma Dose Detail Report 2009 Radiological Environmental Monitoring Program Detail Data APPENDIX C 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 31 33 35 36 53 54 55 56 58 Sample Type TLA TLA TLA TLA TLA TLA TLA TLA TLA Collection Period 1/6/2009 to 1/13/2010 1/6/2009 to 1/13/2010 1/6/2009 to 1/13/2010 1/6/2009 to 1/13/2010 1/6/2009 to 1/13/2010 1/6/2009 to 1/13/2010 1/6/2009 to 1/13/2010 1/6/2009 to 1/13/2010 1/6/2009 to 1/13/2010 Exposure 65.61
+/-
2.44 70.94
+/-
3.56 50.32
+/-
1.58 69.24
+/-
2.49 56.98
+/-
2.87 53.94
+/-
4.55 56.20
+/-
5.13 56.54
+/-
2.62 43.23
+/-
1.56 C-47
APPENDIX C Water Gamma Spectral Detail Report 2009 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 28 Water 12/30/2008 to 1/29/2009
< 10.48
< 3.11
< 1.82
< 3.57
< 3.44 Water 1/29/2009 to 2/27/2009 Water 2/27/2009 to 3/26/2009 Water 3/26/2009 to 4/30/2009 Water 4/30/2009 to 5/28/2009 Water 5/28/2009 to 6/25/2009 Water 6/25/2009 to 7/30/2009 Water 7/30/2009 to 8/31/2009 Water 8/31/2009 to 9/24/2009 Water 9/24/2009 to 10/29/2009 Water 10/29/2009 to 11/24/2009
< 4.56
< 4.71
< 9.14
< 4.72
< 5.36
< 16.80
< 5.67
< 3.49
< 10.80
< 2.85
< 3.00
< 16.61
< 6.31
< 5.29
< 20.78
< 4.18
< 4.96
< 22.71
< 4.37
< 5.22
< 10.20
< 3.84
< 3.96 15.62
< 6.19
< 4.71
< 14.70
< 2.42
< 4.26
< 30.59
< 6.33
< 6.11
< 2.09
< 3.45
< 2.81
< 2.56
< 3.09
< 2.16
< 1.95
< 2.90
< 2.88
< 1.97
< 5.69
< 2.56
< 4.17
< 2.60
< 3.35
< 2.41
< 3.35
< 2.37
< 1.52
< 5.48
< 3.54
< 2.82
< 1.25
< 2.74
< 1.93 1.96
< 1.85
< 2.26
< 1.93
< 2.13 1.56
< 2.63
< 2.03
< 2.94
< 2.46
< 2.19 1.79
< 3.38 1.96
< 2.53
< 2.90
< 4.86
< 1.66
< 2.84
< 3.17
< 2.38
< 3.96
< 2.61
< 2.56
< 3.61
< 3.84
< 2.16
< 2.10
< 2.27
< 3.32
< 2.06
< 2.49
< 2.71
< 1.71
< 2.23
< 3.63
< 5.24
< 5.80
< 4.67
< 3.64
< 6.50
< 2.75
< 3.60
< 2.74 1.81 4.03
< 4.52
< 2.95
< 4.68
< 2.58
< 3.80
< 2.64
< 2.69
< 3.42
< 3.70
< 2.55
< 2.25
< 6.34
< 4.85
'm Vo M
-M "M
) la-4
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O
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,W OW MN W-*' '*n m' '
APPENDIX C Water Gamma Spectral Detail Report 2009 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 28 Water 11/24/2009 to 12/23/2009
< 15.14
< 1.77
< 2.67
< 2.19
< 277 Water 12/30/2008 to 1/29/2009 Water 1/29/2009 to 2/27/2009 Water 2/27/2009 to 3/26/2009 Water 3/26/2009 to 4/30/2009 Water 5/28/2009 to 5/28/2009 Water 5/28/2009 to 6/25/2009 Water 6/25/2009 to 7/30/2009 Water 8/31/2009 to 8/31/2009 Water 8/31/2009 to 9/24/2009
< 3.24
< 4.13
< 10.03
< 3.90
< 2.64
< 14.03
< 3.32
< 3.45
< 16.15
< 5.65
< 5.57
< 9.26
< 3.47
< 2.92
< 17.02
< 2.78
< 4.56
< 16.66
< 6.91
< 6.98
< 20.82
< 7.05
< 2.97
< 10.16
< 4.74
< 4.55
< 20.35
< 4.55
< 5.16
< 2.71
< 1.92
< 2.24 1.95
< 2.09 1.78
< 3.62 1.83
< 2.93 1.71
< 2.57
< 2.89
< 3.38 1.75
< 4.49 1.25
< 3.21
< 2.86
< 3.38
< 2.83
< 2.05
< 2.10
< 1.77
< 2.05
< 1.75
< 2.12
< 1.38
< 2.09
< 2.50
< 1.34
< 2.35
< 3.17
< 2.31
< 2.83 1.98
< 2.33
< 2.35
< 2.55
< 3.27
< 2.33
< 2.03
< 1.99
< 3.30
< 3.31
< 2.75
< 2.34
< 2.96
< 2.02
< 2.57
< 4.21
< 4.68
< 2.25
< 2.93
< 2.19
< 2.55
< 2.76
< 3.68
< 5.40
< 2.29
< 4.11
< 2.45
< 3.50
< 2.72
< 4.51
< 2.40
< 4.35
< 3.50
< 3.22
< 2.33
< 3.81
< 2.26
< 4.65 1.80
< 3.37
< 3.81
< 3.73 C-49
APPENDIX C Water Gamma Spectral Detail Report 2009 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 34 Water 9/24/2009 to 10/29/2009
< 11.68
< 1.54
< 3.12
< 2.76
< 2.52 34 34 Water 10/29/2009 to 11/24/2009 Water 11/24/2009 to 12/23/2009 Water 12/30/2008 to 1/29/2009 36 36 36 36 36 36 Water 1/29/2009 to 2/27/2009 Water 2/27/2009 to 3/26/2009 Water 3/26/2009 to 4/30/2009 Water 4/30/2009 to 5/28/2009 Water 5/28/2009 to 6/25/2009 Water 6/25/2009 to 7/30/2009
< 2.31
< 6.54
< 13.76
< 5.61
< 5.63
< 14.27
< 3.16
< 5.04
< 13.75
< 4.88
< 3.46
< 9.98
< 4.49
< 4.64
< 10.04
< 4.70
< 2.74
< 10.26
< 5.84
< 4.05
< 15.17
< 2.30
< 3.90 12.08
< 5.04
< 5.13 15.70
< 5.34
< 4.98
< 5.61
< 3.66
< 4.86
< 2.27
< 3.19
< 2.02
< 2.29
< 1.85
< 2.08
< 2.51
< 3.63
< 1.21
< 2.87
< 2;22
< 5.12
< 3.00
< 5.61
< 2.75
< 2.14
< 2.88
< 3.14
< 3.68
< 2.54
< 1.71
< 1.88
< 2.20
< 1.86
< 2.40 1.95
< 2.69 1.92
< 3.24 1.82 1.89
< 2.01
< 2.15 1.70 1.68
< 3.45
< 3.17
< 2.77
< 2.40
< 3.75
< 2.31
< 2.75
< 3.01
< 2.50
< 2.39
< 3.09
< 2.41
< 3.13
< 3.60
< 3.44
< 2.46
< 2.94
< 2.63
< 2.86
< 3.86
< 3.63
< 5.89
< 2.93
< 5.88
< 2.49
< 3.57
< 3.20
< 2.01
< 3.01
< 2.00
< 3.41
< 3.72
< 2.45
< 2.27
< 3.16
< 3.84
< 3.44
< 4.00 cm m
o -00 J a W M 0 m
w a mw 'J" m
am O o m MW -on APPENDIX C Water Gamma Spectral Detail Report 2009 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 36 Water 7/30/2009 to 8/31/2009
< 8.75 1.72
< 2.60
< 2.02 1.38 36 36 36 36 Water 8/31/2009 to 9/24/2009 Water 9/24/2009 to 10/29/2009 Water 10/29/2009 to 11/24/2009 Water 11/24/2009 to 12/23/2009 Water 3/18/2009 to 3/26/2009 Water 3/26/2009 to 4/30/2009 Water 4/30/2009 to 5/28/2009 Water 5/28/2009 to 6/25/2009 Water 6/25/2009 to 7/30/2009
< 2.54
< 3.48 13.08
< 4.98
< 2.94 13.87
< 4.57
< 5.24
< 23.81
< 6.08
< 6.54 15.83
< 3.85
< 3.73 19.70
< 3.79
< 5.09
< 10.69
< 3.60
< 4.19 17.57
< 3.26
< 5.25
< 21.26
< 5.00
< 4.31
< 20.45
< 4.71
< 3.57
< 2.34
< 2.51
< 1.55 1.14
< 4.18
< 3.29
< 4.44 1.99
< 3.84 1.99
< 3.75
< 2.15
< 2.43
< 1.33
< 2.61
< 2.61
< 4.96
< 2.10
< 3.68
< 2.48
< 2.40
< 2.26
< 2.00
< 2.87
< 3.61
< 3.29
< 1.59
< 1.05
< 1.48
< 2.03
< 1.80 1.49
< 3.37
< 2.43
< 2.05 1.55
< 1.87
< 2.25
< 2.98
< 2.38
< 2.13
< 2.49
< 2.92
< 3.16
< 2.65
< 1.69
< 3.07
< 2.82
< 3.14
< 1.98
< 2.65
< 1.79
< 2.93
< 2.48
< 4.02
< 2.60
< 3.14
< 4.54
< 2.83
< 3.20
< 2.76
< 2.16
< 4.22
< 5.42 1.83
< 3.29
< 2.69
< 4.60
< 2.84
< 2.37
< 3.17
< 4.49
< 2.86
< 4.92 59 59 59 59 59
< 2.80
< 4.10 C-51
APPENDIX C Water Gamma Spectral Detail Report 2009 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 59 Water 7/30/2009 to 8/31/2009
< 11.46
< 2.70
< 1.80
< 2.59
< 2.37 59 59 59 Water 8/31/2009 to 9/24/2009 Water 9/24/2009 to 10/29/2009 Water 10/29/2009 to 11/24/2009 60 60 60 60 60 60 Water 3/18/2009 to 3/26/2009 Water 3/26/2009 to 4/30/2009 Water 4/30/2009 to 5/28/2009 Water 5/28/2009 to 6/25/2009 Water 6/25/2009 to 7/30/2009 Water 7/30/2009 to 8/31/2009
< 3.74
< 4.52
< 15.11
< 4.14
< 3.68
< 22.42
< 7.46
< 6.33
< 14.97
< 5.57
< 4.60
< 12.21
< 5.06
< 3.78
< 14.73
< 3.63
< 4.64
< 19.17
< 6.28
< 6.80
< 21.32
< 6.08
< 4.76
< 20.27
< 6.58
< 5.22
< 9.23
< 3.32
< 5.27
< 3.00
< 1.48
< 2.65
< 2.53
< 3.19
< 2.01
< 2.36
< 2.25
< 2.20
< 1.77
< 3.73
< 3.51
< 7.43
< 3.39
< 5.45
< 3.68
< 3.13
< 2.96
< 1.77
< 2.57
< 2.72
< 2.78
< 2.22
< 1.63
< 2.92
< 2.97
< 2.59
< 2.59
< 2.24
< 1.77
< 2.49
< 4.45
< 2.42
< 432
< 2.01
< 2.54
< 3.38
< 3.74
< 2.26
< 2.88
< 3.48
< 2.58
< 2.36
< 3.46
< 2.14
< 2.53
< 1.97
< 1.99
< 2.38
< 2.41
< 3.10
< 3.82
< 4.60
< 2.21
< 3.30
< 4.45
< 2.52
< 2.34
< 3.70
< 2.89
< 2.93
< 6.33
< 3.86
< 5.12
< 2.20
< 3.96
< 2.50
< 3.48
< 3.09
< 6.85
< 2.46
< 4.87
< 2.31
< 4.18
< 4.54
< 3.87 m I -
M 4'n At fw
-~
~I
~
~
-~
(~
APPENDIX C Location Sample Type Water Gamma Spectral Detail Report 2009 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 Collection Period 60 60 60 Water 8/31/2009 to 9/24/2009 Water 9/24/2009 to 10/29/2009 Water 10/29/2009 to 11/24/2009 Ba-140 Fe-59 Zr-95
< 22.55
< 5.01
< 6.07
< 17.02
< 4.17
< 5.20 15.95
< 4.26
< 5.13 Co-58 La-140
< 3.31
< 2.51
< 2.64
< 2.55
< 2.17
< 2.58 Co-60 Mn-54
< 2.61
< 3.29 1.70
< 2.44
< 2.22
< 2.62 Cs-134 Nb-95
< 4.07
< 4.08
< 2.03
< 2.64
< 2.28
< 2.01 Cs-137 Zn-65
< 4.09
< 7.33 1.90
< 2.22
< 2.77
< 4.58 C-53
APPENDIX C Water Gross Beta Detail Report 2009 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 Collection Period 12/30/2008 to 1/29/2009 1/29/2009 to 2/27/2009 2/27/2009 to 3/26/2009 3/18/2009 to 3/26/2009 3/26/2009 to 4/30/2009 4/30/2009 to 5/28/2009 5/28/2009 to 5/28/2009 5/28/2009 to 6/25/2009 6/25/2009 to 7/30/2009 7/30/2009 to 8/31/2009 8/31/2009 to 8/31/2009 Sample Type Water Water Water Water Water Water Water Water Water Water Water 28 LLD LLD 3.19 +/- 1.17 LLD LLD LLD LLD LLD 34 LLD LLD 3.09 +/- 1.02 LLD
< 0.83 LLD
< 0.85 36 LLD LLD LLD LLD
< 0.87
< 0.91 LLD
< 0.91 59 LLD LLD LLD
< 0.86 LLD LLD 60 LLD LLD LLD
< 0.91 LLD LLD LLD mW Ma "N m0 on, A
o
no
-w' Im 4"
-,-V-L o W-APPENDIX C Water Gross Beta Detail Report 2009 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 8/31/2009 to 9/24/2009 Water
< 1.99 LLD LLD LLD 1.90 9/24/2009 to 10/29/2009 10/29/2009 to 11/24/2009 11/24/2009 to 12/23/2009 Water Water Water LLD LLD LLD
< 0.86
< 0.93 LLD LLD
< 0.88 LLD LLD LLD LLD LLD C-55
APPENDIX C Water Tritium Detail Report 2009 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 Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water 3/26/2009 6/25/2009 9/24/2009 12/23/2009 3/26/2009 6/25/2009 9/24/2009 12/23/2009 3/26/2009 6/25/2009 9/24/2009 12/23/2009 3/26/2009 6/25/2009 9/24/2009 11/24/2009 3/26/2009 6/25/2009 9/24/2009 11/24/2009
< 158.22
< 143.61
< 150.69
< 150.24
< 158.22
< 143.61
< 150.69
< 150.24
< 158.22
< 143.61
< 150.69 LLD LLD
< 143.61
< 150.69
< 150.24
< 158.22
< 147.74
< 150.69
< 150.24 M low 1" MW Jw
'M 1110
-W
-a mf JM m
At' na
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX D CORRECTIONS TO PREVIOUS ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORTS
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX D CORRECTIONS TO PREVIOUS ANUUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORTS:
There were no corrections identified during this reporting period to any of the previous Annual Environmental and Effluent Release Reports.
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L-10-114, Annual Environmental and Effluent Release Report

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L-10-114, Annual Environmental and Effluent Release Report

Text

SUBJECT:

Enclosure:

SUMMARY

SUMMARY

SUMMARY

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