Text

Annual Environmental and Effluent Release Report for 2006
	ML071280391
Person / Time
Site:	Perry
Issue date:	04/27/2007
From:	Pearce L; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, NRC/NRR/ADRO
References
	FOIA/PA-2010-0209, PY-CEI/NRR-3040L
	Download: ML071280391 (128)
	v • d • e

FENOC FirstEnergy Nuclear Operating Company Perry Nuclear Power Station 10 Center Road Perry, Ohio 44081 L. William Pearce Vice President 440-280-5382 Fax: 440-280-8029 April 27, 2007 PY-CEI/NRR-3040L United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Annual Environmental and Effluent Release Report Ladies and Gentlemen:

Enclosed is the Annual Environmental and Effluent Release Report for the Perry Nuclear Power Plant (PNPP), Unit 1, for the period of January 1, 2006, through December 31, 2006. 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 Specification, the PNPP Offsite Dose Calculation Manual, and the Environmental Protection Plan, Appendix B of the PNPP Operating License.

If you have any questions or require additional information, please contact Mr. Michael J. Alfonso at (440) 280-7204.

Enclosure:

cc: NRC Project Manager NRC Region III NRC Resident Inspector Office

( JA

-7 L__J

o

2006 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, 2007

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT TABLE OF CONTENTS EXECUTIVE SUM M ARY...................................................................................................................

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

.I Radiological Environm ental M onitoring...............................................................................................

1 Land U se Census...................................................................................................................................

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

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

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

3 INTRODU CTION..................................................................................................................................

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

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

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

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

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

6 RAD IOA CTIVE EFFLUENT RELEA SES.....................................................................................

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

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

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

9 M eteorological D ata............................................................................................................................

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

16 Abnorm al Releases..............................................................................................................................

18 Non-Com pliances................................................................................................................................

18 Offsite D ose Calculation M anual Changes....................................................................................

19 Process Control Program Changes................................................................................................

19 RADIOLOGICAL ENVIRONMENTAL MONITORING............................................................

20 Introduction.........................................................................................................................................

20 Sam pling Locations.............................................................................................................................

21 Sam ple A nalysis..................................................................................................................................

25 2006 Sam pling Program......................................................................................................................

26 Inter-Laboratory Cross-Check Comparison Program......................................................................

34 Land U se Census.................................................................................................................................

35 CLAM /M USSEL M ONITORIN G................................................................................................

38 Introduction.........................................................................................................................................

38 Corbicula Program...............................................................................................................................

38 Dreissena Program...............................................................................................................................

39 Conclusions.........................................................................................................................................

39 HERBICIDE APPLICATION S....................................................................................................

40 SPECIAL REPORTS..........................................................................................................................

42 Non-Com pliances................................................................................................................................

42 Unreviewed Environm ental Questions.........................................................................................

42 Appendix A, 2006 Inter-Laboratory Cross Check Comparison Program Results..........................

43 Appendix B, 2006 REM P Data Summ ary Reports.......................................................................

44 Appendix C, 2006 REM P Detailed Data Report............................................................................

45 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, 2006. 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 2005, indicate that the operations of the Perry Nuclear Power Plant did not result in any significant environmental impact.

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

The dose to the general public from the plant's liquid and gaseous effluents was below the applicable regulatory limits. The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP liquid effluents was 1.64E-03 mrem (0.06 % of the applicable limit). The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents was 4.05E-03 mrem (0.08% of the applicable limit). The summation of the hypothetical maximum individual dose from effluents in 2006 is equivalent to < 0.1 % 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 2006, making shipments of solid radioactive waste to a licensed burial site.

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 3000 radioactivity analyses performed on the 1302 radiological environmental samples collected in 2006. 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 complies with applicable federal regulations. The REMP results are divided into four sections:

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

Radiological Effluent Releases Page 1

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Samples of air were collected to monitor the radioactivity in the atmosphere. The 2006 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 2006 indicated concentrations. of radioactivity similar to that found in previous years. Analyses of other terrestrial samples also detected concentrations of natural radioactivity similar to those observed in previous years, and indicated no build-up of radioactivity attributable to the operation of PNPP.

Aquatic monitoring included the collection and analyses of water, fish, and shoreline sediments. The 2006 analytical results for water and fish samples showed normal background radionuclide concentrations. The results of sediment sample analyses indicated that the annual average cesium radioactivity was similar to previous years for the control location. Cesium-137 activity was detected in five (5) of the twelve (.12) samples collected. The average cesiums 137 radioactivity for all locations was 480.42 pCi/kg and is within the maximum value of 864 pCi/kg establishedin 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 2006, enhanced monitoring activities continued within the boundaries of the impoundment. The cobalt-60 remains centered within the organic material located at the top of the spillway, with little or no activity found farther upstream. Sample analyses continue to. identify cobalt-60 levels similar to those found in previous years. Refer to Table 16 for detailed sample results.

Direct radiation measurements showed no change from previous years. The indicator locations averaged 64.77 mremn/year. and control locations averaged 62.56 mrem/year. In 2006, 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 2006, the operation of the PNPP resulted in no significant increase in the radionuclide concentrations observed inthe 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, however, it has been noted that tracts of land once used for farming are now being developed as mini-industrial parks and residential housing tracts. This is reflected in the loss of available milking animals within a five mile radius of PNPP to support the Radiological Environmental Monitoring Program (REMP). For 2006, the predominant land use within the census area continues to be rural/agricultural.

Radiological Effluent Releases Page 2

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CLAMIMUSSEL MONITORING Clam and mussel shells can clog plant piping and components that use water from Lake Erie. For this reason, sampling for clams and mussels has been conducted in Lake Erie in the vicinity of PNPP since 1971. The, monitoring is specifically for Corbicula (Asiatic clams), since their intridiuction.

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 contro0l and is directed at minimizing the mussel's impact on plant operation. As in past years, ihis program has successfullyprevented Dreissena from causing any major 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.

Two, special reports were submitted in 2006:

On February '10, 2006, the Perry Plant reported a noncompliance to the OEPA due to exceeding the effluent limit for pH while draining chemically contaminated water from a valve pit.

On July 8, 2006, the Perry Plant report a noncompliance to the OEPA due to exceeding the maximum daily limit for total suspended solids (TSS) for internal station 601, neutralized demineralizers regenerant waste. This daily exceedance caused the monthly average to be exceeded, which was reported too.

Radiological Effluent Releases Page 3

A.

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT

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

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

Atoms with the same number of protons in their nuclei make up an element. The number of neutrons in the nuclei of an element may vary. Atoms with the same number of protons but different numbers of neutrons are called isotopes. All isotopes of the same element have the. same chemical.properties and many are stable or non-radioactive. An unstable or radioactive isotope of an element is called a radioisotope, or radionuclide. Radionuclides contain an excess amount of energy in the nucleus, which is usually due to an excess number of neutrons.

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

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

Alpha Particles u

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

Radiological Effluent Releases Page 4

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Gamma Rays Gamma rays are bundles of electromagnetic energy, called photons, which belhave as though they were particles. They are similar to visible light,.but of a much higher energy. Gamma rays can travel long distances in air and are often released during radioactive decay, along with alpha and bgta 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 affectsthe 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 microcuirie ([tCi), 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 human body like potassium-40, the decay of radioisotopes used in medical procedures, man-made phosphate fertilizers (phosphates and uranium are often found together in nature), fallout from nuclear weapons testing, and even household items like smoke detectors. In the United States, a person's average annual exposure from background radiation is 360 mrem, and is due to the sources shown in Figure 1 [Source: National Council on Radiation Protection and Measurements].

Figure 1: Sources of Background Radiation Internal Terrestlal 10.9%

Medical/X-Ray Nuclear Fuel Cycle 10.9%

Fall-out 8

Nuclear Medicine 0

Miscellaneous Cosmic4.0%

0.10%

8.%Consumer Products/

2.8%

/1 Oher 0.7%

V Radon Occupational Sources 54.7%

0.30%

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

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

Beryllium-7 and potassium-40 are especially common in REMP samples. Since they are naturally occurring and are expected to be present, positive results for these radionuclides are not discussed in the section for the 2006 Sampling Program results. These radionuclides are included; however, in Appendix A, 2006 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 w;vithin 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 applicabl.eirelease limits. This monitoring equipment is equipped with alarms and indicators in the plantý.ontrol room. The alarms are set to provide warnings to alert.plhwtoperators when radioactivity.rle'els reach a small fraction of actual limits. The waste streamnVe aled and analyzed to identify",d, quantify the radibnuclides being released to the environmen Gaseous effluent release data ik dthpled with on-site meteorological data in order to calculate the dose to the general public. De'ices.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 occuirred.- The Radiological Environmental Monitoring Program (REMP) is described in detai 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, shredding and compacting, or 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)

[ OCFR20], Appendix B; Title 10 of the Code of Federal Regulations, Part 50 (Domestic Licensing of Production and Utilization: Facilities) [10CFR50], Appendix I; and Title 40 of the Code of Federal Regulations, Part 190 (Environmental Radiation Protection Standards for Nuclear Power Plants) [40CFR190].

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 Radiological Effluent Releases Page 7

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 3

no other fuel sources near the PNPP, the 40CFR 190 limits, which are described below, were not exceeded in 2006.

3 The 40CFR190 limit for total direct-radiation dose is 25mrem.. For 2006, the total whole body dose-to a member of the general public, considering all sectors, was 1.17E-2 mrem. This value was determined by summing the annual whole body doses from liquid and gaseous radioactive effluents, the annual gaseous and liquid organ dose (refer to Table 7) and the maximum; direct-radiation dose.

Since the direct radiation dose, as determined by-TLD, was'indistinguishable from natural background (refer to Figure 8), it was not included in the calculation.

Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases, as required by-the ODCM. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 [tCi/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 beyond the site boundary shall be limited to the following:

Noble gases:

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

Iodine-131, Iodine-1 33, 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 tonoble gases to areas at, and beyond the site boundary, shall be limited to the following:.

During any calendar quarter:

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

During any calendar year:

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

Radiological Effluent Releases Page 8

ANNUAL ENVIRONMENTAL AND EFFLUENT. RELEASE REPORT Dose to a member of the public from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half lives greater than eight days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Less than or equalto 7.5 mrem to any organ per any calendar quarter, and Less than or equal to 15 mrem to any organper 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 2006.

Table 1: Liquid Batch Releases QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 TOTAL Number of batch releases 1

2 2

19 24 Total time period for batch releases, min 2.62E+03 5.52E+02 5.59E+02 4.68E+03 8.41E+03 Maximum time for a batch release, min 2.62E+03 2.87E+02, 3.53E+02 2.88E+02 2.62E+03 Average time period for a batch release, min 2.62E+03 2.76E+02 2.80E+02 2.46E+02 3.50E+02 Minimum time for a batch release, min 2.62E+03 2.65E1+02 2.06E+02 2.03E+02 2.03E+02 Average stream flow during periods of effluent 1.70E+05 1.59E+05 2.02E+05 1.84E+05 7.68E+04 release into a flowing stream, Limin In addition to batch releases, a continuous release may occur with the release of the Turbine Building Supply Plenum Drains. The moisture from the outside air is condensed and flows into a drain pan.

During hot, humid months with low wind speed, the potential exists for some of the gaseous effluent exhaust from the plant to be recycled back into the plant through the Turbine Building Supply Plenums. Since the air from the plant gaseous effluents can contain tritium, then the water in the exhaust plenums can also contain tritium. One such continuous release did occur during the year with a duration of 192279 minutes and a discharge volume of 7.05E+06 liters. Tritium concentration for this release was 2.35E-07 ýtCi/ml. Table 2b provides information for releases in 2006.

Radiological Effluent Releases Page 9

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

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

1 2

3 4

TOTAL ERROR, %

A.

Fission and Activation Products

1. Total Released, Ci

<LLD

<LLD 2.22E-04 1.00E+01 (excluding tritium, gases, alpha)

2.

Average Diluted Concentration, pCi/mL*

7.51E-04 4.18E-03 1.19E&03 4.78E-01

3. Percent of Applicable Limit, %

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 B.

Tritium

1. Total Released, Ci 3.38E-01 1.38E+00 1.25E+00 1.42E+01 1.00E+01

2.

Average Diluted Concentration, I.tCi/mL 1.30E-08 4.82E-08 3.14E-08 4.51E-07

3. Percent of Applicable Limit, %

1.30E-03 4.82E-03 3.14E-03 5.78E-02 C.

Dissolved and Entrained Gases

1. Total Released, Ci

<LLD

<LLD 1.OOE+01

2.

Average Diluted Concentration, I.pCi/mL

<LLD

3. Percent of Applicable Limit, %

0 0

D.

Alpha-Activity, Ci.

<LLD

<LLD 1.00E+01 E.

Waste Volume Released, Liters (prior to 0

1.63E+06 4.92E+06 3.29E+61 1.00E+01

\\dilution)

F.

Dilution Water Volume Used, Liters 2.60E+10 2.86E+10 3.98E+10 3.15E+10 1.00E+01

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

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

I I

i I

I I

1 I

I I

I Radiological Effluent Releases Page 10 I1

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 LLD LLD LLD 2.22E-04 1.00E+01 (excluding tritium, gases, alpha)

B.

Tritium Total Released, Ci 7.44E-02 i.26E+O00 1.19E+00 1.34E+01 1.00E+01

'C.

Dissolved and Entrained Gases Total Released, Ci

<LLD

<LLD 1.00E+01 D.

Alpha Activity, Ci LLD

<LLD

<LLD 1.00E+01 E.

Waste Volume Released, Liters (prior to 0

1.63E+06 4.92E+06 3.29E+6 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 Xctivation Products

.Total Released, Ci

<LLD

<LLD 1.OOE+01 (excluding tritium, gases, alpha)

B.

Tritium Total Released, Ci 2.63E-01 1.26E-01 5.68E-02 8.92E-01 1.00E+01 C.

Dissolved and Entrained Gases Total Released, Ci

<LLD

<LLD 1.OOE+01 D. Alpha Activity, Ci

<LLD

<LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 0

1.63E+06 4.92E+06 3.29E+6 1.OOE+01 dilution)

<LLD - Less than the lower limit of detection Radiological 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"

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

Table 3: Radioactive Liquid Effluent Nuclide Composition QUARTER QUARTER QUARTER QUARTER ANNUAL

'UNIT

1.

2 3

4 TOTAL Tritium Ci 7.44E-02 1.26E+00

-1.19E+00 1.34E+01 1.59E+01 Chromium-51 Ci

<LLD

<LLD Manganese-54 Ci

<LLD

<LLD Iron-55 Ci

<LLD

<LLD:

<LLD

<LLD Iron-59 Ci

<LLD

<LLD,

<LLD Cobalt-58 Ci

<LLD

<LLD 2.54E-03 Cobalt-60 Ci

<LLD,

<LLD LLD

.2.22E-04, 2.22E-04 Zinc-65.

Ci

<LLD

<LLD Strontium-92 Ci

<LLD

<LLD Zirconium-95 Ci

<LLD

<LLD Niobium Ci

<LLD

<LLD Technetium-99M Ci

<LLD

<LLD Rhuthenium-105 Ci

<LLD

<LLD Silver-110m Ci

>LLD.

<LLD

<LLD,

<LLD

<LLD Antimony-124 Ci

<LLD

<LLD.

<LLD Antimony-125 Ci

<LLD

<LLD.

<LLD Iodine-131 Ci

<LLD

<LLD Xenon-133 Ci

<LLD

<LLD Cesium-134 Ci

<LLD

<LLD Cesium-137 Ci

<LLD

<LLD Cesium-138 Ci

<LLD

<LLD Lanthanum-140 Ci

<LLD

<LLD Gold-199 Ci

<LLD

<LLD Total for Period Ci 7.44E-02 1.26E+00 1.19E+00 1.34E+01 1.59E+01

<LLD - Less than the lower limit of detection I

I I

U I

I I

U I

I I

I Radiological Effluent Releases Page 12 I

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 aroutine 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 pnot 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 5.84E-03 3.28E-02 9.48E-03 3.80E+00 1.003E+01

' 2.

Average Release Rate, pCilsec 7.51E-04 1 4.18E-03 1.19E-03 4.78E-01

3.

Percent of Applicable Limit, %

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

.B.

Iodine

1.

Total Iodine-131 Released, Ci

<LLD

<LLD 8.06E-05 1.00E+01

2.

Average Release Rate, pCi/sec

<LLD

<LLD I.01E-05

3.

Percent of Applicable Limit, %

N/A N/A N/A N/A C. Particulates with Half-Lives > 8 days

1.

Total Released, Ci 1.21E-05 2.62E-04 5.11E-04 6.24E-04 1.OOE+01O

2.

Average Release Rate,.tCilsec 1.55E-06 3.33E-05 6.42E-05 7.85E-05

3.

Percent of Applicable Limit, %

N/A N/A N/A N/A D. Alpha Activity, Ci 2.38E-05 1.07E-07 1.30E-06 6.51E-07 E.

Tritium

1.

Total Released, Ci

<LLD

<LLD 1.00E+01

2.

Average Release Rate, 4Ci/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 limit for fission and activation products.

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

Radiological Effluent Releases Page 13

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 5: Radioactive Gaseous Effluent Nuclide Composition QUARTER QUARTER QUARTER QUARTER ANNUAL

UNIT, 1

3 4

TOTAL A.

FISSION AND ACTIVATION GASES....

Tritium Ci

'<LLD

<LLD

<LLD Argon-41 Ci

<LLD

<LLD Krypton-85m Ci

<LLD 6.57E-04

<LLD 7.26E-01 7:27E-01 Krypton-85 Ci

<LLD,

<LLD I <LLD

<LLD

<LLD Kryton-87 Ci

<LLD 1.50E703 I <LLD 5.39E-02 J5.54E-02 Krypton-88 Ci

<LL D

<LLD

<LLD 1.17E+00

1.17E+00 Xenon-131m Ci,

<LLD

<LLD Xenon-133m Ci

<LLD

<LLD I <LLD

<LLD

<jLLD Xenon-133 ICi

<LLD

.4.40E-03 3.46E-03 4.49E-0f1 4.57E-01 Xenon-135m Ci

<LLD 4.50E-03

<LLD 2.97E-01:

3.02E-01 Xenon-135 Ci 5.84E-03 1.66E-02

.6.02E-03 7.68E-01 4 7.96E-01 Xenon-137 Ci

<LLD

<LLD Xenon-138 Ci

<LLD 5.23E-03

<LLD 3.33E-01 3.38E-01 Tota for Perod Ci 5.84E-03 3.28E-02 9.48E-03 3.80E+00

-3.85E+00 B.. IODINE Iodine-131 Ci

<LLD

<LLD 8.06E-051 8.06E-05 Iodine-132 Ci

<LLD

<LLD._,

<LLD Iodine-133 Ci

<LLD

<LLD 1.14E-04

i. 14E-04 Iodine-134 I Ci

<LLD

<LLD I

<LLD Iodine-135 I

Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD 1.95E-4 1.95E-4 B.

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 1.21E-05 2.62E-04 5.1iE-4 6.24E-4 1.41E-3 Strontium-90 Ci

<LLD

<LLD.

<LLD Strontium-91 Ci

<LLD

<LLD.

<LLD Yttrium-91m Ci

<LLD

<LLD Strontium-92 Ci

<LLD

<LLD Zirconium-95 Ci

<LLD

<LLDM

<LLD Molybdenum-99 Ci

<LLD

<LLD Cesium-137 Ci

<LLD 9.53E-06

<LLD

<LLD 9.53E-06 Cesium-138 Ci

<LLD

<LLD Barium-139 Ci

<LLD

<LLD Barium-140 Ci

<LLD

<LLD Lanthanum-140 Ci

<LLD

<LLD Total for Period Ci I 1.21E-05 2.72E-04 5.11E-4 I 6.24E-4 9.53E-06

<LLD - Less than the lower limit of detection I

I I

I 1

I I

I Radiological Effluent Releases Page 14

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Solid Waste There were no shipments of PNPP solid radioactive waste transported, by truck, directly to the Barnwell, South Carolina, disposal facility for burial. Solid radioactive waste from PNPP was processed and combined with waste from several other utilities by-intermediate vendors (DuIr-atek in Oak Ridge, TN and Studsvik in Erwin, TN). This waste was ultimately sent to the Barnwell, South Carolina, or Clive, Utah; disposal facilities for burial. No irradiated fuel or components were transported from PNPP in 2006. The solid radioactive waste summary in Table 6 includes all PNPP shipments.

Table 6: Solid Waste Shipped Offsite for Burial or Disposal A.

Type of Solid Waste Shipped Volume Activity Period Est. Total I

Ci Error %

Spent resin, filter sludge, evaporator 11.450 1320.0 1/1/2006-

+/-25 bottoms, etc.

1 12/31/2006 Dry compressible waste, contaminated 62.10 9.672 1/1/2006-

+/- 25 equipment, etc.

12/31/2006 irradiated components, control rods, etc.

0 0

N/A N/A

.,Other (describe) 0

.0 N/A N/A B. Estimate of Major"1 ) Nuclide Composition Abundance Est. Total (by type of waste)

Radionuclide Error, %

Spent Resin, Filter Sludge, Evaporator Bottoms, etc.

Mn-54 9.2

+/-25 Fe-55 19.1 Zn-65 6.9 Co-60 62.7 Dry Compressible Waste, Contaminated Equipment, etc.

Mn-54 4.3

+/-25 Fe-55 30.9 Co-60 31.8 Ni-63 2.9 Zn-65 26.1 Cs-134 1.1 2.0 Irradiated Components, Control Rods, etc.

None N/A N/A' Other (describe)

None N/A N/A C. Disposition Number of Mode of Shipments Transportation Destination Solid Waste-2) 0 N/A N/A Irradiated Fuel Shipments 0

N/A N/A N/A -- Not Applicable

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

(2) -- Additional shipments were made to Studsvik, in Erwin, TN; Duratek, Oak Ridge, TN. This waste was combined with waste from other utilities' disposed of at Bamwell, SC or Envirocare of Utah.

Radiological Effluent Releases Page 15

U ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT METEOROLOGICAL DATA The Meteorological Monitoring System at PNPP consists of a 60-meter tower equipped with two independent systems for measuring wind speed, wind direction, and temperature at both 10-meter and 60-meter heights. The tower also'has instrumentation to measure dew point and barometric I

pressure. Data is logged from the tower.through separate data loggers, and transmitted to a common I

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.

DOSE ASSESSMENT The maximum concentration for any radioactive release is controlled by the limits Set forth in Title 10 of the Code of Federal Regulations, Part 20 (10CFR2O). Sampling, analyzing, processingand monitoring the effluent stream ensures compliance with these concentration limits. Dose.limit compliance is yerifiedthrough periodic dose assessment calculations. Some dose calculations are conservatively performed for a hypothetical individual who is assum ed to reside& on the site boundary at the highest potential dose location all year. This person, called the "maximum individual", would incur the maximum potential dose from direct exposure (air plus ground plus water), inhalation, and I

ingestion of water, milk, vegetation, andfish. Because no one actually meets these criteria,'the actual dose received by a real member of the public is significantly less than what.is calculated for this hypothetical individual.

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

First, they are performed using data for a 360 0 radius around the plant site (land and water based meteorological sectors), even though some of these sectors are over Lake Erie, which has no I

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 ESTIMATED

% OF TYPE OF DOSE ORGAN DOSE, rnrem LIMIT LIMIT Liquid Effluent Whole body 7.17E-04 3.OE+00 2.4E-02 Liver 7.19E-04 L.OE+01 7.2E-03 Noble Gas - gamma air N/A 6.41E-03 1.OE+01 6.4E'02

- beta air N/A 2.15E-03 2.OE+01 1.1E-02 Noble Gas Whole body 4:05E-03 5.OE+00 8..1E-02 Skin 6.21E-03 1.5E+01 4.1E-02 Particulate & Iodine Thyroid 1.34E-02 1.5E+01 8.9E-02 I

I I

Radiological 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 ESTIMATED' ORGAN DOSE person-rem Liquid Effluent Whole body 2.41E-01

Thyroid, 2.4E-01 Gaseous Effluent Whole body 1.2E-04 Thyroid 1.1E-04 Table 9 provides the calculated hypothetical maximum site boundary dose values considering only the land-based sectors. If any radionuclide was not present at a.level greater than the LLD, it was not used-in the dose calculations.

Table 9: Maximum Individual Site Boundary Dose, Considering Sectors on Land ESTIMATED

% OF TYPE OF DOSE ORGAN DOSE, mrem LIMIT LIMIT Liquid Effluent Whole body 1.64E-03 3.OE+00 5.5E-02 G-I Tract 1,64E-03 L.OE+01 1.6E-02 Noble Gas

- gamma air N/A 6.41E-03 1.OE+01 6,4E-02

- beta air N/A 2.15E-03 2.0E+0l L.1E-02 Noble Gas Whole body 4.05E-03 5.OE+00 8.1E-02

__Skin 6.21E-03 1.5E4-01 4.1E'02 Particulate & Iodine Bone 1.34E-02 1.5E+01 8.9E-02 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 Occupancyfactors.

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 ORGAN DOSE, DOSE, mrem mrem First Quarter O.OE+00 O.OE+00 Second Quarter O.OE+00 O.OE+00 Third Quarter O.OE+00 O.OE+00 Fourth Quarter 1.3E-05 1.5E-05 Annual 1.3E-05 1.5E-05 Radiological Effluent Releases Page 17

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT i

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. ý The cases evaluated included traversing a public road within the site boundary, shoreline fishing (assumirng fi11ing 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year)"n n-laint '

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 4.4E-06 9.9E-09 Second Quarter 2.9E-06 8.3E-05 Third Quarter 8.7E-06 7.7E-06 Fourth Quarter 4.4E-04 6.7E-04 Annual 4.4E-04 6.7E-04 An average whole body dose to individual members of the public at or beyond the site boundary is then determined by combining the dose from gaseous and liquid radiological effluents. The dose from gaseous radiological effluents is based upon the population that lives within 50 miles of PNPP (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 Gaseous Effluents (mrem)

Effluents (mrem)

First Quarter 8.3E-10 2.5E-14 Second Quarter 3.3E-09 2.OE-12 Third Quarter 5.4E-08 9.5E-12 Fourth Quarter 4.5E-08 3.6E-11 Annual 1.OE-07 5.OE-11 ABNORMAL RELEASES There were no abnormal radioactive release events during 2006.

On September 5, 2006, routine work activities required the use of a Coppus blower to ventilate the Offgas Building. Ventilation was established to an open manway door, and inadvertently created the potential for an unmonitored release path. Sampling of the area verified that no radiological releases occurred. This incident was documented in Condition Report 06-04029.

NON-COMPLIANCES There was one (1) non-compliance to the ODCM Controls requirements in 2006.

In March, 2006, the Perry Plant began supplemental monitoring of the underdrains system (P72) as a response to tritium releases to groundwater in Region 3. On March 28, 2006, tritium was discovered in the underdrains system at Perry. A root cause investigation was conducted under Condition Report 06-01477, and a comprehensive testing plan was established as part of the corrective actions.

Radiological Effluent Releases Page 18 II I

I U

I i

I I

I

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT There have been no indications of tritium release from the plant through other pathways besides the underdrains. The'underdrain system discharges ultimately to the suction bay of the Emergency Service Water pumphouse, which discharges' to the approved plant outfall. All identified tritium releases to date have been incorporated as part of this report.

OFFSITE DOSE CALCULATION MANUAL CHANGES During this reporting period, there were no (0) revisions' to: the Offsite Dose Calculation Manual.

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

Radiological Effluent Releases Page 19

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I

RADIOLOGICAL ENVIRONMENTAL MONITORING 3

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 I

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 I

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, 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 and'soil. sampling were dropped from the program.

3 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 1

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 I

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 13, Figure 2, Figure 3 and Figure 4 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 I

required by the ODCM are shown in Bold in Table 13.

I Radiological Environmental Monitoring Page 20

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 13: REMP Sampling Locations Location #

Description Miles Direction Media(2) 1 Chapel Road 3.4 ENE TLD, ALP 2

Kanda Garden 1.9 ENE Food Products 3

Meteorological Tower 1.0 SE TLD, AIP 4

Site Boundary 0.7 S

TLD, AIP 5

Quincy Substation 0.6 SW TLD, Air 6

Concord Service Center 11.0 SSW TLD, ALP 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 20 Rainbow Farms 1.9 E

Food Products

21.

Hardy Rd.

5.1 WSW TLD

-22 Corfias Farm (goat) 4.9 S

Milk

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 Veg =

Vegetation TLD =

Thertnolumninescent Dosimeter Radiological Environmental Monitoring Page 21

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 14 provides a list of the analyses performed on environmental samples collected for the PNPP REMP in 2006.

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 2006.

Radiological Environmental Monitoring Page 25

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 2: 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 I

0 1

2 MILES Radiological Environmental Monitoring Page 22

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 3: REMP Sampling Locations Between Two and Eight Miles of Plant Site SW ssw S

sse se 2

3 4

5 10 MILES 0

Radiological Environmental Monitoring Page 23

=

mm m m

n m

m mm n m n m m

rj2 0

0I.

ii

2. ~

10 5

0 5

15 20 MILES 5

0 5

10 15 2OMILES

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 14: REMP Sample Analyses TYPE SAMPLE FREQUENCY ANALYSIS Atmospheric Monitoring Airborne Weekly, Quarterly Gross Beta Activity Particulates Gamma Spectral Analysis Airborne Weekly Iodine-131 Radioiodine Terrestrial Monitoring Milk Bi-Monthly Gamma Spectral Analysis Iodine-131 Food Products Monthly Gamma Spectral Analysis Vegetation As Required Gamma Spectral Analysis Aquatic Monitoring Water Monthly Gross Beta Activity, Gamma Spectral Analysis Quarterly Tritium Activity Fish Annually Gamma Spectral Analysis, Sediment Biannually Gamma Spectral Analysis Direct Radiation Monitoring TLD Quarterly Gamma Dose Annually Gamma Dose 2006 SAMPLING PROGRAM The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the 2006 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, 2006 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 2006.

Program Changes A new milk animal location was identified during the 2005 Land Use Census. In June 2006, the Corfias Farm (sample location 22) officially began participation in the REMP program.

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 sand or bluff erosion and shoreline collapse. Table 15 provides information on samples missed during 2006.

UI I

I I

1 I

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 anmount 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 14 provides a list of the analyses performed on environmental samples collected for the PNPP REMP in 2006.

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 2006.

Radiological Environmental Monitoring Page 25

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 14: REMP Sample Analyses TYPE SAMPLE FREQUENCY ANALYSIS Atmospheric Monitoring Airborne Weekly, Quarterly Gross Beta Activity Particulates Gamma Spectral Analysis Airborne Weekly Iodine-131 Radioiodine Terrestrial Monitoring Milk Bi-Monthly Gamma Spectral Analysis Iodine-131 Food Products Monthly Gamma Spectral Analysis Vegetation As Required Gamma Spectral Analysis Aquatic Monitoring Water Monthly Gross Beta Activity, Gamma Spectral Analysis Quarterly Tritium Activity Fish Annually Gamma Spectral Analysis, Sediment Biannually Gamma Spectral Analysis Direct Radiation Monitoring TLD Quarterly Gamma Dose Annually Gamma Dose 2006 SAMPLING PROGRAM The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the 2006 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, 2006 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 2006.

Program Changes A new milk animal location was identified during the 2005 Land Use Census. In June 2006, the Corfias Farm (sample location 22) officially began participation in the REMP program.

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 sand or bluff erosion and shoreline collapse. Table 15 provides information on samples missed during 2006.

Radiological Environmental Monitoring Page 26 I

I I

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 15: Missed REMP Samples in 2006 MEDIA LOCATION DATE REASON Food Products All April, May, June, Nov. 2006 Insufficient growth or die-off/frost damage.

20, 70 July Excessive rain and unseasonably cold temps.

2M August Excessive rain and unseasonably cold temps.

2, 16, 70 October Excessive rain and unseasonably cold temps.

Lake Water 59 January, February 2006 Sample unavailable due to frozen shoreline 60 January, February 2006 Sample unavailable due to frozen shoreline Milk 22 Oct., Nov., December 2006 Drying period for goats 41, 61 Janm, Feb., March, Oct., Nov.,

Drying period forgoats December 2006 Sediment 63 June and October 2006 Bluff collapse, location inaccessible TLD 7

Annual 2006 Lost due to damage'by heavy equipment Atmospheric Monitoring Air Air sampling is conducted to detect any increase in the concentration of airborne radionuclides. The PNPP ODCM requires five locations (four indicatorand one control). 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 (toadsorb iodine).

The samples are collected on a weekly basis, 52 weeks a year, from each of seven air sampling stations. - 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.

On occasion, air sample locations can experience power losses associated with storms and/or malfunctioning equipment. No power losses or missed samples due to storms or malfunctioning equipment were experienced in 2006.

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 371 for air particulate and 371 air radioiodine samples were collected and analyzed in 2006.

Gross beta activity was detected in all air samples and ranged up to 0.04 pCi/in 3. The average gross beta activity at both indicator and control locations was 0.02 pCi/m3 for 2006. Historically, the concentration of gross beta in air has been essentially identical at indicator and control locations.

Figure 5 reflects the average gross beta activity for 2006 and the previous years.

Except for naturally occurring beryllium-7, no radionuclides were identified in the gamma spectral analysis above the LLD values. Iodine-131 was not detected in any sample above the LLD of 0.05 pCi/m3.

Radiological Environmental Monitoring Page 27

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 5: Annual Average Gross Beta Activity, in Air 0.05l 0.D4 -

0.03 0.021 0.01 -

O~0-CD~

0 0

0.

0 0

0' 0

0t CO 13 Indicator Yr Control Terrestrial Monitoring 3

Collecting and analyzing samples of milk, food products and vegetation provides data to assess the build-up of radionuclides that may be ingested by humans. The historical data from soil and vegetation samples provides informnation on the atmospheric radionuclide deposition. The PNPPl 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 2006 the PNPP REMP included four (4) milk locations located 4.9, 5.8, 7.4 and 9.6 miles away from the plant. In June 2006, a new milk location was added to the Program. Identified during the 2005 Land Use Census, location 22 is 4.9 miles away from the plant in the South sector. Since the majority of milk sampling locations do not meet the requirements of the ODCM (no milk-producing animals located within the required areas),

I food product sampling (discussed below) was performed. Milk is collected from the available locations, 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.

3 Milk samples are analyzed by gamma spectral analysis for radioiodines and other radionuclides. A total of fifty (50) milk samples were collected in 2006. Iodine was not detected above the LLD of 0.75 pCi/L in any of the samples. The concentrations of all radionuclides, except naturally occurring I

potassium-40, were below LLDs in all samples collected.

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

R Radiological Environmental Monitoring Page 28

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT A total of thirty-five (35) food product samples were collected and analyzed by gamma spectral analysis in 2006. Excessive rain and unseasonably cold temperatures severely limited the 2006 growing season, accounting for the missed samples referenced in Table 15. Five (5) food products were collected which included: beet greens, collard greens, turnip greens, chinese cabbage 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 depositioni rmn-off/soil erosion, and!releases of mdi6actvity in liquid effluents from hospitals, universities or other hiddstrnil facilities. -These sources provide two forms of potential radiationexposure, extemna and internal. Externam exposure car! occur from contact with water or shoreline sediiments, while internal. exposure*Can ocur 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. The containers are emptied monthly and the samples shipped to the laboratory for analysis. Samples from two locations are collected weekly and combined. Each month the combined samples for each location are shipped for analysis.

Fifty-six (56) water samples were collected and analyzed for gross beta activity and gamma spectral analysis in 2006. From these monthly samples, a quarterly composite sample was obtained and analyzed for tritium activity. Refer to Table 15 for an explanation of any missed samples.

Gross beta activity was detected in seven (7) of the fifty-six (56) samples collected. For 2006, the detectable gross beta activity was 3.07 pCi/L vs. the lab LLD value of 3.00 pCi/L. Refer to Figure 6 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.

Figure 6: Annual Average Gross Beta Activity, in Water 12 104 4+

No 0

0 0 N

M'T 0 to cc M.

M) 0 E;

N CO It LO Co W) 0W M) C) M)0)0

0)

0) c 0) 00

0)

0) 0

)

0 0

0 Year 0 Indicator U Control Radiological Environmental Monitoring Page 29

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE.REPORT There were no radionuclides detected by gamma spectral analysis above tle '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.

Sediment 3

Sampling lake bottom sediments can provide an indication of the accumulation of particulate radionuclides which may lead to int ernal exposure to humanrs through the ingestion of fish, the re-suspension into drinking Water, or as an external radiation source to fishermen and swimmers from shoreline expoasch re.a Althoughithe

(

NPP o

DCM requires only'one location, Sediment is sampled twiceeach year frosia Sven (7) locathPnsP Two (2D of theqisare piing locations are also fish sampling locations. Sediment samples from offshore are collected using a hand dredge. Shoreline samples are collected using a scoop. Twelve (12) sediment samples were collected in 2006 and analyzed by gamma spectrometry. In 2006, shoreline sample location 63 could not be sampled due to a bluff collapse preventing access. Heavy rains and high lake levels accounted for much of the erosion and collapse.

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.

I Cesium-137 activity was detected in five (5) of.the twelve (12) samples collected and ranged from 145.25 pCi/kg to 907.86 pCi/kg. The annual average cesium-137 activity was 204.18 pCi/kg at the indicator locations and 894.77 pCi/kg at the control location. The average cesium-137 radioactivity I

for all locations was 480.42 pCi/kg and is within the maximum value of 864 pCi/kg established in 1981. Year-to-year variations in lake bottom sediment sample activitiy is expected and beyond the control of PNPP. For example, cesium-137 activity variations (refer to Figure 7) in the control l

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. Sampling in nearly the same location approximately 4V2 miles off-shore, even with GPS, is extremely difficult.

RI I

Radiological Environmental Monitoring Page 30

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 7: Annual Average Cesium-137 Concentration in Sediment

,a 1600 1400 1200 1000 800 600 400 200 0

CC0

'I 0,0

'0)00,)0) 0

)

0 0

Ye ar'j N.

Year E3 Indicator mControl 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. For 2006, sample results for cobalt-60 confirm that no activity was identified at the discharge point (Location #64), and continues to remain within the Northwest Drain Impoundment with activity ranging from <7.3 pCi/kg to 259 +/- 49 pCi/kg (Refer to Table 16). For information purposes, cesium-137 activity within the impoundment is reflected in Table 17.

Table 16: Northwest Drain Impoundment Cobalt-60 Activity, pCi/kg (dry)

Location 06/13/06 06/14/06 10/10/06 10/30/06 64

<7.3

<18.4 64-1

<14.2

<15.3 64-2 24.3 +/- 12.9 37.0 +/- 19.7 64-3

<18.1

<24.4 64-4 64-5

<14.6 64-6

<28.7

<29.7 64-7 123+/-33 126+/-30 64-8

<18.0

<14.3 64-9 166+/-33 259 +- 49 64-10 163+/-22 176+/-31 No sample available or insufficient sample for analysis Radiological Environmental Monitoring Page 31

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 17: Northwest Drain Impoundment Cesium-137 Activity, pCi/kg (dry)

Location 06/13/06 06/14/06 10/10/06 10/30/06 64

<11.3

<13.6 64-1 49+/-28 384+-23 64-2 580+/- 51 545+/-49 64-3 199+/-41 135+/-37 64-4 64-5

<10.0 64-6 780 +/-80 185 +/-48 64-7 1840 +4-90 2978 +4-83 64-8 993 +/- 55 642 +/- 36 64-9 3882 +/- 120 2365 +/- 108:

64-10 1988 +/-64 2337 +/-76.

No sample available or:in.ufficient s mplefor analysis Fish.

Fish are analyzed primarily to quantify the dietary radionuclide intake; by. humans, and secondarily to serve as indicators of radioactivity in the aquatic ecosystem. Fish are co1ected-ftom 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 2006, fish sampling was performed for PNPP by a local licensed sport fisherman.

Two (2) fish samples representing yellow perch were collected and analyzed by gamma spectral analysis in 2006. As expected, naturally occurring potassium-40 was found in all samples. No other radionuclides were detected above the LLD.

Direct Radiation Monitoring The rm7oluminscent 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 251 TLDs were collected and analyzed in 2006. This includes 224 collected on a quarterly basis and twenty-seven (27) of twenty-eight (28) collected annually. One annual TLD, location 7 was lost when the location was hit by construction equipment. Storm culvert repairs adjacent to the sample site were being performed following severe rains/flooding. Annual TLDs are not required per the ODCM and are used for supplemental data only.

Radiological Environmental Monitoring Page 32 UI I

I I

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT For 2006, the annual average dose for all indicator locations was 64.77 mrem, and 62.56 mrem for the control locations. The indicator annual dose. is believed to be influenced by location #36 (Figure

3) which has been consistently higher in dose than TLDs positioned closer to the plant (Figure 2).

Referring to Figure 8, the average quarterly dose for all indicator locations was 12.77 mrem, and 12.64 mrem for all control locations. Please refer to Appendix B, 2006 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 8: Average Quarterly TLD Dose 25

. 20 20

15 o

5 0

ý;

N M

L1 0 1. W 0;;&

-C')

LO CD r.- W M

0 G CMD Co o

WW W

CzM 00 000M0I0000 0

0 0D 02 0ý 0 0

M M

0M 0

0 0

0M 0 0

0 0

0) 0 0

0 0

0 rrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrN N

N N

N NQ N Year E3 Indicator U Control 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 33

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT INTER-LABORATORY CROSS-CHECK COMPARISON PROGRAM Introduction I

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 I

concentration of specific radionuclides are provided to the vendor laboratory. The vendor laboratory measures and reports the concentration of specified radionuclides. The known values are then '

compared to the vendor results. Results consistently outside established acceptance criteria indicate a need to check instruments or procedures. Regulatory Guide 4.15 specifically required that contractor laboratories that performed environmental measurement participate in the EPA's Environmental Radioactivity Laboratory Inter-Comparison Studies Program, or an equivalent' program.

The EPA's program is no longer funded or offered. The reason that the EPA program was referenced in thexregulatory guide is that the EPA standards were traceable to National Bureau of I

Standards (now known as National Institute Standard Technology). In response, to this problem, Teledyne (PNPP vendor lab) incorporated a program offered by Environmental Resource Associates (ERA Company), which covered the same analyses in the same matrix at the same frequency as the EPA program. The ERA Company has received NIST accreditation for its program, as anf equiyalent program. In addition to comparison cross checks performed with the ERA Company, the vendor laboratory routinely monitors the quality of their analyses by:

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

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

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

Conclusion Appendix A, 2006 Inter-Laboratory Cross-Check Comparison Program Results, includesresults from both the above referenced programs and the ERA Company cross-check program.,,

1) Table A-i, Environmental Resource Associates (ERA): Sample STW-1107 for 1-131 analysis failed. The control limits were 16.9-27.3 pCi/L. Vendor results were outside the control limits, ranging from 25.36 to 29.23 pCi/L. A fourth analysis was performed which resulted in 24.89 pCi/l.

2) Table A-2 and Table A-3, In-House "Spike" Samples: The Vendor Laboratory's Cross-Check testing of Thermoluminescent Dosimetry were all within their control limits.

3

3) Table A-4, In-House "Blank" Samples: Two (2) milk samples, SPMI-3991 and SPMI-6383 analyzed for Sr-90 were found to be outside the program acceptance criteria. Low levels of Sr-90 remain in the environment and concentrations of (1-5 pCi/1) found in milk is not unusual.

4) Table A-5, In-House "Duplicate" Samples: The vendor laboratory failed to duplicate the results for fish samples F73312 (Gr. Beta) and grass sample G-6798 (K-40). The vendor attributed the cause as extended counting times which resulted in lower than expected errors.

I Radiological Environmental Monitoring Page 34

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT

5) Table A-6, Department of Energy MAPEP: Six (6) Sample analyses were found to be outside the expected control limits. The failed acceptance ofvegetation SamPle STVE-1082 (Pu-238),

soil samples STSO-1083 (Pu-238, Pu239/40, U-233/4, U-238) and air particulate sample STAP-1085 (Pu-238) were attributed to incomplete dissolution of the samples. All samples were reanalyzed and results found to be within control limits.

LAND USE CENSUS Introduction Each year a land use census, which is required by Section 3/4.12.2 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 2006 Land Use Census, which was conducted July 17th and July 18th provided the garden, residenceand milk animal locations tabulated in Tables 18, 19 and 20 and depicted in Figure 9. Note that the W, WNW, NNW, NW, N, and NNE sectors extend over Lake Erie, and therefore, are not included in the survey.

Discussions and Results In general, the predominant land use within the census area continues to be rural/agricultural. In recent years however, it has been noted that tracts of land once used for farming are now being developed as mini-industrial parks and residential housing tracts. This is reflected in the loss of available milking animals within a five mile radius of PNPP to support the Radiological Environmental Monitoring Program (REMP). The 2006 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 18 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 2006, there were no changes noted for the "nearest residence".

Table 18:Nearest Residence, By Sector LOCATION MILES FROM X/Q VALUE, MAP LOCATOR SECTOR' ADDRESS PNPP sec/m 3 NUMBER NE 4384 Lockwood 0.7 2.66E-06 I

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 4247Redmill 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 Parmly 1.1 8.67E-07 10 Radiological Environmental Monitoring Page 35

SCALE (Miles)

Perry Nuclear wn nw N1 L a ke E r ie Power Plant,

w.

nn Y

0 5Miles 0c 40 W S W v

,,,.4,r ese S,

North Rid11 2*?.

8 o~.

~rand.,,~ri42 Figure 9: Land Use Census Map

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 19 identifies the nearest milking animal by sector, to the PNPP. During the 2006 Land Use Census, two (2) changes were identified regarding the nearest milk animal. The milking animal identified in the ESE sector is no longer there. The remaining male goat is being kept only as a pet.

The milking animal previously identified in the S sector is now a participant in the REMP program beginning in June 2006.

Table 19: Nearest Milk Animal, By Sector LOCATION MILES FROM MAP LOCATOR SECTOR ADDRESS PNPP NUMBER S

5245 Blair Rd.

4.9 22 There was one (1) change in the nearest gardens 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. Table 20 lists the nearest gardens occupying at least 500 square feet identified during the 2006 Land Use Census.

Table 20: Nearest Garden, By Sector LOCATION MILES FROM D/Q VALUE, MAP LOCATOR SECTOR ADDRESS PNPP m"2 NUMBER NE 2330 Lakehurst 0.9 8.91E-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 37

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:

Corbiculafluminea (Asiatic clam) and Dr-eissena polymorpha (zebra mussel).

CORBICULA PROGRAM Monitoring specifically for Corbicula wasinitiated in response to a NRC bulletin and concerns of the Atomic Safety and Licensing Board. The 2006monitoring was done as part of the Environmental Protection Plan (Operating License; Appendix B). The program consists of visually inspecting the raw water systems, whenever 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 or from Lake Erie in the vicinity of 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 2006, samples were collected from the Service Water (SW), Emergency Service Water (ESW),

Circulating Water and Fire Water Systems at PNPP and examined for Asiaticý clam 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 whenever opened for maintenance or repair. Sample collection/inspection dates are listed in Table 21.

Table 21: 2006 Corbicula Monitoring DATE SAMPLE LOCATION DATE SAMPLE LOCATION 4/12/06 Lube oil'cooler 1 N34B0001B B__

4/22/06 LP condenser inlet/outlet water box 4/22/06 LP condenser inlet/outlet water box 5/2/06 Emergency Service Water 1 P45 F0520 5/5/06 N61/N71 LP condenser circ water side 7/22/06 Lube oil cooler 1 N34B0001 A tube sheet 7/22/06 Lube oil cooler 1 N34B0001A upper/lower water box 8/1/06 Lube oil cooler 1N34BOO01B 8/24/06 Lube oil cooler 1 N34B0001 B 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 2006 monitoring program did not identify Corbicula in any/sample collected.

Clam/Mussel Monitoring Page 38 U

U

/3 I

U I

1 I

U

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 normally used in 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 2006 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 requires approval by the Ohio Environmental Protection Agency (OEPA). The chemical selected for use at the PNPP in 2006 was alkyl-dimethyl-benzyl-ammonium chloride. A single treatment was applied on August 23, 2006. The active ingredients were detoxified by adsorption onto 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 whn '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 2006 was 100 %. To date, PNPP has had no major 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 39

U 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 2006 two (2) 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, Riverdale, Karmex,. Peptoil and Glypro Plus. For each application, the type of weed to be treated dictated the herbicide and concentration to be used. Table 22 provides detailed documentation for each application in 2006. The quantity represents the amount of herbicide applied, after any dilution.,

Table 22: 2006 Herbicide Applications DATE LOCATION AMOUNT CHEMICAL APPLIED (GAL.)

NAME 4/26/06 All beds area 0.14 Round-up 5/4/06 Protected Area (NE, NW, SE, SW) quadrants, All beds & transformer alleyway 0.59 Round-up 5/4/06 Training bldg, WHSE, IPC, P&R bldg, Park area 1.76 Round-up 5/4/06 Admin building, Contractor parking lot (South & West) OCA gravel area 0.27 Round-up 5/6/06 Protected Area (NE, NW, SE, SW) Quadrants, Protected Area perimeter 15.8 Round-up 5/22/06 Transmission yard 120 Ibs Krovar 5/22/06 Transmission yard

.70 Oust 5/22/06 Transmission yard 7.5 Razor 5/22/06 Transmission yard 4

2,4D Amine 6/3/06 Protected Area (NE, NW, SE, SW) quadrants, Transmission yard, Gravel area 2.93 Round-up 6/5/06 Admin building 0.05 Round-up 6/21/06 Admin building, Training building, Landscape bed 0.05 Round-up 6/28/06 OCA gravel area 1.17 Round-up 7/5/06 Fire Training grounds, Training, Admin, WHSE, IPC buildings, OCA gravel 3.28 Round-up 7/8/06 Protected area NW, Transmission yard 2.34 Round-up 7/15/06 Training, WHSE and IPC buildings, OCA gravel 2.34 Round-up 7/16/06 Protected area (NE, NW) Quadrants, Protected Area perimeter 4.69 Round-up I

U I

Ua Ia I

I I

I a

I U

I Herbicide Usage Page 40 I

ANNUAL ENVIRONMENTAL AND EFFLUENTRELEASE REPORT Table 22 continued: 2006 Herbicide Applications APPLICATION LOCATION AMOUNT CHEMICAL DATE (GAL)

NAME 717/06 Admin, IPC, P&R buildings, OCA gravel 0.16 Round-up 7/24/06 Waste Accumulation Facility 0.59 Round-up 8/11/06 Fire Training Grounds.

2.34 Round-up 8/21/06 Protected Area (NE, NW, SE, SW) Quadrants, 2.34 Round-up 8/26/06 Parmley roadways 0.59 Round-up 8/30/06 Protected Area (NE, NW, SE, SE) Quadrants, 2.34 Round-up 8/31/06 Admin, IPC buildings, East side of P&R building old parking lot 2.34 Round-up 9/5/06 Protected Area (NE, SE, SW) Quadrants, Cooling to~,er -basin 2.93 Round-up 9/6/06:

Parmley and Main roadways 2.34 Round-up Herbicide Usage Page 41

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.

Two special reports were submitted in 2006:

On February 10, 2006, the Perry Plant reported a noncompliance to the OEPA due to exceeding, the effluentdlimit for pH~while draining chemnically contaminated water from a valvepit. ;Approximately 10 gallons of chemically contaminated rain water with a pH of 2.6 was pumped to a storm drain from a valve pit. A sample collected where the storm drain meets the northwest drain impoundment indicated a pH of 8.03. The procedure governing the valve pit has been revised and the valve pit has been repaired to prevent re-occurrence.

" On July 8, 2006, the Perry Plant report a noncompliance to the OEPA due to exceeding the maximum daily limit for total suspended solids (TSS) for internal station 601, neutralized demineralizers regenerant waste. This daily exceedance caused the monthly average to be exceeded, which was reported too. The cause of the high TSS was a contaminated sample from dirty sample lines. The dirty sample lines were changed out and site specific procedures have been changed to obtain the analysis of the treated water prior to discharge.

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. There were no instances of an EPP non-compliance identified in 2006.

UNRE VIEWED 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 2006 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 42

ANNuAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX A, 2006 INTER-LABORATORY CROSS CHECK COMPARISON PROGRAM RESULTS Appendix A Page 43

-Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

Northbrook, IL 60062-2310 ph. (847) 564-0700 f 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, 2006 through December, 2006

I Appendix A Interlaboratory Comparison Program Results I

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

Participant laboratories measure the concentration, of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and I

specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a needto check the instruments or procedures used.

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

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

Table A-3 lists res~ults 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.

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

Table A-5 listresults of. 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. Data for previous years available upon request.

=.

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

I Attachment A lists acceptance criteria for "spiked" samples..3 Out-of-limit results are explained directly below the result.

Al I

Attachment A ACCEPTANCE CRITERIAFOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma, Emitters

...5 to 100 pCi/liter or kg 5.0 pCiAiter

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

5 to 50 pCi/liter or kg 5.0 pCi/liter

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

5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potassium-40

> 0.1 g/liter or kg 5% of knownvalue Gross alpha

5 20 pCi/liter 5.0 pCi/liter

>.20 pCi/liter

25% of known value Gross beta

_< 100 pCi/liter 5.0 pCiAiter

> 100 pCi/liter 5% of known value Tritium 5 4,000 pCi/liter 1

10 = (pCi/liter) =

169.85 x (kndwn)°°933

> 4,000 pCi/liter 10% of known value Radium-226,-228

_0.1 pCi/liter 15% of known value Plutonium

_0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, *<55 pCi/liter 6.0 pCi/liter Iodine-1 2 9 b

> 55 pCi/liter 10% of known value Uranium-238,

_< 35 pCi/liter 6.0 pCi/liter Nickel-63b

> 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Othersb 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb.

Resultc Limits

°Acceptance STW-1 078 STW-1 078 STW-1079 STW-1079 STW-1079 STW-1 079 STW-1 079 STW-1 080 STW-1080 STW-1081 STW-1081 STW-1081 STW-1088 STW-1 088 STW-1 089 STW-1089 STW-1089 STFW-1089 STW-1 089 STW-1 090 STW-1090 STW-1091 STW-1092 STW-1 092 STW-1 092 STW-1 092 STW-1094 STW-1 094 STW-1095 STW-1 095 STW-1095 STW-1095 STW-1095 STW-1 096 STW-1096 STW -1097 STW-1097 STW-1 097 01/16/06 01/16/06 01/16/06 01/16/06 01/16/06 01/16/06 01/16/06 01//16/06 01/16/06.

01/16/06 01/16/06 01/16/06

,04/19/06

,04/10/06 04/10/06 04/10/06 04/10/06 04/10/06 04/10/06 04/10/06 04/10/06 04/10/06 04/10/06 04/10/06 04/10/06 04/10/06 07/10/06 07/10/06 07/10/06 07/10/06 07/10/06 07/10/06 07/10/06 07/10/06 07/10/06 07/10/06 07/10/06 07/10/06 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226.

Ra-228, Uranium Sr-89 Sr-90 Ba-133; Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium 49.9 +/- 3.5 31.5 +/- 1.5 86.5 +/- 4.1 96.3 +/- 4.1 22.6 +/-3.0 109.0 +/- 5.9 198.0 +/- 11.2 10.8 +/-1.4 -

56.9 +/- 1.9 4.3 +/-0.4 7.1 +/-1.8 20.7 +/- 0.5 29.0 +/- 1.8 8.7 +/- 1.0 10.3.+/- 0.4 114.0 +/-2.8 41.9 +/- 1.4 208.0 +/- 1.1 154.0 +/- 0.8 13.4 +/- 1.1 27.7 +/- 2.1 22.0 +/- 0.3 7960.0 +/- 57.0 2.9 +/- 0.4 20.9 +/- 1.2 68.6 +/- 3.4 15.9 +/- 0.7 24.3 +/- 0.4 94.9 +/- 8.9 104.0 +/- 1.8 48.7 +/- 1.3 236.0 +/-3.0 126.0 +/- 8.0 10.9 +/- 1.0 9.7 +/- 0.4 11.0 +/-0.5 12.2 +/- 0.8 43.4 +/- 0.1 50.2 30.7 95.0 95.3 23.1 111.0 192.0 9.6 61.9 4.6 6.6 22.1:

32.4 9.0 10.0 113.0 43.4 214.0 152.0 21.3 23.0 19.1 8130.0 3.0 19.1 69.1 41.5 -58.9 22.0 - 39.4 78.6 -111.0 86.6 - 104.0 14.4 -:31.8 101.0 - 121.0 159.0 -225.0

,-1.0 -18.3 44.6 - 79.2 3.4 - 5.8 3.7 -9.5 16.9 -27.3 237 - 41.1 0.3 - 17.7 1.3 -18.7 103.0 -123.0 34.7 -52.1 195.0 -233.0 126.0 - 178.0 12.1 -30.5 14.3 -31.7 13.9 -24.3 6720.0 - 9540.0 2.2 - 3.8 10.8 -27.4 57.1 -81.1 11.0 -28.4 17.2 - 34.6 72.9 - 103.0 91.0 -108.0 45.4-62.8 217.0 - 259.0.

100.0 - 142M0 1.3 - 18M6.

0.2 -17.5 7.9-13.5 6.1 -.15.3

.33.3 - 47.3 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 I

I I

U I

U 1

I I

U I

I I

19.7 25.9 88.1 99.7 54.1 238.0 121.0

10.0 8.9 10.7 10.7

40.3 Pass Pass Pass Pass Pass

'Pass Pass Pass Pass Pass Pass Pass "A11

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

Concentration (pCVL)

Lab Code Date Analysis Laboratory, ERA Control Resultb Resultc Limits Acceptance STW-1104 10/06/06 Sr-89 38.4 t-.1.3 39.9 31.2 -45.7 Pass STW-1 104 10/06/06 Sr-90 15.5 t 0.5 16.0 7.3'- 24.7 Pass STW-1105 10/06/06 Ba-133 64.9 t 2.8 70.2 58.1 -82.3 Pass STW-1105 10/06/06 Co-60 61.6 +/- 1.0 62.3 53.6 -71.0 Pass STW-1105 10/06/06 Cs-134 29;0 t 0.9.

29.9 21.2 -38.6 Pass STW-1 105 10/06/06 Cs-1 37 77.8 t 2.4 78.2 69.5 - 86.9 Pass STW-1 105 10/06/06 Zn-65 293.0 +/- 2.4 277.0 229.0 - 325.0 Pass STW-1106 10/06/06 Gr. Alpha 23.9 12.5 "

28.7 16.3 -41.1 Pass STW-1106 10/06/06 Gr. Beta 23.7-+/- 1.4 20.9 12.2 -29.6 Pass STW-1107 d 10/06/06 1-131 28.4

1.2 22.1 16.9-27.3 Fail STW-1108 10/06/06 Ra-226 14.5 +/- 0.5 14.4 10.7-18.1 Pass STW-1 108 10/06/06 Ra-228 6.6 +/- 0.4 5.9 3.3 '-' 8.4 Pass

-STW-1 108 10/06/06 Uranium 2.9 +/- 0.1 3.2 0.0 - 8.4 Pass STW-1 109 10/06/06 H-3;'

3000.0 +/- 142.0 3050.0 2430.0 - 3670.0 Pass a' Results obtained by Environmental, Inc., Midwest Laboratory as'a participant in the crosscheck program for proficiency testing in dlrinking water conducted by Environmental Resources Associates (ERA).

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

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

d The reported result was an average of three analyses, results ranged from 25.36 to 29.23 pCi/L.

A fourth analysis was performed, result of analysis, 24.89 pCi/L.

A1-2

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).

mR Lab Code Date Known' Lab Result Control Description Value

+/- 2 sigma Limits Acceptance Environmental, Inc.

2006-1 6/5/2006 2006-1 6/5/2006 2006-1 6/5/2006 2006-1 6/5/2006 2006-1 6/5/2006 2006-1 6/5/2006 2006-1 6/5/2006 2006-1 6/.5/2006 2006-1

.6/5/2006 Environmental, Inc.

2006-2 11/6/2006 2006-2

.11/6/2006 2006-2

- 11/6/2006 2006-2

-1 1/6/2006 2006-2 1 1/6/2006, 2006-2 11/6/2006 2006-2 A11/6/2006 2006-2 "11/6/2006 2006-2 11/6/2006 30 cm 60 cm 60 cm 90 cm 120 cm 120,cm 150 cm 150 cm 180 cm 30 cm.

40 cm.

50 cm.

60 cm.

75 cm.

90 Cm.

120cm.

150 cm:.

180 cm.

54.81 13.70' 13170 6.09 3.43 3.43 2.19 2.19 1.52 55.61 31.28 20.02 13.90 8.90 6.18 3.48 2.22 1.54 70.73 +/- 0.69 16.71 +/- 1.89 16.69 +/- 0.94 6.57 +/- 0.82 3.65 +/- 0.22 3.09 +/- 0.33 2.35 +/- 0.38

.1.98 +/- 0.10 1.56 +/- 0.26 60.79 +/- 1.32 35.93 +/- 3.70 21.55 +/- 1.20 14.90 +/- 1.42 8.03 +/- 0.51 6.88 +/- 0.68 2.90 +/- 0.20 1.99 +/- 0.07 1.79 +/- 0.94 38.37 - 71.25 9.59 -.17.81 9.59 - 17.81 4.26 -7.92 2.40 - 4.46 2.40 - 4.46 1.53 -2.85

1.53-2.85 1.06-1.98 38.93 - 72.29 21.90 - 40.66 14.01 -26.03 9.73 - 18.07.

6.23 - 11.57 4.33 - 8.03 2.44-4.52 1.55-2.89 1.08 - 2.00 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass I

I I

I 1

I I

I U

I I

U I

I I

I N

A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code'b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-301 SPAP-1224 SPAP-1224 SPAP-1224 SPW-1228 SPW-1230 SPW-1230 SPMI-1 232 SPMI-1232 W-30906 W-30906 SPW-2750 SPW-2869 SPAP-2871 SPAP-2871 SPW-2875 STSO-3155 STSO-3155 STSO-3155 SPAP-2873 SPF-3183 SPF-3183 SPW-3460 W-60606 W-60606 SPW-3988 SPW-3988 SPW-3988 SPW-3988 SPW-3988 SPMI-3990 SPMI-3990 SPMI-3990 SPMI-3991 SPW-4356 W-90506 W-90506 SPAP-6950 SPAP-6950 SPAP-6952 1/20/2006 3/7/2006 3/7/2006 3/7/2006 3/7/2006 3/7/2006 3/7/2006 3/7/2006 3/7/2006 3/9/2006 3/9/2006 4/27/2006 5/1/2006 5/1/2006 5/1/2006 5/1/2006 5/1/2006 5/1/2006 5/1/2006 5/2/2006 5/10/2006 5/10/2006 5/26/2006 6/6/2006 6/6/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 7/5/2006 9/5/2006 9/5/2006 9/30/2006 9/30/2006 9/30/2006 Fe-55 Cs-134 Cs-137 Gr. Beta H-3 Cs-1 34 Cs-137 Cs-134 Cs-137 Gr. Alpha Gr. Beta Ni-63 Fe-55 Cs-134 Cs-137

-7 H-3 Co-60 Cs-134 Cs-137 Gr. Beta Cs-137 Cs-1 34 C-14 Gr. Alpha Gr. Beta Cs-134 Cs-137 1-131(G)

Sr-89 Sr-90 Cs-134 Cs-137 1-131(G) 1-131 1-131 Gr. Alpha Gr. Beta Cs-134 Cs-137 Gr. Beta 2700.10 +/- 70.00 37.13 +/- 3.70 118.25 +/- 8.97 520.32 +/- 7.42 70891.00 +/- 719.00 38.58 +/-2.10 59.44 +/- 4.51 41.20 +/-1.33 57.82 +/- 3.96 24.24 +/- 0.47 63.79 +/- 0.48 116'.00 +/- 2.49 19473.00 +/- 188.00 33.97 +/- 1.10 114.44 +/- 2.81 71057:00 + 730.20 7950.80 +/- 67.29 12.49 +/-0.139 14.10 +/-0.12.,

1724.80 +/- 4.51 2.47 +/-0.03..

0.73 +/- 0.01 4009.60 +/- 14.43 21.94 +/- 0.46, 58.17 +/- 0.49 35.56 +/- 1.40 60.23 +/- 2.72 94.01 +/- 4.38 52.40 +/- 4.23 45.35 +/- 1.95 35.52 +/- 5.05 56.78 +/- 3.86 95.04 +/- 5.05 96.55 +/- 0.87 80.88 +/- 1.09 23.11 +/- 0.45 65.01 +/- 0.51 28.93 +/- 1.56 116.62 +/- 2.97 52.96 +/- 0.14 2502.50 39.52 119.30 455.00 75394.00 39.51 59.65-39.51 59.65 20208 65.73 100.00 23332.00 37.50 118.90 75394.00 7750.00 11.59 11.63 1744.00 2.38,

0.74 4741.00 20.08 65.73 36.00 59.27 99.30 58.16 41.21 36.00 59.27 99.30 99.30 77.23 20.08 65.73 32.65 117.75 53.50 2002.00 - 3003.00 29.52 - 49.52 107.37 - 131.23 364.00 - 637.00 60315.20 -90472.80 29.51 -. 49.51 49.65

. 69.65 29.51 - 49.51 49.65 - 69.65 10.04 -30.12 55.73 - 75.73 60.00 -140.00 18665.60 - 27998.40 27.50 - 47.50 107.01 -"130.79 60315.20 --90472.80 6975.00 -8525.00 i.59-21.59 1.63 - 21.63 1395.20.- 2441.60 1.43-3.33 0.44-1.04 2844..60- 6637.40 10.04*-.30.12 55.73 - 75.73 26.00 - 46.00 49.27 - 69.27 89.30 - 109.30 46.53 - 69.79 32.97 - 49.45 26.00 - 46.00 49.27 - 69.27 89.30 - 109.30 79.44 - 119.16 61.78 - 92.68 10.04 - 30.12 55.73 - 75.73 22.65 - 42.65 105.98 - 129.53 42.80 - 74.90 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)

Lab Code Date Analysis Laboratory results Known Control 2s,.n=lb Activity Limitsc

'Acceptance SPW-6954 SPW-6954 SPMI16956 SPMI-6956 W-120106 W-120106 SPAP-9476 SPAP-9478 SPAP-9478 SPW-9480 SPW-9483 SPW-9488 SPW-9488 SPMI-9490 SPMI-9490 SPF-9492 SPF-9492 9/30/2006 9/30/2006 9/30/2006 9/30/2006 12/1/2006 12/1/2006 12/29/2006 12/29/2006 12/29/2006 12/29/2006 12/29/2006 12/29/2006 12/29/2006 12/29/2006 12/29/2006 12/29/2006 12/29/2006 Cs-134 Cs-137 Cs-134 Cs-137 Gr. Alpha Gr. Beta Gr. Beta Cs-134 Cs-137 H-3 Tc-99 Cs-134 Cs-137 Cs-1 34 Cs-137 Cs-134 Cs-137

' 63.29 +/- 8.24 60.41 +/-7.53 69.26 +/- 4.85 61.35 +/- 7.62 22.40 +/- 1.03 63.70 +/- 1.14 57.51 +/-0.14 26.84 +/- 1.23 110.54 +/- 3.12 68972.20 +/- 748.00 29.43 +/- 0.84 61.35 +/- 1.65 60.30 +/- 2.76 58.99 +/- 5.43 54.16 +/- 7.85' 0.64 +/- 0.01 2.61 +/- 0.03 65.30 58.87 65'.31 58.87 20.08 65.73 53.16 30.06 117.10 72051.60 32.98, 60.10 56.80 60A10 56.80 0.60 2.34 55.30 - 75.30 48.87 - 68.87 55.31'- 75.31 48.87 - 68.87 10.04 - 30:12 55.73 - 75.73 42.53 - 74.42 20.06 - 40.06 105.39 -128.81 57641.28 - 86461.92 20.98 - 44.98 50.10 - 70.10 46.80 - 66.80 50.10'- 70.10 46.80 - 66.80 0.36 '-0.84 1.40 -3.28 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass I

i I

1 I

I I

a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m 3), and solid samples (pCi/g).

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

CH (charcoal canister), F (fish).

c Results are based on single determinations.

d Control limits are based on Attachment A, Page A2 of this report.

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

A3-2

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

Samiple, Date Analysisb Laboratory results (4.66o)

Acceptance Type LLD Activity' Criteria (4.66 Y)

SPW-302 SPAP-1225 SPW-1231 SPW-1231 W-30906 W-30906 SPW-2751 SPW-2868 SPW-2874 SPAP-2872 SPF-3154 SPF-3154 SPW-3461

-W-60606 W-60606 SPW-3989 SPW-3989 SPW-3989 SPW-3989 SPW-3989 SPW-3989 SPMI-3991 SPMI-3991 SPMI-3991 SPMI-3991 SPMI-3991 SPMI-3991 d W-90506 W-90506 SPMI-6383 SPMI-6383 d SPAP-6949 SPAP-6949 SPAP-6951 SPW-6953 SPW-6953 SPW-6953 SPW-6953 water Air Filter..

water water water water.

.water water water.-.

Air Filter Fish Fish water.

ýwater water water -

water water water water water Milk Milk Milk Milk Milk Milk water water Milk Milk Air Filter Air Filter AirFilter water water water water 1/20/2006 3/7/2006 3/7/2006 3/7/2006 3/9/2006 3/9/2006 4/27/2006 5/1/2006 5/1/2006 5/2/2006.

5/10,/2006 5/10/2006 5/26/2006 6/6/2006 6/6/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 6/16/2006 Fe-55 Gr. Beta Cs-134 Cs-137 Gr. Alpha Gr. Beta Ni-63 Fe-55 H-3 Gr. Beta Cs-134 Cs-137 C-14 Gr. Alpha Gr. Beta, Cs-134 Cs-137 1-131 1-131(G)

Sr-89 Sr-90 Cs-134 Cs-137 1-131 1-131(G)

Sr-89 Sr-90 Gr. Alpha Gr. Beta Sr-89 Sr-90 Cs-134 Cs-137 Gr. Beta Cs-1 34 Cs-137 Sr-89 Sr-90 21.21 1.16

-2.71

. 2.05 0.037

.0.076

-'1.48 18.07 166.00

1.18

.16.4

.13.7

10.20

.0.05 0.16 3.00 3.65 0.21 8.34 0.54 0.58 4.42 3.88 0.28 3.76 0.61 0.52 0.06 0.16 0.97 0.57 0.89 0.91 1.12 3.91 5.61 0.79 0.60

-1.82 t 12.75

-0.5.12 +/- 51.20 0.005 +/- 0.026

-0.016 +/- 0,.052 0.37 +/- 0.91 4.33 +/- 11.27,

-8.3 +/- 86.9

-3.65 +/-.0.64

-7.9 +/- 5.20

,0.013 +/- 0.037.'

-0.044 +/- 0.11 0.045 +/- 0.14 0.005 +/- 0.45

-0.079 +/- 0.26

-0.22 +/- 0.19

-0.25 +/- 0.76 0.88 +/- 0.34 1000 3.2 10 10 1

3.2-20 1000 200 3.2 100 200 1

3.2 10 10 0.5 20 5

1 10 10 0.5 20 5

1 1

3.2 5

1 100 100 3.2 10 10 5

9/5/2006 9/5/2006 9/14/2006 9/14/2006 9/30/2006 9/30/2006 9/30/2006 9/3.0/2006 9/30/2006 9/30/2006 9/30/2006 0.00 +/- 0.04 0.05 +/- 0.11

-0.18 +/- 0.92 0.65 +/- 0.33

-0.54 +/- 0.64

-0.14 +/- 0.64 0.11 +/- 0.29 A4-1

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

Acceptance Type

LLD Activity' Criteria (4:66ac)

SPMI-6955 Milk 9/30/2006 Cs-134 2.86 10 SPMI-6955 Milk 9/36/2006 Cs-137 2.39 10 SPMI-6955 Milk 9/30/2006 1]-131(G) 9.98 0.5 W-120106 water 12/1/2006 Gr. Alpha' 0.11 0.066 +/- 0.072 1

W-120106 water 12/1/2006 Gr. Beta 0.30 0.093 +/- 0.16 3.2 SPAP-9477 Air Filter 12/29/2006 Gr. Beta 1.13

-0:37 +/- 0.66 3.2 SPAP-9479 AirFilter 12/29/2006 'Cs-137 0.87 100 SPW-9481 water 12/29/2006 H-3 146.2 63.2 + 80.1 200 SPW-9483 Water 12/29/2006 Tc-99 0.95

-1.20 +/- 0.56 10 SPW-9489 water 12/29/2006 Cs-134 2.30 10 SPMI-9491 Milk' 12/29/2006 Cs-134 3.10 10' SPMI-9491 Milk 12/29/2006 Cs-137 2.90 10 SPMI-9491 Milk 12/29/2006 :1-131(G) 8.00 20 SPF-9493 Fish 12 29/2006 Cs-134 7.6 100 SPF-9493 Fish 12/29/2006 Cs-137 7.9 100 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 d Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCi/L) in milk is not unusual.

A4-2 I

1 I

I I

I

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a

Averaged Lab Code.

Date

.-Analysis First Result Second Result Result Acceptance AP-7466, 7467 AP-7513,.7514 AP-7555, 7556 MI-154, 155.

MI-217, 218 MI-217, 218 MI-287,288 MI-287, 288 WW-314, 315 WW-314, 315 SWT-577, 578 SWU-598, 599 SWU-598, 599 F-3311, 3312 b F-3311, 3312 SW-780, 781 SW-780, 781 DW-934, 935 DW-1024,1025 MI-1078,1079 F-1357, 1358 F-1357,1358 MI-1469,1470 CF-1538,1539 WW-1583,1584 DW-1955,1956 MI-1760,1761 AP-2603, 2604 E-1997,1998 E-1997, 1998 AP-2818, 2819 SWU-2863, 2864 SS-2389, 2390 SS-2389, 2390 DW-2773, 2774 SL-2932, 2933 SL-2932, 2933 SL-2932, 2933 BS-3103, 3104 BS-3103, 3104 MI-3037, 3038 MI-3037, 3038 1/3/2006 1/3/2006 1/3/2006 1/10/2006 1/11/2006 1/11/2006 1/17/2006 1/17/2006 1/19/2006 1/19/2006 1/31/2006 1/31/2006 1/31/2006 2/9/2006 2/9/2006 2/14/2006 2/14/2006 2/17/2006 2/24/2006 3/1/2006 3/10/2006 3/10/2006 3/14/2006 3/21/2006 3/22/2006 3/27/2006 3/29/2006 3/29/2006 4/3/2006 4/3/2006 4/3/2006 4/3/2006 4/11/2006 4/11/2006 4/21/2006 5/1/2006 5/1/2006 5/1/2006 5/1/2006 5/1/2006 5/2/2006 5/2/2006 Be-7 Be-7 Be-7 K-40 K-40 Sr-90 K-40 Sr-90 Gr. Beta H73 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 Gr. Alpha Gr. Beta 1-131 1-131 Sr-90 Gr. Beta K-40 K-40 K-40 Gr. Beta Gr. Beta K-40 Be-7 Gr. Beta K-40 Be-7 Gr. Beta Gr. Beta K-40, 1-131 Be-7 Gr. Beta K-40 Gr. Beta K-40 K-40 Sr-90 0.053

.0.033 0.053 1254.20 1258.00 1.27 1383.10 0.74 9.21 168.64

+/- 0.015

+/- 0.008

+/- 0.007

+/- 87.75

+/- 118.00

+/- 0.37

+/- 110.90

+/- 0.38

1.72

94.94

.3.06 +/- 0.66 2.03 +/- 0.39 260.10 +/- 98.20 4.12 +/- 0.14 2.68 +/- 0.37 4.09 +/- 1.52 5.91 +/- 0.90 0.35 +/- 0.22 0.24 +/- 0.26 1.42 +/- 0.39 3.77 +/- 0.07 2.46 +/- 0.32 1396.30 +/- 120.80 13.66 +/- 0.81 7.66 +/- 0.73 2.25 +/- 0.60 1271.00 +/- 89.00 0.067 +/- 0.015 1.82 +/- 0.07

.1.28 +/-*0.15 0.06 +/- 0.01 3.20 +/- 1.26 10.53 +/- 0.96 5.51.+/- 0.42 0.74 +/- 0.23 1.28 +/- 0.19 6.09 - 0.33 3.13 +/- 0.41 8.27 +/- 1.46 6288.20 +/- 585.20 1238.90 +/- 98.59 1.76 +/- 0.42 0.057 +/- 0.011 0.036 +/- 0.008 0.054 +/- 0.008 1369.60.+/- 102.80 1313.00 +/- 98.00 0.92 +/-.0.33 1457.80 119.10

.0.94 - 0.37 11.52.+/-1.93 210.12 +/- 96.51 3.68 +/- 0.64 1.97 +/- 0.40

.134.10 +/--93.50 3.82 0.,13

$ 2.76 +/-0.39.

3.22 +/-.1.37 5.89,+/- 0.92 0.31 +/- 0.25 0.53 +/- 0.24 1.30 +/- 0.62 3.71 +/- 0.07 2.32 +/- 0.44 1335.60 +/- 113.80 13.97 +/- 0.68 8.87 +/- 0.75 3.15 +/- 0.59 1378.00 +/- 113.00 0.056 +/- 0.010 1.87 +/- 0.07 1.24 +/- 0.21 0.06 +/- 0.01-4.77 +/- 1.30 9.38 +/-,0.84 5.79 +/- 0.40.

0.53 +/- 0.40 1.27 +/- 0.17 5.65 +/- 0.31 3.09 +/- 0.36 9.03 +/- 1.59 5643.70 +/- 599.80 1301.00 +/- 103.90 1.48 +/- 0.42 0.055 +/- 0.009 0.035 +/- 0.006 0.053 +/- 0.005 1311.90 +/- 67.58 1285.50 +/- 76.69 1.10 +/- 0.25 1420.45 +/- 81.37

..0.84 +/- 0.27 10.37 +/- 1.29 189.38 +/- 67.69 3.37 +/- 0.46 2.00 +/- 0.28 197.10 +/- 67.80 3.97 +/- 0.10 2.72 +/- 0.27 3.66 +/- 1.03 5.90 +/- 0.64 0.33 +/- 0.16 0.39 +/- 0.18 1.36 +/- 0.37 3.74 +/- 0.05 2.39 +/- 0.27 1365.95 +/- 82.98 13.81 +/- 0.53 8.26 +/- 0.52 2.70 +/- 0.42 1324.50 +/- 71.92 0.062 +/- 0.009 1.85 +/- 0.05 1.26 +/--0.13 0.06 +/- 0.01 3.99 +/- 0.91 9.96 +/- 0.64 5.65 +/- 0.29 0.63 +/- 0.23 1.28 +/- 0.13 5.87 +/- 0.23 3.11 +/- 0.27 8.65 +/- 1.08 5965.95 +/- 418.99 1269.95 +/- 71.62 1.62 +/- 0.29 Pass Pass 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass A5.1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-3124, 3125 SW-3145, 3146 SW-3145, 3146 MI-3236, 3237 F-3422, 3423 G-3491, 3492 G-3491, 3492 SO-3539, 3540 SO-3539, 3540 WW-3751, 3752 F-3617, 3618 SL-3641, 3642 SL-3641, 3642 SL-3641, 3642 MI-3886, 3887 VE-3949, 3950 VE-3949, 3950 VE-3949, 3950 BS-4016, 4017 BS-4016, 4017 BS-4016, 4017 MI-3992, 3993 LW-4175, 4176 W-4130, 4131 AV-4330, 4331 SWU-4489, 449(

AP-4909, 4910 AP-4952, 4953 5/9/2006 5/9/2006 5/9/2006 5/10/2006 5/19/2006 5/24/2006 5/24/2006 5/24/2006 5/24/2006 5/25/2006 5/30/2006 6/1/2006 6/1/2006 6/1/2006 16/12/2006 6/13/2006 "6/13/2006 6/13/2006 6/13/2006 6/13/2006 6/13/2006 6/14/2006 6/16/2006 6/21/2006 6/26/2006 0 6/27/2006 6/29/?2006 6/29/2006 K-40 Gr. Alpha:

Gr. Beta K-40 H-3 Gr. Beta K-40 Gr. Beta K-40 Gr. Beta K Be-7 Gr. Beta K-40 K-40 Gr. Alpha Gr. Beta K-40 Co-60 Cs-1 37.

K-40 K-40 H-3 H-3 K-40 Gr. Beta Be-7 Be-7 Be-7 Gr. Beta K-40 Be-7 Gr. Beta K-40 Gr. Alpha Gr. Alpha Gr. Alpha K-40 Sr-90 K-40 Gr. Beta 1032.30 +/- 91.12 4.85 +/- 1.68 8.94 +/- 1.46 1412.40 +/- 119.10 8175.00 +/- 252.00 8.89 +/-0.18 5.60 +/- 0.71 19.57 +/- 1.99 12.55 +/- 0.89 9.85 +/- 0.79 2.42 +/- 0.38 1.41 +/- 0.19 5.03 +/- 0.18 2.21 +/- 0.26 1424.20 +/- 118.20 0.13 +/- 0.06 4.53 +/- 0.19 6.02 +/-.0.66 0.18 +/-_0.03 1.97 +/- 0.09 11.03 +/- 0.76 1358.50 +/- 166.40 482.11 +/- 90.25 401.50 +/- 87.85 1717.10 +/-244.30 1.70 +/- 0.38 0.11 +/-0.01 0.08 +/- 0.02 0.08 +/- 0.02 1.85 +/- 0.05 1.25 +/- 0.19 0.82 +/- 0.20 13.20 +/- 0.40 9.96 +/- 0.44 3.24 +/- 1.35 3.70 +/- 1.12 6.87 +/- 1.26 1403.50 +/- 118.80 0.59 +/- 0.34 1286.60 +/- 92.62 1.75 +/- 0.60 1103.60 +/- 120.50 4.12 +/- 1.62 9.14 +/- 1.36 1427.90 +/- 127.70.

8268.00 +/- 253.00-9.03 +/- 0.19 6.30 +/- 0.78 18.98 +/- 1.91 11.49 +/- 0.59 8.96 +/- 0.74 2.53 +/- 0.37 1.31 +/- 0.27 5.30 +/- 0.19 2.14 +/- 0.37 1318.80 +/- 110.50 0.16 +/- 0.07 4.47 +/- 0.18 5.33 +/- 0.66 0.15 +/- 0.03 2.01 +/- 0.09 10.45 +/- 0.78 1395.80 +/- 122.70 397.50 +/- 86.88 236.28 +/- 80.89 1893.10 +/- 223.30 1.93 +/- 0.38 0.11 +/-0.02 0.10 +/- 0.02 0.07 +/- 0.01 1.85 +/- 0.05 1.24 +/- 0.18 0.61 +/- 0.14 14.00 +/- 0.40 10.06 +/- 0.82 2.49 +/- 1.33, 3.09 +/- 1.16 4.77 +/- 1.09 1330.40 +/- 116.50 0.70 +/- 0.35 1358.60 +/- 158.40 2.51 +/- 0M59 1067.95 +/- 75.5,4 Pass 4.48 +/- 1.17 Pass 9.04.+/- 1.00 Pass 1420.15 +/- 87.31_,

Pass 8221.50 +/- 1'78.54*'

Pass 8.96 +/- 0.13 Pass 5.95 +/- 0.53 Pass 19.27 +/- 1.38 Pass 12.02 +/- 0.53 Pass 9.41 +/- 0.54 Pass 2.47 +/- 0.27 Pass 1.36 +/- 0.17 '

Pass 5.17 +/--0.13, Pass 2.18 +/- 0.23 Pass 1371.50'+/- 80.90 Pass 0.15 +/- 0.05 Pass 4.50 +/- 0.13 Pass 5.67 +/- 0.47, Pass 0.16 +/- 0.02 Pass 1.996+/- 0.06 Pass 10.74 +/- 0.54 Pass 1377.15 +/- 103.37 Pass 439.81 +/-.62.63 Pass 318.89 +/- 59.71 Pass 1805.10 +/-,165.49 Pass 1.82 +/-0.27" Pass 0.11+/- 0.01 Pass 0.09 +/- 0.01 Pass I

I I

"I I

I I

I AP-493.0, 4931 7/3/2006 E-4399, 4400 7/5/20061 E-4399, 4400 7/5/2006 G-4420, 4421 7/5/2006 G-4420, 4421 7/5/2006 G-4420, 4421 7/5/2006 DW-60432, 60433 7/6/2006 DW:60514, 60515 7/10/2006 DW-60449, 60450 7/11/2006 MI-4599, 4600 7/12/2006 MI-4599, 4600 7/12/2006 MI-4667, 4668 7/12/2006 LW-4823, 4824 7/14/2006 0..08 +/-.0.01

.1.85 +/- 0.04 1.25 +/--9.13 0.72+/- 0.12 13.60 -0.28 10.01 +/- 0.47 2.87 +/- 0.95 3.40 +/-.0.81 5.82 +/- 0.83 1366.95 +/- 83.20 0.65 +/- 0.24 1322.60 +/- 91.75 2.13 +/- 0.42 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-2 I

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

-Second Result Result Acceptance DW-60502, 60503 7/19/2006 DW-60526, 60527 7/21/2006 DW-60539, 60540 7/21/2006 MI-5125, 5126 7/25/2006 DW-60609, 60610 7/26/2006 DW-60621, 60622 7/31/2006 SL-5265, 5266 8/1/2006 SL-5265, 5266 8/1/2006 SL-5265, 5266 8/1/2006 SL-5265, 5266 8/1/2006 VE-5286, 5287 8/1/2006 VE-5286, 5287 8/1/2006 VE-5286, 5287 8/1/2006 SW-5383, 5384 8/8/2006 SW-5383, 5384 8/8/2006 SW-5971, 5972" 8/8/2006 VE-5404, 5405 8/10/2006 VE-5404, 5405 8/10/2006 DW-5480, 5481 8/11/2006 DW-60645, 60646 8/15/2006 W-5602, 5603 8/16/2006 DW-60634, 60635 8/18/2006 DW-60634, 60635 8/18/2006 MI-5793, 5794 8/22/2006 SWU-6150, 6151 8/29/2006 DW-60657, 60658 8/29/2006 CF-7450, 7451 9/5/2006 SL-6085, 6086 9/5/2006 SL-6085, 6086 9/5/2006 SL-6085, 6086 9/5/2006 DW-60695, 60696 9/11/2006 LW-6266, 6267 9/13/2006 MI-6424, 6425 9/19/2006 DW-60715, 60716 9/19/2006.

SO-6597, 6598 9/22/2006 SO-6597, 6598 9/22/2006 SWU-6718, 6719 9/26/2006 SO-6668, 6669 9/27/2006 Gr. Alpha Gr. Alpha Gr. Alpha K-40 Gr. Alpha Gr. Alpha Be-7 Sr-90 Gr. Beta K-40 Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta H-3 Be-7 K-40 H-3, Gr. Alpha H-3 Gr. Alpha Gr. Beta K-40 Gr. Beta Gr. Alpha Be-7't Co-60 Gr. Beta K-40 Gr. Alpha Gr. Beta Sr-90 Gr. Alpha Cs-137 K-40 Gr. Beta Cs-137 16.27 t 2.49 14.06 t 1.82 5.09 +/- 0.95

.1480.60 +/- 118.30 1.00 + 1.10 3.70 + 1.00 1.10 t 0.46 0.10 +/- 0.03 4.41 +/- 0.41 1.19 +/- 0.52 1.21 +/- 0.30 9.67 +/- 0.35 6.25 +/- 0. 81 3.24 + 1.35 4.86 +/- 0.86 119.90 +/-78.14 0.77 +/- 0.24 4.71 +/- 0.63 169.08 +/- 85.52 10.41 +/- 1.78 2118.79 +/- 151.55 12.99 +/- 1.84 10.51 +/- 1.33 1264.00 +/- 115.00 1.84 +/- 0.28 2.33 +/- 0.80 0.78 +/- 0.45 0.22 +/- 0.03 5.47 +/- 0.69 1.91 +/-0.28 3.93 +/- 1.17 3.09 + 0.48 0.78 +/- 0.38 1.30 +/- 1.00 0.18 +/- 0.04 10.25 +/- 0.66 3.45 +/- 1.21 0.13 +/- 0.04 13.04 +/- 0.90 21.41 +/- 3.21 15.57 +/- 1.77 6.23 +/- 1.05.

1402.60 +/- 120.80

.2.70 +/-1.30 1.90 +/- 0.80 1.38 +/- 0.52 0.16 +/-0.03 3.46 +/- 0.57 0.87 +/- 0.52 1.32 +/- 0.20 9.37 +/- 0.35 6.50 +/- 0.48 2.94 +/- 1.35 5.46 +/- 0.87 144.41 +/- 79.23 1.01 +/- 0.26 4.01 +/- 0.58 133.65 +/- 83.96 10.97 +/- 1.85 2181.82 +/- 153.09 9.67 +/- 1.61 8.61 +/- 1.18 1377.00 +/- 121.00 1.81 +/- 0.28 2.90 +/- 0.78 0.78 +/- 0.27 0.21 +/- 0.02 4.63 +/- 0.58 2.06 +/- 0.41 4.62 +/- 1.12 2.98 +/-,0.48 1.11 +/- 0.37.

2.23 +/- 1.01 0.18 +/- 0.04 10.11 +/-0.64 2.78 +/- 1.19 0.13 +/- 0.02 12.41 +/- 0.54 18.84 +/- 2.03 14.82 +/- 1.27 5.66 +/- 0.71 1441.60 +/-84.54 1.85 +/- 0.85 2.80 +/- 0.64 1.24.+/- 0.35 0.13 +/- 0.02 3.94 +/- 0.35 1.03 +/- 0.37

1.27 +/- 0.18 9.52 +/- 0.25 6.38 +/- 0.47 3.09 +/- 0.96 5.16 +/- 0.61 132.15 +/- 55.64 0.89.+/- 0.18 4.36 - 0.43 151.36 +/-59.92 10.69 +/- 1.28 215.0.30 +/-107.71 11.33 +/-1.22 9.56 +/- 0.89 1320.50 +/- 83.47 1.82 +/- 0.20 2.62 +/-.0.56 0.78 +/-0.26 0.22 +/- 0.02 5.05 +/- 0.45 1.99 +/- 0.25 4.28 +/- 0.81 3.03.+/- 0.34 0.95 +/-0.27 1.77 +/- 0.71 0.18 +/-0.03 10.18 +/-0.46 3.12 +/- 0.85 0.1

+/- 0.02.

12.72 +/-0.53 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass SO-6668,6669 9/27/2006 K-40 A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-6760, 6761 G-6797,6798 G-6797,6798 G-6797,6798 b AP-7531, 7532 AP-7552, 7553 AP-7573, 7574 SO-7103, 7104 SO-7103, 7104 10/2/2006 10/2/2006 10/2/20016 10/2/2006 10/3/2006 10/3/2006 10/13/2006 10/4/2006 10/4/2006 DW-60759, 60760 10/5/2006 MI-7037, 7038 10/10/2006 VE-7058, 7059 10/10/2006 VE-7058, 7059 10/10/2006 VE-7058, 7059 10/10/2006 SS-7079, 7080 160/.10/2006

SS-7079, 7080 1O/1.0/2006 SS-7079, 7080 10/10/2006 MI-7208, 7209 10/11/2006 CF-7450, 7451 10/18/2006 LW-7945, 7946 1.0/26/2006 F-7971, 7972 10/129/2006-SWU-8194, 8195 10/31/2006 BS-8017, 8018 11/1./2006 BS-8017, 8018 11/1/2006 LW-8215, 8216 11/1/2006 F-8345, 8346 11/2/2006 BS-8366, 8367 11/2/2006 MI-8083, 8084 11/6/2006 WW-8259, 8260 11/7/2006:

MI-8484, 8485 11/22/2006 SO-8619, 8620 11/27/2006 SO-8619, 8620 11/27/2006 SO-8619, 8620 11/27/2006 SO-8619, 8620 11/27/2006 SWT-8641, 8642 11/29/2006 SWT-943.6, 9437 12/26/2006 K-40 1413.10 +/- 113.20 Be-7 4.70 +/- 0.31.

Gr. Beta 6.89 +/- 0.26 K-40 5.39 +/- 0.35 Be-7 0.07 +/- 0.01 Be-7 0.08 +/-.0.02 Be-7 0.08 +/- 0.02 Cs-137 0.25 +/- 0.05 K-40 12.95 +/- 1.12 Gr. Alpha 4.93 +/- 0.97 K-40 1326.10 +/- 115.20 Gr. Alpha 0.18 +/- 0.11 Gr. Beta 9.21 +/- 0.34 K-40 10.90 +/- 0.65 Cs-137 0.04 +/- 0.01 Gr. Beta 12.23 +/- 2.46 K-40 7.23 +/- 0.36 K-40 1295.20 +/- 116.90

,K-40 20.40 +/- 0.84 Gr. Beta 1.30 +/- 0.37 K-40 3.63 +/- 0.54 Gr. Beta 1.84 +/- 0.28 Gr. Beta 10.54 +/- 1.72 K-40 10.00 +/- 0.53 Gr. Beta 2.23 +/- 0.61 K-40 2.84 +/- 0.42 K-40 13.69 +/- 0.66 K-40 1295.00 +/- 121.20 H-3 337.00 +/- 95.00 K-40 1405.80 +/- 87.06 Cs-1 37 0.74 +/- 0.08 Gr. Alpha 16.54 +/- 5.65 Gr. Beta 24.99 +/- 3.88 K-40 12.21 +/-1.11 Gr. Beta 2.83 +/- 0.47 Gr. Beta 2.39 +/- 0.64 1187.30 +/- 155.20 4.56 +/- 0.41 7.04 +/- 0.24 4.36 +/- 0.47 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01.,

0.27 +/- 0.06, 12.22 +/- 1.07 5.04 +/- 1.03 1251.40 +/- 115.70 0.32 +/- 0.14 8.83 +/- 0.36

10.42 +/- 0.80 0.04 +/- 0.02 -

11.76 +/- 2.23.

7.37 +/- 0.40 1386.90 +/- 119.10 19.54 +/- 0.99

.1.44 +/- 0.36 3.33 +/- 0.43 1.43 +/- 0.28 10.17 +/- 1.73 9.60 +/- 0.69..

1.64 +/- 0.37 2.89 +/- 0.40 13.61 +/- 0.78 1374.80 +/- 162.80 295.00 +/- 93.00 1390.70 +/- 103.60 0.69 +/- 0.06 12.24 +/- 4.90 28.66 +/- 3.95 12.92 +/- 0.83 2.89 +/- 0.45-2.25 +/- 0.60 1300.20,+/- 96.05 4.63 +/- 0.26 6.97 +/-0.18-4.88 +/- 0.29 -

0.08 +/- 0.01.

0.08 +/- 0.01 0.08 +/- 0.01 7 0.26 +/- 0.04:.

12.58 +/- 0.77,.

.4.99 +/- 0.71.,

1288.75 +/- 81.64 0.25 +/- 0.09 9.02 +/- 0.25 10.66 +/- 0.52

.0.04 +/- 0.01.

11.99 +/- 1.66

.7.30 +/- 0.27.

1341.05 +/- 83.44 19.97+/- 0.65.

1.37 +/- 0.26, 3.48 +/- 0.34' 1.64 +/- 0.20 10.36 +/- 1.22 9.80 +/- 0.44

,1.93,+/- 0.35 2.86 +/-0.29..

13.65 +/- 0.51 1334.90 +/- 101.48*

316.00 +/-E66.47 1398.25 +/- 67.66 0.71. +/- 0.05 14.39 +/- 3.74 26.82 +/-2.77 12.57 +/- 0.69 2.86 +/- 0.33 2.32 +/- 0.44 Pass Pass Pass Fail Pass I 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 I

I I

I i

I 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).

b 200 minute count time or longer, resulting in lower error.

A5-4

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1 082 STVE-1 082 STVE-1 082 STVE-1082 STVE-1082:

STVE-1082' STVE-1082 STVE-1082 STVE-1 082 STVE-1 082 STVE-1 082 STVE-1082.'

STSO-1083, STSO-1083 STSO-1083 STSO-1 083 e STSO-1 083 STSO-10831" STSO-1083.

STSO-1083 STSO-1083 STSO-1083 STSO-1083 STSO-1083 STSO-1083 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06

, 01/01/06 01/01'/06 01/01/06 01/01/06 01/01/06

01/01/06 0 01'/01/06 01/01/06

'01/01/06 01/01/06

.01/01/06 01/01/06 01/01/06 01/01/06 "01/01/06

'01/01/06 Am-241 Co-57 Co-60 Cs-134 Cs-137' Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 Am-241 Co-57 Co-60`

Cs-134 Cs-137 K-40:

Mn-54 Ni-63 Pu-238 Pu-239/40 U-233/4 U-238 Zn-65 Gr. Alpha Gr. Beta Am-241 Co-57 Co-60 Cs-134 Cs-137 Pu-238 Pu-239/40 Sr-90 U-233/4.

U-238 Zn-65 0.16 +/- 0.06 10.40 +/- 0.20 5.00 +/- 0.20

< 0.20 3.40 +/- 0.20 6.90 +/- 0.20 0.08 +/- 0.03 0.17 +/- 003 1.40 +/- 0.20 0.24 +/- 0.05 0.19 +/-0.04 11.10 +/-0.50 0.16 8.58 4.52 0.00 3.07 6.25 0.14 0.16 1.56 0.21 0.22 9.80 54.60 +/- 5.50 762.90 +/- 12.70 504.90 +/- 3.10

< 1.70 406.50 +/- 3.70 719.20 +/- 18.40 415.60 +/- 4.80 261.40 +/- 14.70 14.60 +/- 2.90 14.60 +/- 2.40 13.50 +/- 1.70 15.40 +/- 1.80 783.40 +/- 7.00 0.26 +/- 0.02 0.51 +/- 0.03 57.08 656.29 447.10 0.00 339.69 604.00 346.77 323.51 61.15 45.85:

37.00 38.85 657.36 0.11 - 0.20 6.00 -11.15 3.16 -5.88 2.15-4.00 4.37-8.12 0.10.0.18 0.11'- 0.21 1.09' 2.03 0.15 -0.27 0.15- 0.28 6.86 -12.74 39.96 - 74.20 459.40 - 853:18 312.97 - 581.23 237.78 441.60 422.80 - 785.20

242.74 - 450.80 226.46 - 420.56 42.81 - 79.50 32.09 - 59.61 25.90 - 48.10 27.20 - 50.50 460.15 -854.57 0.00 - 0.72 0.24 - 0.72 Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

. Pass Pass Fail Fail Fail Fail Pass STAP-1084 STAP-1084 STAP-1 085 STAP-1085 STAP-1085 STAP-1085 STAP-1085 STAP-1085' STAP-1085 e STAP-1085 STAP-1085 STAP-1085 STAP-1 085 0.36 0.48 01/01/06 01/01/06 O 1/01/06 01/01/06 S,01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 0.12 +/- 0.02 4.32 +/- 0.10 2.24 +/-0.16 2.96 +/- 0.19 2.64 +/- 0.20 0.03 +/- 0.01

< 0.01 0.77 +/- 0.21 0.03 +/- 0.01 0.02 +/- 0.01 3.94 +/- 0.44 0.09 4.10 2.19 2.93 2.53 0.07 0.00 0.79 0.02 0.02 3.42 0.07 -0.12 2,87 - 5.32 1.53-2.84 2.05-3.81 1.77-3.29 0.05 - 0.09 0.55 -1.03.

0.01- - 0.03.

0.01 - 0.03 2.40 - 4.45 Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass-Pass Pass A6-1

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1 086 STW-1 086 STW-1 086 STW-1 086 STW-1 086 e STW-1086 STW-1 086 STW-1 086 STW-1086 STW-1 086 STW-1086 e STW-1086 STW-1 086 STW-1 086 STW-1086 STW-1 086 STW-1 087 STW-1087 STVE-1098 STVE-1098 g STVE-1098 STVE-1098 STVE-1098 STVE-1 098 STSO-1 099 STSO-1099 STSO-1099 STSO-1099 STSO-1099 STSO-1099 STSO-1099 STSO-1 099 STSO-1099 STSO-1099 STSO-1099 STSO-1099 STSO-1 099 STAP-1100 STAP-1 100 STAP-1 100 STAP-1100 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 01/01/06 0:1/01/06 01/01/06 07/01/06 b 07/01/06 07/01/06 07/01/06

.07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06' 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 07/01/06 Am-241 1.29 +/- 0.05 Co-57 177.10 +/- 1.00 Co-60 158.30 +/- 1.00 Cs-134 96.40 +/- 1.50 Cs-137

< 0.80 Fe-55 102.50 +/- 18.10 H-3 956.60 +/- 16:50 Mn-54 335.30 +/- 2.20.

Ni-63 62.90 +/- 3.60 Pu-238 0.96 +/- 0.07 Pu-239/40

< 0.20 Sr-90 12.80 +/- 1.60 Tc-99 22.30 +/- 1.20 U-233/4 2.02 +/- 0.12 U-238 2.03 +/- 0'.12 Zn-65

, 249.50 +/- 3.40 Gr. Alpha 0.59 +/- 0.10 Gr. Beta..

1.69 +/- 0.07 Co-57

< 0.14 Co-60 6.89 +/- 0.17 Cs-134 8.46 +/- 0.16 Cs-137 6.87 +/- 0.29 Mn-54 10.36 +/- 0.29 Zn-65 7.46 +/- 0.50 1.30 166.12 153.50 95.10 0.00 129.60 952.01 315.00 60.34, 0.91 0.00 13.16 23.38 2.09 2.17 228.16 0.58 1.13 0.00 5.81 7.49 5.50 8.35 5.98 0.91 - 1.69 116.28 -215.96 107.45 - 199.55 66.57 - 123.63 90.72 - 168.48 666.41 - 1238.00 220.50 - 409.50 42.24-78.44 0.70-1.30 Pass

Pass, Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 9.21 16.37 1.46 1.52 159.71

-17.11

-.30.39

-2.72

- 2.82

- 296.61 0.0.0- 1.16 0.56-1.70 4.06-7.55 5.24 - 9.73 3.85 -7.14

.5.85 -10.86 4.19 -7.78 Am-241 Co-57 Co-60 Cs-134

'Cs-137 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 U-233/4 U-238

'Zn-65 Am-241 Co-57 Co-60 Cs-134 130.00 +/- 11.60 784.90 +/- 3.80 2.10 +/- 0.90 500.70 +/- 7.40 624.20 +/- 4.90 701.30 +/- 3.40 699.20 +/- 5.20 614.40 +/-17.1.0 79.90 +/- 5.80

< 0.70 150.50 +/- 5.90 151.60 +/- 6.00 1021.90 +/- 9.20 0.16 +/- 0.03 2.17 +/- 0.06 1.38 +/- 0.07 2.52 +/- 0.13 105.47 676.33 1.98 452.13 525.73 604.00

594.25 672.30.

82.00 0.00 152.44 158.73 903.61 0.14 2.58 1.58 3.15 73.83 - 137.11 473.43 - 879.23 0.00- 5.00 316.49 -587.77 368.01 683.45 423:00 - 785.00 415.98 -772:52 470.60 - 874.00 57.00-I107.00, 106.71 - 198.17 111.11 -206.35 632.53 -1175.00 0.10 -0.19' 1.81 -3.36 1.10 -2.05 2.20 - 4.09 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

, Pass Pass Pass Pass Pass Pass I

I I

I U

I I

Pass Pass Pass Pass A6-2

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

Concentration b

'Known Control:

Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STAP-1100 07/01/06 Cs-137 1.64 +/- 0.08 1.81 1.26 -2.35 Pass STAP-1100 07/01/06 Mn-54 1.76 +/- 0.18 1.92 1.34 -2.50 Pass STAP-1100 07/01/06 Pu-238 0.09 +/- 0.02 0.12 0.08 -0.15 Pass STAP-1100 07/01/06 Sr-90 0.66 +/- 0.21 0.62 0.43 -0.81 Pass STAP-1100 07/01/06 U-233/4 0.15 +/-0.02 0.13 0.09 -0.17 Pass STAP-1100 07/01/06 U-238 0.13 +/- 0.02 0.14 0.10 '0.18 Pass STAP-1 100 e 07/01/06 Zn-65

< 0.07 0.00 Pass STAP-1 101 07/01/06 Gr. Alpha 0.08 +/- 0.03 0.29 0.00 -0.58 Pass STAP-1101 07/01/06 Gr. Beta 0.41 +/- 0.05 0.36 0.18 -0.54 Pass STW-1102 07/01/06 Gr. Alpha..

0.76 +/- 0.07 1.03 0.00 -2.07 Pass STW-1102 07/01/06 Gr. Beta 1.23 +/- 0.06 1.03 0.52-71.54 Pass STW-1103 07/01/06 Am-241 1.86 +/- 0.09 2.31 1.62 -3.00 Pass STW-1103

.07/01/06 Co-57 224.10 +/- 1.20 213.08 149.16.- 277.00 Pass STW-1103 07/01/06 Co-60 49.40 +/- 0.50 47.50 33.20 '61.80 Pass STW-1103 07/01/06 Cs-134

+/-112.70 0.90 112.82 78.97 -146.66 Pass STW-1103 07/01/06 Cs-137 206.60 +/- 1.40

'196.14 137.30 -254.98 Pass STW-1103 07/01/06 Fe-55 138.40 +/- 5.406 165.40 115.80 -215.00 Pass STW-1103 07/01/06 H-3 446.50 +/- 11.80 428.85 300.20 - 557.50 Pass STW-1 103 e 07/01/06 Mn-54

< 0.30 0.00 Pass STW-1103 07/01/06 Ni-63 116.70 +/-3.60" 118.62 83.03 - 154.21 Pass STW-1103 07/01/06 Pu-238 1.27 +/- 0.07 1.39 0.97-1.81 Pass STW-1103 07/01/06 Pu-239/40 1.67 +/- 0.08 1.94 1.36 -2.52 Pass STW-1103 07/01/06 Sr-90 16.40 +/- 1:90 15.69 10.98 - 20.40 Pass STW-1103 07/01/06 Tc-99 29.40 +/- 1.10 27.15 19.00- 35:29 Pass STW-1103 07/01/06 U-233/4 1.97 +/- 0.08 2.15 1.50 -2.80 Pass STW-1103 07/01/06 U-238 1.97 +/- 0.08 2.22 1.55.- 2.89 Pass STW-1103 07/01/06 Zn-65 192.50 +/- 2.40 176.37 123.46 - 229.28 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's.

Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil); Bq/L (water) or Bq/total sample (filters, vegetation).

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

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

e Included in the MAPEP as a false positive.

f Difficulties with the analyses for transuranics isotopes in solid samples (Filters, Soil and vegetation),

were attributed to incomplete dissolution of the samples. Soil samples were repeated, results of reanalyses:

Pu-238, 53.1 +/- 5.3 bq/kg. Pu-239/240, 42.4 +/- 4.7 bq/kg. U-233/4, 33.3 +/- 3.5 bq/kg. U-238, 35.5 +/- 3.6 bq/kg.

g The July vegetation sample was provided in two separate geometries, (100 ml. and 500 ml.). Results reported here used the 500 ml.. standard.size geometry. Results for the 100 ml. geometry showed approximately a 15% higher bias.

A6-3

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX B, 2006 REMP DATA

SUMMARY

REPORTS Appendix B Page 44

m i_

m -

m n-n m

m m

Air Gamma Spectral Summary Report 2006 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 Be-7 N/A 0.06 0.06 4

0.06 0.06 pCi/m3 28 27 /28 23 /24 0.70 3 /20 4/

4 0.04 - 0.08 0.04 - 0.08 S

0.05 -0.07 0.05 - 0.08 Air Co-58 N/A LLD pCi/m3 28 Air Co-60 N/A LLD pCi/m3 28 Air Cs-134 0.04 LLD pCi/m3 28 Air Cs-137 0.05 LLD pCi/m3 28

Air Gross Beta Summary Report 2006 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 andRange Dir ection andRange and Range

.a..

U n. s.......

p e o e d......................

.L.

)..................

a n l* n

.n a g

............D ! e c t o...

n....

R._~

an g Air Gross Beta 0.01 0.02 0.02 5

0.02 0.02 pCi/m3 371 371 /371 318 /318 0.60 53 /53 53 /53 0.01

- 0.04 0.01 - 0.04 SW 0.01

-0.04 0.01

- 0.04 m

mmmmm~

m m m m m m

Air Iodine Summary Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Number of Sample Type Analyses aiid Units Performed Mean of Results from Mean of Results from LcationWith.Highest.......

.Mean Mean of Results from Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Limit Number Detected/Number Collected: Number Detected/Number Collected i Distance and Number Detected/Number Collected Number Detected/Number Collected (LLD) and Range and Range Direction and Range and Range Air pCi/m3 1-131 371 0.05 LLD

Fish Gamma Spectral Summary Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units J

t..

Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Type and Number of Analyses Performed Co-58 2

Mean of Results from Mean of Results from Location with Highest AnnualiMean Mean of Results from Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Limit Number Detected/Number Collected Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected (LLD) and Range and Range Direction

.and Range and Range 97.00 97.00 Co-60 2

Cs-134 2

Cs-137 2

Fe-59 2

K-40 2

97.00 112.00

195.00 LLD LLD LLD LLD LLD

'N/A 1,428.60 2/2 1,280.10-1,577.10 1,280.10 1/

1 1,280.10 - 1,280.10 32 15.80 WSW 1,577.10 1/8 1,577.10

- 1,577.10 1,577.10 1 / 1 1,577.10 - 1,577.10 Mn-54 97.00 2

Zn-65 195.00 2

LLD LLD m

m m

m mm..m.....-...

Food Products Gamma Spectral Summary Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 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 Type and Number of Analyses Performed Be-7 35 Lower Limit (LLD)

N/A Mean of Results from All Locations and Number Detected/Number Collected and Range 490.04 21 / 35 215.25 - 1,764.20 Mean of Results from All Indicator Locations and Number Detected/Number Collected.

and Range 507.94 18 / 30 215.25 -

1,764.20 Location with Highest Annual Mean.

t. w it e

s.

M a J..

Location # and :

Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range 382.60 3/5 235.94 - 565.83 37 1.50 ENE 646.50 9 / 105 225.40

- 1,764.20 Co-58 35 C6-60 35 Cs-134 35 Cs-137 35 1-131 35 K-40 35 N/A N/A 45.00 60.00 45.00 LLD LLD LLD LLD LLD N/A 5,214.31 35 / 35 3,335.50

- 7,674.40 5,264.36 30 / 30 3,335.50 - 7,674.40 16 0.80 S

5,746.99 5 / 35 4,862.60

- 6,702.20 4,914.04 5/5 3,669.90 - 7,189.70

Milk Gamma Spectral Summary Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Number of Analyses Performed Mean of Results from Mean of Results from Location with_.1HighestAnnual_Mean:

Mean of Results from Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Limit Number Detected/Number Collected] Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected (LLD) and Range and Range Direction and Range and Range Sample Type and Units

.U ! s...

Milk pCi/L Milk pCi/L Milk pCi/L Milk pCi/L Ba-140 45.00 50 Cs-134 11.00 50 Cs-137 13.00 50 LLD LLD LLD K-40 50 N/A 1,565.94 50 I 50 1,087.30 - 2,119.30 1,706.47 31 / 31 1,087.30 - 2,119.30 61 7.40 SE 1,798.65 13 / 65 1,431.80

- 2,119.30 1,336.65 19 I 19 1,108.30 -

1,979.60 Milk pCi/L La-140 11.00 50 LLD m m -

m m m m m m m m m m m m m

m-m Milk Iodine Summary Report 2006 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 with1 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

.a d. i ! s......

p } f r e.............

a...R. g....

a

.e..

D................................................

Rn g....................................

ane.......

Milk 1-131 0.75 LLD pCi/L 50

Sediment Gamma Spectral Summary Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Sediment pCi/kg dry Sediment pCi/kg dry Sediment pCi/kg dry Type and Mean of Results from Mean of Results from Location with H.ighest Annual Mean:

Mean of Results from Number of Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Analyses Limit Number Detected/Number Collected; Number Detected/Number Collected:

Distance and Number Detected/Number Collected Number Detected/Number Collected Performed (LLD) and Range and Range Direction and Range and Range Co-58 50.00 LLD 12 Co-60 12 Cs-134 12 140.00 112.00 LLD LLD Sediment pCi/kg dry Sediment pCi/kg dry Cs-137 135.00 12 K-40 N/A 12 480.42 5 / 12 145.25 - 907.86 14,449.88 12 / 12 7,917.80 - 25,552.00 204.18 3 / 10 145.25

- 308.79 12,338.66 10 I 10 7,917.80 17,405.00 32 15.80 WSW 894.77 2 / 10 881.68

- 907.86 894.77 2/2 881.68

- 907.86 25,006.00 2/2 24,460.00 - 25,552.00 32 25,006.00 15.80 2 /10 WSW 24,460.00

- 25,552.00 m

m -

m m m -

m -

m m m -

m M M---

TLD Gamma Dose Summary Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Type and Number of Analyses Performed Mean of Results from Mean of Results from Location with Highest Annual Mean:

Mean of Results from M ean.o..e...s.f...Me.n.f...slts..rm...

l o t o o a i n n

Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Limit Number Detected/Number Collected. Number Detected/Number Collected Distance and Number Detected/Number Collected I Number Detected/Number Collected (LLD) and Range and Range Direction and Range and Range Sample Type and Units TLD TLD Direct 112 Direct 112 Direct 27 1.00 1.00 12.93 112 /.112 8.45 - 18.23 12.58 112 / 112 8.93 16.91 64.61 27 / 27 53.40 - 79.99 12.91 104 / 104 8.45 -

18.22 12.62 104 / 104 8.93 -

16.91 33 4.50 S

33 4.50 S

16.88 4/4 15.47

- 18.00 16.31 4/4 14.67

- 16.91 79.99 1 / 1 79.99 - 79.99 13.26 8/8 10.27 -

18.23 12.01 8/8 10.29 -

12.96 TLD mR/365 days 1.00 64.77 25 / 25 53.40 - 79.99 36 3.90 WSW 62.56 2/2 60.22 - 64.90

Water Gamma Spectral Summary Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Water pCi/L 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 Type and Number of Analyses Performed Mn-54 56 Nb-95 56 Zn-65 56 Mean of Results from Mean of Results from Location with Highest Annual M-ean:

Mean of Results from Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Limit Number Detected/Number Collected Number Detected/Number Collected.

Distance and I Number Detected/Number Collected Number Detected/Number Collected (LLD) and Range and Range Direction and Range and Range 11.00 11.00 22.00 Zr-95 22.00 56 Ba-140 56 Co-58 56 Co-60 56 Cs-134 56 Cs-137 56 Fe-59

.56 La-140 56 45.00 11.00 11.00 11.00 13.00 22.00 11.00 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD m

m.

m.......

m

Water Gross Beta Summary Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units a n. n ~

Water pCi/L Type and Number of Analyses Performed

.F.!f.!.......

Gross Beta 56 Mean of Results from Mean of Results from Location with Highest Annual Mean:

Mean of Results from Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Limit Number Detected/Number Collected Number Detected/Number Collected' Distance and Number Detected/Number Collected Number Detected/Number Collected (LLD) and Range and Range

___Direction and Range and Range_

..L

.n... a *g.......

................... a n.R g e re ! o

.n R a n g e.......

d..R n.g. e 3 00 3.07 3.06 28 3.17 3.17 7 / 56 6 /44 22.00 1 / 12 1 /

12 3.00 - 3.17 3.00 - 3.15 ENE 3.17 - 3.17 3.17 - 3.17

Water Tritium Summary Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Water Water pCiIL Type and Number of Analyses Performed H-3 20 H-3 20 Mean of Results from i

Mean of Results from Location with Highest Annual Mean:

Mean of Results from Lower All Locations and All Indicator Locations and Location # and Mean and All Control Locations and Limit Number Detected/Number Collected: Number Detected/Number Collected Distance and Number Detected/Number Collected Number Detected/Number Collected (LLD) and Range and Range Direction and Range and Range 1,500.00 LLD i

1,500.00 LLD m m m m m m m -

m m m m -

U U

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX C, 2006 REMP DETAILED DATA REPORT Appendix C Page 45

Air Gamma Spectral Detail Report 2006 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 L.ocation Samnle Tvne Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 I

Air 3/29/06 Air 6/28/06 Air 9/27/06 Air 1/3/07 0.055 +/- 0.011 0.073 +/- 0.007 0.064 +/- 0.009 0.048 +/- 0.008 0.001 0.000 0.000 0.000 K

K 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 3/29/06 6/28/06 9/27/06 1/3/07 0.052 +/- 0.008 0.065 +/- 0.009 0.062 +/- 0.009 0.058 +/- 0.011

< 0.014 0.068 +/- 0.011 0.068 +/- 0.007 K 0.000

0.000

0.000

0.000

0.002

0.001

0.000 0.000 0.000 0.001 0.000 0.002 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.000 Air Air Air 3/29/06 6/28/06 9/27/06

Air Gamma Spectral Detail Report 2006 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 Collection Date Be-7 Co-58 Co-60 Location Sample Type Cs-134 Cs-137 4

Air 5

Air 6

Air 1/3/07 3/29/06 6/28/06 9/27/06 1/3/07 3/29/06 6/28/06 9/27/06 1/3/07 0.053 +/- 0.009 0.050 +/-/- 0.010 0.063 +/- 0.009 0.063 +/- 0.010 0.058 +/- 0.009 0.047 +/- 0.010 0.085 +/- 0.015 0.071 +/- 0.012 0.049 +/- 0.008 0.058 +/- 0.008 0.062 +/- 0.010

< 0.001

< 0.000

< 0.001

0.001

< 0.001

0.000

< 0.000

0.000

< 0.000

< 0.001

0.000

< 0.000

0.000

< 0.001

< 0.000

0.000

< 0.000

< 0.001

< 0.000

0.000 0.000

0.000 6

6 7

7 Air Air Air Air 3/29/06 6/28/06

~

= -~

w

~-1 0

It UW M

1 "-

Air Gamma Spectral Detail Report 2006 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 Air 9/27/06 7

Air 35 Air 35 Air 35 Air 1/3/07 3/29/06 6/28/06 9/27/06 0.060 +/- 0.008 0.055 +/-0.009 0.043 +/-0.008 0.081 +/-0.011 0.067 +/-/-0.011

< 0.000

0.000

0.000

0.000

0.000

0.000

0.001

0.000

0.000

0.001

0.000

0.000

0.000

0.000

< 0.000

0.000 K 0.000 K 0.000 K 0.000

< 0.000 35 Air 1/3/07 0.054 +/- 0.007

< 0.000

Air Gross Beta Detail Report 2006 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 Collection Date 1/4/06 1/11/06 1/18/06 1/25/06 2/1/06 2/8/06 2/15/06 2/22/06 3/1/06 3/8/06 3/15/06 3/22/06 3/29/06 4/5/06 4/12/06 Sample Type Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air 1

7 0.020 +/- 0.003 0.023 +/-,0.003 0.026 +/- 0.003 0.023 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.026 +/- 0.003 0.023 +/- 0.003 0.026 +/- 0.003 0.022 +/- 0.003 0.024 +/- 0.003 0.025 +/- 0.003 0.021 +/- 0.003 0.022 +/- 0.003 0.031 +/- 0.003 0.030 +/- 0.003 0.023 +/- 0.003 0.024 +/-0.003 0.014 +/- 0.003 0014 +/- 0.003 0.024 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.018 +/- 0.003 0.010 +/- 0.002 0.010 +/- 0.002 0.022 +/- 0.003 0.020 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.003 3

4 5

0 35 0.022 +/-/- 0.003 0.020 +/- 0.003 0.024 +/- 0.003 0.021 -0.003 0:017 +/- 0.003 0.017 +/- 0.003 0.023 +/- 0.003 0.022 +/- 0.003 0.024 +/-/- 0.003 0.023 +/- 0.003 0.021 +/- 0.003 0.023 +/- 0.003 0.019 +/- 0.003 0.018 +/- 0.003 0.030 +/- 0.003 0.031 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 0.014 +/- 0.002 0.015 +/- 0.003 0.023 +/-0.003 0.021 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 0.009 +/- 0.002 0.011 +/- 0.002 0,020 +/- 0.003 0.019 +/- 0.003 0.015 +/- 0.003 0.018 +/- 0.003 0.023 +/- 0.003 0.025 +/- 0.003 0.018 +/- 0.003 0.022 +/- 0.003 0.028 +/- 0.003 0.023 +/- 0.003 0.023 +/- 0.063 0.027 +/- 0.003 0.026 +/- 0.003 0.015 +/- 0.003 0.023 +/- 0.003 0.019 +/-0.003 0.012 +/- 0.003 0.022 +/- 0.003

.0.019 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0.020 +/-*0.003 0.022 +/-0.003 0.032 +/- 0.003 0.024 +/- 0.003 0.021 +/- 0.003 0.030 +/- 0.003 0.024 +/- 0.003 0.014 +/-0.003 0.024 +/- 0.003 0.021 +/- 0.003 0.009 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 0.023 +/- 0.003 0.026 +/- 0.003

'0.021 +/- 0.003 0.022 +/- 0.003 0.030 +/- 0.003

-0.025 +/- 0.003 0.024 +/- 0.003 0.023 +/- 0.003 0.020 +/- 0.003 0.010 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 go

-o It lo so A" W M

W m

ý al og tm'

-VAM WI"

-Iw

-ý ý I

- u7--

Air Gross Beta Detail Report 2006 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 Collection Date 4/19/06 4/26/06 5/3/06 5/10/06 5/17/06 5/24/06 5/31/06 6/7/06 6/14/06 6/21/06 6/28/06 7/5/06 7/12/06 7/19/06 7/26/06 Sample Type 7

Air 0.018+/-0.003 0.018 +/- 0.003 Air 010144+/- 0.003 0.013 +/- 0.002 Air 0.020 +/- 0.003 0.019 +/- 0.003 Air 0.018 +/- 0.003 0.0.18 +/- 0.003 Air 0.014 +/- 0.003 0.012 +/- 0.002 Air 0.010 +/-0.002 0.010 +/- 0.002 Air 0.028 +/- 0.003 0.025 +/- 0.003 Air 0.017 +/-0.003 0.017 +/- 0.003 Air 0.014 +/- 0.003 0.013.+/- 0.003 Air 0.022 +/- 0.003 0.022 +/- 0.003 Air 0.020 +A 0.003 0.0.18 +/- 0,003 Air 0.025 +/- 0.003 0.025 +/- 0.003 Air 0.023 +/- 0.003 0.018 +/- 0.003 Air 0.028 +/- 0.003 0.023 +/- 0.003 Air 0.027 +/- 0.003 0.026 +/- 0.003 3

35 0.015 +/- 0.003 0.017 +/- 0.003 0.014 +/--0.003 0.014 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.015 +/- 0.003 0.017 +/- 0.003, 0.010 +/- 0.002 0.009 +/- 0.003 0.030 +/- 0.003 0.030 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.093 0.014 +/- 0.003 0.016 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.025 +/- 0.003 0.028 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.003 0.026 +/- 0.003 0.023 +/- 0.003 0.025 +/- 0.003 0.029 +/- 0.003 Location 4-0.019 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.003 0.021 +/- 0.003 0.015 +/- 0.003 0.009 +/- 0.002 0.028 +/- 0.003 0.018 +/- 0.003 0.013 +/- 0.003 0.023 +/- 0.003 0.017 +/- 0.003 0.024 +/- 0.003 0.019 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 5

0.019 +/-0.003 0.015 +/- 0.003 0.019 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.009 +/- 0.002 0.028 +/- 0.003 0.019 +/- 0.003 0.015 +/-- 0.003 0.025 +/- 0.003 0.021 +/- 0.003 0.028 +/- 0.003 0.022 +/- 0.003 0.024 +/- 0.003 0.028 +/- 0.003 6

0.018 +/- 0.003 0.013 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.014 +/- 0.003 0.011 +/- 0.003 0.031 +/- 0.003 0.019 +/- 0.003 0.016 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.003 0.027 +/- 0.003 0.019 +/- 0.003 0.026 +/- 0.003 0.026 +/-/- 0.003

Air Gross Beta Detail Report 2006 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 5

Collection Date 8/2/06 8/9/06 8/16/06 8/23/06 8/30/06 9/6/06 9/13/06 9/20W06 9/27/06 10/4/06 10/11/06 10/18/06 10/25/06 11/1/06 11/8/06 Sample Type Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air 1

7 0.033 +/- 0.003 0.029 +/- 0.003 0.021 +/- 0.003 0.019 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 0:032 +/- 0.003 0.029 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.029 +/- 0.003 0.026 +/- 0.003 0.020 +/- 0.003 0.016 +/- 0.003 0.022 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.003 0.036 +/-0.003 0.032 +/- 0.003 3

35 0.036 +/- 0.003 0.034 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 0.021 +/- 0.003 0.019 +/- 0.003 0.027 +/- 0.003 0.028 +/- 0.003 0.032 +/-0.003 0.036 +/- 0.004 01014 +/- 01003 0.014 +/- 0.003 0.027 +/- 0.003 0.030 +/- 0.003 0.023 +/- 0'003 0.019 +/-/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0.018 +/-0.003 0.016 +/- 0.003 0.023 -/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 0.035 +/- 0.003 0.032 +/- 0.003 4

6 0.028 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.023 +/- 0.003 0.030 +/- 0.003 0.015 -/- 0.003 0.034 +/-0.003 0.019 +/- 0.003 01020 +/- 0.003 0.021 +/- 0.003 0.017 +/- 0.003 0.017 +/- 01003 0.020 +/- 0.003 0.026 +/- 0.003 0.033 +/- 0.003 0.035 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.003 0.024 +/- 0.003 0.032 +/- 0:003 0.013 +/- 0.003 0.027 +/- 0:003 0.018 +/- 0.003 0.021 +/- 0.003 0.023 +/- 0.003 0.017 +/- 0.003 0.021 +/- 0.003 0.016 +/- 0.003 0.019 +/-.0.003 0.034 +/- 0.003 0.032 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.026 +/- 0.003 0.035 +/- 0.004 0.015 +/- 0.003 0.026 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.016 +/- 0.003 0.019 +/- 0.003 0.034 +/- 0.003 sic, #a&

-m A

me ma a gm

-t

>-K

-I

Air Gross Beta Detail Report 2006 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Weekly I Results in pCi/m3 +/-

2 Sigma Location Collection Date 11/16/06 11/22/06 11/29/06 12/6/06 12/13/06 12/20/06 12/27/06 1/3/07 Sample Type Air Air Air Air Air Air Air Air 1

7 0.020 +/- 0.002 0.022 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.003 0.029 +/- 0.003 0.031 +/-.0.003 0.030 +/- 0.003 0.031 +/- 0.003 0.035 +/-/- 0.003 0.031 +/- 0.003 0.034 f/- 0.003 0.032 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0!042 +/-0'003 0.031 +/- 0.003 3

35 4

5 6

0.022 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.003 0.018 +/- 0.003 0.020 +/-/- 0.003 0.020 +/- 0.003.

0.031 +/- 0.003 0.032 +/- 0.003 0.033 +/- 0.003 0.031 +/- 0.003 0.031 +/- 0.003 0.030 +/- 0.003 0.035 +/- 0.003 0.035 +/- 0.003 0.035 +/- 0.003 0.038 +/- 0.003 0.037 +/- 0:003 0.035 +/- 0.003 0.023 +/- 0.003 0.023 +/- 0.003 0.023 +/- 0.003 0.028+/- 0.003 0.034 +/- 0.003 0.037 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.03i +/-0.003 0.031 +/- 0.003 0.034 +/- 0.003 0.038 +/- 0.003 0.023 +/- 0.003 0.034 +/- 0.003 0.022 +/- 0.003 0.017 +/0.003 0.027 +/- 0.003 0.031 +/- 0.003 0.031 +/-0.003 0.034 +/- 0.003 0.022 +/- 0.003 0.032 +/- 0.003

Air Iodine Detail Report 2006 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 1

1 1

Sample Type Collection Dat 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 Air Air Air Air Air Air Air 1/4/06

< 0.006 1/11/06

< 0.009 1/18/06

< 0.007 1/25/06

< 0.004 2/1/06

< 0.008 2/8/06

< 0.004 2/15/06

< 0.011 2/22/06

< 0.008 3/1/06

< 0.008 3/8/06

< 0.009 3/15/06

< 0.007 3/22/06

< 0.008 3/29/06

< 0.008 4/5/06

< 0.005 4/12/06

< 0.006 4/19/06

< 0.005 4/26/06

< 0.008 5/3/06

< 0.008 5/10/06

< 0.006 5/17/06

< 0.003 5/24/06

< 0.007 5/31/06

< 0.005 6/7/06

< 0.009 6/14/06

< 0.009 6/21/06

< 0.004 6/28/06

< 0.003 7/5/06

< 0.007 7/12/06

< 0.008 7/19/06

< 0.004 7/26/06

< 0.004 8/2/06

< 0.003 8/9/06

< 0.006 8/16/06

< 0.007 8/23/06

< 0.006 8/30/06

< 0.007

,9/6/06

< 0.004 9/13/06

< 0.008 9/20/06

< 0.005 9/27/06

< 0.006 10/4/06

< 0.007 10/11/06

< 0.003 10/18/06

< 0.006

-Vm" -ýM' 1m;

slat

~A~ne M Re 06-

,adiological Environmental Monitoring Program Detail Data ar Power Plant, Lake County Ohio Docket no. : 50-440/50-441 mple Frequency is: Weekly Results in pCi/m3 +/-

2 Sigma Location Sample Type Air 1

Air 1

Air I

Air 1

Air 3

Air Collection Dat 10/25/06 11/1/06 11/8/06 11/16/06 11/22/06 11/29/06 12/6/06 12/13/06 12/20/06 12/27/06 1/3/07

.1/4/06 1/11/06 1/18/06 1/25/06 2/1/06 2/8/06 2/15/06 2/22/06 3/1/06 3/8/06 3/15/06 3/22/06 3/29/06 4/5/06 4/12/06 4/19/06 4/26/06 5/3/06 5/10/06 5/17/06 5/24/06 5/31/06 6/7/06 6/14/06 6/21/06 6/28/06 7/5/06 7/12/06 7/19/06 7/26/06 8/2/06 1-131 0.007 0.006 0.008 0.008.

0.0'10 0.005 0.006 0.004 0.005 0.008 0.004 0.006 0.008 0.007 0.004 0.007 0.004 0.010 0.007 0.008 0.008 0.007 0.008 0.007 0.005 0.006 0.005 0.009 0.008 0.006 0.003 0.007 0.005 0.009 0.009 0.004 0.003 0.007 0.008 0.005 0.004 0.003

Air Iodine Detail Report 2006 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

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 Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Collection Dat 8/9/06 8/16/06 8/23/06 8/30/06 9/6/06

.9/13/06 9/20/06 9/27/06 10/4/06 10/11/06 10/18/06 10/25/06 11/1/06 11/8/06 11/16/06 11/22/06

.11/29/06 12/6/06 12/13/06 12/20/06 12/27/06 1/3/07 1/4/06 1/11/06 1/18/06 1/25/06 2/1/06 2/8/06 2/15/06 2/22/06 3/1/06

3/8/06 3/15/06 3/22/06 3/29/06

4/5/06 4/12/06 4/19/06 4/26/06 5/3/06 5/10/06 5/17/06 1-131 0.006 0.007 0.006 0.007 0.004 0.008 0.005

0.006 0.007 0.003 0.006 0.007 0.005 0.007 0.009 0.010 0.005 0.006 0.004 0.005 0.008 0.004 K

K K

K 0.006 0.009 0.008 0.004 0.008 0.005 0.011 0.008 0.008 0.009 0.007

.0.009 0.008 0.005 0.007 0.005 0.008 0.008 0.006 0.003

AW-A#Nne*-*Reo*06-Radiological Environmental Monitoring Program Detail Data car Power Plant, Lake County Ohio Docket no. : 50-440/50-441 mple Frequency is: Weekly Results in pCi/m3 +/-

2 Sigma.

-~ -~ -

~-m Location 4

4 4

5 5

5 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.

Air Air Air Air Air Air Air Collection Dat 5/24/06

< 0 5/31/06

< 0 6/7/06

< 0 6/14/06.

<. 0 6/21/06

< 0 6/28/06

< 0 7/5/06

< 0 7/12/06

< 0 7/19/06

<. 0 7/26/06

< 0 8/2/06

< 0 8/9/06

< 0 8/16/06

< 0 8/23/06

< 0 8/30/06

< 0 9/6/06

< 0 9/13/06

< 0 9/20/06

< 0 9/27/06

< 0 10/4/06

< 0 10/11/06

< 0 10/18/06

< 0 10/25/06

< 0 11/1/06

< 0 11/8/06

< 0 11/16/06

< 0 11/22/06.

< 0 11/29/06

< 0 12/6/06

< 0 12/13/06

< 0 12/20/06

< 0 12/27/06

< 0 1/3/07

< 0 1-131

.007

.005.-

.009

.004

.003

.007

.008

.005

.004

.003

.006

.007

.006.

.007

.004

.008

.005

.006

.007

.004

.006

.007

.005

.007

.009 0.10

.005

.006

.004

.005

.008

.004 1/4/06 1/11/06 1/18/06 1/25/06 2/1/06 2/8/06 2/15/06 2/22/06 3/1/06 0.006 0.009 0.007 0.004 0.008 0.004 0.011 0.008 0.008

Air Iodine Detail Report 2006 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 Dat 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 Air Air Air Air Air Air Air Air 3/8/06 3/15/06 3/22/06 3/29/06 4/5/06 4/12/06 4/19/06 4/26/06 5/3/06 5/10/06 5/17/06 5/24/06 5/31/06 6/7/06 6/14/06 6/21/06 6/28/06 7/5/06 7/12/06 7/19/06 7/26/06 8/2/06 8/9/06 8/16/06 8/23/06 8/30/06 9/6/06

.9/13/06 9/20/06 9/27/06 10/4/06 10/11/06 10/18/06 10/25/06 11/1/06 11/8/06 11/16/06 11/22/06 11/29/06 12/6/06 12/13/06 12/20/06 12/27/06 0.009 0.007 0.009 0.008 0.005 0.007 0.005 0.008 0,008 0.006 0.003 0.007 0.005 0.009 0.009 0.004 0.003 0.006 0.008 0.004 0.004 0.003 0.006 0.006 0.006 0.006 0.004 0.008 0.005 0.006 0.007 0.003 0.005 0.007 0.005 0.007 0.009 0.011 0.005 0.006 0.004 0.005 0.008

-o(N 00---

109--a-W-Oft.4m, -lift

m m

m inAi~nel, RejMO6~

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-o ml nm Location Sample Type Collection Dat 1-131 Air 1/3/07

< 0.004 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 Air Air Air Air Air Air 1/4/06 1/11/06 1/18/06 1/25/06 2/1/06 2/8/06.

2/15/06 2/22/06 3/l/06 3/8/06 3/15/06 3/22/06 3/29/06 4/5/06 4 /12/06.

4/19/06.

4/26/06 5/3/06 5/10/06

.5/17/06 5/24/06 5/31/06 6/7/06 6/14/06 6/21/06 6/28/06 7/5/06 7/12/06 7/19/06 7/26/06 8/2/06 8/9/06 8/16/06 8/23/06 8/30/06 9/6/06 9/13/06 9/20/06 9/27/06 10/4/06 10/11/06 0.006 0.009 0.008 0.004 0.008 0.005.

0.011L 0.008 0.009, 0.009 0.007 0.009 0.008 0.006 0.007 0.005 0.009 0.008 0.007 0.004 0.008 0.005 0.009 0.009 0.005 0.003 0.007 0.008 0.905 0.0,04 0.003 0.006 0.007 0.006 0.007 0.004 0.008 0.005 0.006 0.008 0.004

Air Iodine Detail Report 2006 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 6

6 6

6 7

7 7

7 77 7

7 7

7 Sample Type Air Air Air Air Air Air Air Air Air Air Air Air Collection Dat 10/18/06 10/25/06 11/1/06 11/8/06 11/16/06 11/22/06 11/29/06 12/6/06 12/13/06 12/20/06 12/27/06 1/3/07 K

K K

K 1-131 0.006 0.007 0.005 0.007 0.009 0.010 0.005 0.006 0.004 0.005 0.008 0.004 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 1/4/06 1/11/06 1/18/06 1/25/06 2/1/06 2/8/06 2/15/06 2/22/06 3/1/06 3/8/06 3/15/06 3/22/06 3/29/06 4/5/06 4/12/06 4/19/06

,4/26/06

.- 5/3/06 5/10/06

-5/17/06 5/24/06 5/31/06 6/7/06 6/14/06 6/21/06 6/28/06 7/5/06 7/12/06 7/19/06 7/26/06 0.006 0.009.

0.007 0.004 0.008 0.004 0.011 0.008 0.008 0.009 0.007 0.008 0.007 0.005 0.006 0.005 0.008 0.008 0.0,06 0.003 0.007 0.0,o5 0.009 0.009 0.004 0.003 0.006 0.008 0.004 0.004

--O-Nm m ~

Aifne 1"

ReinO adiological Environmental Monitoring Program Detail Data ar Power Plant, Lake County Ohio Docket no. : 50-440/50-441 nple Frequency is: Weekly Results in pCi/m3 +/-

2 Sigma.

m ~

Location Sample Type Collection Dat 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 Air Air Air Air Air Air Air 8/2/06 8/9/06 8/16/06 8/23/06 8/30/06.

9/6/06 9/13/06 9/20/06 9/27/06 10/4/06 10/11/06 10/18/06 10/25/06 11/1/06 11/8/06 11/16/06 11/22/06 11/29/06 12/6/06 12/13/06 12/20/06 12/27/06 1/3/07 1/4/06 1/11/06 1/18/06 1/25/06 2/1/06 2/8/06 2/15/06 2/22/06.

.3/1/06 3/8/06 3/15/06 3/22/06 3/29/06 4/5/06 4/12/06 4/19/06 4/26/06 5/3/06 5/10/06 0.003 0.006 0.006 0.006 0.006 0.004 0.008 0.005.

0.006t 0.007 0.003 0.006 0.007 0.005 0.007 0.009.

0.011 0.006 0.006 0.004, 0.005 0.008 0.005 0.003 0.008 0.009 0.006 0.008.

0.005 0.010 0.013.

0.002 0.008 0.005 0.001 0.008 0.004 0.028 0.029 0.009 0.010 0.012

Air Iodine Detail Report 2006 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 Dat 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 5/17/06 5/24/06 5/31/06 6/7/06 6/14/06 6/21/06 6/28/06 7/5/06 7/12/06 7/19/06 7/26/06 8/2/06 8/9/06 8/16/06 8/23/06 8/30/06 9/6/06 9/13/06 9/20/06 9/27/06 10/4/06 10/I 1/06 10/18/06 10/25/06 11/1/06 11/8/06 11/16/06 11/22/06 11/29/06 12/6/06 12/13/06 12/20/06 12/27/06 1/3/07 0.013 0.007 0.008 0.014 0.006 0.003 0.008 0.004 0.004 0.007 0.012 0.009 0.004 0.005 0.009 0.008 0.003 0.004 0.005 0.004 0.002 0.004 0.004 0.007 0.004 0.004 0.009 0.009 0.007 0.006 0.008 0.006 0.008 0.007 A

.r-W smU

l-

-0 m" mn.

Sol" "

U7-pm -

Fish Gamma Spectral Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Penry 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 K-40 Co-60 Mn-54 25 perch 32 perch 8/2/06 8/2/06

< 27.33 1,280.10+/- 518.20

< 11.06 1,577.10 +/- 556.30

< 24.04

< 10.54

< 19.45

< 28.73 Cs-134 Zn-65

25.55

51.27

32.06

43.21 Cs-137

28.45

27.79 Fe-5 9

60.29

51.34

Location Sample Type 2

beet greens 2

Swiss chard 2

beet greens 2

swiss chard 2

beet greens 2

swiss chard 2

beet greens Collection Date 7/6/06 7/6/06 7/25/06 7/25/06 8/15/06 8/15/06 9/15/06 7/6/06 7/25/06 7/25/06 8/15/06 9/15/06 Food Products Gamma Spectral Detail Report 2006 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-40 246.31 +/- 143.80

< 10.47

< 7.79

< 11.94 4,620.30 +/- 377.30 215.25 +/- 117.60

< 7.11

< 10.55

< 16.50 5,081.20 +/- 376.70

< 186.61

< 10.72

< 12.92

< 36.35 6,482.30 +/- 623.60

176.86

< 10.95

< 14.01

< 37.03 5,189.80 +/- 478.40 247.10 +/- 104.60

< 6.02

< 5.08

9.61 7,464.40 +/- 320.40

< 103.17

< 10.40

< 5.54

< 16.17 6,004.40 +/- 319.10 469.81 +/- 217.70

< 12.83

< 12.23

< 17.43 5,128.60 +/- 625.40

< 157.69

< 12.73

< 13.01

< 14.54 5,881.85 +/- 382.95

< 86.50

< 7.66

< 5.40

< 26.25 5,238.90 +/- 353.90 408.04+/- 180.80

< 14.19

< 13.56

< 16.97 6,049.40 +/- 495.90 156.16

< 19.23

< 13.40

<. 18.86 4,862.60 +/- 501.00

-412.20 +/- 187.10

< 10.89 14.31

< 27.94 6,702.20 +/- 614.70 lm m

Cs-134

11.60

8.53

< 17.85

< 11.68

< 8.19

< 9.52 13.46 Cs-137

< 9.71

11.62

< 12.14

17.58

9.94

< 10.74

< 22.14 16 16 16 16 16 turnip greens collard greens turnip greens collard greens swiss chard 14.54 9.81 10.89 17.08 13.04 11.65 9.94 18.10 16.11 20.70 m

u a

I IM MI5 M Val

Food Products Gamma Spectral Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sarniple Frequency is: Monthly' Results in pCi/kg wet +/-

2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 20 chinese cabbage 9/15/06 352.10 +/-116.70 14.04

< 9.14

< 11.62

< 9.74

< 15.71 3,954.60 +/- 438.40 20 turnip greens 9/15/06 375.15 +/- 77.41

< 7.30

< 6.74

< 5.04

< 8.25

< 9.00 3,961.90 +/- 265.90 20 chinese cabbage 10/25/06 598.53 +/- 118.80

< 6.95

< 10.24

< 5.26

< 8.79

< 12.16 3,689.70 +/- 308.10 37 collard greens 7/6/06 396.76 +/- 190.60

< 12.28

< 15.18

< 15.52

< 23.09

< 27.17 5,479.10 +/- 645.50 37 swiss chard 7/6/06 225.40 +/- 135.20

< 9.19

< 14.10

< 10.24 12.10 16.68 4,546.70 +/- 405.00 37 turnip greens 7/6/06 336.83 +/- 117.30

< 11.52

< 9.92

< 11.78

< 12.09 13.49 5,090.80 +/- 498.30 37 collard greens 7/25/06 178.11

< 7.49

< 11.70

< 7.27

< 15.29

< 27.41 3,871.80 +/- 336.80 37 swiss chard 7/25/06

< 161.34

< 12.15

< 16.24

< 11.83

< 12.36

< 30.49 3,922.60 +/- 443.70 37 turnip greens 7/25/06

< 162.06

< 12.49

< 6.05

< 10.02

< 13.82

< 22.76 4,600.40 +/- 387.10 37 beet greens 8/15/06 563.61 +/- 238.40

< 11.72

< 24.74

< 16.20

< 21.71

< 40.91 7,341.70 +/- 577.30 37 collard greens 8/15/06

< 111.39 11.31

< 7.72

< 9.26

< 9.69

< 18.85 3,379.00 +/- 217.40 37 swiss chard 8/15/06 310.71 +/- 125.90

< 8.43

< 6.81.

< < 8.40 13.20

< 16.94 5,966.20 +/- 395.30

Food Products Gamma Spectral Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCi/kg wet +/- 2 Sigma Location Sample Type Collection Date Be-7 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 37 collard greens 9/15/06 154.35

< 11.07 15.17 11.84

< 11.92

< 34.82 4,130.60 +/- 392.70 37 swisschard 9/15/06 119.10

< 11.19

< 6.51

< 8.60

< 11.91

< 36.05 3,335.50 +/- 289.50 37 turnip greens 9/15/06 961.90 +/- 109.20

< 8.51

< 9.69

< 4.18

< 9.33 13.72 5,858.30 +/- 315.80 37 beet greens 10/25/06 766.35 +/- 174.80

< 10.58

< 10.80 12.71

< 13.95

< 20.61 6,385.50 +/- 475.80 37 swiss chard 10/25/06 492.72 +/- 91.09

< 4.96

< 8.42 11.56

< 8.95

< 21.04 6,036.05 +/- 295.21 37 turnip greens 10/25/06 1,764.20 +/-172.50

< 10.96

< 7.71

< 7.44

< 9.03 17.20 7,674.40 +/- 417.30 70 collard greens 8/15/06

< 58.29

< 5.53

< 6.90

< 6.70

< 8.70 10.05 4,451.70 +/- 249.40 70 swiss chard 8/15/06 235.94 +/- 140.90

< 6.22

< 5.00

< 9.50

< 10.75

< 24.39 7,189.70 +/-424.20 70 turnip greens 8/15/06 565.83 +/- 115.80

< 3.21

< 8.47

< 7.37

< 12.01

14.38 5,437.30 +/- 358.60 70 collard greens 9/15/0 6 130.04

< 9.31 10.44

< 11.77

< 9.78 K 32.29 3,669.90 +/- 287.70 70 swiss chard 9/15/06 346.03 +/- 134.10

< 8.33

< 11.59

< 8.63

< 14.21

< 30.58 3,821.60 +/- 360.50 m

m ~

m up

Milk Gamma Spectral Detail Report 2006 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 Samnle Tvne Collection Date Ba-140 Cs-'134 Cs-137 K-40 La-140 22 Milk 22 Milk 22 Milk 22 Milk 22 Milk 22 Milk 22 Milk 6/19/06 7/5/06 7/17/06

'8/7/06 8/21/06 9/5/06 9/18/06 4/3/06 5/1/06 5/15/06 6/5/06 6/19/06

< 23

< 30

< 21

< 10

< 13

< 16

< 22

< 19

< 12

< 23

< 15

< 30

< 3

< 7 4

< 4

< 3

< 6

< 4

< 2

< 5

< 4

< 6

< 3

< 6

< 4

< 5

< 8

< 4

<2

< 7

< 4

< 8 1,549 -/- 95 1,521 +/- 195 1,823 +/- 131 1,686 +/- 128 1,712 +/- 127 1,810 +/- 139 1,087 +/- 158 1,399 +/- 86 1,596 +/- 80 1,759 +/- 197 1,556 +/- 128 1,595 +/- 185

< 3

< 4

< 2

< 3

< 4

< 1

< 3

< 3 41 41 41 41 41 Milk Milk Milk Milk Milk

Location Sample Type 41 Milk 41 Milk 41 Milk 41 Milk 41 Milk 41 Milk Collection Date 7/5/06 7/18/06 8/7/06 8/21/06 9/5/06 9/18/06 1/3/06 2/6/06 3/9/06 4/3/06 4/18/06 5/1/06 Milk Gamma Spectral Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/-

2 Sigma Ba-140 Cs-134 Cs-137 K-40

< 11

< 3

< 5 1,676+/-138

< 9

< 3

< 4 1,819+/-146

< 15

< 4

< 3 1,732+/-131

< 14

< 5

< 5 1,744+/-169

< 21

< 5

< 5 1,742+/-175

< 21

< 5

< 8 1,714+/-185 La-140 51 51 51 51 51 51 Milk Milk Milk Milk

-Milk Milk

< 18

< 19

< 11

< 26

< 23

< 20' 3

3 3

3 5

4 5

3 5

5 5

5 1,214 +/- 109 1,292 +/- 112 1,288 +/- 119 1,163 +/- 114 1,173 +/- 130 1,421 +/- 116 M

amgo-M

=

m

-i-*

i i-

_i

-=

m l

Milk Gamma Spectral Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Location Sample Type Collection Date Ba-140 Cs-134 Cs-137 K-40 La-140 Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk 5/15/06 6/5/06 6/20/06 7/5/06 7/17/06 8/7/06 8/21/06 9/5/06 9/18/06 10/2/06 10/16/06 11/6/06

< 25

< 10

< 12

< 10

< 18

< 16

< 18

< 16

< 9

< 14

< 10

< 3

< 6

< 3

< 5

< 3

< 4

< 6

< 3

< 6

< 4

< 3

< 6

< 4

< 3

< 4

< 5

< 4

< 5 1,108 +/- 174 1,309 +/- 116 1,364+/- 117 1,322 +/-/- 109 1,980 +/- 147 1,666 +/- 188 1,369 +/- 122 1,286 +/- 145 1,270 +/- 113 1,327 +/- 111 1,251 +/- 118 1,326 +/- 119

< 7

< 3

< 1

< 2

< 4

< 2

<1

< 3

< 2 51 Milk

Milk Gamma Spectral Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma Ba-140 Cs-134 Cs-137 Location Sample Type 51 Milk Collection Date K-40 La-140 Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk 12/4/06 4/3/06 4/18/06 5/1/06 5/15/06 6/5/06 6/19/06 7/5/06 7/17/06 8/7/06 8/21/06 9/5/06

< 11

< 26

< 25

< 13 34 11

< 10

< 13

< 19

< 14

< 22

< 14

< 3

< 3 1,269 +/- 110 1,769 +/- 158 1,645 +/- 134 1,702 +/- 131 1,432 +/- 196 1,610 +/- 126 1,702 +/- 118 1,703 +/- 186 1,805 +/- 131 1,951 +/- 140 1,951 +/- 199 2,119 +/- 186

< 2

< 7

< 5

< 3

< 7

< I

< 3

< 5

< 4

< 2

< 4

< 5 m

saga-m m -n m-mm m

m

mmmjmmm*m amrm m

mm

~mm m

m-=

-- mm Milk Gamma Spectral Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/-

2 Sigma Location Sample Type Collection Date Ba-140 Cs-134 Cs-137 K-40 La-140 61 Milk 61 Milk 9/18/06 10/2/06

< 13

< 12

< 5

< 4 1,929 +/- 13 f 2,066 4-/- 149

< 2

< 4

Milk Iodine Detail Report 2006 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 22 22 22 22 22 22 22 22 41 41 41 41 41 41 41 41 41 41 41 41 41 51 51 51 51 51 51 51 51 51 51

.51 51 51 51 51 51 51 51 51 Sample Type Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk

, Milk

.Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Milk Collection Dat 1-131 6/19/06 7/5/06 7/17/06 8/7/06 8/21/06 9/5/06 9/18/06 10/2/06 4/3/06 4/18/06 5/1/06 5/15/06 6/5/06 6/19/06 7/5/06 7/18/06 8/7/06 8/21/06 9/5/06 9/18/06 10/2/06 1/3/06 2/6/06 3/9/06 4/3/06 4/18/06 5/1/06 5/15/06 6/5/06

.6/20/06

.7/5/06 7/17/06 8/7/06 8/21/06 9/5/06 9/18/06 10/2/06 10/16/06 11/6/06 12/4/06 K

K 0.34 0.27 0.25 0.18 0.44 0.24 0.45

< 0.28 K

K K

K 0.31 0.25 0.22 0.24 0.28 0.28 0.18 0.32 0.20 0.24

< 0.14

< 0.31

< 0.41

< 0.50

< 0.42

< 0.34

< 0.27

<.0.27

< 0.26

<.0.29

< 0.21

< 0.44

< 0.23

< 0.45

< 0.43

< 0.39

< 0.23

< 0.31 I--

II

m WMi11A!neIR9epmO06 m0 &W-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 Dat

.1-131 61 Milk 4/3/06

< 0.34 61 Milk 4/18/06

< 0.38 61 Milk 5/1/06

< 0.45 61 Milk 5/15/06

< 0.31 61 Milk 6/5/06

< 0.24 61 Milk 6/19/06

< 0.24 61 Milk 7/5/06

< 0.24 61 Milk 7/17/06

< 0.28 61 Milk 8/7/06

< 0.30 61 Milk 8/21/06

< 0.41 61 Milk 9/5/06

< 0.22 61 Milk 9/18/06

< 0.31 61 Milk 10/2/06

< 0.45 61 Milk 10/16/06

Sediment Gamma Spectral Detail Report 2006 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 ate Co-58 Co-60 Cs-134

< 20.93

< 24.28

< 31.21 Location Sample Type 25 Sediment 25 Sediment Collection D Cs-137 K-40 LLD 11,527.00 +/- 591.00 LLD 11,898.00 +/- 701.00 6/14/06 10/9/06

< 36.03

< 28.19

< 42.26 Sediment Sediment Sediment Sediment Sediment Sediment Sediment Sediment 6/14/06 10/9/06 6/14/06 10/9/06 6/14/06 10/9/06 6/14/06 10/10/06

< 15.27

< 31.13

< 16.89

< 24.75

< 32.22

< 44.56

< 11.81

< 13.72

< 28.25

14.91

< 15.94

< 11.43

< 23.47

<.39.63

< 7.34 18.42

< 33.69

< 40.92

< 36.47

< 33.35

51.25

57.65

13.23

< 17.24 145.25 +/- 31.53 LLD 308.79 +/- 58.46 158.51 +/- 30.96 907.86 +/- 82.00 881.68 +/- 68.16

11.35 13.56 16,569.00 +/- 765.20 14,042.00 +/- 680.80 17,405.00 +/- 823.70 15,967.00 +/- 853.70 25,552.00 +/- 1,153.00 24,460.00 +/- 1,246.00 8,472.80 +/- 421.50 8,910.00 +/- 519.60 mn m

m

-ur -u lmn

,m -m

-M At s o ma Sediment Gamma Spectral Detail Report 2006 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 65 Sediment 6/14/06

< 20.56

< 14.28

< 36.89

< 23.22 10,678.00 +-664.60 65 Sediment 10/10/06

< 8.21 13.07

< 21.91

< 11.36 7,917.80+/-497.70

TLD Gamma Dose Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Location Sample Type Collection Period TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD

TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12,06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/1.2/06 1/6/06 4/12/06 7/11/06 10/12/06

. 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/1 i/06 10/12/06 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/,12/06 to 1/4/07 to 4/12/06 to.7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06

'to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to -10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 Exposure 10.53

+/-

8.89

+/-

11.33

+/-

11.83

/-

10.94 9.59 11.04 12.63 11.70 9.63 12.34 12.76 10.16 9.40 11.20 12.76 11.96 10.27 13.10 13.86 11.63 10.42 12.65 13.94

+-I-0.91 0.61 1.39

'0.66 0.75 0.45 0.75 0.67 0.89 0.56 0.69 0.64 0.76 0.49 0.65 0.43 0.81 0.42 0.71 0.48 0.89 0.41 0.90 0.38 0.72 0.49 0.59

.0.53 0.71 0.56 0.65 0.41

.10.11

+/-

9.71

+/-

1107

+/-

12.60

+/-

10.18

+/-

9.54

+/-/-

11.22

+/-

12.11

+/-

10 10 10 1/6/06 to 4/12/06 4/12/06 to 7/11/06 7/11/06 to 10/12/06 13.12

+/-

0.89 11.92

+/-

0.71 14.38

+/-

0.72

S, LD Wna]m*etalortl Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Location Sample Type Collection Period Exposure 10 11 11 11 11 12 12 12 12 13 13 13 13 14 14 14 14 15 15 15 15 21 21 21 21 23 23 23 23 24 24 24 24 TLD TLD TLD TLD TLD TLD TLD.

TLD TLD 10/12/06 to 1/4/07 16.14

+/-

1.80 1/6/06 4/12/06 7/11/06 10/12/06 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 1/6/06 to 4/12/06 4/12/06 to.7/11/06 7/11/06 to 10/12/06 10/12/06 to 1/4/07 12.96 10.68 13.97 13.89 12.14 10.39 12.97 13.30 12.47 9.95 13.21 13.36 i0.89 9.53 11.37 12.67 TLD.

TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 1/6/06 4/12/06 7/11/06 10/12/06, 1/6/06 4/12/06 7/11/06 10/12/0.6 1/6/06 4/12/06 7/1 1/06 10/12/06 1/6/06.

4/12/06 7/11/06 10/12/06 1/6/06 4*/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/1f2/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 0.73 0.46 0.68 0.51 0.73 0.71 0.89 0.74 0.86 0.74 0.87 0.80 0.89 0.34 0.73 0.5 0.86 0.60 0.66 0.65 0.79 0.39 0.81 0.56 0.81 043 0.69 0.36 0.87 0.66 0.60 0.66 10.82

+/-

8.45

+/-

11.20

+/-

9.01

+/-

13.78 15.34 14.84 15.08 14.41 15.51 14.91 15.19 12.21 18.23 12.45 13.98 29 TLD 29 TLD 1/6/06 to 4/12/06 4/12/06 to 7/11/06 16.35

+/-

0.95 13.93

+/-

0.55

TLD Gamma Dose Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Location Sample Type Collection Period Exposure 29 29 30 30 30 30 31 31 31 31 33 33 33 33 35 35 35 35 36 36 36 36 53 53 53 53 54 54 54 54 55 55 55 55 56 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 T*LD TLD TLD TLD TLD TLD TLD TLD TLD TLD 7/11/06 to 10/12/06 10/12/06 to 1/4/07 16.84

+/-

0.84 18.22

+/-

0.63 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 14.30 16.00 14.89 16.25 14.33 17.59 15.36 16.65 15.47 18.00 16.23 17.79 10.31 12.91 11.55 12.74 14.73 16.64 15.80 16.61 11.29 13.75 12.86 13.62 11.16 12.97 12.75 13.84 12.12 14.40 13.14 14.42 1.04 0.71 0.95 1.24 0.92 0.78 0.72 1.24 0.90 0.74 0.75 0.46 0.88 1.11 0.64 0.45 0.94 1.08 0.84 0.83 0.80 0.50 0.80 0.49 1.28 0.50

1.02 1.21 1.71 0.61 1.56 0.57 1/6/06 to 4/12/06 12.03

+/-

0.86

dLD Naamma *,oetagort"

=

Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Quarterly Location Sample Type Collection Period Exposure 56 TLD 4/12/06 to 7/11/06 13.35

+/-/-

0.64 56 TLD 7/11/06 to 10/12/06 12.69

+/-

0.68 56 TLD 10/12/06 to 1/4/07 13.66

+/-

0.79 58 TLD 1/6/06 to 4/12/06 10.21

+/-

0.77 58 TLD 4/12/06 to 7/11/06 11.77

+/-

0.71 58 TLD.

7/11/06 to 10/12/06 11.16

+/-

0.71 58 TLD.

10/12/06 to 1/4/07 12:10

+/-

0.42

TLD Gamma Dose Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Quarterly Location Sample Type Collection Period TLB 1/6/06 to 4/12/06 TLB 4/12/06 to 7/11/06 TLB 7/11/06 to 10/12/06 TLB 10/12/06 to 1/4/07 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 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 to 4/12/06 to 7/11/06 to 10/12/06 to - 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to *4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 Exposure 10.65

+/-

1.27 10.29

+/-

0.69 11.00

+/-

1.32 10.75

+/-

0.82 11.94

+/-

0.80 8.93

+/-

0.78 12.26

+/-

1.19 9.451

+/-

0.80 12.08

+/-

0.59 12.68

+/-

0.64 12.03

+/-

1.05 13.04

+/-

0.65 12.19

+/-

0.57 10.87

+/-

0.76 12.49

+/-

1.22 11.84

+/-

0.69 12.19

+/-

0.76 10.84

+/-

0.57 12.31

+/-

1.11 12.34 f/-

0.57 13.25

+/-

0.65 12.22

+/-

0.79 12,94

+/-

1.16 13.49

+/-

0.80 11.66

+/-

0.66 10.55

+/-

0.62 12.19

+/-

1.02 11.65

+/-

0:57 11.36

+/-

0.67 10.09

+/-

0.73 11.29

+/-

1.10 11.11

+/-

0.59 10 TLB 10 TLB 10 TLB 10 TLB 1/6/06 to 4/12/06 4/12/06 to 7/11/06 7/11/06 to 10/12/06 10/12/06 to 1/4/07 13.93 12.95 14.06 14.44

+/-

0.73

+/-

0.57

+/-

1.37

+/-

0.69

M 8qm LDWmmaD eotai rt M

M M

Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.

50-440/50-441 Sample Frequency is:

Quarterly Location Sample Type Collection Period Exposure 11 TLB 1/6/06 to 4/12/06 11..96

+1-0.53, 11 TLB 4/12/06 to 7/11/06 11.80

+/-

0.61 1l TLB 7/11/06 to 10/12/06 12.89.

+/-

1.88 11 TLB 10/12/06, to 1/4/07 13.32

+/-

0.79 12 TLB 1/6/06 to 4/12/06 13.32

+

o-0.47 12 TLB 4/12/06 to 7/11/06 11.37

+/-

0.49 12 TLB 7/11/06 to 10/12/06 13.61

+/-

1.04 12 TLB 10/12/06 to 1/4/07 12.49

+1-0.78 13 TLB 1/6/06 to 4/12/06 11.74

+/-

0.53 13 TLB 4/12/06 to 7/11/06 10.80

+/-

0.85 13 TLB 7/11/06 to 10/12/06 12.00

+/-

0.99 13 TLB 10/12/06 to 1/4/07 11.94

+/-

1.04 14 TLB 1/6/06 to 4/12/06 10.34

+/-

0.64 14 TLB 4/12/06 to 7/11/06 10.25

+/-

0.64 14 TLB 7/1-1/06 to 10/12/06 10.19

+/-

1.14 14 TLB 10/12/06 to 1/4/07 11.61

+/-

0.93 15 TLB 1/6/06 to 4/12/06 10.07

+/-

0.58 15 TLB 4/12/06 to 7/11/06 9.32

+/-

0.64 15 TLB 7/11/06 to 10/12/06 9.73

+/-

1.12 15 TLB 10/12/06 to 1/4/07 10.72

+/-

0.95 21 TLB 1/6/06 to 4/12/06 13.11

+/-

0.79 21 TLB 4/12/06 to 7/11/06 11.96

+/-

0.84 21 TLB 7/11/06 to 10/12/06 14.03

+/-/-

1.14 21 TLB 10/12/06 to 1/4/07 13.39

+/-

0.91 23 TLB 1/6/06 to 4/12/06 12.42

+/-

1.10 23 TLB 4/12/06 to 7/11/06 12.06

+/-

0.65 23 TLB 7/11/06 to 10/12/06 12.54

+/-

1.36 23 TLB 10/12/06 to 1/4/07 13.50 t/-

0.67 24 TLB 1/6/06 to 4/12/06 12.96

+/-

1.03 24 TLB 4/12/06 to 7/11/06 10.29

+/-

0.65 24 TLB 7/11/06 to 10/12/06 12.81

+/-

1.44 24 TLB 10/12/06 to 1/4/07 12.33

+/-

0.68 29 TLB 1/6/06 to 4/12/06 16.28

+/-

0.88 29 TLB 4/12/06 to 7/11/06 14.92

+/-

0.92 29 TLB 7/11/06 to 10/12/06 16.65

+/-

1.17

TLD Gamma Dose Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Quarterly Location Sample Type Collection Period Exposure 29 TLB 10/12/06 to 1/4/07 16.80

+/-

1.14 30 30 30 30 31 31 31 31 33 33 33 33 35 35 35 35 36 36 36 36 53 53 53 53 54 54 54 54 55 55 55 55 TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 1/6/06 4/12/06 7/11/06 10/12/06 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 15.06 12.52 15.14 14.57 15.77 13.60 16.21 15.41 16.86 14.67 16.91 16.80 12.04 10.11 12.01 11.69 16.32 14.04 16.34 16.20 13.01 11.65 12.85 13.24 13.76 10.88 13.73 12.96 13.20 11.58 13.04 13.41 0.77 0.60 1.08 0.54 1.04 0.57 1.57 0.94 0.90 0.80 1.11 0.71 0.62 0.51 1.03 0.49 0.67 0.74 1.06 0.65 0.56 0.75 1.24 0.65 0.77 0.57

1.18 0.58 0.72 0.80 1.20 0.77 1/6/06 4/12/06 7/11/06 10/12/06 to 4/12/06 to 7/11/06 to 10/12/06 to 1/4/07 56 TLB 56 TLB 1/6/06 to 4/12/06 4/12/06 to 7/11/06 13.39 10.82

+/-

0.73

+/-

0.74

~ILD W!a rf~etail~ort W Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.

50-440/50-441 Sample Frequency is: Quarterly Location Sample Type Collection Period Exposure 56 TLB 7/11/06 to 10/12/06 13.12

+/-

1.05 56 TLB 10/12/06 to 1/4/07 12.54

+/-

0.97 58 58 58 58 TLB TLB TLB TLB 1/6/06 to 4/12/06 4/12/06 to 7/11/06 7/11/06 to 10/12/06 10/12/06 to 1/4/07 10.86

+/-

0.76 9.46

+/-

0.91 9.80

+/-

1.08 10.41

+/-

0.59

TLD Gamma Dose Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is:

Annual Results in mR/365 days +/-

2 Sigma Location Sample Type I

TLA 3

TLA 4

TLA 5

TLA 6

TLA 7

TLA 8

TLA 9

TLA 10 TLA 11 TLA 12 TLA 13 TLA 14 TLA 15 TLA 21 TLA 23 TLA 24 TLA

29 TLA 30 TLA 31 TLA 33 TLA Collection Period 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 1/6/06 to 1/4/07 Exposure 53.93

+/-

2.24 54.77

+/-/-

2.13 63.00

+/-/-

2.21 58.88

+/-

2.47 64.90

+/-

3.45 60.27 56.89 77.15 69.00 64.72 63.68 59.17 54.58 67.67 65.30 60.22 79.37 67.41 74.01 75.79

/-

1.99

+/-

2.14

+/-

3.16

+/-

2.21

/-

1.66

+/-

2.25

+/-

3.04

+/-

1.77 t/- 4.49

+/-

1.62

+/-/-

398

+/-

2.34

+/-

1.68

+/-

4.18

+/-

1.71

SLD amma Ds oetaitort MP Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Annual Results in mR/365 days +/- 2 Sigma Location Sample Type Collection Period Exposure 35 TLA 1/6/06 to 1/4/07 60.12

+/-

1.35 36 TLA 1/6/06 to 1/4/07 79.99

+/-

2.05 53 TLA 1/6/06. to 1/4/07 68.14

+/-

1.68.

54' TLA 1/6/06 to 1/4/07 61.47

+/-

2.07 55 TLA' 1/6/06 to 1/4/07 68.67

+/- 2.09 56 TLA 1/6/06 to 1/4/07 61.88

+/-1.70 58 TLA 1/6/06 to 1/4/07 53.40

+/-

1.17

TLD Gamma Dose Detail Report 2006 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is:

Annual Results in mR/365 days +/-

2 Sigma Location Sample Type Collection Period Exposure

Water Gamma Spectral Detail Report 2006 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 so g

Location Sample Type 28 Water Collection Period Ba-140 Fe-59 Zr-95 Co-58 La-140 Co-60 Mn-54 Cs-134 Nb-95 Cs-137 Zn-65

3.67

2.00 12/29/05 to 1/26/06

< 18.21

5.22

6.02 28 28 28 28 28 28 28 28 28 28 28 Water Water Water Water Water Water Water Water Water Water Water 1/26/06 to 2/23/06 2/23/06 to 3/30/06 3/30/06 to 4/27/06 10.04

5.21

5.36

25.22

3.30

7.50

11.50

2.55

< 8.23 4/27/06 to 5/31/06

< 8.99

< 3.14

< 2.52 5/31/06 to 6/29/06 K

28.64 8.85 12.91

2.85

2.74

3.34

2.13

2.75

2.39

2.45

1.78 1.97

2.43

4.61

6.69

4.97

5.57

4.38

5.41

2.52

3.44

4.28

5.63

3.27

< 3.35

4.24

7.75

2.66

3.15

4.25

2.48

3.01

3.62

2.28 K 3.44

1.32

1.70

3.94

5.72

2.98

4.82

< 3.61

3.72

3.78

4.64

4.49 K 4.59

3.91

5.67

4.33

4.09

2.64

3.92

3.59

4.15

2.92

4.91

3.01

3.73 1.42 1.88

6.59

6.23

5.36

4.44

4.03 K 4.75

6.75

6.03

4.64

6.88 K 4.43

2.93

4.50

4.27 6/29/06 to 7/26/06 7/26/06 to 8/30/06 8/31/06 to 9/28/06 9/28/06 to 10/26/06 11/29/06 to 11/29/06 11/29/06 to 12/28/06 17.66

7.98.

9.16 19.65

4.14 5.31 31.89 K 9.43 10.18

25.88 3.59 13.84 12.94 6.03 6.75 19.70

4.32 11.52

< 2.18

< 3.68

< 4.03

< 4.93

< 3.64

< 3.79 1.89

< 2.97

< 4.81

< 14.39

< 3.61

< 4.87

< 4.39

< 8.54

< 3.48

< 10.43

< 3.22

< 4.00

< 4.97

< 7.88

< 5.94

< 6.87

Water Gamma Spectral Detail Report 2006 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 Fe-59 La-140 Mn-54 Nb-95 Zr-95 34 34 34 34 34 34 34 34 34 34 34 34 Water Water Water Water Water Water Water Water Water Water Water Water 12/29/05 to 1/26/06 1/26/06 to 2/23/06 2/23/06 to 3/30/06 3/30/06 to 4/27/06 4/27/06 to 5/31/06 5/31/06 to 6/29/06 6/29/06 to 7/26/06

< 13.35

<. 4.24

< 6.39 K 8.85 K 6.18

<. 4.20

18.27 K 5.73

6.61

16.14

5.30

4.05 K 9.07

6.64

< 6.65

42.38

6.24

16.69

16.61

8.79

7.13 1.76

< 1.62

2.39

2.19 K 3.90 K 6.86

2.17

4.05

< 3.57

< 5.17

4.73

< 9.90

4.06

7.86

5.65 K 3.83

3.01

6.54

3.83

6.25

5.19

3.05 K 3.72 K 3.09

2.98

2.57 K 2.30

2.59

5.45 K 4.34 K 2.61 K 2.63 K 3.96

4.43

5.63

4.46 K 2.33

4:64

4.58

4.32

3.36

'4.45 K 5.62

3.34

5ý70

3.95 1.80

4.08

2.68

3.03 K 4.15 K 4.20

2.99 K 3.06

.2.72

2.93

3.62 K 3.70 K 5.35

7.95

4.31

.3.72

3.26

5.93

5.37

2.35 K 3.72 K 3.79

3.55 K 4.24 K 2.24

3.61 Cs-137 Zn-65

2.85

3.37

2.88

5.18 K 4.43

7.04

3.39

6.61

2.99

6.46

5.94

6.15 K 5.63 K 8.91 K 5.07

7.10 K 6.12 K 4.10 K 5.14

3.78

3.60

4.13

2.88 K 2.57 7/26/06 to 8/30/06

< 13.01

< 7.88

< 6.81 8/31/06 to 9/28/06

< 31.31

< 3.79

< 7.51 9/28/06 to 10/26/06 10/26/06 to 11/29/06 11/29/06 to 12/28/06 K 21.48 10.14

9.30 K 15.14

5.03

8.19

9.82 K 3.55

5.81 m m m m m m m -

m m

m mM m Water Gamma Spectral Detail Report 2006 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-i40 Mn-54 Nb-95.

Zn-65 Zr-95 36 Water 12/29/05 to.

1/26/06

< 12.70

< 2.51

< 2.84

< 3.09

< 3.91

< 3.46

< 2.32

< 3.64

< 4.86

< 3.16

< 3.09

36.

Water 1/26/06 to 2/23/06

< 9.25

< 1.64

< 2.32ý

< 2.80-

< 3.80

< 4.57

< 1.25

< 2.31

< 2.98

< 6.33

< 4.36 36 Water 2/23/06 to 3/30/06

< 38.09

< 7.15

< 5.20

< 5.01

< 5.02

< 11.87

< 7.58

< 4.34

< 4.97

< 12.22 14.33 36 Water 3/30/06 to 4/27/06

< 12.97 1.91

< 1.39

< 2.42

< 2.40

< 4.90

< 2.97

< 2.04

< 2.81

< 3.03

< 4.92 36 Water 4/27/06 to 5/31/06

< 17.06

< 1.37

< 1.63

< 3.14

< 2.41

< 5.00 1.95

< 1.97

< 3.15

< 2.76

< 3.69

36.

Water 5/31/06 to 6/29/06

< 13.43

< 3.85

< 2.21

< 2:38

< 3.97

< 9.29

< 6.07

< 4.28

< 4.13

< 7.84

< 5.00 36 Water 6/29/06 to 7/26/06

< 19.52

< 3.25

< 2.22

< 4.64

< 6.87

< 4.20

< 5.76

< 4.17

< 3:60

< 3.83

< 6.93 36 Water 7/26/06 to 8/30/06

< 22.90

< 4.05

< 5.76

< 4:33

< 5.30

< 4.90

< 9.53

< 4.71

< 7.09

< 13.86

< 7.96 36 Water 8/31/06 to 9/28/06

< 24.85

< 2.92

< 1.60

< 3.00

< 3.28

< 4.64

< 4.40

< 2.81

< 3.51

< 4.3.1

< 4.36 36 Water 9/28/06 to 10/26/06

< 33.89

< 3.98

< 4.82

< 4.47

< 5.12

< 5.51

< 9.27

< 5.31

< 5.74 10.52

< 8.75 36 Water 10/26/06 to 11/29/06

<. 14.79

< 4.47

< 4.27

< 5.36

< 3.92

< 11:57

< 6.69

< 2.68

< 4.09

< 6.27

< 9.72 36 Water 11/29/06 to 12/28/06

< 14.30

< 1.49

< 1.65

< 2.81

< 3.54

< 4.40

< 3.88

< 2.34

< 3.41

< 3.33

< 5.77

Water Gamma Spectral Detail Report 2006 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 59 59 59 59 59 59 59 59 59 59 60 60 Water Water Water Water Water Water Water Water Water Water Water Water Collection Period 3/30/06 to 3/30/06 3/30/06 to 4/27/06 4/27/06 to 5/31/06 5/31/06 to 6/29/06 6/29/06 to 7/26/06 7/26/06 to 8/30/06 8/31/06 to 9/28/06 9/28/06 to 10/26/06 10/26/06 to 11/29/06 11/29/06 to 12/28/06 3/30/06 to 3/30/06 3/30/06 to 4/27/06 Ba-140 Fe-59 Zr-95

< 25.94

< 11.31

< 7.95

< 22.41

< 4.33

< 9.21

< 11.23

< 4.11

< 3.51

< 18.98

< 5.85

< 6.50

< 12.49

< 4.88

< 5.02

< 11.29

< 3.72

< 3.78

< 31.51

< 12.27

< 10.22

< 31.02

< 6.21

< 12.61 Co-58 La-140

< 2.50

< 4.81

< 4.16

< 6.61

< 2.29

< 3.84

< 5.28

< 4.46

< 4.19

< 9.23

< 2.02

< 4.97

< 3.21

< 4.81

< 5.54

< 8.39

< 2.52 1.98

< 1.39

< 1.61

< 3.71

< 5.48 1.53

< 3.70

5.21

5.19

5.52

3.92 1.68

2.34

2.85

5.24 K 1.95

3.32 K 2.89

2.26

4.97

3.20

5.48

3.23

1.98

3.03 K 1.99

2.04

< 5.42

.< 4.59

2.79

4.01 Co-60 Cs-134 Mn-54 Nb-95

5.88 K 6.20 K 4.02 K 3.73

2.21

1.94 K 4.40

<- 4.93 K 2.90

4.67

2.65

3.06

2.49

5.97

5.60

3.45

3.23 K 2.99

3.06 K 2.56

6.69

4.45

2.16

2.13 Cs-137 Zn-65 K 6.07

7.04 K 4.70 K 3.95

2.02 K 3.13

3.32

5.58

4.25 K 5.10

1.96

4.66 K 4.15 K 3.58

5.97

4.07 K 3.62

5:65 K 3.07

2.85

5.48 K 8.43

2.99 1.82 9.97 6.59 5.45 13.43

6.02

< 5.79 35.72 8.60 10.69 15.03 4.86 6.88 K

K K

mm M

m m

m

-=

m m

m m m m

m Water Gamma Spectral Detail Report 2006 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 Fe-59 Zr-95.,

Co-58 La-140 Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zn-65 60 Water 4127/06 to 5/31/06 60 60 60 60 60 60 60 Water Water Water Water Water Water Water 5/31/06 to 6/29/06 6/29/06 to 7/26/06 7/26/06 to 8/30/06 8/31/06 to 9/28/06 9/28/06 to 10/26/06 10/26/06 to 11/29/06 11/29/06 to 12/28/06

<' 9.47

< 4.72

< 2.85

< 27.64

< 12.45

< 7.71

< 20.63

< 7.56

< 7.50

< 21.45

< 4.44

< 7.12

< 27.75

< 6.01

< 7.80

< 28.08

< 7.43

< 7.96

<. 13.74

< 3.84

< 3.60

< 9.31

< 5.64

< 3.57

< 1.77

< 2.60

< 5.45

< 4.52

< 3.01

< 2.63

< 4.21

< 3.54

< 3.98

< 4.11

< 3.25

< 6.65

< 2.61

< 2.51

< 3.51

< 3.58

< 2.02

< 2.14

< 5.67

< 3.92

< 4.41

< 3.15

< 3.49 2.92

< 2.72

< 2.37

< 3.29

< 2.87

< 3.45

< 1.98

< 3.30

< 1.27

< 2.48

< 2.84

< 5.28

< 4196

< 3.29

< 5.67

< 3.69

< 3.38

< 2.80

< 1.36

< 3.14

< 3.95

< 3.44

< 2.62

< 2.68

< 3.13

< 1.96

< 3.45

< 3.39

< 4.83,

< 4.08

< 5.89

< 3.26

< 5.32

< 3.07

< 3.04

< 4.34

< 4.73

< 3.36

< 3.17

< 3.13

< 4.52

Water Gross Beta Detail Report 2006 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 12/29/05 to 1/26/06 1/26/06 to 2/23/06 2/23/06 to 3/30/06 3/30/06 to 3/30/06 3/30/06 to 4/27/06 4/27/06 to 5/31/06 5/31/06 to 6/29/06 6/29/06 to 7/26/06 7/26/06 to 8/30/06 8/31/06 to 9/28/06 9/28/06 to 10/26/06 10/26/06 to 11/29/06 M

M Sample Water Water Water Water Water Water Water Water Water Water Water Water Fype 28 LLD LLD LLD 34 LLD LLD LLD 36 LLD LLD LLD 59 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.02 +/-0.62 LLD LLD LLD LLD LLD LLD 3.01 +/- 0.64 3.05 +/- 0.60 mm mm m

m 60 LLD LLD LLD LLD 3.15 +/- 0.64 3.00 +/- 0.66 LLD LLD 3.10 +/- 0.66 M

M

r n

m m

-M

-m I M-M Water Gross Beta Detail Report 2006 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 11/29/06 to 11/29/06 11/29/06 to 12/28/06 Water Water LLD 3.17 +/- 0.67 LLD LLD LLD LLD

I 41 I,

>94 94 4.

F 4~99*

4,1 II-'

-1 I.>

I.

-"-9

~9I I

I 4;

,j9 4

>4

>j~)

1-Ax 4

-.99

.9>

V f P1

-'9 4k 19-

>4-K~)

pp K

d.ip K

-'p

- 999 94 94 4

P1 9-

99.

>4 4

.1' For morae informatioh; write:-

Perry Nuclear PowFer Plant S 10Zc-enter Roadik-'-

P.O. ox:97 Pery TOiH 44081-0097'

~9 4-4.

999 lip

=9)

P9 99.9 k.

1..

ps'> -

4

>4' j~>.

49

'9 19-4*,

>4 9>.

99-

>4 9-49.

19-V ~1 I

9-.

999>

49->

f*P*

9*"*'

ML071280391

Text

Enclosure:

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search