Text

Annual Environmental and Effluent Release Report for the Period of January 1, 2005 Through December 31, 2005
	ML061220375
Person / Time
Site:	Perry
Issue date:	03/31/2006
From:	; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, PY-CEI/NRR-2954L
	Download: ML061220375 (127)
	v • d • e

I8 I-0**

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2005 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, 2006

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT TABLE OF CONTENTS EXCECUTIVE

SUMMARY

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

1 Radiological Environmental Monitoring.................................................................

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

2 Clam/Mussel Monitoring.................................................................

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

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

3 INTRODUCTION.................................................................

4 Radiation Fundamentals.................................................................

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

4 Units of Measure.................................................................

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

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

6 RADIOACTIVE EFFLUENT RELEASES.................................................................

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

7 Regulatory Limits.........................................

7 Release Summary.........................................

9 Meteorological Data........................................

16 Dose Assessment........................................

16 Abnormal Releases........................................

18 Non-Compliances........................................

18 Offsite Dose Calculation Manual Changes........................................

19 Piocess Control Program Changes........................................

19 RADIOLOGICAL ENVIRONMENTAL MONITORING.................................................................20 Introduction........................................

20 Sampling Locations....................................

20 Sample Analysis....................................

25 2005 Sampling Program....................................

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

34 Land Use Census..............................................................

35 CLAM/MUSSEL MONITORING..............................................................

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

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

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

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

39 IHERBICIDE APPLICATIONS........................................................

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

42 Non-Compliances........................................................

42 Unreviewed Environmental Questions........................................................

42 Ohio Department of Natural Resources Survey........................................................

42 Appendix A, 2005 Inter-Laboratory Cross Check Comparison Program Results............................... 43 Appendix B, 2005 REMP Data Summary Reports........................................................

44 Appendix C, 2005 REMP Detailed Data Reports........................................................

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, 2005. 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 3.47E-03 mrem (0.12 % of the applicable limit). The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents was 4.02E-03 mrem (0.08% of the applicable limit). The summation of the hypothetical maximum individual dose from effluents in 2005 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 2005, making shipments of solid radioactive waste to a licensed burial site.

RADIOLOGICAL EWNVIRONMIENTAL MONITORING The Radiological Environmental Monitoring Program (REMP) was established in 1981 to monitor L

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.

v There were over 3000 radioactivity analyses performed on the 1274 radiological environmental samples collected in 2005. 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 2005 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 2005 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 20(05 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 fourteen (14) samples collected. The average cesium-137 radioactivity for all locations was 532.34 pCilkg and was within the maximum value of 864 pCi/kg established in 1981.

In 1999, a sediment sample of the northwest drain impoundment (sampling location #64) was analyzed to contain 62 pCi/kg of cobalt-60. During 2005, 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 tc Table 16 for detailed sample results.

Direct radiation measurements showed no change from previous years. The indicator locations averaged 58.12 mrem/year and control locations averaged 53.79 mrem/year. In 2005, 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 2005, the operation of the PNPP resulted in no significant increase in the radionuclide concentrations observed in the environment.

LAND USE CENSUS In order to estimate radiation dose attributable to the operation of PNPP, the potential pathways.

through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed as part of the REMP. During the census, PN\\PP 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 a; mini-industrial parks and residential housing tracts. This is reflected in the loss of available milking arimals within a five mile radius of PNPP to support the Radiological Environmental Monitorifcg Program (REMP). For 2005, the predominant land use within the census area continues to be ruraVagricultural.

Radiological Effluent Releases Page 2

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

operation. As in past years, this program has successfully prevented 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.

No special reports were generated in 2005.

OHIO DEPARTMENT OF NATURAL RESOURCES SURVEY During the summer of 2003, the Ohio Department of Natural Resources (ODNTR), Division of Wildlife was granted access to perform a survey of the Perry Plant's previously documented Spotted U

Turtle habitat. The survey failed to identify any spotted turtles in the previously recorded area and is being attributed to the area having been overrun by the Phraginites sp. However, the discovery of an open canopy of fens further south on the property is prime habitat for Spotted Turtles and has yet to be impacted by Phragmnites sp. Although scheduled for completion in 2005, the ODNR representative did not return as planned to monitor this new habitat and complete the survey.

Radiological Effluent Releases Page 3

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

RADIATION FUNDAMENTALS Atoms are the basic building blocks of all matter. Simply described, atoms are made up of pos.tively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, respectively. The relatively large protons and neutrons are packed together in the center of the atom called the nucleus. Orbiting around the nucleus are one or more smaller electrons. In an electrically neutral atom, the positively charged protons in the nucleus balance the negatively charged electrons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other, which helps hold the atom together. Other attractive forces between thle protons and neutrons keep the densely packed protons from repelling each other, and preventin 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 numnbers of neutrons are called isotopes. All isotopes of the same element have the same chemical properties and many are stable or non-radioactive. An unstable or radioactive isotope of an element is called a radioisotope, or radionuclide. Radionuclides contain an excess amount of energy in the nucleus, which is usually due to an excess number of neutrons.

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

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

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

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

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

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

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

l Actiiity 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 Li the rate at which the atoms are decaying. One curie of activity indicates the decay of 37 billion atoms per second. Smaller units of the curie are often used in this report. Two common units are the microcurie ([iCi), 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.

L, LOWVER 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 L

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 Terrestial 10.9%

Medical/X-Ray Nuclear Fuel Cycle 8.0 10.9%

Fall-Out Nuclear Medicine 0.26%

Miscellaneous Cosmic 4.0/

0.10%

Consumer Products Other 0.7%

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 2005 Sampling Program results. These radionuclides are included; however, in Appendix A, 2005 Inter-Laboratory Cross Check Comparison Program Results.

Cd 0

Radiological Effluent Releases Page 6

L ANNuAL ENVIRONMENTAL AND EFFLUEN RELEASE REPORTL RADIOACTIVE EFFLUENT RELEASES I

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 L

radioactivity released to the environment is minimal and within regulatory limits. Effluent release programs include the operation of monitoring systems, in-plant sampling and analysis, quality assurance, and detailed procedures covering all aspects of effluent monitoring.

The liquid and gaseous radioactive waste treatment systems at PNPP are designed to collect and process these wastes in order to remove most of the radioactivity. Effluent monitoring systems are used to provide continuous indication of the radioactivity present and are sensitive enough to measure several orders of magnitude lower than the applicable release limits. This monitoring equipment is equipped with alarms and indicators in the plant control room. The alarms are set to r

provide warnings to alert plant operators when radioactivity levels reach a small fraction of actual limits. The waste streams are sampled and analyzed to identify and quantify the radionuclides being released to the environment.

Gaseous effluent release data is coupled with on-site meteorological data in order to calculate the L

dose to the general public. Devices are maintained at various locations around PNPP to constantly sample the air in the surrounding environment. Frequent samples of other environmental media are also taken to determine if any radioactive material deposition has occurred. The Radiological L

Environmental Monitoring Program (REMP) is described in detail in the next section.

Generation of solid waste is carefully monitored to identify opportunities for minimization. Limiting the amount of material taken into the plant, sorting material as radioactive or non-radioactive, 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:

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

[10CFR20], Appendix B; Title 10 of the Code of Federal Regulations, Part 50 (Domestic Licensing of Production and L

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 I

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 L

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT no other fuel sources near the PNPP, the 40CFR190 limits, which are described below, were not exceeded in 2005.

The 40CFR 190 limit for total direct-radiation dose is 25 mrem. For 2005, the total whole body dose to a member of the general public, considering all sectors, was 9.40E-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 gCi/mL of total activity. These values are the maximum effluent concentrations.

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

During any calendar quarter:

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

During any calendar year:

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

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

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.

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

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

During any calendar quarter:

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

During any calendar year:

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:

i_

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

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

RELEASE SUNMARY 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, L

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 L

calculations are performed prior to, and after discharging this processed water to Lake Erie to ensure regulatory compliance and dose minimization principals are maintained.

L Liquid radioactive waste system effluents may be intermittently released, which are considered to be L

"batch" releases. Table 1 provides information on the number and duration of these releases for 2005.

L Table 1: Liquid Batch Releases L

l QUARTER l QUARTER2 1QUARTER3 QUARTER 4 TOTAL Number of batch releases 49 19 1

0 69 Total time period for batch releases, min 1.28E+04 4.82E+03 4.32E+02 O.OOE+00 1.81E+04 Maximum time for a batch release, min 4.36E+2 3.52E+2 4.32E+2 O.OOE+00 4.36E+02 Average time period for a batch release, min 2.61E+2 2.54E+2 4.32E+2 O.OOE+00 2.62E+02 Minimum time for a batch release, min 3.70E+1 2.OOE+O 4.32E+2 O.OOE+OO 2.OOE+OO Average stream flow during periods of effluent 1.70E+5 2.04E+5 2.24E+5 O.OOE+00 1.80E+05 release into a flowing stream, L/min 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 203108 minutes and a discharge volume of 7.70E+06 liters. Tritium concentration for this release was 2.35E-07 IiCi/ml. Table 2b provides information for releases in 2005.

Radiological Effluent Releases Page 9 L

L L

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

TCOTAL ERROR, %

A.

Fission and Activation Products

1. Total Released, Ci 5.32E-03 2.35E-03 6.31E-05

<LLD L.OOi_+01 (excluding tritium, gases, alpha)

2.

Average Diluted Concentration, pCi/mL

8.21E+00 6.66E-02 4.67E-04

<LLD

3. Percent of Applicable Limit, %

O.OOE+00 O.OOE+00 N/A N/A B.

Tritium

1. Total Released, Ci 3.42E+01 L.19E+01 6.1SE-01

-1.77E-03 L.001+O1

2.

Average Diluted Concentration. upCi/mL 1.23E-06 3.79E-07 1.66E-08 5.78E-1I

3.

Percent of Applicable Limit. %

1 1.23E-01 3.79E-02 1.66E-03 5.78E-06 C.

Dissolved and Entrained Gases l

1. Total Released, Ci l 1.67E-04 1.72E-05

<LLD

<LLD 1.00IE+Ol

2.

Average Diluted Concentration, MCi/mL 0

1.21E-06

<LLD

3. Percent of Applicable Limit. %

1 O

6.06E-01 0

l O

D. Alpha Activity, Ci 2.21E-05

<LLD

<LLD ll.OO,+0l E.

Waste Volume Released. Liters (prior to I 6.55E+06 J 3.89E+06 4.96E+06 1.49E+6 1.001+01 dilution)

I I

I F.

Dilution Water Volume Used, Liters I 2.79E+10 3.14E+10 l 3.72E+10 l3.06E+10 l1.001+01

<LLD - Less than the lower linit of detection N/A - Not Applicable, the ODCM does nor have a limitforfission and activation products.

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

Radiological Effluent Releases Page 10

L ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT L

Table 2a: Summation of Batch Liquid Effluent Releases ARTER Q UARTER QUARTER QUARTER EST.

1 2

3 4

TOTAL ERROR, %

A.

Fission and Activation Products E

Total Released, Ci 5.32E-03 2.35E-03 6.31 E-05

<LLD l.OOE+iOll (excluding tritium, gases, alpha)

B.

Tritium Total Released. Ci 3.42E+01 L1.9E+01 6.18E-01 0

L.OOE+01 C.

Dissolved and Entrained Gases l

Total Released. Ci 1.67E-04 1.72E-05

<LLD

<LLD l.OOE+01 D.

Alpha Activity, Ci 2.21E-05

<LLD

<LLD l.OOE+Ol E.

Waste Volume Released, Liters (prior to 6.55E+06 3.89E+06 4.96E+06 1.46E+06 l.OOE+01 dilution)

<LLD - Less than the lower limit of detection L

Table 2b: Summation of Continuous Liquid Effluent Releases QUARTER QUARTER QUARTER QUARTER EST.

1 2

3 4

TOTAL ERROR, %

A. Fission and Activation Products E

Total Released, Ci

<LLD

<LLD 6.3 1E-05

<LLD l.OOE+OI (excluding tritium. gases. alpha)

B. Tritium Total Released. Ci

<LLD

<LLD 6.1SE-01 1.77E-03 I.OOE+OI C. Dissolved and Entrained Gases Total Released. Ci

<LLD

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

<LLD

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

0 6.37E+06 1.33E+06 I.OOE+OI dilution)

<LLD - Less tlan the lower limir of detection Radiological Effluent Releases Page 11 L

ANNUAL ENwIRONTMENTAL 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 eitFher 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 TOrAL Tritium Ci 3.42E+01 1.19E+01 4.58E-04 I.77E-03 4.67E'+OI Chromium-5 1 Ci

<LLD

<LLD Manganese-54 Ci 4.92E-04 5.26E-04

<LLD

<LLD 1.021-03 Iron-55 Ci

<LLD

<LLD Iron-59 Ci

<LLD

<LLD cLLD Cobalt-58 Ci 2.07E-04 4.73E-05

<LLD

<LLD 2.541.-03 Cobalt-60 Ci 3.84E-03 I.30E-03 4.58E-04 I.77E-03 5.201,-03 Zinc-65 Ci 3.78E-04 3.48E-04

<LLD

<LLD 7.261L-04 Strontium-92 Ci

<LLD

<LLD Zirconium-95 Ci

<LLD

<LLD Niobium-95 Ci

<LLD

<cLLD Technetium-99M Ci

<LLD

<LLD Rhuthenium-105 Ci

<LLD

<LLD Silver-IIOm Ci 2.41E-05

<LLD

<LLD 2.41 E-05 Antimony-124 Ci

<LLD

<LLD Antimony-125 Ci

<LLD l 3.51E-05

<LLD

<LLD 3.51I'-05 Iodine-131 Ci

<LLD

<LLD cLID Xenon-133 Ci

<LLD

<LLD 4.12E-05 4.561'-04 Cesium-134 Ci 1.42E-04 2.30E-05

<LLD

<LLD 1.651-04 Cesium-137 Ci 2.42E-04 7.02E-05

<LLD

<LLD l3.121.-04 Cesium-138 l

Ci

<LLD

<LLD l<LlD Lanthanum-140 Ci

<LLD

<LLD l

<LLD Gold-I99 Ci

<LLD

<LLD cLl.D Total for Period Ci 3.42E+O1 1.19E+01 6.18E-01 l 1.77E-03 4.67F'+Ol LLLD - Less than the lowi'er limnit of detection Radiological Effluent Releases Pac:e 12

L ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 1-.d Gaseous Effluents Gaseous effluents are made up of fission and activation gases, iodine and particulate releases. The fission and activation gas releases are primarily a result of containment purge operations, small steam leaks, and offgas system operation. The iodine and particulate releases are primarily a result of small steam leaks. Gaseous effluents from PNPP exit the plant via one of four effluent vents.

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

A summation of all gaseous radioactive effluent releases is given in Table 4. If a radionuclide was not present at a level "greater than or equal to the LLD" (ŽLLD), 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 6.38E+01 5.24E-01 3.71E-03

<LLD I.OOE+01

2.

Average Release Rate. pCi/sec 8.21E+00 6.66E-02 4.67E-04

<LLD

3.

Percent of Applicable Limit. %

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

Iodine

1.

Total Iodine-131 Released. Ci2.30E-04

<LLD

<LLD 1.00E+01

2.

Average Release Rate. pCi/sec 2.95E-05

<LLD

<LLD l

<LLD

3.

Percent of Applicable Linut. %

N/A N/A N/A N/A C.

Particulates Mith Half-Lives > 8 days l

l

1.

Total Released. Ci

<LLD 9.53E-06

<LLD

<LLD LOOE+01

2.

Average Release Rate. pCi/sec N/A 1.21E-06

<LLD

3.

Percent of Applicable Limit. %

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

Alpha Activity. Ci 1.03E-06 N/A N/A N/A E.

Tritium

1.

Total Released, Ci 2.74E+00

<LLD

<LLD 1.OOE+01

2.

Average Release Rate. pCi/sec 3.52E-01 l

N/A N/A N/A

3.

Percent of ODCM Limit, %

N/A N/A N/A

<LID - Less than the lower limit of detection N/A - Nor Applicable, the ODCAM does not have a limit forfission and activation products.

II I

The radionuclide composition of all gaseous radioactive effluents for a continuous-mode, ground-level release is given in Table 5. If a radionuclide wvas not present at a level "greater than or equal to the LLD" (ŽLLD), 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

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 5: Radioactive Gaseous Effluent Nuclide Composition QUARTER QTER QUAR TER QUARTER ANNUAL UNIT 234T()TAL A. FISSION A1ND AcTi\\PATION GASES

=

Tntium Ci 2.74E+00

<LLD

<LLD 2.74 E+00 Argon-41 Ci

<LLD 8.82E-03

<LLD

<LLD 8.8'!E-03 Krypton-85m Ci 5.54E-01 5.09E-03

<LLD

<LLD 5.59E-01 Krypton-85 I Ci

<LLD

<LLD Krypton-87 l

Ci 5.75E-01 l 4.27E-02

<LLD

<LLD l

6.18E-01 Krypton-88 Ci 1.IIE+00 ! 2.03E-02 dLLD

<LLD 1.lIlE+00 Xenon-131m I

Ci

<LLD l

<LLD

<LLD l

<LD Xenon-133m I

Ci 7.33E-02 I

<LLD l

<LLD

<LLD l

7.33E-02 Xenon-133

! Ci j 5.33E+01 7.24E-04 J

<LLD

<LLD I 5.3 E+O1 Xenon-135m l

Ci

[ 2.78E-01 l 4.79E-02 j

<LLD

<LLD 3.2GE-01 Xenon-135

[ Ci ! 7.64E+00 5.34E-02 3.71E-03

<LLD 7.6SE+00 Xenon-137 Ci lI.42E-02 l 4.86E-02

<LLD

<LLD l

6.28E-02 Xenon-138 lCi 2.48E-01 l 2.96E-01

<LLD

<LLD J5.44E-01 Total for Period Ci 6.66E+O1 5.24E-01 3.71E-03

<LLD 6.71E+O1 B.

IODLNE Iodine-131 Ci 2.30E-04

<LLD

<LLD 2.30E-04 Iodine-132 Ci

<LLD

<l.LD Iodine-133 Ci 7.89E-05

<LLD dLLD

<LLD 7.89E-05 Iodine-134 Ci

<LLD

<LLD dLLD

<LLD dILD Iodine-135 Ci l

dLLD l

dLLD dLLD

<LLD l

<LLD Total for Period Ci I 3.09E-04

<LLD l

<LLD

<LLD I 3.0SEW04 B.

PARTICULATE II Chromium-5 I Ci

<LLD

<LLD 1 LLD Manganese-54 Ci

<LLD

<LLD l

dLD Iron-59 Ci

<LLD

<LLD Cobalt-58 Ci

<LLD

<LLD l

<LLD Cobalt-60 Ci

<LLD

<LLD Zinc-65 Ci

<LLD

<LLD Rubidium-88 Ci

<LLD

<LLD Rubidium-89 Ci

<LLD

<LLD Strontium-89 Ci

<LLD

<LLD Strontium-90 Ci

<LLD

<LLD Strontium-91 Ci

<LLD

<LLD Yttrium-91m Ci

<LLD

<LLD Strontium-92 Ci

<LLD

<lLD Zirconium-95 Ci

<LLD

<LLD Molybdenum-99 Ci

<LLD

<LLD Cesium-137 Ci

<LLD 9.53E-06

<LLD

<LLD 9.5'$E-06 Cesium-138 I Ci

<LLD

<ILD Barium-139 l

Ci

<LLD

<.LD Barium-140 T

Ci

<LLD

<LLD Lanthanum-140 l

Ci

<LLD

<LLD Total for Period l Ci I

<LLD 9.53E-06 l

<LLD

<LLD l

9.53;E 06

<LLD - Less than the lower limit of detection 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 (Duratek 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 2005. The solid radioactive waste summary in Table 6 includes all PNPP shipments.

Table 6: Solid Waste Shipped OfMsite for Burial or Disposal A. Type of Solid Waste Shipped VOLUNME ACTIVITY PERIOD EST. TOTAL M3 Ci ERROR %

Spent resin, filter sludge, evaporator 8.678 98.25 1/1/2005-

+1-25 bottoms, etc.

12/31/2005 Dry compressible waste, contaminated 31.212 12.131 1/1/2005-

+/-25 equipment, etc.

12/31/2005 Irradiated components, control rods, etc.

0 0

N/A N/A Other (describe) 0 0

N/A N/A B. Estimate of Majors N)uclide Composition ABUNDANCE I EST. TOTAL (by type of waste)

RADIONUCLIDE ERROR, %

Spent Resin, Filter Sludge, Evaporator Bottoms, etc.

Mn-54 6.8

+ 25 Fe-55 38.6 Cs-137 1.4 Co-60 32.7 Zn-65 16.9 Dry Compressible Waste, Contaminated Equipment, etc.

Mn-54 2.7

+25 Fe-55 37.1 Co-60 26.4 Ce-141 14 Ce-144 14 Irradiated Components, Control Rods, etc.

l None l

N/A l

N/A

[-O ther(describe) l None I

N/A N/A C. Disposition Number of Mode of Shipments Transportation l Destination Solid Wastet 2 )

0 N/A l

N/A Irradiated Fuel Shipments l

0 I

N/A l

N/A A/A -- Not Applicable (1 ) -- "Major" is defined as any individual radionuclide identified as >1% of the waste npe abundance.

(2 ) --Additional shipments were made to Studnik, in Erwin. 7N; Durarek. Oak Ridge, TN. This waste was combined with waste from other utilities disposed of at Bamwell, SC or Envirocare of Utah.

IJ I.-

L L

Radiological Effluent Releases Page 15 L

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

pressure. Data is logged from the tower through separate data loggers, and transmitted to a common plant computer. This system compiles the data and calculates a variety of atmospheric parameters, communicates with the Meteorological Information Dose Assessment System (MIDAS), and sends data over communication links to the plant Control Room.

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

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

First, they are performed using data for a 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 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 bcdy or worst-case, organ dose values. If any radionuclide was not present at a level greater tham the LLD, it was not used in the dose calculations.

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

% or TYPE OF DOSE ORGAN DOSE, mrem LINIT LINMIT Liquid Effluent Whole body 3.47E-03 3.OE+00 1.2E-01 Liver 4.54E-03 1.OE+01 4.5E-02 Noble Gas - gamma air N/A 7.80E-03 L.OE+01 7.8E-02

- beta air N/A 1.79E-02 2.OE+01 9.OE-02 Noble Gas Whole body 4.02E-03 5.OE+00 8.OE-02 Skin 1.08E-02 I

.5E+01 7.2E-02 Particulate & Iodine Thyroid 2.31 E-03 1.5E+01 1.5E-02 Radiological Effluent Releases Page 16

L.I 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 1.4E+00 Thyroid I.OE+00 Gaseous Effluent WVhole body 1.2E-03 I

__I_

7Tfroid 1.6E-03 Table 9 provides the calculated hypothetical maximum site boundary dose values considering only the land-based sectors. If any radionuclide was not present at a level greater than the LLD, it was not used in the dose calculations.

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

% OF TYPE OF DOSE ORGAN DOSE, rnrem LnIMT LIMIT Liquid Effluent Whole body 3.47E-03 3.OE+00 1.2E-01 Liver 4.54E-03 I.OE+OI 4.5E-02 Noble Gas

- gamnna air N/A 4.28E-03 L.OE+01 4.3E-02

- beta air N/A 3.42E-03 2.OE+01 1.7E-02 Noble Gas Whole body 2.23E-03 5.OE+00 4.5E-02 Skin 4.53E-03 1.5E+01 3.OE-02 Particulate & Iodine

[ Thyroid J

2.86E-04

[ 1.5E+01 1.9E-03 L

L Other dose calculations are performed for a hypothetical individual who is assumed to be inside the site boundary for some specified amount of time. This person would receive the maximum dose during the time spent inside site boundary. Because no one actually meets the criteria established for these conservative calculations, the actual dose received by a real member of the public is significantly less than what is calculated for this hypothetical individual. This dose is assessed relative to the offsite dose, and considers dilution, dispersion, and occupancy factors.

The higghest 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.

L Table 10: Maximum Site Dose from Liquid Effluents WO'HOLE BODY ORGAN DOSE, DOSE, Mrem nmrem First Quarter 1.9E-04 2.2E-04 Second Quarter 5.7E-05 6.7E-05 Third Quarter 2.2E-06 2.6E-06 Fourth Quarter O.OE+00 O.OE+00 Annual 2.5E-04 2.9E-04

.L Radiological Effluent Releases Page 17 L

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Although several cases were evaluated to determine the highest hypothetical dose from gaseous effluents to members of the public inside site boundary, the activity inside the site boundary with the highest dose potential is also shoreline fishing. The cases evaluated included traversing a publi:

road within the site boundary, shoreline fishing (assuming fishing 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year), non-plant related training, car-pooling, and job interviews. The maximum on-site gaseous doses generated are shown in Table 11.

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

_mrem mrem First Quarter I.OE-03 2.4E-04 Second Quarter 6.6E-05 1.3E-04 Third Quarter 2.3E-07 6.OE-07 Fourth Quarter O.OE+OO O.OE+OO Annual 4.3E-04 I.2E-03 An average whole body dose to individual members of the public at or beyond the site boundary is thmn 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 PNSPP (2,420,000 people). The dose from liquid radiological effluents is determined for the population that re& eives drinking water from intakes within 50 miles of PNTPP (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 1.9E-07 5.OE-10 Second Quarter 54E-08 1.5E-I I Third Quarter 5.SE-09 O.OE+OO Fourth Quarter

.8E-08 O.OE+OO Annual 2.6E-07 5.4E-IO A:BNORMiAL RELEASES There were no abnormal radioactive release events during 2005.

NON-COMPLIANCES There were none (0) non-compliance to the ODCM Controls requirements in 2005.

Radiological Effluent Releases Page 18

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT OFFSITE DOSE CALCULATION MANUAL CHANGES During this reporting period, there were three (3) revisions to the Offsite Dose Calculation Manual:

Revision 12

Incorporated revised wording in Appendix C associated with Controls 3. 0. 4 and 4. 0. 4 per License Amendment 131.

Revision 13

Remove reference to G50-F155 as this is the low flow discharge valve and has been abandoned in place.

Updated Offgas Vent Pipe ventilation flowrate number to correspond with current Updated Final Safety Analysis Report value.

Added note to allow continued operation of Containment Vessel and Drywell Purge Ventilation System during periods of planned maintenance on Unit I Vent radmonitor as long as compliance with Control 3.11.2.1 is met.

Revision 14

Revised Table Notations Step (5), removing the word "flowing".

Added page for ODCM REMP Sample Locations.

Revised Figures 5.1-1, 5.1-2 and 5.1-3.

PROCESS CONTROL PROGRAM CHANGES During this reporting period, there was one (1) change to the Process Control Program:

Incorporated revised wording in Appendix A associated with Controls 3. 0. 4 and 4. 0. 4 per License Amendment 131.

Radiological Effluent Releases Page 19 I

L..j I 1 1

L L

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

SAMPLING LOCATIONS REMP samples are collected at numerous locations, both on site and up to 22 miles away from the plant. Sampling locations are divided into two general categories: indicator and control. Indicator locations are those which would be most likely to display effects caused by plant operation. They are relatively close to the plant. Control locations are those which are considered to be unaffected by plant operation. Typically, they are a greater distance from the plant, in the least prevalent wind directions. Data obtained from the indicator locations are compared with data from the control locations. This comparison allows naturally occurring background radiation to be taken into account when evaluating any radiological impact PNPP may have had on the environment. Table 13, Figure 2, Figure 3 and Figure 4 identify the PI\\TPP REMP sampling locations.

Many REMP samples are collected in addition to those required by the PNPP ODCM. The ODCM requirements for each sample type are discussed in more detail below. Sample types and locations required by the ODCM are shown in Bold in Table 13.

Radiological Environmental Monitoring Page 20

L..

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 13: REMP Sampling Locations (1)

Location#

Description Miles Direction lf Media(2) 1 Chapel Road 3.4 ENE I

TLD, AIP 2

Kanda Garden 1.9 ENE l

FoodProducts 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 Seriice Center 11.0 SSW TLD, AIP 7

Site Boundary J

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 Parmlv Rd.

0.6 SSW TLD 12 Site Boundary 0.6 WSWV TLD 13 Mladison-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 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 l

Sediment 28 CEI Ashtabula Plant Intake l 22.0 j ENE Water 29 1 River Rd.

4.3 SSE TLD 30

] Lane Rd.

4.8 l

SSW' I

TLD 31 W

Wood and River Rd.

4.

SE TLD 32 J Offshore-Mentor 1 15.8 W SW Sediment, Fish 33 l River Rd.

4.5 S

TLD 34 P.NPP Intake 0.7 NW Water 35 Site Boundary P

0.6 E

TLD, AIP 36 Lake County _ 'ater Plant 7

_3.9

_S__'

TLD, Water 37 Gerlica Farm 1

1.5 ENE Food Products 41 Tuttle Farm 5.8 SSE Milk 51 l RettgerMilk Farm

_9.6 S

Milk 53 l Neff Perkins 0.5 l

WSW l

TLD 54 Hale Rd. School l

4.6 SW TLD 55 1 Center Rd.

I 2.5 S

TLD 56 1Madison High School 4.0 ESE TLD 58 l Antioch Rd.

! 0.8 ENE TLD 59 l Lake Shoreline at Green Rd.

4.0 ENE Water 60 l Lake Shoreline at Perry Park 1.0 WSw I

Water 61 l KellerMilk Farm 7.4 SE Milk 63 l Minor Stream Mouth l 0.08 NNE Sediment 64 l Northwest Drain Mouth l

0.09 NW Sediment 65 l Major Stream Mouth 0.18 l

W

[

Sediment 70 l H&1I Farm Stand l

16.2 J SSW Food Products (1) chronologically missing location numbers denote deleted or retired sampling locations.

(2)

AIP = Air, Iodine and Particulate Veg = Vegetation TLD = PiernnoluminescentDosimneter L

L L

Radiological Environmental Monitoring Page 21 L

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 2: REMP Sampling Locations Within Two Miles of Plant Site I

I I

U I

I I

NNW N

NNE NW WNW W

NE ENE E

ESE SE WSW SW SSW S

SSE 1

0 1

2 MILES I

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 0

1 2

3 4

5 10 MILES m -

I Radiological Environmental Monitoring Page 23

W C/ent e W~Ile 0

%M.

0 mils 1Oiies 307W 46

\\

Giddil 534 t

Sho W 1wresl 2*

5 r

-5C irln

}

atgoe me IValley

'4 O

oo b

o tw

~~~ghb Chard\\

mi>\\

r oigvl t

\\(~lqe 91 a

aq r+

rA w

UQ fb t-.)

-P.

5 0

5 10 15 20 MILES

%nm%==mdm I

0 0V) 4 L

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 specif.c 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.

Tiitium 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 resu t 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 aralyses performed on environmental samples collected for the PNPP REMP in 2005.

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 REM':

sample analyses complied with those values in 2005.

Radiological Environmental Monitoring Page 25

L 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-31 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 WVater Monthly Gross Beta Actihity, 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 L

2005 SAMPLING PROGRAM The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the 2005 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, 2005 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 2005.

Program Changes There were no changes in 2005.

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 erosion and shoreline collapse. Table 15 provides information on samples missed during 2005.

Radiological Environmental Monitoring Page 26 I.

U -

L

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 15: Missed REMP Samples in 2005 MIEDIA ILOCATION DATE REASON Food Products l

Al April, May 2005 l

Vegetables not ready for harvest Lake Water 59 January, February, March, Sample unavailable due to frozen shoreline December 2005 Lake Water 60 January, February, March, Sample unavailable due to frozen shoreline lDecember 2005 Milk 41 January, February, March, Drying period for goats December 2005 Milk 61 January, February, March, Drying period for goats October, November, December 2005 Atmospheric Monitoring Air AHI sampling is conducted to detect any increase in the concentration of airborne radionuclides. The PN-,PP ODCM requires five locations (four indicator and one control). Air sampling pumps are used to draw continuous samples at a rate of approximately twvo cubic feet per minute. The air is drawn through glass fiber filters (to collect particulate material) and a charcoal cartridge (to adsorb iodine).

The samples are collected on a weekly basis, 52 weeks a year, from each of seven air sampling stations. Six (6) of these locations are within four miles of the plant site; the seventh is used as a ccntrol location and is eleven miles from PNPP.

On occasion, air sample locations can experience power losses associated with storms and/or malfunctioning equipment. On 9/28/05, 10/5/05 and 11/9/05 isolated power loss was experienced at location #1 due to localized storm activity. In all instances the power loss was short in duration and did not result in any missed samples.

Air samples are analyzed weekly for gross beta activity and radioiodine activity. The air samples are also analyzed by gamma spectral analysis quarterly. A total of 364 for air particulate and 364 air radioiodine samples were collected and analyzed in 2005.

Gross beta activity was detected in all air samples and ranged up to 0.05 pCi/m3. The average gross beta activity at both indicator and control locations was 0.02 pCi/m3 for 2005. 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 2005 and the previous years.

Except for naturally occurring beryllium-7, no radionuclides were identified in the gamma spectral analysis above the LLD values. Iodine-1 31 was not detected in any sample above the LLD of 0.05 pCi/m3.

Radiological Environmental Monitoring Page 27

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 5: Annual Average Gross Beta Activity, in Air 0.05 0.04 i0.03 1

a..

0.02 0.01 U

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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 information on the atmospheric radionuclide deposition. The PNPP ODCM requires neither vegetation nor soil samples.

Milk Samples of milk are collected once each month from November through March, and twice each 3

month from April through October. Sampling is increased during the summer because animals usually feed outside on pasture and not on stored feed. For 2005 the PNPP REMP included three (3) milk locations located 5.8, 7.4 and 9.6 miles away from the plant. Since the milk sampling locations do not meet the requirements of the ODCM (no milk-producing animals located within the required areas), 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.

Milk samples are analyzed by gamma spectral analysis for radioiodines and other radionuclides. A total of forty-two (42) milk samples were collected in 2005. Iodine was not detected above the LLD of 0.75 pCiIL in any of the samples. The concentrations of all radionuclides, except naturally occurring potassium-40, were below LLDs in all samples collected.

Food Products Food products can provide a direct pathway to humans by ingestion. They can absorb radionuclides from atmospheric deposition on soil or from irrigation water drawn from a lake or pond receiving airborne or liquid effluents. Also, radionuclides in the soil may be absorbed by the roots of the

7 plants and become incorporated into the edible portions. Because there is not a sufficient number of milk sampling locations, the PNPP REMP is required to include two food product indicator locations and one control location. Food products are collected monthly during the growing season from five gardens in the vicinity of PNPP. The control location for food products is 16.2 miles from PNPP.

A total of seventy-two (72) food product samples were collected and analyzed by gamma spectral 3

analysis in 2005. 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 Radiological Environmental Monitoring Page 28 i

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT radionuclides, were found in several samples, as expected. No other radionuclides were detected above the required LLDs.

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

Water Water is sampled from five locations along Lake Erie in the vicinity of the PNPP as required by the PNPP ODCM. Samples from three locations are collected using composite sample pumps. The pumps are designed to collect water at regular intervals and composite it in a sample container. 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-two (52) water samples were collected and analyzed for gross beta activity and gamma spectral analysis in 2005. From these monthly samples, a quarterly composite sample was obtained and analyzed for tritium activity. Refer to Table 15 for an explanation of missed samples.

Gross beta activity was detected in seven (7) of the fifty-two (52) samples collected. For 2005, the detectable gross beta activity was 3.30 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 12-10

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Control co'6 Radiological Environmental Monitoring Page 29

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT There were no radionuclides detected by gamma spectral analysis above the LLD. Tritium was not detected above the LLD value in any of the eighteen (18) samples analyzed. These results are well within the range of those measured in previous years, which have ranged from below the LLD to L

2,200 pCi/L.

Sediment L

Sampling lake bottom sediments can provide an indication of the accumulation of particulate radionuclides which may lead to internal exposure to humans through the ingestion of fish, the re-suspension into drinking water, or as an external radiation source to fishermen and swimmers from shoreline exposure. Although the PNPP ODCM requires only one location, sediment is sampled twice each year from seven (7) locations. Two (2) of the sampling locations are also fish sampling locations. Sediment samples from offshore are collected using a hand dredge. Shoreline samples are collected using a scoop. Fourteen (14) sediment samples were collected in 2005 and analyzed by L

gamma spectrometry.

The predominant radionuclide detected by gamma spectral analysis was naturally-occurring potassium-40. Potassium-40 has been detected in all samples, since the program began in 1981.

Cesium-137 activity was detected in five (5) of the fourteen (14) samples collected and ranged from 135.16 pCi/kg to 1085.10 pCi/kg. The annual average cesium-137 activity was 164.14 pCi/kg at the indicator locations and 1084.65 pCi/kg at the control location. The average cesium-137 radioactivity for all locations was 532.34 pCi/k-g and is within the maximum value of 864 pCi/kg established in 198 1. 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 locations from year-to-year may be contributed to:

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

L

2. Sampling in nearly the same location approximately 41/2 miles off-shore, even with GPS, is extremely difficult.

L L

Radiological Environmental Monitoring Page 30

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 7: Annual Average Cesium-137 Concentration in Sediment 1 600 -

1400 -

I 1200-I00

Z_ 1 000-C-,

B,800

.5:

600 400 200 if C) 0)

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C\\I Year 3 Indicator

Control 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 2005, 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 <6.9 pCi/kg to 552 +/- 37 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 05/27/05 06/17/05 09/19/05 09/23/05 64

<14.3

<6.9 64-1

<11.4

<16.2 64-2

<38.3

<21.5 64-3 109+/-35 54+/-28 64-4 64-5 64-6

<34.2

<26.9 64-7 125+/-33 94+/-54 64-8 172+/-49 58+/-34 64-9 268+/-40 163+/-29 64-10 210+/-28 552+/-37

No sample available or insufficient sanmlefor analysis Radiological Environmental Monitoring Page 31

L ANNUAL ENVIRONMIENTAL AND EFFLUENT RELEASE REPORT Table 17: Northwest Drain Impoundment Cesium-137 Activity, pCilkg (dry)

Location 05/27/05 06/17/05 09/19105 09123/05 64

<30.8

<14.4 64.1

<30.9

<26.6 64-2 528+/-61 702+/-52 64-3 997+/-70 579+/-32 64-4 64-5 64-6 513+/-35 583+/-62 64-7 1806+/-71 516+/-77 64-8 1518+/-83 1749+/-90 64-9 3322+/-99 4178+/-128 64-10 2550+/-62 504+/-26

No sample available or insufficient sample for analysis L.-

L Fish Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondarily to serve as indicators of radioactivity in the aquatic ecosystem. Fish are collected from two locations, annually during the fishing season as required by the ODCM. An important sport or commercial species is targeted, and only the fillets are sent to the laboratory for analysis. In 2005, 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 2005. As expected, naturally occurring potassium-40 was found in all samples. No other radionuclides were detected above the LLD.

Direct Radiation Monitoring T7her7noluminscent 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 252 TLDs were collected and analyzed in 2005. This includes 224 collected on a quarterly basis and twenty-eight (28) collected annually. Annual TLDs are not required per the ODCM and are used for supplemental data only.

Radiological Environmental Monitoring Page 32 L

L L

L

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT For 2005, the annual average dose for all indicator locations was 58.12 mrem, and 53.79 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 12.73 mrem, and 12.08 mrem for all control locations. Please refer to Appendix B, 2005 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 c 20 E

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Control Conclusion Sediment samples continue to confirm cobalt-60 in the northwest drain impoundment. The activity level was just above the detection limits. 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.

009 Radiological Environmental Monitoring Page 33

L ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT INTER-LABORATORY CROSS-CHECK COMPARISON PROGRAM Introduction The purpose of the Inter-laboratory Cross-Check Comparison Program (ICCCP) is to provide an independent check on the vendor laboratory's analytical procedures. Samples with a known concentration of specific radionuclides are provided to the vendor laboratory. The vendor laboratory L

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.

L The EPA's program is no longer funded or offered. The reason that the EPA program was referenced in the regulatory guide is that the EPA standards were traceable to National Bureau of Standards (now known as National Institute Standard Technology). In response to this problem, Teledyne (PNPP vendor lab) incorporated a program offered by Environmental Resource Associates (ERA Company), which covered the same analyses in the same matrix at the same frequency as the EPA program. The ERA Company has received NIST accreditation for its program, as an equivalent L

program. In addition to comparison cross checks performed with the ERA Company, the vendor laboratory routinely monitors the quality of their analyses by:

i

+ 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.

L Conclusion Appendix A, 2005 Inter-Laboratory Cross-Check Comparison Program Results, includes results L

from both the above referenced programs and the ERA Company cross-check program.

1) Environmental Resource Associates (ERA), Table A-1: Two samples were initially found to be L

out of limits. Sample STWV-1074, Gross Alpha analysis was inadvertently calculated using an Am-241 efficiency. The sample was recounted/calculated using the correct Th-232 efficiency.

Sample STW1-226, Ra-228 analysis required a higher counting rate due to short lived decay. A

.delay in the count time of 100 minutes provided results within the control limits.

2)

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

3) Table A-4, In-House "Blank" Samples: One (1) milk sample (SPMI-4835) analyzed for Sr-90 was found to be outside the program acceptance criteria. Low levels of Sr-90 remain in the environment and concentrations of (1-5 pCi/l) found in milk is not unusual.

4) Table A-5, In-House "Duplicate" Samples: Three samples were found to be outside their expected control limits. Soil samples SO 3056, 3057, K-40 and Samples G 2958, 2959, Gr. Beta failed their initial analyses due to longer count times which resulted in smaller margins of error.

Water sample 5748, 5749, Gr. Beta initially failed it's analysis. The sample was recounted with results within control limits.

Radiological Environmental Monitoring Page 34 L

ANNUAL ENVIRONMlENTAL AND EFFLUENT RELEASE REPORT

5) MAPEP Program Table A-6: One (1) soil sample (STSO-1063) and one (1) air sample (STAP-1049) where found to be outside the expected control limits. Sample STSO-1063, Am-241 analysis was initially calculated using the incorrect sample weight. The soil sample was recalculated with the correct sample weight to achieve results within the control limits. Sample STAP-1049, Sr-90 analysis initially failed. The strontium carbonate precipitates were re-dissolved and processed. The average of the three analyses was within the control limits. The analysis result of a new prepared sample was also found within the control limits.

LAND USE CENSUS In troduction 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 2005 Land Use Census, which was conducted July 22nd, 25h and 26hl provided the garden, residence and milk animal locations tabulated in Tables 18, 19 and 20 and depicted in Figure 9. Note that the W, WNW, NNW, NWNI, 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 ruralagricultural. 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 2005 Land Use Survey used the 1999 survey map produced by the Commercial Survey Co. of Cleveland. GPS units are 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 2005, there is one (1) change noted for the "nearest residence" in the ESE sector.

Table 18: Nearest Residence, By Sector LOCATION vMILES FROM XlQ VALUE, MlAPLOCATOR SECTOR ADDRESS PNPP sec/m3 NUMBER NE 4384 Lockwood 0.7 2.66E-06 1

ENE 4412 Lockwood 0.7 1.96E-06 2

E 2626 Antioch 1.1 6.77E-07 3

ESE 2836 Antioch 1.0 8.57E-07 4

SE 4537 North Ridge 1.3 3.44E-07 5

SSE 4247 Redmill Valley Rd.

1.1 5.52E-06 6

S 3119 Parnly 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

m

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!Iq 07 Figure 9: Land Use Census Map Coc(

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 19 identifies the nearest milking animal by sector, to the PNPP. During the 2005 Land Use Census, two (2) changes were identified regarding the nearest milk animal. These changes include the loss of one location previously identified in the S sector and the addition of a new milk location identified in the same sector during this year's census. The owner has indicated that he will joi:n the REMP program at the start of the 2006 milking season.

Table 19: Nearest Milk Animal, By Sector LOCATION MILES FROM MIAP LOCATOR SECTOR ADDRESS PdNdP NUMBER I

ESE 6401 Middle Ridge Rd.

4.4 21 S

5245 Blair Rd.

4.9 22 There were four (4) changes in the nearest gardens during this year's census. These changes in-lude 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 tOe 2005 Land Use Census.

Table 20: Nearest Garden, By Sector LOCATION MILES FROM D/Q VALUE, IAP LOCATOR SECTOR ADDRESS PNLPP rn.2 uNIBER 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 Antoch 1.0 3.96E-09 4

SE 3391 Townline 2.4 1.01E-09 [

15 SSE l 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 i 3440 Clark 1.3 1.95E-09 9

WSW l 2975 Perry Park 1.3 2.31E-09 [

20 Radiological Environmental Monitoring Page 37

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CLAM/MUSSEL MONITORING I.

INTRODUCTION L

Sampling for benthic 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:

L Corbiculaflunminea (Asiatic clam) and Dreissena pol'lmorpla (zebra mussel).

CORBICULA PROGRAM Monitoring specifically for Corbicula was initiated in response to a NRC bulletin and concerns of the L

Atomic Safety and Licensing Board. The 2005 monitoring 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 ever 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, 4

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 2005, samples were collected from the Service Water (SW), Emergency Service Water (ES W),

Fire Water, and Circulating Xlater (CW) systems at PNPP and examined for asiatic clam shells and L

fragments. All samples were either collected by Ponar hand dredge, 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: 2005 Corbicula Monitoring DATE SAMPLE LOCATION

[ DATE I SAMPLE LOCATION 1/20/05 Fire Protection Piping, 1P54 F101 8/14/05 Lube oil 1N34B0001B 2/28/05 Water box and LP condenser 8/22/05 Service Water OP41 D0001 B 3/1/05 Emergency Closed Cooling 1 P42 B0001A 8/22/05 Service Water OP41 D0001 D 3/2/05 Emergency Service Water Pump, 1 P45C0001 A 8/24/05 Service Water OP41 D0001 C 3/3/05 Emergency Service Water piping/strainer 8/18/05 Service Water OP41 DOD01 A 3/2/05 Water box and IP condenser 9/19/05 Fire Protection Piping, 1 P54 3/2/05 Water box and HP condenser 8/24/05 Service Water OP41 A0001 C 3/16/05 Residual Heat removal 1 E1 2B0001 C 10/13/05 D HP Water box 6/21/05 Circ Water 1 N71 F0609B 10/19/05 Makeup Pretreatment OP20-NO10 6/21/05 Circ Water 1N71F0609A 7/14/05 Lube oil 1 N34B0001 B L

L L

.L 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 2005 monitoring program did not identify Corbicula in any sample collected.

Clam/Mussel Monitoring Page 38

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT DIreissena 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.

Mlonitoring In addition to visually inspecting the plant's raw water systems when they are opened for mnaintenance or repair, monitoring methods include the use of commercial divers, side-stream rrmonitors, and plankton nets. Commercial divers monitor mussel infestation during the inspect.on 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 Iccations during the mussel season. The side-stream monitors are fitted with slides and inspected for veliger settlement.

Treatment Chemicals used for mussel control in 2005 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 2005 was alkyl-dimethyl-benzyl-ammonium chloride. One treatment was applied on September 8 th, 2005. 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 when systems are open during maintenance or repair. In addition, settlement monitors were inspected for new settlement.

No live settlement has been found in any plant component to date.

The effectiveness of the application of the commercial molluscicide wvas measured by observing xrortality of mussels placed in a flow-through container placed in plant service water and subjected to the chemical treatment. The observed mortality rate in the flow-through container was 99%. 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

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 2005 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 2005. The quantity represents the amount of herbicide applied, after any dilution.

Table 22: 2005 Herbicide Applications APPLICATION LOCATION AMOUNT CHEMICAL DATE (GAL)

NAME 5/9/05 Unit e1 Park and Garden area

.08 Round-up 5/11/05 Transmission yard 120 lbs Krovar 5/11/05 Transmission yard

.70 Oust 5/11/05 Transmission yard 7.5 Razor 5/11/05 Transmission yard 4

2.4D Amine 5/31/05 Protected Area (NE, NW. SE. SW) quadrants. Park area 1.17 Round-up 5/31/05 Admin, Training, WHSE, IPC, P&R Bldg's. & Roadway 3.52 Round-up 6/6/05 Protected Area (NE, NWV, SE, SW) quadrants, Park area 1.17 Round-up 6/6/05 Admin, Training, WHSE, IPC, P&R Bldg's. & Roadway, Contractor Parking lots (West & South) 1.17 Round-up 6n/05 Protected Area (NE, NV. SE. SW) quadrants 3.52 Round-up 6/15/05 Protected Area perimeter & quadrants (NE, NW, SE, SW) 1.17 Round-up 6/15/05 Admnin. Trainine. WVHSE, IPC. P&R B1de's.

1.17 Round-up 6/25/05 Protected Area Perimeter 20 Round-up 6/27/05 Admin and Training Bldg.. Roadway

.44 Round-up 6/28/05 Admin Bldg.

2.34 Round-up 7/1 3/05 Waste Accumulation Facilitv 3.52 Round-up 7/21/05 Transmission yard 120 lbs Krovar 7/21/05 Transmission vard

.70 Oust A.-

ik.

l L

Herbicide Usage Page 40 L

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 22 continued: 2005 Herbicide Applications APPLICATION LOCATION AMOUNT CIEMIICAL DATE (GAL)

NAME 7/21/05 Transmission yard 7.5 Razor 7/21/05 Transmission yard 4

2.41) Amine 7/25/05 Protected Area perimeter & quadrants (NE, NWV. SE SW) 2.34 Rc-und-up 7/25/05 Admin. Training, WHSE, IPC. P&R Bldg's. & Roadway 18.75 Rcund-up 7/26/05 Protected Area perimeter & quadrants (NE. NW, SE, SW) 4.69 Rcund-up 8117/05 Transmission yard 1.17 Rcund-up 9/6/05 Admin, Training. WHSE, IPC. P&R Bldg's. & Roadway 1.17 Rcund-up 9/19/05 Protected Area perimeter & quadrants (NE NW. SE, SV) 3.52 Rcund-up 9/22/05 Admin, Training, VHSE, IPC, P&R Bldg's. & Roadw ay Contractor Parking lots 3.52 Rcund-up (West & South) 9/28/05 Protected Area (NE, NV, SE. SW) quadrants 4.69 Rcund-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 PNTPP. It also specifies the locations from which the plant is allowed to discharge.

There were no NPDES non-compliance issues identified in 2005.

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 2005.

UNREVIEWVED EN-vIRONMENTAL 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 2005 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.

OHIO DEPARTMENT OF NATURAL RESOURCES SURVEY On February 21, 2003, the Ohio Department of Natural Resources (ODNR), Division of Wildlife contacted Perry requesting permission to access areas where Spotted Turtles had been previously documented. Perry granted the ODNR representative access, and the environmental staff participated in the surveys of the area.

The summer 2003 survey did not result in the capture of any Spotted Turtles in the previously recorded area. The wet prairies and meadows along the powerline right-of-way have been overrun by Phragmnites sp. reducing their suitability as Spotted Turtle habitat. (It is believed that this native plant has been hybridized with European Phragmites sp., causing it to become more aggressive in many areas.) However, the discovery of an open canopy fen late in 2003 has renewed hopes that the Spotted Turtle may still be found on the property. This fen has yet to be substantially impacted by Phraginites sp. Other species observed during the 2003 survey included the Common Snapping Turtle (Chelydra serpentina serpentina), the Spotted Salamander (Ambystomna mnaculatum), Red-backed Salamander (Plethodon cinereus), and Western Chorus Frog (Pseudacris triseriata triseiiata). Although scheduled for completion in 2005, the ODNR representative did not return as planned to monitor this new habitat and complete the survey.

Special Reports Page 42

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX A, 2005 INTER-LABORATORY CROSS CHECK COMPARISON PROGRAM RESULTS Appendix A Page 43

a-Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

Northbrook, IL 60062-2310 ph. (847) 564-0700

fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:

Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2005 through December, 2005

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

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

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

4 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 results of the analyses on in-house 'spiked" samples for the past twelve months. All samples a

are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house 'blank" samples for the past twelve months. Data for L

previous years available upon request.

Table A-5 list results 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.

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

Attachment A lists acceptance criteria for 'spiked' samples.

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

Al

Attachment A ACCEPTANCE CRITERIA FOR 'SPIKED' SAMPLES l ABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSEB3 One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

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

> 50 pCi/liter or kg 10% of known value Strontium_90b 2 to 30 pCi/liter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potassium-40 2 0.1 g/Iiter or kg 5% of known value Gross alpha s 20 pCi/liter 5.0 pCi/liter

> 20 pCi/liter 25% of known value Gross beta 5 100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium 5 4,000 pCi/liter i1 a = (pCiAiter) =

169.85 x (known)00 933

> 4,000 pCi/liter 10% of known value Radium-226,-228 2 0.1 pCi/liter 15% of known value Plutonium 2 0.1 pCiAiter, gram, or sample 10% of known value Iodine-1 31, 5 55 pCi/liter 6.0 pCi/liter lodine:-129b

> 55 pCi/liter 10% of known value Uranium-238, 5 35 pCi/liter 6.0 pCi/liter Nickel-63b

> 35 pCi/liter 15% of known value Technetium-99b lron-55t' 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-1 051 STW-1051 STW-1052 STW-1052 STW-1 052 STW-1 052 STW-1 052 STW-1 053 STW-1 053 STW-1054 STW-1054 STW-1054 STW-1055 STW-1055 STW-1 056 STW-1056 STW-1056 STW-1 056 STW-1 056 STW-1057 STW-1 057 STW-1058 STW-1059 STW-1 059 STW-1 059 STW-1060 STW-1067 STW-1 067 STW-1068 STW-1068 STW-1 068 STW-1 068 STW-1 068 STW-1069 STW-1069 STW-1070 STW-1 070 STW-1070 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 05/17/05 05/17/05 05/17/05 05/17/05 05117/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 Sr-89 Sr-90 Ba-133 Co-60 Cs-1 34 Cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-1 33 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Sr-89 Sr-90 Ba-I33 Co-60 Cs-134 Cs-i 37 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium 28.0 +/- 1.2 25.1 i 0.7 52.9 +/- 2.8 54.4 +/- 0.4 67.7 +/- 1.8 39.6 +/- 1.8 159.7 +/- 3.0 55.1 +/- 1.8 46.8 +/- 1.3 13.7 +/- 1.5 13.3 +/- 0.6 5.1.+/- 0.2 45.1 +/-4.1 7.5 +/- 0.9 87.1 +/-2.0 38.4 +/- 0.8 75.3 +/- 0.7 201.0 +/- 8.4 130.0 +/- 6.7 42.7 +/- 2.9 34.0 +/- 0.4 14.7 +/- 0.5 6.6 i 0.1 19.3 +/- 0.7 9.6 +/- 0.1 24100.0 +/- 109.0 29.1 +/- 3.0 36.0 +/- 0.6 107.0 +/- 1.7 15.2 +/- 0.2 89.1 +/- 0.3 72.1 +/- 1.0 67.4 +/- 1.4 44.3 +/- 1.5 58.4 +/-2.1 16.6 +/- 1.5 6.2 +/- 0.3 4.5 +/- 0.1 29.4 24.4 53.4 56.6 64.9 40.2 161.0 67.9 51.1 14.1 13.7 5.0 41.3 5.9 88.4 37.0 78.6 194.0 118.0 37.0 34.2 15.5 7.6 18.9 10.1 24400.0 28.0 33.8 106.0 13.5 92.1 72.7 65.7 55.7 61.3 16.6 6.2 4.5 20.7 - 38.1 15.7 - 33.1 44.2 - 62.6 47.9 - 65.3 56.2 - 73.6 31.5 - 48.9 133.0 - 189.0 38.5 - 97.3 38.5 - 97.3 10.4 -17.8 7.8 - 19.6 0.0 - 10.2 32.6 - 50.0 0.0 - 14.6 73.1 - 104.0 28.3 - 45.7 69.9 - 87.3 184.0 - 218.0 97.6 - 138.0 21.0 - 53.0 25.5 - 42.9 10.3 - 20.7 5.6 - 9.5 10.7 - 27.1 4.9 - 15.3 20200.0 - 28600.0 19.3 - 36.7 25.1 - 42.5 87.7 - 124.0 4.8 - 22.2 83.4 - 101.0 64.0 - 81.4 54.3 - 77.1 31.6 - 79.8 44.0 - 78.6 12.3 - 20.9 3.5 - 8.9 0.0 - 9.7 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass L..

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass L

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

! i L

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

Al-1 L

Lab Code Date Analysis Concentration (pCi/L)

Laboratory ERA Resultb Resultc Control Limits Acceptance STW-1 072 STW-1 072 STW-1 073 STW-1 073 STW-1 (173 STW-1 (173 STW-1 (173 STW-1 (174 a STW-1 (174 STW-1 (C75 STW-1 076 STW-1 (176 e STW-1 (176 STW-1 077 11/15/05 11/15/05 11/15/05 11/15105 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15105 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 20.6 +/- 0.4 15.0 +/- 0.3 31.8 +/- 1.8 85.0 +/- 1.4 37.2 +/- 2.1 27.8 +/- 0.7 109.0 +/- 1.0 41.1 +/- 1.2 42.7 +/- 0.5 20.5 +/- 0.6 7.8 +/- 0.6 5.5 +/- 0.6 15.5 +/- 0.3 12500.0 +/- 238.0 19.0 16.0 31.2 84.1 33.9 28.3 105.0 23.3 39.1 17.4 8.3 3.5 16.1 12200.0 10.3 - 27.7 7.3 - 24.7 22.5 - 39.9 75.4 - 92.8 25.2 - 42.6 19.6 - 37.0 86.8 - 123.0 13.2 - 33.4 30.4 - 47.8 12.2 - 22.6 6.2 - 10.5 2.0 - 5.0 10.9 - 21.3 10100.0 - 14300.0 Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Fail Pass Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing In drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the mean i 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.

dThe original samples were calculated using an Am-241 efficiency. The samples were spiked with Th-232. Samples were recounted and calculated using the Th-232 efficiency. Results of the recount: 27.01 +/- 2.35 pCi/L.

e Decay cf short-lived radium daughters contributed to a higher counting rate. Delay of counting for 100 minutes provided better result Ths reported result was the average of the first cycle of 100 minutes, the average of the second cycle counts was 4.01 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.

2005-1 2005-1 2005-1 2005-1 2005-1 2005-1 2005-1 2005-1 2005-1 414/2005 4/4/2005 4/4/2005 4/4/2005 4/4/2005 4/4/2005 4/4/2005 4/4/2005 4/4/2005 30 cm 60 cm 60 cm 90 cm 90 cm 120 cm 120 cm 150 cm 180 cm 55.01 13.75 13.75 6.11 6.11 3.44 3.44 2.2 1.53 64.02 +/- 2.86 15.43 +/- 1.02 14.98 +/- 0.80 6.24 +/- 0.16 5.45 +/- 0.48 3.50 +/- 0.35 3.15 +/- 0.18 2.31 +/- 0.25 1.65 +/- 0.41 38.51 - 71.51 9.63 - 17.88 9.63 - 17.88 4.28 - 7.94 4.28 - 7.94 2.41 - 4.47 2.41 - 4.47 1.54 - 2.86 1.07 -1.99 Pass Pass Pass Pass Pass Pass Pass Pass Pass 4-Environmental, Inc.

2005-2 2005-2 2005-2 2005-2 2005-2 2005-2 2005-2 2005-2 2005-2 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 30 cm 60 cm 75 cm 90 cm 90 cm 120 cm 150 cm 150 cm 180 cm 54.84 13.71 8.77 6.09 6.09 3.43 2.19 2.19 1.52 59.30 +/- 2.66 17.55 +/- 1.30 8.24 +/- 0.38 5.94 +/- 0.49 5.93 +/- 0.37 3.42 +/- 0.18 1.71 +/- 0.14 1.87 +/- 0.27 1.58 +/- 0.99 38.39 - 71.29 9.60 - 17.82 6.14 - 11.40 4.26 - 7.92 4.26 - 7.92 2.40 - 4.46 1.53 - 2.85 1.53 -2.85 1.06 - 1.98 Pass Pass Pass Pass Pass Pass Pass Pass Pass L

Li Xy I.

4 A2-1 L

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 Limitsd Acceptance W-11105 W-111c05 SPW-7134 SPAP-766 STW-2887 W-301 05 W-301 05 SPW-11336 SPW-11336 SPMI-1 B38 SPMI-1 B38 SPMI-i B38 SPMI-1 B38 SPMI-1 638 SPMI-1 B38 SPVE-1932 SPCH-, 935 SPAP-1966 SPAP-1 966 SPAP-1966 S PAP-1968 SPAP-1968 SPW-2098 SPW-2922 SPW-2922 SPW-2922 SPW-2922 SPAP-2892 SPW-2895 w-601 05 w-601 05 SPF-3039 SPF-30;39 SPW-SPW-47731 SPW-47,732 SPW-4775 SPMI-41334 SPMI-4834 SPMI-4834 SPMI-4834 1/11/2005 1/11/2005 2/18/2005 2/18/2005 2/28/2005 3/1/2005 3/1/2005 4/1512005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4115/2005 4/18/2005 4/18/2005 4/18/2005 4/18/2005 4/18/2005 4/18/2005 4118/2005 4/26/2005 5/31/2005 5/31/2005 5/31/2005 5/31/2005 6/1/2005 6/1/2005 6/1/2005 6/1/2005 6/7/2005 6/7/2005 7/1/2005 8/24/2005 8/24/2005 8/24/2005 8/30/2005 8/3012005 8/30/2005 8/30/2005 Gr. Alpha Gr. Beta H-3 Gr. Beta Tc-99 Gr. Alpha Gr. Beta 1-131 1-131 (G)

Cs-1 34 Cs-137 1-131 1-131(G)

Sr-89 Sr-90 1-131 (G) 1-131 Cs-134 Cs-1 34 Cs-1 37 Cs-134 Cs-137 Fe-55 Cs-134 Cs-1 34 Sr-89 Sr-90 Gr. Beta H-3 Gr. Alpha Gr. Beta Cs-134 Cs-1 37 Ni-63 C-1 4 C-14 Fe-55 Cs-134 Cs-137 Sr-89 Sr-90 24.05 +/- 1.01 61.59 +/- 1.11 77595.00 +/- 764.00 416.08 +/- 5.52 32.91 +/- 1.23 25.22 +/- 0.45 62.27 +/- 0.48 109.79 +/- 0.94 110.25 +/- 9.68 25.94 +/- 1.28 59.31 +/- 3.66 97.71 +/- 0.81 109.45 +/- 3.06 104.44 +/- 2.89 8.97 +/- 0.79 1.00 +/- 0.04 382.40 +/- 14.95 52.10 +/- 7.27 57.28 +/- 13.47 124.68 +/- 18.41 52.10 +/- 7.27 116.79 +/- 14.00 2565.20 +/- 63.66 27.01 +/- 1.09 65.38 +/- 2.92 107.90 +/- 3.60 11.11 +/- 1.13 420.32 +/- 5.55 75271.00 +/- 724.00 23.69 +/- 0.52 60.08 +/- 0.57 1.08 +/- 0.05 2.54 +/- 0.10 20.57 +/- 1.10 2112.30 +/- 9.13 2294.10 +/- 10.37 2633.50 +/- 62.40 49.27 +/- 4.68 58.17 +/- 8.18 66.39 +/- 3.13 11.15 +/- 1.13 20.08 65.70 80543.00 463.00 32.98 20.08 65.73 106.30 106.30 26.60 60.90 106.30 106.30 108.20 7.53 0.73 328.64 53.35 53.35 121.77 53.35 121.77 3017.60 25.54 60.71 113.90 6.90 448.00 78676.00 20.08 65.73 1.02 2.43 16.75 2370.80 2370.80 2777.50 47.02 60.37 65.90 9.60 10.04 - 30.12 55.70 - 75.70 64434.40 - 96651.60 370.40 - 509.30 20.98 - 44.98 10.04 - 30.12 55.73 - 75.73 85.04 - 127.56 95.67 - 116.93 16.60 - 36.60 50.90 - 70.90 85.04 - 127.56 95.67 - 116.93 86.56 - 129.84 0.00 - 17.53 0.44 -1.02 262.91 - 394.37 43.35 - 63.35 43.35 - 63.35 109.59 - 133.95 43.35 - 63.35 109.59 - 133.95 2414.08 - 3621.12 15.54 - 35.54 50.71 - 70.71 91.12 - 136.68 0.00 - 16.90 358.40 - 492.80 62940.80 - 94411.20 10.04 - 30.12 55.73 - 75.73 0.61 - 1.43 1.46 - 3.40 10.05 - 23.45 1422.48 - 3319.12 1422.48 - 3319.12 2222.00 - 3333.00 37.02 - 57.02 50.37 - 70.37 52.72 - 79.08 0.00 - 19.60 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A3-1

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

Lab Code Date Analysis Laboratory results Known Control 2s, n=1b Activity Limitsc Acceptance SPW-4836 8130/2005 Cs-134 47.35 +/- 5.19 47.02 37.02 - 57.02 Pass SPW-4836 8/30/2005 Cs-1 37 62.91 +/- 9.08 60.37 50.37 -70.37 Pass SPW-4836 8/30/2005 Sr-89 11.04 +/- 0.98 9.60 0.00 - 19.60 Pass SPW-4836 8/30/2005 Sr-90 65.89 +/- 2.79 65.90 52.72 - 79.08 Pass SPW-5014 8/30/2005 H-3 77518.20 +/- 753.80 77602.52 62082.02 -93123.02 Pass W-90705 9/7/2005 Gr. Alpha 24.61 +/- 0.48 20.08 10.04 -30.12 Pass W-90705 9/7/2005 Gr. Beta 58.35 +/- 0.49 65.73 55.73 - 75.73 Pass SPW-5237 9/22/2005 C-14 2387.40 +/- 11.00 2370.80 1422.48 -3319.12 Pass SPW-5508 9/26/2005 Ni-63 20.64 +/- 1.23 16.70 10.02 - 23.38 Pass SPW-6019 10/24/2005 Tc-99 547.99 +/- 6.69 539.22 377.45 -700.99 Pass SPF-6293 11/4/2005 Cs-I 34 941.30 +/- 44.10 886.00 797.40 - 974.60 Pass SPF-6293 11/4/2005 Cs-137 2570.40 +/- 105.30 2400.00 2160.00 -2640.00 Pass SPAP-6309 11/7/2005 Cs-134 41.24 +/- 1.91 44.03 34.03 -54.03 Pass SPAP-6309 11/7/2005 Cs-137 114.03 +/- 5.01 120.24 108.22 - 132.26 Pass SPAP-6311 11/7/2005 Gr. Beta 1.58 +/- 0.02 1.42 1.14 -11.42 Pass SPW-6451 11/10/2005 H-3 77126.00 +/-747.00 76749.00 61399.20 -92098.80 Pass W-120105 12/1/2005 Gr. Alpha 25.16 +/- 0.45 20.08 10.04 -30.12 Pass W-120105 12/1/2005 Gr. Beta 74.58 +/- 0.81 65.73 55.73 -75.73 Pass SPW-7440 12/30/2005 Cs-1 34 42.67 +/- 4.22 42.03 32.03 -52.03 Pass SPW-7440 121/30/2005 Cs-137 61.19 +/- 7.20 59.91 49.91 -69.91 Pass SPMI-7442 12/31/2005 Cs-1 34 40.41 +/- 5.66 42.03 32.03 -52.03 Pass SPMI-7442 12/31/2005 Cs-1 37 60.05 +/- 7.80 59.91 49.91 -69.91 Pass Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/rn3), and solid samples (pCi/g).

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

CH (charcoal canister), F (fish).

c Results are based on single determinations.

c 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 L

L L

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

Acceptance Type LLD Activityb Criteria (4.66 a)

W-11105 W-1i1t15 SPW-7-35 SPAP-766 STW-21388 W-301 05 W-301 C'5 SPW-11337 SPW-1 1337 SPW-11337 SPW-1 1337 SPMI-1839 SPMI-1839 SPMI-1839 SPCH-1 934 SPW-2097 SPW-2'323 SPW-2923 SPW-21396 w-60105 w-60105 SPF-3090 SPF-3090 SPW-SPW-4;74 SPW-4776 SPMI-4335 SPMI4335 SPMI-4;335 SPMI-41335 SPMI-4335 SPMI-41335 SPW-4E37 SPW-4E37 SPW-4E37 SPW-4E;37 SPW-4E37 SPW-5C'15 SPW-5238 water water water Air Filter water water water water water water water Milk Milk Milk Charcoal water water water water water water Fish Fish water water water Milk Milk Milk Milk Milk Milk water water water water water water water 1/11/2005 1/11/2005 2/18/2005 2/18/2005 2/28/2005 3/11/2005 3/1/2005 4/15/2005 4/15/2005 4/15/2005 4115/2005 4/15/2005 4/15/2005 4/15/2005 4/18/2005 4/26/2005 5/31/2005 5/31/2005 6/1/2005 6/1/2005 6/1/2005 6/7/2005 6/7/2005 7/1/2005 8/24/2005 8/24/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 9/22/2005 Gr. Alpha Gr. Beta H-3 Gr. Beta Tc-99 Gr. Alpha Gr. Beta Cs-I 34 Cs-I 37 1-131 1-131 (G) 1-131 Sr-89 Sr-90 1-131 (G)

Fe-55 Cs-I 34 Cs-137 H-3 Gr. Alpha Gr. Beta Cs-1 34 Cs-i 37 Ni-63 C-14 Fe-55 Co-60 Cs-134 Cs-1 37 1-1 31(G)

Sr-89 Sr-90 Co-60 Cs-1 34 Cs-1 37 Sr-89 Sr-90 H-3 C-1 4 0.055 0.15 165.8 0.72 1.32 0.067 0.18 4.66 5.38 0.30 6.56 0.26 0.54 0.53 2.34 859.0 3.29 3.87 138.30 0.061 0.16 15.69 11.71 1.60 12.18 833 4.42 4.18 6.25 5.37 0.66 0.66 2.48 3.85 3.00 0.63 0.63 142.8 17.10 0.00 + 0.038

-0.016 +/- 0.10 7.4 i 82.5 0.29 t 0.48 0.45 +/- 0.81

-0.007 + 0.043

-0.04 +/-0.11

-0.13 +/- 0.16

-0.083 +/- 0.14

-0.069 +/- 0.56 0.88 +/- 0.34 96.1 +/- 528.4 48.1 +/- 85.9 0.002 +/- 0.043 0.056 +/- 0.11 0.79 +/- 0.99 2.84 +/- 6.45 275 +/- 525

-0.23 +/- 0.65 1.02 +/- 0.41 0.25 +/- 0.53

-0.035 +/- 0.29 168 +/- 93 3.02 +/- 9.04 1

3.2 200 3.2 10 1

3.2 10 10 0.5 20 0.5 5

1 9.6 1 000 10 10 200 1

3.2 100 100 20 200 1000 10 10 10 20 5

1 10 10 10 5

1 200 200 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/fL)

Lab Code Sample Date Analysis Laboratory results (4.66a)

Acceptance Type LLD Activityb Criteria (4.66 a)

W-90705 water 91712005 Gr. Alpha 0.056 0.034 +/- 0.04 1

W-90705 water 9/7/2005 Gr. Beta 0.16 0.082 +/- 0.11 3.2 SPW-5238 water 9/22/2005 C-14 17.10 3.02 +/- 9.04 200 SPW-5509 water 912612005 Ni-63 1.25 1.23 +/- 0.79 20 SPW-6020 water 10/24/2005 Tc-99 4.81

-1.75 +/- 2.90 10 SPF-6294 Fish 11/4/2005 Cs-134 18.60 100 SPF-6294 Fish 11/4/2005 Cs-137 12.99 100 SPAP-6310 AirFilter 11/7/2005 Cs-134 3.23 100 SPAP-6310 Air Filter 11/7/2005 Cs-1 37 3.86 100 SPAP-6312 Air Filter 11/7/2005 Gr. Beta 1.22

-0.64 +/- 0.64 3.2 W-120105 water 12/1/2005 Gr. Alpha 0.05 0.033 +/- 0.04 1

W-120105 water 12/1/2005 Gr. Beta 0.15

-0.043 +/- 0.11 3.2 SPMI-7419 Milk 12/22/2005 Co-60 7.24 10 SPMI-7419 Milk 12/22/2005 Cs-137 5.61 10 SPMI-7419 Milk 12/22/2005 1-131(G) 10.96 20 SPW-7421 water 12/22/2005 Co-60 2.43 10 SPW-7421 water 12/22/2005 Cs-137 3.12 10 SPW-7441 water 12/30/2005 Cs-134 4.25 10 SPW-7441 water 12/30/2005 Cs-137 1.63 10 SPMI-7443 Milk 12/30/2005 Cs-134 4.74 10 SPMI-7443 Milk 12/30/2005 Cs-137 8.53 10

'-4 L

L L

I.e L

8 Liquid sample results are reported In pCi/Uter, air filters( pCi/filter), charcoal (pCicharcoal canister), and solid samples (pCi/g).

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

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

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 L

L

TABLE A-5. In-House "Duplicate' Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SW-62, 63 SW-62, 63 CF-95, 96 CF-95, 96 AP-791, 792 WW-353, 354 SO-383, 384 LW-431, 43:2 MI-486, 487 SW-511, 512 TD-628, 629 DW-538, 539 MI-564, 565 DW-50134, 5 SWU-893, 894 SW-925, 925 SW-950, 951 SW-950, 951 SW-973, 974 DW-50248, 9 DW-1264, 1265 AP-1955, 1956 AP-1890, 1891 AP-2025, 2CI26 MI-1 346, 1347 AP-2048, 2049 AP-2081, 2(182 SWU-1521, 1522 WW-1 738, 1739 SW-1857, 1358 LW-1911, 1912 F-1976, 1977 Ml-2111, 2112 SWU-2158, 2159 DW-2349, 2;350 SO-2305, 2306 SO-2305, 2106 SO-2305, 2306 SO-2305, 2306 S0-2305, 21306 MI-2260, 2261 F-2630, 2631 VE-2502, 2503 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/14/2005 1/19/2005 1/19/2005 1/27/2005 2/1/2005 2/1/2005 2/1/2005 2/3/2005 2/8/2005 2/11/2005 2/22/2005 2/25/2005 3/1/2005 3/1/2005 3/1/2005 3/16/2005 3/19/2005 3/28/2005 3/29/2005 3/29/2005 3/30/2005 3/30/2005 3/30/2005 3/31/2005 4/5/2005 4/13/2005 4/14/2005 4/18/2005 4/26/2005 4/26/2005 4/29/2005 5/2/2005 5/2/2005 5/2/2005 5/2/2005 5/2/2005 5/3/2005 5/5/2005 5/10/2005 Gr. Beta K-40 Gr. Beta K-40 Be-7 Gr. Beta H-3 Gr. Beta K-40 1-131 H-3 Gr. Beta K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Beta Gr. Beta 1-131 Gr. Alpha 1-131 Be-7 Be-7 Be-7 K-40 Be-7 Be-7 Gr. Beta Gr. Beta Gr. Beta Gr. Beta K-40 K-40 Gr. Beta 1-131 Cs-1 37 Gr. Alpha Gr. Beta K-40 Sr-90 K-40 K-40 Gr. Alpha 3.01 +/- 0.57 2.00 +/- 0.20 6.26 +/- 0.23 5.68 +/- 0.59 0.057 +/- 0.017 8.37 +/- 1.21 453.50 +/- 107.20 2.45 +/- 0.54 1319.40 +/- 163.60 0.37 +/- 0.22 489663 +/- 1918 3.93 +/- 1.18 1316.20 +/- 171.10 18.41 +/- 0.98 4.00 +/- 0.96 5.97 +/- 1.51 0.92 +/- 0.27 2.06 +/- 0.40 1.08 +/- 0.19 5.27 +/- 1.06 0.54 +/- 0.21 0.071 +/- 0.009 0.060 +/- 0.013 0.063 +/- 0.012 1252.80 +/- 120.50 0.075 +/- 0.018 0.073 +/- 0.016 2.83 +/- 1.16 11.44 +/- 1.17 7.04 +/- 1.71 2.50 +/- 0.63 3.09 +/- 0.60 1291.50 +/- 177.90 3.69 +/- 0.74 0.58 +/- 0.27 0.11 +/-0.05 7.55 +/- 2.88 28.74 +/- 2.57 21.51 +/- 1.22 32.90 +/- 9.90 1028.10 +/- 99.36 3.08 +/- 0.46 0.06 +/- 0.03 2.39 +/- 0.58 2.10 +/- 0.20 6.28 +/- 0.23 5.37 +/- 0.48 0.07 +/- 0.04 10.28 +/- 1.34 417.90 +/- 106.00 2.20 +/- 0.54 1177.20 +/- 179.70 0.44 +/- 0.23 491225 +/- 1915 3.62 +/- 1.10 1292.60 +/- 154.40 16.76 +/- 0.98 4.20 +/- 0.72 6.14 +/- 1.55 1.21 +/- 0.27 2.29 +/- 0.44 0.92 +/- 0.18 4.17 +/- 0.90 0.73 +/- 0.20 0.071 +/- 0.009 0.069 +/- 0.013 0.071 +/-0.011 1334.10 +/- 106.60 0.071 +/- 0.015 0.061 +/- 0.018 3.46 +/- 1.23 11.14 +/- 1.62 9.96 +/- 1.65 3.23 +/- 0.67 3.33 +/- 0.40 1323.70 +/- 108.80 3.54 +/- 0.66 0.49 +/- 0.27 0.11 +/- 0.04 12.41 +/- 3.38 28.17 +/- 2.52 2i.42 +/- 1.24 29.60 +/- 13.90 1206.70 +/- 118.50 3.04 +/- 0.51 0.07 +/- 0.04 2.70 2.05 6.27 5.53 0.06 9.32

+/- 0.41

+/- 0.14

+/- 0.16

+/- 0.38

+/- 0.02

+/- 0.90 435.70 +/- 75.38 2.33 +/- 0.38 1248.30 +/- 121.51 0.40 +/- 0.16 490444 +/- 1355 3.78 +/- 0.81 1304.40 +/- 115.23 17.59 +/- 0.69 4.10 +/- 0.60 6.06 +/- 1.08 1.07 +/- 0.19 2.18 +/- 0.30 1.00 +/-0.13 4.72 +/- 0.70 0.63 +/- 0.15 0.071 +/- 0.006 0.065 +/- 0.009 0.067 +/- 0.008 1293.45 +/- 80.44 0.073 +/- 0.012 0.067 +/- 0.012 3.14 +/- 0.85 11.29 +/- 1.00 8.50 +/- 1.19 2.86 +/- 0.46 3.21 +/- 0.36 1307.60 +/- 104.27 3.62 +/- 0.50 0.53 +/- 0.19 0.11 +/- 0.03 9.98 +/- 2.22 28.46 +/- 1.80 21.47 +/- 0.87 31.25 +/- 8.53 1117.40 +/- 77.32 3.06 +/- 0.34 0.07 +/- 0.03 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L) 2 A5-1

Averaged Result Lab Code Date Analysis First Result Second Result Acceptance VE-2502, 2503 VE-2502, 2503 G-2546,2547 G-2546, 2547 SS-2787, 2788 SS-2787, 2788 S0-3056, 3057 S0-3056, 3057 SS-3175, 3176 S0-2865, 2866 S0-2865, 2866 S0-2865, 2866 DW-2935, 2936 SWU-3103, 3104 G-2958, 2959 G-2958, 2959 D G-2958, 2959 BS-4089, 4090 BS-4089, 4090 DW-50527, 8 VE-3278, 3279 MI-3299, 3300 BS-3348, 3349 BS-3348, 3349 BS-3348, 3349 DW-3486, 3487 SWT-3631, 3632 W-3507, 3508 VE-3555, 3556 VE-3555, 3556 AP-3781, 3782 LW-3610, 3611 SW-3760, 3761 E-3654, 3655 E-3654, 3655 Mi-3676, 3677 DW-3739, 3740 W-3808, 3809 DW-3938, 3939 VE-3896, 3897 MI-3963, 3964 DW-4068, 4069 5/10/2005 5/10/2005 5/11/2005 5/11/2005 5/18/2005 5/18/2005 5/19/2005 5/19/2005 5/23/2005 5/25/2005 5/25/2005 5/25/2005 5/27/2005 6/1/2005 6/1/2005 6/1/2005 6/1/2005 6/3/2005 6/3/2005 6/8/2005 6/13/2005 6/15/2005 6/17/2005 6/17/2005 6/17/2005 6/28/2005 6/2812005 6/29/2005 6/29/2005 6/29/2005 6/29/2005 6/30/2005 6/30/2005 7/5/2005 7/5/2005 7/5/2005 7/5/2005 7/6/2005 7/8/2005 7112/2005 7/13/2005 7/15/2005 Gr. Beta K-40 Be-7 K-40 Cs-1 37 K-40 Cs-137 K-40 K-40 Cs-137 Gr. Beta K-40 1-131 Gr. Beta Be-7 Gr. Beta K-40 Co-60 Cs-1 37 Gr. Alpha K-40 K-40 Co-60 Cs-137 K-40 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 Be-7 Gr. Beta Gr. Beta Gr. Beta K-40 K-40 1-131 H-3 1-131 K-40 K-40 1-131 3.81 +/-0.10 3.79 +/- 0.40 0.81 +/- 0.39 9.43 +/- 1.00 0.13 +/- 0.04 12.44 i 0.76 0.18 i 0.04 20.06 +/- 1.10 6.06 i 0.44 0.18 +/- 0.04 32.95 +/- 2.48 21.93 +/- 0.97 0.51 i 0.34 3.29 +/-0.49 1.06 +/- 0.40 8.06 +/- 0.07 5.93 +/- 0.73 0.11 i0.02 0.60 +/- 0.05 11.58 +/- 1.31 6.34 +/- 0.59 1215.40 +/-110.20 0.20 +/- 0.04 2.59 +/- 0.10 11.57 +/- 0.81 0.97 +/- 0.54 2.12 0

0.53 38717 +/-382 7.53 +/- 0.18 5.70 +/- 0.52 0.09 +/- 0.02 1.37 +/- 0.35 9.70 +/- 1.63 1.76 +/- 0.07 1.49 +/- 0.25 1383.90 +/- 116.20 1.93 +/- 0.24 4189.61 +/- 196.68 1.11 i0.30 3.44 +/- 0.62 1438.70 +/- 102.80 0.64 i 0.27 3.86 +/- 0.10 4.30 +/- 0.59 1.25 +/- 0.38 7.96 +/- 0.85 0.14 +/- 0.05 13.33 + 0.83 0.17 +/- 0.01 21.73 +/- 0.36 5.96 +/- 0.61 0.18 +/- 0.03 33.88 + 2.36 22.32 +/- 0.98 0.56 +/-0.30 3.75 +/- 0.66 1.21 i0.28 7.79 +/- 0.07 6.05 +/- 0.28 0.10 +/- 0.02 0.62 +/- 0.05 13.52 +/- 1.43 7.29 +/- 0.68 1250.70 +/- 106.70 0.22 +/- 0.04 2.51 +/-0.07 11.82 +/- 0.76 1.67 +/- 0.58 1.62 i 0.56 38017 +/-535 7.56 +/- 0.18 5.64 +/- 0.53 0.08 +/- 0.02 1.40 +/- 0.36 9.77 +/- 1.61 1.69 +/- 0.07 1.05 +/- 0.21 1428.20 +/- 125.40 2.18 +/- 0.23 4438.33 +/- 201.39 1.26 +/- 0.31 3.60 +/- 0.36 1351.80 +/- 100.80 0.91 +/- 0.28 3.83 +/- 0.07 4.04 +/- 0.36 1.03 +/- 0.27 8.70 +/- 0.66 0.13 +/- 0.03 12.88 +/- 0.56 0.18 +/- 0.02 20.90 +/- 0.58 6.01 +/- 0.38 0.18 +/- 0.02 33.41 +/- 1.71 22.13 +/- 0.69 0.53 +/- 0.23 3.52 +/- 0.41 1.14 +/- 0.24 7.93 +/- 0.05 5.99 +/- 0.39 0.11 +/-0.02 0.61 +/- 0.04 12.55 +/- 0.97 6.81 +/- 0.45 1233.05 +/- 76.70 0.21 +/- 0.03 2.55 +/- 0.06 11.69 +/- 0.56 1.32 +/- 0.40 1.87 +/- 0.39 38367 +/-329 7.55 +/- 0.13 5.67 +/- 0.37 0.09 +/- 0.01 1.39 +/- 0.25 9.73 +/- 1.15 1.72 +/- 0.05 1.27 +/- 0.16 1406.05 +/- 85.48 2.05 +/- 0.17 4313.97 +/- 140.75 1.18 +/- 0.22 3.52 +/- 0.36 1395.25 +/- 71.99 0.78 +/- 0.20 Pass Pass Pass Pass Pass Pass Pass Fail 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 L

L L

Pass Pass Pass Pass Pass Pass Pass Pass Pass L

A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4290, 4291 VE-4290, 4291 SWU-4311, 4312 SWU-4311, 4312 G-4383, 4384 G-4383, 4384 G-4383, 4384 MI-4425, 4426 TD-4446, 4447 SL-4473, 4474 SL-4473, 4474 VE-4532, 4533 VE-4618, 4619 VE-4618, 4619 VE-4618, 4619 F-4639, 4640 F-4639, 4640 F-4639, 4640 DW-4730, 4731 MI-4855, 4856 MI-4855, 4856 2

MI-4945,4946 MI-4945, 4946 TD-4921, 4922 VE-4900,4901 VE-4900,44901 7/26/2005 7/26/2005 7/26/2005 7/26/2005 8/1/2005 8/1/2005 8/1/2005 8/1/2005 811/2005 8/4/2005 8/4/2005 8/5/2005 8/9/2005 8/9/2005 8/9/2005 8/11/2005 8/11/2005 8/11/2005 8/12/2005 8/28/2005 8/28/2005 8/31/2005 8/31/2005 9/1/2005 9/2/2005 9/2/2005 Gr. Alpha Gr. Beta Gr. Beta H-3 Be-7 Gr. Beta K-40 K-40 H-3 Gr. Beta K-40 Gr. Beta Gr. Alpha Gr. Beta K-40 Cs-137 Gr. Beta K-40 1-131 K-40 Sr-90 K-40 Sr-90 H-3 Gr. Beta K-40 Gr. Alpha K-40 K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta 1-131 Gr. Beta 1-131 Be-7 K-40 K-40 Be-7 Cs-1 37 0.11 +/- 0.04 4.55 +/- 0.13 2.62 +/- 0.64 192.30 +/- 92.90 2.06 +/- 0.49 8.76 +/- 0.22 6.74 +/- 0.64 1358.10 +/- 169.20 563.00 +/- 252.00 5.44 +/- 0.48 2.91 +/- 0.83 31.20 +/- 1.20 0.09 +/- 0.05 4.60 +/- 0.13 4.19 +/- 0.46 0.05 +/- 0.02 3.33 +/- 0.11 2.62 +/- 0.57 0.82 +/- 0.23 1341.50 +/- 107.70 0.77 +/- 0.37 1388.90 +/- 158.90 0.67 +/- 0.34 5737.00 +/- 266.00 3.40 +/- 0.06 2.15 +/- 0.27 6.17 +/- 1.42 18.81 +/- 1.12 1584.00 +/- 194.00 0.10 +/- 0.06 6.05 +/- 0.18 4.61 +/- 0.46 1.09 +/- 0.33 0.44 +/- 0.22 2.92 +/- 0.56 0.45 +/- 0.27 0.91 +/- 0.40 1.43 +/- 0.34 1228.80 +/- 78.13 1286.10 +/- 550.80 726.97 +/- 76.24 0.05 +/- 0.03 4.69 +/- 0.14 1.67 +/- 0.37 304.60 +/- 97.40 1.76 +/- 0.29 8.40 +/- 0.20 6.88 +/- 0.92 1267.90 +/- 164.40 529.00 +/- 251.00 4.57 +/- 0.42 2.74 +/- 0.54 31.70 +/- 1.20 0.09 +/- 0.04 4.54 +/- 0.12 4.34 +/- 0.47 0.05 +/- 0.02 3.37 +/- 0.10 2.58 +/- 0.59 0.83 +/- 0.25 1340.00 +/- 114.70 0.87 +/- 0.37 1307.50 +/- 165.20 0.82 +/- 0.36 5860.00 +/- 269.00 3.51 +/- 0.06 2.27 +/- 0.24 6.08 +/- 1.46 19.52 +/- 0.86 1707.60 +/- 173.00 0.09 +/- 0.05 5.92 +/- 0.17 4.74 +/- 0.69 1.18 +/- 0.34 0.31 +/- 0.20 2.95 +/- 0.59 0.55 +/- 0.29 0.64 +/- 0.30 1.38 +/- 0.43 1297.00 +/- 81.03 1222.90 +/- 394.40 677.49 +/- 70.03 0.08 +/- 0.03 4.62 +/- 0.09 2.15 +/- 0.37 248.45 +/- 67.30 1.91 +/- 0.28 8.58 +/- 0.15 6.81 +/- 0.56 1313.00 +/- 117.96 546.00 +/- 177.84 5.00 +/- 0.32 2.82 +/- 0.49 31.45 +/- 0.85 0.09 +/- 0.03 4.57 +/- 0.09 4.27 +/- 0.33 0.05 +/- 0.02 3.35 +/- 0.07 2.60 +/- 0.41 0.83 +/- 0.17 1340.75 +/- 78.67 0.82 +/- 0.26 1348.20 +/- 114.61 0.75 +/- 0.25 5798.50 +/- 189.15 3.45 +/- 0.04 2.21 +/- 0.18 6.13 +/- 1.02 19.17 +/- 0.71 1645.80 +/- 129.97 0.10 +/- 0.04 5.98 +/- 0.12 4.68 +/- 0.41 1.13 +/- 0.24 0.38 +/- 0.15 2.93 +/- 0.41 0.50 +/- 0.20 0.78 +/- 0.25 1.41 +/- 0.27 1262.90 +/- 56.28 1254.50 +/- 338.72 702.23 +/- 51.76 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass DW-50769, 50770 9/2/2005 VE-4990, 4991 MI-5011, 5012 VE-5119, 5120 VE-5119, 5120 VE-5119, 5120 LW-5361, 5362 SW-5098, 51)99 LW-5178, 5179 DW-5239, 5240 CF-5432, 5433 CF-5432, 5433 MI-5292, 5233 BS-5340, 5341 BS-5340, 5341 9/6/2005 9/8/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/13/2005 9/14/2005 9/16/2005 9/19/2005 9/19/2005 9/21/2005 9/2312005 9/23/2005 A5-3

TABLE A-5. In-House 'Duplicate' Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance BS-5340, 5341 DW-5382, 5383 MI-5405, 5406 AP-5769, 5770 AP-5983, 5984 AP-5878, 5879 G-5526, 5527 G-5526, 5527 G-5526, 5527 VE-5721, 5722 VE-5721, 5722 VE-5721, 5722 CF-5695, 5696 CF-5695, 5696 LW-6129, 6130 LW-6129, 6130 DW-50844, 5 LW-5748, 5749 c AP-6485, 6486 SWU-6156, 6157 VE-6186, 6187 LW-6203, 6204 SO-6270, 6271 SO-6270, 6271 SO-6270, 6271 TD-6320, 6321 SO-6605, 6606 CF-6509, 6510 SW-6638, 6639 SO-6887, 6888 SO-6887, 6888 SO-6887, 6888 SWT-6721, 6722 VE-6775, 6776 LW-6743, 6744 DW-51023, 4 SWT-7282, 7283 9/23/2005 9123/2005 9/27/2005 9/27/2005 9/27/2005 9/29/2005 10/3/2005 10/3/2005 10/3/2005 10/10/2005 10/10/2005 10/10/2005 10/11/2005 10/11/2005 10/11/2005 10/11/2005 10/11/2005 10/12/2005 10/20/2005 10/25/2005 10/26/2005 10/27/2005 10/28/2005 10/28/2005 10/28/2005 11/1/2005 11/11/2005 11/14/2005 11/22/2005 11/22/2005 11/22/2005 11/22/2005 11/29/2005 11/29/2005 11/30/2005 12/2/2005 12/27/2005 K-40 1-131 K-40 Be-7 Be-7 Be-7 Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 Be-7 K-40 Gr. Beta H-3 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Gr. Beta Cs-1 37 Gr. Beta K-40 H-3 Gr. Beta K-40 1-131 Gr. Alpha Gr. Beta K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Alpha Gr. Beta 12404 +/- 1154 0.79 +/- 0.31 1324.80 +/- 112.20 0.08 +/- 0.01 0.08 +/- 0.01 0.06 +/- 0.01 4.03 +/- 0.62 8.10 +/- 0.30 4.93 +/- 0.67 0.07 +/- 0.05 5.09 +/- 0.15 4.27 +/- 0.43 2.70 +/- 0.37 11.79 +/- 0.86 1.34 +/- 0.25 304.35 +/- 95.31 5.30 +/- 1.50 1.09 +/- 0.25 0.10 +/- 0.03 4.69 +/- 1.34 2.90 +/- 0.49 2.92 +/- 0.62 0.33 +/- 0.03 26.85 +/- 2.78 13.67 +/- 0.74 444202 +/- 1770 18.22 +/- 2.23 0.85 +/- 0.14 0.95 +/- 0.35 6.80 +/- 2.92 19.27 +/- 2.16 14.29 +/- 1.11 0.98 +/- 0.31 12.75 +/- 0.28 3.19 +/- 0.47 0.55 +/- 1.40 1.62 +/- 0.37 13033 +/-983 0.53 +/- 0.31 1366.80 +/- 99.44 0.09 +/- 0.02 0.08 +/- 0.01 0.07 +/- 0.01 4.07 +/- 0.80 8.80 +/- 0.40 6.00 +/- 0.72 0.08 +/- 0.06 5.00 +/- 0.16 4.20 i 0.34 2.80 i 0.34 13.11 i0.68 1.85 +/- 0.29 369.23 +/- 97.88 4.20 +/- 1.40 1.89 +/- 0.28 0.09 +/- 0.03 4.18 +/- 1.34 2.83 +/- 0.51 3.09 i 0.66 0.34 i 0.04 22.25 +/- 2.41 14.02 +0.76 446633 +/- 1775 18.47 +/- 2.22 0.99 +/- 0.22 0.67 +/- 0.31 10.27 i3.26 18.43 i2.21 13.78 +/- 0.78 0.87 +/-0.31 13.16 +/-0.21 2.50 +/- 0.44 2.21 +/- 1.31 1.85 i 0.38 12719 +/- 758 0.66 +/- 0.22 1345.80 +/- 74.96 0.08 +/- 0.01 0.08 +/- 0.01 0.07 +/- 0.01 4.05 +/- 0.51 8.41 +/- 0.24 5.47 +/- 0.49 0.08 +/- 0.04 5.05 +/- 0.11 4.23 +/- 0.27 2.75 +/- 0.25 12.45 +/- 0.55 1.59 +/- 0.19 336.79 +/- 68.31 4.75 +/- 1.03 1.49 +/- 0.19 0.09 +/- 0.02 4.44 +/- 0.95 2.87 +/- 0.35 3.01 +/- 0.45 0.33 +/- 0.03 24.55 +/- 1.84 13.85 +/- 0.53 445418 +/- 1253 18.35 +/- 1.57 0.92 +/- 0.13 0.81 +/- 0.23 8.53 +/- 2.19 18.85 +/- 1.54 14.03 +/- 0.68 0.93 +/- 0.22 12.96 +/- 0.18 2.85 +/- 0.32 1.38 +/- 0.96 1.74 +/- 0.27 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass i

L L

L' L

4 Note: Duplicate analyses are performed on every twentieth sample received in-house.

analyses with activities that measure below the LLD.

Results are not listed for those a

b C

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

600 minute count time or longer, resulting in lower error.

Recount of W-5748, 2.38 +/- 0.85 pCi/L Averaged result, 2.14 +/- 0.45 pCi/L I.

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 STW-1(045 01/01/05 Gr. Alpha STW-1C045 01/01/05 Gr. Beta 0.45 +/- 0.10 1.90 +/- 0.10 0.53 1.67 0.00 - 1.05 0.84 - 2.51 Pass Pass STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 C)46 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 0)46 STW-1 046 STW-1 046 STW-1046 STVE-1 047 STVE-1 047 STVE-1 047 STVE-1 047 STVE-1 047 STVE-1 047 STSO-1 048 STSO-1048 STSO-1048 STSO-1 048 STSO-1 048 STSO-1048 STSO-1048 STSO-1 048 STSO-1048 STSO-1048 STSO-1048 STSO-1 048 STSO-1048 STSO-1048 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 Am-241 Co-57 Co-60 Cs-134 Cs-137 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-23314 U-238 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 Am-241 Co-57 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 1.62 +/- 0.12 239.40 +/- 1.20 248.70 +/- 1.00 115.50 +/- 1.80 328.50 +/- 1.70 64.90 +/- 7.00 304.00 +/- 9.70 334.80 +/- 1.90 7.10 +/- 1.60 0.01 +/- 0.02 2.50 +/- 0.14 0.70 +/- 0.80 43.20 +/- 1.40 3.31 +/- 0.20 3.38 +/- 0.20 538.40 +/- 3.80 10.60 +/- 0.20 3.00 +/- 0.20 4.80 +/- 0.40 4.10 +/- 0.30 5.10 +/- 0.30 6.20 +/- 0.50 96.60 +/- 10.00 264.00 +/- 2.00 226.50 +/- 2.20 760.60 +/- 3.70 336.20 +/- 3.60 663.70 +/- 18.00 541.30 +/- 3.90 924.30 +/- 17.20 0.60 +/- 0.80 78.00 +/- 4.80 514.60 +/- 18.70 47.90 +/- 4.00 226.30 +/- 8.60 851.30 +/- 7.30 1.72 227.00 251.00 127.00 332.00 75.90 280.00 331.00 9.00 0.02 2.40 0.00 42.90 3.24 3.33 496.00 9.88 3.15 5.00 4.11 5.18 6.29 109.00 242.00 212.00 759.00 315.00 604.00 485.00 1220.00 0.48 89.50 640.00 62.50 249.00 810.00 1.20 - 2.24 158.90 - 295.10 175.70 - 326.30 88.90 - 165.10 232.40 - 431.60 53.13 - 98.67 196.00 - 364.00 231.70 - 430.30 0.00 - 20.00 0.00 - 1.00 1.68 - 3.12 0.00 - 5.00 30.03 - 55.77 2.27 - 4.21 2.33 - 4.33 347.20 - 644.80 6.92 - 12.84 2.21 - 4.10 3.50 - 6.50 2.88 - 5.34 3.63 - 6.73 4.40 - 8.18 76.30 - 141.70 169.40 - 314.60 148.40 - 275.60 531.30 - 986.70 220.50 - 409.50 422.80 - 785.20 339.50 - 630.50 854.00 - 1586.00 0.00 - 1.00 62.65 - 116.35 448.00 - 832.00 43.75 - 81.25 174.30 - 323.70 567.00 - 1053.00 Pass Pa:;s 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 Pas s Pass Pas;s Pas-s Pass Pass Pass Pass STAP-1 050 01/01/05 Gr. Alpha STAP-1050 01/01/05 Gr. Beta 0.11 +/- 0.03 0.38 +/- 0.05 0.23 0.30 0.00 - 0.46 0.15 - 0.45 Pass Pass TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration b A6-1

Known Activity Control Limits d Lab Code' Date Analysis Laboratory result Acceptance STAP-1049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1049 STAP-1049 STAP-1 049 STAP-1049 STAP-i 049 e STAP-1049 STAP-1 049 STAP-1 049 01101/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01101/05 01/01105 01/01/05 01/01/05 01/01/05 01/01/05 Am-241 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239140 Sr-90 U-23314 U-238 Zn-65 0.10 +/- 0.04 4.76 +/- 0.64 2.84 +/- 0.22 3.54 +/- 0.37 2.20 +/- 0.27 3.15 +/- 0.21 0.16 +/- 0.04 0.17 +/- 0.02 2.24 +/- 0.34 0.34 +/- 0.02 0.35 +/- 0.02 3.12 +/- 0.15 0.10 4.92 3.03 3.51 2.26 3.33 0.20 0.17 1.35 0.34 0.35 3.14 0.07 - 0.13 3.44 - 6.40 2.12 - 3.94 2.46 - 4.56 1.58 - 2.94 2.33 - 4.33 0.14 -0.25 0.14 - 0.25 0.95 -1.76 0.24 - 0.44 0.25 - 0.46 2.20 - 4.08 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass STW-1 061 STW-1061 STW-1061 STW-1 061 STW-1 061 STW-1 061 STW-1 061 STW-1 061 STW-1061 STW-1 061 STW-1 061 STW-1061 STW-1 061 STW-1 061 STW-1 061 STW-1061 07/01/05 07/01/05 07/01105 07/01/05 07/01/05 07/01/05 07/01/05 07101/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 Am-241 Co-57 Co-60 Cs-134 Cs-137 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 2.21 +/- 0.13 293.20 +/- 7.30 275.70 +/-1.30 171.80 +/- 4.00 342.10 +/- 2.20 167.80 +/- 9.30 514.20 +/- 12.60 437.00 +/- 2.50 105.10 +/- 3.60 1.64 +/- 0.12 2.32 +/- 0.13 9.20 +/- 1.30 72.30 +/- 2.30 4.11 +/- 0.18 4.14 +/- 0.18 364.60 +/- 4.90 0.57 +/- 0.05 1.36 +/- 0.05 48.40 +/- 3.90 608.30 +/- 2.80 322.70 +/- 2.40 632.10 +/- 5.20 512.40 +/- 4.20 720.50 +/- 19.00 516.80 +/- 5.10 366.50 +/- 13.30 68.80 +/- 15.00 0.00 +/- 0.00 602.90 +/- 17.20 61.50 +/- 1.00 164.50 +/- 16.70 874.70 +/- 8.40 2.23 272.00 261.00 167.00 333.00 196.00 527.00 418.00 100.00 1.91 2.75 8.98 66.50 4.10 4.26 330.00 0.79 1.35 81.10 524.00 287.00 568.00 439.00 604.00 439.00 445.00 60.80 0.00 757.00 52.50 168.00 823.00 1.56 - 2.90 190.40 - 353.60 182.70 - 339.30 116.90 - 217.10 233.10 - 432.90 137.20 - 254.80 368.90 - 685.10 292.60 - 543.40 70.00 - 130.00 1.34 - 2.48 1.93 - 3.58 6.29 - 11.67 46.55 - 86.45 2.87 - 5.33 2.98 - 5.54 231.00 - 429.00 0.21 - 1.38 0.85 - 1.92 56.77 - 105.43 366.80 - 681.20 200.90 - 373.10 397.60 - 738.40 307.30 - 570.70 422.80 - 785.20 307.30 - 570.70 311.50 - 578.50 42.56 - 79.04 0.00 - 0.00 529.90 - 984.10 36.75 - 68.25 117.60 - 218.40 576.10 - 1070.00 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass L

L STW-1 062 07/01/05 Gr. Alpha STW-1062 07/01/05 Gr. Beta Pass Pass L

STSO-1063 T STSO-1063 STSO-1063 STSO-1063 STSO-1 063 STSO-1063 STSO-1063 STSO-1063 STSO-1063 STSO-1063 STSO-1063 STS0-1063 STSO-1063 STSO-1063 07/01/05 07/01/05 07/01/05 07/01105 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 Am-241 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 U-23314 U-238 Zn-65 Fail Pass Pass Pass Pass Pass Pass Pass Pass L

Pass Pass Pass Pass TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEPr.

Concentrationb Known Control Lab Code' Date Analysis Laboratory result Activity Limits c Acceptance L

A6-2 i

L

STVE-1 064 STVE-1 064 STVE-1 064 STVE-1 064 STVE-1 064 STVE-1064 STVE-1064 STVE-1 064 STVE-1 064 STVE-1 064 STVE-1 064 STVE-1 064 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 STAP-1065 07/01/05 Gr. Alpha STAP-1065 07/01/05 Gr. Beta 0.18 +/- 0.03 15.90 +/- 0.20 4.80 +/- 0.10 4.60 +/- 0.20 5.90 +/- 0.30 7.20 +/- 0.20 0.04 +/- 0.02 0.13 +/- 0.02 2.80 +/- 0.30 0.28 +/- 0.03 0.33 i 0.04 11.00 +/- 0.50 0.30 +/- 0.04 0.97 +/- 0.06 0.14 +/-0.03 5.81 +/-0.17 2.79 +/- 0.14 3.67 +/- 0.12 2.93 +/- 0.23 4.11 +/-0.26 0.11 +/-0.02 0.10 +/- 0.01 2.25 +/- 0.29 0.28 +/- 0.02 0.28 +/- 0.02 4.11 +/- 0.26 0.23 13.30 4.43 4.09 5.43 6.57 0.00 0.16 2.42 0.33 0.35 10.20 0.48 0.83 0.16 6.20 2.85 3.85 3.23 4.37 0.10 0.09 2.25 0.27 0.28 4.33 0.16 - 0.30 9.31 - 17.29 3.10 - 5.76 2.86 - 5.32 3.80 - 7.06 4.60 - 8.54 0.00 - 1.00 0.11 - 0.21 1.69 - 3.15 0.23 - 0.43 0.24 - 0.45 7.14 - 13.26 0.00 - 0.80 0.55 - 1.22 0.11 - 0.21 4.34 - 8.06 2.00 - 3.71 2.70 - 5.01 2.26 - 4.20 3.06 - 5.68 0.07 - 0.13 0.06 - 0.12 1.58 - 2.93 0.19 - 0.35 0.20 - 0.37 3.06 - 5.68 Pass Pass Pass Pass PaSs Pass Pa:ss Pass Pass Pa s Pass Pa s Pass Pa:;s Pass Pa!;s Pass Pass Pass Pass Pans Pass Pa;s Pass Pa!.s Pa!;s STAP-1066 STAP-1 066 STAP-1066 STAP-1066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 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 D Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) as requested iy the Department of Energy.

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

o 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 The strontium carbonate precipitates were redissolved and processed. The average of the three analyses was 1.34 although the recovery was only 30%. The result of a new analysis was 1.56 pCi/L.

t Incorrect sample weight used in calculation. Result of recalculation: 97.0 +/- 7.8 Bq/kg.

A6-3

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX B, 2005 REMP DATA

SUMMARY

REPORTS Appendix B Page 44

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fAir Gamma Spectral Summary Report 2005 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50441 r

. Sampic Type and Units Air pCi/m3 Air pCi/m3 Air pCi/m3 Air pCi/m3 Air pCi/m3 Type and Number of Anaiy:cs Performed Bc-7 28 Co-58 28 Co-60 28 Cs-134 28 Cs-137 28 Lower I

I I.n,,,

(LLD)

N/A N/A N/A 0.04 0.05 Mean of Results from Mean of All Locations and All Indicatc

"'..mbr Detectpd/Niimber Collected Number Detecti and Range an 0.06 28 28 24 0.04 - 0.07 0.04 LLD LLD LLD LLD

'Results from ir Locations and td/Number Collected d Range 0.06 4 / 24 4 - 0.07 Location with Highest Annual Mean:

Location # and Mean and Distance and Number Dctected/Number Collected Lirection I

aiiu Rangc 4

0.06 0.70 4 /20 S

0.05 - 0.06 Mean of Results from All Control Locations and Number Detected/Number Collected nni Ranee 0.06 4

0 4

0.05 - 0.07

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Air Gross Beta Summary Report 2005 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Type and Units Air pCi/m3 Type and Number of Analyses Performed Gross Beta 364 Lower Limit (LLD) 0.01 Mean of Results from All Locations and Number Detected/Number Collected i

and Range 0.02 364 1 364 0.01 - 0.05 Mean of Results from L Location with Ilighest Annual Mean:

All Indicator Locations and Location U and Mean and Number Detected/Number Collected!

Distance and i Number Detected/Number Collected and Range Direction and Range 0.0 5

0.02 312/

312 0.60 52 /52

- 0.01 - 0.05 SW.

0.01

- 0.05 Mean of Results from All Control Locations and Number Detected/Number Collected and Range 0.02 52 /52 0.01

- 0.05

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An91y"eR Performed 1-131 364 L

(I ower Limit I Num L~LD).

)5 I

Mean of Results from All Locations and iber Detected/Number Collected and Rangc LLD Mean of Results from All Indicator Locations and Number Detected/Number Collected.

and Range i

Location with Highest Annual Mean:

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

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UJ Fish Gamma Spectral Summary Report 2005 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lakc County Ohio Docket no. : 50-440/50441 Sample Type and Units IFish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/kg wet Fish pCi/k-g wet Fish pCilkg wet Fish pCi/kg wet Fish pCi/kg wet Type and Number of Analyses Performed Co-58 1

2 Co-60 2

Cs-134 2

Cs-137 2

Fe-59 2

K-40 2

Mn-54 2

Lower Limit (LLD) 97.00 97.00 97.00 112.00 195.00 N/A 97.00 Mean of Results from All Locations and Number Detected/Number Collected and Range LLD LLD LLD LLD LLD 1,088.81 2 / 2 816.22 - 1,361.40 LLD Mean of Results from

. All Indicator Locations and Number Detected/Number Collected and Range 1,361.40 1 / 1 1,361.40 - 1,361.40 Location with Highest Annual Mean:

Location # and Mean and Distance and Number Detected/Number Collected Direction and Range Mean of Results from All Control Locations and Number Detected/Number Collected and Range 816.22 8 / 1 816.22 - 816.22

- 25 0.60 NNW 1,361.40 1,361.40 - 1,361.40 Zn-65 2

195.00 LLD

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Samnle Tvne and Units ood Products pCi/lkg wet ooid Product pCi/kg wet ood Products pCi/lg wet ood Products pCi/kg wet ood Products pCi/kg wet ood Products pCikg wet ood Products pCi/kg wet Type and Number of Analyscs Pcrformed Be-7 72 Co-58 72 Co-60 72 Cs-134 72 Cs-137 72 1-131 72 K-40 72 Lower Limit (LLD)

N/A N/A N/A 45.00 60.00 45.00 N/A Mean of Results from All Locations and Number Dcetcted/Number Collected and Range 300.19 8 /72 156.61 - 502.63 LLD LLD LLD LLD LLD 4,630.45

.2,006.70- 172

.2,00.70, 7,657.50 Mean of Results from All Indicator Locations and Number Detected/Number Collected and Kange 271.27

.. 7 / 57 156.61 - 448.99 Location with Ilighcst Annual Mean:

Location # and I Mean and Distance and Number Detected/Number Collected Direction

.aild Ranige 70 502.63 16.20 1 I 105 SSW 502.63

- 502.63 Mean of Results from All Control Locations and Number Detected/Number Collected a.d P--nge 502.63 I / 15 502.63 - 502.63 4,961.25 15 / 15 2,079.90 - 7,657.50 F

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F, 4,543.40 57 / 57 2,006.70

- 7,313.00 '-

.21 E1.90

.: E N E 5,047.58 13 / 91 3,543.50 - 7,313.00

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]

Sample Type and Units IMilk lpCiIL l

Milk iMilk l

pCi/L II Milk I

pCi/L I

Maik Type and Number of Analyses Performed Ba-140 42 Cs-134 42 Cs-137 42 K-40 42 La-140 42 Lower

. Limit (LLD) 45.00 11.00 13.00 N/A 11.00 Mean of Results from All Locations and Number Detected/Number Collected and Range LLD LLD LLD 1,510.63 42 / 42 1,130.20 - 1,829.30 LLD Mean of Results from Location with Highest Annual Mean:

All Indicator Locations and Location # and Mean and Number Detected/Number Collected Distance and Number Detected/Number Collected and Range Direction j

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

_ and Range 1,326.97 19 / 19 1,130.20 -

1,483.90 w

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II 1,662.35 23 / 23 1,463.50 - 1,829.30 61 7.40 SE 1,705.98 9 / 45 1,640.30 - 1,829.30 IvIKI'..

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IMilk Iodine Summary Report 2005 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Dockct no. : 50-440/50-441 r-F Sample Type and Units Milk pCi/L Type and Number of Analyses Pcrformed -.

I-131 42 Mean of Results from Lower All Locations and Limit

. Number Detected/Number Collected (LLD) t and Range 0.75 LLD Mean of Results from Location with Highest Annual Mean:_

All Indicator Locations and lLocation # and Mean and Number Detected/Number Collected Distance and Number Detected/Number Collected and Fange DiimciiuII and Rng, Mean of Results from All Control Locations and Number Detected/Number Collected and Pange

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_ A Scdimenit Gamma Spectral Summary Report 2005 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440150-441 Sample Type and Units Sediment pCi/kg dry Sediment pCi/kg dry Sediment pCi/kg dry

-Sediment

pCi/kg dry I..

I Sediment pCi/kg dry Type and Number of Analyses Performed Co-58 14 Co-60 14 Cs-134 14 Cs-137 14 K40 14

.Lower Limit (LLD) 50.00 40.00 112.00 135.00 Mean of Results from All Locations and Number Detected/Number Collected and Range LLD LLD LLD

.532.34

5. /14

. 135.16.,-

1,085.10 Mean of Results from i

L_ ocation with Iighest Annual Mean:

All Indicator Locations and Location 1 and Mean and Number Detected/Number Collected Distance and I Number Detected/Number Collected and Range Direction and Range

~~..

Mean of Results from All Control Locations and Number Detected/Number Collected and Range 1,084.65 2 /2 1,084.20-1,085.10 29,866.50 2

2 29,236.00 - 30,497.00 I

164.14 3 / 12 135.16.- 221.57 12,114.81

- 12/ 12 8,929.80 - 16,091.00

.32

15.80

. WSW

32 15.80 WSW 1,084.65 2 / 10 1,084.20 - 1,085.10 29,866.50 2 / 10 29,236.00 - 30,497.00 N/Ai 14,650.76 14 / 14

.,..:.8,929.80

- 30,497.00

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17 TLD Gamma Dose Summary Report 2005 Radiological Environmental Monitoring Program Data Summary Pcrry Nuclcar Power Plant, Lakc County Ohio Dockct no. : 50-440/50-441 Vnnnlp Tvne i

and Units TLD TLD i

Typc and Number of Analyses Performed Direct 112 Direct 112 Direct 28 TLD mlV365 days Mean of Results from Lower All Locations and Limit I Number Detccted/Number Collected (LLD) and Range 1.00 12.81 112 / 112 7.49 -. 17.32 1.00 12.56 112 I112 8.59

- 17.37 1.00 57.81 28/28 41.14

- 73.90 Mean of Results from Location with Highest Annual Mean:

All Indicator Locations and Location # and r Mean and Number Detected/Number Collected Distance and Number Dctected/Number Collected and Range Direction I

anu Rangtc 12.83 29 16.54 104/

104 4.30 4 /4 7.49 - 17.32 SSE 15.87 - 17.32 12.63 33 16.62 104/

104 4.50 4 /4 8.59 - 17.37 S

15.07

- 17.37 58.12 36 73.90 26 / 26 3.90 I/I 41.14 - 73.90 WSW 73.90 - 73.90 Mean of Results from All Control Locations and Number Detected/Number Collected and PanO I_

12.53 11.79 - 13.16 Ii 11.62 8 / 8 10.77 - 12.24 53.79 2 / 2 48.47 - 59.11 II I

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2-j Water Ganinna Spectral Summary Report 2005 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50440/50-441 Sample Type and Units Water pCi/L Water pCi/L Water pCi/L Water pCi/L Water pCi/L Water pCi/L Water pCiIL Water pCi/L Water pCi/L Water pCi/L Water pCi/L Type and Number of Analyses Performed Cs-134 52 Cs-137 52 Fe-59 52 La-140 52 Mn-54 52 Nb-95 52 Zn-65 52 Zr-95 52 Ba-140 52 Co-58 52 Co-60 52 Lower Limit (LLD) 11.00 13.00 22.00 11.00 11.00 Mean of Results from All Locations and Number Detected/Number Collected and Range LLD LLD LLD LLD LLD Mean of Results from All Indicator Locations and Number Detected/Number Collected, and Range Location with Ilighest Annual Mean:

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

11.00 LLD 22.00 LLD 22.00 LLD 45.00 LLD 11.00 LLD 11.00 LLD

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EL: i Ej V -i r-r7 WVatcr Gross Bcta Summary Report 2005 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50441 Sample Type and Units Water pCi/L Type and Number of Analyses Performed Gross Beta 52 Lower Limit (LLD) 3.00 Mean of Results from All Locations and Number Dctected/Number Collected and Range 3.30 7 / 52 3.01 - 3.60 Mean of Results from I

Location with Highest Annual Mean:

All Indicator Locations and Location # and Mean and Number Detcted/Number Collectcd Distance and Number Detected/Number Collected and Range Direccion and Ralig 3.28 1

59 3.45 5/

40 4.00 1/

8 3.01 - 3.60 ENE 3.45

- 3.45 Mean of Results from All Control Locations and Number Detected/Number Collected !

and Rn-3.33 2 / 12 3.07 - 3.59

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-- i Water Tritliui Sumimiary Report 2005 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Type and Units Water pCiIL Type and Number of Analyses Performed H-3 18 Lower Limit (LLD) 1,500.00 Mean of Results from All Locations and Number Detected/Number Collected and Range LLD Mean of Results from All Indicator Locations and Number Detected/Number Collected*

and Range

-I Location with _Highest Annual Mean:

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

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX C, 2005 REMP DETAILED DATA REPORT Appendix C Pa.ge 45

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35 0.030 +/- 0.003 0.028 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.003 0.021 +/- 0.003 0.019 +/- 0.003 0.027 +/- 0.003 0.028 +/- 0.003 0.018 +/- 0.002 0.019 +/- 0.003 0.029 +/- 0.003 0.030 +/- 0.003 0.026 +/- 0.003 0.020 +1- 0.003 0.022 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.002 0.021 +/-0.003 0.019 +/- 0.003 0.022 +/- 0.003 0.018 +/- 0.002 0.018 +/- 0.003 0.017 +/-0.002 0.020 +/- 0.003 0.014 +/- 0.003 0.013 +/- 0.003 0.017 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.002 0.023 +/- 0.003 0.024 +/- 0.003 4

5 6

0.031 +/-0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.026 +/- 0.003 0.018 +/- 0.003 0.025 +/- 0.003 0.022 +/- 0.003 0.019 +/- 0.003 0.018 +/-0.003 0.022 +/- 0.003 0.018 +/- 0.003 0.015 +1- 0.002 0.012 +/- 0.003 0.015 +-0.003 0.018 +/- 0.003 0.021 +/- 0.003 0.033 +/- 0.003 0.0 17 +/- 0.003 0.022 +/- 0.003 0.030 +/- 0.003 0.023 +/- 0.003 0.032 +/- 0.003 0.024 +/- 0.003 0.026 +/- 0.003 0.020 +/- 0.003 0.027 +/- 0.003 0.020 +/- 0.003 0.023 +/- 0.003 0.015 +/- 0.003 0.017 +-0.003 0.019 +/- 0.003 0.026 +/- 0.003 0.029 +/- 0.003 0.017 +/- 0.003 0.021 +/- 0.003 0.028 +/- 0.003 0.022 +1- 0.003 0.032 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0.019 +/- 0.002 0.021 +/- 0.003 0.019 +/- 0.002 0.020 +/- 0.002 0.011 +/- 0.003 0.014 +/- 0.002 0.016 +1- 0.002 0.025 +/- 0.003

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35 0.035 +/- 0.003 0.030 +/- 0.003 0.025 +/- 0.003 0.027 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.003 0.015 +/- 0.003 0.018 +/- 0.003 0.040 +/- 0.003 0.042 +/- 0.003 0.028 +/- 0.003 0.032 +/- 0.003 0.036+/- 0.003 0.030 +/- 0.003 0.032 +/- 0.003 0.035 +/- 0.003 0.011 +/-0.002 0.009 +/- 0.002 0.017 +/- 0.003 0.019 +/- 0.003 0.010 +/- 0.003 0.011 +/-0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.034 +/- 0.003 0.033 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.003 0.029 +/- 0.003 0.028 +/- 0.003 4

5 6

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7 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 Ar Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air 9/!4/05 9/21/05 9/28/05 10/5/05 10/12/05 10/19/05 10/26/05 11/2/05 11/9/05 11/16/05 11/23/05 11/30/05 12/7/05 12/14/05 12/21/05 12/28/05 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 1/5/05 1/12/05 1/19/05 1/26/05 2/2/05 2/9/05 2/16/05 2/23105 3/2/05 3/9/05 3/16/05 3/23/05 3/30/05 4/6/05 4/13/05 4/20/05 4/27/05 5/4/05 5/11/05 5/19/05 5/25/05 6/1/05 6/8/05 6/15/05 6/22/05 6/29105 0.006 0.007 0.008 0.005 0.010 0.007 0.009 0.007 0.007 0.007 0.006 0.006 0.007 0.008 0.006 0.005 0.012 0.008 0.009 0.010 0.007 0.007 0.006 0.008 0.009 0.004 0.010 0.013 0.006 0.005 0.006 0.006 0.008 0.005 0.005 0.004 0.006 0.004 0.003 0.006 0.007 0.010

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Location Sample Type Collection Dat 1-131 35 35 35 35

35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 35 Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air Air 7/6/05 7/13/05 7/20/05 7/27/05 8/3/05 8/10/05 8/17/05 8/24/05 8/31/05 9/7/05 9/14/05 9/21/05 9/28/05 1015/05 10/12/05 10/19/05 10/26/05 11/2/05 11/9/05 11/16/05 11/23/05 11/30/05 12/7/05 12/14/05 12/21/05 12/28/05 0.004 0.008 0.006 0.006 0.006 0.003 0.009 0.008 0.008 0.004 0.004 0.009 0.008 0.008 0.004 0.008 0.006 0.008 0.008 0.008 0.008 0.004 0.008 0.005 0.005 0.010

r-r u- -0 r Fish Gamma Spectral Detail Report 2005 Radiological Environmental Monitoring Program Dctail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Bi-Annually Results in pCi/kg wet +/- 2 Sigma

.Vl7 t7 r-_7 UT LucaLuin i Samipk; Type CUolliccfscn, D.-lc Co-58 K40 Co-60 Mn-54 Cs-134 Zn-65 Cs-137 Fc-59 25 yellow perch 32 yellow perch 7/28/05 7/28/05

< 21.25 1,361.40 +/- 403.80

< 32.95 816.22 +/- 403.40

< 27.00

< 13.19

< 12.94

< 24.74

< 21.68

< 31.17

< 15.30

< 25.79

< 11.69

< 40.57

< 12.09

< 27.78

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Location Sample Type Collection Date chinese cabbage collard greens swiss chard beet greens collard greens swiss chard chinese cabbage collard greens swiss chard collard greens swiss chard collard greens 6/28/05 6/28/05 6/28/05 7/12/05 7/12/05 7/12/05 8/9/OS 8/9/05 8/9105 9/13/05 9/13/05 10/12/05 J.

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Food Products Gamma Spectral Detail Report 2005 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50441 Sample Frequency is: Monthly Results in pCi/kg wet +/- 2 Sigma Bc-7 Co-58 Co-60 Cs-134 1-131 K-40

< 139.38

< 7.55

< 9.34

< 11.84

< 18.23 3,543.50 +/- 374.70

< 114.75

< 8.41

< 7.71

< 11.75

< 19.97 4,273.90 +/- 376.60

< 97.39

< 14.66

< 16.40

< 26.36

< 21.93 4,689.90 +/-576.60

< 83.58

< 14.97

< 17.56

< 19.95

< 16.77 6,651.10 +/-458.50

< 125.55

< 8.61

< 13.81

< 15.56

< 14.04 4,749.90 +/- 353.40

< 123.43

< 10.33

< 9.19

< 16.03

< 20.41 5,831.30 +-369.30

< 179.11

< 14.85

< 10.50

< 20.21

< 27.80 4,158.10 +/- 555.60 156.61 +/- 82.25

< 4.55

< 7.68

< 17.90

< 9.84 4,736.80 +/- 376.00

< 154.61

< 7.38

< 8.08

< 15.52

< 10.49 7,121.50 +/- 482.40

< 134.48

< 4.78

< 10.11

< 14.49 4,589.10 +/-344.15 239.60 +/- 125.80

< 11.43

< 9.96

< 10.65

< 17.62 7,313.00 +/- 472.30

< 143.48

< 16.51

< 7.30

< 19.82

< 27.57 3,698.60 +/- 331.00 Cs-137

< 9.03

< 13.15

< 22.12

< 14.92

< 14.75

< 14.12

< 23.16

< 11.72

< 16.80

< 8.35

< 13.47

< 5.98

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on Date Be

-? ro-S8 Co-60 Cs-134 Cs-137 1-131 K-40 2

swiss chard 10/12/05 245.39+/-119.80

< 7.42

< 7.91

< 13.01

< 14.91

< 15.91 4,261.90 +-472.80 16 chinese cabbage 6/28/05

< 99.41

< 19.77

< 10.92

< 9.11

< 19.43

< 19.90 4,393.00 +/- 526.60 16 collard greens 6/28/05

< 134.35

< 10.01

< 15.85

< 18.62

< 10.17

< 21.41 5,055.10 +/-570.30 16 turnip greens 6/28/05

< 174.14

< 16.67

< 18.66

< 17.00

< 20.15

< 21.69 5,309.90+/-639.80 16 chincsecabbage 7/12/05

< 118.04

< 5.94

< 8.12

< 9.81

< 9.70

< 22.85 5,037.80 +-341.40 16 collard greens 7/12/05

< 162.58

< 20.50

. < 10.31

< 9.67

< 16.91

< 15.60 5,720.60 +/- 678.50 16 turnip greens 7/12/05

< 128.43

< 11.36

< 12.28

< 14.57

< 15.43

< 12.71 6,350.20+/-437.10 16 chinesecabbage 8/9/05

< 157.92

< 10.93

< 15.32

< 11.62

< 18.39

< 19.87 3,561.20 +/-500.80 16 collard grecns 8/9/05

< 176.97

< 22.99

< 22.65

< 14.69

< 23.22

< 17.18 4,386.80 +/- 623.10 16 tumipgreens 8/9/05

< 168.12

< 26.10

< 17.34

< 18.28

< 18.46

< 18.63 7,221.30 +/-643.20 16 chinese cabbage Wii3Y05

< i 6.&33

< I1.3

.5

<. !9.5!

< 15 R5

< 11.46 3,357.60 +/-493.80 16 collard greens 9/13/05

< 175.49

< 19.16

< 15.13

< 13.35

< 14.58

< 18.77 5,448.10 +/-597.90

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< 182.03

<.13.30

< 16.98

< 16.42

< 27.18

< 27.10 6,447.50+/- 757.10 16 collard greens 10/12/05

< 189.00

< 14.24

< 7.28

< 12.85

< 17.95

< 38.67 3,194.50 +-447.00 16 turnip greens 10/12/05 349.38 +/- 169.70

< 13.19

< 14.70

< 10.23

< 7.09

< 19.57 4,739.20 +/- 445.60 chinese cabbage collard greens turnip greens chinese cabbage collard greens turnip greens chinese cabbage collard greens turnip greens 6/28/05 6/28/05 6/28/05 7/12/05 7/12/05 7/12/05 8/9/05 8/9/05 8/9/05

< 98.80

< 15.76

< 105.57

< 13.34

< 176.15

< 12.36

< 93.05

< 16.22

< 183.37

< 15.55

< 102.95 17.22

< 150.15

< 10.25

< 165.18

< 25.05 276.36 +1-108.24

< 11.91

< 11.99 3,806.25 +/- 249.83

< 13.89 3,280.80 +/- 362.70

< 13.47 3,351.40 +/- 491.20

< 7.72 2,772.70 +/- 275.40

< 6.94 3,524.05 +/- 358.09

< 12.05 3,338.90 +/- 300.90

< 11.14 3,022.60 +/- 460.70

< 9.83 4,182.90 +/-530.70

< 7.83 3,616.55 +1-309.71

< 10.44

< 9.27

< 16.17

< 8.89

< 8.33

< 11.40

< 12.04

< 13.13

< 9.35

< 10.12

< 10.50

< 14.62

< 6.75

< 19.94

< 10.10

< 16.09

< 15.82

< 12.67

< 7.60

< 8.84

< 16.14

< 9.05

< 7.83

< 13.14

< 15.19

< 20.27

< 9.60

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Cs-134 C

1-131 K-40

.20 chinese cabbage 9/13/05

< 144.96

< 6.14

< 9.59

< 15.94

< 18.51 2,006.70 +/-311.10 20 collard grecns 9/13/05

< 130.68

< 11.23

< 13.26

< 14.75

< 19.67 4,084.00 +/- 434.40 20 swiss chard 9/13/05

< 144.62

< 10.23

< 12.82

< 19.09

< 19.79 4,972.50 +/- 560.20 20 chinese cabbage 10/12/05

< 161.59

< 11.79

< 13.19

< 13.17

< 23.34 3,010.70 +/- 405.50 20 collard grecns 10/12/05

< 172.57

< 9.25

< 15.18

< 15.36

< 27.32 3,932.90 +/- 445.90 20 swiss chard 10/12/05

< 165.65

< 7.38

< 7.87

< 12.33

< 18.25 3,746.50+/-458.10 U

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'-137 12.22 11.65 17.57 14.66 15.22 13.60 37 chinese cabbage 37 swiss chard 37 turnip greens 37 chinese cabbage 37 collard greens 37 swiss chard 6/28/05 6/28/05 6/28/05 7/12/05

'/i~iu 7/12/05

< 121.53

< 21.10

< 160.49

< 20.36 182.58 +/- 88.72

< 14.66

< 77.81

< 12.90 i6 iO5.29

< 12.07

< 188.72

< 18.95

< 5.68 3,981.10 +/- 369.90

< 16.23 6,083.30 +/- 619.30

< 13.83 5,819.90 +/- 424.70

< 14.51 3,482.30 +/- 509.80 22.J2 4,616.30 +/- 650.00

< 10.57 6,233.30 +/- 603.50

< 8.64

< 11.46

< 10.07

< 16.09

< 12.74

< 14.28

< 22.28

< 17.71

< 13.02 A.29

< 17.17

< 5.62

< 18.95

< 14.74

< 15.94 e 22.69

< 24.56

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Location Sample Type Collection Date 37 37 37 37 37 37 37 37 37 collard greens swiss chard turnip greens chinese cabbage collard greens turnip greens collard greens swiss chard turnip greens 8/9105 8/9/05 8/9/05 9/13/05 9/13/05 9/13/05 10/12/05 10/12/05 10/12/05

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< 156.05

< 20.46

< 12.85

< 21.10 3,953.40 +/- 587.20

< 191.46

< 15.89

< 17.63

< 14.78 7,058.30 +/- 655.80

< 198.20

< 19.93

< 10.59

< 28.14 5,829.30 +/- 683.50

< 115.00

< 6.17

< 9.62

< 17.09 3,543.00+/-384.30

< 165.21

< 18.17

< 14.54

23.96 4,523.00+/- 511.10

< 204.69

< 9.89

< 12.87

< 34.21 3,952.10 +/- 516.10

189.58

< 23.20

< 14.07

< 44.68 3,395.90 +/- 681.90

< 196.71

< 10.58

< 24.15

< 24.22 4,483.20 +/- 475.70 448.99 +/- 196.30

< 13.02

< 7.77

< 18.48 3,528.40 +/- 466.70 Cs-134 Cs-137

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< 13.85

< 20.97

< 18.92

< 9.29

< 14.40

< 15.78

< 19.32

< 18.06

< 12.91

< 16.00

< 23.33

< 19.34

< 13.49

< 12.66

< 17.25

< 17.87

< 20.85

< 20.26 70 chinese cabbage 70 70 swiss chard turnip greens 6/28/05 6/28/05 6/28/05 162.78 20.36 181.34 29.00 183.52 20.03

< :13.26 5,330.60 +/- 529.10

< 17.01 6,697.80 +/- 597.70

< 14.60 5,502.80 +/- 657.20

< 10.98

< 11.54

< 9.05

< 12.56

< 22.53

< 17.96

< 20.17

< 11.24

< 13.00

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Food Products Gamnina Spectral Detail Report 2005 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no. : 50-440/50-441 Sample Frequency is: Monthly Results in pCilkg wet +/- 2 Sigma Location oariiplcTypc Collection Date Bc-7 CO-S8 Co-f0 Cs-134 Cs-137 1-131 K-40 70 chinesecabbage 7/12/05

< 211.27

< 15.87

< 9.45

< 20.62

< 16.91

< 21.23 4,394.20 +/- 495.20 70 swiss chard 7/12/05

< 156.84

< 15.73

< 13.85

< 15.68

< 10.26

< 21.92 7,657.50 +/- 644.40 70 turnip greens 7/12/05

< 176.62

< 16.71

< 9.15

< 20.74

< 13.77

< 20.26 5,606.50 +/- 619.80 70 chinesc cabbagc 8/9/05

< 95.07

< 2.73

< 13.86

< 15.08

< 9.21

< 16.58 2,589.00 +/- 338.80 70 swiss chard 8/9/05

< 159.11

< 10.39

< 19.38

< 10.28

< 16.00

< 20.98 5,787.80 +/- 588.70 70 turnip greens 819105 502.63 +/-185.80

< 16.53

< 25.65

< 14.46

< 22.35

< 29.09 6,765.90 +/- 648.30 70 chinesc cabbage 9/13/05

< 137.33

< 6.41.

< 10.70

< 13.46

< 12.58

< 9.08 2,529.30 +/-318.00 70 collardgrcens 9/13/05

< 120.18

< 11.80

< 4.16

< 13.73

< 12.85

< 8.02 3,748.40 +/- 339.40 70 swiss chard 9/13/05

< 147.59

< 6.89

< 14.28

< 16.46

< 13.92

< 16.09 6,789.10 +/- 646.90 70 chincsc cabbage 10/12/05

< 171.95

< 9.45

< 13.22

< 15.35

< 11.78

< 15.39 2,079.90+/-402.90 70 collard greens 10/12/05

< 109.32

< 11.79

< 9.68

< 8.75

< 8.08 l.nA99 4,2A3.00 +!- ;? Rn 70 swiss chard 10/12/05

< 155.67

< 12.80

< 16.29

< 13.45

< 18.22

< 28.83 4,706.90 +/- 497.80

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Milk Gamma Spectral Detail Report 2005 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 Milk 4/18/05 5/2/05 5/16/05 6/6/05 6/20/05 7/5/05 7/18/05 8/1/05 8/15/05 9/6/05 9/20/05 10/3/05 1,496 +/- 171 1,464 +/- 122 1,694 +/- 121 1,498 +/- 185 1,778 +/- 134 1,784 +/- 176 1,625 +/- 116 1,670 +/- 130 1,633 +/- 134 1,699 +/- 167 1,683 +/- 168 1,789 +/- 195 S

< 5

< 2

< 9

< I

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< 2

< 6

< 5

< 3

< 4

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nollrtinnn fltp fln-140 Cq-134 Cs-137 K40 La-140 Loentinn Sam

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-I 41 M.ilk 41 Milk Milk Milk Milk Milk Milk Milk Milk Milk IVMilk Milk 1017/05 11/7/05 1/3/05 2/7/05 3/7/05 4/4/05 4/18/05 5/2105 5/16/05

< 13

< 17

< 12

< 14

< 9

< 20

< 19

< 25

< 32

< 21

< 36

< 5

< 7

< 5

< 4

< 3

< 2

< 5

< 4

< 3

< 5

< 6

< 4

< 3

< 4

< 5

< 4

< 5

< 3

.7

< 3 1,471 +/-119 1,596 +/- 185 1,338 +/- 120 1,285 +/- 94 1,276 +/- 122 1,312 +1-107 1,130 +/- 173 1,413 +/- 118 1,484 +/- 176 1,345 +/- 127

!,nE 1,395 +/- 114

< 7

< 6

< 2

< 3

< 5

< 2

< 6

< 3

< 8

< 5 6/6/05 7I5UIUJ 7/5/05

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)

J J I

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-51 Milk 7118/05

< 14

< 5

< 2 1.322 +/-115

< 4 51 51 51 51 51 51 51 51 61 61 61 Milk Milk Milk Milk Milk Milk Milk Milk 8/1/05 8/15/05 9/C/05 9/20/05 10/3/05 10/17/05 I 1/7/05 12/5/05

< 19

< 25

< 18

< 20

< 15

< 25

< 14

< 4

< 3

< 4

< 5

< 4

< 5

< 3

< 4

< 5

< 4

< 2

< 4

< 5 1,331 +/- 106 1,450 +/- 193 1,405 +/- 99 1,401 +/- 118 1,264 +/- 116 1,253 +/- 103 1,266 +/- 118 1,235 +/- 107

< 2

< 5

< 3

< 4

< 3

< 6

< I

< 8

< 2

< 7 Milk Milk Milk 4/18/05 5/2/05

< 20

< 25

< 29

< 4

< 5

< 3

< 4

< 3

< 5 1,640 +/- 138 1,652 +/- 123 1,641 +/- 203 5/16/05

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K-Milk Ganmha Spectral Detail Report 2005 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 T.nrtntinn Simnlc Tvnc I.

Collection Date Ba-140

. Cs-134 Cs-137 K-40 La-140 61 Milk 61 Milk 61 Milk 61 Milk 61 Milk 6/6/05 6/20/05 7/5/05 8/15/05 9/6/05

< 41

< 2..

.< 5

< 5

< 20 1,745 +/- 126 1,674 +/- 93 1,669 +/- 120

< 24

< 13

< 14

< 4

< 2 1,829 +/- 128

< 3 1,684 +/- 130 61 Milk 9/20/05

< 13

< 4 1,821 +/- 134

< 4

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Mlilk Iodine Detail Rcport 2005 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 41 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 61 61 61 61 61 61 61 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 4/18/05 5/2/05 5/16/05 6/6/05 6/20/05 7/5/05 7/18/05 8/1/05 8/15/05 9/6/05 9/20/05 10/3/05 10/17/05 11/7/05 1/3/05 2/7/05 3/7/05 4/4/05 4/18/05 5/2/05 5/16/05 6/6/05 6/20/05 7/5/05 7/18/05 8/1/05 8/15/05 9/6/05 9/20/05 10/3/05 10/17/05 11/7/05 12/5/05 4/18/05 5/2/05 5/16/05 6/6/05 6/20/05 7/5/05 7/18/05 1-131 0.34 0.22 0.21 0.23 0.25 0.23 0.20 0.22 0.26 0.25 0.27 0.36 0.29 0.24 0.19 0.16 0.34 0.25 0.36 0.24 0.24 0.24 0.26 0.25 0.21 0.25 0.36 0.35 0.27 0.23 0.33 0.33 0.21 0.37 0.26 0.26 0.22 0.23 0.25

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Radiological Environmental Monitoring Program Detail Data Perry Nuclcar Power Plant, Lake County Olio Docket no.: 50-440/50-441 Sample Frequency is: Bi-Monthly Results in pCi/L +/- 2 Sigma r- -

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Location Sample Type Collection Dat 1-131 VAl 61 61 61 61

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"- A Location Sample Type Collection Date

. Co-58 Co-60 Cs-134 Cs-137 K-40 25 Sediment 5/26/05

< 34.03

< 32.65

< 59.78 13516 +/-45.09 1,012.f00+/-959.40 25 Sediment 9/19/05

< 16.76

< 10.53

< 14.64 LLD 10,909.00 +/- 595.60 26 26 27 27 32 32 Sediment Sediment Sediment Sediment Sediment Sediment 5/26/05 9119/05 5/26/05 9/19/05 5/26/05 9/19/05

< 40.16

< 42.23

< 17.79

< 18.48

< 29.23

< 36.99

< 33.42 18.10

< 18.62

< 12.96

< 24.05

< 12.95

< 45.03

< 53.52

< 25.23 15.51

< 39.71

< 78.96 135.69 +/- 39.17 LLD 221.57 +/- 28.91 LLD 1,084.20 +/- 52.13 1,085.10 +/- 94.71 14,430.00 +/- 936.30 14,726.00 +/- 1,064.00 16,091.00 +/- 489.50 14,418.00 +/- 757.90 30,497.00 +/- 763.20 29,236.00 +/- 1,651.00 63 63 Sediment Sediment 5/27/05 9/19105

< 27.18

< 26.46

<. 28.02

< 21.32

< 37.17

< 37.97

< 23.03

< 21.95 9,826.10 +/- 762.60 8,929.80 +/- 716.30

t -- r:

i-c, r

Sedimcnt Gamma Spectral Dctail Report 2005 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 Sqnmnp Tuc

. rn1ler1tion Dlate Co-58 Co-60 Cs-134 Cs-137 K-40 64 Sediment 5/27/05

< 30.12

<.14.32

< 37.82

< 30.83 11,396.00+/- 899.80 64 Sediment 65 Scdiment 9/19/05 5/27/05

< 18.49

< 29.34

< 6.87

< 19.41

< 10.48

< 44.60

< 14.43

< 26.52 10,630.00 +/- 573.60 11,244.00 +/- 950.80 65 Sediment 9/19/05

< 15.00

< 9.01

< 14.04

< 13.98 9,765.80 +/- 541.70

_i J

r.

I 1

I

-- 1

]

I7

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_ J

__ J L2_j TLD Gamimia Dose Detail Rcport 2005 Radiological Environmental Monitoring Program Dctail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Quarterly Location Sample Type Collection Period Exposure I

TLD 1/5/05 to 4/5/05 10.61

+/-

1.14 I

TLD 4/5/05 to 7/7/05 10.56

+/-

0.84 I.

TLD 7/7/05 to 10/4/05 11.64

+/-

0.77

.1 TLD 10/4/05 to 1/6/06 11.45

+1-0.78 3

TLD 1/5/05 to 4/5/05 11.33

+/-

0.73 3

TLD 4/5/05 to 7/7/05 11.19

+/-

0.62 3

TLD 7/7/05 to 10/4/05 12.39

+/-

1.13 3

TLD 10/4/05 to 1/6/06 11.94

+/-

0.56 4

TLD 1/5/05 to 4/5/05 11.68

+/-

0.82 4

TLD 4/5/05 to 7/7/05 11.87

+/-

0.85 4

TLD 7/7/05 to 10/4/05 12.70

+/-

0.68 4

TLD 10/4/05 to 1/6/06 12.47

+/-

0.58 5

TLD 1/5/05 to 4/5/05 10.01

+/-

0.75 5

TLD 4/5/05 to 7/7/05 11.00

+/-

0.58 5

TLD 7/7/05 to 10/4/05 11.17

+/-

0.74 5

TLD 10/4/05 to 1/6/06 12.10

+/-

0.44 6

TLD 1/5/05 to 4/5/05 12.00

+/-

0.82 6

TLD 4/5/05 to 7/7/05 11.79

+/-

0.62 6

TLD 7/7/05 to 10/4/05 12.85

+/-

0.74 6

TLD 10/4/05 to 1/6/06 12.51

+/-

0.46 7

TLD 1/5/05 to 4/5/05 11.23

+/-

0.82 7

TLD 4/5/05 to 7/7/05 11.72

+/-

0.55 7

TLD 7/7/05 to 10/4/05 12.55

+/-

0.66 7

TLD 10/4/05 to 1/6/06 12.80

+/-

0.45 8

TLD 1/5/05 to 4/5/05 10.07

+/-

0.84 8

TLD 4/5/05 to 7/7/05 10.88

+/-

0.50 8

TLD 7/7/05 to 10/4/05 11.41

+/-

0.58 8

TLD 10/4/05 to 1/6/06 12.07

+/-

0.45 9

TLD 1/S/05 to 4/5/05 10.37

+/-

1.08 9

TLD 4/5/05 to 7/7/05 10.13

+/-

0.65 9

TLD 7/7/05 to 10/4/05 11.42

+/-

0.58 9

TLD 10/4/05 to 1/6/06 12.49

+/-

0.49 10 TLD 1/5/05 to 4/5/05 12.88

+/-

0.70 10 TLD 4/5/05 to 7/7/05 12.98

+/-

0.90 10 TLD 7/7/05 to 10/4/05 14.08

+/-

0.64

r0 r-0 rx-r r z ri.

r-:

u= r= r r-r-- r TLD Gamma Dosc Detail teport u2005 Radiological Environmcntal Monitoring Program Dctail Data Perry Nuclcar Power Plant, Lakc County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Quarterly r--

r t

r Ir z

Location Sample Type Collection Period Exposure 10 TLD 1Q0/4/05 to

!/6/06 14.34 41-

.567 11 11 11 11 12 12 12 12 i

13 13 13 13 I

14 14 14 14 15 15 15 15 21 21 21 21 23 23 23 23 24 24 24 24 TLD TLD TLD TLD 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 13.24 12.40 14.56 13.45 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 12.27 11.74 13.87 13.24 12.52 11.38 13.40 12.63 10.99 11.26 11.64 12.33

+1-

+1-0.81 0.65 0.58 0.42 0.87 0.95 0.73 0.48 0.69 0.80 0.70 0.71 0.76 0.68 0.68 0.51 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 10.83

+/-

0.84 7.49

+/-

0.70 11.48

+/-

0.67 8.97

+/-

0.53 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 TLD TLD TLD TLD

1/5/05

. 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 to 4i/505 to 7/7/05 to 10/4/05 to 1/6/06 14.06 13.61 14.93 14.79 14.81 13.86 15.67 14.90 i2.9; 12.23 12.79 13.16

-i/I-0.70 0.71 0.68 0.54 1.00 0.52 0.77 0.58 O.uS 0.92 0.59 0.52 TLD TLD TLD TLD Ui/S/O 4/5/05 7/7/05 10/4/05 29 TLD 29 TLD 1/5/05 to 4/5/05 16.07

+/-

0.87 4/5/05 to 7/7/05 15.87

+/-

0.62

J I

J-j -- j

-j j

J I

1

J I.]

_ J-TLD Gamma Dose Dctail Report 2005 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50440/50-441 Sample Frequency is: Quarterly i

Location Sample Type Collection Period Exposure

-.29 -inrr 7 '7/05 In 1

0AIA5/A 1'7.32)

+-

0o 29 I JL1I TLD 10/4/0 to 1/6l/0 1014105 to 116106

.16.90

+/-

0.52 0.52 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 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06

14.56 14.10 14.97 15.10 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 14.42 15.35 15.42 16.26 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 1 5.62 16.00 16.89 16.38 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 10.81 10.98 11.34 12.23 1.09 0.67 0.90 0.42 0.71 0.59 0.71 0.71 0.99 0.80 0.92 0.38 0.80 0.76 0.67 0.79 0.99 0.75 0.82 0.74 0.85 0.51 0.68 0.46 1.22 0.60 1.03 0.45 1.39 0.71 1.63 0.48 TLD TLD TLD TLD

1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 14.97 14.03 15.45 15.36 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 11.96 11.85 12.88 12.90 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 11.84 11.41 12.18 12.35 TLD TLD TLD TLD 1/5/05 4/5/05 7/7/05 10/4/05 to 4/5/05 to 7/7/05 to 10/4/05 to 1/6/06 12.64 12.46 14.17 13.43 56 TLD 1/5/05 to 4/5/05 12.93

+/-

0.75

U-FIT-r r

ED.

f r z j-rv r-rTm r

I ~TLD Gamma Dosc Dce~il Iteport 2005 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Dockct no.: 50-440/50-441 Sample Frcquency is: Quarterly F

17 Location.

Sample Type Collection Period Exposure 56 56 56

'VT re TLD TLD A/W5/0 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 11.90

+!-

0 79 13.48

+/-

1.06 12.91

+/-

0.60 58 58 58 58 TLD TLD TLD TLD 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 10.88

+/-

0.75 10.44

+/-

0.66 11.95

+/-

0.61 11.35

+/-

0.42

A

__J Ji TLD Gamma Dose Detail Report 2005 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Quarterly A

_ 1j

-J A

!1j

_J Location Sample Type Collection Period Exposure TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 9.61

+/-

0.85 10.46

+/-

0.67 10.78

+/-

1.06 10.87

+/-

0.71 TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 10.44

+/-

0.79 8.68

+/-

0.51 11.87

+/-

0.56 9.44

+/-

0.55 TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 10.64 12.20 12.28 13.18 TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 10.76 11.43 11.88 12.06 TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 10.77 11.66 11.52 11.69

+/-

+1-

+/-

+/..

+/-

0.58 0.59 0.40 1.13 0.56 0.55 0.46 0.53 0.77 0.53 0.68 0.46 0.58 0.86 0.48 0.82 0.61 0.56 0.66 0.39 TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 11.64 13.11 12.76 13.38 TLB TL13 TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 10.42 11.37 11.94 11.80 TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 9.97

+/-

0.56 10.69

+/-

0.46 11.14

+/-

0.62 11.90

+/-

0.54 10 10 10 10 TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 12.32 14.67 14.00 14.44

+l-

+l-/

+l-

+l-0.67 0.51 0.63 0.45

rz F EZ-r r

U TL -a'mmai7)os'c Dcfu itepolu05 F

F.

Z-C Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Quarterly r7i-r 'U -

Location Sample Type Collection Period Exposure I I

. 11 11 11

12 12 12 12 13 13 1 3 1 3 TLB TLB TLB TLB TLB TLB TLB TLB 1/5/05 to 4/5105 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 415105 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4105 to 1/6/06 115/05 to 415105 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4105 to 116106 10.33 13.38 12.15 13.59 11.78 12.55 13.66 13.01

-Il-0.59 0.63 0.65 0.45 0.55 0.54 0.51 0.59 0.62 0.60 0.59 0.83 TLB TLB TLB TLB 10.73 12.14 12.06 12.33 14 14 14 14 15 15 15 15 21 21 21 21 23 23 23

.23

.24 24 24 24 29 29 29 TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 8.92

+/-

0.68 11.47

+/-

0.64 10.25

+/-

0.60 11.83

+/-

0.53 8,59

+/-

.0.67 10.75

+/-

0.69 9.62

+/-

0.54 11.29

+/-

0.71 TLB TLB TLB TLB TLB TLB TLIB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 12.38 13.57 13.95 13.50 TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05

10/4/05 to 1/6/06 11.25 13.83 13.15 13.66 0.72 0.76 0.68 0.69 0.86 0.74 0.79 0.63 0.95 0.60 0.83 0.50 0.99 0.95 0.58 TLB TTR TLB TLB 1/5/05 to 4/5/05 A/5/05 tn 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 11.63 11.70 12.24 11.78 TLB TLB TLB

1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 14.50 16.99 16.86

_J

~J J

I IJ _.J Z

J IJ J

I

_J J

3 J

1 ~:'

-...TLD Ganima Dose Detail Report 2005 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Quarterly

-J Location Sample Type Collection Period Exposure 29 TLB 10/4/05 to 1/6/06 16.38

+/-

0.81 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 56 TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB TLB 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 15.07 17.37 17.06 16.96 14.31 15.59 15.98 15.35 10.61 11.64 11.65 11.62 13.57 14.64 14.93 14.26

+1-

+1-14.17 15.56 16.47 16.20 0.82 0.45 0.71 0.45 1.03 0.47 0.92 0.61 0.58 0.41 0.75 0.99 0.62 0.43 0.57 0.43 0.71 0.76 0.53 1.14 0.59 0.76 0.48 0.62 0.68 0.74 0.57 0.47 0.69 0.77 0.66 0.90 0.68 0.71 TLB TLB TLB TLB 11.74 13.23 13.41 13.22 TLB TLB TLB TLB 13.22 12.96 13.55 12.65 TLB TLB TLB TLB 12.31 13.49 13.57 13.43 TLB TLI3 12.85

+/-

12.07

+/-

x.

r -

Vr-E- r1 TLiWGaminm ooscDcI kt-i leporLtit5 F7' r

Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Quarterly r7 U

~ ri-rzrz]~_

Location Sample Type Collection Pcriod Exposure 6

56 58 58 58 58 TT l TLB TLB TLB TLB TLB 7/7/05 to 10/4/05 10/4/05 to 1/6/06 1/5/05 to 4/5/05 4/5/05 to 7/7/05 7/7/05 to 10/4/05 10/4/05 to 1/6/06 12.89

+/-

0.71 11.71

+/-

0.63 10.24

+/-

0.83 10.42

+/-

0.69 10.82

+/-

0.73 10.35

+/-

0.49

I

-J

.- J J

_ J, :__

L-L1 L~J

-7 L_

I TLD Gaxnuia Dose Detail Report 2005 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 mR1365 days +/- 2 Sigma A

IX

)

L--J

-Li Location 3

4 5

6 7

8 9

10 11 12 13 14 15 21 23 24 29 30 31 33 35 Sample Type TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA TLA Collection Period 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 Exposure 49.33

+1 47.57

+

59.99

+/

50.63

+/-

59.11

+/

58.82

+/-

57.73

+/

51.88

+/-

72.10

+/-

62.63

+1 60.27

+/-

57.27

+1 41.14

+/-

46.21

+/-

61.68

+/-

55.81

+/

48.47

+1 63.88

+1-62.69

+1-68.14

+/-

73.14

+

54.55

+

2.34 1.56 1.35 1.35 1.58 1.34 2.08 2.92 2.32 2.42 2.36 3.21 2.46 1.26 4.46 1.17 1.70 1.82 3.83 3.14 3.87 1.65

EL 17 7

I TLGmma Dose Dcil I(eportlU5 2

L5 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 mRI365 days +/- 2 Sigma Location Sample Type Collection Period Exposure 36 53 54 55 56 58 TLA TLA TLA TLA TLA TLA 1/5/05 to 1/6/06 115105 to 1/6106 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 1/5/05 to 1/6/06 73.90

+/-

1.96 58.61

+/-

2.97 59.99

+/-

4.57 58.14

+/-

5.06 57.50

+/-

3.33 47.52

+/-

1.36

J Ai J

J

-] -

I A

- - j J

I I

Water Gamnma Spectral Detail Rcport 2005 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Dockct no.: 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma 31

]

- 1J I

-i,.

Location Sample Type Collection Period Ba-140 Fe-59 Zr-95 Co-58 La-140 Co-60 Mn-54 Cs-134 Nb-95 Cs-137 Zn-65 28 Water 12/30/04 to 1/27/05

< 21.33

- < 6.30

< 6.54

< 3.02

< 3.80

< 1.52

< 3.56 Water Water Water Water Water Water Water Water Water Water Water 1/27/05 to 2/24/05 2/24/05 to 3/31/05

< 20.75

< 3.92

< 8.26

< 10.44

< 4.04

< 4.18

< 2.61

< 1.53 3/31/05 to 4/28/05

< 21.21

< 4.17

< 4.82 4/28/05 to 5/25/05

< 15.35

< 9.24

< 10.08 6/30/05 to 6/30/05

< 16.46

<. 4.57

< 3.11 6/30/05 to 7/28/05

< 16.23

< 9.29

< 3.37 7/28/05 to 8/24/05

< 18.60

< 7.90

< 8.48

< 2.63

< 6.24

< 3.30

< 4.40

< 2.76

< 3.30

< 3.75

< 4.87

< 4.44

< 3.50

< 4.91

< 2.51

< 2.02

< 2.24

< 1.50

< 2.48

< 2.88

< 2.84

< 2.33

< 1.67

< 3.98

< 5.18 1.11

< 2.24

< 2.18

< 4.75

< 3.44

< 3.83

< 5.30

< 3.98

< 2.64

< 2.80

< 3.40

< 4.10

< 2.79

< 3.17

< 2.83

< 3.47

< 3.15

< 3.80

< 2.88

< 2.54

< 3.04

< 3.71

< 3.03

< 4.61

< 3.79

< 4.11

< 4.44

< 2.83

< 4.55

< 4.89

< 4.17

< 3.95

< 3.53

< 3.45

< 3.06

< 4.56

< 5.12

< 4.37

< 2.22

< 3.88

< 1.41

< 6.82

< 3.36

< 2.71

< 2.38

< 4.24

< 4.77

< 7.30

< 3.34

< 2.84

< 3.85

< 3.73

< 3.47

< 5.92

< 4.16

< 6.67

< 3.32

< 3.85

< 2.49

< 3.05

< 4.60

< 6.80 8/24/05 to 9/28/05 9/28/05 to 10/27/05 10/27/05 to 11130/05 11/30/05 to 12/29/05

< 11.50

< 12.72

< 11.75

< 10.08

< 5.21

< 3.29

< 11.87

< 7.26

< 5.94

< 26.94

< 6.87

< 9.02

< 1.75

< 4.22

< 2.02

< 2.33

< 3.20

< 3.89

U-1-

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F7 JA rT Ii r-ri Water Gammiiia Spectral Detail Report 2005 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 oam 11c

.ri-;,.,-,

C t

Peri d ia-!40 C--58 C'.o-60 Cs-134 Cs-137 Fc-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 34 Water 12/30/04 to 1/27/05

< 9.40

< 1.53

< 1.49

< 4.21

< 3.47

< 5.38

< 3.93

< 2.88

< 2.39

< 2.44

< 2.59 34 34 34 34 Water Water Water Water 1/27/05 to 2/24/05

< 14.06

< 4.05

< 2.76

< 1.99

< 3.20 34 Water 2/24/05 to 3/31/05

< 14.56

< 6.34

< 6.67 3/31/05 to 4/28/05

< 22.92

< 8.04

< 10.83 5/25/05 to 5/25/05

< 14.37

< 5.76

< 3.47 5/25/05 to 6/30/05

<. 23.66

< 3.33

< 4.17 6/30/05 to 7/28/05

< 14.08

< 4.64

< 4.92 7/28/05 to 8/24/05

< 19.12

< 4.09

< 4.04 8/24/05 to 9/28/05

< 10.72

< 9.29

< 10.49

< 1.62

< 1.56

< 4.27

< 5.79

< 2.60

< 2.09

< 2.77

< 2.49

..<- 2.73

< 3.47

< 2.01

< 3.50

< 2.69

< 3.89

< 2.00

< 4.14 34 34 34 34 34 34 Water Water Water Water Water Water

< 1.77

< 3.01

< 2.53

< 2.52

< 4.19

< 4.37

< 1.46

< 2.46

< 2.89

< 4.00

< 3.28

< 2.15

< 2.58

< 1.87

< 4.08

< 3.89

< 1.86

< 1.98

< 2.20

< 1.77

< 2.76

< 1.62

< 2.06

< 3.63

< 3.87

< 3.61

< 3.82

< 3.09

< 3.16

< 3.73

< 3.14

< 2.62

< 2.87

< 3.31

< 2.43

< 3.85

< 4.12

< 2.88

< 2.89

< 2.98

< 2.93

< 2.38

< 3.21

< 2.82

< 2.23

< 3.28

< 3.41

< 3.60

< 4.93

< 1.60

< 2.89

< 2.33

< 5.82

< 4.43

< 2.57

< 3.48

< 6.30

< 3.95

< 4.86

< 2.03

< 3.14

< 2.16

< 3.12

< 2.36

< 2.00 9/28/05 to 10/27/05 10/27/05 to 11/30/05 11/30/05 to 12/29/05

< 11.86

< 5.30

< 4.94

< 9.02 1.37

< 2.74

< 18.15

< 4.63

< 5.68

< 1.32 e 1.71

< 2.41

< 2.95

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WVatcr Gamma Spcctral Dctail Report 2005 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 Typc Collection Period Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59

-. La-140 Mn-54 Nb-95 Zn-65 Zr-95 36 Water 12/30104 to 1/27/05

< 9.25

< 2.70

< 2.67

< 3.07

< 2.15

< 4.99

< 4.04

< 3.60

< 2.72

< 4.51

< 3.05 Water Water Water Water Water Water Water Water Water Water Water 1/27/05 to 2/24/05 2/24/05 to 3/31/05 3/31/05 to 4/28/05 4/28/05 to 5/25/05 5/25/05 to 6/30/05 6/30/05 to 7/28/05 7/28/05 to 8/24/05 8/24/05 to 9/28/05 9/28/05 to 10/27/05 10/27/05 to 11/30/05 11/30/05 to 12/29/05

< 9.86

< 2.50

< 5.14

.< 2.43

< 3.56

< 9.86

< 5.25

< 4.94

< 2.13

< 4.30

< 18.59

< 7.63

< 11.33

< 1.78

< 5.06

< 17.40

< 5.66

< 9.38

< 2.82

< 3.48

< 13.71

< 4.74

< 2.73

< 2.96

< 4.71

< 15.07

< 4.75

< 3.79

..< 2.74

< 1.54

< 3.18

< 2.81

< 1.48

< 2.50

< 4.41

< 2.43

< 2.20

< 2.39

< 2.57

< 3.06

< 2.56

< 3.14

< 1.94

< 5.83

< 2.99

< 1.18

< 2.19

< 4.78

< 2.06

< 3.03

< 3.65

< 3.02

< 2.93

< 4.45

< 2.16

< 3.23

< 4.47

< 4.06

< 2.12

< 4.83

< 3.10

< 2.32

< 4.00

< 3.24

< 4.00

< 2.31

< 2.82

< 2.25

< 4.58

< 4.96

< 3.76

< 4.13

< 3.73

< 3.98

< 1.76

< 4.81

< 2.80

< 6.76

< 2.68

< 5.88

< 2.71

< 2.76

< 3.28

< 5.21

< 3.84

< 8.16

< 5.63

< 7.08

< 3.18

< 3.62

< 5.50

< 6.02

< 3.09

< 5.02

< 3.39

< 2.46

< 18.72

< 5.39

< 7.10

< 3.83

< 5.12

< 12.70

< 4.84

< 6.69

< 3.20

< 3.68

< 30.19

< 4.68

< 11.61

< 2.30

< 4.83 10.00

< 4.97

< 6.10

< 1.16

< 2.60

< 13.77

< 4.43

< 5.24

< 4.15

< 2.29

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Water Gamma Spectral Dctail Report 2005 Radiological Environmcntal 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 Locat.n Samp-e Type Collrc ioC oerind 1T-140 Co-5g Co-60 Cs-134 Cs-137 Fc-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 59 Water 4/20/05 to 4/28/05

< 13.81

< 2.82

< 2.17

< 2.46

< 3.59

< 4.58

< 4.13

< 6.78

< 2.39

< 3.34

< 1.83 Water Water Water Watcr Water Watcr Water Water Water WY atel Watcr 4/28/05 to 5/25/05

< 13.30

< 6.24

< 4.54 5/25/05 to 6/30/05

< 35.59

< 9.33

< 6.36 6/30/05 to 7/28/05

< 18.02

< 5.79

< 5.80 7/28/05 to 8/24/05

< 13.50

< 3.49

< 5.15 8/24/05 to 9/28/05

< 17.04

< 3.39

< 5.72

< 2.80

<. 2.26

< 3.87

< 7.91

< 1.64

< 2.14

< 3.46

< 3.62

< 4.47

< 2.97

.< 3.53

< 5.36 9/28/05 to 10/27/05 10/27/05 to 11/30/05 4/20/05 to 4/28/05 4/28/05 to 5/25/05

2;/U5J iu Uf3i;VM 6/30/05 to 7/28/05

< 16.93

< 4.82

< 8.14

< 25.35

< 5.18

< 10.12

< 14.34

< 7.42

< 5.99

< 21.65

< 5.93

< 6.47

< 3.97

< 5.65

< 15.21

< 5.29

< 5.21

< 1.44

< 2.89

< 2.96

< 3.16

< 1.82

< 3.14

< 2.81

< 2.09

< 3.08

< 4.37

< 3.10

< 3.68

< 4.07

< 2.93

< 4.41

< 2.90

<.3.32

< 2.11

< INQ

< 3.28

< 2.93

< 2.18

< 5.10

< 4.25

< 2.86

< 2.40

< 3.88

< 4.66

< 2.47

< 2.03

< 3.74

< 2.71

< 4.72

< 3.38

< 4.08

< 4.23

< 4.10

< 2.94

< 2.38

< 3.95 3.1N

< 5.15

< 2.02

< 1.99

< 3.21

< 2.49

< 2.78

< 4.94

< 2.38

< 3.67

< 2.97

< 4.95

< 4.70

< 3.71

< 3.18

< 5.26

< 4.25

< 3.75

< 3.01

< 7.48

< 2.99

< 4.97

< 7 64

< 4.55

< 3.39

< 2.88

< 3.67

< 3.90

< 3.21

< 3.43

< 2.94

< 4.98

< 4.13

< 2.90

< 1.29

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Watcr Gamma Spectral Dctail Report 2005 Radiological Environmental Monitoring Program Detail Data Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50441 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 Fc-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 60 Water 7/28/05 to 8/24/05

< 15.11

< 2.07

< 2.24

< 2.28

< 3.53

< 3.43

< 5.79

< 3.27

< 2.31

< 3.95

< 5.07 60 60 60 Water Water Water 8/24/05 to 9/28/05 9/28/05 to 10/27/05 10/27/05 to 11/30/05

< 20.77

< 10.24

< 7.80

< 2.57

< 3.82

< 17.07

< 4.98

< 7.08

< 2.65

< 6.48

< 3.30

< 4.14

< 2.29

< 3.44

< 343

< 3.61

< 3.40

< 4.11

< 2.68

< 5.28

< 4.74

< 4.54

< 3.71

< 6.42

< 2.05

< 6.25

< 3.97

< 5.32

< 30.48

< 5.46

< 7.37

< 3.26

< 8.31

F_

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F 1-1F-Water Gross Bcta Dctail Rcport 2005 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 Fz]

r r

r-- r Collection Period 12/30/04 to 1/27/05 1/27/05 to 2/24/05 2/24/05 to 3/31/05 3/31/05 to 4/28/05 4/20/05 to 4/28/05 4/28/05 to 5/25/05 5/25/05 to 5/25/05 5/25/05 to 6/30/05 6/30/05 to 6/30/05 6/30/05 to 7/28/05 7/28/05 to 8/24/05 8/24/05 to 9/28/05 Sample Type Water Watcr Water Water Water Water Watcr Water Water Watcr Watcr Water 28 LLD LLD LLD LLD 34 LLD LLD LLD LLD 36 LLD LLD LLD LLD 59 60 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.10 +/- 0.63 LLD LLD LLD LLD

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-j Water Gross Beta Dctail Report 2005 Radiological Environmental Monitoring Program Data Summary Perry Nuclear Power Plant, Lake County Ohio Docket no.: 50-440/50-441 Sample Frequency is: Monthly Results in pCi/L +/- 2 Sigma Location 28 34 36 59 60 Collection Period Sample Type 9/28/05 to 10/27/05 Water LLD 3.01 +/- 0.45

.3.26 +/- 0.66 LLD LLD 10/27/05 to 11/30/05

.: Water 3.07 +/- 0.49

LLD -:

LLD 3.45 +/- 0.49 3.60 +/- 0.51 11/30/05 to 12/29/05

,; Water 1

oW3.59

+/- 0.74 LLD LLD

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F Water Tritium Detail Report 2005 Radiological Environmcntal Monitoring Program Dctail Data Pcrry Nuclear Power Plant, Lakc County Ohio Docket no.: 50-440150-441 Samplc Frequency is: Quartcrly Rcsults in pCi/L +/- 2 Sigma Location Sample Type Collection Date H-3 28 28 28 28 34 34 34 34 36 36 36 36 59 59 59 59 60 60 60 60 Water Water Water Water 3/31/05 6/30/05 9/28/05 12/29/05 Water Water Water Water 3/31/05 6/30/05 9/28/05 12/29/05 Water

. Water Water Water 3/31/05 6/30/05 9/28/05 12/29/05 LLD

< 164.66

< 176.96

< 183.93 LLD 164.66 LLD

< 183.93 143.95 164.66

< 176.96 183.93

< 164.66

< 176.96

< 184.75

< 164.66 LLD

< 184.75 Water Water Water Water 3/31/05 6/30/05 9/28/05 11/30/05 Water Water Water Water 3/31/05 6/30/05 9/28/05 11/30/05

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SUMMARY

SUMMARY

SUMMARY

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