Text

Annual Environmental and Effluent Release Report
	ML13123A209
Person / Time
Site:	Perry
Issue date:	04/30/2013
From:	; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	L-13-138
	Download: ML13123A209 (128)
	v • d • e

2012 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT for the Perry Nuclear Power Plant PREPARED BY:

CHEMISTRY SECTION PERRY NUCLEAR POWER PLANT FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY, OHIO APRIL, 2013

2012 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT for the Perry Nuclear Power Plant PREPARED BY:

CHEMISTRY SECTION PERRY NUCLEAR POWER PLANT FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY, OHIO APRIL, 2013

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT TABLE OF CONTENTS EX EC UT IVE S UMMA RY ..................................................................................................... 1 Radioactive Effluent Releases ................................................................................................... 1 Radiological Environm ental Monitoring .............................................................................. 2 Land Use Census ........................................................................................................ ..... 2 C lam /Mussel Monitoring ......................................................................................................... 3 Herbicide Use ............................................................................................................................... 3 Special Reports ............................................................................................................................ 3 INT RO D UC T IO N........................................................................................................... 4 Radiation Fundam entals ....................................................................................................... 4 Radiation and Radioactivity .................................................................................................. 4 Units of Measure .......................................................................................................................... 5 Lower Lim it of Detection ......................................................................................................... 6 Background radiation .............................................................................................................. 6 RA D IOA C TIV E EFFLU ENT R ELEAS ES ...................................................................... 8 Introduction ................................................................................................................................... 8 Regulatory Lim its ......................................................................................................................... 8 Release Sum m ary ................................................................................................................. 10 Meteorological Data ............................................................................................................... 17 Dose Assessm ent ...................................................................................................................... 17 Carbon-14 Supplem ental Inform ation ................................................................................. 21 O n-Site G roundwater Monitoring Program ...................................................................... 22 Corrections to Previous Annual Environmental and Effluent Release Reports .......... 26 Abnorm al Releases .............................................................................................................. 26 O DC M Non-Com pliances .................................................................................................... 26 O ffsite Dose Calculation Manual Changes ....................................................................... 26 Process Control Program Changes ................................................................................... 26 RADIOLOGICAL ENVIRONMENTAL MONITORING ............................................... 27 Introduction ................................................................................................................................. 27 Sam pling Locations .............................................................................................................. 27 Sam ple Analysis ......................................................................................................................... 32 2012 Sam pling Program ....................................................................................................... 33 Inter-Laboratory C ross-Check Com parison Program ...................................................... 40 Land Use Census ...................................................................................................................... 41 Northwest Drain Impoundm ent ........................................................................................... 44 C LA M/MUSS EL MO NITO R ING .................................................................................... 45 Introduction ................................................................................................................................. 45 Corbicula Program ................................................................................................................. 45 Dreissena Program ............................................................................................................... 46 HER B IC IDE A PPLIC AT IO NS ........................................................................................ 47 S PEC IAL R EPO RTS ...................................................................................................... 48 Non-Com pliances ...................................................................................................................... 48 Un-Reviewed Environm ental Q uestions ............................................................................ 48 Table of Contents Page i

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I APPENDICES Appendix A: 2012 Inter-Laboratory Cross Check Comparison Program Results U

Appendix B: 2012 REMP Data Summary Reports Appendix C: 2012 REMP Detailed Data Report I

Appendix D: Corrections to Previous AEERR Appendix E: Abnormal Releases Appendix F: ODCM Non-Compliances I Appendix G: Changes to the Process Control Program I

Table of Contents Page ii a

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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, 2012. This report meets all of the requirements in PNPP Technical Specifications, the Offsite Dose Calculation Manual, 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 2012 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 2.67E-03 mrem (0.089% of the applicable limit). The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents (excluding C-1 4) for 2012 was 5.96E-02 mrem (1.2% of the applicable limit).

In 2012, radioactivity released to the environment in the form of gaseous Carbon-14 (C-14) was estimated based on plant type and power production. This is based on an industry initiative supported by the Nuclear Energy Institute (NEI) and the NRC. The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents for 2012, including C-14 is 2.54E-01 mrem. Refer to page 21 for additional Carbon-14 information.

The summation of the hypothetical maximum individual dose from effluents in 2012 is less than 1 % of the total dose an individual living in the PNPP area receives from all sources of manmade and background 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 2012, making shipments of solid radioactive waste to a licensed burial site.

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

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

The REMP was established at PNPP six (6) years before the plant became operational.

This pre-operational program was designed to provide data on background radiation and radioactivity normally present in the area. PNPP has continued to monitor the environment during plant operation by collecting and analyzing samples of air, precipitation, milk, fish, produce, water and sediment, as well as by measuring radiation directly. The results of the REMP program indicate adequate control of radioactivity released from PNPP plant effluents. These results also demonstrate that PNPP complies with applicable federal regulations. The REMP results are divided into four sections: atmospheric monitoring, terrestrial monitoring, aquatic monitoring, and direct radiation monitoring.

Air samples were collected to monitor the radioactivity in the atmosphere; the results were similar to those observed for the pre-operational and operational programs from prior years.

Terrestrial monitoring included the analysis of milk and produce; the results indicated concentrations of radioactivity similar to that found in previous years. Analyses of produce samples detected only natural radioactivity similar to those observed in previous years, and indicated no build-up of radioactivity attributable to the operation of PNPP.

Aquatic monitoring included the collection and analyses of water, fish, and shoreline sediments. The 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 eight (8) of the twelve (12) samples collected. The average cesium-1 37 radioactivity for all locations was 217.7 pCi/kg and is lower than the highest identified value of 864 pCi/kg established in 1981.

In 1999, a sediment sample of the Northwest Drain Impoundment (sampling location #64) was analyzed to contain 62 pCi/kg of cobalt-60. Enhanced monitoring activities continued within the boundaries of the impoundment for 2011. The cobalt-60 remains centered within the organic material located at the top of the spillway, with little or no activity found farther upstream. Sample analyses continue to identify cobalt-60 levels similar to those found in previous years. Refer to Table 20 for detailed sample results.

Direct radiation measurements showed no real change from previous years. The indicator locations averaged 64.9 mrem/year and control locations averaged 61.3 mrem/year. In 2012, 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 2012, 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.

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT During the census, PNPP personnel travel public roads 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 ten meteorological land sectors that surround the plant. The information obtained from the census is entered into a computer program, which is used to assess the hypothetical dose to members of the public.

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

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

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

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

There was one report submitted in 2012:

On May 6, 2012, during daily chlorination activities, it was identified that the NPDES permit limit for Total Residual Chlorine was exceeded between 0935 and 0947 hours0.011 days 0.263 hours 0.00157 weeks 3.603335e-4 months . The maximum measured value was 0.29 mg/I, which exceeded the NPDES Maximum Concentration limit of 0.2 mg/l.

On May 6, 2012 at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months , a "Non-compliance Notification for Exceedance of a Daily Maximum Discharge Limit" was made to the Ohio Environmental Protection Agency.

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

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

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

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

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

Alpha Particles Alpha particles consist of two protons and two neutrons and have a positive charge.

Because of their charge and large size, alpha particles do not travel very far when released (less than 4 inches, in air). They are unable to penetrate any solid material, such as paper or skin, to any significant depth. However, if alpha particles are released inside the body, Page 4

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT they can damage the soft internal tissues because they deposit all their energy in a small area.

Beta Particles Beta particles are essentially free electrons, which usually carry a negative electrical charge. They are much smaller than alpha particles and travel at nearly the speed of light.

Thus they can travel for longer distances than alpha particles. External beta radiation primarily affects the skin. Because of their electrical charge, paper, plastic or thin metals can stop beta particles.

Gamma Rays Gamma rays are bundles of electromagnetic energy, called photons, which behave as though they were particles. They are similar to visible light, but of a much higher energy.

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

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

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

Activity Activity is the number of atoms in a material that decay per unit of time. Each time an atom decays, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms are decaying. One curie of activity indicates the decay of 37 billion atoms per second. Smaller units of the curie are often used in this report. Two common units are the microcurie (pCi), one millionth of a curie, and the picocurie (pCi), one trillionth of a curie. The mass, or weight, of radioactive material, which would result in one (1) curie of activity, depends on the disintegration rate.

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 Page 5

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose (as measured in rads),

the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any type of ionizing radiation. The dose equivalent is measured in terms of the Roentgen Equivalent Man (rem). When discussing environmental radiation effects, the rem is a large unit. Therefore, a smaller unit, the millirem (mrem) is often used.

One mrem is equivalent to 1/1000 of a rem.

LOWER LIMIT OF DETECTION Sample results are often reported as below the Lower Limit of Detection (LLD). The LLD for an analysis is the smallest amount of radioactive material that will show a positive result for which there can be a 95% confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample analysis. When a measurement is reported as less than the LLD (<LLD), it means that no radioactivity was detected. Had radioactivity been present at (or above) the stated LLD value, it statistically would have been detected. The NRC has established LLD values for environmental and effluent sample analyses.

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].

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Internal Terrestial 10.94%

75edica/X-Ray Nuclear Fuel Cycle 0.09%

Cosmic Nuclear Medicine Consumer Products Ilaneous 2.80 Fall-Out )/

S- Ot herr0.26%

0.75%

Occupational Sources 0.30%/6 Radon 54.69%

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

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

Potassium-40, a naturally occurring radionuclide normally found in humans and throughout the environment, and

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

Beryllium-7 and potassium-40 are especially common in REMP samples. Since they are naturally occurring and are expected to be present, positive results for these radionuclides are not discussed in the section for the 2012 Sampling Program results. These radionuclides are included; however, in Appendix A, 2012 Inter-Laboratory Cross Check Comparison Program Results.

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT RADIOACTIVE EFFLUENT RELEASES INTRODUCTION 3 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 generatedI remain within the nuclear fuel pellet and fuel cladding. Most fission products that escape from the fuel cladding, as well as the majority of the activated corrosion products, are removed by plant processing equipment.

During the normal operation of a nuclear power plant, small amounts of radioactive material are released in the form of solids, liquids, and gases. PNPP was designed, and is operated in such a manner as to control and monitor these effluent releases. Effluents are controlled to ensure any radioactivity released to the environment is minimal and within regulatory I

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 theI plant control room. The alarms are set to provide warnings to alert plant operators when radioactivity levels reach a small fraction of actual limits. The waste streams are sampled and analyzed to identify and quantify the radionuclides being released to the environment.i Gaseous effluent release data is coupled with on-site meteorological data in order to calculate the dose to the general public. Devices are maintained at various locations around PNPP to constantly sample the air in the surrounding environment. Frequent samples of other environmental media are also taken to determine if any radioactive I

material deposition has occurred. The Radiological Environmental Monitoring Program (REMP) is described in detail later in this report.

Generation of solid waste is carefully monitored to identify opportunities for minimization.

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

'I REGULATORY LIMITS The Nuclear Regulatory Commission has established limits for liquid and gaseous effluents that comply with: I Title 10 of the Code of Federal Regulations, Part 20 (Standards for Protection Against Radiation) [10CFR20], Appendix B; U Title 10 of the Code of Federal Regulations, Part 50 (Domestic Licensing of Production and Utilization Facilities) [10CFR50], Appendix I; and Title 40 of the Code of Federal Regulations, Part 190 (Environmental Radiation i Protection Standards for Nuclear Power Plants) [40CFR1 90].

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT These limits were incorporated into the PNPP Technical Specifications, and subsequently into the PNPP Offsite Dose Calculation Manual (ODCM). The ODCM prescribes the maximum doses and dose rates due to radioactive effluents resulting from the operation of PNPP. These limits are defined in several ways to limit the overall impact on persons living near the plant. Since there are no other fuel sources near the PNPP, the 40CFR1 90 limits, which are described below, were not exceeded in 2012.

The 40CFR1 90 limit for whole body dose is 25 mrem. For 2012, the total whole body dose to a member of the general public, considering all sectors, was 2.54E-01 millirems. This value was determined by summing the annual whole body doses from liquid and gaseous radioactive effluents and the annual gaseous Carbon-14 dose. Since the direct radiation dose, as determined by TLD, was indistinguishable from natural background (see Figure 9),

it was not included in the calculation.

Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases, as required by the ODCM.

For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-04 gCi/mI of total activity. These values are the maximum effluent concentrations.

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

During any calendar quarter:

Less than or equal to 1.5 mrem to the whole body, and Less than or equal to 5 mrem to any organ During any calendar year:

Less than or equal to 3 mrem to the whole body, and Less than or equal to 10 mrem to any organ Gaseous Effluents Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

Noble gases:

Less than or equal to 500 mrem per year to the whole body, and Less than or equal to 3000 mrem per year to any organ Iodine-1 31, Iodine-1 33, Tritium, and all radionuclides in particulate form with half lives greater than eight days:

Less than or equal to 1500 mrem per year to any organ Air dose due 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:

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Less than or equal to 10 mrad for gamma radiation, and Less than or equal to 20 mrad for beta radiation Dose to a member of the public from Iodine-1 31, Iodine-1 33, Tritium, and all radionuclides in particulate form with half lives greater than eight days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 7.5 mrem to any organ per any calendar quarter, and Less than or equal to 15 mrem to any organ per any calendar year The PNPP ODCM does not contain a concentration limit for gaseous effluents. For this reason, effluent concentrations are not used to calculate maximum release rates for gaseous effluents.

RELEASE

SUMMARY

Effluents are sampled and analyzed to identify both the type and quantity of radionuclides present. This information is combined with effluent path flow measurements to determine the composition, concentration, and dose contribution of the radioactive effluents.

Liquid Effluents The PNPP liquid radioactive waste system is designed to collect and treat all radioactive liquid waste produced in the plant. The treatment process used for radioactive liquid waste depends on its physical and chemical properties. It is designed to reduce the concentration of radioactive material in the liquid by filtration to remove suspended solids and demineralization to remove dissolved solids. Normally, the effluent from the liquid radioactive waste system is returned to plant systems. To reduce the volume of water stored in plant systems; however, the processed liquid effluent may be discharged from the plant via a controlled release. In this case, effluent activity and dose calculations are performed prior to, and after discharging this processed water to Lake Erie to ensure regulatory compliance and dose minimization principals are maintained.

Liquid radioactive waste system effluents may be intermittently released, which are considered to be "batch" releases. Table 1 provides information on the number and duration of these releases for 2012.

Table 1: Liquid Batch Releases QUARTER 1

QUARTER 2

QUARTER 3

QUARTER 4

U Number of batch releases 23 19 39 7 Total time period for batch releases, min Maximum time for a batch release, min 5.17E+03 2.42E+02 3.40E+03 2.31 E+02 8.84E+03 2.51 E+02 2.16E+03 4.58E+02 U

Average time period for a batch release, min 2.25E+02 1.79E+02 2.27E+02 3.09E+02 Minimum time for a batch release, min Average stream flow during periods of effluent 2.15E+02 1.21 E+05 2.OOE+00 2.35E+05 2.21 E+02 2.16E+05 2.07E+02 1.68E+05 U

release into a flowing stream, L/min U

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

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

1 2 3 4 TOTAL ERROR,

_______ __ ___ _ __ ___ (%)

A. Fission and Activation Products

1. Total Released, Ci 1.24E-02 5.64E-03 4.27E-03 1.06E-02 1.OOE+01 (excluding tritium, gases, alpha)

2. Average Diluted Concentration, 7.52E-10 2.05E-10 1.47E-10 5.87E-10 iCi/mL *

3. Percent of Applicable Limit, % 1.94E-02 5.72E-03 3.90E-03 1.74E-02 B. Tritium

1. Total Released, Ci 4.52E+00 4.25E+00 1.17E+01 2.66E+00 1.OOE+01

2. Average Diluted Concentration, 2.74E-07 1.54E-07 4.02E-07 1.47E-07 pCi/mL

3. Percent of Applicable Limit, % 2.74E-02 1.54E-02 4.02E-02 1.47E-02 C. Dissolved and Entrained Gases

1. Total Released, Ci 6.93E-07 1.72E-04 4.90E-06 <LLD 1.OOE+01

2. Average Diluted Concentration, 4.20E-14 6.25E-12 1.68E-13 NA p*Ci/mL

3. Percent of Applicable Limit, % 2.1OE-08 3.12E-06 8.42E-08 NA D. Gross Alpha Activity, Ci <LLD <LLD <LLD <LLD 1.OOE+01 E. Waste Volume Released, Liters (prior to 4.50E+06 3.62E+06 7.36E+06 2.15E+06 dilution)

F. Dilution Water Volume Used, Liters 1.65E+10 2.75E+10 2.91E+10 1.81E+10

<LLD - Less than the lower limit of detection

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

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

QUARTER 1

QUARTER 2

QUARTER 3

QUARTER 4

EST.

TOTAL ERROR, I

(%)

A. Fission and Activation Products B.

Total Released, Ci (excluding tritium, gases, alpha)

Tritium 1.05E-02 3.28E-03 3.08E-03 9.89E-03 1.OOE+01 I

Total Released, Ci 4.49E+00 4.25E+00 1.17E+01 2.66E+00 1.00E+01 C. Dissolved and Entrained Gases Total Released, Ci <LLD 1.72E-04 <LLD <LLD 1.OOE+01 D. Gross Alpha Activity, Ci <LLD <LLD <LLD <LLD 1.OoE+01 E. Waste Volume Released, Liters (prior to 2.99E+06 1.70E+06 4.86E+06 1.38E+06 NA dilution)

<LLD - Less than the lower limit of detection I Table 2b: Summation of Continuous Liquid Effluent Releases QUARTER 1

QUARTER 2

QUARTER 3

QUARTER 4

EST.

TOTAL ERROR,

(%)

I A. Fission and Activation Products Total Released, Ci (excluding tritium, gases, alpha) 1.86E-03 2.35E-03 1.20E-03 6.89E-04 1.OOE+01 I B. Tritium C.

Total Released, Ci Dissolved and Entrained Gases 3.28E-02 5.49E-03 6.22E-03 4.69E-03 1.OOE+01 I Total Released, Ci D. Gross Alpha Activity, Ci E. Waste Volume Released, Liters (prior to 6.93E-07

<LLD 1.51E+06 6.1OE-08

<LLD 1.92E+06 4.90E-06

<LLD 2.51 E+06

<LLD

<LLD 7.62E+05 1.OOE+01 1.OOE+01 NA I

dilution)

<LLD - Less than the lower limit of detection I

i I

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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 3 lists the total number of curies (Ci) of each radionuclide present in liquid effluent releases for each quarter. Ifa radionuclide was not present at a level "greater than or equal to the LLD" (Ž>LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, the LLDs were either met, or were below the levels required by the ODCM.

Table 3: Radioactive Liquid Effluent Nuclide Composition QUARTER QUARTER QUARTER QUARTER UNITS 1 2 3 4 Tritium Ci 4.52E+00 4.25E+00 1.17E+01 2.66E+00 Sodium-24 Ci 3.91 E-04 9.57E-05 2.68E-04 1.74E-04 Chromium-51 Ci 5.47E-04 1.39E-04 2.19E-05 6.70E-05 Manganese-54 Ci 7.98E-04 3.55E-04 2.74E-04 8.11 E-04 Manganese-56 Ci 1.20E-05 1.76E-06 1.81 E-05 4.28E-06 Iron-59 Ci 5.92E-06 3.59E-06 1.08E-06 3.23E-06 Cobalt-58 Ci 3.81 E-04 2.63E-04 4.12E-05 4.60E-05 Cobalt-60 Ci 8.68E-03 4.45E-03 3.1OE-03 9.18E-03 Zinc-65 Ci 9.20E-04 2.70E-04 9.15E-06 1.79E-04 Zinc-69M Ci 4.71 E-07 <LLD <LLD <LLD Strontium-92 Ci <LLD 2.57E-07 5.21 E-05 <LLD Niobium-95 Ci <LLD 4.71 E-07 <LLD <LLD Yttrium-95m Ci <LLD <LLD 4.41 E-07 <LLD Technetium-99m Ci <LLD 5.05E-08 1.86E-07 <LLD Silver- 110m Ci 2.55E-04 5.19E-05 4.92E-04 1.13E-04 Antimony-124 Ci 8.19E-05 <LLD <LLD <LLD Antimony-125 Ci 2.93E-04 <LLD <LLD <LLD Xenon-133 Ci <LLD 1.72E-04 3.66E-06 <LLD Xenon-135 Ci 6.93E-07 6.1OE-08 1.24E-06 <LLD Cesium-1 37 Ci 8.75E-06 <LLD <LLD 1.55E-08 Gold-199 Ci 2.09E-05 <LLD 5.32E-07 1.60E-06

-LLD - Less than the lower limit of detection Page 13

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I

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 I

purge operations, small steam leaks, and offgas system operation. The iodine and particulate releases are primarily a result of small steam leaks. Gaseous effluents from PNPP exit the plant via one of four effluent vents. Each of these four effluent vents contains radiation detectors that continuously monitor the air to ensure that the levels of radioactivity released are below regulatory limits. Samples are also collected and analyzed on a periodic basis to ensure regulatory compliance and dose minimization principals are I

maintained. The majority of gaseous effluents released from PNPP are considered continuous and at ground level.

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

met or were below the levels required by the PNPP ODCM.

Discussion of Carbon-14 doses is listed on page 21, Carbon-14 supplemental information.

i 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 1.84E-01 1.OOE+02 2.05E+00 7.54E-01 1.OOE+01

2. Average Release Rate, j.Ci/sec 2.34E-02 1.28E+01 2.58E-01 9.49E-02 3.

B. Iodine Percent of Applicable Limit, %

1. Total Iodine-131 Released, Ci N/A 2.37E-06 N/A 5.74E-05 N/A

<LLD N/A

<LLD 1.00E+01 I

2.

3.

Average Release Rate, j.Ci/sec Percent of Applicable Limit, %

C. Particulates with Half-Lives > 8 days 3.02E-07 N/A 7.30E-06 N/A

<LLD N/A

<LLD N/A I

1. Total Released, Ci 4.78E-08 1.43E-05 <LLD <LLD 1.OOE+01

2. Average Release Rate, Cici/sec

3. Percent of Applicable Limit, %

6.08E-09 N/A 1.81 E-06 N/A

<LLD N/A

<LLD N/A I

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

1. Total Released, Ci <LLD <LLD 9.77E-01 2.63E+00 1.OOE+01 I

2. Average Release Rate, g.Ci/sec <LLD <LLD 1.23E-01 3.31 E-01

3. Percent of Applicable Limit, %

F. Carbon-14, Ci N/A 4.55 N/A 4.52 N/A 4.78 N/A 4.78 1.OOE+01 I

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

I The radionuclide composition of all gaseous radioactive effluents for a continuous-mode, ground-level release is given in Table 5. If a radionuclide was not present at a level "greater than or equal to the LLD" (_>LLD), then the value is expressed as "less than the i

LLD" (<LLD). In each case, LLDs were met or were below the levels required by the ODCM.

Page 14 I

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 5: Radioactive Gaseous Effluent Nuclide Composition UNIT QUARTER QUARTER QUARTER QUARTER I 1 1 2 3 4 A. FISSION AND ACTIVATION PRODUCTS Tritium Ci <LLD <LLD 9.77E-01 2.63E+00 Argon-41 Ci <LLD <LLD <LLD <LLD Krypton-85m Ci <LLD 5.11E-01 1.31 E-01 3.62E-02 Krypton-85 Ci <LLD <LLD <LLD 3.23E-03 Kryton-87 Ci <LLD 1.18E-01 <LLD <LLD Krypton-88 Ci <LLD 5.57E-01 <LLD <LLD Xenon-1 31m Ci <LLD <LLD <LLD <LLD Xenon-133m Ci <LLD 1.19E+00 <LLD <LLD Xenon-133 Ci <LLD 8.53E+01 4.99E-02 1.30E-01 Xenon-135m Ci <LLD 2.15E+00 <LLD <LLD Xenon-1 35 Ci <LLD 1.03E+01 1.87E+00 5.85E-01 Xenon-1 37 Ci <LLD <LLD <LLD <LLD Xenon-138 Ci 1.84E-01 2.82E-01 <LLD <LLD Total for Period 1.84E-01 1 .OOE+02 3.03E+00 3.38E+00 B. IODINE Iodine-131 Ci 2.37E-06 5.74E-05 <LLD <LLD Iodine-1 32 Ci <LLD <LLD <LLD <LLD Iodine-1 33 Ci <LLD 6.74E-05 <LLD <LLD Iodine-134 Ci <LLD <LLD <LLD <LLD Iodine-135 Ci <LLD <LLD <LLD <LLD Total for Period 2.37E-06 1.25E-04 <LLD <LLD C. PARTICULATE Chromium-51 Ci <LLD <LLD <LLD <LLD Manganese-54 Ci <LLD <LLD <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-58 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD <LLD <LLD <LLD Zinc-65 Ci <LLD <LLD <LLD <LLD Rubidium-88 Ci <LLD <LLD <LLD <LLD Rubidium-89 Ci <LLD <LLD <LLD <LLD Strontium-89 Ci 4.78E-08 7.42E-07 <LLD <LLD Strontium-90 Ci <LLD <LLD <LLD <LLD Yttrium-91m Ci <LLD <LLD <LLD <LLD Strontium-92 Ci <LLD <LLD <LLD <LLD Zirconium-95 Ci <LLD <LLD <LLD <LLD Molybdenum-99 Ci <LLD <LLD <LLD <LLD Cesium-137 Ci <LLD <LLD <LLD <LLD Cesium-138 Ci <LLD 1.35E-05 <LLD <LLD Barium-139 Ci <LLD <LLD <LLD <LLD Barium-140 Ci <LLD <LLD <LLD <LLD Lanthanum-140 Ci <LLD <LLD <LLD <LLD Total for Period 4.78E-08 1.43E-05 <LLD <LLD

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

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Solid Waste All solid radioactive waste from PNPP was processed and combined with waste from I

several other utilities by intermediate vendors (Energy Solutions, Duratek in Oak Ridge, TN and Studsvik, in Erwin, TN). This waste was ultimately sent to Clive, Utah disposal facilities for burial. The solid radioactive waste summary in Table 6 includes all PNPP shipments for 2012. I Table 6: Solid Waste Shipped Offsite for Burial or Disposal A. TYPE OF SOLID WASTE SHIPPED I

VOLUME ACTIVITY EST. TOTAL 3

(M ) (CI) ERROR (%)

Resins, Filters and Evaporator Bottoms 1.1 7E+02 2.78E+02 +/- 25 Dry Active Waste Irradiated components, control rods, etc.

1.86E+03 0.OOE+00 4.45E-01 0.OOE+00

+/- 25

+/- 25 I

Other Waste 0.OOE+00 0.OOE+00 +/- 25 B.

TYPE OF WASTE) 1 ESTIMATE OF MAJOR" ) NUCLIDE COMPOSITION (BY Resins, Filters and Evaporator Bottoms RADIONUCLIDE Fe-55 ABUNDANCE

(%)

31.49 EST. TOTAL ERROR, (%)

+/- 25 I

Co-60 Ni-63 Cs-1 37 62.42 2.12 2.32 I

Dry Active Waste H-3 Mn-54 Fe-55 1.60 6.52 26.64

+/- 25 I

Co-60 62.89 Irradiated Components, Control Rods, etc.

Ni-63 None 1.02 0

I Other Waste None 0 C. DISPOSITION NUMBER OF MODE OF TRANSPORTATION DESTINATION I

SHIPMENTS Solid Waste(2)

Solid Waste(2) 26 41 Public Highway Public Highway Studsvik, Erwin, TN Energy Solutions, Bear I

Creek, TN N/A -- Not Applicable

( 1 ) -- "Major"is defined as any individualradionuclide identifiedas > 1%of the waste type abundance.

I

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

I Page 16

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

A detailed report of the monthly and annual operation of the PNPP Meteorological Monitoring Program is produced under separate cover. For the period of January 1, 2012 through December 31, 2012, the report substantiates the quality and quantity of meteorological data collected in accordance with applicable regulatory guidance.

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

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

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

Page 17

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I

Table 7: Maximum Individual Site Boundary Dose, Considering All Sectors TYPE OF DOSE ORGAN ESTIMATED DOSE, (MREM)

LIMIT % OF LIMIT I Liquid Effluent Whole body 2.67E-03 3.OE+00 8.9E-02 Noble Gas gamma air beta air Liver N/A N/A 3.77E-03 9.87E-02 1.77E-01 1.OE+01 1.OE+01 2.OE+01 3.8E-02 9.9E-01 8.9E-01 I

Noble Gas Whole body 5.96E-02 5.OE+00 1.2E+00 Skin 1.48E-01 1.5E+01 9.8E-01 Particulate & Iodine Thyroid 2.65E-03 1.5E+01 1.8E-02 The calculated hypothetical, maximum 50-mile radius population dose values at the site I

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

Liquid Effluent Whole body Thyroid 3.5E-01 1.9E-01 I

Gaseous Effluent Whole body 1.5E-03 Thyroid 1.5E-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 I

greater than the LLD, it was not used in the dose calculations.

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

TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT % OF Liquid Effluent Whole Body (MREM) 2.67E-03 3.OE+00 LIMIT 8.9E-02 I

Liver 3.77E-03 1.OE+01 3.8E-02 Noble Gas -

gamma air beta air N/A N/A 1.55E-03 2.69E-03 1.OE+01 2.0E+01 1.6E-02 1.3E-02 I

Noble Gas Whole Body 5.04E-04 5.OE+00 1.OE-02 Particulate & Iodine Skin Thyroid 1.23E-03 1.94E-04 1.5E+01 1.5E+01 8.2E-03 1.3E-03 I

Carbon-14* Whole Body 2.54E-01 5.OE+00 5.1 E+00

C-14 Dose calculated at nearest garden.

I!

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 I maximum dose during the time spent inside site boundary. Because no one actually meets Page 18 I

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT the criteria established for these conservative calculations, the actual dose received by a member of the public is significantly less than what is calculated for this hypothetical individual. This dose is assessed relative to the offsite dose, and considers dilution, dispersion, and occupancy factors.

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

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

First Quarter 8.2E-04 9.5E-04 Second Quarter 3.3E-04 3.8E-04 Third Quarter 1.8E-04 2.1E-04 Fourth Quarter 5.9E-04 6.9E-04 Annual 2.OE-03 2.2E-03 Although several cases were evaluated to determine the highest hypothetical dose from gaseous effluents to members of the public inside site boundary, the activity inside the site boundary with the highest dose potential is also shoreline fishing. The cases evaluated included traversing a public road within the site boundary, shoreline fishing (assuming fishing 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year), non-plant related training, car-pooling, and job interviews. The maximum on-site gaseous doses generated are shown in Table 11.

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

First Quarter 5.3E-07 1.OE-06 Second Quarter 4.8E-05 1.3E-04 Third Quarter 1.8E-04 3.7E-04 Fourth Quarter 1.5E-04 1.8E-04 Annual 6.6E-03 1.6E-02 Page 19

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT U An average whole body dose to individual members of the public at or beyond the site boundary is then determined by combining the dose from gaseous and liquid radiological I

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

Table 12: Average Individual Whole Body Dose I

LIQUID EFFLUENTS (MREM)

GASEOUS EFFLUENTS (MREM) I First Quarter 7.1E-05 7.5E-10 Second Quarter Third Quarter 2.3E-05 2.6E-05 4.6E-07 8.3E-08 I

Fourth Quarter Annual 2.6E-05 1.5E-04 9.6E-08 6.3E-07 I I

I I

U i

I Page 20 I

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CARBON-1 4 SUPPLEMENTAL INFORMATION Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. C-14 is released primarily from BWRs through the off-gas system in the form of carbon dioxide (C02). The quantity of gaseous C-14 released to the environment can be estimated using a C-14 source term scaling factor based on power generation.

The U.S. Nuclear Regulatory Commission (NRC) requires an assessment of gaseous C-1 4 dose impact to a member of the public resulting from routine releases in radiological effluents. Prior to 2011, the industry did not estimate the dose impact of C-14 releases.

Since the dose contribution had been considered negligible compared to the dose impact from effluent releases of noble gases, tritium, particulates and radioiodines. At PNPP, improvements over the years in effluent management practices and fuel performance have resulted in a decrease in the concentration and changes in the distribution of gaseous radionuclides released to the environment.

PNPP's 2012 Annual Environmental Effluent Release Report (AEERR) contains estimates of C-14 radioactivity released in 2012, and estimates of public dose resulting from the C-14 effluent. Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste at PNPP is not required. Refer to Table 4 and Table 9 for C-14 estimated release values and doses.

Page 21

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 3 ON-SITE GROUNDWATER MONITORING PROGRAM Introduction History In March, 2006, a routine sample of the underdrain system at the PNPP plant showed detectable tritium concentrations. The underdrains are a porous pipe system which drains groundwater from the foundations of the site buildings. As such, it would not be expected to be a contaminated system. Condition Report 06-01477 was submitted and a Root i Cause Investigation was conducted. Concurrently, a program of groundwater monitoring was initiated.

It was determined at that time that there was no detectable tritium beyond the boundaries of the underdrain system. Piezometer tubes located both inside and outside of the power block, (i.e., area encompassing equipment used for the generation of electricity) were sampled and analyzed. In 2007, PNPP contracted with Environmental Resource Management (ERM) of Boston, Massachusetts to perform site hydrogeology evaluations, I

and to facilitate installation of additional groundwater monitoring wells, based on their findings. FirstEnergy fleet chemistry formalized the program with the issuance of fleet procedure NOP-OP-2012, "Groundwater Monitoring."

Cause 3 The buildings at the PNPP site are designed with seismic spaces between building walls.

These would serve to drain plant buildings in the event of an earthquake of sufficient strength to break plant piping, minimizing the flooding of vital equipment areas, and facilitate continued safe operation, or safe shutdown, as conditions warrant.

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

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

UnderdrainSystem 3 As mentioned earlier, the underdrain system drains water away from plant foundations. It is separate and distinct from the storm drain system, which is designed purely for rain water control. The underdrain system has a number of installed sump pumps, with the ability to gravity-drain and cascade forward should the pumps fail. There are two major branches of I

underdrains, one for each of the east and west sides of the power block. These branches ultimately flow into 2 underdrain manholes, designated MH-20 and MH-23, before draining to the suction bay of the Emergency Service Water (ESW) pump house. From there, the I

water is discharged from the plant. Refer to Figure 2 for locations of Manholes 1 through

27. 3 Sampling Locations Prior to the installation of monitoring wells, Manholes 20 and 23 were sampled to assess groundwater tritium in-leakage to the system. These manholes were sampled daily through the middle of 2007, and weekly thereafter through the end of the year. Besides tritium, the Page 22 3

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT samples were also analyzed via gamma spectroscopy to environmental lower limits of detection. No gamma activity was ever detected in any sample.

Tritium releases from the station were documented as abnormal releases, and the required dose calculations were completed per the Offsite Dose Calculation Manual (ODCM).

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

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

There are 4 sets of triplet wells installed at each location. Each triplet has a shallow well (approximately 25 feet), a mid-depth well of approximately 50 feet, and a deep well of approximately 75 feet. These 3 depths are designated A, B and C, from shallowest to deepest, respectively. Refer to Figure 2 for locations of Groundwater wells 1A through 4C.

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

Page 23

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

Manholes 0 Piezometers*

Groundwater Wells ***

........ ... ........................ *i

U U

U.

-UD U

UUU U

W I Pae2 amn n nnig*- i n /

mimnmRIni

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT State of the Program Currently, the monitoring wells are sampled twice annually, in spring and fall. The sampling is done under a controlled protocol, and is conducted by personnel from FirstEnergy's BETA Laboratories. The samples are shipped to Midwest Laboratories in Illinois. Midwest analyzes the sample for gamma isotopic and tritium.

Table 13: Summary of Onsite Groundwater Samples Monitoring H-3 MAX. (PCi/L) REQUIRED H-3 NEI AND FENOC EPA REPORTING Well LLD (PCI/L) LEVEL FOR H-3 LEVEL FOR H-3 (PCI/L) (PCI/L)

First Half 2012 Well 1A <153 < 2000 2000 20000 Well 1 B <153 < 2000 2000 20000 Well 1C <153 < 2000 2000 20000 Well 2A <153 < 2000 2000 20000 Well 2B <153 < 2000 2000 20000 Well 2C <153 < 2000 2000 20000 Well 3A 200 < 2000 2000 20000 Well 3B <153 < 2000 2000 20000 Well 3C <153 < 2000 2000 20000 Well 4A <153 < 2000 2000 20000 Well 4B <153 < 2000 2000 20000 Well 4C <153 < 2000 2000 20000 Second Half 2012 Well 1A <147 < 2000 2000 20000 Well 1B <147 < 2000 2000 20000 Well 1C <147 < 2000 2000 20000 Well 2A <150 < 2000 2000 20000 Well 2B <147 < 2000 2000 20000 Well 2C <147 < 2000 2000 20000 Well 3A 156 < 2000 2000 20000 Well 3B <147 < 2000 2000 20000 Well 3C <147 < 2000 2000 20000 Well 4A 159 < 2000 2000 20000 Well 4B <147 < 2000 2000 20000 Well 4C <147 < 2000 2000 20000 Page 25

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

ABNORMAL RELEASES 3 See Appendix E for description of an Abnormal Release from the Nuclear Closed Cooling (NCC) system.

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

OFFSITE DOSE CALCULATION MANUAL CHANGES I During this reporting period, ODCM revision number 19 was made effective on 12/10/12.

Summary of changes: 3

1. Revised sections 6.9.1.6 & 7 to state that the Annual Reports shall be submitted by May 1 of each year. This was done to match the wording contained in Technical Specifications sections 5.6.2 and 5.6.3.

2. Modified first footnote and added second footnote to Tables 5.1-2 and 3.12.1-2, n Reporting Levels for Radioactivity Concentrations in Environmental Samples, to match the footnotes contained in NUREG 1302 (Supplement No. 1 to Generic Letter 89-01). These changes allow for higher reporting levels for H-3 and/or 1-131 if the sample was taken from a non-drinking water pathway. (CR-2011-02282)

3. Added table number to ODCM REMP Sample Locations table (Table 5.1-4) and added table number to table of contents.

4. Modified first footnote to Table 5.1-4; removed the term "chronologically" from the beginning of the sentence to clarify meaning. 3 PROCESS CONTROL PROGRAM CHANGES See Appendix G for description of changes to the Process Control Program U P

I I

Page 263

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

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

To ensure that the REMP data are meaningful and useful, detailed sampling methods and procedures are followed. This ensures that samples are collected in the same manner and from the same locations each time. All samples are packaged on site, and then shipped to an independent vendor laboratory for analysis. The vendor laboratory analyzes the samples and reports results to the PNPP Chemistry Unit staff, the Lake County General Health District, and the State of Ohio Department of Health. Additionally the Lake County General Health District obtains monthly "split" samples of milk, water and vegetation. This permits an independent verification of PNPP's radiological environmental monitoring program.

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

Many REMP samples are collected in addition to those required by the PNPP ODCM. The ODCM requirements for each sample type are discussed in more detail later in the report.

Sample types and locations required by the ODCM are shown in Bold in Table 14.

Page 27

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I

Table 14: REMP Sampling Locations (1) I LOCATION # DESCRIPTION MILES DIRECTION MEDIA( 2) 1 2

3 Chapel Road Kanda Garden Meteorological Tower 3.4 1.9 1.0 ENE ENE SE TLD, AlP Food Products TLD, AlP I

4 Site Boundary 0.7 S TLD, AlP 5

6 7

Quincy Substation Concord Service Center Site Boundary 0.6 11.0 0.6 SW SSW NE TLD, AlP TLD, AlP TLD, AlP I

8 Site Boundary 0.8 E TLD 9

10 11 Site Boundary Site Boundary Parmly Rd.

0.7 0.8 0.6 ESE SSE SSW TLD TLD TLD I

12 Site Boundary 0.6 WSW TLD 13 14 15 Madison-on-the-Lake Hubbard Rd.

Eagle St. Substation 4.7 4.9 5.1 ENE E

ESE TLD TLD TLD I

16 Eubank Garden 0.9 S Food Products 18 19 20 Kijauskas Farm (goat)

Goodfield Dairy Rainbow Farms 2.5 8.7 1.9 E

S E

Food Products, Milk Milk Food Products I

21 Hardy Rd. 5.1 WSW TLD 23 24 25 High St. Substation St. Clair Ave.

Offshore - PNPP discharge 7.9 15.1 0.6 WSW SW NNW TLD TLD Sediment, Fish I

26 Offshore - Redbird 4.2 ENE Sediment 27 28 29 30 Offshore - Fairport Harbor CEI Ashtabula Plant Intake River Rd.

Lane Rd.

7.9 22.0 4.3 4.8 WSW ENE SSE SSW Sediment Water TLD TLD I

31 32 33 Wood and River Rd.

Offshore - Mentor River Rd.

4.8 15.8 4.5 SE WSW S

TLD Sediment, Fish TLD Water I

34 PNPP Intake 0.7 NW 35 36 37 41 Site Boundary Lake County Water Plant Gerlica Farm Tuttle Farm (goat) 0.6 3.9 1.5 5.8 WSW E

ENE SSE TLD, AlP TLD, Water Food Products Milk I

51 Rettger Milk Farm (cow) 9.6 S Milk 53 Neff Perkins 0.5 WSW TLD 54 55 Hale Rd. School Center Rd.

4.6 2.5 SW S

ESE TLD TLD TLD I

I 56 Madison High School 4.0 58 Antioch Rd. 0.8 ENE TLD 59 Lake Shoreline at Green Rd. 4.0 ENE Water 60 Lake Shoreline at Perry Park 1.0 WSW Water 64 Northwest Drain Mouth 0.09 NW Sediment (1) 65 70 Major Stream Mouth H&H Farm Stand 0.18 16.2 W

SSW Missing location numbers denote deleted or retiredsampling locations.

Sediment Food Products I (2) A/P =

TLD =

Air, Iodine and Particulate Thermoluminescent Dosimeter !

Page 28

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 3: REMP Sampling Locations Within Two Miles of Plant Site U NW NNW N NNE I

I I WNW I

W I

U WSW I

I I SW SSW S SSE I I m m 0 I I

2 MILES I

I I

I Page 29

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 4: REMP Sampling Locations Between Two and Eight Miles of the Plant Site SW SSW S sse se Page 30

- - _m m nm mn m m m m m - m m ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 5: REMP Sampling Locations Greater Than Eight Miles from the Plant Site 5 0 5 10 15 20 MILES I m m Page 31

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 3 SAMPLE ANALYSIS 3 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. 3 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 I

with gamma radiation, identification of specific beta-emitting nuclides is more difficult.

Therefore, gross beta activity only indicates whether the sample contains normal or abnormal amounts of beta-emitting radioactivity; it does not specifically identify the radionuclides present.

Gamma spectral analysis provides more specific information than does the analysis for gross i 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.

I Tritium activity analysis measures the amount of the radionuclide tritium (H-3) present in a sample. Tritium is an isotope of hydrogen that emits low-energy beta particles. Tritium occurs naturally and is also man-made.

Gamma doses received by Thermoluminescent Dosimeters (TLD) while in the field are determined by a special laboratory procedure. Thermoluminescence is a process by which i ionizing radiation interacts with the sensitive phosphor material in the TLD. Energy is trapped in the TLD material and can be stored for months or years. This capability provides a method to measure the dose received over long periods of time. The amount of energy that was stored in the TLD as a result of interaction with radiation is released by a controlled heating process and measured in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy as light. The amount of light is directly proportional to the amount of radiation to which the TLD was exposed. The reading process also zeroes the TLD and prepares it for reuse. Table 15 provides a list of the analyses performed on environmental samples collected for the PNPP REMP in 2012. I Sample results are often reported as less than the lower limit of detection (< LLD), which is defined as the smallest amount of radioactive material that will show a positive result for which there can be confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample analysis. When a measurement is reported as

< LLD, it means that no radioactivity was detected at a value above, or equal to the appropriate ODCM table value. The NRC has established LLD values for REMP sample analyses. The vendor laboratory for REMP sample analyses complied with those values in I

2012.

Page 32

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

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

Iodine-1 31 Food Products Monthly Gamma Spectral Analysis Aquatic Monitoring Water Monthly Gross Beta Activity &

Gamma Spectral Analysis Quarterly Tritium Activity Fish Annually Gamma Spectral Analysis Sediment Biannually Gamma Spectral Analysis Direct Radiation TLD Quarterly & Gamma Dose Monitoring Annually 2012 SAMPLING PROGRAM The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the 2012 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, 2012 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 2012.

Program Changes Discontinued collecting milk from the Keller Milk Farm, location number 61; they are no longer providing milk.

Discontinued collecting shoreline sediment from location number 63. Due to beach and bluff erosion, that location is no longer accessible.

Missed Samples On occasion, samples cannot be collected. This can be due to a variety of events, including equipment malfunction, animal husbandry practices, or lost shipments. Events may also occur which prevent a sample from being collected in the normal way, or prevent a complete sample from being collected. The drying period for goats is an annual occurrence, since unlike cows, goats do not normally produce milk year-round. Food products are weather dependent and are susceptible to excessive spring rains or summer drought that can significantly impact the garden harvest. Shoreline lake water samples are collected by grab sample utilizing a container and scoop. During the winter months the shoreline can become inaccessible due to ice and snow buildup, preventing the safe collection of these samples.

Shoreline sediment samples are collected with spoon and container. On occasion, the Page 33

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT accessibility of these locations and sample collection may be impacted due to high lake levels, shifting lake bottom sediment, bluff erosion and shoreline collapse. For 2012, there was no impact to the on program requirements as a2012.

result of any missed samples. Table 16 I

provides information samples missed during Table 16: Missed REMP Samples in 2012 MEDIA Food Products LOCATION All DATE Jan.- May, Nov. - Dec.

REASON Insufficient growth/temperature. Die-I off/Frost damage.

I Lake Water 59, 60 Jan. Sample unavailable due to frozen Milk 18 Jan - Mar, Nov. - Dec shoreline Drying period for goats/sample I

availability 41 Jan - Mar, Oct. - Dec. Drying period for goats/sample availability I

I Atmospheric Monitoring Air U Air sampling is conducted to detect any increase in the concentration of airborne radionuclides. The PNPP REMP maintains an additional 2 air sampling locations above the five locations (four indicators and one control) required by the ODCM. Six (6) of these I

locations are within four miles of the plant site; the seventh is used as a control location and is eleven miles from PNPP. Air sampling pumps are used to draw continuous samples at a rate of approximately two cubic feet per minute. The air is drawn through glass fiber filters I (to collect particulate material) and a charcoal cartridge (to adsorb iodine). The samples are collected on a weekly basis, 52 weeks a year, from each of the seven air sampling stations.

Air samples are analyzed weekly for gross beta activity and radioiodine activity. The air I

samples are also analyzed by gamma spectral analysis quarterly. A total of 371 air particulate and 371 air radioiodine samples were collected and analyzed in 2012.

Gross beta activity was detected in all the air samples and ranged up to 0.058 pCi/m 3. The I

average gross beta activity for the indicator locations was 0.025 pCi/m 3 and for the controls it was 0.026 pCi/m 3. Historically, the concentration of gross beta in air has been essentially identical at indicator and control locations. Figure 6 reflects the average gross beta activity I

for 2012 and the previous years. All radioiodine samples were less than the lower limit of detection for 1-131.

Except for naturally occurring beryllium-7, no radionuclides were identified in the gamma I

quarterly spectral analysis above the LLD values.

I Page 34

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 6: Annual Average Gross Beta Activity, in Air 0.05

' 0.04 O 0.03 0.02 4 0.01 Year rlndcator EControl Terrestrial Monitoring Collecting and analyzing samples of milk and food products provides data to assess the build-up of radionuclides that may be ingested by humans. The historical data from soil and vegetation samples provides information on the atmospheric radionuclide deposition.

Milk Samples of milk are collected once each month from November through March, and twice each month from April through October. Sampling is increased during the summer because animals usually feed outside on pasture and not on stored feed. The PNPP REMP includes four (4) milk locations located 2.5, 5.8, 8.7 and 9.6 miles away from the plant.

Since the milk sampling locations do not meet the requirements of the ODCM (only one milk-producing animal is located within the required distance vs. two required), food product sampling (discussed below) is performed. Milk is collected from the available location to augment food product sampling. If new locations that meet the ODCM requirements are identified in the future, they will be added to the program.

Milk samples are analyzed by gamma spectral analysis for radioiodines and other radionuclides. A total of sixty-four (64) milk samples were collected in 2012. With the exception of naturally occurring Potassium-40, no other radionuclides were detected Broadleaf Vegetation Because there are not a sufficient number of milk sampling locations, the PNPP REMP samples broadleaf vegetation. These samples are collected monthly during the growing season from six (6) gardens in the vicinity of PNPP and one control location 16.2 miles SSW from PNPP.

A total of eighty-two (82) samples were collected and analyzed by gamma spectral analysis in 2012.

Four (4) vegetation types were grown and collected: Japanese greens, collard greens, turnip greens and Swiss chard. Beryllium-7 and potassium-40, naturally-occurring radionuclides, were found in several samples, which is expected. No other radionuclides were detected above the required LLDs.

Page 35

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Aquatic Monitoring i 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 U 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. i Water Water is sampled from five (5) locations along Lake Erie in the vicinity of the PNPP as required by the PNPP ODCM. Samples from two (2) locations are collected using composite sample pumps. The pumps are designed to collect water at regular intervals and composite it in a sample container. One (1) sample is collected from a slow continuous feed to a collection container. Samples from the two (2) other locations are manually collected weekly and combined. The containers are emptied monthly and the samples shipped to the vendor laboratory for analysis.

Fifty-eight (58) water samples were collected and analyzed for gross beta activity and gamma spectral analysis. From these monthly samples, twenty (20) quarterly composite samples were obtained and analyzed for tritium and gamma activity. i Gross beta activity was detected in fifty-one (51) of the fifty-eight (58) samples collected.

The indicator average gross beta activity was 2.0 pCi/L and the control average gross beta activity was 2.0 pCi/L. Refer to Figure 7 for the annual average gross beta activity for both indicator and control locations.

i Figure 7: Annual Average Gross Beta Activity, in Wateri 4.5 I 4

3.5 2.5 S1.5 2I 0.5 0

I o eN c '-t Ci U') (0 fl, CD C) (D - J Cl) '- LO CD t. CD aD 0 - (\J a)0)0)a)0 a a a a ) 00D 0 0 0 0 0 '-

[Ind cato r EControl There were no tritium or radionuclides detected by gamma spectral analysis.

I Pag 36I

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Sediment Sampling of lake bottom sediments can provide an indication of the accumulation of particulate radionuclides which may lead to internal exposure to humans through the ingestion of fish, the re-suspension into drinking water, or as an external radiation source to fishermen and swimmers from shoreline exposure. Sediment is sampled twice each year from six (6) locations.

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

Twelve (12) sediment samples were collected in 2012 and analyzed by gamma spectroscopy. The predominant radionuclide detected by gamma spectral analysis was naturally occurring potassium-40.

Cesium-1 37 activity was detected in eight (8) of the twelve (12) samples collected and ranged from 35.7 pCi/kg to 529.6 pCi/kg. The indicator average cesium-1 37 activity was 132.9 pCi/kg and the control average was 472.2 pCi/kg. The average cesium-137 radioactivity for all locations was 217.7 pCi/kg and is lower than the highest identified value of 864 pCi/kg established in 1981. Year-to-year variations in lake bottom sediment sample activity is expected and beyond the control of PNPP. For example, cesium-1 37 activity variations (refer to Figure 8) in the control locations from year-to-year may be contributed to:

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

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

Figure 8: Annual Average Cesium-137 Concentration in Sediment 1600 1400 1200 1 000 800 600 400 200 0

0WO0 M)) 0 ",-

0 C' 0.J C',

00 I 0LO 0CD O 0-- 0CO 00) 0

'a- '- C'J

0) 0) 0 0 0 0 0 0 0 0 0 0 0 0 Yea r J ) DJ OJ 0" C C4 C4 C C 01 J Yea r Qi1nd icato r EControl Page 37

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Fish Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and i secondarily to serve as indicators of radioactivity in the aquatic ecosystem. Fish are collected from two (2) 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 2012, fish sampling was performed for PNPP by a local I

licensed sport fisherman.

Three (3) fish samples including (1) Yellow Perch, and (2) Freshwater Drum were collected and analyzed by gamma spectral analysis in 2012. As expected, naturally occurring potassium-40 was found in all samples. No other radionuclides were detected above the LLD.

Direct Radiation Monitoring Thermoluminescent Dosimeter (TLD)

Environmental radiation is measured directly at twenty-eight (28) locations around the PNPP site, two (2) of which are control locations. The locations are positioned in two rings around i the plant as well as at the site boundary. The inner ring is within a one-mile radius of the plant site; the outer ring is four miles to five miles from the plant. The control locations are over ten miles from the plant in the two least prevalent wind directions. Each location is equipped with three TLDs, two of which are changed quarterly and one is changed annually.

I A total of two hundred fifty-two (252) TLDs were collected and analyzed in 2012. This includes two hundred twenty-four (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.

For 2012, the annual average dose for all indicator locations was 64.9 mrem, and 61.3 mrem for the control locations.

Referring to Figure 9, the average quarterly dose for all indicator locations was 13.8 mrem, i and 13.2 mrem for all control locations. Please refer to Appendix C, 2012 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.

I I

Page 38

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 9: Average Quarterly TLD Dose 18 16 c 14 E 12 10

" 8 0

S4 2

0 0 - N*I 1" LO 0 N W M ) 0 - N M) tO 10(0 WI O0)0 -

0M) 0M ) 0) M 0 0 0 0 0 0 0 0 0 0 0 0 0 Year ndicator In mControl Conclusion Operation of the Perry Nuclear Power Plant is having no detectable radiological effect on the surrounding environment.

Page 39

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 I known concentration of specific radionuclides are provided to the vendor laboratory. The vendor laboratory measures and reports the concentration of specified radionuclides. The known values are then compared to the vendor results. Results consistently outside established acceptance criteria indicate a need to check instruments or procedures.

I Regulatory Guide 4.15 specifically required that contractor laboratories that performed environmental measurement participate in the EPA's Environmental Radioactivity Laboratory Inter-Comparison Studies Program, or an equivalent program.

The EPA's program is no longer funded or offered. The reason that the EPA program was referenced in the regulatory guide is that the EPA standards were traceable to National Bureau of Standards (now known as National Institute Standard Technology). In response to I

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

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

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

See Appendix A, for vendor 2012 Inter-Laboratory Cross-Check Comparison Program Results. 3 Page 40

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT LAND USE CENSUS Introduction Each year a Land Use Census, which is required by Section 5.2 of the PNPP ODCM, is conducted to identify the locations of the nearest milk animal, garden (of greater than 500 square feet), and residence in each of the meteorological sectors that is over land.

Information gathered during the Land Use Census is used for off-site dose assessment and to update sampling locations for the Radiological Environmental Monitoring Program (REMP). 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 2012 Land Use Census, which was conducted on September 2 1 st 2012 provided the garden, residence and milk animal locations tabulated in Tables 17, 18 and 19 and depicted in Figure 10. Note that the W, WNW, NW, NNW, N, and NNE sectors extend over Lake Erie, and are not included in the survey.

Discussions and Results In general, the predominant land use within the census area continues to be rural/

agricultural. In recent years however, it has been noted that tracts of land once used for farming are now being developed as mini-industrial parks and residential housing tracts.

This is reflected in the loss of available milking animals within a five mile radius of PNPP to support the REMP.

Table 17 identifies the nearest residences, by sector, to the PNPP. There were some fractional changes for the "Miles from PNPP" distances due to using GPS coordinates instead of a map.

Table 17: Nearest Residence, By Sector SECTOR LOCATION ADDRESS MILES FROM MAP LOCATOR PNPP NUMBER NE 4384 Lockwood 0.7 1 ENE 4602 Lockwood 1.1 2 E 2626 Antioch 1.0 3 ESE 2836 Antioch 1.1 4 SE 4495 North Ridge 1.3 5 SSE 3119 Parmly 0.9 6 S 3121 Center 0.9 7 SSW 3850 Clark 0.9 8 SW 2997 Perry Park 1.2 9 WSW 3460 Parmly 1.0 10 Page 41

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 18 identifies the nearest milking animal by sector, to the PNPP. During the 2012 Land Use Census, no additional new milking animals were identified.

I Table 18: Nearest Milk Animal, By Sector SECTOR LOCATION ADDRESS MILES FROM MAP LOCATOR I

PNPP NUMBER E 2591 McMackin Rd. 2.5 21 I

There were two (2) changes for the nearest gardens identified during this year's census.

Table 19 lists the nearest gardens occupying at least 500 square feet identified during the I Land Use Census. Two new garden locations were identified in the SSW and WSW sectors.

There were also some fractional changes for in the "Miles from PNPP" distances due to using GPS coordinates instead of a map. I Table 19: Nearest Garden, By Sector I SECTOR LOCATION ADDRESS MILES FROM MAP LOCATOR NE ENE 2340 4630 Hemlock Lockwood PNPP 0.9 1.1 NUMBER 11 12 I

E 2626 Antioch 1.0 3 ESE 2836 Antioch 1.1 4 SE 4671 North Ridge 1.3 15 SSE 4225 Red Mill Valley 1.1 16 S 3121 Center Rd. 0.9 7 SSW 3431 Perry Park 1.9 17 SW 3032 Perry Park 1.3 13 WSW 3460 Parmly 1.0 14 Page 42 I

= - - - m - - = - m - m - - - - = --

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 10: Land Use Census Map Garden l Residence M Milking Animal Page 43

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT NORTHWEST DRAIN IMPOUNDMENT In 1999, a sediment sample from location #64 (shoreline discharge point of the Northwest Drain Impoundment) was found to contain trace levels of cobalt-60. Ten (10) additional sample locations were established upstream from location #64 and within the Impoundment to identify the boundary of the cobalt-60 activity and to support supplemental monitoring activities. In recent years, the shoreline adjacent to the impoundment has experienced extensive bluff erosion and collapse, preventing access and sample collection for locations 64-4 and 64-5. Detailed maps of the impoundment, sample locations and sample results are maintained by the PNPP Chemistry unit.

In 2010, during spring sampling, cobalt-58 (a short half-life isotope) was identified at location 64-9. Additionally, increased levels of cobalt-60 were identified at locations 64-6 and 64-9.

Condition report 10-79628 was written to document the identification of cobalt-58 which led to subsequent investigation and corrective actions. The investigation identified that source of the newer activity may have been the result of contaminated runoff water from radioactive material movements and transport vehicles within the protected area. For 2012, results from the nine (9) impoundment sample locations shows that the activity remains within the Northwest Drain Impoundment. Co-58 was not detected in 2012. Additionally, the shoreline sediment samples exhibiting no activity demonstrate that activity is not migrating to the shoreline. Table 20 shows the sample results for 2012.

Table 20: Northwest Drain Impoundment Activity, pCi/kg (dry)

LOCATION MAY 2012 SEPTEMBER 2012 U 64 Co-60

<LLD Cs-1 37

<LLD Co-60

<LLD Cs-1 37

<LLD I 64-1 <LLD 29.0 <LLD <LLD 64-2 64-3 64-6

<LLD

<LLD 85.9 345 140 1002

<LLD 57 131 604 85 1505 I

64-7 64-8 64-9 72.1 50.8 185 1154 613 1177 112

<LLD 190 1573 723 1247 I

64-10 64-11 152 27.8 1188 481 145 40 1322 417 I Page 44

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

CORBICULA PROGRAM Monitoring specifically for Corbicula was initiated in response to a NRC bulletin and concerns of the Atomic Safety and Licensing Board. The 2012 monitoring was done as part of the Environmental Protection Plan (Operating License, Appendix B). The program consists of visually inspecting the raw water systems, when they are opened for maintenance. The purpose of this program is to detect Corbicula, should it appear at PNPP.

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

Monitoring In 2012, samples were collected from the Service Water (SW) and Emergency Service Water (ESW) pump houses at PNPP and examined for shells and fragments. Samples were either collected by hand scoop or scraper. In addition to sample collections, plant components that use raw water are inspected when opened for maintenance or repair. Sample collection/inspection dates are listed in Table 21.

Table 21: 2012 Corbicula Monitoring DATE SAMPLE LOCATION 6/29/2012 1N34B0001 A - Lube Oil Cooler 7/27/2012 N43B0001 B - Lube Oil Cooler 8/17/2012 1 P54F5263 - Fire Water 8/29/2012 N43B0001 B - Lube Oil Cooler 10/01/2012 P43B0001B - Nuclear Closed Cooling 10/24/2012 1 P54F0722 - Fire Water 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 Page 45

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT PNPP. As in the past, the 2012 monitoring program did not identify Corbicula in any sample collected.

DREISSENA PROGRAM Dreissena or Zebra mussels were first discovered at PNPP in September, 1988. The initial collection of nineteen (19) mussels was made as part of the Corbicula monitoring program.

The Dreissena monitoring program began in 1989, with monitoring and testing. The current I control program was designed and implemented in 1990.

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

forebays, basins, and the intake and discharge structures. Divers have also been used to take underwater videotapes of the water basins and intake tunnel. Side-stream monitors are flow-through containers that receive water diverted from plant systems and are set up at two in-plant locations during the mussel season.

I Treatment Chemicals used for mussel control in 2012 included sodium hypochlorite and a commercial molluscicide. The chlorine is intermittently injected into the plant service water, emergency service water, and circulating water systems by metering sodium hypochlorite into each system's influent. Sodium bisulfite is added at the plant discharge structure for dechlorination prior to return into Lake Erie.

The use of a commercial molluscicide has been approved by the Ohio Environmental Protection Agency (OEPA). The chemical selected for use at the PNPP in 2012 was alkyl-dimethyl-benzyl-ammonium chloride. Treatment was applied once in 2012, on October 1 6 th.

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

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

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

The effectiveness of the application of the commercial molluscicide was measured by observing mortality of mussels placed in a flow-through container placed in plant service water and subjected to the chemical treatment. The observed mortality rate utilizing the flow-I through container for 2012 was 20%.

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

Page 46

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Conclusions PNPP has taken the approach that the best method for avoiding problems with zebra mussels is preventive treatment of plant water systems. The current program of monitoring and chemical treatment will be continued to minimize the possibility that PNPP will experience future problems due to zebra mussels.

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

In 2012, four (4) general and three (3) specific herbicide requests were initiated for chemical applications. Each application was in compliance with the Ohio Environmental Protection Agency's rules and regulations. There were no adverse environmental impacts observed during weekly site environmental inspections as a result of these applications. The herbicides approved for use in the Owner-Controlled Area are Round-Up, Round-Up Promax, Accord, Polaris, Kingpin, Tempo Ultra, Oust, Escort, Super Signal Blue Concentrate and Razor. For each application, the type of weed to be treated dictated the herbicide and concentration to be used. Table 22 provides detailed documentation for each application in 2012. The quantity represents the amount of herbicide applied, prior to any dilution.

Table 22: 2012 Herbicide Applications DATE LOCATION AMOUNT CHEMICAL NAME APPLIED 4/26/12 Security Towers, Booths, PAF, Vehicle Trap, SWPH 14 gal Tempo Ultra Ladders and Stairs 5/30/12 Per field Security Zone 24 gal Round-Up Promax 6/4/12 Per field Security Zone 24 gal Round-Up Promax 6/14/12 Switch Yard 2 gal Oust 6 pints Razor 2 gal Escort 7/9/12 Security Towers, Booths, PAF, Vehicle Trap, SWPH 10 gal Tempo Ultra Ladders and Stairs 9/5/12 Security Towers, Booths, PAF, Vehicle Trap, SWPH 12 gal Tempo Ultra Ladders and Stairs _

9/5/12 Service Building Office Areas 1 qt Dupont Arilon 9/6/12 Transmission Yard Right of Ways 900 gal Accord / Polaris Page 47

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

There was one report submitted in 2012:

On May 6, 2012, during daily chlorination activities, it was identified that the NPDES permit limit for Total Residual Chlorine was exceeded between 0935 and 0947 hours0.011 days 0.263 hours 0.00157 weeks 3.603335e-4 months .

The maximum measured value was 0.29 mg/I, which exceeded the NPDES Maximum Concentration limit of 0.2 mg/l.

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.

Other than the non-compliance NPDES report (mentioned above) no other reports were submitted in 2012.

UN-REVIEWED ENVIRONMENTAL QUESTIONS All proposed changes to the PNPP design or operation, as well as tests or experiments, must be evaluated for potential environmental impacts in accordance with the EPP and administrative quality assurance procedures.

In 2012 there was one new test evaluated for environmental impacts. A new chemical, Trasar, was approved to be utilized at the NPDES outfall 004, discharge tunnel. The chemical will pose no environmental threats to Lake Erie. The chemical has been approved for use by the Ohio Environmental Protection Agency to test the integrity of the underground service water dechlorination feed line. This chemical was reviewed under environmental I

evaluation, 2012-001.

I Page 48

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX A 2012 INTER-LABORATORY CROSS CHECK COMPARISON PROGRAM RESULTS

14, ATI Environmental, Inc.

Midwest Laboratory 700 Landwehr Road

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

January, 2012 through December, 2012

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

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

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

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

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

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

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

Complete analytical data for duplicate analyses is available upon request.

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

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

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

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

Al

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

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

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

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

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

> 100 pCi/liter 5% of known value Tritium < 4,000 pCi/liter +/-1o =

0 0 933 169.85 x (known)

> 4,000 pCi/liter 10% of known value Radium-226,-228 > 0.1 pCi/liter 15% of known value Plutonium > 0.1 pCi/liter, gram, or sample 10% of known value Iodine-1 31, < 55 pCi/liter 6 pCi/liter Iodine-1 2 9 b > 55 pCi/liter 10% of known value Uranium-238, < 35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Other Analyses b 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 Result b Result c Limits Acceptance ERW-1783 04/09/12 Sr-89 62.2 +/- 6.0 58.5 46.9 - 66.3 Pass ERW-1783 04/09/12 Sr-90 33.7 +/- 2.1 37.4 27.4 -43.1 Pass ERW-1786 04/09/12 Ba-1 33 75.7 +/- 4.1 82.3 69.1 -90.5 Pass ERW-1786 04/09/12 Co-60 71.9 +/- 4.0 72.9 65.6 - 82.6 Pass ERW-1786 04/09/12 Cs-134 70.0 +/- 4.3 74.2 60.6 - 81.6 Pass ERW-1786 04/09/12 Cs-137 151.5 +/- 6.1 155.0 140.0 - 172.0 Pass ERW-1786 04/09/12 Zn-65 108.3 +/- 89.0 105.0 94.5 - 125.0 Pass ERW-1789 04/09/12 Gr. Alpha 55.0 +/- 2.4 62.9 33.0 - 78.0 Pass d

ERW-1789 04/09/12 Gr. Beta 76.2 +/- 1.8 44.2 29.6 - 51.5 Fail ERW-1795 04/09/12 Ra-226 6.4 +/- 0.4 5.7 4.3 - 6.9 Pass ERW-1795 04/09/12 Ra-228 5.4 +/- 1.2 4.6 2.7 - 6.3 Pass ERW-1795 04/09/12 Uranium 56.2 +/- 2.6 61.5 50.0 - 68.2 Pass ERW-1798 04/09/12 H-3 16023 +/-355 15800 13800 -17400 Pass ERW-6283 10/05/12 Sr-89 41.5 +/- 4.1 39.1 29.7 -46.1 Pass ERW-6283 10/05/12 Sr-90 19.7 +/- 1.6 20.1 14.4 -23.8 Pass ERW-6286 10/05/12 Ba-133 82.7 +/- 4.4 84.8 71.3 -93.3 Pass ERW-6286 10/05/12 Co-60 77.2 +/- 3.7 78.3 70.5 -88.5 Pass ERW-6286 10/05/12 Cs-134 74.4 +/- 1.5 76.6 62.6 -84.3 Pass ERW-6286 10/05/12 Cs-137 183.0 +/-6.2 183.0 165.0 -203.0 Pass ERW-6286 10/05/12 Zn-65 211.0 +/- 9.9 204.0 184.0 -240.0 Pass ERW-6288 10/05/12 Gr. Alpha 47.0 +/- 2.3 58.6 30.6 -72.9 Pass ERW-6288 10/05/12 Gr. Beta 33.4 +/- 1.2 39.2 26.0 -46.7 Pass ERW-6290 10/05/12 1-131 23.3 +/- 1.0 24.8 20.6 -29.4 Pass ERW-6295e 10/05/12 Ra-226 17.5 +/- 0.7 15.0 11.2 -17.2 Fail ERW-6295e 10/05/12 Ra-228 7.4 +/- 1.5 4.6 2.7 - 6.2 Fail ERW-6295 10/05/12 Uranium 61.2 +/- 1.8 62.5 50.8 - 69.3 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

d Result of reanalysis: 38.3 +/- 1.3 pCi/L. Sample dilution problem suspected. A new dilution was prepared.

e Results of reanalyses, original submission (pCi/L): Ra-226, 16.5 +/- 0.7 Ra-228, 4.9 +/- 1.1 A new test was ordered from Environmental Resources Associates, results will be updated for first quarter, 2013.

A1-1

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

I mR I

Lab Code Date Known Lab Result Control Description Value +/- 2 sigma Limits Acceptance I

Environmental, Inc.

I 2012-1 2/7/2012 30 cm. 74.87 87.22 +/- 2.86 52.41 - 97.33 Pass 2012-1 2012-1 2012-1 2/7/2012 2/7/2012 2/7/2012 40 cm.

50 cm.

70 cm.

42.12 26.95 13.75 53.70 33.04 13.26

+/- 4.53

+/- 1.96

+/- 1.15 29.48 18.87 9.63

- 54.76

- 35.04

- 17.88 Pass Pass Pass I

2012-1 2012-1 2012-1 2/7/2012 2/7/2012 2/7/2012 75 cm.

80 cm.

90 cm.

11.98 10.53 8.32 13.38 11.27 7.79

+/- 1.68

+/- 0.95

+/- 0.83 8.39 7.37 5.82

- 15.57

- 13.69

- 10.82 Pass Pass Pass I

2012-1 2012-1 2012-1 2/7/2012 2/7/2012 2/7/2012 100 cm.

110 cm.

120 cm.

6.74 5.57 4.68 5.91 4.63 3.96

+/- 0.25

+/- 0.83

+/- 1.68 4.72 3.90 3.28

- 8.76

- 7.24

- 6.08 Pass Pass Pass I

2012-1 2/7/2012 150 cm. 2.99 2.41 +/- 0.08 2.09 - 3.89 Pass 2012-1 2/7/2012 180 cm. 2.08 2.02 +/- 0.25 1.46 -2.70 Pass I

Environmental, Inc.

I 2012-2 9/11/2012 40 cm. 33.75 43.74 +/- 1.31 23.63 - 43.88 Pass U 2012-2 2012-2 2012-2 2012-2 9/11/2012 9/11/2012 9/11/2012 9/11/2012 50 60 70 80 cm.

cm.

21.6 15 11.02 8.44 25.37 16.63 10.58 8.55

+/- 0.82

+/- 0.45

+/- 0.20

+/- 1.18 15.12 10.50 7.71 5.91 28.08 19.50 14.33 10.97 Pass Pass Pass Pass a

2012-2 2012-2 2012-2 9/11/2012 9/11/2012 9/11/2012 90 cm.

100 cm.

110 cm.

6.67 5.4 4.46 5.75 4.44 3.85

+/- 0.33

+/- 0.22

+/- 0.05 4.67 3.78 3.12

- 8.67

- 7.02

-5.80 Pass Pass Pass 1

2012-2 2012-2 2012-2 9/11/2012 9/11/2012 9/11/2012 120 cm.

150 cm.

180 cm.

3.75 2.4 1.67 3.03 1.82 1.19

+/- 0.71

+/- 0.10

+/- 0.34 2.63 1.68 1.17

- 4.88

-3.12

-2.17 Pass Pass Pass I

I I

A2-1 I

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 C Activity Limits d Acceptance SPW-41824 2/15/2012 Ra-228 24.85 +/- 2.14 28.75 20.13 -37.38 Pass W-22712 2/27/2012 Gr. Alpha 14.59 +/- 0.34 20.00 10.00 - 30.00 Pass W-22712 2/27/2012 Gr. Alpha 43.57 +/- 0.40 41.70 20.85 - 62.55 Pass SPAP-1032 3/5/2012 Cs-134 7.06 +/- 1.71 5.26 0.00 - 15.26 Pass SPAP-1032 3/5/2012 Cs-137 102.63 +/- 3.13 104.24 93.82 - 114.66 Pass SPAP-1034 3/5/2012 Gr. Beta 44.30 +/- 0.11 46.88 28.13 -65.63 Pass SPW-1 036 3/5/2012 Cs-134 43.23 +/- 3.84 39.42 29.42 - 49.42 Pass SPW-1036 3/5/2012 Cs-137 57.44 +/- 4.60 52.12 42.12 -62.12 Pass SPW-1036 3/5/2012 Sr-90 60.51 +/- 1.93 61.52 49.22 - 73.82 Pass SPMI-1038 3/512012 Cs-134 37.79 +/- 4.06 39.42 29.42 - 49.42 Pass SPM1-1038 3/5/2012 Cs-137 54.75 +/- 5.09 52.12 42.12 -62.12 Pass SPW-1 045 3/5/2012 H-3 68022 +/- 746 69048 55238 - 82858 Pass SPW-1 047 3/5/2012 Ni-63 217.10 +/- 3.64 206.64 144.65 - 268.63 Pass SPW-1049 3/5/2012 C-14 3858.90 +/- 12.79 4738.80 2843.28 - 6634.32 Pass W-31412 3/14/2012 Ra-226 13.13 +/- 0.36 16.70 11.69 - 21.71 Pass SPW-1 520 3/23/2012 U-238 45.67 +/- 2.02 41.70 29.19 -54.21 Pass SPW-41825 4/10/2012 Ra-228 28.48 +/- 2.51 28.35 19.85 -36.86 Pass WW-1547 4/16/2012 Ba-133 18.99 +/- 4.67 26.70 16.70 -36.70 Pass WW-1547 4/16/2012 Cs-134 9.28 +/- 2.82 8.68 0.00 - 18.68 Pass WW-1547 4/16/2012 Cs-137 27.77 +/- 4.49 29.70 19.70 -39.70 Pass W-51712 5/17/2012 Ra-226 17.29 +/- 0.43 16.70 11.69 - 21.71 Pass W-61112 6/11/2012 Gr. Alpha 22.16 +/- 0.45 20.00 10.00 - 30.00 Pass W-61112 6/11/2012 Gr. Beta 43.57 +/- 0.40 45.20 35.20 - 55.20 Pass SPAP-4418 7/25/2012 Gr. Beta 43.74 +/- 0.11 46.50 27.90 - 65.10 Pass SPAP-4420 7/25/2012 Cs-134 4.54 +/- 0.73 4.60 2.76 - 6.44 Pass SPAP-4420 7/25/2012 Cs-137 104.70 +/- 2.77 103.30 92.97 -113.63 Pass SPMI-4422 7/25/2012 Co-60 31.43 +/- 2.12 31.62 21.62 -41.62 Pass SPMI-4422 7/25/2012 Cs-134 16.50 +/- 1.17 16.15 6.15 -26.15 Pass SPMI-4422 7/25/2012 Cs-137 29.60 +/- 2.61 26.64 16.64 - 36.64 Pass SPMI-4422 7125/2012 Sr-90 31.60 +/- 1.35 30.47 24.38 - 36.56 Pass SPW-4424 7/25/2012 Co-60 38.52 +/- 1.76 37.95 27.95 - 47.95 Pass SPW-4424 7/25/2012 Cs-137 33.23 +/- 2.27 32.01 22.01 -42.01 Pass SPW-4424 7/25/2012 Sr-90 36.56 +/- 1.58 40.60 32.48 - 48.72 Pass SPF-4426 7/25/2012 Cs-134 947.50 +/- 42.50 1025.00 922.50 -1127.50 Pass SPF-4426 7/25/2012 Cs-137 2692.00 +/- 62.40 2480.00 2232.00 - 2728.00 Pass SPW-4428 7/25/2012 C-14 4325.70 +/- 15.80 4738.80 2843.28 - 6634.32 Pass SPW-4430 7/25/2012 H-3 70119.40 +/- 773.40 67570.00 54056.00 - 81084.00 Pass SPW-4432 7/25/2012 Ni-63 187.20 +/- 3.85 206.80 144.76 - 268.84 Pass W-81712 8/17/2012 Ra-226 14.94 +/- 0.40 16.70 11.69 - 21.71 Pass SPW-5407 8/29/2012 U-238 42.95 +/- 0.11 41.70 29.19 - 54.21 Pass SPW-18022 9/10/2012 Ra-228 29.03 +/- 2.80 28.21 19.75 -36.67 Pass A3-1

I TABLE A-3. In-House "Spiked" Samples I

Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control I a

2s, n=1 c Activity Limits d Acceptance W-91012 9/10/2012 Gr. Alpha 19.95 +/- 0.42 20.00 10.00 - 30.00 Pass W-91012 9/10/2012 Gr. Beta 43.47 +/- 0.40 45.20 35.20 - 55.20 Pass W-100312 10/3/2012 Gr. Alpha 19.95 +/- 0.41 20.00 10.00 - 30.00 Pass I

W-100312 10/3/2012 Gr. Beta 44.21 +/- 0.40 45.20 35.20 - 55.20 Pass W-101812 ESO-7235 SPW-7753 10/18/2012 12/6/2012 12/6/2012 Ra-226 Sr-90 U-238 18.80 138.79 45.55

+/- 0.43

+/- 2.67

+/- 5.05 16.70 161.05 41.70 11.69 128.84 29.19

- 21.71

- 193.26

-54.21 Pass Pass Pass I

SPW-18023 12/18/2012 Ra-228 31.59 +/- 2.99 25.98 18.19 - 33.77 Pass I

I U

I 1

U I

I I

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

b Laboratory codes : W (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).

c Results are based on single determinations.

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

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

I 3

A3-2 I

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

SPW-41814 Water 2/15/2012 Ra-228 0.65 0.49 +/- 0.36 2 W-22712 Water 2/27/2012 Gr. Alpha 0.42 -0.04 +/- 0.29 1 W-22712 Water 2/27/2012 Gr. Beta 0.74 -0.54 +/- 0.50 3.2 SPAP-1031 Air Filter 3/5/2012 Cs-134 1.89 100 SPAP-1031 Air Filter 3/5/2012 Cs-137 1.16 100 SPAP-1033 Air Filter 3/5/2012 Gr. Beta 0.003 0.013 +/- 0.003 0.01 SPW-1035 Water 3/5/2012 Cs-134 2.40 10 SPW-1035 Water 3/5/2012 Cs-137 2.88 10 SPW-1035 Water 315/2012 1-131(G) 2.35 20 SPW-1035 Water 3/5/2012 Sr-90 0.60 -0.11 +/- 0.26 1 SPM1-1037 Milk 3/5/2012 Cs-134 2.85 10 SPM1-1037 Milk 3/5/2012 Cs-137 3.73 10 SPM I-1037 Milk 3/5/2012 1-131(G) 3.24 20 SPW-1044 Water 3/5/2012 H-3 146.10 37.10 +/- 74.40 200 SPW-1046 Water 3/5/2012 Ni-63 19.07 8.30 +/- 11.79 20 SPW-1048 Water 3/5/2012 C-14 5.70 2.99 +/- 3.04 200 SPW-1 166 water 3/9/2012 C-14 6.79 1.11 200 W-31412 Water 3/14/2012 Ra-226 0.034 0.043 +/- 0.027 1 SPW-1521 Water 3/23/2012 U-238 0.10 0.09 +/- 0.11 1 W-51712 Water 4/24/2012 Ra-226 0.04 0.04 +/- 0.03 1 W-61112 Water 6/11/2012 Gr. Alpha 0.47 -0.14 +/- 0.32 1 W-61112 Water 6/11/2012 Gr. Beta 0.71 0.29 +/- 0.51 3.2 SPW-41815 Water 7/7/2011 Ra-228 0.77 0.52 +/- 0.42 2 SPAP-4417 Air Filter 7/25/2012 Gr. Beta 0.001 0.021 +/- 0.003 0.01 SPMI-4421 Milk 7/25/2012 Co-60 4.29 10 SPMI-4421 Milk 7/25/2012 Cs-1 34 3.58 10 SPMI-4421 Milk 7/25/2012 Cs-137 4.60 10 SPMI-4421 Milk 7/25/2012 Sr-90 0.45 0.53 +/- 0.27 1 SPW-4423 Water 7/25/2012 Co-60 1.88 10 SPW-4423 Water 7/25/2012 Cs-134 2.38 10 SPW-4423 Water 7/25/2012 Cs-137 2.80 10 SPW-4423 water 7/25/2012 Sr-90 0.45 0.08 +/- 0.22 1 SPF-4425 Fish 7/25/2012 Co-60 6.74 100 SPF-4425 Fish 7/25/2012 Cs-134 7.47 100 SPF-4425 Fish 7/25/2012 Cs-137 9.62 100 SPW-4427 Water 7/25/2012 C-14 10.93 3.54 +/- 5.84 200 SPW-4431 Water 7/25/2012 Ni-63 19.00 5.50 +/- 11.70 20 W-81712 Water 8/17/2012 Ra-226 0.038 0.035 +/- 0.030 1 SPW-5408 Water 8/29/2012 U-238 0.039 0.015 +/- 0.057 1 A4-1

U TABLE A-4. In-House "Blank" Samples I Lab Code Sample Date Analysis" Concentration (pCi/L)a Laboratory results (4.66o) Acceptance I SPW-1 8032 Type Water 9/10/2012 Ra-228 LLD 0.78 Activityc 0.85 +/- 0.46 Criteria (4.66 a) 2 a

W-91012 W-91012 W-100312 Water Water Water 9/10/2012 9/10/2012 10/3/2012 Gr. Alpha Gr. Beta Gr. Beta 0.42 0.75 0.77 0.027

-0.13

-0.32

+/-

0.29 0.52 0.53 1

3.2 3.2 I

W-100312 Water 10/3/2012 Gr. Beta 0.43 0.06 +/- 0.30 3.2 W-101812 SPW-7754 SPW-1 8033 Water Water Water 10/18/2012 12/6/2012 12/18/2012 Ra-226 U-238 Ra-228 0.04 0.10 0.98 0.038 0.022 0.43

+/-

0.031 0.075 0.50 2 I

I I

I a

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

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

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

a g

I I

A4-2 I

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 1/3/2012 Gr. Beta 14.50 +/- 0.29 15.02 +/- 0.30 14.76 +/- 0.21 Pass CF-20, 21 1/3/2012 K-40 12.88 +/- 0.55 12.40 +/- 0.53 12.64 +/- 0.38 Pass CF-20, 21 1/3/2012 Sr-90 0.01 +/- 0.01 0.01 +/- 0.01 0.01 +/- 0.00 Pass P-9133, 9134 1/3/2012 H-3 108.86 +/- 83.03 206.60 +/- 86.38 157.73 +/- 59.91 Pass U-302, 303 1/17/2012 Beta (-K40) 6.84 +/- 2.91 5.24 +/- 2.56 6.04 +/- 1.94 Pass S-386, 387 1/23/2012 Ac-228 0.77 +/- 0.11 0.79 +/- 0.14 0.78 +/- 0.09 Pass S-386, 387 1/23/2012 Bi-214 0.80 +/- 0.07 0.73 +/- 0.11 0.77 +/- 0.07 Pass S-386, 387 1/23/2012 Pb-214 0.74 +/- 0.06 0.75 +/- 0.11 0.75 +/- 0.06 Pass S-386, 387 1/23/2012 TI-208 0.21 +/- 0.02 0.21 +/- 0.04 0.21 +/- 0.02 Pass S-386, 387 1/23/2012 U-235 0.05 +/- 0.02 0.12 +/- 0.05 0.09 +/- 0.03 Pass WW-619, 620 1/31/2012 H-3 257.20 +/- 86.00 305.80 +/- 88.30 281.50 +/- 61.63 Pass MI-702, 703 2/6/2012 K-40 1337.00 +/- 123.00 1460.40 +/- 102.00 1398.70 +/- 79.90 Pass WW-892, 893 2/17/2012 Gr. Beta 3.46 +/- 0.56 3.77 +/- 0.59 3.61 +/- 0.41 Pass S-850, 851 2/22/2012 Cs-134 0.14 +/- 0.02 0.13 +/- 0.02 0.14 +/- 0.01 Pass S-850, 851 2/22/2012 Cs-137 0.21 +/- 0.03 0.22 +/- 0.03 0.22 +/- 0.02 Pass W-1251, 1252 3/6/2012 Gr. Alpha 1.20 +/- 0.62 1.27 +/- 0.92 1.24 +/- 0.55 Pass W-1251, 1252 3/6/2012 Gr. Beta 16.86 +/- 1.43 15.14 +/- 1.34 16.00 +/- 0.98 Pass W-1251, 1252 3/6/2012 H-3 5235.52 +/- 230.91 4893.24 +/- 224.55 5064.38 +/- 161.05 Pass W-1251, 1252 3/6/2012 Tc-99 19.67 +/- 3.60 14.46 +/- 3.51 17.07 +/- 2.51 Pass AP-1209, 1210 3/8/2012 Be-7 0.24 +/- 0.12 0.20 +/-0.11 0.22 +/- 0.08 Pass XWW-1564, 1565 3/14/2012 H-3 308.00 +/- 88.00 293.00 +/- 87.00 300.50 +/- 61.87 Pass SG-1438, 1439 3/19/2012 Ac-228 6.01 +/- 0.30 6.23 +/- 0.31 6.12 +/- 0.22 Pass SG-1438, 1439 3/19/2012 Pb-214 4.69 +/- 0.49 5.20 +/- 0.54 4.95 +/- 0.36 Pass WW-1 585, 1586 3/19/2012 H-3 3124.50 +/- 176.96 2982.38 +/- 173.62 3053.44 +/- 123.96 Pass AP-2103, 2104 3/28/2012 Be-7 0.080 +/- 0.016 0.076 +/- 0.013 0.078 +/- 0.010 Pass AP-2166, 2167 3/28/2012 Be-7 0.061 +/- 0.020 0.071 +/- 0.016 0.066 +/- 0.013 Pass AP-1632, 1633 3/29/2012 Be-7 0.26 +/- 0.12 0.24 +/- 0.12 0.25 +/- 0.08 Pass E-1653, 1654 4/2/2012 Gr. Beta 1.53 +/- 0.05 1.55 +/- 0.04 1.54 +/- 0.03 Pass E-1653, 1654 4/2/2012 K-40 1.34 +/- 0.13 1.36 +/- 0.14 1.35 +/- 0.10 Pass SG-1677, 1678 4/2/2012 Ac-228 6.63 +/- 0.37 6.49 +/- 0.33 6.56 +/- 0.25 Pass SG-1677, 1678 4/2/2012 Pb-214 4.77 +/- 0.16 5.07 +/- 0.14 4.92 +/- 0.11 Pass SWU-1719, 1720 4/3/2012 Gr. Beta 1.16 +/- 0.41 1.53 +/- 0.44 1.35 +/- 0.30 Pass W-1698, 1699 4/5/2012 Gr. Beta 10.86 +/- 1.49 9.42 +/- 1.32 10.14 +/- 1.00 Pass W-1698, 1699 4/5/2012 Ra-226 0.41 +/- 0.15 0.67 +/- 0.18 0.54 +/- 0.12 Pass W-1698, 1699 4/5/2012 Ra-228 1.46 +/- 0.76 1.48 +/- 0.74 1.47 +/- 0.53 Pass SG-1761, 1762 4/10/2012 Ac-228 16.26 +/- 0.53 16.55 +/- 0.44 16.41 +/- 0.34 Pass SG-1761, 1762 4/10/2012 Pb-214 14.16 +/- 1.44 15.40 +/- 1.56 14.78 +/- 1.06 Pass AP-2019, 2020 4/12/2012 Be-7 0.17 +/- 0.10 0.17 +/- 0.08 0.17 +/- 0.07 Pass DW-2272, 2273 4/20/2012 1-131 0.52 +/- 0.24 0.49 +/- 0.27 0.51 +/- 0.18 Pass DW-2356, 2357 4/24/2012 Gr. Beta 12.82 +/- 2.01 9.47 +/- 1.74 11.14 +/- 1.33 Pass A5-1

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

Concentration (pCi/L)a Lab Code Date Analysis First Result Second Result Averaged Result Acceptance I

G-2403, 2404 G-2403, 2404 5/1/2012 5/1/2012 Be-7 K-40 1.77 6.38

+/- 0.21

+/- 0.50 1.55 6.93

+/-

0.33 0.72 1.66 6.66

+/- 0.20

+/- 0.44 Pass Pass 3 BS-2445, 2446 5/11/2012 Gr. Beta 8.92 +/- 1.52 9.29 +/- 1.63 9.11 +/- 1.11 Pass BS-2445, 2446 SWU-2550, 2551 WW-2614, 2615 5/11/2012 5/1/2012 5/1/2012 K-40 Gr. Beta Gr. Beta 5.86 2.07 2.03

+/- 0.38

+/- 0.65

+/- 1.04 6.22 1.59 2.36

+/-

0.48 0.62 1.14 6.04 1.83 2.20

+/- 0.31

+/- 0.45

+/- 0.77 Pass Pass Pass I

WW-2614, 2615 BS-2656, 2657 BS-2656, 2657 5/1/2012 5/2/2012 5/2/2012 H-3 Cs-137 K-40 750.60 0.13 10.15

+/- 106.20

+/- 0.07

+/- 0.97 653.20 0.07 11.13

+/- 102.30

+/- 0.04

+/- 0.90 701.90 0.10 10.64

+/- 73.73

+/- 0.04

+/- 0.66 Pass Pass Pass 3

SO-2635, 2636 SO-2635, 2636 MI-2677, 2678 5/3/2012 5/3/2012 5/7/2012 Cs-137 K-40 K-40 0.046 13.20 1415.30

+/- 0.024

+/- 0.74

+/- 131.40 0.050 14.01 1348.10

+/- 0.027

+/- 0.67

+/- 109.00 0.048 13.61 1381.70

+/- 0.018

+/- 0.50

+/- 85.36 Pass Pass Pass I

VE-2719, 2720 5/7/2012 K-40 4.15 +/- 0.36 4.19 +/- 0.38 4.17 +/- 0.26 Pass SWU-3221, 3222 SWU-3221, 3222 5/8/2012 5/8/2012 Gr. Beta H-3 1.67 236.90

+/- 0.47

+/- 101.90 1.39 281.90

+/- 0.45

+/- 103.70 1.53 259.40

+/- 0.33

+/- 72.69 Pass Pass I

WW-3073, 3074 5/14/2012 H-3 339.12 +/- 145.45 337.23 +/- 98.19 338.18 +/- 87.74 Pass AP-2968, 2969 F-3031, 3032 F-3031, 3032 5/17/2012 5/22/2012 5/22/2012 Be-7 H-3 K-40 0.25 11291.00 3528.90

+/- 0.12

+/- 372.80

+/- 372.80 0.21 11167.00 3677.20

+/- 0.09

+/- 315.00

+/- 392.40 0.23 11229.00 3603.05

+/- 0.07

+/- 244.03

+/- 270.63 Pass Pass Pass I

G-3094, 3095 F-3412, 3413 F-3412, 3413 5/23/2012 5/23/2012 5/23/2012 Gr. Beta Gr. Beta K-40 7.89 3.46 2.40

+/- 0.16

+/- 0.10

+/- 0.38 8.01 3.33 2.55

+/- 0.16

+/- 0.10

+/- 0.43 7.95 3.40 2.48

+/- 0.11

+/- 0.07

+/- 0.29 Pass Pass Pass I

MI-3067, 3068 SO-3305, 3306 SO-3305, 3306 5/24/2012 5/30/2012 5/30/2012 K-40 Cs-137 Gr. Beta 1267.20 0.024 10.95

+/- 105.00

+/- 0.013

+/- 0.89 1305.70 0.030 10.86

+/- 109.80

+/- 0.015

+/- 0.89 1286.45 0.027 10.91

+/- 75.96

+/- 0.010

+/- 0.63 Pass Pass Pass I

Pass SO-3305, 3306 LW-3454, 3455 BS-3697, 3698 5/30/2012 5/31/2012 6/14/2012 TI-208 Gr. Beta Be-7 0.068 2.12 2.05

+/- 0.018

+/- 0.86

+/- 0.19 0.062 2.27 2.27

+/- 0.017

+/- 0.77

+/- 0.38 0.065 2.20 2.16

+/- 0.012

+/- 0.58

+/- 0.21 Pass Pass I

BS-3697, 3698 6/14/2012 Cs-137 2.32 +/- 0.39 2.26 +/- 0.66 2.29 +/- 0.38 Pass BS-3697, 3698 VE-3798, 3799 6/14/2012 6/20/2012 K-40 K-40 6.67 5.93

+/- 0.28

+/- 0.38 6.64 6.03

+/- 0.42

+/- 0.37 6.66 5.98

+/- 0.25

+/- 0.26 Pass Pass 1

WW-4790, 4791 6/20/2012 H-3 251.33 +/- 86.51 372.48 +/- 92.27 311.90 +/- 63.24 Pass DW-30103, 30104 DW-30103, 30104 LW-3970, 3971 6/27/2012 6/27/2012 6/28/2012 Ra-226 Ra-228 Gr. Beta 0.30 0.76 1.49

+/- 0.08

+/- 0.54

+/- 1.06 0.42 0.78 0.72

+/- 0.09

+/- 0.54

+/- 0.53 0.36 0.77 1.11

+/- 0.06

+/- 0.38

+/- 0.59 Pass Pass Pass I

DW-3949, 3950 SG-4075, 4076 SG-4075, 4076 6/29/2012 7/2/2012 7/2/2012 1-131 Ac-228 K-40 0.54 0.33 6.71

+/- 0.26

+/- 0.09

+/- 0.58 0.25 0.34 7.20

+/- 0.26

+/- 0.06

+/- 0.32 0.40 0.34 6.96

+/- 0.18

+/- 0.05

+/- 0.33 Pass Pass Pass U

SG-4075, 4076 AP-4390, 4391 AP-4390, 4391 7/2/2012 7/3/2012 7/3/2012 Pb-214 Be-7 Be-7 0.46 0.09 0.11

+/- 0.05

+/- 0.02

+/-0.02 0.49 0.09 0.10

+/- 0.03

+/- 0.01

+/- 0.01 0.48 0.09 0.11

+/- 0.03

+/- 0.01

+/- 0.01 Pass Pass Pass I

0.29 +/- 0.16 Pass I

AP-4012, 4013 7/5/2012 Be-7 0.27 +/- 0.09 0.28 +/- 0.09 SW-4033, 4034 7/5/2012 H-3 614.99 +/- 107.99 512.31 +/- 103.83 563.65 +/- 74.91 Pass I

A5-2 U

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4054, 4055 7/9/2012 K-40 7.28 +/- 0.56 7.42 +/- 0.63 7.35 +/- 0.42 Pass VE-4222, 4223 7/13/2012 Be-7 0.16 +/- 0.08 0.22 +/- 0.09 0.19 +/- 0.06 Pass VE-4222, 4223 7/13/2012 K-40 7.20 +/- 0.30 6.60 +/- 0.30 6.90 +/- 0.21 Pass DW-30113, 30114 7/13/2012 Ra-228 1.93 +/- 0.66 1.03 +/- 0.53 1.48 +/- 0.42 Pass DW-30115, 30116 7/13/2012 Gr. Alpha 7.46 +/- 1.21 7.02 +/- 1.14 7.24 +/- 0.83 Pass DW-30124, 30125 7/13/2012 Ra-226 1.16 +/- 0.15 0.90 +/- 0.12 1.03 +/- 0.10 Pass DW-30124, 30125 7/13/2012 Ra-228 1.38 +/- 0.56 1.72 +/- 0.60 1.55 +/- 0.41 Pass DW-30126, 30127 7/13/2012 Gr. Alpha 6.23 +/- 1.16 6.75 +/- 1.29 6.49 +/- 0.87 Pass AP-4433, 4434 7/19/2012 Be-7 0.17 +/- 0.09 0.21 +/- 0.10 0.19 +/- 0.07 Pass SG-4475, 4476 7/19/2012 Gr. Alpha 17.03 +/-4.17 15.56 +/- 3.96 16.30 +/- 2.88 Pass SG-4475, 4476 7/19/2012 Gr. Beta 13.23 +/- 2.61 14.36 +/- 2.47 13.80 +/- 1.80 Pass WW-4685, 4686 7/24/2012 H-3 289.00 +/- 99.00 375.00 +/- 103.00 332.00 +/- 71.43 Pass AP-4706, 4707 7/26/2012 Be-7 0.28 +/- 0.14 0.24 +/- 0.14 0.26 +/- 0.10 Pass SO-4748, 4749 7/26/2012 Gr.Beta 20.45 +/- 1.04 19.22 +/- 0.94 19.84 +/- 0.70 Pass SO-4748, 4749 7/26/2012 U-233/4 0.11 +/- 0.02 0.10 +/- 0.01 0.11 +/- 0.01 Pass SO-4748, 4749 7/26/2012 U-238 0.12 +/- 0.02 0.11 +/- 0.01 0.12 +/- 0.01 Pass VE-4832, 4833 8/1/2012 K-40 4.06 +/- 0.22 4.08 +/- 0.24 4.07 +/- 0.16 Pass DW-30149, 30150 8/1/2012 Ra-226 2.69 +/- 0.22 2.79 +/- 0.22 2.74 +/- 0.16 Pass DW-30149, 30150 8/1/2012 Ra-228 2.77 +/- 0.75 1.61 +/- 0.57 2.19 +/- 0.47 Pass SG-4916, 4917 8/3/2012 Ac-228 11.03 +/- 0.33 11.08 +/- 0.44 11.06 +/- 0.28 Pass SG-4916, 4917. 8/3/2012 K-40 6.39 +/- 0.80 6.98 +/- 0.88 6.69 +/- 0.59 Pass F-5313, 5314 8/9/2012 Cs-137 0.05 +/- 0.02 0.05 +/- 0.02 0.05 +/- 0.01 Pass F-5313, 5314 8/9/2012 Gr. Beta 4.12 +/- 0.08 4.10 +/- 0.08 4.11 +/- 0.06 Pass F-5313, 5314 8/9/2012 K-40 3.07 +/- 0.42 3.14 +/- 0.40 3.11 +/- 0.29 Pass VE-5166, 5167 8/15/2012 K-40 4.26 +/- 0.28 3.66 +/- 0.47 3.96 +/- 0.27 Pass VE-5376, 5377 8/22/2012 Gr. Beta 7.72 +/- 0.17 7.61 +/- 0.16 7.67 +/- 0.12 Pass VE-5334, 5335 8/27/2012 K-40 1.65 +/- 0.17 1.72 +/- 0.15 1.68 +/- 0.12 Pass VE-5481, 5482 8/28/2012 Be-7 2.52 +/- 0.19 2.65 +/- 0.21 2.59 +/- 0.14 Pass VE-5481, 5482 8/28/2012 K-40 5.05 +/- 0.37 4.79 +/- 0.39 4.92 +/- 0.27 Pass VE-5481, 5482 8/28/2012 Sr-90 0.01 +/- 0.00 0.01 +/- 0.01 0.01 +/- 0.00 Pass DW-30164, 30165 8/30/2012 Ra-226 1.33 +/- 0.15 1.59 +/- 0.17 1.46 +/- 0.11 Pass DW-30164, 30165 8/30/2012 Ra-228 2.76 +/- 0.66 1.54 +/- 0.56 2.15 +/- 0.43 Pass VE-5166, 5167 9/4/2012 K-40 2.05 +/- 0.32 2.53 +/- 0.36 2.29 +/- 0.24 Pass ME-5607, 5608 9/4/2012 Gr. Beta 2.92 +/- 0.08 2.89 +/- 0.08 2.90 +/- 0.06 Pass ME-5607, 5608 9/4/2012 K-40 2.06 +/- 0.32 2.53 +/- 0.36 2.29 +/- 0.24 Pass SW-5901, 5902 9/17/2012 H-3 10909.00 +/- 311.00 10817.00 +/- 310.00 10863.00 +/- 219.56 Pass BS-6048, 6049 9/24/2012 K-40 1.24 +/- 0.20 1.18 +/- 0.21 1.21 +/- 0.14 Pass AP-6482, 6483 9/27/2012 Be-7 0.09 +/- 0.02 0.09 +/- 0.03 0.09 +/- 0.02 Pass A5-3

U TABLE A-5. In-House "Duplicate" Samples I

Concentration (pCi/L)a Lab Code Date Analysis First Result Second Result Averaged Result Acceptance I

G-6090,6091 G-6090,6091 G-6090,6091 10/1/2012 10/1/2012 10/11/2012 Be-7 Gr. Beta K-40 3.74 10.81 5.99

+/- 0.33

+/- 0.34

+/- 0.47 3.54 10.72 5.45

+/-

0.30 0.33 0.44 3.64 10.77 5.72

+/- 0.22

+/- 0.24

+/- 0.32 Pass Pass Pass I

SO-6111, 6112 SO-6111, 6112 W-6795, 6796 10/1/2012 10/1/2012 10/1/2012 Cs-137 K-40 H-3 0.06 19.66 215.20

+/- 0.03

+/- 0.84

+/- 88.00 0.04 20.09 292.80

+/-

0.02 0.80 91.60 0.05 19.88 254.00

+/- 0.02

+/- 0.58

+/- 63.51 Pass Pass Pass I

AP-6461, 6462 WW-6279,6280 W-6346,6347 10/2/2012 10/3/2012 10/3/2012 Be-7 Gr. Beta Ra-226 0.07 1.54 0.30

+/- 0.01

+/- 0.68

+/- 0.10 0.07 1.67 0.36

+/- 0.02

+/- 0.75

+/- 0.10 0.07 1.61 0.33

+/- 0.01

+/- 0.51

+/- 0.07 Pass Pass Pass I

VE-6503, 6504 WW-6606,6607 WW-6606,6607 10/9/2012 10/10/2012 10/10/2012 K-40 Gr. Beta H-3 5.23 3.18 273.10

+/- 0.83

+/-

1.31 85.70 6.00 2.42 219.80

+/- 0.45

+/- 1.27

+/- 83.10 5.04 2.80 246.45

+/- 0.27

+/- 0.91

+/- 59.69 Pass Pass Pass I

WW-7237, 7238 10/12/2012 H-3 175.44 +/- 99.84 180.75 +/- 100.03 178.10 +/- 70.66 Pass F-6627, 6628 VE-6669, 6670 10/15/2012 10/16/2012 K-40 Be-7 3.05 0.48

+/-

0.39 0.26 3.23 0.50

+/- 0.37

+/- 0.13 3.14 0.49

+/- 0.27

+/- 0.15 Pass Pass I

VE-6669, 6670 10/16/2012 K-40 4.06 +/- 0.28 3.68 +/- 0.26 3.87 +/- 0.19 Pass SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 10/16/2012 10/16/2012 10/16/2012 Ac-228 Bi-214 0.16 0.13 14.20

+/-

0.05 0.03 0.89 0.17 0.16 12.67

+/- 0.06

+/- 0.03

+/- 0.88 0.17 0.14 13.44

+/- 0.04

+/- 0.02

+/- 0.63 Pass Pass Pass I

Gr. Beta +/-

SS-6711, 6712 SS-6711, 6712 WW-7258, 7259 10/16/2012 10/16/2012 10/22/2012 Pb-212 TI-208 H-3 0.15 0.06 214.69

+/-

0.06 0.02 85.42 0.13 0.04 314.60

+/- 0.02

+/- 90.25 0.14 0.05 264.65

+/- 0.03

+/- 0.01

+/- 62.13 Pass Pass Pass U

WW-7655, 7656 WW-7747, 7748 MI-6963, 6964 10/25/2012 10/25/2012 10/28/2012 H-3 H-3 K-40 159.00 156.50 1384.60

+/-

86.10 84.70 111.70 159.00 170.20 1421.60

+/- 86.10

+/- 85.30

+/- 107.60 159.00 163.35 1403.10

+/- 60.88

+/- 60.10

+/- 77.55 Pass Pass Pass I

MI-7174, 7175 SG-7221, 7222 DW-30216, 30217 11/5/2012 11/9/2012 11/9/2012 K-40 Pb-214 Gr. Alpha 1283.60 31.49 2.23

+/-

97.45 0.70 0.86 1293.20 30.11 2.31

+/- 91.37

+/-0.80

+/- 0.92 1288.40 30.80 2.27

+/- 66.79

+/- 0.53

+/- 0.63 Pass Pass Pass I

DW-30216, 30217 11/9/2012 Ra-226 0.72 +/- 0.12 0.82 +/- 0.14 0.77 +/- 0.09 Pass DW-30216, 30217 MI-7363, 7364 11/9/2012 11/13/2012 Ra-228 K-40 0.92 1304.40

+/-

0.52 103.30 1.26 1496.10

+/- 0.53

+/- 121.30 1.09 1400.25

+/- 0.37

+/- 79.66 Pass Pass N

CF-7384, 7385 11/13/2012 K-40 11.75 +/- 0.52 10.94 +/- 0.59 11.35 +/- 0.39 Pass VE-7489, 7490 AP-7531, 7532 BS-7573,7574 11/16/2012 11/21/2012 11/24/2012 K-40 Be-7 K-40 2.22 0.19 7.21

+/-

0.23 0.10 0.41 1.91 0.29 7.57

+/- 0.22

+/- 0.17

+/- 0.39 2.06 0.24 7.39

+/- 0.16

+/- 0.10

+/- 0.28 Pass Pass Pass I

LW-7865, 7866 SG-8095, 8096 SG-8095, 8096 12/5/2012 12/19/2012 12/19/2012 Gr. Beta Ac-228 Gamma 2.16 25.15 26.98

+/-

0.56 0.73 2.72 1.64 25.47 28.68

+/- 0.62

+/- 0.54

+/- 2.89 1.90 25.31 27.83

+/- 0.42

+/- 0.45

+/- 1.98 Pass Pass Pass

£ Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those I

I analyses with activities that measure below the LLD.

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

1 A5-4 I

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits C Acceptance STW-1670 02/01/12 1-129 9.31 +/- 0.31 12.29 8.60 - 15.98 Pass STSO-1766 d 02/01/12 Am-241 88.50 +/- 8.30 159.00 111.00 -207.00 Fail STSO-1766 02/01/12 Co-57 1352.10 +/- 4.00 1179.00 825.00 - 1533.00 Pass STSO-1766 02/01/12 Co-60 1.70 +/- 0.70 1.56 1.00 - 2.00 Pass STSO-1766 02/01/12 Cs-134 842.20 +/- 4.30 828.00 580.00 - 1076.00 Pass STSO-1766 02/01/12 Cs-1 37 0.40 +/- 0.90 0.00 0.00 - 1.00 Pass STSO-1766 02/01/12 K-40 1729.60 +/- 22.20 1491.00 1044.00 - 1938.00 Pass STSO-1766 02/01/12 Mn-54 647.60 +/- 4.20 558.00 391.00 -725.00 Pass STSO-1766 02/01/12 Ni-63 781.50 +/- 9.70 862.00 603.00 - 1121.00 Pass STSO-1766 02/01/12 Pu-238 142.40 +/- 9.70 136.00 97.00 - 177.00 Pass STSO-1766 02/01/12 Pu-239/40 66.10 +/- 6.40 65.80 46.10 - 85.50 Pass STSO-1766 02/01/12 Sr-90 383.20 +/- 15.30 392.00 274.00 - 510.00 Pass STSO-1766 02/01/12 Tc-99 289.60 +/- 10.90 374.00 262.00 - 486.00 Pass STSO-1766 02/01/12 U-233/4 63.20 +/- 5.40 68.10 47.70 - 88.50 Pass STSO-1766 02/01/12 U-238 310.80 +/- 12.10 329.00 230.00 - 428.00 Pass STSO-1766 02/01/12 Zn-65 766.70 +/- 6.70 642.00 449.00 - 835.00 Pass STAP-1 772 02/01/12 Am-241 0.062 +/- 0.02 0.073 0.051 -0.10 Pass STAP-1 772 02/01/12 Co-57 0.010 +/- 0.01 0.00 0.000 - 1.00 Pass STAP-1772 02/01/12 Co-60 2.40 +/- 0.08 2.18 1.53 -2.84 Pass STAP-1772 02/01/12 Cs-134 2.33 +/- 0.13 2.38 1.67 - 3.09 Pass STAP-1 772 02/01/12 Cs-1 37 2.07 +/- 0.10 1.79 1.25 - 2.33 Pass STAP-1 772 02/01/12 Mn-54 3.77 +/- 0.14 3.24 2.27 - 4.21 Pass STAP-1 772 02/01/12 Pu-238 0.003 +/- 0.004 0.002 0.000 -0.10 Pass STAP-1772 02/01/12 Pu-239/40 0.098 +/- 0.017 0.097 0.07 -0.13 Pass STAP-1 772 02/01/12 Sr-90 -0.010 +/- 0.060 0.000 -0.10 -0.13 Pass STAP-1 772 e 02/01/12 U-233/4 0.016 +/- 0.006 0.019 0.013 - 0.024 Pass STAP-1 772 02/01/12 U-238 0.11 +/- 0.02 0.12 0.09 -0.16 Pass STAP-1772 02/01/12 Zn-65 3.67 +/- 0.20 2.99 2.09 - 3.89 Pass STAP-1 773 02/01/12 Gr. Alpha 0.51 +/- 0.05 1.20 0.40 - 2.00 Pass STAP-1 773 02/01/12 Gr. Beta 2.75 +/- 0.10 2.40 1.20 - 3.60 Pass STVE-1 776 02/01/12 Co-57 14.57 +/- 0.28 12.00 8.40 - 15.60 Pass STVE-1 776 02/01/12 Co-60 6.45 +/- 0.23 6.05 4.24 - 7.87 Pass STVE-1 776 02/01/12 Cs-134 8.39 +/- 0.29 8.43 5.90 - 10.96 Pass STVE-1 776 02/01/12 Cs-1 37 0.01 +/- 0.09 0.00 0.00 -0.10 Pass STVE-1 776 02/01/12 Mn-54 0.03 +/- 0.08 0.00 0.00 -0.10 Pass STVE-1 776 02/01/12 Zn-65 10.31 +/- 0.67 8.90 6.23-11.57 Pass STW-1960 02/01/12 Gr. Alpha 1.68 +/- 0.09 2.14 0.64 - 3.64 Pass STW-1960 02/01/12 Gr. Beta 6.33 +/- 0.10 6.36 3.18 -9.54 Pass A6-1

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

I Concentration a Lab Code b Date Analysis Laboratory result Known Activity Control Limits c Acceptance I

STW-1964 STW-1964 STW- 1964 02/01/12 02/01/12 02/01/12 Am-241 Co-57 Co-60 1.28 33.30 23.20

+/-

0.12 0.40 0.40 1.63 32.90 23.72 1.14 23.00 16.60

-2.12

- 42.80

- 30.84 Pass Pass Pass I

STW-1964 02/01/12 Cs-1 34 0.30 +/- 3.00 0.00 0.00 - 1.00 Pass STW-1964 02/01/12 Cs-137 40.10 +/- 0.60 39.90 27.90 - 51.90 Pass STW-1964 STW-1 964 STW-1 964 02/01/12 02/01/12 02/01/12 Fe-55 H-3 K-40 65.10 460.00 153.00

+/-

9.50 12.10 4.20 81.90 437.00 142.00 57.30 306.00 99.00

- 106.50

- 568.00

- 185.00 Pass Pass Pass I

STW-1 964 02/01/12 Mn-54 32.70 +/- 0.60 31.80 22.30 - 41.30 Pass STW-1 964 STW- 1964 STW- 1964 02/01/12 02/01/12 02/01/12 Ni-63 Pu-238 Pu-239/40 49.80 0.58 1.30

+/-

2.90 0.06 0.15 60.00 0.63 1.34 42.00 0.44 0.94

- 78.00

- 0.82

-1.74 Pass Pass Pass U

STW- 1964 02/01/12 Sr-90 0.10 +/- 0.20 0.00 0.00 - 1.00 Pass STW- 1964 02/01/12 Tc-99 23.70 +/- 0.80 27.90 19.50 - 36.30 Pass STW- 1964 02/01/12 U-233/4 0.40 +/- 0.05 0.39 0.27 - 0.51 Pass STW- 1964 02/01/12 U-238 2.67 +/- 0.13 2.76 1.93 - 3.59 Pass STW- 1964 02/01/12 Zn-65 0.01 +/- 0.20 0.00 0.00 - 1.00 Pass STW-5391 08/01/12 1-129 5.73 +/- 0.28 6.82 4.77 - 8.87 Pass STSO-5392 08/01/12 Am-241 129.30 +/- 12.70 111.00 78.00 - 144.00 Pass STSO-5392 08/01/12 Ni-63 376.20 +/- 20.60 406.00 284.00 - 528.00 Pass STSO-5392 STSO-5392 STSO-5392 08/01/12 08/01/12 08/01/12 Pu-238 Pu-239/40 Sr-90 118.70 140.70 483.52

+/- 9.30

+/- 9.90

+/- 16.47 105.80 134.00 508.00 74.10 94.00 356.00

- 137.50

- 174.00

- 660.00 Pass Pass Pass I

STSO-5392 08/01/12 Tc-99 432.50 +/- 23.10 469.00 328.00 -610.00 Pass STSO-5394 STSO-5394 STSO-5394 08/01/12 08/01/12 08/01/12 Co-57 Co-60 Cs-134 1528.00 592.00 933.60

+/- 4.10

+/- 3.20

+/- 5.82 1316.00 531.00 939.00 921.00 372.00 657.00

- 1711.00

- 690.00

- 1221.00 Pass Pass Pass I

STSO-5394 STSO-5394 STSO-5394 08/01/12 08/01/12 08/01/12 Cs-137 K-40 Mn-54 1319.80 737.30 1083.20

+/- 5.50

+/- 17.70

+/- 5.20 1150.00 632.00 920.00 805.00 442.00 644.00

- 1495.00

- 822.00

- 1196.00 Pass Pass Pass 3

STSO-5394 08/01/12 U-233/4 55.80 +/- 4.20 60.30 42.20 - 78.40 Pass STSO-5394 08/01/12 U-238 231.20 +/- 8.60 263.00 184.00 - 342.00 Pass STSO-5394 08/01/12 Zn-65 696.10 +/- 7.00 606.00 424.00 - 788.00 Pass I

I A6-2

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance STVE-5395 g 08/01/12 Co-57 7.44 +/- 0.17 5.66 3.96 - 7.36 Fail STVE-5395 08/01/12 Co-60 5.90 +/- 0.15 5.12 3.58 - 6.66 Pass STVE-5395 08/01/12 Cs-134 7.40 +/- 0.31 6.51 4.56 - 8.46 Pass STVE-5395 08/01/12 Cs-137 5.45 +/- 0.18 4.38 3.07 - 5.69 Pass STVE-5395 08/01/12 Mn-54 4.06 +/- 0.21 3.27 2.29 -4.25 Pass STAP-5398 08/01/12 Gr. Alpha 0.41 +/- 0.05 0.97 0.29 - 1.65 Pass STAP-5398 08/01/12 Gr. Beta 2.11 +/- 0.09 1.92 0.96 - 2.88 Pass STAP-5401 h 08/01/12 Am-241 0.12 +/- 0.02 0.08 0.05 -0.10 Fail STAP-5403 08/01/12 Co-57 1.96 +/- 0.05 1.91 1.34 -2.48 Pass STAP-5403 08/01/12 Co-60 1.76 +/- 0.07 1.73 1.21 -2.25 Pass STAP-5403 08/01/12 Cs-134 2.74 +/- 0.18 2.74 1.92 -3.56 Pass STAP-5403 08/01/12 Cs-1 37 0.00 +/- 0.03 0.00 -0.01 -0.01 Pass STAP-5403 08/01/12 Mn-54 2.52 +/- 0.10 2.36 1.65 -3.07 Pass STAP-5403 08/01/12 Pu-238 0.050 +/- 0.015 0.063 0.044 - 0.081 Pass STAP-5403 08/01/12 Pu-239/40 0.001 +/- 0.004 0.00081 0.000 - 0.010 Pass STAP-5403' 08101112 U-233/4 0.009 +/- 0.011 0.014 0.010 - 0.018 Fail STAP-5403 08/01/12 U-238 0.08 +/- 0.02 0.10 0.070 - 0.130 Pass STAP-5403 08/01/12 Zn-65 0.01 +/- 0.06 0.00 -0.010 - 0.010 Pass STW-5445 08/01/12 Fe-55 79.80 +/- 4.10 89.30 62.50 - 116.10 Pass STW-5445 08/01/12 Ni-63 74.30 +/- 3.40 66.30 46.40 - 86.20 Pass STW-5445 08/01/12 U-233/4 0.46 +/- 0.05 0.45 0.32 - 0.59 Pass STW-5445 08/01/12 U-238 3.14 +/- 0.14 3.33 2.33 -4.33 Pass STW-5445 J 08/01/12 Am-241 0.64 +/- 0.04 1.06 0.74 - 1.38 Fail

" Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

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

d Investigation was inconclusive, there was not enough sample for reanalysis. ERA results (A-7) for the same matrix were acceptable.

e No errors found in calculation or procedure, original analysis result; 0.010 +/- 0.010 Bq/filter.

f Reanalysis results were within limits, but low. ERA results (A-7) for the same matrix were acceptable.

The efficiency factor was recalculated for the second round of MAPEP testing. Original analysis results 55.8 +/- 12.6 Bq/L.

Result of reanalysis; 6.74 +/- 0.15 Bq/sample. Gamma emitters for the vegetation matrix exhibited a high bias, only Co-57 exceeded acceptance limits. Recounted using a geometry more closely matched to the MAPEP sample size.

Result of reanalysis; 0.070 + 0.013 Bq/filter.

Result of reanalysis; 0.013 + 0.005 pCi/filter. A larger sample size was used to reduce the counting error.

Result of reanalysis 1.07 +/- 0.06 pCi/L. The analyses of the MAPEP sample matrix resulted in recovery factors greater than 100%.

A correction was made using recovery based on analysis of blank samples. A new tracer solution is on order, future samples for MAPEP testing will include batch spike and blank samples.

A6-3

I TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a Concentration (pCi/L) b I

Lab Code b Date Analysis Laboratory Result c ERA Result d Control Limits Acceptance U ERAP-1393 03/19/12 Co-60 917.5 +/- 7.0 880.0 681.0 - 1100.0 Pass ERAP-1393 ERAP-1393 03/19/12 03/19/12 Cs-1 34 Cs-137 586.6 +/- 7.4 1255.9 +/- 9.4 656.0 1130.0 417.0 -814.0 849.0 - 1480.0 Pass Pass I ERAP-1393 03/19/12 Mn-54 < 3.4 0.0 Pass ERAP-1393 ERAP-1394 03/19/12 03/19/12 Zn-65 Am-241 1085.2 +/- 18.0 86.9 +/- 2.9 897.0 68.8 642.0 - 1240.0 42.4 -93.1 Pass Pass I

Pass U

ERAP-1394 03/19/12 Pu-238 70.2 +/- 3.6 63.2 43.3 -83.1 ERAP-1394 03/19/12 Pu-239/40 66.0 +/- 1.0 63.0 45.6 - 82.4 Pass ERAP-1394 03/19/12 Sr-90 112.5 +/- 15.4 89.6 43.8 - 134.0 Pass ERAP-1394 03/19/12 U-233/4 43.4 +/- 0.8 47.5 29.4 - 71.6 Pass ERAP-1394 ERAP-1394 03/19/12 03/19/12 U-238 Uranium 44.0 89.1

+/- 1.2

+/- 2.2 47.1 96.7 30.4 53.5

- 65.1

- 147.0 Pass Pass I ERAP-1396 ERAP-1396 03/19/12 03/19/12 Gr. Alpha Gr. Beta 81.1 +/- 1.5 68.4 +/- 0.7 77.8 52.5 26.1 -121.0 33.2 - 76.5 Pass Pass U ERSO-1397 ERSO-1397 03/19/12 03/19/12 Ac-228 Am-241 1303.4 856.0

+/- 89.3

+/- 123.7 1570.0 938.0 1010.0 549.0

-2180.0

- 1220.0 Pass Pass I ERSO-1397 03/19/12 Bi-212 1379.2 +/- 247.2 1550.0 413.0 -2280.0 Pass ERSO-1397 03/19/12 Bi-214 965.2 +/- 38.4 1100.0 665.0 - 1590.0 Pass ERSO-1397 03/19/12 Co-60 3693.6 +/- 32.1 3500.0 2370.0 - 4820.0 Pass ERSO-1397 ERSO-1397 03/19/12 03/19/12 Cs-134 Cs-137 2257.3 9444.5 11277.0

+/- 45.4

+/- 58.4

+/- 275.1 2180.0 8770.0 11600.0 1420.0 6720.0 8470.0

-2620.0

- 11300.0

-15600.0 Pass Pass Pass I

ERSO-1397 03/19/12 K-40 ERSO-1397 03/19/12 Mn-54 < 21.0 0.0 Pass ERSO-1397 03/19/12 Pb-212 1208.4 +/- 26.3 1510.0 992.0 - 2110.0 Pass ERSO-1397 ERSO-1397 ERSO-1397 03/19/12 03/19/12 03/19/12 Pb-214 Pu-238 Pu-239/40 1041.6 921.0 1028.0

+/- 46.9

+/- 112.6

+/- 112.6 1110.0 984.0 879.0 647.0 592.0 575.0

- 1650.0

- 1360.0

- 1210.0 Pass Pass Pass I

ERSO-1397 03/19/12 Sr-90 8128.0 +/- 329.0 8800.0 3360.0 - 13900.0 Pass ERSO-1397 03/19/12 Th-234 2711.3 +/- 253.6 2000.0 632.0 - 3760.0 Pass ERSO-1397 03/19/12 U-233/4 1859.3 +/- 126.6 1960.0 1200.0 -2510.0 Pass ERSO-1397 03/19/12 U-238 2003.3 +/- 130.3 2000.0 1240.0 - 2540.0 Pass ERSO-1397 ERSO-1397 03/19/12 03/19/12 Uranium Zn-65 3939.5 4200.4

+/- 283.8

+/- 65.9 4030.0 3650.0 2190.0 2910.0

- 5320.0

-4850.0 Pass Pass I I

A7-1 I

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result 0 Limits Acceptance ERVE-1400 03/19/12 Am-241 4194.8 +/- 199.5 4540.0 2780.0 - 6040.0 Pass ERVE-1400 03/19/12 Cm-244 1471.2 +/- 113.1 1590.0 779.0 - 2480.0 Pass ERVE-1400 03/19/12 Co-60 2347.8 +/- 47.9 2210.0 1520.0 - 3090.0 Pass ERVE-1400 03/19/12 Cs-134 2847.5 +/- 64.0 2920.0 1880.0 -3790.0 Pass ERVE-1400 03/19/12 Cs-137 1503.5 +/- 52.5 1340.0 972.0 - 1860.0 Pass ERVE-1400 03/19/12 K-40 34105.7 +/- 745.3 28600.0 20700.0 -40100.0 Pass ERVE-1400 03/19/12 Mn-54 < 26.8 0.0 Pass ERVE-1400 03/19/12 Pu-238 2509.0 +/- 213.6 2350.0 1400.0 - 3220.0 Pass ERVE-1400 03/19/12 Pu-239/40 2690.4 +/- 208.9 2570.0 1580.0 - 3540.0 Pass ERVE-1400 03/19/12 Sr-90 7881.5 +/- 470.8 8520.0 4860.0 - 11300.0 Pass ERVE-1400 03/19/12 U-233/4 3149.6 +/- 165.2 3610.0 2370.0 - 4640.0 Pass ERVE-1400 03/19/12 U-238 3203.6 +/- 166.5 3580.0 2390.0 - 4550.0 Pass ERVE-1400 03/19/12 Uranium 6463.7 +/- 363.2 7350.0 4980.0 -9150.0 Pass ERVE-1400 03/19/12 Zn-65 2701.9 +/- 105.5 2310.0 1670.0 - 3240.0 Pass ERW-1403 03/19/12 Am-241 119.9 +/-3.2 135.0 91.0 -181.0 Pass ERW-1403 03/19/12 Fe-55 713.7 +/- 127.4 863.0 514.0 - 1170.0 Pass ERW-1403 03/19/12 Pu-238 131.9 +/-6.4 135.0 99.9 - 168.0 Pass ERW-1403 03/19/12 Pu-239/40 108.9 +/- 10.2 112.0 86.9 -141.0 Pass ERW-1403 03/19112 U-233/4 93.1 +/- 7.9 105.0 78.9 - 135.0 Pass ERW-1403 03/19/12 U-238 96.9 +/- 5.5 104.0 79.3 - 128.0 Pass ERW-1403 03/19/12 Uranium 190.0 +/- 13.8 214.0 157.0 -277.0 Pass ERW-1405 03/19/12 Co-60 858.7 +/- 5.6 875.0 760.0 - 1020.0 Pass ERW-1405 03/19/12 Cs-134 560.4 +/- 4.4 609.0 447.0 - 700.0 Pass ERW-1405 03/19/12 Cs-137 1239.9 +/- 7.4 1250.0 1060.0 - 1500.0 Pass ERW-1405 03/19/12 Mn-54 < 7.4 0.0 Pass ERW-1405 03/19/12 Sr-90 944.3 +/- 26.2 989.0 644.0 - 1310.0 Pass ERW-1405 03/19/12 Zn-65 786.9 +/- 20.6 749.0 624.0 - 945.0 Pass ERW-1406 03/19/12 Gr. Alpha 85.9 +/- 3.0 103.0 36.6 - 160.0 Pass ERW-1406 03/19/12 Gr. Beta 45.7 +/- 1.6 43.7 25.0 - 64.7 Pass ERW-1409 03/19/12 H-3 9045.0 +/- 284.0 9150.0 6130.0 - 13000.0 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).

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

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

A7-2

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX B 2012 REMP DATA

SUMMARY

REPORTS

- _ - m - m, m m n-, - m - m m Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2012 Mean of Results Mean of Results Location with Highest Annual Mean Mean of Results Type and from All Locations from All Indicator from All Control Number of and Number Locations and Mean and Number Locations and Sample Type and Units Analyses Lower Limit (LLD) Detected/Number Number Location # and Detected/Number Number Performed Collected and Detected/Number Distance and Collected and Detected/Number Range Collected Range and Direction Range Collected Range and 0.065 0.065 4 0.067 0.064 Air Be-7 N/A 28/28 24/24 0.7 4/4 4/4 pCi/m3 28 0.047 - 0.085 0.047 - 0.085 S 0.051 - 0.074 0.054 - 0.075 Air Co-58 N/A < LLD pCi/m3 28 Air Co-60 N/A < LLD pCi/m3 28 Air Cs-134 0.037 < LLD pCi/m3 28 Air Cs-137 0.045 < LLD - -

pCi/m3 28 0.025 0.025 6 0.026 0.026 Air Gross Beta 0.0075 371 /371 318/318 11.0 53/53 53/53 pCi/m3 371 p_____ 0.009 - 0.058 0.009 - 0.058 SSW 0.010 - 0.053 0.010 - 0.053 Air 1-131 0.05 < LLD -

pCi/m3 371 1265.3 1269.5 25 1269.5 1257 Fish K-40 N/A 3-3 2/2 0.6 2/2 1/1 pCi/gm wet 3 959-1580 959-1580 NNW 959-1580 1257-1257 Fish Mn-54 94 < LLD pCi/gm wet 3 Fish Fe-59 195 < LLD pCi/gm wet 3 B-1

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2012 Mean of Results Location with Highest Annual Mean Mean of Results Type and from All Locations from All Indicator from All Control Number of and Number Locations and Mean and Number Locations and Sample Type and Units Analyses Lower Limit (LLD) Detected/Number Number Location # and Detected/Number Number Performed Collected and Detected/Number Distance and Collected and Detected/Number Pand Collected and Direction Range Collected and Range Range Range Fish Co-58 97 < LLD pCi/gm wet 3 Fish Co-60 97 < LLD pCi/gm wet 3 Fish Zn-65 195 < LLD pCi/gm wet 3 Fish Cs-134 97 < LLD pCi/gm wet 3 Fish Cs-1 37 112 < LLD - -

pCi/gm wet 3 Broadleaf Vegetation Be-7 458.5 411.6 70 605.4 605.4 N/A 66/82 50/64 16.2 16/18 16/18 pCi/Kg wet 82 73 -2038 106 -870 SSW 73 -2038 73 -2038 5211.1 4912.3 18 6383.8 6273.3 Broadleaf Vegetation K-40 N/A 82/82 64/64 2.5 12/12 18/18 pCi/Kg wet 82 3016 -9645 3016 -9645 E 4146 -9645 4059 -9190 Broadleaf Vegetation Co-58 N/A < LLD--

pCi/Kg wet 82 Broadleaf Vegetation Co-60 N/A < LLD--

pCi/Kg wet 82 Broadleaf Vegetation 1-131 pCi/Kg wet 82 ________

45 1 < LLD B-2 mmmmm -~ "MMnm m mm mmm

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

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2012 Mean of Results Mean of Results Location with Highest Annual Mean Mean of Results Type and from All Locations from All Indicator from All Control Number of and Number Locations and Mean and Number Locations and Sample Type and Units Analyses Lower Limit (LLD) Detected/Number Number Location # and Detected/Number Number Performed Collected and Detected/Number Distance andCollected and Detected/Number Range Collected and Direction Range Collected and Range Range Broadleaf Vegetation Cs-134 45 < LLD--

pCi/Kg wet 82 Broadleaf Vegetation Cs-137 60 < LLD - -

pCi/Kg wet 82 1409.0 1612.5 41 1828.3 926.8 Milk K-40 N/A 64/64 45/45 5.8 12/12 19/19 pCi/L 64 626 -2028 1255 -2028 SSE 1630- 1927 626-1397 Milk 1-131 0.8 < LLD - -

pCi/L 64 Milk Cs-134 11 < LLD pCi/L 64 Milk Cs-137 13 < LLD pCi/L 64 Milk Ba-140 45 < LLD pCi/L 64 Milk La-140 11 < LLD -

pCi/L 64 13097.0 11936.4 32 18900.0 18900.0 Sediment K-40 N/A 12/12 10/10 15.8 2/2 2/2 pCi/kg wet 12 7853- 20844 7853 -16892 WSW 16956 - 20844 16956 - 20844 Sediment Co-58 50 < LLD pCi/kg wet 12 __________________ ___________________________

B-3

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2012 Mean of Results Mean of Results Location with Highest Annual Mean Mean of Results Meanfof ReuLtis from All Indicator from All Control Type and from All Locations Locations and Mean and Number Locations and Sample Type and Units Analyses Lower Limit (LLD) Detected/Number Number Location # and Detected/Number Number Performed Collected and Detected/Number Distance and Collected and Detected/Number Rang Collected and Direction Range Collected and Range Range Range Sediment Co-60 40 < LLD pCi/kg wet 12 Sediment Cs-134 112 < LLD -

pCi/kg wet 12 217.7 132.9 32 472.2 472.2 Sediment Cs-137 135 8/12 6/10 15.8 2/2 2/2 pCi/kg wet 12 35.7-529.6 35.7 -271.4 WSW 414.7 - 529.6 414.7 - 529.6 13.5 13.5 33 17.4 13.1 TLD Direct 1.0 112/112 104/104 4.5 4/4 8/8 mR/91 days 112 9.0-18.2 9.0-18.2 S 16.5-18.2 12.3-14.6 14.0 14.0 33 18.0 13.2 TLD Direct 1.0 112/112 104/104 4.5 4/4 8/8 mR/91 days 112 9.4-20.6 9.4-20.6 S 16.0-20.6 10.5-15.8 64.7 64.9 36 81.5 61.3 TLD Direct 1.0 28/28 26/26 3.9 1/1 2/2 mR/365 days 28 52.2-81.5 52.2-81.5 WSW 81.5-81.5 59.3-63.2 2.0 2.0 60 2.3 2.0 Water Gross Beta 3.0 ..... 51/58 40/46 1.0 8/11 11/12 pCi/L 58 0.9-3.7 0.9-3.7 WSW 1.2-3.7 1.2-2.6 Water H-3 1500 <LLD--

pCi/L 20 Water Mn-54 pCi/L 58 11 <LLD5 B-4

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2012 Mean of Results Location with Highest Annual Mean Mean of Results Mean of Results from All Indicator from All Control Type and from All Locations Locations and Mean and Number Locations and Sample Type and Units Analyses Lower Limit (LLD) Detected/Number Number Location # and mber Number Performed Collected and Detected/Number Distance and Collected and Detected/Number Collected and Direction Collected and Range Range Range Range Water Fe-59 22 <LLD pCi/L 58 Water Co-58 11 <LLD pCi/L 58 Water Co-60 11 <LLD pCi/L 58 Water Zn-65 22 <LLD pCi/L 58 Water Zr-95 22 <LLD pCi/L 58 Water Nb-95 11 <LLD pCi/L 58 Water Cs-134 11 <LLD pCi/L 58 Water Cs-137 13 <LLD pCi/L 58 Water Ba-140 45 <LLD pCi/L 58 Water La-140 11 <LLD pCi/L 58 1 _ _1_1_1_1 B-5

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 3 APPENDIXOC i 2012 REMP DETAILED DATA REPORT I

I I

U I

PNPP Direct Radiation (TLDs), Quarterly Exposure.

Units: mR/91 days 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Date Placed 01-06-12 04-16-12 07-17-12 09-25-12 Date Removed 04-16-12 07-17-12 09-25-12 01-08-13 E-1 11.5 +/-0.9 10.3 +/- 0.8 10.3 +/- 1.3 11.8 +/- 1.2 E-3 11.9 +/- 1.0 11.7 +/-_0.7 11.4 +/- 1.2 13.1 +/- 1.0 E-4 13.4 +/- 0.8 13.1 +/-_0.7 12.0 1.1 14.3 +/- 0.9 E-5 11.9 +/-0.8 12.3 +/- 0.6 10.9 +/-0.9 13.8 +/- 0.9 E-6 13.9 +/- 1.0 13.5 +/- 0.6 12.6 +/-0.8 14.6 +/- 0.9 E-7 13.3 +/- 0.6 13.4 +/- 0.7 12.0 +/-0.9 14.6 +/- 0.9 E-8 11.9 +/-0.6 12.6 +/- 0.6 11.1 +/-1.0 14.4 +/- 1.5 E-9 11.2 +/-_0.7 11.6 +/-0.6 11.3 +/-0.8 12.9 +/- 0.6 E-10 14.3 +/- 0.7 14.9 +/- 1.1 15.2 _ 1.4 15.8 +/- 0.9 E-11 14.2 +/- 0.8 13.3 +/- 0.4 14.4 +/- 1.7 14.4 +/- 0.7 E-1 2 12.8 +/- 0.9 12.8 +/- 0.6 12.6 +/-1.2 13.8 +/- 1.3 E-1 3 12.9 +/- 0.7 12.4 +/- 0.9 12.3 +/-0.9 13.1 +/- 1.0 E-14 11.5 +/-0.9 11.6 +/-_0.5 10.3 +/- 1.1 12.2 +/- 0.7 E-1 5 11.1 +/-0.6 9.0 +/- 0.6 9.8 +/- 0.8 9.6 +/- 0.8 E-21 13.4 +/- 0.8 13.7 +/- 0.6 13.0 +/- 1.0 13.8 +/- 0.6 E-23 14.6 +/- 0.6 14.2 +/- 0.7 14.1 +/-0.8 14.6 +/- 0.8 E-24 12.4 +/- 0.7 12.3 +/-0 .8 12.3 +/- 1.7 13.2 +/- 1.0 E-29 16.3 +/- 0.7 16.3 +/- 0.6 16.1 +/-1.1 16.9 +/-0 .9 E-30 15.0 +/- 0.7 15.4 +/-0 .5 14.8 +/-0.9 16.0 +/- 0.8 E-31 15.2 +/- 0.8 17.3 +/- 0.6 15.0 +/-0.9 17.8 +/- 0.9 E-33 16.8 +/- 0.9 18.0 +/-0.7 16.5 +/- 1.1 18.2 +/- 1.0 E-35 12.2 +/- 0.8 12.7 +/-0.5 11.6 +/-0.8 13.5 +/- 0.7 E-36 15.7 +/- 0.8 16.8 +/-0.6 17.6 +/-0.7 16.7 +/- 0.8 E-53 13.2 +/- 0.6 14.3 +/-0.6 14.7 +/-0.8 14.3 +/- 1.0 E-54 12.6 +/-0 .9 13.1 +/-0.4 14.1 +/-1.2 13.5 +/- 0.7 E-55 13.5 +/- 1.4 14.2 +/-0.6 16.5 +/- 1.0 13.9 +/- 1.0 E-56 12.9 +/- 0.6 13.5 +/-0.5 13.7 +/-0.9 13.2 +/- 0.9 E-58 10.7 +/- 0.6 11.2 +/-0.6 10.9 +/-1.4 11.1 +/-_0.7 Mean +/- s.d. 13.2 +/- 1.6 13.4 +/-2.0 13.1 +/-2.1 14.1 +/-1.9 E-Control 1 7.0 +/- 0.8 7.6 +/-0.5 7.0 +/- 0.9 6.9 +/- 0.3 E-Control 2 6.6 +/- 0.7 7.3 _0.5 6.5 +/- 0.6 6.8 +/-0.2 C-1

PNPP 3 Direct Radiation (TLDs), Quarterly Exposure.

Collection: Quarterly Composite I

Units: pCi/m Date Placed 3

1st Qtr.

01-06-12 2nd Qtr.

04-16-12 3rd Qtr.

07-17-12 4th Qtr.

09-25-12 I

Date Removed 04-16-12 07-17-12 09-25-12 01-08-13 Q-1 Q-3 10.4 12.3

+/- 1.1

+/- 0.5 9.4 9.9

+/- 1.2

+/- 0.9 12.4 14.5

+/- 2.4

+/- 2.2 10.6 11.3

+/- 1.1

+/- 1.1 I

Q-4 Q-5 Q-6 13.1 13.0 13.5

+/- 0.5

+/- 0.4

+/- 0.9 12.2 10.9 11.7

+/-0 .8

+/- 1.2

+/-0.8 15.0 15.5 15.8

+/- 2.3

+/- 2.1

+/- 2.1 13.9 12.6 13.5

+/- 1.1

+/- 1.2

+/- 0.8 I

Q-7 14.1 +/-0.3 13.9 +/- 1.2 16.6 +/- 2.2 15.0 +/- 0.8 Q-8 Q-9 12.3 12.2

+/- 0.4

+/- 0.6 12.1 12.5

+/-0.7

+/-3.2 14.9 15.3

+/- 2.2

+/- 2.3 13.3 12.9

+/- 1.1

+/- 0.9 I

Q-10 14.7 +/- 0.8 14.0 +/- 1.0 18.0 +/- 2.3 15.4 +/- 0.9 Q-11 Q-12 13.0 13.1

+/- 0.3

+/-0.3 13.0 12.4

+/-0.8

+/- 1.0 16.6 16.7

+/- 2.8

+/- 2.4 14.4 13.7

+/- 0.9

+/- 1.1 I

Q-13 12.7 +/-0.3 12.2 +/-0.8 15.1 +/- 2.2 13.2 +/- 1.2 Q-14 Q-15 Q-21 11.5 10.9 13.9

+/-0.4

+/-0.5

+/-0.5 11.3 9.7 12.5

+/-0.8

+/- 0.8

+/-0.9 13.6 12.9 16.2

+/- 2.2

+/-2.2 12.5 11.3 13.5

+/- 0.8

+/-_0.9

+/- 0.9 I

Q-23 Q-24 Q-29 13.9 13.2 16.5

+/-0.4

+/-1.3

+/-0.4 13.1 10.5 15.4

+/-1.1

+/-0.7

+/- 1.1 16.6 15.4 19.4

+/-2.3

+/-2.5

+/-2.3 13.6 12.1 16.4

+/- 1.1

+/- 0.9

+/- 1.2 I

Q-30 15.4 +/- 0.4 13.4 +/-0.7 18.4 +/-2.2 14.5 +/- 0.8 Q-31 Q-33 16.6 17.6

+/- 0.6

+/- 0.8 14.7 16.0

+/- 1.1

+/- 1.1 19.6 20.6

+/-2.2

+/- 2.2 16.5 17.6

+/- 1.0

+/- 0.9 I

Q-35 13.0 +/- 0.4 11.2 +/-0.8 15.1 +/-2.3 13.1 +/-_0.9 Q-36 Q-53 16.4 13.8

+/- 0.6

+/- 0.4 15.1 13.0

+/-0.8

+/-0.8 19.5 16.2

+/- 2.2

+/-_2.1 16.4 14.0

+/- 1.0

+/- 0.8 U

Q-54 13.5 +/- 0.5 12.5 +/-0.7 16.2 +/- 2.2 14.0 Q-55 Q-56 Q-58 13.9 13.5 11.0

+/- 0.9

+/- 0.8

+/-0.6 13.5 12.6 10.3

+/-0.9

+/- 1.0

+/- 0.7 16.3 15.1 12.9

+/- 2.2

+/-_2.3

+/- 2.4 14.6 13.8 11.5

+/- 1.0

+/- 1.1

+/-0.9 I

Mean +/- s.d. 13.5 +/- 1.8 12.5 +/- 1.7 16.1 +/-2.1 13.8 +/- 1.7 I Q-Control 1 Q-Control 2 7.7 +/- 0.3 7.9 +/- 0.4 7.0 +/- 0.9 7.3 +/- 0.8 9.0 +/- 2.1 9.3 +/- 2.2 7.3 +/- 0.8 7.1 +/-0.8 U I

I I

C-2 I

PNPP Direct Radiation (TLDs), Annual Exposure.

Units: mR/365 days 2012 Date Placed 01-06-12 Date Removed 01-08-13 A-1 52.2 +/- 3.2 A-3 56.7 +/- 1.9 A-4 62.8 +/- 1.9 A-5 59.0 +/- 2.6 A-6 63.2 +/- 2.8 A-7 62.4 +/- 3.1 A-8 58.6 +/- 3.1 A-9 55.5 +/- 1.7 A-10 70.1 +/-2.1 A-11 64.5 + 2.4 A-12 63.4 +/- 2.1 A-13 61.5 +/-2.9 A-14 57.4 + 2.6 A-15 53.0 +/- 2.3 A-21 67.8 +/- 5.1 A-23 64.9 +/- 3.1 A-24 59.3 +/- 3.4 A-29 77.2 +/- 4.1 A-30 69.3 +/- 2.6 A-31 75.4 +/- 4.0 A-33 79.3 +/- 2.8 A-35 60.0 +/- 1.6 A-36 81.5 +/- 1.9 A-53 69.7 +/- 2.1 A-54 67.4 +/- 2.2 A-55 72.0 +/- 2.2 A-56 69.0 +/- 2.8 A-58 57.4 +/- 2.6 Mean +/- s.d. 64.7 +/- 7.8 A-Control 1 23.6 +/- 1.3 A-Control 2 23.2 + 1.0 C-3

I Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31.

PNPP U Location:

Units: pCi/m 3

P-1 I

Collection: Continuous, weekly exchange.

Date Volume Date Volume I Collected (me) Gross Beta 1-131 Collected (mi) Gross Beta 1-131 Required LLD 0.0075 0.050 0.0075 0.050 I 01-04-12 577 0.020 +/- 0.003 < 0.010 07-10-12 578 0.030 +/- 0.003 < 0.004 01-11-12 01-18-12 581 568 0.025 +/- 0.003 0.020 +/- 0.003

< 0.009

< 0.011 07-17-12 07-25-12 589 647 0.025 0.027

+/-

0.003 0.003

< 0.004

< 0.011 I

01-25-12 601 0.030 +/- 0.003 < 0.011 08-01-12 578 0.019 +/- 0.003 < 0.009 02-01-12 02-07-12 568 507 0.027 +/- 0.003 0.026 +/- 0.003

< 0.006

< 0.009 08-08-12 08-15-12 580 578 0.026 0.018

+/-

0.003 0.003

< 0.005

< 0.006 I

02-15-12 02-22-12 02-29-12 647 578 574 0.021 0.025 0.020

+/- 0.002

+/- 0.003

< 0.006

< 0.010

< 0.010 08-23-12 08-29-12 652 493 0.023 0.037

+/-

0.003 0.003

< 0.008

< 0.010 I 09-05-12 585 0.027 +/- 0.003 < 0.012 03-07-12 03-13-12 563 498 0.024 0.023

+/- 0.003

< 0.011

< 0.008 09-11-12 09-19-12 490 667 0.023 0.029

+/-

0.003 0.003

< 0.004

< 0.011 I

03-21-12 644 0.022 +/- 0.002 < 0.009 09-26-12 565 0.023 +/- 0.003 <0.013 03-29-12 655 0.020 +/- 0.002 < 0.008 10-03-12 559 0.021 +/- 0.003 < 0.007 U

1Q 2012 Mean +/- s.d. 0.023 +/- 0.003 < 0.011 3Q 2012 Mean +/- s.d. 0.025 +/- 0.005 < 0.013 04-05-12 570 0.015 +/- 0.003 < 0.004 10-10-12 572 0.032 +/- 0.003 < 0.008 I

04-11-12 472 0.020 +/- 0.003 < 0.013 10-17-12 552 0.027 +/- 0.003 < 0.005 04-18-12 04-25-12 05-02-12 570 554 561 0.018 0.019 0.021

+/- 0.003

+/- 0.003 0.006 0.010 0.007 10-24-12 11-01-12 558 642 0.035 0.018

+/- 0.003

+/- 0.002

< 0.013

< 0.011 I 05-09-12 05-16-12 580 589 0.019 +/- 0.003 0.019 +/- 0.003 0.007 0.011 11-08-12 11-14-12 11-21-12 542 457 553 0.016 +/- 0.003 0ý048 +/- 0.004 0.051 +/- 0.004

< 0.010

< 0.009

< 0.009 I

05-23-12 589 0.017 +/- 0.003 < 0.010 11-28-12 538 0.041 +/- 0.003 < 0.016 05-30-12 578 0.028 +/- 0.003 0.012

< 0.010 12-05-12 552 0.058 +/- 0.004

+/- 0.003

< 0.007 I

06-06-12 580 +/- 0.002 < 0.006 12-12-12 538 0.023 < 0.008 06-13-12 06-20-12 06-26-12 576 587 480 0.016 0.021 0.022

+/- 0.003

< 0.008

< 0.005

< 0.007 12-20-12 12-26-12 01-02-13 615 444 499 0.055 0.028 0.036

+/- 0.003

+/- 0.004

+/- 0.003

< 0.025

< 0.007

< 0.010 I

07-03-12 576 0.029 +/- 0.003 < 0.005 I

2Q 2012 Mean +/- s.d. 0.020 +/- 0.005 < 0.013 4Q 2012 Mean +/- s.d. 0.036 +/- 0.014 < 0.025 Cumulative Average 0.026 I

I C-4

PNPP Airborne particulates and charcoal canisters, analyses for gross beta and iodine-i 31.

Location: P-3 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (mi) Gross Beta 1-131 Collected (mi) Gross Beta 1-131 Required LLD 0.0075 0.050 0.0075 0.050 01-04-12 569 0.023 +/- 0.003 < 0.010 07-10-12 570 0.029 +/- 0.003 < 0.004 01-11-12 578 0.027 +/- 0.003 < 0.009 07-17-12 582 0.026 +/- 0.003 < 0.004 01-18-12 582 0.020 +/- 0.003 < 0.011 07-25-12 648 0.023 +/- 0.003 < 0.011 01-25-12 592 0.032 +/- 0.003 < 0.011 08-01-12 574 0.021 +/- 0.003 < 0.009 02-01-12 565 0.025 +/- 0.003 < 0.006 08-08-12 573 0.025 + 0.003 < 0.005 02-07-12 504 0.022 +/- 0.003 < 0.009 08-15-12 569 0.020 +/- 0.003 < 0.006 02-15-12 644 0.022 +/- 0.002 < 0.006 08-23-12 646 0.022 +/- 0.003 < 0.008 02-22-12 584 0.028 +/- 0.003 < 0.010 08-29-12 481 0.035 +/- 0.003 < 0.010 02-29-12 573 0.021 +/- 0.003 < 0.010 09-05-12 578 0.029 +/- 0.003 < 0.012 03-07-12 551 0.020 +/- 0.003 < 0.011 09-11-12 467 0.022 +/- 0.003 < 0.004 03-13-12 497 0.022 +/- 0.003 < 0.008 09-19-12 661 0.026 + 0.002 < 0.011 03-21-12 643 0.020 +/- 0.002 < 0.009 09-26-12 551 0.022 +/- 0.003 <0.013 03-29-12 642 0.017 +/- 0.002 < 0.009 10-03-12 533 0.019 + 0.003 < 0.007 1Q 2012 Mean +/- s.d. 0.023 +/- 0.004 < 0.011 3Q 2012 Mean +/- s.d. 0.025 +/- 0.004 < 0.013 04-05-12 554 0.014 +/- 0.003 < 0.004 10-10-12 554 0.027 +/- 0.003 < 0.009 04-11-12 468 0.020 +/- 0.003 < 0.013 10-17-12 544 0.027 +/- 0.003 < 0.006 04-18-12 564 0.017 +/- 0.003 < 0.006 10-24-12 556 0.037 +/- 0.003 < 0.013 04-25-12 543 0.018 +/- 0.003 < 0.010 11-01-12 635 0.018 +/- 0.002 < 0.011 05-02-12 543 0.021 +/- 0.003 < 0.008 11-08-12 539 0.015 +/- 0.003 < 0.010 05-09-12 578 0.021 +/- 0.003 < 0.007 11-14-12 500 0.040 +/- 0.004 < 0.008 05-16-12 584 0.020 +/- 0.003 <0.011 11-21-12 626 0.038 +/- 0.003 < 0.008 05-23-12 594 0.017 +/- 0.003 < 0.010 11-28-12 596 0.041 +/- 0.003 < 0.014 05-30-12 577 0.029 +/- 0.003 < 0.010 12-05-12 612 0.045 + 0.003 < 0.006 06-06-12 554 0.011 +/- 0.003 < 0.006 12-12-12 586 0.017 + 0.003 < 0.007 06-13-12 580 0.015 +/- 0.003 < 0.008 12-20-12 675 0.041 + 0.003 < 0.024 06-20-12 585 0.019 +/- 0.003 < 0.005 12-26-12 505 0.023 + 0.003 < 0.007 06-26-12 483 0.020 +/- 0.003 < 0.007 01-02-13 581 0.031 + 0.003 < 0.009 07-03-12 572 0.025 +/- 0.003 < 0.005 2Q 2012 Mean +/- s.d. 0.019 +/- 0.004 < 0.013 4Q 2012 Mean +/- s.d. 0.031 +/- 0.010 < 0.024 Cumulative Average 0.024 C-5

I Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

PNPP U Location:

Units: pCi/m 3

P-4 I

Collection: Continuous, weekly exchange.

Date Collected Volume Date Volume I (ms) Gross Beta 1-131 Collected (mi) Gross Beta 1-131 Required LLD 0.0075 0.050 0.0075 0.050 I 01-04-12 580 0.021 +/- 0.003 < 0.010 07-10-12 544 0.033 +/- 0.003 < 0.005 01-11-12 01-18-12 576 622 0.027 0.026

+/- 0.003

+/- 0.003 0.009 0.010 07-17-12 07-25-12 563 646 0.028 + 0.003 0.025 + 0.003

< 0.005

< 0.011 I

01-25-12 635 0.033 +/- 0.003 < 0.010 08-01-12 550 0.019 + 0.003 < 0.009 02-01-12 02-07-12 610 529 0.028 +/- 0.003 0.027 +/- 0.003

< 0.006

< 0.009 08-08-12 08-15-12 552 550 0.027 0.017

+ 0.003

< 0.006

< 0.006 I

02-15-12 02-22-12 02-29-12 703 585 587 0.021 +/- 0.002 0.028 +/- 0.003 0.023 +/- 0.003

< 0.005

< 0.010

< 0.010 08-23-12 08-29-12 630 458 0.023 0.037

+ 0.003

+ 0.004

< 0.008

< 0.011 I 09-05-12 561 0.028 + 0.003 < 0.013 03-07-12 03-13-12 588 536 0.026 0.023

+/- 0.003

< 0.010

< 0.007 09-11-12 09-19-12 459 642 0.026 0.029

+ 0.003

< 0.004

< 0.011 I

03-21-12 695 0.022 +/- 0.002 < 0.008 09-26-12 547 0.022 + 0003 < 0.013 03-29-12 736 0.019 +/- 0.002 < 0.008 10-03-12 530 0.018 +/- 0.003 < 0.007 I

102012 Mean +/- s.d. 0.025 +/- 0.004 < 0.010 3Q 2012 Mean +/- s.d. 0.026 +/- 0.006 < 0.013 04-05-12 04-11-12 590 0.015 +/- 0.002 < 0.004 10-10-12 552 0.030 +/- 0.003 < 0.009 I 526 0.019 +/- 0.003 < 0.011 10-17-12 545 0.025 +/- 0.003 < 0.006 04-18-12 04-25-12 05-02-12 627 604 615 0.016 +/- 0.002 0.019 +/- 0.003 0.022 +/- 0.003

< 0.005

< 0.009

< 0.007 10-24-12 11-01-12 551 630 0.034 +/- 0.003 0.017 +/- 0.002

< 0.013

< 0.011 I 11-08-12 527 +/- < 0.010 05-09-12 05-16-12 559 583 0.021 0.017

+/- 0.003

< 0.007

< 0.011 11-14-12 11-21-12 497 580 0.013 0.041 0.048

+/-

0.003 0.004 0.003

< 0.008

< 0.009 I

05-23-12 566 0.016 +/- 0.003 < 0.011 11-28-12 572 0.037 +/- 0.003 < 0.015 05-30-12 06-06-12 571 0.026 +/- 0.003 < 0.010 12-05-12 585 0.051 +/- 0.003 < 0.007 I 553 0.009 +/- 0.002 < 0.006 12-12-12 555 0.023 +/- 0.003 < 0.008 06-13-12 06-20-12 06-26-12 549 565 464 0.018 0.021 0.024

+/- 0.003

< 0.008

< 0.005

< 0.007 12-20-12 12-26-12 01-02-13 623 488 573 0.047 0.026 0.032

+/- 0.003

< 0.024

< 0.007

< 0.009 I

07-03-12 544 0.031 + 0.003 < 0.005 2Q 2012 Mean +/- s.d. 0.020 +/- 0.005 < 0.011 4Q 2012 Mean +/- s.d. 0.033 +/- 0.012 < 0.024 I Cumulative Average 0.026 I

I I

C-6

PNPP Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: P-5 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (me) Gross Beta 1-131 Collected (me) Gross Beta 1-131 Required LLD 0.0075 0.050 0.0075 0.050 01-04-12 545 0.024 +/- 0.003 < 0.011 07-10-12 578 0.033 +/- 0.003 < 0.004 01-11-12 547 0.025 +/- 0.003 < 0.009 07-17-12 591 0.027 +/- 0.003 < 0.004 01-18-12 562 0.029 +/- 0.003 < 0.011 07-25-12 654 0.027 +/- 0.003 < 0.011 01-25-12 561 0.033 +/- 0.003 < 0.012 08-01-12 583 0.019 +/- 0.003 < 0.009 02-01-12 536 0.031 +/- 0.003 < 0.007 08-08-12 581 0.028 +/- 0.003 < 0.005 02-07-12 467 0.030 +/- 0.003 < 0.010 08-15-12 586 0.020 +/- 0.003 < 0.006 02-15-12 618 0.023 +/- 0.002 < 0.006 08-23-12 656 0.023 +/- 0.002 < 0.008 02-22-12 545 0.029 +/- 0.003 < 0.011 08-29-12 499 0.036 +/- 0.003 <0.010 02-29-12 548 0.023 +/- 0.003 < 0.011 09-05-12 586 0.026 +/- 0.003 < 0.012 03-07-12 533 0.026 +/- 0.003 < 0.011 09-11-12 496 0.026 +/- 0.003 < 0.004 03-13-12 469 0.026 +/- 0.003 < 0.008 09-19-12 676 0.030 +/- 0.003 < 0.010 03-21-12 614 0.024 +/- 0.003 < 0.009 09-26-12 570 0.021 +/- 0.003 < 0.013 03-29-12 634 0.018 +/- 0.002 < 0.009 10-03-12 573 0.022 +/- 0.003 < 0.007 1Q 2012 Mean +/- s.d. 0.026 +/- 0.004 < 0.012 3Q 2012 Mean +/- s.d. 0.026 +/- 0.005 < 0.013 04-05-12 543 0.016 +/- 0.003 < 0.004 10-10-12 585 0.029 +/- 0.003 < 0.008 04-11-12 464 0.020 +/- 0.003 < 0.013 10-17-12 581 0.026 +/- 0.003 < 0.005 04-18-12 553 0.020 +/- 0.003 < 0.006 10-24-12 587 0.037 +/- 0.003 < 0.012 04-25-12 541 0.016 +/- 0.003 < 0.010 11-01-12 663 0.019 +/- 0.002 < 0.010 05-02-12 540 0.027 +/- 0.003 < 0.008 11-08-12 560 0.016 +/- 0.003 < 0.009 05-09-12 580 0.019 +/- 0.003 < 0.007 11-14-12 495 0.041 +/- 0.004 < 0.008 05-16-12 592 0.021 +/- 0.003 < 0.011 11-21-12 581 0.047 +/- 0.003 < 0.009 05-23-12 586 0.014 +/- 0.002 < 0.010 11-28-12 575 0.040 +/- 0.003 <0.015 05-30-12 579 0.028 +/- 0.003 < 0.009 12-05-12 582 0.051 +/- 0.003 < 0.007 06-06-12 585 0.012 +/- 0.002 < 0.006 12-12-12 564 0.021 +/- 0.003 < 0.008 06-13-12 583 0.018 +/- 0.003 < 0.008 12-20-12 607 0.052 +/- 0.003 < 0.013 06-20-12 586 0.020 +/- 0.003 < 0.005 12-26-12 455 0.028 +/- 0.003 < 0.007 06-26-12 510 0.023 +/- 0.003 < 0.007 01-02-13 560 0.034 +/- 0.003 < 0.009 07-03-12 579 0.029 +/- 0.003 < 0.005 2Q 2012 Mean +/- s.d. 0.020 +/- 0.005 < 0.013 4Q 2012 Mean +/- s.d. 0.034 +/- 0.012 < 0.015 Cumulative Average 0.026 C-7

I Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

PNPP I Location:

Units: pCi/m 3

P-6 I

Collection: Continuous, weekly exchange.

Date Collected Volume (mi) Gross Beta 1-131 Date Volume I

Collected (mi) Gross Beta 1-131 Required LLD 0.0075 0.050 0.0075 0.050 I 01-04-12 575 0.022 +/- 0.003 < 0.010 07-10-12 541 0.031 +/- 0.003 < 0.005 01-11-12 01-18-12 567 572 0.029 +/- 0.003 0.021 +/- 0.003

< 0.009

< 0.011 07-17-12 07-25-12 566 613 0.023 +/- 0.003 0.028 +/- 0.003

< 0.005

< 0.012 U

01-25-12 586 0.030 +/- 0.003 < 0.011 08-01-12 548 0.024 +/- 0.003 < 0.010 02-01-12 02-07-12 552 494 0.027 +/- 0.003 0.027 +/- 0.003

< 0.006

< 0.009 08-08-12 08-15-12 543 544 0.027 0.020

+/- 0.003

< 0.006

< 0.006 I

02-15-12 02-22-12 02-29-12 637 574 574 0.023 0.027 0.022

+/- 0.002

+/- 0.003

< 0.006

< 0.010

< 0.010 08-23-12 08-29-12 618 461 0.026 0.042

+/- 0.003

+/- 0.004

< 0.008

<0.010 I 09-05-12 545 0.028 +/- 0.003 <0.013 03-07-12 03-13-12 557 497 0.021 0.031

+/- 0.003

< 0.011

< 0.008 09-11-12 09-19-12 451 644 0.024 0.031

+/-

0.003 0.003

< 0.004

< 0.011 I

03-21-12 614 0.022 +/- 0.003 < 0.009 09-26-12 529 0.028 +/- 0.003 < 0.014 03-29-12 639 0.021 +/- 0.002 < 0.009 10-03-12 533 0.022 +/- 0.003 < 0.007 U

1Q 2012 Mean +/- s.d. 0.025 +/- 0.004 < 0.011 3Q 2012 Mean +/- s.d. 0.027 +/- 0.006 < 0.014 04-05-12 534 0.015 +/- 0.003 < 0.004 10-10-12 542 0.027 +/- 0.003 < 0.009 I

04-11-12 466 0.019 +/- 0.003 < 0.013 10-17-12 537 0.029 +/- 0.003 < 0.006 04-18-12 04-25-12 05-02-12 568 545 566 0.016 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003

< 0.006

< 0.010

< 0.007 10-24-12 11-01-12 554 623 0.034 +/- 0.003 0.014 +/- 0.002

< 0.013

< 0.011 I 05-09-12 05-16-12 565 578 0.021 +/- 0.003 0.021 +/- 0.003 0.007 0.011 11-08-12 11-14-12 11-21-12 519 494 581 0.016 0.044 0.050

+/- 0.003

+/- 0.004

+/- 0.003

< 0.010

< 0.008

< 0.009 I

05-23-12 570 0.016 +/- 0.003 < 0.011 11-28-12 554 0.041 +/- 0.003 < 0.015 05-30-12 06-06-12 564 0.027 +/- 0.003 < 0.010 12-05-12 582 0.053 +/- 0.004 < 0.007 I 554 0.010 +/- 0.003 < 0.006 12-12-12 556 0.019 +/- 0.003 < 0.008 06-13-12 06-20-12 06-26-12 547 549 472 0.018 0.020 0.025

+/- 0.003

< 0.008

< 0.005

< 0.007 12-20-12 12-26-12 01-02-13 628 474 565 0.047 +/- 0.003 0.030 +/- 0.003 0.033 +/- 0.003

< 0.018

< 0.007

< 0.009 I

07-03-12 554 0.028 +/- 0.003 < 0.005 2Q 2012 Mean +/- s.d.

I 0.020 +/- 0.005 < 0.013 4Q 2012 Mean +/- s.d. 0.034 +/- 0.013 < 0.018 Cumulative Average 0.026 I

I C-8

PNPP Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31.

Location: P-7 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (ms) Gross Beta 1-131 Collected (ms) Gross Beta 1-131 Required LLD 0.0075 0.050 0.0075 0.050 01-04-12 589 0.026 +/- 0.003 < 0.010 07-10-12 527 0.028 +/- 0.003 < 0.005 01-11-12 584 0.025 +/- 0.003 < 0.009 07-17-12 590 0.024 +/- 0.003 < 0.004 01-18-12 574 0.020 +/- 0.003 < 0.011 07-25-12 645 0.023 + 0.003 < 0.011 01-25-12 592 0.028 +/- 0.003 < 0.011 08-01-12 577 0.018 + 0.003 < 0.009 02-01-12 573 0.025 +/- 0.003 < 0.006 08-08-12 577 0.024 +/- 0.003 < 0.005 02-07-12 508 0.032 +/- 0.003 < 0.009 08-15-12 574 0.018 +/- 0.003 < 0.006 02-15-12 649 0.018 +/- 0.002 < 0.006 08-23-12 627 0.022 + 0.003 < 0.008 02-22-12 578 0.030 +/- 0.003 < 0.010 08-29-12 477 0.037 +/- 0.004 < 0.010 02-29-12 577 0.020 +/- 0.003 < 0.010 09-05-12 554 0.026 + 0.003 < 0.013 03-07-12 568 0.022 +/- 0.003 < 0.011 09-11-12 464 0.022 +/- 0.003 < 0.004 03-13-12 501 0.023 +/- 0.003 < 0.008 09-19-12 665 0.027 + 0.002 < 0.011 03-21-12 642 0.019 +/- 0.002 < 0.009 09-26-12 571 0.021 +/- 0.003 < 0.013 03-29-12 657 0.016 +/- 0.002 < 0.008 10-03-12 567 0.016 + 0.003 < 0.007 1Q 2012 Mean +/- s.d. 0.023 +/- 0.005 < 0.011 3Q 2012 Mean +/- s.d. 0.024 +/- 0.005 < 0.013 04-05-12 560 0.016 +/- 0.003 < 0.004 10-10-12 581 0.024 +/- 0.003 < 0.008 04-11-12 466 0.019 +/- 0.003 < 0.013 10-17-12 576 0.024 + 0.003 < 0.005 04-18-12 569 0.021 +/- 0.003 < 0.006 10-24-12 582 0.032 +/- 0.003 < 0.012 04-25-12 545 0.021 +/- 0.003 <0.010 11-01-12 658 0.016 +/- 0.002 < 0.011 05-02-12 568 0.022 +/- 0.003 < 0.007 11-08-12 563 0.012 00.003 < 0.009 05-09-12 582 0.018 +/- 0.003 < 0.007 11-14-12 480 0.035 +/- 0.004 < 0.009 05-16-12 592 0.020 +/- 0.003 < 0.011 11-21-12 579 0.047 + 0.003 < 0.009 05-23-12 588 0.014 +/- 0.002 < 0.010 11-28-12 558 0.039 +/- 0.003 < 0.015 05-30-12 580 0.024 +/- 0.003 < 0.009 12-05-12 561 0.054 +/- 0.004 < 0.007 06-06-12 587 0.011 +/- 0.002 < 0.006 12-12-12 540 0.018 +/- 0.003 < 0.008 06-13-12 584 0.016 +/- 0.003 < 0.008 12-20-12 620 0.044 +/- 0.003 < 0.025 06-20-12 588 0.018 +/- 0.003 < 0.005 12-26-12 441 0.027 +/- 0.004 < 0.007 06-26-12 505 0.019 +/- 0.003 < 0.007 01-02-13 540 0.032 - 0.003 < 0.009 07-03-12 575 0.026 +/- 0.003 < 0.005 2Q 2012 Mean +/- s.d. 0.019 +/- 0.004 < 0.013 4Q 2012 Mean +/- s.d. 0.031 +/- 0.013 < 0.025 Cumulative Average 0.024 C-9

I PNPP I Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31.

Location: P-35 Units: pCi/m 3

Collection: Continuous, weekly exchange.

I Date Volume Date Volume I

Collected (ms) Gross Beta 1-131 Collected (ms) Gross Beta 1-131 Required LLD 0.0075 0.050 0.0075 0.050 I 01-04-12 580 0.020 +/- 0.003 < 0.013 07-10-12 578 0.028 + 0.003 < 0.012 01-11-12 01-18-12 586 571 0.024 +/- 0.003 0.022 +/- 0.003

< 0.011

< 0.012 07-17-12 07-25-12 590 630 0.023 0.025

+ 0.003

< 0.008

<0.013 I

01-25-12 604 0.030 +/- 0.003 < 0.010 08-01-12 563 0.020 + 0.003 < 0.012 02-01-12 02-07-12 575 508 0.024 +/- 0.003 0.024 +/- 0.003

< 0.009

< 0.013 08-08-12 08-15-12 573 540 0.027 0.018

+ 0.003

< 0.007

< 0.005 I

02-15-12 02-22-12 02-29-12 649 582 577 0.019 0.025 0.020

+ 0.002

+/- 0.003

< 0.008

< 0.007

< 0.005 08-23-12 08-29-12 617 458 0.026 0.036

+ 0.003

+ 0.004

< 0.008

< 0.016 I 09-05-12 545 0.027 +/- 0.003 < 0.006 03-07-12 03-13-12 576 503 0.021 0.022

+/- 0.003

< 0.009

< 0.008 09-11-12 09-19-12 456 623 0.026 0.027

+/- 0.003

< 0.015

< 0.012 I

03-21-12 646 0.019 +/- 0.002 < 0.009 09-26-12 527 0.023 +/- 0.003 < 0.015 03-29-12 660 0.018 +/- 0.002 < 0.005 10-03-12 523 0.019 +/- 0.003 < 0.005 I

1Q 2012 Mean +/- s.d. 0.022 +/- 0.003 < 0.013 3Q 2012 Mean +/- s.d. 0.025 +/- 0.005 < 0.016 04-05-12 575 0.013 +/- 0.002 < 0.008 10-10-12 536 0.031 +/- 0.003 < 0.006 I

04-11-12 482 0.018 +/- 0.003 < 0.014 10-17-12 533 0.027 +/- 0.003 < 0.008 04-18-12 04-25-12 05-02-12 573 546 560 0.016 0.018 0.022

+/- 0.003

+/- 0.003 0.012 0.011 0.009 10-24-12 11-01-12 539 621 0.037 +/- 0.003 0.017 +/- 0.002

< 0.015

< 0.008 I 05-09-12 05-16-12 582 589 0.019 0.021

+/- 0.003

< 0.008

< 0.013 11-08-12 11-14-12 11-21-12 524 465 553 0.015 0.041 0.051

+/- 0.003

+/- 0.004

+/- 0.004 0.014 0.014 0.019 I

05-23-12 580 0.015 +/- 0.003 < 0.014 11-28-12 537 0.044 +/- 0.004 < 0.012 05-30-12 576 0.026 +/- 0.003 < 0.009 12-05-12 555 0.051 +/- 0.004 < 0.013 I

06-06-12 573 0.012 +/- 0.002 < 0.010 12-12-12 537 0.021 +/- 0.003 < 0.015 06-13-12 06-20-12 06-26-12 580 578 493 0.018 0.019 0.020

+/-

0.003 0.003 0.003

< 0.008

<0.010

< 0.009 12-20-12 12-26-12 01-02-13 619 461 563 0.050 0.026 0.032

+/- 0.003

< 0.028

<0.018

< 0.009 U

07-03-12 576 0.026 +/- 0.003 < 0.009 2Q 2012 Mean + s.d. 0.019 +/- 0.004 < 0.014 4Q 2012 Mean +/- s.d. 0.034 +/- 0.013 < 0.028 Cumulative Average 0.025 I

I C-1 0 I

PNPP Airborne particulates, analyses for gamma-emitting isotopes.

Collection: Quarterly Composite 3

Units: pCi/m Location PE-1 Quarter 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Req. LLD Lab Code PEAP- 2173 PEAP- 4439 PEAP- 6492 PEAP- 8477 3

Vol. (m ) 7558 7861 7561 7062 Be-7 0.058 +/- 0.008 0.073 +/- 0.009 0.065 +/- 0.009 0.062 +/- 0.009 Co-58 < 0.0006 < 0.0003 < 0.0003 < 0.0004 Co-60 < 0.0003 < 0.0002 < 0.0006 < 0.0004 -

Cs-1 34 < 0.0004 < 0.0004 < 0.0002 < 0.0003 0.037 Cs-1 37 < 0.0002 < 0.0003 < 0.0003 < 0.0003 0.045 Location PE-3 Lab Code PEAP- 2174 PEAP- 4440 PEAP- 6493 PEAP- 8478 Vol. (m3) 7524 7780 7433 7509 Be-7 0.060 +/- 0.009 0.085 +/- 0.011 0.071 +/- 0.010 0.049 +/- 0.009 Co-58 < 0.0004 < 0.0003 < 0.0004 < 0.0003 Co-60 < 0.0003 < 0.0002 < 0.0006 < 0.0004 -

Cs-134 < 0.0003 < 0.0003 < 0.0003 < 0.0004 0.037 Cs-137 < 0.0004 < 0.0003 < 0.0002 < 0.0004 0.045 Location PE-4 Lab Code PEAP- 2175 PEAP- 4441 PEAP- 6494 PEAP- 8479 3

Vol. (M ) 7938 7914 7234 7278 Be-7 0.067 +/- 0.009 0.074 +/- 0.011 0.074 +/- 0.009 0.051 +/- 0.008 Co-58 < 0.0004 < 0.0002 < 0.0004 < 0.0003 Co-60 < 0.0004 < 0.0002 < 0.0006 < 0.0002 -

Cs-134 < 0.0005 < 0.0003 < 0.0002 < 0.0003 0.037 Cs-1 37 < 0.0003 < 0.0002 < 0.0003 < 0.0003 0.045 Location PE-5 Lab Code PEAP- 2176 PEAP- 4442 PEAP- 6495 PEAP- 8480 Vol. (M3) 7178 7820 7630 7395 Be-7 0.061 +/- 0.009 0.080 +/- 0.009 0.065 +/- 0.010 0.047 +/- 0.009 Co-58 < 0.0003 < 0.0004 < 0.0003 < 0.0005 Co-60 < 0.0003 < 0.0003 < 0.0006 < 0.0005 -

Cs-134 < 0.0003 < 0.0003 < 0.0003 < 0.0004 0.037 Cs-137 < 0.0005 < 0.0005 < 0.0004 < 0.0002 0.045 C-1I

PNPP I

Airborne particulates, analyses for gamma-emitting isotopes.

I Collection: Quarterly Composite Units: pCi/m3 I Location Quarter 1st Qtr. 2nd Qtr.

PE-6 3rd Qtr. 4th Qtr. Req. LLD I Lab Code PEAP- 2177 PEAP- 4443 PEAP- 6496 PEAP- 8481 Vol. 3 (M ) 7437 7632 7136 7209 I Be-7 0.053 +/- 0.009 0.077 +/- 0.009 0.072 +/- 0.009 0.051 +/- 0.010 Co-58 Co-60

< 0.0004

< 0.0002

< 0.0004

< 0.0003

< 0.0004 -

I Cs-134 < 0.0004 < 0.0003 < 0.0003 < 0.0003 0.037 Cs-137 < 0.0002 < 0.0004 < 0.0004 < 0.0003 0.045 I

Location Lab Code 3

PEAP- 2178 PEAP- 4444 PE-7 PEAP- 6497 PEAP- 8482 I Vol. (M ) 7594 7891 7415 7279 Be-7 0.069 +/- 0.010 0.070 +/- 0.008 0.066 +/- 0.008 0.055 +/- 0.010 I

Co-58 < 0.0003 < 0.0002 < 0.0003 < 0.0004 Co-60 Cs-1 34 0.0002 0.0005

< 0.0002

< 0.0003

< 0.0004

< 0.0002 0.037 I

Cs-1 37 < 0.0003 < 0.0003 < 0.0006 < 0.0003 0.045 Location PE-35 I

Lab Code Vol. 3 (M )

PEAP- 2179 7616 PEAP- 4445 7863 PEAP- 6498 7224 PEAP- 8483 7043 I Be-7 Co-58 0.057 +/- 0.007

< 0.0003 0.071 +/- 0.010

< 0.0004 0.075 +/- 0.010

< 0.0004 0.054 +/- 0.009

< 0.0003

< 0.0005 I

Co-60 < 0.0002 < 0.0005 < 0.0006 -

Cs-1 34 Cs-137

< 0.0003

< 0.0002

< 0.0004

< 0.0003

< 0.0002

< 0.0003

< 0.0002 0.037 0.045 I

C-12

PNPP Lake water, analyses for gross beta and gamma emitting isotopes.

Location: P-28 Collection: Monthly composites Units: pCi/L Lab Code PELW- 569 PELW- 988 PELW- 1659 PELW- 2461 Start Date 12-29-11 01-26-12 02-23-12 03-29-12 Req. LLD End Date 01-26-12 02-23-12 03-29-12 04-26-12 Gross beta 2.4 +/- 1.1 2.0 +/- 0.8 2.6 +/- 1.1 < 1.9 3.0 Mn-54 < 1.5 < 2.2 < 1.8 < 2.2 11 Fe-59 < 3.1 < 4.0 < 5.1 < 3.3 22 Co-58 < 2.6 < 1.5 < 1.9 < 1.9 11 Co-60 < 1.7 < 2.0 < 1.5 < 2.1 11 Zn-65 < 2.6 < 2.1 < 2.1 < 3.4 22 Zr-95 < 2.8 < 5.8 < 4.9 < 5.0 22 Nb-95 < 3.0 < 3.0 < 1.9 < 3.0 11 Cs-134 < 2.0 < 1.6 < 2.4 < 2.3 11 Cs-1 37 < 2.4 < 3.4 < 2.6 < 2.3 13 Ba-1 40 < 18.0 < 15.6 < 12.1 < 10.4 45 La-1 40 < 3.4 < 2.4 < 4.6 < 2.5 11 Lab Code PELW- 3454 PELW- 3966 PELW- 4711 PELW- 5560 Start Date 04-26-12 05-31-12 06-28-12 07-26-12 Req. LLD End Date 05-31-12 06-28-12 07-26-12 08-30-12 Gross beta 2.1 +/- 0.9 1.5 +/- 0.6 2.5 +/- 1.1 1.2 +/- 0.6 3.0 Mn-54 < 1.8 < 1.4 < 1.5 < 3.4 11 Fe-59 < 5.5 < 4.4 < 3.6 < 5.9 22 Co-58 < 2.4 < 1.1 < 2.3 < 1.7 11 Co-60 < 1.6 < 2.1 < 1.7 < 1.9 11 Zn-65 < 3.8 < 3.1 < 1.7 < 4.8 22 Zr-95 < 6.1 < 4.5 < 3.5 < 4.9 22 Nb-95 < 3.6 < 3.4 < 1.9 < 3.3 11 Cs-1 34 < 2.1 < 1.8 < 1.9 < 3.1 11 Cs-1 37 < 2.6 < 1.7 < 2.0 < 3.2 13 Ba-1 40 < 11.3 < 34.5 < 17.7 < 18.1 45 La-1 40 < 6.4 < 6.7 < 4.3 < 2.1 11 Lab Code PELW- 6083 PELW- 7143 PELW- 7810 PELW- 8255 Start Date 08-30-12 09-26-12 10-25-12 11-29-12 Req. LLD End Date 09-26-12 10-25-12 11-29-12 12-27-12 Gross beta 2.3 +/- 1.2 1.5 +/- 0.6 2.6 +/- 1.1 1.4 +/- 0.6 3.0 Mn-54 < 2.4 < 2.7 < 2.0 < 2.1 11 Fe-59 < 6.0 < 6.4 < 4.5 < 4.6 22 Co-58 < 3.1 < 2.6 < 2.0 < 2.0 11 Co-60 < 2.9 < 2.3 < 2.6 < 1.7 11 Zn-65 < 4.8 < 3.1 < 5.5 < 1.3 22 Zr-95 < 4.8 < 5.3 < 3.7 < 2.4 22 Nb-95 < 4.4 < 3.4 < 3.1 < 2.7 11 La- 140 < 5.8 < 4.5 < 3.7 < 2.3 11 C-1 3

PNPP I

Lake water, analyses for gross beta and gamma emitting isotopes.

I Location: P-34 Lab Code PELW- 570 Collection: Monthly composites PELW- 989 PELW- 1660 Units: pCi/L PELW- 2462 I

Start Date 12-29-11 01-26-12 02-23-12 03-29-12 Req. LLD End Date Gross beta 01-26-12 1.9 +/- 0.9 02-23-12 2.5 +/- 0.7 03-29-12 1.9 +/- 1.0 04-26-12

< 1.6 3.0 I

Mn-54 < 4.1 < 2.5 < 2.9 < 2.9 11 Fe-59 Co-58

< 6.1

< 3.1

< 8.6

< 3.8

< 6.9

< 3.2

< 5.5

< 3.1 22 11 I Co-60 < 2.3 < 3.7 < 2.6 < 3.2 11 Zn-65 Zr-95 Nb-95

< 3.1

< 5.7

< 4.9

< 5.7

< 6.5

< 3.5

< 2.6

< 7.5

< 3.1

< 5.9

< 4.9

< 4.2 22 22 11 I

Cs-1 34 Cs-1 37 Ba-1 40

< 3.7

< 2.2

< 12.5

< 2.2

< 5.0

< 26.5

< 3.4

< 3.2

< 17.4

< 2.9

< 4.2

< 22.5 11 13 45 i

La-1 40 < 3.2 < 5.5 < 4.9 < 7.7 11 Lab Code PELW- 3456 PELW- 3967 PELW- 4712 PELW- 5561 I

Start Date 04-26-12 05-31-12 06-28-12 07-26-12 Req. LLD End Date Gross beta Mn-54 05-31-12 2.3 +/- 0.8

< 2.7 06-28-12 1.2 +/- 0.5

< 1.8 07-26-12 1.9 +/- 0.9

< 1.9 08-30-12 1.4 +/- 0.6

< 2.1 3.0 11 I

Fe-59 Co-58 Co-60

< 6.0

< 2.6

< 1.9

< 4.0

< 2.2

< 1.1

< 4.1

< 1.8

< 1.5

< 4.3

< 2.9

< 2.6 22 11 11 I

Zn-65 Zr-95 Nb-95

< 5.7

< 5.4

< 2.5

< 1.7

< 3.6

< 3.0

< 2.0

< 3.3

< 2.8

< 2.1

< 4.8

< 3.9 22 22 11 I

Cs-134 < 1.9 < 1.5 < 1.8 < 2.1 11 Cs-137 Ba-140

< 3.9

< 24.0

< 2.1

< 21.2

< 2.1

< 19.4

< 3.1

< 21.3 13 45 I

La-140 < 2.6 < 5.5 < 4.8 < 4.6 11 Lab Code Start Date PELW- 6084 08-30-12 PELW- 7144 09-26-12 PELW- 7811 10-25-12 PELW- 8256 11-29-12 Req. LLD I

End Date Gross beta Mn-54 09-26-12 2.1 +/- 0.9

< 2.2 10-25-12 1.2 +/- 0.5

< 3.2 11-29-12 2.5 +/- 1.1

< 2.1 12-27-12 1.3 +/- 0.5

< 2.4 3.0 11 I

Fe-59 < 4.8 < 5.0 < 4.4 < 3.9 22 Co-58 Co-60

< 2.4

< 3.4

< 2.8

< 1.0

< 2.1

< 2.8

< 2.0 11 11 I

Zn-65 < 4.6 < 2.3 < 3.0 < 3.4 22 Zr-95 Nb-95

< 4.5

< 3.5

< 3.2

< 5.1

< 3.8

< 3.0

< 4.4

< 1.4 22 11 I

Cs-1 34 < 2.7 < 2.4 < 2.1 < 2.9 11 Cs-137 Ba-1 40 La-1 40

< 1.8

< 25.8

< 3.5

< 2.4

< 31.7

< 8.1

< 2.9

< 16.5

< 3.3

< 2.8

< 14.4

< 4.2 13 45 11 I

I C-14 I

PNPP Lake water, analyses for gross beta and gamma emitting isotopes.

Location: P-36 Collection: Monthly composites Units: pCi/L Lab Code PELW- 571 PELW- 990 PELW- 1661 PELW- 2463 Start Date 12-29-11 01-26-12 02-23-12 03-29-12 Req. LLD End Date 01-26-12 02-23-12 03-29-12 04-26-12 Gross beta 3.1 +/- 1.1 2.4 +/- 0.8 2.4 +/- 1.0 2.7 +/- 1.0 3.0 Mn-54 < 2.8 < 3.1 < 1.4 < 2.2 11 Fe-59 < 5.5 < 8.5 < 3.2 < 5.4 22 Co-58 < 2.6 < 2.2 < 1.6 < 1.8 11 Co-60 < 1.9 < 2.7 < 1.9 < 2.3 11 Zn-65 < 4.1 < 6.8 < 2.3 < 4.6 22 Zr-95 < 6.9 < 7.3 < 2.9 < 5.6 22 Nb-95 < 3.9 < 2.6 < 1.4 < 4.4 11 Cs-134 < 2.5 < 2.9 < 1.5 < 2.2 11 Cs-1 37 < 3.8 < 4.6 < 1.6 < 3.3 13 Ba-140 < 19.6 < 13.1 < 8.3 < 18.9 45 La-140 < 3.6 < 4.6 < 3.2 < 2.3 11 Lab Code PELW- 3457 PELW- 3968 PELW- 4713 PELW- 5562 Start Date 04-26-12 05-31-12 06-28-12 07-26-12 Req. LLD End Date 05-31-12 06-28-12 07-26-12 08-30-12 Gross beta 2.3 +/- 0.7 1.0 +/- 0.5 2.0 +/- 1.0 1.1 +/- 0.5 3.0 Mn-54 < 2.0 < 2.2 < 1.6 < 1.9 11 Fe-59 < 3.7 < 5.3 < 3.7 < 7.5 22 Co-58 < 2.0 < 2.6 < 1.5 < 1.8 11 Co-60 < 2.2 < 1.4 < 1.7 < 2.9 11 Zn-65 < 3.9 < 3.5 < 1.9 < 4.5 22 Zr-95 < 3.7 < 4.3 < 2.6 < 3.7 22 Nb-95 < 4.6 < 4.0 < 2.5 < 3.7 11 Cs-134 < 2.3 < 2.4 < 1.4 < 2.6 11 Cs-137 < 3.3 < 2.9 < 1.5 < 3.3 13 Ba- 140 < 20.7 < 33.6 < 14.8 < 19.9 45 La-1 40 < 2.6 < 9.6 < 2.9 < 2.5 11 Lab Code PELW- 6085 PELW- 7145 PELW- 7812 PELW- 8257 Start Date 08-30-12 09-26-12 10-25-12 11-29-12 Req. LLD End Date 09-26-12 10-25-12 11-29-12 12-27-12 Gross beta 2.4 +/- 1.0 1.0 +/- 0.5 2.5 +/- 1.0 0.9 +/- 0.5 3.0 Mn-54 < 1.4 < 2.4 < 2.0 < 2.2 11 Fe-59 < 5.0 < 7.5 < 6.7 < 3.7 22 Co-58 < 2.4 < 3.1 < 2.3 < 2.2 11 Co-60 < 1.4 < 1.6 < 2.0 < 2.0 11 Zn-65 < 3.5 < 4.3 < 3.3 < 2.4 22 Zr-95 < 4.9 < 4.3 < 5.5 < 3.3 22 Nb-95 < 2.9 < 4.5 < 3.5 < 2.5 11 Cs-134 < 2.2 < 3.3 < 2.8 < 2.2 11 Cs-137 < 3.2 < 3.5 < 2.2 < 2.6 13 Ba-1 40 < 30.3 < 24.4 < 25.9 < 15.1 45 La-1 40 < 5.2 < 5.4 < 4.3 < 2.9 11 C-15

PNPP I

Lake water, analyses for gross beta and gamma emitting isotopes.

U Location: P-59 Lab Code NSa Collection: Monthly composites PELW- 991 PELW- 1662 Units: pCi/L PELW- 2464 I

Start Date End Date Gross beta 01-27-11 01-26-12 02-23-12 2.5 +/- 0.7 02-23-12 03-29-12 2.9 +/- 1.0 03-29-12 04-26-12 2.1 +/- 0.9 Req. LLD 3.0 I

Mn-54 < 2.7 < 2.3 < 2.0 11 Fe-59 Co-58

< 2.8

< 2.3

< 4.7

< 1.9

< 3.3

< 3.3 22 11 I

Co-60 < 2.2 < 2.7 < 1.9 11 Zn-65 Zr-95 Nb-95

< 2.8

< 3.4

< 2.8

< 4.8

< 6.4

< 2.8

< 4.4

< 5.8

< 2.9 22 22 11 I

Cs-1 34 Cs-1 37 Ba-1 40

< 2.0

< 2.8

< 16.1

< 1.9

< 2.5

< 24.1

< 3.1

< 3.3

< 19.4 11 13 45 I

La-1 40 < 3.7 < 2.4 < 2.1 11 Lab Code PELW- 3458 PELW- 3969 PELW- 4714 PELW- 5563 I

Start Date 04-26-12 05-31-12 06-28-12 07-26-12 Req. LLD End Date Gross beta 05-31-12 2.1 +/- 0.8 06-28-12 1.4 +/- 0.5 07-26-12 1.9 +/- 0.9 08-29-12 1.5 +/- 0.6 3.0 I

Mn-54 < 2.3 < 1.1 < 1.8 < 3.0 11 Fe-59 Co-58 Co-60

< 3.6

< 1.7

< 1.0

< 2.7

< 0.7

< 0.9

< 4.6

< 1.3

< 1.9

< 2.6

< 2.9

< 2.9 22 11 11 I

Zn-65 Zr-95 Nb-95

< 4.5

< 4.7

< 3.3

< 2.3

< 2.6

< 1.9

< 2.9

< 4.3

< 2.9

< 2.7

< 5.0

< 3.7 22 22 11 I

Cs-1 34 < 3.2 < 0.9 < 2.0 < 1.7 11 Cs-1 37 Ba-1 40

< 2.8

< 15.3

< 1.3

< 12.6

< 2.6

< 19.5

< 2.8

< 22.5 13 45 I

La-1 40 < 2.6 < 4.0 < 4.2 < 2.9 11 Lab Code PELW- 6086 PELW- 7146 PELW- 7813 PELW- 8258 I Start Date 08-29-12 09-26-12 10-24-12 11-28-12 Req. LLD End Date Gross beta Mn-54 09-26-12

< 1.6

< 2.8 10-24-12

< 0.9

< 2.3 11-28-12 2.4 +/- 0.9

< 2.8 12-27-12 1.2 +/- 0.5

< 1.7 3.0 11 I

Fe-59 Co-58 Co-60

< 5.2

< 1.4

< 2.6

< 3.1

< 2.7

< 2.4

< 3.0

< 2.7

< 2.2

< 3.2

< 2.4

< 2.2 22 11 11 I

Zn-65 < 3.7 < 3.8 < 3.9 < 2.3 22 Zr-95 Nb-95

< 5.8

< 3.1

< 2.1

< 3.2

< 4.4

< 2.7

< 4.8

< 2.5 22 11 11 I

Cs-134 < 2.2 < 2.5 < 1.8 < 2.0 Cs-137 Ba-140 La-140

< 2.5

< 21.4

< 4.3

< 2.2

< 31.7

< 8.9

< 2.2

< 12.5

< 3.3

< 2.5

< 17.1

< 3.4 13 45 11 I

a No sample available, shoreline frozen.

I C-1 6 I

PNPP Lake water, analyses for gross beta and gamma emitting isotopes.

Location: P-60 Collection: Monthly composites Units: pCi/L Lab Code NSa PELW- 992 PELW- 1663 PELW- 2465 Start Date 01-26-12 02-23-12 03-29-12 Req. LLD End Date 01-27-11 02-23-12 03-29-12 04-26-12 Gross beta 3.7 +/- 0.8 3.1 +/- 1.1 < 1.8 3.0 Mn-54 < 2.6 < 2.3 < 3.4 11 Fe-59 < 3.7 < 3.5 < 2.2 22 Co-58 < 2.7 < 2.0 < 3.4 11 Co-60 < 1.1 < 2.6 < 2.5 11 Zn-65 < 3.9 < 5.8 < 3.4 22 Zr-95 < 2.2 < 3.6 < 3.6 22 Nb-95 < 2.3 < 2.1 < 3.2 11 Cs-134 < 2.2 < 3.1 < 2.6 Cs-1 37 < 3.1 < 3.1 < 3.3 13 Ba-1 40 < 18.2 < 12.2 < 24.0 45 La-1 40 < 2.3 < 5.9 < 2.7 11 Lab Code PELW- 3459 PELW- 3971 PELW- 4715 PELW- 5564 Start Date 04-26-12 05-31-12 06-28-12 07-26-12 Req. LLD End Date 05-31-12 06-28-12 07-26-12 08-29-12 Gross beta 1.2 +/- 0.4 < 1.9 < 1.8 1.8 +/- 0.6 3.0 Mn-54 < 2.3 < 1.4 < 4.4 < 2.8 11 Fe-59 < 4.0 < 2.4 < 3.6 < 3.8 22 Co-58 < 2.5 < 1.9 < 2.4 < 0.8 11 Co-60 < 1.6 < 1.5 < 3.0 < 2.5 11 Zn-65 < 3.6 < 3.1 < 4.5 < 2.4 22 Zr-95 < 6.9 < 2.4 < 5.2 < 3.6 22 Nb-95 < 4.6 < 2.1 < 1.9 < 3.2 11 Cs-1 34 < 3.0 < 1.5 < 2.9 < 2.8 11 Cs-1 37 < 3.0 < 1.6 < 3.1 < 3.0 13 Ba-1 40 < 18.8 < 14.4 < 23.2 < 17.1 45 La-140 < 6.7 < 6.3 < 3.8 < 3.9 11 Lab Code PELW- 6087 PELW- 7147 PELW- 7814 PELW- 8259 Start Date 08-29-12 09-26-12 10-24-12 11-28-12 Req. LLD End Date 09-26-12 10-24-12 11-28-12 12-27-12 Gross beta 1.9 +/- 1.0 1.4 +/- 0.6 3.5 +/- 1.0 1.6 +/- 0.6 3.0 Mn-54 < 2.8 < 2.2 < 2.5 < 2.0 11 Fe-59 < 2.5 < 6.0 < 4.8 < 1.9 22 Co-58 < 2.0 < 3.9 < 2.7 < 1.4 11 Co-60 < 1.6 < 1.9 < 2.5 < 2.1 11 Zn-65 < 2.0 < 3.2 < 4.3 < 3.8 22 Zr-95 < 3.3 < 3.4 < 5.3 < 3.4 22 Nb-95 < 3.0 < 3.3 < 2.6 < 1.7 11 Cs-134 < 2.1 < 3.2 < 2.4 < 1.6 11 Cs-137 < 2.5 < 2.6 < 3.1 < 2.2 13 Ba-1 40 < 19.9 < 23.0 < 12.5 < 11.3 45 La- 140 < 4.3 < 6.8 < 4.5 < 2.8 11 a No sample available, shoreline frozen.

C-17

PNPP I

Lake Water, analysis for tritium.

I Collection: Quarterly composites of monthly collections.

Units: pCi/L Required limit of detection: 1500 pCi/L I

Location Period 1st Qtr. 2nd Qtr.

P-28 3rd Qtr. 4th Qtr.

I Lab Code PELW- 1692 PELW- 4197 PELW- 6257 PELW- 8281 H-3 < 144 < 149 < 150 < 139 I

Location Period Lab Code 1st Qtr.

PELW- 1693 2nd Qtr.

PELW- 4198 P-34 3rd Qtr.

PELW- 6258 4th Qtr.

PELW- 8282 II H-3 < 144 < 149 < 150 < 139 I

Location P-36 Period Lab Code 1st Qtr.

PELW- 1694 2nd Qtr.

PELW- 4199 3rd Qtr.

PELW- 6260 4th Qtr.

PELW- 8283 I

H-3 < 144 < 149 < 150 < 139 Location P-59 I

Period Lab Code H-3 1st Qtr.

PELW- 1695

< 144 2nd Qtr.

PELW- 4200

< 149 3rd Qtr.

PELW- 6261

< 150 4th Qtr.

PELW- 8284

< 139 I

Location P-60 Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code PELW- 1696 PELW- 4201 PELW- 6262 PELW- 8285 H-3 < 144 < 149 < 150 < 139 C-1 8

PNPP Milk, analyses for iodine-131 and gamma-emitting isotopes.

Collection: Semimonthly during grazing season, monthly at other times.

Collection Lab Concentration (pCi/L)

Date Code 1-131 Cs-134 Cs-137 Ba-140 La-140 K-40 Required LLD (pCi/L) 0.8 11 13 45 11 P-1 8 01-03-12 NDa 02-06-12 ND 03-05-12 ND 04-02-12 PEMI- 1684 < 0.3 < 2.6 <3.1 < 15.5 < 2.4 1281 +/-111 04-16-12 PEMI- 2095 < 0.3 <3.1 <4.1 < 22.9 <2.5 1620 +/- 124 05-07-12 PEMI- 2679 < 0.4 <3.2 <3.2 < 11.8 <3.3 1634 +/-114 05-22-12 PEMI- 3084 <0.2 < 3.0 <4.0 < 16.7 <4.4 1781 +/-119 06-04-12 PEMI- 3447 < 0.4 <3.0 < 3.8 < 25.1 < 1.9 1720 +/-135 06-18-12 PEMI- 3678 < 0.2 <3.2 <4.2 < 24.2 < 6.5 1813 +/-111 07-02-12 PEMI- 3956 < 0.4 < 2.9 < 3.3 < 24.0 <7.1 1891 +/-125 07-16-12 PEMI- 4205 < 0.4 < 4.2 < 4.8 < 29.2 <2.4 1641 +/-118 08-06-12 PEMI- 4939 < 0.2 < 3.5 <4.0 < 39.8 <5.2 1822 +/- 117 08-20-12 PEMI- 5261 < 0.3 < 2.5 <3.9 < 20.7 < 1.4 1841 +/-114 09-04-12 PEMI- 5556 <0.2 <2.9 <4.5 < 18.1 < 4.7 1872 +/- 117 09-17-12 PEMI- 5903 < 0.4 <3.2 < 2.9 < 25.4 < 3.3 1911 +/- 106 10-02-12 PEMI- 6209 < 0.4 <2.3 < 3.4 < 39.7 < 4.5 1909 +/-123 10-15-12 PEMI- 6690 < 0.5 <3.0 < 3.0 < 28.0 < 5.7 2028 +/-117 11-05-12 ND 12-03-12 ND P-19 01-03-12 PEMI- 65 < 0.4 <3.3 < 3.5 < 28.1 < 3.5 1289 +/- 107 02-06-12 PEMI- 721 < 0.3 < 2.8 < 2.7 < 18.3 < 2.5 1369 +/- 92 03-05-12 PEMI- 1147 < 0.3 <2.5 < 2.9 < 18.4 <4.1 1403 +/- 102 04-02-12 PEMI- 1656 < 0.2 < 2.8 <4.2 < 14.8 <2.6 1277 +/- 115 04-16-12 PEMI- 2096 < 0.4 < 3.6 <3.9 < 19.7 < 1.9 1453 +/- 116 05-07-12 PEMI- 2680 < 0.4 < 2.7 <3.9 < 22.1 < 1.9 1359 +/- 112 05-21-12 PEMI- 3085 < 0.2 < 2.9 <3.3 < 23.0 < 1.8 1421 +/- 109 06-04-12 PEMI- 3448 <0.3 <2.5 < 3.8 < 19.4 < 2.5 1255 +/- 106 06-18-12 PEMI- 3679 <0.2 <2.7 <3.2 < 25.0 < 4.8 1369 +/- 101 07-02-12 PEMI- 3957 < 0.3 <2.6 < 3.0 < 18.5 < 4.0 1400 +/- 102 07-16-12 PEMI- 4206 <0.2 <2.7 < 3.8 < 27.4 < 2.9 1439 +/- 114 08-06-12 PEMI- 4940 < 0.3 < 2.7 < 3.0 < 27.1 <6.1 1376 +/- 87 08-20-12 PEMI- 5262 < 0.3 < 2.7 <2.3 < 21.7 < 3.4 1376 +/-113 09-04-12 PEMI- 5557 < 0.2 < 2.9 <3.2 < 15.6 <2.8 1413 +/-95 11-05-12 PEMI- 7170 < 0.3 < 3.5 <3.9 < 10.5 <2.4 1316 +/- 97 12-03-12 PEMI- 7774 < 0.5 < 3.3 <4.1 < 20.9 <3.7 1321 +/- 108 a ND = No data, no milk available.

C-1 9

PNPP I

Milk, analyses for iodine-131 and gamma-emitting isotopes (continued).

I Collection: Semimonthly during grazing season, monthly at other times.

Collection Lab Concentration (pCi/L)

I Date Code 1-131 Cs-134 Cs-137 Ba-140 La-140 K-40 Required LLD (pCi/L) 0.8 11 13 45 11 I P-41 01-03-12 NDa I

02-06-12 ND 03-05-12 04-02-12 04-16-12 PEMI-PEMI-ND 1657 2097

< 0.2

< 0.3

<4.1

< 3.6

<4.8

< 4.4

< 20.2

< 10.9

<4.2

< 4.7 1630 1868

+/- 126

+/- 123 I

05-07-12 05-21-12 06-04-12 PEMI-PEMI-PEMI-2681 3086 3449

< 0.4

< 0.2

<0.3

<2.5

<2.1

<3.4

<3.7

< 17.1

< 10.6

<11.1

< 2.7

< 1.8

< 1.7 1776 1810 1828

+/- 129

+/-120

+/- 130 I

06-18-12 PEMI- 3680 < 0.2 <2.7 <4.0 < 36.2 < 5.3 1847 +/- 119 07-02-12 07-16-12 PEMI-PEMI-3958 4207

< 0.3

<0.3

<3.2

<3.0

<4.1

<3.5

< 26.2

< 22.7

<4.2

<8.1 1801 1825

+/-113

+/-121 I

08-06-12 PEMI- 4941 < 0.4 <2.6 < 3.4 < 35.1 <4.3 1927 +/- 113 08-20-12 09-04-12 PEMI-PEMI-5263 5558

< 0.3

< 0.2

<4.9

<3.2

< 3.8

< 34.8

< 19.4

<3.2

< 2.8 1904 1800

+/-139

+/-135 I

09-17-12 PEMI- 5905 < 0.4 <3.2 <4.6 < 38.5 <7.9 1924 +/- 121 10-02-12 10-15-12 11-05-12 ND ND ND I

12-03-12 P-51 ND I

01-03-12 02-06-12 PEMI- 66 PEMI- 722

< 0.3

<0.3

<2.7

<3.0

<4.1

< 25.4

< 16.8

<3.6

<4.4 1051 802

+/- 90

+/- 83 I

03-05-12 PEMI- 1148 <0.3 <2.2 <3.1 <11.2 <2.6 848 +/- 73 04-02-12 04-16-12 PEMI- 1658 PEMI- 2098

< 0.2

<0.2

<2.5

< 1.6

< 2.8

< 2.9

< 18.0

< 16.3

< 3.7

<3.7 810 851

+/- 90

+/- 85 I

05-07-12 PEMI- 2682 <0.4 < 3.0 < 3.4 <11.5 < 3.9 946 +/- 96 05-21-12 06-04-12 06-18-12 PEMI-PEMI-PEMI-3087 3450 3681

<0.5

<0.4

<0.2

<2.8

< 2.9

< 2.2

< 3.8

<2.3

< 2.8

<11.0

< 21.0

< 31.4

<2.2

< 1.9

<3.5 972 1004 921

+/- 101

+/- 96

+/- 80 I

07-02-12 07-16-12 08-06-12 PEMI-PEMI-PEMI-3959 4208 4942

<0.3

< 0.3

<0.3

<2.4

<2.1

< 2.3

< 2.8

< 2.9

< 14.5

< 32.8

< 30.1

<3.6

<5.1

<5.0 775 1377 1397

+/- 66

+/- 102

+/- 93 I

08-20-12 PEMI- 5264 <0.3 < 3.0 < 3.7 < 29.7 <5.5 927 +/- 98 09-04-12 09-17-12 PEMI-PEMI-5559 5906

< 0.2

< 0.3

< 3.6

< 2.3

< 3.0

< 1.6

< 18.4

< 31.4

<2.5

<6.3 956 818

+/- 97

+/- 85 I

10-02-12 PEMI- 6211 < 0.4 < 2.5 < 2.6 < 29.0 <6.1 804 +/- 74 10-15-12 11-05-12 PEMI-PEMI-6693 7171

< 0.4

< 0.3

< 2.8

< 4.3

< 1.8

< 3.9

< 28.1

< 18.0

<3.2

< 1.8 738 987

+/- 77

+/- 94 I 12-03-12 PEMI- 7775 < 0.5 < 4.9 <5.3 < 31.9 <2.5 626 +/- 103 a ND = No data, no milk available. I C-20

PNPP Food Products, analyses for gamma emitting isotopes.

Collection: Monthly Units: pCi/kg wet Location: P-2 Lab Code PEVE- 4222 PEVE- 4224 PEVE- 5164 PEVE- 5165 Date Collected 07-13-12 07-13-12 08-15-12 08-15-12 Req. LLD Sample Type Swiss Chard Japan. Greens Turnip Greens Japan. Greens Be-7 163 +/- 82 306 +/- 81 562 +/- 149 510 +/- 120 K-40 7230 +/- 324 4641 +/- 244 4522 +/- 378 3711 +/- 282 Co-58 < 6.3 < 6.3 < 9.9 < 8.3 Co-60 < 8.0 < 6.8 < 7.6 < 4.8 1-131 < 16.2 < 14.0 < 13.0 < 21.7 45 Cs-1 34 < 7.6 < 6.9 < 11.6 < 6.6 45 Cs-137 < 9.1 < 8.2 < 11.7 < 7.9 60 Lab Code PEVE- 5166 PEVE- 5168 PEVE- 5833 PEVE- 5834 Date Collected 08-15-12 08-15-12 09-12-12 09-12-12 Req. LLD Sample Type Collard Greens Swiss Chard Japan. Greens Collard Greens Be-7 < 77 255 +/- 85 563 +/- 99 210 +/- 120 K-40 4260 +/- 277 4924 +/- 286 3421 +/- 222 4209 +/- 284 Co-58 < 7.7 < 4.7 < 8.9 < 8.3 Co-60 < 4.8 < 7.2 < 4.5 < 7.1 1-131 < 12.7 < 13.5 < 28.5 < 35.0 45 Cs-134 < 6.6 < 5.5 < 4.8 < 8.3 45 Cs-137 < 9.0 < 8.6 < 6.7 < 8.1 60 Lab Code PEVE- 5835 PEVE- 5836 PEVE- 6667 PEVE- 6668 Date Collected 09-12-12 09-12-12 10-16-12 10-16-12 Req. LLD Sample Type Swiss Chard Turnips Japan. Greens Turnip Greens Be-7 361 +/- 85 582 +/- 95 870 +/- 127 859 +/- 128 K-40 5582 +/- 302 4516 +/- 233 4537 +/- 306 6370 +/- 347 Co-58 < 6.4 < 7.4 < 9.5 < 7.1 Co-60 < 4.9 < 4.8 < 10.0 < 5.9 1-131 < 20.4 < 26.8 < 35.1 < 28.3 45 Cs-1 34 < 7.6 < 4.6 < 6.2 < 6.5 45 Cs-1 37 < 8.8 < 6.4 < 9.1 < 8.7 60 Lab Code PEVE- 6669 PEVE- 6671 Date Collected 10-16-12 10-16-12 Req. LLD Sample Type Collard Greens Swiss Chard Co-58 < 7.0 < 8.4 Co-60 < 8.4 < 7.5 1-131 < 33.6 < 42.8 45 Cs-134 < 8.6 < 8.3 45 Cs-137 < 8.6 < 12.2 60 C-21

PNPP I

Food Products, analyses for gamma emitting isotopes.

I Collection: Monthly Location: P-16 Units: pCi/kg wet I

Lab Code PEVE- 3798 PEVE- 3800 PEVE- 3801 PEVE- 4225 Date Collected Sample Type 06-20-12 Japan. Greens 06-20-12 Swiss Chard 06-20-12 Collard Greens 07-13-12 Collard Greens Req. LLD I Be-7 K-40

< 102 5931 +/- 377

< 127 7174 +/- 452 5107 +/-

< 96 333

< 79 4746 +/- 279 I

Co-58 < 6.9 < 7.9 < 12.3 < 8.0 Co-60 1-131 Cs-134

< 3.5

< 11.9

< 6.1

< 12.3

< 20.9

< 8.1

< 11.1

< 19.1

< 7.1

< 7.2

< 17.3

< 7.4 45 45 I

Cs-137 Lab Code

< 9.4 PEVE- 4226

< 13.8 PEVE- 4227

< 7.9 PEVE- 5169

< 8.9 PEVE- 5170 60 I

Date Collected 07-13-12 07-13-12 08-15-12 08-15-12 Req. LLD Sample Type Japan. Greens Swiss Chard Collard Greens Swiss Chard I

Be-7 314 +/- 91 213 +/- 99 < 75 215 +/- 115 K-40 Co-58 Co-60 5339 +/- 291

< 7.4

< 10.9 5498 +/- 275

< 8.9

< 7.8 3788 +/-

253 6.1 6.0 5652 +/- 387

< 7.1

< 10.4 I

1-131 Cs-134 Cs-137

< 10.9

< 4.8

< 8.4

< 14.7

< 7.5

< 10.5 11.5 5.6 6.9

< 16.3

< 11.0

< 9.7 45 45 60 I

Lab Code PEVE- 5171 PEVE- 5837 PEVE- 5838 PEVE- 5840 Date Collected 08-15-12 09-12-12 09-12-12 09-12-12 Req. LLD I Sample Type Japan. Greens Japan. Greens Swiss Chard Collard Greens Be-7 K-40 336 +/- 77 4967 +/- 320 501 +/- 83 4394 +/- 239 300 +/- 84 4964 +/- 282 3780 +/-

< 91 293 I

Co-58 Co-60 1-131

< 4.6

< 6.8

< 11.6

< 5.9

< 5.8

< 17.8

< 8.1

< 7.0

< 26.7 8.3 3.7 24.3 45 I

Cs-1 34 Cs-137

< 8.1

< 9.9

< 5.1

< 7.0

< 6.2

< 9.1 8.1 7.3 45 60 I Lab Code PEVE- 6672 PEVE- 6673 PEVE- 6674 Date Collected Sample Type 10-16-12 Swiss Chard 10-16-12 Japan. Greens 10-16-12 Collard Greens Req. LLD I Be-7 K-40 736 +/- 142 5018 +/- 357 749 +/- 151 6092 +/- 359 598 +/- 116 3320 +/- 273 I

Co-58 < 7.6 < 10.8 < 5.5 Co-60 1-131 Cs-1 34

< 7.0

< 24.6

< 7.9

< 12.2

< 27.3

< 10.2

< 7.4

< 31.8

< 9.8 45 45 I

Cs-1 37 < 13.0 < 8.2 < 7.2 60 I

C-22

PNPP Food Products, analyses for gamma emitting isotopes.

Collection: Monthly Units: pCi/kg wet Location: P-18 Lab Code PEVE- 3802 PEVE- 4228 PEVE- 4229 PEVE- 5172 Date Collected 06-20-12 07-13-12 07-13-12 08-15-12 Req. LLD Sample Type Japan. Greens Japan. Greens Swiss Chard Collard Greens Be-7 443 +/- 152 307 +/- 61 290 +/- 86 177 +/- 68 K-40 7999 +/- 494 6843 +/- 256 9645 +/- 358 4974 +/- 317 Co-58 < 12.8 < 5.8 < 12.5 < 7.1 Co-60 < 15.9 < 5.6 < 10.3 < 7.9 1-131 < 20.4 < 10.8 < 16.6 < 15.6 45 Cs-134 < 13.9 < 5.4 < 6.4 < 5.4 45 Cs-1 37 < 11.2 < 6.6 < 7.8 < 8.8 60 Lab Code PEVE- 5173 PEVE- 5174 PEVE- 5841 PEVE- 5842 Date Collected 08-15-12 08-15-12 09-12-12 09-12-12 Req. LLD Sample Type Swiss Chard Japan. Greens Swiss Chard Japan. Greens Be-7 372 +/- 93 401 + 99 452 +/- 85 395 +/- 81 K-40 5404 +/- 301 5127 +/- 323 7473 +/- 325 5899 +/- 304 Co-58 < 5.4 < 6.3 < 8.4 < 6.6 Co-60 < 4.1 < 6.6 < 7.6 < 7.6 1-131 < 14.1 < 13.9 < 19.0 < 24.4 45 Cs-134 < 6.2 < 8.0 < 6.7 < 6.8 45 Cs-1 37 < 8.7 < 8.5 < 6.6 < 6.2 60 Lab Code PEVE- 5843 PEVE- 6675 PEVE- 6676 PEVE- 6677 Date Collected 09-12-12 10-16-12 10-16-12 10-16-12 Req. LLD Sample Type Collard Greens Collard Greens Japan. Greens Swiss Chard Be-7 288 + 84 430 +/- 110 570 +/- 113 660 +/- 144 K-40 4146 + 250 5823 +/- 287 5993 +/- 349 7279 +/- 419 Co-58 6.8 7.2 < 6.7 < 7.3 Co-60 7.2 7.0 < 5.7 < 9.7 1-131 21.8 18.4 < 25.6 < 37.9 45 Cs-134 5.2 5.2 < 8.2 < 6.4 45 Cs-137 7.2 7.0 < 12.5 < 11.5 60 C-23

PNPP I

Food Products, analyses for gamma emitting isotopes.

Collection: Monthly Units: pCi/kg wet I

Location: P-20 Lab Code PEVE- 4230 PEVE- 5175 PEVE- 5176 PEVE- 5177 I

Date Collected Sample Type 07-13-12 Japan. Greens 08-15-12 Japan. Greens 08-15-12 Turnip Greens 08-15-12 Collard Greens Req. LLD I

Be-7 251 +/- 77 262 +/- 79 337 +/- 90 < 143 K-40 Co-58 4611 +/- 230

< 5.4 3260 +/- 269

< 5.1 4063 +/- 299

< 8.0 3439 +/-

332 5.9 I

Co-60 < 7.5 < 6.8 < 9.0 < 7.5 1-131 Cs-1 34 Cs-1 37

< 14.9

< 5.5

< 7.0

< 17.0

< 9.2

< 12.9

< 7.4

< 10.5 25.3 7.7 11.1 45 45 60 I

Lab Code PEVE- 5844 PEVE- 5845 PEVE- 6678 PEVE- 6679 I

I Date Collected 09-12-12 09-12-12 10-16-12 10-16-12 Req. LLD Sample Type Collard Greens Japan. Greens Japan. Greens Collard Greens Be-7 239 +/- 76 429 +/- 75 850 +/- 135 301 +/- 107 K-40 Co-58 4027 +/- 219

< 5.9 3839 +/- 250

< 5.9 5547 +/- 362

< 5.2 4016 +/- 301

< 11.4 U

Co-60 +/- 6.7 < 7.6 < 12.0 < 7.1 1-131 Cs-1 34 Cs-1 37

< 23.1

< 4.5

< 5.0

< 17.0

< 5.6

< 4.1

< 39.5

< 7.8

< 12.0

< 36.2

< 10.3

< 6.9 45 45 60 I

I I

C-24 I

PNPP Food Products, analyses for gamma emitting isotopes.

Collection: Monthly Units: pCi/kg wet Location: P-37 Lab Code PEVE- 3803 PEVE- 3804 PEVE- 3805 PEVE- 4231 Date Collected 06-20-12 06-20-12 06-20-12 07-11-12 Req. LLD Sample Type Japan. Greens Swiss Chard Collard Greens Japan. Greens Be-7 < 95 < 98 < 92 216 +/- 57 K-40 4942 +/- 291 4358 +/- 369 4011 +/- 322 3604 +/- 214 Co-58 < 6.5 < 6.7 < 6.5 < 4.7 Co-60 < 7.5 < 2.7 < 3.9 < 5.5 1-131 < 12.6 < 15.4 < 12.0 < 10.5 45 Cs-134 < 7.1 < 4.5 < 7.7 < 6.0 45 Cs-137 < 8.9 < 9.1 < 9.1 < 8.8 60 Lab Code PEVE- 4232 PEVE- 4233 PEVE- 5178 PEVE- 5179 Date Collected 07-11-12 07-11-12 08-15-12 08-15-12 Req. LLD Sample Type Collard Greens Swiss Chard Swiss Chard Japan. Greens Be-7 < 74 287 +/- 81 386 +/- 108 296 +/- 132 K-40 3636 +/- 255 3100 +/- 236 3282 +/- 314 5366 +/- 449 Co-58 < 4.0 < 8.0 < 5.1 < 7.4 Co-60 < 7.4 < 4.4 < 5.1 < 6.6 1-131 < 10.1 < 14.0 < 19.8 < 14.0 45 Cs-1 34 < 7.6 < 8.0 < 9.9 < 9.5 45 Cs-137 < 9.2 < 9.4 < 9.8 < 12.2 60 Lab Code PEVE- 5180 PEVE- 5846 PEVE- 5847 PEVE- 5848 Date Collected 08-15-12 09-12-12 09-12-12 09-12-12 Req. LLD Sample Type Collard Greens Swiss Chard Collard Greens Japan. Greens Be-7 < 111 246 +/- 86 < 74 150 +/- 64 K-40 5160 +/- 327 3802 +/- 247 3724 +/- 180 3781 +/- 221 Co-58 < 8.2 < 4.1 < 4.5 7.0 Co-60 < 10.4 < 4.2 < 4.6 3.2 1-131 < 23.9 < 23.7 < 18.4 25.5 45 Cs-1 34 < 7.5 < 6.2 < 4.3 5.4 45 Cs-1 37 < 11.0 < 8.1 < 6.8 7.0 60 Lab Code PEVE- 6680 PEVE- 6681 PEVE- 6682 Date Collected 10-16-12 10-16-12 10-16-12 Req. LLD Sample Type Swiss Chard Collard Greens Japan. Greens Be-7 602 +/- 125 106 +/- 58 412 +/- 49 K-40 3016 +/- 243 4388 +/- 169 4754 +/- 164 Co-58 < 8.8 < 3.9 < 5.7 Co-60 < 9.1 < 4.9 < 5.3 1-131 < 25.7 < 20.7 < 21.7 45 Cs-134 < 7.2 < 4.4 < 4.9 45 Cs-137 < 10.2 < 6.3 < 5.5 60 C-25

PNPP U

Food Products, analyses for gamma emitting isotopes.

Collection: Monthly Units: pCi/kg wet I

Location: P-70 Lab Code PEVE- 3806 PEVE- 3807 PEVE- 3808 PEVE- 3809 I

I Date Collected 06-20-12 06-20-12 06-20-12 06-20-12 Req. LLD Sample Type Japan. Greens Swiss Chard Turnip Greens Collard Greens Be-7 227 +/- 99 167 +/- 72 333 +/- 96 < 76 K-40 Co-58 5673 +/- 347

< 7.0 8047 +/- 427

< 4.3 6642 +/- 413

< 6.8 7014 +/-

364 5.5 I

Co-60 < 7.5 < 5.3 < 6.5 < 5.2 1-131 Cs-1 34 Cs-1 37

< 16.7

< 8.4

< 10.0

< 13.3

< 7.0

< 8.7

< 16.0

< 5.7

< 8.8 13.3 8.5 7.4 45 45 60 I

Lab Code Date Collected PEVE- 4234 07-13-12 PEVE- 4235 07-13-12 PEVE- 4236 07-13-12 PEVE- 4237 07-13-12 Req. LLD U

Sample Type, Swiss Chard Japan. Greens Collard Greens Turnip Greens Be-7 333 +/- 95 557 +/- 92 269 +/- 98 739 +/- 99 I

K-40 9190 +/- 385 6273 +/- 271 5581 +/- 275 6864 +/- 281 Co-58 Co-60 1-131

< 10.2

< 8.6

< 13.2

< 4.4

< 6.0

< 10.9

< 8.4

< 7.1

< 9.0

< 5.8

< 4.3

< 11.6 45 I

Cs-134 Cs-137

< 6.3

< 10.4

< 6.6

< 6.2

< 7.4

< 8.7

< 6.8

< 8.5 45 60 I Lab Code PEVE- 5181 PEVE- 5182 PEVE- 5183 PEVE- 5184 Date Collected 08-15-12 08-15-12 08-15-12 08-15-12 Req. LLD I Sample Type Japan. Greens Turnip Greens Collard Greens Swiss Chard Be-7 K-40 1028 +/- 128 5432 +/- 337 2038 +/- 358 5014 +/- 304 4630 +/-

< 75 318 450 + 121 6647 +/- 393 I

Co-58 < 10.3 < 12.8 < 7.5 < 6.1 Co-60 1-131 Cs-134

< 6.3

< 13.0

< 7.1

< 6.2

< 0.0

< 7.2 6.0 9.4

< 7.1

< 11.3

< 14.2

< 8.6 45 45 I

Cs-137 Lab Code

< 10.4 PEVE- 5849

< 8.6 PEVE- 5850

< 9.7 PEVE- 5851

< 10.6 PEVE- 6683 60 I

I Date Collected 09-12-12 09-12-12 09-12-12 10-16-12 Req. LLD Sample Type Collard Greens Swiss Chard Turnips Collard Greens Be-7 150 +/- 75 406 +/- 124 715 +/- 100 73 +/- 41 K-40 Co-58 4774 +/- 324

< 6.9 7941 +/- 407

< 12.0 5954 +/- 278

< 7.2 4059 +/- 145

< 4.5 I

Co-60 < 9.6 < 4.8 < 7.3 < 4.1 1-131 Cs-1 34 Cs-137

< 36.8

< 8.8

< 10.2

< 31.2

< 7.6

< 10.6

< 21.8

< 5.2

< 7.1

< 13.2

< 4.1

< 5.2 45 45 60 I

I C-26 I

PNPP Food Products, analyses for gamma emitting isotopes.

Collection: Monthly Units: pCi/kg wet Location: P-70 Lab Code PEVE- 6684 PEVE- 6685 Date Collected 10-16-12 10-16-12 Req. LLD Sample Type Turnip Greens Swiss Chard Be-7 1356 +/- 160 845 +/- 142 K-40 5522 +/- 329 7663 +/- 396 Co-58 < 7.5 < 7.5 Co-60 < 7.8 < 11.1 1-131 < 29.5 < 39.7 45 Cs-134 < 7.1 < 9.1 45 Cs-137 < 6.0 < 11.7 60 C-27

PNPP I

Fish, analyses for gamma emitting isotopes. I Collection: Annually Units: pCi/kg wet I

Location P-25 Lab Code Date Collected PEF- 5373 08-23-12 PEF- 5374 08-23-12 Req. LLD I

Sample Type Yellow Perch Freshwater Drum I K-40 1580 +/- 325 959 +/- 277 Mn-54 Fe-59 17.2 40.2 19.4 46.4 94 195 I

Co-58 < 11.9 < 10.9 97 Co-60 Zn-65 7.2 16.5 7.8 32.1 97 195 I

Cs-1 34 < 13.5 < 11.2 97 Cs-1 37 < 13.8 < 14.2 112 I

Location Lab Code PEF- 5375 P-32 I

Date Collected Sample Type 08-20-12 Freshwater Drum Req. LLD I

K-40 Mn-54 1257 +/- 311

< 14.2 94 i

Fe-59 < 46.7 195 Co-58 Co-60 13.3 13.7 97 97 i

Zn-65 < 21.0 195 Cs-134 Cs-137 17.7 19.9 97 112 I C-28 I

PNPP Sediments, analyses for gamma emitting isotopes.

Collection: Semiannually Units: pCi/kg dry Location P-25 Lab Code PEBS- 3810 PEBS- 6184 Date Collected 06-19-12 09-11-12 Req. LLD K-40 11635 +/- 557 14554 +/- 632 Co-58 < 20.2 < 21.2 50 Co-60 < 9.8 < 15.5 40 Cs-134 < 14.5 < 17.2 112 Cs-137 81.5 +/- 17.2 271.4 +/- 22.2 135 Location P-26 Lab Code PEBS- 3811 PEBS- 6185 Date Collected 06-19-12 09-11-12 Req. LLD K-40 12029 +/- 441 12807 +/- 602 Co-58 < 21.1 < 26.1 50 Co-60 < 11.2 < 18.5 40 Cs-134 < 12.7 < 15.3 112 Cs-137 35.7 +/- 11.7 75.4 +/- 27.7 135 Location P-27 Lab Code PEBS- 3812 PEBS- 6186 Date Collected 06-19-12 09-11-12 Req. LLD K-40 16892 +/- 767 16579 +/- 666 Co-58 < 26.7 < 14.8 50 Co-60 < 22.0 < 14.1 40 Cs-134 < 24.3 < 17.2 112 Cs-137 152.2 +/- 30.4 181.3 +/- 27.2 135 Location P-32 Lab Code PEBS- 3813 PEBS- 6187 Date Collected 06-19-12 09-11-12 Req. LLD K-40 16956 +/- 487 20844 +/- 807 Co-58 < 19.2 < 29.2 50 Co-60 < 21.2 < 8.4 40 Cs-134 < 13.7 < 20.0 112 Cs-137 414.7 +/- 21.6 529.6 +/- 41.1 135 C-29

PNPP I

1 Sediments, analyses for gamma emitting isotopes.

Collection: Semiannually Location P-64 Units: pCi/kg dry I

Lab Code PEBS- 2972 PEBS- 6188 Date Collected 05-15-12 09-17-12 Req. LLD i K-40 9384 +/- 512 8464 +/- 445 Co-58 Co-60 20.1 12.0 15.3 11.4 50 40 I

Cs-134 < 11.7 < 12.0 112 Cs-137 < 14.8 < 11.0 135 U

Location P-65 Lab Code Date Collected PEBS- 2973 05-15-12 PEBS- 6189 09-17-12 Req. LLD I K-40 9167 +/- 501 7853 +/- 440 Co-58 Co-60 16.6 6.4 14.7 12.1 50 40 I

Cs-134 < 14.0 < 11.9 112 Cs-137 < 13.4 < 13.6 135 I

i i

I i

I C-30 I

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

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

2011 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT

1. There was an inadvertent inclusion of 3.73E-01 Ci of Xenon 138 for first quarter in Table 5. There was no Xenon 138 released in the first quarter of 2011

2. The Report contained two pages that were numbered 8.

3. Some activities were not included when effluents released and doses were determined. When corrected, multiple tables were affected. Changes were less than 10% of what was originally reported. Included with Appendix D are the corrected pages that can be inserted directly into the 2011 report.

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT During any calendar year:

Less than or equal to 10 mrad for gamma radiation, and Less than or equal to 20 mrad for beta radiation Dose to a member of the public from Iodine-1 31, Iodine-1 33, Tritium, and all radionuclides in particulate form with half lives greater than eight days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 7.5 mrem to any organ per any calendar quarter, and Less than or equal to 15 mrem to any organ per any calendar year The PNPP ODCM does not contain a concentration limit for gaseous effluents. For this reason, effluent concentrations are not used to calculate maximum release rates for gaseous effluents.

RELEASE

SUMMARY

Effluents are sampled and analyzed to identify both the type and quantity of radionuclides present. This information is combined with effluent path flow measurements to determine the composition, concentration, and dose contribution of the radioactive effluents.

Liquid Effluents The PNPP liquid radioactive waste system is designed to collect and treat all radioactive liquid waste produced in the plant. The treatment process used for radioactive liquid waste depends on its physical and chemical properties. It is designed to reduce the concentration of radioactive material in the liquid by filtration to remove suspended solids and demineralization to remove dissolved solids. Normally, the effluent from the liquid radioactive waste system is returned to plant systems. To reduce the volume of water stored in plant systems; however, the processed liquid effluent may be discharged from the plant via a controlled release. In this case, effluent activity and dose calculations are performed prior to, and after discharging this processed water to Lake Erie to ensure regulatory compliance and dose minimization principals are maintained.

Liquid radioactive waste system effluents may be intermittently released, which are considered to be "batch" releases. Table 1 provides information on the number and duration of these releases for 2011.

Table 1: Liquid Batch Releases QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 ANNUAL TOTAL Number of batch releases 22 72 37 16 147 Total time period for batch releases, min 4.91 +E03 1.60E+04 8.26E+03 3.55E+03 3.25E+04 Maximum time for a batch release, min 2.28E+02 3.84E+02 2.30E+02 2.27E+02 3.84E+02 Average time period for a batch release, 2.23E+02 2.22E+02 2.23E+02 2.22E+02 2.23E+02 min Minimum time for a batch release, min 2.02E+02 6.OOE+00 2.02E+02 2.05E+02 6.OOE+00 Average stream flow during periods of 1.14E+05 2.04E+05 2.33E+05 1.67E+05 1.80E+05 effluent release into a flowing stream, Llmin Radioactive Effluent Releases Page 10

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I Table 2 provides information on the nuclide composition for the liquid radioactive effluent system releases. If a radionuclide was not present at a level "greater than or equal to the I

LLD" (>LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, LLDs were met, or were below the levels required by the ODCM. Table 2a provides information specific to radioactive effluent batch releases while Table 2b provides I

information specific to continuous radioactive effluent releases.

I Table 2: Summation of All Liquid Effluent Releases QUARTER 1

QUARTER 2

QUARTER 3

QUARTER 4

EST.

TOTAL ERROR, I

_______ _ ______ _ __ ___ (%)

A.

1.

Fission and Activation Products Total Released, Ci 1.43E-03 2.55E-02 5.21 E-03 5.34E-03 1.OOE+01 I

(excluding tritium, gases, alpha)

2. Average Diluted Concentration,

.. Ci/mL

8.80E-11 2.56E-03 8.68E-10 2.10E-02 1.61 E-10 4.75E-03 2.63E-10 8.14E-03 NA NA I

3. Percent of Applicable Limit, %

B. Tritium

1. Total Released, Ci

2. Average Diluted Concentration, 1.08E+01 6.63E-07 1.49E+01 5.07E-07 6.51 E+00 2.02E-07 3.59E+00

1. 77E-07 1.O0E+01 I 4Ci/mL C.

3. Percent of Applicable Limit, %

Dissolved and Entrained Gases 6.63E-02 5.07E-02 2.02E-02 1.77E-02 I

1. Total Released, Ci <LLD <LLD <LLD 1.62E-07 1.OOE+01

2. Average Diluted Concentration, jýi0/mL_

<LLD <LLD <LLD 7.96E-15 NA I

3. Percent of Applicable Limit, % N/A N/A N/A 3.99E-09 NA D.

E.

Gross Alpha Activity, Ci Waste Volume Released, Liters (prior to dilution)

<LLD 2.86E+06

<LLD 8.72E+06 2.94E_10

<LLD 6.33E+06

<LLD 2.74E+06 1.OOE+01 NA I 3.23E_10 2.03E_10 NA F. Dilution Water Volume Used, Liters

<LLD - Less than the lower limit of detection 1.63E+10 2.94E+10 3.23E+10 N/A - Not Applicable, the ODCM does not have a limit for fission and activation products.

2.03E+10 NA I

Averagediluted concentrations are based on total volume of water releasedduring quarter.

Radioactive Effluent Releases Page I1

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 2a: Summation of Batch Liquid Effluent Releases Fission and Activation Products -

A.

Total Released, Ci 1.43E-03 2.55E-02 5.21 E-03 5.07E-03 1.OOE+01 (excluding tritium, gases, alpha)

B. Tritium Total Released, Ci 1.08E+01 1.49E+01 6.51E+00 3.59E+00 1.00E+01 C. Dissolved and Entrained Gases Total Released, Ci <LLD <LLD <LLD <LLD 1.OOE+01 D. Gross Alpha Activity, Ci <LLD <LLD <LLD <LLD 1.OOE+01 E. Waste Volume Released, Liters (prior to 2.86E+06 8.72E+06 4.80E+06 2.34E+06 NA dilution)

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

1 2 3 4 TOTAL ERROR,

(%)

A. Fission and Activation Products Total Released, Ci <LLD <LLD <LLD 2.65E-04 1.OOE+01 (excluding tritium, gases, alp ha)

B. Tritium Total Released, Ci <LLD 2.57E-04 1.55E-03 4.87E-03 1.OOE+01 C. Dissolved and Entrained Gases Total Released, Ci <LLD <LLD <LLD 1.62E-07 1.OOE+01 D. Gross Alpha Activity, Ci <LLD <LLD <LLD <LLD 1.ooE+01 E. Waste Volume Released, Liters (prior to 0.OOE+00 0.OOE+00 1.53E+06 4.01 E+05 NA dilution)

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

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I 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 I

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

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

UNITS 1 2 3 4 TOTAL Tritium Sodium-24 Ci Ci 1.08E+01

<LLD 1.49E+01

<LLD 6.51E+00

<LLD 3.59E+00 1.24E-04 3.51E+01 9.25E-05 U

Chromium-51 Ci <LLD 2.26E-03 <LLD <LLD 2.26E-03 Manganese-54 Manganese-56 Iron-55 Ci Ci Ci 1.49E-04

<LLD

<LLD 2.76E-03

<LLD

<LLD 1.18E-04

<LLD

<LLD 1.02E-04 1.83E-06

<LLD 3.12E-03 1.09E-06

<LLD I

Iron-59 Cobalt-58 Cobalt-60 Ci Ci Ci

<LLD

<LLD 1.23E-03

<LLD 7.09E-04 1.67E-02

<LLD

<LLD 4.25E-03

<LLD 3.41 E-04 4.71 E-03

<LLD 1.05E-03 2.69E-02 I

Zinc-65 Ci <LLD 9.35E-04 2.45E-04 <LLD 1.18E-03 Zinc-69M Strontium-92 Ci Ci

<LLD

<LLD 2.38E-07

<LLD I

Zirconium-95 Ci <LLD <LLD <LLD <LLD <LLD Niobium-95 Technetium-99M Ci Ci

<LLD

<LLD I

Rhuthenium-105 Ci <LLD <LLD <LLD <LLD <LLD Silver-1 lOm Antimony-124 Antimony-125 Ci Ci Ci

<LLD

<LLD 5.30E-05 1.38E-04 2.09E-04 5.03E-04 3.29E-04

<LLD 2.70E-04

<LLD

<LLD 1.71 E-03 2.09E-04 8.26E-04 I

Iodine-131 Ci <LLD <LLD <LLD <LLD <LLD Xenon-135 Cesium-1 34 Ci Ci

<LLD

<LLD 1.62E-07

<LLD I

Cesium-1 37 Ci <LLD <LLD <LLD 5.92E-05 5.27E-05 Cesium-138 Lanthanum-140 Ci Ci

<LLD

<LLD I Gold-199 Ci <LLD <LLD <LLD <LLD <LLD Total for Period

<LLD - Less than the lower limit of detection 1.08E+01 1.49E+01 6.51 E+O0 3.34E+00 3.52E+01 i

Radioactive Effluent Releases Page 13

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Gaseous Effluents Gaseous effluents are made up of fission and activation gases, iodine and particulate releases. The fission and activation gas releases are primarily a result of containment purge operations, small steam leaks, and offgas system operation. The iodine and particulate releases are primarily a result of small steam leaks. Gaseous effluents from PNPP exit the plant via one of four effluent vents. Each of these four effluent vents contains radiation detectors that continuously monitor the air to ensure that the levels of radioactivity released are below regulatory limits. Samples are also collected and analyzed on a periodic basis to ensure regulatory compliance and dose minimization principals are maintained. The majority of gaseous effluents released from PNPP are considered continuous and at ground level.

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

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

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

A. Fission and Activation Products

1. Total Released, Ci O.OOE+00 1.75E-01 O.OOE+00 1.19E-02 1.OOE+01

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

3. Percent of Applicable Limit, % N/A N/A N/A N/A B. Iodine

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

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

3. Percent of Applicable Limit, % N/A N/A N/A N/A C. Particulates with Half-Lives > 8 days

1. Total Released, Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.OOE+01

2. Average Release Rate, .Ci/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

3. Percent of Applicable Limit, % N/A N/A N/A N/A D. Alpha Activity, Ci 4.31 E-07 1.16E-07 6.43E-08 6.04E-07 1.OOE+01 E. Tritium

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

2. Average Release Rate, 0Ci/sec 4.80E-02 2.76E-01 O.OOE+00 O.OOE+00

3. Percent of Applicable Limit, % N/A N/A N/A N/A F. Carbon-14 4.58 1.84 4.72 3.81 1.00E+01

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

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

Radioactive Effluent Releases Page 14

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I Table 5: Radioactive Gaseous Effluent Nuclide Composition I UNIT QUARTER QUARTER QUARTER QUARTER ANNUAL A. FISSION AND ACTIVATION GASES 12 3 4 TOTAL I

Tritium Ci 3.73E-01 2.17E+00 <LLD <LLD 2.54E+00 Argon-41 Krypton-85m Krypton-85 Ci Ci Ci

<LLD

<LLD I

Kryton-87 Krypton-88 Xenon-131m Ci Ci Ci

<LLD

<LLD 2.21 E-02

<LLD

<LLD 2.21 E-02

<LLD

<LLD I

Xenon-133m Xenon-133 Xenon-135m Ci Ci Ci

<LLD

<LLD 5.44E-03 3.21E-02

<LLD

<LLD 5.44E-03 3.21E-02 I

Xenon-1 35 Xenon-137 Xenon-138 Ci Ci Ci

<LLD

<LLD 4.04E-02

<LLD 7.54E-02

<LLD

<LLD 2.57E-03

<LLD 9.34E-03 4.30E-02

<LLD 8.47E-02 I

Total for Period 3.73E-01 2.35E+00 O.OOE+00 1.19E-02 2.73E+00 B. IODINE Iodine-131 Ci <LLD 1.84E-06 1.87E-05 2.11E-05 4.16E-05 I

Iodine-132 Iodine-133 Iodine-1 34 Ci Ci Ci

<LLD

<LLD 4.31E-06

<LLD

<LLD 2.70E-04

<LLD

<LLD 1.60E-04

<LLD

<LLD 4.34E-04

<LLD I

I Iodine-1 35 Ci <LLD <LLD <LLD <LLD <LLD Total for Period O.OOE+00 6.15E-06 2.88E-04 1.81 E-04 4.76E-04 C. PARTICULATE Chromium-51 Ci <LLD <LLD <LLD <LLD <LLD Manganese-54 Iron-59 Ci Ci

<LLD

<LLD I

Cobalt-58 Ci <LLD <LLD <LLD <LLD <LLD Cobalt-60 Zinc-65 Ci Ci

<LLD

<LLD I

Rubidium-88 Ci <LLD <LLD <LLD <LLD <LLD Rubidium-89 Strontium-89 Ci Ci

<LLD

<LLD I

Strontium-90 Ci <LLD <LLD <LLD <LLD <LLD Yttrium-91m Strontium-92 Ci Ci

<LLD

<LLD I

Zirconium-95 Ci <LLD <LLD <LLD <LLD <LLD Molybdenum-99 Cesium-137 Ci Ci

<LLD

<LLD I Cesium-138 Ci <LLD <LLD <LLD <LLD <LLD Barium-1 39 Ci <LLD <LLD <LLD <LLD <LLD Barium-1 40 Lanthanum-140 Total for Period Ci Ci

<LLD

<LLD I

<LLD - Less than the lower limit of detection I

Radioactive Effluent Releases Page 15

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Solid Waste All solid radioactive waste from PNPP was processed and combined with waste from several other utilities by intermediate vendors (Energy Solutions, Duratek in Oak Ridge, TN and Studsvik, in Erwin, TN). This waste was ultimately sent to Clive, Utah disposal facilities for burial. The solid radioactive waste summary in Table 6 includes all PNPP shipments for 2011.

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

Spent resin, filter sludge, evaporator 7.36E+01 2.15 E+02 1/1/2011- +/-25 bottoms, etc. 12/31/2011 Dry compressible waste, contaminated 1.09E+03 5.88 E+00 1/1/2011- +/- 25 equipment, etc. 12/31/2011 Irradiated components, control rods, etc. 0 0 1/1/2011-12/31/2011 Other (Standby Liquid Control Waste 0 0 1/1/2011-Water) 12/31/2011 1

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

Spent Resin, Filter Sludge, Evaporator Bottoms, Mn-54 5.30 +/- 25 etc. Fe-55 29.50 Co-60 62.02 Zn-65 1.64 Dry Compressible Waste, Contaminated Mn-54 8.01 +/- 25 Equipment, etc. Fe-55 22.80 Co-60 66.51 Zn-65 1.12 Irradiated Components, Control Rods, etc. None 0 Other (Standby Liquid Control Waste Water) None 0 C. DISPOSITION NUMBER OF MODE OF TRANSPORTATION DESTINATION SHIPMENTS Solid Waste(2) 16 Public Highway Studsvik, Erwin, TN Solid Waste(2) 27 Public Highway Energy Solutions, Bear I I Creek, TN Irradiated Fuel Shipments 0 N/A N/A N/A -- Not Applicable

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

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

Radioactive Effluent Releases Page 16

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

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 U

to the plant Control Room.

A detailed report of the monthly and annual operation of the PNPP Meteorological a Monitoring Program is produced under separate cover. For the period of January 1,2011 through December 31, 2011, the report substantiates the quality and quantity of meteorological data collected in accordance with applicable regulatory guidance. I DOSE ASSESSMENT 3 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 I concentration limits. Dose limit compliance is verified through periodic dose assessment calculations. Some dose calculations are conservatively performed for a hypothetical individual who is assumed to reside on the site boundary at the highest potential dose location all year. This person, called the "maximum individual", would incur the maximum I

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 U

this hypothetical individual.

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

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

Radioactive Effluent Releases Page 17

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 7: Maximum Individual Site Boundary Dose, Considering All Sectors TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT % OF (MREM) LIMIT Liquid Effluent Whole body 2.59E-03 3.OE+00 8.6E-02 Liver 3.37E-03 1.OE+01 3.4E-02 Noble - gamma air N/A 4.97E-04 1.OE+01 5.OE-03 Gas - beta air N/A 3.37E-04 2.OE+01 1.7E-03 Noble Gas Whole body 2.75E-04 5.OE+00 5.5E-03 Skin 5.74E-04 1.5E+01 3.8E-03 Particulate & Iodine Thyroid 1.36E-03 1.5E+01 9.1 E-04 The calculated hypothetical, maximum population dose values at the site boundary are provided in Table 8. This table considers all meteorological sectors around PNPP and provides either the whole body or worst-case, organ dose values.

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

Liquid Effluent Whole body 4.2E-01 Thyroid 2.6E-01 Gaseous Effluent Whole body 3.7E-04 Thyroid 6.1 E-04 Table 9 provides the calculated hypothetical maximum site boundary dose values considering only the land-based sectors. Ifany radionuclide was not present at a level greater than the LLD, it was not used in the dose calculations.

Table 9: Maximum Individual Site Boundary Dose, Considering Sectors on Land TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT % OF (MREM) LIMIT Liquid Effluent Whole Body 2.59E-03 3.OE+O0 8.2E-02 Liver 3.37E-03 1.OE+01 3.3E-02 Noble Gas - gamma air N/A 3.49E-05 1.OE+01 3.5E-04

- beta air N/A 2.51 E-05 2.OE+01 1.3E-04 Noble Gas Whole Body 2.68E-06 5.OE+00 5.7E-05 Skin 5.23E-06 1.5E+01 3.7E-05 Particulate & Iodine Thyroid 6.21 E-05 1.5E+01 3.4E-04 Carbon-14 Whole Body 1.60E-01 5.OE+00 3.2E+00 Other dose calculations are performed for a hypothetical individual who is assumed to be inside the site boundary for some specified amount of time. This person would receive the maximum dose during the time spent inside site boundary. Because no one actually meets the criteria established for these conservative calculations, the actual dose received by a real member of the public is significantly less than what is calculated for this hypothetical Radioactive Effluent Releases Page 18

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I individual. This dose is assessed relative to the offsite dose, and considers dilution, dispersion, and occupancy factors.

I The highest hypothetical dose from liquid effluents to a member of the public inside the site boundary is to a person who is fishing on Lake Erie from the shore on PNPP property. The i 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. I Table 10: Maximum Site Dose from Liquid Effluents WHOLE BODY DOSE, ORGAN DOSE I

(MREM) (MREM)

First Quarter Second Quarter 1.1E-04 9.3E-04 1.3E-04 1.1 E-03 I

Third Quarter 2.OE-04 2.3E-04 Fourth Quarter Annual 3.3E-04 1.6E-03 3.8E-04 1.8E-03 I

Although several cases were evaluated to determine the highest hypothetical dose from I gaseous effluents to members of the public inside site boundary, the activity inside the site boundary with the highest dose potential is also shoreline fishing. The cases evaluated included traversing a public road within the site boundary, shoreline fishing (assuming fishing 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year), non-plant related training, car-pooling, and job interviews. The I

maximum on-site gaseous doses generated are shown in Table 11.

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

ORGAN DOSE (MREM)

I First Quarter Second Quarter Third Quarter 1.4E-05 1.2E-04 2.2E-07 1.4E-05 1.6E-04 4.5E-05 I

Fourth Quarter Annual 1.4E-06 1.4E-04 9.4E-06 2.1 E-04 I Radioactive Effluent Releases Page 19

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT An average whole body dose to individual members of the public at or beyond the site boundary is then determined by combining the dose from gaseous and liquid radiological effluents. The dose from gaseous radiological effluents is based upon the population that lives within 50 miles of PNPP. The dose from liquid radiological effluents is determined for the population that receives drinking water from intakes within 50 miles of PNPP. The results of this calculation are provided in Table 12.

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

First Quarter 3.8E-05 1.5E-08 Second Quarter 7.1 E-05 1.4E-07 Third Quarter 2.OE-05 4.6E-1 1 Fourth Quarter 4.2E-05 3.1E-10 Annual 1.8E-04 1.5E-07 Radioactive Effluent Releases Page 20

I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I CARBON- 4 SUPPLEMENTAL INFORMATION I

Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is I

also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. C-14 is released primarily from BWRs through the off-gas system in the form of carbon dioxide (C02). The quantity of I

gaseous C-14 released to the environment can be estimated using a C-14 source term scaling factor based on power generation.

The U.S. Nuclear Regulatory Commission (NRC) is now requiring assessment of gaseous I

C-14 dose impact to a member of the public resulting from routine releases in radiological effluents. Prior to 2011, the industry did not estimate the dose impact of C-14 releases.

Since the dose contribution had been considered negligible compared to the dose impact I

from effluent releases of noble gases, tritium, particulates and radioiodines. At Perry, improvements over the years in effluent management practices and fuel performance have resulted in a decrease in the concentration and changes in the distribution of gaseous I radionuclides released to the environment.

Perry's 2011 Annual Environmental Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2011, and estimates of public dose resulting from the C-14 I

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

values.

I Radioactive Effluent Releases Page 21

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX E ABNORMAL RELEASES

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

The source of this activity has been identified as the Reactor Recirculation System. There is some leakage from the NCC system to Service Water and from there to the environment.

Conservatively, activity calculations are done assuming that all leakage from the NCC system is going to Service Water. Daily NCC samples are being analyzed and system leakage is being tracked. The calculated activity released from NCC has been included in the total radioactivity released. Repair of NCC heat exchangers has reduced the leak rate to environment by about a factor of five. Repairs to isolate the source of reactor water leakage into the NCC system are planned for the PNPP 2013 refueling outage.

QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 A. Fission and Activation Products (Ci)

NA24 3.91 E-04 9.57E-05 2.68E-04 1.74E-04 CR51 5.47E-04 1.39E-04 2.19E-05 6.70E-05 MN54 1.86E-04 2.02E-04 7.59E-05 5.79E-05 MN56 1.20E-05 1.76E-06 1.81 E-05 4.28E-06 FE59 5.92E-06 3.59E-06 1.08E-06 3.23E-06 CO58 7.56E-05 9.61 E-05 4.12E-05 4.60E-05 C060 6.09E-04 1.79E-03 7.56E-04 3.19E-04 ZN65 7.74E-06 1.80E-05 9.15E-06 1.62E-05 ZN69M 4.71 E-07 <LLD <LLD <LLD SR92 <LLD 2.57E-07 3.73E-06 <LLD NB95 <LLD 4.71 E-07 <LLD <LLD Y91 M <LLD <LLD 4.41 E-07 <LLD TC99M <LLD 5.05E-08 1.86E-07 <LLD AG110M <LLD <LLD <LLD <LLD SB124 <LLD <LLD <LLD <LLD SB125 <LLD <LLD <LLD <LLD CS137 8.75E-06 <LLD <LLD 1.55E-08 AU199 2.09E-05 <LLD 5.32E-07 1.60E-06 B. Tritium 3.28E-02 5.49E-03 6.22E-03 4.69E-03 C. Dissolved and Entrained Gases (Ci)

Xe-133 <LLD <LLD 3.66E-06 <LLD Xe-135 6.93E-07 6.1OE-08 1.24E-06 <LLD D. Gross Alpha Activity, (Ci) <LLD <LLD <LLD <LLD

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

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX F ODCM NON-COMPLIANCES Following an upgrade to the Unit 2 Plant Vent Effluent Monitor, the monitor was out of service for greater than 30 days; from 4/15/2012 to 6/01/2012. Delay in returning monitor to service was due to spiking. Troubleshooting identified source of spiking and condition was corrected. No further problems were experienced.

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

ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX G CHANGES TO THE PROCESS CONTROL PROGRAM During this reporting period, there were no changes to the Process Control Program.

L-13-138, Annual Environmental and Effluent Release Report

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