ML13123A209
| 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) | |
Text
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 IV E S U M M A RY.....................................................................................................
1 Radioactive Effluent Releases...................................................................................................
1 Radiological Environm ental M onitoring..............................................................................
2 Land Use Census........................................................................................................
..... 2 C lam /M ussel M onitoring.........................................................................................................
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 M easure..........................................................................................................................
5 Lower Lim it of Detection.........................................................................................................
6 Background radiation..............................................................................................................
6 RA D IO A C TIV E EFFLU ENT R ELEAS ES......................................................................
8 Introduction...................................................................................................................................
8 Regulatory Lim its.........................................................................................................................
8 Release Sum m ary.................................................................................................................
10 M eteorological Data...............................................................................................................
17 Dose Assessm ent......................................................................................................................
17 Carbon-14 Supplem ental Inform ation.................................................................................
21 O n-Site G roundwater M onitoring 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 M anual 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 Im poundm ent...........................................................................................
44 C LA M /M USS EL M O N ITO R IN G....................................................................................
45 Introduction.................................................................................................................................
45 Corbicula Program.................................................................................................................
45 Dreissena Program...............................................................................................................
46 H ER B IC ID E A PPLIC AT IO N S........................................................................................
47 S PEC IA L R EPO RTS......................................................................................................
48 Non-Com pliances......................................................................................................................
48 Un-Reviewed Environm ental Q uestions............................................................................
48 Table of Contents Page i
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDICES Appendix A: 2012 Inter-Laboratory Cross Check Comparison Program Results Appendix B: 2012 REMP Data Summary Reports Appendix C: 2012 REMP Detailed Data Report Appendix D: Corrections to Previous AEERR Appendix E: Abnormal Releases Appendix F: ODCM Non-Compliances Appendix G: Changes to the Process Control Program Table of Contents Page ii I
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Ia I
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT EXECUTIVE
SUMMARY
The Annual Environmental and Effluent Release Report (AEERR) details the results of environmental and effluent monitoring programs conducted at the Perry Nuclear Power Plant (PNPP) from January 01 through December 31, 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 <br />0.263 hours <br />0.00157 weeks <br />3.603335e-4 months <br />. 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 <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br />, 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-r0.26%
Ot her 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 I
to ensure any radioactivity released to the environment is minimal and within regulatory limits. Effluent release programs include the operation of monitoring systems, in-plant sampling and analysis, quality assurance, and detailed procedures covering all aspects of
=
effluent monitoring.
The liquid and gaseous radioactive waste treatment systems at PNPP are designed to collect and process these wastes in order to remove most of the radioactivity. Effluent monitoring systems are used to provide continuous indication of the radioactivity present and are sensitive enough to measure several orders of magnitude lower than the applicable release limits. This monitoring equipment is 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 I
samples of other environmental media are also taken to determine if any radioactive material deposition has occurred. The Radiological Environmental Monitoring Program (REMP) is described in detail 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 QUARTER QUARTER QUARTER 1
2 3
4 Number of batch releases 23 19 39 7
Total time period for batch releases, min 5.17E+03 3.40E+03 8.84E+03 2.16E+03 Maximum time for a batch release, min 2.42E+02 2.31 E+02 2.51 E+02 4.58E+02 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 2.15E+02 2.OOE+00 2.21 E+02 2.07E+02 Average stream flow during periods of effluent 1.21 E+05 2.35E+05 2.16E+05 1.68E+05 release into a flowing stream, L/min U
U U
U Page 10 3
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.
- 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 released during quarter.
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 2a: Summation of Batch Liquid Effluent Releases QUARTER QUARTER QUARTER QUARTER EST.
1 2
3 4
TOTAL
- ERROR,
(%)
A.
Fission and Activation Products Total Released, Ci 1.05E-02 3.28E-03 3.08E-03 9.89E-03 1.OOE+01 (excluding tritium, gases, alpha)
B.
Tritium 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 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 1.86E-03 2.35E-03 1.20E-03 6.89E-04 1.OOE+01 (excluding tritium, gases, alpha)
B.
Tritium Total Released, Ci 3.28E-02 5.49E-03 6.22E-03 4.69E-03 1.OOE+01 C.
Dissolved and Entrained Gases Total Released, Ci 6.93E-07 6.1OE-08 4.90E-06
<LLD 1.OOE+01 D. Gross Alpha Activity, Ci
<LLD
<LLD
<LLD
<LLD 1.OOE+01 E. Waste Volume Released, Liters (prior to 1.51E+06 1.92E+06 2.51 E+06 7.62E+05 NA dilution)
<LLD - Less than the lower limit of detection 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. If a radionuclide was not present at a level "greater than or equal to the LLD" (Ž>LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, the LLDs were either met, or were below the levels required by the ODCM.
Table 3: Radioactive Liquid Effluent Nuclide Composition 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
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 21, 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 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.
Percent of Applicable Limit, %
N/A N/A N/A N/A B. Iodine
- 1. Total Iodine-131 Released, Ci 2.37E-06 5.74E-05
<LLD
<LLD 1.00E+01
- 2.
Average Release Rate, j.Ci/sec 3.02E-07 7.30E-06
<LLD
<LLD
- 3.
Percent of Applicable Limit, %
N/A N/A N/A N/A C. Particulates with Half-Lives > 8 days
- 1. Total Released, Ci 4.78E-08 1.43E-05
<LLD
<LLD 1.OOE+01
- 2.
Average Release Rate, Cici/sec 6.08E-09 1.81 E-06
<LLD
<LLD
- 3.
Percent of Applicable Limit, %
N/A N/A N/A N/A 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
- 2.
Average Release Rate, g.Ci/sec
<LLD
<LLD 1.23E-01 3.31 E-01
- 3. Percent of Applicable Limit, %
N/A N/A N/A N/A F.
Carbon-14, Ci 4.55 4.52 4.78 4.78 1.OOE+01
<LLD - Less than the lower limit of detection N/A -Not Applicable, the ODCM does not have a limit for fission and activation products.
The radionuclide composition of all gaseous radioactive effluents for a continuous-mode, ground-level release is given in Table 5. If a radionuclide was not present at a level "greater than or equal to the LLD" (_>LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, LLDs were met or were below the levels required by the ODCM.
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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
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 2012.
Table 6: Solid Waste Shipped Offsite for Burial or Disposal A.
TYPE OF SOLID WASTE SHIPPED VOLUME ACTIVITY EST. TOTAL (M 3)
(CI)
ERROR (%)
Resins, Filters and Evaporator Bottoms 1.1 7E+02 2.78E+02
+/- 25 Dry Active Waste 1.86E+03 4.45E-01
+/- 25 Irradiated components, control rods, etc.
0.OOE+00 0.OOE+00
+/- 25 Other Waste 0.OOE+00 0.OOE+00
+/- 25 B.
ESTIMATE OF MAJOR"1 ) NUCLIDE COMPOSITION (BY RADIONUCLIDE ABUNDANCE EST. TOTAL TYPE OF WASTE)
(%)
ERROR, (%)
Resins, Filters and Evaporator Bottoms Fe-55 31.49
+/- 25 Co-60 62.42 Ni-63 2.12 Cs-1 37 2.32 Dry Active Waste H-3 1.60
+/- 25 Mn-54 6.52 Fe-55 26.64 Co-60 62.89 Ni-63 1.02 Irradiated Components, Control Rods, etc.
None 0
Other Waste None 0
C.
DISPOSITION NUMBER OF MODE OF TRANSPORTATION DESTINATION SHIPMENTS Solid Waste(2) 26 Public Highway Studsvik, Erwin, TN Solid Waste(2) 41 Public Highway Energy Solutions, Bear Creek, TN N/A -- Not Applicable
( 1 ) -- "Major" is defined as any individual radionuclide identified as > 1% of the waste type abundance.
( 2 ) -- This waste was combined with waste from other utilities and disposed of at Clive, Utah.
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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. If any radionuclide was not present at a level greater than the LLD, it was not used in the dose calculations.
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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 2.67E-03 3.OE+00 8.9E-02 Liver 3.77E-03 1.OE+01 3.8E-02 Noble
- gamma air N/A 9.87E-02 1.OE+01 9.9E-01 Gas
- beta air N/A 1.77E-01 2.OE+01 8.9E-01 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 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.
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Liquid Effluent Whole body 3.5E-01 Thyroid 1.9E-01 Gaseous Effluent Whole body 1.5E-03 Thyroid 1.5E-03 Table 9 provides the calculated hypothetical maximum site boundary dose values I
considering only the land-based sectors. If any radionuclide was not present at a level greater than the LLD, it was not used in the dose calculations.
Table 9: Maximum Individual Site Boundary Dose, Considering Sectors on Land TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT
% OF (MREM)
LIMIT Liquid Effluent Whole Body 2.67E-03 3.OE+00 8.9E-02 Liver 3.77E-03 1.OE+01 3.8E-02 Noble Gas - gamma air N/A 1.55E-03 1.OE+01 1.6E-02
- beta air N/A 2.69E-03 2.0E+01 1.3E-02 Noble Gas Whole Body 5.04E-04 5.OE+00 1.OE-02 Skin 1.23E-03 1.5E+01 8.2E-03 Particulate & Iodine Thyroid 1.94E-04 1.5E+01 1.3E-03 Carbon-14*
Whole Body 2.54E-01 5.OE+00 5.1 E+00
- C-14 Dose calculated at nearest garden.
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 Page 18 U
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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 <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> 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 <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> 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
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 7.1E-05 7.5E-10 Second Quarter 2.3E-05 4.6E-07 Third Quarter 2.6E-05 8.3E-08 Fourth Quarter 2.6E-05 9.6E-08 Annual 1.5E-04 6.3E-07 I
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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.
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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 I
Management (ERM) of Boston, Massachusetts to perform site hydrogeology evaluations, and to facilitate installation of additional groundwater monitoring wells, based on their findings. FirstEnergy fleet chemistry formalized the program with the issuance of fleet procedure NOP-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 I
facilitate continued safe operation, or safe shutdown, as conditions warrant.
It was surmised that these "rattle spaces" also allow the drainage from some plant systems to reach the outside. Since this discovery, the plant has developed a more rigorous stance towards plant observations, and has minimized process water intrusion into the rattle spaces.
It should be noted that no leakage was identified from either the radwaste system, or from the Fuel Handling Building.
Underdrain System 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 I
gravity-drain and cascade forward should the pumps fail. There are two major branches of underdrains, one for each of the east and west sides of the power block. These branches ultimately flow into 2 underdrain manholes, designated MH-20 and MH-23, before draining I
to the suction bay of the Emergency Service Water (ESW) pump house. From there, the water is discharged from the plant. Refer to Figure 2 for locations of Manholes 1 through
- 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.
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 2: Underdrain System and On-Site Groundwater Wells Manholes 0
Piezometers*
Groundwater Wells
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nnig*-
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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
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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.
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I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 14: REMP Sampling Locations (1)
LOCATION #
DESCRIPTION MILES DIRECTION MEDIA( 2) 1 Chapel Road 3.4 ENE TLD, AlP 2
Kanda Garden 1.9 ENE Food Products 3
Meteorological Tower 1.0 SE TLD, AlP 4
Site Boundary 0.7 S
TLD, AlP 5
Quincy Substation 0.6 SW TLD, AlP 6
Concord Service Center 11.0 SSW TLD, AlP 7
Site Boundary 0.6 NE TLD, AlP 8
Site Boundary 0.8 E
TLD 9
Site Boundary 0.7 ESE TLD 10 Site Boundary 0.8 SSE TLD 11 Parmly Rd.
0.6 SSW TLD 12 Site Boundary 0.6 WSW TLD 13 Madison-on-the-Lake 4.7 ENE TLD 14 Hubbard Rd.
4.9 E
TLD 15 Eagle St. Substation 5.1 ESE TLD 16 Eubank Garden 0.9 S
Food Products 18 Kijauskas Farm (goat) 2.5 E
Food Products, Milk 19 Goodfield Dairy 8.7 S
Milk 20 Rainbow Farms 1.9 E
Food Products 21 Hardy Rd.
5.1 WSW TLD 23 High St. Substation 7.9 WSW TLD 24 St. Clair Ave.
15.1 SW TLD 25 Offshore - PNPP discharge 0.6 NNW Sediment, Fish 26 Offshore - Redbird 4.2 ENE Sediment 27 Offshore - Fairport Harbor 7.9 WSW Sediment 28 CEI Ashtabula Plant Intake 22.0 ENE Water 29 River Rd.
4.8 SSW TLD 31 Wood and River Rd.
4.8 SE TLD 32 Offshore - Mentor 15.8 WSW Sediment, Fish 33 River Rd.
4.5 S
TLD 34 PNPP Intake 0.7 NW Water 35 Site Boundary 0.6 E
TLD, AlP 36 Lake County Water Plant 3.9 WSW TLD, Water 37 Gerlica Farm 1.5 ENE Food Products 41 Tuttle Farm (goat) 5.8 SSE Milk 51 Rettger Milk Farm (cow) 9.6 S
Milk 53 Neff Perkins 0.5 WSW TLD 54 Hale Rd. School 4.6 SW TLD 55 Center Rd.
2.5 S
TLD 56 Madison High School 4.0 ESE TLD 58 Antioch Rd.
0.8 ENE TLD 59 Lake Shoreline at Green Rd.
4.0 ENE Water 60 Lake Shoreline at Perry Park 1.0 WSW Water 64 Northwest Drain Mouth 0.09 NW Sediment 65 Major Stream Mouth 0.18 W
Sediment 70 H&H Farm Stand 16.2 SSW Food Products (1) Missing location numbers denote deleted or retired sampling locations.
(2)
A/P =
Air, Iodine and Particulate TLD =
Thermoluminescent Dosimeter I
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 3: REMP Sampling Locations Within Two Miles of Plant Site U
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 4: REMP Sampling Locations Between Two and Eight Miles of the Plant Site SW SSW S
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 5: REMP Sampling Locations Greater Than Eight Miles from the Plant Site 5
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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 I
continuous energy spectrum rather than the discrete energy levels, or "peaks", associated with gamma radiation, identification of specific beta-emitting nuclides is more difficult.
Therefore, gross beta activity only indicates whether the sample contains normal or abnormal amounts of beta-emitting radioactivity; it does not specifically identify the radionuclides 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 I
chemical separation before being analyzed by gamma spectral analysis.
Tritium activity analysis measures the amount of the radionuclide tritium (H-3) present in a sample. Tritium is an isotope of hydrogen that emits low-energy beta particles. Tritium occurs naturally and is also man-made.
Gamma doses received by Thermoluminescent Dosimeters (TLD) while in the field are determined by a special laboratory procedure. Thermoluminescence is a process by which 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 I
analyses. The vendor laboratory for REMP sample analyses complied with those values in 2012.
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 15: REMP Sample Analyses TYPE SAMPLE FREQUENCY ANALYSIS Atmospheric Monitoring Airborne Weekly &
Gross Beta Activity &
Particulates Quarterly Gamma Spectral Analysis Airborne Radioiodine Weekly Iodine-131 Terrestrial Monitoring Milk Bi-Monthly Gamma Spectral Analysis &
Iodine-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 I
was no impact to the program requirements as a result of any missed samples. Table 16 provides information on samples missed during 2012.
Table 16: Missed REMP Samples in 2012 MEDIA LOCATION DATE REASON Food Products All Jan.- May, Nov. - Dec.
Insufficient growth/temperature. Die-off/Frost damage.
Lake Water 59, 60 Jan.
Sample unavailable due to frozen shoreline Milk 18 Jan - Mar, Nov. - Dec Drying period for goats/sample availability 41 Jan - Mar, Oct. - Dec.
Drying period for goats/sample availability Atmospheric Monitoring Air Air sampling is conducted to detect any increase in the concentration of airborne radionuclides. The PNPP REMP maintains an additional 2 air sampling locations above the five locations (four indicators and one control) required by the ODCM. Six (6) of these locations are within four miles of the plant site; the seventh is used as a control location and is eleven miles from PNPP. Air sampling pumps are used to draw continuous samples at a rate of approximately two cubic feet per minute. The air is drawn through glass fiber filters (to collect particulate material) and a charcoal cartridge (to adsorb iodine). The samples are collected on a weekly basis, 52 weeks a year, from each of the seven air sampling stations.
Air samples are analyzed weekly for gross beta activity and radioiodine activity. The air samples are also analyzed by gamma spectral analysis quarterly. A total of 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 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 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 quarterly spectral analysis above the LLD values.
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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.
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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 i
indicator and control locations.
Figure 7: Annual Average Gross Beta Activity, in Wateri 4.5 I
4 3.5 2.5 2I S1.5 0.5 I
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(D J
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[Ind cato r
EControl There were no tritium or radionuclides detected by gamma spectral analysis.
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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
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- 0) 0 C'J 0W M) 0 0
0 00 0
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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 I
the laboratory for analysis. In 2012, fish sampling was performed for PNPP by a local 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 I
equipped with three TLDs, two of which are changed quarterly and one is changed annually.
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 I
provided in the 1988 Annual Environmental Operating Report.
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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
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)
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tO 10(0 O0)0 WI 0M) 0M
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- 0) 0 0
0 0
0 0
0 0
0 0
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0 Year In ndicator mControl Conclusion Operation of the Perry Nuclear Power Plant is having no detectable radiological effect on the surrounding environment.
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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 I
established acceptance criteria indicate a need to check instruments or procedures.
Regulatory Guide 4.15 specifically required that contractor laboratories that performed environmental measurement participate in the EPA's Environmental Radioactivity Laboratory Inter-Comparison Studies Program, or an equivalent program.
The EPA's program is no longer funded or offered. The reason that the EPA program was referenced in the regulatory guide is that the EPA standards were traceable to National I
Bureau of Standards (now known as National Institute Standard Technology). In response to this problem, Teledyne (PNPP vendor lab) incorporated a program offered by Environmental Resource Associates (ERA Company), which covered the same analyses in the same matrix at the same frequency as the EPA program. The ERA Company has received NIST accreditation for its program, as an equivalent program. In addition to comparison cross checks performed with the ERA Company, the vendor laboratory routinely monitors the 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.
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT LAND USE CENSUS Introduction Each year a Land Use Census, which is required by Section 5.2 of the PNPP ODCM, is conducted to identify the locations of the nearest milk animal, garden (of greater than 500 square feet), and residence in each of the meteorological sectors that is over land.
Information gathered during the Land Use Census is used for off-site dose assessment and to update sampling locations for the Radiological Environmental Monitoring Program (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 1st 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.
Table 18: Nearest Milk Animal, By Sector SECTOR LOCATION ADDRESS MILES FROM MAP LOCATOR PNPP NUMBER E
2591 McMackin Rd.
2.5 21 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 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.
Table 19: Nearest Garden, By Sector SECTOR LOCATION ADDRESS MILES FROM MAP LOCATOR PNPP NUMBER NE 2340 Hemlock 0.9 11 ENE 4630 Lockwood 1.1 12 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 I
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 10: Land Use Census Map Garden l
Residence M
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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 Co-60 Cs-1 37 Co-60 Cs-1 37 64
<LLD
<LLD
<LLD
<LLD 64-1
<LLD 29.0
<LLD
<LLD 64-2
<LLD 345
<LLD 604 64-3
<LLD 140 57 85 64-6 85.9 1002 131 1505 64-7 72.1 1154 112 1573 64-8 50.8 613
<LLD 723 64-9 185 1177 190 1247 64-10 152 1188 145 1322 64-11 27.8 481 40 417 U
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CLAM/MUSSEL MONITORING INTRODUCTION Sampling for macro-invertebrates (clams and mussels) has been conducted in Lake Erie in the vicinity of PNPP, since 1971. The clam/mussel program currently focuses on two species: Corbicula fluminea (Asiatic clam) and Dreissena polymorpha (zebra mussel).
CORBICULA PROGRAM Monitoring specifically for Corbicula was initiated in response to a NRC bulletin and concerns of the Atomic Safety and Licensing Board. The 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 1 N34B0001 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-I stream monitors. Commercial divers monitor mussel infestation during the inspection of forebays, basins, and the intake and discharge structures. Divers have also been used to take underwater videotapes of the water basins and intake tunnel. Side-stream monitors are flow-through containers that receive water diverted from plant systems and are set up at two in-plant locations during the mussel season.
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-I dimethyl-benzyl-ammonium chloride. Treatment was applied once in 2012, on October 16 th.
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 I
water and subjected to the chemical treatment. The observed mortality rate utilizing the flow-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 <br />0.263 hours <br />0.00157 weeks <br />3.603335e-4 months <br />.
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 I
service water dechlorination feed line. This chemical was reviewed under environmental 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 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium Iodine-1 31, Iodine-1 2 9b Uranium-238, Nickel-63b Technetium-99b Iron-55b
> 0.1 g/liter or kg
< 20 pCi/liter
> 20 pCi/liter
< 100 pCi/liter
> 100 pCi/liter
< 4,000 pCi/liter
> 4,000 pCi/liter
> 0.1 pCi/liter
> 0.1 pCi/liter, gram, or sample
< 55 pCi/liter
> 55 pCi/liter
< 35 pCi/liter
> 35 pCi/liter 50 to 100 pCi/liter
> 100 pCi/liter 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value
+/-1o =
169.85 x (known)0 0 933 10% of known value 15% of known value 10% of known value 6 pCi/liter 10% of known value 6 pCi/liter 15% of known value 10 pCi/liter 10% of known value 20% of known value Other Analyses b a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1783 04/09/12 Sr-89 ERW-1783 04/09/12 Sr-90 ERW-1786 ERW-1786 ERW-1786 ERW-1786 ERW-1786 ERW-1789 ERW-1789 d ERW-1795 ERW-1795 ERW-1795 04/09/12 04/09/12 04/09/12 04/09/12 04/09/12 Ba-1 33 Co-60 Cs-134 Cs-137 Zn-65 62.2 +/- 6.0 33.7 +/- 2.1 75.7 +/- 4.1 71.9 +/- 4.0 70.0 +/- 4.3 151.5 +/- 6.1 108.3 +/- 89.0 58.5 37.4 82.3 72.9 74.2 155.0 105.0 62.9 44.2 5.7 4.6 61.5 46.9 - 66.3 27.4 -43.1 69.1 -90.5 65.6 - 82.6 60.6 - 81.6 140.0 - 172.0 94.5 - 125.0 33.0 - 78.0 29.6 - 51.5 4.3 - 6.9 2.7 - 6.3 50.0 - 68.2 04/09/12 Gr. Alpha 55.0 +/- 2.4 04/09/12 Gr. Beta 76.2 +/- 1.8 04/09/12 04/09/12 04/09/12 Ra-226 Ra-228 Uranium ERW-1798 04/09/12 H-3 ERW-6283 10/05/12 Sr-89 ERW-6283 10/05/12 Sr-90 ERW-6286 ERW-6286 ERW-6286 ERW-6286 ERW-6286 10/05/12 10/05/12 10/05/12 10/05/12 10/05/12 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 6.4 +/- 0.4 5.4 +/- 1.2 56.2 +/- 2.6 16023 +/-355 41.5 +/- 4.1 19.7 +/- 1.6 82.7 +/- 4.4 77.2 +/- 3.7 74.4 +/- 1.5 183.0 +/-6.2 211.0 +/- 9.9 47.0 +/- 2.3 33.4 +/- 1.2 23.3 +/- 1.0 17.5 +/- 0.7 7.4 +/- 1.5 61.2 +/- 1.8 39.1 20.1 84.8 78.3 76.6 183.0 204.0 58.6 39.2 24.8 15.0 4.6 62.5 15800 13800 -17400 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Fail Pass 29.7 -46.1 14.4 -23.8 71.3 -93.3 70.5 -88.5 62.6 -84.3 165.0 -203.0 184.0 -240.0 30.6 -72.9 26.0 -46.7 20.6 -29.4 11.2 -17.2 2.7 - 6.2 50.8 - 69.3 ERW-6288 10/05/12 Gr. Alpha ERW-6288 10/05/12 Gr. Beta ERW-6290 10/05/12 1-131 ERW-6295e ERW-6295e ERW-6295 10/05/12 10/05/12 10/05/12 Ra-226 Ra-228 Uranium 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
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).
mR Lab Code Date Known Lab Result Control Description Value
+/- 2 sigma Limits Acceptance Environmental, Inc.
2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 30 cm.
40 cm.
50 cm.
70 cm.
75 cm.
80 cm.
90 cm.
100 cm.
110 cm.
120 cm.
150 cm.
180 cm.
74.87 42.12 26.95 13.75 11.98 10.53 8.32 6.74 5.57 4.68 2.99 2.08 87.22 +/- 2.86 53.70 +/- 4.53 33.04 +/- 1.96 13.26 +/- 1.15 13.38 +/- 1.68 11.27 +/- 0.95 7.79 +/- 0.83 5.91 +/- 0.25 4.63 +/- 0.83 3.96 +/- 1.68 2.41 +/- 0.08 2.02 +/- 0.25 52.41 - 97.33 29.48 - 54.76 18.87 - 35.04 9.63 - 17.88 8.39 - 15.57 7.37 - 13.69 5.82 - 10.82 4.72 - 8.76 3.90 - 7.24 3.28 - 6.08 2.09 - 3.89 1.46 -2.70 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass I
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2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 9/11/2012 40 cm.
9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 50 cm.
60 cm.
70 cm.
80 cm.
90 cm.
100 cm.
110 cm.
120 cm.
150 cm.
180 cm.
33.75 21.6 15 11.02 8.44 6.67 5.4 4.46 3.75 2.4 1.67 43.74 +/- 1.31 25.37 +/- 0.82 16.63 +/- 0.45 10.58 +/- 0.20 8.55 +/- 1.18 5.75 +/- 0.33 4.44 +/- 0.22 3.85 +/- 0.05 3.03 +/- 0.71 1.82 +/- 0.10 1.19 +/- 0.34 23.63 - 43.88 15.12 - 28.08 10.50 - 19.50 7.71 - 14.33 5.91 - 10.97 4.67 - 8.67 3.78 - 7.02 3.12 -5.80 2.63 - 4.88 1.68 -3.12 1.17 -2.17 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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 W-22712 W-22712 SPAP-1032 SPAP-1032 SPAP-1034 SPW-1 036 SPW-1036 SPW-1036 SPMI-1038 SPM1-1038 SPW-1 045 SPW-1 047 SPW-1049 W-31412 SPW-1 520 SPW-41825 WW-1547 WW-1547 WW-1547 W-51712 W-61112 W-61112 SPAP-4418 SPAP-4420 SPAP-4420 SPMI-4422 SPMI-4422 SPMI-4422 SPMI-4422 SPW-4424 SPW-4424 SPW-4424 SPF-4426 SPF-4426 SPW-4428 SPW-4430 SPW-4432 W-81712 SPW-5407 SPW-18022 2/15/2012 2/27/2012 2/27/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/512012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/14/2012 3/23/2012 4/10/2012 4/16/2012 4/16/2012 4/16/2012 5/17/2012 6/11/2012 6/11/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7125/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 8/17/2012 8/29/2012 9/10/2012 Ra-228 Gr. Alpha Gr. Alpha Cs-134 Cs-137 Gr. Beta Cs-134 Cs-137 Sr-90 Cs-134 Cs-137 H-3 Ni-63 C-14 Ra-226 U-238 Ra-228 Ba-133 Cs-134 Cs-137 Ra-226 Gr. Alpha Gr. Beta Gr. Beta Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Sr-90 Co-60 Cs-137 Sr-90 Cs-134 Cs-137 C-14 H-3 Ni-63 Ra-226 U-238 Ra-228 24.85 +/- 2.14 14.59 +/- 0.34 43.57 +/- 0.40 7.06 +/- 1.71 102.63 +/- 3.13 44.30 +/- 0.11 43.23 +/- 3.84 57.44 +/- 4.60 60.51 +/- 1.93 37.79 +/- 4.06 54.75 +/- 5.09 68022 +/- 746 217.10 +/- 3.64 3858.90 +/- 12.79 13.13 +/- 0.36 45.67 +/- 2.02 28.48 +/- 2.51 18.99 +/- 4.67 9.28 +/- 2.82 27.77 +/- 4.49 17.29 +/- 0.43 22.16 +/- 0.45 43.57 +/- 0.40 43.74 +/- 0.11 4.54 +/- 0.73 104.70 +/- 2.77 31.43 +/- 2.12 16.50 +/- 1.17 29.60 +/- 2.61 31.60 +/- 1.35 38.52 +/- 1.76 33.23 +/- 2.27 36.56 +/- 1.58 947.50 +/- 42.50 2692.00 +/- 62.40 4325.70 +/- 15.80 70119.40 +/- 773.40 187.20 +/- 3.85 14.94 +/- 0.40 42.95 +/- 0.11 29.03 +/- 2.80 28.75 20.00 41.70 5.26 104.24 46.88 39.42 52.12 61.52 39.42 52.12 69048 206.64 4738.80 16.70 41.70 28.35 26.70 8.68 29.70 16.70 20.00 45.20 46.50 4.60 103.30 31.62 16.15 26.64 30.47 37.95 32.01 40.60 1025.00 2480.00 4738.80 67570.00 206.80 16.70 41.70 28.21 20.13 -37.38 10.00 - 30.00 20.85 - 62.55 0.00 - 15.26 93.82 - 114.66 28.13 -65.63 29.42 - 49.42 42.12 -62.12 49.22 - 73.82 29.42 - 49.42 42.12 -62.12 55238 - 82858 144.65 - 268.63 2843.28 - 6634.32 11.69 - 21.71 29.19 -54.21 19.85 -36.86 16.70 -36.70 0.00 - 18.68 19.70 -39.70 11.69 - 21.71 10.00 - 30.00 35.20 - 55.20 27.90 - 65.10 2.76 - 6.44 92.97 -113.63 21.62 -41.62 6.15 -26.15 16.64 - 36.64 24.38 - 36.56 27.95 - 47.95 22.01 -42.01 32.48 - 48.72 922.50 -1127.50 2232.00 - 2728.00 2843.28 - 6634.32 54056.00 - 81084.00 144.76 - 268.84 11.69 - 21.71 29.19 - 54.21 19.75 -36.67 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A3-1
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 W-91012 W-91012 W-100312 W-100312 W-101812 ESO-7235 SPW-7753 SPW-18023 9/10/2012 Gr. Alpha 9/10/2012 Gr. Beta 10/3/2012 10/3/2012 10/18/2012 12/6/2012 12/6/2012 12/18/2012 Gr. Alpha Gr. Beta Ra-226 Sr-90 U-238 Ra-228 19.95 +/- 0.42 43.47 +/- 0.40 19.95 +/- 0.41 44.21 +/- 0.40 18.80 +/- 0.43 138.79 +/- 2.67 45.55 +/- 5.05 31.59 +/- 2.99 20.00 45.20 20.00 45.20 16.70 161.05 41.70 25.98 10.00 - 30.00 35.20 - 55.20 10.00 - 30.00 35.20 - 55.20 11.69 - 21.71 128.84 - 193.26 29.19 -54.21 18.19 - 33.77 Pass Pass Pass Pass Pass Pass Pass Pass I
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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.
NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.
A3-2
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66cv)
Acceptance Type LLD Activityc Criteria (4.66 cy)
SPW-41814 W-22712 W-22712 SPAP-1031 SPAP-1031 SPAP-1033 SPW-1035 SPW-1035 SPW-1035 SPW-1035 SPM1-1037 SPM1-1037 SPM I-1037 SPW-1044 SPW-1046 SPW-1048 SPW-1 166 W-31412 SPW-1521 W-51712 W-61112 W-61112 SPW-41815 SPAP-4417 SPMI-4421 SPMI-4421 SPMI-4421 SPMI-4421 SPW-4423 SPW-4423 SPW-4423 SPW-4423 SPF-4425 SPF-4425 SPF-4425 SPW-4427 SPW-4431 W-81712 SPW-5408 Water Water Water Air Filter Air Filter Air Filter Water Water Water Water Milk Milk Milk Water Water Water water Water Water Water Water Water Water Air Filter Milk Milk Milk Milk Water Water Water water Fish Fish Fish Water Water Water Water 2/15/2012 2/27/2012 2/27/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 315/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/9/2012 3/14/2012 3/23/2012 4/24/2012 6/11/2012 6/11/2012 7/7/2011 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 8/17/2012 8/29/2012 Ra-228 Gr. Alpha Gr. Beta Cs-134 Cs-137 Gr. Beta Cs-134 Cs-137 1-131(G)
H-3 Ni-63 C-14 C-14 Ra-226 U-238 Ra-226 Gr. Alpha Gr. Beta Ra-228 Gr. Beta Co-60 Cs-1 34 Cs-137 Sr-90 Co-60 Cs-134 Cs-137 Sr-90 Co-60 Cs-134 Cs-137 C-14 Ni-63 Ra-226 U-238 0.65 0.42 0.74 1.89 1.16 0.003 2.40 2.88 2.35 0.60 2.85 3.73 3.24 146.10 19.07 5.70 6.79 0.034 0.10 0.04 0.47 0.71 0.77 0.001 4.29 3.58 4.60 0.45 1.88 2.38 2.80 0.45 6.74 7.47 9.62 10.93 19.00 0.038 0.039 0.49 +/- 0.36
-0.04 +/- 0.29
-0.54 +/- 0.50 0.013 +/- 0.003
-0.11 +/- 0.26 37.10 +/- 74.40 8.30 +/- 11.79 2.99 +/- 3.04 1.11 0.043 +/- 0.027 0.09 +/- 0.11 0.04 +/- 0.03
-0.14 +/- 0.32 0.29 +/- 0.51 0.52 +/- 0.42 0.021 +/- 0.003 0.53 +/- 0.27 0.08 +/- 0.22 3.54 +/- 5.84 5.50 +/- 11.70 0.035 +/- 0.030 0.015 +/- 0.057 2
1 3.2 100 100 0.01 10 10 20 1
10 10 20 200 20 200 200 1
1 1
1 3.2 2
0.01 10 10 10 1
10 10 10 1
100 100 100 200 20 1
1 A4-1
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis" Laboratory results (4.66o)
Acceptance Type LLD Activityc Criteria (4.66 a)
SPW-1 8032 W-91012 W-91012 W-100312 W-100312 W-101812 SPW-7754 SPW-1 8033 Water Water Water Water Water Water Water Water 9/10/2012 9/10/2012 9/10/2012 10/3/2012 10/3/2012 10/18/2012 12/6/2012 12/18/2012 Ra-228 Gr. Alpha Gr. Beta Gr. Beta Gr. Beta Ra-226 U-238 Ra-228 0.78 0.42 0.75 0.77 0.43 0.04 0.10 0.98 0.85 +/- 0.46 0.027 +/- 0.29
-0.13 +/- 0.52
-0.32 +/- 0.53 0.06 +/- 0.30 0.038 +/- 0.031 0.022 +/- 0.075 0.43 +/- 0.50 2
1 3.2 3.2 3.2 2
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I 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.
A4-2
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 CF-20, 21 CF-20, 21 P-9133, 9134 U-302, 303 S-386, 387 S-386, 387 S-386, 387 S-386, 387 S-386, 387 WW-619, 620 MI-702, 703 WW-892, 893 S-850, 851 S-850, 851 W-1251, 1252 W-1251, 1252 W-1251, 1252 W-1251, 1252 AP-1209, 1210 XWW-1564, 1565 SG-1438, 1439 SG-1438, 1439 WW-1 585, 1586 AP-2103, 2104 AP-2166, 2167 AP-1632, 1633 E-1653, 1654 E-1653, 1654 SG-1677, 1678 SG-1677, 1678 SWU-1719, 1720 W-1698, 1699 W-1698, 1699 W-1698, 1699 SG-1761, 1762 SG-1761, 1762 AP-2019, 2020 DW-2272, 2273 DW-2356, 2357 1/3/2012 1/3/2012 1/3/2012 1/3/2012 1/17/2012 1/23/2012 1/23/2012 1/23/2012 1/23/2012 1/23/2012 1/31/2012 2/6/2012 2/17/2012 2/22/2012 2/22/2012 3/6/2012 3/6/2012 3/6/2012 3/6/2012 3/8/2012 3/14/2012 3/19/2012 3/19/2012 3/19/2012 3/28/2012 3/28/2012 3/29/2012 4/2/2012 4/2/2012 4/2/2012 4/2/2012 4/3/2012 4/5/2012 4/5/2012 4/5/2012 4/10/2012 4/10/2012 4/12/2012 4/20/2012 4/24/2012 Gr. Beta K-40 Sr-90 H-3 Beta (-K40)
Ac-228 Bi-214 Pb-214 TI-208 U-235 H-3 K-40 Gr. Beta Cs-134 Cs-137 Gr. Alpha Gr. Beta H-3 Tc-99 Be-7 H-3 Ac-228 Pb-214 H-3 Be-7 Be-7 Be-7 14.50 +/- 0.29 12.88 +/- 0.55 0.01 +/- 0.01 108.86 +/- 83.03 6.84 +/- 2.91 0.77 +/- 0.11 0.80 +/- 0.07 0.74 +/- 0.06 0.21 +/- 0.02 0.05 +/- 0.02 257.20 +/- 86.00 1337.00 +/- 123.00 3.46 +/- 0.56 0.14 +/- 0.02 0.21 +/- 0.03 1.20 +/- 0.62 16.86 +/- 1.43 5235.52 +/- 230.91 19.67 +/- 3.60 0.24 +/- 0.12 308.00 +/- 88.00 6.01 +/- 0.30 4.69 +/- 0.49 3124.50 +/- 176.96 0.080 +/- 0.016 0.061 +/- 0.020 0.26 +/- 0.12 15.02 +/- 0.30 12.40 +/- 0.53 0.01 +/- 0.01 206.60 +/- 86.38 5.24 +/- 2.56 0.79 +/- 0.14 0.73 +/- 0.11 0.75 +/- 0.11 0.21 +/- 0.04 0.12 +/- 0.05 305.80 +/- 88.30 1460.40 +/- 102.00 3.77 +/- 0.59 0.13 +/- 0.02 0.22 +/- 0.03 1.27 +/- 0.92 15.14 +/- 1.34 4893.24 +/- 224.55 14.46 +/- 3.51 0.20 +/-0.11 293.00 +/- 87.00 6.23 +/- 0.31 5.20 +/- 0.54 2982.38 +/- 173.62 0.076 +/- 0.013 0.071 +/- 0.016 0.24 +/- 0.12 14.76 +/- 0.21 12.64 +/- 0.38 0.01 +/- 0.00 157.73 +/- 59.91 6.04 +/- 1.94 0.78 +/- 0.09 0.77 +/- 0.07 0.75 +/- 0.06 0.21 +/- 0.02 0.09 +/- 0.03 281.50 +/- 61.63 1398.70 +/- 79.90 3.61 +/- 0.41 0.14 +/- 0.01 0.22 +/- 0.02 1.24 +/- 0.55 16.00 +/- 0.98 5064.38 +/- 161.05 17.07 +/- 2.51 0.22 +/- 0.08 300.50 +/- 61.87 6.12 +/- 0.22 4.95 +/- 0.36 3053.44 +/- 123.96 0.078 +/- 0.010 0.066 +/- 0.013 0.25 +/- 0.08 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Gr. Beta K-40 Ac-228 Pb-214 Gr. Beta Gr. Beta Ra-226 Ra-228 Ac-228 Pb-214 Be-7 1-131 Gr. Beta 1.53 +/- 0.05 1.34 +/- 0.13 6.63 +/- 0.37 4.77 +/- 0.16 1.16 +/- 0.41 10.86 +/- 1.49 0.41 +/- 0.15 1.46 +/- 0.76 16.26 +/- 0.53 14.16 +/- 1.44 0.17 +/- 0.10 0.52 +/- 0.24 12.82 +/- 2.01 1.55 +/- 0.04 1.36 +/- 0.14 6.49 +/- 0.33 5.07 +/- 0.14 1.53 +/- 0.44 9.42 +/- 1.32 0.67 +/- 0.18 1.48 +/- 0.74 16.55 +/- 0.44 15.40 +/- 1.56 0.17 +/- 0.08 0.49 +/- 0.27 9.47 +/- 1.74 1.54 1.35 6.56 4.92 1.35 10.14 0.54 1.47 16.41 14.78 0.17 0.51 11.14
+/- 0.03
+/- 0.10
+/- 0.25
+/- 0.11
+/- 0.30
+/- 1.00
+/- 0.12
+/- 0.53
+/- 0.34
+/- 1.06
+/- 0.07
+/- 0.18
+/- 1.33 A5-1
I TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-2403, 2404 G-2403, 2404 BS-2445, 2446 BS-2445, 2446 SWU-2550, 2551 WW-2614, 2615 WW-2614, 2615 BS-2656, 2657 BS-2656, 2657 SO-2635, 2636 SO-2635, 2636 MI-2677, 2678 VE-2719, 2720 SWU-3221, 3222 SWU-3221, 3222 WW-3073, 3074 AP-2968, 2969 F-3031, 3032 F-3031, 3032 G-3094, 3095 F-3412, 3413 F-3412, 3413 MI-3067, 3068 SO-3305, 3306 SO-3305, 3306 SO-3305, 3306 LW-3454, 3455 BS-3697, 3698 BS-3697, 3698 BS-3697, 3698 VE-3798, 3799 WW-4790, 4791 DW-30103, 30104 DW-30103, 30104 LW-3970, 3971 DW-3949, 3950 SG-4075, 4076 SG-4075, 4076 SG-4075, 4076 AP-4390, 4391 AP-4390, 4391 AP-4012, 4013 SW-4033, 4034 5/1/2012 5/1/2012 5/11/2012 5/11/2012 5/1/2012 5/1/2012 5/1/2012 5/2/2012 5/2/2012 5/3/2012 5/3/2012 5/7/2012 5/7/2012 5/8/2012 5/8/2012 5/14/2012 5/17/2012 5/22/2012 5/22/2012 5/23/2012 5/23/2012 5/23/2012 5/24/2012 5/30/2012 5/30/2012 5/30/2012 5/31/2012 6/14/2012 6/14/2012 6/14/2012 6/20/2012 6/20/2012 6/27/2012 6/27/2012 6/28/2012 6/29/2012 7/2/2012 7/2/2012 7/2/2012 7/3/2012 7/3/2012 7/5/2012 7/5/2012 Be-7 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta H-3 Cs-137 K-40 Cs-137 K-40 K-40 K-40 Gr. Beta H-3 H-3 Be-7 H-3 K-40 Gr. Beta Gr. Beta K-40 K-40 Cs-137 Gr. Beta TI-208 Gr. Beta Be-7 Cs-137 K-40 K-40 H-3 Ra-226 Ra-228 Gr. Beta 1-131 Ac-228 K-40 Pb-214 Be-7 Be-7 Be-7 H-3 1.77 +/- 0.21 6.38 +/- 0.50 8.92 +/- 1.52 5.86 +/- 0.38 2.07 +/- 0.65 2.03 +/- 1.04 750.60 +/- 106.20 0.13 +/- 0.07 10.15 +/- 0.97 0.046 +/- 0.024 13.20 +/- 0.74 1415.30 +/- 131.40 4.15 +/- 0.36 1.67 +/- 0.47 236.90 +/- 101.90 339.12 +/- 145.45 0.25 +/- 0.12 11291.00 +/- 372.80 3528.90 +/- 372.80 7.89 +/- 0.16 3.46 +/- 0.10 2.40 +/- 0.38 1267.20 +/- 105.00 0.024 +/- 0.013 10.95 +/- 0.89 0.068 +/- 0.018 2.12 +/- 0.86 2.05 +/- 0.19 2.32 +/- 0.39 6.67 +/- 0.28 5.93 +/- 0.38 251.33 +/- 86.51 0.30 +/- 0.08 0.76 +/- 0.54 1.49 +/- 1.06 0.54 +/- 0.26 0.33 +/- 0.09 6.71 +/- 0.58 0.46 +/- 0.05 0.09 +/- 0.02 0.11 +/-0.02 0.27 +/- 0.09 614.99 +/- 107.99 1.55 +/- 0.33 6.93 +/- 0.72 9.29 +/- 1.63 6.22 +/- 0.48 1.59 +/- 0.62 2.36 +/- 1.14 653.20 +/- 102.30 0.07 +/- 0.04 11.13 +/- 0.90 0.050 +/- 0.027 14.01 +/- 0.67 1348.10 +/- 109.00 4.19 +/- 0.38 1.39 +/- 0.45 281.90 +/- 103.70 337.23 +/- 98.19 0.21 +/- 0.09 11167.00 +/- 315.00 3677.20 +/- 392.40 8.01 +/- 0.16 3.33 +/- 0.10 2.55 +/- 0.43 1305.70 +/- 109.80 0.030 +/- 0.015 10.86 +/- 0.89 0.062 +/- 0.017 2.27 +/- 0.77 2.27 +/- 0.38 2.26 +/- 0.66 6.64 +/- 0.42 6.03 +/- 0.37 372.48 +/- 92.27 0.42 +/- 0.09 0.78 +/- 0.54 0.72 +/- 0.53 0.25 +/- 0.26 0.34 +/- 0.06 7.20 +/- 0.32 0.49 +/- 0.03 0.09 +/- 0.01 0.10 +/- 0.01 0.29 +/- 0.16 512.31 +/- 103.83 1.66 +/- 0.20 6.66 +/- 0.44 9.11 +/- 1.11 6.04 +/- 0.31 1.83 +/- 0.45 2.20 +/- 0.77 701.90 +/- 73.73 0.10 +/- 0.04 10.64 +/- 0.66 0.048 +/- 0.018 13.61 +/- 0.50 1381.70 +/- 85.36 4.17 +/- 0.26 1.53 +/- 0.33 259.40 +/- 72.69 338.18 +/- 87.74 0.23 +/- 0.07 11229.00 +/- 244.03 3603.05 +/- 270.63 7.95 +/- 0.11 3.40 +/- 0.07 2.48 +/- 0.29 1286.45 +/- 75.96 0.027 +/- 0.010 10.91 +/- 0.63 0.065 +/- 0.012 2.20 +/- 0.58 2.16 +/- 0.21 2.29 +/- 0.38 6.66 +/- 0.25 5.98 +/- 0.26 311.90 +/- 63.24 0.36 +/- 0.06 0.77 +/- 0.38 1.11 +/- 0.59 0.40 +/- 0.18 0.34 +/- 0.05 6.96 +/- 0.33 0.48 +/- 0.03 0.09 +/- 0.01 0.11 +/- 0.01 0.28 +/- 0.09 563.65 +/- 74.91 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass I
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I 3
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U A5-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4054, 4055 VE-4222, 4223 VE-4222, 4223 DW-30113, 30114 DW-30115, 30116 DW-30124, 30125 DW-30124, 30125 DW-30126, 30127 AP-4433, 4434 SG-4475, 4476 SG-4475, 4476 WW-4685, 4686 AP-4706, 4707 SO-4748, 4749 SO-4748, 4749 SO-4748, 4749 VE-4832, 4833 DW-30149, 30150 DW-30149, 30150 SG-4916, 4917 SG-4916, 4917.
F-5313, 5314 F-5313, 5314 F-5313, 5314 VE-5166, 5167 VE-5376, 5377 VE-5334, 5335 VE-5481, 5482 VE-5481, 5482 VE-5481, 5482 DW-30164, 30165 DW-30164, 30165 VE-5166, 5167 ME-5607, 5608 ME-5607, 5608 SW-5901, 5902 BS-6048, 6049 AP-6482, 6483 7/9/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/19/2012 7/19/2012 7/19/2012 7/24/2012 7/26/2012 7/26/2012 7/26/2012 7/26/2012 8/1/2012 8/1/2012 8/1/2012 8/3/2012 8/3/2012 8/9/2012 8/9/2012 8/9/2012 8/15/2012 8/22/2012 8/27/2012 8/28/2012 8/28/2012 8/28/2012 8/30/2012 8/30/2012 9/4/2012 9/4/2012 9/4/2012 9/17/2012 9/24/2012 9/27/2012 K-40 Be-7 K-40 Ra-228 Gr. Alpha Ra-226 Ra-228 Gr. Alpha Be-7 Gr. Alpha Gr. Beta H-3 Be-7 Gr. Beta U-233/4 U-238 K-40 Ra-226 Ra-228 Ac-228 K-40 Cs-137 Gr. Beta K-40 K-40 Gr. Beta K-40 Be-7 K-40 Sr-90 Ra-226 Ra-228 K-40 Gr. Beta K-40 H-3 K-40 Be-7 7.28 +/- 0.56 0.16 +/- 0.08 7.20 +/- 0.30 1.93 +/- 0.66 7.46 +/- 1.21 1.16 +/- 0.15 1.38 +/- 0.56 6.23 +/- 1.16 0.17 +/- 0.09 17.03 +/-4.17 13.23 +/- 2.61 289.00 +/- 99.00 0.28 +/- 0.14 20.45 +/- 1.04 0.11 +/- 0.02 0.12 +/- 0.02 4.06 +/- 0.22 2.69 +/- 0.22 2.77 +/- 0.75 11.03 +/- 0.33 6.39 +/- 0.80 0.05 +/- 0.02 4.12 +/- 0.08 3.07 +/- 0.42 4.26 +/- 0.28 7.72 +/- 0.17 1.65 +/- 0.17 2.52 +/- 0.19 5.05 +/- 0.37 0.01 +/- 0.00 1.33 +/- 0.15 2.76 +/- 0.66 2.05 +/- 0.32 2.92 +/- 0.08 2.06 +/- 0.32 10909.00 +/- 311.00 1.24 +/- 0.20 0.09 +/- 0.02 7.42 +/- 0.63 0.22 +/- 0.09 6.60 +/- 0.30 1.03 +/- 0.53 7.02 +/- 1.14 0.90 +/- 0.12 1.72 +/- 0.60 6.75 +/- 1.29 0.21 +/- 0.10 15.56 +/- 3.96 14.36 +/- 2.47 375.00 +/- 103.00 0.24 +/- 0.14 19.22 +/- 0.94 0.10 +/- 0.01 0.11 +/- 0.01 4.08 +/- 0.24 2.79 +/- 0.22 1.61 +/- 0.57 11.08 +/- 0.44 6.98 +/- 0.88 0.05 +/- 0.02 4.10 +/- 0.08 3.14 +/- 0.40 3.66 +/- 0.47 7.61 +/- 0.16 1.72 +/- 0.15 2.65 +/- 0.21 4.79 +/- 0.39 0.01 +/- 0.01 1.59 +/- 0.17 1.54 +/- 0.56 2.53 +/- 0.36 2.89 +/- 0.08 2.53 +/- 0.36 10817.00 +/- 310.00 1.18 +/- 0.21 0.09 +/- 0.03 7.35 0.19 6.90 1.48 7.24 1.03 1.55 6.49 0.19 16.30 13.80 332.00 0.26 19.84 0.11 0.12 4.07 2.74 2.19 11.06 6.69 0.05 4.11 3.11 3.96 7.67 1.68 2.59 4.92 0.01 1.46 2.15 2.29 2.90 2.29 10863.00 1.21 0.09
+/- 0.42
+/- 0.06
+/- 0.21
+/- 0.42
+/- 0.83
+/- 0.10
+/- 0.41
+/- 0.87
+/- 0.07
+/- 2.88
+/- 1.80
+/- 71.43
+/- 0.10
+/- 0.70
+/- 0.01
+/- 0.01
+/- 0.16
+/- 0.16
+/- 0.47
+/- 0.28
+/- 0.59
+/- 0.01
+/- 0.06
+/- 0.29
+/- 0.27
+/- 0.12
+/- 0.12
+/- 0.14
+/- 0.27
+/- 0.00
+/- 0.11
+/- 0.43
+/- 0.24
+/- 0.06
+/- 0.24
+/- 219.56
+/- 0.14
+/- 0.02 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-3
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-6090,6091 G-6090,6091 G-6090,6091 SO-6111, 6112 SO-6111, 6112 W-6795, 6796 AP-6461, 6462 WW-6279,6280 W-6346,6347 VE-6503, 6504 WW-6606,6607 WW-6606,6607 WW-7237, 7238 F-6627, 6628 VE-6669, 6670 VE-6669, 6670 SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 WW-7258, 7259 WW-7655, 7656 WW-7747, 7748 MI-6963, 6964 MI-7174, 7175 SG-7221, 7222 DW-30216, 30217 DW-30216, 30217 DW-30216, 30217 MI-7363, 7364 CF-7384, 7385 VE-7489, 7490 AP-7531, 7532 BS-7573,7574 LW-7865, 7866 SG-8095, 8096 SG-8095, 8096 10/1/2012 10/1/2012 10/11/2012 10/1/2012 10/1/2012 10/1/2012 10/2/2012 10/3/2012 10/3/2012 10/9/2012 10/10/2012 10/10/2012 10/12/2012 10/15/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/22/2012 10/25/2012 10/25/2012 10/28/2012 11/5/2012 11/9/2012 11/9/2012 11/9/2012 11/9/2012 11/13/2012 11/13/2012 11/16/2012 11/21/2012 11/24/2012 12/5/2012 12/19/2012 12/19/2012 Be-7 Gr. Beta K-40 Cs-137 K-40 H-3 Be-7 Gr. Beta Ra-226 K-40 Gr. Beta H-3 H-3 K-40 Be-7 K-40 Ac-228 Bi-214 Gr. Beta Pb-212 TI-208 H-3 H-3 H-3 K-40 K-40 Pb-214 Gr. Alpha Ra-226 Ra-228 K-40 K-40 K-40 Be-7 K-40 Gr. Beta Ac-228 Gamma 3.74 +/- 0.33 10.81 +/- 0.34 5.99 +/- 0.47 0.06 +/- 0.03 19.66 +/- 0.84 215.20 +/- 88.00 0.07 +/- 0.01 1.54 +/- 0.68 0.30 +/- 0.10 5.23 +/- 0.83 3.18 +/- 1.31 273.10 +/- 85.70 175.44 +/- 99.84 3.05 +/- 0.39 0.48 +/- 0.26 4.06 +/- 0.28 0.16 +/- 0.05 0.13 +/- 0.03 14.20 +/- 0.89 0.15 +/- 0.06 0.06 +/- 0.02 214.69 +/- 85.42 159.00 +/- 86.10 156.50 +/- 84.70 1384.60 +/- 111.70 1283.60 +/- 97.45 31.49 +/- 0.70 2.23 +/- 0.86 0.72 +/- 0.12 0.92 +/- 0.52 1304.40 +/- 103.30 11.75 +/- 0.52 2.22 +/- 0.23 0.19 +/- 0.10 7.21 +/- 0.41 2.16 +/- 0.56 25.15 +/- 0.73 26.98 +/- 2.72 3.54 +/- 0.30 10.72 +/- 0.33 5.45 +/- 0.44 0.04 +/- 0.02 20.09 +/- 0.80 292.80 +/- 91.60 0.07 +/- 0.02 1.67 +/- 0.75 0.36 +/- 0.10 6.00 +/- 0.45 2.42 +/- 1.27 219.80 +/- 83.10 180.75 +/- 100.03 3.23 +/- 0.37 0.50 +/- 0.13 3.68 +/- 0.26 0.17 +/- 0.06 0.16 +/- 0.03 12.67 +/- 0.88 0.13 +/- 0.02 0.04 +/- 0.02 314.60 +/- 90.25 159.00 +/- 86.10 170.20 +/- 85.30 1421.60 +/- 107.60 1293.20 +/- 91.37 30.11 +/-0.80 2.31 +/- 0.92 0.82 +/- 0.14 1.26 +/- 0.53 1496.10 +/- 121.30 10.94 +/- 0.59 1.91 +/- 0.22 0.29 +/- 0.17 7.57 +/- 0.39 1.64 +/- 0.62 25.47 +/- 0.54 28.68 +/- 2.89 3.64 +/- 0.22 10.77 +/- 0.24 5.72 +/- 0.32 0.05 +/- 0.02 19.88 +/- 0.58 254.00 +/- 63.51 0.07 +/- 0.01 1.61 +/- 0.51 0.33 +/- 0.07 5.04 +/- 0.27 2.80 +/- 0.91 246.45 +/- 59.69 178.10 +/- 70.66 3.14 +/- 0.27 0.49 +/- 0.15 3.87 +/- 0.19 0.17 +/- 0.04 0.14 +/- 0.02 13.44 +/- 0.63 0.14 +/- 0.03 0.05 +/- 0.01 264.65 +/- 62.13 159.00 +/- 60.88 163.35 +/- 60.10 1403.10 +/- 77.55 1288.40 +/- 66.79 30.80 +/- 0.53 2.27 +/- 0.63 0.77 +/- 0.09 1.09 +/- 0.37 1400.25 +/- 79.66 11.35 +/- 0.39 2.06 +/- 0.16 0.24 +/- 0.10 7.39 +/- 0.28 1.90 +/- 0.42 25.31 +/- 0.45 27.83 +/- 1.98 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass U
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I Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).
A5-4
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 STSO-1766 d STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STAP-1 772 STAP-1 772 STAP-1772 STAP-1772 STAP-1 772 STAP-1 772 STAP-1 772 STAP-1772 STAP-1 772 STAP-1 772 e STAP-1 772 STAP-1772 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 88.50 1352.10 1.70 842.20 0.40 1729.60 647.60 781.50 142.40 66.10 383.20 289.60 63.20 310.80 766.70 0.062 0.010 2.40 2.33 2.07 3.77 0.003 0.098
-0.010 0.016 0.11 3.67
+/- 8.30
+/- 4.00
+/- 0.70
+/- 4.30
+/- 0.90
+/- 22.20
+/- 4.20
+/- 9.70
+/- 9.70
+/- 6.40
+/- 15.30
+/- 10.90
+/- 5.40
+/- 12.10
+/- 6.70
+/- 0.02
+/- 0.01
+/- 0.08
+/- 0.13
+/- 0.10
+/- 0.14
+/- 0.004
+/- 0.017
+/- 0.060
+/- 0.006
+/- 0.02
+/- 0.20 159.00 1179.00 1.56 828.00 0.00 1491.00 558.00 862.00 136.00 65.80 392.00 374.00 68.10 329.00 642.00 0.073 0.00 2.18 2.38 1.79 3.24 0.002 0.097 0.000 0.019 0.12 2.99 111.00 -207.00 825.00 - 1533.00 1.00 - 2.00 580.00 - 1076.00 0.00 - 1.00 1044.00 - 1938.00 391.00 -725.00 603.00 - 1121.00 97.00 - 177.00 46.10 - 85.50 274.00 - 510.00 262.00 - 486.00 47.70 - 88.50 230.00 - 428.00 449.00 - 835.00 0.051 -0.10 0.000 - 1.00 1.53 -2.84 1.67 - 3.09 1.25 - 2.33 2.27 - 4.21 0.000 -0.10 0.07 -0.13
-0.10 -0.13 0.013 - 0.024 0.09 -0.16 2.09 - 3.89 Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1 773 02/01/12 Gr. Alpha STAP-1 773 02/01/12 Gr. Beta 0.51 +/- 0.05 2.75 +/- 0.10 STVE-1 776 STVE-1 776 STVE-1 776 STVE-1 776 STVE-1 776 STVE-1 776 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Zn-65 14.57 6.45 8.39 0.01 0.03 10.31
+/- 0.28
+/- 0.23
+/- 0.29
+/- 0.09
+/- 0.08
+/- 0.67 1.20 2.40 12.00 6.05 8.43 0.00 0.00 8.90 2.14 6.36 0.40 - 2.00 1.20 - 3.60 8.40 - 15.60 4.24 - 7.87 5.90 - 10.96 0.00 -0.10 0.00 -0.10 6.23-11.57 0.64 - 3.64 3.18 -9.54 STW-1960 02/01/12 Gr. Alpha STW-1960 02/01/12 Gr. Beta 1.68 +/- 0.09 6.33 +/- 0.10 A6-1
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-1964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1 964 STW-1 964 STW-1 964 STW-1 964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Am-241 Co-57 Co-60 Cs-1 34 Cs-137 Fe-55 H-3 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 1.28 +/- 0.12 33.30 +/- 0.40 23.20 +/- 0.40 0.30 +/- 3.00 40.10 +/- 0.60 65.10 +/- 9.50 460.00 +/- 12.10 153.00 +/- 4.20 32.70 +/- 0.60 49.80 +/- 2.90 0.58 +/- 0.06 1.30 +/- 0.15 0.10 +/- 0.20 23.70 +/- 0.80 0.40 +/- 0.05 2.67 +/- 0.13 0.01 +/- 0.20 5.73 +/- 0.28 1.63 32.90 23.72 0.00 39.90 81.90 437.00 142.00 31.80 60.00 0.63 1.34 0.00 27.90 0.39 2.76 0.00 6.82 111.00 406.00 105.80 134.00 508.00 469.00 1316.00 531.00 939.00 1150.00 632.00 920.00 60.30 263.00 606.00 1.14 -2.12 23.00 - 42.80 16.60 - 30.84 0.00 - 1.00 27.90 - 51.90 57.30 - 106.50 306.00 - 568.00 99.00 - 185.00 22.30 - 41.30 42.00 - 78.00 0.44 - 0.82 0.94 -1.74 0.00 - 1.00 19.50 - 36.30 0.27 - 0.51 1.93 - 3.59 0.00 - 1.00 4.77 - 8.87 78.00 - 144.00 284.00 - 528.00 74.10 - 137.50 94.00 - 174.00 356.00 - 660.00 328.00 -610.00 921.00 - 1711.00 372.00 - 690.00 657.00 - 1221.00 805.00 - 1495.00 442.00 - 822.00 644.00 - 1196.00 42.20 - 78.40 184.00 - 342.00 424.00 - 788.00 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-5391 08/01/12 1-129 STSO-5392 STSO-5392 STSO-5392 STSO-5392 STSO-5392 STSO-5392 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 Am-241 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 U-233/4 U-238 Zn-65 129.30 376.20 118.70 140.70 483.52 432.50 1528.00 592.00 933.60 1319.80 737.30 1083.20 55.80 231.20 696.10
+/- 12.70
+/- 20.60
+/- 9.30
+/- 9.90
+/- 16.47
+/- 23.10
+/- 4.10
+/- 3.20
+/- 5.82
+/- 5.50
+/- 17.70
+/- 5.20
+/- 4.20
+/- 8.60
+/- 7.00 I
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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
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1393 ERAP-1393 ERAP-1393 ERAP-1393 ERAP-1393 ERAP-1394 ERAP-1394 ERAP-1394 ERAP-1394 ERAP-1394 ERAP-1394 ERAP-1394 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 Co-60 Cs-1 34 Cs-137 Mn-54 Zn-65 Am-241 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium 917.5 +/- 7.0 586.6 +/- 7.4 1255.9 +/- 9.4
< 3.4 1085.2 +/- 18.0 86.9 +/- 2.9 70.2 +/- 3.6 66.0 +/- 1.0 112.5 +/- 15.4 43.4 +/- 0.8 44.0 +/- 1.2 89.1 +/- 2.2 880.0 656.0 1130.0 0.0 897.0 68.8 63.2 63.0 89.6 47.5 47.1 96.7 ERAP-1396 03/19/12 Gr. Alpha ERAP-1396 03/19/12 Gr. Beta 81.1 +/- 1.5 68.4 +/- 0.7 77.8 52.5 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 Ac-228 Am-241 Bi-212 Bi-214 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 Th-234 U-233/4 U-238 Uranium Zn-65 1303.4 +/- 89.3 856.0 +/- 123.7 1379.2 +/- 247.2 965.2 +/- 38.4 3693.6 +/- 32.1 2257.3 +/- 45.4 9444.5 +/- 58.4 11277.0 +/- 275.1
< 21.0 1208.4 +/- 26.3 1041.6 +/- 46.9 921.0 +/- 112.6 1028.0 +/- 112.6 8128.0 +/- 329.0 2711.3 +/- 253.6 1859.3 +/- 126.6 2003.3 +/- 130.3 3939.5 +/- 283.8 4200.4 +/- 65.9 1570.0 938.0 1550.0 1100.0 3500.0 2180.0 8770.0 11600.0 0.0 1510.0 1110.0 984.0 879.0 8800.0 2000.0 1960.0 2000.0 4030.0 3650.0 681.0 - 1100.0 417.0 -814.0 849.0 - 1480.0 642.0 - 1240.0 42.4 -93.1 43.3 -83.1 45.6 - 82.4 43.8 - 134.0 29.4 - 71.6 30.4 - 65.1 53.5 - 147.0 26.1 -121.0 33.2 - 76.5 1010.0 -2180.0 549.0 - 1220.0 413.0 -2280.0 665.0 - 1590.0 2370.0 - 4820.0 1420.0 -2620.0 6720.0 - 11300.0 8470.0 -15600.0 992.0 - 2110.0 647.0 - 1650.0 592.0 - 1360.0 575.0 - 1210.0 3360.0 - 13900.0 632.0 - 3760.0 1200.0 -2510.0 1240.0 - 2540.0 2190.0 - 5320.0 2910.0 -4850.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass I
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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 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1405 ERW-1405 ERW-1405 ERW-1405 ERW-1405 ERW-1405 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19112 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 Am-241 Cm-244 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 Am-241 Fe-55 Pu-238 Pu-239/40 U-233/4 U-238 Uranium Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 4194.8 +/- 199.5 1471.2 +/- 113.1 2347.8 +/- 47.9 2847.5 +/- 64.0 1503.5 +/- 52.5 34105.7 +/- 745.3
< 26.8 2509.0 +/- 213.6 2690.4 +/- 208.9 7881.5 +/- 470.8 3149.6 +/- 165.2 3203.6 +/- 166.5 6463.7 +/- 363.2 2701.9 +/- 105.5 119.9 +/-3.2 713.7 +/- 127.4 131.9 +/-6.4 108.9 +/- 10.2 93.1 +/- 7.9 96.9 +/- 5.5 190.0 +/- 13.8 858.7 +/- 5.6 560.4 +/- 4.4 1239.9 +/- 7.4
< 7.4 944.3 +/- 26.2 786.9 +/- 20.6 85.9 +/- 3.0 45.7 +/- 1.6 9045.0 +/- 284.0 4540.0 1590.0 2210.0 2920.0 1340.0 28600.0 0.0 2350.0 2570.0 8520.0 3610.0 3580.0 7350.0 2310.0 135.0 863.0 135.0 112.0 105.0 104.0 214.0 875.0 609.0 1250.0 0.0 989.0 749.0 103.0 43.7 2780.0 - 6040.0 779.0 - 2480.0 1520.0 - 3090.0 1880.0 -3790.0 972.0 - 1860.0 20700.0 -40100.0 1400.0 - 3220.0 1580.0 - 3540.0 4860.0 - 11300.0 2370.0 - 4640.0 2390.0 - 4550.0 4980.0 -9150.0 1670.0 - 3240.0 91.0 -181.0 514.0 - 1170.0 99.9 - 168.0 86.9 -141.0 78.9 - 135.0 79.3 - 128.0 157.0 -277.0 760.0 - 1020.0 447.0 - 700.0 1060.0 - 1500.0 644.0 - 1310.0 624.0 - 945.0 36.6 - 160.0 25.0 - 64.7 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass ERW-1406 03/19/12 Gr. Alpha ERW-1406 03/19/12 Gr. Beta ERW-1409 03/19/12 H-3 9150.0 6130.0 - 13000.0 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 Collected and Direction Range Collected and Range Range Range 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 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
458.5 411.6 70 605.4 605.4 Broadleaf Vegetation Be-7 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 45
< LLD 1
pCi/Kg wet 82 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 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 11
<LLD5 pCi/L 58 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
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PNPP Direct Radiation (TLDs), Quarterly Exposure.
Units: mR/91 days Date Placed Date Removed E-1 E-3 E-4 E-5 E-6 E-7 E-8 E-9 E-10 E-11 E-1 2 E-1 3 E-14 E-1 5 E-21 E-23 E-24 E-29 E-30 E-31 E-33 E-35 E-36 E-53 E-54 E-55 E-56 E-58 1 st Qtr.
01-06-12 04-16-12 11.5 +/-0.9 11.9 +/- 1.0 13.4 +/- 0.8 11.9 +/-0.8 13.9 +/- 1.0 13.3 +/- 0.6 11.9 +/-0.6 11.2 +/-_0.7 14.3 +/- 0.7 14.2 +/- 0.8 12.8 +/- 0.9 12.9 +/- 0.7 11.5 +/-0.9 11.1 +/-0.6 13.4 +/- 0.8 14.6 +/- 0.6 12.4 +/- 0.7 16.3 +/- 0.7 15.0 +/- 0.7 15.2 +/- 0.8 16.8 +/- 0.9 12.2 +/- 0.8 15.7 +/- 0.8 13.2 +/- 0.6 12.6 +/-0.9 13.5 +/- 1.4 12.9 +/- 0.6 10.7 +/- 0.6 2nd Qtr.
04-16-12 07-17-12 10.3 +/- 0.8 11.7 +/-_0.7 13.1 +/-_0.7 12.3 +/- 0.6 13.5 +/- 0.6 13.4 +/- 0.7 12.6 +/- 0.6 11.6 +/-0.6 14.9 +/- 1.1 13.3 +/- 0.4 12.8 +/- 0.6 12.4 +/- 0.9 11.6 +/-_0.5 9.0 +/- 0.6 13.7 +/- 0.6 14.2 +/- 0.7 12.3 +/-0.8 16.3 +/- 0.6 15.4 +/-0.5 17.3 +/- 0.6 18.0 +/-0.7 12.7 +/-0.5 16.8 +/-0.6 14.3 +/-0.6 13.1 +/-0.4 14.2 +/-0.6 13.5 +/-0.5 11.2 +/-0.6 3rd Qtr.
07-17-12 09-25-12 10.3 +/- 1.3 11.4 +/- 1.2 12.0 1.1 10.9 +/-0.9 12.6 +/-0.8 12.0 +/-0.9 11.1 +/-1.0 11.3 +/-0.8 15.2 _ 1.4 14.4 +/- 1.7 12.6 +/-1.2 12.3 +/-0.9 10.3 +/- 1.1 9.8 +/- 0.8 13.0 +/- 1.0 14.1 +/-0.8 12.3 +/- 1.7 16.1 +/-1.1 14.8 +/-0.9 15.0 +/-0.9 16.5 +/- 1.1 11.6 +/-0.8 17.6 +/-0.7 14.7 +/-0.8 14.1 +/-1.2 16.5 +/- 1.0 13.7 +/-0.9 10.9 +/-1.4 4th Qtr.
09-25-12 01-08-13 11.8 +/- 1.2 13.1 +/- 1.0 14.3 +/- 0.9 13.8 +/- 0.9 14.6 +/- 0.9 14.6 +/- 0.9 14.4 +/- 1.5 12.9 +/- 0.6 15.8 +/- 0.9 14.4 +/- 0.7 13.8 +/- 1.3 13.1 +/- 1.0 12.2 +/- 0.7 9.6 +/- 0.8 13.8 +/- 0.6 14.6 +/- 0.8 13.2 +/- 1.0 16.9 +/-0.9 16.0 +/- 0.8 17.8 +/- 0.9 18.2 +/- 1.0 13.5 +/- 0.7 16.7 +/- 0.8 14.3 +/- 1.0 13.5 +/- 0.7 13.9 +/- 1.0 13.2 +/- 0.9 11.1 +/-_0.7 Mean +/- s.d.
E-Control 1 E-Control 2 13.2 +/- 1.6 7.0 +/- 0.8 6.6 +/- 0.7 13.4 +/-2.0 7.6 +/-0.5 7.3 _0.5 13.1 +/-2.1 7.0 +/- 0.9 6.5 +/- 0.6 14.1 +/-1.9 6.9 +/- 0.3 6.8 +/-0.2 C-1
PNPP 3
Direct Radiation (TLDs), Quarterly Exposure.
Collection: Quarterly Composite Units: pCi/m 3
Date Placed Date Removed Q-1 Q-3 Q-4 Q-5 Q-6 Q-7 Q-8 Q-9 Q-10 Q-11 Q-12 Q-13 Q-14 Q-15 Q-21 Q-23 Q-24 Q-29 Q-30 Q-31 Q-33 Q-35 Q-36 Q-53 Q-54 Q-55 Q-56 Q-58 1 st Qtr.
01-06-12 04-16-12 10.4 +/- 1.1 12.3 +/- 0.5 13.1 +/- 0.5 13.0 +/- 0.4 13.5 +/- 0.9 14.1 +/-0.3 12.3 +/- 0.4 12.2 +/- 0.6 14.7 +/- 0.8 13.0 +/- 0.3 13.1 +/-0.3 12.7 +/-0.3 11.5 +/-0.4 10.9 +/-0.5 13.9 +/-0.5 13.9 +/-0.4 13.2 +/-1.3 16.5 +/-0.4 15.4 +/- 0.4 16.6 +/- 0.6 17.6 +/- 0.8 13.0 +/- 0.4 16.4 +/- 0.6 13.8 +/- 0.4 13.5 +/- 0.5 13.9 +/- 0.9 13.5 +/- 0.8 11.0 +/-0.6 2nd Qtr.
04-16-12 07-17-12 9.4 +/- 1.2 9.9 +/- 0.9 12.2 +/-0.8 10.9 +/- 1.2 11.7 +/-0.8 13.9 +/- 1.2 12.1 +/-0.7 12.5 +/-3.2 14.0 +/- 1.0 13.0 +/-0.8 12.4 +/- 1.0 12.2 +/-0.8 11.3 +/-0.8 9.7 +/- 0.8 12.5 +/-0.9 13.1 +/-1.1 10.5 +/-0.7 15.4 +/- 1.1 13.4 +/-0.7 14.7 +/- 1.1 16.0 +/- 1.1 11.2 +/-0.8 15.1 +/-0.8 13.0 +/-0.8 12.5 +/-0.7 13.5 +/-0.9 12.6 +/- 1.0 10.3 +/- 0.7 3rd Qtr.
07-17-12 09-25-12 12.4 +/- 2.4 14.5 +/- 2.2 15.0 +/- 2.3 15.5 +/- 2.1 15.8 +/- 2.1 16.6 +/- 2.2 14.9 +/- 2.2 15.3 +/- 2.3 18.0 +/- 2.3 16.6 +/- 2.8 16.7 +/- 2.4 15.1 +/- 2.2 13.6 +/- 2.2 12.9 +/- 2.2 16.2 +/-2.2 16.6 +/-2.3 15.4 +/-2.5 19.4 +/-2.3 18.4 +/-2.2 19.6 +/-2.2 20.6 +/- 2.2 15.1 +/-2.3 19.5 +/- 2.2 16.2 +/-_2.1 16.2 +/- 2.2 16.3 +/- 2.2 15.1 +/-_2.3 12.9 +/- 2.4 4th Qtr.
09-25-12 01-08-13 10.6 +/- 1.1 11.3 +/- 1.1 13.9 +/- 1.1 12.6 +/- 1.2 13.5 +/- 0.8 15.0 +/- 0.8 13.3 +/- 1.1 12.9 +/- 0.9 15.4 +/- 0.9 14.4 +/- 0.9 13.7 +/- 1.1 13.2 +/- 1.2 12.5 +/- 0.8 11.3 +/-_0.9 13.5 +/- 0.9 13.6 +/- 1.1 12.1 +/- 0.9 16.4 +/- 1.2 14.5 +/- 0.8 16.5 +/- 1.0 17.6 +/- 0.9 13.1 +/-_0.9 16.4 +/- 1.0 14.0 +/- 1.0 14.0 +/- 0.8 14.6 +/- 1.0 13.8 +/- 1.1 11.5 +/-0.9 I
I I
I I
I I
I I
U I
I U
I I
I I
Mean +/- s.d.
Q-Control 1 Q-Control 2 13.5 +/- 1.8 7.7 +/- 0.3 7.9 +/- 0.4 12.5 +/- 1.7 7.0 +/- 0.9 7.3 +/- 0.8 16.1 +/-2.1 9.0 +/- 2.1 9.3 +/- 2.2 13.8 +/- 1.7 7.3 +/- 0.8 7.1 +/-0.8 C-2
PNPP Direct Radiation (TLDs), Annual Exposure.
Units: mR/365 days Date Placed Date Removed 2012 01-06-12 01-08-13 A-1 A-3 A-4 A-5 A-6 A-7 A-8 A-9 A-10 A-11 A-12 A-13 A-14 A-15 A-21 A-23 A-24 A-29 A-30 A-31 A-33 A-35 A-36 A-53 A-54 A-55 A-56 A-58 52.2 +/- 3.2 56.7 +/- 1.9 62.8 +/- 1.9 59.0 +/- 2.6 63.2 +/- 2.8 62.4 +/- 3.1 58.6 +/- 3.1 55.5 +/- 1.7 70.1 +/-2.1 64.5 + 2.4 63.4 +/- 2.1 61.5 +/-2.9 57.4 + 2.6 53.0 +/- 2.3 67.8 +/- 5.1 64.9 +/- 3.1 59.3 +/- 3.4 77.2 +/- 4.1 69.3 +/- 2.6 75.4 +/- 4.0 79.3 +/- 2.8 60.0 +/- 1.6 81.5 +/- 1.9 69.7 +/- 2.1 67.4 +/- 2.2 72.0 +/- 2.2 69.0 +/- 2.8 57.4 +/- 2.6 64.7 +/- 7.8 23.6 +/- 1.3 23.2 + 1.0 Mean +/- s.d.
A-Control 1 A-Control 2 C-3
PNPP Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31.
Location:
P-1 Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (me)
Gross Beta 1-131 Collected (mi)
Gross Beta 1-131 Required LLD 0.0075 0.050 0.0075 0.050 01-04-12 01-11-12 01-18-12 01-25-12 02-01-12 02-07-12 02-15-12 02-22-12 02-29-12 03-07-12 03-13-12 03-21-12 03-29-12 577 581 568 601 568 507 647 578 574 563 498 644 655 0.020 +/- 0.003 0.025 +/- 0.003 0.020 +/- 0.003 0.030 +/- 0.003 0.027 +/- 0.003 0.026 0.021 0.025 0.020 0.024 0.023 0.022 0.020
+/- 0.003
+/- 0.002
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.002
+/- 0.002
< 0.010
< 0.009
< 0.011
< 0.011
< 0.006
< 0.009
< 0.006
< 0.010
< 0.010
< 0.011
< 0.008
< 0.009
< 0.008 07-10-12 07-17-12 07-25-12 08-01-12 08-08-12 08-15-12 08-23-12 08-29-12 09-05-12 09-11-12 09-19-12 09-26-12 10-03-12 578 589 647 578 580 578 652 493 585 490 667 565 559 0.030 +/- 0.003 0.025 +/- 0.003 0.027 +/- 0.003 0.019 +/- 0.003 0.026 +/- 0.003 0.018 +/- 0.003 0.023 +/- 0.003 0.037 +/- 0.003 0.027 +/- 0.003 0.023 +/- 0.003 0.029 +/- 0.003 0.023 +/- 0.003 0.021 +/- 0.003
< 0.004
< 0.004
< 0.011
< 0.009
< 0.005
< 0.006
< 0.008
< 0.010
< 0.012
< 0.004
< 0.011
<0.013
< 0.007 I
U I
I I
I I
I I
U I
I I
I I
I I
I 1Q 2012 Mean +/- s.d.
0.023 +/- 0.003 04-05-12 04-11-12 04-18-12 04-25-12 05-02-12 05-09-12 05-16-12 05-23-12 05-30-12 06-06-12 06-13-12 06-20-12 06-26-12 07-03-12 570 472 570 554 561 580 589 589 578 580 576 587 480 576 0.015 0.020 0.018 0.019 0.021 0.019 0.019 0.017 0.028 0.012 0.016 0.021 0.022 0.029
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.002
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
< 0.011
< 0.004
< 0.013
< 0.006
< 0.010
< 0.007
< 0.007
< 0.011
< 0.010
< 0.010
< 0.006
< 0.008
< 0.005
< 0.007
< 0.005 3Q 2012 Mean +/- s.d.
10-10-12 10-17-12 10-24-12 11-01-12 11-08-12 11-14-12 11-21-12 11-28-12 12-05-12 12-12-12 12-20-12 12-26-12 01-02-13 572 552 558 642 542 457 553 538 552 538 615 444 499 0.025 +/- 0.005 0.032 +/- 0.003 0.027 +/- 0.003 0.035 +/- 0.003 0.018 +/- 0.002 0.016 +/- 0.003 0ý048 +/- 0.004 0.051 +/- 0.004 0.041 +/- 0.003
< 0.013
< 0.008
< 0.005
< 0.013
< 0.011
< 0.010
< 0.009
< 0.009
< 0.016
< 0.007
< 0.008
< 0.025
< 0.007
< 0.010 0.058 0.023 0.055 0.028 0.036
+/- 0.004
+/- 0.003
+/- 0.003
+/- 0.004
+/- 0.003 2Q 2012 Mean +/- s.d.
0.020 +/- 0.005
< 0.013 4Q 2012 Mean +/- s.d.
Cumulative Average 0.036 +/- 0.014
< 0.025 0.026 C-4
PNPP Airborne particulates and charcoal canisters, analyses for gross beta and iodine-i 31.
Location:
P-3 Units: pCi/m 3 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 01-11-12 01-18-12 01-25-12 02-01-12 02-07-12 02-15-12 02-22-12 02-29-12 03-07-12 03-13-12 03-21-12 03-29-12 569 578 582 592 565 504 644 584 573 551 497 643 642 0.023 +/- 0.003 0.027 +/- 0.003 0.020 +/- 0.003 0.032 +/- 0.003 0.025 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.002 0.028 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.002 0.017 +/- 0.002
< 0.010
< 0.009
< 0.011
< 0.011
< 0.006
< 0.009
< 0.006
< 0.010
< 0.010
< 0.011
< 0.008
< 0.009
< 0.009 07-10-12 07-17-12 07-25-12 08-01-12 08-08-12 08-15-12 08-23-12 08-29-12 09-05-12 09-11-12 09-19-12 09-26-12 10-03-12 570 582 648 574 573 569 646 481 578 467 661 551 533 0.029 +/- 0.003 0.026 +/- 0.003 0.023 +/- 0.003 0.021 +/- 0.003 0.025 + 0.003 0.020 +/- 0.003 0.022 +/- 0.003 0.035 +/- 0.003 0.029 +/- 0.003 0.022 +/- 0.003 0.026 + 0.002 0.022 +/- 0.003 0.019 + 0.003
< 0.004
< 0.004
< 0.011
< 0.009
< 0.005
< 0.006
< 0.008
< 0.010
< 0.012
< 0.004
< 0.011
<0.013
< 0.007 1Q 2012 Mean +/- s.d.
04-05-12 04-11-12 04-18-12 04-25-12 05-02-12 05-09-12 05-16-12 05-23-12 05-30-12 06-06-12 06-13-12 06-20-12 06-26-12 07-03-12 554 468 564 543 543 578 584 594 577 554 580 585 483 572 0.023 +/- 0.004 0.014 +/- 0.003 0.020 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.017 +/- 0.003 0.029 +/- 0.003 0.011 +/- 0.003 0.015 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.025 +/- 0.003
< 0.011
< 0.004
< 0.013
< 0.006
< 0.010
< 0.008
< 0.007
<0.011
< 0.010
< 0.010
< 0.006
< 0.008
< 0.005
< 0.007
< 0.005 3Q 2012 Mean +/- s.d.
10-10-12 10-17-12 10-24-12 11-01-12 11-08-12 11-14-12 11-21-12 11-28-12 12-05-12 12-12-12 12-20-12 12-26-12 01-02-13 554 544 556 635 539 500 626 596 612 586 675 505 581 0.025 +/- 0.004 0.027 +/- 0.003 0.027 +/- 0.003 0.037 +/- 0.003 0.018 +/- 0.002 0.015 +/- 0.003 0.040 +/- 0.004 0.038 +/- 0.003 0.041 +/- 0.003
< 0.013
< 0.009
< 0.006
< 0.013
< 0.011
< 0.010
< 0.008
< 0.008
< 0.014
< 0.006
< 0.007
< 0.024
< 0.007
< 0.009 0.045 0.017 0.041 0.023 0.031
+ 0.003
+ 0.003
+ 0.003
+ 0.003
+ 0.003 2Q 2012 Mean +/- s.d.
0.019 +/- 0.004
< 0.013 4Q 2012 Mean +/- s.d.
Cumulative Average 0.031 +/- 0.010
< 0.024 0.024 C-5
PNPP Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location:
P-4 Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (ms)
Gross Beta 1-131 Collected (mi)
Gross Beta 1-131 Required LLD 0.0075 0.050 0.0075 0.050 01-04-12 01-11-12 01-18-12 01-25-12 02-01-12 02-07-12 02-15-12 02-22-12 02-29-12 03-07-12 03-13-12 03-21-12 03-29-12 580 576 622 635 610 529 703 585 587 588 536 695 736 0.021 0.027 0.026 0.033 0.028
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003 0.027 +/- 0.003 0.021 +/- 0.002 0.028 +/- 0.003 0.023 +/- 0.003 0.026 +/- 0.003 0.023 +/- 0.003 0.022 +/- 0.002 0.019 +/- 0.002
< 0.010
< 0.009
< 0.010
< 0.010
< 0.006
< 0.009
< 0.005
< 0.010
< 0.010
< 0.010
< 0.007
< 0.008
< 0.008 07-10-12 07-17-12 07-25-12 08-01-12 08-08-12 08-15-12 08-23-12 08-29-12 09-05-12 09-11-12 09-19-12 09-26-12 10-03-12 544 563 646 550 552 550 630 458 561 459 642 547 530 0.028 0.025 0.019 0.027 0.017 0.023 0.037 0.028 0.026 0.029 0.022
+ 0.003
+ 0.003
+ 0.003
+ 0.003
+ 0.003
+ 0.003
+ 0.004
+ 0.003
+ 0.003
+ 0.003
+ 0003 0.033 +/- 0.003
< 0.005
< 0.005
< 0.011
< 0.009
< 0.006
< 0.006
< 0.008
< 0.011
< 0.013
< 0.004
< 0.011
< 0.013
< 0.007 I
U I
I I
I I
I I
I I
I I
I I
0.018 +/- 0.003 102012 Mean +/- s.d.
04-05-12 04-11-12 04-18-12 04-25-12 05-02-12 05-09-12 05-16-12 05-23-12 05-30-12 06-06-12 06-13-12 06-20-12 06-26-12 07-03-12 590 526 627 604 615 559 583 566 571 553 549 565 464 544 0.025 +/- 0.004 0.015 +/- 0.002 0.019 +/- 0.003 0.016 +/- 0.002 0.019 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.003 0.026 +/- 0.003 0.009 +/- 0.002 0.018 +/- 0.003 0.021 +/- 0.003 0.024 +/- 0.003 0.031 + 0.003
< 0.010
< 0.004
< 0.011
< 0.005
< 0.009
< 0.007
< 0.007
< 0.011
< 0.011
< 0.010
< 0.006
< 0.008
< 0.005
< 0.007
< 0.005 3Q 2012 Mean +/- s.d.
10-10-12 10-17-12 10-24-12 11-01-12 11-08-12 11-14-12 11-21-12 11-28-12 12-05-12 12-12-12 12-20-12 12-26-12 01-02-13 552 545 551 630 527 497 580 572 585 555 623 488 573 0.026 +/- 0.006 0.030 +/- 0.003 0.025 +/- 0.003 0.034 +/- 0.003 0.017 +/- 0.002 0.013 +/- 0.003 0.041 +/- 0.004 0.048 +/- 0.003 0.037 +/- 0.003 0.051 +/- 0.003 0.023 +/- 0.003 0.047 +/- 0.003 0.026 +/- 0.003 0.032 +/- 0.003
< 0.013
< 0.009
< 0.006
< 0.013
< 0.011
< 0.010
< 0.008
< 0.009
< 0.015
< 0.007
< 0.008
< 0.024
< 0.007
< 0.009
< 0.024 I
2Q 2012 Mean +/- s.d.
0.020 +/- 0.005
< 0.011 4Q 2012 Mean +/- s.d.
Cumulative Average 0.033 +/- 0.012 0.026 I
I I
C-6
PNPP Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location:
P-5 Units: pCi/m 3 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 01-11-12 01-18-12 01-25-12 02-01-12 02-07-12 02-15-12 02-22-12 02-29-12 03-07-12 03-13-12 03-21-12 03-29-12 545 547 562 561 536 467 618 545 548 533 469 614 634 0.024 +/- 0.003 0.025 +/- 0.003 0.029 +/- 0.003 0.033 +/- 0.003 0.031 +/- 0.003 0.030 +/- 0.003 0.023 +/- 0.002 0.029 +/- 0.003 0.023 +/- 0.003 0.026 +/- 0.003 0.026 +/- 0.003 0.024 +/- 0.003 0.018 +/- 0.002
< 0.011
< 0.009
< 0.011
< 0.012
< 0.007
< 0.010
< 0.006
< 0.011
< 0.011
< 0.011
< 0.008
< 0.009
< 0.009 07-10-12 07-17-12 07-25-12 08-01-12 08-08-12 08-15-12 08-23-12 08-29-12 09-05-12 09-11-12 09-19-12 09-26-12 10-03-12 578 591 654 583 581 586 656 499 586 496 676 570 573 0.033 +/- 0.003 0.027 +/- 0.003 0.027 +/- 0.003 0.019 +/- 0.003 0.028 +/- 0.003 0.020 +/- 0.003 0.023 +/- 0.002 0.036 +/- 0.003 0.026 +/- 0.003 0.026 +/- 0.003 0.030 +/- 0.003 0.021 +/- 0.003 0.022 +/- 0.003
< 0.004
< 0.004
< 0.011
< 0.009
< 0.005
< 0.006
< 0.008
<0.010
< 0.012
< 0.004
< 0.010
< 0.013
< 0.007 1Q 2012 Mean +/- s.d.
04-05-12 04-11-12 04-18-12 04-25-12 05-02-12 05-09-12 05-16-12 05-23-12 05-30-12 06-06-12 06-13-12 06-20-12 06-26-12 07-03-12 543 464 553 541 540 580 592 586 579 585 583 586 510 579 0.026 +/- 0.004 0.016 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.016 +/- 0.003 0.027 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.014 +/- 0.002 0.028 +/- 0.003 0.012 +/- 0.002 0.018 +/- 0.003 0.020 +/- 0.003 0.023 +/- 0.003 0.029 +/- 0.003
< 0.012
< 0.004
< 0.013
< 0.006
< 0.010
< 0.008
< 0.007
< 0.011
< 0.010
< 0.009
< 0.006
< 0.008
< 0.005
< 0.007
< 0.005 3Q 2012 Mean +/- s.d.
10-10-12 10-17-12 10-24-12 11-01-12 11-08-12 11-14-12 11-21-12 11-28-12 12-05-12 12-12-12 12-20-12 12-26-12 01-02-13 585 581 587 663 560 495 581 575 582 564 607 455 560 0.026 +/- 0.005 0.029 +/- 0.003 0.026 +/- 0.003 0.037 +/- 0.003 0.019 +/- 0.002 0.016 +/- 0.003 0.041 +/- 0.004 0.047 +/- 0.003 0.040 +/- 0.003 0.051 +/- 0.003 0.021 +/- 0.003 0.052 +/- 0.003 0.028 +/- 0.003 0.034 +/- 0.003
< 0.013
< 0.008
< 0.005
< 0.012
< 0.010
< 0.009
< 0.008
< 0.009
<0.015
< 0.007
< 0.008
< 0.013
< 0.007
< 0.009 2Q 2012 Mean +/- s.d.
0.020 +/- 0.005
< 0.013 4Q 2012 Mean +/- s.d.
Cumulative Average 0.034 +/- 0.012
< 0.015 0.026 C-7
PNPP Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location:
P-6 Units: pCi/m 3
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 01-11-12 01-18-12 01-25-12 02-01-12 02-07-12 02-15-12 02-22-12 02-29-12 03-07-12 03-13-12 03-21-12 03-29-12 575 567 572 586 552 494 637 574 574 557 497 614 639 0.022 +/- 0.003 0.029 +/- 0.003 0.021 +/- 0.003 0.030 +/- 0.003 0.027 +/- 0.003 0.027 +/- 0.003 0.023 +/- 0.002 0.027 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.003 0.031 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.002
< 0.010
< 0.009
< 0.011
< 0.011
< 0.006
< 0.009
< 0.006
< 0.010
< 0.010
< 0.011
< 0.008
< 0.009
< 0.009 07-10-12 07-17-12 07-25-12 08-01-12 08-08-12 08-15-12 08-23-12 08-29-12 09-05-12 09-11-12 09-19-12 09-26-12 10-03-12 541 566 613 548 543 544 618 461 545 451 644 529 533 0.031 +/- 0.003 0.023 +/- 0.003 0.028 +/- 0.003 0.024 +/- 0.003 0.027 +/- 0.003 0.020 +/- 0.003 0.026 +/- 0.003 0.042 +/- 0.004 0.028 +/- 0.003 0.024 +/- 0.003 0.031 +/- 0.003 0.028 +/- 0.003 0.022 +/- 0.003
< 0.005
< 0.005
< 0.012
< 0.010
< 0.006
< 0.006
< 0.008
<0.010
<0.013
< 0.004
< 0.011
< 0.014
< 0.007 I
I I
I I
U I
I I
U I
I I
I I
I I
1Q 2012 Mean +/- s.d.
0.025 +/- 0.004 04-05-12 04-11-12 04-18-12 04-25-12 05-02-12 05-09-12 05-16-12 05-23-12 05-30-12 06-06-12 06-13-12 06-20-12 06-26-12 07-03-12 534 466 568 545 566 565 578 570 564 554 547 549 472 554 0.015 0.019 0.016 0.019 0.020 0.021 0.021 0.016 0.027 0.010 0.018 0.020 0.025 0.028
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.003
< 0.011
< 0.004
< 0.013
< 0.006
< 0.010
< 0.007
< 0.007
< 0.011
< 0.011
< 0.010
< 0.006
< 0.008
< 0.005
< 0.007
< 0.005 3Q 2012 Mean +/- s.d.
10-10-12 10-17-12 10-24-12 11-01-12 11-08-12 11-14-12 11-21-12 11-28-12 12-05-12 12-12-12 12-20-12 12-26-12 01-02-13 542 537 554 623 519 494 581 554 582 556 628 474 565 0.027 +/- 0.006 0.027 +/- 0.003 0.029 +/- 0.003 0.034 +/- 0.003 0.014 +/- 0.002 0.016 +/- 0.003 0.044 +/- 0.004 0.050 +/- 0.003 0.041 +/- 0.003 0.053 +/- 0.004 0.019 +/- 0.003 0.047 +/- 0.003 0.030 +/- 0.003 0.033 +/- 0.003
< 0.014
< 0.009
< 0.006
< 0.013
< 0.011
< 0.010
< 0.008
< 0.009
< 0.015
< 0.007
< 0.008
< 0.018
< 0.007
< 0.009 2Q 2012 Mean +/- s.d.
0.020 +/- 0.005
< 0.013 4Q 2012 Mean +/- s.d.
Cumulative Average 0.034 +/- 0.013
< 0.018 0.026 C-8 I
PNPP Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31.
Location:
P-7 Units: pCi/m 3 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 01-11-12 01-18-12 01-25-12 02-01-12 02-07-12 02-15-12 02-22-12 02-29-12 03-07-12 03-13-12 03-21-12 03-29-12 589 584 574 592 573 508 649 578 577 568 501 642 657 0.026 +/- 0.003 0.025 +/- 0.003 0.020 +/- 0.003 0.028 +/- 0.003 0.025 +/- 0.003 0.032 +/- 0.003 0.018 +/- 0.002 0.030 +/- 0.003 0.020 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0.019 +/- 0.002 0.016 +/- 0.002
< 0.010
< 0.009
< 0.011
< 0.011
< 0.006
< 0.009
< 0.006
< 0.010
< 0.010
< 0.011
< 0.008
< 0.009
< 0.008 07-10-12 07-17-12 07-25-12 08-01-12 08-08-12 08-15-12 08-23-12 08-29-12 09-05-12 09-11-12 09-19-12 09-26-12 10-03-12 527 590 645 577 577 574 627 477 554 464 665 571 567 0.028 +/- 0.003 0.024 +/- 0.003 0.023 + 0.003 0.018 + 0.003 0.024 +/- 0.003 0.018 +/- 0.003 0.022 + 0.003 0.037 +/- 0.004 0.026 + 0.003 0.022 +/- 0.003 0.027 + 0.002 0.021 +/- 0.003 0.016 + 0.003
< 0.005
< 0.004
< 0.011
< 0.009
< 0.005
< 0.006
< 0.008
< 0.010
< 0.013
< 0.004
< 0.011
< 0.013
< 0.007 1Q 2012 Mean +/- s.d.
04-05-12 04-11-12 04-18-12 04-25-12 05-02-12 05-09-12 05-16-12 05-23-12 05-30-12 06-06-12 06-13-12 06-20-12 06-26-12 07-03-12 560 466 569 545 568 582 592 588 580 587 584 588 505 575 0.023 +/- 0.005 0.016 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.003 0.022 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.014 +/- 0.002 0.024 +/- 0.003 0.011 +/- 0.002 0.016 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.003 0.026 +/- 0.003
< 0.011
< 0.004
< 0.013
< 0.006
<0.010
< 0.007
< 0.007
< 0.011
< 0.010
< 0.009
< 0.006
< 0.008
< 0.005
< 0.007
< 0.005 3Q 2012 Mean +/- s.d.
10-10-12 10-17-12 10-24-12 11-01-12 11-08-12 11-14-12 11-21-12 11-28-12 12-05-12 12-12-12 12-20-12 12-26-12 01-02-13 581 576 582 658 563 480 579 558 561 540 620 441 540 0.024 +/- 0.005 0.024 +/- 0.003 0.024 + 0.003 0.032 +/- 0.003 0.016 +/- 0.002 0.012 0 0.003 0.035 +/- 0.004 0.047 + 0.003 0.039 +/- 0.003 0.054 +/- 0.004 0.018 +/- 0.003 0.044 +/- 0.003 0.027 +/- 0.004 0.032 - 0.003
< 0.013
< 0.008
< 0.005
< 0.012
< 0.011
< 0.009
< 0.009
< 0.009
< 0.015
< 0.007
< 0.008
< 0.025
< 0.007
< 0.009 2Q 2012 Mean +/- s.d.
0.019 +/- 0.004
< 0.013 4Q 2012 Mean +/- s.d.
Cumulative Average 0.031 +/- 0.013
< 0.025 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.
Date Volume Date Volume Collected (ms)
Gross Beta 1-131 Collected (ms)
Gross Beta 1-131 Required LLD 01-04-12 01-11-12 01-18-12 01-25-12 02-01-12 02-07-12 02-15-12 02-22-12 02-29-12 03-07-12 03-13-12 03-21-12 03-29-12 580 586 571 604 575 508 649 582 577 576 503 646 660 0.0075 0.020 +/- 0.003 0.024 +/- 0.003 0.022 +/- 0.003 0.030 +/- 0.003 0.024 +/- 0.003 0.024 +/- 0.003 0.019 + 0.002 0.025 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.022 +/- 0.003 0.019 +/- 0.002 0.018 +/- 0.002 0.050 0.0075
< 0.013
< 0.011
< 0.012
< 0.010
< 0.009
< 0.013
< 0.008
< 0.007
< 0.005
< 0.009
< 0.008
< 0.009
< 0.005 07-10-12 07-17-12 07-25-12 08-01-12 08-08-12 08-15-12 08-23-12 08-29-12 09-05-12 09-11-12 09-19-12 09-26-12 10-03-12 578 590 630 563 573 540 617 458 545 456 623 527 523 0.028 0.023 0.025 0.020 0.027 0.018 0.026 0.036
+ 0.003
+ 0.003
+ 0.003
+ 0.003
+ 0.003
+ 0.003
+ 0.003
+ 0.004 0.050
< 0.012
< 0.008
<0.013
< 0.012
< 0.007
< 0.005
< 0.008
< 0.016
< 0.006
< 0.015
< 0.012
< 0.015
< 0.005 0.027 +/- 0.003 0.026 +/- 0.003 0.027 +/- 0.003 0.023 +/- 0.003 0.019 +/- 0.003 I
I I
I I
I I
I I
I I
I U
1Q 2012 Mean +/- s.d.
04-05-12 04-11-12 04-18-12 04-25-12 05-02-12 05-09-12 05-16-12 05-23-12 05-30-12 06-06-12 06-13-12 06-20-12 06-26-12 07-03-12 575 482 573 546 560 582 589 580 576 573 580 578 493 576 0.022 +/- 0.003 0.013 +/- 0.002 0.018 +/- 0.003 0.016 +/- 0.003 0.018 +/- 0.003 0.022 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.015 +/- 0.003 0.026 +/- 0.003 0.012 +/- 0.002 0.018 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.026 +/- 0.003
< 0.013
< 0.008
< 0.014
< 0.012
< 0.011
< 0.009
< 0.008
< 0.013
< 0.014
< 0.009
< 0.010
< 0.008
<0.010
< 0.009
< 0.009 3Q 2012 Mean +/- s.d.
10-10-12 10-17-12 10-24-12 11-01-12 11-08-12 11-14-12 11-21-12 11-28-12 12-05-12 12-12-12 12-20-12 12-26-12 01-02-13 536 533 539 621 524 465 553 537 555 537 619 461 563 0.025 +/- 0.005 0.031 +/- 0.003 0.027 +/- 0.003 0.037 +/- 0.003 0.017 +/- 0.002 0.015 +/- 0.003 0.041 +/- 0.004 0.051 +/- 0.004 0.044 +/- 0.004 0.051 +/- 0.004 0.021 +/- 0.003 0.050 +/- 0.003 0.026 +/- 0.003 0.032 +/- 0.003
< 0.016
< 0.006
< 0.008
< 0.015
< 0.008
< 0.014
< 0.014
< 0.019
< 0.012
< 0.013
< 0.015
< 0.028
<0.018
< 0.009
< 0.028 2Q 2012 Mean + s.d.
0.019 +/- 0.004
< 0.014 4Q 2012 Mean +/- s.d.
Cumulative Average 0.034 +/- 0.013 0.025 I
I I
C-1 0
PNPP Airborne particulates, analyses for gamma-emitting isotopes.
Collection: Quarterly Composite Units: pCi/m 3
Location PE-1 Quarter 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Req. LLD Lab Code PEAP-2173 PEAP-4439 PEAP-6492 PEAP-8477 Vol. (m3) 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 Vol. (M3) 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 Airborne particulates, analyses for gamma-emitting isotopes.
Collection: Quarterly Composite Units: pCi/m3 Location PE-6 Quarter 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Req. LLD Lab Code PEAP-2177 PEAP-4443 PEAP-6496 PEAP-8481 Vol. (M3) 7437 7632 7136 7209 Be-7 0.053 +/- 0.009 0.077 +/- 0.009 0.072 +/- 0.009 0.051 +/- 0.010 Co-58
< 0.0004
< 0.0004
< 0.0003
< 0.0003 Co-60
< 0.0002
< 0.0003
< 0.0003
< 0.0004 Cs-134
< 0.0004
< 0.0003
< 0.0003
< 0.0003 0.037 Cs-137
< 0.0002
< 0.0004
< 0.0004
< 0.0003 0.045 Location PE-7 Lab Code PEAP-2178 PEAP-4444 PEAP-6497 PEAP-8482 Vol. (M3) 7594 7891 7415 7279 Be-7 0.069 +/- 0.010 0.070 +/- 0.008 0.066 +/- 0.008 0.055 +/- 0.010 Co-58
< 0.0003
< 0.0002
< 0.0003
< 0.0004 Co-60
< 0.0002
< 0.0002
< 0.0003
< 0.0004 Cs-1 34
< 0.0005
< 0.0003
< 0.0004
< 0.0002 0.037 Cs-1 37
< 0.0003
< 0.0003
< 0.0006
< 0.0003 0.045 Location PE-35 Lab Code PEAP-2179 PEAP-4445 PEAP-6498 PEAP-8483 Vol. (M3) 7616 7863 7224 7043 Be-7 0.057 +/- 0.007 0.071 +/- 0.010 0.075 +/- 0.010 0.054 +/- 0.009 Co-58
< 0.0003
< 0.0004
< 0.0004
< 0.0003 Co-60
< 0.0002
< 0.0005
< 0.0006
< 0.0005 Cs-1 34
< 0.0003
< 0.0002
< 0.0003
< 0.0003 0.037 Cs-137
< 0.0003
< 0.0004
< 0.0002
< 0.0002 0.045 I
I I
I I
I I
I I
I I
I I
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 Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-1 37 Ba-1 40 La-1 40 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-1 37 Ba-1 40 La-1 40 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 La-140 PELW-569 12-29-11 01-26-12 2.4 +/- 1.1
< 1.5
< 3.1
< 2.6
< 1.7
< 2.6
< 2.8
< 3.0
< 2.0
< 2.4
< 18.0
< 3.4 PELW-3454 04-26-12 05-31-12 2.1 +/- 0.9
< 1.8
< 5.5
< 2.4
< 1.6
< 3.8
< 6.1
< 3.6
< 2.1
< 2.6
< 11.3
< 6.4 PELW-6083 08-30-12 09-26-12 2.3 +/- 1.2
< 2.4
< 6.0
< 3.1
< 2.9
< 4.8
< 4.8
< 4.4
< 5.8 PELW-988 01-26-12 02-23-12 2.0 +/- 0.8
< 2.2
< 4.0
< 1.5
< 2.0
< 2.1
< 5.8
< 3.0
< 1.6
< 3.4
< 15.6
< 2.4 PELW-3966 05-31-12 06-28-12 1.5 +/- 0.6
< 1.4
< 4.4
< 1.1
< 2.1
< 3.1
< 4.5
< 3.4
< 1.8
< 1.7
< 34.5
< 6.7 PELW-7143 09-26-12 10-25-12 1.5 +/- 0.6
< 2.7
< 6.4
< 2.6
< 2.3
< 3.1
< 5.3
< 3.4
< 4.5 PELW-1659 02-23-12 03-29-12 2.6 +/- 1.1
< 1.8
< 5.1
< 1.9
< 1.5
< 2.1
< 4.9
< 1.9
< 2.4
< 2.6
< 12.1
< 4.6 PELW-4711 06-28-12 07-26-12 2.5 +/- 1.1
< 1.5
< 3.6
< 2.3
< 1.7
< 1.7
< 3.5
< 1.9
< 1.9
< 2.0
< 17.7
< 4.3 PELW-7810 10-25-12 11-29-12 2.6 +/- 1.1
< 2.0
< 4.5
< 2.0
< 2.6
< 5.5
< 3.7
< 3.1
< 3.7 PELW-2461 03-29-12 04-26-12
< 1.9
< 2.2
< 3.3
< 1.9
< 2.1
< 3.4
< 5.0
< 3.0
< 2.3
< 2.3
< 10.4
< 2.5 PELW-5560 07-26-12 08-30-12 1.2 +/- 0.6
< 3.4
< 5.9
< 1.7
< 1.9
< 4.8
< 4.9
< 3.3
< 3.1
< 3.2
< 18.1
< 2.1 PELW-8255 11-29-12 12-27-12 1.4 +/- 0.6
< 2.1
< 4.6
< 2.0
< 1.7
< 1.3
< 2.4
< 2.7
< 2.3 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 Req. LLD 3.0 11 22 11 11 22 22 11 11 C-1 3
PNPP Lake water, analyses for gross beta and gamma emitting isotopes.
Location: P-34 Collection: Monthly composites Units: pCi/L Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-1 37 Ba-1 40 La-1 40 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-137 Ba-1 40 La-1 40 PELW-570 12-29-11 01-26-12 1.9 +/- 0.9
< 4.1
< 6.1
< 3.1
< 2.3
< 3.1
< 5.7
< 4.9
< 3.7
< 2.2
< 12.5
< 3.2 PELW-3456 04-26-12 05-31-12 2.3 +/- 0.8
< 2.7
< 6.0
< 2.6
< 1.9
< 5.7
< 5.4
< 2.5
< 1.9
< 3.9
< 24.0
< 2.6 PELW-6084 08-30-12 09-26-12 2.1 +/- 0.9
< 2.2
< 4.8
< 2.4
< 2.4
< 4.6
< 4.5
< 3.5
< 2.7
< 1.8
< 25.8
< 3.5 PELW-989 01-26-12 02-23-12 2.5 +/- 0.7
< 2.5
< 8.6
< 3.8
< 3.7
< 5.7
< 6.5
< 3.5
< 2.2
< 5.0
< 26.5
< 5.5 PELW-3967 05-31-12 06-28-12 1.2 +/- 0.5
< 1.8
< 4.0
< 2.2
< 1.1
< 1.7
< 3.6
< 3.0
< 1.5
< 2.1
< 21.2
< 5.5 PELW-7144 09-26-12 10-25-12 1.2 +/- 0.5
< 3.2
< 5.0
< 3.4
< 2.8
< 2.3
< 3.2
< 5.1
< 2.4
< 2.4
< 31.7
< 8.1 PELW-1660 02-23-12 03-29-12 1.9 +/- 1.0
< 2.9
< 6.9
< 3.2
< 2.6
< 2.6
< 7.5
< 3.1
< 3.4
< 3.2
< 17.4
< 4.9 PELW-4712 06-28-12 07-26-12 1.9 +/- 0.9
< 1.9
< 4.1
< 1.8
< 1.5
< 2.0
< 3.3
< 2.8
< 1.8
< 2.1
< 19.4
< 4.8 PELW-7811 10-25-12 11-29-12 2.5 +/- 1.1
< 2.1
< 4.4
< 1.0
< 2.1
< 3.0
< 3.8
< 3.0
< 2.1
< 2.9
< 16.5
< 3.3 PELW-2462 03-29-12 04-26-12
< 1.6
< 2.9
< 5.5
< 3.1
< 3.2
< 5.9
< 4.9
< 4.2
< 2.9
< 4.2
< 22.5
< 7.7 PELW-5561 07-26-12 08-30-12 1.4 +/- 0.6
< 2.1
< 4.3
< 2.9
< 2.6
< 2.1
< 4.8
< 3.9
< 2.1
< 3.1
< 21.3
< 4.6 PELW-8256 11-29-12 12-27-12 1.3 +/- 0.5
< 2.4
< 3.9
< 2.8
< 2.0
< 3.4
< 4.4
< 1.4
< 2.9
< 2.8
< 14.4
< 4.2 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 I
I I
I I
I i
I I
I I
I I
I I
I I
I I
Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 C-14
PNPP Lake water, analyses for gross beta and gamma emitting isotopes.
Location: P-36 Collection:
Monthly composites Units: pCi/L Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-1 37 Ba-140 La-140 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-1 40 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-1 40 La-1 40 PELW-571 12-29-11 01-26-12 3.1 +/- 1.1
< 2.8
< 5.5
< 2.6
< 1.9
< 4.1
< 6.9
< 3.9
< 2.5
< 3.8
< 19.6
< 3.6 PELW-3457 04-26-12 05-31-12 2.3 +/- 0.7
< 2.0
< 3.7
< 2.0
< 2.2
< 3.9
< 3.7
< 4.6
< 2.3
< 3.3
< 20.7
< 2.6 PELW-6085 08-30-12 09-26-12 2.4 +/- 1.0
< 1.4
< 5.0
< 2.4
< 1.4
< 3.5
< 4.9
< 2.9
< 2.2
< 3.2
< 30.3
< 5.2 PELW-990 01-26-12 02-23-12 2.4 +/- 0.8
< 3.1
< 8.5
< 2.2
< 2.7
< 6.8
< 7.3
< 2.6
< 2.9
< 4.6
< 13.1
< 4.6 PELW-3968 05-31-12 06-28-12 1.0 +/- 0.5
< 2.2
< 5.3
< 2.6
< 1.4
< 3.5
< 4.3
< 4.0
< 2.4
< 2.9
< 33.6
< 9.6 PELW-7145 09-26-12 10-25-12 1.0 +/- 0.5
< 2.4
< 7.5
< 3.1
< 1.6
< 4.3
< 4.3
< 4.5
< 3.3
< 3.5
< 24.4
< 5.4 PELW-1661 02-23-12 03-29-12 2.4 +/- 1.0
< 1.4
< 3.2
< 1.6
< 1.9
< 2.3
< 2.9
< 1.4
< 1.5
< 1.6
< 8.3
< 3.2 PELW-4713 06-28-12 07-26-12 2.0 +/- 1.0
< 1.6
< 3.7
< 1.5
< 1.7
< 1.9
< 2.6
< 2.5
< 1.4
< 1.5
< 14.8
< 2.9 PELW-7812 10-25-12 11-29-12 2.5 +/- 1.0
< 2.0
< 6.7
< 2.3
< 2.0
< 3.3
< 5.5
< 3.5
< 2.8
< 2.2
< 25.9
< 4.3 PELW-2463 03-29-12 04-26-12 2.7 +/- 1.0
< 2.2
< 5.4
< 1.8
< 2.3
< 4.6
< 5.6
< 4.4
< 2.2
< 3.3
< 18.9
< 2.3 PELW-5562 07-26-12 08-30-12 1.1 +/- 0.5
< 1.9
< 7.5
< 1.8
< 2.9
< 4.5
< 3.7
< 3.7
< 2.6
< 3.3
< 19.9
< 2.5 PELW-8257 11-29-12 12-27-12 0.9 +/- 0.5
< 2.2
< 3.7
< 2.2
< 2.0
< 2.4
< 3.3
< 2.5
< 2.2
< 2.6
< 15.1
< 2.9 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 C-15
PNPP Lake water, analyses for gross beta and gamma emitting isotopes.
Location: P-59 Collection:
Monthly composites Units: pCi/L Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-1 37 Ba-1 40 La-1 40 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-1 37 Ba-1 40 La-1 40 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 NSa 01-27-11 PELW-3458 04-26-12 05-31-12 2.1 +/- 0.8
< 2.3
< 3.6
< 1.7
< 1.0
< 4.5
< 4.7
< 3.3
< 3.2
< 2.8
< 15.3
< 2.6 PELW-6086 08-29-12 09-26-12
< 1.6
< 2.8
< 5.2
< 1.4
< 2.6
< 3.7
< 5.8
< 3.1
< 2.2
< 2.5
< 21.4
< 4.3 PELW-991 01-26-12 02-23-12 2.5 +/- 0.7
< 2.7
< 2.8
< 2.3
< 2.2
< 2.8
< 3.4
< 2.8
< 2.0
< 2.8
< 16.1
< 3.7 PELW-3969 05-31-12 06-28-12 1.4 +/- 0.5
< 1.1
< 2.7
< 0.7
< 0.9
< 2.3
< 2.6
< 1.9
< 0.9
< 1.3
< 12.6
< 4.0 PELW-7146 09-26-12 10-24-12
< 0.9
< 2.3
< 3.1
< 2.7
< 2.4
< 3.8
< 2.1
< 3.2
< 2.5
< 2.2
< 31.7
< 8.9 PELW-1662 02-23-12 03-29-12 2.9 +/- 1.0
< 2.3
< 4.7
< 1.9
< 2.7
< 4.8
< 6.4
< 2.8
< 1.9
< 2.5
< 24.1
< 2.4 PELW-4714 06-28-12 07-26-12 1.9 +/- 0.9
< 1.8
< 4.6
< 1.3
< 1.9
< 2.9
< 4.3
< 2.9
< 2.0
< 2.6
< 19.5
< 4.2 PELW-7813 10-24-12 11-28-12 2.4 +/- 0.9
< 2.8
< 3.0
< 2.7
< 2.2
< 3.9
< 4.4
< 2.7
< 1.8
< 2.2
< 12.5
< 3.3 PELW-2464 03-29-12 04-26-12 2.1 +/- 0.9
< 2.0
< 3.3
< 3.3
< 1.9
< 4.4
< 5.8
< 2.9
< 3.1
< 3.3
< 19.4
< 2.1 PELW-5563 07-26-12 08-29-12 1.5 +/- 0.6
< 3.0
< 2.6
< 2.9
< 2.9
< 2.7
< 5.0
< 3.7
< 1.7
< 2.8
< 22.5
< 2.9 PELW-8258 11-28-12 12-27-12 1.2 +/- 0.5
< 1.7
< 3.2
< 2.4
< 2.2
< 2.3
< 4.8
< 2.5
< 2.0
< 2.5
< 17.1
< 3.4 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 I
U I
I I
I I
I I
I I
I I
I I
I I
I I
Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 a No sample available, shoreline frozen.
C-1 6
PNPP Lake water, analyses for gross beta and gamma emitting isotopes.
Location: P-60 Collection:
Monthly composites Units: pCi/L Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-1 37 Ba-1 40 La-1 40 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-1 37 Ba-1 40 La-140 Lab Code Start Date End Date Gross beta Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-1 40 La-140 NSa 01-27-11 PELW-3459 04-26-12 05-31-12 1.2 +/- 0.4
< 2.3
< 4.0
< 2.5
< 1.6
< 3.6
< 6.9
< 4.6
< 3.0
< 3.0
< 18.8
< 6.7 PELW-6087 08-29-12 09-26-12 1.9 +/- 1.0
< 2.8
< 2.5
< 2.0
< 1.6
< 2.0
< 3.3
< 3.0
< 2.1
< 2.5
< 19.9
< 4.3 PELW-992 01-26-12 02-23-12 3.7 +/- 0.8
< 2.6
< 3.7
< 2.7
< 1.1
< 3.9
< 2.2
< 2.3
< 2.2
< 3.1
< 18.2
< 2.3 PELW-3971 05-31-12 06-28-12
< 1.9
< 1.4
< 2.4
< 1.9
< 1.5
< 3.1
< 2.4
< 2.1
< 1.5
< 1.6
< 14.4
< 6.3 PELW-7147 09-26-12 10-24-12 1.4 +/- 0.6
< 2.2
< 6.0
< 3.9
< 1.9
< 3.2
< 3.4
< 3.3
< 3.2
< 2.6
< 23.0
< 6.8 PELW-1663 02-23-12 03-29-12 3.1 +/- 1.1
< 2.3
< 3.5
< 2.0
< 2.6
< 5.8
< 3.6
< 2.1
< 3.1
< 3.1
< 12.2
< 5.9 PELW-4715 06-28-12 07-26-12
< 1.8
< 4.4
< 3.6
< 2.4
< 3.0
< 4.5
< 5.2
< 1.9
< 2.9
< 3.1
< 23.2
< 3.8 PELW-7814 10-24-12 11-28-12 3.5 +/- 1.0
< 2.5
< 4.8
< 2.7
< 2.5
< 4.3
< 5.3
< 2.6
< 2.4
< 3.1
< 12.5
< 4.5 PELW-2465 03-29-12 04-26-12
< 1.8
< 3.4
< 2.2
< 3.4
< 2.5
< 3.4
< 3.6
< 3.2
< 2.6
< 3.3
< 24.0
< 2.7 PELW-5564 07-26-12 08-29-12 1.8 +/- 0.6
< 2.8
< 3.8
< 0.8
< 2.5
< 2.4
< 3.6
< 3.2
< 2.8
< 3.0
< 17.1
< 3.9 PELW-8259 11-28-12 12-27-12 1.6 +/- 0.6
< 2.0
< 1.9
< 1.4
< 2.1
< 3.8
< 3.4
< 1.7
< 1.6
< 2.2
< 11.3
< 2.8 Req. LLD 3.0 11 22 11 11 22 22 11 13 45 11 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 Req. LLD 3.0 11 22 11 11 22 22 11 11 13 45 11 a No sample available, shoreline frozen.
C-17
PNPP Lake Water, analysis for tritium.
Collection: Quarterly composites of monthly collections.
Units: pCi/L Required limit of detection:
1500 pCi/L Location P-28 Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code PELW-1692 PELW-4197 PELW-6257 PELW-8281 H-3
< 144
< 149
< 150
< 139 Location P-34 Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code PELW-1693 PELW-4198 PELW-6258 PELW-8282 H-3
< 144
< 149
< 150
< 139 Location P-36 Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code PELW-1694 PELW-4199 PELW-6260 PELW-8283 H-3
< 144
< 149
< 150
< 139 Location P-59 Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code PELW-1695 PELW-4200 PELW-6261 PELW-8284 H-3
< 144
< 149
< 150
< 139 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 I
I I
I I
II I
I I
I 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 02-06-12 03-05-12 04-02-12 04-16-12 05-07-12 05-22-12 06-04-12 06-18-12 07-02-12 07-16-12 08-06-12 08-20-12 09-04-12 09-17-12 10-02-12 10-15-12 11-05-12 12-03-12 NDa ND ND PEMI-1684 PEMI-2095 PEMI-2679 PEMI-3084 PEMI-3447 PEMI-3678 PEMI-3956 PEMI-4205 PEMI-4939 PEMI-5261 PEMI-5556 PEMI-5903 PEMI-6209 PEMI-6690 ND ND
< 0.3
< 0.3
< 0.4
<0.2
< 0.4
< 0.2
< 0.4
< 0.4
< 0.2
< 0.3
<0.2
< 0.4
< 0.4
< 0.5
< 2.6
<3.1
<3.2
< 3.0
<3.0
<3.2
< 2.9
< 4.2
< 3.5
< 2.5
<2.9
<3.2
<2.3
<3.0
<3.1
<4.1
<3.2
<4.0
< 3.8
<4.2
< 3.3
< 4.8
<4.0
<3.9
<4.5
< 2.9
< 3.4
< 3.0
< 15.5
< 22.9
< 11.8
< 16.7
< 25.1
< 24.2
< 24.0
< 29.2
< 39.8
< 20.7
< 18.1
< 25.4
< 39.7
< 28.0
< 2.4
<2.5
<3.3
<4.4
< 1.9
< 6.5
<7.1
<2.4
<5.2
< 1.4
< 4.7
< 3.3
< 4.5
< 5.7 1281 +/-111 1620 +/- 124 1634 +/-114 1781 +/-119 1720 +/-135 1813 +/-111 1891 +/-125 1641 +/-118 1822 +/- 117 1841 +/-114 1872 +/- 117 1911 +/- 106 1909 +/-123 2028 +/-117 P-19 01-03-12 02-06-12 03-05-12 04-02-12 04-16-12 05-07-12 05-21-12 06-04-12 06-18-12 07-02-12 07-16-12 08-06-12 08-20-12 09-04-12 11-05-12 12-03-12 PEMI-65 PEMI-721 PEMI-1147 PEMI-1656 PEMI-2096 PEMI-2680 PEMI-3085 PEMI-3448 PEMI-3679 PEMI-3957 PEMI-4206 PEMI-4940 PEMI-5262 PEMI-5557 PEMI-7170 PEMI-7774
< 0.4
< 0.3
< 0.3
< 0.2
< 0.4
< 0.4
< 0.2
<0.3
<0.2
< 0.3
<0.2
< 0.3
< 0.3
< 0.2
< 0.3
< 0.5
<3.3
< 2.8
<2.5
< 2.8
< 3.6
< 2.7
< 2.9
<2.5
<2.7
<2.6
<2.7
< 2.7
< 2.7
< 2.9
< 3.5
< 3.3
< 3.5
< 2.7
< 2.9
<4.2
<3.9
<3.9
<3.3
< 3.8
<3.2
< 3.0
< 3.8
< 3.0
<2.3
<3.2
<3.9
<4.1
< 28.1
< 18.3
< 18.4
< 14.8
< 19.7
< 22.1
< 23.0
< 19.4
< 25.0
< 18.5
< 27.4
< 27.1
< 21.7
< 15.6
< 10.5
< 20.9
< 3.5
< 2.5
<4.1
<2.6
< 1.9
< 1.9
< 1.8
< 2.5
< 4.8
< 4.0
< 2.9
<6.1
< 3.4
<2.8
<2.4
<3.7 1289 +/- 107 1369 +/- 92 1403 +/- 102 1277 +/- 115 1453 +/- 116 1359 +/- 112 1421 +/- 109 1255 +/- 106 1369 +/- 101 1400 +/- 102 1439 +/- 114 1376 +/- 87 1376 +/-113 1413 +/-95 1316 +/- 97 1321 +/- 108 a ND = No data, no milk available.
C-1 9
PNPP Milk, analyses for iodine-131 and gamma-emitting isotopes (continued).
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-41 01-03-12 02-06-12 03-05-12 04-02-12 04-16-12 05-07-12 05-21-12 06-04-12 06-18-12 07-02-12 07-16-12 08-06-12 08-20-12 09-04-12 09-17-12 10-02-12 10-15-12 11-05-12 12-03-12 NDa ND ND PEMI-1657 PEMI-2097 PEMI-2681 PEMI-3086 PEMI-3449 PEMI-3680 PEMI-3958 PEMI-4207 PEMI-4941 PEMI-5263 PEMI-5558 PEMI-5905 ND ND ND ND
< 0.2
< 0.3
< 0.4
< 0.2
<0.3
< 0.2
< 0.3
<0.3
< 0.4
< 0.3
< 0.2
< 0.4
<4.1
< 3.6
<2.5
<2.1
<2.1
<2.7
<3.2
<3.0
<2.6
<4.9
<3.2
<3.2
<4.8
< 4.4
<3.4
<3.4
<3.7
<4.0
<4.1
<3.5
< 3.4
< 3.8
< 3.8
<4.6
< 20.2
< 10.9
< 17.1
< 10.6
<11.1
< 36.2
< 26.2
< 22.7
< 35.1
< 34.8
< 19.4
< 38.5
<4.2
< 4.7
< 2.7
< 1.8
< 1.7
< 5.3
<4.2
<8.1
<4.3
<3.2
< 2.8
<7.9 1630 +/- 126 1868 +/- 123 1776 +/- 129 1810 +/-120 1828 +/- 130 1847 +/- 119 1801 +/-113 1825 +/-121 1927 +/- 113 1904 +/-139 1800 +/-135 1924 +/- 121 I
I I
I I
I I
I I
I I
I I
I I
I I
I P-51 01-03-12 02-06-12 03-05-12 04-02-12 04-16-12 05-07-12 05-21-12 06-04-12 06-18-12 07-02-12 07-16-12 08-06-12 08-20-12 09-04-12 09-17-12 10-02-12 10-15-12 11-05-12 12-03-12 PEMI-66 PEMI-722 PEMI-1148 PEMI-1658 PEMI-2098 PEMI-2682 PEMI-3087 PEMI-3450 PEMI-3681 PEMI-3959 PEMI-4208 PEMI-4942 PEMI-5264 PEMI-5559 PEMI-5906 PEMI-6211 PEMI-6693 PEMI-7171 PEMI-7775
< 0.3
<0.3
<0.3
< 0.2
<0.2
<0.4
<0.5
<0.4
<0.2
<0.3
< 0.3
<0.3
<0.3
< 0.2
< 0.3
< 0.4
< 0.4
< 0.3
< 0.5
<2.7
<3.0
<2.2
<2.5
< 1.6
< 3.0
<2.8
< 2.9
< 2.2
<2.4
<2.4
<2.1
< 3.0
< 3.6
< 2.3
< 2.5
< 2.8
< 4.3
< 4.9
<4.1
<4.1
<3.1
< 2.8
< 2.9
< 3.4
< 3.8
<2.3
< 2.8
< 2.3
< 2.8
< 2.9
< 3.7
< 3.0
< 1.6
< 2.6
< 1.8
< 3.9
<5.3
< 25.4
< 16.8
<11.2
< 18.0
< 16.3
<11.5
<11.0
< 21.0
< 31.4
< 14.5
< 32.8
< 30.1
< 29.7
< 18.4
< 31.4
< 29.0
< 28.1
< 18.0
< 31.9
<3.6
<4.4
<2.6
< 3.7
<3.7
< 3.9
<2.2
< 1.9
<3.5
<3.6
<5.1
<5.0
<5.5
<2.5
<6.3
<6.1
<3.2
< 1.8
<2.5 1051 +/- 90 802 +/- 83 848 +/- 73 810 +/- 90 851 +/- 85 946 +/- 96 972 +/- 101 1004 +/- 96 921 +/- 80 775 +/- 66 1377 +/- 102 1397 +/- 93 927 +/- 98 956 +/- 97 818 +/- 85 804 +/- 74 738 +/- 77 987 +/- 94 626 +/- 103 a ND = No data, no milk available.
C-20
PNPP Food Products, analyses for gamma emitting isotopes.
Collection:
Monthly Location: P-2 Units: pCi/kg wet Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-1 34 Cs-137 Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-137 PEVE-4222 07-13-12 Swiss Chard 163 +/- 82 7230 +/- 324
< 6.3
< 8.0
< 16.2
< 7.6
< 9.1 PEVE-5166 08-15-12 Collard Greens
< 77 4260 +/- 277
< 7.7
< 4.8
< 12.7
< 6.6
< 9.0 PEVE-5835 09-12-12 Swiss Chard 361 +/- 85 5582 +/- 302
< 6.4
< 4.9
< 20.4
< 7.6
< 8.8 PEVE-6669 10-16-12 Collard Greens
< 7.0
< 8.4
< 33.6
< 8.6
< 8.6 PEVE-4224 07-13-12 Japan. Greens 306 +/- 81 4641 +/- 244
< 6.3
< 6.8
< 14.0
< 6.9
< 8.2 PEVE-5168 08-15-12 Swiss Chard 255 +/- 85 4924 +/- 286
< 4.7
< 7.2
< 13.5
< 5.5
< 8.6 PEVE-5836 09-12-12 Turnips 582 +/- 95 4516 +/- 233
< 7.4
< 4.8
< 26.8
< 4.6
< 6.4 PEVE-6671 10-16-12 Swiss Chard
< 8.4
< 7.5
< 42.8
< 8.3
< 12.2 PEVE-5164 08-15-12 Turnip Greens 562 +/- 149 4522 +/- 378
< 9.9
< 7.6
< 13.0
< 11.6
< 11.7 PEVE-5833 09-12-12 Japan. Greens 563 +/- 99 3421 +/- 222
< 8.9
< 4.5
< 28.5
< 4.8
< 6.7 PEVE-6667 10-16-12 Japan. Greens 870 +/- 127 4537 +/- 306
< 9.5
< 10.0
< 35.1
< 6.2
< 9.1 PEVE-5165 08-15-12 Japan. Greens 510 +/- 120 3711 +/- 282
< 8.3
< 4.8
< 21.7
< 6.6
< 7.9 PEVE-5834 09-12-12 Collard Greens 210 +/- 120 4209 +/- 284
< 8.3
< 7.1
< 35.0
< 8.3
< 8.1 PEVE-6668 10-16-12 Turnip Greens 859 +/- 128 6370 +/- 347
< 7.1
< 5.9
< 28.3
< 6.5
< 8.7 Req. LLD 45 45 60 Req. LLD 45 45 60 Lab Code Date Collected Sample Type Req. LLD Be-7 K-40 Co-58 Co-60 1-131 Cs-1 34 Cs-1 37 45 45 60 Lab Code Date Collected Sample Type Co-58 Co-60 1-131 Cs-134 Cs-137 Req. LLD 45 45 60 C-21
PNPP Food Products, analyses for gamma emitting isotopes.
Collection:
Monthly Location: P-16 Units: pCi/kg wet Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-137 Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-137 PEVE-3798 06-20-12 Japan. Greens
< 102 5931 +/- 377
< 6.9
< 3.5
< 11.9
< 6.1
< 9.4 PEVE-4226 07-13-12 Japan. Greens 314 +/- 91 5339 +/- 291
< 7.4
< 10.9
< 10.9
< 4.8
< 8.4 PEVE-5171 08-15-12 Japan. Greens 336 +/- 77 4967 +/- 320
< 4.6
< 6.8
< 11.6
< 8.1
< 9.9 PEVE-6672 10-16-12 Swiss Chard 736 +/- 142 5018 +/- 357
< 7.6
< 7.0
< 24.6
< 7.9
< 13.0 PEVE-3800 06-20-12 Swiss Chard
< 127 7174 +/- 452
< 7.9
< 12.3
< 20.9
< 8.1
< 13.8 PEVE-4227 07-13-12 Swiss Chard 213 +/- 99 5498 +/- 275
< 8.9
< 7.8
< 14.7
< 7.5
< 10.5 PEVE-5837 09-12-12 Japan. Greens 501 +/- 83 4394 +/- 239
< 5.9
< 5.8
< 17.8
< 5.1
< 7.0 PEVE-6673 10-16-12 Japan. Greens 749 +/- 151 6092 +/- 359
< 10.8
< 12.2
< 27.3
< 10.2
< 8.2 PEVE-3801 06-20-12 Collard Greens
< 96 5107 +/- 333
< 12.3
< 11.1
< 19.1
< 7.1
< 7.9 PEVE-5169 08-15-12 Collard Greens
< 75 3788 +/- 253
< 6.1
< 6.0
< 11.5
< 5.6
< 6.9 PEVE-5838 09-12-12 Swiss Chard 300 +/- 84 4964 +/- 282
< 8.1
< 7.0
< 26.7
< 6.2
< 9.1 PEVE-6674 10-16-12 Collard Greens 598 +/- 116 3320 +/- 273
< 5.5
< 7.4
< 31.8
< 9.8
< 7.2 PEVE-4225 07-13-12 Collard Greens
< 79 4746 +/- 279
< 8.0
< 7.2
< 17.3
< 7.4
< 8.9 PEVE-5170 08-15-12 Swiss Chard 215 +/- 115 5652 +/- 387
< 7.1
< 10.4
< 16.3
< 11.0
< 9.7 PEVE-5840 09-12-12 Collard Greens
< 91 3780 +/- 293
< 8.3
< 3.7
< 24.3
< 8.1
< 7.3 45 45 60 Req. LLD Req. LLD I
I I
I I
I I
I I
I 45 45 60 Lab Code Date Collected Sample Type Req. LLD I
Be-7 K-40 Co-58 Co-60 1-131 Cs-1 34 Cs-137 45 45 60 Lab Code Date Collected Sample Type Req. LLD I
I I
I I
I I
Be-7 K-40 Co-58 Co-60 1-131 Cs-1 34 Cs-1 37 45 45 60 C-22
PNPP Food Products, analyses for gamma emitting isotopes.
Collection:
Monthly Location:
P-18 Units: pCi/kg wet Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-1 37 Lab Code Date Collected Sample Type PEVE-3802 06-20-12 Japan. Greens 443 +/- 152 7999 +/- 494
< 12.8
< 15.9
< 20.4
< 13.9
< 11.2 PEVE-5173 08-15-12 Swiss Chard 372 +/- 93 5404 +/- 301
< 5.4
< 4.1
< 14.1
< 6.2
< 8.7 PEVE-5843 09-12-12 Collard Greens PEVE-4228 07-13-12 Japan. Greens 307 +/- 61 6843 +/- 256
< 5.8
< 5.6
< 10.8
< 5.4
< 6.6 PEVE-5174 08-15-12 Japan. Greens 401 + 99 5127 +/- 323
< 6.3
< 6.6
< 13.9
< 8.0
< 8.5 PEVE-6675 10-16-12 Collard Greens Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-1 37 PEVE-4229 07-13-12 Swiss Chard 290 +/- 86 9645 +/- 358
< 12.5
< 10.3
< 16.6
< 6.4
< 7.8 PEVE-5841 09-12-12 Swiss Chard 452 +/- 85 7473 +/- 325
< 8.4
< 7.6
< 19.0
< 6.7
< 6.6 PEVE-6676 10-16-12 Japan. Greens 570 +/- 113 5993 +/- 349
< 6.7
< 5.7
< 25.6
< 8.2
< 12.5 PEVE-5172 08-15-12 Collard Greens 177 +/- 68 4974 +/- 317
< 7.1
< 7.9
< 15.6
< 5.4
< 8.8 PEVE-5842 09-12-12 Japan. Greens 395 +/- 81 5899 +/- 304
< 6.6
< 7.6
< 24.4
< 6.8
< 6.2 PEVE-6677 10-16-12 Swiss Chard 660 +/- 144 7279 +/- 419
< 7.3
< 9.7
< 37.9
< 6.4
< 11.5 Req. LLD Req. LLD 45 45 60 Req. LLD 45 45 60 Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-137 288 +
4146 +
84 250 6.8 7.2 21.8 5.2 7.2 430 +/-
5823 +/-
110 287 7.2 7.0 18.4 5.2 7.0 45 45 60 C-23
PNPP Food Products, analyses for gamma emitting isotopes.
Collection: Monthly Location:
P-20 Units:
pCi/kg wet Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-1 34 Cs-1 37 PEVE-4230 07-13-12 Japan. Greens 251 +/- 77 4611 +/- 230
< 5.4
< 7.5
< 14.9
< 5.5
< 7.0 PEVE-5844 09-12-12 Collard Greens 239 +/- 76 4027 +/- 219
< 5.9
+/- 6.7
< 23.1
< 4.5
< 5.0 PEVE-5175 08-15-12 Japan. Greens 262 +/- 79 3260 +/- 269
< 5.1
< 6.8
< 17.0
< 9.2
< 9.2 PEVE-5845 09-12-12 Japan. Greens 429 +/- 75 3839 +/- 250
< 5.9
< 7.6
< 17.0
< 5.6
< 4.1 PEVE-5176 08-15-12 Turnip Greens 337 +/- 90 4063 +/- 299
< 8.0
< 9.0
< 12.9
< 7.4
< 10.5 PEVE-6678 10-16-12 Japan. Greens 850 +/- 135 5547 +/- 362
< 5.2
< 12.0
< 39.5
< 7.8
< 12.0 PEVE-5177 08-15-12 Collard Greens
< 143 3439 +/- 332
< 5.9
< 7.5
< 25.3
< 7.7
< 11.1 PEVE-6679 10-16-12 Collard Greens 301 +/- 107 4016 +/- 301
< 11.4
< 7.1
< 36.2
< 10.3
< 6.9 Req. LLD 45 45 60 Lab Code Date Collected Sample Type Req. LLD Be-7 K-40 Co-58 Co-60 1-131 Cs-1 34 Cs-1 37 45 45 60 I
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PNPP Food Products, analyses for gamma emitting isotopes.
Collection:
Monthly Location: P-37 Units: pCi/kg wet Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-137 Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-1 34 Cs-137 PEVE-3803 06-20-12 Japan. Greens
< 95 4942 +/- 291
< 6.5
< 7.5
< 12.6
< 7.1
< 8.9 PEVE-4232 07-11-12 Collard Greens
< 74 3636 +/- 255
< 4.0
< 7.4
< 10.1
< 7.6
< 9.2 PEVE-5180 08-15-12 Collard Greens
< 111 5160 +/- 327
< 8.2
< 10.4
< 23.9
< 7.5
< 11.0 PEVE-6680 10-16-12 Swiss Chard 602 +/- 125 3016 +/- 243
< 8.8
< 9.1
< 25.7
< 7.2
< 10.2 PEVE-3804 06-20-12 Swiss Chard
< 98 4358 +/- 369
< 6.7
< 2.7
< 15.4
< 4.5
< 9.1 PEVE-4233 07-11-12 Swiss Chard 287 +/- 81 3100 +/- 236
< 8.0
< 4.4
< 14.0
< 8.0
< 9.4 PEVE-5846 09-12-12 Swiss Chard 246 +/- 86 3802 +/- 247
< 4.1
< 4.2
< 23.7
< 6.2
< 8.1 PEVE-6681 10-16-12 Collard Greens 106 +/- 58 4388 +/- 169
< 3.9
< 4.9
< 20.7
< 4.4
< 6.3 PEVE-3805 06-20-12 Collard Greens
< 92 4011 +/- 322
< 6.5
< 3.9
< 12.0
< 7.7
< 9.1 PEVE-5178 08-15-12 Swiss Chard 386 +/- 108 3282 +/- 314
< 5.1
< 5.1
< 19.8
< 9.9
< 9.8 PEVE-5847 09-12-12 Collard Greens
< 74 3724 +/- 180
< 4.5
< 4.6
< 18.4
< 4.3
< 6.8 PEVE-6682 10-16-12 Japan. Greens 412 +/- 49 4754 +/- 164
< 5.7
< 5.3
< 21.7
< 4.9
< 5.5 PEVE-4231 07-11-12 Japan. Greens 216 +/- 57 3604 +/- 214
< 4.7
< 5.5
< 10.5
< 6.0
< 8.8 PEVE-5179 08-15-12 Japan. Greens 296 +/- 132 5366 +/- 449
< 7.4
< 6.6
< 14.0
< 9.5
< 12.2 PEVE-5848 09-12-12 Japan. Greens Req. LLD Req. LLD 45 45 60 45 45 60 Lab Code Date Collected Sample Type Req. LLD Be-7 K-40 Co-58 Co-60 1-131 Cs-1 34 Cs-1 37 150 +/-
3781 +/-
64 221 7.0 3.2 25.5 5.4 7.0 45 45 60 Lab Code Date Collected Sample Type Req. LLD Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-137 45 45 60 C-25
PNPP Food Products, analyses for gamma emitting isotopes.
Collection: Monthly Location:
P-70 Units: pCi/kg wet Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-1 34 Cs-1 37 Lab Code Date Collected Sample Type, Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-137 PEVE-3806 06-20-12 Japan. Greens 227 +/- 99 5673 +/- 347
< 7.0
< 7.5
< 16.7
< 8.4
< 10.0 PEVE-4234 07-13-12 Swiss Chard 333 +/- 95 9190 +/- 385
< 10.2
< 8.6
< 13.2
< 6.3
< 10.4 PEVE-5181 08-15-12 Japan. Greens 1028 +/- 128 5432 +/- 337
< 10.3
< 6.3
< 13.0
< 7.1
< 10.4 PEVE-5849 09-12-12 Collard Greens 150 +/- 75 4774 +/- 324
< 6.9
< 9.6
< 36.8
< 8.8
< 10.2 PEVE-3807 06-20-12 Swiss Chard 167 +/- 72 8047 +/- 427
< 4.3
< 5.3
< 13.3
< 7.0
< 8.7 PEVE-4235 07-13-12 Japan. Greens 557 +/- 92 6273 +/- 271
< 4.4
< 6.0
< 10.9
< 6.6
< 6.2 PEVE-5182 08-15-12 Turnip Greens 2038 +/- 358 5014 +/- 304
< 12.8
< 6.2
< 0.0
< 7.2
< 8.6 PEVE-5850 09-12-12 Swiss Chard 406 +/- 124 7941 +/- 407
< 12.0
< 4.8
< 31.2
< 7.6
< 10.6 PEVE-3808 06-20-12 Turnip Greens 333 +/- 96 6642 +/- 413
< 6.8
< 6.5
< 16.0
< 5.7
< 8.8 PEVE-4236 07-13-12 Collard Greens 269 +/- 98 5581 +/- 275
< 8.4
< 7.1
< 9.0
< 7.4
< 8.7 PEVE-5183 08-15-12 Collard Greens
< 75 4630 +/- 318
< 7.5
< 6.0
< 9.4
< 7.1
< 9.7 PEVE-5851 09-12-12 Turnips 715 +/- 100 5954 +/- 278
< 7.2
< 7.3
< 21.8
< 5.2
< 7.1 PEVE-3809 06-20-12 Collard Greens
< 76 7014 +/- 364
< 5.5
< 5.2
< 13.3
< 8.5
< 7.4 PEVE-4237 07-13-12 Turnip Greens 739 +/- 99 6864 +/- 281
< 5.8
< 4.3
< 11.6
< 6.8
< 8.5 PEVE-5184 08-15-12 Swiss Chard 450 + 121 6647 +/- 393
< 6.1
< 11.3
< 14.2
< 8.6
< 10.6 PEVE-6683 10-16-12 Collard Greens 73 +/- 41 4059 +/- 145
< 4.5
< 4.1
< 13.2
< 4.1
< 5.2 45 45 60 Req. LLD Req. LLD U
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PNPP Food Products, analyses for gamma emitting isotopes.
Collection:
Monthly Location: P-70 Units: pCi/kg wet Lab Code Date Collected Sample Type Be-7 K-40 Co-58 Co-60 1-131 Cs-134 Cs-137 PEVE-6684 10-16-12 Turnip Greens 1356 +/- 160 5522 +/- 329
< 7.5
< 7.8
< 29.5
< 7.1
< 6.0 PEVE-6685 10-16-12 Swiss Chard 845 +/- 142 7663 +/- 396
< 7.5
< 11.1
< 39.7
< 9.1
< 11.7 Req. LLD 45 45 60 C-27
PNPP Fish, analyses for gamma emitting isotopes.
Collection: Annually Units: pCi/kg wet Location P-25 Lab Code Date Collected Sample Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-1 34 Cs-1 37 PEF-5373 08-23-12 Yellow Perch 1580 +/- 325
< 17.2
< 40.2
< 11.9
< 7.2
< 16.5
< 13.5
< 13.8 Freshwater Drum 959 +/- 277
< 19.4
< 46.4
< 10.9
< 7.8
< 32.1
< 11.2
< 14.2 PEF-5374 08-23-12 Req. LLD 94 195 97 97 195 97 112 Location P-32 Lab Code PEF-5375 Date Collected 08-20-12 Req. LLD Sample Type Freshwater Drum K-40 1257 +/- 311 Mn-54
< 14.2 94 Fe-59
< 46.7 195 Co-58
< 13.3 97 Co-60
< 13.7 97 Zn-65
< 21.0 195 Cs-134
< 17.7 97 Cs-137
< 19.9 112 I
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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 Date Collected K-40 Co-58 Co-60 Cs-134 Cs-137 PEBS-3813 06-19-12 16956 +/- 487
< 19.2
< 21.2
< 13.7 414.7 +/- 21.6 PEBS-6187 09-11-12 20844 +/- 807
< 29.2
< 8.4
< 20.0 529.6 +/- 41.1 Req. LLD 50 40 112 135 C-29
PNPP Sediments, analyses for gamma emitting isotopes.
Collection: Semiannually Units: pCi/kg dry Location P-64 Lab Code PEBS-2972 PEBS-6188 Date Collected 05-15-12 09-17-12 Req. LLD K-40 9384 +/- 512 8464 +/- 445 Co-58
< 20.1
< 15.3 50 Co-60
< 12.0
< 11.4 40 Cs-134
< 11.7
< 12.0 112 Cs-137
< 14.8
< 11.0 135 Location P-65 Lab Code PEBS-2973 PEBS-6189 Date Collected 05-15-12 09-17-12 Req. LLD K-40 9167 +/- 501 7853 +/- 440 Co-58
< 16.6
< 14.7 50 Co-60
< 6.4
< 12.1 40 Cs-134
< 14.0
< 11.9 112 Cs-137
< 13.4
< 13.6 135 I
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C-30
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 Table 2 provides information on the nuclide composition for the liquid radioactive effluent system releases. If a radionuclide was not present at a level "greater than or equal to the LLD" (>LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, LLDs were met, or were below the levels required by the ODCM. Table 2a provides information specific to radioactive effluent batch releases while Table 2b provides information specific to continuous radioactive effluent releases.
Table 2: Summation of All Liquid Effluent Releases QUARTER QUARTER QUARTER QUARTER EST.
1 2
3 4
TOTAL
- ERROR,
(%)
A.
Fission and Activation Products
- 1. Total Released, Ci 1.43E-03 2.55E-02 5.21 E-03 5.34E-03 1.OOE+01 (excluding tritium, gases, alpha)
- 2.
Average Diluted Concentration, 8.80E-11 8.68E-10 1.61 E-10 2.63E-10 NA
.. Ci/mL *
- 3.
Percent of Applicable Limit, %
2.56E-03 2.10E-02 4.75E-03 8.14E-03 NA B.
- 1. Total Released, Ci 1.08E+01 1.49E+01 6.51 E+00 3.59E+00 1.O0E+01
- 2.
Average Diluted Concentration, 6.63E-07 5.07E-07 2.02E-07
- 1. 77E-07 4Ci/mL
- 3.
Percent of Applicable Limit, %
6.63E-02 5.07E-02 2.02E-02 1.77E-02 C.
Dissolved and Entrained Gases
- 1. Total Released, Ci
<LLD
<LLD
<LLD 1.62E-07 1.OOE+01
- 2.
Average Diluted Concentration,
<LLD
<LLD
<LLD 7.96E-15 NA jýi0/mL_
- 3.
Percent of Applicable Limit, %
N/A N/A N/A 3.99E-09 NA 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 6.33E+06 2.74E+06 NA dilution) 2.94E_10 3.23E_10 2.03E_10 NA F.
Dilution Water Volume Used, Liters 1.63E+10 2.94E+10 3.23E+10 2.03E+10 NA
<LLD - Less than the lower limit of detection N/A - Not Applicable, the ODCM does not have a limit for fission and activation products.
- Average diluted concentrations are based on total volume of water released during quarter.
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Radioactive Effluent Releases Page I 1
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 2a: Summation of Batch Liquid Effluent Releases A.
Fission and Activation Products 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
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 3 lists the total number of curies (Ci) of each radionuclide present in liquid effluent releases for each quarter. If a radionuclide was not present at a level "greater than or equal to the LLD" (_>LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, the LLDs were either met, or were below the levels required by the ODCM.
Table 3: Radioactive Liquid Effluent Nuclide Composition QUARTER QUARTER QUARTER QUARTER ANNUAL UNITS 1
2 3
4 TOTAL Tritium Ci 1.08E+01 1.49E+01 6.51E+00 3.59E+00 3.51E+01 Sodium-24 Ci
<LLD
<LLD
<LLD 1.24E-04 9.25E-05 Chromium-51 Ci
<LLD 2.26E-03
<LLD
<LLD 2.26E-03 Manganese-54 Ci 1.49E-04 2.76E-03 1.18E-04 1.02E-04 3.12E-03 Manganese-56 Ci
<LLD
<LLD
<LLD 1.83E-06 1.09E-06 Iron-55 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Iron-59 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Cobalt-58 Ci
<LLD 7.09E-04
<LLD 3.41 E-04 1.05E-03 Cobalt-60 Ci 1.23E-03 1.67E-02 4.25E-03 4.71 E-03 2.69E-02 Zinc-65 Ci
<LLD 9.35E-04 2.45E-04
<LLD 1.18E-03 Zinc-69M Ci
<LLD
<LLD
<LLD 2.38E-07 2.38E-07 Strontium-92 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Zirconium-95 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Niobium-95 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Technetium-99M Ci
<LLD
<LLD
<LLD
<LLD
<LLD Rhuthenium-105 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Silver-1 lOm Ci
<LLD 1.38E-04 3.29E-04
<LLD 1.71 E-03 Antimony-124 Ci
<LLD 2.09E-04
<LLD
<LLD 2.09E-04 Antimony-125 Ci 5.30E-05 5.03E-04 2.70E-04
<LLD 8.26E-04 Iodine-131 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Xenon-135 Ci
<LLD
<LLD
<LLD 1.62E-07 1.62E-07 Cesium-1 34 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Cesium-1 37 Ci
<LLD
<LLD
<LLD 5.92E-05 5.27E-05 Cesium-138 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Lanthanum-140 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Gold-199 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Total for Period 1.08E+01 1.49E+01 6.51 E+O0 3.34E+00 3.52E+01
<LLD - Less than the lower limit of detection I
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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.
- 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.
- 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, products.
the ODCM does not have a limit for fission and activation 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
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 5: Radioactive Gaseous Effluent Nuclide Composition UNIT QUARTER QUARTER QUARTER QUARTER ANNUAL 1 2 3
4 TOTAL A.
FISSION AND ACTIVATION GASES Tritium Ci 3.73E-01 2.17E+00
<LLD
<LLD 2.54E+00 Argon-41 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Krypton-85m Ci
<LLD
<LLD
<LLD
<LLD
<LLD Krypton-85 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Kryton-87 Ci
<LLD 2.21 E-02
<LLD
<LLD 2.21 E-02 Krypton-88 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Xenon-131m Ci
<LLD
<LLD
<LLD
<LLD
<LLD Xenon-133m Ci
<LLD
<LLD
<LLD
<LLD
<LLD Xenon-133 Ci
<LLD 5.44E-03
<LLD
<LLD 5.44E-03 Xenon-135m Ci
<LLD 3.21E-02
<LLD
<LLD 3.21E-02 Xenon-1 35 Ci
<LLD 4.04E-02
<LLD 2.57E-03 4.30E-02 Xenon-137 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Xenon-138 Ci
<LLD 7.54E-02
<LLD 9.34E-03 8.47E-02 Total for Period 3.73E-01 2.35E+00 O.OOE+00 1.19E-02 2.73E+00 B.
IODINE Iodine-131 Ci
<LLD 1.84E-06 1.87E-05 2.11E-05 4.16E-05 Iodine-132 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Iodine-133 Ci
<LLD 4.31E-06 2.70E-04 1.60E-04 4.34E-04 Iodine-1 34 Ci
<LLD
<LLD
<LLD
<LLD
<LLD 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 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Iron-59 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Cobalt-58 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Cobalt-60 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Zinc-65 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Rubidium-88 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Rubidium-89 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Strontium-89 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Strontium-90 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Yttrium-91m Ci
<LLD
<LLD
<LLD
<LLD
<LLD Strontium-92 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Zirconium-95 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Molybdenum-99 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Cesium-137 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Cesium-138 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Barium-1 39 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Barium-1 40 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Lanthanum-140 Ci
<LLD
<LLD
<LLD
<LLD
<LLD Total for Period
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD - Less than the lower limit of detection I
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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 B.
ESTIMATE OF MAJOR 1 ) NUCLIDE COMPOSITION (BY RADIONUCLIDE ABUNDANCE EST. TOTAL TYPE OF WASTE)
(%)
ERROR, (%)
Spent Resin, Filter Sludge, Evaporator Bottoms, Mn-54 5.30
+/- 25 etc.
Fe-55 29.50 Co-60 62.02 Zn-65 1.64 Dry Compressible Waste, Contaminated Mn-54 8.01
+/- 25 Equipment, etc.
Fe-55 22.80 Co-60 66.51 Zn-65 1.12 Irradiated Components, Control Rods, etc.
None 0
Other (Standby Liquid Control Waste Water)
None 0
C.
DISPOSITION NUMBER OF MODE OF TRANSPORTATION DESTINATION SHIPMENTS Solid Waste(2) 16 Public Highway Studsvik, Erwin, TN Solid Waste(2) 27 Public Highway Energy Solutions, Bear I
I Creek, TN Irradiated Fuel Shipments 0
N/A N/A N/A -- Not Applicable
( 1 ) -- "Major" is defined as any individual radionuclide identified as > 1% of the waste type abundance.
( 2 ) -- This waste was combined with waste from other utilities and disposed of at Clive, Utah.
Radioactive Effluent Releases Page 16
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 I
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 U
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 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 (1 OCFR20). 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 I
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 U
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 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. If any radionuclide was not present at a level greater than the LLD, it was not used in the dose calculations.
Table 9: Maximum Individual Site Boundary Dose, Considering Sectors on Land TYPE OF DOSE ORGAN ESTIMATED DOSE, LIMIT
% OF (MREM)
LIMIT Liquid Effluent Whole Body 2.59E-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
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT individual. This dose is assessed relative to the offsite dose, and considers dilution, dispersion, and occupancy factors.
The highest hypothetical dose from liquid effluents to a member of the public inside the site boundary is to a person who is fishing on Lake Erie from the shore on PNPP property. The calculations assume that this person will spend 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year fishing, with a liquid dilution factor of 10. The ratio of the exposure pathway to the doses calculated for offsite locations yields the dose values shown in Table 10.
Table 10: Maximum Site Dose from Liquid Effluents WHOLE BODY DOSE, ORGAN DOSE (MREM)
(MREM)
First Quarter 1.1E-04 1.3E-04 Second Quarter 9.3E-04 1.1 E-03 Third Quarter 2.OE-04 2.3E-04 Fourth Quarter 3.3E-04 3.8E-04 Annual 1.6E-03 1.8E-03 Although several cases were evaluated to determine the highest hypothetical dose from gaseous effluents to members of the public inside site boundary, the activity inside the site boundary with the highest dose potential is also shoreline fishing. The cases evaluated included traversing a public road within the site boundary, shoreline fishing (assuming fishing 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> 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 1.4E-05 1.4E-05 Second Quarter 1.2E-04 1.6E-04 Third Quarter 2.2E-07 4.5E-05 Fourth Quarter 1.4E-06 9.4E-06 Annual 1.4E-04 2.1 E-04 I
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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
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CARBON-4 SUPPLEMENTAL INFORMATION Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. C-14 is released primarily from BWRs through the off-gas system in the form of carbon dioxide (C02). The quantity of gaseous C-14 released to the environment can be estimated using a C-14 source term scaling factor based on power generation.
The U.S. Nuclear Regulatory Commission (NRC) is now requiring assessment of gaseous C-14 dose impact to a member of the public resulting from routine releases in radiological effluents. Prior to 2011, the industry did not estimate the dose impact of C-14 releases.
Since the dose contribution had been considered negligible compared to the dose impact from effluent releases of noble gases, tritium, particulates and radioiodines. At Perry, improvements over the years in effluent management practices and fuel performance have resulted in a decrease in the concentration and changes in the distribution of gaseous radionuclides released to the environment.
Perry's 2011 Annual Environmental Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2011, and estimates of public dose resulting from the C-14 effluent. Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste at Perry is not required. Refer to Table 4 and Table 9 for C-14 estimated release values.
Radioactive Effluent Releases Page 21 I
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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)
<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.