L-20-043, Annual Environmental and Effluent Release Report

Annual Environmental and Effluent Release Report

ML20119A519
Person / Time
Site:	Perry
Issue date:	04/17/2020
From:	Payne F FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-20-043
Download: ML20119A519 (300)

Text

April 17,2020 L-20-043 10CFR50.36(a)

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

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440 Annual Environmental and Effluent Release Report Enclosed is the Annual Environmental and Effluent Release Report for the Perry Nuclear Power Plant (PNPP) for the period of January 1, 2019 through December 31, 2019. This document includes the radiological environmental operating report and the radioactive effluent release report, which satisfies the requirements of the PNPP Technical Specifications (TS), the PNPP Offsite Dose Calculation Manual (ODCM), and the Environmental Protection Plan, Appendix B of the PNPP Operating License. Also enclosed is a copy of the revised Offsite Dose Calculation Manual and support documentation.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Steven Benedict, Chemistry Manager at (440) 280-5032.

Frank Payne

Enclosures:

A PNPP 2019 Annual Environmental and Effluent Release Report B Offsite Dose Calculation Manual, Revision 23 cc: NRC Project Manager NRC Resident Inspector NRC Region III

Enclosure A L-20-043 PNPP 2019 Annual Environmental and Effluent Release Report

2019 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT for the Perry Nuclear Power Plant PreparedBy:

Chemistry Section Perry Nuclear Power Plant Perry, Ohio MARCH, 2020

2019 Annual Environmental and Effluent Release Report Table of Contents EXECUTIVE

SUMMARY

, *** 1 Radioactive Effluent Releases ;v.._................ * '

Radiological Environmental Monitoring.......:'......^.;.;'.:::.

• 2 Pre-Operational REMP ..........;..,...... 2 Operational REMP 2 Land Use Census ** **'* *' ...t,:.'..:. ....3 INTRODUCTION ****  :.',...:..,...i..,: 4 Radiation Fundamentals * ***** .,.....***. 4 Radiation and Radioactivity * ....:....'.. *.* 4 Lower Limit of Detection ...v .*:.:..*:.,.,. -*** * - ..,...**. 6 Other Sources of Radiation Dose to the U.S. Population... 6 Environmental Radionuclides ** 7 RADIOACTIVE EFFLUENT RELEASES ** -8 Introduction Regulatory Limits * **

40CFR190 and 10CFR72.104 - Uranium Fuel Cycle Dose Assessment..... 9 Liquid Effluents ^

Gaseous Effluents 9 Independent Spent Fuel Storage Installation 10 Release Summary ^

Meteorological Data

• 19 Dose Assessment '9 CARBON-14 SUPPLEMENTAL INFORMATION

• 23 GROUNDWATER MONITORING PROGRAM 23 RADIOLOGICAL ENVIRONMENTAL MONITORING 26 Introduction

• 2^

Sampling Locations

• 26 Sample Analysis *** J:

Sampling Program.....

• 33 Program Changes 33 Atmospheric Monitoring 33 Terrestrial Monitoring -34 Aquatic Monitoring 35 Direct Radiation Monitoring

• 37 Conclusion 37 Inter-Laboratory Cross-Check Comparison Program c. 38 Land Use Census..... 38 ANNUAL ENVIRONMENTAL OPERATING REPORT 42 Table of Contents Page i

2019 Annual Environmental and Effluent Release Report Appendices Appendix A: 2019 Inter-Laboratory Cross Check Comparison Program Results Appendix B: 2019 REMP Data Summary Reports Appendix C: 2019 REMP Detailed Data Report Appendix D: Corrections to Previous AEERR Appendix E: Abnormal Releases Appendix F: ODCM Non-Compliances Appendix G: ODCM Changes Appendix H: Changes to the Process Control Program - ,

Table of Contents Page ii

2019 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 31,2019. This report meets all of the requirements in PNPP Technical Specifications, the Offsite Dose Calculation Manual (ODCM), the Environmental Protection Plan (EPP), and Regulatory Guide 1.21: This report incorporates the requirements of the Annual Radioactive Effluent Release Report (ARERR) and the Annual Radiological Environmental Operating Report (AREOR). Report topics include radioactive effluent releases, radiological environmental monitoring, and the land use census. The results of the environmental and effluent programs indicate that the operations of the PNPP did not result in any adverse environmental impact.

Radioactive Effluent Release?

During the normal operation of a nuclear power plant, small quantities of radioactivity are released to the environment through liquid and gaseous effluent pathways. Radioactive material is also shipped offsite 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.

Dose to the general public from the plant's liquid and gaseous effluent pathways Were well below regulatory limits. The calculated maximum individual whole-body dose potentially received by an individual resulting from PNPP liquid effluents was 2.03E-03 mrem (0.068%

of the regulatory limit). The calculated maximum individual whole-body dose potentially received by an individual resulting from PNPP gaseous effluents, excluding carbon-14 (C-14) was 1.60E-03 mrem (0.011% of the regulatory limit).

Radioactivity released to the environment in the form of gaseous, C-14 was estimated based on plant type and power production. The calculation is based on an industry initiative supported by the Nuclear Energy Institute (NEl), the Electric Power Research Institute (EPRI), arid the NRC. The calculated hypothetical maximum annual individual whole-body dose potentially received by an individual resulting from PNPP gaseous effluents for C-14'is 2.35E-01 mrem/yr (4.702% of the limit). Refer to page 23 for additional C-14 information.

The summation of the hypothetical maximum individual dose from effluents is less than 1%

of the total dose an individual living in the PNPP area receives from all sources of man-made 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 regulations governing radioactive shipments of solid radioactive waste. . .'_'

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2019 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 operational REMP was initiated in 1986 and has continued through this reporting period.. The REMP is conducted in accordance with the PNPP ODCM. This program includes collection and analysis of environmental samples and evaluation of results at indicator as well as control locations. Indicator samples are collected at locations determined to be most influenced by operation of the PNPP. Control samples are collected at locations beyond the measurable influence of the PNPP for data comparison.

Pre-Operational REMP The REMP was established at PNPP six years before the plant became operational.

Between 1981 and 1986 environmental monitoring involved collection and analysis of environmental samples. This pre-operational program was designed to provide data on background radiation levels and radioactivity normally present in the area in order to establish a baseline for data comparison prior to operation of the plant. PNPP has continued to monitor the environment during plant operation by collecting and analyzing samples of air, milk, fish, vegetation, water, and sediment, as well as by measuring radiation directly.

The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the environmental monitoring program with pre-operational data, operational data from previous years, and control location data. The results for each sample type are compared to historical data to determine whether trends or changes in concentrations are observable.

Operational REMP Results of air samples collected to. monitor .the radioactivity in the atmosphere revealed normal background radionuclide concentrations. Terrestrial monitoring included the analysis of vegetation due to the unavailability of milk Samples; the results of which indicated concentrations of radioactivity similar to those found in previous years. Analyses of vegetation samples detected only natural radioactivity similar to that observed in previous years and indicated no radioactivity attributable to operation of the PNPP.

Aquatic monitoring included the collection and analyses of water, fish! and shoreline sediments. The analytical results of these samples showed normal background radionuclide concentrations.

Direct radiation measurements showed no significant changes from previous years. The indicator locations averaged 12.9 mrem/quarter and control locations averaged 12.9 mrem/quarter. Radiation dose in the area of PNPP were similar to the radiation dose measured at locations greater than ten miles away from PNPP.

Results from indicator samples collected during this reporting period were compared to control sample results and pre-operational data. Based on the results, it can be concluded that the operation of the PNPP resulted in no measurable increase in the radionuclide concentrations observed in the surrounding environment. The results of the REMP indicate adequate control of radioactivity released from PNPP. These results also demonstrate that PNPP complies with federal regulations.

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2019 Annual Environmental and Effluent Release Report Land Use Census ii In order to estimate radiation dose attributable to operation of the PNPP, the potential pathways through which public exposure can occur must be known. To identify these pathways.an Annual Land Use Census is performed as part of the REMP. During the census, PNPP personnel travel public roads within a five mile radius of the plant to locate key radiological exposure pathways. These key pathways include the nearest resident, garden, in each of the ten meteorological land sectors that surround the plant. The information obtained from the census is entered into a computer program used to assess hypothetical dose to members of the public. The predominant land use within the census area continues to be rural and/or agricultural.,

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2019 Annual Environmental and Effluent Release Report INTRODUCTION Nuclear energy provides an alternative energy source that is readily available with a very limited impact upon the environment. To more fully understand nuclear energy as a source of generating electricity, it is helpful to understand basic radiation concepts and the occurrence of radioactivity in nature, Radiation Fundamentals Atoms are the basic building blocks of all matter. Simply described, atdmsare 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 prevent 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 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 alpha and beta particles and gamma rays. Radionuclides vary greatly in the rate at which they decay. 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 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. If alpha particles are released inside the body, however, they can damage the soft internal tissues because they deposit all their energy in a small area.

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> 2019 Annual Environmental And Effluent Release Report Beta Particles Beta particles have the same characteristics as electrons but originate from the nucleus.

They are much smaller than alpha particles and travel at nearly the speed of light, thus they travel longer distances than alpha particles. External beta radiation primarily affects the skin. Because of their electrical charge, beta particles are stopped by paper, plastic, or thin metal. \ *'..*.-*

Gamma Rays Gamma rays are bundles of electromagnetic energy called photons. They are similar to visible light, but at 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^O is an example of a naturally-occurring radionuclide that emits a gamma ray when it decays and is found in all humans.  :

Interaction with Matter When radiation interacts with other materials it affects the atoms of those materials principally by removing the negatively charged electrons out of their orbits. 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 thus the radiation is called ionizing radiation.  : *

Activity * ** " . , .- : ' -* - _*'*** *;'. -^:."-

• Activity is the number of atoms in a material that decay per unit of time. Each time an atom decays, radiation is emitted. A 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 (uCi); 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 curie of activity depends on the, disintegration rate. For example, one gram of radium-226 is equivalent to one curie of activity. It would require about 1.5 million grams of natural uranium, however, to equal one 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 that cause dense local ionization, can result in much more biological damage for the same energy imparted than does gamma or beta radiation. A quality factor, therefore, must be applied to account for the different ionizing capabilities of various types of ionizing radiation.

When the quality factor is multiplied by the absorbed dose (as measured in rads), the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any type of ionizing radiation. The dose equivalent is measured in terms of the Roentgen Equivalent Man (rem). When discussing environmental radiation effects, the rem is a large unit; therefore, a smaller unit, the millirem (mrem) is often used. One mrem is equivalent to 1/1000 of a rem.

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2019 Annual Environmental and Effluent Release Report 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 the required LLD values for environmental and effluent sample analyses. )

Other Sources of Radiation D6se to the U.S. Population This section discusses the doses that the average American typically receives each year from naturally-occurring background radiation and all other sources of radiation. With the information presented in this section, the reader can compare the doses received from Nuclear Power Plant (NPP) effluents with the doses received from natural, medical, and other sources of radiation. This comparison provides some context to the concept of radiation dose effects., ."""

In March 2009, the National Council on Radiation Protection and Measurements (NCRP) published Report No. 160 as an update to the 1987 NCRP Report No. 93, Ionizing Radiation Exposure of the Population of the United States. Report No. 160 describes the doses to the U.S. population from all sources of ionizing radiation for 2006, the most recent data available at the time the NCRP report was written. The NCRP report also includes information on the variability of those doses from one individual to another. The NCRP estimated that the average person in the United States receives about 620 mrem of radiation dose each year. NCRP Report No. 160 describes each of the sources of radiation that contribute to this dose, including: <

Naturally-occurring sources (natural background) such as cosmic radiation from space, terrestrial radiation from radioactive materials in the earth, and naturally-occurring radioactive materials in the food people eat and in the air people breathe; Medical sources from diagnosis and treatment of health disorders using radioactive Pharmaceuticals and radiation-producing equipment; Consumer products (such as household smoke detectors);

Industrial processes, security devices, educational tools, and research activities; and Exposures of workers that result from their occupations.

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2019 Annual Environmental and Effluent Release Report Space Radon & Ihoron (fc^ckgr oukJ)

Industrial irctytfes doscsto ff>> setaSc (row Consumer

?%* Cwweititatal Figure 1: Sources of Radiation Exposure to the U.S. Pbpulation Figure 1 shows the contribution of various sources of exposure to the total collective effective dose and the total effective doseper individual in the U.S. population in .2006.

Larger contributors to dose are represented by proportionally larger slices of the pie. Doses to the public from NPPs are included inthe industrial category; doses to workers from nuclear power generation are included in the category of occupational dose. Doses to the public due to effluents from NPPs are less than 6.1 % of what the average person receives each year from all other sources of radiation.

Environmental Radionuclides 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, 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; radionuclides from nuclear weapons testing fallout, including tritium and cesium-137; and tritium, due to the interaction of cosmic rays with nitrogen in the air.

Beryllium-7 and potassium-40 are 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 Sampling Program results. These radionuclides are included; however, in Appendix A, 2019 Inter-Laboratory Gross Check Comparison Program Results.

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2019 Annual Environmental and Effluent Release Report RADIOACTIVE EFFLUENT RELEASES Introduction The source of radioactive material in a nuclear power plant is the generation of fission products (e.g., noble gas, iodine, and particulate) or neutron activation of water and corrosion products (e.g., tritium and cobalt). The majority of the fission products generated remain within the nuclear fuel pellet and fuel cladding. Most fission products that escape from the fuel cladding, as well as the majority of the activated corrosion products, are removed by plant processing equipment.

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

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

Gaseous effluent release data is coupled with on-site meteorological data in order to calculate the dose to the general public. Devices are maintained at various locations around PNPP to continuously sample the air in the surrounding environment. Frequent samples of other environmental media are also taken to determine if any radidactive material deposition has occurred. The REMP is described in detail later in this report.

Generation of solid waste is controlled to identify opportunities for minimization. Limiting the amount of material taken into the plant and sorting material as radioactive or non-radioactive waste helps to lower the volume of radioactive solid waste generated. After vendor processing, solid waste is shipped to a licensed burial site.

Regulatory Limits '";

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

10 CFR 20: Title 10 of the Code of Federal Regulations, Part 20, Standards for Protection Against Radiation, Appendix B;

,.;. 10 CFR 50: Title 10 ofthe Code of Federal Regulations, Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix I; 10 CFR 72.104: Title 10 ofthe Code of Federal Regulations, Part 72.104, Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS 40 CFR 190: Title 40 ofthe Code of Federal Regulations, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations Page 8

2019 Annual Environmental and Effluent Release Report These limits were incorporated into the PNPP Technical Specifications, and subsequently into the PNPP ODCM. The ODCM prescribes the maximum doses and dose ratesdue to radioactive effluents resulting from the operation of PNPP, These limits are defined in several ways and serve to limit the overall impact on persons living near the plant. Since there are no other fuel sources near the PNPP, the 40 CFR 190 limits described below were not exceeded.

40CFR190 and 10CFR72.104-Uranium Fuel Cycle Dose Assessment The 4.0 CFR 190 limit for whole body dose is 25 mrem. Considering all sectors, the total whole-body dose to a member of the general public was 2.39E-01 mrem. This value was determined by summing the annual whole-body dosesfrom liquid and gaseous radioactive effluents and the annual gaseous C-14 dose. Since the direct radiation dose, as determined by TLD, was indistinguishable from natural background (Figure 8), it was not included in the calculation. More information regarding direct radiation dose and the Independent Spent Fuel Storage Installation (ISFSI), may be found on page 10.

Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, 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 is limited to 2.0E-04 uCi/ml. 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 , , ,

The dose rate due to radioactive materials released in gaseous effluents (including any releases from the on-site ISFSI) from the site to areas at and beyond the site boundary are governed by 10 ,CF£ 20 and shall be limitecj to the following as required by the PNPP

' ODCM: " /' ' ' v":>':;;- ' ' '"' " ' ' ' " - ' . ':: ,

• Noble;gases: . . ..,

Less than or equalto 500 mrem per year to the whole body, and v Less than or equal to13000'mrem per year to theskin

.i

• iodiner131,iodine-133,,tritium, and all radionuclides in particulate form with half-

. ,. lives greater than eight days:; .:/"':*..  :

> Less than or equal to 1500 mrem per year to any organ ,

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2Q19 Annual Environmental and Effluent Release Report Air dose due to noble gases to areas at and beyond the site boundary are governed by 10 CFR 50 Appendix I and shall be limited to the following:

• During any calendar quarter: "

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

• During any calendar year:

Less than or equal to 10 mrad for gamma radiation, and ~*

Less than or equal to 20 mrad for beta radiation Dose to 5 member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Less than or 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.

Independent Spent Fuel Storage Installation (ISFSI)

Dose rates from the ISFSI contributing to a dose to a member of the public at or beyond the site boundary is governed by 10CFR72.104 and shall be limited to the following as required by the PNPP ODCM during any calendar year:. ,

Less than or equal to 25 mrem whole body.dose;  ; -,.

Less than or equal to 75 mrem thyroid dose; and Less than or equal to 25 mrem to any other critical organ.

Release Summary V 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.

10CFR72.104, ISFSI Compliance Since installation of the Independent Spent Fuel Storage Installation (JSFSI) in 2011, eight TLDs have been placed on the outer perimeter fence of the cask storage area (located within the site boundary) to monitor dose due to direct radiation from the spent fuel stored on the ISFSI.

Since the dosimeters measure an accumulation of all sources of radiation, the following justification was used to determine how to most accurately calculate the dose received to the nearest resident contributed only by the spent fuel at the ISFSI.

To determine the dose contributed by the spent fuel only, one would need to discriminate out the dose associated with background radiation as described above and other sources.

Dosimeters close to the plant are susceptible to "shine" which is radiation from nitrogen-16 that is reflected by the atmosphere. These two sources of radiation affect the surrounding TLDs almost uniformly. * ^

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2019 Annual Environmental and Effluent Release Report The dosimeters closest to the dry casks receive more dose from the spent fuel and are thus affected by a lesser percentage by background radiation and plant effluents than those further away. To more accurately calculate the dose contribution to the nearest resident from the spent fuel, the dosimeter nearest to the point source should be used.

The dose calculation was performed using the location of the nearest residence, assuming they remain at the location all year, because that individual would incur the maximum potential dose from direct exposure. The TLD at REMP location 7 (refer to Figure 3) is positioned neighboring the nearest resident, was also reviewed for significant changes in readings.  ;

To determine the dose rate to the nearest resident and demonstrate compliance, the following equation was used:

DiRi2=D2R22  : ", ';',

Where:

Di = dose rates (mrem/yr) at the TLD location D2 = dose rates (mrem/yr) to nearest resident R1 = distance (feet) of nearest TLD location to max individual R2 = distance (feet) to nearest resident The two nearest TLDs were chosen to estimate dose rates/which were #15 and #20, directly east and west of the dry casks. The corresponding estimated dose rates to the nearest resident was 0.2033 and 0.1744 mrem/yr, respectively, in 2019. In 2018, the calculated values were slightly lower, but statistically comparable to results of 2019. Unlike the whole body dose value of 2.39E-01 mrem presented on page 9, the dose rates of 0.2033 and 0.1744 mrem/yr are an estimate based on TLD readings to demonstrate compliance, the calculation confirms that direct dose from the ISFSI does not exceed the 40 CFR 190 limit of 25 mrem/year.

Review of the TLD results from 2019 have shown no detectable impact on dose to the public due to radiation from the ISFSI nor significant changes in results to the public since employment of the ISFSI. )

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2019 Annual Environmental and Effluent Release Report 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 effluents 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 principles 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 2019.

Table 1: Liquid Batch Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Number of batch releases 27 24 33 2 Total time period for batch releases, miri 6.22E+03 5.12E+03 7.48E+03 4.64E+02 Maximum time for a batch release, min 2.94E+02 2.82E+02 2.35E+02 2.34E+02 Average time period for a batch release, min 2.30E+02 2.13E+02 2.27E+02 2.32E+02 Minimum time for a batch release, min 2.11E+02 6.80E+01 1.81 E+02 2.30E+02 Average quarterly flow rate, L/min 2.18E+05 1.79E+05 2.91 E+05 1.48E+05 Page 12

2019 Annual Environmental and Effluent Release Report Table 2 provides information on the nuclide composition for the liquid radioactive effluent system releases. In each case, LLDs were at or below the required values. Table 2a provides information specific to radioactive effluent batch releases and Table 2b provides information specific to continuous radioactive effluent releases. A batch release is the

.discharge of liquid waste of a discrete volurne. A continuous release is the discharge of fluid wastes of a rion-discrete volume. Potential sources for a continuous release at Perry are RHR heat exchanger leakage into the Emergency Service Water system, Nuclear Closed Cooling (NCC) out-leakage into the Emergency Service Water system, tritium activity in the Turbine Building HVAC (M35) Supply Plenum drain into storm drains, and Alternate Decay Heat Removal (ADHR) heat exchanger leakage intoService Water.

Table 2: Summation of All Liquid Effluent Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error, (%)

A. Fission and Activation Products

1. Total Released, Ci 1.22E-02 1.66E-02 3.97E-03 4.99E-04 1.00E+01 texcludina tritium, qases, alpha) 4.92E-10. 7.34E-10 1.18E-10 2.06E-11 , -'

2 Averaqe Diluted Concentration, uCi/mL *

3. Percent of Applicable Limit, % ; , 1.33E-02 1.80E-02 3.18E-03 6.87E-04 B. Tritium 1.03E+01 5.10E+00 6.22E+00 5.72E-01 1.00E+01

1. Total Released, Ci 2 Averaae Diluted Concentration, ijCi/mL 4.15E-07 2.26E-07 1.85E-07 2.36E-08

3. Percent of Applicable Limit, % 4.15E-02 2.26E-02 1.85E-02 2.36E-03 C. Dissolved and Entrained Gases 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E+01

1. Total Released, Ci 2 Averaqe Diluted Concentration, uCi/mL 0.00E+00 6.00E+00 0.00E+00 0.00E+00 3 Percent of Applicable Limit, % 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.29E-09 3.76E-09 4.61 E-09 1.00E+01 D. Gross Alpha Activity, Ci E. Waste Volume Released, Liters (prior to 4.37+08 4.00E+07 2.49E+08 1.13E+09 dilution)*

2.48E+10 2.26E+10 3.37E+10 2.42E+10 F. Dilution Water Volume Used, Liters

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

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2019 Annual Environmental and Effluent Release Report Table 2a: Summation of Batch Liquid Effluent Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total

. Error, (%)

A. Fission and Activation Products -. '-

Total Released, Ci 1.22E-02 1.65E-02 3.97E-03 4.99E-04 1.00E+01 (excluding tritiunfi, gases, alpha)

B. Tritium  :

Total Released, Ci 1.03E+01 5.10E00 6.22E00 5.72E-01 1..00E+01 C. Dissolved and Entrained Gases ,

Total Released, Gi <LLD <LLD <LLD <LLD 1.00E+01 D. Gross Alpha Activity, Ci <LLD <LLD 1.60E-4 <LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 3.55E+06 2.88E+06 4.33E+06 2.64E+05 dilution)*

<LLD - Less than the lower limit of detection

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

Table 2b: Summation of Continuous Liquid Effluent Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error, (%)

A. Fission and Activation Products Total Released, Ci <LLD 3.01 E-08 7.79E-07 <LLD 1.00E+01 (excluding tritium, gases, alpha)

B. Tritium Total Released, Ci 5.67E-06 9.00E-07 3.15E-07 <LLD 1.00E+01 C. Dissolved and Entrained Gases Total Released, Ci <LLD <LLD <LLD <LLD 1.00E+01 D. Gross Alpha Activity, Ci <LLD 6.29E-09 3.76E-09 4.61 E-09 1.00E+01 E. Waste Volume Released, Liters (prior to 1.13E+09 4.34E+08 3.56E+07 2.48E+08 dilution)*

<LLD - Less than the lower limit of detection

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

Page 14

2019 Annual Environmental and Effluent Release Report Table 3 lists the total number of curies of each radionuclide present in liquid effluent releases for each quarter. 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 1 Quarter 2 Quarter 3 Quarter 4 Annual Isotope Unit 1.03E+01 5.10E+00 6.22E+00 5.72E-01 . 2.22E+01 Tritium Ci

<5.0E-071 <5.0E-07 1 <5.0E-07 1 <5.0E-07 1 <5.0E-07 1 Chrbmium-51 Ci .

Mahgariese-54 Ci ^.30E-03 3.29E-03 7.54E-05 "' <5.0E-07 1 4.67E-03 Ci <1.0E-061 <1.0E-061^ <1 OE-06 1 <1 .OE-061 <1 .OE-061 lron-55 ,,,. ...

Cobalt-58 Ci 4.25E-04 1.42E-03 2.76E-04 , <5.0E-07 1 2.12E-03

<5.0E-07 1 <5.0E4)71 . 4.68E-04 <5,0E-071 ;r 4.68E-04 lron-59 Ci 8.73E-03 1.05E-02 2.84E-03 4.99E-04 2.26E-02 Cobalt-60 Ci

<1.0E-06 <1.0E-06 <1.OE-06 <1 .OE-06 <1.OE-06 Nickel-63 Ci Ci 6.39E-04 7.01 E-05 2.39E-04 <5.0E-07 1 9.48E-04 Zinc-65

<5.0E-08 1 <5:0E-08 1 <5.0E-08 1 <5.0E-08 1 <5.0E-08 1 Strontium-^ Ci Ci <5.0E-081 <5.0E-08 1 <5.0E-081 ^ <5.0E-081 <5.0E-081 Strontium-90 Ci <5.0E-07i <5.0E-07 1 <5.0E-071' <5.0E-071 <5.0E-071 Molybdenum-99 5.13E-05 <5.0E-07 1 6.85E-05 <5.0E-07 1 1.20E-04 Silver-110m Ci

<5.0E-071 <5.0E-071 <5.0E-07 1 <5.0E-07 1 <5.0E-07 1 Tin-113 Ci Antimony-124 Ci

• 8.11E-04 8.97E-04 <5.0E-07 1 <5.0E-07 1 1.71E-03 Antimony-125 Ci 1.79E-04 1.17E-04 <5.0E-071 <5.0E-07 1 2.96E-04 Ci <1.0E-061 <1.0E-061 <1.OE-061 <1 .OE-061 <1.OE-061 lodine-131 Ci <5.0E-07 1 <5.0E-07 1 <5.0E-07 1 <5.0E-071 <5.0E-07 1 Cesium-134 Cesium-T37 Ci 7.60E-05 2.54E-04 <5.0E-07 1 <5.0E-07 1 3.30E-04 Ci <5.0E-07 1 <5.0E-07 1 <5.0E-071 <5.0E-07 1 <5.0E-07 1 Cerium-141

<5.0E-071 <5.0E-07 1 <5.0E-07 1 <5.0E-07 1 <5.0E-07 1 Cerium-144 Ci Ci <1.0E-051 <1.0E-051 <1 .OE-05 1 <1.OE-051 <1.0E-Q51 Krypton-88

<1.OE-051 <1.0E-051 <1 .OE-05 1 <1.OE-05 1 <1.OE-051 Xenon-133 Ci

<1.0E-071 6.29E-09 3.76E-09 4.61 E-09 1.47E-08 Gross Alpha Ci 1 - (<) Less than the ODCM-required lower limit of detection, units in pCl/mL

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

2019 Annual Environmental and Effluent Release Report Gaseous Effluents Gaseous effluents are made up of fission and activation gases, iodine, and particulate releases. 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. Gaseous effluents released from PNPP are considered continuous and at ground level.

In 2013, PNPP increased the volume of air sampled for tritium in gaseous effluents, increasing the detection capability by a factor of 20, which lowered the LLD. With the increased sample volume, gaseous effluent tritium releases can be detected; whereas, in previous years the concentration was too dilute to measure. This has resulted in increased reported tritium releases since then. A summation of all gaseous radioactive effluent releases is given in Table 4.

Table 4: Summation of All Gaseous Effluents Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error. %

A. Fission and Activation Products

1. Total Released, Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E+01

,,* 2. Average Release Rate. uCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00

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

1. Total lodine-131 Released, Gi 1.62E-05 0.00E+00 7.11E-05 0.00E+00 1.00E+01

2. Average Release Rate. uCi/sec 2.09E-06 0.00E+00 8.95E-6 0.00E+00

3. Percent of Applicable Limit. %  ::': '* -

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

C. Participates with Half-Lives > 8 days

1. Total Released, Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E+01

2. Average Release Rate, uCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Percent of Applicable Limit, % N/A N/A N/A v N/A

4. Alpha Activity, Ci 2.11E-05 2.19E-06 3.63E-6 5.07E-06 D. Tritium 1> Total Released, Ci 4.51 E-01 3.26E-01 2.31 E-01 3.70E-01 1.00E+01

2. Average Release Rate, gCi/sec , 5.80E-02 4.14E-02 2.91 E-02 4.66E-02

3. Percent of Applicable Limit, % N/A N/A N/A N/A E. Carbon-14, Ci 2.67E+00 4.23E+00 4.18E+00 4.73E+00 1.00E+00 N/A - Not Applicable, the ODCM does not have a release rate limit for gaseous effluents Carbon-14 activity was calculated based on power production and using the EPRI-provided spreadsheet Page 16

2019 Annual Environmental and Effluent Release Report The radionuclide composition of all gaseous radioactive effluents for a continuous-mode, ground-level release is given in Table 5. In each case, LLDs were met or were below the levels required by the QDCM. ,

Table 5: Radioactive Gaseous Effluent Nuclide Composition Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Isotope

1. Fission and Activation Gases Ci 4.51 E-01 3.26E-01 2.31 E-01 3J0E-01 1.38E+00 Tritium Ci <1 .OE-04 1 <1.OE-041 <1.OE-041 <1 .OE-04 1 <1.OE-041 Arqon-41 Ci <1 .OE-04 1 <1.OE-041 <1.OE-041 <1 .OE-041 <1.OE-041 KrvDtbn-85m ." v Ci <1 .OE-04 1 <1.OE-041 <1.OE-041 <1 .OE-041 <1.OE-041 Krypton-87 '" * - .'

Ci <1 .OE-041 <1 .OE-041 <1 .OE-041 <1 .OE-041 <1 .OE-041 Krypton-88 Ci <1 .OE-041 <1.0E-04 1 <1.OE-041 <1 .OE-041 <1.OE-041 Xenon-133m .-

<1 .OE-041 <1 .OE-04.1 <1 .OE-041 <1 .OE-041 <1 .OE-041 Xenoh-133 Ci Ci <1 .OE-04 1 <1.OE-041 <1.OE-041 <1 .OE-04 1 <1 .OE-041 Xenon-135m Ci <1 .OE-04 1 <1.OE-041 <1.OE-04 1 <1 .OE-04 1 <1 .OE-041 Xenon-135 Ci <1 .OE-04 1 <1.OE-041 <1.OE-041 <1 .OE-041 <1 .OE-041 Xenon-138 Ci 4.5,1 E-01 3.26E-01 2.31 E-01 3.70E-01 1.38E+00 Total for Period

2. lodine/Haloqens lodine-131 Ci 1.62E-05 <1.0E-121 7.11E-05 <1.0E-121 8.73E-05 Ci 8.93E-06 <1.0E-101 4.74E-5 <1.0E-101 5.63E-5 lodine-133

<LLD 1.19E-04 <LLD 1.44E-04 Total for Period ci 2.52E-05

3. Particulates Ci <1 0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Chromium-51 Manqanese-54 ' Ci <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Ci <1:0E-11 1 <1.0E-11 1 <1.OE-11 1 <1.0E-11 1 <1.0E-11 1 lron-59 a <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Cobalt-58 Ci <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Cobalt-60 Ci <1.0E-11 1 <1.0E-11 1 .<1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Zinc-65 Ci <1.0E-11r1) <1.0E-11 1- <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Strontium-89 Ci <1.0E-11 1 <1.0E-11 1 ,<1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Molybdenum-99 , , _;

Ci <1.0E-11 1 <l.0E-11 !:: ,^1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Gesium-134  ;

Ci <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Cesiunri-137 ,..-.- ~

Ci <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Cerium-141 Ci <1.0E-11,1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 <1.0E-11 1 Cerium-144

<LLD <LLD <LLD <LLD <LLD Total for Period Ci 1 - (<) Less than the ODCM-required lower limit of detection, units in LjCi/mL

<LLD - Less than the ODCM-required lower limit of detection Page 17

2019 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. The final waste after processing is sent to Energy Solutions disposal facility in Clive, Utah for burial.

Table 6: Solid Waste Shipped Offsite for Burial or Disposal

1. Type of Solid Waste Shipped Volume (m3) Activity (Ci) Est. Total Error'(%)

a. Resins, Filters; and Evaporator Bottoms 1.55E+02 4.22E+02 +/- 25

b. Dry Active Waste 6.87E-i;02 5.58E+00 +/-25

c. Irradiated Components  ; . 0.00E+00 0.00E+00 +/-25

d. Other Waste 0.00E+00 0.00E+00 +/-25

2. Estimate..of Major.^ Nuclide Composition (by type Radionuclide Abundance Est. Total of waste) ,

(%) Error, (%)

a. Resins, Filters and Evaporator Bottoms Mn-54 4.07 +/-25 Fe-55 23.51 Co-58 1.33 Co-60 62.34 Zn-65 6.11 Cs-137 1.46

b. Dry Active Waste Cr-51 2.31 +/-25 Mn-54 3.64 Fe-55 45.43 Co-60 44.39

c. Irradiated Components, Control Rods, etc. N/A N/A N/A

d. Other Waste N/A N/A N/A" (1) - "Major" is defined as any individual radibnuclide identified as >1% of the waste type abundance.

N/A - Not applicable due to no shipments

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 39 Hittman Transport Energy Solutions Bear Creek Operations 12 Hittman Transport Erwin Resin Solutions, LLC 151 T.C Runnion Road :

1 Landstar Ranger Energy Solutions Bear Creek Operations Page 18

2019 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 program 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 as a separate document that is retained in PNPP Records and is available upon request. 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 10 CFR 20. Sampling, analyzing, processing, and monitoring the effluent streams 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 maximum 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, vegetation, and fish. Because no individual 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:

• Using data for a 360-degree 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;

• 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 whole body and worst-case organ-dose values.

Page 19

2019 Annual Environmental and Effluent Release Report Table 7: Maximum Yearly Individual Site Boundary Dose, Considering All Sectors Type of Dose Organ Estimated Limit (mrem)  % of Limit Dose, (mrem)

Liquid Effluent Whole body t 2.03E-03 3. 6.8E-02 Liver 3.13E-03 10 3.1E-02 Noble Gas Air Dose Gamma 0.00E+00- 10 N/A (mrad)

Air Dose Beta O.OOE+00 20 N/A (mrad)

Noble Gas Whole body 0.00E+00 - 5 N/A Skin 0.00E+00 15 N/A Tritium, Particulate Whole Body 1.60E-03 15  :,', 1.1E-02

& Iodine Carbon-14

• Whole Body 2.35E-01 5 4.7E+00

• C-14 dose calculated at nearest garden.

The hypothetical maximum dose within a 50-mile radius of site was calculated andis presented in Table 8. This table considers all meteorological sectors around PNPP and provides whole body and worst-case organ dose values.

TableS: Population Yearly Dose, Considering All Sectors out to 50 miles

' ( v Organ -,-.. Estimated Dose (person-rem)

Liquid Effluent Whole body 3.4E-01 Thyroid 1.4E-01 Gaseous Effluent Whole body 2.0E.04 Thyroid 5.0E-04 Page 20

2019 Annual Environmental and Effluent Release Report Table 9 provides the calculated hypothetical maximum site boundary dose values considering only the land-based sectors.

fable 9: Maximum Yearly Individual Site Boundary Dose (Only Land Sectors)

Estimated Limit (mrem)  % of Limit Type of Dose Organ Dose, (mrem) 2.03E-03 3 6.8E-02 Liquid Effluent Whole Body 3.13E-03 10 3.1E-02 Liver Noble Gas Air Dose 10 N/A 0.00E+00 Gamma (mrad)

Air Dose Beta 20 N/A 0;00E+00 (mrad) 0.00E+00 5 N/A Noble Gas Whole Body V . - - 0.00E+00 15 N/A Skin 1.58E-04 15 1.1E-03 Tritium, Particulate& Thyroid Iodine

• -: 2.35E-01 5 47E+00 Carbon-14* Whole Body

• C-14 dose calculated at nearest garden:

Other dose calculations are performed for a hypothetical individual 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 person actually meets 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) 4.3E-03 6.7E-03 First Quarter Second Quarter 7.3E-03 1.1E-02 Third Quarter 1.2E-03 2.0E-03 2.2E-04 3.9E-04 Fourth Quarter 1.3E-02 1.8E-02 Annual Page 21

2019 Annual Environmental and Effluent Release Report Although several cases were evaluated to determine the highest hypothetical dose from gaseous effluents to members of the public inside the 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 2.44E-05 2.95E-05 Second Quarter 1.47E-06 1.47E-06 Third Quarter 1.53E-05 1.12E-04 Fourth Quarter 2.44E-05 2.44E-05 Annual 7.65E-05 1.72E-04 An average whole body dose to individual members of the public at or beyond the site boundary is then determined by combining the dose from gaseous and liquid radiological effluents. The dose from gaseous radiological effluents is based upon the population that lives within 50 miles of PNPP. 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 5.0E-05 2.2E-08 Second Quarter 1.4E-04 3.0E-08 Third Quarter 1.4E-05 3.0E-08 Fourth Quarter 2.3E-06 1.4E-08 Annual  ; 1.4E-04 8.3E-08 Page 22

2019 Annual Environmental and Effluent Release Report Carbon-14 Supplemental Information Carbon-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. Carbon-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. It is released primarily from Boiling Water Reactors through the Off-gas system in the form of carbon dioxide (CO2). 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 requires an 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 because the dose contribution had been considered negligible compared to the dose impact from effluent releases of noble gases, tritium, particulates, and radioiodines.

This report contains estimates of the gaseous C-14 radioactivity released and the resulting public dose resulting from this release. The calculation is performed using a spreadsheet provided by EPRI and is based on power production and is adjusted for growing season, percent daylight, age (adult) and undepleted atmospheric dispersion (x/Q) value for the critical receptor. This method for estimating C-14 released has been endorsed by the NRC.

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. \

Revisions of ODCM tables and distances due to changing meteorological conditions over time caused distance corrections. This affected the x/Q value used to calculate C-14. The most conservative distance and updated x/Q value changed C-14 values significantly from last year's AEERR and is the contributing factor. Refer to Table 4, Table 7, and Table 9 for C-14 estimated release values and doses.

Groundwater Monitoring Program Based on the Environmental Resource Management hydrogeology study, 12 groundwater monitoring wells were recommended for the site. Since most groundwater flow drains north toward Lake Erie, the majority of wells are drilled north of the plant. A set of control wells were drilled south of the plant to assess a typical groundwater profile.

There are sets of three wells installed at four locations. Each set has a shallow well with a depth of approximately 25 feet, a mid-depth well with a depth of approximately 50 feet, and a deep-well of approximately 75 feet in depth. These three depths are designated A, B, and C, from shallowest to deepest, respectively.

PNPP has an Underdrain system to prevent groundwater hydrostatic pressure buildup on plant structures. The Underdrain system has two installed radiation monitors that assess the process stream prior to the stream flowing into the Emergency Service Water system.

Refer to Figure 2 for locations of Groundwater Wells 1A through 4C and Underdrain Manholes 20 and 23. These wells and manholes encompass the groundwater monitoring locations at PNPP. j Page 23

2019 Annual Environmental and Effluent Release Report H Manholes Piezometers

(_) Groundwater Wells Figure 2: Underdrain System and Groundwater Monitoring Wells Page 24

2019 Annual Environmental and Effluent Release Report The monitoring wells are sampled twice annually, in spring and fall. The samples are shipped to a vendor for gamma isotopic and tritium analysis. Any positive result less than 500 pCi/L is considered as background activity and not due to plant operations. The ODCM reporting level for tritium in an environmental water sample is 20,000 pCi/L. The tritium results of samples obtained in 2019 can be found in Table 13. There was no indication of any effluent releases via grouhdwater and no known spills/leaks to groundwater for this reporting year. v / f ' .J, .

Table 13: Summary of Onsite Groundwater Samples Monitoring Well Spring Fall

, -H-3-, pCi/L H-3, pCi/L

.... 1A * -'-V-:: <150 <150 1B <150 <150 1C , , , <150 ' <150 2A <150 <150 2B '* <154 <150 2C NS NS

' 3A <150 254 3B <150 <150 3C <150 <150 4A <150 212 4B , , <150 <150..."

4C <150 <150

(<) Less than valuesrepreseht the MDA of the instrument at the time of analysis NS-Insufficient sample volume for analysis  ? *  ;

The Underdrain manholes are sampled and analyzed quarterly for principal gamma emitters and tritium by PNPP personnel in accordance with site procedures. The tritium results of samples obtained in 2019 can be found in Table 14.:

Table 14: Summary of Underdrain Manhole Samples^

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Underdrain Manhole H-3, pCi/L H-3, pCi/L H-3, pCi/L H-3, pCi/L

<1.0E-05 <1.0E-05 <1.0E-05 <1.0E-05 20

<1.0E-05 .OE-05 <1.0E-05 .OE-05 23

(<) Less than values represent the ODCM LLD value Page 25

2019 Annual Environmental and Effluent Release Report RADIOLOGICAL ENVIRONMENTAL MONITORING Introduction The 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 Appendix B of the PNPP Operating License, Technical Specifications, and the ODCM. The Nuclear Regulatory Commission 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 variables. 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 is significant and valuable, detailed sampling methods and >.

procedures are followed to ensure 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 when available, water, and vegetation to perform an independent verification of PNPP's REMP.

Sampling Locations REMP samples are collected at numerous locations, both on site and up to 16.2 miles away from the plant. Sampling locations are divided into two general categories: indicator and control. Indicator locations are relatively close to the plant and monitor for any environmental impact due to plant operations. Control locations are those that are unaffected by plant operation; they are a greater distance from the plant and 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 15, 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.

Page 26

2019 Annual Environmental and Effluent Release Report Table 15: REMP Sampling Locations Location # Description Miles Direction Media (1)

-*. 1 Chapel Road 3.4 ENE , TLD, AIP 2 Kanda Garden 1.9 ENE Broadleaf Vegetation 3 Meteorological Tower 1.0 . SE- TLD, AIP

, *, 4 Site Boundary 0.7 S  : TLD, AIP 5 Quincy Substation 0.6 SW TLD, AIP 6 Concord Service Center  ! li.O SSW TLD, AIP 7 Site Boundary 0.6 NE TLD, AIP 8 Site Boundary 0.8 E TLD 9 Site Boundary 0.7 ESE TLD 10 Site Boundary 0.8 SSE TLD 11 Parmly Rd. at Center 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 Broadleaf Vegetation 20 Rainbow Farms 1.9 E Broadleaf Vegetation 21 Hardy Rd. - Painesville Township Park 5.1 WSW TLD 23 High St. Substation 7.9 WSW TLD 24 . , St. Clair Ave. at Mentor Substation 15.1 SW TLD 25 Offshore - PNPP discharge 0.6 NNW Fish 29 River Rd.at Turney Rd. 4.3 SSE TLD 30 Lane Rd. 4.8 SSW TLD 31 Wood Rd. at River Rd. 4.8 SE TLD 32 Offshore - Mentor-on-the-Lake 15.8 WSW Fish 33 River Rd. at Blair Rd. 4.5 S TLD 34 PNPP Intake 0.2 NW Surface Water 35 Site Boundary 0.6 E TLD, AIP 36 Lake County Water Plant 3.9 WSW TLD, Drinking Water 37 Gerlica Farm 1.5 ENE Broadleaf Vegetation 39 Painesville Purification Plant 8.3 W Drinking Water 53 3715 Parmly Rd. 0.5 WSW TLD 54 Hale Rd. School 4.6 SW TLD 55 Center Rd. behind soccer field 2.5 S TLD 56 Madison High School 4.0 ESE TLD 57 Perry High School 1.7 S TLD 58 Antioch Rd. 0.8 ENE TLD Page 27

2019 Annual Environmental and Effluent Release Report Location # Description Miles ' Direction Media (1) 59 Lake Shoreline at Green Rd. 4.0 ENE Surface Water 60 Lake Shoreline at Perry Park 1.0 WSW Surface Water 64 Northwest Drain Mouth 0.4 WNW Sediment 66 Lake Shore, Metropolitan Park 1.4 NE Sediment 70 H&H Farm Stand 16.2 SSW Broadleaf Vegetation (1) AIP - Air, Iodine and Particulate TLD = Thermoluminescent Dosimeter Page 28

2019 Annual Environmental and Effluent Release Report NNW N NW WNW ENE wsw ESE ssw SSE 2 MILES Figure 3: REMP Sampling Locations within Two Miles of the Plant Site Page 29

2019 Annual Environmental and Effluent Release Report sw ssw SSE SE 0 1 2 3 4 5 10 MILES Figure 4: REMP Sampling Locations between Two and Eight Miles from the Plant Site Page 30

2019 Annual Environmental and Effluent Release Report Figure 5: REMP Sampling Locations Greater Than Eight Miles from the Plant Site Page 31

2019 Annual Environmental and Effluent Release Report Sample Analysis When environmental samples are analyzed for radioactivity, several types of measurements are performed to provide information about the types of radiation and radionuclides present.

The major analyses that are performed are discussed below.

Gross beta activity measures the total amount of beta-emitting radioactivity present in a sample and acts as a tool to identify samples that may require further analysis. Beta radiation may be released by many different radionuclides. Since beta-decay results in a continuous energy spectrum rather than the discrete energy levels, or "peaks", associated with gamma radiation, identification of specific beta-emitting nuclides is more difficult.

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

Gamma spectral analysis provides more specific information than does the analysis for gross beta activity. Gamma spectral analysis identifies each radionuclide and the amount of radioactivity present in the sample that is 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 (e.g., air sample charcoal cartridges) are analyzed directly by gamma spectral analysis. With other media (e.g., milk when available), the radioiodines are extracted by chemical separation before being analyzed by gamma spectral analysis.

Tritium activity analysis measures the amount of the radionuclide tritium (H-3) present in a sample. Tritium is an isotope of hydrogen that emits low-energy beta particles. Tritium occurs naturally from interactions with atmospheric cosmic rays and is also man-made from the nuciear fission process.

Gamma doses received by Thermoluminescent Dosimeters (TLD) while in the field are determined by a special laboratory procedure. Thermoluminescence is a process by which ionizing radiation interacts with the sensitive phosphor material in the TLD. Energy is trapped in the TLD material and can be stored for months or years. This capability provides a method to measure the dose received bver long periods of time. The amount of energy that was stored in the TLD as a result of interaction wjth 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. Table 16 provides a list of the analyses performed on environmental samples collected for the PNPP REMP.

The required REMP detection limits for samples is determined by sample media and the radionuclide that is being analyzed. The NRC has established LLDs for REMP sample analysis. These LLDs are listed in the PNPP ODCM. The vendor laboratory for REMP sample analysis has complied with these LLDs.

Page 32

2019 Annual Environmental and Effluent Release Report Table 16: REMP Sample Analyses Type Sample Frequency Analysis Atmospheric Airborne Qross Beta Activity & . .,

Weekly & Quarterly Particulates Gamma Spectral Analysis..

Monitoring Airborne lodine-131

• Weekly Radioiodine Monthly &

Terrestrial Gamma Spectral Analysis &

Milk . , Semi-Monthly when Monitoring lodine-131 l animals are on pasture Broadleaf Monthly during Gamma Spectral Analysis &

Veqetation . growinq season lodine-131 .....

Gross Beta Activity &

Aquatic Monitoring Water Monthly Gamma Spectral Analysis Quarterly Tritium Activity Fish Semi-Annually Gamma Spectral Analysis Sediment Semi-annually Gamma Spectral Analysis Quarterly &

Direct Radiation Gamma Dose TLD Monitoring Annually Sampling Program  ?

The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the environmental monitoring 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, 2019 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 those limits.

Program Changes There were no changes to the REMP program during this reporting period.

Atmospheric Monitoring Air Air sampling is conducted to detect any increase in the concentration of airborne

^radionuclides. The PNPP REMP maintains an additional two air sampling locations above the five locations (four indicators and one control) required by the ODCM. Six 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 draw continuous samples at a rate of approximately two cubic feet per minute. The air is drawn through glass fiber filters to collect Page 33

2019 Annual Environmental and Effluent Release Report participate 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 364 air participate and 364 air radioiodine samples were collected arid analyzed.

Gross beta activity was detected in 364 of the 364 air samples. The average gross beta activity for indicator locations was 0.023 pCi/m3 and the controls was 0.025 pCi/m3.

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 2019 and previous years. In addition, all radioiodine samples were less than the lower limit of detection for ipdine-131.

With the exception of naturally-occurring beryllium-7, no radionuclides were identified in the quarterly gamma spectral analysis above the LLD values.

0.035 0 025 m

E 0.02 -

u Q. 0.015 ~

0.01 -

0.005 -  :::

0 -

. . - , Year ' ' v:

. . . Indicator Control Figure 6

Annual Average Gross Beta Activity, in Air Terrestrial Monitoring Collecting and analyzing samples of milk when available and broadleaf vegetation provides data to assess the build-up of radionuclides that may be ingested by humans. The historical data from soil and vegetation samples provides information on atmospheric radionuclide deposition.

Page 34

2019 Annual Environmental and Effluent Release Report Milk Since the milk sampling locations do not meet the requirements of the ODCM (no milk-producing animals are located within the required distance), broadleaf vegetation sampling (discussed below) is performed. Milk was collected from the available locations to augment vegetation sampling until Spring 2018.

Broadleaf Vegetation Because there is not a milking animal within 5 km of the plant, PNPP sampled broadleaf vegetation as required by the bDCM. These samples are collected monthly during the growing season from four gardens in the vicinity of PNPP and one control location 16.2 miles SSW from PNPP.

Forty-one (41) samples were collected and analyzed by gamma spectral analysis. Four vegetation types were grown and collected: collard greens, turnip greens, Japanese greens, and Swiss chard. Beryllium-7 and potassium-40, both naturally-occurring radionuclides, were found in the samples. No other radionuclides were detected: ..

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

Water Water is sampled from five locations along Lake Erie in the vicinity of the PNPP as required by the PNPP ODCM when available and weather permits. Fifty-four (54) water samples were collected and analyzed for gross beta activity and gamma spectral analysis. From these monthly samples, 18 quarterly composite, samples were analyzedfor tritium activity.

Gross beta activity was detected in 42 of the 54 samples collected. The indicator average gross beta activity was 1.3 pCi/L and the control average gross beta activity was 1.2 pCi/L. Refer to Figure 7 for the annual average gross beta activity for both indicator and control locations. No tritium or gamma activity was detected.

Page 35

2019 Annual Environmental and Effluent Release Report 0000 rg (N (N <n rsliN (NrsirM Year Indicator Control Figure 7: Annual Average Gross Beta Activity, in Water Sediment Sampling shoreline sediments provides an indication of the accumulation of particulate ;

, radionuclides which may lead to an external radiation source to fishermen and swimmers from shoreline exposure. Sediment was sampled from two locations.

Four sediment samples were collected and analyzed by gamma spectroscopy. The only radionuclide detected was naturally-occurring potassium-40.

Fish Fish are analyzed primarily to quantify the radionuclide intake by humans and secondarily to serve as indicators of radioactivity in the aquatic ecosystem. Fish are collected from two Ideations annually during the fishing season as required by the ODCM. Important sport or commercial species are targeted, and only the fillets are sent to the laboratory for analysis.

Twenty-three fish samples were collected and analyzed: 13 indicator and 10 control samples.

The species were; lake trout, smallmouth bass, white perch, walleye, gizzard chad, redhorse sucker, common carp, white sucker, channel catfish, freshwater drum, white bass, and yellow perch. Only naturally-occurring potassium-40 was detected in these samples.

Page 36

2019 Annual Environmental and Effluent Release Report Direct Radiation Monitoring Thermoluminescent Dosimeter (TLD)

Environmental radiation is measured directly at 27 locations around the PNPP site and at two control locations. The locations are positioned in two rings around the plant as well as at the site boundary. The inner ring is within a one-mile radius of the plant site; the outer ring is four to five miles from the plant. The control locations are over ten miles from the plant in the two least prevalent wind directions. Each location has three TLDs.two of which are changed quarterly, and one that is changed annually: ,  ;

A total of 277 TLDs were collected and analyzed. This includes 24$ collected on a quarterly basis and 29 collected annually. Annual TLDs are not required per the ODCM arid are used for supplemental data only.

The annual average dose for all indicator locations was 58.9 mrerfi and 57J mrem for the control locations. ,

The average quarterly dose for the indicator locations was 12.9 mrem* and 12.9 mrem for the control locations (Q-6 and Q-24). Refer to Figure 8 for the average quarterly TLD dose rates for both indicator and control locations.

18 0 <- J o

o

-r\i Year Indicator Control Figure 8: Average Quarterly TLD Dose Conclusion {

There are no discernable trends or increase in radiological parameters when comparing current monitoring results to pre-operatidnal studies. Non-routine analyses were not required during this reporting period. There is no detectable radiological effect on the surrounding environment due to operation of the Perry Nuclear Power Plant.

Page 37

2019 Annual Environmental and Effluent Release Report Inter-Laboratory Cross-Check Comparison Program Introduction The purpose of the Inter-laboratory Cross-Check Comparison Program is to provide an independent check on the vendor laboratory's analytical procedures. Samples with a known concentration of specific radionuclides are provided to the vendor laboratory. The vendor laboratory measures and reports the concentration of specified radionuclides. The known values are then compared to the vendor results. Results consistently outside established acceptance criteria indicate a need to check instruments or procedures. Regulatory Guide 4.15 specifically requires that contractor laboratories that performed environmental measurement participate in the EPA's Environmental Radioactivity Laboratory Inter-Comparison Studies Program, or an equivalent program.

The EPA's program is no longer funded or offered. The reason that the EPA program was referenced in the regulatory guide is that the EPA standards were traceable to National Bureau of Standards (now known as National Institute of Standards and Technology). In response, the vendor lab incorporated a program offered by Environmental Resource Associates (ERA), which covered the same analyses in the same matrix at the same frequency as the EPA program. ERA has received NIST accreditation as an equivalent program. In addition to comparison cross checks performed with ERA, the vendor laboratory routinely monitors the quality of their analyses by analyzing "spiked" samples (samples with a specific quantity of radioactive material present in them) and participating in the Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

See Appendix A, for the vendor Inter-Laboratory Cross-Check Comparison Program Results.

Land Use Census Introduction Each year a Land Use Census is conducted to identify the locations of the nearest available milking 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 REMP. The census is conducted by traveling all roads within a five-mile radius of the plant site and recording and mapping the locations of the nearest resident, available milk animal, and vegetable garden. The Land Use Census was conducted in August, 2019. The census identified the garden, and residence locations identified in Table 17 and Table 18 and depicted in Figure 9. Note that the W, WNW, NW, NNW, N, and NNE sectors extend over Lake Erie and are not included in the survey. No location with an available milking animal was discovered.

Page 38

2019 Annual Environmental and Effluent Release Report 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.

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

There were no changes to the REMP sampling locations compared to the 2018 Land Use Census. Refer to Figure 3, Figure 4, and Figure 5 for the REMP sampling locations.

Table 17 identifies the nearest residences,5by sector, to the PNPP. There were no changes from the 2018 Land Use Census.' Refer to Figure 9 for map locator numbers.,

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 Ridqe 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 39

2019 Annual Environmental and Effluent Release Report Table 18 lists the nearest gardens by sector to the PNPP consisting of at least 500 square feet. Refer to Figure 9 for map locator numbers.

Table 18: Nearest Garden, By Sector Sector Location Address Miles from Map Locator PNPP Number NE 2348 W. Hemlock 0.9 11 ENE 2452 Antioch 1.1 12 E 2634 Antioch 1.1 3 l 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 3300 Ohio St. 2.3 17 SW 3021 Perry Park 1.3 13 WSW 3460 Parmly 1.0 14 Page 40

2019 Annual Environmental and Effluent Release Report Figure 9: Land Use Census Map Page 41

2019 Annual Environmental and Effluent Release Report Annual Environmental Operating Report The Nuclear Regulatory Commission (NRC) issued Amendment No. 178 to Facility Operating License No. NPF-58 on 10/19/17. This amendment revises the PNPP "Environmental Protection Plan (Nonradiological)" to clarify and enhance wording to remove duplicative or outdated program information, and to relieve the burden of submitting unnecessary or duplicative information to the NRC.

As a result of the above Amendment issued in October 2017, redundant program information is no longer required to be compiled and included in this report. This includes the sections: Clam/Mussel Monitoring, Herbicide Applipations, and Special Reports which included NPDES Permit exceedances and the Environmental Protection Plan from previous years.

Page 42

2019 annual Environmental and Effluent Release Report Appendix A Inter-Laboratory Cross Check Comparison Program Results

2019 Annual Environmental and Effluent Release Report Environmental, Inc.

Midwest Laboratory 700 Landwehr Rood'Northbrook. II 60062-2310 phone (647) 66+0700 <? fax {847) 864-4317 APPENDIX A INTERLABORATORY AND INTRALABORATORY COMPARISON PROGRAM RESULTS NOTE: Appendix A is updated four times a year. The complete appendix is included in March.

June, September and December monthly progress reports only.

January. 2019 through December. 2019

Appendix A Interlaboratorv/ Intralaboratorv Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interiaboratory 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 RAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Results in Table A-2 were obtained through participation in the New York Department of Health Environmental Laboratory Approval Program (ELAP) PT Table A-3 lists results for thermoluminescent dosimeters (TLDs), via irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.

Table A-4 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-5 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-6 lists analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the each result being with 25% of the mean of the two results or the two sigma uncertanties of each result overlap.

The results in Table A-7 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-8 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory acceptance criteria for various analyses.

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

A-1

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES Analysis Ratio of lab result to known value.

Gamma Emitters 0.8 to 1.2 Strontium-89, 0.8 to 1.2 Strontium-90 Potassium-40 0.8 to 1.2 Gross alpha 0.5 to 1.5 Gross beta 0.8 to 1.2 Tritium 0.8 to 1.2 Radium-226. 0.7 to, 1.3 Radium-228 Plutonium 0.8 to 1.2 0.8 to 1.2 lodine-129.

lodine-131 Njckel-63. 0.7 to 1.3 Technetium-99, Uranium-238

< lron-55 0.8 to 1.2 Other Analyses 0.8 to 1.2 A-2

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

__^ RAD study Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance ERW-71 1/7/2019 Ba-133 97.9 +/-4.5 99.5 84.1 -109 Pass ERW-71 1/7/2019 Cs-134 45.4 +/-3.1 49.1 39.5 -54.0 Pass ERW-71 1/7/2019 Cs-137 129 +/-6 125 112 -140 Pass ERW-71 1/7/2019 Co-60 98.1 +/-4.1 96.4 86.8 -108 Pass ERW-71 1/7/2019 Zn-65 80.4 +/- 7.8 77.4 69.5 +/-93.2 Pass ERW-73 1/7/2019 Gr. Alpha 22.2 +/-1.6 21.8 10.9 -29.5 Pass ERW-73 1/7/2019 Gr. Beta 46.4 +/-1.4 55.7 38.1 -62.6 Pass ERW-75 1/7/2019 Ra-226 7.19 +/-0.30 7.37 5.55 +/- 8.72 Pass ERW-75 1/7/2019 Ra-228 4.02 +/- 0.70 4.28 2.48 -5.89 Pass ERW-75 1/7/2019 Uranium 50.2 +/- 2.9 68.2 55.7 -75.0 Failb ERW-77 1/7/2019 H-3 2,129 +/-158 2,110 1,740 -2,340 Pass ERW-397 2/11/2019 1-131 27.2 +/-1.0 25.9 25.1 -30.6 Pass ERW-1141 4/8/2019 Ra-226 7.58 +/- 0.53 7.15 5.39 -8.48 Pass ERW-1141 4/8/2019 Ra-228 , 2.64 +/-0.79 2.94 1.54 -4.35 Pass ERW-1141 4/8/2019 Uranium 67.0 +/- 0.9 55.9 45.6 -61.5 Failc ERW-2471 7/8/2019 Ba-133 66.5 +/- 4.0 66.9 55.8 -73.6 Pass  ;

ERW-2471 7/8/2019 Cs-134 29.6 +/- 2.6 32.0 25.1 -35.2 Pass ERW-2471 7/8/2019 Cs-137 21.3 +/-3.6 21.4 17.6 -26.7 Pass ERW-2471 7/8/2019 Co-60 99.9 +/-4.4 95.1 85.6 -107.0 Pass ERW-2471 7/8/2019 Zn-65 43.7 +/- 6.2 41.2 35.3 -51.4 Pass ERW-2473 7/8/2019 Gr. Alpha 41.7 +/-2.1 70.6 37.1 -87.1 Pass ERW-2473 7/8/2019 Gr. Beta 57.0 +/-1.6 63.9 44.2 -70.5 Pass ERW-2477 7/8/2019 Ra-226 16.2 +/-0.5 18.5 13.8 -21.1 Pass ERW-2477 7/8/2019 Ra-228 6.2 +/- 0.8 8.2 5.2 -10.3 Pass ERW-2477 7/8/2019 Uranium 63.8 +/- 3.6 68.3 55.8 -75.1 Pass ERW-2479 7/8/2019 H-3 8,630 +/- 200 16,700 14,600 -18,400 Faild ERW-2475 7/8/2019 1-131 33.6 +/-1.3 29.6 24.6 -34.6 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resource Associates (ERA).

b In order to get to the root cause of the above Tail" resolution the U-232 tracer was standardized using a known concentration of NIST U-238 solution. A duplicate analysis was performed and the results obtained were well within the acceptance range (Known value for Total Uranium=68.2 pCi/L, acceptance range of (55.7-75 pCi/L). The results obtained were 63.3 pCi/L and 66.0 pCi/L respectively. '

c The standardized U-232 value utilized on ERA sample ERW-1141 above was found to be estimated high due to interferences in the U-238 solution causing ERW-1141 to fail the study. After performing U-isotopic chemistry on the NIST-Uranium solution to remove interferences a more accurate U-232 tracer concentration was obtained.

The Uranium result in the subsequent ERA PT study was acceptable. See ERW-2477 Uranium result above.

d ElML's routine H-3 analysis does include a blank sample. The ERA provided blank was paired with a H-3 standard vial and ElML's blank was also paired with a standard vial. Inadvertently the efficiency was overestimated by a factor of 2.

This understated the calculated results by half. The result of reanalysis (17,400 pCi/L) is within the control limits for the study.

A-3

TABLE A-2. Interlaboratory Comparison Crosscheck program, New York Department of Health (ELAP)8.

Concentration (pCi/L)

Analysis Laboratory Assigned Acceptance Lab Code Date Result .Value Limits Acceptance Shipment 427R 5250 +/- 229 4991 4280 - 5490 Pass NYW-3472 9/17/2019 H-3 18.0 +/-1.2 20.1 9.99-27.5 Pass NYW-3476 9/17/2019 Gross Alpha 22.7 +/-1.0 27.2 17.1 -35.1 Pass NYW-3476 9/17/2019 Gross Beta 18.7 +/-1.8 15.6  ;;.'12.8 -19.3 Pass NYW-3478 9/17/2019; 1-131 Ra-226 5.02 +/- 0.37 4.41 3.37 -5.43 Pass NYW-3480 9/17/2019 Ra-228 16.0 +/-1.9 18.3 12.3-21.9 Pass NYW-3480 9/17/2019 13.7 +/-0.9 13.9 11.0-15,7 Pass NYW-3480 9/17/2019 Uranium 63.9 +/- 4.0 63.0 ~ 56.7-71.8 Pass NYW-3482 9/17/2019 Co-60 108 +/-9 113 97.2-129 Pass '

NYW-3482 9/17/2019 Zn-65 53.3 +/-4.3 61.9 51.4 -68.2 Pass '

NYW-3482 9/17/2019 Ba-133 47.2 +/- 3.4 55.8 45.1 -61:4 Pass NYW-3482 9/17/2019 Cs-134 52.0 +/- 4.6 53.8 48.4 -62.0 Pass NYW-3482 9/17/2019 Cs-137 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by the New York Department of Health Laboratory Approval Program(NY ELAP).

A-4

TABLE A-3. Thermoluminescent Dosimetry. (TLD, CaSO4: Dy Cards).'

mrem Lab Code Irradiation Delivered Reported6 Performance0 Date Description Dose Dose Quotient (P)

Environmental. Inc. Group 1 \

2019-1. 11/11/2019 Spike 1 126.0 128.3 0.02 2019-1 11/11/2019 Spike 2 126.0 122.2 -0.03 2019-1 11/11/2019 Spike 3 126.0 122.5 -0.03 2019-1 11/11/2019 Spike 4 126.0 119.3 -0:05 2019-1 11/11/2019 Spike 5 126.0 116.9 -0.07 2019-1 11/11/2019 Spike 6 126.0 109.5 -0.13 2019-1 11/11/2019 Spike 7 126.0 114.6 -0.09 2019-1 11/11/2019 Spike 8 126.0 121.8 -0.03 2019-1  ; 11/11/2019 Spike 9 126.0 .120.2 -0.05 2019-1 11/11/2019 Spike 10 126.0 126.4 0.00 2019-1 11/11/2019 Spike 11 126.0 125.0 -0.01 2019-1 11/11/2019 Spike 12 126.0 109.0 -0.13 2019-1 11/11/2019 Spike 13 126.0 123.4 -0.02 2019-1 11/11/2019 Spike 14 126.0 118.2 -0.06 2019-1 11/11/2019 Spike 15 126.0 134.3 0.07 2019-1 11/11/2019 Spike 16 126.0 120.1 -0.05 2019-1 11/11/2019 Spike 17 126.0 131.3 0.04 2019-1 11/11/2019 Spike 18 126.0 120.4 -0.04 2019-1 11/11/2019 Spike 19 126.0 121.1 -0.04 2019-1 11/11/2019 Spike 20 126.0 " 122.8 -0.03 Mean (Spike 1-20) 121.4 -0.04 Passd Standard Deviation (Spike 1-20) 6.2 0.05 Passd a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose, b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(10)Ka = 1.20 . mrem/cGy = 1000.

c Performance Quotient (P) is calculated as ((reported dose - conventially true value) + conventially true value) where the

, conventially true value is the delivered dose.

d Acceptance is achieved when neither the absolute value of the mean of the P values, nor the standard deviation of the P values exceed 0.15.

A-5

TABLE A-3. Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).'

mrem Lab Code Irradiation Delivered Reportedb Performance0 Date Description Dose Dose Quotient (P)

Environmental. Inc. Group 2 11/11/2019 Spike 21 79.0 78.8 0.00 2019-2 11/11/2019 Spike 22 { 79.0 71.8 -0.09 2019-2 11/11/2019 Spike 23 79.0 75.8 -0.04 2019-2 11/11/2019 Spike 24 79.0 71.3 -0.10 2019-2 11/11/2019 - Spike 25 79.0 74.5 -0.06 2019-2

-0.09 1 2019-2 11/11/2019 Spike 26 79.0 71.6 11/11/2019 Spike 27 79.0 73.3 -0.07 2019-2 2019-2 11/11^2019 Spike 28 79.0 - 74.0 -006 11/11/2019 Spike 29 79.0 73.8 -0.07 2019-2 11/11/2019 Spike 30 79.0 76.0 -0.04 2019-2 11/11/2019 Spike 31 79.0 76.7 -0.03 2019-2 11/11/2019 Spike 32 79.0 77.8 -0.02 2019-2 11/11/2019 Spike 33 79.0 75.2 -0.05 2019-2 11/11/2019 Spike 34 79.0 69.1 -0.13 2019-2 11/11/2019 Spike 35 79.0 68.7 -0.13 2019-2 11/11/2019 Spike 36 79.0 68.2 -0.14 2019-2 11/11/2019 Spike 37 79.0 67.9 -0.14 2019-2 11/11/2019 Spike 38 79.0 68.9 -0.13 2019-2 11/11/2019 Spike 39 79.0 78.1 -0.01 2019-2 11/11/2019 Spike 40 79.0 68.6 -0.13 2019-2 73.0 -0.08 Pass Mean (Spike 21-40)

I  ;*

3.6 0.05 Pass Standard Deviation (Spike 21-40) a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the resutts were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.

b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(10)K8= 1.20. mrem/cGy = 1000.

c Performance Quotient (P) is calculated as ((reported dose - conventially true value) conventially true value) where the conventially true value is the delivered dose. .

d Acceptance is achieved when neither the absolute value of the mean of the P values, nor the standard deviation of the P values exceed 0.15.

A-6

TABLE A-4. In-House "Spiked" Samples Concentration8 Lab Code" Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limits"

- SPW-61 1/5/2019 Ra-226 13.4 +/-0.4 12.3 9.8 -14.8 Pass 1.09 SPW-118 1/14/2019 H-3 15,463 +/-369 16.507 13,206 -19.808 Pass 0.94 SPW-178 1/16/2019 Ra-228 17.7 +/-2.1 15.1 12.10 -18.14 Pass 1.17 SPW-199 1/18/2019 Sr-90 17.6 +/-1.2 17.9 14.3-21.5 Pass 0.98 SPW-250 1/24/2019 Ni-63 356.3 +/- 44.5 465 326 - 605 Pass 0.77 SPW-256 1/15/2019 Ra-226 12.0 +/-0.4 12.3 9.8 -14.8 Pass 0.98 SPW-271 3/18/2019 H-3 22.035 +/- 450 21,700 17.360 -26,040 Pass 1.02 SPW-281 1/25/2019 Ra-226 11.6 +/-0.4 12.3 9.8-14.8 Pass ,0.94 W-012119 4/29/2016 Cs-134 37.3 +/-10.6 36.2 29.0 - 43.4 Pass 1.03 W-012119 4/29/2016 Cs-137 82.7 +/- 8.0 71.9 57.5 - 86.3 Pass 1.15 W-012319 4/29/2016 Cs-134 33.4 +/-10.1 36.2 25.3 -47.1 Pass 0.92 W-012319 4/29/2016 Cs-137 79.1 +/-9.6 71.9 57.5 - 86.3 Pass 1.10 W-012519 4/29/2016 Cs-134 35.0 +/- 7.7 - 36.2 29.0 - 43.4 Pass 0.97 W-012519 4/29/2016 Cs-137 79.2 +/- 7.9 71.9 57.5 - 86.3 Pass 1.10 W-012919 4/29/2016 Cs-134 32.3 +/- 8.3 36.2 29.0 - 43.4 Pass 0.89 W-012919 4/29/2016 Cs-137 82.3 +/- 8.3 - 71.9 57.5 -86.3. Pass 1.14 SPW-370 3/19/2019 H-3 21,689 +/-444 21,700 17,360 -26,040 Pass 1.00 SPW-400 1/31/2019 Ra-226 11.6 +/-0.4 12.3 8.6 -16.0 Pass 0.95 '

SPW-461 2712/2019 Ra-226 11.1 +/-0.4 12.3 8.6 -16.0 Pass 0.90 W-020619 4/26/2016 Cs-134 35.0 +/-14.9 36.2 29.0 - 43.4 Pass 0.97 W-020619 4/29/2016 Cs-137 72.8 +/- 8.9 71.9 57.5 - 86.3 Pass 1.01 W-020819 4/26/2016 Cs-134 36.7 +/- 8.6 36.2 29.0 - 43.4 Pass 1.01 W-020819 4/29/2016 Cs-137 76.7 +/-8.7 71.9 57.5 - 86.3 Pass 1.07 SPW-568 2/21/2019 Ra-226 10.3 +/-0.3 12.3 8.6 -16.0 Pass 0.84 W-021319 4/29/2016 Cs-134 37.7 +/-11.5 36.2 29.0 - 43.4 Pass 1.04 W-021319 4/26/2016 Cs-137 75.8 +/- 9.6 71.9 57.5 - 86.3 Pass 1.05 SPW-469 3/19/2019 H-3 21,696 +/-447 21,700 17,360-26,040 Pass i.oo SPW-600 3/6/2019 H-3 20,710 +/-425 21,700 17,360 -26,040 Pass 0.95 SPW-837 3/21/2019 Ra-228 11.7 +/-1.5 15.1 10.58 -19.66 Pass 0.78 SPW-709 3/19/2019 H-3 20,369 +/- 421 21,700 17,360 -26,040 Pass 0.94 SPW-818 3/19/2019 H-3 20,457 +/- 424 21,700 17,360 -26,040 Pass 0.94 SPW-845 3/22/2019 U-234 15.1 +/-0:5 13.6 9.5 -17.7 Pass 1.11 SPW-845 3/22/2019 U-238 15.3 +/-0.5 13.1., 9.2 -17.0 Pass 1.17 SPW-934 3/19/2019 H-3 20,487 +/- 421 21,700 17,360-26,040 Pass 0.94 SPW-1061 3/1/2019 Ra-226 10.6 +/-0.3 12.3 8.6 -16.0 Pass 0.86 SPW-1091 4/10/2019 H-3 20,323 +/- 421 ' 21,700 17,360 -26.040 Pass 0.94 SPW-1093 4/8/2019 Ra-228 14.9 +/-1.9 15.1 ib.6 -19.6 - Pass 0.98 SPW-1267 4/16/2019 H-3 20,302 +/-421 21,700 17,360 -26,040 Pass 0.94 SPW-1339 4/18/2019 H-3 19,924 +/-417 21,700 17,360-26,040 Pass 0.92 SPW-1403* 4/25/2019 Gr. Alpha 56.7 +/- 2.6 72.4 36.2 -108.6 Pass 0.78 SPW-1403e .4/25/2019 Gr. Beta 43.2 +/-1.4 54.8 43.8 - 65.8 Fail 0.79 SPW-1427 4/26/2019 H-3 20,119 +/-418 21,700 15,190 -28,210 Pass 0.93 SPW-1537 5/6/2019 Sr-90 19.9 +/-1.2 17.9 . 14.3-21.5 Pass 1.11 W-050719 4/29/2016 Cs-134 38.5 +/- 9.0 36.2 29.0 - 43.4 , Pass 1.06 W-050719 4/26/2016 Cs-137 85.2 +/- 8.5 71.9 57.5 - 86.3 Pass 1.18 SPW-1582 5/9/2019 H-3 20,492 +/- 423 21,700 15,190 -28,210 Pass 0.94 A-7

TABLE A-4. In-House "Spiked" Samples Concentration3 Known Control Ratio Lab Code6 Date Analysis Laboratory results

_-2s, n=1c Activity Limits" Acceptance Lab/Known 37.4 +/- 8.9 36.2 29.0-43.4 Pass 1.03 .

W-050919 4/29/2016 Cs-134 81.5 +/-7.8 71.9 57.5 - 86.3 Pass 1.13 W-050919 4/26/2016 Cs-137 Ra-228 14.1 +/-1.7 15.1  ; 10.6-19.6 Pass 0.94 SPW-1596 5/8/2019 Cs-134 36.2 +/-11.7 36.2 29.0-43.4 Pass 1100 W-051419 4/29/2016 75.8 +/- 10.0 71.9 57.5 - 86.3 Pass 1.05 **;

W-051419 4/26/2016 v Cs-137 20,233 +/-420 21,700 ' 15,190 -28,210 Pass 0.93 SPW-1676 5/17/2019 H-3 20,428 +/- 422 21,700 15,190-28,210 Pass 0.94 SPW-1799 '" 5/20/2019 H-3 20,367 +/- 522 21,700 15,190-28,210 Pass 0.94 SPW-1858 5/28/2019 H-3 20,206 +/-419 21,700 15,190-28,210 Pass 0.93 SPW-1890 5/30/2019 H-3 1,1.9 +/-0.3 12.3 y 8.6 -16.0 Pass 0.97 SPW-2014 . 5/31/2019 Ra-226 377 +/-45 464.8 . 325 - 604 Pass 0.81 SPW-2030 6/12/2019 NI-63 20,158 +/-418 21,700 17,360 - 26,040 v Pass  ; 0.93 SPW-2093 . 6/18/2019 H-3 33.0 +/-12.4 36.2 29.0 - 43.4 Pass 0;91 W-062419 4/29/2016 Cs-134 66.0 +/- 10.4 . 71.9 57.5 - 86.3 Pass 0.92 W-062419 4/26/2016 Cs-137 20,032 +/-417 21,700 17,360 - 26,040 Pass  : 0.92 SPW-2338 6/26/2019 H-3 20.4 +/-1.5 - 21.8 10.9-32.7 ':'*' Pass , 0.94 SPW-2552 7/1/2019 Gr. Alpha Gr. Beta 46.1 +/-1.3 55.? 44.6 - 66.8  ; Pass 0.83 SPW-2552 7/1/2019 36.3 +/- 9.2 3612 29.0-43.4 Pass 1.00 W-072619 4/29/2016 Cs-134 Cs-137 , 79.7 +/-7.6 71.9 57.5 - 86.3 Pass *' 1.11 WrO72619 4/26/2016 Ra-226 11.9 +/-0.3 12;3 . 8.6 -16;0 1 Pass 0.97 SPW-3188 7/30/2019 20,128 +/-425 21,700, 17,360 -26,040 Pass 0.93 SPW-2947 8/9/2019 H-3 20,588 +/- 435 21,700 17,360-26,040 Pass 0.95 SPW-3003 8/14/2019 H-3 36.2 +/- 9.2 36.2 29.0 - 43.4 Pass 1.00 W-081519 4/26/2019 Cs-134 78.1 +/- 8.4 71.9 57.5 - 86.3 Pass 1.09 W-081519 4/26/2019 Cs-137 32.8 +/-9.1 36.2 29.0 - 43.4 Pass 0.91 W-082119 4/26/2019 Cs-134 79.1 +/- 7.9 71.9 57.5 - 86.3 Pass 1.10 W-082119 4/26/2019 Cs-137 20,329 +/- 428 21,700 17,360 - 26,040 Pass 0.94 SPW-3151 8/26/2019 H-3 33.3 +/- 17.8 36.2 29.0 - 43.4 Pass 0.92 W-082619 4/26/2019 Cs-134 82.6 +/-13.2 71.9 57.5 - 86.3 Pass 1.15 W-082619 4/26/2019 Cs-137 33.9 +/- 7.0 36.2 29.0-43.4 Pass 0.94 W-082719 4/26/2019 Cs-134 81.4 +/-6.0 71.9 57.5 - 86.3 Pass 1.13 W-082719 4/26/2019 Cs-137 72.4 36.2 -108.6 Pass 0.75 SPW-3359 8/30/2019 Gr. Alpha 54.2 +/- 0.3 59.7 +/-0.2 54.8 43.8 - 65.8 Pass 1.09 SPW-3359 8/30/2019 Gr. Beta 12.7 +/-1.8 15.1 10.6 -19.6 Pass 0.84 SPW-3323 9/6/2019 Ra-228 31.0 +/-11.3 36.2 29.0 - 43.4 Pass 0.86 W-091019 4/26/2019 Cs-134 80.5 +/- 10.0 71.9 57.5 - 86.3 Pass 1.12 W-091019 4/26/2019 Cs-137 19,851 +/-422 21,700 17,360 ^26,040 Pass 0.91 SPW-3349 9/10/2019 H-3 20,267 +/- 431 21,700 17,360 - 26,040 Pass 0.93 SPW-3410 9/13/2019 H-3 39.3 +/- 12.6 36.2 29.0 - 43.4 Pass 1.09 W-091719 4/26/2019 Cs-134 81.1 +/-9.9 71.9 57.5 - 86.3 Pass 1.13 W-091719 4/26/2019 Cs-137 20,036 +/-427 - '21.700 17.360-26,040 *. Pass 0.92 SPW-3450 9/17/2019 H-3 40.0 +/-10.7 36.2 29.0-43.4 Pass 1.10 W-091919 9/19/2019 Cs-134 71.9 57.5-86.3 Pass 0.99 W-091919 9/19/2019 Cs-137 71.0 +/-8.7 11.9 +/-0.3 12.3 8.6-16.0 Pass 0.97 SPW-3569 8/28/2019 Ra-226 21,026 +/-440 21^700 ' 17,360-26,040 Pass 0.97 SPW-3571 9/27/2019 H-3  :

A-8

TABLE A-4. In-House "Spiked" Samples Concentration8 Lab Code" Date Analysis Laboratory results Known Control Ratio 2s. n=1c Activity Limits" SPW-3615 10/1/2019 Ra-228 18.9 12.5 14.9 10.4 -19.3  : Pass 1.27 SPW-3706 10/8/2019 H-3 20.082 +/- 427 21,700 17,360-26,040 Pass 0.93 SPW-4093 10/14/2019 Gr. Alpha 20.8 +/- 0.1 19.7 9.9 - 29.6 Pass 1.06 SPW-4093 -10/14/2019 Gr. Beta 63.2 +/-0.1 61.1 48.9 - 73.3 Pass 1.03 SPW-4095 10/24/2019 H-3 20.684 +/- 432 21,700 17.360-26,040 Pass 0.95 SPW-4144 9/26/2019 Ra-226 12.8 +/-0.3 12.3 8.6 - 16.0 Pass 1.04 W-091719 3/19/2018 H-3 22,291 +/-470 21,700 17,360 - 26,040 Pass 1.03 SPW-4239 10/30/2019 Ra-228 12.4 +/-1.8 14.9 10.4 - 19.3 Pass 0.84 SPW-4254 11/8/2019 H-3 20.187 +/-427 21,700 17.360 -26,040 Pass 0.93 SPW-4368 11/14/2019 H-3 20,386 +/- 429 21,700 17,360 -26,040 Pass 0.94 SPW-4370 10/30/2019 Ra-226 12.8 +/-0.4 12.3 8.6 -16.0 Pass 1.04 SPW-4472 11/21/2019 H-3 20,479 +/- 432.0 21,700 17,360 -26,040 Pass 0.94 SPW-4474 11/22/2019 Sr-90 18.9 +/-1.2 17.9 14.3-21.5 Pass 1.06 SPW-4602 12/5/2019 H-3 20,187 +/-429 21,700 17,360 -26,040 Pass 0.93 W-121119 3/19/2018 H-3 22,734 +/- 477 21,700 17,360-26,040 . Pass 1.05 SPW-4663 12/11/2019 Ra-228 11.2 +/-1.6 14.9 10.4 -19.3 Pass 0.75 SPW-4688 12/13/2019 H-3 20,506 +/- 431 21,700 17,360-26,040 Pass 0.94 SPW-4734 11/15/2019 Ra-226 12.6 +/-0.3 12.3 8.6 -.16.0 Pass 1.02 SPW-4743 12/5/2019 Ra-226 10.0 +/- 0.3 12.3 8.6 -16:0 Pass 0.81 SPW-4745 12/19/2019 H-3 20,067 +/- 427 21,700 17,360-26,040 Pass 0:92 SPW-4889 12/19/2019 Ra-226 9.3 +/-0.3 12.3 8.6 - 16.0 Pass 0.76 SPW-4636 12/27/2019 Tc-99 94.3 +/-8.2 90.3 72.2 - 108.4 Pass 1.04 SPW-4899 1/3/2020 H-3 20,386 +/-432 21,700 17,360-26,040 Pass 0.94 a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

b Laboratory codes : W & SPW (Water). Ml (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 listed in Attachment A of this report.

8 The LCS sample was prepared from an Environmental Resource Associates (ERA) sample of known activity. While the analysis did satisfy the acceptance criteria of the ERA study from which it was sourced, it did not satisfy ElML's internal LCS acceptance criteria. An investigation is in process to determine the reason for the low bias and to evaluate the acceptance criteria.

NOTE: For fish, gelatin is used for the spike matrix. For vegetation, cabbage is used for the spike matrix.

A-9

TABLE A-5. In-House "Blank" Samples.

r Concentration3 Analysis0 Laboratory results (4.66a) Acceptance Lab Codeb Sample Date Type j LLD Activity0 Criteria (4.66 o)

Water 1/7/2019 Gr. Alpha 0.76 -0.30 +/- 0.52 2 SPW-5449 Water 1/7/2019 Gr. Beta 0.42 0.19 +/-0.31 4 SPW-5449 1/7/2019 1-131 0.36 0.13 +/-0.18 1 SPW-34 Water 11/5/2018 Ra-226 0.03 0.15 +/-0.03 2 SPW-60 Water Water 1/14/2019 H-3 148- 42 +/-80 200 SPW-119 Water 1/16/2019 Ra-228 0.93 -0.10 +/-0.42 2 SPW-177 Water 1/18/2019 Sr-89 0.67 0.25 +/- 0.50 5 SPW-198 1/18/2019 Sr-90 . 0.67 -0.16 +/-0.29 1 SPW-198 Water Water 1/24/2019 Ni-63 67 31 +/-41 200 SPW-249 Water 1/15/2019 Ra-226 0.04 0.16 +/-0.03 2 SPW-255 Water 1/25/2019 Ra-226 0.06 -0.09 +/-0,14 2 SPW-280 Water 1/31/2019 Ra-226 0.03 , 0.15 +/-0.03 2 SPW-399 SPW-460 Water 2/12/2019 Ra-226 0.03 0.15 +/-0.02 1 2 Water 2/21/2019 Ra-226 0.03 0.13 +/-0.02 2 SPW-567 3/22/2019 U-234 0.19 0.04 +/-0.14 1 SPW-844 Water 3/22/2019 U-238 0.19 0.00 +/-0.11 1 SPW-844 Water Water 3/21/2019 Ra-228 0.74. 0.53 +/- 0.41 2 SPW-836 Water 3/31/2019 Ra-226 0.04 -0.02 +/-0.03 2 SPW-1060 Water 4/10/2019 H-3 155 -14 +/-72 200 SPW-1090 Water 4/8/2019 Ra-228 0.82 0.75 +/- 0.46 ., 2 SPW-1092 Water 4/16/2019 H-3 152 67 +/-74 200 SPW-1266 Water 4/18/2019 H-3 152 66 +/- 79 200 SPW-1338 SPW-1386 Water 4/8/2019 Ra-226 0.03 0.09 +/- 0.03 2 Water 4/26/2019 H-3 156 34 +/- 75 200 SPW-1426 5/6/2019 Sr-89 0.66 -0.07 +/-0.45 5 SPW-1536 Water 5/6/2019 Sr-90 0.59 -0.10 +/-0.26 1 SPW-1536 Water SPW-1581 Water 5/9/2019 H-3 147 73 +/-77 200 Water 4/22/2019 Ra-226 0.02 0.15 +/-0.02 2 SPW-1644 Water 5/17/2019 H-3 154; -30 +/- 71 200 SPW-1675 Water 5/20/2019 H-3 149 24 +/-73 200 SPW-1798 5/28/2019 H-3 150 54 +/- 74 200 SPW-1857 Water Water 5/30/2019 H-3 152 45 +/-73 200 SPW-1889 5/31/2019 Ra-226 0.01 0.13 +/-0.02 2 SPW-2013 Water Water 6/12/2019 Ni-63 66 10 +/-40 200 SPW-2029 6/18/2019 H-3 154 42 +/-70 200 SPW-2092 Water Water ,6/26/2019 H-3 150 -9 +/-69 200 SPW-2237 6/18/2019 1-131 0.16 0.04 +/- 0.09 1 SPW-2107 Water 0.04 +/- 0.09 1 SPW-2152 Water 6/19/2019 1-131 0.16 A-10

TABLE A-5. In-House "Blank" Samples Concentration8 Lab Code" Sample Date Analysis0 Laboratory results (4.66a) Acceptance Type LLD Activity0 Criteria (4.66 c)

SPW-3187 Water. 7/30/2019 Ra-226 0.02 0.17 +/-0.02 2 SPW-2924 Water 8/6/2019 Sr-89 0.71 -0.06 +/- 0.57 5 SPW-2924 Water 8/6/2019 Sr-90 0.59 0.08 +/- 0.28 1 SPW-2946 Water . 8/9/2019 H-3 152 33 +/- 72 200 SPW-3002 Water 8/14/2019 H-3 152 -22 +/-74 200 SPW-3150 Water 8/26/2019 H-3 151 115 +/-77 200 SPW-3358 Water 8/30/2019 Gr. Alpha 0.44 -0.08 +/- 0.30 2 SPW-3358 Water 8/30/2019 Gr. Beta 0.72 -0.31 +/-0.49 4 SPW-3568 Water 8/28/2019 Ra-226 0.03 0.16 +/-0.03 2 SPW-3322 Water 9/6/2019 Ra-228 0.82 0.46 +/- 0.43 2 SPW-3348 Water 9/10/2019 H-3 150 107 +/-76 200 SPW-3409 Water 9/13/2019 H-3 154 133 +/-79 .200 SPW-3449 Water' 9/17/2019 H-3 147 102 +/-79 200 SPW-3570 Water 9/27/2019 H-3 151 70 +/- 77 200 SPW-3614 Water 10/1/2019 Ra-228 1.29 1.03 +/-0.73 2 SPW-3705 Water 10/8/2019 H-3 147 107 +/- 77 200 SPW-4238 Water 10/30/2019 Ra-228 0.99 0.58 +/- 0.52 2 SPW-4253 Water ' 11/8/2019 H-3 151 80 +/-76 200 SPW-4367 Water 11/14/2019 H-3 154 42 +/- 74 200 SPW-4369 Water 10/30/2016 Ra-226 0.03 0.14 +/- 0.03 2 SPW-4471 Water 11/21/2019 H-3 155 81 +/-77 200 SPW-4474 Water 11/21/2019 C-14 12 0+/-7 200 SPW-4476 Water 11/22/2019 Sr-89 0.62 0.23 +/- 0.45 5 SPW-4476 Water 11/22/2019 Sr-90 0.57 -0.16 +/-0.24 1 SPW-4601 Water 12/5/2019 H-3 155 28 +/- 74 200 SPW-4635 Water 12/9/2019 Tc-99 12 -6+/-7 20 SPW-4662 Water . 12/17/2019 Ra-228 0.77 0.55 +/- 0.42 , 2 SPW-4687 Water 12/13/2019 H-3 150 143 +/- 78 200 SPW-4733 Water 11/15/2019 Ra-226 0.03 . ,  ; 0.13 +/-0.03 2 SPW-4742 Water 12/5/2019 Ra-226 0.04 0.10 +/-0.10 2 SPW-4744 Water 12/19/2019 H-3 151 119 +/-81 200 SPW-4888 Water 12/19/2019 Ra-226 0.03 0.15 +/-0.02 2 SPW-4898 Water 1/3/2020 H-3 159 19 +/-78 200 8 Uquid sample results are reported in pCi/Uter. air filters (pCi/m3). charcoal (pCi/charcoal canister), and solid samples (pCi/g).

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

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

d Activity reported is a net activity result. >

A-ll

TABLE A-6. In-House "Duplicate" Samples Concentration8 Averaged Second Result Result Acceptance Lab Code" Date Analysis First Result 984 +/-158 Pass AP-5499,5500 1/2/2019 Fe-55 941 +/- 220 1027 +/-226 14.9 +/-5.7 17.5 +/-4.7 Pass AP-5499,5500 1/2/2019 Sr-89 20.2 +/- 7.3 15.6 +/- 8.5 13.8 +/-6.0 Pass AP-5499,5500 1/2/2019 Ni-63 12.1 +/-8.5 10.7 +/- 0.2 10.3 +/-0.2 Pass CF-20,21 1/2/2019 Gr. Beta 10.0 +/-0.2 0.005 +/-0.001 Pass 1/2/2019 Sr-90 0.005 +/- 0.002 0.005 +/- 0.002 CF-20,21 0.28 +/- 0.06 Pass -

1/2/2019 Be-7 0.27 +/-0.09 0.29 +/-0.08 CF-20,21 6.83 +/-0.34 6.76 +/- 0.24 Pass CF-20,21 1/2/2019 K-40 6.69 +/- 0.34 8.50 +/-1.11 9.79 +/-0.19 Pass SG-211,212 1/21/2019 Ra-226 7.94 +/-1.15 4.55 +/- 0.28 Pass SG-211,212 1/21/2019 Ac-228 4.46 +/-0.37 4.63 +/-0.43 0.59 +/-0.32 Pass WW-324,325 2/4/2019 Gr. Alpha 0.68 +/- 0.44 0.49 +/- 0.46 2.95 +/- 0.63 2.37 +/- 0.42 Pass \

WW-324,325 2/4/2019 Gr. Beta 1.80 +/-0.55 261 +/- 60 Pass W-345,346 2/4/2019 H-3 245 +/- 84 277 +/-85 193 +/- 58 -Pass WW-797,798 3/5/2019 H-3 165 +/-80 222 +/-83 608 +/- 72 Pass WW-648,649 3/8/2019 H-3 587 +/-101 630 +/-102 290 +/-62 Pass SW-713,714 3/14/2019 H-3 326 +/- 90 254 +/-86 0.108 +/- 0.020 0.103 +/-0.013 Pass AP-1241,1242 4/2/2019 Be-7 0.097 +/-0.0.18 0.078 +/-0.012 0.079 +/-0.009 Pass AP-1285,1286 4/3/2019 Be-7 0.080 +/-0.014 0.096 +/-0.011 0.090 +/- 0.007 Pass AP-1306.1307 4/3/2019 Be-7 0.085 +/- 0.009 0.079 +/-0.011 .0.078 +/- 0.007 Pass AP-1327,1328 4/3/2019 Be-7 0.078 +/-0.010 Pass AP-1327,1328 4/3/2019 fK^0 0.012 +/-0.007 0.021 +/-0.010 0.017 +/-0.006 0.265 +/-0.116 0.270 +/- 0.076

• Pass AP-2119,2120 ' 4/3/2019 Be-7 0.276 +/-0.098 0.208 +/-0.123 0.220 +/- 0.089 Pass AP-2225,2226 4/3/2019 Be-7 0.231 +/-0.128*

6.63 +/-0.37 6.51 +/- 0.24 Pass CF-820,821 *4/3/2019 K-40 6.39 +/- 0.30 608 +/-72 Pass WW-648,649 4/5/2019 H-3 587 +/-101 630 +/-102 662 +/-121 664 +/-86 Pass WW-1043,1044 4/5/2019 H-3 666 +/-121 10,164 +/-214 Pass SW-1087,1088 4/8/2019 H-3 . . 9,997 +/-300 10,330 +/-305 640 +/-102 601 +/- 71 Pass WW-1198.1199 4/9/2019 H-3 562 +/-99 1.46 +/-0^57 1.27 +/-0.39 Pass LW-1503,1504 4/25/2019 Gr; Beta 1.09+0.55

. 383 +/- 64 Pass WW-1789,1790 5/7/2019 H-3 366 +/- 90 400 +/-92 40.3 +/-0.5 39.7 +/-0.4 Pass SG-2269,2270 5/7/2019 Pb-214 . 39.1 +/-0.5 57.1 +/-1.0 55.2 +/-0.7 Pass SG-2269,2270 5/7/2019 Ac-228 53.2 +/-1.0 1.49 +/-6.10 Pass DW-10049,10050 5/7/2019 Ra-226 1.31 +/-0.13 1.66 +/-0.15 1.29 +/-0.37 Pass DW-10049,10050 5/7/2019 Ra-228 1.24 +/-0.52 1.33 +/-0.53 303 +/- 93 314 +/-64 Pass WW-1690A.B 5/8/2019 H-3 325 +/-89 23.3 +/-1.0 22.6 +/- 0.7 Pass S-1812,1813 5/16/2019 K-40 22.0 +/- 0.9 .

, Q.06 +/-0.02 Pass S-1812,1813 5/16/2019 Cs-137 0.05 +/- 0.03 0.07 +/- 0.04 1.14 +/-0.72 1.04 +/-0.48 Pass DW-10053,10054 5/22/2019 Gr. Alpha 0.93 +/- 0.63 .

1.13 +/-0.59 1,28 +/-0.43 .Pass DW-10053,10054 5/22/2019 Gr.Beta 1.43 +/-0.62 1521 +/-94 Pass W-2053,2054 5/29/2019 H-3 1572 +/-135 1470 +/-131 A-12

TABLE A-6. In-House "Duplicate" Samples Concentration3 Averaged Lab Codeb Date Analysis First Result Second Result Result G-1989,1990 6/3/2019 Be-7 0.80 +/-0.18 0.72 +/-0.15 0.76 +/-0.12 Pass G-1989,1990 6/3/2019 K-40 6.15 +/-0.51 5.98 +/- 0.46 6.07 +/- 0.34 Pass G-1989,1990 6/3/2019 Gr. Beta 7.24 +/-0.19 7.00 +/-0.19 712 +/-0.13 Pass WW-2204,2205 6/6/2019 H-3 3861 +/-194 . 3722 +/- 191 3792 +/-136 Pass S-2031,2032 6/10/2019 Pb-214 5.16 +/-0.19- 4.75 +/-0.22 4.96 +/-0.15 Pass S-2031,2032 6/10/2019 Ac-228 3.81 +/- 0.31 3.63 +/- 0.33 3.72 +/- 0.23 Pass S-2010,2011 6/10/2019 Pb-214 1.48 +/-0.10 1.05 +/-0.11 1.27 +/-0.07 Pass F-2140,2141 6/12/2019 K-40 1.01 +/-0.28 1.39 +/-0.32 1.20 +/-0.21 Pass S-2162.2163 6/12/2019 Pb-214 0.65 +/- 0.06 0.54 +/- 0.05 0.60 +/- 0.04 Pass S-2162,2163 6/12/2019 Ac-228 0.46 +/-0.10 0.44 +/- 0.08 0.45 +/- 0.07 Pass S-2162.2163 6/12/2019 K-40 4.22 +/- 0.49 3.81 +/-0.41 4.02 +/-0.32 Pass S-2162,2163 6/12/2019 TI-208 0.09 +/- 0.02 0.10 +/-0.02 0.09 +/-0.01 Pass S-2162,2163 6/12/2019 Pb-212 0.34 +/- 0.03 0.26 +/- 0.03 0.30 +/- 0.02 Pass SWT-2355,2356 6/25/2019 Gr. Beta 1.12 +/-0.57 1.24 +/-0.56 1.18 +/-0.40 Pass AP-2689,2690 6/28/2019 Be-7 0.089 +/-0.020 0.075 +/-0.018 0.082 +/-0.013 Pass AP-2710,2711 7/1/2019 Be-7 0.091 +/-0.010 0.097 +/- 0.010 0.094 +/- 0.007 Pass AP-2731,2732 7/2/2019 Be-7 0.073 +/-0.013 0.072 +/-0.011 0.072 +/- 0.009 Pass DW-10062,10063 7/5/2019 Ra-226 4.10 +/-0.30 .' 4.03 +/- 0.30 4.07 +/-0.21 Pass DW-10062,10063 7/5/2019 Ra-228 '* 1.95 +/-0.60 2.31 +/-0.62 2.13 +/-0.43 Pass AP-70818,70819 7/8/2019 Gr; Beta 0.021 +/-0.004 0.023 +/- 0.004 0.022 +/- 0.003 Pass XW-2459.2460 7/10/2019 H-3 304 +/-92 234 +/- 89 269 +/- 64 Pass VE-2516,2517 7/10/2019 Be-7 0.63 +/-0.16 0.52 +/-0.19 0.58 +/-0.12 Pass VE-2516,2517 7/10/2019 K-40 6.50 +/- 0.47 6.81 +/- 0.54 6.66 +/- 0.36 Pass AP-71518A.B 7/15/2019 Gr. Beta 0.022 +/- 0.004 0.025 +/- 0.004 0.023 +/-0.003 Pass VE-2668,2669 7/16/2019 K-40 3.84 +/- 0.27 3.74 +/-0.26 3.79 +/-0.19 Pass DW-10076,10077 7/16/2019 Gr. Alpha 3.01 +/-0.92 4.13 +/-0.91 3.57 +/-0.65 Pass DW-10073.10074 7/16/2019 Ra-226 1.57 +/-0.18 1.51 +/-0.21 1.54 +/-0.14 Pass DW-10073,10074 7/16/2019 Ra-228 1.29 +/-0.56 1.48 +/-0.57 1.385 +/-0.40 Pass AP-72218A.B 7/22/2019 Gr. Beta 0.013 +/- 0.004 0.016 +/- 0.004 0.015 +/-0.003 Pass G-2752,2753 7/23/2019 K-40 4.53 +/- 0.42 4.47 +/- 0.46 4.50 +/- 0.31 Pass G-2752,2753 7/23/2019 Be-7 1.98 +/-0.29 1.96 +/-0.29 1.97 +/-0.20 Pass I

AP-2800,2801 7/25/2019 Be-7 0.208 +/- 0.090 0.321 +/-0.147 0.264 +/- 0.086 Pass AP-72918A.B 7/29/2019 Gr. Beta 0.026 +/- 0.005 0.025 +/-0.005 0.025 +/- 0.003 Pass VE-2840,2841 7/31/2019 K-40 3.94 +/- 0.38 3.99 +/- 0.47 3.96 +/- 0.30 Pass AP-2903,2904 8/1/2019 Be-7 0.198 +/-0.102 0.228 +/-0.102 0.213 +/-0.072 Pass P-2882,2983 8/1/2019 H-3 265 +/- 85 327 +/- 88 296 +/-61 Pass SG-2926,2927 8/5/2019 Pb-214 9.07 +/- 0.39 8.82 +/- 0.39 8.95 +/-0.28 Pass SG-2926,2927 8/5/2019 Ac-228 9.00 +/- 0.76 8.58 +/- 0.72 8.79 +/- 0.52 Pass AV-2993,2994 ' 8/9/2019 Gr. Beta 1.22 +/-0.19 1.28 +/-0.21 1.25 +/-0.14 Pass AV-2993,2994 8/9/2019 K-40 3.12 +/-0.36 3.14 +/- 0.35 Pass 3.13 +/-0.25 A-13

TABLE A-6. In-House "Duplicate" Samples Concentration3 Averaged First Result Second Result Result Acceptance Lab Code" Date Analysis 0.90 +/- 0.35 Pass DW-10088.10089 8/9/2019 Ra-228 0.60 +/-0.50 1.20 +/-0.50

- 1.17 +/-0.14 , Pass DW-10088,10089 8/9/2019 Ra-226 1.40 +/-0.20 0.94 +/- 0.20 0.43 0.15 Pass VE-3016,3017 8/12/2019 Be-7 0.39 +/-0.12 0.47 0.28 6.18 0.38 Pass VE-3016.3017 8/12/2019 K-40 6.13 +/-0.41 6.24 0.64 4.35 0.27 4.39 0.21 Pass G-3600,3601 8/12/2019 Be-7 4.42 +/- 0.33 r

401 +/- 92 . ,441 +/-66 ,j Pass WW-3100,3101 8/14/2019 H-3 480 +/- 96 1923 +/-136 1893 +/-94 Pass MI-3211.3212 8/27/2019 K-40 1862 +/-131.

0.73 +/-0.22 Pass 8/27/2019 Sr-90 0.90 +/-0.33 0.56 +/- 0.29 MI-3211,3212 1.39 +/-0.58 1.09 +/-0.38 Pass LW-3512,3513 8/30/2019 Gr. Beta 0.79 +/- 0.50

. ,_ 0.54 +/-0.08 Pass DW-10100,10101 9/5/2019 Ra-226 0.50 +/-0.11 0.57 0.12 2.54 1.03 2.96 +/- 0.66 Pass DW-10100.10101 9/5/2019 Ra-228 3.38 +/- 0.82 ,

1.41 0.68 1.57 +/-0.50 Pass DW-10111,10112 9/23/2019 Gr. Alpha 1.72 +/-0.73 3.21 +/-0.52 Pass DW-10115.10116 9/25/2019' Ra-228 3.65 +/- 0.80 2.76 0.68 2.87 +/-0.17 Pass DW-10115,10116 9/25/2019 Ra-226 2.99 +/- 0.23 2.74 0.25 4.05 +/- 0.84 Pass WW-3793.3794 10/8/2019 Gr. Beta 3.75 +/-1.18 4.34 1.20 0.63 +/-0.03 Pass BS-3879,3880 10/9/2019 Pb-214 0.60.+/-0.03 0.65 +/- 0.05 1.15 +/-0.14 1.21 +/-0.10 Pass BS-3879.3880 10/9/2019 Ra-226 1.27 +/-0.14 10.69 +/-0.30 10.87 +/-0.21 1 Pass BS-3879,3880 10/9/2019 K-40 11.05+/-0.29 BS-3879.3880 10/9/2019 Pb-212 0.58 +/-0.02 0.55 +/-0.02 0.56^0.01 Pass BS-3879,3880 10/9/2019 Tl-208 0.21 +/-0,02 0.21 +/- 0.01 / 0.21 +/-0 01 Pass 0.62 +/-0.17 0.68 +/-0.12 Pass BS-3879,3880 10/9/2019 Bi-212 0,75 +/- 0.17 0^52 +/-0.06 0.54 +/-0.03 Pass BS-3879,3880 10/9/2019 BI-214 0.57 +/- 0.02 15.3 +/-0.7 15.3 +/- 0.5 Pass BS-4161,4162 10/29/2019 K-40 15.3 +/-0.6 2.27 +/- 0.78 2.22 +/- 0.43 Pass BS-4161,4162 10/29/2019 Ra-226 2.16 +/-0.35 1.19 +/-0.62 1.02 +/-0.42 Pass DW-10126,10127 10/22/2019 Ra-228 0.85 +/- 0.58 3.06 +/-0.95 2.25 +/- 0.68 Pass DW-10129,10130 10/22/2019 Gr. Alpha 1.44 +/-0.96 2.16 +/-0.20 2.13 +/-0.13 Pass SG-4071 10/22/2019 Ac-228 2.10 +/-0.16 1.29 +/-0.08 1.45+/-0.06 Pass SPSG-4071,4072 10/22/2019 Pb-214 1.61 +/-0.10 0.29 +/-0.14 0.19 +/-0.12 0.24 +/- 0.09 Pass SS-3900,3901 10/15/2019 Bi-212 528 +/- 97 505 +/- 68 Pass WW-4291,4292 11/5/2019 H-3 481 +/-97 2.26 +/- 0.63 2.44 +/- 0.44 Pass DW-10139,10140 11/6/2019 Ra-228 2.61 +/-0.62 1.32 +/-0.19 1.41 +/-0.13 Pass DW-10139.10140 11/6/2019 Ra-226 1.49 +/-0.17 165 +/-81 139 +/-56 Pass WW-4270.4271 11/6/2019 H-3 112 +/-78 23.0 +/- 0.9 21.6 +/-0.6 Pass S-4312.4313 11/7/2019 K-40 20.2 +/-0.8 0.134 +/-0.073 0.134 +/-0.052 Pass AP-4379,4380 11/12/2019 Be-7 0.133 +/-0.075 1.25 +/-0.07 Pass 11/13/2019 Pb-214 1.22 +/-0.09 1.28 +/-0.10 S-4422,4223 1.21 +/-0.17 1.18 10.11 Pass S-4422,4423 11/13/2019 Ac-228 1.14 +/-0.15 460 +/- 69 Pass WW-4556,4557 11/13/2019 H-3 438 +/- 96 482 +/- 98 6.26 +/- 0.58 6.43 10.40 Pass SO-5024.5025 11/14/2019 K-40 6.60 +/- 0.54 1322 179 Pass MI-4443.4444 11/18/2019 K-40 1304 +/-114 1340 +/-109 A-14

TABLE A-6. In-House "Duplicate" Samples Concentration8 Averaged Lab Code" Date Analysis First Result Second Result Result SW-4492,4493 11/19/2019 H-3 188 +/-87 264 +/-97 226 +/- 65 Pass WW-4577,4578 11/21/2019 H-3 212 +/-83 232 +/-84 222 +/-59, Pass AP-4514.4515 11/21/2019 Be-7 0.130 +/-0.055 0.193 +/-0.112 0.162 +/-0.062 Pass SWT-4598,4599 11/26/2019 Gr. Beta 1.43 +/-0.57 1.14 +/-0.54 1.28 +/-0.39 Pass AP-120218A.B 12/2/2019 Gr. Beta 0.009 +/- 0.004 0.013 +/-0.004 0.011 +/-0.003 Pass S-4644,4645 12/4/2019 Pb-214 1.01 +/-0.09 0.91 +/- 0.09 0.96 +/- 0.06 Pass S-4644.4645 12/4/2019 Ac-228 0.85 +/-0.15 0.96 +/-0.16 0.91 +/-0.11 Pass AP-121618A.B 12/16/2019 Gr. Beta 0.028 +/- 0.005 0.030 +/- 0.005 0.029 +/- 0.003 Pass S-4735,4736 12/16/2019 Pb-214 9.33 +/- 0.38 9.45 +/- 0.27 9.39 +/- 0.23 Pass S-4735,4736 12/16/2019 Ac-228 13.4 +/-0.7 14.9 +/-0.7 14.1 +/-0.5 Pass AP-122318A.B 12/23/2019 Gr. Beta 0.034 +/- 0.005 0.035 +/- 0.005 0.035 +/-0.003 Pass AP-123018A.B 12/30/2019 Gr. Beta 0.037 +/- 0.005 0.037 +/- 0.005 0.037 +/-0.004 Pass 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.

3 Results are reported in units of pd/L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil and sediment (pCi/g).

b CH (Charcoal Canister). DW (Drinking Water), E (Egg), F (Fish), G (Grass), LW (Lake Water), P (Precipitation).

PM (Powdered Milk). S. (Solid). SG (Sludge). SO (Soil), SS (Shoreline Sediment), SW (Surface Water),

SWT (Surface Water Treated), SWU (Surface Water Untreated). VE (Vegetation), W Water (Water). WW (Well Water).

A-15

TABLE A-7. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration8 ___

Reference Known Control Lab Code' Date Analysis Laboratory result Activity Limits0 Acceptance 2/1/2019 Gross Alpha 0.16 +/- 0.03 0.528 0.158-0.898 . Pass MAAP-609 2/1/2019 Gross Beta 1.09 +/-0.07 0.948 0.474-1.422 Pass MAAP-609 2/1/2019 Gross Alpha 0.73 +/- 0.08 0.84 0.25-1:43 Pass MAW-550 2/1/2019 Gross Beta 2.26 +/-0.06 2.33 1.17 -3.50 Pass MAW-550 2/1/2019 Am-241 38.89 +/-5.92 49.9 34.9 +/-649 Pass MASO-605 MASO-605 2/1/2019 Cs-134 0.45 +/- 2.52 0.0 NAC Pass Cs-137 1273.1 +/- 13.0 1164 815-1513 Pass MASO-605 2/1/2019 MASO-605 2/1/2019 Co-57 0.46 +/-1.1 0.0 NAC Pass 2/1/2019 Co-60 857.96 +/- 8.52 855.0 599-1112 Pass MASO-605 2/1/2019 Mn-54 1,138.0 +/-13.5 , 1027 719-1335 Pass MASO-605 2/1/2019 Zn-65 730.92 +/- 16.48 668 468-868 Pass MASO-605 410-761 Pass MASO-605 2/1/2019 ; K-40 676 +/-47 585 MASO-605 ~ 2/1/2019 Sr-90 0.0007 +/- 0.0007 0.000 NAC Pass 2/1/2019 Pu-238 78.15 +/-6.11 71.0 49.7 - 92.3 Pass MASO-605 2/1/2019 Pu-239/240 65.00 +/-5.4 59.8 ' 41.9-77.7 Pass MASO-605 2/1/2019 U-234 65 +/- 13 56 39.- 73 Pass MASO-605 MASO-605 2/1/2019 U-238 237 +/- 23 205 144 -267 Pass 2/1/2019 Am-^41 0.46 +/-0.03 0.582 0.407 -0757 Pass MAW-613 2/1/2019 Cs-134 5.49 +/-0.18 5.99 4.19-7.79 Pass MAW-613 MAW-613 2/1/2019 Cs-137 0.089 +/- 0.080 0 NAC i Pass 2/1/2019 Co-57 10.87 +/- 0.24 10.00 < 7.0,13.0 Pass MAW-613 2/1/2019 Co-60 6.78+/-0;19 6.7 4.7-8.7 Pass MAW-613 2/1/2019 Mn-54 8.98 +/-0.17 8.4 ... 5.9 -10.9 Pass MAW-613 2/1/2019 Zn-65 0.096 +/-0.141 0 NAC Pass MAW-613 2/1/2019 Fe-55 0.004 +/-4.00 0 NAC Pass.

MAW-613 2/1/2019 Ni-63 5.54 +/-1.52 5.8 4.1 -7.5 Pass MAW-613 2/1/2019 Sr-90 6.02 +/-0.53 6.35 4.45-8.26 Pass MAW-613 2/1/2019 Pu-238 0.315 +/-0.088 0.451 0.316 - 0.586 Fall" MAW-613 MAW-613 2/1/2019 Pu-239/240 0.07 +/- 0.07 0.005 NAd Pass U-234 0.98 +/- 0.07 0.800 0.56 +/-1.04 Pass MAW-613 2/1/2019 2/1/2019 U-238 0.94 +/- 0.07 0.810 0.57 +/-1.05 Pass MAW-613 2/1/2019 Cs-134 0.185 +/- 0.025 0.216 0.151 *0.281 Pass MAAP-611 Cs-137 0.288 +/-0.045 0.290 0.203 - 0.377 Pass MAAP-611 2/1/2019 2/1/2019 Co-57 0.369 +/- 0.033 0.411 0.288

• 0.534 Pass MAAP-611 2/1/2019 Co-60 0.333 +/- 0.045 0.340 0.238 - 0.442 Pass MAAP-611 Mn-54 0.546 +/-0.058 0.547 0.383-0.711 Pass MAAP-611 2/1/2019 2/1/2019 Zn-65 0.025 +/-0.0348 0 NAC Pass MAAP-611 MAAP-611 2/1/2019 Sr-90 1.34 +/-0.13 0.662 0.463 - 0.861 . Fail*

MAAP-611 2/1/2019 U-234, 4.14 +/-0.97 0.106 0.074-0.138 Fail1 2/1/20.19 U-238 3.89 +/-0.94 , 0.110 0.077-0.143 Fail*

MAAP-611 2/1/2019 1-129 0.56 +/-0.08 0.616 0.431 -0.801 Pass MAW-601 A-16

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

Concentration" Reference Known Control Lab Code" Date Analysis Laboratory result Activity -Limits0 Acceptance MAVE-607 2/1/2019 Cs-134 2.33 +/-0.10 . 2.44 1.71 -3.17 Pass MAVE-607 2/1/2019 . Cs-137 2.62 tO. 13 2.30 . 1.61 -2.99 Pass MAVE-607 2/1/2019 Co-57 2.39 +/-0.11 2.07 1.45 -2.69 Pass MAVE-607 2/1/2019 Co-60 0.046 +/- 0.04 0 NAC Pass MAVE-607 2/1/2019 Mn-54 0.031 +/-0.04 0 NAC Pass MAVE-607 2/1/2019 Sr-90 0.013 +/-0.022 0 NAC Pass MAAP-3299 8/1/2019 Gross Alpha 0.13 +/-0.03 0.528 0.158-0.898 Fail9 MAAP-3299 8/1/2019 Gross Beta 1.08 +/-0.07 0.937 0.469-1.406 Pass MAW-3252 8/1/2019 Gross Alpha 0.93 +/-0.06 1.06 0.32 -1.80 Pass MAW-3252 8/1/2019 Gross Beta 3.03 +/- 0.07 3.32 1.66 r 4.98 Pass MASO-3297 8/19/2019 Cs-134 881.98 +/-9.03^ 1020 714 -1326 Pass MASO-3297 8/19/2019 Cs-137 871.50 +/-10.83 789 552 -1026 Pass MASO-3297 8/19/2019 Co-57 -1.72 +/-3.01 0 NAC Pass MASO-3297 8/19/2019 Co-60 783.69 +/- 8.21 760 532

• 988 Pass MASO-3297 8/19/2019 Mn-54 834.48 +/-11.29 745 522

• 969 Pass MASO-3297, 8/19/2019 Zn-65 -3.01 +/- 5.27 0 NAC Pass MASO-3297 8/19/2019 K-40 662.91 +/-42.65 555 389 - 722 Pass MAW-3240 8/1/2019 Cs-134 *0.08 +/- 0.08 0 NAC Pass MAW-3240 8/1/2019 Cs-137 18.48 +/- 0.90 18.4 12.9-23.9 Pass MAW-3240 8/1/2019 Co-57 14.68 +/-0.52 15.6 10.9-20.3 Pass MAW-3240 8/1/2019 Co-60 8.67 +/-0.39 8.8 6.2-11.4 Pass MAW-3240 8/1/2019 Mn-54 ' 20.72 +/-0.93 20.6 14.4 - 26.8 Pass MAW-3240 8/1/2019 Zn-65 20.52 +/-1.05 20.3 14.200 - 26.400 Pass MAW-3240 8/1/2019 K-40 5.11 +/-0.68 0 NAC Fail MAW-3240 8/1/2019 H-3 179.52 +/-3.32 175 123-228 Pass MAW-3240 8/1/2019 U-234 1.11 +/-0.04 1.07 .0.75 -1.39 Pass MAW-3240 8/1/2019 U-238 1.08 +/-0.04 1.05 0.74 -1.37 Pass MAVE-3295 8/1/2019 Cs-134 0.02 +/- 0.02 0 NAC Pass MAVE-3295 8/1/2019 Cs-137 3.38 +/- 0.32 3.28 2.30 - 4.26 Pass MAVE-3295 8/1/2019 Co-57 4.99 +/-0.51 4.57 3.20 - 5.94 Pass MAVE-3295 8/1/2019 Co-60 5.29 +/- 0.39 5.30 3.71 - 6.89 Pass MAVE-3295 8/1/2019 Mn-54 4.73 +/- 0.45 4.49 3.14-5.84 Pass MAVE-3295 8/1/2019 Zn-65 3.10 +/-0.31 2.85 2.00 - 3.71 Pass 8 Results are reported In units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air fitter), MASO (soil) and MAVE (vegetation).

c MAPEP results are presented as the known values and expected laboratory precision (1 slgma, 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 Provided In the series for "sensitivity evaluation". MAPEP does not provide control limits.

0 Past results have been acceptable so will watch to see If a trend develops.

1 An erroneous volume conversion caused some Incorrect values to be submitted. If the conversion had been performed properly the results In Bq/sample would have been (Sr-90:0.671 +/- 0.066) and (U-234:0.153 +/- 0.036) and (U-238:0.144 +/- 0.035).

This result had been Included In the Uranium Investigation. See footnote "C" on Table A-1.

0 The lab will adopt a MAPEP specific gross alpha/beta filter calibration as discussed In the MAPEP test Instructions.

Utilizing a MAPEP specific calibration, the result In Bq/sample (0.39 +/- 0.09 Bq/tota!) which passes the MAPEP acceptance criteria.

A-17

TABLE A-8. Intertaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)3.

MRAD-30 Study ___

Concentration Lab Code' Date Analysis Laboratory ERA Control Result Value Limitsd Acceptance 3/18/2019 Am-241 19.1 18.7 13.3-24.9 Pass ERAP-846 3/18/2019 Cs-134 612 721 468 - 884 Pass ERAP-846 3/18/2019 Cs-137 679 634 521 -832 Pass ERAP-846 3/18/2019 Co-60 93.7 93.8 79.7-119 Pass ERAP-846 3/18/2019 Fe-55 612 718 262 -1150 Pass ERAP-846 3/18/2019 Mn-54 <0.5 <50.0 0.00 - 50.0 Pass ERAP-846 3/18/2019 Zn-65 1500 1380 1130 -2110 Pass ERAP-846 Pu-238 34.0 33.8 25.5-41.5 Pass ERAP-846 3/18/2019 3/18/2019 Pu-239 64.9 67.0 50.1 -80.8 Pass ERAP-846 3/18/2019 Sr-90 199 181 114-246 Pass ERAP-846 3/18/2019 U-234e 29.0 18.2 13.5-21,3 Fail ERAP-846 3/18/2019 U-238e 28.6 18.1 13.7-21.6 Fail ERAP-846 3/18/2019 Grosst 48.4 50.3 26.3 - 82.9 Pass ERAP-848 3/18/2019 Gross I 95.5 78.6 47.7-119 Pass ERAP-848 Results obtained by Environmental, Inc., Midwest Laboratory (EIML) as a participant in the crosscheck program for proficiency testing administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

Laboratory code ERAP (air filter). Results are reported in units of (pCi/Filter).

The ERA Assigned values for the air filter standards are equal to 100% of the parameter present in the standard as determined by the gravimetric and/or volumetric measurements made during standard preparation as applicable.

1 The acceptance limits are established per the guidelines contained in the Department of Energy (DOE) report EML-564, Analysis of Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP)

Data Determination of Operational Criteria and Control Limits for Performance Evaluation Purposes or ERA'S SOP for the generation of Performance Acceptance Limits.

! Failure traced to an over-estimated U-232 tracer value. Tracer has been re-standardized. (See footnote "c" on Table A-1).

A-18

2019 Annual Environmental and Effluent Release Report 2019 Annual Environmental and Effluent Release Report Appendix B 2019 REMP Data Summary Reports

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2019 Number of Mean for Indicator Location with Highest Annual Mean Mean for Control Non-routine Type and Mean for All Locations Pathway Lower Limit i Locations Locations Reported  ;

Sampled Total Number Mean Detected/ Detected/Collected Measurements of Detection Detected/Collected Location #

of Analyses Detected/Collected Collected (LLD) Distance &

Units Performed Range Range Range Direction Ranqe 0.072 4 0.078 0.078 0 0.070 Air Be-7 4/4 N/A 28/28 24/24 0.7 > <' 4/4 pCi/m3 28 0.069-0.085 0.069 - 0.085 0.049 - 0.089 0.049- 0.089 S

< LLD v <LLD 0

<LLD Co-58 ~i Air 0/4 N/A 0/28 0/24 pCi/m3 28

<LLD < LLD ,0

<LLD Air Co-60 0/4 N/A 0/28 0/24 pCi/m3 28

<LLD .. 0

<LLD <LLD Air Cs-134 0/4 0!037 0/28 0/24 '

pCi/m3 28

<LLD <LLD 0

<LLD Air Cs-137 0/4 0.045 0/28 0/24 pCi/m3 28 0.023' 4 0.025 0.025 .0. .

0.024 Air Gross Beta 52/52 52/52 0.0075 364/364 312/312 0.7 pCi/m3 364 S 0.011 -0.055 0.011 -0.055 0.006 - 0.055 0.006 - 0.055 B-l

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2019 Mean for Indicator . Location with Highest Annual Mean Number of Pathway Type and Mean for All Locations Mean for Control Lower Limit Locations Non-routine Sampled Total Number Locations of Detection Detected/Collected Reported of Analyses Location # Mean Detected/ Detected/Collected (LLD) Detected/Collected Measurements Units Performed Distance & Collected Range Range Range Direction Ranqe

<LLD <LLD <LLD Air 1-131 0 0.05 0/364 0/312  ; . 0/52 pCi/m3 364 Broadleaf 390.2 323.3 70 737.8 737.8 Be-7 0 Vegetation N/A 31/41 26/36 17.1 5/5 5/5 41 pCi/kg wet 124-2555 124-622 SSW 252 - 2555 Broadleaf 4739.4 4636.2 70 5482.0 5482.0 K-40 0 Vegetation N/A 41/41 36/36 17.1 5/5 41

'5/5 pCi/kg wet 2833 - 8257 2833 - 8257 SSW 4196-6968 4196-6968 Broadleaf <LLD <LLD <LLD Co-58 0 Vegetation N/A 0/41 0/36 41 0/5 pCi/kg wet Broadleaf <LLD <LLD <LLD Co-60 0 Vegetation N/A 0/41 0/36 . 0/5 41 pCi/kg wet Broadleaf <LLD <LLD <LLD 1-131 0 Vegetation 45 0/41 0/36 0/5 '

41 pCi/kg wet B-2

Environmental'Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2019 o Number of Mean for Indicator Location with Highest Annual Mean Mean for Control Non-routine

• Type and Mean for All Locations Pathway Lower Limit Locations Locations:, Reported Sampled Total. Number Detected/Collected Mean Detected/

• Detected/Collected of Detection Location # Measurements of Analyses Detected/Collected Collected (LLD) Distance &

Units Performed Range Range Range Direction Ranqe .

<LLD <LLD 0

<LLD Broadleaf Cs-134 f 0/5 Vegetation 45 0/41 0/36  :

41 pCi/kg wet

<LLD <LLD 0

<LLD Broadleaf Vegetation Cs-137 60 0/41 0/36  : 0/5 41 pCi/kg wet 1791.2 ' 25 1791.2

• 1496.6 0 1663.1 Fish . K-40 10/10 N/A 23/23 13/13 0.6 13/13 pCi/kg wet 23 .964-3195 885 3260 885 - 3260 NNW 964-3195

<LLD <LLD .0

<LLD Fish Mn-54 ,  ! 0/10 94 0/23 0/13 .

pCi/kg wet 23

<LLD <LLD 0

<LLD Fish Fe-59 0/10 195 0/23 0/13 pCi/kg wet 23

<LLD <LLD 0

<LLD "r . ' . . . >"

Fish Co-58 0/10 97 0/23 0/13 pCi/kg wet 23 B-3

Environmental Radiological Monitoring Program Annual Summary Perry Nuplear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2019 Mean for Indicator Location with Highest Annual Mean Number of Pathway Type and Mean for All Locations Mean for Control Non-routine Lower Limit Locations Sampled Total Number Locations Reported of Detection Detected/Collected Mean Detected/.

of Analyses Detected/Collected Location # Detected/Collected Measurements Units (LLD) Collected Performed Range Distance &

Range Range Direction Ranqe

<LLD <LLD <LLD  ; 0 Fish <LLD -

Co-60 0/23 0/13 '

• 0/13 ' 0/23 pCi/kg wet 23

<LLD <LLD <LLD 0 Fish <LLD Zn-65 0/23 0/13 0/13 pCi/kg wet 0/23 23

<LLD <LLD <LLD

• o <LLD Fish Cs-134 0/23 . . 0/13 0/13 0/23 pCi/kg wet 23

<LLD <LLD , <LLD 0 Fish Cs-137 112 0/13 0/13 0/10 pCi/kg wet 23 10530.0 10530.0 64 11200.5 N/A 0 Sediment K-40 N/A 4/4 4/4 , 0.4 2/2 N/A pCi/kg wet 4 9581-11716 9581 -11716 WNW 10685-11716 N/A

<LLD <LLD . N/A 0 Sediment Co-58 50 0/4 ,  % 0/4 N/A pCi/kg wet 4 N/A B-4

Environmental Radiological Monitoring Program Arinual Summary 1 Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting. Period: 2019 Number of Mean for Indicator Location with Highest Annual Mean Mean for Control: Non-routine Type and  ; Mean for All Locations Pathway Lower Limit Locations Locations . Reported Sampled Total Number of Detection Detected/Collected

• Location #

Mean Detected/' Detected/Collected. Measurements of Analyses Detected/Collected Collected (LLD); Distance &

Units Performed Range Range Range Direction Ranqe

<LLD N/A 0 .

<LLD "

Sediment Co-60 40 0/4 0/4 ' N/A pCi/kg wet 4 , N/A

<LLD N/A 0

<LLD Sediment Cs-134 ' N/A 112 0/4 0/4 .

pCi/kg wet 4 N/A

<LLD ' N/A

• 0

<LLD Sediment Cs-137 N/A 135 0/4 0/4 ' '

pCi/kg wet 4 N/A .

12.5 33 18.5 12.3 0 12.5 TLD (E)

Direct 116/116 ' 108/108 4.7 4/4 8/8 1.0 mR/91 X116 9.0-15.3 days 5.3 18.3 8.5-18.3 S - 17.1-20.1 12.9 ' 31 16.9 12.9 0 ...

12.9 TLD (Q)

Direct 8/8 116/116 108/108 4.8 4/4 1.0 mR/91 116 11.7-13.8 days 9.1 17.4 9.1 -17.4 SE 16.5-17.1 58.9 1 29 74.3 57.7 . 0 58.8 TLD Direct r2/2 1.0 29/29 27/27 4.5 1/1 mR/365 29 57.0 - 58.4 days 47.7 74.3 . 47.7-74.3 SSE 74.3 - 74.3 B-5

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2019 Mean for Indicator Location with Highest Annual Mean Number of Pathway Type and Mean for All Locations Mean for Control Lower Limit Locations Non-routine .

Sampled Total Number Locations of Detection Detected/Collected Reported of Analyses Location # Mean Detected/ Detected/Collected (LLD) Detected/Collected Measurements Units Performed Distance & Collected Range Range Range Direction Ranqe 1.3 1.3 . 36 1.5 1.2 0 Water Gross Beta 3.0 42/54 32/42 3.9 9/12 10/12 pCi/L 54 0.9-1.9 0.9-1.9 WSW 1.0-1.9 0.9-1.4

<LLD <LLD <LLD 0 Water H-3 1500 0/18 0/14 . 0/4 pCi/L 18

<LLD <LLD - <LLD 0 Water Mn-54 11 0/54 0/42 pCi/L 0/12 54

<LLD <LLD , <LLD 0 Water Fe-59 22 0/54 0/42-pCi/L 0/12 54

<LLD <LLD <LLD 0 Water Co-58 11 0/54 0/44 pCi/L

0/12 54

<LLD <LLD <LLD 0 Water Co-60 11 0/54 0/42 pCi/L

. 0/12 54 B-6

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2019 Number of Mean for Indicator Location with Highest Annual Mean Mean for Control . Non-routine.

Type and Mean for All Locations Pathway Lower Limit Locations Locations : Reported .

Total Number Mean Detected/ Detected/Collected Measurements Sampled of Detection1 Detected/Collected Location #

of Analyses Detected/Collected Collected (LLD) Distance & Range Units Performed Range Range Direction Ranqe

<LLD 0

<LLD  ; <LLD Water Zn-65 0/12 22 0/54 0/44 pCi/L 54

<LLD 0

<LLD <LLD Water Zr-95 0/12 22 0/54 0/42 pCi/L 54

<LLD 0

<LLD <LLD Water Nb-95 0/12 11 0/54 0/42 pCi/L 54

<LLD 0

<LLD <LLD Water Cs-134 0/12 11 0/54 0/42 pCi/L 54

<LLD 0

<LLD <LLD Water Cs-137 0/12 13 0/54 0/42 pCi/L 54

<LLD 0

<LLD <LLD Water Ba-140 0/12 45 0/54 0/42 pCi/L 54 B-7

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2019 Mean for Indicator Location with Highest Annual Mean Number of Pathway Type and > Mean for All Locations Mean for Control Lower Limit Locations Non-routine Sampled Total Number Locations of Detection Detected/Collected Reported of Analyses Location # Mean Detected/ Detected/Collected (LLD)

• Detected/Collected Measurements Units ' Performed Distance & Collected Range Range Range Direction Range

<LLD <LLD <LLD Water La-140 0 11 0/54 0/42 .

pCi/L 54 0/12 "

B-8

2019 Annual Environmental and Effluent Release Report Appendix C 2019 REMP Detailed Data Report

Environmental, line; Midwest Laboratory 700 Umaotv Rood

• Ncrthtooc*. 0.60082-2310 ph, (847) S644J700-tax (847) 58*4517 MONTHLY PROGRESS REPORT

to  ;. "

FIRST ENERGY CORPORATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

--... '. ,-. ^ .-.. .;::. TOR THE". *;;- *.-; .'--.-. '"/-.-:.* ** ,

, PERRY NUCLEAR POWER PLANT jRepbfting Period: January-Deoember. 2019

/ .,v Prepared and Submitted by

• ,  ; -'; lENyiRONMENtAL.lNC.,

^ MIDWEST LABORAtdRV Proiect Number 8033 Reviewedand C>t^ <<~w*~~ - ^. Date Approved / ' r /? .. <^- &*&

A. Banavali. PhD.

Laboratoiy Manager Distribution: K; Yeager P. Hiniz, OWpDepartment oJ Health B. Mechehbier,:La'l>> Cbunly HeaJth Department

TABLE OF CONTENTS Section Page List of Tables jjj

1.0 INTRODUCTION

....: \ jv 2.0 LISTING OF MISSED SAMPLES v 3.0 DATATABLES , vi Appendices A Interlaboratory Comparison Program Results A-1 B Data Reporting Conventions B-1

PERRY NUCLEAR POWER PLANT LIST OF TABLES 1 Direct Radiation, Quarterly and Annual 1"1 2 Airborne Particulate Filters and Charcoal Canisters 2-1 3 Airborne Particulate Filters ............. 3-1 4 LakeWater... .,......,..;.. *, **** 4-1 5 Milk ....;.......... 5-1 7 Food Products **, 7"1 9 Fish...v...........

• 9"1 11 Sediments ,......:.....: '. *  : 1^-

PERRY NUCLEAR POWER PLANT

1.0 INTRODUCTION

The following constitutes the current 2019 report for the Radiological Environmental Monitoring Program conducted at the Perry Nuclear Power Plant in Perry, Ohio. Results of completed analyses are presented in the attached tables.

The data obtained in the program Were within ranges previously encountered and to be expected in the environmental media sampled.

All concentrations, except gross beta, are decay corrected to the time of collection Airborne iodine is decay corrected to the midpoint of the collection period.

All samples were collected within the scheduled period, unless noted otherwise in Table 2.0, Listing of Missed Samples.

iv

PNPP 2.0 LISTING OF MISSED SAMPLES Expected Sample Type Location Collection  :;.;_ . ' Reason" *. . . ;,^;,-., ; - -^

Date

LW P-59W 01-25-18 No sample sent. Water frozen.

LW P-60;; 01-25-18 No sarnple sent. Water frozen.

Aw P-59 02-27-19 No sample sent/Water frpz0n.

p^6 02-27-19 ^ No sample sent. Water frozen. -

LW P-59 Q3-28-19 No sample sent. Water frozen.

LW P-60 03-28-19 No sample sent. Water frozen.

VE *' P4 08-20-19 No sample sent.

PNPP Table 1. Direct Radiation (TLDs), Quarterly Exposure:

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

Date Placed 01-08-19 04-04-19 07-10-19 10-31-19 Date Removed 04-04-19 07-10-19 10-30-19 02-10-20 E-1 11.0 +/-1.2 11.2 +/-2.4 11.1 +/-0.8 13.0 +/-1.8 E-3 9.1 +/-07 9.1 +/-2.3 9.0 +/- 0.5 10.2 +/-1.1 E-4 11.6 +/-0.9 11.0 +/-2.2 12.1 +/-0.6 13.5 +/-1.1 E-5 10.1 +/-0.8 8.5 +/- 2.2 10.5 +/-0.5 10.4 +/-1.1 E-6 12.0 +/-1.2 10.6 +/-2.2 12.0 +/-0.7 12.8 +/-1.2 E-7 11.7 +/-0.8 10.7 +/-2.3 11.7 +/-0.8 12.4 +/-1.3 E-8 8.5 +/-0.6 10.5 +/- 2.2 10.8 +/-0.5 12.0 +/-1.0 E-9 9.7 +/- 0.8 9.7 +/- 2.2 10.3 +/-0.6 11.4 +/- 1.1 E-10 11.5 +/-0.7 11.3 +/-2.2 11.5 +/-0.6 11.8 +/-1.2 E-11 11.7 +/-0.9 12.2 +/- 2.3 12.5 +/-0.8 13.5 +/-1.3 E-12 11.3 +/-0.9 11.1 +/-2.3 12.1 +/-0.7 13.7 +/-1.3 E-13 11.1 +/-0.9 11.3 +/-2.2 11.5 +/-0.8 12.8 +/-1.3 E-14 11.6 +/-0.8 11.5 +/-2.2 12.3 +/- 0.9 12.7 +/-1.1 E-15 10.3 +/-0.7 10.7 +/-2.2 10.4 +/- 0.6 12.0 +/-1.1 E-21 12.0 +/-0.8 12.7 +/-2.2 14.6 +/-0.7 14.7 +/-1.1 E-23 14.8 +/-1.0 13.2 +/-2.3 14.8 +/-0.6 15.4 +/-1.3 E-24 13 2 +/- 0.9 11.4 +/-2.3 12.5 +/-0.6 12.7 +/-1.3 E-29 16.3 +/-1.3 15.5 +/-2.2 16.6 +/-0.9 17.3 +/-1.3 E-30 14.2 +/- 0.8 14.1 +/-2.3 14.3 +/-0.7 15.7 +/-1.3 E-31 15.7 +/- 1.0 17.0 +/-2.2 16.2 +/-0.8 16 7 +/-1.2 E-33 16.3 +/- 0.6 16.2 +/- 2.3 18.3 +/-0.8 17.6 +/-1.3 E-35 11.2 +/-1.0 10.6 +/- 2.3 11.5 +/-0.9 12.0 +/-1.1 E-36 16.4 +/- 0.8 13.6 +/-2.2 15.9 +/-0.7 ^ 15.3 +/-1.1 E-53 10.8 +/-0.8 9.8 +/- 2.3 13.9 +/- 1.0 / 12.4 +/- 1.2 E-54 13.0 +/- 0.8 10.7 +/- 2.2 12.9 +/-0.7 12.2 +/-1.2 E-55 11.6 +/-1.3 12.1 +/- 2.5 13.4 +/-1.5 13.8 +/-1.4 E-56 11.7 +/-1.0 11.4 +/-2.4 12.1 +/-0.9 13.1 +/-1.5 E-57 13.5 +/-1.0 12.9 +/-2.3 14.7 +/-0.8 14.2+/-1.4 E-58 9.1 +/-1.0 8.5 +/- 2.3 10.1 +/-0.6 10:5 +/-1.2 Mean +/- s.d. 12.1 +/-2.2 11.7 +/-2.1 12 7 +/- 2.2 13.3 +/-1.9 E-Control 1 5.4 +/- 0.6 6.4 +/- 2.3 6.4 +/- 0.8 7.3 +/-1.3 E-Control 2 7.2 +/- 0.8 5.3 +/- 2.2 7.7 +/- 0.6 6.4 +/-1.3 1-1

PNPP Table 1. Direct Radiation (TLDs), Quarterty Exposure.

Units: mR/91 days 2hdQtr. 3rd Qti.r 4th Qtr, Date Placed 01-15-18 04-04-19 07-10-19 10-31-19 04-04-19 07-1 CM 9 10-30-19 02-10-20 Date Removed 13 6 +/-1.3 10 8 +/-1.6 12.2 +/- 11 12.2 +/-17 Q-1 11.0 +/-0.8 9.1 +/-1.3 9.8 +/- 07 9.3 +/-1.0 Q-3 Q-4 . /V>;- -_.;:* 13.0 +/-0.5 1l8+/-1.5 11 8 +/-0.7 11.2 +/-0.9 Q-5 117 +/-0.7 110 +/-1.2 113 +/-0.6 \ 10.2 +/-1.1 1,3.7 +/- 0.6 12.4 +/-11 13;2+/-0.6 117 +/-0.9 Q-6

/-.' 12 0 +/-1,2 127 +/-06 115 +/-0:8 Q-7 "-:,-.\-i .::::... 126 +/-07 12.1 +/-1.0 11 6 +/-10 11.6 +/-0.6 113 +/-0,9 Q-8 118 +/-1.0 9 7 +/-1.2 11.7 +/-0.9 10.9 +/-12 Q-9 109 +/-10 13 0 +/-07 10,9 +/-0.9 O-ib 129 +/-0:8 13.9 +/- 0.9 f 13.3 +/-1.2 14 8 +/-1.0 13.0 +/-10 Q-11 13:2 +/-0.9 ' 117 +/-17 13.5 +/-0.6 114 +/-0.9 Q-12 Q-13 . -": --. 124 +/-0 8 121 +/-14 12:4 +/-07 128 +/-14 12.5 +/-0.8 12.1 +/-11 12.3 +/-0.6 11.5 +/-11 Q-14 Q-15 12.9 +/-0.9 112 +/-1.1 122+/-0r6 111 +/-11 14.1 +/-0.8 i3;S +/-14 14:8+/-O.8 13:6 +/-1.2 Q-21 14.7 +/-13 14.8 +/-1.4 14.9 +/-12 14.1 +/- 14 Q-23 Q-24 13.8 +/-16 124 +/-12 13 1 +/-13 127 +/-13 Q-29 17.2 +/-1.2 Y ' 15:7'+/-ll^ - 17,4 +/-0.8 15.8 +/-11 16.1 +/-12 13,1 +/-1.0 15.3 +/-0.8 13,2 +/-0.9 Q-30 16:5 +/-1.0 17 0 +/-12 17.1 +/-0,6 16.8 +/-1.2 Q-31 16.9 +/-li 170 +/-0.8 1610 +/-10 Q-33 15.7 +/-0.9 12.4 +/-0.6 10,7 +/-10 12.1 +/-06 107 +/-0.9 Q-35 Q-36 16.0 +/-0.8 14.4 +/-10 17;O+/-O.6 14.7 +/-0.6 12.1 +/-10 12,4 +/-11 13:5 +/-0.8 13;4+/-lO Q-53 13.6 +/-0.6 12.5 +/-1.1 13.9 +/-0.6 12.6 +/- 0.9 Q-54 13.9 +/-10 111 +/-1.0 135 +/-03 111 +/-0.9 Q-55 13.1 +/-1.4 12,4 +/-12 12:8 +/-1.0 12'2+/-lb Q-56 12.8 +/-1.3 12.2 +/-1.0 13.7 +/-11 12.9 +/-0.9 Q-57

^  : * ..-.

96*0.9 10.1 +/-10 101 +/-0:8 10,2 +/-0.9 Q-58 ,'- .*:;>;.

Meams.d. 13.4 +/-17 124 +/-19 13i4+/-20 12.4 +/-1^8 6.7 +/-11 74 +/-0.5 6.8 +/-0.9 Q-Control 1 7.7 +/-0.5 74 +/-0.6 6.6 +/-0.9 73 +/-0.5 (B.5+/-08 Q-Control2 1-2

PNPP Table 1. Direct Radiation (TLDs), Annual Exposure.

Units: mR/365 days 2019 Date Placed 014)8-19 bate Removed 02-10-20 A-1 A-3 47.7 +/-2.3 A-4 53.7 +/-2.1 A-5 52.6 +/-2.4 A-6 57.0 +/-1.8 A-7 55.2 +/-2.8 A-8  ! 528 +/-2.3 A-9 54.3 +/- 2.9 A-10 53.0 +/- 2.2 A-11 59.7 +/-1.9 A-12 57.1 +/-2.2 A-13 58.3 +/- 3.2 A-14 56.2 +/-3.6 A-15 53.2 +/-4;4 A-21 64 4 +/-41 A-23 70,9 +/-27 A-24 58.4 +/-3.9 A-29 74 3 +/-3.1 A-30 62.0 +/-2.8 A-31 67.7 +/-2.5 A-33 72.5 +/-3.4 A-35 52.7 +/-2.4 A-36 701 +/-4.3 A-53 60JO +/-2.8 A-54 59.5 +/-4^1 A-65 56.1 +/-1.7 A-56 59^9 +/-36 A-57 597+/-4;7 A-58) 53.5^+/-^9 Mean+/-s.d. 58.8 +/-6.7 A-Control 1 25.4 +/-15 A-Contrd2 24:6 +/-1.7 1-3

PNPP Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 Location: P-1 Units: pCi/rn?

Collection: Continuous, weekly exchange

' ] '".

Date Volume Date Volume Collected (mJ) Gross Beta 1-131 Collected <m<) Gross Beta 1-131 Reauired LLD 0.0075 0050 6;0075 0050 01-10-19 606 , 0.028 +/-0.003 <i 0.010 07-10-19 639 0.022 +/-0.003 < 0.005 0.023 +/- 0.004 < 0.009 07-17-19 557 0.016 +/-0.003 < 0.007 01-15-19 395 0.020 +/- 0.003

• 0.005 07-24-19 542 0.019 +/-0.003 < 0.010 01-23-19 601 0.028 +/-0.004 < 0.007 07-31-19 545 0.031*0.003 <0.010 01-29-19 455 02-0649 604 6635 +/-0.003 1c 0.004 08-07-19  ::-:-;::"545 ':- " 0.025 +/- 0.003 < o:66b 0.017 +/-0 003 < 0.005 08-14-19 560 0 026 +/- 0,003 < 0.Q09 02-13-19 552 02-20-19 525 0.029 +/-0.003 < 0.007 08-21-19 545 6.027 +/-0.003 < 0.004 02-27-19 504 0.040 +/-0 004 < 0.005 08-28-19 539 0.016 +/-0.003 < o.oio 03-06-19 526 0.029 +/- 0.003 < 0.008 09-04-19 537 0.029 +/- 0.003 < 0.067 565 0.042 +/- 0.003 < 0.007 09-11-19 543 0.027 +/- 0.003 < 0:007 03-13-19 03-20-19 533 0.026 +/- 0.003 < 0.005 09-18-19 488 0.030 +/- 0.004 < 0.007 539 0.017 +/-0.003 < 0.010 09-25-19 536 0.039 +/- 0.003 < 0.006 03-27-19 537 0.021 +/- 0.003 < 0.009 10-02-19 534 0.026 +/- 0.003 < 0:005 04-03-19 0.027 +/- 0.008 < 0.010 3Q2019 Mean+/-s.d. 0.026 +/- 0.006 < 0.010 1Q2019 Meants.d.

0.021 +/-0003 < 0.010 10-09-19 550 0.024 +/-0.003 < 0:006 04-10-19 540 0.015 +/-0.003 < 0.007 10-16-19 519 0.025 +/- 0.003 < 0.005 04-17-19 536 0.011 +/-0.003 < 0.004 10-23-19 517 0.027 +/-0.003 < 0.008 04-24-19 538 05-01-19 550 0.018 +/-0.003 < 0.007 10-30-19 497 0.026 +/-0.003 < 0.007 05-08-19 537 0.011 +/-0.003 < 0.003 11-05-19 429 0.021 +/-0.004 < 0.008 0.017 +/-0.003 < 0.005 11-13-19 585 0.021 +/-0.003 < 0.007 05-16-19 616 532 0.018 +/-0.003 < 0.007 11-20-19 578 0.037 +/-0.003 < 0.008 05-23-1?

470 0.013 +/-0.003 < 0.009 11-28-19 636 0.031 +/-0.003 < 0.006 05.29-19 603 0.015 +/-0.003 < 0.004 12-04-19 492 0.016 +/- 0.003 < 0.011 06-06-19 0.015 +/-0.003 < 0.009 12-10-19 473 0.031 +/-0.004 < 0.011 06-12-19 474 0.016 +/-0.003 < 0.007 12-18-19 648 0.039 +/- 0.003 < 0.004 06-19-19 530 0.016 +/-0.003 < 0.007 12-25-19 554 0.042 +/- 0.003 < 0.007 06-26-19 548 477 0.022 +/-0.003 < 0.006 01-01-20 543 0.039 +/- 0.003 < 0.005 07-02-19, 2Q2019 Mean+/-s.d. 0.016 +/-0.003 < 0.010 4Q 2019 Mean +/- s.d. 0.029 +/- 0.008 < 0.011 Cumulative Average 0.025  ;

2-1

PNPP Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 Location: P-3 Units: pCUtrf Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected Gross Beta 1-131 Collected Gross Beta 1-131 .

Reauired LLD 0.0075 0.050 0.0075\ ,0.050 Q1-10-19 643 0.030 +/- 0.003 < 0.010 07-10-19 692 0.022 +/- 0.003 < 0.004 01-15-19 448 0.020 +/-0.003 < 0.008 07-17-19 614 0.016 +/- 0.003 < 0.006 6l-23-19 630 0.023 +/-0.003 < 0 005 07-24-19 591 0.017 +/- 0.003 < 0.009 01-29-19 492 . 0.030 +/-0.004 < 0.006 07-31-19 614 0.026 +/- 0.003 < 0.009 02-08-19 648 0.029 +/-0.003 < 0.003 08-07-19 618 0.024 +/-0 003 < 0.007 02-13-19 584 0.016 +/- 0.003 < 0.005 Q8r14-19 624 0.022 +/-0 003 < 0.008 02-20^19 557 0.030 +/-0.003 < 0.006 08-21-19 600 0.026 +/- 0.003 < 0.004 02-27-19 552 0.038 +/-0.004 < 0.005 08-28-19 606 0.015 +/-0.002 < 0.009 03-06-19 585 0 030 +/-0.003 .v < 0.007 09-04-19 602 0.025 +/- 0.003 < 0.006 03-13-19 578 0.041 +/- 0.003 < 0.007 09-11-19 617 0.024 +/-0.003 < 0.006 03-20-19 562 0.024 +/- 0.003 < 0.005 09-18-19  ; 565 0.027 +/- 0.003 < 0.006 03-27-19 585 0.019 +/-0.003 <0010 09-25-19 588 0 034 +/- 0.003 < 0.005 04-03-19 598 0,017 +/-0.003 < 0.008 10-02-19 611 0.025 +/- 0.003 < 0.005 1Q2019 Mean+/-s.dr 0.027 +/-0.008 < 0.010 3Q2019 Mean +/- s.d. 0.023 +/-0.005 <0.009r 04-10-19 581 0.024 +/-0.003 <0.010 10-09-19 632 0.019 +/- 0.003 < 0.005 04-17-19 581 0.016 +/- 0.003 < 0.007 10-16-19 602 0.020 +/- 0.003 <0.005 04-24-19 642 0.012 +/-0.002 < 0.003 10-23-19 599 0.024+0.003 < 0.007 05-01-19 618 0.019 +/-0.003 < 0.008 10-30-19 639 0.021 +/- 0.003 < 0.005 05-08-19 608 0.009 +/-0.002 < 0.003 11-05-19 498. 0.023 +/-0.003 <Q007 05-16-19 739 0.015 +/-0.002 < 6.005 11-13-19 672 0.021 +/-0.003 < 0.006 05-2&19 605 0.016 +/-0.003 < 0.006 -. 11-20-19 626 0.034 +/-0.003 <0XiO8 05-29-19 525 0.011 +/-0.003 < 0.008 11-28-19 701 0.031 +/-0.003 <0.005 06-06^19 713 0.015 +/-0.002 <0.004 12-04.19 512 0.017 +/-0 003 < 0.011 06-12^19 542 0.015 +/- 0.003 < 0.008 12-10-19 510 0.027 +/-0.003 <Q.Q1Q 06-19^19 623 0.006 +/-0.002 < 0.006 12-18-19 731 0.033 +/-0.003 < 0.003 06-26-19 600 0.015 +/-0.003 < 0.006 12-25-19 606 0.036 +/-0.003 < 0.006 07-02-19 510 0.022 +/-0.003 < 0.006 01-01-20 594 0.037 +/-0.003 < 0.005 2Q2019 Mean +/- s.d. 0.015 +/-0.005 < 0.010 4Q 2019 Mean +/- s d. 0.026 +/- 0.007 < 6.011 Cumulative Average 0.023 2-2

PNPP Table 2 Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 Location: P-4 Units: pCi/m3 Collection: Continuous, weekly exchange.

Date Volume Date Volume (mJ) Gross Beta 1-131. Collected Gross Beta 1-131 Collected 0.0075 0.050 O.OC 0.050 Reauired LLD 0.027 +/- 0.003 < 0.009 07-10-19 622 0.019 +/- 0.003 < 0.005 01-10-19 649 0.021 +/- 0.003 < 0.008 07-17-19 547 0.019 +/- 0.003 < 0.007 01-15-19 450 0.021 10.003 < 0.005 07-24-19 536 0.019 +/- 0.003 < 0.010 01-23-19 638 497 0.031 +/- 0.004 < 0.006 07-31-19 555 0.028 +/- 0.003 < 0.010 01-29-19 02-06-19 655 0.039 +/-0.003 < 0.003 08-07-19 534 0.026 +/- 0.003 < 0.008 0.016 +/-0.003 < 0.005 08-14-19 548 0.027 +/-0.003 < 0.009 02-13-19 585 0.033 +/-0.003 < 0.006 08-21-19 545 0.029 +/- 0.003 < 0.004 02-20-19 561 0.040 +/-0.004 < 0.005 08-28-19 523 0.016 +/-0.003 < 0.010 02-27-19 522 0.030 +/-0.003 < 0.007 09-04-19 525 0.030 +/- 0.003 < 0.007 03-06-19 564 0.040 +/- 0.003 < 0.007 09-11-19 534 0.024 +/- 0.003 < 0.007 03-13-19 596

< 0.005 09-18-19 489 0.030 +/- 0.004 < 0.007 03-20-19 545 0.025 +/- 0.003 0.019 +/-0.003 < 0.010 09-25-19 510 0.055 +/-0.004 < 0.006 03-27-19 552 0.016 +/- 0.003 < 0.009 10-02-19 523 0.028 +/- 0.003 < 0.006 04-03-19 548 0.028 +/- 0.009 < 0.010 3Q 2019 Mean +/- s.d. 0.027 +/- 0.010 < 0.010 1Q2019 Mean +/- s.d.

0.023 +/-0.003 < 0.011 10-09-19 533 0.021 +/- 0.003 < 0.006 04-10-19 537 0.017 +/-0.003 < 0.007 10-16-19 518 0.026 +/- 0.003 < 0.005 04-17-19 . 537 0.013 +/-0.003 < 0.004 10-23-19 534 0.028 +/- 0.003 < 0.008 04-24-19 547 05-01-19 537 . 0.018 +/-0.003 < 0.007 10-30-19 531 0.025 +/- 0.003 < 0.006 0.011 +/-0.003 < 0.003 11-05-19 462 0.024 +/- 0.004 < 0.007 05-08-19 540 625 0.016 +/- 0.002 < 0.005 11-13-19 601 0.024 +/- 0.003 < 0.006 05-16-19 539 0.017 +/- 0.003 < 0.007 11-20-19 538 0.040 +/- 0.004 < 0.009 05-23-19 05-29-19 461 0.013 +/- 0.003 < 0.009 11-28-19 616 0.031 +/- 0.003 < 0.006^

06-06-19 608 0.015 +/-0.003 < 0.004 12-04-19 446 ,' 0.017 +/- 0.003 < 0.013 0.016 +/- 0.003 < 0.009 12-10-19 452 0.031 +/- 0.004 < 0.011 06-12-19 470 06-19-19 526 0.014 +/- 0.003 < 0.007 12-18-19 631 0.044 +/- 6.003 < 0.004 0.015 +/-0.003 < 0.007 12-25-19 520 0 044 +/- 0.004 < 0.007 06-26-19 546 0.024 +/- 0.003 < 0.006 01-01-20 524 0.039 +/- 0.004 < 0.005 07-02-19 469 2Q2019 Mean +/- s.d. 0.016 +/-0.004 < 0.011 4Q2019 Mean +/- s.d. 0.030 +/-0.009 < 0.013 Cumulative Average 0.025

PNPP Table 2. Airborne particutates and charcoal canisters, analyses for gross beta and iodine-131, Location: P-5 Units: pCi/nrJ" Collection: Continuous, weekly exchange.

Pate Volume Pate Volume Collected Cross Beta 1-131 Collected Cross Beta 1-131 ReauiredLLD 00075 0 050 6.0075 Q;Q5fJ 01-10-19 635 0.029 +/- 0 003 <: 6.010 07-10-19 681 0.017 +/-0.002 < 0.004 61^15-19 425 0.020 +/-0 004 <6:0O8 07-17-19 606 0.015 +/- 0.003 < 0.007 01-23-19 612 0.022 +/-0.003 < 6.005 07-24-19 590 0 013 +/-0.003 < 0.009 01-29-19 460 0.033+/-0.004 < 0.007 07-31-19 603 0.023 +/- 0.003 <0 009 02-06-19 613 0.030 +/-0.003 < 6.003 08-07.19 578 0 020 +/-0.003 <0 608 02-13-19 553 0.015 +/-0 003 < 0.005 08-14-19 611 0.021 +/- 0.003 < 0.008 02-20-19 537 0.032 +/- 0.003 < 6.006 08-21-19 583 0.022 +/-0.003 < 0.004 02-27-19 518 0.036 +/-0.004 < 0.005 08-28-19 585 6.014 +/-0.003 < 0.009 03-06-19 542 0.029 +/-0.003 <0008 09-04-19 574 0.021 +/-0.003 < 0.006 03-13-19 579 0.043 +/- 0.003 < 0.007 09-11-19 604 0.021 +/-0.063 < 6.006 0330-19 553 0.025 +/-0.003 < 0.005 09-18-19 551 0.023 +/-0.003 < 0.006 03-27-19 i 577 0.018 +/-0,003 < 0.010 09-25-19 566 0.031 +/- 0.003 < 6.006 04-03-19 595 0.617 +/-0.003 < 0.668 10-02-19 573 0 020 +/-0.003 < 0.005 1Q 2019 Mean +/-s.d. 0.027 +/-0.008 < 0.010 3^2019 Mean+/-s.d. PO2O+/-6.6P5 < 0.009 64-10-19 568 0.021 +/-0.003 <o;oio 10-09-19 573 0 023 +/-0 003 < 0.668 04-17-19 568 0.014 +/-0.003 < 0.007 10-16-19 539 0 020 +/-0.003 < 0.005 04-24-19 543 0.012 +/-0.003 < 6.004 10-23-19 534 0.023 +/-0.003 < 0.008 05-01-19 549 0.017 +/-0.003 < 0.007 10-30-19 535 0.022 +/-0.003 < 0.008 05-08-19 548 6.609 +/-6.003 <o;o63 11-05-19 464 0.016 +/-0003 < 0.007 05-16-19 620 0.014 +/- 0.002 < 6.005 11-13-19 576 0.021 +/-0.003 < 0.607 05-23-19 544 0,016 +/-6.003 <P007 11-20-19 476 0.035 +/-0.004 < 6010 05-29-19 ,460 0.012 +/-0.003 < 6.009 11-28-19 575 0.028 +/-0 003 < 6.607 06-06-19 604 0.014 +/-0.003 <0004 12-04-19 416 0.012 +/-0.003 < 0.013 06-12-19 434 0.017 +/- 0.003 < 0.010 10-19 422 0.027 +/-0004 < 0.012 06-19-19 528 0.015 +/-6.003 <o;oo7 12-18-19 552 < 0.004 0 034 +/-0.003 06-26-19 497 0.016 +/- 0.003 < 0.008 12-25-19 450 0.041 +/-0.004 < 0.009 07-02-19 519 0.017 +/-0.003 < 0.006 01-01-20 460 0.035 +/- 0.004 < 0.006 2Q2019 Mean+/-s.d. 0015 +/-0.003 <0.010 4Q2pi9 Mean+/-s.d. 0026 +/-0.668 <0.013 Cumulative Average 0.022 2.4

PNPP Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 Location: P-6 Units: pCi/m3 -

Collection: Continuous, weekly exchange.

Volume Date Volume Date (m*) Gross Beta 1-131 Collected Gross Beta 1-131 Collected 0.0075 0050 0.0075 0.050 Reouired LLC>

< 0.009 07-10-19 683 0.022 10.003 < 0.004 01-10-19 661 0.024 +/- 0.003 0.024 +/- 0.004 < 0.008 07-17-19 570 0.017 10.003 < 0.007 01-15-19 443

< 0.005 07-24-19 564 0.018 +/-0.003 < 0.009 01-23-19 655 0.023 10.003 0.029 +/- 0.003 < 0.006 07-31-19 546 0.025 10.003 < 0.010 01-29-19 491 0.031 1 0.003 < 0.003 08-07-19 541 0.024 1 0.003 < 0.008 02-06-19 658 594 0.014 1 0.003 < 0.005 08-14-19 548 0.022 10003 < 0.009 02-13-19 0.028 +/- 0.003 < 0.006 08-21-19 495 0.031 10.003 < 0.005 02-20-19 565 0.040 +/- 0.004 < 0.005 08-28-19 499 0.017 10.003 < 0.011 02-27-19 540 585 0.029 +/- 0.003 < 0.007 09-04-19 470 0.031 10.004 < 0.008 03-06-19 0.042 +/- 0.003 < 0.007 09-11-19 483 0.026 10.003 < 0.007 03-13-19 603 0.023 +/- 0.003 < 0.005 09-18-19 487 0.029 10.004 < 0.007 03-20-19 575 593 0.019 10.003 < 0.010 09-25-19 477 0.044 1 0.004 < 0.007 03-27-19 0.017 1 0.003 < 0.008 10-02-19 469 0028 10.004 < 0.006 04-03-19 631

. 0.02610.008 < 0.010 3Q2019 . Mean i s.d. 0.026 10.007 < 0.011 1Q2019 IMean +/- s.d.

0.01910.003 < 0.010 10-09-19 471 0.026 1 0.004 < 0.007 04-10-19 581 0.014 10.003 < 0.007 10-16-19 446 0.026 +/- 0.004 < 0.006 04-17-19 581 0.011 +/-0.002 <0.004 10-23-19 438 0.028 l 0.004 < 0.010 04-24-19 583 0.015 +/-0003 < 0.006 10-30-19 426 0.028 10.004 < 0.008 05-01-19 569 0009 10.003 < 0.003 11-05-19 463 0.024 10.004 < 0.007 05-08-19 573 0.012 10.002 < 0.005 11-13-19 453 0.028 +/-0004 < 0.008 05-16-19 667 0.015 +/-0.003 < 0.007 11-20-19 586 0.043 1 0.003 < 0.008 05-23-19 603 0.015 +/-0003 < 0.008 11-28-19 665 0.033 10.003 < 0.006 05-29-19 501 0.016 10.002 < 0.004 12-04-19 508 0.019 10.003 < 0.011 06-O6-19 682 0.016 10.003 < 0.008 12-10-19 508 0.034 10.004 < 0.010 06-12-19 541 0.014 10.003. < 0.007 12-18-19 667 0.048 10.003 < 0.004 06-19-19 577 0.014 10.003 < 0.007 12-25-19 567 0.048 10.004 < 0.007 06-26-19 576 500 0.021 10.003 < 0.006 01-01^20 577 0.044 10.003 < 0.005 07-02-19 2Q2019 Mean! s.d. 0.01510.003 < 0.010 4Q2019 Mean l s.d. 0.03310.010 < 0.011

"^ Cumulative Average 0.025 2-5

PNPP Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 Location: P-7 Units: pCi/ro3 Collection: Continuous, weekly exchange.

Date Volume Date Volume (fleeted (nV) , Gross Beta 1-131 Collected Gross Beta 1-131 Required L+/-CI'*: *'-.' 00075/ ;0050 0.0075 0.050 01-10-19 620 0.029 +/- 0.003 < 0.010 07-10-19 665 0.021 +/-0.003 < 0.004 01-15-19 408 0.021 +/-0.004 <0 009 07-17-19 571 0.017 +/-0 003 < 0.007 01-23-19 c 606 ? 0.020 +/-0.003 < 0.005 07-24.19 556 0.019 +/- 0.003 < 0.010 01-29-19 454 0.032 +/-0 004 < 0.007 07-31-19 557 0.027 +/-0.003

• 0.009

> 02-08-19 593 0.031 +/-0.003 < 0.004 08-07-19 559 0.027 +/-0.003 < 0.008 02-13-19 493 0.018 +/- 0 003 < 0.006 08-14-19 560 0.025 +/-0.003 < 0.009 02-20-19 519 0 030 +/-0.003 <0007 08-21-19 ODD 0.028 +/- 0.003 "<-6.004 02-27-19 523 0.036 +/-0.004 < 0.005 08-28-19 54? Q.017 +/- 0003 < 0 010 03-06-19 528 0 029 +/- 0.003 < 0.008 09-04-19 546 0.025 +/- 0.003 < 6.007 03-13-19 568 0.046 +/-0.003 < 6.007 09-11,19 556 0.025 +/-0.003 <b;666 03-20-19 543. 0.023 +/- 0.003 < 0005 09-18-19 538 0 025 +/-0.003 < 0^006 03-27-19 543/ 0 020 +/-0,003 < 0.010 09-25-19 553 0.040 +/- 0.003 < 0,006 04^03>19 551 0 021 +/-0.003 < 0.009 10-02-19 546 0.023 +/-0.003 <X).OO5

iQ26i9r Meants-d. <*027+/-0008 <0;010 3Q2019 Mean+/-s.d. 0 025 +/-0.006 < O.OI6 04-1CH9 556 0,021 +/-0,003 < 0.010 10-09-19 562 0 024 +/-0.003 < 6,006 04-17-19 556 0017 +/-0.003

• 0.007 10-16^19 535 0 024 +/-0.003 < 0.005 04-24-19 575 0.014 +/-0003 < 0.004 10-23r19 531 .0.023 +/-0.003 < 6.008 05-01-10 585 0.6i8+/-6003 <O.6O6 10-30-19 $42 0024 +/-0 003 < 0.006 05-08-19 580 0.008 +/-0 003 > 0.003 11-05-19 471 0 022 +/-0.003 <O.007 05-16-19( 635 0014 +/-0.002 < 0.005 11-13-19 615 0.022 +/-0.003 <0 006 05-23^19 544 0.019 +/-0,003 < 0.007 11-20-19 537 0 037 +/-0.003 <0 009 05-29-19 475 0 016 +/-0,003 < 0,009 11-28-19 606 0,030 +/-a003 ^0.006 06-08-119 612 0;016+/- 0.003 < 0.004 12-04-19 474 0.015 +/-0.003 <0012 06-12-19 494 0.017 +/-0003 < 0.009 12-10-19 450 0.029 +/-0.004 < 0.011-.

06-19-19 540 0.016 +/-0 003 < 0.007 12-18-19 630 0.036 +/- 0.003 < 0.004 06-26-19 554 0.014 +/-0.003 < 0.007 12-25-19 538 0.041 +/-0.004 < 0.007 07-02-19 501 0.023 +/-0003 < 0.006 01-01-20 530 0.038 +/-0003 < 0.005

': '"{' .

2Q 2019 Mean +/- s.d. 0.016 +/-0.004 < 0.010 4Q 2019 Mean +/- s.d. 0 028 +/-6.008 < 0.012 Cumulative Average 0024 2-6

PNPP Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and todine-131 Location: P-35 Units: pCi/m3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (nv*) Gross Beta 1-131 Collected (m*) Gross Beta 1-131 Reauired LLD 00075 0.050 0.0075 0.050 614 0.031 +/- 0.003 < 0.011 07-10-19 484 0.024 +/- 0.003 < 0.019 01-1O-19 01-15-19 410 0.023 +/- 0.004 < 0.026 07-17-19 271 a 0.046 +/- 0.006 < 0.019 01-23-19 612 0.021 +/- 0.003 < 0.010 07-24-19 564 0.014 +/-0.003 < 0.011 473 0.031 +/-0.004 < 0.014 07-31-19 563 0.022 +/- 0.003 < 0.015 01-29-19 02-06-19 659 0.031 +/- 0.003 < 0.012 08-07-19 548 0.020 +/-0.003 < 0.009 0016 +/-0003 < 0.017 08-14-19 561 0.019 +/- 0.003 < 0.008 02-13-19 575 0.031 +/- 0.003 < 0.013 08-21-19 547 0.023 +/- 0.003 < 0.009 02-20-19 533 02-27-19 514 0.037 +/- 0.004 < 0.008 08-28-19 536 0.011 +/-0.003 < 0.016 0.029 +/- 0.003 < 0.016 09-04-19 573 0.012 +/-0.003 < 0.007 03-06-19 555 0.043 +/-0.003 < 0.010 09-11-19 548 0.020 +/- 0.003 < 0.010 03-13-19 590 559 0.025 +/- 0.003 < 0.012 09-18-19 490 0.023 +/- 0.003 < 0.011 03-20-19 0.018 +/- 0.003 < 0.013 09-25-19 533 0.031 +/- 0.003 < 0.016 03-27-19 573 0.019 +/- 0.003 < 0.014 10-02-19 533 0.018 +/- 0.003 < 0.012 04-03-19 566 1Q 2019 Mean +/- s.d. 0.027 +/- 0.008 < 0.026 3Q2019 Mean +/- s.d. 0.022 +/- 0.009 < 0.019 0.027 +/- 0.003 < 0.014 10-09-19 554 0.017 +/- 0.003 < 0.012 04-10-19 558 0.015 +/-0.003 < 0.016 10-16-19 526 0.021 +/- 0.003 < 0.015 04-17-19 558 0.011 +/-0.002 < 0.012 10-23-19 530 0.024 +/- 0.003 < 0.011 04-24-19 579 594 0.020 +/- 0.003 < 0.016 10-30-19 527 0.020 +/-0.003 < 0.015 05-01-19 0.009 +/- 0.003 < 0.016 11-05-19 462 0.019 +/- 0.003 < 0.013 05-08-19 581 661 0.016 +/-0.002 < 0.005 11-13-19 611 0.019 +/- 0.003 < 0.011 05-16-19 0.018 +/-0.003 < 0.012 11-20-19 533 0.027 +/- 0.003 < 0.017 05-23-19 583 0.011 +/-0.003 < 0.015 11-28-19 598 0.026 +/- 0.003 < 0.014 05-29-19 511 653 0.018 +/-0.003 < 0.015 12-04-19 467 0.011 +/-0.003 < 0,011 06-06-19 496 0.016 +/- 0.003 < 0.008 12-10-19 444 0.022 +/- 0.004 < 0.016 06-12-19 06-19-19 578 0.015 +/-0.003 < 0.014 12-18-19 626 0.030 +/-0.003 < 0.009 0.012 +/-0.003 < 0.013 12-25-19 529 0.029 +/- 0.003 < 0.014 06-26-19 555 0.025 +/- 0.003 < 0.020 01-01-20 519 0.029 +/- 0.003 < 0.012 07-02-19 475 2Q 2019 Mean +/- s.d. 0.016 +/- 0.005 < 0.020 4Q 2019 Mean +/- s.d. 0.023 +/- 0.006 < 0.017 Cumulative Average 0.022 8 No reason given for the lower volume.

2-7

PNPP Table 3, Airborne partictJlates, analyses for gamma^emitting Isotopes.

Collection: Quarterly Composite Units: pCi/m3 Location PE-1 Quarter istotr. 2hdQtr. 3rdQtr. 4th Qtr. Req. LLD Lab Code PEAP- 1321 PEAP- 2725 PEAP-4045 PEAP-5086 Vbl.(rnV 6942 6951 7108 7021 Be-7 0.084 +/-0.011 0 071 +/- 0.069 6.089 +/- 0.012 0.062 +/-6 016 C6.58 < 0.0006 < 0.0005 < 0.0004 < 0.0006 '>'-' -.'.

Cb-60 < 0.0003 < 0.0003 < 0.0005 < 6.0003 ...

Cs-134 < 0.0007 < 6.0005 < 0.0006 < 6.0004 0.005 Cs-137 < 0.0006 < 0.0003 < 0.0003 < 0.0005 6.045 Location PE-3^ ::'.-. . *  :*:* ""r '/'' ".-.'"

Lab Code PEAP-1322 PEAP-2726 PEAP-4046 PEAP-5087 VoMm3) .. ::. 74& 7887 . . ' -78412'.-:. ":.: 7922

^Be-7;;'. v.'*..; 0.075 +/-0.012 0d63+/- 0.010 0 066 0 0.009 0;054+/- 0.009 * ** -...- * .*

• Co-58  ? < 00003 < 0 0003 < 00003 < 0.0003 . '

• i'--. *. -.

Co-60 < Q.0008 < 0.0002 < 0.6004 r < 0,0002 '*rtf,-

Cs-134 < 6.0005 < 0 0005 < o;o6o5 < 0.6005 0 005 Cs-137 < 0.0005 < 0:0003 < 0.0002  ; < 0.0004 0,045 Location . -.:-'  :.':-....': PE-4-.  :  :  :::

Lab Code PEAP-1323 PEAP-2727 PEAP-4047 PEAP-5088 Voi (m3)  ::;;;V, .;736;>; -;*. '"'".':: #90 .;' $908; Be>7 -:."'.: 0b69+/- 0.009 0.085 +/- 0:014 0.685 +/- 0 011 0.072 +/- 6 609 Co-58 < 0.0004 < 0 0003 < 6,0006 < 0.0004 *. -

Co-60 < 6.0003 < 0 0006 < 0 0004 < 0.0004 Cs-134 < 00008 < 0.0007 : < 0.0608 ' < oiooos 0.605 Cs-137 < 0.0003 < 0.0005 < OQ005 < 0 0005; 0045 Location  : . : *::. ..-. :.::pe-5 -* -:*.....* -

Lab Code PEAP- 1324 PEAP-2728  ; PEAP- 4048 PEAP- 5089 NAJJ (nrV3) 7199 6982 ';*.; 7704 . 6572 Be-7:-- ' :;-. 0.081 +/-6610 0076 +/-6.012 6,668 +/-0.609 0.655 +/- 0 010 Co-58 5 0.0002 < 0.0006 < 0.0005 ':'< 0 0004 -m Co-60 < 00002 '< 0.0002 < 6.0004 < 0.0003 Cs.134 < 0.0005 < 00005 < P'6005 < 0.0005 0.005 CSr137 ^0.0003 < 6.0004

• ., -..- .. -. < 00003 < 6,0004 0045

- / ** *-"":.  ;....- , . .

3-1

PNPP Table 3. Airborne particulates, analyses for gamma-emitting isotopes.

Collection: Quarterly Composite Units: pCi/m3 Location PE-6 1stQtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Req. LLD Quarter Lab Code PEAP- 1325 PEAP- 2729 PEAP- 4049 PEAP- 5090 Vol. (m3) 7594 7534 6832 6775 0.067 +/- 0.009 0.071 +/- 0.011 0.082 +/- 0.011 0.077 +/- 0.012 -

Be-7

< 0.0003 < 0.0006 < 0.0004 < 0.0002 Co-58

< 0.0003 < 0.0003 < 0.0004 < 0.0003 -

Co-60

< 0.0004 < 0.0005 < 0.0006 < 0.0005 0.005 Cs-134

< 0.0002 < 0.0003 < 0.0006 < 0.0004 0.045 Cs-137 Location PE-7 Lab Code PEAP- 1326 PEAP- 2730 , PEAP-4050 PEAP- 5091 Vol. (m3) 6949 7207 7323 7021 0.080 +/- 0.011 0.073 +/- 0.013 0.074 +/- 0.009 0.072 +/- 0.014 -

Be-7

< 0.0003 < 0.0004 < 0.0003 < 0.0005 Co-58

< 0.0005 < 0.0002 < 0.0003 < 0.0005 -

Co-60

< 0.0005 < 0.0005 < 0.0005 < 0.0007 0.005 Cs-134

< 0.0005 < 0.0003 < 0.0004 < 0.0005 0.045 Cs-137 Location PE-35 PEAP- 1327 PEAP- 2731 PEAP- 4052 PEAP- 5092 Lab Code Vol. (m3) 7233 7382 6749 6926 0.079 +/- 0.011 0.072 +/- 0.011 0.068 +/- 0.011 0.049 +/- 0.010 -

Be-7

< 0.0004 < 0.0006 < 0.0003 < 0.0002 -

Co-68

< 0.0003 < 0.0004 < 0.0003 < 0.0003 Co-60

< 0.0006 < 0.0008 < 0.0004 < 0.0005 0.005 Cs-134

< 0.0005 < 0.0005 < 0.0002 < 0.0003 0.045 Cs-137 3-2

table 4. Lake water, analyses for gross beta and gamma emitting isotopes. PNPP Location: P-34 Collection: Monthly composites Units: pCi/L Lab Code PELW- 337 PELW- 623 PELW-959 PELW- 1502  :

Start Date 12-27-18 01-31-19 02-27-19 03-28-19 Req. LLD End Date 01-31-19 02-27-19 03-28-19 04-25-19 Gross beta 1.3 +/-6.6 1.6 +/-0.6 1.2 +/- 0.6 < 6.9 3.0 Mn-54 ".- ' ::-<--2.3 ' '. <2.5 < 2.8  :" *';, ";< 3.2  ; 11 Fe-59 "-. ' < 4.9  :' . ".< 5.0 < 4.1 < 6.0 *.: 22 Co-58 ***< 17 < 28 < 1.5 < 3.2 Co-60  : < 2.3 <29 < 2.6 . ' '. ;. < 2.4 ' :. '..: i.i::

Zn-65 ' ,*-.: < 3.1 .;: < 2.6 < 2.1 < 5.3 22 Zr-95 <5:0 V l -;*<e.4- <4.8 < 6.6 22 Nb-95  : : *.:::* 1.8 . . < 3 7 < 2.5 < 28 '..;'. 11

• CsVl34 < 3.9 '..;*.. <f,2.9- * /'.'.ii '.*'

Cs-i37  : . :.,< 2,1  : : ' *';* *.<:3.;4; ;-;; < 3.8 < 3 8  ;,*:.. "-'13-"

Ba-140 . :... < 16.1 < 14.2 < 20 7 < 17.8 45 La-140 < 3.0 < 2.9  :  :<&[ :* 11 Lab Code PELW- 2096 PELW- 2429 PELW-2832 PELW- 3512 Start Date 04-25-19 05^30-19 08-28-19 07-25-19 -Req.-LLO End Date 05-30-19 08-28-19 07-25-19 08-30-19 Grbssbeta 1.6 +/- 6.5 < 0.9 w ";<.0.9'..:.** .*i-'t.4'+/--o.6'-v:' 30

Mn-54 ;', ' ; *'**'. <2 7 ' '*:: : :/:< 3.2- * . < 19 **"  ;< 37  ;:'- ;'ii: "'

Fe-59 -. '.":'"< 2.4...'"':. ;; *'* v<;3.6;;;-.:. .\':'..: < 42 * ' '* -. :.:'<.8J6 22 Cb-58 "':' : r<.ixi: ':  :*':' '<'\1 *'*- .' ' ' < )2  : ' '< 57 "'

Co-60  ;;:-;;:; :...;< 13 ]\--y * ' '< 1.3: ' /'"  :.. ;  : <2S.':; V \\'.': < 3:i v:' '"::-iii'

.Zn-65.-"-::*;,:;-',.. *..<'.3.5 ..'.'".. ,. *<....i:7.':':,-:':  ; <*J6 .. 22 '-"

2r-95 ;_':. .*;: . ^6.0 *'. ' ' ;:*:; .<'3.8. '..:: <5.5 '.'* '* < 46 .. 22 Nb-95  ; ' .':;"" .' <'5;7 .' ' ***'..< 2 6 < 3.3 < 5.6 11 Cs-134;-: ";; :.-: '.'.'I'S*'!}'*.: V;*. '.': *3:i'--' ".. < 3,r' -:-  :'.. :iv Cs-137  ;; ' *: ... *<:3.3;.-:)'. '.-.'< 2.6 -, ':

..;;<;3i6:'.  ;-; < 29 .:-';-.;T3: .:;"

Ba-140 *..**..\:<;35.4'  : .< 24.7 < 203 , < 29.6 45 La-140 ' ".' ::./*75 '::::; < 3:2 :- /;* <6J '.**.'*;^-6.3 ; '.- * ^ ' 11 ;' ' ,

Lab Code :.:i..:'. PELW-3882 PELW-4437 PELW-4581 PELW- 5010 Start Date 08-30-19 09-27-19 10-31-19 11-27-19 Req LLD End Date 09-27-19 10-31-19 11-27-19 12-31-19 v Gross beta *:-. * <o.9  ;. 1.5 +/- 0:6 1.0 t 0.5 <0J9 . 3.6

..;.: <Ai *-: :

Mn-54 <2.9 < 1.8 < 3.2 -11' '

Fe-59 .-..:-. ': 5.5,7 ^ '. ' < 35 < 2.9  :....' '. < 7.4 .  ; 22 Co-58 [:/:; :<: 2.5  : . : < -1..4 < 3.3 < 2.3 ' 11 Co-60 '..< 2;7 < 1.0 <2.6 <2.8 *"". 11.. .':;

Zn-65 "':'; . '  :<'4;2 ' < 18 < 17 *.' **:.'- < 4.7 ' 22 Zr-95 *.:::;: ;:<.37 ' ,/ < 17 <3.8 " .< 6.3  :-' 22 Nb-95  ;.:;:'*::;*< 3.5--l ;:'. < 1.4 < 27 ':*: '.' <"2'.4; ;-:- 11 Cs-134 "*.'.'* ^2.9 * ' "< 15 ..' < 3.4 ..'.; . ';< 3.2 /: *if..

Csi137 '*' .. ^:< 3;8, ;.. ':.'. . ' < 1.2 *'.  : - : <:2.9::':'"; ..: .13' :'"

<4:0 Ba-140 ^34.2 *;.;'.. <12A  ;*

< 15-1 < 239 ".': A5 :

U-140 ./ -< 4.6: ;;:;; < 2.8 .:::;:<;i3v."---; < 39 4-1

PNPP Table 4. Lake water, analyses for gross beta and gamma emitting isotopes.

Location: P-36 Collection: Monthly composites Units: pCi/L Lab Code PELW- 338 PELW- 624 PELW- 961 PELW- 1503 12-27-18 01-31-19 02-27-19 03-28-19 Req. LLD Start Date 01-31-19 02-27-19 03-28-19 04-25-19 End Date 1.4 10.6 1.91 0.6 1.71 0.6 1.5 1 0.6 3.0 Gross beta

< 2.0 < 3.1 < 2.9 < 2.9 11 Mn-54

<4.5 <4.5 < 3.8 < 4.5 22 Fe-59

< 1.8 < 1.2 < 2.0 < 2.5 11 Co-58

< 3.1 < 1.4 < 1.7 11 Co-60 <2.3

<2.4 <3.0 < 1.7 < 3.5 22 Zn-65

<4.4 < 3.9 < 4.1 < 5.9 22 Zr-95

< 1.9 < 4.2 < 2.2 < 3.5 11 Nb-95

< 3.1 < 3.5 < 3.0 < 4.0 11 Cs-134

<2.6 <2.5 <2.5 < 3.1 13 Cs-137

< 11.5 < 12.9 < 15.1 < 21.6 45 Ba-140

< 2.5 < 3.5 < 4.0 11 La-140 < 2.0 Lab Code PELW- 2097 PELW- 2430 PELW- 2833 PELW- 3514 04-25-19 05-30-19 06-28-19 07-25-19 Req. LLD Start Date End Date 05-30-19 06-28-19 07-25-19 08-30-19

< 0.8 1.0 1 0.5 1.3 +/-0.6 3.0 Gross beta < 0.9

<3.3 <2.2 < 2.9 < 2.4 11 Mn-54

< 4.4 < 5.0 < 7.7 22 Fe-59 < 7.9

< 3.0 < 1.1 <4.0 11 Co-58 < 3.7

< 2.8 < 1.5 < 1.7 < 1.4 11 Co-60

<4.8 < 3.2 < 3.1 < 5.8 22 Zn-65

< 5.1 < 3.2 < 3.8 22 Zr-95 <3.9

< 3.2 < 4.0 11 Nb-95 <4.8

< 3.9 < 3.8 < 3.4 11 Cs-134 < 3.4

< 1.9 < 1.9 <2.6 < 3.1 13 Cs-137

< 39.1 < 27.6 < 28.6 < 43.4 45 Ba-140

< 6.5 < 6.4 < 8.1 11 La-140 < 7.9 PELW- 3883 PELW- 4438 PELW- 4582 PELW-5011 Lab Code 08-30-19 09-27-19 10-31-19 11-27-19 Req. LLD Start Date 09-27-19 10-31-19 11-27-19 12-31-19 End Date 1.6 1 0.6 1.6 +/- 0.6 1.1 +/- 0.5 3.0 Gross beta < 0.9

< 1.2 < 3.7 < 2.6 11 Mn-54 < 2.5

< 5.2 < 1.9 < 6.7 < 5.9 22 Fe-59

< 1.3 < 3.4 < 2.5 11 Co-58 < 2.7

< 1.8 < 1.3 < 1.4 < 3.0 11 Co-60

< 6.1 < 2.3 < 3.5 < 4.9 22 Zn-65

<4.2 < 3.0 < 7.6 <4.6 22 Zr-95

< 1.9 < 5.2 < 3.0 11 Nb-95 <5.2 Cs-134 < 3.2 < 1.4 <4.2 < 3.4 , 11

< 2.1 < 1.6 < 3.3 < 3.6 13 Cs-137

< 30.0 < 9.9 < 13.8 < 16.9 45 Ba-140

< 5.1 < 3.8 < 5.5 <3.2 11 La-140 4-2

Table A. Lake water; analyses for gross beta arid gamma emitting isotopes. PNPP Location: P-39 Gollectton: Monthly composites Units: pCJ/L Lab Code PELW-339 PELW- 625 PELW-962 PELW- 1505 Start bate 12-27-18 61-31-19 02-27-19 03-28-19 Req. LLD End Date \[- 01-31-19 02-27-19 03-28-19 04-25-19; Gross beta 1.0 +/- 0.5 '< 0 9 14 +/- 06 14 +/-0.6 3.0 Mn-54 < 3.0 < 27 <6.2 '  ; .-.. < 19 '.*/ 11 Fe-59 < 5-5 < 45 <53 22 00-58 < 3.0 < 19 <4.4 * .'.. ,:< ii'.'.; ,- 11 Co-60 l <2.9 < 16 < 41 < 2.4 11 Zn-65 <45 <2:5 < 12^0 *..'..-.* :^:4:3-'. ' 22 Zr-95 <6.6 <6.3 < 6.5 < 57 22 Nb-95 < 3.2 < 35 < 6.9 .  : :.'* <25 -.-: 11 Cs-134 < 4.3 < 2.6 <5.3 < 3.5 11 Cs-137 <25  :. ' < 2 8 ':..'..< 5,4:'.:; 13 fea-140 < 14.9 < 20.1 <308 < 205  ;:' 45 La-140 < 3.9 < 2:5 < 4.0 **'. *.. **< 3.4 v.: :; 11 Lab Code PELW- 2099 PELW-2431 PELW-2834 PELW-3515 Start Date 04-25-19 05-30-19 08-28-19 07-25-19 Req. LLD End Date 05-30-19 ** 08-28-19 0^25-19 08-30^19 ';::{.'.-.;'.".

Gross beta 1,3 +/-06 13+/-0j6 10 +/-05 0,9 +/-0.5^

Mn-54 < 30 < 2.0 <2.8 .[:{

Fe-59 < 55 /:;<74 :  : <6.2 ': .;'":V 5:4.5 ';;. - 22 Co-58J r ',/< 43 ':'.'.V. ;:... *2A  ::-':-' ]- <zx) *.*;:i.t.'--'":

Cc-60 '"\ ". <29 .-..: :: <i.5- *' '.': <zz -\ 11 Zri-65 -: *  :-::' :.::<-;3.3::...-::  ::::- :* <4.4: : -: '.'. '* < 4-5  :: .-'; .; < z:i"':: 22 Zr-95  : -.' < 3.6 .; *.-*,' : < 5:4  :' --. .< 7$  :.:' * <'3:6 "i::: -.' :=22-:"-:;::

Nb-95 < 2.9 < 3.6 .'.. < 3?7':- '.- .-<"3^-;-::--/ :-.l";ti Cs-134 ':y-:'-'\ :;-;:;-: <^2;6; *' . ";: :'. <-3.6 _-" * < 36  :;.. *:;;.-< ZJ2'-.'-:[ - 11 Cs-137 <2:g  :-.-;* <3.5;  :, < 3.9 ,'. '..'<$&".".:.. 13 Bii-140 <25.7 <26 6 < 25:6 - < 316 .;.:. 45 La-140 '* '.';<< 38 " ' '...^3.5:--;- .'* : 11 '.:':.

Lab Code  : PELW-3884 PELW-4439 PELW-4814 PELW-5012-v Start Date i 08-30-19 09-27r19 10-31-19 11-3M9 Req. LLD End Date 09-27-19 10-31-19 11-30-19 ,'-.- 12-31-19  ;  ;:

Gross beta 13 +/-0.6 11 +/-0.6 14 +/- ae  ;* :: "< 0.8 3 0 Mn-54 **';.-;<i.!Bi;'- :'. '*/' ': < 1.8 ,: *-i:.3 :.'.-.' ./:'. <-:i8.';--- ;; 11  ;

• Fe-59  ; :;.*'.7.4'.', :  :*;* .;*. <42 ' ;' < 3.6  :".' '*' '<3,6. .:* *. 22 '

Co-58 .:..: ' <4.0 /. < 2.3 ":;; ;' *.:.; <:i4 *'-: "' ' ":.-:-:<. 17;' *.::

Co-60  ; " .'<-1.JBi'."*- "< 19 *..'**';.*. < 26 /{;\i. '::.'.

Zn-65 ' *.-.' 5'3-7::v.'.- < 3.7 ':..". ':-:<'2-3 '*": ' *: **;-"<:!8.\' ;, *' '22-;^

Zf-95 ** :./: -<:.4.5 - .-. . : i!"-'. <3.a'/---'-::;^ : <-3.2'; ' * ..: :::;<2Je:-;.*;:; 22 Nb-95 <40 ':-" -:'* *..* < 2.6  :,- <2.7 ':'.;..;< 2.4'. ;-Vi ':; 11 Cs-134  :.::.*

• 3.9 ':'..  :<i9v:-':::- .' 5 16 '..*:.':; :< 3.0';'v;i-Cs-137' *...** .' iv<:i.<<-:';::" :** <-i,9-:'- " *'" '.-.:< 10 : : " / *: <i.O .:.:.:. .:vi3;-.^:.

Ba-140 < 192 <25-7 ;:^. :, <211  ::.;.::'. <ZM ** :i0:'v:-

La-140 < 5.3 .'*.. ""< 4.4?;:";/:-:'.: . <3* ' '.': .*<;3;3:-;-':^' ..*ii.;:-;-

4-3

PNPP Table 4. Lake water, analyses for gross beta and gamma emitting isotopes.

Location: P-59 Collection: Monthly composites Units: pCi/L Lab Code NDa NDa ND° PELW- 1506 03-28-19 Req. LLD Start Date End Date 01-31-19 02-27-19 03-28-19 04-25-19 Gross beta - - 1.2 +/- 0.6 3.0

< 3.1 11 Mn-54 -

< 2.7 22 Fe-59 -- -.

--* < 1.7 11 Co-58 -

< 1.9 11 Co-60 -

< 4.2 22 Zn-65 -

< 3.0 22 Zr-95 --

< 2.9 11 Nb-95 -

< 3.0 11 Cs-134 - -

< 2.1 13 Cs-137 .-

< 25.2 45 Ba-140 ,.-

< 2.5 11 La-140 - -

Lab Code PELW-2100 PELW- 2432 PELW- 2835 PELW- 3516 04-25-19 05-30-19 08-28-19 07-25-19 Req. LLD Start Date 05-30-19 08-28-19 07-25-19 08-30-19 End Date 1.5 +/- 0.6 1.5 +/- 0.5 0.9 +/- 0.5 1.1 t 0.6 3.0 Gross beta

< 2.4 K < 3.4 < 3.9 <2.9 11 Mn-54

< 3.5 < 5.8 < 11.1 < 8.7 22 Fe-59

< 3.0 < 2.8 < 3.9 < 2.9 11 Co-58

< 2.4 < 2.9 < 4.3 < 2.6 11 Co-60

< 6.6 < 4.7 < 5.4 < 5.7 22 Zn-65 Zr-95 < 6.1 < 4.4" < 8.8 < 6.1 22

< 4.4 <3.4 < 8.1 < 5.5 11 Nb-95

< 3.3 < 3.3 < 5.1 < 3.0 11 Cs-134

< 2.5 < 2.2 < 5.6 < 3.1 13 Cs-137 Ba-140 < 36.6 < 27.2 < 33.2 <42.2 45

< 8.7 < 3.5 < 7:3 < 9.3 11 La-140 PELW- 3885 PELW- 4440 PELW- 4815 PELW- 5013 Lab Code 08-30-19 09-27-19 10-31-19 11-30-19 Req. LLD Start Date End Date 09-27-19 10-31-19 11-30-19 12-31-19 1.2 +/-0.5 0.9 +/- 0.5 1.6 t 0.6 1.6 +/- 0.6 3.0 Gross beta

< 3.2 < 1.8 < 1.1 < 3.7 11 Mn-54

<2.6 < 3.3 < 2.0 < 5.8 22 Fe-59

<3.3 < 1.9 < 1.2 < 2.6 11 Co-58

< 1.6 < 1.4 < 1.3 < 2.8 11 Co-60

< 6.1 < 2.9 < 1.9 < 3.6 22 Zn-65

< 5.8 < 4.0 < 3.3 < 4.3 22 Zr-95

< 2.2 < 2.1 < 3.8 11 Nb-95 < 3.8

< 4.1 < 1.9 < 1.4 < 3.9 11 Cs-134

<4.3 < 2.3 < 1.5 < 2.8 13 Cs-137 Ba-140 < 22.3 < 17.2 < 14.3 < 23.3 45

<3.7 < 3.7 < 5.0 < 6.5 11 La-140 0 "ND" = No data; see Tabte 2.0. Listing of Missed Samples.

4-4

Table 4. Lake water, analyses for gross beta arid gamma emitting isotopes. PNPP Location: P-60 Collection: Monthly composites Units: pCi/L Lab Code NO8 NDa ND° PELW-1507 Start Date 03-28-19 Req. LLD End Date 01-31-19 02-27-19 03-28-19 04-25-19 Gross beta ' ' '*'. -  : ..'*I *.....'. *'".- ' '":' '- ' * " 1.1 +/-0.6 3.6 Mn-54 < 3.1 r --

11 Fe-5$ - -

<2.0 22 Co-58 - .-; -

< 1.7 11 Co-60 - .-

< 2.1 11 Zn-65 - - -

<4.3 22 Zr-95 -

< 5.0 22 Nb-95 - - -

< 3.5 11 Cs-134 - N -- -

< 3.9 11 Cs-137 - -

< 2.7 13 Ba-140 - -

< 17.8 45 La-140 - - < 4.0 11 Lab Code PELW- 2101 PELW- 2433 PELW- 2836 PELW- 3517 Start Date 04-25-19 05-30-19 08-28-19 07-25-19 Req. LLD End Date 05-30-19 06-28-19 07-25-19 08-28-19 Gross beta 1.4 +/- 0.6 1.6 +/- 0.6 < 0.9 1.2 l 0.6 3.0 Mn-54 <2.5 <2.4 < 3.4 < 2.4 11 Fe-59 < 3.5 < 3.8 <6.8 <4.3 . 22 Co-58 < 1.7 <2.6 < 3.1 < 3.0 11 Co-60 < 2.5 <2.2 < 4.2 < 2.0 11 Zn-65 < 2.1 < 2.9 < 3.8 < 2.3 22 Zr-95 < 5.8 < 4.7 < 4.7 < 4.7 22 Nb-95 < 3.9 < 3.1 < 5.8 < 3.5 11 Cs-134 <2.7 < 3.1 <4.5 < 2.3 11 Cs-137 < 2.9 < 3.8 < 4.7 < 2.8 13 Ba-140 < 39.6 < 16.1 < 24.7 < 22.5 45 La-140 < 8.1 < 2.4 < 9.4 < 6.9 11 Lab Code PELW- 3886 PELW- 4441 PELW- 4816 PELW- 5014 Start Date 08-30-19 09-27-19 10-31-19 11-30-19 Req. LLD End Date 09-27-19 10-31-19 11-30-19 12-31-19 Gross beta <0.9 1.4 +/- 0.6 1.0 +/- 0.5 1.1 +/- 0.5 3.0 Mn-54 < 1.9 <2.4 < 1.3 < 2.7 11 Fe-59 < 3.7 * < 5.1 < 1.4 < 5.6 22 Co-58 < 3.0 < 2.1 < 7.6 < 3.7 11 Co-60 < 1.8 < 1.8 < 1.3 < 2.1 11 Zn-65 < 4.5 < 2.8 < 2.6 < 2.9 22 Zr-95 <2,7 <4.6 < 2.5 < 7.6 22 Nb-95 <2.6 < 3.6 < 2.1 < 3.3 11 Cs-134 <2.9 <2.5 < 1.2 < 3.6 11 Cs-137 < 3.2 < 2.2 < 1.3 < 4.1 13 Ba-140 <25.5 < 15.5 < 12.5 < 31.2 45 La-140 < 4.2 <4.9 < 5.0 < 7.1 11 3 "ND" = No data; see Table 2.0, Listing of Missed Samples.

4-5

PNPP Table 4. Lake Water, analysis for tritium.

Collection: Quarterly composites of monthty collections.

.:': " ' ..' Units:' pCtfL '-.'.:: '.'.'.'""'.-. ' \;:;- :...;' ...;.V : ..-..

Required limit of detection; 1500pCi/L Location *^*:^:-:-v"--:-.p44"V:.

Period /-: :'. 1st Qtr.  ; 4th Qtr.

Lab Code PELW-2449 PELW-5015 H-3 *f---.: ;

• 155 .':':' -

v

-^

4 CO ' '

ly9

• :** 'V <-15i"-'-;.'-\'

Location P-36 y.'.-/':;.' * -:; ,..' .,. <

Period y-'-. 1st Qtr 2nd Qtr Srddtr. 4th Qtr.

Lab Code PELW-Q979 PELW-2450 PELW-3896 PELW-5016 H-3 .  ! . : < 155 -.  :'" * '< 151 '.'.

':'.' 'V -' '.' ' **' -

Location  :..,..;. P-39 Period ' ;.:; \':y,irt.Hr:-r';-':'* '. ;'.-. 2nd Qtr 3rdQtrV 4thQtr.

Lab Code PELW-0980 PELW-2451 PELW-3897 PELVV-5di7 H-3 Location ^;:-;,T-;r-^::':-P-59^;;"

4triQtr.

Period .^:^-.:;;::1stQtr,^, ..:;;

Lab Code PELW-245i PELW-3898  : PELW^5018 H-3 \ A'  ::'.:'.-'."-.:':<' 151 I'-...:0--

Location 3rd Qtr. 4thQtr.

Period

-'

.;1?t.?u-.

..;;.

;.

Lab Code PELW-2453 PELWv3899 PELW-5b20 h-3^.;.;;:;;;: ) .. ' -.< 159  ;;-:.V. < 151 '.:::;.  :;::. *.;;;.< 158  ;

aoNS" No sample available, shoreline frozen.

4-6

PNPP Tabte 7. Food Products, analyses for gamma emitting isotopes.

Collection: Monthly Units: pCi/kgwet

.^"*' .' Location: P-2  ;. ..',. ':.-.:. -.'..'; '_:',",.:

Lab Code PEVE- 2685 PEVE- 2666 NS* PEVE-3535 Date Coflected 07-16-19 07-16-19 08-20-19 09-18-19 Req. LLD Sample type Japanese greens .. Turnip greens Japanese greens Be-7 180 +/-93.5 188 +/- 99.2 622 +/- 138 K-40 3851 +/- 308.8 3570 +/- 307.4 5423 +/- 390 ' . ' * ;

Cd-58 *"< 8.7 < 8 3 < 8.2 Co-60 < 5.1 < 8,8 < 8.8 * .i 1-131 < 16 8 < 19.8 < 14.9 45 Cs-134 < 81 < 9.1 < 10,7 45 Cs-137 .< 35:8 <10.2 < 12.3 60 Lab Code PEVE 3536 bate Collected 09-1M9 Req LLD Sample Type Turnip greens Be-7 574 +/-106 K-40 5093 +/-298 bo-58 * /*'* 5.4 Co-60 < 8.7 1-131 < 8.3 45 45 Cs-137 60 "NS" = No sample; see Table 2.0, Listing of Missed Samples.

PNPP Table 7. Food Products, analyses for gamma emitting isotopes.

Collection. Monthly Units: pCj/kg wet Location: P-16 Lab Code PEVE- 2667 PEVE- 2668 PEVE-2670 PEVE- 3128 Date Collected 07-16-19 07-16-19 07-16-19 08-20-19 Req. LLD Sample Type Japanese greens Turnip greens Swiss chards Swiss chards Be-7 160 +/- 84 < 83 319 +/- 142 363 +/-119 K-40 3785 +/- 272 3741 +/- 264 8257 +/- 491 4901 +/- 309 Co-58 < 90 < 9.1 < 11.6 < 10.1 "-'

Co-60 ' . ;. : < 6:8  : < 7JB *< 12.1 . ' - '  :< 6i1  ; '

1-131 < 184 < 13.3 < 22.8 < 25,4 45 Cs-134 <68 < 79  ; < 13:2  : < 9.3 45 Cs-137  ; ' '. ;< 4 8 .  ; < 11.6 ..' . ,< 11,1 60 Lab Code PEVE-3129 PEVE- 3130 PEVE- 3537 PEVE- 3538 Date Collected 08-20-19 08-20-19 69^18-19 ^ 09-18-19 Req. LLD Sample Type Japanese greens Collard greens Swiss chards Japanese greens Be-7 355 +/-88V56 < 65 2 307 +/-110 349 +/- 122 *' .-'--

K-40 2856 +/- 220.80 2833 +/-219 4236 +/- 288 5930 +/-339 -:

• '. .-'*-

• 7i>" : :A " * -' /"** '*'".<" 4i;2 *':---/:: - .- : ' :<;7-6 V::- '*-.*. .':v.< 4-a -.:.*- -- *'* ":V. ,.-

Co-60 < 6.0 < 5.7 < 10.6 1-131 -*-.-:'-' < 14.1 ' : *.- < y\$ ' < 20.3 .- * " > :- <v17.9: *. . ' ;/; 45  ;

• '. ^; 9-5 < 9.1 45 Cs-134 '..,.' . - : < 7,5 . - < 5;9 Cs-137 * ..*; < 8.3  : '": < 65  : <94 < 10:8 60 Lab Code PEVE-3539 PEVE- 3540 Date Collected 09-18-19 09-18-19 Req. LLD Sample type Turnip greens Collard greens Be-7 481 +/-149 < 90 ' -*-

K-40 6180 +/-385 3357 +/- 224 Co-58 < 6.1 < 60 Co-60 < 9,5 < 8.4 ' --=.-;: . '

< 25.9 < 17.1 45 M31 Cs>134  ;'..* :-; . ':'<. 11.3 * *< 7 8 45

< 5.8 60 Cs-137 < 12.4 7-2

PNPP table 7. Food Products, analyses for gamma emitting isotopes.

Collection: Monthly Units: pCi/kgwet

_ Location: P-20 Lab Code PEVE-2671 PEVE-2672 PEVE-2673 PEVE-2674 Date Collected 07-16-19 07-16-19 07-16-19 07r16r19 Req LLD Sample type Cojlard greens Japanese greens Swiss chards Turnip greens

; Be-7

'

:.'./;.:_; ':- .<8i -:> : 221 +/- 98 223 +/- 117 244 +/-111 K-40 4160 +/- 297 5270 +/-363 8138 +/-415 5700 +/- 411 Co-58 < 7.1 < 6.0 < 8.5 < 11.9 COr60 < 7,8 ' ,*-4.2 '.- * *' < 114 < 5.6 1-131 < 17;8 < 13.7 < 18-0 < 28.6 45 Cs-134 < 11.8 < 9.9 < 107 < 13.4 45 V/v"?-'  :

CM 37 < 68 < 12J2 < 9.8 Lab Code PEVE-3131 PEVE-3132 PEVE-3541 PEVE- 3542, Date Collected Oa-20-19 08-20-19 09-18-19 09-18-19 Req. LLD Sample Type CoDard greens Swiss chards Collard greens Turnip greens

.:-':'** Be-7 .**:. :': < 121 474 +/-104 V <$s  ;.':; 345 +/-101 K-40 4166 +/- 340 5770 +/- 320 4093 +/-291 6038 +/- 335 Co-58 < 9.3 < 9,2 "..< 7.9 < 9.1 Co-60 <8.9 i : . "' < 6'3 '.].;.,.. ': :<8..1," *-.':" < 8.5 1-131 * * .::.v ' < 18,8 '"' ' ^ '16*2 .-.' <277i < 18.7 45

' . Cs-134 y\\::^'. *';\ < 12.1 .- ;-.' < 88  :'-' < 10.1 < 8'2 45

,--,,.Cs-i37.;;-  :^ ;: < 1QO  :\,<;11,r:;:.;-:: *- < 84 60 Lab Code PEVE-3543

• . .'.*  :-L:y'-r-  :"  : : .: 'V/'. Y;>

Date Collected 09-18.19 ReqiLLD Sample type Swiss chards

. * :.. Be-7 *; : 245 +/-102

. ,:k4o. .  ; . . 4071 +/- 250 * " ;. ' ; V : '-

Co-58  :*:" '< 4.4 ' *'

Co-60 >*...  ;.' < Q2 ' .-. '-" ' -

/!  :. 1-131 .:'* */::. .-*< 15.8 45 Cs-134 < 72 45 Cs-137  : -':' ": < 8.2 60 7-3

PNPP Table 7. Food Products, analyses for gamma emitttng isotopes.

Collection: Monthly Units: pCi/kgwet Location: P-37 Lab Code PEVE- 2675 PEVE- 2676 PEVE- 3133 PEVE- 3134 Date Collected 07-16-19 07-16-19 08-20-19 08-20-19 Req. LLD Sample Type CoOard greens Turnip greens Collard greens Turnip greens Be-7 <84 <98 < 111 435 +/- 157 --

K-40 4786 i 295 5435 +/- 363 3077 +/- 294 4491 t 380 **

Co-58 < 5.4 < 9.5 < 8.2 < 7.9 -**

Co-60 < 11.5 < 11.5 < 7.0 < 5.6 -

M31 < 15,2 < 18.4 < 26.4 < 30.8 45 Cs-134 < 10.0 < 9.1 < 10.6 < 14.3 45 Cs-137 < 8.6 < 11.8 <62 < 14.0 60 Lab Code PEVE- 3135 PEVE- 3544 PEVE- 3545 PEVE-3546 Date Collected 08-20-19 09-18-19 09-18-19 09-18-19 Req. LLD Sample Type Swiss chards Collard greens Turnip greens Swiss chards Be-7 420 +/- 159 < 92 208 +/- 102 267 +/-87 K-40 3534 +/- 308 4380 +/- 247 3936 +/- 293 3596 +/- 279 -

Co-58 < 11.5 < 6.9 < 7.8 <6.2 -

Co-60 < 7.9 <6.9 < 11.4 < 8.3 .-

M31 < 15.8 < 19.5 < 17.5 < 19.9 45 Cs-134 < 12.4 < 6.5 < 11.8 <8.4 45 Cs-137 < 12.0 < 82 < 7.6 < 7.9 60 Lab Code PEVE- 3547 PEVE- 3875 PEVE- 3876 PEVE- 3877 Date Collected 09-18-19 09-27-19 09-27-19 09-27-19 Req. LLD Sample Type Japanese greens Collard greens Turnip greens Swiss chards Be-7 297 +/- 95 124 +/- 71 258 +/- 106 373 +/- 120 -"

K-40 3679 +/- 236 3734 +/-212 5145 +/- 273 4919 +/- 290 --

Co-58 < 7.5 < 7.7 < 7.1 < 8.0 -

Co-60 < 5.7 < 5.3 < 10.7 < 8.9 -

1-131 < 12.3 < 37.1 < 40.3 < 31.9 45 Cs-134 < 7.1 < 5.7 < 7.2 < 9.0 45 Cs-137 <6.5 < 7.1 < 8.0 < 10.1 60 Lab Code PEVE- 3878 Date Collected 09-27-19 Req. LLD Sample Type Japanese greens Be-7 379 +/- 111 .-

K-40 4773 t 283 .-

Cq-58 < 5.0 -

Co-60 < 7.4 -?

1-131 < 36.3 45 Cs-134 <9.2 45 Cs-137 < 8.7 60 7-4

PNPP Table 7, Food Products, analyses for gamma emitting isotopes.

uouectioi1: Monthly Units: pCi/kg wet Location: R-70 Lab Code PEVE- 3136 PEVE-3137 PEVE-3548 PEVE- 3549 Date Collected 08>20-19 08-20-19 09-18-19 09-18-19 Req.aD Sample Type Turnip greens Wild vegetation Turnip greens Swiss chards Be-7 291 +/-88 2555 +/-318 255 +/- 112 336 +/-135 K-40 4196 +/- 255 6795 +/-648 5032 +/- 372 6968 +/- 438 . 2-:

Co-58 < 77 < 23.6 < 7.5 < 121 ' ' i'ii. :'.

CcUBO < 5.5 < 110 < 9.9 < 14.2 . - '

M31 < 13 7 <34.1 < 21 6 <201 45 Cs-134 <7.6 < 20.3 < 13.4 '*< 156 45 Cs-137 <6;8 < 242 < 9,3 < 13.1 60 Lab Code PEVE- 3550 Date Collected 09-1 tV1$ Req. LLD Sample Type CoHard greens -

Be-7 252 i 98 K-40 4419 +/-304 .' i - - '

C<>-58 < 53 Co-60 **:/ *-..5.4---'-- ' '*.

M31 <26;9 45 Cs-134 <96 45 Cjf137 < B.6 '...: <<1i 7-5

PNPP Table 9. Fish, analyses for gamma emitting isotopes.

Collection: Annually Units:. pCi/kg wet Location P-25 PEF- 2140 PEF- 2142 PEF- 2143 PEF- 2144 Lab Code 08-12-19 06-12-19 06-12-19 06-12-19 Req. LLD Date Collected Lake Trout White Perch Yellow Perch Walleye Sample Type 1387 +/- 325 1006 +/- 261 3260 +/- 348 1974 +/- 333 >>-

K-40

< 20.9 < 12.8 < 21.4 < 16.3 94 Mn-54

< 31.7 < 26,7 < 41.9 <23.4 195 Fe-59

< 24.4 < 7.6 < 26.0 <23.1 97 Co-58

< 14.1 < 9.5 < 17.9 < 10.5 97 Co-60

< 32.8 <25.0 < 44 6 < 32.9 195 Zn-65

< 15.6 < 21.6 < 17.5 97 Cs-134 , < 21.4

< 18.3 < 10.9 < 22.7 <20.1 112 Cs-137 Location P-25 Lab Code PEF- 2145 PEF- 2146 PEF- 3863 PEF- 3864 06-12-19 10-09-19 10-09-19 Req LLD Date Collected 08-12-19 Freshwater Drum White Sucker Lake Trout Smattmouth Bass Sample Type K-40 1839 i 360 885 +/-303 2134 +/- 400 1351 +/- 319 '-

< 20.2 < 19.8 < 15.5 94 Mn-54 < 22.1

< 19.8 < 45.3 <31.2 < 25.5 195 Fe-59

< 17.0 <25.6 < 17.4 < 14.5 97 Co-58

< 16.0 < 16.9 < 10.6 97 Co-60 < 9.3

< 31.1 <3Q4 <39.0 < 42.4 195 Zn-65

< 18.4 < 18.9 < 20.8 97 Cs-134 < 18.0

< 16.7 < 20.4 < 23.1 < 20.1 112 Cs-137 Location P-25 PEF- 3865 PEF- 3866 PEF- 3867 PEF. 3868 Lab Code 10-09-19 KMJ9-19 10-09-19 10-09-19 Req. LLD Date Collected White Bass Walleye Channel Catfish White Sucker Sample Type K-40 23131 541 1919 +/- 382 1261 +/- 356 1740 +/- 428

< 20.2 < 17.5 < 17.1 94 Mn-54 < 39.9

< 52.0 <47.9 < 62.7 195 Fe-59 <49.0

< 36.6 < 16.0 < 22.4 < 15.6 97 Co-58

< 14.8 < 16.9 < 10.2 97 Co-60 <20.2

< 75.4 < 37.9 < 39.3 < 47.8 195 Zn-65

< 41.6 < 18.9 < 19.4 < 20.4 97 Cs-134

< 19.6 < 19.0 < 24.6 <20.4 112 Cs-137 9-1

PNPP Location P-25 LabCpde PEF- 3869 Date Collected 10-09-19 Req. LLD Sample Type Redhorse Sucker k-40 2217 +/-375 Miv54 < 18.9 94 Fe-59 " .'*

• 322 . 195 C6-58 < 12.3

• 97 Co-60 < 13.9 97 2<<v66 < 19.3 195 Cs-134 < 21.8 97 Cs-137 < 96 112

PNPP Table 9. Fish, analyses for gamma emitting isotopes.

Collection: Annually Units: pCi/kg wet Location P-32 Lab Code PEF- 2147 PEF- 2148 PEF- 2149 PEF- 2150 Date Collected 06-12-19 08-12-19 06-12-19 06-12-19 Req LLD Sample Type Walleye White Perch White Sucker Smallmouth Bass K-40 1240 +/- 331 1454 1 343 964 1 211 1291 l 331 -

Mn-54 < 24.0 < 13.4 < 17.6 < 12.9 94 Fe-59 < 32.0 < 35.3 < 35.6 < 30.8 195 Co-58 < 23.7 < 16.6 < 17.7 < 10.1 97 Co-60 < 15.2 < 12.4 < 12.9 < 16.1 97 Zn-85 < 29.5 < 18.7 ' < 26.9 < 17.2 195 Cs-134 < 20.8 < 16.2 < 12.8 < 17.0 97 Cs-137 ' < 18.7 < 20.5 < 12.0 < 8.9 112 Location Pt32 Lab Code PEF- 2151 PEF- 3870 PEF- 3871 PEF- 3872 Date Collected 08-12-19 10-09-19 10-09-19 10-09-19 Req. LLD Sample Type Freshwater Orum Redhorse Sucker Common Carp White Bass K-40 1214 +/- 512 1167+/- 340 1658 1 335 1802 l 603 -

Mn-54 <21.7 < 15.6 <21.0 < 10.7 94 Fe-59 < 32.3 < 45.3 < 33.2 < 53.0 195 Co-58 <28.6 < 13.4 < 21.0 < 21.9 97 Co-60 < 12.7 < 10.9 < 122 < 16.4 97 Zn-65 < 55.4 < 29.0 < 39.3 < 23.5 195 Cs-134 < 26.9 < 16.9 < 17.7 < 22.4 97 Cs-137 < 11.2 < 16.4 < 14.8 < 22.0 112 Location P-32 Lab Code PEF- 3873 PEF- 3874 Date Collected 10-09-19 10-09-19 Req. LLD Sample Type Walleye Gizzard Chad K-40 3195 +/- 442 981 1 307 Mn-54 < 19.8 < 14.9 94 Fe-59 < 51.3 < 46.8 195 Co-58 < 17.0 < 11.5 97 Co-60 < 13.9 < 14.2 97 Zn-65 < 25.6 < 25.8 195 Cs-134 < 24.1 < 19.7 97 Cs-137 < 17.1 < 15.3 112 9-3

PNPP Table 11. Sediments, analyses for gamma emitting isotopes.

Collection: Semiannual^ Units: pCi/kgdry Location P-64 Lab Code PEBS- 1500 PEBS- 3879 Date Collected 04-25-19 10-09-19 1009-19 Req LLO K-40 11716 1 303 10685 +/- 298 Co-58 < 9.4 < 15.5 50 Co-60 < 7.1 < 8.3 40 Cs-134 < 8.0 < 9.0 112 CSr137 < 9.3 < 7.6 135 Location P-66 Lab Code PEBS- 1501 PEBS- 3881 Date Collected 04-25-19 09-27-19 Req. LLD K-40 9581 +/- 271 10138 +/- 263 Co-58 , < 112 < 13.7 50 Co-60 < 7.6 < 8.5

<8.5 40 Cs-134 < 6.2 < 7.7 112 Cs-137 < 5.5 < 9.6 135 11-1

2019 Annual Environmental and Effluent Release Report Appendix D Corrections to Previous AEERR

2019 Annual Environmental and Effluent Release Report APPENDIX D Corrections to Previous Annual Environmental and Effluent Release Reports There were no corrections from the previous reports.

D-1

2019 Annual Environmental and Effluent Release Report Appendix E Abnormal Releases

2019 Annual Environmental and Effluent Release Report APPENDIX E Abnormal Releases Residual radioactivity remains in the Nuclear Closed Cooling (NCC) system due to past leakage from the reactor coolant system. This radioactivity will continue to be monitored, and any detectable activity measured from the NCC system to Emergency Service Water is tracked and recorded as a continuous abnormal release.

Residual radioactivity was detected in the NCC system the months of June, July, August, September, and October (Quarters 2, 3, and 4) and were recorded as a continuous abnormal release. Cobalt-60 in the range of 3.19E-07uCi/mL to 6.91 E-07uCi/mL was detected June through September. Gross alpha activity was detected in the September, and October monthly composites.

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total time period for continuous release, min 0.00E+00 4.32E+04 1.32E+05 4.46E+04 Total volume released, liters 0.00E+00 1.26E+04 3.87E+04 1.30E+04 Average quarterly flow rate, L/min 1.67E+05 1.51E+05 2.32E+05 1.44E+05 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual A. Fission and Activated Products (Ci)

Cobalt-60 <5.0E-07 1 3.80E-07 1.47E-06 <5.0E-07 1 1.85E-06 B. Tritium (Ci) - <LLD <LLD <LLD <LLD <LLD C. Noble Gases (Ci) <LLD <LLD <LLD <LLD <LLD D. Gross Alpha (Ci) <LLD <LLD 2.37E-08 2.45E-08 4.82E-08 1 - (<) Less than the ODCM-required lower limit of detection, units in uCi/mL

<LLD - Less than the ODCM required lower limit of detection There were no abnormal gaseous releases in 2019.

E-l

2019 Annual Environmental and Effluent Release Report Appendix F ODCM Non-Compliances

2019 Annual Environmental and Effluent Release Report APPENDIX F ODCM Non-Compliances There were no ODCM non-compliances for 2019.

Anomalies Environmental Monitoring:

Shoreline water sampling (#59 and #60) was not obtained in the months of January, February, and March of 2019 due to the shoreline being frozen and, or unsafe conditions to obtain the sample. This is normal for this time of year, and sampling resumed when conditions changed.

On 5/8/19 groundwater well MW-2C was not sampled due to insufficient sample volume available. Piezometer tube N-3-83 detected 325 pCi/L of tritium on 5/7/19. These results are below the reporting level of 2000 pCi/L REMP broadleaf vegetation participant (#70) did not have samples available for July.

Excessive rains in June coupled with health issues resulted in immature plants that were insufficient in quantity to obtain a sample. This is the control location located 16.2 SSW from PNPP. Location #70 is at a higher elevation and vastly different weather compared to the plant. Two to four samples were obtained from the four indicator participants around the site.

This was the first month to obtain samples in 2019.

On 7/17/19 Antioch (#35) air sampler was found with no flow on the keypad indicating a turbine failure. Time and flow as found was: 127:27 hrs and 44 ft3 and the air filter paper was discolored, indicating proper run time. The turbine was placed on an air flow meter to check flow and read 1.25 ft3. The turbine was replaced, and it was recalibrated satisfactorily. The total volume of air sent to the lab was changed to 9,558.75 ft3 (instead of 44ft3), which is the flowrate of 1.25 ft3/min x 127:27 hrs.

REMP broadleaf vegetation participant (#2) on 8/20/19 had insufficient growth and no vegetation samples were able to be collected. This missed sample was captured on the field form and documented in the monthly report issued by the vendor.

F-1

2019 Annual Environmental and Effluent Release Report Appendix G ODCM Changes

2019 Annual Environmental and Effluent Release Report APPENDIX G ODCM Changes Revision 23 Effective October 8, 2019 Scope of Revision:

1. Updated Tables A-2, A-3, and A-4 with new calculated %/Q and D/Q values. These changes occurred on pages 79-81 of CHI-ODCM with clearly identified markings.

2. Deleted data in Table A-3 and A-4 at distances not used in MIDAS or the USAR.

These changes occurred on pages 80 and 81 of CHI-ODCM with clearly identified markings.

3. Reworded Section 4.1 to comply with the requirements of 40 CFR 190 for Total Dose.

These changes occurred on page 67 of CHI-ODCM with clearly identified markings.

4. Updated old references to 10CFR20.405c to 10CFR20.2203 in section 4.1. These changes occurred on page 67 of CHI-ODCM with clearly identified markings.

5. Removed reference to G50-K805A/B and G50-K926/7 from Section 2.1.1.3.

Indication was removed as part of the digital upgrade per ECP-05-0147-003. These changes occurred on page 4 of CHI-ODCM with clearly identified markings.

Justification for Change Meteorological conditions change over time. An evaluation is necessary as to whether the changes are significant enough to warrant updates to data used for dose projections.

The periodic review of site meteorological data from 2006 to 2016 indicated that site meteorology had changed significantly from the 1972 -1982 data originally used to develop the atmospheric dispersion (x/Q) and deposition parameters (D/Q). ODCM Tables A-2, A-3, and A-4 were updated with new calculated x/Q and D/Q values as recommended by the 2016 study that examined the meteorological data from 2006 to 2016. Deletion of data in ODCM Tables A-3 and A-4 aligns the ODCM with the distances and data in the USAR. The data removed is not used within the MIDAS program for release calculations Section 4.1 was reworded to comply with the requirements of 40 CFR 190 for Total Dose.

Editorial changes removed the non-conservative "twice" factor. Old references were also updated in section 4.1 from 10CFR20.405c to 10CFR20.2203. 10CFR20.405c no longer exists.

G50-K805 is no longer a valid component number. G50-K926 was removed from service as part of ECP-05-0147-003 when the supply lead was lifted. This was performed as part of a conversion of portions of the radwaste system from analog control logic to digital logic.

Section 2.1.1.3 was updated to remove references to G50-K805A/B and G50-K926/7 equipment that is no longer in service.

G-1

2019 Annual Environmental and Effluent Release Report Change Determination No change in intent or methodology was made that would change the level of radioactive effluent control. Meteorology data was updated based on historical data between the years of 2006 to 2016. The update to the meteorology data will improve the accuracy of the effluent calculations based on fact that the dispersion data is more representative of current meteorological conditions. The data was updated from original USAR data generated between 1972 to 1982 to more recent and representative current data generated between the years of 2006 to 2016. Therefore, there is no adverse impact.

G-2

2019 Annual Environmental and Effluent Release Report Appendix H Changes to Process Control Program

2019 Annual Environmental and Effluent Release Report APPENDIXH Process Control Program Changes There were no changes to the Process Control Program during this reporting period.

\

r

\

V I

H-1

Enclosure B L-20-043 Offsite Dose Calculation Manual, Revision 23

ODCM Page: ii Rev.: 23 TABLE OF CONTENTS

1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS ZZZZZZZZZZZZ.2 2.1 Batch Releases 2 2.1.1 Monitor Alarm Setpoint Determination 3 2.1.2 10CFR20 Compliance-Liquid Effluent Concentration ^"5 2.2 Continuous Releases 7 2.2.1 Monitor Alarm Setpoint Determination ., 8 2.3 10CFR50, Appendix I Compliance-Liquid Effluent Dose..... ..:..... ZZ' 9 2.3.1 Dose Calculations { 9 2.3.2 Cumulation of Doses n 2.3.3 Projection of Doses [ n 2.3.4 Population Dose ' n 3.0 GASEOUS EFFLUENTS ZZZZZZZZZ. 29 3.0.1 Batch Releases ZZZZZZZ.29 3.0.2 Continuous Releases 29 3V1 Monitor Alarm Setpoint Determination , ZZZZZ'.M 3.1.1 Determination of "Mix" (Noble Gas RadionUclide Composition) of Gaseous Effluents 32 3.1.2 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Whole Body Dose Rate Limit 32 3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Skin Dose Rate Limit 33 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent 34 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides 35 3.2 10CFR20 Compliance - Gaseous Effluent Dose Rate 36 3.2.1 Noble Gases 36 3.2.2 Radioiodines, Particulates, and Other Radionuclides i' 36 3.2.3 Dose Rate Calculations 36 3.3 10CFR50, Appendix I Compliance - Gaseous Effluent Dose 63 3:3:1 ;- Noble Gases...: ,....:.:...  ;..*.....** .::..[...::..........: ..........63 3.3.2 Radioiodines, Particulates, and Other Radionuclides 63 3.3.3 Dose Calculations ZZZZZZ.'.64 3.3.4 Cumulation of Doses 65 3.3.5 Projection of Doses .........66 3.4 Population Dose 66 4.0 TOTAL DOSE> ZZZZZZZZZZZZZZZZZZZ.'. 67 4.1 40CFR190 and 10CFR72.104 Compliance - Uranium Fuel Cycle Dose ZZZZZZZZZ - 67 4.2 Direct Radiation Dose from PNPP (including the ISFSI) 68 4.3 Dose to Members of the Public While Onsite 68 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ZZZZZZZ.'.'.7O 5.1 , Monitoring Program 70 5.2 Land Use Census Program ZZ.70 5.3 Inter-Laboratory Comparison Program 71 Appendix A ZZZZZZZZZZZ. 76 Appendix B ' 82 Appendix C ' ZZZZZZZZZZZ.85 Records ,. 159 Commitments ' 159 REFERENCES ' 160

ODCM Page: iii Rev.: 23 List of Tables Table 2.3-1 Organs Used for Liquid Effluent Dose Calculations f 12 2'3-2 Age Groups Used for Liquid Effluent Dose Calculations .

2.3-3 Liquid Effluent Dose Pathways ': . . 12 2.3-4 Bio-Accumulation Factors (BiP) (pCi/kg per pCi/liter) '

2.3-5 Ingestion Dose Factors for Adult (mrem/pCi ingested) ' . '

2.3-6 ingestion Dose Factors for Teenager (mrem/pCi ingested) 16 2.3-7 Ingestion Dose Factors for Child (mrem/pCi ingested)

• 1° 2.3-8 Ingestion Dose Factors for Infant (mrem/pCi ingested) ' 20 2.3-9 External Dose Factors for Standing oh Contaminated Ground 22 2 3-10 Liquid Effluent Dilution Factors (Mp) 24 2.3-11 Transit Times Required for Nuclides to Reach the Point of Exposure (tp) 24 2.3-12 Usage Factors (Uap) 'mn oc 2 3-13 Dilution Factors for Each of the Potable Water Intakes within 50 Miles of PNPP 2b 2.3-14 Dilution Factors for the Fish Ingestion Pathway Individual Grid Locations 27 2.3-15 Dilution Factors for the Shore Exposure Pathway 28 3.1-1 Whole Body and Skin Dose Factors ?3 3.1-2 Flow Rates and Effluent Monitor Efficiencies 3*

3^2-1 Organs Used for Gaseous Effluent Dose Calculations 41 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations 41 3.2-3 Gaseous Effluent Dose Pathways *\

3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 42 3.2-5 External Dose Factors for Standing on Contaminated Ground 43 3.2-6 Inhalation Dose Factors for Adult (mrem/pCi inhaled) ^ 45 3.2-7 Inhalation Dose Factors for Teenager (mrem/pCi inhaled) 47 3.2-8 inhalation Dose Factors for Child (mrem/pCi inhaled) 49 3.2-9 Inhalation Dose Factors for Infant (mrem/pCi inhaled) 51 3.2-10 Ingestion Dose Factors for Adult (mrem/pCi ingested) 53 3.2-11 Ingestion Dose Factors for Teenager (mrem/pCi ingested) 55 3.2-12 Ingestion Dose Factors for Child (mrem/pCi ingested) 57 3.2-13 Ingestion Dose Factors for Infant (mrem/pCi ingested) 59 3.2-14 Annual Usage Factors for the Maximum Exposed Individual 61 3.2-15 Annual Usage Factors for the Average Individual 61 3.3-1 Gamma and Beta Air Dose Factors for Semi-Infinite Plume 65 5.1-1 ODCM REMP Sample Locations 'J-A-1 Atmospheric Depletion and Deposition Factors 78 A-2 Site Boundary Atmospheric Dispersion (%IQ) and Deposition Parameters (D/Q) for PNPP Unit 1 £9 A-3 Atmospheric Dispersion (x/Q) as a Function of Distance (s/m3) 80 A-4 Atmospheric Dispersion (D/Q) as a Function of Distance (nr2) 81

ODCM Page: iv Rev.: 23 List of Figures Title Liquid Radioactive Waste (LRW) Discharge System 2 Gaseous Effluent System Flow Diagram .. 30 PNPP Site Boundary and Unrestricted Area V 62 Technical Specification Required REMP Sampling Locations Within Two Miles of the Plant Site 73 5.1-2 Technical Specification Required REMP Sampling Locations.

Between Two and Eight Miles from the Plant Site 74 5.1-3 Technical Specification Required REMP Sampling Locations Greater Than Eight Miles from the Plant Site 75

ODCM Page: v Rev.: 23 SCOPE OF REVISION:

Rev. 23 1. Updated Tables A-2, A-3, and A-4 with new calculated x/Q and D/Q values.

<CA-2019-06256-001 > ' '

2.' Deleted data in Table A-3 and A-4 at distances not used in MIDAS or the USAR.

3. Reworded Section 4.1 to comply with the requirements of 40CFR190 for Total Dose.

<CA-2019-06219-001 >

4. Updated old references to 10CFR20:405c to 10CFR20.2203 in section AA.

<ATL-2018-2202-ATA-02>

5. Removed reference to G50-K805A/B and G50-K926/7 from Section 2.1.1.3. Indication was removed as part of the digital upgrade per ECP-05-0147-003.

<CR-2019-06255-ATA-01 >

ODCM Page: 1 Rev.: 23

1.0 INTRODUCTION

This Offsite Dose Calculation Manual (ODCM) contains information and methodologies to be used by the Perry Nuclear Power Plant (PNPP), Unit 1, to ensure compliance with PNPP Radiological Effluent Technical Specifications. The Technical Specifications and this ODCM are written to satisfy 10CFR20, 10CFR50.36 and Appendix I, 40CFR190 and 10CFR72.104 requirements. This ODCM applies to doses from radioactivity and radiation from the Perry Nuclear Power Plant, which is considered to include the onsite Independent Spent Fuel Storage Installation (ISFSI).

Sections 2 and 3 of this manual deal with liquid and gaseous radiological effluents, respectively.

Each of these sections contain alarm setpoint determination, radiation dose and dose rate calculation methodologies, as well as limits and requirements. Section 4 covers uranium fuel cycle related radiation dose limits including direct dose from the Perry Nuclear Power Plant includinq the ISFSI.

Also included in this manual, in Section 5, is information relating to the Radiological Environmental Monitoring Program (REMP). The figures and tables contained therein designate specific sample types and locations currently used to satisfy the Technical Specification requirements for the REMP as well as sampling reporting and detection capability limits. The sample types and locations are subject to change based on factors including the results of the annual Land Use Census.

The ODCM has been prepared, as generally as possible, in order to minimize future revisions.

However, any such changes will be reviewed and approved as per the Administrative Control Section of the PNPP Technical Specifications.

Supplemental information needed to support calculations is contained in the appendices at the end of this manual. Appendix A contains atmospheric dispersion and deposition parameters and Appendix B presents the methodology for determining the lower limit of detection (LLD).

Appendix C of the ODCM was prepared based on guidance of NUREG-1302, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors,"

Generic Letter 89-01, Supplement No. 1. This appendix along with plant procedures will be used by plant personnel to demonstrate compliance with Specification 5.5.4 (Radioactive Effluent Controls Program) of the PNPP Technical Specifications.

ODCM Page: 2

Rev.

23 2.0 LIQUID EFFLUENTS .

2.1 Batch Releases A batch release is the discharge liquid radioactive waste of a discrete volume. Batch releases from the liquid radwaste system "may occur from any of the following tanks: waste sample tank, floor drain sample tank, chemical waste distillate tank, and detergent drain tank (see Figure 2.1-1). The maximum release rate possible, due to pump capacity, is 200 gallons per minute from all release tanks except the detergent drain tanks, which have a maximum release rate of 50 gallons per minute: All of the above liquid radwaste releases go to the Emergency Service Water discharge which is then released through the discharge tunnel after miking with Service Water effluent and/or and blowdown from Circulating Water system, if present.

Figure 2.1-1 '" ' [ '  :

Liquid Radioactive Waste (LRWV Discharge System

ODCM Page: 3 Rev.: 23 The-type and frequency of sampling and analysis required by.the ODCM is given in Appendix C, Table 4.11.1.1.1-1. Prior to sampling for analysis, each batch should be isolated, and thoroughly mixed to assure representative sampling. For mixing, the contents of the tank are recirculated by isolating the tank and turning on equipment that takes suction from and discharges back into the tank. Recycle lines are provided with one or more mixing eductors located near the bottom of the tanks to promote better mixing as well as reducing recirculation time. This ensures that the water in the tank will be mixed and will be representative of the activity in the tank. The minimum recirculation performed is the equivalent of two volumes of the tank contents.

Monitor alarm setpoints will be determined in order to ensure compliance with 10CFR20. The radioactive content of each batch release will be determined prior to release in accordance with ODCM, Appendix C, Table 4.11.1.1.1-1. Concentrations for tritium and other non-gamma emitting isotopes will be those most recently determined in the previous month/quarter. If there are no tritium results from the most recent month the most recent steam cycle value may be used as this will be a conservative number used for calculating batch releases. If there is sufficient time prior to a planned release, a composite of samples that are expected to be representative of the release may be analyzed for thetritium and other non-gamma emitting isotope values.

2.1.1 Monitor Alarm Setpoint Determination The following methodology is used to calculate the setpoints for the Radwaste Discharge Radiation Monitor - ESW Discharge and Liquid Radwaste Adjustable High Flow Trip Unit to ensure that liquid radwaste effluent releases from the site to unrestricted areas are below the limiting effluent concentrations (EC) specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases. An EC of 2.0E-4 uCi/ml has been established for dissolved and entrained noble gases. The Radwaste Discharge Radiation Monitor - ESW Discharge provides alarm and automatic termination of releases prior to exceeding these limits.

NOTE: Liquid radwaste discharge flow rate shall be verified at least once per four hours, whenever the flow rate measuring device(s) is inoperable during actual releases. v 2.1.1.1 Minimum Acceptable Dilution Factor Determination:

Where ;>.

DF0 - the minimum acceptable dilution factor determined from analysis of the liquid effluent to be released; d = the concentration of radionuclide "i" in the batch to be released, uCi/ml. If the concentration of a radionuclide is below the lower limit of detection, the radionuclide shall not be included as a source term in the setpoint calculation.

Ed = the effluent concentration of radionuclide T, from 10CFR20, Appendix B,

, Table 2, Column 2, in uCi/ml. (2.0E-4 uCi/ml for noble gases).

DF = lODFo (2.1-2)

Where: J DF = the conservative dilution factor used by PNPP to calculate the maximum release rate prior to release in order to ensure compliance with 10CFR20; dfo = the minimum acceptable dilution factor, as per equation 2.1-1; 10 = a factor of ten less than 10CFR20, Appendix B, Table 2, Column 2, limits; which represents an order of magnitude of conservatism for liquid radwaste releases from PNPP.

ODCM Page: 4 Rev.: 23 2.1.1.2 Maximum Allowable Radwaste Tank Discharge Flow Rate (0.64)MDF (2.1-3)

max DF Where:

' Fmax = the maximum allowable radwaste tank discharge flow rate for the batch to be released, gpm; DF = the conservative dilution factor, per equation 2,1-2; MDF = the minimum dilution flow - supplied by the Service Water system, Emergency Service yVater system, or Circulating Water system blowdown, gpm; 0.64 .= an engineering factor to prevent spurious alarms 2.1.1.3 ' Liquid Radwaste Discharge Flow Monitor Alarm Setpoint <L00434>

Monitor alarm setpoirits are determined to ensure that the concentration of radionudides in the liquid radwaste effluent released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table 2, Column 2, for radionudides other than dissolved and entrained noble gases. A limiting effluent concentration of 2.0E-4 uCi/ml has been established for dissolved and entrained noble gases in liquid effluents.

(2.1-4)

SPf= 1.25 (Fact)

Where:

10/2019 SPf = liquid radwaste adjustable high flow trip unit alarm setpoint, gpm; Fact = actual allowable radwaste tank discharge flow rate for the batch to be released, not to exceed the maximum allowable radwaste discharge flow rate Fmax as defined in equation 2.1-3, gpm; 1.25 = an engineering safety factor to prevent spurious alarms The liquid radwaste tank discharge flow should be maintained at or below this Fact value by proper regulation of the high or low volume discharge throttle valves. (G50-F153 or G50-F155, respectively). . ..

2.1.1.4 Liquid Radwaste Discharge Radiation^ Monitor AlarmfiYip Setpoint Monitor alarm/trip setpoints are determined to ensure that the concentration of radionudides in the liquid radwaste effluent released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table 2, Column 2 for radionudides other than dissolved or entrained noble gases. A limiting effluent concentration of 2.0E-4 uCi/ml has been established for dissolved and entrained noble gases in liquid effluents.

(2.1-5)

CRc = I(Ci) (Ei)

Where:

CRc the calculated monitor count rate above background, cpm; the concentration of radionuclide "i" in the batch to be released, uCi/ml; Ei the detector efficiency of the monitor for radionuclide "i", cpm/uCi/ml.

OR

ODCM Page: 5 Rev.: 23 CRx (Rs) (Fx) (ZCi) (2.1-6)

Where:

CRX the cross-calibrated monitor count rate above background, cpm; Fx the cross-calibration factor is used to ratio the liquid radwaste discharge radiation monitor actual response to the Cs-137 calibrated response; Rs the response of the Liquid Radwaste Discharge Radiation Monitor to a Cs-137 calibrated standard, cpm/(nCi/ml).

/Fmax"1 SPr 1.25 + B (2.1-7)

VFact Where:

SPr the Radwaste Discharge Radiation Monitor - ESW Discharge alarm/trip setpoint, in cpm; -

BG background count rate due to internal contamination and radiation levels in the area of the monitor, cpm; CRn monitor net count rate, either CRc or CRX, per equation 2.1-5 or 2.1-6, cpm; 1.25 an engineering factor to prevent spurious alarms; r max/Fact an adjustment factor (to account for the difference between an actual radwaste discharge flow rate to be used for the discharge and maximum allowable radwaste discharge flow rate) to allow operational flexibility and to minimize spurious alarms; Where:

Fact actual radwaste discharge flow rate, this value must always be less than or equal to Fmax, gpm; ,

maximum allowable radwaste discharge flow rate, per equation 2.1-3, gpm.

2.1.2 10CFR20 Compliance-Liquid Effluent Concentration In order to show compliance with 10CFR20, the concentrations of radionuclides in liquid effluents will be determined and compared with the limiting effluent concentrations as defined in 10CFR20, Appendix B, Table 2, Column 2, (2.0E-4 uCi/ml for dissolved and entrained noble gases). Concentrations of radioactivity in effluents prior to dilution will be determined.

Concentration in diluted effluent will be calculated using these results prior to each batch release, and following each batch release.

2.1.2,1 Concentration of Radionuclides in Prerelease ,

The radioactivity content of each batch release will be determined prior to release. PNPP will show compliance with 10CFR20 in the following manner:

The concentration of the various radionuclides in batch releases prior to dilution is divided by the minimum dilution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:

ODCM Page: 6 Rev.: 23 (2.1-8)

MDF

' \ -t'

• Where: '

C0HCi = the concentration of radionuclide "i" at the unrestricted area, liCi/ml; C- = the concentration of radionuclide T in the batch to be released, uCi/ml; f = the radwaste tank discharge flow rate for the batch to be released, gpm; MDF = the minimum dilution flow, per equation 2.1-3, gpm.

The projected radionuclide concentrations in the unrestricted area are compared to the limiting effluent concentrations in 10CFR20, Appendix B, Table 2, Column 2 (2.0E-4 uCi/ml for dissolved and entrained noble gases) in order to give a final 10CFR20 compliance check, i.e.; the following equation must be met:

Conci ^ (2 1-9)

^ EC, ~ *-.

• Where: - , , -

- - the concentration ofradionuclide "i" at the unrestricted area, uCi/ml; ECi = the limiting effluent concentration of radionuclide "i", from 10CFR20, Appendix B, Table 2, Column 2 (2.0E-4 npi/ml for dissolved and entrained noble gases), liCi/ml.  ;

2.1 2.2 Post Release The actual radioactivity content of each batch release will be determined following release to show final compliance with 10CFR2p. , . ,

The concentration of the various radionuclides in batch releases prior to dilution is divided by the actual dilution to obtain the concentration 7at the unrestricted area. This calculation is shown in the following equation:

.., ., (2.1-10)

Where: ]<  ; ';';

CoriCi = the actual concentration of radionuclide T at the unrestricted area for the release, jiCi/ml;

,',.. .' C( ,; = the concentration of radionuclide,"i" in the batch released, uCi/ml;...,

VdU = the actual volume of dilution wafer during the release (total plant discharge flow, including Service WatefrEmergency Service Water, and cooling tower blowdown), in gallons;

ODCM Page: 7 Rev.: 23

'irt = the actual volume of the liquid radwaste tank discharged for the batch, gal.

The concentrations in the unrestricted area are compared to the limiting effluent concentrations in 10CFR20, Appendix B, Table 2, Column 2 (2.0E-4 uCi/ml for dissolved and entrained noble gases). In order to demonstrate final compliance with 10CFR20, the following equation must be met:

(2.1-11)

Where: .

Lonei = concentration of radionuclide "i" at the unrestricted area,

= limiting effluent concentration of radionuclide T, from 10CFR20, Appendix B, Table 2, Column 2, uCi/ml.

2.2 Continuous Releases A continuous release is the discharge of fluid wastes of a non-discrete volume, i.e., from a volume or system that has an input flow during the continuous release. Potential sources for a continuous release at Perry are RHR heat exchanger leakage into the Emergency Service Water system, tritium activity in the M35 Supply Plenum drain into storm drains, and Alternate Decay Heat Removal (ADHR) heat exchanger leakage into Service Water.

Potentially contaminated discharges from the ESW are monitored by an installed radiation monitoring system. This system consists of two channels, one for monitoring downstream of equipment in Emergency Service Water System Loop A and the other for Emergency Service Water Loop B. If radiation is detected, the affected Emergency Service Water line can be manually isolated. The decision of whether to isolate or not is dependent upon other conditions. The PNPP staff will take appropriate action to limit release.

The Emergency Service Water discharged will be sampled and analyzed in accordance with ODCM Appendix C, Table 4.11.1.1.1-1. To show compliance with 10CFR20, the sum of the concentrations of radionuclide "i" in unrestricted areas due to both continuous and batch releases divided by that isotope's limiting effluent concentration must be less than 1.

During the summer months, the Turbine Building Supply Plenums (1M35B0001A, B, C) are used as a cooling source; condensation from the cooling coils is collected in the M35 plenum drain pans.

Moisture from the outside air is condensed and flows into the drain pan. The potential exists for the outside air to contain tritium from the plant vents, thus the M35 Turbine Building Supply Plenums could also contain tritium. During the summer months, the M35 drains are routed to storm drains due to the large quantity of condensation. Grab samples are obtained in accordance with ODCM Appendix C Table 4.11.1.1.1-1.

The ADHR system has an installed radiation monitor on the Service Water line that provides cooling to the AHDR heat exchanger. The Service Water (ADHR) system will be sampled and analyzed in accordance with ODCM Appendix C, Table 4.11.1.1.1-1. If radiation is detected, the

" ADHR system can be isolated. The decision of whether to isolate or not is dependent upon other

<v; conditions. The PNPP staff will take appropriate action to limit release.

ODCM Page: 8 Rev.: 23 2.2.1 Monitor Alarm Setpoint Determination The following methodology is used to calculate the alarm setpoints for the Emergency Service Water loops A & B and Service Water (ADHR) Radiation Monitors. This

• methodology ensures an alarm will be received prior to exceeding the limiting effluent concentration listed in 10CFR20, Appendix B, Table 2, Column 2.

2.2.1.1 Alarm Setpoint ^

CRc = (BG + MR) (0.75)

Where:

. -\ . CRc = the calculated monitor count rate in cpm;

? BG =

• the background count rate due to internal contamination and radiation levels in the area of the monitor in cpm; MR = expected monitor response due to 1.0 EC of a typical reactor water isotopic mix; -

0.75 engineering safety factor (

.2.2.1.2 Minimum Allowable Backgrounds BGmin = CRc-MR Where: v BGmin = minimum allowable background to ensure monitor will alarm prior to

.*_ . exceeding 1.0 EC; ,

CRc = the calculated monitor count rate in cpm; MR = expected monitor response due to 1.0 EC of a typical reactor water isotopic mix; NOTE: If calculated value is negative, then 0 cpm will be used as the minimum allowable background.

2.2.1.3. Expected Monitor Response Based on the Reactor Water Source Term MR = I (EG x % x Effi)

Where: .

MR = expected monitor response due to 1.0 EC of a typical reactor

'* ' * ' .-*"./..*.- water isotopic mix; o/b. -  ; percent of isotope (i) in a typical reactor water isotopic mixture; t Effi = radiation rfibnitor detector efficiency for isotope (i);

ECi = Effluent concentration value for isotope (i), Appendix B,

' Table 2, Column 2,10CFR20. _ J 2.2.1.4. Minimum Allowable Setpoint Based on Monitor Background

ODCM Page: 9 Rev.: 23 Where:

CRmin = Minimum allowable setpoint for a given monitor background (BG);

BG . . = the background count rate due to internal contamination and radiation levels in the area of the monitor in cpm; 2 = 95% confidence level; 2TC = two times the instrument time'-constant where TC _ (LogiQBG - Log10Locpm)(TChicpm - TClocpm j, It u ' ^ ' lOCpm Time Constants:

Hi/Lo cpm TC Hi/Lo cpm 10 cpm 1.25 min 100 com 1.25 min 1,000 cpm 1.25 min 10.000 CDm , 0.2 min 100.000 cpm 0.042 min 1,000,000 cpm 0.0033 min For Backgrounds less than 400 cpm, the following values will be used:  ;

Locpm = 100cpm TClocpm = 1.25 min .

Hicpm = 1000 cpm TCHlcpm = 1.25 min For Backgrounds > 400 cpm and less than 1,000 cpm, the following values will be used:

Locpm = 1,000 cpm TClocpm = 1.25 min Hicpm = 10,000 cpm TCHjcpm = °-2 min 2.3 10CFR50. Appendix I Compliance - Liquid Effluent Dose '

Doses resulting from liquid effluents will be calculated at least monthly to show compliance with 10CFR50, Appendix I. A cumulative summation of whole body and organ doses for the current quarter and year will be maintained. Additionally, doses due to liquid releases are projected monthly. y 2.3.1 Dose Calculations Radiation doses due to liquid radioactive effluents from PNPP are calculated based on three main.dose pathways: potable water, aquatic foods (namely fresh water fish ingestion), and exposure to shoreline deposits., Irrigated food pathways, as discussed in Regulatory Guide 1.109, will not be of concern atPNPP as little or no water from Lake Erie is used for irrigation in the nearby Ohio counties of Lake, Ashtabula, Cuyahoga and Lorain. Nursery businesses and other agricultural activities that require supplemental water generally rely on water drawn from small ponds and streams. . . .

Radiation dose to members of the public for liquid radioactive releases from PNPP will be calculated for the potable water, aquatic food, and shoreline deposit pathways using the following equations:

ODCM Page: 10 Rev.: 23 Potable Water f 1100. Uap Z (Qi) (Daipj) exp (-^i tp) \ . . ...;\. , . -,(2.3-1)

, .;_ (MP)(F) . . _ . . . " ......

Aquatic Foods RaiD =1100 Uap Z (Qi) (Bip) (Daipj) exp (-Xi tp) (2.3-2) ajP (M)(F)

(MP)(F)

Shoreline Deposits Z (Qi) (Ti) (Daipj) [exp(- ^itp)].[l - exP;(- ^tb)] (2.3-3)

(Mp) (F)

Where:

= the dose to individuals of age group "a" to organ "j" from all the radionuclides in Rajp pathway "p", in mrem; B. = the equilibrium bioaccumulation factor for radionuclide Y in pathway "p", expressed

' as the ratio of the concentration in biota (pOi/kg) to the radionuclide concentration in water (pCi/l), from Table 2.3-4, I/kg; v '

• the dose factor, specific to a given age group "a", radionuclide Y; pathway up", and Jaip]

organ uj", which can be used to calculate the radiation dose from an intake of a

, radionuclide (mrem/pCi); or from exposure to a given concentration of a radio nuclide in sediment, expressed as a ratio of the dose rate (mrem/h), and the areal radionuclide concentration, (pCi/m2), from Tables 2.3-5 through 2.3-9; F' = the flow rate of the liquid effluent, ft3/s'ec;

, NOTE: The normal minimum dilution flow will be 30,000 gpm (USAR.11.2.3.2). y./V M = the dilution factor at the midpoint of exposure (or the point of withdrawal of drinking water, point of harvest of aquatic food or shoreline), from Table 2.3-10, dimehsionless;  ; .  ;

Qi = the release of radionuclide "i",Ci;

^ = the period of time for which the sedimentor soil is exposed to the contaminated U water, 1.75 x105hf (20 yrs);

Ti = the half-life of radionuclide Y, days; t = the average transit time required for radionuclides to reach the point of exposure, from Table 2.3-11; for internal dose, tp is the total time elapsed between release of the radionuclides and the ingestion of fdod or water, hr;

• u = the usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway "p", from Table 2.3-12, hr/yr, 1/yr, or kg/yr; W .= the shoreline width factor, 0.3 (from Regulatory Guide 1.109);

x = radioactive decay constant of radionuclide ui", h1; 1100 \= a factor to convert from (Ci/yr)/(ft3/s) to pCi/l; 110,000 = a factor to convert from (Ci/yr)/(ft3/s) to pCi/l and to account for the proportionality constant used in the sediment radioactivity model.

ODCM Page: 11 Rev.: 23 2.3.2 Cumulation of Doses The dose contribution from liquid effluents will be calculated at least monthly. Calculations will be performed to determine the maximum whole body as well as the maximum organ dose to an individual. These dose calculations will be summed for comparison with quarterly and annual limits. These results will be summed with the doses cumulated from the other months in the quarter of interest and in the year of interest. To assure compliance with the dose limits of 10CFR50, Appendix I the following relationships shall hold:

for the quarter:

Dose < 1.5 mrem whole body; Dose < 5 mrem any organ; for the year:

Dose < 3 mrem whole body; Dose < 10 mrem any organ.

The quarterly limits given above represent one-half of the annual design objective. If these quarterly or annual limits are exceeded, a special report will be submitted to the NRC, in accordance with ODCM Appendix C controls, stating the reason and corrective action to be taken.

2.3.3 Projection of Doses Anticipated doses resulting from the release of liquid effluents will be projected monthly. The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month.

If the projected dose, when averaged over 31 days, exceeds 0.06 mrem to the whole body or 0.2 mrem to any organ, the liquid radwaste system will be used to process waste. The values for the projected dose impact levels correspond to approximately one forty-eighth of the 10CFR50, Appendix I design objective. If continued at this rate for one year, the projected impact would correspond to less than one-fourth of the 10CFR50, Appendix I limit.

The projected doses will be calculated using equations 2.3-1, 2.3-2, and 2.3-3.

In this case, the source term will be adjusted to reflect this information and the justification for the adjustment noted. This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the coming month.

2.3.4 Population Dose PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, wilj include total population dose and average individual doses calculated for radioactive effluent releases. The total population dose and average individual doses will be calculated using average individual transit times and usage factors, Table 2.3-12, (as compared to maximum exposed individual factors used for individual doses). The total population dose <

will be calculated by dose pathway and organ, with pathway doses being corrected for the fraction of the population assumed to be in each age group (adult, teen, child and infant 0.71,0.11, 0.18, 0.0 respectively).

ODCM Page: 12 Rev.: 23 Table 2.3-1 Organs Used for Liquid Effluent Dose Calculations

1. Bone 2 Gl Tract

3. Kidney

4. Liver

5. Lung

6. Thyroid

7. Whole Body

8. Skin Table 2.3-2 Age Groups Used for Liquid Effluent Dose Calculations

1. Adult (17 yrs. and older)

2. Teen (11-17 yrs)

3. Child (1 -11 yrs)

4. Infant (0 -1 yr)

Table 2.3-3 Liquid Effluent Dose Pathways

1. Water Ingestion

2. Shore Exposure

3. Fresh Water Fish Ingestion

ODCM Page: 13 Rev.: 23 Table 2.3-4 Bio-Accumulation Factors (BjD) (pCi/kq per pCi/liter)

Element Fish H 9.0E-01 C 4.6E+03 Na ., 1.0E+02 P 1.0E+05 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 Rb 2.0E+03 Sr 3.0E+0i Y 2.5E+01 Zr 3.3E+00 Nb 3.0E+04 Mo 1.0E+01 Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 Sb 1.0E+00 Te 4.0E+02 I . 1.5E+01 Cs 2.0E+03 Ba , 4.0E+00 La 2.5E+01 Ce . 1..0E+00 Pr 2.5E+01 Nd 2.5E+01 Ta 1.0E+00 W 1.2E+03 Re ( 1.0E+00 Au  ; 1.0E+00 Np . < 1.0E+01

ODCM Page: 14 Rev.: 23 Table 2.3-5 Inaestion Dose Factors for Adult (mrem/pCi ingested)

WHOLE BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE BONE LIVER 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 H-3 0.00E+00 1.05E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 C-14 2.84E-06 5.68E-07 1.70E-06 ' 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 Na-24 1.70E-06 7.46E-061 0.00E+00 O.OOE+00 O.OOE+00' 2.17E-05 P-32 1.93E-04 1.20E-05 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Cr-51 O.OOE+00 0.00E+00 8.72E-07 0.00E+00 1.36E-06 O.OOE+00 1.40E-05 Mn-54 0.00E+00' 4.57E-06 1.15E-07 2.04E-08 0.00E+00 1.46E-07 O.OOE+00 3.67E-06 Mn-56 O.OOE+00 O.OOE+00 1.06E-06 1.09E-06, Fe^55 2.75E-06 1.90E-06 -* 4.43E-07 0.00E+00 3.91 E-06 " 0.00E+00 O.OOE+00 2.85E-06 3.40E-05 Fe-59 4.34E-06 1.02E-05 1.67 E-06 0.00E+00 O.OOE+00 O.OOE+00 1.51E-05 Co-58 0.00E+00 7.45E-07 4.72E-06 0.00E+00 O.OOE+00 O.OOE+00 : 4.02E-05 Co-60 O.OOE+00 2.14E-06 4.36E-06 0.00E+00 O.OOE+00 O.OOE+00 : 1.88E-06 Ni-63 1.30E-04 9.01 E-06 3.13E-08 O.OOE+00 O.OOE+00 O.OOE+00

• 1.74E-06 Ni-65 5.28E-07 6.86E-08 3.91 E-08 0.00E+00 ' 2.10E-07 O.OOE+00 7.10E-06 Cu-64 0.00E+00 8.33E-08 0.00E+00 2.24E-07 2.62E-07 2.27E-07 1.07E-05 Cu-67 2.95E-07 8.41 E-07 6.96E-06 O.OOE+00 1.03E-05 O.OOE+00 9.70E-06 Zn-65 4.84E-06 1.54E-05 1.03E-08 1.97E-08 1.37E O.OOE+00 1.28E-08 O.OOE+00 2.96E-09 Zn-69 4.02E-08 O.OOE+00 O.OOE+00 O.OOE+00 5.79E-08 Br-83 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 4.09E-13 Br-84 0.00E+00: 0.00E+00 5.21 E-08 O.OOE+00 2.14E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 0.00E+00 0.00E+00 9.83E-06 O.OOE+00 O.OOE+00 O.OOE+00 4.16E-06 Rb-86 0.00E+00 2.11E-05 3.21 E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.36E-19 Rb-88 O.OOE+00 6.05E-08 2.82E-08 O.OOE+00 O.OOE+00 O.OOE+00 2.33E-21 Rb-89 0.00E+00 4.01 E-08 0.00E+00 2.96E-09 2.58E-08 6.92E-09 2.15E-07 Sr-87M 1.52E-08 1.77E-08 0.00E+00 8.84E-06 O.OOE+00 O.OOE+00 O.OOE+00 4.94E-05 Sr-89 3.08E-04 1.86E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.19E-04 Sr-90 7.58E-03 0.00E+00 2.29E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.70E-05 Sr-91 5.67E-06 0.00E+00 9.30E-08 O.OOE+00 O.OOE+00 O.OOE+00 4.26E-05 Sr-92 2.15E-06 0.00E+00 9.62E-09 O.OOE+OO 2.58E-10 O.OOE+OO O.OOE+OO o.obE+ob 1.02E-04 Y-90 O.OOE+00 O.OOE+00 O.OOE+00 2.67E-10 Y-91M 9.09E-11 "* 0.00E+00 3.52E-12 3.77E-09 O.OOE+00 O.OOE+00 O.OOE+00 7.67E-05

. Y-91 1.41E-07 0.00E+00 2.47E-11 O.OOE+00 O.OOE+00 O.OOE+00 1.48E-05 Y-92 8.45E-10' 0.00E+00 7.40E-11 O.OOE+00 O.OOE+00 O.OOE+00 8.50E-05 Y-93 2.68E 0.00E+00 6.60E-09 O.OOE+00 1.53E-08 O.OOE+00 3.09E-05 '

Zr-95 3.04E-08 9.75E-09 1.55E-10 O.OOE+00 5.12E-10 O.OOE+00 1.05E-04 Zr-97 1.68E-09' 3.39E-10 1.86E-09 O.OOE+00 3.42E-09 O.OOE+00 2.10E-05 Nb-95 6.22E-09 3.46E-09 8.20E-07 O.OOE+00 9.76E-06 O.OOE+00 9.99E-06 Mo-99 0.00E+00 4.31 E-06 6.98E-10 8.89E-09 O.OOE+00 1.06E-08 3.42E-10 4.13E-07 '

TC-99M 2.47E-10

ODCM Page: 15 Rev.: 23 Table 2.3-5 (Cont.)

Ingestion Dose Factors for Adult (mrem/pCi ingested)

WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI Tc-101 , 2.54E-10 3.66E.10 3.59E-09 0.00E+00  : 6.59E-09 1.87E-10 1.10E-21 Ru-103  : 1:85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05

,Ru-105 1.54E-08 . 0.00E+00 6.08E-09 0.00E+00 1.99E-07 O.OOE+00 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31 E-06 0.00E+00 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 , 0.00E+00 2.91 E-07 0.00E+00 6.04E-05 Te-125M 2.68E-06 9.17E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 .

,Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08,. 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 O.OOE+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 0.00E+00 2.37E-08 Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 O.OOE+00 7.71 E-05 1-130 7.56E-07 2.23E-06, 8.80E-07 1.89E-04 3.48E-06 O.OOE+00 1.92E-06 1-131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 O.OOE+00 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 0.00E+00 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+00 2.51E-10 ,

1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31 E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 ,* 6.51 E-06, 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 . 1.23E-05 2.11 E-06.

Cs-138 5.52E-08 . 1.09E-07 5.40E-08 0.00E+00 8.01 E-08 7.91 E-09 4.65E-13 Ba-139 9.70E-08 6.91 E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71 E-08 3.56E-11 1.59E-09 0.00E+00 3.31 E-11 2.02E-11 - 2.22E-17 Ba-142 2.13E-08, 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11 , 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce-144

• 4.88E-07 2.04E-07 2.62E-08 0.00E+00, 1.21 E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 - 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 ,' 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 Ta-183 4.77E-11 2.92E-10 2.39E-11 0.00E+00 1.66E-10 0.00E+00 1.76E-04 W-187 1.03E-07^ 8.61 E-08 3.01 E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Re-188 2.42E-07 1.90E-07 5.37E-07 1.26E-05 0.00E+00 0.00E+00 1.56E-05 Au-198 0.00E+00 1.12E-08 1.90E-08 0.00E+00 3.42E-08 0.00E+00 8.67E-06 Au-199 0.00E+00 7.00E-08 5.89E-08 0.00E+00 2.74E-07 , O.OOE+00 1.13E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.00E+00 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E+00 1.38E-06 1.97E-05

ODCM Page: 16 Rev.: 23 Table 2.3-6 ihgestion Dose Factors for Teenager (mrem/pCi ingested)

WHOLE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI /'

ISOTOPE" 0.00E+00 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 H-3 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 C-14 \ 4.06E-06

• 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 Na-24 2.30E-06 1.71E-05 1.07E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.32E-05 P-32 2.76E-04 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Cr-51 0.00E+00 O.OOE+00 5.90E-06 1.17E-06 O.OOE+00 1.76E-06 O.OOE+00 1.21E-05 Mn-54 0.00E+00 1.58E-07 2.81E-08 O.OOE+00 2.00E-07 O.OOE+00 1.04E-05 Mn-56 O.OOE+00 2.68E-06 6.25E-07 O.OOE+00 O.OOE+00 1.70E-06 1.16E-06 Fe-55 3.78E-06 1.37E-05 5.29E-06 O.OOE+00 O.OOE+00 4.32E-06 3.24E-05 Fe-59 5.87E-06

- 9.72E-07 2.24E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.34E-05 Co-58 0.00E+00 2.81 E-06 6.33E-06 O.OOE+00 O.OOE+00 O.OOE+00' 3.66E-05 :

Co-60 O.OOE+00 1.25E-05 6.00E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.99E-06 Ni-63 1.77E-04 9.57E-08 4.36E-08 O.OOE+00 O.OOE+00 O.OOE+00 5.19E-06 Ni-65 7.49E-07 1.07E-06 O.OOE+00 2.74E-07 3.19E-7 2.81 E-07 1.32E-05 Cu-64 3.54E-07 1.15E-07 5.41 E-08 O.OOE+00 2.91 E-07 O.OOE+00 8.92E-06 Cu-67 O.OOE+00 2.00E-05 9.33E-06 O.OOE+00 1.28E-05 O.OOE+00 8.47E-06 Zn-65 5.76E-06 2.80E-08 1.96E-09 O.OOE+00 1.83E-08 O.OOE+00 5.16E-08 Zn-69 , 1.47E-08 O.OOE+00 5.74E-08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 0.00E+00 O.OOE+00 7.22E-08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 3.05E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 0.00E+00 2.98E-05 1.40E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.41 E-06 Rb-86 O.OOE+00 8.52E-08 4.54E-08 O.OOE+00 O.OOE+00 O.OOE+00 7.30E-15 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.43E-17 Rb-89 O.OOE+00 5.50E-08

• 3.89E-08 2.18E-08 O.OOE+00 4.40E-9 3.00E-08 9.91 E-09 2.42E-07 Sr-87M 2.81 E-8 O.OOE+00 1.26E-05 O.OOE+00 O.OOE+00 O.OOE+00 5.24E-05 Sr-89 4.40E-04 O.OOE+00 2.05E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.33E-04 Sr-90 8.30E-03 O.OOE+00 3.21 E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.66E-05 Sr-91 8.07E-06 3.05E-06 O.OOE+00 1.30E-07 O.OOE+00 O.OOE+00 O.OOE+00 7.77E-05 Sr-92 O.OOE+00 369E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-04 -

Y-90 1.37E-08 O.OOE+00 4.93E-12 O.OOE+00 O.OOE+00 O.OOE+00 6.09E-09 Y-91M 1.29E-10 O.OOE+00 O.OOE+00 O.OOE+00 8.24E-05 Y-91 2.01E-07 O.OOE+00 5.39E-09 3.50E-11 O.OOE+00 O.OOE+00 O.OOE+00 3.32E-05 Y-92 1.21 E-09 O.OOE+00 1.05E-10 O.OOE+00 o:ooe+oo O.OOE+00 1.17E-04 Y-93 3.83E-09 O.OOE+00 8.94E-09 O.OOE+00 1.91 E-08 O.OOE+00 3.00E-05 Zr-95 4.12E-08 1.30E-08, 2.37E-09 4.69E-10 2.16E-10 O.OOE+00 7.11E-10 " O.OOE+00 1.27E-04 Zr-97 4.56E-09 2.51 E-09 O.OOE+00 4.42E-09 O.OOE+00 1.95E-05 Nb-95 8.22E-09 1.15E-06 O.OOE+00 1.38E-05 O.OOE+00 1.08E-05 Mo-99 O.OOE+00 6.03E-06 1.20E-08 O.OOE+00 1.38E-08 5.14E-10 6.08E-07 TC-99M 3.32E-10 9.26E-10

ODCM Page: 17 Rev.: 23 Table 2.3-6 (Cont.)

Ingestion Dose Factors for Teenager (mrem/pCi ingested)

WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI Tc-101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 . 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 , 0.00E+00 8.99E-07 0.00E+00 2.13E-05 Ru-105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 O.OOE+QO 1.88E-04 Ag-110M 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 Te-125M s 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41 E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 Te-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 Te-131M . 2.44E-06 1.17E-06 9.76E-07; 1.76E-06 1.22E-05 0.00E+00 9.39E-05 fe-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132. 3.49E-06 2.21 E-06 2.08E-06 > 2.33E-06 2.12E-05 0.00E+00 7.00E-05 1-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 1-131 5.85E-06 8.19E-061 4.40E-06 2.39E-03 1.41E-05 aooE+oo 1.62E-06 1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 1-133 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 1-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 1-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 1.74E-06 Cs-134 - 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 , 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 '

Cs-138. 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E-07 . 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11: 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71 E-08 5.01 E-11 2.24E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E-10 7.95E-11 ' 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71 E-06 1.91E-10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 172E-07 0.00E+00 1.75E-04 Pr-143 1.31 E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31 E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01 E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 Ta-183 6.81 E-11 4.15E-10 3.42E-11 0.00E+00 2.37E-10 0.00E+00 1.86E-04 W-187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Re-188 3.45E-07 2.70E-07 7.66E-07 1.68E-05 0.00E+00 0.00E+00 2.33E-05 Au-198 r^ 0.00E+00 1.60E-08 2.72E-08 0.00E+00 4.88E-08 O.OOE+00 9.84E-06 Au-199 0.00E+00 9.92E-08 8.41 E-08 0.00E+00 3.92E-07 0.00E+00 1.17E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05 Sb-124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0.00E+00 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71 E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05

ODCM Page: 18 Rev.: 23

" Table 2.3-7 Inaestion Dose Factors for Child (mrem/pCi ingested)

WHOLE BObY *** THYROID KIDNEY LUNG  : GI-LLI ISOTOPE BONE ! LIVER 2.03E-07 ' 2.03E-07

• 203E-07 2.03E-07 2.03E-07 H-3 O.OOE+00 2.03E-07 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 C-14 1.21E-05 5.80E-06 5.80E-06 5.80E-06 ' 5.80E-06 5.80E-06 5.80E-06

• Na-24 5.80E-06 8.25E-04 3.86E-05 3.18E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.28E-05 P-32 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Cr-51 O.OOE+00 O.OOE+00 1.07E-05 " 2.85E-06 O.OOE+OO 3.00E-06 O.OOE+OO 8.98E-06 Mn-54 O.OOE+00 Mn-56 O.OOE+00 3.34E-07 7.54E-08 O.OOE+OO 4.04E-07 o.ooE+bd' 4.84E-05 6.10E-06 1.89E-06 O.OOE+OO O.OOE+OO 3.45E-06 1.13E-06 Fe-55 '1.15E-05 -

1.33E-05' O.OOE+OO O.OOE+OO 7.74E-06 2.78E-05 Fe-59 1.65E-05' 2.67E-05 Co-58 O.OOE+00

• 1.80E-06 5.51 E-06 O.OOE+OO O.OOE+OO O.OOE+OO' 1.05E-05 5.29E-06 1.56E-05 O.OOE+OO O.OOE+OO - O.OOE+OO 2.93E-05 <

Co-60 O.OOE+00 2.88E-05 >* 1.83E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-06 Ni 5.38E-04 O.OOE+OO O.OOE+OO 2.56E-05 Ni-65 2.22E-06 ' 2.09E-07 1.22E-07 O.OOE+OO 2.52E-06 O.OOE+OO" 7.83E-07 8.74E-07 7.81 E-07 3.89E-05 Cu-64 9.21E-07

• 2.45E-b7 1.48E-07 O.OOE+OO ; 5.92E-07 O.OOE+OO 1.15E-05 Cu-67 O.OOE+00 3.65E-05 2.27E-05 O.OOE+OO 2.30E-05 O.OOE+OO 6.41 E=06 Zn-65 1.37E-05 4.38E-08 6.33E-08 5.85E-09  ! O.OOE+OO, 3.84E-08 O.OOE+00 '" 3.99E-06 Zn-69 1.71E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83" O.OOE+00 O.OOE+OO O.OOE+00 1.98E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+00 O.OOE+00 9.12E-09 O.OOE+OO O.OOE+OO *> O.OOE+OO O.OOE+OO Br-85 O.OOE+00 6.70E-05 4.12E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.31 E-06 Rb-86 O.OOE+00 1.32E-07 O.OOE+OO O.OOE+OO O.OOE+OO 9.32E-09 Rb-88 O.OOE+00 1.90E-07 O.OOE+00 1.17E-07 1.04E-07 O.OOE+OO O.OOE+OO O.OOE+OO - 1.02E-09 Rb-89 O.OOE+OO 1.34E-08 6.65E-08 ' 2.57E-08 6.66E-07 Sr-87M 5.47E-08' 6.78E-08 1.32E-03 O.OOE+00 3.77E-05:i O.OOE+OO O.OOE+OO O.OOE+OO : 5.11E-05 Sr-89 4.31 E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-04 Sr-90 1.70E-02 O.OOE+00 9.06E-07 O.OOE+OO O.OOE+OO  ; O.OOE+OO 5.30E-05 Sr-91 2.40E-05 O.OOE+00 3.62E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.71E-04 Sr-92 9.03E-06 O.OOE+OO 4.11E-08 O.OOE+OO 1.10E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1 1.17E-04  :

Y-90 1.39E-11 O.OOE+OO O.OOE+OO O.OOE+OO 7.48E-07 Y-91M 3.82E-10 O.OOE+OO 1.61E-08 O.OOE+OO O.OOE+OO O.OOE+OO 8.02E-05' Y-91 6.02E-07 ' O,OOE+OO 1.03E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E-04 Y-92 3.60E-09 O.OOE+OO 3.13E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.70E-04 Y-93 ' 1.14E-08 O.OOE+OO 2.27E-08 ' O.OOE+OO 3.65E-08 O.OOE+OO 2.66E-05 Zr-95 1.16E-07 2.55E-08 5.96E-10 O.OOE+OO 1.45E-09 O.OOE+OO 1.53E-04 Zr-97 6.99E-09 1.01E-09 6.26E-09 O.OOE+OO 8.23E-09 O.OOE+OO 1.62E-05 Nb-95 2.25E-08 8.76E-09  ;

3.29E-06 o.obE+bo 2.8.4E-05 O.OOE+OO 1.10E-05 Mo-99 O.OOE+00 1.33E-05 3.00E-08 O.OOE+OO 2.63E-08 9.19E-10 1.03E-06 Tc-99M 9.23E-10 1.81E-09

ODCM Page: 19 Rev.: 23 Table 2.3-7 (Cont.)

Ingestion Dose Factors for Child (mrem/pCi ingested)

WHOLE ISOTOPE . BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91 E-08 5.92E-10 3.56E-09 ,

Ru-103 7.3.1 E-07 0.00E+00 2.81 E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E-08 : 0.00E+00 2.34E-08 O.OOE+00 5.67E-07 . 0.00E+00 4.21 E-05 Ru-106; 1.17E-05 ' O.OOE+00 1.46E-06 . O.OOE+00 1.58E-05 0.00E+00 1.82E-04 Ag-110M 5.39E-07 3.64E-07 2.91 E-07 0.00E+00 . 6.78E-07 0.00E+00- 4.33E-05 Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 0.00E+00 2.34E-05 Te-127  ; 4.71 E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 . 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E 2.41 E-05 . 0.00E+00 1.01E-04 Te-13,1 8.30E-08 , 2.53E-08' 2.47E-08 6.35E-08 2.51 E-07 O.OOE+00 4.36E-07 Te-132 1.01 E-05 4.47E-06 5.40E-06 6.51 ErO6 4.15E-05 O.OOE+00 4.50E-05 .

1-130 2.92E 5.90E-06 3.04E-06 6.50E 8.82E-06 0.00E+00 2.76E-06 1-131 1.72E-05 1.73ErO5 9.83E-06 5.72E-03 2.84E-05 O.OOE+00 1.54E-Q6 -

1-132 8.00E-07 1.47E-06 6.76E-07 6.82E-0$ 2.25E-06 0.00E+00 1.73E-06 1-133 5.92E-06 - 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 1-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-Q7 1-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 , 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 119E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 ' 6.46E-05 4.18E-05 O.OOE+00 3.44E-05 5.13E-06 2.27E-06 Cs-137; , 3.27E-Q4 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01 E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21 E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31 E-05 7.28E-08 4.85E-06 O.OOE+00 2.37E-08 4.34E-08, 4.21 E-05.

Ba-141 2.00E-07 1.12E-10 6.51 E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 O.OOE+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01 E-08 3.53E-09 1.19E-09 0.00E+00 O.OOE+00 0.00E+00 9.84E-05 La-142 '5.24E-10 1.67E-10 5.23E-11 0.00E+00 0.00E+00 0.00E+00 3.31 E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 O.OOE+00 8.68E-09 0.00E+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11 E-07 0.00E+00 3.61 E-07 0.00E+00 1.70E-04:

Pr-143 3.93E-08 << 1.18E-08 1.95E-09 O.OOE+00 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 O.OOE+00 . 1.24E-08 0.00E+00 3.58E-05 Ta-183 2.04E-10 9.40E-10 1.02E-10 0.00E+00 4.98E-10 0.00E+00 2.07E-04 .

W-187 4.29E-07 2.54E-07 1.14E-07 O.OOE+00 0.00E+00 O.OOE+00 3.57E-05 Re-188. 1.03E-06 6.12E-07  ; 2.29E-06 5.03E-05 0.00E+00 0.00E+00 4.12E-05 Au-198 0.00E+00 3.61 E-08 8.12E-08 0.00E+00 1.02E-07 0.00E+00 1.20E-05 Au-199 0.00E+00 2.25E-07 2.51 E-07 0.00E+00 8.23E-07 0.00E+00 1.27E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 Sb-124 1.11 E-05 1.44E-07 3.89E-06 2.45E-08 0.00E+00 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52 E-08 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71 E-05

ODCM Page: 20 Rev.: 23 Table 2.3-8 Inaestion Dose Factors for Infant (mrem/pCi ingested)

WHOLE KIDNEY LUNG GI-LLI ISOTOPE BONE LIVER '*" BODY THYROID 3.08E-07 3.08E-07 3.08E-07 . 3.08E-07 3.08E-07 H-3 0.00E+00 3.08E-07 5.06E-06 5.06E-06 5.06E-06 ; 5.06E-06 5.06E-06 C-14 -* 2.37E-05 ; 5.06E-06 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 Na-24 1.01 E-05 1.01E-05 1.00E-04 6.59E-05 O.OdE+00 O.OOE+00 0.00E+00 2.30E-05 P-32 < 1.70E-03 1.41E-08 9.20E-09 2.01 E-09 1.79E-08 4.11E-07 Cr-51 0.00E+00 O.OOE+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06. 0.00E+00 7.31 E-06 Mn-54 O.OOE+00 8.18E-07 1.41E-07: 0.00E+00 7.03E-07 O.OOE+00 7.43E-05 Mn-56 0.00E+00 8.98E-06 2.40E-06 0.00E+00 O.OOE+00 4.39E-06 1.14E-06 Fe-55 < 1.39E-05 :

3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 '

Fe-59 3.60E-06 8.98E-06 O.OOE+00 Q.OOE+00 0.00E+00; 8.97E-06 Co-58 O.OOE+00 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Co-60 0.00E+00 1.08E-05 0.00E+00 0.00E+00 O.OOE+00 / 1.95E-06 Ni-63 -: 6.34E-04 3.92E-05 2.20E-05 2.42E-07 0.00E+00 O.OOE+00 O.OOE+00- 4.05E-05 Ni-65 4.70E-06 5.32E-07 0.00E+00 '4.93E-06 4.98E-06 4.87E-06 1.36E-05 Cu-64

• 5.26E-06 1.42E-05 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 Cu-67 O.OOE+00 2.91 E-05 . 0.00E+00 3.06E-05 0.00E+00 5.33E-05 Zn-65 1.84E-05 6.31 E-05 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 Zn-69 9.33E-08 1.68E-07 0.00E+00 3.63E-07 0.00E+00 /O.OOE+00 0.00E+00 0.00E+00 Br-83 O.OOE+00 3.82E-07 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Br-84 O.OpE+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.70E-04 8.40E-05 0.00E+00 O.OOE+00 0.00E+00 4.35E-06 Rb-86 O.OOE+00 2.73E-07 0.00E+00 0.00E+00 O.OOE+00 4.85E-07 Rb-88  ; 0.00E+00 4.98E-07 1.97E-07 O.OOE+00 0.00E+00 O.OOE+00 9.74E-08 Rb-*89 0;00E+00 2.86E-07 1.56E-07' 0.00E+00 4.70E-08 1.37E-07 7.71 E-08 1.49E-06 Sr-87M ' 2.22E-07 0.00E+00 7.20E-05 O.OOE+00 0.00E+00 0.00E+00 5.16E-05 "

Sr-89 2.51 E-03 4.71 E-03 0.00E+00 0.00E+00 0.00E+00 2.31 E-04 Sr-90 1.85E-02 0.00E+00 1.81E-06

• 0.00E+00 O.OOE+00 0.00E+00' 5.92E-05 Sr-91 5.00E-05' O.OOE+00 7.13E-07 O.OOE+00 0.00E+00 0.00E+00 2.07E-04 Sr-92 1.92E-05 0.00E+00 2.33E-09 0.00E+00 0.00E+001 O.OOE+00 1.20E-04 Y-90 8.69E-08 0.00E+00 2.76E-11 " O.OOE+00 O.OOE+00 0.00E+00 2.70E-06 Y-91M 8.10E-10 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 8.10E-05 Y-91 1.13E-06 " 0.00E+00 ^ 3.01 E-08 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y-92 7.65E-09 0.00E+00 J 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 Y-93 2.43E-08 O.OOE+00 3.56E-08 0.00E+00 5.41 E-08 0.00E+00 2.50E-05 Zr-95 2.06E-07 5.02E-08 1.16E-09 0.00E+00 2.56E-09 - O.OOE+00 1.62E-04 Zr-97 '** 1.48E-08 ' 2.54E-09 1.00E-08 0.00E+00 1.24E-08 O.OOE+00 1.46E-05 Nb-95 4.20E-08 1.73E-08 3.40E-05 6.63E-06 0.00E+00 5.08E-05 >; O.OOE+00 1.12E-05 Mo-99 O.OOE+00 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 TC-99M 1.92E-09 3.96E-09

ODCM Page: 21 Rev.: 23 Table 2.3-8 (Cont.)

Ingestion Dose Factors for Infant (mrem/pCi ingested)

WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI.

Tc-101 2.27E-09 2.86E-09 2.83E-08 . 0.00E+00. 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 O.OOE+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-1.05 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41 E-05 ,

Ru-106, 2.41E-05 0.00E+00 3.01E-0.6 O.OOE+00 2.85E-05 O.OOE+00 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81 E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Te-125M , 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11E-05 ,

Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 , 8.14E-07 2.44EtO6 O.OOE+00 2.10E-05 Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 O.OOE+00 5:97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 , 2.27E-05 Te-131M : 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11 E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 , 3.81 E-05 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 1-131 .: 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.OOE+OQ 1.51 E-06.

1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+00 2.73ErO6 1-133 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 O.OOE+00 3.08E-06 1-134 ,.. 8.69E-07 1.78E-06 6.33E-07 4.15E-05, 1.99E-06 O.OOE+00 1.84E-06 1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+00 2.62E-Q6 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 - 1.91 E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 . 5.22E-04 6.11E-04 4.33E-05 O.OOE+00 1.64E-04 6.64E-05 1.91 E-06 Cs-138 4.81 E-07 7.82E-07 3.79E-07 0.00E+00 . 3.90E-07 6.09E-08 1.25E-06 Ba-139 . 8.81 E-07 5.84E-10 2.55E-08 0.00E+00 3.51 E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71 E-07 8.81 E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91 E-10 1.34E-08 O.OOE+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 O.OOEfKX) 8.81 E-11 9.26E-11 7.59E-07 *.

La-140 - 2.11E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 O.OOE+00 9.77E-05 La-142 1.10E-09 4.04E 9.67E-11 O.OOE+00 0.00E+00 O.OOE+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 O.OOE+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 O.OOE+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 O.OOE+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 O.OOE+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.3.8E-11 0.00E+00 3.84E-11 O.OOE+00 4.93E-06 :

Nd-147  : 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 O.OOE+00 3.60E-05, Ta-183 4.33E-10 2.49E-09 2.17E-10 0.00E+00 9.05E-10 O.OOE+00 2.10E-04 W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 O.OOE+00 3.69E-05 Re-188 ' 2.20E-06 1.62E-06 4.86E-06 1.25E-04 0.00E+00 O.OOE+00 472E-05 Au-198 O.OOE+00 9.56E-08 1.73E-07 0.00E+00 1.86E-07 O.OOE+00 1.25E-05 Au-199 0.00E+00 5.91 E-07 5.32E-07 0.00E+00 1.49E-06 O.OOE+00 1.28E-b5 Np-239 1.11E-08 9.93E-10 5.61 E-10 0.00E+00 1.98E-09 O.OOE+00 2.87E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.08E-08 0.00E+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05

ODCM Page: 22 Rev.: 23 Table 2.3-9 External Dose Factors for Standing on Contaminated Ground (mrem/h per pCi/m2)

Element Whole Bodv Skin H-3 ; 0.0 0.0 .

C-14 0.0 0.0.

Na-24 2.50E-08 2.90E-08 P-32. 0.0; o.o Cr-51 . 2.20E-10 2.6QE-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.1,0E-08 1.30E-08 Fe-55 0.0 ..." . 0.0 Fe^59 , 8.00E-09 9.40E-09 Co-58 7.00E-09 8:20E-09 Co-60  ! 1.70E-08 2.00E-08 Ni-63 0.0 0.0 '

Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Cu-67 1.40E-09 2.14E-9 Zn-65 4:00E-O9-- 4.60E-09 Zn-69 0.0 -,:,, 0.Q, \u Br-83 6.40E^11 9.30E-11 Brr84 1.20E-08 1.40E-08 Br-85 o!o 0.0.

Rb-86. 6.30E-10 7.20E-10 Rb-88 .*. 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-87M 4.05E-09 5.36E-09 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.3bE-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3;80E^09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93, 5:70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Mo-95 5.10E-09 6.00Er09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09

ODCM Page: 23 Rev.: 23 Table 2.3-9 (Cont.)

External Dose Factors for Standing on Contaminated Ground (mrem/h per pCi/m2)

Element Whole Bodv Skin Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Je-131 2.20E-09 2.60E-06 te-132 1.70E-09 2.00E-09 Sb-124 2.28E-08 6.93E-08 Sb-125 5.67E-09 7^96E-09 1-130 1.40E-08 1.70E-08 1-131 2.80E-09: 3.40E-09 1-132 1.70E-08 2.00E-08 1-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.9QE-09 9.00E-09 La-:140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.00E+00 0.00E+00 Pr-144 2.00E-10 2.30E-10 Nd-147 / 1.00E-09 1.20E-09 Ta-183 3.76E-09 7.30E-09 W-187 3.10E-09 3.60E-09 Re-188 7.86E-10 1.18E-07 Au-198 5.33E-09 3.36E-08 Au-199 1.13E-9 1.39E-09 Np-239 9.50E-10 1.10E-09

ODCM Page: 24 Rev.: 23 table 2.3-10 Liquid Effluent Dilution Factors (MP)

Maximum Individual Dilution Factors Pathway " Location lJp Potable Water Ingestion 3.9 miles WSWof site 32.2 Fresh Water Fish Ingestion Near Discharge Structure 10.9 Shoreline Exposure 0.7 miles ENE of Site 14.5 Population Dose Dilution Factors*

Pathway Location  %

Potable Water I ngestion Population Weighted Average 314 Fresh Water Fish Ingestion Catch Weighted Average 77.4 Shoreline Exposure , 7.7 miles WSW of site 162

• for total population and average individual dose calculations <

Table 2.3-11

( Transit Times Required for Nudides to Reach the Point of Exposure (to)

Maximum Average Exposed Exposed Individual Individual*

Eventual transit time for water ingestion 12 h 24 h Eventual transit time for fish ingestion 24 h 168 h Eventual transit time for shore exposure Oh Oh

• for total population and average individual dose calculations

ODCM Page: 25 Rev.: 23 Table 2.3-12 Usage Factors (UaP)

Maximum Average Exposed Exposed Individual Individual*

Water ingestion (L/yr) Adult 730 370 Water ingestion (L/yr) Teen 510 260 Water ingestion (L/yr) Child 510 260 Water ingestion (L/yr) Infant 330 -

Fresh water fish ingestion (kg/yr) Adult 21 6.9 .

Fresh water fish ingestion (kg/yr) Teen 16 5.2 Fresh water fish ingestion (kg/yr) Child 6.9 2.2 Fresh water fish ingestion (kg/yr) Infant Shore exposure (h/yr) Adult 12 8.3 Shore exposure (h/yr) Teen 67 47 Shore exposure (h/yr) Child 14 9.5 Shore exposure (h/yr) Infant

• for total population and average individual dose calculations

ODCM Page: 26 Rev.: 23 Table 2.3-13 Dilution Factors for Each of the Potable Water Intakes within 50 Miles of PNPP The total population dilution factor of 314 is population weighted using dilution factors for each of the potable water intakes within 50 miles of PNPP. ' f Weighted Dist. Fraction of Dilution Dilution Population Population Factor Factor Intake (Mi) Dir Ohio American 38,500 2.12E-02 187.7 3.98E+00 Water Serv. Co. 20 ENE 13,500 7.43E-03 238.2 1.77E+00 Conneaut 33 ENE Avon Lake 50 WSW 99,500 5.48E-02 388.5 2.13E+01 1,437,000 7.92E-01 326.7 2.59E+02 Cleveland 35 SW 3,200 1.76E-03 154.2 2.71 E-01 Fairport Harbor 7 WSW Lake County East 3.5 WSW 10,258 5.65E-03 107.4 6.07E-01 Lake County West J5 WSW 85,000 4.68E-02 220.0 1.03E+01 Ohio Water Serv. ^10 WSW 60,000 181.9 6:00E+00 Painesville 7.5 WSW 27,000 1:49E-02 159.3 2.37E+00

. * \

Kent County Water 2.31 E-02 388.5 8.97E+00 Supply 50 NW 1.00E+0 TOTAL DF 3.14E+02 TOTALS Dist, Dir Population = distance, direction, and population values obtained from the 1989 Engineering Report "Lake Erie Potable Water Facilities and Intakes within 50 Miles of PNPP" (Ref. SO-11552 "E").

Fraction of Population = The ratio of the population receiving drinking water from that intake to the total population number for all drinking water intakes located within 50 miles of PNPP. ^

Dilution Factor = Values obtained from the Perry-Environmental Report - Operating License Stage, Table 5.1-10 "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP" and Q&R Page 2.1-2. Lake County West dilution factor per interpolation. Kent County Water Supply dilution factor was estimated. .

The Weighted Dilution Factor = (Fraction of Population) x (Dilution Factor), based on the population for each drinking water intake; the sum of which is to be used as the potable water total population dilution factor for radioactive liquid effluent releases from PNPP.

\ ODCM r Page: 27 Rev.: 23 Table 2.3-14 Dilution Factors for the Fish Inaestion Pathway Individual Grid Locations The total population dilution factor of 77A is catch distance and volume weighted using dilution factors at those locations. Fish harvest is based on Ohio Department of Natural Resources the total angler catch (1987 annual) values for Lake Erie within 50 mile of PNPP.

Grid No. of Fraction Distance Dilution (Frac Fish)x Fish of Fish (mi) Factor (Dil Factor) 617 52823 3.91 E-02 29 92 3.60E+00 618 76004 5.63E-02 36 100 5.63E+00

, 714 102522 7.59E-02 9 52 3.96E+00

,715 10743 7.95E-03 9 52 4.13E-01 716 19817 1.47E-02 11 56 8.21E-01

-717; 73401 5.43E-02 24 83 v 4.51 E+00 718 118676 8.78E-02 33 95 8.34E+00 809 0 0.00E+00 48 115 0.00E+00 810 3953 2.93E-03 39 105 3.07E-01 811 13648 1.01 E-02 30 92 9.29E-01 812 33923 2.51E-02 22 78 1.96E+00 813 182663 1.35E-01 13 61 8.25E+00 814 164369 1.22E-01 4 34 4.14E+00 909 80753 5.98E-02 50 116 6.93E+00 910 43800 3.24E-02 42 110 3.57E+00 911 117430 8.69E-02 33 95 8.26E+00

. 912 256529 1.90E-01 24 83 1.58E+01 TOTAL 1351054 1.00E+00 TOTAL D.F. 7.74E+01 Grid No. and No. of Fish = Total angler catch (1987 annual) for each grid location; per letter from Michael R. Rawson, Fairport Fisheries Research Station, Ohio Department of Natural Resources to Richard Cochnar (6/20/88). Commercial harvest data were not used as they were differentiated by harbor location only, not by geographical grid location. ,

Fraction of Fish = The ratio of the fish caught in that grid to the total number of fish caught in all grids located within 50 miles of PNPP.

Distance = Distance to the center of that grid from PNPP, in miles Dilution Factor = Derived, for the appropriate distance (center of each grid), from annual average dilution factor data (non-adjusted), per Perry Environmental Report - Operating License Stage, Table 5.1-10 "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP."

(Fraction of Fish) x (Dilution Factor) = The weighted dilution factor, based on catch, for each grid; the sum of which is to be used as the fish ingestion total population dilution factor for radioactive liquid effluent .

releases from PNPP.

ODCM Page: 28 Rev.: 23 Table 2.3-15 Dilution Factors for the Shore Exposure Pathway *".."

- MAXIMUM EXPOSED INDIVIDUAL DILUTION FACTOR The point of exposure assumed for this pathway is the shoreline at the PNPP site boundary 0.7 miles down shore from the plant discharge structure. Interpolation of the data presented in the Perry Environmental Report - Operating License Stage, Table 5.1-10, "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP" yields a maximum individual dose dilution factor of 14.5 (dilution factor unadjusted for current frequency). /

TOTAL POPULATION DILUTION FACTOR The total population dilution factor of 162 is that of the Headlands Beach State Park, 7.7 miles WSW of PNPP (interpolated, adjusted WSW dilution factor). This location was selected because of its lake site location and it has, by far, the highest attendance of any park located in vicinity of PNPP (Perry Environmental Report - Operating License State, Table 2.1-2 "Major Camps and Parks within 10 Miles of thePNPP"). *  :

ODCM Page: 29 Rev.: 23 3.0 GASEOUS EFFLUENTS 3.0.1 Batch Releases A batch release is the discontinuous discharge of gaseous radioactive effluents of known radionuclide concentration(s) and flowrate taking place over a finite period of time, usually hours or days. A batch release to the environmentmay occur as a result of an effluent flowpath that bypasses treatment or monitoring. Since radioactive releases approaching 10CFR20 limits are not anticipated, an ODCM Control is not entered for batch releases.

Every reasonable effort will be made to maintain the levels of radioactive material in the gaseous effluents ALARA.

The radioactive gaseous effluent release flowpath is monitored for principal gamma emitters (noble gases, particulates, and halogens) as if the inoperable radioactive effluent monitor requirements of Table 3.3.7.10-1 had been entered. This action ensures the dose to a member of the general public is within the limits of Controls 3.11.2.2 and 3.11.2.3. If radioactivity is detected, the radionuclide concentration(s) is added to the dose calculations for the appropriate radioactive gaseous effluent continuous release point. Administrative instructions are employed to establish minimum monitoring requirements for these batch releases to ensure^compliance with all regulatory requirements. The administrative instructions shall also ensure that the specific activity that will cause a batch release has been reviewed for the requirements of 10 CFR 50.59.

3.0.2 Continuous Releases There are four environmental release points for gaseous effluents used for Unit 1 operation of the Perry Nuclear Power Plant: Turbine Bldg/Heater Bay Vent, Off-Gas Vent, Unit 1 Vent, and Unit 2 Vent (see Figure 3.0-1). The Unit 1 and Unit 2 Vents are located on the top of the Intermediate Building, Elevation 753'9". The Turbine Bldg/Heater Bay Vent is located on the top of the Heater Bay Building, Elevation 722'0". The Off-Gas Vent is located on the top of the Off-Gas Building, Elevation 723'0". Site ground level elevation is 620'0n. Radiological releases from each vent are monitored by a noble gas radiation monitor.

All gaseous effluent releases from PNPP via these vents will be continuous releases, and are considered to be long-term (i.e., greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year) and ground level, Containment/drywell purges and vents will be considered periods of increased radiological release as they are vented through the Unit 1 Vent, concurrent with normal, continuous releases.

ODCM Page: 30 Rev.: 23 Figure 3.0-1 . .

> .'.n>> '.'*.';"",

Gaseous FfBiJBnt System Flow Diagram orros in >> <<

A "

mnm.

UE-n r<<UIK UMUITU

ODCM Page: 31 Rev.: 23 3.1 Monitor Alarm Setpoint Determination The following calculation methods provide a means of determining the High Alarm Setpoint (HSP) and the Alert Setpoint (ASP) to ensure compliance with the regulatory dose rate limit to areas at or beyond the site boundary of 500 mrem/yr for the following noble gas monitors:

1. Unit 1 Vent radiation monitor (1D17K0786)

2. Unit 2 Vent radiation monitor (2D17K0786)

3. Off-Gas Vent radiation monitor (1D17K0836)

4. Turbine Building/Heater Bay Vent radiation monitor (1D17K0856)

The Unit 2 Vent radiation monitor is included for the operation of Unit 1 of the Perry Nuclear Power Plant because the second train of the Unit 1 Annulus Exhaust and the Control Complex and Intermediate Building ventilations are exhausted through the Unit 2 Vent.

The High Alarm Setpoint (HSP) for each release point radiation monitor will be set at 70% of the annual dose rate limit (350 mrem/yr) and the Alert Setpoint (ASP) will be at 10% of the annual dose rate limit (50 mrem/yr). ,

NOTE: These values are set as a small fraction of the total activity that may be released via the monitored pathways to ensure that the site boundary dose rate limits are not exceeded. Any single ASP can be exceeded without exceeding the 500 mrem/yr dose rate limit. , .

a. Upon receipt of a valid alert alarm, a sample from the alarming effluent path will be obtained and analyzed. If two or more effluent monitors exceed the ASP or if any one effluent monitor

/exceeds the HSP, the potential exists that the 500 mrem/yr dose rate limit may be exceeded.

In this case, all four effluent paths will be sampled and analyzed with the appropriate actions initiated to limit gaseous releases to below the annual dose rate limit. '

b. If a single high alarm setpoint continues to be exceeded, verification shall be made at least" once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, via the gaseous effluent radiation monitors, that plant releases are below the ODCM Appendix C 3.11.2.1 dose rate limits. Sampling and analysis shall be performed on the four gaseous effluent release points at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

This procedure determines the monitor alarm setpoints that indicate if the dose rate beyond the site boundary due to noble gas radionuclides in gaseous effluent released from the site exceeds 500 mre'm/year to the whole body, or 3000 mrem/year to the skin.

ODCM Page: 32 y Rev.: 23 3.1.1 Determination of "Mix" (Noble Gas Radionuclide Composition) of Gaseous Effluents y

a. The gaseous source terms that are representative of the "mix" of the gaseous effluent are determined. Gaseous source terms are the concentrations of the noble gas radionuclides in the effluent as determined by analysis of the various sources of gaseous effluents. During the early period of plant operation, before a sufficient operational effluent source term data base has been obtained, source terms will be those generated by the GALE code, Revision 0 for PNPP (FSAR Tables 11.3-9 and 11.3-10).

b. Determination of the fraction of the total radioactivity inthe gaseous effluent for each noble gas radionuclide in the gaseous effluent.

. -. " " .* *... _j S, =  :* * (31-1)

Where:

Si the fraction of the total for radionuclide "in in the effluent;

.:,:,.: -Ai- the activity of radionuclide "i" in the gaseous effluent.

NOTE: If the activity of a noble gas radionuclide is below the lower limit of detection the noble gasradionuclide is not included as a source term in this setpoint calculation.

3.1 \l ^ Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Whole Body Dose Rate Limit 500 (3.1-2)

Qb =

Where:

the maximum acceptable total activity release rate of all noble gas Qb radionuclides in the effluent (for whole body exposure), nCi/s; the whole body dose factor for a semi-infinite cloud of radionuclide "i" (includes 5g/cm2 tissue attenuation) from Table 3.1-1, (mrem/yr)/(^Ci/m3);

Si = the fraction of the total for radionuclide T, as per equation 3.1.1; x/Q = the annual average dispersion factor in s/m3 (see Appendix A);

NOTE: The dispersion parameters (x/Q) used in these calculations are the highest calculated site boundary values for any of the land-based sectors only. At PNPP the site boundary locations in the following sectors are totally over water: N, NNE, NNW, NW, W, WNW.

500 = the whole body dose rate limit, in mrem/yr.

ODCM Page: 33 Rev.: 23 3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Skin Dose Rate Limit 3000.

(3.1-3)

Where:

Qs = the maximum acceptable total activity release rate of all noble gas radionuclides in the effluent (for skin exposure), in jaCi/s; l+/- = the beta skin dose factor for a semi-infinite cloud of radionuclide "i" (includes attenuation by the outer "dead" layer of skin), in (mrem/yr)/(nCi/m3);

Mi = the gamma air dose factor for a uniform semi-infinite cloud of radionuclide T, in (mrad/yr)/(nCi/m3);

s+/- = the fraction of the total for radionuclide T, per equation 3.1.1;

%/Q - the annual average dispersion factor in s/m3 (see Appendix A);

1.11 = the air dose to tissue dose equivalent conversion factor, in mrem/mrad; 3000 = the skin dose rate limit, in mrem/yr.

(l+/- + i . i i m+/-) values are shown in Table 3.1-1. - v-Table 3.1-1 Whole Body and Skin Dose Factors Whole Body Dose Factor (Ki) Skin Dose Factor Radionuclide (Li+1.11 Mi)

(mrem/yr/nCi/m3) (mrem/yr/nCi/m3)

Kr-83m 7.56E-02 2.14E+01, Kr-85m 1.17E+03 2.83E+03 Kr-85 1.61E+01 1.36E+03 Kr-87 , 5-92E+03 1.66E+04 Kr-88  ;. -,. 1.47E+04 , 1.92E+04 Kr-89 1.66E+04 2.93E+04 Xe-131m 9.15E+01 6.49E+02 Xe-133m 2.51 E+02 1.36E+03 Xe-133 2.94E+02 6.97E+02.

Xe-135 1.81E+03 3.99E+03 Xe-135m 3.12E+03 4.44E+03 Xe-137 1.42E+03 1.39E+04 Xe-138 8.83E+03 1.44E+04 Ar-41 8.84E+03 1.30E+04

ODCM Page: 34 Rev.: 23 3.1 A ' Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent 2.12x10 Jj(Qt) I Wt.)

(3.1-4)

Where:

'V = the maximum acceptable total radioactivity concentration of all noble gas radionuclides in the effluent, in nCi/cc; f = the flow rate for the release point from the respective flow rate.recorders, in

' ft3/min; design flow rates, which incorporate a 10% flow rate inaccuracy correction, may be used in lieu of actual flow rates (refer to flow rates in Table 3.1-2). rw-  :

Qt .= the smaller of Qb and Qs, calculated in equations 3.1-2 and 3.1 -3, respectively, >Ci/s; ^

2.12E-03 = the conversion factor to convert (lxCi/s)(ft3/min), (iCi/cc.

Table 3.1-2 Flow Rates and Effluent Monitor Efficiencies

. Flow Rate Effluent Pathway /cfm^

- Uniti Plant Veni . 140,000 -;

Unit 2 Plant Vent ,60,000 Off Gas Vent Pipe 16,700

• 400,000 (summer)

Turbine Building/Heater Bay 220,000 (winter/reduced summer)

ODCM Page: 35 Rev.: 23 3.1,5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides CRC = (0.8)(ct)(Em) (3.1-5)

Where: . . . ,.

crc = the calculated monitor count rate above background attributed to noble gas radionuclides, in cpm;

• ct = the maximum acceptable radioactivity concentration, per equation 3.1-4, liCi/cc;

..'.< Em = tne detector efficiency of the monitor for the "mix" of noble gas radionuclides in the effluent, in cpm/(nCi/cc);

= the total nCi/cc concentration divided into the net monitor count rate taken at the time the sample was taken; during the early period of operation, before a sufficient operational effluent source.term data base has been obtained, the value will be calculated using monitor calibration data; 0.8 = an engineering safety factor, 3.1.5.1 Determination of the Monitor High Alarm Setpoint HSP = (O.7O)(CRC) + BG .,, . , (3.1-6)

Where: . ' .

HSP = the high alarm setpoint (including background), in cpm; BG = the background count rate due to internal contamination and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in cpm; crc = the calculated monitor net count rate, per equation 3.1-5, in cpm; 0.70 = the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways.

3.1.5.2 Determination of the Monitor Alert Setpoint ASP = (0. 1O)(CRC)+ BG (3.1-7)

Where:

ASP = the alert setpoint (including background), in cpm; BG = the background count rate due to internal contamination and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in cpm; crc = the calculated monitor net count rate, per equation 3.1-5, cpm; 0.10 = the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways.

ODCM Page: 36 Rev.: 23 3.2 10CFR20 Compliance - Gaseous Effluent Dose Rate Dose rates resulting from the release of noble gases, radioiodines, tritium, and radionuclides in particulate form must be calculated to show compliance with 10CFR20. The limits of 10CFR20 are conservatively applied for the release period at the controlling location.

3.2.1 Noble Gases . ... (,

The dose rate in unrestricted areas resulting from noble gas effluents is limited, by ODCM Appendix C controls, to 500 mrem/yr to the whole body and 3000 mrem/yr to the skin. Only the external dose pathway will be considered for noble gases. Because all gaseous effluent releases from PNPP are considered ground level, the controlling location for these dose rate limits is the site boundary location (see Figure 3.3-1) with the highest relative dispersion factor (x/Q). (See Appendix A for elaboration on atmospheric dispersion.)

The alarm setpoint determinations discussed in the previous section should ensure compliance with these dose rate limits. However, if any one high alarm or two or more alert alarms occur, the dose rates in unrestricted areas resulting from the release of noble gas radionuclides from all vents will be calculated. The calculations will be based on the results of analyses obtained pursuant to the ODCM, Appendix C, CONTROLS.

3.2.2 Radioiodines, Particulates, and Other Radionuclides The dose rate in unrestricted areas resulting from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days is limited, by ODCM Appendix C controls, to 1500 mrem/yr to any organ. The calculation of dose rate from these radionuclides will be performed based on results of analyses obtained pursuant to those Appendix C controls. The controlling location for this limit is the location of the highest relative deposition (D/Q) for the period of release as well as the actual receptor pathway. The receptor pathway locations will be reviewed once per year following the performance of the Land Use Census to include consideration of nearest residences, garden, and farm animal locations in each sector.

3.2.3 Dose Rate Calculations ' <

The following is the equation used to calculate the dose rate resultant from the release of radioactive materials in gaseous effluents to areas at or beyond the site boundary for the purpose of showing compliance with ODCM Appendix C controls as related to 10CFR20.

(3.2-1)

^ j y/ w / \i) -"r/ ' '

Where:

= the organ "j" dose rate as a function of age group "a" and pathway Dajp 91 "p", mrem/yr;

= the dose factor for organ type uj", age group "a", pathway "p" for isotope T (see Tables 3.2-1 through 3.2-3); units and equations used (equations 3.2-2 through 3.2-6) are provided later in this section;

%/Q or D/Q = the normal or depleted relative dispersion factor (%/Q) in s/m3, or relative deposition (D/Q) in nrv2, at the receptor distance (see Appendix A);

ODCM Page: 37 Rev.: 23 3.15xi o1 = conversion factor to convert (mrem VCi)/(Ci*s) to mrem/yr; Qi = release rate of isotope Y (annualized), uCi/s

= (472)(Ci)(f)

Where:

ci = the concentration of radionuclide Y in the gaseous effluent, in jiCi/cc; '

f = the gaseous effluent flow rate during the release, ft3/min; 472 = conversion factor, (cc/ft3)/(s/min).

The following relationships are used to derive the dose factors (Dfaijp)for noble gases, tritium, radioiodines and particulates used in equation 3.2-1.

a. Whole Body Dose Factors from Exposure to a Semi-Infinite Plume Where: j T

. DF j_ = the whole body factor due to immersion in a semi-infinite cloud of radionuclide Y, (mrem

• m3)/(Ci

• s);

DFBi = the whole body gamma dose factdr for a semi-infinite cloud of radionuclide Y which includes the attenuation of 5 g/cm2 of tissue from Table 3.2-4, mrem/yr per pCi/m3; sF = the attenuation factor that accounts for the dose reduction due to the shielding provided by residential structures, optional, dimensionless:

= maximum exposed individual = 0.7, population dose 0.5 (Regulatory Guide 1.109), if calculating dose rate = 1.0; Xi = the annual average concentration of radionuclide "i" in air (pCi/m3), for a unit release rate (Ci/yr) and a unit x/Q (s/m3), (pCi/m3)/(Ci/yr)(s/m3).

b. Skin Dose Factors for Exposure to a Semi-Infinite Plume (3,2-3)

Where:

S DF j_ = the skin dose factor due to immersion in a semi-infinite cloud of radionuclide Y, (mrem

• m3)/(Ci

• s);

y '

DF j_ = the gamma air dose factor for a uniform unifo semi-infinite cloud of radionuclide "i", from Table 3.2-4, mrad/yr per pCi/m3;

ODCM Page: 38

( Rev.: 23 dsf+/- = the beta skin dose factor for a semi-infinite cloud of radionuclide "i" (includes attenuation by the outer "dead" layer of skin), from Table 3.2-4, mrem/yr per pCi/m3; sF = the attenuation factor that accounts for the dose reduction due to the shielding provided by residential structures, optional, dimensionless:

= maximum exposed individual = 0.7, population dose 0.5 (Regulatory Guide 1.109), if calculating dose rate = 1.0; xi - the annual average concentration of radionuclide "i" in air (pCi/m3), for a unit release rate (Ci/yr) and a unit x/Q (s/m3), (pCi/m3)/(Ci/yr)(s/m3);

1.11= the air dose to tissue dose equivalent conversion factor, mrem/mrad.

c. Dose Factors from External Irradiation from Radionuclides Deposited onto the Ground Surface DFiG.= (87 60) [cfj (DFGij) (sF) '* (3.2-4)

Where:

c DF . . = the dose factor for radionuclide "i" to organ "j" resulting from exposure to radionuclides deposited onto the ground surface, (mrem

• m2)/Ci;

• c , * -

C . = the ground plane concentration (pCi/m2) of radionuclide "i" for a unit release rate (Ci/yr) and a unit D/Q, relative ground deposition (nrr2),

. (pCi/m2)/(Ci/yr)(nrr2);

dfg+/- = the open field ground plane dose conversion factor for organ "j" fr°m radionuclide "i", from Table 3.2-5, mrem/yr per pCi/m2; sF .= the attenuation factor that accounts for the dose reduction due to the

, shielding provided by residential structures, optional, dimensionless:

. .,= maximum exposed individual = 0.7, population dose 0.5 (Regulatory Guide 1.109), if calculating dose rate = 1.0; 8760 = the number of hours per year.

d. Dose Factors frpm Inhalation of Radionuclides in Air DF = (DFAaij) (Ra) (xi) (3-2"5)

Where:

DF a . . = the dose factor for radionuclide T to organ uj" of an individual in age aij ...

group "a" due to inhalation, (mrem m3)/(Ci s) [equivalent to (mrem/yr)(yr/Ci)(m3/s)];

ODCM Page: 39 Rev.: 23

= the inhalation dose factor for radionuclide T, organ "j", and age

- . . group "a" (the value for skin is assumed to be 0), from Tables 3.2-6 through 3.2-9, mrem/pCi; Ra *= the annual air intake for individuals in age group "a", from Table 3.2-14, m3/yr; X. - the annual average concentration of radionuclide "i" in air (pCi/m3),

for a unit release rate (Ci/yr) and a unit %/Q (s/m3),

. . '- (pCi/m3)/(Ci/yr)(s/m3). ,

e. Dose Factors from the Ingestion of Atmospherically Released Radionuclides in Food

^kK>k^ + uIkR (3.2-6)

Where:

D '

DF aj_ j = the dose factor for radionuclide "i" to organ "j" of an individual in age group "a" from the ingestion of meat, leafy vegetables, milk, and produce (non-leafy vegetables, fruits, and grains) in (mrem

• m2)/Ci, or in the cases of H-3 and C-14 in (mrem

• m3)/(Ci

• s);

F L M V i, i, i i = the concentrations of radionuclide "i" in meat, leafy vegetables, milk, and produce, respectively (pCi/kg or pCi/L) for a unit release rate (Ci/yr) and a unit D/Q, relative ground deposition (nrr2), or in cases of j+3 and C14, a unit x/Q, relative ground-level concentration (s/m3), in (pCi/kg)(Ci/yr)(nv2) or (pCi/kg)/(Ci/yr)(s/m3) or (pCi/L)/(Ci/yr)(m-2) or (pCi/L)(yr/Ci)(s/m3);

DFiaij = the ingestion dose factor for radionuclide "i", organ uj", and age group "a", from Tables 3.2-10 through 3.2-13, mrem/pCi; fc , fv = the respective fractions of the ingestion rates of leafy vegetables and produce that are produced in the garden of interest, 1.0 and 0.76 respectively (Regulatory Guide 1.109);

F L M ' V

• U a, U a, U a, U a = the annual intake (usage) of meat, leafy vegetables, milk, and produce respectively, for individuals in age group "a", from Table 3.2-14, kg/yr or l/yr.

f. Dose rate example problem:

1) For the purpose of this sample problem, the following assumptions are utilized: a release of Xe-133 at 1 .OE-5 uCi/cc, a flow rate of 1.0E5 ft3/min, and a whole body dose factor of 2.94E-4 mrem/yr per pCi/m3. Dose rate and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cumulative dose are calculated.

2) Whole Body Dose Factor per ODCM equation 3.2-2.

ODCM Page: 40 Rev.: 23 For final dose calculation:

12 pCi/m3 mremm3 For dose rate:

IE + 12 pCi/m3 mrem m3 (c,/yr)(3 l5E + 07sec/m3)J

3) Dose Rate per ODCM equation 3.2-1.

For final dose calculation:

15E1) 5.8E - 6^r-V m Cisecll ft3sec cc yr For dose rate:

mrem

= 0.845 m3 Cisec sec yr Final dose calculation:

](ihr) = 6.74E - 5 mrem yr J /l8760

ODCM Page: 41 Rev.: 23 Table 3.2-1 Organ Used for Gaseous Effluent Dose Calculations

1. Bone

2. Gl Tract

3. Kidney

4. Liver

5. Lung

6. Thyroid,

7. Whole Body

8. Skin Table 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations

1. Adult (17 yr and older)

2. Teen (11-17 yr)

3. Child (1-11 yr)

4. Infant (0-1 yr)

Table 3.2-3 Gaseous Effluent Dose Pathwavs

1. Plume

2. Ground Shine

3. Vegetables

4. Meat

5. Cow Milk

6. Goat Milk

7. Inhalation

ODCM Page: 42 Rev.: 23

^ Table 3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Gamma Air**

Whole Body* Beta Skin* Dose Factor Gamma Dose Dose Factor Y Nuclide Factor (DFB^ (DFS,) , (df,)

Kr-83m 7.56E-08 1.93E-05 Kr-85m . 1.17E-03 1.46E-03 1.23E-03 Kr-85 ^ 1.61E-05 1.34E-03 .1.72E-05 Kr-87 5.92E-03 9.73E-03 6.17E-03 Kr-88 1.47E-02 2.37E-03 1.52E-02 Kr-89 1.66E-02 1.01E-02 1.73E-02 Kr-90 ,1:56E-02 v 7.29E-03 1.63E-02i Xe-131m 9.15E-05 476E-04 i.56E-04 -

Xe-133m 2.51 E-04 9.94E-04 3.27E-04 Xe-133 2.94E-04 3.06E-04 3.53E-04 Xe-135m  ; , 3.12E-03 7.11 E-04  :. 3.36E-03 Xe-135 1.81E-03 v 1.86E-03 1.92E-03 Xe-137 .1.42E-03 1.22E-02 1:51E-O3 Xe-138 8.83E-03 4:13E-O3 9.21 E-03 Ar-41 8.84E-03 2.69E-03 9.30E-03"

• mrem/yr per pCi/m3

• • mrad/yr per pCi/m3 I

ODCM Page: 43 I

Rev.: 23 Table 3.2-5 External Dose Factors for Standina on Contaminated Ground (mrem/h per pCi/m2)

Element Whole Bodv Skin H-3 O.OOE+00 , O.OOE+00 C-14 O.OOE+00 O.OOE+00 Na-24\ 2.50E-08 2.90E-08 P-32 0.00E+00 O.OOE+00 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 - A Mn-56 1.10E-08 1.30E-08 Fe-55 0.00E+00 O.OOE+00 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 ,.

Ni-63 0.00E+00 O.OOE+00 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 O.OOE+00 O.OOE+00 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 O.OOE+00 O.OOE+00 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Mo-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08

ODCM Page: 44 Rev.: 23 Table 3.2-5 (Cont.)

External Dose Factors for Standing on Contaminated Ground (mrem/h per pCi/m2) '

Element Whole Bodv Skin

• '" . > >\

Te-125M 3.50E-11  : 4.80E-11  :

Te-127M ..- 1.10E-12, 1.30E-12 Te-127 , 1.0QE-11 1.10E-11 Te-129M L7.70E-^0 ,[ 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09

• 990E-09 Te-131 2.20E-09 2.60E-06  :

Te-132 1.70E-09 2.00E-09 1-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 , 1.70E-08  : 2.00E-08 1-133 . 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 '

1-135 1.20E-08 1.40E-08 ,

Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137

• 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 -'

Ba-139 2.40E-09; . 2.70E-09 ;'*';.

Ba-140 2.10E-09 2.40E-09 Ba-141  : 4.30E-09 : - 4.90E-09 Ba-142 7.90E-09 9.00E-09  :.

La-140 1.50E-08 170E-08 La-142 1.50E-08 . 1.80E-08 Ce-141 5.50E-10; ,, 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-iav . . 3.70E-10

• Pr-143 0.00E+00

• 0.00E+00 Pr-144 2.00E-10 2.30E-10 Nd-147 T.00Er09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09

ODCM Page: 45 Rev.: 23 Table 3.2-6 Inhalation Dose Factors for Adult (mrem/DCi inhaled)

WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H-3 NO DATA 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 NO DATA NO DATA NO DATA 1.08E-05 Cr-51 NO DATA NO DATA 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-06 Mn-56 NO DATA 1.55E-10 2.29E-11 NO DATA 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.23E-07 NO DATA NO DATA 9.01 E-06 7.54E-07 Fe-59 1.47E-06 . 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 Co-58 NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1.16E-04 1.33E-05 Co-60 NO DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E-05 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81 E-06 NO DATA NO DATA 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 NO DATA NO DATA 7.00E-07 1.54E-06 Cu-64 NO DATA 1 83E-10 7.69E-11 NO DATA 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 NO DATA 5.27E-12 1.15E-07 2.04E-09 Br-83 NO DATA NO DATA 3.01 E-08 NO DATA NO DATA NO DATA 2.90E-08 Br-84

• NO DATA NO DATA 3.91 E-08 NO DATA NO DATA NO DATA 2.05E-13 Br-85 NO DATA NO DATA 1.60E-09 NO DATA NO DATA NO DATA LT E-24 Rb-86 NO DATA 1.69E-05 7.37E-06 NO DATA NO DATA NO DATA 2.08E-06 Rb-88 NO DATA 4.84E-08 2.41 E-08 NO DATA NO DATA NO DATA 4.18E-19 Rb-89 NO DATA 3.20E-08 2.12E-08 NO DATA NO DATA NO DATA 1.16E-21 Sr-89 3.80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 Sr-90 1.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1.20E-03 9.02E-05 Sr-91 7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 Sr-92 8.43E-10 NO DATA 3.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y-90 2.61 E-07 , NO DATA 7.01 E-09 NO DATA NO DATA 2.12E-05 6.32E-05 Y-91M 3.26E-11 NO DATA 1.27E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y-91 5.78E-05 NO DATA, 1.55E-06 NO DATA NO DATA 2.13E-04 4.81 E-05 Y-92 1.29E-09 NO DATA 3.77E-11 NO DATA NO DATA 1.96E-06 9.19E-06 Y-93 1.18E-08 NO DATA 3.26E-10 NO DATA NO DATA 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91 E-06 NO DATA 6.77E-06 2.21 E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 NO DATA 3.71 E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 . 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31 E-05 1.30E-05 Mo-99 NO DATA 1,51 E-08 2.87E-09 NO DATA 3.64E-08 1.14E-05 3.10E-05 Tc-99M 1.29E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07

ODCM Page: 46 Rev.: 23 Table 3,2-6 (Cont.)

Inhalation Dose Factors for Adult (mrem/pCi inhaled)

WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI Tc-101 5.22E-15 7.52E-15 7.38E-14 NO DATA 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91 E-07 NO DATA 8.23E-08 NO DATA 7.29E-07 6.31 E-05 1.38E-05 Ru-105 9.88E-11 NO DATA 3.89E-11 NO DATA 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 NO DATA 1.00E-06 NODATA 1.67E-05 1.17EO3 1.14E-04 Ag-110M 1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 5.79E-04 3.78E-05 Te-125M 4.27E-07 1.98E 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-05 Te-127M 1.58E-06 7.21 E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 T.75E-10 8.00E-11 3.87E-11 1.32E-10 6.37E-10 8.14E 7.17E-06 Te-T29M 1.22E-06 5.84E-07 1.98E-07 > 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1 82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 s 6.37E-05 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 NO DATA 9.61 E-07 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 1-131 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NODATA 5.08E-08 1-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-10 1-135 3.35E-07 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 NO DATA 1.07E-05 1.50E 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 NO DATA 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-i2 NO DATA 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21 E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41 E-15 4.20E-13 NODATA 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15' 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 NODATA NO DATA 7.91 E-07 2.64E-07 Ce-141 2.49E-06 1.69E 1.91 E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 NO DATA 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 NODATA 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51 E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91 E-13 NO DATA 8.81 E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07' 4.56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 NO DATA NODATA 3.63E-06 1.94E-05 Np-239 2.37E-08 2.82E-09 1.55E-09 NODATA 8.75E-09 4.70E-06 1.49E-05

ODCM Page: 47 Rev.: 23 Table 3.2-7 Inhalation Dose Factors for Teenager (mrem/pCi inhaled)

WHOLE NUCLIDE . BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H NO DATA 1.59E-07 1.59EO7 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72 E-06. 1.72E-06 1.72E-06 1J2E-06 1.72E-06 1.72E^06 P-32 2.36E-04 1.37E-05 8.95E-06 NO DATA NODATA NODATA 1.16E-05 Cr-51 NO DATA NO DATA 1.69E-08 9.37E-09 3.84E-09 2.62E-06 , 3.75E-07 Mn-54 NO DATA 6.32E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 8.35E-06 Mn-56 NO DATA 2.12E-10 3.15E-11 NO DATA 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 / 7.99E-07 Fe-59 1.29E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 Co-58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 Co-60, NO DATA 1.89E-06 2.48E-06 NO DATA; NODATA 1.09E-03 3.24E-05 Ni-63 7.25E-05 5/43E-06 2.47E-06 NO DATA NO DATA 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 ... NO DATA NO DATA 1.17E-06 4.59E-06 Cu-64 NO DATA 2.54E-10 1.06E-10 NO DATA 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 ..

Zn-69 6.04E-12 1.15E-11 8.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 Br-83 NO DATA NO DATA 4.30E-08 NO DATA NO DATA NODATA LT E-24 Br-84 NO DATA NO DATA 5.41 E-08 NO DATA NO DATA NODATA LT E-24 Br-85 NO DATA , NO DATA 2.29E-09 NODATA NODATA NO DATA LTE-24 Rb-86 NO DATA 2.38E-05 1.05E-05 NO DATA NODATA NO DATA 2.21 E-06.

Rb-88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 Rb-89 NO DATA 4.40E-08 2.91 E-08 NO DATA NO DATA NO DATA 4.22E-17 Sr-89 5.43E-05 NO DATA 1.56E-06 NODATA NO DATA 3.02E-04 4.64E-05 Sr-90 . 1.35E-02 NO DATA 8.35E-04 NO DATA. NO DATA 2.06E-03 9.56E-05 Sr-91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05, ,

Sr-92 1.19E-09 NO DATA 5.08E-11 NO DATA NO DATA 3.43E-06 1.49E-05 Y-90 3.73E-07 NO DATA 1.00E-08 NO DATA NO DATA 3.66E-05 6.99E-05 Y-91M 4.63E-11 NO DATA 1.77E-12 NODATA NODATA 4.00E-07 3.77E-09 Y-91 8.26E-05 NO DATA 2.21 E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y-92 1.84E-09 NO DATA 5.36E-11 NO DATA NODATA 3.35E-06 2.06E-05.

Y-93 , 1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05 Zr-95. .... 182E-05 5.73E-Q6 3.94E-06 NO DATA 8.42E-06 3.36E-04 1.86E-05 Zr-97 . 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 NODATA 1.25E-06 8.39E-05 1.21E-05 -

Mo-99 NO DATA 2.11.E-08 4.03E-09 NODATA 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73.E-13 4.83E-13 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.66E-07

ODCM Page: 48 Rev.: 23 Table 3.2-7 (Cont.)

Inhalation Dose Factors for Teenager (mrem/pCi inhaled)

WHOLE NUCLIDE BONE ; LIVER BODY THYROID KIDNEY; LUNG GI-LLI Tc-101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 Ru-103 ^ 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.36E-05 -

Ru-105. . 1.40E-10 - NO DATA 5.42E-11 NO DATA. 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 NO DATA 1.55E-06 NO DATA 2.38E-05 2.01 E-03 1.20E-04 Ag-110M 1.73E-06 1.64E-06 9.99E-07 .' NO DATA 3.13E-06 8.44E-04 3.41 E-05 Te-125M 6.10E-07 2.80E-07 8.34E-08  : 1.75E-07 NO DATA 6.70E-05 9.38E-06 ,

Te-127M 2:25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 -.v 1.99E-05 Te-127 2.51 E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01 E-05 Te-129M 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131M 1.23E-08 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.97E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05

-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06

-131 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11 E-07

-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1.59E-07

-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06

-134 1.11 E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09

-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71 E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51 E-05 1.06E-06 Cs-i38 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 NO DATA 1.23E-14 4.11 E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 NO DATA NO DATA 2.68E-05 6.09E-05 La-142 1.20E-10 5.31 E-11 1.32E-11 NO DATA NO DATA 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06. 2.71 E-07 NO DATA 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 V 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 Nd-147: 9.83E-07 1.07E-06 6.41 E-08 NO DATA 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21 E-05 Np-239 4.23E-08 3.99E-09 2.21 E-09 NO DATA 1.75E-08 8.11E-06 1.65E-05

i ODCM Page: 49 Rev.: 23 Table 3.2-8 Inhalation Dose Factors for Child (mrem/pCi inhaled)

WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H-3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06  : 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 < 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 Cr-51 NO DATA NO DATA 4.17E-08 2.31 E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 NO DATA 1.1.6E-05 2.57E-06 NO DATA 2.71 E-06 4.26E-04 6.19E-06 Mn-56 NO DATA 4.48E-10 8.43E-11 NO DATA 4.52Er10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51 E-06 NO DATA NO DATA 3.43E-04. , 1.91 E-05 Co-58 NO DATA 4.70E-07 8.55E-07 , NO DATA NO DATA 2.99E-04 9.29E-06 Co-60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05

• Ni-63 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1.71 E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 NO DATA NO DATA 2.21E-06 2.27E-05 Cu-64 NO DATA. 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41 E-06 Zn-69 1.81E-11 2.61 E-11 2.41 E-12 NO DATA 1.58E-11 3.84E-07 2.75E-06 Br-83 . NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 Br-84 < NO DATA NO DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 Br-85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 Rb-86 NO DATA 5.36E-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06 Rb-88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 Rb-89 NO DATA 9.33E-08 7.83E-08 NO DATA NO DATA NO DATA 5.11E-10 Sr-89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 Sr-90 2.73E-02 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 Sr-91 3.28E-08 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.70E-05 Sr-92 3.54E-09 NO DATA , 1.42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 Y-90 1.11 E-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y-91M 1.37E-10 NO DATA- 4.98E-12 NO DATA NO DATA 7.60E-07 4.64E-07 Y-91 2.47E-04 NO DATA 6.59E-06 . NO DATA NO DATA 7.10E-04 4.97E-05 Y-92 5.50E-09 NO DATA 1.57E-10 , NO DATA NO DATA 6.46E-06 6.46E-05 Y-93 5.04E-08 NO DATA 1.38E-09 NO DATA NO DATA 2.01 E-05 1.05E-04 Zr-95 5.13E-05 . 1.13E-05 1.00E-05 NO DATA 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08. 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-05 Mo,99 NO DATA 4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-05 ..

Tc-99M 4.81 E-13 . 9.41 E-13 1.56E-1.1 NO DATA 1.37E-11 2.57E-07 1.30E-06

ODCM Page: 50 Rev.: 23 Table 3.2-8 (Cont.)

Inhalation Dose Factors for Child (mrem/pCi inhaled)

WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG ^ GI-LLI Tc-101 2.19E-T4 2.30E-14 2.91 E-13 NO DATA 3.92E-13 1.58E-07 4.41 E-09 Ru-103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 NO DATA 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 3.68E-05 NO DATA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 Ru-106 Ag-110M 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74E-06 ' 1.48E-03 ";< 2.71 E-05 Te-125M 1.82E-06 6.29E 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 Te-127M 6.72E-06 2.31 E-06 8.18E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71 E-06

• 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71 E-06 1.36E-05 4.76E-04 4.91 E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 - 7.93E^07 6.89E-06 Te-'131M 3.63E-08 , 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 ' 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 - 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05

-130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 NO DATA 1.38E-06

-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 5.72E-07 1.10E 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07

-132

-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 NO DATA 1.48E-06 3.17E-07. 5.84E-07 2.09E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07

-134

-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81 E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 NO DATA 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 NO DATA 5.71 E-09 4.71 E-04 2.75E-05 Ba-14i 5.29E-11 2.95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 2.73E-15 7.54E-13 NO DATA 7.87E-I5 4.44E-07 7.41 E-10 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 La-140 La-142 3.50E-T0 1.11 E-10 3.49E-11 NO DATA NO DATA 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.31 E-06 1.47E-05 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04 Ce-144 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.11E-07 1.17E-04 2.63E-05 Pr-143 Pr-144 1.61 E-11 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-06 8.87E-05 2.22E-05 W-187 4.41 E-09 2.61 E-09 1.17E-09 NO DATA NO DATA 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05

ODCM Page: 51 Rev.: 23 Table 3.2-9 Inhalation Dose Factors for Infant (mrem/pCi inhaled)

WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H-3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06' 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 Cr-51 NO DATA NO DATA 6.37E-08 4.11 E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 NO DATA 1.81E-05 3.56E-06 , NO DATA 3.56E-06 7.14E-04 5.04E-06 Mn-56  ;. NO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 NO DATA NO DATA  ; 6.21E-05 7.82E-07.

Fe-59 9.69E-06 1.68E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 Co-58 NO DATA 8.71 E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 Co-60 NO DATA 5.73E-06 8.41 E-06 NO DATA NO DATA 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 NO DATA NO DATA 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 Cu-64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 .

Zn-69 3.85E-11 6.91 E-11 5.13E-12 NO DATA 2.87E-11 1.05E-06 9.44E-06 Br-83 NO DATA NO DATA 2.72E-07 NO DATA NO DATA NO DATA LT E-24 Br-84 NO DATA NO DATA 2.86E-07: , NO DATA

• NO DATA NO DATA LT E-24 Br-85 NO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA LT E-24 Rb-86 NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 Rb-88 NO DATA 3.98E-07 2.03E-07 NO DATA NO DATA, NO DATA 2.42E-07 Rb-89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 Sr-89 2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 Sr-90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 Sr-91 6.83E-08 NO DATA 2.47E-09 NO DATA NO DATA 3.76E-05 5 24E-05^

Sr-92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1.00E-04 Y-90 2.35E-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 Y-91M 2.91 E-10 NO DATA 9.90E-12 , NO DATA NO DATA 1.99E-06 1.68E-06 Y-91

• 4.20E-04 NO DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y-92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05 Y-93 1..07E-07 NO DATA 2.91 E-09 NO DATA NO DATA 5.46E-05 1.19E-04 Zr-95  ; 8.24E-05 1.99E-05 1.45E-06 NO DATA 2.22E-05 1.25E-03 1.55E-05

• Zr-97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-04 Nb-95

• 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 Mo-99 NO DATA 1.18E-07 2.31 E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 <

Tc-99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 . 1.45E-06 ,

ODCM Page: 52 Rev.: 23 Table 3.2-9 (Cont.)

Inhalation Dose Factors for Infant (mrem/pCi inhaled)

WHOLE NUCLIDE BONE - LIVER BODY THYROID KIDNEY / LUNG GI-LLI 4.65E-14 5.58E-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07 Tc-101 Ru-103  : 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05 -

6.20E-05 NO DATA 7.77E-06 NO DATA 7.61 E-05 8.26E-03 1.17E-04 Ru-106 Ag-110M 7.13 E-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 Te-125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81 E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01 E-05 4.35E-06 1.59E-06

• 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-129 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51 E-05 ^

Te-131M 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-131 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 Te-132 4.54E-06 9.91 E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06

-130 1.71 E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07

-131

-132 1.21 E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-06

-133 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21 E-07

-134

-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 NO DATA 1.31 E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 NODATA 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61 E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 Cs-137 3.61 E-07 5.5.8EtO7 2.84E-07 NODATA 2.93E-07 4.67E-08 6.26E-07 Cs-138 7.03E-13 3.07E-11 NO DATA 4.23E-13 4.25E-06 3.64E-05 Ba-139 1.06E-09 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 Ba-140 1:12E-10 7.70E-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 Ba-141 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.11 E-06 4.95E-07 Ba-142 3.61 E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04. 6.06E-05 La-140 7.36E-10 2.69E-10 3.46E-11 NO DATA NO DATA 5.87E-06 4.25E-05 La-142 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.75E-06 3.69E-04 1.54E-05 2.09E-07 1.38E-07 1.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 Ce-143 Ce-144 2.28E-03 8.65E-04 1.26E-04' NO DATA 3.84E-04 7.03E-03; 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41 E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.15E.06 3.06E-06 Nd-147 5.67E-06 5.81 E-06 3.57E-07 NO DATA 2.25E-06 . 2.30E-04 2.23E-05 9.26E-09 6.44E-09 2.23E-09 NO DATA NODATA 2.83E-05 2.54E-05 W-187 Np-239 2.65E-07 2.37E-08 1.34E-08 NODATA 4.l73E-08 4.25E-05 1.78E-05

ODCM Page: 53 Rev: 23 Table 3.2-10 Inqestion Dose Factors for Adult (mrem/pCi inqested)

WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 > 1.70E-Q6 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 O.OOE+00 O.OOE+00 2.17E-05 Cr-51 O.OOE+00 O.OOE+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 O.OOE+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 O.OOE+00 1.40E-05 Mn-56 - O.OOE+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 O.OOE+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 O.OOE+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91 E-06 O.OOE+00 O.OOE+00 2.85E-06 3.40E-05 Co-58 O.OOE+00 7.45E-07 1.67E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.51E-05 Co-60 O.OOE+00 2.14E-06 4.72E-06 0.00E+00 O.OOE+00 O.OOE+00 4.02E-05 Ni-63 1.30E-04 9.01 E-06 4.36E-06 0.00E+00 O.OOE+00 O.OOE+00 1.88E-06 Ni-65 5.28E-07 6.86EtO8 3.13E-08 0.00E+00 O.OOE+00 O.OOE+00 1.74E-06.

Cu-64 O.OOE+00 8.33E-08 3.91 E-08 0.00E+00 2.10E-07 O.OOE+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 O.OOE+00 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09, 0.00E+00 1.28E-08 O.OOE+00 2.96E-09 .

Br-83 O.OOE+00, O.OOE+00 4.02E-08 0.00E+00 O.OOE+00 O.OOE+00 5.79E-08 Br-84 O.OOE+00 , O.OOE+00 5.21 E-08 0.00E+00 O.OOE+00 O.OOE+00 4.09E-13 Br-85 O.OOE+00 O.OOE+00 2.14E-09 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 2.11E-05 9.83E-06 0.00E+00 O.OOE+00 O.OOE+00 4.16E-06 Rb-88 O.OOE+00 6.05E-08 3.21 E-08 0.00E+00 O.OOE+00 O.OOE+00 8.36E-19 Rb-89 o:ooE+oo 4.01 E-08 2.82E-08 O.OOE+00 O.OOE+00 O.OOE+00 2.33E-21 Sr-89 3.08E-04 O.OOE+00 8.84E-06 0.00E+00 O.OOE+00 O.OOE+00 4.94E-05 Sr-90. 7.58E-03 O.OOE+00 1.86E-03 0.00E,+00 O.OOE+00 O.OOE+00 2.19E-04 Sr-91 5.67E-06 O.OOE+00 2.29E-07 . O.OOE+00 O.OOE+00 O.OOE+00 2.70E-05 Sr-92 2.15E-06 O.OOE+00 9.30E-08 O.OOE+00 O.OOE+00 O.OOE+00 . 4.26E-05 Y-90 9.62E-09 O.OOE+00 2.58E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.02E-04 Y-91M 9.09E-11 O.OOE+00 3.52E-12 O.OOE+00 O.OOE+00 O.OOE+00 2.67E-10 Y-91 1.41E-07 O.OOE+00 3.77E-09 0.00E+00 O.OOE+00 O.OOE+00 7.67E-05 Y-92 8.45E-10 O.OOE+00 2.47E-11 0.00E+00 O.OOE+00 O.OOE+00 1.48E-05 Y-93 2.68E-09 J O.OOE+00 7.40E-11 . 0.00E+00 O.OOE+00 O.OOE+00 8.50E-05 Zr-95 3.04Er08 "" 9.75E-09 6.60E-09 0.00E+00 1.53E-08 O.OOE+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 O.OOE+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 O.OOE+00 2.10E-05 Mo-99 O.OOE+00 4.31 E-06 8.20E-07 0.00E+00 9.76E-06 O.OOE+00 9.99E-06 Tc-99M 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07

ODCM Page: 54 Rev.: 23 Table 3.2-10 (Cont.)

Indestion Dose Factors for Adult (mrem/pCi ingested)

WHOLE ISOTOPE ' BONE- LIVER BODY THYROID KIDNEY LUNG GI-LLI Tc-101 ; 2.54E-10 3.66E-10 3.59E-09" 0.00E+001 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 -- 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08 O.OOE+00 6.08E-09 O.OOE+00 199E-07 O.OOE+00 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31 E-06 0.00E+00 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91 E-07 0.00E+00 6.04E-05 Te-125M 2.68E-06 9.17E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 ' 8.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129M: 1.15E-05 4.29E-06 1.82Ey-d6 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08-; 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 - 0.00E+00 2.37E-08 Te-131M 1.73E-06 8.46E-07: 7.05E-07 1.34E-06 8.57E-06 O.OOE+OO 8.40E-05 Te-131 *"' 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 O.OOE+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71 E-05 1-130 7.56E-07 2.23E 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 1-131 .- "-< 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 - 1.02E-05 O.OOE+00 1.57E-06 1-132 -"' 2.03E-07 . 5.43E-07 1.90E-07 1.90E-05 8.65E-07 O.OOE+00 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 O.OOE+00 2.22E-06

• 1-134 """ 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+00- 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 O.OOE+00 1.31 E-06 Cs-134 6.22E-05: 1.48E-04 1.21E-04' 0.00E+00 4.79E-05 1.59E-05 ' 2.59E-06 Cs-136 '" 6.51 E-06 2.57E-05 1.85E-05 ' 0.00E+00' 1.43E-05 1.96E 2.92E-06 Cs-i3? 7.97E-05 1.09E-04 7.14E-05 O.OOE+00 3.70E-05 1.23E-05':! 2.11 E-06 Cs-138 5.52E-08 1.09E-07 -^ 5.40E-08 O.OOE+00 8.01 E-08

• 7.91 E-09 4.65E-13 Ba-139 9.70E-08 6.91 E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 . 1.72E-07 Ba-140 2.03E-05 2.55E-08 ' I 1.33E-06 O.OOE+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71 E-08 3.56E-11 1.59E-09 O.OOE+00 3.31 E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 O.OOE+00 1.85E-11 1.24E-11', 3.00E-26 La-140 2.50E-09" 1.26E-09 3.33E-10 0.00E+00 0:00E+00 O.OOE+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 O.OOE+00 O.OOE+00 4.25E-07 Ce-141 9.36E-09 6.33E-09' 7.18E-10 O.OOE+00 2.94E-09 O.OOE+00 2.42E-05 Ce-143 1.65E-09' 1.22E-06 1.35E-10 0.00E+00 5.37E-10 O.OOE+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 O.OOE+00 1.21 E-07 O.OOE+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 O.OOE+00 4.03E-05 Pr-144 3.O1E-11"; 1.25E-11 1.53E-12 0.00E+00 7.05E-12 O.OOE+00 4.33E-18 '

Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 O.OOE+00 3.49E-05 W-187 1.03EH07-" ;:- .8.6.1 E-08 3.01 E-08 O.OOE+00 0.00E+00 " O.OOE+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 O.OOE+00 2.40E-05

ODCM Page: 55 Rev.: 23 Table 3.2-11 Inqestion Dose Factors for Teenager (mrem/pCi ingested)

WHOLE ISOTOPE BONE LIVER. BODY  : THYROID . KIDNEY LUNG . GI-LLI **

H-3 O.OOE+00 1.06E-07 , 1.06E-07 1.06E-07 1.06E-07 1.06E-Q7 '<. 1.06E-07 C-14 4.06E-06 8.12E-07, 8.12E-07 , 8.12E-07 8.12E-07  ;: 8.12E-07, 8.12E-07 Na-24 , 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 .

P-32 2.76E-04 1.71E-05 . 1.07E-05 ',, 0.00E+00 0.00E+00 0.00E+00 2.32E-05 Cr-51 O.OOE+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 O.OOE+00, 5.90E-Q6 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 Mn-56 O.OOE+00 1.58E-07 2^81 E-08 O.OOE+00 2.00E-07 0.00E+00- 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 O.OOE+00 O.OOE+00 1.70E-06, 1.16E-06 Fe-59 5.87E-06 1.37E-05. 5.29E-06 .' 0.00E+00 0.00E+00 4.32E-06: 3.24E-05 Co-58 O.OOE+00, 9.72E-07 2.24E-06 0.00E+00 O.OOE+00 0.00E+00 . 1.34E-05 Co-60 O.OOE+00 2.81 E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 O.OOE+00 0.00E+00 5.19E-06 ,

Cu-64,  : O.OOE+00 1.15E-07 5.41 E-08 0.00E+00 2.91 E-07 O.OOE+00 8.92E-06 Zn-65.; 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 O.OOE+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 Br-83 O.OOE+00 0.00E+00 5.74E-08 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Br-85 O.OOE+00 0.00E+00 3.05E-09 . 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 2.98E-05 1.40E-Q5 0.00E+00 , 0.00E+00 O.OOE+00 . 4.41 E-06 Rb-88 O.OOE+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 O.OOE+00 7.30E-15 Rb-89 O.OOE+00 5.50E-08 3.89E-08, O.OOE+00 O.OOE+00 O.OOE+00 , 8.43E-17 Sr-89 4.40E-04 0.00E+00 1.26E-05 O.OOE+00 0.00E+00 O.OOE+00 : 5.24E-05 Sr-90 8.30E-03 0.00E+00 2.05E-03 O.OOE+00 0.00E+00 O.OOE+00 2.33E-04.,

Sr-91 . 8.07E-06 0.00E+00 3.21 E-07 O.OOE+00 0.00E+00 O.OOE+00 3.66E-05 .

Sr-92 3.05E-06, 0.00E+00 1.30E-07 O.OOE+00 0.00E+00 O.OOE+00 7.77E-05 Y-90: 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 O.OOE+00. 1.13E-04'.

Y-91M 1.29E-10 0.00E+00 4.93E-12 0.00E+00 O.OOE+00 O.OOE+00 6.09E-09 Y-91, . , 2.01 E-07 O.OQE+00 5.39E-09, 0.00E+00 0.00E+00 O.OOE+00 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 i 0.00E+00 0.00E+00 O.OOE+00 . 3.32E-05 Y-93  ; 3.83E-09 O.OOE+00 1.05E-10s 0.00E+00 0.00E+00 O.OOE+00 ,. 1.17E-04 Zr.95. 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91 E-08 O.OOE+00 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 O.OOE+00 7.11E-10 O.OOE+00 - 1.27E-04 Nb-95 8.22E-Q9 4.56E-09 2.51 E-09 0.00E+00 4.42E-09 O.OOE+00 1.95E-05 ,

Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 O.OOE+00 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 O.OOE+00 1.38E-08. 5.14E-10 6.08E-07

ODCM Page: 56 Rev.: 23 Table 3.2-11 (Cont.)

Indestion Dose Factor for Teenager (mrem/pCi ingested)

WHOLE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Tc-101 3.60E-10 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 O.OOE+QO 2.13E-05 Ru-103 0.00E+60 - 8.46E-09 0.00E+00' 2.75E-07 0.00E+00 1.76E-05 Ru-105 2.18E-08 O.OOE+00 4.94E-07 O.OOE+00 7.56E-06 0.00E+00 1.88E Ru-106 3.92E-06 2.05E-07 1.94E-07^ 1.18E-07 O.OOE+00 ' 3.70E-07 0.00E+00 5.45E-05 Ag-110M 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-125M 3.83E-06 9.67E-06 3.43E-06 1.15E-06 2.30E 3.92E-05 O.OOE+00 2.41 E-05 Te-127M 3.40E-08 1.09E-07  : 6.40E-07 0.00E+00 1.22E-05 Te-127 1.58E-07 5.60E-08 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129'M 1.63E-05 6.05E-06 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 Te-1'29 4.48E-08 1.67E-08 Te-131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 O^OOE+OO 9.39E-05

• Te-131 2.79E-08 1.15E-08 8.72E-09;.- 2:15E-08 1.22E-07 O.OOE+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2^08E-06 2.33E-06 2.12E-05 O.OOE+00 ' . 7.00E-05 2.98E-06 1.19E-06 - 2.43E-04 4.59E-06 0:00E+00 2.29E-061-1-130 / 1.03E 8.19E-06 4.40E-06 2.39E-03' 1.41E-05 O.OOE+00 1.62E-06 1-131 5.85E-06 7.30E-07 2.62E-07 2.46E-05 1.15E-06 O.OOE+00 3.18E-07

.1-132 2.79E-07 3.41 E-06 1.04E-06 ' 4.76E-04 5.98E-06 O.OOE+00 2.58E-06 1-133 2.01 E-06 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+00 5.10E-09 !

1-134 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 O.OOE+00 1.74E-06 1-135 8.37E-05 1.97E-04 9.14E-05 O.OOE+00 6.26E-05 2.39E-05 2.45E-06 Cs-134 8.59E-06 3.38E-05 2.27E-05 O.OOE+00 1.84E-05 2.90E-06 2.72E-06 Cs-136 1.12E-04 1.49E-04 5.f9E-05 O.OOE+00 5.07E-05 1.97E-05 2.12E-06 Cs-137 7.76E-08 1.49E-07 7.45E-08' 0.00E+00 1.10E-07 1.28E-08 ' 6.76E-11 **

Cs-138 139E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba-139 '

2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-140 6.71E-08 5.01 E-11 2.24E-09 *' 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-141 2.99E-08 2.99E-11 ; 1.84E-09 > 0.00E+00 ; 2.53E-11 1.99E-11 9.18E-20 Ba-142 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 O.OOE+00 9.82E-05 La-140 7.95E-11; 1.98E-11 O.OOE+00 0.00E+00 O.OOE+00 2.42E-06 La-142 1.79E-10 Ce-141 1.33E-08 8.88E-09 '*. 1.02E-09 O.OOE+00 4.18E-09 O.OOE+00 2.54E-05 2.35E-09 1.71 E-06:- 1.91E-10 0.00E+00 7.67E-10 O.OOE+00 5.14E-05 Ce-143 2.88E-07 3.74E-08 O.OOE+00 1.72E-07 O.OOE+00 1.75E-04 Ce-144 6.96E-07 5.23E-09 6.52E-10 O.OOE+00 3.04E-09 O.OOE+00 4.31 E-05 Pr-143 1.31E-08 1.76E-11 2.18E-12 O.OOE+00 - 1.01 E-11 O.OOE+00 4.74E-14 Pr-144 4.30E-11 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-09 O.OOE+00 3.68E-05 Nd-147 1.19E-07 4.17E-08 0.00E+00 ' 0.00E+00 O.OOE+00 . 3.22E-05 W-187 1.46E-07 1.66E-10 9.22E-11 0.00E+00 5.21E-10 O.OOE+00 2.67E-05 Np-239 1.76E-09

ODCM Page: 57 Rev.: 23 Table 3.2-12 Ingestion Dose Factors for Child (mrem/pCi ingested)

WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG -; GI-LLI H-3 O.OOE+00 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 ..

Na-24 5.80E-06 . 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 *< 3.18E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.28E-05 ,-

Cr-51 , O.OOE+00 O.OOE+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 ,

Mn-54 O.OOE+00 1.07E-05 2.85E-06 O.OQE+OO 3.00E-06 O.OOE+00 8.98E-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 O.OOE+00 4.04E-07 O.OOE+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 O.OQE+OO O.OOE+00 3.45E-06 1.13E-06 Fe-S^ 1.65E-05. 2.67E-05 1.33E-05 O.OOE+00 O.OOE+00 . 7.74E-06 2.78E-05 Co-58 O.OOE+00 1.80E.06 . 5.51 E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.05E-05 Co-60 O.OOE+00<< 5.29E-06 1.56E-05 O.OOE+00. O.OOE+00 O.OOE+00 2.93E-05 Ni-63 5.38E-Q4 2.88E-05, 1.83E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-06 .*;.

Ni-65 2.22E-06 2.09E-07 1.22E-07  : O.OOE+00 O.OOE+00 O.OOE+00 2.56E-05 Cu-64 0.00E+00 2.45E-07. 1.48E-07 O.OOE+00 5.92E-07 O.OOE+00 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 O.OOE+00 2.30E-05 O.OOE+00 6.41 E-06.

Zn-69  ; 4.38E-08 6.33E-08 5.85E-09 O.OOE+00 3.84E-08 O.OOE+00 3.99E-06 Br-83 O.OOE+00 O.OOE+00 1.71E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 1.98E-07 ., O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 9.12E-09 O.OOE+00., O.OOE+00 O.OOE+00 O.OOE+00 Rb-86

• O.OOE+00 6.70E-05 4.12E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.31 E-06 Rb-88 O.OOE+00 1.90E-07 1.32E-07 O.OOE+00 O.OOE+00 O.OOE+00 9T32E-09 Rb-89 " O.OOE+00 1.17E-07 1.04E-07 O.OOE+00 O.OOE+00 O.OOE+pp 1.02E-09 Sr-89',..-. 1.32E-03 O.OOE+00 3.77E-05 O.OOE+00 O.OOE+00 O.OOE+00 , 5.11E-05 Sr-90 1.70E-02 O.OOE+00 4.31 E-03 O.OOE+00 O.OOE+00 - O.OOE+00 2.29E-04 Sr-91 2.40E-05 O.OOE+00 9.06E-07 O.OOE+00 O.OOE+00 O.OOE+00 5.30E-05 .

Sr-92 9.03E-06 O.OOE+00 3.62E-07 O.OOE+00 O.OOE+00 O.OOE+00 ;. 1.71E-04 Y-90 4.11E-08 O.OOE+00 1.10E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.17E-04 Y-91M 3.82E-10 , O.OOE+00 1.39.E-11 O.OOE+00 O.OOE+00 O.OOE+00 / 7.48E-07.

Y-91

• 6.02E-07 O.OOE+00 1.61 E-08 O.OOE+007 O.OOE+00 O.OOE+00 8.02E-05 Y-92 3.60E-09. O.OOE+00 1.03E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.04E-04 Y-93 1.14E-08 O.OOE+00 3.13E-10 O.OOE+00. O.OOE+00 O.OOE+00 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 O.OOE+00 3.65E-08 O.OOE+00 2.66E-05, Zr-97 6.99E-09 1.01E-09 5.96E-10 O.OOE+00 1.45E-09 O.OOE+00 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 O.OOE+00 8.23E-09 O.OOE+00 1.62E-05 Mo-99 O.OOE+00 1.33E-05 3.29E-06 O.OOE+00 2.84E-05 O.OOE+00 1.10E-05 Tc-99M 9.23E-10 1.81E-09 3.00E-08 O.OOE+00 2.63E-08 9.19E-10 1.03E^06

ODCM Page: 58 Rev.: 23 Table 3.2-12 (Cont.)

Indestion Dose Factors for Child (mrem/pCi ingested)

WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI

• Tc-101  ; 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 - 5.92E-10 3.56E-09 Ru-103 7.31 E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E-08 0.00E+00- 2.34E-08v 0.00E+00 5.67E-07 O.OOE+00 4.21 E-05 1.17E-05  ; 0.00E+00 1.46E-06; 0.00E+00 1.58E-05 0.00E+00 1.82E-04 Ru-106 Ag-110M 5.39E-07 "* 3.64E-07 2.91 E-07 0.00E+00 6.78E-07 '* 0.00E+00 4.33E-05 Te-125M 1.14E-05  ; 3.09E-06 1.52E-06^ 3.20E-06 O.OOE+00 O.OOE+00 1.10E-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 0.00E+00 2.34E-05 Te-127' 4.71 E-07' 1.27E-07 '* 1.01 E-07 3.26E-07 1.34E-06 O.OOE+00 T.84E-05 '

Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+00 5.94E-05 Te-129 1.34E-0? 3.74E-08 3.18E-08 9.56E-08 3.92E-07 O.OOE+00 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41 E-05 O.OOE+00 1.01E-04 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51 E-07 0.00E+00 4.36E-07 Te-131 Te-132 1.01E-05

• 4.47E-06 5.40E-06 *-' 6.51 E-06 4.15E-05 0.00E+00 4.50E-05 1-130 2.92E-06 5.90E-CJ6 3.04E-06 6.50E-04 8.82E-06 O.OOE+00' 2.76E-06 1-131 1.72E-05 1.73E-05V 9.83E-06 5.72E-03 2.84E-05 O.OOE+00 1.54E-06 8.00E-07 1..47E-06 6.76E-07 6.82E-05 2.25E-06 O.OOE+00 1.73E-06 1-132 1-133 5.92E-06 7.32E-06 ' 2.77E-06 1.36E-03 1.22E-05 O.OOE+00 2.95E-06 4.19E-07 7.78E-07 3.58E-07

• 1.79E-05 1.19E-06 O.OOE+00 5.16E-07 1-134 2.79E-04 4.83E-06 O.OOE+00 2.40E-06 1-135 ""'< 1.75E-06 3.15E-06 1.49E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6:46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 " 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01 E-07 0.00E+00 2.23E-07 2.40E-08; 1.46E-07 Ba-139 4.14E-07 2.21 E-10 1.20E-08 O.OOE+00 1.93E-10 1.30E-10 '* 2.39E-05 Ba-140 8.31 E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21 E-05 2.00E-07 1.12E-10 6.51 E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-141 Ba-142 8.74E-08 6.29E-11: 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 ' 0.00E+00 O.OOE+00 O.OOE+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 0.00E+00 o:ooe+oo O.OOE+00 3.31 E-05 3.97E-08 1.98E-08" 2.94E-09 O.OOE+00 8.68E-09 O.OOE+00 2.47E-05 Ce-141 Ce-143 6.99E-09 3.79E-06 - 5.49E-10 O.OOE+00 1.59E-09 O.OOE+00 5.55E-05 2.08E-06 6.52E-07*' '* 1.11 E-07 O.OOE+00 3.61 E-07 O.OOE+00 1.70E-04 Ce-144 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 O.OOE+00 "4.24E-05 Pr-143 3.99E-11 6.49E-12 0.00E+00 2.11E-11 O.OOE+00 8.59E-08 Pr-1-44 *-* 1.29E-10 Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 O.OOE+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+00

• 0.00E+00v O.OOE+00 . 3.57E-05 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 O.OOE+00 2.79E-05 Np-239

ODCM Page: 59 Rev.: 23 Table 3.2-13i Ingestion Dose Factors for Infant (mrem/pCi ingested)

WHOLE ISOTOPE . . BONE LIVER BODY THYROID KIDNEY \ LUNG GI-LLI H-3 O.OOE+00 3.08E-07 3.08E-07 3.08E-07 - 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 .

Na-24. 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.0.1 E-05 1.01 E-05 1.01 E-05 P-32, 1.70E-03 1.00E-04 6.59E-05 0.00E+00 O.OOE+00. O.OOE+00 2.30E-05 Cr-51 O.OOE+00 O.OOE+00 1.41 E-08 9.20E-09 2.01 E-09 1.79E-08 4.11 E-07  :..

Mn-54 0.00E+00 1.99E-05 4.51 E-06 0.00E+00 4.41 E-06 O.OOE+00 7.31 E-06 Mn-56 0.00E+00 8.18E-07 1.41 E-07 0.00E+00 7.03E-07 O.OOE+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 O.OOE+00 O.OOE+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 O.OOE+00 1.59E-05 2.57E-05 Co-58 0.00E+00 3.60E-06 8.98E-06 O.OOE+00 O.OOE+00 O.OOE+00 8.97E-06 Co-60 O.OOE+00 1.08E-05 2.55E-05 0.00E+00 O.OOE+00 ; O.OOE+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 O.OOE+00 O.OOE+00 . 1.95E-06 Ni-65 ' 4.70E-06 5.32E-07 2.42E-07 0.00E+00 O.OOE+00 O.OOE+00 4.05E-05 Cu-64 O.OOE+00 . 6.09E-07 2.82E-07 0.00E+00 1.03E-06 O.OOE+00 1.25E-05 Zn-65 1.84E-05 . 6.31 E-05 2.91 E-05 0.00E+00 3.06E-P5 O.OOE+00 5.33E-Q5 Zn-69 9.33E-08 1.68E-07 1.25E-08 O.OOE+00 6.98E-08 O.OOE+00 1.37E-05 Br-83 .*, O.OOE+00 O.OOE+00 3.63E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 3.82E-07 O.OOE+00. O.OOE+00 O.OOE+00 O.OOE+00 Br-85. O.OOE+00 O.OOE+00 1.94E-08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00  ;

Rb-86 O.OOE+00 1.70E-04 8.40E-05 O.OpE+00 o!ooe+oo . O.OOE+00 4.35E-06 Rb-88 O.OOE+00 4.98E-07 2.73E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.85E-07 Rb-89 O.OOE+00 2.86E-07 1.97E-07 O.OOE+00 O.OOE+00 O.OOE+00 9.74E-08 Sr-89 2.51 E-03 O.OOE+00 7.20E-05 O.OOE+00 O.OOE+00 O.OOE+00 5.16E-05 Sr-90 1.85E-02 O.OOE+00 4.71.E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.31 E-04 Sr-91 5.00E-05, O.OOE+00 . 1.81 E-06 O.OOE+00 O.OOE+00 O.OOE+00 5.92E-05 Sr-92 , 1.92E-05 O.OOE+00 7.13E-07 O.OOE+00  : O.OOE+00 O.OOE+00 2.07E-04 Y-90 8.69ErO8 O.OOE+00 2.33E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.20E-04 Y-91M 8.10E-10, O.OOE+00 2.76E-11 O.OOE+OO O.OOE+00 O.OOE+00 2.70E-06 Y-91 1.13E-06 O.OOE+00 3.01 E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.10E-05 Y-92 7.65E-09 O.OOE+00 2.15E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.46E-04, Y-93 2.43E-08:, O.OOE+00 6.62E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.92E-04, Zr-95 2.06E-07 5.02E-08 3.56E-08 O.OOE+00 5.41 E-08 O.OOE+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 O.OOE+00 2.56E-09 O.OOE+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 O.OOE+00 1.24E-08 O.OOE+00 1.46E-05 Mo-99 O.OOE+00 3.40E-05 6.63E-06 O.OOE+00 5.08E-05 O.OOE+00 1.12E-05 Tc-99M 1.92E-09 3.96E-09 5.10E-08 O.OOE+00 4.26E-08 2.07E-09 1.15E-06

ODCM Page: 60 Rev.: 23 Table 3.2-13 (Cont.)

Inqestidn Dose Factors for Infant WHOLE ISOTOPE BONE 1 LIVER BODY THYROID KIDNEY LUNG GI-LLI Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4i95E-07 0.00E+00 308E-06 0.00E+00 1.80E-05 '

Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41 E-05 Ru-106 2.41 E-05 0.00E+00 3.01 E-06 O.QOE+OO 2.85E-05 0.00E+00 1.83E-04 Ag-110M 9'96E-07 7.27E-07 4.81 E-07 0:00E+00 1.04E-06 0.00E+00 3.77E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11 E-05 Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0:00E+00 7.11 E-06 Te-132 2.08E-05 1.03E-05 9.61 E-06 1.52E-05 6.44E-05 0.00E+00 3.81 E-05 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51 E-06 1-132 1.66E-06 3.37E^06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 0.00E+00 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 415E-05 1.99E-06 0.00E+00 1.84E-06 1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+OQ 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91 E-06 Cs-136 4.59E-05 1.35E.04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91 E-06 Cs-138 4.81 E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81 E-07 5.84E-10 2.55E-08 0.00E+00 3.51 E-10 3:54E-10 5.58E-05 Ba-140 1.71E-04 1.71 E-07 8.81 E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91 E-10 1:34E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81 E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Ce-143 1.48E-08 _ 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 Ce-144 2^98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E-11 0.00E+00 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09  ! 0.00E+00 2.19E-08 O.OOE+OQ 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61 E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05

ODCM

^ Page: 61 Rev.: 23 Table 3.2-14 Annual Usage Factors for the Maximum Exposed Individual Pathway Infant Child Teen Adult Fruits, vegetables & - 520 630 520 grain (kg/yr)*

Leafy - 26 42 64 vegetables(kg/yr)

Milk (LVyr)

• 330 330 400 310 Meat & poultry _, - 41 65 110 (kg/yr) . .

i'.' . ' - .

Inhalation (m3/yr) 1400 3700 8000 8000 Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.

Table 3.2-15 Annual Usage Factors for the Average Individual**

Pathway Infant Child Teen Adult Fruits, vegetables & 200 240 190 grain (kg/yr)*

Milk (L/yr) 170 200 110 Meat & poultry . -. 37 59 95 (kg/yr) )

Inhalation (m3/yr) __

3700 8000 8000 Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.

For total population and average individual dose calculations.

ODCM Rev.: 23 Page: 62 Figure 3.2-1 PNPP Site Boundarv and Unrestricted Area TOLiqpip WWWIXnOKTB, SHE WIWIT tNitwrnrr WWMIUIIW lU'-t" HOXBt The boondary line almas the lake ahore only to liquid effluents oarcatrlctied area boundary.

-I UNRESTRICTED AREA

ODCM Page: 63 Rev.: 23 3.3 10CFR50. Appendix I Compliance - Gaseous Effluent Dose Doses resulting from the release of noble gases, radioiodines, tritium and radionuclides in particulate form must be calculated to show compliance with 10CFR50, Appendix I. The calculations will be performed at least monthly for all gaseous effluents.

3.3.1 Noble Gases 10CFR50, Appendix I, Section II.B.1, limits the releases of gaseous effluents from each reactor to unrestricted areas such that the estimated annual gamma air dose is limited to 10 millirads and the beta air dose is limited to 20 millirads. The external dose pathway only will be considered for noble gases. The controlling location for the above stated dose limits is the nearest site boundary location for the period of release.

ODGM Appendix C controls limit the dose resulting from the release of noble gas radionuclides in gaseous effluents to the following:

a. For gamma radiation, during the current quarter: k D < 5 mrad, air .

. b. For beta radiation, during the current quarter: .

Dair \ < 10 mrad,

c. For gamma radiation, during the current year:

"'- D air *

< 10 mrad,

' . .; .. , * \- -

\ d; For beta radiation, during the current year: . .

Dv . < 20 mrad. '

air ' * *).;'

3.3:2 Radioiodines, Particulates, and Other Radionuclides 10CFR50, Appendix I, Section II.C, limits the annual release of radioiodines and radioactive materials in particulate form from each reactor such that estimated dose or dose commitment v to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. The controlling location for this organ dose limit is the nearest site boundary, the deposition (D/Q) for the period of release, and the receptor pathway. Receptor pathway locations will be reviewed once per year following the performance of the Land Use Census to include consideration of nearest residences, garden, and farm animal locations in each sector.

ODCM Page: 64 Rev.: 23 ODCM, Appendix C, CONTROLS limit the dose resultant from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days to the following:

a. During the current quarter:

Dose to Any Organ < 7.5 mrem

b. During the current year:

Dosei to Any Organ < 1*5 mrem 3.3.3 Dose Calculations The following calculations are used to determine gamma and beta air doses resultant from noble gas release to areas at or beyond the site boundary for purpose of showing compliance with 10CFR50, Appendix I. The equations used to calculate organ doses resultant from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than eight days are those found in Section 3.2.3.

Dose values are obtained by applying the dose rates over the appropriate surveillance or sampling time period.  ;

a. Gamma Air Dose from Noble Gas Releases \

Where:  ; .

Y D = the annual gamma air dose due to noble gas radionuclides, mrad/yr; all =*'

• DF ! = the gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i", from Table 3.3-1, (mrad m3)/(s Ci);

Qi = the release rate of radionuclide T, nCi/s; x/Q = tne annual average dispersion factor (see Appendix A), s/m3; 3.15 x i 01 = the conversion factor to convert (mrad>Ci)/(Ci*s) to mrad/yr.

ODCM Page: 65 Rev.: 23

b. Beta Air dose from Noble Gas Releases Where:

D air = the annual beta air dose due to noble gas radionuclides, mrad/yr; O

DF j_ = the beta air dose factor for a uniform semi-infinite cloud of radionuclide T, from Table 3.3-1, (mrad m3)/(Ci s);

q+/- , = the release rate of radionuclide T, nCi/s; x/Q = the annual average dispersion factor (see Appendix A), s/m3;

' / 3.15x10 = the conversion factor to convert (mrad>Ci)/(Ci*s) to mrad/yr.

3.3.4 Cumulation of Doses The dose contribution from gaseous effluents will be calculated at least monthly Calculations will be performed to determine the maximum air dose as well as the maximum organ dose to an individual. These dose calculations will be summed for comparison with quarterly and annual limits. To assure compliance with 10CFR50, Appendix I, the dose limits for air dose and organ dose are those found in Sections 3.3.1 and 3.3.2, respectively. The quarterly limits specified in those sections represent one half of the annuai design objectives.

If these limits are exceeded, a special report will be submitted to the NRC in accordance with ODCM Appendix C controls.

Table 3.3-1 Gamma and Beta Air Dose Factors for Semi-Infinite Plume (mrad/s per Ci/m3)

Gamma Air Beta Air Dose Factor Dose Factor H) / H)

Ar-41 2.95E+02 1.04E+02 Kr-83m 6.12E-01 9.13E+00 Kr-85m 3.90E+01 6.24E+01 Kr-85 5.45E-01 6.18E+01 Kr-87 1.96E+02 3.27E+02 Kr-88 4.82E+02 9.29E+01 Kr-89 5.48E+02 3.36E+02 Kr-90 5.14E+02 2.48E+02 Xe-131m 4.95E+00 3.53E+01 Xe-133m 1.04E+01 4.69E+01 Xe-133 1.12E+01 3.33E+01 Xe-135m 1.07E+02 2.34E+01 Xe-135 6.09E+01 7.80E+01 Xe-137 4.79E+01 4.03E+02 Xe-138 2.92E+02 1.51E+02

ODCM Page: 66 Rev.: 23 3.3.5 Projection of Doses Anticipated doses resulting from the release of gaseous effluents will be projected monthly.

The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month.

In this case the source term will be adjusted to. reflect this information and the justification for the adjustment rioted. -<v: *'*':

If the sum of the projected doses for the 31-day period exceeds 0.3 mrem to any organ, appropriate portions of the ventilation exhaust treatment system will be operated to reduce releases. The values for the projected dose impact levels correspond to about one forty-eighth of the 10CFR50, Appendix I dose limits. If continued for a year, these values would correspond to less than one-fourth of the 10GFR50, Appendix ! dose limits.

3.4 Population Dose  :

PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, will include total population dose and average individual doses calculated for all radioactive gaseous effluent releases. The total population dose and average individual dose will be computed, taking into account geographical population distribution and pathway(s) using the equations in Section 3.2.

However, the dose factors, DFayp, differ; total population and average individual doses are calculated in a manner similar to that used for maximum individuals except that Regulatory Guide 1.109, Revision 1, assumptions for average individuals are used rather than for maximum exposed individuals and they are averaged over all ag& groups after weighting by the fraction of population in each age group. ^

ODCM Page: 67 Rev.: 23 4.0 TOTAL DOSE 4.1 40OFR190 and 10CFR72.104 Compliance - Uranium Fuel Cycle Dose ,

Annual dose contributions from liquid and gaseous effluent releases, as discussed in Sections 2.3.2 and 3.3.4, are summed to evaluate compliance with the 40CFR190 and 10CFR72.104 annual limit of 25 mrem whole body or any organ (except the thyroid, which is 75 mrem).

PNPP does not intend to exceed 40CFR190 or 10CFR72.104 limits during normal operation.

However, if such a situation should occur, violations would be handled asper ODCM Appendix C Control 3/4.11.4a. which requires the following:

Calculations shall be made to include direct radiation contributions from the reactor units, from the ISFSI, from outside storage tanks, and any other sources from the uranium fuel cycle, to determine whether the above limits of Control 3.11.4 have been exceeded. If such is the case, prepare and 10/2019 submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10CFR20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the.above limits, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

This Special Report shall contain:

1. A determination of which fuel cycle facilities or operations, in addition to the nuclear power reactor unit(s) at the site, contribute to the annual dose to the maximum exposed individual.

Nuclear fuel facilities over five miles from PNPP need not be considered in this determination.

2. A determination of the maximum exposed individual.

3. A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents and direct radiation using the methodologies described in this ODCM. Where additional information on pathways and nuclides is needed, the best available information will be used and documented.

4. A determination of the dose resulting from direct radiation from the plant and storage facilities, including the ISFSI.

The whole body and organ doses resulting from liquid effluents from the PNPP will be summed with the doses resulting from gaseous releases of noble gases, radioiodines, tritium, and particulates with half-lines greater than eight days when any of the dose limits outlined in Sections 2.3.2, 3.3.1 or 3.3.2 are exceeded by a factor of two. The doses from the PNPP will be summed with the dose to the maximum exposed individual contributed from other operations of the uranium fuel cycle.

ODCM Page: 68 Rev.: 23 4.2 Direct Radiation Dose from PNPP (including the ISFSI)

Potential direct radiation dose to individuals outside PNPP will arise from (a) skyshine and direct dose from the turbines, (b) direct dose from the external surfaces of buildings, and (c) direct dose from stored radwaste. ' - -!i' ' ' '

Coolant activation by high energy neutrons, the O16(n,p)N16 reaction, is of interest in boiling water reactors, like PNPP, because it can result in turbine skyshine and direct dose. The N-16 present in the steam of a direct cycle BWR is carried with the steam into the turbine moisture separators, and

, associated equipment. Although N-16 has a half-life of 7.13 seconds, its gamma emission can present a radiation dose problem to the site boundary as a result of the high energy gamma scatter from structures and the atmosphere.

All external walls of buildings at PNPP have been designed to attenuate radiation sources from within the plant to maximum of 0.5 mrem/h outside, with an expected radiation dose not to exceed 0.25 mrem/h.

Projected direct radiation dose assessment for normal operations was performed, based on 80%

load factor and 100% occupancy, for the closest site boundary location (WSW sector). Direct dose from turbine skyshine was calculated to be 1.3 mrem/yr and direct dose from the surface of buildings was calculated to be 2.2 E-3 mrem/yr.

Direct radiation doses at PNPP will be measured by self-contained dosimeters encircling the site located in the general area of the site boundary. These self-contained dosimeters will be of the thermoluminescent variety (TLDs) with monitoring performed per Table 3.12.1-1, Radiological Environmental Monitoring Program.

4.3 Dose to Members of the Public While Onsite ODCM Appendix C Control 6.9.1.7 requires "assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary." This assessment is included in Annual Radioactive Effluent Release Reporting.

A member of the public is defined in ODCM Appendix C to include anyone who is not occupational^ associated with the plant, i.e., not a utility employee, contractor or vendor. Also excluded from this,category is any person who enters the site to service equipment or make deliveries.

Maximum dose to member of the public while onsite is conservatively assessed relative to offsite dose values. The assessment methodology incorporates use of appropriate dilution, dispersion, and occupancy factors for onsite activities.

The only liquid effluent dose pathway affecting members of the public while onsite is shore exposure, which is assumed to be fishing on the Lake Erie shoreline. Onsite dose assessment is made via ratio to the maximum calculated offsite shore exposure dose, using adjustments for occupancy factor and liquid effluent dilution.

, ODCM Page: 69 Rev.: 23 Several cases are considered for gaseous effluent dose assessment to member of the public while onsite including: traversing a public road within the site boundary, lakeshore fishing, non-PNPP related training sessions at the Training and Education Center, car-pooling to the Primary Access Control Point (PACP) parking lot, and job applicant interviews. This evaluation is made using "relative %/Q" (atmospheric dispersion) values. "Relative %/Q" values are the product of the highest annual average %/Q for the point of concern, and occupancy factor for the case. The ratio of the highest onsite "relative x/Q" to the highest site boundary "relative %/Q" is used as an adjustment factor. (A unity occupancy factor is used in the determination of the highest site boundary "relative x/Q"). A conservative onsite dose determination is made by applying the "relative %/Q" adjustment factor for the highest potential onsite dose activity to the highest calculated gaseous effluent offsite dose. . , *-.-:'

ODCM Page: 70 Rev.: 23 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5.1 Monitoring Program ^

Environmental samples shall be collected and analyzed according to Table 3.12.1-1 at locations shown in Figures 5.1-1, 5.1-2 and 5.1-3. Analytical techniques used shall ensure that the detection capabilities in Table 4.12.1-1 are achieved.

Ground water sampling will not be conducted as part of PNPP's REMP because this source is not tapped for drinking or irrigation purposes in the area of the plant. The position of the plant and the underdrain system with respect to the hydraulic gradient is such that any leakage or overflow from the underdrain system will flow north towards Lake Erie. Local domestic wells outside the exclusion area boundary are up-gradient from the plant. As part of the REMP, samples will be routinely collected from the closest potable water intakes on Lake Erie.

The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. The initial radiological environmental monitoring program was conducted for the first three years of commercial operation; program changes may now be proposed based on operational experience.

5.2 Land Use Census Program A Land Use Census shall be conducted annually to identify, within a distance of 8 km (5 miles), the location in each of the meteorological sectors of the nearest residence, the nearest garden* greater than 50m2 (500 ft2) and the nearest milk-producing animal.

If a Land Use Census identifies a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at the location from which samples are currently being obtained the new location(s) will be added to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.

The Land Use Census shaH be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, general observations, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.

Broad leaf vegetation sampling of at least three different types of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12.1-1 shall be followed, including analysis of control samples.

ODCM Page: 71 Rev.: 23 5.3 Inter-Laboratory Comparison Program The laboratories of the licensee and/or licensee's contractors which perform analyses shall participate in an Interlaboratory Comparison Program which has been approved by the Commission. This participation shall include all of the determinations (sample medium-radionuclide combinations) that are included in the monitoring program. The results of analysis of these comparison samples shall be included in the Annual Radiological Environmental Operating Report.

If the results of a determination in the comparison crosscheck program are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it.

The results of this investigation and corrective action shall be included in the Annual Radiological Environmental Operating Report.

ODCM Page: 72 Rev.: 23 Table 5.1-1 ODCM REMP Sample Locations Location # Description Miles Direction Media <1) 1 Chapel Road 3.4 . ENE TLD, AlP Kanda Garden 1.9 ENE Broadleaf Vegetation 2

3 Meteorological Tower 1.0 SE TLD 4 Site Boundary 0.7 S TLD, AlP 5 Quincy Substation 0.6 SW TLD 6 Concord Service Center 11.0 SSW TLD, AlP 7 Site Boundary 0.6 NE TLDl AlP Site Boundary 0.8 E TLD 8

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 Madison-on-the-Lake 4.7 ENE TLD 13 14 HubbardRd. 4.9 E

• TLD 15 Eagle St. Substation 5.1 ESE TLD Eubank Garden 0.9 S Broadleaf Vegetation 16 Rainbow Farms 1.9 E . Broadleaf Vegetation 20 21 Hardy Rd. 5.1 WSW TLD 23 High St. Substation 7.9 WSW TLD St. Clair Ave. 15.1 SW TLD 24 Offshore - PNPP discharge 0.6 NNW Fish 25 River Rd. 4.3 SSE TLD 29 30 Lane Rd. 4.8 SSW TLD Wood and River Rd. 4.8 SE TLD 31 Offshore - Mentor 15.8 WSW . Fish 32 River Rd. 4.5 S TLD 33 35 Site Boundary 0.6 E TLD, AlP Lake County Water Plant 3.9 i WSW TLD, Drinking Water 36 Gerlica Farm 1.5 ENE Broadleaf Vegetation 37 Painesville Purification Plant 8.3 W Drinking Water 39 3715 Parmly Rd. : 0.5 WSW TLD 53 Hale Rd. School 4.6 SW TLD 54 Center Rd. 2.5 S TLD 55 Madison Hiqh School 4.0 ESE TLD 56 Perry Hiqh School .1.7 S TLD ,

57 Antioch Rd. 0:8 ENE TLD 58 Lake Shoreline at Green Rd. 4.0 ENE Surface Water 59 Lake Shoreline at Perry Park 1.0 WSW Surface Water 60 Lake Shore Metropolitan Park 1.4 NE Sediment 66 H&H Farm Stand 16.2 SSW Broadleaf Vegetation 70 (1) AlP = Air, Iodine and Particulate TLD = Thermoluminescent Dosimeter

ODCM Page: 73 Rev.: 23 Figure 5.1-1 ODCM REMP sample locations Within two miles of PNPP NNW NNE NW NE WNW ENE W E WSW ESE sw SE SSW SSE

ODCM Page: 74 Rev.: 23 Figure 5.1-2 ODCM required REMP sample locations between two and eight miles of PNPP sw ssw SSE SE

ODCM Rev.: 23 Page: 75 Figure 5.1-3 ODCM required REMP sample locations greater than eight miles from PNPP

ODCM Page: 76

/ Rev.: 23 APPENDIX A ATMOSPHERIC DISPERSION AND DEPOSITION-PARAMETERS

ODCM Page: 77 Rev.: 23 The atmospheric dispersion and deposition parameters used to calculate gaseous effluent doses will be calculated using the following equations. Dose calculations will be performed using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or using historical average atmospheric conditions. All atmospheric releases at PNPP are considered to be ground-level releases.

a. Constant Mean Wind Direction Relative Dispersion Factor

/ _ (2.032)(Tf )

AT (A"1)

Where:

= the annual average dispersion factor, s/m3; Tf = the terrain correction factor, from FSAR Table 2.3-26, dimensionless; u = the wind speed (measured at 10m), in m/s; X = the distance of calculation, in m; 2.032 = (2ln)'A divided by the width in radians of a 22.5°sector a = the lesser of Ll + ik or (Oz) f3i/21 Where:

hc = the building height (44.8m);

ctz = the vertical dispersion coefficient, per Regulatory Guide 1.111, in m.

b. Depleted Relative Dispersion Factor x/Qd = (x/q)(dpl-J (A-2)

Where:

= tne depleted relative dispersion factor (for airborne halogens and particulates), in s/m3; j = the ground depletion factor for the uj"th distance, interpolated from Table A-1, dimensionless; x/Q = the annual average dispersion factor per equation A-1, s/m3.

c. Ground Deposition (DEP-J(Tf)

D/Q = / 3'\f' (A-3)

(0.3927)(x)

Where:

d/q = the relative deposition per unit area (for halogens and particulates), rrr2; DEPj = the ground deposition factor for the "j"th distance, interpolated from Table A-1, m-1; Tf = terrain correction factor, from FSAR Table 2.3-26, dimensionless; x = the "j"th distance, m; 0.3927 = radians per 22.5° sector

ODCM Page: 78 Rev.: 23 Table A-1

\ Atmospheric DeDletion and Deposition Factors Depletion Deposition Factors Factors (dplj) ";. ' (DEPj.m-1)

Pasquill Stability . Class All , ; All Distance (meters) 200 0.970 - 1.25E-04

. . 500 * > 0.936 8.0E-05

-) 1,000 r 0.900 5.4E-05 2,000 0.860 3.2E-05 3,000 0.832 / 2.6E-05

' ' 6,000  ; 0.770 " 1.5E-05 10,000 0.714 9.9E-06 30,000 0.590 4.5E-06 50,000  ; 0.517 3.0E-06 80.000 0.440 2.0E-06 The following tables contain annual average atmospheric dispersion and deposition parameters for long-term releases at PNPP. Long-term releases are those that occur greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year:

The highest annual average relative concentration (%/Q) value at the site boundary for sectors over land shall be used for radioactive gaseous effluent monitor setpoint calculations. The dispersion model used was XOQDOQ, with PNPP FSAR site-specific terrain adjustment factors included. Dispersion values are based on seven years of meteorological data (May 1, 1972 through April 30, 1974 and September 1,1977 through August 31,1982), ground-level releases, sector spread for purge calculations, and twelve wind speed classes. < .

ODCM Page: 79 Rev.: 23 Table A-2 Site Boundary AtmosDheric Dispersion (y/Q) and DeDosition Parameters (D/Q) for PNPP1 Unit 1 Distance Distance x/Q D/Q Sector (miles) (meters) (sec/m3) (perm2)

N 0.18 294 5.0E-05* 1.4E-07 NNE 0.25 402 2.4E-05* 9.0E-08 10/2019 NE 0.42 678 , 7.4E-06* > 3.5E-08 ENE 0.67 1079 2.5E-06* ' 1.8E-08 E 0.67 1072 2.2E-06 1.6E-08 ESE 0.67 1083 1.8E-06 1.2E-08 SE 0.79 1269 1.5E-06 9.5E-09 SSE 0.82 1316 2.8E-06 1.4E-08 S 0.80 1298 3.3E-06 1.6E-08 SSW 0.80 < 1284 1.9E-06 8.6E-09

, sw 0.65  ; 1047 3.6E-06* 1.3E-08 wsw , 0.55 893 7.2E-06 1.7E-08 w .";' .', 0.27 430 3.6E-05* V.6E-08 WNW 0-18 283 ,. 6.8E-05* - 8.7E-08, NW . 0.17 273 6.9E-05* 1.0E-07 NNW 0.17 280 5.8E-05* 1.1E-07 ; **  ;

NOTE: All y/GI and D/Q values are taken fronri the Updated Safetv Analvsis Rebc5rt iruSARV Table 2.3-27. All marked values (*) are from Unit 1 USAR x/Q values and the balance are 10/2019 Unit 2 values. In each case, the most conservative x/Q value is utilized with the corresponding D/Q.

ODCM Page: 80

- Rev.: 23 Table A-3 Atmospheric Dispersibn (v/QVas a Function Of Distance (s/m3)

ECTOR - 0.5 - 1.5 2.5 3.5 4.5

' (MILES)  ; (MILES)  % (MILES) (MILES) (MILES)

N 9.36E-06 1.12E-06 5.58E-07 3.54E-07  : 2.30E-07 NNE ' : 7.93E 1.07E-06 5.21 E-07 3.28E-07 2.11 E-07 10/2019 NE 5.65E-06 7.51 E-07 3.28E-07  : 2.04E-07 1043E-07 ENE 4.02E-06 5.13E-07 2.39E-07 1.46E-07  ! 1.01 E-07 E 3.49E-06 4.35E-07 : -1.83E-07 1.11 E-07 ;  : 7.65E-08 ESE 2.82E-06 3.48E-07 "v'1.60E-07 - 8.75E-08 6.02E-08 SE 3.13E-06 3.09E-07 142E-07 8.54E-08 5.34E-08 SSE '6.17E-06  : 4.55E-07 146E-07 ~':' 8.91 E-08 6.18E-08 S 7.00E-06 5.73E-07 1!34E-07 8.19E-08 5.69E-08 SSW 4.00E-06 4.70E-07 i:60E-07 - 9.88E-08 ' 6.93E-08 SW 5.53E-06 .5.77E-07 2.83E-07 1.78E-07 ': 1.26E-07 WSW 8.51 E-06 I 9.57E-07 7.39E-07  : 3.87E-07 ' 2.38E-07 W 1.22E-05 1.46E-06 '1.15E-06 7.00E-07 ' 3.80E-07 WNW1 1.10E-05 - 1.40E-06 1.04E-06 i 7.59E-07 4.27E-07 NW - 1.05E-05 "'"* 1.34E-06 6.83E-07 }  ; 4.80E-07 3.47E-07 NNW  ; 9.51 E-06 1.21 E-06 6:11 E-07 ;;" 3.91 E-07  ; 2.56E-07 ECTOR 7.5 15.0 25.0 35.0 45.0 (MILES) (MILES) (MILES) (MILES) (MILES)

N ' 1.17E-07 4.77E-08 2.49E-08 'M.63E-08 1.19E-08 NNE 1.06E-07 4.25E-08 2.19E-08 1.43E-08 1.04E-08 10/2019 NE 7.09E-08 2.78E-08 1.41 E-08 9.08E-09 6.55E-09 ENE 4.86E-08 1.83E-08 9.06E-09 5.73E-09 4.08E-09 E 3.65E-08 1.36E-08 6.73E-09 4.25E-09 3.03E-09 ESE 2.85E-08 1.05E-08 5.17E-09 3.25E-09 2.31 E-09 SE 2.52E-08 9.29E-09 4.54E-09 2.85E-09 2.02E-09 SSE 2.97E-08 1.13E-08v 5.60E-09 3.56E-09 " 2.54E-09 S 2.75E-08 1.05E-08 5.23E-09 3.33E-09 2.39E-09 SSW v 3.41E-08 7 1.34E-08 6.81 E-09 4.39E-09 3.18E-09 SW 6.37E-08 " 2.57E-08 1.33E-08 8.71 E-09  ; 6.36E-09 WSW 1.22E-07  : 4.98E-08 2.61 E-08

• 1.72E-08 " 1.26E-08 W 1.98E-07 A 8.30E-08 4.42E-08 2.93E-08; *' 2.16E-08 WNW 2.23E-07 9.38E-08 5.00E-08 S^E-Oo^ 2.45E-08 NW 1.81 E-07 7.57E-08 4.03E-08  ; 2.67E-0& 1.97E-08 NNW 1.32E-07 5.46E-08 2.89E-08

• 1.90E-08  ;- 1.40E-08

ODCM Page: 81 Rev.: 23 Table A-4 AtmosDheric Dispersion (D/Q) as a Function of Distance"(nv?)

ector 0.5 1.5 2.5 3.5 4.5 (MILES) '*- (MILES) (MILES)

.r (MILES) (MILES)

N 2.97E-08 2.86E-09 1.17E-09 6.45E-10 374E-10 NNE 3.04E-08 3.29E-09 1.35E-09  ; 743E-10 ! /* 4.31 E-10 10/2019 NE 2.64E-08 2.85E-09 , 1.06E-09 5.86E-10 3.74E-10 ENE 2.86E-08 3.09E-09 .1.27E-09 6.97E-10 4.45E-10 E 2.52E-08 2.72E-09 1.02E-09 5.59E-10 3.57E-10 ESE 1.94E-08 2.10E-09 8.60E-10 ." 4.31E-10 2.75E-10, SE 2.01 E-08. . 1.74E-09 7.12E-10 3.92E-10 2.27E-10 SSE 3.05E-08 ., 1.92E-09  : 5.41 E-10 2.98E-10 1.90E-10 S 3.47E-08 ,-,,...,. 2.42E-09 4.97E-10 2.74E-10 1.75E-10 SSW 1.85E-08 1.85E-09  : 5:42E-10 2.99E-10 1.91 E-10 SW 1.93E-08 1.67E-09 , 6.85E-10 , 3.77E-10 2.41 E-10 WSW 1.97E-08 1.79E-09 1.14E-09 5.16E-10 2.82E-10 W 1.70E-08 1.64E-09  ; 1.04E-09 5.37E'-10 2.57E-10 WNW 1.74E-08 1.77E-09 1.06E-09 6.56E-10 3.25E-10 NW 1.98E-08 2.02E-09 8.27E-10 4.97E-10 3.17E-10, NNW 2.18E-08 2.22E-09 9.11 E-10 5.02E-10 2.91E-10 SECTOR 7.5 15.0 25.0 35.0 45.0 (MILES) (MILES) .. (MILES) ,; (MILES) (MILES)

N 1.52E-10 4.81 E-11 1.95E-11 1.05E-11 6.52E-12 NNE 1.75E-10 5.54E-11 2.25E-11 1.21 E-11 7.51 E-12 NE 1.52E-10 4.80E-11 1.95E-11 ...> 1.05E-11 6.52E-12 ENE 1.80E-10 5.72E-11 , 2.32E-11 1.25E-11 7.75E-12 10/2019 E 1.45E-10 4.58E-11 , 1.86E-11 1.00E-11 6.22E-12 ESE 1.11E-10 3.53E-11. 1.43E-11 7.71 E-12 4.79E-12 SE 9.22E-11 .: 2.92E-11 , 1.19E-11 6.38E-12 3.97E-12 SSE 7.70E-11 , 2.44E-11 9.92E-12 5.34E-12 3.31E-12<:

S 7.08E-11 2.25E-11 9.11E-12 ... 4.90E-12 3.04E-12 *"

SSW 7.72E-11 , 2.45E-11 ' 9.94E-12 ' 5.35E-12 3.32E-12 SW 9.76E-11 3.09E-11 1.26E-11  : 6.76E-12 4.20E-12 WSW 1.14E-10 .- 3.63E-11 1.47E-11 7.91E-12 , 4.92E-12:

W 1.04E-10 3.30E-1L 1.34E-11 7.21 E-12 4.48E-12 WNW 1.32E-10 4.18E-11 1.70E-11 9.13E-12, 5.67E-12 NW 1.28E-1Q >> 4.07E-11 1.65E-11 8.8J9E-12 . . . 5.52E-12 NNW 1.18E-10 3.74E-11 1.52E-11 8.17E-12 5.07E-12

ODCM Page: 82 Rev.: 23 APPENDIX B LOWER LIMIT OF DETECTION

ODCM

/ Page: 83 Rev.: 23 The lower limit of detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected with a 95 percent probability with a 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

The LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

For a measurement system (which may include radiochemical separation) based on gross beta, gross alpha, liquid scintillation, or other analyses where a background count determined by a separate measurement with no sample (or blank sample) is subtracted from the gross sample count to obtain a net count due to sample activity:

1/2 LLD =

(c)(E)(v)(Yc)exp(-XAt) . (B"1)

Where:

LLD = the "a priori" lower limit of detection, as defined above; C = the conversion factor of transformations per unit time per ^Ci or pCi; E = the detector efficiency; r rb = the background count rate in units of transformations per unit time; tb = the counting time of background; ts = the counting time of the sample; V = the sample size, in units of mass or volume; yc = the fractional radiochemical sample collection or concentration yield (when applicable);

At = for plant effluents, the elapsed time between the midpoint of sample collection and time of counting; for environmental samples, the elapsed time between sample collection (or end of the sample collection period) and time of counting; X = the radioactive decay constant for the radionuclide in question.

For the purpose of routine analyses, count times for both the sample(s) and background(s) are equal.

This satisfies the given ODCM Appendix C control for lower limit of detection definition, as the numerator of equation B-1 simplifies to 4.66 Sb, where Sb is the standard deviation of the background count rate or the count rate of a blank sample, as appropriate.

For gamma ray spectroscopy analyses:

At LD exp 0.693

= (c)(E)(t)(v)(YcH^T Where:

LLD = the lower limit of detection, in nCi or pCi per unit mass or volume; C -= the conversion factor of transformations per unit time per jj.Ci or pCi; E = the detector efficiency for the energy in question; t = the data collection (counting) time of sample; ti / 2 = the half-life of the radionuclide in question; V = the sample size, in units of mass or volume;

ODCM Page: 84 Rev.: 23 the fractional radiochemical, sample collection, or concentration yield (when applicable);

the yield of the gamma ray in question; At for plant effluents the elapsed time between midpoint of sample collection and time of counting; for environmental samples, the elapsed time between sample collection (or end of the sample collection period) and the time of counting; Ld the detection limit (B-3) kz + 2k 1 +

Where:

Bl the number of counts in "n" background channels below the peak due to Compton scattering, etc., determined at the same time a photopeak is measured; the number of counts in the "n" background channels above the peak; an abscissa of the normal distribution corresponding to confidence level, 1.645 at a confidence level of 95%;

the measured value of interference in the photopeak of interest due to environmental background, detector contamination, etc., determined by a separate measurement with no sample; N the number of channels in the photopeak of interest; n the number of background .channels on each side of the photopeak of interest; CTl the standard deviation of I.

Typical values of E, V, Y, and At shall be used in the calculation.

In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g.,

potassium-40 in milk samples).

Analyses shall be performed in such a manner that the LLD's listed in Tables 4.11.1.1.1-1, 4.11.2.1.2-1, and 4.12.1-1 of the ODCM Appendix C controls for the Perry Nuclear Power Plant will be achieved under routine conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nudides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

ODCM Page: 85 Rev.: 23 APPENDIX C CONTROLS

ODCM Page: 86 Rev.: 23 INDEX nFFINITIONR SECTION PAGE 1.0 DEFINITIONS  ;.....;..^ ..../..::.....:....:.....: .,;....:... ........ 97 Table 1.1, Surveillance Frequency Notation ....101 Table 1.2,-MODES ,

• 102 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY  ;!:..*..>- 1Q4 3/4.3 INSTRUMENTATION K -

Radioactive Liquid Effluent Monitoring Instrumentation  :>. 106 Table 3.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation.............:...... 107 Table 4.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ..;........:...:."...........:. 109 Radioactive Gaseous Effluent Monitoring Instrumentation .. 111 Table 3:3.7.10-1 Radioactive Gaseous Effluent Monitoring Instrumentation ...:. .;. .,......:........:....;.....  : 112 Table 4.3.7.10-1 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements *..!......,. ....: 115 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS ' ^ -

Concentration ......:....:......,:;.....,.....: ......,../.. ......: ...:..:...:..: ........,; 118 Table 4.11.1.1.1-1 Radioactive Liquid Waste Sampling and Analysis Program..... , 119 Dose .......-  ;*****;' ***

• 122 Liquid Radwaste Treatment System 123 3/4.11.2 GASEOUS EFFLUENTS Dose Rate ,.;. ...:.;.a;....;.. ....:.,......'. 124 <;

Table 4.11.2.1.2-1 Radioactive Gaseous Waste Sampling and Analysis Program .:;......,......; 125 Dose- Noble Gases../. 128 Dose - lodine-131, lodine-133, Tritium and Radionuclides in Particulate Form... .129 Gaseous Radwaste (Off-Gas) Treatment  :.. 130 Ventilation Exhaust Treatment Systems ,, ...:..... ..****** ***131 3/4.11.4 TOTAL DOSE. * .,..:...u. 1.32 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM  ;.....;.  :.... ...;.,:..U.,.;'J....:..:.: -.:.: 133 Table 3.12.1-1 Radiological Environmental Monitoring Program..... 135 Table 3.12.1-2 Reporting Levels for Radioactivity Concentrations  ;"

In Environmental Samples 140

' :\ Table 4.12.1-1 Maximum Values for the Lower Limits of Detection v.

(LLD) In Environmental Samples  !....; -141 PERRY - UNIT 1

ODCM Page: 87 Rev.: 23 CONTROLS AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4,121.2 LAND USE CENSUS... 144 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 145 BASES 3/4.0 APPLICABILITY ,-. j ..- ,.,  :.... 147 3/4.3 INSTRUMENTATION  :

Radioactive Liquid Effluent Monitoring Instrumentation 155 Radioactive Gaseous Effluent Monitoring Instrumentation..... ........t.................... 155 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration .-:. 156 Dose ,.,....; 156 Liquid Radwaste Treatment System 157 3/4J1.2 GASEOUS EFFLUENTS Dose Rate .' f58 Dose- Noble Gases  :  :............. -.-....'  ;... 158 Dose - lodine-131, lodine-133, Tritium and Radionuclides in Particulate Form .........;.; .-. .159

. Gaseous Radwaste Treatment (Offgas) System and Ventilation Exhaust Treatment Systems....,, 160 3/4.11.4 TOTAL DOSE , ,...,'..,.,..,  : , 160 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM , 161 3/4.12.2 LAND USE CENSUS  :,...,..,.'. i;. . 161 3/4,12.3 INTERLABORATORY COMPARISON PROGRAM  :...... ...;. 161 ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS 6.9.1.6 Annual Radiological Environmental Operating Report .......,......: 163 6.9.1.7 Annual Radioactive Effluent Release Report .....: 164 6.9.2 SPECIAL REPORTS., ,.. , ,....,....-.: .... 165 6.10 RECORD RETENTION ...  !'...'...>. * * ....., ;....., 165 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 166 PERRY - UNIT 1 ii

ODCM Page: 88 Rev.: 23 SECTION 1,0 DEFINITIONS

ODCM Page: 89 Rev.: 23 10 DEFINITIONS v The following terms are defined so that uniform interpretation of these Controls may be achieved. The defined terms appear in capitalized type and shall be applicable throughout these Controls.

ACTIONS ACTIONS shall be that part of a Control that prescribes remedial measures to be taken under designated conditions.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping or total channel steps so that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131,1-132,1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989.

PERRY - UNIT 1 1-1

ODCM Page: 90 Rev.: 23 DEFINITIONS FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.  :

GASEOUS RADWASTE TREATMENT (OFF-GAS) SYSTEM The GASEOUS RADWASTE TREATMENT (OFF-GAS) SYSTEM is the system designed arid installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gasses from the main condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. .-..-.

LIQUID RADWASTE TREATMENT SYSTEM i The LIQUID RADWASTE TREATMENT SYSTEM is any process or control equipment used to reduce the amount or concentration of liquid radioactive materials prior to their discharge to UNRESTRICTED AREAS. It involves all the installed and available liquid radwaste management system equipment, as well as their controls, power instrumentation, and services that make the system functional.

MEMBER OF THE PUBLIC MEMBER OF THE PUBLIC means any individual except when that individual is receiving an OCCUPATIONAL DOSE.

MODE ,

A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.2 with fuel in the reactor vessel.

OCCUPATIONAL DOSE OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under § 35.75, from voluntary participation in medical research programs, or as a member of the public.

PERRY - UNIT 1 1-2

ODCM Page: 91 Rev.: 23 DEFINITIONS OFFSITE DOSE CALCULATION MANUAL (ODCM) - . * ' ,

The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and.parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the radiological environmental monitoring program. The ODCM shall also contain the Radioactive Effluent Controls Program required by Technical Specification 5.5.4, the Radiological Environmental Monitoring Programs and descriptions of the information that should be included in the Annual Radioactive Effluent Release Report required by Technical Specifications 5.6.2 and 5.6.3.

OPERABLE - OPERABILITY A system, subsystem, division, component or device shall be OPERABLE or have OPERABILITY when.it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, division, component or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure,,humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of

.3758 MWT.  : v REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in 10CFR50 73.

SITE BOUNDARY -, 4 r  :

The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. .

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

PERRY - UNIT 1 1-3

ODCM Page: 92 Rev.: 23 THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of MEMBERS OF THE PUBLIC from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEMS A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components provided the ESF system is not utilized to treat normal releases.

VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

PERRY - UNIT 1 1-4

ODCM Page: 93 Rfev.: 23 TABLE 1.1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY r

S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

0.  ; At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days. -

SA , At least once per 184 days.

A , At least once per 366 days.

R At least once per 24 months.

S/U Prior to each reactor startup.

P' :

• Completed prior to each release.

4H  ! ,. . , , Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when required.

N.A. Not aDDlicable PERRY - UNIT 1 1-5

ODCM Page: 94 Rev.: 23 TABLE 1.2 MODES REACTOR MODE AVERAGE REACTOR MODE TITLE SWITCH POSITION COOLANT TEMPERATURE 1 POWER OPERATION Run NA 2 STARTUP Refuel (a) or Startup/Hot NA Standby 3 HOT SHUTDOWN (a) Shutdown > 200°F COLD SHUTDOWN (a) Shutdown < 200°F REFUELING (b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

(b) One or more reactor vessel head closure bolts less than fully tensioned.

PERRY - UNIT 1 1-6

ODCM Page: 95 Rev.: 23 SECTIONS 3.0 and 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS

ODCM Page: 96 Rev.: 23 3/4.0 APPLICABILITY 3.0.1 Controls shall be met during the MODES or other conditions specified in the Applicability except as provided in Control 3.0.2.

3.0.2 Upon discovery of a failure to meet a Control, the requirements of the Actions shall be met except as provided in Control 3.0.5. If the Control is met or is no longer applicable prior to expiration of the specified time interval(s), completion of the Action(s) is not required, unless otherwise stated:

3.0.3 When a Cdntrolis not met and the associated ACTIONS are not met, ah associated ACTidN is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the Control is not applicable. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in: v

a. MODE 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />;

b. MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and sc. MODE 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.

Exceptions to this Control are stated in the individual Controls.

Where corrective measures are completed that permit operation in accordance with the Control or >

ACTIONS, completion of the actions required by Control 3.0.3 is not required. ',:

Control 3.0.3 is only applicable in MODES 1,2, and 3.  ; ",

3.0.4 When a Control is not met, entry into a MODE or other specified condition in the Applicability shall only be made:: -;>>':. . ,. . .. .

a. When the associated ACTIONS to;be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Control are stated in the individual Controls, or c: When an allowance is stated in the individual value, parameter, or other Control.

This Control shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS, or that are part of a shutdown of the unit.

PERRY - UNIT 1 3/4 0-1

ODCM Page: 97 Rev.: 23 3/4.0 APPLICABILITY CONTROLS (Continued) 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to Control 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY:

SURVEILLANCE REQUIREMENT (SR) 4.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual Controls, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the surveillance or between performances of the Surveillance, .

shall be failure to meet the Control. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the Control except as provided in SR 4.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. r 4.0.2 The specified frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the frequency, as measured from the previous performance or as measured from the time a specified condition of the frequency is met.

If a completion time for an action requires periodic performance on a "once per..." basis, the above frequency extension applies to each performance after the initial performance.

Exceptions to this SR are stated in the individual SR's.

4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the Control not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is less. This delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the Control must immediately be declared not met, and the applicable ACTION(s) must be entered. When the Surveillance is performed within the delay period and the Surveillance is not met, the Control must immediately be declared not met, and the applicable ACTION(s) must be entered..

4.0.4 Entry into a MODE or other specified condition in the Applicability of a Control shall only be made when the Control's Surveillances have been met within their specified frequency, except as provided by Surveillance Requirement 4.0.3. When a control is not met due to Surveillances not having been met, entry into a MODE or other specified Condition in the Applicability shall only be made in accordance with Control 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

PERRY - UNIT 1 3/4 0-2

ODCM Page: 98

\ Rev.: 23 3/4.3 INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.9 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.9-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION: . .";..

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.9-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

c. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.9-1.

PERRY - UNIT 1 3/4 1-1

ODCM " Rev!: 23 Page: 99 TABLE 3.3.7.9-1 -;

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Discharge Radiation Monitor - . . 110 ESW Discharge

2. ^ GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Emergency Service Water Loop A Radiation Monitor 111

b. Emergency Service Water Loop B Radiation Monitor 111 c Service Water Radiation Monitor (ADHR) 111

3. FLOW RATE MEASUREMENT DEVICES

a. Radwaste High-Flow Discharge Header Flow 112

b. Service Water Discharge Header Flow Monitor 113

, c. Unit 1 Emergency Service Water Header Flow Monitor or 113 individual ESW HX Monitors

1) Emergency Service Water Flow Monitor, or

2) Individual RHR, ECC and DG HX Flow Monitors PERRY - UNIT 1 3/4 1-2"

ODCM Page: 100 Rev.: 23 TABLE 3.3.7.9-1 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 110 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from this pathway may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Control 4.11.1.1.1, and , . . ,

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valve lineup; Otherwise, suspend release of radioactive effluents via this pathway; ACTION 111- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 107 uCi/ml.

ACTION 112 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the

, discharge valve position is verified to be consistent with the flow rate provisions of the release permit at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Prior to initiating another release, at least two technically qualified members of the Facility Staff shall independently verify the discharge line valve lineup and that the discharge,valve position corresponds to the desired flow rate. Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 113 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves generated in place as well as other curves generated using pump performance may be used to estimate flow.

PERRY - UNIT 1 3/4 1-3

ODCM Rev.: 23 Page: 101

,  ; TABLE 4.3.7.9-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FLOW SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CHECK CALIBRATION TEST

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Discharge Radiation N.A. R(3)

' Monitor'- ESW Discharge

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Emergency Service Water Loop A Radiation Monitor D N.A. M ..-, R(3) Q(2)

b. Emergency Service Water Loop B Radiation Monitor D N.A. M R(3) Q(2)

c. Service Water Radiation Monitor (ADHR)(6) D N.A. M R(3) Q(2)

3. FLOW RATE MEASUREMENT DEVICES

a. Radwaste High-Flow Discharge Header Flow D(4) N.A. N.A: R Q

b. Service Water Discharge Header Flow D(4) N.A. N.A. R Q

c. " Unit 1 Emergency Service Water Header Fiow

1) Emergency Service Water Flow, or D(4) N.A. NA . . R Q

2) Combination of Individual RHR, ECC & D(4) 4H(5) N.A: N.A. N.A.

DG HX Flows

3) Individual RHR, ECC, & DG HX Flows N.A. N.A. N.A.

PERRY - UNIT 1 3/4 1-4

ODCM Page: 102

' Rev.: 23 TABLE 4.3.7.9-1 (Continued) *'..

RADIOACTIVE LIQUID EFFLUENT MONITORING  :

INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Instrument indicates a downscale failure. i

3. Instrument controls not set in operate mode except in high voltage position.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation

'*"* occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.

2. Instrument indicates a downscale failure.

3. Instrument controls not set in operate mode, except in high voltage position.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow. A CHANNEL CHECK shall be made initially and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days when continuous, periodic or batch releases occurs.

Pump performance curves may be used to verify the indication of flow from flow instrumentation.

(5) FLOW CHECK shall consist of verifying indication of flow by summing the individual RHR, ECC and DG heat exchanger flows. A FLOW CHECK shall be made initially, prior to securing E^W pumps, at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during a Liquid Radwaste discharge, and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during operation of ESW pumps.

(6) Surveillance requirements are in effect only when the system is in service.

PERRY"- UNIT 1 3/4 1-5

ODCM

. " . Page: 103

^ J Rev.: 23 INSTRUMENTATION i v RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.10 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.a, the radioactive gaseous effluent monitoring instrumentation channels shown .'in Table 3.3.7.10-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The alarm/trip setpoints of applicable channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3.7.10-1 ACTION: ,. ,

a. '; With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint .

less conservative than required by the above specification, declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report. l ^

c. The provisions of Control 3.0.3 are not applicable. , . ,.

SURVEILLANCE REQUIREMENTS V 4.3.7.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.

PERRY - UNIT 1 3/4 1-6

ODCM  ;

• Rev.: 23 Page:-104 TABLE 3.3.7.10-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. OFF-GAS VENT RADIATION MONITOR

a. Noble Gas Activity Monitor 121,124

b. Iodine Sampler <1> 122

c. Paniculate Sampler w 122

d. Effluent System Flow Rate Monitor 123

e. Sampler Flow Rate Monitor (Victoreen Flow Monitor) 1 *123 '

2. UNIT 1 VENT RADIATION MONITOR

a. Noble Gas Activity Monitor 1 1,2,3 1 ' 121,124,125 4,5 121,124

b. Iodine Sampler i1' * '.- 122 *

• ,'. '" 122

c. Particulate Sampler <1>

• - *-. > * ' 123 '

d. Effluent System Flow Rate Monitor 123

e. Sampler Flow Rate Monitor (Victoreen Flow Monitor) 1 PERRY - UNIT 1 3/4 1-7

ODCM Rev.: 23 Page: 105 TABLE 3.3.7.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTIO[N

3. UNIT 2 VENT RADIATION MONITOR

a. Noble Gas Activity Monitor 1 . * ...:-. 121, 124

b. Iodine Sampler <1> 1 122

c. Paniculate Sampler <1> 1 122

d. Effluent System Flow Rate Monitor 1 ' . * * '. 123

e. Sampler Flow, Rate Monitor (Victoreen Flow Monitor) 1

• 123

4. TURBINE BUILDING/HEATER BAY VENT RADIATION MONITOR

a. i Noble Gas Activity Monitor , 1

• 121,124

b. Iodine Sampler <1> 1

• 122

c. Paniculate Sampier <*> 1

• 122

d. Effluent System Flow Rate Monitor 1

• 123

e. Sampler Flow Rate Monitor (Victoreen Flow Monitor) 1 * - 123 PERRY - UNIT 1 j 3/4 1-8

ODCM Page: 106 Rev.: 23 TABLE 3.3.7.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION (1) This encompasses the isokinetic and Victoreen photohelics

• At all times ACTION 121 - With the number of channels OPERABLE less than required by the Minimum Channels 1 OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for principal gamma emitters as required by Table 4.11.2.1.2-1.

ACTION 122 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with auxiliary sampling equipment as required by Table 4.11.2.1.2-1. If the inoperability is due to failure of the AMC skid, the Victoreen skid alone can be used as the auxiliary sampling equipment for a maximum of 30 consecutive days. Loss of the isokinetic flow monitor constitutes inoperability of particulate and iodine channels (b, c).

ACTION 123 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent release via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This action applies to both the effluent system flow and Victoreen sample flow (d, e).

ACTION 124 - With the 1H13-P680 panel annunciator for noble gas channels locked in due to a

, downscale condition on the radiation monitoring panel, the affected noble gas monitor Channels shall be verified in the Control Room at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to ensure that no unmonitored high or alert level alarms are present. . ,.

ACTION 125 - With the number of channels OPERABLE less than required bythe Minimum Channels OPERABLE requirement, except as a result of a non-conservative setpoint or within the criteria specified in Action 126, immediately suspend operation of the Containment Vessel and Drywell Purge (M14) system. Priorto resuming M14 System operation, ensure compliance with Control 3.11.2.1 requirements. If Control 3.11.2.1 compliance is met, operation of the M14 System may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzed for principal gamma emitters, as required by Table 4.11.2.1.2-1.

ACTION 126 - For periods of planned maintenance or performance of surveillance requirements in support of the requirements listed in Table 4.3.7.10-1, which will reduce the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, compliance with Control 3.11.2.1 may be verified prior to reducing the number of OPERABLE channels below the requirement. If Control 3.11.2.1 compliance is met, operation of the M14 System need not be suspended for the channel provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzed for principal gamma emitters, as required by Table 4.11.2.1.2-1.

PERRY - UNIT 1 3/4 1-9

ODCM Rev.: 23 c' Page: 107 TABLE 4.3.7.10-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

1. OFFGAS VENT RADIATION MONITOR

a. Noble Gas Activity. Monitor D , . . M RW

b. Iodine Sampler W<3>  ; N.A. . N;A. N.A.

c- ParticulateSampler - , W(3) N.A. N.A. . N.A.

d. Effluent System Flow Rate Monitor D N.A. R

• rr- ' : Q

e. . Sampler Flow Rate Monitor D N.A. R Q

2. UNIT 1 VENT RADIATION MONITOR

a. Noble Gas Activity Monitor D M R(2) Q(1)

b. Iodine Sampler W<3> N.A. N.A. N.A

. c. Particulate Sampler Wt3) . N.A. ; N.A. N.A

d. Effluent System Flow Rate Monitor D ' 'N.A. R Q

e. Sampler Flow Rate Monitor D . N.A. R Q PERRY - UNIT 1 3/4 1-10

ODCM , Rev.: 23;,.  ;  ;..,,, Page: 108 TABLE 4.3.7.10-1 (Continued) ' '

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

3. UNIT 2 VENT RADIATION MONITOR J

^ a. Noble Gas Activity Monitor D M; ;r<2) .. q(id na ;

b. Iodine Sampler NA NA ;

c. Paniculate Sampler w<3> N.A. NA. NA

d. Effluent System Flow Rate Monitor D NA ', R Q

e. Sampler Flow Rate Monitor D NA R Q

4. TURBINE BUILDING/HEATER BAY VENT RADIATION MONITOR

a. Noble Gas Activity Monitor D M R(2) Q(D

b. Iodine Sampler W<3) N.A. NA. N.A

c. Particulate Sampler W?) NA NA. N.A

d. Effluent System Flow Rate Monitor D NA R Q

e. Sampler Flow Rate Monitor D NA R Q PERRY - UNIT 1 3/4 1-11

ODCM Page: 109 Rev.: 23 TABLE 4.3.7.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION

• At all times ,

\

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs jf any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpdint.

. 2., Instrument indicates a downscale failure.

3. Instrument controls not set in operate mode.

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial Calibration shall be used.

(3) The iodine cartridges and particulate filters will be changed at least once per 7 days. Performance of this CHANNEL CHECK does not render the system inoperable, and the applicable ACTION statements need not be entered.

PERRY - UNIT 1 3/4 1-12

ODCM Page: 110 Rev.: 23 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with Perry Nuclear Power Plant TS 5.5.4.b and c, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 3.2-1) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved and entrained noble gases, the concentration shall be limited to 2 x 10"4 uCi/ml total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS  ?

4.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 4.11.1.1.1-1. The results of pre-release analyses shall be used with thev calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 3.11.1.1.

4.11.1.1.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4.11.1.1.1-1. The results of the radioactivity analysis shall be used in accordance with the .methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.

4.11.1.1.3 Continuous releases of radioactive liquid effluents shall be sampled and analyzed in accordance with Table 4.11.1.1.1-1. The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.

PERRY - UNIT 1 3/4 2-1

ODCM Page: 111 Rev.: 23 TABLE 4.11.1.1.1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Lower Limit Liquid Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (LLD)

(nCi/ml)a A. Batch Waste . P P Principal Gamma 5x10-7 Release Tanks0 Each batch Each batch Emittersd .

1-131 1x10-6 P M Dissolved and 1x10-5 One Batch/M Entrained Gases (Gamma emitters)

.' P ,  : M H-3' , 1x10-5 Each Batch Composite13 Gross Alpha 1x10-7 P Q Sr-89, Sr-90 5x10-8 Each Batch Composite6 Fe-55 1x10"6 B. Continuous D W Principal Gamma ,:i 5x10-7 ReleaseseRHR Grab Compositebf Emittersd Heat x Sample^- h Exchanger ESW Outlet, 1-131 1x10-6 M35 Drains, or Service 1 Water* Ms- M Dissolved and 1x10"5 Grab Sample Entrained Gases (Gamma emitters)

D M H-3 1x10-5 Grab Samples- Compositeb Gross Alpha ^ 1x10"7 D Q Sr-89, Sr-90 5x10-8 Grab Samples- Composite"^-

Fe-55 1x106 PERRY - UNIT 1 3/4 2-2

ODCM Page: 112

! Rev.: 23 TABLE 4.11.11:1 -1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION ,

a. The LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.  :

For a particular measurement system (which may include radiochemical separation):

'- '

• 4.66Sb '  :..'. .'.-* '

LLD =

(E)(v)[2.22xlO6](Y)exp(- XAt)

Where: ..('.

LLD is the "a priori" lower limit of detection as defined above (as jiCi per unit mass or volume).  ; '.'.:.

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E  : is the counting efficiency (as counts per disintegration) .'..-

V is the sample size (in units of mass or volume) ~

2.22 x 106 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)

X . is the radioactive decay constant for the particular radionuclide (sec-1)

At is the elapsed time between sample collection (or end of the sample collection period) and time.of counting (sec) .

Typical values of E, V, Y and At should be used in the calculation.

PERRY - UNIT 1 3/4 2-3

i ODCM Page: 113 Rev.: 23 TABLE 4.11.1.1.1-1 (Continued)

RADIOACTIVE LIQUID. WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued)

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. A composite sample may also be obtained from liquid batches of similar origin that are not discharged as these liquid batches are expected to be representative of samples that could be discharged. Composite samples for batch liquids that were not released is performed to provide non-gamma emitting isotopic values to verify other batches are within limits prior to release when recent non-gamma emitting isotopic values for discharged liquids are not available.

c. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling:

d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 5x106. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Annual Radioactive Effluent Release Report pursuant to Control 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

e. A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., from a volume of a system that has an input flow during the continuous release. Sampling/Analysis of RHR Heat Exchanger is only applicable when there is ESW flow through the RHR Heat Exchanger. ^

f. Sampling and analysis is required of the RHR heat exchanger ESW outlet every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the samples indicate levels greater than'LLD.

g- Sampling is only required for M35 drains, when the M35 drains have been lined up to storm drains. If activity other than tritium or naturally occurring isotopes is detected in the M35 drains, then these drains shall be lined up to radwaste

h. Sampling/Analysis of Service Water is only applicable when there is Service Water flow through the ADHR Heat Exchanger.

> i .

PERRY - UNIT 1 3/4 2-4 . . v.

ODCM Page: 114 Rev.: 23 RADIOACTIVE EFFLUENTS V

DOSE HONTROI S 3.11.1.2 In accordance with Perry Nuclear Power Plant Unit i TS 5.5.4.d and e, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 3.2-1) shall be limited:

a. During the current quarter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ; and '

b. During the current year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times. -  :

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the corrective actions to be taken to ensure that future releases will be in compliance with the above limits.

b. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents for the current quarter and the current year shall be determined in accordance with the methodology and parameters of the ODCM at least once per 31 days.

PERRY;,- UNIT 1 3/4 2-5

ODCM Page: 115 Rev.: 23 RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM CONTROLS ,

3.11.1.3 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.f, the LIQUID RADWASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of the system shall be used to reduce the release of radioactivity when the projected doses due to the liquid effluent from each reactor unit to UNRESTRICTED AREAS (see Figure 3.2T1) would exceed 0r06 mrem to the whole body or.

0.2 mrem to any organ, in a 31-day period.

APPLICABILITY: At all times. ,, .-.,*

ACTION: . . -

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, and any portion of the liquid radwaste treatment system not in operation, prepare and submit to the Commission, within 30 days pursuant to Control 6.9.2, a Special Report which includes the following information:

1.. Explanation of why liquid radwaste was being discharged without,treatment, identification of any inoperable equipment or subsystems, and the reason for the

inoperability, and

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with methodology and parameters in the ODCM.

4.11.1.3.2 The installed LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.

PERRY - UNIT 1 3/4 2-6

ODCM Page: 116 Rev.: 23 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 3.11.2.1 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.C and g, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to the whole body and less than or equal to 3000 mrem/yr to the skin, and

b. For all iodine-131, ipdine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ. . .-....-.

APPLICABILITY: At all times.  ! . ^

ACTION: ,.._

With the dose rate(s) exceeding the above limits, immediately decrease the release rate(s) to within the above limit(s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases, in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM:

4.11.2.1.2 The dose rate due to iodine-131, iodine-133; tritium and to radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the, ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1. ,

PERRY - UNIT 1 3/4 2-7

ODCM Rev.: 23 Page: 117 TABLE 4.11.2.1.2-1 - . -. .

FRADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION (LLD) <a>

GASEOUS RELEASE PATH FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/mL)

A. Containment Vessel and Each PURGE '" Each PURGE*) Principal Gamma 1x10^*

Drywell Purge (M14) and VENT and VENT Emitters <e>

System, and Combustible Grab Sample Gas Control (M51) System M

Grab Sample M H-3 1X1CT6 B. Offgas Vent, Unit 1 Vent, Unit 2 Vent, and Turbine M

Grab Sample MO) Principal Gamma Emitters <be> , ;* ,

1X10"4 Bldg/Heater

) ' "

Bay Vent H-3 1X10"6 C. All Release Paths as listed in B above' Continuous (d>>

Charcoal Sample 1-131 1X10"12 1-133 ixio-1o;;

Continuous <d>> W<c)

Particulate Sample Principal Gamma Emitters<e>

1X10-11 Continuous <d> M Composite Particulate Filter Gross Alpha

- 1X10"11 Continuous <d) Q Sr-89, Sr-90 1X10"11 Composite Particulate Filter Continuous(d) Noble Gas ;

Monitor Noble Gases Gross Beta or Gamma 1X10"6 (Xe-133 equivalent)

PERRY - UNIT 1 3/4 2-8

ODCM Page: 118

, Rev.: 23 TABLE 4.11.2,1.2-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION

a. The LLD is the smallest cohcentration of radibactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.  : >

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.  ; : ?

For a particular measurement system (which may include radiochemical separation):

4:66 S^: .-...*:; i ..'**.. ,:..:.,

LLD =

(e ) (v) f2.22 x 106l (y) exp'(- I At)

Where:

LLD isjhe "a priori" lower limit of detection as defined above (as jxCi per unit mass or volume). ,  : '/...*

sb ,. is.the standard deviation of the background counting rate or of the counting rate

, of a blank sample as appropriate (as counts per minute) . ,;

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 x 10? is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)

X is the radioactive decay constant for the particular radionuclide (sec-1)

At is the elapsed time between sample collection (or end of the sample collection

.period) and time of counting (sec) ,  :>.,

Typical values of E, V, Y and At should be used in the calculation.  :

PERRY - UNIT 1 3/4 2-9

ODCM Page: 119 Rev.: 23 TABLE 4.11.2.1.2-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued)

b. Analyses shall also be performed following startup, shutdown, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. r <

c. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampler. Sampling and analyses shall also be performed at least daily (> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply if:

(1) Analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) The noble gas monitor shows that effluent activity has not increased more than a factor of 3.

If the noble gas monitor is not operable, then a grab sample may be used to demonstrate that activity has not increased by a factor of 3.

d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Control 3.11.2.1, 3.11.2.2 and 3.11.2.3.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions

/ and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,1-131, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Annual Radioactive Effluent Release Report pursuant to Control 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

f. Sampling and analysis of gaseous release points shall be performed initially whenever a high alarm setpoint is exceeded or whenever two or more of the alert setpoints are exceeded. If the high alarm setpoint or two or more of the alert setpoints continue to be exceeded, verify at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> via the radiation monitors that plant releases are below the Control 3.11.2.1 dose rate limits and sampling and analysis shall be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

PERRY - UNIT 1 3/4 2-10

ODCM Page: 120 Rev.: 23 RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES CONTROLS 3.11.2.2 In accordance with Perry Nuclear Power Plant Uhit 1 TS 5.5.4.e and h, the air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) shall be limited to the following: >

a. During the current quarter: Less than or equal to 5 mrad for gamma radiationand less than or equal to 10 mrad for beta radiation; and

b. During the current year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation. ' ^

APPLICABILITY: At all times.

ACTION: * << "  ! ' '

a. With the calculated air dose from the radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and

' defines the corrective actions to be taken to ensure that future releases will be in compliance with Control 3.11.2.2.

b. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations. Cumulative dose contributions for noble gases for the current quarter and current year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. .  :

PERRY - UNIT 1 ' -3/4 2-11

ODCM Page: 121 Rev.: 23 RADIOACTIVE EFFLUENTS .*:.-.,

DOSE - IODINE-131. IODINE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.e and i, the dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) shall be limited to the following: ,

a. During the current quarter: Less than or equal to 7.5 mrem to any organ; and

b. During the current year: Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of iodine-131, iodine-133, tritium and radionuclides in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to ensure that future releases will be in compliance with Control 3.11.2.3.

b. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations. Cumulative dose contributions from iodine-131, iodine-133, tritium and radionuclides in; particulate form with half-lives greater than 8 days for the current quarter and current year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

• PERRY - UNIT 1 3/4 2-12

ODCM Page: 122 Rev.: 23 RADIOACTIVE EFFLUENTS GASEOUS RADWASTE (OFF-GAS) TREATMENT CONTROLS 3.11.2.4 The GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM shall be in operation*, the Charcoal bypass mode shall hot be'used unless the off-gas post-treatment radiation monitor is OPERABLE  ;

APPLICABILITY: Whenever the main condenser air ejector evacuation system is in operation.

ACTION:

a. With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 consecutive days, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which includes the following information:

• ' 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for inoperability.

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 The readings of relevant instrumentation shall be checked at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the main condenser air ejector is iri use to ensure that the gaseous radwaste treatment system is functioning.

• Flow directed through the adsorber beds.

PERRY - UNIT 1 / 3/4 2-13

ODCM Page: 123 Rev.: 23 RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEMS CONTROLS 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEMS shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected dose due to gaseous effluent releases from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) in a 31 day period would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times. -

ACTION:

a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to

.-._* Control 6.9.2, a Special Report which includes the following information: ..

. 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence..

b. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS

. . -- ^ . . . .

4.11.2.5.1 Doses due to gaseous releases from each reactor unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEMS shall be demonstrated OPERABLE by meeting Controls 3.11.2.1 and 3.11.2.3.

PERRY - UNIT 1 3/4 2-14

ODCM Page: 124 Rev.: 23 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4J, the current year dose or dose commitment to any MEMBER of THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. .

APPLICABILITY: At all times.

ACTION: < **'-"

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3,11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b.,

3.11.2.3a, or 3.11.2.3b., calculations shall be made including direct radiation contributions from the reactor units, from the ISFSI and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded:

1. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.

2. This Special Report, as defined in 10CFR20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the current year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

3. i If the estimated dbse(s) exceeds the above limits, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR190.

Submittal of the report is considered a timely request, and a variance is granted until

': staff action on the request is complete.  ;

b. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS _

4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.1 i.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM. '>,'<

4.11.4.2 If the cumulative dose contributions exceed the limits defined in 3.11.4, ACTION a, cumulative dose contributions from direct radiation from unit operation including from the ISFSI and outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM.

PERRY - UNIT 1 ' 3/4 2-15

ODCM Page: 125 Rev.: 23 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1, . , * . , ,-. , ,

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Environmental and Effluent Release Report per Control 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over the current quarter, prepare and submit to the Commission within 30 days pursuant to Control 6.9.2 a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the current year limits of Control 3.11.1.2, 3.11.2.2 and 3.11.2.3. When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) +... >1.0 reporting level (1) . reporting level (2)

When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC is equal to or greater than the current year limits of Control 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the annual Radiological Environmental Operating Report required by Control 6.9.1.6.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report. ,

PERRY - UNIT 1 3/4 3-1

ODCM Page: 126 Rev.: 23 RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS

c. With milk or broad leaf vegetation samples unavailable from one or more of the sample locations required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Control 6.9.1.7, submit in the next Annual Radiological Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the

- selection of the new locatioh(s) for obtaining samples.

d. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figures in the ODCM and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.

PERRY - UNIT 1 3/4 3-2

ODCM Rev.: 23 Page: 127 TABLE 3.12.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM*

Number of Samples Exposure Pathway ' and <*> Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis

1. Direct Twenty-nine routine monitoring stations Quarterly Gamma dose quarterly Radiation*2' either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, NNE, NNW, NW, W, WNW), in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, NE, NNE, NNW, NW, W, WNW), in the 6- to 8-km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations PERRY - UNIT 1 3/4 3-3

ODCM " Rev.: 23 Page: 128 TABLE 3:12.1-1 (Continued) r RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples \

Exposure Pathway and'1' Sampling and Type and Frequency and/or Sample- Sample Locations.." Collection Frequency of Analysis

2. Airborne Radioiodine and Samples from five locations:  !' Continuous sampler operation Radioiodine Canister:

Paniculate with sample collection weekly, 1-131 analysis weekly Three samples from close to the three SITE or more frequently if required by

'". BOUNDARY locations; in different sectors, dust loading of the highest calculated annual average ' Particulate Sampler:

ground-level D/Q; Gross beta radioactivity analysis following filter replacement <3>;

One sample from the vicinity of a and gamma isotopic analysis <4>

community having the highest calculated of composite (by location) annual average ground-level D/Q; and quarterly One sample from a control location, as for

> example 15 to 30 km distant and in the least prevalent wind direction

3. Waterborne

a. Surface - Two samples Composite sample over a Gamma isotopic analysis(4) 1-month period (5> r .monthly. Composite for tritium analysis quarterly PERRY - UNIT 1 3/4 :5-4

ODCM Rev.: 23 Page: 129 TABLE 3.12.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and<)> Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis -.

3. Waterborne (Continued)

b. Drinking One sample of each of one to three of the Composite sample over 2-week 1-131 analysis on each nearest water supplies that could be period (5) when 1-131 analysis is composite when the dose affected by its discharge performed; monthly composite calculated from the consumption

^ otherwise of the water is greater than One sample from a control location 1 mrem per year(6>. Composite for gross beta and gamma isotopic analyses <4> monthly.

Composite for tritium analysis quarterly Sediment One sample from area with existing or Semi-annually Gamma isotopic analysis <4>

from potential recreational value semi-annually shoreline

4. Ingestion V

a. Milk Samples from milking animals in three Semi-monthly when animals are Gamma isotopic analysis(4> and locations within 5 km distance having the on pasture; monthly at other 1-131 analysis semi-monthly, highest dose potential. If there are none, times when animals are on pasture; then one sample from milking animals in monthly at other times each of between 5 to 8 km distant where doses are three areas calculated to be greater than 1 mrem per yr <6>>. One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.

PERRY - UNIT 1 . 3/4 3-5

ODCM . Rev.: 23 Page: 130 TABLE 3.12.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway .-. and<1> Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis

4. Ihgestion (Continued)

b. , Fish and One sample of each commercially and One.sample in season or ... Gamma isotppic analysis <4) on Invertebrates recreationally important species (if seasonal) in semiannually if they are not edible portions vicinity of plant discharge area " ^ seasonal One sample of same species in areas not influenced by plant discharge c' Food Sample of three different kinds of broad leaf Monthly during growing season Gamma isotopic analysis <4> and Products vegetation grown nearest each of two different  ;  ; 1-131 analysis offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed One sample of each of the similar broad leaf Monthly during growjng season ', Gamma isotopic analysis <4> and vegetation grown 15 to 30 km distant in the least ...... .1-131 analysis

' prevalent wind direction if milk sampling is not

• ' performed  :

PERRY - UNIT 1 3/4 3-6

ODCM Page: 131 Rev.: 23 TABLE 3.12.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS

• Sample locations are given on the figure and the table in the ODCM.

(1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal; unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made with 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to Control 6.9.1.7, submit in the next annual Radioactive Effluent Release Report documentation for a change in the ODCM, including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location(s) for obtaining samples.

(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. (The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.)

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(5) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(6) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

PERRY - UNIT 1 3/4 3-7

ODCM Rev.: 23 Page: 132 TABLE 3.12.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Water Airborne Particulate Fish " Milk Broadleaf Vegatation Analysis (pCi/L) or Gases (pCi/m3) (pCi/kg,wet) (pCi/L) (pCi/kg, wet) 4a H-3 2x10 N.A. N.A. .. N.A. NA.

Mn-54 1 x103 N.A. 3X104 N.A. N.A.

Fe-59 4X102 N.A. 1 X104 N.A. N.A.

Co-58 1 x 103 N.A. 3 x 104 N.A. N-A  ; -,

Co-60 3x102 N.A. 1 X104 N.A. N.A.

Zn-65 3x102 N.A. 2x10* N.A. VN.A Zr-Nb-95 4 x 102 N.A. N.A. N.A. N.A.

1-131 2b 0.9 - N.A. 3 1 x 102 Cs-134 30 10 1x103 60 .1 x 103 Cs-137 50 20 2x103 70 2x103 Ba-La-140 1 2x102 N.A. N.A. 3x102 N.A aFor drinking water samples. This is a 40CFR141 value: If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

"If no drinking water pathway exists, a value of 20 pCi/L may be used.

PERRY - UNIT 1 3/4 3-8

ODCM , Rev.: 23 Page: 133 TABLE 4.12.1-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

IN ENVIRONMENTAL SAMPLES Airborne Particulate Broad Leaf Analysis . Water. or Gases Fish Milk Vegetation Sediment (pCi/l) (pCi/m3) (pCi/kg, wet) (pCi/l) (pCi/kg,wet) (pCi/kg,wet)

Gross beta 4 1 x 102 N.A. N.A. N.A. N.A.

H-3 2000* N.A. N.A. N.A. N.A. N.A.

c Mn-54 15 N.A. 130 N.A. N.A. N.A.

Fe-59 \ 30 N.A. 260 N.A. N.A. N.A.

Co-58,60 15 n;a. 130 N.A. N.A. N.A.V Zn-65 30 N.A. 260 N.A. N.A. N.A.

Zr-95 30 N.A. N.A. N.A. N.A. N.A.

y Nb-95 15 N.A. N.A. N.A. N.A. N.A.

1-131 1" 7x102 - N.A. 1 60 N.A.

Cs-134 15 5x10"3 130 15 60 150 Cs-137 18 6x102 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A.

La-140 15 N:A. N.A. 15 N.A. N.A.

• lf no drinking water pathway exists, a value of 3000 pCi/l may be used.

• • lf no drinking water pathway exists, a value of 15 pCi/l may be used.

PERRY - UNIT 1 3/4 3-9

ODCM Page: 134 Rev.: 23 TABLE 4.12.1-1 (Continued)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

TABLE NOTATION aAcceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. ,

Table 4.12-1 indicates acceptable detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs): The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiqchemical separation): r 4.66 Sb , .

LLD =

(e ) (v) [2:22 x 106 ] (y) exp (- X At)

Where:

LLD is the "a priori" lower limit of detection as defined above (as ^Ci per unit mass or volume).

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 x 106 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)

A is the radioactive decay constant for the particular radionuclide (sec-1)

At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (sec) i ' .

Typical values of E, V, Y and At should be used in the calculation.

PERRY - UNIT 1 . 3/4 3-10

ODCM Page: 135

Rev.

• 23 TABLE 4.12.1-1 (Continued)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

TABLE NOTATION (continued)

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

Occasionally background fluctuations, unavoidable small sample size, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors should be identified and described in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.

The value of sb used in the calculation of the LLD for a particular measurement system should be based oh the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.

This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.16.

PERRY - UNIT 1 3/4 3-11

ODCM Page: 136 Rev.: 23 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS \

CONTROLS 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation. ^

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, identify the new location(s)*

in the next Annual Radioactive Effluent Release Report, pursuant to Control 6.9.1.7.

b. With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which milk and/or broad leaf vegetation samples are currently being obtained in accordance with Control 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days. If no milk and/or broad leaf vegetation samples are identified in the new sector with the highest D/Q value, then the next sector with the highest D/Q value will be considered and so on until a sampling location can be established. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.* Identify the new location(s) in the next annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table(s) for the ODCM reflecting the new location(s).

c. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census.shall be included in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.

• Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Controls for broad leaf vegetation sampling in Table 3.12.1-1 shall be followed, including analysis of control samples.

PERRY - UNIT 1 3/4 3-12

ODCM Page: 137 Rev.: 23 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS /

\

3.12.3 Analyses shall be performed on radioactive materials that correspond to samples required by Table 3.12.1-1. These materials are supplied as part of an Inter-laboratory Comparison Program.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Environmental and Effluent Release Report pursuant to Control 6.9.1.6.

b. The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Inter-Laboratory Comparison Program shall be included in the annual Radiological Environmental Operating Report pursuant to; Control 6.9.1.6.

PERRY - UNIT 1 3/4 3-13

ODCM Page: 138 Rev.: 23 BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE: The BASES contained in succeeding pages summarize the reasons for the Controls in Section 3.0 and 4.0, but are not part of these Controls.

ODCM Page: 139 Rev.: 23 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY BASES Controls 3.0.1 through 3.0.5 establish the general requirements applicable to Appendix C Controls and apply at all times, unless otherwise stated.

Control 3.0:1 establishes the Applicability statement within each individual control as the requirement for when the Control is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each Control).

Control 3.0.2 establishes that upon discovery of a failure to meet a Control, the associated ACTIONS shall be met. The Completion Time of each ACTION condition is applicable from the point in time that an ACTIONS condition is entered. The ACTIONS establish those remedial measures that must be taken within specified times when the requirements of a Control are not met. This Control establishes that:

a. Completion of the ACTIONS within the specified times constitutes compliance with a Control; and . ' ,

b. Completion of the ACTIONS is not required when a Control is met within the specified time, unless otherwise specified.

There are two basic types of ACTION\requirements. The first type of ACTIONS specifies a time limit in which the Control must be met. This time limit is the time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of ACTION is not completed within the specified completion time, a shutdown may be required to place the unit in a MODE or condition in which the Control is not applicable. (Whether stated as an ACTION or not, correction of the entered condition is an action that may always be considered upon entering ACTIONS.) The second type of ACTION specifies the remedial measures that permit continued operation of the unit that is not further restricted by the completion time. In this case, compliance with the ACTIONS provides an acceptable level of safety for continued operation.

Completing the ACTIONS is not required when a Control is met or is no longer applicable, unless otherwise stated in the individual Control.

The nature of some ACTIONS of some conditions necessitates that, once the condition is entered, the ACTIONS must be completed even though the associated condition no longer exists. The individual Control's ACTIONS specify where this is the case.

PERRY - UNIT 1 B 3/4 0-1

ODCM Page: 140 Rev.: 23 3/4.0 APPLICABILITY RASES (Continued!.

The completion times of the ACTIONS are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to; performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience.

Alternatives that would not result in redundant equipment being inoperable should be used instead.

Doing so limits the time both subsystems/divisions of a safety function are inoperable and limits the time other conditions exist which result in Control 3.0.3 being entered. Individual Controls may specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the completion times of ACTIONS are applicable when this time limit expires, if the equipment remains removed from service or bypassed.

When a change in MODE or other specified condition is required to comply with an ACTION, the unit may enter a MODE or other specified condition in which another Control becomes applicable. In this case, the completion times of the associated ACTIONS would apply from the point in time that the new Control becomes applicable and the ACTIONS condition(s) are entered. J Control 3.0.3 establishes the actions that must be implemented when a Control is not met and:

a. An associated ACTION and completion time is not met and no other condition applies; or

b. The condition of the unit is not specifically addressed by the associated ACTIONS. This

' means that no combination of conditions stated in the ACTIONS can be made that exactly

! corresponds to the actual condition of the unit: Sometimes, possible combinations of conditions are such that entering Control 3.0.3 is warranted; in such cases, the ACTIONS specifically state a condition corresponding to such combinations and also that Control 3.0.3 be entered immediately. -  :

This Control delineates the time limits for placing'the unit in a safe MODE or other specified condition when operation cannot be maintained within the limits for safe operation as defined by the Control arid its ACTIONS. It is not intended to be used as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. '

PERRY - UNIT 1 B 3/4 0-2

ODCM Page: 141 Rev.: 23 3/4.0 APPLICABILITY BASES (Continued)

Upon entering Control 3.0.3,1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to prepare for an orderly shutdown before initiating a .

change in unit operation. This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the .

unit, assuming that only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems under conditions to which this Control applies.

A unit shutdown required in accordance with Control 3.0.3 may be terminated and Control 3.0.3 exited if any of the following occurs:

a. The Control is met.

b. A condition exists for which the ACTIONS have now been performed.

c. ACTIONS exist that do not have expired completion times. These completion times are applicable from the point in time that the condition is initially entered and not from the time Control 3.0.3 is exited.

The time limits of Control 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the unit to be in MODE 4 when a shutdown is required during MODE 1 operation. If the unit is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE applies. If a lower MODE of operation is reached in less time than allowed, however, the total allowable time to reach MODE 4, or other applicable MODE, is not reduced. For example, if MODE 2 is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the time allowed for reaching MODE 3 is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, because the total time for reaching MODE 3 is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Therefore, if remedial measures are completed that would permit a return to MODE 1, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

In MODES 1, 2, and 3, Control 3.0.3 provides actions for conditions not covered in other Controls. The requirements of Cqntrol 3.0.3 do not apply in MODES 4 and 5 because the unit is already in the most restrictive condition required by Control 3.0.3. The requirements of Control 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual, Controls sufficiently define the remedial measures to be taken.

Exceptions to Control 3.0.3 are provided in instances where requiring a unit shutdown, in accordance with Control 3.0.3, would not provide appropriate remedial measures for the associated condition of the unit.

These exceptions are addressed in the individual Controls.

PERRY - UNIT 1 ' ,  ; B 3/4 0-3

ODCM Page: 142 Rev.: 23 3/4.0 APPLICABILITY BASES (Continued^

Control 3.0.4 establishes limitations on changes in MODES of other specified conditions in the Applicability when a Control is not met. It allows placing the Unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability desired to be entered) when unit conditions are such that the requirements of the LCO would not be met, in accordance with Control 3.0.4.a, 3.0.4.b, or 3:0 4.c.

Per Control 3.0.4.a, compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the plant before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the ACTION requirements.

Per Control 3.0.4.b, changes in MODE may be made even if the ACTION requirements include a requirement to exit the Applicability, PROVIDED a risk assessment is performed (and is determined to be acceptable) which addresses the inoperable systems/components, and any appropriate risk management actions are put in place.

The provisions of this control should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before Unit startup.

The provisions of Control 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of Control 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE associated with transitioning from MODE 1 to MODE 2 or 3, MODE 2 to 3, and MODE 3 to 4.

Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, utilizing Control 3.0.4 is not a violation of SR 4.0.1 or SR 4.0.4 for any Surveillances that have not been performed on inoperable equipment.

However, SRs must be met to ensure OPERABILITY priorto declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected Control.

PERRY - UNIT 1 B 3/4 0-4

ODCM Page: 143 Rev.: 23 3/4.0 APPLICABILITY BASES (Continued^

Control 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole ...

purpose of this Control is to provide an exception to Control 3.0.2 (e.g., to not comply with the applicable ACTION(s)) to allow the performance of SRs to demonstrate:

a.  : The OPERABILITY of the equipment being returned to service; or

b. The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the allows SRs. This Control does not provide time to perform any other preventative or corrective maintenance:

SR 4.0.1 through 4.0.5 establish the general requirements applicable to all Controls and apply at all times, unless otherwise stated.

SR 4.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the Control apply, unless otherwise specified in the individual SRs. This Control is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified frequency, in accordance with SR 4.0.2, constitutes a failure to meet a Control.

Systems and components are assumed to be OPERABLE when the associated SRs have been met.

Nothing in this Control, however, is to be construed as implying that systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the SRs; or

b. The requirements of the Surveillance(s) are known to be not met between required Surveillance performances.

Surveillances do not have to be perfonned when the unit is in a MODE or other specified condition for which the requirements of the associated Control are not applicable, unless otherwise specified. The SRs associated with a Special Operations Control are only applicable when the Special Operations Control is used as an allowable exception to the requirements of a Control.

Surveillances, including Surveillances invoked by ACTIONS, do not have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 4.0.2, prior to returning equipment to OPERABLE status.

PERRY - UNIT 1 B 3/4 0-5

ODCM Page: 144 Rev.: 23 3/4.0 APPLICABILITY BASES (Continued)

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 4.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing >

has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.  ;

SR 4.0.2 establishes the requirements for meeting the specified frequency for Surveillances arid, any ACTIONS with a completion time that requires the periodic performance of the ACTION on a "once per.;."

interval:  :  : '  : ->

SR 4.0.2 permits a 25% extension of the interval specified in the frequency. This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).

The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. The exceptions to SR 4.0.2 are those Surveillances for which the 25% extension of the interval specified in the frequency does not apply. These exceptions are stated in the individual Controls.' i

• - ,  : .' ;'.

• v *"* :-** . . '.:'; .;;. - -, .:[' . -.

As stated in SR 4.0.2, the 25% extension also does not apply to the initial portion of a periodic completion time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance. The initial performance of the ACTION, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single completion time. One reason for not allowing the 25% extension to this completion time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.  : . -

The provisions of SR 4.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic '.:

completion time intervals beyond those specified.  ;

PERRY - UNIT 1 B 3/4 0-6

ODCM Page: 145 Rev.: 23 3/4.0 APPLICABILITY BASES (Continued)

SR 4.0.3 establishes.the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified frequency.; A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is.

less, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 4.0.2, and not at the time that the specified frequency was not met. This delay period provides adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with ACTIONS or other remedial measures that might preclude completion of the Survejllance.  ; . ., - . .

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.

When a Surveillance with a frequency based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, SR 4.0,3 allows the full delay period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the Surveillance.

• '"." - -.. . * ' . * * * .' ;\ '

SR 4.0.3 also provides a time limit for completion of Surveillances that become applicable as a consequence of MODE changes imposed by ACTIONS.

Failure to comply with specified frequencies for Surveillance Requirements is expected to be an infrequent occurrence. Use of the delay period established by SR 4.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals.

If a Surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable then is considered outside the specified limits and the completion times of the ACTIONS for the applicable Control conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the completion times of the required ACTIONS for the applicable Control conditions begin immediately upon failure of the Surveillance.

Completion of the Surveillance within the delay period allowed by this Control, or within the completion time of the ACTIONS, restores compliance with SR 4.0.1.;

SR 4.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability, with two exceptions as described in SR 4.0.4.

PERRY - UNIT 1 . B 3/4 0-7

ODCM Page: 146 Rev.: 23 3/4.0 APPLICABILITY RASFS This Control ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit/ .  ;

However, in certain circumstances, failing to meet an SR will not result in SR 4.0.4 restricting a MODE change or other specified condition change. When a system, subsystem/division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 4.0.1, which states that surveillances do not have to be performed on inoperable equipment or variables outside specified limits. When equipment is inoperable, or variables are outside their specified limits, SR 4.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified frequency, on equipment that is inoperable, or on variables that are.outside specified limits, does not result in an SR 4.0.4 restriction to changing MODES or other specified conditions in the Applicability:

However, since the Control is not met in this instance, Control 3.0.4 will govern any restrictions that may (or may hot) apply to MODE or other specified condition changes.

The provisions of this Control should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

The provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE associated with transitioning from MODE 1 to MODE 2 or 3, MODE 2 to 3, and MODE 3 to 4.

The precise requirements for performance of SRs are specified such that exceptions to SR 4.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated Control prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the Control's Applicability would have its frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a note as not required (to be met or performed) until a particular event, condition, or time has been reached.

PERRY - UNIT 1 B 3/4 0-8

ODCM Page: 147 Rev.: 23 3/4.3 INSTRUMENTATION BASES 3/4.3.7 MONITORING INSTRUMENTATION  :

3/4.3.7.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR20. The OPERABILITY and use of this instrumentation is consistent with the requirements of 10CFR50, Appendix A, General Design Criteria 60, 63, and 64.

3/4.3.7.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm will occur prior to exceeding the limits of 10CFR20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of 10CFR50, Appendix A, General Design Criteria 60, 63, and 64.

PERRY - UNIT 1

• B 3/4 1-1

ODCM Page: 148 Rev.: 23 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10CFR20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A. design objectives of 10CFR50, Appendix I, to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20 to the population. The concentration limit for dissolved and entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its limiting effluent concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. .

This Control applies to the release of radioactive materials in liquid effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs) Detailed discussion of the LLD, and other detection limits, can be found in: * -;  ; *  :  ;

(1) Currie, L A.., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 - ,-.

, (September, 1984). -.-.,.* ,-, -..-.,

(2) HASL Procedures Manual. HASL-300 (revised annually).

3/4.11 1.2 DOSE * . . ' .

This Control is provided to implement the requirements of 10CFR50, Appendix I, Sections II.A, III.A and IV.A. The Control implements the guides set forth in of 10CFR50, Appendix I, Section II.A. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in of 10CFR50, Appendix I, Section IV.A which assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR141. The dose calculations in the ODCM implement the requirements in 10CFR50, Appendix I, Section III.A that conformance with the guides of 10CFR50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive PERRY - UNIT 1 B 3/4 2-1

ODCM Page: 149 Rev.: 23 RADIOACTIVE EFFLUENTS BASES 3/4.11.1.2 DOSE (Continued) y, v  ;

materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, RevisionT, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluent from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM '<'

The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Control implements the requirements of 10CFR50.36a; 10CFR50, Appendix A, General Design Criterion 60; and the design objective given in 10CFR50, Appendix I, Section II.D. The specified limit governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in 10CFR50, Appendix I, Section II.A, for liquid effluents.

This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing the system.

PERRY - UNIT 1 B 3/4 2-2

ODCM Page: 150 Rev.: 23 RADIOACTIVE EFFLUENTS RASES 3/4.11.2 GASEOUS EFFLUENTS V 3/4.11.2.1 DOSE RATE

• This Control is provided to ensure that the dose any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20 for UNRESTRICTED AREAS. The annual dose rate limits are those associated with the concentrations of those limiting effluent concentrations, as described in Regulatory Guide 1.109. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in 10CFR20, Appendix B, Table II. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC af or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the whole body or to less than or equal to 3000 mrem/year to the skin.

These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year:

This Control applies to the release of radioactive materials in gaseous effluents from all reactors at the site. The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limit of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in: ' s ~

(1)

• Currie, L: A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984). *  ; ": *

(2) HASL Procedures Manual. HASL-300 (revised annually). " ,

3/4.11.2.2 DOSE - NOBLE GASES This Control is provided to implement the requirements of 10CFR50, Appendix I, Sections II.B, III.A and IV.A. The Control implements the guides set forth in 10CFR50, Appendix I, Section II.B. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in 10CFR50; Appendix I,Section IV.A to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will b6 kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in 10CFR50, Appendix I, Section MIA that conformance with the guides of 10CFR50, Appendix I, be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

PERRY - UNIT 1 B 3/4 2-3

ODCM Page: 151 Rev.: 23 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.2 DOSE - NOBLE GASES (Continued) ....

The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, Revision 1",

October 1977, and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are made using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or are based upon the historical average atmospheric conditions.  : -,

This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

3/4.11.2.3 DOSE - IODINE-131. IODINE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM This Control is provided to implement the requirements of 10CFR50, Appendix I, Sections II.C, III.A and IV.A. The Controls are the guides set forth in 10CFR50, Appendix I, Section II.C. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in 10CFR50, Appendix I, Section IV.A, to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in 10CFR50, Appendix I, Section III.A, that conformance with the guides of 10CFR50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or are based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, iodine-133, tritium and radionuclides in particulate form are dependent on the existing radionuclide pathway to man in the areas at and beyond the SITE BOUNDARY. The pathways which were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

PERRY - UNIT 1 B 3/4 2-4

ODCM Page: 152 Rev.: 23 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.4 AND 3/4.11.2.5 GASEOUS RADWASTE TREATMENT (OFF-GAS) SYSTEM AND VENTILATION EXHAUST TREATMENT SYSTEMS The OPERABILITY of the GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEMS ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of the systems be used, when specified, provides"reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

This Control implements the requirements of 10CFR50.36a; 10CFR50, Appendix A, General Design Criterion; and the design objectives given in 10CFR50, Appendix I Section II.D. The specified limits governing the use of appropriate portions of the systems were specified as a suitable-fraction of the dose design objectives set forth in 10CFR50, Appendix I, Sections ILB and II.C, for gaseous effluents.

This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportional among the units-sharing that system.

3/4.11.4 TOTAL DOSE This Control is provided to meet the dose limitations of 40CFR190 that have been incorporated into 10CFR20 by 46 FR 18525 and the dose limitations of 10CFR72.104. The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40CFR190, if the individual reactors remain within.twice the dose design objectives of 10CFR50, Appendix I, and if direct radiation doses from the units including outside storage tanks, etc. are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40CFR190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40CFR190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR190 have not already been corrected), in accordance with the provisions of 40CFR190.11 and 10CFR20;2203, is considered to be a timely request and fulfills the requirements of 40CFR190 until NRC staff action is completed. The variance only relates to the limits of 40CFR190, and does not apply in any way to the other requirements for dose limitation of 10CFR20,as addressed in ODCM Controls 3.11.1.1 .

and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

PERRY - UNIT 1 , B 3/4 2-5

ODCM Page: 153 Rev.: 23 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM - ,  : ,

The Radiological Environmental Monitoring Program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC -

resulting from the plant operation. This monitoring prograrnximplements 10CFR50,. Appendix I, .

Section IV.B.2, and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by ODCM Table 4.12-1 are considered optimum for.routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in:

(1) Currie, L. A; "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 .

(September 1984).

. *;.( * . . . . ,

(2) HASL Procedure Manual. HASL-300 (revised annually). -

3/4.12.2 LAND USE CENSUS \ '  : -

This Control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program given in the ODCM are made if required by the results of the census. The best information from door-to-door survey, visual or aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of 10CFR50, Appendix I, Section IV.B.3. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2kg/m2. . .  : , .

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of 10CFR50, Appendix!,Section IV.B.2.

PERRY - UNIT 1 B 3/4 3-1

ODCM Page: 154 Rev.: 23 6.0 ADMINISTRATIVE CONTROLS

ODCM Page: 155 Rev.: 23 ADMINISTRATIVE CONTROLS ANNUAL REPORTS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous year shall be submitted by May 1 of each year.

The annual Radiological Environmental Operating Report shall include:

a. Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-

, operational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment;

b. The results of land use censuses required by Control 3.12.2;

c. The results of analysis of all radiological environmental samples and of all locations specified in the table and figures in the Offsite Dose Calculation Manual, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological )

Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report;

d. A summary description of the Radiological Environmental Monitoring Program; at least two legible maps* covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Inter-laboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12.1-2 but are not the result of plant effluents, pursuant to ACTION b of Control 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12.1-1 was not achievable.

• One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

PERRY - UNIT 1 4-1

ODCM Page: 156 Rev.: 23 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLLJENT RELEASE REPORT ^

6.9.1.7 Routine radioactive release reports covering the operation of the unit during the previous year shall be submitted annually. The Report shall be submitted by May 1 of each year.

The Annual Radioactive Effluent Release Report shall include:

a. A summary of the quantities of radioactive liquid and gaseous<effluents released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

b. A summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

c. An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous year. This report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (see Figure 3.2-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time, and location, shall be included in these reports. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

d. An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40CFR190, "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

e. A list and description of unplanned releases from the site to UNRESTRICTED AREAS (see Figure 3.2-1) of radioactive materials in gaseous and liquid effluents made during the reporting period.

f. Any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM), pursuant to PNPP Technical Specification 5.5.1 as well as any major change to Liquid or Gaseous Treatment Systems pursuant to Control 6.15. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Control 3.12.2.

g. The report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Control 3.3.7.9 or 3.3.7.10, respectively; and description of the events leading to liquid holdup tanks exceeding total curie limits PERRY - UNIT 1 4-2

ODCM Page: 157 Rev.: 23 SPECIAL REPORTS 6.9.2 - Special reports shall be submitted in accordance wijtMOCF. R50..4 within the time period

, specified for each report.

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10 Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 Records of surveillance,activities, inspections, and calibrations required by these Controls shall be retained for at least 5 years..

PERRY - UNIT 1 3

ODCM Page: 158 Rev.: 23 ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS*

6.15.1 Licensee initiated major changes to the radioactive waste systems, liquid, gaseous and solid:

1. Shall be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussion of each change shall contain: _

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems

d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change which shows the expected maximum exposures to MEMBERS OF THE PUBLIC in the UNRESTRICTED AREA and to the general N population that differ from those previously estimated in the license application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

2. Shall become effective upon review and approval by the Plant Manager.

• Licensee may choose to submit the information called for in this Control as part of the annual USAR update.

PERRY - UNIT 1 4-4

ODCM Page: 159 Rev.: 23 RECORDS The following records are completed/generated by this document:

Quality Records Annual Radioactive Effluent Release Report Non-Qualitv Records None , ... . .',-.

Commitments IL00434I

ODCM Page: 160 Rev.: 23 REFERENCES

1. Title 10, "Energy," Chapter 1, Code of Federal Regulations: Part 20, U.S. Government Printing Office, Washington, D.C. 20402, May 21,1991.  ;

2. Title 10, "Energy," Chapter 1, Code of Federal Regulations: Part 50; U.S. Government Printing Office, Washington, D.C. 20402, January 1,1984. '" °-

3. Title 40, "Protection of Environment," Chapter 1, Code of Federal Regulations. Part 190, Federal Register, Vol. 42, Washington, D.C. 20402, January 13; 1977.

4? U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," USNRC NUREG-0133, Washington, D.C. 20555, October, 1981.

5. U.S. Nuclear Regulatory Commission, "Draft Radiological Effluent Technical Specifications for PWR's," USNRC NUREG-0473, Revision 2, Washington, D.C. 20555, February, 1980.

6. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, U.S. Nuclear Regulatory Commission, Washington, DC.

20555, June 1974.

7. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50; Appendix I," Revision 0, U.S.

Nuclear Regulatory Commission, Washington, D.C. 20555, March 1976.

8. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, October 1977.

9. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, U.S.

Nuclear Regulatory Commission, Washington, D.C. 20555, July 1977.

10. Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, April 1977.

11. Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operation) - Effluent Streams and the Environment," U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, February 1979.

12. U.S. Nuclear Regulatory Commission, "Branch Technical Position," Revision 1, Washington, D.C.

20555, November 1979.

13. Perry Nuclear Power Plant, Unit 1 and 2, "Final Safety Analysis Report," Amendment 14, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, August 1984.

14. Perry Nuclear Power Plant, Units 1 and 2, "Environmental, Report, Operating License Stage,"

Supplement 3, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, November 1981.

ODCM Page: 161 -LAST Rev.: 23 REFERENCES (Cont.)

15. Perry Nuclear Power Plant, Units 1 and 2, "Radiological Environmental Monitoring Program.

Manual," The Cleveland Electric Illuminating Company, Perry, Ohio 44081, February 1985.

16. "MIDAS User's Manual, for the Cleveland Electric Illuminating Company, Perry Nuclear Power Plant," Pickard, Lowe and Garrick, Washington, DC. 20036, July 1983.

17. Kocher, D.C, "Radioactive Decay Data Tables," Technical Information Center, U.S. Department of Energy, Springfield, Virginia 22161, September 1985. . .,.

18. 1989 Engineering Report "Lake Erie Potable Water Facilities and Intakes within 50 Miles of PNPP, (Ref. SO-11552 "E").

19. Perry Environmental Report Operating License Stage, Table 5.1-10 "Annual Average Dilution Factors for Lake Water Intakes within 50jMiles of PNPP and Q&R Page 2.1-2.

20. PNPP Ohio Power Siting Commission application of August 1974, Appendix 1304-C-2, Table IV-A-2,

21. Total Angler Catch (1987 annual) for Each Grid Location; per letter from Michael R. Rawson, Fairport Fisheries Research Station, Ohio Department of Natural Resources (6-20-88).

22. Offsite Dose Calculation Manual Guidance: Standard Radiological. Effluent Controls for Boiling Water Reactors; Generic Letter 89-01, Supplement No. 1.

23. Federal Guidance Report 13 CD Supplement: Cancer Risk Coefficients for Environmental Exposure to Radionuclides.