Text

Oyster Creek, Unit 1, Annual Radiological Environmental Operating Report for 2017
	ML18123A353
Person / Time
Site:	Oyster Creek
Issue date:	04/30/2018
From:	; Exelon Generation Co, Teledyne Brown Engineering Environmental Services
To:	; Office of Nuclear Reactor Regulation
References
	RA-18-046
	Download: ML18123A353 (125)
	v • d • e

Docket No: 50-219 OYSTER CREEK GENERATING STATION UNITl Annual Radiological Environmental Operating Report 1 January through 31 December 2017 Prepared By Teledyne Brown Engineering Environmental Services Exelon Generation

~ Oyster Creek Generating Station Forked River, NJ 08731 April 2018 Intentionally left blank

-~ Table of Contents Preface ................................................................................................................................... 1 I. Summary and Conclusions

............................................................................................. 12 II. Introduction

...................................................................................................................... 14 A. Objectives of the REMP .....................

................................................................. 14 B. Implementation of the Objectives

........................................................................ 14 C. Discussion

............

............................................................................................... 15 Ill. Program Description

....................................................................................................... 18 A. Sample Collection

................................................................................................ 18 B. Sample Analysis .................................................................................................. 20 C. Data Interpretation

............................................................................................... 20 D. Program Exceptions

............................................................................................ 22 E. Program Changes ............................................................................................... 24 IV. Results and Discussion

................................................................................................. 24 A. Aquatic Environment

........................................................................................... 24 B. Atmospheric Environment

................................................................................... 29 C. Ambient Gamma Radiation

................................................................................. 33 D. Land Use Survey ................................................................................................. 33 E. Summary of Results -Inter-laboratory Comparison Program ............................ 34 V. References

...................................................................................................................... 38 VI. Errata ............................................................................................................................. 38 -I Appendix A Tables Table A-1 Appendix B Tables Table B-1 Table B-2 Table B-3 Figu r es Figure B-1 Figure B-2 Figure B-3 Appendix C Tables Table C-1.1 Table C-1.2 Table C-11.1 Table C-11.2 Appendices Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Oyster Creek Generat i ng Stat i o n , 2017 Location Designation , Distance & Direction , and Sample Collection

& Analytical Methods Location Designation and Identification System for the Oyster Creek Generating Station Radiolog i cal Environmental Monitoring Program -Sampl i ng Locations , Distance and Direction , Oyster Creek Generating Station , 2017 Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods , Oyster Creek Generating Station , 2017 Locations of REMP Stations within a 1-mile radius of the Oyster Creek Generating Station Locations of REMP Stations within a 1 to 5-mile radius of the Oyster Creek Generating Station Locations of REMP Stations greater than 5 miles from the Oyster Creek Generating Station Data Tables and Figures -Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicin i ty of Oyster Creek Generating Station , 2017 ii Table C-11.3 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-111.1 Concentrations of Tritium in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-111.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-IV.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-IV.2 Concentrations of Gamma Emitters in Clam and Crab Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-Vl.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-Vl.2 Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-Vl.3 Concentrations of Strontium in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-Vl.4 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicin i ty of Oyster Creek Generating Station , 2017 Table C-Vll.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-Vlll.1 Concentrations of Strontium and Gamma Emitters in Vegetation Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Table C-IX.1 Quarterly OSLO Results for Oyster Creek Generating Station , 2017 Table C-IX.2 Mean Quarterly OSLO Results for the Site Boundary , Intermediate , Special Interest, and Control Locations for Oyster Creek Generating Station, 2017 Table C-IX.3 Summary of the Ambient Dosimetry Program for Oyster Creek Generating Station , 2017 Figures Figure C-1 Mean Cobalt-60 Concentration in Clams Oyster Creek Generating Station , 1983 -2017 iii Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Figure C-7 Appendix D Tables Table D-1.1 Table D-1.2 Table D-11.1 Table D-11.2 Table D-11.3 Table D-111.1 Table D-111.2 Table D-IV.1 Table D-V.1 Table D-VI. 1 Mean Cobalt-60 Concentration in Aquatic Sediment Oyster Creek Generating Station, 1984 -2017 Mean Cesium-137 Concentration in Aquatic Sediment Oyster Creek Generating Station , 1984 -2017 Mean Weekly Gross Beta Concentrations in Air Particulates Oyster Creek Generating Station , 2008 -2017 Mean Monthly Gross Beta Concentrations in Air Particulates Oyster Creek Generating Station , 1984 -2017 Mean Quarterly OSLO Gamma Dose Oyster Creek Generating Station, 2017 Mean Quarterly TLD/OSLD Gamma Dose Oyster Creek Generating Station , 1990 -2017 Data Tables -QC Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity Of Oyster Creek Generating Station , 2017 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity o f Oyster Creek Generating Station , 2017 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2017 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2017 Concentrations of Tritium in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2017 Concentrations of Gamma Emitters in Clam Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 Concentrations of Strontium and Gamma Emitters in Vegetation Samples Collected in the Vicinity of Oyster Creek Generating Station , 2017 iv Appendix E Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Table E-6 Appendix F Appendix G Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering , 2017 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Teledyne Brown Engineering , 2017 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering , 2017 ERA MRAD Statistical Summary Proficiency Testing Program Environmental, Inc., 2017 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Teledyne Brown Engineering , 2017 ERA RAD Statistical Summary Proficiency Testing Program Environmental, Inc., 2017 Errata Data Annual Radiological Groundwater Protection Program Report (ARGPPR) V Preface The nuclear power industry uses terms and concepts that may be unfamiliar to all readers of this report. This section of the report is intended to help the reader better understand some of these terms and concepts. In this section , we will discuss radiation and exposure pathways. This section is intended only to give a basic understand i ng of these subjects to hopefully allow the reader to better understand the data provided within the report. Every nuclear power station is required to submit two reports annually , the Annual Radioactive Effluents Release Report (ARERR) and the Annual Radiological Environmental Operating Report (AREOR). The following information is provided in both reports for Oyster Creek Generating Station. Understanding Radiation Radiation is simply defined as the process of emitting radiant energy in the form of waves or particles.

Radiation can be categorized as ionizing or non-ionizing radiation. If the radiation has enough energy to displace electrons from an atom it is termed ionizing radiation. Typically you will see a warning sign where there is a potent i al to be exposed to man-made ionizing radiation. These signs normally have the trefoil symbol on a yellow background. DANGER RADIOACTIVE

- - * ** 6 MATERIALS 6 Example Radiological warn i ng signs People do not always recognize non-ionizing radiation as a form of radiation , such as light , heat given off from a stove , radiowaves and microwaves. In our report we focus on the ionizing radiation that is produced at a nuclear power plant though it is important to note that ionizing radiation comes from many sources. In fact , the amount of ionizing 1 radiation an average person is exposed to due to operation of a nuclear power plant is a very small fraction of the total ionizing radiation they will be exposed to in their lifetime and will be discussed later. From this point forward we will only be discussing ionizing radiation but we will just use the term radiation. Since this report discusses radiation in different forms and different pathways we first need to understand where the radiation comes from that we report. Radiation comes from atoms. So, what are atoms and how does radiation come from atoms? You may have seen a Periodic Table of the Elements G r oup-I 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 !Per i od The Periodic Table of the Elements 1 2 3 4 5 6 7 Lanthanides Actinides This table lists all the elements found on earth. An atom is the smallest part of an element that maintains the characteristics of that element. An atom is made up of three parts, protons , neutrons and electrons.

2 Electron The number of protons in an atom determines the element. A hydrogen atom will always have one proton while an oxygen atom will always have eight protons. The protons are clustered with the neutrons at the center of the atom and this is called the nucleus. Orbiting around the nucleus are the relatively small electrons. Neutrons do not have an electrical charge , protons have a positive charge while electrons have a negative charge. In an electrically neutral atom, the negative and positive charges are balanced. Atoms of the same element that have a different number of neutrons in their nucleus are called isotopes. Isotopes are atoms that have the same number of protons but different number of neutrons. They all have the same chemical properties and many isotopes are nonradioactive or stable while other isotopes may be unstable and are radioactive. Radioactive isotopes can be called a radionuclide , a radioisotope or simply called a radioactive atom. A radionuclide usually contains an excess amount of energy in the nucleus usually due to a deficit or excess of neutrons in the nucleus. There are two basic ways radionuclides are produced at a nuclear power plant. The first way is a direct result of the fission process and the radionuclides created through this process are termed fission products.

Fission occurs when a very large atom , such as U-235 (Uranium-235) and Pu-239 (Plutonium-239), absorbs a neutron into its nucleus making the atom unstable. In this instance the atom can actually split into smaller atoms , this splitting of the atom is called fission. When fission occurs there is also a large amount of energy released from the atom in the form of heat which is what is used to produce the steam that will spin the turbines to produce electricity at a nuclear power plant. 3 The second way a radionuclide is produced at a nuclear power plant is through a process called activation and the radionuclides produced in this method are termed activation products.

Water passes through the core where the fission process is occurring.

This water is used to both produce the steam to turn the turbines and to cool the reactor. Though the water passing through the core is considered to be very pure water , there is always some other material within the water. This material typically comes from the material used in the plant's construction.

As the water passes through the core, the material is exposed to the fission process and the radiation within the core can react with the material causing it to become unstable, creating a radionuclide.

The atoms in the water itself can become activated and create radionuclides.

Over time, radioactive atoms will reach a stable state and no longer be radioactive.

To do this they must release the excess energy. The release of excess energy can be in different forms and is called radioactive decay and the energy released is called radiation.

The time it takes for a radionuclide to become stable is measured in units called half-lives.

A half-life is the amount of time it takes for half of the original radioactivity to decay. Each radionuclide has a specific half-life. Some half-lives can be very long and are measured in years while others may be very short and are measured in seconds. 1000 800 Activity 600 400 200 0 1 half-life Half-life 2 half-lives 4 The amount of time it takes for half of the orig i nal radioactivity to decay 3 half-lives 4 half-lives In this report , you will see radionuclides listed such as K-40 (potassium-40) and Co-60 (cobalt-60). The letter(s) represents the element and the number represents the specific isotope of that element and is the number of nuetrons in the nucleus of that radionuclide. You may hear the term naturally occurring radionuclide which refers to radionuclides that naturally occur in nature such as K-40. There are man-made radionuclides such as Co-60 that we are concerned with since these man-made radionuclides result as a by-product when generating electricity at a nuclear power plant. There are other ways man-made radionuclides are produced , such as detonating nuclear weapons , and this is important to note since nuclear weapons testing deposited these man-made radionuclides into the environment and some are still present today. There is a discussion in the AREOR for the radionculides Cs-137 , Sr-89 and Sr-90. The reason we only see some of the radionuclides today is due to the fact that some of the radionuclides released into the environment had relatively short half-lives and all the atoms have decayed to a stable state while other radionuclides have relatively long lives and will be measururable in the environment for years to come. 5 Sources of Radiation People are exposed to rad i ation every day of their lives and have been since the dawn of mankind. Some of this radiation is naturally occurring whi l e some is man-made. There are many factors that will determine the amount of radiation an i nd i vidual wi ll be exposed to such as where you live , medical treatments , etc. Below are examples of some of the typ i cal sou r ces of radiation an individual is exposed to i n a year . .So u rce s o f Radia t ion Expos ur e i n t he U.S. Cosm i c (Space) -5% Terrestrial (So il) -3% Inte rn al-5% D Natural Sources -50% -3 1 0 mill i rem (0.31 rem) Source: NC RP R eport No. 160(20091 Indust r ia l and Occupatio n al <0.1% Consumer -2% Manm ad e Sources -50% -310 mill i rem (0.31 rem) Full report isanilo1bleonthe NORPwebsiteatwww

.NCRPonline.org Adapted w i th permission of the National Council on Radiation Protection and Measurements , http://NCRPonline.org As you can see from the graph , the largest natural source of radiation is due to Radon. That is because essentially all air contains Radon. Cosmic and Internal make up the next largest natural sources of radiation.

Cosmic radiation comes from the sun and stars and there are multiple factors which can impact the amount of cosmic radiation you are exposed to such as the elevation at which you live and the amount of air travel you take a year. The internal natural source of rad i ation mainly comes from two sources. Technically , all organic material is slightly radioactive due to C-14 (Carbon-14), including humans and the food we eat. C-14 makes up a percentage of the carbon in all organic material.

Another contributor to the i nternal natural source is K-40 (Potass i um-40). Potassium i s present in many of the foods we eat , such as brazil nuts , bananas, carrots and red meat. The smallest natural source l i sted is terrestrial.

Soil and rocks contain radioactive materials such as Radium and Uranium. The amount of t errestrial radiation you are exposed to depends on where you live. The map below 6 shows terrestrial exposure levels across the United States. The radiation released from nuclear power plants is included in the Industrial and Occupational slice and is listed as <0.1%. Terrest ri al Gamma-Ray Ex p os ur e at 1 m above grou nd 2.5 1,1 Rl!\r Exposure Pathways Source o' data: U , S_ Geo l og i ca l Survey D i g rta l Da t a Series ODS-9. 1 993 Radiological exposure pathways define the methods by which people may become exposed to rad i oactive material.

The major pathways of concern are those which could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive mater i al released into the environment and how the environment is used. The way radioact i ve material is transported in the environment includes consideration of physical factors , such as the hydrological (water) and meteorological (weather) characteristics of the area. An annual average of the water flow , wind speed , and w i nd direction are used to evaluate how the rad i onuclides will be distributed in an area for gaseous or liquid releases. An important factor in evaluating the exposure pathways is the use of the environment.

Many factors are considered such as dietary intake of residents , recreational use of the area , and the locat i ons of homes and farms in the area. The external and internal exposure pathways considered are shown i n Figure 2.1. The release of rad i oactive gaseous effluents involves pathways such as external whole-7 body exposure, deposition of radioactive material on plants , deposition on soil, inhalation by animals destined for human consumption, and inhalation by humans. The release of radioactive material in liquid effluents involves pathways such as drinking water, fish , and direct exposure from the water at the shoreline while swimming. Although radionuclides can reach humans by many different pathways , some result in more dose than others. The critical pathway is the exposure route that will provide , for a specific radionuclide, the greatest dose to a population, or to a specific group of the population called the critical group. The critical group may vary depending on the radionuclides involved , the age and diet of the group , or other cultural factors. The dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest fraction of the dose is called the critical organ. Oepaslionto GrOU'ld Or i nlci(ll SISfac:e Wat e r a Groundwater This simple diagram demonstrates some potent i al exposure pathways from Oyster Creek Generating Station. 8 Radiation Risk U.S. radiation protection standards are based on the premise that any radiation exposure carries some risk. There is a risk whether the radiation exposure is due to man-made sources or natural sources. There have been many studies performed trying to determine the level of risk. The following graph is an example of one study that tries to relate risk from many different factors. This graph represents risk as " Days of Lost Life Expectancy

." All the categories are averaged over the entire population except Male Smokers, Female Smokers and individuals that are overweight.

Those risks are only for people that fall into those categories. The category for Nuclear Power is a government estimate based on all radioactivity releases from nuclear power, including accidents and wastes. Smoking -Male Heart Disease Smoking -Female Cance r Every 10 I bs overweight S t roke -Mo t o r Vehicle A cciden t -Air Pollution

Rad on I Chemical R esidue in Foods I Drowning I Hurricanes and Tornadoes lightning Nuclear Power 0 Hurricanes and Tornadoes lightning Nuclear Power I 0 0.2 Days of Lost Life Expectancy 500 1000 1500 2000 2500 3000 Days of Lost Life Expectancy 0.4 0.6 0.8 1.2 1.4 1.6 1.8 2 Adapted from the article by Bernard L. Cohen , Ph.D. in the Journal of American Physicians and Surgeons Volume 8 Number 2 Summer 2003. The full article can be found at http://www.jpands

.org/vol8no2/cohen

.pdf 9

~ Annual Reports All nuclear power plants are required to perform sampling of both the potential release paths from the plant and the potential exposure pathways in the environment.

The results of this sampling are required to be reported annually to the Nuclear Regulatory Commission (NRC) and made available to the public. There are two reports generated annually , the Annual Rad i oactive Effluents Release Report (ARE RR) and the Annual Radiological Environmental Operating Report (AREOR). The ARERR summarizes all of the effluents released from the plant and quantifies the doses to the public from these effluents.

The AREOR summarizes the results of the samples obtained in the environment looking at all the potential exposure pathways by sampling different media such as air , vegetation , direct radiation , etc. These two reports are related in that the results should be aligned. The AREOR should validate that the effluent program is accurate.

The ARERR and AREOR together ensure Nuclear Power Plants are operating in a manner that adequately protects the public. In the reports , there are four different but interrelated units for measuring radioactivity , exposure, absorbed dose, and dose equivalent.

Together , they are used to properly capture both the amount of radiation and its effects on humans.

Radioactivity refers to the amount of ionizing radiation released by a material.

The units of measure for radioactivity used within the AREOR and ARERR are the curie (Ci). Small fractions of the Ci often have a prefix, such as µCi that means 1/1,000,000. That means there are 1 , 000 , 000 µCi in one Ci.

Exposure describes the amount of radiation traveling through the air. The units of measure for exposure used within the AREOR and ARERR are the roentgen (R). Traditionally direct radiation monitors placed around the site are measured in milliroentgen (mR), 1/1 , 000 of one R.

Absorbed dose describes the amount of radiation absorbed by an object or person. The units of measure for absorbed dose used within the AREOR and ARERR are the rad. Noble gas air doses are reported by the site are measured in millirad (mrad), 1/1,000 of one rad.

Dose equivalent (or effective dose) combines the amount of radiation absorbed and the health effects of that type of radiation. The units used within the ARE OR and ARERR are the roentgen equivalent man (rem). Regulations require doses to the whole body , specific organ, and direct radiation to be reported in millirem (mrem), 1/1 , 000 of one rem. 10 Typically releases from nuclear power plants are so low that the samples taken in the environment are below the detection levels required to be met by all nuclear power plants. There are some radionuclides identified in the environment during the routine sampling but this i s typically background radiation from nuclear weapons testing and events such as Chernobyl and these radionuclides are d i scussed in the AREOR. Each report l i sts the types of samples that a r e collected and the analyses performed. Different types of media may be used at one sample location looking for specific radionuclides. For example , at our gaseous effluent release points we use different media to collect samples for particulates , iod i nes , noble gases and tritium. There are also examples where a sample collected on one media is analyzed differently depending on the radionuclide for which the sample is being analyzed. These annual reports , and much more information related to nuclear power, are available on the NRC website at www.nrc.gov. 11 I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Oyster Creek Generating Station (OCGS) by Exelon Nuclear covers the period 01 January 2017 through 31 December 2017. During that time period , 1596 analyses were performed on 1224 samples. In assessing all the data gathered for this report and comparing these results with historical data , it was concluded that the operation of OCGS had no adverse radiological impact on the environment.

REMP-designated surface water samples were analyzed for concentrations of tritium and gamma-emitting nuclides.

No tritium, fission or activation products were detected in any of the surface water samples collected as part of the Radiological Environmental Monitoring Program during 2017. REMP designated drinking water samples were analyzed for concentrations of gross beta, tritium , lodine-131 (1-131), and gamma-emitting nuclides.

The preoperational environmental monitoring program did not include analysis of drinking water for gross beta. No tritium , 1-131 , or fission or activation products were detected in any of the drinking water samples collected. REMP-designated groundwater samples were analyzed for concentrations of tritium and gamma-emitting nuclides. No tritium and no fission or activation products were detected in REMP groundwater samples. Fish (predator and bottom feeder}, clams , crabs , and sediment samples were analyzed for concentrations of gamma-emitting nuclides. No OCGS-produced fission or activation products were detected in fish, clams , or crabs. Cesium-137 (Cs-137) was not detected in any sediment samples. Air particulate samples were analyzed for concentrations of gross beta , emitting nuclides , Strontium-89 (Sr-89), and Strontium-90 (Sr-90). Gross beta and cosmogenic Beryllium-? (Be-7) were detected at levels consistent with those detected in previous years. No fission or activation products were detected.

Sr-89 and Sr-90 analyses were performed on quarterly composites of air particulate samples. All Sr-89 and Sr-90 results were below the minimum detectable activity. lodine-131 (1-131) analyses were performed on weekly air samples. All results were less than the minimum detectable concentration. Vegetation samples were analyzed for gamma-emitting nuclides , Sr-89 , and Sr-90. Concentrations of naturally-occurring Potassium-40 (K-40) were consistent with those detected in previous years. No fission or activation products were detected. All Sr-89 results were below the minimum detectable activity.

Sr-90 and Cs-137 activity were detected at levels consistent with those detected in previous years at both control and indicator stations , and can be attributed to historical nuclear weapons testing and the Chernobyl accident.

12 Environmental gamma radiation measurements were performed quarterly using Optically Stimulated Luminescence Dosimeters (OSLO). Beginning in calendar year 2012 , Exelon began using OSLDs and discontinued the use of Thermoluminescent Dosimetry (TLD). There were two main reasons for this change. First, OSLDs have minimal " fade" over a quarterly time period. Fade is where the dose on the dosimeter drifts lower over time. Second , OSLDs may be r e-r ead i f necessary. TLDs are reset to zero after they are read. Levels detected were consistent with those observed in previous years. The maximum dose to any member of the public attributable to radioactive effluents and direct radiation from the OCGS was less than the 25 mRem/year limit established by the United Stated Environmental Protection Agency (EPA). 13 II. Introduction The Oyster Creek Generating Station (OCGS), consisting of one boiling water reactor owned and operated by Exelon, is located on the Atlantic Coastal Plain Physiographic Province in Ocean County, New Jersey , about 60 miles south of Newark , 9 miles south of Toms River, and 35 miles north of Atlantic City. It lies approximately 2 m i les inland from the Barnegat Bay. The property , covering approximately 781 acres , is situated partly in Lacey Township and , to a lesser extent , in Ocean Township. Access is provided by U.S. Route 9, passing through the site and separating a 637-acre eastern portion from the balance of the property west of the highway. The station is about% mile west of the highway and 1 % miles east of the Garden State Parkway. The site property extends about 2% miles inland from the bay; the maximum width in the south direction is almost 1 mile. The site location is part of the New Jersey shore area with its relatively flat topography and extensive freshwater and saltwater marshlands.

The South Branch of Forked River runs across the northern side of the site and Oyster Creek partly borders the southern side. A preoperational Radiological Environmental Monitoring Program (REMP) for OCGS was established in 1966 , and continued prior to the plant becoming operational in 1969. This report covers those analyses performed by Teledyne Brown Engineering (TSE), Landauer and Environmental Inc. (Midwest Labs) on samples collected during the period 01 January 2017 through 31 December 2017. A. Objectives of the REMP The objectives of the REMP are to: 1. Determine whether any significant increase occurs in the concentration of radionuclides in major pathways 2. Identify and evaluate the buildup , if any, of radionuclides in the local environment, or any changes in normal background radiation levels 3. Verify the adequacy of the plant's controls for the release of radioactive materials

4. Fulfill the obligations of the radiological surveillance sections of Oyster Creek's Offsite Dose Calculation Manual (ODCM) 8. Implementation of the Objectives The implementation of the objectives is accomplished by: 14

1. Identifying significant exposure pathways 2. Establishing baseline radiological data for media within those pathways 3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment C. Discussion

1. General Program The Radiological Environmental Monitoring Program (REMP) was established in 1966 , before the plant became operat i onal. This preoperational surveillance program was established to describe and quantify the radioactivity, and its variability, in the area prior to the operation of OCGS. After OCGS became operational in 1969, the operational surveillance program continued to measure radiation and radioactivity in the surrounding areas. A variety of environmental samples are collected as part of the REMP at OCGS. The selection of sample types is based on the established pathways for the transfer of radionuclides through the environment to humans. The selection of sampling locations is based on sample availability , local meteorological and hydrological characteristics, local population characteristics , and land usage in the area of interest.

The selection of sampling frequencies for the various environmental media is based on the radionuclides of interest, their respective half-lives , and their behavior in both the biological and physical environment.

2. Preoperational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental monitoring prior to constructing the facility. This preoperational surveillance program is aimed at collecting the data needed to identify pathways, including selection of the radioisotope and sample media combinations to be included in the environmental surveillance program conducted after facility operation begins. Radiochemical analyses performed on the environmental samples should include not only those nuclides expected to be released during facility operation, but should also include typical radionuclides from nuclear weapons testing and natural background radioactivity.

All environmental media with a 15 potential to be affected by facility operation as well as those media directly in the major pathways , should be sampled on at least an annual basis during the preoperational phase of the environmental surveillance program. The preoperational surveillance design, including nuclide/media combinations, sampling frequencies and locations, collection techniques, and radioanalyses performed , should be carefully considered and incorporated in the design of the operational surveillance program. In this manner, data can be compared in a variety of ways (for example, from year to year, location to location , etc.) in order to detect any radiological impact the facility has on the surrounding environment.

Data collection during the preoperational phase should be planned to provide a comprehensive database for evaluating any future changes in the environment surrounding the nuclear facility. OCGS began its preoperational environmental surveillance program three years before the plant began operating in 1969. Data accumulated during those early years provide an extensive database from which environmental monitoring personnel are able to identify trends in the radiological characteristics of the local environment.

The environmental surveillance program at OCGS will continue after the plant has reached the end of its economically useful life and decommissioning has begun. 3. Consideration of Plant Effluents Effluents are strictly monitored to ensure that radioactivity released to the environment is as low as reasonably achievable and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs , quality assurance programs for effluent and environmental programs , and procedures covering all aspects of effluent and environmental monitoring. Both radiological environmental and effluent monitoring indicate that the operation of OCGS does not result in significant radiation exposure of the people or the environment surrounding OCGS and is well below the applicable levels set by the Nuclear Regulatory Commission (NRC) and the EPA. There were liquid radioactive effluent releases during 2017 of concentrations of tritium too low to detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution Discharge 16 Elimination System (NJPDES) permitted main condenser outfall. The releases were part of nearly continuous pumping of groundwater at approximately 60 gpm containing low levels of tritium and no detectable gamma. Exelon and the State of New Jersey Department of Environmental Protection (NJDEP) agreed to this remediation action instead of natural attenuation to address concentrations of tritium in groundwater.

Well 73 and supporting equipment and piping were installed to pump groundwater to the intake structure at the inlet of the main circulating water pumps. Provisions were established for both batch and continuous releases of groundwater.

Continuous releases occurred approximately 303 days in 2017. The nearly continuous releases occurred from January 1 , 2017 through October 5 , 2017 and from December 12 , 2017 through December 31, 2017 with a total of 2.85 E+07 gallons of groundwater pumped resulting in 2.17E-01 Ci of tritium released to the discharge canal. The dose to the most limiting member of the public due to the release of groundwater was 1.02E-06 mRem. Utilizing gaseous effluent data , the maximum hypothetical dose to any individual during 2017 was calculated using a mathematical model, which is based on the methods defined by the U.S. Nuclear Regulatory Commission.

These methods accurately determine the types and quantities of radioactive materials being released to the environment.

The maximum calculated organ dose (Bone) from iodines , tritium, Carbon-14 (C-14), and particulates to any individual due to gaseous effluents was 5.39E-01 mRem, which was approximately 3.59E+OO percent of the annual limit of 1.50E+01 mRem. The maximum calculated gamma air dose in the UNRESTRICTED AREA due to noble gas effluents was 5.86E-04 mrad , which was 5.86E-03 percent of the annual 10 CFR 50 Appendix I , As Low As Reasonably Achievable (ALARA) limit of 1.00E+01 mrad. The majority of organ dose from gaseous effluents was due to C-14. The maximum hypothetical calculated whole body dose to any individual due to noble gas effluents was 2.61 E-04 mRem which was *s.22E-03 percent of the annual limit of 5.00E+OO mRem. The total maximum organ dose (Bone) was 5.39E-01 mRem received by any individual from gaseous effluents from the Oyster Creek Generating Station for the reporting period. During 2017, the maximum direct radiation dose to the most likely exposed MEMBER OF THE PUBLIC potentially attributable to the operation of Oyster Creek beyond the site boundary in the west 17 sector , as shown by offsite OSLO readings at station 55 was 6.50EO mRem. This includes a shielding factor of 7.00E-01. The nearest member of the public is considered a part-time resident that works 2 , 000 hours0 days 0 hours 0 weeks 0 months per year at a warehouse located west of the plant. Environmental sampling of airborne iodine and particulates showed no radioactivity attributable to the operation of OCGS. Ill. Program Description A. Sample Collection Samples for the OCGS REMP were collected for Exelon by on-site personnel and Normandeau Associates , Incorporated. This section describes the general collection methods used to obtain environmental samples for the OCGS REMP in 20 1 7. Sample locations and descriptions can be found i n Tables B-1 and B-2 , and Figures B-1 , B-2 , and B-3 , Appendix B. The collection procedures are listed in Table B-3. Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water , drinking water , groundwater , fish , clams , crabs , and sediment.

One gallon water samples were collected monthly from two surface locations (33 and 94), semiannually at two surface water locations (23 and 24), monthly from five drink i ng water wells (1 N , 1 S, 37 , 38 , and 114) and quarterly from 2 groundwater stations (MW-24-3A and W-3C). Control locations were 94 and 37. All samples were collected in plastic bottles , which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups , bottom feeder and predator , were collected semiannually at three locations (33 , 93 and 94 (control)). Clams were collected semiannually from three locations (23 , 24, and 94 [control]). Two annual crab samples were collected from two locations (33 and 93). Sed i ment samples were collected at four locations semiannually (23 , 24 , 33 , and 94 [control]).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of a i r particulate and airborne iodine. Airborne iodine and particulate samples were collected and analyzed weekly at eight locations (C , 3, 20 , 66 , 71, 72 , 73 , and 111). The control location was C. Airborne iodine and particulate samples were obtained at each 18 location, using a vacuum pump with charcoal and glass fiber filters attached.

The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis. Terrestrial Environment The terrestrial environment was evaluated by performing radiological analyses on samples of garden vegetation.

No commercial dairy operations and no dairy animals producing milk for human consumption are located within a 5 mile radius of the plant. Therefore , vegetation samples were collected in lieu of milk. Vegetation samples were collected , when available , at four locations (35 , 36 , 66 , and 115). Station 36 was the control location. All samples were collected in 18" x 24" new unused plastic bags and shipped promptly to the laboratory. Ambient Gamma Radiation Direct rad i ation measurements were made using Al203: C Opt i cally Stimulated Luminescence Dosimetry (OSLO). Exelon changed the dosimetry used for environmental monitoring. Beginning in calendar year 2012 , Exelon began using OSLDs and discontinued the use of Thermoluminescent Dosimetry (TLD). There were two main reasons for this change. First, OSLDs are not subject to " fade". Fade is where the dose on the dosimeter drifts lower over time. Second , OSLDs may be read if necessary. TLDs are reset to zero after they are read. The OSLDs were placed on and around the OCGS site and were categorized as follows: An inner ring consisting of 19 locations (1 , T1, 51 , 52, 53 , 54, 55 , 56 , 57, 58 , 59, 61 , 62 , 63, 64 , 65, 66 , 112, and 113) near the site boundary.

An outer ring consisting of 31 locations (4 , 5 , 6 , 8 , 9 , 22 , 46 , 47 , 48 , 68, 73 , 74 , 75 , 78 , 79 , 82 , 84 , 85 , 86 , 98, 99,100 , 101 , 102 , 103 , 104 ,1 05 , 106 , 107 , 109 , and 110) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

Special interest stations consisting of 9 locations (3 , 11 , 71 , 72 , 81 , 88 , 89 , 90 , and 92) representing special interest areas such as population centers, state parks , etc. Background (Control) stations consisting of two locations (C and 14) greater than 20 miles distant from the site. Indicator OSLDs were placed systematically , with at least one station in each of 16 meteorological compass sectors in the general area of the site 19 boundary.

OSLDs were also placed i n each meteorological sector in the 1 to 5 mile range , where reasonable highway access would permit , in areas of public interest and population centers. Background locations were located greater than twenty miles distant from the OCGS and generally in an upwind direction from the OCGS. Two OSLDs were placed at each locat i on approx i mately three to e i ght feet above ground level. The OSLDs were exchanged quarterly and sent to Landauer for analysis. 8. Sample Analysis This section describes the general analytical methodologies used by TSE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the OCGS REMP in 2017. The analytical procedures used by the laboratories are listed in Table 8-3. In order to achieve the stated objectives , the current program includes the following analyses: 1. Concentrations of beta emitters in air particulates and drinking water 2. Concentrations of gamma emitters in surface , drinking water , groundwater , fish , clams , crabs , sediment , air particulates and vegetation

3. Concentrations of tritium in REMP-designated surface , drinking water and groundwater

4. Concentrations of 1-131 in air i odine cartridges and dr i nk i ng water 5. Concentrations of strontium i n air particulates and vegetation

6. Ambient gamma radiation levels at var i ous locations around the OCGS C. Data Interpretation For trending purposes , the radiological and direct radiat i on data collected du ri ng 2017 were compared with data from past years. The results of env i ronmental sampling show that radioactivity levels have not increased from the background radioactivity detected prior to the operation of OCGS. The operation of OCGS continues to have no measurable radiological impact upon the environment.

20 Several factors were important in the interpretation of the data: 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criterion for the presence of activity.

All analyses were designed to achieve the required OCGS detection capabilities for environmental sample analysis. 2. The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity.

Since the REMP measures extremely small changes in radioactivity in the environment , background variations may result in sample activity being lower than the background activity , which results in a negative number. An MDC was reported in all cases where positive activity was not detected. Gamma spectroscopy results for each type of sample were grouped as follows: For surface , drinking water , and groundwater

-12 nuclides:

Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95 , Nb-95 , 1-131, Cs-134 , Cs-137, Ba-140 , and La-140 were reported For fish -eight nuclides:

K-40 , Mn-54 , Co-58 , Fe-59, Co-60 , Zn-65 , Cs-134 , and Cs-137 were reported For clams -eight nuclides: K-40, Mn-54, Co-58 , Fe-59 , Co-60 , Zn-65 , Cs-134 , and Cs-137 were reported For crabs-eight nuclides:

K-40, Mn-54, Co-58 , Fe-59, Co-60 , Zn-65, Cs-134, and Cs-137 were reported 21 For sediment-nine nuclides: Be-7 , K-40, Mn-54 , Co-58 , Co-60 , Cs-134 , Cs-137 , Ra-226 , and Th-228 were reported For air particulate

-six nuclides: Be-7 , Mn-54 , Co-58 , Co-60 , Cs-134, and Cs-137 were reported Fo r a ir i od i ne ca rtri dges-one nuclide: 1-131 was r eported For vegetation

-seven nuclides: Be-7 , K-40 , 1-131 , Cs-134 , Cs-137 , Ba-140 , and La-140 were reported Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty. D. Program Exceptions For 2017, the OCGS REMP had a sample recovery rate in excess of 99%. Exceptions are listed below: Environmental Dosimetry

1. First Quarter: Station 61 -One of the dos i meters was missing. 2. First Quarter: Stat i on 84 -One of the dosimeters was found out of its holder on the ground. Data was used in reporting. 3. Second Quarter: Station 6 -Both dosimeters were m i ssing. The clip holding the dosimeters in place was also missing. 4. Third Quarter: Station 101 -Both dosimeters were missing. The entire holder and clip holding the dosimeters in place was also missing. 1. Week 5 (01/29/17

-02/04/17)

Station 72-Pump was not running. Changed the vanes on the pump and the pump was returned to service. Per procedure , since the pump was inoperable , but the timer was running normally , the samples were not sent to the lab for analysis. 2. Week 25 (06/18/17

-06/24/17): Station 71 -Pump was not runn i ng. The main breaker switch was turned off by the utility performing work on the power in the vicinity.

No sample collected. 22

3. Week 29 {07/16/17

-07/22/17): Station 111 -Pump was not running. Changed the vanes on the pump and the pump was returned to service. Per procedure , since the pump was inoperable but the timer was running normally , the samples were not sent to the lab for analysis. 4. Week 33 (08/13/17 -08/19/17): Station 72-Pump was no t running. Changed the vanes on the pump and the pump was returned to service. Per procedure , since the pump was inoperable but the timer was running normally , the samples were not sent to the lab for analysis. 5. Week 36 (09/03/17

-09/09/17): Station 71 -Pump was not running. The main breaker switch was found off. Sample was not valid. 6. Week 47 (11/19/17

-11/25/17)

Station 73-The part i culate filter was not sent to the lab for analysis.

Filter was torn and covered in mud. Appears to be weather-related.

Iodine cartridge was sent to the lab for analysis. Drinking Water Note: Stations 1 Sand 1 N are on-site drinking water wells. Typically , only one well is in service at a time. They are only listed as deviations when there is not a sample for every week of the composite period. 1 . Station 1 S -Month of March was a composite for 3 of the 4 weeks. Well was out of service for 1 week of the month. 2. Station 1 S -Month of May was a composite for 4 of the 5 weeks. Well was out of service for 1 week of the month. 3. Station 1 S -Month of July was a composite for 2 of the 4 weeks. Well was out of service 2 weeks of the month. 4. Station 1 N -Month of March was a composite for 1 of the 4 weeks. Well was out of service 3 weeks of the month. 5. Station 1 N -Month of April was a composite for 1 of the 4 weeks. Well was out of service for 3 weeks of the month. 6. Station 1 N -Month of May was a composite for 1 of the 5 weeks. Well was out of service for 4 weeks of the month. The lab was unable to analyze for gross beta due to insufficient sample volume. 23

7. Station 1 N -Month of July was a composite for 2 of the 4 weeks. Well was out of service for 2 weeks of the month. Program exceptions are tracked and investigated to understand the causes of the program exception. Sampling and maintenance errors are reviewed with the personnel involved to prevent recurrence. The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation. E. Program Changes There were no changes to the program in 2017. IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken via grab sample methodology at two locations (33 and 94) on a monthly schedule. In addition, grab samples were collected semi-annually at two locations (23 and 24). Of these locations 23 , 24 , and 33 , located downstream , could be affected by Oyster Creek's effluent releases. The following analyses were performed: Tritium Surface water sampling began in 1966, and the samples were analyzed for tritium as well as other radioactivity.

During this preoperational program , tritium was detected at an average concentration of 1.05E+03 pCi/L. At that time , counting instrumentation was not as sensitive as it now , and the minimum detectable concentration was 1.00E+03 pCi/L versus 2.00E+02 pCi/L used today. By comparing the 2017 sampling results to the decay corrected average preoperational concentration reported in the 2007 Annual Radiological Environmental Operating Report (1.11 E+02 pCi/L}, it can be seen that the inventory of tritium in the environment is due to fallout from past atmospheric nuclear weapons testing and Chernoby l, and is decreasing with time. Samples from all locations were analyzed for tritium activity (Table C-1.1 , Appendix C). No tritium activity was detected. 24 Gamma Spectrometry Samples from all locations were analyzed for gamma-emitting nuclides (Table C-1.2 , Appendix C). All nuclides were less than the MDC. 2. Dr i nk i ng wate r Monthly samples were composited from monthly grab samples from six drinking water wells (1 N , 1 S , 37 , 38 , 39 , and 114). Station 1 , because it is located on the OCGS site, could potentially be affected by radioactive releases from the plant. Station 1 was split into two separate locations , 1 N and 1 S. Station 38 , the Ocean Township Municipal Utility Authority Well , could potentially be affected by effluent releases from the OCGS. Given its distance from the facility (1.6 miles) and depth (approximately 360 feet), however , the probability of any OCGS-related impacts is very small. Stations 37 and 39, Lacey Township Municipal Utility Authority wells , are not likely to be impacted by effluents from the OCGS. These wells are located generally up-gradient of the regional groundwater flow direction (southeast).

In addition , because of their depth (> 200 feet) and distance from the s i te (2.2 and 3.5 miles respectively), they are unlikely to be affected by OCGS operations.

The following analyses were performed: Tr i t i um Monthly samples from all locations were analyzed for tritium activity (Table C-11.1 , Appendix C). No tritium activity was detected. Drinking water was sampled during the preoperational program and throughout the 43 years of the plant's operational program. Tritium sampling results during the preoperational years , yielded results all less than the minimum detectable concentration of 1.00E+03 pCi/L. 2017 results are all less than the current MDC of 2.00E+02 pCi/L. Gross Beta Monthly samples from all locations were analyzed for concentrations of total gross beta activity (Tables C-11.2 , Appendix C). Gross beta was detected in 42 of 51 samples , and is expected due to natural sources and fallout residual from previous bomb testing. The values ranged from 1.80E+OO to 12.90E+OO pC i/L. The investigation level for gross beta in water is 15.00E+OO pCi/L. 25 Drinking water sample 1 N result for gross beta exceeded the investigation level beginning in January 2012. The initial result for gross beta was 15.1 OE+OO pCi/L in 2012. This issue was entered into the Corrective Action Program (CAP) and an investigation initiated.

The 1 N water sample was analyzed for known beta emitters Sr-89 , Sr-90 , lron-55 (Fe-55) and Nickel-63 (Ni-63). These analyses results were all <MDC. It was also identified that the 1 N well treatment system was upgraded the previous month and a potassium chloride softener system was added as part of the upgrade. Samples were obtained pre-and post-treatment.

The pre-treatment result for gross beta was 3.60E+OO pCi/L, which is a value that has been seen previously in drinking water samples. The post-treatment sample result for gross beta was 22.20E+OO pCi/L. Based on the fact that there were no typical plant-produced emitters detected and that natural potassium is a known emitter , along with the results of the pre-and post-sampling , the gross beta values obtained for 1 N can be attributed to the addition of the water softener system installed during the system upgrade in December of 2011. Iodine Monthly samples from all locations were analyzed for 1-131 by the low level method to detect down to 1.00E+OO pCi/L (Table C-11.3 , Appendix C). All results were less than the MDC. Gamma Spectrometry Samples from all locations were analyzed for gamma-emitting nuclides (Table C-11.4 , Appendix C). All nuclides were less than the MDC. 3. Groundwater The following analyses were performed: Tritium Samp l es from all locations were analyzed for tritium activity (Table C-111.1 , Appendix C). No tritium activity was detected. 26 Gamma Spectrometry Samples from all locations were analyzed for gamma-emitting nuclides (Table C-111.2 , Appendix C). All nuclides were less than the MDC. 4. Fish Fish samples comprised of bottom feeder (American eel , red drum, cownose ray, tautog) and predator (bluefish , white perch, striped bass) were collected at three locations (33, 93, and 94) semiannually.

Locations 93 and 33 could be affected by Oyster Creek's effluent releases.

The following analysis was performed:

Gamma Spectrometry The edible portions of fish samples from three locations were analyzed for gamma-emitting nuclides (Table C-IV.1 , Appendix C). Naturally-occurring K-40 was found at all stations and ranged from 2,583 to 4,573 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were found. No fish were sampled during the preoperational sampling program for OCGS. 5. Clams and Crabs Clams were collected at three locations (23 , 24 , and 94) semiannually. Crabs were collected at two locations (33 and 93) annually.

Locations 23, 24, 33 , and 93 could be affected by Oyster Creek's effluent releases. The following analysis was performed: Gamma Spectrometry The edible portions of clam samples from all three locations were analyzed for gamma-emitting nuclides (Table C-IV.2 , Appendix C). Naturally-occurring K-40 was found at all stations and ranged from 713 to 2,167 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were found. Historical levels of Co-60 in clams are shown in Figure C-1 , Appendix C. Preoperational clam sample results for naturally-occurring K-40 ranged from 600 to 9 , 800 pCi/kg wet , which are consistent with current sample results. 27 The edible portions of crab samples from 2 locations were analyzed for gamma-emitting nuclides (Table C-IV.2, Appendix C).

occurring K-40 was found at both stations and ranged from 1,568 to 2 , 981 pCi/kg wet, consistent with levels detected in previous years. No fission or activation products were found. Crabs were not sampled during the preoperational years of the OCGS environmental monitoring program. 6. Sediment Aquatic sediment samples were collected at four locations (23 , 24 , 33 , and 94) semiannually.

Of these locations, stations 23 , 24, and 33 located downstream , could be affected by Oyster Creek's effluent releases.

The following analysis was performed: Gamma Spectrometry Sediment samples from all four locations were analyzed for gamma-emitting nuclides (Table C-V.1 , Appendix C).

occurring K-40 was found at all stations and ranged from 3,882 to 15 , 930 pCi/kg dry. Naturally-occurring Ra-226 was found at three locations with a concentration range of 983 to 2,238 pCi/kg dry. Naturally-occurring Th-228 was found at all stations and ranged from 361 to 803 pCi/kg wet. Cs-137 was not detected in any of the samples. No fission or activation products were found. Figure C-3 , Appendix C graphs show Cs-137 concentrations in sediment from 1984 through 2017 and figure C-2 , Appendix C graphs show Co-60 concentrations in sediment from 1984 through 2017. The requirement for sampling sediment is a requirement of ODCM 3.12.1 , Table 3.12.1-1.d.

ODCM Table 3.12.1-2, "Reporting Levels for Radioactive Concentrations in Environmental Samples Reporting Levels" does not include requirements for sediment. AA-170-1000, Radiological Environmental Monitoring Program and Meteorological Program Implementation , Attachment 1 , Analytical Results Investigation Levels , includes sediment investigation level for Cs-137 of 1000E+OO pCi/kg dry. While aquatic sediment sampling was part of the preoperational program, samples were not analyzed for gamma-emitting nuclides until 1981. In conclusion, the 2017 aquatic monitoring results for surface water, drinking water, groundwater , fish , clams, crabs , and sediment 28 showed only naturally-occurring radioactivity and were consistent with levels measured prior to the operation of OCGS, and with levels measured in past years. No radioactivity attributable to activities at OCGS was detected in any aquatic samples during 2017 and no adverse long-term trends are shown in the aquatic monitoring data. B. Atmospheric Environment

1. Airborne a. Air Particulates Continuous air particulate samples were collected from eight locations on a weekly basis. The eight locations were separated into three groups: Group I represents locations near the OCGS site boundary (20 , 66 and 111 ), Group II represents the locations at an intermediate distance from the OCGS site (71 , 72 , and 73), and Group Ill represents the control and locations at a remote distance from OCGS (C and 3). The following analyses were performed: Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-Vl.1 and C-Vl.2 , Appendix C). Detectable gross beta activity was observed at all locations.

Comparison of results among the three groups aids in determining the effects , if any , resulting from the operation of OCGS. The results from the Site Boundary locations (Group I) ranged from 6.00E-03 to 24.00E-03 pCi/m 3 with a mean of 13.00E-03 pCi/m 3. The results from the Intermediate Distance locations (Group II) ranged from 5.00E-03 to 22.00E-03 pCi/m 3 with a mean of 12.00E-03 pCi/m 3. The results from the Distant locations (Group Ill) ranged from 5.00E-03 to 22.00E-03 pCi/m 3 with a mean of 12.00E-03 pCi/m 3. The similarity of the results from the three groups indicates that there is no relationship between gross beta activity and distance from OCGS. These results are consistent with data from previous years and indicate no effects from the operation of OCGS (Figures C-4 and C-5 , Appendix C). Air sample filters have been analyzed for gross beta activity since the inception of the preoperational environmental 29

Air sample filters have been analyzed for gross beta activity since the inception of the preoperational environmental monitoring program in 1966. The preoperational data values ranged from 1.90E-02 to 2. 77E-01 pCi/m3. 2017 gross beta activity values ranged from < 5.00E-03 to 24.00E-03 pCi/m3. The 2017 results are consistent with historical operational data (Figure C-5 , Appendix C) and fall within the range of results observed during the preoperational period. Strontium-89 and Strontium-90 Weekly samples were composited quarterly and analyzed for Sr-89 and Sr-90 (Table C-Vl.3 , Appendix C). No strontium was detected in any of the samples. These results are consistent with historical operational data. The preoperational environmental monitoring program did not include analysis of air samples for Sr-89 and Sr-90. Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma-emitting nuclides (Table C-Vl.4 , Appendix C). Naturally a occurring Be a 7 due to cosmic ray activity was detected in 32 of 32 samples. The values ranged from 46.00E-03 to 97.00E-03 pCi/m 3. All other nuclides were less than the MDC. These results are consistent with historical operational data. The preoperational environmental monitoring program did not include analysis of air samples for gamma-emitting nuclides. b. A i rborne Iodine Continuous air samples were collected from eight (C , 3, 20 , 66 , 71, 72, 73 , 111) locations and analyzed weekly for 1-131 (Table C-Vll.1 , Appendix C). Consistent with historical operational data, all results were less than the MDC for 1-131. The preoperational environmental mon i toring program for OCGS did not include analysis of air media for 1-131. In conclusion, the atmospheric monitoring data are consistent with preoperational and prior operational data and show no long-term trends in the environment attributable to the operation of OCGS. 30

2. Terrestrial

a. Vegetation Samples were collected from four locations (35 , 36 , 66 , and 115) when available. The following analyses were performed: Strontium-89 and Strontium-90 Vegetation samples from all locations were analyzed for concentrations of Sr-89 and Sr-90 (Table C-Vlll.1 , Appendix C). All Sr-89 results were less than the MDC. Sr-90 was detected in 24 of 41 samples. The values ranged from 3.0 to 20.3 pCi/kg wet , which is consistent with historical data. The following information on Sr-90 is available on the NRC web page under "Backgrounder Radiation Protection and the " Tooth Fairy" Issue" published in December of 2004: The largest source of Sr-90 in the environment

(-99%) is from weapons testing fallout. Approximately 16.8 million curies of Sr-90 were produced and globally dispersed in atmospheric nuclear weapons testing until 1980. As a result of the Chernobyl accident, approximately 216 , 000 curies of Sr-90 were released into the atmosphere.

With a 28-year half-life , Sr-90 still remains in the environment at nominal levels. The total annual release of Sr-90 into the atmosphere from all 103 commercial nuclear power plants operating in the United States is typically 111000th of a curie. (NUREG/CR-2907 Vol.12). At an individual nuclear power plant , the amount of Sr-90 is so low that it is usually at or below the minimum detectable activity of sensitive detection equipment.

Oyster Creek did not report any Sr-90 released in the Annual Radioactive Effluent Release Report as all analyses for Sr-90 performed were less than the minimum detectable activity. Gamma Spectrometry Vegetation samples from locations 35 , 36 , 66 , and 115 were 31 L analyzed for concentrations of gamma-emitting nuclides (Table C-Vlll.1, Appendix C). Naturally-occurring K-40 activity was found in all samples and ranged from 1,344 to 6 , 986 pCi/kg wet. Naturally-occurring Be-7 was detected in 27 of 41 samples and ranged from 186 to 812 pCi/kg wet. Cs-137 was detected in 3 samples and ranged from 19 to 72 pCi/kg wet. All other nuclides were less than the MDC. Preoperational vegetation sample analyses did not include strontium analyses or gamma spectroscopy. Oyster Creek conducted a Cs-137 study in 2006/2007. A report was generated titled "Evaluation of Cesium-137 in Environmental Samples from the Amergen Property East of the Oyster Creek Generating Station". Below is an excerpt from that report: " The levels of Cs-137 observed in the soil and vegetation samples are consistent with environmental concentrations known to be attributable to fallout from historic nuclear weapons testing and the Chernobyl accident.

In addition , the variability of Cs-137 concentrations in soil and vegetation on the farm property appears to be driven by a number of environmental factors. Cs-137 concentrations in soil were non-detectable. Vegetation samples exhibited Cs-137 concentrations from non-detectable to 0.130 pCi/g , with a mean concentration of 0.078 pCi/g. For comparison , in the year 2000 , as part of the confirmatory release survey for the adjacent Forked River site to the west of OCGS , the NRC reported that the maximum observed soil concentration of 0.53 pCi/g was not distinguishable from the variation in Cs-137 in the environment due to these fallout sources. The NRC also reported background Cs-137 concentrations in New Jersey coastal plain soils as high as 1.5 and 2.8 pCi/g. In addition , decay-corrected historic REMP data from a predominantly upwind location , nearly four miles from the OCGS, yields present-day Cs-137 concentrations ranging from 0.862 to 1.68 pCi/g." In 2017 , there was no Cs-137 identified in REMP soil samples , but it was detected in 3 vegetation samples. The concentrations ranged from 19 to 72 pCi/kg wet. It is not unusual for Cs-137 to be identified given the known environmental levels of this radionuclide attributable to atmospheric nuclear weapons testing and the Chernobyl accident.

32 In conclusion, terrestrial monitoring results for vegetation samples during 2017 showed only naturally-occurring radioactivity and radioactivity associated with fallout from past atmospheric nuclear weapons testing and Chernobyl.

The radioactivity levels detected were consistent with levels measured in past years, and no radioactivity attributable to activities at OCGS was detected in any terrestrial samples. The terrestrial monitoring data show no adverse long-term trends in the terrestrial environment.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured using Optically Stimulated Luminenscence Dosimeters (OSLO). Sixty-one OSLO locations were monitored around the site. Results of non-background corrected OSLO measurements are summarized in Tables C-IX.1 to C-IX.3 and Figures C-6 and C-7. The non-background corrected OSLO measurements ranged from 4.9 to 22.6 mR/standard quarter. In order to correct these results for background radiation, the mean of the dose rates measured at the background OSLO stations (C and 14) was subtracted from the dose measured at each indicator station. The maximum annual background corrected dose was 12.6 mR/year at Station 55 , located near the site boundary , 0.3 miles west of the OCGS. This OSLO is located in an area where public access is restricted but the nearest member of the public for direct radiation is considered an individual that works in the warehouse west of the site. The individual is assumed to work 2 , 000 hours0 days 0 hours 0 weeks 0 months per year at this location.

The preoperational environmental monitoring program utilized film badges, the results of which are not comparable with the doses measured using thermoluminescent dosimeters or optically stimulated dosimeters during the operational REMP. In conclusion , the 2017 OSLO results are consistent with past operational measurements of direct radiation, and demonstrate that the OCGS continues to be in compliance with the 40 CFR 190 limit on maximum dose to the public. D. Land Use Survey A Land Use Survey , conducted in September 2017 around the Oyster Creek Generating Station (OCGS), was performed by Normandeau Associates, Inc. for Exelon Nuclear. The purpose of the survey is to identify within a distance of 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 500 ft 2 producing broad leaf 33 vegetation. The census shall also identify within a distance of 3 miles the location in each of the 16 meteorological sectors all milk animal and all gardens greater than 500 square feet producing broadleaf vegetation. For animals producing milk for human consumption in each of the sixteen meteorological sectors out to a distance of 5 miles from the OCGS, none were observed. The distance and direction of all locations from the OCGS Reactor Bu i ld i ng were determined using Global Positioning System {GPS) technology. Though there was a garden found closer in the ENE sector , there were no changes required to the OCGS REMP since that garden is not used in the sample program. The results of this survey are summarized below: Distance in Feet from the OCGS Reactor Building Sector Residence (ft) Garden* (ft) 1 N 5 , 655 6,434 2 NNE 3 , 240 3 , 541 3 NE 3 , 245 5 , 115 4 ENE 5 , 704 6 , 093 5 E 6 , 549 1 , 758 6 ESE 3, 189 2 , 081 7 SE 3 , 073 2,321 8 SSE 4 , 666 5 , 248 9 S 7,971 8,328 10 SSW 8,344 8,690 11 SW 9 , 285 9,776 12 WSW 10 , 713 14 , 802 13 W 22 , 191 None 14 WNW None None 15 NW 27 , 985 None 16 NNW 7,506 12,159 *Greater than 500 ff in size producing broad leaf vegetation E. Summary of Results -Inter-laboratory Comparison Program The TBE Laboratory analyzed Performance Evaluation (PE) samples of air particulate , air iodine , milk , soil , vegetation, and water matrices for various analytes. The PE samples supplied by Analytics Inc., Environmental Resource Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

A. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by 34 Analytics , TBE evaluates the reported ratios based on internal QC requirements based on the DOE MAPEP criteria. B. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA , National Environmental Laboratory Accreditation Conference (NELAC}, state-specific Performance Testing (PT) program requirements or ERA's SOP for the Generation of Performance Acceptance Limits , as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

C. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. MAPEP defines three levels of performance:

Acceptable (flag = " A") -result within +/- 20% of the reference value

Acceptable with Warning (flag = " W') -result falls in the +/- 20% to +/- 30% of the reference value

Not Acceptable (flag = "N") -bias is greater than 30% of the reference value Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities. For the TBE laboratory, 168 out of 173 analyses performed met the specified acceptance criteria.

Five analyses did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program. 1. The ERA April 2017 two nuclides in water were evaluated as Not Acceptable. (NCR 17-09) a. The Zn-65 result of 39.3 pCi/L , exceeded the lower acceptance limit of 47.2. The known value was unusually low for this study. The sample was run in duplicate on two different detectors. The results of each were 39.3 +/- 18.2 pCi/L (46% error and lower 35 efficiency) and 59.3 +/- 8.23 pCi/L (13.9% error and higher efficiency).

The result from the 2nd detector would have been well within the acceptable range (47.2 -65.9) and 110.2% of the known value of 53.8 pCi/L. b. The Sr-89 result of 40.7 pCi/L exceeded the lower acceptance limit of 53.8. All associated QC and recoveries were reviewed and no apparent cause could be determined for the failure. The prior three cross-check results were from 99 -115% of the known values and the one that followed this sample (November, 2017) was 114% of the known value. 2. The DOE MAPEP August 2017 air particulate U-238 result of 0.115 +/- 0.025 Sq/sample was higher than the known value of 0.087 +/- 0.002 with a ratio of 1.32, therefore the upper ratio of 1.30 (acceptable with warning) was exceeded. TSE's result with error easily overlaps with the acceptable range. MAPEP does not evaluate results with any associated error. Also , the spike level for this sample was very low (2.35 pCi) compared to TSE's normal LCS of 6 pCi. TSE considers this result as passing. (NCR 17-15) 3. The Analytics September 2017 soil Cr-51 result was evaluated as Not Acceptable (Ratio of TSE to known result at 0.65). The reported value was 0.230 +/- 0.144 pCi/g and the known value was 0.355 +/- 0.00592 pCi/g. The sample was counted overnight for 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months , however the Cr-51 was spiked at a very low level and had a counting error of 65%. Cr-51 has a 27-day half-life, making level quantification even more difficult.

The error does not appear to have been taken into consideration for this result. If it had been evaluated with the error, the highest result would have been 105% of the reference value, which is acceptable. Also , the known value is significantly lower than TSE's typical MDC for this nuclide in a soil matrix and would typically not be reported to clients (unless specified).

The results of all of the previous cross-checks have been in the acceptable (80 -120%) range. TSE will evaluate further upon completion of the next ICP sample. (NCR 17-16) 4. The ERA November 2017 water Sr-90 sample was evaluated as Not Acceptable.

TSE's result of 27.1 pCi/L exceeded the lower acceptance range (30.8 -48.0 pCi/L). After reviewing the associated QC data for this sample, it was determined that a l though the spike recovery for Sr-90 was within our laboratory guidelines (70% -130%), both the spike result and our ERA result were biased low. The original cross-check sample was completely consumed and we were unable to reanalyze before submitting the 36 result. We have modified our preparation process to avoid this situation for future cross-check samples. We also have enhanced LIMS programming to force a LCSD when a workgroup includes cross-check samples (as opposed to running a DUP). (NCR 17-19) The Environmental , Inc., Midwest Laboratory ana l yzed Pe rf ormance Evaluation (PE) samples of air particulate , soil , water , and vegetation for various analytes.

For the EIML laboratory , 181 of 189 analyses met the specified acceptance criteria. Eight analyses did not meet the specified acceptance criteria for the following reasons: 1. The MAPEP February 2017 wate r Co-57 result of 2.7 Bq/L sample was lower than the known value of 28.5 Bq/L sample. The decimal point was misplaced while performing a unit conversion. The result is within control limits when the proper un i t conversion is performed. 2. The MAPEP February 2017 air filter Am-241 result of 0.0540 Sq/total sample was higher than the known value of 0.0376 Sq/total sample. The sample was reanalyzed in duplicate w i th acceptable results. Original plating was inferior to plating obta i ned during reanalysis.

It i s believed that isotopic trace r was not accurately quantified due to poor resolution of its peak. 3. The ERA March 2017 MRAD air filter Fe-55 result of 590 pCi/filter was higher than the known value of 256 pCi/filter , exceeding the upper control limit of 500 pCi/filter. The 1000-minute recount result of 254 pCi/filter fell within acceptance criteria. 4. The ERA March 2017 MRAD air filter Gross Beta result of 67.6 pC i/filter was higher than the known value of 45.2 pCi/filter , exceeding the lower control limit of 65.9 pCi/filter. ERA appears to have applied the standard material to the filter in a pattern closer to the center of the filter compared to previous studies and different from the filter efficiency utilized by the lab , causing the effic i ency calculation to be understated and the lab result to be overstated. Associated QC was acceptable. 5. The ERA March 2017 MRAD soil Pu-239/240 result of 252 pCi/kg was lower than the known value of 484 pCi/kg , exceeding the lower control limit of 316 pC i/kg. The sample was reanalyzed in duplicate with acceptable results. Suspected poor electroplating for low orig i nal analysis result. 37

6. The ERA March 2017 MRAD soil U-233/234 result of 1 , 030 pCi/kg was lower than the known value of 1,950 pCi/kg, exceeding the lower control limit of 1, 190 pCi/kg. The sample was reanalyzed in duplicate with acceptable results. Suspected poor electroplating for low orig i nal analysis result. 7. The ERA March 2017 MRAD water Fe-55 result of 1 , 400 pCi/L was higher than the known value of 984 pC i/L , exceeding the upper control limit of 1 , 340 pCi/L. The sample was recounted with results in the acceptable range. 8. The MAPEP August 2017 air filter Am-241 result of 0.0400 Sq/total sample was lower than the known value of 0.0612 Sq/total sample. The laboratory is not currently offer i ng analys i s for air particulate Am-241. The Inter-Laboratory Comparison Program provides evidence of " in control" counting systems and methods , and that the laboratories are producing accurate and reliable data. V. References

1. Exelon Nuclear Offsite Dose Calculation Manual for Oyster Creek Generating Station , Procedure CY-OC-170-301. 2. United States Nuclear Regulatory Commission Branch Technical Position , An Acceptable Radiological Environmental Monitoring Program , Revision 1 , November 1979. 3 Pre-Operational Environmental Radiation Survey , Oyster Creek Nuclear Electric Generating Station , Jersey Central Power and Light Company , March 1968. VI. Errata There was no errata data for 2017. 38 Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK G E NERATING STATION, 2017 NAME OF F AGILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER: 50-219 LOCATION OF FACILITY: OCEAN COUNTY , NJ REPORTING PERIOD: 2017 IN DI CATOR CON T ROL LOCATION WI TH HIGH E S T ANNUA L MEAN (M) MEDIUM OR REQUIRED LOC ATIONS L OCA T ION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN (M) MEAN (M) STATION# NON ROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECT ION (F) (F) (F) NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND D I R E CTION MEASUREMENTS SURFACE WATER H-3 28 200 <LLD <LLD 0 (PCIIL/TER)

GAMMA 28 MN-54 1 5 *<LLD <LLD u C0-58 15 <LLD <LLD u FE-59 30 *<LLD <LLD u C 0-60 15 <LL D <LLD u ZN-65 30 <LLD <LLD u NB-95 15 <LLD <LLD u ZR-95 3 0 -<LLD <LLD u 1-131 1 5 *<LLD <LLD u )> CS-134 1 5 <LLD <LLD u I CS-137 18 -<LLD <LLD u .... BA-140 60 <LLD <LLD u LA-140 15 <LLD <LLD u DRINKING WA TE R H-3 52 NA <LLD <LLD 0 {PCI/LITER)

GR-B 51 4 4.8 2.1 9.1 1N INDICATOR 0 (37/39) (5/1 2) (11/1 1) ON-SIT E DOMESTIC WELL AT OCGS T.8 -12.9 1.3-2.3 2. -12.9 0.2 MILES N OF SITE 1-131 (L OW LVL) 52 <LL D <LLD 0 GAMMA 52 M N-54 15 <LLD <LLD u C0-58 15 <LLD <LLD u FE-59 3 0 <LLD <LLD u C0-60 1 5 <L LD <LLD u ZN-65 30 <LLD <LLD u NB-9 5 15 <LL D <LLD u Z R-95 30 <LL D <LLD u CS-134 1 5 <L LD <LLD u CS-137 18 <LLD <LLD u BA-140 60 <L LD <LLD u LA-140 1 5 <L LD <LLD u (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indieated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CRE E K GENERATING STATION, 2017 NAME OF F AGILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER: 50-219 LOCATION OF FACILITY: OCEAN COUNTY , NJ REPORTING PERIOD: 2017 IN D ICATOR CONTROL LOCAT I ON WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR REQUIRED L OC ATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION# NONROUTINE (UNITO F ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD) RANGE RANGE RANGE D I STANCE AND D I RECTION MEASUREMENTS GROUNDWATER H-3 8 200 <LLD NA 0 (PC/IL/TE R) GAMMA 8 MN-54 15 *<LLD NA 0 C0-58 15 <LLD NA 0 FE-59 30 *<LLD NA 0 C0-60 15 -<LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0 )> ZR-95 30 <LLD NA 0 I 1-131 15 *<LLD NA 0 I\.) CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 BA-140 60 *<LLD NA 0 LA-140 15 <LLD NA 0 BOTTOM FEEDER GAMMA 5 (PCI/KG WET) K-40 NA 2918 3477 3477 94 C ONTROL 0 (3/3) (212) (2/2) GREAT BAY A.ITTLE EGG HARBOR 2583 -3213 3322 -3 632 3 322 -3632 20.0 MILES SSW OF S IT E MN-54 130 <LLD NA 0 C0-58 130 <LLD NA 0 FE-59 260 <LLD NA 0 C0-60 130 <LLD NA 0 ZN-65 260 <LLD NA 0 CS-134 130 <LLD NA 0 CS-137 150 <LLD NA 0 (M) The Mean Value s are c alculated using the positive values. {f) Fraction of detectable measurem e nt are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2017 NAME OF F AGILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER: 50-219 LOCATION OF FACILITY: OCEAN COUNTY, NJ REPORTING PERIOD: 2017 IN DI CATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN(M) MEAN (M) STATION# NONROUTINE (UNITOF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS PREDATOR GAMMA 10 (PCI/KG WET} K-40 NA 3645 3929 3929 94CONTROL 0 (6/6) (414) (4/4) GREAT BAY/LITTLE EGG HARBOR 2977

4573 3601-4112 3601-4112 20.0 MILES SSW OF SITE MN-54 130 <LLD <LLD u C0-58 130 <LLD <LLD u FE-59 260 <LLD <LLD u C0-60 130 <LLD <LLD u ZN-65 260 <LLD <LLD u CS-134 130 <LLD <LLD u CS-137 150 <LLD <LLD u )> , Cl,) CLAMS GAMMA 6 (PCIIKG WET} K-40 NA 1444.5 1440 1445 24 INDICATOR 0 (4/4) (2/2) (2/2) BARNEGAT BAY 1250

1640 713

2167 1250-1640 2.1 MILES E OF SITE MN-54 130 <LLD <LLD u C0-58 130 <LLD <LLD u FE-59 260 <LLD <LLD u C0-60 130 <LLD <LLD u ZN-65 260 <LLD <LLD u CS-134 130 <LLD <LLD u CS-137 150 <LLD <LLD u CRABS GAMMA 2 (PCIIKG WET} K-40 NA 2274.5 NA 2981 33 INDICATOR 0 (2/2) (1/1) EAST OF RT 9 BRIDGE IN OCGS DISCHARGE 1568

2981 0.4 MILES ESE OF SITE MN-54 130 <LLD NA u C0-58 130 <LLD NA u FE-59 260 <LLD NA u C0-60 130 <L LD NA u ZN-65 260 <L LD NA u CS-134 130 <LLD NA u CS-137 150 <LLD NA u (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2017 NAME OF FACILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER: 50-219 LOCATION OF FACILITY:

OCEAN COUNTY , NJ REPORTING PERIOD: 2017 IN DI CATOR CONTROL LOCATION WITH HIGHEST ANNUA L MEAN (M) MEDIUM OR REQUIRED L OC ATIONS L OCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN(M) MEAN (M) STATION# NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD) RANG E RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SEDIMENT GAMMA 8 (PCI/KG DRY) BE-7 NA ..:LLD 1443 1443 94CONTROL 0 (1/2) (1/2) GREAT BAY/LITTLE EGG HARBOR 20.0 MILES SSW OF SITE K-40 NA 8095 14835 14835 94CONTROL 0 (6/6) (2/2) (2/2) GREAT BAY/LITTLE EGG HARBOR 388'2 -15 , 850 13,740-15 , 930 13.740 -15 , 930 20.0 MILES SSW OF SITE MN-54 NA <LLD <LLD 0 C0-58 NA *<L LD <LLD 0 C0-60 NA <LLD <LLD 0 CS-134 150 <LLD <LLD 0 )> CS-137 180 *<LLD <LLD 0 , Ra-226 NA 1657 <LLD 2238 24 INDICATOR 0 .i::,. (5/6) (1/2) BARNEGAT BAY 983-2238 2.1 M I LES E OF SITE Th-226 NA 503 651 651 94CONTROL 0 (6/6) (2/2) (212) GREAT BAY/LITTLE EGG HARBOR 361-613 499-803 499-803 20.0 MILES SSW OF SITE AIR PARTICULATE GR-B 410 10 12 12 13 CCONTROL 0 (E-3 PC/ICU.METER)

(262/306)

(90/104) (46/52) JCP&L OF F ICE -COOKSTOWN NJ 5-24 5-22 6 -22 24.7 MILES NW OF SITE SR-89 32 10 <LLD <LLD 0 SR-90 32 10 <LLD <LLD 0 GAMMA 32 BE-7 NA 61.5 69.2 74.7 73 IN DICATOR 0 (24/24) (8/8) (4/4) BAY PARKWAY -SANDS POINT HARBOR 46.3 -96.9 48.8 -92.7 54.0 -96.9 1.8 MILES ESE OF SITE MN-54 NA <LLD <LLD 0 C0-58 NA <L LD <LLD 0 C0-60 NA <LLD <LLD 0 CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD 0 (M) The Mean Values are calculated using the positive values. (f) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GE NERATING STATION, 2017 NAME OF F ACILITY: OYS T ER CR EE K G E NERA T ING S T A T ION DO CK E T NUMBER: 50-21 9 LOCATION OF FACILITY:

OC E AN COUNTY , NJ RE PO RTING PERIOD: 2017 I NDIC A TO R CONTRO L L OCA TI ON WI TH HIGH E ST ANNUA L MEAN (M) MEDIUM OR REQUIRED L OC A T IONS L O C A T ION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN(M) MEAN (M) STATION# NONROUTINE (UNITOF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS AIR I ODIN E GAMMA 411 (E-3 PC/ICU.METER) 1-131 70 <LLD <LLD 0 V EGET ATION S R-89 41 2 5 <LLD <LLD 0 (PCIIKGWET)

SR-90 41 5 8.9 4 10.9 115 INDICATOR 0 (21/29) (4/12) (10/12) EAST OF SITE ON FINNINGER FARM 3.8-20.3 3-4.5 5.9-20.3 0.3 MILES E OF SITE G AMMA 41 )> BE-7 NA 438.9 266.6 640.6 66 INDICATOR 0 ' (20/29) (7/12) (5/6) EAST O F RT 9 AND SOUTH OF OCGS DISCHG C1I 185.5 -811.5 196-467.4 316.7 -811.5 0.4 MILES SE OF SITE K-40 NA 2482.5 3895.6 3895.6 36CONTROL 0 (29/29) (12/12) (12/12) LI.PICK FARM -NEW EGYPT NJ 1344 -4010 1359-6986 1359-6986 23.1 MILES NW OF SITE /-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 8 0 37.7 <LLD 37.7 1151NDICATOR 0 (3/29) (3/11) EAST OF SITE ON FINNINGER FARM 19.5-72.1 19.5 -72.1 0.3 MILES E OF SITE BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 DI R ECT RA DIA TIO N OSLD-Q UA RTERL Y 242 NA 9.5 10 20.2 55 INDICATOR 0 (MILL/REM/STD.MO.)

(234/234) (8/8) (4/4) SOUTHERN AREA STORES SECURITY FENCE 4.9-226 8-12.3 17.5

226 0.3MILES W (M) The Mean Values are calculated using the positive values. (f) Fraction of detectable measurement are indicated in parentheses.

Intentionally left blank APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION

& ANALYTICAL METHODS Intentionally left blank TABLE B-1: Sample Medium Station Code Distance Az i muth Descr i ption Location Designat i on and Identification System for the Oyster Creek Generating Stat i on APT = Ai r Particulate Clam = Clam AIO = Air Iodine OSLO = Optically Stimulated ow = Dr i nking Water Dos i metry VEG = Vegetation Fish = F i sh SWA = Surface Water Crab = Crab AQS = Aquatic Sediment GW = Ground Water Station's Designation D i stance from the OCGS in miles Az i muth with respect to the OCGS in degrees Meteorological sector in which the station is located and a narrative descript i on B-1 TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations , Distance and Direction, Oyster Creek Generating Station , 2017 Sample Station Distance Azimuth Medium Code (miles) (degrees)

Description OSLO 0.4 219 SW of site at OCGS Fire Pond, Forked River , NJ ow 1S 0.1 209 On-site southern domestic well at OCGS , Forked River , NJ ow 1N 0.2 349 On-site northern domestic well at OCGS , Forked River , NJ APT , AIO , OSLO 3 6.0 97 East of site , near old Coast Guard Station , Island Beach State Park OSLO 4 4.6 213 SSW of site , Route 554 and Garden State Parkway , Barnegat, NJ OSLO 5 4.2 353 North of site , at Garden State Parkway Rest Area , Forked River , NJ OSLO 6 2.1 13 NNE of site , Lane Place , behind St. Pius Church, Forked River , NJ OSLO 8 2.3 177 South of site , Route 9 at the Waretown Substation , Waretown , NJ OSLO 9 2.0 230 WSW of site , west of where Route 532 and the Garden State Parkway meet , Waretown , NJ CJ APT , AIO , OSLO NW of site , JCP&L office in rear parking l ot , Cookstown , NJ I C 24.7 313 I\) OSLO 11 8.2 152 SSE of site , 80 11, and Anchor Streets , Harvey Cedars , NJ OSLO 14 20.8 2 North of site , Larrabee Substation on Randolph Road , Lakewood , NJ APT , AIO 20 0.7 95 East of site , on F ill ninger Farm on south side of access road , Forked River , NJ OSLO 22 1.6 145 SE of site , on Long John Silver Way , Sk i ppers Cove , Waretown , NJ SWA , CLAM , AQS 23 3.6 64 ENE of site , Barnegat Bay off Stouts Creek , approximately 400 yards SE of " Flashing Light 1" SWA , CLAM , AQS 24 2.1 101 East of site , Barnegat Bay , approximately 250 yards SE of " Flashing Light 3" SWA , AQS , 33 0.4 123 ESE of site , east of Route 9 Bridge in OCGS Discharge Canal FISH , CRAB VEG 35 0.4 111 ESE of site , east of Route 9 and north of the OCGS Discharge Canal , Forked River , NJ VEG 36 23.1 319 NW of site , at " U-Pick" Farm , New Egypt , NJ TABLE 8-2: Radiological Environmental Mon i toring Program -Sampling Locations , Distance and Direction , Oyster Creek Generating Station , 2017 Sample Station Distance Azimuth Medium Code (miles) (degrees)

Description OW 37 2.2 18 NNE of Site , off !Boox Road at Lacey MUA Pumping Station , Forked R i ver , NJ ow 38 1.6 197 SSW of Site , on Route 532 , at Ocean Township MUA Pumping Station , Waretown , NJ ow 39 3.5 353 North of Site , Trenton Ave. off Lacey Rd , Lacey Twp. MUA Pump Station , Forked River , NJ OSLO 46 5.6 323 NW of site , on Lacey Road , adjacent to utility pole BT 259 65 , Forked River , NJ OSLO 47 4.6 26 NNE of site , Route 9 and Harbor Inn Road , Bayville , NJ OSLO 48 4.5 189 South of site , at intersection of Brook and School Streets , Barnegat , NJ OSLO 51 0.4 358 North of site, on the access road to Forked River site, Forked River, NJ OSLO 52 0.3 333 NNW of site , on the access road to Forked River site , Forked River , NJ CD I (.I) OSLO 53 0.3 309 NW of site , at sewage lift station on the access road to the Forked River site , Forked River , NJ OSLO 54 0.3 288 WNW of site , on the access road to Forked River site , Forked River , NJ OSLO 55 0.3 263 West of site , on Southern Area Stores security fence , west of OCGS Switchyard, Forked River, NJ OSLO 56 0.3 249 WSW of site , o n utility pole east of Southern Area Stores , west of the OCGS Switchyard , Forked River , NJ OSLO 57 0.2 206 SSW of site , on Southern Area Stores access road , Forked River , NJ OSLO 58 0.2 188 South of site , on Southern Area Stores access road , Forked River , NJ OSLO 59 0.3 166 SSE of site , oni Southern Area Stores access road , Waretown , NJ OSLO 61 0.3 104 ESE of site , oni Route 9 south of OCGS Main Entrance , Forked River , NJ

*---------TABLE 8-2: Radiological Environmental Monitoring Program -Sampling Locations , Distance and D i rection , Oyster Creek Generating Station , 2017 Sample Station Distance Azimuth Code {miles) {degrees)

Description OSLO 62 0.2 83 East of site , o n Route 9 at access road to OCGS Main Gate , Forked R i ve r, NJ OSLO 63 0.2 70 ENE of site , o n Route 9 , between ma i n gate and OCGS North Gate access road , Forked River , NJ OSLO 64 0.3 42 NE of s i te , 0 111 Route 9 North at entrance to F i nn i nger Farm , Forked R i ver , NJ OSLO 65 0.4 19 NNE of site , on Route 9 at Intake Canal Bridge , Forked River , NJ APT , AIO , 66 0.4 133 SE of site , ea st of Route 9 and south of the OCGS D i scharge Canal , I nside fence , Waretown , NJ OSLO , VEG OSLO 68 1.3 266 West of site , on Garden State Pa r kway North at mile marker 71.7 , Lacey Township , NJ APT , AIO , OSLO 71 1.6 164 SSE of site , o n Route 532 at the Waretown Municipal Building , Waretown , NJ APT , AIO , OSLO 72 1.9 25 NNE of site , on Lacey Road at Knights of Columbus Hall , Forked River , NJ CXl APT , AIO , OSLO 7 3 1.8 108 ESE of site , o n Bay Parkway , Sands Po i nt Harbor , Waretown , NJ I .i:,. OSLO 74 1.8 88 East of site , Cxlando Drive and Penguin Court , Forked River , NJ OSLO 75 2.0 71 ENE of site , Beach Blvd. and Mau i Drive , Forked R i ver , NJ OSLO 78 1.8 2 North of site , 1 514 Arient Road , Forked River , NJ OSLO 79 2.9 160 SSE of site , H i ghtide Drive and Bonita Drive , Waretown , NJ OSLO 81 3.5 201 SSW of site , on Rose Hill Road at intersection with Barnegat Boulevard , Barnegat , NJ OSLO 82 4.4 36 NE of site , Ba y Way and Clairmore Avenue , Lanoka Harbor , NJ OSLO 84 4.4 332 NNW of site , on Lacey Road , 1.3 m i les west of the Garden State Parkway on siren pole , Lacey Township , NJ OSLO 85 3.9 250 WSW of site , on Route 532 , just east of Wells Mills Park , Waretown , NJ OSLO 86 5.0 224 SW of site , o n Route 554 , 1 m i le west of the Garden State Parkway , Barnegat , NJ TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations , Distance and Direction , Oyster Creek Generating Station , 2017 Sample Station Distance Azimuth Code l.!!!i..!lll (degrees)

Description OSLO 88 6.6 125 SE of site , eastern end of 3 r d Street , Barnegat Light , NJ OSLO 89 6.1 108 ESE of site , Job Francis residence , Island Beach State Park OSLO 90 6.3 75 ENE of site , parking lot A-5 , Island Beach State Park OSLO 92 9.0 108 NE of site , at Guard Shack/Toll Booth , Island Beach State Park FISH , CRAB 93 0.1 242 WSE of site , OCGS Discharge Canal between Pump D i scharges and Route 9 , Forked River , NJ SWA , AQS , 94 20.0 198 SSW of site , in Great Bay/Little Egg Harbor CLAM , FISH OSLO 98 1.6 318 NW of site , on Garden State Parkway North at mile marker 73 , Lacey Township , NJ OSLO 99 1.5 310 NW of site , on Garden State Parkway at mile marker 72.8 , Lacey Townsh i p , NJ OJ I U1 OSLO 100 1.4 43 NE of site , Yacht Basin Plaza South off Lakes i de Dr., Lacey Township , NJ OSLO 101 1.7 49 NE of site , end of Lacey Rd. East , Lacey Township , NJ OSLO 102 1.6 344 NNW of site , end of Sheffield Dr., Barnegat P i nes , Lacey Township , NJ OSLO 103 2.4 337 NNW of site , Llewellyn Pkwy., Barnegat P i nes , Lacey Township , NJ OSLO 104 1.8 221 SW of site , Rt. 532 West , before Garden State Parkway , Ocean Township , NJ OSLO 105 2.8 222 SW of site , Garden State Parkway North beside mile marker 69.6 , Ocean Township , NJ OSLO 106 1.2 288 WNW of si t e , Garden State Parkway North beside mile marker 72.2 , Lacey Townsh i p , NJ OSLO 107 1.3 301 WNW of si t e , Garden State Parkway North beside mile marker 72.5 , Lacey Township , NJ OSLO 109 1.2 141 SE of site , Lii ghthouse Dr., Waretown , Ocean Township , NJ TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations , Distance and Direction , Oyster Creek Generating Station , 2017 Sample Station Distance Azimuth Medium Code (miles) (degrees)

Description OSLD 110 1.5 127 SE of site , Tiller Dr. and Admiral Way , Waretown , Ocean Townsh i p , NJ APT , AIO 111 0.3 64 ENE of site , Finninger Farm property along access road , Lacey Township , NJ OLSD 112 0.2 176 S of site , along southern access road OLSD 113 0.3 90 E of site , along Rt.9 , North DW 114 0.8 267 Well at Bldg 25 on Forked River site VEG 115 0.3 96 E of Site , on Finninger Farm OSLD T1 0.4 219 SW of site , at OCGS Fire Pond , Forked River , NJ GW MW-24-3A 0.8 97 ESE of site , Finninger Farm on South side of access road , Lacey Township , NJ OJ GW W-3C 0.4 112 ESE of s it e , Finninger Farm adjacent to Station 35 , Lacey Township , NJ I a, TABLE B-3: Sample Medium Drinking Water Drinking Water Drink i ng water Drinking Water Surface Water Surface Water Groundwater Groundwater Fish Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods , Oyster Creek Generating Station, 2017 Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number ER-OCGS-06 , Collection of water samples for TBE , TBE-2007 Gamma em i tting radioisotopes analysis radiological analysis Gamma Spectroscopy Monthly samples 1 gallon Env. Inc., GS-01 Determination of gamma emitters by CY-OC-120-1200 , REMP sample collection procedure

-well wate11' gamma spectroscopy ER-OCGS-06 , Collection of water samples for TBE , TBE-2010 Tritium and carbon-14 analysis by liquid radiological analysis scintillation Tritium Monthly samples 1 gallon CY-OC-120-1200 , REMP sample collection Env. Inc., T-02 Determ i nation of tritium in water (direct procedure

-well wate11' method) ER-OCGS-06 , Collection of TBE , TBE-2 031 Radioiodine in drinking water water samples for radiological analysis Iodine Monthly Samples 1 gallon Env. Inc., 1-131-01 Determination of 1-131 in water by CY-OC-120-1200 , REMP sample collection procedure

-well water anion exchange TBE , TBE-2008 Gross Alpha and/or gross beta activity in ER-OCGS-06 , Collection of various matrices water samples for radiological analysis Env. Inc., W(DS)-01 Determination of gross alpha and/or Gross Beta Monthly Samples 1 gallon CY-OC-120-1200 , REMP sample collection gross beta In water (dissolved solids or total residue) procedure

-well wate11' Env. Inc., W(SS)-02 Determ i nation of gross alpha and/or gross beta I n water (suspended sol i ds) ER-OCGS-06 , Collection of water samples for TBE , TBE-2007 Gamma emitting radioisotopes analysis Gamma Spectroscopy Grab Sample radiological analysis 1 gallon Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy ER-OCGS-06 , Collection of water samples for TBE , TBE-2 010 Tritium and carbon-1 4 ana l ysis by liquid Tritium Grab Sample radiological analysis 1 gallon scintillation Env. Inc., T-02 Determination of tritium in water (direct method) ER-OCGS-06 , Collection of water samples for TBE , TBE-2010 Tritium and carbon-1 4 analysis by liquid Tritium Grab Sample radiological analys i s 1 gallon scintillation Gamma Grab Sample ER-OCGS-06 , Collection of water samples for 1 gallon TBE , TBE-2007 Gamma-emitting radioisotopes analysis radiological analysis Semi-annual samples ER-OCGS-14 , Collection of fish samples for TBE , TBE-2007 Gamma emitting radioisotopes analysis Gamma Spectroscopy collected via hook and radiological analysis 250 grams (wet) Env. Inc., GS-01 Determination of gamma emitters by line technique and traps gamma spectroscopy TABLE B-3: Sample Medium Clams and Crabs Sediment Air Particulates Air Particulates en I (X) Air Particulates Air Iodine Vegetation Vegetation OSLO Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods , Oyster Creek Generating Station , 2017 Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Semi-annual and annual ER-OCGS-16 , Collection of clam and crab TBE , TBE-2007 Gamma emitting radioisotopes analysis Gamma Spectroscopy samples collected using samples for radiological analysis 300 grams (wet) Env. Inc., GS-01 Determination of gamma emitters by clam tongs and traps. gamma spectroscopy ER-OCGS-03 , Collection of aquatic sediment TBE , TBE-2007 Gamma emitting radioisotopes analysis Gamma Spectroscopy Semi-annual grab samples for radiological analysis 1000 grams (dry) samples Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy One-week composite of TBE , TBE-2008 Gross alpha and/or beta activity in continuous air sampling ER-OCGS-05 , Collection of air iodine and air 1 filter (approximately various matrices Gross Beta particulate samples for radiological analysis 300 cubic meters through glass fiber filter weekly) Env. Inc., AP-02 Determination of gross alpha and/or paper gross beta in air particulate filters TBE , TBE-2023 Compositing of samples 13 filters TBE , TBE-2007 Gamma emitting radioisotopes analysis Gamma Spectroscopy Quarterly composite of Env. Inc., AP-03 Procedure for compositing air (approximately 4000 each station particulate filters for gamma spectroscopic Env. Inc., GS-01 Determination of gamma emitters by analysis cubic meters) gamma spectroscopy Quarterly composite of ER-OCGS-05 , Collection of air iodine and air 13 filters Stronlium-89/90 particulate samples for radiological analys i s (approximately 4000 TBE , TBE-2019 Radiostrontium analysis by ion exchange each station cubic meters) One-week composite of ER-OCGS-05 , Collection of air iodine and air 1 filter (approximately TBE , TBE-2007 Gamma emitting radioisotopes analysis Gamma Spectroscopy continuous air sampling particulate samples for radiological analysis 300 cubic meters Env. Inc., 1-131-02 Determination of 1-131 in charcoal through charcoal filter weekly) canisters by gamma spectroscopy (batch method) ER-OCGS-04 , Collection of food products and TBE , TBE-2007 Gamma emitting radioisotopes analysis Gamma Spectroscopy Grab sample during broadleaf vegetation samples for radiological 1000 grams growing season analysis Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy ER-OCGS-04 , Collection of food products and Strontium-89/90 Grab sample during broad leaf vegetation samples for radiological 1000 grams TBE , TBE-2019 Radiostrontium analysis by ion exchange growing season analysis Optically Stimulated Quarterly OSLDs Luminescence comprised of two ER OCGS-02, Collection/Exchange of Field 2 dosimeters Landauer Incorporated Al 2 0a: C Landauer Dosimeters for Radiological Analysis Dosimetry Incorporated elements.

Oyster Creek Generating Station REMP Sample Locations within a 1 Mile Radius Q.3 0.15 0 0.3 Milti _c::::=_c:=:

___ _ Figure B-1 Locations of REMP Stations within a 1-mile radius of the Oyster Creek Generating Station 8-9 s Date: 09/04/1 2 Oyster Creek Gene r ating Stat i on REMP Sample Locations w i thin a 1 to 5 Mile Radius 1.5 0.7 5 1 5MHs _c:::_c:::

___ _ Figure B-2 Locations of REMP Stations within a 1 to 5-mile radius of the Oyster Creek Generating Station B-10 s Orne: 08/27/12 Oyster Creek Generating S t at i on REMP Sample Locations over a 5 Mile Radius 6, 2.1, a 5, , -c:::::::J-=:::::a---*

Figure 8-3 Locations of REMP Stations greater than 5 miles from the Oyster Creek Generating Station B-11 s Date: 0 8/27/1 2 Intentionally left blank APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY Intentionally left blank Table C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RES UL TS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 23 24 3 3 94 01/04/17 -01/26/17 < 1 8 6 < 184 01/31/17 -03/02/17 < 187 < 188 0 3/09/17 -03/29/17 < 19 8 < 194 04/07/17 -04/2 7/17 < 194 < 19 0 0 5/0 5/17 -06/01/17 < 1 89 < 1 90 < 1 85 < 181 06/08/17 -06/28/17 < 17 4 < 175 0 7 /0 6/17 -0 7 1261 17 < 191 < 195 08/0 2/17 -08/30/1 7 < 1 9 4 < 187 09/0 7/17 -09/2 8/17 < 18 3 < 178 1 0/0 4/17 -10/26/17 < 1 81 < 1 78 < 17 6 < 175 11/0 1/17 -11/2 9/17 < 177 < 17 6 12/06/17 -12/27/17 < 194 < 192 M EA N C-1 Table C-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 23 05/16/17 -05/16/17 <6 < 7 < 13 < 6 < 15 < 7 < 12 < 14 < 7 < 7 < 36 < 9 10/16/17 -10/16/17 < 7 <6 < 12 < 7 < 16 < 7 < 8 < 12 < 6 <6 < 28 < 13 MEAN 24 05/16/17 -05/16/17 < 5 < 6 < 14 < 6 < 14 <6 < 10 < 11 < 7 <5 < 30 < 9 10/17/17 -10/17/17 <6 <6 < 15 < 6 < 13 < 7 < 11 < 12 < 7 <6 < 29 < 9 MEAN 33 01/04/17 -01/25/17 < 7 < 6 < 15 <n < 14 < 7 < 13 < 12 < 8 < 8 < 29 < 11 01/31/17 -03/02/17 < 7 <6 < 13 < 7 < 10 < 8 < 12 < 9 < 7 < 7 < 25 < 8 03/09/17 -03/29/17 < 7 < 7 < 16 < 8 < 15 < 8 < 14 < 9 < 7 <8 < 28 < 9 () 04/07/17 -04/27/17 <6 < 5 < 13 < 6 < 11 < 7 < 13 < 9 <7 < 7 < 27 < 10 I 05/05/17 -06/01/17 <7 < 7 < 17 < 8 < 13 < 8 < 16 < 11 < 9 < 7 < 31 < 12 I\) 06/08/17 -06/28/17 < 8 < 8 < 18 < 7 < 18 < 7 < 13 < 11 < 7 < 8 < 38 < 13 07/06/17 -07/26/17 <9 <7 < 15 < 8 < 22 < 9 < 16 < 12 < 10 < 8 < 41 < 11 08/02/17 -08/30/17 < 8 < 7 < 20 < 7 < 18 < 9 < 15 < 14 < 11 < 9 < 36 < 12 09/07/17 -09/28/17 < 7 < 7 < 15 < 8 < 15 < 8 < 14 < 12 < 7 <8 < 37 < 8 10/04/17 -10/25/17 < 4 < 5 < 11 < 5 < 10 <5 < 8 < 8 < 6 < 5 < 24 < 8 11/01/17 -11/29/17 < 9 <6 < 17 < 6 < 17 < 7 < 14 < 11 < 9 < 8 < 27 < 12 12/06/17 -12/27/17 < 4 <6 < 15 < 8 < 16 <6 < 10 < 10 < 7 <6 < 32 < 8 MEAN 94 01/04/17 -01/26/17 < 9 < 8 < 21 < 10 < 28 < 10 < 19 < 13 <8 <9 < 38 < 11 01/31/17 -03/02/17 < 9 <6 < 22 < 7 < 13 <9 < 16 < 11 < 10 < 10 < 40 < 8 03/09/17 -03/29/17 < 9 < 8 < 18 < 8 < 12 <8 < 17 < 14 < 9 < 10 < 45 < 10 04/07/17 -04/27/17 < 9 < 9 < 21 < 6 < 17 < 9 < 17 < 12 < 11 < 9 < 41 <6 05/05/17 -06/01/17 < 5 < 8 < 21 < 9 < 17 < 8 < 12 < 11 < 7 < 9 < 38 < 13 06/08/17 -06/28/17 < 7 < 7 < 14 < 9 < 14 < 9 < 13 < 13 < 8 < 8 < 34 < 9 07/06/17 -07/25/17 < 7 <6 < 16 < 6 < 15 <6 < 13 < 11 <6 < 7 < 29 < 11 08/03/17 -08/30/17 < 8 < 7 < 18 < 8 < 15 < 8 < 14 < 14 < 10 < 8 < 40 < 12 09/07/17 -09/28/17 < 7 < 8 < 15 < 9 < 18 < 8 < 16 < 15 < 8 < 8 < 34 < 13 10/04/17 -10/26/17 < 7 < 7 < 16 < 8 < 15 <6 < 14 < 9 < 8 < 8 < 34 < 11 11/03/17 -11/29/17 <6 <6 < 16 <6 < 13 < 7 < 12 < 11 < 7 <6 < 27 < 8 12/08/17 -12/27/17 < 8 < 9 < 15 < 10 < 20 <8 < 16 < 14 <7 < 9 < 33 < 13 MEAN Table C-11.1 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 114 1N 1S 37 38 01/03/17 -01/25/17 < 185 < 180 (1) < 181 < 178 01/31/17 -03/02/17 < 184 < 187 (1) < 189 < 188 03/08/17 -03/30/17 < 190 < 195 < 194 < 195 < 198 04/04/17 -04/27/17 < 184 < 188 < 191 < 186 < 188 05/02/17 -06/01 /17 < 182 < 186 < 180 < 181 < 181 06/06/17 -06/28117 < 176 < 174 (1) < 174 < 176 07/04/17 -07/26/17 < 195 < 194 < 195 < 199 < 196 08/01/17 -08/30/17 < 180 < 183 (1) < 186 < 184 09/05/17 -09/28/17 < 180 < 183 (1) < 184 < 183 10/03/17 -10/26/17 < 180 < 180 (1) < 176 < 176 10/31/17 -11/29/17 < 174 < 179 (1) < 178 < 178 12/05/17 -12/27/17 < 195 < 194 (1) < 192 < 193 MEAN Table C-11.2 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 114 1N 1S 37 38 01/03/17 -01/25/17 5.2 +/- 1.4 6.4 +/- 1.6 (1) < 1.7 1.8 +/- 1.2 01/31/17 -03/02/17 3.7 +/- 1.3 5.5 +/- 1.5 (1) < 1.6 2.1 +/- 1.1 03/08/17 -03/30/17 3.4 +/- 1.3 2.0 +/- 1.2 2.0 +/- 1.2 2.2 +/- 1.1 1.8 +/- 1.1 04/04/17 -04/27/17 3.5 +/- 1.3 12.3 +/- 1.9 3.4 +/- 1.4 < 1.6 2.4 +/- 1.2 05/02/17 -06/01 /17 2.7 +/- 1.2 (1) 2.1 +/- 1.2 2.0 +/- 1.1 < 1.5 06/06/17

06/28/1 7 3.0 +/- 1.2 12.4 +/- 1.8 (1) < 1.4 2.3 +/- 1.1 07/04/17 -07/26/17 5.6 +/- 1.4 11.7 +/- 1.8 2.5 +/- 1.2 2.3 +/- 1.1 1.8 +/- 1.1 08/01/17 -08/30/17 3.6 +/- 1.3 12.9 +/- 1.9 (1) < 1.6 2.5 +/- 1.2 09/05/17 -09/28/17 5.1 +/- 1.3 11.4 +/- 1.8 (1) 1.6 +/- 1.0 2.4 +/- 1.1 10/03/17 -10/26/17 4.0 +/- 1.7 10.6 +/- 1.8 (1) 2.3 +/- 1.1 < 2.8 10/31/17 -11/29/17 3.1 +/- 1.3 7.0 +/- 1.6 (1) < 1.7 1.9 +/- 1.2 12/05/17 -12/27/17 2.7 +/- 1.3 8.0 +/- 1.6 (1) < 1.6 2.6 +/- 1.2 MEAN :t 2 STD DEV 3.8 +/- 2.0 9.1 +/- 7.1 2.5 +/- 1.3 2.1 +/- 0.6 2.1 +/- 0.7 Table C-11.3 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION , 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 114 1N 1S 37 38 01/03/17 -01/25/17 < 0.6 < 0.7 (1) < 0.5 < 0.6 01/31/17 -03/02/17 < 0.6 < 0.6 (1) < 0.5 < 0.5 03/08/17 -03/30/17 < 0.4 < 0.5 < 1.0 < 0.6 < 0.5 04/04/17 -04/27 /17 < 0.5 < 0.7 < 0.8 < 0.5 < 0.5 05/02/17 -06/01 /17 < 0.8 < 4.9 < 0.8 < 0.6 < 0.6 06/06/17 -06/28/17 < 0.5 < 0.8 (1) < 0.8 < 0.5 07/04/17 -07/26/17 < 0.8 < 0.8 < 0.9 < 0.6 < 0.6 08/01/17 -08/30/17 < 0.6 < 0.5 (1) < 0.5 < 0.7 09/05/17 -09/28/17 < 0.5 < 0.7 (1) < 0.5 < 0.7 10/03/17 -10/26/17 < 0.7 < 0.8 (1) < 0.9 < 0.6 10/31/17 -11/29/17 < 0.8 < 0.6 (1) < 0.8 < 0.5 12/05/17 -12/27 /17 < 0.4 < 0.5 (1) < 0.4 < 0.5 MEAN Bold value indicates LLD was not met due to the age of the sample at the time of receipt at the laboratory THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-3 Table C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 114 01/04/17 -01/25/17 < 8 < 8 < 14 < 7 < 17 < 8 < 14 < 8 < 8 < 43 < 11 01/31/17 -03/02/17 < 7 < 9 < 14 < 7 < 17 < 8 < 13 < 8 < 9 < 31 < 9 03/08/17 -03/30/17 < 7 < 5 < 15 < 8 < 16 < 7 < 14 < 11 < 8 < 35 < 13 04/07 /17 -04/27 /17 < 5 < 7 < 10 < 8 < 11 < 7 < 13 < 7 < 9 < 28 < 9 05/05/17 -06/01 /17 < 8 < 7 < 19 < 7 < 17 < 9 < 12 < 9 < 7 < 38 < 13 06/06/17 -06/28/17 < 7 <6 < 12 < 6 < 15 <6 < 12 < 7 < 7 < 32 < 10 07/06/17 -07/25/17 < 5 <6 < 13 < 5 < 10 < 6 < 11 < 7 <6 < 31 <9 08/03/17 -08/30/17 <8 <9 < 14 < 8 < 18 < 7 < 14 < 9 < 10 < 38 < 11 09/07 /17 -09/28/17 < 8 <6 < 13 < 9 < 14 < 8 < 15 < 9 < 8 < 38 < 14 10/04/17 -10/26/17 < 4 < 3 < 9 < 3 < 9 < 4 < 7 < 5 < 3 < 20 <6 11/03/1 7 -11/29/17 < 7 < 9 < 19 < 7 < 15 < 10 < 15 < 8 < 9 < 36 < 14 12/08/17 -12/27/17 < 5 < 5 < 11 < 6 < 11 < 6 < 9 < 7 < 5 < 31 < 10 MEAN 1N 01 /03/17 -01 /25/17 < 8 < 5 < 15 < 9 < 10 < 8 < 9 < 8 < 8 < 38 < 9 02/02/17 -02/28/17 < 8 < 8 < 14 < 6 < 17 < 10 < 16 < 9 < 9 < 40 < 14 C) 03/08/17 -03/08/17 < 1 < 2 <4 < 1 < 3 < 2 < 3 < 2 < 1 < 19 <6 I :,. 04/14/17 -04/14/17 < 2 < 2 <5 < 2 < 4 < 2 <4 < 2 < 2 < 22 < 7 05/09/17 -05/09/17 < 1 <2 <4 < 1 < 3 < 2 < 3 < 1 < 1 < 21 <6 06/06/17 -06/27 /17 < 8 < 5 < 20 < 7 < 11 < 9 < 6 < 8 <6 < 32 < 12 07 /04/17 -07 /25/17 < 8 < 8 < 21 < 8 < 20 < 9 < 16 < 10 < 9 < 43 < 13 08/01/17 -08/29/17 < 9 < 8 < 19 < 9 < 19 < 10 < 16 < 10 < 9 < 44 < 14 09/05/17 -09/26/17 < 5 <6 < 12 < 5 < 11 < 6 < 8 < 6 <5 < 24 < 12 10/03/17 -10/24/17 < 5 < 5 <9 < 6 < 11 < 6 < 8 < 5 <6 < 22 < 8 10/31/17 -11/28/17 <4 < 5 < 9 < 6 < 14 < 7 < 8 < 5 < 5 < 26 < 10 12/05/17 -12/26/17 < 7 < 7 < 17 < 8 < 16 < 9 < 13 < 8 < 7 < 36 < 9 MEAN 1S 01/03/17 -01/25/17 (1) 02/02/17 -02/28/17 (1) 03/14/17 -03/28/17 < 8 < 9 < 17 < 8 < 15 < 10 < 12 < 7 < 8 < 32 < 13 04/04/17 -04/25/17 <6 < 5 < 14 <6 < 11 < 7 < 13 < 8 < 7 < 31 < 11 05/02/17 -05/30/17 < 8 < 7 < 17 < 9 < 15 < 8 < 11 < 8 < 7 < 38 < 12 06/06/17 -06/27/17 (1) 07/11/17 -07/18/17 < 5 < 5 < 11 < 5 < 10 < 5 < 8 < 5 < 4 < 35 < 10 08/01/17 -08/29/17 (1) 09/05/17 -09/26/17 (1) 10/03/17 -10/24/17 (1) 10/31/17 -11/28/17 (1) 12/05/17 -12/26/17 (1) MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION Table C-11.4 CONCENTRATIONS OF GAMMA EM IT TERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYS T ER CREEK GENERATING STATION , 2017 R ES U LT S IN U N ITS O F PCI/LI TER +/- 2 SI G MA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 37 01/04/17 -01/25/17 < 8 < 7 < 17 <8 < 10 < 7 < 11 < 7 < 7 < 30 < 14 01/31/17 -03/02/17 <6 < 7 < 13 < 7 < 15 < 9 < 12 < 9 < 9 < 36 < 12 03/08/17 -03/29/17 < 8 < 8 < 17 <6 < 19 < 7 < 12 < 9 < 9 < 40 < 10 04/05/17 -04/27/17 < 5 < 5 < 13 <6 < 10 < 6 < 11 <6 <6 < 32 <6 05/05/17 -06/01/17 < 7 < 7 < 15 <6 < 16 < 7 < 13 < 8 < 7 < 40 < 7 06/07/17 -06/28/17 <6 < 8 < 18 <6 < 13 < 9 < 13 < 10 < 7 < 38 < 10 07 /06/17 -07 /26/17 < 9 < 8 < 16 < 10 < 19 < 9 < 16 < 9 < 10 < 44 < 13 08/0 2/17 -08/30/17 <6 < 7 < 13 <6 < 14 < 7 < 11 < 6 < 5 < 29 < 9 09/07/17 -09/27/17 <6 <6 < 15 <6 < 15 < 8 < 13 < 7 < 7 < 32 < 11 10/04/17 -10/26/17 < 5 <6 < 13 < 7 < 11 < 6 < 11 < 6 <6 < 28 < 8 11/03/17 -11/29/17 < 10 < 9 < 18 < 12 < 20 < 9 < 12 < 11 <9 < 42 < 14 12/0 8/17 -12/27/17 <6 < 6 < 17 < 7 < 16 < 6 < 11 < 9 <6 < 35 < 11 MEAN 38 01/04/17 -01/25/17 < 8 < 7 < 18 <7 < 18 < 9 < 13 < 8 < 8 < 39 < 12 01/31/17 -03/02/17 < 8 < 8 < 17 < 7 < 14 < 8 < 14 < 8 < e < 34 < 9 (') 03/09/17 -03/30/17 < 5 < 6 < 14 < 7 < 16 <6 < 12 < 8 < 5 < 31 < 10 I CJl 04/05/17 -04/27 /17 < 5 <6 < 8 <6 < 13 <6 < 8 < 7 < 6 < 22 < 5 05/05/17 -06/01/17 < 7 < 8 < 19 < 10 < 13 < 9 < 15 < e < e < 38 < 12 06/0 8/17 -06/28/17 < 6 < 7 < 19 < 6 < 16 < 8 < 12 < 8 < 8 < 33 < 13 07 /06/17 -07126/17 < 6 < 4 < 15 < 5 < 12 <6 <6 < 7 < 7 < 28 < 9 08/03/17 -08/30/17 < 8 < 7 < 19 < 8 < 16 < 9 < 16 < 8 < 10 < 42 < 11 09/07/17 -09/28/17 < 6 <6 < 11 < 4 < 11 <6 < 10 < 7 < 5 < 32 < 8 1 0/0 4/17 -10/25/17 < 6 <6 < 12 <6 < 13 <6 < 10 < 7 < e < 26 < 8 11 /03/17 -11 /29/17 < 6 <6 < 12 < 11 < 11 < 8 < 12 < 8 < 7 < 34 < 9 12/08/17 -12/27/17 < 6 <6 < 8 <6 < 11 <6 < 8 < 6 <4 < 24 < 5 MEAN Table C-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD MW-24-3A W-3C 01/09/17 -01/09/17 < 193 < 195 04!0 7/17 -04!0 7/17 < 184 < 1 8 7 07/12/17 -07/12/17 < 191 < 193 10/12/17 -10/12/17 < 176 1 1 /09/17 -11 /09/17 < 179 MEAN C-6 Table C-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PC I/LITER+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MW-24-3A 01/09/17 -01/09/17 < 5 < 4 < 11 < 6 < 9 < 5 < 9 < 8 < 4 < 5 < 26 < 9 04/07 /17 -04/07 /17 < 5 < 6 < 11 < 7 < 11 < 7 < 10 < 8 < 6 < 6 < 27 < 9 07/12/17 -07/12/17 < 7 < 5 < 10 < 7 < 10 < 7 < 10 < 8 < 7 < 7 < 26 < 7 11/09/17 -11/09/17 < 6 < 7 < 13 < 6 < 15 < 6 < 12 < 13 < 8 < 7 < 36 < 9 MEAN W-3C 01/09/17 -01/09/17 < 5 < 7 < 14 < 6 < 12 < 6 < 12 < 11 < 6 < 6 < 28 < 11 04/07/17 -04/07/17 < 5 < 6 < 13 < 4 < 12 < 7 < 11 < 10 < 7 < 6 < 25 < 8 07/12/17 -07/12/17 < 9 < 8 < 19 < 7 < 18 < 10 < 14 < 15 < 9 < 9 < 40 < 13 10/12/17 -10/12/17 < 4 < 4 < 8 < 4 < 7 < 4 < 6 < 9 < 4 < 4 < 24 < 8 () MEAN I .....

Table C-IV.1 CONCENTRATIONS OF GAMMA E M ITTERS I N PREDATOR AND BOTTOM FEEDER (FISH) SAMPLES COLLECTED IN THE VIC IN ITY OF OYSTER CREEK GENERATING STATION , 2017 R E SULTS IN UNI TS O F PC I/K G W ET+/- 2 SIGMA C O LLECTION SITE PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 33 05/11/17 3510 +/- 1035 < 65 < 70 < 1 27 < 53 < 126 < 68 < 67 PREDATOR 05/15/17 4573 +/- 1205 < 84 < 62 < 145 < 80 < 141 < 85 < 87 1 0/18/17 2917 +/- 85 8 < 40 < 43 < 88 < 46 < 109 < 4 9 < 51 MEAN+/- 2 STD DEV 3667 +/- 1678 33 05/15/17 3213 +/- 824 < 40 < 52 < 92 < 52 < 92 < 37 < 45 BOTTOM FEEDER MEAN+/- 2 STD DEV 3213 +/- 0 93 05/17/17 3358 +/- 832 < 5 7 < 62 < 113 < 56 < 110 < 64 < 65 PREDATOR 10/17/17 3246 +/- 921 < 39 < 46 < 88 < 56 < 7 8 < 5 0 < 54 10/17/17 4266 +/- 786 < 65 < 63 < 143 < 81 < 125 < 67 < 60 (') I MEAN+/- 2 STD DEV 3263 +/- 1119 00 93 10/17/17 2583 +/- 735 < 51 < 46 < 91 < 47 < 112 < 4 8 < 57 BOTTOM FEEDER 10/17/17 2958 +/- 957 < 7 8 < 72 < 133 < 85 < 154 < 75 < 72 MEAN+/- 2 STD DEV 2771 +/- 530 94 05/16/17 4112 +/- 959 < 53 < 59 < 111 < 55 < 133 < 65 < 51 PREDATOR 05/16/17 3601 +/- 769 < 52 < 44 < 78 < 48 < 87 < 50 < 52 10/18/17 4067 +/- 801 < 4 7 < 44 < 128 < 48 < 117 < 48 < 56 10/18/17 3936 +/- 981 < 38 < 40 < 93 < 51 < 90 < 56 < 55 MEAN+/- 2 STD DEV 3929 +/- 462 94 05/16/17 3632 +/- 795 < 38 < 44 < 104 < 37 < 78 < 51 < 39 BOTTOM FEEDER 10/18/17 3322 +/- 1413 < 7 4 < 76 < 158 < 83 < 206 < 99 < 74 MEAN+/- 2 STD DEV 3477 +/- 438 THE MEAN AND TWO STANDARD DEV/A TION ARE CALCULA TE D USING THE POSITIVE VALUES Table C-IV.2 CONCENTRATIONS OF GAMMA EMITTERS IN CLAM AND CRAB SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/KG WET+/- 2 SIGMA COLLECTION SITE PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 23 Clams 05/16/17 1302 +/- 407 < 25 < 27 < 53 < 29 < 51 < 31 < 29 10/16/17 1586 +/- 970 < 72 < 68 < 202 < 76 < 167 < 77 < 71 MEAN +/- 2 STD DEV 1444 +/- 402 24 Clams 05/15/17 1250 +/- 501 < 42 < 32 < 64 < 33 < 83 < 31 < 34 10/16/17 1640 +/- 596 < 43 < 44 < 90 < 35 < 81 < 28 < 42 MEAN +/- 2 STD DEV 1445 +/- 552 0 33 I Crabs 10/16/17 2981 +/- 868 < 46 < 48 < 97 < 39 < 83 < 40 < 45 (0 MEAN +/- 2 STD DEV 2981 +/- 0 93 Crabs 10/16/17 1568 +/- 696 < 47 < 45 < 82 < 65 < 113 < 65 < 62 MEAN+/- 2 STD DEV 1568 +/- 0 94 Clams 05/16/17 2167 +/- 466 < 32 < 29 < 53 < 33 < 63 < 37 < 31 10/18/17 713 +/- 635 < 51 < 55 < 117 < 43 < 77 < 73 < 59 MEAN+/- 2 STD DEV 1440 +/- 2056 THE MEAN AND TWO STANDARD DEV/A TION ARE CALCULATED USING THE POSITIVE VALUES Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION , 2017 RESULTS IN UNI TS OF PCI/KG DRY +/- 2 SIGMA COLLECTION S I TE PE R I O D Be-7 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 R a-226 T h-2 2 8 23 05/16/17 < 542 6245 +/- 1112 < 58 < 58 < 44 < 73 < 57 1402 +/- 1221 478 +/- 85 10/16/17 < 30 1 6696 +/- 811 < 37 < 3 8 < 30 < 43 < 41 1 4 63 +/- 8 66 533 +/- 6 0 MEAN+/- 2 sm DEV 6471 +/- 638 1433 +/- 8 6 5 05 +/- 77 24 05/16/17 < 7 1 1 1585 0 +/- 16 0 6 < 80 < 8 1 < 81 < 94 < 8 5 < 1615 555 +/- 191 1 0/16/17 < 592 7055 +/- 1224 < 71 < 71 < 69 < 84 < 77 2238 +/- 1134 4 8 0 +/- 105 ME AN+/- 2 sm D EV 11453 +/- 12438 2238 +/- 0 51 8 +/- 105 33 05/15/17 < 6 27 8842 +/- 1132 < 44 < 5 0 < 5 2 < 5 8 < 71 2198 +/- 1277 613 +/- 92 C) 10/16/17 < 404 3882 +/- 734 < 36 < 35 < 31 < 56 < 47 983 +/- 676 361 +/- 60 I ..... 0 MEAN+/- 2 s m D EV 6362 +/- 7 0 1 4 1590 +/- 1719 4 8 7 +/- 356 94 05/16/17 1443 +/- 703 13740 +/- 2009 < 79 < 83 < 65 < 109 < 98 < 1685 499 +/- 140 10/18/17 < 683 15930 +/- 1592 < 75 < 74 < 80 < 86 < 83 < 1630 803 +/- 107 MEAN+/- 2 s m D EV 1443 +/- 0 14835 +/- 30 9 7 6 51 +/- 429 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES Table C-Vl.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYS T ER CREEK GENERATING STATION , 201 7 R ESULTS IN U N ITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION G R OUP I GROUP II GROUP Ill PERIOD 20 66 111 71 72 01/04117 -01112/17 14 +/- 5 < 7 12 +/- 5 8 +/- 4 11 +/- 4 01112/17 -01118117 10 +/- 5 11 +/- 5 12 +/- 6 9 +/- 5 12 +/- 5 0111 8 117 -01/26/17 7 +/- 4 7 +/- 4 8 +/- 4 6 +/- 4 7 +/- 3 01126117 -02/01117 12 +/- 5 12 +/- 6 16 +/- 6 10 +/- 5 (1) 02/01117 -02/08/17 16 +/- 5 15 +/- 5 19 +/- 5 13 +/- 5 18 +/- 5 02/08117 -02/15/17 13 +/- 5 11 +/- 5 14 +/- 5 13 +/- 5 13 +/- 5 02/15117 -02/22/17 17 +/- 5 17 +/- 5 16 +/- 5 16 +/- 5 16 +/- 4 02122/17 -03102/17 < 5 11 +/- 4 10 +/- 4 12 +/- 4 9 +/- 4 03102/17 -03108117 17 +/- 5 21 +/- 6 18 +/- 5 19 +/- 6 18 +/- 5 03108117 -03116/17 9 +/- 4 9 +/- 4 9 +/- 4 9 +/- 4 12 +/- 4 03116117 -03122/17 15 +/- 5 12 +/- 5 17 +/- 5 16 +/- 6 13 +/- 5 0312 2 117 -0 3129117 16 +/- 5 1 1 +/- 5 15 +/- 5 11 +/- 4 10 +/- 4 03129117 -04/05117 9 +/- 4 7 +/- 4 <5 6 +/- 4 7 +/- 4 04105117 -04112/17 7 +/- 4 7 +/- 4 10 +/- 4 9 +/- 4 11 +/- 4 04112117 -04119117 12 +/- 4 11 +/-4 12 +/- 4 13 +/- 4 8 +/- 4 04119117 -04127117 < 5 <6 < 5 < 5 5 +/- 4 04127117 -05103/17 <7 < 7 8 +/-5 < 7 < 7 05103117 -05110117 10 +/- 4 <6 8 +/-4 6 +/- 4 10 +/- 4 05110117 -05117117 6 +/- 4 <6 7 +/- 4 6 +/- 4 <6 05117117 -05124117 19 +/- 5 15 +/- 4 14 +/- 4 12 +/- 4 13 +/- 4 0512 4/17 -06101117 < 5 < 5 <5 6+/-4 8 +/- 4 06101/17 -06107117 9 +/- 5 11 +/- 5 9 +/- 4 12 +/- 5 13 +/- 5 06107117 -06115117 18 +/- 4 20 +/- 4 12 +/- 4 16 +/- 6 18 +/- 4 06115117 -06121117 7 +/- 5 < 7 <7 (1) 7 +/- 5 06121117 -06128117 8 +/- 4 15 +/- 5 14 +/- 5 9 +/- 4 13 +/- 5 06/28/17 -07106/17 19 +/- 5 16 +/- 4 12 +/- 4 14 +/- 4 15 +/- 4 07106/17 -07/12/17 11 +/- 5 10 +/- 5 11 +/- 5 12 +/- 5 9 +/- 5 07/12/17

07/20/17 17 +/- 4 16 +/- 4 (1) 14 +/- 4 14 +/- 4 07/20117 -07126117 19 +/- 5 23 +/- 6 15 +/- 5 20 +/- 6 18 +/- 6 0712 6 11 7 -0 8 102117 13 +/- 4 1 0 +/- 4 14 +/- 4 12 +/- 4 16 +/- 4 08102117 -08109117 10 +/- 4 9 +/- 4 9 +/- 4 12 +/- 4 11 +/- 4 08109117 -08116117 15 +/- 5 15 +/- 5 13 +/- 4 16 +/- 5 (1) 0811 6 117 -0 8/24117 16 +/- 4 15 +/- 4 18 +/- 4 15 +/- 4 17 +/- 4 0812 4 1 1 7 -0 8/30117 < 7 <8 < 7 8 +/- 5 < 7 08/3 0 117 -09107117 14 +/- 4 16 +/- 4 13 +/- 4 (1) 13 +/- 4 09107117 -09113117 9 +/- 5 < 7 7 +/- 5 < 7 9 +/- 5 09113117 -09/21/17 14 +/- 4 14 +/- 4 13 +/- 4 15 +/- 4 14 +/- 4 09/21117 -0 9127117 9 +/- 5 <8 10 +/- 5 < 8 9 +/- 5 09127117 -1 0 104117 13 +/- 4 1 5 +/- 4 1 0 +/- 4 19 +/- 4 13 +/- 4 10104117 -10112/17 9 +/- 4 7 +/- 4 14 +/- 4 12 +/- 4 9 +/- 4 10112/17 -10119117 < 7 7 +/- 5 <6 8 +/- 5 < 7 10119117 -1 0 125117 1 2 +/- 5 < 7 12 +/- 5 12 +/- 5 8 +/- 5 10125117 -11101117 7 +/- 5 9 +/- 5 9 +/- 5 11 +/- 5 10 +/- 5 11101117 -11108117 12 +/- 5 12 +/- 5 8 +/- 4 10 +/- 4 10 +/- 4 11108117 -11115117 17 +/- 5 18 +/- 5 15 +/- 5 13 +/- 5 13 +/- 5 11115117 11/21117 12 +/- 5 < 8 10 +/- 5 9 +/- 5 8 +/- 5 11121117 -11129117 17 +/- 4 14 +/- 4 16 +/- 4 16 +/- 4 14 +/- 4 11/2 9 117 -12/06117 15 +/- 4 13 +/- 4 17 +/- 4 10 +/- 4 16 +/- 5 12106117 -12113117 17 +/- 5 17 +/- 5 14 +/- 4 16 +/- 5 15 +/- 4 12/13/17 -12/20117 24 +/- 5 19 +/- 5 20 +/- 5 15 +/- 5 22 +/- 5 1212 0 117 12/27117 13 +/- 4 12 +/- 4 12 +/- 4 10 +/- 4 11 +/- 4 12/27117 -01/03118 19 +/- 5 13 +/- 5 14 +/- 4 13 +/- 5 12 +/- 4 MEAN+/- 2 STD DEV 13 +/- 8 13 +/- 8 13 +/- 7 12 +/- 7 12 +/- 7 THE MEAN A N D TWO STA N D AR D DEVIATION A R E CALCULATE D US I NG THE POSITIVE VALUES (1) SEE PR OGRAM EXCEPTI ON S SECTION F O R EXPLANATION C-11 73 3 C 7 +/- 4 13 +/- 4 13 +/- 4 11 +/- 5 12 +/- 5 16 +/- 5 <5 6 +/- 3 6 +/- 3 9 +/- 5 12 +/- 5 10 +/- 5 21 +/- 5 17 +/- 5 15 +/- 4 12 +/- 5 < 6 14 +/- 5 20 +/- 5 18 +/- 4 22 +/- 5 9 +/- 4 < 5 10 +/- 4 18 +/- 6 2 0 +/- 6 21 +/- 6 < 7 9 +/- 4 9 +/- 4 14 +/- 5 14 +/- 5 14 +/- 5 13 +/- 5 7 +/- 4 13 +/- 5 <6 6 +/- 4 6 +/- 4 7 +/- 4 7 +/- 4 13 +/- 4 12 +/- 4 15 +/- 5 13 +/- 4 <6 <5 <5 < 7 <7 9 +/- 5 6 +/- 4 12 +/- 4 <8 7 +/- 4 7 +/- 4 <6 13 +/- 4 13 +/- 4 16 +/- 4 <5 5 +/- 4 6 +/- 4 11 +/- 5 1 0 +/- 5 8 +/- 5 15 +/- 4 10 +/- 4 17 +/-" 4 < 7 <7 <7 14 +/- 5 12 +/- 5 15 +/- 5 13 +/- 4 15 +/- 4 13 +/- 4 10 +/- 5 10 +/- 5 13 +/- 5 12 +/- 4 12 +/- 4 14 +/- 4 14 +/- 5 17 +/- 5 14 +/- 5 1 2 +/- 4 8 +/- 4 14 +/- 4 12 +/- 4 8 +/- 4 12 +/- 4 14 +/- 5 13 +/- 5 18 +/- 5 14 +/- 4 13 +/- 4 19 +/- 4 <8 <8 < 7 11 +/- 4 9 +/- 4 11 +/- 4 8 +/- 5 7 +/- 5 <7 14 +/- 4 11 +/- 4 16 +/- 4 <8 <8 13 +/- 5 12 +/- 4 14 +/- 4 16 +/- 4 7 +/- 4 12 +/- 4 14 +/- 4 < 7 < 7 8 +/- 5 14 +/- 5 1 2 +/- 5 12 +/- 5 9 +/- 5 9 +/- 5 9 +/- 5 < 6 7 +/- 4 13 +/- 5 14 +/- 5 14 +/- 5 16 +/- 5 (1) 10 +/- 5 10 +/- 5 14 +/- 4 15 +/- 4 13 +/- 4 < 6 11 +/- 4 13 +/- 4 13 +/- 4 21 +/- 5 19 +/- 5 17 +/- 5 17 +/- 5 16 +/- 5 11 +/- 4 12 +/- 4 11 +/- 4 14 +/- 5 11 +/- 4 11 +/- 4 12 +/- 7 12 +/- 7 13 +/- 7 Table C-Vl.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER+/- 2 SIGMA GROUP I -ON-S ITE LOCATIONS GROUP II -INTERMEDIATE DISTANCE LOCATIONS GROUP Ill -CONTROL LOCATIONS COLLECTION MEAN COLLECTION MEAN COLLECTION MEAN PERIOD MIN MAX +/-2SD PERIOD MIN MAX +/-2SD PERIOD MIN MAX +/-2SD 01/04/17 -02/01/17 7 16 11 +/- 6 01/04/17 -02/01/17 6 12 9 +/- 4 01/04/17 -02/01/17 6 16 11 +/- 7 02/01/17 -03/02/17 10 19 14 +/- 6 02/01/17 -03/02/1 7 9 21 14 +/- 8 02/01/17 -03/02/17 10 22 16 +/- 8 03/02/17 -03/29/17 9 21 14 +/- 8 03/02/17 -03/29/17 9 19 14 +/- 7 03/02/17 -03/29/17 7 21 13 +/- 10 03/29/17 -05/03/17 7 12 9+/-4 03/29/17 -04/27/17 5 13 9+/-6 03/29/17 -05/03/17 6 15 10 +/- 7 05/03/17 -05/24/17 6 19 11 +/- 9 05/03/17 -06/01/17 6 13 9+/-6 05/03/17 -06/01/17 5 16 10 +/- 9 06/01/17 -06/28/17 7 20 12 +/- 8 06/01/17 -06/28/17 7 18 13 +/- 6 06/01/17 -06/28/17 8 17 12 +/- 6 06/28/17 -08/02/17 10 23 15 +/- 8 06/28/17 -08/02/17 9 20 14 +/- 6 06/28/17 -08/02/17 8 17 13 +/- 5 08/02/17 -08/24/17 9 18 13 +/- 6 08/02/17 -08/30/17 8 17 13 +/- 6 08/02/17 -08/24/17 8 19 14 +/- 8 C) 08/30/17 -10/04/17 7 16 12 +/- 5 08/30/17 -10/04/17 8 19 13 +/- 6 08/30/17 -10/04/17 7 16 12 +/- 6 I 10/04/17 -11/01/17 7 14 10 +/- 5 10/04/17 -11/01/17 7 14 10 +/- 4 10/04/17 -11/01/17 8 14 11 +/- 5 ...... "' 11/01/17 -11/29/17 8 18 14 +/- 7 11/01/17 -11/29/17 8 16 12 +/- 5 11/01/17 -11/29/17 7 16 12 +/- 6 11/29/17 -01/03/18 12 24 16 +/- 7 11/29/17 -01/03/18 10 22 14 +/- 7 11/29/17 -01/03/18 11 21 14 +/- 7 01/04/17 -01/03/18 6 24 13 +/- 8 01/04/17 -01/03/18 5 22 12 +/- 7 01/04/1 7 -01/03/18 5 22 12 +/- 7 T a ble C-Vl.3 CONCENTRATIONS OF STRONTIUM IN AIR PARTICULATE SAMP L ES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION , 2017 RESULT S I N UN ITS OF E-3 P CI/CU ME TER +/- 2 SIGMA CO LLECTIO N SITE P ERIOD SR-8 9 SR-90 3 0 1/04/17 -03/29/17 < 5 < 7 03/29/17 -06/28/17 < 5 <4 06/28/17 -09/27 /17 < 6 <6 09/27/17 -01/03/18 < 3 <5 MEAN 20 01 /04/17 -03/29/17 < 5 < 8 03/29/17 -06/28/17 <6 < 4 06/28/17 -09/27 /17 < 7 <4 09/27 /17 -01 /03/18 < 3 <7 MEAN 66 01/04/17 -03/29/17 <6 < 7 03/29/17 -06/28/17 <6 < 6 06/28/17 -09/27/17 <6 <7 09/27 /17 -01 /03/18 < 3 <4 MEAN 71 01/04/17 -03/29/17 <4 < 8 03/29/ 17 -06/28/ 17 < 5 < 5 06/28/17 -09/27/17 < 8 < 6 09/27/17 -01/03/18 < 8 <6 MEAN 72 01/04/17 -03/29/17 < 7 < 8 03/29/17 -06/28/17 <6 <4 06/28/17 -09/27/17 < 7 <4 09/27/17 -01/03/18 < 3 < 3 MEAN 73 01/0 4/17 -03/29/17 < 5 < 7 03/29/17 -06/28/17 < 7 < 6 06/28/17 -09/27/17 < 7 <4 09/27/17 -01/03/18 < 3 < 5 MEAN 111 01/04/17 -03/29/17 <4 <6 03/2 9/17 -06/28/17 <6 < 5 06/28/17 -09/27/17 < 8 < 10 09/27117 -01 /03/18 < 3 < 6 MEAN C 01/04/17 -03/29/17 <4 <6 03/29/17 -06/28/17 <6 < 5 06/28/17 -09/27 /17 < 7 < 3 09/27/17 -01/03/18 < 3 <4 MEAN C-13 Table C-Vl.4 CONCENTRATIONS OF GAMMA EMITTERS IN A I R PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION , 20 17 RES U LTS IN U NI TS OF E-3 PCI/C U METER+/- 2 SIGMA COLLECTION SITE PER I OD Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 3 01/04/17 -03/29/17 77 +/- 22 <2 < 3 < 3 < 3 <3 03/29/17 -06/28/17 49 +/- 19 < 2 < 2 < 3 < 2 < 3 06/2.8/17

-09/2.7/17 75 +/- 34 <4 <4 <4 <3 <2 09/27/17 -01/03/18 55 +/- 18 <3 <4 <4 < 3 <3 MEAN+/- 2 STD DEV 64 +/- 28 20 01/04/17 -03/29/17 74 +/- 18 < 3 < 2 < 3 < 2 <2 03/29/17 -06/28/17 69 +/- 18 < 2 < 3 < 3 <2 < 2 06/28/17 -09/27/17 46 +/- 25 < 3 <4 < 3 < 3 < 3 09/27/17 -01/03/18 56 +/- 17 < 2 <2 < 2 < 2 < 2 MEAN+/- 2 STD DEV 61 +/- 26 66 01/04/17 -03/29/17 80 +/- 21 < 3 < 3 < 3 < 3 <2 03/29/17 -06/28/17 53 +/- 20 < 2 < 2 < 3 < 2 <2 06/28/17 -09/27/17 65 +/- 23 < 2 <4 < 2 < 3 < 3 09/27/17 -01/03/18 51 +/- 17 < 2 < 3 < 2 < 2 < 2 MEAN+/-2 STDDEV 62 +/- 26 71 01/04/17 -03/29/17 70 +/- 17 < 2 < 2 < 2 < 2 < 2 03/29/17 -06/28/17 50 +/- 22 < 5 < 4 < 5 < 3 <3 06/28/17 -09/27/17 74 +/- 32 < 3 < 5 < 6 < 3 <4 09/27/17 -01/03/18 51 +/- 16 < 2 < 2 < 2 < 2 <2 MEAN+/- 2 STD DEV 61 +/- 25 72 01/04/17 -03/29/17 66 +/- 22 < 3 <2 < 4 < 3 < 3 03/29/17 -06/28/17 50 +/- 19 < 2 < 3 < 3 <3 < 3 06/28/17 -09/27/17 55 +/- 29 < 3 <4 < 3 <4 < 3 09/27/17 -01/03/18 46 +/- 20 < 2 < 3 < 3 < 2 < 2 MEA N+/- 2 STD DEV 54 +/- 17 73 01/04/17 -03/2 9/17 97 +/- 21 < 2 < 3 < 2 <4 < 2 03/29/17 -06/28/17 82 +/- 23 < 3 < 3 < 3 < 3 < 3 06/28/1 7 -09/27/17 54 +/- 39 < 3 <4 < 3 < 5 < 3 09/27/17 -01/03/18 66 +/- 20 < 3 < 3 < 2 < 2 < 2 MEAN+/- 2 STD DEV 75 +/- 37 111 01/04/17 -03/29/17 50 +/- 36 <4 < 2 < 5 <4 < 4 03/29/17 -06/28/17 50 +/- 19 < 3 < 2 < 3 <3 < 2 06/28/17 -09/27/17 71 +/- 30 < 4 < 5 <4 <4 < 3 09/27/17 -01/03/18 48 +/- 21 < 4 < 3 < 3 < 3 < 3 MEAN+/- 2 STD DEV 55 +/- 21 C 01/04/17 -03/29/17 93 +/- 25 < 3 < 3 < 3 < 3 < 3 03/29/17 -06/28/17 67 +/- 21 < 3 <4 < 3 <4 <4 06/28/17 -09/27/17 81 +/- 29 < 4 < 3 < 4 <4 < 3 09/27/17 -01/03/18 57 +/- 17 < 2 < 2 < 2 < 3 < 2 MEAN+/- 2 STD DEV 74 +/- 31 THE MEAN AND TWO STA N DARD DEV/A TION ARE CALCULATED USING THE POSITIVE VALUES C-1 4 Tab l e C-Vll.1 CONCENTRATIONS OF 1-13 1 IN AIR IODINE SAMPLES COL L ECTED IN THE VICINITY OF OYSTER CREEK GENERATING STAT I ON , 2017 R ESULTS I N UN ITS OF E-3 PC I/C U METER+/- 2 SIGMA COLLE C TION GRO UP I I GROUP II I G ROU P Ill P ERIOD 2 0 66 111 71 72 73 3 C 01/04/17 -01/12/17 < 3 8 < 40 < 40 < 17 < 32 < 39 < 32 < 32 01/12/17 -01/18/17 < 59 < 60 < 61 < 25 < 43 < 59 < 17 < 43 01/18/17 -01/26/17 < 35 < 44 < 44 < 18 < 41 < 43 < 13 < 33 01/26/17 -02/01/17 < 62 < 64 < 64 < 27 (1) < 63 < 18 < 47 02/01/17 -02I08/17 < 52 < 53 < 54 < 22 < 48 < 52 < 48 < 18 02/08/17 -02/15/17 < 61 < 63 < 63 < 32 < 55 < 61 < 53 < 28 02/15/17 -02/22/17 < 55 < 56 < 57 < 23 < 47 < 55 < 49 < 19 02/22/17 -03/02/17 < 47 < 48 < 18 < 47 < 38 < 48 < 38 < 38 03/02/17 -03/08/17 < 48 < 50 < 47 < 20 < 54 < 49 < 21 < 55 03/08/17 -0 3/16/17 < 46 < 47 < 45 < 16 < 46 < 62 < 36 < 35 03/16/17 -0 3/22/17 < 55 < 55 < 53 < 23 < 54 < 55 < 54 < 54 03/22/17 -03/29/17 < 57 < 58 < 23 < 57 < 16 < 58 < 42 < 42 03/29/17 -04/05/17 < 59 < 60 < 24 < 59 < 39 < 60 < 40 < 39 04/05/17 -04/12/17 < 46 < 46 < 44 < 19 < 46 < 46 < 48 < 47 04/12/17 -04/19/17 < 36 < 36 < 35 < 15 < 12 < 36 < 32 < 31 04/19/17 -0 4/27/17 < 4 2 < 43 < 41 < 19 < 43 < 43 < 23 < 44 04/27 /17 -05/03/17 < 4 3 < 43 < 41 < 19 < 27 < 44 < 52 < 54 05/03/17 -05/10/17 < 37 < 37 < 36 < 15 < 37 < 37 < 15 < 57 05/10/17 -05/17/17 < 39 < 39 < 38 < 15 < 16 < 39 < 42 < 41 05/17 /17 -05/24/17 < 43 < 44 < 18 < 43 < 53 < 44 < 54 < 53 05/24/17 -06/0 1/17 < 42 < 43 < 41 < 42 < 45 < 18 < 46 < 46 06/01/17 -06/07/17 < 38 < 38 < 15 < 38 < 11 < 38 < 28 < 28 06/07/17 -06/15/17 < 39 < 40 < 16 < 59 < 29 < 40 < 11 < 29 06/15/17 -06/21/17 < 49 < 55 < 22 (1) < 55 < 56 < 43 < 42 06/21/17

06/28/17 < 52 < 52 < 21 < 51 < 54 < 52 < 55 < 54 06/28/17 -07/06/17 < 42 < 42 < 17 < 42 < 12 < 42 < 31 < 31 07/06/17 -07/12/17 < 46 < 47 < 19 < 46 < 44 < 47 < 44 < 17 07/12/17 -07/20/17 < 38 < 38 (1) < 17 < 38 < 38 < 23 < 45 07 /20/17 -0 7 /2 6/17 < 49 < 50 < 47 < 21 < 50 < 5 0 < 46 < 18 07 /26/17 -08/02/17 < 41 < 42 < 14 < 18 < 40 < 42 < 40 < 39 08/02/17 -0 8/09/17 < 55 < 55 < 25 < 28 < 55 < 55 < 47 < 47 08/09/17 -08/16/17 < 44 < 44 < 42 < 18 (1) < 44 < 37 < 37 08/16/17 -0 8/24/17 < 33 < 34 < 32 < 12 < 16 < 34 < 37 < 37 0 8/24/17 -08/3 0/17 < 5 4 < 54 < 22 < 54 < 34 < 5 4 < 41 < 41 08/30/17 -09/07 /17 < 41 < 41 < 17 (1) < 25 < 41 < 31 < 30 09/07 /17 -09/13/17 < 55 < 56 < 23 < 56 < 24 < 56 < 44 < 43 09/13/17 -09/21 /17 < 44 < 44 < 18 < 44 < 24 < 45 < 29 < 29 09/21/17 -09/27/17 < 37 < 37 < 36 < 37 < 26 < 16 < 32 < 31 0 9/27 /17 -1 0/0 4/17 < 53 < 54 < 26 < 53 < 24 < 54 < 45 < 44 10/04/17 -1 0/12/17 < 29 < 30 < 12 < 29 < 22 < 30 < 27 < 26 10/12/17 -1 0/19/17 < 42 < 42 < 17 < 42 < 29 < 42 < 34 < 34 10/19/17 -10/25/17 < 45 < 46 < 44 < 19 < 27 < 46 < 34 < 34 10/25/17 -11/01/17 < 31 < 32 < 30 < 13 < 23 < 32 < 27 < 27 11/01/17 -11/08/17 < 32 < 32 < 31 < 13 < 19 < 32 < 38 < 37 11/08/17 -11/15/17 < 45 < 46 < 44 < 19 < 24 < 46 < 30 < 29 11/15/17 -11/21/17 < 51 < 52 < 25 < 51 < 24 < 52 < 45 < 45 11/21/17 -11/2 9/17 < 39 < 40 < 38 < 16 < 22 < 40 < 27 < 26 11 /29/17 -12/06/17 < 54 < 54 < 22 < 54 < 26 < 55 < 31 < 31 12/06/17 -12/13/17 < 31 < 31 < 30 < 17 < 14 < 32 < 41 < 40 12/13/17 -12/20/17 < 29 < 29 < 28 < 12 < 13 < 30 < 15 < 15 12/20/17 -12/27/17 < 50 < 51 < 48 < 26 < 27 < 51 < 51 < 50 12/27/17 -0 1/03/18 < 52 < 56 < 51 < 2 2 < 26 < 53 < 31 < 31 MEAN (1) SEE PR O GRAM EXCEPTIONS SECTION FOR EXPLANATION C-15 Table C-Vlll.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITIERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/KG WET+/- 2 SIGMA COLLECTION SITE PERIOD Sr-89 Sr-90 Be-7 K-40 1-1 31 Cs-134 Cs-1 37 Ba-140 La-140 115 Cabbage 07/26/17 < 12 7.4 +/- 2.8 < 394 1445 +/- 526 < 54 < 41 < 45 < 186 < 49 Collards 07/26/17 Original < 13 20.3 +/- 3.7 < 446 2482 +/- 757 < 59 < 43 < 52 < 184 < 39 Collards 07/26/17 Reanalysis 13.7 +/- 2.4 Kale 07/26/17 < 20 < 3.9 < 400 2659 +/- 649 < 51 < 42 72 +/- 41 < 161 < 60 Cabbage 08/30/17 < 16 8.8 +/- 3.7 186 +/- 139 1344 +/- 236 < 46 < 14 < 17 < 103 < 29 Collards 08/30/17 < 15 10.9 +/- 2.8 492 +/- 114 1882 +/- 210 < 41 < 12 19 +/- 12 < 80 < 23 Kale 08/30/17 < 16 5.9 +/- 2.7 349 +/- 116 2098 +/- 191 < 34 < 12 < 13 < 74 < 19 Cabbage 09/20/17 < 21 < 4.0 < 161 1863 +/- 307 < 49 < 19 < 21 < 113 < 39 Collards 09/20/17 < 15 8.7 +/- 1.9 596 +/- 189 2646 +/- 368 < 52 < 18 < 19 < 113 < 44 Kale 09/20/17 < 13 8.0 +/- 1.9 312 +/- 157 2376 +/- 340 < 49 < 18 22 +/- 18 < 119 < 25 Collards 10/25/17 < 11 15.6 +/- 3.1 329 +/- 212 2764 +/- 456 < 38 < 28 < 29 < 104 < 29 C) Kale 10/25/17 < 11 9.6 +/- 2.4 602 +/- 297 2849 +/- 683 < 47 < 37 < 25 < 143 < 29 I 0) MEAN+/- 2 STD DEV 10.9 +/- 8.8 409 +/- 315 2219 +/- 1055 38 +/- 60 35 Kale 07/26/17 < 14 < 3.4 < 338 4010 +/- 679 < 50 < 40 < 42 < 155 < 52 Collards 07/26/17 < 15 9.9 +/- 2.0 293 +/- 157 3024 +/- 550 < 35 < 27 < 28 < 112 < 13 Cabbage 07/26/17 < 13 6.9 +/- 2.0 291 +/- 210 2214 +/-411 < 31 < 20 < 24 < 97 < 24 Cabbage 08/30/17 < 21 6.5 +/- 3.1 < 105 1618 +/- 222 < 30 < 14 <13 < 68 < 24 Collards 08/30/17 < 16 6.9 +/- 2.6 446 +/- 117 2089 +/- 251 < 52 < 15 < 15 < 109 < 33 Kale 08/30/17 < 17 < 4.4 335 :t 96 2566 +/- 235 < 29 < 12 < 13 < 69 < 19 Cabbage 09/20/17 < 17 < 2.8 < 140 1442 +/- 236 < 41 < 17 < 20 < 84 < 35 Collards 09/20/17 < 14 < 4.6 432 :t 151 2384 +/- 298 < 47 < 18 < 20 < 104 < 35 Kale 09/20/17 < 22 < 3.8 205 :t 110 2715 +/- 344 < 46 < 18 < 19 < 107 < 18 Cabbage 10/25/17 < 12 8.2 +/- 2.3 < 201 1718 +/- 363 < 37 < 26 < 24 < 105 < 32 Collards 10/25/17 < 14 8.2 +/- 2.4 278 +/- 220 2165 +/- 355 < 30 < 21 < 21 < 91 < 19 Kale 10/25/17 < 11 3.8 +/- 1.7 431 :t 151 2871 +/- 338 < 24 < 16 < 21 < 69 < 16 MEAN +/- 2 STD DEV 7.2 +/- 3.8 339 +/- 177 2401 +/- 1416 THE MEAN AND TWO STANDARD DEV/A TION ARE CALCULATED USING THE POSITIVE VALUES Table C-Vlll.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/KG WET+/- 2 SIGMA COLLECTION SITE PERIOD Sr-89 Sr-90 Be-7 K-40 1-131 Cs-134 Cs-137 Ba-140 La-140 Control 36 Cabbage 07/26/17 < 13 < 3.0 < 256 1359 +/- 488 < 37 < 36 < 36 < 145 < 25 Collards 07/26/17 < 16 4.5 +/- 2.1 316 +/- 184 3149 +/- 566 < 58 < 35 < 37 < 157 < 37 Kale 07/26/17 < 14 < 4.0 467 :t 200 4235 +/- 570 < 36 < 26 < 29 < 103 < 34 Cabbage 08130/17 < 18 < 2.0 < 98 2260 +/- 169 < 31 < 12 < 11 < 70 < 17 Collards 08/30/17 < 17 < 2.4 234 :t 91 6986 +/- 318 < 33 < 13 < 12 < 77 < 21 Kale 08/30/17 < 23 < 3.7 219 :t 158 6076 +/- 420 < 47 < 18 < 17 < 104 < 30 Cabbage 09/20/17 < 14 < 2.3 < 146 1822 +/- 351 < 51 < 19 < 18 < 99 < 30 Collards 09/20/17 < 15 < 4.7 217 :t 139 4247 +/- 438 < 51 < 17 <18 < 113 < 32 Kale 09/20117 < 12 < 2.5 196 :t 149 5323 +/- 525 < 49 < 23 < 19 < 108 < 43 Cabbage 10125/17 < 11 3.0 +/- 2.0 < 143 1851 +/- 327 < 27 < 18 < 16 < 80 < 23 0 Collards 10125/17 < 12 4.2 +/- 2.2 217 :t 202 4668 +/- 627 < 39 < 30 < 23 < 99 < 25 ' Kale 10/25/17 < 12 4.3 +/- 2.3 < 255 4771 +/- 623 < 38 < 21 < 23 < 101 < 31 ...... --.j MEAN +/- 2 STD DEV 4.0 +/- 1.4 267 +/- 193 3896 +/- 3623 66 Cabbage 08/30117 < 15 5.6 +/- 2.8 317 +/- 136 4008 +/- 342 < 53 < 21 < 20 < 126 < 34 Collards 08/30/17 < 25 < 3.1 672 +/- 210 3696 +/- 423 < 55 < 22 < 24 < 126 < 34 Kale 08/30/17 < 18 10.5 +/- 3.5 649 +/- 244 3853 +/- 426 < 54 < 22 < 22 < 132 < 37 Cabbage 09/20/17 < 22 < 2.9 < 194 2043 +/- 362 < 59 < 23 < 23 < 142 < 40 Collards 09/20/17 < 14 8.7 +/- 2.0 812 :t 176 2382 +/- 299 < 53 < 21 < 19 < 122 < 37 Kale 09/20/17 < 20 3.9 +/- 2.0 754 +/- 206 2787 +/- 325 < 58 < 20 <19 < 134 < 36 MEAN +/- 2 STD DEV 7.2 +/- 5.9 641 +/- 385 3128 +/- 1667 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES Table C-IX.1 QUARTERLY OSLD RESULTS FOR OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF MILLIREM/STD. QUARTER+/- 2 STANDARD DEVIATION STATION MEAN CODE +/- 2 S.D. JAN-MAR APR-JUN JUL-SEP OCT-DEC 11.3 +/- 3.5 10.4 +/- 2.5 11.2 +/- 3.3 13.7 +/- 1.0 9.7 +/- 0.8 3 7.6 +/- 3.5 8.0 +/- 1.4 5.8 +/- 1.6 9.8 +/- 1.0 6.7 +/- 1.1 4 9.0 +/- 3.5 8.0 +/- 0.1 10.1 +/- 2.4 10.8 +/- 4.1 7.0 +/- 0.8 5 13.9 +/- 1.2 13.5 +/- 0.4 13.4 +/- 1.8 14.7 +/- 3.5 14.1 +/- 0.8 6 10.1 +/- 3.3 9.5 +/- 0.7 (1) 12.0 +/- 2.1 8.9 +/- 4.4 8 8.2 +/- 1.0 8.0 +/- 1.5 8.0 +/- 0.3 7.9 +/- 1.1 9.0 +/- 1.1 9 7.1 +/- 0.6 7.2 :t 1.3 6.9 :t 0.4 7.4 :t 1.3 6.7 :t 3.5 C 9.2 +/- 1.9 9.0 +/- 1.0 9.3 +/- 1.6 10.3 +/- 2.4 8.0 +/- 0.3 11 9.1 +/- 3.9 11.3 +/- 1.0 9.5 +/- 0.4 9.1 +/- 1.6 6.6 +/- 0.7 14 10.9 +/- 2.1 10.8 +/- 1.1 9.7 +/- 0.4 12.3 +/- 2.0 10.7 +/- 2.4 22 11.1 +/- 1.0 11.7 +/- 2.5 11.3 +/- 1.6 10.7 +/- 4.8 10.6 +/- 1.1 46 6.7 +/- 2.9 4.9 +/- 1.6 8.3 +/- 0.1 7.2 +/- 1.6 6.4 +/- 2.0 47 9.2 +/- 0.9 8.8 +/- 0.4 9.7 +/- 0.1 9.4 +/- 1.0 8.8 +/- 3.3 48 8.1 +/- 2.5 7.3 +/- 0.3 9.9 +/- 0.4 7.2 +/- 0.4 8.1 +/- 4.8 51 11.3 +/- 2.0 10.7 +/- 1.0 11.2 +/- 3.8 12.8 +/- 1.0 10.6 +/- 1.0 52 14.0 +/- 2.5 12.8 +/- 2.1 13.3 +/- 0.1 15.7 +/- 0.1 14.1 +/- 5.1 53 13.2 +/- 4.2 10.8 +/- 3.4 12.4 +/- 0.1 15.6 +/- 0.7 14.1 +/- 0.0 54 9.6 +/- 3.5 7.8 +/- 0.7 8.7 +/- 1.4 11.8 +/- 0.6 10.2 +/- 4.9 55 20.2 +/- 4.2 17.5 +/- 1.0 20.7 +/- 7.6 22.6 +/- 0.8 20.0 +/- 6.6 56 17.8 +/- 3.3 16.9 +/- 0.7 17.5 +/- 3.5 20.2 +/- 1.6 16.6 +/- 1.7 57 14.7 +/- 4.5 13.5 +/- 0.6 12.5 +/- 2.1 17.7 +/- 1.8 15.0 +/- 2.3 58 14.1 +/- 2.7 13.7 +/- 5.9 13.1 +/- 0.7 16.1 +/- 1.0 13.6 +/- 0.6 59 11.9 +/- 4.4 12.1 +/- 1.3 10.2 +/- 2.3 14.9 +/- 1.3 10.3 +/- 2.0 61 8.1 +/- 1.9 8.8 +/- 0.0 8.5 +/- 3.4 6.7 +/- 1.8 8.2 +/- 1.7 62 9.7 +/- 1.0 9.7 +/- 0.1 9.8 +/- 0.3 10.2 +/- 0.1 9.0 +/- 1.1 63 8.9 +/- 0.7 8.8 +/- 1.1 8.9 +/- 0.3 8.4 +/- 1.8 9.3 +/- 1.4 64 9.3 +/- 1.3 10.0 +/- 0.7 8.4 +/- 0.4 9.5 +/- 4.5 9.4 +/- 1.1 65 8.8 +/- 1.0 8.4 +/- 0.4 9.5 +/- 4.7 8.6 +/- 2.3 8.6 +/- 0.6 66 8.3 t 1.9 9.3 ;1; 2 , 6 8.2 ;1; 0.4 8.7 ;1; 0.9 7.1 ;1; 2.1 68 7.1 +/- 2.0 6.4 +/- 3.1 6.2 +/- 0.0 7.6 +/- 0.7 8.3 +/- 0.8 71 9.0 +/- 2.8 10.6 +/- 0.0 9.1 +/- 0.4 9.0 +/- 2.1 7.2 +/- 1.4 72 8.4 +/- 0.4 8.5 +/- 0.3 8.2 +/- 0.7 8.2 +/- 4.0 8.6 +/- 0.7 73 7.8 +/- 1.3 8.6 +/- 1.0 7.4 +/- 0.0 8.1 +/- 0.3 7.2 +/- 0.0 74 7.7 +/- 1.0 7.4 +/- 0.0 8.4 +/- 0.0 7.6 +/- 0.7 7.3 +/- 0.6 75 10.2 +/- 1.2 10.6 :I: 2.8 9.7 :I: 1.1 10.7 :1: 1.6 9.6 +/- 1.4 78 9.1 +/- 2.4 8.6 :I: 1.6 10.8 +/- 0.6 9.0 +/- 2.1 8.0 +/- 1.8 79 9.7 +/- 1.6 9.5 +/- 1.5 10.8 +/- 5.6 8.9 +/- 0.7 9.7 +/- 0.9 81 7.8 +/- 1.8 7.8 +/- 3.3 8.0 +/- 0.6 8.7 +/- 2.5 6.5 :I: 0.1 82 8.4 :I: 1.4 9.3 :I: 2.8 8.2 +/- 2.8 7.7 +/- 0.3 8.2 +/- 1.7 84 8.4 +/- 1.1 8.7 +/- 0.6 8.4 +/- 1.8 7.7 +/- 2.5 8.9 +/- 1.1 85 7.3 +/- 2.7 7.7 +/- 0.1 7.5 +/- 0.8 8.6 +/- 0.0 5.4 +/- 2.0 86 9.0 +/- 1.6 9.2 +/- 2.0 9.0 :I: 0.8 9.9 +/- 2.3 8.0 +/- 1.8 88 6.1 :1: 1.1 6.8 +/- 0.1 5.6 :I: 0.8 6.4 +/- 0.4 5.7 +/- 1.4 89 6.7 +/- 1.2 7.0 +/- 0.7 6.4 +/- 2.3 7.4 +/- 0.7 6.0 +/- 1.1 90 7.9 +/- 2.1 8.3 +/- 0.3 6.9 +/- 3.8 9.2 +/- 0.6 7.3 +/- 2.5 92 8.7 +/- 2.9 9.9 +/- 1.4 7.4 +/- 0.4 10.0 +/- 0.1 7.5 +/- 2.0 98 7.7 +/- 2.1 7.9 +/- 3.0 6.6 +/- 0.1 7.2 +/- 2.0 9.0 +/- 3.0 99 7.0 +/- 2.8 8.0 +/- 0.3 5.0 :1: 1.0 8.0 +/- 0.6 7.0 +/- 1.1 T1 12.0 +/- 2.9 12.5 +/- 0.3 10.9 +/- 0.7 13.8 +/- 1.7 10.8 +/- 2.8 100 7.8 :I: 1.7 7.2 +/- 0.7 8.3 +/- 2.1 8.7 +/- 2.1 7.0 :1: 1.6 101 8.4 +/- 1.4 8.6 :I: 0.1 7.6 :I: 2.4 (1) 8.9 :1: 0.7 102 9.5 :I: 2.3 8.0 +/- 0.0 9.6 +/- 0.3 10.8 :I: 4.2 9.4 +/- 1.7 103 8.6 +/- 1.5 9.4 +/- 4.7 8.0 +/- 2.5 7.9 +/- 1.3 9.0 +/- 2.0 104 8.3 +/- 1.0 8.1 +/- 0.4 8.6 +/- 2.8 8.7 +/- 2.3 7.6 +/- 0.1 105 6.7 +/- 2.0 7.3 :I: 0.1 7.0 +/- 1.4 7.2 +/- 0.1 5.2 +/- 1.8 106 6.9 +/- 1.0 6.8 +/- 1.3 6.3 +/- 1.8 7.5 +/- 0.7 6.9 +/- 1.4 107 8.4 :I: 2.1 8.6 +/- 0.7 7.9 +/- 0.4 9.7 +/- 0.1 7.3 +/- 1.3 109 8.5 +/- 2.2 9.1 :I: 4.8 8.6 +/- 1.8 9.4 +/- 2.3 6.9 +/- 0.3 110 8.0 +/- 2.3 7.6 +/- 1.7 8.4 +/- 0.4 9.4 +/- 1.1 6.7 +/- 2.0 112 14.4 +/- 3.5 13.1 +/- 5.5 13.0 +/- 1.7 16.8 :1: 3.3 14.6 +/- 2.0 113 9.3 +/- 0.7 9.7 +/- 0.6 9.3 +/- 0.3 9.2 :I: 1.0 8.8 +/- 1.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-18

() I ..... <O TABLE C-IX.2 COLLECTION PERIOD JAN-MAR APR-JUN JUL-SEP OCT-DEC MEAN QUARTERLY OSLO RESULTS FOR THE SITE BOUNDARY, INTERMEDIATE , SPECIAL INTEREST, AND CONTROL LOCATIONS FOR OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF MILLIREM PER STANDARD QUARTER+/- 2 STANDARD DEVIATION STANDARD DEVIAT I ONS OF THE STATION DATA SITE BOUNDARY INTERMEDIATE SPECIAL INTEREST CONTROL +/-2 S.D. +/- 2 S.D. +/-2 S.D. +/-2 S.D. 11.4 +/- 5.4 8.4 +/- 3.2 8.7 +/- 3.1 9.9 +/- 2.5 11.4 +/- 6.5 8.5 +/- 3.4 7.4 +/- 2.8 9.5 +/- 0.6 13.3 +/- 8.7 8.9 +/- 3.4 8.6 +/- 2.3 11.3 +/- 2.8 11.6 +/- 6.8 8.1 +/- 3.4 6.9 +/- 1.7 9.4 +/- 3.8 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR OYSTER CREEK GENERATING STATION , 2017 RESULTS IN UNITS OF MILLIREM/STD. QUARTER SAMPLES PERIOD PERIOD PERIOD MEAN LOCATION ANALYZED M I NIMUM MAXIMUM +/- 2 S.D. SITE BOUNDARY 76 6.7 22.6 11.9+/-7.0 INTERMEDIATE 122 4.9 14.7 8.5 +/- 3.4 SPECIAL INTEREST 36 5.6 11.3 7.9 +/- 2.9 CONTROL 8 8.0 12.2 10.0 +/- 2.6 SITE BOUNDARY STATIONS-1 , 112 , 113 , 51 , 52 , 53 , 54 , 55 , 56 , 57 , 58 , 59 , 61 , 62 , 63 , 64 , 65 , 66 , T1 INTERMEDIATE STATIONS-100 , 101 , 102 , 103 , 104 , 105 , 106 , 107 , 109 , 110 , 22 , 4 , 46 , 47 , 48 , 5 , 6 , 68 , 73 , 74 , 75 , 78 , 79 , 8 , 82 , 84 , 85 , 86 , 9 , 98 , 99 SPECIAL INTEREST STATIONS -11 , 3 , 71 , 72 , 81 , 88 , 8*9 , 90 , 92 CONTROL STATIONS -14 , C

---*------------(') I I\) 0 FIGURE C-1 MEAN COBALT-60 CONCENTRATION IN CLAMS OYSTER CREEK GENERATING STATION, 1983 -2017 20 -* * * * * * * * * * * * * * * * -* * * * * * * * * * * * * -* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * -* -!, INDICATOR STATION -BACKGROUND STATION 915 -* * * * * * * * * * * * * * * * * * * * -* * * * * * * * * * * * * * * * -* * * * * * * * * * * -* * * * * * * * * * -* * * * * * * * * * * * *,___ _______________

__, I.. 0 ] mo -*** *c:: > * = u 0 *a 5 -.... -. 0 f'f') QC) 0\ ,-.( <> I.C r---QC) QC) QC) QC) 0\ 0\ 0\ ,-.( ,-.( ,-.( 0\ = ,-.( M f'f') "" "' 0\ "' ,-.( QC) 0\ 0\ 0\ 0\ 0\ 0\ 0\ = ,-.( 0\ 0\ 0\ 0\ 0\ 0\ 0\ 0\ = = ,-.( ,-.( ,-.( ,-.( ,-.( ,-.( ,-.( ,-.( M M YEAR

The year designations on the x-axis reflect multiple sampling periods in a given year, as well as historical changes in the number of sampling periods per year. r---,-.( = M

-. "O "-" 5 C: i.. bJ) Q (') i.. I Q,j I\) Q. -"' Q,j *-i.. = u Q *-Q. FIGURE C-2 MEAN COBALT-60 CONCENTRATION IN AQUATIC SEDIMENT OYSTER CREEK GENERATING STATION, 1984 -2017 300 -------------------------------------------------------------------------------------------------------* * --------------------+-INDICATOR STATION MFAN 250 ----------------------------------------* * ----* * * * * * * * * * * * --* * --* * * * * * * * * * * * * * * * * * -Q.-BACKGROUND STATION MFAN 200 ----* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * ----------------------------------------------------------------. ------------.... --. 150 -100 * ---------*

50 0 '!!' ti) \C t-00 0-.. ""' '!!' t-'!!' = 00 00 00 00 00 00 0-.. 0-.. 0-.. = ""' 0-.. 0-.. 0-.. 0-.. 0-.. 0-.. 0-.. 0-.. 0-.. = = ""' ""' ""' ""' ""' ""' ""' ""' ""' N N YEAR

The year designations on the x-axis reflect multiple sampling periods in a given year, as well as historical changes in the number of sampling periods per year. t-""' = N

(") I N N FIGURE C-3 MEAN CESIUM-137 CONCENTRATION IN AQUATIC SEDIMENT OYSTER CREEK GENERATING STATION, 1984-2017 600 -----------------

-~------------------------------

-INDICATOR -e-BACKGROUND 0 ""' 1/'l \C t--00 Q'\ .... ""' t--""' Q t--00 00 QO 00 00 00 Q'\ Q'\ Q'\ Q .... .... Q'\ Q'\ Q'\ Q'\ Q'\ Q'\ Q'\ Q'\ Q'\ Q Q Q ... ... .... ... ... ... ... .... ... N N N Y EAR

The year designations on the x-axis reflect multiple sampling periods in a given year, as well as historical changes in the number of sampling periods per year.

t. -= .... cc c,.t Q. r,.i *-t. = u 0 *-Q. 0.05 0.04 0.03 0.02 0.01 FIGURE C-4 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES OYSTER CREEK GENERA TING STATION, 2008 -2017 -Indicator

-Background 0 +--t--+---+--+--t-+-tt-t-+--+--+-+-1--+-t-+--t--t--+--il--+-+-tt--+-+--il--+-t--t--+t--t--ir-+-+----+-.+-+-l Date 0.18 0.16 i.. QI 0.14 ..... QI a Cj 0.12 *-c:c ~i.. 0.1 QI C. I'll QI *-0.08 i.. = u 0 Cj 0.06 *-C. 0.04 0.02 0 /..9 cP'j( FIGURE C-5 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES OYSTER CREEK GENERATING STATION, 1984-2017 CHERNOBYL ACCIDENT -Indicator Stations -Back round Station* YEAR

Data from Cookstown station ONLY after December 1996

t. t: = 0 "O t. "O 0 = I I\) -01 00 t. C. 5 f *---*-5 FIGURE C-6 MEAN QUARTERLY OSLO GAMMA DOSE OYSTER CREEK GENERATING STATION, 2017 30 ---------------------------------------------------------------~

25 --------------------

---~--------------------------------------

20 ---------------------------------------------------------------~-------------------------------------------------

15 ---------------------------------------------------------------~-----------------------------------------

10 5 0 +----OT02 MILES *1Q17 2 T05 MILES DISTANCE RING FROM PLANT D2Ql7 3Q17 O y ster Creek's dosimetr y changed from TLD to OSLD in 201 2. OVER5MILES D4Ql7 r... e,: = 0 "C r... e,: "C 0 C I e,: I\.) -en 00 r... C. e f *---*-e 40.0 ---------------------------------...... FIGURE C-7 MEAN QUARTERLY TLD/OSLD GAMMA DOSE OYSTER CREEK GENERATING STATION, 1990 -2017* ----------------------------------------------------------------------------------------------

_______

In di ca tor Mean ___________

*

Background Mean 30.0 -----------------------------------------------------------------------------------------------

* 20.0 --------------------------------------------------------------------------------------------------------------------------------

* 10.0 o.o = !") IC °' N 1/'l QC -',t r--°' °' °' °' = = ... .; -°' °' °' °' = = = = ... ---N N N N N N Year *O yster Creek's dosimetr y changed from TLD to OSLD in 2012. *ln order for O y ster Creek to align with the new ANSI N 13.37-2014 Environmental Dosimetry

-Criteria for System Design and Implementation , the data was reviewed back to the beginning of 2007 and updated per t h e guidance in the ANSI Standard.

APPENDIX D DATA TABLES QC LABORATORY The following section presents the results of data analysis performed by the QC laboratory , Environmental Inc. Duplicate samples were obtained from several locations and media and were split with the primary laboratory , Teledyne Brown Engineering (TBE) and the QC Laboratory. Comparison of the results for all media were within expected ranges.

Table D-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 05/16/17 10/17/17 MEAN 24 < 190 < 178 0-1 QCA < 192 < 181 QCB < 155 < 182 Table D-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 24 05/16/17 < 5 <6 < 14 < 6 < 14 <6 < 1 0 < 7 < 5 < 30 < 9 10/17/17 <6 <6 < 15 <6 < 13 < 7 < 1 1 < 7 < 6 < 29 < 9 MEAN QCA 05/16/17 < 5 <6 < 10 < 5 < 11 <6 < 10 < 5 <6 < 20 < 8 10/17/17 <6 < 7 < 17 <6 < 11 < 8 < 12 < 8 < 8 < 40 < 10 MEAN 0 I I\) QCB 05/16/17 < 3 < 2 < 3 < 2 < 3 < 3 < 5 < 2 < 2 < 12 < 3 10/17/1 7 < 3 < 3 < 5 < 3 < 4 < 3 <6 < 4 < 3 < 10 < 2 MEAN _I Table D-11.1 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 1N 1S QCB1N QCB1S 01/03/17 -01/25/17 < 180 (1) < 169 (1) 02/02/17 -02/28/17 < 187 (1) < 146 (1) 03/08/17 -03/28/17 < 195 < 194 < 151 04/05/17 -04/27/17 < 188 < 191 < 148 05/05/17 -06/01/17 < 186 < 180 < 153 06/06/17 -06/27 /17 < 174 (1) < 149 (1) 07/04/17 -07/25/17 < 194 < 195 < 151 < 151 08/01/17 -08/29/17 < 183 (1) < 149 (1) 09/05/17 -09/26/17 < 183 (1) < 144 (1) 10/03/17 -10/24/17 < 180 (1) < 154 (1) 10/31/17 -11/28/17 < 179 (1) < 148 (1) 12/05/17 -12/26/17 < 194 (1) < 154 (1) MEAN TABLE D-11.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 1 N 1S QCB1N QCB1S 01/03/17 -01/25/17 < 0.7 (1) < 0.3 (1) 02/02/17 -02/28/17 < 0.6 (1) < 0.3 (1) 03/08/17 -03/28/17 < 0.5 < 1.0 < 0.4 04/05/17 -04/27/17 < 0.7 < 0.8 < 0.3 05/05/17 -06/01/17 < 4.9 < 0.8 < 0.5 06/06/17 -06/27 /17 < 0.8 (1) < 0.2 (1) 07/04/17 -07/25/1 7 < 0.8 < 0.9 < 0.4 < 0.5 08/01/17 -08/29/17 < 0.5 (1) < 0.3 (1) 09/05/17 -09/26/17 < 0.7 (1) < 0.3 (1) 10/03/17 -10/24/17 < 0.8 (1) < 0.4 (1) 10/31/17 -11/28/17 < 0.6 (1) < 0.3 (1) 12/05/17 -12/26/17 < 0.5 (1) < 0.3 (1) MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION D-3 Table 0-11.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-137 Ba-140 La-140 1N 01/03/17 -01/25/17 < 8 < 5 < 15 < 9 < 10 <8 < 9 <8 <8 < 38 < 9 02/02/17 -02/28/17 < 8 < 8 < 14 < 6 < 17 < 10 < 16 <9 <9 < 40 < 14 03/08/17 -03/08/17 < 1 < 2 <4 < 1 < 3 < 2 < 3 < 2 < 1 < 19 <6 04/14/17 -04/14/17 < 2 < 2 < 5 < 2 <4 < 2 <4 < 2 < 2 < 22 < 7 05/09/17 -05/09/1 7 < 1 <2 < 4 < 1 < 3 <2 < 3 < 1 < 1 < 21 < 6 06/06/17 -06/27/17 < 8 < 5 < 20 < 7 < 11 < 9 <6 < 8 <6 < 32 < 12 07/04/17 -07/25/17 < 8 < 8 < 21 < 8 < 20 < 9 < 16 < 10 <9 < 43 < 13 08/01/17 -08/29/17 < 9 <8 < 19 < 9 < 19 < 10 < 16 < 10 <9 < 44 < 14 09/05/17 -09/26/17 < 5 <6 < 12 < 5 < 11 < 6 < 8 <6 <5 < 24 < 12 10/03/17 -10/24/17 < 5 < 5 < 9 < 6 < 11 <6 < 8 < 5 <6 < 22 < 8 10/31/17 -11/28/17 <4 < 5 < 9 < 6 < 14 < 7 < 8 < 5 < 5 < 26 < 10 12/05/17 -12/26/17 < 7 < 7 < 17 < 8 < 16 < 9 < 13 < 8 < 7 < 36 < 9 0 MEAN I .i:,. 1S 01/03/17 -01/25/17 (1) 02/02/17 -02/28/17 (1) 03/14/17 -03/28/17 < 8 < 9 < 17 < 8 < 15 < 10 < 12 < 7 < 8 < 32 < 13 04/04/17 -04/25/17 <6 < 5 < 14 < 6 < 11 < 7 < 13 < 8 <7 < 31 < 11 05/02/17 -05/30/17 < 8 < 7 < 17 < 9 < 15 < 8 < 11 < 8 < 7 < 38 < 12 06/06/17 -06/27/17 (1) 07/11/17 -07/18/17 < 5 < 5 < 11 < 5 < 10 < 5 < 8 < 5 < 4 < 35 < 10 08/01 /17 -08/29/17 (1) 09/05/17 -09/26/17 (1) 10/03/17 -10/24/17 (1) 10/31/17 -11/2 8/17 (1) 12/05/17 -12/26/17 (1) MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION Table D-11.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLEC T ED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 QCB1N 01/03/17 -01/25/17 <2 < 2 <4 <2 < 5 < 3 < 3 < 2 <2 < 11 < 3 02/02/17 -02/28/17 <2 < 2 <4 < 1 <4 <2 < 5 < 2 <3 < 14 < 2 03/08/17 -03/08/17 04/14/17 -04/14/17 05/09/17 -05/09/17 06/06/17 -06/27/17 < 3 < 2 < 6 < 1 < 6 < 3 < 5 < 3 <3 < 14 < 3 07/04/17 -07/25/17 < 2 < 1 < 4 < 2 < 3 < 3 < 5 < 2 <2 < 15 < 2 08/01/17 -08/29/17 < 3 < 2 < 5 < 3 < 3 <4 < 3 < 3 <3 < 11 < 2 09/05/17 -09/26/17 <3 < 2 < 6 < 2 < 2 < 2 < 5 < 2 <3 < 11 < 5 10/03/17 -10/24/17 <2 < 2 < 2 < 2 < 5 < 2 < 4 < 2 < 3 < 11 <4 10/31/17 -11/28/17 <2 < 2 < 7 < 2 <4 < 2 < 5 < 2 < 2 < 15 <4 12/05/17 -12/26/17 <2 < 4 <6 < 3 < 7 < 3 <6 < 3 < 2 < 10 < 3 0 MEAN I <11 QCB1S 01/03/17 -01/25/17 (1) 02/02/17 -02/28/17 (1) 03/14/17 -03/28/17 < 3 < 2 < 4 < 3 < 3 < 3 < 5 < 3 < 2 < 14 < 2 04/04/17 -04/25/17 < 2 < 3 < 2 < 2 < 3 < 3 < 5 < 3 < 2 < 12 < 3 05/02/17 -05/30/17 < 3 < 2 < 2 < 2 < 3 < 2 <4 < 3 < 3 < 12 <4 06/06/17 -06/27/17 (1) 07/11/17 -07/18/17 <2 < 2 < 3 < 1 < 3 < 2 < 4 < 2 <2 < 12 < 3 08/01/17 -08/29/17 (1) 09/05/17 -09/26/17 (1) 10/03/17 -10/24/17 (1) 10/31/17 -11/28/17 (1) 12/05/17 -12/26/17 (1) MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION Table D-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION , 2017 R E SULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD W-3C QC B 0 1/09/17 -0 1/0 9/17 < 195 < 155 04/07117 -04/07117 < 187 < 151 0 7/12117 -07/1 2/17 < 193 < 149 1 0/1 2/17 -1 0/1 2/17 < 176 < 149 ME AN D-6 Table D-111.2 SITE W-3C QCB 0 I ..... CONCENTRATIONS OF GAMMA EMI TT ERS IN GROUNDWATER SAMPLES COLLE C TED IN TH E VICINITY OF OYST E R CREEK GENERATING STATION , 2017 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA C O LL E CTION PERI O D Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 01/09/17 -01/09/17 < 5 < 7 < 14 <6 < 12 < 6 < 12 < 11 <6 < 6 04/07/17 -04/07/17 < 5 < 6 < 13 <4 < 12 < 7 < 11 < 10 < 7 < 6 07/12/17 -07/12/17 < 9 < 8 < 19 <7 < 18 < 10 < 14 < 15 < 9 < 9 10/1 2/17 -1 0/12/17 <4 <4 < 8 <4 < 7 < 4 <6 < 9 < 4 <4 MEAN 01/09/17 -01/09/17 < 2 < 2 < 5 < 2 < 5 < 3 < 5 < 6 < 2 < 3 04/07 /17 -04/07 /17 < 3 < 3 < 5 <2 < 3 < 3 < 5 < 11 < 3 < 2 07/12/17 -07/12/17 < 4 < 3 < 8 < 2 < 5 < 2 < 3 < 13 < 3 < 2 10/12/17 -10/12/17 < 2 < 5 <6 < 3 < 5 < 3 <6 < 8 < 3 <5 MEAN Ba-140 La-140 < 28 < 11 < 25 < 8 < 40 < 13 < 24 < 8 < 10 <4 < 20 < 3 < 25 < 5 < 21 < 3 Table D-IV.1 SITE 24 QCA QCB 0 I 00 CONCENTRATIONS O , f GAMMA EMITTERS IN CLAM SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 COLLECTION PERIOD 05/15/17 05/15/17 05/15/17 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA K-40 M n-54 Co-58 Fe-59 Co-60 1250 +/- 501 < 42 < 32 < 64 < 33 1391 +/- 782 <54 <48 < 97 < 45 1480 +/- 89 <5 <4 < 16 < 5 Zn-65 Cs-134 Cs-137 < 83 < 31 < 34 < 94 < 49 < 48 <8 <4 <3 Table D-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-228 24 05/16/17 < 711 15850 +/- 1606 < 80 < 81 < 81 < 94 < 85 < 1615 555 +/- 191 10/16/17 < 592 7055 +/- 1224 < 71 < 71 < 69 < 84 < 77 2238 +/- 1134 480 +/- 105 MEAN+/- 2 STD DEV 11453 +/- 12438 2238 +/- 0 518 +/- 122 QCA 05/16/17 < 849 12250 +/- 2008 < 91 < 94 < 88 < 99 < 88 2100 +/- 1604 636 +/- 159 10/16/17 < 517 10550 +/- 875 < 56 < 61 < 64 < 75 < 63 1747 +/- 917 688 +/- 130 MEAN+/- 2 STD DEV 11400 +/- 2404 1924 +/- 972 662 +/- 41 QCB 05/16/17 < 314 12819 +/- 736 < 29 < 18 < 17 < 23 < 25 1140 +/- 649 2364 +/- 1326 0 10/16/17 < 202 10156 +/-611 < 23 I < 17 < 15 < 18 < 17 1197 +/- 351 1701 +/- 1010 (0 MEAN +/- 2 STD DEV 11488 +/- 3766 1169 +/- 421 2033 +/- 447 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES TABLE 0-Vl.1 SITE 36 Cabbage Collards Kale QCA Cabbage Collards Kale C ' ...... 0 QCB Cabbage Collards Kale CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/KG WET+/- 2 SIGMA COLLECTION PERIOD Sr--89 Sr-90 Be-7 K-40 1-131 Cs-134 Cs-137 Ba-140 08/30/17 < 16 8.8 +/- 3.7 186 +/- 139 1344 +/- 236 < 46 < 14 < 17 08/30/17 < 15 10.9 +/- 2.8 492+/- 114 1882 +/- 210 < 41 < 12 19 +/- 12 08/30/17 < 16 5.9 +/- 2.7 349+/-116 2098 +/- 191 < 34 < 12 < 13 MEAN +/- 2 STD DEV 8.5 +/- 5 342 +/- 307 1775 +/- 777 08/30/17 < 20 < 3.6 < 172: 2596 +/- 323 < 50 < 20 < 19 < 124 08/30/17 < 22 < 2.9 < 189 6212 +/- 453 < 52 < 20 < 20 < 124 08/30/17 < 22 < 3.3 < 162 5507 +/- 441 < 47 < 20 < 26 < 114 MEAN +/- 2 STD DEV 4772 +/- 3834 08/30/17 < 4 <6 < 92 2148 +/- 255 < 30 < 7 <6 < 69 08/30/17 < 10 < 14 < 97 4943 +/- 300 < 21 < 6 < 7 < 41 08/30/17 < 18 < 13 156 +/- 91 6147 +/- 412 < 16 < 8 < 10 < 56 MEAN +/- 2 STD DEV 156 +/- 0 4413 +/- 4103 La-140 < ##-< 80 < 74 < 29 < 36 < 34 < 17 <6 < 9 APPENDIX E INTER-LABORATORY COMPARISON PROGRAM Intentionally left blank TABLE E.1 Ana lytics Environmental Radioactivity Cross Check Program Teledlne Brown EnsineerinS Environmental Services Identification TBE Known Ratio of TBE to Month/Year Number Matrix Nuclide Units Reported Value<*) Analytics Result Evaluation Cb) Value March 2017 E11811 Milk Sr-89 pCi/L 87 97.7 0.89 A Sr-90 pCi/L 12.4 16.2 0.77 w E11812 Milk Ce-141 pCi/L 135 145 0.93 A Co-5 8 pCl/L 153 150 1.02 A Co-60 pCi/L 182 183 1.00 A Cr-51 pCi/L 258 290 0.89 A Cs-134 pCi/L 104 120 0.87 A Cs-137 pCi/L 142 140 1.02 A Fe-59 pCi/L 135 129 1.05 A 1-131 pCi/L 92.6 97.9 0.95 A Mn-54 pCi/L 173 164 1.05 A Zn-65 pCi/L 208 199 1.04 A E11813 Charcoal 1-131 pCi 92 93.9 0.98 A E11814 AP Ce-141 pCi 99.9 101 0.99 A Co-58 pCi 95.4 104 0.92 A Co-60 pCi 140 127 1.10 A Cr-51 pCi 211 201 1.05 A Cs-134 pCI 82.1 83.2 0.99 A Cs-137 pCi 92.8 97.0 0.96 A Fe-59 pCi 107 89.3 1.20 A Mn-54 pCi 106 114 0.93 A Zn-65 pCi 137 138 0.99 A E11816 Soil Ce-141 pCi/g 0.258 0.250 1.03 A Co-58 pCi/g 0.241 0.258 0.93 A Co-60 pCi/g 0.312 0.315 0.99 A Cr-51 pCi/g 0.439 0.500 0.88 A Cs-134 pCi/g 0.176 0.207 0.85 A Cs-137 pCi/g 0.304 0.317 0.96 A Fe-59 pCi/g 0.210 0.222 0.95 A Mn-54 pCi/g 0.292 0.283 1.03 A Zn-65 pCi/g 0.353 0.344 1.03 A E11815 Water Fe-55 pCi/L 1600 1890 0.85 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparat i on (b) Analytics evaluation based on TBE internal QC limits: A= Acceptable

-reported result falls within ratio limits of0.80-1.20 W = Acceptable with warning -reported result falls within 0. 70-0. 80 or 1. 20-1. 30 N = Not Acceptable

-reported result falls outside the ratio limits of< 0. 70 and > 1. 30 (Page 1 of 4) E-1 TABLE E.1 Analytics Environmental Radioactivity Cross Check Program Teled:i:ne Brown En~ineerin~

Environmental Services Identification TBE Known Ratio of TBE to MonthNear Number Matrix Nuclide Units Reported Va l ue Cal Analytics Result Value June 2017 E11844 Milk Sr-89 pCi/L 81.3 92.6 0.88 Sr-90 pCi/L 12.1 1 3.5 0.90 E11846 Milk Ce-141 pCi/L 142 151 0.94 Co-58 pCi/L 147 155 0.95 Co-60 pCi/L 185 19 1 0.97 Cr-51 pC i/L 321 315 1.02 Cs-134 pCi/L 168 188 0.89 Cs-137 pCi/L 148 150 0.99 Fe-59 pCi/L 116 115 1.01 1-131 pC i/L 1 02 93.6 1.09 Mn-54 pCi/L 168 172 0.98 Zn-65 pCi/L 195 204 0.96 E11847 Charcoal 1-131 pCi 87.9 84.8 1.04 E11845 AP Sr-89 pCi 7 0.8 79.1 0.90 Sr-90 pCi 9.10 11.5 0.79 E11848 AP Ce-141 pCi 112 116 0.96 Co-5 8 pC I 1 19 11 9 1.00 Co-60 pCi 171 146 1.17 Cr-51 pCi 270 241 1.12 Cs-134 pCi 152 144 1.05 Cs-137 pCi 114 115 0.99 Fe-59 pCi 94.1 88.3 1.07 Mn-54 pCi 139 132 1.06 Zn-65 pCi 141 156 0.90 E11849 Water Fe-55 pCi/L 1 840 1 890 0.97 Ju l y 2017 E11901 AP GR-A pCi 50.1 44.2 1.13 GR-8 pCi 218 233 0.93 (a) The Analytics kno w n value is equal to 100% of the paramete r present i n the standard as determ i ned b y grav i met ri c a nd/o r volumetric measurements made during standard preparat i o n (b) Analytics evaluation based on TBE internal QC limits: A = Acceptable

-reported resu l t falls w i thin ratio limits of 0. 80-1. 20 W = Acceptable wi th warn i ng -reported result falls wi th i n O. 70-0. 80 o r 1. 20-1. 30 N = Not Acceptable

-reported result falls ou t s i de the rat i o li m i ts o f< O. 7 0 and > 1. 30 E-2 Evaluation (b l A A A A A A A A A A A A A A w A A A A A A A A A A A A (Page 2 of 4)

TABLE E.1 Analytics Environmental Radioactivity Cross Check Program Teledlne Brown En~ineerin~

Environmental Services Identification TBE Known Ratio of TBE to Month/Year Number Matrix Nuclide Units Reported Value Ca l Analytics Result Evaluation Cb> Value Septemb er 2017 E11914 Milk Sr-89 pCi/L 84.3 82.7 1.02 A Sr-90 pCi/L 12.6 12.1 1.04 A E11915 Milk Ce-141 pCi/l 93.9 87.0 1.08 A Co-58 pC i/L 115 117 0.98 A Co-60 pCi/L 265 262 1.01 A Cr-51 pCi/L 273 217 1.26 w Cs-134 pCi/l 186 201 0.93 A Cs-137 pCi/L 175 172 1.02 A Fe-59 pCi/L 137 125 1.09 A 1-13 1 pCi/L 78.0 71.0 1.10 A Mn-54 pCi/L 128 123 1.04 A Zn-65 pCi/L 206 184 1.12 A E11916 Charcoal 1-131 pCi 71.9 64.4 1.12 A E11917 AP Ce-141 pCi 80.1 86.3 0.93 A Co-58 pCi 110 116 0.95 A Co-60 pCi 277 260 1.07 A Cr-51 pCi 275 215 1.28 w Cs-134 pC I 192 199 0.96 A Cs-137 pCi 165 170 0.97 A Fe-59 pCi 122 124 0.98 A Mn-54 pCi 120 122 0.99 A Zn-65 pCi 175 183 0.96 A E11918 Water Fe-55 pCi/l 1630 1630 1.00 A E11919 Soil Ce-141 pCi/g 0.136 0.142 0.96 A Co-58 pCi/g 0.179 0.191 0.94 A Co-60 pCi/g 0.405 0.429 0.94 A Cr-51 pCi/g 0.230 0.355 0.65 N c 1> Cs-134 pCi/g 0.272 0.328 0.83 A Cs-137 pCi/g 0.336 0.356 0.94 A Fe-59 pCi/g 0.210 0.205 1.02 A Mn-54 pCi/g 0.210 0.201 1.05 A Zn-65 pCi/g 0.301 0.301 1.00 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparat i on (b) Analytics evaluation based on TBE internal QC limits: A = Acceptable

-reported result falls within ratio limits of O. 80-1. 20 W= Acceptable with warning-reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable

-reported result falls outside the rat i o limits of< 0. 70 and > 1. 30 (1) See NCR 17-16 (Page 3 of 4) E-3 TABLE E.1 Analytics Environmental Radioactivity Cross Check Program Teledine Brown EnsineerinS Environmental Services Identification TBE Known Ratio of TBE to Month/Year Number Matrix Nuclide Units Reported Value<*> Analytics Result Value December 2017 E12054 Milk Sr-89 pCi/L 92.1 92.3 1.00 Sr-90 pCi/L 18.3 16.9 1.09 E12055 Milk Ce-141 pCi/L 97.8 98.3 0.99 Co-58 pCi/L 92.3 89.9 1.03 Co-60 pCi/L 176 173 1.02 Cr-51 pCi/L 226 242 0.93 Cs-134 pCi/L 118 125 0.95 Cs-137 pCi/L 148 141 1.05 Fe-59 pCi/L 123 113 1.08 1-131 pCi/L 66.0 57.8 1.14 Mn-54 pCi/L 173 161 1.08 Zn-65 pCi/L 233 211 1.10 E12056 Charcoal 1-131 pCi 48.1 47.5 1.01 E12057A AP Ce-141 pCi 10 8 111 0.97 Co-58 pCi 89.5 102 0.88 Co-60 pCi 223 196 1.14 Cr-51 pCi 311 274 1.13 Cs-134 pCi 141 142 1.00 Cs-137 pCi 162 160 1.01 Fe-59 pCi 121 129 0.94 Mn-54 pCi 177 182 0.97 Zn-65 pCi 203 239 0.85 E12058 Water Fe-55 pCi/L 1970 1740 1.13 E12059 AP Sr-89 pCi 71.2 87.4 0.81 Sr-90 pCi 12.9 16.0 0.81 (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits: A = Acceptable

-reported result falls within ratio limits of 0. 80-1. 20 W = Acceptable with warning -reported result falls within 0. 70-0.80 or 1.20-1.30 N = Not Acceptable

-reported result falls outside the rat i o limits of< O. 70 and> 1.30 E-4 Evalua tion (bl A A A A A A A A A A A A A A A A A A A A A A A A A (Page 4 of 4)

TABLE E.2 DOE's Mixed Analyte Perfonnance Evaluation Program (MAPEP) Teledine Brown EnsineerinS Environmental Services Identification TBE Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (b l Number Value Value <*J Range February 2017 17-MaS36 Soil Ni-63 Sq/kg -5.512 (1) A Sr-90 Sq/kg 571 624 437-811 A 17-MaW36 Water Am-241 Sq/l 0.693 0.846 0.592-1.100 A Ni-63 Bq/l 13.4 12.2 8.5-15.9 A Pu-238 Bq/l 0.7217 0.703 0.492 -0.914 A Pu-239/240 Bq/l 0.9277 0.934 0.654 -1.214 A 17-RdF36 AP U-234/233 Sq/sample 0.0911 0.104 0.073 -0.135 A U-238 Sq/sample 0.0967 0.107 0.075 -0.139 A 17-RdV36 Vegetation Cs-134 Sq/sample 6.44 6.95 4.87 -9.04 A Cs-137 Sq/sample 4.61 4.60 3.22 -5.98 A Co-57 Sq/sample

-0.0229 (1) A Co-60 Sq/sample 8.52 8.75 6.13 -11.38 A Mn-54 Sq/sample 3.30 3.28 2.30 -4.26 A Sr-90 Sq/sample 1.30 1.75 1.23 -2.28 w Zn-65 Sq/sample 5.45 5.39 3.77 -7.01 A Aug u st2017 17-MaS37 Soil Ni-63 Sq/kg 1130 1220 854 -1586 A Sr-90 Bq/kg 296 289 202 -376 A 17-MaW37 Water Am-241 Sq/l 0.838 0.892 0.624 -1.160 A Ni-63 Bq/l -0.096 (1) A Pu-238 Sq/l 0.572 0.603 0.422 -0.784 A Pu-239/240 Sq/l 0.863 0.781 0.547 -1.015 A 17-RdF37 AP U-234/233 Sq/sample 0.103 0.084 0.059-0.109 w U-238 Sq/sample 0.115 0.087 0.061-0.113 N c 2J 17-RdV37 Vegetation Cs-134 Sq/sample 2.34 2.32 1.62 -3.02 A Cs-137 Sq/sample 0.05 (1) A Co-57 Sq/sample 3.32 2.8 2.0 -3.6 A Co-60 Sq/sample 2.09 2.07 1.45 -2.69 A Mn-54 Sq/sample 2.90 2.62 1.83 -3.41 A Sr-90 Sq/sample 1.17 1.23 0.86 -1.60 A Zn-65 Sq/sample 6.07 5.37 3.76 -6.98 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric me a surements made during standard preparation (b) DOE!MAPEP evaluation

A = Acceptable

-reported result falls within ratio limits of 0. 80-1. 20 W = Acceptable with warning -reported result falls within 0. 70-0. 80 or 1. 20-1. 30 N = Not Acceptable

-reported result falls outside the ratio limits of< O. 70 and > 1.30 (1) False positive test (2) See NCR 17-15 (Page 1 of 1) E-5 TABLE E.3 ERA Environmental Radioactivity Cross Check Program Teledine Brown EnaineerinS Environmental Services TBE ldentrification Known Acceptance Month/Year Number Matrix Nudide Units Reported Value<*> Limits Evaluation (b l Value March 2017 MRAD-26 AP GR-A pCi/sample 76.3 85.5 28.6 -133 April2017 RAD-109 Water Ba-133 pCi/L 49.2 49.7 40.8 -55.1 Cs-134 pCi/L 83.2 90.1 74.0 -99.1 Cs-137 pCi/L 202 206 185 -228 Co-60 pCi/L 51.2 54.7 49.2 -62.7 Zn-65 pCi/L 39.3 53.8 47.2 -65.9 GR-A pCi/L 53.6 75.0 39.5 -92.3 GR-B pCi/L 42.7 38.5 25.5 -46.0 U-Nat pCi/L 50.1 55.6 45.2 -61.7 H-3 pCi/L 7080 6850 5920-7540 Sr-89 pCi/L 40.7 66.2 53.8 -74.3 Sr-90 pCi/L 26.9 26.7 19.3-31.1 1-131 pCi/L 26.7 29.9 24.9 -34.9 September 2017 MRAD-27 AP GR-A pCi/sample 40.9 50.1 16.8 -77.8 AP GR-B pCi/sample 58.0 61.8 39.1 -90.1 October 2017 RAD-111 Water Ba-133 pCi/L 71.3 73.7 61.7 -81.1 Cs-134 pCi/L 43.0 53.0 42.8 -58.3 Cs-137 pCi/L 48.2 52.9 47.6-61.1 Co-60 pCi/L 69.0 69.5 62.6 -78.9 Zn-65 pCi/L 335 348 313 -406 GR-A pCi/L 32.5 35.6 18.3 -45.8 GR-B pCi/L 24.3 25.6 16.0 -33.6 U-Nat pCi/L 36.6 37.0 30.0 -40.9 H-3 pCi/L 6270 6250 5390 -6880 1-131 pCi/L 26.4 24.2 20.1 -28.7 November 2017 1113170 Water Sr-89 pCi/L 57.1 50.0 39.4 -57.5 Sr-90 pCi/L 27.1 41.8 30.8-48.0 (a) The ERA known value is equal to 100% of the parameter present in the standard as determined by grav i metric and/or volumetric measurements made during standard preparation. (b) ERA evaluation

A = Acceptable

-Reported value falls within the Acceptance Limits N = Not Acceptable

-Reported value falls outside of the Acceptance Limits (1) See NCR 17-09 (2) See NCR 17-19 E-6 A A A A A N c1> A A A A N c1J A A A A A A A A A A A A A A A N c2J (Page 1 of 1)

TAB L E E.4 lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERAt MRAD Study Environmental, Inc., Midwest Laboratory Concentration Lab Code b Date Analysis Laboratory ERA Result Control Limits c Acceptance Result ERAP-1112 3/20/2017 Am-241 55.3 +/- 2.8 76.4 47.1 -103.0 Pass ERAP-1112 3/20/2017 Co-60 1 , 230 +/- 8 1030 797 -1290 Pass ERAP-1112 3/20/2017 Cs-134 1 , 110 :t 9 1 100.0 7 00-1360 Pass ERAP-1112 3/20/2017 Cs-137 1 , 810+/-12 1390 1 , 040 -1 , 830 Pass ERAP-1112 d 3/20/2017 Fe-55 590 +/- 385 256 79.4 -500 Fail ERAP-1112 3/20/2017 Mn-54 < 5.14 < 50.0 0.00 -50.0 Pass ERAP-1112 3/20/2017 Pu-238 54.6 +/- 2.8 54.3 37.2 -71.4 Pass ERAP-1112 3/20/2017 Pu-239/240 63.6 +/- 3.0 62.0 44.9 -81.0 Pass ERAP-1112 3/20/2017 Sr-90 55.3 +/- 8.3 52.4 25.6 -78.5 Pass ERAP-1112 3/20/2017 U-233/234 65.7 +/- 3.0 73.1 45.3-110 Pass ERAP-1112 3/20/2017 U-238 67.3 +/- 3.0 72.4 46.8 -100 Pass ERAP-1112 3/20/2017 Zn-65 1 , 355 +/- 16 984.0 705 -1 , 360 Pass ERAP-1114 3/20/2017 Gr. Alpha 106 +/- 5 85.5 28.6 -133 Pass ERAP-1114 8 3/20/2017 Gr. Beta 67.6 +/- 3.0 45.2 28.6-65.9 Fail ERS0-1116 3/20/2017 Am-241 418 +/- 98 448 262 -582 Pass ERS0-1116 3/20/2017 Ac-228 1 , 540 +/- 260 1240 795 -1 , 720 Pass ERS0-1116 3/20/2017 Bi-212 1 , 550 +/- 90 1240.0 330 -1 , 820 Pass ERS0-1116 3/20/2017 Bi-214 2 , 560 +/- 20 2750 1 , 660 -3 , 960 Pass ERS0-1116 3/20/2017 Co-60 4 , 620 +/- 100 4430.0 3 , 000 -6 , 100 Pass ERS0-1116 3/20/201 7 Cs-134 8 , 340 +/- 100 8860.0 5 , 7 90 -10,600 Pass ERS0-1116 3/20/2017 Cs-137 8,420 +/- 100 7500.0 5 , 750 -9 , 650 Pass ERS0-1116 3/20/2017 K-40 13 , 600 +/- 900 10600.0 7 , 740 -14 , 200 Pass ERS0-1116 3/20/2017 Mn-54 < 68.1 < 1000 0.00 -1 , 000 Pass ERS0-1116 3/20/2017 Pb-212 1 , 060 +/- 70 12 4 0.0 812 -1 , 730 Pass ERS0-1116 3/20/2017 Pb-214 2 , 620 +/- 160 2890.0 1 , 690-4 , 310 Pass ERS0-1116 3/20/2017 Pu-238 424 +/- 154 648.0 390-894 Pass ERS0-1116 1 3/20/2017 Pu-239/240 252+/-112 484 316 -669 Fail ERS0-1116 g 3/20/2017 Pu-239/240 436 +/- 106 484 316 -669 Pass ERS0-1116 3/20/2017 Sr-90 7 , 930 +/- 250 9150 3,490 -14 , 500 Pass ERS0-1116 3/20/2017 Th-234 1 , 820 +/- 200 1940 614 -3 , 650 Pass

Results ob t a i ned by Env i ronmental , Inc., M i d w est Laboratory as a participant in the crosscheck program for profic i ency testing administered by Environmental Resources Associates , serv i ng as a replacement for studies conducted previously by the Environmental Measurements Laboratory Qua li ty Assurance Program (EIML) b Labora t ory codes as follo w s: ERW (water), ERAP (a i r filte r), ERSO (soil), ER V E (vegetation

). Results are reported i n units of pC il, except fo r air filters (pCi/F i lte r), vegetation and soil (pCilkg. c Resul t s are presented as t he known values , e x pected labora t ory prec i sion (2 s i gma , 1 determinat i on) and control li m it s as provided b y ERi d Fe-55 ana l ys i s result w as outs i de the acceptab l e range. Recount i ng the sample disk for 1000 m i nutes resulted i n 254 +/- 364 w i th a n L LD calculat i on of< 342. Insuffic i ent sample w as ava i lable afte r perfo rmi ng other requ i red analyses on t he sample to quan ti fy the act i v i ty wit h c uncertainty less than the activ i ty. 8 ERA appears to have applied the standard material to the filter i n a pattern closer to the center of the filter compared to previous studies an different from the filter effic i ency utilized by the laboratory. Th i s likely caused the efficency used t he calculation to be understated and the result obt ai ned by the labora t ory to be oversta t ed. For compa ri son , the AP gross beta in-house spike had a ratio of O. 94 of lab result to kno ' Analysis result for Plutonium-2391240 was below the lower lim i t of acceptance.

u Samples were reanalyzed i n duplicate with acceptable results for each. Original analysis had poor resolution possib l y due to a poor elctrop l at i ng and i s suspec t ed i n contribut i ng to poor resu l ts. (Page 1 of 2) E-7 TABLE E.4 lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERAt MRAD Study Environmental, Inc., Midwest Laboratory Concentration Lab Code b Date Analysis Laboratory ERA Result Control Limits c Acceptance Result ERS0-1116 h 3/20/2017 U-233/234 1 , 030 +/- 130 1950 1 , 190-2 , 500 Fail ERS0-1116' 3/20/2017 U-233/234 1 , 820 +/- 200 1950 1 , 190-2 , 500 Pass ERS0-1116 3/20/2017 U-238 1 , 240 +/- 140 1940 1,200 -2,460 Pass ERS0-1116; 3/20/2017 U-238 1 , 930 +/- 200 1940 1 , 200 -2,460 Pass ERS0-1116 3/20/2017 Zn-65 7 , 190 +/- 240 6090 4 , 850 -8 , 090 Pass ERW-1122 3/20/2017 Gr. Alpha 65.3 +/- 2.4 89.5 31.8-139 Pass ERW-1122 3/20/2017 Gr. Beta 54.8 +/- 1.5 61 34.9 -90.4 Pass ERW-1124 3/20/2017 H-3 19 , 000 +/- 410 19400 13 , 000 -27 , 700 Pass ERVE-1118 42814 Am-241 1 , 560 +/- 140 1860 1 , 140-2,470 Pass ERVE-1118 42814 Cm-244 530 +/- 80 734 360 -1 , 140 Pass ERVE-1118 42814 Co-60 1,400 +/- 350 1390 959 -1 , 940 Pass ERVE-1118 42814 Cs-134 1 , 650 +/- 460 1830 1 , 180 -2 , 380 Pass ERVE-1118 42814 Cs-137 2 , 580 +/- 540 2500 1 , 810 -3,480 Pass ERVE-1118 42814 K-40 32 , 100 +/- 700 30900 22,300 -43,400 Pass ERVE-1118 42814 Mn-54 < 27.3 < 300 0.00 -300 Pass ERVE-1118 42814 Zn-65 889 +/- 64 853 615-1 , 200 Pass ERVE-1118 42814 Pu-238 3 , 250 +/- 210 3250 1 , 940 -4,450 Pass ERVE-1118 42814 Pu-239/240 2 , 180 +/- 170 2150 1 , 320 -2 , 960 Pass ERVE-1118 42814 Sr-90 665 +/- 135 726 414 -963 Pass ERVE-1118 42814 U-233/234 2 , 840 +/- 200 3090 2 , 030 -3 , 970 Pass ERVE-1118 42814 U-238 2 , 990 +/- 200 3060 2,040 -3 , 890 Pass ERW-1120 42814 Am-241 108 +/- 7 140 94.3 -188 Pass ERW-1120 42814 Co-60 2 , 600 +/- 198 2540 2 , 210 -2 , 970 Pass ERW-1120 42814 Cs-134 2 , 380 +/- 250 2510 1 , 840 -2880 Pass ERW-1120 42814 Cs-137 1,470 +/- 243 1400 1 , 190 -1 , 680 Pass ERW-1120 42814 Mn-54 < 12.3 < 100 0.00 -100 Pass ERW-1120 42814 Pu-238 117 +/- 4 128 94.7 -159 Pass ERW-1120 42814 Pu-239/240 74.8 +/- 3.3 85.8 66.6 -108 Pass ERW-1120 42814 U-233/234 75.3 +/- 3.2 90.3 67.8-116 Pass ERW-1120 42814 U-238 76.4 +/- 3.2 89.5 68.2-110 Pass ERW-1120 42814 Zn-65 2 , 130 +/- 378 1960 1630 -2,470 Pass ERW-1120 i 42814 Fe-55 1,400 +/- 403 984 587 -1 , 340 Fail ERW-1120 k 42814 Fe-55 1 , 081 +/- 383 984 587 -1 , 340 Pass ERW-1120 42814 Sr-90 652 +/- 12 714 465 -944 Pass

Results obtained by Environmental , Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates , serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assurance Program (EIML) b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi l, except for air filters (pCi!Filter). vegetation and soil (pCilkg). c Results are presented as the known values , expected laboratory precision (2 sigma , 1 determ i nation) and control limits as provided by ER, h Analysis result for Uranium-2331234 was below the lower limit of acceptance i Samples were reanalyzed in duplicate with acceptable results for each. Original analysis had poor resolution possibly due to a poor elctroplating and i s suspected in contributing to poor results. j Iron -55 analysis result was outside acceptable range i Result of recounting was acceptable. Using available aliquot after dividing sample for other analyses leaves insufficient sample to reliably determ i ne the activity present in sample. (Page 2 of 2) E-8 TABLE E.5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Environmental, Inc., Midwest Laboratory Concentration Lab Codeb Reference Analysis Laboratory Known Control Limits c Acceptance Date Result Activity MAS0-903 2/1/2017 Am-241 60.9 +/- 6.9 67 46.9 -87.1 Pass MAS0-903 2/1/2017 Cs-134 1360 +/- 14 1550 1085 -2015 Pass MAS0-903 2/1/2017 Cs-137 678 +/- 13 611 428 -794 Pass MAS0-903 2/1/2017 Co-57 1.63+/-1.69 0.000 NA C Pass MAS0-903 2/1/2017 Co-60 909 +/- 12 891.0 624 -1158 Pass MAS0-903 2/1/2017 Mn-54 1052 +/- 17 967.0000 677 -1257 Pass MAS0-903 2/1/2017 K-40 657 +/- 68 607.0000 425-789 Pass MAS0-903 2/1/2017 Zn-65 -0.52 +/- 7.40 0.0 NA C Pass MAS0-903 2/1/2017 N i-63 3.25 +/- 7.17 0.0000 NA C Pass MAS0-903 2/1/2017 Pu-238 0.46 +/- 0.69 0.4100 NA e Pass MAS0-903 2/1/2017 Pu-239/240 56.8 +/- 5.9 59.8 41.9 -77.7 Pass MAS0-903 2/1/2017 Sr-90 501 +/- 17 624.00 437-811 Pass MAS0-903 2/1/2017 Tc-99 748 +/- 16 656.00 459-853 Pass MAW-849 2/1/2017 1-129 -0.05 +/- 0.12 0.0000 NA C Pass MAVE-905 2/1/2017 Cs-1 34 6.61 +/- 0.16 6.95 4.87 -9.04 Pass MAVE-905 2/1/2017 Cs-137 4.97 +/- 0.18 4.60 3.22 -5.98 Pass MAVE-905 2/1/2017 Co-57 -0.01 +/- 0.03 0.00 NA C Pass MAVE-905 2/1/2017 Co-60 9.51 :I: 0.17 8.75 6.13-11.38 Pass MAVE-905 2/1/2017 Mn-54 3.67+/-0.17 3.28 2.30 -4.26 Pass MAVE-905 2/1/2017 Zn-65 6.12+/-0.44 5.39 3.77 -7.01 Pass MAW-847 2/1/2017 Am-241 0.679 +/- 0.079 0.846 0.592 -1.100 Pass MAW-847 2/1/2017 Cs-134 0.03 +/- 0.10 0 NA C Pass MAW-847 2/1/2017 Cs-137 12.7 +/- 0.4 11.100 7.8 -14.4 Pass MAW-847 d 2/1/2017 Co-57 2.7 +/- 0.3 28.500 20.0 -37.1 Fail MAW-847 2/1/2017 Co-60 13.5 +/- 0.3 12.300 8.6 -16.0 Pass MAW-847 2/1/2017 Mn-54 16.5 +/- 0.4 14.900 10.4-19.4 Pass MAW-847 2/1/2017 K-40 287 +/-6 254.0 178 -330 Pass MAW-847 2/1/2017 Zn-65 -0.15 +/- 0.23 0.000 NA C Pass MAW-847 2/1/2017 H-3 275 +/- 10 249.000 174 -324 Pass MAW-847 2/1/2017 Fe-55 2.4 +/- 13.6 1.7 NAe Pass MAW-847 2/1/2017 Ni-63 10.1 +/- 2.8 12.20 8.5 -15.9 Pass MAW-847 2/1/2017 Pu-238 0.729 +/- 0.097 0.70 0.492 -0.914 Pass MAW-847 2/1/2017 Pu-239/240 0.866 +/- 0.102 0.934 0.654 -1.214 Pass MAW-847 2/1/2017 Ra-226 0.506 +/- 0.053 0.504 0.353 -0.655 Pass MAW-847 2/1/2017 Sr-90 10.0 +/- 0.8 10.10 7.1 -13.1 Pass

Results are reported in units of Bqlkg (soil), Bq/L (water) or Bqltotal sample (filt ers. vegetation) b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation) c MAPEP results are presented as the known values and expected laboratory precision (1 sigma , 1 determination) and control limits as defined by the MAPEP. A known value of " zero" indicates an analysis was i ncluded in the testing serit as a false positive". MAPEP does not provide control limits. d Dec imal point was misplaced while performing a unit conversion. The result is within control limits when the proper ur conversion is performed.

Provided in the series for sensitivity evaluation". MAPEP does not prov i de control limits. (Page 1 of 3) E-9 TABLE E.5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Environmental, Inc., Midwest Laboratory Concentration Lab Codeb Reference Analysis Laboratory Known Control Limits c Acceptance Date Result Activity MAW-847 2/1/2017 Tc-99 4.77 +/- 0.62 6.25 4.38-8.13 Pass MAW-847 2/1/2017 U-234/233 1.19+/-0.10 1.16 0.81 -1.51 Pass MAW-847 2/1/2017 U-238 1.15 +/- 0.10 1.20 0.84-1.56 Pass MAAP-907 1 2/1/2017 Am-241 0.0540 +/- 0.0140 0.0376 0.0263 -0.0489 Fail MAAP-907 2/1/2017 Cs-134 1.31 +/- 0.06 1.42 0.99-1.85 Pass MAAP-907 2/1/2017 Cs-137 0.797 +/- 0.080 0.685 0.480 -0.891 Pass MAAP-907 2/1/2017 Co-57 1.86 +/- 0.06 1.70 1.19 -2.21 Pass MAAP-907 2/1/2017 Co-60 0.86 +/- 0.05 0.78 0.55 -1.01 Pass MAAP-907 2/1/2017 Mn-54 0.01 +/- 0.03 0.00 NA C Pass MAAP-907 2/1/2017 Zn-65 1.62 +/- 0.13 1.29 0.90 -1.68 Pass MAAP-907 2/1/2017 Pu-238 0.0530 +/- 0.0190 0.0598 0.0419 -0.0777 Pass MAAP-907 2/1/2017 Pu-239/240 0.0490 +/- 0.0160 0.0460 0.0322 -0.0598 Pass MAAP-907 2/1/2017 Sr-90 0.648 +/- 0.120 0.651 0.456 -0.846 Pass MAAP-907 2/1/2017 U-234/233 0.086 +/- 0.024 0.104 0.073 -0.135 Pass MAAP-907 2/1/2017 U-238 0.097 +/- 0.024 0.107 0.075 -0.139 Pass MAS0-4515 8/1/2017 Am-241 45.9 +/- 7.0 58.8 41.2 -76.4 Pass g MAS0-4515 8/1/2017 Cs-134 409+/-7 448 314 -582 Pass g MAS0-4515 8/1/2017 Cs-137 798 +/- 12 722 505

939 Pass 9 MAS0-4515 8/1/2017 Co-57 1572+/-10 1458 1021 -1895 Pass g MAS0-4515 8/1/2017 Co-60 0.2 +/- 1.4 0.00 NA C Pass g MAS0-4515 8/1/2017 Mn-54 934 +/- 13 825 578 -1073 Pass g MAS0-4515 8/1/2017 K-40 704 +/- 53 592 414 -770 Pass g MAS0-4515 8/1/2017 Zn-65 667 +/- 17 559 391 -727 Pass g MAS0-4515 8/1/2017 Pu-238 101 +/- 9 92 64 -120 Pass g MAS0-4515 8/1/2017 Pu-239/240 74.8+/-7.7 68.8 48.2 -89.4 Pass g MAS0-4515 8/1/2017 Sr-90 252 +/- 7 289 202 -376 Pass g MAW-4494 8/1/2017 1-129 2.31 +/- 0.10 2.31 1.62 -3.00 Pass MAVE-4517 8/1/2017 Cs-134 2.40 +/- 0.10 2.32 1.62 -3.02 Pass MAVE-4517 8/1/2017 Cs-137 -0.002 +/- 0.048 0.000 NA C Pass MAVE-4517 8/1/2017 Co-57 3.3 +/- 0.1 2.8 2.0 -3.6 Pass MAVE-4517 8/1/2017 Co-60 2.10 +/- 0.10 2.07 1.45 -2.69 Pass MAVE-4517 8/1/2017 Mn-54 3.00 +/- 0.20 2.62 1.83 -3.41 Pass MAVE-4517 8/1/2017 Zn-65 5.90 +/- 0.30 5.37 3.76 -6.98 Pass a Results are reported in units of Bqlkg (soil), Bq/L (water) or Bqltotal sample (filters , vegetation) b Laboratory codes as follows: MAW (water). MAAP (air filter), MASO (soil), MAVE (vegetation) c MAPEP results are presented as the known values and expected laboratory precision (1 sigma , 1 detennination) and control limits as defined by the MAPEP. A known value of zero" indicates an analysis was included i n the testing serii as a false positive".

MAPEP does not provide control limits. ' Sample was reanalyzed in duplicate with acceptable results. Original plating was inferior to platings obtained during reanalysis. It is believed that isotopic tracer was not accurately quantified due to poor resolution of its peak. g Data were e"oneously submitted in units of Bqlg. All results pass MAPEP criteria when evaluated in units of Bq!Kg. (Page 2 of 3) E-10 TABLE E.5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Environmental, Inc., Midwest Laboratory Concentration Lab Codeb Reference Analysis Laboratory Known Control Limits c Acceptance Date Result Activity MAW-4513 8/1/2017 Am-241 0.820 +/- 0.220 0.89 0.624 -1.160 MAW-4513 81112017 Cs-134 10.3 :t 0.3 11.50 8.1-15.0 MAW-4513 8/1/2017 Cs-137 17.2 +/- 0.5 16.30 11.4-21.2 MAW-4513 8/1/2017 Co-57 12.7 +/- 0.4 12.1000 8.5-15.7 MAW-4513 8/1/2017 Co-60 10.6 +/- 0.3 10.70 7.5-13.9 MAW-4513 8/1/2017 Mn-54 15.6 +/- 0.4 14.900 10.4-19.4 MAW-4513 8/1/2017 Zn-65 15.9 +/- 0.7 15.50 10.9-20.2 MAW-4513 8/1/2017 H-3 255 +/- 9 258.00 181 -335 MAW-4513 8/1/2017 Fe-55 21.6 +/- 6.6 19.40 13.6 -25.2 MAW-4513 8/1/2017 Ni-63 -0.1 +/- 2.0 0.00 NA C MAW-4513 8/1/2017 Pu-238 0.590 +/- 0.080 0.6030 0.422 -0.784 MAW-4513 8/1/2017 Pu-239/240 0.740 +/- 0.090 0.7810 0.547 -1.015 MAW-4513 8/1/2017 Ra-226 1.000 +/- 0.100 0.858 0.601 -1.115 MAW-4513 8/1/2017 Sr-90 7.80 +/- 0.60 7.770 5.44-10.10 MAW-4513 8/1/2017 Tc-99 6.70 +/- 0.40 6.730 4.71 -8.75 MAW-4513 8/1/2017 U-2344/233 0.94 +/- 0.06 1.0 0.71 -1.31 MAW-4513 8/1/2017 U-238 0.97 +/- 0.07 1 0.73-1.35 MMP-4519h 8/1/2017 Am-241 0.0400 +/- 0.0100 0 0.0428

0.0796 MAAP-4519 8/1/2017 Cs-134 0.90 +/- 0.10 0.70-1.30 MAAP-4519 8/1/2017 Cs-137 0.90 +/- 0.10 0.82 0.57 -1.07 MAAP-4519 8/1/2017 Co-57 0.01 +/- 0.01 0 NA C MAAP-4519 8/1/2017 Co-60 0.70 +/- 0.10 0.48 -0.88 MAAP-4519 8/1/2017 Mn-54 1.50 +/- 0.10 0.91 -1.69 MAAP-4519 8/1/2017 Zn-65 1.30+/-0.10 0.76-1.40 MAAP-4519 8/1/2017 Pu-238 0.0300 +/- 0.0100 0.0 0.0209 -0.0387 MAAP-4519 8/1/2017 Pu-239/240 0.0400 +/- 0.0200 0 0.0328 -0.0608 MAAP-4519 8/1/2017 Sr-90 0.800 +/- 0.100 0.80 0.561 -1.041 MAAP-4519 8/1/2017 U-234/233 0.070 +/- 0.010 0.08 0.059 -0.109 MAAP-4519 8/1/2017 U-238 0.090 +/- 0.010 0.087 0.061-0.113

Results are reported in units of Bqlkg (soil), Bq/L (water) or Bqlfotal sample (filters , vegetation) b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation)

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fall Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass c MAPEP results are presented as the known values and expected laboratory precision (1 sigma , 1 determination) and con t rol limits as defined by the MAPEP. A known value of " zero* indicates an analysis was included in the testing seri1 as a false positive". MAPEP does not provide control limits. h Laboratory is not currently offering analysis for Am-241 in Air Particulate samples E-11 (Page 3 of 3)

TABLE E.6 lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERAt RAD Study Environmental, Inc., Midwest Laboratory Lab Code Date Analysis Laboratory ERA Result Control Limits Acceptance Result ERW-95 1/9/2017 Sr-89 51.9 +/- 4.6 55.5 44.3-63.2 Pass ERW-95 1/9/2017 Sr-90 43.6+/- 2.4 43.1 31.8-49.5 Pass ERW-97 1/9/2017 Ba-133 78.2 +/- 4.1 85.6 72.0 -94.2 Pass ERW-97 1/9/2017 Cs-134 53.9 +/- 3.8 52.6 42.4 -57.9 Pass ERW-97 1/9/2017 Cs-137 122 +/- 6 112 101 -126 Pass ERW-97 1/9/2017 Co-60 117 +/- 4 113.0 102 -126 Pass ERW-97 1/9/2017 Zn-65 208 +/- 13 189.0 170 -222 Pass ERW-99 1/9/2017 Gr. Alpha 48.9 +/- 2.4 52.3 27.3 -65.5 Pass ERW-99 1/9/2017 Gr. Beta 37.1 +/- 1.3 41.6 27.7 -49.0 Pass ERW-101 1/9/2017 1-131 22.3 +/- 0.6 24.3 20.2 -28.8 Pass ERW-103 1/9/2017 Ra-226 11.3 +/- 0.4 12.7 9.5 -14.7 Pass ERW-103 1/9/2017 Ra-228 6.10 +/- 0.90 6.2 3.8-8.1 Pass ERW-103 1/9/2017 Uranium 11.8 +/- 0.8 12.6 9.9 -14.4 Pass ERW-106 1/9/2017 H-3 12,600 +/- 300 12500 10 , 900 -13 , 800 Pass ERW-3344 7/10/2017 Sr-89 29.0 +/- 10.0 26.4 18.4 -32.9 Pass ERW-3344 7/10/2017 Sr-90 33.8 +/- 3.3 36 26.4-41.5 Pass ERW-3346 7/10/2017 Ba-133 66.4 +/- 4.1 66.3 55.2 -72.9 Pass ERW-3346 7/10/2017 Cs-134 27.0 +/- 4.3 24.4 18.7-27.2 Pass ERW-33 46 7/10/2017 Cs-137 57.4 :t 4.5 51.6 46.4-59.6 Pass ERW-3346 7/10/2017 Co-60 92.6 +/- 4.4 88.6 79.7 -99.8 Pass ERW-3346 7/10/2017 Zn-65 32.4 +/- 6.0 32.7 27.3-41.6 Pass ERW-3348 7/10/2017 Gr. Alpha 23.7+/-1.9 25.7 13.0 -34.1 Pass ERW-3348 7/10/2017 Gr. Beta 54.6 +/- 1.6 63 43.5 -69.6 Pass ERW-3350 7/10/2017 1-131 25.4 :t 1.3 25.5 21.2-30.1 Pass ERW-3352 7/10/2017 Ra-226 1.38 +/- 0.15 1.3 1.07 -1.95 Pass ERW-3352 7/10/2017 Ra-228 6.70 :t 0.93 5.7 3.45 -7.47 Pass ERW-3352 7/10/2017 Uranium 58.4 +/- 0.9 66.7 54.3 -73.9 Pass ERW-3354 7/10/2017 H-3 5 , 254 :t 224 5060 4 , 340 -5 , 570 Pass

Results obtained by Environmental, Inc., Midwest Laboratory as a partic i pant in the crosscheck program for profic iency testing in drink i ng water conducted by Environmental Resources Associates (ERA). (Page 1 of 1) E-12 APPENDIX F ERRATA DATA There is no errata data for 2017 APPENDIX G ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)