ML19120A082

2018 Annual Radiological Environmental Operating Report

ML19120A082
Person / Time
Site:	Limerick
Issue date:	04/30/2019
From:	Libra R Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LG-19-039
Download: ML19120A082 (133)

Text

Exelon Generation TS 6.9.1.7 LG-19-039 April 30, 2019 U. S. Nuclear Regulatory Commission Attn : Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353

Subject:

2018 Annual Radiological Environmental Operating Report In accordance with the requirements of Section 6.9.1.7 of Limerick Generating Station (LGS)

Unit 1 and Unit 2 Technical Specifications (TS), and Section 6.1 of the LGS Units 1 and 2 Offsite Dose Calculation Manual (ODCM), this letter submits the 2018 Annual Radiological Environmental Operating Report. This report provides the 2018 results for the Radiological Environmental Monitoring Program (REMP) as called for in the ODCM.

In assessing the data collected for the REMP, it has been concluded that the operation of LGS, Units 1 and 2 had no adverse impact on the environment. No plant-produced fission or activation products, with the exception of CS-137, were found in any pathway modeled by the REMP. The detected CS-137 was concluded to not be from LGS. The results of the groundwater protection program are also included in this report. Positive tritium was found in 4 of 13 groundwater monitoring locations that ranged from non-detectable to 1,480 pCi/L; which is below the EPA limit of 20,000 pCi/L.

There are no commitments contained in this letter.

If you have any questions or require additional information, please contact Orlando Credendino at 610-718-2701.

Respectfully,

~~

Richard W. Libra Vice President-Limerick Generating Station Exelon Generation Company, LLC

Attachment:

2018 Annual Radiological Environmental Operating Report

LG-19-039 Page 2 cc: D. Lew, Administrator, Region I, USNRC (w/attachment)

S. Rutenkroger, LGS USNRC Senior Resident Inspector (w/attachment)

H. Anagnostopoulos, Inspector Region I, USNRC (w/attachment)

V. Sreenivas, Senior Project Manager-NRA, USNRC (w/attachment)

Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 AND 2 Annual Radiological Environmental Operating Report 1 January through 31 December 2018 Prepared By Teledyne Brown Engineering Environmental Services Limerick Power Station Pottstown, PA 19464 April 2019

Intentionally left blank Table of Contents I. Preface.1 II. Summary and Conclusions ............................................................................................. 8 III. Introduction................................................................................................................... 10 A. Objectives of the REMP..................................................................................... 10 B. Implementation of the Objectives ...................................................................... 10 IV. Program Description .................................................................................................... 11 A. Sample Collection .............................................................................................. 11 B. Sample Analysis ................................................................................................ 13 C. Data Interpretation ............................................................................................. 13 D. Program Exceptions .......................................................................................... 15 E. Program Changes ............................................................................................. 15 F. Compliance to 10CFR190 Limits ....................................................................... 16 V. Results and Discussion ................................................................................................ 17 A. Aquatic Environment ......................................................................................... 17

1. Surface Water ......................................................................................... 17

2. Drinking Water ........................................................................................ 17

3. Fish ......................................................................................................... 18

4. Sediment ................................................................................................. 18 B. Atmospheric Environment ................................................................................. 19

1. Airborne .................................................................................................. 19

a. Air Particulates ............................................................................. 19

b. Airborne Iodine............................................................................. 20

2. Terrestrial ................................................................................................ 20

a. Milk............................................................................................... 20

b. Broad Leaf Vegetation ................................................................. 20 C. Ambient Gamma Radiation ............................................................................... 21 D. 10 CFR 20.2002 Permit Storage Area .............................................................. 21 E. Independent Spent Fuel Storage Area .............................................................. 21 F. Land Use Survey ............................................................................................... 21 H. Summary of Results - Inter-Laboratory Comparison Program ......................... 22 VI. References .................................................................................................................. 25 i

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2018 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Tables Table B-1 Location Designation and Identification System for the Limerick Generating Station Table B-2 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2018 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2018 Figures Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2018 Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2018 Figure B-3 Environmental Sampling Locations Greater Than 26,400 Feet from the Limerick Generating Station, 2018 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-I.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-I.2 Concentrations of I-131 in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-I.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-II.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-II.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-II.3 Concentrations of I-131 in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-II.4 Concentrations of Gamma Emitters in Drinking Water Samples ii

Collected in the Vicinity of Limerick Generating Station, 2018 Table C-III.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-VI.1 Concentrations of I-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-VII.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-VIII.1 Concentrations of Gamma Emitters in Broad Leafy Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table C-IX.1 Quarterly DLR Results for Limerick Generating Station, 2018 Table C-IX.2 Mean Quarterly Dosimeter Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2018 Table C-IX.3 Summary of the Ambient Dosimetry Program for Limerick Generating Station, 2018 Figures Figure C-1 Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2018 Figure C-2 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2018 Figure C-3 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2018 Figure C-4 Mean Quarterly Ambient Gamma Radiation Levels (DLR) in the Vicinity of LGS, 1985 - 2018 Appendix D Data Tables and Figures - Comparison Laboratory Tables Table D-I.1 Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2018 iii

Table D-I.2 Concentrations of I-131 in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2018 Table D-I.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2018 Table D-I.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table D-II.1 Concentrations of Gross Beta in Air Particulate and I-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table D-II.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2018 Table D-III.1 Concentrations of I-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2018 Figures Figure D-1 Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2018 Figure D-2 Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2018 Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2018 Table E-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2018 Table E-03 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2018 Table E-4 Analytics Environmental Radioactivity Cross Check Program Exelon Industrial Services, 2018 Table E-5 ERA Environmental Radioactivity Cross Check Program Exelon Industrial Services, 2018 Table E-6 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

GEL Laboratories, 2018 Table E-7 ERA Environmental Radioactivity Cross Check Program GEL Laboratories, 2018 Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

Intentionally Left Blank I. Preface The following sections of the preface are meant to help define key concepts, provide clarity, and give context to the readers of this report.

Annual Reports The Nuclear Regulatory Commission (NRC) is the federal agency who has the role to protect public health and safety related to nuclear energy. Nuclear Power Plants have made many commitments to the NRC to ensure the safety of the public. As part of these commitments, they provide two reports annually to specifically address how the stations operation impacts the environment of the local communities. The NRC then reviews these reports and makes them available to the public. The names of the reports are the Annual Radioactive Effluent Release Report (ARERR) and the Annual Radiological Environmental Operating Report (AREOR).

The ARERR reports the results of the sampling from the effluent release paths at the station and analyzed for radioactivity. An effluent is a liquid or gaseous waste containing plant-related radioactive material emitted at the boundary of the facility.

The AREOR reports the results of the samples obtained in the environment surrounding the station and analyzed for radioactivity. Environmental samples include air, water, vegetation, and other sample types that are identified as potential pathways radioactivity can reach humans.

Graphic 1. Examples of Gaseous and Liquid Effluent Pathways Graphic 1 demonstrates some potential exposure pathways from Limerick Generating Station. The ARERR and AREOR together ensure Nuclear Power 1

Plants are operating in a manner that is within established regulatory commitments meant to adequately protect the public.

Understanding Radiation Generally radiation is defined as emitted energy in the form of waves or particles.

If radiation has enough energy to displace electrons from an atom it is termed ionizing, otherwise it is non-ionizing. Non-Ionizing radiation includes light, heat given off from a stove, radiowaves and microwaves. Ionizing radiation occurs in atoms, particles too small for the eye to see. So, what are atoms and how does radiation come from them?

Graphic 2. Types of Radiation, from NASA Hubblesite An atom is the smallest part of an element that maintains the characteristics of that element. Atoms are made up of three parts: protons, neutrons, and electrons.

Graphic 3. Structure of an Atom The number of protons in an atom determines the element. For example, a hydrogen atom will always have one proton while an oxygen atom will always have eight protons. The protons are clustered with the neutrons forming the nucleus at the center of the atom. Orbiting around the nucleus are the relatively small electrons.

Isotopes are atoms that have the same number of protons but different numbers 2

of neutrons. Different isotopes of an element will all have the same chemical properties and many isotopes are radioactive while other isotopes are not radioactive. A radioactive isotope can emit radiation because it contains excess energy in its nucleus. Radioactive atoms and isotopes are also referred to as radionuclides and radioisotopes.

There are two basic ways that radionuclides are produced at a nuclear power plant. The first is fission, which creates radionucides that are called fission products. Fission occurs when a very large atom, such as uranium-235 (U-235) or plutonium-239 (Pu-239), absorbs a neutron into its nucleus making the atom unstable. The unstable atom can then split into smaller atoms. When fission occurs there is a large amount of energy released in the form of heat. A nuclear power plant uses the heat generated to boil water that spins turbines to produce electricity.

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. Pure water that passes over the fissioning atoms is used to cool the reactor and also produce steam to turn the turbines. Although this water is considered to be very pure, there are always some contaminiants within the water from material used in the plants construction and operation.

These contaminants are exposed to the fission process and may become activation products. The atoms in the water itself can also 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 their excess energy. This release of excess energy is called radioactive decay. 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 measured in years while others may be very short and measured in seconds.

Graphic 4. Radioactive Decay Half-Life In the annual reports you will see both man made and naturally ocurring 3

radionuclides listed, for example potassium-40 (K-40, natural) and cobalt-60 (Co-60, man-made). We are mostly concerned about man-made radionuclides because they can be produced as by-products when generating electricity at a nuclear power plant. It is important to note that there are also other ways man-made radionuclides are produced, such as detonating nuclear weapons.

Weapons testing has deposited some of the same man-made radionuclides into the environment as those generated by nuclear power, and some are still present today because of long half-lives.

Measuring Radiation There are four different but interrelated units for measuring radioactivity, exposure, absorbed dose, and dose equivalent. Together, they are used to scientifically report the amount of radiation and its effects on humans.

x 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 SUHIL[VXFKDVWKHPLFUR&XULH &L ZKLFKPHDQVRID&XULH

x 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 VLWHDUHPHDVXUHGPLOOL5RHQWJHQ P5 1,000 of one R.

x 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 (mrDG RIRQHUDG

x 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 AREOR and ARERR are the Roentgen equivalent man (rem).

Regulations require doses to the whole body, specific organ, and direct UDGLDWLRQWREHUHSRUWHGLQPLOOLUHP PUHP RIRQHUHP

4

Sources of Radiation People are exposed to radiation every day of their lives and have been since the dawn of mankind. Some of this radiation is naturally occurring while some is man-made. There are many factors that will determine the amount of radiation individuals will be exposed to such as where they live, medical treatments, etc.

The average person in the United States is exposed to approximately 620 mrem each year. 310 mrem comes from natural sources and 310 from man-made sources. The Graphic 5 shows what the typical sources of radiation are for an individual over a calendar year:

Graphic 5. Sources of Radiation Exposure in the U.S., from NCRP Report No. 160 The radiation from a nuclear power plant is included in the chart as part of the Industrial and Occupational fraction, <0.1%. The largest natural source of radiation is from radon, because radon gas travels in the air we breathe.

Perhaps you know someone who had a CT scan at a hospital to check his or her bones, brain, or heart. CT scans are included in the chart as Medical Procedures, which make up the next largest fraction. Graphic 6 on the following page shows some of the common doses humans receive from radiation every year.

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Graphic 6 .Relative Doses from Radiation Sources, from EPA Radiation Doses and Sources 6

Radiation Risk Current science suggests there is some risk from any exposure to radiation.

However, it is very hard to tell whether cancers or deaths can be attributed to very low doses of radiation or by something else. U.S. radiation protection standards are based on the premise that any radiation exposure carries some 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.

Graphic 7. Days of Lost Life Expectancy, Adapted from the Journal of American Physicians and Surgeons Volume 8 Number 2 Summer 2003 7

II. Summary and Conclusions In 2018, the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 90 curies of noble gas, fission and activation products and approximately 27 curies of tritium.

The dose from both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits were as follows:

Gaseous and Liquid Radiation Doses to Members of the Public at the Highest Dose Receptor

% of Applicable Estimated Age Maximum Individual Noble Gas Applicable Limit Unit Dose Dose Group Limit Nearest Residence Gamma Air Dose 3.45E-03 All 1.73E-02 20 mRad Nearest Residence Beta Air Dose 2.13E-03 All 5.33E-03 40 mRad Nearest Residence Total Body 3.25E-03 All 3.25E-02 10 mrem Nearest Residence Skin 5.35E-03 All 1.78E-02 30 mrem Iodine, Particulate, C-14 & Tritium Vegetation Pathway Bone 1.28E+00 Child 4.26E+00 30 mrem Liquid LGS Outfall Total Body 4.90E-04 Teen 8.16E-03 6 mrem LGS Outfall Liver 6.59E-04 Adult 3.29E-03 20 mrem The calculated doses, from the radiological effluents released from Limerick, were a very small percentage of the allowable limits.

This report on the Radiological Environmental Monitoring Program conducted for the Limerick Generating Station (LGS) by Exelon covers the period 1 January 2018 through 31 December 2018. During that time period, 1,505 analyses were performed on 1,257 samples.

Surface and drinking water samples were analyzed for concentrations of tritium, low level Iodine-131 (I-131) and gamma-emitting nuclides. Drinking water samples were also analyzed for concentrations of total gross beta. Iodine-131 was not detected in primary laboratory samples nor in the secondary laboratory for drinking water. Gross beta activities detected were consistent with those detected in previous years. No other fission or activation products were detected.

Fish (predator and bottom feeder) samples were analyzed for concentrations of gamma-emitting nuclides. Concentrations of naturally-occurring Potassium-40 (K-40) were consistent with those detected in previous years. No fission or activation products were detected in fish.

Sediment samples were analyzed for concentrations of gamma-emitting nuclides.

Samples collected upstream of the discharge had Cesium-137 (Cs-137) concentrations that were consistent with those detected in previous years. No other station-produced fission or activation products were found in sediment. For 8

results, discussion and dose to member of the public calculation see Section IV.A.4.

Air particulate samples were analyzed for concentrations of gross beta and gamma-emitting nuclides. Gross beta and cosmogenic, naturally-occurring Beryllium-7 (Be-7) were detected at levels consistent with those detected in previous years. No fission or activation products were detected.

High-sensitivity I-131 analyses were performed on weekly air samples. All results were less than the minimum detectable concentration.

Cow milk samples were analyzed for concentrations of I-131 and gamma-emitting nuclides. Concentrations of naturally-occurring Potassium-40 (K-40) were consistent with those detected in previous years. No fission or activation products were found.

Broad leaf vegetation samples were analyzed for gamma-emitting nuclides.

Concentrations of naturally-occurring Be-7 and K-40 were detected. Radium-226 (Ra-226) was found in 11 of 39 samples. Thorium-228 (Th-228) was found in 5 of 39 samples. Naturally-occurring Ra-226 and Th-228 were detected in low concentrations, which are consistent with historical values.

Review of the gamma spectroscopy results from the surface water samples located at the Limerick intake (24S1) and downstream of the 10 CFR 20.2002 permitted storage area showed no evidence of offsite radionuclide transport from the 2002 permitted storage area.

Environmental ambient gamma radiation measurements were performed quarterly using Dosimeters of Legal Record (DLR). Levels detected were consistent with those observed in previous years.

A review of the dosimetry data for the nearest residence to the Independent Spent Fuel Storage Installation (ISFSI) indicates no direct dose was received.

A Radiological Groundwater Protection Program (RGPP) was established in 2006 as part of an Exelon Nuclear fleetwide assessment of potential groundwater intrusion from the operation of the Station. In 2018, well water samples were analyzed for tritium (H-3), strontium-89 (Sr-89), strontium-90 (Sr-90), gross alpha, gross beta, and gamma emitters. Surface water samples were analyzed for tritium, Sr-89, Sr-90 and gamma emitters. Precipitation water samples were analyzed for tritium. Most of the tritium values for well water, surface water and SUHFLSLWDWLRQZDWHUZHUHOHVVWKDQWKHORZHUOLPLWRIGHWHFWLRQRIS&L/

Results and Discussion of groundwater samples are covered in Appendix G.

In assessing the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of LGS had no adverse radiological impact on the environment.

9

III. Introduction The Limerick Generating Station (LGS), consisting of two 3,515 MW boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank, elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL to the western site boundary.

A Radiological Environmental Monitoring Program (REMP) for LGS was initiated in 1971. Review of the 1971 through 1977 REMP data resulted in the modification of the program to comply with changes in the Environmental Report Operating License Stage (EROL) and the Branch Technical Position Paper (Rev.

1, 1979). The preoperational period for most media covers the periods 1 January 1982 through 21 December 1984 and was summarized in a separate report.

This report covers those analyses performed by Teledyne Brown Engineering (TBE), Mirion Technologies, and Environmental Inc., Midwest Laboratory (EIML) on samples collected during the period 1 January 2018 through 31 December 2018.

On 6 July 1996 a 10 CFR 20.2002 permit was issued to Limerick for storage of slightly contaminated soils, sediments and sludges obtained from the holding pond, cooling tower and spray pond systems. These materials will decay to background while in storage. Final disposition will be determined at Station decommissioning.

On 21 July 2008 an ISFSI pad was put into service. The ISFSI is dry cask storage, where spent nuclear fuel is stored.

A. Objective of the REMP The objectives of the REMP are to:

1. Provide data on measurable levels of radiation and radioactive materials in the site environs

2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure B. Implementation of the Objectives The implementation of the objectives is accomplished by:

10

1. Identifying significant exposure pathways

2. Establishing baseline radiological data of 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 IV. Program Description A. Sample Collection Samples for the LGS REMP were collected for Exelon Nuclear by Exelon Industrial Services (EIS) and Normandeau Associates, Inc. (NAI). This section describes the general collection methods used to obtain environmental samples for the LGS REMP in 2018. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by EIS are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, fish, and sediment.

Two-gallon water samples were collected monthly from composite samplers located at two surface water locations (13B1 and 24S1) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising of the flesh of two groups, bottom feeder (ZKLWHVXFNHUFRPPRQFDUSFKDQQHOFDWILVKQRUWKHUQKRJVXFNHU and SUHGDWRU VPDOOPRXWKEDVVURFNEDVVFKDQQHOFDWILVKIODWKHDG

FDWILVKEOXHJLOO ZHUH collected semiannually at two locations, 16C5 and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at three locations semiannually, 16B2, 16C4, and 33A2 (control).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk. Airborne iodine and particulate samples were collected and analyzed weekly at seven locations (6C1, 10S3, 11S1, 13S4, 14S1, 15D1, and 22G1). The control location was 22G1. Airborne iodine and particulate samples were obtained at each 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.

11

Terrestrial Environment Milk samples were collected biweekly at four locations (18E1, 19B1, 23F1, and 25C1) from April through November, and monthly from December through March. One additional location (36E1) was sampled quarterly.

Locations 36E1 and 23F1 were controls. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Broad leaf vegetation was collected monthly, during the growing season, at three locations (11S3, 13S3, and 31G1). The control location was 31G1. Eleven different kinds of vegetation samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Ambient Gamma Radiation Direct Radiation measurements were made using thermoluminescent dosimeters. The DLR locations were placed on and around the LGS site as follows:

A site boundary ring consisting of 16 locations (36S2, 3S1, 5S1, 7S1, 10S3, 11S1, 13S2, 14S1, 18S2, 21S2, 23S2, 25S2, 26S3, 29S1, 31S1, and 34S2) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from LGS releases.

An intermediate distance ring consisting of 16 locations (36D1, 2E1, 4E1, 7E1, 10E1, 10F3, 13E1, 16F1, 19D1, 20F1, 24D1, 25D1, 28D2, 29E1, 31D2, and 34E1) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

The balance of eight locations (5H1, 6C1, 9C1, 13C1, 15D1, 17B1, 20D1, and 31D1) representing control and special interests areas such as population centers, schools, etc.

The specific dosimetry locations were determined by the following criteria:

1. The presence of relatively dense population;

2. Site meteorological data taking into account distance and elevation for each of the sixteen-GHJUHHVHFWRUVDURXQGWKHVLWH

where estimated annual dose from LGS, if any, would be most significant;

3. On hills free from local obstructions and within sight of the vents (where practical);

4. And near the closest dwelling to the vents in the prevailing downwind direction.

Two dosimeters were placed at each location in a PVC conduit located approximately three feet above ground level. The dosimeters were exchanged quarterly and sent to Mirion Technologies for analysis.

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10 CFR 20.2002 Permit Storage Area In 1996, the Limerick Generating Station received NRC approval to store slightly contaminated soils, sludges and sediments on site per the requirements of 10 CFR 20.2002. These materials will be stored until end of the site's renewed operating license. At that time the material will be evaluated along with the site for decommissioning. The area is approximately 1.5 acres in size and was evaluated to hold a maximum of 1.12E+06 cubic feet with no more than 7E+04 cubic feet added to the area in any single year. After each material placement on the storage area, the area is graded and seeded to prevent erosion. Since all groundwater movement is to the river, the use of the REMP surface water sampling program is used as a check on potential groundwater movement from the pad. In 2018, no material was placed on the permitted storage area.

Independent Spent Fuel Storage Installation (ISFSI)

The results from the dosimeter locations 36S2 and 3S1 were used to determine the direct radiation exposure to the nearest residence from the ISFSI pad.

B. Sample Analysis This section lists the analyses performed by the primary laboratory (TBE)

DQGWKHVHFRQGDU\ODERUDWRU\ (,6*(//DERUDWRULHV RQHQYLURQPHQWDO

samples for the LGS REMP in 2018. The analytical procedures used by the laboratories are listed in Appendix B Table B-3. Analysis results from TBE are provided in Appendix C. Analysis results from Exelon Industrial 6HUYLFHV*HO/DERUDWRULHVDUHSURYLGHGLQ$SSHQGL['RIWKLVUHSRUW

In order to achieve the stated objectives, the current program includes the following analyses:

1. Concentrations of beta emitters in drinking water and air particulates

2. Concentrations of gamma emitters in surface and drinking water, air particulates, milk, fish, broad leaf vegetation, and sediment

3. Concentrations of tritium in surface and drinking water

4. Concentrations of I-131 in air, milk, and drinking water

5. Ambient gamma radiation levels at various site environs C. Data Interpretation The radiological and direct radiation data collected prior to LGS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this report, LGS was considered operational at initial criticality. In addition, data were compared to 13

previous years' operational data for consistency and trending. 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 criteria for the presence of activity. All analyses are designed to achieve the required LGS detection limits for environmental sample analysis.

The minimum detectable concentration (MDC) is defined as above with the exception that the measurement is an after the fact estimate of the presence of activity.

2. 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 affecting 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 and drinking water, twelve nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, I-131, Cs-134, Cs-137, Ba-140, and La-140 were reported For broad leaf vegetation, eleven nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, I-131, Cs-134, Cs-137, Ra-226, Th-228, and Th-232 were reported For fish, nine nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, I-131, Cs-134, and Cs-137 were reported For sediment, eight nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, I-131, Cs-134, and Cs-137 were reported For air particulates, six nuclides, Be-7, Mn-54, Co-58, Co-60, Cs-134, and Cs-137 were reported For milk, five nuclides, K-40, Cs-134, Cs-137, Ba-140, and 14

La-140 were reported Means and standard deviations of positive results were calculated.

The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.

D. Program Exceptions For 2018 the LGS REMP had a sample recovery rate of greater than 99%.

Exceptions are listed below:

1. 0LONVDPSOHVIRUORFDWLRQ(IRUDQG

ZHUHQRWDYDLODEOHGXH to a fire at the farm (IR 4070461).

2. Air sample from location 6C1 for the week of 0418 - 0418 was not available due to the pump not running.

3. Air sample from location 6C1 for the week of 1118 - 1118 was not available due to the pump not running.

Each program exception was reviewed to understand the causes of the program exception. Occasional equipment breakdowns were unavoidable. 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 revisions to the Offsite Dose Calculation Manual (ODCM) in 2018.

Revision 30 was implemented in May 2018 and there were no changes to the REMP program with this revision.

Revision 31 was also implemented in May 2018. Prior to this revision there were REMP sample stations that were above the required number of sample locations and the additional sample stations were not listed in the ODCM. All of these additional sample locations were added to the ODCM with revision 31. This change did not impact the AREOR since all of the sample location results have always been included in the report.

There are complete copies of both ODCM revisions included with the 2018 ARERR submittal.

15

F. Compliance to 40 CFR 190 Limits

1. Dose to Members of the Public at or Beyond Site Boundary Per the ODCM Control 6.2, the Annual Radioactive Effluent Release Report shall include an assessment of the radiation doses to the hypothetically highest exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources. The ODCM does not require population doses to be calculated. For purposes of this calculation the following assumptions were made:

x /RQJWHUPDQQXDODYHUDJHPHWHRURORJ\;4DQG'4DQG actual gaseous effluent releases were used.

x Gamma air dose, Beta air dose, Total Body and Skin doses were attributed to noble gas releases.

x Critical organ and age group dose attributed to iodine, particulate, Carbon-14 and tritium releases.

x 100 percent occupancy factor was assumed.

x Dosimetry measurements (minus background levels) obtained from the Radiological Environmental Monitoring Program for the nearest residence to the Independent Spent Fuel Storage Installation (ISFSI) was used to determine direct radiation exposure.

x The highest doses from the critical organ and critical age group for each release pathway was summed and added to the net dosimetry measurement from nearest residence to the ISFSI for 40 CFR 190 compliance.

40 CFR 190 Compliance:

The maximum calculated dose to a real individual would not exceed 2.90E-01 mRem (total body), 1.29E+00 mRem (organ), or 2.90E-01 mRem (thyroid).

All doses calculated were below all ODCM and 40 CFR Part 190 limits to a real individual.

Table 1: 40 CFR 190 Compliance 40 CFR 190 Compliance Gaseous Effluents

% of Particulate, Liquid Net Direct Noble Total Applicable Limit Unit Iodine, C-14 Effluents Radiation Gas Limit

& Tritium Total Body Dose 3.25E-02 2.57E-01 4.90E-04 0.00E+00 2.90E-01 1.16E+00 25 mRem Organ Dose 5.35E-03 1.28E+00 6.59E-04 0.00E+00 1.29E+00 5.14E+00 25 mRem Thyroid Dose 3.25E-02 2.57E-01 2.92E-04 0.00E+00 2.90E-01 3.86E-01 75 mRem 16

V. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken from a continuous sampler at two locations (13B1 and 24S1) on a monthly schedule. Of these locations only 13B1 located downstream, could be affected by Limericks effluent releases. The following analyses were performed:

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Appendix C, Table C-I.1). All results were below the required LLD.

Iodine-131 Monthly samples were taken from location 24S1 and analyzed for low level I-131 activity (Appendix C, Table C-I.2). All results were below the required LLD.

Gamma Spectrometry Samples from all locations were analyzed for gamma-emitting nuclides (Appendix C, Table C-I.3). All nuclides were below the required LLDs.

2. Drinking Water Monthly samples were collected from continuous water samplers at four locations (15F4, 15F7, 16C2, and 28F3). Three locations (15F4, 15F7, and 16C2) could be affected by Limericks effluent releases. The following analyses were performed:

Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Appendix C, Tables C-II.1). The values ranged from

WRS&L/&RQFHQWUDWLRQVGHWHFWHGZHUHFRQVLVWHQWZLWK

those detected in previous years (Appendix C, Figure C-1).

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity. All results were below required LLD (Appendix C, Table C-II.2).

17

Iodine-131 Monthly samples were taken from all locations and analyzed for I-131 activity (Appendix C, Table C-II.3). All results were below the required LLD.

Gamma Spectrometry Samples from all locations were analyzed for gamma-emitting nuclides (Appendix C, Table C-II.4). All results were below the required LLDs.

3. Fish Fish samples comprised of bottom feeder (ZKLWHVXFNHUFDUS

catfish) and SUHGDWRU VXQILVKEDVVURFNEDVVFDWILVK  were collected at two locations (16C5 and 29C1) in the spring and fall season. Location 16C5 could be affected by Limericks effluent releases. The following analysis was performed:

Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma-emitting nuclides (Appendix C, Table C-III.1).

Naturally-occurring K-40 was found at all stations and ranged from

WRS&LNJZHWDQGZDVFRQVLVWHQWZLWKOHYHOVGHWHFWHG

in previous years. No other activity was detected and the required LLD was met.

4. Sediment Aquatic sediment samples were collected at three locations (16B2, 16C4 and 33A2) semiannually. Two of these locations (16B2 and 16C4) could be affected by Limericks effluent releases. The following analysis was performed:

Gamma Spectrometry Sediment samples from all three locations were analyzed for gamma-emitting nuclides (Appendix C, Table C-IV.1). Nuclides detected were naturally-occurring Be-7 and K-40, as well as the fission product Cs-137.

Be-7 was found at all locations and ranged from 2,209 to 4,979 S&LNJGU\.-40 was found at all locations and ranged from 12,540 WRS&LNJGU\7KHILVVLRQSURGXFW&V-137 was found at two ORFDWLRQVDQGUDQJHGIURPWRS&LNJGU\

18

The Cs-137 activity detected was consistent with those detected in the pre-operational years. The activity at the control location, 33A2, was just above the detection limit. The downstream location, 16C4, showed no activity. Therefore, at 16B2, the Cs-137 activity found is not attributed to LGS radioactive effluent releases.

However, the dose to a teenager's skin and whole body was conservatively calculated at 3.49E-04 mRem and 2.99E-04 mRem, respectively. This dose represents 1.75E-03% and 4.99E-03%, of the Appendix I to 10 CFR Part 50 dose limits, respectively. No other Limerick fission or activation products were found.

B. Atmospheric Environment

1. Airborne

a. Air Particulates Continuous air particulate samples were collected from seven locations on a weekly basis. The seven locations were separated into three groups: Group I represents locations within the LGS site boundary (10S3, 11S1, 13S4, and 14S1), Group II represents the locations at an intermediate distance from the LGS site (6C1 and 15D1),

and Group III represents the control location at a remote distance from LGS (22G1). The following analyses were performed:

Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Appendix C, Table C-V.1 and C-V.2).Detectable gross beta activity was observed at all locations. The results from the on-site locations (Group I) ranged from 5E-03 to 37E-03 S&LP3 with a mean of 16E-03 S&LP3. The results from the intermediate distance location (Group II) ranged from 6E-03 to 30E-03 S&LP3 with a mean of 14E-03 S&Lm3.

The results from the remote distance locations (Group III) ranged from 5E-03 to 26E-03 S&LP3 with a mean of 15E-03 S&LP3. Comparison of the 2018 air particulate data with previous years data indicates no effects from the operation of LGS (Appendix C, Figure C-2). In addition, a comparison of the weekly mean values for 2018 indicates no notable differences among the three groups.

(Appendix C, Figure C-3).

Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma-emitting nuclides (Appendix C, Table C-V.3).

19

Naturally-occurring Be-7 was detected in all 28 samples and is contributed to cosmic ray activity. These values ranged from 35E-03 to 151E-03 S&LP3. All other nuclides were below the required LLDs.

b. Airborne Iodine Continuous air samples were collected from seven locations (6C1, 10S3, 11S1, 13S4, 14S1, 15D1, and 22G1) and analyzed weekly for I-131 (Appendix C, Table C-VI.1). All results were below the required LLD.

2. Terrestrial

a. Milk Samples were collected from four locations (18E1, 19B1, 23F1, and 25C1) biweekly April through November and monthly December through March. Samples from one additional location (36E1) were taken quarterly. The following analyses were performed:

Iodine-131 Milk samples from all locations were analyzed for concentrations of I-131 (Appendix C, Table C-VII.1). All results were below the required LLD.

Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma-emitting nuclides (Appendix C, Table C-VII.2).

Naturally-occurring K-40 activity was found in all samples DQGUDQJHGIURPWRS&L/$OORWKHUQXFOLGHVZHUH

below the required LLDs.

b. Broad Leaf Vegetation Eleven types of broadleaf vegetation samples were collected from three locations (11S3, 13S3, and 31G1) monthly from June through October. The following analysis was performed:

Gamma Spectrometry Each broad leaf vegetation sample was analyzed for concentrations of gamma-emitting nuclides (Appendix C, Table C-VIII.1).

20

Cosmogenic, naturally-occurring Be-7 was found in 35 of 39 VDPSOHVDQGUDQJHGIURPWRS&LNJZHW1DWXUDOO\-

occurring K-40 was found in all samples and ranged from 2,980 to S&LNJZHW1DWXUDOO\-occurring Ra-226 was found in 11 of 39 samples and ranged from 743 to 5,105 S&LNJZHW1DWXUDOO\-occurring Th-228 was found in 5 of 39 VDPSOHVDQGUDQJHGIURPWRS&LNJZHW$OORWKHU

nuclides were below the required LLDs.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO4) thermoluminescent dosimeters. Forty dosimeter locations were established around the site. Results of dosimeter measurements are listed in Appendix C, Tables C-IX.1 and C-IX.2, Figure C-4. Dosimeter PHDVXUHPHQWVZHUHUHSRUWHGLQP5VWDQGDUGPRQWK$OOGRVLPHWHU

PHDVXUHPHQWVZHUHEHORZP5VWDQGDUGPRQWKZLWKDUDQJHRIWR

P5VWDQGDUGPRQWK$FRmparison of the Site Boundary and Intermediate Distance data to the Control Location (5H1) data indicate that the ambient gamma radiation levels from the Control Location were consistently higher than all other locations, except 13S2. Location 13S2 historically shows higher ambient gamma radiation, which is due to the rock substrate. The area that this dosimeter is located in has been determined to emanate radon prodigy.

D. 10 CFR 20.2002 Permit Storage Area The results of the surface water aquatic monitoring program from Location 24S1 were used to determine if radioactivity from the permit storage area had made it to the Schuylkill River. The data obtained from the gamma analysis program did not detect any migration of radioactivity from the permit storage area.

E. Independent Spent Fuel Storage Installation The results of the ambient gamma radiation level at dosimeter locations 36S2 and 3S1 were used to determine the direct radiation exposure to the nearest residence from the ISFSI pad. The data, after subtracting background, shows the net direct radiation exposure to the nearest residence was 0.0 mRem for the year.

F. Land Use Survey A Land Use Survey conducted in the fall of 2018 around Limerick Generating Station (LGS) was performed by Exelon Industrial Services to comply with Bases 3.3.2 of the Limericks Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident, 21

milk-producing animal and garden of greater than 500 ft2 in each of the sixteen 22 1/2 degree sectors out to five miles around the site. The distance and direction of all locations from the LGS reactor buildings were positioned using Global Positioning System (GPS) technology. The 2018 Land Use Survey identified differences in locations for gardens and meat animals between 2016 and 2018. 19 new gardens in sectors N, NE, S, SSW, SW, WSW, W, NW and NNW are newly identified. The new garden sectors NE and SW were identified as the closest garden for that sector.

Gardens planted in sectors ESE and SE that are maintained for the REMP program were not included in the survey because of location on LGS property. The nearest gardens in all other sectors were the same as in last years report. The location for meat animals in sectors ESE, SSE, WSW and W sectors are closer than in 2017 and there were no meat animals identified in the E, WNW and NW sectors. All other locations were the same as in the 2017 report. There were no changes required to the LGS REMP as a result of this survey. The results of this survey are summarized below:

Distance in feet from the LGS Reactor Buildings (Out to 26,400 feet)

Residence Garden Milk Farm Meat Animal Sector Feet Feet Feet Feet 1 N 3,109 3,333 24,775 24,775 2 NNE 2,706 12,399 - 13,418 3 NE 3,469 13,452 - 16,044 4 ENE 3,231 8,241 - 7,451 5 E 2,864 7,868 - -

6 ESE 3,434 3,434 - 12,264 7 SE 3,945 7,139 - 10,903 8 SSE 5,403 6,912 - 8,177 9 S 4,347 6,103 22,114 12,210 10 SSW 5,063 5,732 10,390 10,390 11 SW 3,251 6,319 - 23,145 12 WSW 3,799 4,507 14,177 4,635 13 W 3,627 8,886 - 14,123 14 WNW 3,685 12.022 - -

15 NW 3,619 8,200 - -

16 NNW 5,050 6,473 - 12,065 G. Summary of Results - Inter-laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation, and water matrices for various analytes (Appendix E). 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:

22

A. Analytics Evaluation Criteria Analytics evaluation report provides a ratio of TBEs result and Analytics known value. Since flag values are not assigned by Analytics, TBE evaluates the reported ratios based on internal QC requirements based on the DOE MAPEP criteria.

B. ERA Evaluation Criteria ERAs evaluation report provides an acceptance range for control and warning limits with associated flag values. ERAs acceptance limits are established per the USEPA, National Environmental Laboratory Accreditation Conference (NELAC), state-specific Performance Testing (PT) program requirements or ERAs 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 MAPEPs evaluation report provides an acceptance range with associated flag values. MAPEP defines three levels of performance:

x Acceptable (flag = A) - result within +/- 20% of the reference value x Acceptable with Warning (flag = W) - result falls in the +/- 20%

to +/- 30% of the reference value x 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, 164 out of 172 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. TBE was unable to report the February 2018 DOE MAPEP vegetation Sr-90 result due to QC failure and limited sample amount. (NCR 18-09) 23

2. The Analytics September 2018 milk Fe-59 result was evaluated as Not Acceptable (Ratio of TBE to known result at 133%). The UHSRUWHGYDOXHZDVS&L/DQGWKHNQRZQYDOXHZDV

S&L/1RFDXVHIRUWKHIDLOXUHFRXOGEHGHWHUPLQHG7%(

has passed 24 of the previous 27 milk cross-check results since 2012. This sample was run in duplicate on a different detector with FRPSDUDEOHUHVXOWV - S&L/ NOTE: TBEs 4th Qtr result passed at 105% (NCR 18-20)

3. The Analytics September milk I-131 result was evaluated as Not Acceptable (Ratio of TBE to known result at 143%). Due to a personnel change in the gamma prep lab, the sample was not SUHSSHGFRXQWHGLQDWLPHO\PDQQHUVXFKDVWRDFFRPPRGDWHWKH,-

131 8-day half-life. Analysts have been made aware of the urgency for this analysis and it will be monitored more closely by QA. NOTE:

TBEs 4th Qtr result passed at 101% (NCR 18-24)

4. The Analytics September soil Cr-51 result was evaluated as Not Acceptable (Ratio of TBE to known result at 131%). As with #3 above, the sample was noWSUHSSHGFRXQWHGLQDWLPHO\PDQQHU

such as to accommodate the Cr-51 27-day half-life. The same corrective action applies here as in #3. (NCR 18-21)

5. The MAPEP November vegetation Sr-UHVXOWRI%TVDPSOH

was evaluated as Not Acceptable (Lower acceptable range was

%TVDPSOH ,WDSSHDUVWKDWWKHUHKDVEHHQLQFRPSOHWH

dissolution of Sr-90 due to the composition of the MAPEP vegetation matrix. To resolve this issue, the TBE-2018 procedure has been modified to add H2O2 to assist in breaking down the organic material that comprises this matrix. This corrective action will be monitored closely by QA. (NCR 18-25).

6. The ERA November 2018 water Sr-90 sample was evaluated as Not Acceptable7%(¶VLQLWLDOUHSRUWHGUHVXOWRIS&L/

exceeded the upper acceptance range (22.9 - S&L/ $IWHU

reviewing the data for this sample, it was discovered that there was a typographical error at the time the results were entered at the ERA website. The correct result in LIMS of 36.2 should have been submitted instead. This result is within ERAs acceptance limits. In addition to the typo error, ERAs very stringent upper acceptance limit of 116% is not a reflection of TBEs ability to successfully perform this analysis. (NCR 18-23)

For the EIS laboratory, 63 of 63 analyses met the specified acceptance criteria.

For the GEL laboratory, 345 of 352 analyses met the specified acceptance 24

criteria. Seven analyses did not meet the specified acceptance criteria, none of which were for tritium, which is the only analysis done for Exelon.

The Inter-Laboratory Comparison Program provides evidence of in control counting systems and methods, and that the laboratories are producing accurate and reliable data. Interlaboratory Comparison results may be found in Appendix E.

VI. References A. Environmental Report Operating License Stage, Limerick Generating Station, Units 1 and 2, Volumes 1-5 Philadelphia Electric Company B. NUREG-1302 Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors C. Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1, November 1979 D. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation 25

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

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

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2018 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2018 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR REQUIRED 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) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER H-3 8 200 <LLD <LLD - 0 (PCI/LITER)

GAMMA 24 MN-54 15 <LLD <LLD - 0 CO-58 15 <LLD <LLD - 0 FE-59 30 <LLD <LLD - 0 CO-60 15 <LLD <LLD - 0 ZN-65 30 <LLD <LLD - 0 NB-95 15 <LLD <LLD - 0 A-1 ZR-95 30 <LLD <LLD - 0 I-131 15 <LLD <LLD - 0 CS-134 15 <LLD <LLD - 0 CS-137 18 <LLD <LLD - 0 BA-140 60 <LLD <LLD - 0 LA-140 15 <LLD <LLD - 0 I-131 (LOW LVL) 12 1 <LLD <LLD 0 DRINKING WATER GR-B 48 4 3.4 3 3.7 15F4 INDICATOR 0 (PCI/LITER) (22/36) (8/12) (9/12) AQUA AMERICA (2.1/4.8) (1.9/5.1) (2.7/4.8)

H-3 16 200 <LLD <LLD - 0 I-131 (LOW LVL) 48 1 <LLD <LLD - 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2018 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2018 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR REQUIRED 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) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS DRINKING WATER GAMMA 48 (PCI/LITER) MN-54 15 <LLD <LLD - 0 CO-58 15 <LLD <LLD - 0 FE-59 30 <LLD <LLD - 0 CO-60 15 <LLD <LLD - 0 ZN-65 30 <LLD <LLD - 0 NB-95 15 <LLD <LLD - 0 ZR-95 30 <LLD <LLD - 0 CS-134 15 <LLD <LLD - 0 A-2 CS-137 18 <LLD <LLD - 0 BA-140 60 <LLD <LLD - 0 LA-140 15 <LLD <LLD - 0 FISH - BOTTOM FEEDER GAMMA 4 (PCI/KG WET) K-40 NA 2966 2722.5 2966 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL (2745/3187) (2372/3073) (2745/3187) DOWNSTREAM OF DISCHARGE MN-54 130 <LLD <LLD - 0 CO-58 130 <LLD <LLD - 0 FE-59 260 <LLD <LLD - 0 CO-60 130 <LLD <LLD - 0 ZN-65 260 <LLD <LLD - 0 I-131 NA <LLD <LLD - 0 CS-134 130 <LLD <LLD - 0 CS-137 150 <LLD <LLD - 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2018 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2018 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR REQUIRED 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) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS FISH - PREDATOR GAMMA 4 (PCI/KG WET) K-40 NA 3323 3331.5 3331.5 29C1 CONTROL 0 (2/2) (2/2) (2/2) POTTSTOWN VICINITY (2998/3648) (3138/3525) (3138/3525) UPSTREAM OF INTAKE MN-54 130 <LLD <LLD - 0 CO-58 130 <LLD <LLD - 0 FE-59 260 <LLD <LLD - 0 CO-60 130 <LLD <LLD - 0 ZN-65 260 <LLD <LLD - 0 A-3 I-131 NA <LLD <LLD - 0 CS-134 130 <LLD <LLD - 0 CS-137 150 <LLD <LLD - 0 SEDIMENT GAMMA 6 (PCI/KG DRY) BE-7 NA 3784 2693 4571 16B2 INDICATOR 0 (3/4) (1/2) (2/2) LINFIELD BRIDGE (2209/4979) (4163/4979) 1.35 MILES SSE OF SITE K-40 NA 14575 12730 15165 16C4 INDICATOR 0 (4/4) (2/2) (2/2) VINCENT DAM (13500/15780) (12540/12920) (14550/15780) 2.18 MILES SSE OF SITE MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 I-131 NA <LLD <LLD - 0 CS-134 150 <LLD <LLD - 0 CS-137 180 133 127 133 16B2 INDICATOR 0 (1/4) (1/2) (1/2) LINFIELD BRIDGE 1.35 MILES SSE OF SITE (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2018 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2018 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR REQUIRED 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) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS AIR PARTICULATE GR-B 362 10 15 15 20 13S4 INDICATOR 0 (E-03 PCI/CU.METER) (327/335) (56/56) (56/56) LONGVIEW ROAD NEAR 500 KV YARD (5/37) (5/26) (8/37) 1186 FEET SE OF SITE GAMMA 28 BE-7 NA 67.5 62.7 98.7 13S4 INDICATOR 0 (24/24) (4/4) (4/4) LONGVIEW ROAD NEAR 500 KV YARD (35/151) (53/68) (70/151) 1186 FEET SE OF SITE MN-54 NA <LLD <LLD - 0 A-4 CO-58 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 CS-134 50 <LLD <LLD - 0 CS-137 60 <LLD <LLD - 0 AIR IODINE GAMMA 362 (E-03 PCI/CU.METER) I-131 (GELI) 70 <LLD <LLD - 0 MILK I-131 (LOW LVL) 88 1 <LLD <LLD - 0 (PCI/LITER)

GAMMA 88 K-40 NA 1221 1280 1303 23F1 CONTROL 0 (62/62) (26/26) (22/22)

(970/1465) (743/1547) (743/1547) 5.02 MILES SW OF SITE CS-134 15 <LLD <LLD - 0 CS-137 18 <LLD <LLD - 0 BA-140 60 <LLD <LLD - 0 LA-140 15 <LLD <LLD - 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2018 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2018 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR REQUIRED 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) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS VEGETATION GAMMA 39 (PCI/KG WET) BE-7 NA 1117 2102 2102 31G1 CONTROL 0 (25/27) (10/12) (10/12) PROUTS'S JOLLYVIEW FARM (CONTROL)

(281/6255) (389/4757) (389/4757) 71,808 FEET NW OF SITE K-40 NA 4642.3 4780.7 4818 13S3 INDICATOR 0 (27/27) (12/12) (14/14) VINCENT DAM (2980/7018) (3199/9051) (2980/7018) 0.24 MILES SE OF SITE MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 A-5 CO-60 NA <LLD <LLD - 0 I-131 60 <LLD <LLD - 0 CS-134 60 <LLD <LLD - 0 CS-137 80 <LLD <LLD - 0 RA-226 NA 1929.4 971.5 1929.4 13S3 INDICATOR 0 (10/27) (1/12) (10/14) VINCENT DAM (743/5105) (743/5105) 0.24 MILES SE OF SITE TH-228 NA 68.9 50.4 92.3 11S3 INDICATOR 0 (4/27) (1/12) (1/13) LGS INFORMATION CENTER (17/114) 0.35 MILES ESE OF SITE TH-232 NA <LLD <LLD - 0 DIRECT RADIATION OSLD-QUARTERLY 320 NA 5.6 6.8 7.7 13S2 INDICATOR 0 (MILLI-ROENTGEN/STD.MO.) (312/312) (8/8) (8/8) 500 KV SUBSTATION 3.6 - 9.8 6.2 - 7.3 7.5 - 8 0.41 MILES SE (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

Intentionally left blank APPENDIX B LOCATION DESIGNATION, DISTANCE &

DIRECTION, AND SAMPLE COLLECTION &

ANALYTICAL METHODS

Intentionally left blank TABLE B-1: Location Designation and Identification System for the Limerick Generating Station XXYZ - General code for identification of locations, where:

XX - Angular Sector of Sampling Location. The compass is divided into 36 sectors of 10 degrees each with center at Limerick's Units 1 and 2 off-gas vents. Sector 36 is centered due North, and others are numbered in a clockwise direction.

Y - Radial Zone of Sampling Location (in this report, the radial distance from the Limerick vent for all regional stations).

S  : on-site location E  : 21,120-26,400 feet off-site A  : 0-5,280 feet off-site F  : 26,400-52,800 feet off-site B  : 5,280-10,560 feet off-site G  : 52,800-105,600 feet off-site C  : 10,560-15,840 feet off-site H  : 105,600-528,000 feet off-site D  : 15,840-21,120 feet off-site Z - Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.

B-1

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction Limerick Generating Station, 2018 Location Location Description Distance & Direction From Site A. Surface Water 13B1 Vincent Dam 9,225 feet SE 24S1 Limerick Intake (control) 1,058 feet SW B. Drinking (Potable) Water 15F4 AQUA Water Company 45,514 feet SE 15F7 Phoenixville Water Works 33,400 feet SSE 16C2 PA American 14,034 feet SSE 28F3 Pottstown Borough Authority, Water Distribution Division (control) 30,811 feet WNW C. Milk - bi-weekly / monthly 10F4 34,848 feet ESE 18E1 22,229 feet S 19B1 10,317 feet SSW 23F1 Control 26,505 feet SW 25C1 14,224 feet WSW D. Milk - quarterly 36E1 Control 24,816 feet N E. Air Particulates / Air Iodine 10S3 Keen Road 2,648 feet E 11S1 LGS Information Center 2,017 feet ESE 11S2 LGS Information Center (quality control) 2,017 feet ESE 13S4 Longview Road, near 500 kv Yard 1,186 feet SE 14S1 Longview Road 3,319 feet SSE 15D1 Spring City Substation 16,877 feet SE 22G1 Manor Substation (control) 93,619 feet SW 6C1 Limerick Airport 11,305 feet NE F. Fish 16C5 Vincent Pool Downstream of Discharge 29C1 Pottstown Vicinity (control) Upstream of Intake G. Sediment 16B2 Linfield Bridge 7,128 feet SSE 16C4 Vincent Dam 11,510 feet SSE 33A2 Upstream of Intake (control) 4,435 feet NNW H. Broad Leaf Vegetation 11S3 LGS Information Center 1,848 feet ESE 13S3 LGS 500 KV Yard 1,267 feet SE 31G1 Prout's Jollyview Farm (control) 71,808 feet NW B-2

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction Limerick Generating Station, 2018 Location Location Description Distance & Direction From Site I. Environmental Dosimetry - DLR Site Boundary 36S2 Evergreen & Sanatoga Road 3,183 feet N 3S1 Sanatoga Road 2,301 feet NNE 5S1 Possum Hollow Road 2,350 feet NE 7S1 LGS Training Center 3,099 feet ENE 10S3 Keen Road 2,648 feet E 11S1 LGS Information Center 2,017 feet ESE 13S2 500 KV Substation 2,149 feet SE 14S1 Longview Road 3,319 feet SSE 18S2 Rail Line along Longview Road 1,390 feet S 21S2 Near Intake Building 977 feet SSW 23S2 Transmission Tower 2,793 feet SW 25S2 Sector Site Boundary 2,445 feet WSW 26S3 Met. Tower #2 2,088 feet W 29S1 Sector Site Boundary 2,886 feet WNW 31S1 Sector Site Boundary 1,395 feet NW 34S2 Met. Tower #1 3,071 feet NNW Intermediate Distance 36D1 Siren Tower No. 147 18,527 feet N 2E1 Laughing Waters GSC 25,112 feet NNE 4E1 Neiffer Road 25,221 feet NE 7E1 Pheasant Road 22,489 feet ENE 10E1 Royersford Road 20,826 feet E 10F3 Trappe Substation 29,442 feet ESE 13E1 Vaughn Substation 22,772 feet SE 16F1 Pikeland Substation 26,608 feet SSE 19D1 Snowden Substation 18,439 feet S 20F1 Sheeder Substation 27,648 feet SSW 24D1 Porters Mill Substation 20,972 feet SW 25D1 Hoffecker & Keim Streets 21,044 feet WSW 28D2 W. Cedarville Road 20,231 feet W 29E1 Prince Street 26,110 feet WNW 31D2 Poplar Substation 20,446 feet NW 34E1 Varnell Road 24,243 feet NNW Control and Special Interest 5H1 Birch Substation (control) 130,742 feet NE 6C1 Limerick Airport 11,305 feet NE 9C1 Reed Road 11,377 feet E 13C1 King Road 14,980 feet SE 15D1 Spring City Substation 16,877 feet SE 17B1 Linfield Substation 8,462 feet S 20D1 Ellis Woods Road 16,157 feet SSW 31D1 Lincoln Substation 15,853 feet WNW B-3

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2018 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium TBE, TBE-2007 Gamma emitting radioisotope analysis Monthly composite CY-ES-210 EIS Collection of water Surface Gamma from a continuous samples for Radiological Analysis 2 gallon Water Spectroscopy EIS, CY-ES-205, Rev. 001 Gamma Counting Using the water compositor (Limerick Generating Station)

HPGe Detector with the Genie PC Counting System TBE, TBE-2011 Tritium analysis in drinking water by Quarterly composite CY-ES-210 EIS Collection of water liquid scintillation Surface Tritium from a continuous samples for Radiological Analysis 500 ml Water water compositor (Limerick Generating Station) GEL, EPA906.0 Mod, for Tritium analysis by Liquid Scintillation TBE, TBE-2008 Gross Alpha and/or gross beta activity in Monthly composite CY-ES-210 EIS Collection of water various matrices Drinking Gross Beta from a continuous samples for Radiological Analysis 2 gallon Water water compositor (Limerick Generating Station) EIS, CY-ES-206, Operation of the Tennelec S5E Proportional Counter TBE, TBE-2012 Radioiodine in various matrices Monthly composite CY-ES-210 EIS Collection of water Drinking I-131 from a continuous samples for Radiological Analysis 2 gallon B-4 Water EIS, CY-ES-205, Rev. 001 Gamma Counting Using the water compositor (Limerick Generating Station)

HPGe Detector with the Genie PC Counting System TBE, TBE-2007 Gamma emitting radioisotope analysis Monthly composite CY-ES-210 EIS Collection of water Drinking Gamma from a continuous samples for Radiological Analysis 2 gallon Water Spectroscopy EIS, CY-ES-205, Rev. 001 Gamma Counting Using the water compositor (Limerick Generating Station)

HPGe Detector with the Genie PC Counting System TBE, TBE-2011 Tritium analysis in drinking water by Quarterly composite CY-ES-210 EIS Collection of water liquid scintillation Drinking Tritium from a continuous samples for Radiological Analysis 500 ml Water water compositor (Limerick Generating Station) GEL, EPA906.0 Mod, for Tritium analysis by Liquid Scintillation Semi-annual samples RMC-ER6 Collection of fish samples Gamma collected via 1000 grams Fish for radiological analysis (Limerick TBE-2007 Gamma emitting radioisotope analysis Spectroscopy electroshocking or (wet)

Generating Station) other techniques RMC-ER7 Collection of sediment Gamma Semi-annual grab Sediment samples for radiological analysis 500 grams (dry) TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples (Limerick Generating Station)

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2018 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium TBE, TBE-2008 Gross Alpha and/or gross beta activity in One-week composite CY-ES-208 Sample Collection of Air 1 filter various matrices Air of continuous air Iodine and Air Particulate for (approximately Gross Beta Particulates sampling through Radiological Analysis (Limerick 280 cubic EIS, CY-ES-206, Rev. 001 Operation of the Tennelec glass fiber filter paper Generating Station) meters weekly)

S5E Proportional Counter TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis Air Gamma Quarterly composite of (approximately Particulates Spectroscopy each station CY-ES-204, Rev. 001 Sample 3600 cubic EIS, CY-ES-205, Rev. 001 Gamma Counting Using the Preparation for Gamma and Beta meters) HPGe Detector with the Genie PC Counting System Counting One-week composite CY-ES-208 Sample Collection of Air 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis Gamma of continuous air Iodine and Air Particulate for (approximately Air Iodine Spectroscopy sampling through Radiological Analysis (Limerick 280 cubic EIS, CY-ES-205, Rev. 001 Gamma Counting Using the charcoal filter Generating Station) meters weekly) HPGe Detector with the Genie PC Counting System Bi-weekly grab sample TBE, TBE-2012 Radioiodine in various matrices B-5 CY-ES-209 EIS Sample Collection when cows are on Milk I-131 for Gamma Counting - Milk 2 gallon pasture; Monthly all EIS, CY-ES-205, Rev. 001 Gamma Counting Using the (Limerick Generating Station) other times HPGe Detector with the Genie PC Counting System Bi-weekly grab sample TBE, TBE-2007 Gamma emitting radioisotope analysis CY-ES-209 EIS Sample Collection Gamma when cows are on Milk for Gamma Counting - Milk 2 gallon Spectroscopy pasture; Monthly all EIS, CY-ES-205, Rev. 001 Gamma Counting Using the (Limerick Generating Station) other times HPGe Detector with the Genie PC Counting System Quarterly DLRs RMC-ER9 Collection of OSLD Thermoluminescent DLR comprised of two samples for radiological analysis 2 dosimeters Mirion Technologies Dosimetry dosimeter elements (Limerick Generating Station)

Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2018 B-6

Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2018 B-7

Figure B-3 Environmental Sampling Locations Greater than 26,400 Feet from the Limerick Generating Station, 2018 B-8

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank Table C-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 13B1 24S1 01/02/18 - 04/02/18 < 188 < 193 04/02/18 - 07/02/18 < 191 < 192 07/02/18 - 10/01/18 < 192 < 192 10/01/18 - 01/02/19 < 185 < 185 MEAN - -

Table C-I.2 CONCENTRATIONS OF I-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 24S1 01/02/18 - 01/29/18 < 0.9 01/29/18 - 02/26/18 < 0.5 02/26/18 - 04/02/18 < 0.8 04/02/18 - 04/30/18 < 1.0 04/30/18 - 05/29/18 < 0.6 05/29/18 - 07/02/18 < 0.4 07/02/18 - 07/30/18 < 0.6 07/30/18 - 08/28/18 < 0.5 08/28/18 - 10/01/18 < 0.6 10/01/18 - 10/31/18 < 0.7 10/31/18 - 12/05/18 < 0.9 12/05/18 - 01/02/19 < 0.6 MEAN -

C-1

Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 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 I-131 Cs-134 Cs-137 Ba-140 La-140 13B1 01/02/18 - 01/29/18 < 6 < 5 < 9 < 6 < 12 < 6 < 9 < 11 < 4 < 6 < 26 < 11 01/29/18 - 02/26/18 < 6 < 7 < 20 < 10 < 17 < 9 < 15 < 10 < 8 < 8 < 32 < 11 02/26/18 - 04/02/18 < 4 < 4 < 10 < 4 < 9 < 4 < 8 < 8 < 4 < 5 < 19 < 9 04/02/18 - 04/30/18 < 2 < 2 < 4 < 2 < 4 < 2 < 4 < 8 < 2 < 2 < 16 < 5 04/30/18 - 05/29/18 < 3 < 3 < 7 < 3 < 6 < 3 < 6 < 10 < 3 < 3 < 23 < 8 05/29/18 - 07/02/18 < 5 < 7 < 11 < 6 < 13 < 6 < 11 < 10 < 5 < 6 < 28 < 12 07/02/18 - 07/30/18 < 7 < 6 < 12 < 7 < 15 < 7 < 11 < 14 < 6 < 6 < 35 < 15 07/30/18 - 08/28/18 < 5 < 7 < 12 < 5 < 13 < 5 < 10 < 13 < 6 < 7 < 36 < 9 08/28/18 - 10/01/18 < 6 < 5 < 14 < 7 < 11 < 7 < 10 < 13 < 6 < 6 < 34 < 12 10/01/18 - 10/31/18 < 5 < 4 < 12 < 6 < 10 < 5 < 9 < 9 < 5 < 5 < 25 < 10 10/31/18 - 12/05/18 < 6 < 5 < 15 < 7 < 11 < 7 < 10 < 11 < 6 < 6 < 31 < 8 12/05/18 - 01/02/19 < 6 < 6 < 13 < 6 < 10 < 6 < 9 < 11 < 5 < 7 < 27 < 6 C-2 MEAN - - - - - - - - - - - -

24S1 01/02/18 - 01/29/18 < 4 < 5 < 10 < 4 < 10 < 5 < 8 < 10 < 5 < 4 < 26 < 7 01/29/18 - 02/26/18 < 7 < 7 < 13 < 7 < 11 < 7 < 11 < 8 < 7 < 8 < 21 < 9 02/26/18 - 04/02/18 < 4 < 5 < 10 < 4 < 7 < 5 < 8 < 8 < 4 < 5 < 21 < 9 04/02/18 - 04/30/18 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 6 < 2 < 2 < 12 < 5 04/30/18 - 05/29/18 < 3 < 3 < 7 < 3 < 5 < 3 < 5 < 9 < 3 < 3 < 19 < 7 05/29/18 - 07/02/18 < 6 < 6 < 12 < 8 < 13 < 6 < 12 < 13 < 6 < 7 < 39 < 11 07/02/18 - 07/30/18 < 6 < 7 < 10 < 6 < 12 < 7 < 12 < 14 < 6 < 6 < 34 < 11 07/30/18 - 08/28/18 < 6 < 5 < 10 < 4 < 10 < 5 < 9 < 15 < 4 < 5 < 34 < 11 08/28/18 - 10/01/18 < 5 < 6 < 12 < 6 < 11 < 6 < 9 < 12 < 6 < 6 < 29 < 10 10/01/18 - 10/31/18 < 6 < 6 < 13 < 6 < 14 < 6 < 13 < 11 < 6 < 7 < 30 < 12 10/31/18 - 12/05/18 < 5 < 6 < 11 < 7 < 14 < 6 < 10 < 11 < 7 < 9 < 33 < 11 12/05/18 - 01/02/19 < 8 < 7 < 10 < 6 < 17 < 7 < 13 < 10 < 6 < 8 < 27 < 10 MEAN - - - - - - - - - - - -

Table C-II.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 01/02/18 - 01/29/18 4.2 +/- 1.9 3.0 +/- 1.6 < 2.4 2.8 +/- 1.6 01/29/18 - 02/26/18 < 2.0 < 1.9 3.7 +/- 1.5 1.9 +/- 1.3 02/26/18 - 04/02/18 < 2.2 < 2.0 < 2.1 < 2.0 04/02/18 - 04/30/18 4.8 +/- 1.7 2.1 +/- 1.5 < 2.2 2.9 +/- 1.5 04/30/18 - 05/29/18 2.7 +/- 1.6 2.8 +/- 1.5 < 2.3 2.5 +/- 1.5 05/29/18 - 07/02/18 3.2 +/- 1.8 3.3 +/- 1.8 < 2.7 3.0 +/- 1.8 07/02/18 - 07/30/18 4.6 +/- 1.7 3.8 +/- 1.6 3.5 +/- 1.7 5.1 +/- 1.7 07/30/18 - 08/28/18 3.6 +/- 1.6 3.1 +/- 1.5 3.5 +/- 1.7 2.8 +/- 1.5 08/28/18 - 10/01/18 3.1 +/- 1.5 3.3 +/- 1.5 < 2.1 < 1.9 10/01/18 - 10/31/18 4.0 +/- 1.6 3.1 +/- 1.5 < 2.3 < 2.2 10/31/18 - 12/05/18 3.4 +/- 1.5 3.4 +/- 1.5 < 2.3 2.8 +/- 1.5 12/05/18 - 01/02/19 < 2.1 2.8 +/- 1.5 < 2.4 < 2.2 MEAN +/- 2 STD DEV 3.7 + 1.4 3.1 + 0.9 3.5 + 0.2 3.0 + 1.8 Table C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 01/02/18 - 04/02/18 < 184 < 186 < 182 < 187 04/02/18 - 07/02/18 < 188 < 195 < 190 < 193 07/02/18 - 10/01/18 < 192 < 191 < 194 < 195 10/01/18 - 01/02/19 < 186 < 191 < 185 < 183 MEAN - - - -

Table C-II.3 CONCENTRATIONS OF I-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 01/02/18 - 01/29/18 < 0.7 < 0.4 < 0.7 < 0.7 01/29/18 - 02/26/18 < 0.6 < 0.5 < 0.5 < 0.5 02/26/18 - 04/02/18 < 0.9 < 0.8 < 0.9 < 0.9 04/02/18 - 04/30/18 < 1.0 < 0.8 < 0.8 < 0.7 04/30/18 - 05/29/18 < 0.7 < 0.8 < 0.7 < 0.6 05/29/18 - 07/02/18 < 0.4 < 0.4 < 0.4 < 0.4 07/02/18 - 07/30/18 < 0.8 < 0.5 < 0.5 < 0.5 07/30/18 - 08/28/18 < 0.7 < 0.9 < 0.7 < 0.5 08/28/18 - 10/01/18 < 0.6 < 0.4 < 0.5 < 0.5 10/01/18 - 10/31/18 < 0.9 < 0.6 < 0.7 < 0.6 10/31/18 - 12/05/18 < 0.7 < 0.8 < 0.9 < 0.8 12/05/18 - 01/02/19 < 0.7 < 0.6 < 0.9 < 0.8 MEAN - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-3

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER + 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 15F4 01/02/18 - 01/29/18 < 6 < 5 < 13 < 6 < 13 < 6 < 10 < 5 < 6 < 28 < 10 01/29/18 - 02/26/18 < 8 < 8 < 14 < 7 < 17 < 7 < 13 < 6 < 8 < 28 < 11 02/26/18 - 04/02/18 < 4 < 4 < 10 < 4 < 8 < 5 < 7 < 4 < 5 < 24 < 7 04/02/18 - 04/30/18 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 14 < 4 04/30/18 - 05/29/18 < 3 < 3 < 7 < 3 < 6 < 3 < 5 < 3 < 3 < 19 < 8 05/29/18 - 07/02/18 < 6 < 6 < 13 < 8 < 12 < 5 < 12 < 5 < 6 < 40 < 13 07/02/18 - 07/30/18 < 6 < 5 < 12 < 6 < 11 < 5 < 11 < 5 < 5 < 31 < 10 07/30/18 - 08/28/18 < 5 < 6 < 11 < 6 < 13 < 5 < 11 < 5 < 5 < 33 < 9 08/28/18 - 10/01/18 < 5 < 5 < 12 < 5 < 10 < 5 < 10 < 5 < 5 < 30 < 10 10/01/18 - 10/31/18 < 4 < 4 < 9 < 5 < 11 < 6 < 8 < 4 < 5 < 25 < 9 10/31/18 - 12/05/18 < 6 < 6 < 13 < 7 < 14 < 7 < 12 < 7 < 6 < 33 < 12 12/05/18 - 01/02/19 < 7 < 4 < 12 < 7 < 13 < 7 < 12 < 6 < 7 < 19 < 13 C-4 MEAN - - - - - - - - - - -

15F7 01/02/18 - 01/29/18 < 7 < 5 < 11 < 7 < 12 < 6 < 10 < 6 < 6 < 29 < 11 01/29/18 - 02/26/18 < 10 < 9 < 16 < 9 < 21 < 9 < 14 < 11 < 9 < 39 < 11 02/26/18 - 04/02/18 < 5 < 5 < 9 < 5 < 11 < 6 < 8 < 4 < 5 < 26 < 8 04/02/18 - 04/30/18 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 13 < 5 04/30/18 - 05/29/18 < 3 < 3 < 6 < 3 < 6 < 3 < 6 < 3 < 3 < 21 < 6 05/29/18 - 07/02/18 < 6 < 4 < 15 < 8 < 9 < 7 < 13 < 5 < 7 < 38 < 14 07/02/18 - 07/30/18 < 6 < 7 < 10 < 9 < 15 < 7 < 13 < 6 < 6 < 37 < 14 07/30/18 - 08/28/18 < 5 < 4 < 10 < 5 < 10 < 5 < 8 < 5 < 4 < 33 < 9 08/28/18 - 10/01/18 < 6 < 5 < 16 < 6 < 11 < 7 < 12 < 7 < 6 < 37 < 12 10/01/18 - 10/31/18 < 6 < 8 < 13 < 7 < 16 < 8 < 13 < 6 < 8 < 38 < 11 10/31/18 - 12/05/18 < 6 < 6 < 12 < 5 < 9 < 7 < 11 < 6 < 7 < 34 < 12 12/05/18 - 01/02/19 < 7 < 7 < 16 < 10 < 14 < 5 < 15 < 6 < 8 < 29 < 10 MEAN - - - - - - - - - - -

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER + 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 16C2 01/02/18 - 01/29/18 < 5 < 5 < 9 < 6 < 13 < 7 < 10 < 5 < 6 < 26 < 10 01/29/18 - 02/26/18 < 6 < 6 < 17 < 6 < 20 < 8 < 14 < 6 < 8 < 35 < 13 02/26/18 - 04/02/18 < 5 < 5 < 9 < 5 < 10 < 6 < 10 < 5 < 5 < 31 < 11 04/02/18 - 04/30/18 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 13 < 4 04/30/18 - 05/29/18 < 4 < 4 < 8 < 4 < 7 < 4 < 7 < 3 < 4 < 25 < 9 05/29/18 - 07/02/18 < 5 < 6 < 12 < 7 < 8 < 6 < 8 < 5 < 6 < 29 < 11 07/02/18 - 07/30/18 < 5 < 5 < 12 < 5 < 9 < 5 < 8 < 4 < 5 < 26 < 10 07/30/18 - 08/28/18 < 6 < 6 < 14 < 6 < 13 < 6 < 11 < 5 < 7 < 31 < 13 08/28/18 - 10/01/18 < 6 < 5 < 10 < 6 < 14 < 7 < 12 < 6 < 7 < 29 < 11 10/01/18 - 10/31/18 < 6 < 6 < 17 < 7 < 13 < 7 < 11 < 7 < 8 < 41 < 12 10/31/18 - 12/05/18 < 7 < 6 < 12 < 7 < 12 < 5 < 11 < 6 < 7 < 23 < 12 12/05/18 - 01/02/19 < 6 < 7 < 12 < 7 < 14 < 7 < 10 < 5 < 5 < 28 < 11 C-5 MEAN - - - - - - - - - - -

28F3 01/02/18 - 01/29/18 < 5 < 6 < 11 < 5 < 13 < 5 < 10 < 5 < 6 < 26 < 10 01/29/18 - 02/26/18 < 9 < 7 < 21 < 8 < 18 < 8 < 12 < 7 < 8 < 37 < 12 02/26/18 - 04/02/18 < 5 < 5 < 9 < 5 < 11 < 5 < 9 < 5 < 4 < 23 < 8 04/02/18 - 04/30/18 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 15 < 4 04/30/18 - 05/29/18 < 3 < 3 < 7 < 3 < 6 < 3 < 7 < 3 < 3 < 20 < 7 05/29/18 - 07/02/18 < 5 < 6 < 14 < 5 < 10 < 6 < 12 < 5 < 5 < 31 < 10 07/02/18 - 07/30/18 < 8 < 7 < 16 < 8 < 13 < 7 < 12 < 6 < 6 < 36 < 14 07/30/18 - 08/28/18 < 4 < 5 < 11 < 4 < 8 < 5 < 8 < 4 < 5 < 29 < 11 08/28/18 - 10/01/18 < 8 < 9 < 16 < 8 < 16 < 8 < 11 < 7 < 7 < 42 < 14 10/01/18 - 10/31/18 < 7 < 8 < 16 < 7 < 20 < 9 < 13 < 7 < 8 < 41 < 13 10/31/18 - 12/05/18 < 6 < 6 < 15 < 4 < 13 < 8 < 13 < 6 < 7 < 32 < 8 12/05/18 - 01/02/19 < 7 < 5 < 9 < 5 < 9 < 7 < 11 < 6 < 8 < 26 < 8 MEAN - - - - - - - - - - -

Table C-III.1 CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH)

SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 I-131 Cs-134 Cs-137 16C5 PREDATOR 06/18/18 2998 +/- 1114 < 70 < 65 < 156 < 79 < 107 < 126 < 74 < 93 10/24/18 3648 +/- 907 < 71 < 80 < 145 < 66 < 143 < 236 < 70 < 75 MEAN +/- 2 STD DEV 3323 +/- 919 - - - - - - - -

16C5 BOTTOM FEEDER 06/18/18 2745 +/- 923 < 49 < 47 < 121 < 40 < 137 < 85 < 48 < 53 10/24/18 3187 +/- 1152 < 67 < 59 < 149 < 60 < 157 < 200 < 61 < 63 MEAN +/- 2 STD DEV 2966 +/- 625 - - - - - - - -

C-6 29C1 PREDATOR 06/15/18 3525 +/- 913 < 58 < 53 < 143 < 45 < 126 < 116 < 60 < 54 10/25/18 3138 +/- 1113 < 66 < 65 < 163 < 82 < 162 < 182 < 48 < 58 MEAN +/- 2 STD DEV 3332 +/- 547 - - - - - - - -

29C1 BOTTOM FEEDER 06/15/18 3073 +/- 990 < 64 < 75 < 109 < 72 < 129 < 131 < 63 < 68 10/25/18 2372 +/- 1126 < 95 < 101 < 159 < 93 < 249 < 353 < 88 < 95 MEAN +/- 2 STD DEV 2723 +/- 991 - - - - - - - -

THE MEAN AND 2-STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 I-131 Cs-134 Cs-137 16B2 06/14/18 4163 +/- 828 13500 +/- 1970 < 101 < 91 < 109 < 167 < 85 < 118 11/20/18 4979 +/- 1018 14470 +/- 2028 < 110 < 116 < 116 < 219 < 91 133 +/- 86 MEAN +/- 2 STD DEV 4571 +/- 1154 13985 + 1372 - - - - - 133 +/- 0 16C4 06/14/18 < 1029 15780 +/- 2051 < 104 < 91 < 104 < 136 < 78 < 133 11/20/18 2209 +/- 1011 14550 +/- 2329 < 91 < 85 < 118 < 162 < 101 < 146 MEAN +/- 2 STD DEV 2209 +/- 0 15165 + 1739 - - - - - -

33A2 06/14/18 2693 +/- 972 12540 +/- 1709 < 100 < 82 < 103 < 146 < 89 < 120 C-7 11/20/18 < 634 12920 +/- 2132 < 89 < 85 < 114 < 117 < 91 127 +/- 90 MEAN +/- 2 STD DEV 2693 +/- 0 12730 + 537 - - - - - 127 +/- 0 THE MEAN AND 2-STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF E-03 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD 10S3 11S1 13S4 14S1 6C1 15D1 22G1 01/02/18 - 01/08/18 23 +/- 6 22 +/- 6 25 +/- 6 22 +/- 6 23 +/- 6 18 +/- 6 23 +/- 5 01/08/18 - 01/16/18 21 +/- 5 15 +/- 4 17 +/- 4 18 +/- 5 18 +/- 4 17 +/- 4 18 +/- 4 01/16/18 - 01/22/18 24 +/- 6 27 +/- 7 37 +/- 7 27 +/- 7 27 +/- 6 28 +/- 7 26 +/- 6 01/22/18 - 01/29/18 14 +/- 4 16 +/- 4 18 +/- 4 15 +/- 4 16 +/- 4 12 +/- 4 16 +/- 4 01/29/18 - 02/05/18 11 +/- 4 9 +/- 4 17 +/- 4 9 +/- 4 9 +/- 4 11 +/- 4 10 +/- 4 02/05/18 - 02/13/18 15 +/- 4 15 +/- 4 16 +/- 3 15 +/- 4 17 +/- 4 16 +/- 4 12 +/- 3 02/13/18 - 02/19/18 17 +/- 5 20 +/- 5 29 +/- 5 22 +/- 5 22 +/- 5 23 +/- 5 22 +/- 5 02/19/18 - 02/26/18 9 +/- 3 7 +/- 3 13 +/- 4 11 +/- 4 10 +/- 4 8 +/- 3 11 +/- 3 02/26/18 - 03/06/18 16 +/- 4 19 +/- 4 21 +/- 4 15 +/- 4 16 +/- 4 16 +/- 4 16 +/- 4 03/06/18 - 03/12/18 < 6 < 6 10 +/- 5 6 +/- 4 7 +/- 4 < 6 5 +/- 4 03/12/18 - 03/20/18 13 +/- 3 16 +/- 4 20 +/- 4 16 +/- 4 14 +/- 3 15 +/- 4 14 +/- 3 03/20/18 - 03/26/18 12 +/- 4 8 +/- 4 8 +/- 4 7 +/- 4 13 +/- 5 9 +/- 4 10 +/- 4 03/26/18 - 04/02/18 11 +/- 4 11 +/- 4 23 +/- 5 14 +/- 4 12 +/- 4 12 +/- 4 12 +/- 4 04/02/18 - 04/09/18 11 +/- 4 10 +/- 4 17 +/- 4 15 +/- 4 (1) 13 +/- 4 11 +/- 3 04/09/18 - 04/16/18 14 +/- 4 17 +/- 4 25 +/- 4 16 +/- 4 20 +/- 4 18 +/- 4 15 +/- 4 04/16/18 - 04/23/18 8 +/- 3 7 +/- 3 13 +/- 4 12 +/- 4 8 +/- 3 8 +/- 3 9 +/- 3 04/23/18 - 04/30/18 11 +/- 4 14 +/- 4 15 +/- 4 10 +/- 4 12 +/- 4 9 +/- 4 10 +/- 4 04/30/18 - 05/07/18 23 +/- 4 29 +/- 5 34 +/- 5 22 +/- 4 24 +/- 5 30 +/- 5 23 +/- 4 05/07/18 - 05/14/18 11 +/- 4 11 +/- 4 21 +/- 5 11 +/- 4 11 +/- 4 12 +/- 4 11 +/- 4 05/14/18 - 05/21/18 7 +/- 4 < 5 9 +/- 4 6 +/- 4 8 +/- 4 7 +/- 4 6 +/- 3 05/21/18 - 05/29/18 14 +/- 4 13 +/- 4 23 +/- 4 10 +/- 3 10 +/- 3 14 +/- 4 14 +/- 4 05/29/18 - 06/05/18 9 +/- 4 9 +/- 4 10 +/- 4 5 +/- 3 8 +/- 4 6 +/- 3 6 +/- 3 06/05/18 - 06/11/18 11 +/- 4 16 +/- 5 15 +/- 5 14 +/- 5 13 +/- 5 11 +/- 4 17 +/- 5 06/11/18 - 06/18/18 10 +/- 3 14 +/- 4 21 +/- 4 12 +/- 4 13 +/- 4 13 +/- 4 15 +/- 4 06/18/18 - 06/25/18 11 +/- 4 11 +/- 4 17 +/- 4 8 +/- 3 13 +/- 4 12 +/- 4 12 +/- 4 06/25/18 - 07/02/18 20 +/- 4 15 +/- 4 29 +/- 6 9 +/- 3 18 +/- 4 16 +/- 4 18 +/- 4 07/02/18 - 07/09/18 26 +/- 5 23 +/- 5 37 +/- 6 20 +/- 4 20 +/- 4 22 +/- 5 26 +/- 5 07/09/18 - 07/16/18 14 +/- 4 16 +/- 4 29 +/- 6 11 +/- 4 15 +/- 4 11 +/- 4 14 +/- 4 07/16/18 - 07/23/18 12 +/- 4 13 +/- 4 19 +/- 5 10 +/- 4 11 +/- 4 11 +/- 4 8 +/- 4 07/23/18 - 07/30/18 8 +/- 4 14 +/- 4 19 +/- 5 12 +/- 4 14 +/- 4 12 +/- 4 11 +/- 4 07/30/18 - 08/06/18 13 +/- 4 15 +/- 4 22 +/- 5 13 +/- 4 14 +/- 4 16 +/- 4 11 +/- 4 08/06/18 - 08/13/18 20 +/- 4 25 +/- 5 29 +/- 5 20 +/- 4 22 +/- 4 22 +/- 4 20 +/- 4 08/13/18 - 08/20/18 14 +/- 4 17 +/- 5 26 +/- 5 19 +/- 5 19 +/- 5 19 +/- 5 18 +/- 4 08/20/18 - 08/28/18 17 +/- 4 17 +/- 4 23 +/- 4 20 +/- 4 17 +/- 4 15 +/- 4 15 +/- 4 08/28/18 - 09/04/18 21 +/- 5 17 +/- 4 27 +/- 5 20 +/- 4 20 +/- 4 21 +/- 5 21 +/- 5 09/04/18 - 09/11/18 10 +/- 4 13 +/- 4 17 +/- 5 11 +/- 4 10 +/- 4 12 +/- 4 8 +/- 4 09/11/18 - 09/18/18 < 5 < 5 8 +/- 4 6 +/- 4 7 +/- 4 7 +/- 4 9 +/- 4 09/18/18 - 09/24/18 9 +/- 4 14 +/- 5 13 +/- 5 14 +/- 5 11 +/- 4 8 +/- 4 15 +/- 5 09/24/18 - 10/01/18 9 +/- 4 9 +/- 4 18 +/- 5 9 +/- 4 17 +/- 5 11 +/- 4 15 +/- 5 10/01/18 - 10/09/18 15 +/- 4 22 +/- 4 23 +/- 4 21 +/- 4 17 +/- 4 19 +/- 4 20 +/- 4 10/09/18 - 10/15/18 12 +/- 4 9 +/- 4 12 +/- 4 14 +/- 4 14 +/- 4 11 +/- 4 11 +/- 4 10/15/18 - 10/22/18 14 +/- 4 16 +/- 4 17 +/- 4 17 +/- 4 13 +/- 4 15 +/- 4 13 +/- 4 10/22/18 - 10/31/18 8 +/- 3 10 +/- 3 10 +/- 3 7 +/- 3 10 +/- 3 9 +/- 3 8 +/- 3 10/31/18 - 11/05/18 17 +/- 5 14 +/- 5 22 +/- 5 15 +/- 5 15 +/- 5 13 +/- 5 19 +/- 5 11/05/18 - 11/12/18 18 +/- 5 15 +/- 4 27 +/- 5 8 +/- 4 15 +/- 4 10 +/- 4 7 +/- 4 11/12/18 - 11/19/18 15 +/- 4 11 +/- 4 13 +/- 4 15 +/- 4 11 +/- 4 17 +/- 4 17 +/- 4 11/19/18 - 11/26/18 21 +/- 4 22 +/- 5 30 +/- 5 20 +/- 5 (1) 21 +/- 5 22 +/- 5 11/26/18 - 12/05/18 10 +/- 3 8 +/- 3 13 +/- 4 8 +/- 3 8 +/- 3 8 +/- 3 8 +/- 3 12/05/18 - 12/11/18 18 +/- 5 20 +/- 5 33 +/- 6 20 +/- 5 17 +/- 5 17 +/- 5 20 +/- 5 12/11/18 - 12/18/18 19 +/- 5 23 +/- 5 33 +/- 6 19 +/- 5 21 +/- 5 22 +/- 5 22 +/- 5 12/18/18 - 12/26/18 10 +/- 3 13 +/- 4 15 +/- 3 11 +/- 3 11 +/- 3 12 +/- 4 15 +/- 4 12/26/18 - 01/02/19 13 +/- 4 17 +/- 4 17 +/- 4 15 +/- 4 13 +/- 4 13 +/- 4 15 +/- 4 MEAN +/- 2 STD DEV 14 +/- 10 15 +/- 10 20 +/- 15 14 +/- 10 14 +/- 9 15 +/- 11 15 +/- 10 THE MEAN AND 2-STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8

Table C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF E-03 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II - INTERMEDIATE DISTANCE LOCATIONS GROUP III - CONTROL LOCATIONS COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN PERIOD +/- 2SD PERIOD +/- 2SD PERIOD +/- 2SD 01/02/18 - 01/29/18 14 37 21 +/- 12 01/02/18 - 01/29/18 12 28 20 +/- 11 01/02/18 - 01/29/18 16 26 21 +/- 9 01/29/18 - 02/26/18 7 29 15 +/- 11 01/29/18 - 02/26/18 8 23 14 +/- 12 01/29/18 - 02/26/18 10 22 14 +/- 11 02/26/18 - 04/02/18 6 23 14 +/- 10 02/26/18 - 04/02/18 7 16 13 +/- 6 02/26/18 - 04/02/18 5 16 11 +/- 8 04/02/18 - 04/30/18 7 25 13 +/- 9 04/02/18 - 04/30/18 8 20 13 +/- 10 04/02/18 - 04/30/18 9 15 11 +/- 5 04/30/18 - 05/29/18 6 34 16 +/- 17 04/30/18 - 05/29/18 7 30 14 +/- 16 04/30/18 - 05/29/18 6 23 13 +/- 14 05/29/18 - 07/02/18 5 29 13 +/- 11 05/29/18 - 07/02/18 6 18 12 +/- 7 05/29/18 - 07/02/18 6 18 13 +/- 9 07/02/18 - 07/30/18 8 37 18 +/- 16 07/02/18 - 07/30/18 11 22 14 +/- 9 07/02/18 - 07/30/18 8 26 15 +/- 16 07/30/18 - 09/04/18 13 29 20 +/- 9 07/30/18 - 09/04/18 14 22 19 +/- 6 07/30/18 - 09/04/18 11 21 17 +/- 8 09/04/18 - 10/01/18 6 18 11 +/- 7 09/04/18 - 10/01/18 7 17 10 +/- 6 09/04/18 - 10/01/18 8 15 12 +/- 7 10/01/18 - 10/31/18 7 23 14 +/- 10 10/01/18 - 10/31/18 9 19 14 +/- 7 10/01/18 - 10/31/18 8 20 13 +/- 10 C-9 10/31/18 - 12/05/18 8 37 17 +/- 13 10/31/18 - 12/05/18 8 21 14 +/- 8 10/31/18 - 12/05/18 7 22 16 +/- 11 12/05/18 - 01/02/19 10 33 19 +/- 13 12/05/18 - 01/02/19 11 22 16 +/- 8 12/05/18 - 01/02/19 15 22 18 +/- 7 01/02/18 - 01/02/19 5 37 16 +/- 13 01/02/18 - 01/02/19 6 30 14 +/- 10 01/02/18 - 01/02/19 5 26 15 +/- 10

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF E-03 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 10S3 01/02/18 - 04/02/18 64 +/- 21 < 3 < 2 < 3 < 2 < 2 04/02/18 - 07/02/18 107 +/- 31 < 3 < 4 < 4 < 4 < 3 07/02/18 - 10/01/18 58 +/- 19 < 2 < 3 < 3 < 3 < 2 10/01/18 - 01/02/19 61 +/- 15 < 3 < 3 < 3 < 2 < 2 MEAN +/- 2 STD DEV 73 +/- 46 - - - - -

11S1 01/02/18 - 04/02/18 69 +/- 24 < 3 < 4 < 4 < 4 < 4 04/02/18 - 07/02/18 83 +/- 19 < 3 < 3 < 2 < 2 < 2 07/02/18 - 10/01/18 57 +/- 19 < 3 < 2 < 2 < 2 < 2 10/01/18 - 01/02/19 53 +/- 19 < 1 < 2 < 2 < 2 < 2 MEAN +/- 2 STD DEV 65 +/- 27 - - - - -

13S4 01/02/18 - 04/02/18 96 +/- 38 < 4 < 4 < 3 < 4 < 4 04/02/18 - 07/02/18 151 +/- 26 < 3 < 3 < 3 < 3 < 3 07/02/18 - 10/01/18 79 +/- 28 < 4 < 3 < 5 < 3 < 3 10/01/18 - 01/02/19 70 +/- 17 < 3 < 2 < 3 < 2 < 2 MEAN +/- 2 STD DEV 99 +/- 73 - - - - -

14S1 01/02/18 - 04/02/18 70 +/- 17 < 2 < 2 < 2 < 3 < 2 04/02/18 - 07/02/18 52 +/- 23 < 3 < 3 < 3 < 3 < 2 07/02/18 - 10/01/18 65 +/- 28 < 3 < 2 < 2 < 2 < 2 10/01/18 - 01/02/19 54 +/- 16 < 3 < 3 < 3 < 3 < 3 MEAN +/- 2 STD DEV 60 +/- 17 - - - - -

15D1 01/02/18 - 04/02/18 57 +/- 17 < 3 < 3 < 1 < 2 < 2 04/02/18 - 07/02/18 49 +/- 29 < 2 < 3 < 3 < 3 < 2 07/02/18 - 10/01/18 69 +/- 24 < 2 < 3 < 3 < 2 < 2 10/01/18 - 01/02/19 35 +/- 19 < 2 < 3 < 3 < 2 < 3 MEAN +/- 2 STD DEV 52 +/- 28 - - - - -

22G1 01/02/18 - 04/02/18 68 +/- 18 < 3 < 4 < 3 < 3 < 3 04/02/18 - 07/02/18 63 +/- 37 < 3 < 4 < 4 < 4 < 4 07/02/18 - 10/01/18 67 +/- 20 < 2 < 3 < 3 < 2 < 2 10/01/18 - 01/02/19 53 +/- 18 < 3 < 3 < 3 < 2 < 3 MEAN +/- 2 STD DEV 63 + 14 - - - - -

6C1 01/02/18 - 04/02/18 61 +/- 16 < 2 < 2 < 2 < 2 < 2 04/09/18 - 07/02/18 57 +/- 28 < 2 < 2 < 2 < 2 < 2 07/02/18 - 10/01/18 62 +/- 19 < 2 < 3 < 2 < 2 < 2 10/01/18 - 01/02/19 43 +/- 16 < 2 < 2 < 3 < 3 < 3 MEAN +/- 2 STD DEV 56 +/- 18 - - - - -

THE MEAN AND 2-STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-10

Table C-VI.1 CONCENTRATIONS OF I-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF E-03 PCI/CU METER + 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD 10S3 11S1 13S4 14S1 6C1 15D1 22G1 01/02/18 - 01/08/18 < 48 < 49 < 31 < 35 < 48 < 34 < 25 01/08/18 - 01/16/18 < 35 < 35 < 25 < 28 < 35 < 27 < 26 01/16/18 - 01/22/18 < 58 < 59 < 57 < 63 < 58 < 62 < 55 01/22/18 - 01/29/18 < 42 < 43 < 22 < 25 < 42 < 25 < 24 01/29/18 - 02/05/18 < 57 < 58 < 45 < 45 < 57 < 44 < 39 02/05/18 - 02/13/18 < 30 < 30 < 30 < 34 < 30 < 33 < 31 02/13/18 - 02/19/18 < 48 < 48 < 34 < 38 < 47 < 38 < 36 02/19/18 - 02/26/18 < 40 < 41 < 26 < 29 < 40 < 29 < 28 02/26/18 - 03/06/18 < 30 < 29 < 19 < 22 < 30 < 21 < 20 03/06/18 - 03/12/18 < 51 < 50 < 39 < 37 < 51 < 36 < 26 03/12/18 - 03/20/18 < 34 < 35 < 25 < 28 < 34 < 28 < 9 03/20/18 - 03/26/18 < 38 < 39 < 19 < 21 < 38 < 20 < 18 03/26/18 - 04/02/18 < 39 < 40 < 31 < 29 < 39 < 28 < 26 04/02/18 - 04/09/18 < 25 < 25 < 24 < 25 (1) < 25 < 19 04/09/18 - 04/16/18 < 32 < 33 < 31 < 34 < 14 < 34 < 31 04/16/18 - 04/23/18 < 30 < 30 < 21 < 20 < 30 < 20 < 15 04/23/18 - 04/30/18 < 26 < 26 < 32 < 27 < 22 < 15 < 32 04/30/18 - 05/07/18 < 42 < 43 < 50 < 44 < 36 < 21 < 45 05/07/18 - 05/14/18 < 48 < 49 < 64 < 48 < 48 < 59 < 23 05/14/18 - 05/21/18 < 38 < 38 < 38 < 39 < 39 < 40 < 38 05/21/18 - 05/29/18 < 20 < 21 < 24 < 22 < 20 < 22 < 9 05/29/18 - 06/05/18 < 52 < 53 < 58 < 54 < 52 < 52 < 49 06/05/18 - 06/11/18 < 50 < 51 < 52 < 50 < 50 < 56 < 55 06/11/18 - 06/18/18 < 29 < 30 < 24 < 29 < 29 < 25 < 25 06/18/18 - 06/25/18 < 16 < 16 < 22 < 16 < 16 < 21 < 21 06/25/18 - 07/02/18 < 62 < 63 < 68 < 62 < 26 < 50 < 56 07/02/18 - 07/09/18 < 21 < 21 < 42 < 21 < 21 < 36 < 41 07/09/18 - 07/16/18 < 32 < 32 < 57 < 32 < 32 < 44 < 44 07/16/18 - 07/23/18 < 44 < 44 < 29 < 44 < 44 < 26 < 26 07/23/18 - 07/30/18 < 29 < 29 < 47 < 29 < 29 < 42 < 42 07/30/18 - 08/06/18 < 20 < 20 < 30 < 28 < 17 < 28 < 28 08/06/18 - 08/13/18 < 16 < 16 < 19 < 19 < 13 < 19 < 21 08/13/18 - 08/20/18 < 43 < 43 < 36 < 42 < 42 < 36 < 35 08/20/18 - 08/28/18 < 45 < 45 < 41 < 41 < 19 < 43 < 44 08/28/18 - 09/04/18 < 59 < 59 < 34 < 59 < 58 < 67 < 64 09/04/18 - 09/11/18 < 42 < 42 < 64 < 42 < 41 < 69 < 69 09/11/18 - 09/18/18 < 53 < 53 < 52 < 21 < 53 < 50 < 50 09/18/18 - 09/24/18 < 30 < 30 < 61 < 30 < 30 < 54 < 54 09/24/18 - 10/01/18 < 29 < 29 < 34 < 29 < 29 < 37 < 36 10/01/18 - 10/09/18 < 67 < 67 < 60 < 66 < 66 < 60 < 61 10/09/18 - 10/15/18 < 65 < 65 < 50 < 49 < 35 < 49 < 49 10/15/18 - 10/22/18 < 60 < 60 < 50 < 41 < 59 < 50 < 50 10/22/18 - 10/31/18 < 49 < 49 < 29 < 49 < 49 < 31 < 31 10/31/18 - 11/05/18 < 31 < 32 < 19 < 32 < 31 < 20 < 20 11/05/18 - 11/12/18 < 20 < 20 < 13 < 19 < 19 < 12 < 12 11/12/18 - 11/19/18 < 47 < 47 < 51 < 50 < 47 < 49 < 49 11/19/18 - 11/26/18 < 40 < 40 < 44 < 40 (1) < 43 < 42 11/26/18 - 12/05/18 < 40 < 40 < 45 < 18 < 17 < 43 < 46 12/05/18 - 12/11/18 < 64 < 64 < 51 < 64 < 64 < 47 < 38 12/11/18 - 12/18/18 < 54 < 54 < 66 < 53 < 53 < 61 < 61 12/18/18 - 12/26/18 < 49 < 49 < 18 < 49 < 49 < 49 < 52 12/26/18 - 01/02/19 < 61 < 61 < 14 < 61 < 60 < 39 < 39 MEAN - - - - - - -

(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-11

Table C-VII.1 CONCENTRATIONS OF I-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION CONTROL FARM INDICATOR FARM PERIOD 23F1 36E1 18E1 19B1 25C1 01/16/18 < 0.6 < 0.5 (1) < 0.6 < 0.7 02/14/18 < 0.5 (1) < 0.9 < 0.4 03/06/18 < 0.7 (1) < 0.7 < 0.6 04/03/18 < 0.3 < 0.8 (1) < 0.5 < 0.7 04/17/18 < 0.5 < 0.5 < 0.8 < 0.8 05/01/18 < 0.6 < 0.7 < 0.6 < 0.6 05/15/18 < 0.6 < 0.7 < 0.6 < 0.8 05/29/18 < 0.3 < 0.5 < 0.3 < 0.6 06/12/18 < 0.5 < 0.7 < 0.6 < 0.8 06/26/18 < 0.5 < 0.8 < 0.9 < 0.8 07/09/18 < 0.5 < 0.7 < 0.5 < 0.5 < 0.2 07/24/18 < 0.7 < 0.4 < 0.5 < 0.8 08/07/18 < 0.8 < 0.8 < 0.5 < 0.6 08/21/18 < 0.6 < 0.6 < 0.6 < 0.8 09/04/18 < 0.7 < 0.6 < 0.8 < 0.8 09/18/18 < 1.0 < 0.7 < 0.7 < 0.8 10/02/18 < 0.7 < 0.7 < 0.6 < 0.5 < 0.6 10/16/18 < 0.4 < 0.4 < 0.4 < 0.6 10/31/18 < 0.9 < 0.7 < 0.8 < 1.0 11/13/18 < 0.6 < 0.6 < 0.6 < 0.8 11/26/18 < 0.4 < 0.6 < 0.6 < 0.7 12/11/18 < 0.6 < 0.5 < 0.7 < 0.5 MEAN - - - - -

(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-12

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140

` 18E1 01/16/18 (1) 02/14/18 (1) 03/06/18 (1) 04/17/18 1003 +/- 206 < 8 < 7 < 21 < 7 05/01/18 1197 +/- 145 < 6 < 7 < 39 < 15 05/15/18 1244 +/- 150 < 6 < 6 < 25 < 9 05/29/18 1176 +/- 157 < 7 < 7 < 37 < 14 06/12/18 1188 +/- 135 < 6 < 6 < 27 < 8 06/26/18 1334 +/- 200 < 9 < 9 < 49 < 13 07/09/18 1212 +/- 159 < 6 < 7 < 24 < 7 07/24/18 1096 +/- 198 < 7 < 9 < 30 < 12 08/07/18 1331 +/- 214 < 9 < 9 < 29 < 12 08/21/18 1354 +/- 177 < 7 < 5 < 29 < 8 09/04/18 1308 +/- 154 < 7 < 8 < 30 < 11 09/18/18 1208 +/- 165 < 8 < 8 < 48 < 12 10/02/18 1266 +/- 138 < 5 < 7 < 37 < 12 10/16/18 1347 +/- 214 < 6 < 9 < 37 < 15 10/31/18 1132 +/- 180 < 7 < 7 < 31 < 13 11/13/18 1165 +/- 140 < 6 < 7 < 49 < 15 11/26/18 1273 +/- 167 < 7 < 7 < 32 < 6 12/11/18 1197 +/- 151 < 6 < 7 < 27 < 7 MEAN +/- 2 STD DEV 1224 +/- 188 - - - -

19B1 01/16/18 1262 +/- 149 < 6 < 6 < 40 < 11 02/14/18 1176 +/- 191 < 7 < 9 < 46 < 13 03/06/18 1201 +/- 174 < 7 < 6 < 23 < 13 04/03/18 1210 +/- 141 < 6 < 6 < 21 < 6 04/17/18 1287 +/- 161 < 6 < 6 < 25 < 6 05/01/18 1180 +/- 126 < 5 < 5 < 36 < 12 05/15/18 1151 +/- 104 < 4 < 5 < 20 < 7 05/29/18 1206 +/- 174 < 6 < 7 < 35 < 8 06/12/18 1276 +/- 169 < 6 < 8 < 24 < 10 06/26/18 1251 +/- 161 < 6 < 7 < 36 < 12 07/09/18 1331 +/- 178 < 7 < 9 < 33 < 12 07/24/18 1193 +/- 158 < 7 < 7 < 26 < 7 08/07/18 1059 +/- 210 < 9 < 9 < 38 < 10 08/21/18 1204 +/- 193 < 10 < 11 < 38 < 14 09/04/18 1301 +/- 154 < 8 < 7 < 27 < 6 09/18/18 1420 +/- 191 < 7 < 7 < 43 < 10 10/02/18 1465 +/- 210 < 9 < 9 < 57 < 10 10/16/18 1248 +/- 200 < 8 < 7 < 38 < 12 10/31/18 1224 +/- 150 < 7 < 9 < 40 < 13 11/13/18 1144 +/- 164 < 6 < 7 < 43 < 13 11/26/18 1359 +/- 189 < 7 < 8 < 37 < 10 12/11/18 1277 +/- 153 < 5 < 6 < 19 < 6 MEAN +/- 2 STD DEV 1247 +/- 184 - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-13

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 23F1 01/16/18 1345 +/- 157 < 7 < 7 < 41 < 9 02/14/18 1262 +/- 164 < 11 < 9 < 60 < 13 03/06/18 1281 +/- 214 < 7 < 9 < 42 < 7 04/03/18 1376 +/- 220 < 6 < 7 < 31 < 9 04/17/18 1137 +/- 164 < 6 < 7 < 34 < 10 05/01/18 1377 +/- 165 < 6 < 7 < 41 < 13 05/15/18 1228 +/- 115 < 5 < 5 < 24 < 5 05/29/18 1271 +/- 154 < 6 < 7 < 32 < 11 06/12/18 1139 +/- 166 < 6 < 6 < 29 < 10 06/26/18 1460 +/- 194 < 7 < 7 < 35 < 7 07/09/18 1414 +/- 168 < 6 < 8 < 25 < 8 07/24/18 1174 +/- 212 < 8 < 10 < 39 < 10 08/07/18 1514 +/- 182 < 7 < 8 < 28 < 8 08/21/18 1259 +/- 193 < 7 < 8 < 32 < 10 09/04/18 1502 +/- 191 < 6 < 8 < 29 < 9 09/18/18 1450 +/- 153 < 7 < 7 < 40 < 13 10/02/18 1191 +/- 176 < 6 < 7 < 56 < 15 10/16/18 1394 +/- 194 < 7 < 8 < 48 < 14 10/31/18 1430 +/- 208 < 7 < 7 < 38 < 10 11/13/18 1182 +/- 151 < 8 < 8 < 45 < 15 11/26/18 743 +/- 168 < 5 < 9 < 31 < 12 12/11/18 1547 +/- 187 < 8 < 6 < 27 < 7 MEAN +/- 2 STD DEV 1303 +/- 355 - - - -

25C1 01/16/18 1254 +/- 161 < 7 < 8 < 41 < 15 02/14/18 1372 +/- 178 < 6 < 7 < 36 < 13 03/06/18 1172 +/- 190 < 8 < 9 < 36 < 12 04/03/18 1089 +/- 172 < 5 < 6 < 20 < 10 04/17/18 1130 +/- 191 < 7 < 7 < 27 < 10 05/01/18 1267 +/- 142 < 5 < 7 < 44 < 8 05/15/18 1277 +/- 51 < 2 < 2 < 8 < 3 05/29/18 1194 +/- 180 < 6 < 8 < 40 < 15 06/12/18 1377 +/- 161 < 6 < 7 < 32 < 10 06/26/18 1312 +/- 202 < 8 < 9 < 52 < 13 07/09/18 1261 +/- 203 < 6 < 9 < 35 < 10 07/24/18 1208 +/- 152 < 8 < 8 < 25 < 8 08/07/18 1332 +/- 189 < 6 < 7 < 29 < 7 08/21/18 1126 +/- 162 < 7 < 7 < 29 < 10 09/04/18 1056 +/- 186 < 6 < 10 < 32 < 8 09/18/18 1169 +/- 207 < 7 < 6 < 33 < 9 10/02/18 1344 +/- 122 < 6 < 5 < 36 < 12 10/16/18 979 +/- 145 < 8 < 9 < 48 < 15 10/31/18 1208 +/- 162 < 7 < 8 < 31 < 10 11/13/18 1053 +/- 171 < 7 < 10 < 45 < 13 11/26/18 1124 +/- 166 < 7 < 8 < 33 < 12 12/11/18 970 +/- 112 < 5 < 5 < 20 < 5 MEAN +/- 2 STD DEV 1194 +/- 240 - - - -

36E1 01/16/18 1103 +/- 128 < 5 < 6 < 24 < 7 04/03/18 1017 +/- 224 < 8 < 9 < 29 < 12 07/09/18 1357 +/- 181 < 6 < 7 < 26 < 9 10/02/18 1119 +/- 167 < 6 < 7 < 25 < 9 MEAN +/- 2 STD DEV 1149 +/- 291 - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-14

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 I-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 11S3 06/26/18 Cabbage Leaves 281 +/- 194 5466 +/- 715 < 25 < 32 < 37 < 56 < 30 < 22 < 673 < 61 < 120 06/26/18 Collard Leaves < 266 5856 +/- 617 < 26 < 28 < 32 < 54 < 24 < 29 < 577 < 52 < 84 06/26/18 Kale Leaves 369 +/- 251 5874 +/- 617 < 30 < 27 < 37 < 50 < 23 < 24 < 540 < 49 < 119 07/24/18 Cabbage Leaves 447 +/- 209 3212 +/- 514 < 23 < 28 < 23 < 33 < 23 < 21 < 553 92 +/- 42 < 103 07/24/18 Collard Leaves 551 +/- 211 4272 +/- 531 < 21 < 23 < 24 < 29 < 21 < 28 < 617 < 49 < 88 07/24/18 Kale Leaves 330 +/- 197 3039 +/- 421 < 21 < 22 < 16 < 22 < 23 < 20 < 484 < 41 < 79 08/21/18 Cabbage Leaves 1231 +/- 288 3746 +/- 549 < 28 < 30 < 33 < 45 < 27 < 31 < 538 < 51 < 105 08/21/18 Collard Leaves 457 +/- 238 3340 +/- 600 < 29 < 31 < 33 < 57 < 27 < 28 < 581 < 56 < 132 08/21/18 Kale Leaves 543 +/- 278 3929 +/- 494 < 25 < 27 < 30 < 54 < 24 < 23 < 678 < 39 < 104 09/20/18 Eggplant Leaves 2526 +/- 156 4556 +/- 301 < 14 < 14 < 16 < 24 < 12 < 14 < 314 < 24 < 60 09/20/18 Collard Leaves 1116 +/- 142 4214 +/- 279 < 14 < 14 < 16 < 23 < 14 < 15 < 300 < 22 < 58 09/20/18 Kale Leaves 665 +/- 124 5347 +/- 362 < 17 < 16 < 18 < 25 < 14 < 17 < 353 < 27 < 65 10/25/18 Eggplant Leaves 1393 +/- 398 5039 +/- 760 < 35 < 30 < 41 < 45 < 32 < 37 < 886 < 54 < 165 MEAN +/- 2 STD DEV 826 +/- 1304 4453 +/- 1984 - - - - - - - 92 +/- 0 -

13S3 06/26/18 Cabbage Leaves 633 +/- 87 4506 +/- 254 < 11 < 10 < 12 < 21 < 9 < 10 < 183 17 +/- 14 < 41 06/26/18 Collard Leaves < 335 7018 +/- 837 < 37 < 34 < 55 < 57 < 28 < 36 2032 +/- 754 < 61 < 152 06/26/18 Kale Leaves 511 +/- 205 5234 +/- 656 < 30 < 30 < 39 < 56 < 22 < 26 2141 +/- 652 < 47 < 109 07/24/18 Eggplant Leaves 6255 +/- 318 6678 +/- 438 < 14 < 13 < 18 < 21 < 14 < 16 5105 +/- 654 53 +/- 29 < 77 07/24/18 Collard Leaves 608 +/- 218 4748 +/- 584 < 28 < 22 < 36 < 32 < 25 < 23 1891 +/- 711 < 52 < 134 C-15 07/24/18 Kale Leaves 586 +/- 197 2980 +/- 531 < 25 < 25 < 38 < 29 < 21 < 30 1141 +/- 693 < 50 < 123 08/21/18 Eggplant Leaves 2616 +/- 310 7006 +/- 592 < 30 < 30 < 35 < 60 < 31 < 33 1500 +/- 702 114 +/- 51 < 139 08/21/18 Collard Leaves 1794 +/- 335 4902 +/- 644 < 29 < 28 < 36 < 51 < 29 < 33 3008 +/- 762 < 65 < 132 08/21/18 Kale Leaves 801 +/- 310 3920 +/- 527 < 26 < 27 < 34 < 56 < 25 < 29 743 +/- 584 < 51 < 116 09/20/18 Rhubarb Leaves 798 +/- 176 4093 +/- 311 < 18 < 18 < 21 < 28 < 17 < 20 < 343 < 28 < 78 09/20/18 Collard Leaves 1472 +/- 291 3716 +/- 572 < 31 < 33 < 41 < 53 < 28 < 28 826 +/- 649 < 59 < 126 09/20/18 Kale Leaves 648 +/- 256 3335 +/- 512 < 22 < 18 < 31 < 35 < 19 < 17 908 +/- 592 < 43 < 79 10/25/18 Rhubarb Leaves 946 +/- 354 5525 +/- 829 < 35 < 49 < 41 < 58 < 40 < 44 < 655 < 70 < 179 10/25/18 Collard Leaves 360 +/- 162 3791 +/- 470 < 20 < 26 < 32 < 35 < 22 < 28 < 465 < 42 < 89 MEAN +/- 2 STD DEV 1387 +/- 3186 4818 +/- 2663 - - - - - - 1929 +/- 2648 61 +/- 99 -

35G1 06/26/18 Cabbage Leaves < 265 3730 +/- 606 < 24 < 26 < 28 < 48 < 18 < 25 < 566 < 48 < 102 06/26/18 Broccoli Leaves 389 +/- 154 3390 +/- 435 < 21 < 21 < 23 < 36 < 17 < 14 < 448 < 30 < 93 06/26/18 Kale Leaves < 308 6484 +/- 787 < 25 < 25 < 38 < 49 < 24 < 26 < 642 < 50 < 148 07/24/18 Cabbage Leaves 828 +/- 264 4080 +/- 578 < 22 < 24 < 26 < 24 < 21 < 20 < 590 < 44 < 123 07/24/18 Broccoli Leaves 1521 +/- 268 4330 +/- 567 < 22 < 20 < 34 < 26 < 21 < 21 < 593 < 42 < 122 07/24/18 Cauliflower Leaves 629 +/- 255 3470 +/- 637 < 28 < 29 < 36 < 36 < 27 < 25 < 746 < 51 < 157 08/21/18 Cucumber Leaves 3585 +/- 369 5538 +/- 592 < 23 < 25 < 33 < 53 < 24 < 20 < 612 < 39 < 135 08/21/18 Squash Leaves 1832 +/- 225 4278 +/- 449 < 23 < 19 < 25 < 42 < 17 < 21 < 419 < 34 < 82 08/21/18 Corn Leaves 3845 +/- 387 4073 +/- 543 < 25 < 24 < 30 < 55 < 26 < 29 972 +/- 604 < 53 < 100 09/20/18 Eggplant Leaves 4757 +/- 429 5745 +/- 568 < 21 < 18 < 26 < 42 < 23 < 24 < 527 < 39 < 100 09/20/18 Rhubarb Leaves 914 +/- 276 3199 +/- 599 < 29 < 31 < 41 < 49 < 26 < 27 < 694 < 50 < 109 09/20/18 Pepper Leaves 2715 +/- 331 9051 +/- 701 < 14 < 15 < 20 < 29 < 16 < 15 < 390 50 +/- 34 < 72 MEAN +/- 2 STD DEV 2102 +/- 3070 4781 +/- 3376 - - - - - - 972 +/- 0 50 +/- 0 -

THE MEAN AND 2-STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-IX.1 QUARTERLY DLR RESULTS FOR LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF MILLIROENTGEN/STANDARD MONTH +/- 2 STANDARD DEVIATIONS STATION MEAN CODE +/- 2 S.D. JAN - MAR APR - JUN JUL - SEP OCT - DEC 2E1 5.0 +/- 0.6 5.4 +/- 0.6 5.1 +/- 0.5 5.0 +/- 0.9 4.7 +/- 0.8 3S1 4.8 +/- 0.7 5.3 +/- 0.3 4.9 +/- 1.1 4.7 +/- 0.9 4.5 +/- 0.4 4E1 3.5 +/- 0.5 3.8 +/- 0.9 3.5 +/- 0.9 3.6 +/- 0.4 3.1 +/- 0.3 5H1 6.3 +/- 0.6 6.4 +/- 0.9 6.3 +/- 0.6 6.6 +/- 1.1 5.9 +/- 0.9 5S1 5.6 +/- 0.6 6.0 +/- 0.7 5.6 +/- 0.6 5.6 +/- 1.1 5.3 +/- 0.6 6C1 4.9 +/- 0.6 4.7 +/- 0.6 5.0 +/- 0.4 5.3 +/- 0.6 4.6 +/- 0.4 7E1 5.2 +/- 0.8 5.7 +/- 0.5 5.1 +/- 0.5 5.3 +/- 0.7 4.8 +/- 0.6 7S1 5.2 +/- 1.0 5.9 +/- 0.4 5.0 +/- 0.8 5.3 +/- 0.6 4.7 +/- 0.6 9C1 4.9 +/- 0.9 5.5 +/- 0.2 4.6 +/- 0.7 4.9 +/- 0.4 4.5 +/- 0.4 10E1 5.2 +/- 0.3 5.4 +/- 1.0 5.2 +/- 0.9 5.1 +/- 1.0 5.2 +/- 2.4 10F3 5.1 +/- 0.3 5.1 +/- 0.4 5.2 +/- 0.5 5.1 +/- 0.4 4.9 +/- 0.6 10S3 5.1 +/- 0.5 5.4 +/- 0.7 5.0 +/- 0.7 5.1 +/- 0.4 4.9 +/- 0.7 11S1 6.0 +/- 0.1 6.1 +/- 0.5 5.9 +/- 0.6 6.0 +/- 0.5 6.0 +/- 0.8 13C1 3.6 +/- 0.7 4.1 +/- 0.5 3.4 +/- 0.5 3.3 +/- 0.6 3.4 +/- 0.4 13E1 5.3 +/- 0.4 5.6 +/- 0.5 5.2 +/- 0.6 5.2 +/- 0.6 5.3 +/- 0.8 13S2 7.7 +/- 0.8 7.8 +/- 0.8 7.4 +/- 0.8 7.4 +/- 0.8 8.2 +/- 1.4 14S1 4.8 +/- 0.6 5.1 +/- 0.8 5.1 +/- 2.8 4.5 +/- 0.5 4.7 +/- 2.0 15D1 5.4 +/- 0.5 5.8 +/- 0.3 5.3 +/- 1.0 5.3 +/- 1.2 5.3 +/- 0.7 16F1 5.3 +/- 0.4 5.6 +/- 0.4 5.2 +/- 0.7 5.2 +/- 0.4 5.2 +/- 1.0 17B1 4.7 +/- 0.3 4.9 +/- 0.6 4.6 +/- 0.9 4.7 +/- 0.5 4.7 +/- 0.5 18S2 5.6 +/- 0.3 5.8 +/- 0.5 5.6 +/- 0.9 5.6 +/- 0.5 5.5 +/- 0.5 19D1 4.6 +/- 0.7 5.1 +/- 0.5 4.5 +/- 0.9 4.4 +/- 0.9 4.6 +/- 0.6 20D1 4.5 +/- 0.6 5.0 +/- 0.4 4.4 +/- 0.9 4.5 +/- 0.7 4.2 +/- 0.7 20F1 4.9 +/- 0.5 5.3 +/- 0.9 4.8 +/- 1.2 4.9 +/- 0.5 4.7 +/- 0.5 21S2 4.6 +/- 0.5 4.9 +/- 0.6 4.6 +/- 1.1 4.6 +/- 0.5 4.3 +/- 0.6 23S2 4.3 +/- 0.6 4.7 +/- 0.5 4.0 +/- 0.6 4.5 +/- 0.3 4.2 +/- 0.8 24D1 4.0 +/- 0.6 4.2 +/- 0.8 4.1 +/- 0.4 4.1 +/- 0.5 3.6 +/- 0.5 25D1 3.9 +/- 0.6 4.3 +/- 0.5 3.8 +/- 1.2 3.6 +/- 0.5 3.9 +/- 0.5 25S2 4.0 +/- 0.7 4.1 +/- 1.0 3.7 +/- 1.0 4.5 +/- 1.0 3.9 +/- 1.4 26S3 4.3 +/- 0.5 4.7 +/- 0.5 4.4 +/- 1.1 4.2 +/- 0.5 4.1 +/- 0.4 28D2 4.2 +/- 0.6 4.5 +/- 0.7 3.9 +/- 1.5 4.5 +/- 0.8 4.1 +/- 0.6 29E1 4.4 +/- 0.3 4.5 +/- 0.8 4.4 +/- 1.2 4.5 +/- 0.5 4.2 +/- 1.2 29S1 4.4 +/- 0.5 4.7 +/- 1.2 4.2 +/- 1.0 4.4 +/- 0.9 4.2 +/- 0.7 31D1 6.0 +/- 0.5 6.3 +/- 1.0 5.8 +/- 0.9 6.2 +/- 0.7 5.7 +/- 0.8 31D2 5.0 +/- 0.9 5.5 +/- 0.4 4.9 +/- 0.7 5.2 +/- 0.6 4.5 +/- 1.1 31S1 5.4 +/- 0.7 5.8 +/- 0.4 5.2 +/- 0.4 5.5 +/- 0.4 5.1 +/- 0.7 34E1 4.8 +/- 0.8 5.2 +/- 0.3 4.7 +/- 0.8 5.0 +/- 0.6 4.3 +/- 0.5 34S2 4.8 +/- 0.5 5.0 +/- 0.8 5.0 +/- 0.7 4.9 +/- 0.8 4.5 +/- 0.6 36D1 4.1 +/- 0.6 4.4 +/- 0.6 4.1 +/- 0.4 4.2 +/- 0.7 3.7 +/- 0.3 36S2 5.0 +/- 1.0 5.4 +/- 0.6 5.1 +/- 1.0 5.3 +/- 0.3 4.3 +/- 1.1 C-16

Table C-IX.2 MEAN QUARTERLY DLR RESULTS FOR THE SITE BOUNDARY, MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF MILLIROENTGEN/STANDARD MONTH

+/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION SITE BOUNDARY MIDDLE CONTROL PERIOD +/- 2 S.D. +/- 2 S.D. +/- 2 S.D.

JAN-MAR 5.4 +/- 1.7 5.0 +/- 1.3 6.4 +/- 0 APR-JUN 5.0 +/- 1.8 4.6 +/- 1.3 6.3 +/- 0 JUL-SEP 5.1 +/- 1.6 4.7 +/- 1.3 6.6 +/- 0 OCT-DEC 4.9 +/- 2.1 4.5 +/- 1.3 5.9 +/- 0 Table C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF MILLIROENTGEN/STANDARD MONTH

+/- 2 STANDARD DEVIATIONS OF THE STATION DATA SAMPLES PERIOD PERIOD PERIOD MEAN LOCATION ANALYZED MINIMUM MAXIMUM +/- 2 S.D.

SITE BOUNDARY 128 3.7 8.2 5.1 +/- 1.8 MIDDLE 184 3.1 6.3 4.7 +/- 1.3 CONTROL 8 5.9 6.6 6.3 +/- 0.6 SITE BOUNDARY STATIONS - 10S3, 11S1, 13S2, 14S1, 18S2, 21S2, 23S2, 25S2, 26S3, 29S1, 31S1, 34S2, 36S2, 3S1, 5S1, 7S1 MIDDLE STATIONS - 10E1, 10F3, 13C1, 13E1, 15D1, 16F1, 17B1, 19D1, 20D1, 20F1, 24D1, 25D1 28D2, 29E1, 2E1, 31D1, 31D2, 34E1, 36D1, 4E1, 6C1, 7E1, 9C1 CONTROL STATIONS - 5H1 C-17

FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2018 12 10 8

C-18 6 pCi/liter 4

2 CONTROL INDICATOR 0

82 88 94 00 06 12 19 YEAR Note: 2005 analysis changed from Insoluble & Soluble to Total Gross Beta LGS CRITICALITY UNIT NO. 1: 12/22/84 LGS CHANGED TO TOTAL GROSS BETA AT THE BEGINNING OF 2005.

UNIT NO. 2: 08/11/89 PREVIOUS DATA INCLUDED SUMMATION OF LESS THAN VALUES.

FIGURE C-2 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2018 150 Group I 135 Group II 120 Group III Chernobyl 105 90 C-19 75 LGS CRITICALITY 60 UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/11/89 E-03 pCi/cubic meter 45 30 15 0

82 89 96 04 11 19 YEAR

FIGURE C-3 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2018 50 GROUP I GROUP II GROUP III 40 30 C-20 E-03 pCi/cubic meter 20 10 0

4 8 12 16 20 24 28 32 36 40 44 48 52 WEEK NO.

FIGURE C-4 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (DLR)

IN THE VICINITY OF LGS, 1985 - 2018 NOTE: Control Station 5H1 became the only distant location beginning in 1995 13 SITE 12 INTERMEDIATE CONTROL 11 Control 5H1 10 9

C-21 8

7 milli-Roentgen/std. mo.

6 5

4 85 93 02 10 19 YEAR

Intentionally left blank APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

Intentionally left blank TABLE D-I.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 01/02/18 - 01/29/18 2.6 +/- 0.7 01/29/18 - 02/26/18 1.4 +/- 0.6 02/26/18 - 04/02/18 1.9 +/- 0.7 04/02/18 - 04/30/18 1.4 +/- 0.6 04/30/18 - 05/29/18 2.5 +/- 0.7 05/29/18 - 07/02/18 2.4 +/- 0.7 07/02/18 - 07/30/18 1.5 +/- 0.6 07/30/18 - 08/28/18 1.6 +/- 0.7 08/28/18 - 10/01/18 1.9 +/- 0.7 10/01/18 - 10/31/18 1.4 +/- 0.6 10/31/18 - 12/05/18 1.3 +/- 0.7 12/05/18 - 01/02/19 1.2 +/- 0.6 MEAN +/- 2 STD DEV 1.8 +/- 1.0 TABLE D-I.2 CONCENTRATIONS OF I-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 01/02/18 - 01/29/18 < 0.6 01/29/18 - 02/26/18 < 0.6 02/26/18 - 04/02/18 < 0.9 04/02/18 - 04/30/18 < 0.7 04/30/18 - 05/29/18 < 0.7 05/29/18 - 07/02/18 < 0.7 07/02/18 - 07/30/18 < 0.7 07/30/18 - 08/28/18 < 0.8 08/28/18 - 10/01/18 < 0.6 10/01/18 - 10/31/18 < 0.6 10/31/18 - 12/05/18 < 0.6 12/05/18 - 01/02/19 < 0.7 MEAN -

TABLE D-I.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 01/02/18 - 04/02/18 < 126 04/02/18 - 07/02/18 < 120 07/02/18 - 10/01/18 < 102 10/01/18 - 01/02/19 < 141 MEAN -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES D-1

TABLE D-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 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 I-131 Cs-134 Cs-137 Ba-140 La-140 16C2 01/02/18 - 01/29/18 < 4 < 5 < 10 < 5 < 9 < 6 < 8 < 5 < 4 < 5 < 17 < 9 01/29/18 - 02/26/18 < 3 < 3 < 7 < 4 < 8 < 4 < 6 < 6 < 3 < 4 < 18 < 6 02/26/18 - 04/02/18 < 3 < 3 < 6 < 3 < 7 < 3 < 5 < 4 < 3 < 3 < 14 < 5 04/02/18 - 04/30/18 < 4 < 4 < 9 < 4 < 8 < 4 < 6 < 8 < 4 < 4 < 20 < 9 04/30/18 - 05/29/18 < 3 < 3 < 6 < 3 < 7 < 4 < 5 < 6 < 3 < 3 < 17 < 5 05/29/18 - 07/02/18 < 3 < 3 < 6 < 3 < 6 < 3 < 5 < 3 < 3 < 3 < 14 < 4 07/02/18 - 07/30/18 < 5 < 6 < 11 < 5 < 11 < 6 < 8 < 14 < 5 < 5 < 30 < 13 07/30/18 - 08/28/18 < 5 < 5 < 11 < 6 < 12 < 6 < 9 < 9 < 6 < 6 < 23 < 11 08/28/18 - 10/01/18 < 4 < 4 < 7 < 4 < 8 < 4 < 6 < 6 < 4 < 4 < 17 < 6 10/01/18 - 10/31/18 < 5 < 5 < 12 < 5 < 11 < 5 < 8 < 8 < 5 < 5 < 21 < 10 10/31/18 - 12/05/18 < 4 < 3 < 8 < 3 < 6 < 4 < 6 < 8 < 3 < 4 < 21 < 7 12/05/18 - 01/02/19 < 3 < 3 < 8 < 3 < 8 < 4 < 6 < 7 < 3 < 4 < 18 < 5 MEAN - - - - - - - - - - - -

D-2

TABLE D-II.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE AND I-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF E-03 PCI/CU METER +/- 2 SIGMA COLLECTION 11S2 11S2 PERIOD GROSS BETA I-131 01/02/18 - 01/08/18 21 +/- 3 < 22 01/08/18 - 01/16/18 22 +/- 3 < 19 01/16/18 - 01/22/18 46 +/- 3 < 32 01/22/18 - 01/29/18 16 +/- 2 < 16 01/29/18 - 02/05/18 20 +/- 2 < 18 02/05/18 - 02/13/18 22 +/- 2 < 15 02/13/18 - 02/19/18 38 +/- 3 < 21 02/19/18 - 02/26/18 15 +/- 2 < 27 02/26/18 - 03/06/18 22 +/- 2 < 11 03/06/18 - 03/12/18 10 +/- 2 < 32 03/12/18 - 03/20/18 20 +/- 2 < 20 03/20/18 - 03/26/18 15 +/- 2 < 21 03/26/18 - 04/02/18 20 +/- 2 < 18 04/02/18 - 04/09/18 17 +/- 2 < 18 04/09/18 - 04/16/18 25 +/- 2 < 19 04/16/18 - 04/23/18 13 +/- 2 < 13 04/23/18 - 04/30/18 14 +/- 2 < 26 04/30/18 - 05/07/18 19 +/- 2 < 25 05/07/18 - 05/14/18 12 +/- 2 < 22 05/14/18 - 05/21/18 12 +/- 2 < 17 05/21/18 - 05/29/18 15 +/- 2 < 12 05/29/18 - 06/05/18 10 +/- 2 < 14 06/05/18 - 06/11/18 14 +/- 2 < 16 06/11/18 - 06/18/18 15 +/- 2 < 16 06/18/18 - 06/25/18 13 +/- 2 < 23 06/25/18 - 07/02/18 23 +/- 2 < 31 07/02/18 - 07/09/18 23 +/- 2 < 17 07/09/18 - 07/16/18 21 +/- 2 < 19 07/16/18 - 07/23/18 17 +/- 2 < 15 07/23/18 - 07/30/18 17 +/- 2 < 23 07/30/18 - 08/06/18 22 +/- 2 < 25 08/06/18 - 08/13/18 33 +/- 3 < 17 08/13/18 - 08/20/18 26 +/- 2 < 17 08/20/18 - 08/28/18 23 +/- 2 < 24 08/28/18 - 09/04/18 27 +/- 2 < 20 09/04/18 - 09/11/18 19 +/- 2 < 17 09/11/18 - 09/18/18 10 +/- 2 < 15 09/18/18 - 09/24/18 19 +/- 2 < 22 09/24/18 - 10/01/18 15 +/- 2 < 18 10/01/18 - 10/09/18 30 +/- 2 < 16 10/09/18 - 10/15/18 14 +/- 2 < 15 10/15/18 - 10/22/18 20 +/- 2 < 32 10/22/18 - 10/31/18 14 +/- 2 < 12 10/31/18 - 11/05/18 22 +/- 3 < 14 11/05/18 - 11/12/18 15 +/- 2 < 23 11/12/18 - 11/19/18 21 +/- 2 < 27 11/19/18 - 11/26/18 28 +/- 2 < 12 11/26/18 - 12/05/18 14 +/- 2 < 13 12/05/18 - 12/11/18 28 +/- 3 < 12 12/11/18 - 12/18/18 28 +/- 3 < 16 12/18/18 - 12/26/18 23 +/- 2 < 11 12/26/18 - 01/02/19 19 +/- 2 < 17 MEAN +/- 2 STD DEV 20 +/- 14 -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES D-3

TABLE D-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF E-03 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 11S2 01/02/18 - 04/02/18 68 +/- 12 < 1.8 < 1.6 < 1.4 < 1.5 < 1.6 04/02/18 - 07/02/18 69 +/- 11 < 1.3 < 1.3 < 1.2 < 1.0 < 1.4 07/02/18 - 10/01/18 68 +/- 14 < 1.7 < 1.9 < 1.5 < 1.5 < 1.4 10/01/18 - 01/02/19 53 +/- 13 < 1.8 < 1.9 < 1.8 < 1.6 < 1.4 MEAN +/- 2 STD DEV 65 +/- 15 - - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES D-4

TABLE D-III.1 CONCENTRATIONS OF I-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD I-131 K-40 Cs-134 Cs-137 Ba-140 La-140 19B1 01/16/08 < 0.6 1430 +/- 87 < 4 < 4 < 19 < 6 02/14/18 < 0.7 1400 +/- 86 < 3 < 4 < 38 < 13 04/03/18 < 1.0 1460 +/- 89 < 4 < 5 < 30 < 9 07/09/18 < 0.8 1340 +/- 85 < 3 < 4 < 14 < 5 10/02/18 < 0.6 1330 +/- 102 < 4 < 5 < 22 < 7 MEAN +/- 2 STD DEV - 1392 +/- 113 - - - -

25C1 01/16/08 < 0.6 1410 +/- 94 < 4 < 5 < 22 < 7 02/14/18 < 0.5 1280 +/- 81 < 3 < 4 < 41 < 14 04/03/18 < 0.9 1310 +/- 85 < 4 < 4 < 29 < 9 07/09/18 < 0.7 1370 +/- 93 < 4 < 5 < 17 < 6 10/02/18 < 0.5 1220 +/- 111 < 5 < 5 < 19 < 7 MEAN +/- 2 STD DEV - 1318 +/- 149 - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES D-5

FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENV AND TBE, 2018 D-6

FIGURE D-2 COMPARISON OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11S1 AND 11S2, 2018 60 11S2 - EIS 50 11S1 - TBE 40 D-7 30 20 E-03 pCi/cubic meter 10 0

1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.

Intentionally left blank APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank Analytics Environmental Radioactivity Cross Check Program TABLE E.1 Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Analytics Result Value March 2018 E12133 Milk Sr-89 pCi/L 76.1 90.1 0.84 A Sr-90 pCi/L 12.2 12.5 0.98 A E12134 Milk Ce-141 pCi/L 77.8 77.0 1.01 A Co-58 pCi/L 105 114 0.92 A Co-60 pCi/L 181 187 0.97 A Cr-51 pCi/L 298 326 0.92 A Cs-134 pCi/L 150 180 0.84 A Cs-137 pCi/L 164 172 0.95 A Fe-59 pCi/L 140 139 1.01 A I-131 pCi/L 105 108.0 0.97 A Mn-54 pCi/L 133 131 1.01 A Zn-65 pCi/L 242 244 0.99 A E12135 Charcoal I-131 pCi 93.7 95.4 0.98 A E12136 AP Ce-141 pCi 92.6 85.3 1.09 A Co-58 pCi 130 126 1.03 A Co-60 pCi 237 207 1.14 A Cr-51 pCi 411 361 1.14 A Cs-134 pCi 194 199 0.98 A Cs-137 pCi 200 191 1.05 A Fe-59 pCi 160 154 1.04 A Mn-54 pCi 152 145 1.05 A Zn-65 pCi 267 271 0.99 A E12137 Water Fe-55 pCi/L 1990 1700 1.17 A E12138 Soil Ce-141 pCi/g 0.148 0.118 1.26 W Co-58 pCi/g 0.171 0.174 0.98 A Co-60 pCi/g 0.297 0.286 1.04 A Cr-51 pCi/g 0.537 0.498 1.08 A Cs-134 pCi/g 0.274 0.275 1.00 A Cs-137 pCi/g 0.355 0.337 1.05 A Fe-59 pCi/g 0.243 0.212 1.15 A Mn-54 pCi/g 0.228 0.201 1.14 A Zn-65 pCi/g 0.395 0.374 1.06 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 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 ratio limits of < 0.70 and > 1.30 (Page 1 of 4)

E-1

Analytics Environmental Radioactivity Cross Check Program TABLE E.1 Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Analytics Result Value June 2018 E12205 Milk Sr-89 pCi/L 74.9 84.6 0.89 A Sr-90 pCi/L 10.5 11.4 0.92 A E12206 Milk Ce-141 pCi/L 89.2 82.2 1.08 A Co-58 pCi/L 94.8 89 1.07 A Co-60 pCi/L 125 113 1.10 A Cr-51 pCi/L 256 239 1.07 A Cs-134 pCi/L 112 114 0.99 A Cs-137 pCi/L 107 98.8 1.08 A Fe-59 pCi/L 95.9 86.0 1.12 A I-131 pCi/L 69.8 71.9 0.97 A Mn-54 pCi/L 138 130 1.06 A Zn-65 pCi/L 186 157 1.18 A E12207 Charcoal I-131 pCi 69.6 72.2 0.96 A E12208 AP Ce-141 pCi 151 165 0.92 A Co-58 pCi 174 178 0.98 A Co-60 pCi 290 227 1.28 W Cr-51 pCi 452 478 0.95 A Cs-134 pCi 215 227 0.95 A Cs-137 pCi 206 198 1.04 A Fe-59 pCi 180 172 1.05 A Mn-54 pCi 265 260 1.02 A Zn-65 pCi 280 315 0.89 A E12209 Water Fe-55 pCi/L 1790 1740 1.03 A E12210 AP Sr-89 pCi 77.8 90.3 0.86 A Sr-90 pCi 9.54 12.2 0.78 W (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 ratio limits of < 0.70 and > 1.30 (Page 2 of 4)

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Analytics Environmental Radioactivity Cross Check Program TABLE E.1 Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Analytics Result Value September 2018 E12271 Milk Sr-89 pCi/L 79.4 81.7 0.97 A Sr-90 pCi/L 12.2 14.8 0.82 A E12272 Milk Ce-141 pCi/L 152 128 1.19 A Co-58 pCi/L 161 144 1.12 A Co-60 pCi/L 208 190 1.10 A Cr-51 pCi/L 244 265 0.92 A Cs-134 pCi/L 124 123 1.01 A Cs-137 pCi/L 166 147 1.13 A Fe-59 pCi/L 158 119 1.32 N(1)

I-131 pCi/L 83.1 58.2 1.43 N(2)

Mn-54 pCi/L 191 167 1.14 A Zn-65 pCi/L 229 201 1.14 A E12273 Charcoal I-131 pCi 83.0 80.7 1.03 A E12274 AP Ce-141 pCi 101 85.6 1.18 A Co-58 pCi 92.7 96.0 0.97 A Co-60 pCi 142 127 1.12 A Cr-51 pCi 218 177 1.23 W Cs-134 pCi 81.2 81.9 0.99 A Cs-137 pCi 99.0 98.5 1.01 A Fe-59 pCi 93.7 79.7 1.18 A Mn-54 pCi 116 112 1.04 A Zn-65 pCi 139 134 1.04 A E12302 Water Fe-55 pCi/L 2120 1820 1.17 A E12276 Soil Ce-141 pCi/g 0.259 0.221 1.17 A Co-58 pCi/g 0.279 0.248 1.12 A Co-60 pCi/g 0.367 0.328 1.12 A Cr-51 pCi/g 0.597 0.457 1.31 N (3)

Cs-134 pCi/g 0.261 0.212 1.23 W Cs-137 pCi/g 0.376 0.330 1.14 A Fe-59 pCi/g 0.248 0.206 1.20 A Mn-54 pCi/g 0.317 0.289 1.10 A Zn-65 pCi/g 0.407 0.347 1.17 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 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 ratio limits of < 0.70 and > 1.30 (1) See NCR 18-20 (2) See NCR 18-24 (3) See NCR 18-21 (Page 3 of 4)

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Analytics Environmental Radioactivity Cross Check Program TABLE E.1 Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Analytics Result Value December 2018 E12313 Milk Sr-89 pCi/L 71.9 91.9 0.78 W Sr-90 pCi/L 12.1 13.3 0.91 A E12314 Milk Ce-141 pCi/L 124 133 0.93 A Co-58 pCi/L 110 119 0.93 A Co-60 pCi/L 202 212 0.95 A Cr-51 pCi/L 292 298 0.98 A Cs-134 pCi/L 146 171 0.85 A Cs-137 pCi/L 118 121 0.98 A Fe-59 pCi/L 120 114 1.05 A I-131 pCi/L 94.2 93.3 1.01 A Mn-54 pCi/L 151 154 0.98 A Zn-65 pCi/L 266 264 1.01 A E12315 Charcoal I-131 pCi 94.8 89.9 1.05 A E12316A AP Ce-141 pCi 92.3 94.0 0.98 A Co-58 pCi 73.4 83.8 0.88 A Co-60 pCi 137 150 0.91 A Cr-51 pCi 202 210 0.96 A Cs-134 pCi 115 121 0.95 A Cs-137 pCi 85.0 85.4 1.00 A Fe-59 pCi 83.1 80.8 1.03 A Mn-54 pCi 104 109 0.96 A Zn-65 pCi 168 187 0.90 A E12317 Water Fe-55 pCi/L 2110 1840 1.15 A E12318 AP Sr-89 pCi 81.1 83.0 0.98 A Sr-90 pCi 11.4 12.0 0.95 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 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 ratio limits of < 0.70 and > 1.30 (Page 4 of 4)

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DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

TABLE E.2 Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Range Value February 2018 18-MaS38 Soil Ni-63 Bq/kg 9.94 (1) A Sr-90 Bq/kg 0.846 (1) A 18-MaW38 Water Am-241 Bq/L 0.785 0.709 0.496 - 0.922 A Ni-63 Bq/L 12.6 14.0 9.8 - 18.2 A Pu-238 Bq/L 0.0214 0.023 (2) A Pu-239/240 Bq/L 0.544 0.600 0.420 - 0.780 A 18-RdF38 AP U-234/233 Bq/sample 0.111 0.124 0.087 - 0.161 A U-238 Bq/sample 0.123 0.128 0.090 - 0.166 A 18-RdV38 Vegetation Cs-134 Bq/sample 2.46 3.23 2.26 - 4.20 W Cs-137 Bq/sample 3.14 3.67 2.57 - 4.77 A Co-57 Bq/sample 4.12 4.42 3.09 - 5.75 A Co-60 Bq/sample 1.86 2.29 1.60 - 2.98 A Mn-54 Bq/sample 2.21 2.66 1.86 - 3.46 A Sr-90 Bq/sample NR(3)

Zn-65 Bq/sample -0.201 (1) A November 2018 18-MaS39 Soil Ni-63 Bq/kg 703 765 536 - 995 A Sr-90 Bq/kg 137 193 135 - 251 W 18-MaW39 Water Am-241 Bq/L 0.0363 (1) A Ni-63 Bq/L 6.18 7.0 4.9 - 9.1 A Pu-238 Bq/L 0.73 0.674 0.472 - 0.876 A Pu-239/240 Bq/L 0.89 0.928 0.650 - 1.206 A 18-RdF39 AP U-234/233 Bq/sample 0.159 0.152 0.106 - 0.198 A U-238 Bq/sample 0.162 0.158 0.111 - 0.205 A 18-RdV39 Vegetation Cs-134 Bq/sample 1.85 1.94 1.36 - 2.52 A Cs-137 Bq/sample 2.5 2.36 1.65 - 3.07 A Co-57 Bq/sample 3.53 3.31 2.32 - 4.30 A Co-60 Bq/sample 1.6 1.68 1.18 - 2.18 A Mn-54 Bq/sample 2.61 2.53 1.77 - 3.29 A Sr-90 Bq/sample 0.338 0.791 0.554 - 1.028 N(4)

Zn-65 Bq/sample 1.32 1.37 0.96 - 1.78 A (a) The MAPEP 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) 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 < 0.70 and > 1.30 (1) False positive test (2) Sensitivity evaluation (3) See NCR 18-09 (4) See NCR 18-25 (Page 1 of 1)

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ERA Environmental Radioactivity Cross Check Program TABLE E.3 Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Limits Value March 2018 MRAD-28 AP GR-A pCi/sample 65.7 43.4 22.7 - 71.5 A GR-B pCi/sample 57.2 52 31.5 - 78.6 A April 2018 RAD-113 Water Ba-133 pCi/L 91.2 91.5 77.1 - 101 A Cs-134 pCi/L 70.4 75.9 62.0 - 83.5 A Cs-137 pCi/L 122 123 111 - 138 A Co-60 pCi/L 64.8 64.3 57.9 - 73.2 A Zn-65 pCi/L 98.6 86.7 78.0 - 104 A GR-A pCi/L 32.8 28.6 14.6 - 37.5 A GR-B pCi/L 62.9 73.7 51.4 - 81.1 A U-Nat pCi/L 6.7 6.93 5.28 - 8.13 A H-3 pCi/L 17100 17200 15000 - 18900 A Sr-89 pCi/L 38.6 48.8 38.3 - 56.2 A Sr-90 pCi/L 27.1 26.5 19.2 - 30.9 A I-131 pCi/L 26.7 24.6 20.4 - 29.1 A September 2018 MRAD-29 AP GR-A pCi/sample 49.7 55.3 28.9 - 91.1 A AP GR-B pCi/sample 75.3 86.5 52.4 - 131 A October 2018 RAD-115 Water Ba-133 pCi/L 15.2 16.3 11.9 - 19.4 A Cs-134 pCi/L 85.9 93.0 76.4 - 102 A Cs-137 pCi/L 229 235 212 - 260 A Co-60 pCi/L 81.9 80.7 72.6 - 91.1 A Zn-65 pCi/L 348 336 302 - 392 A GR-A pCi/L 38.9 60.7 31.8 - 75.4 A GR-B pCi/L 36.5 41.8 27.9 - 49.2 A U-Nat pCi/L 17.48 20.9 16.8 - 23.4 A H-3 pCi/L 2790 2870 2410 - 3170 A I-131 pCi/L 26.9 27.2 22.6 - 32.0 A Sr-89 pCi/L 57.2 56.9 45.5 - 64.6 A Sr-90 pCi/L 36.8 31.4 22.9- 36.4 N(1)

(a) The ERA 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) 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 18-23 (Page 1 of 1)

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TABLE E. Analytics Environmental Radioactivity Cross Check Program Exelon Industrial Services EIS Identification Known Ratio of Analytics Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) to EIS Result Value March 2018 E 12085 Water Gr-B pCi/L 272 275 98.9 Pass E 12086 D4 Charcoal I-131 pCi 85.2 94.3 90.3 Pass E 12084 D3 Milk I-131 pCi/L 106 108 98.1 Pass Ce-141 pCi/L 80.0 77.0 104 Pass Cr-51 pCi/L 317 326 97.2 Pass Cs-134 pCi/L 178 180 98.9 Pass Cs-137 pCi/L 176 172 102 Pass Co-58 pCi/L 118 114 104 Pass Mn-54 pCi/L 140 131 107 Pass Fe-59 pCi/L 148 139 106 Pass Zn-65 pCi/L 264 244 108 Pass Co-60 pCi/L 192 187 103 Pass June 201 E12177 AP Ce-141 pCi/Filter 153 148 103 Pass Cr-51 pCi/Filter 437 429 102 Pass Cs-134 pCi/Filter 193 204 94.6 Pass Cs-137 pCi/Filter 179 178 101 Pass Co-58 pCi/Filter 158 160 98.8 Pass Mn-54 pCi/Filter 236 233 101 Pass Fe-59 pCi/Filter 173 155.0 112 Pass Zn-65 pCi/Filter 268 283 94.7 Pass Co-60 pCi/Filter 200 204 98.0 Pass E12176 Water I-131 pCi/L 77 74 104 Pass Ce-141 pCi/L 90 86 105 Pass Cr-51 pCi/L 259 249 104 Pass Cs-134 pCi/L 101 119 84.9 Pass Cs-137 pCi/L 106 103 103 Pass Co-58 pCi/L 88 93 94.6 Pass Mn-54 pCi/L 132 135 97.8 Pass Fe-59 pCi/L 97 89.7 109 Pass Zn-65 pCi/L 171 164 104 Pass Co-60 pCi/L 112 118 94.9 Pass E12175 Water Gr-B pCi/L 215.9 251 86.0 Pass September 2018 E12245 AP Gr-B pCi 220.3 211 104.4 Pass (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 EIS internal QC limits in accordance with the NRC Resolution Test criteria (Page 1 of 2)

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TABLE E. Analytics Environmental Radioactivity Cross Check Program Exelon Industrial Services EIS Identification Known Ratio of Analytics Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) to EIS Result Value December 201 E12343 Water Gr-B pCi/L 257 295 87.1 Pass E12344 Cartridge I-131 pCi 86.2 89.7 96.1 Pass E12342A AP Ce-141 pCi/Filter 97.9 97.0 101 Pass Cr-51 pCi/Filter 226 217 104 Pass Cs-134 pCi/Filter 112.0 125.0 89.6 Pass Cs-137 pCi/Filter 98.8 88.2 112 Pass Co-58 pCi/Filter 85.7 86.5 99.1 Pass Mn-54 pCi/Filter 123 112.0 110 Pass Fe-59 pCi/Filter 97.9 83.4 117 Pass Zn-65 pCi/Filter 201 193 104 Pass Co-60 pCi/Filter 158 155 102 Pass E12345 Milk I-131 pCi/L 95.8 93.3 103 Pass Ce-141 pCi/L 145 133.0 109 Pass Cr-51 pCi/L 372 298 125 Pass Cs-134 pCi/L 193 171 113 Pass Cs-137 pCi/L 141 121 117 Pass Co-58 pCi/L 123.0 119.0 103 Pass Mn-54 pCi/L 178 154 116 Pass Fe-59 pCi/L 127 114 111 Pass Zn-65 pCi/L 242 264 91.7 Pass Co-60 pCi/L 215 212 101 Pass (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 EIS internal QC limits in accordance with the NRC Resolution Test criteria (Page 2 of 2)

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TABLE E. ERA Environmental Radioactivity Cross Check Program Exelon Industrial Services EIS Acceptance Known Acceptance Month/Year ID Number Matrix Nuclide Units Reported Ratio of ERA Evaluation (b)

Value (a) Limits Value to EIS Result April 2018 RAD-113 Water Ba-133 pCi/L 88.0 91.5 96.2 Pass Cs-134 pCi/L 81.1 75.9 107 Pass Cs-137 pCi/L 131 123 107 Pass Co-60 pCi/L 70.0 64.3 109 Pass Zn-65 pCi/L 95.9 86.7 111 Pass I-131 pCi/L 24.1 24.6 98.0 Pass GR-B pCi/L 64.6 73.7 87.7 Pass July 2018 RAD-114 H-3 pCi/L 215.9 251 86.0 Pass September 201 MRAD-29 AP Am-241 pCi/Filter 52.3 64.1 81.6 Pass Cs-134 pCi/Filter 870 921 94.5 Pass Cs-137 pCi/Filter 403 373 108 Pass Co-60 pCi/Filter 1178 1130 104 Pass Zn-65 pCi/Filter 696 660 105 Pass October 201 RAD-115 Water Ba-133 pCi/L 13.4 16.3 82.2 Pass Cs-134 pCi/L 87.9 93.0 94.5 Pass Cs-137 pCi/L 223.4 235.0 95.1 Pass Co-60 pCi/L 80.2 80.7 99.4 Pass Zn-65 pCi/L 317.8 336 94.6 Pass I-131 pCi/L 28.1 27.2 103 Pass (a) The ERA 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 EIS internal QC limits in accordance with the NRC Resolution Test criteria (Page 1 of 1)

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TABLE E.6 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

GEL Laboratories - H-3 only Identification Reported Known Quarter/Year Matrix Nuclide Units Acceptance Range Evaluation (b)

Number Value Value (a) 2nd/201 18-MaW38 Water H-3 Bq// 1.14 False Positive Test A 4th/201 18-MaW39 Water H-3 Bq// 331 338 237 - 439 A (a) The MAPEP 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) 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 < 0.70 and > 1.30 (Page 1 of 1)

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TABLE E.7 ERA Environmental Radioactivity Cross Check Program GEL Laboratories - H-3 Only Identification Reported Known Acceptance Quarter/Year Matrix Nuclide Units Evaluation (b)

Number Value Value (a) Limits 1st/201 RAD-112 Water H-3 pCi/L 20,000 21,200 18,600 - 23,000 A pCi/L 20,00 21,200 18,600 - 23,000 A 2nd/201 MRAD-26 Water H-3 pCi/L 18,900 19,400 13,000 - 27,700 A 3rd/201 RAD-114 Water H-3 pCi/L 19,900 20,400 17,900 - 22,400 A H-3 pCi/L 21,200 20,400 17,900 - 22,400 A 4th/201 MRAD-27 Water H-3 pCi/L 3,030 3,020 2,280 - 3,680 A (a) The ERA 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) ERA evaluation:

A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (Page 1 of 1)

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Intentionally left blank APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally Left Blank Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 AND 2 Annual Radiological Groundwater Protection Program Report 1 January through 31 December 2018 Prepared By Teledyne Brown Engineering Environmental Services Limerick Power Station Pottstown, PA 19464 April 2019

Intentionally Left Blank Table of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..................................................................................................................... 2 A. Objectives of the RGPP ...................................................................................... 2 B. Implementation of the Objectives ........................................................................ 2 C. Program Description ........................................................................................... 3 D. Characteristics of Tritium (H-3) ........................................................................... 4 III. Program Description ...................................................................................................... 5 A. Sample Analysis .................................................................................................. 5 B. Data Interpretation............................................................................................... 5 C. Background Analysis........................................................................................... 6

1. Background Concentrations of Tritium ..................................................... 6 IV. Results and Discussion ................................................................................................. 8 A. Groundwater Results........................................................................................... 8 B. Surface Water Results ........................................................................................ 9 C. Precipitation Sample Results ............................................................................ 10 D. Drinking Water Well Survey .............................................................................. 10 E. Summary of Results - Inter-laboratory Comparison Program .......................... 11 F. Leaks, Spills, and Releases .............................................................................. 11 G. Trends ............................................................................................................... 11 H. Investigations .................................................................................................... 11 I. Actions Taken ..................................................................................................... 11 V. References ................................................................................................................... 11 i

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2018 Figures Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 Figure 2 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 Figure 3 Routine Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 Appendix B Data Tables Tables Table B-I.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 Table B-I.2 Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 Table B-I.3 Concentrations of Hard To Detects in Groundwater Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 Table B-II.1 Concentration of Tritium and Strontium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 Table B-II.2 Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 Table B-III.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 ii

I. Summary and Conclusions This report on the Radiological Groundwater Protection Program (RGPP) conducted for the Limerick Generating Station (LGS) by Exelon Nuclear covers the period 01 January 2018 through 31 December 2018. During that time period, 265 analyses were performed on 134 samples from 13 groundwater, 7 surface water and 4 precipitation water locations collected from the environment, both on and off station property in 2018.

Groundwater and surface water was analyzed for tritium. All sample results were at concentrations less than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at 4 of the 13 groundwater monitoring locations and at 1 of the 7 surface water monitoring locations. All other results were less than the required Exelon-specified LLD of 200 pCi/L.

Groundwater and surface water was analyzed for Strontium-89 (Sr-89) and Strontium-90 (Sr-90). All Sr-89 and Sr-90 results were less than the MDC.

Groundwater was analyzed for gross alpha and gross beta in dissolved and suspended fractions. Gross alpha (dissolved) results were less than the MDC.

Gross alpha (suspended) was detected at 1 of the 13 groundwater locations sampled. Gross beta (dissolved) was detected at 10 of 13 groundwater locations sampled. Gross beta (suspended) was detected at 1 of the 13 groundwater locations sampled.

Groundwater and surface water was analyzed for gamma-emitting radionuclides associated with the renewed licensed plant operation. Naturally-occurring Potassium-40 (K-40) was detected in 1 of 13 groundwater locations. All other gamma isotopic results were less than the MDC.

Hard-To-Detect (HTD) analyses are routinely performed on a once per five year frequency for all groundwater monitoring locations. No HTD analyses were performed in 2018.

Precipitation water samples were analyzed for tritium. Tritium was detected at 2 of 4 precipitation locations sampled.

In assessing all the data gathered for this report, it was concluded that the operation of Limerick Generating Station had no adverse radiological impact on the environment offsite of LGS. Additionally, there does not appear to be an active source of tritium to groundwater at the Station.

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II. Introduction The Limerick Generating Station (LGS), consisting of two 3515 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2018.

In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Limerick Generating Station. This evaluation involved numerous station personnel and contractor support personnel.

A. Objective of the RGPP The long-term objectives of the RGPP are as follows:

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.

2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.

3. Perform routine water sampling and radiological analysis of water from selected locations.

4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

B. Implementation of the Objectives The objectives identified have been implemented at Limerick Generating Station as discussed below:

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1. Exelon and its consultant identified locations as described in the 2006 Phase 1 study. The Phase 1 study results and conclusions were made available to state and federal regulators in station specific reports.

2. The Limerick Generating Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.

3. Limerick Generating Station will continue to perform routine sampling and radiological analysis of water from selected locations.

4. Limerick Generating Station has procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.

5. Limerick Generating Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.

C. Program Description Samples for the ongoing ground water monitoring program were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2018. Sample locations can be found in Table A-1, Appendix A.

1. Sample Collection Groundwater and Surface Water Samples of both groundwater and surface water were collected, managed, transported and analyzed in accordance with approved procedures following EPA methods. Sample locations, sample collection frequencies and analytical frequencies were controlled in accordance with approved station procedures. Contractor and/or station personnel were trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories were subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits. Station personnel reviewed and evaluated all analytical data deliverables as data were received.

Both station personnel and an independent hydrogeologist reviewed analytical data results for adverse trends or changes to hydrogeological conditions.

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Precipitation A five-gallon precipitation collection bucket fitted with a funnel was installed at four locations around the Limerick Generating Station.

Three collection buckets were located on site in the highest prevalent wind sectors and one located on site in the least prevalent wind sector.

D. Characteristics of Tritium (H-3)

Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen.

Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

Tritium has a half-life of approximately 12.3 years. It decays spontaneously to Helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

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III. Program Description A. Sample Analysis This section lists the analyses performed by TBE and EIML on environmental samples for the LGS RGPP in 2018. The analytical procedures used by the laboratories are listed in the AREOR Appendix B Table B-3.

In order to achieve the stated objectives, the current program includes the following analyses:

1. Concentrations of tritium in groundwater, surface water and precipitation water

2. Concentrations of Gross Alpha, Dissolved and Suspended and Gross Beta, Dissolved and Suspended in groundwater

3. Concentrations of gamma-emitters (Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, I-131, Cs-134, Cs-137, Ba-140, and La-140) in groundwater and surface water

4. Concentrations of Strontium (Sr-89 and Sr-90) in groundwater and surface water B. Data Interpretation The radiological data collected prior to Limerick Generating Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Limerick Generating Station was considered operational at initial criticality. 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 LGS detection capabilities for environmental sample analysis.

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.

5

2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.

Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting error) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated. Exelon reports the TPU by following the result with plus or minus (+/-) the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.

Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR.

C. Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, aquatic life, and foodstuffs. The results of the monitoring were detailed in the report entitled Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.

The pre-operational REMP contained analytical results from samples collected from both surface water and groundwater.

Monthly surface water sampling began in 1982, and the samples were analyzed for tritium as well as other radioactive analytes. During the preoperational program tritium was detected at a maximum concentration of 420 pCi/L, indicating that these preoperational results were from nuclear weapons testing and is radioactively decaying as predicted. Gamma isotopic results from the preoperational program were all less than or at the minimum detectable concentration (MDC) level.

1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background 6

measurements of tritium in various media performed by others.

Additional detail may be found by consulting references.

a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, Cosmogenic tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle.

Below ground, lithogenic tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and Sr-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.

b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPAs RadNet database. GNIP provides tritium precipitation concentration data for samples collected worldwide since 1960. RadNet provides tritium precipitation concentration data for samples collected at stations throughout the U.S. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time.

Tritium concentrations have typically been below 100 pCi/L 7

since approximately 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above.

Water from previous years was naturally captured in groundwater. As a result, some well water sources today are affected by the surface water from the 1960s that contained elevated tritium activity.

c. Surface Water Data Tritium concentrations are routinely measured in the Schuylkill and Delaware Rivers. Pennsylvania surface water data are typically less than 100 pCi/L.

The USEPA RadNet surface water data typically has a reported Combined Standard Uncertainty of 35 to 50 pCi/L.

According to USEPA, this corresponds to a +/-70 to 100 pCi/L 95% confidence bound on each given measurement.

Therefore, the typical background data provided may be subject to measurement uncertainty of approximately +/- 70 to 100 pCi/L.

The radioanalytical laboratory is counting tritium results to an Exelon specified LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 -

240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from background at this concentration. The surface water data ends in 1999 as the USEPA RadNet surface water program was terminated in March 1999.

IV. Results and Discussion A. Groundwater Results Samples were collected from onsite wells throughout the year in accordance with the station Radiological Groundwater Protection Program.

Analytical results and anomalies are discussed below:

Tritium Samples from 13 locations were analyzed for tritium activity. (Appendix B, Table B-I.1) Tritium values ranged from non-detectable to 1,480 pCi/L.

Although no drinking water pathway is available from groundwater, the theoretical dose via the drinking water pathway was calculated at 8.76E-02 mrem to a child (total body), which represents 1.46E+00% of the 10 CFR 50, Appendix I dose limit of 6 mrem.

8

Strontium Samples were analyzed for Sr-89 and Sr-90. All results were below the required LLDs. (Appendix B, Table B-I.1)

Gross Alpha and Gross Beta (dissolved and suspended)

All samples were analyzed for gross alpha and gross beta in the dissolved and suspended fractions once in May, 2018. Gross alpha (dissolved) results were below the required LLDs. Gross alpha (suspended) was detected in 1 of 13 groundwater locations sampled at a concentration of 5.7 pCi/L. Gross beta (dissolved) was detected in 10 of 13 groundwater locations sampled. The concentrations ranged from 1.7 to 14.2 pCi/L.

Gross beta (suspended) was detected in 1 of the 13 groundwater locations sampled at a concentration of 13.6 pCi/L. (Appendix B, Table B-I.1)

Gamma Emitters Samples were analyzed for gamma-emitting nuclides. Naturally-occurring Potassium-40 (K-40) was detected in 1 of the 13 locations sampled at a concentration of 148 pCi/L, All other gamma results were below the required LLDs. (Appendix B, Table B-I.2)

Hard-To-Detect No HTD analyses were performed in 2018. (Appendix B, Table B-I.3)

B. Surface Water Results In accordance with the Station's Radiological Groundwater Protection Program surface water samples were collected from streams that transverses the site, as well as, from other water bodies that could influence the tritium concentration at Limerick. Analytical results and anomalies are discussed below.

Tritium Samples from 7 locations were analyzed for tritium activity (Appendix B, Table B-II.1). Tritium was detected in 1 of the 7 locations, sampled at a concentration of 217 pCi/L. The theoretical dose via the drinking water pathway was calculated at 1.28E-02 mrem to a child (total body), which represents 2.14E-01% of the 10 CFR 50, Appendix I dose limit of 6 mrem.

Strontium Samples were analyzed for Sr-89 and Sr-90. All results were below the required LLDs. (Appendix B, Table B-II.1) 9

Gamma Emitters Samples were analyzed for gamma-emitting nuclides. All gamma results were below the required LLDs. (Appendix B, Table B-II.2)

C. Precipitation Sample Results Tritium Tritium activity was detected in 3 of 4 precipitation water locations analyzed. The concentrations ranged from 192 to 526 pCi/L. These concentrations are consistent with historical values observed. (Appendix B, Table B-III.1)

D. Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CRA 2006) around the Limerick Generating Station. CRA reviewed the Pennsylvania Groundwater Information System database to identify wells within a 1-mile radius from the center of the Station. Forty-six domestic withdrawal wells, two industrial wells, two commercial wells, and one institutional well were identified within the specified radius. The well depths range from 78 to 345 feet below ground surface (BGS), and they yield between 8 and 100 gallons per minute (gpm). All wells are completed in the Brunswick Formation.

The Station has one potable supply well and one fire water well. The potable supply well is constructed as an open-rock borehole. Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2014. The pump was placed at a depth of approximately 294 feet BGS.

The total well depth and the depth of the steel casing are approximately 310 feet BGS. The well is located approximately 175 feet east of the Reactor Building. The potable supply well is sampled as part of the RGPP and designated as DW-LR-1. The fire water well is constructed as an open-rock borehole. Groundwater was encountered at 121 feet BGS during a well pump replacement in 2004. The well pump was placed at a depth of approximately 399 feet BGS. The total well depth and the depth of the steel casing are unknown. The well is located approximately 500 feet east of the cooling towers. The well is used in an emergency fire situation and for system testing and flushing. In 2018, approximately 909,194 gallons were pumped from the well.

10

E. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.

F. Leaks, Spills, and Releases There were no spills to ground containing radioactive material in 2018.

However, the Power Block Foundation Sump, which collects groundwater around the reactor buildings, turbine building and rad waste building, had identified tritium in the third and fourth quarter samples and analysis of potentially contaminated systems (IRs 04157321 and 04166840). The maximum activity of 1.94E-06 uCi/ml was recorded. The source of the tritium is groundwater movement from the previously identified and reported leaks/spills.

G. Trends Low level tritium detections in monitoring well MW-LR-5 are being trended.

H. Investigations Intermittent, low-level tritium detections in monitoring well MW-LR-5 are currently being investigated.

I. Actions Taken

1. Compensatory Actions There have been no station events requiring compensatory actions at the Limerick Generating Station.

2. Installation of Monitoring Wells No New monitoring well

3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes.

V. References

1. Conestoga Rovers and Associates, Fleetwide Assessment, Limerick Generating Station, Sanatoga, Pennsylvania, Ref. No. 045136(17),

September 2006

2. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation 11

Intentionally left blank APPENDIX A LOCATION DESIGNATION

Intentionally left blank TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2018 Location Type Distance MW-LR-1 Monitoring Well Onsite MW-LR-2 Monitoring Well Onsite MW-LR-3 Monitoring Well Onsite MW-LR-4 Monitoring Well Onsite MW-LR-5 Monitoring Well Onsite MW-LR-6 Monitoring Well Onsite MW-LR-7 Monitoring Well Onsite MW-LR-8 Monitoring Well Onsite MW-LR-9 Monitoring Well Onsite MW-LR-10 Monitoring Well Onsite P11 Monitoring Well Onsite P14 Monitoring Well Onsite P17 Monitoring Well Onsite P3 Monitoring Well Onsite SP22 Monitoring Well Onsite DW-LR-1 Monitoring Well Onsite SW-LR-2 Surface Water Offsite SW-LR-4 Surface Water Offsite SW-LR-6 Surface Water Offsite SW-LR-7 Surface Water Onsite SW-LR-8 (Hold Pond) Surface Water Onsite SW-LR-9 (Spray Pond) Surface Water Onsite SW-LR-10 Surface Water Onsite 36S3 Precipitation Water Onsite E-5 Precipitation Water Onsite ESE-6 Precipitation Water Onsite SE-7 Precipitation Water Onsite A-1

Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 A-2

Figure 2 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 A-3

Figure 3 Routine Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2018 A-4

APPENDIX B DATA TABLES

Intentionally left blank TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

DW-LR-1 02/20/18 < 185 DW-LR-1 05/08/18 < 185 < 5.4 < 1.0 < 1.2 < 1.1 < 1.3 < 1.5 DW-LR-1 08/14/18 < 196 DW-LR-1 10/30/18 < 190 MW-LR-1 05/08/18 < 195 < 1.9 < 0.8 < 2.1 < 0.6 < 1.7 < 1.6 MW-LR-2 02/21/18 < 185 MW-LR-2 05/08/18 < 186 < 3.7 < 0.9 < 1.3 < 1.1 1.7 +/- 0.9 < 1.5 MW-LR-2 08/14/18 265 +/- 130 MW-LR-2 11/01/18 < 190 MW-LR-3 02/21/18 < 185 MW-LR-3 05/08/18 < 192 < 3.1 < 0.9 < 1.7 < 1.2 2.4 +/- 1.1 < 1.5 MW-LR-3 08/14/18 < 195 MW-LR-3 10/30/18 < 194 MW-LR-4 02/21/18 < 186 MW-LR-4 05/08/18 < 193 < 3.0 < 0.7 < 2.4 < 1.1 4.8 +/- 1.3 < 1.5 MW-LR-4 08/14/18 < 195 MW-LR-4 10/29/18 < 190 MW-LR-5 02/11/18 TBE 272 +/- 130 MW-LR-5 02/21/18 TBE 264 +/- 128 MW-LR-8 02/21/19 GEL 242 +/- 95 MW-LR-5 05/08/18 TBE 653 +/- 147 < 2.9 < 0.6 < 1.8 < 1.2 6.6 +/- 1.2 < 1.5 MW-LR-5 05/08/18 TBE 655 +/- 146 < 1.0 < 0.4 < 1.7 < 0.6 8.6 +/- 1.3 < 1.5 MW-LR-8 05/08/18 GEL 726 +/- 104 < 0.6 < 0.4 (1) < 3.3 (1) 8.9 +/- 1.5 MW-LR-5 08/14/18 TBE < 194 MW-LR-5 08/14/18 TBE 252 +/- 139 MW-LR-5 08/14/18 GEL < 107 MW-LR-5 11/01/18 TBE < 191 MW-LR-5 11/01/18 TBE < 192 MW-LR-5 11/01/19 GEL 172 +/- 79 MW-LR-7 02/19/18 < 192 MW-LR-7 05/07/18 < 194 < 5.8 < 0.8 < 0.7 < 0.6 2.6 +/- 0.7 < 1.5 MW-LR-7 08/14/18 < 194 MW-LR-7 10/29/18 < 188 MW-LR-8 02/20/18 TBE 580 +/- 141 MW-LR-8 02/20/18 TBE 460 +/- 139 MW-LR-8 02/20/18 GEL 427 +/- 96 MW-LR-8 05/09/18 TBE 440 +/- 138 < 1.1 < 0.5 < 2.0 < 0.6 2.0 +/- 1.0 < 1.5 MW-LR-8 05/09/18 TBE 563 +/- 142 < 1.9 < 0.7 < 2.0 < 1.2 2.0 +/- 1.0 < 1.5 MW-LR-8 05/09/18 GEL 527 +/- 142 < 0.7 < 0.3 (1) < 3.2 (1) 4.4 +/- 1.9 MW-LR-8 08/15/18 TBE 840 +/- 159 MW-LR-8 08/15/18 TBE 658 +/- 148 MW-LR-8 08/15/18 GEL 659 +/- 104 MW-LR-8 10/30/18 TBE 527 +/- 141 MW-LR-8 10/30/18 TBE 392 +/- 134 MW-LR-8 10/30/18 GEL 461 +/- 96 MW-LR-9 02/20/18 TBE 738 +/- 148 MW-LR-9 02/20/18 TBE 766 +/- 149 MW-LR-9 02/20/18 GEL 569 +/- 98 MW-LR-9 05/09/18 TBE 976 +/- 169 < 2.9 < 0.4 < 2.4 < 1.2 8.3 +/- 1.4 < 1.5 MW-LR-9 05/09/18 TBE 1480 +/- 220 < 4.2 < 0.6 < 2.5 5.7 +/- 2.1 8.4 +/- 1.4 13.6 +/- 2.4 MW-LR-9 05/09/18 GEL 1370 +/- 125 < 0.9 < 1.7 (1) 51 +/- 16 (1) 112 +/- 11 (1) Total Gross Alpha & Gross Beta results reported (not Suspended)

B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

MW-LR-9 08/15/18 TBE 1140 +/- 186 MW-LR-9 08/15/18 TBE 1170 +/- 189 MW-LR-8 08/15/18 GEL 1040 +/- 121 MW-LR-9 10/30/18 TBE 923 +/- 167 MW-LR-9 10/30/18 TBE 855 +/- 160 MW-LR-9 10/30/18 GEL 732 +/- 109 MW-LR-10 02/20/18 < 184 MW-LR-10 05/09/18 < 193 < 1.1 < 0.5 < 1.3 < 0.6 3.9 +/- 1.1 < 1.5 MW-LR-10 08/15/18 < 197 MW-LR-10 10/30/18 < 190 P11 02/20/18 < 195 P11 05/09/18 < 191 < 4.0 < 0.6 < 2.7 < 0.6 14.2 +/- 1.6 < 1.5 P11 08/15/18 < 190 P11 10/30/18 < 191 P14 02/20/18 < 184 P14 05/09/18 < 192 < 4.3 < 0.8 < 5.0 < 0.6 6.0 +/- 2.5 < 1.6 P14 08/15/18 < 195 P14 10/30/18 < 194 P17 05/07/18 < 192 < 2.4 < 0.6 < 1.8 < 1.5 Bolded values indicate LLD was not met due to high solid content in the sample B-2

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 DW-LR-1 05/08/18 < 74 < 117 < 7 < 8 < 18 < 8 < 15 < 11 < 13 < 15 < 7 < 7 < 35 < 11 MW-LR-1 05/08/18 < 60 < 63 < 7 < 6 < 12 < 7 < 15 < 8 < 14 < 12 < 6 < 6 < 34 < 15 MW-LR-10 05/09/18 < 60 < 69 < 7 < 6 < 14 < 7 < 13 < 7 < 10 < 12 < 6 < 7 < 35 < 11 MW-LR-2 05/08/18 < 53 < 54 < 7 < 6 < 14 < 7 < 14 < 7 < 12 < 10 < 6 < 8 < 34 < 8 MW-LR-3 05/08/18 < 46 < 41 < 5 < 5 < 13 < 7 < 11 < 7 < 10 < 10 < 5 < 6 < 26 < 8 MW-LR-4 05/08/18 < 55 < 137 < 7 < 6 < 14 < 8 < 14 < 7 < 12 < 14 < 8 < 8 < 34 < 11 MW-LR-5 05/08/18 < 67 < 139 < 8 < 5 < 16 < 6 < 21 < 9 < 17 < 11 < 7 < 10 < 34 < 14 MW-LR-5 05/08/18 < 56 < 104 < 6 < 6 < 13 < 7 < 13 < 9 < 11 < 10 < 6 < 6 < 29 < 10 MW-LR-5 05/08/18 GEL (1) (1) < 1 < 1 < 4 < 1 < 3 < 2 < 3 < 13 < 1 < 1 < 18 < 7 MW-LR-7 05/07/18 < 56 < 108 < 5 < 7 < 15 < 8 < 16 < 8 < 11 < 13 < 6 < 8 < 41 < 11 MW-LR-8 05/09/18 TBE < 75 < 119 < 8 < 11 < 22 < 10 < 18 < 10 < 17 < 13 < 9 < 10 < 44 < 15 MW-LR-8 05/09/18 TBE < 59 < 70 < 6 < 6 < 15 < 7 < 14 < 9 < 13 < 11 < 7 < 7 < 32 < 11 MW-LR-8 05/09/18 GEL (1) (1) < 1 < 2 < 3 < 2 < 3 < 2 < 3 < 13 < 1 < 1 < 19 < 8 MW-LR-9 05/09/18 TBE < 56 148 +/- 95 < 6 < 8 < 13 < 7 < 12 < 7 < 11 < 11 < 8 < 7 < 30 < 12 MW-LR-9 05/09/18 TBE < 51 < 108 < 7 < 6 < 10 < 5 < 12 < 8 < 10 < 10 < 6 < 6 < 26 < 8 MW-LR-9 05/09/18 GEL (1) (1) < 1 < 2 < 4 < 2 < 3 < 2 < 3 < 12 < 1 < 1 < 19 < 7 B-3 P11 05/09/18 < 66 < 70 < 9 < 8 < 15 < 8 < 18 < 8 < 12 < 13 < 9 < 7 < 34 < 10 P14 05/09/18 < 63 < 70 < 6 < 7 < 16 < 8 < 19 < 8 < 12 < 13 < 6 < 8 < 29 < 11 P17 05/07/18 < 59 < 114 < 6 < 7 < 14 < 8 < 17 < 6 < 9 < 14 < 7 < 8 < 32 < 10 (1) No result received

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION STC PERIOD AM-241 CM-242 CM-243/244 PU-238 PU-239 U-233/234 U-235 U-238 FE-55 NI-63 There were no HTD's Analyzed in 2018 B-4

TABLE B-II.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 SW-LR-2 02/19/18 < 194 SW-LR-2 05/07/18 < 190 < 5.3 < 0.8 SW-LR-2 08/14/18 < 193 SW-LR-2 10/29/18 < 190 SW-LR-4 02/19/18 < 196 SW-LR-4 05/07/18 < 196 < 2.9 < 0.9 SW-LR-4 08/14/18 < 188 SW-LR-4 10/29/18 < 188 SW-LR-6 02/19/18 < 196 SW-LR-6 05/07/18 < 192 < 2.4 < 1.0 SW-LR-6 08/14/18 < 189 SW-LR-6 10/29/18 < 193 SW-LR-7 02/19/18 < 195 SW-LR-7 05/07/18 < 192 < 1.8 < 1.0 SW-LR-7 08/14/18 < 194 SW-LR-7 10/29/18 < 188 SW-LR-8 02/20/18 < 180 SW-LR-8 05/08/18 < 192 < 1.9 < 0.9 SW-LR-8 08/14/18 217 +/- 127 SW-LR-8 10/30/18 < 190 SW-LR-9 02/19/18 < 193 SW-LR-9 05/07/18 < 194 < 1.6 < 0.8 SW-LR-9 08/14/18 < 190 SW-LR-9 10/30/18 < 189 SW-LR-10 02/19/18 < 196 SW-LR-10 05/08/18 < 194 < 1.8 < 0.8 SW-LR-10 08/14/18 < 194 SW-LR-10 10/29/18 < 189 B-5

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 SW-LR-2 05/07/18 < 77 < 69 < 6 < 6 < 17 < 9 < 15 < 8 < 12 < 15 < 7 < 8 < 44 < 8 SW-LR-4 05/07/18 < 67 < 106 < 7 < 7 < 11 < 5 < 11 < 6 < 10 < 13 < 6 < 7 < 29 < 12 SW-LR-6 05/07/18 < 69 < 153 < 7 < 7 < 15 < 6 < 13 < 8 < 13 < 15 < 6 < 7 < 37 < 12 SW-LR-7 05/07/18 < 54 < 129 < 6 < 6 < 16 < 8 < 15 < 8 < 12 < 11 < 6 < 6 < 33 < 13 SW-LR-8 05/08/18 < 66 < 74 < 7 < 6 < 13 < 8 < 17 < 7 < 12 < 13 < 7 < 7 < 37 < 11 SW-LR-9 05/07/18 < 75 < 68 < 7 < 8 < 16 < 7 < 14 < 8 < 12 < 15 < 7 < 7 < 36 < 12 SW-LR-10 05/08/18 < 57 < 57 < 8 < 9 < 17 < 9 < 17 < 8 < 18 < 14 < 6 < 8 < 49 < 11 B-6

TABLE B-III.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 36S3 12/29/17 - 01/29/18 < 193 36S3 01/29/18 - 02/26/18 < 186 36S3 02/26/18 - 04/02/18 < 175 36S3 04/02/18 - 04/30/18 < 178 36S3 04/30/18 - 05/30/18 < 193 36S3 05/30/18 - 06/29/18 < 196 36S3 06/29/18 - 07/30/18 < 187 36S3 07/30/18 - 08/31/18 < 186 36S3 08/31/18 - 10/01/18 < 190 36S3 10/01/18 - 10/29/18 < 195 36S3 10/29/18 - 12/05/18 < 173 36S3 12/05/18 - 01/02/19 < 182 E-5 12/29/17 - 01/29/18 < 195 E-5 01/29/18 - 02/26/18 < 186 E-5 02/26/18 - 04/02/18 < 170 E-5 04/02/18 - 04/30/18 < 177 E-5 04/30/18 - 05/30/18 < 183 E-5 05/30/18 - 06/29/18 < 196 E-5 06/29/18 - 07/30/18 < 191 E-5 07/30/18 - 08/31/18 < 187 E-5 08/31/18 - 10/01/18 < 194 E-5 10/01/18 - 10/29/18 < 190 E-5 10/29/18 - 12/05/18 < 172 E-5 12/05/18 - 01/02/19 < 178 ESE-6 12/29/17 - 01/29/18 377 +/- 137 ESE-6 12/29/17 - 01/29/18 Recount 267 +/- 129 ESE-6 01/29/18 - 02/26/18 246 +/- 130 ESE-6 01/29/18 - 02/26/18 Recount 213 +/- 129 ESE-6 02/26/18 - 04/02/18 < 175 ESE-6 04/02/18 - 04/30/18 < 173 ESE-6 04/30/18 - 05/30/18 < 190 ESE-6 05/30/18 - 06/29/18 < 194 ESE-6 06/29/18 - 07/30/18 192 +/- 124 ESE-6 07/30/18 - 08/31/18 < 190 ESE-6 08/31/18 - 10/01/18 < 190 ESE-6 10/01/18 - 10/29/18 < 192 ESE-6 10/29/18 - 12/05/18 < 176 ESE-6 12/05/18 - 01/02/19 < 184 SE-7 12/29/17 - 01/29/18 241 +/- 135 SE-7 01/29/18 - 02/26/18 202 +/- 124 SE-7 02/26/18 - 04/02/18 526 +/- 132 SE-7 04/02/18 - 04/30/18 < 175 SE-7 04/30/18 - 05/30/18 < 192 SE-7 05/30/18 - 06/29/18 < 190 SE-7 06/29/18 - 07/30/18 < 189 SE-7 07/30/18 - 08/31/18 < 186 SE-7 08/31/18 - 10/01/18 < 194 SE-7 10/01/18 - 10/29/18 < 193 SE-7 10/29/18 - 12/05/18 < 178 SE-7 12/05/18 - 01/02/19 < 188 B-7