ML20121A115

Annual Radiological Environmental Operating Report

ML20121A115
Person / Time
Site:	Limerick
Issue date:	04/29/2020
From:	Sturniolo F Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LG-20-045
Download: ML20121A115 (147)

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Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 AND 2 Annual Radiological Environmental Operating Report 1 January through 31 December 2019 Prepared By Teledyne Brown Engineering Environmental Services Limerick Power Station Pottstown, PA 19464 April 2020

Intentionally left blank Table of Contents I. Preface ............................................................................................................................ 1 II. Summary and Conclusions ............................................................................................. 8 III. Introduction................................................................................................................... 10 A. Objective 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 40 CFR 190 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............................................................................. 19

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 G. Summary of Results - Inter-Laboratory Comparison Program ......................... 22

1. TBE Laboratory Results .......................................................................... 23

2. EIS Laboratory Results ........................................................................... 25

3. GEL Laboratory Results.......................................................................... 25 VI. References .................................................................................................................. 27

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2019 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, 2019 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2019 Figures Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2019 Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2019 Figure B-3 Environmental Sampling Locations Greater Than 26,400 Feet from the Limerick Generating Station, 2019 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, 2019 Table C-I.2 Concentrations of I-131 in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-I.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-II.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-II.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-II.3 Concentrations of I-131 in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-II.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2019

Table C-III.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2019 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, 2019 Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-VI.1 Concentrations of I-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-VII.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-VIII.1 Concentrations of Gamma Emitters in Broad Leafy Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2019 Table C-IX.1 Quarterly DLR Results for Limerick Generating Station, 2019 Figures Figure C-1 Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2019 Figure C-2 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2019 Figure C-3 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2019 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, 2019 Table D-I.2 Concentrations of I-131 in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2019 Table D-I.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2019 Table D-I.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2019

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, 2019 Table D-II.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2019 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, 2019 Figures Figure D-1 Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between EIS and TBE, 2019 Figure D-2 Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2019 Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2019 Table E-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2019 Table E-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2019 Table E-4 Analytics Environmental Radioactivity Cross Check Program Exelon Industrial Services, 2019 Table E-5 ERA Environmental Radioactivity Cross Check Program Exelon Industrial Services, 2019 Table E-6 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

GEL Laboratories, 2019 Table E-7 ERA Environmental Radioactivity Cross Check Program GEL Laboratories, 2019 Table E-8 Analytics Environmental Radioactivity Cross Check Program GEL Laboratories, 2019 Appendix F Errata Data Appendix G Annual Radiological Groundwater Protection Program Report (ARGPPR)

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 analyses of samples taken from the effluent release paths at the station. 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 analyses of samples obtained in the environment surrounding the station. 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 Plants are operating in a manner that is within established regulatory commitments meant to adequately protect the public.

1

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 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.

2

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 contaminants 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 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 3

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 prefix, such as the PLFUR&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 site DUHPHDVXUHGPLOOL5RHQWJHQ 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.

5

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 2019, the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 48 curies of noble gas, fission and activation products and approximately 99 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 Estimated Age Maximum Individual Noble Gas Applicable Dose Applicable Limit Unit Dose Group Limit Nearest Residence Gamma Air Dose 1.03E-03 All 5.15E-03 20 mRad Nearest Residence Beta Air Dose 6.12E-04 All 1.53E-03 40 mRad Nearest Residence Total Body 9.79E-04 All 9.79E-03 10 mrem Nearest Residence Skin 1.62E-03 All 5.40E-03 30 mrem Iodine, Particulate, C-14 & Tritium Vegetation Pathway Bone 1.26E+00 Child 4.22E+00 30 mrem Liquid LGS Outfall Total Body 9.63E-03 Adult 1.61E-01 6 mrem LGS Outfall Liver 1.23E-02 Teen 6.17E-02 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 2019 through 31 December 2019. During that time period, 1,503 analyses were performed on 1,254 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. The Cs-137 identified in sediment is attributed to weapons testing fallout partly due to the fact that there is no Cs-134 identified, which would be expected if related to plant 8

effluents. No other station-produced fission or activation products were found in sediment. For 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.

The air monitoring systems employed in the nuclear industry have proven to be capable of detecting very low levels of activity in the atmosphere, as activity from both the Chernobyl and Fukushima events was detected at many of the worlds nuclear power plants, including Limerick Generating Station.

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.

Broadleaf vegetation samples were analyzed for gamma-emitting nuclides. Only naturally-occurring activity was detected. Be-7 and K-40 were detected in all samples.

Radium-226 (Ra-226) was found in 8 of 34 samples. Thorium-228 (Th-228) was found in 17 of 34 samples. Thorium-232 (Th-232) was found in 2 of 34 samples. No activity due to plant operations were detected.

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 and no facility-related dose was detected. 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 2019, 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 precipitation water were less than the ORZHUOLPLWRIGHWHFWLRQRIS&L/5HVXOWVDQG'LVFXVVLRQRIJURXQGZDWHU

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, DQG([HORQ,QGXVWULDO6HUYLFHV (,6 *(//DERUDWRULHV *(/ RQVDPSOHVFROOHFWHG

during the period 1 January 2019 through 31 December 2019.

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. Validate the radioactive effluent control program by evaluating 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:

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 10

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 2019. 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. Control locations are sample locations that are not expected to be impacted by plant operations and are used to determine a baseline in the environment for each type of sample.

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 QRUWKHUQKRJVXFNHU

ZKLWHKRJVXFNHUFDUS and SUHGDWRU VPDOOPRXWKEDVV$PHULFDQHHOURFN

EDVVEOXHJLOOVXQILVKUHGEUHDVWVXQILVKEODFNFUDSSLH 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.

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, 11

preserved with sodium bisulfite, and shipped promptly to the laboratory.

Broadleaf vegetation was collected monthly, during the growing season, at three locations (11S3, 13S3, and 31G1). The control location was 31G1.

Twelve 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-GHJUHHVHFWRUVDURXQGWKHVLWHZKHUH

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 mesh basket tube located approximately three feet above ground level. The dosimeters were exchanged quarterly and sent to Mirion Technologies for analysis.

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 12

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 2019, 2,835 cubic feet of cooling water sludge 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, Teledyne Brown Engineering (TBE), the secondary laboratories, Exelon Industrial Services, LLC (EIS) and GEL Laboratories, LLC (GEL) and also Mirion Technologies on environmental samples for the LGS REMP in 2019. 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 EIS and GEL Laboratories are provided in Appendix D of this report.

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 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 13

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 analyzes samples for the full range of nuclides. All nuclides that identified positive results are reported. Each type of sample also looks for specific nuclides and the results for each type of sample were reported 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 broadleaf 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 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.

14

D. Program Exceptions For 2019 the LGS REMP had a sample recovery rate of greater than 99%.

Exceptions are listed below:

1. $LUVDPSOHIURPORFDWLRQ'IRUWKHZHHNRI- ZDV not available due to the pump not running due to broken vanes. The vanes were replaced, and the pump was returned to service.

(IR 4271443)

2. Air sample from location 13S4 for the week of 0519 - 0619 was not available due not available due to the pump not running due to broken vanes. The vanes were replaced, and the pump was returned to service.

(IR 4271443)

3. Air sample from location 14S1 for the week of 0619 - 0619 was not available due to the pump not running due to a blown fuse caused by a bad bearing. The pump and fuse were replaced, and the sampler was returned to service. (IR 4271447)

NOTE: As part of the corrective actions for air sample pumps not running, telemetry was installed at all air sample stations to notify station personnel when any of the stations is involved in a loss of power incident.

4. Drinking water sample from location 16C2 did not have enough sample for the QC split sample for low-level iodine analysis. This was due to a human performance error while acidifying the weekly samples for gamma analysis. This error only impacted the QC split sample as there was enough sample for the required monthly sample. (IR 4293514)

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 Revision 32 of the Offsite Dose Calculation Manual (ODCM) was implemented in 2019. A summary of changes are:

x Page 84, Section 1.2.2 under LIQUID EFFLUENT MONITOR SETPOINT DETERMINATION there is discussion for the monitor setpoint calculation which describes default values and has values listed for the default values. This change is removing the listed default values and changing the wording to station procedurally controlled default values to allow a blowdown line value lower than the current listed value of 5,000 gpm when conditions are such that a minimum 5,000 gpm blowdown flow rate cannot be achieved. There is NO change to the actual setpoint calculation in step 1.2.1.1 15

x Page 327, Figure A-2 was updated to show the entire section of river used for REMP sample locations 29C1 and 16C5 for fish sampling.

(Administrative Change)

A complete copy of ODCM Revision 32 is included with the Limerick 2019 Annual Radioactive Effluent Release Report.

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 obtained from the REMP 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 0.27 mRem (total body), 1.28 mRem (organ), or 0.26 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 Gaseous Effluents

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

& Tritium Total Body Dose 9.79E-04 2.56E-01 9.63E-03 0.00E+00 2.66E-01 1.06E+00 25 mRem Organ Dose 1.62E-03 1.26E+00 1.23E-02 0.00E+00 1.28E+00 5.11E+00 25 mRem Thyroid Dose 6.12E-04 2.56E-01 2.92E-04 0.00E+00 2.56E-01 3.42E-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 2.2 to

S&L/DQGWRWDOJURVVEHWDZDVGHWHFWHGDWDOOVDPSOHORFDWLRQV

Concentrations detected were consistent with 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 QRUWKHUQKRJVXFNHUwhite KRJVXFNHUFDUS and SUHGDWRU VPDOOPRXWKEDVV$PHULFDQHHOURFN

EDVVEOXHJLOOVXQILVKUHGEUHDVWVXQILVKEODFNFUDSSLH 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 ZDVIRXQGDWDOOVWDWLRQVDQGUDQJHGIURPWRS&LNJZHW

and was consistent with levels detected 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-ZDVIRXQGDWWZRORFDWLRQVDQGUDQJHGIURPWRS&LNJ

dry. K-40 was found at all locations and ranged from 12,230 to 16,030 S&LNJGU\7KHILVVLRQSURGXFW&V-137 was found at one location at a FRQFHQWUDWLRQRIS&LNJGU\

The very low level of Cs-137 activity detected was consistent with those detected in the pre-operational years and can be attributed to weapons 18

testing fallout. 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 1.94E-03 mRem and 1.66E-03 mRem, respectively. This dose represents 9.69E-03% and 2.77E-02%, 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 as expected. The results from the on-site locations (Group I) ranged from 6E-03 to 31E-S&LP3 with a mean of 15E-S&LP3. The results from the intermediate distance location (Group II) ranged from 5E-03 to 30E-S&LP3 with a mean of 14E-S&LP3. The results from the remote distance locations (Group III) ranged from 8E-03 to 27E-S&LP3 with a mean of 14E-

S&LP3. Comparison of the 2019 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 2019 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. Naturally-occurring Be-7 was detected in all 28 samples and is attributed to cosmic ray activity (cosmogenic).

These values ranged from 43E-03 to 115E-S&LP3. All other nuclides were below the required LLDs. (Appendix C, Table C-V.3)

b. Airborne Iodine Continuous air samples were collected from seven locations (6C1, 10S3, 11S1, 13S4, 14S1, 15D1, and 22G1) and analyzed weekly for 19

I-131. All results were below the required LLD.

(Appendix C, Table C-VI.1)

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. All results were below the required LLD.

(Appendix C, Table C-VII.1)

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 and ranged IURPWRS&L/$OORWKHUQXFOLGHVZHUHEHORZWKHUHTXLUHG

LLDs.

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

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

Cosmogenic, naturally-occurring Be-7 was found in 23 of 34 samples DQGUDQJHGIURPWRS&LNJZHW1DWXUDOO\-occurring K-40 wDVIRXQGLQDOOVDPSOHVDQGUDQJHGIURPWRS&LNJZHW

Naturally-occurring Ra-226 was found in 8 of 34 samples and ranged IURPWRS&LNJZHW1DWXUDOO\-occurring Th-228 was found in

RIVDPSOHVDQGUDQJHGIURPWRS&LNJwet. Naturally-occurring Thorium-232 was found in 2 of 34 samples and ranged from

WRS&LNJZHW$OORWKHUQXFOLGHVZHUHEHORZWKHUHTXLUHG//'V

20

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, Table C-IX.1. Dosimeter measurements were reported in P5VWDndard month. All dosimeter measurements were below 26 P5VWDQGDUGPRQWKZLWKDUDQJHRIWRP5VWDQGDUGPRQWK$

comparison 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. NRC Regulatory Guide 4.13, Revision 2 was released in 2019 and provided a new methodology for determining facility-related dose. Exelon procedures were revised to adopt the new methodology and starting in this report, results will be reported per this revision.

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 did not identify any facility-related dose as a result of operation of the ISFSI pad.

F. Land Use Survey A Land Use Survey conducted in the fall of 2019 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 land use survey is to look for all potential pathways of radiation to a person. This is accomplished by documenting the nearest resident, 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 2019 Land Use Survey identified differences in locations for gardens and meat animals between 2018 and 2019. Twelve (12) new gardens were located this year in sectors N, S, SSW, WSW, W, and NNW meteorological sectors. Gardens planted in sectors ESE 21

and SE that are maintained for the REMP program were not included in the survey because of location on LGS property. These REMP program gardens are used as the sample locations for the REMP program. There were eight (8) new meat sites identified this year in N, NNW, ESE, SSW, WSW and W sectors. All other locations were the same as in the 2018 report. There were no changes required to the LGS REMP as a result of this survey. There was no observed water usage for agricultural irrigation of root vegetables drawn directly from the Schuylkill River downriver from Limerick Generation Station.

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 10,077 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 3,928 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 4,506 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:

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.

22

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.

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.

1. TBE Laboratory Results For the TBE laboratory, 119 out of 129 analyses performed met the specified acceptance criteria. Ten analyses did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program. A summary is found below:

a) The ERA April 2019 water Cs-134 result was evaluated as Not Acceptable. The UHSRUWHGYDOXHZDVS&L/ HUURUS&L/ 

DQGWKHNQRZQUHVXOWZDVS&L/ DFFHSWDQFHUDQJHRI-

S&L/ :LWKWKHHUURUWKHUHSRUWHGUHVXOWRYHUODSVWKH

acceptable range. This sample was run as the workgroup duplicate on a different dHWHFWRUZLWKDUHVXOWRIS&L/ ZLWKLQDFFHSWDEOH

range). (NCR 19-10) b) The ERA April 2019 water Sr-89 result was evaluated as Not Acceptable7KHUHSRUWHGYDOXHZDVS&L/DQGWKHNQRZQUHVXOW

ZDVS&L/ DFFHSWDQFHUDQJHRI- S&L/). The sample was only counted for 15 minutes instead of 200 minutes. The sample 23

was re-prepped in duplicate and counted for 200 minutes with results RIS&L/DQGS&L/7KLVZDVWKHst high failure for Sr-89 in 5 years. (NCR 19-11) c) The MAPEP February 2019 soil Sr-90 result was not submitted and therefore evaluated as Not Acceptable. The sample was run in duplicate, with results of -%TNJ  DQG-1.030 +/- 3.55

%TNJ  7KHNQRZQUHVXOWZDVDIDOVHSRVLWive test (no significant activity). TBE did not submit a result because it appeared that the results may not be accurate. TBE analyzed a substitute soil Sr-90 sample from another vendor, with a result within the acceptable range. (NCR 19-12) d) The MAPEP February 2019 water Am-241 result was evaluated as Not Acceptable7KHUHSRUWHGYDOXHZDV%T/ZLWK

DNQRZQUHVXOWRI%T/ DFFHSWDEOHUDQJH- %T/ 

TBEs result falls within the upper acceptable range with the error. It appeared that a non-radiological interference was added and lead to an increased mass and higher result. (NCR 19-13) e) The MAPEP February 2019 vegetation Sr-90 result was evaluated as Not Acceptable. The reported result was -%TNJDQG

the known result was a false positive test (no significant activity).

TBEs result was correct in that there was no activity. MAPEPs evaluation was a statistical failure at 3 standard deviations.

(NCR 19-14) f) The ERA October 2019 water Gross Alpha result was evaluated as Not Acceptable7%(¶VUHSRUWHGUHVXOWZDVS&L/DQGWKH

NQRZQUHVXOWZDVS&L/ UDWLRRI7%(WRNQRZQUHVXOWDW 

With the associated error, the result falls within the acceptable range (14.0 - S&L/ 7KH sample was run as the workgroup duplicate RQDGLIIHUHQWGHWHFWRUZLWKDUHVXOWRIS&L/ ZLWKLQWKH

acceptable range). This was the first failure for drinking water Gr-A since 2012. (NCR 19-23) g) The ERA October 2019 water Sr-90 result was evaluated as Not Acceptable7%(¶VUHSRUWHGUHVXOWZDVS&L/DQGWKH

NQRZQUHVXOWZDVS&L/ UDWLRRI7%(WRNQRZQUHVXOWDW 

With the associated error, the result falls within the acceptable range (19.2 - S&L/ 7KHVDPSOHZDs run as the workgroup duplicate RQDGLIIHUHQWGHWHFWRUZLWKDUHVXOWRIS&L/ ZLWKLQWKH

acceptable range). Both TBE results are within internal QC limits. A substitute quick response sample was analyzed with an acceptable result of 18.6 S&L/ NQRZQUDQJHRI- S&L/  1&5-24) h) The MAPEP August 2019 soil Ni-UHVXOWRI%TNJZDV

HYDOXDWHGDV1RW$FFHSWDEOH7KHNQRZQUHVXOWZDV%TNJ

24

(acceptable range 440 - %TVDPSOH :LWKWKHDVVRFLDWHGHUURU

the TBE result falls within the lower acceptance range. All associated QC was acceptable. No reason for failure could be found.

This is the first failure for soil Ni-63 since 2012. (NCR 19-25).

i) The MAPEP August 2019 water Am-241 result was not reported and therefore evaluated as Not Acceptable. Initial review of the results showed a large peak where Am-241 should be (same as the February, 2019 sample results). It is believed that Th-228 was intentionally added as an interference. The sample was re-prepped and analyzed using a smaller sample aliquot. The unusual large peak (Th-228) was seen again and also this time a smaller peak (Am- 7KHUHVXOWZDV%T/ DFFHSWDEOHUDQJH

%T/ 7K-228 is not a typical nuclide requested by clients, so there is no analytical purpose to take samples through an additional separation step. TBE will pursue using another vendor for Am-241 water cross-checks that more closely reflects actual customer samples. (NCR 19-26) j) The Analytics September 2019 soil Cr-51 sample was evaluated as Not Acceptable7%(¶VUHSRUWHGUHVXOWRIS&LJ

exceeded the upper acceptance range (140% of the known result of

S&LJ 7KH7%(UHVXOWZDVZLWKLQWKHDFFHSWDEOHUDQJH -

S&LJ ZLWKWKHDVVociated error. The Cr-51 result is very close to TBEs normal detection limit. In order to get a reportable result, the sample must be counted for 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> (10x longer than client samples). There is no client or regulatory requirement for this nuclide and TBE will remove Cr-51 from the reported gamma nuclides going forward. (NCR 19-27)

2. EIS Laboratory Results For secondary QC samples, EIS laboratory analyzed gross beta, gamma and low-level I-131. For the EIS Laboratory, 114 out of 114 analyses performed met the specified acceptance criteria.

3. GEL Laboratory Results For the secondary QC samples, GEL laboratory analyzed only H-3 for

/*65(03*(/DOVRDQDO\]HGJDPPDJURVVDOSKDEHWD+-3, and Sr-IRU/*65*33)RUWKHVHDQDO\VHVRIFURVV-check samples met the specified acceptance criteria. All failures were addressed through GELs Corrective Action Program and the pertinent failures are described below:

a) Two ERA 1st quarter 2019 water Sr-89 results were evaluated as Not Acceptable7KHUHSRUWHGYDOXHVZHUHS&L/DQGS&L/

7KHNQRZQUHVXOWZDVS&L/ZLWKDQDFFHSWDQFHUDQJHRI-

S&L/$UHYLHZRIWKHGDWDDVZHOODVRIWKHSUHSDUDWLRQ

25

processes did not reveal any errors or possible contributors to the high bias. The Laboratory has concluded that this positive bias was an isolated occurrence and that the overall process is within control.

In addition, the reported value is 117% of the reference value, which LVZLWKLQWKHODE¶VVWDQGDUGDFFHSWDQFHFULWHULDRI- 25% for Laboratory Control Samples. No permanent corrective or preventative actions or improvements made at the time. The laboratory will continue to monitor the recoveries to ensure that there are no continued issues in the process. (CARR190225-1192) b) The ERA 2nd quarter 2019 vegetation Sr-90 result was evaluated as Not Acceptable7KHUHSRUWHGYDOXHZDVS&LNJDQGWKHNQRZQ

UHVXOWZDVS&LNJ DFFHSWDQFHUDQJHRI- S&L/).

The reanalysis was performed using the same processes as the original reported analysis. The reanalysis result met the acceptance range with 96% recovery. No permanent corrective or preventative actions or improvements made at the time. The laboratory will continue to monitor the recoveries to ensure that there are no continued issues in the process. (CARR190530-1211) c) One of the two ERA 3rd quarter 2019 water Sr-89 results was evaluated as Not Acceptable7KHUHSRUWHGYDOXHZDVS&L/

and the knRZQUHVXOWZDVS&L/ DFFHSWDQFHUDQJHRI-

S&L/ $UHYLHZRIWKHGDWDDVZHOODVRIWKHSUHSDUDWLRQ

processes did not reveal any errors or possible contributors to the high bias. The Laboratory has concluded that this positive bias was an isolated occurrence and that the overall process is within control.

In addition, the reported value is 118% of the reference value, which LVZLWKLQWKHODE¶VVWDQGDUGDFFHSWDQFHFULWHULDRI- 25% for Laboratory Control Samples. In addition, a duplicate sample was run using separation resin and that result was within the acceptance range. The results from the two methods compared with a relative percent difference (RPD) of 11.1%, which meets the labs duplicate acceptance criteria. The Laboratory has concluded that these positive biases were isolated occurrences and that the overall process is within control. The lab will complete PT studies for these parameters as they become available to verify that these were isolated incidences. (CARR190826-1250) d) One of the two ERA 3rd quarter 2019 water gross alpha results was evaluated as Not Acceptable7KHUHSRUWHGYDOXHZDVS&L/

DQGWKHNQRZQUHVXOWZDVS&L/ DFFHSWDQFHUDQJHRI-

S&L/ 7KHDQDO\VLVGDWDZDVUHYLHZHGDQGQRHUURUVZHUe found. The investigation into the sample preparation did not result in any contributors to the high bias. This analysis was performed by Co-Precipitation. The Laboratory also reported the gross alpha analysis by the evaporation method (EPA 900.0) and had an 26

acceptable result. The labs alpha results between the two methods compared with a relative percent difference (RPD) of 9.45%, which meets the labs duplicate acceptance criteria. The Laboratory has concluded that these positive biases were isolated occurrences and that the overall process is within control. The lab will complete PT studies for these parameters as they become available to verify that these were isolated incidences. (CARR190826-1250)

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 27

Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

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

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2019 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2019 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 25 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) 13 1 <LLD <LLD 0 DRINKING WATER GR-B 48 4 3.3 3.5 3.6 16C2 INDICATOR 0 (PCI/LITER) (23/36) (7/12) (5/12) CITIZENS HOME WATER COMPANY 2.2 - 5.8 2.6 - 4.5 2.6 - 5.7 2.66 MILES SSE OF SITE H-3 16 200 <LLD <LLD - 0 I-131 (LOW LVL) 48 1 <LLD <LLD - 0

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2019 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2019 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 3055 3114 3114 29C1 CONTROL 0 (2/2) (2/2) (2/2) POTTSTOWN VICINITY 3004 - 3105 2975 - 3252 2975 - 3252 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 I-131 NA <LLD <LLD - 0 CS-134 130 <LLD <LLD - 0 CS-137 150 <LLD <LLD - 0

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2019 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2019 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 3401 2502 3401 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL 3088 - 3713 1804 - 3200 3088 - 3713 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 A-3 I-131 NA <LLD <LLD - 0 CS-134 130 <LLD <LLD - 0 CS-137 150 <LLD <LLD - 0 SEDIMENT GAMMA 9 (PCI/KG DRY) BE-7 NA 2367 <LLD 2420 16B2 INDICATOR 0 (3/6) (2/3) LINFIELD BRIDGE 1366 - 3474 1366 - 3474 1.35 MILES SSE OF SITE K-40 NA 0 14677 13373 15333 16C4 INDICATOR (6/6) (3/3) (3/3) VINCENT DAM MN-54 NA 13680 - 16030 12230 - 15100 14590 - 16030 2.18 MILES SSE OF SITE 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-137 180 100 <LLD 100 16B2 INDICATOR 0 (1/6) (1/3) LINFIELD BRIDGE 1.35 MILES SSE OF SITE

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2019 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2019 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 361 10 14 14 16 13S4 INDICATOR 0 (E-03 PCI/CU.METER) (308/309) (51/52) (51/51) LONGVIEW ROAD 5 - 31 8 - 27 8 - 27 1186 FEET SE OF SITE GAMMA 28 BE-7 NA 74 80 88 13S4 INDICATOR 0 (24/24) (4/4) (4/4) LONGVIEW ROAD 43 - 115 74 - 94 66 - 115 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 361 (E-03 PCI/CU.METER) I-131 (GELI) 70 <LLD <LLD - 0 MILK I-131 (LOW LVL) 92 1 <LLD <LLD - 0 (PCI/LITER)

GAMMA 92 K-40 NA 1242 1273 1303 23F1 CONTROL 0 (66/66) (26/26) (22/22) 875 - 1521 1020 - 1505 1038 - 1505 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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2019 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2019 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 34 (PCI/KG WET) BE-7 NA 1130 1645 1645 31G1 CONTROL 0 (13/22) (10/12) (10/12) PROUTS'S JOLLYVIEW FARM (CONTROL) 335 - 3332 153 - 3719 153 - 3719 71,808 FEET NW K-40 NA 5460 5367 5635 11S3 INDICATOR 0 (22/22) (12/12) (11/11) LGS INFORMATION CENTER 3358 - 9170 2885 - 8971 3358 - 8816 0.35 MILES ESE 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 1680 <LLD 1680 13S3 INDICATOR 0 (8/22) (8/11) VINCENT DAM 797 - 2871 797 - 2871 0.24 MILES SE OF SITE TH-228 NA 106 131 131 31G1 CONTROL 0 (9/22) (8/12) (8/12) PROUTS'S JOLLYVIEW FARM (CONTROL) 51 - 244 86 - 218 86 - 218 71,808 FEET NW TH-232 NA <LLD 99 99 31G1 CONTROL 0 (2/12) (2/12) PROUTS'S JOLLYVIEW FARM (CONTROL) 91 - 107 91 - 107 71,808 FEET NW 0 DIRECT RADIATION OSLD-QUARTERLY 320 NA 17.1 22.3 24.6 13S2 INDICATOR 0 (MILLI-ROENTGEN/STD.MO.) (312/312) (8/8) (8/8) 500 KV SUBSTATION 11.3 - 17.1 21.3 - 24.0 23.4 - 25.4 0.41 MILES SE

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, 2019 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, 2019 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, 2019 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Monthly composite CY-ES-240 EIS Collection of water Surface Gamma from a continuous samples for Radiological Analysis 2 gallon Water Spectroscopy EIS, CY-ES-205 Gamma Counting Using the HPGe water compositor (Limerick Generating Station)

Detector with the Genie PC Counting System TBE, TBE-2011 Tritium Analysis in Drinking Water by Quarterly composite CY-ES-240 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 Monthly composite CY-ES-240 EIS Collection of water in 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-240 EIS Collection of water Drinking I-131 from a continuous samples for Radiological Analysis 2 gallon B-4 Water EIS, CY-ES-205 Gamma Counting Using the HPGe water compositor (Limerick Generating Station)

Detector with the Genie PC Counting System TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Monthly composite CY-ES-240 EIS Collection of water Drinking Gamma from a continuous samples for Radiological Analysis 2 gallon Water Spectroscopy EIS, CY-ES-205 Gamma Counting Using the HPGe water compositor (Limerick Generating Station)

Detector with the Genie PC Counting System TBE, TBE-2011 Tritium Analysis in Drinking Water by Quarterly composite CY-ES-240 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 TBE-2007 Gamma-Emitting Radioisotope Analysis Spectroscopy electroshocking or (wet)

(Limerick 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, 2019 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity One-week composite CY-ES-237 Sample Collection of Air 1 filter in Various Matrices Air of continuous air Iodine and Air Particulate for (approximately Gross Beta Particulates sampling through Radiological Analysis 280 cubic EIS, CY-ES-206 Operation of the Tennelec S5E glass fiber filter paper (Limerick Generating Station) meters weekly)

Proportional Counter TBE, TBE-2023 Compositing of 13 filters TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Samples Air Gamma Quarterly composite of (approximately Particulates Spectroscopy each station 3600 cubic EIS, CY-ES-205 Gamma Counting Using the HPGe CY-ES-204 Sample Preparation for meters) Detector with the Genie PC Counting System Gamma and Beta Counting One-week composite CY-ES-237 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 280 cubic EIS, CY-ES-205 Gamma Counting Using the HPGe charcoal filter (Limerick Generating Station) meters weekly) Detector with the Genie PC Counting System Bi-weekly grab sample TBE, TBE-2012 Radioiodine in Various Matrices B-5 CY-ES-238 EIS Sample Collection when cows are on Milk I-131 for Gamma Counting - Milk 2 gallon pasture; Monthly all EIS, CY-ES-205 Gamma Counting Using the HPGe (Limerick Generating Station) other times Detector with the Genie PC Counting System Bi-weekly grab sample TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis CY-ES-238 EIS Sample Collection Gamma when cows are on Milk for Gamma Counting - Milk 2 gallon Spectroscopy pasture; Monthly all EIS, CY-ES-205 Gamma Counting Using the HPGe (Limerick Generating Station) other times Detector with the Genie PC Counting System Quarterly DLRs CY-ES-239 EIS Sample Collection Thermoluminescent DLR comprised of two for OSLD 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, 2019 B-6

Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2019 B-7

Figure B-3 Environmental Sampling Locations Greater than 26,400 Feet from the Limerick Generating Station, 2019 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, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 13B1 24S1 01/02/19 - 04/02/19 < 194 < 189 04/02/19 - 07/02/19 < 191 < 190 07/02/19 - 09/30/19 < 184 < 184 09/30/19 - 12/30/19 < 188 < 187 MEAN - -

Table C-I.2 CONCENTRATIONS OF I-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 24S1 01/02/19 - 01/28/19 < 0.7 01/28/19 - 02/26/19 < 0.6 02/26/19 - 04/02/19 < 1.0 04/02/19 - 04/29/19 < 0.7 04/29/19 - 06/03/19 < 0.8 06/03/19 - 07/02/19 < 0.8 07/02/19 - 07/30/19 < 0.8 07/30/19 - 09/03/19 < 0.9 09/03/19 - 09/30/19 < 0.8 09/30/19 - 10/28/19 < 0.9 10/28/19 - 12/03/19 < 0.7 11/25/19 - 12/03/19 < 0.6 12/03/19 - 12/30/19 < 0.7 MEAN -

C-1

Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 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 01/02/19 - 01/28/19 < 7 < 8 < 19 < 8 < 20 < 7 < 13 < 12 < 7 < 7 < 32 < 12 01/28/19 - 02/26/19 < 7 < 7 < 13 < 9 < 14 < 7 < 11 < 12 < 9 < 7 < 32 < 12 02/26/19 - 04/02/19 < 6 < 3 < 12 < 4 < 6 < 7 < 11 < 11 < 7 < 6 < 30 < 12 04/02/19 - 04/29/19 < 4 < 6 < 10 < 4 < 9 < 6 < 10 < 10 < 7 < 6 < 27 < 11 04/29/19 - 06/03/19 < 4 < 5 < 14 < 5 < 9 < 4 < 9 < 12 < 6 < 6 < 27 < 9 06/03/19 - 07/02/19 < 5 < 6 < 11 < 6 < 11 < 6 < 9 < 10 < 6 < 6 < 26 < 7 07/02/19 - 07/30/19 < 6 < 7 < 11 < 7 < 13 < 7 < 15 < 12 < 8 < 8 < 30 < 10 07/30/19 - 09/03/19 < 7 < 5 < 13 < 8 < 13 < 9 < 12 < 14 < 9 < 8 < 29 < 14 09/03/19 - 09/30/19 < 8 < 8 < 15 < 7 < 15 < 9 < 9 < 13 < 8 < 8 < 36 < 13 09/30/19 - 10/28/19 < 7 < 6 < 14 < 9 < 12 < 6 < 9 < 11 < 7 < 6 < 28 < 14 10/28/19 - 12/03/19 < 7 < 4 < 13 < 7 < 10 < 6 < 12 < 11 < 6 < 5 < 25 < 11 12/03/19 - 12/30/19 < 7 < 7 < 15 < 7 < 15 < 7 < 14 < 13 < 6 < 7 < 35 < 6 C-2 MEAN - - - - - - - - - - - -

24S1 01/02/19 - 01/28/19 < 6 < 7 < 17 < 6 < 14 < 7 < 14 < 10 < 6 < 8 < 32 < 13 01/28/19 - 02/26/19 < 7 < 8 < 15 < 7 < 15 < 7 < 14 < 15 < 9 < 7 < 37 < 13 02/26/19 - 04/02/19 < 4 < 6 < 14 < 7 < 17 < 6 < 13 < 13 < 7 < 7 < 29 < 9 04/02/19 - 04/29/19 < 4 < 6 < 12 < 5 < 9 < 7 < 11 < 11 < 7 < 6 < 31 < 12 04/29/19 - 06/03/19 < 6 < 6 < 10 < 6 < 10 < 5 < 8 < 13 < 6 < 5 < 33 < 6 06/03/19 - 07/02/19 < 5 < 6 < 9 < 7 < 10 < 7 < 10 < 9 < 7 < 7 < 27 < 10 07/02/19 - 07/30/19 < 7 < 8 < 15 < 7 < 14 < 8 < 11 < 12 < 8 < 8 < 38 < 10 07/30/19 - 09/03/19 < 6 < 6 < 12 < 6 < 11 < 7 < 13 < 14 < 6 < 6 < 33 < 10 09/03/19 - 09/30/19 < 7 < 6 < 18 < 7 < 14 < 8 < 12 < 12 < 8 < 8 < 31 < 12 09/30/19 - 10/28/19 < 6 < 6 < 14 < 6 < 12 < 9 < 12 < 14 < 8 < 5 < 37 < 11 10/28/19 - 12/03/19 < 6 < 6 < 13 < 8 < 13 < 7 < 10 < 9 < 8 < 7 < 32 < 12 11/25/19 - 12/03/19 < 8 < 6 < 16 < 8 < 17 < 7 < 11 < 9 < 8 < 8 < 27 < 6 12/03/19 - 12/30/19 < 7 < 6 < 13 < 6 < 12 < 7 < 12 < 14 < 6 < 7 < 34 < 12 MEAN - - - - - - - - - - - -

Table C-II.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 01/02/19 - 01/28/19 2.4 +/- 1.5 2.8 +/- 1.5 < 2.3 2.6 +/- 1.5 01/28/19 - 02/26/19 < 2.3 2.2 +/- 1.5 < 2.3 < 2.2 02/26/19 - 04/02/19 < 2.3 < 2.2 < 2.3 < 2.2 04/02/19 - 04/29/19 2.4 +/- 1.6 < 2.2 < 2.4 2.6 +/- 1.6 04/29/19 - 06/03/19 < 2.3 < 2.3 2.6 +/- 1.7 < 2.2 06/03/19 - 07/02/19 3.1 +/- 1.6 2.7 +/- 1.6 3.2 +/- 1.7 4.5 +/- 1.8 07/02/19 - 07/30/19 3.3 +/- 1.6 3.1 +/- 1.7 2.6 +/- 1.7 3.7 +/- 1.7 07/30/19 - 09/03/19 3.6 +/- 1.6 3.1 +/- 1.5 < 2.2 < 2.2 09/03/19 - 09/30/19 4.1 +/- 2.0 2.8 +/- 1.9 < 2.8 4.4 +/- 2.0 09/30/19 - 10/28/19 4.0 +/- 1.7 5.8 +/- 1.8 5.7 +/- 1.8 3.8 +/- 1.6 10/28/19 - 12/03/19 4.2 +/- 1.7 2.8 +/- 1.6 3.9 +/- 1.6 3.1 +/- 1.6 12/03/19 - 12/30/19 2.2 +/- 1.3 2.6 +/- 1.4 < 1.9 < 1.9 MEAN +/- 2 STD DEV 3.2 +/- 1.6 3.1 +/- 2.1 3.6 +/- 2.6 3.5 +/- 1.6 Table C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 01/02/19 - 04/02/19 < 192 < 195 < 195 < 189 04/02/19 - 07/02/19 < 188 < 193 < 190 < 187 07/02/19 - 09/30/19 < 185 < 182 < 188 < 186 09/30/19 - 12/30/19 < 188 < 187 < 188 < 185 MEAN - - - -

Table C-II.3 CONCENTRATIONS OF I-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 01/02/19 - 01/28/19 < 0.8 < 0.8 < 0.8 < 0.9 01/28/19 - 02/26/19 < 0.5 < 0.7 < 0.7 < 0.7 02/26/19 - 04/02/19 < 1.0 < 0.9 < 0.9 < 1.0 04/02/19 - 04/29/19 < 0.9 < 0.7 < 0.8 < 0.7 04/29/19 - 06/03/19 < 0.7 < 0.9 < 0.8 < 0.7 06/03/19 - 07/02/19 < 0.8 < 0.7 < 0.7 < 0.9 07/02/19 - 07/30/19 < 0.8 < 0.8 < 0.6 < 0.8 07/30/19 - 09/03/19 < 0.9 < 0.8 < 0.9 < 0.9 09/03/19 - 09/30/19 < 0.8 < 0.9 < 0.9 < 0.8 09/30/19 - 10/28/19 < 0.9 < 0.8 < 0.7 < 0.9 10/28/19 - 12/03/19 < 0.9 < 0.9 < 0.7 < 0.8 12/03/19 - 12/30/19 < 0.9 < 0.8 < 0.7 < 0.7 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, 2019 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 01/02/19 - 01/28/19 < 5 < 5 < 12 < 6 < 12 < 7 < 9 < 5 < 6 < 27 < 9 01/28/19 - 02/26/19 < 6 < 6 < 11 < 6 < 12 < 5 < 10 < 7 < 7 < 30 < 8 02/26/19 - 04/02/19 < 7 < 6 < 14 < 8 < 11 < 7 < 11 < 7 < 5 < 34 < 8 04/02/19 - 04/29/19 < 5 < 5 < 13 < 5 < 10 < 6 < 8 < 8 < 6 < 27 < 10 04/29/19 - 06/03/19 < 6 < 6 < 15 < 7 < 12 < 8 < 11 < 7 < 6 < 30 < 14 06/03/19 - 07/02/19 < 6 < 5 < 14 < 6 < 13 < 7 < 10 < 7 < 6 < 27 < 9 07/02/19 - 07/30/19 < 6 < 5 < 12 < 6 < 16 < 7 < 10 < 6 < 7 < 28 < 10 07/30/19 - 09/03/19 < 5 < 7 < 13 < 6 < 13 < 7 < 9 < 7 < 6 < 34 < 10 09/03/19 - 09/30/19 < 5 < 7 < 9 < 6 < 14 < 6 < 11 < 6 < 7 < 34 < 11 09/30/19 - 10/28/19 < 5 < 7 < 14 < 8 < 16 < 9 < 14 < 7 < 7 < 35 < 11 10/28/19 - 12/03/19 < 7 < 6 < 15 < 8 < 15 < 7 < 11 < 8 < 7 < 33 < 12 12/03/19 - 12/30/19 < 6 < 6 < 13 < 7 < 14 < 6 < 9 < 5 < 5 < 31 < 12 C-4 MEAN - - - - - - - - - - -

15F7 01/02/19 - 01/28/19 < 8 < 7 < 13 < 8 < 11 < 9 < 10 < 5 < 7 < 37 < 12 01/28/19 - 02/26/19 < 5 < 6 < 11 < 6 < 12 < 6 < 10 < 6 < 6 < 30 < 8 02/26/19 - 04/02/19 < 7 < 7 < 13 < 8 < 15 < 6 < 12 < 7 < 7 < 35 < 13 04/02/19 - 04/29/19 < 4 < 6 < 8 < 7 < 10 < 6 < 10 < 6 < 5 < 26 < 9 04/29/19 - 06/03/19 < 6 < 6 < 14 < 5 < 10 < 5 < 10 < 5 < 7 < 37 < 10 06/03/19 - 07/02/19 < 6 < 5 < 17 < 11 < 13 < 7 < 10 < 8 < 7 < 33 < 13 07/02/19 - 07/30/19 < 6 < 5 < 11 < 7 < 15 < 8 < 13 < 6 < 7 < 27 < 9 07/30/19 - 09/03/19 < 6 < 7 < 13 < 7 < 10 < 8 < 9 < 6 < 7 < 37 < 12 09/03/19 - 09/30/19 < 7 < 4 < 12 < 7 < 13 < 6 < 10 < 8 < 5 < 31 < 8 09/30/19 - 10/28/19 < 7 < 8 < 12 < 8 < 14 < 8 < 12 < 7 < 7 < 37 < 7 10/28/19 - 12/03/19 < 6 < 6 < 18 < 9 < 15 < 6 < 11 < 6 < 6 < 34 < 9 12/03/19 - 12/30/19 < 6 < 6 < 14 < 6 < 14 < 6 < 13 < 8 < 6 < 34 < 14 MEAN - - - - - - - - - - -

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 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 01/02/19 - 01/28/19 < 6 < 7 < 14 < 6 < 13 < 5 < 10 < 6 < 5 < 31 < 13 01/28/19 - 02/26/19 < 6 < 5 < 13 < 8 < 12 < 6 < 12 < 9 < 8 < 31 < 7 02/26/19 - 04/02/19 < 7 < 5 < 12 < 6 < 13 < 7 < 11 < 7 < 6 < 31 < 8 04/02/19 - 04/29/19 < 4 < 7 < 14 < 7 < 10 < 6 < 10 < 7 < 6 < 31 < 10 04/29/19 - 06/03/19 < 6 < 5 < 14 < 7 < 15 < 7 < 10 < 4 < 5 < 37 < 13 06/03/19 - 07/02/19 < 7 < 6 < 10 < 6 < 12 < 6 < 11 < 6 < 6 < 31 < 9 07/02/19 - 07/30/19 < 8 < 7 < 13 < 7 < 15 < 9 < 15 < 9 < 8 < 36 < 13 07/30/19 - 09/03/19 < 7 < 7 < 12 < 6 < 13 < 8 < 11 < 8 < 7 < 39 < 12 09/03/19 - 09/30/19 < 6 < 6 < 9 < 7 < 20 < 6 < 11 < 6 < 7 < 36 < 14 09/30/19 - 10/28/19 < 7 < 7 < 13 < 7 < 17 < 7 < 12 < 7 < 8 < 35 < 15 10/28/19 - 12/03/19 < 5 < 7 < 13 < 8 < 13 < 6 < 12 < 9 < 7 < 28 < 8 12/03/19 - 12/30/19 < 4 < 5 < 11 < 7 < 13 < 6 < 8 < 6 < 6 < 29 < 12 C-5 MEAN - - - - - - - - - - -

28F3 01/02/19 - 01/28/19 < 7 < 7 < 16 < 6 < 16 < 9 < 10 < 7 < 7 < 28 < 10 01/28/19 - 02/26/19 < 8 < 7 < 13 < 7 < 13 < 7 < 13 < 8 < 7 < 32 < 12 02/26/19 - 04/02/19 < 6 < 5 < 15 < 8 < 16 < 6 < 13 < 6 < 7 < 36 < 14 04/02/19 - 04/29/19 < 4 < 5 < 10 < 6 < 10 < 5 < 11 < 6 < 5 < 25 < 9 04/29/19 - 06/03/19 < 6 < 6 < 13 < 6 < 11 < 5 < 10 < 5 < 6 < 31 < 10 06/03/19 - 07/02/19 < 7 < 6 < 15 < 7 < 15 < 7 < 10 < 7 < 7 < 30 < 10 07/02/19 - 07/30/19 < 4 < 5 < 10 < 10 < 14 < 6 < 12 < 8 < 8 < 28 < 15 07/30/19 - 09/03/19 < 6 < 5 < 12 < 6 < 10 < 5 < 10 < 6 < 5 < 27 < 14 09/03/19 - 09/30/19 < 5 < 4 < 14 < 9 < 14 < 7 < 10 < 7 < 7 < 31 < 15 09/30/19 - 10/28/19 < 5 < 6 < 9 < 7 < 10 < 8 < 11 < 7 < 7 < 34 < 11 10/28/19 - 12/03/19 < 6 < 8 < 14 < 7 < 12 < 7 < 12 < 6 < 7 < 27 < 11 12/03/19 - 12/30/19 < 5 < 5 < 10 < 7 < 13 < 5 < 12 < 6 < 7 < 34 < 10 MEAN - - - - - - - - - - -

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

SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 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 06/07/19 3713 +/- 837 < 48 < 52 < 139 < 60 < 130 < 131 < 56 < 56 11/05/19 3088 +/- 641 < 46 < 36 < 81 < 43 < 84 < 63 < 49 < 44 MEAN +/- 2 STD DEV 3401 +/- 884 - - - - - - - -

16C5 BOTTOM FEEDER 06/07/19 3004 +/- 775 < 59 < 58 < 128 < 55 < 114 < 110 < 64 < 49 11/05/19 3105 +/- 734 < 36 < 36 < 85 < 36 < 86 < 53 < 47 < 43 MEAN +/- 2 STD DEV 3055 +/- 143 - - - - - - - -

C-6 29C1 PREDATOR 05/10/19 3200 +/- 946 < 54 < 55 < 137 < 54 < 115 < 67 < 38 < 45 11/07/19 1804 +/- 678 < 44 < 41 < 95 < 42 < 87 < 85 < 61 < 54 MEAN +/- 2 STD DEV 2502 +/- 1974 - - - - - - - -

29C1 BOTTOM FEEDER 05/10/19 3252 +/- 1095 < 58 < 53 < 103 < 61 < 125 < 81 < 53 < 55 11/07/19 2975 +/- 977 < 48 < 55 < 122 < 49 < 98 < 64 < 44 < 53 MEAN +/- 2 STD DEV 3114 +/- 392 - - - - - - - -

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, 2019 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 06/12/19 3474 +/- 780 13680 +/- 1535 < 89 < 79 < 89 < 98 < 117 100 +/- 54 12/04/19 1366 +/- 888 14030 +/- 2110 < 125 < 113 < 94 < 146 < 142 < 137 12/04/19 < 856 14350 +/- 1904 < 102 < 87 < 91 < 128 < 130 < 125 MEAN +/- 2 STD DEV 2420 +/- 2981 14020 +/- 670 - - - - - 100 +/- 0 16C4 06/12/19 2261 +/- 515 15380 +/- 1288 < 65 < 61 < 75 < 68 < 86 < 77 12/04/19 < 681 16030 +/- 2143 < 102 < 87 < 101 < 105 < 104 < 83 12/04/19 < 783 14590 +/- 1880 < 102 < 81 < 78 < 125 < 128 < 95 MEAN +/- 2 STD DEV 2261 +/- 0 15333 +/- 1442 - - - - - -

C-7 33A2 06/12/19 < 550 12790 +/- 1512 < 84 < 57 < 76 < 77 < 96 < 66 12/04/19 < 737 15100 +/- 1840 < 94 < 83 < 78 < 144 < 115 < 91 12/04/19 < 848 12230 +/- 1904 < 109 < 80 < 99 < 139 < 112 < 107 MEAN +/- 2 STD DEV - 13373 +/- 3043 - - - - - -

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, 2019 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 01/02/19 - 01/07/19 16 +/- 5 8 +/- 5 16 +/- 5 13 +/- 5 13 +/- 5 15 +/- 5 15 +/- 5 01/07/19 - 01/14/19 11 +/- 4 12 +/- 4 15 +/- 4 9 +/- 3 11 +/- 4 12 +/- 4 10 +/- 4 01/14/19 - 01/22/19 11 +/- 4 13 +/- 4 18 +/- 4 14 +/- 4 13 +/- 4 15 +/- 4 11 +/- 4 01/22/19 - 01/28/19 19 +/- 5 12 +/- 4 17 +/- 5 15 +/- 5 15 +/- 5 16 +/- 5 14 +/- 5 01/28/19 - 02/04/19 23 +/- 5 16 +/- 2 27 +/- 5 21 +/- 5 20 +/- 5 16 +/- 4 25 +/- 5 02/04/19 - 02/11/19 17 +/- 4 14 +/- 4 20 +/- 4 15 +/- 4 15 +/- 4 17 +/- 4 17 +/- 4 02/11/19 - 02/18/19 17 +/- 4 15 +/- 4 23 +/- 4 17 +/- 4 14 +/- 4 15 +/- 4 10 +/- 4 02/18/19 - 02/26/19 17 +/- 4 20 +/- 5 22 +/- 4 18 +/- 4 18 +/- 4 21 +/- 4 16 +/- 4 02/26/19 - 03/04/19 19 +/- 5 20 +/- 5 19 +/- 5 17 +/- 4 18 +/- 5 14 +/- 4 18 +/- 4 03/04/19 - 03/11/19 15 +/- 4 16 +/- 4 21 +/- 4 18 +/- 4 16 +/- 4 15 +/- 4 13 +/- 4 03/11/19 - 03/18/19 19 +/- 4 17 +/- 4 24 +/- 4 16 +/- 4 19 +/- 4 12 +/- 4 17 +/- 4 03/18/19 - 03/25/19 12 +/- 4 13 +/- 4 17 +/- 4 10 +/- 4 13 +/- 4 10 +/- 4 11 +/- 4 03/25/19 - 04/02/19 13 +/- 4 16 +/- 4 20 +/- 4 12 +/- 3 15 +/- 4 15 +/- 4 14 +/- 4 04/02/19 - 04/08/19 12 +/- 4 13 +/- 4 17 +/- 5 12 +/- 4 12 +/- 4 (1) 12 +/- 4 04/08/19 - 04/15/19 6 +/- 4 < 5 8 +/- 4 7 +/- 4 8 +/- 4 8 +/- 4 < 5 04/15/19 - 04/22/19 8 +/- 4 9 +/- 4 12 +/- 4 6 +/- 3 7 +/- 3 5 +/- 3 8 +/- 4 04/22/19 - 04/29/19 6 +/- 3 7 +/- 4 16 +/- 4 10 +/- 4 8 +/- 4 7 +/- 4 12 +/- 4 04/29/19 - 05/07/19 7 +/- 3 8 +/- 3 10 +/- 3 7 +/- 3 6 +/- 3 7 +/- 3 8 +/- 3 05/07/19 - 05/13/19 12 +/- 4 13 +/- 4 15 +/- 4 11 +/- 4 13 +/- 4 6 +/- 4 11 +/- 4 05/13/19 - 05/20/19 15 +/- 4 17 +/- 4 20 +/- 4 15 +/- 4 15 +/- 4 14 +/- 4 20 +/- 5 05/20/19 - 05/28/19 10 +/- 4 7 +/- 3 14 +/- 4 6 +/- 3 8 +/- 3 11 +/- 4 9 +/- 3 05/28/19 - 06/03/19 8 +/- 5 12 +/- 5 (1) 13 +/- 5 11 +/- 5 7 +/- 5 9 +/- 5 06/03/19 - 06/11/19 10 +/- 3 13 +/- 4 14 +/- 4 (1) 11 +/- 3 11 +/- 4 13 +/- 4 06/11/19 - 06/17/19 11 +/- 4 12 +/- 5 12 +/- 5 10 +/- 4 11 +/- 4 10 +/- 4 12 +/- 5 06/17/19 - 06/24/19 8 +/- 4 9 +/- 4 14 +/- 4 10 +/- 4 8 +/- 4 10 +/- 4 11 +/- 4 06/24/19 - 07/02/19 9 +/- 4 12 +/- 4 19 +/- 4 11 +/- 4 12 +/- 4 7 +/- 4 8 +/- 4 07/02/19 - 07/08/19 12 +/- 4 14 +/- 5 21 +/- 5 12 +/- 4 12 +/- 4 17 +/- 5 15 +/- 5 07/08/19 - 07/15/19 12 +/- 4 14 +/- 4 21 +/- 5 11 +/- 4 14 +/- 4 12 +/- 4 14 +/- 4 07/15/19 - 07/22/19 9 +/- 4 9 +/- 4 12 +/- 4 10 +/- 4 11 +/- 4 9 +/- 4 9 +/- 3 07/22/19 - 07/30/19 16 +/- 4 14 +/- 4 13 +/- 3 13 +/- 4 13 +/- 4 17 +/- 4 14 +/- 3 07/30/19 - 08/05/19 22 +/- 5 19 +/- 5 22 +/- 5 22 +/- 5 17 +/- 5 17 +/- 5 20 +/- 5 08/05/19 - 08/12/19 13 +/- 4 18 +/- 4 15 +/- 4 16 +/- 4 15 +/- 4 16 +/- 4 17 +/- 4 08/12/19 - 08/19/19 23 +/- 5 25 +/- 5 23 +/- 4 25 +/- 5 26 +/- 5 21 +/- 4 27 +/- 5 08/19/19 - 08/26/19 12 +/- 4 8 +/- 4 16 +/- 4 16 +/- 4 18 +/- 4 13 +/- 4 16 +/- 4 08/26/19 - 09/03/19 13 +/- 4 12 +/- 3 12 +/- 4 14 +/- 4 13 +/- 4 12 +/- 3 14 +/- 4 09/03/19 - 09/10/19 14 +/- 4 17 +/- 4 14 +/- 4 17 +/- 4 16 +/- 4 15 +/- 4 16 +/- 4 09/10/19 - 09/16/19 19 +/- 4 23 +/- 5 19 +/- 4 23 +/- 5 20 +/- 5 20 +/- 4 21 +/- 5 09/16/19 - 09/23/19 22 +/- 4 22 +/- 4 21 +/- 4 23 +/- 4 20 +/- 4 18 +/- 4 24 +/- 4 09/23/19 - 09/30/19 15 +/- 4 17 +/- 4 15 +/- 4 16 +/- 4 22 +/- 4 18 +/- 4 18 +/- 4 09/30/19 - 10/07/19 9 +/- 3 8 +/- 3 8 +/- 3 9 +/- 3 10 +/- 3 9 +/- 3 9 +/- 3 10/07/19 - 10/14/19 14 +/- 4 17 +/- 4 14 +/- 4 12 +/- 4 16 +/- 4 14 +/- 4 13 +/- 4 10/14/19 - 10/21/19 14 +/- 4 14 +/- 4 14 +/- 4 15 +/- 4 13 +/- 3 12 +/- 3 13 +/- 4 10/21/19 - 10/28/19 12 +/- 4 12 +/- 4 12 +/- 4 10 +/- 4 9 +/- 4 8 +/- 4 13 +/- 4 10/28/19 - 11/05/19 9 +/- 3 9 +/- 3 8 +/- 3 10 +/- 3 9 +/- 3 9 +/- 3 9 +/- 3 11/05/19 - 11/11/19 16 +/- 4 14 +/- 4 19 +/- 4 12 +/- 4 20 +/- 4 16 +/- 4 15 +/- 4 11/11/19 - 11/18/19 13 +/- 4 14 +/- 4 9 +/- 3 17 +/- 4 14 +/- 4 11 +/- 4 16 +/- 4 11/18/19 - 11/25/19 14 +/- 4 13 +/- 4 11 +/- 4 15 +/- 4 18 +/- 4 11 +/- 4 14 +/- 4 11/25/19 - 12/03/19 11 +/- 3 9 +/- 3 8 +/- 3 11 +/- 3 11 +/- 3 10 +/- 3 11 +/- 3 12/03/19 - 12/09/19 16 +/- 4 12 +/- 4 12 +/- 4 15 +/- 4 13 +/- 4 11 +/- 4 14 +/- 4 12/09/19 - 12/16/19 13 +/- 3 14 +/- 3 12 +/- 3 15 +/- 4 15 +/- 4 15 +/- 4 16 +/- 4 12/16/19 - 12/23/19 16 +/- 4 19 +/- 4 15 +/- 4 18 +/- 4 21 +/- 4 16 +/- 4 18 +/- 4 12/23/19 - 12/30/19 27 +/- 5 31 +/- 5 23 +/- 4 30 +/- 5 30 +/- 5 29 +/- 5 24 +/- 4 MEAN +/- 2 STD DEV 14 +/- 9 14 +/- 10 16 +/- 9 14 + 10 14 +/- 9 13 +/- 9 14 +/- 9 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, 2019 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 01/02/19 - 02/04/19 8 27 15 +/- 9 01/02/19 - 02/04/19 11 20 15 +/- 5 01/02/19 - 02/04/19 10 25 15 +/- 12 02/04/19 - 02/26/19 14 23 18 +/- 6 02/04/19 - 02/26/19 14 21 17 +/- 5 02/04/19 - 02/26/19 10 17 14 +/- 7 02/26/19 - 04/02/19 10 24 17 +/- 7 02/26/19 - 04/02/19 10 19 15 +/- 6 02/26/19 - 04/02/19 11 18 15 +/- 6 04/02/19 - 04/29/19 6 17 10 +/- 7 04/02/19 - 04/29/19 5 12 8 +/- 4 04/02/19 - 04/29/19 8 12 11 +/- 4 04/29/19 - 06/03/19 6 20 12 +/- 8 04/29/19 - 06/03/19 6 15 10 +/- 7 04/29/19 - 06/03/19 8 20 11 +/- 10 06/03/19 - 07/02/19 8 19 12 +/- 6 06/03/19 - 07/02/19 7 12 10 +/- 3 06/03/19 - 07/02/19 8 13 11 +/- 4 07/02/19 - 07/30/19 9 21 13 +/- 7 07/02/19 - 07/30/19 9 17 13 +/- 6 07/02/19 - 07/30/19 9 15 13 +/- 6 07/30/19 - 09/03/19 8 25 17 +/- 10 07/30/19 - 09/03/19 12 26 17 +/- 8 07/30/19 - 09/03/19 14 27 19 +/- 10 09/03/19 - 09/30/19 14 23 18 +/- 7 09/03/19 - 09/30/19 15 22 19 +/- 5 09/03/19 - 09/30/19 16 24 20 +/- 7 09/30/19 - 10/28/19 8 17 12 +/- 5 09/30/19 - 10/28/19 8 16 11 +/- 5 09/30/19 - 10/28/19 9 13 12 +/- 4 C-9 10/28/19 - 12/03/19 8 19 12 +/- 6 10/28/19 - 12/03/19 9 20 13 +/- 8 10/28/19 - 12/03/19 9 16 13 +/- 6 12/03/19 - 12/30/19 12 31 18 +/- 13 12/03/19 - 12/30/19 11 30 19 +/- 14 12/03/19 - 12/30/19 14 24 18 +/- 9 01/02/19 - 12/30/19 6 31 15 +/- 10 01/02/19 - 12/30/19 5 30 14 +/- 9 01/02/19 - 12/30/19 8 27 14 +/- 9

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 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 01/02/19 - 04/02/19 91 +/- 21 < 3 < 3 < 3 < 3 < 3 04/02/19 - 07/02/19 78 +/- 23 < 3 < 4 < 3 < 3 < 2 07/02/19 - 09/30/19 84 +/- 19 < 2 < 2 < 2 < 2 < 2 09/30/19 - 12/30/19 42 +/- 14 < 2 < 2 < 2 < 1 < 2 MEAN +/- 2 STD DEV 74 +/- 43 - - - - -

11S1 01/02/19 - 04/02/19 81 +/- 19 < 2 < 2 < 3 < 2 < 2 04/02/19 - 07/02/19 75 +/- 31 < 2 < 3 < 3 < 4 < 3 07/02/19 - 09/30/19 67 +/- 20 < 2 < 2 < 3 < 2 < 1 09/30/19 - 12/30/19 45 +/- 17 < 3 < 2 < 3 < 2 < 3 MEAN +/- 2 STD DEV 67 +/- 31 - - - - -

13S4 01/02/19 - 04/02/19 115 +/- 22 < 3 < 3 < 3 < 4 < 3 04/02/19 - 07/02/19 94 +/- 23 < 2 < 2 < 2 < 2 < 2 07/02/19 - 09/30/19 77 +/- 19 < 2 < 2 < 3 < 2 < 2 09/30/19 - 12/30/19 66 +/- 41 < 8 < 8 < 8 < 9 < 7 MEAN +/- 2 STD DEV 88 +/- 43 - - - - -

14S1 01/02/19 - 04/02/19 88 +/- 20 < 2 < 3 < 2 < 3 < 3 04/02/19 - 07/02/19 69 +/- 20 < 2 < 3 < 2 < 3 < 2 07/02/19 - 09/30/19 70 +/- 18 < 2 < 2 < 3 < 2 < 1 09/30/19 - 12/30/19 54 +/- 16 < 2 < 1 < 2 < 2 < 2 MEAN +/- 2 STD DEV 70 +/- 28 - - - - -

15D1 01/02/19 - 04/02/19 87 +/- 26 < 4 < 3 < 3 < 3 < 4 04/02/19 - 07/02/19 64 +/- 23 < 3 < 3 < 3 < 3 < 3 07/02/19 - 09/30/19 92 +/- 23 < 2 < 3 < 3 < 3 < 2 09/30/19 - 12/30/19 50 +/- 13 < 2 < 1 < 2 < 2 < 2 MEAN +/- 2 STD DEV 73 +/- 40 - - - - -

22G1 01/02/19 - 04/02/19 93 +/- 20 < 2 < 2 < 1 < 2 < 2 04/02/19 - 07/02/19 77 +/- 27 < 3 < 3 < 2 < 2 < 2 07/02/19 - 09/30/19 74 +/- 22 < 2 < 2 < 2 < 3 < 3 09/30/19 - 12/30/19 76 +/- 20 < 3 < 3 < 2 < 2 < 3 MEAN +/- 2 STD DEV 80 +/- 18 - - - - -

6C1 01/02/19 - 04/02/19 75 +/- 18 < 2 < 2 < 2 < 2 < 2 04/02/19 - 07/02/19 72 +/- 21 < 3 < 3 < 3 < 3 < 2 07/02/19 - 09/30/19 81 +/- 21 < 2 < 3 < 3 < 2 < 2 09/30/19 - 12/30/19 65 +/- 18 < 2 < 3 < 2 < 2 < 3 MEAN +/- 2 STD DEV 73 +/- 14 - - - - -

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, 2019 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 01/02/19 - 01/07/19 < 57 < 57 < 25 < 57 < 56 < 28 < 28 01/07/19 - 01/14/19 < 36 < 36 < 58 < 35 < 35 < 65 < 66 01/14/19 - 01/22/19 < 43 < 43 < 18 < 43 < 43 < 21 < 21 01/22/19 - 01/28/19 < 56 < 56 < 25 < 56 < 56 < 27 < 26 01/28/19 - 02/04/19 < 47 < 47 < 38 < 42 < 25 < 42 < 44 02/04/19 - 02/11/19 < 48 < 48 < 31 < 48 < 48 < 35 < 36 02/11/19 - 02/18/19 < 45 < 45 < 63 < 45 < 44 < 67 < 64 02/18/19 - 02/26/19 < 18 < 20 < 12 < 18 < 18 < 10 < 24 02/26/19 - 03/04/19 < 29 < 29 < 45 < 47 < 24 < 47 < 45 03/04/19 - 03/11/19 < 29 < 29 < 44 < 29 < 29 < 46 < 46 03/11/19 - 03/18/19 < 37 < 37 < 18 < 19 < 36 < 19 < 19 03/18/19 - 03/25/19 < 36 < 36 < 32 < 36 < 36 < 34 < 34 03/25/19 - 04/02/19 < 20 < 8 < 13 < 20 < 20 < 14 < 15 04/02/19 - 04/08/19 < 42 < 42 < 46 < 41 < 42 (1) < 45 04/08/19 - 04/15/19 < 28 < 29 < 12 < 28 < 28 < 30 < 30 04/15/19 - 04/22/19 < 44 < 45 < 32 < 44 < 44 < 33 < 33 04/22/19 - 04/29/19 < 39 < 39 < 28 < 38 < 38 < 30 < 30 04/29/19 - 05/07/19 < 24 < 25 < 26 < 25 < 13 < 24 < 28 05/07/19 - 05/13/19 < 35 < 35 < 41 < 34 < 35 < 45 < 42 05/13/19 - 05/20/19 < 22 < 22 < 15 < 22 < 22 < 16 < 17 05/20/19 - 05/28/19 < 51 < 51 < 33 < 35 < 50 < 29 < 34 05/28/19 - 06/03/19 < 48 < 49 (1) < 19 < 48 < 20 < 20 06/03/19 - 06/11/19 < 57 < 57 < 35 (1) < 56 < 36 < 35 06/11/19 - 06/17/19 < 29 < 30 < 17 < 30 < 29 < 17 < 17 06/17/19 - 06/24/19 < 34 < 33 < 22 < 33 < 14 < 34 < 22 06/24/19 - 07/02/19 < 48 < 49 < 25 < 48 < 47 < 20 < 24 07/02/19 - 07/08/19 < 15 < 15 < 20 < 15 < 8 < 16 < 20 07/08/19 - 07/15/19 < 34 < 34 < 22 < 33 < 18 < 34 < 23 07/15/19 - 07/22/19 < 11 < 11 < 29 < 12 < 10 < 12 < 25 07/22/19 - 07/30/19 < 26 < 26 < 34 < 26 < 14 < 26 < 11 07/30/19 - 08/05/19 < 24 < 25 < 25 < 20 < 23 < 24 < 13 08/05/19 - 08/12/19 < 18 < 22 < 33 < 20 < 21 < 20 < 33 08/12/19 - 08/19/19 < 14 < 20 < 19 < 19 < 14 < 8 < 21 08/19/19 - 08/26/19 < 11 < 12 < 21 < 20 < 10 < 8 < 21 08/26/19 - 09/03/19 < 10 < 16 < 16 < 15 < 10 < 15 < 6 09/03/19 - 09/10/19 < 25 < 26 < 16 < 25 < 11 < 25 < 16 09/10/19 - 09/16/19 < 48 < 50 < 24 < 46 < 21 < 46 < 31 09/16/19 - 09/23/19 < 11 < 12 < 15 < 11 < 12 < 15 < 15 09/23/19 - 09/30/19 < 14 < 20 < 20 < 19 < 12 < 19 < 16 09/30/19 - 10/07/19 < 24 < 21 < 29 < 23 < 24 < 23 < 27 10/07/19 - 10/14/19 < 17 < 16 < 27 < 15 < 17 < 25 < 26 10/14/19 - 10/21/19 < 29 < 13 < 24 < 29 < 28 < 28 < 24 10/21/19 - 10/28/19 < 12 < 24 < 28 < 24 < 23 < 23 < 26 10/28/19 - 11/05/19 < 34 < 26 < 12 < 27 < 33 < 27 < 28 11/05/19 - 11/11/19 < 25 < 12 < 12 < 25 < 25 < 25 < 25 11/11/19 - 11/18/19 < 38 < 38 < 23 < 17 < 38 < 41 < 20 11/18/19 - 11/25/19 < 21 < 27 < 23 < 25 < 25 < 26 < 27 11/25/19 - 12/03/19 < 20 < 20 < 24 < 20 < 19 < 21 < 23 12/03/19 - 12/09/19 < 23 < 23 < 22 < 21 < 21 < 10 < 15 12/09/19 - 12/16/19 < 23 < 23 < 33 < 22 < 20 < 23 < 33 12/16/19 - 12/23/19 < 30 < 30 < 15 < 25 < 30 < 36 < 39 12/23/19 - 12/30/19 < 37 < 16 < 26 < 37 < 37 < 37 < 21 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, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION CONTROL FARM INDICATOR FARM PERIOD 23F1 36E1 18E1 19B1 25C1 01/15/19 < 0.5 < 0.7 < 0.7 < 0.9 < 0.4 02/12/19 < 0.6 < 0.5 < 0.7 < 0.9 03/05/19 < 0.7 < 0.4 < 0.7 < 0.8 04/01/19 < 0.7 < 0.8 < 0.9 < 1.0 < 0.7 04/16/19 < 0.7 < 0.6 < 0.7 < 0.8 04/29/19 < 0.7 < 0.7 < 0.6 < 0.6 05/14/19 < 0.5 < 0.7 < 0.6 < 0.7 05/28/19 < 0.8 < 0.6 < 0.5 < 0.7 06/11/19 < 0.8 < 1.0 < 0.7 < 0.9 06/24/19 < 0.7 < 0.6 < 0.8 < 0.7 07/09/19 < 0.8 < 0.9 < 0.8 < 0.9 < 0.9 07/22/19 < 0.9 < 0.9 < 0.8 < 0.8 08/06/19 < 0.6 < 0.8 < 0.9 < 0.6 08/21/19 < 0.9 < 0.7 < 0.7 < 0.7 09/03/19 < 0.7 < 0.7 < 0.8 < 0.7 09/16/19 < 0.7 < 0.8 < 0.7 < 0.7 10/01/19 < 0.7 < 0.8 < 0.7 < 0.9 < 0.8 10/15/19 < 0.9 < 0.8 < 0.8 < 0.9 10/29/19 < 0.9 < 0.9 < 0.8 < 0.7 11/12/19 < 0.5 < 0.8 < 0.7 < 0.6 11/25/19 < 0.8 < 0.8 < 0.8 < 0.9 12/10/19 < 0.8 < 0.9 < 0.9 < 0.9 MEAN - - - - -

C-12

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 18E1 01/15/19 1196 +/- 185 < 7 < 8 < 29 < 10 02/12/19 1206 +/- 172 < 8 < 8 < 25 < 10 03/05/19 1145 +/- 181 < 8 < 8 < 38 < 10 04/01/19 1290 +/- 162 < 11 < 10 < 36 < 10 04/16/19 1288 +/- 111 < 7 < 6 < 25 < 7 04/29/19 1233 +/- 140 < 6 < 6 < 25 < 5 05/14/19 1155 +/- 157 < 7 < 6 < 22 < 9 05/28/19 1347 +/- 173 < 7 < 5 < 25 < 5 06/11/19 1241 +/- 177 < 8 < 7 < 40 < 11 06/24/19 1276 +/- 189 < 8 < 10 < 30 < 7 07/08/19 1129 +/- 152 < 8 < 7 < 24 < 7 07/22/19 1195 +/- 180 < 9 < 9 < 35 < 8 08/05/19 1143 +/- 201 < 10 < 6 < 26 < 8 08/20/19 1167 +/- 181 < 9 < 8 < 43 < 13 09/03/19 1321 +/- 172 < 7 < 9 < 29 < 13 09/16/19 1019 +/- 140 < 9 < 9 < 31 < 10 10/01/19 1124 +/- 116 < 8 < 7 < 24 < 7 10/15/19 1226 +/- 187 < 8 < 9 < 32 < 12 10/29/19 1056 +/- 190 < 9 < 10 < 34 < 9 11/12/19 1104 +/- 190 < 7 < 9 < 26 < 10 11/25/19 1218 +/- 201 < 9 < 9 < 33 < 12 12/10/19 1259 +/- 150 < 6 < 6 < 23 < 8 MEAN +/- 2 STD DEV 1197 +/- 168 - - - -

19B1 01/15/19 1117 +/- 166 < 10 < 9 < 41 < 12 02/12/19 1205 +/- 204 < 5 < 7 < 28 < 8 03/05/19 1202 +/- 139 < 10 < 9 < 40 < 13 04/01/19 1136 +/- 150 < 11 < 11 < 39 < 8 04/16/19 1124 +/- 184 < 8 < 7 < 28 < 9 04/29/19 1365 +/- 202 < 9 < 9 < 31 < 10 05/14/19 1303 +/- 150 < 6 < 6 < 24 < 6 05/28/19 1213 +/- 140 < 6 < 7 < 29 < 6 06/11/19 1198 +/- 151 < 7 < 7 < 31 < 9 06/24/19 1287 +/- 150 < 9 < 9 < 28 < 9 07/08/19 1181 +/- 192 < 7 < 7 < 29 < 5 07/22/19 1280 +/- 201 < 8 < 8 < 27 < 11 08/05/19 1401 +/- 196 < 9 < 5 < 20 < 8 08/20/19 1197 +/- 174 < 8 < 8 < 41 < 11 09/03/19 1165 +/- 194 < 9 < 9 < 29 < 9 09/16/19 1029 +/- 191 < 8 < 6 < 21 < 6 10/01/19 1247 +/- 145 < 8 < 6 < 22 < 7 10/15/19 1253 +/- 118 < 6 < 6 < 18 < 6 10/29/19 1261 +/- 160 < 13 < 12 < 39 < 9 11/12/19 1268 +/- 183 < 8 < 7 < 28 < 4 11/25/19 1448 +/- 197 < 9 < 7 < 37 < 10 12/10/19 1253 +/- 123 < 5 < 5 < 20 < 8 MEAN +/- 2 STD DEV 1233 +/- 192 - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-13

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 23F1 01/15/19 1210 +/- 228 < 7 < 7 < 24 < 6 02/12/19 1356 +/- 159 < 6 < 5 < 21 < 7 03/05/19 1038 +/- 189 < 8 < 8 < 29 < 9 04/01/19 1347 +/- 169 < 12 < 11 < 41 < 10 04/16/19 1270 +/- 176 < 7 < 7 < 22 < 6 04/29/19 1485 +/- 178 < 8 < 7 < 29 < 11 05/14/19 1262 +/- 142 < 8 < 7 < 23 < 6 05/28/19 1181 +/- 124 < 7 < 6 < 28 < 8 06/11/19 1359 +/- 164 < 7 < 7 < 31 < 7 06/24/19 1360 +/- 137 < 6 < 6 < 24 < 6 07/08/19 1146 +/- 188 < 7 < 7 < 31 < 9 07/22/19 1471 +/- 191 < 7 < 7 < 26 < 9 08/05/19 1261 +/- 203 < 8 < 9 < 31 < 10 08/20/19 1154 +/- 190 < 7 < 7 < 39 < 8 09/03/19 1381 +/- 216 < 7 < 9 < 34 < 10 09/16/19 1496 +/- 191 < 8 < 7 < 25 < 8 10/01/19 1315 +/- 152 < 6 < 7 < 19 < 5 10/15/19 1250 +/- 99.1 < 7 < 7 < 25 < 7 10/29/19 1505 +/- 206 < 9 < 9 < 31 < 9 11/12/19 1443 +/- 202 < 10 < 9 < 33 < 8 11/25/19 1260 +/- 162 < 7 < 7 < 25 < 8 12/10/19 1119 +/- 153 < 6 < 6 < 19 < 6 MEAN +/- 2 STD DEV 1303 +/- 262 - - - -

25C1 01/15/19 875 +/- 144 < 6 < 6 < 25 < 5 02/12/19 1305 +/- 179 < 7 < 7 < 32 < 6 03/05/19 1472 +/- 171 < 9 < 8 < 35 < 11 04/01/19 1397 +/- 217 < 8 < 10 < 34 < 13 04/16/19 1375 +/- 201 < 8 < 7 < 24 < 5 04/29/19 1521 +/- 197 < 7 < 8 < 28 < 10 05/14/19 1335 +/- 198 < 8 < 9 < 38 < 11 05/28/19 1431 +/- 175 < 8 < 8 < 33 < 11 06/11/19 1516 +/- 155 < 6 < 6 < 28 < 8 06/24/19 1464 +/- 118 < 6 < 5 < 19 < 6 07/08/19 1235 +/- 187 < 9 < 8 < 29 < 10 07/22/19 993 +/- 187 < 8 < 7 < 28 < 9 08/06/19 1365 +/- 170 < 4 < 6 < 24 < 7 08/21/19 1315 +/- 202 < 10 < 10 < 36 < 10 09/03/19 1310 +/- 172 < 7 < 7 < 29 < 10 09/16/19 1261 +/- 165 < 7 < 7 < 27 < 9 10/01/19 1158 +/- 152 < 7 < 7 < 23 < 8 10/15/19 1146 +/- 123 < 5 < 5 < 16 < 6 10/29/19 1372 +/- 176 < 7 < 7 < 23 < 9 11/12/19 1216 +/- 200 < 7 < 8 < 31 < 9 11/25/19 1345 +/- 152 < 7 < 7 < 34 < 10 12/10/19 1062 +/- 139 < 6 < 6 < 22 < 7 MEAN +/- 2 STD DEV 1294 +/- 334 - - - -

36E1 01/15/19 1055 +/- 176 < 6 < 7 < 27 < 8 04/01/19 1163 +/- 183 < 12 < 11 < 40 < 10 07/09/19 1198 +/- 188 < 7 < 6 < 26 < 10 10/01/19 1020 +/- 163 < 7 < 6 < 22 < 7 MEAN +/- 2 STD DEV 1109 +/- 170 - - - -

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, 2019 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 06/25/19 Swiss Chard leaves 335 +/- 172 5513 +/- 533 < 15 < 19 < 20 < 21 < 23 < 23 < 385 55 +/- 28 < 78 06/25/19 Collard leaves < 228 3573 +/- 531 < 27 < 27 < 33 < 30 < 33 < 27 < 642 54 +/- 47 < 137 06/25/19 Kale leaves < 184 4846 +/- 642 < 24 < 25 < 25 < 24 < 25 < 22 < 623 < 43 < 101 07/23/19 Swiss Chard leaves 663 +/- 247 8816 +/- 728 < 24 < 25 < 35 < 30 < 26 < 28 < 549 < 54 < 96 07/23/19 Collard leaves 866 +/- 209 5173 +/- 580 < 19 < 21 < 25 < 23 < 19 < 22 < 433 < 34 < 104 07/23/19 Kale leaves 1190 +/- 222 3389 +/- 523 < 24 < 18 < 26 < 24 < 21 < 18 < 610 < 49 < 80 08/19/19 Swiss Chard leaves 537 +/- 242 8068 +/- 886 < 25 < 26 < 23 < 27 < 34 < 29 < 697 < 66 < 139 08/19/19 Collard leaves 1180 +/- 275 5236 +/- 701 < 25 < 28 < 24 < 30 < 28 < 23 < 632 < 60 < 103 08/19/19 Kale leaves 1419 +/- 350 3358 +/- 532 < 24 < 24 < 34 < 20 < 25 < 28 < 628 51 +/- 40 < 112 09/24/19 Swiss Chard leaves < 307 7037 +/- 1014 < 32 < 27 < 37 < 32 < 40 < 31 < 622 128 +/- 60 < 126 09/24/19 Eggplant leaves 981 +/- 373 6978 +/- 962 < 33 < 26 < 42 < 41 < 39 < 38 < 927 244 +/- 71 < 152 MEAN +/- 2 STD DEV 896 +/- 736 5635 +/- 3758 - - - - - - - 106 +/- 167 -

13S3 06/25/19 Swiss Chard leaves < 448 7248 +/- 1058 < 46 < 42 < 34 < 37 < 49 < 45 < 896 < 72 < 202 06/25/19 Collard leaves < 438 3808 +/- 780 < 45 < 41 < 47 < 42 < 49 < 48 1531 +/- 1004 108 +/- 64 < 167 06/25/19 Kale leaves < 334 3646 +/- 833 < 52 < 38 < 55 < 48 < 48 < 41 1419 +/- 918 91 +/- 69 < 193 07/23/19 Eggplant leaves 3332 +/- 243 5018 +/- 431 < 19 < 19 < 18 < 23 < 20 < 20 797 +/- 500 < 41 < 87 07/23/19 Collard leaves 1233 +/- 350 3752 +/- 600 < 33 < 29 < 35 < 37 < 33 < 31 2871 +/- 803 < 58 < 139 C-15 07/23/19 Kale leaves 767 +/- 237 3822 +/- 568 < 27 < 28 < 22 < 24 < 22 < 26 1626 +/- 663 < 48 < 81 08/19/19 Kale leaves 1140 +/- 324 4260 +/- 649 < 33 < 30 < 31 < 38 < 30 < 32 2639 +/- 914 94 +/- 56 < 165 08/19/19 Collard leaves 1041 +/- 296 4613 +/- 817 < 45 < 33 < 30 < 41 < 41 < 35 1408 +/- 846 < 74 < 176 08/19/19 Swiss Chard leaves < 565 6889 +/- 1116 < 54 < 46 < 43 < 57 < 59 < 56 1146 +/- 924 < 107 < 234 09/24/19 Eggplant leaves < 414 5911 +/- 689 < 34 < 28 < 39 < 39 < 38 < 41 < 946 124 +/- 57 < 157 09/24/19 Swiss Chard leaves < 497 9170 +/- 1132 < 39 < 40 < 47 < 55 < 51 < 46 < 1256 < 100 < 194 MEAN +/- 2 STD DEV 1503 +/- 2075 5285 +/- 3625 - - - - - - 1680 +/- 1428 104 +/- 31 -

31G1 06/25/19 Cabbage leaves 799 +/- 251 3692 +/- 616 < 27 < 24 < 32 < 24 < 31 < 29 < 671 159 +/- 39 < 115 06/25/19 Cauliflower leaves 299 +/- 143 3426 +/- 414 < 17 < 14 < 21 < 19 < 23 < 20 < 461 101 +/- 34 91 +/- 35 06/25/19 Asparagus leaves 153 +/- 136 2885 +/- 409 < 17 < 18 < 21 < 18 < 20 < 21 < 383 138 +/- 39 < 77 07/23/19 Yellow Squash leaves 2891 +/- 349 6264 +/- 654 < 23 < 25 < 24 < 26 < 30 < 26 < 550 86 +/- 43 < 134 07/23/19 Cucumber leaves 1902 +/- 333 5515 +/- 665 < 26 < 26 < 26 < 36 < 31 < 29 < 660 < 53 107 +/- 46 07/23/19 Watermelon leaves 2560 +/- 354 3827 +/- 673 < 31 < 22 < 27 < 39 < 46 < 32 < 748 < 62 < 161 08/19/19 Sunflower leaves 3719 +/- 490 7950 +/- 882 < 35 < 23 < 40 < 32 < 39 < 38 < 881 100 +/- 71 < 132 08/19/19 Swiss Chard leaves 795 +/- 374 5983 +/- 870 < 34 < 33 < 48 < 32 < 35 < 29 < 782 117 +/- 55 < 139 08/19/19 Eggplant leaves 1053 +/- 347 6084 +/- 744 < 39 < 32 < 28 < 34 < 43 < 37 < 838 218 +/- 74 < 157 09/24/19 Sunflower leaves 2280 +/- 365 8971 +/- 812 < 36 < 32 < 37 < 41 < 36 < 33 < 785 < 62 < 147 09/24/19 Swiss Chard leaves < 327 6311 +/- 798 < 28 < 32 < 33 < 33 < 28 < 33 < 796 126 +/- 56 < 109 09/24/19 Rhubarb leaves < 274 3492 +/- 699 < 27 < 26 < 28 < 25 < 25 < 27 < 557 < 57 < 108 MEAN +/- 2 STD DEV 1645 +/- 2403 5367 +/- 3856 - - - - - - - 131 +/- 84 99 +/- 23 THE MEAN AND 2-STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-IX.1 QUARTERLY DLR RESULTS FOR LIMERICK GENERATING STATION, 2019 Qtr 1 Qtr 2 Qtr 3 Qtr 4 Normalized BA + Annual Facility Annual Facility Location Annual Dose, MA BA(1) Dose, FA Dose, (mrem) (mrem) (mrem) (mrem) MDDA(2)

(mrem/yr) (mrem) FA >10 mrem 10E1 16.4 19.1 20.3 17.6 73.4 71.0 82.7 ND No 10F3 15.5 17.5 19.3 17.1 69.5 69.7 81.4 ND No 10S3 15.8 18.1 18.0 17.4 69.3 70.9 82.6 ND No 11S1 18.3 21.0 20.6 19.9 79.8 83.1 94.8 ND No 13C1 11.7 13.6 11.3 11.3 47.9 49.8 61.5 ND No 130 16.7 18.6 19.6 18.7 73.6 70.1 81.8 ND No 13S2 23.4 24.8 25.4 24.7 98.3 112.1 123.8 ND No 14S1 14.8 17.0 15.8 15.4 63.1 63.2 74.9 ND No 15D1 16.4 18.5 18.5 18.2 71.7 72.5 84.2 ND No 16F1 16.1 17.9 17.6 16.6 68.3 73.4 85.1 ND No 17B1 14.8 14.9 17.3 16.9 64.0 66.8 78.5 ND No 18S2 17.4 18.3 21.1 19.0 75.8 78.4 90.1 ND No 19D1 15.6 15.7 17.4 15.8 64.4 66.3 78.0 ND No 20D1 14.2 16.4 16.1 15.7 62.4 63.0 74.7 ND No 20F1 15.4 16.8 18.4 16.3 66.9 67.5 79.2 ND No 21S2 15.2 15.4 17.4 15.3 63.3 64.1 75.8 ND No 23S2 15.2 17.3 17.9 15.6 66.0 63.9 75.6 ND No 24D1 14.1 15.2 16.3 14.3 59.8 59.7 71.4 ND No 25D1 12.9 14.6 14.6 14.0 56.0 56.5 68.2 ND No 25S2 14.2 15.0 16.9 13.7 59.8 58.1 69.8 ND No 26S3 14.0 15.7 17.0 15.0 61.7 60.4 72.1 ND No 28D2 15.2 16.9 15.4 15.6 63.1 63.5 75.2 ND No 29E1 15.0 16.1 18.3 14.8 64.2 62.3 74.0 ND No 29S1 14.0 14.7 15.4 14.4 58.5 61.4 73.1 ND No 2E1 17.3 18.0 20.3 17.8 73.4 71.9 83.6 ND No 31D1 20.9 19.6 20.8 20.0 81.3 83.0 94.7 ND No 31D2 18.4 18.3 19.5 17.2 73.4 71.2 82.9 ND No 31S1 18.5 17.4 20.2 18.1 74.1 71.6 83.3 ND No 34E1 16.7 16.0 18.7 16.8 68.1 67.0 78.7 ND No 34S2 15.9 17.6 17.8 16.1 67.4 71.6 83.3 ND No 36D1 14.5 15.1 16.8 14.4 60.9 62.1 73.8 ND No 36S2 17.1 19.0 20.6 17.9 74.6 73.4 85.1 ND No 3S1 17.8 18.1 19.8 17.4 73.0 70.1 81.8 ND No 4E1 13.6 13.7 14.7 12.4 54.4 51.4 63.1 ND No 5H1 21.9 22.0 24.0 21.3 89.2 86.3 98.0 ND No 5S1 19.6 20.1 21.7 18.1 79.5 80.0 91.7 ND No 6C1 17.8 18.1 20.4 16.0 72.3 69.5 81.2 ND No 7E1 17.8 18.9 20.1 16.9 73.6 74.6 86.3 ND No 7S1 16.8 18.5 20.1 17.5 72.9 73.1 84.8 ND No 9C1 15.4 14.8 19.3 16.0 65.4 68.1 79.8 ND No (1)

Baseline background dose (BBA): The estimated mean background radiation dose at each field monitoring location annually based on historical measurements, excluding any dose contribution from the monitored facility (2)

Minimum differential dose (MDDA): The smallest amount of facility related dose at each monitored location annually above the baseline background dose that can be reliably detected by an environmental dosimetry system C-16

FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2019 12 10 8

C-17 6 pCi/liter 4

2 CONTROL INDICATOR 0

82 91 01 10 20 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 - 2019 150 Group I 135 Group II Group III 120 Chernobyl 105 90 C-18 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 94 07 20 YEAR

FIGURE C-3 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2019 50 GROUP I GROUP II GROUP III 40 30 C-19 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-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2019 12 10 8

6 pCi/liter 4

2 CONTROL INDICATOR 0

82 91 01 10 20 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 - 2019 150 Group I 135 Group II Group III 120 Chernobyl 105 90 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 94 07 20 YEAR

FIGURE C-3 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2019 50 GROUP I GROUP II GROUP III 40 30 E-03 pCi/cubic meter 20 10 0

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

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, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 01/02/19 - 01/28/19 1.9 +/- 0.7 01/28/19 - 02/26/19 2.2 +/- 0.7 02/26/19 - 04/02/19 1.2 +/- 0.6 04/02/19 - 04/29/19 1.1 +/- 0.7 04/29/19 - 06/03/19 1.1 +/- 0.8 06/03/19 - 07/02/19 1.3 +/- 0.6 07/02/19 - 07/30/19 1.7 +/- 0.6 07/30/19 - 09/03/19 2.2 +/- 0.7 09/03/19 - 09/30/19 3.1 +/- 0.7 09/30/19 - 10/28/19 2.7 +/- 0.7 10/28/19 - 12/03/19 2.6 +/- 0.7 12/03/19 - 12/30/19 3.3 +/- 7.7 MEAN +/- 2 STD DEV 2.0 +/- 1.6 TABLE D-I.2 CONCENTRATIONS OF I-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 01/02/19 - 01/28/19 < 0.6 01/28/19 - 02/26/19 < 0.6 02/26/19 - 04/02/19 < 0.8 04/02/19 - 04/29/19 < 0.7 04/29/19 - 06/03/19 < 0.8 06/03/19 - 07/02/19 < 0.8 07/02/19 - 07/30/19 < 0.8 07/30/19 - 09/03/19 < 0.7 09/03/19 - 09/30/19 < 0.6 09/30/19 - 10/28/19 (1) 10/28/19 - 12/03/19 < 0.9 12/03/19 - 12/30/19 < 0.7 MEAN -

TABLE D-I.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 01/02/19 - 04/02/19 < 119 04/02/19 - 07/02/19 < 138 07/02/19 - 09/30/19 < 139 09/30/19 - 12/30/19 < 166 MEAN -

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

TABLE D-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2019 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 01/02/19 - 01/28/19 < 5 < 5 < 11 < 5 < 10 < 5 < 8 < 9 < 4 < 5 < 22 < 12 01/28/19 - 02/26/19 < 3 < 3 < 6 < 3 < 7 < 3 < 5 < 5 < 3 < 3 < 14 < 5 02/26/19 - 04/02/19 < 3 < 3 < 7 < 3 < 6 < 4 < 6 < 9 < 3 < 3 < 22 < 9 04/02/19 - 04/29/19 < 3 < 3 < 7 < 3 < 6 < 4 < 6 < 7 < 3 < 3 < 18 < 7 04/29/19 - 06/03/19 < 4 < 5 < 12 < 5 < 11 < 5 < 8 < 9 < 4 < 5 < 28 < 10 06/03/19 - 07/02/19 < 3 < 3 < 7 < 3 < 7 < 4 < 6 < 7 < 3 < 3 < 18 < 7 07/02/19 - 07/30/19 < 3 < 4 < 8 < 3 < 7 < 4 < 6 < 12 < 3 < 3 < 26 < 9 07/30/19 - 09/03/19 < 3 < 3 < 6 < 3 < 6 < 3 < 5 < 5 < 3 < 3 < 16 < 5 09/03/19 - 09/30/19 < 5 < 4 < 11 < 4 < 9 < 5 < 8 < 8 < 4 < 4 < 19 < 8 09/30/19 - 10/28/19 < 5 < 5 < 9 < 5 < 8 < 5 < 8 < 7 < 5 < 4 < 22 < 8 10/28/19 - 12/03/19 < 4 < 4 < 9 < 4 < 8 < 4 < 6 < 6 < 4 < 4 < 18 < 7 12/03/19 - 12/30/19 < 5 < 5 < 10 < 6 < 9 < 5 < 8 < 7 < 5 < 5 < 19 < 10 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, 2019 RESULTS IN UNITS OF E-03 PCI/CU METER +/- 2 SIGMA COLLECTION 11S2 11S2 PERIOD GROSS BETA I-131 01/02/19 - 01/07/19 24 +/- 3 < 18 01/07/19 - 01/14/19 18 +/- 2 < 16 01/14/19 - 01/22/19 21 +/- 2 < 15 01/22/19 - 01/28/19 24 +/- 3 < 18 01/28/19 - 02/04/19 30 +/- 3 < 22 02/04/19 - 02/11/19 20 +/- 2 < 20 02/11/19 - 02/18/19 24 +/- 2 < 41 02/18/19 - 02/26/19 27 +/- 2 < 13 02/26/19 - 03/04/19 21 +/- 3 < 26 03/04/19 - 03/11/19 23 +/- 2 < 18 03/11/19 - 03/18/19 31 +/- 3 < 13 03/18/19 - 03/25/19 19 +/- 2 < 13 03/25/19 - 04/02/19 19 +/- 2 < 10 04/02/19 - 04/08/19 21 +/- 3 < 18 04/08/19 - 04/15/19 13 +/- 2 < 10 04/15/19 - 04/22/19 15 +/- 2 < 13 04/22/19 - 04/29/19 14 +/- 2 < 20 04/29/19 - 05/07/19 11 +/- 2 < 11 05/07/19 - 05/13/19 13 +/- 2 < 13 05/13/19 - 05/20/19 21 +/- 2 < 13 05/20/19 - 05/28/19 13 +/- 2 < 14 05/28/19 - 06/03/19 18 +/- 2 < 17 06/03/19 - 06/11/19 14 +/- 2 < 8 06/11/19 - 06/17/19 14 +/- 2 < 16 06/17/19 - 06/24/19 15 +/- 2 < 12 06/24/19 - 07/02/19 20 +/- 2 < 19 07/02/19 - 07/08/19 24 +/- 3 < 15 07/08/19 - 07/15/19 21 +/- 2 < 12 07/15/19 - 07/22/19 22 +/- 2 < 20 07/22/19 - 07/30/19 24 +/- 2 < 18 07/30/19 - 08/05/19 29 +/- 3 < 14 08/05/19 - 08/12/19 14 +/- 2 < 16 08/12/19 - 08/19/19 22 +/- 2 < 10 08/19/19 - 08/26/19 19 +/- 2 < 9 08/26/19 - 09/03/19 13 +/- 2 < 12 09/03/19 - 09/10/19 13 +/- 2 < 10 09/10/19 - 09/16/19 15 +/- 2 < 12 09/16/19 - 09/23/19 19 +/- 2 < 20 09/23/19 - 09/30/19 15 +/- 2 < 13 09/30/19 - 10/07/19 12 +/- 2 < 17 10/07/19 - 10/14/19 16 +/- 2 < 12 10/14/19 - 10/21/19 25 +/- 2 < 15 10/21/19 - 10/28/19 18 +/- 2 < 13 10/28/19 - 11/05/19 11 +/- 2 < 12 11/05/19 - 11/11/19 21 +/- 2 < 19 11/11/19 - 11/18/19 21 +/- 2 < 9 11/18/19 - 11/25/19 18 +/- 2 < 18 11/25/19 - 12/03/19 14 +/- 2 < 12 12/03/19 - 12/09/19 17 +/- 2 < 13 12/09/19 - 12/16/19 16 +/- 2 < 8 12/16/19 - 12/23/19 22 +/- 2 < 10 12/23/19 - 12/30/19 37 +/- 3 < 20 MEAN +/- 2 STD DEV 19 +/- 11 -

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, 2019 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 01/02/19 - 04/02/19 76 +/- 13 < 1.6 < 1.6 < 1.2 < 1.3 < 1.5 04/02/19 - 07/02/19 83 +/- 13 < 1.6 < 1.6 < 1.0 < 1.3 < 1.2 07/02/19 - 09/30/19 52 +/- 9 < 0.9 < 1.0 < 1.2 < 0.9 < 1.2 09/30/19 - 12/30/19 57 +/- 12 < 1.5 < 1.4 < 1.3 < 1.1 < 1.4 MEAN +/- 2 STD DEV 67 +/- 30 - - - - -

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, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD I-131 K-40 Cs-134 Cs-137 Ba-140 La-140 19B1 01/15/19 < 0.9 1250 +/- 113 < 5 < 5 < 31 < 10 04/01/19 < 0.6 1280 +/- 111 < 5 < 6 < 27 < 11 07/08/19 < 0.8 1270 +/- 110 < 5 < 6 < 23 < 10 10/01/19 < 0.8 1330 +/- 89 < 4 < 5 < 22 < 9 MEAN +/- 2 STD DEV - 1283 +/- 68 - - - -

25C1 01/15/19 < 0.6 1160 +/- 106 < 4 < 5 < 19 < 6 04/01/19 < 0.4 1450 +/- 120 < 5 < 5 < 20 < 8 07/08/19 < 0.7 1330 +/- 93 < 5 < 3 < 22 < 7 10/01/19 < 0.7 1410 +/- 87 < 3 < 4 < 19 < 7 MEAN +/- 2 STD DEV - 1338 +/- 257 - - - -

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, 2019 10.0 9.0 EIS TBE 8.0 7.0 6.0 D-6 5.0 pCi/liter 4.0 3.0 2.0 1.0 0.0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH

FIGURE D-2 COMPARISON OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11S1 AND 11S2, 2019 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 7DEOH( 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 2019 E12468A Milk Sr-89 pCi/L 87.1 96 0.91 A Sr-90 pCi/L 12.6 12.6 1.00 A E12469A Milk Ce-141 pCi/L 113 117 0.97 A Co-58 pCi/L 153 143 1.07 A Co-60 pCi/L 289 299 0.97 A Cr-51 pCi/L 233 293 0.80 A Cs-134 pCi/L 147 160 0.92 A Cs-137 pCi/L 193 196 0.98 A Fe-59 pCi/L 153 159 0.96 A I-131 pCi/L 91.5 89.5 1.02 A Mn-54 pCi/L 149 143 1.04 A Zn-65 pCi/L 209 220 0.95 A E12470 Charcoal I-131 pCi 77.5 75.2 1.03 A E12471 AP Ce-141 pCi 60.7 70.2 0.87 A Co-58 pCi 87.9 85.8 1.02 A Co-60 pCi 175 179 0.98 A Cr-51 pCi 165 176 0.94 A Cs-134 pCi 91.2 95.9 0.95 A Cs-137 pCi 120 118 1.02 A Fe-59 pCi 108 95.3 1.13 A Mn-54 pCi 94.2 85.7 1.10 A Zn-65 pCi 102 132 0.77 W E12472 Water Fe-55 pCi/L 2230 1920 1.16 A E12473 Soil Ce-141 pCi/g 0.189 0.183 1.03 A Co-58 pCi/g 0.209 0.224 0.93 A Co-60 pCi/g 0.481 0.466 1.03 A Cr-51 pCi/g 0.522 0.457 1.14 A Cs-134 pCi/g 0.218 0.250 0.87 A Cs-137 pCi/g 0.370 0.381 0.97 A Fe-59 pCi/g 0.263 0.248 1.06 A Mn-54 pCi/g 0.248 0.223 1.11 A Zn-65 pCi/g 0.371 0.344 1.08 A E12474 AP Sr-89 pCi 88.3 95.2 0.93 A Sr-90 pCi 11.7 12.5 0.94 A August 2019 E12562 Soil Sr-90 pCi/g 4.710 6.710 0.70 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 1 of )

E-1

Analytics Environmental Radioactivity Cross Check Program 7DEOH( 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 2019 E12475 Milk Sr-89 pCi/L 70.0 93.9 0.75 W Sr-90 pCi/L 12.0 12.9 0.93 A E12476 Milk Ce-141 pCi/L 150 167 0.90 A Co-58 pCi/L 170 175 0.97 A Co-60 pCi/L 211 211 1.00 A Cr-51 pCi/L 323 331 0.98 A Cs-134 pCi/L 180 207 0.87 A Cs-137 pCi/L 147 151 0.97 A Fe-59 pCi/L 156 148 1.05 A I-131 pCi/L 81.1 92.1 0.88 A Mn-54 pCi/L 160 154 1.04 A Zn-65 pCi/L 303 293 1.03 A E12477 Charcoal I-131 pCi 95.9 95.1 1.01 A E12478 AP Ce-141 pCi 129 138 0.93 A Co-58 pCi 128 145 0.88 A Co-60 pCi 181 174 1.04 A Cr-51 pCi 292 274 1.07 A Cs-134 pCi 166 171 0.97 A Cs-137 pCi 115 125 0.92 A Fe-59 pCi 119 123 0.97 A Mn-54 pCi 129 128 1.01 A Zn-65 pCi 230 242 0.95 A E12479 Water Fe-55 pCi/L 1810 1850 0.98 A E12480 Soil Ce-141 pCi/g 0.305 0.276 1.10 A Co-58 pCi/g 0.270 0.289 0.93 A Co-60 pCi/g 0.358 0.348 1.03 A Cr-51 pCi/g 0.765 0.547 1.40 N(1)

Cs-134 pCi/g 0.327 0.343 0.95 A Cs-137 pCi/g 0.308 0.321 0.96 A Fe-59 pCi/g 0.257 0.245 1.05 A Mn-54 pCi/g 0.274 0.255 1.07 A Zn-65 pCi/g 0.536 0.485 1.11 A E12481 AP Sr-89 pCi 95.9 91.9 1.04 A Sr-90 pCi 12.3 12.6 0.97 A E12563 Soil Sr-90 pCi/g 0.392 0.360 1.09 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 19-27 (Page 2 of 

E-2

DOE's Mixed Analyte Performance Evaluation Program (MAPEP) 7DEOH( Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Range Value February 2019 19-GrF40 AP Gross Alpha Bq/sample 0.184 0.528 0.158 - 0.898 A Gross Beta Bq/sample 0.785 0.948 0.474 - 1.422 A 19-MaS40 Soil Ni-63 Bq/kg 420 519.0 363 - 675 A Sr-90 Bq/kg (1) NR(3) 19-MaW40 Water Am-241 Bq/L 0.764 0.582 0.407 - 0.757 N(4)

Ni-63 Bq/L 4.72 5.8 4.1 - 7.5 A Pu-238 Bq/L 0.443 0.451 0.316 - 0.586 A Pu-239/240 Bq/L -0.00161 0.0045 (2) A 19-RdF40 AP U-234/233 Bq/sample 0.1138 0.106 0.074 - 0.138 A U-238 Bq/sample 0.107 0.110 0.077 - 0.143 A 19-RdV40 Vegetation Cs-134 Bq/sample 2.14 2.44 1.71 - 3.17 A Cs-137 Bq/sample 2.22 2.30 1.61 - 2.99 A Co-57 Bq/sample 2.16 2.07 1.45 - 2.69 A Co-60 Bq/sample 0.02382 (1) A Mn-54 Bq/sample -0.03607 (1) A Sr-90 Bq/sample -0.1060 (1) N(5)

Zn-65 Bq/sample 1.35 1.71 1.20 - 2.22 W August 2019 19-GrF41 AP Gross Alpha Bq/sample 0.192 0.528 0.158 - 0.898 W Gross Beta Bq/sample 0.722 0.937 0.469 - 1.406 A 19-MaS41 Soil Ni-63 Bq/kg 436 629 440 - 818 N(6)

Sr-90 Bq/kg 444 572 400 - 744 W 19-MaW41 Water Am-241 Bq/L NR(7)

Ni-63 Bq/L 7.28 9.7 6.8 - 12.6 W Pu-238 Bq/L 0.0207 0.0063 (2) A Pu-239/240 Bq/L 0.741 0.727 0.509 - 0.945 A 19-RdF41 AP U-234/233 Bq/sample 0.0966 0.093 0.065 - 0.121 A U-238 Bq/sample 0.0852 0.096 0.067-0.125 A 19-RdV41 Vegetation Cs-134 Bq/sample 0.0197 (1) A Cs-137 Bq/sample 3.21 3.28 2.30 - 4.26 A Co-57 Bq/sample 4.62 4.57 3.20 - 5.94 A Co-60 Bq/sample 4.88 5.30 3.71 - 6.89 A Mn-54 Bq/sample 4.54 4.49 3.14 - 5.84 A Sr-90 Bq/sample 0.889 1.00 0.70 - 1.30 A Zn-65 Bq/sample 2.78 2.85 2.00 - 3.71 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 19-12 (4) See NCR 19-13 (5) See NCR 19-14 (6) See NCR 19-25 (Page  of )

(7) See NCR 19-26 E-3

ERA Environmental Radioactivity Cross Check Program 7DEOH( Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value Value (a) Limits April 2019 Rad-117 Water Ba-133 pCi/L 26.3 24.1 18.6 - 27.8 A (1)

Cs-134 pCi/L 15.2 12.1 8.39 - 14.4 N Cs-137 pCi/L 33.6 33.1 28.8 - 39.4 A Co-60 pCi/L 11.9 11.5 8.67 - 15.5 A Zn-65 pCi/L 87.1 89.2 80.3 - 107 A GR-A pCi/L 19 19.3 9.56 - 26.5 A GR-B pCi/L 20.2 29.9 19.1 - 37.7 A U-Nat pCi/L 55.5 55.9 45.6 - 61.5 A H-3 pCi/L 21500 21400 18700 - 23500 A Sr-89 pCi/L 44.9 33.3 24.5 - 40.1 N(2)

Sr-90 pCi/L 24.5 26.3 19.0 - 30.7 A I-131 pCi/L 28.9 28.4 23.6 - 33.3 A October 2019 Rad-119 Water Ba-133 pCi/L 42.7 43.8 35.7 - 48.8 A Cs-134 pCi/L 53.5 55.9 45.2 - 61.5 A Cs-137 pCi/L 77.7 78.7 70.8 - 89.2 A Co-60 pCi/L 51.5 53.4 48.1 - 61.3 A Zn-65 pCi/L 36.6 34.0 28.5 - 43.1 A GR-A pCi/L 40.5 27.6 14.0 - 36.3 N(3)

GR-B pCi/L 36.3 39.8 26.4 - 47.3 A U-Nat pCi/L 27.66 28.0 22.6 - 31.1 A H-3 pCi/L 22800 23400 20500 - 25700 A Sr-89 pCi/L 47.1 45.5 35.4 - 52.7 A (4)

Sr-90 pCi/L 32.5 26.5 19.2 - 30.9 N I-131 pCi/L 26.0 23.9 19.8 - 28.4 A December 2019 QR 120419D Water Sr-90 pCi/L 20.1 18.6 13.2 - 22.1 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 (1) See NCR 19-10 (2) See NCR 19-11 (3) See NCR 19-23 (4) See NCR 19-24 (Page  of )

E-4

TABLE E.4 Analytics Environmental Radioactivity Cross Check Program Exelon Industrial Services (2019)

EIS Identification Known Ratio of Analytics Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) to EIS Result Value March 2019 E 12379 Water Gr-B pCi/L 264 288 92 Pass E 12380 Charcoal I-131 pCi 73.0 75.6 97 Pass E 12378A Milk I-131 pCi/L 92 89.5 103 Pass Ce-141 pCi/L 101 117 86 Pass Cr-51 pCi/L 227 293 77 Pass Cs-134 pCi/L 138 160 86 Pass Cs-137 pCi/L 184 196 94 Pass Co-58 pCi/L 128 143 90 Pass Mn-54 pCi/L 141 143 99 Pass Fe-59 pCi/L 149 159 94 Pass Zn-65 pCi/L 177 220 80 Pass Co-60 pCi/L 262 299 88 Pass June 2019 E12383 AP Ce-141 pCi/Filter 97.7 88 111 Pass Cr-51 pCi/Filter 222 223 100 Pass Cs-134 pCi/Filter 80.9 93 87 Pass Cs-137 pCi/Filter 119 111 107 Pass Co-58 pCi/Filter 77.7 74 105 Pass Mn-54 pCi/Filter 142 126 113 Pass Fe-59 pCi/Filter 121 93.5 129 Pass Zn-65 pCi/Filter 185 164 113 Pass Co-60 pCi/Filter 139 131 106 Pass E12382 Water I-131 pCi/L 115 89.1 129 Pass Ce-141 pCi/L 142 145 98 Pass Cr-51 pCi/L 327 368 89 Pass Cs-134 pCi/L 139 153 91 Pass Cs-137 pCi/L 186 184 101 Pass Co-58 pCi/L 115 122 94 Pass Mn-54 pCi/L 214 207 103 Pass Fe-59 pCi/L 154 154 100 Pass Zn-65 pCi/L 257 270 95 Pass Co-60 pCi/L 216 216 100 Pass E12381 Water Gr-B pCi/L 199 199 100 Pass September 2019 E12384 AP Gr-B pCi 270.7 221 122 Pass December 2019 E12386 Water Gr-B pCi/L 260 269 97 Pass E12387 Cartridge I-131 pCi 79.0 88.2 90 Pass Detector 2 E12387 Cartridge I-131 pCi 79.1 88.2 90 Pass Detector 3 E12387 Cartridge I-131 pCi 79.2 88.2 90 Pass Detector 4 December 2019 E12385 AP Ce-141 pCi/Filter 98.5 99.1 99 Pass Detector 2 Cr-51 pCi/Filter 246 288 85 Pass Cs-134 pCi/Filter 123 135.0 91 Pass Cs-137 pCi/Filter 128 121.0 106 Pass Co-58 pCi/Filter 117 107.0 109 Pass Mn-54 pCi/Filter 170 155.0 110 Pass Fe-59 pCi/Filter 124 104.0 119 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 E-5

TABLE E.4 Analytics Environmental Radioactivity Cross Check Program Exelon Industrial Services (2019)

EIS Identification Known Ratio of Analytics Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) to EIS Result Value December 2019 E12385 AP Zn-65 pCi/Filter 194 190 102 Pass Detector 2 Co-60 pCi/Filter 139 138 101 Pass E12385 AP Ce-141 pCi/Filter 95.7 99.1 97 Pass Detector 3 Cr-51 pCi/Filter 257.1 288 89 Pass Cs-134 pCi/Filter 128 135.0 95 Pass Cs-137 pCi/Filter 128 121.0 105 Pass Co-58 pCi/Filter 111 107.0 104 Pass Mn-54 pCi/Filter 173 155.0 112 Pass Fe-59 pCi/Filter 121.7 104.0 117 Pass Zn-65 pCi/Filter 203 190 107 Pass Co-60 pCi/Filter 147.5 138 107 Pass E12385 AP Ce-141 pCi/Filter 102 99.1 103 Pass Detector 4 Cr-51 pCi/Filter 299 288 104 Pass Cs-134 pCi/Filter 122 135.0 90 Pass Cs-137 pCi/Filter 122 121.0 101 Pass Co-58 pCi/Filter 102 107.0 95 Pass Mn-54 pCi/Filter 167 155.0 108 Pass Fe-59 pCi/Filter 132 104.0 127 Pass Zn-65 pCi/Filter 195 190 103 Pass Co-60 pCi/Filter 146 138 106 Pass E12388 Milk I-131 pCi/L 100 94.5 106 Pass Detector 2 Ce-141 pCi/L 82.4 83.0 99 Pass Cr-51 pCi/L 271 241 112 Pass Cs-134 pCi/L 112 113 99 Pass Cs-137 pCi/L 123 102 121 Pass Co-58 pCi/L 84.9 89.9 94 Pass Mn-54 pCi/L 128 130 98 Pass Fe-59 pCi/L 95.5 87 110 Pass Zn-65 pCi/L 148 159 93 Pass Co-60 pCi/L 119 115 103 Pass E12388 Milk I-131 pCi/L 99.3 94.5 105 Pass Detector 3 Ce-141 pCi/L 80.7 83.0 97 Pass Cr-51 pCi/L 227.9 241 95 Pass Cs-134 pCi/L 103.4 113 92 Pass Cs-137 pCi/L 109.2 102 107 Pass Co-58 pCi/L 101.9 89.9 113 Pass Mn-54 pCi/L 140.8 130 108 Pass Fe-59 pCi/L 102.1 87 117 Pass Zn-65 pCi/L 166.2 159 105 Pass Co-60 pCi/L 111 115 97 Pass E12388 Milk I-131 pCi/L 104 94.5 110 Pass Detector 4 Ce-141 pCi/L 78.3 83.0 94 Pass Cr-51 pCi/L 235.4 241 98 Pass Cs-134 pCi/L 114 113 101 Pass Cs-137 pCi/L 105 102 103 Pass Co-58 pCi/L 92 89.9 102 Pass Mn-54 pCi/L 143 130 110 Pass Fe-59 pCi/L 104 87 119 Pass Zn-65 pCi/L 164 159 103 Pass Co-60 pCi/L 123 115 107 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 E-6

TABLE E.5 ERA Environmental Radioactivity Cross Check Program Exelon Industrial Services (2019)

EIS Acceptance Known Month/Year ID Number Matrix Nuclide Units Reported Ratio of ERA Evaluation (b)

Value (a)

Value to EIS Result April 2019 RAD-117 Water Ba-133 pCi/L 23.0 24.1 95 Pass Cs-134 pCi/L 10.8 12.1 89 Pass Cs-137 pCi/L 34 33.1 104 Pass Co-60 pCi/L 11.3 11.5 98 Pass Zn-65 pCi/L 88.0 89.2 99 Pass I-131 pCi/L 25.3 28.4 89 Pass GR-B pCi/L 28.8 29.9 96 Pass H-3 pCi/L 20,766 21,400 97 Pass July 2019 RAD-118 Water H-3 pCi/L 17,684 16,700 106 Pass September 2019 MRAD-31 AP Am-241 pCi/Filter 28.4 32 89 Pass Cs-134 pCi/Filter 60.7 59 103 Pass Cs-137 pCi/Filter 440 437 101 Pass Co-60 pCi/Filter 57.5 58.4 98 Pass Zn-65 pCi/Filter 381 364 105 Pass October 2019 RAD-119 Water Ba-133 pCi/L 37.2 43.8 85 Pass Cs-134 pCi/L 52.2 55.9 93 Pass Cs-137 pCi/L 80.3 78.7 102 Pass Co-60 pCi/L 54.8 53.4 103 Pass Zn-65 pCi/L 39.3 34 116 Pass I-131 pCi/L 25.4 23.9 106 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) ERA evaluation based on EIS internal QC limits in accordance with the NRC Resolution Test criteria E-7

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

GEL Laboratories (Gamma, Gross Alpha/Beta, H-3 & Sr-90)

Identification Reported Known Quarter/Year Matrix Nuclide Units Acceptance Range Evaluation (b)

Number Value Value (a) 2nd/2019 19-GrW40 Water Gr-A Bq/L 0.819 0.840 0.25 - 1.43 A Gr-B Bq/L 2.39 2.33 1.17 - 3.50 A 19-MaS40 Soil Sr-90 Bq/Kg 3.44 A 19-MaW40 Water H-3 Bq/L 389 421 295 - 547 A Sr-90 Bq/L 5.86 6.35 4.45 - 8.26 A Cs-134 Bq/L 5.32 5.99 4.19 - 7.79 A Cs-137 Bq/L 0 False Positive Test A Co-60 Bq/L 6.7 6.7 4.7 - 8.7 A Fe-55 Bq/L 0.0173 False Positive Test A Mn-54 Bq/L 8.8 8.4 5.9 - 10.9 A Zn-65 Bq/L -0.0318 False Positive Test A 19-RdF40 AP Sr-90 Bq/sample 0.616 0.662 0.463 - 0.861 A 19-RdV40 Veg Sr-90 Bq/sample 0.00951 False Positive Test A 4th/2019 19-MaS41 Soil S-90 Bq/Kg 609 572 400 - 744 A 19-MaW41 Water H-3 Bq/L 166 175 123 - 228 A Sr-90 Bq/L 9.34 10.6 7.4 - 13.8 A Cs-134 Bq/L 0.0266 False Positive Test A Cs-137 Bq/L 19.7 18.4 12.9 - 23.9 A Co-60 Bq/L 9.01 8.8 6.2 - 11.4 A Fe-55 Bq/L 13.8 15.70 11.0 - 20.4 A Mn-54 Bq/L 22.6 20.6 14.4 - 26.8 A Zn-65 Bq/L 23.1 20.3 5.27 - 9.79 A 19-RdF41 AP Sr-90 Bq/sample 0.442 0.498 0.349 - 0.647 A 19-RdV41 Veg Sr-90 Bq/sample 0.847 1.00 0.70 - 1.30 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 E-8

TABLE E.7 ERA Environmental Radioactivity Cross Check Program GEL Laboratories (Gamma, Gross Alpha/Beta, H-3 & Sr-89/90)

Identification Reported Known Acceptance Quarter/Year Matrix Nuclide Units Evaluation (b)

Number Value Value (a) Limits 1st/2019 RAD-116 Water Cs-134 pCi/L 48.2 49.1 39.5 - 54.0 A Cs-137 pCi/L 128 125 112 - 140 A Co-60 pCi/L 104 96.4 86.8 - 108 A Zn-65 pCi/L 88.1 77.4 69.5 - 93.2 A Gr-A pCi/L 22.3 21.8 10.9 - 29.5 A Gr-A pCi/L 23.5 21.8 10.9 - 29.5 A Gr-B pCi/L 43.6 55.7 38.1 - 62.6 A H-3 pCi/L 2,160 2,110 1,740 - 2,340 A H-3 pCi/L 1,920 2,110 1,740 - 2,340 A Sr-89 pCi/L 78.5 66.9 54.4 - 75.0 N(1)

Sr-89 pCi/L 76.5 66.9 54.4 - 75.0 N(1)

Sr-90 pCi/L 40.1 41.0 30.2 - 47.1 A Sr-90 pCi/L 42.2 41.0 30.2 - 47.1 A 2nd/2019 MRAD-30 Soil Sr-90 pCi/kg 1,220 1,350 420 - 2,100 A Veg Sr-90 pCi/kg 4,670 3,530 1,900 - 4,600 N(2)

AP Sr-90 pCi 169 181 114 - 246 A Water Sr-90 pCi/L 365 315 227 - 389 A Gr-A pCi/L 79.8 68.5 25.0 - 94.5 A Gr-B pCi/L 140 151 75.5 - 208 A H-3 pCi/L 22,200 23,700 17,900 - 28,800 A Cs-134 pCi/L 116 123 92.9 - 135 A Cs-137 pCi/L 126 125 107 - 142 A Co-60 pCi/L 1,200.0 1,100 949 - 1,260 A Fe-55 pCi/L 1,310 1,320 776 - 1,920 A Mn-54 pCi/L <5.6 <100 <100 A Zn-65 pCi/L 1,990 1,780 1,580 - 2,250 A RAD-116 Water Sr-89 pCi/L 35.9 33.3 24.5 - 40.2 A Sr-89 pCi/L 34.4 33.3 24.5 - 40.2 A 3rd/2019 RAD-118 Water Cs-134 pCi/L 30.4 32.0 25.1 - 35.2 A Cs-137 pCi/L 23 21 17.6 - 26.7 A Co-60 pCi/L 102 95.1 85.6 - 107 A Zn-65 pCi/L 49.2 41.2 35.3 - 51.4 A Gr-A pCi/L 88.7 70.6 37.1 - 87.1 N(3)

Gr-A pCi/L 80.7 70.6 37.1 - 87.1 A Gr-B pCi/L 57.7 63.9 44.2 - 70.5 A H-3 pCi/L 14,700 16,700 14,600 - 18,400 A H-3 pCi/L 14,700 16,700 14,600 - 18,400 A H-3 pCi/L 15,000 16,700 14,600 - 18,400 A Sr-89 pCi/L 69.4 58.7 47.1 - 66.5 N(3)

Sr-89 pCi/L 62.1 58.7 47.1 - 66.5 A Sr-90 pCi/L 34.3 38.5 28.3 - 44.3 A Sr-90 pCi/L 33.4 38.5 28.3 - 44.3 A 4th/2019 MRAD-31 Soil Sr-90 pCi/kg 1,660 1,910 594 - 2,980 A Veg Sr-90 pCi/kg 4,010 3,940 2,220 - 5,130 A AP Sr-90 pCi 34.8 34.5 21.8 - 47.0 A Water Sr-90 pCi/L 508 481 346 - 595 A Gr-A pCi/L 147 124 45.3 - 17 A Gr-B pCi/L 72.9 68.0 34.0 - 93.6 A H-3 pCi/L 20,900 22,300 16,800 - 27,100 A Cs-134 pCi/L 1,820 1,960 1,480 - 2,160 A Cs-137 pCi/L 1,820 1,840 1,580 - 2,090 A Co-60 pCi/L 1,970 1,870 1,610 - 2,150 A Fe-55 pCi/L 1,410 1,460 858 - 2,120 A Mn-54 pCi/L <7.24 <100 <100 A Zn-65 pCi/L 1,490 1,370 1,220 - 1,730 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 (1) CARR190225-1192 (2) CARR190530-1211 E-9 (3) CARR190826-1250

TABLE E.8 Analytics Environmental Radioactivity Cross Check Program GEL Laboratories (Gamma and Sr-89/90 only)

Identification Reported Known Acceptance Quarter/Year Matrix Nuclide Units Evaluation (b)

Number Value Value (a) Limits 1st/2019 E12367 Water Cs-134 pCi/L 143 155 0.92 A Cs-137 pCi/L 209 191 1.10 A Co-58 pCi/L 143 139 1.03 A Co-60 pCi/L 318 290 1.10 A Fe-59 pCi/L 176 154 1.14 A M:n-54 pCi/L 155 139 1.12 A Zn-65 pCi/L 244 214 1.14 A 2nd/2019 E12361 Milk Sr-89 pCi/L 101 82.9 1.22 A Sr-90 pCi/L 12.1 13.5 0.90 A E12363 Water Cs-134 pCi/L 137 153 0.89 A Cs-137 pCi/L 190 184 1.03 A Co-58 pCi/L 122 122 1.00 A Co-60 pCi/L 222 216 1.03 A Fe-59 pCi/L 173 154 1.12 A Mn-54 pCi/L 227 270 1.10 A Zn-65 pCi/L 301 270 1.11 A 3rd/2019 E12369 Milk Sr-89 pCi/L 87.1 93.9 0.93 A Sr-90 pCi/L 7.02 12.9 0.54 A E12371 Water Cs-134 pCi/L 150 157 0.96 A Cs-137 pCi/L 122 114 1.07 A Co-58 pCi/L 136 133 1.03 A Co-60 pCi/L 168 160 1.04 A Fe-59 pCi/L 127 112 1.13 A Mn-54 pCi/L 134 117 1.15 A Zn-65 pCi/L 257 222 1.16 A 4th/2019 E12373 Milk Sr-89 pCi/L 66.0 80.6 0.82 A Sr-90 pCi/L 11.1 11.0 1.00 A E12375 Water Cs-134 pCi/L 106 114 0.93 A Cs-137 pCi/L 109 103 1.06 A Co-58 pCi/L 95.4 91.1 1.05 A Co-60 pCi/L 122 117 1.05 A Fe-59 pCi/L 93.2 88.2 1.06 A Mn-54 pCi/L 144 131 1.10 A Zn-65 pCi/L 191 161 1.19 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 laboratory's internal acceptance criteria of 75% - 125%:

A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits E-10

APPENDIX E ERRATA DATA

Intentionally left blank Errata Data for 2019

1. Pages 6 and 7 of the 2016 ARERR, Table 1 - Summary of Gaseous and Liquid Effluent Doses to Members of the Public at the Highest Dose Receptors and Table 2

- Summary of Gaseous and Liquid Effluent Doses to Members of the Public for 40CFR190 Compliance.

During a review of the 2016 calculated doses, it was determined that there were nine release permits associated with the North Stack that did not calculate dose for C-14.

The curies were correct, but the dose was not calculated. These permits were then recalculated and the correct dose was applied. This impacted the dose reported in Table 1 - Summary of Gaseous and Liquid Effluent Doses to Members of the Public at the Highest Dose Receptors for Iodine, Particulate, C-14 & Tritium and in Table 2

- Summary of Gaseous and Liquid Effluent Doses to Members of the Public for 40CFR190 Compliance for Organ Dose. None of the changes resulted in an applicable limit being exceeded.

See attached original and corrected pages for actual values updated highlighted in yellow.

2. Pages 14 and 15 of the 2018 ARERR, Table 1 - Summary of Gaseous and Liquid Effluent Doses to Members of the Public at the Highest Dose Receptors and Table 2

- Summary of Gaseous and Liquid Effluent Doses to Members of the Public for 40CFR190 Compliance.

The percent of applicable limit was transposed instead of the estimated dose from Table 1 to Table 2 for both Total Body Dose and Thyroid Dose for Gaseous Effluent Noble Gas. The percent of applicable limit value was 3.25E-03, while the estimated dose value was 3.25E-02. This resulted in a conservative value being listed in Table 2 - Summary of Gaseous and Liquid Effluent Doses to Members of the Public for 40CFR190 Compliance.

See attached original and corrected pages for actual values updated highlighted in yellow.

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• 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 2019 Prepared By Teledyne Brown Engineering Environmental Services Limerick Power Station Pottstown, PA 19464 April 2020

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 ................................................................................................. 9 A. Groundwater Results........................................................................................... 9 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 ............................................................................................................... 12 H. Investigations .................................................................................................... 12 I. Actions Taken ..................................................................................................... 12 V. References ................................................................................................................... 12

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2019 Figures Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2019 Figure 2 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2019 Figure 3 Routine Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2019 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, 2019 Table B-I.2 Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2019 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, 2019 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, 2019 Table B-II.2 Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2019 Table B-III.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2019

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 2019 through 31 December 2019. During that time period, 302 analyses were performed on 147 samples from 13 groundwater, 7 surface water and 4 precipitation water locations collected from the environment, both on and off station property in 2019.

Groundwater and surface water was analyzed for tritium. 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) was detected at 4 of the 13 groundwater locations sampled. Gross alpha (suspended) was detected at 1 of the 13 groundwater locations sampled. Gross beta (dissolved) was detected at 11 of 13 groundwater locations sampled. Gross beta (suspended) was detected at 2 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 2019.

Precipitation water samples were analyzed for tritium. Tritium was detected at 1 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 2019.

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:

1. Exelon and its consultant identified locations as described in the 2006 Phase 1 study. The Phase 1 study results and conclusions were made 2

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 by Exelon Industrial Services (EIS). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2019. 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.

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.

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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 GEL Laboratories, LLC (GEL) on environmental samples for the LGS RGPP in 2019. 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 measurements of tritium in various media performed by others.

Additional detail may be found by consulting references.

6

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 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 7

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.

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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 2,120 pCi/L.

Although no drinking water pathway is available from groundwater, the theoretical dose via the drinking water pathway was calculated at 0.125 mrem to a child (total body), which represents 2.09% 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-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, 2019. Gross alpha (dissolved) was detected in 4 of the 13 groundwater locations. The concentrations ranged from 1.3 to 5.2 pCi/L. Gross alpha (suspended) was detected in 1 of 13 groundwater locations sampled with concentrations ranging from 1.3 to 5.2 pCi/L. Gross beta (dissolved) was detected in 11 of 13 groundwater locations sampled. The concentrations ranged from 1.8 to 15.3 pCi/L.

Gross beta (suspended) was detected in 2 of the 13 groundwater locations sampled with concentrations ranging from 2.0 to 23.2 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 83 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 2019. (Appendix B, Table B-I.3)

B. Surface Water Results In accordance with the Station's Radiological Groundwater Protection 9

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 366 pCi/L. The theoretical dose via the drinking water pathway was calculated at 0.022 mrem to a child (total body), which represents 0.36% 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)

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 1 of 4 precipitation water locations analyzed. The concentrations ranged from 249 to 275 pCi/L. These concentrations are consistent with historical values observed.

(Appendix B, Table B-III.1)

D. Drinking Water Well Survey In April, 2019, GHD (formerly Conestoga Rover Associates) conducted a comprehensive database search (PaGWIS) for private and public wells within one mile of the Station. The detailed results of the 2019 well search are presented in Appendix C of the 2019 Hydrogeologic Investigation Report for Limerick Generating Station. In general, the well depths range from 45 to 585 feet bgs, and yield between 2 and 65 gpm. All wells are completed in the Brunswick Formation. In the GHD report, Figure 2.3 presents the approximate locations of the water wells that surround the Station.

A review of the PaGWIS database table reveals the following type and associated number of off-Station wells within the on-mile radius of the Station:

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x Domestic = 41 wells (68%)

x Industrial = 5 wells (8%)

x Observation = 9 wells (15%)

x Abandoned = 5 wells (8%)

x Total = 60 wells One well was identified at the active quarry, which is approximately 2,000 feet to the northwest of the Station. The PaGWIS database search identifies the quarry well as constructed to a depth of 100 feet bgs, and reportedly yields at least 50,400 gpd (35 gpm). A well inventory included in the Stations USFAR cites the total depth of the quarry supply well as 130 feet bgs, with a yield of 100 gpm, and typical operation of 50 gpm for ten hours a day.

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. In 2019, DW-LR-1 pumped 6,785,500 gallons.

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 2019, 1,709,275 gallons were pumped from the well.

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 2019.

However, the Power Block Foundation Sump, which collects groundwater around the reactor buildings, turbine building and rad waste building, identified tritium in one sample of potentially contaminated systems (IR 0423206). The activity of 1.33E-06 Ci/mL was recorded. The source of the tritium is groundwater movement from the previously identified and reported leaks/spills.

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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 wells.

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

V. References

1. GHD, Inc. Hydrogeologic Investigation Report, Limerick Generating Station, 3146 Sanatoga Road, Pottstown, Pennsylvania, Ref. No. 11189800(1),

December 2019

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 12

APPENDIX A LOCATION DESIGNATION

Intentionally left blank TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2019 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, 2019 A-2

Figure 2 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2019 A-3

Figure 3 Routine Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2019 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, 2019 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 02/06/19 < 183 DW-LR-1 05/06/19 < 193 1.5 +/- 0.8 < 0.8 < 1.3 < 1.4 DW-LR-1 08/14/19 < 195 < 3.9 < 0.9 DW-LR-1 11/04/19 < 184 MW-LR-1 05/08/19 < 197 < 3.2 < 0.7 < 0.6 < 0.4 5.4 +/- 1.1 < 1.7 MW-LR-2 02/06/19 < 188 MW-LR-2 05/08/19 < 191 < 5.7 < 0.6 < 0.6 < 0.8 3.4 +/- 0.9 < 1.4 MW-LR-2 08/14/19 < 191 MW-LR-2 11/04/19 194 +/- 124 MW-LR-3 02/06/19 < 183 MW-LR-3 05/08/19 < 193 < 4.2 < 0.6 < 0.9 < 0.8 3.0 +/- 1.1 < 1.4 MW-LR-3 08/14/19 < 197 MW-LR-3 11/04/19 < 194 MW-LR-4 02/06/19 < 192 MW-LR-4 05/08/19 < 190 < 3.4 < 0.8 < 1.6 < 0.4 3.8 +/- 1.1 < 1.7 MW-LR-4 08/14/19 < 195 MW-LR-4 11/04/19 < 191 MW-LR-5 02/06/19 311 +/- 141 MW-LR-5 02/06/19 DUP < 192 MW-LR-5 02/06/19 GEL < 114 MW-LR-5 04/22/19 226 +/- 127 MW-LR-5 05/08/19 2120 +/- 281 < 3.7 < 0.6 < 1.0 < 0.4 5.0 +/- 1.0 < 1.7 MW-LR-5 05/08/19 R1 1750 +/- 244 MW-LR-5 05/08/19 DUP 1940 +/- 263 < 4.1 < 0.5 1.3 +/- 0.8 < 0.4 5.6 +/- 1.0 < 1.7 MW-LR-5 05/08/19 DUP R1 1830 +/- 250 MW-LR-5 05/08/19 GEL 1860 +/- 481 < 0.6 < 0.7 < 3.2 (1) < 2.2 (1)

MW-LR-5 08/14/19 214 +/- 127 MW-LR-5 08/14/19 DUP < 194 MW-LR-5 08/14/19 GEL 203 +/- 89 MW-LR-5 11/04/19 273 +/- 127 MW-LR-5 11/04/19 DUP 328 +/- 129 MW-LR-5 11/04/19 GEL < 175 MW-LR-7 02/06/19 < 188 MW-LR-7 05/08/19 < 188 < 2.7 < 0.8 < 0.6 < 0.8 1.8 +/- 0.7 < 1.4 MW-LR-7 08/13/19 < 184 MW-LR-7 11/04/19 < 174 MW-LR-8 02/05/19 364 +/- 127 MW-LR-8 02/05/19 DUP 516 +/- 135 MW-LR-8 02/06/19 GEL 545 +/- 104 MW-LR-8 05/10/19 509 +/- 141 < 6.1 < 0.8 < 2.8 < 0.8 3.7 +/- 1.3 2.0 +/- 1.1 MW-LR-8 05/10/19 DUP 699 +/- 150 < 4.9 < 0.7 2.5 +/- 1.3 < 1.8 3.8 +/- 1.4 < 1.9 MW-LR-8 05/10/19 GEL 681 +/- 112 < 0.8 < 0.7 6.6 +/- 2.4 (1) 5.5 +/- 1.9 (1)

MW-LR-8 08/16/19 460 +/- 136 MW-LR-8 08/16/19 DUP 494 +/- 141 MW-LR-8 08/16/19 GEL 590 +/- 116 MW-LR-8 11/06/19 584 +/- 141 MW-LR-8 11/06/19 DUP 519 +/- 138 MW-LR-8 11/06/19 GEL 549 +/- 126 (1) Total gross alpha/beta results reported (not dissolved/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, 2019 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 02/05/19 679 +/- 145 MW-LR-9 02/05/19 DUP 900 +/- 165 MW-LR-9 02/05/19 GEL 904 +/- 123 MW-LR-9 05/10/19 855 +/- 163 < 8.9 < 0.8 4.2 +/- 1.7 8.6 +/- 3.8 15.3 +/- 2.4 23.2 +/- 4.9 MW-LR-9 05/10/19 DUP 1000 +/- 176 < 8.4 < 0.9 5.2 +/- 2.1 8.2 +/- 3.6 11.0 +/- 2.3 19.1 +/- 4.6 MW-LR-9 05/10/19 GEL 722 +/- 111 < 0.8 < 0.7 30.4 +/- 8.9 (1) 22.2 +/- 4.8 (1)

MW-LR-9 08/16/19 886 +/- 170 MW-LR-9 08/16/19 DUP 954 +/- 176 MW-LR-9 08/16/19 GEL 862 +/- 129 MW-LR-9 11/06/19 800 +/- 157 MW-LR-9 11/06/19 DUP 930 +/- 171 MW-LR-9 11/06/19 GEL 772 +/- 145 MW-LR-10 02/05/19 < 196 MW-LR-10 05/10/19 < 192 < 4.5 < 0.4 < 0.8 < 0.4 2.9 +/- 1.1 < 1.7 MW-LR-10 08/16/19 < 195 MW-LR-10 11/06/19 < 185 P11 02/05/19 < 183 P11 05/10/19 < 193 < 1.5 < 0.8 10.5 +/- 1.4 < 1.4 P11 08/16/19 < 196 < 6.3 < 0.9 P11 11/06/19 < 193 P14 02/05/19 < 191 P14 05/10/19 < 196 < 2.6 < 0.4 < 2.2 < 1.7 P14 08/16/19 < 193 < 4.5 < 0.7 P14 11/06/19 < 186 P17 05/08/19 < 196 < 1.2 < 0.4 2.1 +/- 1.2 < 1.7 (1) Total gross alpha/beta results reported (not dissolved/suspended)

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, 2019 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 DUP < 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 DW-LR-1 05/06/19 < 29 < 52 < 4 < 3 < 6 < 3 < 7 < 4 < 6 < 8 < 3 < 3 < 20 < 6 MW-LR-1 05/08/19 < 59 < 94 < 7 < 6 < 12 < 6 < 11 < 8 < 11 < 13 < 6 < 5 < 33 < 12 MW-LR-2 05/08/19 < 35 < 43 < 4 < 4 < 9 < 4 < 8 < 5 < 7 < 7 < 4 < 4 < 21 < 7 MW-LR-3 05/08/19 < 37 83 +/- 52 < 4 < 4 < 8 < 4 < 9 < 5 < 7 < 7 < 4 < 4 < 22 < 7 B-3 MW-LR-4 05/08/19 < 39 < 37 < 4 < 4 < 8 < 4 < 9 < 5 < 9 < 8 < 5 < 5 < 22 < 8 MW-LR-5 05/08/19 DUP < 47 < 52 < 6 < 5 < 12 < 5 < 13 < 6 < 10 < 10 < 6 < 5 < 29 < 9 MW-LR-5 05/08/19 GEL (1) (1) < 1 < 2 < 3 < 2 < 3 < 2 < 3 < 5 < 2 < 2 < 10 < 3 MW-LR-5 05/08/19 < 45 < 78 < 5 < 5 < 10 < 6 < 10 < 6 < 9 < 10 < 5 < 5 < 25 < 10 MW-LR-7 05/08/19 < 43 < 59 < 5 < 6 < 12 < 6 < 11 < 6 < 10 < 11 < 7 < 6 < 26 < 8 MW-LR-8 05/10/19 < 40 < 92 < 5 < 5 < 10 < 4 < 10 < 5 < 7 < 7 < 5 < 4 < 19 < 7 MW-LR-8 05/10/19 DUP < 46 < 98 < 5 < 5 < 12 < 5 < 9 < 7 < 10 < 10 < 6 < 5 < 25 < 9 MW-LR-8 05/10/19 GEL (1) (1) < 1 < 2 < 3 < 1 < 3 < 1 < 3 < 4 < 1 < 2 < 8 < 3 MW-LR-9 05/10/19 < 58 < 65 < 8 < 6 < 14 < 6 < 16 < 9 < 10 < 11 < 7 < 6 < 34 < 10 MW-LR-9 05/10/19 DUP < 48 < 82 < 5 < 6 < 12 < 6 < 11 < 7 < 9 < 9 < 6 < 6 < 25 < 10 MW-LR-9 05/10/19 GEL (1) (1) < 1 < 1 < 3 < 2 < 3 < 2 < 3 < 4 < 1 < 2 < 9 < 3 MW-LR-10 05/10/19 < 51 < 110 < 6 < 6 < 10 < 6 < 11 < 6 < 9 < 9 < 6 < 6 < 25 < 9 P11 05/10/19 < 61 < 70 < 6 < 7 < 13 < 7 < 14 < 8 < 12 < 12 < 8 < 7 < 34 < 9 P14 05/10/19 < 55 < 111 < 4 < 5 < 12 < 7 < 16 < 6 < 10 < 9 < 6 < 6 < 31 < 13 P17 05/08/19 < 55 < 71 < 8 < 7 < 15 < 7 < 13 < 7 < 14 < 12 < 9 < 6 < 38 < 9 (1) No result

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE 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 2019 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, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 SW-LR-2 02/06/19 < 183 SW-LR-2 05/06/19 < 190 < 6.2 < 0.8 SW-LR-2 08/13/19 < 193 SW-LR-2 11/06/19 < 180 SW-LR-4 02/06/19 < 182 SW-LR-4 05/06/19 < 189 < 6.4 < 0.6 SW-LR-4 08/13/19 < 182 SW-LR-4 11/06/19 < 186 SW-LR-6 02/06/19 < 189 SW-LR-6 05/06/19 < 187 < 3.9 < 0.8 SW-LR-6 08/13/19 < 182 SW-LR-6 11/06/19 < 180 SW-LR-7 02/06/19 < 188 SW-LR-7 05/06/19 < 192 < 4.3 < 0.8 SW-LR-7 08/13/19 < 181 SW-LR-7 11/06/19 < 192 SW-LR-8 02/05/19 < 192 SW-LR-8 05/06/19 366 +/- 136 < 4.9 < 0.6 SW-LR-8 08/14/19 < 181 SW-LR-8 11/05/19 < 183 SW-LR-9 02/05/19 < 184 SW-LR-9 05/06/19 < 185 < 4.3 < 0.7 SW-LR-9 08/14/19 < 198 SW-LR-9 11/04/19 < 184 SW-LR-10 02/06/19 < 190 SW-LR-10 05/08/19 < 186 < 6.1 < 0.6 SW-LR-10 08/13/19 < 184 SW-LR-10 11/06/19 < 183 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, 2019 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 05/06/19 < 58 < 137 < 7 < 6 < 13 < 7 < 12 < 7 < 11 < 14 < 5 < 6 < 28 < 15 SW-LR-4 05/06/19 < 52 < 120 < 4 < 6 < 13 < 7 < 12 < 6 < 10 < 12 < 6 < 5 < 25 < 13 SW-LR-6 05/06/19 < 54 < 59 < 6 < 6 < 15 < 6 < 12 < 6 < 10 < 13 < 7 < 6 < 39 < 8 SW-LR-7 05/06/19 < 37 < 41 < 4 < 4 < 9 < 5 < 8 < 5 < 7 < 9 < 4 < 5 < 24 < 9 SW-LR-8 05/06/19 < 68 < 130 < 7 < 6 < 15 < 8 < 14 < 7 < 10 < 14 < 8 < 4 < 34 < 6 SW-LR-9 05/06/19 < 53 < 117 < 6 < 6 < 10 < 7 < 13 < 7 < 12 < 13 < 7 < 5 < 33 < 9 SW-LR-10 05/08/19 < 35 < 39 < 4 < 4 < 7 < 4 < 7 < 4 < 6 < 7 < 4 < 4 < 20 < 5 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, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 36S3 01/02/19 - 01/28/19 < 188 36S3 01/28/19 - 02/26/19 < 194 36S3 02/26/19 - 04/02/19 < 198 36S3 04/02/19 - 04/30/19 < 190 36S3 04/30/19 - 06/03/19 < 191 36S3 06/03/19 - 07/01/19 < 199 36S3 07/01/19 - 07/29/19 < 182 36S3 07/29/19 - 09/04/19 < 192 36S3 09/04/19 - 09/30/19 < 186 36S3 09/30/19 - 10/28/19 < 186 36S3 10/28/19 - 12/03/19 < 189 36S3 12/03/19 - 12/30/19 < 190 E-5 01/02/19 - 01/28/19 < 189 E-5 01/28/19 - 02/26/19 < 188 E-5 02/26/19 - 04/02/19 < 196 E-5 04/02/19 - 04/30/19 < 189 E-5 04/30/19 - 06/03/19 < 188 E-5 06/03/19 - 07/01/19 < 193 E-5 07/01/19 - 07/29/19 < 184 E-5 07/29/19 - 09/04/19 < 189 E-5 09/04/19 - 09/30/19 < 189 E-5 09/30/19 - 10/28/19 < 183 E-5 10/28/19 - 12/03/19 < 188 E-5 12/03/19 - 12/30/19 < 189 ESE-6 01/02/19 - 01/28/19 < 192 ESE-6 01/28/19 - 02/26/19 < 190 ESE-6 02/26/19 - 04/02/19 < 194 ESE-6 04/02/19 - 04/30/19 < 194 ESE-6 04/30/19 - 06/03/19 < 189 ESE-6 06/03/19 - 07/01/19 < 197 ESE-6 07/01/19 - 07/29/19 < 186 ESE-6 07/29/19 - 09/04/19 < 186 ESE-6 09/04/19 - 09/30/19 < 185 ESE-6 09/30/19 - 10/28/19 < 186 ESE-6 10/28/19 - 12/03/19 < 191 ESE-6 12/03/19 - 12/30/19 < 189 SE-7 01/02/19 - 01/28/19 < 194 SE-7 01/28/19 - 02/26/19 < 190 SE-7 02/26/19 - 04/02/19 249 +/- 132 SE-7 04/02/19 - 04/30/19 < 186 SE-7 04/30/19 - 06/03/19 < 198 SE-7 06/03/19 - 07/01/19 < 196 SE-7 07/01/19 - 07/29/19 275 +/- 124 SE-7 07/29/19 - 09/04/19 < 190 SE-7 09/04/19 - 09/30/19 < 189 SE-7 09/30/19 - 10/28/19 257 +/- 125 SE-7 10/28/19 - 12/03/19 < 191 SE-7 12/03/19 - 12/30/19 < 197 B-7

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