Text

2017 Annual Radiological Environmental Operating Report
	ML18120A182
Person / Time
Site:	Limerick
Issue date:	04/30/2018
From:	Libra R; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LG-18-053
	Download: ML18120A182 (134)
	v • d • e

Exelon Generation ,

TS 6.9.1.7 LG-18-053 April 30, 2018 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRG Docket Nos. 50-352 and 50-353

Subject:

2017 Annual Radiological Environmental Operating Report In accordance with the requirements of Section 6.9.1.7 of Limerick Generating Station (LGS)

Unit 1 and Unit 2 Technical Specifications (TS), and Section 6.1 of the LGS Units 1 and 2 Offsite Dose Calculation Manual (ODCM), this letter submits the 2017 Annual Radiological Environmental Operating Report. This report provides the 2017 results for the Radiological Environmental Monitoring Program (REMP) as called for in the ODCM.

In assessing the data collected for the REMP, it has been concluded that the operation of LGS, Units 1 and 2 had no adverse impact on the environment. No plant-produced fission or activation products, with the exception of CS-137 and 1-131, were found in any pathway modeled by the REMP. Neither CS-137nor1-131 was concluded to be from LGS. The results of the groundwater protection program are also included in this report. Positive tritium was found in 3 of 13 groundwater monitoring locations that ranged from non-detectable to 770 pCi/L; which is below the EPA limit of 20,000 pCi/L.

There are no commitments contained in this letter.

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

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

Attachment:

2017 Annual Radiological Environmental Operating Report

LG-17-053 Page 2 cc: D. Dorman, Administrator, Region I, USNRC (w/attachment)

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

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

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

ATTACHMENT 2017 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 AND 2 Annual Radiological Environmental Operating Report 1 January through 31 December 2017 Prepared By Teledyne Brown Engineering Environmental Services Limerick Power Station Pottstown, PA 19464 April 2018

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

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

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

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

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

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

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

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

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

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

b. Broad Leaf Vegetation .................................................................. 21 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 ................................................................................................. 22 H. Summary of Results - Inter-Laboratory Comparison Program.......................... 22 VI. References..................................................................................................................... 26

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2017 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, 2017 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2017 Figures Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2017 Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2017 Figure B-3 Environmental Sampling Locations Greater Than 26,400 Feet from the Limerick Generating Station, 2017 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, 2017 Table C-I.2 Concentrations of I-131 in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-I.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-II.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-II.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-II.3 Concentrations of I-131 in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2017

Table C-II.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-III.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2017 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, 2017 Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-VI.1 Concentrations of I-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-VII.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-VIII.1 Concentrations of Gamma Emitters in Broad Leafy Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2017 Table C-IX.1 Quarterly DLR Results for Limerick Generating Station, 2017 Table C-IX.2 Mean Quarterly Dosimeter Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2017 Table C-IX.3 Summary of the Ambient Dosimetry Program for Limerick Generating Station, 2017 Figures Figure C-1 Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2017 Figure C-2 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2017 Figure C-3 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2017 Figure C-4 Mean Quarterly Ambient Gamma Radiation Levels (DLR) in the Vicinity of LGS, 1985 - 2017 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, 2017 Table D-I.2 Concentrations of I-131 in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2017 Table D-I.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2017 Table D-I.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2017 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, 2017 Table D-II.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2017 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, 2017 Figures Figure D-1 Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2017 Figure D-2 Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2017 Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2017 Table E-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2017 Table E-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2017 Table E-4 ERA MRAD Statistical Summary Proficiency Testing Program, Environmental, Inc., 2017 Table E-5 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2017 Table E-6 ERA RAD Statistical Summary Proficiency Testing Program, Environmental, Inc., 2017 Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR)

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

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

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

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

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

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

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

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

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

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

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

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

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

The second way a radionuclide is produced at a nuclear power plant is through a process called activation and the radionuclides produced in this method are termed activation products. Pure water that passes over the fissioning atoms is used to cool the reactor and also produce steam to turn the turbines. Although this water is considered to be very pure, there are always some contaminiants within the water from material used in the plants construction and operation.

These contaminants are exposed to the fission process and may become activation products. The atoms in the water itself can also become activated and create radionuclides.

Over time, radioactive atoms will reach a stable state and no longer be radioactive. To do this they must release their excess energy. This release of excess energy is called radioactive decay. The time it takes for a radionuclide to become stable is measured in units called half-lives. A half-life is the amount of time it takes for half of the original radioactivity to decay. Each radionuclide has a specific half-life. Some half-lives can be very long and measured in years while others may be very short and measured in seconds.

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

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

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

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

x Radioactivity refers to the amount of ionizing radiation released by a material. The units of measure for radioactivity used within the AREOR and ARERR are the Curie (Ci). Small fractions of the Ci often have a SUHIL[VXFKDVWKHPLFUR&XULH &L ZKLFKPHDQVRID&XULH

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

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 radiation to be reported in millirem (mrem), 1/1,000 of one rem.

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

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

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

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

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

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

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

The following graph is an example of one study that tries to relate risk from many different factors. This graph represents risk as Days of Lost Life Expectancy. All the categories are averaged over the entire population except Male Smokers, Female Smokers, and individuals that are overweight. Those risks are only for people that fall into those categories. The category for Nuclear Power is a government estimate based on all radioactivity releases from nuclear power, including accidents and wastes.

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

II. Summary and Conclusions In 2017, the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 70 curies of noble gas, fission and activation products and approximately 67 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 Effluent Applicable Estimated Age Group Location % of Limit Unit Organ Dose Applicable Limit Noble Gas Gamma - Air Dose 2.42E-03 All Nearest Residence 1.21E-02 20 mRad Noble Gas Beta - Air Dose 1.45E-03 All Nearest Residence 3.62E-03 40 mRad Noble Gas Total Body (Gamma) 2.29E-03 All Nearest Residence 2.29E-02 10 mrem Noble Gas Skin (Beta) 3.78E-03 All Nearest Residence 1.26E-02 30 mrem Iodine, Particulate, Bone 1.24E+00 Child Vegetation 4.13E+00 30 mrem Tritium & C-14 Liquid Total Body 5.43E-02 Child Phoenixville, PA 9.05E-01 6 mrem Liquid Liver 5.48E-02 Child Phoenixville, PA 2.74E-01 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 2017 through 31 December 2017. During that time period, 1,496 analyses were performed on 1,246 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. Samples taken in December from the onsite settling basin showed low levels of I-131 due to an upstream hospital. For results, discussion, and dose to member of the public calculation see Section IV.A.2. Gross beta activities detected were consistent with those detected in previous years. No other fission or activation products were detected.

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

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

Samples collected upstream of the discharge had Cesium-137 (Cs-137) concentrations that were consistent with those detected in previous years. No 8

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.

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

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

Concentrations of naturally-occurring Be-7 and K-40 were detected. Radium-226 (Ra-226) was found in 6 of 32 samples. Thorium-228 (Th-228) was found in 10 of 32 samples. Naturally-occurring Ra-226 and Th-228 were detected in low concentrations, which are consistent with historical values.

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

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

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

A Radiological Groundwater Protection Program (RGPP) was established in 2006 as part of an Exelon Nuclear fleetwide assessment of potential groundwater intrusion from the operation of the Station. In 2017, well water samples were analyzed for tritium, 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 lower limit of detection of 200 pCi/L.

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

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

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

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

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

This report covers those analyses performed by Teledyne Brown Engineering (TBE), Mirion Technologies, and Environmental Inc., Midwest Laboratory (EIML) on samples collected during the period 1 January 2017 through 31 December 2017.

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

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

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

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

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

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1. Identifying significant exposure pathways

2. Establishing baseline radiological data of media within those pathways

3. Continuously monitoring those media before and during station operation to assess station radiological effects (if any) on man and the environment IV. Program Description A. Sample Collection Samples for the LGS REMP were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used by NAI to obtain environmental samples for the LGS REMP in 2017. 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 NAI are listed in Table B-3.

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

Two-gallon water samples were collected monthly from composite samplers located at two surface water locations (13B1 and 24S1) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising of the flesh of two groups, bottom feeder (white sucker/carp/catfish) and predator (sunfish/bass/rock bass/catfish), were collected semiannually at two locations, 16C5 and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at three locations semiannually, 16B2, 16C4, and 33A2 (control).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk. Airborne iodine and particulate samples were collected and analyzed weekly at seven locations (6C1, 10S3, 11S1, 13S4, 14S1, 15D1, and 22G1). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.

11

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

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

Broad leaf vegetation was collected monthly, during the growing season, at three locations (11S3, 13S3, and 31G1). The control location was 31G1. Nine 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-22 1/2 degree sectors around the site, where estimated annual dose from LGS, if any, would be most significant;

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

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

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

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10 CFR 20.2002 Permit Storage Area In 1996, the Limerick Generating Station received NRC approval to store slightly contaminated soils, sludges and sediments on site per the requirements of 10 CFR 20.2002. These materials will be stored until end of the site's renewed operating license. At that time the material will be evaluated along with the site for decommissioning. The area is approximately 1.5 acres in size and was evaluated to hold a maximum of 1.12E+06 cubic feet with no more than 7E+04 cubic feet added to the area in any single year. After each material placement on the storage area, the area is graded and seeded to prevent erosion. Since all groundwater movement is to the river, the use of the REMP surface water sampling program is used as a check on potential groundwater movement from the pad. In 2017, no material was placed on the permitted storage area.

Independent Spent Fuel Storage Installation (ISFSI)

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

B. Sample Analysis This section lists the analyses performed by the primary laboratory (TBE) and the secondary laboratory (EIML) on environmental samples for the LGS REMP in 2017. 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 Environmental Inc.,

Midwest Laboratory 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 13

previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses are designed to achieve the required LGS detection limits for environmental sample analysis.

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

2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity was not detected.

Gamma spectroscopy results for each type of sample were grouped as follows:

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

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

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

D. Program Exceptions For 2017 the LGS REMP had a sample recovery rate of greater than 99%.

Exceptions are listed below:

1. Air sample from location 11S2 for the week of 01/17/17 - 01/24/17 was not available due to the pump not running. The pump was replaced on 01/26/17 (IR 3968583).

2. Air sample from location 10S3 for the week of 06/05/17 - 06/12/17 was not available due to the pump not running. The pump and fuse were replaced on 06/12/17 (IR 4037354).

3. Air sample from location 13S4 for the week of 6/27/17 - 7/4/17 was not available since the GFI breaker was tripped. The GFI was replaced on 7/6/17 (IR 4029563).

4. Air sample from location 6C1 for the week of 7/24/17 - 7/31/17 was not available due to an equipment issue (IR 4053146).

5. DLR data from location 36S2 was not reported for 3rd quarter of 2017 due to the TLD not being received by the vendor upon shipment. Data from 36S2 is normally used to calculate dose to the public to verify that the dose commitments of ODCM control 3.2.3 have been met. In lieu of this data, TLD location 3S1, a location closer to the plant, was used to show compliance. (IR 4097481).

6. Milk samples for location 18E1 for 10/31/17, 11/14/17, 11/28/17, and 12/12/17 were not available due to a fire at the farm (IR 4070461).

Each program exception was reviewed to understand the causes of the program exception. Occasional equipment breakdowns were unavoidable. The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E. Program Changes There were no program changes in 2017.

15

F. Compliance to 40 CFR 190 Limits

1. Dose to Members of the Public at or Beyond Site Boundary Per 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 Long term annual average meteorology X/Q and D/Q and actual gaseous effluent releases were used.

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

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

x 100 percent occupancy factor was assumed.

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

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

40 CFR 190 Compliance:

The maximum calculated dose to a real individual would not exceed 3.06E-01 mRem (total body), 1.30E+00 mRem (organ), or 3.05E-01 mRem (thyroid).

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

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

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

& Tritium Total Body 2.29E-03 2.49E-01 5.43E-02 0.00E+00 3.06E-01 1.22E+00 25 mRem Dose Organ Dose 3.78E-03 1.24E+00 5.48E-02 0.00E+00 1.30E+00 5.19E+00 25 mRem Thyroid Dose 2.29E-03 2.49E-01 5.41E-02 0.00E+00 3.05E-01 4.07E-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. A non-routine sample was taken in December from surface water location 13B1 and analyzed for low level I-131. I-131 was detected at 1.8 pCi/L. Coinciding with the positive I-131 identified at 13B1 during 4th quarter of 2017, a sample taken from the onsite settling basin also showed positive I-131 (IR 4083746). However, there were no radiological releases from the station during this period. After thorough evaluation, the I-131 is determined to be from an upstream hospital where the radiation emitted from I-131 is used to treat many types of cancer and non-malignant diseases. However, the dose to an infant's thyroid was conservatively calculated at 2.06E+00 mRem. This dose represents 1.03E+01% of the 10 CFR Part 50 Appendix I dose limits.

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:

17

Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Appendix C, Tables C-II.1). The values ranged from 2.1 to 5.1 pCi/L. 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).

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 (white sucker/carp/catfish) and predator (sunfish/bass/rock bass/catfish),

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

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

Naturally-occurring K-40 was found at all stations and ranged from 2,691 to 3,973 pCi/kg wet 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:

18

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

Be-7 was found at a two locations and ranged from 1,492 to 3,561 pCi/kg dry. K-40 was found at all locations and ranged from 8,645 to 15,390 pCi/kg dry. The fission product Cs-137 was found at location 16B2 with a concentration of 120 pCi/kg dry (IR 4037366).

The Cs-137 activity detected was consistent with those detected in the pre-operational years. The control location, 33A2, and a downstream location, 16C4, both showed no activity. Therefore, at 16B2, the Cs-137 activity found is not attributed to LGS radioactive effluent releases. However, the dose to a teenager's skin and whole body was conservatively calculated at 3.15E-04 mRem and 2.70E-04 mRem, respectively. This dose represents 1.58E-03%

and 4.50E-03%, of the Appendix I to 10 CFR Part 50 dose limits, respectively. No other Limerick fission or activation products were found.

B. Atmospheric Environment

1. Airborne

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

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

Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Appendix C, Table C-V.1 and C-V.2).Detectable gross beta activity was observed at all locations. The results from the on-site locations (Group I) ranged from 5E-3 to 29E-3 pCi/m3 with a mean of 14E-3 pCi/m3. The results from the intermediate distance location (Group II) ranged from 7E-3 to 29E-3 pCi/m3 with a mean of 15E-3 pCi/m3.

The results from the remote distance locations (Group III) 19

ranged from 7E-3 to 29E-3 pCi/m3 with a mean of 15E-3 pCi/m3. Comparison of the 2017 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 2017 indicates no notable differences among the three groups.

(Appendix C, Figure C-3).

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

Naturally-occurring Be-7 was detected in all 28 samples and is contributed to cosmic ray activity. These values ranged from 46E-3 to 105E-3 pCi/m3. All other nuclides were below the required LLDs.

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

2. Terrestrial

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

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

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

Naturally-occurring K-40 activity was found in all samples and ranged from 956 to 1,509 pCi/L. All other nuclides were below the required LLDs.

20

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

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

Cosmogenic, naturally-occurring Be-7 was found in 13 of 32 samples and ranged from 219 to 874 pCi/kg wet. Naturally-occurring K-40 was found in all samples and ranged from 1,219 to 7,356 pCi/kg wet. Naturally-occurring Ra-226 was found in 6 of 32 samples and ranged from 1,008 to 1,792 pCi/kg wet. Naturally-occurring Th-228 was found in 10 of 32 samples and ranged from 38 to 163 pCi/kg wet. All other nuclides were below the required LLDs.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO4) thermoluminescent dosimeters. Forty dosimeter locations were established around the site. Results of dosimeter measurements are listed in Appendix C, Tables C-IX.1 and C-IX.2, Figure C-4. Dosimeter measurements were reported in mR/standard month. All dosimeter measurements were below 10 mR/standard month, with a range of 3.7 to 8.3 mR/standard month. A 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.

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 21

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

F. Land Use Survey A Land Use Survey conducted in September 2017 around Limerick Generating Station (LGS) was performed by Normandeau Associates, Inc.

for Exelon Nuclear to comply with Bases 3.3.2 of the Limericks Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident, 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 2017 Land Use Survey identified differences in locations for gardens and meat animals between 2016 and 2017. The gardens identified in sectors ENE, E, ESE, SE, and WNW are newly identified and closer than in 2016. The location for meat animals in sectors NNE, SE, and NNW are closer than in 2016 and location for meat animals in sectors NE and SSW are farther away than in 2016. There were no changes required to the LGS REMP as a result of this survey.

The results of this survey are summarized below:

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

Sector Residence Garden Milk Farm Meat Animal Feet Feet Feet Feet 1 N 3,109 3,333 24,775 24,775 2 NNE 2,706 12,399 - 25,067 3 NE 3,469 16,718 - 16,044 4 ENE 3,231 8,241 - 7,451 5 E 2,864 7,868 - -

6 ESE 3,434 3,434 - 12,385 7 SE 3,945 7,139 - 10,903 8 SSE 5,403 6,912 - -

9 S 4,347 6,103 22,114 12,210 10 SSW 5,063 5,732 10,390 10,390 11 SW 3,251 6,544 - 23,145 12 WSW 3,799 4,507 14,177 14,177 13 W 3,627 8,886 - 17,137 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 22

(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:

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

B. ERA Evaluation Criteria ERAs evaluation report provides an acceptance range for control and warning limits with associated flag values. ERAs acceptance limits are established per the USEPA, National Environmental Laboratory Accreditation Conference (NELAC), state-specific Performance Testing (PT) program requirements or ERAs SOP for the Generation of Performance Acceptance Limits, as applicable.

The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

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

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

to +/- 30% of the reference value x Not Acceptable (flag = N) - bias is greater than 30% of the reference value Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities.

For the TBE laboratory, 168 out of 173 analyses performed met the specified acceptance criteria. Five analyses did not meet the specified 23

acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program.

1. The Analytics September 2017 soil Cr-51 result was evaluated as Not Acceptable (Ratio of TBE to known result at 0.65). The reported value was 0.230 +/- 0.144 pCi/g and the known value was 0.355 +/- 0.00592 pCi/g. The sample was counted overnight for 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months , however the Cr-51 was spiked at a very low level and had a counting error of 65%. Cr-51 has a 27-day half-life, making low-level quantification even more difficult. The error does not appear to have been taken into consideration for this result. If it had been evaluated with the error, the highest result would have been 105%

of the reference value, which is acceptable. Also, the known value is significantly lower than TBEs typical MDC for this nuclide in a soil matrix and would typically not be reported to clients (unless specified). The results of all of the previous cross-checks have been in the acceptable (80 - 120%) range. TBE will evaluate further upon completion of the next ICP sample. (NCR 17-16)

2. The DOE MAPEP August 2017 air particulate U-238 result of 0.115

+/- 0.025 Bq/sample was higher than the known value of 0.087 +/-

0.002 with a ratio of 1.32, therefore the upper ratio of 1.30 (acceptable with warning) was exceeded. TBEs result with error easily overlaps with the acceptable range. MAPEP does not evaluate results with any associated error. Also, the spike level for this sample was very low (2.35 pCi) compared to TBEs normal LCS of 6 pCi. TBE considers this result as passing. (NCR 17-15)

3. The ERA April 2017 two nuclides in water were evaluated as Not Acceptable. (NCR 17-09)

a. The Zn-65 result of 39.3 pCi/L, exceeded the lower acceptance limit of 47.2. The known value was unusually low for this study.

The sample was run in duplicate on two different detectors. The results of each were 39.3 +/- 18.2 pCi/L (46% error and lower efficiency) and 59.3 +/- 8.23 pCi/L (13.9% error and higher efficiency). The result from the 2nd detector would have been well within the acceptable range (47.2 - 65.9) and 110.2% of the known value of 53.8 pCi/L.

b. The Sr-89 result of 40.7 pCi/L exceeded the lower acceptance limit of 53.8. All associated QC and recoveries were reviewed and no apparent cause could be determined for the failure. The prior three cross-check results were from 99 - 115% of the known values and the one that followed this sample (November, 2017) was 114% of the known value.

24

4. The ERA November 2017 water Sr-90 sample was evaluated as Not Acceptable. TBEs result of 27.1 pCi/L exceeded the lower acceptance range (30.8 - 48.0 pCi/L). After reviewing the associated QC data for this sample, it was determined that although the spike recovery for Sr-90 was within our laboratory guidelines (70% -130%), both the spike result and our ERA result were biased low. The original cross-check sample was completely consumed and we were unable to reanalyze before submitting the result. We have modified our preparation process to avoid this situation for future cross-check samples. We also have enhanced LIMS programming to force a LCSD when a workgroup includes cross-check samples (as opposed to running a DUP). (NCR 17-19)

For the EIML laboratory, 181 of 189 analyses met the specified acceptance criteria. Eight analyses did not meet the specified acceptance criteria for the following reasons:

1. The ERA March 2017 MRAD air filter Fe-55 result of 590 pCi/filter was higher than the known value of 256 pCi/filter, exceeding the upper control limit of 500 pCi/filter. The 1000-minute recount result of 254 pCi/filter fell within acceptance criteria.

2. The ERA March 2017 MRAD air filter Gross Beta result of 67.6 pCi/filter was higher than the known value of 45.2 pCi/filter, exceeding the lower control limit of 65.9 pCi/filter. ERA appears to have applied the standard material to the filter in a pattern closer to the center of the filter compared to previous studies and different from the filter efficiency utilized by the lab, causing the efficiency calculation to be understated and the lab result to be overstated.

Associated QC was acceptable.

3. The ERA March 2017 MRAD soil Pu-239/240 result of 252 pCi/kg was lower than the known value of 484 pCi/kg, exceeding the lower control limit of 316 pCi/kg. The sample was reanalyzed in duplicate with acceptable results. Suspected poor electroplating for low original analysis result.

4. The ERA March 2017 MRAD soil U-233/234 result of 1,030 pCi/kg was lower than the known value of 1,950 pCi/kg, exceeding the lower control limit of 1,190 pCi/kg. The sample was reanalyzed in duplicate with acceptable results. Suspected poor electroplating for low original analysis result.

5. The ERA March 2017 MRAD water Fe-55 result of 1,400 pCi/L was higher than the known value of 984 pCi/L, exceeding the upper 25

control limit of 1,340 pCi/L. The sample was recounted with results in the acceptable range.

6. The MAPEP February 2017 water Co-57 result of 2.7 Bq/L sample was lower than the known value of 28.5 Bq/L sample. The decimal point was misplaced while performing a unit conversion. The result is within control limits when the proper unit conversion is performed.

7. The MAPEP February 2017 air filter Am-241 result of 0.0540 Bq/total sample was higher than the known value of 0.0376 Bq/total sample. The sample was reanalyzed in duplicate with acceptable results. Original plating was inferior to plating obtained during reanalysis. It is believed that isotopic tracer was not accurately quantified due to poor resolution of its peak.

8. The MAPEP August 2017 air filter Am-241 result of 0.0400 Bq/total sample was lower than the known value of 0.0612 Bq/total sample.

The laboratory is not currently offering analysis for air particulate Am-241.

The Inter-Laboratory Comparison Program provides evidence of in control counting systems and methods, and that the laboratories are producing accurate and reliable data.

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 26

Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2017 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2017 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR REQUIRED NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER H-3 8 200 <LLD <LLD - 0 (PCI/LITER)

GAMMA 24 MN-54 15 <LLD <LLD - 0 CO-58 15 <LLD <LLD - 0 FE-59 30 <LLD <LLD - 0 CO-60 15 <LLD <LLD - 0 ZN-65 30 <LLD <LLD - 0 A-1 NB-95 15 <LLD <LLD - 0 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) 14 1 1.8 <LLD 1.8 13B1 INDICATOR 0 (1/1) (1/1) VINCENT DAM 1.75 MILES SE OF SITE DRINKING WATER GR-B 48 4 3.6 3.3 4 15F4 INDICATOR 0 (PCI/LITER) (31/36) (9/12) (12/12) AQUA WATER COMPANY 2.1 - 5.1 2.5 - 4.8 2.4 - 5.1 H-3 16 200 <LLD <LLD - 0 I-131 (LOW LVL) 48 1 <LLD <LLD - 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2017 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2017 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 A-2 CS-134 15 <LLD <LLD - 0 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 3520 3462 3520 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL 3067 - 3973 3442 - 3482 3067 - 3973 DOWNSTREAM OF DISCHARGE MN-54 130 <LLD <LLD - 0 CO-58 130 <LLD <LLD - 0 FE-59 260 <LLD <LLD - 0 CO-60 130 <LLD <LLD - 0 ZN-65 260 <LLD <LLD - 0 I-131 NA <LLD <LLD - 0 CS-134 130 <LLD <LLD - 0 CS-137 150 <LLD <LLD - 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2017 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2017 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 3086.5 3001.5 3086.5 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL 2736 - 3437 2691 - 3312 2736 - 3437 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 A-3 ZN-65 260 <LLD <LLD - 0 I-131 NA <LLD <LLD - 0 CS-134 130 <LLD <LLD - 0 CS-137 150 <LLD <LLD - 0 SEDIMENT GAMMA 6 (PCI/KG DRY) BE-7 NA 2194 <LLD 2600 16B2 INDICATOR 0 (4/4) (2/2) LINFIELD BRIDGE 1492 - 3561 1638 - 3561 7128 FEET SSE OF SITE K-40 NA 14113 9478 14940 16B2 INDICATOR 0 (4/4) (2/2) (2/2) LINFIELD BRIDGE 11380 - 15390 8645 - 10310 14490 - 15390 7128 FEET SSE OF SITE MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 I-131 NA <LLD <LLD - 0 CS-134 150 <LLD <LLD - 0 CS-137 180 120 <LLD 120 16B2 INDICATOR 0 (1/4) (1/2) LINFIELD BRIDGE 1.35 MILES SSE OF SITE (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2017 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2017 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 15 15 14S1 INDICATOR 0 (E-3 PCI/CU.METER) (304/309) (52/52) (50/52) LONGVIEW ROAD 5 - 29 7 - 29 7 - 28 3319 FEET SSE OF SITE GAMMA 28 BE-7 NA 69.9 70.1 77.1 6C1 INDICATOR 0 (24/24) (4/4) (4/4) LIMERICK AIRPORT 46.4 - 105.4 55.7 - 81 51.7 - 105.4 11305 FEET NE OF SITE A-4 MN-54 NA <LLD <LLD - 0 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-3 PCI/CU.METER) I-131 (GELI) 70 <LLD <LLD - 0 MILK I-131 (LOW LVL) 88 1 <LLD <LLD - 0 (PCI/LITER)

GAMMA 88 K-40 NA 1241 1259 1288 23F1 CONTROL 0 (62/62) (26/26) (22/22) 1021 - 1509 956 - 1456 1200 - 1456 26505 FEET SW OF SITE CS-134 15 <LLD <LLD - 0 CS-137 18 <LLD <LLD - 0 BA-140 60 <LLD <LLD - 0 LA-140 15 <LLD <LLD - 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2017 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD: 2017 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 32 (PCI/KG WET) BE-7 NA 514 457.7 537.5 13S3 INDICATOR 0 (5/21) (8/11) (3/10) LGS 500 KV YARD 328.2 - 873.5 219.3 - 695.7 328.2 - 873.5 1267 FEET SE OF SITE K-40 NA 4512 4640.2 4640.2 31G1 CONTROL 0 (21/21) (11/11) (11/11) PROUT'S JOLLYVIEW FARM 1219 - 7356 2319 - 6607 2319 - 6607 71,808 FEET NW OF SITE MN-54 NA <LLD <LLD - 0 A-5 CO-58 NA <LLD <LLD - 0 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 1382.2 <LLD 1382.2 13S3 INDICATOR 0 (6/21) (6/10) LGS 500 KV YARD 1008 - 1991 1008 - 1991 1267 FEET SE OF SITE TH-228 NA 90.9 103.7 103.7 31G1 CONTROL 0 (7/21) (3/11) (3/11) PROUT'S JOLLYVIEW FARM 38 - 163 55.3 - 148.3 55.3 - 148.3 71,808 FEET NW OF SITE TH-232 NA <LLD <LLD - 0 DIRECT RADIATION OSLD-QUARTERLY 318 NA 5.6 6.8 7.7 13S2 INDICATOR 0 (MILLI-ROENTGEN/STD.MO.) (156/156) (4/4) (4/4) 500 KV SUBSTATION 3.6 - 9.8 6.2 - 7.3 7.5 - 8 0.41 MILES SE (M) The Mean Values are calculated using the positive values. (F) Fraction of dectectable measurements at specified locations are indicated in parentheses.

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, 2017 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, 2017 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, 2017 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Monthly composite from RMC-ER5 Collection of water samples TBE, TBE-2007 Gamma emitting radioisotope analysis Gamma Surface Water a continuous water for radiological analysis (Limerick 2 gallon Env. Inc., GS-01 Determination of gamma emitters by Spectroscopy compositor Generating Station) gamma spectroscopy TBE, TBE-2011 Tritium analysis in drinking water by liquid Quarterly composite RMC-ER5 Collection of water samples scintillation Surface Water Tritium from a continuous water for radiological analysis (Limerick 500 ml compositor Generating Station) Env. Inc., T-02 Determination of tritium in water (direct method)

TBE, TBE-2008 Gross Alpha and/or gross beta activity in various matrices Monthly composite from RMC-ER5 Collection of water samples Env. Inc., W(DS)-01 Determination of gross alpha and/or Drinking Water Gross Beta a continuous water for radiological analysis (Limerick 2 gallon gross beta in water (dissolved solids or total residue) compositor Generating Station)

Env. Inc., W(SS)-02 Determination of gross alpha and/or gross beta in water (suspended solids)

B-4 Monthly composite from RMC-ER10 Collection of water samples TBE, TBE-2012 Radioiodine in various matrices Drinking Water I-131 a continuous water for radiological analysis (Limerick 2 gallon Env. Inc., I-131-01 Determination of I-131 in water by an ion compositor Generating Station) exchange Monthly composite from RMC-ER5 Collection of water samples TBE, TBE-2007 Gamma emitting radioisotope analysis Gamma Drinking Water a continuous water for radiological analysis (Limerick 2 gallon Env. Inc., GS-01 Determination of gamma emitters by Spectroscopy compositor Generating Station) gamma spectroscopy TBE, TBE-2011 Tritium analysis in drinking water by liquid Quarterly composite RMC-ER5 Collection of water samples scintillation Drinking Water Tritium from a continuous water for radiological analysis (Limerick 500 ml compositor Generating Station) Env. Inc., T-02 Determination of tritium in water (direct method)

Semi-annual samples TBE-2007 Gamma emitting radioisotope analysis RMC-ER6 Collection of fish samples for Gamma collected via 1000 grams Fish radiological analysis (Limerick Env. Inc., GS-01 Determination of gamma emitters by Spectroscopy electroshocking or (wet)

Generating Station) gamma spectroscopy other techniques RMC-ER7 Collection of sediment TBE, TBE-2007 Gamma emitting radioisotope analysis Gamma Semi-annual grab 500 grams Sediment samples for radiological analysis Env. Inc., GS-01 Determination of gamma emitters by Spectroscopy samples (dry)

(Limerick Generating Station) gamma spectroscopy

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2017 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium One-week composite of 1 filter TBE, TBE-2008 Gross Alpha and/or gross beta activity in RMC-ER8 Collection of air particulate various matrices continuous air sampling (approximately Air Particulates Gross Beta and air iodine samples for radiological through glass fiber filter 280 cubic Env. Inc., AP-02 Determination of gross alpha and/or gross analysis (Limerick Generating Station) paper meters weekly) beta in air particulate filters TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis Gamma Quarterly composite of Env. Inc., AP-03 Procedure for (approximately Air Particulates Env. Inc., GS-01 Determination of gamma emitters by Spectroscopy each station compositing air particulate filters for 3600 cubic meters) gamma spectroscopy gamma spectroscopic analysis 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis One-week composite of RMC-ER8 Collection of air particulate Gamma (approximately Air Iodine continuous air sampling and air iodine samples for radiological Spectroscopy 280 cubic Env. Inc., I-131-02 Determination of I-131 in charcoal through charcoal filter analysis (Limerick Generating Station) meters weekly) canisters by gamma spectroscopy (batch method)

B-5 Bi-weekly grab sample TBE, TBE-2012 Radioiodine in various matrices RMC-ER10 Collection of milk samples for when cows are on Milk I-131 radiological analysis (Limerick 2 gallon pasture; Monthly all Env. Inc., I-131-01 Determination of I-131 in milk by anion Generating Station) other times exchange Bi-weekly grab sample TBE, TBE-2007 Gamma emitting radioisotope analysis RMC-ER10 Collection of milk samples for Gamma when cows are on Milk radiological analysis (Limerick 2 gallon Spectroscopy pasture; Monthly all Env. Inc., GS-01 Determination of gamma emitters by Generating Station) other times gamma spectroscopy Quarterly DLRs RMC-ER9 Collection of dosimetry Thermoluminescent DLR comprised of two samples for radiological analysis 2 dosimeters Mirion Technologies Dosimetry dosimeter elements (Limerick Generating Station)

Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2017 B-6

Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2017 B-7

Figure B-3 Environmental Sampling Locations Greater than 26,400 Feet from the Limerick Generating Station, 2017 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, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 13B1 24S1 12/27/16 - 03/28/17 < 193 < 197 03/28/17 - 06/26/17 < 189 < 195 06/26/17 - 10/03/17 < 173 < 180 10/03/17 - 01/02/18 < 192 < 194 MEAN - -

Table C-I.2 CONCENTRATIONS OF I-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 13B1 24S1 01/30/17 - 02/28/17 < 0.5 02/28/17 - 03/28/17 < 0.4 03/28/17 - 05/01/17 < 0.5 05/01/17 - 05/31/17 < 0.8 05/31/17 - 06/26/17 < 0.6 06/26/17 - 08/01/17 < 0.5 08/01/17 - 08/29/17 < 0.3 08/29/17 - 10/03/17 < 0.4 10/03/17 - 10/31/17 < 0.5 10/31/17 - 11/28/17 < 0.8 11/28/17 - 01/02/18 < 0.6 12/12/17 - 12/19/17 1.8 +/- 0.4 < 0.6 12/13/17 - 12/13/17 < 0.5 MEAN +/- 2 STD DEV 1.8 +/- 0 -

THE MEAN AND 2-STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1

Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 13B1 12/27/16 - 01/30/17 < 7 < 7 < 13 < 7 < 14 < 6 < 9 < 6 < 6 < 7 < 22 < 9 01/30/17 - 02/28/17 < 7 < 9 < 18 < 8 < 23 < 9 < 15 < 9 < 8 < 9 < 28 < 8 02/28/17 - 03/28/17 < 5 < 4 < 9 < 5 < 10 < 5 < 7 < 6 < 5 < 5 < 17 < 6 03/28/17 - 05/01/17 < 7 < 6 < 14 < 8 < 12 < 7 < 12 < 10 < 6 < 8 < 24 < 9 05/01/17 - 05/31/17 < 8 < 7 < 15 < 7 < 16 < 8 < 11 < 13 < 10 < 8 < 32 < 10 05/31/17 - 06/26/17 < 9 < 8 < 18 < 8 < 21 < 8 < 16 < 10 < 8 < 10 < 36 < 14 06/26/17 - 08/01/17 < 8 < 9 < 19 < 10 < 16 < 9 < 16 < 10 < 9 < 7 < 40 < 11 08/01/17 - 08/29/17 < 8 < 5 < 13 < 8 < 13 < 7 < 11 < 12 < 6 < 7 < 33 < 14 08/29/17 - 10/03/17 < 7 < 7 < 16 < 8 < 13 < 7 < 12 < 14 < 5 < 7 < 36 < 9 10/03/17 - 10/31/17 < 8 < 7 < 17 < 8 < 16 < 9 < 11 < 9 < 7 < 7 < 30 < 11 10/31/17 - 11/28/17 < 8 < 6 < 9 < 5 < 16 < 6 < 8 < 6 < 5 < 7 < 26 < 4 11/28/17 - 01/02/18 < 9 < 10 < 18 < 12 < 19 < 11 < 15 < 10 < 9 < 12 < 34 < 12 C-2 MEAN - - - - - - - - - - - -

24S1 12/27/16 - 01/30/17 < 4 < 4 < 9 < 5 < 8 < 5 < 8 < 5 < 4 < 5 < 15 < 6 01/30/17 - 02/28/17 < 8 < 6 < 15 < 8 < 16 < 7 < 10 < 8 < 7 < 7 < 25 < 7 02/28/17 - 03/28/17 < 6 < 6 < 11 < 7 < 12 < 6 < 9 < 7 < 5 < 6 < 17 < 7 03/28/17 - 05/01/17 < 7 < 7 < 15 < 7 < 16 < 7 < 12 < 9 < 7 < 8 < 28 < 8 05/01/17 - 05/31/17 < 9 < 7 < 18 < 8 < 14 < 9 < 16 < 14 < 8 < 8 < 36 < 11 05/31/17 - 06/26/17 < 4 < 5 < 11 < 5 < 9 < 5 < 9 < 6 < 5 < 5 < 18 < 5 06/26/17 - 08/01/17 < 9 < 8 < 16 < 8 < 17 < 9 < 17 < 11 < 10 < 10 < 33 < 10 08/01/17 - 08/29/17 < 5 < 5 < 12 < 5 < 12 < 5 < 9 < 9 < 4 < 5 < 21 < 7 08/29/17 - 10/03/17 < 8 < 8 < 16 < 8 < 15 < 7 < 14 < 15 < 7 < 7 < 37 < 10 10/03/17 - 10/31/17 < 6 < 6 < 11 < 7 < 10 < 6 < 11 < 7 < 6 < 7 < 20 < 8 10/31/17 - 11/28/17 < 6 < 6 < 16 < 8 < 10 < 6 < 13 < 8 < 6 < 9 < 27 < 9 11/28/17 - 01/02/18 < 7 < 6 < 13 < 7 < 14 < 7 < 13 < 6 < 6 < 7 < 24 < 8 MEAN - - - - - - - - - - - -

Table C-II.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 12/27/16 - 01/30/17 3.9 +/- 1.6 3.0 +/- 1.5 3.7 +/- 1.6 3.2 +/- 1.5 01/30/17 - 02/28/17 4.6 +/- 1.8 2.4 +/- 1.5 3.2 +/- 1.6 3.8 +/- 1.6 02/28/17 - 03/28/17 3.1 +/- 1.8 < 2.6 < 2.7 < 2.6 03/28/17 - 05/01/17 3.5 +/- 1.5 3.0 +/- 1.4 2.4 +/- 1.3 2.5 +/- 1.3 05/01/17 - 05/31/17 3.5 +/- 1.5 < 2.0 2.1 +/- 1.4 < 2.0 05/31/17 - 06/26/17 2.4 +/- 1.6 < 2.2 < 2.3 < 2.2 06/26/17 - 08/01/17 5.1 +/- 1.8 3.3 +/- 1.5 2.8 +/- 1.6 2.7 +/- 1.5 08/01/17 - 08/29/17 3.7 +/- 1.5 4.4 +/- 1.5 2.2 +/- 1.5 2.8 +/- 1.4 08/29/17 - 10/03/17 4.9 +/- 1.7 4.5 +/- 1.7 3.0 +/- 1.6 4.8 +/- 1.7 10/03/17 - 10/31/17 5.1 +/- 1.7 3.6 +/- 1.7 4.6 +/- 1.8 4.8 +/- 1.7 10/31/17 - 11/28/17 4.3 +/- 1.6 4.0 +/- 1.5 3.5 +/- 1.6 2.9 +/- 1.5 11/28/17 - 01/02/18 4.3 +/- 1.7 5.0 +/- 1.8 2.4 +/- 1.6 2.6 +/- 1.6 MEAN +/- 2 STD DEV 4.0 +/- 1.7 3.7 +/- 1.7 3.0 +/- 1.6 3.3 +/- 1.8 Table C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 12/27/16 - 03/28/17 < 191 < 195 < 190 < 193 03/28/17 - 06/26/17 < 190 < 193 < 190 < 188 06/26/17 - 10/03/17 < 178 < 178 < 178 < 178 10/03/17 - 01/02/18 < 192 < 192 < 190 < 190 MEAN - - - -

Table C-II.3 CONCENTRATIONS OF I-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 12/27/16 - 01/30/17 < 0.7 < 0.6 < 0.8 < 0.7 01/30/17 - 02/28/17 < 0.5 < 0.7 < 0.7 < 0.5 02/28/17 - 03/28/17 < 0.3 < 0.3 < 0.4 < 0.4 03/28/17 - 05/01/17 < 0.5 < 0.6 < 0.5 < 0.4 05/01/17 - 05/31/17 < 0.7 < 0.7 < 0.7 < 0.7 05/31/17 - 06/26/17 < 0.7 < 0.6 < 0.7 < 0.7 06/26/17 - 08/01/17 < 0.6 < 0.5 < 0.5 < 0.4 08/01/17 - 08/29/17 < 0.4 < 0.6 < 0.5 < 0.3 08/29/17 - 10/03/17 < 0.7 < 0.8 < 0.4 < 0.4 10/03/17 - 10/31/17 < 0.5 < 0.6 < 0.5 < 0.5 10/31/17 - 11/28/17 < 0.7 < 0.6 < 0.6 < 0.8 11/28/17 - 01/02/18 < 0.6 < 0.7 < 0.6 < 0.8 MEAN - - - -

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

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 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 12/27/16 - 01/30/17 < 5 < 5 < 10 < 5 < 9 < 5 < 9 < 5 < 5 < 19 < 5 01/30/17 - 02/28/17 < 7 < 5 < 13 < 7 < 14 < 7 < 13 < 6 < 8 < 27 < 8 02/28/17 - 03/28/17 < 4 < 4 < 7 < 5 < 10 < 5 < 8 < 4 < 5 < 18 < 4 03/28/17 - 05/01/17 < 7 < 7 < 14 < 6 < 13 < 5 < 11 < 6 < 7 < 23 < 7 05/01/17 - 05/31/17 < 7 < 6 < 17 < 8 < 13 < 8 < 13 < 7 < 7 < 38 < 11 05/31/17 - 06/26/17 < 6 < 7 < 12 < 8 < 12 < 7 < 13 < 7 < 6 < 22 < 9 06/26/17 - 08/01/17 < 7 < 8 < 15 < 8 < 16 < 10 < 12 < 8 < 8 < 32 < 12 08/01/17 - 08/29/17 < 7 < 5 < 14 < 8 < 8 < 6 < 12 < 6 < 6 < 30 < 6 08/29/17 - 10/03/17 < 7 < 8 < 12 < 7 < 15 < 6 < 13 < 6 < 8 < 34 < 15 10/03/17 - 10/31/17 < 7 < 7 < 13 < 5 < 18 < 7 < 13 < 7 < 7 < 30 < 11 10/31/17 - 11/28/17 < 6 < 7 < 12 < 8 < 13 < 6 < 9 < 6 < 7 < 27 < 8 11/28/17 - 01/02/18 < 7 < 6 < 11 < 9 < 18 < 7 < 11 < 6 < 9 < 30 < 6 C-4 MEAN - - - - - - - - - - -

15F7 12/27/16 - 01/30/17 < 8 < 7 < 15 < 8 < 18 < 8 < 14 < 8 < 8 < 32 < 10 01/30/17 - 02/28/17 < 7 < 6 < 14 < 8 < 17 < 7 < 13 < 7 < 7 < 29 < 7 02/28/17 - 03/28/17 < 6 < 6 < 11 < 6 < 9 < 4 < 9 < 6 < 6 < 21 < 6 03/28/17 - 05/01/17 < 6 < 8 < 10 < 8 < 17 < 7 < 13 < 8 < 9 < 27 < 11 05/01/17 - 05/31/17 < 7 < 8 < 15 < 9 < 18 < 8 < 14 < 7 < 7 < 36 < 13 05/31/17 - 06/26/17 < 8 < 7 < 23 < 10 < 14 < 7 < 15 < 8 < 10 < 28 < 10 06/26/17 - 08/01/17 < 8 < 8 < 20 < 10 < 18 < 10 < 15 < 10 < 12 < 37 < 11 08/01/17 - 08/29/17 < 7 < 6 < 13 < 7 < 15 < 8 < 13 < 7 < 8 < 36 < 11 08/29/17 - 10/03/17 < 5 < 5 < 11 < 4 < 10 < 5 < 8 < 4 < 5 < 25 < 10 10/03/17 - 10/31/17 < 7 < 7 < 16 < 9 < 15 < 9 < 10 < 10 < 10 < 32 < 6 10/31/17 - 11/28/17 < 8 < 8 < 18 < 8 < 21 < 8 < 12 < 10 < 9 < 32 < 9 11/28/17 - 01/02/18 < 4 < 5 < 7 < 6 < 10 < 5 < 9 < 5 < 6 < 18 < 7 MEAN - - - - - - - - - - -

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 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 12/27/16 - 01/30/17 < 6 < 6 < 9 < 5 < 11 < 5 < 9 < 5 < 6 < 23 < 6 01/30/17 - 02/28/17 < 6 < 6 < 12 < 7 < 12 < 7 < 12 < 7 < 8 < 26 < 11 02/28/17 - 03/28/17 < 5 < 4 < 10 < 5 < 11 < 5 < 9 < 5 < 5 < 20 < 8 03/28/17 - 05/01/17 < 6 < 5 < 15 < 6 < 16 < 7 < 16 < 8 < 8 < 28 < 6 05/01/17 - 05/31/17 < 7 < 6 < 13 < 7 < 16 < 6 < 10 < 6 < 7 < 29 < 7 05/31/17 - 06/26/17 < 6 < 7 < 11 < 5 < 12 < 7 < 12 < 6 < 7 < 25 < 8 06/26/17 - 08/01/17 < 9 < 7 < 18 < 10 < 20 < 8 < 17 < 11 < 9 < 34 < 12 08/01/17 - 08/29/17 < 6 < 7 < 17 < 8 < 13 < 5 < 13 < 6 < 7 < 34 < 14 08/29/17 - 10/03/17 < 7 < 6 < 14 < 5 < 14 < 6 < 12 < 7 < 6 < 34 < 10 10/03/17 - 10/31/17 < 10 < 10 < 18 < 9 < 18 < 9 < 16 < 13 < 9 < 31 < 12 10/31/17 - 11/28/17 < 6 < 7 < 15 < 8 < 15 < 8 < 12 < 8 < 7 < 28 < 9 11/28/17 - 01/02/18 < 6 < 6 < 14 < 6 < 10 < 7 < 12 < 6 < 6 < 25 < 7 C-5 MEAN - - - - - - - - - - -

28F3 12/27/16 - 01/30/17 < 5 < 5 < 9 < 5 < 10 < 4 < 7 < 4 < 5 < 20 < 5 01/30/17 - 02/28/17 < 7 < 6 < 9 < 7 < 14 < 6 < 11 < 5 < 7 < 21 < 7 02/28/17 - 03/28/17 < 6 < 7 < 13 < 7 < 13 < 7 < 14 < 6 < 7 < 26 < 10 03/28/17 - 05/01/17 < 6 < 7 < 16 < 6 < 15 < 7 < 13 < 7 < 9 < 24 < 12 05/01/17 - 05/31/17 < 8 < 8 < 16 < 8 < 14 < 10 < 13 < 7 < 7 < 35 < 13 05/31/17 - 06/26/17 < 7 < 6 < 15 < 8 < 16 < 7 < 12 < 6 < 8 < 28 < 10 06/26/17 - 08/01/17 < 8 < 9 < 19 < 10 < 18 < 8 < 13 < 9 < 10 < 33 < 12 08/01/17 - 08/29/17 < 7 < 6 < 12 < 6 < 13 < 5 < 12 < 6 < 6 < 26 < 9 08/29/17 - 10/03/17 < 7 < 8 < 14 < 8 < 11 < 7 < 13 < 6 < 7 < 31 < 12 10/03/17 - 10/31/17 < 5 < 7 < 14 < 8 < 14 < 7 < 13 < 6 < 7 < 25 < 8 10/31/17 - 11/28/17 < 7 < 8 < 12 < 8 < 15 < 8 < 14 < 7 < 10 < 30 < 5 11/28/17 - 01/02/18 < 8 < 8 < 16 < 7 < 20 < 9 < 11 < 8 < 9 < 28 < 12 MEAN - - - - - - - - - - -

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

SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 I-131 Cs-134 Cs-137 16C5 PREDATOR 06/08/17 3437 +/- 765 < 40 < 41 < 88 < 55 < 123 < 67 < 51 < 48 10/10/17 2736 +/- 1032 < 77 < 65 < 128 < 68 < 193 < 114 < 64 < 72 MEAN +/- 2 STD DEV 3087 +/- 991 - - - - - - - -

16C5 BOTTOM FEEDER 06/08/17 3067 +/- 1063 < 60 < 75 < 125 < 56 < 148 < 76 < 67 < 78 10/10/17 3973 +/- 1044 < 50 < 54 < 113 < 62 < 121 < 97 < 48 < 55 MEAN +/- 2 STD DEV 3520 +/- 1281 - - - - - - - -

C-6 29C1 PREDATOR 06/15/17 2691 +/- 928 < 68 < 54 < 140 < 59 < 126 < 85 < 65 < 60 10/11/17 3312 +/- 1074 < 77 < 70 < 123 < 86 < 135 < 101 < 70 < 82 MEAN +/- 2 STD DEV 3002 +/- 878 - - - - - - - -

29C1 BOTTOM FEEDER 06/15/17 3482 +/- 863 < 44 < 52 < 115 < 62 < 107 < 62 < 46 < 45 10/11/17 3442 +/- 745 < 62 < 53 < 126 < 65 < 135 < 91 < 67 < 62 MEAN +/- 2 STD DEV 3462 +/- 57 - - - - - - - -

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, 2017 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 I-131 Cs-134 Cs-137 16B2 06/14/17 3561 +/- 858 14490 +/- 1924 < 106 < 66 < 108 < 93 < 64 120 +/- 84 12/06/17 1638 +/- 810 15390 +/- 2163 < 102 < 101 < 151 < 145 < 101 < 160 MEAN +/- 2 STD DEV 2600 +/- 2720 14940 +/- 1273 - - - - - 120 +/- 0 16C4 06/14/17 2083 +/- 817 11380 +/- 1477 < 82 < 51 < 98 < 98 < 77 < 103 12/06/17 1492 +/- 786 15190 +/- 2201 < 107 < 99 < 126 < 150 < 96 < 139 MEAN +/- 2 STD DEV 1788 +/- 836 13285 +/- 5388 - - - - - -

33A2 06/14/17 < 882 10310 +/- 1976 < 113 < 93 < 94 < 100 < 98 < 131 C-7 12/06/17 < 951 8645 +/- 1966 < 118 < 109 < 143 < 175 < 111 < 124 MEAN +/- 2 STD DEV - 9478 +/- 2355 - - - - - -

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, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD 10S3 11S1 13S4 14S1 6C1 15D1 22G1 01/03/17 - 01/09/17 14 +/- 6 9 +/- 5 8 +/- 3 11 +/- 5 9 +/- 5 12 +/- 5 10 +/- 5 01/09/17 - 01/17/17 17 +/- 4 18 +/- 5 11 +/- 3 16 +/- 4 17 +/- 4 15 +/- 4 18 +/- 4 01/17/17 - 01/24/17 < 6 8 +/- 5 12 +/- 3 7 +/- 4 < 6 10 +/- 5 12 +/- 5 01/24/17 - 01/30/17 13 +/- 5 11 +/- 5 9 +/- 3 12 +/- 5 14 +/- 6 12 +/- 5 16 +/- 6 01/30/17 - 02/06/17 16 +/- 5 15 +/- 5 17 +/- 3 17 +/- 5 17 +/- 5 22 +/- 5 17 +/- 5 02/06/17 - 02/13/17 22 +/- 5 24 +/- 5 19 +/- 3 22 +/- 5 21 +/- 5 23 +/- 5 25 +/- 5 02/13/17 - 02/21/17 19 +/- 5 21 +/- 5 15 +/- 3 18 +/- 4 18 +/- 4 18 +/- 5 18 +/- 5 02/21/17 - 02/27/17 15 +/- 5 14 +/- 5 13 +/- 3 14 +/- 5 14 +/- 5 12 +/- 5 15 +/- 5 02/27/17 - 03/06/17 17 +/- 5 16 +/- 5 15 +/- 3 15 +/- 5 13 +/- 5 13 +/- 5 17 +/- 5 03/06/17 - 03/13/17 12 +/- 5 11 +/- 5 10 +/- 3 11 +/- 5 18 +/- 5 11 +/- 5 12 +/- 5 03/13/17 - 03/20/17 24 +/- 5 13 +/- 5 13 +/- 3 16 +/- 5 16 +/- 5 19 +/- 5 17 +/- 5 03/20/17 - 03/27/17 19 +/- 5 21 +/- 5 16 +/- 3 19 +/- 5 19 +/- 5 17 +/- 5 22 +/- 5 03/27/17 - 04/03/17 < 6 8 +/- 4 8 +/- 3 < 6 9 +/- 4 8 +/- 4 7 +/- 4 04/03/17 - 04/10/17 8 +/- 4 14 +/- 5 7 +/- 3 9 +/- 4 11 +/- 4 8 +/- 4 10 +/- 4 04/10/17 - 04/17/17 13 +/- 5 13 +/- 5 12 +/- 3 12 +/- 5 14 +/- 5 12 +/- 5 18 +/- 5 04/17/17 - 04/24/17 13 +/- 5 8 +/- 4 6 +/- 3 7 +/- 4 9 +/- 4 8 +/- 4 11 +/- 5 04/24/17 - 05/02/17 10 +/- 4 10 +/- 4 7 +/- 2 10 +/- 4 8 +/- 4 10 +/- 4 10 +/- 4 05/02/17 - 05/08/17 7 +/- 5 10 +/- 5 8 +/- 3 12 +/- 5 12 +/- 5 11 +/- 5 8 +/- 5 05/08/17 - 05/15/17 9 +/- 4 11 +/- 4 7 +/- 2 12 +/- 4 11 +/- 4 14 +/- 4 9 +/- 4 05/15/17 - 05/22/17 12 +/- 5 17 +/- 5 11 +/- 3 15 +/- 5 13 +/- 5 11 +/- 5 9 +/- 5 05/22/17 - 05/30/17 6 +/- 4 6 +/- 4 5 +/- 3 < 6 9 +/- 4 7 +/- 4 7 +/- 4 05/30/17 - 06/05/17 14 +/- 5 16 +/- 5 10 +/- 3 11 +/- 5 10 +/- 5 15 +/- 5 15 +/- 5 06/05/17 - 06/12/17 (1) 10 +/- 5 12 +/- 3 11 +/- 5 14 +/- 5 10 +/- 5 11 +/- 5 06/12/17 - 06/19/17 13 +/- 4 19 +/- 5 15 +/- 3 19 +/- 5 17 +/- 5 15 +/- 4 14 +/- 4 06/19/17 - 06/27/17 12 +/- 4 17 +/- 4 15 +/- 5 15 +/- 4 16 +/- 4 20 +/- 5 13 +/- 4 06/27/17 - 07/03/17 14 +/- 5 15 +/- 5 (1) 16 +/- 6 19 +/- 6 22 +/- 6 20 +/- 5 07/03/17 - 07/11/17 11 +/- 4 15 +/- 4 14 +/- 4 15 +/- 4 12 +/- 4 14 +/- 4 17 +/- 4 07/11/17 - 07/17/17 17 +/- 6 19 +/- 6 16 +/- 4 15 +/- 6 15 +/- 6 14 +/- 6 19 +/- 6 07/17/17 - 07/24/17 20 +/- 5 12 +/- 5 14 +/- 3 18 +/- 5 21 +/- 5 17 +/- 5 20 +/- 5 07/24/17 - 07/31/17 9 +/- 4 8 +/- 4 6 +/- 3 8 +/- 4 (1) 10 +/- 4 7 +/- 4 07/31/17 - 08/08/17 13 +/- 4 11 +/- 4 18 +/- 5 16 +/- 4 9 +/- 4 11 +/- 4 17 +/- 4 08/08/17 - 08/14/17 22 +/- 6 15 +/- 7 17 +/- 4 18 +/- 6 16 +/- 5 16 +/- 5 17 +/- 5 08/14/17 - 08/22/17 23 +/- 5 18 +/- 4 18 +/- 3 20 +/- 5 16 +/- 4 23 +/- 5 20 +/- 4 08/22/17 - 08/28/17 9 +/- 5 11 +/- 5 12 +/- 4 14 +/- 6 10 +/- 5 10 +/- 5 15 +/- 5 08/28/17 - 09/05/17 11 +/- 4 14 +/- 4 12 +/- 3 13 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 09/05/17 - 09/11/17 9 +/- 5 10 +/- 5 10 +/- 3 11 +/- 5 13 +/- 5 11 +/- 5 10 +/- 5 09/11/17 - 09/19/17 15 +/- 4 19 +/- 5 19 +/- 3 18 +/- 5 20 +/- 5 18 +/- 4 20 +/- 4 09/19/17 - 09/25/17 26 +/- 6 26 +/- 6 20 +/- 4 25 +/- 6 23 +/- 5 29 +/- 6 24 +/- 5 09/25/17 - 10/02/17 10 +/- 4 11 +/- 4 13 +/- 3 19 +/- 5 14 +/- 5 13 +/- 5 11 +/- 4 10/02/17 - 10/10/17 12 +/- 4 16 +/- 4 13 +/- 3 14 +/- 4 14 +/- 4 14 +/- 4 13 +/- 4 10/10/17 - 10/16/17 11 +/- 5 8 +/- 5 10 +/- 4 10 +/- 5 11 +/- 5 15 +/- 5 7 +/- 4 10/16/17 - 10/23/17 22 +/- 5 20 +/- 5 17 +/- 4 27 +/- 6 20 +/- 5 24 +/- 5 21 +/- 5 10/23/17 - 10/30/17 12 +/- 5 15 +/- 5 13 +/- 3 15 +/- 5 15 +/- 5 15 +/- 5 12 +/- 4 10/30/17 - 11/06/17 14 +/- 5 13 +/- 5 10 +/- 3 12 +/- 5 15 +/- 5 12 +/- 4 16 +/- 4 11/06/17 - 11/13/17 16 +/- 4 15 +/- 4 15 +/- 3 19 +/- 5 17 +/- 4 14 +/- 4 15 +/- 4 11/13/17 - 11/20/17 16 +/- 5 15 +/- 5 12 +/- 3 15 +/- 5 13 +/- 5 12 +/- 5 14 +/- 5 11/20/17 - 11/27/17 23 +/- 5 20 +/- 5 19 +/- 4 24 +/- 5 24 +/- 5 18 +/- 5 29 +/- 5 11/27/17 - 12/04/17 22 +/- 5 16 +/- 5 17 +/- 4 19 +/- 5 22 +/- 5 23 +/- 6 22 +/- 5 12/04/17 - 12/11/17 29 +/- 5 19 +/- 5 20 +/- 4 28 +/- 5 24 +/- 5 22 +/- 5 23 +/- 5 12/11/17 - 12/18/17 12 +/- 4 12 +/- 4 10 +/- 3 15 +/- 5 13 +/- 4 11 +/- 4 15 +/- 4 12/18/17 - 12/26/17 16 +/- 4 15 +/- 4 14 +/- 3 15 +/- 4 9 +/- 4 16 +/- 4 17 +/- 4 12/26/17 - 01/02/18 14 +/- 5 15 +/- 5 13 +/- 3 13 +/- 5 12 +/- 5 14 +/- 5 11 +/- 4 MEAN +/- 2 STD DEV 15 +/- 10 14 +/- 9 13 +/- 8 15 +/- 9 15 +/- 8 15 +/- 9.6 15 +/- 10 THE MEAN AND 2-STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8

Table C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF E-3 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 01/03/17 - 01/30/17 7 18 12 +/- 7 01/03/17 - 01/30/17 9 17 13 +/- 6 01/03/17 - 01/30/17 10 18 14 +/- 7 01/30/17 - 02/27/17 13 24 18 +/- 7 01/30/17 - 02/27/17 12 23 18 +/- 8 01/30/17 - 02/27/17 15 25 19 +/- 8 02/27/17 - 04/03/17 8 24 15 +/- 9 02/27/17 - 04/03/17 8 19 14 +/- 8 02/27/17 - 04/03/17 7 22 15 +/- 11 04/03/17 - 05/02/17 6 14 10 +/- 5 04/03/17 - 05/02/17 8 14 10 +/- 5 04/03/17 - 05/02/17 10 18 12 +/- 7 05/02/17 - 05/30/17 5 17 10 +/- 7 05/02/17 - 05/30/17 7 14 11 +/- 5 05/02/17 - 05/30/17 7 9 8 +/- 2 05/30/17 - 07/03/17 10 19 14 +/- 5 05/30/17 - 07/03/17 10 22 16 +/- 8 05/30/17 - 07/03/17 11 20 14 +/- 7 07/03/17 - 07/31/17 6 20 14 +/- 8 07/03/17 - 07/31/17 10 21 15 +/- 7 07/03/17 - 07/31/17 7 20 16 +/- 11 07/31/17 - 08/28/17 9 23 16 +/- 8 07/31/17 - 08/28/17 9 23 14 +/- 10 07/31/17 - 08/28/17 15 20 17 +/- 4 08/28/17 - 10/02/17 9 26 16 +/- 11 08/28/17 - 10/02/17 11 29 17 +/- 11 08/28/17 - 10/02/17 10 24 16 +/- 12 10/02/17 - 10/30/17 8 27 15 +/- 10 10/02/17 - 10/30/17 11 24 16 +/- 8 10/02/17 - 10/30/17 7 21 13 +/- 12 C-9 10/30/17 - 12/04/17 10 24 17 +/- 7 10/30/17 - 12/04/17 12 24 17 +/- 9 10/30/17 - 12/04/17 14 29 19 +/- 13 12/04/17 - 01/02/18 10 29 16 +/- 11 12/04/17 - 01/02/18 9 24 15 +/- 11 12/04/17 - 01/02/18 11 23 17 +/- 10 01/03/17 - 01/02/18 5 29 14 +/- 9 01/03/17 - 01/02/18 7 29 15 +/- 9 01/03/17 - 01/02/18 7 29 15 +/- 10

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 10S3 01/03/17 - 04/03/17 55 +/- 20 < 3 < 2 < 3 < 2 < 2 04/03/17 - 07/03/17 69 +/- 22 < 3 < 3 < 3 < 2 < 2 07/03/17 - 10/02/17 63 +/- 18 < 3 < 3 < 3 < 3 < 2 10/02/17 - 01/02/18 64 +/- 16 < 3 < 3 < 3 < 3 < 3 MEAN +/- 2 STD DEV 63 +/- 12 - - - - -

11S1 01/03/17 - 04/03/17 68 +/- 25 < 4 < 2 < 3 < 2 < 2 04/03/17 - 07/03/17 73 +/- 27 < 4 < 4 < 4 < 4 < 4 07/03/17 - 10/02/17 83 +/- 40 < 3 < 5 < 4 < 4 < 4 10/02/17 - 01/02/18 58 +/- 15 < 2 < 2 < 2 < 2 < 2 MEAN +/- 2 STD DEV 71 +/- 21 - - - - -

13S4 01/03/17 - 04/03/17 69 +/- 17 < 2 < 2 < 2 < 2 < 2 04/03/17 - 06/27/17 78 +/- 17 < 2 < 2 < 1 < 2 < 1 07/06/17 - 10/02/17 62 +/- 16 < 2 < 2 < 2 < 1 < 2 10/02/17 - 01/02/18 46 +/- 12 < 2 < 2 < 1 < 2 < 1 MEAN +/- 2 STD DEV 64 +/- 27 - - - - -

14S1 01/03/17 - 04/03/17 84 +/- 31 < 4 < 3 < 3 < 4 < 4 04/03/17 - 07/03/17 75 +/- 19 < 3 < 2 < 2 < 2 < 2 07/03/17 - 10/02/17 68 +/- 24 < 2 < 3 < 3 < 3 < 2 10/02/17 - 01/02/18 72 +/- 21 < 3 < 3 < 2 < 3 < 2 MEAN +/- 2 STD DEV 75 +/- 13 - - - - -

15D1 01/03/17 - 04/03/17 75 +/- 19 < 3 < 3 < 2 < 2 < 2 04/03/17 - 07/03/17 81 +/- 22 < 2 < 3 < 3 < 3 < 3 07/03/17 - 10/02/17 76 +/- 23 < 3 < 3 < 1 < 3 < 3 10/02/17 - 01/02/18 50 +/- 17 < 3 < 3 < 2 < 2 < 2 MEAN +/- 2 STD DEV 70 +/- 28 - - - - -

22G1 01/03/17 - 04/03/17 77 +/- 32 < 3 < 3 < 2 < 3 < 3 04/03/17 - 07/03/17 81 +/- 16 < 3 < 3 < 4 < 3 < 3 07/03/17 - 10/02/17 66 +/- 31 < 4 < 4 < 3 < 3 < 3 10/02/17 - 01/02/18 56 +/- 25 < 3 < 4 < 5 < 3 < 4 MEAN +/- 2 STD DEV 70 +/- 23 - - - - -

6C1 01/03/17 - 04/03/17 52 +/- 31 < 4 < 4 < 4 < 4 < 4 04/03/17 - 07/03/17 77 +/- 26 < 3 < 3 < 4 < 4 < 4 07/03/17 - 10/02/17 105 +/- 27 < 2 < 3 < 3 < 2 < 3 10/02/17 - 01/02/18 74 +/- 20 < 2 < 3 < 2 < 3 < 2 MEAN +/- 2 STD DEV 77 +/- 44 - - - - -

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, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER + 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD 10S3 11S1 13S4 14S1 6C1 15D1 22G1 01/03/17 - 01/09/17 < 28 < 28 < 20 < 32 < 28 < 33 < 33 01/09/17 - 01/17/17 < 23 < 23 < 15 < 23 < 23 < 26 < 26 01/17/17 - 01/24/17 < 36 < 36 < 22 < 36 < 36 < 38 < 38 01/24/17 - 01/30/17 < 47 < 47 < 24 < 47 < 46 < 40 < 39 01/30/17 - 02/06/17 < 40 < 40 < 25 < 42 < 40 < 43 < 43 02/06/17 - 02/13/17 < 33 < 33 < 9 < 33 < 14 < 38 < 37 02/13/17 - 02/21/17 < 22 < 22 < 17 < 22 < 22 < 28 < 28 02/21/17 - 02/27/17 < 47 < 47 < 10 < 44 < 46 < 44 < 42 02/27/17 - 03/06/17 < 30 < 30 < 10 < 30 < 12 < 44 < 44 03/06/17 - 03/13/17 < 36 < 36 < 20 < 36 < 35 < 35 < 33 03/13/17 - 03/20/17 < 29 < 29 < 29 < 47 < 29 < 47 < 48 03/20/17 - 03/27/17 < 43 < 44 < 15 < 44 < 43 < 49 < 46 03/27/17 - 04/03/17 < 32 < 33 < 15 < 32 < 32 < 26 < 26 04/03/17 - 04/10/17 < 23 < 23 < 12 < 23 < 22 < 20 < 19 04/10/17 - 04/17/17 < 35 < 35 < 19 < 31 < 34 < 31 < 31 04/17/17 - 04/24/17 < 40 < 40 < 10 < 40 < 39 < 37 < 36 04/24/17 - 05/02/17 < 31 < 31 < 18 < 29 < 31 < 29 < 28 05/02/17 - 05/08/17 < 40 < 40 < 9 < 38 < 40 < 39 < 41 05/08/17 - 05/15/17 < 39 < 39 < 7 < 28 < 38 < 29 < 29 05/15/17 - 05/22/17 < 59 < 59 < 14 < 59 < 58 < 58 < 57 05/22/17 - 05/30/17 < 34 < 34 < 26 < 41 < 34 < 42 < 40 05/30/17 - 06/05/17 < 38 < 38 < 19 < 29 < 37 < 30 < 30 06/05/17 - 06/12/17 (1) < 24 < 6 < 24 < 23 < 24 < 24 06/12/17 - 06/19/17 < 41 < 40 < 14 < 41 < 40 < 41 < 38 06/19/17 - 06/27/17 < 20 < 20 < 26 < 20 < 20 < 23 < 21 06/27/17 - 07/03/17 < 40 < 40 (1) < 40 < 15 < 40 < 38 07/03/17 - 07/11/17 < 20 < 20 < 19 < 20 < 20 < 19 < 17 07/11/17 - 07/17/17 < 46 < 46 < 17 < 47 < 46 < 61 < 58 07/17/17 - 07/24/17 < 35 < 36 < 19 < 36 < 35 < 31 < 29 07/24/17 - 07/31/17 < 29 < 12 < 19 < 30 (1) < 30 < 27 07/31/17 - 08/08/17 < 35 < 36 < 9 < 22 < 35 < 22 < 19 08/08/17 - 08/14/17 < 18 < 63 < 12 < 42 < 42 < 41 < 40 08/14/17 - 08/22/17 < 30 < 30 < 11 < 39 < 30 < 38 < 34 08/22/17 - 08/28/17 < 39 < 40 < 19 < 31 < 39 < 30 < 29 08/28/17 - 09/05/17 < 25 < 25 < 7 < 26 < 25 < 31 < 29 09/05/17 - 09/11/17 < 45 < 45 < 20 < 46 < 45 < 32 < 30 09/11/17 - 09/19/17 < 35 < 35 < 10 < 36 < 35 < 27 < 25 09/19/17 - 09/25/17 < 36 < 36 < 22 < 34 < 36 < 34 < 32 09/25/17 - 10/02/17 < 34 < 34 < 19 < 30 < 34 < 29 < 27 10/02/17 - 10/10/17 < 30 < 30 < 11 < 31 < 30 < 20 < 18 10/10/17 - 10/16/17 < 34 < 35 < 16 < 29 < 34 < 29 < 27 10/16/17 - 10/23/17 < 40 < 40 < 20 < 31 < 40 < 31 < 28 10/23/17 - 10/30/17 < 49 < 50 < 27 < 41 < 49 < 41 < 39 10/30/17 - 11/06/17 < 41 < 42 < 24 < 37 < 41 < 36 < 34 11/06/17 - 11/13/17 < 35 < 35 < 18 < 27 < 35 < 27 < 25 11/13/17 - 11/20/17 < 40 < 40 < 16 < 46 < 40 < 46 < 43 11/20/17 - 11/27/17 < 36 < 37 < 9 < 39 < 36 < 38 < 36 11/27/17 - 12/04/17 < 32 < 33 < 14 < 21 < 32 < 20 < 19 12/04/17 - 12/11/17 < 40 < 41 < 12 < 20 < 40 < 20 < 19 12/11/17 - 12/18/17 < 32 < 33 < 27 < 45 < 32 < 44 < 41 12/18/17 - 12/26/17 < 37 < 38 < 23 < 38 < 37 < 38 < 35 12/26/17 - 01/02/18 < 40 < 41 < 11 < 21 < 40 < 21 < 19 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, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION CONTROL FARM INDICATOR FARM PERIOD 23F1 36E1 18E1 19B1 25C1 01/10/17 < 0.7 < 0.7 < 0.8 < 0.6 < 0.7 02/07/17 < 0.3 < 0.4 < 0.3 < 0.4 03/07/17 < 0.9 < 0.9 < 0.8 < 0.5 04/04/17 < 0.7 < 0.7 < 0.9 < 0.8 < 0.8 04/18/17 < 0.9 < 0.8 < 0.6 < 0.6 05/02/17 < 0.5 < 0.8 < 0.8 < 1.0 05/16/17 < 0.9 < 0.9 < 0.9 < 0.9 05/30/17 < 0.4 < 0.4 < 0.3 < 0.3 06/13/17 < 0.8 < 0.7 < 0.5 < 0.5 06/27/17 < 0.6 < 0.7 < 0.6 < 0.6 07/11/17 < 0.5 < 0.7 < 0.7 < 0.5 < 0.6 07/25/17 < 0.7 < 0.5 < 0.7 < 0.6 08/08/17 < 0.8 < 0.8 < 0.8 < 0.8 08/22/17 < 0.5 < 0.4 < 0.4 < 0.7 09/05/17 < 0.7 < 0.7 < 0.7 < 1.0 09/19/17 < 0.5 < 0.5 < 0.8 < 1.0 10/03/17 < 0.6 < 0.7 < 0.4 < 0.3 < 0.6 10/17/17 < 0.4 < 0.3 < 0.6 < 0.4 10/31/17 < 0.6 (1) < 0.8 < 0.5 11/14/17 < 0.6 (1) < 0.8 < 0.8 11/28/17 < 0.7 (1) < 0.5 < 0.5 12/12/17 < 0.4 (1) < 0.8 < 0.8 MEAN - - - - -

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

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 18E1 01/10/17 1034 +/- 189 < 9 < 9 < 29 < 11 02/07/17 1276 +/- 187 < 6 < 5 < 31 < 8 03/07/17 1307 +/- 215 < 11 < 10 < 40 < 10 04/04/17 1344 +/- 228 < 13 < 13 < 43 < 10 04/18/17 1137 +/- 135 < 7 < 6 < 21 < 9 05/02/17 1054 +/- 182 < 7 < 8 < 30 < 9 05/16/17 1296 +/- 128 < 5 < 5 < 14 < 7 05/30/17 1282 +/- 173 < 7 < 8 < 32 < 11 06/13/17 1130 +/- 160 < 15 < 12 < 40 < 11 06/27/17 1338 +/- 170 < 10 < 10 < 40 < 12 07/11/17 1285 +/- 146 < 5 < 7 < 34 < 9 07/25/17 1021 +/- 195 < 8 < 9 < 35 < 10 08/08/17 1272 +/- 158 < 6 < 7 < 27 < 7 08/22/17 1105 +/- 201 < 9 < 9 < 44 < 9 09/05/17 1079 +/- 139 < 6 < 6 < 23 < 9 09/19/17 1231 +/- 143 < 5 < 6 < 30 < 9 10/03/17 1376 +/- 156 < 5 < 7 < 32 < 8 10/17/17 1377 +/- 188 < 6 < 7 < 27 < 7 MEAN +/- 2 STD DEV 1219 +/- 245 - - - -

19B1 01/10/17 1324 +/- 153 < 6 < 7 < 20 < 7 02/07/17 1159 +/- 150 < 5 < 7 < 24 < 6 03/07/17 1190 +/- 216 < 10 < 10 < 34 < 13 04/04/17 1118 +/- 172 < 9 < 9 < 31 < 9 04/18/17 1328 +/- 118 < 5 < 5 < 19 < 5 05/02/17 1117 +/- 188 < 7 < 9 < 29 < 8 05/16/17 1145 +/- 183 < 7 < 11 < 39 < 12 05/30/17 1161 +/- 218 < 9 < 9 < 46 < 15 06/13/17 1201 +/- 183 < 11 < 9 < 42 < 14 06/27/17 1047 +/- 202 < 9 < 11 < 34 < 9 07/11/17 1171 +/- 190 < 7 < 7 < 41 < 12 07/25/17 1351 +/- 168 < 10 < 8 < 33 < 10 08/08/17 1249 +/- 185 < 6 < 8 < 22 < 9 08/22/17 1280 +/- 155 < 10 < 10 < 49 < 13 09/05/17 1366 +/- 197 < 8 < 10 < 28 < 7 09/19/17 1140 +/- 151 < 6 < 6 < 32 < 10 10/03/17 1175 +/- 189 < 7 < 9 < 42 < 8 10/17/17 1214 +/- 199 < 9 < 9 < 33 < 8 10/31/17 1100 +/- 153 < 6 < 7 < 26 < 7 11/14/17 1502 +/- 153 < 6 < 6 < 23 < 6 11/28/17 1154 +/- 161 < 8 < 9 < 26 < 5 12/12/17 1270 +/- 173 < 8 < 10 < 26 < 9 MEAN +/- 2 STD DEV 1216 +/- 215 - - - -

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, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 23F1 01/10/17 1347 +/- 161 < 8 < 10 < 31 < 9 02/07/17 1327 +/- 208 < 8 < 8 < 36 < 9 03/07/17 1200 +/- 175 < 8 < 8 < 36 < 10 04/04/17 1456 +/- 182 < 7 < 8 < 28 < 10 04/18/17 1224 +/- 125 < 8 < 8 < 28 < 8 05/02/17 1268 +/- 171 < 7 < 9 < 29 < 11 05/16/17 1304 +/- 158 < 5 < 6 < 23 < 7 05/30/17 1361 +/- 199 < 6 < 8 < 36 < 11 06/13/17 1206 +/- 198 < 9 < 11 < 35 < 10 06/27/17 1274 +/- 186 < 10 < 10 < 33 < 12 07/11/17 1212 +/- 166 < 7 < 7 < 34 < 9 07/25/17 1391 +/- 212 < 8 < 10 < 31 < 8 08/08/17 1234 +/- 184 < 6 < 7 < 25 < 10 08/22/17 1370 +/- 157 < 7 < 7 < 29 < 11 09/05/17 1209 +/- 177 < 7 < 8 < 22 < 9 09/19/17 1308 +/- 174 < 7 < 8 < 36 < 9 10/03/17 1299 +/- 193 < 7 < 8 < 39 < 9 10/17/17 1202 +/- 174 < 8 < 8 < 33 < 8 10/31/17 1444 +/- 191 < 7 < 8 < 27 < 7 11/14/17 1239 +/- 156 < 5 < 6 < 18 < 8 11/28/17 1266 +/- 154 < 6 < 8 < 25 < 9 12/12/17 1203 +/- 158 < 8 < 10 < 32 < 8 MEAN +/- 2 STD DEV 1288 +/- 159 - - - -

25C1 01/10/17 1328 +/- 185 < 7 < 9 < 29 < 10 02/07/17 1213 +/- 183 < 7 < 8 < 30 < 8 03/07/17 1342 +/- 169 < 10 < 9 < 32 < 6 04/04/17 1211 +/- 142 < 10 < 10 < 30 < 8 04/18/17 1250 +/- 138 < 4 < 5 < 20 < 4 05/02/17 1363 +/- 181 < 7 < 9 < 31 < 9 05/16/17 1283 +/- 158 < 6 < 7 < 28 < 7 05/30/17 1360 +/- 185 < 8 < 10 < 50 < 14 06/13/17 1462 +/- 230 < 8 < 11 < 38 < 9 06/27/17 1430 +/- 215 < 9 < 11 < 35 < 10 07/11/17 1509 +/- 171 < 11 < 11 < 49 < 15 07/25/17 1233 +/- 186 < 10 < 9 < 37 < 11 08/08/17 1173 +/- 199 < 9 < 9 < 31 < 11 08/22/17 1235 +/- 193 < 8 < 9 < 34 < 12 09/05/17 1205 +/- 221 < 9 < 11 < 31 < 12 09/19/17 1162 +/- 203 < 8 < 8 < 42 < 11 10/03/17 1274 +/- 171 < 6 < 8 < 33 < 8 10/17/17 1297 +/- 174 < 9 < 9 < 24 < 9 10/31/17 1282 +/- 155 < 11 < 10 < 36 < 8 11/14/17 1096 +/- 140 < 5 < 6 < 25 < 6 11/28/17 1204 +/- 170 < 6 < 8 < 22 < 7 12/12/17 1332 +/- 196 < 8 < 9 < 29 < 9 MEAN +/- 2 STD DEV 1284 +/- 202 - - - -

36E1 01/10/17 956 +/- 172 < 8 < 9 < 27 < 8 04/04/17 1050 +/- 182 < 8 < 9 < 31 < 9 07/13/17 1101 +/- 194 < 9 < 11 < 47 < 13 10/03/17 1287 +/- 111 < 7 < 8 < 34 < 8 MEAN +/- 2 STD DEV 1098 +/- 279 - - - -

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, 2017 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 I-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 11S3 06/26/17 Cabbage < 278 1898 +/- 596 < 39 < 41 < 48 < 35 < 33 < 40 < 746 < 61 < 162 06/26/17 Collards < 226 4206 +/- 688 < 28 < 26 < 41 < 28 < 27 < 29 < 689 163 +/- 51 < 117 06/26/17 Swiss Chard < 359 6867 +/- 885 < 30 < 31 < 47 < 33 < 24 < 28 < 756 74 +/- 61 < 136 07/20/17 Cabbage < 336 1503 +/- 508 < 41 < 43 < 45 < 55 < 42 < 41 < 999 < 72 < 174 07/20/17 Collards < 319 3590 +/- 532 < 33 < 31 < 41 < 49 < 36 < 37 < 877 < 65 < 141 07/20/17 Swiss Chard < 336 7293 +/- 887 < 28 < 32 < 47 < 38 < 29 < 31 < 683 < 51 < 124 08/24/17 Cabbage < 227 2907 +/- 581 < 28 < 29 < 31 < 42 < 25 < 32 < 709 < 57 < 93 08/24/17 Collards < 333 3287 +/- 527 < 36 < 32 < 36 < 49 < 35 < 37 < 829 < 63 < 122 08/24/17 Swiss Chard 380 +/- 218 4862 +/- 632 < 30 < 30 < 32 < 39 < 31 < 34 < 646 < 47 < 115 09/26/17 Swiss Chard < 269 7356 +/- 718 < 30 < 29 < 42 < 50 < 28 < 31 < 740 < 58 < 114 10/31/17 Swiss Chard 577 +/- 156 7176 +/- 498 < 17 < 18 < 23 < 18 < 17 < 17 < 401 38 +/- 25 < 74 MEAN +/- 2 STD DEV 479 +/- 278 4631 +/- 4442 - - - - - - - 92 +/- 129 -

13S3 06/26/17 Cabbage < 234 5733 +/- 641 < 22 < 23 < 26 < 27 < 23 < 20 1991 +/- 566 101 +/- 39 < 95 06/26/17 Collards < 263 3931 +/- 673 < 24 < 25 < 33 < 25 < 22 < 29 < 645 144 +/- 43 < 128 06/26/17 Swiss Chard < 263 5097 +/- 567 < 21 < 21 < 27 < 23 < 21 < 24 < 665 65 +/- 35 < 85 07/20/17 Cabbage < 294 1219 +/- 574 < 31 < 31 < 36 < 39 < 27 < 37 < 713 < 58 < 145 C-15 07/20/17 Collards < 274 2701 +/- 507 < 29 < 29 < 38 < 34 < 27 < 24 < 691 < 54 < 95 07/20/17 Swiss Chard 328 +/- 248 5224 +/- 685 < 36 < 30 < 31 < 38 < 31 < 36 1213 +/- 806 < 57 < 141 08/24/17 Swiss Chard < 239 4989 +/- 660 < 25 < 34 < 35 < 47 < 31 < 29 1008 +/- 658 < 61 < 124 08/24/17 Wild Grape Leaves 874 +/- 256 4852 +/- 555 < 24 < 18 < 30 < 30 < 22 < 26 1792 +/- 509 < 44 < 87 09/26/17 Swiss Chard < 287 4230 +/- 674 < 33 < 32 < 36 < 56 < 31 < 33 1191 +/- 685 < 53 < 123 10/31/17 Swiss Chard 411 +/- 113 5832 +/- 378 < 14 < 12 < 18 < 16 < 14 < 15 1098 +/- 352 52 +/- 21 < 64 MEAN +/- 2 STD DEV 538 +/- 588 4381 +/- 2890 - - - - - - 1382 +/- 812 90 +/- 83 -

31G1 06/26/17 Broccoli Leaves 491 +/- 228 4291 +/- 606 < 19 < 27 < 32 < 23 < 20 < 28 < 646 148 +/- 59 < 102 06/26/17 Cabbage < 229 2319 +/- 486 < 25 < 23 < 32 < 28 < 28 < 30 < 742 55 +/- 46 < 127 06/26/17 Swiss Chard 583 +/- 221 6607 +/- 787 < 30 < 30 < 39 < 30 < 31 < 34 < 747 108 +/- 52 < 139 07/20/17 Cabbage 502 +/- 215 3981 +/- 629 < 27 < 21 < 33 < 34 < 23 < 23 < 529 < 44 < 116 07/20/17 Kale 472 +/- 306 5091 +/- 600 < 33 < 34 < 40 < 44 < 38 < 35 < 864 < 63 < 140 07/20/17 Swiss Chard 347 +/- 221 4774 +/- 723 < 27 < 26 < 30 < 34 < 26 < 29 < 651 < 50 < 109 08/24/17 Kale 350 +/- 212 5979 +/- 772 < 27 < 29 < 39 < 38 < 22 < 30 < 554 < 49 < 108 08/24/17 Squash Leaves 696 +/- 264 4684 +/- 715 < 39 < 30 < 42 < 41 < 32 < 35 < 618 < 51 < 136 08/24/17 Swiss Chard 219 +/- 180 4256 +/- 558 < 26 < 21 < 30 < 29 < 20 < 24 < 479 < 33 < 98 09/26/17 Red Beet Leaves < 229 4048 +/- 406 < 28 < 26 < 31 < 45 < 30 < 26 < 618 < 47 < 100 09/26/17 Swiss Chard < 221 5012 +/- 416 < 27 < 23 < 29 < 44 < 30 < 28 < 627 < 47 < 98 MEAN +/- 2 STD DEV 458 +/- 299 4640 +/- 2233 - - - - - - - 104 +/- 93 -

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

Table C-IX.1 QUARTERLY DLR RESULTS FOR LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF MILLIROENTGEN/STANDARD MONTH +/- 2 STANDARD DEVIATIONS STATION MEAN CODE +/- 2 S.D. JAN - MAR APR - JUN JUL - SEP OCT - DEC 2E1 5.7 +/- 0.5 5.9 +/- 0.7 5.4 +/- 0.0 5.9 +/- 0.2 5.7 +/- 0.4 3S1 5.5 +/- 0.6 5.7 +/- 0.5 5.2 +/- 0.2 5.8 +/- 0.0 5.4 +/- 0.9 4E1 4.1 +/- 0.4 4.3 +/- 0.0 3.9 +/- 0.3 4.2 +/- 0.7 3.9 +/- 0.8 5H1 7.0 +/- 0.4 7.1 +/- 0.5 6.7 +/- 0.2 7.0 +/- 0.8 7.1 +/- 0.2 5S1 6.3 +/- 0.6 6.4 +/- 0.3 5.9 +/- 0.2 6.6 +/- 0.0 6.2 +/- 1.4 6C1 5.7 +/- 0.7 5.7 +/- 0.5 5.3 +/- 0.2 6.1 +/- 0.6 5.5 +/- 1.4 7E1 5.8 +/- 0.6 6.1 +/- 0.0 5.4 +/- 0.5 5.9 +/- 0.5 5.9 +/- 0.2 7S1 5.7 +/- 0.6 5.8 +/- 0.5 5.2 +/- 1.3 5.9 +/- 0.3 5.8 +/- 0.2 9C1 5.3 +/- 0.2 5.4 +/- 0.1 5.2 +/- 0.3 5.4 +/- 0.8 5.2 +/- 0.4 10E1 5.6 +/- 0.5 5.7 +/- 0.6 5.3 +/- 0.1 5.9 +/- 0.6 5.6 +/- 0.5 10F3 5.5 +/- 0.6 5.5 +/- 0.6 5.1 +/- 0.0 5.8 +/- 0.0 5.4 +/- 0.3 10S3 5.6 +/- 0.7 5.5 +/- 0.2 5.1 +/- 0.0 5.9 +/- 0.3 5.7 +/- 0.7 11S1 6.4 +/- 0.4 6.3 +/- 0.3 6.1 +/- 0.4 6.5 +/- 1.2 6.6 +/- 0.3 13C1 3.9 +/- 0.3 3.9 +/- 0.3 3.7 +/- 0.6 4.1 +/- 0.3 3.8 +/- 0.8 13E1 5.6 +/- 0.4 5.6 +/- 0.0 5.4 +/- 0.2 5.9 +/- 0.5 5.6 +/- 0.1 13S2 8.0 +/- 0.8 7.8 +/- 1.1 7.5 +/- 0.5 8.3 +/- 0.0 8.3 +/- 0.1 14S1 4.8 +/- 0.6 4.7 +/- 0.9 4.5 +/- 0.1 5.2 +/- 0.3 4.9 +/- 0.6 15D1 5.8 +/- 0.4 5.6 +/- 0.5 5.6 +/- 0.1 6.0 +/- 0.7 5.9 +/- 0.4 16F1 5.4 +/- 0.7 5.3 +/- 0.1 5.1 +/- 0.1 5.9 +/- 0.5 5.2 +/- 0.7 17B1 5.3 +/- 0.4 5.2 +/- 0.7 5.0 +/- 0.1 5.3 +/- 0.1 5.5 +/- 0.1 18S2 6.1 +/- 0.3 6.1 +/- 0.3 5.9 +/- 0.2 6.2 +/- 1.0 6.3 +/- 0.4 19D1 5.0 +/- 0.4 4.9 +/- 1.4 4.8 +/- 0.7 5.2 +/- 0.4 5.1 +/- 1.0 20D1 4.9 +/- 0.5 4.9 +/- 0.1 4.5 +/- 0.0 5.1 +/- 0.9 5.0 +/- 0.8 20F1 5.3 +/- 0.8 4.9 +/- 2.0 4.9 +/- 0.1 5.6 +/- 1.2 5.6 +/- 0.9 21S2 5.0 +/- 0.8 4.6 +/- 2.1 4.7 +/- 0.1 5.2 +/- 0.4 5.4 +/- 0.9 23S2 5.1 +/- 0.4 5.1 +/- 0.3 4.8 +/- 0.2 5.3 +/- 0.1 5.2 +/- 0.0 24D1 4.6 +/- 0.4 4.9 +/- 0.9 4.4 +/- 0.5 4.6 +/- 1.1 4.6 +/- 0.1 25D1 4.4 +/- 0.3 4.5 +/- 0.4 4.2 +/- 0.6 4.4 +/- 0.1 4.5 +/- 0.1 25S2 4.6 +/- 0.8 4.8 +/- 0.3 4.0 +/- 0.3 4.9 +/- 0.4 4.7 +/- 0.9 26S3 4.8 +/- 0.6 5.0 +/- 0.2 4.4 +/- 1.0 5.0 +/- 0.1 4.9 +/- 1.0 28D2 5.0 +/- 0.4 4.9 +/- 0.2 4.7 +/- 0.4 5.1 +/- 0.8 5.1 +/- 1.6 29E1 5.1 +/- 0.7 4.8 +/- 1.7 4.7 +/- 0.1 5.2 +/- 0.5 5.5 +/- 0.9 29S1 4.9 +/- 0.5 4.9 +/- 0.6 4.5 +/- 0.1 5.1 +/- 0.3 4.9 +/- 0.5 31D1 6.8 +/- 0.6 6.9 +/- 0.7 6.4 +/- 0.6 6.7 +/- 1.2 7.1 +/- 1.7 31D2 5.7 +/- 0.7 6.0 +/- 0.0 5.4 +/- 1.2 6.0 +/- 0.5 5.4 +/- 1.0 31S1 5.8 +/- 0.6 6.0 +/- 0.1 5.4 +/- 0.2 6.0 +/- 1.0 5.6 +/- 0.9 34E1 5.4 +/- 0.3 5.5 +/- 0.3 5.2 +/- 0.1 5.5 +/- 0.7 5.3 +/- 0.3 34S2 5.4 +/- 0.4 5.6 +/- 0.5 5.2 +/- 0.4 5.4 +/- 0.5 5.2 +/- 0.1 36D1 4.9 +/- 0.5 5.1 +/- 0.4 4.6 +/- 0.6 5.0 +/- 0.2 4.7 +/- 0.1 36S2 5.7 +/- 0.7 6.1 +/- 1.0 5.4 +/- 0.5 (1) 5.7 +/- 0.2 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16

Table C-IX.2 MEAN QUARTERLY DLR RESULTS FOR THE SITE BOUNDARY, MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF MILLIROENTGEN/STANDARD MONTH

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

JAN-MAR 5.7 +/- 1.6 5.2 +/- 1.3 7.1 +/- 0 APR-JUN 5.2 +/- 1.7 4.9 +/- 1.2 6.7 +/- 0 JUL-SEP 5.8 +/- 1.7 5.4 +/- 1.4 7.0 +/- 0 OCT-DEC 5.7 +/- 1.8 5.2 +/- 1.4 7.1 +/- 0 Table C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF MILLIROENTGEN/STANDARD MONTH

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

SITE BOUNDARY 126 4 8.3 5.6 +/- 1.7 MIDDLE 184 3.7 7.1 5.2 +/- 1.3 CONTROL 8 6.7 7.1 7.0 +/- 0.4 SITE BOUNDARY STATIONS - 10S3, 11S1, 13S2, 14S1, 18S2, 21S2, 23S2, 25S2, 26S3, 29S1, 31S1, 34S2, 36S2, 3S1, 5S1, 7S1 MIDDLE STATIONS - 10E1, 10F3, 13C1, 13E1, 15D1, 16F1, 17B1, 19D1, 20D1, 20F1, 24D1, 25D1 28D2, 29E1, 2E1, 31D1, 31D2, 34E1, 36D1, 4E1, 6C1, 7E1, 9C1 CONTROL STATIONS - 5H1 C-17

FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2017 12 10 8

6 pCi/liter C-18 4

2 0

82 86 90 94 98 02 06 10 14 18 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 - 2017 150 Group I 135 Group II Group III 120 Chernobyl 105 90 C-19 75 LGS CRITICALITY 60 UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/11/89 E-3 pCi/cubic meter 45 30 15 0

82 88 94 00 06 12 18 YEAR

FIGURE C-3 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2017 50 GROUP I GROUP II GROUP III 40 30 C-20 E-3 pCi/cubic meter 20 10 0

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

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

IN THE VICINITY OF LGS, 1985 - 2017 NOTE: Control Station 5H1 became the only distant location beginning in 1995 13 SITE 12 INTERMEDIATE CONTROL 11 Control 5H1 10 9

C-21 8

7 milli-Roentgen/std. mo.

6 5

4 85 89 93 97 01 05 09 13 17 YEAR

Intentionally left blank APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

Intentionally left blank TABLE D-I.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 12/27/16 - 01/30/17 2.6 +/- 0.8 01/30/17 - 02/28/17 0.9 +/- 0.5 02/28/17 - 03/28/17 2.1 +/- 0.7 03/28/17 - 05/01/17 1.4 +/- 0.6 05/01/17 - 05/31/17 1.0 +/- 0.5 05/31/17 - 06/26/17 1.9 +/- 1.0 06/26/17 - 08/01/17 1.0 +/- 0.5 08/01/17 - 08/29/17 1.3 +/- 0.6 08/29/17 - 10/03/17 0.5 +/- 0.5 10/03/17 - 10/31/17 1.6 +/- 0.6 10/31/17 - 11/28/17 1.3 +/- 0.6 11/28/17 - 01/02/18 1.6 +/- 0.6 MEAN +/- 2 STD DEV 1.4 +/- 1.2 TABLE D-I.2 CONCENTRATIONS OF I-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 12/27/16 - 01/30/17 < 0.2 01/30/17 - 02/28/17 < 0.3 02/28/17 - 03/28/17 < 0.4 03/28/17 - 05/01/17 < 0.3 05/01/17 - 05/31/17 < 0.3 05/31/17 - 06/26/17 < 0.2 06/26/17 - 08/01/17 < 0.4 08/01/17 - 08/29/17 < 0.1 08/29/17 - 10/03/17 < 0.2 10/03/17 - 10/31/17 < 0.2 10/31/17 - 11/28/17 < 0.2 11/28/17 - 01/02/18 < 0.3 MEAN -

TABLE D-I.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 12/27/16 - 03/28/17 < 150 03/28/17 - 06/26/17 < 148 06/26/17 - 10/03/17 < 144 10/03/17 - 01/02/18 < 158 MEAN -

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

TABLE D-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 16C2 12/27/16 - 01/30/17 < 2 < 2 < 5 < 3 < 4 < 3 < 3 < 3 < 3 < 3 < 11 < 2 01/30/17 - 02/28/17 < 3 < 2 < 4 < 1 < 3 < 5 < 2 < 6 < 2 < 3 < 12 < 2 02/28/17 - 03/28/17 < 1 < 2 < 3 < 3 < 4 < 3 < 3 < 4 < 2 < 2 < 13 < 2 03/28/17 - 05/01/17 < 2 < 3 < 5 < 3 < 6 < 4 < 3 < 11 < 3 < 2 < 22 < 5 05/01/17 - 05/31/17 < 3 < 2 < 4 < 2 < 4 < 3 < 4 < 4 < 3 < 3 < 11 < 2 05/31/17 - 06/26/17 < 3 < 2 < 3 < 2 < 5 < 3 < 3 < 6 < 2 < 2 < 12 < 5 06/26/17 - 08/01/17 < 2 < 3 < 3 < 1 < 4 < 2 < 2 < 11 < 2 < 3 < 23 < 3 08/01/17 - 08/29/17 < 2 < 2 < 3 < 2 < 3 < 5 < 2 < 6 < 2 < 2 < 14 < 2 08/29/17 - 10/03/17 < 3 < 2 < 4 < 3 < 5 < 4 < 3 < 5 < 2 < 2 < 14 < 3 10/03/17 - 10/31/17 < 2 < 4 < 4 < 2 < 5 < 4 < 3 < 7 < 4 < 2 < 10 < 2 10/31/17 - 11/28/17 < 3 < 3 < 4 < 2 < 6 < 5 < 3 < 3 < 2 < 3 < 9 < 2 11/28/17 - 01/02/18 < 1 < 3 < 3 < 3 < 5 < 5 < 4 < 4 < 2 < 2 < 14 < 3 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, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION 11S2 11S2 PERIOD GROSS BETA I-131 01/03/17 - 01/09/17 18 +/- 5 < 15 01/09/17 - 01/17/17 23 +/- 4 < 14 01/17/17 - 01/24/17 (1) (1) 01/24/17 - 01/30/17 26 +/- 7 < 10 01/30/17 - 02/06/17 25 +/- 5 < 19 02/06/17 - 02/13/17 26 +/- 5 < 14 02/13/17 - 02/21/17 27 +/- 4 < 13 02/21/17 - 02/27/17 23 +/- 5 < 17 02/27/17 - 03/06/17 27 +/- 5 < 20 03/06/17 - 03/13/17 20 +/- 4 < 10 03/13/17 - 03/20/17 24 +/- 5 < 10 03/20/17 - 03/27/17 25 +/- 5 < 14 03/27/17 - 04/03/17 10 +/- 4 < 14 04/03/17 - 04/10/17 14 +/- 4 < 16 04/10/17 - 04/17/17 22 +/- 5 < 11 04/17/17 - 04/24/17 10 +/- 4 < 20 04/24/17 - 05/02/17 10 +/- 4 < 18 05/02/17 - 05/08/17 13 +/- 4 < 14 05/08/17 - 05/15/17 8 +/- 4 < 19 05/15/17 - 05/22/17 22 +/- 5 < 13 05/22/17 - 05/30/17 9 +/- 4 < 17 05/30/17 - 06/05/17 20 +/- 5 < 14 06/05/17 - 06/12/17 25 +/- 4 < 21 06/12/17 - 06/19/17 25 +/- 5 < 18 06/19/17 - 06/27/17 26 +/- 4 < 14 06/27/17 - 07/03/17 25 +/- 5 < 26 07/03/17 - 07/11/17 22 +/- 4 < 14 07/11/17 - 07/17/17 25 +/- 5 < 21 07/17/17 - 07/24/17 31 +/- 5 < 23 07/24/17 - 07/31/17 16 +/- 4 < 16 07/31/17 - 08/08/17 23 +/- 4 < 11 08/08/17 - 08/14/17 38 +/- 7 < 19 08/14/17 - 08/22/17 33 +/- 5 < 22 08/22/17 - 08/28/17 26 +/- 5 < 21 08/28/17 - 09/05/17 21 +/- 4 < 8 09/05/17 - 09/11/17 21 +/- 5 < 21 09/11/17 - 09/19/17 31 +/- 4 < 9 09/19/17 - 09/25/17 36 +/- 6 < 11 09/25/17 - 10/02/17 19 +/- 4 < 16 10/02/17 - 10/10/17 22 +/- 4 < 18 10/10/17 - 10/16/17 21 +/- 5 < 15 10/16/17 - 10/23/17 32 +/- 5 < 21 10/23/17 - 10/30/17 24 +/- 4 < 14 10/30/17 - 11/06/17 21 +/- 5 < 10 11/06/17 - 11/13/17 21 +/- 5 < 14 11/13/17 - 11/20/17 22 +/- 5 < 17 11/20/17 - 11/27/17 34 +/- 5 < 21 11/27/17 - 12/04/17 35 +/- 5 < 11 12/04/17 - 12/11/17 41 +/- 5 < 16 12/11/17 - 12/18/17 18 +/- 4 < 13 12/18/17 - 12/26/17 31 +/- 4 < 14 12/26/17 - 01/02/18 30 +/- 5 < 25 MEAN +/- 2 STD DEV 23 +/- 15 -

(1) Invalid sample due to pump malfunction 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, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 11S2 01/03/17 - 04/03/17 94 +/- 18 < 1.1 < 1.0 < 0.8 < 1.2 < 1.1 04/03/17 - 07/03/17 87 +/- 17 < 1.0 < 1.0 < 1.2 < 0.4 < 0.6 07/03/17 - 10/02/17 87 +/- 18 < 0.9 < 1.2 < 0.9 < 0.8 < 0.5 10/02/17 - 01/02/18 79 +/- 16 < 0.7 < 0.4 < 0.7 < 1.1 < 0.5 MEAN +/- 2 STD DEV 87 +/- 12 - - - - -

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, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD I-131 K-40 Cs-134 Cs-137 Ba-140 La-140 19B1 01/10/17 < 0.3 1392 +/- 117 < 3 < 4 < 24 < 4 04/04/17 < 0.3 1310 +/- 100 < 2 < 3 < 29 < 3 07/11/17 < 0.3 1415 +/- 104 < 3 < 3 < 27 < 5 10/03/17 < 0.4 1395 +/- 93 < 3 < 3 < 30 < 4 MEAN +/- 2 STD DEV - 1378 +/- 93 - - - -

25C1 01/10/17 < 0.3 1445 +/- 112 < 2 < 3 < 20 < 7 04/04/17 < 0.3 1284 +/- 119 < 4 < 4 < 25 < 7 07/11/17 < 0.3 1435 +/- 95 < 3 < 2 < 26 < 3 10/03/17 < 0.4 1456 +/- 103 < 3 < 3 < 38 < 9 MEAN +/- 2 STD DEV - 1405 +/- 162 - - - -

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, 2017 10.0 9.0 ENV 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, 2017 60 11S2 - ENV 50 11S1 - TBE 40 D-7 30 E-3 pCi/cubic meter 20 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 TABLE E.1 Analytics Environmental Radioactivity Cross Check Program 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 2017 E11811 Milk Sr-89 pCi/L 87 97.7 0.89 A Sr-90 pCi/L 12.4 16.2 0.77 A E11812 Milk Ce-141 pCi/L 135 145 0.93 A Co-58 pCi/L 153 150 1.02 A Co-60 pCi/L 182 183 1.00 A Cr-51 pCi/L 258 290 0.89 A Cs-134 pCi/L 104 120 0.87 A Cs-137 pCi/L 142 140 1.02 A Fe-59 pCi/L 135 129 1.05 A I-131 pCi/L 92.6 97.9 0.95 A Mn-54 pCi/L 173 164 1.05 A Zn-65 pCi/L 208 199 1.04 A E11813 Charcoal I-131 pCi 92 93.9 0.98 A E11814 AP Ce-141 pCi 99.9 101 0.99 A Co-58 pCi 95.4 104 0.92 A Co-60 pCi 140 127 1.10 A Cr-51 pCi 211 201 1.05 A Cs-134 pCi 82.1 83.2 0.99 A Cs-137 pCi 92.8 97.0 0.96 A Fe-59 pCi 107 89.3 1.20 A Mn-54 pCi 106 114 0.93 A Zn-65 pCi 137 138 0.99 A E11816 Soil Ce-141 pCi/g 0.258 0.250 1.03 A Co-58 pCi/g 0.241 0.258 0.93 A Co-60 pCi/g 0.312 0.315 0.99 A Cr-51 pCi/g 0.439 0.500 0.88 A Cs-134 pCi/g 0.176 0.207 0.85 A Cs-137 pCi/g 0.304 0.317 0.96 A Fe-59 pCi/g 0.210 0.222 0.95 A Mn-54 pCi/g 0.292 0.283 1.03 A Zn-65 pCi/g 0.353 0.344 1.03 A E11815 Water Fe-55 pCi/L 1600 1890 0.85 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (Page 1 of 4)

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

Number Value (a) Analytics Result Value June 2017 E11844 Milk Sr-89 pCi/L 81.3 92.6 0.88 A Sr-90 pCi/L 12.1 13.5 0.90 A E11846 Milk Ce-141 pCi/L 142 151 0.94 A Co-58 pCi/L 147 155 0.95 A Co-60 pCi/L 185 191 0.97 A Cr-51 pCi/L 321 315 1.02 A Cs-134 pCi/L 168 188 0.89 A Cs-137 pCi/L 148 150 0.99 A Fe-59 pCi/L 116 115 1.01 A I-131 pCi/L 102 93.6 1.09 A Mn-54 pCi/L 168 172 0.98 A Zn-65 pCi/L 195 204 0.96 A E11847 Charcoal I-131 pCi 87.9 84.8 1.04 A E11845 AP Sr-89 pCi 70.8 79.1 0.90 A Sr-90 pCi 9.10 11.5 0.79 W E11848 AP Ce-141 pCi 112 116 0.96 A Co-58 pCi 119 119 1.00 A Co-60 pCi 171 146 1.17 A Cr-51 pCi 270 241 1.12 A Cs-134 pCi 152 144 1.05 A Cs-137 pCi 114 115 0.99 A Fe-59 pCi 94.1 88.3 1.07 A Mn-54 pCi 139 132 1.06 A Zn-65 pCi 141 156 0.90 A E11849 Water Fe-55 pCi/L 1840 1890 0.97 A July 2017 E11901 AP GR-A pCi 50.1 44.2 1.13 A GR-B pCi 218 233 0.93 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (Page 2 of 4)

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TABLE E.1 Analytics Environmental Radioactivity Cross Check Program 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 2017 E11914 Milk Sr-89 pCi/L 84.3 82.7 1.02 A Sr-90 pCi/L 12.6 12.1 1.04 A E11915 Milk Ce-141 pCi/L 93.9 87.0 1.08 A Co-58 pCi/L 115 117 0.98 A Co-60 pCi/L 265 262 1.01 A Cr-51 pCi/L 273 217 1.26 W Cs-134 pCi/L 186 201 0.93 A Cs-137 pCi/L 175 172 1.02 A Fe-59 pCi/L 137 125 1.09 A I-131 pCi/L 78.0 71.0 1.10 A Mn-54 pCi/L 128 123 1.04 A Zn-65 pCi/L 206 184 1.12 A E11916 Charcoal I-131 pCi 71.9 64.4 1.12 A E11917 AP Ce-141 pCi 80.1 86.3 0.93 A Co-58 pCi 110 116 0.95 A Co-60 pCi 277 260 1.07 A Cr-51 pCi 275 215 1.28 W Cs-134 pCi 192 199 0.96 A Cs-137 pCi 165 170 0.97 A Fe-59 pCi 122 124 0.98 A Mn-54 pCi 120 122 0.99 A Zn-65 pCi 175 183 0.96 A E11918 Water Fe-55 pCi/L 1630 1630 1.00 A E11919 Soil Ce-141 pCi/g 0.136 0.142 0.96 A Co-58 pCi/g 0.179 0.191 0.94 A Co-60 pCi/g 0.405 0.429 0.94 A Cr-51 pCi/g 0.230 0.355 0.65 N (1)

Cs-134 pCi/g 0.272 0.328 0.83 A Cs-137 pCi/g 0.336 0.356 0.94 A Fe-59 pCi/g 0.210 0.205 1.02 A Mn-54 pCi/g 0.210 0.201 1.05 A Zn-65 pCi/g 0.301 0.301 1.00 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard 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 17-16 (Page 3 of 4)

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

Number Value (a) Analytics Result Value December 2017 E12054 Milk Sr-89 pCi/L 92.1 92.3 1.00 A Sr-90 pCi/L 18.3 16.9 1.09 A E12055 Milk Ce-141 pCi/L 97.8 98.3 0.99 A Co-58 pCi/L 92.3 89.9 1.03 A Co-60 pCi/L 176 173 1.02 A Cr-51 pCi/L 226 242 0.93 A Cs-134 pCi/L 118 125 0.95 A Cs-137 pCi/L 148 141 1.05 A Fe-59 pCi/L 123 113 1.08 A I-131 pCi/L 66.0 57.8 1.14 A Mn-54 pCi/L 173 161 1.08 A Zn-65 pCi/L 233 211 1.10 A E12056 Charcoal I-131 pCi 48.1 47.5 1.01 A E12057A AP Ce-141 pCi 108 111 0.97 A Co-58 pCi 89.5 102 0.88 A Co-60 pCi 223 196 1.14 A Cr-51 pCi 311 274 1.13 A Cs-134 pCi 141 142 1.00 A Cs-137 pCi 162 160 1.01 A Fe-59 pCi 121 129 0.94 A Mn-54 pCi 177 182 0.97 A Zn-65 pCi 203 239 0.85 A E12058 Water Fe-55 pCi/L 1970 1740 1.13 A E12059 AP Sr-89 pCi 71.2 87.4 0.81 A Sr-90 pCi 12.9 16.0 0.81 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (Page 4 of 4)

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TABLE E.2 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

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

Number Value (a) Range Value February 2017 17-MaS36 Soil Ni-63 Bq/kg -5.512 (1) A Sr-90 Bq/kg 571 624 437 - 811 A 17-MaW36 Water Am-241 Bq/L 0.693 0.846 0.592 - 1.100 A Ni-63 Bq/L 13.4 12.2 8.5 - 15.9 A Pu-238 Bq/L 0.7217 0.703 0.492 - 0.914 A Pu-239/240 Bq/L 0.9277 0.934 0.654 - 1.214 A 17-RdF36 AP U-234/233 Bq/sample 0.0911 0.104 0.073 - 0.135 A U-238 Bq/sample 0.0967 0.107 0.075 - 0.139 A 17-RdV36 Vegetation Cs-134 Bq/sample 6.44 6.95 4.87 - 9.04 A Cs-137 Bq/sample 4.61 4.60 3.22 - 5.98 A Co-57 Bq/sample -0.0229 (1) A Co-60 Bq/sample 8.52 8.75 6.13 - 11.38 A Mn-54 Bq/sample 3.30 3.28 2.30 - 4.26 A Sr-90 Bq/sample 1.30 1.75 1.23 - 2.28 W Zn-65 Bq/sample 5.45 5.39 3.77 - 7.01 A August 2017 17-MaS37 Soil Ni-63 Bq/kg 1130 1220 854 - 1586 A Sr-90 Bq/kg 296 289 202 - 376 A 17-MaW37 Water Am-241 Bq/L 0.838 0.892 0.624 - 1.160 A Ni-63 Bq/L -0.096 (1) A Pu-238 Bq/L 0.572 0.603 0.422 - 0.784 A Pu-239/240 Bq/L 0.863 0.781 0.547 - 1.015 A 17-RdF37 AP U-234/233 Bq/sample 0.103 0.084 0.059 - 0.109 W U-238 Bq/sample 0.115 0.087 0.061 - 0.113 N (2) 17-RdV37 Vegetation Cs-134 Bq/sample 2.34 2.32 1.62 - 3.02 A Cs-137 Bq/sample 0.05 (1) A Co-57 Bq/sample 3.32 2.8 2.0 - 3.6 A Co-60 Bq/sample 2.09 2.07 1.45 - 2.69 A Mn-54 Bq/sample 2.90 2.62 1.83 - 3.41 A Sr-90 Bq/sample 1.17 1.23 0.86 - 1.60 A Zn-65 Bq/sample 6.07 5.37 3.76 - 6.98 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric 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) See NCR 17-15 (Page 1 of 1)

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

Number Value (a) Limits Value March 2017 MRAD-26 AP GR-A pCi/sample 76.3 85.5 28.6 - 133 A April 2017 RAD-109 Water Ba-133 pCi/L 49.2 49.7 40.8 - 55.1 A Cs-134 pCi/L 83.2 90.1 74.0 - 99.1 A Cs-137 pCi/L 202 206 185 - 228 A Co-60 pCi/L 51.2 54.7 49.2 - 62.7 A (1)

Zn-65 pCi/L 39.3 53.8 47.2 - 65.9 N GR-A pCi/L 53.6 75.0 39.5 - 92.3 A GR-B pCi/L 42.7 38.5 25.5 - 46.0 A U-Nat pCi/L 50.1 55.6 45.2 - 61.7 A H-3 pCi/L 7080 6850 5920 - 7540 A Sr-89 pCi/L 40.7 66.2 53.8 - 74.3 N (1)

Sr-90 pCi/L 26.9 26.7 19.3 - 31.1 A I-131 pCi/L 26.7 29.9 24.9 - 34.9 A September 2017 MRAD-27 AP GR-A pCi/sample 40.9 50.1 16.8 - 77.8 A AP GR-B pCi/sample 58.0 61.8 39.1 - 90.1 A October 2017 RAD-111 Water Ba-133 pCi/L 71.3 73.7 61.7 - 81.1 A Cs-134 pCi/L 43.0 53.0 42.8 - 58.3 A Cs-137 pCi/L 48.2 52.9 47.6 - 61.1 A Co-60 pCi/L 69.0 69.5 62.6 - 78.9 A Zn-65 pCi/L 335 348 313 - 406 A GR-A pCi/L 32.5 35.6 18.3 - 45.8 A GR-B pCi/L 24.3 25.6 16.0 - 33.6 A U-Nat pCi/L 36.6 37.0 30.0 - 40.9 A H-3 pCi/L 6270 6250 5390 - 6880 A I-131 pCi/L 26.4 24.2 20.1 - 28.7 A November 2017 111317O Water Sr-89 pCi/L 57.1 50.0 39.4 - 57.5 A Sr-90 pCi/L 27.1 41.8 30.8 - 48.0 N (2)

(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 17-09 (2) See NCR 17-19 (Page 1 of 1)

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TABLE E.4 Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)a MRAD Study Environmental, Inc., Midwest Laboratory Concentration b Laboratory Lab Code b Date Analysis ERA Result Control Limits c Acceptance Result ERAP-1112 3/20/2017 Am-241 55.3 +/- 2.8 76.4 47.1 - 103.0 Pass ERAP-1112 3/20/2017 Co-60 1,230 +/- 8 1030 797 - 1290 Pass ERAP-1112 3/20/2017 Cs-134 1,110 +/- 9 1100.0 700 - 1360 Pass ERAP-1112 3/20/2017 Cs-137 1,810 +/- 12 1390 1,040 - 1,830 Pass ERAP-1112 d 3/20/2017 Fe-55 590 +/- 385 256 79.4 - 500 Fail ERAP-1112 3/20/2017 Mn-54 < 5.14 < 50.0 0.00 - 50.0 Pass ERAP-1112 3/20/2017 Pu-238 54.6 +/- 2.8 54.3 37.2 - 71.4 Pass ERAP-1112 3/20/2017 Pu-239/240 63.6 +/- 3.0 62.0 44.9 - 81.0 Pass ERAP-1112 3/20/2017 Sr-90 55.3 +/- 8.3 52.4 25.6 - 78.5 Pass ERAP-1112 3/20/2017 U-233/234 65.7 +/- 3.0 73.1 45.3 - 110 Pass ERAP-1112 3/20/2017 U-238 67.3 +/- 3.0 72.4 46.8 - 100 Pass ERAP-1112 3/20/2017 Zn-65 1,355 +/- 16 984.0 705 - 1,360 Pass ERAP-1114 3/20/2017 Gr. Alpha 106 +/- 5 85.5 28.6 - 133 Pass ERAP-1114 e 3/20/2017 Gr. Beta 67.6 +/- 3.0 45.2 28.6 - 65.9 Fail ERSO-1116 3/20/2017 Am-241 418 +/- 98 448 262 - 582 Pass ERSO-1116 3/20/2017 Ac-228 1,540 +/- 260 1240 795 - 1,720 Pass ERSO-1116 3/20/2017 Bi-212 1,550 +/- 90 1240.0 330 - 1,820 Pass ERSO-1116 3/20/2017 Bi-214 2,560 +/- 20 2750 1,660 - 3,960 Pass ERSO-1116 3/20/2017 Co-60 4,620 +/- 100 4430.0 3,000 - 6,100 Pass ERSO-1116 3/20/2017 Cs-134 8,340 +/- 100 8860.0 5,790 - 10,600 Pass ERSO-1116 3/20/2017 Cs-137 8,420 +/- 100 7500.0 5,750 - 9,650 Pass ERSO-1116 3/20/2017 K-40 13,600 +/- 900 10600.0 7,740 - 14,200 Pass ERSO-1116 3/20/2017 Mn-54 < 68.1 < 1000 0.00 - 1,000 Pass ERSO-1116 3/20/2017 Pb-212 1,060 +/- 70 1240.0 812 - 1,730 Pass ERSO-1116 3/20/2017 Pb-214 2,620 +/- 160 2890.0 1,690 - 4,310 Pass ERSO-1116 3/20/2017 Pu-238 424 +/- 154 648.0 390 - 894 Pass ERSO-1116 f 3/20/2017 Pu-239/240 252 +/- 112 484 316 - 669 Fail ERSO-1116 g 3/20/2017 Pu-239/240 436 +/- 106 484 316 - 669 Pass ERSO-1116 3/20/2017 Sr-90 7,930 +/- 250 9150 3,490 - 14,500 Pass ERSO-1116 3/20/2017 Th-234 1,820 +/- 200 1940 614 - 3,650 Pass a

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assurance Program (EIML) b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/,

except for air filters (pCi/Filter), vegetation and soil (pCi/kg.

c Results are presented as the known values, expected laboratory precision (2 sigma, 1 determination) and control limits as provided by ERA d

Fe-55 analysis result was outside the acceptable range. Recounting the sample disk for 1000 minutes resulted in 254 +/- 364 with an LLD calculation of < 342. Insufficient sample was available after performing other required analyses on the sample to quantify the activity with a uncertainty less than the activity.

e ERA appears to have applied the standard material to the filter in a pattern closer to the center of the filter compared to previous studies an different from the filter efficiency utilized by the laboratory. This likely caused the efficency used the calculation to be understated and the result obtained by the laboratory to be overstated. For comparison, the AP gross beta in-house spike had a ratio of 0.94 of lab result to kno f

Analysis result for Plutonium-239/240 was below the lower limit of acceptance.

g Samples were reanalyzed in duplicate with acceptable results for each. Original analysis had poor resolution possibly due to a poor elctroplating and is suspected in contributing to poor results.

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TABLE E.4 Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)a MRAD Study Environmental, Inc., Midwest Laboratory Concentration b Laboratory Lab Code b Date Analysis ERA Result Control Limits c Acceptance Result ERSO-1116 h 3/20/2017 U-233/234 1,030 +/- 130 1950 1,190 - 2,500 Fail ERSO-1116 i 3/20/2017 U-233/234 1,820 +/- 200 1950 1,190 - 2,500 Pass ERSO-1116 3/20/2017 U-238 1,240 +/- 140 1940 1,200 - 2,460 Pass ERSO-1116 i 3/20/2017 U-238 1,930 +/- 200 1940 1,200 - 2,460 Pass ERSO-1116 3/20/2017 Zn-65 7,190 +/- 240 6090 4,850 - 8,090 Pass ERW-1122 3/20/2017 Gr. Alpha 65.3 +/- 2.4 89.5 31.8 - 139 Pass ERW-1122 3/20/2017 Gr. Beta 54.8 +/- 1.5 61 34.9 - 90.4 Pass ERW-1124 3/20/2017 H-3 19,000 +/- 410 19400 13,000 - 27,700 Pass ERVE-1118 42814 Am-241 1,560 +/- 140 1860 1,140 - 2,470 Pass ERVE-1118 42814 Cm-244 530 +/- 80 734 360 - 1,140 Pass ERVE-1118 42814 Co-60 1,400 +/- 350 1390 959 - 1,940 Pass ERVE-1118 42814 Cs-134 1,650 +/- 460 1830 1,180 - 2,380 Pass ERVE-1118 42814 Cs-137 2,580 +/- 540 2500 1,810 - 3,480 Pass ERVE-1118 42814 K-40 32,100 +/- 700 30900 22,300 - 43,400 Pass ERVE-1118 42814 Mn-54 < 27.3 < 300 0.00 - 300 Pass ERVE-1118 42814 Zn-65 889 +/- 64 853 615 - 1,200 Pass ERVE-1118 42814 Pu-238 3,250 +/- 210 3250 1,940 - 4,450 Pass ERVE-1118 42814 Pu-239/240 2,180 +/- 170 2150 1,320 - 2,960 Pass ERVE-1118 42814 Sr-90 665 +/- 135 726 414 - 963 Pass ERVE-1118 42814 U-233/234 2,840 +/- 200 3090 2,030 - 3,970 Pass ERVE-1118 42814 U-238 2,990 +/- 200 3060 2,040 - 3,890 Pass ERW-1120 42814 Am-241 108 +/- 7 140 94.3 - 188 Pass ERW-1120 42814 Co-60 2,600 +/- 198 2540 2,210 - 2,970 Pass ERW-1120 42814 Cs-134 2,380 +/- 250 2510 1,840 - 2880 Pass ERW-1120 42814 Cs-137 1,470 +/- 243 1400 1,190 - 1,680 Pass ERW-1120 42814 Mn-54 < 12.3 < 100 0.00 - 100 Pass ERW-1120 42814 Pu-238 117 +/- 4 128 94.7 - 159 Pass ERW-1120 42814 Pu-239/240 74.8 +/- 3.3 85.8 66.6 - 108 Pass ERW-1120 42814 U-233/234 75.3 +/- 3.2 90.3 67.8 - 116 Pass ERW-1120 42814 U-238 76.4 +/- 3.2 89.5 68.2 - 110 Pass ERW-1120 42814 Zn-65 2,130 +/- 378 1960 1630 - 2,470 Pass ERW-1120 j 42814 Fe-55 1,400 +/- 403 984 587 - 1,340 Fail ERW-1120 k 42814 Fe-55 1,081 +/- 383 984 587 - 1,340 Pass ERW-1120 42814 Sr-90 652 +/- 12 714 465 - 944 Pass a

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assurance Program (EIML) b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/,

except for air filters (pCi/Filter), vegetation and soil (pCi/kg).

c Results are presented as the known values, expected laboratory precision (2 sigma, 1 determination) and control limits as provided by ERA h

Analysis result for Uranium-233/234 was below the lower limit of acceptance i Samples were reanalyzed in duplicate with acceptable results for each. Original analysis had poor resolution possibly due to a poor elctroplating and is suspected in contributing to poor results.

j Iron -55 analysis result was outside acceptable range i Result of recounting was acceptable. Using available aliquot after dividing sample for other analyses leaves insufficient sample to reliably determine the activity present in sample.

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TABLE E.5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., Midwest Laboratory Concentration a Reference Laboratory Known Lab Code b Analysis Control Limits c Acceptance Date Result Activity MASO-903 2/1/2017 Am-241 60.9 +/- 6.9 67 46.9 - 87.1 Pass MASO-903 2/1/2017 Cs-134 1360 +/- 14 1550 1085 - 2015 Pass MASO-903 2/1/2017 Cs-137 678 +/- 13 611 428 - 794 Pass MASO-903 2/1/2017 Co-57 1.63 +/- 1.69 0.000 NA c Pass MASO-903 2/1/2017 Co-60 909 +/- 12 891.0 624 - 1158 Pass MASO-903 2/1/2017 Mn-54 1052 +/- 17 967.0000 677 - 1257 Pass MASO-903 2/1/2017 K-40 657 +/- 68 607.0000 425 - 789 Pass MASO-903 2/1/2017 Zn-65 -0.52 +/- 7.40 0.0 NA c Pass MASO-903 2/1/2017 Ni-63 3.25 +/- 7.17 0.0000 NA c Pass MASO-903 2/1/2017 Pu-238 0.46 +/- 0.69 0.4100 NA e Pass MASO-903 2/1/2017 Pu-239/240 56.8 +/- 5.9 59.8 41.9 - 77.7 Pass MASO-903 2/1/2017 Sr-90 501 +/- 17 624.00 437 - 811 Pass MASO-903 2/1/2017 Tc-99 748 +/- 16 656.00 459 - 853 Pass MAW-849 2/1/2017 I-129 -0.05 +/- 0.12 0.0000 NA c Pass MAVE-905 2/1/2017 Cs-134 6.61 +/- 0.16 6.95 4.87 - 9.04 Pass MAVE-905 2/1/2017 Cs-137 4.97 +/- 0.18 4.60 3.22 - 5.98 Pass MAVE-905 2/1/2017 Co-57 -0.01 +/- 0.03 0.00 NA c Pass MAVE-905 2/1/2017 Co-60 9.51 +/- 0.17 8.75 6.13 - 11.38 Pass MAVE-905 2/1/2017 Mn-54 3.67 +/- 0.17 3.28 2.30 - 4.26 Pass MAVE-905 2/1/2017 Zn-65 6.12 +/- 0.44 5.39 3.77 - 7.01 Pass MAW-847 2/1/2017 Am-241 0.679 +/- 0.079 0.846 0.592 - 1.100 Pass MAW-847 2/1/2017 Cs-134 0.03 +/- 0.10 0 NA c Pass MAW-847 2/1/2017 Cs-137 12.7 +/- 0.4 11.100 7.8 - 14.4 Pass MAW-847 d 2/1/2017 Co-57 2.7 +/- 0.3 28.500 20.0 - 37.1 Fail MAW-847 2/1/2017 Co-60 13.5 +/- 0.3 12.300 8.6 - 16.0 Pass MAW-847 2/1/2017 Mn-54 16.5 +/- 0.4 14.900 10.4 - 19.4 Pass MAW-847 2/1/2017 K-40 287 +/- 6 254.0 178 - 330 Pass MAW-847 2/1/2017 Zn-65 -0.15 +/- 0.23 0.000 NA c Pass MAW-847 2/1/2017 H-3 275 +/- 10 249.000 174 - 324 Pass MAW-847 2/1/2017 Fe-55 2.4 +/- 13.6 1.7 NA e Pass MAW-847 2/1/2017 Ni-63 10.1 +/- 2.8 12.20 8.5 - 15.9 Pass MAW-847 2/1/2017 Pu-238 0.729 +/- 0.097 0.70 0.492 - 0.914 Pass MAW-847 2/1/2017 Pu-239/240 0.866 +/- 0.102 0.934 0.654 - 1.214 Pass MAW-847 2/1/2017 Ra-226 0.506 +/- 0.053 0.504 0.353 - 0.655 Pass MAW-847 2/1/2017 Sr-90 10.0 +/- 0.8 10.10 7.1 - 13.1 Pass a

Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation) c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing serie as a "false positive". MAPEP does not provide control limits.

d Decimal point was misplaced while performing a unit conversion. The result is within control limits when the proper un conversion is performed.

e Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.

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TABLE E.5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., Midwest Laboratory Concentration a Reference Laboratory Known Lab Code b Analysis Control Limits c Acceptance Date Result Activity MAW-847 2/1/2017 Tc-99 4.77 +/- 0.62 6.25 4.38 - 8.13 Pass MAW-847 2/1/2017 U-234/233 1.19 +/- 0.10 1.16 0.81 - 1.51 Pass MAW-847 2/1/2017 U-238 1.15 +/- 0.10 1.20 0.84 - 1.56 Pass MAAP-907 f 2/1/2017 Am-241 0.0540 +/- 0.0140 0.0376 0.0263 - 0.0489 Fail MAAP-907 2/1/2017 Cs-134 1.31 +/- 0.06 1.42 0.99 - 1.85 Pass MAAP-907 2/1/2017 Cs-137 0.797 +/- 0.080 0.685 0.480 - 0.891 Pass MAAP-907 2/1/2017 Co-57 1.86 +/- 0.06 1.70 1.19 - 2.21 Pass MAAP-907 2/1/2017 Co-60 0.86 +/- 0.05 0.78 0.55 - 1.01 Pass MAAP-907 2/1/2017 Mn-54 0.01 +/- 0.03 0.00 NA c Pass MAAP-907 2/1/2017 Zn-65 1.62 +/- 0.13 1.29 0.90 - 1.68 Pass MAAP-907 2/1/2017 Pu-238 0.0530 +/- 0.0190 0.0598 0.0419 - 0.0777 Pass MAAP-907 2/1/2017 Pu-239/240 0.0490 +/- 0.0160 0.0460 0.0322 - 0.0598 Pass MAAP-907 2/1/2017 Sr-90 0.648 +/- 0.120 0.651 0.456 - 0.846 Pass MAAP-907 2/1/2017 U-234/233 0.086 +/- 0.024 0.104 0.073 - 0.135 Pass MAAP-907 2/1/2017 U-238 0.097 +/- 0.024 0.107 0.075 - 0.139 Pass MASO-4515 8/1/2017 Am-241 45.9 +/- 7.0 58.8 41.2 - 76.4 Pass g MASO-4515 8/1/2017 Cs-134 409 +/- 7 448 314 - 582 Pass g MASO-4515 8/1/2017 Cs-137 798 +/- 12 722 505 - 939 Pass g MASO-4515 8/1/2017 Co-57 1572 +/- 10 1458 1021 - 1895 Pass g MASO-4515 8/1/2017 Co-60 0.2 +/- 1.4 0.00 NA c Pass g MASO-4515 8/1/2017 Mn-54 934 +/- 13 825 578 - 1073 Pass g MASO-4515 8/1/2017 K-40 704 +/- 53 592 414 - 770 Pass g MASO-4515 8/1/2017 Zn-65 667 +/- 17 559 391 - 727 Pass g MASO-4515 8/1/2017 Pu-238 101 +/- 9 92 64 - 120 Pass g MASO-4515 8/1/2017 Pu-239/240 74.8 +/- 7.7 68.8 48.2 - 89.4 Pass g MASO-4515 8/1/2017 Sr-90 252 +/- 7 289 202 - 376 Pass g MAW-4494 8/1/2017 I-129 2.31 +/- 0.10 2.31 1.62 - 3.00 Pass MAVE-4517 8/1/2017 Cs-134 2.40 +/- 0.10 2.32 1.62 - 3.02 Pass MAVE-4517 8/1/2017 Cs-137 -0.002 +/- 0.048 0.000 NA c Pass MAVE-4517 8/1/2017 Co-57 3.3 +/- 0.1 2.8 2.0 - 3.6 Pass MAVE-4517 8/1/2017 Co-60 2.10 +/- 0.10 2.07 1.45 - 2.69 Pass MAVE-4517 8/1/2017 Mn-54 3.00 +/- 0.20 2.62 1.83 - 3.41 Pass MAVE-4517 8/1/2017 Zn-65 5.90 +/- 0.30 5.37 3.76 - 6.98 Pass a

Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation) c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing serie as a "false positive". MAPEP does not provide control limits.

f Sample was reanalyzed in duplicate with acceptable results. Original plating was inferior to platings obtained during reanalysis. It is believed that isotopic tracer was not accurately quantified due to poor resolution of its peak.

g Data were erroneously submitted in units of Bq/g. All results pass MAPEP criteria when evaluated in units of Bq/Kg.

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TABLE E.5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., Midwest Laboratory Concentration a Reference Laboratory Known Lab Code b Analysis Control Limits c Acceptance Date Result Activity MAW-4513 8/1/2017 Am-241 0.820 +/- 0.220 0.89 0.624 - 1.160 Pass MAW-4513 8/1/2017 Cs-134 10.3 +/- 0.3 11.50 8.1 - 15.0 Pass MAW-4513 8/1/2017 Cs-137 17.2 +/- 0.5 16.30 11.4 - 21.2 Pass MAW-4513 8/1/2017 Co-57 12.7 +/- 0.4 12.1000 8.5 - 15.7 Pass MAW-4513 8/1/2017 Co-60 10.6 +/- 0.3 10.70 7.5 - 13.9 Pass MAW-4513 8/1/2017 Mn-54 15.6 +/- 0.4 14.900 10.4 - 19.4 Pass MAW-4513 8/1/2017 Zn-65 15.9 +/- 0.7 15.50 10.9 - 20.2 Pass MAW-4513 8/1/2017 H-3 255 +/- 9 258.00 181 - 335 Pass MAW-4513 8/1/2017 Fe-55 21.6 +/- 6.6 19.40 13.6 - 25.2 Pass MAW-4513 8/1/2017 Ni-63 -0.1 +/- 2.0 0.00 NA c Pass MAW-4513 8/1/2017 Pu-238 0.590 +/- 0.080 0.6030 0.422 - 0.784 Pass MAW-4513 8/1/2017 Pu-239/240 0.740 +/- 0.090 0.7810 0.547 - 1.015 Pass MAW-4513 8/1/2017 Ra-226 1.000 +/- 0.100 0.858 0.601 - 1.115 Pass MAW-4513 8/1/2017 Sr-90 7.80 +/- 0.60 7.770 5.44 - 10.10 Pass MAW-4513 8/1/2017 Tc-99 6.70 +/- 0.40 6.730 4.71 - 8.75 Pass MAW-4513 8/1/2017 U-2344/233 0.94 +/- 0.06 1.0 0.71 - 1.31 Pass MAW-4513 8/1/2017 U-238 0.97 +/- 0.07 1 0.73 - 1.35 Pass MAAP-4519 h 8/1/2017 Am-241 0.0400 +/- 0.0100 0 0.0428 - 0.0796 Fail MAAP-4519 8/1/2017 Cs-134 0.90 +/- 0.10 1 0.70 - 1.30 Pass MAAP-4519 8/1/2017 Cs-137 0.90 +/- 0.10 0.82 0.57 - 1.07 Pass MAAP-4519 8/1/2017 Co-57 0.01 +/- 0.01 0 NA c Pass MAAP-4519 8/1/2017 Co-60 0.70 +/- 0.10 1 0.48 - 0.88 Pass MAAP-4519 8/1/2017 Mn-54 1.50 +/- 0.10 1 0.91 - 1.69 Pass MAAP-4519 8/1/2017 Zn-65 1.30 +/- 0.10 1 0.76 - 1.40 Pass MAAP-4519 8/1/2017 Pu-238 0.0300 +/- 0.0100 0.0 0.0209 - 0.0387 Pass MAAP-4519 8/1/2017 Pu-239/240 0.0400 +/- 0.0200 0 0.0328 - 0.0608 Pass MAAP-4519 8/1/2017 Sr-90 0.800 +/- 0.100 0.80 0.561 - 1.041 Pass MAAP-4519 8/1/2017 U-234/233 0.070 +/- 0.010 0.08 0.059 - 0.109 Pass MAAP-4519 8/1/2017 U-238 0.090 +/- 0.010 0.087 0.061 - 0.113 Pass a

Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation) c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing serie as a "false positive". MAPEP does not provide control limits.

h Laboratory is not currently offering analysis for Am-241 in Air Particulate samples (Page 3 of 3)

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

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally Left Blank Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 AND 2 Annual Radiological Groundwater Protection Program Report 1 January through 31 December 2017 Prepared By Teledyne Brown Engineering Environmental Services Limerick Power Station Pottstown, PA 19464 April 2018

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

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2017 Figures Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2017 Figure 2 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2017 Figure 3 Routine Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2017 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, 2017 Table B-I.2 Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2017 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, 2017 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, 2017 Table B-II.2 Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2017 Table B-III.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2017

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 2017 through 31 December 2017. During that time period, 274 analyses were performed on 141 samples from 13 groundwater, 7 surface water and 4 precipitation water locations collected from the environment, both on and off station property in 2017.

Groundwater and surface water was analyzed for tritium. All sample results were at concentrations less than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at 3 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 1 of 13 groundwater locations sampled. All gross alpha (suspended) results were less than the MDC. Gross beta (dissolved) was detected at 10 of 13 groundwater locations sampled. All gross beta (suspended) results were less than the MDC.

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 7 surface water 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 2017.

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

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

1

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 2017.

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

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

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

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

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

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

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

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

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

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

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

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

C. Program Description Samples for the ongoing ground water monitoring program were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2017. Sample locations can be found in Table A-1, Appendix A.

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

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

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

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

D. Characteristics of Tritium (H-3)

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

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

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

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

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III. Program Description A. Sample Analysis This section lists the analyses performed by TBE and EIML on environmental samples for the LGS RGPP in 2017. 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.

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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.

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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.

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 7

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 activity.

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

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

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

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

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

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

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

Analytical results and anomalies are discussed below:

Tritium Samples from 13 locations were analyzed for tritium activity. (Appendix B, Table B-I.1) Tritium values ranged from non-detectable to 770 pCi/L.

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Although no drinking water pathway is available from groundwater, the theoretical dose via the drinking water pathway was calculated at 4.56E-02 mrem to a child (total body), which represents 7.59E-01% of the 10 CFR 50, Appendix I dose limit of 6 mrem.

Strontium Samples were analyzed for Sr-89 and Sr-90. All results were below the required LLDs. (Appendix B, Table B-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 April 2017. Gross alpha (dissolved) was detected in 1 of 13 groundwater locations sampled at a concentration of 2.2 pCi/L. Gross alpha (suspended) results were below the required LLDs.

Gross beta (dissolved) was detected in 10 of 13 groundwater locations sampled. The concentrations ranged from 2.3 to 15.9 pCi/L. Gross beta (suspended) results were below the required LLDs.

(Appendix B, Table B-I.1)

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

Hard-To-Detect No HTD analyses were performed in 2017. (Appendix B, Table B-I.3)

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

Program surface water samples were collected from streams that

transverses the site, as well as, from other water bodies that could influence

the tritium concentration at Limerick. Analytical results and anomalies are

discussed below.

Tritium Samples from 7 locations were analyzed for tritium activity (Appendix B,

Table B-II.1). Tritium was detected in 1 of the 7 locations, sampled at a

concentration of 2 pCi/L. The theoretical dose via the drinking water

pathway was calculated at 1.45E-02 mrem to a child (total body), which

represents 2.42E-01% of the 10 CFR 50, Appendix I dose limit of 6 mrem.

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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. Naturally-occurring K-40 was detected in 1 of 7 locations at a concentration of 103 pCi/L. All other gamma results were below the required LLDs.

(Appendix B, Table B-II.2)

C. Precipitation Sample Results Tritium Tritium activity was detected in 2 of 4 precipitation water locations analyzed.

The concentrations ranged from 190 - 347 pCi/L. These concentrations are consistent with historical values observed. (Appendix B, Table B-III.1)

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

The Station has one potable supply well and one fire water well. The potable supply well is constructed as an open-rock borehole. Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2014. The pump was placed at a depth of approximately 294 feet BGS. The total well depth and the depth of the steel casing are approximately 310 feet BGS. The well is located approximately 175 feet east of the Reactor Building. The potable supply well is sampled as part of the RGPP and designated as DW-LR-1. The fire water well is constructed as an open-rock borehole. Groundwater was encountered at 121 feet BGS during a well pump replacement in 2004. The well pump was placed at a depth of approximately 399 feet BGS. The total well depth and the depth of the steel casing are unknown. The well is located approximately 500 feet east of the cooling towers. The well is used in an emergency fire situation and for system testing and flushing. In 2017, approximately 1.4 million gallons were pumped from the well.

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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 groundwater in 2017.

G. Trends No trends were identified.

H. Investigations Currently no investigations are ongoing.

I. Actions Taken

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

2. Installation of Monitoring Wells No New monitoring well

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

V. References

1. Conestoga Rovers and Associates, Fleetwide Assessment, Limerick Generating Station, Sanatoga, Pennsylvania, Ref. No. 045136(17), September 2006

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

Intentionally left blank APPENDIX A LOCATION DESIGNATION

Intentionally left blank TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2017 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, 2017 A-2

Figure 2 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2017 A-3

Figure 3 Routine Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2017 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, 2017 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 01/05/17 < 194 DW-LR-1 04/05/17 < 192 < 3.5 < 0.5 2.2 +/- 1.3 < 1.0 < 1.8 < 1.5 DW-LR-1 07/10/17 < 180 DW-LR-1 10/03/17 < 180 MW-LR-1 04/11/17 < 194 < 4.6 < 0.6 < 1.1 < 1.0 4.4 +/- 1.0 < 1.5 MW-LR-2 01/05/17 < 199 MW-LR-2 04/11/17 < 194 < 4.5 < 0.6 < 1.4 < 0.6 2.9 +/- 0.9 < 1.4 MW-LR-2 07/07/17 < 187 MW-LR-2 10/04/17 < 178 MW-LR-3 01/05/17 < 197 MW-LR-3 04/11/17 < 191 < 6.3 < 0.8 < 1.9 < 0.6 3.7 +/- 1.2 < 1.4 MW-LR-3 07/06/17 < 190 MW-LR-3 10/04/17 < 176 MW-LR-4 01/05/17 < 197 MW-LR-4 04/11/17 < 192 < 4.7 < 0.7 < 4.3 < 0.6 6.4 +/- 1.5 < 1.4 MW-LR-4 07/07/17 < 186 MW-LR-4 10/04/17 < 177 MW-LR-5 01/05/17 TBE < 198 MW-LR-5 01/05/17 TBE < 194 MW-LR-5 01/04/17 EIML < 151 MW-LR-5 04/11/17 TBE < 193 < 5.2 < 0.6 < 1.3 < 1.0 8.1 +/- 1.3 < 1.5 MW-LR-5 04/11/17 TBE < 194 < 4.4 < 0.6 < 1.7 < 0.6 7.3 +/- 1.2 < 1.4 MW-LR-5 04/11/17 EIML 222 +/- 83 < 0.6 < 0.5 < 0.0 (1) 7.6 +/- 0.9 (1)

MW-LR-5 07/07/17 TBE 312 +/- 129 MW-LR-5 07/07/17 TBE 335 +/- 131 MW-LR-5 07/07/17 EIML 269 +/- 96 MW-LR-5 10/04/17 TBE 736 +/- 143 MW-LR-5 10/04/17 TBE Original 654 +/- 137 MW-LR-5 10/04/17 TBE Reanalysis 770 +/- 144 MW-LR-5 10/04/17 EIML 710 +/- 102 MW-LR-7 01/05/17 < 199 MW-LR-7 04/11/17 < 194 < 3.7 < 0.6 < 0.7 < 0.6 2.6 +/- 0.8 < 1.4 MW-LR-7 07/06/17 < 185 MW-LR-7 10/03/17 < 173 MW-LR-8 01/04/17 TBE 266 +/- 137 MW-LR-8 01/04/17 TBE 365 +/- 139 MW-LR-8 01/04/17 EIML 356 +/- 91 MW-LR-8 04/12/17 TBE 247 +/- 130 < 3.8 < 0.5 < 2.7 < 0.5 4.8 +/- 1.5 < 1.5 MW-LR-8 04/12/17 TBE 491 +/- 142 < 5.2 < 0.6 < 2.5 < 0.6 2.3 +/- 1.5 < 1.4 MW-LR-8 04/12/17 EIML 416 +/- 93 < 0.6 < 0.5 < 0.0 (1) 2.3 +/- 1.2 (1)

MW-LR-8 07/06/17 TBE 448 +/- 135 MW-LR-8 07/06/17 TBE 506 +/- 134 MW-LR-8 07/06/17 EIML 440 +/- 102 MW-LR-8 10/03/17 TBE 514 +/- 133 MW-LR-8 10/03/17 TBE 558 +/- 136 MW-LR-8 10/03/17 EIML 594 +/- 98 (1) Total Gross Alpha & Gross Beta results reported (not Dissolved)

Bolded values indicate LLD was not met due to high solid content in the sample 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, 2017 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 01/04/17 TBE 520 +/- 151 MW-LR-9 01/04/17 TBE 622 +/- 156 MW-LR-9 01/04/17 EIML 631 +/- 103 MW-LR-9 01/25/17 636 +/- 154 MW-LR-9 02/06/17 431 +/- 143 MW-LR-9 04/12/17 TBE 278 +/- 133 < 4.0 < 0.6 < 1.3 < 0.5 14.5 +/- 1.6 < 1.6 MW-LR-9 04/12/17 TBE 400 +/- 139 < 4.6 < 0.6 < 1.4 < 0.6 9.5 +/- 1.6 < 1.4 MW-LR-9 04/12/17 EIML 519 +/- 97 < 0.7 < 0.5 < 0.0 (1) 3.1 +/- 1.2 (1)

MW-LR-9 07/06/17 TBE 278 +/- 125 MW-LR-9 07/06/17 TBE 277 +/- 130 MW-LR-9 07/06/17 EIML 342 +/- 98 MW-LR-9 10/03/17 TBE 299 +/- 127 MW-LR-9 10/03/17 EIML 344 +/- 86 MW-LR-10 01/04/17 < 198 MW-LR-10 04/12/17 < 191 < 5.2 < 0.8 < 6.0 < 1.0 6.4 +/- 1.9 < 1.5 MW-LR-10 07/06/17 < 188 MW-LR-10 10/03/17 < 178 P11 01/04/17 < 193 P11 04/12/17 < 191 < 4.2 < 0.5 < 2.4 < 1.0 15.9 +/- 1.9 < 1.5 P11 07/06/17 < 190 P11 10/03/17 < 185 P14 01/04/17 < 196 P14 04/12/17 < 195 < 4.4 < 0.6 < 5.9 < 1.0 < 2.8 < 1.5 P14 07/06/17 < 186 P14 10/03/17 < 187 P17 04/11/17 < 190 < 4.6 < 0.9 < 5.4 < 1.0 < 2.7 < 1.5 (1) Total Gross Alpha & Gross Beta results reported (not Dissolved)

Bolded values indicate LLD was not met due to high solid content in the sample B-2

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2017 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 04/05/17 < 43 < 36 < 4 < 5 < 10 < 4 < 10 < 5 < 6 < 13 < 5 < 5 < 30 < 9 MW-LR-1 04/11/17 < 58 < 144 < 6 < 5 < 14 < 7 < 11 < 5 < 9 < 11 < 6 < 6 < 30 < 7 MW-LR-2 04/11/17 < 52 < 154 < 6 < 6 < 14 < 6 < 13 < 7 < 12 < 11 < 5 < 7 < 33 < 10 MW-LR-3 04/11/17 < 53 < 62 < 7 < 5 < 10 < 7 < 12 < 7 < 12 < 14 < 7 < 7 < 32 < 11 MW-LR-4 04/11/17 < 44 < 44 < 5 < 5 < 9 < 6 < 9 < 6 < 9 < 10 < 5 < 5 < 21 < 9 MW-LR-5 04/11/17 TBE < 61 < 68 < 6 < 7 < 13 < 6 < 10 < 7 < 12 < 14 < 6 < 7 < 34 < 10 MW-LR-5 04/11/17 TBE < 77 < 156 < 7 < 7 < 17 < 7 < 17 < 9 < 14 < 13 < 8 < 9 < 40 < 12 MW-LR-5 04/11/17 EIML < 48 < 72 < 4 < 3 < 3 < 4 < 8 < 4 < 6 < 8 < 4 < 3 < 25 < 5 MW-LR-7 04/11/17 < 45 < 94 < 4 < 5 < 9 < 5 < 9 < 5 < 9 < 9 < 5 < 5 < 25 < 7 MW-LR-8 04/12/17 TBE < 65 < 120 < 8 < 8 < 14 < 6 < 16 < 8 < 11 < 12 < 7 < 6 < 35 < 6 MW-LR-8 04/12/17 TBE < 81 < 121 < 9 < 7 < 16 < 7 < 13 < 9 < 11 < 11 < 7 < 8 < 36 < 12 MW-LR-8 04/12/17 EIML < 21 < 52 < 2 < 2 < 4 < 2 < 4 < 2 < 5 < 6 < 2 < 2 < 15 < 2 MW-LR-9 04/12/17 TBE < 62 < 139 < 7 < 7 < 13 < 9 < 14 < 7 < 13 < 14 < 7 < 9 < 30 < 9 MW-LR-9 04/12/17 TBE < 55 < 143 < 7 < 6 < 13 < 6 < 11 < 7 < 11 < 12 < 6 < 7 < 30 < 11 B-3 MW-LR-9 04/12/17 EIML < 23 < 44 < 2 < 2 < 3 < 2 < 4 < 3 < 4 < 5 < 2 < 2 < 16 < 4 MW-LR-10 04/12/17 < 38 < 44 < 4 < 4 < 11 < 4 < 11 < 6 < 8 < 9 < 5 < 6 < 21 < 9 P11 04/12/17 < 53 < 117 < 6 < 7 < 14 < 8 < 17 < 9 < 9 < 12 < 8 < 8 < 29 < 8 P14 04/12/17 < 52 < 182 < 7 < 6 < 16 < 7 < 17 < 7 < 16 < 15 < 7 < 8 < 35 < 14 P17 04/11/17 < 49 < 47 < 5 < 5 < 10 < 4 < 10 < 5 < 9 < 8 < 4 < 6 < 22 < 6

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION STC PERIOD AM-241 CM-242 CM-243/244 PU-238 PU-239 U-233/234 U-235 U-238 FE-55 NI-63 There were no HTD's Analyzed in 2017 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, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 SW-LR-2 01/03/17 < 199 SW-LR-2 04/10/17 < 196 < 3.5 < 0.9 SW-LR-2 07/05/17 < 186 SW-LR-2 10/02/17 < 177 SW-LR-4 01/03/17 < 196 SW-LR-4 04/10/17 < 197 < 5.1 < 0.7 SW-LR-4 07/05/17 < 188 SW-LR-4 10/02/17 < 175 SW-LR-6 01/03/17 < 195 SW-LR-6 04/10/17 < 196 < 4.9 < 0.6 SW-LR-6 07/05/17 < 186 SW-LR-6 10/02/17 < 175 SW-LR-7 01/03/17 < 195 SW-LR-7 04/11/17 < 192 < 3.8 < 0.5 SW-LR-7 07/05/17 < 188 SW-LR-7 10/02/17 < 178 SW-LR-8 01/04/17 228 +/- 133 SW-LR-8 01/04/17 Reanlaysis 245 +/- 135 SW-LR-8 04/05/17 < 195 < 5.2 < 0.6 SW-LR-8 07/11/17 < 182 SW-LR-8 10/03/17 < 179 SW-LR-9 01/06/17 < 192 SW-LR-9 04/05/17 < 190 < 3.9 < 0.5 SW-LR-9 07/12/17 < 178 SW-LR-9 10/03/17 < 177 SW-LR-10 01/03/17 < 199 SW-LR-10 04/11/17 < 197 < 4.7 < 0.5 SW-LR-10 07/05/17 < 190 SW-LR-10 10/02/17 < 178 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, 2017 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 04/10/17 < 59 < 69 < 7 < 6 < 13 < 6 < 13 < 7 < 11 < 13 < 6 < 7 < 33 < 10 SW-LR-4 04/10/17 < 49 < 104 < 5 < 6 < 11 < 5 < 9 < 6 < 10 < 12 < 5 < 7 < 26 < 10 SW-LR-6 04/10/17 < 61 < 110 < 4 < 6 < 12 < 4 < 13 < 5 < 8 < 10 < 6 < 6 < 30 < 6 SW-LR-7 04/11/17 < 57 < 97 < 5 < 5 < 14 < 8 < 12 < 6 < 12 < 8 < 6 < 6 < 26 < 7 SW-LR-8 04/05/17 < 50 103 +/- 63 < 5 < 5 < 11 < 6 < 8 < 5 < 8 < 15 < 5 < 5 < 32 < 13 SW-LR-9 04/05/17 < 40 < 87 < 5 < 5 < 13 < 6 < 11 < 5 < 8 < 15 < 4 < 4 < 32 < 8 SW-LR-10 04/11/17 < 46 < 119 < 5 < 6 < 15 < 6 < 13 < 7 < 11 < 10 < 6 < 6 < 26 < 11 B-6

TABLE B-III.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 36S3 12/29/16 - 01/30/17 < 199 36S3 01/30/17 - 02/27/17 < 195 36S3 02/27/17 - 03/27/17 < 193 36S3 03/27/17 - 04/28/17 < 174 36S3 04/28/17 - 05/26/17 < 181 36S3 05/26/17 - 06/29/17 < 180 36S3 06/29/17 - 07/28/17 < 181 36S3 07/28/17 - 08/24/17 < 174 36S3 08/24/17 - 09/26/17 < 187 36S3 09/26/17 - 10/30/17 < 177 36S3 10/30/17 - 12/07/17 < 182 36S3 12/07/17 - 12/29/17 < 187 E-5 12/29/16 - 01/30/17 < 191 E-5 01/30/17 - 02/27/17 < 192 E-5 02/27/17 - 03/27/17 < 192 E-5 03/27/17 - 04/28/17 < 174 E-5 04/28/17 - 05/26/17 < 180 E-5 05/26/17 - 06/29/17 < 186 E-5 06/29/17 - 07/28/17 < 179 E-5 07/28/17 - 08/24/17 < 174 E-5 08/24/17 - 09/26/17 < 180 E-5 09/26/17 - 10/30/17 < 175 E-5 10/30/17 - 12/07/17 < 182 E-5 12/07/17 - 12/29/17 < 184 ESE-6 12/29/16 - 01/30/17 < 195 ESE-6 01/30/17 - 02/27/17 < 192 ESE-6 02/27/17 - 03/27/17 190 +/- 124 ESE-6 03/27/17 - 04/28/17 < 169 ESE-6 04/28/17 - 05/26/17 < 178 ESE-6 05/26/17 - 06/29/17 < 183 ESE-6 06/29/17 - 07/28/17 < 181 ESE-6 07/28/17 - 08/24/17 < 174 ESE-6 08/24/17 - 09/26/17 < 181 ESE-6 09/26/17 - 10/30/17 < 181 ESE-6 10/30/17 - 12/07/17 < 182 ESE-6 12/07/17 - 12/29/17 < 196 SE-7 12/29/16 - 01/30/17 < 198 SE-7 01/30/17 - 02/27/17 < 190 SE-7 02/27/17 - 03/27/17 < 188 SE-7 03/27/17 - 04/28/17 < 175 SE-7 04/28/17 - 05/26/17 < 181 SE-7 05/26/17 - 06/29/17 347 +/- 129 SE-7 06/29/17 - 07/28/17 < 179 SE-7 07/28/17 - 08/24/17 < 173 SE-7 08/24/17 - 09/26/17 227 +/- 122 SE-7 09/26/17 - 10/30/17 < 180 SE-7 10/30/17 - 12/07/17 < 187 SE-7 12/07/17 - 12/29/17 < 187 B-7