Text

2013 Annual Radiological Environmental Operating Report
	ML14143A094
Person / Time
Site:	Limerick
Issue date:	04/30/2014
From:	Dougherty T; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LG-14-068
	Download: ML14143A094 (144)
	v • d • e

AMENEW ANNIP-Exelon Generation.

TS 6.9.1.7 LG-1 4-068 April 30, 2014 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353

Subject:

2013 Annual Radiological Environmental Operating Report

Dear Sir:

In accordance with the requirements of Section 6.9.17 of Limerick Generating Station (LGS)

Unit 1 and Unit 2 Tech. Specs., and Section 6.1 of the LGS Units 1 and 2 Offsite Dose Calculation Manual (ODCM), this letter submits the 2013 Annual Radiological Environmental Operating Report. This report provides the 2013 results for the Radiological Environmental Monitoring Program (REMP) as called for in the Offsite Dose Calculation Manual.

In assessing the data collected for the REMP, it has been concluded that the operation of LGS, Units 1 and 2 had no adverse impact on the environment. No plant-produced fission or activation products, with the exception of Cs-137, were found in any pathway modeled by the REMP. Cesium-1 37 levels detected in sediment were consistent with levels found in previous years and were attributable to LGS liquid releases. 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 up to 477 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, ple not hesitate to contact us.

Sincerely, Thomas J. Dougherty Vice President -LGS Exelon Generation Company, LLC

Attachment:

2013 Annual Radiological Environmental Operating Report cc:

W. Dean, Administrator, Region I, USNRC (w/Attachment)

E. DiPaolo, USNRC Senior Resident Inspector, LGS (w/Attachment)

R. Ennis -Senior Project Manager-NRR, USNRC (w/Attachment)

R. Nimitz, Inspector, Region I, USNRC (w/Attachment)

-I- ~

ATTACHMENT 1 2013 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 2013 Prepared By Teledyne Brown Engineering Environmental Services N

ExeLon Generation.

April 2014

Intentionally left blank

Table Of Contents I. Sum m ary and Conclusions.........................................................................................

1 I1. Introduction............................................................................................................

3 A. Objectives of the REM P..................................................................................

3 B. Im plem entation of the Objectives..................................................................

4 III. Program Description..................................................................................................

4 A. Sam ple Collection...........................................................................................

4 B. Sam ple Analysis..............................................................................................

6 C. Data Interpretation........................................................................................

7 D. Program Exceptions.......................................................................................

8 E. Program Changes...........................................................................................

9 F. Com pliance to 10CFR190 Lim its....................................................................

9 IV. Results and Discussion...........................................................................................

10 A. Aquatic Environm ent....................................................................................

10

1. Surface W ater.....................................................................................

10

2. Drinking W ater..................................................................................

10

3. Fish....................................................................................................

11

4. Sedim ent............................................................................................

11 B. Atm ospheric Environment.............................................................................

12

1. Airborne.............................................................................................

12

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

12

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

13

2. Terrestrial...........................................................................................

13

a. M ilk.........................................................................................

13

b. Broad Leaf Vegetation.............................................................

13 C. Am bient Gam m a Radiation...........................................................................

14 D. 10 CFR 20.2002 Perm it Storage Area........................................................

14 E. Independent Spent Fuel Storage Area.......................................................

14 F. Land Use Survey...........................................................................................

14 G. Errata Data..................................................................................................

15 H. Summary of Results - Inter-Laboratory Comparison Program.................... 16 V. R e fe re n c e s...................................................................................................................

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Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Appendix B Tables Table B-1 Table B-2 Table B-3 Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2013.

Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Location Designation and Identification System for the Limerick Generating Station.

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2013.

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2013.

Fi-gures Figure B-1 Figure B-2 Figure B-3 Appendix C Tables Table C-1.1 Table C-1.2 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2013.

Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2013.

Environmental Sampling Locations Greater Than 26,400 Feet from the Limerick Generating Station, 2013.

Data Tables and Figures - Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2013.

4

Table C-11.1 Table C-11.2 Table C-11.3 Table C-II.4 Table C-111.1 Table C-IV. 1 Table C-V. 1 Table C-V.2 Table C-V.3 Table C-VI. 1 Table C-VII.1 Table C-VII.2 Table C-VIII.1 Table C-IX.1 Table C-IX.2 Figqures Figure C-1 Figure C-2 Figure C-3 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2013 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Quarterly OSLD Results for Limerick Generating Station, 2013.

Mean Quarterly Dosimeter Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2013.

Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2013.

Mean Annual Cs-1 37 Concentrations in Fish Samples Collected in the Vicinity of LGS, 1982 - 2013.

Concentrations of Cs-1 37 in Sediment Samples Collected in the Vicinity of LGS, 1982 - 2013.

Figure C-4 Figure C-5 Appendix D Tables Table D-1.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-11.1 Table D-11.2 Table D-111.1 Figures Figure D-1 Figure D-2 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2013.

Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2013.

Data Tables and Figures - Comparison Laboratory Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2013.

Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2013.

Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Gross Beta in Air Particulate and 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Concentrations of 1-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2013.

Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2013.

Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2013.

Appendix E Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Appendix F Appendix G Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2013.

ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2013.

DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2013.

ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2013.

DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2013.

Errata Data Annual Radiological Groundwater Protection Program Report (ARGPPR)

Intentionally Left Blank

I.

Summary and Conclusions In 2013, the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 151 curies of noble gas, fission and activation products and approximately 40 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 Location

% of Limit Unit Organ Dose Group Applicable Limit Noble Gas Gamma - Air Dose 6.22E-03 All Nearest Residence 3.11 E-02 20 mRad Noble Gas Beta - Air Dose 3.83E-03 All Nearest Residence 9.58E-03 40 mRad Noble Gas Total Body (Gamma) 5.85E-03 All Nearest Residence 5.85E-02 10 mrem Noble Gas Skin (Beta) 9.64E-03 All Nearest Residence 3.21 E-02 30 mrem

Iodine, Particulate, Bone 1.55E-00 Child Vegetation 5.17E-00 30 mrem Tritium & C-14 Liquid Total Body 1.79E-04 Child AQUA PA 2.98E-03 6

mrem Liquid GI-Lli 1.79E-04 Child AQUA PA 8.95E-04 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 2013 through 31 December 2013. During that time period, 1265 analyses were performed on 1025 samples.

Surface and drinking water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of total gross beta and 1-131. No 1-131 was detected. No fission or activation products were detected. Gross beta activities detected were consistent with those detected in previous years.

Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish.

Sediment samples collected below the discharge had Cesium-1 37 concentrations that were consistent to those from previous years. No other station produced fission or activation products were found in sediment. The calculated dose to a teenager's skin and whole body was 4.54E-04 mrem and 3.89E-04 mrem, respectively. This dose represents 2.27E-03% and 6.48E-03%,

respectively of the 10 CFR Part 50, Appendix I dose limits.

1

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

High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable concentration.

Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. All 1-131 results were below the minimum detectable concentration. Concentrations of naturally occurring 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 was found in 11 of 43 samples. Thorium-228 was found in 2 of 43 samples.

Radium-226 and Thorium-228 were detected in low concentration just above the MDC (minimum detectable concentration). No activation or fission products were detected.

Review of the gamma spectroscopy results from the surface water samples located at the Limerick intake (24S1) and downstream of the 10CFR20.2002 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. Levels detected were slightly higher than what has been detected in previous years. This step change in data is attributed to the change in methodology used to calculate the ambient gamma dose in 2013.

A review of the dosimetry data for the nearest residence to the Independent Spent Fuel Storage Installation (ISFSI) indicates 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 2013, well water samples were analyzed for tritium, Sr-89, Sr-90, gross alpha, gross beta, and gamma emitters.

Surface water samples were analyzed for tritium, Sr-89, Sr-90, and gamma emitters. Most of the tritium values for well water and surface water were less than the lower limit of detection of 200 pCi/L. Results and Discussion of groundwater samples are covered in Appendix G. Precipitation water samples were also analyzed for tritium. No tritium was detected in any precipitation samples.

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.

2

II.

Introduction The Limerick Generating Station (LGS), consisting of two 3,515 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 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), Landauer Incorporated and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2013 through 31 December 2013.

On 6 July 1996 a 10CFR20.2002 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.

3

B.

Implementation of the Objectives The implementation of the objectives is accomplished by:

1.

Identifying significant exposure pathways.

2.

Establishing baseline radiological data of media within those pathways.

3.

Continuously monitoring those media before and during station operation to assess station radiological effects (if any) on man and the environment.

Ill.

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 2011. 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 (caffish/carp/white suckers) and predator (sunfish/bass/rock bass),

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, 13C1, 14S1, 15D1 and 22G). 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.

4

Terrestrial Environment Milk samples were collected biweekly at five locations (1 0F4, 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 at three locations (11 S3, 13S3 and 31G1). The control location was 31G1. Seven different kinds of vegetation samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP).

Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and Thermoluminescent Dosimetry (TLD) were discontinued. A step change of increased readings was observed. Side by side comparison of the OLSDs and the TLDs was performed during second, third and fourth quarters of 2012, with an average 2 standard deviation of 5.55. The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation).The dosimeter 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 rinq 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 31 D1) 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; 5

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 Landauer Technologies for analysis.

10CFR20.2002 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 10CFR20.2002. These materials will be stored until end of the site's 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 2002 pad, 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.

Independent Spent Fuel Storage Installation (ISFSI)

The results from the dosimeter location 36S2 were used to determine the direct radiation exposure to the nearest residence from the ISFSI pad.

B.

Sample Analysis This section describes the general analytical methodologies used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the LGS REMP in 2011. The analytical procedures used by the laboratories are listed in Appendix B Table B-3.

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 1-131 in air, milk, and drinking water.

5.

Ambient gamma radiation levels at various site environs.

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C.

Data Interpretation The radiological and direct radiation data collected prior to LGS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this report, LGS was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:

1.

Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration 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.

If no positive activity was detected, then gamma spectroscopy MDC 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, Zr-95, Nb-95, 1-131, 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, 1-131, 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, 1-131, Cs-134, and Cs-137 were reported.

For sediment eight nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, 1-131, Cs-134, and Cs-1 37 were reported.

7

For air particulate six nuclides, Be-7, Mn-54, Co-58, Co-60, Cs-1 34, and Cs-1 37 were reported.

For milk five nuclides, K-40, Cs-1 34, Cs-1 37, Ba-140, and La-140 were reported.

Means and standard deviations of positive results were calculated.

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

D.

Program Exceptions For 2013 the LGS REMP had a sample recovery rate of 99%. Exceptions are listed below:

1.

Air sample from location 11 S1 for the week of 02/4/13 - 02/11/13 was not available due to loss of power (IR 1494664).

2.

Air sample from location 6C1 for the week of 03/18/13 - 03/26/13 was not available due to equipment malfunction (IR 1494671).

3.

Air particulate sample from location 15D1 for the week of 07/15/13

- 07/22/13 was not available due to invalid particulate filter.

Deviation memorandum dated 7/25/13. (IR 1541267).

4.

Air sample from location 22G1 for the week of 09/09/13 - 09/16/13 was not available due to loss of power (IR 1561512).

5.

Grab samples were taken for the composite surface water sampler at location 13B1 during the following periods due to frozen sample line and loss of power due to landscaping:

10/29/13-11/05/13 (IR 1609841) 12/10/13 - 12/17/13 (IR 1609834)

6.

Grab samples were taken for the composite drinking water sampler at location 15F7 during the following periods due to loss of power:

07/01/13 - 07/09/13 (I R 1609833)

Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and freezing temperatures were unavoidable.

The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

8

E.

Program Changes

1.

In March 2013, the air station 13C1 located in the SE sector was shut down due to its inconvenient location. Air station 15D1 in the SE sector was started up as its replacement. See Appendix B for detailed location information.

2.

In April 2013, sampling at milk station 10F4 was discontinued.

F.

Compliance to 40CFR190 Limits A.

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:

" Long term annual average meteorology X/Q and D/Q and actual gaseous effluent releases were used.

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

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

100 percent occupancy factor was assumed.

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.

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 40CFR1 90 compliance.

40 CFR 190 Compliance:

The maximum calculated dose to a real individual would not exceed 1.07E+01 mrem (total body), 1.20E+01 mrem (organ), or 1.07 E+01 mrem (thyroid).

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

9

Table 1 40CFR190 Compliance 40 CFR 190 Compliance Gaseous Effluents

% of Noble Particulate, Liquid Net Direct T

of Total Applicable Limit Unit Gas lodone, C-14 Effluents Radiation Limit

& Tritium Total Body 6.76E-03 3.12E-01 1.79E-04 1.04E+01 1.07E+01 4.28E+01%

25 mrem Dose Organ Dose 6.76E-03 1.55E+00 1.79E-04 1.04E+01 1.20E+01 4.80E+01%

25 mrem Thryoid Dose 6.76E-03 3.12E-01 1.78E-04 1.04E+01 1.07E+01 1.43E+01%

75 mrem IV.

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 Limerick's 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-1.1). All results met the required LLD.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Appendix C, Table C-1.2). All nuclides met 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 Limerick's effluent releases. The following analyses were performed:

Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Appendix C, Tables C-11.1). The values ranged from 1.9 to 8.8 pCi/L. Concentrations detected were consistent with those detected in previous years (Appendix C, Figure C-1).

10

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity. All results met the required LLD (Appendix C, Table C-11.2).

Iodine-131 Monthly samples were taken from all locations and analyzed for Iodine-131 activity (Appendix C, Table C-11.3). All results met the required LLD.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Appendix C, Table C-11.4). All results met the required LLDs.

3.

Fish Fish samples comprised of bottom feeder (catfish/carp/white suckers) and predator (sunfish/bass/rock bass), were collected at two locations (16C5 and 29C1) in the spring and fall season.

Location 16C5 could be affected by Limerick's 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-111.1).

Naturally occurring K-40 was found at all stations and ranged from 3,061 to 4,824 pCi/kg wet and was consistent with levels detected in previous years. No other activity was detected and the required LLD was met. Though Cs-1 37 was not detected in 2013, historical levels of Cs-1 37 are shown in Appendix C, Figure C-2.

4.

Sediment Aquatic sediment samples were collected at three locations (16B2, 16C4 and 33A2) semiannually. Of these locations two, 166B2 and 16C4, could be affected by Limerick's effluent releases. The following analysis was performed:

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

11

Beryllium-7 was found at all locations and ranged from 2,736 to 5,637 pCi/kg dry. Potassium-40 was found at all locations and ranged from 14,370 to 19,190 pCi/kg dry. The fission product Cs-1 37 was found at location 16C4 at a concentration of 173 pCi/kg dry (Appendix C, Figure C-4).

The activity detected was consistent with those detected in the pre-operational years. Due to the control location, 33A2, not showing positive activity, the Cs-1 37 activity found at 16C4 is attributed to LGS radioactive effluent releases. The dose to a teenager's skin and whole body was conservatively calculated at 4.54E-04 mrem and 3.89E-04 mrem, respectively. This dose represents 2.27E-03% and 6.48E-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 six locations on a weekly basis. The six locations were separated into three groups: Group I represents locations within the LGS site boundary (10S3, 11S1, and 14S1),

Group II represents the locations at an intermediate distance from the LGS site (6C1, 13C1, 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 7 E-3 to 36 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3. The results from the intermediate distance location (Group II) ranged from 8 E-3 to 35 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3. The results from the remote distance locations (Group Ill) ranged from 7 E-3 to 31 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3. Comparison of the 2013 air particulate data with previous year's data indicate no effects from the operation of LGS (Appendix C, Figure C-4). In addition, a comparison of the weekly mean values for 2013 indicate no notable differences among the three groups (Appendix C, Figure C-5).

12

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 24 out of 25 samples and is contributed to cosmic ray activity. These values ranged from 42 E-3 to 95 E-3 pCi/m 3. All other nuclides met the required LLDs.

b.

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

2.

Terrestrial

a.

Milk Samples were collected from five locations (10F4, 18E1, 1981, 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-1 31 Milk samples from all locations were analyzed for concentrations of 1-131 (Appendix C, Table C-VII. 1). All results met 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 1,107 to 1,515 pCi/L. All other nuclides met the required LLDs.

b.

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

13

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

Cosmogenic Be-7 was found in 28 of 43 samples and ranged from 122 to 6,680 pCi/kg wet. Naturally occurring K-40 was found in all samples and ranged from 2,039 to 8,809 pCi/kg wet. All other nuclides met the required LLDs.

C.

Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing A120 3:C optically stimulated luminescence 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,.

Dosimeter measurements were reported in mrem/standard month. Most dosimeter measurements were below 10 mrem/standard month, with a range of 7.7 to 13.7 mrem/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 The result of the ambient gamma radiation level at dosimeter location 36S2 was 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 10.4 mrem for the year.

F.

Land Use Survey A Land Use Survey conducted in August 2013 around Limerick Generating Station (LGS) was performed by Normandeau Associates, Inc.

14

for Exelon Nuclear to comply with Bases 3.3.2 of the Limerick's 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 2 degree sectors around the site. The distance and direction of all locations from the LGS reactor buildings were positioned using Global Positioning System (GPS) technology. 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 Sector Residence Garden Milk Farm Meat Animal Feet Feet Feet Feet 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 3,109 2,706 3,469 3,231 2,864 3,434 5,108 5,403 4,347 5,063 3,251 3,799 3,627 3,932 3,619 5,051 3,335 9,610 3,494 14,266 7,776 5,780 6,470 6,898 6,103 5,320 4,562 12,013 4,208 3,932 8,169 5,586 24,775 22,115 10,390 14,175 14,654 24,775 21,274 20,552 25,739 10,927 12,211 10,390 18,547 14,175 14,654 G.

Errata Data

1.

Teledyne Brown Engineering (TBE) provides data results [activity, uncertainty and minimum detectable concentration {MDC}]. The MDC is calculated using a multiplier of 4.66.

4.66

't MDA =

At 2.22 (v)(y) (a)(-)

Where:

At = counting time for sample (minutes)

= background rate of instrument blank (cpm) 2.22 = dpm/pCi or : 2.22 x 106 dpm/lpCi v = volume or mass of sample analyzed y = chemical yield 15

E = efficiency of the counter The formulas for calculating the activity, uncertainty and MDC are contained in the software of the counting equipment. For the gamma system, when the new detector number 08 was added to the system in January 2012, the default value of 3.29 was used to calculated the MDCs on detector 08. The activity and uncertainty were not affected. The multiplier has been changed from 3.29 to the required 4.66.

When the MDCs were recalculated using 4.66, the MDC values increased by 41.6%. The greatest impact is on the short-lived nuclides which have an LLD requirement, e.g. 1-131, Ba-140 and La-140. The missed LLDs are identified in the Errata Data Appendix F table of the 2013 annual report.

2.

Total body and organ dose for liquid releases in 2010, 2011, and 2012 were recalculated due to a software error identified (IR 1613017). Due to the software error, dose calculations were being performed without the inclusion of the Schuylkill River dilution factor as required by the ODCM dose methodology. The corrected data in Appendix F includes the dose calculations post dilution and the updated 40 CFR 190 Compliance table. No limits have been exceeded.

H.

Summary of Results - Inter-laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices for various analytes. (Appendix E) The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

1.

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

2.

ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, National Environmental 16

Laboratory Accreditation Conference (NELAC), state specific Performance Testing (PT) program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable.

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

3.

DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.

The MAPEP defines three levels of performance: Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/- 20% to +/- 30% of the reference value. If the bias is greater than 30%, the results are deemed not acceptable.

For the TBE laboratory, 178 out of 185 analyses performed met the specified acceptance criteria. Seven analyses (Sr-89 and Sr-90 in milk, Co-57, Zn-65 and Sr-90 in soil, Cs-1 34 in air particulate and Sr-90 in vegetation [two low warning in a row]) did not meet the specified acceptance criteria or internal QA requirements for the following reason:

1.

Teledyne Brown Engineering's Analytics September 2013 Sr-89 in milk result of 63.9 pCi/L was lower than the known value of 96.0 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15

2.

Teledyne Brown Engineering's Analytics September 2013 Sr-90 in milk result of 8.88 pCi/L was lower than the known value of 13.2 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15

3. & 4. Teledyne Brown Engineering's MAPEP September 2013 Co-57 and Zn-65 in soil were evaluated as failing the false positive test.

While MAPEP evaluated the results as failures, the gamma software listed the results as non identified nuclides. The two nuclides would never have been reported as detected nuclides to a client. MAPEP does not allow laboratories to put in qualifiers for the submitted data nor "less than" results. MAPEP evaluates results based on the relationship between the activity and the 17

uncertainty. MAPEP spiked the soil sample with an extremely large concentration of Eu-1 52, which was identified by the gamma software as an interfering nuclide, resulting in forced activity results that were evaluated by MAPEP as detected Co-57 and Zn-65. No client samples were affected by these failures. NCR 13-14

5.

Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in soil result of 664 Bq/kg was higher than the known value of 460 Bq/kg, exceeding the upper control limit of 598 Bq/kg. An incorrect Sr-90 result was entered into the MAPEP database. The correct Sr-90 activity of 322 Bq/kg would have been evaluated as acceptable with warning.

No client samples were affected by this failure. NCR 13-14

6.

Teledyne Brown Engineering's MAPEP September 2013 Cs-134 in air particulate activity of -0.570 Bq/sample was evaluated as a failed false positive test, based on MAPEP's evaluation of the result as a significant negative value at 3 standard deviations. A negative number would never have been reported as a detected nuclide to a client, therefore no client samples were affected by this failure.

NCR 13-14

7.

Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in vegetation result was investigated due to two low warnings in a row. It appears the September sample was double spiked with carrier, resulting in a low activity. With a recovery of around 50%

lower, the Sr-90 result would have fallen within the acceptance range. No client samples were affected by this issue. NCR 13-14 For the EIML laboratory, 89 of 92 analyses met the specified acceptance criteria. Three analyses (AP - Gross Alpha, Soil - Sr-90 and Co-57) did not meet the specified acceptance criteria for the following reasons:

1.

Environmental Inc., Midwest Laboratory's MAPEP February 2013 air particulate gross alpha result of 0.14 Bq/total sample was lower than the known value of 1.20 Bq/total sample, exceeding the lower control limit of 0.36 Bq/total sample. The filter was recounted overnight. No significant activity could be detected.

2.

Environmental Inc., Midwest Laboratory's MAPEP February 2013 soil Co-57 result of 408.40 Bq/kg was lower than the known value of 628.0 Bq/kg, exceeding the lower control limit of 440.0 Bq/kg. The sample was reanalyzed using additional fuming nitric separations. The reanalysis result of 574.4 fell within the control limits.

3.

Environmental Inc., Midwest Laboratory's MAPEP August 2013 soil Co-57 result of 699.60 Bq/kg was higher than the known value of 0.00 Bq/kg, exceeding the upper control limit 18

of 5.00 Bq/kg. Interference from Eu-152 resulted in misidentification of Co-57.

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

V.

References 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.

19

Intentionally Left Blank

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER)

H-3 8

200

<LLD

<LLD 0

GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 24 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD

<LLD 0

0 0

0 NB-95

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER)

ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD 4

3.8 (31/36)

(1.9/8.8)

<LLD

<LLD 0

0 0

0 DRINKING WATER (PCI/LITER)

GR-B 48 3.2 (10/12)

(2.3/5.0) 4.7 (11/12)

(2.4/8.8) 15F4 INDICATOR 0

PHILADELPHIA SUBURBAN WATER COMPANY 8.62 MILES SE OF SITE

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS DRINKING WATER (PCI/LITER)

H-3 1-131 GAMMA MN-54 CO-58 FE-59 CO-60 16 48 48 200

<LLD 1

<LLD

<LLD 0

0 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD

<LLD 0

0 0

ZN-65

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS DRINKING WATER (PCI/LITER)

NB-95 ZR-95 CS-134 CS-1 37 BA-140 LA-140 GAMMA K-40 15

<LLD 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD

<LLD 0

0 0

0 BOTTOM FEEDER (PCI/KG WET)

NA 4203 (2/2)

(3871/4535) 3672 (2/2)

(3096/4247) 4203 (2/2)

(3871/4535) 16C5 INDICATOR VINCENT POOL DOWNSTREAM OF DISCHARGE 0

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS BOTTOM FEEDER (PCI/KG WET) i-i MN-54 CO-58 FE-59 CO-60 ZN-65 130

<LLD 130

<LLD 260

<LLD 130

<LLD 260

<LLD NA

<LLD 130

<LLD

<LLD 0

0 0

1-131 CS-134

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS BOTTOM FEEDER (PCI/KG WET)

PREDATOR 61 (PCI/KG WET)

CS-137 GAMMA K-40 MN-54 CO-58 FE-59 CO-60 150

<LLD

<LLD 0

4 NA 4426 (212)

(4028/4824) 3509 (2/2)

(3061/3957) 4426 (212)

(4028/4824) 16C5 INDICATOR VINCENT POOL DOWNSTREAM OF DISCHARGE 0

0 130

<LLD 130

<LLD 260

<LLD 130

<LLD 260

<LLD

<LLD 0

0 0

ZN-65 0

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS PREDATOR (PCI/KG WET) 1-131 CS-134 CS-137 GAMMA BE-7 NA

<LLD 130

<LLD 150

<LLD

<LLD 0

0 0

SEDIMENT (PCI/KG DRY) 6 NA 5097 (3/4)

(470115637)

NA 17848 (4/4)

(16840/19190) 2736 (1/2) 5637 (1/2) 16C4 INDICATOR VINCENT DAM 2.18 MILES SSE OF SITE 16B2 INDICATOR LINFIELD BRIDGE 1.35 MILES SSE OF SITE K-40 15475 (2/2)

(14370/16580) 18015 (2/2)

(16840/19190) 0 0

0 0

MN-54 CO-58 NA

<LLD NA

<LLD

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS SEDIMENT (PCI/KG DRY)

CO-60 00 1-131 CS-134 CS-137 GR-B GAMMA BE-7 NA

<LLD NA

<LLD 150

<LLD 180 173 (1/4) 10 17 (263/269)

(7/36)

NA 77 (20/21)

(61/95)

NA

<LLD

<LLD 0

0 0

AIR PARTICULATE (E-3 PCI/CU.METER) 320 25

<LLD 16 (51/51)

(7/31) 71 (4/4)

(42/85) 173 (1/2) 19 (10/12)

(13/28) 81 (4/4)

(71/93) 16C4 INDICATOR VINCENT DAM 2.18 MILES SSE OF SITE 13C1 INDICATOR KING ROAD 2.84 MILES SE OF SITE 6C1 INDICATOR 11305 FEET NE OF SITE 0

0 MN-54

<LLD

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS AIR PARTICULATE (E-3 PCI/CU.METER)

CO-58 CO-60 CS-134 CS-137 GAMMtA 1-13 1 NA

<LLD NA

<LLD 50

<LLD 60

<LLD

<LLD 0

0 0

0 AIR IODINE (E-3 PCI/CU.METER) 321 70

<LLD 1

<LLD

<LLD 0

0 MILK (PCI/LITER) 1-131 95

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS MILK (PCI/LITER)

GAMMA K-40 CS-134 CS-137 BA-140 LA-140 GAMMA BE-7 NA 1284 (69/69)

(1108/1515) 15

<LLD 1281 (26/26)

(1107/1422) 1302 (22/22)

(1146/1457) 19B1 INDICATOR 1.95 MILES SSW OF SITE 18

<LLD 60

<LLD 15

<LLD 95

<LLD

<LLD 0

0 0

VEGETATION (PCI/KG WET) 43 NA 681 (19/28)

(122/2384) 1095 (9/15)

(255/6680) 1095 (9/15)

(255/6680) 31G1 CONTROL

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS VEGETATION (PCI/KG WET)

K-40 NA 5008 (28/28)

(2039/7354) 5635 (15/15)

(3624/8809) 5635 (15/15)

(3624/8809) 31G1 CONTROL 0

MN-54 CO-58 CO-60 NA

<LLD NA

<LLD 60

<LLD 80

<LLD

<LLD 0

0 1-131 CS-134 CS-137 0

0

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2013 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2013 LOCATION OF FACILITY: MONTGOMERY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS VEGETATION (PCI/KG WET)

RA-226 TH-228 TH-232 NA 982 (11/28)

(198/2099)

NA 35 (2/28)

(17/53)

NA

<LLD NA 10 (156/156)

(7.7/13.7)

<LLD

<LLD 1061 (10/15)

(223/2099) 35 (2/13)

(17/53) 13S3 INDICATOR VINCENT DAM 0.24 MILES SE OF SITE 11 S3 INDICATOR LGS INFORMATION CENTER 0.35 MILES ESE OF SITE 0

0 0

DIRECT RADIATION OSLD-QUARTERLY (MILLI-ROENTGEN/STD.MO.)

160 11.6 (4/4)

(11.0/12.3) 13.4 (4/4)

(13.0/13.7) 13S2 INDICATOR 500 KV SUBSTATION 0.41 MILES SE

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

APPENDIX B LOCATION DESIGNATION, DISTANCE &

DIRECTION, AND SAMPLE COLLECTION &

ANALYTICAL METHODS

Intentionally left blank

TABLE B-1:

XXYZ -

Location Designation and Identification System for the Limerick Generating Station 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.

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

Y S

A B

C D

on-site location 0-5,280 feet off-site 5,280-10,560 feet off-site 10,560-15,840 feet off-site 15,840-21,120 feet off-site E : 21,120-26,400 feet off-site F : 26,400-52,800 feet off-site G : 52,800-105,600 feet off-site H : 105,600-528,000 feet off-site Z

Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.

B-I

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2013 Location Location Description Distance & Direction From Site A.

Surface Water 13B1 Vincent Dam 24S1 Limerick Intake (control)

B.

Drinking (Potable) Water 9,225 feet SE 1,058 feet SW 15F4 15F7 16C2 28F3 AQUA Water Company Phoenixville Water Works Citizens Home Water Company Pottstown Water Authority (control)

C.

Milk - bi-weekly / monthly 10F4 18E1 19B1 23F1 Control 25Cl D.

Milk - quarterly 36E1 Control E.

Air Particulates / Air Iodine 45,514 feet SE 33,400 feet SSE 14,034 feet SSE 30,811 feet WNW 34,848 feet ESE 22,229 feet S 10,317 feet SSW 26,505 feet SW 14,224 feet WSW 24,816 feet N 10S3 11S1 11S2 13C1 14S1 15D1 22G1 6Cl Keen Road LGS Information Center LGS Information Center (quality control)

King Road Longview Road Spring City Substation Manor Substation (control)

Limerick Airport 2,648 feet E 2,017 feet ESE 2,017 feet ESE 14,980 feet SE 3,319 feet SSE 16,877 feet SE 93,619 feet SW 11,305 feet NE F.

Fish 16C5 29C1 Vincent Pool Pottstown Vicinity (control)

Downstream of Discharge Upstream of Intake G.

Sediment 1 6B2 16C4 33A2 Linfield Bridge Vincent Dam Upstream of Intake (control) 7,128 feet SSE 11,510 feet SSE 4,435 feet NNW H.

Broad Leaf Vegetation 11S3 13S3 31G1 LGS Information Center LGS 500 KV Yard Prout's Jollyview Farm (control) 1,848 feet ESE 1,267 feet SE 71,808 feet NW B-2

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2013 Location Location Description Distance & Direction From Site I. Environmental Dosimetry - OSLD Site Boundary 36S2 3S1 5S1 7S1 10S3 11IS1 13S2 14S1 18S2 21S2 23S2 25S2 26S3 29S1 31S1 34S2 Evergreen & Sanatoga Road Sanatoga Road Possum Hollow Road LGS Training Center Keen Road LGS Information Center 500 KV Substation Longview Road Rail Line along Longview Road Near Intake Building Transmission Tower Sector Site Boundary Met. Tower #2 Sector Site Boundary Sector Site Boundary Met. Tower #1 Intermediate Distance 36D1 2E1 4E1 7E1 10E1 1 0F3 13E1 16F1 19D1 20F1 24D1 25D1 28D2 29E1 31 D2 34E1 Siren Tower No. 147 Laughing Waters GSC Neiffer Road Pheasant Road Royersford Road Trappe Substation Vaughn Substation Pikeland Substation Snowden Substation Sheeder Substation Porters Mill Substation Hoffecker & Keim Streets W. Cedarville Road Prince Street Poplar Substation Vamell Road 3,183 feet N 2,301 feet NNE 2,350 feet NE 3,099 feet ENE 2,648 feet E 2,017 feet ESE 2,149 feet SE 3,319 feet SSE 1,390 feet S 977 feet SSW 2,793 feet SW 2,445 feet WSW 2,088 feet W 2,886 feet WNW 1,395 feet NW 3,071 feet NNW 18,527 feet N 25,112 feet NNE 25,221 feet NE 22,489 feet ENE 20,826 feet E 29,442 feet ESE 22,772 feet SE 26,608 feet SSE 18,439 feet S 27,648 feet SSW 20,972 feet SW 21,044 feet WSW 20,231 feet W 26,110 feet WNW 20,446 feet NW 24,243 feet NNW 130,742 feet NE 11,305 feet NE 11,377 feet E 14,980 feet SE 16,877 feet SE 8,462 feet S 16,157 feet SSW 15,853 feet WNW Control and Special Interest 5H1 6C1 9C1 13C1 15D1 17B1 20D1 31D1 Birch Substation (control)

Limerick Airport Reed Road King Road Spring City Substation Linfield Substation Ellis Woods Road Lincoln Substation B-3

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2013 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Water Gamma Spectroscopy Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis a continuous water radiological analysis (Limerick Generating compositor.

Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Surface Water Tritium Quarterly composite RMC-ER5 Collection of water samples for 500 ml TBE, TBE-2011 Tritium analysis in drinking water by liquid from a continuous water radiological analysis (Limerick Generating scintillation compositor.

Station)

Env. Inc., T-02 Determination of tritium in water (direct method)

Drinking Water Gross Beta Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2008 Gross Alpha and/or gross beta activity in a continuous water radiological analysis (Limerick Generating various matrices compositor.

Station)

Env. Inc., W(DS)-01 Determination of gross alpha and/or gross beta in water (dissolved solids or total residue)

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

Drinking Water 1-131 Monthly composite from RMC-ER10 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices a continuous water radiological analysis (Limerick Generating compositor.

Station)

Env. Inc., 1-131-01 Determination of 1-131 in water by an ion exchange Drinking Water Gamma Spectroscopy Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis a continuous water radiological analysis (Limerick Generating compositor.

Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Drinking Water Tritium Quarterly composite RMC-ER5 Collection of water samples for 500 ml TBE, TBE-2011 Tritium analysis in drinking water by liquid from a continuous water radiological analysis (Limerick Generating scintillation compositor.

Station)

Env. Inc., T-02 Determination of tritium in water (direct method)

Fish Gamma Spectroscopy Semi-annual samples RMC-ER6 Collection of fish samples for 1000 grams (wet)

TBE-2007 Gamma emitting radioisotope analysis collected via radiological analysis (Limerick Generating electroshocking or other Station)

Env. Inc., GS-01 Determination of gamma emitters by techniques gamma spectroscopy Sediment Gamma Spectroscopy Semi-annual grab RMC-ER7 Collection of sediment samples for 500 grams (dry)

TBE, TBE-2007 Gamma emitting radioisotope analysis samples radiological analysis (Limerick Generating Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Particulates Gross Beta One-week composite of RMC-ER8 Collection of air particulate and air 1 filter (approximately TBE, TBE-2008 Gross Alpha and/or gross beta activity in continuous air sampling iodine samples for radiological analysis 280 cubic meters various matrices through glass fiber filter (Limerick Generating Station) weekly) paper Env. Inc., AP-02 Determination of gross alpha and/or gross beta in air particulate filters B-4

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2013 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis each station (approximately 3600 Env. Inc., AP-03 Procedure for compositing air cubic meters)

Env. Inc., GS-01 Determination of gamma emitters by particulate filters for gamma spectroscopic gamma spectroscopy analysis Air Iodine Gamma Spectroscopy One-week composite of RMC-ER8 Collection of air particulate and air 1 filter (approximately TBE, TBE-2007 Gamma emitting radioisotope analysis continuous air sampling iodine samples for radiological analysis 280 cubic meters through charcoal filter (Limerick Generating Station) weekly)

Env. Inc., 1-131-02 Determination of 1-131 in charcoal canisters by gamma spectroscopy (batch method)

Milk 1-131 Bi-weekly grab sample RMC-ER10 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices when cows are on radiological analysis (Limerick Generating pasture. Monthly all Station)

Env. Inc., 1-131-01 Determination of 1-131 in milk by anion other times exchange Milk Gamma Spectroscopy Bi-weekly grab sample RMC-ER10 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on radiological analysis (Limerick Generating pasture. Monthly all Station)

Env. Inc., GS-01 Determination of gamma emitters by other times gamma spectroscopy OSLD Optically Stimulated Quarterly OSLDs RMC-ER9 Collection of dosimetry samples for 2 dosimeters Landauer Incorporated Luminescence comprised of two radiological analysis (Limerick Generating Dosimetry A120 3:C Landauer Station)

_____________Incorporated elements.

B-5

.~.--.-..

OUr, NN N-r NE

7.

w, 33A2 N

S2/

2961

\\

I*/-....

10S3 E

7'

/\\1S 7'l,')fS"

/

0, 25S I \\

\\

-0 7

0

\\S 1083 I"

0E SI

/14SSE "SW...

SSE s

Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2013 B-6

Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2013 B-7

U2~rc O

91 eNean NNW 00 0NE Figure B-Envionmnta Saplig LcatonsGretertha 26400Fee fro te LmeickGeerain Sttin, NE1 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, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 1381 24S1 12/31/12

- 04/01/13 04/01/13 - 07/01/13 07/01/13 - 09/30/13 09/30/13 - 12/30/13

< 194

< 191

< 195

< 176

< 192

< 190

< 191

< 164 (1)

MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-i

Table C-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 SITE COLLECTION PERIOD 13B1 12/31/12 - 01/29/13 01/29/13 - 02/26/13 02/26/13 - 04101/13 04/01/13 - 04/29/13 04/29/13 - 06/04/13 06/04/13 - 07/01/13 07/01/13 - 07/30/13 07/30/13 - 08/27/13 08/27/13 - 09/30/13 09/30/13 - 10129/13 10/29113 - 12/03/13 12/03/13 - 12/30/13 (1)

(1)

¢o MEAN

<4

<5

<4

<2

<5

<7

<4

<5

<3

<6

<5

<3

<5

<7

<6

<5

<4

< 4

<7

<6

<4

<2

<5

<8

<4

<6

<3

<6

<7

<4

<3

<6

<5

< 9

<8

<11

10

<10

<11

<5

<8

<10

< 15

< 10

<11

<7

<8

<12

<13

<9

<5

< 12

< 10

<19

13

<10

<5

<4

<5

<7

<5

<4

<2

<5

<6

<7

<5

<3

<4

<5

<6

<3

<6

<4

<7

<5

< 10

<9

10

<13

12

10

<10

<4

10

<10

<15

<10

<13

<5

<6

<11

<10

<9

<6

<12

<9

< 15

< 13

< 10

<6

<4

<5

<6

<4

<5

<2

<5

<7

<5

<6

<3

<6

<8

<4

<3

<6

<8

<5

<5 8

7 9

11 11 8

7 3

8 9

15 7

10 5

5 11 12 8

5 10 9

13 11 9

<8

<6

<8

<14

<9

<7

<3

< 12

<10

<13

< 10

<3

<4

<6

<5

<4

<2

<4

<7

<4

<5

<4

<5

<7

<6

<5

<4

<2

<4

<5

<8

<5

<6

<3

<4

<6

<8

<4

<3

<6

<5

<7

<6

<5

< 27

<16

21

32

< 27

< 21

21

<8

25

<19

< 39

< 20

28

<13

16

< 34

< 28

23

<13

< 26

29

< 35

32

< 26

<9

<5

<7

<11

< 12

<9

<7

<3

<6

<9

< 12

<8

<9

<5

<7

<8

< 12

<6

<5

<9

10

13

<9

<7 24S1 12/31/12 01/29/13 02/26/13 04/01/13 04/29/13 06/04/13 07/01/13 07/30/13 08/27/13 09/30/13 10/29/13 12/03/13 MEAN

- 01/29/13

- 02/26/13

- 04/01/13

- 04/29/13

- 06/04113

- 07/01/13

- 07/30/13

- 08/27/13

- 09/30/13

- 10/29/13

- 12/03/13

- 12/30/13 13 4

7 13 12 8

5 11 13 13 12 12

<7

<3

<6

<4

<3

<5

<4

<7

<5

<4 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 12/31/12 - 01/29/13 01/29/13 - 02/26113 02/26/13 - 04/01113 04/01/13 - 04/29/13 04/29/13 - 06/04/13 06/04/13 - 07/01/13 07/01/13 - 07/30/13 07/30/13 - 08/27/13 08/27/13 - 09/30/13 09/30/13 - 10/29/13 10/29/13 - 12/03/13 12/03/13 - 12/30/13 2.4 +/- 1.5

< 2.2 4.2 4.0 2.8 8.8 4.0

< 1.8 4.6 3.8 4.3 7.0 5.4

+

1.2 1.4 1.1 1.4 1.1 1.3 1.3 1.2 1.3 1.4 2.1 +/- 1.0 3.2 +/- 1.3 2.3 +/- 1.1 3.9 +/- 1.2 2.7 +/- 1.0 2.4 +/- 1.2 4.2 +/- 1.3 3.1 +/- 1.3 4.1 +/- 1.2 5.7 +/- 1.3 4.8 +/- 1.3 3.5 +/- 2.3 (1)

< 2.3

< 1.5 3.2 +/- 1.4

< 1.6 2.5 +/- 1.3 3.3 +/- 1.1 2.1 +/- 1.3 3.6 +/- 1.4 2.9 +/- 1.3 3.0 +/- 1.2 1.9 +/- 1.3 4.8 +/- 1.4 3.0 +/- 1.7

< 2.2 2.5 2.3 2.3 2.7 3.1

< 1.6 3.3 3.4 4.2 3.7 5.0

-+/-

+-

+/--

+-

+

+-

1.0 1.3 1.1 1.2 1.0 1.3 1.3 1.2 1.3 1.3 MEAN 4.7 +/- 3.7 3.2 t 1.7 Table C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 12/31/12 - 04/01/13 04/01/13 - 07/01/13 07/01/13 - 09/30/13 09/30/13 - 12/30/13

< 189

< 188

< 181

< 193

< 192

< 172

< 182 (1)

< 194

< 191

< 188

< 171

< 194

< 190

< 191

< 187

< 192 MEAN Table C-II.3 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 I

12/31/12 - 01/29/13 01/29/13 - 02/26/13 02/26/13 - 04/01/13 04/01/13 - 04/29/13 04/29/13 - 06/04/13 06/04/13 - 07/01/13 07/01/13 - 07/30/13 07/30/13 - 08/27/13 08/27/13 - 09/30/13 09/30/13 - 10/29/13 10/29/13 - 12/03/13 12/03/13 - 12/30/13

< 0.7

< 0.6

< 0.7

< 0.8

< 0.7

< 0.6

< 0.7

< 0.8

< 0.6

< 0.5

< 0.6

< 0.5

< 0.6

< 0.7

< 0.8

< 0.7

< 0.7 (1)

< 0.9

< 0.7

< 0.6

< 0.7

< 0.6

< 0.7

< 0.5

< 0.7

< 0.5

< 1.0

< 0.9

< 0.8

< 0.7

< 0.6

< 0.7

< 0.6

< 0.7

< 0.6

< 1.0

< 0.7

< 0.6

< 0.8

< 0.6 MEAN THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-3

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- SIGMA SITE COLLECTION PERIOD 15F4 12/31/12 - 01/29/13 01/29/13 - 02/26/13 02/26/13 - 04/01/13 04/01/13 - 04/29/13 04/29/13 - 06/04/13 06/04/13 - 07/01/13 07/01/13 - 07/30/13 07/30/13 - 08/27/13 08/27/13 - 09/30/13 09/30/13 - 10/29/13 10/29/13

- 12/03/13 12/03/13

- 12/30/13 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140

<9

<5

<6

< 6

<4

<5

<7

<6

<4

<8

<4

<5

<7

<6

<5

<6

<5

<4 MEAN

< 18

< 10

< 11

< 13

12

<5

10

10

<9

<14

<13

<9

<12

<6

<7

14

13

< 11

<8

< 11

< 13

< 12

<11

<8

<4

<5

<6

<5

<4

<5

<6

<4

<7

<8

<4

<6

<4

<6

<5

<4

<5

<7

<5

< 18

<9

10

<13

<10

<9

<10

<8

<6

13

14

<7

<8

<4

<5

<6

<4

<5

<4

<5

<6

<5

<6

<4

<6

<5

<6

<4

<5

<6

<5

<6

<4

< 15

<7

<10

<11

< 12

<8

<9

<8

<9

< 12

<8

< 10

<6

<8

<9

<6

<9

<10

<13

<11

<7

<4

<5

<6

<4

<5

<6

<4

<6

<3

<5

<6

<5

<3

<5

<4

<7

<5

<6

<5

<6

<5

<6

<8

<4

<5

<4

<6

<4

<6

<7

<5

< 32

< 20

22

30

< 24

27

23

22

< 26

28

< 31

23

28

<17

<21

< 30

< 28

30

17

27

<34

< 32

23

22

< 14

<7

<9

< 10

<8

<6

<9

<8

<9

< 11

< 10

<6

<9

<4

<5

<10

<9

<7

<5

<9

<8

12

10

<8 15F7 12/31/12

- 01/29/13 01/29/13 - 02/26/13 02/26/13 - 04/01/13 04/01/13 - 04/29/13 04/29/13 - 06/04/13 06/04/13 - 07/01/13 07/01/13 - 07/30/13 07/30/13 - 08/27/13 08/27/13 - 09/30/13 09/30/13 - 10/29/13 10/29/13 - 12103/13 12/03/13 - 12/30/13

<5

<4

<3

<6

<5 (1) < 3

<4

<5

<6

<5

<4

<5

<3

<4

<6

<5

<4

<5

<7

<5

< 10

<6

<11

<12

<10

<7

< 10

< 11

< 14

<9

<8 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 SITE COLLECTION PERIOD 16C2 12/31/12 - 01/29/13 01/29/13 - 02/26/13 02/26/13 - 04/01/13 04/01/13 - 04129/13 04/29/13 - 06/04113 06/04/13 - 07/01/13 07/01/13 - 07/30/13 07/30/13 - 08/27/13 08/27/13 - 09/30/13 09/30/13 - 10/29/13 10/29/13 - 12/03113 12/03/13 - 12/30/13 MEAN

<5

<3

<4

<5

<7

<4

<5

<7

<4

<6

<3

<4

<5

<4

<5

<6

<5

<6

<3

<6

<8

<7

<5

<4

<5

<9

<4

<7

<3

<4

<6

<5

<4

<5

<7

<5

<6

<5

<13

<7

<8

<12

< 15

<17

<9

< 10

< 11

< 13

< 12

<9

< 12

<7

<9

< 10

10

<10

<13

< 12

13

<6

<3

<6

<8

<4

<5

<4

<5

<6

<3

<6

<4

<5

<6

<5

<4

<5

<6

<5

<4

<11

<6

<7

12

< 17

12

<11

< 10

<6

< 11

< 17

<7

< 12

<5

<9

< 10

<9

<12

<14

<8

<11

<10

<7

<3

<6

<8

<7

<5

<7

<4

<7

<3

<4

<5

<6

<5

<4

<5

<7

<6

<5

<9

<6

< 10

15

14

<9

<8

<7

<9

< 12

<7

< 12

<5

<7

<9

< 10

<8

12

12

10

<11

<9

<5

<3

<6

<8

<6

<4

<5

<4

<6

<3

<4

<5

<6

<4

<5

<6

<5

<6

<5

<4

<6

<9

<7

<4

<5

<6

<7

<4

<6

<3

<5

<6

<4

<5

<7

<5

32

<14

<16

< 34

46

38

20

23

24

29

< 37

21

< 34

<14

21

<34

28

< 26

20

< 26

30

29

27

31

< 10

<5

<7

<9

13

12

<6

<8

<7

<13

<6

< 14

<5

<6

<9

<6

<7

<11

< 10

<11

<9 28F3 12/31/12 01/29/13 02/26/13 04/01/13 04/29/13 06104/13 07/01/13 07/30/13 08/27/13 09/30/13 10/29/13 12/03/13

- 01/29/13

- 02/26/13

- 04/01/13

- 04/29/13

- 06/04/13

- 07/01/13

- 07/30/13

- 08/27/13

- 09/30/13

- 10/29/13

- 12/03/13

- 12/30/13 MEAN

Table C-II1.1 CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH)

SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD 16C5 PREDATOR 06/06/13 10/22/13 MEAN 16C5 BOTTOM FEEDER 06/06/13 10/22/13 MEAN 29C1 PREDATOR 06/05/13 10/21/13 MEAN 29C1 BOTTOM FEEDER 06/05/13 10/21/13 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-134 Cs-137 4028 +/- 684

< 44 4824 +/- 1074

< 52 4426 +/- 1126 3871 +/- 952

< 68 4535 +/- 942

< 73 4203 +/- 939 3957 +/- 935

< 61 3061 +/- 908

< 65 3509 +/- 1267 3096 +/- 771

< 41 4247 +/- 894

< 51

< 37

< 59

< 104

< 170

< 47

< 46

< 95

< 87

< 105

- 379

< 37

< 47

< 45

< 61

< 67

< 73

< 137

< 150

< 71

< 67

< 101

< 142

< 148

< 417

< 62

< 55

< 59

< 68

< 61

< 82

< 115

< 182

< 59

< 82

< 148

< 138

< 178

< 427

<54

< 59

< 58

< 68

<42

< 64

< 81

< 137

< 45

< 42

<86

< 112

< 116

< 393

< 37

< 42

< 36

< 40 MEAN 3672 +/- 1628

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 SITE COLLECTION PERIOD 1682 06/06/13 10/30/13 MEAN 16C4 06/06/13 10/30/13 MEAN 33A2 06/06/13 10/30/13 MEAN Cs-1 37 4701 +/- 1222 4952 +/- 1377 4827 +/- 355 5637 +/- 860

< 1466 2736 +/- 884

< 1096 16840 +/-

19190 +/-

18015 +/-

16990 +/-

18370 +/-

17680 +/-

16580 +/-

14370 +/-

15475 +/-

1999 2737 3323 1580 2053 1952 2090 1870 3125

< 111

137

< 90

< 120

81

104

109

145

< 79

127

86

115

< 131

< 340

< 109

< 771

< 111

124

132

< 99

261

< 744

327

< 649

< 97

< 123

82

< 111

84

< 99

< 106

< 169 173 +/- 69

< 154

< 106

< 114

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD GROUP I 1151 GROUP 11 6C1 13C1 (2)

IGROUP III 22G1 10S3 14S1 15D1 12/31/12 01/06/13 01/14/13 01/22/13 0 1/29/13 02/04/13 02/11/13 02/19/13 02/25/13 03/04/13 03/11/13 03/18/13 03/26/13 04/01/13 04/08/13 04/15/13 04/22/13 04/29/13 05/06/13 05/13/13 05/20/13 05/28/13 06/03/13 06/10/13 06/17/13 06/24/13 07/01/13 07/08/13 07/15/13 07/22/13 07/29/13 08/05/13 08/12/13 08/19/13 08/26/13 09/03/13 09/09/13 09/16/13 09/23/13 09/30/13 10/07/13 10/15/13 10/21/13 10/28/13 11/04/13 11/11/13 11/18/13 11/25/13 12/02/13 12/09/13 12/16/13 12/23/13

-01/06/13

-01/14/13

-01/22/13

-01/29/13

-02/04/13

-02/11/13

-02/19/13

-02/25/13

-03/04/13

-03/11/13

-03/18/13

-03/26/13

-04/01/13

-04/08/13

-04/15/13

-04/22/13

-04/29/13

-05/06/13

-05/13/13

-05/20/13

-05/28/13

-06/03/13

-06/10/13

-06/17/13

-06/24/13

-07/01/13

-07/08/13

-07/15/13

-07/22/13

-07/29/13

-08/05/13

-08/12/13

-08/19/13

-08/26/13

-09/03/13

-09/09/13

-09/16/13

-09/23/13

-09/30/13

-10/07/13

-10/15/13

-10/21/13

-10/28/13

-11/04/13

-11/11/13

-11/18/13

-11/25/13

-12/02/13

-12/09/13

-12/16/13

-12/23/13

-12/30/13 25 +/- 7 27 +/- 5 19 +/- 5 19 +/- 5 26 +/- 6 20 +/- 5 14 +/-5 11 +/-6 7+/-5 9+/-5 17 +/-5 16 +/-3 13 +/-5 15 +/-5 11 +/-5 14 +/-5 12 +/-5 7+/-5 10 +/-5 11 5

15 +/- 5 15 +/- 6 9+/-5 11 +/-5 13 5

16 +/-5 9+/-4 15 +/-4 20 +/-5 9+/-5 15 +/-5 17 +/-5 16 +/-5 13 +/-5 21 +/-5 11 +/-6 29 +/-6 15 +/-5 15 5

35 +/-6 16 +/-4 24 +/-6 15 +/-5 24 +/-6 10 +/-5 16 +/-5 15 +/-5 21 5

36 +/-6 23 5

23 +/-6 16 +/-5 27 +/- 7 33 +/- 5 18 +/- 5 22 +/- 5 23 +/- 6 (1) 11 +/-4

< 8 7+/-5 7+/-4 15 +/-5 17 +/-3 8+/-5 15 +/-5 11 +/-5 15 +/-5 14 +/-5 7+/-5

< 6 10 11 16 9

8 11 18 9

10 20 10 15 16 14 20 27 9

24 16 12 34 15 17 14 29 12 15 13 20 34 22 22 17

+/-6

+/-4

+/-6

+/-4

+/-5

+/-6

+/-5

+/-4

+/-5

+/-6

+/-5

+/-6

+/-5

+/-6

+/-4

+/-6

+/-5

+/-6

+/-5

+/-6

+/-5

+/-6

+/-5 30 +/- 7 31 +/- 5 21 +/- 5 24 +/-5 23 +/-6 22 +/-8 13 +/-6 11 +/-6 7+/-5 8+/-5 17 +/-5 14 +/-3 10 5

14 +/-5 15 +/-5 13 5

14 +/-5 11 +/-5 7+/-4 9+/-5 13 +/-4 17 +/-6 10 +/-5 11 +/-5 15 +/-5 18 +/- 6 13 +/- 5 11 +/-4 20 +/-5 10 +/-5 21 +/-6 15 +/-5 15 +/-5 16 +/-5 25 +/-5 12 +/-6 23 +/-6 14 +/-5 10 +/-5 36 +/- 6 22 +/- 5 21 +/- 6 16 +/- 5 20 +/- 6 10 +/- 5 15 +/- 5 20 +/- 5 17 +/- 5 33 +/- 6 27 +/- 6 25 +/- 6 20 +/- 6 26 29 16 20 26 19 20

< 8

+/-7

+/-5

+/-6

+/-5

+/-5 8+/-5 11 +/-5 15 +/-5 13 +/-5 14 +/-5 12 +/-5 10 +/- 5 14 +/- 5 12 +/- 5 9+/-4 15 +/-5 12 +/-4 18 +/-6 13 +/-5 11 5

11 +/-5 13 +/-5 11 +/-5 11 +/-4 22 +/-5 11 +/-5 17 5

11 +/-5 15 +/-5 18 5

26 +/-5 10 +/- 6 29 +/- 6 13 5

13 +/-5 35 +/-6 17 +/-4 20 +/-6 11 +/- 5 22 +/-6 8+/-5 18 +/-5 11 +/-5 19 +/-5 34 +/-6 25 +/- 5 21 +/- 6 12 +/- 5 26 28 17 15 19 20 14

< 9

< 7 17 13 19

+/-7

+/-5

+/-6

+/-5

+/-3 26 +/- 7 29 +/- 5 19 +/- 5 21 +/- 5 27 +/- 6 22 +/- 5 14 +/- 5 10 +/- 6 12 +/- 5 16 +/-5 17 +/-5 20 +/-3 9+/-5 13 +/-5 12 +/-5 12 +/- 5 13 +/- 5 12 +/- 5

<6 12 +/- 5 16 +/- 5 17 +/- 6 9+/-5 13 +/-5 11 +/-5 20 +/-6 10 +/-4 14 +/-5 11 5

12 5

15 +/-5 15 +/-5 15 5

21 5

10 5

24 +/- 6 14 +/- 5 14 +/- 5 31 +/- 6 17 +/- 5 17 +/- 6 16 +/- 5 23 +/- 6 13 +/- 5 15 +/- 5 14 +/- 5 16 +/- 5 34 +/-6 26 +/-6 21 +/-5 12 +/-5 23 +/- 7 30 +/- 5 16 +/- 5 17 +/- 5 24 +/- 6 20 +/- 5 15 +/- 5 11 +/-6 7+/-5 12 +/-5 16 +/-5 18 +/-3 11 +/-5 25 +/- 6 13 +/- 5 17 5

11 5

12 +/-5 11 +/-5 11 +/-5 15 +/-5 17 +/- 6 10 +/- 5 9+/-5 12 5

17 +/-6 9+/-5 13 +/-4 23 +/-5 10 +/-5 16 +/-5 11 +/-5 16 +/-5 20 +/-5 30 +/-5 13 +/-6 18 +/-6 11 +/-5 31 +/-6 16 +/- 4 20 +/- 6 13 +/- 5 23 +/- 6 9+/-5 17 +/-5 13 +/-5 21 +/-5 30 +/-6 23 +/- 5 18 +/- 5 19 +/- 5 MEAN 17 +/-13 16 +/-14 17 +/-13 17 +/-13 19 +/-10 17 +/-12 16 +/-12 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2) SEE PROGRAM CHANGES 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, 2013 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 PERIOD MIN MAX MEAN+/-

2sD COLLECTION PERIOD MIN MAX MEAN+

2cSf COLLECTION PERIOD 2SD 12/31/12 01/29/13 03/04/13 04/01/13 04/29/13 06/03/13 07/01/13 07/29/13 09103/13 09/30/13 11/04/13 12/02/13 01129/13 03/04/13 04/01/13 04/29/13 06/03/13 07/01/13 07/29/13 09/03/13 09/30/13 11/04/13 12/02/13 12130/13 18 7

7 11 7

8 9

13 9

14 10 16 33 26 17 15 17 18 20 27 29 36 21 36 25 +/- 10 15 +/- 13 12 +/- 8 14 +/- 3 11 +/-6 12+/- 7 13+/- 9 18+/- 8 16 +/- 13 22 +/- 15 15 7

25 +/- 13 12/31/12 01/29/13 03/04/13 04/01/13 04/29/13 06/03/13 07/01/13 07/29/13 09103/13 09/30/13 11/04/13 12/02/13 01/29/13 03/04/13 04/01/13 04/29/13 06/03/13 07/01/13 07/29/13 09/03/13 09/30/13 11/04/13 12/02/13 12/30/13 15 8

9 10 9

9 10 11 10 11 8

12 29 27 20 14 18 20 22 26 29 35 19 34 23 18 15 13 14 13 13 17 16 21 14 23

+/- 10

+/- 12

+/-7

+/-3

+/-6

+/-8

+/-9

+ 14

+/-15

+/-7

+/- 16 12/31/12 01/29/13 03/04/13 04/01/13 04/29/13 06/03/13 07/01/13 07/29/13 09/03/13 09/30/13 11/04/13 12/02/13 01/29/13 03/04/13 04/01/13 04/29113 06/03/13 07/01/13 07/29/13 09/03/13 09/30/13 11/04/13 12/02/13 12/30/13 MIN MAX MEAN+

2SD 16 30 22 +/- 13 7

24 15 +/- 14 11 18 14 +/- 7 11 25 17 +/- 13 11 17 13 +/- 6 9

17 12 +/- 7 9

23 14 +/- 13 11 30 19 +/- 15 11 18 14 +/- 7 13 31 21 +/- 14 9

21 15 +/- 10 18 30 23 +/- 11 12/31/12 - 12/30/13 7

36 17 +/- 13 12/31/12 - 12/30/13 8

35 17 +/- 12 12/31/12 - 12/30/13 7

31 16 +/- 12

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD 10S3 12/31/12 - 04/01/13 04/01/13 - 07/01/13 07/01/13 - 09/30/13 09/30/13 - 12/30/13 MEAN 11S1 12/31/12 - 04/01/13 04/01/13 - 07/01/13 07/01/13 - 09/30/13 09/30/13 - 12/30/13 MEAN 13C1 12/31/12 - 03/26/13 04/01/13 - 07/01/13 07/01/13 - 09/30/13 09/30/13 - 12/30/13 Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137

< 42 95 +/- 36 81 +/- 28 63 +/- 22 80 +/- 32 62 +/- 29 85 +/- 31 67 +/- 22 79 + 30 73 + 21

< 3

<4

<2

<3

<4

<3

<4

<5

<4

<3

<5

<4

<5

< 3

<5

<3

<2

<3

<4

<3

<4

<3

<5

<3

<4

<3

<5

<3

<4

<5

<2

<3

<2

<4

<3 64 +/- 25

< 3

<6 (2)

(2)

MEAN 14S1 12/31/12 - 04/01/13 04/01/13 - 07/01/13 07/01/13 - 09/30/13 09/30/13 - 12/30/13 MEAN 15D1 12/31/12 - 04/01/13 04/01/13 - 07/01/13 07/01/13 - 09/30/13 09/30/13 - 12/30/13 MEAN 22G1 12/31/12 - 04/01/13 04/01/13 - 07/01/13 07/01/13 - 09/30/13 09/30/13 - 12/30/13 MEAN 6C1 12/31/12 - 04/01/13 04/01/13 - 07/01/13 07/01/13 - 09/30/13 09/30/13 - 12/30/13 80 +/- 35 87 +/- 28 72 +/- 30 61 +/- 24 75 +/- 22 62 +/- 30 90 +/- 41 83 +/- 34 84 + 22

<4

<3

<5

<3

<4

<5

<4

<6

<3

<6

<4

<3

<6

<3

<4

<5

<3

<4

<3

<6

<3

<4

<5

<4

<3

<2

<4

<3

<3 80 +/- 24 42 +/- 24 73 +/- 22 85 +/- 31 84 +/- 31

<3

<2

<3

<4

<3

<2

<3

<4

<3

<2

<3 71 +/- 40 93 +/- 31 73 +/- 22 71 +/- 34 85 +/- 29 81 +/- 21

<4

<3

<2

<4

<3

<4

<3

<4

<3

<2

<4

<3

<2

<3 MEAN THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-1O

Table C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I IGROUP 11 GROUP III PERIOD 10S3 iiSi 1451 601 13C1 (2) 15131 22G 1 12/31/12 -01/06/13

< 58

< 42

< 24

< 59

< 43

< 43 01/06/13 - 01/14/13

< 23

< 39

< 23

< 24

< 40

< 40 01/14/13 -01/22/13

< 21

< 49

< 43

< 48

< 50

< 43

< 43 01/22/13 -01/29/13

< 26

< 20

< 26

< 21

< 21 01/29/13 -02/04/13

< 36

< 13

< 35

< 36

< 37

< 35

< 35 02/04/13 - 02/11/13

< 45 (1)

< 60

< 44

< 45

< 40

< 40 02/11/13 - 02/19/13

< 26

< 32

< 25

< 10

< 25

< 25 02/19/13 -02/25/13

< 49

< 34

< 49

< 50

< 34

< 34 02/25/13 -03/04/13

< 24

< 10

< 24

< 25

< 25 03/04/13 - 03/11/13

< 27

< 32

< 26

< 27

< 32

< 32 03/11/13 -03/18/13

< 21

< 29

< 21

< 30

< 12

< 29 03/18/13 - 03/26/13

< 25

< 42 (1)

< 25

< 43

< 43 03/26/13 - 04/01/13

< 32

< 27

< 32

< 27

< 10 04/01/13 - 04/08/13

< 21

< 28

< 21

< 28

< 28 04/08/13 - 04/15/13

< 31

< 13

< 33

< 32 04/15/13 - 04/22/13

< 18

< 29

< 18

< 29

< 29 04/22/13 - 04/29/13

< 11

< 30

< 21

< 29

< 21

< 21 04/29/13 - 05/06/13

< 43

< 44

< 44 05/06/13 - 05/13/13

< 23

< 12

< 23

< 31

< 30 05/13/13 - 05/20/13

< 16

< 19

< 16

< 16 05/20/13 - 05/28/13

< 34

< 59

< 33

< 21

< 59 05/28/13 - 06/03/13

< 44

< 38

< 43

< 39

< 38 06/03/13 - 06/10/13

< 61

< 49

< 61

< 50

< 21 06/10/13 - 06/17/13

< 28

< 27

< 32

< 27

< 32

< 32 06/17/13 - 06/24/13

< 33

< 34

< 29

< 15

< 28

< 29 06/24/13 - 07/01/13

< 20

< 21

< 27

< 20

< 26

< 26 07/01/13 - 07/08/13

< 66

< 69

< 65

< 67

< 62

< 65 07/08/13 - 07/15/13

< 58

< 59

< 56

< 59

< 56

< 55 07/15/13 -07/22/13

< 53

< 54

< 61

< 53

< 58

< 60 07/22113 -07/29/13

< 37

< 38

< 43

< 37

< 42

< 42 07/29/13 - 08/05/13

< 41

< 42

< 39

< 42

< 38

< 39 08/05/13 - 08/12/13

< 59

< 61

< 48

< 60

< 46

< 47 08/12113 -08/19/13

< 47

< 48

< 47

< 48

< 19

< 47 08/19/13 - 08/26/13

< 62

< 63

< 56

< 62

< 54

< 54 08/26/13 - 09/03/13

< 21

< 30

< 21

< 29

< 16 09/03/13 -09/09/13

< 54

< 56

< 49

< 55

< 47

< 48 09/09/13 - 09/16/13

< 18

< 19

< 6

< 19 (1) 09/16/13 - 09/23/13

< 36

< 37

< 52

< 37

< 50

< 60 09/23/13 - 09/30/13

< 56

< 58

< 53

< 57

< 51

< 52 09/30/13 -

10/07/13

< 55

< 56

< 36

< 55

< 35

< 35 10/07/13-10/15/13

< 45

< 46

< 35

< 45

< 35

< 34 10/15/13 -

10/21/13

< 61

< 63

< 48

< 62

< 47

< 49 10/21/13 -

10/28/13

< 48

< 50

< 62

< 49

< 62

< 61 10/28/13-11/04/13

< 52

< 53

< 50

< 52

< 48

< 49 11/04/13-11/11/13

< 32

< 33

< 29

< 32

< 28

< 28 11/11/13-11/18/13

< 52

< 53

< 60

< 52

< 59

< 58 11/18/13-11/25/13

< 38

< 39

< 55

< 39

< 60

< 21 11/25/13 -

12/02/13

< 66

< 68

< 70

< 67

< 68 12/02113 -12/09/13

< 51

< 52

< 51

< 20

< 49

< 50 12/09/13 -

12/16/13

< 61

< 63

< 49

< 62

< 48

< 49 12/16/13 -

12/23/13

< 45

< 46

< 43

< 46

< 41

< 42 12/23/13 -

12/30/13

< 57

< 58

< 63

< 57

< 61

< 63 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-1Il

Table C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM 36E1 INDICATOR FARM COLLECTION PERIOD 23F1 10F4 18E1 19B1 25C1 01/08/13 02/12/13 03/13/13 04/03/13 04/16/13 04/30/13 05/14/13 05/28/13 06/11/13 06/25/13 07/09/13 07/23/13 08/06/13 08/20/13 09/03/13 09/17/13 10/01/13 10/15/13 10/29/13 11/12/13 11/25/13 12/10/13

<0.6

< 0.7

< 0.6

< 0.8

< 0.7

< 0.6

< 0.7

< 0.5

< 0.8

< 0.6

< 0.5

< 0.6

< 0.5

< 1.0

< 0.6

< 0.5

<0.7

< 0.8

< 0.9

< 0.8

< 0.9 (2)

< 0.7

< 0.8

< 0.5

< 0.4

< 0.7

< 0.6

< 0.7

< 0.6

< 0.5

< 0.7

< 0.6

< 0.7

< 0.8

< 0.5

< 0.6

< 0.7

< 0.6

< 0.8

< 0.6

< 0.7

< 0.6

< 0.8

< 0.7

< 0.4

< 0.8

< 0.6

< 0.5

< 0.6

< 0.7

< 0.8

< 0.7

< 0.8

< 0.7

< 0.8

< 0.9

< 0.8

< 0.7

< 0.8

< 0.6

< 0.8

< 0.7

< 0.6

< 0.9

< 0.5

< 0.6 MEAN (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-12

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 1Ui14 U1iUW/13 02/12/13 03/12/13 04/03/13 04/16/13 04/30/13 05/14/13 05/28/13 06/11/13 06/25/13 07/09/13 07/23/13 08/06/13 08/20/13 09/03/13 09/17/13 10/01/13 10/15/13 10129/13 11/12/13 11/25/13 12/10/13 MEAN 18E1 01/08/13 02/12/13 03/12/13 04/03/13 04/16/13 04/30/13 05/14/13 05/28/13 06/11/13 06/25/13 07/09/13 07/23/13 08/06/13 08/20/13 09/03/13 09/17/13 10/01/13 10/15/13 10/29/13 11/12/13 11/25/13 12/10/13 MEAN 1168 +/- 100 1223 +/- 175 1405 +/- 155 (2) 1265 + 248

<4

<7

<5

<8

<5

< 25

< 36

< 27

<7

< 12

<7 1210 1308 1198 1108 1277 1170 1231 1384 1199 1280 1243 1199 1341 1198 1328 1383 1389 1379 1260 1188 1350 1160 152 179 143 151 134 185 116 118 168 166 163 158 123 126 143 173 176 58 138 104 180 124

<5

<7

<6

<8

<6

<8

<4

<7

<5

<6

<4

<5

<7

<2

<5

<4

<6

.<4

<6

<7

<6

<8

<6

<8

<5

<8

<7

<5

<6

<7

<2

<6

<4

<5

<6

< 31

< 37

< 29

< 43

< 31

< 46

< 36

< 24

< 40

< 34

< 31

< 37

< 30

< 38

< 46

< 27

< 52

< 23

< 50

< 25

< 11

<9

< 11

<9

< 12

< 13

< 12

<7

< 11

<9

< 12

<7

< 10

< 14

< 11

<9

<7

<8

< 15

< 13

<7 1263 +/- 168 (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-13

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD 19B1 01/08/13 02/12/13 03/12/13 04/02/13 04/16/13 04/30/13 05/14/13 05/28/13 06/11/13 06/25/13 07/09/13 07/23/13 08/06/13 08/20/13 09/03/13 09/17/13 10/01/13 10/15/13 10/29/13 11/12/13 11/25/13 12/10/13 MEAN 23F1 01/08/13 02/12/13 03/13/13 04/02/13 04/16/13 04/30/13 05/14/13 05/28/13 06/11/13 06/25/13 07/09/13 07/23/13 08/06/13 08/20/13 09/03/13 09/17/13 10/01/13 10/15/13 10/29/13 11/12/13 11/25/13 12/10/13 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1253 +/-

1146 +/-

1295 +/-

1387 +/-

1272 +/-

1297 +/-

1276 +/-

1357 +/-

1341 +/-

1437 +/-

1206 +/-

1204 +/-

1457 +/-

1324 +/-

1339 +/-

1315 +/-

1256 +/-

1258 +/-

1257 +/-

1211 +/-

1434 +/-

1314 +/-

116 161 131 130 153 151 168 150 153 123 155 156 180 158 153 163 117 55 176 91 164 139 1302 +/- 160

<4

<5

<6

<7

<5

<7

<4

<6

<7

<5

<2

<8

<4

<6

<5

<7

<5

<4

<6

<5

<6

<5

<6

<7

<6

<5

<6

<4

<2

<5

<4

<6

<5

<7

<5

<8

<7

<6

<7

<5

<2

<8

<4

<8

<7

<5

<8

<5

<6

<5

<7

<6

<8

<6

<7

<8

<4

<2

<7

<5

<8

<5

26

32

26

27

< 42

31

51

31

< 37

30

< 33

36

< 47

< 44

< 34

22

< 39

< 44

< 49

31

30

< 37

28

28

<34

36

46

< 33

29

< 33

32

< 44

< 47

< 45

< 37

29

<19

< 34

50

< 47

< 24

<8

<12

10

<9

<15

<8

15

<10

<8

<9

<11

<9

<12

14

<13

10

<9

<7

<13

<15

14

12

<8

< 10

<9

10

<13

14

<9

<7

<11

< 10

<5

14

<13

<12

< 10

<9

<6

<8

<15

<11

<7 1247 1189 1279 1319 1212 1351 1344 1389 1312 1422 1204 1341 1264 1318 1371 1368 1370 1337 1286 1253 1229 1136 120 160 145 108 121 158 166 138 133 136 146 151 168 136 140 182 123 51 138 99 162 108 1297 +/- 147 C-14

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD 25C1 01/08/13 02/12/13 03/12/13 04/02/13 04/16/13 04/30/13 05/14/13 05/28/13 06/11/13 06/25/13 07/09/13 07/23/13 08/06/13 08/20/13 09/03/13 09/17/13 10/01/13 10/15/13 10/29/13 11/12/13 11/25/13 12/10/13 MEAN 36E1 01/08/13 04/02/13 07/09/13 10/01/13 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1165 1243 1287 1374 1269 1275 1278 1290 1333 1282 1515 1303 1368 1169 1277 1261 1330 1337 1269 1228 1309 1222

+/- 125

+/- 178

+/- 135

+/- 128

+/- 130

+/- 135

+/- 121

+/- 147

+ 146

+ 136

_ 171

- 140

_ 144

+ 144

+ 145

+ 168

+/- 123

+/- 52

+/- 140

+/- 105

+/- 159

+/- 107

<4

<6

<5

<6

<5

<7

<4

<6

<5

<6

<7

<6

<4

<2

<6

<4

<6

<4

<5

<3

<4

<6

<5

<8

<6

<5

<7

<5

<6

<9

<6

<8

<6

<7

<8

<7

<8

<5

<2

<6

<4

<7

<5

<6

<4

<5

<7

27

30

28

26

< 39

36

< 37

< 33

41

29

< 45

32

< 37

52

51

26

< 34

21

27

< 46

< 49

25

26

23

22

< 35

<8

< 10

<8

<9

<11

<9

<8

<10

<9

<8

<9

12

10

10

<6

<9

15

<15

<6

< 10

<8

<7

< 12 1290 +/- 147 1107 1302 1239 1107

+/- 119

+/- 102

+/- 108

+/- 146 1189 +/- 196 C-15

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCIIKG WET +/- 2 SIGMA SITE COLLECTION PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 11S3 U06M8di/3 06/18/13 06/18/13 07/16/13 07/16/13 07/16/13 08/19/13 08/19/13 08/19/13 09/09/13 09109/13 10/15/13 10/15/13 MEAN Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Cabbage Zucchini Leaves Swiss Chard Swiss Chard Zuchinni Leaves Swiss Chard Zucchini Leaves Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Zucchini Leaves Collards Swiss Chard Collards Swiss Chard Zucchini Leaves Collards Swiss Chard Zucchini Leaves 139 +/- 99

< 133 122 +/- 80

< 231 260 +/- 222 485 +/- 175

164 498 +/- 238

209 286 +/- 159 691 +/- 193 606 +/- 110 2384 +/- 124 5695 +/- 315 5641 +/- 379 3889 +/- 254 2736 +/- 528 5724 +/- 699 7245 +/- 619 2039 +/- 386 4689 +/- 486 7354 +/- 567 5522 +/- 497 5294 +/- 537 5197 +/- 226 5331 +/- 195 608 +/- 1391 5104 +/- 3033

< 14

<14

< 10

25

28

22

< 16

< 22

21

19

23

<8

22

<14

19

18

20

27

23

<19

23

28

17

< 24

<7

<8

< 12

<13

<10

26

30

25

18

23

21

19

< 20

<10

21

<13

<18

< 24

< 26

22

< 26

21

22

23

< 18

26

<8

< 10

<9

< 15

20

<12

28

< 35

31

<21

< 24

28

25

30

<10

10

27

18

23

24

< 30

30

27

< 30

< 29

< 24

< 34

<9

10

<10

< 27

< 30

< 21

< 47

< 53

< 45

< 37

< 39

< 43

< 59

<54

52

< 60

< 46

30

< 39

< 43

52

<56

52

< 44

< 47

< 59

< 45

< 59

< 53

<54

52

< 13

14

<9

22

< 24

< 18

23

20

20

20

<7

<8

23

13

17

20

20

21

24

21

19

23

< 17

< 24

<7

< 13

16

<11

< 21

< 33

25

20

24

< 26

21

24

<8

<9

< 20

<16

< 18

<21

24

26

< 26

23

< 23

< 32

< 13

22

<7

<8 13S3 06/18/13 06/18/13 06/18/13 07/16/13 07/16/13 07/16/13 08/19/13 08/19/13 08/19/13 09/09/13 09109/13 09/09/13 10/15/13 10/15/13 10/15/13

200

< 141 311 +/- 139

< 254

< 216 394 +/- 298 556 +/- 233 314 +/- 155 309 +/- 164

< 249 255 +/- 178 813 +/- 234 2099 +/- 146 584 +/- 99 1841 +/- 108 3459 +/- 429 3681 +/- 331 6148 +/- 474 3505 +/- 480 4000 +/- 562 6507 +/- 603 5392 +/- 578 3453 +/- 508 5549 +/- 503 4463 +/- 677 5621 +/- 484 5577 +/- 613 5951 +/- 261 5536 +/- 220 5011 +/- 193

< 337

307

238

568

524

458

348

463

450

541

478 198 +/- 147

175 695 +/- 491 272 +/- 240 875 +/- 430 1081 +/- 497

614 2099 +/- 581

467

548 1501 +/- 522

< 594 1037 +/- 545

571 1657 +/- 275 1164 +/- 184 223 +/- 151 1060 +/- 1179

26

23

18

< 43

38 53 +/- 41

29

32

< 37

< 43

< 35 17 +/- 13

14

< 56

71

< 45

104

120

< 96

< 82

< 106

< 94

83

87

< 33

38 35 +/- 51

< 40

21

< 33

< 43

< 42

51

< 47

< 39

< 37

< 49

32

< 43

17

<15

13

< 81

58

< 81

76

< 95

115

< 95

104

92

< 115

< 73

< 102

< 36

< 33

< 32 MEAN 748 +/- 1338 4924 +/- 2131 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD 31G1 06/18/13 Cat 06/18/13 Bro.

06/18/13 Swi 07/16/13 Cat 07/16/13 Bru 07/16/13 Swi 08/19/13 Cat 08/19/13 Zuc 08/19/13 Swi 09/09/13 Cat 09/09/13 Kali 09/09/13 Swi 10/15/13 Cat 10/15/13 Kali 10/15/13 Swi Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 bage ccoli Leaves ss Chard bage ssel Sprout Leaves ss Chard bage chini Leaves ss Chard bage e

ss Chard bage ess Chard

< 147 436 +/- 128 259 +/- 149 364 +/- 143

260 284 +/- 205

< 181 820 +/- 202

229

188 368 +/- 161 255 +/- 164

< 63 386 +/- 69 6680 +/- 171 3934 +/- 305 4604 +/- 371 6802 +/- 506 4128 +/- 442 5339 +/- 526 7847 +/- 695 5270 +/- 553 3946 +/- 494 6849 +/- 624 4900 +/- 414 7057 +/- 508 8809 +/- 686 3624 +/- 153 6352 +/- 206 5059 +/- 203

12

<13

21

< 20

20

28

<19

23

< 22

< 18

<19

24

<6

<8

<7

14

<15

<18

20

20

< 24

23

< 21

< 17

<19

30

<6

<9

<8

< 17

<19

< 26

27

< 26

32

25

< 26

25

< 19

< 26

31

<7

<10

10

< 33

< 27

< 37

< 44

< 55

< 42

< 46

<46

< 41

< 40

< 45

< 57

< 39

52

<56

< 15

< 12

19

< 22

25

< 24

< 23

< 21

< 20

16

< 18

21

<5

<7

< 15

15

< 21

< 25

23

25

< 23

< 22

< 20

21

< 22

<6

<8

350

310

372

564

< 599

512

< 537

563

< 466

431

450

< 493

124

158

200

26

25

< 27

< 41

< 49

< 43

< 44

< 47

36

27

32

< 40

10

14

16

< 59

< 63

91

83

< 102

102

83

< 94

< 102

< 69

< 96

87

< 26

< 32

< 31

-4 MEAN 1095 +/- 4203 5635 +/- 3142 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-IX.1 QUARTERLY OSLD RESULTS FOR LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF MREM/STANDARD MONTH +/-2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE

+/- 2 S.D.

2E1 10.9 + 1.4 9.9 +/- 0.4 11.3 +/- 1.0 10.9 +/- 0.8 11.4 +/- 1.6 3S1 9.2 +/- 3.0 10.3 +/- 0.4 8.0 +/- 1.1 10.7 +/- 0.7 7.8 +/- 1.0 4E1 10.2 +/- 3.8 8.4 +/- 0.4 11.8 +/- 0.8 8.7 +/- 2.4 11.9 +/- 2.9 5Hi 11.6 +/- 1.2 12.0 +/- 0.1 11.0 +/- 0.2 12.3 +/- 1.4 11.2 +/- 0.6 5S1 10.7 +/- 1.4 11.5 +/- 0.1 10.1 +/- 0.1 11.1 +/- 0.0 10.2 +/- 0.2 6C1 10.4 +/- 0.8 9.8 +/- 0.2 10.4 +/- 0.9 10.8 +/- 2.6 10.4 +/- 0.4 7E1 10.6 +/- 1.5 10.2 +/- 1.1 10.1 +/- 0.1 11.7 +/- 0.2 10.4 +/- 0.5 7S1 10.2 +/- 1.2 10.4 +/- 1.1 10.3 +/- 1.0 10.8 +/- 0.1 9.4 +/- 0.3 9Cl 9.7 +/- 0.9 9.8 +/- 0.3 9.5 +/- 0.4 10.2 +/- 0.1 9.2 +/- 0.1 10E1 10.4 +/- 0.5 10.6 +/- 0.1 10.0 + 0.6 10.5 +/- 0.8 10.3 +/- 0.7 10F3 9.9 +/- 0.7 9.9 +/- 0.6 9.9 +/- 1.2 10.2 +/- 0.1 9.4 +/- 2.3 10S3 10.1 + 0.3 10.2 +/- 0.6 9.9 +/- 0.8 10.2 +/- 0.4 10.0 +/- 2.1 1iSi 11.4 +/- 0.3 11.2 +/- 0.6 11.3 +/- 2.0 11.5 +/- 1.1 11.4 +/- 0.4 13C1 8.0 +/- 0.4 8.1 +/- 0.1 7.7 +/- 0.4 8.2 +/- 0.1 8.0 +/- 0.6 13E1 10.1 +/- 0.4 10.0 +/- 0.8 10.2 +/- 1.4 10.3 +/- 1.6 9.9 +/- 0.1 13S2 13.4 +/- 0.6 13.6 +/- 0.7 13.0 +/- 2.3 13.7 +/- 1.4 13.3 +/- 1.2 14S1 9.3 +/- 0.3 9.2 +/- 0.5 9.4 +/- 1.6 9.1 +/- 0.3 9.3 +/- 0.9 15D1 10.7 +/- 0.8 10.4 +/- 0.4 10.6 +/- 1.0 11.3 +/- 1.1 10.5 +/- 0.4 16F1 10.4 +/- 0.7 10.3 +/- 0.8 10.4 +/- 0.3 10.9 +/- 0.8 10.0 +/- 0.7 17B1 9.7 +/- 0.4 9.9 +/- 0.6 9.4 +/- 0.2 9.6 +/- 0.2 9.8 +/- 0.5 18S2 10.8 +/- 0.6 11.0 t 0.1 10.4 +/- 0.6 11.0 +/- 0.8 10.7 +/- 0.2 19D1 9.8 +/- 0.9 9.6 +/- 1.3 10.4 +/- 2.3 9.4 +/- 1.1 9.7 +/- 0.1 20D1 9.3 +/- 0.6 9.6 +/- 0.1 9.3 +/- 0.6 9.3 +/- 0.1 8.9 +/- 0.4 20F1 9.8 +/- 0.6 9.6 +/- 0.3 10.1 +/- 0.8 10.0 +/- 0.4 9.5 +/- 0.1 21S2 9.5 +/- 0.6 9.6 +/- 0.0 9.8 +/- 1.5 9.1 +/- 1.9 9.5 +/- 1.1 23S2 9.5 +/- 0.5 9.8 +/- 0.1 9.6 +/- 0.3 9.3 +/- 0.3 9.3 +/- 0.3 24D1 9.0 +/- 0.7 8.8 +/- 0.7 9.5 +/- 2.1 8.8 +/- 0.4 8.8 +/- 1.3 25D1 8.7 +/- 0.4 8.5 +/- 0.0 8.5 +/- 1.5 8.9 +/- 0.5 8.7 +/- 1.3 25S2 9.0 +/- 0.4 8.9 +/- 0.8 9.1 +/- 1.1 9.2 +/- 0.1 8.7 +/- 0.5 26S3 9.2 +/- 0.2 9.3 +/- 0.2 9.1 +/- 0.5 9.3 +/- 0.8 9.2 +/- 0.0 28D2 9.3 +/- 0.3 9.2 +/- 0.7 9.4 +/- 0.1 9.4 +/- 0.4 9.1 +/- 1.0 29E1 9.2 +/- 1.3 8.8 +/- 0.1 8.9 +/- 0.4 10.1 +/- 0.2 8.8 +/- 0.3 29S1 9.8 +/- 1.2 9.3 +/- 0.3 10.4 +/- 1.2 9.3 +/- 1.3 10.2 +/- 0.3 31D1 11.0 +/- 2.1 12.0 +/- 0.4 10.3 +/- 3.0 11.7 +/- 0.6 9.9 +/- 1.6 31D2 10.3 +/- 0.3 10.2 +/- 0.7 10.1 +/- 0.1 10.5 +/- 0.1 10.2 +/- 0.6 31S1 10.0 +/- 1.2 10.3 +/- 0.0 9.4 +/- 2.3 10.7 +/- 0.1 9.7 +/- 0.4 34E1 10.0 +/- 0.6 9.9 +/- 0.1 10.4 +/- 0.8 10.0 +/- 0.6 9.7 +/- 0.1 34S2 9.7 +/- 1.3 10.6 +/- 1.6 9.2 +/- 2.5 9.9 +/- 1.3 9.2 +/- 0.9 36D1 9.5 +/- 1.1 9.1 +/- 0.2 10.2 +/- 0.0 9.0 +/- 0.1 9.6 +/- 1.3 36S2 10.2 +/- 0.8 10.3 +/- 0.6 10.3 +/- 3.1 10.6 +/- 0.3 9.7 +/- 1.0 C-18

TABLE C-IX.2 MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY, MIDDLE, AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF MREM/STANDARD MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD JAN-MAR APR-JUN JUL-SEP OCT-DEC TABLE C-IX.2 SITE BOUNDARY MIDDLE CONTROL

+/- 2 S.D.

10.3 +/- 2.3 9.7 +/- 1.7 12.0 +/- 0 10.0 +/- 2.2 9.9 +/- 1.7 11.0 +/- 0 10.3 +/- 2.4 10.0 +/- 1.9 12.3 +/- 0 9.9 +/-2.5 9.7 +/- 1.8 11.2 +/- 0 MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF MREM/STANDARD MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA LOCATION SAMPLES ANALYZED PERIOD PERIOD MINIMUM MAXIMUM PERIOD MEAN

+/- 2 S.D.

SITE BOUNDARY MIDDLE CONTROL 64 92 4

7.8 7.7 11.0 13.7 12.0 12.3 10.1 +/- 2.3 9.8 +/- 1.8 11.6 + 1.2 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-19

FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2013 12 10 8

n CL 6

4 2

Y1~TI2~CONTROL

---*--INDICATOR I

1%

I I

I l

I I

I-I I

I I

1 I

82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 11 12 13 Note: 2005 analysis changed from Insoluble & Soluble to Total Gross Beta YEAR LGS CRITICALITY UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/11/89 LGS CHANGED TO TOTAL GROSS BETA AT THE BEGINNING OF 2005. PREVIOUS DATA INCLUDED SUMMATION OF LESS THAN VALUES.

6 FIGURE C-2 MEAN ANNUAL CS-137 CONCENTRATIONS IN FISH SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2013 65

-- 16C5

-A--20Sl 5

-* -29C1 1___":.

Note: Second half of 2000.

.switched to reporting < MDC when no activity was detected.

45 Using MDC values result in a L..

larger number. LLD < 150 pCikg.

E LGS CRITICALITY UNIT NO. 1: 12/22/84 0

UNIT NO. 2: 08/11189...

o.X_

25 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 11 12 13 YEAR CONTROL = 29C1 Station 20S1 discontinued in 1995

FIGURE C-3 CONCENTRATIONS OF CS-137 IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2013 1400 -

"- 16B2 LGS CRITICALITY 1200...

UNIT NO. 1: 12/22/84...

--, - 16C4 UNIT NO. 2: 08111189 LGs IR 439395 33A2 CONTROL 33A2 Source Unknown S00 200

~~~~~..

.i

i.

I

I-1I-i iI I

...... ii I...

I...

82 83 85 86 88 89 91 92 94 95 97 98 00 01 03 04 06 07 09 10 12 13 Year

FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2013

.4 r*

n~

-IU 135 120 105 E

90

.0

=

75 C

60 C?w 45 30 15 n

-u--Group I

--*- Group 11 G ro up III Chernobyl LGS CRITICALITY UNIT NO. 1: 12/22184 UNIT NO. 2: 08111189 II

.11 AM I

I I

1 I

I I

1 1

I I

I 1

I I

I l

1 1

I 1

t J

'IP I

1 I

l I

I I

82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 12 YEAR m

FIGURE C-5 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2013 50 40

-s-GROUP I GROUP II

.- GROUP III n)

E U

.0 U

0 0.

w 30-20 -

10 0

.. I..,.... I,........., I.. ý I..............,.. I,........ I...

........ I. I..

. I...I

.......................I

'i.

I ii

,i, ii

,i, 3

6 9

12 15 18 21 24 27 30 33 36 39 42 45 48 51 WEEK NO.

0P

FIGURE C-6 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (TLD)

IN THE VICINITY OF LGS, 1985-2011 NOTE: Control Station 5H1 became the only distant location beginning in 1995 13 SITE

12.

INTERMEDIATE CONTROL 11 Control 5H1

)

=,.

-=

r

=-'

....==

'l r*--

r-'

4..

8..........

6

-a....----'

S--------

4-5 85 86 87 88 89 90 91 92 93 94 95 96 97 98 990001 02 03 04 05 06 07 08 09 1011 12 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, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/31/12

- 01/29 01/29/13 - 02/26 02/26/13

- 04/01 04/01/13 - 04/29 04/29/13

- 06/04 06/04/13

- 07/01 07/01/13

- 07/30 07/30/13

- 08/27 08/27/13

- 09/30 09/30/13

- 10/29 10/29/13

- 12/03 12/03/13

- 12/30 16C2 1/13

/13

/13 1/13

/13

'/13

/13

'/13

/13

/13 4.7 +/- 1.6 1.6 +/- 0.6

< 1.4 1.7 +/- 0.8

< 3.7 1.3 +/- 0.5 2.3 +/- 0.7 2.6 +/- 0.6 2.9 +/-1.1

< 1.3 3.2 +/-0.8 1.8 +/-1.0 MEAN 2.4 +/- 2.1 TABLE D-I.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 I

12/31/12 -

01/29/13 -

02/26/13 -

04/01/13 -

04/29/13 -

06/04/13 -

07/01/13 -

07/30/13 -

08/27/13 -

09/30/13 -

10/29/13 12/03/13 -

01/29/13 02/26/13 04/01/13 04/29/13 06/04/13 07/01/13 07/30/13 08/27/13 09/30/13 10/29/13 12/03/13 12/30/13

< 0.5

< 0.2

< 0.5

< 0.3

<0.3

< 0.5

< 0.2

< 0.4

< 0.2

< 0.2 MEAN TABLE D-1.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/31/12 - 04/01 04/01/13 - 07/01 07/01/13 - 09/30 09/30/13 - 12/30 16C2

/13

< 150

< 156

< 148

< 149 MEAN D-I

TABLE D-1.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD 16C2 12/31/12 01/29/13

< 2

< 3

< 7

< 2

< 4

< 3

< 12

< 3

< 2

< 25

< 5 01/29/13 02/26/13

< 3

< 6

< 5

< 6

< 7

< 4

< 3

< 14

< 4 02/26/13 04/01/13

< 2

< 6

< 3

< 6

< 4

< 6

< 3

< 15

< 4 04/01113 04/29113

< 3

< 2

< 10

< 3

< 6

< 3

< 6

< 3

< 11

< 2 04/29/13 06/04/13

< 2

< 7

< 2

< 3

< 10

< 3

< 2

< 20

< 3 06/04/13 07/01/13

< 2

< 3

< 2

< 4

< 3

< 4

< 3

< 17

< 2 07101113 07130/13

< 3

< 2

< 4

< 3

< 9

< 2

< 3

< 23

< 5 07/30/13 08/27/13

< 7

< 5

< 8

< 4

< 8

< 9

< 3

< 8

< 6

< 5

< 25

< 4 08/27/13 09/30/13

< 1

< 2

< 1

< 2

< 11

< 1

< 16

< 3 09/30/13 10/29/13

< 3

< 4

< 7

< 5

< 4

< 6

< 5

< 4

< 17

< 3 10/29/13 12/03/13

< 2

< 3

< 5

< 3

< 6

< 4

< 10

< 3

< 15

< 3 12/03/13 12/30/13

< 2

< 3

< 2

< 3

< 4

< 3

< 14

< 4 MEAN

TABLE D-1I.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE AND 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA 12 01 01 01 01 02 02 02 02 03 03 03 03 04 04 04 04 04 05 05 05 05 06 06 06 06 07 07 07 07 07 08 08 08 08 09 09 09 09 09 10 10 10 10 11 11 11 11 12 12 12 12 COLLECTION PERIOD

/06/13 01/14/13

/14/13 01/22/13

/22/13 01/29/13

/29/13 02/04/13

/04/13 02/11/13

/11/13 02/19/13

/19/13

- 02/25/13

/25/13 03/04/13

/04/13

- 03/11/13

/11/13

- 03/18/13

/18/13 03/26/13

/26/13 04/01/13

/01/13 04/08/13

/08/13 04/15/13

/15/13 04/22/13

/22/13 04/29/13

/29/13 05/06/13 106/13 05/13/13

/13/13 05/20/13

/20/13 05/28/13

/28/13 06/03/13

/03/13 06110/13

/10/13 06/17/13

/17/13 06/24/13

/24/13 07/01/13

/01113 07/08/13

/08/13 07/15/13

/15/13 07/22/13

/22/13 07/29/13

/29/13 08/05/13

/05/13 08/12/13

/12/13 08/19/13

/19/13 08/26/13

/26/13 09/03/13

/03/13 09/09/13

/09/13 09/16/13

/16/13 09/23/13

/23/13 09/30/13

/30/13 10/07/13

/07/13 10/15/13

/15/13 10/21/13

/21/13 10/28/13

/28/13 11/04/13

/04/13 11/11/13

/11/13 11/18/13

/18/13 11/25/13

/25/13 12/02/13

/02/13 12/09/13

/09/13 12/16/13

/16/13 12/23/13

/23/13 12/30/13 11S2 GROSS BETA 41 b

38 +/-_5 24 +4 28 +4 34 +5 43 + 12 22 +4 7+4 12

_+4 9+/-4 23 +4 14 _+3 12 +/--4 28 +4 17+/- 4 18+/- 4 21 +/-+4 18+/- 4 9+/-4 18+/- 4 16+/- 4 24 +/-+5 10+/- 4 18+/- 5 14+/- 4 22 +5 15 +/- 4.

22 +/- 4 31 +/- 5 19 +/- 4 21 +/- 4 19 +/- 5 17 +/- 4 23 +/- 5 33 +/- 4 18 +/- 5 29 +/- 5 18 +/- 5 22 +/- 4 40 +/- 5 23 +/- 4 29 +/-+5 23 +/-+5 32 +/-+5 21 +/-+4 26 +5 19+/- 5 22 +/-+4 44 +/-+5 29 +/- 5 25 +/- 5 31 +/- 4 11S2 1-131

< 16

< 12

<9

< 16

< 46

< 10

< 14

< 18

< 17

< 11

< 19

< 17

< 16

< 18

< 12

< 13

< 14

< 16

< 18

< 21

< 14

< 13

< 18

< 13

< 16

< 18

< 21

< 15

< 18

< 13

<9

< 15

< 14

< 19

< 13

< 17

< 21

< 11

< 16

< 20

< 16

< 10

< 22

< 12

< 14

< 15

< 16

< 15

< 22

< 25 MEAN 23 +/- 17 D-3

TABLE D-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD 11S2 12/31/12 04/01/13 04/01/13

- 07/01/13 07/01/13

- 09/30/13 09/30/13 12/30/13 MEAN Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 59 81 61 69

+ 20

_ 19

+ 20

+ 16

< 0.8

< 1.1

< 0.7

< 1.1

< 1.0

< 0.7

< 0.8

< 0.5

< 0.9

< 1.0

< 0.5

< 1.2

< 0.7

< 0.4

< 0.9

< 0.5

< 0.4

< 0.9

< 0.5 68 +/- 20 D-4

TABLE D-Ill.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD 1-131 K-40 Cs-1 34 Cs-1 37 Ba-140 La-140 10F4 01/08/13 04/02/13 07/09/13 10/01/13

<0.5 1318 +/- 92

<3

< 21

<3 MEAN 19B1 01/08/13 04/02/13 07/09/13 10/01/13 MEAN

0.4

0.3

0.2

< 0.4

0.4

0.3

0.4

0.2 1452 +/- 104 1319 +/- 111 1397 +/- 102 1440 +/- 103 1402 +/- 120 1399 +/- 88 1377 +/- 109 1485 +/- 96 1404 +/- 15 1416 +/- 95

<4

<3

<4

<3

<4

<3

<4

<3

<2

<3

<2

<4

<3

<4

< 29

<14

< 32

< 42

< 18

< 20

< 17

< 61

<3

<6

<11 25C1 01/08/13 04/02/13 07/09/13 10/01/13

<7

<3

<9

<9 MEAN D-5

FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENV AND TBE, 2013 10 8

E 8..... *.........,""......

...\\ *.........- -......*=-=..- *....* - !...

48.

C-)

0.,"

0 I

I I

N 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 11SI AND 11S2, 2013 50 40

-4.

I..0

'I..0230

.0 C.)~20 C?

w 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, 2013 (PAGE 1 OF 3)

Identification Month/Year Number Reported Known Units Value(a)

Value (b)

Ratio (c)

TBE/Analvtics Evaluation (d)

Matrix Nuclide March 2013 E10477 E10478 E10480 E10479 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 120 99.7 pCi/L 9.21 11.0 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 87.1 186 463 201 262 200 215 266 311 384 95.3 264 123 142 112 115 139 163 212 100 187 472 214 266 208 208 252 301 400 95.6 241 109 136 106 106 129 153 204 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 June 2013 El10481 El10564 E10545 E10547 E10546 pCi 90.1 92.6 pCi/L 1840 1890 pCi/L 110 95.0 pCi/L 15.8 17.0 1.20 0.84 0.87 0.99 0.98 0.94 0.98 0.96 1.03 1.06 1.03 0.96 1.00 1.10 1.13 1.04 1.06 1.08 1.08 1.07 1.04 0.97 0.97 1.16 0.93 0.97 0.92 1.01 0.94 0.95 0.93 0.99 1.04 1.01 0.97 1.00 1.07 1.09 1.07 1.06 1.16 1.14 1.24 1.05 0.96 A

A A

A W

A A

Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 92.6 83.1 253 118 143 87.1 171 125 220 169 56.8 168 85.2 101 62.7 125 85.7 169 116 95.5 90.4 250 125 151 94.0 172 120 217 175 56.7 157 78.4 94.6 58.9 108 75.0 136 110 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi 86.5 89.7 E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b) TBE/Analytics Evaluation (d)

June 2013 E10549 Water Fe-55 pCi/L 1610 1610 pCi/L 63.9 96.0 pCi/L 8.88 13.2 September2013 E10646 E10647 E10672 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 93.9 98.3 272 150 125 105 138 125 264 187 208 143 106 97.0 116 98.6 219 166 277 172 131 108 139 130 266 196 223 139 105 86.5 112 105 214 158 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 E10648 E10673 pCi 76.3 71.7 pCi/L 1790 1690 pCi/L 97.3 93.8 pCi/L 13.3 12.9 1.00 0.67 0.67 0.96 0.98 0.87 0.95 0.97 0.99 0.96 0.99 0.95 0.93 1.03 1.01 1.12 1.04 0.94 1.02 1.05 1.06 1.06 1.04 1.03 0.93 0.91 1.00 0.91 1.00 1.04 0.99 1.06 1.02 0.96 0.97 1.17 1.08 1.01 0.94 0.98 1.14 0.85 1.00 N (1)

N (1)

A NA (2)

A A

NA (2)

A A

A December2013 E10774 El 0775 E10777 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 89.7 99.8 297 129 126 116 167 117 757 141 85.1 278 123 102 84.4 132 101 506 118 96.1 110 297 142 126 112 168 110 741 147 88.0 238 114 101 89.9 135 88.3 595 118 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December 2013 E10776 El 0778 Charcoal 1-131 Water Fe-55 pCi 84.7 80.5 pCi/L 2010 1910 1.05 1.05 A

A (1) Milk, Sr-89/90 - The failure was due to analyst error. No client samples were affected by this failure. NCR 13-15 (2) The sample was not spiked with Ce-141 (a) Teledyne Brown Engineering reported result.

(b) 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.

(c) Ratio of Teledyne Brown Engineering to Analytics results.

(d) Analytics evaluation based on TBE intemal 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.

E-3

TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 1 OF 1)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Limits Evaluation (c)

May 2013 RAD-93 MRAD-18 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A pCi/L 48.3 41.3 pCi/L 19.3 23.9 pCi/L 81.9 82.1 pCi/L 40.9 42.8 pCi/L 44.0 41.7 pCi/L 61.9 65.9 pCi/L 202 189 pCi/L 34.2 40.8 pCi/L 18.0 21.6 pCi/L 23.8 23.8 pCi/L 60.4 61.2 pCi/L 3970 4050 pCi/filter Lost during processing 31.6 -48.4 17.2 - 28.0 69.0 - 90.3 34.2-47.1 37.0 -48.8 59.3 - 75.0 170-222 21.1 -51.9 13.0-29.7 19.7 - 28.3 49.8 - 67.9 3450 - 4460 A

A A

A November 2013 RAD-95 pCi/L 25.5 pCi/L 14.3 pCi/L 57.2 pCi/L 83.3 pCi/L 201 pCi/L 104 pCi/L 361 pCi/L 29.5 pCi/L 30.1 pCi/L 23.1 pCi/L 5.53 pCi/L 17650 pCi/filter 33.0 21.9 18.1 54.2 86.7 206 102 333 42.8 32.2 23.6 6.24 17700 83.0 14.4 - 28.2 12.8-21.5 44.7 - 59.9 71.1 -95.4 185-228 91.8-114 300 - 389 22.2 - 54.3 20.8 - 39.9 19.6-28.0 47.0 - 7.44 15500 - 19500 A

A A

MRAD-19 27.8-129 (a) Teledyne Brown Engineenng reported result.

(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetnc measurements made during standard preparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.

E-4

TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2013 (PAGE 1 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Range Evaluation (c)

March 2013 13-MaW28 Water Cs-134 Cs-1 37 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Water Gr-A Gr-B Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 21.0 24.4 17.1 -31.7 0.0446 (1) 28.3 30.9 21.6-40.2 18.2 19.56 13.69 - 25.43 506 507 355 - 659 25.7 27.4 19.2-35.6 2.09 (1) 10.5 10.5 7.4-13.7 29.2 30.4 21.3-39.5 A

A A

13-GrW28 13-MaS28 13-RdF28 Bq/L 2.74 2.31 Bq/L 15.6 13.0 0.69 - 3.93 6.5 - 19.5 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 859 887 621-1153 633 587 411-763 0.256 (1) 738 691 484-898 0.671 (1) 714 625.3 437.7 - 812.9 442 628 440-816 1057 995 697-1294 13-GrF28 13-RdV28 September 2013 13-MaW29 13-GrW29 AP Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Water Cs-134 Cs-1 37 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Water Gr-A Gr-B Bq/sample 1.73 1.78 Bq/sample 2.73 2.60 Bq/sample 2.38 2.36 Bq/sample 0.0302 Bq/sample 4.36 4.26 Bq/sample 1.43 1.49 Bq/sample 3.14 3.13 Bq/sample 0.767 1.20 Bq/sample 0.871 0.85 1.25-2.31 1.82 - 3.38 1.65-3.07 (1) 2.98 - 5.54 1.04-1.94 2.19-4.07 0.36-2.04 0.43-1.28 A

A A

A W

A A

A W

A A

W A

A A

Bq/sample

-0.197 (1)

Bq/sample 7.39 6.87 4.81 - 8.93 Bq/sample 9.87 8.68 6.08 - 11.28 Bq/sample 6.08 5.85 4.10-7.61 Bq/sample -0.0104 (1)

Bq/sample 1.28 1.64 1.15-2.13 Bq/sample 6.84 6.25 4.38-8.13 Bq/L 29.1 30.0 21.0-39.0 Bq/L 34.5 31.6 22.1-41.1 Bq/L 0.0358 (1)

Bq/L 24.6 23.58 16.51 - 30.65 Bq/L 2.45 (1)

Bq/L 0.0337 (1)

Bq/L 0.193 (1)

Bq/L 9.12 7.22 5.05-9.39 Bq/L 38.1 34.6 24.2 -45.0 Bq/L 1.13 0.701 0.210- 1.192 Bq/L 7.61 5.94 2.97 - 8.91 E-5

TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2013 (PAGE 2 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Range Evaluation (c)

September 2013 13-MaS29 13-RdF29 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 1150 1100 670 502 758 796 664 210

-0.570 2.85 3.30 2.41 3.65 1.40 2.90 1172 820-1524 977 684-1270 (1) 451 316-586 674 472-876 633 443-823 460 322-598 (1) 13-GrF29 13-RdV29 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 2.7 3.4 2.3 3.5 1.81 2.7 (1) 1.9-3.5 2.4 - 4.4 1.6-3.0 2.5-4.6 1.27 - 2.35 1.9-3.5 A

A N (2)

A A

W N (2)

N (2)

A A

W A

A A

A W (2)

W Bq/sample 0.872 0.9 0.3-1.5 Bq/sample 1.57 1.63 0.82 - 2.45 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 5.29 7.48 0.0129 0.0523 8.78 1.63 3.18 5.20 3.64 - 6.76 6.60 4.62 - 8.58 (1)

(1) 7.88 5.52 - 10.24 2.32 1.62-3.02 2.63 1.84 - 3.42 (I) False positive test.

(2) Soil, Co-57 & Zn-65 identified by gamma software as not detected, MAPEP evaluated as failing the false positive test. A large concentration of Eu-152 was spiked into the sample, causing interference in the analysis. Gamma software recognized the interference and identified them as not detected. MAPEP does not allow clients to enter non-detect designation. NCR 13-04 Soil, Sr incorrect results were submitted to MAPEP. Actual result was 332 bq/kg, which is within the acceptance range. NCR 13-04 AP, Cs-134 - MAPEP evaluated the -0. 570 as a failed false positive test. No client samples were affected by these failures. NCR 13-04 Vegetation, Sr it appears that the carrer was double spiked into the sample, resulting in the low activity for this sample. NCR 13-04 (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetnc and/or volumetric measurements made during standard preparation.

(c) DOE/MAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.

E-6

TABLE E-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa ENVIRONMENTAL, INC., 2013 (Page I of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result (b)

Result (c)

Limits Acceptance ERW-1593 04/08/13 Sr-89 43.6 +/- 4.3 41.30 31.6 -48.4 Pass ERW-1593 04/08/13 Sr-90 23.2 +/- 1.7 23.90 17.2 -28.0 Pass ERW-1596 04/08/13 Ba-133 74.80 4.00 82.10 69.00 90.30 Pass ERW-1596 04/08/13 Co-60 65.50 3.42 65.90 59.30 75.00 Pass ERW-1 596 04/08/13 Cs-1 34 41.10 3.47 42.80 34.20 47.10 Pass ERW-1596 04/08/13 Cs-137 42.30 4.03 41.70 37.00 48.80 Pass ERW-1596 04/08/13 Zn-65 200.3 +/- 10.1 189.0 170.0 - 222.0 Pass ERW-1598 04/08/13 Gr. Alpha 34.30 1.98 40.80 21.10 51.90 Pass ERW-1598 04/08/13 Gr. Beta 18.70 0.98 21.60 13.00 29.70 Pass ERW-1600 04/08/13 1-131 23.00 +/- 1.10 23.80 19.70 -28.30 Pass ERW-1600 04/08/13 1-131(G) 23.48 +/- 9.44 23.80 19.70 +/- 28.30 Pass ERW-1606 04/08/13 H-3 4041 +/- 194 4050 3450 -4460 Pass ERW-6009 10/07/13 Sr-89 22.00 2.80 21.90 14.40 28.20 Pass ERW-6009 10/07/13 Sr-90 17.10 2.55 18.10 12.80 21.50 Pass ERW-6012 10/07/13 Ba-133 48.20 4.29 54.20 44.70 59.90 Pass ERW-6012 10/07/13 Co-60 100.8 +/- 4.7 102.0 91.8-114.0 Pass ERW-6012 10/07/13 Cs-1 34 87.30 4.35 86.70 71.10 95.40 Pass ERW-6012 10/07/13 Cs-137 199.6 +/- 7.4 206.0 185.0 - 228.0 Pass ERW-6012 10/07/13 Zn-65 356.2 +/- 13.2 333.0 300.0 - 389.0 Pass ERW-6015 10/07/13 Gr. Alpha 30.70 11.90 42.80 22.20 54.30 Pass ERW-6015 10/07/13 Gr. Beta 25.70 6.48 32.20 20.80 39.90 Pass ERW-6019 10/07/13 1-131 22.50 1.01 23.60 19.60 28.00 Pass ERW-6024 10/07/13 H-3 18397 695 17700 15500 19500 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).

b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

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

E-7

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

ENVIRONMENTAL, INC., 2013 (Page 1 of 2)

Concentration (a)

Known Control Lab Code (b) Date Analysis Laboratory result Activity Limits (c)

Acceptance MAAP-738 MAAP-738 MAAP-738 MAAP-738 MAAP-738 MAAP-738 MAAP-738 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Sr-90 Zn-65 Gr. Alpha Gr. Beta 2.58 +/- 0.06 0.01 +/- 0.03 1.82 +/- 0.13 2.93 +/- 0.10 4.87 +/- 0.13 1.39 +/- 0.14 3.84 +/- 0.20 0.14 +/- 0.03 0.93 +/- 0.06 2.36 0.00 1.78 2.60 4.26 1.49 3.13 1.20 0.85 1.65 - 3.07 0.00 -0.10 1.25 - 2.31 1.82 -3.38 2.98 - 5.54 1.04-1.94 2.19 -4.07 0.36 - 2.04 0.43 - 1.28 MAAP-738 d 02/01/13 MAAP-738 02/01/13 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 Co-57 Co-60 Cs-1 34 Cs-1 37 Fe-55 H-3 K-40 Mn-54 Sr-90 Zn-65 MAW-811 02/01/13 Gr. Alpha MAW-811 02/01/13 Gr. Beta MASO-739 MASO-739 MASO-739 MASO-739 MASO-739 MASO-739 MASO-739 MASO-744 e MAVE-747 MAVE-747 MAVE-747 MAVE-747 MAVE-747 MAVE-747 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Zn-65 Sr-90 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Cs-134 Cs-137 K-40 Mn-54 31.20 0.40 19.70 +/- 0.30 23.20 +/- 0.50 0.03 +/- 0.12 34.00 +/- 3.30 511.60 +/- 12.50 2.20 +/- 0.90 27.60 +/- 0.50 9.30 +/- 0.80 31.60 +/- 0.80 1.87 +/- 0.09 13.04 +/- 0.13 0.60 +/- 0.50 739.20 +/- 28.50 863.30 +/- 34.10 661.80 +/- 25.70 745.80 +/- 33.30 1.10 +/- 1.00 1109.60 +/- 44.10 408.40 +/- 14.00 10.37 +/- 0.17 6.48 +/- 0.17 0.02 +/- 0.04 7.79 +/- 0.21 0.00 +/- 0.05 7.29 +/- 0.33 699.60 +/- 3.90 1191.70 +/- 23.00 1072.00 +/- 5.10 760.00 +/- 16.20 753.80 +/- 4.90 30.90 16.56 24.40 0.00 44.00 507.00 0.00 27.40 10.50 30.40 2.31 13.00 0.00 691.00 887.00 587.00 625.30 0.00 995.00 628.00 8.68 5.85 0.00 6.87 0.00 6.25 0.00 1172.00 977.00 633.00 674.00 21.60 40.20 13.69 - 25.43 17.10 - 31.70 0.00-1.00 30.80 - 57.20 355.00 - 659.00 0.00 - 5.00 19.20 - 35.60 7.40 - 13.70 21.30 - 39.50 0.69 - 3.93 6.50 - 19.50 0.00 - 5.00 484.00 - 898.00 621.00 - 1153.00 411.00 - 763.00 437.70 - 812.90 0.00 - 5.00 697.00 - 1294.00 440.00 - 816.00 6.08-11.28 4.10 -7.61 0.00 -0.10 4.81 - 8.93 0.00 -0.10 4.38 -8.13 0.00 - 5.00 820.00 - 1524.00 684.00 - 1270.00 443.00 - 823.00 472.000 - 876.000 Pass Pass Pass Pass Pass Pass Pass Fail (1)

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail (2)

Pass Pass Pass Pass Pass Pass Fail (3)

Pass Pass Pass Pass MASO-5043 f 08/01/13 MASO-5043 08/01/13 MASO-5043 08/01/13 MASO-5043 08/01/13 MASO-5043 08/01/13 E-8

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

ENVIRONMENTAL, INC., 2013 (Page 2 of 2)

Concentration (a)

Known Control Lab Code (b) Date Analysis Laboratory result Activity Limits (c)

Acceptance MASO-5043 08/01/13 Sr-90 383.90 +/- 14.50 460.00 322.00 - 598.00 Pass MASO-5043 08/01/13 Zn-65

-351.50 +/- 5.50 0.00 0.00 - 0.00 Pass MAW-5094 08/01/13 Co-57 0.01 +/- 0.09 0.00 0.00 - 5.00 Pass MAW-5094 08/01/13 Co-60 23.20 +/- 0.32 23.58 16.51 - 30.65 Pass MAW-5094 08/01/13 Cs-134 27.60 +/- 0.58 30.40 21.00 - 39.00 Pass MAW-5094 08/01/13 Cs-137 32.31 +/- 0.52 31.60 22.10 - 41.10 Pass MAW-5094 08/01/13 Fe-55 39.20 +/- 3.50 53.30 37.30 - 69.30 Pass MAW-5094 08/01/13 Gr. Alpha 0.54 +/- 0.05 0.70 0.21 -1.19 Pass MAW-5094 08/01/13 Gr. Beta 5.85 +/- 0.09 5.94 2.97 - 8.91 Pass MAW-5094 08/01/13 H-3 1.20 +/- 3.00 0.00 0.00 - 5.00 Pass MAW-5094 08/01/13 K-40 2.22 +/- 0.90 0.00 0.00 - 5.00 Pass MAW-5094 08/01/13 Mn-54 0.010 +/- 0.11 0.00 0.00 -5.00 Pass MAW-5094 08/01/13 Sr-90 6.40 +/- 0.60 7.22 5.05 - 9.39 Pass MAW-5094 08/01/13 Zn-65 35.30 +/- 0.90 34.60 24.20 - 45.00 Pass MAVE-5046 08/01/13 Co-57 0.01 +/- 0.03 0.00 0.00 - 0.00 Pass MAVE-5046 08/01/13 Co-60 0.00 +/- 0.04 0.00 0.00 - 0.00 Pass MAVE-5046 08/01/13 Cs-134 5.71 +/- 0.23 5.20 3.64 - 6.76 Pass MAVE-5046 08/01/13 Cs-137 7.64 +/- 0.20 6.60 4.62 -8.58 Pass MAVE-5046 08/01/13 Mn-54 9.08 +/- 0.24 7.88 5.52 - 10.24 Pass MAVE-5046 08/01/13 Zn-65 2.92 +/- 0.25 2.63 1.84 -3.42 Pass MAAP-5046 08/01/13 Co-57 3.48 +/- 0.14 3.40 1.90 -3.50 Pass MAAP-5046 08/01/13 Co-60 2.44 +/- 0.08 3.40 1.60 -3.00 Pass MAAP-5046 08/01/13 Cs-134 0.01 +/- 0.03 0.00 0.02 -0.04 Pass MAAP-5046 08/01/13 Cs-137 3.09 +/- 0.13 2.70 1.90 -3.50 Pass MAAP-5046 08/01/13 Gr. Alpha 0.28 +/- 0.04 0.90 0.27 -1.53 Pass MAAP-5046 08/01/13 Gr. Beta 1.90 +/- 0.08 1.63 0.82 -2.45 Pass MAAP-5046 08/01/13 Mn-54 3.95 +/- 0.12 3.50 2.50 -4.60 Pass MAAP-5046 08/01/13 Sr-90 1.69 +/- 4.10 1.81 1.27 -2.35 Pass MAAP-5046 08/01/13 Zn-65 3.27 +/- 0.18 2.70 2.50 -4.60 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 series as a "false positive". MAPEP does not provide control limits.

(1) The filter was recounted overnight, no significant alpha activity could be detected.

(2) The sample was reanalyzed using additional fuming nitric separations. Result of reanalysis: 574.4 +/- 35.2 Bq/kg.

(3) Interference from Eu-152 resulted in misidentification of Co-57.

E-9

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APPENDIX F ERRATA DATA

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Due to an incorrect setting on gamma detector 08, 3.29 rather than 4.66 was used in the MDC calculation. Nonconformance 13-07 was initiated and corrective actions have been implemented to address this issue. All samples counted on detector 08 were reprocessed using the correct calculation. As a result, all MDCs for these samples have increased by 41.6%. The previously reported activities and uncertainties were not affected. In some cases, the increased MDC resulted in missed LLDs. All samples with MDCs affected by this issue are listed below. The samples with missed LLDs are shown in the table for 2012, and 2013. All other required LLDs were met.

F-!

2012 START END REQUIRED REVISED CLIENT ID DATE DATE MATRIX NUCLIDE MDC MDC UNITS 1602 12/27/11 01/31/12 Drinking Water 15F4 02/28/12 04/02/12 Drinking Water 25C1 03/13/12 03/13/12 Milk 15F4 04/02/12 04/30/12 Drinking Water 1-131

<15

<15.98 pCi/L 15F4 04/02/12 04/30/12 Drinking Water La-140

<15

<18.2 pCi/L 10F4 04/03/12 04/03/12 Milk MW-LR-3 04/24/12 RGPP SW-LR-4 04/25/12 RGPP 25C1 05/29/12 05/29/12 Milk 28F3 05/29/12 07/02/12 Drinking Water 11S3 (Collards) 06/13/12 06/13/12 Vegetation 3Q12 22G1 07/01/12 10101/12 Air Particulate 11 S3 (Swiss Chard) 07/17/12 Vegetation 23F1 08/07/12 08/07/12 Milk 11 S3 (Smss Chard) 08/07/12 Vegetation 31 G1 (Squash Leaves) 08/07/12 Vegetation 10F4 08/21/12 08/21/12 Milk 15F4 08/28/12 10/02/12 Drinking Water 31G1 (Zucchini Leaves) 09/05/12 09/05/12 Vegetation 23F1 09/18/12 09/18/12 Milk 4Q12 13C1 10/01/12 12/31/12 Air Particulate 13S3 (Collards) 10/09/12 10/09/12 Vegetation 1-131

<60

<71.69 pCi/kg Wet 13S3 (zucchini Leaves) 10/09/12 10/09/12 Vegetation 1-131

<60

<84.89 pCi/kg Wet 11 S3 (Svrss Chard) 10/09/12 10/09/12 Vegetation 31G1 (Kale) 10/09/12 10/09/12 Vegetation 13B1 10/29/12 12/04/12 Surface Water 15F7 10/29/12 12/04/12 Drinking Water 25C1 11/27/12 11/27/12 Milk 16C2 12/04/12 12/31/12 Drinking Water 23F1 12/11/12 12/11/12 Milk

Required LLDs were achieved F-2

2013 START END REQUIRED REVISED CLIENT ID DATE DATE MATRIX NUCLIDE MDC MDC UNITS 15F4 12/31/12 01/29/13 Drinking Water 1-131

<15

<15.45 pCi/L 18E1 01/08/13 01/08/13 Milk 15F4 01/29/13 02/26/13 Drinking Water

Required LLDs were achieved F-3

ERRATA 2010 - 2012 Annual Radiological Environmental Operating Report Correction to 2010 ARERR Total body and organ dose for liquid releases were recalculated due to a software error identified (IR 1613017). Due to the software error, dose calculations were being performed without the inclusion of the Schuylkill River dilution factor as required by the ODCM dose methodology. The corrected data in this section includes the dose calculations post dilution and the updated 40 CFR 190 Compliance table. No limits have been exceeded.

Correction to 2011 ARERR Total body and organ dose for liquid releases were recalculated due to a software error identified (IR 1613017). Due to the software error, dose calculations were being performed without the inclusion of the Schuylkill River dilution factor as required by the ODCM dose methodology. The corrected data in this section includes the dose calculations post dilution and the updated 40 CFR 190 Compliance table. No limits have been exceeded.

Correction to 2012 ARERR Total body and organ dose for liquid releases were recalculated due to a software error identified (IR 1613017). Due to the software error, dose calculations were being performed without the inclusion of the Schuylkill River dilution factor as required by the ODCM dose methodology. The corrected data in this section includes the dose calculations post dilution and the updated 40 CFR 190 Compliance table. No limits have been exceeded.

F-4

2010 Annual Radiological Environmental Operating Report I.

Summary and Conclusion Gaseous and liquid radiation doses to members of the public at locations Effluent Applicable Estimated Age Location

% of tOrgan Dose Group Applicable Limit Unit Limit Noble Gas Gamma - Air Dose 4.04E-03 All Nearest 2.00E-02 20 mRad Residence Nearest Noble Gas Beta - Air Dose 2.40E-03 All rest 6.OOE-03 40 mRad Residence Nearest Noble Gas Total Body (Gamma) 3.83E-03 All Resident 3.80E-02 10 mrem Noble Gas Skin (Beta) 6.39E-03 All Nearest 2.10E-02 30 mrem Residence Iodine, Particulate Bone 2.06E-01 Child Cow Milk 6.87E-01 30 mrem

& Tritium Liquid Total Body 1.25E-03 Child Phoenixville, Pa 2.08E-02 6

mrem Liquid Liver 1.40E-03 Child Phoenixville, Pa 7.00E-03 20 mrem 40 CFR 190 Compliance Gaseous Effluents Noble Gas Particulate, Liquid Direct

% of lodone, C-Effluents Radiation Total Applicable Limit Unit 14 &

Limit Tritium Total Body 3.84E-03 4.25E-02 1.25E-03 0.OOE+00 4.76E-02 1.90E-01 25 mrem Dose I

I I

Organ Dose 3.84E-03 2.06E-01 1.40E-03 0.OOE+00 2.11E-01 8.44E-01 25 mrem Thryoid Dose 3.84E-03 4.25E-02 1.18E-03 0.OOE+00 4.75E-02 6.33E-02 75 mrem Doses calculated were well below all ODCM and 40 CFR Part 190 limits to a real individual.

F-5

2011 Annual Radiological Environmental Operating Report I.

Summary and Conclusion Gaseous and liquid radiation doses to members of the public at the highest dose receptor Applicable Estimated Age Location

% of Effluent Organ Dose Group Applicable Limit Unit Limit Noble Gas Gamma - Air Dose 1.46E-02 All Nearest 7.28E-02 20 mRad Residence Nearest Noble Gas Beta - Air Dose 8.73E-03 All resi 2.18E-02 40 mRad Residence Noble Gas Total Body (Gamma) 1.39E-02 All Residence 1.39E-02 10 mrem Noble Gas Skin (Beta) 2.30E-02 All Nearest 7.67E-02 30 mrem Residence Iodine, Particulate, Bone 4.13E-01 Child Cow Milk 1.38E-00 30 mrem Tritium & C-14 Liquid Total Body 5.28E-04 Child LGS Outfall 8.80E-03 6

mrem Liquid GI-Lli 6.OOE-04 Child LGS Outfall 3.OOE-03 20 mrem 40 CFR 190 Compliance Gaseous Effluents Noble Particulate, Liquid Net Direct Total

% of Gas

lodone, Effluents Radiation Limit C-14 &

Limit Tritium Total Body 1.39E-02 8.26E-02 5.28E-04 0.OOE+00 9.70E-02 3.88E-01 25 mrem Dose I

Organ Dose 1.39E-02 4.13E-01 6.OOE-04 0.OOE+00 4.28E-01 1.71E+00 25 mrem Thyroid Dose 1.39E-02 8.26E-02 4.77E-04 0.OOE+00 9.70E-02 1.29E-01 75 mrem F-6

2012 Annual Radiological Environmental Operating Report I.

Summary and Conclusions Gaseous and liquid radiation doses to members of the public at the highest dose receptor Applicable Estimated Age Location

% of Effluent Organ Dose Group Applicable Limit Unit Limit Noble Gas Gamma - Air Dose 4.69E-03 All Nearest 2.35E-02 20 mRad Residence Nearest Noble Gas Beta - Air Dose 3.02E-03 All resi 7.55E-03 40 mRad I

Residence Nearest 44E0 0me Noble Gas Total Body (Gamma) 4.45E-03 All Residence 4.45E-02 10 mrem Noble Gas Skin (Beta) 7.47E-03 All Nearest 2.49E-02 30 mrem Residence Iodine, Particulate, Bone 6.28E-01 Child Vegetation 2.09E-00 30 mrem Tritium & C-14 Liquid Total Body 9.79E-04 Adult LGS Outfall 1.63E-02 6

mrem Liquid Liver 1.1OE-03 Adult LGS Outfall 5.50E-03 20 mrem 40 CFR 190 Compliance:

The maximum calculated dose to a real individual would not exceed 2.14E-01 mrem (total body), 7.15E-01 mrem (organ), or 2.14 E-01 mrem (thyroid).

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

Table 1 40CFR190 Compliance 40 CFR 190 Compliance Gaseous Effluents Noble Particule Liquidof

culate, Direct Total Applicab Limit Unit Gas lodone, C-14 Effluents Radiation le Limit

& Tritium Total Body Dose 4.45E-03 1.27E-01 9.79E-04 0.OOE+00 1.32E-01 5.28E-01 25 mrem Organ Dose 4.45E-03 6.28E-01 1.10E-03 0.OOE+00 6.34E-01 2.54E-00 25 mrem Thryoid Dose 4.45E-03 1.27E-01 7.98E-04 0.OOE+00 1.32E-01 11.76E-01 75 mrem F-7

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APPENDIX G ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

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Docket No:

50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2013 Prepared By Teledyne Brown Engineering Environmental Services MMM Exelon Generation, April 2014

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Table of Contents I. Sum m ary and Conclusions..............................................................................................

1 II. Introduction............................................................................................................

2 A. Objectives of the RG PP.................................................................................

2 B. Im plem entation of the Objectives....................................................................

2 C. Program Description......................................................................................

3 D. Characteristics of Tritium (H-3)......................................................................

4 II1. Program Description..................................................................................................

4 A. Sam ple Analysis..............................................................................................

4 B. Data Interpretation.........................................................................................

5 C. Background Analysis.......................................................................................

6

1. Background Concentrations of Tritium.................................................

6 IV. Results and Discussion...........................................................................................

8 A. G roundwater Results.......................................................................................

8 B. Surface W ater Results....................................................................................

8 C. Precipitation W ater Results...........................................................................

9 D. Drinking W ater W ell Survey...........................................................................

9 E. Summary of Results - Inter-laboratory Comparison Program......................

10 F. Leaks, Spills, and Releases........................................................................

10 G. Trends.........................................................................................................

10 H. Investigations................................................................................................

10 I. Actions Taken................................................................................................

10 V. References...................................................................................................................

10

Appendices Appendix A Tables Table A-1 Location Designation Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2013 Fiqures Figure 1 Figure 2 Figure 3 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2013 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2013 Routine Precipitation Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2013 Appendix B Tables Table B-I.1 Data Tables Table B-1.2 Table B-11.1 Table B-11.2 Table B-Ill.1 Concentrations of Tritium, Strontium-89, Strontium-90, Gross Alpha and Gross Beta in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2013.

Concentrations of Tritium, Strontium-89 and Strontium-90 in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2013.

Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2013.

Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2013.

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 2013 through 31 December 2013. During that time period, 391 analyses were performed on 136 samples from 13 groundwater, 7 surface water and 4 precipitation water locations collected from the environment, both on and off station property in 2013.

In 2012 there was one known release into the groundwater at the Limerick Generating Station that occurred from an over flow of the cooling tower blowdown line during a radioactive waste tank release. The flow path of the water traveled over a road and into Possum Hollow Creek. One well (LM-MW-5) located in the travel path showed a tritium value as high as 14,200 pCi/L. In 2013, only one of five samples analyzed for tritium was positive at a concentration of 183 pCi/I.

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 three of the thirteen groundwater monitoring locations. All surface water tritium sample results were less than the required Exelon specified LLD of 200 pCi/L.

Groundwater and surface water was analyzed for Strontium-89 and Strontium-

90. All Sr-89 and Sr-90 results were less than the MDA.

Groundwater and surface water was analyzed for gross alpha and gross beta in dissolved and suspended fractions. Gross alpha (dissolved) was detected at 8 of 12 groundwater locations sampled. Gross alpha (suspended) was detected at 3 of 12 groundwater locations sampled. Gross beta (dissolved) was detected at 11 of 12 groundwater locations sampled. Gross beta (suspended) was detected at 6 of 12 groundwater locations.

Groundwater and surface water was analyzed for gamma emitting radionuclides associated with the licensed plant operation. All gamma isotopic results were less than the MDA.

Precipitation water samples were analyzed for tritium. All tritium results met the Exelon specified LLD of 200 pCi/L.

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.

1

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 2013.

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

A.

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

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

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

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

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

B.

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

1.

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

2

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 2013. Sample locations can be found in Table A-I, 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 hydrogeologic conditions.

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

Three collection buckets were located on site boundary in the highest prevalent wind sectors and one located on site in the least prevalent 3

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.

Ill.

Program Description A.

Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Limerick Generating Station RGPP in 2013.

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.

4

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, 1-131, 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.

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.

5

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

C.

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

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

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

1.

Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others.

Additional detail may be found by consulting references.

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 strontium-90 6

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 USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected worldwide since 1960. RadNet provides tritium precipitation concentration data for samples collected at stations throughout the U.S. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations have typically been below 100 pCi/L since approximately 1980.

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

Water from previous years was naturally captured in groundwater. As a result, some well water sources today are affected by the surface water from the 1960s that contained elevated tritium 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 7

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.

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 thirteen locations were analyzed for tritium activity (Appendix B, Table B-I.1). Tritium values ranged from non detectable to 477 pCi/L.

Although no drinking water pathway is available from groundwater, the theoretical dose via the drinking water pathway was calculated at 0.03 mrem to a child (total body), which represents 0.47% of the 10 CFR 50, Appendix I dose limit of 6 mrem.

Strontium Samples were analyzed for Sr-89 or Sr-90. All results met required LLDs (Appendix B, Table B-1.1).

Gross Alpha and Gross Beta (dissolved and suspended)

All samples were analyzed for gross alpha and gross beta in the dissolved and suspended fractions during all quarters in 2013. Gross alpha (dissolved) was detected in 8 of 12 groundwater locations sampled. The concentrations ranged from 1.1 to 4.0 pCi/L. Gross alpha (suspended) was detected in 3 of 12 groundwater locations sampled. The concentrations ranged from 1.7 to 3.6 pCi/L. Gross beta (dissolved) was detected in 11 of 12 groundwater locations sampled. The concentrations ranged from 2.4 to 23.0 pCi/L. Gross beta (suspended) was detected in 6 of 12 groundwater locations sampled.

The concentrations ranged from 1.6 to 10.1 pCi/L (Appendix B, Table B-1.1).

Gamma Emitters Samples were analyzed for gamma emitting nuclides. All results met the required LLDs (Appendix B, Table B-1.2).

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 8

concentration at Limerick. Analytical results and anomalies are discussed below.

Tritium Samples from seven locations were analyzed for tritium activity. Tritium activity was not detected in any surface water samples analyzed (Appendix B, Table B-I.1).

Strontium No Sr-89 or Sr-90 activity was detected in any surface water samples analyzed (Appendix B, Table B-11.1).

Gamma Emitters Potassium-40 was detected at one surface water location with a concentration of 82 pCi/L. No other gamma emitting nuclides were detected (Appendix B, Table B-11.2).

C.

Precipitation Sample Results Tritium No tritium activity was detected in any precipitation water samples analyzed.

(Appendix B, Table B-Ill.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 2004 (personal communication with Station, 2006). The pump was placed at a depth of approximately 294 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 175 feet east of the Reactor Building. The Station estimates that the well is pumped at approximately 2 gpm. 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 9

unknown. The well is located approximately 500 feet east of the cooling towers. The well is used only in an emergency fire situation; therefore, water use is estimated to be zero.

E.

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

F.

Leaks, Spills, and Releases There were no spills to ground containing radioactive material in 2013.

However, during the first quarter and fourth quarter of 2013, tritiated water was identified leaking from the expansion joints of the Unit 1 Turbine Building condenser bay. The water was contained and disposed of via the normal radioactive waste processing system. No elevated tritium results were observed in the monitoring wells or the Power Block Foundation Sump in 2013.

G.

Trends No trends were identified.

H.

Investigations Conclusions from the Phase 1 report have been made available to state and federal regulators and to the public. Currently no investigations are on going.

1.

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 wells were installed in 2013

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.

10

APPENDIX A LOCATION DESIGNATION a

Intentionally left blank

TABLE A-i:

Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2013 Location MW-LR-1 MW-LR-2 MW-LR-3 MW-LR-4 MW-LR-5 MW-LR-6 MW-LR-7 MW-LR-8 MW-LR-9 P11 P14 P16 P17 P3 SP22 DW-LR-1 Type Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Distance Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite SW-LR-2 SW-LR-4 SW-LR-6 SW-LR-7 SW-LR-8 (Hold Pond)

SW-LR-9 (Spray Pond)

SW-LR-10 36S3 E-5 ESE-6 SE-7 Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Offsite Offsite Offsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Precipitation Water Precipitation Water Precipitation Water Precipitation Water A-I

Figure 1 Routine Well Water, Surface Water and Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2013.

A-2

SW-LR-3

'.000ýýý Figure 1 Routine Well Water, Surface Water and Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2013.

A-3

n aR

Pm4.ta Smioa Locan Pmecotimu Sample LoMflon Lknedck Guwathu Sbfia Figure 1 Routine Well Water, Surface Water and Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2013.

A-4

APPENDIX B DATA TABLES

Intentionally left blank

TABLE B-1.1 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, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION DATE H-3 SR-89 SR-90 GR-A (DIS)

GR-A (SUS)

GR-B (DIS)

GR-B (SUS)

DW-LR-1 DW-LR-1 DW-LR-1 MW-LR-1 MW-LR-2 MW-LR-2 MW-LR-2 MW-LR-2 MW-LR-3 MW-LR-3 MW-LR-3 MW-LR-3 MW-LR-4 MW-LR-4 MW-LR-4 MW-LR-4 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-7 MW-LR-7 MW-LR-7 MW-LR-7 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 05/07/13 07/30/13 11/07/13 05/09/13 01/15/13 05/09/13 07/30/13 11/06/13 01/15/13 05/09/13 07/31/13 11/06/13 01/15/13 05/09/13 07/30/13 11/05/13 01/15/13 04/12/13 05/09/13 07/30/13 11/05/13 01/16/13 05/09/13 07/31/13 11/06/13 01/15/13 01/15/13 01/15/13 01/30/13 05/07/13 05/07/13 05/07/13 07/30/13 07/30/13 07/30/13 11/05/13 11/05/13 11/05/13 11/20/13 12/27/13 01/15/13 01/15/13 01/15/13 01/30/13 05/07/13 05/07/13 05/07/13 07/30/13 07/30/13 07/30/13 11/05/13

< 178

< 193

< 161

< 163

< 171

< 184

< 185

< 170

< 176

< 186

< 194

< 170

< 180

< 184

< 193

< 169

< 181 183 + 119

< 169

< 183

< 172

< 175

< 191

< 165

< 175

< 176 366 +/- 87

< 176 279 +/- 115 286 +/- 121 228 +/- 82 319 +/- 136 477 +/- 142 376 +/- 95 226 +/- 112 248 +/- 113 289 +/- 99

< 187 234 +/- 128 181 +/- 119 246 +/- 121 352 +/- 86 240 +/- 120

< 162

< 178

< 7.9

< 7.5

< 8.0

< 8.5

< 7.8

< 7.7

< 8.4

< 8.8

< 8.7

< 0.6

< 0.6 2.7 1.8 4.0

<0.5

<2.3 1.2

<0.4

<0.9 1.5

< 1.1 2.2

<0.5

<0.9 1.6

< 1.1

< 1.2

<0.5

<1.5

< 1.7 2.2 1.1

+/- 0.9 < U.5

+/- 0.7 < 0.4

+/- 1.2 < 0.5

< 0.6

+/- 0.7 1.7 - 0.9

< 0.9

+/- 0.8 < 0.4

< 0.8

+/- 0.9 < 0.8

< 0.9

+/- 0.9 < 0.4

< 0.8

< 0.9

< 0.4

+/- 1.3 < 0.8

0.7 < 0.4

0.7 < 0.9

0.6 < 0.4

+0.8 < 0.8

< 0.4

< 0.9

< 0.4

< 0.5

< 0.4 2.2 + 0.9 2.4 +/- 1.0 2.4 t 1.0

< 2.0 10.4 +/- 1.7 3.2 +/- 1.1 2.7 +/- 1.0 2.7 +/- 1.0 3.5 +/- 1.1 3.7 +/- 1.2 3.4 +/- 1.1 3.5 +/- 1.1 4.2 +/- 1.1 4.7 +/- 1.2 4.2 +/- 1.2 3.8 +/- 1.2 5.4 +/- 1.2 7.0 +/- 1.2 1.5 1.6 1.5 1.6 1.8 1.6 1.4 2.1 -+1.0 1.8 1.6 1.4 1.4 1.8 1.6 1.4 1.4 1.6 1.6 1.4 1.4 1.6 1.6 1.4 1.7 1.6 2.9 -+1.3 TBE TBE EIML TBE TBE EIML TBE TBE EIML TBE TBE EIML TBE TBE EIML TBE TBE

< 0.4

< 0.5

<0.6

< 0.6

< 0.6 1.1 1.2 1.9 0.5 1.2 0.6 1.0 1.4 1.6 5.0 4.5 5.9 3.5

< 1.6 3.8 2.9 2.6 4.1

+/- 1.0

+/- 0.9

+/- 1.2

+/- 0.8

+/- 1.2

+/- 1.3 1.6

< 0.8 2.3 +/- 1.0 < 1.0 3.5 +/- 1.4 < 0.4 1.9 +/- 1.2 < 0.4 5.0 +/- 1.2

< 1.5 6.3 +/- 1.2

< 1.6 3.8 +/- 1.2

< 1.6 3.5 +/- 1.2

< 1.6 3.6 +/- 1.2

< 1.7 3.1 +/- 1.1

< 1.7

< 1.5 1.4

< 0.9

+ 0.8 < 0.5

< 6.6

< 9.5

< 0.8

< 0.5

< 0.6

< 0.7 1.7 +/- 0.8 < 0.6

< 0.8

< 0.7 1.5 +/- 0.9 < 0.9

< 0.6

< 0.5 2.5 +/- 0.8 < 0.4 2.1 +/- 0.9 < 0.4 1.4 +/- 0.8 < 0.9 6.3 +/- 1.1 6.1 +/- 1.1 7.3 +/- 1.2 2.8 +/- 0.9

< 1.5 6.7 +/- 1.5 3.6 +/- 1.3

< 1.5 EIML <

TBE TBE EIML TBE 144 247 +/-

255 +/-

298 +/-

267 +/-

132 131 91 114 6.4 +/- 1.1

< 1.6 5.0 +/- 1.1

< 1.6 6.6 + 1.1

< 1.7 B-1

TABLE B-1.1 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, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION DATE H-3 SR-89 SR-90 GR-A (DIS)

GR-A (SUS)

GR-B (DIS)

GR-B (SUS)

I MW-LR-9 MW-LR-9 MW-LR-9 P-11 P-1I P-11 P-1I P-14 P-14 P-14 P-14 P-16 P-17 11/05/13 TBE 11/05/13 EIML 12/27/13 01/15/13 05107/13 07/30/13 11/05/13 01/15/13 05/07/13 07/30/13 11/05/13 01/15/13 05/09/13 223 +/- 114 349 +/- 101 355 +/- 136

182

174

196

163

177

177

198

164

173

175

< 0.9

<0.5 7.2 +/- 1.2

< 1.7

8.8

8.8

6.9

< 2.6

< 0.6

< 2.7

< 0.5 1.9 +/- 1.1

< 0.4

< 1.6

< 0.5

< 2.8

< 0.6

< 0.7

< 1.3

< 2.3

< 3.0

< 2.4

< 2.6 3.6 +/- 1.5

< 0.7

< 1.3

< 0.5 19.8 +/- 2.0 13.9 +/- 1.9 14.9 +/- 1.6 23.0 +/- 1.8 4.2 +/- 1.4

< 1.7 2.4 +/- 1.4 3.0 +/- 1.4

< 1.5 1.6 +/- 1.0

1.6

<1.7

1.5 9.2 +/- 2.0 4.4 +/- 1.4 10.1 +/- 1.9

< 1.7 1.7 +/- 1.0 B-2

-II TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE DW-LR-1 05/07/13

< 36 MW-LR-1 05/09/13

< 41 MW-LR-2 05/09/13

< 32 MW-LR-3 05/09/13

< 47 MW-LR-4 05/09/13

< 38 MW-LR-5 05/09/13

< 35 MW-LR-7 05/09/13

< 49 MW-LR-8 05/07/13 TBE

< 30 MW-LR-8 05/07/13 TBE

< 39 MW-LR-8 05/07/13 EIML < 18 MW-LR-9 05/07/13 TBE

< 29 MW-LR-9 05/07/13 TBE

< 39 MW-LR-9 05/07/13 EIML < 25 P-11 05/07/13

< 35 P-14 05/07/13

< 32 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140

< 58

81

< 55

85

< 45

72

< 55

28

< 74

< 55

25

32

< 54

< 64

< 24

<3

<4

<7

<4

<6

<4

<6

<14

<3

<4

<29

<7 5

3 4

4 4

5 3

4 2

3 4

2 3

3 4

3 5

4 3

6 4

4 2

3 4

3 3

3

<10

<6

<9

<10

<8

< 14

<8

<9

<7

<9

<3

<9

<7

<3

<5

<4

<6

<3

<4

<3

<4

<3

<4

<3

<7

<6

<11

<9

<7

< 12

<5

<7

<6

<7

<5

<4

<5

<3

<4

<3

<5

<3

<4

<9

<7

<8

<7

<8

<6

<7

<5

<6

<7

<4

<7

<6

15

<10

<13

12

< 11

14

13

14

<6

13

14

<5

14

14

<4

<3

<4

<3

<5

<3

<4

<3

<2

<3

<4

<3

<5

<4

<5

<3

<4

<3

<4

<2

<4

<3

< 35

22

32

30

23

<34

28

29

15

25

32

<15

< 29

< 26

<11

<7

<8

<11

<8

<10

<7

<9

<2

<9

<3

<8

<7 P-1 7 05/09/13

< 33

< 25

<4

<3

<7

<4

<6

<4

<6

<11

<3

<4

<21

<7

TABLE B-II.1 CONCENTRATIONS OF TRITIUM, STRONTIUM-89 AND STRONTIUM-90 IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-LR-10 SW-LR-10 SW-LR-10 SW-LR-10 SW-LR-2 SW-LR-2 SW-LR-2 SW-LR-2 SW-LR-4 SW-LR-4 SW-LR-4 SW-LR-4 SW-LR-6 SW-LR-6 SW-LR-6 SW-LR-6 SW-LR-7 SW-LR-7 SW-LR-7 SW-LR-7 SW-LR-8 SW-LR-8 SW-LR-8 SW-LR-8 SW-LR-9 SW-LR-9 SW-LR-9 SW-LR-9 COLLECTION DATE 01/16/13 05/06/13 07/29/13 11/04/13 01/16/13 05/08/13 07/29/13 11/04/13 01/16/13 05/06/13 07/29/13 11/04/13 01/16/13 05/06/13 07/29/13 11/04/13 01/16/13 05/06/13 07/29/13 11/04/13 01/16/13 05/08/13 07/29/13 11/06/13 01/15/13 05/09/13 07/29/13 11/05/13 H-3 SR-89 SR-90

< 175

< 178

< 193

< 163

< 175

< 178

< 192

< 162

< 176

< 173

< 196

< 163

< 180

< 195

< 162

< 177

< 176

< 191

< 166

< 180

< 177

< 193

< 160

< 170

< 179

< 188

< 160

< 9.4

< 7.6

< 7.7

< 7.6

< 0.6

< 0.7

< 0.6

< 7.5

< 0.7

< 8.6

< 7.9

< 0.8

< 0.6 B-4

6 A.'

4 TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 SW-LR-10 05/06/13 SW-LR-2 05/08/13 SW-LR-4 05/06/13 SW-LR-6 05/06/13 SW-LR-7 05/06/13 SW-LR-8 05/08/13 SW-LR-9 05/09/13

< 30

< 57

< 3

<31

< 52

< 3

< 34

< 29

< 3

< 33 82 +/- 41

< 3

< 29

< 22

< 3

< 32

< 31

< 3

< 36

< 4

<3

<7

<3

<7

<4

<8

<4

<8

<3

<6

<3

<8

<4

<9

<3

<4

<3

<2

<3

<4

<5

<6

<7

<6

<7

<3

<6

<3

<6

<4

<7

<3

<6

<3

<5

<3

<6

<3

<7

<14

<3

<10

<3

<15

<3

<13

<3

<13

<3

<13

<3

<14

<4

<3

<27

<7

<3

<23

<7

<4

<30

<7

<4

<27

<8

<3

<22

<7

<3

<23

<8

<4

<30

<9

TABLE B-1I1.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA SITE COLLECTION H-3 DATE 36S3 01/30/13

< 165 36S3 02/26/13

< 198 36S3 03/25/13

< 163 36S3 04/30/13

< 185 36S3 05/29/13

< 183 36S3 06/26/13

< 179 36S3 08/02/13

< 183 36S3 08/28/13

< 192 36S3 09/25/13

< 197 36S3 11/25/13

< 189 36S3 11/25/13

< 182 E-5 01/30/13

< 167 E-5 02/26/13

< 195 E-5 03/25/13

< 180 E-5 04/30/13

< 179 E-5 05/29/13

< 183 E-5 06/26/13

< 184 E-5 08/02/13

< 180 E-5 08/28/13

< 194 E-5 09/25/13

< 196 E-5 11/25/13

< 157 E-5 11/25/13

< 183 ESE-6 01/30/13

< 166 ESE-6 02/26/13

< 200 ESE-6 03/25/13

< 177 ESE-6 04/30/13

< 182 ESE-6 05/29/13

< 183 ESE-6 06/26/13

< 178 ESE-6 08/02/13

< 178 ESE-6 08/28/13

< 195 ESE-6 09125/13

< 197 ESE-6 11/25/13

< 192 ESE-6 11/25/13

< 183 SE-7 01/30/13

< 177 SE-7 02/26/13

< 197 SE-7 03/25/13

< 160 SE-7 04/30/13

< 181 SE-7 05/29/13

< 182 SE-7 06/26/13

< 179 SE-7 08/02/13

< 175 SE-7 08/28/13

< 179 SE-7 09/25/13

< 196 SE-7 11/25/13

< 191 SE-7 11/25/13

< 184 B-6

LG-14-068, 2013 Annual Radiological Environmental Operating Report

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