ML13142A009

Limerick, Units 1 and 2, Annual Radiological Environmental Operating Report, January 1 Through 31 December 2012

ML13142A009
Person / Time
Site:	Limerick
Issue date:	04/30/2013
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML13142A009 (122)

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Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2012 b Prepared By Teledyne Brown Engineering Environmental Services 4 Exeton Generation.

Limerick Generating Station Sanatoga, PA 19464 April 2013 Table Of Contents I. Sum m ary and Conclusions

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1 I1. Introduction

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

3 B. Im plem entation of the O bjectives

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4 II1. Program Description

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4 A. Sam ple Collection

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

6 C. Data Interpretation

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7 D. Program Exceptions

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

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

9 IV. Results and Discussion

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

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

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

10 3. Fish ....................................................................................................

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

11 B. Atmospheric Environm ent .............................................................................

12 1. Airborne .............................................................................................

12 a. Air Particulates

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

13 2. Terrestrial

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

13 b. Broad Leaf Vegetation

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14 C. Am bient Gam m a Radiation

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

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

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

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

15 V. References

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18 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, 2012.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, 2012.Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2012.Figqures 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, 2012.Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2012.Environmental Sampling'Locations Greater Than 26,400 Feet from the Limerick Generating Station, 2012.Data Tables and Figures -Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 201,2.Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2012.

Table C-11.1 Table C-1I.2 Table C-1I.3 Table C-11.4 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, 2012.Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2012 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating'Station, 2012.Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentration.s of 1-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating, Station, 2012.Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2012.Quarterly OSLD Results for Limerick Generating Station, 2012.Mean Quarterly Dosimeter Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2012.Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 -2012.Mean Annual Cs-137 Concentrations in Fish Samples Collected in the Vicinity of LGS, 1982 -2012.Concentrations of Cs-137 in Sediment Samples Collected in the Vicinity of LGS, 1982 -2012.

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-II.1 Table D-Il.2 Table D-1Il.1 Figures Figure D-1 Figure D-2 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 -2012.Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2012.Data Tables and Figures -Comparison Laboratory Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2012.Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2012.Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2012.Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of Gross Beta in Air Particulate and 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2012.Concentrations of 1-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2012.Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2012.Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2012.4 Appendix E Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Appendix F Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2012.ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2012.DOE's Mixed Analyte Performance Evaluation Program (MAPEP)Teledyne Brown Engineering, 2012.ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2012.DOE's Mixed Analyte Performance Evaluation Program (MAPEP)Environmental, Inc., 2012.Annual Radiological Groundwater Protection Program Report (ARGPPR)

Intentionally Left Blank ,4

1. Summary and Conclusions In 2012, the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 72 curies of noble gas, fission and activation products and approximately 88 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 4.69E-03 All Nearest Residence 2.35E-02 20 mRad Noble Gas Beta -Air Dose 3.02E-03 All Nearest Residence 7.55E-03 40 mRad Noble Gas Total Body (Gamma) 4.45E-03 All Nearest Residence 4.45E-02 10 mrem Noble Gas Skin (Beta) 7.47E-03 All Nearest Residence 2.49E-02 30 mrem Iodine, Particulate, Bone 6.28E-01 Child Vegetation 2.09E-00 30 mrem Tritium & C-14 Liquid Total Body 8.09E-02 Child Phoenixville PA 1.35E-00 6 mrem Liquid Liver 8.09E-02 Child Phoenixville PA 4.05E-01 20 mrem The calculated doses, from the radiological effluents released from Limerick, were a very small percentage of the allowable limits.This report on the Radiological Environmental Monitoring Program conducted for the Limerick Generating Station (LGS) by Exelon covers the period 1 January 2012 through 31 December 2012. During that time period, 1277 analyses were performed on 1019 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-137 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 8.33E-05 mrem and 7.14E-05 mrem, respectively.

This dose represents 4.16E-04%

and 1.19E-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.

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 15 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.Environmental gamma radiation measurements were performed quarterly using dosimeters..

Levels detected were consistent with those observed in previous years.Reviewof the gamma spectroscopy results from the surface water samples located at the Limerick intake (24S1) and downstream of the 1 OCFR20.2002 permitted storage area showed no evidence of offsite radionuclide transport from the 2002 permitted storage area.A review of the dosimetry data for the nearest residence to the Independent Spent Fuel Storage Installation (ISFSI) indicates no direct dose was received.A radiological groundwater protection program (RGPP) was established in 2006 as part of an Exelon Nuclear fleetwide assessment of potential groundwater intrusion from the operation of the Station. In 2012, 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 F. 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), Mirion Technologies (Dosimetry Services Division), Landauer Incorporated and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2012 through 31 December 2012.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 REMPin 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 continuous 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 (catfish/carp/white suckers) and predator (sunfish/ba'ss/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 0 analyses on samples of air particulate, airborne iodine, and milk. Airborne iodine and particulate samples were collected and analyzed weekly at six locations (6C1, 10S3, 11S1, 13C1, 14S1, and 22G). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, usinga 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 (10F4, 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. Eight 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, 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, 1OE1, 10F3, 13E1, 16F1, 19D1', 20F1, 24D1, 25D1; 28D2, 29E1, 31D2, and 34E1) extending to approximately5 miles from the site designed to measure possible exposures to close-in population.

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

were determined by the following criteria: 1. The presence of relatively dense population;

2. Site meteorological data taking into account distance and elevation for each of the sixteen-22 1/2 degree sectors around the site, where estimated annual dose from LGS, if any, would be most significant; 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.1OCFR20.2002 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 IOCFR20.2002.

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.6 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-137 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 2012 the LGS REMP had a sample recovery rate of 99%. Exceptions are listed below: 1. Air sample from location 6C1 for the week of 02/13/12 -02/21/12 was not available due to equipment malfunction (IR 1353167).2. Air sample from location 10S3 for the week of 03/12/12 -03/19/12 was not available due to equipment malfunction (IR 1353169).3. Air sample from location 14S1 for the week of 05/14/12 -05/21/12 was not available due to equipment malfunction (IR 1370293).4. Air sample from location 14S.1 for the week of 09/17/12 -09/24/12 was not available due.to loss of power (IR 1419015).5. Limited vegetation.

samples available at station 11 S3 for the month of October (IR 1458463)6. Grab samples were taken. for the composite surface water sampler at location 13B1 during the following periods due to equipment malfunction., frozen sample line, and loss of power due to construction:

01/03/12 -01/09/12. (I R 1353163)01/16/12 -01/23/12 (IR 1353166)06/25/12 -07/01/12 (IR 1458479)07/30/12 -08/06/12 (IR 1458508)'10/29/12 -11/05/12 (IR 1458518)*11/05/12

-11/12/12 (IR.1458520)

7. Grab samples were taken for the composite drinking water sampler at location 16C2 during the following periods due to equipment malfunction:

06/18/12 -08/06/12 (IR 1458472)8. Drinking water location 28F3 showed positive 1-131 above the LLD of 1 pCi/L. The sample was recounted twice at one and four days after the original count, and the concentration of 1-131 increased 8 throughout that period. Due to the short half life of 1-131, this is not consistent with normal 1-131 decay. The increase in activity is thought to be due to an interfering naturally occurring nuclide.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.

E. Program Changes There were no changes in 2012.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 40CFR190 compliance.

.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 9 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

..Net % of Noble Particulate, Liquid Direct Total Applicab Limit Unit Gas lodone, C-14 Effluents Radiation le Limit& Tritium Total Body 4.45E-03 1.27E-01 8.09E-02 O.OOE+00 2.12E-01 8.49E-01 25 mrem Dose Organ Dose 4.45E-03 6.28E-01 8.09E-02 O.OOE+00 7.13E-01 2.85E-02 25 mrem Thryoid Dose 4.45E-03 1.27E-01 8.08E-02 O.OOE+00 I 2.12E-01 2.83E-03 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 (Table C-I. 1, Appendix C). All results met the required LLD.Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-i.2, Appendix C). 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:

10 Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Tables C-11.1, Appendix C). The values ranged from 1.7 to 5.2 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C).Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-11.2, Appendix C). One sample was positive at a concentration of 186 pCi/L.Iodine-131 Monthly samples were taken from all locations and analyzed for lodine-131 activity (Table C-II.3, Appendix C). All results met the required LLD.Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-I1.4, Appendix C). 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 (Table C-I11.1, Appendix C).Naturally occurring K-40 was found at all stations and ranged from 3,286 to 4,517 pCi/kg wet and was consistent with levels detected in previous years. No other gamma emitting nuclides were found.Historical levels of Cs-137 are shown in Figure C-2, Appendix C.4. Sediment Aquatic sediment samples were collected at three locations (16B2, 16C4 and 33A2) semiannually.

Of these locations two, 16B2 and 16C4, located downstream, could be affected by Limerick's effluent releases.

The following analysis was performed:

11 Gamma Spectrometry Sediment samples from all three locations were analyzed for gamma emitting nuclides (Table C-IV. 1, Appendix C). Nuclides detected were naturally occurring Be-7, K-40 and the fission product Cs-137.Beryllium-7 was found at locations 16B2 and 16C4 and ranged from 2,434 to 5,003 pCi/kg dry. Potassium-40 was found at all locations and ranged from 13,500 to 20,710 pCi/kg dry. The fission product Cs-137 was found at locations 16B2 and 16C4 and ranged from 109 to 177 pCi/kg dry (Figure C-4, Appendix C).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-137 activity found at 16B2 and 16C4 is attributed to LGS radioactive effluent releases.

The dose to a teenager's skin and whole body was conservatively calculated at 8.33E-05 mrem and 7.14E-05 mrem, respectively.

This dose represents 4.16E-04%

and 1.19E-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, 1 1S1, and 14S1), Group II represents the locations at an intermediate distance from the LGS site (6C1 and 13C1), 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 (Table C-V.1 and C-V.2, Appendix C).Detectable gross beta activity was observed at all locations.

The results from the on-site locations (Group I) ranged from 6 E-3 to 31 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 29 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3.The results from the Distant locations (Group Ill)ranged from 8 E-3 to 30 E-3 pCi/m 3 with a mean of 17 E-3 12 pCi/m 3.Comparison of the 2012 air particulate data with previous year's data indicate no effects from the operation of LGS (Figure C-4, Appendix C). In addition, a comparison of the weekly mean values for 2011 indicate no notable differences among the three groups (Figure C-5, Appendix C).Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C).Naturally occurring Be-7 due to cosmic ray activity was detected in 23 out of 24 samples. These values ranged from 36 E-3 to 112 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, 1iS1, 14S1, 13C1, and 22G1)and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). All results met the required LLD.2. Terrestrial

a. Milk Samples were collected from five locations (10F4, 18E1, 19B1, 23F1, and 25C1) biweekly April through November and monthly December through March. Samples from one additional location (36E1) were taken quarterly.

The following analyses were performed:

Iodine-131 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VII.1, Appendix C). All results met the required LLD.Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C).Naturally occurring K-40 activity was found in all samples and ranged from 1,017 to 2,049 pCi/L. All other nuclides met the required LLDs.13

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

Gamma Spectrometry Each broad leaf vegetation sample was analyzed for concentrations of gamma emitting nuclides (Table C-VIII.1, Appendix C).Cosmogenic Be-7 was found in 30 of 43 samples and ranged from 226 to 1,818 pCi/kg wet. Naturally occurring K-40 was found in all samples and ranged from 2,124 to 11,430 pCi/kg wet. All other nuclides met the required LLDs.C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing A1 2 0 3:C optically stimulated luminescence dosimeters.

Forty dosimeter locations were established around the site. Results of dosimeter measurements are listed in Tables C-IX.1 and C-IX.2, Appendix C.Dosimeter measurements were reported in gross mrem. Most dosimeter measurements were below 35 mrem/quarter, with a range of 15.6 to 45.6 mrem/quarter.

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, 14 shows the net direct radiation exposure to the nearest residence was zero mrem.F. Land Use Survey A Land Use Survey conducted in September 2012 around Limerick Generating Station (LGS) was performed by Normandeau Associates, Inc.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 ft 2 in each of the sixteen 22 1/2degree 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 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 Residence Feet 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 Garden Feet 3,335 9,610 3,494 14,964 7,776 7,212.6,470 6,898 6,103 5,320 6,527 12,013 4,208 3,932 8,169 5,586 Milk Farm Feet 24,775 22,115 10,390 14,175 14,654 Meat Animal Feet 24,775 20,552 10,927 12,211 10,390 18,547 14,175 14,654 G. Summary of Results -Inter-laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices for 18 and 14 analytes, respectively (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria: 15

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 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, 12 out of 18 analytes met the specified acceptance criteria.

Six analytes (Co-60, Gross Alpha, Gross Beta, Sr-89, Sr-90 and Zn-65) did not meet the specified acceptance criteria for the following reason: 1. Teledyne Brown Engineering's MAPEP March 2012 Co-60 in soil result of 7.61 Bq/kg was higher than the known value of 1.56 Bq/kg, resulting ina found to known ratio of 4.88 on a sensitivity evaluation.

NCR 12-08 was initiated to investigate this failure. No cause could be found for the failure. TBE is monitoring the Co-60 in soil analyses on a case-to-case basis.2. Teledyne Brown Engineering's MAPEP March 2012 Zn-65 in AP result of 4.19 Bq/sample was higher than the known value of 2.99 Bq/sample, exceeding the upper control limit of 3.89 Bq/sample.

NCR 12-08 was initiated to investigate this failure. No cause could 16 be found for the failure and is considered an anomaly specific to the MAPEP sample. The first and second quarter 2012 Analytics AP Zn-65 analyses were acceptable.

3. Teledyne Brown Engineering's MAPEP September 2012 Sr-90 in water result of 19.6 pCi/L was higher than the known value of 12.2 pCi/L, exceeding the upper control limit of 15.9 pCi/L. NCR 12-11 was initiated to investigate this failure. An incorrect aliquot was entered into LIMS. Using the correct aliquot, the result would have fallen within the acceptance range..4. Teledyne Brown Engineering's ERA May 2012 Gross Alpha in water result of 82.4 pCi/L was higher than the known value of 62.9 pCi/L, which exceeded the upper control limit of 78.0 pCi/L. NCR 12-05 was initiated to investigate this failure. The G-1 detector is slightly biased high for Th-230 based measurements.

The G-1 detector is used only for ERA samples. The detector was recalibrated.

5. Teledyne Brown Engineering's ERA November 2012 Gross Beta in water result of 59.3 pCi/L was higher than the known value of 39.2 pCi/L, which exceeded the upper control limit of 46.7 pCi/L. NCR 12-13'was initiated to investigate this failure. The rerun result of 44.8 fell within the control limits. It appears an incorrect aliquot was entered into LIMS.6.. Teledyne Brown Engineering's ERA November 2012 Sr-89 in water result of 46.5 pCi/L was higher than the known value of 39.1 pCi/L, which exceeded the upper control limit of 46.1 pCi/L. NCR 12-13 was initiated to investigate this failure. The found to known ratio was 1.19, which TBE considers acceptable with warning.For the EIML laboratory, 12 out of 14 analytes met the specified acceptance.

criteria.

Two analytes (Gross Beta and Co-57) did not meet the specified acceptance criteria for the following reason: 1. Environmental Inc., Midwest Laboratory's ERA April 2012 Gross Beta in water result of 76.2 pCi/L was higher than the known value of 44.2 pCi/L, exceeding the upper control limit of 51.5 pCi/L. The rerun result of 38.3 fell within the control limits. A sample dilution problem is suspected.

2. Environmental Inc., Midwest Laboratory's MAPEP August 2012 Co-57 in vegetation result of 7.44 pCi/L was higher than the known value of 5.66 pCi/L, exceeding the upper control limit of 7.36 pCi/L.The recount result of 6.74 fell within the control limits. The sample was recounted using a geometry more closely matched to the MAPEP sample size.17 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.

18 APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (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 24 FE-59 CO-60 ZN-65 NB-95 15 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD<LLD<LLD 0 0 0<LLD<LLD<LLD<LLD 0 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (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-1 34 CS-137 BA-140 LA-140 30 <LLD 15 <LLD 15 <LLD 18 <LLD 60 <LLD 15 <LLD<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0 0 DRINKING WATER (PCI/LITER)

GR-B 48 4 3.3 3.2 3.5 15F7 INDICATOR (31/36) (10/12) (11/12) PHOENIXVILLE WATER WORKS (1.8/5.2)

(1.7/4.7)

(2/5.2) 6.33 MILES SSE 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (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 16 48 48 200 186 (1/12)1 <LLD<LLD (1/12)<LLD 186 (1/4)1 (1/12)15F4 INDICATOR 0 PHILADELPHIA SUBURBAN WATER COMPANY 8.62 MILES SE OF SITE 28F3 CONTROL POTTSTOWN WATER AUTHORITY 5.84 MILES WNW OF SITE 0 GAMMA MN-54 15 <LLD CO-58 FE-59 CO-60 ZN-65 15 <LLD 30 <LLD 15 <LLD 30 <LLD<LLD<LLD<LLD<LLD 0 0 0 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (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 1-131 CS-134 CS-137 BA-140 LA-140 15 <LLD 30 <LLD 15 <LLD 15 <LLD 18 -5LLD 60 <LLD 15 <LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (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)GAMMA K-40 4 NA 4076 (2/2)(3634/4517) 4655 (2/2)(4316/4993) 4655 (2/2)(4316/4993) 29C1 CONTROL POTTSTOWN VICINITY UPSTREAM OF INTAKE MN-54 CO-58 FE-59 CO-60 ZN-65 130 <LLD 130 <LLD 260 <LLD 130 <LLb 260 <LLD NA <LLD<LLD 0 0 0 0<LLD<LLD<LLD<LLD<LLD 0 0 0 1-131* 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F). (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 (PCI/KG WET)CS-1 34 CS-137 GAMMA K-40 MN-54 CO-58 FE-59 CO-60 130 <LLD 150 <LLD<LLD<LLD 0 0 4 NA' 3660 (2/2)(3286/4034) 3667 (2/2)(3341/3992) 3667 (2/2)(3341/3992) 29C1 CONTROL POTTSTOWN VICINITY UPSTREAM OF INTAKE 130 <LLD.130 <LLD 260 <LLD 130 <LLD<LLD-<LLD<LLD<LLD 0 0 0 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS PREDATOR (PCI/KG WET)ZN-65 1-131 260 <LLD NA <LLD 130 <LLD 150 <LLD<LLD<LLD<LLD<LLD 0 0 0 0 CS-134 CS-1 37 SEDIMENT (PCI/KG DRY)GAMMA BE-7 6 NA 3550 (4/4)(2434/5003)

NA .17080 (4/4)(14820/20710)

<LLD 4210 (2/2)(3417/5003) 18475 (2/2)(16240/20710) 16C4 INDICATOR VINCENT DAM 2.18 MILES SSE OF SITE 16C4 INDICATOR VINCENT DAM 2.18 MILES SSE OF SITE 0 K-40 13795 (2/2)(13500/14090) 0 0 MN-54 NA <LLD<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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (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-58 CO-60 1-131 NA <LLD NA <LLD NA <LLD 150 <LLD 180 143.(2/4).(109/177)10 17 (249/256)(6/31)<LLD<LLD<LLD<LLD 0 0 0 0 0 0 CS-134 CS-137 GR-B<LLD 17 (51/52)(8/30)177 (1/2)18 (49/50)(8/29)16C4 INDICATOR VINCENT DAM 2.18 MILES SSE OF SITE 14S1 INDICATOR LONGVIEW ROAD 0.63 MILES SSE OF SITE AIR PARTICULATE (E-3 PCI/CU.METER) 308* 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (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)

GAMMA BE7 MN-54 24 CO-58 NA 72 (20/20)(36/112)NA <LLD NA <LLD NA <LLD 50 <LLD 60 <LLD 64 (3/4)(42/80)79 (4/4)(41/112)14S1 INDICATOR LONGVIEW ROAD 0.63 MILES SSE OF SITE<LLD 0 0<LLD 0 CO-60 CS-1 34 CS-1i37<LLD 0 0<LLD<LLD 0 AIR IODINE (E-3 PCI/CU.METER)

GAMMA 308 1-131* THE MEAN AND 2 STANDARD 70 <LLD <LLD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES 0 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK (PCI/LITER) 1-131 114 114 1 <LLD<LLD 0 ,>GAMMA K-40 CS-134 " CS-137 BA-140 LA-140 NA 1312 (88/88)(1017/2049) 15 <LLD*18 <LLD 60 <LLD 15 <LLD 1255 (26/26)(1102/1503) 1444 (22/22)(1196/2049) 10F4 INDICATOR 6.60 MILES ESE OF SITE<LLD 0 0<LLD<LLD<LLD 0 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION (PCI/KG WET)GAMMA BE-7 43 ,>NA 518 (18/28)(226/1179)

NA 5538 (28/28)(2124/11430) 542 (12/15)(235/1818) 5986 (15/15)(2432/8334) 616 (9/15)(226/1179) 6131 (13/13)(2124/11430) 13S3 INDICATOR VINCENT DAM 0.24 MILES SE OF SITE 11S3 INDICATOR LGS INFORMATION CENTER 0.35 MILES ESE OF SITE K-40 MN-54 CO-58 CO=60 NA <LLD NA <LLD NA <LLD 60 <LLD 60 <LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 1-131 "" CS-134 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, 2012 Name of Facility:

LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 2012 Location of Facility:

MONTGOMERY COUNTY, PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION (PCI/KG WET)CS-1 37 RA-226 TH-228 TH-232 80 <LLD<LLD 0 0 NA 1031 (15/28)(265/1998)

NA 44 (4/28)(32/58)NA <LLD NA 26.8 (156/156)(15.6/45.6)

<LLD 73 (5/15)(55/111)128 (1/15)1031 (15/15)(264.6/1998) 73 (5/15)(55/112)128 (1/15)38.4 (4/4)(30.3/45.6) 13S3 INDICATOR VINCENT DAM 0.24 MILES SE OF SITE 31G1 CONTROL 31G1 CONTROL 13S2 INDICATOR 500 KV SUBSTATION 0.41 MILES SE 0 0 0 DIRECT RADIATION OSLD-QUARTERLY (MILLI-ROENTGEN/STD.MO.)

160 32.4 (4/4)(27.9/37.7)

• 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 TABLE B-i: XXYZ -xx Y_Location Designation and Identification System for the Limerick Generating Station General code for identification of locations, where: 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).

S : on-site location A : 0-5,280 feet off-site B : 5,280-10,560 feet off-site C : 10,560-15,840 feet off-site D : 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, 2012 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 Philadelphia Suburban Water Company Phoenixville Water Works Citizens Home Water Company Pottstown Water Authority (control)C. Milk -bi-weekly

/ monthly 10F4 18E1 1981 23F1 Control 25C1 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 22G1 6C1 Keen Road LGS Information Center LGS Information Center (quality control)King Road Longview Road Manor Substation (control)Pottstown Landing Field 2,648 feet E 2,017 feet ESE 2,017 feet ESE 14,980 feet SE 3,319 feet SSE 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 16B2 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 Veqetation 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, 2012 Location Location Description Distance & Direction From Site I. Environmental Dosimetry

-OSLD Site Boundary 36S2 3S1 5S1 7S1 10S3 11S1 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 1OE1 10F3 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 5H 1 6C1 9C1 13C1 15D1 1781 20D1 31DI Birch Substation (control)Pottstown Landing Field 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, 2012 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, 2012 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-ER1 0 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 TLD Thermoluminescence Quarterly TLDs RMC-ER9 Collection of TLD samples for 2 dosimeters Midon Technologies Dosimetry comprised of two radiological analysis (Limerick Generating Panasonic 814 Station)(containing 3 each CaSO4 elements)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 A1 2 0 3:C Landauer Station)Incorporated elements.B-5 I Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2012 B-6 Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2012 B-7 N N N W 2. 5 5 1 4Fo teLimerick G Si 01 G en eratig M03 E r J E P 2.2G 10 SE 1ýMiles Figure B-3 Environmental Sampling Locations Greater than 26,400 Feet from the Limerick Generating Station, 2012 B-8 APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY TABLE C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION 13B1 24S1 PERIOD 12/27/11 -04/02/12 04/02/12 -07/02/12 07/02/12 -10/02/12 10/02/12 -12/31/12< 151 (1) < 149< 200 (1)< 200 (1)< 162 (1)< 193< 196< 188 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1 TABLE C-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 .Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-1 40 PERIOD 13B1 12/27/11 01/31/12 (1) < 4 01/31/12 -02128112 < 5 02/28/12 -04/02/12 < 4 04/02/12 -04/30/12 < 6 04/30/12 -05/29/12 < 4 05/29/12 -07/02/12 (1) < 5 07/02/12 -07/31/12 (1) < 5 07/31/12 -08/27/12 (1) < 3 08/27/12 -10/02/12 < 8 10/02/12 -10/29/12 < 7 10/29/12 -12104/12 (1) < 5 12/04/12 -12/31/12 < 3 MEAN<5<5<4<6<4<4<8< 3.<7<7<5<3<3<5<4<5<7<6<6<4<6<6<5<4< 10< 12<7< 14<6< 10< 13.< 6< 13< 16< 9 56<5<4<3<6<4<4<6<3<7<7<5<3<4<7<4<5<8<5<7<4<6<7<5<4<9<8<8< 13< 10< 10<9<6< 14< 13<9<7<5<4<4<7<3<5<7<3<7<9<4<4<7< 10<6< 11<7<9< 11<5< 14< 14<9<6<6< 10<8< 12<6<8< 11<6< 12< 15<7<7<4< 10<8<9< 15< 12< 10<8< 13< 13<7<8<3<5<4<7<4<5<6<3<7<7<4<3<3<6<3<6<6<5<6<4<6<7<4<3<5<7<3<7<4<4<7<3<7<7<5<4< 19< 30< 20< 32< 17< 30< 29< 16< 40< 38< 20< 18< 15< 23< 20< 24< 36< 25< 33< 23< 34< 31< 20< 22<6<8<6< 11<6<7< 10<5<8< 15<7<5 24S1 12/27/11 -01/31/12 < 3 01/31/12 -02/28/12 < 5 02/28/12 -04/02/12 < 3 04/02/12 -04/30/12 < 5 04/30/12 -05/29/12 < 7 05/29/12 -07/02/12 < 5 07/02/12 -07/31/12 < 6 07/31/12 -08/28/12 < 4 08/28/12-10/02112 < 6 10/02/12 -10/29/12 < 7 10/29/12 -12/04/12 < 4 12/04/12 -12/31/12 < 4<7< 10<8< 10< 14<9< 14<9.< 16< 11< 10<8<8<8<8< 11< 14< 10< 14<9< 11< 12<8<7<4<6<4<5<8<6<6<5< 7<8<4<4<6<8<6<8<9<9< 10<6< 14< 13<8<7<3<5<4<5<9<5<7<4<6<7<4<4<5<7<6<7<7< 11<9<7<9< 12<7<8 MEAN TABLE C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 12/27/11 -01/31/12 01/31/12 -02/28/12 02/28/12 -04/02/12 04/02/12 -04/30/12 04/30/12 -05/29/12 05/29/12 -07/02/12 07/02/12 -07/31/12 07/31/12 -08/27/12 08/28/12 -10/02/12 10/02/12 -10/29/12 10/29/12 -12/04/12 12/04/12 -12/31/12 1.8 4.3 4.8 2.7 2.5 3.3 3.6 3.8 5.2 3.8 2.4 2.8+ 1.0+ 1.5+/- 2.1+/- 1.3+/- 1.5+ 1.1+ 1.2+/- 1.2+/- 1.3+ 1.1+ 1.1+ 1.4 2.0 +/- 1.1 3.3 +/-4.8 +/-3.2 +/-2.3 +/-3.2 +/-3.7 +/-4.5 +/-5.2 +/-4.2 +/-+/-< 2.1 1.4 2.2 1.3 1.5 1.0 1.2 1.3 1.4 1.1 1.1 2.3 +/- 1.1 4.2 +/- 1.5< 3.3< 2.0< 2.5 (1) 3.1 +/- 1.2 (1) 2.3 +/- 1.2 (1) 1.9 +/- 1.2 3.1 +/- 1.3 3.9 +/- 1.1 2.3 +/- 1.2< 2.3 2.9 +/- 1.6 1.7 3.0 3.7 3.0< 2.2 2.2 3.1 3.9 4.5 4.7 2.4< 2.1+/- 1.0+/- 1.4+/- 2.1+/- 1.3+/-+/-!+/-1.0 1.2 1.3 1.5 1.1 1.1 MEAN 3.4 t 2.0 3.5 +/- 2.2 3.2 +/- 2.0 TABLE C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 12/27/11 -04/02/12 04/02/12 -07/02112 07/02112 -10/02/12 10/02/12 -12/31/12 15F4 15F7 16C2 28F3 186 +/- 105 < 149< 195 < 196< 196 <195< 160 < 160< 154< 199 (1)< 198 (1)< 174< 150< 192< 198< 160 MEAN 172 +/- 41 190 +/- 51 TABLE C-11.3 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 12/27/11 01131/12 02/28/12 04/02/12 04/30/12 05/29/12 07/02/12 07/31112 08/28/12 10/02/12 10/29/12 12/04/12-01/31/12-02/28/12-04/02/12-04/30/12-05/29/12-07/02/12-07/31/12-08/27/12-10/02/12-10/29/12-12/04/12-12/31/12< 0.5< 0.3< 0.3< 0.1< 0.3< 0.6< 0.6< 0.6< 0.7< 0.4< 0.6< 0.4< 0.5< 0.6< 0.3< 0.3< 0.3< 0.7< 0.7< 0.6< 0.7< 0.8< 0.6< 0.4< 0.4< 0.4< 0.3< 0.1< 0.3< 0.8< 0.7< 0.7< 0.7< 0.4< 0.6< 0.5 (1)(1)(1)< 0.3< 0.4< 0.3< 0.5< 0.3< 0.6< 0.6 1.2 +/- 0.5 (1)< 0.6< 0.4< 0.5< 0.4 MEAN* THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING 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, 2012 RESULTS IN UNITS OF PCI/LITER

+/- SIGMA SITE COLLECTION PERIOD 15F4 12/27/11 -01/31/12 01/31/12 -02/28/12 02/28/12 -04/02/12 04/02/12 -04/30/12 04/30/12 -05/29/12 05/29/12 -07/02/12 07/02/12 -07/31/12 07/31/12 -08/28/12 08/28/12 -10/02/12 10/02/12 -10/29/12 10/29/12 -12/04/12 12/04/12 -12/31/12 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140<4<7<5<7<6<4<6<3<6<6<4<3<4<6<4<7<5<5<7<4<5<5<4<4< 9< 11<9< 15< 10<7< 13<7< 13< 11< 10<6<4<6<5<6<5<4<7<3<6<6<5<3< 15<9< 17< 12< 12< 12<6< 11< 11< 10<6<4<6<5<7<6<5<7<4<7<7<5<3 MEAN< 8< 11<8< 12< 11<9< 11<6<9< 11<8<6<8< 12<9< 13<9<9< 10<6< 12< 11<7<6< 5<9<8< 11<7< 10< 11<7<9< 14<8<7<4<6<4<7<5<5<6<3<5<7<5<3< 5<6<4<7<7<6<7<4<6<7<5<3< 15< 32< 22< 33< 20< 27< 30< 18< 27< 36< 19< 18< 18< 28< 26< 36< 24< 28< 27< 19< 31< 33<16< 20< 5<8<6< 13<7<6< 10<6< 10< 11<7<5<6< 13<7< 12<9< 10< 10<6< 12< 13<7<6 15F7 12/27/11 01/31/12 02/28/12 04/02/12 04/30/12 05/29/12 07/02/12 07/31/12 08/28/12 10/02/12 10/29/12 12/04/12 01/31/12 02/28/12 04/02/12 04/30/12 05/29/12 07/02/12 07/31/12 08/28/12 10/02/12 10/29/12 12/04/12 12/31/12<5<7<5<7<5<5<5<4<7<5<3<4<5<3<5<8<4<6<5<4<7.<8<3<4<9< 16<9< 15< 11< 11< 15<8< 13< 12<7<7<4<7<5<7<6<4<7<4<6<7<5<4<8< 13< 10< 17<8< 11< 13<8< 15< 12<8<6<5<7<6<8<6<6<6<4<8<8<4<4<7< 11< 10< 14<8< 11<9<7< 10< 12<6<8<5<6<5<8<5<6<5<3<6<7<4<4<6<8<6<8<5<6<6<4<6<7<4<4 MEAN TABLE C-1I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- SIGMA SITE COLLECTION PERIOD 16C2 12/27/11 -01/31/12 01/31/12 -02/28/12 02/28/12 -04/02/12 04/02/12 -04/30/12 04/30/12 -05/29/12 05/29/12 -07/02/12 07/02/12 -07/31/12 07/31/12 -08/27/12 08/27/12 -10/02/12 10/02/12 -10/29/12 10/29/12 -12/04/12 12/04/12 -12/31/12 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 (1)(1)(1)MEAN<5<7<4<6<6<5<5<4<6<5<4<3<4<6<4<6<7<6<5<5<7<7<4<3<4<6<5<6<7<5<6<4<6<6<4<3<4<7<4<7<7<5<6<5<7<7<5<3< 8< 15< 10< 14< 17<8< 14< 8.< 11< 11<9<8<9< 12< 12< 13< 12< 11< 10< 11< 15< 16< 10<7<5<7<5<7<9<5<6<3<5<6<4<4<4<5<5<6<5<5<7<4<7<7<5<3<8< 13<8< 13< 16< .11< 10<7< 12< 10<9<7<6< 13< 10< 15< 12< 12< 11<8< 15< 14< 10<6<5<6<5<6<7<6<6<4<7<6<4<3<4<6<6<7<6<6<6<4<8<9<5<3<7< 11<9< 10< 15< 10< 10<6< 10< 12<8<5<8< 11<9< 12<9<9< 11<8<9< 14<9<5<5< 11<9< 10< 14< 10< 11<9< 10< 14<8<7<6< 11< 11< 13< 11< 10< 10< 11< 13< 12<8<7<4<5<5<6<7<5<6<3<6<5<4<3<5<5<5<7<6<5<5<4<6<7<4<3<5<7<4<7<8<6<6<4<6<5<5<4<5<6<6<8<7<5<6<5<7<8<5<3< 17< 35< 26< 28< 37< 30< 32< 21< 28< 32< 20< 18< 19< 27< 27< 35< 29< 23< 31< 24< 35< 34< 21< 17<7< 11<9<9< 14<6<9<6< 10< 12<6<6<4<9<7< 10< 11< 10< 10<9< 10< 12<4<5 28F3 12/27/11 01/31/12 02/28/12 04/02/12 04/30/12 05/29/12 07/02/12 07/31/12 08/27/12 10/02/12 10/29/12 12/04/12 01/31/12 02/28/12 04/02/12 04/30/12 05/29/12 07/02/12 07/31/12 08/27/12 10/02/12 10/29/12 12/04/12 12/31/12 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION TABLE C-1I1.1 CONCENTRATIONS OF GAMMA EMMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH)SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD 16C5 PREDATOR 05/09/12 10/25/12 MEAN 16C5 BOTTOM FEEDER 05/09/12 10/25/12 MEAN 29C1 PREDATOR 05/08/12 10/24/12 MEAN 29C1 BOTTOM FEEDER 05/08/12 10/24/12 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-134 Cs-137 4034 +/- 879 < 52 3286 +/- 918 <54 3660 +/- 1058 -4517 +/- 1001 < 15 3634 +/- 959 < 49 4076 +/- 1249 -3992 +/- 955 < 58 3341 +/- 926 < 59 3667 +/- 921 -4993 +/- 919 < 48 4316 +/- 864 <54< 42< 59< 117< 105< 52< 58.101< 104< 164< 180<44< 53< 43< 53< 12< 42< 26< 116< 34< 54< 40< 107< 99< 116< 20< 40< 21< 52< 69< 55< 152< 170< 56< 55< 126< 123< 271< 209< 73<44< 64< 56< 47< 55< 106< 102< 60< 72< 85< 122< 178< 158< 46< 54<41< 60 MEAN 4655 +/- 957 TABLE C-IV,1 SITE COLLECTION PERIOD 1682 06/12/12 11/19/12 MEAN 16C4 06/12/12 11/19/12 MEAN 33A2 06/12/12 11/19/12 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs- 137 2434 +/- 693 3346 +/- 841 2890 +/- 1290 3417 +/- 917 5003 +/- 1020 4210 +/- 2243< 501< 1005 16550 +/- 1437 14820 +/- 1617 15685 +/- 2447 16240 +/- 1608 20710 +/- 2105 18475 +/- 6322 13500 +/- 1190 14090 +/- 1907 13795 +/- 834< 74< 98< 78< 110< 51<84< 73* 85< 80< 109< 53< 94< 75< 86<84< 119< 57< 78< 330* 217< 374< 252* 244* 229< 64< 90< 66< 97< 47< 94 109 +/- 84< 116< 81 177 +/- 120< 53< 100 TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD GROUP I I GROUP II I GROUP III 10S3 11i1 14S1 U1 1 351 22G1 01/03/12 01/09/12 01/16/12 01/23/12 01/30/12 02/06/12 02/13/12 02/21/12 02/27/12 03/05/12 03/12/12 03/19/12 03/26/12 04/02/12 04/09/12 04/16/12 04/23/12 04/30/12 05/07/12 05/14/12 05/21/12 05/29/12 06/04/12 06/11/12 06/18/12 06/25/12 07/01/12 07/09/12 07/16/12 07/23/12 07/30/12 08/06/12 08/13/12 08/20/12 08/27/12 09/04/12 09/10/12 09/17/12 09/24/12 10/01/12 10/08/12 10/15/12 10/22/12 10/29/12 11/05/12 11/12/12 11/19/12 11/26/12 12/03/12 12/10/12 12/17/12 12/23/12-01/09/12-01/16/12-01/23/12-01/30/12-02/06/12-02/13/12-02/21/12-02/27/12-03/05/12-03/12/12-03/19/12-03/26/12-04/02/12-04/09/12-04/16/12-04/23/12-04/30/12-05/07/12-05/14/12-05/21/12-05/29/12-06/04/12-06/11/12-06/18/12-06/25/12-07/01/12-07/09/12-07/16/12-07/23/12-07/30/12-08/06/12-08/13/12-08/20/12-08/27/12-09/04/12-09/10/12-09/17/12-09/24/12-10/01/12-10/08/12-10/15/12-10/22/12-10/29/12-11/05/12-11/12/12-11/19/12-11/26/12-12/03/12-12/10/12-12/17/12-12/23/12-12/31/12 17 +/-14 t 16 +/-16 t 18 t 16 +/-17 t 16 +/-8+/-<6 6 5 5 5 5 5 5 5 4 (1)16" 6 12" 5 17" 6 11 5 9+/-5 14" 5 15 5 17+/- 5 14+/- 5 6+/-4 13 6 11 5 13 5 16+/- 5 14 6 16+/- 5 18+/- 5 16 5 18+/- 5 17 5 16 5 22 +/-5 22 +/- 6 29 +/-5 13 6 14 5 15+/- 5 20 +/-5 22 +/-6 14+/- 5 15 5 31 +6<9 20 +/-6 22 +/- 6 27 5 31 +/- 6 10 +/- 5 30 +/- 6 14+/- 6 15+/- 5 14 6 13 5 14+/- 5 16" 5 16+/- 5 15+/- 5 21 +/-5 16+/- 5 13 5 15 5 23 +/-6 11 +/- 5 9+/-5 14+/- 6 12" 5 11 "5 13" 5 10+/- 5 16+/- 5 15+/- 5 11 +/-4 13 6 11+/- 5 9+/-5 17 +/-5 15. 6 16+/- 5 12 5 20 +/-5'21 +/- 5 16+/- 5 21 +/-5 17 +/- 5 25 +/- 6 24 +/- 5 12 +/- 6 14 +/- 5 17 +/- 5 20 +/- 5 21 +/- 5 15 +/- 5 14 +/- 5 25 +/- 6<6 19 +/- 5 25 +/- 6 27 +/- 5 30 +/- 6 17 +/- 5 26 +/- 6 11+/- 5 13+/- 5+/-+/-6 t+/-5+/-5+/-5+/-5+/-5+/-5+/-6+/-5+/-5+/-6.5+/-5+/-6+5"5+5+/-5"5 (1)+/-4+/-6"5+5+5+/-6+/-5+5.5+5+/-5+/-5+/-5+/-6+/-5+/-6"5 (1)+/- 11*+/- 6+5+/-5+/-5 15 +/- 6 14 +/- 5 20 +/- 5 15 +/- 5 15 +/- 5 14 +/- 5 (1)18 +/- 6 12 +/- 5 16 +/- 5 20 +/- 6 16 +/- 6 10 +/- 5 11 +/- 5 12 t 5 9+/-5 18 +/- 5 10 +/- 5 15 +/- 5 11 +/-5 10+/- 4 8 .+/- 5 10 5 11 5 17 5 15 ." 6 19+/-5 13+/-5 13 +/-5 17 5 16 +/- 5 18 +/- 5 13 +/- 5 14 +/- 5 25 +/- 5 12 +/- 6 14 +/- 5 14 +/- 5 20 +/- 5.23 +/-6 20 +/- 5 20 +/- 5 23 +/- 6<6 21 +/- 6 22 +/- 6 29 +/- 5 29 +/- 6 18 +/- 5 23 +/- 6 15 6 14" 5 14 12 11 17 16 14 11 17 9 17 17 9 10 12 13 9 16 12 12<7+/-6+/-5+/-5+/-5+/-'5+/-5+4+/-5"5+/-5"5 t5+/-5+/-6+/-5+/-5+/-5"5+.5 9+/-4 12 6 10+/- 5 12 5 20 +/- 5 24 +/- 6 15+/- 5'12 +/- 5 15+/- 5 21 +/-5 24 6 15+/- 5 18+/- 5 24 +/- 6 25 +/- 5 16 +/- 6 17 +/- 5 12 +/- 5 21:1 6 21 +/-6 16 +/-5 11 "*5 21 +/-6<7 22 +/-6 24 f 6 27 +/-5 26 +/-6 12 +/-.8 23 +/-7 16 +/-6 12" 5 17 9 13 22 14 18 18 18 16 21 20 14 10 18 16 8 17 14 13 14 10 15 12 i1i 19 21 19 11 17 21 20 22 20 26 30 14 16 16 21 21 15 17 23<6 19 16 26 30 14 26 19 13+/-6+/-5+/-5+5+/-5"5"5+/-5"5+/-5+5+/-5"5+/-6+/-5+/-5"5+5+/-5+5+4+/-6+/-5+/-5+/-6+/-5+5+5+/-5"5+/-5+5+/-6+/-5+/- 6."5+/-5+/-6."6+/-5+5+/-6+/-6+/-5+/-5+/-6"5+/- 5.9+ 5.8+/- 4.7 17 28 18 16 19<6 16 5 17+/- 5 24 +/-5 29 +/-6 16+/- 5 23+/- 6 19 6 17 + 5 MEAN 17 +/- 11 16 +/- 10 18 +/- 9 16 +/- 10 16 +/- 10 17 +/- 10* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8 TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 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 01/03/12 01/30/12 02/27/12 04/02/12 04/30/12 05/29/12 07/01/12 07/30/12 09/04/12 10/01/12 11/05/12 12/03/12 01/30/12 02/27/12 04/02/12 04/30/12 05/29/12 07/01/12 07/30/12 09/04/12 10/01/12 10/29/12 12/03/12 12/31/12 MIN MAX MEAN+/-2SD 13 20 16 +/- 4 15 21 17 +/- 4 8 23 14 +/- 10 9 17 13:+/- 5 6 17 13 +/- 6 9 21 14 +/- 6 12 21 17 +/- 6 16 29 21 +/- 7 12 20 16 +/- 5 14 31 20 +/- 11 16 31 24 +/- 10 10 30 17 +/- 12 6 31 17 +/- 10 COLLECTION PERIOD 01/03/12 01/30/12 02/27/12 04/02/12 04/30/12 05/29/12 07/01/12 07/30/12 09/04/12 10/01/12 11/05/12 12/03/12-01/30/12-02/27/12-04/02/12-04/30/12-05/29/12-07/01/12-07/30/12-09/04/12-10/01/12-10/29/12-12/03/12-12/31/12 MIN MAX MEAN+2SD 11 20 15 6 11 -18 15 5 9 20 14 8 9 18 13 7 9 15 11 +/-4 8 24 14 +/- 10 12 21 15 +/-6 13 25 19 +/- 10 12 21 16 +/- 7 11 23 19 +/- 8 21 29 25 +/- 7 12 23 17 +/- 9 8 29 16 +/- 10 COLLECTION PERIOD 01/03/12 01/30/12 02/27/12 04/02/12 04/30/12 05/29/12 07/01/12 07/30/12 09/04/12 10/01/12 11/05/12 12/03/12 01/30/12 02/27/12 04/02/12 04/30/12 05/29/12 07/01/12 07/30/12 09/04/12 10/01/12 10/29/12 12/03/12 12/31/12 MIN MAX MEAN+2SD 9 22 15 +/- 12 14 18 17 +/- 4 10 21 16 +/- 9 8 18 15 +/- 9 10 14 13 +/- 3 11 21 15 +/- 9 11 21 17 +/- 9 20 30 24-+/- 9 14 21 17 +/- 6 15 23 19 +/- 7 16 30 23 +/- 13 13 26 18 +/- 12 8 30 17 +/- 10-I 01/03/12 -12/31/12 01/03/12 -12/31/12 01/03/12 -12/31/12* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD 10S3 01/03112.-

04/02112 04/02/12 -07/01/12 07/01/12 -10/01/12 10/01/12 -12/31/12 Be-7 Mn-54 Co-58 Co-60 Cs- 134 Cs-137 79 91 63 50+/- 26+/- 25+/- 26+/- 19 MEAN 71 +/- 36< 2<3<2<2<3<3<2<3 11S1 01/03/12 04/02/12 07/01/12 10/01/12 MEAN 13C1 01/03/12 04/02/12 07/01/12 10/01/12-04/02/12-07/01/12-10/01/12-12/31/12-04/02/12-07/01/12-10/01/12-12/31/12-04/02/12-07/01/12-10101/12-12/31/12 79 72 66 62 70 +/- 15 -+/- 31+/- 27+/- 21+/- 23<3< 3<4<3<3<4<3<4<3<3<5<3<4<4<3<2<3< 3<2<3<3<3<2<3<3<2<3<3<2<3<3<3< 3.<3< 3<2<3<4<2<4<3<2<3<3<3<4<5<2 56 91 73 36+/- 24+/- 22+/- 34+/- 26 MEAN 64 +/- 48 14S1 01/03/12 04/02/12 07/01/12 10/01/12 72 89 112 41+/- 24+/- 30+/- 45+/- 17<3<2.< 3<3<3<3<3<2<3<3<3<2<2<3<3<2<4<4<2<3<3< 2<3<2< 3<3<4<2<3<2<3<2 MEAN 79 +/- 59 22G1 01/03/12 04/02/12 07/01/12 10/01/12 04/02/12 07/01/12 10/01/12 12/31/12 71 +/- 23 80 +/- 24< 36 42 +/- 15 3 3 5 1<3<2<3<1<4<3<3<2 MEAN*64 +/- 40 6C1 01/03/12 04/02/12 07/01/12 10/01/12 04/02/12 07/01/12 10/01/12 12/31/12 68 105 70 47+/- 26+/- 28+/- 33+ 22<3<3<2<2<4<4<3<3<3<3<3<2<4<3<3<2<4<2<2<2 MEAN 73 +/- 47* THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-10 TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 01/03/12 -01/09/12 01/09/12 -01/16/12 01/16/12 -01/23/12 01/23/12 -01/30/12 01/30/12 -02/06/12 02/06/12 -02/13/12 02/13/12 -02/21/12 02/21/12 -02/27/12 02/27/12 -03/05/12 03/05/12 -03/12/12 03/12/12 -03/19/12 03/19/12 -03/26/12 03/26/12 -04/02/12 04/02/12 -04/09/12 04/09/12 -04/16/12 04/16/12 -04/23/12 04/23/12 -04/30/12 04/30/12 -05/07/12 05/07/12 -05/14/12 05/14/12 -05/21/12 05/21/12 -05/29/12 05/29/12 -06/04/12 06/04/12 -06/11/12 06/11/12 -06/18/12 06/18/12 -06/25/12 06/25/12 -07/01/12 07/01/12 -07/09/12 07/09/12 -07/16/12 07/16/12 -07/23/12 07/23/12 -07/30/12 07/30/12 -08/06/12 08/06/12 -08/13/12 08/13/12 -08/20/12 08/20/12 -08/27/12 08/27/12 -09/04/12 09/04/12 -09/10/12 09/10/12 -09/17/12 09/17/12 -09/24/12 09/24/12 -10/01/12 10/01/12 -10/08/12 10/08/12 -10/15/12 10/15/12 -10/22/12 10/22/12 -10/29/12 10/29/12 -11/05/12 11/05/12 -11/12/12 11/12/12 -11/19/12 11/19/12 -11/26/12 11/26/12 -12/03/12 12/03/12 -12/10/12 12/10/12 -12/17/12 12/17/12 -12/23/12 12/23/12 -12/31/12 10S3< 45< 33< 34* 48* 29< 53<11<18< 57* 24 (1)< 20< 33< 26* 26* 21<41* 41< 33* 58* 68* 61* 51< 54* 60* 68< 28* 58< 40* 24* 13< 23* 25* 68< 47* 29* 62* 19< 53< 34< 39* 36< 54* 40<18< 65< 43< 40< 52* 36* 68< 34 GROUP I lisi* 46< 33< 34< 49* 30< 54* 30<19* 23* 24* 26<18* 29* 25* 26* 21* 42* 42* 56< 59* 27* 63* 52< 55* 60* 68* 28* 58* 40< 24< 35* 23<11* 68< 47* 29< 24<19< 53< 34< 39* 36< 54< 24* 46* 65*16* 40* 52* 36* 68< 34 14S1< 50* 38* 12< 49< 43* 63< 29* 36< 54< 45< 34< 26* 14< 29< 24* 28< 41< 46< 44 (1)< 47< 69* 25< 62* 25* 67* 23< 31< 45* 28< 34< 20< 20* 31* 27< 35< 21 (1)* 19* 38< 36< 36< 44* 28< 45< 47< 42* 31< 32< 35< 69< 45 GROUP II 6C1 13C1< 46 < 20< 33 < 39< 34 < 29< 49 < 50< 30 < 43< 54 < 64 (1) < 30< 19 < 36< 58 < 59< 24 < 45< 26 < 34< 18 < 26< 33 < 29< 25 < 29< 26 < 25< 21 < 28< 23 < 41< 42 < 47< 56 < 57< 59 < 60< 69 < 47< 63 .< 70< 52 < 22< 54 < 62< 59 < 43< 68 67< 28 < 23< 57 < 31< 14 < 40< 24 < 27< 34 < 34< 23 < 21< 25 < 20< 67 < 58< 47 < 19< 28 < 35< 62 < 49< 18 < 22< 52 < 58<34 < 38< 15 < 39< 36. < 36< 18 < 55< 24 < 25< 46 < 47< 64 < 66< 43 < 44< 40 < 41< 51 < 53< 35 < 43< 67 < 69< 34 < 35 I GROUP III 22G1< 49< 37< 27< 48< 17< 62< 29< 35< 52< 44< 33< 25< 28< 28< 10< 27< 40< 45< 43< 58< 45< 68< 24< 60< 43< 66< 10< 31< 45< 27< 35< 20< 20< 58< 27< 35< 50< 21<24< 38<37< 36< 44< 29< 45.< 47< 43< 32< 32< 35< 29< 45 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-ll TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 23F1 CONTROL FARM 36E1 I 10F4 INDICATOR FARM 18E1 19B1 25C1 01/10/12 02/14/12 03/13/12 04/03/12 04/17/12 05/01/12 05/15/12 05/29/12 06/12/12 06/26/12 07/10/12 07/24/12 08/07/12 08/21/12 09/04/12 09/18/12 10/02/12 10/17/12 10/31/12 11/13/12 11/28/12 12/11/12< 0.6< 0.5< 0.5< 0.4< 0.3< 0.3< 0.3< 0.3< 0.5< 0.6< 0.5< 0.6< 0.6< 0.7< 0.5< 0.6< 0.5< 0.4< 0.5< 0.5< 0.7< 0.5< 0.8< 0.4< 0.6< 0.8< 0.7< 0.4< 0.5< 0.4< 0.5< 0.3< 0.5< 0.4< 0.7< 0.6< 0.5< 0.6< 0.6< 0.9< 0.6< 0.7< 0.8< 0.5< 0.8< 0.6< 0.7< 0.6< 0.5< 0.4< 0.5< 0.4< 0.5< 0.3< 0.3< 0.3< 0.6< 0.7< 0.6< 0.7< 0.6< 0.8< 0.6< 0.7< 0.7< 0.5< 0.8< 0.6< 0.8< 0.6< 0.6< 0.7< 0.7< 0.5< 0.5< 0.3< 0.3< 0.4< 0.6< 0.7< 0.6< 0.7< 0.5< 0.8<* 0.5< 0.7< 0.6< 0.5< 0.8< 0.6< 0.7< 0.7< 0.5< 0.6< 0.5< 0.5< 0.4< 0.4< 0.4< 0.3< 0.7< 0.7< 0.6< 0.7< 0.7< 0.7< 0.6< 0.6< 0.7< 0.5< 0.7< 0.8< 0.8< 0.6 MEAN C-12 TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD 10F4 01/10/12 02/14/12 03/13/12 04/03/12 04/17/12 05/01/12 05/15/12 05/29/12 06/12/12 06/26/12 07/10/12 07/24/12 08/07/12 08/21/12 09/04/12 09/18/12 10/02/12 10/16/12 10/30/12 11/13/12 11/27/12 12/11/12 K-40 Cs-1 34 1283 +/-1538 +/-1248 +/-1196 +/-1317 +/-1368 +/-1257 +/-1332 +/-1357 +/-1483 +/-1264 +/-1898 +/-1687 +/-1318 +/-1701 +/-1204 +/-1253 +/-1514 +/-2049 +/-1798 +/-1214 +/-1481 +/-120 186 138 182 126 142 202 175 111 149 142 216 122 148 198 148 161 207 175 136 153 146 MEAN 1444 +/- 485<5<7<6<6<5<6<9<7<4<5<5<7<4<4<6<6<6<7<5<3<6<5<6<6<5<5<6<5<7<7<6<6<6<7<4<5<7<7<7<7<6<5<7<4<5<8<6<5<6<7<8<7<5<6<6<9<5<5<7<7<6<8<7<5<7<6<5<7<6<6<7<5<9<9<6<7<6<9<5<5<8<5<7<9<7<5<8<5< 21< 37< 29< 27< 25< 22< 39< 42< 22< 23< 24< 41< 21< 22< 30< 30< 52< 32< 31< 23< 36< 29< 32< 27< 27< 28< 28< 27< 40< 44< 30< 30< 31< 30< 21< 24< 40< 33< 51< 36< 32< 25< 28< 23 Cs-137 Ba-140 La-140<7< 13<9<9<7<7< 13<9<7<7<7< 10<5<7< 12< 11< 13< 10<8<6<9<9<8< 12< 10<8< 11<7< 14< 13< 10<9<9<8<7<5< 10<8< 13<9<8< 10< 11<7 18E1 01/10/12 02/14/12 03/13/12 04/03/12 04/17/12 05/01/12 05/15/12 05/29/12 06/1 2/12 06/26/12 07/10/12 07/24/12 08/07/12 08/21/12 09/04/12 09/18/12 10/02/12 10/17/12 10/31/12 11/13/12 11/28/12 12/11/12 1079 +/- 158 1285 +/- 179 1288 +/- 117 1232 +/- 136 1359 +/- 143 1261 +/- 118 1111 +/- 170 1154 +/- 182 1302 +/- 147 1224 +/- 143 1220 +/- 137 1290 +/- 169 1261 +/- 118 1104 +/- 122 1184 +/- 174 1159 +/- 171 1170 +/- 142 1315 +/- 195 1275 +/- 181 1213 +/- 140 1289 +/- 164 1182 +/- 114 MEAN 1225 +/- 150 C-13 TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK.GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD 1961 01/10/12 02/14/12 03/13/12 04/03/12 04/17/12 05/01/12 05/15/12 05129112 06/12/12 06/26/12 07/10/12 07/24/12 08/07/12 08/21/12 09104/12 09/18/12 10/02/12 10/16/12 10/30/12 11/13/12 11/27/12 12/11/12 K-40 Cs-134 Cs-137 Ba-140 La-140 1334 +/- 144 1243 +/- 175 1287 +/- 139 1242 +/- 127 1180 +/- 141 1207 +/- 152 1260 +/- 177 1331 +/- 180 1257 +/- 150 1306 +/- 124 1319 +/- 126 1212 +/- 173 1357 +/- 105 1347 +/- 122 1083 +/- 171 1194 +/- 141 1366 +/- 130 1333 +/- 166 1204 +/- 181 1267 +/- 138 1154 +/- 139 1231 +/- 124 MEAN 1260 +/- 147<6<8<6<6<6<5<8<6<6<4<4<6<4<4<7<6<5<6<8<5<6<6<5<5<5<6<5<5<6<5<5<6<5<8<4<5<6<6<5<7<7<4<3<5<7<9<6<6<6<6<7<7<6<6<5<5<5<6< 10<6<6<8<9<7<7<6<6<5<6<6<5<6<7<7<7<7<5<9<4<6<7<7<6<7<7<5<4<6< 28< 35< 31< 28< 30< 30< 40< 39< 27< 28< 20< 35< 18< 24< 46< 34< 46< 45< 37< 29< 31< 27< 24< 27< 26< 26< 28< 26< 30< 26< 30< 35< 24< 40< 19< 27<41< 28< 38< 43< 36< 22< 14< 27< 10.< 14< 10<8<8<9< 13< 14< 11<8<6<9<6<7< 14<9< 15< 11< 11<7<7<7<6<7<8<7<6<8<7<5< 10<8<7<9<5<9<9< 10< 11< 10< 10<5<5<9 23F1 01/10/12 02/14/12 03/13/12 04/03/12 04/17/12 05/01/12 05/15/12 05/29/12 06/12/12 06126/12 07/10/12 07/24/12 08/07/12 08/21/12 09/04/12 09/18/12 10/02/12 10/16/12 10/31/12 11/13/12 11/27/12 12/11/12 MEAN 1130 1267 1249 1102 1280 1267 1187 1503 1315 1386 1365 1249 1280 1244 1280 1144 1222 1324 1258 1187 1153 1339 123 134 134 130 121 118 144 157 138 154 122 165 136 119 192 199 116 186 180 124 150 160 1261 +/- 185 C-14 TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 25C1 01/10/12 02/14/12 03/13/12 04/03/12 04/17/12 05/01/12 05/15/12 05/29/12 06/12/12 06/26/12 07/10/12 07/24/12 08/07/12 08/21/12 09/04/12 09/18/12 10/02/12 10/16/12 10/30/12 11/13/12 11/27/12 12/11/12 MEAN 36E1 01/10/12 04/03/12 07/10/12 10/02/12 1371 +/-1282 +/-1313 +/-1292 +/-1373 +/-1163 +/-1017 +/-1321 +/-1359 +/-1360 +/-1402 +/-1324 +/-1311 +/-1327 +/-1304 +/-1399 +/-1418 +/-1380 +/-1288 +/-1393 +/-1323 +/-1340 +/-143 129 130 154 168 131 155 203 124 116 146 171 103 102 170 197 146 187 145 151 166 123<6<6<4<4<5<6<6<5<5<5<5<7<4<4<8<6<6<7<7<5<6<5<6<5<5<5<7<6<4<5<7<7<8<7<5<5<6<7<5<4<9<7<7<9<6<7<7<5<7<5<6<6< 29< 29< 17< 19< 31< 28< 30< 30< 28< 28< 22< 36< 19< 21< 36< 36< 43< 42< 34< 29< 38< 30< 32< 21< 28< 42<9<7<5<7<6< 10< 10<6<7<6<8< 12<6<6<9<9< 12< 13<9<9<8<9< 10<7<9< 12 1321 +/- 175 1219 +/-1198 +/-1291 +/-1184 +/-154 111 118 133 MEAN 1223 +/- 95 C-15 TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD 11S3 06/13/12 Cat 06/13/12 Coil 06/13/12 Swi 07117112 Cab 07/17/12 Coil 07/17/12 Swi 08/07/12 Cat 08/07/12 Coil 08/07/12 Swi 09/05/12 Cab 09/05/12 Coil 09/05/12 Swi 10/09/12 Swi 10/09/12 (1)10/09/12 (1)Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 bage ards ss Chard ards ss Chard bage ards ss Chard bage ards ss Chard ss Chard 340 +/- 169 529 +/- 238 456 +/- 194< 192 238 +/- 208< 205< 123< 179 465 +/- 201 435 +/- 168 326 +/- 192 506 +/- 170 479 +/- 217 6496 +/- 601 8246 +/- 716 6456 +/- 550 4162 +/- 464 11430 +/- 626 4954 +/- 614 2124 +/- 303 6986 +/- 475 6626 +/- 647 5615 +/- 440 5861 +/- 457 5322 +/- 392 5423 +/- 711< 26< 15< 16< 21< 19< 18< 18< 19< 20< 16< 14< 17< 19< 26< 13< 19< 22< 20< 21< 15< 16< 19< 17< 16< 18< 20< 32< 23< 22< 25< 27< 23< 21< 22< 23< 21< 18< 23< 25< 40< 24< 36< 41< 43< 30< 24< 32< 26< 32< 30< 31< 39< 21< 13< 18< 19< 19< 17< 15< 15< 16< 16< 15< 15< 19< 24< 16< 20< 21< 20< 19< 14< 20< 20< 18< 18< 19< 19< 547< 292< 463< 468< 493< 379< 381< 429< 366< 399< 360< 385< 407< 43< 26< 41< 31< 39< 32< 30 32 +/- 26< 25< 35< 28 38 +/- 24< 34< 94< 60< 77< 77< 86< 78< 64< 76< 75< 69< 70< 76< 94 MEAN*419 +/- 193 6131 +/- 4343 35 +/- 8 13S3 06/13/12 06/13/12 06/13/12 07/17/12 07/17/12 07/17/12 08/07/12 08/07/12 08/07/12 09/05/12 09/05/12 09/05/12 10/09/12 10/09/12 10/09/12 Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Collards Swiss Chard Zucchini Leaves Collards Swiss Chard Zucchini Leaves 226 +/- 182 278 +/- 232 645 +/- 224< 143< 248 479 +/- 238< 96< 193 383 +/- 263< 192 846 t 197 1101_+/- 253.< 182 411 +/- 133 1179 +/- 287 4322 +/- 495 5707 +/- 569 8347 +/- 610 2986 +/- 321 6270 +/- 615 8433 +/- 710 2275 +/- 262 4797 +/- 500 6117 +/- 610 3740 +/- 399 4673 +/- 470 4661 +/- 477 4021 +/- 622 3547 +/- 276 5470 +/- 531< 21< 21< 23< 14< 29< 25< 11< 19< 25< 20< 23< 21< 18< 11< 19< 20< 22< 25< 14< 25< 27< 12< 19< 21< 19< 22< 25< 16< 11< 20< 25< 28< 32< 16< 29< 33< 13< 25< 27< 16< 25< 27< 19< 13< 23< 38< 41< 41< 27< 49< 59< 20< 30< 39< 36< 42< 42< 51< 33< 60< 21< 23< 22< 14< 22< 25< 11< 15< 22< 19< 20< 22< 16< 10< 18< 22< 23< 25< 14< 26< 27< 13< 20< 23< 19< 23< 24< 17< 12< 20 933 +/-650 +/-1511 +/-835 +/-1998 +/-1547 +/-265 +/-773 +/-1304 +/-627 +/-779 +/-1662 +/-1024 +/-739 +/-819 +/-455 512 422 401 685 509 263 503 579 435 443 519 597 282 609< 35< 39< 42< 26< 52< 52< 24< 38< 47< 37< 33.< 43< 33 47 +/- 19 57 +/- 45< 90< 92< 100< 52< 81< 110< 45< 93< 112< 69< 86< 95.< 74< 52< 70 MEAN*616 +/- 703 5024 +/- 3522 1031 +/- 943 52 +/- 15* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION 4 TABLE C-VIIIA CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/KG 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 31G1 06/13/12 06/13/12 06/13/12 07/17/12 07/17/12 07/17/12 08/07/12 08/07/12 08/07/12 09/05/12 09/05/12 09/05/12 10/09/12 10/09/12 10/09/12 Broccoli Leaves Brussel Sprout Leaves Cabbage Broccoli Leaves Brussel Sprout Leaves Cabbage Kale Squash Leaves Zucchini Leaves Broccoli Leaves Cabbage Zucchini Leaves Broccoli Leaves Cabbage Kale 345 +/- 166 240 +/- 146 339 +/- 197 255 +/- 199 249 +/- 187< 211 418 +/- 189 510 +/- 267 610 +/- 199 235 +/- 192< 203 1818 +/- 266 247 +/- 216< 116 1235 +/- 398 5482 +/- 505 4414 +/- 488 4772 +/- 419 7193 +/- 544 5850 +/- 559 8334 +/- 642 6656 +/- 563 6134 +/- 664 7752 +/- 531 4953 +/- 478 6671 +/- 484 6009 +/- 598 5847 +/- 545 2432 +/- 308 7288 +/- 823< 24< 21< 18< 21< 25< 19* 21< 20<19<18< 19*19* 21<15* 25< 22< 20< 20< 22* 24* 23* 20* 20* 22< 17< 20<18* 22* 12*21* 26< 26* 22< 26< 32< 33< 29< 26* 26* 26* 23< 25< 29*18* 28< 40< 27< 33< 40< 50< 45< 35< 29* 31< 36* 36< 30< 46< 29< 42* 21< 19*16< 20< 22< 22< 17< 18* 19< 18< 20< 17< 21*14* 21< 21< 19< 19* 20< 25< 26< 24< 22* 22< 18< 22<16< 22* 14* 27< 543< 441* 467< 466* 587< 528<446* 328< 535* 451< 425< 305< 577* 296* 405* 38< 38< 30* 30< 46< 37< 39 79 +/- 36 111 +/- 34 61 +/- 27 55 +/- 27* 23< 40< 32 57 +/- 50< 89< 76< 83< 95< 103* 105< 106< 92 128 +/- 63< 73< 93< 75< 102< 57* 102 C-)MEAN*542 +/- 982 5986 +/- 2960 -73 +/- 47 -THE MEAN AND 2 STANDARD DEVIATION-VALUES ARE CALCULATED USING THE POSITIVE VALUES TABLE C-IX.1 QUARTERLY OSLD RESULTS FOR LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF MREM/QUARTER

+/- 2 STANDARD DEVIATIONS OF THE STATION DATA STATION MEAN JAN -MAR APR -JUN JUL -SEP OCT -DEC CODE + 2 S.D.2E1 28.9 +/- 8.3 27.5 +/- 4.2 34.6 +/- 0.0 24.8 +/- 4.2 28.6 +/- 0.8 3S1 26.6 +/- 9.7 24.5 +/- 1.4 32.5 +/- 3.1 21.3 +/- 0.7 28.3 +/- 2.4 4E1 21.8 +/- 7.7 21.0 +/- 2.8 26.5 +/- 6.8 17.2 +/- 1.3 22.6 +/- 0.7 5H1 32.4 +/- 8.3 31.0 +/- 0.0 37.7 +/- 1.7 27.9 +/- 4.4 33.0 +/- 0.7 5S1 29.7 +/- 9.7 28.0 +/- 0.0 35.8 +/- 1.6 24.3 t 1.0 31.0 +/- 1.0 6C1 27.7 +/- 10.0 25.5 +/- 1.4 34.7 +/- 0.6 23.1 +/- 2.5 27.7 +/- 1.6 7E1 27.8 +/- 9.9 25.0 +/- 2.8 34.2 +/- 4.0 22.9 +/- 3.4 29.0 +/- 0.1 7S1 27.5 +/- 8.0 27.5 +/- 4.2 31.9 +/- 3.5 22.2 +/- 1.7 28.6 +/- 0.8 9C1 27.0 +/- 11.1 25.0 +/- 2.8 34.6 +/- 3.1 21.5 +/- 1.7 26.9 +/- 1.4 10E1 27.1 +/- 10.2 24.0 +/- 0.0 33.4 +/- 1.0 22.0 +/- 0.4 28.9 +/- 1.7 10F3 26.6 +/- 9.1 25.5 +/- 1.4 32.5 +/- 0.4 21.5 +/- 1.4 26.9 +/- 1.8 10S3 27.2 + 8.2 25.5 +/- 1.4 32.5 +/- 0.8 22.9 +/- 1.0 28.0 +/- 2.4 liSi 31.9 +/- 10.0 30.0 +/- 0.0 38.3 +/- 2.4 26.5+/- 2.1 32.8 +/- 2.1 13C1 20.5 +/- 7.5 20.0 +/- 0.0 24.6 + 1.7 15.6 +/- 0.6 21.6 +/- 0.0 13E1 26.6 +/- 7.4 25.0 +/- 0.0 30.9 +/- 0.3 22.3 +/- 0.6 28.0 +/- 2.5 13S2 38.4 +/- 12.6 38.5 +/- 4.2 45.6 +/- 0.6 3013 +/- 0.7 39.4 +/- 0.6 14S1 24.8 +/- 9.0 23.0 +/- 0.0 30.8 +/- 0.7 20.2 +/- 1.6 25.3 +/- 0.0 15D1 28.9 +/- 9.1 27.5 +/- 4.2 35.2 t 1.7 24.4 +/- 4.1 28.6 +/- 0.3 16F1 28.0 +/- 10.2 25.0 +/- 2.8 34.8 +/- 6.8 23.4 +/- 0.7 28.9 +/- 0.7 17B1 26.0 +/- 8.7 24.5 +/- 4.2 31.5 +/- 4.7 21.1 +/- 0.8 26.8 +/- 2.1 18S2 30.3 +/- 9.9 29.0 +/- 2.8 36.9 +/- 1.6 25.0 +/- 2.7 30.3 +/- 0.8 19D1 25.2 +/- 9.1 23.0 +/- 0.0 31.1 +/- 3.3 20.5 +/- 1.7 26.2 +/- 1.6 20D1 25.0 +/- 8.0 23.5 +/- 1.4 30.2 +/- 0.3 20.7 +/- 0.3 25.5 +/- 0.1 20F1 26.3 +/- 8.9 25.0 +/- 2.8 31.7 +/- 1.3 21.1 +/- 4.1 27.6 +/- 1.6 21S2 25.9 +/- 9.9 24.5 +/- 1.4 32.3 +/- 0.3 20.5 +/- 5.2 26.4 +/- 1.7 23S2 25.5 +/- 9.9 23.5 +/- 1.4 31.9 +/- 4.2 20.2 +/- 1.4 26.5 +/- 0.8 24D1 23.2 +/- 8.1 21.5 +/- 1.4 28.1 +/- 1.7 18.7 +/- 0.7 24.6 +/- 2.3 25D1 22.5 +/- 6.9 21.5 +/- 1.4 26.7 +/- 0.7 18.4 +/- 1.1 23.5 +/- 0.1 25S2 23.7 +/- 8.3 22.5 +/- 7.1 29.2 +/- 1.6 19.2 +/- 1.0 23.9 +/- 0.0 26S3 25.2 +/- 10.2 23.5 +/- 1.4 32.5 +/- 8.6 20.5 +/- 2.7 24.5 +/- 0.4 28D2 25.0 +/- 8.8 23.5 +/- 4.2 30.7 +/- 4.1 20.2 +/- 1.6 25.5 +/- 0.3 29E1 26.1 +/- 7.3 25.0 +/- 2.8 30.7 +/- 0.0 21.9 +/- 1.7 26.6 +/- 0.0 29S1 24.7 +/- 8.4 24.5 +/- 1.4 30.1 +/- 1.6 19.8 +/- 0.4 24.4 +/- 0.3 31D1 31.7 +/- 11.6 29.5 +/- 1.4 39.3 +/- 8.1 25.6 +/- 0.4 32.7 +/- 1.6 31D2 28.2 +/- 9.5 28.5 +/- 4.2 33.9 +/- 1.8 22.3 +/- 0.4 28.0 +/- 1.1 31S1 27.4 +/- 9.4 25.5 +/- 1.4 33.3 +/- 0.7 22.2 +/- 2.8 28.8 +/- 0.6 34E1 26.5 +/- 11.2 24.5 +/- 1.4 34.1 +/- 3.0 20.8 +/- 1.0 26.9 +/- 0.4 34S2 27.5 +/- 8.7 26.0 +/- 0.0 33.0 +/- 2.3 22.6 +/- 0.3 28.5 +/- 2.1 36D1 24.6 +/- 7.4 23.5 +/- 4.2 29.0 +/- 2.7 20.2 +/- 3.3 25.8 +/- 0.3 36S2 27.4 +/- 11.4 25.5 +/- 1.4 34.3 +/- 3.5 20.7 +/- 3.7 29.0 +/- 1.6 C-18 TABLE C-IX.2 MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY, MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF MREM/QUARTER

+/- 2 STANDARD DEVIATIONS OF THE STATION DATA 6 COLLECTION PERIOD SITE BOUNDARY+/- 2 S.D.MIDDLE CONTROL I JAN-MAR APR-JUN JUL-SEP OCT-DEC 26.3 +/- 7.8 33.8 +/- 7.9 22.4 +/- 5.8 28.5 +/- 7.7 24.5 +/- 4.6 31.8 +/- 6.8 21.3 +/- 4.7 26.8 +/- 4.8 31.0 +/- 0 37.7 +/- 0 27.9 +/- 0 33.0 +/- 0 SITE BOUNDARY STATIONS -10S3, l1S1, 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 -2012 12 l. ...:. .....8.. -.. ..... ... ..---*T -i -... ....--L_4..a.6 4~7H V1VI'Z¶~I 2 Tf CONTROL' 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 Note: 2005 analysis changed from Insoluble

& Soluble to Total Gross Beta YEAR LGS CRITICALITY LGS CHi UNIT NO. 1: 12/22/84 OF 2005.UNIT NO. 2: 08/11/89 THAN VW J3 1 99 00 01 02 03 04 05 06 07 08 09 10 11 12 ,NGED TO TOTAL GROSS BETA AT THE BEGINNING PREVIOUS DATA INCLUDED SUMMATION OF LESS ,LUES.

FIGURE C-2 MEAN ANNUAL CS-137 CONCENTRATIONS IN FISH SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 -2012 516C5-*--20SI 55 *-2C ss ... ... ... ... ...-2 9 C I .............................

.. ...... ........ ............i : -Note: Second half of 2000 switched to reporting

< MDC when no activity was detected.Using MDC values result in a..larger number. LLD < 150 35- pCi/kg.E LGS CRITICALITY UNIT NO. 1: 12/22/84..

0 UNIT NO. 2: 08/11/89...

S..........................

..........

C.)15- ..---------------

..------------

5 4 ----- -:--- --. -; ....... I- .... J-. -------- --I- ------- L- ------ ------.----

-L -. " L 82 838485 86 87 88 89 9091 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 11 12 YEAR CONTROL = 29CI Station 20S1 discontinued in 1995 FIGURE C-3 CONCENTRATIONS OF CS-137 IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 -2012 1400-* n -.. , 1

• n -* a.. J *J ".. .... . .. .. ......." .........6B-.16B2 1200 ---. ..:---- -- --.. .--1 C' ;, .- *" *" ,"GS CRITICAL"r1'Y o: : -*-33A~2 UNIT NO. 1: 12122/84 1000 --- : .: UNIT NO. 2-O8/08/11/89..;..................

CONTROL. = 33A~2..00 ..... ...........

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

v 80 a .......im 600 .......--

---

---

------------------

.- ...S400- ~---, .--------. ........200 0 ...... ..........

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

-200 i 82 83 85 86-88-89 91 92 94 95. 97 98 00 .01 03 04 06 07 09 10 12 Year boFIGURE-C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 -2012 150 -..: .: ...10 t !--Groupl 135--- --------------

---

---

--Group II 1-+- Group III 120 : : : : : i i : i i : i l".....1 Chernobyl:...

105 ------E 907-- .----------.------------

.0 90 ... .........-

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

75 ....................................................................

...--- -- ------ ---: : LGS CRITCALITY oo ..... .... ............

_1 ...................................

..."' 4 ... :!

C.)..............

.... ..... .. ..L~l 50 ---------------

NT7 ----- -..AI 15 0 ' I [ i i , * , *.... ... ..: : .... 'o 0 82 84 86 88.. 90 92 94 96 98 00 02 04 06 08 10 12 YEAR FIGURE C-5 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2012 50-GROUP I-*- GROUP II-GROUP III 4 0 -- ---------------------------------------------------I~~E CL C.)w 30 20 10 0 3 6 9 12 15 18 21 24 27 30 33 36 39 42 45 48 51 WEEK NO.

4 APPENDIX D DATA TABLES COMPARISON AND FIGURES LABORATORY TABLE D-I.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+ 2 SIGMA COLLECTION PERIOD 16C2 I 12/27/11 01/31/12 02/28/12 04/02/12 04/30/12 05/29/12 07/02/12 07/31/12 08/27/12 10/02/12 10/29/12 12/04/12 01/31/12 02/28/12 04/02/12 04/30/12 05/29/12 07/02/12 07/31/12 08/20/12 10/02/12 10/29/12 12/04/12 12/31/12 2.3 t 0.8< 1.2 1.3 +/- 0.6< 2.6< 1.9< 1.2< 1.9 1.0 t 0.6 2.6 t 1.0 1.4 t 0.3< 3.2 2.0 t 1.1 1.5 +/- 1.3 MEAN TABLE D-1.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 16C2 12/27/11 -01/31/12 01/31/12 -02/28/12 02/28/12 04/02/12 04/30/12 05/29/12 07/02/12 04/02/12 04/30/12 05/29/12 07/02/12 07/31/12 07/31/12 -08/20/12< 0.2< 0.2< 0.4< 0.2< 0.4< 0.2< 0.4< 0.4< 0.2 08/27/12 10/02/12 10/29/12 12104/12 10/02/12 10/29/12 12/04/12 12/31/12 MEAN TABLE D-1.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 12/27/11 -04/02/12 04102/12 -07/02/12 07/02/12 10/02/12 10/02/12 -12/31/12 136C2* 134* 145* 143* 144 MEAN D-1 TABLE D-1.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD 16C2 12/27/11 -01/31/12 01/31/12 -02/28/12 02/28/12 -04/02/12 04/02/12 -04/30/12 04/30112 -05/29112 05/29/12 -07/02/12 07/02/12 -07/31/12 07/31/12 -08/20/12 08/27/12 -10/02/12 10/02/12 -10/29/12 10/29/12 -12/04/12 12/04/12 -12/31/12 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140<4<2<3<2<3<2<2<4<4<4<4<3<2<2<3<5<3<1<3<2<2<3<3<2<8<5<8<5<4<7<6<8<8<9< 13<6<2<2<3<3<1<3<3<2<2<4<3<2<5<5<5<6<4<2<3<5<5<4<6<5<6<4<7<8<4<4<6<7<7<6<8<3<2<3<5<4<4<2<3<3<3<5<4<2<5<4<8<4<5<5< 12<7<7< 10<9<2<2<3<4<5<3<3<3<3<3<3<5<2<3<2<3<4<3<3<2<3<3<3<4<2< 16<8< 13< 18< 18< 12< 18* 16*16< 23< 27* 12<5<3<3<2<4<2<3<3<3<4<7<2 MEAN TABLE D-II.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE AND 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD Ul/U;/12 -Ul/u9ll2 01/09/12 -01/16/12 01/16/12 -01/23/12 01/23/12 -01/30/12 01/30/12 -02/06/12 02/06/12 -02/13/12 02/13/12 -02/21/12 02/21/12 -02/27/12 02/27/12 -03/05/12 03/05/12 -03/12/12 03/12/12 -03/19/12 03/19/12 -03/26/12 03/26/12 -04/02/12 04/02/12 -04/09/12 04/09/12 -04/16/12 04/16/12 -04/23/12 04/23/12 -04/30/12 04/30/12 -05/07/12 05/07/12 -05/14/12 05/14/12 -05/21/12 05/21/12 -05/29/12 05/29/12 -06/04/12 06/04/12 -06/11/12 06/11/12 -06/18/12 06/18/12 -06/25/12 06/25/12 -07/01/12 07/01/12 -07/09/12 07/09/12 -07/16/12 07/16/12 -07/23/12 07/23/12 -07/30/12 07/30/12 -08/06/12 08/06/12 -08/13/12 08/13/12 -08/20/12 08/20/12 -08/27/12 08/27/12 -09/04/12 09/04/12 -09/10/12 09/10/12 -09/17/12 09/17/12 -09/24/12 09/24/12 -10/01/12 10/01/12 -10/08/12 10/08/12 -10/15/12 10/15/12 -10/22/12 10/22/12 -10/30/12 10/30/12 -11/05/12 11/05/12 11/12/12 11/12/12 -11/19/12 11/19/12 -11/26/12 11/26/12 -12/03/12 12/03/12 -12/10/12 12/10/12 -12/17/12 12/17/12 -12/23/12 12/23/12 -12/31/12 11S2 GROSS BETA 21 + b 25 +/- 4 19 +/- 4 26 +/- 4 28 +/- 4 21 +/- 4 24 +/- 4 22 +/- 5 18 +/- 4 23 +/- 4 22 +/- 4 16 +/- 4 9+/-4 20 -+4 17- 4 17+ 4 23 -+4 14 +/- 4 21 +/- 4 12 +/- 4 13 +/- 4 21 +/- 5 14 +/- 4 12 +/- 4 28 +/- 5 28 +/- 5 26 +/- 4 25 +/- 4 23 +/- 4 24 +/- 4 28 +/- 4 22 +/- 4 26 +/- 4 31 +/- 4 39 +/- 4 26 +/- 5 26 +/- 4 19 +/- 4 28 +/- 4 33 +/- 5 23 +/- 4 21 +/- 4 38 +/- 5 5+/-3 32 -+5 31 +/- 5 36 +/- 5 24 +/-+6 25 +/- 4 32 +/- 5 22 +/- 5 16 +/- 4 11S2 1-131<22Z< 23< 14< 18< 15<7< 13< 16< 18< 10< 12<8< 10< 11< 25< 16< 16< 14< 15< 17< 14< 16< 13< 10< 12< 19< 10< 18<7< 17< 14< 15< 14< 19< 20< 12< 17< 18< 14< 20< 21< 15.< 18< 15< 16< 11< 21< 22< 19< 22< 23< 14 I MEAN 23 +/- 14 D-3 TABLE D-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD 11S2 01/03/12 -04/02/12 04/02/12 -07/01/12 07/01/12 -10/01/12 10/01/12 -12/31/12 MEAN Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 68 + 13 < 0.7 106 +/- 18 < 0.7 88 + 17 < 0.4 54 +/- 18 < 0.5< 0.7< 1.2< 0.9< 0.6< 0.6< 0.8< 1.2< 0.9< 0.7< 1.0< 0.5< 0.9< 0.6< 0.8< 0.5< 0.6 I 79 +/- 46 D-4 TABLE D-II1.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION 1-131 PERIOD K-40 Cs-1 34 Cs-1 37 Ba-140 La-140 0 I 1OF4 01/10/12 04/03/12 07/10/12 10/02/12 MEAN 19B1 01/10/12 04/03/12 07/10/12 10/02/12< 0.2< 0.3< 0.2< 0.3< 0.2< 0.3< 0.2< 0.3< 0.3< 0.4< 0.2< 0.2 1224 +/- 96 1298 +/- 110 1351 +/- 91 1356 +/- 95 1307 +/- 123 1401.4 +/- 101 1361 +/- 106 1396 +/- 112 1455 +/- 89 1403 +/- 78 1273 +/- 95 1363 +/- 106 1317 +/- 113 1416 +/- 81 1342 +/- 122< 3.5< 4.5< 3.7<2.1< 3.2< 2.5< 3.6<3.1< 3.9< 2.5< 3.0< 2.8< 2.9< 4.0< 3.0< 3.2< 2.6< 2.7< 3.3< 2.5< 2.7< 3.9< 2.7< 2.9< 16.2< 13.2< 24.8< 51.9< 19.8< 15.4< 16.3< 23.7< 21.8< 11.4< 22.2< 24.0< 3.0< 2.0< 4.2< 4.8< 6.8< 2.6< 5.7< 3.6< 3.3< 3.4< 6.7< 4.0 MEAN 26C1 01/10/12 04/03/12 07/10/12 10/02/12 MEAN D-5 FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENV AND TBE, 2012 10 9 ..ENV .........................................

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6 ................................................................................................................

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j .... ...Jan -Feb Apr May -Jun -Jul' Aug Sep Oct Nov Dec~~MONTH -

U-f FIGURE D-2 COMPARISON OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11S1 AND 11S2, 2012 50---11S2 -ENV 11SI -TBE 440 C 2 0 -------................................................. ....C? i ' ý A 1x 30 10 -- ----- ----.- ---- ---................

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0 1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.

Intentionally left blank I APPENDIX E INTER-LABORATORY COMPARISON PROGRAM TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2012 (PAGE 1 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)March 2012 E10066 E10067 E10069 E10068 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 101 94.8 pCi/L 11.7 13.5 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 87.5 247 435 133 156 127 190 179 327 274 167 310 107 109 87.6 133 113 226 185 92.5 260 436 149 159 132 195 168 333 279 164 276 94.5 101 83.5 123 106 210 176 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 June 2012 E10070 E10198 E10199 E10201 E10200 pCi 92.8 94.2 pCi/L 1800 1570 pCi/L 86.1 99.8 pCi/L 9.2 12.7 1.07 0.87 0.95 0.95 1.00 0.89 0.98 0.96 0.97 1.07 0.98 0.98 1.02 1.12 1.13 1.08 1.05 1.08 1.07 1.08 1.05 0.99 1.15 0.86 0.72 0.89 0.89 0.98 0.91 0.97 0.97 0.98 1.01 0.97 0.96 0.97 1.00 1.04 1.06 1.01 0.98 1.07 0.99 1.04 1.05 A Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 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 pCi 88.9 72.8 394 159 206 89.5 129 129 193 342 73.2 367 165 205 84.7 118 125 181 338 99.7 82.2 402 174 212 92.3 132 128 199 355 75.1 366 159 193 84.2 121 117 182 324 A W A A A A A A A A A A A A A A A A A A A A AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 101 96.6 E-1 TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2012 (PAGE 2 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)June 2012 E10202 Water Fe-55 pCi/L 1890 1580 pCi/L 106 99.6 pCi/L 13.6 16.0 September2012 E10296 E10297 E10299 E10298 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 89.8 160 230 101 174 97.2 188 159 195 155 145 219 94.1 140 88.3 173 136 165 133 99.6 164 248 108 174 100 196 152 192 152 135 205 89.4 144 83.0 162 125 159 125 AP Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 E10300 pCi 95.5 97.2 pCi/L 1630 1900 pCi/L 101 96.6 pCi/L 11.3 13.8 1.20 1.06 0.85 0.90 0.98 0.93 0.94 1.00 0.97 0.96 1.05 1.02 1.02 1.07 1.07 1.05 0.97 1.06 1.07 1.09 1.04 1.06 0.98 0.86 1.05 0.82 1.03 1.03 1.07 0.95 0.97 0.96 1.00 1.07 1.02 1.01 1.04 1.10 1.02 0.99 1.01 1.05 0.94 0.92 1.08 A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A December2012 E10334 E10335 E10337A Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 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 93.1 52.5 373 157 113 94.1 116 124 190 172 51.8 372 165 113 96.5 118 105 166 179 90.0 51.0 348 165 117 98.5 116 116 186 170 49.6 338 161 114 95.8 112 112 181 165 F..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, 2012 (PAGE 3 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value(a) Value (b) TBE/Analytics Evaluation (d)December 2012 E10336 E10333 Charcoal 1-131 Water Fe-55 pCi 73.1 72.7 pCi/L 1550 1750 1.01 0.89 A A (a)(b)(c)(d)Teledyne Brown Engineering reported result.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.

Ratio of Teledyne Brown Engineering to Analytics results.Analytics evaluation based on TBE internal QC limits: A= Acceptable.

Reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.

N = Not Acceptable.

Reported result falls outside the ratio limits of < 0. 70 and > 1.30.E-3 TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2012 (PAGE 1 OF 1)Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits Evaluation (c)May 2012 RAD-89 MRAD-16 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3.Filter Gr-A Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 Filter Gr-A pCi/L 63.4 pCi/L 33.5 pCi/L 89.2 pCi/L 66.5 pCi/L 152 pCi/L 73.3 pCi/L 109 pCi/L 82.4 pCi/L 43.6 pCi/L 25.9 pCi/L 15433 pCi/filter 39.5 pCi/L 46.5 pCi/L 16.6 pCi/L 85.2 pCi/L 76.9 pCi/L 177 pCi/L 77.4 pCi/L .209 pCi/L 50.6 pCi(L 59.3 pCi/L 22.9 pCi/L 5020 pCi/filter 59.6 58.5 37.4 82.3 74.2 155 72.9 105 62.9 44.2 27.1 15800 46.9 -66.3 27.4 -43.1 69.1 -90.5 60.6 -81.6 140- 172 65.6 -82.6 94.5- 125 33.0 -78.0 29.6 -51.5 22.5-31.9 13800 -17400 77.8 26.1-121 A A A A A A A N (1)A A A A N (2)A A A A A A A N (3)A A November, 2012 RAD-91 39.1 20.1 84.8 76.6 183 78.3 204 58.6 39.2 24.8 4890 29.7 -46.1 14.4 -23.8 71.3 -93.3 62.6 -84.3 165- 203 70.5 -88.5 184 -240 30.6 -72.9 26.0 -46.7 20.6 -29.4 4190-5380 MRAD-17 87.5 29.3-136 A (1) Detector GI is slightly biased high for Th-230 based measurements used only for ERA Gross Alpha samples. NCR 12-05 (2) The Sr-89 found to known ratio was 1.19, which TBE considers acceptable.

NCR 12-13 (3) It appears the aliquot was entered incorrectly for the Gross Beta. NCR 12-13 (a) Teledyne Brown Engineering reported result.(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(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, 2012 (PAGE 1 OF 2)Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)March 2012 12-MaW26 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 -0.0045 Bq/L 37.5 39.9 Bq/L 30.8 32.9 Bq/L 22.4 23.72 Bq/L 456 437 Bq/L 31.0 31.8 Bq/L 144 142 Bq/L -0.0084 Bq/L -0.369 (1)27.9 -51.9 23.0 -42.8 16.60 -30.84 306 -568 22.3 -41.3 99 -185 (1)(1)A A A A A A A A A A A 12-GrW26 Bq/L 2.06 Bq/L 7.48 2.14 0.64-3.64 6.36 3.18 -9.54 12-MaS26 12-RdF26 12-GrF26 12-RdV26 September 2012 12-MaW27 12-GrW27 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 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-137 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/kg 831 828 Bq/kg 0.145 Bq/kg 1270 1179 Bq/kg 7.61 1.56 Bq/kg 634 558 Bq/kg 1690 1491 Bq/kg 328 392 Bq/kg 753 642 Bq/sample 2.31 2.38 Bq/sample 2.15 1.79 Bq/sample

-0.0701 Bq/sample 2.62 2.182 Bq/sample 4.13 3.24 Bq/sample 0.0185 Bq/sample 4.19 2.99 Bq/sample 0.365 1.2 Bq/sample 2.31 2.4 Bq/sample 8.72 8.43 Bq/sample 0.0424 Bq/sample 15.5 12.0 Bq/sample 6.80 6.05 Bq/sample 0.0057 Bq/sample 2.24 2.11 Bq/sample 10.5 8.90 Bq/L 21.4 23.2 Bq/L 17.0 16.7 Bq/L 28.7 29.3 Bq/L 0.179 Bq/L 387 334 Bq/L 18.1 17.8 Bq/L 139 134 Blq/L 19.6 12.2 Bq/L 27.2 25.9 Bq/L 0.966 1.79 Bq/L 10.0 9.1 580- 1076 (1)825 -1533 (2)391 -725 1044- 1938 274 -540 449 -835 1.67-3.09 1.25 -2.33 (1)1.527 -2.837 2.27 -4.21 (1)2.09 -3.89 0.4 -2.0 1.2 -3.6 5.90- 10.96 (1)8.4- 15.6 4.24 -7.87 (1)1.48 -2.74 6.23- 11.57 16.2 -30.2 11.7-21.7 20.5 -38.1 (1)234 -434 12.5-23.1 94 -174 8.5 -15.9 18.1 -33.7 0.54 -3.04 4.6- 13.7 A A A N (3)A A A A A W A W W A N (3)A A A A W A A A A A A A A A A A N (4)A A A E-5 TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING, 2012 (PAGE 2 OF 2)Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)September 2012 12-MaS27 Soil Cs-134 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 880 1220 1330 552 1000 674 528 665 939 1150 1316 531 920 632 508 606 657-1221 805-1495 921 -1711 372-690 644-1196 442-822 356-660 424-788 12-RdF27 12-GrF27 12-RdV27 AP Cs-134 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 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 2.760 0.0415 2.00 1.78 2.40 0.931-0.688 2.74 1.92 -3.56 (1)191.00 1.34-2.48 1.728 1.210 -2.246 2.36 1.65-3.07 1.03 0.72 -1.34 (1)A A A A A A A A A A A A A A A A A A A A A A A A i Bq/sample 0.434 0.97 0.29- 1.65 Bq/sample 1.927 1.92 0.96 -2.88 Bqlsample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 6.28 4.62 6.51 5.32 3.59 0.00 12-0.046 6.51 4.38 5.66.5.12 3.27 4.56- 8.46 3.07 -5.69 3.96 -7.36 3.58 -6.66 2.29 -4.25 (1)(1)r (1) False positive test.(2) Sensitivity evaluation (3) No cause was found for the failed high soil Co-60 sensitivity test or the high Zn-65 in AP, which TBE considers an anomaly. NCR 12.08 (4) Sr-90 in water high due to incorrect aliquot entered in LIMS. 12-11 (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 gravimetric 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., 2012 (Page 1 of 1)I Concentration (pCi/L)Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1 783 04/09/12 Sr-89 62.2 +/- 6.0 58.5 46.9 -66.3 Pass ERW-1 783 04/09/12 Sr-90 33.7 +/- 2.1 37.4 27.4 -43.1 Pass ERW-1786 04/09/12 Ba-133 75.7 +/- 4.1 82.3 69.1 -90.5 Pass ERW-1786 04/09/12 Co-60 71.9 +/- 4.0 72.9 65.6 -82.6 Pass ERW-1786 04/09/12 Cs-134 70.0 +/- 4.3 74.2 60.6 -81.6 Pass ERW-1786 04/09/12 Cs-137 151.5 +/- 6.1 155.0 140.0 -172.0 Pass ERW-1786 04/09/12 Zn-65 108.3 +/- 89.0 105.0 94.5 -125.0 Pass ERW-1 789 04/09/12 Gr. Alpha 55.0 +/- 2.4 62.9 33.0 -78.0 Pass ERW-1789a 04/09/12 Gr. Beta 76.2 +/- 1.8 44.2 29.6-51.5 Fail ERW-1798 04/09/12 H-3 16023 +/- 355 15800 13800 -17400 Pass ERW-6283 10/05/12 Sr-89 41.5 +/- 4.1 39.1 29.7 -46.1 Pass ERW-6283 10/05/12 Sr-90 19.7 +/- 1.6 20.1 14.4- 23.8 Pass ERW-6286 10/05/12 Ba-133 82.7+/- 4.4 84.8 71.3 -93.3 Pass ERW-6286 10/05/12 Co-60 77.2+/- 3.7 78.3 70.5 -88.5 Pass ERW-6286 10/05/12 Cs-134 74.4 +/- 1.5 76.6 62.6 -84.3 Pass ERW-6286 10/05/12 Cs-137 183.0 +/- 6.2 183.0 165.0 -203.0 Pass ERW-6286 10/05/12 Zn-65 211.0 +/- 9.9 204.0 184.0 -240.0 Pass ERW-6288 10/05/12 Gr. Alpha 47.0 +/- 2.3 58.6 30.6 -72.9 Pass ERW-6288 10/05/12 Gr. Beta 33.4 +/- 1.2 39.2 26.0 -46.7 Pass ERW-6290 10/05/12 1-131 23.3 +/- 1.0 24.8 20.6 -29.4 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.d Result of reanalysis:

38.3 +/- 1.3 pCi/L. Sample dilution problem suspected.

A new dilution was prepared.6 E-7 TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)ENVIRONMENTAL, INC., 2012 (Page 1 of 2)Concentration a Known Control Lab Code b Date Analysis -oratory result Activity Limits c Acceptance I STSO-1 766 STSO-1 766 STSO-1 766 STSO-1 766 STSO-1 766 STSO-1 766 STSO-1 766 STSO-1766 STAP-1 772 STAP-1 772 STAP-1 772 STAP-1 772 STAP-1 772 STAP-1 772 STAP-1 772 STAP-1 773 STAP-1 773 STVE-1 776 STVE-1 776 STVE-1 776 STVE-1 776 STVE-1 776 STVE-1 776 02/01/12 02/01/12 02/01/12 02101/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Sr-90 Zn-65 1352.10 1.70 842.20 0.40 1729.60 647.60 383.20 766.70 0.010 2.40 2.33 2.07 3.77-0.010 3.67+/- 4.00+/- 0.70+/- 4.30+/- 0.90+/- 22.20+/- 4.20+/- 15.30+/- 6.70+/- 0.01+/- 0.08+/- 0.13+/-_0.10+/- 0.14+/- 0.060+/- 0.20 1179.00 1.56 828.00 0.00 1491.00 558.00 392.00 642.00 0.00 2.18 2.38 1.79 3.24 0.000 2.99 825.00 -1533.00 1.00 -2.00 580.00 -1076.00 0.00-1.00 1044.00 -1938.00 391.00- 725.00 274.00 -510.00 449.00 -835.00 0.000 -1.00 1.53 -2.84 1.67- 3.09 1.25 -2.33 2.27 -4.21-0,10 -0.13 2.09 -3.89 02/01/12 Gr. Alpha 02/01/12 Gr. Beta 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Zn-65 STW-1960 02/01/12 Gr. Alpha STW-1960 02/01/12 Gr. Beta 0.51 +/- 0.05 2.75 +/- 0.10 14.57 +/- 0.28 6.45 +/- 0.23 8.39 +/- 0.29 0.01 +/- 0.09 0.03 +/- 0.08 10.31 +/- 0.67 1.68 +/- 0.09 6.33 +/- 0.10 33.30 +/- 0.40 23.20 +/- 0.40 0.30 +/- 3.00 40.10 +/- 0.60 460.00 +/- 12.10 153.00 +/- 4.20 32.70 +/- 0.60 0.10 +/- 0.20 0.01 +/- 0.20 1.20 2.40 12.00 6.05 8.43 0.00 0.00 8.90 0.40 -2.00 1.20 -3.60 8.40 -15.60 4.24 -7.87 5.90 -10.96 0.00 -0.10 0.00 -0.10 6.23-11.57 0.64 -3.64 3.18 -9.54 Pass Pass Pass*Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Co-57 Co-60 Cs-1 34 Cs-1 37 H-3 K-40 Mn-54 Sr-90 Zn-65 2.14 6.36 32.90 23.72 0.00 39.90 437.00 142.00 31.80 0.00 0.00 23.00 16.60 0.00 27.90 306.00 99.00 22.30 0.00 0.00-42.80-30.84-1.00-51.90-568.00-185.00-41.30-1.00-1.00 E-8 TABLE E-5 DOE'S.MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)ENVIRONMENTAL, INC., 2012 (Page 2 of 2)Concentration a Known Control Lab Code b Date Analysis oratory result Activity Limits 0 Acceptance STSO-5392 08/01/12 Sr-90 483.52 +/- 16.47 508.00 356.00 -660.00 Pass STSO-5394 08/01/12 Co-57 1528.00 +/- 4.10 1316.00 921.00 -1711.00 Pass STSO-5394 08/01/12 Co-60 592.00 +/- 3.20 531.00 372.00 -690.00 Pass STSO-5394 08/01/12 Cs-1 34 933.60 +/- 5.82 939.00 657.00 -1221.00 Pass STSO-5394 08/01/12 Cs-137 1319.80 +/- 5.50 1150.00 805.00 -1495.00 Pass STSO-5394 08/01/12 K-40 737.30 +/- 17.70 632.00 442.00 -822.00 Pass STSO-5394 08/01/12 Mn-54 1083.20 +/- 5.20 920.00 644.00 -1196.00 Pass STSO-5394 08/01/12 Zn-65 696.10 +/- 7.00 606.00 424.00 -788.00 Pass STVE-5395 d 08/01/12 Co-57 7.44 +/- 0.17 5.66 3.96 -7.36 Fail STVE-5395 08/01/12 Co-60 5.90 +/- 0.15 5.12 3.58 -6.66 Pass STVE-5395 08/01/12 Cs-134 7.40 +/- 0.31 6.51 4.56-- 8.46 Pass STVE-5395 08/01/12 Cs-137 5.45 +/- 0.18 4.38 3.07 -5.69 Pass STVE-5395 08/01/12 Mn-54 4.06 +/- 0.21 3.27 2.29 -4.25 Pass STAP-5398 08/01/12 Gr. Alpha 0.41 +/- 0.05 0.97 0.29 -1.65 Pass STAP-5398 08/01/12 Gr. Beta 2.11 +/- 0.09 1.92 0.96 -2.88 Pass STAP-5403 08/01/12 Co-57 1.96 +/- 0.05 1.91 1.34 -2.48 Pass STAP-5403 08/01/12 Co-60 1.76 +/- 0.07 1.73 1.21 -2.25 Pass STAP-5403 08/01/12 Cs-1 34 2.74 +/- 0.18 2.74 1.92 -3.56 Pass STAP-5403 08/01/12 Cs-137. 0.00 +/- 0;03 0.00 -0.01 -0.01 Pass STAP-5403 08/01/12 Mn-54 2.52 +/- 0.10 2.36 1.65 -3.07 Pass STAP-5403 08/01/12 Zn-65 0.01 +/- 0.06 0.00 -0.010 -0.010 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: STW (water), STAP (air filter), STSO (soil), STVE (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.d Result of reanalysis; 6.74 +/- 0.15 Bq/sample.

Gamma emitters for the vegetation matrix exhibited a high bias, only Co-57 exceeded acceptance limits. Recounted using a geometry more closely matched to the MAPEP sample size.4 E-9 Intentionally left blank APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2012 Prepared By Teledyne Brown Engineering Environmental Services SExton Generation, Limerick Generating Station Sanatoga, PA 19464 U April 2013 Table of Contents I. Sum m ary and Conclusions

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

J I1. In tro d u c tio n ........................................................................................................................

2 A. Objectives of the RGPP ..................................................................................

2 B. Im plem entation of the O bjectives

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2 C. Program Description

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

4 Ill. Program Description

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5 A. Sam ple Analysis ...............................................................................................

5 B. Data Interpretation

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

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

7 IV. Results and Discussion

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

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

9 C. Precipitation W ater Results ............................................................................

10 D. Drinking W ater W ell Survey ............................................................................

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

11 F. Leaks, Spills, and Releases ............................................................................

11 G .Trends .............................................................................................................

11 H. Investigations

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12 I. Actions Taken ...................................................................................................

12 V. References

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12 0 Appendices Appendix A Tables Table A-1 Location Designation Radiological Groundwater Protection Program -Sampling Locations for the Limerick Generating Station, 2012 Figures Figure 1 Figure 2 Figure 3 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2012 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating.

Station, 2012 Routine Precipitation Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2012 Appendix B Tables Table B-1.1 Data Tables Table B-1.2 Table B-11.1 Table B-11.2 Table B-1ll.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, 2012.Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2012.Concentrations of Tritium, Strontium-89 and Strontium-90 in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2012.Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2012.Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2012.ii I. Summary and Conclusions This report on the Radiological Groundwater Protection Program (RGPP)conducted for the Limerick Generating Station (LGS) by Exelon Nuclear covers the period 01 January 2012 through 31 December 2012. During that time period, 399 analyses were performed on 158 samples from 12 groundwater, 9 surface water and 4 precipitation water locations collected from the environment, both on and off station property 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.Tritium was not detected in any of the groundwater or surface water samples at concentrations greater 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 four of the twelve groundwater monitoring locations.

The tritium concentrations ranged from 156 to 14,200 pCi/L. Low levels of tritium were detected at three of seven surface water locations.

The concentrations ranged from 172 to 191 pCi/L.Tritium was not detected in any precipitation water samples above the Exelon specified LLD of 200 pCi/L.Strontium-89 and Strontium-90 were not detected in either the groundwater or surface water samples.Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions performed on groundwater samples during all quarters in 2012. Gross Alpha (dissolved) was detected at 7 of 12 groundwater locations.

The concentrations ranged from 1.0 to 3.6 pCi/L. Gross Alpha (suspended) was detected at.3 of 12 groundwater.

The concentrations ranged from 2.4 to 7.7 pCi/L. Gross Beta (dissolved) was detected at all 12 groundwater locations.

The concentrations ranged from 2.3 to 22.2 pCi/L. Gross Beta (suspended) was detected at 3 of 12 groundwater locations.

The concentrations ranged from 2.0 to 9.0 pCi/L.Gamma-emitting radionuclides associated.with licensed plant operations were not detected in either groundwater or surface water samples.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 II. Introduction The Limerick Generating Station (LGS), consisting of two 3515 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania.

Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL.This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2012.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 2

were made available to state and federal regulators in station specific reports.2. The Limerick Generating Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.

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

4. Limerick Generating Station has procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.5. Limerick Generating Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.C. Program Description Samples for the ongoing ground water monitoring program were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2012. 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.3 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 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 (3 He). 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 4 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 2012.In order to achieve the stated objectives, the current program includes the following analyses: 1. Concentrations of tritium in groundwater, surface water and precipitation water.2. Concentrations of Gross Alpha, Dissolved and Suspended and Gross Beta, Dissolved and Suspended in groundwater.

3. Concentrations of gamma emitters in groundwater and surface water.4. Concentrations of strontium 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 loperational 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 5 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.

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.

6 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 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 7 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 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 Gamma spectroscopy results for groundwater and surface water sample were reported for 14 nuclides (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).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.8 Tritium Samples from twelve locations were analyzed for tritium activity (Table B-1.1, Appendix B). Tritium values ranged from non detectable to 14,200 pCi/L. Well MW-LR-5 had the highest value of 14,200 pCi/L. Although no drinking water pathway is available from groundwater, the theoretical dose via the drinking water pathway was calculated at 0.08 mrem to a child (total body), which represents 1.30% of the 10 CFR 50, Appendix I dose limit of 6 mrem.Strontium No Sr-89 or Sr-90 activity was detected in any of the ground water samples analyzed (Table B-1.1, Appendix B).Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during all quarters in 2012. Gross Alpha (dissolved) was detected in 7 of 12 groundwater locations.

The concentrations ranged from 1.0 to 3.6 pCi/L. Gross Alpha (suspended) was detected in 3 of 12 groundwater locations.

The concentrations ranged from 2.4.to 7.7 pCi/L. Gross Beta (dissolved) was detected in all 12 groundwater locations.

The concentrations ranged from 2.3 to 22.2 pCi/.L. Gross Beta (suspended) was detected in 3 of 12 groundwater locations.

The concentrations ranged from 2.0 to 9.0 pCi/L (Table B-1.1, Appendix B).Gamma Emitters No gamma emitting nuclides were detected (Table B-1.2, Appendix B).B. Surface Water Results In accordance with the Station's radiological groundwater protection program surface water samples were collected from streams that transverses the site, as well as, from other water bodies, that could influence the tritium concentration at Limerick.

Analytical results and anomalies are discussed below.Tritium Samples from eight locations were analyzed for tritium activity.

Tritium activity was detected in stations SW-LR-8 and SW-LR-10.

The concentrations were 172 and 191 pCi/Liter (Table B-11.1, Appendix B).9 Strontium No Sr-89 or Sr-90 activity was detected in any surface water samples analyzed (Table B-11.1, Appendix B).Gamma Emitters Potassium-40 was detected at one surface- water location with a concentration of 134 pCi/L. No other gamma emitting nuclides were detected (Table B-11.2, Appendix B).C. Precipitation Sample Results Tritium No tritium activity was detected in any precipitation water samples analyzed. (Table B-1ll.1 Appendix B)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 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.10 E. Summary of Results -Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.F. Leaks, Spills, and Releases On March 19, 2012 water was observed overflowing from the Cooling Tower Blowdown Line emergency relief top hat. Concurrently, a tank of contaminated water was being released via the approved pathway to the Schuylkill River. The overflowed water traveled into Possum Hollow Creek and then to the Schuylkill River. The initial sample taken showed only tritium, at a concentration of 112,000 pCi/L. The area was remediated on 3/20/12 by pumping out the standing water and removing the sludge and silt in the nearby ditch where water had accumulated.

A bounding dose calculation was performed.

The maximum daily organ dose from the 3/19/2012 release to Possum Hollow was 0.175 mrem to a child liver. The maximum daily total body dose to a child was 0.123 mrem.This calculation was based upon the following assumptions:

1. Reg Guide 1.109 equation D-1 methodology was used.2. A dilution factor of 30 was used for cooling tower dilution.3. Drinking Water and Fish dose calculated at LGS Discharge (same location as.Possum Hollow).4. 1 day exposure (2 L drinking water consumption, 0.5 kg fish consumption).

The resulting calculations were both less than 10 % of the Appendix I Annual dose limits of 20 mrem organ dose and 6 mrem total body dose.This issue is documented in the following IRs: 1342540, 1344180, 1347829, 1342884, and 1350714.G. Trends No trends were identified.

11 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.I. Actions Taken 1. Compensatory Actions There have been no station events requiring compensatory actions at the Limerick Generating Station.2. Installation of Monitoring Wells No new wells were installed in 2012 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.

12 APPENDIX A LOCATION DESIGNATION Intentionally Left Blank TABLE A-i: Radiological Groundwater Protection Program -Sampling Locations for the Limerick Generating Station, 2012'4 9 Location MW-LR-1 MW-LR-2 MW-LR-3 MW-LR-4 MW-LR-5 MW-LR-7 MW-LR-8 MW-LR-9 P11 P14 P16 P17 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 Distance 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 (Possum Hollow Creek)Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Precipitation Precipitation Precipitation Precipitation Offsite Offsite Offsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite 36S3 E-5 ESE-6 SE-7 4 A-1 P-3 MW-LR-7 0 P-17 S sw-LR-9 Sh2 8P22 s9 VWLR-6 J~W"A1R-94 MW-~2~ p160 A-4R LI Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2012 Il R-1 V-LR-7 lb A-2

0) SW -R ...............

SW-LR-2 SWV-LR-6 4WLR Figure 2 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2012 A-3 3+&4 R 4 0 SEI ES"4 m7 a Ps Puedmw $amp* LoeWun Eniqion *.npl. o i i Figure 3 Routine Precipitation Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2012 0 A-4 4 it APPENDIX B DATA TABLES f Intentionally Left Blank TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM-89, STRONTIUM-90, GROSS ALPHA AND GROSS BETA IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUND WATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION H-3 SR-89 SR-90 GR-A (DIS) GR-A (SUS)GR-B (DIS) GR-B (SUS)4 MW-LR-1 MW-LR-2 MW-LR-2 MW-LR-2 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-4 MW-LR-4 MW-LR-4 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 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 DATE 04/24/12 01/24/12 03/22/12 03/23/12 03/26/12 04/24/12 07/18/12 10/09/12 01/25/12 04/24/12 07/18/12 10/09/12 01/25/12 03/22/12 03/23/12 03/26/12 04/24/12 07/18/12 10/09/12 01/24/12 03/20/12 03/21/12 03/21/12 03/22/12 03/23/12 03/26/12 04/02/12 04/09/12 04/16/12 04/24/12 04/24/12 04/24/12 06/05/12 07/18/12 07/18/12 07/18/12 10/09/12 01/24/12 04/24/12 07/18/12 10/09/12 01/24/12 01/24/12 01/24/12 04/24/12 07/17/12 10/10112 10/10/12 10/10/12 10/10/12 11/29/12< 170< 169< 169< 187< 189< 189< 194< 192< 160< 191< 195< 181< 172< 174< 183< 189< 187< 194< 196< 170 14200 +/- 1450 11400 +/- 1180 11177 +/- 312 8200 +/- 862 4270 +/- 479 1280 +/- 187 1660 +/- 219 383 +/- 122 274 +/- 116 720 +/- 141 1020 +/- 172 696 +/- 107 307 +/- 127 397 +/- 141 267 +/- 132 485 +/- 102 215 +/- 131< 169< 188< 194< 193 180 +/- 113 225 +/- 116< 4.0< 3.9< 3.9< 0.9 < 0.8< 1.0< 0.8 1.0< 1.0 2.5 1.5< 0.7 < 1.0< 1.4 2.9< 1.8< 0.5< 0.4 8.2 +/- 1.3 < 1.6 2.6 +/- 0.9 < 1.5+/- 0.6 < 0.7< 0.5+1.1 < 1.0+ 0.9 < 0.4< 0.7< 0.5+ 1.4 < 1.0< 0.4+/- 1.3 < 0.7< 0.5+ 1.4 < 1.0+0.6 < 0.4 2.3 2.6 4.3 4.8 3.9 3.1 3.5 6.7 4.0 3.9 6.4 6.1+/- 0.9+/- 0.9+/- 1.2+/- 1.1+ 1.2+/- 1.2+/- 1.2+ 1.3< 1.6< 1.6< 1.8< 1.5< 1.6< 1.6< 1.8< 1.5< 1.6< 1.6< 1.7< 1.5< 3.6< 0.9 EIML EIML EIML 2.2< 2.1 2.2 1.4< 0.5< 0.8+/-+/-+/-+1.3 1.3 1.4 1.0<4.1< 3.7< 0.8< 0.8< 0.6< 0.5< 0.5 3.6 +/- 0.8 < 1.6 5.1 +/- 1.1 < 1.6 I<4.1 1.5< 1.1 1.9 1.9< 0.4< 0.9 < 0.6< 0.9< 0.8< 1.7 1.8< 0.7 < 1.7< 1.8< 2.3 3.6< 3.1+/- 0.7 < 0.3< 0.4+/- 1.2 < 1.3+/- 0.9 < 1.0< 0.8< 0.5< 0.4< 1.0< 0.3+/- 0.9 < 0.8< 0.5< 0.4< 1.0+/- 2.2 < 1.0< 0.5 5.8 5.5 5.6 7.8 3.7 3.0 2.9 3.5 4.9 3.4+ 1.1+ 1.1+ 1.5+ 1.3+/- 0.9+/- 0.9+/- 0.9+ 0.9+/- 1.3+ 1.2< 1.7< 1.7< 3.8< 1.8< 1.5< 1.6< 1.7< 1.8< 1.8< 1.5< 1.6< 1.7< 1.9< 1.9 EIML < 143 286 +/- 130 < 4.2< 194< 193 258 + 133 195 + 119 273 +/- 86 275 +/- 119< 1.9< 1.8 2.8 +/- 1.3 4.4 +/- 1.5 EIML 3.2 +/- 1.3 < 1.7 B-1 TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM-89, STRONTIUM-90, GROSS ALPHA AND GROSS BETA IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUND WATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2012 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-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 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 P1l Pl1 P1l P1l P1l P14 P14 P14 P14 P16 P16 P16 P16 P17 12/12/12 12/27/12 01/24/12 01/24/12 01124/12 04/24/12 04/24/12 04/24/12 07/17/12 07/17/12 07/17/12 08129112 10/10/12 10/10/12 10/10/12 11/29/12 12/12/12 12/27/12 01/24/12 04/24/12 07/17/12 10/10/12 11/29/12 01/24/12 04/24/12 07/17/12 10/10/12 01/24/12 04/24/12 07/17/12 10/10/12 04/24/12 338 +/- 125< 192 197 +/- 107< 167 EIML 156 +/- 94 222 +/- 114 < 3.9 319 +/- 133 < 3.8 EIML < 153 795 +/- 161 833 +/- 159 EIML 739 +/- 112 872 +/- 148 274 +/- 135 346 +/- 144 EIML 318 +/- 88 362 +/- 124 372 +/- 128 312 +/- 135< 171< 188 < 3.7< 188< 197< 168< 170 270 +/- 131 < 4.6< 194< 194< 170< 1.1 2.4 +/- 0.9 1.7 +/- 0.9 < 0.8 7.5 +/- 1.2 '2.0 +/- 1.3 9.9 +/- 1.3 < 1.6< 1.0< 0.8< 0.6 1.9 + 0.7 < 0.5 1.7 +/- 0.8 < 1.2 5.9 +/- 1.1 5.1 +/- 1.1<3.1< 0.7 2.2 1.7 2.1 2.5< 1.6<0.7 <3.2< 1.5<3.0<2.9<0.4 <2.4<2.1<2.9<6.8 1.7< 3.2<0.9 <1.3< 0.6< 0.7 1.4 < 1.3 0.8 < 1.0 0.9 < 1.0 1.2 < 0.5 15.8 +/-5.1 +/-5.6 +/-6.1 +/-7.0 +/-4.9 +/-15.0 +/-22.2 +/-22.0 +14.1 +/-2.7 1.1 1.5 1.1 1.1 1.2 1.6 2.1 1.9 1.6< 0.8< 1.1-< 0.6< 1.0< 1.6 2.8 +/- 1.2< 2.8< 1.8< 3.8< 1.9< 1.9 2.8 +/-1.3< 1.5< 1.5< 1.8<1.7 3.5 +/-1.4< 1.5< 1.8< 1.8 9.0 +/-5.1< 1.7< 2.9< 1.6 2.4 +/- 1.0< 1.1< 0.6< 1.1 7.7 +/- 2.7+/-0.8 < 0.3 4.9 +/- 1.3< 0.5 4.1 +/- 1.5 2.9 +/- 1.3< 2.2 2.4 +/- 1.4 14.7 +/- 7.5 5.8 +/- 1.2 13.8 +/- 3.1 3.8 +/- 1.2< 192< 191< 174< 187< 4.2 B-2

-& q -TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2012 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 MW-LR-1 04/24/12 < 50 < 46 MW-LR-2 04/24/12 < 28 < 75 MW-LR-3 04/24/12 < 31 < 66 MW-LR-4 04/24/12 < 50 < 94 MW-LR-5 03/20/12 < 53 < 58 MW-LR-5 03/21/12 < 43 < 77 MW-LR-5 03/21/12 EIML < 26 < 60 MW-LR-5 04/24/12 < 61 < 95 MW-LR-5 04/24/12 < 47 < 119 MW-LR-5 04/24/12 EIML < 38 < 76 MW-LR-7 04/24/12 < 62 < 59 MW-LR-8 04/24/12 < 51 < 65 MW-LR-9 04/24/12 < 49 < 62 MW-LR-9 04/24/12 < 34 < 61 MW-LR-9 04/24/12 EIML < 19 < 61 P11 04/24/12 < 61 < 96 P14 04/24/12 < 42 < 118 P17 04/24/12 < 46 < 33<5 <6 <12<3 <3 <7< 3 <4 <8<5 <5 <12<6 <5 <9<4 <4 <10<3 <3 <6<7 <7 <13<6 <4 <6<4 <2 <9<6 <6 <13<6 <6 <12<5 <6 <10<4 <4 <8<3 <2 <5<5 <6 <12<5 <7 <10<4 <4 <12<5 <10 <6 <9<3 <5 <3 <3<4 <7 <4 <6<6 <11 <6 <10<5 <10 <7 <10<5 <10 <5 <8<3 <7 <3 <4<7 <16 <9 <12<5 <10 <6 <7<4 <7 <6 <7<5 <14 <9 <10<5 <11 <7 <11<6 <11 <6 <9<4 <9 <5 <7<2 <5 <2 <6<5 <12 <8 <9<6 <11 <7 <10<7 <10 <6 <8<10 <5 <6 <25 <8<6 <3 <4 <14 <5<5 <3 <3 <15 <5<10 <6 <6 <26 <9<7 <5 <6 <22 <7<6 <5 <5 <19 <6<5 <3 <3 <17 !c 2<12 <6 <6 <35 <12<8 <3 <4 <25 <7<10 <5 <3 <13 <6<13 <6 <6 <31 <10<11 <5 <6 <29 <7<11 <5 <6 <27 <9<7 <4 <4 <22 <5<5 <3 <3 <16 <3<10 <6 <6 <30 <11<11 <6 <6 <26 <8<8 <5 <6. <22 <9 TABLE B-II.1 CONCENTRATIONS OF TRITIUM, STRONTIUM-89 AND STRONTIUM-90 IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION DATE H-3 SR-89 SR-90 I SW-LR-10 SW-LR-10 SW-LR-10 SW-LR-1 0 SW-LR-10 SW-LR-10 SW-LR-10 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 01/25/12 03/19/12 03/19/12 03/20/12 03/21/12 03/21/12 03/23/12 03/26/12 04/25/12 07/16/12 10/08/12 01/25/12 04/25/12 07116t12 10/08/12 01/25/12 04/25/12 07/16/12 10/08/12 01/25/12 04/25/12 07/16/12 10/08/12 01/25/12 04/25/12 07/16/12 10/08/12 01/25/12 04/24/12 07/17/12 10/10/12 01/24/12 04/23/12 07/17/12 10/08/12 191 t 110< 171< 184< 172< 174 EIML < 143< 187< 187< 187* 194* 193< 169* 188< 195< 195< 171< 187< 191< 194< 156< 188< 193< 191< 170< 192< 190* 196 172 +/- 109< 188< 191< 192< 168< 183< 192< 193< 3.8< 4.0<. 4.2< 4.2< 4.8< 7.2< 6.8< 0.7< 0.7< 0.7< 0.6< 0.9 I j B-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, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION Be-7 DATE SW-LR-2 04/25/12 < 39 SW-LR-4 04/25/12 < 40 SW-LR-6 04/25/12 < 44 SW-LR-7 04/25/12 < 52 SW-LR-8 04124/12 < 49 SW-LR-9 04/23/12 < 47 SW-LR-10 03/19/12 < 75 SW-LR-10 03/21/12 < 46 SW-LR-10 03/21/12 EIML < 23 SW-LR-10 04/25/12 < 34 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< 93< 41< 92< 135< 98< 103 134<84< 51< 29<4<5<6<8<6<6+75 < 9<5<2<4<5<5<5<5<6<5<9<4<2<3< 11< 12< 10< 13< 12< 13< 15< 10<5<9<4<6<6<6<6<6<7<3<2<4<7< 10< 10< 13< 11< 10< 17< 12<3<6<4<6<5<6<6<6< 11<5<2<4<8< 11<8< 13<8< 10< 16<8<4<7<7<8<9< 10< 13< 11< 12<5<5<7<4<5<5<5<5<6<9<5<3<4<5<5<6<6<6<4<9<6<3<4< 21< 23< 18< 27< 28< 30< 36< 15< 12< 15<6* 10* 10<9<7<8< 14<7<3<6 TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/-2 SIGMA SITE COLLECTION H-3 DATE 36S3 01/31/12 < 178 36S3 02/27/12 < 183 36S3 04/30/12 < 160 36S3 06/26/12 < 190 36S3 07/30/12 < 166 36S3 07/30/12 < 170 36S3 08/28/12 < 198 36S3 10/02/12 < 179 36S3 10/26/12 < 176 36S3 11/26/12 < 199 E-5 01/31/12 < 180 E-5 02/27/12 < 185 E-5 04/30/12 < 161 E-5 06/26/12 < 189 E-5 07/30112 < 171 E-5 07/30/12 < 167 E-5 08/28/12 < 195 E-5 10/02/12 < 171 E-5 10/26/12 < 178 E-5 11/26/12 < 197 ESE-6 01/31/12 < 177 ESE-6 02/27/12 < 188 ESE-6 04/30/12 < 163 ESE-6 06/26/12 < 191 ESE-6 07/30/12 < 168 ESE-6 07/30/12 < 169 ESE-6 08/28/12 < 195 ESE-6 10/02/12 < 174 ESE-6 10/26/12 < 179 ESE-6 11/26/12 < 162 SE-7 01/31/12 < 175 SE-7 02/27/12 < 186 SE-7 04/30/12 < 162 SE-7 06126/12 < 188 SE-7 07/30/12 < 167 SE-7 07/30/12 < 167 SE-7 08/28/12 < 198 SE-7 10/02/12 < 175 SE-7 10/26/12 < 176 SE-7 11/26/12 < 199 B-6