Text

Annual Radiological Environmental Operating Report
	ML12121A620
Person / Time
Site:	Limerick
Issue date:	04/20/2012
From:	Kearney F; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML12121A620 (137)
	v • d • e

Limerick GeneTating Station www.exeloncorp.com Exelon, 3146 Sanatoga Rd. Nuclear Pottstown, PA 19464 TS 6.9.1.7 April 20, 2012 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353

Subject:

2011 Annual Radiological Environmental Operating Report

Dear Sir:

In accordance with the requirements of Section 6.9.17 of Limerick Generating Station (LGS) Unit 1 and Unit 2 Tech. Specs., and Section 6.1 of the LGS Units 1 and 2 Offsite Dose Calculation Manual (ODCM), this letter submits the 2011 Annual Radiological Environmental Operating Report No. 26. This report provides the 2011 results for the Radiological Environmental Monitoring Program (REMP) as called for in the Offsite Dose Calculation Manual.

In assessing the data collected for the REMP, we have concluded that the operation of LGS, Units 1 and 2 had no adverse impact on the environment. No plant-produced fission or activation products, with the exception of Cs-i137, were found in any pathway modeled by the REMP. Cesium-1 37 levels detected in sediment were consistent with levels found in previous years and were attributable to LGS liquid releases. Results of the groundwater protection program are also included in this report. Positive tritium was found in 2 of 12 groundwater monitoring locations that ranged up to 1,154 pCi/L.

There are no commitments contained in this letter.

If you have any questions, please do not hesitate to contact us.

Sincerely, eF . Kea/ney Vice Presi ent -LGS Exelon Generation Company, LLC

Attachment:

2011 Annual Radiological Environmental Operating Report No. 27 cc: W. Dean, Administrator, Region I, USNRC (w/Attachment)

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

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

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

LIMERICK GENERATING STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DISTRIBUTION LIST bcc: P. Gardner - GML 5-1 (w/o Attachment)

F. Kearney -GML 5-1 (w/o Attachment)

D. Merchant - GML 1-1 (w/o Attachment)

J. Hunter III - SSB 2-4 (w/Attachment)

R. Lance- SSB 2-2(w/Attachment)

L:. Birkmire -SSB 2-2 (w/Attachment)

C. Smith - SSB 2-2 (w/Attachment)

S. Gamble - SSB 2-4 (w/o Attachment)

A. Columbus- SMB 1-2 (w/Attachment)

K. Jury - Cantara (w/o Attachment)

J. Mudrick - KSA 3N (w/o Attachment)

C. Lewis - KSA 3N (w/o Attachment)

D. Helker - KSA 3E (w/o Attachment)

R. Janati-Commonwealth of PA (w/Attachment)

M. Murphy- PA DEP BRP Inspector - SSB 2-4 (w/Attachment)

S. Focht - ANI (w/Attachment)

David Katz - Deputy Water Commissioner Environmental Policy and Planning City of Phila. Water Dept, ARAMark Tower 5 'hFIr, 1101 Market St. Phila. PA 19107-2994 (w/Attachment)

Aqua Pennsylvania 762 West Lancaster Avenue Bryn Mawr, PA 19010 (w/Attachment)

Andrew Fabian -Phoenixville Water Works 140 Church St Phoenixville, PA 19460 (w/Attachment)

Pennsylvania American Water 800 W. Hershey Park Dr. Hershey, PA 17033 (w/Attachment)

James Hennessey - Pottstown Water Authority 100 E. High St Pottstown, PA 19464-9525 (w/Attachment)

Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2011 Prepared By Teledyne Brown Engineering Environmental Services Exelkn..

Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2012

Table Of Contents I. Sum m ary and Conclusions ............................................... :........................................... 1 I1. Intro d u c tio n ........................................................................................................................ 4 A. O bjectives of the REM P .................................................................................... 4 B. Im plem entation of the O bjectives ...................................................................... 5 Ill. Program Description ................................................................................................... 5 A. Sam ple Collection .............................................................................................. 5 B. Sam ple Analysis ................................................................................................ 7 C. Data Interpretation ............................................................................................ 7 D. Program Exceptions ......................................................................................... 9 E. Program Changes ........................................................................................... 10 IV. Results and Discussion ............................................................................................. 10 A. Aquatic Environm ent ...................................................................................... 10

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

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

3. Fish ........................................................................................................ 11

4. Sedim ent .............................................................................................. 11 B. Atm ospheric Environm ent ............................................................................... 12

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

a. Air Particulates .......................................................................... 12

b. Airborne Iodine .......................................................................... 13

2. Terrestrial .............................................................................................. 13

a. Milk ..................................................... .......... ............ 13

b. Broad Leaf Vegetation .............................................................. 13 C. Am bient Gam m a Radiation ............................................................................. 14 D. 10 CFR 20.2002 Perm it Storage Area ............................................................ 14 E. Independent Spent Fuel Storage Area ............................................................ 15 F. Land Use Survey ........................................................................................... 15 G. Summary of Results - Inter-Laboratory Comparison Program ...................... 15 V. ERRATA ......................................................................................................................... 18 VI. References ..................................................................................................................... 18

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2011.

Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Tables Table B-1 Location Designation and Identification System for the Limerick Generating Station.

Table B-2 Radiological Environmental Monitoring Program -.Sampling Locations, Distance and Direction, Limerick Generating Station, 2011.

Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2011.

Figures Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2011.

Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick-Generating Station, 2011.

Figure B-3. Environmental Sampling Locations Greater Than 26,400 Feet from the Limerick Generating Station, 2011.

Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table C-1.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2011.

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Table C-I1.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station,.201 1.

Table C-II.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table C-11.3 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2011 Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table C-111.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2011.

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, 2011.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples' Collected in the Vicinity of Limerick Generating Station, 2011.

Table C-VI.3 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table C-VII.1 -Concentrations of 1-131 .in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2011...

Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 201 1.*

Table C-VIII.1 Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table C-IX.1 Quarterly TLD Results for Limerick Generating Station, 2011.

Table C-IX.2 Mean Quarterly TLD Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2011.

Table C-IX.3 Summary of the Ambient Dosimetry Program for Limerick Generating Station, 2011.

Figqures Figure C-1 Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2011.

Figure C-2 Mean Annual Cs-137 Concentrations in Fish Samples Collected in the Vicinity of LGS, 1982 - 2011.

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Figure C-3 Concentrations of Cs-137 in Sediment Samples Collected in-the Vicinity of LGS, 1982 - 2011.

Figure C-4 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2011. :%

Figure C-5 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2011.

Figure C-6 Mean Quarterly Ambient Gamma Radiation Levels (TLD) in the Vicinity of LGS, 1985 - 2011.

Appendix D Data Tables and Figures - Comparison Laboratory Tables Table D-I.1 Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2011.

Table D-1.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2011.

Table D-1.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table D-11.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table D-11.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Table D-Ill.1 Concentrations of 1-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2011.

Fi-gures Figure D-1 Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2011.

Figure D-2 Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2011.

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Appendix E 'Inter-Laboratory Comparison Program Tables.

Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2011.

Table E-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2011.

Table E-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2011.

Table E-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2011.

Table E-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2011.

Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR)

Appendix G ERRATA - 2010 AREOR Appendix A V

Intentionally Left Blank

1. Summary and Conclusions In 2011, the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 187 curies of noble gas, fission and activation products and approximately 63 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 1.46E-02 All Nearest Residence 7.28E-02 20 mRad Noble Gas Beta -Air Dose 8.73E-03 All Nearest Residence 2.18E-02 40 mRad Noble Gas Total Body (Gamma) 1.39E-02 All Nearest Residence 1.39E-02 10 mrem Noble Gas Skin (Beta) 2.30E-02 All Nearest Residence 7.67E-02 30 mrem Iodine, Particulate, Bone 4.13E-01 Child Cow Milk 1.38E-00 30 mrem Tritium & c-14 Liquid Total Body 8.38E-02 Child Phoenixville PA 1.40E-00 6 mrem Liquid Liver 8.38E-02 Child Phoenixville PA 4.19E-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 2011 through 31 December 2011. During that time period, 1256 analyses were performed on 1022 samples.

On March 11, 2011 an earthquake off the Japanese islands produced a massive tsunami that caused a nuclear accident at four of the six Fukushima Daiichi reactors. In planning for the potential radioactive plume reaching the United States, Exelon Nuclear increased the sampling frequency and added additional analyses of select media from pathways that were expected to be the most sensitive to any increase in ambient radiation levels. Low level 1-131 analyses and gamma spectroscopy analyses were performed on air particulates, air iodine, and milk, as appropriate.

The resulting radioactive plume was first detected in the environs of Limerick Generating Station on March 22, 2011. The final date of positive detection was April 11, 2011. The radionuclide identified was Iodine-131. Maximum activity levels found by media were 100 pCi/m 3 for air iodine. Samples collected were compared to offsite control locations to verify that these positive detections were not attributable to licensed activities. All other radionuclides analyzed for were below the minimum detectable concentration (MDC).

The radioactive half-life of 1-131 is about 8 days. This short half-life allowed the 1

effects of this radioactive plume to subside over about 3 weeks. As of April 12, 2011 no further impacts from the Fukushima Daiichi accident was evident.

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 5.73E-04 mrem and 4.91 E-04 mrem, respectively. This dose represents 2.86E-03% and 8.18E-03%, respectively of the 10 CFR Part 50, Appendix I dose limits.

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 with the exception of eleven samples which were positive for 1-131. These positive results are directly attributed to the Fukushima event in March of 2011.

Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. All 1-131 results were below the minimum detectable concentration. Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found.

Broad leaf vegetation samples were analyzed for gamma emitting nuclides.

Concentrations of naturally occurring Be-7 and K-40 were detected. Radium-226 was found in 11 of 42 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 thermoluminescent dosimeters (TLD). Levels detected were consistent with those observed in previous years.

Review of the gamma spectroscopy results from the surface water samples located at the Limerick intake (24S1) and downstream of the 10CFR20.2002 permitted storage area showed no evidence of offsite radionuclide transport from the 2002 permitted storage area.

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A review of the TLD 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 2011, well water samples were analyzed for tritium, Sr-90, gross alpha, gross beta, and gamma emitters.

Surface water samples were analyzed for tritium, 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. 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.

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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), and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2011 through 31 December 2011.

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~st6rage. 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; 4

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 du ring station operation to assess station radiological effects (if any) on man and the environment.

Ill. Program Description A. Sample Collection Samples for the LGS REMP were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used by NAI to obtain environmental samples for the LGS REMP in 2011. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by NAI are'listed in Table*B-3.

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

Two-gallon water samples were collected monthly from continuous samplers located at two surface water locations (13B11 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/bass), were collected semiannually at two locations, 16C5 and 29C1 (control).

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

Atmospheric Environment The atmospheric environment-was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk. Airborne iodine and particulate samples were collected and analyzed weekly at six locations (6C1, 10S3, 11S1, 13C1f 14S1, and 22G). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.

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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 Direct radiation measurements were made using Panasonic 814 calcium sulfate (CaS0 4 ) thermoluminescent dosimeters (TLD). The TLD 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 bepotentially greater than maximum annual off-site doses) from LGS releases.

An intermediate distance ring consisting of 1'6 locations (36D1, 2E1, 4E1, 7E1, 10EI, 10F3, 13E1, 16F1, 19D1, 20F1, 24D1,.25D1, 28D2, 29E1, 31D2,:and:34E1). extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

The balance of eight locations (51H, 6C1, 9C1, 13C1, 15D1, 17B1, 20D1 and 31 D1) representing control and special interests areas such as population centers, schools, etc.

The specific TLD locations Were determined by the following criteria:

1. The presence of relatively dense population;

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

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

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

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Two TLDs - each comprised of three CaSO4 thermoluminescent phosphors enclosed in plastic - were placed at each location in a PVC conduit located approximately three~feet above ground level. The TLDs were exchanged quarterly and sent to Mirion Technologies for analysis.

10CFR20.2002 Permit Storagqe Area, In 1996 the Limerick Generating Station received NRC approval to store slightly contaminated soils, sludges and sediments on site per the requirements of 10CFR20.2002. These materials will be stored until end of the site's operating license. -At that time the material will be evaluated along with the site for decommissioning. The area is approximately 1.5 acres in size and was evaluated to hold a maximum of 1.12E+06 cubic feet with no more than 7E+04 cubic feet added to the area in any single year. After each material placement on the 2002 pad,;the area is graded and seeded to prevent erosion. Since all groundwater movement is to the river, the use of the REMP surface water sampling program is used as a check on potential groundwater movement from the pad.

Independent Spent Fuel Storage Installation (ISFSI)

The results from the TLD 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.

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 7

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-1 34, Cs-1 37, 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.

For air particulate six nuclides, Be-7, Mn-54, Co-58, Co-60, Cs-134, and Cs-137 were reported.

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

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Means and standard deviations of positive results were calculated.

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

D. Program Exceptions For 2011 the LGS REMP had a sample recovery rate in excess of 99%.

Exceptions are listed below:

1. Air sample from location 22G1 for the week of 02/14/11 - 02/21/11 was not available due to equipment malfunction (IR 01240992 02).

2. Air sample from location 10S3 for the week of 05/09/11 - 05/16/11 was not available due to equipment malfunction (IR 01240992 07).

3. Air sample from location 11 S2 for the week of 07/18/11 - 07/25/11 was not available due to equipment malfunction (IR 01240992 05).

4. Limited vegetation samples available at station 11 S3 for the month of June and July (IR 01240992 04 and IR 01240992 06).

5. 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:

.01/24/11 ý-02/14/11 (1R 01240992 01).

03/07/11 - 03/14/11, (IR 01240992 03) 08/23/11 - 08/30/11 (!R 01240992 08) 09/06/11 - 09/13/11 (IR 01240992 12) 09/20/11 - 09/27/11 (IR 01240992 13) 10/11/11 - 10/18/11 (IR 01240992 14) 111/20/11 -. 12/27/11 (IR 01240992 16)

6. Grab samples were taken for the Composite drinking water sampler at location 16C2 during the following periods due to equipment malfunction: 10/18/11 - 10/25/11 (IR 01240992 15)

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 power outages were unavoidable.

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

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E. Program Changes Starting in July 2011, low level 1-131 analysis was added to drinking water in order to meet the LLD of 1 pCi/L.

IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken from a continuous sampler at two locations (133B1 and 24S1) on a monthly schedule. Of these locations only 133B1 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-1.1, Appendix C). All results met the required LLD.

Gamma Spectrometry

- Samples from all locations were analyzed, for gamma emitting nuclides (Table C-IL2, 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:

Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Tables C-I1.1, Appendix C). The values ranged from 2.0 to 5.6 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). All results met the required LLD.

10

Iodine-1 31 Samples were taken from all locations on a monthly basis starting in July and analyzed for Iodine-131 activity (Table C-11.3, Appendix C). All results met the required LLD.

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

3. Fish Fish samples comprised of bottom feeder (catfish/carp/white suckers) and predator (sunfish/bass), 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-111.1, Appendix C).

Naturally occurring K-40 was found at all stations and ranged from 3,200 to 5,370 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 beaffected by Limerick's effluent releases. The following analysis was performed:

Gamma Spectrometry Sediment samples from. all three locations were analyzed for gamma emitting nuclides (Table C-IV.l, 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 1,900 to 7,160 pCi/kg*dry. Potassium-40 was found at all locations and ranged from 12,700 to 19,300 pCi/kg dry. The fission product Cs-1 37 was found at locations 16B2 and 16C4 and ranged from 179 to 218 pCi/kg dry (Figure C-4, Appendix C).

11

The activitydetected was consistent with those detected in the pre-operational years. Due to the control location, 33A2, not showing positive activity, the Cs-1 37 activity found at 166B2 and 16C4 is attributed to LGS radioactive effluent releases. The dose to a teenager's skin and whole body was conservatively calculated at 5.73E-04 mrem and 4.91 E-04 mrem, respectively. This dose represents 2.86E-03% and 8.18E-03%, of the Appendix I to 10 CFR Part 50 dose limits, respectively. No other Limerick fission or activation products were found.

B. Atmospheric Environment 1.. Airborne

a. Air Particulates Continuous air particulate samples were collected from six locations on a weekly basis. The six locations were separated into three groups: Group I represents locations within the LGS site boundary (10S3, 11S1, and 14S1),

Group II represents the locations at an intermediate distance from the LGS site (6C1 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 39 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 7 E-3 to 33 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m3, The results from the Distant locations (Group Ill) ranged from 8 E-3 to 29 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3 . Comparison of the 2011 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 all samples. These values ranged from 50 E-3 12

to 104 E-3 pCi/m 3 . All other nuclides met the required LLDs.

Additional sampling occurred in the weeks immediately following the Fukushima event in 2011. All nuclides met the required LLDs.

b. Airborne Iodine Continuous air samples were collected from six locations (6C1, 10S3,1 1S1, 14S1, 13C1, and 22G1) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). All results met the required LLD with the exception of 11 samples which were positive for 1-131. These positive results are directly attributed to the Fukushima event in March of 2011.

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. Additional sampling occurred in. the weeks immediately following the Fukushima event. 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 402 to 1,450 pCi/L. All other nuclides met the required LLDs.

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

13

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

Cosmogenic Be-7 was found in 25 of 42 samples and ranged from 170 to 2,040 pCi/kg wet. Naturally occurring K-40 was found in all samples and ranged from 1,880 to 6,950 pCi/kg wet. All other nuclides met the required LLDs.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO 4 ) thermoluminescent dosimeters. Forty TLD locations were established around the site. Results of TLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.

Most TLD measurements were below 10 mR/standard month, with a range of 4.8 to 10.9 mR/standard month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Location 5H1 were consistently higher than all other locations except 13S2.

Location, 13S2 historically shows higher ambient gamma radiation, which is assumed due to the rock substrate. The area that this TLD is located in has been determined to emanate radon prodingy.

The historical ambient gamma radiation data from Location 5H1 were plotted along with similar data from the Site, Intermediate Distance and Outer Ring Locations (Figure C-6, Appendix C). Location 5H1 has a historical high bias, but tracked with the data from all three groups. This bias is most likely due to radon emanating from the ground.

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.

14

E. Independent Spent Fuel Storage Installation The result of the ambient gamma radiation level at TLD location 36S2 was Used to determine the direct radiation exposure to the nearest residence from the ISFSI pad. The data, after, subtracting background, shows the net direct radiation exposure to the nearest residence was zero mrem.

F. Land Use Survey A Land Use Survey conducted in September 2011 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 1/2 degree sectors around the site. The distance and direction of all locations from the LGS reactor buildings were positioned using Global Positioning System (GPS) technology. There were no changes required to the LGS REMP, as a result of this survey.

The results of this survey are summarized below.

Distance in miles from the LGS Reactor Buildings Sector Residence Garden MilkFarm Meat Animal Feet . Feet Feet. Feet 1 N 3,109 3,335 .24,775 24,775 2 NNE 2,706 9,610 -

3 NE 3,469 3,494 4 ENE 3,231 14,964 20,552 5, E 2,8.64 12,628 -

6 ESE - 3,434 1,822 --

7 SE 5,108 1,282 - 10,927 8 SSE 5,403 6,898 - -

9 S 4,347 -6,103 22,115 12,211 10 SSW 5,063 5,320 10,390 10,390 11 SW 3,251 4,559 - 18,547 12 WSW 3,799 12,013 14,175 14,175 13 W 3,627 4,208 14,654 14,654 14 WNW 3,932 3,932 - -

15 NW .3,619 8,169 16 NNW 5,051 71107 -

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, NELAC, state specific 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 primary laboratory, 14 out of 18 analytes met the specified acceptance. criteria.: Four analytes (one sample each of Cr-51, Sr-89 and Sr-90 and two Gross Alpha samples) did not meet the specified acceptance criteria for the following reason:

1. Teledyne Brown Engineering's Analytics March 2011 Cr-51 in milk result of 398 pCi/L was higher than the known value of 298 pCi/L, resulting in a found toknown ratio of 1.34. NCR 11-13 was initiated to investigate, this failure. There was a slightly high bias in all the gamma activities. The June gamma results in milk did not show a high bias. No further action was required.

2. Teledyne Brown Engineering's ERA May 2011 Gross Alpha in water result of 64.1 pCi/L was higher than the known value of 50.1 pCi/L, which exceeded the upper control limit of 62.9 pCi/L. NCR 11-08 was initiated to investigate this failure. The solids on the 16

planchet exceeded 100 mg, which was beyond the range of the efficiency curve.

3. Teledyne Brown Engineering's MAPEP March 2011 Gross Alpha in air particulate result of 0.101 Bq/sample was lower than the known value of 0.659 Bq/sample, which exceeded the lower control limit of 0.198 Bq/sample. NCR 11-11 was initiated to investigate this failure. The air particulate filter was counted on the wrong side.

4. Teledyne Brown Engineering's ERA November 2011 Sr-89 in water result of 81.0 pCi/L was higher than the known value of 69.7 pCi/L, which exceeded the upper control limit of 77.9 pCi/L. NCR 11-16 was initiated to investigate this failure. The TBE reported value to known ratio of 1.16 fell within the acceptable range of +/- 20%, which TBE considers acceptable.

5. Teledyne Brown Engineering's MAPEP March 2011 Sr-90 in soil, air particulate and vegetation were non-reports that were evaluated as failed. NCR 11-11 was initiated to investigate these failures.

MAPEP evaluated the non-reports as failed due to not reporting a previously reported analyte.

.For the secondary laboratory, Environmental, Inc., 12 out of 14 analytes met the specified acceptance criteria. Two analytes (one sample of Cs-134 and two Sr-90 samples) did not meet the specified acceptance criteria for the following reason:

1. Environmental. Inc.'s ERA October 2011 Cs-134 in water result of 38.8 pCi/L was higher than the known value of 33.4 pCi/L, which exceeded the upper control limit of 36.7 pCi/L. The sample was reanalyzed. The reanalyzed result of 32.9 was acceptable.

2. Environmental Inc.'s, MAPEP February 2011 Sr-90 in air particulate result of 1.89 Bq/sample was higher than the known value of 1.36 Bq/sample, which exceeded the upper control limit of 1.77 Bq/sample. No errors were found in the. calculation orprocedure.

The reanalyzed result of 1.73 Bq/sample was acceptable.

3. Environmental Inc.'s MAPEP August 2011 Sr-90 in soil result of 219.4 Bq/kg, less than the known value of 320 Bq/kg, was below the lower control limit of 224 Bq/kg. The sample was reanalyzed in triplicate through a strontium column. The reanalyzed result of 304.2 Bq/kg was acceptable.

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

17

V. ERRATA A. Correction to 2010 AREOR In the 2010 AREOR Table A-1 some nuclides were not captured in the report due to formatting. Nuclides included Cs-137, Ba-140, La-140. A corrected table is included in Appendix G of this report.

VI. References A. Environmental Report Operating License Stage, Limerick Generating Station, Units 1 and 2, Volumes 1-5 Philadelphia Electric Company.

B. NUREG-1302 Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors C. Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1, November 1979.

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

18

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 H-3 8 200 <LLD <LLD (PCI/LITER)

GAMMA 24 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD FE-59 30 <LLD <LLD CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD NB-95 15 <LLD <LLD 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)

A-1

A-2 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 ZR-95 30 <LLD <LLD (PCI/LITER) 1-131 15 <LLD <LLD CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA- 140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD DRINKING WATER GR-B 48 4 3.9 3.9 4 16C2 INDICATOR (PCI/LITER) (20/36) (4/12) (4/12) CITIZENS HOME WATER COMPANY (2.2/5.1) (2.0/5.6) (3.7/4.5) 2.66 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,-2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 H-3 16 200 <LLD <LLD (PCI/LITER) 1-131 24 <LLD <LLD GAMMA 48 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD FE-59 30 <LLD <LLD CO-60 15 <LLD' <LLD ZN-65 30 <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)

A-3

A-4 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 NB-95 15 <LLD <LLD 0 (PCI/LITER)

ZR-95 30 <LLD <LLD 0 1-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-1 37 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 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, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 GAMMA 4 (PCI/KG WET) K-40 NA 4455 3625 4455 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL (3540/5370) (3460/3790) (3540/5370) DOWNSTREAM OF DISCHARGE MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 CO-60 130 <LLD <LLD 0 ZN-65 260- <LLD - <LLD 0 1-131 NA <LLD <LLD 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)

A-5

A-6 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 CS-134 130 <LLD <LLD 0 (PCI/KG WET)

CS-137 150 <LLD <LLD 0 PREDATOR GAMMA 4 (PCI/KG WET) K-40 NA 3400 3230 3400 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL (3300/3500) (3200/3260) (3300/3500) DOWNSTREAM OF DISCHARGE MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD FE-59 260 <LLD <LLD CO-60

130 <LLD <LLD 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, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 ZN-65 260 <LLD <LLD 0 (PCI/KG WET) 1-131 NA <LLD <LLD 0 CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 SEDIMENT GAMMA (PCI/KG DRY) BE-7 NA 3618 <LLD 4580 16B2 INDICATOR 0 (4/4) (2/2) LINFIELD BRIDGE (1900/7160) (2000/7160) 1.35 MILES SSE OF SITE K-40 NA 16175 13650 16200 16B2 INDICATOR 0 (4/4) (2/2) (2/2) LINFIELD BRIDGE (13000/19300) (12700/14600) (15000/17400) 1.35 MILES SSE OF SITE MN-54 NA <LLD <LLD 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)

A-7

A-8 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 CO-58 NA <LLD <LLD 0 (PCI/KG DRY)

CO-60 NA <LLD <LLD 1-131 NA <LLD <LLD CS-134 150 <LLD <LLD 0 CS-137 180 196 <LLD 199 16B2 INDICATOR (3/4) (2/2) LINFIELD BRIDGE (179/218) (179/218) 1.35 MILES SSE OF SITE AIR PARTICULATE GR-B " 310 10 17 17 18 14S1 INDICATOR (E-3 PCI/CU.METER) (251/259) (49/51) (52/52) LONGVIEW ROAD (6/39) (8/29) (7/39) 0.63 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, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 GAMMA 24 (E-3 PCI/CUMETER) BE-7 NA 75 76 86 6C1 INDICATOR (20/20) (4/4) (4/4)

(50/104) (60/83) (70/104) 11305 FEET NE OF SITE MN-54 NA <LLD <LLD CO-58 NA <LLD <LLD CO-60 NA <LLD <LLD 0 CS-134 50 <LLD <LLD* 0 CS-137 60 <LLD . - <LLD 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)

A-9

A-10 TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 IODINE GAMMA 310 (E-3 PCI/CU.METER) 1-131 70 63 59 85 13C1 INDICATOR 0 (10/259) (1/51) (2/52) KING ROAD (24/100) (70/100) 2.84 MILES SE OF SITE MILK 1-131 114 <LLD <LLD (PCI/LITER)

MILK GAMMA 114 (PCI/LITER) K-40 NA 1173 1222 1277 19B1 INDICATOR 0 (88/88) (26/26) (22/22) 1.95 MILES SSW OF SITE (402/1450) (1030/1430) (1130/1450)

CS-134 15 <LLD <LLD CS-137 18' <LLD <LLD BA-140 60 <LLD <LLD LA-140 15 <LLD <LLD 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-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE-LIMERICK GENERATING STATION, 2011 .

Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 GAMMA 42 (PCI/KG WET) BE-7 NA 471 836 836 31G1 CONTROL 0 (13/27) (12/15) (12/15)

(219/1020) (170/2040) (170/2040)

K-40 NA 4405 4827 4827 31G1 CONTROL 0 (27/27) (15/15) (15/15)

(1880/6870) (2930/6950) (2930/6950)

MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 1-131 60 <LLD <LLD 0 CS-134 60 <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)

A-1i1

A-12 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2011 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2011 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 CS-137 80 1 <LLD <LLD 0 (PCI/KG WET)

RA-226 NA 1621 266 1701 13S3 INDICATOR 0 (10/27), (1/15) (9/15) VINCENT DAM (764/3200),, (764/3200) 0.24 MILES SE OF SITE TH-228 NA 43 60 60 31G1 CONTROL 0

.(6/27) (4/15) (4/15)

(18/68), (24/125) (24/125)

TH-232 NA <LLD <LLD 0 DIRECT RADIATION TLD-QUARTERLY 160 NA 7.1 8.4 9.9 13S2 INDICATOR 0 (MILLI-ROENTGEN/STD.MO.) (1.56/156) (4/4) (4/4) 500 KV SUBSTATION (4.8/1 0.9) (7.7/9.1) (8.8/10.9) 0.41 MILES SE

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

APPENDIX B LOCATION DESIGNATION, DISTANCEA&

DIRECTION, AND SAMPLE COLLECTION.&

ANALYTICAL METHODS

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

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

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

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

B-1

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2011 Location Location Description Distance & Direction-From Site A. Surface Water 13B1 Vincent Dam 9,225 feet SE 24S1 Limerick Intake (control) 1,058 feet SW B. Drinking (Potable) Water 15F4 Philadelphia Suburban Water Company 45,514 feet SE 15F7 Phoenixville Water Works 33,400 feet SSE 16C2 Citizens Home Water Company 14,034 feet SSE 28F3 Pottstown Water Authority (control) 30,811 feet WNW C. Milk - bi-weekly / monthly 110F4 34,848 feet ESE 18E1 22,229 feet S 19B1 10,317 feet SSW 23F1 Control 26,505 feet SW 25C1 14,224 feet WSW D. Milk - quarterly 36E1 Control 24,816 feet N E. Air Particulates / Air Iodine 10S3 Keen Road

2,648 feet E 11S1 LGS Information Center 2,017 feet ESE 11S2 LGS Information Center (quality control) 2,017 feet ESE 13C1 King Road 14,980 feet SE 14S1 Longview Road 3,319 feet SSE 22G1 Manor Substation (control) 93,619 feet SW 6Cl Pottstown Landing Field 11,305 feet NE F.Fish 16C5 Vincent Pool Downstream of Discharge 29Cl Pottstown Vicinity (control) Upstream of Intake .

G. Sediment 16B2 Linfield Bridge 7,128 feet SSE 16C4 Vincent Dam 11,510 feet SSE 33A2 Upstream of Intake (control) 4,435 feet NNW H. Broad Leaf Vegqetation 11S3 LGS Information Center 1,848 feet ESE 13S3 LGS 500 KV Yard 1,267 feet SE 31G1 Prout's Jollyview Farm (control) 71,808 feet NW B-2

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2011 Location Location Description Distance & Direction From Site I. Environmental Dosimetry - TLD Site Boundary 36S2 Evergreen & Sanatoga Road 3,183 feet N 3S1 Sanatoga Road 2,301 feet NNE 5S1 Possum Hollow Road 2,350 feet NE 7S1 LGS Training Center 3,099 feet ENE 10S3 Keen Road 2,648 feet E 11IS1 LGS Information Center 2,017 feet ESE 13S2 500 KV Substation 2,149 feet SE 14S1 Longview Road 3,319 feet SSE 18S2 Rail Line along Longview Road 1,390 feet S 21S2 Near Intake Building 977 feet SSW 23S2 Transmission Tower 2,793 feet SW 25S2 Sector Site Boundary 2,445 feet WSW 26S3 Met. Tower #2 2,088 feet W 29S1 Sector Site Boundary 2,886 feet WNW 31S1 Sector Site Boundary 1,395 feet NW 34S2 Met. Tower #1 3,071 feet NNW Intermediate Distance 36D1 Siren Tower No. 147 18,527 feet N 2E1 Laughing Waters GSC 25,112 feet NNE 4E1 Neiffer Road 25,221 feet NE 7E1 Pheasant Road 22,489 feet ENE 10E1 Royersford Road 20,826 feet E 10F3 Trappe Substation' 29,442 feet ESE 13E1 Vaughn Substation .22,772 feet.SE 16F1 Pikeland Substation 26,608 feet SSE 19D1 Snowden Substation 18,439 feet S 20F1 Sheeder Substation 27,648 feet SSW 24D1 Porters Mill Substation 20,972 feet SW 25D1 Hoffecker & Keim Streets 21,044 feet WSW 28D2 W. Cedarville Road 20,231 feet W 29E1 Prince Street 26,110 feet WNW 31 D2 Poplar Substation 20,446 feet NW 34E1 Varnell Road 24,243 feet NNW Control and Special Interest 5H 1 Birch Substation (control) 130,742 feet NE 6C1 Pottstown Landing Field 11,305 feet NE 9C1 Reed Road 11,377 feet E 13C1 King Road 14,980 feet SE 15D1 Spring City Substation 16,877 feet SE 17B1 Linfield Substation 8,462 feet S 20D1 Ellis Woods Road 16,157 feet SSW 31D1 Lincoln Substation 15,853 feet WNW B-3

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2011 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-ER1 0 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-201 1 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, 2011 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 emnittersby 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 Mirion Technologies Dosimetry comprised of two radiological analysis (Limerick Generating Panasonic 814 Station)

(containing 3 each I__ __

_ _ 1CaSO4 elements) I I B-5

N/ NE W// 33A2

% ENE

-* ~.*.05S I\ z111 0

S w SSE Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2011 B-6

i N

3EI NE

@3601

@31D2 O7E1 e14DI "4C1 28D2 L'1ý11 .

09CI 1100¶

=5CI 2¶I "4I) 0lICVIý elSE1 8

o 0,5 1 2 3 4 Mis Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2011 B-7

NNW 10NE N E 3101I frm heLierckGeneratng MStaton 2011 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, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 13B1 24S1 PERIOD 12/27/10 - 03/29/11 < 162 (1) < 167 03/29/11 - 06/27/11 < 178 < 173 06/27/11 - 09/27/il < 187 (1) < 188 09/27/11 - 12/27/11 < 173 (1) < 175 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, 2011 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-1 34 Cs-1 37 Ba-140 La-140 PERIOD 13B1 12/27/10 - 01/31/11 <5 <12 <5 < 10 <5 <11 <9 <5 <6 < 24 <7 01/31/11 - 03/01/11 <5 <11 <4 < 10 <6 <9 -. <15 <5 <5 < 31 <9 03/01/11 - 03/29/11 <4 <8 <3 <7 <4 <7 <14 <3 <3 < 28 <8 03/29/11 - 05/03/11 <1 <3 <2 <1 <2 <12 <1 <1 < 16 <5 05/03/11 - 05/31/11 <1 <3 <2 <1 <2 <14 <1 <1 < 19 <5 05/31/11 - 06/27/11 <5 <13 < 6 < 15 <6 11i .. < 13 < 8 <6 < 32 < 10 06/27/11 - 08/02/11 <7 <12 < 10 <8 <11 <9 <7 <8 < 24 <8 08/02/11 - 08/29/11 <4 <10 .<6 <7 <5 <8 <9 <5 <4 < 21 <8 08/29/11 - 09/27/11 <6 <13 <5 < 12 <6 < 11 < 11 < 5 <5 < 28 <8 09/27/11 - 11/01/11 <5 < 10 <5 <8 <6 <9 <10 <5 <5 < 21 <7 11/01/11 - 11/28/11 <5 <10 <6 < 10 <6 <10 <9 <5 <6 < 26 <8 11/28/11 - 12/27/11 <5 <11 <5 < 10 <6 <9 <9 <5 <5 < 28 <8 MEAN 24S1 12/27/10 - 01/31/11 < 5 <5 <9 < 10 <5 <9 <10 <5 <6 <26 <8

<5 01/31/11 - 03/01/11 < 4 <4 <9 <8 <5 <9 <14 <4 <4 <28 <8

<.4 03/01111 - 03/29/11 < 4 <4 <9 * < '-4 <7 <4 <7 <15 <4 <4 <30 <9 03/29/11 - 05/03/11 < 1 <1 <2 <1 <1 <2 <10 <1 <1 <14 <4

< 1 <I1 05/03/11 - 05/31/11 <2 <4 <3 <2 <3 <14 <1 <1 <21 <7 05/31/11 - 06/27/11 < 6 <6 <13 <7 < 15 <7 < 12 <13 <7 <6 <35 < 12 06/27/11 - 08/02/11 < 7 <8 <15 <8 < 17 <8 < 12 <9 <6 <8 <28 <8 08/02/11 - 08/29/11 < 4 <5 <8 <4 <7 <5 <7 <9 <3 <5 <23 <9 08/29/i1 - 09/27/11 < 2 <2' <3 <2 <3 <2 <3 <3 <2 <2 <8 <3 09/27/11 - 11/01/11 <.5 <4 <<10 <6 < 12 <6 <8 <9 <4 <5 <22 <8 11/01/11 - 11/29/11 <4 <3 <6 <4 <6 <4 <6 <6 <4 <4 <16 <4 11/29/11 - 12/27/11 < 6 <4 <13 <5 < 13 <8 < 12 <12 <6 <6 <32 <6 MEAN C-2

TABLE C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 15F4 15F7 16C2 28F3 PERIOD 12/27/10 011/31/11 4.0 +/- 2.5 < 3.9 3.7 +/- 1.8 < 3.2 01/31/11 03/01/11 3.8 +/- 1.9 3.7 +/- 1.7 3.7 +/- 1.9 < 2.3 03/01/11 03/29/11 < 3.4 < 3.2 < 3.7 < 3.3 03/29/11 05/03/11 < 3.5 < 3.5 < 3.9 < 3.5 05/03/11 05/31/11 3.9 +/- 2.2

3.1

3.2 < 3.5 05/31/11 06/27/11 < 3.4 3.4 +/- 2.2 < 3.5 < 3.4 06/27/11 08/02/11 5.1 +/- 1.8 5.1 +/- 1.8 4.5 +/- 1.9 3.5 +/- 1.7 08/02/111 08/29/11 4.3 +/- 2.2 3.3 +/- 2.1 < 3.6 < 3.3 08/29/11 09/27/11 4.4 +/- 2.0 4.9 +/- 1.9 < 3.0 4.6 +/- 2.0 09/27/11 11/01/11 3.3 +/- 1.5 < 2.3 < 2.5 < 2.3 11/01/11 11/28/11 3.3 +/- 2.0 4.1 +/- 2.1 4.2 +/- 2.2 5.6 +/- 2.2 11/29/11 12/27/11 2.4 +/- 1.0 2.2 +/- 1.0 < 1.7 2.0 +/- 1.0 MEAN 3.8 +/- 1.6 3.8 +/- 2.0 4.0 +/- 0.8 3.9 +/- 3.1 TABLE C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED INTHE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 15F4 15F7 16C2 28F3 PERIOD 12/27/10 - 03/29/11 < 185 < 163 < 162 < 163 03/29/11 - 06/27/11 < 173 < 176 < 178 < 175 06/27/11 - 09/27/11 < 186 < 186 < 186 < 187 09/27/11 - 12/27/11 < 177 < 181 < 175

176 MEAN TABLE C-I.3 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 15F,4 15F7 16C2 28F3 PERIOD 06/27/11 08/02/11 (1) < 0.8 < 0.7 < 0.8 < 0.8 08/02/11 08/29/11 < 0.6

0.6

0.6

0.6 08/29/11 09/27/11 < 0.5 < 0.5 < 0.6 < 0.5 09/27/11 11/01/11 < 0.8 < 0.6 < 0.6 < 0.6 11/01/11 11/28/11 < 0.6 < 0.6 < 0.6 < 0.7 11/29/11 12/27/11 < 0.4 < 0.4 < 0.5 < 0.4 MEAN THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-3

TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 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-140 PERIOD 15F4 12/27/10 - 01/31/11 <5 <5 <12 <5 < 10 <5 <8 <9 <4 <5 < 27 <8 01/31/11 - 03/01/11 <4 <4 <9 <3 <9 <4 <8 12 <4 <3 < 29 <9 03/01/11 - 03/29/11 <3 <3 <6 <2 <4 <3 <5 < 11 <2 <3 < 22 <7 03/29/11 - 05/03/11 <1 <1 <3 <1 <2 <1 <2 < 12 <1 <1 < 17 <6 05/03/11 - 05/31/11 <1 <1 <3 <1 <2 <1 <2 < 12 <1 <1 < 17 <5 05/31/11 - 06/27/11 <6 <7 <13 <7 < 14 <8 < 13 < 13 <6 <6 < 39 < 13 06/27/11 - 08/02/11 <4 <6 <15 <7 < 14 <6 < 11 <8 <6 <7 < 26 <7 08/02/11 - 08/29/11 <6 <6 <11 <6 < 10 <6 <9 < 11 <5 <6 < 27 <8 08/29/11 - 09/27/11 <4 <3 <7 <4 < 7 <4 <6 <7 <3 <-3 < 18 <6 09/27/11 - 11/01/11 <5 <5 <11 <5 < 10 <6 <8 < 10 <4 <5 < 25 <8 11/01/11 - 11/29/11 <4 <4 <7 <4 <8 <5 <7 <7 <4 <4 < 19 <5 11/29/11 - 12/27/11 <5 <5 <11 <4 <9 <5 <8 <8 <5 <5 < 26 <8 MEAN 15F7 12/27/10 01/31/11 <3 <3 <8 <3 <6 <3 <6 <7 <3 <4 < 17 <5 01/31/11 03/01/11 <5 <5 < 11 <5 < 10 <5 <8 < 14 <5 <5 < 32 <7 03/01/11 03/29/11 <2 <3 <6 <3 <5 <3 <5 < 10 <2 <2 < 21 <7 03/29/11 05/03/11 <1 <1 <2 <1 <2 <1 <2 < 12 <1 <1 < 15 <5 05/03/11 05/31/11 <1 <2 <4 <1 <3 <2 <3 < 14 <1 <1 < 22 <7 05/31/11 06/27/11 <5 <5 < 11 <5 <8 <5 < 11 < 12 <5 <5 < 29 < 10 06/27/11 08/02111 < 6 <'5 <9 <.7 < 13 <7 < 12 <8 <7 <6 < 24 -< 13 08/02/11 08/29/11 < 6 <5 < 11 <5 <8 <5 < 10 < 10 <4 <6 < 26 < 10 08/29/11 09/27/11 <2 <2 <4 <2 <4 <2 <4 <4 <2 <2 < 11 <c3 09/27/11 11/01/11 <6 <5 < 12 <6 < 10 <6 <9 < 10 <5 <6 < 25 <8 11/01/11 11/29/11 <4 <5 <9 <5 < 10 <5 <7 <8 <5 <4 < 22 <8 11/29/11 12/27/11 <6 <6 < 11 <5 <7 <6 < 10 < 11 <6 <6 < 30 < 12 MEAN C-4

TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 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-140 PERIOD 16C2 12/27/10 - 01/31/11 <2 <3 <6 <3 <6 <3 <5 <7 <3 <3 < 15 <5 01/31/11 - 03/01/11 <4 <5 < 10 <5 < 10 <5 <7 < 14 <4 <5 < 30 <8 03/01/11 - 03/29/11 <3 <3 <8 <4 <7 <4 <6 < 13 <3 <3 < 29 < 10 03/29/11 - 05/03/11 <1 <2 <3 <1 <3 <2 <3 < 15 <1 <1 < 19 <5 05/03/11 - 05/31/11 <1 <1 <3 < 1. <2 <2 <3 < 14 <1 <1 < 18 <5 05/31/11 - 06/27/11 <6 <5 < 14 <6 < 11 <7 < 13 < 14 <7 <6 < 36 < 14 06/27/11 - 08/02/11 <7 <8 < 14 <5 < 13 <7 < 12 <8 <7 <7 < 24 <9 08/02/11 - 08/29/11 <4 <5 < 13 <5 <9 <5 <9 <9 <4 <4 < 23 <9 08/29/11 - 09/27/11 <5 <6 < 10 <5 < 11 <7 < 10 < 10 <5 <6 < 26 <7 09/27/11 - 11/01/11 <6 <6 < 11 <7 < 14 <8 < 11 < 12 <5 <6 < 32 < 11 11/01/11 - 11/28/11 <6 <7 < 10 < 6. < 14 <6 < 11 <9 <5 <5 < 27 <9 11/28/11 -12127/11

<4 <6 < 13 <4 < 11 <5 <8 < 12 <6 <6 < 26 <8 MEAN 28F3 12/27/10 - 01/31/11 <5 <6 < 11 <5 < 11 <6 <9 < 11 <5 <5 < 30 <9 01/31/11 - 03/01/11 <4 <5 < 10 <4 <8 <6 <7 < 14 <4 <5 < 26 < 10 03/01/11 - 03/29/11 <4 <4 <9 <7

<4 <7 <5 < 15 <4 <4 < 32 <9 03/29/11 - 05/03/11 <1 < 1 <3 <1 2ý <1 <2 < 12 <1 <1 < 17 <4 05/03/11 - 05/31/11 <1 <2 <4 <1 <3.

2 S.<3 <.14 <1 <2 < 24 < 5, 05/31/11 -. 06/27/11 <5 <6 < 15 <7 < 13 <8 < 12 < 10 <6 <7 < 29 < 13 06/27/1.1 - 08/02/11 <5 <6 < 12 <5. < 11 <6 < 10 <7 <6 <6 < 25 <6 08/02/11 - 08/29/11 <6 <7 < 12 <6 < 13 <6 <9 < 11 <6 <6 < 28 < 10 08/29/11 - 09/27/11 <6. .< 7 < 14 <6 < 15 <8 < 10 < 10 <7 <8 < 36 < 12 09/27/11 - 11/01/11 <7 < 7

<8 < 16 < 16 < 10 < 13 < 12 <7 <7 < 38 < 13 11/01/11 - 11/28/11 <4 <5 <9 <.6 < 10 <5 <8 <8 <4 <5 < 20 <8 11/28/11 - 12/27/11 <7 <7 <9 <5 < 12 <5 < 11 < 10 <5 <6 < 30 <6 MEAN C-5

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

SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-134 Cs-137 PERIOD 16C5 PREDATOR 05/09/11 3500 +/- 832 < 19 < 34 < 53 < 30 < 53 < 156 < 28 < 30 10/25/11 3300 +/- 986 < 59 <65 < 141 < 78 < 99 < 125 < 63 < 71 MEAN 3400 +/- 283 16C5 BOTTOM FEEDER 05/09/11 3540 +/- 600 < 21 < 25 < 54 < 14 < 38 < 131 < 24 < 16 10/25/11 5370 +/- 1240 < 83 < 80 < 215 < 65 < 172 < 196 < 79 < 82 MEAN 4455 +/- 2588 29C1 PREDATOR 05/12/11 3200 +/- 798 < 46 < 62 < 129 < 54 < 120 < 909 < 64 < 50 10/24/11 3260 +/- 1040 < 49 < 77 < 167 < 57 < 132 < 177 < 70 < 67 MEAN 3230 +/- 85 29C1 BOTTOM FEEDER 05/12/11 3460 +/- 810- <59 S88 ... -

<217 <61 < 117 < 828 < 61 < 51 10/24/1.1 3790 +/- 1050 < 67 < 46 < 139 < 65 < 131 < 151 < 54 < 63 MEAN 3625 +/- 467 C-6

TABLE C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/KG DRY + 2 SIGMA SITE COLLECTION Be-7 K-40. Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 PERIOD 16B2 06/06/11 7160 +/- 1330 15000 +/- 1790 < 51 < 68 < 48 < 655 < 40 179 +/- 93 12/13/11 2000 +/- 1040 17400 +/- 2040 < 102 < 119 < 115 < 755 < 93 218 +/- 104 MEAN 4580 +/- 7297 16200 +/- 3394 - - - - - 199 +/- 55 16C4 06/06/11 3410 +/- 1720 19300 +/- 2860 < 118 < 142 < 128 < 1470 < 92 < 173 12/13/11 1900 +/- 1140 13000 +/- 2130 < 115 < 115 < 108 < 771 < 113 191 + 101 MEAN 2655 +/- 2135 16150 +/- 8910 - - - - - -

33A2 06/06/11 < 862 12700 +/- 1650 < 102. < 91. < 97 < 778 < 89 < 107 12/13/11 <,798 14600 +/- 1560 < 63 < 86 < 78 < 409 < 67 < 78 MEAN - 13650 +/- 2687 - - - - - -

C-7

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA INAIR PARTICULATE SAMPLES COLLECTED INTHE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II I GROUP III PERIOD 10S3 1iSi 14S1 6C1 13C1 22G1 01/03/11 01/10/11 32 +/- 6 34 +/- 6 30 +/- 6 29 1 6 33 +/- 6 28 +/- 6 01/10/11 01/17/11 12 +/- 5 13 +/- 5 17 +/- 6 12 +/- 5 <7 14 +/- 5 01/17/11 01/24/11 24 +/- 6 21 +/- 5 17 +/- 5 25 +/- 6 18 +/- 5 19 1 5 01/24/11 01/31/11 20 +/- 6 18 +/- 5 19 +/- 6 20 +/- 6 20 +/- 6 17+/- 5 01/31/11 02/07/11 12 +/- 5 8+/-5 14+/- 5 13 +/- 5 10 +/- 5 11 +/-5 02/07/11 02/14/11 18 +/- 5 19+/- 5 18+/- 5 22 +/- 6 15 +/- 5 17+/- 5 02/21/11 15 1 5 14 5 15+/- 5 14 +/- 5 17 +/- 5 (1) 02/14/11 02/21/11 02/28/11 14 +/- 5 8+/-5 12+/- 5 16 +/- 5 14+/- 5 16+/- 6 02/28/11 03/07/11 10 1 5 14 +5 15+/- 5 13 +/- 5 14+/- 5 11 +/-5 03/07/11 03/14/11 11 5 11 +/-6 16+/- 6 14 +/- 6 10+/- 5 12+/- 6 03/14/11 03/22/11 11 4 11 +/-4 13+/- 5 11 +/-5 12 +4 13+/- 5 03/22/11 03/28/11 22 7 23 +7 38 +/- 8 32 +8 19+/- 7 28 +/-8 03/28/11 04/04/11 23 +/-6 29 +/-6 39 +/- 7 25 +/-6 30+/- 6 25 +/-6 04/04/11 04/11/11 19 5 18+/- 5 22 +/- 5 21 +5 23 +5 24 +/- 5 04/11/11 04/18/11 12+/- 5 10+/- 5 15 +/- 5 9+/-5 13+/-5 13 +/- 5 04/18/11 04/25/11 14+/- 5 14+/- 5 14+/- 5 23 +/-6 18+/- 6 15 +/- 6 04/25/11 05/02/11 8+/-5 <7 8+/-5 9+/-5 9+/-5 8+/-5 05/02/11 05/09/11 15 5 9+/-4 13+/- 5 12 +/-5 16+/- 5 10+/- 5 05/09/11 05/16/11 (1) 6+/-4 9+/-4 8+/-4 7+/-4 <6 05/16/11 05/23/11 14 5 8+/-4 9+/-4 13+/- 4 10+/- 4 11 +/-4 05/23/11 05/31/11 18+/- 5 20 +/-5 22 +/-5 17+/- 5 22 +/-5. 15+/- 4 05/31/11 06/06/11 19 6 19+/- 6 18 6 17 +/-5 14+/- 5 22 +/-6 06/06/11 06/13/11 21 +/-5 20 +/-5 21 +/-5 26 +/-6 22 +/-5 22 +/- 5 06/13/11 06/20/11 12 +/-5 8+/-5 14 5 14 +/-5 12+/- 5 11 +/-5 06/20/11 06/27/11 12 5 15+/- 5 15 +/- 5 12 +/-5 11 +/-5 16 +/-5 06/27/11 07/05/11 14+/- 5 10+/- 5 16+/- 5 17 +/-5 11 +/-5 16+/- 5 07/05/11 07/11/11 15+/- 5 22 +/-6 24 +/-6 24 +/-6 .20 +/-6 24 +/-6 07/11/11 07/18/11 13 5 16+/- 5 21 +/-5 15+/- 5 9+/-4 16+/- 5 07/18/11 07/25/11 19 6 26 +6 22 1 6 27 +6 17+/- 6 27 +/-6 07/25/11 08/01/11 17 +/- 5 21 +5 24 +/- 6 19+/- 5 20 +/- 8 18+/- 5 08/01/11 08/08/11 17 +/- 5 18 +/- 5 18 +/- 5 17 +/- 5 23 +/- 7 14+/- 5 08/08/11 08/15/11 12 +/- 5 13 +/- 5 15 +/- 5 14 +/- 5 9+/-5 13+/- 5 08/15/11 08/22/11 17 +/- 5 16 +/- 5 .18 +/- 5 18 +/- 5 16+/- 5 16+/- 5 9+/--5 08/22/11 08/29/11 10 +/- 5 16 +/- 5 11-+/- 5 10+/- 5 18+/- 6 08/29/11 09/05/11 26 +/- 6 27 +/-6 28 +6 20 1 5 24 +/-6 26 +/-6 09/05/11 09/12/11 9+/-5 7+/-5 7. 5 <7 <8 10+/- 5 09/12/11 09/19/11 21 +/-5 17 +/-5 23 +/-5 18+/- 5 18.+/-5 22 +/-5 09/19/11 09/26/11 19+/- 6 15+/- 6 15+/- 6 9+/-5 10"+/- 6 13+/- 5 09/26/11 10/03/11 <6 10+/- 5 8+/-5 8+/-5 8+/-5 +/- 5 10/03/11 10/11/11 25+/- 5 25 5 33 1 5 24 +/-5 28 +/-5 28 +/-5 10/11/11 10/17/11 <9 <9 11 +/-6 12 +/- 6 <9 <9 10/17/11 10/24/11 12+/- 5 12 +/- 5 14+/- 5 12 +/- 5 11 +/-5 17+/- 5 10/24/11 10/31/11 20 +/- 5 14 +/- 5 .20 +/-5 17 +/- 5 20 +6 21 +/-5 10/31/11 11/07/11 18 +/- 6 15 +/- 6 18+/- 6 18 +/- 6 11+/- 5 16 +/- 6 11/07/11 11/14/11 28 +/- 6 27 +/- 6 29+/- 6 29 +/- 6 24 +/-'6 29 +/- 6 11/14/11 11/21/11 21 +/- 6 19 +/- 6 17 +/- 6 19 +/- 6 20 +/- 6 23 +/- 6 11/21/11 11/28/11 11 +/-5 12 +/- 5 21 +/- 6 18 +/- 6 12 +/- 6 19 .+/- 6 11/28/11 12/05/11 16+/- 5 16 +/-.6 14+/- 6 15 +/- 6 16 +/- 6 13+/-5 12/05/11 12/12/11 16+/- 5 13+/- 5 16+/- 5 17 +/- 5 10 +/- 5 15 +/- 5 12/12/11 12/19/11 31 +/-6 27 +/-6 36 +/-6 27 +/- 6 22 +/- 5 24 +/- 5 12/19/11 12/27/11 19 5 14 +5 18+/- 5 18 +/- 5 13 +/- 5 16 +/- 5 12/27/11 01/03/12 17 1 5 18 5 16+/- 5 13 +/- 5 12 +/- 5 17 +/- 5 MEAN 17 +/- 11 16 +/- 13 18 +/- 15 17 +/- 12 16 +/- 12 17 +/- 11

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, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP Ii - INTERMEDIATE DISTANCE LOCATIONS GROUP III- CONTROL LOCATIONS COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/-

PERIOD 9.1r) PERIOD PERIOD 2SD 2SD Ul/03/11 01/31/11 12 34 21 +14 01/03/11 - 01/31/11 12 33 22 +/- 14 01/03/11 - 01/31/11 14 28 20 +/- 12 01/31/11 02/28/11 8 19 14 7 01/31/11 - 02/28/11 10 22 15 +/- 7 01/31/11 - 02/28/11 11 17 15 +/- 6 02/28/11 03/28/11 10 38 16 + 16 02/28/11 - 03/28/11 10 32 16 +/- 14 02/28/11 - 03/28/11 11 28 16 +/- 16 03/28/11 05/02/11 8 39 17 +/- 17 03128/11 - 05/02/11 9 30 18 +/- 15 03/28/11 - 05/02/11 8 25 17 +/- 14 05/02/11 05/31/11 6 22 13 +/- 11 05/02/11 -. 05/31/11 7 22 13 +/- 10 05/02/11 - 05/31/11 10 15 12 +/- 6 05/31/11 06/27/11 8 21 16 8 05/31/11 - 06/27/11 11 26 16 +/- 11 05/31/11 - 06/27/11 11 22 18 +/- 10 06/27/11 08/01/11 10 26 19+/- 9 06/27/11 - 08/01/11 9 27 18 +/- 11 06/27/11 - 08/01/11 16 27 20 +/- 10 08/01/11 08/29/11 10 18 15+/- 6 08/01/11 - 08/29/11 9 23 14 +/- 10 08/01/11 - 08/29/11 13 18 15 +/- 4 08/29/11 10/03/11 7 28 17 +/- 15 08/29/11 - 10/03/11 8 24 14 +/- 12 08/29/11 - 10/03/11 8 26 16 +/- 15 10/03/11 10/31/11 11 33 19 +/- 15 10/03/ 11 - 10/31/11 11 28 18 +/- 13 10/03/11 - 10/31/11 17 28 22 +/- 11 10/31/11 11/28/11 11i 29 20 +/- 12 10/31/11 - 11/28/11 11 29 19 +/- 12 10/31/11 -11/28/11 16 29 22 +/- 11 11/28/11 - 01/03/12 13 36 19 +/- 13 11/28/11 - 01/03/12 10 27 16 +/- 10 11/28/11 - 01/03/12 13 24 17 +/- 9 01/03/11 01/03/12 6 39 17 +/- 13 01/03/11 - 01/03/12 7 33 17 +/- 12 01/03/11 01/03/12 8 29 17 +/- 11

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-9

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 PERIOD 10S3 01/03 - 03/28/11 76 +/- 27 <3 <4 <3 < 2 <3 03/28 - 06/27/11 96 +/- 45 < 4 <6 <4 <4 <4 06/27 - 10/03/1.1 50 +/- 38 <3 <5 <3 <3 <3 10/03 - 01/03/12 60 +/- 15 <2 <2 <2 <2 <2 MEAN 71 +/- 39 11S1 01/03 - 03/28/11 89 +/- 27 <3 <3 <2 <2 <3 03/28 - 06/27/11 79 +/- 26 < 3 <4 <2 <2 <2 06/27 -10/03/11 65 +/- 31 <4 <4 <4 <4 <3 10/03 - 01/03/12 66 +/- 13 < 2 <2 <2 <2 <2 MEAN 75 +/- 23 -

13C1 01/03 - 03/28/11 55 +/- 26 < 3 <4 <4 <3 <3 03/28 - 06/27/11 86 +/- 26 < 3 <.3 <3 <3 <3 06/27 - 10/03/11 68 +/- 23 < 3 <4 <3 <3 <1 10/03 01/03/12 62 +/- 22 < 3 <2 <3 <2 <3 MEAN 68 +/- 27 -

14S1 01/03 -03/28/11 72 +/- 25 < 2 <4 <2 <3 <2 03/28 - 06/27/11 74 +/- 34 < 2 <3 <3 <2 <3 06/27 - 10/03/11 69 +/- 29 <4 <4 <4 <4 <3 10/03 - 01/03/12 82 +/- 22 < 2 <3 <3 <3 <3 MEAN 74 +/- 11 -

22G1 01/03 - 03/28/11 80 +/- 22 <2 <3 <3 <3 <2 03/07 - 03114/11 < 329 < 30 < 34

30 < 37 < 29 03/14 - 03/22/11 < 243 < 20 < 22

31 < 28 < 25 03/22 - 03/28/11 < 226 < 28 < 24 < 33- < 34 < 32 03/28 .- 04/04/11 < 280 < 38

33 <31 < 45 < 35 03/28 - 06/27/11 80 +/- 35 < 3 <5 <2 <2 <2 04104 - 04/11111 < 293 < 39 < 29 < 37 < 31 < 31 06/27 - 10/03/11 . 83 +/- 33 < 3 <6 <3 <3 <3 10/03 -. 01/03/12 60 +/- 22 <3 <.3 <4 <3 <3 MEAN 76 +/- 22 -

6C1 01/03 -,03/28/11 104 +/- 34 < 3 <4 <3 <3 <4 03/28 - 06/27/11 88 +/- 26 .< 3 <3 <3 <2 <3 06/27 -. 10/03/11 70 +/- 26 < 2 <3 <2 <2 <2 10/03 - 01/03/12 81 +/- 14 < 1 <2 <2 <2 <2 MEAN 86 +/- 29

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT C-10

TABLE C-VI.1 CONCENTRATIONS OF 1-131 INAIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUPII GROUPIII I

PERIOD 10S3 11S1 14S1 6C1 13C1 22G1 0 U I

01/03/11 01/10/11 <21 < 38 < 50 < 39 < 38 < 51 01/10/11 01/17/11 < 51 < 52 < 62 < 52 < 61 < 63 01/17/11 01/24/11 < 27 < 27 < 29 < 27 < 28 < 29 01/24/11 01/31/11 < 39 < 39 < 60 < 40 < 59 < 60 01/31/11 02/07/11 < 22 < 22 < 36 < 22 < 12 < 37 02/07/11 02/14/11 < 20 <*21 < 30 < 21 < 30 < 30 02/14/11 02/21/11 < 64 < 66 < 22 < 64 < 51 (1) 02/21/11 02/28/11 < 59 < 59 < 49 < 60 < 48 < 59 02/28/11 03/07/11 < 42 < 58 < 58 < 43 < 58 < 25 03/07/11 03/14/11 < 50 < 50 < 51 < 50 < 50 < 67 03/14/11 03/22/11 < 23 < 25 < 25 < 28 < 20 < 25 03/22/11 03/28/11 6 3 +/- 29 89 +/- 30 < 33 < 53 100 +/- 22 < 55 03/28/11 04/04/11 7 6 +/- 30 70 +/- 18 70 +/- 17 24 +/- 18 70 +/- 23 59 +/-20 04/04/11 04/11/11 4 1 +/- 24 < 30 28 +/- 18 < 36 < 34 < 39 04/11/11 04/18/11 < 31 < 27 < 37 < 38 < 41 < 26 04/18/11 04/25/11 < 34 < 35 < 36 < 35 < 35 < 36 04/25/11 05/02/11 < 58 < 58 < 66 < 59 < 66 < 66 05/02111 05/09/11 < 48 < 48 < 51 < 48 < 50 < 52 05/09/11 05/16/11 (1 < 60 < 50 < 60 < 49 < 50 05/16/11 05/23/11 < 35 < 31 < 45 < 30 < 44 < 45 05/23/11 05/31/11 < 32 < 32 < 39 '< 33 < 38 < 38 05/31/11 06/06/11 < 69 < 69 < 52 < 69 < 51 < 53 06/06/11 06/13/11 < 52 < 52 < 46 < 53 < 45 <46 06/13/11 06/20/11 < 34 < 34 < 32 < 34 < 32 < 33 06/20/11 06/27/11 < 26 < 62 < 54 < 61 < 62 < 52 06/27/11 07/05/11 < 26 < 26 < 37 < 26 < 38 < 37 07/05/11 07/11/11 < 36 < 37 < 56 < 37

57 < 55 07/11/11 07/18/11 < 23 < 24 < 25' < 23 < 25 < 24 07/18/11 <29 07/25/11 < 53 < 54 < 51 ":< 54 < 50 07/25/11 08/01/11 < 54 < 56 < 36 < 55 < 54 < 35 08/01/11 08/08/11 < 18 < 18 < 14' < 18 < 19 < 14 08/08/11 08/15/11 < 37 < 38 < 61 < 38 < 61 <58 08/15/11 08/22/11 < 58 < 59 < 621 * < 58 < 63 <33 08/22/11 08/29/11 < 29 < 30 < 28 < 30 < 28 < 31 08/29/11 09/05/11 < 37 < 38 < 49 < 21 < 50 < 48 09/05/11 09/12/11 < 48 < 49 < 51 < 49 < 61 < 50 09/12/11 09/19/11 <19 < 45 < 39 < 45 < 46 < 39 09/19/11 09/26/11 < 39 < 40 < 33 < 40 < 33 < 32 09/26/11 10/03/11 < 25 < 25 < 29 < 25 < 30 < 28 10/03/11 10/11/11 < 20 < 20 < 31 < 20 < 31 < 30 10/11/11 10/17111 < 42 < 42 < 59 < 42 < 24 < 58 10/17/11 10/24/11 < 37 < 37 < 11 < 37 < 11 < 6 10/24/11 10/31/11 < 38 < 39 < 49 < 40 < 50 < 47 10/31/11 11/07/11 < 47 < 48 < 53 < 48 < 53 < 52 11/07/11 11/14/11 <16 < 16 < 22 < 16 < 23 < 22 11/14/11 11/21/11 < 47 < 48 < 68 < 48 < 69 < 66 11/21/11 11/28/11 < 42 < 42 < 38 < 18 < 43 < 37 11/28/11 12/05/11 < 44 < 45 < 30 < 45 < 31 < 30 12/05/11 12/12/11 < 20 < 36 < 40 < 36 < 37 < 39 12/12/11 12/19/11 < 39 < 40 < 40 < 40 < 40 < 39 12/19/11 12/27/11 < 31 < 32 < 30 < 32 < 32 < 29 12/27/11 01/03/12 < 23 < 23 < 41 < 23 < 41 < 40 MEAN 60 +/- 36 79 +/- 27 49 +/- 59 85 +/- 41 -

(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-11.

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM I INDICATOR FARM '

COLLECTION 23F1 36E1 10F4 18E1 19B1 25C1 DATE 01/11/11 < 0.4 < 0.5

0.6 < 0.5 < 0.5

0.6 02/16/11 < 0.4 < 0.5 < 0.6 < 0.4

0.9 03/15/11 < 0.5

0.7 < 0.6 < 0.8 < 0.7 03/23/11 < 0.3 03/30/11 < 0.4 04/05/11 < 0.6

0.9 < 0.8 < 0.7 < 0.5

0.8 04/13/11 < 0.2 04/19/11 < 0.4

0.6 < 0.4 < 0.4 < 0.7 04/25/11 < 0.6 05/04/11 < 0.6 < 0.4 < 0.5 < 0.6 < 0.6 05/17/11 < 0.3 < 0.4 < 0.4 < 0.3 < 0.4 05/31/11 < 0.5

0.6

0.4 < 0.4 < 0.5 06/14/11 < 0.7 < 0.8

0.6 < 0.8 < 0.9 06/28/11 < 0,5 < 0.5 < 0.5 < 0.9 < 0.7 07/12/11 < 0.7 < 0.7 < 0.8

0.8 < 0.9 < 0.9 07/26/11

0.6 < 1.0 < 0.7 < 0.9 < 0.8 08/09/11 < 0.5 < 0.7 < 0.6 < 0.7 < 0.8 08/23/11 < 0.6 < 0.6 < 0.5 < 0.7 < 0.8 09/06/11 < 0.5 < 0.6 < 0.5 < 0.6 < 0.7 09/20/11 < 0.5 < 0.7 < 0.6

0.6

0.6 10/04/11

0.5 < 0.7 < 0.9 < 0.7 < 0.6 < 0.8 10/18/11 < 0.5 < 0.7 < 0.7

0.7 < 0.7 11/01/11 < 0.6 < 0.7 < 0.6

0.7 < 0.8 11/15/11

0.8 < 0.6 < 0.7 < 0.6 < 0.8 11/29/11

0.6 < 0.5 < 0.6 < 0.7 < 0.6

< 0.6 12/13/11 < 0.5 < 0.6 < 0.7 < 0.6 MEAN -

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT C-12

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS, IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD 10F4 01/11/11 1420 +/- 125 <5 <6 < 36 *<1 02/15/11 1290 +/- 168 <7 <8 < 56 < 14 03/15/11 1340 +/- 160 <7 <7 < 51 < 15 04/05/11 1390 +/- 134 <5 <5 < 49 < 10 04/19/11 1260 +/- 138 <5 <6 < 48 < 13 05/04/11 1290 +/- 119 <5 <4 < 32 < 11 05/17/11 1340 +/- 123 <4 <5 < 32 <9 05/31/11 1200 +/- 120 <5 <5 < 55 < 12 06/14/11 1210 +/- 155 <5 <5 < 31 < 13 06/28/11 788 +/- 104 <5 <6 < 43 < 12 07/12/11 709 +/- 170 <7 < 10 < 35 < 12 07/26/11 404 +/- 138 <7 <8 < 39 < 13 08/09/11 402 +/- 114 <7 <7 < 35 < 10 08/23/11 639 +/- 137 <7 <7 < 32 <7 09/06/11 1140 +/- 136 <5 <5 < 25 <7 09/20/11 669 +/- 119 <6 <6 < 34 < 10 10/04/11 734 +/- 152 <8 <7 < 48 <9 10/18/11 482 +/- 127 <8 <7 < 33 < 14 11/01/11 1230 +/- 144 <5 <6 < 33 <8 11/15/11 1030 +/- 242 <9 < 10 < 32 < 12 11/29/11 1340 +/- 178 <7 <7 < 29 < 13 12/13/11 1040 +/- 182 <8 <9 < 42 < 13 MEAN 1016 +/- 688 18E1 01/11/11 1100 +/- 97 <4 <5 < 25 <8 02/15/11 1180 +/- 143 <6 <7 < 42 < 13 03/15/11 1270 +/- 141 <6 <7 < 55 < 15 04/05/11 1190 +/- 129 <4 <5 < 43 < 15 04/19/11 1040 +/- 122 <5 <5 < 44 < 10 05/03/11 924 +/- 132 <5 <6 < 46 < 11 05/17/11 1190 +/- 126 <5 <5 < 40 < 10 05/31/11 1110 +/- 119 <6 <5 < 50 < 14 06/14/11 1220 +/- 169 <6 <6 < 50 < 14 06/28/11 1270 +/- 141 <6 <6 < 44 < 15 07/12/11 1210 +/- 197 <8 <9 < 39 <13 07/26/11 1180 +/- 170 <8 <8 < 37 <8 08/09/11 923 +/- 123 <5 <6 < 24 <6 08/23/11 924 +/- 144 <6 <7 < 26 <7 09/06/11 1060 +/- 165 <6 <5 < 32 <11 09/20/11 1040 +/- 141 <5 <5 < 27 <7 10/04/11 1140 +/- 160 < 11 < 11 < 50 < 10 10/18/11 1100 +/- 151 <6 <8 < 31 < 12 11/01/11 1310 +/- 171 <8 <7 < 42 <9 11/15/11 1280 +/- 56 <2 <2 < 37 < 10 11/29/11 1140 +/- 155 <7 <7 < 32 < 10 12/13/11 1220 +/- 154 <6 <6 < 31 < 11 MEAN 1137 +/- 231 C-13

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD 19B1 01/11/11 1180 124 <5 <6 < 34 <9 02/15/11 1340 143 <5 <6 < 35 <8 03/15/11 1270 149 <7 <6 < 54 < 15 04/05/11 1220 120 <4 <4 < 39 < 12 04/19/11 1360 129 <5 <6 < 41 < 12 05/03/11 1220 142 <5 <6 < 43 < 15 05/17/11 1220 137 <.6 <6 < 41 < 13 05/31/11 1210 98 <4 <4 < 40 < 15 06/14/11 1130 148 <6 <6 < 46 <8 06/28/11 1310 159 <6 <7 < 50 < 12 07/12/11 1330 178 <9 <8 < 38 <7 07/26/11 1250 173 <5 <7 < 29 <5 08/09/11 1350 148 <6 <6 < 30 <7 08/23/11 1350 176 <7 <6 < 36 <9 09/06/11 1380 129 <5 <7 < 30 <7 09/20/11 1260 126 <5 <6 < 31 <7 10/04/11 1210 176 <7 <9 < 37 < 12

.10/18/11 1450 174 <8 <8 < 37 < 10 11/01/11 1150 185 <5 <8 < 33 ,< 13 11/15/11 1300 162 <6 <7 < 32 <8 11/29/11 1300 127 <5 <6 < 30 <8 12/13/11 1310 150 <6 <7 < 37 <9 MEAN 1277 +/- 160 25C1 01/11/11 1270 +/- 104 <4 <4 < 25 <5 02/15/11 1280 +/- 144 <5 <7 < 42 < 12 03/15/11 1340 +/- 130 <5 <5 < 49 < 13 04/05/11 1300 +/- 134 <3 <5 < 42 < 12 04/19/11 1250 +/- 116 <4 <5' < 35 < 10 05/03/11 1320 +/- 148 <6 <6 < 41 < 13 05/17/11 1280 +/- 154 <6 <7 < 48 < 13 05/31/11 1220 +/- 129 < 5 <6 < 60 < 13 06/14/11 1250 +/- 144 <5 <8 < 43 < 12 06/28/11 1290 +/- 124 <4 <5 < 39 < 13 07/12/11 1300 +/- 179 <7 <7 < 35 < 11 07/26/11 1270 +/- 127 <5 <5 < 24 <6 08/09/11 1260 +/- 126 <6 <6 < 29 <9 08/23/11 1130 +/- 176 <7 <7 < 31 < 13 09/06/11 1430 +/- 177 <6 <6 < 30 < 10 09/20/11 1410 +/- 144 <5 <5 < 32 < 12 10/04/11 1270 +/- 196 <6 <8 < 41 < 14 10/18/11 1100 +/- 141 <7 <7 < 36 <9 11/01/11 1230 +/- 168 <8 <7 < 39 < 12 11/15/11 1220 +/- 176 <7 <8 < 42 < 14 11/29/11 1180 +/- 126 <5 <5 < 23 <4 12/13/11 1180 +/- 151 <7 <7 < 30 < 11 MEAN 1263 +/- 155 C-14

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD 23F1 01/11/11 1300 +/- 126 <5 <6 < 32 <8 02/16/11 1170 +/- 131 <5 <7 < 51 < 12 03/15/11 1160 +/- 100 <5 <5 < 37 < 14 03/23/11 1270 +/- 116 <5 <6 < 49 < 14 03/30/11 1310 +/- 213 <8 < 12 < 33 < 10 04/05/11 1320 +/- 135 <3 <4 < 42 <9 04/13/11 1120 +/- 53 <1 <1 <19 <4 04/19/11 1210 +/- 120 <5 <5 < 39 < 13 04/25/11 1120 +/- 149 <5 <6 < 44 < 13 05/03/11 1120 +/- 126 <6 <6 < 37 <9 05/17/11 1170 +/- 128 <5 <6 < 44 < 11 05/31/11 1210 +/- 74 <3 <3 < 31 <9 06/14/11 1340 +/- 125 <5 <6 < 39 < 13 06/28/11 1260 +/- 145 <6 <7 < 48 <.14 07/12/11 1160 +/- 174 <7 <8 < 32 < 11 07/26/11 1240 +/- 129 <5 <6 < 25 <7 08/09/11 1180 +/- 166 <6 <6 < 29 < 10 08/23/11 1200 +/- 139 <6 <6. < 31 <9 09/06/11 1290 +/- 166 <7 <9 < 38 < 14 09/20/11 1280 +/- 141 <5 < 6 < 31 <9

.10/04/11 1360 +/- 176 < 10 <11 < 52 < 11 10/18/11 1080 +/- 146 <7 S<8 < 37 < 13 11/01/11 1320 +/- 198 <6 <7 < 45 <9 11/15/11 1330 +/- 186 <7 < 8-

< 39 < 12 11/29/11 1430 +/- 167 <6 <7 < 31 <9 12/13/11 1250 +/- 150 <7 < 8. < 31 < 12 MEAN 1238 +/- 176 36E1 01/11/11 1030 +/- 162 <4 <6 < 23 <7 04/05/11 1170 +/- 96 <4 <5 < 43 < 14 07/12/11 1110 +/- 173 <7 <7 < 41 < 11 10/04/11 1070 +/- 149 <9 < 9- < 38 <.10 MEAN 1095 +/- 119 BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT C-15

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED INTHE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 PERIOD 11S3 06/28/11 Cabbage - (1) 06/28/11 Collards - (1) 06/28/11 Kale - (1) 07/25/11 Cabbage < 226 (1) 5750 +/- 561 < 18 < 25 < 21 < 47 < 21 < 25 < 554 < 41 < 90 07/25/11 Kale < 213 (1) 6340 +/- 516 < 20 < 27 < 29 < 53 < 23 < 25 < 595 < 40 < 103 07/25/11 Swiss Chard < 266 (1) 6870 +/- 628 < 28 < 29 < 32 < 58 < 28 < 34 < 620 < 50 < 117 08/18/11 Cabbage < 67 " 2490 +/- 273 <6 <8 <7 < 12 <7 <7 845 +/- 263 18 +/- 14 < 42 08/18/11 Collards < 193 3530 +/- 414 < 17 < 21 < 21 < 35 < 21 < 22 < 494 < 36 < 88 08/18/11 Kale < 219 3210 +/- 489 < 24 < 24 < 29 < 29 < 21 < 24 < 482 < 39 <-102 09/19/11 Collards 478 +/- 180 3520 +/- 456 < 22 < 21 < 26 < 43 < 20 < 23 < 433 41 +/- 28 < 96 09/19/11 Kale 595 +/- 226 3460 +/- 609 < 27 < 33 < 32 < 54 < 22 < 26 < 568 < 42 < 105 09/19/11 Swiss Chard 1020 +/- 224 4460 +/- 440 < 18 < 20 < 25 < 43 < 17 < 20 < 473 56 +/- 32 < 82 10/12/11 Cabbage 406 +/- 230 3240 +/- 608 < 29 < 28 < 35 < 47 < 26 < 31 < 634 < 60 < 126 10/12/11 Collards 384 +/- 273 3640 +/- 692 <.37 < 34 < 44 < 54 < 31 < 33 < 765 <*53 < 148 10/12/11 Kale < 212 2300 +/- 428 < 27 < 25 < 33 < 46 < 24 < 25 < 542 43 +/- 31 < 105 MEAN 577 +/- 522 4068 +/- 2965 39 +/- 31 13S3 06/28/11 Cabbage < 123 4880 +/- 318 < 12 < 15 < 14 < 53 < 12

13 1830 +/- 385 < 22 < 56 06/28/11 Collards < 149 4950 +/- 392 < 15 < 16 < 20 < 58 < 15 < 16 1430 +/- 403 < 27 < 64 06/28/11 Kale < 99 5820 +/- 277 <9 < 11 < 11 < 58 <9

10 1350 +/- 291 31 +/-17 < 40 07/25/11 Cabbage < 208 5690 +/- 521 < 22 < 21 < 30 .< 51 < 25 < 24 2590 +/- 651 < 42 < 110 07/25/11 Collards < 245 6330 +/- 571 < 24 < 26 < 28 < 56 < 23 < 22 3200 +/- 750 < 43 <100 07/25/11 Kale < 239 6730 +/- 668 < 24 < 31 < 34 < 51 < 25 < 22 764 +/- 573 < 53 <110 08/18/11 Cabbage < 113 1880 +/- 367 < 17 *< 14 < 18 < 23 < 12 < 15 < 361 < 29 < 60 08/18/11 Collards 219 +/- 124 3290 +/- 358 < 14 < 13 < 18 < 28 < 15 < 17 < 357 < 26 < 76 08/18/11 Kale 230 +/- 196 3620 +/- 408 < 20 < 18 < 22 < 30 < 17

18 < 449 < 40 < 90 09/19/11 Collards 533 +/- 176 3740 +/- 502 < 24 < 20 < 24 < 47 < 20 < 23 1460 +/- 718 < 43 < 99 09/19/11 Kale 344 +/- 200 4540 +/- 705 < 26 < 27 < 25 < 49 < 24 < 26 < 629 < 46 < 92 09/19/11 Swiss Chard 746 +/- 242 5770 +/- 549 < 20 < 21 < 25 < 43 < 19 < 22 1760 +/- 520 < 45 4 96 10/12/11 Collards 428 +/- 309 4200 +/--683 < 31 < 32 < 44 < 48 < 29 < 35 978 +/- 761 < 60 < 136 10/12/11 Kale 265 t 221 4520 +/- 552 < 24 < 20 < 27 < 41 < 22 < 24 < 541 68 +/-51 < 94 10/12/11 Swiss Chard 476 +/- 228 4170 +/- 585 < 23 < 24 < 23 < 36 < 25 < 21 < 704 < 51 < 120 MEAN 405 +/- 360 4675 +/- 2556 - 1707 +/- 1535 49 +/- 52 -

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 PFRIflfl PERIOD 31G1 06/28/11 Cabbage 170 +/- 97 5060 +/- 229 <9 < 10 < 10 < 50 <8 <9 266 +/- 180 24 +/- 14 < 37.

06/28/11 Kale 192 +/- 99 5730 +/- 289 < 12 < 13 < 15 < 59 < 10 < 12 < 228 39 +/- 17 < 49 06/28/11 Lettuce 328 +/- 91 6950 +/- 253 <9 <9 < 12 < 32 <8 <9 < 171 < 14 < 39 07/25/11 Broccoli Leaves 245 +/- 171 6940 +/- 520 < 18 < 18 < 20 < 40 < 17 < 17 < 462 < 33 < 80 07/25/11 Cabbage < 207 5640 +/- 580 < 27 < 29 < 36 < 46 < 22 < 23 < 394 < 38 < 97 07/25/11 Kale < 178 2930 +/- 337 < 16 < 18 < 19 < 36 < 16 < 19 < 415 < 37 < 65 08/18/11 Cabbage < 111 3630 +/- 481 < 13 < 13 < 12 < 18 < 11 < 14 < 287 < 24 < 65 08/18/11 Kale 632 +/- 241 3080 +/- 695 < 30 < 28 < 34 < 34 < 23 < 30 < 541 < 52 < 100 08/18/11 Squash Leaves 2040 +/- 294 5480 +/- 592 < 23 < 22 < 31 < 31 < 19 < 19 < 469 < 46 < 101 09/19/11 Broccoli Leaves 1270 +/- 264 4900 +/- 622 < 23 < 22 < 29 < 59 < 23 < 24 < 569 < 48 < 110 09/19/11 Cabbage 350 +/- 244 3490 +/- 469 < 19 < 16 < 22 < 48 < 19 < 23 < 451 53 +/- 38 < 81 09/19/11 Kale 2030 +/- 345 6680 +/- 740 < 25 < 26 < 28 < 52 < 25 < 25 < 541 125 +/- 40 < 122 10/12/11 Broccoli Leaves 1410 +/- 444 3810 +/- 485 < 25 < 27 < 22 < 46 < 30 < 27 < 719 < 56 < 109 10/12/11 Cabbage 674 +/- 309 4530 +/- 646 < 31 < 25 < 37 < 55 < 24 < 29 < 664 < 47 < 111 10/12/11 Cauliflower Leaves -.695 +/- 166 3550 +/- 394 < 18 < 16 < 27 < 30 < 19 < 17 < 392 < 34 < 81 MEAN 836 +/- 1373 4827 +/- 2777 60 +/- 90

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-1 7

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE + 2 S.D.

2E1 7.3 +/- 1.2 7.0 +/- 0.7 6.6 +/- 0.9 7.9 +/- 0.6 7.6 +/- 0.9 3S1" 7.2 +/- 1.3 7.0 +/- 0.5 6.5 +/- 0.7 7.2 +/- 0.6 8.1 +/- 0.7 4E1 5.9 +/- 1.1 6.1 +/- 0.6 5.3 +/- 0.7 6.5 +/- 1.4 5.6 +/- 0.9 5H1 8.4 +/- 1.1 8.4 +/- 0.6 7.7, +/- 0.8 8.4 +/- 0.8 9.1 +/- 0.7 5S1 8.0 +/- 1.5 7.6 +/- 0.6 7.2 +/- 0.6 8.2 +/- 0.5 8.9 +/- 0.9 6C1 7.1 +/- 0.8 7.2 +/- 0.7 6.5 +/- 0.3 7.3 +/- 0.2 7.4 +/- 0.6 7E1 7.3 +/- 1.2 7.2 +/- 1.1 6.6 +/- 0.2 8.1 +/- 1.2 7.4 +/- 0.7 7S1 7.5 +/- 1.6 7.1 +/- 0.6 6.7 +/- 0.5 7.7 +/- 0.6 8.5 +/- 0.5 9C1 7.0 +/- 1.1 7.5 +/- 1.0 6.2 +/- 0.7 7.2 +/- 0.4 7.0 +/- 1.6 10E1 7.3 +/- 1.2 7.6 +/- 0.5 6.5 +/- 0.5 7.9 +/- 1.2 7.2 +/- 0.6 10F3 7.3 +/- 0.7 7.4 +/- 0.6 6.8 +/- 0.4 7.6 +/- 0.5 7.4 +/- 0.7 10S3 7.5 +/- 1.5 7.0 +/- 0.3 6.7 +/- 0.5 7.8 +/- 0.7 8.4 +/- 0.4 i1lS 8.5 +/- 1.7 8.2 +/- 0.4 7.4 +/- 0.4 9.2 +/- 1.8 9.2 +/- 0.7 13C1 5.4 +/- 0.8 5.7 +/- 0.6 4.8 +/- 0.5 5.6 +/- 0.7 5.6 +/- 0.5

-13E1 7.1 +/- 1.2 7.8 +/- 0.9 6.4 +/- 0.4 7.0 +/- 0.4 7.2 +/- 0.9 13S2 9.9 +/- 1.7 9.9 +/- 1.4 8.8 +/- 0.6 10.1 +/- 0.6 10.9 +/- 0.8 14S1 6.7 +/- 1.1 6.8 +/- 0.5 6.1 +/- 0.5 7.4 +/- 1.3 6.4 +/- 0.5 15D1 7.4 +/- 0.7 7.3 +/- 0.7 6.9 +/- 0.3 7.4 +/- 0.7 7.8 +/- 0.6 16F1 7.2 +/- 0.6 7.3 +/- 0.8 6.8 +/- 0.4 7.5 +/- 0.9 7.0 +/- 1.1 17B1 7.0 +/- 0.8 7.2 +/- 0.4 6.4 +/- 0.7 7.0 +/- 0.6 7.2 +/- 0.8 18S2 7.7 +/- 1.0 7.8 +/- 0.9 7.0 +/- 0.5 7.9 +/- 0.4 8.1 +/- 0.7 19D1 6.7 +/- 0.8 6.6 +/- 0.3 6.1.+/- 0.6 6.9 +/- 0.3 7.0 +/- 1.0 20D1 6.5 +/- 0.9 7.0 +/- 0.3 5.9 +/- 0.5 6.6 +/- 0.5 6.6 +/- 0.5 20F1 7.0 +/- 0.9 7.1 +/- 0.9 6.4 +/- 0.5 6.9 +/- 0.6 7.5 +/- 0.9 21S2 6.6 +/- 1.0 6.7 +/- 0.6 6.0 +/- 0.3 6.6 +/- 1.4 7.2 +/- 0.6 23S2 6.6 +/- 1.0 6.8 +/- 0.3 5.9 +/- 0.6 6.8 +/-'0.6 7.0 +/- 0.7 24D1 6.2 +/- 1'.1 6.5 +/- 0.6 5.4 +/- 0.4' 6.5 +/- 0.8 6.5 +/- 0.8 25D1 6.1 +/- 0.8 6.3 +/- 1.2 5.5 +/- 0.3 6.0 +/- 0.6 6.4 +/- 0.5 25S2 6.3 +/- 1.1 5.9 +/- 0.5 5.7 +/- 0.3 6.7 +/- 0.3 6.7 +/- 0.5 26S3 6.5 +/- 1.2 6.2 +/- 0.5 5.8 +/- 0.4 6.7 +/- 1.0 7.2 +/- 0.7 28D2 6.6 +/- 0.5 6.7 +/- 0.8 6.2 +/- 0.4 6.6 +/- 0.8 6.8 +/- 1.1 29E1 6.8 +/- 1.2 7.1 +/- 0.7 6.1 +/- 0.5 6.5 +/- 0.7 7.4 +/- 1.1 29S1 6.5 +/- 0.8 6.9 +/- 0.7 5.9 +/- 0.5 6.6 +/- 0.7 6.6 +/- 0.6 31D1 8.2 +/- 1.1 8.5 +/- 0.3 7.4 +/- 0.4 8.4 +/- 0.4 8.6 +/- 0.7 31D2 7.3 +/- 1.1 7.2 +/- 0.7 6.6 +/- 0.5 7.5 +/- 0.5 7.9 +/- 0.8 31S1 7.3 +/- 1.0 7.4 +/- 0.4 6.7 +/- 0.6 7.9 +/- 1.0 7.0 +/- 0.8 34E1 7.0 +/- 0.8 7.3 +/- 0.4 6.4 +/- 0.5 7.0 +/- 0.6 7.3 +/- 0.5 34S2 7.2 +/- 0.8 7.0 +/- 0.3 6.9 +/- 0.8 7.2 +/- 0.8 7.8 +/- 0.7 36D1 6.6 +/- 0.5 6.3 +/- 1.4 6.8 +/- 1.7 6.7 +/- 0.6 6.4 +/- 0.8 36S2 7.4 +/- 1.1 7.1 +/- 1.1 6.9 +/- 0.6 7.4 +/- 0.4 8.2 +/- 1.3 C-18

!TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, INTERMEDIATE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION SITE BOUNDARY INTERMEDIATE CONTROL PERIOD +/- 2 S.D.

JAN-MAR 7.2 +/- 1.8 7.0 +/- 1.2 8.4 +/- 0.0 APR-JUN 6.6 +/- 1.6 6.3 +/- 1.2 7.7 +/- 0.0 JUL-SEP 7.6 +/- 1.9 7.1 +/- 1.3 8.4 +/- 0.0 OCT-DEC 7.9 +/- 2.3 7.1 +/- 1.4 9.1 +/- 0.0 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/- 2 S.D.

SITE BOUNDARY 64 5.7 10.9 7.3 +/- 2.1 MIDDLE 92 4.8 8.6 6.9 +/- 1.4 ICONTROL 4 7.7 9.1 8.4 +/- 1.1

. SITE BOUNDARY STATIONS - 10S3, 11S 1, 13S2, 14S1, 18S2,21S2,23S2, 25S2, 26S3, 29S1, 31S1, 34S2, 36S2, 3S1, 5S1, 7S1 MIDDLE STATIONS - 10EI, 10F3, 13C1, 13E1, 15D1, 16F1, 171B1, 19D1, 20D1, 20F1, 24D1, 25D1, 28D2, 29E1, 2E1, 31D1, 31D2, 34E1, 36D1, 4E1 6C1, 7E1, 9C1 CONTROL STATIONS - 5H1I C-19

C-20 FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2011 120 10 ._----- ..............................................

i,:~ . . . . . ~ . ...

'~~~~~~

8 -- 4 --1: --- - --- -- ---. ":: ----- ------.----- -- ----- ----- -----

T.- -- --

t '

4--

O4. :A

L - 0 ... . .......

-:-- . - .L............................. : * - :-.-

] = CONTROL S-INDICATOR .

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

FIGURE C-2 MEAN ANNUAL CS-137 CONCENTRATIONS IN FISH SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2011 65 --- ----------- -. . ....

-"--16C5

-&-20S1 55 ...................... .. ..

',............,, .:....F. .. .. .

. 29C 45..... . .. Note: Second half of 20W--

switched to reportigg <MDC

............................... when no activity was detected.

Using MDC values result in a larger number. LLD < 150-.

pCi/kg.

E LGS CRITICALITY UNIT NO. 1: 12/22/84 gUNIT NO. 2:, 08/11/89 25 . ...................

-5... , . . . ', ,, ,,. . ,. ,. , ,. ,. , , : '.

82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 11 YEAR CONTROL = 29C1 Station 20Sl discontinued in 1995 C-21

C-22 FIGURE C-3 CONCENTRATIONS OF CS-137 IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982- 2011 1400 -

1400-................... .....*..' 16B2 LGS CRITICALITY3 80 - . . . UNIT NO. 1: 12/22/84 . . . . . a. .I 1000 -- -UNITNO.2: 08/11189 .. ......

CONTROL 33A2 4200 ". .....

a-I ............

, ............ . . . ........ r ... ...I .......... .

m 600 - . . -- -- - - - - - - - - - - - - - - - -

0 1....... .. ................. . . ............................. ..

0- - ----- - -- - -- ,

0200 82 83 85 86 88 89 91 92 94 95 97 98 00 01 03 04 06 07 09 10 12 Year

FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982- 2011 1 oU

-- Group I 135

............. *,* ,-*-G rou p III

- -- I'IL . .. .. ... ...

120

..... Chernobyl 105 90 CL

0) 75 ........ ......... . .......... ..........

0)

SLGS CRITICALITY 60 -- -------- ------ UNIT NO. 1: 12/22/841-89 45 30 15 U N 2 0 /11/89 0

82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 12 YEAR C-23

C-24 FIGURE C-5 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2011 50O I-s--GROUP I

-i--GROUP II 40_---GROUP III 40 ....... -- .......................... . ........... ........................................... . .

IJJ.

20....-- .- ...- - .- ...- ...........-,............ ....

C?

wi 10 ............................. ......... .. . ........

0 H iw il i il b l t ii .1 1 3 6 9 12 15 18 21 24 27 30 33 36 39 42 45 48 51 WEEK NO.

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

IN THE VICINITY OF LGS, 1985- 2011 NOTE: Control Station 5H1 became the only distant location beginning in 1995 13 1 ........... ...................... ":.....................--SI OTE O 12 ........................... .................... INTERMEDIATE

Control 5H1-1 r . . '. .

9 8% . . .!. . - i -. - .:. . . . . ; . . . . . . :. . .: - . , - - - . -... ... . . .. .. - -, .... ... , * ,.. .

0-9 ~ ~:

7.

-.:~'

. .,. . - -%I. - - , - - .- : . .. .,--.----- .. ..- , .--

6 . ....... ......... ------ ---- ---- ---

5 . . . . ... . . .. .........

4 85 86 87 88 89 90 91 92 93 94 95 96 97 98 990001 0203 040506070809 1011 12 YEAR C-25

Intentionally Left Blank APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

TABLE D-1.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 16C2 PERIOD 12/27/10 01/31/11 1.8 +/- 0.5 01/31/11 03/01/11 3.0 +/- 0.9 03/01/11 03/29/11 < 1.8 03/29/11 05/03/11 1.3 +/- 0.8 05/03/11 05/31/11 1.2 +/- 0.6 05/31/11 06/27/11 0.9 +/- 0.5 06/27/11 08/02/11 < 2.0 08/02/11 08/29/11 2.1 + 1.1 08/29/11 09/27/11 3.0 + 0.8 09/27/11 11/01/11 1.1 + 0.5 11/01/11 11/28/11 < 0.9 11/29/11 12/27/11 < 0.9 MEAN 1.8 +/- 0.8 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 146C2 PERIOD 12/27/10 - 03/29/11

146 03/29/11 - 06/27/11

149 06/27/11 - 09/27/11

149 09/27/11 - 12/27/11

151 MEAN D-1

TABLE D-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED INTHE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD 16C2 12/27/10 01/31/11 <4 <2 <5 <3 <5 <3 <3 <5 <2 <2 < 13 <2 01/31/11 03/01/11 <3 <1 <3 <2 <4 <3 <3 <4 <3 <3 <9 <2 03/01/11 03/29/11 <2 <2 <2 <2 <6 <4 <2 <4 <3 <3 <9 <.2 03/29/11 05/03/11 <3 <2 <5 <2 <5 <4 <3 < 10 <3 <3 < 22 <5 05/03/11 05/31/11 <3 <2 <5 <2 <5 <5 <2 <4 <3 <2 < 12 <2 05/31/11 06/27/11 <2 <2 <5 <2 <4 <4 <3 <6 <3 <3 < 13 <2 06/27/11 08/02/11 <2 <2 <6 <1 <3 <2 <2 <8 <2 <1 < 14 <3 08/02/11 08/29/11 <2 <2 <3 <1 <5 <2 <2 <2 <3 <3 < 10 <2 08/29/11 09/27/11 <3 <2 <5 <2 <3 <4 <2 <3 <2 <3 < 14 <3 09/27/11 - 11/01/11 <4 <2 <5 <2 <3 <5 <3 <5 <2 <3 < 16 <3 11/01/11 - 11/29/11 <5 <5 <11 <5 <5 <6 <7 <7 <4 <3 < 23 <6 11/29/11 - 12/27/11 <3 <2 <5 <1 <4 <4 <3 <3 <3 <3 <9 <2 MEAN D-2

TABLE D-1.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION 11S2 PERIOD l0/U3/11 - U1/1U/11 42 +/- b 01/10/11 - 01/17/11 21 +/- 4 01/17/11 01/24/11 25 +/- 4

'01/24/11 - 01/31/11 29 +/- 4 01/31/11 - 02/07/11 20 +/- 4 02/07/11 - 02/14/11 22 +/- 4 02/14/11 - 02/21/11 21 +/- 4 02/21/11 - 02/28/11 18 +/- 4 02/28/11 - 03/07/11 17 +/- 4 03/07/11 - 03/14/11 15 +/- 4 03/14/11 - 03/22/11 17 +/- 3

'03/22/11 - 03/28/11 37 +/- 5 103/28/11 04/04/11 40 +/- 5

'!04/04/11 - 04/11/11 22 +/- 4

'04/11/11 - 04/18/11 16 +/- 4 04/18/11 - 04/25/11 14 +/- 4 04/25/11 - 05/02/11 17 +/- 4 05/02/11 - 05/09/11 13 +/- 4 05/09/11 - 05/16/11 11 +/- 3 05/16/11 - 05/23/11 9 +/- 3 05/23/11 - 05/31/11 20 +/- 4 05/31/11 - 06/06/11 19 +/- 5 06/06/11 - 06/13/11 29 +/- 4 06/13111 - 06/20/11 23 +/- 4 06/20/11 - 06/27/11 18 +/- 4 06/27/11 - 07/05/11 24 +/- 4 07/05/11 - 07/11/11 30 +/- 5 07/11/11 - 07/18/11 12 +/- 5 07/18/11 - 07/25/11 (1) 07/25/11 - 08/01/11 26 +/- 5 08/01/11 - 08/08/11 25 +/- 4 08/08/11 - 08/15/11 23 +/- 4 08/15/11 - 08/22/11 23 +/- 4 08/22/11 - 08/29/11 12 +/- 4 08/29/11 - 09/05/11 26 +/- 4 09/05/11 - 09/12/11 12 +/- 4 09/12/11 - 09/19/11 30 +/- 4 09/19/11 - 09/26/11 14 +/- 4 09/26/11 - 10/03/11 10 +/- 3 10/03/11 10/11/11 35 +/- 4 10/11/11 10/17/11 18 +/- 4

,110/17/11 10/24/11 18 +/- 4 10/24/11 - 10/31/11 24 +/- 4 10131111 - 11/07111 25 +/- 4 11/07/11 11/14/11 32 +/- 5 11/14/11 11/21/11 25 +/- 4 11/21/11 11/28/11 25 +/- 4 11/28/111 12/05/11 21 +/- 4 12/05/11 - 12/12111 23 +/- 4 12/12/11 12/19/11 42 +/- 5 12/19/11 12/27/11 26 +/- 4 12/27/11 - 01/03/12 17 +/- 4 MEAN 22 +/- 16 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION D-3

TABLE D-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 PERIOD 11S2 01/03/11 - 03/28/11 85 + 15 < 0.7

0.8 < 1.1 <1.1 < 1.2 03/28/11 - 06/27/11 81 + 16 < 0.4 < 0.7

0.5 < 0.9 < 0.8 06/27/11 - 10/03/11 67 + 13 < 0.6 < 0.8 < 0.8 < 0.5 < 0.5 10/03/11 - 01/03/12 63 + 13

0.5 < 1.0 < 0.6 < 1.0 < 0.5 MEAN 74 +/- 21 D-4

TABLE D-Ill.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION 1-131 K-40 Cs- 134 Cs-137 Ba-140 La-140 PERIOD 19B1 01/11/11 < 0.16 1228 +/- 110 < 3.0 < 2.8 < 12.7 < 2.0 04/05/11 < 0.5 1301 +/- 105 < 3.1 < 1.7 < 20.6 < 3.4 07/12/11 < 0.36 1346 +/- 103 < 3.0 < 2.1 < 22.1 < 3.7 10/04/11 < 0.2 1452 +/- 118 < 2.1 < 3.3 < 18.4 < 2.3 MEAN 1332 +/- 188 10F4 011/11/11 < 0.15 1462 +/- 109 < 2.6

2.9 < 14.9 < 1.9 04/05/11 < 0.2 1383 +/- 119 < 3.6 < 3.5 < 13.6 < 2.2 07/12/11 < 0.27 834 +/- 92 < 3.7 < 3.6 < 20.4 < 3.3 10/04/11 < 0.14 654 +/- 82 < 2.1 < 3.4 < 13.9 < 4.0 MEAN 1083 +/- 800 25C1 01/11/11 < 0.18 1264 +/- 107 < 3.4 < 3.6 < 15.9 < 1.8 04/05/11 < 0.26 1366 +/- 108 < 2.7 < 3.6 < 27 <4 07/12/11 < 0.17 1478 +/- 112 < 2.5 < 2.8 < 21.7 < 3.4 10/04/11 < 0.36 1348 +/- 104 < 2.1 < 2.7 < 17.8 < 2.9 MEAN 1364 +/- 176 D-5

D-6 FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENV AND TBE, 2011 10 9 . ............. - -- ENV ....................................................................

87. . ..--- T BE '....................................................................

6 ....................... *............---.. ...... *..... ....... ... J......................................... ..........

6

.3 5 --- -- ... ..... ........................

4.-.--.- ------- "" * '

. -- - - -- - - - -- - - -- - - - A 3 . ...... -.. .............................................................. .............

0.

0 I I I I a I I a Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH

FIGURE D-2 COMPARISON OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11Sl AND 11S2, 2011 50

--- 11S2-ENV I11SI -TBE E 40 40 .. ................... .......................... .................. .... ......... ....... .... ..

CE 2 0 4.. -. --.. - ----........... ..... ... ..... . . . . .

10 -- - - - - - - - - ----------------------- ............ ..........

A AA 0" : "I

o....

1.,.:- A N ':. , " "

..... I , .. . . . . . .. . . . . . . . . * . . . . . I*.. . . . .

0 l I 11I

~ I l 1I * ~ lI' I I I II I* I I l' I I 1I I I I I~I I I I II I 1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.

D-9

Intentionally Left Blank APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

March 2011 E7460-396 Milk Sr-89 pCi/L 98.8 97.4 1.01 A Sr-90 pCi/L 15.2 15.8 0.96 A E7461-396 Milk 1-131 pCi/L 92.9 96.9 0.96 A Ce-141 pCi/L not provided by Analytics for this study Cr-51 pCi/L 398 298 1.34 N (1)

Cs-1 34 pCi/L 130 130 1.00 A Cs-1 37 pCi/L 232 205 1.13 A Co-58 pCi/L 121 113 1.07 A Mn-54 pCi/L 289 266 1.09 A Fe-59 pCi/L 201 175 1.15 A Zn-65 pCi/L 287 261 1.10 A Co-60 pCi/L 186 172 1.08 A E7463-396 AP Ce-141 pCi not provided by Analytics for this study Cr-51 pCi 243 215 1.13 A Cs-1 34 pCi 85.0 94.2 0.90 A Cs-1 37 pCi 168 148 1.14 A Co-58 pCi 89.2 81.8 1.09 A Mn-54 pCi 171 192 0.89 A Fe-59 pCi 129 126 1.02 A Zn-65 pCi 159 189 0.84 A Co-60 pCi 132 124 1.06 A E7462-396 Charcoal 1-131 pCi 96.5 96.3 1.00 A June 2011 E7851-396 Milk Sr-89 pCi/L 96.7 103 0.94 A Sr-90 pCi/L 13.8 15.6 0.88 A E7852-396 Milk 1-131 pCi/L 110 103.0 1.07 A Ce-141 pCi/L 68.1 79.9 0.85 A Cr-51 pCi/L 186 206 0.90 A Cs-1 34 pCi/L 164 190 0.86 A Cs-1 37 pCi/L 140 138 1.01 A Co-58 pCi/L 141 152 0.93 A Mn-54 pCi/L 136 138 0.99 A Fe-59 pCi/L 128 123 1.04 A Zn-65 pCi/L 263 261 1.01 A Co-60 pCi/L 189 195 0.97 A E7854-396 AP Ce-141 pCi 49.9 42.9 1.16 A Cr-51 pCi 95.6 110 0.87 A Cs- 134 pCi 104 102 1.02 A Cs-1 37 pCi 83.8 74.0 1.13 A Co-58 pCi 90.7 81.3 1.12 'A Mn-54 pCi 74.5 73.9 1.01 A Fe-59 pCi 62.0 66.1 0.94 A Zn-65 pCi 140 140 1.00 A Co-60 pCi 119 104 1.14 A E7853-396 Charcoal 1-131 pCi 76.2 86.1 0.89 A E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 3)

Identification Reported Known Ratio (c),

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

September2011 E8070-396 Milk Sr-89 pCi/L 102 90.8 1.12 Sr-90 pCi/L 13.2 14.7 0.90 E8071-396 Milk 1-131 pCi/L 74.2 89.2 0.83 Ce-141 pCi/L 66.9 66.7 1.00 Cr-51 pCi/L 249 226 1.10 Cs- 134 pCi/L 116 128 0.91 Cs-137 pCi/L 106 114 0.93 Co-58 pCi/L 95.4 97.5 0.98 Mn-54 pCi/L 147 151 0.97 Fe-59 pCi/L 53.1 54.8 0.97 Zn-65 pCi/L 175 180 0.97 Co-60 pCi/L 150 157 0.96 E8073-396 AP Ce-141 pCi 66.6 67.5 0.99 Cr-51 pCi 263 229 1.15 Cs-1 34 pCi 139 130 1.07 Cs-1 37 pCi 110 115 0.96 Co-58 pCi 108 98.6 1.10 Mn-54 pCi 152 153 0.99 Fe-59 pCi 57.5 55.5 1.04 Zn-65 pCi 190 183 1.04 Co-60 pCi 156 159 0.98 E8072-396 Charcoal 1-131 pCi 77.6 80.6 0.96 December, 2011 E8230-396 Milk Sr-89 pCi/L 93.3 93.1 1.00 A Sr-90 pCi/L 12.7 15.4 0.82 A E8231-396 Milk 1-131 pCi/L 82.5 90.2 0.91 A Ce-141 pCi/L not provided by Analytics for this study Cr-51 pCi/L 465 566 0.82 A Cs- 134 pCi/L 142 171 0.83 A Cs-1 37 pCi/L 185 210 0.88 A Co-58 pCi/L 177 221 0.80 A Mn-54 pCi/L 208 241 0.86 A Fe-59 pCi/L 164 183 0.90 A Zn-65 pCi/L 259 291 0.89 A Co-60 pCi/L 224 270 0.83 A E8233-396 AP Ce-141 pCi not provided by Analytics for this study Cr-51 pCi 344 368 0.93 A Cs-1 34 pCi 105 111 0.95 Cs-137 pCi 129 137 0.94 A Co-58 pCi 145 144 1.01 A Mn-54 pCi 137 157 0.87 A Fe-59 pCi 119 119 1.00 A Zn-65 pCi 145 190 0.76 W Co-60 pCi 168 176 0.95 A E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

December 2011 E8232-396 Charcoal 1-131 pCi 100 89.5 1.12 A (1) Sample appearsto be biased high. CorrectiveAction evaluated after the 2nd QuarterAnalytics PE sample; no action required. NCR 11-13 (a) Teledyne Brown Engineeringreportedresult.

(b) The Analytics known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.

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

(d) Analytics evaluation based on TBE internalQC limits: A= Acceptable. Reported result falls within ratio limits of O.80-1.20.

W-Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30. N =NotAcceptable. 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, 2011 (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)

May 2011 RAD-85 Water Sr-89 pCi/L 59.8 63.2 51.1-71.2 A Sr-90 pCi/L 42.5 42.5 31.3 -48.8 A Ba-1 33 pCi/L 73.3 75.3 63.0 - 82.8 A Cs-1 34 pCi/L 64.9 72.9 59.5 - 80.2 A Cs-1 37 pCi/L 74.6 77.0 69.3 - 87.4 A Co-60 pCi/L 87.8 88.8 79.9 - 100 A Zn-65 pCi/L 103 98.9 89.0-118 A Gr-A pCi/L 64.1 50.1 26.1 - 62.9 N (i)

Gr-B pCi/L 51.8 49.8 33.8 - 56.9 A 1-131 pCi/L 27.4 27.5 22.9 - 32.3 A U-Nat pCi/L 38.5 39.8 32.2 -44.4 A H-3 pCi/L 10057 10200 8870-11200 A MRAD-14 Filter Gr-A pCi/filter 79.7 74.3 38.5-112 A November 2011 RAD-87 Water Sr-89 pCi/L 81.0 69.7 56.9 - 77.9 N (2)

Sr-90 pCi/L 35.5 41.4 30.2 - 47.2 A Ba-133 pCi/L 90.7 96.9 81.8- 106 A Cs-1 34 pCi/L 36.6 33.4 26.3 - 36.7 A Cs-1 37 pCi/L 44.7 44.3 39.4-51.7 A Co-60 pCi/L 118.7 119 107-133 A Zn-65 pCi/L 80.2 76.8 68.9 - 92.5 A Gr-A pCi/L 34.2 53.2 27.8- 66.6 A Gr-B pCi/L 39.3 45.9 30.9 - 53.1 A 1-131 pCi/L 22.9 27.5 22.9 - 32.3 A U-Nat pCi/L 46.8 48.6 39.4 - 54.0 A H-3 pCi/L 15733 17400 15200 - 19100 A MRAD-1 5 Filter Gr-A pCi/filter 44.6 58.4 30.3 - 87.8 A (1) The solids on the planchet exceeded 100 mg, which was beyond the range of the efficiency curve. NCR 11-08 (2) Sr-89 TBE to known ratio of 116 fell within acceptablerange of+/-20%. No action required. NCR 11-16 (a) Teledyne Brown Engineering reportedresult.

(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made duringstandardpreparation.

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

E-4

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

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 2)

M Identification Reported Known Acceptance Month/ear Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

March 2011 11 -MaW24 Water Cs-1 34 Bq/L 19.1 21.5 15.1 -28.0 A Cs-1 37 Bq/L 29.0 29.4 20.6 - 38.2 A Co-57 Bq/L 0.139 (1) A Co-60 Bq/L 23.9 24.6 17.2 - 32.0 A H-3 Bq/L 265 243 170-316 A Mn-54 Bq/L 31.8 31.6 22.1 -41.1 A K-40 Bq/L 94.8 91 64 - 118 A Sr-90 Bq/L 9.64 8.72 6.10- 11.34 A Zn-65 Bq/L -0.142 (1) A 11-GrW24 Water Gr-A Bq/L 0.767 1.136 0.341 - 1.931 A Gr-B Bq/L 3.43 2.96 1.48 -4.44 A 11-MaS24 Soil Cs-1 34 Bq/kg 612 680 476- 884 A Cs-1 37 Bq/kg 772 758 531 - 985 A Co-57 Bq/kg 910 927 649 - 1205 A Co-60 Bq/kg 500 482 337 - 627 A Mn-54 Bq/kg 0.607 (1) A K-40 Bq/kg 569 540 378-702 A Sr-90 Bq/kg NR 160 112 -208 N (2)

Zn-65 Bq/kg 1497 1359 951 -1767 A 11-RdF24 AP Cs-134 Bq/sample '3.26 3.49 2.44 -4.54 A Cs-1 37 Bq/sample 2.36 2.28 1.60-2.96 A Co-57 Bq/sample 3.30 3.33 2.33 - 4.33 A Co-60 Bq/sample 0.0765 (1) A Mn-54 Bq/sample 2.84 2.64 1.85 - 3.43 A Sr-90 Bq/sample NR 1.36 0.95 - 1.77 N (2)

Zn-65 Bq/sample 3.30 3.18 2.23 -4.13 A 11-GrF24 AP Gr-A Bq/sample 0.101 0.659 0.198- 1.120 N (3)

Gr-B Bq/sample 1.23 1.323 0.662 - 1.985 A 11-RdV24 Vegetation Cs-134 Bq/sample 4.97 5.50 3.85-7.15 A Cs-137 Bq/sample 0.0356 (1) A Co-57 Bq/sample 10.8 9.94 6.96 - 12.92 A Co-60 Bq/sample 4.89 .4.91 3.44 - 6.38 A Mn-54 Bq/sample 6.42 6.40 4.48 - 8.32 A Sr-90 Bq/sample NR 2.46 1.72 - 3.20 N (2)

Zn-65 Bq/sample 3.07 2.99 2.09 - 3.89 A September2011 11-MaW25 Water Cs-134 Bq/L 16.0 19.1 13.4 - 24.8 A Cs-1 37 Bq/L 0.0043 (1) A Co-57 Bq/L 33.1 36.6 25.6 - 47.6 A Co-60 Bq/L 26.9 29.3 20.5 - 38.1 A H-3 Bq/L 1011 1014 710- 1318 A Mn-54 Bq/L 23.2 25.0 17.5 - 32.5 A K-40 Bq/L 147 156 109 - 203 A Sr-90 Bq/L 15.8 14.2 9.9 - 18.5 A Zn-65 Bq/L 27.3 28.5 20.0 - 37.1 A E-5

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

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

September 2011 11-GrW25 Water Gr-A Bq/L 0.894 0.866 0.260 - 1.472 A Gr-B Bq/L 5.87 4.81 2.41 - 7.22 A 11-MaS25 Soil Cs-134 Bq/kg -0.213 (1) A Cs-137 Bq/kg 1110 979 685-1273 A Co-57 Bq/kg 1290 1180 826-1534 A Co-60 Bq/kg 731 644 451 -837 A Mn-54 Bq/kg 987 848 594-1102 A K-40 Bq/kg 753 *625 438-813 W Sr-90 Bq/kg 276 320 224-416 A Zn-65 Bq/kg 1870 1560 1092-2028 A September 2011 11-RdF25 AP Cs-134 Bq/sample -0.043 (1) A Cs-1 37 Bq/sample 3.09 2.60 1.82 - 3.38 A Co-57 Bq/sample 5.36 5.09 3.56 - 6.62 A Co-60 Bq/sample 3.41 3.20 2.24 -4.16 A Mn-54 Bq/sample 0.067 (1) A Sr-90 Bq/sample 1.84 1.67 1.17-2.17 A zn-65 Bq/sample 5.17 4.11 2.88- 5.34 W 11-GrF25 AO Gr-A Bq/sample 0.0058 (1) A Gr-B Bq/sample -0.01 (1) A 11-RdV25 Vegetation Cs-1 34 Bq/sample 0.0081 (1) A Cs- 137 Bq/sample 4.94 4.71 3.30 -6.12 A Co-57 Bq/sample 0.0639 (1) A Co-60 Bq/sample 3.36 3.38 2.37 - 4.39 A Mn-54 Bq/sample 5.89 5.71 4.00 - 7.42 A Sr-90 Bq/sample 1.31 1.26 0.88 - 1.64 A Zn-65 Bq/sample 6.54 6.39 4.47 - 8.31 A (1) Falsepositive test (2) Evaluated as failed due to not reporting a previously reportedanalyte. NCR 11-11 (3) The filter for GrossAlpha was counted on the wrong side. Recounted on the correct side resultedin acceptableresults. NCR 11-11 (a) Teledyne Brown Engineering reportedresult.

(b) The MAPEP known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.

E-6

TABLE E-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa ENVIRONMENTAL, INC., 2011 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date.. Analysis Laboratory ERA Control

.. Result b Result c Limits Acceptance STW-1243 04/04/11 Sr-89 68.2 +/- 5.8 63.2 51.1 -71.2 Pass STW-1 243 04/04/11 Sr-90 44.3 +/- 2.4 42.5 31.3 -48.8 Pass STW-1244 04/04/11 Ba-133 69.8 +/- 3.9 75.3 63.0 - 82.8 Pass STW-1244 04/04/11 Co-60 87.9 +/- 3.8 88.8 79.9 - 100.0 Pass STW-1 214 04/04/11 Cs- 134 69.5 +/- 3.7 72.9 59.5 - 80.2 Pass STW- 1214 04/04/11 Cs-137 77.9 +/- 5.3 77.0 69.3 - 87.4 Pass STW-1 244 04/04/11 Zn-65 105.2 +/- 8.4 98&9 89.0 -118.0 Pass STW-1 245 04/04/11 Gr. Alpha 41.5 +/- 2.3 50.1 26.1 -62.9 Pass STW-1245 04/04/11 Gr. Beta 48.9 +/- 1.8 49.8 33.8 - 56.9 Pass STW-1246 04/04/11 1-131 26.6 +/- 1.7 27.5 22.9 - 32.3 Pass STW-1248 04/04/11 H-3 10322 +/-285 10200.0 8870 -11200 Pass STW-1256 10/07/11 Sr-89 68.7 +/- 6.0 69.7 56.9 - 77.9 Pass STW-1256 10/07/11 Sr-90 36.9 +/- 2.4 41.1 30.2 -47.2 Pass STW-1 257 10/07/11 Ba-133 88.2 +/- 7.8 96.9 81.8 -106.0 Pass STW-1 257 10/07/11 Co-60 116.5 +/-7.1 119.0 107.0 - 133.0 Pass d

STW-1257 10/07/11 Cs- 134 38.8 +/- 8.0 33.4 26.3 - 36.7 Fail STW-1257 10/07/11 Cs-137 45.6 +/- 7.3 44.3 39.4 -51.7 Pass STW-1 257 .10/07/11 Zn-65 84.9 +/- 15.4 76.8 68.9 - 92.5 Pass STW-1258 10/07/11 Gr. Alpha 35.7 +/- 3.8 53.2 27.8 - 66.6 Pass STW-1258 10/07/11 Gr. Beta 36.1 +/- 3.3 45.9 30.9 - 53.1 Pass STW-1259 10/07/11 1-131 25.0 +/- 1.1 27.5 22.9 - 32.3 Pass STW-1261 10/07/11 H-3 17435 +/- 382 17400 15200 -19100 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 The sample was reanalyzed. Result of reanalysis was acceptable, 32.9 +/- 7.4 pCi/L.

E-7

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEPr ENVIRONMENTAL, INC., 2011

.(Page, 1 of 2)

Concentration b Lab Code c Date Analysis Laboratory result Activity Limits d'! Acceptance STW-1237 02/01/11 Co-57 <0.2 0.00 Pass STW-1237 02/01/11 Co-60 24.10 +/- 0.40 24.60 17.20 -32.00 Pass STW-1237 02/01/11 Cs- 134 19.80 +/- 0.40 21.50 15.10 -28.00 Pass STW-1237 02/01/11 Cs-137 29.40 +/- 0.50 29.40 20.60 -38.20 Pass STW-1237 02/01/11 H-3 238.90 +/- 8.80 243.00 170.00 -316.00 Pass STW-1237 02/01/11 K-40 95.40 +/- 3.10 91.00 64.00 -118.00 Pass STW-1237 02/01/11 Mn-54 32.50 +/- 0.60 31.60 22.10 -41.10 Pass STW-1237 02/01/11 Sr-90 8.70 +/- 0.70 8.72 6.10 -11.34 Pass STW-1237 02/01/11 Zn-65 < 0.5 0.00 Pass STW-1238 02/01/11 Gr. Alpha 0.82 +/- 0.07 1.14 0.34 -1.93 Pass STW-1238 02/01/11 Gr. Beta 2.82 +/- 0.07 2.96 1.48 -4.44 Pass STVE-1 239 02/01/11 Co-57 11.27 +/- 0.21 9.94 6.96 -12.92 Pass STVE-1239 02/01/11 Co-60 4.95 +/- 0.16 4.91 3.44 - 6.38 Pass STVE-1239 02/01/11 Cs- 134 5.18 +/- 0.19 5.50 3.85 -7.15 Pass STVE-1239 02/01/11 Cs-137 < 0.09 0.00 Pass STVE-1239 02/01/11 Mn-54 6.91 +/- 0.25 6.40 4.48 - 8.32 Pass STVE-1239 02/01/1.1 Zn-65 3.10 +/- 0.32 2.99 2.09 - 3.89 Pass STSO-1240 02/01/11 Co-57 984.10 +/- 4.10 927.00 649.00 -1205.00 *Pass STSO-1240 02/01/11 Co-60 540.70 +/- 3.00 482.00 337.00 -627.00 Pass STSO-1240 02/01/1-1 Cs-1 34 726.70 +/- 5.92 680.00 476.00 -884.00 Pass STSO-1240 02/01/11 Cs-1 37 883.10 +/-4.70 758.00 531.00 -985.00 Pass STSO-1240 02/01/11 , K-40 622.70 +/- 16.70 540.00 378.00 -702.00 Pass ST-SO-1240 02/01/11 Mn-54 -0.30 +/- 1.00. 0.00 Pass STSO-1240 02/01/11 Zn-65 1671.00 +/- 13.10 1359.00 951.00 -1767.00 Pass STAP-1241 02/01/11 Co-57 3.48 +/- 0.06 3.33 2.33 - 4.33 Pass STAP-1241 02/01/11 Co-60 0.00 +/- 0.02 0.00 -0.10 -0.10 Pass STAP-1241 02/01/11 Cs-134 3.44 +/- 0.27 3.49 2.44 -4.54 Pass STAP-1241 02/01/11 Cs-137 2.46 +/- 0.27 2.28 1.60 -2.96 Pass STAP-1241 02/01/11 Gr. Alpha 0.39 +/- 0.05 0.66 0.20 -1.12 Pass STAP-1241 02/01/11 Gr. Beta 1.54 +/- 0.07 1.32 0.66 -1.99 Pass STAP-1241 02/01/11 Mn-54 2.90 +/- 0.10 2.64 1.85 - 3.43 Pass STAP-1241 e 02/01/11 Sr-90 1.89 +/- 0.15 1.36 0.95 -1.77 Fail STAP-1241 02/01/11 Zn-65 3.80 +/- 0.18 3.18 2.23 -4.13 Pass STVE-1250 08/01/11 Co-57 0.01 +/- 0.02 0.00 Pass STVE-1250 08/01/11 Co-60 3.57 +/- 0.13 3.38 2.37 -4.39 Pass STVE-1250 08/01/11 Cs-134 -0.02 +/- 0.04 0.00 -0.10 -0.10 Pass STVE-1250 08/01/11 Cs-1 37 5.28 +/- 0.20 4.71 3.30 -6.12 Pass STVE-1250 08/01/11 Mn-54 6.48 +/- 0.22 5.71 4.00 - 7.42 Pass STVE-1250 08/01/11 Zn-65 7.35 +/- 0.34 6.39 4.47 - 8.31 Pass E-8

TABLEEE-5 "" DOE'SMIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEPr ENVIRONMENTAL, INC., 2011 (Page 2 of 2) b Concentration Known Control Lab Code c Date' Analysis Laboratory result Activity Limits d Acceptance STSO-1251 08/01/11 Co-57 1333.90 +/- 4.20 1180.00 826.00 - 1534.00 Pass STSO-1251 08/01/11 Co-60 701.30 +/- 3.40 644.00 451.00 -837.00 Pass STSO-1251 08/01/11 Cs-134 0.71 +/- 1.05 0.00 Pass STSO-1251 08/01/11 Cs-137 1106.00 +/- 5.60 979.00 685.00 -1273.00 Pass STSO-1251 08/01/11 K-40 749.20 +/- 19.00 625.00 438.00 -813.00 Pass STSO-1251 08/01/11 Mn-54 984.30 +/- 5.40 848.00 594.00 -1102.00 Pass STSO-1251 f 08/01/11 Sr-90 219.40 +/- 16.70 320.00 224.00 -416.00 Fail STSO-1251 08/01/11 Zn-65 1639.90 +/- 11.40 1560.00 1092.00 -2028.00 Pass STAP-1252 08/01/11 Co-57 5.06 +/- 0.08 5.09 3.56 -6.62 Pass STAP-1252 08/01/11 Co-60 3.13 +/- 0.09 3.20 2.24 -4.16 Pass STAP-1252 08/01/11 Cs-134 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1 252 08/01/11 Cs-137 2.61 +/- 0.09 2.60 1.82 -3.38 Pass STAP-1 252 08/01/11 Mn-54 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1252 08/01/11 Sr-90 1.65 +/- 0.16 1.67 1.17 -2.17 Pass -

STAP-1252 08/01/11 Zn-65 4.46 +/- 0.23 4.11 2.88 -5.34 Pass STW-1254 08/01/11 Co-57 37.20 +/- 0.50 36.60 25.60 -47.60 Pass STW-1254 08/01/11 Co-60 28.80 +/- 0.40 29.30 20.50 -38.10 Pass' STW-1254 08/01/11 Cs-134 18.00 +/- 0.60 19.10 13.40 -24.80 Pass STW-1254 08/01/11 Cs-137 0.06 +/- 0.13 0.00 Pass STW-1254 08/01/11 H-3 1039.90 +/- 17.90 1014.00 710.00 -1318.00 Pass STW-1254 .08/01/11 K-40 161.40 +/- 4.10 156.00 .109.00 -203.00 Pass' STW-1254 08/01/11 Mn-54 25.70 +/- 0.50 25.00 17.50 -32.50 Pass STW-1254 08/01/11 Sr-90 15.60 +/-1.80 14.20 9.90 18:50 Pass STW-1254 08/01/11 Zn-65 30.20 +/- 0.90 28.50 20.00 -37.10 Pass STW-1 255 08/01/11 Gr. Alpha 0.72 +/- 0.12 0.87 0.26-1.47 Pass STW-1 255 08/01/11 Gr. Beta 4.71 +/- 0.15 4.81 2.41 -7.22 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's MixedAnalyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d 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. '

e No errors found in calculation or procedure, results of reanalysis; 1.73 Bq/filter.

f The analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bq/kg.

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 2011 Prepared By Teledyne Brown Engineering Environmental Services ExelOn" Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2012

Table Of Contents I. Sum m ary and Conclusions ................................................................................................ 1 II. Introduction ......................................................................................................................... 2 A. O bjectives of the RG PP ................................................................................... 2 B. Im plem entation of the O bjectives ..................................................................... 3 C . Program Description ......................................................................................... 3 D. Characteristics of Tritium (H-3) ....................................................................... 4 I1l. Program Description ................................................................................................... 5 A. Sam ple Analysis ................................................................................................ 5 B. Data Interpretation ........................................................................................... 5 C . Background Analysis ......................................................................................... 6

1. Background Concentrations of Tritium .................................................. 7 IV, Results and Discussion . ........... ........ 99..................

A. Groundwater Results ....................................... 9....

B. Surface Water Results ................................................................................... 10 C. Precipitation Water Results .................................. 11 D. Drinking W ater W ell Survey .......................................................................... 11 E. Summary of Results - Inter-laboratory Comparison Program ........................ 11 F. Leaks, Spills, and Releases ............................................................................. 11 G . Trends .......................................................................... 12 H. Investigations .................................................................................................... 12 I. Actions Taken .................................................................................................. 12 V. References ...................................................................................................................... 12 p

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 20:11 Figures Figure 1 Routine Well Water, Surface Water and Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 20111 Appendix B Data Tables Tables Table B-I.1 .Concentrations of Tritium, Strontium-90, Gross Alpha and Gross Beta in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2011.

Table B-I.22 Concentrations of Gamma Emitters. in Well Water Samples Collected

.as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2011.

Table B-Il. 1 Concentrations of Tritium and Strontium-90 in Surface Water Samples SCollected as Part of the Radiological:Groundwater Protection Program, LimerickGenerating Station, 2011.

Table B-Il. 2 Concentrations of Gamma Emitters in Surface Water, Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2011.

Table B-Ill .1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2011.

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 2011 through 31 December 2011. During that time period, 384 analyses were performed on 132 samples from 1.2 groundwater, 7 surface water, and 4 precipitation water locations collected from the environment, both on and off station property in 2011.

There were no spills that could affect the ground water monitoring program in 2011.

Tritium was .not detected in any of the groundwater, surface water, or precipitation 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 two of the 12 groundwater monitoring locations and one of seven surface water locations. The tritium concentrations ranged from 177 to 1,154 pCi/L for groundwater and 236 to 1607 pCi/L for surface water.

Strontium-90 was not detected and met the required LLD groundwaterand surface water samples.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions performed on groundwater water samples throughout 2011. Gross Alpha (dissolved) was detected-at 5 of .12 groundwater locations. The concentrations ranged from 1.2 to 2.7 pCi/L. Gross Alpha (suspended) was detected at 4 of 12 groundwater.locations,, The concentrations, ranged from 1.3 to.82.8 pCi/L. Gross Beta (dissolved) was detected at 12 of 12 groundwater water locations. The concentrations ranged from 2.0 to 31.2 pCi/L. Gross Beta (suspended) was detected at 8 of 12 groundwater locations. The concentrations ranged from 1.6 to 407 pCi/L.

Naturally occurring K-40 was detected in one sample. All other gamma-emitting radionuclides associated with licensed plant operations met the required LLDs.

Tritium in precipitation samples associated with the recapture of Limerick gaseous tritium releases met the LLD.

Hard-To-Detect analyses were not performed in 2011.

Although no drinking water pathway is available from groundwater, the dose via the drinking water pathway was calculated at 0.07 mrem to a child (total body),

which was 1.14% of the 10 CFR 50, Appendix I dose limit.

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 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 boundary.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2011.

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 theRGPP 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.

/ 2

B. Implementation of the Objectives.

The objectives identified have been implemented at Limerick Generating Station as discussed below: .

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

2. 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 implemented new 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 2011. Sample locations can be found in Table A-I, Appendix A.

1. Sample Collection Groundwater, Surface Water, and Precipitation Water Samples of groundwater, surface water, and precipitation 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.

3

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 was received.

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

-hydrogeologic conditions.

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. th'e 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. Tritiated water, like normal 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 (He-3). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk fromrexposure to tritium. Tritium is one of the 4

least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to

-these tissues is generally uniform and is dependent on the water content of the specific tissue.

Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Limerick Generating Station RGPP in 2011.

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-90 in groundwater.and surface water.

B. Data Interpretation The radiological data collected prior to Limerick Generating Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Limerick Generating Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of-falsely concluding that'a blank observation represents a "real" signal. The LLD is intended as a before the fact 5

estimate of a system (including instrumentation, procedure and sample type) and not asan after the fact criterion for the presence of activity. All analyses are designed to achieve the required LGS detection capabilities for environmental sample analysis.

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

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

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

Exelon reports the.TPU by following the result with plus or minus +

the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.

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.

6

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 was radioactively decaying as predicted.

Gamma isotopic results from the preoperational program were all less than or at the minimum detectable concentration (MDC) level.

1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. Additional detail may be found by consulting references.

a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e.; man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle., Below ground, 'lithogenic" tritium- is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium-and thorium.; Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic Source of tritium and strontium-90 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.

7

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 world wide since 1960: RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. Based on GNIP data for sample stations located in the U.S., tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with theatmospheric 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 Smay 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 -

8

240 pCi/L or 140 +/- 100 pCi/L. At this concentration, these sample results cannot be distinguished as different from background.

IV. Results and Discussion-.

Gamma spectroscopy results for groundwater and surface water sample were reported for fourteen 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.

Tritium Samples from twelve locations were analyzed for tritium activity (Table B-1.1, Appendix B). Tritium values ranged from non detectable to 1,154 pCi/L. Well MW-LR-9 had the highest'value of 1,154 pCi/L. The activity in this well is from a 2009 leak to:ground. Although no drinking water pathway is available from groundwater, the theoretical dose via the drinking water pathway was calculated at 0.07 mrem to a child (total body), which represents 1.14% of the 10 CFR 50, Appendix I dose limit of 6 mrem.

Strontium All Sr-90 analysesmet the required LLD (Table B-I.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 throughout the sampling year.

Gross Alpha (dissolved) was detected at 5 of 12 groundwater locations.

The concentrations ranged from 1.2 to 2.7 pCi/L. Gross Alpha (suspended) was detected at 4 of 12 groundwater locations. The concentrations ranged from 1.3 to 82.8 pCi/L. Gross Beta (dissolved) was detected at 12 of 12 groundwater water locations. The concentrations ranged from 2.0 to 31.2 pCi/L. Gross Beta (suspended) was detected at 8 of 12 groundwater locations. The concentrations ranged from 1.6 to 407 9

pCi/L (Table B-1.1, Appendix B).

Gamma Emitters Potassium-40 was detected at one of 12 groundwater locations at a concentration of 81 pCi/L. All other gamma emitting nuclides met their respective LLDs (Table B-1.2, Appendix B).

Hard-To-Detect Hard-To-Detect analyses were performed in 2011.

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 seven locations were analyzed for tritium activity. Tritium activity was detected in station SW-LR-8. The concentrations ranged from 236 to 1,607 pCi/Liter (Table B-11.1, Appendix B).

Strontium All Sr-90 analyses met the required LLD (Table B-11.1, Appendix B).

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses were not performed on any surface water samples in 2011.

Gamma Emitters All gamma emitting nuclides met their respective LLDs (Table B-11.2, Appendix B).

10

C. Precipitation Water Results Tritium All tritium analyses met the required LLDs (Table B-Ill.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 blow ground surface (bgs),. and they yield between 8 and 100 gallons per minute (gpm). All wells are completed in the Brunswick Formation.

The Limerick Generating 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 welldepth 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.

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

F. Leaks, Spills, and Releases There were no spills to ground containing radioactive material in 2011.

t 11

However, the Power Block Foundation Sump, which collects groundwater around the reactor buildings, turbine building and rad waste building, had identified tritium in the first quarter sample and analysis of potentially contaminated systems (IR1200128). The activity was recorded as 21,000 pCi/L. The source of the tritium was determined to be from groundwater movement from the 2009 turbine building leak. Trending over a period of months showed that tritium activity returned to below the radioactive effluent control program's MDC of 3500 pCi/L.

G. Trends Tritium concentrations in well MW-LR-9 continue to decrease from the levels observed from the 2009 leak. The tritium levels at well MW-LR-8 have increased to the same levels of well MW-LR-9.

H. Investigations Conclusions from the Phase 1 report in 2006 have been made available to state and federal regulators and to the public. Currently no investigations are on going.

1. Actions Taken

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

2. Installation of Monitoring Wells No new wells have been installed in 2011

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

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2011 Location Type Distance MW-LR-1 Monitoring Well Onsite MW-LR-2 Monitoring Well Onsite MW-LR-3 Monitoring Well Onsite MW-LR-4 Monitoring Well Onsite MW-LR-5 Monitoring Well Onsite MW-LR-6 Monitoring Well Onsite MW-LR-7 Monitoring Well Onsite MW-LR-8 Monitoring Well Onsite MW-LR-9 Monitoring Well Onsite P11 Monitoring Well Onsite P14 Monitoring Well Onsite P16 Monitoring Well Onsite P17 Monitoring Well Onsite P3 Monitoring Well Onsite SP22 Monitoring Well Onsite SW-LR-2 Surface Water Offsite SW-LR-4 Surface Water Offsite SW-LR-6 Surface Water Offsite SW-LR-7 Surface Water Onsite SW-LR-8 (Hold Pond) Surface Water Onsite SW-LR-9 (Spray Pond) Surface Water Onsite SW-LR-10 Surface Water Onsite 36S3 Precipitation Water Onsite E-5 Precipitation Water Onsite ESE-6 Precipitation Water Onsite SE-7 Precipitation Water Onsite A-1

Figure 1 Routine Well Water, Surface Water and Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2011.

A-2

0 SW-LR-3 Figure 1 Routine Well Water, Surface Water and Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2011.

A-3

we ~ ~0NOFi SPupbw Sw~ipeLeadloI Predc~m SempleLfa~ni Figure 1 Routine Well Water, Surface Water and Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2011.

A-4

APPENDIX B DATA TABLES

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM-90, GROSS ALPHA, AND GROSS BETA INWELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER _+2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS) GR-A (SUS) GR-B3(DIS) GR-B3(SUIS)

,ýMW-LR-1 04/19/11 < 191 < 0.8 < 0.8 < 0.9 4.5 +/- 0.9 < 1.6 MW-LR-2 01/19/11 < 147 2.0 +/- 0.8 < 0.8 6.4 +/- 2.9 2.7 +/- 1.6

,MW-LR-2 04/19/11 < 192 < 0.8 1.5 +/- 0.7 < 0.9 3.7 +/- 0.9 < 1.6 MW-LR-2 07/19/11 < 172 < 1.3 < 0.8 2.0 +/- 1.1 1.6 +/- 1.0 MW-LR-2 11/15/111 < 169 < 0.8 < 0.6 4.4 +/- 1.1 <- 1.7 MW-LR-3 01/19/11 < 150 1.2 +/- 0.7 < 0.7 6.2 +/-12.9 < 2Z3 MW-LR-3 04/19/11 < 189 < 0.8 1.4 +/- 0.9 < 0.9 3.9 +/- 1.1 < 1.6 MW-LR-3 07/20/11 < 169 < 1.5 < 0.8 2.8 +/- 1.1 < 1.5 MW-LR-3 11/15/11 < 167 2.7 +/- 1.0 < 0.6 4.3 +/- 1.1 < 1.7 MW-LR-4 01/19/11 < 147 < 1.3 1.3 +0.8 7.5 +/- 3.5 < 2.4 MW-LR-4 04/19/11 < 190 < 0.8 < 1-9 < 0.9 5.2 +/- 1,3 < 1.6 MW-LR-4 07/20/11 < 170 < 2.2 < 0.8 5.0 +/- 1.3 < 1.5 MW-LR-4 11/15/11 < 169 < 1.3 < 0.6 5.6 +/- 1.2 < 1.7 MW-LR-5 01/19/11 < 155 < 4.2 < 2.1 23.5 +/- 10.2 < 3.5 MW-LR-5 04/19/11 < 189 < 0.7 < 0.8 < 0.9 5.0 +/- 1.0 < 1.6 MW-LR-5 07/19/11 < 171 < 1.6 < 0.4 5.8 +/- 1.2 1.6 +/- 0.9 MW-LR-5 11/15/111 < 190 1.7 +0.8 < 0.4 13.5 +/- 1.4 2.1 +/- 1.1 IIMW-LR-7 01/19/11 < 146 < 2.0 <0.9 5.3 +/- 2.3 3.7 +/- 1.7

'!MW-LR-7 04/19/11 < 190 < 0.8 < 0.6 < 0.5 3.8 +/- 0.8 < 1.5 MW-LR-7 07/19/11 < 169 < 0.9 < 0.4 2.9 +/- 0.9 < 1.3 MW-LR-7 11/15/11 < 170 < 0.5 < 0.4 4.1 +/- 0.9 < 1.6 MW-LR-8 01/19/11 TBE < 160 < 1.0 k* 0.7 5.0 +/- 3.2 2.4+ 1.6 MW-LR-8 01/19/11 TBE 181 +/- 105 1.9+/- 0.9 < 0.7 3.1 +/- 1.1 < 2.4 MW-LR-8 01/19/11 EIML 289 +/- 95 MW-LR-8 01119/11 EIML 211 +/- 86 MW-LR-8 04119/11 TBE < 188 < 0.9 < 1.7 < 0.5 2.2 +/- 1.2 < 1.5 MW-LR-8 04/19/11 TBE < 192 < 0.7 < 1.6 < 0.5 3.8:1:1.2 < 1.5 MW-LR-8 04/19/11 EIML 217 +/- 97 < 0.5 MW-LR-8 07/19/11 265 +/- 122 < 3.5 < 0.7 < 2.3 < 1.8 MW-LR-8 07/19111 296 +/- 120 < 2.4 < 0.4 2.3 t 1.2 < 1.3 MW-LR-8 07/19/11 EIML 211 +/- 86 MW-LR-8 11/16/11 TBE 278 +/- 130 < 1.6 < 0.8 3.8 +/- 1.2 < 1.5 MW-LR-8 11116/11 TBE 360 +/- 132 2.3 +/- 1.2 < 0.4 4.6 +/- 1.3 < 1.6 MW-LR-8 11/16/111 EIML 287 +/- 85 MW-LR-9 01/19/11 TBE 177 +/- 106 1.3 +/- 0.8 < 0.8 8.6 +/- 3.1 < 2.4 MW-LR-9 01/19/11 TBE 388 +/- 116 < 0.7 < 0.8 6.2 +/- 2.8 < 2.4 MW-LR-9 01/19/11 EIML 348 +/- 97 MW-LR-9 01/19/11 EIML 361 +/-:193 MW-LR-9 04/12/11 626 +/- 363

'MW-LR-9 04/19111 TBE 1070 +/- 172 < 0.7 < 1.4 5.3 +/- 2.5 8.6 +/- 1.7 ### +/- 3.6 MW-LR-9 04/19/11 TBE 1090 +/- 175 < 0.8 < 1.3 7.9 +/- 3.5 8.0 +/- 1.6 ### +/- 5.2 MW-LR-9 04119/11 EIML 1154 +/- 130 < 0.6 MW-LR-9 05/09/11 546 +/- 143 MW-LR-9 06/07/11 568 +/- 137 MW-LR-9 07/19/11 447 +/- 128 < 0.6 < 0.7 3.0 +/- 0.7 < 1.8 MW-LR-9 07/19/11 303 +/- 120 < 1.7 < 0.7 6.3 +/- 1.2 < 1.6 MW-LR-9 07/19/11 EIML 361 t 93 MW-LR-9 11/16/111 TBE 243 +/- 124 1.5 +/- 0.8 1.4 +/- 0.8 7.7 +/- 1.1 2.1 +/- 1.1 MW-LR-9 11/16111 TBE 270 +/- 126 2.0 +/- 0.9 1.7 +/- 0.9 8.1 +/- 1.2 2.8 +/- 1.2 MW-LR-9 11116/11 EIML 271 +/- 85 Pll 01/19/11 < 157 < 2.6 < 1.9 31.2 +/- 9.4 2.2 +/- 1.3 Pll 04/19/11 < 191 < 0.8 < 4.5 < 2.5 22.5 +/- 5.2 < 4.0 Pll 07/19111 < 172 < 4.1 < 0.7 22.8 +/- 2.1 < 1.6 Pll 11/16/111 < 181 < 1.7 < 0.6 20.2 +/- 1.7 < 1.6 P14 01/19/11 < 154 < 1.8 30.1 +/- 11.9 5.6 +/- 2.4 #:## +/- 9.7 P14 04/19/11 < 191 < 0.7 < 2.0 6.7 +/- 2.6 3.7 +/- 1.8 ##:# +/- 3.5 P14 07/19/11 < 169 < 5.0 2.4 +/- 1.2 4.7 +/- 1.6 ### + 1.9 P14 11/16/11 < 181 < 2.6 < 0.7 14.9 +/- 1.8 3.4 +/- 1.3 P16 01/20/11 < 158 < 2.9 82.8 +/- 16.0 26.5 +/- 7.3 407 +/- 16.1 P16 04/19/11 < 189 < 0.7 < 5.1 < 2.6 24.3 +/- 5.7 < 4.1 P16 07/19/11 < 182 < 8.6 < 3.6 9.9 +/- 5.9 < 4.2 P16 11/16111 < 184 < 4.1 5.5 +/- 1.6 17.9 +/- 2.3 4.7 +/- 1.6 P17 04/19/11 < 193 < 0.6 < 1.3 < 0.5 2.8 t 1.1 < 1.5 B-1

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS INWELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION 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 La-140 DATE Pll 04/19/11 < 18 < 16 <2 <2 <3 <2 <4 <2 <3 < 13 <2 <2 < 21 <5 P14 04/19/11 < 13 < 50 <2 <2 <3 <1 <3 <2 <3 < 15 <1 <2 < 20 <6 P16 04/19/11 < 15 < 10 <1 <2 <3 <1 <2 <2 <3 < 14 <1 <1 < 19 <5 P17 04/19/11 < 19 < 11 <1 <2 <3 <1 <3 <2 <3 < 14 <1 <1 < 24 <*7 MW-LR-1 04/19/11 < 13 < 11 <1 <1 <4 <1 <2 <2 <3 < 10 <1 <1 < 15 <4 MW-LR-2 04/19/11 < 20 < 55 <2 <2 <5 <2 <4 <3 <4 < 14 <2 <2 < 23 <7 MW-LR-3 04/19/11 < 18 < 38 <2 <2 <4 <1 <3 <2 <3 < 12 <2 <1 < 19 <6 MW-LR-4 04/19/11 < 21 < 15 <2 <2 <4 <2 <3 <2 <3 < 13 <2 <2 < 20 <.7 MW-LR-5 04/19/11 < 19 < 40 <1 <2 <5 <1 <3 <2 <3 < 14 <2 <2 < 17 < 6 MW-LR-7 04/19/11 < 14 < 14 <1 <2 <3 <1 <3 <2 <3 < 11 <1 <2 < 17 <5 MW-LR-8 04/19/11 TBE < 16 < 16 <1 <2 <4 <2 <3 <2 <3 *14 <1 <2 < 21 <5 MW-LR-8 04/19/11 TBE < 21 < 19 <2 <2 <4 <2 <4 <2 <4 < 14 <2 <2 < 25 <8 MW-LR-8 04/19/11 EIML

20 < 58 <2 <3 <5 <2 <4 <2 <5 <8 <2 <3 < 19 <3 MW-LR-8 11/16/11 EIML < 59 < 118 <7 <5 < 12 <6 < 16 < 13 < 14 < 10 <6 <7 < 37 < 10 MW-LR-9 04/12111 < 37 < 49 <4 <3 <9 <4 <9 <5 <7 < 15 <4 <4 < 32 < 12 MW-LR-9 04/19/11 TBE < 14 < 13 <1 <2 <3 <2 <3 <2 <3 < 15 <1 <1 < 18 <6 MW-LR-9 04/19/11 TBE < 18 81 +40 < 2 <2 <5 <2 <4 <2 <3 < 14 <2 <2 < 22 <8 MW-LR-9 04/19/11 EIML < 29 < 69 <2 <2 <7 <2 <5 <2 <7 < 12 <3 <3 < 23 <3 MW-LR-9 11/16/11 EIML < 40 < 90 <5 <4 < 13 <5 <9 <3 <7 <9 <6 <5 < 29 <2 B-2

TABLE B-II.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM-90 IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 SW-LR-10 01/20/11 < 162 SW-LR-10 04120111 < 192 < 0.7 SW-LR-10 07/18/11 < 173 SW-LR-10 11/14/11 < 158 SW-LR-2 01/20/11 < 157 SW-LR-2 04/20/11 < 170 < 0.7 SW-LR-2 07/18/11 < 172 SW-LR-2 11/14/11 < 181 SW-LR-4 01/20/11 < 157 SW-LR-4 04/20/11 < 170 < 0.7 SW-LR-4 07/18/11 < 169 SW-LR-4 11/14/11 < 183 SW-LR-6 01/20/11 < 155 SW-LR-6 04/20/11 < 170 < 0.6 SW-LR-6 07/18/11 < 173 SW-LR-6 11/14/11 < 183 SW-LR-7 01/20/11 < 161 SW-LR-7 04/20/11 < 169 < 0.8 SW-LR-7 07/18/11 < 171 SW-LR-7 11/14/11 < 184 SW-LR-8 01/19/11 301 +/- 113 SW-LR-8 04/19/11 TBE 1450 +/- 200 < 0.8 SW-LR-8 04/19/11 EIML 1607 +/- 136 < 0.6 SW-LR-8 07/20/11 < 173 SW-LR-8 11/14/11 236 +/- 112 SW-LR-9 01/18/11 < 163 SW-LR-9 04/19/11 < 191 < 0.7 SW-LR-9 07/20/11 < 171 SW-LR-9 11/17/11 < 154

~B-3 B

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE.WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION 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 La-140 DATE SW-LR-10 04/20/11 < 23 < 19 <2 <3 <5 <2 <5 <3 <4 <13 <2 <2 <25 <7 SW-LR-2 04/20/11 < 27 < 24 <3 <3 <6 <3 <6 <3 <6 <15 <2 <3 <27 <8 SW-LR-4 04/20/11 < 29 < 46 <3 <3 <7 <3 <5 <3 <4 <15 <3 <3 <26 <8 SW-LR-6 04/20/11 < 24 < 34 <2 <3 <5 <2 <4 <3 <4 <14 <2 <2 <25 <8 SW-LR-7 04/20/11 < 19 < 43 <2 <2 <4 <2 <4 <2 <3 <12 <2 <2 <21 <6 SW-LR-8 04/19/11 < 22 < 16 <2 <2 <5 <2 <4 <3 <4 <14 <2 <2 <27 <6 SW-LR-9 04/19/11 TBE < 20 < 16 <2 <2 <4 <2 <4 <2 <3 <13 <2 <2 <21 <77?

SW-LR-8 04/19/11 EIML < 27 < 64 <2 <2 <7 <2 <4 <3 <6 <11 <2 <2 <22 <5 B-4

TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 36S3 03/18/11 < 181 36S3 03/29/11 < 179 36S3 05/02/11 < 187 36S3 05/31/11 < 176 36S3 06/27/11 < 184 36S3 07/26/11 < 169 36S3 08/30/11 < 175 36S3 09/23/11 < 185 36S3 10/26/11 < 185 36S3 11/28/11 < 179 E-5 03/18/11 < 182 E-5 03/29/11 < 180 E-5 05/02/11 < 186 E-5 05/31/11 < 186 E-5 06/27/11 < 185 E-5 07/26/11 < 169 E-5 08/30/11 < 177 E-5 09/23/11 < 182 E-5 10/26/11 < 188 E-5 11/28/11 < 178 ESE-6 03/18/11 < 183 ESE-6 03/29/11 < 179 ESE-6 05/02/11 < 185 ESE-6 05/31/11 < 175 ESE-6 06/27/11 < 184 ESE-6 07/26/11 < 168 ESE-6 08/30/11 < 176 ESE-6 09/23/11 < 187 ESE-6 10/26/11 < 185 ESE-6 11/28/11 < 181 SE-7 03/18/11 < 165 SE-, 03/29/11 < 181 SE-7 05/02/11 < 186 SE-7 05/31/11 < 187 SE-7 06/27/11 < 181 SE-7 07/26/11 < 167 SE-7 08/30/11

176 SE-7 09/23/11 < 189 SE-7 10/26/11 < 187 SE-7 11/28/11 < 184 B-5

- '1/2' *',~

1/2~ '

Intentionally Left Blank

APPENDIX G ERRATA 2010 AREOR APPENDIX A

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL-MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 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 H-3 8 200 <LLD <LLD 0 (PCI/LITER)

GAMMA 24 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0

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

G-1

G-2 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 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 ZR-95 30 <LLD <LLD 0 (PCI/LITER)

<LLD 1-131 15 <LLD 0

<LLD CS-134 15 <LLD 0

<LLD CS-137 18 <LLD 0

<LLD BA-140 . 60, <LLD .0 LA-140 15 <LLD . LLD' " '0 DRINKING WATER GR-B 48 4 4.4 3.8 5.2 15F4 INDICATOR 0 (PCI/LITER) -(256/367) (10312J)- (96/12' PHILADELPHIA SUBURBAN WATER COMPANY

-' " :(2.516.7) (3.215.3):: : -"!(3:7/&6'7)'-p- !. -8.62 MILESýSEOF SITE H-3 16 200 <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE. LIMERICK GENERATING STATION, 2010 . , C.

Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 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 GAMMA 48 (PCI/LITER) MN-54 15 <LLD <LLD 0

<LLD CO-58 15 <LLD 0

<LLD 0 FE-59 30 <LLD 0

<LLD CO-60 15 <LLD ZN-65 30 <4LD <LLD:-

- 0

. *, =P,:

.[.

NB-95 15 :<LLD

-0

'* "'".**+ *..........

" 30*,

ZR-95 <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 PARENTHESES (F)

G-3

G4 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 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 1-131 15 <LLD <LLD 0 (PCI/LITER)

CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-14( <LLD" <LLD 0 BOTTOM FEEDER GAMMA 4 (PCI/KG WET) K-40 NA 3780 U27Q 3780 , 16C5 INDICATOR 0 (2/2) (2/2) (2/2)

.3'.646"/3§126j: VINCENT POOL (3640/3920) (3260/3280) -DCW*NStREAM&O. DISCHARGE MN-54 130 <LLD <LLD -. " 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 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 CO-58 130 <LLD <LLD 0 (PCI/KG WET)

FE-59 260 <LLD <LLD 0 CO-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0 1-131 NA... " . .L.D

. <LLD CS-134 130 - <LLDDLLD 0 CS-137 '.: 150 <LPL <LLD`-". 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

G-5

G-6 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353:

Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 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 GAMMA (PCI/KG WET) K-40 NA 3075 3210 3210 2gci CONTROL 0 (2/2) .. (2/2) (2/2) POTrSTOWN VICINITY (2640/3510) (311013310) (3110/3310) UPSTREAM'OF INTAKE MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD 0 FE 260 <LLD <LLD 0 CO-60 *-130 <LLD <LLD *0 ZN-65 260 <LLD -. ;1L"D' " 0 1-131 NA <LLD <LLD - 0

. .. - *. , ' ,,;, '/.- ,. ;.;...

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

TABLE A-1 -RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 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 CS-134 130 <.LLD <LLD 0 (PCI/KG WET)

CS-137 150 <LLD <LLD 0 SEDIMENT GAMMA (PCI/KG DRY) BE-7 NA 2685 <LLD 3740 16B2 INDICATOR 0 (2/4)107 (1/2).:. LINF!ELDBRIDGE (1630/3740) 1.35 MILES SSE OF SITE K-40;,," NA 14225 13350 15700 1612 INDICATOR 0 (4/4) (2/2) (2/2) LINFIELD BRIDGE (10800/16100) (13000/13700) (15300/16100) 1.35 MILES SSE OF SITE MN-54 .NA. <LLD <LLD

- I,. f CO-58 NA** <LLD' " <L'D CO-60 NA <LLD <LLD7 0 J

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

GJ7

G-8

- *.'I.,,~- ~ -

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION . DOCKET NUMBER:., 50-352 & 507353 .

Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010, 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 1-131 NA <LLD <LLD, 0 (PCI/KG DRY)

CS-134 150 <LLD <LLD CS-137 180 165 <LLD 166 16C4 INDICATOR 0 (2/4)" (1/2) VINCENT DAM (1641166) 2.18 MILES SSE OF SITE AIR PARTICULATE GR-B 267 10 16 16 17 10S3 INDICATOR 0 (E-3 PCI/CU.METER) (207/214) (52/53) (51/53) KEEN ROAD (6/35) (7/32) (8/34) 0.50 MILES E OF SITE GAMMA 21 BE-7., NA. - 7 .,,- 135. 6C1 INDICATOR.. 0 (17/17) (1/,1) 4/4)

(47/135). :79/103) 11305 FEET NE OF SITE MN-54 NA <LLD <LLD CO-58 NA I <LLD.....* <LLD -- 0

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

' * ,1:'-* .

TABLE A-1 RADIOLOGICAL-ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCdATIONS 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 CO-60 NA <LLD. -" <LLD 0 (E3: PCI/CU.METER)

CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD AIR' IODINE, GAMMA 267 (E-3:PCI/CU.METER) 1-131 170 <LLD <LLO 0

,0

. 1.. ,*LD, MILK I~131. t (PCIILITER)

GAMMA 114 . . ". .

K-40 NA 1283' 129". 23F1VCONTROL ." " " 0 (88/88) (26/26) (22/22)

(1050/1500) (,114011410)-, (1140/1410) 5.02 MILES SWOF SITE CS-134 15 <LLD <LLD 0

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

G-9

G-10 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 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 CS-137 18 <LLD <LLD 0 (PCI/LITER)

BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 VEGETATION GAMMA 33 (PCI/KG WET) BE-7 NA 298: 1334 1334 31G1 CONTROL 0 (9/21) (8/12) (8/12)

-(124/564) (85/2150) (85/2150)

K-40 NA 4799. 5330 5330 31G1 CONTROL 0 (21/21) (12/12) (12/12)

(3420/8510 I (3490/9660) (3490/9660)

MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 -

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) ME_ N (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 CO-60 NA <LLD <LLD (PCI/KG WET) 1-131 60 <LLD <LLD CS-1 34 60 <LLD <LLD CS-137 80 <LLD <LLD 0 RA-226 ýNA 2707 2080 2707 13S3 INDICATOR (7/21) (13/2) (7/10)-. VINCENT DAM.

(1380/4140) (1380/4140) 0.24 MILES SE OF SITE

71 " .0 TH-228 NA 62, 11 S3 INDICATOR (1/11) LGS INFORMATION CENTER (20499) (30/68) -

0.35 MILES ESE OF SITE 0

TH-232 NA 45 35 ' - ,:'45-.- 13S3 INDICATOR-

- 121) (35/36) VINCENT DAM 0.24 MILES SE OF SITE DIRECT RADIATION TLD-QUARTERLY 159 NA 6.8 8.4 9.3 13S2 INDICATOR 0 (MILLI-ROENTGEN/STD.MO.) (155/155) (4/4) (4/4) 500 KV SUBSTATION (4.9/9.8) (7.8/9.1) (8.8/9.8) 0.41 MILES SE

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

G-131

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